NRC 2011-0039, Redacted - Point Beach, Units 1 and 2, Submittal of 2010 Annual Monitoring Report

Redacted - Point Beach, Units 1 and 2, Submittal of 2010 Annual Monitoring Report

ML112210455
Person / Time
Site:	Point Beach
Issue date:	04/29/2011
From:	Jim Costedio Point Beach
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
NRC 2011-0039
Download: ML112210455 (183)

Text

POINT BEACH April 29, 201 1 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-27 201 0 Annual Monitorinn Re~ort NRC 201 1-0039 10 CFR 72.44 TS 5.6.2 In accordance with Point Beach Nuclear Plant (PBNP) Technical Specification 5.6.2, enclosed is the Annual Monitoring Report for PBNP Units 1 and 2, for the period January I through December 31,2010.

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 201 0. 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. contains the PBNP Environmental Manual, which was revised in April 2010.

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

Very truly yours, NextEra Energy Point Beach, LLC James Costedio w 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 Office of Nuclear Material Safety and Safeguards, USNRC NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241

ENCLOSURE 1

(

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

RENEWED LICENSES DPR-24 and DPR-27 January 1,2010 through December 31,2010

TABLE OF CONTENTS Summary Part A: Effluent Monitoring 1.0 lntroduction 2.0 Radioactive Liquid Releases 3.0 Radioactive Airborne Releases 4.0 Radioactive Solid Waste Shipments 5.0 Nonradioactive Chemical Releases 6.0 Circulating Water System Operation Part 6: Miscellaneous Reporting Requirements 7.0 Additional Reporting Requirements Part C: Radiological Environmental Monitoring 8.0 lntroduction 9.0 Program Description 10.0 Results I

1. Discussion 12.0 REMP Conclusion Part D: Groundwater Monitoring 13.0 Program Description 14.0 Results 15.0 Groundwater Summary Appendix 1 : Environmental, Inc. Midwest Laboratory, "Final Report for Point Beach Nuclear Plant" Appendix 2: University of Waterloo (Ontario) Environmental Isotope Laboratory, precipitation

LIST OF TABLES Table 2-1 Table 2-2 Table 2-3 Table 2-4 Table 3-1 Table 3-2 Table 3-3 Table 3-4 Table 4-1 Table 4-2 Table 4-3 Table 6-1 Table 9-1 Table 9-2 Table 9-3 Table 9-4 Table 9-5 Table 9-6 Table 10-1 Table 10-2 Table 10-3 Table 1 1-1 Table 1 1-2 Table I 1-3 Table 1 1-4 Table 14-1 Table 14-2 Table 14-3 Table 14-4 Table 14-5 Table 14-6 Table 14-7 Table 14-8 Table 14-9 Table 14-10 Table 14-11 Figure 9-1 Figure 9-2 Figure 9-3 Figure 11-1 Figure 1 1-2 Figure 13-1 Figure 14-1 Figure 14-2 Comparison of 2010 Liquid Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives Summary of Circulating Water Discharge lsotopic Composition of Circulating Water Discharges (Curies)

Subsoil System Drains - Tritium Summary Comparison of 201 0 Airborne Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives Radioactive Airborne Effluent Release Summary lsotopic Composition of Airborne Releases Comparison of Airborne Effluent Doses Quantities and Types of Waste Shipped from PBNP 201 0 Estimated Solid Waste Major Radionuclide Composition 201 0 PBNP Radioactive Waste Shipments Circulating Water System Operation for 201 0 PBNP REMP Sample Analysis and Frequency PBNP REMP Sampling Locations ISFSl Sampling Sites Minimum Acceptable Sample Size Deviations from Scheduled Sampling and Frequency Sample Collection for the State of Wisconsin Summary of Radiological Environmental Monitoring Results for 2010 ISFSl Fence TLD Results for 2010 C-I 4 in Crops Average Indicator TLD Results from 1993-201 0 Average ISFSl Fence TLD Results (mRl7days)

Average TLD Results Surrounding the ISFSl (mRl7days)

Average Gross Beta Measurements in Air Intermittent Streams and Bogs 201 0 Beach Drain Tritium U2 Faqade Subsurface Drainage Sump H-3 201 0 East Yard Area Manhole Tritium 2010 West Yard Area Manhole Tritium 201 0 Faqade Well Water Tritium 201 0 Potable Well Water Tritium 2010 Monitoring Well Water Tritium 201 0 Precipitation H-3 at Boundary Locations AC Condensate H-3 Concentration 201 0 H-3 Concentrations Close to Plant LIST OF FIGURES PBNP REMP Sampling Sites Map of REMP Sampling Sites Located Around PBNP Enhanced Map Showing REMP Sampling Sites Closest to PBNP Sr-90 Concentration in Milk 201 0 Airborne Gross Beta Concentration (pci/m3) vs. Time Groundwater Monitoring Locations 2010 S-1 and S-3 Beach Drain Concentrations (pCi/l) vs. Time 2010 H-3 Concentrations SSD Pump

The Annual Monitoring Report for the period from January 1, 201 0, through December 31, 2010, 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 2010, the following Curies (Ci) of radioactive material were released via the liquid and atmospheric pathways:

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

1 Atmospheric particulate includes radioiodine (1-1 31, 1-1 33).

2 Liquid is measured, atmospheric is calculated.

For the purpose of compliance with the effluent design objectives of Appendix I to 10 CFR 50, doses from effluents are calculated for the hypothetical maximally exposed individual (MEI) for each age group and compared to the Appendix I objectives. Doses less than or equal to the Appendix I values are considered to be evidence that PBNP releases are as low as reasonably achievable (ALARA). The maximum annual calculated doses in millirem (mrem) or millirad (mrad) are shown below and compared to the corresponding design objectives of 10 CFR 50, Appendix I.

LIQUID RELEASES Dose Category Whole body dose Organ dose ATMOSPHERIC RELEASES Calculated Dose 0.0045 mrem 0.0182 mrem Dose Categow Calculated Dose Organ dose 0.223 mrem Noble gas beta air dose 0.000186 mrad Noble gas gamma ray air dose 0.000436 mrad Noble gas dose to the skin 0.000632 mrem Noble gas dose to the whole body 0.000414 mrem Appendix I Dose 6 mrem 20 mrem Appendix I Dose 30 mrem 40 mrad 20 mrad 30 mrem 10 mrem

The results show that during 2010, the doses from PBNP effluents were a small percentage (0.68%) of the Appendix I design objectives. Therefore, operation of PBNP continues to be ALARA.

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

The 2010 Radiological Environmental Monitoring Program (REMP) collected 767 individual samples for radiological analyses and 128 sets of thermoluminescent dosimeters (TLDs) to measure ambient radiation in the vicinity of PBNP and the ISFSI. Quarterly composite of weekly air particulate filters generated an additional 24 samples and quarterly composites of monthly lake water samples resulted in a further 18 samples. This yields a total of 807 samples.

Air monitoring from six different sites showed only background radioactivity from naturally occurring radionuclides. Terrestrial monitoring consisting of soil, vegetation and milk found no influence from PBNP. Similarly, samples from the aquatic environment, consisting of lake and well water, fish and algae revealed no buildup of PBNP radionuclides released in liquid effluents. Therefore, the data show no plant effect on its environs.

There were no new dry storage units added to the ISFSl in 2010. The total number remains at 30 dry storage casks: 16 ventilated, vertical storage casks (VSC-24) and 14 NUHOMSB, horizontally stacked storage modules. The subset of the PBNP REMP samples used to evaluate the environmental impact of the PBNP ISFSl showed no environmental impact from its operation.

The environmental monitoring conducted during 201 0 confirmed that the effluent control program at PBNP ensured a minimal impact on the environment.

Approximately 500 samples were analyzed for H-3 a part of the groundwater monitoring program (GWP). These samples came from drinking water wells, monitoring wells, yard drain outfalls, yard manholes, and surface water on site. Also included in this number were a sump and manholes associated with the subsurface drainage system (SSD) located under the plant foundation and four groundwater containment integrity monitoring wells located in the facades.

The results show no substantial change in H-3 from previous years. Low levels of tritium continue under the plant foundation. No drinking water wells (depth >I00 feet) have any detectable H-3. Tritium continues to be confined to the upper soil layer where the flow is toward the lake. Groundwater samples from wells in the vicinity of the remediated, former earthen retention pond continue to show low levels of H-3 whereas none was detectable in the wells monitoring the potential offsite tritium movement. Precipitation sampling to evaluate the onsite recapture of discharged airborne H-3 found concentrations up to 440 pCi/l close to the plant and decreasing to less than detectable levels at the site boundary. In addition to H-3 measurements, some of the water samples were scanned for gamma emitters and analyzed for hard-to-detect (HTD) radionuclides. None were found. Soil obtained from the SSD manholes also were gamma scanned and analyzed for HTDs. Only Cs-137 and Sr-90, both long-lived radionuclides were found. No transuranics were found in these soil samples.

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 licensee's calculated effluent doses may be compared. These doses are a small fraction of the dose limits specified by 10 CFR 20.1301 and lower than the Environmental Protection Agency (EPA) limits specified in 40 CFR 190.

10 CFR 20.1 302 directs PBNP to make the appropriate surveys of radioactive materials in effluents released to unrestricted and controlled areas. Liquid wastes are monitored by inline radiation monitors as well as by isotopic analyses of samples of the waste stream prior to discharge from PBNP. Airborne releases of radioactive wastes are monitored in a similar manner. Furthermore, for both liquid and atmospheric releases, the appropriate portions of the radwaste treatment systems are used as required to keep releases ALARA. Prior to release, results of isotopic analyses are used to adjust the release rate of discrete volumes of liquid and atmospheric wastes (from liquid waste holdup tanks and from gas decay tanks) such that the concentrations of radioactive material in the air and water beyond PBNP are below the PBNP Technical Specification concentration limits for liquid effluents and release rate limits for gaseous effluents.

Solid wastes are shipped offsite for disposal at NRC licensed facilities. The amount of radioactivity in the solid waste is determined prior to shipment in order to determine the proper shipping configuration as regulated by the Department of Transportation and the NRC.

10 CFR 72.210 grants a general license for an Independent Spent Fuel Storage Installation (ISFSI) to all nuclear power reactor sites operating under 10 CFR 50. The annual reporting requirement pursuant to 10 CFR 72.44(d)(3) is no longer applicable.

However, any release of radioactive materials from the operation of the ISFSl must also comply with the limits of Part 20 and Part 50 Appendix I design objectives. The dose criteria for effluents and direct radiation specified by 10 CFR 72.104 states that during normal operations and anticipated occurrences, the annual dose equivalent to any real individual beyond the controlled area must not exceed 25 mrem to the whole body, 75 mrem to the thyroid, and 25 mrem to any other organ. The dose from naturally occurring radon and its decay products are exempt. Because the loading of the storage casks occurs within the primary auxiliary building of PBNP, the doses from effluents due to the loading process will be assessed and quantified as part of the PBNP Radiological Effluent Control Program.

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 Liauid 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 ME1 is assumed to reside at the site boundary in the highest x/Q sector and is maximized with respect to occupancy, food consumption, and other uses of this area. As such, the ME1 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 ME1 is a very small fraction of the Appendix I design objective.

Table 2-1 Comparison of 2010 Liquid Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives 201 0 Circulating Water Radionuclide Release Summary Annual Limit [mrem]

6 (whole body) 20 (any organ)

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.

201 0 Isotopic Composition of Circulatinq Water Discharges Highest Total Calculated Dose

[mrem]

0.0045 0.0182 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.

% of Design Objective 0.075 %

0.091 %

The total isotopic distribution (gamma emitters plus hard-to-detects other that strontium) shows a slight increase from 2009, with increases in Co-58, Nb-95, Sb-124, and Ni-63. There was no Sr-89/90 in liquids in 2010. Tritium is lower by approximately 100 Curies from 2009. Tritium continues to be the major radionuclide released via liquid discharges.

2.4 Beach Drain System Releases Tritium Summaw Beach drain is the term used to describe the point at which the site yard drainage system empties onto the beach of Lake Michigan. Six of the drains carry yard and roof drain runoff 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 2010, 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 also 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. For seven months during 2010, beach drain S-1 received water from a groundwater sump under the plant. In August this sump was rerouted to the waste water effluent discharge point.

Table 2-2 Summaw of Circulating Water Discharge January 1, 201 0 through December 31,201 0 1 HTDs include Fe-55, C-14, Ni-63, and Tc-99. Does not include strontium which is totaled separately.

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

3 Circulating water discharge from both units.

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

Table 2-4 Subsoil System Drains - Tritium Summary January 1,201 0, through December 31,201 0 2.6 Land Application of Sewaqe Sludqe 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 required analyses prior to every disposal. Based upon an investigation of the source of the radionuclides, a combination of engineering modifications and administrative controls 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. However, as a precaution, sludge is routinely monitored at the sensitivity level to achieve environmental LLDs.

There were no sludge disposals by land application during 2010. All disposals were done at the Manitowoc Sewage Treatment Plant.

Carbon-I 4 (C-14) is a naturally occurring radionuclide. Nuclear weapons testing of the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Small amounts of C-14 also are produced by nuclear reactors, but the amounts produced are less than C-14 produced by weapons testing or that occur naturally. NextEra began evaluating C-14 liquid discharges in 2009, prior to the issuance of Regulatory Guide 1.21 [RG 1.211, Rev 2 in June of 2009.

For 2010, the NRC has requested that nuclear plants report C-14 emissions.

Pursuant to NRC guidance in RG 1.21, evaluation of C-14 in liquid wastes is not required because the quantity released via this pathway is much less than that contributed by gaseous emissions. However, analyses show that C-14 meets the principal radionuclide criterion of RG 1.21. A principal radionuclide may be determined based on its relative contribution to the public dose compared to the 10 CFR 50, Appendix I dose objectives, or the amount of activity discharged compared to other radionuclides in its effluent type. In this case, it is compared to other radionuclides discharged in liquids. Furthermore, RG 1.21 states that a radionuclide is a principal effluent component if it contributes greater than 1% of the Appendix I design objective dose compared to the other radionuclides in the effluent type, or, if it is greater than 1% of the activity of all radionuclides in the effluent type. For 2010, the monthly and total C-14 (3.39E-03 Ci) in liquid discharges are documented in Table 2-3. The C-14 dose contribution is included in the doses calculated for the hypothetically, maximally exposed individual.

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 ME1 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 calculated doses include the C-14 contribution. This is the first time C-14 has been required by the NRC (see Sections 3.4 through 3.6, below, for a more detailed description). The comparison between airborne effluent doses with and without C-14 are shown in Table 3-4. The highest dose is the child-bone category. 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 2010 are summarized in Table 3-2. Noble gases are slightly higher than 2009 with the airborne tritium being twenty curies lower.

3.3 Isotopic Airborne Releases The monthly isotopic airborne releases for 2010, from which the airborne doses were calculated, are presented in Table 3-3. Carbon-14 is not included in Table 3-3 because it was calculated and not measured. C-14 is explained in the following sections.

C-14 is a naturally occurring radionuclide. Nuclear weapons testing of the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Small amounts of C-14 also are produced by nuclear reactors as neutrons interact with the dissolved oxygen and nitrogen in the primary coolant. However, these amounts produced by nuclear reactors are much less that those produced by weapons testing or that occur naturally. The NRC has requested that nuclear plants report C-14 emissions.

Pursuant to NRC guidance (Regulatory Guide 1.21, Rev 2, p. 16, June 2009),

most of the C-14 emissions from nuclear plant occur in the gaseous phase.

C-14 is a hard-to-detect radionuclide. It is not a gamma emitter and must be chemically separated from the effluent stream before it can be measured.

Because nuclear plants currently are not equipped to perform this type of sampling, RG 1.21 allows for calculating C-14 discharges based on fission rates.

The Electric Power Research Institute (EPRI) undertook the task of developing the methodology for calculating C-14 generation and releases for the nuclear industry. The results were published as Technical Report 1021 106 (December 2010), "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents."

NextEra participated in the generation of the EPRI Technical Report by providing data to EPRI required to calculate C-14 generation. The C-14 generation rate calculated by EPRI for each PBNP Unit was 5.23 Cily for a total of 10.46 Ci (EPRI, Table 4-25, p. 4-26, Units W-D and W-E). This value is four orders of magnitude higher than the 3.39E-03 Ci of C-14 measured in the liquid waste batch discharges.

3.5 C-14 Airborne Effluent Dose Calculation The dose from the airborne C-14 is dependent on its chemical form. The C-14 released to the atmosphere consists of both organic and inorganic species. Both the inorganic and organic C-14 contributes to the inhalation dose. Only the inorganic I4co2 species contributes to the dose from the ingestion of photosynthetically incorporated C-14. The organic forms such as methane, CH4, are not photosynthetically active. For PWRs such as PBNP most of the gaseous 14 C-14 occurs as methane, CH4, not as carbon dioxide, I4co2.

The amount of I4co2 present in the PBNP airborne effluent has not been measured. However, such measurements have been made at a comparable PWR sites similar to the PBNP design. The Ginna nuclear generating station (Ginna) is of similar design to PBNP. It is a Westinghouse 2-loop PWR of the same vintage as PBNP and approximately the same power. Measurements at Ginna for 18 months in 1980 - 1981 (Kunz, "Measurement of I4c Production and Discharge From the Ginna Nuclear Power Reactor," 1982) found that ten percent of the C-I 4 was discharged as I4co2. Therefore, 10% of the 10.46 Ci of C-14 calculated for PBNP by EPRI will be used in the ingestion dose calculations.

C-14 dose calculations were made using the dose factors and the methodology of Regulatory Guide 1.109. The inhalation dose was calculated using all of the C-14 calculated to be released. All the C-14 is used because whether the C-14 is in the form of I4co2 or one of the organic forms, such as CH4, both would be inhaled and contributes to a lung dose.

For the other pathways, milk, meat, produce, and leafy vegetables, the dose depends upon the amount incorporated into biomass consumed by cattle and people: forage for cattle or produce and vegetables for humans. Incorporation only occurs via photosynthesis. Photosynthesis only incorporates I4co2 and

hence the use only of the 10% fraction of the total C-14 release for these pathways.

The airborne effluent C-14 dose calculations were made as described above.

They were made for the ME1 as explained in Section 2.1. This approach assumes that all pathways are applicable to a hypothetical person residing at the site boundary. Because C-14 is present as a gas, the assumed pathways are milk, meat, leafy vegetables and produce (vegetables, fruit, and grain) and the Regulatory Guide 1.109, Table E-5 usage factors applied to the calculation. As such, the resulting dose will conservative in that the produce usage factor includes grain and fruit and these pathways do not exist in the vicinity of the point for which the C-I 4 doses are calculate. However, this ME1 approach is used to maintain continuity between the C-14 and the other radionuclide dose calculation methodologies as described in the ODCM.

3.6 C-14 Measurements Although no C-14 measurements were made of PBNP effluents, C-14 was measured in crops grown on fields in the owner controlled area located in the highest x/Q sector at the site's south boundary. One field is leased for feed corn by a dairy south of the plant. That dairy is part of the REMP. In an adjacent field soybeans are grown by another farmer. These two crops were sampled in this sector and as well in a background location about 17 miles SW of the plant.

Based on the measurement error, there is no statistical difference between the results obtained on site in the highest x/Q sector as compared to the background site some 17 miles away (Table 10-3). These results demonstrate that the dose from C-14 in Point Beach airborne effluents should not measurably increase the C-14 dose compared to that received from naturally occurring C-14 in plants.

TABLE 3-3 lsotopic Cornposition of Airborne Releases January 1, 201 0 through December 31, 201 0 Note: The Noble Gases listed above include the liquid contribution

Table 3-4 Comparison of Airborne Effluent Doses 2010 Airborne Particulate + Tritium Dose (mrem)

Bone Liver T-WB Thyroid Kidney Lung GI-LLI Skin Adult 4.16E-04 1.35E-02 1.34E-02 1.86E-02 1.34E-02 1.34E-02 1.34E-02 7.17E-06 Teen 5.52E-04 1.55E-02 1.54E-02 1.95E-02 1.54E-02 1.54E-02 1.54E-02 7.17E-06 Child 8.76E-04 2.26E-02 2.26E-02 2.99E-02 2.26E-02 2.25E-02 2.25E-02 7.17E-06 lnfant 2.61 E-04 9.96E-03 9.94E-03 2.21 E-02 9.96E-03 9.91 E-03 9.92E-03 7.17E-06 Carbon-14 Dose (mremlyr)

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 6.32E-02 1.26E-02 1.26E-02 1.26E-02 1.26E-02 1.26E-02 1.26E-02 0.00E+00 Teen 9.67E-02 1.92E-02 1.92E-02 1.92E-02 1.92E-02 1.92E-02 1.92E-02 0.00E+00 Child 2.22E-01 4.42E-02 4.42E-02 4.42E-02 4.42E-02 4.42E-02 4.42E-02 0.00E+00 lnfant 1.09E-01 2.32E-02 2.32E-02 2.32E-02 2.32E-02 2.32E-02 2.32E-02 0.00E+00 2010 Total Airborne Non-Noble Gas Dose (mrem)

Bone Liver T-WB Thyroid Kidney Lung GI-LLI Skin Adult 6.36E-02 2.60E-02 2.60E-02 3.12E-02 2.60E-02 2.60E-02 2.60E-02 7.17E-06 Teen 9.72E-02 3.47E-02 3.47E-02 3.88E-02 3.47E-02 3.46E-02 3.47E-02 7.17E-06 Child 2.23E-01 6.68E-02 6.68E-02 7.41E-02 6.68E-02 6.67E-02 6.67E-02 7.17E-06 lnfant 1.10E-01 3.32E-02 3.32E-02 4.53E-02 3.32E-02 3.31 E-02 3.31 E-02 7.17E-06 Ann.Limit 3.00E+01 3.00E+01 3.00E+01 3.00E+01 3.00E+01 3.00E+01 3.00E+01

% Limit 7.42E-01 2.23E-01 2.47E-01 2.23E-01 2.22E-01 2.22E-01 2.39E-05

4.0 RADIOACTIVE SOLID WASTE SHIPMENTS 4.1 Tvpes, Volumes, and Activitv of Shipped Solid Waste The following types, volumes, and activity of solid waste were shipped from PBNP for offsite disposal or burial during 2010. No Type C or D waste was 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 4.2 Maior Nuclide Composition (by Type of Waste)

The major radionuclide content of the 2010 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.

Table 4-2 2010 Estimated Solid Waste Major Radionuclide Composition

4.3 Solid Waste Disposition There were ten solid waste shipments from PBNP during 2010. The dates and destinations are shown in Table 4-3.

Table 4-3 201 0 PBNP Radioactive Waste Shipments

5.0 NONRADIOACTIVE CHEMICAL RELEASES 5.1 Scheduled Chemical Waste Releases Scheduled chemical waste releases to the circulating water system from January 1, 2010, to June 30, 2010, included 7.23E+05 gallons of neutralized wastewater. The wastewater contained 8.42E-01 pounds of suspended solids and 1.26E+03 pounds of dissolved solids.

Scheduled chemical waste releases to the circulating water system from July 1, 2010, to December 31, 2010, included 4.81 E+05 gallons of neutralized wastewater. The wastewater contained 3.51 E-03 pounds of suspended solids and 1.20E+03 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, 2010, to June 30, 2010, included 2.16E+07 gallons of clarified wastewater. The wastewater contained 1.98E+03 pounds of suspended solids.

Miscellaneous chemical waste releases from the wastewater effluent (based on effluent analyses) to the circulating water for July 1, 2010, to December 31, 2010, included I

.93E+07 gallons of clarified wastewater. The wastewater contained 2.62E+03 pounds of suspended solids.

Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from January 1, 2010, to June 30, 2010, included 4.06E+05 pounds of sodium bisulfite solution (1.54E+05 Ibs. sodium bisulfite) and 5.41 E+05 Ibs of Stabrex ST70 solution (3.44E+04 sodium hypochlorite and 4.99E+04 Ibs sodium bromide). 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, 2010, to December 31, 2010, included 4.87E+05 pounds of sodium bisulfite solution (1.85E+05 Ibs sodium bisulfite) and 3.74E+05 pounds of Stabrex ST70 (2.38E+04 Ib sodium hypochlorite and 3.45E+04 Ibs sodium bromide), 1.53E+05 pounds Sodium Hypochlorite Solution (1.91 E+04 pounds sodium hypochlorite), and 7.91 E+02 pounds Acti-Brom 1338 (3.56+E02 pounds sodium bromide). Stabrex ST70 and Acti-Brom 1338 are liquid bromine biocides.

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 2010

• U1 outage 31211 0 - 4/1/10

• • For days with cooling water discharge flow.

Table 6-1 (continued)

Circulating Water System Operation for 2010

• • For days with cooling water discharge flow.

7.0 ADDITIONAL REPORTING REQUIREMENTS 7.1 Revisions to the PBNP Effluent and Environmental Programs The ODCM was not revised in 2010. However, the Environmental Manual (EM) was revised. The EM is part of the ODCM. Copies of the revised manual are being submitted with this 2010 Annual Monitoring Report.

7.2 Interlaboratow 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 201 0. 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 2010.

RADIOLOGICAL E

8.0 INTRODUCTION

The objective of the PBNP Radiological Environmental Monitoring Program (REMP) is to determine whether the operation of PBNP or the ISFSl 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 I 0 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 ISFSl are maintained within the dose limits of 10 CFR 72.104. Because the ISFSl 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 ISFSl is provided by selected sampling sites, which are part of the PBNP REMP.

For the aquatic environment, the samples include water as well as the biological integrators, such as fish and filamentous algae. Because of their migratory behavior, fish are wide area integrators. In contrast, the filamentous algae periphyton is attached to shoreline rocks and concentrate nuclides from the water flowing by their point of attachment. Grab samples of lake water provide a snapshot of radionuclide concentrations at the time the sample is taken; whereas analysis of fish and filamentous algae yield concentrations integrated over time.

The air-grass-cow-milk exposure pathway unites the terrestrial and atmospheric environments. This pathway is important because of the many dairy farms around PBNP. Therefore, the REMP includes samples of air, general grasses, and milk from the PBNP environs. An annual land use survey is made to determine whether the assumptions on the location of dairy cattle remain conservative with respect to dose calculations for PBNP effluents. The dose calculations assume that the dairy cattle are located at the south site boundary, the highest depositional sector. In addition, soil samples are collected and analyzed in order to monitor the potential for long-term buildup of radionuclides in the vicinity of PBNP.

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

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 I )

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

radionuclide half-life may be used to evaluate whether the result is real or a statistical artifact. Based on the actual measurement of the sample and its background, it is possible to calculate the minimum detectable concentration (MDC) of a sample in the same manner the a priori LLD is calculated. This is the most common method of determining whether or not a radionuclide is present in a sample.

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 ISFSl 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 ISFSl fence TLDs.

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

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

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

9.5 Proqram Modifications No new monitoring sites were added in 2010.

Table 9-1 PBNP REMP Sample Analysis and Frequency Sample Type Environmental Radiation Exposure Vegetation Algae Fish Well Water Lake Water Sample Codes E-01, -02, -03, -04, -05

-06, -07, -08, -09, -1 2

-14, -15, -16, -1 7, -18,

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

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

-31, -32, -38, -39,-41,

-42,-43, -TC E-01, -02, -03, -04, -06,

-08, -09, -20, E-05, -1 2 E-I 3 E-10 Milk Air Filters Soil E-01, -05, -06, -33 Shoreline Sediment TLD Gross Beta Gamma Isotopic Analysis Gross Beta Gamma lsotopic Analysis Gross Beta Gamma lsotopic Analysis (Analysis of edible portions only)

Gross Beta, H-3 Sr-89, 90, 1-1 31 Gamma lsotopic Analysis E-I I, -40, -21 E-01, -02, -03, -04,

-08, -20 E-01, -02, -03, -04, ISFSl Ambient Radiation Exposure Frequency Quarterly 3xlyr as available 3xlyr as available 3xlyr as available Quarterly Gross Beta, Sr-89/90, H-3 1-1 31 Gamma lsotopic Analysis

-06, -08, -09, -20, E-01, -05, -06, -1 2, -33, Monthly 1 Quarterly composite monthly collections Monthly Monthly Sr-89, 90 1-1 31 Gamma lsotopic Analysis Gross Beta 1-1 31 Gamma lsotopic Analysis Gross Beta North, East, South, West Fence Sections Monthly Weekly (particulate)

Weekly (charcoal)

Quarterly (on composite particulate filters) 2xlyr Gamma Isotopic Analysis Gross Beta 2xlyr Gamma lsotopic Analysis TLD Quarterly

Table 9-2 PBNP REMP Sampling Locations Location Code E-01 E-02 E-03 E-04 E-05 E-06 E-07 E-08 E-09 E-10 E-I I E-12 E-13 E-14 E-I 5 E-I 6 E-17 E-I 8 E-20 E-21 E-22 E-23 E-24 E-25 E-26 E-27 E-28 E-29 E-30 E-31 Location Description Primary Meteorological Tower South of the Plant Site Boundary Control Center - East Side of Building Tapawingo Road, about 0.4 Miles West of Lakeshore Road North Boundary Two Creeks Park Point Beach State Park - Coast Guard Station; TLD located South of the Lighthouse on Telephone pole WPSC Substation on County V, about 0.5 Miles West of Hwy 42 G.J. Francar Property at Southeast Corner of the Intersection of Cty. B and Zander Road Nature Conservancy PBNP Site Well Dairy Farm about 3.75 Miles West of Site Discharge FlumelPier Pumphouse South Boundary, about 0.2 miles East of Site Boundary Control Center Southwest Corner of Site WSW, Hwy 42, a residence about 0.25 miles North of Nuclear Road North of Mishicot, Cty. B and Assman Road, Northeast Corner of Intersection Northwest of Two Creeks at Zander and Tannery Roads Reference Location, 17 miles Southwest, at Silver Lake College Local Dairy Farm just South of Site 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 Intersection of Saxonburg and Nuclear Roads, Southwest Corner, about 4 Miles WSW TLD site on western most pole between the 2nd and 3'C' parking lots.

Area of North Meteorological Tower.

NE corner at Intersection of Tapawingo and Lakeshore Roads.

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

E-33 E-38 E-39 E-40 E-41 E-42 E-43 E-TC E-32 I

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 creek.

