NRC 2012-0028, 2011 Annual Monitoring Report, for the Period January 1 Through December 31, 2011

2011 Annual Monitoring Report, for the Period January 1 Through December 31, 2011

ML12122A213
Person / Time
Site:	Point Beach
Issue date:	04/30/2012
From:	Jim Costedio Point Beach
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
NRC 2012-0028
Download: ML12122A213 (219)

Text

I BEACH April 30, 2012 NRC 2012-0028 10 CFR 72.44 TS 5.6.2 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266, 50-301 and 72-005 Renewed License Nos. DPR-24 and DPR-27 201 1 Annual Monitorins Report In accordance with Point Beach Nuclear Plant (PBNP) Technical Specification 5.6.2, enclosed is the Annual Monitoring Report for PBNP Units 1 and 2, for the period January 1 through December 31,201 1.

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 1. The report also covers the results of radiological monitoring of the PBNP Independent Spent Fuel Storage Installation (ISFSI), as required by 10 CFR 72.44.

Enclosure 2 contains the PBNP Environmental Manual, which was revised in March 201 1 This letter contains no new regulatory commitments and no revisions to existing regulatory commitments.

Very truly yours, NextEra E n e r a Point Beach, LLC Y & F James ostedio 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 Wl 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 I ANNUAL MONITORING REPORT 201 1 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 1,201 1 through December 31,201 1

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 B: Miscellaneous Reporting Requirements 7.0 Additional Reporting Requirements Part C: Radiological Environmental Monitoring 8.0 Introduction 9.0 Program Description 10.0 Results 11.0 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

LlST OF TABLES Table 2-1 Comparison of 201 1 Liquid Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives Table 2-2 Summary of Circulating Water Discharge Table 2-3 Isotopic Composition of Circulating Water Discharges (Curies)

Table 2-4 Subsoil System Drains - Tritium Summary Table 3-1 Comparison of 201 1Airborne Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives Table 3-2 Radioactive Airborne Effluent Release Summary Table 3-3 Isotopic Composition of Airborne Releases Table 3-4 Comparison of Airborne Effluent Doses Table 4-1 Quantities and Types of Waste Shipped from PBNP Table 4-2 201 1 Estimated Solid Waste Major Radionuclide Composition Table 4-3 201 1 PBNP Radioactive Waste Shipments Table 6-1 Circulating Water System Operation for 201 1 Table 9-1 PBNP REMP Sample Analysis and Frequency Table 9-2 PBNP REMP Sampling Locations Table 9-3 ISFSl Sampling Sites Table 9-4 Minimum Acceptable Sample Size Table 9-5 Deviations from Scheduled Sampling and Frequency Table 9-6 Sample Collection for the State of Wisconsin Table 9-7 Comparison of 2001 TLDs: LiF Chips vs. TLD Cards Table 10-1 Summary of Radiological Environmental Monitoring Results for 201 1 Table 10-2 ISFSl Fence TLD Results for 201 1 Table 10-3 Fukushima Gross Beta and Charcoal Cartridge Results Table 10-4 Additional Fukushima 1-131 Results Table 10-5 Gamma Scan of Weekly Airborne Composite Samples Table 10-6 Precipitation Results South, West, and North of Point Beach Table 11-1 Average Indicator TLD Results from 1993-2011 Table 11-2 Average ISFSl Fence TLD Results (mW7days)

Table 11-3 Average TLD Results Surrounding the ISFSl (mW7days)

Table 11-4 Average Gross Beta Measurements in Air Table 14-1 Intermittent Streams and Bogs Table 14-2 201 1 Beach Drain Tritium Table 14-3 U2 Faqade Subsurface Drainage Sump H-3 Table 14-4 201 1 East Yard Area Manhole Tritium Table 14-5 201 1 F a ~ a d e Well Water Tritium Table 14-6 201 1 Potable Well Water Tritium Table 14-7 201 1 Monitoring Well Water Tritium Table 14-8 201 1 Precipitation H-3 at Boundary Locations Table 14-9 201 1 H-3 Concentrations Close to Plant LlST OF FIGURES Figure 9-1 PBNP REMP Sampling Sites Figure 9-2 Map of REMP Sampling Sites Located Around PBNP Figure 9-3 Enhanced Map Showing REMP Sampling Sites Closest to PBNP Figure 11-1 ISFSl Area TLD Results Figure 11-2 Sr-90 Concentration in Milk Figure 11-3 201 1 Airborne Gross Beta Concentration (pci/m3) vs. Time

Figure 13-1 Groundwater Monitoring Locations Figure 14-1 201 1 S-I and S-3 Beach Drain Concentrations (pCill) vs. Time Figure 14-2 201 1 H-3 Concentrations SSD Sump Figure 14-3 Location of WashoutlRecapture Sampling Sites

SUMMARY

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

Li uid Atrn os heric Tritium Ci particulate (Ci) 0.0447 0.00021 7 Noble Gas Ci Ic-14' I 0.0148 10.46 I

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

' ~ t m o s ~ h e rparticulate ic includes radioiodine (1-131, 1-133).

2 Liquid is measured, atmospheric is calculated.

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

LIQUID RELEASES Dose Cateqow Calculated Dose Appendix I Dose Whole body dose 0.00675 mrem 6 mrem Organ dose 0.00692 mrem 20 mrem ATMOSPHERIC RELEASES Dose Cateaow Calculated Dose Appendix I Dose Organ dose 0.223 mrem 30 mrem Noble gas beta air dose 0.000710 mrad 40 mrad Noble gas gamma ray air dose 0.00150 mrad 20 mrad Noble gas dose to the skin 0.00219 mrem 30 mrem Noble gas dose to the whole body 0.00142 mrem 10 mrem

The results show that during 2011, the doses from PBNP effluents were a small percentage (4.707%) 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. Of the sixteen compass sectors around PBNP, six are over Lake Michigan. A land use census (LUC) of remaining ten land containing sectors identified the closest garden, occupied dwelling, and dairy in each sector. The LUC results confirm the assumption that, for the purpose of calculating effluent doses, the maximally exposed person lives at the south boundary remains conservative.

The 201 1 Radiological Environmental Monitoring Program (REMP) collected 768 individual samples for radiological analyses and 125 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 16 samples. This yields a total of 808 samples.

Air monitoring from six different sites did not reveal any effect from Point Beach effluents.

However, the air particulate, charcoal cartridges, and precipitation samples in March and April showed fallout from the Fukushima Daiichi event. Sample results obtained before and after these two months consisted of background radioactivity from naturally occurring radionuclides.

In addition to the scheduled REMP samples, an additional five sets (particulate and radioiodine) of air samples were obtained during this time period. During the time of the Fukushima event, air particulate filter were composited weekly and gamma scanned for radioactivity.

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. Although 1-131 from the March Fukushima event was found in air samples, no 1-131 was found in any of the milk samples obtained in the months following the event.

There were no new dry storage units added to the ISFSl in 2011. The total number remains at 30 dry storage casks: 16 ventilated, vertical storage casks (VSC-24) and 14 NUHOMSO, horizontally stacked storage modules. The subset of the PBNP REMP samples used to evaluate the environmental impact of the PBNP lSFSl showed no environmental impact from its operation.

The environmental monitoring conducted during 2011 confirmed that the effluent control program at PBNP ensured a minimal impact on the environment.

Approximately 281 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.

Tritium being discharged via various plant stacks may be recaptured via precipitations and deposited on site. Precipitation sampling to evaluate the onsite recapture of discharged airborne H-3 found concentrations up to 2200 pCi/l close to the plant. The concentrations in rain water decreased to less than detectable levels at the site boundary. This demonstrates that the recapture of stack discharged H-3 can explain the H-3 concentrations found in the yard drain system and the various on-site, below ground electrical vaults. All recaptured tritium drains to Lake Michigan.

Part A EFFLUENT MONITORING

1.0 INTRODUCTION

The PBNP effluent monitoring program is designed to comply with federal regulations for ensuring the safe operation of PBNP with respect to releases of radioactive material to the environment and its subsequent impact on the public. Pursuant to 10 CFR 50.34a, operations should be conducted to keep the levels of radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARA). In 10 CFR 50, Appendix I, the Nuclear Regulatory Commission (NRC) provides the numerical values for what it considers to be the appropriate ALARA design objectives to which the licensee's calculated effluent doses may be compared. These doses are a small fraction of the dose limits specified by 10 CFR 20.1301 and lower than the Environmental Protection Agency (EPA) limits specified in 40 CFR 190.

10 CFR 20.1302 directs PBNP to make the appropriate surveys of radioactive materials in effluents released to unrestricted and controlled areas. Liquid wastes are monitored by inline radiation monitors as well as by isotopic analyses of samples of the waste stream prior to discharge from PBNP. Airborne releases of radioactive wastes are monitored in a similar manner. Furthermore, for both liquid and atmospheric releases, the appropriate portions of the radwaste treatment systems are used as required to keep releases ALARA. Prior to release, results of isotopic analyses are used to adjust the release rate of discrete volumes of liquid and atmospheric wastes (from liquid waste holdup tanks and from gas decay tanks) such that the concentrations of radioactive material in the air and water beyond PBNP are below the PBNP Technical Specification concentration limits for liquid effluents and release rate limits for gaseous effluents.

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

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 1 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 li-quid 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 2011 Liquid Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives Annual Limit [mrem] Highest Total Calculated Dose  % of Design

[mrem] Objective 6 (whole body) 0.00675 0.1 13 %

20 (any organ) 0.00692 0.0346 %

201 1 Circulatins Water Radionuclide Release Summaw 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, the Unit 1 and 2 facade sumps and the subsurface drainage system sump.

201 1 Isotopic Composition of Circulating Water Discharges The isotopic composition of circulating water discharges during the current reporting period is presented in Table 2-3. The noble gases released in liquids are reported with the airborne releases in Section 3.

The total isotopic curie distribution (gamma emitters plus hard-to-detects other than strontium) decreased by about 40% from 2010, with the main decrease being a factor of 20 decrease in Co-58. As in 2010, there was no Sr-89/90 in liquids in 2011. In 2011, H-3 is about 60 curies lower than 2010. Tritium continues to be the major radionuclide released via liquid discharges.

2.4 Beach Drain Svstem Releases Tritium Summary Beach drain is the term used to describe the point at which the site yard drainage system empties onto the beach of Lake Michigan. Six of these outfalls carry yard and roof drain runoff to the beach. A seventh 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 2011, no tritium was observed in any of the beach drains at the effluent LLDs.

The principle source of water for the beach drains is the yard drain system. In addition to rain, snow melt also enters these drains. During the winter natural melting is enhanced by the use of snow melting machines. This water is poured into the yard drain system. Various roof drains connect to the yard drain system.

The roof drains carry precipitation as well as the condensate from various building AC units. Depending upon the integrity of the buried drainage system piping, groundwater inleakage may occur. Because there are no external storage tanks or piping that carry radioactive liquids, the main source of radioactivity for this system is recapture/washout of airborne H-3 discharges. If groundwater inleakage occurs, then groundwater flow of H-3 from the up gradient area of the former retention pond could contribute H-3 to this system. Also, precipitation recharging the groundwater close to the plant would be another source of this H-3. Because of these various recapture sources, the beach drains also are sampled as part of the ground water monitoring program. These results and other groundwater monitoring results are presented in Part D of this Annual Monitoring Report.

Table 2-2 Summary of Circulating Water Discharge January 1,2011 through December 31,201 I 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 2-3 Isotopic Composition of Circulating Water Discharges (Ci)

January, 201 1 through December 31,201 1 Note: The dissolved noble gases detected in liquid effluents (e.g., Xe-133, Xe-135, etc.) are added to the atmospheric release summaries. "-" = no analysis 8

Table 2-4 Subsoil System Drains Tritium Summary January 1,201I , through December 31,201 1 2.6 Land Application of Sewaae Sludse 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 201 1. All disposals were done at the Manitowoc Sewage Treatment Plant.

Carbon-14 (C-14) is a naturally occurring radionuclide. Nuclear weapons testing of the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Small amounts of C-14 also are produced by nuclear reactors, but the amounts produced are less than C-14 produced by weapons testing or that occur naturally. NextEra Point Beach began evaluating C-14 liquid discharges in 2009, prior to the issuance of Regulatory Guide 1.21 (RG 1.21), Rev 2 in June of 2009. Point Beach continues to analyze batch liquid waste discharges for C-14 and reporting the results in the Annual Monitoring Report.

Beginning with the 2010 monitoring reports, the NRC requested that all nuclear plants report C-14 emissions. Pursuant to NRC guidance in RG 1.21(Rev 2) ,

evaluation of C-14 in liquid wastes is not required because the quantity released via this pathway is much less than that contributed by gaseous emissions.

However, based upon participation in industry workshops, PBNP began C-14 analyses and reporting prior to the issuance of RG 1.21 (Rev 2). The results 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 201 1, the monthly and total C-14 (1.48E-02 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. The C-14 dose contribution has been required since 2010 (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 Summarv Radioactivity released in airborne effluents for 201 1 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 201 1, from which the airborne doses were calculated, are presented in Table 3-3. Carbon-14 is not included in Table 3-3 because it was calculated and not measured. C-14 is discussed in the following sections.

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-I4 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 1021106 (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 roughly three orders of magnitude higher than the 1.26E-02 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 C-14 occurs as methane, 1 4 ~ not , carbon dioxide, I4co2.

~ 4 as 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 I4cProduction and Discharge From the Ginna Nuclear Power Reactor," 1982) found that ten percent of the C-14 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.I 09. 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 show as conservative in that the produce usage factor includes grain and fruit and these pathways do not exist in the vicinity of the point for which the C-14 doses are 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 No C-14 measurements were made of PBNP effluents. In 2010, C-14 was measured in crops grown on fields in the owner controlled area located in the highest xIQ 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 xIQ sector as compared to the background site some 17 miles away (Table 10-3). These results demonstrate that the dose from C-14 in PBNP airborne effluents should not measurably increase the C-14 dose compared to that received from naturally occurring C-14 in plants.

3.7 Errata to Previous Annual Monitorinn Reports During the process of upgrading the PBNP ODCM, the xIQ and DIQ values in the Final Safety Analysis Report (FSAR) table containing the summary of meteorological parameters used in the ODCM were found to have been incorrectly transcribed from the other tables in the FSAR. As a result, the airborne effluent doses have been determined to have positive and negative biases. The xIQ value used for noble gas dose calculations was determined to be 0.75% low. The DIQ value used in the ODCM for airborne particulates was 5.6% high. As a result, the noble gas doses are 0.75% low and the airborne ingestion doses are conservative by 5.6%. This situation has existed since approximately 1987. Pursuant to Reg. Guide 1.21 (Rev 2) any error 4 0% is considered a minor error and may be addressed in the effluent section of the AMR with a brief explanation and no revision to previous AMRs are required.

FSAR transcription errors were captured in the corrective action system.

Table 3-1 Comparison of 2011 Airborne Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives Annual Appendix I Design January-December Percent of Appendix I Category Objective Calculated Dose Design Objective Particulate 30 rnrernlorgan 0.223 rnrern . 0.743 Noble gas 40 rnrad (beta air) 0.00071 0 rnrad 0.00178 Noble gas 20 rnrad (gamma air) 0.00150 rnrad 0.00750 Noble gas 30 rnremlskin 0.00219 rnrern 0.00729 Noble gas 10 rnrern (whole body) 0.00142 rnrern 0.0142 Table 3-2 Radioactive Airborne Effluent Release Summary January 1, 201 I,through December 31, 201 1

' Total noble gas (airborne + liquid releases).

Airborne radioiodines only include 1-131 and 1-133. Although for dose calculations iodines are grouped with particulates, for this reporting table they are separated from the particulate group.

Total Particulate is the sum of alpha, strontium, and others. It does not include radioiodines or C-14. C-14 was calculated for the year and no monthly values are available.

TABLE 3-3 Isotopic Composition of Airborne Releases January 1,2011 through December 31,201 1 Note: The Noble Gases listed above include the liquid contribution

Table 3-4 Comparison of Airborne Effluent Doses 201 1 Airborne Particulate + Tritium Dose (mrem)

Bone Liver T-WB Thyroid Kidney Lung GI-LLI Skin Adult 2.34E-04 1.84E-02 1.84E-02 1.84E-02 1.83E-02 1.83E-02 1.83E-02 5.48E-05 Teen 3.15E-04 2.1 1E-02 2.1 1E-02 2.12E-02 2.1 1E-02 2.1 1E-02 2.1 1E-02 5.48E-05 Child 5.08E-04 3.08E-02 3.09E-02 3.09E-02 3.08E-02 3.08E-02 3.08E-02 5.48E-05 lnfant 1.54E-04 1.36E-02 1.36E-02 1.38E-02 1.36E-02 1.36E-02 1.35E-02 5.48E-05 Carbon-I4 Dose (mrem)

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 6.37E-02 1.27E-02 I.27E-02 1.27E-02 1.27E-02 1.27E-02 1.27E-02 0.00E+00 Teen 9.75E-02 1.94E-02 1.94E-02 I.94E-02 1.94E-02 1.94E-02 1.94E-02 0.00E+00 Child 2.23E-01 4.44E-02 4.44E-02 4.44E-02 4.44E-02 4.44E-02 4.44E-02 0.00E+00 lnfant 1.10E-01 2.34E-02 2.34E-02 2.34E-02 2.34E-02 2.34E-02 2.34E-02 0.00E+00 2011 Total Airborne Non-Noble Gas Dose (Particulate + H-3 + C-14 (mrem))

Bone Liver T-WB Thyroid Kidney Lung GI-LLI Skin Adult 6.40E-02 3.10E-02 3.11E-02 3.11E-02 3.10E-02 3.10E-02 3.10E-02 5.48E-05 Teen 9.78E-02 4.05E-02 4.05E-02 4.05E-02 4.05E-02 4.04E-02 4.05E-02 5.48E-05 Child 2.23E-01 7.52E-02 7.53E-02 7.54E-02 7.52E-02 7.52E-02 7.52E-02 5.48E-05 lnfant 1.10E-01 3.70E-02 3.70E-02 3.72E-02 3.69E-02 3.69E-02 3.69E-02 5.48E-05 Ann.Limit 3.00E+01 3.00E+01 3.00E+01 3.00E+01 3.00E+01 3.00E+01 3.00E+01

% Limit 7.44E-01 2.51E-01 2.51 E-01 2.51E-01 2.51 E-01 2.51 E-01 1.83E-04 The percent of limit is calculated using the highest total dose, the Child Age Group.