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

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

Local Dairy Farm, W side of Hwy 42, about 1.8 miles north of the Nuclear Rd intersection NW corner of Woodside and Nuclear Rds (Kewaunee County)

NW corner of Church and Division, East of Mishicot West side of Tannery Rd south of Elmwood (7th pole south of Elmwood)

Transportation Control; Reserved for TLDs

Figure 9-1 PBNP REMP Sampling Sites

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

Table 9-3 lSFSl Sampling Sites Table 9-4 Minimum Acceptable Sample Size Ambient Radiation Monitoring (TLD)

E-03 E-28 Soil, Vegetation and Airborne Monitoring E-02 E-03 Sample Type Vegetation Lake Water Air Filters Well Water Milk Size 100-1 000 grams 8 liters 250 m3 (volume of air) 8 liters 8 liters

Table 9-5 Deviations from Scheduled Sampling and Frequency Table 9-6 Sample Collections for State of Wisconsin Fish Precipitation Milk Well Water E-13 E-04 E-08 Quarterly, As Available Twice a month, As Available E-11 E-19 E-10 Monthly Twice per year

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 2010.

9.7 Description of Analvtical 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, 23-95, Nb-95, Ru-103, Ru-106, 1-1 31, Ba-La-140, Cs-I 34, 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, TI-208, Ac-228, Be-7, and K-40.

9.7.2 Gross Beta Analysis Gross beta analysis is a non-specific analysis that consists of measuring the total beta activity of the sample. No individual radionuclides are identifiable by this method. Gross beta analysis is a quick method of screening samples for the presence of elevated activity that may require additional, immediate analyses.

9.7.3 Water Samples Water samples include both Lake Michigan and well water. The Lake Michigan samples are collected along the shoreline at two locations north and two locations south of PBNP. The well water is sampled from the on-site PBNP well. Gross beta measurements are made on the solids remaining after evaporation of the unfiltered sample to dryness. Gamma isotopic analyses are performed using I

-liter liquid samples. Strontium is determined by chemical separation and beta counting.

9.7.4 Air Samples Particulate air filters are allowed to decay at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> before gross beta measurements are made in order for naturally occurring radionuclides to become a negligible part of the total activity. Gross beta measurements serve as a quick check for any unexpected activity that may require immediate investigation. Quarterly composites of the particulate air filters are analyzed for long-lived radionuclides such as Cs-134 and Cs-137. Charcoal cartridges for radioiodine are counted as soon as possible so the 1-131 will undergo only minimal decay prior to analyses. The weekly charcoal cartridges are screened for 1-1 31 by

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

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

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

For 201 0, special vegetation samples were obtained for C-14 analyses.

Samples of soybeans and feed corn were obtained from fields at the site boundary in the highest xIQ section for comparison to the same crops obtained from the background site some 17 miles away.

9.7.6 Environmental Radiation Exposure The 201 0 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.

9.7.7 ISFSl Ambient Radiation Exposure Although the ISFSl 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 ISFSl 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 10.1 Summarv of 201 0 REMP Results Radiological environmental monitoring conducted at PBNP from January 1, 2010, through December 31, 2010, 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 prior; lower limit of detection N:

Number of samples analyzed Average:

Average value + the standard deviation of N samples High:

Highest measured value + it's associated 2 sigma counting error Units:

Units of measurement For certain analyses, an LLD, which is lower than that required by REMP, is used because the lower value derives from the counting time required to obtain the LLDs for radionuclides that are more difficult to detect. For these analyses, both LLDs are listed with the REMP LLD given in parentheses. The results are discussed in the narrative portion of this report (Section 11). Blank values have not been subtracted from the results presented in Table 10-1. A listing of all the individual results obtained from the contracted analytical laboratory and the laboratory's radioanalytical quality assurance results and lnterlaboratory Crosscheck Program results are presented in the Appendix.

Table 10-1 contains a summary of REMP results. No results are reported as less than LLD. All results reported to NextEra by the contracted radioanalytical laboratory "as measured" whether positive or negative. A Table 10-1 value reported as ND indicates that none of the results were detected based on a comparison to the minimum detectable concentration (MDC). The laboratory calculates the MDC based on results and background for the individual sample.

If one result is greater than an MDC, all the values, whether positive or negative (and less than an MDC) are used to calculate the average and standard deviation reported in Table 10-1. Some of the reported averages may be 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 and greater than an MDC based on counting statistics.

The method of determining averages based on "as measured" results follows the recommendations made in NUREG-0475 (1978), "Radiological Environmental Monitoring by NRC Licensees for Routine Operations of Nuclear Facilities Task Force Report," and in Health Physics Society Committee Report HPSR-1 (1 980),

"Upgrading Environmental Radiation Data" released as document EPA 52011 012 and in more recent documents such as ANSl N42.23-1996, "Instrument Quality Assurance for Radioassay Laboratories;" ANSl N13.30-1996, "Performance Criteria for Radiobioassay;" DE91-013607, "Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance" and NUREG-1 576, "Multi-Agency Radiological Laboratory Analytical Protocols Manual."

Table 10-2 contains the ISFSl fence TLD results.

10.2 Correction to 2009 Annual Monitoring Report The 2009 Annual Monitoring Report (AMR) contained one gross beta data point used to calculate the annual average and standard deviations reported in Table 10-1 and Table 11-4 which should not have been used. The sample from location E-02 for April 22, 2009, should not have been included in the calculations. Due to loss of power to the sampler prior to when the sample was collected, the correct volume required for calculating the concentration was unknown. The collected sample was sent to the contracted lab for analysis to see if there was any above normal activity. However, the cover letter did not specify that the analytical result should not be reported in the monthly REMP report. The inclusion of that sample result in the monthly REMP report was not caught during the review of April 2009 results. Subsequently the data point was used in the preparation of annual averages reported in Table 10-1 and 11-4 and in the discussions presented in the 2009 PBNP AMR.

There were 308 gross beta air particulate samples used in generating the reported averages. The reported gross beta average and its standard deviation based on the 308 samples as reported in Tables 10-1 and 11-4 was 0.025 pci/m3 + 0.01 1 pci/m3. Removing the E-02 data point for April 22, 2009 yields 0.025 p ~ i / m 3

+ 0.01 1 pci/m3. The only difference between the two statistical calculations occurs in the 4th - 6th decimal places (not shown) which are used only in rounding off and have no other statistical validity because the results are reported using 2 significant figures.

Therefore, using the E-02 data from April 22, 2009, did not change the results reported on Table 10-1 and on Table 11-4. Conclusions derived from the inclusion of the data point are not changed.

Table 10-1 Summary of Radiological Environmental Monitoring Results for 2010 (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 or less than the MDA.

Table 10-1 (continued)

Summary of Radiological Environmental Monitoring Results for 2010 (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 or <MDA.

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

Table 10-2 lSFSl Fence TLD Results for 2010 10.3 2010 Special Sample Results The results of the C-14 measurements on the corn and soybean special samples collected are shown in Table 10-3.

Table 10-3 C-I4 IN CROPS 11.0 DISCUSSION 11.1 TLDCards 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. I 1 mW7-days and 1.I 0 mW7-days at the control location. These results are not significantly different from each other nor from those observed from 2001 through 2009 (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.

There were no new dry fuel storage cask additions to the ISFSl in 201 0. The higher ISFSl fence TLD averages, when compared to the 2009 averages, show that the current number of casks were not all present in 2009 (Table 11-2). The west fence TLDs continue to record higher exposures. The north and east fence TLDs are statistically equal (2.65t 0.38 vs. 3.03t 0.44). The south fence continues to record the lowest exposures (Table 11-2).

Table 11-1 Average Indicator TLD Results from 1993 - 2010

• St. Dev = Standard Deviation Table 11-2 Average ISFSl Fence TLD Results (mR17 days)

There is no significant exposure impact on the TLD monitoring locations around the ISFSl (Table 11-3). The results continue to be higher at E-03 and E-31 which are west of the ISFSl corresponding to the higher exposure at the west fence.

As expected, the values at E-03 are higher than those at E-31. E-03 is located halfway between the ISFSl and E-31 [see Figs. 9-1 and 9-2 for locations]. The results near the site boundary (E-31, I.I 7 rt 0.1 9; E-32, 1.05 rt 0.27) are comparable to the background site E-20 (1.09 rt 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 11-3 Average TLD Results Surrounding the ISFSl (mW7 days)

• 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.

Naturally occurring potassium-40 (1421 rt 75 pCi/l) continues to be the most prevalent radionuclide measured in milk at concentrations roughly 2000 times higher than the only potential plant related radionuclide, Sr-90 (0.7 rt 0.3 pCiIl),

detected in milk. The annual average Sr-90 concentrations in milk continue to be similar to previous years. None of the other required radionuclides in the milk analyses, 1-1 31, Cs-1341137, Ba-La-140, and Co-60 were detected.

Strontium-90 results are similar to results from prior years. A plot of the annual averages starting with 1997 shows a logarithmic decrease over time (Figure 11-1). Using the annual average Sr-90 concentration in milk between 1997 and 2010, the environmental half-life can be calculated yielding a 16.7 year half-life. Because the radiological half-life is 28 years, the shorter removal half-life indicates that environmental factors as well as radioactive decay are working to decrease the concentration of Sr-90 in milk.

Figure 11-1 Sr-90 Concentration in Milk Sr-90 in Milk 10.0 I

1.o p = G q 0.1 Year The Sr-90 in milk persists due to cycling in the biosphere after the atmospheric weapons tests of the '50s, '60s, and '70s and the Chernobyl accident in the late 1980s. Therefore, it is concluded that the milk data for 2010 show no radiological effects of the plant operation.

The average annual gross beta concentrations (plus/minus the one-sigma uncertainty) in weekly airborne particulates at the indicator and control locations were 0.022 + 0.01 4 pci/m3 and 0.023 + 0.01 4 pcilm3, respectively, and are similar to levels observed from 1993 through 2009 (Table 11-4).

Table I 1 -4 Average Gross Beta Measurements in Air The 201 0 weekly gross beta concentrations reveal higher winter values and lower summer values. This is a repeat of the patterns seen in 2006 - 2009.

Again, as in previous years, another high period 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 11-2 2010 Airborne Gross Beta Concentration (pcilm3) vs. Time 0.050

+

E-0 1 0.040 0.030 0.020 E-04 0.010 E-20 0.000 "To "70 "70

• To

'Q

• TO DATE In 2005, the new method of evaluating airborne 1-131 was instituted. Instead of counting each charcoal cartridge separately, all six cartridges for the week are counted as one sample in a predetermined geometry to screen the samples for 1-131. If any airborne radioiodine is detected, each sample cartridge is counted individually. With no detectable 1-131, the reported analytical result is the minimum detectable activity (MDA) conservatively calculated using the smallest of the six sample volumes. The reported MDAs ranged from 0.006 to 0.029 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 1-131 was detected, it is concluded that the release of small amounts of radioiodine from March - June (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 and Co-60 are less than the minimum detectable concentration (MDC). One Cs-137 result (0.0006 k 0.0004 pci/m3) from collection site E-08 located greater than 5 miles to the WNW of PBNP) was greater that its MDC of 0.0005 pCi/m3. Because PBNP released no airborne Cs-137 during 201 0, this positive Cs-137 is either a false positive or, most likely, indicates the resuspension of soil containing Cs-137. Due to radioactive fallout from atmospheric weapons testing in the 1950s to 1970s, Cs-137 occurs in the soils around PBNP (see Section 11.8). By comparison, this Cs-137 is about 1%

of the 2010 average concentration of the naturally radioisotope Be-7 was 0.077 k 0.01 1 p~i/m3.

In summary, the 2010 air data does not demonstrate an environmental impact from the operation of PBNP.

11.4 Lake Water For the REMP-specified gamma emitting radionuclides listed in Table 10-1, reported concentrations continue to occur as small, negative and positive values scattered around zero, indicating no radiological impact from the operation of PBNP. Lake Michigan water samples are collected north (E-33 and E-05) and south (E-01 and E-06) of PBNP (see Figure 9-1). Icy conditions precluded obtaining samples from E-06 in January and February and from all four sites in December.

There were four slightly positive indications of gamma emitters during 2010. On April 15, 2010, Zn-65 was greater than the MDC. This occurred at site E-05, which is about 1.6 miles north of PBNP. This site is upstream based on the current flow in the area. On the same date, a slightly positive result but less than the MDC occurred south of PBNP at site E-01. On April 5, 201 0, PBNP had a Zn-65 discharge. The discharge concentration was about 1000 times lower than the measured lake water concentration. Based on the sample locations, on the measured concentrations, and on the PBNP Zn-65 discharge history, it is unlikely that the small, positive Zn-65 results are the result of any PBNP discharge.

Therefore, the Zn-65 results at E-05 and E-01 are determined to be a false positive.

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 1960s. Therefore, it is not surprising that there were four slightly positive results for Sr-90. None of the results were above the MDC.

Furthermore, PBNP had no Sr-89 or Sr-90 liquid discharges during 201 0.

Therefore, it is concluded that the small, positive results due to the statistical nature of radioactivity measurements.

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 2010, ranged from less than MDC to 642 pCi1l. Although 7 of the 16 composites showed results above zero, only two of these results (E-05, 431 1 104 pCiIl, 1.6 miles north of PBNP and E-06, 642 ~t 112 pCill, about 6 miles south), both occurring in the fourth quarter, were above the MDC. Based on these results, the individual months used to make the composites were analyzed separately. The tritium concentrations at E-05 are unlikely to be the result of PBNP discharges because, as mentioned above, this site north of the plant is upstream with respect to the current flow on this side of Lake Michigan. Due to icy conditions, the fourth quarter E-06 composite consists of only two monthly samples, October and November. The October sample had 490 1 97 pCill; November, 11 39 It 11 9 pCi1l. The H-3 concentrations could have resulted from PBNP effluents because, in both cases, H-3 discharges occurred one to two days prior to the sample collection. The concentrations are roughly 2.5% and 5%, respectively, of the EPA drinking water standard.

11.5 Alqae Filamentous algae attached to rocks along the Lake Michigan shoreline are known to concentrate radionuclides from the water. Co-60 or Cs-I 34 was not detected. However, low concentrations of Co-58 and Cs-137 were detected.

Four of the samples had positive results but only two Cs-137 results were greater than the MDC: 0.023 1 0.010 pCi1g (August 4, 2010 at the PBNP discharge area) and 0.025 10.014 pCiIg (October 6, 2010, at E-05 north of PBNP). In 2010 PBNP did not discharge Cs-137 until August 10, 2010, six days after the algae samples were taken. Therefore, it is unlikely that the observed results are due to PBNP effluents. Because fallout Cs-137 from 1950s and 60s weapons testing is known to still persist in Lake Michigan, the Cs-137 results may be indicative of recycling of fallout Cs-137 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:

1.12 1 0.32 and 2.62 It 1.23 pCiIg respectively. Therefore, the algae monitoring results do not indicate any effect by PBNP upon the environs.

The analyses of 11 fishes produced 7 positive Cs-137 results greater than the MDC. No other radionuclide was detected. The highest Cs-137 concentration 0.055 1 0.026 is comparable to the results from 2005 - 2009. But this is lower than the high of 0.1 72 pCilg in 2005 and considerably lower than the 2.8 pCiIg 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. However, based on the

recycling of fallout Cs-137 in Lake Michigan, atmospheric weapons testing fallout is the most likely source of the observed Cs-137 in fish. This conclusion is supported by the absence of any other radionuclides present in PBNP effluents.

By comparison, the concentration of naturally occurring K-40 (1.I 1-5.86 pCilg) is about 20 -100 times higher than the highest Cs-137 concentration. Based on these results, it is concluded that fish do not indicate an effect of plant effluents.

11.7 Well Water No plant related radionuclides were detected in well water during 2010, as all results were less than the MDC and not significantly different from zero. The gross beta values result from naturally occurring radionuclides. Therefore, it is concluded that there is no evidence of PBNP effluents getting into the aquifer supplying drinking water to PBNP.

Cs-137 is present in the soils throughout North America and the world resulting from the atmospheric nuclear weapons testing in the 1950s, 1960s, and 1970s and from the 1986 Chernobyl accident. 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. Erosion, radioactive decay, and human activities modify the Cs-137 concentrations. Evidence for the latter are the higher Cs-137 concentrations found at E-06, where trees growing and incorporating Cs-137 during the time of atmospheric fallout are now being burned in camp fires thereby releasing the incorporated Cs-137 to the surrounding area. All 2010 samples had low levels of Cs-137 with the highest levels being found at E-06. The results from the indicator sites, except for E-06, are comparable to those from the background site some 17 miles away in the low xIQ 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.

1 1.9 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. Nine of the ten 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 fine particles, such as clay, as opposed to the sand found on the beach. Lake Michigan sediments are a known reservoir of fallout Cs-137. Wave action suspends lake sediments depositing them on the beach. The fine particles deposited on the beach eventually are winnowed from the beach leaving the heavier sand; hence the lower Cs-137 concentrations in beach samples. In contrast to Cs-137, K-40, which is actually part of the minerals making up the clay and sand, is at a

concentration about 100 times higher than the Cs-137 that is attached to particle surfaces. Therefore, it is not surprising that Cs-137 is present at concentrations 1 % or less of the naturally occurring concentrations of K-40. The absence of any PBNP effluent nuclides, such as Co-58/60, other than Cs-137 indicates that the most likely source of the observed Cs-137 is the cycling of radionuclide in the Lake Michigan environment and not current PBNP discharges. This is supported by the fact that PBNP's first discharge of Cs-137 did not occur until August 2010 whereas four of the five shoreline sediment samples from April tested positive for Cs-137. Therefore, the shoreline sediment data indicate no radiological effects from current plant operation.

1 1. I 0 Veqetation 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 breaks up 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 0.061 pCi/g is approximately 2% of the average vegetation Be-7 concentration of 2.64 pCi/g and 1.3% of the average K-40 concentration of 3.88 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 in the ash into the soil where they are available for uptake by growing plants and trees. The campfires also create an airborne Cs-137 source which can spread to surrounding areas.

PBNP airborne effluents contained no Cs-137 during 201 0. Also, no Cs-137 attributable to PBNP was found in the air samples from the area around the site.

[See discussion on air samples in Section 11.3.1 As mentioned in Section 2.6, NextEra previously disposed sewage by land application on certain fields on site.

However, this practice has been discontinued. To check whether any radioactive material could have been incorporated into vegetation via ground uptake, corn and soybeans were obtained and analyzed from a field at the site boundary where the sewage used to be land applied. No licensed material was found during the analyses. However, the naturally occurring radionuclide Be-7 was found at concentrations comparable to those for the same crops obtained over 17 miles away at the REMP background site.

Based on the 2010 vegetation sampling results, it is concluded that no effect from PBNP effluents are indicated.

1 1.1 1 Veqetation C-14 For 2010, the NRC requested that nuclear plants report their C-14 emissions and to determine its impact and dose contribution. The amount of C-14 released was determined by a methodology developed by EPRl for the nuclear industry.

Special sampling and analyses for C-14 were conducted as part of the REMP to assess the C-14 in vegetation, the principal pathway by which the C-14 dose is expressed. Samples of corn and soybeans were obtained from fields at the site boundary in the highest x/Q sector. The same samples were obtained from fields at the REMP background location some 17 miles away. The results from the special vegetation samples collected for C-14 show slightly higher C-14 concentration in the samples collected at the site boundary as compared to the background site (Table 10-3). However, there is no statistical difference between the two locations at the 95% confidence limit.

1 1.12 Land Use Census In accordance with the requirements of Section 2.5 of the Environmental Manual, a visual verification of animals grazing in the vicinity of the PBNP site boundary was completed in 2010. 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 807 environmental samples, and from 128 sets of TLDs that comprised the PBNP REMP for 2010, 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.

13.0 PROGRAM DESCRIPTION PBNP monitors groundwater for tritium. During 2010 the sampling program consisted of seven beach drains, six intermittent stream and bog locations, four drinking water wells, four fa~ade wells, twenty-two yard electrical manholes, six ground water monitoring wells, 27 subsurface drainage (SSD) system manholes, and the Unit 2 facade 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 this observation, modifications were made to the pool, and the tritium concentrations decreased below the effluent LLDs. Beach drain effluents continue to be monitored and are accounted for in the monthly effluent quantification process. Because the beach drains are susceptible to groundwater in-leakage from other sources such as the area around the former retention pond which is known to contain H-3, the beach drains are monitored as part of the groundwater monitoring program.

Three intermittent stream locations and the Energy Information Center (EIC) well were added to the groundwater monitoring program in the late 1990s when it was discovered that tritium diffusion from the then operable, earthen retention pond was observable in the intermittent streams which transverse the site in a NW to SE direction. A fourth stream location closer to the plant was added in 2008. These streams pass on the east and west sides of the former retention pond and empty into Lake Michigan about half a mile south of the plant near the meteorological tower. The intermittent stream samples track H-3 in the surface groundwater.

The groundwater monitoring program also includes two bogs 1 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 system was designed to lessen hydrostatic pressure on the foundation by controlling the flow of water under the plant and around the perimeter of the foundation walls. The SSD system flows to a sump in the Unit 2 facade. The sump was sampled a minimum of once per month during 2010. Access to other parts of the SSD is obtained vial manholes located in the facades, turbine building, and other locations. The manholes were lifted in 201 0 to check of the physical condition of the SSD.

Many holes were dry. When water was found, a sample was obtained. Eight samples were obtained in the facades and 19 in the Turbine Building area.

In the 1990s, two wells were sunk in each unit's fa~ade to monitor the groundwater levels and look at evidence of concrete integrity as part of the IS1 IWE Containment Inspection Program. 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.

14.0 RESULTS 14.1 Streams and Boas The results from the surface groundwater monitoring associated with the former retention pond are presented in Table 14-1. For the most part, the creek results are barely above the detection level. 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 (pCi1l)

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 minimum detectable concentration. The LLD = 200 pCill.

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

None of the samples from the confluence of the two creeks (GW-OI), ESE of the former retention pond, and only three of the West (GW-03) and East (G-02) Creek samples south of the former retention pond have results above the minimum detectable concentration (MDC). In contrast, seven of the results from the north (GW-17) section of the East Creek, near the sewage treatment plant, and from the one bog (E-08) SE of the former retention pond are >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 pCill seen in the late 90s. The E-08 bog result is down from the 3000 pCi/l seen before the pond was remediated in 2002.

14.2 Beach Drains and SSD Sump The 2010 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 2009, S-1 and S-3 were sampled more frequently than once per month. S-I 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 faqade. [Note: In August 2010, a modification rerouted the SSD sump output to an effluent pathway with an in-line monitor.] 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-I I 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-I H-3 concentrations are in the 300 - 700 pCill range with only four in the 1200 - 1400 range. At S-3, the H-3 concentrations are more uniform with one spike at 1334 and another at 1139 pCiIl with neither of the spikes exceeding 3600. Possible H-3 contributions to S-I from groundwater inleakage upstream of this discharge were investigated.

Tritium concentrations in groundwater from the electrical vaults immediately west of S-I were not detectable to very low (Table 14-4). Therefore, the high concentration spikes found at S-I may be attributable to receiving discharges from the SSD sump. The higher H-3 concentrations at S-I during February, June and July occur during the time frame in which the SSD sump H-3 concentrations also are high (Figure 14-2).

Table 14-2 2010 Beach Drain Tritium Average H-3 Concentration (pCill)

Feb 1402 + 132 NF f Mar 468 + 176 NF rt:

APr 377 + 170 NF f May 357 + 260 NF 2 Jun 367 1 567 NF f Jul 407 + 845 NF +

Aug 219 2 245 NF +

SeP 189 + 101 NF f Oct 366 + 114 NF +

Nov 250 + 98 NF +

Dec 239 + 82 NF +

AVG 380 f 254 ND = not detected, <MDC NF = no sample due to no flow Although the H-3 concentrations at S-I are generally lower beginning in August corresponding to the time the discharge from the SSD sump was routed to another discharge path, the continued presence of H-3 indicates other sources,

but unknown at this time. The reason for the two spikes at S-3 (1 139 and 1334 pCi/l) 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. The data from the remaining beach drains from the plant area (S-7 to S-I 1) are sparse in that there is no flow unless there is precipitation or some groundwater intrusion. In contrast, at S-I I 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 2010 H-3 Concentrations for S-I and S-3 Tritium Concentrations (pCill)

-- 1200 g I000 Z :::

8 400 200 g g g g g g g g g g g g C ! C ! C ! C ! C ! C ! C ! C ! C ! C ! C ! C !

S s i S $ S $ S S S S S s i T

T r

Date The SSD sump is located in the Unit 2 fa~ade. The monthly averages are presented in Table 14-3. These results are generally higher than those from S-I, the beach drain to which the sump is pumped. The source of the higher SSD sump tritium concentrations is under investigation. Results of gamma scans of composites for the months of January, February, March, April, and May were below the MDC.

Figure 14-2 2010 H-3 Concentrations SSD SUMP Tritium Concentrations (pCill) 3500 3000 2500

+

h A

3 i

D b

P l

n f

Date

+SSD Sump

Table 14-3 2010 Unit 2 Facade SubsurFace Drain Sump Average H-3 Concentration (pCill) 14.3 Electrical Vaults and Other Manholes Manholes for access to below ground electrical facilities are susceptible to groundwater in-leakage. The east side of the plant, between the Turbine building and Lake Michigan have low H-3 concentrations (Table 14-4) Z-065AIB are directly east of the midpoint of the Turbine Building. The Z-066 and 2-067 series manholes as well at 2-068 are located on the NE section of the yard beginning just north of the Z-065AIB manhole and run in parallel, side-by-side from the Unit 2 truck bay north to the EDG building. Based on being side-by-side, it is not unexpected that the each pair of manholes AIA, BIB, etc. would have nearly the same H-3 concentration.

Table 14-4 2010 East Yard Area Manhole Tritium Average Activity (pCill)

Tritium results from manholes on the west side of the plant have higher H-3 concentrations (Table 14-5). On the west side of the plant there is a pocket of manholes MH-3, -4, and -6, that have higher H-3 concentrations that than those on the east side and the surrounding west side manholes. These H-3 concentrations are similar to the values seen in beach drain S-3. Why the H-3 concentrations in manholes 3, 4, and 6 are higher than the others is not known.

Table 14-5 2010 West Yard Area Manhole Tritium Average Activity (pCi1l) 14.4 Facade Wells Each unit's facade has two wells used to monitor the groundwater for conditions which could impact containment integrity. The samples from these wells are also analyzed for H-3 (Table 14-6). In Unit 2 there is one on each side of containment, approximately 180" apart. The Unit 1 facade wells are east of the containment in the SE (12-361A) and NE (12-361 B) corners of the fa~ade.

Some samples could not be collected because the well cap could not be removed.

Table 14-6 2010 Facade Well Water Tritium H-3 Concentration (pCi1l)

ND = not detected * = average of 2 samples NS = sample not collected

The 2010 results are similar to those obtained in 2008 and 2009. The Unit 2 wells continue to have low H-3 concentrations, only a few of which are above the MDC (22-361B). Well 12-361A, in the SE corner of the Unit 1 faqade, continues to have the highest H-3 concentrations, up to 462 pCi/l, although lower than the 1 169 pCi/l seen in 2008.

Based on these results, the conclusion that H-3 is not evenly distributed under the plant remains valid.

14.5 Potable Water and Monitoring Wells Outside of the protected area, nine wells, in addition to the main plant well (Section 11.7), are used for monitoring H-3 in groundwater: three potable water wells, GW-04 (Energy Information Center or EIC), GW-05 (Warehouse 6), and GW-06 (Site Boundary Control Center), and six H-3 groundwater monitoring wells, GW-11 through GW-16 (Figure 13-1). The potable water wells monitor the deep, drinking water aquifer whereas the monitoring wells penetrate less than 30 feet to monitor the top soil layer. The potable water aquifer is separated from the shallow, surface water aquifer by a thick, impermeable clay layer. Two of the monitoring wells, GW-15 and GW-16, are in the apparent groundwater flow path from the former retention pond. The other four of the surface layer wells are located at the periphery of the area which may be affected by diffusion from the former retention pond.

The potable water wells have no detectable H-3 (Table 14-7).

Table 14-7 2010 Potable Well Water Tritium H-3 Concentration (pCi1l)

Month Jan Feb Mar A P ~

May Jun Jul Aug S ~ P Oct Nov Dee ND EIC WELL GW-04 NS ND ND ND ND ND ND ND ND ND ND NS dot Detected Warehouse 6 Well GW-05 ND ND ND ND NS=No Sam[

SBCC Well GW-06 ND ND ND ND EIC MDC 146 148 149 143 164 159 160 160 154 139 144 -

GW-05,C MDC 154 178 105 160 Two monitoring wells show consistent, detectable H-3 (GW-15, GW-16) in the flow path from the retention pond area to the lake (Table 14-8). The highest H-3 concentrations occur at GW-15, the well closest to the former retention pond.

Table 14-8 2010 Monitoring Well Water Tritium H-3 Concentration (pCill) 14.6 Miscellaneous Sampling In addition to groundwater, analyses have been made of precipitation, rainwater and snow, in order to obtain information on the recapture/washout of H-3 in airborne effluents.

Although there is one occurrence of a H-3 concentration greater than 100 pCi/l at both the south (E-03) and north (E-03) boundaries, most results do not indicate any significant concentrations H-3 at the site boundary (Table 14-9).

Measurements of tritium in the condensate from AC unit condensers for various buildings revealed higher concentrations than the values at the site boundary.

(Table 14-1 0).

Table 14-9 2010 Precipitation H-3 at Boundary Locations Table 14-10 AC CONDENSATE H-3 CONCENTRATIONS Location

~ C i l l 2 0 MDC Based on these results, sampling at locations closer to the plant was initiated to determine the H-3 washout closed to the plant (Table 14-1 1). The lowest Table 14-1 1 2010 H-3 Concentrations Close to Plant

• December = average of 2 samples

November H-3 results show the lowest concentrations occur along the Lake Michigan shoreline (7, 8, and 12) and about 600 yards to the NW (3). The locations closest to the plant (1, 2, 4, and 5) generally have higher H-3 concentrations. The reason for the ti-3 concentrations in precipitation being lower than those found in the AC condensate are not known but may be related to collection method and the time of year which the samples were obtained. That being said, it is evident that the precipitation H-3 concentrations could account for the low H-3 concentrations in the water from the manholes on the east side of the plant (the Z-066, -067, and -068 series) and beach drain S-1 I.

15.0 GROUNDWATER

SUMMARY

Groundwater monitoring indicates that low levels of tritium continue to occur in the upper soil layer but not in the deep, drinking water aquifer. These results also indicate that the low levels of tritium are restricted to a small, well defined area close to the plant. Results from precipitation analyses and from AC condensate analyses show that airborne H-3 concentrations are higher close to the plant as compared to results at the site boundaries. 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.

APPENDIX 1 Environmental, Inc. Midwest Laboratory Final Report for the Point Beach Nuclear Plant and Other Analyses Reporting Period: January - December 201 0

Environmental, Inc.

Midwest Laboratory F Road

• Northbrook. IL 60062-2310 phone (847) 564-0700 fax (847) 564-4517 FINAL REPORT TO NextEra Energy RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

FOR THE POINT BEACH NUCLEAR PLANT TWO RIVERS, WISCONSIN PREPARED AND SUBMITTED BY ENVIRONMENTAL INCORPORATED MIDWEST LABORATORY Project Number: 8006 Reporting Period: January-December, 2010 Distribution:

K. Johansen, 1 hardcopy, 1 e-mail

POINT BEACH NUCLEAR PLANT TABLE OF CONTENTS Section List of Tables 111 1.O INTRODUCTION iv 2.0 LISTING OF MISSED SAMPLES.............................................. v 3

DATA TABLES vi Appendices A

Interlaboratory Comparison Program Results A-I Data Reporting Conventions B-I Sampling Program and Locations C-I Graphs of Data Trends D-1 Supplemental Analyses....................................

....................... E-1 Duplicate Analysis.................................................................... F-I

POINT BEACH NUCLEAR PLANT LIST OF TABLES Airborne Particulates and Iodine-I31 Location E.01. Meteorological Tower 1-1 Location E.02. Site Boundary Control Center 1-2 Location E.03. West Boundary......................................................

1-3 Location E.04. North Boundary....................................................

1-4 Location E.08. G J Francar Residence 1-5 Location E.20. Silver Lake College 1-6 Airborne Particulates. Gamma Isotopic Analyses 2-1 Milk 3-1 Well Water.............................................................................................

4-1 Lake Water.............................................................................................

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

POINT BEACH NUCLEAR PLANT

1.0 INTRODUCTION

The following constitutes the final 2010 Monthly Progress Report for the Environmental Radiological Monitoring Program conducted at the Point Beach Nuclear Plant, Two Rivers, Wisconsin. Results of analyses are presented in the attached tables. Data tables reflect sample analysis results for both Technical Specification requirements and Special Interest locations and samples are randomly selected within the Program monitoring area to provide additional data for cross-comparisons.

For gamma isotopic analyses, the spectrum covers an energy range from 80 to 2048 KeV. Specifically included are Mn-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95, Nb-95, Ru-103, Ru-106, 1-131, Ba-La-140, Cs-134, Cs-137, Ce-141, and Ce-144. Naturally occurring gamma-emitters, such as K-40 and Ra daughters, are frequently detected in soil and sediment samples. Specific isotopes listed are K-40, TI-208, Pb-212, Bi-214, Ra-226 and Ac-228. Unless noted otherwise, the results reported under "Other Gammas" are for Co-60 and may be higher or lower for other radionuclides.

Duplicate analyses are reported in Appendix F unless otherwise noted.

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 LW E-06 01-13-10 Unsafe to obtain.

LW E-06 02-1 1-1 0 Unsafe to obtain APII E-04 03-1 1-1 0 No sample received.

APll E-02 04-07-1 0 No power to sampler.

APII E-04 08-1 8-1 0 Air sampler issues.

APll E-03 10-27-10 Loss of power.

LW E-0 1 12-1 5-1 0 Unsafe to obtain.

LW E-05 12-15-10 Unsafe to obtain.

Unsafe to obtain.

Unsafe to obtain.

POINT BEACH NUCLEAR PLANT 3.0 Data Tables

POINT BEACH NUCLEAR PLANT Table 1. Airbome particulates and charcoal canisters, analyses for gross beta and iodine-I 31.

Location: E-01, Meteorological Tower Units: pci/m3 Collection: Continuous, weekly exchange.

Date Vol.

Date Vol.

Collected (m3)

Gross Beta 1-131 Collected (m3)

Gross Beta 1-131 Reauired LLD o.030 Required LLD o.010 o.030 I

st Quarter 3rd Quarter Mean f s.d.

0.024 f 0.007 < 0.014 Mean f s.d.

0.021 f 0.005 < 0.013 2nd Quarter 4th Quarter Mean f s.d.

0.016 f 0.004 < 0.01 1 Mean f s.d.

0.027 f 0.008 < 0.012 Cumulative Average 0.022 rt 0.007 < 0.013 a "ND" = No data; see Table 2.0, Listing of Missed Samples.

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: 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 0.030 Required LLD o.030 1st Quarter 3rd Quarter Mean + s.d.

0.026 f 0.006 < 0.015 Mean f s.d.

0.022 f 0.004 < 0.013 2nd Quarter 4th Quarter Mean f s.d.

0.017 f 0.005

< 0.013 Mean _+ s.d.

0.026 rt: 0.007 < 0.013 Cumulative Average 0.023 f 0.007 < 0.013

" "ND" = No data; see Table 2.0, Listing of Missed Samples.

POINT BEACH NUCLEAR PLANT Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-? 31.

Location: E-03, West Boundary Units: pci/m3 Collection: Continuous, weekly exchange.

Date Vol.

Date Vol.

Collected (m3)

Gross Beta 1-131 Collected (rn3)

Gross Beta 1-1 31 Reauired LLD O.ol0 o.030 Reauired LLD 0.010 0.030 I

st Quarter 3rd Quarter Mean 1 s.d.

0.024 4 0.006 < 0.014 Mean rf: s.d.

0.022 1 0.006 < 0.013 2nd Quarter 4th Quarter Mean rt s.d.

0.015 f 0.004 < 0.013 Mean rf: s.d.

0.026 f 0.007 < 0.013 Cumulative Average 0.022 rt 0.007 < 0.013

" "ND" = No data; see Table 2.0, Listing of Missed Samples.

POINT BEACH NUCLEAR PLANT Table 1. 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 0.010 0.030 Required LLD 0.010 0.030 1st Quarter 3rd Quarter Mean rf: s.d.

0.023 f 0.008 < 0.014 Mean f s.d.

0.021 f 0.004 < 0.012 2nd Quarter 4th Quarter Mean f s.d.

0.017 f 0.006 < 0.012 Mean f s.d.

0.028 f 0.009 < 0.013 Cumulative Averaae 0.022 f 0.008 < 0.012

""ND" = No data; see Table 2.0, Listing of Missed Samples.

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 0.010 o.030 Required LLD 0.010 0.030 03-11-10 03-17-10 03-24-1 0 03-31-1 0 I st Quarter Mean f s.d.

04 10 04-14-10 04-21-10 04-28-10 05-05-1 0 05-12-10 05-19-1 0 05-26-1 0 06-02-1 0 06-09-10 06-16-10 06-23-1 0 06-30-1 0 09-08-1 0 09-15-10 09-22-1 0 09-29-1 0 3rd Quarter Mean + s.d.

10-06-1 0 10-13-10 10-21-10 1 0 1 0 11-03-10 11-10-10 11-17-10 11-23-10 12-01-10 12-08-1 0 12-15-10 12-21-10 12-29-10 2nd Quarter 4th Quarter Mean -i: s.d.

0.017 -i: 0.005 < 0.012 Mean f s.d.

0.025 2 0.008 < 0.013 Cumulative Average 0.023 f 0.007 < 0.013

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 1-1 31 Collected (m3)

Gross Beta 1-1 31 Required LLD 0.010 0.030 Required LLD 0.01 0 0.030 I

st Quarter 3rd Quarter Mean f s.d.

0.027 t 0.007 < 0.014 Mean f s.d.

0.023 f 0.004 < 0.01 3 2nd Quarter 4th Quarter Mean f s.d.

0.018 f 0.005 < 0.013 Mean rt s.d.

0.026 1: 0.008 < 0.013 Cumulative Average 0.023 + 0.007 < 0.013 All Locations Annual Mean k s.d.

0.022 f 0.007 < 0.013

POINT BEACH NUCLEAR PLANT Table 2. Gamma emitters in quarterly composites of air particulate filters Units: pci/m3 (Other)

(Other)

Location Lab Code Be-7 Be-7 Cs-134 Cs-134 Cs-137 Cs-137 Co-60 (Co60) Volume Req. LLD MDC 0.01 MDC 0.01 MDC (0.10)

MDC m3 1st Quarter 2nd Quarter E-01 EAP-3672 0.074 f 0.013 0.0001 f 0.000 0.0006 -0.0003 i 0.001

< 0.0006

-0.0007 f 0.001

< 0.0007 3987 E-02

- 3673 0.075 f 0.018 0.0008 f 0.001

< 0.0011 0.0000 f 0.001

< 0.0007

-0.0005 f 0.001

< 0.0010 3579 E-03

- 3674 0.088 f 0.018

-0.0004 f 0.001

< 0.0008

-0.0002 f 0.001

< 0.0006

-0.0001 f 0.001

< 0.0010 3785 E-04

- 3675 0.079 f 0.015

-0.0005 f 0.000 0.0007

-0.0003 2 0.001

< 0.0008 0.0003 f 0.001

< 0.0008 4130 E-08

- 3676 0.081 f 0.017

-0.0003 f 0.000

< 0.0004

-0.0001 f 0.001

< 0.0010 0.0001 f 0.001

< 0.0005 3931 E-20

- 3677 0.079 f 0.014 0.0000 f 0.001

< 0.0007 0.0003 f 0.001

< 0.0007

-0.0001 i 0.001

< 0.0008 3930 3rd Quarter EAP-7665

- 7666

- 7667

- 7668

- 7669

- 7670 4th Quarter Annual Meanfs.d.

0.077 f 0.011

-0.0001 f 0.0003

< 0.0007 0.0000 f 0.0002 < 0.0006 0.0001 f 0.0004 < 0.0007

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

E-I I Larnbert Dairy Farm MDC MDC 02-1 0-1 0 MDC Required LLD Collection Date Lab Code EMI-119 EMI-512 EMI-988 K-40 Cs-134 Cs-137 Ba-La-140 Other (CoSO)

MDC MDC MDC Required 04-14-1 0 05-12-10 06-09-10 LLD Collection Date Lab Code EMI-1590 EMI-2337 EMI-2966 3-89 Sr-90 1-131 K-40 Cs-134 CS-1 37 Ba-La-140 Other (Co-60)

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

E-I I Larnbert Daiw Farm MDC MDC MDC Required Collection Date 07-14-10 08-11-10 09-08-1 0 LLD Lab Code EMI-3803 EMI-4464 EMI-5004 K-40 1384 f 108 1 2 6 7 f 9 5 1359 f 112 CS-134

-0.4 i 2.1

< 3.5 1.1f1.3

<2.7 0.3 f 1.6

< 3.3 5.0 CS-137

-1.6 + 2.2

< 2.8 2.2 rt 1.6

< 2.8

-1.1 f 1.6

< 2.3 5.0 Ba-La-140

-4.0 f 1.9

< 1.9

-0.2 i 1.3

< 1.9

-0.8 i 2.0

< 2.9 5.0 Other (Co-60) 1.9 f 2.0

< 3.2 1.4k1.3

<3.0 0.8 f 2.0

< 3.8 15.0 Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-134 Cs-137 Ba-La-140 Other (CoSO) 10-13-10 EMI-5722 0.0 i 0.8 1.3 f 0.4 0.03 f 0.16 1393 f 111

-0.5 f 2.5 1.2 i 2.6

-0.3 f 1.9

-2.4 f 2.3 MDC

< 0.7

< 0.5

< 0.32

< 4.8

< 4.9 c 1.7

< 3.5 11-10-10 EMI-6693

-0.6 k 0.7 1.O f 0.4 0.10 f 0.13 1444 r 118

-1.7 f 2.2

-1.9 i 2.7 1.6 f 2.2 0.4 f 2.9 MDC

< 0.6

< 0.5

< 0.19

< 3.1

< 3.0

< 3.6 c 6.2 12-08-1 0 EMI-7185 0.0 f 0.9 0.8 i 0.3

-0.11 + 0.17 1370 f 105 0.5 + 1.4 0.7 f 2.0 1.9 f 1.6

-0.8 f 1.9 MDC

< 0.9

< 0.5

< 0.32

< 2.6

< 4.1

< 2.4

< 2.3 Required LLD 5.0 1.o 0.5 5.0 5.0 5.0 15.0

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

E-21 Strutz Dairy Farm MDC MDC 02-10-10 MDC Required LLD Collection Date Lab Code EMI-120 EMI-513 EMI-989 K-40 Cs-134 Cs-137 Ba-La-140 Other (Co-60)

MDC

< 0.9

.: 0.6

< 0.38

< 2.7 c 2.7 c 2.0

< 2.6 MDC

< 0.8

< 0.6

< 0.29

< 3.4

< 3.7

< 2.1

< 4.2 MDC

< 0.8

< 0.5

< 0.25

< 2.0 c 2.9

<: 3.2

< 2.8 Required LLD 5.0 1.o 0.5 5.0 5.0 5.0 15.0 Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-134 Cs-137 Ba-La-140 Other (Co-60) 04-14-1 0 EMI-1591 0.3 f 0.8 0.1 f 0.3 0.07 f 0.19 1402 f 97

-0.4 It 1.4 1.1 f 1.6

-2.1 f 1.8

-2.1 f 1.8 05-1 2-1 0 EMI-2338 0.3 t 0.7 0.1 f 0.3 0.09 2 0.16 1415 f 104 0.0 t 1.9

-0.3 f 2.1 0.5 f 1.8

-0.6 f 2.1 06-09-10 EMI-2967 0.3 i 0.7 0.2 f 0.3 0.13 f 0.14 1411 f 112

-1.1 t 1.4 1.8 t 1.8 0.6 f 1.7

-0.6 f 1.9

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

Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 CS-1 34 CS-137 Ba-La-140 Other (Co-60)

Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-134 CS-1 37 Ba-La-140 Other (Co-60) 07-1 4-1 0 EMI-3804

-0.5 f 1.0 0.6 f 0.4 0.05 f 0.14 1461 f 117

-0.8 f 2.0 0.2 f 2.3

-2.9 f 1.7 1.0

• 2.1 10-13-10 EMI-5723 0.3 + 0.7 0.3 f 0.3 0.09 f 0.12 1401 f 118 2.2

• 2.0 2.3 f 2.4 1.0 f 2.0 2.5 t 2.2 MDC

< 1.1

< 0.7

< 0.25

< 3.7

< 2.7

< 2.0

< 3.1 MDC

< 0.7

< 0.5

< 0.22

< 3.6

< 4.4

< 3.2

< 3.3 E-21 Strutz Dairy Farm MDC 08-1 1-10 EMI-4465

-0.1 f 0.8

< 1.3 0.2 f 0.3

< 0.5 0.04 f 0.21

< 0.34 1498 f 94 0.3 f 1.6

< 3.0 0.3 It 1.6

< 2.7

-0.7 f 1.5

< 4.5 1.8f1.7

~ 3. 0 17-10-10 EMI-6694

-0.4 1 0.7 0.5 t 0.4 0.05 t 0.16 1273 t 107

-1.7 t 2.0 1.4 f 1.9 1.2 f 1.6

-1.4 + 2.5 MDC

< 0.6

< 0.7

< 0.28

< 3.2

< 3.7

< 3.8

< 3.9 09-08-10 EMI-5005 0.2 + 0.7 0.4 f 0.3

-0.03 f 0.15 1464 f 102

-1.8 f 1.8 2.1 f 1.9 0.2 f 1.6

-1.3 + 2.1 12-08-1 0 EMI-7186

-0.2 f 0.7 0.4 f 0.3

-0.12 It 0.19 1339 f 117 1.5 f 1.7 0.1 + 2.0

-0.4 r 2.1 0.8 f 1.9 MDC

< 0.7

< 0.5

< 0.28

< 2.3

< 3.2

< 4.6

< 2.9 MDC

< 0.7

< 0.5

< 0.35

< 3.5

< 3.7

< 2.6

< 3.5 Required LLD 5.0 1.o 0.5 5.0 5.0 5.0 15.0 Required LLD 5.0 1.o 0.5 5.0 5.0 5.0 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 01-13-10 02-10-10 03-10-10 LLD Lab Code EMI-121 EMI-514 EMI-990 K-40 Cs-134 CS-137 Ba-La-140 Other (Co-60)

MDC MDC MDC Required Collection Date 04-1 4-1 0 05-12-1 0 06-09-1 0 LLD Lab Code EMI-1592 EMI-2339 EMI-2968 K-40 1462 f 97 1422f105 1560f105 CS-134 0.9 -+ 1.5 c 2.7

-0.2 f 1.4

< 2.8

-0.5 t 1.4

< 2.4 5.0 CS-137 1. 2 f 1. 7

<3.2

-0.8 f 1.7

< 3.2 0.6 f 1.7

< 2.3 5.0 Ba-La-140

-1.I f 1.4

< 2.6

-3.3 f 2.2

< 2.5 0.7 f 1.7

< 4.4 5.0 Other (CoBO)

-0.9 f 2.2

< 1.8 1.4 i 2.0

< 3.8

-1.3 f 1.8

< 2.6 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 07-1 4-1 0 08-1 4-10 09-08-1 0 LLD Lab Code EMI-3805 EMI-4467 EMI-5006 K-40 1489f117 1559f105 1428 f 113 CS-134 1.1i1.6

~ 3. 1 1. 1 f 1. 8

~ 3. 5

-1.O f 1.5

< 2.6 5.0 CS-137 1.3f1.9

<3.8

-0.7 f 2.2

< 2.1

-0.2 f 1.8

< 2.2 5.0 Ba-La-140 1.6 f 1.6

< 4.0

-4.4 f 1.8

< 3.1

-1.0 f 1.4

< 2.5 5.0 Other (Co-60) 0.8 f 1.9

< 3.0 1.4 f 2.1

< 3.8

-1.2 It 1.8

< 3.0 15.0 MDC MDC MDC Required Collection Date 10-13-10 11-10-10 72-08-7 0 LLD Lab Code EMI-5724 EMI-6695 EMI-7187 K-40 1496 f 108 1361 i 90 1495 + 129 CS-134 1.6 f 1.9

< 3.2

-0.1 f 1.6

< 2.4

-1.5 + 2.2

< 4.2 5.0 CS-137

-0.5 ?: 2.2

< 2.9

-0.9 f 1.8

< 2.5

-0.3 f 2.6

< 4.1 5.0 Ba-La-140

-1.3 ?: 1.7

< 4.6

-0.3 rt 1.7

< 4.0 2.0 + 2.3

< 3.8 5.0 Other (Co-60)

-0.9 f 2.0

< 2.9 0.1 f 1.9

< 3.9 1.2 +_ 2.4

< 3.7 15.0 Sr-89 Annual Mean + s.d.

Sr-90 Annual Mean + s.d.

1-131 Annual Mean + s.d.

K4O Annual Mean + s.d.

Cs-134 Annual Mean + s.d.

Cs-137 Annual Mean + s.d.

Ba-La Annual Mean + s.d.

Co-60 Annual Mean + s.d.

POINT BEACH NUCLEAR PLANT Table 4. Radioactivity in Well Water Samples, E-10 Collection: Quarterly Units: pCi/L I

st Qtr.

2nd Qtr.

3rd Qtr.

4th Qtr.

Req.

Annual LLD Mean s.d 01-13-10 EWW-258

-0.4 rt 0.7 26.5 i 73.4 0.1 i 0.7 0.0 It 0.4 0.20 It 0.33

-0.5 i 1.2 2.3 S 2.2

-0.2 i 1.1

-0.1 k 1.3

-1.7 k 2.5

-1.3 It 1.3 0.4 rt 1.2 0.3 + 1.4 0.1 + 1.4 0.6 i 1.2 04-15-10 EWW-1639 0.7 + 0.7 27.4 f 89.2 0.6 + 0.5

-0.2

• 0.2 0.03 i 0.14

-0.2

• 1.7 0.0 i. 2.4

-1.0 rt 1.5 0.7 i 1.5 0.5 i 3.3

-2.9 i 2.0 0.7 rt 1.9 0.2 f 2.0

-2.9 f 1.9 0.4 i 1.6 07-15-10 EWW-3817 1.5 i 0.4 29.2 + 56.0 0.1 rt 0.5 0.1

• 0.2 0.12 i 0.15

-1.2 rt 2.3

-5.9

• 4.3 0.8

• 1.8 1.o r 2.0

-5.0 r 4.8 0.4 i 2.0

-0.4 f 2.3 0.2

• 2.5

-0.5 f 3.2

-0.5 + 2.6 10-15-10 EWW-5882 3.6 r 1.8 56.0 f 82.2 0.4 f 0.5

-0.3 S 0.2 0.04 i 0.14 0.7 r 2.3 0.2 f 4.3 1.4 f 2.0 0.6 k 2.4

-6.5 k 5.2

-2.5 + 2.6 0.4 f 2.4

-1.0 + 2.8

-0.8 i 3.0 0.2 k 2.4 Req.

LLD 4.0 500 5.0 1.o 0.5 10 30 10 10 30 15 10 10 15 30 Collection Date Lab Code Gross Beta H-3 Sf-89 Sr-90 1-131 Mn-54 Fe-59 CO-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Other (Ru-I 03)

MDC Data Collection Date Req.

Lab Code EWW-258 EWW-1639 EWW-3817 EWW-5882 LLD Gross Beta Mn-54 Fe-59 CO-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Other (Ru-103)

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

Localion: E-01 (Meteorological Tower)

Collection: Monthly composites Units: pCiL MDC MDC Lab Code ECW-255 ELW-507 ELW-1037 Date Collected 01-13-10 02-11-10 03-12-10 Gross beta 1.2 t 1.0

< 1.8 1.8 f 1.0

< 1.9 3.3 f 0.7

< 0.9 1-131 0.15 f 0.31

< 0.48 0.10 f 0.12

< 0.17 0.05 i 0.14

< 0.20 Be-7

-2.4 f 11.0

< 27.8 4.4 f 10.5

< 20.2

-3.1 f 16.0

< 28.9 MII-54

-1.2 f 1.3 c 1.9 1.1 f 1.1 c 1.8

-0.9 f 1.6

< 2.7 Fe-59

-1.6 f 2.6

< 4.3

-1.3 f 2.7

< 2.8 1.0 f 3.2

< 4.9 Co-58

-1.0 f 1.2

< 2.1

-0.8 f 1.1 c 1.2

-0.6 I-1.4

< 1.5 Co-60

-0.6 f 1.2

< 1.8 0.5 2 1.3

< 1.1 0.5 f 1.6

< 2.5 Zn-65

-1.1 i 2.5

< 3.4

-1.0 f 2.5

< 2.0

-3.0 f 4.0 c 4.8 Zr-Nb-95 1.5 f 1.3

< 2.5 0.2 f 1.3 c 2.5

-0.8 f 1.7 c 2.4 Cs-134 0.8 i 1.1

< 2.1

-0.3 f 1.2

< 1.8

-0.5 f 1.7

< 3.1 CS-137 0.9 f 1.4

< 3.0 0.8 f 1.5

< 2.8 0.0 f 1.7

< 2.6 Ba-La-140 0.8 f 1.5

< 3.6

-0.4 f 1.3

< 1.9

-0.7 f 1.6

< 3.1 Other(Ru-103)

-0.1 f 1.2

< 2.6 0.3 f 1.3 c 2.0

-1.0 f 1.8 c 2.3 Lab Code Date Coilected 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)

Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 CO-60 Zn-65 Zr-Nb-95 6s-134 CS-137 Ba-La-140 Other (Ru-103)

ELW-2373 05-13-10 3.3 f 2.0

< 3.6 0.11 f 0.16

< 0.31 8.3 f 10.9

< 16.2

-0.1i1.4 c l. 3 0.2 f 2.6

< 4.2

-1.7f1.2 q l. 3 1.0f1.2 c2.1 I

• 2.1 c 3.5

-0.3 f 1.3 s 1.7

-0.5t1.3

~ 1. 8 1. 5 f 1. 5

~ 3. 0

-0.8t1.4

~ 1. 6 0.1 f 1.2

< 2.4 ELW-5197 09-15-10 ELW-3096 06-16-10 ELW-5786 10-14-10 1.350.8

<1.3 0.05 f 0.16

< 0.28

-3.2 f 16.7

< 25.2 4.2 f 1.5

< 2.3 0.2 f 2.8

< 3.7

-1.1 f 1.6

< 2.0

-0.4 f 2.4

< 3.8 2.2 f 3.5

< 4.5

-1.0 f 2.0

< 2.2 0.2 f 2.0

< 3.8 2.0 f 2.0

< 3.6

-1.1 f 2.2

< 2.2 0.9 i 2.0

< 3.4 ELW-3812 07-13-10 ELW-6839 11-17-10 3.8 f 0.9 0.03 f 0.16

-4.0 f 17.2

-1.2 i-1.6

-0.6 f 2.5 1.1 f 1.4 0.2 1: 2.0 4.2 f 3.3

-1.6 f 1.5

-0.5 f 1.8 1.2 f 1.9

-1.1 f 1.8

-3.2 f 2.0 MDC ELW-1635 04-15-10 1.6 f 0.6

< 0.9 0.05 f 0.13

< 0.23

-9.9 f 15.3

< 26.7 0.1 f 1.8

< 3.4 1.0 f 2.9

< 4.8 2.2 f 1.5

< 2.7 0.4 f 1.6

< 1.8

-1.0 f 3.2

< 1.4 0.0 i 1.5

< 2.6

-1.2 i 1.8

< 2.7 0.6 f 1.8

< 2.4 1.6 f 2.0

< 4.4 0.4

• 2.2

< 3.8 ELW-4468 08-11-10 0.8 f 0.9

< 1.8 0.07 f 0.18

< 0.33 10.3 f 20.0

< 35.2 0.0 f 1.7

< 2.3 2.2 f 3.9

< 6.6 0.521.9

< 1. 6 0.8 f 2.1

< 3.1 0.9 f 4.4 c 6.1 0.6 f 1.9 c 2.5 0.6 f 2.0 c 3.2

-0.1 f 2.3

< 4.0 0.6 f 2.5

< 3.2

-0.6 f 2.2

< 2.3 Req. LLD 4.0 0.5 Req. LLD 4.0 0.5 Req. LLD 4.0 0.5

'"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-05 (Two Creeks Park)

Collection: Monthly composites Units: pCilL MDC MDC MDC 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)

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)

ELW-256 01-13-10 0.9 f 0.9

< 1.7

-0.03 f 0.30

< 0.44

-2.4 f 10.5

< 16.0 O. l f 1. 2

~ 1. 9 1.1 f 2.8

< 4.8

-0.1

• 1.3 c 2.8

-0.4 f 1.3 c 1.4

-0.3 f 2.6

< 1.9

-0.8 f 1.2

< 2.9

-1.2i1.3

~ 1. 9 1.0f1.3

~ 2. 0

-0.7 f 1.3

< 4.7

-0.9 f 1.5

< 2.3 ELW-2374 05-13-10 3.5 f 1.8

< 3.1 0.03 i 0.12

< 0.22 ELW-508 02-1 1-10 2.7 f 1.0

< 1.9 0.08 f 0.14

< 0.25 4.4 f 9.5

< 16.5

-0.2 f 1.2

< 2.3 1.2 f 2.2

< 3.1

-1.0 f 1.2

< 1.5

-0.1 f 1.4

< 1.9

-3.2 f 2.2

< 2.6 0.2 f 1.3

< 2.0 0.5 f 1.2

< 2.2

-0.7 It 1.4 c 1.6 1.8i1.5

~ 3. 1

-1.0 f 1.1 c 1.5 ELW-3097 06-16-10 5.6 f 2.1 3.6

-0.11f0.16 c0.30 Lab Code ELW-5198 ELW-5787 Date Collected 09-15-10 10-14-10 Gross beta 1.4f1.0

<1.7 2.2f0.7

~ 1. 2 1-131 0.05 i 0.22

< 0.38 0.16 + 0.20

< 0.34 Be-7 5.9 f 23.6

< 46.4

-7.6 f 17.5

< 33.7 Mn-54 2.0 f 3.1

< 4.0 0.7 f 1.6

< 2.5 Fe-59 1.8 i 4.3

< 7.7

-0.9 f 2.9

< 5.4 Cc-58 1.4 f 2.7

< 3.3 0.9 f 1.7

< 2.2 Co-60 2.3 f 3.1

< 5.3 1.1 f 2.0

< 3.7 Zn-65

-7.9 f 6.2 c 2.4 1.4 f 3.7

< 2.8 Zr-Nb-95

-1.8 f 2.7 c 4.9 0.3 f 1.8

< 2.4 Cs-134

-1.7 f 2.6

< 4.5

-1.4 f 1.8

< 3.0 Cs-137 0.2 f 3.3

< 3.0

-1.0 f 2.0

< 2.2 Ba-La-140

-0.5 f 3.8

< 6.5 1.7 f 1.8

< 3.4 Other(Ru-103)

-1.7 f 3.1

< 6.8

-0.4 f 1.9

< 2.5 a'NS" = NO sample: see Table 2.0, Listing of Missed Samples.

ELW-1038 03-12-10 2.5 f 0.7

< 0.9 0.05 f 0.13

< 0.25

-7.7 f 14.0

< 24.7 O. l f 1. 5

<1.2

-0.4 f 2.6

< 3.8

-0.4 f 1.2

< 1.7

-0.6f1.3

<1.2 0.9 f 3.6 c 4.4 0.3 f 1.3

< 2.7

-0.7 f 1.5

< 2.7 1. 1 f 1. 6

<2.9

-1.6 f 1.7

< 3.1 0.0 f 1.5

< 2.6 ELW-3814 07-14-10 1.0 f 0.3

< 0.4 0.03 f 0.22

< 0.40

-0.2 t 18.3 c 32.9 0.5 It 2.2

< 3.4

-2.0

• 3.9

< 5.4 0.6 f 2.1

< 3.7 1.1 f 2.1

< 1.8 0.5 t 4.5

< 5.0

-2.7 f 1.9

< 2.7 0.0 f 2.3

< 4.0 1.7 t 2.3

< 4.1

-0.3 2 2.5

< 2.9

-0.7 f 2.2

< 3.6 ELW-6840 11-18-10 1.7 f 0.4

< 0.6 0.08 f 0.15

< 0.27

-4.9 f 11.2

< 22.0 1.6 f 1.6

< 2.5 0.6 f 2.7

< 3.8 0.4 f 1.4 c 2.3 0.7 f 1.4

< 2.9

-0.5 f 2.6 4 3.5 1.4f1.8 c3.4

-0.9 f 1.5

< 2.6 I f 1.5

< 2.7

-1.5 f 2.0

< 2.3

-0.3 f 1.5

< 2.2 MDC ELW-1636 04-15-10 1.2 f 0.6

< 0.9

-0.05 f 0.13

< 0.23 16.5 f 17.9 c 34.3 2.8 f 1.7

< 3.1

-2.7 f 3.8

< 5.2

-0.1 f 2.1

< 4.0 0.8f1.7

<1.6 4.2 r 3.9

< 3.4 0.9 f 1.7

< 3.8

-0.6 f 1.9

< 3.1

-1.3 f 2.1

< 2.3 1.3 f 2.0

< 2.4 0.2 f 2.2

< 3.7 ELW-4469 08-12-10

-0.7 f 0.8

< 1.7 0.12 f 0.13

< 0.18 12.5 f 15.3

< 27.1 0.8 f 1.6

< 2.7 0.4 f 3.3

< 5.2 0.1 f 1.5 c 2.6

-0.2 f 1.7

< 3.6

-0.8 _C 3.5

< 2.7 0.4 f 1.5

< 2.9

-0.1 f 1.7

< 3.2 0.0 f 1.8 c 3.7 0.2 i 1.9

< 2.8

-0.9 2 1.7

< 1.9 Req. LLD 4.0 0.5 Req. LLD 4.0 0.5 Req. LLD 4.0 0.5

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

Location: E-06 (Coast Guard Station)

Collection: Monlhiy composites Units: pCiL MDC MDC MDC MDC Lab Code NS" NSa ELW-1039 ELW-1637 Date Collected 01-13-10 02-11-10 03-12-10 04-15-10 Req. LLD Gross bet?