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 201 1. 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 in 201 1 Type of Waste Quantity Activity A. Spent resins, filter sludge, evaporator bottoms, etc. 11.700 m3 1.821 Ci 414.8 ft3 B. Drycompressible waste, contaminated equipment, etc 660.2 m3 0.268 Ci 23314.0 ft3 C. Irradiated components, control rods, etc. NIA m3 NIA Ci ft3 D. Other NIA m3 NIA Ci ft3 4.2 Maior Nuclide Composition (bv Tvpe of Waste)

The major radionuclide content of the 201 1 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 2011 Estimated Solid Waste Major Radionuclide Composition TYPE A TYPE B TYPE C TYPE D Percent Pencent Percent Percent Nuclide Abundance Nuclide Abmdance Nuclide Abmdance Nuclide Abmdance Ce60 30.7300% (3-60 42.5100%

Ni-63 17.0400% Fe-55 15.9500%

Sb125 10.9000% Nb95 13.6200%

Nb95 9.4300% Ni-63 10.9500%

Fe-55 9.2200% Sb125 3.0700%

H-3 7.7900% Zr-95 2.4800%

C058 4.7400% CS-137 2.4300%

Cs137 2.9800% 01-58 2.1400%

Ag-I 1Om 1.6700% Ag-I 1Om 1.6500%

Zr-95 1.6200% MI-54 1.4100%

Sb124 0.9500% Tc-99 1.3500%

Mn-54 0.9500% Sb124 1.1000%

Mn-54 0.7700% K3 0.7700%

C-14 0.5650% Nb94 0.1600%

Ni-59 0.1900% GI4 0.0900%

Zn-65 0.1000% Sr-90 0.0900%

Ce-144 0.0900% Pu-241 0.0700%

Nb94 0.0900% Am241 0.0400%

St--90 0.0600% 31-65 0.0300%

Pu-241 0.0600% Ce-144 0.0300%

Am-241 0.0200% Ag-I 08m 0.0100%

Cm243 0.0000% (3-57 0.0100%

Pu-239 0.0000% Pu-239 0.0100%

Pu-238 0.0000% Cm-243 0.0100%

Pu-240 0.0000% Sr-89 0.0100%

Cm242 0.0000% Pu-238 0.0100%

Cm244 0.0000% Pu-240 0.0000%

011-242 0.0000%

In-I 13m 0.0000%

4.3 Solid Waste Disposition There were seventeen solid waste shipments from PBNP during 201 1. The dates and destinations are shown in Table 4-3.

Table 4-3 2011 PBNP Radioactive Waste Shipments

5.0 NONRADIOACTIVE CHEMICAL RELEASES Scheduled Chemical Waste Releases Scheduled chemical waste releases to the circulating water system from January 1, 201 1, to June 30, 201 1, included 7.23E+05 gallons of neutralized wastewater. The wastewater contained 6.66E+00 Ibs. of suspended solids and 3.92E+03 Ibs. of dissolved solids.

Scheduled chemical waste releases to the circulating water system from July 1, 201 1, to December 31, 201 1, included 9.72E+05 gallons of neutralized wastewater. The wastewater contained 9.63E+00 Ibs. of suspended solids and 1.57E+03 Ibs. 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, 201 1, to June 30, 201 1, included 1.95E+07 gallons of clarified wastewater. The wastewater contained 4.05E+03 Ibs. of suspended solids.

Miscellaneous chemical waste releases from the wastewater effluent (based on effluent analyses) to the circulating water for July 1, 201 1, to December 31, 201 1, included 1.86E+07 gallons of clarified wastewater. The wastewater contained 2.93E+03 Ibs. of suspended solids.

Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from January 1, 201 1, to June 30, 201 1, included 2.64E+05 Ibs. of sodium bisulfite solution (1.00E+05 Ibs. sodium bisulfite),

2.23E+05 Ibs of Sodium Hypochlorite Solution (2.78E+04 Ibs. sodium hypochlorite), and 4.56E+03 Ibs. Acti-Brom 1338 (2.05E+03 Ibs. sodium bromide).

Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from July 1, 201 1, to December 31, 201 1, included 4.91 E+05 Ibs. of sodium bisulfite solution (1.86E+05 Ibs sodium bisulfite),

5.33E+05 Ibs. Sodium Hypochlorite Solution (6.67E+04 Ibs. sodium hypochlorite), 5.94E+03 Ibs. Acti-Brom 1338 (2.67E+03 Ibs. sodium bromide).

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 2011 UNlT JAN FEB MAR* APR MAY JUN Average Volume Cooling 1 291.9 291.9 314.5 316.0 412.2 506.6 Water Discharge [million gallday]** 2 291.9 291.9 233.8 *

• 320.2 Average Cooling Water 1 38.1 37.3 37.0 42.0 48.3 53.2 Intake Temperature ["F] 2 38.7 38.5 38.2 *

• 54.5 Average Cooling Water 1 70.0 69.0 67.5 72.7 72.9 72.8 Discharge Temperature ["F] 2 71.2 70.0 36.5 *

• 61.8

, Average Ambient Lake Temperature ["F] , , 34.1 , 33.5 , 33.2 , 38.3 , 44.4 , 00s ,

• U2 outage circ water shut down 313111 - 616111

• • For days with cooling water discharge flow.

OOS - Data not available due to instrument issues.

Table 6-1(continued)

Circulating Water System Operation for 201 1 UNlT JUL AUG SEP OCT NOV DEC Average Volume Cooling 1 499.3 499.3 499.3 453.2

• 291.9 Water Discharge [million gallday]** 2 499.3 499.3 499.3 519.9 523.4 310.3 7

Average Cooling Water 1 56.6 64.2 59.1 56.5

• 43.1 Intake Temperature ["F] 2 57.8 65.2 59.8 51.4 44.7 40.5 Average Cooling Water 1 76.6 84.4 79.6 67.9

• 63.7 Discharge Tem~eratureT°F1 2 79.1 87.1 81.9 74.4 62.7 75.0 I Average Ambient Lake Temperature ["F] ( 1 00s 1 00s 1 00s 1 00s 1 42 1 36.2 1

• U1 outage circ water shut down 1014111 - 12113111

• • For days with cooling water discharge flow.

Part B Miscellaneous Reporting Requirements 7.0 ADDITIONAL REPORTING REQUIREMENTS 7.1 Revisions to the PBNP Effluent and Environmental Proarams The ODCM was not revised in 201 1. However, the Environmental Manual (EM) was revised. The EM is part of the ODCM. Copies of the revised EM are being submitted with this 201 1 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 1. 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 201 1.

Part C RADIOLOGICAL ENVIRONMENTAL MONITORING L

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 10 CFR 20.1 302, 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 ISFSl 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 Reportinn Convention The vendor used by PBNP to analyze the environmental samples is directed to report analysis results as measured by a detector, which can meet the required lower limit of detection (LLD) as specified in Table 2-2 of the Environmental Manual for each sample. The report provided by the vendor (see Appendix 1) contains values, which can be either negative, positive or zero plus/minus the two sigma counting uncertainty, which provides the 95% confidence level for the measured value.

The LLD is an a priori concentration value that specifies the performance capability of the counting system used in the analyses of the REMP samples.

The parameters for the a priori LLD are chosen such that only a five percent chance exists of falsely concluding a specific radionuclide is present when it is not present at the specified LLD. Based on detector efficiency and average background activity, the time needed to count the sample in order to achieve the desired LLD depends upon the sample size. Hence, the desired LLD may be achieved by adjusting various parameters. When a suite of radionuclides are required to be quantified in an environmental sample such as lake water, the count time used is that required to achieve the LLD for the radionuclide with the longest counting time. Therefore, in fulfilling the requirement for the most difficult to achieve radionuclide LLD, the probability of detecting the other radionuclides is increased because the counting time used is longer than that required to achieve the remaining radionuclide LLDs.

The REMP results in this report are reported as averages of the measurements made throughout the calendar year plus/minus the associated standard deviation. If all net sample concentrations are equal to or less than zero, the result is reported as "Not Detectable" (ND), indicating no detectable level of activity present in the sample. If any of the net sample concentrations indicate a positive result statistically greater than zero, all of the data reported are used to generate the reported statistics. Because of the statistical nature of radioactive decay, when the radionuclide of interest is not present in the sample, negative and positive results centered about zero will be seen. Excluding validly measured concentrations, whether negative or as small positive values below the LLD, artificially inflates the calculated average value. Therefore, all generated data are used to calculate the statistical values (i.e., average, standard deviation) presented in this report. The calculated average may be a negative number.

As mentioned above, radioactive decay is a statistical process which has an inherent uncertainty in the analytical result. No two measurements will yield exactly the same result. However, the results are considered equal if the results fall within a certain range based upon the statistical parameters involved in the process. The REMP analytical results are reported at the 95% confidence limit in

which the true result may be two standard deviations above or below the reported result. This means that there is only a 5% chance of concluding that the identified radioactive atom is not there when it really is present in the sample. A false positive is an analytical result which statistically shows that the radionuclide is present in the sample when it really is not there. Typically, if the 95%

confidence interval for a positive does not include zero, the radionuclide is considered to be present. For example, the result is reported as 100 k 90. One hundred minus 90 yields a positive result and therefore may be considered to be present. However, this may be a false positive. If the radionuclide was not in the plant effluent, this result would fall into that category which 5% of the time it is falsely concluded that the radionuclide is present when in actuality it is not. This usually happens at low concentrations at or near the LLD where fluctuations in the background during the counting process skew the results to produce a positive result.

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

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

9.2 Sam~linaParameters 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 lSFSl fence TLDs.

9.3 Deviations from Required Collection Frequencv 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 permanent monitoring sites were added in 201 I.Two temporary air sampling sites close to the plant were added during the Fukushima event. Those results are reported in Table 10-4.

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

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

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

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

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

-42,--43, -TC Vegetation E-01, -02, -03, -04, -06, Gross Beta 3x/yr as available

-08, -09, -20, Gamma Isotopic Analysis Algae E-05, -12 Gross Beta 3xIyr as available Gamma lsotopic Analysis Fish E-13 Gross Beta 3xlyr as available Gamma lsotopic Analysis (Analysis of edible portions only)

Well Water E-10 Gross Beta, H-3 Quarterly Sr-89, 90, 1-131 Gamma lsotopic Analysis Lake Water E-01, -05, -06, -33 Gross Beta, Sr-89/90, H-3 Monthly / Quarterly composite of monthly collections 1-131 Monthly Gamma lsotopic Analysis Monthly Milk E-11, -40, -21 Sr-89, 90 Monthly 1-131 Gamma lsotopic Analysis Air Filters E-01, -02, -03, -04, Gross Beta Weekly (particulate)

-08, -20 1-131 Weekly (charcoal)

Gamma lsotopic Analysis Quarterly (on composite particulate filters)

Soil E-01, -02, -03, -04, Gross Beta 2x/yr

-06, -08, -09, -20, Gamma Isotopic Analysis Shoreline Sediment E-01, -05, -06, -12, -33, Gross Beta 2xIyr Gamma lsotopic Analysis ISFSl Ambient North, East, South, Radiation Exposure West Fence Sections TLD Quarterly

Table 9-2 PBNP REMP Sampling Locations Location Code Location Description E-01 Primary Meteorological Tower South of the Plant E-02 Site Boundary Control Center - East Side of Building E-03 Tapawingo Road, about 0.4 Miles West of Lakeshore Road E-04 North Boundary E-05 Two Creeks Park Point Beach State Park - Coast Guard Station; TLD located South of the Lighthouse on E-06 Telephone pole E-07 WPSC Substation on County V, about 0.5 Miles West of Hwy 42 E-08 G.J. Francar Property at Southeast Corner of the Intersection of Cty. B and Zander Road E-09 Nature Conservancy E-10 PBNP Site Well E-I I Dairy Farm about 3.75 Miles West of Site E-12 Discharge FlumeIPier E-13 Pumphouse E-14 South Boundary, about 0.2 miles East of Site Boundary Control Center E-15 Southwest Corner of Site E-16 WSW, Hwy 42, a residence about 0.25 miles North of Nuclear Road E-I 7 North of Mishicot, Cty. B and Assman Road, Northeast Corner of Intersection E-I 8 Northwest of Two Creeks at Zander and Tannery Roads E-20 Reference Location, 17 miles Southwest, at Silver Lake College E-21 Local Dairy Farm just South of Site on Lakeshore and Irish Roads E-22 West Side of Hwy 42, about 0.25 miles North of Johanek Road E-23 Greenfield Lane, about 4.5 Miles South of Site, 0.5 Miles East of Hwy 42 E-24 North Side of County Rt. V, near intersection of Saxonburg Road E-25 South Side of County Rt. BB, about 0.5 miles West of Norman Road E-26 804 Tapawingo Road, about 0.4 miles East of Cty. B, North Side of Road E-27 Intersection of Saxonburg and Nuclear Roads, Southwest Corner, about 4 Miles WSW E-28 TLD site on western most pole between the 2" and 3rdparking lots.

E-29 Area of North Meteorological Tower.

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

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

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

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

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

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

E-40 Local Dairy Farm, W side of Hwy 42, about 1.8 miles north of the Nuclear Rd intersection E-41 NW corner of Woodside and Nuclear Rds (Kewaunee County)

E-42 NW corner of Church and Division, East of Mishicot E-43 West side of Tannery Rd south of Elmwood (7th pole south of Elmwood)

E-TC Transportation Control; Reserved for TLDs

FIGURE 2-10 MON l TOR lNG PROGRAM S l TES KILOMETER Figure 9-1 PBNP REMP Sampling Sites

F I W E 2-lb SITE MAP POINT BEACH NUCLEAR PLANT 22 r..".~..".~..-..-..

0 E

TLD @ TLD L A I R A A OTHER cm ~ I L E10~48 Figure 9-2 Map of REMP Sampling Sites Located Around PBNP

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

Table 9-3 ISFSl Sampling Sites Ambient Radiation Monitoring (TLD) Soil, Vegetation and Airborne Monitoring E-03 E-02 E-28 E-03 E-29 E-04 E-30 E-31 E-32 Table 9-4 Minimum Acceptable Sample Size

Table 9-5 Deviations from Scheduled Sampling and Frequency Sample Location Collection Reason for not conducting REMP Plans for Preventing Recurrence Type Date as required APIA1 E-04 3110111 Power loss In all three cases the power was lost to the sampler E-03 512411 1 Power loss to sampler resulting in a low volume. Hence each sample was E-03 6130/11 Power loss to sampler considered t o lost.

TLDs E-42 07/07/11 TLD missing in the field All three losseswere beyond program control asthe E-15 10/07/11 TLD missing in the field poles to which the TLDs were attached were changed E-31 10/07/11 TLD missing in the field out. The TLD was removed with the pole. In one instance the cage containing the TLD was found the next quarter but the data was not used.

Table 9-6 Sample Collections for State of Wisconsin

9.6 Analvtical 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 201 1.

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, Zr-95, Nb-95, Ru-103, Ru-106, 1-131, Ba-La-140, Cs-134, Cs-137, Ce-141, and Ce-144. However, other detected nuclear power plant produced radionuclides also are noted. The above radionuclides detected by gamma isotopic analysisare 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-I 34 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 1-131 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.

No special vegetation samples were obtained for C-14 analyses in 201 1.

9.7.6 Environmental Radiation Exposure The 201 1 environmental radiation exposure measurements were made using TLD cards. The TLD card is a small passive detector, which integrates radiation exposure. Each TLD consists of a Teflon sheet coated with a crystalline, phosphorus material (calcium sulfate containing dysprosium) which absorbs the gamma ray energy deposited in them.

Each TLD is read in four distinct areas to yield four exposure values which are averaged. Prior to the third quarter of 2001, exposure data was obtained using three lithium fluoride (LiF) TLD chips sealed in black plastic. The difference in material types can impact the amount of exposure measured. A comparison of the first quarters to the last two quarters in 2001, shows that the TLD cards typically produce a higher measured exposure value than the LiF chips (Table 9-7).

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

As seen in Table 9-7, the change from LiF chips to TLD cards resulted in an average readout of 14%. If only the positive changes are compared, the increase is 17%. The largest increase was at Site E-38, a location near the former retention pond prior to completion of its remediation.

Table 9-7 Comparison of 2001 TLDs: LiF Chips vs. TLD Cards LiF Chips TLD Cards AVG Percent Site Q1 Q2 AVG Q3 Q4 AVG A Change E-01 0.96 0.98 0.97 0.99 1.15 1.07 0.10 10.46 E-02 1.12 1.12 1.12 1.28 1.43 1.35 0.23 20.79

• E-03 1.00 0.98 0.99 1.76 1.51 1.64 0.65 65.34 E-04 0.99 0.99 0.99 1.35 1.08 1.21 0.22 22.65 E-05 0.97 0.92 0.94 1.29 1.21 1.25 0.31 32.79 E-06 0.93 1.01 0.97 1.18 0.89 1.03 0.06 6.45 E-07 0.95 0.94 0.94 1.04 0.85 0.95 0.00 0.25 E-08 0.89 0.88 0.88 1.03 1.02 1.03 0.14 16.28 E-09 0.99 0.99 0.99 1.27 1.07 1.17 0.18 18.08 E-12 0.93 1.0 0.97 0.95 0.77 0.86 -0.11 -11.09 E-14 1.1 1.09 1.1 1.17 1.06 1.11 0.02 1.73 E-15 1.23 1.26 1.25 1.24 1.36 1.30 0.05 4.30 E-16 0.97 0.97 0.97 1.09 1.01 1.05 0.08 8.70 E-17 0.90 0.86 0.88 1.21 1.07 1.14 0.26 29.68 E-18 1.25 1.26 1.26 1.41 1.20 1.30 0.05 3.82 E-22 1.03 0.98 1.01 1.29 1.14 1.21 0.21 20.37 E-23 1.14 1.14 1.14 1.36 1.19 1.27 0.14 11.95 E-24 0.98 0.95 0.97 1.34 1.13 1.23 0.27 27.62 E-25 1.04 1.02 1.03 1.19 1.12 1.15 0.12 11.63 E-26 0.88 0.88 0.88 1.05 0.86 0.96 0.08 8.97 E-27 1.01 1.02 1.01 1.15 1.05 1.10 0.08 8.31 Statistics for all values Avg A = 0.14 14.46 =Avg.A%

Statistics for all + increases Avg +A = 0.17 17.45 = AVg. +A %

Statistics for selected TLD sites Avg A % non-ISFSI TLDs 14.83 Avg A % ISFSl TLDs 13.93 ISFSl sites Avg A % ISFSl TLDs wlo E-03 13.87 The next highest increase, 65%, occurred at E-03, the site nearest the dry cask storage modules at the ISFSI. Two of the five TLD sites used to monitor the ISFSl saw a reduction. The increase at E-31 at the site boundary is comparable to the average of all non-ISFSI increases.

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 40.1 Summarv of 201 1 REMP Results Radiological environmental monitoring conducted at PBNP from January 1, 201 1, through December 31, 201 1, consisted of analysis of air filters, milk, lake water, well water, soil, fish, shoreline sediments, algae, and vegetation as well as TLDs. The results are summarized in Table 10-1.

Table 10-1 contains the following information:

Sample: Type of the sample medium

Description:

Type of measurement LLD: a priori lower limit of detection N: Number of samples analyzed Average: +

Average value the standard deviation of N samples High: +

Highest measured value it's associated 2 sigma counting error Units: Units of measurement For certain analyses, a LLD, which is lower than 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 Interlaboratory 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 a 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 (1980),

"Upgrading Environmental Radiation Data" released as document EPA 52011-80-012 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-1576, "Multi-Agency Radiological Laboratory Analytical Protocols Manual."

Table 10-2 contains the ISFSl fence TLD results.

Japanese Fukushima Daiichi Event On March 1I , 201 1, an underwater earthquake occurred off the shore of Japan and the resulting tsunami caused extensive damage to the Fukushima Daiichi nuclear plant. The prevailing global wind patterns transported the radioactive material released from this plant across the Pacific Ocean where it soon was detected along the west coast of the United States. Soon afterward this radioactivity was detected by the PBNP radiological environmental monitoring program (REMP) and by other REMPs across the country. As a result of this event, additional PBNP REMP samples obtained and analyses were made. The following is a description of the actions taken and the results obtained.