1.8 + 0.6

< 0.9 2.5 f 0.7

< 0.9 4.0 1-131 0.09 + 0.18

< 0.31 0.14 f 0.19

< 0.36 0.5 Be-7

-2.8 i 11.4

< 22.7

-16.6 i 16.1

< 24.4 Mn-54

-0.2 f 1.6

< 2.5 1.1 i 1.7

< 3.4 10 Fe-59 1.4 f 2.7 c 5.2

-2.7 f 3.7

< 2.4 30 Co-58 0. 0 f 1. 3

<1.7

-1.3f1.6 c2.1 10 CO-60 1.3 f 1.5

< 2.7 0.1 f 1.9

< 3.5 10 Zn-65

-0.8 f 2.7

< 4.3

-3.6 f 3.9

< 3.3 30 Zr-Nb-95

-2.3f1.5

<1.8

-0.4f1.4 c1.9 15 Cs-134

-0.4 f 1.2

< 2.7 0.8 f 1.6

< 2.9 10 Cs-137

-0.3 f 1.5

< 2.9

-0.5 f 1.9

< 2.4 10 Ba-La-140 2.4 f 1.6

< 2.1

-4.0 f 1.6

< 1.5 15 Other (Ru-103) 1.0 f 1.2

< 2.8

-0.4 f 1.9

< 2.8 30 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)

Lab Code Date Coliected 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)

ELW-2375 05-13-10 2.6 f 1.9

< 3.5

-0.02 f 0.12

< 0.22 1.6 f 16.1

< 23.1 1.0 f 1.6

< 2.4 0.1 f 3.4

< 6.1 1.1f1.6

~ 2. 4 0.3 f 1.5

< 2.2 1.7 5 4.0

< 7.2 0.4 f 1.6 c 1.8 0.7 f 1.6

< 2.9 0.2 f 1.8

< 3.4 1. 1 f 1. 3

~ 1. 3

-0.9 f 1.8

< 2.7 ELW-5200 09-15-10 2.4f1.0

<1.6 0.13f0.16

<0.28 20.5 f 13.3

< 28.8 1.Of1.5

~ 2. 3

-2.8 f 3.0

< 4.1

-1.6 f 1.6

< 1.7 0.7 f 1.3 T 3.2 2.5 f 3.4

< 4.8 1.5

• 1.8

< 4.0

-0.9 f 1.5

< 3.4

-0.8 5 1.5

< 2.4 0.8 f 1.6 c 2.5 0.0 f 1.6 c 4.1 ELW-3098 06-16-10 4.7 f 1.9

< 3.2 0.04 f 0.14

< 0.24

-3.5 f 13.6

< 23.5 0.5 f 1.6

< 2.6

-1.6 t 2.4

< 2.9 0.2 f 1.5

< 2.6

-0.7 f 1.7

< 2.0 0.7 f 3.0

< 3.7

-1.5f1.7

< 2. 7 5.6 f 1.3

< 2.6

-0.2 f 1.7

< 2.8 2.0 f 2.0

< 4.7

-0.4 f 1.4

< 2.6 ELW-5788 10-14-10 1.750.8 c1.3 0.02 f 0.17

< 0.31

-14.9 f 24.0

< 35.0 0.5 f 2.3

< 3.4 0.6 f 4.7

< 7.4

-0.8 f 2.3

< 4.2 1.6 f 2.5

< 3.6

-1.9 r 5.2

< 3.9 0.2 f 2.0

< 3.8 0.1 f 2.4

< 3.9 1.3 f 2.3

< 4.3 7.8 f 2.8

< 4.2

-0.6 f 2.2

< 2.8 ELW-3815 07-13-10 0.9 f 0.3

< 0.4 0.17 f 0.18

< 0.25

-0.2 f 18.2

< 29.5 0.6 i 1.7

< 2.3 1.5 It 3.1

< 6.3

-0.5 f 1.8

< 3.1 2.0 2.4

< 3.5 1.2 f 3.7

< 5.2

-0.9 f 1.8

< 2.4

-0.5 f 1.9

< 2.9

-0.2 f 2.1

< 2.6 0.6 f 2.2

< 3.4

-1.3 + 2.1

< 3.8 ELW-6841 11-18-10 1.7 f 0.5

< 0.6

-0.01 f 0.17

< 0.31 7.8 f 23.7

< 50.1

-0.7 f 3.3

< 5.3 2.9 f 5.9 4 6.8 0.2 f 2.9

< 4.8 1.5 f 3.1

< 5.2

-4.158.0

<7.7 1.3 f 3.2

< 6.4

-1.8 f 3.2 c 5.0 2.8 f 3.1

< 4.6

-5.2 f 4.0

< 5.2

-1.4 f 2.8

< 4.6 ELW-4470 08-11-10 l.Ofl.O C1.8 0.10 f 0.13

< 0.18

-13.0 f 12.5

< 29.9 1.Of1.4

<2.6 1.0 f 2.4

< 5.9 0.3 f 1.3

< 2.6

-0.3 f 1.8

< 3.0 0.8 r 2.7 c 3.5

-1.4 f 1.6 c 2.8

-0.4 f 1.5

< 2.5 1.0 f 1.6

< 2.6

-4.3 f 1.5

< 6.6 0.9 f 1.3

< 3.9 Req. LLD 4.0 0.5 NSa 12-15-10 Req. LLD 4.0 0.5 a"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-33 (Nature Conservancy)

Collection: Monthly composites Units: pCi/L MDC MDC MDC Lab Code ELW-257 ELW-509 ELW-1040 Date Collected 01-13-10 02-11-10 03-12-10 Gross beta 1.6 i 1.0 c 1.8 2.5 f 1.0 1.8 0.7 f 0.5

< 0.9 1-131 0.46 f 0.34

< 0.49

-0.03 f 0.14

< 0.25 0.12 f 0.17

< 0.30 Be-7

-16.6f13.1

~ 1 6. 6 -4.3f9.2

< 10.8

-12.9 f 11.8

<20.2 Mn-54

-1.6 f 1.5

< 1.8 0.6 f 1.3

< 2.4 0.7 f 1.3

< 2.5 Fe-59 1.9 f 2.8 c 5.8 0.4 f 2.1 c 3.2

-3.0 f 2.4

< 2.8 Co-58

-0.2 f 1.3

< 1.7

-0.3 f 1.1

< 1.4 0.4 f 1.5

< 2.6 Cc-60 1.3 f 1 6

< 2.5 0.3 t 1.0 c 2.0 1.1 f 1.8

< 2.5 211-65

-2.0 f 2.6

< 3.9 0.2 f 2.1

< 2.9

-0.4 f 2.2

< 2.6 Zr-Nb-95 0.3 f 1.4

< 2.9 0.0 f 1.3

< 1.7

-2.0 C 1.6

< 2.0 Cs-134

-0.6 f 1.4 c 2.1 0.3 f 1.1

< 1.9

-0.1 f 1.3

< 1.8 Cs-137 0.5 i 1.5

< 2.2 0.4 f 1.3

< 2.5 0.0 f 1.7

< 2.6 Ba-La-140

-2.9 f 1.6

< 4.7 0.7 f 1.7

< 2.1

-0.9 f 1.6

< 4.0 Other(Ru-103) 0.9 f 1.4

< 2.6

-0.9 f 1.1

< 1 4

-0.1 f 1.1

< 2.1 Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Cc-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Other (Ru-103)

ELW-2376 05 0.5 f 1.9 0.09 f 0.14

-2.1 i 14.6 0.4 f 1.6 0.8 f 3.3

-1.7 f 1.6

-1.1 f 1.9

-2.8 f 4.3 0.5 f 1.6 0.7 f 1.6

-0.4 f 1.9

-1.3 f 2.1

-0.2 f 1.9 ELW-3099 06-16 1.7 f 1.0

-0.05 i 0.13

-6.3 f 12.8

-0.2 f 1.5

-1.5 f 2.7 0.3 f 1.4 0.5 f 1.7

-1.4 f 3.3

-1.9 f 1.8 1.4f 1.7 0.1 f 1.8 1.4 f 1.5 1.1 f 1.5 ELW-3816 07-14-10 1.2 f 0.3

< 0.4 0.12 f 0.23

< 0.45

-3.5 f 19.8

< 39.9 1.7 f 2.0

< 3.2 3.6 t 3.8

< 4.4 1.8 f 2.0

< 3.2 0.3 f 2.5

< 3.8 0.4 f 4.0

< 4.9

-0.6 f 2.2

< 3.8 1.1 2 2.0

< 3.7 0.6 f 2.2

< 4.2 2.2 It 2.6 c 2.6 1.6 i: 22.

2 5.2 Lab Code ELW-5201 ELW-5789 ELW-6842 Date Collected 09-15-10 10-14-10 11-18-10 Gross beta 1.0 f 1.0

< 1.8 1.9i0.8

~ 1. 3 1.1f0.4

~ 0. 6 1-131 0.10 f 0.12

< 0.17 0.08 f 0.16

< 0.29 0.08 f 0.13 c 0.19 Be-7 3.0 f 12.6

< 30.3 7.2 f 20.7

< 40.0 2.0 f 11.7

< 29.1 Mn-54 0.9 f 1.5

< 2.3

-0.6 f 2.1 c 3.3 0.9 t 1.2

< 2.3 Fe-59

-0.7 f 2.6

< 3.5 0.4 i 4.3

< 6.2

-0.1 f 2.8

< 3.7 CO-58 1.6 f 1.3

< 2.7 1.1 f 2.1

< 4.5 0.9 f 1.3

< 1.5 Co-60

-1.2 i 1.7

< 2.6

-0.6 f 2.2

< 3.8 0.5 1 1. 3

< 2.4 Zn-65

-2.0 f 2.8

< 2.2 1.9 f 4.3 c 4.6

-2.3 f 2.6

< 2.7 Zr-Nb-95 0.9 f 1.5

< 3.1 0.6 f 1.9

< 3.8

-2.1 f 1.5

< 1.9 CS-134 0.0 f 1.6 2 3.0

-0.3 f 2. 4

< 4.1

-0.9 % 1.4

< 1.9 CS-137

-0.2 f 1.6

< 2.3

-0.4 f 2.3 3.9 0.1 f 1.5

< 2.1 Ba-La-I 40

-0.4 f 1.6

< 4.4

-0.3 f 2.5 c 3.2

-0.9 f 1.7

< 3.1 Other (Ru-103) 1.3 f 1.4

< 2.7

-2.0 f 2.2 c 3.2 0.0 f 1.2

< 2.0 a"NS = No sample; see Table 2.0. Listing of Missed Samples.

MDC ELW-1638 04-15-10 1.0 f 0.5

< 0.8 0.11 f 0.15

< 0.25 21.0 f 14.0

< 29.6 0.2 f 1.5

< 2.5 5.2 f 2.5

< 3.8 0.4f1.5

<1.9

-1.5f1.7 c 1. 3 0.5 f 2.4

< 2.5

-3.3 i 1.7

< 1.8

-0.6 f 1.6

< 2.4 0.0 f 1.7

< 2.0

-1.7 f 1.5 s 2.1 0.8 f 1.3 c 2.7 ELW-4471 08-12 0.2 f 0.8

-0.01 It 0.11

-12.4 2 13.8 1.6 i: 1.6 0.3 12.3

-0.6 f 1.5 0.0 i: 1.2 0.1 f 3.0

-1.1 i: 1.6 5. 4 f 1.2 0.1 f 1.4

-3.6 f 1.9

-2.2 f 1.4 NS' 12-15-10 Req. LCD 4.O 0.5 Req. LLD 4.0 0.5 10 30 10 10 30 15 10 10 15 30 All locations Annual Req. LLD Mean s.d.

4.0 1.8 t 1.2 0.5 0.07 t 0.09 0.1 t 9.8 10 0.4 t 0.9 30 0.1 t 1.5 10 0.1 f 9.0 10 0.3 t 0.9 30

-0.3 t 2.4 15

-0.5 t 1.2 10

-0.2 f 0.8 10 0.3 t 0.9 15

-0.3 f 1.8 30

-0.3 t 1.0

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

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

Period 1st Qtr.

MDC 2nd Qtr.

MDC 3rd Qtr.

MDC 4th Qtr.

MDC Lab Code ELW-1070 ELW-3145 ELW-5668 ELW-7585 Req. LLDs Location E-05 (Two Creeks Park)

Period 1st Qtr.

2nd Qtr.

3rd Qtr.

4th Qtr.

Lab Code ELW-1071 ELW-3146 ELW-5669 ELW-7586 Req. LLDs H-3 2 3 i 7 8

< I 4 5 1 1 7 f 9 8

< I 5 2 9 7 i 1 0 1

< I 5 9 4 3 1 f 1 0 4 a < 1 4 1 500 Sr-89

-0.05 i 0.60 c 0.75 0.51 i 0.71

< 0.74 0.00 i 1.18

< 1.39

-0.08 f1.40

< 1.41 5.0 Sr-90 0.18 t0.27

< 0.53 0.23 t 0.30

< 0.59 0.15 f 0.31

< 0.62 0.29 k0.30

< 0.57 1.0 Location E-06 (Coast Guard Station)

Period 1st Qtr.

2nd Qtr.

3rd Qtr.

4th Qtr.

Lab Code ELW-1072 ELW-3147 ELW-5670 ELW-7587 Req. LLDs Location E-33 (Nature Consewancy)

Period 1st Qtr.

2nd Qtr.

3rd Qtr.

4th Qtr.

Lab Code ELW-1073 ELW-3148 ELW-5671 ELW-7588 Req. LLDs a Tritium reanalyzed with a result of 391i97 pCiiL. October sample tritium = 8282109 pCi/L; November = 20+75 pCi/L.

Tritium reanalyzed with a result of 797i118 pCilL. October sample tritium = 490+97 pCiiL; November = 11 39i119 pCi/L.

Tritium Annual Mean + s.d.

136 k 168 Sr-89 Annual Mean + s.d.

0.1 0 t 0.32 9-90 Annual Mean + s.d.

0.25 + 0.1 0

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

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

LLD Collection Date 01-28-10 02-08-1 0 08-25-1 0 Lab Code EF-1032 EF-1033 EF-4756 TY pe Burbot King Salmon Lake Trout Ratio (wetldry wt.)

Gross Beta K-40 Mn-54 Fe-59 CO-58 Co-60 Zn-65 CS-1 34 CS-137 Other (Ru-103)

Collection Date 08-25-1 0 Lab Code EF-4757 Type Unknowna Ratio (wetldry wt.)

6.58 Gross Beta 1.1 1 + 0.05

< 0.027 1 1-04-1 0 EF-6564 Lake Trout 3.35 5.86 + 0.1 1

< 0.031 11 1 0 EF-6565 Lake Trout 3.43' 3.87 + 0.08 0.031 Mn-54 Fe-59 CO-58 Co-60 Zn-65 CS-1 34 Cs-137 Other (Ru-103) a Small sample size; specimen yielded only 63 gr of flesh

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

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

Req.

MDC MDC MDC LLD Collection Date 11-04-10 Lab Code EF-6567 Type Lake Trout Ratio (wetldry wt.)

4.31 1 1-04-1 0 EF-6568 Salmon 4.68 1 1-04-1 0 EF-6569 Salmon 4.94 Gross Beta 3.67 rt 0.08

< 0.025 Mn-54 Fe-59 CO-58 Co-60 Zn-65 Cs-I 34 CS-137 Other (Ru-103)

Collection Date 11-04-10 Lab Code EF-6570 Type Brook Trout Ratio (wetJdry wt.)

7.77 1 1-04-1 0 EF-6571 Rainbow Trout 6.98 Annual Mean s.d.

2.81 i: 1.48 Gross Beta 1.82 r 0.05

< 0.023 K-40 Mn-54 Fe-59 CO-58 Co-60 Zn-65 CS-1 34 CS-1 37 Other (Ru-103)

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

MDC MDC MDC Collection Date 4/15/2010 4/15/2010 4/15/2010 Req.

Lab Code ESS-1839 ESS-1840 ESS-1841 LLD Location E-0 1 E-05 E-06 Gross Beta 14.52 f 1.24

< 1.38 9.32 f 1.04

< 1.24 10.00 f 1.02

< 1.19 2.0 Collection Date Lab Code Location Gross Beta 4/15/2010 ESS-1842 411 51201 0 ESS-1843

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

Sample Description and Concentration (pCi/g dry)

MDC MDC MDC Collection Date 10/14/2010 10/14/2010 10114/2010 Req.

Lab Code ESS-5892 ESS-5893 ESS-5894 LLD Location E-01 E-05 E-06 Gross Beta 8.96 t 1.26

< 1.77 6.78 t 1.08

< 1.54 12.72 c 1.35

< 1.75 2.0 Collection Date 10114/2010 10/14/2010 Lab Code ESS-5895 ESS-5896 Location E-12 E-33 Annual Mean s.d.

Gross Beta 9.46 t 1.16

< 1.53 14.45 t 1.39

< 1.73 2.0 10.69 f 2.53

POINT BEACH NUCLEAR PLANT Table 9. Radioactivity in soil samples Collection: Semiannual Sample Description and Concentration (pCilg dry)

MDC MDC MDC Collection Date 5/26/20 10 5/26/2010 5/26/20? 0 Req.

Lab Code ESO-2727 ESO-2728 ESO-2729 LLD Location E-01 E-02 E-03 Gross Beta 31.18f1.33

<1.26 29.38f1.22

<1.09 39.23f1.38

< ?. I 7 2.0 Collection Date 5/26/20 1 0 Lab Code ESO-2731 5/26/201 0 ESO-2732 5/26/2010 ESO-2733 Location E-04 E-06 E-08 Gross Beta 33.11 f 1.35

< 1.24 30.06 f 1.59

< 1.51 26.01 r 1.39

< 1.38 2.0 Collection Date 5/26/20 1 0 Lab Code ESO-2734 5/26/2010 ESO-2735 Location E-09 E-20 Gross Beta 39.65 f 2.15

< 1.96 37.81 f 2.12

< 1.89 2.0

POINT BEACH NUCLEAR PLANT Table 9. Radioactivity in soil samples Collection: Semiannual Collection Date Lab Code Location Gross Beta Collection Date Lab Code Location Gross Beta Collection Date Lab Code Location Gross Beta Sample Description and Concentration (pCi@ dry)

MDC MDC MDC 10/2712010 1 0/28/2010 10/28/2010 Req.

ESO-6331 ESO-6332 ESO-6333 LLD 10/28/2010 10/28/2010 10/28/2010 ESO-6334 ESO-6335 ESO-6336 1012812010 1 0/2812010 ESO-6338 ESO-6339 Annual E-09 E-20 Mean s.d.

POINT BEACH NUCLEAR PLANT Table 70. Radioactivity in vegetation samples Collection: Tri-annual Sample Description and Concentration (pCilg wet)

MDC E-02 5/26/2010 EG-2696 MDC E-03 5/26/2010 EG-2697 MDC Location Collection Date Lab Code E-01 5/26/201 0 EG-2695 Ratio (wetldry)

Gross Beta Be-7 K-4 0 1-131 Cs-134 Cs-137 Other (Co-60)

Location Collection Date Lab Code E-04 5/26/2010 EG-2698 E-06 5/26/2010 EG-2699 E-08 5/26/2010 EG-2700 Ratio (wevdry)

Gross Beta Be-7 K-40 1-131 Cs-134 CS-137 Other (Co-60)

E-20 5/26/2010 EG-2702 Location Collection Date Lab Code E-09 5/26/2010 EG-2701 Ratio (wevdry)

Gross Beta Be-7 K-40 1-131 Cs-134 CS-1 37 Other (Co-60)

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

MDC MDC E-02 71281201 0 EG-4035 MDC E-03 7/28/20 10 EG-4036 Location Collection Date Lab Code E-01 7/28/2010 EG-4034 Ratio (wetldry)

Gross Beta Be-7 K-40 1-131 CS-134 Cs-137 Other (Co-60)

Location Collection Date Lab Code E-04 7/28/2010 EG-4038 E-06 7/28/2010 EG-4039 E-08 7/28/2010 EG-4040 Ratio (wetldry)

Gross Beta Be-7 K-40 1-131 CS-134 CS-137 Other (Co-60)

Location Collection Date Lab Code E-09 7/28/2010 EG-4041 E-20 7/28/201 0 EG-4042 Ratio (weUdry)

Gross Beta Be-7 K-40 1-131 CS-134 CS-137 Other (Co-60)

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

MDC Location E-01 Collection Date 9/30/2010 Lab Code EG-5450 MDC E-02 9/8/201 0 EG-5451 Corn MDC E-02 9/8/2010 EG-5452 Soybeans Req. LLD Ratio (wetldry)

Gross Beta H-3b Be-7 K-40 1-131 Cs-134 CS-137 Other (CoBO)

Location Collection Date Lab Code Ratio (wetldry)

Gross Beta Be-7 K-40 1-131 CS-134 CS-137 Other (Co-60)

E-03 9/30/2010 EG-5453 4.37 6.96 t 0.17

< 0.064 2.20 t 0.20 4.91 t 0.39

-0.001 t 0.007

< 0.029

-0.002 t 0.008

< 0.016 0.014 t 0.008

< 0.014 0.001 + 0.009

< 0.018 E-04 9/30/2010 EG-5454 4.41 8.21 t 0.20

< 0.073 1.29 t 0.18 4.79 t 0.36 0.012 t 0.006

< 0.016 0.001 t 0.007

< 0.012

-0.004 t 0.007

< 0.01 1

-0.004 t 0.008

< 0.008 E-06 9/30/2010 EG-5455 3.87 4.56 t 0.13 c 0.050 0.93 k 0.16 2.84 + 0.32

-0.009 t 0.007

< 0.017 0.002 + 0.007

< 0.012 0.061 t 0.021

< 0.018 0.005 t 0.007

< 0.014 Req. LLD Location E-08 Collection Date 9/30/2010 Lab Code EG-5456 E-09 9/30/2010 EG-5457 E-20 9/8/2010 EG-5458 Corn Req. LLD Ratio (wetldry)

Gross Beta H-3 Be-7 K-40 1-131 Cs-134 CS-137 Other (Co-60)

Location E-20 Collection Date 9/8/2010 Lab Code EG-5459 Soybeans Ratio (weUdry)

Gross Beta ND' H-3 139.0 + 83.9

< 159 Req. LLD Be-7 1.55 t 0.12 K-40 3.88 t 0.17 1-131

-0.013 i 0.003

< 0.048 CS-134

-0,001 t 0.003

< 0.005 Cs-137 0.001 t 0.003

< 0.006 Other (Co-60) 0.000 1: 0.003 c 0.006

" "ND" = No data; gross beta analysis not required.

Tritium units = pCi/L Gross Beta Annual Mean + s.d 6.83 f 1.21 Be-7 Annual Mean + s.d.

2.32 f 1.84 K-40 Annual Mean + s.d.

5.04 f 1.46 1-131 Annual Mean + s.d. -0.002 f 0.009 Cs-134 Annual Mean + s.d. -0.001 f 0.005 Cs-137 Annual Mean + s.d. 0.004 f 0.012 Co-60 Annual Mean + s.d. 0.002 f 0.006

POINT BEACH NUCLEAR PLANT Table 11. Aquatic Vegetation, analyses for gross beta and gamma emitting isotopes.

Collection: Triannual Units: pCilg wet Sample Description and Concentration Collection Date Lab Code Location Ratio (wet wt.ldry wt.)

Gross Beta Be-7 K-4 0 CO-58 CO-60 CS-1 34 CS-137 Collection Date Lab Code Location Ratio (wet wt.ldry wt.)

Gross Beta Be-7 K-40 CO-58 Co-60 CS-134 CS-137 Collection Date Lab Code Location Ratio (wet wt./dry wt.)

Gross Beta Be-7 K-40 CO-58 Co-60 CS-134 CS-137 06-09-1 0 ESL-2970 E-05 5.10 4.67 i 0.15 1.60 rt 0.22 2.03 rt 0.28 0.01 1 It: 0.008

-0.003 rt 0.009 0.000 It 0.008 0.018 + 0.010 08-04-1 0 ESL-4243 E-05 8.09 2.45 It: 0.13 0.97 It 0.28 2.01 rt 0.33 0.003 rt 0.007

-0.002 f 0,009

-0.001 f 0.008 0.002 4 0.009 10-06-1 0 ESL-5631 E-05 7.30 1.85 + 0.14 0.69 2 0.20 1.69 2 0.31

-0.01 1 F 0.007

-0.004 f 0.009 0.005 + 0.007 0.025 5 0.014 MDC

< 0.12

< 0.15

< 0.016

< 0.008

< 0.012

< 0.019

< 0.10

< 0.14

< 0.012

< 0.014

< 0.014

< 0.011

< 0.14

< 0.12

< 0.015

< 0.013

< 0.012

< 0.016 06-09-1 0 ESL-2971 E-12 2.48 6.48 It 0.33 1.15 rt 0.26 5.05 k 0.58 0.010 2 0.011

-0.002 2 0.013

-0.004 + 0.009 0.01 1 f 0.013 08-04-1 0 ESL-4244 E-12 6.48 2.63 rt 0.17 1.37 rt 0.23 2.54 It: 0.31 0.000 + 0.007 0.005 + 0.009 0.003 5 0.006 0.023 2 0.010 10-06-10 ESL-5632 E-12 5.19 3.13 f 0.25 0.97 2 0.22 2.37 2 0.37

-0.005 _+ 0.010 0.007 f 0.01 1

-0.004 k 0.009 0.018 2 0.01 1 MDC

< 0.33

< 0.20

< 0.022

< 0.019

< 0.018

.: 0.024

< 0.16

< 0.88

< 0.013

< 0.013

< 0.008

< 0.009

< 0.25

< 0.12

< 0.019

< 0.015

< 0.014

< 0.020 Req.

LLD 0.25 0.25 0.25 0.25 0.25 Req.

LLD Req.

LLD Annual Mean s.d.

POINT BEACH NUCLEAR PLANT Table 12.

Ambient Gamma Radiation LLD17days: < I mRITLD 1st. Quarter, 2010 Date Annealed:

12-01-09 Days in the field 85 Date Placed:

01-06-10 Days from Annealing Date Removed:

04-01-10 to Readout:

127 Date Read:

04-07-10 Days in Location indicator E-I E-2 E-3 E-4 E-5 E-6 E-7 E-8 E-9 E-12 E-14 E-15 E-16 E-17 E-18 E-22 E-23 E-24 E-25 E-26 E-27 E-28 E-29 E-30 E-31 E-32 E-38 E-39 E-41 E-42 E-43 Control E-20 Field Total mR Net mR Net mR per 7 days In-Transit Exposure Date Annealed 12-01-09 03-08-10 Date Read 01-13-10 04-07-1 0 Total mR ITC-1 6.5 It- 0.5 3.0 + 0.1 ITC-2 6.2 rf: 0.3 3.1 +_ 0.1

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation 2nd Quarter, 2010 Date Annealed:

03-08-1 0 Days in the field 97 Date Placed:

04-01-10 Days from Annealing Date Removed:

07-07-1 0 to Readout:

126 Date Read:

07-12-10 Days in Location Field Total mR Net mR Net mR per 7 days Indicator Control E-20 97 17.8 + 0.7 13.9 + 0.8 1.OO + 0.06 In-Transit Exposure Date Annealed 03-08-1 0 06-09-1 0 Date Read 04-07-1 0 07-12-10 Total mR ITC-1 3.0 + 0.1 4.9 + 0.4 ITC-2 3.1 + 0.1 4.6 + 0.1

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation 3rd Quarter, 201 0 Date Annealed:

06-09-10 Days in the field 90 Date Placed:

07-08-1 0 Days from Annealing Date Removed:

10-06-10 to Readout:

125 Date Read:

10-12-10 Days in Location Field Total mR Net mR Net mR per 7 days Indicator E-I 90 14.2 + 0.8 9.8 + 0.9 0.76 rt 0.07 E-2 90 18.9 + 0.3 14.5 + 0.6 1.13 k0.04 E-3 90 22.9 + 1.6 18.5 + 1.7 1.44 a 0.13 E-4 90 18.5 1.3 14.1 + 1.4 1.09 20.11 E-5 90 19.0 + 1.1 14.6 + 1.2 1.I3 + 0.09 E-6 90 18.2 + 1.O 13.8 f 1.1 1.07 + 0.09 E-7 90 18.6 1.0 14.2 + 1.1 1.10 k0.09 E-8 90 17.6 + 0.6 13.2 f 0.8 1.02 + 0.06 E-9 90 20.3 + 0.7 15.9 + 0.8 1.23 + 0.07 E-12 90 15.2 rtr 0.3 10.8 + 0.6 0.84 + 0.04 E-14 90 19.1 -+ 0.5 14.7 + 0.7 1.14 + 0.05 E-15 90 19.9 + 0.7 15.5 + 0.8 1.20 + 0.07 E-16 90 18.3 + 0.4 13.9 + 0.6 1.08 + 0.05 E-I7 90 19.1 + 0.6 14.7 + 0.8 1.14 + 0.06 E-18 90 19.9 + 1.1 15.5 + 1.2 1.20 + 0.09 E-22 90 19.9 k 1.2 15.5 + 1.3 1.20 +0.10 E-23 90 19.5 + 0.3 15.1 + 0.6 1.I7 + 0.04 E-24 90 19.3 + 0.6 14.9 + 0.8 1.16 _+ 0.06 E-25 90 18.8 + 0.2 14.4 + 0.5 1.12 + 0.04 E-26 90 17.3 + 0.5 12.9 + 0.7 1.OO + 0.05 E-27 90 21.3 + 0.4 16.9 + 0.6 1.31 + 0.05 E-28 90 14.6 + 0.4 10.2 + 0.6 0.79 + 0.05 E-29 90 15.4 + 0.8 11.0 rt 0.9 0.85 + 0.07 E-30 90 17.7 It 1.2 13.3 f 1.3 1.03 rtO.10 E-31 90 19.6 + 0.8 15.2 + 0.9 1.18 k0.07 E-32 90 21.6 + 0.8 17.2 + 0.9 1.34 + 0.07 E-38 90 18.6 + 1.3 14.2 + 1.4 1.10 + 0.11 E-39 90 16.3 + 0.5 11.9 +0.7 0.92 + 0.05 E-41 90 16.7 + 0.6 12.3 + 0.8 0.95 + 0.06 E-42 90 17.7 + 0.6 13.3 + 0.8 1.03 rt 0.06 E-43 90 17.7 + 0.4 13.3 + 0.6 1.03 + 0.05 Control E-20 90 18.5 + 0.9 14.1 5 1.0 1.09 + 0.08 In-Transit Exposure Date Annealed 06-09-1 0 09-09-1 0 Date Read 07-1 2-1 0 10-12-10 Total mR ITC-I 4.9 + 0.4 4.1 + 0.2 ITC-2 4.6 kO.1 4.1 + 0.1

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation 4th Quarter, 2010 Date Annealed:

09-09-1 0 Days in the field 89 Date Placed:

10-08-10 Days from Annealing Date Removed:

01 1 I to Readout:

124 Date Read:

01-11-11 Days in Location Field Total mR Net mR Net mR per 7 days Indicator E-I 89 15.4 i 0.8 11.5 + 0.9 0.90 + 0.07 E -2 89 20.9 i 1.0 17.0 + 1.1 1.34 i 0.08 E-3 89 22.1 rt 1.6 18.2 i 1.6 1.43 k 0.13 E-4 89 18.3 $ 0.2 14.4 rt 0.4 1.13 rir 0.03 E-5 89 19.8 $ 0.4 15.9 k 0.5 1.25 $ 0.04 E-6 89 18.1 + 1.2 14.2 i 1.3 1.1f k 0.10 E-7 89 17.5 + 0.3 13.6 k 0.5 1.07 i 0.04 E-8 89 18.3 + 0.8 14.4 i 0.9 1.13 $ 0.07 E-9 89 20.5 + 1.0 16.6 2 1.1 1.30 + 0.08 E-12 89 15.2 + 1.1 11.3 $ 1.2 0.89 tt 0.09 E-14 89 18.4 k 0.5 14.5 k 0.6 1.14 -+ 0.05 E-15 89 21.4 i 0.7 17.5 k 0.8 1.37 2 0.06 E-16 89 18.2 i 0.3 14.3 k 0.5 1.12 $ 0.04 E-17 89 18.4 i 1.1 14.5 + 1.2 1.I4 k 0.09 E-18 89 19.4 i 0.4 15.5 k0.5 1.22 k 0.04 E-22 89 18.6 i 0.5 14.7 k 0.6 1.15 $0.05 E-23 89 20.6 i 0.7 16.7 k0.8 1.31 +- 0.06 E-24 89 18.9 $ 0.3 15.0 k 0.5 1.18 + 0.04 E-25 89 20.3 2 0.2 16.4 k 0.4 1.29 i 0.03 E-26 89 17.4 k 0.6 13.5 i 0.7 1.06 It 0.06 E-27 89 21.5 i 0.6 17.6 k 0.7 1.38 + 0.06 E-28 89 15.4 i 0.3 11.5 k0.5 0.90 $ 0.04 E-29 89 15.8 $ 0.5 11.9 k0.6 0.93 k 0.05 E-30 89 18.3 i 1.0 14.4 $ 1.1 1.13 $0.08 E-31 89 20.2 k 1.7 16.3 $ 1.7 1.28 $0.14 E-32 89 20.1 i 0.1 16.2 $ 0.4 1.27.t 0.03 E-38 89 17.6 k 0.4 13.7 k 0.5 1.08 5 0.04 E-39 89 17.0 k 0.4 13.1 rt 0.5 1.03 -+ 0.04 E-41 89 18.0 k 0.5 14.1 $ 0.6 1.11 k0.05 E-42 89 19.1 k 0.4 15.2 i 0.5 1.19 k 0.04 E-43 89 16.9 k 0.6 13.0 rt 0.7 1.02 k 0.06 Control E-20 89 18.1 + 0.8 14.2 4 0.9 1.11 + 0.07 ln-Transit Exposure Date Annealed 09-09-1 0 12-13-10 Date Read 10-12-10 01-11-1 1 Total mR ITC-1 4.1 + 0.2 3.8 $ 0.2 ITC-2 4.1 k 0.1 3.7 k 0.2 Annual Indicator Mean+s.d.

18.5 E 1.9 14.3 2 1.9 1.11 0.15 Annual Control Mean+s.d.

18.4 + 0.6 14.2 +. 0.3 1.10 0.08 Annual IndicatorlControl Mean+s.d.

18.5 f 1.9 14.3 f 1.9 1.11 0.15 12-4

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

Sample ID GW-01 GW-02 Collection MDC Collection MOC Date Lab Code Tritium (pCilL)

(pCi)

Date Lab Code Tritium (pCi1L)

(pcv~)

01 1 0 NSa 01-27-10 NSa 02-26-10 NSa 02-26-1 0 NSa 03-24-10 EWW-1215 88 1 7 8

< 148 03-24-10 EWW-1216 202 f 84

< 148 04-28-1 0 E W - 21 01 76 f 78

< 149 04-28-10 EWW-2103 61 f 77

< 149 05-26-10 EWW-271 1 137 f 83

< 144 05-26-10 EWW-2712 228 f 83

< 143 06-30-10 EWW-3392 4 7 f 8 4

< I 6 4 06-30-10 EWW-3393 95 t 86

< 164 07-29-10 EWW-4251 49 f 86

< 159 07-29-10 EWW-4252 85 f 88

< 159 08-25-1 0 EWW-4727 8 6 ~ 8 8 < I 6 0 08-25-10 EWW-4728 45 f 86

< 160 09-29-10 EWW-5427 2 5 2 8 6

~ 1 6 0 09-29-10 EWW-5428 173 t 93

< 160 10-27-10 EWW-6320 110 1: 87

< 154 10-27-10 EWW-6321 40 f 83

< 154 12-01-10 EWW-7063 74 t 73

< 139 12-01-10 E W - 7 0 6 4 1 1 0 f 7 5

< I 3 9 Mean + s.d.

77 i 34 Mean + s.d.

115 f 69 Sample ID GW-03 GW-17 Collection MDC Collection MDC Dale Lab Code Tritium (pCiIL)

(pcii)

Date Lab Code Tritium (pCi/L)

(PC&)

01-27-10 NSa 01-27-10 EWW-289 135 f 83

< 154 02-26-10 NSa 02-26-1 0 NSa 03-24-10 EWW-121 7 3 1 2 7 5

< I 4 8 03-24-10 E W - 1 2 1 9 1 7 9 f 8 3

<148 04-28-10 EWW-2104 7 8 i 7 8

< I 4 9 04-28-10 EWW-2106 190 f 84

< 149 05-26-10 EWW-2713 201 f 82

< 143 05-26-10 EWW-2717 238 f 84

< 143 06-30-10 EWW-3395 5 1 i 8 4

< I 6 4 06-30-1 0 E W - 3397 272 i 95

< 164 07-29-10 EWW-4253 3 0 f 8 5

< I 5 9 07-29-10 EWW-4255 85 t 88

< 159 08-25-10 EWW-4729 3 2 2 8 6

< I 6 0 08-25-10 EWW-4731 110 f 89

< 160 09-29-10 EWW-5429

- 3 f 8 4

< I 6 0 09-29-10 EWW-5431 167 i 93

< 160 10-27-10 EWW-6322 5 1 2 8 4

< I 5 4 10-27-10 EWW-6324 108 f 87 2 154 12-01 -10 EWW-7065 2 7 f 7 0

<139 12-01-10 EWW-7067 1 0 8 f 7 5

< I 3 9 12-28-10 EWW-7411 151 t 79

< 144 Mean + s.d.

55 f 59 Mean + s.d.

159 f 58 Wells Sample ID GW-04 (EIC Well)

GW-11 (MW-1)

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

(pcvl)

Date Lab Code Tritium (pCilL)

(pca) 01-28-10 NSa 01-22-10 EWW-1167 5 9 f 9 6

~ 1 5 3 02-26-10 EWW-71 1

- 8 i 7 2

<146 02-26-10 EWW-712 55 f 75 146 03-24-10 EWW-1218 2 f 7 3

<148 03-18-10 EWW-1171 92 f 96 c 152 04-28-10 EWW-2105

-25 f 72

< 149 04-23-10 EWW-2265 60 f 80 c 147 05-26-10 EWW-2714 8 2 f 7 5

<143 05-26-10 EWW-2721 149 f 79 c 143 06-30-10 EWW-3396

-61 f 78

< 164 06-25-10 EWW-3458 82 f 88

< 160 07-29-1 0 EWW-4254 2 8 f 8 5

< I 5 9 07-29-1 0 EWW-4245 11 f 84 c 159 08-25-10 EWW-4730 37 f 86

< 160 08-19-10 EWW-4855 105 f 82

< 154 09-29-10 EWW-5430 8 f 8 5

< I 6 0 09-24-70 EWW-5624 101 f 82

< 159 10-28-1 0 EWW-6323 2 0 i 8 2

< I 5 4 10-19-10 EWW-6325 181 f 90

< 154 12-01-10 EWW-7066 6 8 f 7 3

< I 3 9 11-22-10 EWW-6919 131 f 82

< 144 12-28-10 EWW-7410

- 5 k 7 1 c.144 12-20-10 EWW-7355 46 f 82

< 161 Mean + s.d.

13 i 41 Mean + s.d.

89 f 48 a "NS" = no sample; not sent

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

Sample ID GW-12 (MW-2)

GW-13 (MW-6)

Collection M DC Collection MDC Date Lab Code Tritium (pCilL)

(pen)

Date Lab Code Tritium (pCilL)

(PC&)

01-22-10 EWW-1168

- 2 7 i 9 2

< I 5 3 01-22-10 EWW-1169 5 7 f 9 6

<153 02-26-10 EWW-713 2 f 7 3

<146 02-26-10 EWW-714 43 f 75 c 146 03-18-10 EWW-1172 1 5 f 9 3

<152 03-18-10 EWW-1174 27 f 93

< 152 04-23-1 0 EWW-2266

- 9 f 7 7

< I 4 7 04-23-10 EWW-2267 98 f 62

< 147 05-26-10 EWW-2722 68 f 75

< 143 05-26-10 EWW-2723 212 f 82 c 143 06-25-1 0 EWW-3459 3 4 f 8 6

<160 06-25-10 EWW-3460 80 f 88 c 160 07-29-10 EWW-4246

- 8 f 8 3

< I 5 9 07-29-10 EWW-4247 57 f 86

< 159 08-19-10 EWW-4656 4 f 7 6

~ 1 5 4 08-19-10 EWW-4857 41 f 79

< 154 09-24-1 0 EWW-5625 31 f 78 159 09-241 0 EWW-5627 103 f 82

< 159 10-19-10 EWW-6326 1 8 f 8 2

< I 5 4 10-19-10 EWW-6327 108 f 87

< 154 11-22-10 EWW-6920

-69 f 72 144 11-22-10 EWW-6921 8 1 f 8 0 c144 12-20-1 0 EWW-7356

-88 f 75 c 161 12-20-10 EWW-7357 88 f 84

< 161 Mean + s.d.

-3 f 43 Mean + s.d.

83 f 48 Sample ID GW-14 (MW-5)

GW-15 (MW4)

Collection MDC Collection MDC Dale Lab Code Tritium (pCi/L)

(PC&)

Date Lab Code Tritium (pCIIL)

(pcii) 01-22-10 EWW-1170 19 f 94

< 153 01-28-10 EWW-424 422 f 96

< 152 02-26-10 EWW-71 5 1 4 1 f 8 0

< I 4 6 02-26-10 EWW-716 388 f 92

< 146 03-18-10 EWW-1175 1 7 f 9 3

<152 03-18-10 EWW-1176 3 7 4 f 1 0 8

<152 04-23-10 EWW-2268 142 f 85

< 147 04-23-1 0 EWW-2269 359 f 95

< 147 05-26-10 EWW-2724 133 f 78

< 143 05-26-1 0 EWW-2725 486 f 95

< 143 06-25-10 EWW-3461 126 f 90

< 160 06-25-10 EWW-3462 379 f 102

< 160 07-29-1 0 EWW-4248 9 8 f 8 8

<159 07-29-10 EWW-4249 363 f 100

< 159 08-19-10 EWW-4858 9 0 f 8 1

~ 1 5 4 08-19-10 EWW-4859 393 f 96

< 154 09-24-10 EWW-5628 112 f 82

< 159 09-24-10 EWW-5629 464 f 99

< 159 10-19-10 EWW-6328 198 f 91

< 154 10-19-10 EWW-6329 441 f 102

< 154 11-22-10 EWW-6922 123 f 82

< 144 11 1 0 EWW-6924 337 f 92

< 144 12-20-10 EWW-7358 95 f 84

< 161 12-20-10 EWW-7359 378 f 97

< 161 Mean + s.d.

108 f 51 Mean + s.d.

398 f 45 Sample ID GW-16 (MW-3)

Collection MDC Date Lab Code Tritium (pCilL)

(PC&)

01-28-10 NSa 02-26-1 0 NSa 03-18-10 NSa 04-23-10 EWW-2270 298 f 92

< 147 05-26-10 EWW-2726 301 t 87

< 143 06-25-10 EWW-3463 237 f 96

< 160 07-29-10 EWW-4250 212 f 94

< 159 08-19-10 EWW-4860 235 f 89

< 154 09-24-10 EWW-5630 31 9 f 93

< 159 10-19-10 EWW-6330 2 6 0 f 9 4

<154 11-22-10 EWW-6925 240 f 88

< 144 12-20-10 EWW-7360 207 f 89

< 161 Mean + s.d.

257 f 41 a "NS" = no sample; not sent

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

Beach Drains Sample ID Collection Date 01-07-10 02-18-10 03-01-10 03-04-1 0 03-04-1 0 03-06-10 03-08-1 0 03-10-10 03-17-10 03-22-10 03-24-10 03-26-10 03-29-1 0 03-31-10 04-02-1 0 04-05-10 04-07-10 04-07-1 0 04-09-1 0 04-12-10 04-14-10 04-16-10 04-19-10 04-21-10 04-23-1 0 04-26-1 0 04-29-10 04-30-10 05-03-1 0 05-05-10 05-05-1 0 05-07-10 05-10-10 05-12-10 05-14-1 0 05-1 7-1 0 05-19-10 05-21-10 05-24-10 05-26-10 05-28-10 06-01-10 06-02-1 0 06-04-10 06-07-10 06-09-10 06-10-10 06-1 1-10 06-15-10 06-1 6-10 06-18-10 06-21-10 06-23-1 0 Lab Code EW-75 EW-609 EW-901 suz EW-888 7m EW-902 EW-903 EW-1098 EW-1099 EW-1282 EW-1283 EW-1426 EW-1284 EW-1427 EW-1428 EW-1429 EW-1551 EW-1522 EW-1552 EW-1553 EW-1644 EW-1645 EW-1647 EW-1967 EW-1968 EW-1969 EW-21 18 EW-2119 EW-2120 EW-2271 EW-2242 EW-2272 EW-2273 EW-2402 EW-2403 EW-2404 EW-2543 EW-2544 EW-2546 EW-2676 EW-2877 EW-2678 EW-2879 EW-3018 EW-3020 EW-3021 EW-3022 EW-2978 EW-3023 EW-3129 EW-3130 EW-3131 EW-3305 EW-3306 Tritium (pCiiL) 111 f 102 1402 f 132 354 i 105 395 f 94 324 f 104 513 f 111 429 f 97 652 f 106 536 f 111 464 f 108 485 f 105 455 + 107 522 i 107 488 rt 105 470 f 105 494 f 105 259 f 99 387 f 102 579 f 108 313 f 100 312 f 100 365 f 102 365 f 104 332 f 102 390 i 104 320 f 106 374 f 108 322 f 106 371 i 95 170 f 90 209 f 88 289 1: 91 238 f 63 247 f 83 655 101 443 f 105 359 i 102 388 t 103 478 i 99 405 r 96 388 f 95 336 f 93 1216 f 130 819 f 116 265 f 93 250 i 92 304 i 93 154 t 87 154 f 104 243 f 108 416 i 115 287 f 95 201 f 91 MDC (PC&)

< 161

< 146 c 149

< 151

< 149

< 149

< 145

< 145 c 146 c 145 c 187 145 z 167

< 167

< 167

< 165 c 144

< 165 c 165

< 178

< 178 c 178

< 171 c 171

< 171

< 151

< 151

< 151

< 147

< 156

< 147

< 147

< 142

< 142

< 142

< 142

< 142

< 142

< 145

< 145

< 145

< 145

< 160

< 160

< 160

< 160

< 149

< 160

< 160 c 160 s 180

< 154

< 154 s-1 Collection Date 06-25-10 06-28-10 06-30-1 0 07-02-1 0 07-06-10 07-06-10 07-09-10 07-1 2-1 0 07-13-10 07-1 6-1 0 07-19-10 07-21-10 07-23-10 07-28-10 07-30-1 0 08-02-10 08-04-10 08-04-10 08-06-10 08-09-1 0 08-11-10 08-13-10 09-10-10 10-07-1 0 11-01-10 12-09-10 Lab Code EW-3307 EW-3505 EW-3506 EW-3507 EW-351 1 EW-3575 EW-3576 EW-3829 EW-3630 EW-3831 EW-3944 EW-3945 EW-3946 EW-4256 EW-4257 EW-4364 EW-4365 EW-4260 EW-4366 EW-4496 EW-4497 EW-4498 EW-5070 EW-5653 EW-6717 EW-7300 MDC Tritium (pCi/L)

( p c u ~ )

361 f 99

< 154 272 f 96

< 166 229 f 94

< 166 245 f 94

< 186 1289i135 <166 1319 f 147

< 164 346f114

< I 6 4 161 i 68

< 104 266 f 71

< 104 1 6 3 i 8 9

< I 5 6 221 t 93

< 157 191 f 92

< 157 262f103

< I 7 8 181 f 95

< 164 234 A 97 c 164 257 f 108

< 188 351 f 111

< 188 301 t 98

< 159 255 f 108

< 188 5 0 f 8 6

< I 5 8 43 f 85

< 156 275 f 96

< 158 189C101

< I 5 3 366i114

< I 6 6 250 i 98

< 165 239A82

~ 1 4 1 Mean + s.d.

380 f 254

POINT BEACH NUCLEAR PLANT Table 13. Ground~~ater Tritium Monitoring Program (Monthly Collections)

Sample ID S-3 Collection MDC Collection MDC Date Lab Code Tritium (pCiiL)

(pCI/L)

Date Lab Code Tritium (pCilL)

(PC&)

EW-76 EW-61 1 728 EW-904 EW-889 7.12 EW-906 1221 EW-907 EW-1100 EW-1101 EW-1285 EW-1287 EW-1288 EW-1289 EW-1430 EW-1431 EW-1432 EW-1554 EW-1523 EW-1556 EW-1557 EW-1648 EW-1649 EW-1650 EW-1970 EW-1971 EW-1972 EW-2121 EW-2122 EW-2123 EW-2274 EW-2243 EW-2275 EW-2276 EW-2405 EW-2406 EW-2407 EW-2546 EW-2547 EW-2548 EW-2881 EW-2882 EW-2883 EW-2884 EW-3024 EW-3025 EW-3026 EW-3027 EW-2979 EW-3028 EW-3132 EW-3133 EW-3134 EW-3308 EW-3309 EW-331 1 EW-3508 EW-3509 EW-3510 EW-3512 EW-3577 EW-3578 EW-3832 EW-3833 EW-3834 EW-3947 EW-3948 EW-3949 EW-4258 EW-4259 EW-4367 EW-4368 EW-4261 EW-4369 EW-4499 EW-4500 EW-4501 EW-5071 EW-5654 EW-6718 EW-7301 Mean + s.d.

435 i 173

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

Sample ID S-7 S-8 Collection MDC Collection MDC Date Lab Code Tritium (pCill)

(pcvl)

Date Lab Code Tritium (pCdL)

(pcin) 01-07-10 NSa 01-07-10 NSa 02-18-10 NSa 02-18-10 NSa 03-31-10 NSa 03-31-10 NSa 04-30-10 NSa 04-30-10 NSa 05-31-10 NSa 05-31-10 NSa 06-30-1 0 NS" 06-30-10 NSa 07-29-1 0 NSa 07-29-10 NSa 08-25-10 NS' 08-25-10 NSa 09-30-10 NSa 09-30-10 NSa 10-27-10 NSa 10-27-10 NSa 11-01-10 NSa 11-01-10 NSa 12-09-10 NSa 12-09-10 NSa Mean + s.d.

Mean + s.d.

Sample ID S-9 S-10 Collection MDC Collection MDC Date Lab Code Tritium (pCilL)

(pC'fi)

Date Lab Code Tritium (pCiL)

(PC&)

NSa EW-612 66 f 80 NSa EW-1524 165 i 95 EW-1558 224 1: 96 EW-2244 531 i 108 EW-2277 577 i 104 NSa NSa NSa NSa NSa NSa 12-09-10 NSa Mean + s.d.

312 f 228 Mean + s.d.

Sample ID S-11 Collection MDC Date Lab Code Tritium (pCilL)

(PC'&)

EW-1290 EW-1525 EW-1559 EW-1560 EW-1651 EW-1652 EW-1653 EW-1973 EW-1974 04-23-10 04-26-10 05-05-10 05-05-10 06-10-10 07-06-10 07-12-10 08-25-10 09-30-10 10-27-10 11-01-10 12-09-10 Mean + s.d.

EW-1975 161 f 96

< 171 EW-2124 1 2 5 f 9 7

< I 5 1 EW-2245 1 9 f 8 3

~ 1 5 6 EW-2278 85 f 82

< 147 EW-2980 1 5 5 f 8 6

<149 EW-3514 1 1 1 f 8 8

~ 1 6 6 EW-3835 105 f 86

< 156 NSa NSa NSa NSa a "NS" = no sample; not sent.

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program Sample ID Collection Date Lab Code EW-274 EW-275 EW-276 EW-277 EW-278 EW-908 EW-909 EW-910 EW-595 EW-596 EW-911 EW-912 EW-913 EW-914 EW-915 EW-916 EW-917 EW-918 EW-597 EW-598 EW-919 EW-920 EW-921 EW-922 EW-923 EW-924 EW-925 EW-927 EW-1902 EW-1903 EW-1904 EW-1905 EW-1906 EW-1907 EW-1908 EW-1909 EW-1911 EW-1912 EW-1913 EW-1914 EW-1915 EW-1916 EW-1917 EW-1918 EW-1919 EW-1920 EW-2322 EW-2323 Units = pCi/L U2 Fagade Subsurface Drain Sump Collection Tritium (pCi1L)

MDC Date Lab Code (pCilL) 550 f 102

< 155 04-23-10 EW-2324 560 f 103

< 155 04-26-10 EW-2325 853 f 114

< 155 04-28-10 EW-2327 497f100

< I 5 5 04-30-10 EW-2328 685 f 108

< 155 05-03-1 0 EW-2329 2109 f 152

< 148 05 10 EW-2744 2114f152

< I 4 8 05-07-10 EW-2745 587f104

< I 4 8 05-10-10 EW-2746 580 f 104

< 147 05-1 2-1 0 EW-2747 1072f122

< I 4 7 05-14-10 EW-2740 696 f 108

< 148 05-17-10 EW-2741 637 f 106

< 148 05-19-10 EW-2742 542 f 99

< 148 05-21-10 EW-2743 579 t 101

< 148 05-24-10 EW-4054 678f105

< I 4 8 05-26-10 EW-4055 672 f 105

< 148 05-28-1 0 EW-4056 649 r 104

< 148 05-31-10 EW-2981 657 t 104

< 148 06-02-10 EW-2982 3288 f 181

< 147 06-04-10 EW-2983 2694 i 167

< 146 06-07-10 EW-3135 2105 f 151

< 148 06-09-10 EW-3136 18862145

< I 4 8 06-1 1-90 EW-3137 1656f138

< I 4 7 06-14-10 EW-3464 1521f.134

< I 4 7 06-16-10 EW-3465 1370f.129

< I 4 7 06-18-10 EW-3466 1490 f 133

< 147 06-21-10 EW-3467 716 f 106

< 147 06-23-10 EW-3468 564f100

< I 4 7 06-25-10 EW-3469 618 f 114

< 145 06-28-1 0 EW-4057 576 f 113

< 145 06-30-10 EW-4058 652 f 116

< 145 07-05-1 0 EW-4059 1083f131

< I 4 5 07-07-10 EW-4060 705 f 118 c 145 07-09-10 EW-4061 627f115

< I 4 5 07-12-10 EW-4062 468 f 108

< 145 07-14-10 EW-4063 1529f.145

< I 4 5 07-1 6-1 0 EW-4065 545f111

< I 4 5 07-19-10 EW-4066 764f120

< I 4 5 07-21-10 EW-4067 684 f 117

< 145 07-23-$0 EW-4068 701 f 117

< 145 07-26-1 0 EW-4361 645 1116

< 147 07-28-1 0 EW-4362 2027 c 158 c 147 07-30-10 EW-4363 1242 f 135

< 147 08-02-10 EW-4629 552f111

< I 4 4 08-04-10 EW-4630 1295*137

< I 4 4 08-06-10 EW-4631 617 f 114

< 147 08-09-10 EW-4626 465 t 95

< 145 08-1 1-10 EW-4628 623 f 102

< 145 08-16-10 EW-4758 Tritium (pCilL)

MDC (PCI/L) 556 i 99

< 145 399 f 92 r 145 1446f132

< I 4 5 370 f 91 i 145 487f96

< I 4 5 657 i 103

< 143 631 t 102

< 143 856t110

~ 1 4 3 687 t 104

< 143 629t101

< I 4 3 1051 f 117

< 143 818 t 109

< 143 1080 f 118

< 143 715 r 114

< 157 781

• 117

< 157 615 f 110

< 157 604 f 106

< 149 1001.e 120

< 149 1607 f 140

< 149 916 f 133

< 161 771 f 128

< 160 550f120

< I 6 0 502+107

< I 6 0 414 f 103

< 160 436f104

< I 6 0 549f109

< I 6 0 514 t 107

< 160 573f110

< I 6 0 951f122

< I 5 7 809%117

< I 5 7 639 f 111

< 156 1415 i 137

< 156 502f105

<I56 4915105

<156 469f104

< I 5 6 829f118

<I56 509f105

< I 5 6 357 f 99

< 156 312 f 97

< 156 549f101

< I 5 1 341 f 92

< 151 514 f 100 s 151 342 f 94

< 154 485 f 100

< 154 400 f 96

< 154 391f96

< I 5 4 424 f 97

< 154 446 i 104

< 160

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program Units = pCilL Sample ID U2 F a ~ a d e Subsurface Drain Sump (cont.)

Collection Lab Code Tritium (pCiiC)

MDC Collection Date Lab Code Tritium (pCi1L)

MDC Date (pci/~)

(pCilL)

EW-4759 EW-4861 EW-5135 EW-5134 EW-5471 EW-5812 EW-5813 EW-5814 EW-6294 EW-6296 EW-6716 EW-6853 EW-7068 521f107

< I 6 0 1 1-22-1 0 EW-7302 429 f 91

< 141 496f100

< I 5 4 11-29-10 EW-7303 665 f 101

< 141 659f111

< I 5 5 12-06-10 EW-7412 470 It 94

< 144 530 + 106

< 155 12-13-10 EW-7414 708f103 4 4 4 8985122

< I 6 0 12-20-10 EW-7415 479 i 94

< 144 618 f 106

< 158 12-27-10 EW-7438 603 f 99

< 144 488 f 100 c 158 816 f 113

< 158 1681 f 146

< 154 8 4 8 f 1 1 8

< I 5 4 8862123

< I 6 5 521 f 106

< 163 520 f 94

< 139 Mean + s.d.

819 f 513

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program Manholes Sample ID MH 2-065A MH 2-0656 Collection Collection Date Lab Code Tritium (pCiIL)

MX Date Lab Code Tritium (pCilL)

~ o c (pCVL)

(pCilL) 03-15-10 EW-1053 139 i 85

< 149 03-15-10 EW-1054 158 i 86

< 149 Mean + s.d.

Mean + s.d.

Sample ID MH 2-065C MH 2-065D Col'ection Lab Code Tritium (pCilL)

MDC Collection Lab Code Date Tritium (pCilL)

MDC Date (PCilL)

(~Cifl) 03-15-10 EW-1055 447 i 99

< 149 03-15-10 EW-1056 643 i 107

< 149 Mean + s.d.

Mean + s.d.

Sample ID MH 2-066A MH 2-0668 Collection Lab Code Tritium (pCi/L)

MoC Lab Code Date Tritium (pCi/L)

MDC Date (pcifl)

(PC~A) 03-11-10 EW-1044 146k86 4 4 9 03-11-10 EW-1045 220 f 89

< 149 04-06-10 EW-1947 215598 4 7 2 Gross beta EW-1947 55.8 + 3.4

< 3.6 11-03-10 EW-6546 1 1 4 i 9 0 4 6 1 Mean + s.d.

158 + 52 Mean + s.d.

Sample ID MH 2-066C MH 2-066D Collection Lab Code Tritium (pCiiL)

MDC Collection Lab Code Date (pCi/L)

Date (pCiR)

Tritium (pCi/L)

MDC 03-11-10 EW-1046 150 i 86

< 149 03-11-10 EW-1047 65 t 82

< 149 04-06-10 EW-1948 81 ir 93

< 172 Gross beta EW-1948 649.9 10.2

< 5.1 a

Mean + s.d.

116 k 48 Mean + s.d Sample ID MH 2-067A MH 2-0676 Lab Code Tritium (pCilL)

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

MDC (pCi1L)

(pCilL) 03-1 1-10 EW-1048 156 i 86

< 149 03-11-10 EW-1049 201 i 88

< 149 04-06-10 EW-1949 218 r 99

< 147 1 1-03-1 0 EW-6547 136 i: 91

< 161 Mean + s.d.

170 i 43 Mean + s.d.

a Due to high weight of suspended solids only 50 mL. of sample analyzed; counted for 1000 minutes.

POINT BEACH NUCLEAR PLANT Manholes (cont.)

Sample ID MH Z-067C MH Z-067D Coltection Lab Code Tritium (pCi/L)

MDC Collection Date Lab Code Tritium (pCiR)

"DC Date (PCW (PC~W 03-11-10 EW-1050 96

• 83

< 149 03-1 1-1 0 EW-1051 71

• 82

< 149 Mean + s.d.