The first indication of activity from Fukushima occurred as 1-131 collected on charcoal cartridges for the time period of March 16 to March 24,201 1. There was no definitive indication on the individual air particulate filters (APs) analyzed by gross beta counting. With the finding of 1-131, the weekly APs were composited and gamma scanned. In addition to the 6 REMP air sampling sites, additional air samplers were set up at Warehouse 1 and the ISFSI. Also, precipitation samples were collected on March 22, 25, and April 6, 19, and 21,201 1.

Fukushima results are shown in the various tables. The results of individual gross beta and 1-131 analyses from the six air sampling sites are shown in Table 10-3. Results of individual samples close to the site are shown in Table 10-4. In order to enhance the ability to see airborne particulate activity, each week's six air particulate samples were composited and gamma scanned (Table 10-5). Finally, precipitation samples collected from rain events from March 22 to April 21, 201 1 were analyzed (Table 10-6).

Table 10-1 Summary of Radiological Environmental Monitoring Results for 2011 Ce60 6 0.25 0.051 + 0.114 0.284 ? 0.043 p cilg CS-134 6 0.2 5 0.001

• 0.012 0.016 + 0.013 pcilg CS-137 6 0.25 0.019 2 0.013 0.042 + 0.019 pcilg (a) When two LLD values are listed, the required LLD per the PBNP REMP is enclosed in the parentheses. Whenever possible, PBNP uses the lower value to obtain greater sensitivity.

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

Table 10-1 (continued)

Summary of Radiological Environmental Monitoring Results for 2011 Average k I Std.

Sample Description N LLD (a) Deviation (b) High f 2 sigma Units Lake Wafer Gross beta 48 4 2.1 + 1.8 11.3 + 1.2 pCilL 1-131 48 0.5 (2) ND PCi1L Mn-54 48 lO(15) ND pCilL Fe-59 48 30 +

-0.2 2.0 5.7 + 5.4 pCilL CO-58 48 1O(15) +

0.1 1.0 2.5 + 1.6 PCilL Co-60 48 1O(15) +

-0.1 1.1 2.3 + 1.6 pCilL Zn-65 48 30 +

-0.5 2.0 3.9 + 2.9 pCi1L Zr-Nb-95 48 15 -0.5 + 1.4 2.1 + 1.6 pCi1L Cs-134 48 lO(15) ND pCi/L Cs-137 48 lO(18) +

0.3 1.2 2.5 + 2.4 pCi/L Ba-La-140 48 I5 +

-0.2 1.7 3.9 + 2.5 pCi/L Ru-103 (Other gamma) 48 30 +

-0.3 1.1 2.5 + 1.5 pCi/L Sr-89 16 5( 10) ND pCilL Sr-90 16 1 (2) +

0.25 0.15 0.53 + 0.38 pCilL H-3 16 200 (3000) +

1503 5496 22096 + 449 PCilL (a) When two LLD values are listed, the required LLD per the PBNP REMP is enclosed in the parentheses. Whenever possible, PBNP uses the lower value to obtain greater sensitivity.

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

Other gamma emitters typically refer to '20-60 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 ISFSl Fence TLD Results for 2011 Fence Location Average f Standard Deviation Units North 2.44

• 0.1 mW7 days East 2.62 f 0.46 mW7 days South 1.31

• 0.1 mW7 days West 4.75 + 0.5 mW7 days Table 10-3 Fukushima Gross Beta and Charcoal Cartridge Results E-01 E-02 E-03 Particulate Charcoal Particulate Charcoal Particulate Charcoal Date Gross p 1-131 Gross p 1-131 Gross p 1-131 03-16-11 0.024 f 0.003 < 0.016 0.024 f 0.003 < 0.015 0.022 f 0.003 < 0.017 03-24-11 03-30-11 04-06-11 04-13-11 04-20-11 Table 10-4 Additional Fukushima 1-131 Results Warehouse 1 Warehouse 1 ISFSl ISFSl Date Air articulate Charcoal Air articulate Charcoal

- No sample

Table 10-5 Gamma Scan of Weekly Airborne Composite Samples.

March 16 March 24 30-Mar 1-131 ND 0.0245 + 0.0034 0.0399 + 0.0038 CS-I34 ND 0.0007a 0.0006 ND CS-137 ND 0.0010 + 0.0007 ND April 6 April 13 April 20 1-131 0.0238+ 0.0028 0.0057+ 0.0033 0.0076 + 0.0007 CS-I 34 0.0017 k 0.0008 0.0019 + 0.0010 0.0037 a 0.0012 CS-I37 0.0026 + 0.0014 0.0020 + 0.0012 0.0038 + 0.0016 April 27 May 4 1-131 ND 0.0008+ 0.0006 CS-134 0.0010+ 0.0009 ND CS-I37 0.0014a 0.0010 0.0010 + 0.0007 ND Sample result is below the minimum detectable concentration Table 10-6 Precipitation Results South, West, and North of Point Beach Fukushima Precipitation Samples (pCill)

E-02 (S) E-03 (W) E-04 (N)

March 22 1-131 11.7 + 3.8 10.4 + 3.6 14.1 + 5.1 CS-I37 ND ND ND Sr-90 ND ND 0.9 k 0.7 March 25 1-131 +

24.4 4.9 18.3 + 4.8 33.1 + 4.7 CS-I37 1.8k 1.8 ND ND Sr-90 ND ND ND April 6 1-131 12.6k 1.6 13.6 + 1.5 10.8 k 1.5 CS-I37 ND ND ND Sr-90 ND ND ND April 19 1-131 1.00k0.18 1.23 a 0.19 0.86 k 0.27 CS-137 ND ND ND Sr-90 ND ND ND April 21 1-131 0.10 + 0.22 +

0.05 0.53 1.23 + 0.30 April 19 and 21, 1-131 by beta counting after column extraction March 22 - April 6, 1-131 by gamma scan ND = not detected

11.0 DISCUSSION 11.1 TLD Cards The ambient radiation was measured in the general area of the site boundary, at an outer ring four -five miles from the plant, at special interest areas, and at one control location, roughly 17 miles southwest of the plant. The average indicator

+ +

TLD cards is 1. I 4 0.50 mRl7 days and 1.I5 0.08 mRl7 days at the background location. These two values are not significantly different from each other. Neither are the indicator TLD values significantly different from those observed from 2001 through 2011 (tabulated below in Table 11-1) from 2000 to 2001. 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).

Table 11-1 Average Indicator TLD Results from 1993 - 2011

• St. Dev = Standard Deviation There were no new dry fuel storage cask additions to the ISFSI in 2011. No new storage casks have been added since 2009 when 5 horizontal storage modules were loaded on the east pad. The west fence TLDs continue to record higher

+

exposures. The north and east fence TLDs are statistically equal (2.44 0.1 1 vs.

+

2.62 0.46). The south fence continues to record the lowest exposures (Table 11-2).

Table 11-2 Average ISFSl Fence TLD Results (mRl7 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, 1.25 k 0.31; E-32, 1.32 0.23) are comparable to the background site E-20 (1.1 1 + 0.19) within the associated measurement error, indicating no measurable increase in ambient gamma radiation at the site boundary due to the operation of the ISFSI.

Further data supporting this conclusion is the comparison of the TLD results at selected locations around the ISFSl before and after the storage of spent fuel at the ISFSl (Figure 11-1). As discussed in Section 9.7.6, the TLD values increased in the second half of 2001 when the TLD monitoring devices were changed from LiF chips in the first half of the year to calcium sulfate impregnated TLD cards beginning at the second half of the year. After that initial change, the radiation exposure as measured by the TLD cards has remained fairly constant even with the addition of stored fuel at the ISFSI. The results from E-30 continue to be lower than the results from E-31 even though E-30 is closer to the ISFSl than E-31. Each year the variations in the TLD results appear to move in concert with each other and with the background site, E-20, which is 17 miles south west of the ISFSI.

Therefore, the TLD monitoring results indicate that there is little or not effect on the ambient gamma radiation from the operation of the plant. Data supporting

this conclusion is the comparison of TLD results for the first half of 2001 with the last half of 2001. As previously mentioned, for the last two quarters of 2001, the LiF TLD chips were replaced with calcium sulfate impregnated Teflon TLD cards which resulted in a higher reported background exposure (Figure 11-1).

Figure 11-1 ISFSl AREA TLD RESULTS 1.6 1.4 1.2 E-28 U) m 1 k

0.8 x E-30 2 0.6 x E-31 0.4 E-32 0.2 0

1990 1995 2000 2005 2010 2015 YEAR Table 11-3 Average TLD Results Surrounding the ISFSl (mR17 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 70 pCill) continues to be the most prevalent radionuclide measured in milk at concentrations roughly 1800 times

+

higher than the only potential plant related radionuclide, Sr-90 (0.8 0.8 pCi/l),

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, 1-131, Cs-1341137, Ba-La-140, and Co-60 were detected.

Though similar to previous years, the Strontium-90 results show a logarithmic decrease over time (Figure 11-2). The environmental half-life of Sr-90 calculated using the annual average Sr-90 concentration in milk between 1997 and 201 1 is 23.9 years. Because the radiological half-life is 28 years, the shorter environmental half-life indicates that environmental factors as well as radioactive decay are working to decrease the concentration of Sr-90 in milk. The calculated physical removal half-life is 147 years. This indicates that the radiological half-life dominates the decrease of Sr-90 in the milk samples obtained around PBNP.

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 201 1 show no radiological effects of the plant operation.

Figure 11-2 Sr-90 Concentration in Milk Sr-90 in Milk Year The average annual gross beta concentrations (pluslminus the two-sigma uncertainty) in weekly airborne particulates at the indicator and control locations

+

were 0.026 0.01 8 pci/m3 and 0.026 + 0.01 8 pci/m3, respectively, and are similar to levels observed from 1993 through 2010 (Table 11-4).

Table 11-4 Average Gross Beta Measurements in Air 0.022 0.022 The 201 1 weekly gross beta concentrations reveal higher winter values and lower summer values (Figure 11-3). This is a repeat of the patterns seen in 2006 - 2010. Again, as in previous years, another high period occurs during July-September. The cause for this scatter is not known but, may be due to a shift in land use or weather patterns. Also shown in Figure 11-3 is a slight increase in gross beta results beginning in March attributable to the Fukushima event. This small increase more perceptible when all the data are plotted as compared to merely looking at the tabulated, monthly results.

Figure 11-3 201 1 Airborne Gross Beta (pCilmA3)vs. Time 11-18-10 02-26-11 06-06-11 09-14-1 1 12-23-11 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 0.005 to 0.020 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 0.003 pcilm3.

1-131 was detected at all six REMP air sampling sites in weekly REMP samples and in the special samples obtained closer to the plant (Tables 10-3 through 10-6) beginning with the week of March 16 to March 24, 2011 and ending with the sample for the week of April 6 to April 13, 2011. 1-131 appeared in both the particulate phase (particulate filters) and on the charcoal canisters (the gas or vapor phase). Comparing all of the measured 1-131 concentrations indicates a uniform distribution over an area as far as 17 miles from the plant. PBNP released 1-131 at a concentration of 5.6E-14 ~ C i l c c(0.056 pci/m3) during the week of March 21, to March 28, 2011. This release concentration is lower that the particulate+gas/vapor phase concentrations seen in the REMP and special airborne samples obtained during this period. Because the 1-131 concentrations found in the PBNP REMP and special samples are higher than that released by PBNP, the 1-131 found by monitoring is attributable to the Fukushima event and not to the small amount of 1-131 PBNP released during the one week in March.

Therefore, it is concluded that the release of the small amount of radioiodine by PBNP during the week of March 21 to March 28,201 1 had no measurable impact on the environment.

At each airborne REMP monitoring site the weekly air particulate filters are composited quarterly for gamma spectroscopic analysis. During the Fukushima event, all the individual, weekly particulate samples were composited for gamma analysis prior to being added to the quarterly composite of each location.

Gamma scans of these weekly particulate filter composites indicates that 1-131 was detectable in particulate samples at the same time it was detected in the analyses of individual charcoal canisters.

The detection of particulate 1-131 occurs two weeks prior to the detection of either Cs-134 or Cs-137 and at higher concentrations (Table 10-5). All three continued to be easily detectable on particulate filters during the first three weeks of April until the week ending April 20, 201 1. Because the only PBNP 1-131 release prior to the first detection on particulate filters and charcoal canisters occurred in the week ending January 17, 201 1, the 1-131 is not attributable to PBNP because the PBNP 1-131 would have decayed to below detectable levels by March 24, 2011. Similarly, PBNP had no Cs-134 or Cs-137 emissions during January to May of 201 1. Therefore, the detected Cs-134 and Cs-I 37 could not be from PBNP. This is a further evidence that the radionuclides detected in PBNP airborne samples could not be attributable to the operation of PBNP.

In summary, the 201 1 air data does not demonstrate an environmental impact from the operation of PBNP.

1I.4 Lake Water For the REMP-specified gamma emitting radionuclides listed in Table 10-1, reported concentrations continue to occur as small, negative and positive values scattered around zero, indicating no radiological impact from the operation of PBNP. Lake Michigan water samples are collected north (E-33 and E-05) and south (E-01 and E-06) of PBNP (see Figure 9-1).

There were nineteen, slightly positive indications of gamma emitters during 201 1.

None of the concentrations were equal or greater than the MDC. Twelve positive results occurred at the two locations 1.5 and 4.5 miles north of the plant. These locations are considered to be upstream based on the north to south current flow on the west shore of Lake Michigan and therefore are very unlikely to be an indication of PBNP effluent. Of the remaining seven occurrences, four are for radionuclides not discharged the months they had a positive indication in Lake Michigan (Ru-103 in January; Fe-59, Cs-137, and BaILa-140 in August). The remaining three positives are for Co-60 in January, Co-58 in May and

+

September. In each case, the highest measured concentration, 2.5 1.6 pCi/l is higher than the corresponding discharge concentration of 0.00067 pCill.

Because the positive concentrations measured in the lake are higher than the discharge concentrations and because any discharges would be further diluted by mixing in the lake, the observed positive concentrations are considered to be false positives. Therefore, based on the results of the gamma scans of Lake Michigan water, there is no measureable impact on the lake from PBNP discharges.

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

There were six samples in which Sr-90 concentrations were slightly positive but below the MDC. Because PBNP did not discharged Sr-90 during 201 1, these results are considered to be either false positives or the indication of persisting low levels of Sr-90 in the lake which resulted from fallout from atmospheric weapons testing in the1950s and 1960s.

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 201 1, ranged from less than MDC to 22,096 pCi/l. This high occurred in the first quarter. Tritium analyses of the individual months in this quarter indicated that the March Lake Michigan sample had a tritium concentration of 64,741 pCi/l. This sampling location is locate 4.5 miles north of PBNP near another nuclear facility and is considered to be up-current from PBNP based on the currents on the west side of Lake Michigan.

It is concluded that the PBNP sample was obtained sometime after a H-3 discharge from that facility. The only other quarterly H-3 result above its MDC occurred in the first quarter from a location approximately 0.7 miles south of the PBNP discharge. Analyses of the individual months indicates that elevated H-3 concentration resulted from the January 13, 201 1 sample which had a 2709 pCill tritium concentration. A review of liquid discharge permits revealed that a waste tank containing H-3 was discharged that day. Therefore, is concluded that the measured concentration resulted from sampling either during or shortly after the

discharge which occurred on January 13, 201 1. The measured concentration is at about 10% of the EPA drinking water limit.

Based on analyses of Lake Michigan water, there is no measureable impact on the waters of Lake Michigan other than that indicated by the elevated H-3 concentration in the January 13, 201 1 sample.

Filamentous algae attached to rocks along the Lake Michigan shoreline are known to concentrate radionuclides from the water. Samples were obtained at Two Creeks Park and at the PBNP discharge (locations 5 and 12 in Figure 9-1) in June, August, and October of 201 1. There was one positive result for Cs-134 and that occurred at location 12 near the PBNP discharge. Because no Cs-134 was detected in any of the PBNP batch releases, this occurrence of Cs-134 is considered to be a false positive indication. Five of the six samples had measureable Cs-137 concentrations which were above the MDC. Three of the positive results were from north of PBNP and therefore are not considered to be related to any PBNP discharges. The only PBNP Cs-137 liquid discharge prior to the October sample occurred in February of 201 1. The June algae sample from the vicinity of the PBNP discharge had no detectable Cs-137 even though it is the sample closest to the PBNP Cs-137 discharge date. The August sample from the same location was the highest of the six samples, 0.042 k 0.019 pCi1g.

These Cs-137 results, like those in the past, are attributable to the recycling of bomb fallout, from weapons testing in the '50% 60's and other nuclear events such as Chernobyl, in the Lake Michigan environment.

PBNP discharged Co-60 and Co-58 every month in 201 1. However, only the June 201 1 sample from the location close to the PBNP discharge had any

+

appreciable Co-58 (0.093 0.044 pCiIg) and Co-60 (0.284 k 0.043 pCilg). In the subsequent samples from this location there is little or no radio-cobalt present.

Similarly, at the site north of PBNP, no Co-58 was detected in any of the three samples. Only two of the three samples had detectable Co-60 concentrations and these concentrations were barely positive (0.010 k 0.007 and 0.007 +

0.003 pcilg).

The Cs-137 and Co-60 results are well below the naturally occurring radionuclides Be-7 and K-40. The concentrations of these two radionuclides range from 0.87 k 0.07 to 2.84 k 0.34 pCiIg for Be-7 and from 0.96 k 0.50 to 4.27 k 0.50 pCi/g for K-40.

Based on the low concentrations of radio-cobalt and radio-cesium, the algae monitoring results indicate little to no effect by PBNP upon the environs.

All six fish samples were positive for Cs-I 37 with results greater than the MDC.

+

The average Cs-137 concentration was 0.043 0.060 pCi/g with a high of

+

0.103 0.021 pCi/g (Table 10-1). The other Cs-137 concentrations ranged from

+ +

0.024 0.014 to 0.040 0.014 pCi/g. Of the other radionuclides specifically looked for in fish, only Fe-59 and Co-58 had any (5) positive values different from

+

zero. Only one of these five values, Fe-59 at 0.033 0.01 7 pCi/g, was above its MDC of 0.023 pCi/g. No Co-60, Zn-65, Mn-54, or Cs-134 was detected in any of the fish. Because no Co-60 was found, even though both Co-58 and Co-60 were discharged in 201 1 and because none of the Co-58 results were greater than its MDC, it is likely that the two positive occurrences of Co-58 are false positives.

By comparison to the aforementioned radionuclides, the concentration of naturally occurring K-40 (2.1 7- 3.04 pCi/g) is about 10 times higher than the highest Cs-137 concentration.

Based on these results, it is concluded that there is no to little indication of plant effluents in fish.

11.7 Well Water No plant related radionuclides were detected in well water during 201 1, 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, and1970s 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-I 37 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 201 1

+

samples had low levels of Cs-I 37 with the highest level (0.42 0.04 pCi/g) being found at E-06. The results from the indicator sites, except for E-06, are

+

comparable to those from the concentration (0.23 0.03 pCi/g) at the background site some 17 miles away in the low N/Q sector. This is expected for the source of Cs-137 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 well below levels of

+

naturally occurring K-40 (5.74 0.39 to 23.33 _+ 1.52 pCi/g).