Mean + s.d Sample ID MH 2-068 MH-3 Collection Lab Code Tritium (pCilL)

MDC Lab Code Date Tritium (pCilL)

Date (pci~i)

(PC~L) 03-1 1-10 EW-1052 453 i 99

< 149 04-04-10 EW-1941 375 f 105

< 147 05-04-1 0 EW-2984 237 f 90

< 150 11-03-10 EW-6548 111 f 90

< 161 Mean + s.d.

267 f 173 Mean + s.d 04-04-1 0 EW-1942 479 f 109

< 147 04-05-10 EW-1943 464 f 109

< 147 Mean + s.d.

Mean + s.d.

Sample ID MH-7 MH-8 Collection Lab Code Date Tritium (pCi/L)

MDC Lab Code Date Tritium (pCi/L)

MDC IpCiR)

IpClL) 04-05-1 0 EW-1944 196 98

< 147 04-05-1 0 EW-1945 173 i 97 c 147 Mean + s.d.

Mean + s.d.

Sample ID 04-04-10 EW-1946 296 f 102

< 147 Mean + s.d.

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

Sample ID GW-05 (WH 6 Well)

GW-06 (SBCC Well)

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

(~c~IL)

Date Lab Code Tritium (pCi/L)

(~c~IL) 01-13-10 EWW-259

-23 f 75

< 154 01-13-10 EWW-260

- 3 6 i 7 5

< I 5 4 04-15-10 EWW-1654

-40 f 86

< 178 04-15-10 EWW-1655

-73

• 85

< 178 07-15-10 EWW-3818 11 f 55

< 105 07-15-10 EWW-3819 2 r 55

< 105 10-14-10 EWW-5883 30 fr 81

< 160 10-15-10 EWW-5884 34 i 81

< 160 Mean + s.d.

-6 f 32 Mean + s.d.

-18 i 46 Sample ID GW-09 1Z-361A GW-09 12-3618 Collection MDC Collection MDC Date Lab Code Tritium (pCilL)

(pCiiL)

Date Lab Code Tritium (pCi/L)

( p ~ i ~ )

01 10 EWW-1658 393 f 106

< 147 01-27-10 EWW-1659 1 1 1 f 9 4

~ 1 4 7 02-03-1 0 EWW-592 462 r 99

< 147 02-03-10 EWW-593 193 f 87

< 147 03-21-10 EWW-1662 404 + 106

< 145 03-21-10 EWW-1663 144fr95

< I 4 5 04-11-10 EWW-1898 359 i 104

< 144 04-11-10 EWW-1899 90 f 92

< 144 05-17-10 EWW-2736 333 f 88

< 143 05-17-10 EWW-2737 118 rt 78

< 143 07-08-10 EWW-4049 356 i 99

< 156 07-08-10 EWW-4050 133 t 89

< 156 09-07-10 EWW-5803 442 f 98

< 159 09-07-10 EWW-5804 94 f 81

< 159 09-16-10 EWW-5807 318 + 93

< 159 09-16-10 EWW-5808 136 t 84

< 159 11-28-10 EWW-7304 402 r 90

< 141 11-28-10 EWW-7305 132 f 77

< 141 12-19-10 EWW-7435 274

• 85

< 144 12-19-10 EWW-7436 116 1 7 7

< 144 Mean + s.d.

374 58 Mean + s.d.

127 29 Sample ID GW-I0 22-361A GW-I0 22-3618 Collection MDC Collection MDC Date Lab Code Tritium (pCilL)

(~CIIL)

Date Lab Code Tntium (pCilL)

(~CIIL)

Mean + s.d.

EWW-1660 49 f 91

< 147 01-27-10 EWW-1661 7 5 f 9 2 4 4 7 EWW-1664

-6 r 88

< 145 02-03-10 EWW-594 129 +8 84

< 147 EWW-1900 79

• 91

< 144 03-21-10 EWW-1665 110 rt 93

< 145 EWW-2738 81 i 75

< 143 04-11-10 EWW-1901 99 i 92

< 144 EWW-4051

-19 i 81

< 156 05-17-10 EWW-2739 222 r 83

< 143 EWW-5805

-16 i 75

< 159 07-08-10 EWW-4052 279 f 96

< 156 EWW-5810 7 0 t 8 0

< I 5 9 09-07-10 EWW-5806 307 & 92

< 159 EWW-7306 1 3 4 k 7 7

< I 4 1 09-16-10 EWW-581 1 255 90

< 159 11 1 0 EWW-7307 172 + 79

< 141 12-19-10 EWW-7437 58 r 74

< 144 46 i 55 Mean + s d.

171 r 90 Groundwater Tritium Monitonng Program (Annual Collections)

Bogs Sample ID GW-07 (North Bog)

GW-08 EIC Bog Collection MDC Collection MDC Date Lab Code Tritium (pCilL)

(pCi/L)

Date Lab Code Tritium (pCilL)

(pCi/L) 05-26-10 EWW-2715 295 i 86

< 143 05-26-10 EWW-2716 548 +8 98

< 143

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program Units = pCilL Sample ID U l Fa~ade Subsurface Drainage Manholes Collection Date Lab Code Tritium (pCilL)

MDC (pCiG 05-17-10 # I EW-2750 500 f 109 r 146 05-17-10 #2 EW-2752 449 f 108

< 146 05-17-10

1. 3 EW-2753 494 f 109

< 146 05-17-10

1. 4 EW-2754 467 f 108

< 146 07-22-10 Ma EW-4053 324 1 9 7 r 155 Sludge liquid Mean + s.d.

447 1 72 Sample ID U2 Fa~ade Subsurface Drainage Manholes Collection Date Lab Code Tritium (pCilL)

MDC (PCW 08-30-10 #2 EW-7416 443 1 94 x 146 08-30-10

1. 4 EW-7417 400 f 92 i 146 08-30-10 #5a EW-7418 400 1 92

< 146 08-30-10 #9 EW-7419 239 It 85

< 146 Mean + s.d Groundwater lnleakaae Sample ID U1 Fapde Pillar Q-10 Collection Date Lab Code Tritium (pCilL)

MDC (PC~R) 06-23-1 0 EW-3471 224 1 9 5

< 160 09-01-1 0 EW-7584 78 f 84

< 133 Mean + s.d.

151

• 103 a Resample of 05-17-10 collection (EW-2754). Previous sample confirmed as contaminated.

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program Units = pCi/L Sample ID U l Turbine Building Subsurface Drainage Manholes Collection Lab Code Tritium (pCilL)

MDC Date (PCW TSC AFW TB#6 TB#8 TWlO TB#l1 TB#12 TB#13 TB#14 Mean + s.d.

EW-4862 EW-4864 EW-4865 EW-4866 EW-4867 EW-4868 EW-4869 EW-4870 EW-4871 Sample ID U2 Turbine Building Subsurface Drainage Manholes Collection Date Lab Code Tritium (pCilL)

MDC IPCW EW-4872 EW-4873 EW-4874 EW-4875 EW-4876 EW-4877 EW-4878 EW-4879 EW-4880 EW-4881

< 154

< 154

< 154

< 160 Prime

< 154

< 154

< 154

< 160

< 160

< 160 Mean + s.d.

815 f 604

APPENDIX B DATA REPORTING CONVENTIONS

Data Rersortinq Conventions I.O. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.

2.0. Sinqle Measurements Each single measurement is reported as follows:

x + s where:

x = value of the measurement; s = 20 counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is less than the lower limit of detection L, it is reported as: < L, where L = the lower limit of detection based on 4.660 uncertainty for a background sample.

3.0. Duplicate analvses If duplicate analyses are reported, the convention is as follows. :

3.1 Individual results: For two analysis results; x, + s, and x2 i s, 2

2 Reported result:

x k s; where x = (112) (x, + x,)

and s = (112) d s, + s2 3.2.

Individual results:

< L,, < L, Reported result: c L, where L = lower of L, and L, 3.3.

Individual results:

x rt s, < L Reported result:

x i s if x 2 L; < L otherwise.

4.0. Computation of Averaqes 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,, x2... xn 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 following rules are followed:

4.5.1.

If the number following those to be retained is less than 5, the number is dropped, and the retained numbers are kept unchanged. As an example, 11.443 is rounded off to 11.44.

4.5.2.

If the number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11.445 is rounded off to 11.45.

POINT BEACH NUCLEAR PLANT APPENDIX C Sampling Program and Locations

POINT BEACH NUCLEAR PLANT Locations Collection Type Analysis Sample Type No.

Codes (and Type)=

(and ~requency)~

(and ~ r e q u e n c ~ ) ~

Airborne Filters 6

E-1-4, 8, 20 Weekly GB, GS, on QC for each location Airborne Iodine 6

E-1-4, 8, 20 Weekly 1-131 Ambient Radiation 22 E-1-9, 12, 14-18, 20, Quarterly Ambient Gamma (TLD's) 22-32, 34-36, 38,39 Lake Water 5

E-I, 5, 6, 33 Monthly GB, GS, 1-131 on MC H-3, Sr-89-90 on QC Well Water 1

E-I 0 Quarterly GB, GS, H-3, Sr-89-90, 1-131 Vegetation 3x 1 year as available Shoreline Silt 5

E-1, 5, 6, 12, 33 2x 1 year Soil 8

E-1-4, 6, 8, 9, 20 2x 1 year GB, GS GB, GS GB, GS Milk 3

E-1 I, 40, 21 Monthly GS, 1-1 31, Sr-89-90 Algae Fish 3x / year as available GB, GS 2x 1 year GB, GS (in edible portions) as available 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, 1-1 31 = iodine-1 31. Analysis frequency is coded as follows:

MC = monthly composite, QC = quarterly composite.

POINT BEACH NUCLEAR PLANT APPENDIX D Graphs of Data Trends

POINT BEACH Air Particulates - Gross Beta Location E-I, monthly averages 2006-201 0 0.05 1 2006 2007 2008 2009 2010 Year Location E-2, monthly averages 2006-201 0 0

i f t - t - ~ I l / ~ l : : l i l i l l i ~ : i l l l l i l : l l l ~ l ~ l i l l I l i ~ l 2006 2007 2008 2009 201 0 Year

POINT BEACH Air Particulates - Gross Beta Location E-3, monthly averages 2006-201 0 2006 2007 2008 2009 201 0 Year Location E-4, monthly averages 2006-201 0 Year

POINT BEACH Air Particulates - Gross Beta Location E-8, monthly averages 2006-201 0 0 ~

~

I i

I I

I i

i i

i

~

~

~

i

~

i

~

f

~

f

~

~

(

~

~

~

~

~

~

~

~

~

~

2006 2007 2008 2009 2010 Year Location E-20, monthly averages 2006-201 0 Year

POINT BEACH NUCLEAR PLANT APPENDIX E Supplemental Analyses

POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: sediment = pCi\\gdry Water and water extracted from sediment (H-3) = pCi\\L Location UIFSSD Ul FSSD

1. 4

1. 2 Collection Date 05-17-10 05-1 7-10 Lab Code EW-2754 MDC ESG-2755 MDC Sr-89 0.99 f 1.49

< 1.71 Sr-90 0.14 f 0.41

< 0.84 0.00 f 0.09

< 0.20 Fe-55

-134 f 395.0

< 660 H-3 467k108

< I 4 6 5 6 5 f 1 1 2

< I 4 6 Be-7 18.2 f 10.8

< 29.4 1 2. 2

~ 2 8. 1 K-40 212.8 f 25.5

< 65.3 30.7 f 30.7

< 8.2 Mn-54 0.1f1.3

<2.4 0.076 f 0.14

< 0.3 Fe-59

-2.7 f 2.5

< 8.0

-0.066 f 0.32

< 0.8 CO-58

-0.3 f 1.3

< 3.0

-0.089 f 0.14

< 0.3 CO-60 1.3 f 1.4

< 2.9 0.16f0.18

<0.3 Zn-65 2.4 k 2.4

< 5.8 0.18 f 0.35

< 0.5 Zr-Nb-95

-3.2 f 1.4

< 4.8 0.037 f 0.15

< 0.5 CS-134

-0.8 f 1.6

< 2.7

-0.25 f 0.16

< 0.2 CS-137 1.2f1.6 i 3. 0 0.64 f 0.30 Ba-La-I40 0.4 f 1.6 c 14.2 0.090 f0.17

< 1.1 Ce-141 2.2 f 2.1

< 7.9 0.051 f 0.17

< 0.5 Ce-144

-1.1 f 9.5

< 17.8 0.31 f 0.74

< 1.4 Other Gammas (Ru-I 03)

-2.0 f 1.2

< 4.2

-0.28 f 0.14

< 0.4 Location UIFSSD" UIFSSD

1. 4

1. 6 Collection Date 05-1 7-1 0 05-1 7-10 Lab Code ESG-2757 MDC ESG-2758 MDC H-3 582 f 112

< 146 478

• 99

< 145 Fe-55 Be-7 0.012 f 0.25

< 0.58 0.16 i 0.17

< 0.44 K-40 10.39 f 1.13 5.89 f 0.72 Mn-54 0.010 f 0.028

< 0.063 0.032 f 0.018 < 0.040 Fe-59

-0.018 f 0.054

< 0.14 0.015 f 0.036 < 0.081 CO-58 0.33 f 0.11 0.010 f 0.018 < 0.028 Co-60 0.73 f 0.064 0.020 f 0.023 < 0.039 Zn-65 0.070 f 0.061

< 0.11

-0.004 f 0.040 < 0.052 Zr-Nb-95

-0.014 2 0.030

< 0.081

-0.047 f 0.020 < 0.041 CS-134 0.012 f 0.026

< 0.054 0.009 f 0.019 < 0.037 CS-137 4.40 i 0.13 1.01 i 0.055 Ba-La-140 0.17 f 0.10

< 0.14 0.003 f 0.021 < 0.31 Ce-141

-0.030 f 0.031

< 0.061

-0.028 f 0.023 < 0.036 Ce-144

-0.043 f 0.14

< 0.28

-0.074 f 0.099 < 0.11 Other Gammas (Ru-103)

-0.054 f 0.027

< 0.073

-0 003 f 0.019 < 0.049 a Results indicate contamination.

Resample of Manhole #4 (ESG-2757) to confirm previous sample was contaminated.

UIFSSD

1. 3 05-1 7-1 0 ESG-2756 MDC 522 f 110

-0.12 i 0.25 7.2 f 1.1 0.020 f 0.026

-0.009 f 0.058

-0.031 f 0.028 0.13 f 0.043 0.055 f 0.061 0.035 f 0.028

-0.013 f 0.036 1.30 f 0.11

-0.063 f 0.026

-0.024 t 0.035 0.035 f 0.15

-0.064 f 0.027 UIFSSD~

1. 4 07-22-1 0 ESG-4053 324 f 97 12.9 f 18

-0.21 f 0.27 12.89 f 1.41 0.017 f 0.032

-0.041 f 0.064 0.005 2 0.030 0.057 f 0.040 0.022 f 0.069 0.041 i 0.034 0.016 k 0.032 2.33 f 0.15

-0.023 f 0.038 0.031 2 0.043 0.134 i 0.18 0.017 f 0.032 MDC

< 155

< 28.7

< 0.44

POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: sediment = pCi\\gdry Water and water extracted from sediment (H-3) = pCi\\L Location Collection Date Lab Code Water Treatment U2TBSSD TB#I Sump-Turbine Bldg.

08-1 1-10 08-30-1 0 EW-4463 MDC EW-4872 MDC Be-7 12.1 f 11.0

< 26.8 K-40 57.7 f 24.3

< 54.3 Mn-54

-0.7 k 1.5

< 2.6 Fe-59

-2.5 f 2.4

.: 3.3 CO-58

-1.2 f 1.2

< 1.7 CO-60 0. 2 f 1. 1

<2.5 21-65

-0.5 +- 2.5

< 3.3 Zr-Nb-95

-0.6 f 1.3

< 2.4 CS-1 34 0.2 f 1

< 2.6 CS-137 0.2 f 1.2

< 2.6 Ba-La-140 5.3 f 1.5

< 5.1 Ce-141

-1.8 f 2.7

< 7.9 Ce-144

-1.3512.2 d 6. 3 Other Gammas (Ru-103)

-1.3 f 1.3

< 3.4 Location U2FSSD U2FSSD February composite #1 February composite #2 Collection Date 02-1 9-1 0 02-28-10 Lab Code EW-4503" MDC EW-4504a MDC Be-7

-245.0 f 15.6

< 21 1.7 21.1 f 15.1

< 272.6 K-40 275.4 f 33.1

< 108.7 298.4 f 35.8

< 84.9 Mn-54

-0.1k0.8

<3.1 3.1 f 1.8

.r 4.7 Fe-59

-8.3 f 3.6

< 67.8 2.7 f 3.6

< 107.8 CO-58 1.4 f 1.6

< 17.6

-4.2 + 1.8

< 10.6 Co-60

-1.5 f 2.j

< 3.5 0.4 f 1.9

< 4.0 Zn-65 0.3 f 4.1

< 11.8

-2.8 f 3.9 i

11.1 Zr-Nb-95

-80.0 f 1.9

< 99.0

-41.6 f 2.0

< 74.5

'3-134 1. 1 f 1. 8

<4.2 1.2f1.6 i 2. 9 CS-137 2.2 f 1.8 3.5 2.4 f 1.9 i

4.2 Ba-La-140

- f -

- A -

i Ce-141

-86.1 f 2.7

< 260.4

-35.8 f 2.7 i

131.2 Ce-144

-9.5 f 11.9

< 25.8 0.9 f 11.8

< 28.0 Other Gammas (Ru-103)

-53.5 f 1.8

< 47.8 9.4 f 1.7

< 55.9

-a Ba-La-140 = >12 halflives due to age of sample; composited August 2010.

U2FSSD January composite 01-15-10 EW-4502~

MDC U2FSSD March composite 03-24-1 0 EW-4505 MDC

POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: sediment = pCi\\gdry Water and water extracted from sediment (H-3) = pCi\\L Location U2FSSD U2FSSD U2FSSD April composite May composite MH-4 Solids Collection Date 04-28-1 0 05-21-1 0 08-30-1 0 Lab Code EW-4506 MDC EW-4507 MDC E W - 7583 MDC Be-7 K-40 Mn-54 Fe-59 CO-58 Co-60 Zn-65 Zr-Nb-95 CS-I34 Cs-137 Ba-La-140 Ce-141 Ce-144 Other Gammas (Ru-103)

POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: sediment = pCi\\gdry Water and water extracted from sediment (H-3) = pCi\\L Collection Date 07-07-1 0 07-07-1 0 07-07-1 0 Lab Code EP-3558 MDC EP-3559 MDC EP-3560 MDC Units pCilL pCi/L pCilL STP SG EPU AC CHEM OFFICE Collection Date 09-28-1 0 09-28-10 09-27-1 0 Lab Code EP-5472 MDC EW-5473 MDC EW-5474 MDC Units pCilL pCilL pCilL Location UIFSSD UIFSSD UIFSSD

1. 4

1. 2

1. 3 Collection Date 07-22-1 0 05-17-1 0 05-1 7-1 0 Lab Code ESG-4053 MDC ESG-2755 MDC ESG-2756 MDC

APPENDIX F DUPLICATE ANALYSES

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

Units: p~ilrn3 Collection: Continuous, weekly exchange.

Date Volume Location Collected (m3)

Gross Beta

F -2. Lake Water, duplicate analyses for gross beta, iodine-1 31 andgamma isotopic.

Units: pCi/L Collections: Monthly Location E-0 1 E-05 Lab Code Date Collected Gross beta 1-1 31 Be-7 Mn-54 Fe-59 CO-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Ru-1 03 ELW-3813 07-13-10 0.9 + 0.3 0.14 f 0.28

-13.7 f 17.3

-1.3 f 2.0

-0.3 f 2.9 1.9 + 1.6 0.1 f 2.1 1.4 r 3.8

-0.7 + 1.7

-0.2 f 1.7 1.1 f 2.0

-3.8 f 2.2

-1.4 + 1.7 ELW-5199 09-15-1 0 1.1 + 0.9 0.05 + 0.21

-0.5 4 18.7

-1.0 f 1.9

-2.6 f 2.9

-0.4 4 1.6

-0.8 + 1.4 2.1 + 4.4

-1.1 f 2.0

-0.6 f 1.9 1.2 2 2.1

-0.5 f: 1.5

-1.0 r 2.0 F -3. Lake Water, duplicate analyses for tritium, strontium-89 and strontium-90.

Location E-033 Lab Code ELW-5672 Collection Period 3rd Qtr.

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

Units: pCi/L Collection: Monthly Location Lab Code Date Collected E-40 EMI-2969 E-21 EMI-4466 08-11-10 E-40 EMI-7188

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

Units: pCi/L Collections: Monthly, quarterly, quarterly composites Location GW-15 S-I Collection Date 01-28-10 02-18-10 Lab Code EWW-425 EWW-610 Location U2FSSD GW-12 S-3 Collection Date 03-03-1 0 03-18-10 03-17-1 0 Lab Code EWW-926 EWW-1173 EWW-I268 Location MH-Z65D GW-01 Collection Date 03-1 5-10 04-28-1 0 Lab Code EWW-1057 EWW-2102 Location S-I S-I I Collection Date 04-14-10 04-23-1 0 Lab Code EWW-1646 EWW-1976 Location U2FSSD UlSSD # I Collection Date 04 1 0 05-17-10 Lab Code EWW-2326 EW-275 1 Location GW-2 S-1 Collection Date 06-30-1 0 06-02-1 0 Lab Code EWW-3394 ESW-3019 Location U2FSSD U2FSSD Collection Date 06-25-10 07-14-10 Lab Code EWW-3470 EWW-4064 Location SSD TSC GW-12 Collection Date 08-30-10 09-24-1 0 Lab Code EW-4863 EW-5626

F-5. Surface Water/Well Water, duplicate analyses for tritium, continued.

Units: pCi/L Collections: Monthly, quarterly, quarterly composites Location U2FSSD GW-09 12-361 B U2FSSD Collection Date 09-06-10 09-16-10 10-18-10 Lab Code EW-5136 EW-5809 EW-6295 Location GW-14 Collection Date 11-22-10 Lab Code EW-6923

F.6 SedirnenVsoil, duplicate analyses for gross beta and gamma isotopic Units: pCilg dry Collection: Semiannual Location E-03 E-08 Collection Date 51261201 0 10/28/2010 Lab Code ESO-2730 ESO-6337 Gross Beta 38.96 + 1.32 24.78 +. 1.52 F.7 Grass, duplicate analyses for gross beta and gamma isotopic Units: pCilg dry Collection: Semiannual Location Collection Date Lab Code Ratio (wetidry)

Gross Beta Be-7 K-40 1-1 31 CS-1 34 Cs-137 Co-60 E-20 51261201 0 EG-2703 4.51 5.29 0.1 1 1.10 + 0.24 4.76 k 0.57 0.01 1

• 0.01 I 0.004 f 0.009

-0.006 f 0.013 0.003 + 0.015 E-20 7/28/20 10 EG-4037 2.90 7.61 + 0.30 6.05 + 0.51 5.86 + 0.70 0.006 + 0.016

-0.001 f 0.016 0.004 + 0.018 0.006 k 0.016

F.8 Fish, duplicate analyses for gross beta and gamma isotopic Units: pCilg wet Collection: Semiannual Collection Date 11 1 0 Lab Code EF-6566 Location E-13 Ratio (weffdry) 3.43 Gross Beta K-40 Mn-54 Fe-59 (20-58 Co-60 Zn-65 Cs-134 Cs-137 Other (Ru-103)

F.9 Air particulates, duplicate analysis for quarterly gamma emitting isotopes.

Collection Period Lab Code Location

APPENDIX 2 University of Waterloo (Ontario)

Environmental Isotope Laboratow Precipitation Monitoring Results for the Point Beach Nuclear Plant Reporting Period: January - December 201 0

Client: Johansen ISQ# 201 0030 FPLE Point Beach Nuclear Plant Location: T -

Contract #: 25473 3 for 3H NPL 2010-0007 Tritium is reported in Tritium Units.

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

1TU = 0.1191 9 BecquerelsIL per IAEA, 2000 Report.

t To Contact uwEILAB:

519 8884732 Environmental Isotope Lab 4/4/2011 1 of 1 Rick Heemskerk uwElLAB Manager rkhmskrk@uwaterloo.cb 51 9 888 4567 ext 35838

Client: Johansen FPL Energy Point Beach Contract # 25473 NPL 2010-0042 ISO# 2010107 Location: T -

3 for 3H Tritium is reported in Tritium Units.

1TU = 3.221 PicocurriesIL per IAEA, 2000 Report.

1TU = 0.11 91 9 BecquerelsIL per IAEA, 2000 Report.

To Contact uwEILAB:

b 5198884732 Environmental Isotope Lab 4/4/2011 1 of 1 Rick Heemskerk uwElLAB Manager rkhdskrk@uwaterlso.ca 519 888 4567 ext 35838

Client: Johansen FPL Energy Point Beach Contract #: 25473 NPL 201 0-0092 ISO# 201 01 92 Location: T -

3 for 3H Environmental Isotope Lab 4/4/20 1 1 1 of 1 Tritium is reported in Tritium Units.

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

1TU = 0.11919 Becquerelslb per IAEA, 2000 Report.

To Contact uwEILAB:

5198884732 Rick Heemskerk uwElLAB Manager rkhmskrk@uwaterloo.ca 51 9 888 4567 ext 35838

Client: Johansen FPL Energy Point Beach Contact #: 2547'3 NPL 2010-01 14 ISOW 201 0236 Location: T-8 3for 3H Tritium is reported in Tritium Units.

1TU = 3.221 PicocurrieslL per IAEA, 2000 Report.

1TU = 0.11919 Becquerelslb per IAEA, 2000 Report.

To Contact uwEILAB:

51 9 888 4732 Environmental Isotope Lab 4/4/2 0 1 1 1 o f I Rick Heemskerk uwElLAB Manager rkhmskrk@hwaterloo.ca 51 9 888 4567 ext 35838

Client: Johansen FPb Energy Point Beach Contract #: 25473 NPL 2010-0153

!SO# 201 0301 Location: T -

3 for 3H Environmental Isotope Lab 4/4/26 1 1 1 of 1 Tritium is reported in Tritium Units.

1TU = 3.221 PicocurriesIL per IAEA, 2000 Report.

1 TU = 0.1 191 9 Becquerels/L per IAEA, 2000 Report Conductivity pCi/l H

Rick Heemskerk uwElLAB Manager rkhmskrk@uwaterloo.ca 51 9 888 4567 ext 35838

Client: Johansen

!SO# 201 0372 FPLE Point Beach Nuclear Plant Location: T -

Contract #: 25473 3 for 3H NPL 2010-0190 Environmental Isotope Lab 4/4/20 1 1 1 of 1 Tritium is reported in Tritium Units.

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

1TU = 0.11 91 9 BecquerelsIL per IAEA, 2000 Report.

To Contact uwEILAB:

5198884732 Rick Heemskerk uwElLAB Manager rkhmskrJk@uwaterloo.ca 51 9 888 4567 ext 35838

Client: Johansen ISO# 201 0563 FPLE Point Beach Nuclear Plant, LLC Location: T -

Contract #25473 6 for 3H NPL 201 0-0225-1 NPL 201 0-0268 Tritium is reported in Tritium Units.

ITU = 3.221 PicocurrieslL per IAEA, 2000 Report.

1 TU = 0.1 191 9 BecquerelslL per IAEA, 2000 Report.

bottle bottle bottle bottle bottle bottle Environmental Isotope Lab 4/4/20 1 1 1 o f 1 Rick Heemskerk uwElLAB Manager rkhmskrk@uwaterloo.ca 519 888 4567 ext 35838

Tritium is reported in Tritium Units.

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

1TU = 0.1 191 9 BecquerelslL per IAEA, 2000 Report.

Client: Johansen ISO# 201 0584 Environmental isotope Lab FPLE Point Beach Nuclear Plant, LLC Location:

4/4/2011 Contract #: 25473 3 for 3H 1 o f 1 NPL 2010-0316 9

Conductivity 125ml bottle 125ml bottle 125ml bottle To Contact uwEILAB:

5198884732 pCi/l

<MBA

<MDA

<MDA Rick Heemskerk uwElLAB Manager rkhmsk~k@uwaterloo.ca 519 888 4567 ext 35838

Client: Johansen FPL Energy Point Beach Contract#: 25473 NPL 2010-0346 ISO# 201 0650 Location:

3 for 3H Environmental Isotope Lab 41412 0 1 1 1 of 1 Tritium is reported in Tritium Units.

1TU = 3.221 PicocurriesIL per IAEA, 2800 Report.

1 TU = 0. I 191 9 BecquerelsIL per IAEA, 2000 Report.

Rick Heemskerk uwElLAB Manager rkhmskrk@uwaterloo.ca 519 888 4567 ext 35838

Client: Johansen FPL Energy Point Beach Contract #24573 NPL 2010-0415 lSO# 201 0747 Location:

3 for 3H Environmental Isotope Lab 4/4/20 1 1 1 o f 1 Tritium is reported in Tritium Units.

lTU = 3.221 Picocurries/L per IAEA, 2000 Report.

1TU = 0.11 91 9 Becquerels/L per IAEA, 2000 Report.

To Contact uwEILAB:

5198884732 Rick Heemskerk uwEl LAB Manager rkhmskrk'@uwaterloo.ca 51 9 888 4567 ext 35838

Client: Johansen FPL Energy Point Beach Contract #: 25473 NPL 201 0-0438 ISOW 201 0797 Location: T - 8 3 for 3t-I Environmental Isotope Lab 4/4/20 1 1

'iof1 Tritium is reported in Tritium Units.

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

1TU = 0.11 91 9 Becquerelslb per IAEA, 2000 Report.

To Conlact uwEILAB:

5198884732 Rick Heemskerk uwEl LAB Manager rkhmskrk@uwaterloo.ca 51 9 888 4567 ext 35838

ENCLOSURE 2 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 ENVIRONMENTAL MANUAL REVISION 22 APRIL 20, 2010 34 pages follow

EM ENVIRONMENTAL MA DOCUhlENT TYPE:

CLASSIFICATION:

REVISION :

EFFECTIVE DATE:

REVIEWER:

APPROVAL AUTHORITY:

PROCEDURE OWNER (title):

OWNER GROUP:

Controlled Reference N A 9 7 --

April 20. 20 10 Plant Operatioi~s ReFrieu. Committee (PORC)

Plant Manager (PORC Chair)

Group Head Cliemistr~

POINT BEACH NUCLE.4R PLANT ENVIRONklENTAL MANUAL EM Revision 22 April 20. 21) 10 ENVIRONMENTAL MANUAL TABLE OF CONTENTS SECTION TITLE PAGE 1.1 Definition and Basis 3

1.2 Respollsibilities for Program Iii~plen~eiltatio~~

4 1.3 Quality Assurance 'Quality Control 7

1.4 Program Revisions 8

2.0 K4DIOLOGlC'AL ENVIRONMENTAL blON1TOlilNG X

2.1 Program Overview X

2.2 Program Parameters 9

2.3 Assistailce to the State of 11 iscoilsin 14 2.1 Specification of Saillpling Procedures...........................................................

I S 2.5 Milk Survey..................................................................................................... 23 TABLE 2-1 Recoil~illel~ded i\\liniinum Sail~ple Sizes...........................................................

25 TABLE 2-2 Sainple Types And Associated Lokver Level Of Detection (Lld) And Notitication Level Values.......................................................................................... 26 TABLE 2-3 Radiological Environmental Sampliilg Locations......................................................

28 TABLE 2-1 PBNP Radiological Environmental Saimple Collection And Ana1~-sis Frequency 30 TABLE 2-5 San~ples Collected For State Of 1i;iscoi1sin 31 FIGURE 2-la Radiological Environmental Salnpliilg Locatioils 32 FlGURE 2-1 b Radiological Envisonmental Sampling Locations 33 FlGURE 2-lc Radiological Emironmental Sampling Locations 33 Page 2 of 34 I

1NFORMATlON USE

POiNT BEACH NUCLEAR PLAN?

ENVIRONblENTAL I\\/lANUAL EM Revision 22

.4psil 20. 30 10 1.0 RADIOLOGICAL ENVIRONMENTAL MONlTORlNG PROGRAM ADIv~INISTRATION 1.1 Definition and Basis Radiological environmental monitoring is the measurement of radioactivity in samples collected from the atn~ospheric. aquatic and terrestrial environment arouild the Point Beach Nuclear Plant (PBNP). Monitoring radioactivin-in eft-luent streams at or prior to the point of discharge to the environment is not part of the Radiological En~.ironinental blonitoring Program (REMP).

1.1.2 Basis The E > l P is designed to f~~lfill the requiremeiits of 10 C'FR 20.1302. PBNP GDC 17. and Sections 1V.B.2 and lV.B.3 of Appendix I to 10 C'FR 50.

Teclmical Specification 5.5.1.b requires the Offsite Dose Calculation Manual (ODCM) to coiltai~~

the radiological en~ironn~eistal monitorixlg actjvities. A coinplete descriptioil of the PBNP radiological environmental monitosing program. ii~cludi~sg procedulres and responsibilities. is contained in the Environmental IvJvlnnual (EM). The EM is incosposated into the ODCM b~

reference (ODC'kl. Sectioil6 0).

No significant radionuclide concentrations of plant ollgin are expected in the plant environs because radioacti~.i~-

in plant efil~1ent is continuous1~-

nlonitored to ensure that releases are well below levels which are coilsidered safe upper limits. The REhlP is coilducted to demonstrate conlpliance wit11 applicable standards. to assess the radiological en~ironmental iinpact of PBNP operations. and to ii~onitor the efficac~ of in plant efflueilt controls. T11e RETVIP. as outlined ill Tables 2-2 tlxough 2-4 is designed to provide sufficieiit sample ppes aid locations to detect and to evaluate changes in enviroi~mental radioactivi~

Radioactivi~ is released in liquid and gaseous efiluents. Air sainplers and theimol~iminescent dosimeters placed at vaiious locations provide means of detecting cl~anges in enviroimental radioactivit~ as a result of plant releases to the atmosphere. Because the land area around PBNP is used prirnarilj-for farming and d a i i ~

operatioi~s. sampling of vegetation is conducted to detect changes in radiological coilditioils at the base of the food chain. Sampling of area-produced milk is conducted because dail? fasnliing is a major irnd~istq in the area.

t Page 3 of 34 ILNFORMATION USE

POINT BEACH NUCLEAR PLAN?

EN M IRON MENTAL IVIAN U AL ELI Revision 22 Apiil 20. 20 10 It ater. perip1-i~-ton. and fish are anal! zed to illoilitor mdionuclide levels ill Lake Michigan in the vicinits of PBNP. Periph2-ton. attached algae. along wit11 lake \\;rrater samples. pro\\.ide a ineans of detecting changes hl-hicl~ ma^

have a potential ilxp~ct on the radionuclide concentrations in Lalte Michigan fish. Because of the n1igrator~- bel-ia\\.ior of fish. fish sanlpling is of ininiinal value for deterilliniilg radiological impact specifically related to the operation of the Point Beach Nuclear Plant. Hobvever. fisl~ sampling is carried out as n conservative measure with emphasis on species ~vhich are of intermediate tropl~ic level and wlsich exhibit miniinel inigration in order to monitor the status of radioactivit~ in fish.

Vegetation. algae. and fish sanlpling fsequencies are qualified on an "as available" basis recogiliziilg that certaii~ biological samples may occasion all^

be una~ailable due to environmental conditions.

1.2 Responsibilities for Proera111 In~pleruentation Chemistrj-together with Regulators-Affairs (RA) provides the Plant illanager M it11 the technical. regulato1-y. licensing. and adi=niilistrati~-e support necessary for the i~~~pleil~ei~tatioil of the progmnl. The Chemistry admiisistrative h~nctions relating to the E I v W fall illto the six broad areas oi~tlined below.

a. Prograisl scope The scope of the REIvlP is deteriuined bj the cognizant Chemist based on radiological principles for the f~~lfillment of PBNP Teclznicnl Specifications (TS) aid tlse applicable Federal Regulations. Based on the scope. the Ei~viroinmental Manual (EM) is kvritten to accomplisl~ the collectioil and analyses of the necessar: environmental samples. The E141 is revised as necessar! to co11forn1 to changes in procedures and scope.

Cl~emistr! inoilirors the R E k P eft'ectiveness and coinpliailce with TS and t\\ ith the procedures and directives in the EM. In order to verifi compliance uith TS. Nuclear Oversight arranges for program audits and S~lpplier AssessisIents of the contracted mdioanal~ tical lnboratoi:.

Cheinistrl; reviews the EM annuall! via the Annual Monitoring Report.

b. Record lteepiilg The monthl! radioanal) tical results from the contracted laboratoi~ are reviekved b:

Chemistrj and one cop! of the monthl) radioan~ls tical results from the contracted laboratoi~ is kept for the lifetime of the plant The vendors monthl~ reports are cuinulative (e.g. T11e September report contaiils all the results from Januai2--September). T11e co gnizant Chemist review.s the current n~ontl~s results. signs and dates the cover page. and seilds the reviewed report to plcints records for retention.

I Page 4 of 34 INFORMATlON USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Re\\.ision 23 April 20. 20 10 ENVIRONMENTAL M-4NUAL

c. Data nloilitoriilg Chemists>- revie\\vs the montl~l~

anal: tical results fro111 the vendor.

Trei~ds. if ail:. are noted. An: rzsulting corrections. modiiications and additions to the data are made by Chemistq Tlie review is documented and sent to records. as iloted in Section 1.2. l.b. lncol~sisteilcies are investigated b: Chemish: with the cooperatioil of Radiatioil Protectioi~

(W) and contractor personnel. as required Radioactivity levels in excess of adininistrative notification levels would be evaluated and notifications made. as appropsiate. in accordance with the PBNP Reportabilit: Manual and applicable fleet policies and procedures.

d. Data summary REMP results shall be summatized annually for i1lclusioi1 in the PBNP Annual Monito~ing Report. This s~n~illary advises the Plant Manager of the radiological status of the environment ill the vicinit: of PBNP. The summar: shall ii~clude the numbers and t y e s of saillples as \\\\-ell as the aLerages. statistical coi~iidence lin~its and the ranges of anal:-tical results bletllods used in s~unmarizing data are at the discretion of Chemistry.

e. Contmctor coillmunications Communication \\?.it11 the contractor regarding data. analytical procedures.

locver limits of detection. notiiication levels and contmctual nlatters are normal1~- conducted b ~ -

C'11emist~~-.

Communication regarding stlinple shipnleilt may be done by either RP or Cheinisti7-as appropriate.

f. Reportable iteins

1.

C11emistr:- shall generate reports related to the operation of the REklP. The material included shall be sufiicieilt to f~lliill the ob.jectives outlined in Sections 1V.B.2 and IV.B.3 of Appendix I to 10 CFR 50. The following itenls and occunences. are required to be reported in the PBNP Anilual klonitoring Report:

(a) summa^^ and discussioil of i-noiiitoring results including nuillber and type of saitlples and measurements. and all detected radionuclides. except for nat~~ralll; occurring radionuclides:

(b)

Unavailable. missing. and lost samples and plans to prevent recurrence and coillillents 01-1 any sigilificailt portioi~ of the REMP not conducted as indicated in Tables 2-3 through 2-4.

Page 5 of 34 INFORhlATION USE

POINT BEACH NUCLE-4R PLA4NT ENVIRONkENTAL MANUAL ENVIRONMENTAL MANUAL (c)

New or relocated sampling locations and reason for chai~ge:

(d)

LLDs that are higher than specified ill Table 2-2 and factors contributing to inability ro achieve specified LLDs:

(e)

Notification that the anal:-tical laboratol~ does not participate in an inter la born tor^ coillparisoil program and corrective action talten to preclude a recurrence: a11d (i) Results of the annual milk saillpliilg prograin la11d use census "mill< sur~ey" to ~.isuall\\, verifi-that the location of grazing al~imals in the vicinit~- of the PBNP site boundas>- so as to ellsure that the milk san~pling program reil~cliils as conservative as practicable.

(g)

Tile annual results from the contracted REMP analytical 1aborator~-

as well as the laborator!-'s analj tical QA QC results.

in-l~ouse blanlts. intes1aborator~- comparisons. etc.. shall be s~lbinitted to the NRC, via the A11nua1 Monitoring Report.

(11)

The A~lnual Monitoring Report for the previous 12 mont1.l peiiod. or fraction tl~eseof. eildiilg December I; 1. shall be submitted to the NRC b:

Ap~il 30 of the follo\\ving !-em.

The psimai7-responsibility for the implei-iaentatioi of the PBNP REMP and for an>- actions to be talten at PBNP. based on the results of the program. resides with the Plant Manager.

a. Manual control and distribution The distribution of the PBNP En~ironinental Manual is the responsibi1it.i-of Docuilleilt Control.

The dai1.i-operation of the program is coilducted b: PBNP Radiation Protectioil persoilnel. ai~d other qualified personilel as required. under the supervision of an RP staff melnber who consults. as needed. with C11einistr~-. Tlle dail!- administrative functions of the RP klanagement Emploj ee address those fit~lctions recluired for the effective operation of the PBNP Radiological Environmental blonitoring Program. Tl~ese administrative f~~nctions include the follou ing:

1.

Ensuring that samples are obtained in accordailce wit11 the type and frequency ill Table 2-4 follo.~~ing proced~~res outlii~ed in this mall~~al:

1 Page 6 of 34 INFORhlATlON USE

P01NT BEACH NUCLEAR PL.4NT ENVIRONIVEN'IAL h,IANLIAE ENVIRONMENTAL M-4NUAL

2.

Ensuring adequate sampling s~lpplies and calibrated. operable ecluipineilt are available at all times:

3.

Ensuring that air sampling pumps are maintained. repaired and calibrated as required and that an adeq~~ate number of baclaip puinps are readil~ available at a11 times:

3.

Reporting lost or unavailable sanlples as well as other potential deviations from the san~pling regime in Table 2-3 via the Corrective Action Program (CAP) and notifi ing the cognizant Chemist.

5. Assisting the State of ~i~isconsii~

in obtaining samples at co-located and other sainpliilg sites based upon a :-earl>-. renewable agreement:

aid

6.

Assisting Chen~isti?~.

as necessa~?-. %~.\\.ith investigations illto elevated mdioactivin-levels in environmental samples.

1.3 Oualin Assurance 'Oualits-Control O u a l i ~ assurance considerations are ml integral part of PBNP's Radiological Environmental Monitoring Progranl The program involves the interaction of Chernistr?.

site q u a l i ~ assurance m d the contracted anal: tical vendor. The coiltracted vendor shall participate in an interlabolator: coillpaiison program. The l~borato~?

is audited periodicall!. either bs PBNP or b> an independent third part)

Qualit>- control for the PBNP portion of the Radiological En\\-ironmental i\\/lonitoring Program is achieved bj-following the procedures contained in this nlanual. Radiation Prorectioil Tecl~nologists (RPTs) collect. package and ship ei~vironmental samples under the supervision of Radiation Protection s~~pervisors.

The? are ad~vised b~ Radiation Protection Management who has immediate responsibili~ for the overall tecl~nical operatioil of the en~.ironmental sampling functions. The M T s recei1.e classroom training as well as on-the-.job training in cal~ying out these procedures.

Ail audit of the PBN P Radiolo gical Environmental hllonito~ing Pro grain and its results shall be completed periodicalls-as a means of inoilitol-iilg progra111 e&ctiveness and ass~uring coinpliance with program directives The audit sl~all be performed in accordance with Section 1.3 of the ODCkl.

i Page 7 of 33 INFORMATION USE

PO1NT BEACH NbC'LEAR PLAN?

ENVlRONblENTAL MANUAL Ebl Revision 32 Aplil 30. 20 10 ENVIRONMENTAL hlANUAL 1.4 Procran1 Revisions This manual describes the current scope of the PBYP Radiological Environmental Monitoring Progmm. Program iteins or proced~tres pedodicall: ma? be updated or changed. consistent \\\\,it11 good radiologicallj monitoring practices. either to re-flect new conditions or to improve prograim effectiveness. Technical and prograin features described in this illanual sl~all be reviewed bj PORC purs~~ant to the requirei1leilts stated in the ODC'Ivl.

2.0 RADIOLOGICAL ENVIRONMENTAL I\\/lONlTORlNG 2.1.1 Purpose No sigiliiicant or unexpected radionuclide concentratioils of plant oiigin are expected because each noril~al effluent pathtvaj at PBNP is n~oilitored at or before the release point. However. the MNlP is conducted to veii@ that plant operations produce no significant radiological in~pacr on the eisvironment and to demonstrate compliance wit11 applicable standards.

Samples for the REMP are obtained froin the aquatic. tel-sestrial and atlnospheric environment. The sainple types represent Ice! ilsdicators or csitical pathu~ay which have been identitied by applying radiological principles from NRC' and otl~er guidance docuinents to the PBNP enviroui?nent.

2.1.3 Monitoring sensitii-itj-The effectiveness of the REMP in f~llfilling its purpose depends ~ ~ p o n the abilit: to accuratelj determine the nature and origins of fluctuations in low levels of ewironmental radioactivi~. This requires a high degree of sensiti~.ity so tl~at it is possible to correctlj discriininate betbyeen il~lctuatioils in background radiation lei-els and lei,els of radioactivitj that nla? be attributable to the operation of PBNP. Therefore. persoililel actisel>-

participating in the inonitoring program should malte evei? effort to i~linimize the possibilitj of contaminating environmental samples and to obtain samples of the appropriate size,

)

Page 8 of 34 b

INFORM-TION USE

POINT BEACH NUCLEAR PLAN?

ENVIRONMENTAL MANUAL 2.2 Prolrram Parameters 2.2.1 C'ontamination avoidai~ce Contamination prevents the accurate quantification of environmental radioactivitj and the correct differentiation between iluctuating bacliground iadioactivit\\ and levels of radiozctivi~ attributable to the operation of PBNP.

Therefore. it is necessary that all personnel associated bvitln collecting and handling radiological environmental sainples take the appropriate precautions to illinimize the possibili~ of contaminating tlne samples. Sonne of the precautions that should be taliell and u.lnic11 byill help to nnirliinize contamination are listed below:

a Equipnlelnt which has been on the controlled side. even if released clean.

should not norn~all~

be used in conj~ui~ction byit11 radiological enr.ironmenta1 monitoring. An exception to this is tlne Health P1n;-sics Test Instruineint (HPTI) equipillent used to calibrate the air ilow calibrator.

b. Store sainnpliing equipment in radiologicnll!- clean areas 0111;-:

c. Store radiological eina.ironmeilta1 samples oill!- in radiologically clean areas wlnen salnnples cannot be shipped to the corntractor on the same day the! me collected;

d. Treat each saillple as a possible source of containiilatioin for other samples so as to illiniinize tlls possibility of cross-contamiinatioix

e. Radiological environmental inonitoring equipiuent should be repaired in clean-side slnops:

f C'ontamination avoidance h r eilvironinental TLDs is covered in Section 2.4.2; and

g. Avoid entering contaminated areas prior to collecting en~~ironmental sarnples.

2.2.2 Sanlple size Sample size affects the sensitir'it: achievable in cluantiQ-ing low ler-els of enr.ironn~ental radioactivitj. Therefore. sainnpling personilel must attempt to attain the quantities of sample specified in Table 2-1. 11 hen a range is given.

ever! effort should be made to obtain a cluantit~ at the upper part of the range.

Page 9 of34 I

INFORMATION USE

POINT BEACI-I NUCLEAR PLANT EN VIRONklENTAL hlL4N UAL ENVIRONMENTAL I\\.lA4NU-4L Ehl Revision 32 Apiil 20. 20 10 7 7 3 L.L.

Lower limit of detection The sensitivit: requiied for il speciiic anal: sis of an ei~vironmental sample is defined in terins of the lo~ier limit of detection (LLD) The LLD is the smallest concentration of mdioactive material in a sample that will 5. ield a net count. above s>-stem background. thar ~ i i l l be detected \\\\.it11 a 95% probabilits and have 01115. a 5% probabili~ of falsel: coilcludirlg that a blank observation represents a real sigilal Mathematicall. the LLD is defined bs the foi~liula 4.66 sb LLD = E s V s 2.22 s Y s EXP(-?,AT)

LED the a psiori lo\\ver limit of detection in picocuries per unit volume or mass. as applicable; S b the standard deviation of the background countiiig rate or the counting rate of a bla111t sainple. as appropriate. in counts per minutes:

E couiltiilg efiicienc~- in counts per disintegrationt V

saillple size in units of volume or mass, as applicable:

2.22

~~unlber of disil~tegrations per ~~linute per picocurie:

Y the fractional cheillical yield as applicable:

/b the radioactive decay constailt for the partic~~lar radionuclide: and AT the elapsed time between sanlple collection. or the end of the collection period. and the time of counting.

7s-pica1 values of E. V. Y. and AT are used to calculate the LLD. As defined.

the LLD is an a psiori linlit represei~ti~lg the capabi1i~- ofa measuring SJ-stem and not an a posteriori liinit for a particulm measurement.

The required anal: sis for each environmeiltal sample and the highest acceptable LLD associated with each analysis are listed in Table 2-2, L i l~enever LLD values 1o\\~er than those speciiied in Table 2-2 are reasonahl:

achievable. the aiml~ tical contractor for the radiological enr.ironmenta1 sainples will do so LL hen the LLDs listed in Table 2-2 are not achieved. a description of the factors contributing to the higher LLD shall be reported in the nest PBNP Ai~nual Monitoriilg Report.

9 Page 10 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT Ebl ENVIRONMENTAL MANUAL Revisioii 22 April 20. 20 10 ENVIRONbfENTAL hllANL1 AL 2.2.-I Notification levels The Notification Level (NL) is tkat measured quailtity of radioactivitl-in ail ei~vironmental saniple \\vhich. bvhen exceeded. requires a notification of such an occurrence be made to the appropriate parts-, Regulatory and administr3tive ilotificatioil levels are listed in Table 2-2.

a. Regulatory notification levels The regulator? notification levels listed in Table 2-2 represent the concentration levels at \\vl~icll NRC' notification is required. If a measured lei-el ofradioactivit) in ail:- radiological environinental inonitoring prograin sainple exceeds the regulator? notification level listed in Table 2-2. res3inpling and or reanal) sis for confirmation shall be coinpleted uirhin 30 days of the determination of tile anoinalous result. If the confilmed measured level of radioactivi~ remains above the notification level. a bvritten report sllall be s~lbinitted to the NRC', If inore than one of the radionuclides listed in Table 2-2 are detected in an:

environmental medium. a \\I-eighted suin calculation shall be perforined if the inensured coilceiltratioil of a detected radionuclide is greater than 25%

of the notification levels. For those mdionuclides nit11 LLDs in excess of 25% of the inotification level. a \\veighted suin calculation needs to be perfomed o n l ~ if the reported \\due exceeds the LLD. Radionuclide coilceiitration levels. called Cf eigllted Sum Action Levels. \\i\\hich trigger a weighted suill calculation are listed in Tnble 2-2.

T11e weighted sum is calculated as follows:

coi1ceiltratioil( 1) coilceiltration (2)

T t.. = bveighted suin ilotification level (1) notification le\\.el (2)

If the calculated M-eighted suill is equal to or greater than 1. resainpling and or re anal^ sis for confillnation shall be coinpleted within 30 days of the deteiinii~ation of the anoi~~alous result. If the coi~firined calculated wei(rl1ted sunl remains equal to or greater than 1. see Section 1.2. 1.c for t

notihcation guidance. This calculation requiren~ent and report is not req~lired if the ineasured level of radioactivity u-as not the result of plant effluents.

b. Administrati\\,e notification le\\.els The administmtive notification levels are the coi~centration levels at \\vhich the contracted anal? tical laborator! pron~ptl? notifies the cognizant Chemists:- Specialist by phone. followed b~ a formal \\vritten coinm~ulication. The adnlinistrative notification levels are lobver than the NRC' regulator^ notification levels and 1ob1.e~ than. or equal to. the weighted sum action levels so the nature and origin of the increased level of ei~vironmental radioactivih ma1. be ascertained and cosrecti\\.e actions taken. if required.

1 I

Page 11 of 34 1NFORMATION USE

POINT BEACH NUCLEAR PLANT ENVlRONbENTAL MANUAL En1 Revisioil22 April 20. 20 10 1 7 5 Sampling locations A list of sampling locations and the corresponding locatioil codes appear in Table 2-3. The locations dso are shown in Figures 2-la. 2-1 b. and 2-lc. It is concei.i.able that sninples inn:- becoine una\\.ailable from specified sclinple locations. If this u-ere to occur. new locations for obtaining replacement samples shall be identified and added to the Radiological Environmental Itlonitoring Program. If milk or vegetation samples become unavailable fro111 the specified salnpling locations. neb\\, sampling locations will be identified within 30 days. The specific locations \\?.here samples were una\\.aiIable ma:

be deleted from the monitoring program in accordance with established provisions for assessing chai~ges. An? significant cl~anges in existing sampling location and the criteria for the change sllall be reported in the Anilual ivlonitoring Report for the period in wlich the change occurred.

Additioilal sampling locations rnaj. be designated if deemed necessar: b:-

cog~liza~lt companj. persoixlel. Figures and tables in this manual shall be revised to reilect the changes 2.2.6 Sampling media and frequent:

Thz sanlpling frequent? for the environmental media I-equired bj. the PBNP REbP is found in Table 2-3. 111 addition to san~ples required b> the former Tech~lical Specifications. the Radiological Enviroim~ental Moi~itoring Progranl also iilcludes the sainpling of soil and shorzline sediment. To ensure that all sainples are obtained at tlle appropiiate times. a checklist is used The checklist provides a inonth-b: -month iildication of all samples. to be obtained at each sanlpling location (PBF-4121 a through 4 1211). T11ese cl~ecltlists also identi@- the schedule for the anliual milk survej. and provides space f'or recordiilg the date samples bvere slipped offsite for anal: sis. 111 addition. the checklist lists each sampling location to identi@- all samples. to be obtained and the collection date. Because the weeklj. air sainples require additional infornlation. a separate checldist is used for each individual air sampling location for calculatioiss and other illformation as sh0u.n in PBF--1.078.

It is recognized that on occasions samples will be lost or that samples cannot be collected at the specified frequent: because of hazardous conditions.

seasonable unavailability. autoinatic sanlpliilg equipment malf~~nctions and other legitimate reasons. Reasonable efikrts will be mado to recover lost or inissed sal~lples if urarranted and appropriate. If samples me no6 obtained at the indicated frequencj.- or location. the reasons or explanatioils for deviations from the sampling frequencj. specified in Table 2-4 shall be docuinented in a C&4P.

Page 12 of 31 I

INFORI\\/IATION USE

POlNT BEACH N~JC'LEAR PLANT EM ENVIRONMENTAL MANUAL Re~ision 22 Aplil 20. 20 10 ENVIRONMENTAL MANUAL 2.2.7 Sainplz labeling All sais1ples nlust be properls-labeled to ensure that the necessary information is conves-ed to the anal! tical contractor and that the results are associated with the correct geograpllical location. Each label (PBF-4026) must contain the follouing :

b. Sainple location from Table 2-3;

c. Date aid time (as appropriate) collected:

d. Air san~ples ISILIS~ show the total vol~uine in 111": vol~uil~es for m-ater and inillt are in gallons; vegetation. sediment. soil. and algae are indicated as 1 1 000 grams: and fish 21 000 grains:

e. Anal>-szs for routine sainples are indicated as "per contract." For special samples. the Radiation Protectioil manager or anothel-Radiation Protectioil Mailagemeixt Employe u-ill designate tl~e anal>-ses required; and

f. Nanle of person collecting the sample.

A perrnailent or iildelible i11k Fpe felt-tip maslter shall be used.

A separate sanlple label is lieeded for each sample t:pe and location.

Labels are securel~ attached to each sainple container. In addition to sainple labels. other identifs-ing marltings rna: be placed on sanlple containers as appropriate.

Sanxple shipping All enviroi~mental sartlples are shipped to a coi~tractor for anal) sis T11e samples shall be packaged and shipped in such a was as to ininiinize the possibilitl, of cross-contamination. loss. spoilage and leakage Each saillple shipment shall have a ts-ped cover letter and..cvhen appropriate. a contractor data collectioi1 sheet. Included in the letter shall be the saixe inforinatioi~

required for the saillple labels as well as the specifk anal:-ses required The oliginsl co\\ er lettei and data collecrioil sheet shall be sent to the contractor ui~der separate cover: one cop! of each is to be used as a packing list and a cops of each shall be kept: in the appropriate PBNP file. T11e data collectioi~

sheet (PBF-4 1403) also serves as the Chain of Custod) form. so it is requiied that the collector. pacl<er. and sl~ipper sign the form.

Page 13 of 34 I

1NFORMATION USE

POINT BEACH NUCLEAR PLAN?

ENVIRONMENTAL IvlANUAL ENVIRONIvlENTAL MANUAL 7 7 9

&.A.

Sample anal?-ses and hequenc~-

The PBNP REMP samples shall be anal: zed for designated parameters at the heclueilc>- listed in Table 2-4 Gamma iso~opic 31131~ sis ineans the ideiltificatioil and qunntiffcation of gaillina-emitting radionuclides that ins> be attsibutable to effluents from PBNP. TJ-picall:. this entails the scanning of the spectrum from 80 to 2048 lteV and deca: correctiilg identified radionutclides to the time of collection The anal>-sis specifically includes. but is not liinited to. Mil-54. Fe-59. Zn-65. Co-58. Co-60. Zr-Nb-95. Ru-103.1-131. Cs-134.

Cs-137. Ba-La-140. Ce-14 1. ~ n d Ce-143.

T11e anal> ses shall be perforined bq a laborator> that participates in an interlaborators crosscheck program If the laborato~l is not participating in such a program. a report shall be made pursuant to 1.2.1.f. 1.(e). The current laboratory is:

Enviroi~mental Incorporated blid\\vest Laborator!-

700 Laildkvehr Road Northbrook. IL 60063-35 17 (81'7) 564-0700 This laboratol: perfori~~s the analyses in such a 111anner as to attain the desired LLDs. 71.12 contracted laborator? participates in an inter-laboratoq compakson crosscheclt pro, (7ra111 I k e contractor is respoilsible for providing prolnpt notification to the cognizant Chemist regarding an?- samples found to exceed the administrative notitication levels as identitied in Table 2-2.

Assistailce to the State of Ll;isconsin As a courtesj and convenience. PBNP persoilnel obtain certaiil environmental saixples for the Section of Radiation Protection. Depmtinent of Health and Farnil? Services of the State of 1% iscoilsi~l as listed in Table 2-5 A cl~ecltlist is used 111 addition. a State of 1'1 iscoi~sii~

air sampling data sheet is submitted uith each. salmple obtained at 1'1 isconsin air sampling locations serviced b:- PBNP personnel State of ti isconsii~ precipitatioil sainples collected tn~ice a montll (or as available) require a state sample tag to be placed in a box wit11 the quart cubitainer. State supplied labels for air particulate filters require start and stop time. date and beginiling and endiilg volume. Fish sent to the state identif: o111y the quarter and the )ear using a PBNP label (PBF-4026). The monthl> lalie water sample mas-be piclted up b? state personnel and in

\\vhich case these samples require on15 that the date and locatioil be bvritten on the box for the cubitainer. The well bvater samples. 2 times year. ma> be piclted sinlilar to lake water samples.

f Page 13 of 34 INFORMATION USE

POINT BEACH TU'UCLEAR PL.4NT EM ENVIRONMENTAL MANUAL Revision 22 Aplil 20. 20 I0 ENVIRONMENTAL MANUAL Samples obtaiiled for the State of I\\,

isconsill are eitl~er gi~.en directlj-to state persoilnel or shipped as req~~ired.

711s departmeilt address is:

State Lab of HJ-giene Radioc11emistr~- Unit 260 1 Agriculture Dr.

PO Box 7996 Madison. I\\,

isconsii~ 53707-7996 2.4 Specification of Samplinc Procedures Creileral radiological en~ironmental saillpling procedures follow the directi1.e~ presented in Sections 2.1 and 2.2. Specific information for handling individual sample types follow 2.4.1 Vegetation Vegetation saillples consist of green. growing grasses and ~ e e d s and are obtained three tiines per year. as available. from specified locations. New

~ ' r o ~ ~ ~ 1 1.

not dead vegetation, should be used because these sainples are iildicators of recent atmospl~eric deposition. Use a scissors or other sllarp cutting tool to c ~ t the grasses and kveeds off as close to rile ground as possible.

Do not ii~clude plant roots and take care not to contaminate the sample with soil Total sample collected should exceed 500 grams and ideally sl~ould be 1000 grams. Place entire sanlple in an appropriate coiltaiiler. S L I C ~ ~

as a plastic bag ( t q e the bag shut) and label the coiltaiiler as described in Section 2.9.7.