11.9 Shoreline Sediment Shoreline sediment consists of sand and other sediments washed up on the Lake Michigan shore. As in soil samples, the only non-naturally occurring radionuclide found in these samples is Cs-137. All ten samples have Cs-137 concentrations statistically different from zero. The shoreline sediment Cs-137 concentrations continue to be about one-tenth of that found in soils. This is expected because Cs-137 in the geological media is bound to fine particles, such as clay, as opposed to the sand found on the beach. Lake Michigan sediments are a known reservoir of fallout Cs-137. Wave action suspends lake sediments depositing them on the beach. The fine particles deposited on the beach eventually are winnowed from the beach leaving the heavier sand; hence the lower Cs-137 concentrations in beach samples. In contrast to Cs-137, K-40, which is actually part of the minerals making up the clay and sand, is at a concentration about 300 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. Therefore, the shoreline sediment data indicate no radiological effects from current plant operation.

11.I0 Vesetation 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 atoms 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 1950s and 1960s is now being incorporated into growing plants in the same manner as potassium because it is in the same chemical family as potassium. This fallout Cs-137 has been found in firewood ash at many locations in the United States that are far from any nuclear plants (S. Farber, "Cesium-137 in Wood Ash, Results of a Nationwide Survey," 5th Ann.

Nat. Biofuels Conf., 10/21/1992).

In 201 1 only six of the twenty-four vegetation samples had a positive indication for Cs-I 37 and only one of these (E-02, 0.019 k 0.008, MDC = 0.014 pCi/g) was detected above the MDA. Typically, only the vegetation collected at monitoring site E-06, in the Point Beach State Park south of PBNP, has detectable levels of Cs-137. Of the three samples obtained at this site in 201 1, only one had a positive indication for Cs-137 (0.016 & 0.014 pCi/g) and that value was below its MDC (0.025.pCilg). The highest Cs-137 concentration (0.019 & 0.008 pCi/g) occurred in the sample obtained from the Site Boundary Control Center (E-02),

on May 23, 201 1. However, PBNP did not discharge any airborne effluent containing Cs-137 until the following month. Therefore, it is unlikely that the positive Cs-I 37 value resulted from PBNP releases. For the same reason, the

slightly positive Cs-134 concentration (0.012 + 0.007 pCi/g) which is above its MDC (0.011 pCi/g) also is a false positive.

Only two other radionuclides had positive indications: Co-60 and 1-131. PBNP released small amounts of airborne 1-131 in two of the months preceding vegetation sampling: 1.46 pCi in January and 2.16 pCi in March 201 1. Based on 1-131's 8-day half-life the amount released in March 201 1 would have decayed to approximately 0.7% of its original amount by the time the May 23,201 1 sample was taken. The amount released in January 201 1 would have decay substantially more. Therefore, the three samples with a positive indication for 1-131 and below the 1-131 MDC are considered to be false positives. Small amounts of (20-60 were released in March 201 1 (0.47 yCi),

April 201 1 (0.52 yCi), and June 201 1 (0.08 yCi) prior to collecting vegetation samples. Given the dispersion which occurs during atmospheric transport from PBNP to E-02 (about 0.8 miles) and to E-06 (about 5 miles), it is unlikely that these small amounts for Co-60 would be detectable. Therefore, the small, positive Co-60 are considered to be false positives.

Based on the 201 1 vegetation sampling results, it is concluded that there are little or no effect from PBNP effluents.

11.12 Land Use Census In accordance with the requirements of Section 2.5 of the Environmental Manual, a visual verification of animals grazing in the vicinity of the PBNP site boundary was completed in 201 1. No significant change in the use of pasturelands or grazing herds was noted. Therefore, the existing milk-sampling program continues to be acceptable. In addition to visual verification, a land use census was performed to identify the nearest residence, garden >500 ft2, and nearest dairy. The nearest dairy lies in the SSE sector and it is one of the PBNP REMP milk sampling sites. This dairy leases land in the S and SSE sectors at the PBNP site boundary for growing feed corn. Also, the highest x/Q (1.09E-06) and D/Q (6.23E-09) values occur in these sectors. Therefore, dose calculations to the maximum exposed hypothetical individual, assumed to reside at the site boundary in the S sector, continues to be conservative for the purpose of calculating doses via the grass-cow-milk and the other ingestion pathways.

12.0 REMP CONCLUSION Based on the analytical results from the 808 environmental samples, and from 125 sets of TLDs that comprised the PBNP REMP for 201 1 and on the approximately 30 additional air and precipitation samples obtained during the period of March 16 through April 20, 201 1, PBNP effluents had no discernable, permanent effect on the surrounding environs. The 1-131, Cs-137, and Cs-134 detected in air and precipitation samples from March 16 through April 20, 201 1 only occur during the period that Fukushima fallout was present over North America. They did not occur at any other time of the year. Furthermore, the observed concentrations are fairly uniform over a large area which includes the background site over 17 miles from PBNP. This is indicative sampling from a large, uniform air mass and would not be the case if the origin of these radionuclides were a

point source such as PBNP. 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.

Part D GROUNDWATER MONITORING 13.0 PROGRAM DESCRIPTION PBNP monitors groundwater for tritium. During 201 1 the sampling program consisted of beach drains, intermittent stream and bog locations, drinking water wells, f a ~ a d ewells, yard electrical manholes, ground water monitoring wells, and the subsurface drainage (SSD) system sump located in the U-2 faqade.

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 / 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 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 201 1. Access to other parts of the SSD can be obtained vial manholes located in the facades, turbine building, and other locations. The SSD manholes were not sampled in 201 1 because of the two Extended Power Uprate outages.

In the 1990s, two wells were sunk in each unit's f a ~ a d eto monitor the groundwater levels and look for 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.

Figure 13-1 Groundwater Monitoring Locations 14.0 RESULTS AND DISCUSSION 14.1 Streams and Bogs The results from the surface groundwater monitoring associated with the former retention pond are presented in Table 14-1. 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)

Month GW-01(E-01) GW-02 GW-03 GW-17 BOGS MDC Creek Confluence , E. Creek W. Creek STP GW-07 GW-08 Jan NF + NF + NF + NF +

Feb NF + NF + NF + NF +

Mar NF + NF + NF + 422 + 96 146 APr ND + 322 + 97 179 + 91 393 + 100 166 May ND + 130 + 80 ND + 132 + 80 160 + 84 331 + 92 140 Jun ND + 217 + 89 ND + 184 + 88 149 Jul ND + ND + ND + ND + 171 Aug ND + ND + ND + ND + 150 SeP ND + 156 + 80 ND + ND + 144 Oct 191 + 84 185 + 84 ND + 251 + 87 142 Nov ND + 214 + 95 ND + 269 + 97 162 Dec ND + 259 + 88 ND + ND + 144 NF = no flow: 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.

Only one of the samples from the confluence of the two creeks (GW-OI), ESE of the former retention pond, and only one from the West (GW-03) have measureable levels of H-3. In contrast, at least six samples from the East Creek (G-02) (southeast of the former retention pond) and from GW-17, (directly east of the former retention pond) have results above the MDC. [Note that site GW-17 is at the north, upstream end of the east intermittent creek.] The bog (GW-08) SE of the former retention pond is higher than the bog at GW-07 north of the former retention pond. These results are in conformance with the west to east groundwater flow described in the Site Conceptual Model and the FSAR. The East Creek concentrations are generally lower than the 300 - 350 pCi/l seen in the late 1990s before the retention pond remediation. Likewise, 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 201 1 results for the beach drains are presented in Table 14-2. [The drain data from left to right in the table are in the order of the drains from north to south.] S-I collects yard drainage from the north part of the site yard; S-3, from the south part of the site yard. Note that S-I no longer receives the output from the SSD sump located in the Unit 2 fa~ade.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 Iis not connected to any yard drain system and mainly carries groundwater flow and runoff from a small lawn area south of the plant.

Table 14-2 2011 Beach Drain Tritium The concentration profiles for S-I and S-3 are similar (Figure 14-1). Both peak in February and March and then are fairly constant after the March maximum with the concentrations at S-3 being higher at S-I. The February-March tritium peaks Figure 14-1 201 1 H-3 Concentrations for S-I and S-3 Tritium Concentrations (pCi1l) 2500 2000 S 1500 0, 1000 500 0

1/, + G7 + 9/, 7%

Date

also occurred in 2010. At that time is was believed that the S-I peak to be caused by the discharge of the subsurface drainage system (SSD) into the yard drain emptying into Lake Michigan at S-I. While that may have been a contributing factor, it did not explain the concurrence with the S-3 peak. Based on the completed H-3 washout/recapture study, it now is concluded that recapture of airborne H-3 discharges by snow followed by snow melting is the result of the concurrent, elevated H-3 concentrations found at S-I and S-3.

During February and March snow was melted on site and discharged via the yard drains. The reason for the higher H-3 concentrations at S-3 for the remainder of the year also may be related to washout and recapture. The washout study results will be discussed in more detail later in this section.

The SSD sump is located in the Unit 2 faqade and its contents are discharged via the wastewater effluent line. The monthly averages are presented in Table 14-3.

These H-3 concentrations appear to be slowly decreasing over the year (Figure 14-2).

Table 14-3 2011 Unit 2 Facade SSD Sump Monthly Average H-3 (pCi1l)

Month Avg 20 Jan 572 + 198 Feb 650 + 109 Mar 559 + 138 APr 576 + 157 May 584 + 199 Jun 448 + 358 Jul 695 + 222 Aug 460 + 114 SeP 561 + 102 Oct 519 + 174 Nov 437 + 193 Dec 437 + 98 Figure 14-2 2011 H-3 Concentrations SSD SUMP Tritium Concentrations (pCi1l) 1000

-0, 800 CI 600 2

C 400 al g 200 0

0 11-18-10 02-26-11 06-06-11 09-14-1 1 12-23-11 04-01-12 Date

14.3 Electrical Vaults and Other Manholes Manholes for access to below ground electrical facilities are susceptible to groundwater in-leakage. The manholes east side of the plant, between the Turbine building and Lake Michigan have low H-3 concentrations (Table 14-4).

These manholes Z-066A and Z-067A through Z-066D AND Z-067D run in parallel in the NE section of the yard beginning just north of the Unit 2 truck bay and run from the Unit 2 truck bay north to the Emergency Diesel Generator (EDG) building. 2-068 is located just west of the EDG building. Based on being side-by-side, it is not unexpected that the each pair of manholes 66A/67A, etc.

would have similar H-3 concentrations. Note the highest concentrations occur near the time that beach drains S-I and S-2 also have their highest H-3 concentration.

Table 14-4 2011 East Yard Area Manhole Tritium (pCiIl)

I MH 1 4/5/2011 1 912812011 1 12/2/2011 Z-067A 160 + 84 90 + 91 117 + 82 Z-066B 711 k 108 108 + 92 NS +

Z-067B 456 + 97 90 + 91 NS +

Z-066C 242 + 88 62 + 80 NS +

Z-067C 287 + 90 62 + 90 NS +

Z-066D 485 + 99 288 + 100 NS +

Z-067D NS + 280 + 99 NS k 2-068 454 + 97 199 + 82 253 + 88 MDC 145 166 144 INS = not sampled 14.4 Facade Wells The four fa~adewells monitor the H-3 concentration under the plant footprint (Table 14-5). Each unit's fa~adehas two wells used to monitor the Ta ~le14-5 2011 Facade Well Water UNIT 1 Month 12-361A 12-3618 Jan NS + NS +

Feb 372 + 93 224 + 86 Mar 248 + 87 ND +

Apr 373 I?- 92 164 I?- 83 May 227 + 93 136 + 89 Jun 228 + 87 ND +

Jul 246 + 99 ND +

Aug 172 + 94 ND +

Sep NS + NS +

Oct 262 + 97 ND +

Nov If8 + 85 NU +

Dec NS + NS +

ND = not detected I S = sample not collected

groundwater for conditions that could impact containment integrity. Samples from these wells also are analyzed for H-3 (Table 14-5). In Unit 2 there is one well on each side of containment, approximately 180" apart. The Unit 1 f a ~ a d e wells are east of the containment in the SE (12-361A) and NE (12-3618) corners of the fa~ade.Some samples could not be collected because the well cap could not be removed.

The 201 1 results are similar to those obtained in previous years. The Unit 1 wells continue to have higher H-3 concentrations than the U2 wells with 12-361A, in the SE corner of the Unit 1 fa~ade,having the highest H-3 concentrations.

The 201 1 high is lower that the tritium concentrations of 1169 - 1331 pCi/l seen in 2007 and 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. Damage to the monitoring well casings was repaired in 201 1. The potable water wells have no detectable H-3 (Table 14-6).

Table 14-6 2011 Potable Well Water Tritium Concentration (pCill)

Warehouse SBCC EIC WELL 6 Well Well EIC GW-05,OE

-Month Jan ND GW-04 ND GW-05 ND GW-06 MD(

138 MDC 138 Feb ND 152 Mar ND 146 Apr ND ND ND 166 142 May ND 140 Jun ND 149 Jul ND ND ND 171 148 Aug ND 150 Sep ND 144 Oct ND ND ND 142 145 Nov ND 162 Dec ND ND lot Detected NS=No Sarn~

-144

The two monitoring wells showing consistent, detectable H-3 (GW-15, GW-16) are in the flow path from the retention pond area to the lake (Table 14-7). The highest H-3 concentrations occur at GW-15, the well closest to the former retention pond.

Table 14-7 2011 Monitoring Wells Tritium Concentration (pCi1l)

During 2010 and 201 1, PBNP analyzed numerous precipitation samples to determine whether the washout/recapture of airborne effluent H-3 could contribute to the H-3 concentrations found onsite in manholes and the beach drain samples. Because the H-3 concentrations in precipitation samples obtained at the North, West, and South boundaries were expected to be low, these samples were analyzed at a lab that has a H-3 MDC of 6 Tritium Units or 19.3 pCi/l (1 TU = 3.221 pCi/). This value is roughly one-tenth of the LLD of 200 pCi/l obtained by the lab used for the REMP tritium analysis.

The H-3 concentrations at the site boundaries in 201 1 (Table 14-8) are similar to those observed during 2010 with the highest concentration at roughly 120 pCi/l.

In 201 1, as in 2010, the highest H-3 concentration in precipitation occurred at the south boundary, site E-02. Although there is one occurrence of a H-3 concentration greater than 100 pCi/l at both the south (E-02) and north (E-03) boundaries, most results do not indicate significant concentrations H-3 at the site boundary.

In next phase of the investigation, twelve sampling sites were established to ascertain the recapture concentrations at locations closer to Units 1 and 2 (Figure14-3)

Table 14-8 2011 Precipitation H-3 at Boundary Locations I

12-Decl 47.7 I ND I 22.9 MDC = 19.3 pCill ND = CMDC 20 = 51.5 The northern-most site (3) is about 1400 feet NW of Unit 2; the southern-most site (12), about 1400 feet SSE of Unit 1. Sites 1, 2, and 4-7 are in areas where yard drains run-off is expected to discharge via the beach drains. Precipitation from sites 9 -1 1 will discharge to Lake Michigan via the East Creek. Precipitation site 12 is close to the monitoring well GW-1 I.Precipitation at site 3 will not impact any of the groundwater monitoring locations.

By comparison to the H-3 concentrations of 1000 and 5000 pCill in AC condensate obtained close to the plant, the 2010 H-3 concentrations in the precipitation from sites 1-12 were low. However, the 201 1 precipitation samples from these same sites had H-3 concentrations up to 2200 pCi/l (Table 14-9). The highest concentrations of 800 - 2200 pCi1l are more in line with the AC condensate results from 2010.

Precipitation constitutes the main source of water for samples obtained at the beach drains. However, there are additional water sources as evidenced by beach drain flow even many days after a precipitation event. One of these sources is the roof drains that are connected to the yard drains. Because condensate from the AC unit on the roof of the South Service Building is piped to that building's roof drain, the high H-3 concentration found in this liquid is discharged via S-3, the southern most beach drain. This may account for the higher H-3 levels found at S-3 as compared to S-1 (Figure 14-1). Another source

may be groundwater inleakage into the yard drainage system. However, this ias not been verified.

Figure 14-3 Location of Washout/Recapture Sampling Sites Based on the H-3 concentrations observed in rainwater close to the plant, recapture of H-3 in airborne effluents are sufficient to account for the concentrations seen in the beach drains and in the yard manholes.

Table 14-9 2010 and 2011 H-3 Concentrations Close to Plant Date -> 11115/2010 12/6/2010 411 112011 411912011 412012011 Location pCi1l pCi1l pCi1l pCi/l pCill 1 147 313 1670 53.5 60.2 2 148 437 1533 NS 58.3 3 93.4 88.8 609 69.9 38.7 4 401 266 670 287 35.1 5 230 NS ND 2200 2130 6 128 50.9 354 786 82 1 7 115 46.4 302 717 32.9 8 102 31.6 247 514 57 9 216 NS 208 315 180 I0 276 NS 35 1 863 332 11 168 ND ND 24 1 114 12 37.7 NS 170 130 82.8 NS = no sample collected ND = not detected 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 show that airborne H-3 concentrations are higher close to the plant as compared to results at the site boundaries. The observed tritium concentrations in the beach drains can be explained by the higher H-3 in precipitation close to the plant and in the condensate from AC units that are connected to the yard drains. The use of snow melting equipment during February and March may be an important source of the peaking of beach drain H-3 concentrations during those months.

Except for the monitoring wells downstream from the former retention pond, the monitoring well tritium concentrations are not different from zero. The higher H-3 concentrations at beach drain S-3 suggests that it is impacted more that beach drain S-1 by the known inputs of AC condensate and the possible inleakage of groundwater recharged by precipitation. The impact of the flow of tritiated groundwater from the vicinity of the former retention pond toward the lake can not be discounted. The impact of this flow would be greater on beach drain S-3 than on S-1 because the eastward flow in the area of S-3 would be less impacted by plant structures than the drainage system feeding beach drain S-1.

In conclusion, the groundwater H-3 concentrations observed at Point Beach are below the EPA drinking water standards prior to emptying into Lake Michigan where they will undergo further dilution. All analyses to date indicate that the drinking water contains no tritium. None of the H-3 in the upper soil layer is migrating off-site toward the

surrounding population. This is based on the known west-to-east groundwater flow toward Lake Michigan and the negative results from the four wells (GW-11 through GW-14, Figure 13-1). Additionally, because no H-3 is detected in either the three on-site drinking water wells close to the power block or from the drinking water well at the site boundary, none of the H-3 observed in the upper soil layer has penetrated into the drinking water aquifer to endanger either on-site or off-site personnel.

APPENDIX 1 Environmental, Inc. Midwest Laboratory Final Report for the Point Beach Nuclear Plant and Other Analyses Reporting Period: January - December 2011

Environmental, Inc.

Midwest Laboratory 700 Landwehr Road Northbrook. IL 60062-2310 phone (847) 564-0700 fax (847) 564-4517 FINAL REPORT TO NextEra Energy RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

FOR THE POINT BEACH NUCLEAR PLANT TWO RIVERS, WISCONSIN PREPARED AND SUBMITTED BY ENVIRONMENTAL INCORPORATED MIDWEST LABORATORY Project Number: 8006 Reporting Period: January-December, 201 1 Distribution: K. Johansen, Ihardcopy, 1 e-mail

POINT BEACH NUCLEAR PLANT TABLE OF CONTENTS Section List of Tables .......................

iii 1.o INTRODUCTION .....................................................................iv 2.0 LISTING OF MISSED SAMPLES ............................................. v 3 DATA TABLES ........................................................................

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

D-I E Supplemental Analyses ............................................................

E-I

POINT BEACH NUCLEAR PLANT LIST OF TABLES Airborne Particulates and lodine-131 Location E.01. Meteorological Tower .............................................. 1-1 Location E.02. Site Boundary Control Center .................................. 1-2 Location E.03. West Boundary ................... ............................. 1-3 Location E-04, North Boundary ................................................ 1-4 Location E-08. G. J . Francar Residence ....................................... 1-5 Location E-20, Silver Lake College ..................... . . . ................... 1-6 Airborne Particulates. Gamma Isotopic Analyses ...................... . . . ...... 2-1 Milk ...................................................................................................... 3-1 Well Water ............................................................................................. 4-1 Lake Water ........................................................................................... 5-1 Lake Water. Analyses on Quarterly Composites .............................................. 6-1 Fish ...................................................................................................................

7-1 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 201 1 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 APIA1 E-04 03-10-11 Volume estimated @ 295m3; AP result = 0.024t0.003 pci/m3 Al result = <0.009 pci/m3 E-03 05-24-11 Loss of power; volume = 172.4 m3.

AP result = 0.01 1+0.004 pci/m3 Al result = <0.029 pcilm3 APIA1 E-03 06-30-11 Run time=5 hrs.; volume = 9.0 m3.

AP result = 0.005+0.063 pcilm3 Al result = <0.37 pci/m3 TLD E-42 07-07-11 TLD missing in'field.

NOTE: TLD removed 10-07-11; read 10119111.

TLD E-15 10-07-11 TLD missing in field.

TLD E-31 10-07-11 TLD missing in field.

POINT BEACH NUCLEAR PLANT 3.0 Data Tables

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

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

Date Vol. Date Vol.

Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Reauired LLD 0.010 0.030 Required LLD 0.010 0.030 Ist Quarter 3rd Quarter Mean f s.d. 0.029 f 0.006 0.086 Mean f sad. 0.023 + 0.005 < 0.009 2nd Quarter 4th Quarter Mean f s.d. 0.019 f 0.007 0.035 +

Mean s.d. 0.032 f 0.01 1 < 0.009 Cumulative Average 0.026 f 0.008 0.060

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: pcilm3 Collection: Continuous, weekly exchange.

Date Vol. Date Vol.

Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Reauired LLD p.010 0.030 Reauired LLD 0.010 0.030 1st Quarter 3rd Quarter Mean -I s.d. 0.028 f 0.005 0.080 Mean f s.d. 0.023 f 0.004 < 0.010 2nd Quarter 4th Quarter Mean s.d. 0.019 f 0.007 0.061 Mean f s.d. 0.031 f 0.010 < 0.009 Cumulative Average 0.025 + 0.008 0.070

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

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

Date Vol. Date Vol.

Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Reouired LLD 0.010 o.030 Reauired LLD o.010 0.030 1st Quarter 3rd Quarter Mean f s.d. 0.028 + 0.004 0.075 +

Mean s.d. 0.023 f 0.005 < 0.009 2nd Quarter 4th Quarter Mean rt s.d. 0.020 f 0.007 0.065 +

Mean sad. 0.030 f 0.010 < 0.009 Cumulative Average 0.025 It: 0.007 0.070 a"ND" = NOdata; 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: pci/m3 Collection: Continuous, weekly exchange.

Date Vol. Date Vol.

Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Reauired LLD 0.010 0.030 Reauired LLD 0.010 o.030 1st Quarter 3rd Quarter

+

Mean s d . 0.031 f 0.006 0.100 +

Mean s.d. 0.025 + 0.005 < 0.010 2nd Quarter 4th Quarter

+

Mean s.d. 0.018 f 0.007 0.058 Mean ?: s.d. 0.031 f 0.010 < 0.009 Cumulative Average 0.026 f 0.008 0.079 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-08, G.J.Francar Residence Units: pci/m3 Collection: Continuous, weekly exchange.

Date Vol. Date Vol.

Collected (m3) Gross Beta 1-131 Collected (rn3) Gross Beta 1-131 Reauired LLD 0.010 0.030 Required LLD 0.010 o.030 1st Quarter 3rd Quarter Mean 2 s.d. 0.028 f 0.006 0.080 Mean f s.d. 0.024 f 0.004 4 0.010 2nd Quarter 4th Quarter Mean f s.d. 0.020 + 0.007 0.061 Mean +, s.d. 0.030 +, 0.010 < 0.009 Cumulative Average 0.025 2 0.008 0.070 Indicator Locations Annual Mean f s.d. 0.026 i 0.008 0.070

POINT BEACH NUCLEAR PLANT Table 2. Gamma emitters in quarterly composites of air particulate filters Units: pCilm3 (Other) (Other)

Location Lab Code Be-7 Be-7 Cs-134 Cs-134 Cs-137 Cs-137 Co-60 (CO-60) volume Req. LLD MDC 0.01 MDC 0.01 MDC (0.10 ) MDC m3 1st Quarter E-01 EAP- 1880 0.069 f 0.012 - 0.0000 f 0.000 < 0.0007 0.0000 f 0.001 < 0.0008 0.0004 f 0.000 < 0.0005 3902 E-02 - 1881 0.065 f 0.013 - 0.0000 f 0.000 < 0.0004 0.0002 f 0.000 < 0.0005 -0.0001 f 0.000 < 0.0006 3934 E-03 - 1882 0.073 f 0.016 - -0.0008 f 0.001 < 0.0005 -0.0002 f 0.000 < 0.0002 0.0002 f 0.001 < 0.0008 3675 E-04 - 1883 0.071 f 0.015 - 0.0003 f 0.001 < 0.0009 -0.0003 f 0.001 < 0.0003 -0.0006 f 0.001 < 0.0007 3472 E-08 - 1885 0.081 f 0.018 - 0.0004 f 0.000 < 0.0006 0.0001 f 0.001 < 0.0007 0.0003 f 0.001 < 0.0007 3933 E-20 - 1886 0.064 f 0.017 - 0.0001 f 0.001 < 0.0010 0.0000 f 0.001 < 0.0009 0.0008 f 0.001 < 0.0006 3788 2nd Quarter 3rd Quarter E-01 7045 0.064 f 0.016 - 0.0000 f 0.001 < 0.0006 0.0002 f 0.001 < 0.0009 0.0000 f 0.001 < 0.0005 3965 E-02 7046 0.073 f 0.017 - -0.0015 f 0.001 < 0.0010 -0.0003 f 0.001 < 0.0007 0.0000 f 0.001 < 0.0009 3918 E-03 7047 0.062 f 0.012 - -0.0003 f 0.000 < 0.0005 0.0004 f 0.000 < 0.0007 0.0001 f 0.000 < 0.0008 3970 E-04 7048 0.068 f 0.01 1 - -0.0005 f 0.000 < 0.0004 0.0002 f 0.000 < 0.0006 0.0002 f 0.000 < 0.0003 3897 E-08 7049 0.074 f 0.014 - -0.0001 f 0.000 < 0.0007 0.0000 f 0.000 < 0.0006 0.0000 f 0.001 < 0.0007 3936 E-20 7050 0.080 f 0.013 - 0.0004 f 0.000 < 0.0006 0.0003 f 0.000 < 0.0006 -0.0001 f 0.001 < 0.0005 3965 4th Quarter Annual M e a n h d . 0.071 f 0.008 0.0001 f 0.0005 < 0.0007 0.0001 f 0.0003 < 0.0007 0.0001 f 0.0003 c 0.0006

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

E-I ILambert Dairv Farm MDC MDC MDC Required Collection Date 02-09-11 LLD Lab Code EMI- 107 EMI- 535 EMI- 995 K-40 Cs-134 Cs-137 Ba-La-140 Other (Co-60)

MDC MDC MDC Required Collection Date 04-13-11 05-11-11 06-08-11 LLD Lab Code EMI- 1981 EMI- 2817 EMI- 3643 Sr-89

• 0.3 0.8 < 0.6 0.2

• 1.2 < 0.7 -0.4

• 0.9 < 0.8 5.0 Sf-90 0.9 .t 0.3 < 0.5 0.9

• 0.5 < 0.8 1.1

• 0.3 < 0.5 1.o 1-131 0.13

• 0.14 < 0.20 0.04 + 0.18 < 0.32 0.12

• 0.19 < 0.33 0.5 K-40 1433

• 121 1478

• 96 1505

• 93 Cs-I 34 1.3

• 2.2 < 4.2 -1.4 It 1.6 < 2.1 0.6

• 1.7 < 3.2 5.0 Cs-137 -1.4

• 2.7 < 2.8 -0.3

• 1.9 < 3.2 -0.6

• 1.9 < 2.7 5.0 Ba-La-140 0.2 f 2.3 < 4.4 0.2 r 1.4 < 3.8 0.2 k 1.5 < 3.1 5.0 Other (Co-60) -0.1

• 2.1 < 3.0 -0.6

• 1.8 < 1.3 -0.2

• 2.0 < 3.9 15.0

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

E-I ILambert Dairy Farm MDC MDC MDC Required Collection Date 08-17-11 LLD Lab Code EMI- 4465 EMI- 5594 EMI- 6172 K-40 Cs-134 CS-137 Ba-La-140 Other (Co-60)

MDC MDC MDC Required Collection Date 10-12-1 1 11-09-11 12-14-11 LLD Lab Code EMI- 6893 EMI- 7854 EMI- 8657 Sr-89 -0.7 f 0.9 c 0.7 0.1 f 0.8 < 0.7 0.8 f 0.8 < 0.7 5.0 Sr-90 1.5 f 0.4 < 0.5 1.2 f 0.3 < 0.5 0.7 f 0.3 < 0.5 1.o 1-131 0.13 f 0.22 < 0.37 0.06 f 0.14 < 0.25 -0.04 f 0.14 c 0.21 0.5 K-40 1376 f 81 1352 f 99 1336 f 91 CS-134 -0.6 f 1.1 < 1.7 -0.1 f 1.5 c 2.4

• 0.4 1.5 < 2.7 5.0 CS-137 -1.2

• 1.6 c 2.2 0.9 f 2.0 < 3.7 -1.4 k 1.8 c 2.4 5.0 Ba-La-140 -2.5

• 1.5 c 3.2 -2.9 f 1.6 < 2.6

• 0.2 1.5 < 1.6 5.0 Other (Co-60) -0.9 f 1.4 c 2.1 0.7 f 1.5 < 1.8 -0.1 f 2.0 < 2.6 15.0

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

E-21 Strutz Dairv Farm MDC MDC MDC Required Collection Date 01-12-11 02-09-11 03-09-11 LLD Lab Code EMI- 108 EMI- 538 EMI- 996 K-40 1487 r 116 - 1433f108 - 1429 f 106 -

CS-134 -1.0 f 2.2 < 3.5 0.4 f 1.6 < 3.1 1.or1.5 <3.1 5.0 CS-137 -2.1 f 2.3 < 2.8 -1.0 f 2.1 < 2.5 0.1 f 1.5 < 2.8 5.0 Ba-La-140 0.3 f 2.0 < 2.0 0.2 f 2.2 < 2.8 -0.2 f 1.2 < 1.7 5.0 Other (Co-60) 1.4 f 2.2 < 4.1 -0.1 f 2.2 < 1.7 2.4 f 1.8 G 2.7 15.0 MDC MDC MDC Required Collection Date 04-13-11 05-1 1-11 LLD Lab Code EMI- 1982 EMI- 2818 Sr-89 -0.6 f 0.7 < 0.7 *

-1.2 1.1 < 0.7 < 0.9 5.0 Sr-90 0.6 f 0.3 < 0.5 0.8 f 0.4 < 0.8 < 0.5 1.o 1-131 0.12 f 0.16 < 0.27 -0.13 f 0.17 < 0.32 < 0.44 0.5 K-40 1329 f 110 1334 f 95 Cs-134 -0.2 f 1.5 < 2.8 0.1 f 1.3 z 2.7 < 2.7 5.0 Cs-137 0.5 k 1.8 < 3.3 -0.1 r 1.8 c 2.8 < 3.4 5.0 Ba-La-140 -2.3 f 2.1 < 4.7 -1.7 f 1.4 < 1.5 < 2.3 5.0 Other (Co-60) -0.1 k 1.8 < 2.2 -1.1 f 1.9 < 1.9 < 2.1 15.0

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

E-21 Strutz Dairy Farm MDC MDC MDC Required Collection Date 07-13-1 1 08-17-11 09-14-11 LLD Lab Code EMI- 4466 EMI- 5595 EMI- 6173 Sr-89 -0.4 f 0.7 < 0.8 0.2 f 0.7 < 0.8 -0.6 f 0.9 < 0.7 5.0 Sr-90 0.4 f 0.3 < 0.5 0.4 f 0.3 < 0.5 1.0 f 0.4 < 0.6 1.o 1-131 0.06 f 0.20 < 0.35 -0.07 f 0.12 < 0.18 0.00 +_ 0.14 < 0.25 0.5 K-40 1488 f 100 1368 f 119 - 1380 rt 98 Cs-134 -0.1 f 1.8 < 2.9 1.6f1.8 <2.4 2.7 f 1.7 < 3.1 5.0 Cs-137 1.8 f 1.7 < 3.0 -0.5 f 2.4 < 2.9 0.5 +_ 1.9 < 3.6 5.0 Ba-La-140 -1.6 f 1.5 < 4.0 -0.2 f 2.3 < 4.9 -1.4 f 1.5 < 3.6 5.0 Other (Co-60) 1.3 f 1.9 < 1.8 0.3 f 2.2 < 2.6 0.9 f 1.8 < 3.0 15.0 MDC MDC MDC Required

~ollection'Date 10-12-1 1 11-09-11 12-14-11 LLD Lab Code EMI- 6894 EMI- 7855 EMI- 8658 Sr-89 0.0

• 0.7 < 0.8 0.4 f 0.8 < 0.8 -0.5 f 0.8 < 0.9 5.0 Sr-90 0.5

• 0.3 < 0.5 0.3 f 0.4 < 0.7 0.6 f 0.3 < 0.6 1.o 1-131 0.03

• 0.16 c 0.29 0.05 rt: 0.1 6 < 0.28 0.11 f 0.16 < 0.23 0.5 K-40 1369 f 80 1437 f 102 1411 f 95 Cs-134 -0.1 f 1.1 < 2.3 0.4 & 1.8 < 3.3 -0.8 f 1.3 < 2.1 5.0 Cs-137 -0.7

• 1.5 < 2.3 0.0

• 2.0 < 3.6 1.9 f 2.0 < 3.4 5.0 Ba-La-140 -0.2 f 1.4 < 4.5 0.3 f 1.5 < 2.5 +

-0.2 1.3 < 1.5 5.0 Other (Co-60) -0.6 f 1.7 < 2.2 3.1 f 1.9 < 2.9 -0.5 + 1.6 < 0.9 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 01-12-11 02-09-11 03-09-11 LLD Lab Code EMI- 109 EMI- 538 EMI- 997 Sr-89 -0.3 f 0.7 < 0.7 0.4 f 0.7 < 0.6 0.6 f 0.7 < 0.7 5.0 3-90 0.6 i 0.3 < 0.5 0.6 k 0.3 < 0.5 0.5 f 0.3 c 0.4 1.o 1-131 -0.04 f 0.1 8 c 0.33 -0.09 f 0.15 < 0.28 0.14 f 0.19 < 0.28 0.5 K-40 1362 f 104 1433 f 108 1425 f 94 CS-134 -0.6 f 1.5 < 3.3 0.4 f 1.6 c 3.1 -1.9 f 1.9 < 2.7 5.0 Cs-137 -0.3 f 1.7 < 3.3 *

-1.0 2.1 < 2.5 2.9 f 2.1 < 4.0 5.0 Ba-La-140 -2.1 t 1.5 < 2.1 0.2 f 2.2 < 2.8 *

-1.4 1.7 < 1.4 5.0 Other (Co-60) 0.9 f 1.9 < 3.4 *

-0.1 2.2 < 1.7 -0.1 f 1.5 < 2.4 15.0 MDC MDC MDC Required Collection Date 04-13-11 05-11-11 06-08-11 LLD Lab Code EMI- 1983 EMI- 2819 EMI- 3646 Sr-89 0.4 f 0.8 < 0.6 -1.9 f I.4 < 0.7 -0.6 k 0.8 c 0.7 5.0 Sr-90 0.5 f 0.3 c 0.6 1.4 f 0.5 < 0.8 0.7 f 0.3 < 0.5 1.o 1-131 0.14 f 0.17 < 0.29 -0.01 f 0.18 < 0.33 0.08 f 0.13 < 0.20 0.5 K-40 1474 f 118 1489 f 121 1438 f 86 Cs-134 0.1 f 1.9 < 2.9 -0.5 k 1.6 < 2.7 -0.6 f 1.5 < 2.5 5.0 Cs-137 1.8 f 2.2 < 3.5 1.8 f 2.3 < 2.5 +

-0.1 1.5 < 2.7 5.0 Ba-La-140

• 1.o 2.0 < 3.9 -2.3 k 2.0 < 4.2 0.5 f 1.4 c 2.3 5.0 Other (Co-60) 1.3 f 2.4 < 2.9 1.3 f 2.5 < 2.6 0.1 f 1.8 < 3.3 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 07-13-1 1 08-17-11 09-14-11 LLD Lab Code EMI- 4467 EMI- 5596 EMI- 6174 Sr-89 0.1 f 0.8 < 0.7 -0.3 f 0.7 < 0.7 0.1 f 0.7 < 0.6 5.0 Sr-90 0.7 f 0.3 < 0.5 * '

0.8 0.3 < 0.4 0.5 f 0.3 < 0.5 1.o 1-131 -0.05 f 0.19 < 0.34 0.00

• 0.1 1 < 0.16 -0.06 f 0.12 < 0.22 0.5 K-40 1535 f 99 1506 4 118 1411

• 107 CS-134 0.8 f 1.3 < 2.7 *

-0.1 1.5 < 2.9 -1.4 f 1.9 c 3.0 5.0 Cs-137 2.0 f 1.6 < 3.1 0.1 f 2.3 < 2.7 -0.2

• 1.9 < 2.9 5.0 Ba-La-140 -3.6 f 1.6 < 2.9 -1.5 f 1.2 < 2.3 -2.0 f 1.8 < 3.4 5.0 Other (Co-60) -0.9 f 1.8 < 1.7 1.5 f 1.9 < 2.9 0.4 f 2.4 < 1.9 15.0 MDC MDC MDC Required Collection Date 10-12-1 1 11-09-11 12-14-11 LLD Lab Code EMI- 6895 EMI- 7856 EMI- 8659 Sr-89 *

-0.8 0.8 < 0.8 0.2 f 0.6 c 0.6

• 0.1 0.8 < 0.8 5.0 Sr-90 1.0 f 0.4 c 0.5

• 0.5 0.3 < 0.5 0.5 f 0.3 c 0.5 1.o 1-131 0.17 f 0.20 < 0.37 0.06 f 0.14 0.20 -0.09 f 0.14 < 0.20 0.5 K-40 1557

• 117 1297 f 97 1528

• 117 Cs-134 -0.1 f 1.6 < 2.6 0.6 f 1.4 c 3.1 -0.7 f 1.5 < 2.2 5.0 CS-137 2.6 f 2.1 < 3.5 0.3 f 1.8 < 2.6 -1.4

• 2.2 < 2.8 5.0 Ba-La-140 1.8

• 1.4 < 2.9 1.9 f 1.2 < 2.8 -3.8 f 2.2 < 1.7 5.0 Other (Co-60) -0.1

• 2.1 < 2.9 0.1

• 2.1 < 2.1 -0.2 f 2.2 < 3.3 15.0 Sr-89 Annual Mean + s.d.