2.4.2 Theri~~olui~~ii~escent dosiilleters (TLDs)

TLDs capable of multiple. iildependeilt measureinents of the saisne exposure are posted at locations speci-tied in Table 2-4 and are changed iluarterlj-. The uti~lost care ilz ha~~dling is required to iniilimize unnecessal? exposure during tmnsit. storage and posting because the TLDs begin recording all radiation froin the illoilleilt they are ani~ealed (heated to rezero) at the contractor's laboratory. Pncltages of TLDs in trailsit sllould be illarlted "DO NOT X-RAY."

Trailsportation control (TLDs) sl~all accoinpan: the new batch in transit froill the contractor's laborator) to the plant. The control TLDs shall accoinpail?

the batch durii~g biief storage and subsecluent posting. The same coi~trol TLDs shall accompail: the "old" or exposed batch on its was-back to the contractor. Therefore. each control represents the s ~ m of approximatel: half the in-tmnsit exposure of the tu-o batches. This coiltrol sj-stem is able to identie an! iulusual in-transit exposure.

Page 15 of 34 t

INFORhIATION USE

POINT BEACH NUCLEAR PLANT ENVIRONMENTAL MANUAL ENVIRONIvlENTAL MANUAL Ehl Revision 32 Apiil 20. 2010 Envirolmlental TLDs should never be brought into the plai~t RCA or an!- other area with elevated radiation. but ma^ be stored for brief periods in a shielded ellclosure in the RP Ofiice Area or other loby bacliground area. such as the Eilerg~ inforil~ation Center or the Site Boundarj-Control C'enter. The contractor is to time shipments to coincide as closelj as possible with the beginling of a calendar quarter. TLDs should be shipped back to the contractor irnmediatel~ or within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of removal. The contractor is instructed to process the sanlples immediatel~ upon receipt. The contractor shall report removal data and cumulati\\.e readings in inR for all locations and control. correct for in-transit exposure and express results in net rnR 7 d a ~

S.

Labels of the exposed set for shiprneilt to contractor sl~ould s h o ~

both posting and removal dates.

Lake water Lalte water sanlples are obtained rnontld! at specified 1oc:ltions. The contractor is responsible for the coinpositing for quarterl~ anal~ses. Collect approsimate1~- 8000 in1 (2 gallons) of lake bvater in the req~jired number of cubitaii~ers. or other appropiiate contaii~ers. at each location and label as directed in Section 2.2.7.

Also. lake water is collected for the State of LJ isconsii~ purs~~ant to Table 3-5 T11e sainple is collected. labeled. and forwarded to the appropriate State agency.

LVell water L;L ell bvater samples are obtained c~uarterlj-from the single oilsite well.

Saillple should be obtained from Pi%:-80. T-90 H~:dro-pneumatic Tanli Drain After purging S gallons. collect approsimatelj-8000 1111 (2 gallons) of u.ell bvater using the required nuinber of cubitailless or other appropriate containers. Label as directed in Section 2.2.7.

Air Air iilters are changed ~veeld~

at specified locations and placed in glassiile ei~velopes for shipment to the vendor for anal> ses. Talte preca~~tions to avoid loss of collected mateiial and to avoid containinatioll bvl~en handling filters 11 ashing hands before leaving the plant to change filters is a reconlmended practice.

Page 16 of 34 I

1N FORIV~ATION USE

POINT BEACH NUCLEAR PLANT ENVIRONRLENTAL MANUAL ENVIRONMENTAL IclANIJ AL Both particulate filters and charcoal cartridges are eiliplo~ ed at each saillpliilg location. Particulate filters are anal-\\-zed for gross beta activit!

after ~ ~ a i t i n g for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to allow for the dzca\\- of short-lived radon and tlloron dnughter prod~lcts. The coiltractor ilsaltes quarterly coinposites of the \\I eeld: partic~late sai~iples for gaillnla isotopic ailalj-ses.

A regulated pump (Eberline Model R4S-1 or equivalent) is used at each air sail1pliilg location. Because of the automatic flotr regulation. rotaineter readings at the beginning and endiilg of the sampling period should be nearl~ identical. S~bstai~tial differei~ces ill readings usual1~- require soille investigation to deteiinine the cause. The rotaineters attached to the puinps are calibrated in liters per minute. 11 he:1 ne\\y filters are installed.

flow rate should be about 25-30 lpm. Flow rates less thail 26 lpin or Irreater t11ai1 32 lpin require that the pump regulator be readjusted. T11e correct flou rate is deterilliiled b~ inultipl: ing the rotai~leter reading b ~ -

the correctioi1 factor indicated on the calibration sticlter affixed to the rotametor.

Seine puillps are equipped with a17 elapsed tiilie ineter wl~ich reads in hours. Forin PBF-31)78 is ~ ~ s e d for recording pertinent air sampling dma for each locntion. At a ilorillal filtei chailge. the following proced~lre will appl! :

1.

Record "date off" and "time off."

2.

Record rotailleter reading for end of period (It2).

3.

Turi-i off pump. if necessnr:-. and record hour meter reading or actual tilllo for end of period (t?).

3.

Before removing the filter. label the sample envelope as directed in Sectioil 2.2.7. Also enter ally other pertiileilt iilforillatioil at this time. Albvays write data on the envelope before inserting the particulate filter in the emelope.

5.

Remove particulate filter being carefill to handle filter onlj bj edges.

place in the glassine envelope. Do not fold the iilter. Folding and unfolding may dislodge material from the filter, It also may illake a reproducible countiilg geometi~ iillpossible to achieve.

6.

Re~nove chascoal carrridge, place in plastic bagr and label as directed in Sectioil2.2.7, 7,

lilstall new charconl cartridge and particulate iilter being sure to clleclt the cl~arcoal cartridge for brealts and the particulate filter for holes in the filter surface, Discard ~uilacceptable filter media.

Page 17 of 34 INFORMATION USE

POINT BEACH NUCLE-4R PLANT EM ENVIRONMENTAL MANUAL We~.ision 22 April 20. 30 10 ENVIRONh/ENTAL klANLIAL

8.

Record "date on."

9. Record hour nletzr reading or time for begiilning of period (tl j.

10. Turi~ pump on (if necessai~).

1 1. Perforill weelt1:- gross leak test bj-bloclting tke air flow with a large rubber stopper. (For this test 0111~. tile rotameter ball may register zero or drop all the way to the bottom. The diffirence betc~een zero and tlle bottoi~~

is not sigilificant.)

12. Record rotameter reading for beginning of peiiod (R1 j.

13. Record correctioii factor 3s indicated on calibration stislter affixed to rotameter (C').

13. Observe that the starting rotameter reading (RI ) is close to the previous ending reading (R2j. A substantial difference indicates need for f~irtl~er investigation because the regulator will generall) maintnin coilstnilt flow regardless of filter loading.

1 5 Calculate total volume for period and elites on data sl~eet (1n3) (This step maj be perforilzed at a later rime.)

16. An>- uilusual conditions or observations should be referenced under (9 a11d recorded under ""NOTES" at the bottom of the data sheet.

,4ir saillples are collected for the State of 'A iscoilsill at tcso locations.

one of which is co-located \\\\it11 a PBNP air sail~plii~g site. The) are hai~dled in a maniler similar to PBNP sail~ples except that no charcoal cartridges are in~~olved.

However. state samplers are equipped cyith ~ o l ~ u i l ~ e integrating meters. Therefore. clock tiil~e must be recorded in additioil to tl~e eildiilg and beginning volumes.

Label and forward samples to the State.

Page 1 S of 34 INFO&iATION USE

POINT BE-4CH NUCLEAR PLANT Ehl ENVIRONMENTAL MANUAL Re\\.ision 2%

Aplil 20. 20 10 ENVIRONMENTAL MAN IJ AL

b. Air sampling system description T11e air monitoring equipillelit fol tlle PBNP air sampling program consists of a Regulated Rate Control S: stein. The Regulated Rate Control Sl stein is used at PBNP because of its silnplici~ and reliabilit:

It is designed to minimize hot11 calibration difficulties and the potential for leaks The regulated rate control s: stein includes a p~imp. a flow regulator. the appropriate filter holders and a nlinini~i~n of tubing. Also. it ma: include an elapsed time meter. In this s~stem. the total volume sanlpled can be calculated siinpl: and accurately fro111 the elapsed time and the flobv rate wl~icl~

is kept coilstant b~ the regul~tor regardless of filter loading.

The air sainplers are Eberline Model U S - 1 (or ecluivalent) and ha1.e built-in rotaineters which read in liters per minute. The s:-sten~s also include an Eberline 1. PH-1 (or equivalent) weatherproof housing and an iodine cartridge holder and mounting Itit and ma: iilclude ml electric hour meter. Glass fiber. 47 nlin diallleter. particulate filters capable of collectiilg 95% of 1 inicron diailleter particles and iodine impregnated cl~arcoal cartridges (Scott or equivalent) collstitute the filter media.

Calibrate the p~uinp rotaineter at initial installation and at J earl! intervals thereafter b: connecting a laboratorj -qualin reference fIo\\v iileter with NIST tr~ceable calibration to the filter face ~ i t h the particulate filter and charcoal cartridge in position. Upon completion. a calibration sticker ilidicating the co~~ection factor is affjxed to. or near. the built-in rotameter.

The results are recorded on Form PBF-4070 eeltly gross leak c11ec1is shall be accoii~plisl~ed as indicated in the appropriate PBNP procedure.

For i~orinal operation. the regulators should be adjusted to maintaii~ a true flow rate of 28-30 liters per minute. Ad.i~iustments are made b~ t ~ ~ r i ~ i n g the screw inarlted FLOI! ADJUST located on tl~e side of the regulator bod: :

co~~ntercloclt~~

ise i~~creases flo\\v. clockwise decreases flow. Flow rates should be observed at all filter clzanges. Flou* rates less than 26 lpin or inore tllan 32 lpin require readjustment of the regulator. Particular attention should be paid to Bobv rate readings u-ith the "old." loaded filter and \\1itl1 new. un~lsed filters in position. Because of the regulator. the difference in flow sho~rld be barel: perceptible. perhaps no inore t11an one Ipm. Significant diffirences in flobv rates recluire further investigation to determine the cause.

Preventive lnaiiltenailce shall be perfoiined as indicated in the appropriate PBNP procedure on all en~.iromnental air sainplers and the results recorded on Form PBF-4020.

b I

Page 19 of 31 IN FORlMATION USE

POINT BEACH NUCLEAR PLANT ENVIRONMENTAL A/liliN U AL EM Revision 22 April 20. 20 10 e. P~li11p repair and replacellleilt The pumps can opemte for long periods of time bvith minimal or no maii?tenance. The vane assemblj of the pump is nlost susceptible to hil~tre. indicated b~ escessi~.e noise or inability to maintain sufficient flow across loaded filters, At least one staridb~ puillp sllould be available for temporar~ service duriilg the repair pesiod. 111 the event of il~otor failures due to causes other than defective connections. complete replacelllent of the unit ma! be ilecessaq. All puiilp repairs sl~ould be done in a clean-side shop wit11 clean tools 2.4.6 Milk Because of iodine decal. and protein billding of iodine in aging milk samples.

speed is in1perati-t.e in processiilg and saillples must be l<ept cool to avoid degradation and sl~uildge of the sai~lples Milk samples are obtained 111onthl~

in coi$~~nction b~ith the State of L i iscoilsin Mill< Sai~ipling Pro~ram from three individual dairj faril~ers located north. south. and west of the site hlillt sampling data can also be obtained from the Kewa~ulee Pobver Station (KPS).

\\\\-hose radiological environmental illoilitoriilg program includes sai~lples talien from a dairy i11 Green BJ!.

\\;I I. This location could act as a control location Because tcvo of the three sites are co-located. the PBNP picltup is coordinated to coincide \\sit11 the State arranged schedule. The picltup usuallj-will be the secoild 'l\\i ednesdaj of tke ~11oi~t11.

The folloc~ing seclueilce sllould be followed:

a. After verifj-ing the State milk picltup date nith the blailitowoc Public Health Department (Mr. &lark Chateizlta. phone ilumber 683-1154). notif!

dairies of picltup date.

b. Because the 111ill~ must be kept cool. but not frozen. fill enoug1-1 cubitainers. or other appropriate coiltainers. wit11 cvater and freeze to be able to put one in each sl~ipping container. Fill the coiltainers with bvater and freeze the daj-preceding the piclc~lp or use ice packs.

c. T11e milk fi-oin the Strutz farm (E-2 1) inust be piclied up before 0900 because that is the tiilie the Str~tz illilk is shipped. A late arrival ma!-

mean a missed sample. hlillt from sites E-1 1 and E-30 ma) be piclted up 311:

time after the Strutz piclt~~p.

d. Identifj ~ottrself and the nature of J our business at each milk pickup site.

Collect tcvo one-gallon samples from each site. uslilg a i-i~lnnel if necessar~.

If sllipillei1t cannot occur on the collectioil d a ~

. store the mill< in the environmental refrigerator at the SBCC overnight. DO NOT FREEZE.

i Page 20 of 31 INFORMATION USE

P01NT BEACH NUCLEAR PLAN?

ENVlRONMENTAL MANUAL ENVIRONMENTAL MANUAL

e. Complete a PBNP sample tag according to Section 2.2.7 for each gallon sample and place in the box with the sample and ice or ice paclts Do not seal the box. Place the sai~lples in insulated containers and turn tllem over to Ready Stores personnel for shipinant nilalte sure that the cover lettcr and. as appropriate. tke contractor data collzctioil sheets are sent according to Section 2.2.8 of this manual.

2.4.7 Algae Fi1:lineiitous algae are collected from pilings or roclts tl-~ree tiixes per ear. as available. fro111 two locatioils. The loi~g. grass:-. darlt green algae call iioi~nallj be cut wit11 scissors. The shorter. light green algae normall! 111ust be scraped from roclts or pilings \\I* he11 scrapi~~g algae, be caref~~l not to include pieces of rock in the sai-nple. The sample call be ligl~r-1:- rinsed in the saine medium in t~hich it is grouing. This rinse tvill llelp rid the saiilple of pieces of rock and gr~vel that ma! have been inadvertentls collected with the sample. Because roclis 2nd sedinlent contaiil~~atlirall~

occurring radioactive materials. their iilclusion inaj give false sample results. Collect between 100 and 1000 gm of algae A sample greater tha1-1 500 gin is preferred. Place the algae in a uide-1110~1th pol: bottlz or other appropriate coiltainer and label the container as director in Section 2 2 7 Tlie algae inust be ltept cool to prevent spoilage.

t Page 2 1 of 34

)

INFORniIAT10N USE

POlNT BEACH NUCLEAR PLANT Ehl ENV IRON~JLENTAL h.1.4NUAL Revision 22 Apiil 20. 20 10 ENVIRONMENTAL MAN 1J-4L 2.4.8 Fish The iish for tlse Point Beach E M P are obtained from either the tra\\,eling screens as wshed illto the fish baslcets or b:- otller inetl~ods. as required. Tlze two-fold objective of liish sampling is to obtain commercial1~- and recreationall:- insportant fish (game fish) tlzat occur in the vicinit: of the plant and to deterilliile if there is evidence of PBNP released radioi~uclides ill the fish.

Tllere are three coilfo~lildillg factors affecting this objective. The first is tl~e rec:-cling of non-PBNP sources sucll as fallout fro113 atinosplleric weapoi1s testing ill the 1930s and 1960s and subsequent Chinese tests. fallout from the C'heri~ob: 1 accident. and release from other plants on Lake Michigan. Due to the long residence time of u ater in Lalte Michigan (about 200 5 ears).

radioi~uclides eilterillg Lalte Michigan reinaiil in the lalce for a long time. This means that a 1oi1g half life radionuclide such as C's-137 is still preseilt in the lake and in the fish.

The secoild coilfoulldiilg factor is the migrator> behavior of tlse Irish. In addition to moving around tile Ialte. iisls move from deep water to the sl~allovzer. iilsllore areas. It is 0111: ~vheil the fish are in the inshore area that the: are susceptible to being d r a w illto the PBNP water intalte. Therefore.

the radioacti~jtl\\- ill tlse fish so caught ma:- not originate fi-om PBNP but from an!- of the above nalxed sources.

In addition to the migratoq beha\\.ior of fish. fish sampling also is effected b>-

the fish detei~ent system used at the PBNP \\vater intake. The purpose of this sj stein is to prevent sclsools of f7sh froin being suclted into the coolin, cr l~ater intalte.

As a result of all these factors. the avai1abili~- offish is not ~riliforin throughout the :-ear. Based 011 experience. the period from late Spring to earl:-

Fall appears to be the best pesiod for obtaining game fish. Therefore. iish foi the PBNP M M P ill be sent for analysis at least ttvice a :-ear based on seasolla1 availabilit:. Fish also are supplied to the State of \\i iscoilsin at the same fi.equenc~-. (Fish ma; be sent illore freq~~ently if available.)

Operatioils reinoves the fish from the fish baslcet pursuant to 0 1 38 Attachment D. Each game iish is identified. placed in a clear plastic bag and the bag sealed. and the collectioil date and fish naiile written on the bag. The fish are placed in the game fish freezer in the puiilp house. Trash fish. such as carp are bagged and placed in the trash fish freezer.

Page 22 of 34 I

INFORMATION USE

POINT BEACH NLC'LEAR PLAN?

ENVIRONMENTAL MANLIAL ENVIRONA4ENTAL MANUAL Because individual fish are anal>-zed. emphasis is placed 011 large fish tvhicll will J-ield at least 1000 grains (2.2 Ibs.) of fillets in order to easily achieve the required LLD. Bec~~use of the aforeineiltioned factors. it n l a ~ not be possible to have enough large fish to fulfill the 1000 granl rzq~~irenlent.

LL he11 this occurs. the lab lvill adjust count tinle on the available fish in order to achie1.e the required LLD.

1. Obtain the game fish froill the freezer and package for shipinelit to the PBNP contracted mdioanalytical lab and to the State. (If no gaine fish are mailable. trash fish from the lmger freezer ill the p ~ ~ i i ~ p house ma>- be used.)

3. Pack fish in an insulated container nit11 ice or other siinilar cold media. as necessar>-. to prevent spoilage of the iisli during transit. To aid in pre\\ entiilg the fish from tha\\ving during trai~sit. fish sl~o~sld be sliipped so that the>- will arrive on or before Friday. lf this is not possible. include enough cooling material so that the ilsl~ cvill not spoil if sitting on a loading dock o\\.er the weekend.

3. Ser,d fish at the end of Ma: and the end of August.

4. Dividz the available fish approximatel\\ in I~alf for shipmeilt with PBNP contracted mdioanalytical lab secei~ing the larger portioil when an odd nu~nber of -fish are available. If additioinl ganle fish are available later in the :-ear. the! u-ill be sent duriilg the fo~srt1-1 quarter.

5. The cogilizai~t Chemist will illalte the filial decision sl~ould fish sampling questions aiise.

2.4.9 Soil Soil iiltegrates atmospheric depositioil and acts as a reservoir for long-lived mdionuclides. Altl~o~~gll soil sainpling is a poor technique for assessing si~lall increineiltal releases and for moilitoring routiile releases. it does pro~ide a means of monitoring long-ten11 treilds in atmosphelic depositioil in the vicinity of PBNP. Therefore. soil sanlpies are obtained two times per >-ear from specified locations.

Clear the vegetation from a 6" s 6" area: being careful to leave the rop layer of soil relatively intact. Remove root bound soil by sllaltiilg the soil onto the cleared area or into the sample container before discarding the roots. W11en iiecessai-y, it is preferable to leave soille roots in the soil rather than to lose the top layer of soil.

Page 23 of 34 IN FORIvlATION USE

POINT BEACH NUCLEAR PLtlNT ENVIRONhiENTAL MANUAL ENVIRONMENTAL MANUAL EM Revision 22 Apiil 20. 30 10 Remo\\.e the soil to a depth of three ii~ches. If necessar:. expand the area.

instead of digging deeper. to obtain the recluired amo~ui~t of sample. If a11 area larger than 6" s 6" is used. notif) Cllemistr: of the area used The miniinruin acceptable quantity is 500 gmins. Place the entire soil sainple in a wide-mouth pol: bottle or ai~other appropriate container. If a plastic bag is used. seal the bag with tape. Label the sample as directed in Sectioil2.2.7.

Tl-iis procedure assumes that the salllples are obtained from uildisturbed land:

land that has not beell plowed within approxiinatel: the last 25 I. ears. If the land 11as beell plou-ed. the soil should be sampled to the plow depth which typicall: is eight iizclles. Place the soil in a cleat1 bucket or appropriate size plastic bag. homogenize the soil and place 1000 graills of the well mixed soil sample in a plastic bag. or otller appropriate container. and label as described ahove.

Shoreline sediineilt coilsistiilg of sand and sinaller gmin size material is sampled tn o tiines per J. ear froin specified locations. The 1000 gram sainple is collected. from beach areas near the water ridge. At each locatioil collect representati~e samples of sediineilt types roughl~ ill proportioil to their occuiTence. For example. at E-06 a~.oid collectiilg a sample wllii.11 consists esclusi\\.ely of the dark-broun to black sedi~neilts u711ic11 occur in la: ers up to several inches tl~ick. Pacltage the sa~nplz in a \\vide-mouth pol: bottle or other appropriate coiltaiiler and label as described in Sectioii 2.2.7.

Milk Survel-The 111illt saillpliilg prograin is reviewed al~i~~iall:-.

iilcludiilg a vis~al verification of animal grazing ill tlze \\'icini~ of the site boundar:. to ensure that saillpling locatioils reillail1 as conservative as practicable. The verification is co~lducted each suinlnev by cognizant PBNP personnel. Because it is already assuined that milk ani~nals ma>- graze up to the site bounda1:-. it is 0111:- necessaiT-to verifi-that these animals haye not moved oilto the site. No ailiinal census is required. Upoil coi~lpletioi~

of the visual check. a memo ti-ill be generated to docuineilt tke r e ~ i e b ~

and the memo sent to file. To ellsure perforinance of the annual \\.erification. "milk re\\.ie\\v" is identified on the sampling checldisb (i.e.. the PBF-4 12 la-1 series).

P Page 23 of 31 INFORMATlON USE

POINT BEAC'H NUCLEAR PLANT Ehl ENVIRONlvENTAL MANLlAL Revision 32 April 20. 20 10 ENVIRONMENTAL MANUAL TABLE 2-1 REC'OhlhlENDED ? i l I N l ~ I l J ~ l SAMPLE SIZES Sample Tvpe Size Vegetation Lalte l\\;'ater Air Filters Well Water Millc Algae Fish (edible portions)

Soil Shoreline Sediineilt b

Page 25 of 34 100 - 1000 gill S liters (4 gal) 2.50 m3 S liters (2 p l )

S liters (3 gal) 100- 1000 Ell1 1000 gin 500- 1000 gill 500-1000 g111 b

INFORLLlATION USE

POINT BEACH NUC'LEAR PLANT EM ENVIRONMENTAL M.4NUAL Rzvision 22 April 20. 20 10 ENVIRONMENTAL IdANU AL TABLE 3-72 SAMPLE TYPES AND ASSOCIATED LOIJ,ER 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 pCi/g wet Gross Beta CS-137 CS-134 1-131 other'"'

Shoreline pCi/g dry Gross Bets Sediment and Cs-I37 Soil other'"'

Algae pCi,ig wet Gross Beta (3-137 CS-134 Co-5s Co-60 other'"'

Fish pCi/g wet Gross Beta CS-137 CS-134 Co-58 Co-60

&In-54 Fe-59 Zn-65 other'"'

TLDs mRI7 days Gamma Exposure 5mW7 days

~akewater'"

p ~ i / ~ - ~. ~. ( d '

Gross Beta and Well Water Cs-134 CS-137 Fe-59 Zn-65 Zr-N b-95 Ba-La-140 CO-58 Co-60 b

INFORMATION USE Page 26 of 34

POINT BEACH NUCLEAR PLANT EM ENVlRONrVlENTAL hlANUAL Revisioi~ 22 Aplil 20. 20 10 ENVIRONMENTAL MANUAL TABLE 2-2 SAMPLE TYPES Aru'D ASSOCIATED LO11 ER LEVEL OF DETECTION (L.LD) AND NOTIFICATlON LEVEL VALUES Lakewater p ~ i / ~ - ~. ~. ' "

'111-54 I5 (IOj 1,000 100 250 and Well Water 1-131 2 (0.5)

--=

2 (Continued)

Other 30 100 H-3 (Lakewater) 3,000 (200) 30.000 3,000 7,500 H-3 (Well Water) 3,000 (200) 20,000 3,000 7,500 Sr-89 10 (5) 50

--=

Sr-90 2 (1) 20 Milk Sr-89 5

100 9-90 I

100 1-131 0.5 3

0.5 0.75 CS-134 15 (5) 60 15 15 CS-137 l S (5) 70 IS IS Ba-La-140 15 (5) 300 3 0 75 other'")

15 3 0 Air Filter Gross Beta 0.0 1 1.O I

1-131 0.07 (0.03) 0.9 0.09 0.2 CS-137 0.06 20 2.0 5.0 CS-134 0.05 10 I.O 2.5 other.(")

0. I I.O I (a)

The LLDs in this column are the maximum acceptable values. The values in parentheses are the LLDs currently used (see Section 2.2.3)

(b)

The values in this column are not technical specifications.

I (c)

Other refers to non-specified identifiable gamma emitters. resulting ftorn the operation of PBNP. Narurally occurring radionuclides are not included.

(dj T.S. = total solids.

(e)

No drinking water t

Page 27 of 34 1NFORMATION USE

POlNT BEACH NUCLEAR PLANT ENVIRONhlENTAL MANUAL ENVIRONl\\/lENTAL MANUAL TABLE 2-3 RADIOLOtilCAL ENVIRONMENTAL SXhlPLlNG LOCATlONS 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 from 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 Corner of the Intersection of Cty. B and Zander Road Nature Conservancy, East side of Hwy 42. Corner 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 1 Pier, U-I side Pumphouse South Boundary. about 0.2 miles East of Site Boundary Control Center SW Corner of Site, N side of Nuclear Rd at junction with Twin Elder Rd.

LVSW. Hwy. 41, Residence. about 0.25 miles North of Nuclear Road North of Mishicot, Cty. B and Assman Road, NE Corner of Intersection N W of Two Creeks at Zandet 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 NormanISaxonberg Road 804 Tapawingo Road, about 0.4 miles East of Cty. B. North Side of Road NE corner of Saxonburg and Nuclear Roads, about 4 Miles WSW TLD on westernmost pole between the 2nd and 3rd parking lots.

On microwave tower fence NE corner at Intersection of Tapawingo and Lakeshore Roads.

On utility pole North side of Tapawingo Road closest to the gate at the West property line 9

Page 28 of 31 t

1NFORMATlON USE

POINT BEACH NUCLE-4R PL-AN?

EN 1;IRONhENTAL AflAN UAL ENVIRONMENTAL MANUAL E-4 1 E-42 E-43 E-TC TABLE 2-3 RADIOLOGdC'AL ENVIRONMENTAL SA&IPLlKG LOCATIONS On a conduitlpoie located near the junction of property lines, about 500 feet east of the west gate in line wirh first designated treeline on Tapawingo Road and about 1300 feet south of Tapawingo Road. The location is almost under the power lines between the blue and gray transmission towers. (The conduit/pole is about 6 feet high).

Lake Michigan shoreline accessed from area just S of KPS discharge.

On tree West of former Retention Pond site On tree East of former Retention Pond site Local Dairy Farm (Barta). about I.S miles norrh of intersection of Highway 42 and Nuclear Road (Manitowoc County), on West side of Highway 43.

N W corner of Woodside and Nuclear Roads (Kewaunee Co.)

NW corner of Church and Division, East of Misliicot West Side of Tannery Road Soutfi of Eltnwood (7th pole South of Elmwood)

Transportation Control; Reserved for TLDs t

INFORMATliON USE

POINT BErlCH NUCLEAR PLANT ENVIRONhlENTAL MANUL4L ENVIRONMENTAL &!I-4NUAL TABLE 2-4 PBNP K4DIOLOGlCAL ENVIRONMENTAL S-AblPLE COLLECTION AND ANALYSlS FREQUENCY Sample Type Sample Codes Analyses Freq~~ency Quarterly Environmental Radiation E-0 1, -02. -03, -04, -05, TLD Exposure

-06. -07, -08, -09, -12.

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

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

-26, -27, -25. -29, -30,

-3 1, -32. -35. -39. -4 1,

-42, -43, -TC I

Vegetation E-0 1. -02, -03, -04, -06.

Gross Beta

-08, -09, -20.

Gamma Isotopic Analysis 3x/yr as available 3dyr as available Gross Beta Gamma Isotopic Analysis Algae I Fish Gross Beta Gamma Isotopic Analysis (Analysis of edible portions only) 2x/yr as available Well Water Lake Water Gross Beta, H-3 Sr-89, 90, 1-13 1 Gamma isotopic Analysis (on total solids)

Quarterly Gross Beta H-3, Sr-59,90 Monthly Quarterly composite of monthly collections Montllly Monthly 1-13 1 Gamma Isotopic Analysis (on total solids)

Milk Sr-89, 90 1-131 Gamma isotopic Analysis Monthly Weekly (particulate)

Weekly (charcoal)

Quarterly (on composite particulate filters)

Air Filters E-0 1. -02, -03, -04, Gross Beta

-08, -20 1-131 Gamma isotopic Analysis Soil E-0 1, -02, -03, -04, Gross Beta

-06, -08, -09, -20, Gamma lsotopis Analysis Shorelins Sediment E-01, -05, -06, -12, Gross Beta

-3 3 Gamma Isotopic Analysis 1

Page 30 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT ENVIRONMENTAL MANUAL TABLE 2-5 SAMPLES COLLECTED FOR STATE OF \\i ISCONSIN Sample Type Location Frequencv I.

Lake Water E-0 1 Monthly 3 -

Air Filters E-07 E-OY

3.

Fish

4.

Precipitation E-04 E-OY 5 -.

Milk E-2 1 E-40

6.

Well Water E-I0 I

Page 3 1 of 31 Weekly Semianl~ually, As Available Twice a month.

As Available Monthly 2 timeslyear t

INFORMATION USE

PO137 BEACH NIJCLEAR PLAN7 ENVIRONMENTAL MANUAL Ehl Revision 22 Ap1i1 20. 20 10 ENVIRONklENTAL MANUAL FlGURE 2-1 a RADlOLOGlCAL ENVIRONMENTAL SAlClPElNG LOCATIONS FLCURE 2-10 8

Page 32 of 34 lN FORMATlON U

POINT BEACH NUCLEAR PLANT ENVIRONMENTAL lClANUAL Ehl Revision 22 April 20. 20 10 ENVIRO_NMENTAL MANUAL FIGURE 2-IC RADIOLOGICAL ENVIRONMEhTAL SAMPLlNG LOCATIONS 8

Page 34 of 34 INFORfvlATlON USE