Sr-90Annual Mean + s.d.

1-131Annual Mean + s.d.

K-40 Annual Mean + s.d.

Cs-134 Annual Mean + s.d.

Cs-137 Annual Mean + s.d.

Ba-La Annual Mean + s.d.

Co-60Annual Mean + s.d.

POINT BEACH NUCLEAR PLANT Table 4. Radioactivity in Well Water Samples, E-10

- Collection: Quarterly Units: pCilL Ist Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Req. Annual LLD Mean s.d Collection Date 01-13-11 04-19-11 07-14-11 10-13-11 Req.

Lab Code EWW- 123 EWW- 2227 EWW- 4616 EWW- 6934 LLD Gross Beta 1.9

• 1.6 0.7 k 1.1 0.0

• 0.4 3.0 f 1.7 4.0 H-3 53.4 f 86.2 58.6

• 77.9 -44.2

• 70.7 -14.1 f 86.6 500 Sr-89 -0.3 1 0.7 -0.2 k 0.5 +

0.2 0.5 0.3 It 0.5 5.0 3-90

• 0.0 0.3

• 0.0 0.2 -0.1 k 0.3 -0.2 f 0.2 1.o 1-131 -0.03

• 0.14 -0.01

• 0.15 0.09 f 0.20 0.15 k 0.16 0.5 Mn-54 -1.6

• 1.7 2.1

• 2.0 0.2 f 1.5 -1.3

• 2.2 10 Fe-59 -2.8 f 3.1 1.0 f 2.8 3.0 k 3.2 -2.0 Zk 4.9 30 CO-58 -1.3 k 1.5 -0.8 k 1.7 -0.8

• 1.8 0.3 f 2.0 10 CO-60 -0.5 k 1.8 -1.4

• 2.0 -1.1 k 1.5 -1.1

• 2.4 10 Zn-65 -0.4 rt 3.3 2.0 & 3.6 1.0

• 3.5 -5.4 i 5.6 30 Zr-Nb-95 -2.7 f 2.3 -0.1

• 2.0 -1.5 f 2.0 -4.1 + 2.2 15 Cs-134 -1.4

• 2.0 -1.0 k 1.7 0.3 1.4 0.7 k 2.1 10 Cs-I 37 0.2 2.3 2.2

• 2.1 -0.2 f 1.6 2.1 f 2.5 10 Ba-La-140 2.0

• 2.0 2.5

• 2.0 1.1

• 2.0 0.5 + 2.4 15 Other (Ru-103) -0.3 f 2.0 -3.5

• 2.1 -0.2

• 1.4 -0.8 + 2.5 30 MDC Data Collection Date 01-13-10 04-19-11 07-14-11 10-13-11 Req.

Lab Code EWW- 123 EWW- 2227 EWW- 4616 EWW- 6934 LLD Gross Beta < 2.9 < 2.0 < 0.8 < 2.9 4.0 < 2.2 Mn-54 Fe-59 CO-58 Co-60 21-1-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Other (Ru-103)

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

Location: E-01 (Meteorological Tower)

Collection: Monthly composites Units: pCllL MDC MDC MDC MDC Lab Code ELW- 119 ELW- 618 ELW- 1148 ELW- 2137 Date Collected 01-13-10 02-16-11 03-17-11 04-14-11 Req. LLD Gross beta 4.9 f 0.9 < 1.2 3.0 f 0.5 < 0.6 5.5 f 0.9 < 1.4 1.7 f 0.6 < 0.9 4.0 1-131 0.11 f 0.16 < 0.29 -0.09 f 0.15 < 0.28 0.03 f 0.13 < 0.20 0.07 f 0.18 < 0.31 0.5 Be-7 -5.8 f 11.4 c 17.9 -3.5 f 13.1 c 27.9 -1.9 f 14.2 < 27.6 1.5 f 14.9 < 29.2 Mn-54 0.7 f 1.5 < 3.0 -0.7 f 1.6 < 2.3 1.3 f 1.5 < 3.0 -0.4 f 1.9 < 2.3 10 Fe-59 -0.2 f 2.7 < 3.0 -0.9 f 2.8 < 3.7 0.1 f 2.5 < 3.5 -4.4 f 3.6 < 5.4 30 Co-58 1.0 f 1.2 c 21 0.2 f 1.5 < 2.2 1.5 f 1.6 < 2.4 0.8 f 1.6 < 2.4 10 CO-60 1.1 f 1.0 c 2.2 0.3 f 1.5 < 1.8 -0.3 f 2.0 < 2.6 0.0 f 1.5 < 1.8 10 Zn-65 -0.8 f 3.2 < 6.8 -0.3 f 3.1 4 5.2 -1.4 f 3.4 <, 2.9 0.1 f 3.8 c 5.7 30 Zr-Nb-95 -1.4 f 1.7 < 2.3 -1.9 f 1.7 < 1.7 -0.8 f 1.9 < 2.7 0.2 f 1.9 < 3.4 15 Cs-134 -0.9 f 1.4 < 2.3 -0.2 f 1.5 < 2.6 -0.4 f 1.8 c 2.9 0.7 f 1.4 < 2.9 10 CS-137 -0.5 f 1.5 < 2.4 2.6 f 1.8 < 3.4 0.4 f 2.1 < 3.0 -0.1 f 1.6 < 3.0 10 Ba-La-140 0.1 f 1.5 c 2.6 -3.0 f 1.4 < 1.7 0.8 f 1.6 13 0.3 f 1.7 < 4.0 15 Other(Ru-103) 0,111.3 <2.3 -0.3f1.4 <2.2 -1.0f1.5 c2.2 -2.321.3 ~ 2 . 1 30 Lab Code ELW- 3046 ELW- 3851 ELW- 4493 ELW- 5609 Date Collected 05-16-11 06-17-11 07-14-11 08-18-11 Req. LLD Gross beta 0.9 f 0.5 < 0.9 2.0 f 0.8 < 1.3 0.7 f 0.5 < 0.9 1.0 i0.5 < 0.9 4.0 1-131 0.11 f 0.12 < 0.21 0.04 f 0.22 < 0.39 -0.02 f 0.19 < 0.34 0.01 f 0.16 < 0.23 0.5 Be-7 -4.0 f 14.7 z 28.2 -8.7 f 13.2 c 21.1 1.4 f 17.9 < 28.5 6.7 f 21.5 < 46.6 Mn-54 0.4 f 1.5 c 2.7 1.1f1.5 <2.6

• 0.7 2.0 < 4.1 -2.6 f 2.9 c 3.5 10 Fe-59 0.0 f 2.6 < 2.6 -0.1 f 2.5 < 2.5 2.4 f 4.0 < 3.7 5.7 f 5.4 < 8.8 30 CO-58 1.5f1.3 e1.8 0.2f1.5 <1.6 -1.0 f 1.9 < 3.6 1.8 f 2.6 c 2.8 10 CO-60 0.2 f 1.5 < 2.0 -0.8 f 1.4 < 1.4 0.1 f 1.8 < 2.0 -1.0 f 2.8 < 3.7 10 Zn-65 -1.4 f 3.4 c 6.0 2.3 f 2.5 < 3.0 -1.2 f 4.6 < 6.1 -3.5 f 7.8 c 5.2 30 Zr-Nb-95 -0.6 f 1.9 -= 2.4 1.0 f 1.6 c 3.4 -1.4 f 1.9 < 2.5 1.6 f 2.9 < 2.9 15 CS-134 -1.6 f 1.7 c 2.2 -0.2 f 1.2 < 1.9 -1.2 f 2.0 c 2.8 -4.1 f 3.0 < 4.2 10 CS-137 0.5 f 2.1 < 3.7 0.0 f 1.5 < 2.2 1.2 f 2.2 c 3.8 -0.7 f 3.1 < 4.4 10 Ba-La-140 1.8f1.9 e5.7 1.Of1.8 <2.9 -0.1 f 1.8 < 2.8 -2.8 f 2.9 < 3.4 15 Other (Ru-103) 0.1 It 1.6 < 3.7 0.3 f 1.6 < 3.0 0.2 f 2.2 < 3.2 -0.4 f 2.5 < 5.3 30 Lab Code ELW- 6238 ELW- 6936 ELW- 8075 ELW- 8730 Date Collected 09-13-11 10-13-11 11-16-11 12-15-11 Req. LLD Gross beta 0.6 f 0.4 < 0.6 2.6 t 0.8 < 1.3 1.9 f 0.6 < 0.9 2.4 f 0.8 < 1.2 4.0 1-131 0.14 f 0.20 < 0.34 0.00 f 0.19 < 0.33 0.09 f 0.23 < 0.40 0.06 f 0.13 < 0.18 0.5 Be-7 9.1 f 12.7 < 30.3 5.6 f 17.1 c 37.3 -7.7 f 12.6 < 26.8 -3.3 f 17.9 c 38.2 Mn-54 -0.3 f 1.5 < 2.5 0.1 f 1.8 < 3.7 0.7 f 1.5 < 2.6 1.0 f 2.3 < 3.9 10 Fe-59 1.3 f 3.4 < 7.0 -2.5 f 3.5 < 4.5 1.7 f 2.4 < 4.2 -1.3 f 4.4 c 4.4 30 CO-58 2.5 f 1.6 < 2.5 1.2 f 1.8 < 2.7 -1.9f1.4 4 . 4 *

-0.2 2.0 < 2.2 10 CO-60 1.6f1.6 c1.8 -1.122.2 <2.7 -1.4 f 1.6 < 0.8 0.2 f 2.4 < 2.7 10 Zn-65 -1.6 f 3.8 < 4.2 -3.6 f 3.5 < 2.4 -0.9 f 2.8 c 3.8 1.5 f 4.0 c 7.2 30 Zr-Nb-95 2.1 f 1.6 c 3.9 2.0 f 1.8 < 4.4 0.1 f 1.6 s 3.7 -0.7 f 2.3 < 5.1 15 CS-134 0.9 f 1.4 < 2.7 -0.4 f 1.9 < 3.7 0.3 f 1.3 < 2.1 -0.7

• 2.4 < 2.8 10 CS-137 -1.3 f 1.9 < 2.5 0.0 f 2.1 < 2.6 1.1f1.6 <2.8 2.1 i 2.6 < 5.3 10 Ba-La-140 -1.5 f 1.8 < 4.0 -3.2 f 2.6 < 5.4 1.8f2.0 <4.1 2.1 f 2.2 < 3.4 15 Other (Ru-103) -0.8 f 1.2 < 2.2 0.9 f 2.0 < 3.6 -0.5 f 1.5 < 3.9 -3.2 f 2.4 < 2.4 30

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

Location: E-05 (Two Creeks Park)

Collection: Monthly composites Units: pCilL MDC MDC MDC MDC Lab Code ELW- 120 ELW- 619 ELW- 1149 ELW- 2138 Date Collected 01-13-11 02-16-11 03-17-11 04-14-11 Req. LLD Gross bela 2.4 f 0.8 < 1.2 1.5 f 0.4 < 0.6 2.3 f 0.7 < 1.1 1.2 f 0.6 < 0.9 4.0 1-131 0.12 f 0.12 < 0.18 -0.11 f 0.16 < 0.30 0.01 f 0.14 < 0.21 -0.03 f 0.19 < 0.35 0.5 Bed -2.4 f 12.0 < 22.7 1.0 f 17.3 < 37.7 10.1 f 13.4 < 26.4 12.2 f 13.7 < 39.9 Mn-54 0.0 f 1.3 c 2.3 0.2 f 2.0 c 2.8 0.5 f 1.6 < 2.7 -0.1 f 1.6 c 1.7 10 Fe-59 0.3 f 2.4 < 4.4 -1.6 f 2.7 < 4.6 -0.9 f 2.9 < 5.4 -0.2 f 2.6 < 3.6 30 CO-58 -1.4.f 1.4 < 2.4 1.2 It 1.9 < 3.5 -0.6 f 1.8 < 1.7 -0.8 f 1.6 c 2.6 10 CO-60 -0.5 f 1.4 < 1.2 0.3 t 1.6 < 2.4 -1.0 f 2.0 < 2.4 1.6 f 1.4 < 1.6 10 Zn-65 0.2 f 2.9 < 5.0 0.9 f 3.8 < 5.0 -0.9 f 3.1 c 4.2 1.3 f 2.4 < 2.1 30 Zr-Nb-95 0.2 f 1.6 < 3.3 0.2 f 1.9 < 3.5 -4.7 f 2.3 < 2.3 -1.7 f 1.9 < 4.1 15 Cs-134 -0.8 f 1.2 < 2.2 -0.4 f 2.0 < 3.3 -1.9 f 1.5 c 2.5 1.2 f 1.7 < 3.1 10 Cs-137 -0.2 f 1.5 c 3.0 1.2 f 2.2 c 4.1 -0.7 f 2.1 < 3.1 -1.9 f 1.9 c 2.8 10 Ba-La-140 -1.1 f 1.6 c 2.4 0.3 f 1.6 < 2.5 1.1 f 1.8 < 3.3 -1.3 f 1.5 < 3.6 15 Other(Ru-103) 0.3 f 1.2 c 2.3 -1.3 f 2.0 < 2.6 0.7 f 1.3 < 2.4 1.7 f 1.4 c 3.9 30 Lab Code ELW- 3047 ELW- 3852 ELW- 4494 ELW- 5610 Date Collected 05-16-11 06-17-11 07-14-1I 08-18-11 Req. LLD Gross beta 1.1 f 0.6 < 0.9 1.8 f 0.6 < 0.9 4.0 1-131 -0.04 f 0.18 < 0.32 0.12 f 0.14 < 0.21 0.5 Be-7 1.4 f 13.8 < 33.9 11.2 f 21.1 c 35.6 Mn-54 -0.4 f 1.7 c 2.1 -1.1 f 2.4 < 4.6 10 Fe-59 -1.0 f 3.1 < 3.1 2.5 f 4.1 c 6.2 30 CO-58 1.5 f 1.5 < 2.8 1.4 f 2.0 < 3.4 10 CO-60 -2.7f1.8 4 . 5 0.9 f 2.3 < 2.5 10 Zn-65 -1.4 f 3.4 c 3.3 2.1 f 4.7 c 4.2 30 Zr-Nb-95 -0.7f1.8 <l.8 -1.9f2.4 <4.6 15 Cs-134 0.3 f 1.5 c 2.6 1.7 f 2.1 < 2.9 10 Cs-137 0.4 f 2.0 < 3.5 -0.2 f 2.4 c 3.0 10 Ba-La-140 -0.6 f 1.8 < 3.4 0.3 f 2.6 < 3.9 15 Other (Ru-103) 0.4 f 1.5 < 3.2 0.4 f 2.5 c 4.1 30 Lab Code ELW- 6239 ELW- 6937 ELW- 8077 ELW- 8731 Date Collected 09-13-11 10-13-11 11-18-11 12-15-11 Req. LLD Gross beta 0.9 f 0.4 < 0.6 1.9f0.7 <1,1 1.5 f 0.6 < 1.0 2.8 f 0.8 < 1.3 4.0 1-131 0.10 f 0.19 < 0.33 0.13 f 0.20 < 0.34 -0.07 f 0.15 < 0.28 0.10 f 0.13 C 0.19 0.5 Be-7 0.6 f 13.1 < 27.6 -5.7 f 15.0 c 21.6 -0.9 f 11.8 < 29.7 -0.5 f 10.4 < 19.1 Mn-54 0.6 f 1.5 < 2.7 1.4 f 1.5 < 2.5 -0.2 f 1.6 < 2.7 -0.1 f 1.3 c 2.2 10 Fe-59 -1.0 f 2.6 < 3.7 2.7 f 3.1 < 6.9 -1.8 f 2.3 c 5.1 -0.2 f 2.0 < 3.3 30 Co-58 -0.8 f 1.4 c 2.3 0.1 f 1.4 < 1.5 -0.1 f 1.3 < 1.3 0.5 f 1.2 < 1.9 10 CO-60 -1.5 + 1.5 c 1.6 0.3 t 1.5 < 2.3 0.4 f 1.3 c 1.2 0.1 f 1.4 10.7 10 Zn-65 2.0 f 3.2 < 5.7 -3.7 f 3.3 < 3.3 1.2 f 3.0 < 4.2 -0.7 f 2.7 < 4.7 30 Zr-Nb-95 -1.4 f 1.4 < 1.6 1.1 f 1.6 c 4.4 -0.4 f 1.6 < 3.8 0.4 f 1.4 < 2.4 15 CS-134 0.7 f 1.5 < 2.8 0.1 f 1.5 < 2.9 0.0 f 1.3 < 2.7 0.4 f 1.1 < 2.0 10 Cs-137 2.3 f 1.7 < 2.7 0.2 f 1.8 < 4.2 1.7 f 1.6 < 2.7 0.4 r 1.6 c 2.8 10 Ba-La-140 -0.9 f 1.5 < 4.7 3.9 f 1.8 c 5 1

• 1 . 1.8 < 5.5 -0.3 t 1.3 < 1.8 15 Other(Ru-103) -0.4 f 1.4 c 3.6 -0.3 f 1.7 c 2.8 -0.7 f 1.4 < 2.2 -0.6 t 1.1 < 1.7 30

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

Location: E-06 (Coast Guard Station)

Collection: Monthly composites Units: pCi1L MDC MDC MDC MDC Lab Code ELW- 121 ELW- 620 ELW- 1150 ELW- 2139 Date Collected 01-13-11 02-16-11 03-17-11 04-14-11 Req. LLD Gross beta 11.3 f 1.2 < 1.2 2.3 f 0.5 < 0.6 2.7 f 0.8 < 1.3 0.4 f 0.5 c 0.9 4.0 1-131 0.06 f 0.14 < 0.24 -0.01 f 0.18 < 0.33 -0.05 f 0.23 < 0.46 -0.13 f 0.18 < 0.33 0.5 Be-7 3.2 f 16.9 c 30.6 11.9 f 14.0 < 30.6 3.7 f 13.8 < 34.3 14.4 f 14.1 c 32.8 Mn-54 -0.5 f 1.7 < 2.5 0.1 f 1.7 c 2.0 0.6 f 1.6 < 2.4 -0.4 f 1.8 < 2.7 10 Fe-59 -2.0 f 3.0 < 5.4 -2.3 f 3.4 < 5.8 -1.7 f 2.5 < 2.5 0.9 f 3.2 c 3.9 30 CO-58 -0.7 f 1.6 < 2.9 0.4 f 1.4 < 1.6 -0.5 f 1.5 c 2.3 0.1 f 1.6 < 1.8 10 Co-60 0.6 f 1.9 < 2.5 -1.0 f 1.8 < 2.1 -0.5 f 1.8 < 2.8 -0.1 f 1.6 < 1.3 10 Zn-65 -1.7 f 3.5 c 4.2 0.5 f 2.3 c 2.7 3.5 f 3.0 c 3.3 -1.6 f 3.0 < 4.2 30 Zr-Nb-95 -0.1 f 1.7 < 2.0 -0.7 f 1.7 c 2.9 -1.0 f 1.8 < 3.2 -1.7 f 1.6 < 3.1 15 Cs-134 -1.3 i1.8 < 3.2 -0.5 f 1.4 < 3.1 0.1 f 1.5 c 2.3 -0.1 f 1.7 < 2.4 10 CS-137 0.2 f 1.9 < 3.9 0.4 f 1.6 C 2.9 -2.1 f 1.9 < 2.1 -0.1 f 1.8 < 3.0 10 Ba-La-140 0.3 f 1.7 c 3.6 -1.1 f 1.9 < 2.3 -1.6 f 1.8 < 1.3 -0.3 f 1.9 < 5.0 15 Other (Ru-103) 2.3 f 2.0 < 4.5 -1.7 f 1.5 < 1.9 0.2 f 1.5 < 3.0 0.4 f 1.4 < 4.2 30 Lab Code ELW- 3048 ELW- 3853 ELW- 4495 ELW- 5611 Date Collected 05-16-11 06-17-11 07-14-1 1 08-18-1 1 Req. LLD Gross beta 1.4 f 0.9 < 1.7 1.2f0.8 <1.3 1.1 f 0.6 < 0.9 1.4 f 0.6 < 0.9 4.0 1-131 0.02 f 0.12 c 0.22 0.10 i 0.22 < 0.39 -0.04 f 0.20 < 0.41 0.06f0.13 C0.19 0.5 Be-7 12.7 f 14.9 < 35.6 12.6 f 18.9 < 36.2 -7.2 f 17.7 < 23.5 11.2 f 21.9 c 36.8 Mn-54 -0.3f1.3 <1.5 -0.6 f 1.8 c 3.0 0.5 f 1.8 < 3.2 -0.9 f 2.2 < 2.6 Fe-59 -1.2 f 2.5 < 3.2 0.4 f 4.0 c 7.0

• 0.7 3.3 < 6.8 0.4 f 4.6 < 6.2 CO-58 0.8 f 1.7 c 2.9 -1.1 f 1.7 < 2.1 -1.8f1.7 c1.5

• 0.1 2.1 < 4.3 CO-60 -0.7 f 1.6 < 1.7 -0.9 f 1.6 c 1.7 0.7 f 1.7 < 2.4 0.2 f 2.7 < 2.3 Zn-65 -2.6 f 3.0 c 2.3 0.5 f 4.7 c 4.1 3.1f3.1 c3.7 0.4 f 4.4 c 2.9 Zr-Nb-95 -1.7 f 1.8 < 2.7 -1.8 f 1.9 < 2.6 0.4 f 1.8 c 3.0 0.2 f 2.4 < 3.3 Cs-134 0.1 f 1.5 < 3.1 1.1 f 2.1 < 3.9 0.5 f 1.7 c 2.4 0.3 f 2.0 c 3.4 CS-137 -0.1 f 1.6 < 3.1 1.9 f 2.5 c 4.0 1.4 f 2.1 c 3.4 2.5 f 2.4 < 3.7 Ba-La-140 -2.5 f 1.9 < 2.2 -1.4 f 2.3 c 7.0 -0.2f1.8 <1.6 2.7 f 2.3 < 3.5 Other (Ru-103) 0.2 f 1.5 < 3.0 -0.7 f 2.2 < 4.3 -0.8 f 2.0 < 2.9 1.0 f 2.4 < 4.6 Lab Code ELW- 6240 ELW- 6938 ELW- 8078 ELW- 8732 Date Collected 09-13-11 10-13 11-16-11 12-15-11 Req. LLD Gross beta 0.9 f 0.4 < 0.6 2.1 f 0.8 0.6 f 0.5 < 0.9 2.9 f 0.7 C 1.1 4.0 1-131 -0.02 f 0.21 C 0.38 0.11 f 0.15 0.00 f 0.16 < 0.29 -0.02 f 0.19 < 0.37 0.5 Be-7 -4.7 f 11.5 c 25.1 -6.7 f 20.2 12.4f11.5 <31.5 6.9 f 10.5 < 19.8 Mn-54 -0.1 f 1.4 < 1.5 -1.3 f 1.9 0.7 f 1.6 c 3.1 -0.1 f 1.3 < 2.8 10 Fe-59 1.8 f 2.7 < 5.2 0.9 f 4.0 -0.7 f 2.6 < 5.6 2.3 f 2.7 < 5.6 30 CO-58 0.2f1.2 c1.9 -0.1 f 1.6 -0.6f1.2 <1.4 -0.3 f 1.3 < 1.9 10 CO-60 0.6f1.4 <1.9 2.1 f 2.4 -1.3 f 1.7 c 1.7 0.8f1.4 c2.2 10 Zn-65 *

-1.2 2.7 c 3.0 -0.3 f 4.2 -3.4 f 3.1 < 2.9 -3.0 f 2.4 < 2.0 30 Zr-Nb-95 1.5f1.5 e2.8 -1.3 f 1.7 -0.6 f 1.7 < 4.9 0.1 f 1.4 < 2.4 15 Cs-134 0.6 f 1.3 < 2.9 0.7 i 2.0 0.0f1.3 <1.9 -0.5 f 1.1 < 1.8 10 Cs-137 0.6 f 1.7 < 3.2 0.0 f 2.3 -0.4 f 1.7 < 3.0 -1.5 f 1.4 < 2.2 10 Ba-La-140 0.3 f 1.7 c 3.9 3.9 f 2.5 -0.6 f 1.6 < 2.7 0.4 f 1.6 < 1.6 15 Other (Ru-103) -0.1 f 1.4 c 3.9 -0.9 f 2.1 -1.0 f 1.3 c 2.3 -1.5f1.1 1 . 30

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

Location: E-33 (Kewaunee)

Collection: Monthly composites Unlts: pCiR MDC MDC MDC MDC Lab Code ELW- 122 ELW- 621 ELW- 1151 ELW- 2140 Date Collected 01-13-11 02-16-11 03-17-11 04-14-11 Req. LLD

~ r o s beta s 5.3 f 1.0 c 1.2 2.2 i0.5 < 0.6 4.5 i0.9 < 1.3 1.2 f 0.6 <10 4.0 1-131 0.10 f 0.15 C 0.25 -0.11 f 0.17 < 0.31 0.16 f 0.17 < 0.30 -0.11 f 0.19 < 0.35 0.5 Be-7 -3.9 f 12.4 c 23.5 10.9 f 19.5 c 33.3 -11.0 f 13.4 c 21.2 -4.5 f 12.6 < 22.6 Mn-54 0.6 f 1.5 c 2.3 -0.6 f 2.1 < 3.1 0.8 f 1.6 c 2.6 1.5f1.6 e1.9 10 Fe-59 1.9 f 2.3 c 4.4 0.4 f 4.1 < 6.7 -0.7 f 2.9 < 3.9 -1.9 f 2.7 < 2.9 30 CO-58 0.0 2 1.2 c 1.9 -0.8 f 2.0 < 3.2 1.7 f 1.5 c 1.7 -1.3 f 1.5 c 2.2 10 CO-60 0.4 f 1.2 c 2.5 -1.4 f 2.0 < 2.9 2.3 i1.6 < 2.4 1.8f1.5 e2.1 10 211-65 3.9 f 2.9 c 5.4 2.4 f 4.1 c 5.3 -1.4 f 2.6 c 3.5 -0.3 f 3.4 5.0 30 Zr-Nb-95 -0.4 f 1.4 c 2.7 -0.6 f 2.1 c 4.1 -1.7 f 1.8 < 2.4 -3.1 f 1.8 < 3.2 15 CS-134 0.2 f 1.4 c 2.5 1.3 f 2.1 < 3.4 -0.4 f 1.5 < 2.4 -0.2 i1.4 c 3.1 10 Cs-137 0.1 f 1.5 c 2.2 2.0 f 2.5 < 4.7 0.2 f 1.7 < 3.8 -1.3 f 1.9 2.2 10 Ba-La-140 1.4 f 1.5 < 1.7 -2.5 f 2.5 < 3.0 1.2 f 2.1 c 2.2 -1.5 f 1.6 < 3.3 15 Other(Ru-103) 0.3 f 1.4 c 3.0 1.4

• 2.3 c 4.0 -0.7 f 1.5 < 2.2 -0.1 f 1.4 < 2.8 30 Lab Code ELW- 3049 ELW- 3854 ELW- 4496 ELW- 5612 Date Collected 05-16-11 06-27-11 07-14-1 1 08-18-11 Req. LLD Gross beta 0.6 f 1.0 < 1.9 2.0 f 0.8 < 1.3 2.8 f 0.7 < 1.0 1.2 f 0.5 < 0.8 4.0 1-131 0.04 f 0.13 < 0.23 0.01 f 0.20 < 0.35 0.12 f 0.21 < 0.39 0.01 f 0.14 < 0.20 0.5 Be-7 12.8 f 12.2 c 28.8 4.3 f 17.0 c 30.8 1.1 f 11.4 c 22.2 6.7 f 23.2 c 39.9 Mn-54 1.4f1.9 c3.0 -0.2 f 1.7 < 2.5 0.4 f 1.5 < 2.9 -0.9 f 2.8 < 4.5 I0 Fe-59 -4.6 f 3.4 < 5.4 -0.2 f 2.9 c 2.3 0.3 f 2.7 c 4.1 -0.5 f 6.7 c 9.9 30 CO-58 0.4f1.4 ~1.9 -1.2 f 1.7 < 2.0 1.0 f 1.4 c 1.9 1.1 f 3.2 < 6.0 10 CO-60 -1.4 f 1.9 c 1.7 -1.4i1.9 ~ 2 . 8 -1.3f1.5 ~ 1 . 2 -2.0 f 3.5 < 3.8 10 Zn-65 -2.8 f 2.6 c 1.9 1.5 f 3.8 c 4.3 0.7 f 2.8 c 3.0 -5.2 f 7.4 c 7.2 30 Zr-Nb-95 1.4 f 1.8 c 3.6 0.5 f 1.7 c 4.0 -0.4 f 1.7 c 2.4 -2.7 f 2.7 c 3.2 15 Cs-134 -0.2 f 1.4 < 2.3 0.8 f 1.8 c 2.2 0.9 f 1.6 < 2.9 0.7 f 3.1 c 3.9 10 Cs-137 2.0 f 2.1 < 3.5 -1.9 f 1.9 < 2.4 -0.7 f 1.9 < 2.1 -1.1 f 3.6 < 5.3 10 Ba-La-140 -2.6 f 1.9 < 2.8 2.0 f 2.0 c 4.5 -1.5 f 1.6 c 3.0 -1.7 f 3.6 < 3.8 15 Other (Ru-103) -0.9 f 1.3 < 2.1 -1.3 f 2.1 c 2.7 0.4 f 1.5 c 3.5 -0.7 f 2.8 c 4.7 30 All locations Lab Code ELW- 6241 ELW- 6939 ELW- 8079 ELW- 8733 Annual Date Collected 09-14-11 10-13-1I 11-17. 12-15-11 Req. LLD Mean f s.d.

Gross beta 0.2 f 0.4 < 0.6 1.5 f 0.7 C 1.2 0.5 f 0.5 3.0 f 0.8 < 1.3 4.0 2.1 f 1.8 1-131 0.12 f 0.17 < 0.29 0.02 f 0.17 < 0.31 -0.06 f 0.14 0.15 f 0.21 < 0.37 0.5 0.04 f 0.08 Be-7 2.7 f 9.6 < 24.7 8.9 f 12.4 c 29.1 11.0 f 10.4 7.9 f 11.0 c 22.7 3.0 f 7.2 Mn-54 -0.5 f 1.3 c 2.2 0.1 f 1.3 c 2.4 0.3 f 1.2 0.5 f 1.3 c 2.2 10 0.1 f 0.8 Fe-59 2.3 f 2.2 c 5.6 2.6 f 2.3 c 4.4 -0.8 f 2.5 -1.7 f 2.7 c 3.8 30 -0.2 f 2.0 CO-58 0.2 f 1.1 < 2.1 -0.3 f 1.3 ~ 2 . 4 -1.5f1.3 -0.6 f 1.4 c 1.7 10 +

0.1 1.0 Co-60 0.3f1.2 c1.8 0.7 f 1.3 c 2.2

< 4.0 0.5 f 1.0

-1.5 f 2.9

-1.1 f 1.7

-2.3 f 2.5 c 0.9 c 2.2 10 30

-0.1 1.1

-0.5 k 2.0 211-65 0.9 f 2.5 < 4.5 0.9 f 2.9 Zr-Nb-95 -0.6 f 1.4 c 3.0 -1.9 f 1.3 c 2.7 2.1 f 1.6 -0.2 f 1.4 c 2.1 15 -0.5k1.4 CS-134 -0.5 f 1.0 c 2.1 0.0 f 1.2 < 2.0 1 . 7 0.0 f 1.5 0.5f1.7

-0.7 f 1.3 0.2i1.4 c 3.0 c1.9 10 10

-0.1 1.0 0.3f1.2 Cs-137 1.3f1.4 ~2.6 0.2 f 1.5 Ba-La-I40 1.1f1.6 ~4.3 -0.6 f 1.4 c 2.5 0.5 1: 1.7 -1.3 f 1.8 c 2.5 15 -0.2i1.7 Other (Ru-103) -0.7 f 1.1 < 2.6 -1.1 f 1.5 < 2.6 -0.6 f 1.3 -1.4 f 1.3 c 2.6 30 -0.3 f 1.1

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

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

Period 1st Qtr. MDC 2nd Qtr. MDC 3rd Qtr. MDC 4th Qtr. MDC Lab Code ELW- 1152 ELW- 4332 ELW- 6277 ELW- 8740 Req. LLDs H-3 9 0 5 ~ t 1 2 3 ~ < 1 6 3 855Z76 <I44 75+79 <I43 555~76 <I47 500 Sr-89 0.05k0.47 <0.52 -0.4950.83 <0.74 -0.15?~0.60 <0.72 0.10f0.68 <0.75 5.0 Sr-90 0.28f0.25 <0.47 0.5350.38 i0.70 0.33f0.28 <0.53 0.28f0.28 <0.53 1.0 Location E-05 (Two Creeks Park)

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

Lab Code ELW- 1153 ELW- 4333 ELW- 6278 ELW- 8741 Req. LLDs Location E-06 (Coast Guard Station)

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

Lab Code ELW- 1154 ELW- 4334 ELW- 6279 ELW- 8742 Req. LLDs Location E d 3 (Kewaunee)

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

Lab Code ELW- 1155 ELW- 4335 ELW- 6280 ELW- 8743 Req. LLDs H-3 220965Z449b<163 -1572 <I44 3 0 ~ 7 7 <I43 945~78 e l 4 7 500 Sr-89 -0.10 50.49 < 0.56 0.19 k0.63 < 0.66 0.22 k0.52 < 0.58 -0.03 5~0.71 < 0.71 5.0 Sr-90 0.21 *0.35 < 0.55 0.03 5~0.28 < 0.59 0.29 f 0 . 2 4 < 0.45 0.43 k0.30 < 0.53 1.0 a January sample tritium = 2709k194 pCilL; February tritium = I1 I t 119 pCilL; March tritium = 60k117 -CiIL.

Tritium reanalyzed with a result of 22307t456 pCi1L. January sample tritium = 73i100 pCilL; February = 64t99 pCilL; March = 64741k758 pCi/L.

Tritium Annual Mean + s.d. 1503 k 5496 Sr-89Annual Mean +sad. 0.08 f 0.30 Sr-90Annual Mean + s.d. 0.25 f 0.15

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

Location: E-I 3 Collection: 2x 1year Units: pCilg wet Sample Description and Concentration Req.

MDC MDC LLD Collection Date 02-24-11 05-24-11 08-15-11 Lab Code EF- 3174 EF- 3175 EF- 5824 Type Burbot Lake Trout Brown Trout Ratio (wetldry wt.) 4.97 4.75 Gross Beta 3.20 f 0.12 < 0.043 K-40 Mn-54 Fe-59 CO-58 Co-60 Zn-65 CS-134 Cs-137 Other (Ru-103)

Collection Date 08-30-11 11-08-11 11-19-11 Lab Code EF- 5825 EF- 8662 EF- 8663 Type Rainbow Trout Coho Salmon Coho Salmon Ratio (wetldry wt.) 3.44 4.1 7 3.74 Gross Beta 3.72 f 0.08 < 0.024 Mn-54 Fe-59 CO-58 Co-60 Zn-65 CS-134 CS-137 Other (Ru-

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 (pCi/g wet) Req.

MDC MDC MDC LLD Annual Mean s.d.

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

MDC MDC MDC Collection Date 411412011 4/14/2011 411412011 Lab Code ESS- 2147 ESS- 2148 ESS- 2149 LLD Location Gross Beta Collection Date 411412011 411412011 Lab Code ESS- 2150 ESS- 2151 Location Gross Beta Be-7 K-40 Cs-137 TI-208 Pb-212 Bi-214 Ra-226 Ac-228

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

Sample Description and Concentration (pCilg dry)

MDC MDC MDC Collection Date 1011312011 10113/2011 1011312011 Req.

Lab Code ESS- 7154 ESS- 7155 ESS- 7156 LLD Location E-01 E-05 E-06 Gross Beta 6.83 f 1.19 < 1.75 9.34 f 1.12 < 1.45 8.4721.13 ~ 1 . 5 4 2.0 Collection Date 1011312011 1011312011 Lab Code ESS- 7157 ESS- 7158 Annual Location E-12 E-33 Mean s.d.

Gross Beta 7.05 f 1.16 < 1.69 8.08 f 1.26 < 1.83 2.0 8.61 f 1.27

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

MDC MDC MDC Collection Date 5/23/2011 5/23/20 11 5/23/2011 Req.

Lab Code ESO- 3201 ESO- 3202 ESO- 3203 LLD Location E-01 E-02 E-03 Gross Beta 10.67 m 1.25 < 1.52 33.41

• 1.51 < 1.40 28.60 !i 1.44 < 1.38 2.0 Collection Date 5/23/2011 512312011 5/23/2011 Lab Code ESO- 3204 ESO- 3205 ESO- 3206 Location E-04 E-06 E-08 Gross Beta - 30.12 f 1.74 < 1.74 14.37 f 1.25 < 1.44 20.49 f 1.50 < 1.68 2.0 Collection Date 5/23/2011 5/23/2011 Lab Code ESO- 3207 ESO- 3208 Location E-09 E-20 Gross Beta 33.30 f 1.38 < 1.24 32.63 f 1.38 < 1.24 2.0

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

MDC MDC MDC Collection Date 10/27/2011 10/27/2011 10/27/2011 Req.

Lab Code ESO- 7522 ESO- 7523 ESO- 7524 LLD Location Gross Beta Collection Date I0/27/2011 10/27/2011 10/27/2011 Lab Code ESO- 7525 ESO- 7526 ESO- 7527 Location Gross Beta Collection Date 10/27/2011 10/27/2011 Lab Code ESO- 7528 ESO- 7529 Annual Location E-09 E-20 Mean s.d.

Gross Beta

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

MDC MDC MDC Location E-01 E-03 Collection Date 5/23/2011 5/23/2011 Lab Code EG- 3176 EG- 3178 EG- 3179 Req. LLD Ratio (wetldry) 4.16 6.03 5.29 Gross Beta 8.26 f 0.19 < 0.062 6.74 f 0.15 8.25 f 0.17 Be-7 1.12 f 0.17 2.32 f 0.23 0.82 f 0.15 K-40 4.99 f 0.40 4.15 f 0.38 5.85 f 0.40 1-131 0.000 f 0.006 < 0.023 -0.006 f 0.007 0.003 f 0.006 CS-134 0.010 f 0.007 < 0.011 0.012 f 0.007 -0.001 f 0.006 CS-137 0.008 f 0.007 < 0.012 0.019 f 0.008 0.007 f 0.008 Other (Co-60) -0.002 f 0.007 < 0.010 -0.002 f 0.008 -0.003 f 0.007 Location E-04 E-06 E-08 Collection Date 5/23/2011 512312011 5/23/2011 Lab Code EG- 3180 EG- 3181 EG- 3182 Req. LLD Ratio (wetldry) 5.24 5.55 4.01 Gross Beta 8.38 f 0.18 < 0.055 8.33 f 0.17 < 0.052 10.92 f 0.31 Be-7 0.69 f 0.16 0.56 f 0.14 K-40 5.37 f 0.40. 6.62 f 0.46 1-131 0.006 f 0.006 < 0.020 0.010 f 0.008 < 0.029 CS-134 0.001 f 0.007 < 0.011 0.004 f 0.008 < 0.015 CS-137 0.005 f 0.008 < 0.014 -0.003 f 0.009 < 0.015 Other (Co-60) -0.003 f 0.009 < 0.009 0.001 f 0.010 < 0.013 Location E-09 E-20 Collection Date 5/23/2011 5/23/2011 Lab Code EG- 3183 EG- 3184 Req. LLD Ratio (wetldry) 4.44 4.80 Gross Beta 8.76 f 0.24 < 0.073 8.67 f 0.25 < 0.080 Be-7 0.78 f 0.12 0.66 f 0.19 K-40 6.44 f 0.37 6.31 f 0.50 1-131 0.004 f 0.004 < 0.015 -0.006 f 0.008 < 0.037 Cs-134 0.009 f 0.005 < 0.010 0.010 f 0.009 < 0.013 CS-137 0.004 f 0.007 < 0.012 -0.008 f 0.010 < 0.010 Other (Co-60) 0.001 f 0.007 < 0.006 0.008 + 0.011 < 0.014

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

MDC MDC MDC Location E-01 E-02 E-03 Collection Date 712812011 712812011 712812011 Lab Code EG- 5123 EG- 5124 EG- 5126 Req. LLD Ratio (wetldry) 2.77 3.03 2.64 Gross Beta 5.41 + 0.21 7.48 f 0.20 < 0.088 6.16 f 0.21 Be-7 2.42 f 0.26 3.04 f 0.36 1.44 f 0.26 K-40 4.91 f 0.47 5.21 f 0.52 5.16 f 0.52 1-131 -0.007 f 0.009 0.012 f 0.010 < 0.030 0.000 f 0.010 CS-134 0.013 f 0.009 0.002 f 0.010 < 0.020 -0.006 f 0.010 Cs-137 0.004 f 0.012 0.008 f 0.013 < 0.022 0.009 f 0.012 Other (Co-60) 0.008 f 0.012 0.005 f 0.012 < 0.015 0.010 f 0.012 Location E-04 E-06 E-08 Collection Date 712812011 7/28/2011 712812011 Lab Code EG- 5127 EG- 5128 EG- 5129 Req. LLD Ratio (wetldry) 2.30 2.34 2.14 Gross Beta 4.87 f 0.19 4.14 f 0.09 < 0.036 7.08 f 0.23 Be-7 2.31 f 0.26 0.76 f 0.23 2.02 f 0.25 K-40 3.23 f 0.40 3.01 f 0.46 5.93 f 0.51 1-131 0.009 f 0.009 -0.008 f 0.01 1 < 0.036 -0.003 f 0.008 Cs-134 -0.003 f 0.009 -0.003 f 0.01 1 < 0.01 9 0.003 f 0.008 CS-137 0.012 f 0.010 0.016 + 0.014 < 0.025 0.004 f 0.01 1 Other (Co-60) 0.001 f 0.010 0.020 f 0,011 < 0.014 -0.006 f 0.010 Location E-09 E-20 Collection Date 712812011 712812011 Lab Code EG- 5130 EG- 5131 Req. LLD Ratio (wetldry) 2.46 3.78 Gross Beta 7.87 f 0.26 7.09 f 0.23 < 0.089 Be-7 1.87 f 0.25 2.76 f 0.29 K-40 6.67 f 0.58 6.12 f 0.52 1-131 0.004 f 0.009 0.013 f 0.008 < 0.033 CS-134 -0.004 f 0.008 0.009 f 0.009 < 0.016 CS-137 0.012 f 0.012 0.001 f 0.012 < 0.020 Other (Co-60) -0.010 f 0.012 0.002 f 0.010 < 0.012

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

MDC MDC MDC Location E-01 E-02 E-03 Collection Date 9/29/2011 9/29/2011 9/29/2011 Lab Code EG- 6504 EG- 6505 EG- 6506 Req. LLD Ratio (wet/dry) 3.08 2.97 3.85 Gross Beta 5.50 f 0.19 < 0.078 5.55 f 0.23 7.26 f 0.23 Be-7 5.39 f 0.38 4.41 f 0.37 5.15 f 0.42 K-40 5.69 f 0.55 3.96 f 0.46 6.10 f 0.61 1-131 0.020 f 0.011 < 0.043 0.002 f 0.010 -0.001 f 0.01 1 CS-134 -0.012 f 0.010 < 0.015 -0.007 f 0.008 -0.002 f 0.010 CS-137 0.013 f 0.015 < 0.023 0.009 f 0.013 -0.005 f 0.012 Other (Co-60) 0.011 f 0.013 < 0.012 0.005 f 0.01 1 0.030 f 0.015 Location E-04 E-06 E-08 Collection Date 9/29/2011 9/29/2011 9/29/2011 Lab Code EG- 6507 EG- 6508 EG- 6509 Req. LLD Ratio (wetldry) 2.64 1.93 1.98 Gross Beta 5.39 f 0.22 < 0.103 4.06 -1 0.13 < 0.042 3.68 f 0.16 Be-7 K-40 5.60 4.52

• f 0.46 0.40 3.01 2.88 f 0.32 f 0.38 8.85 f 0.46 1.94 f 0.31 1-131 0.000 f 0.010 < 0.037 -0.003 f 0.009 < 0.031 0.003 f 0.010 (3-134 0.004 f 0.008 < 0.016 0.002 f 0.010 < 0.021 0.000 f 0.007 CS-137 0.019 f 0.011 < 0.020 0.003 f 0.012 < 0.020 -0.002

• 0.010 Other (Co-60) 0.002 f 0.01 1 < 0.015 -0.017 + 0.012 < 0.009 0.002 f 0.008 Location E-09 E-20 Collection Date 9/29/2011 912912011 Lab Code EG- 6510 EG- 6511 Req. LLD Ratio (wet/dry)

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

Beta Annual Mean + s.d. 6.81 f 1.82 Be-7 Annual Mean + s.d. 2.68 + 2.05 K-40 Annual Mean + sad. 5.04 f 1.30 1-131 Annual Mean + s.d. 0.002 f 0.007 Cs-I34 Annual Mean + s.d. 0.001 f 0.007 Cs-137 Annual Mean + s.d. 0.006 f 0.007 Co-60 Annual Mean + s.d. 0.002 f 0.009

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 06-17-11 MDC 06-17-11 MDC Req.

Lab Code ESL- 3860 ESL- 3861 LLD Location E-05 E-12 Ratio (wet wt./dry wt.) 6.30 6.23 Gross Beta 5.00 i 0.27 < 0.21 2.80 f 0.19 < 0.17 0.25 Be-7 1.37 2 0.1 7 +

2.14 0.53 K-40 3.33 k 0.26 0.96 k 0.50 CO-58 0.000 f 0.005 < 0.009 +

0.093 0.044 c 0.035 0.25 CO-60 0.010 f 0.007 < 0.010 0.284 ). 0.043 < 0.040 0.25 Cs-134 0.003 r 0.004 < 0.008 -0.022 f 0.016 < 0.026 0.25 CS-137 0.01 1 F 0.006 < 0.010 +

0.004 0.025 < 0.047 0.25 Collection Date 08-11-11 08-11-11 Req.

Lab Code ESL- 5506 ESL- 5507 LLD Location E-05 E-12 Ratio (wet wt./dry wt.) 3.88 2.48 Gross Beta 5.59 f 0.22 < 0.20 +

5.86 0.24 < 0.20 0.25 Be-7 +

2.05 0.10 +

2.84 0.34 K-40 3.19 f: 3.19 +

4.27 0.50 CO-58 0.000 f: 0.003 c 0.006 +

0.012 0.014 < 0.032 0.25 Co-60 +

0.007 0.003 < 0.005 +

0.002 0.017 c 0.032 0.25 Cs-134 0.004 f 0.003 < 0.005 +

0.016 0.013 < 0.024 0.25 Cs-137 +

0.023 0.006 < 0.006 +

0.042 0.019 < 0.034 0.25 Collection Date 10-05-11 10-05-11 Req.

Lab Code ESL- 6678 ESL- 6679 LLD Annual Location E-05 E-12 Mean s.d.

Ratio (wet &./dry wt.) 5.74 5.34 Gross Beta 3.66 f 0.24 < 0.22 4.02 -1 0.25 < 0.21 0.25 Be-7 1.23 st: 0.08 0.87 2 0.07 K-40 2.01 f 0.1 I +

2.40 0.10 (20-58 -0.001 f 0.002 < 0.004 -0.001 r 0.002 < 0.003 0.25 Co-60 0.002 i 0.003 < 0.004 0.003 r 0.002 < 0.004 0.25 Cs-134 0.002 r 0.002 < 0.004 0.000 f 0.002 < 0.004 0.25 CS-137 0.020 f 0.007 < 0.006 +

0.010 0.004 < 0.005 0.25

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation LLD17days: c Im W L D Ist. Quarter, 2011 Date Annealed: 12-13-10 Days in the field 90 Date Placed: 01-05-11 Days from Annealing Date Removed: 04-05-1I to Readout: 123 Date Read: 04-15-11 Days in mR/Stnd Qtr Location Field Total mR Net mR (91 days) Net mR per 7 days Indicator E-1 90 14.1 f 0.6 9.9 f 0.7 14.3 + 0.6 0.77 f 0.05 Control E-20 90 18.2 k 1.0 14.0 f 1.O 18.2 f 1.0 1.09 + 0.08 In-Transit Ex~osure Date Annealed 12-13-10 03-10-11 Date Read 01-11-11 04-15-11 Total mR ITC-1 +

3.8 0.2 4.6 k 0.1 ITC-2

• 3.7 0.2

• 4.7 0.1

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation 2nd Quarter, 2011 Date Annealed: 03-10-11 Days in the field 93 Date Placed: 04-05-11 Days from Annealing Date Removed: 07-07-11 to Readout: 127 Date Read: 07-15-11 Days in mWStnd Qtr Location Field Total mR Net mR (91 days) Net mR per 7 days Indicator E-I 93 17.4 f 0.8

• 12.1 1.0 17.0 f 0.8 0.91 f 0.07 E-2 93 23.8 f 1.0 18.5 f 1.1 23.3 f 1.0

• 1.39 0.09 E-3 93 25.6 f 1.7 20.3 f 1.8 25.1 f 1.6 1.53 f0.13 E-4 93 20.5 4 0.4 15.2 f 0.7 20.1 f 0.4 1.15 f 0.05 E-5 93 22.8 f 0.7 17.5 f 0.9

• 22.3 0.7 1.32 f 0.07 E-6 93 20.3 f 0.8 15.0 f 1.0 19.9 f 0.8 1.I3 f 0.07 E-7 93 19.8 f 0.3 14.5 f 0.6 +

19.4 0.3 1.09 f 0.05 E-8 93 20.4 f 0.9 15.1 f 1.I 20.0 0.9 +

1.14 0.08 E-9 93 22.7 f 1.0 17.4 f 1.I

• 22.2 1.O 1.31 f 0.09 E-12 93 15.9 k 0.5 10.6 rt 0.7 15.6 f 0.5

• 0.80 0.06 E-I4 93 21.5 f 1.7 +

16.2 1.8 21.O f I.6 1.22 rt0.13 E-15 93 24.9 f 1.2 19.6 f I.3 24.4 f 1.2 1.48 f 0.10 E-16 93 19.7 f 0.7 14.4 f 0.9 19.3 f 0.7 1.09 f 0.07 E-17 93 20.3 f 1.3

• 15.0 1.4

• 19.8 1.3 1.13 fO.11 E-18 93 21.9 rt0.6 16.6 f 0.8 21.4 k 0.6 1.25 f 0.06 E-22 93 21.6 f 0.4 16.3 f 0.7 21.If 0.4 1.23 f 0.05 E-23 93 +

23.5 0.8

• 18.2 1.0 23.0 rt 0.8 1.37 f 0.07 E-24 93 21.1 f 0.4 15.8 f 0.7 20.6 f 0.4 1.19 f0.05 E-25 93 23.0 f 0.3 17.7 0.6 22.5 f 0.3 1.33 f 0.05 E-26 93 19.2 & 0.8 13.9 f 1.0 +

18.8 0.8 1.05 f 0.07 E-27 93

• 24.2 1.0

• 18.9 1.1 +

23.7 1.0 1.42 f 0.09 E-28 93 +

16.4 0.4 11.1 f 0 . 7 16.1 k0.4

• 0.84 0.05 E-29 93 17.0 f 0.7 11.7 f 0 . 9 16.7 f 0.7

• 0.88 0.07 E-30 93 19.8 f 0.8 14.5 f 1.0 19.3 f 0.8 1.09 f 0.07 E-31 93

• 22.9 2.1 17.6 f 2 . 2 22.4 f 2.1 +

1.33 0.16 E-32 93 23.0 f 0.3

• 17.7 0.6 22.5 f 0.3 1.33 f 0.05 E-38 93

• 19.8 0.2

• 14.5 0.6 19.2 f 0.2 1.09 f 0.04 E-39 93 18.7 f 0.5

• 13.4 0.7 18.1 f 0.5 1.01 f 0.06 E-41 93 20.3 f 0.6 15.0 k 0.8 19.6 f 0.5 1.13 f 0.06 E-42 93 NDa E-43 93 18.9

• 0.6 13.6 f 0.8 18.5

• 0.6 1.03

• 0.06 Control E-20 92 20.2 f 0.8 14.9 f 1.0 20.0 f 0.8 1.14 f 0.07 In-Transit Exposure Date Annealed 03-10-11 06-03-11 Date Read 04-15-11 07-15-11 Total mR ITC-1 4.6 rt 0.1 6.0 f 0.5 ITC-2 +

4.7 0.1 5.8 f 0.2 a "ND" = NOdata; see Table 2.0, Listing of Missed Samples. 'Placed 04-06-11.

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation 3rd Quarter, 201 1 Date Annealed: 06-03-11 Days in the field 92 Date Placed: 07-07-11 Days from Annealing Date Removed: 10-07-11 to Readout: 137 Date Read: 10-18-11 Days in mRlStnd Qtr Location Field Total mR Net mR (91 days) Net rnR per 7 days Indicator E-I Control E-20 92 20.7 f 0.8 15.5 k 1.0 20.4 1.0.8 1.18 It: 0.08 In-Transit Exposure Date Annealed 06-03-11 09-16-1I Date Read 07-15-11 10-18-11 Total mR ITC-1 6.0 f 0.5 4.5 f 0.2 ITC-2 5.8 k 0.2 +

4.5 0.1

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

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation 4th Quarter, 2011 Date Annealed: 09-16-1 1 Days in the field Date Placed: 10-07-11 Days from Annealing Date Removed: 01-06-12 to Readout:

Date Read: 01-12-12 Days in rnRlStnd Qtr Location Field Total mR Net mR (91 days) Net mR per 7 days lndicator E-I 91

• 16.2 0.6

• 12.5 0.7

• 16.2 0.6

• 0.96 0.05 E-2 91

• 22.1 1.0 18.4 f 1.1

• 22.1 1.o

• 1.41 0.08 E-3 91 24.1 ir 1.5 20.4 4 1.5

• 24.1 1.5

• 1.57 0.12 E-4 91 19.4 ir 0.4

• 15.7 0.5

• 19.4 0.4

• 1.21 0.04 E-5 91

• 21.3 0.4 17.6 rt 0.5

• 21.3 0.4

• 1.35 0.04 E-6 91

• 19.0 0.4 15.3 f 0.5

• 19.0 0.4 1.I

• 8 0.04 E-7 91 18.5 ir 0.5

• 14.8 0.6

• 18.5 0.5

• 1.14 0.05 E-8 91 19.3 rt 0.8

• 15.6 0.9

• 19.3 0.8

• 1.20 0.07 E-9 91

• 21.8 0.8

• 18.1 0.9

• 21.8 0.8

• 1.39 0.07 E-12 91

• 15.5 0.9 11.8 k1.0 15.5 It 0.9

• 0.91 0.07 E-14 91

• 19.0 0.2

• 15.3 0.4

• 19.0 0.2 1.18 k0.03 E-15 91 22.4 ir 1.O

• 18.7 1.1

• 22.4 1.O

• 1.44 0.08 E-I 6 91 18.5 0.6

• 14.8 0.7

• 18.5 0.6 1. I 4 i 0.05 E-17 91

• 19.1 1.2

• 15.4 1.3 19.1 -1 1.2 1.18 kO.10 E-18 91

• 21 .O 0.3

• 17.3 0.5 21.O ir 0.3

• 1.33 0.04 E-22 91 20.7 0.6

• 17.0 0.7

• 20.7 0.6 1.31 0.05 E-23 91

• 21.8 0.5 18.1 20.6

• 21.8 0.5

• 1.39 0.05 E-24 91

• 19.4 0.6

• 15.7 0.7

• 19.4 0.6

• 1.21 0.05 E-25 91

• 20.5 0.5

• 16.8 0.6 20.5 0.5 1.29 ir 0.05 E-26 91

• 17.7 0.7

• 14.0 0.8

• 17.7 0.7

• 1.08 0.06 E-27 91

• 22.4 1.O 18.7 k 1.I

• 22.4 1.O

• 1.44 0.08 E-28 91 +

15.4 0.2 11.7 zt 0.4

• 15.4 0.2

• 0.90 0.03 E-29 91

• 15.6 0.7

• 11.9 0.8

• 15.6 0.7

• 0.91 0.06 E-30 91

• 18.2 0.4 14.5 rt 0.5

• 18.2 0.4 1.I

• 1 0.04 E-31 91

• 21.7 1.6 18.0 rt 1.6

• 21.7 1.6

• 1.38 0.13 E-32 91

• 21.4 0.2

• 17.7 0.4

• 21.4 0.2

• 1.36 0.03 E-38 91

• 18.3 0.4 14.6 ir 0.5

• 18.3 0.4

• 1.12 0.04 E-39 91

• 18.0 0.6 14.3 ir 0.7

• 18.0 0.6 1. I 0 5 0.05 E-4 1 91

• 19.2 1.3

• 15.5 1.3

• 19.2 1.3

• 1.19 0.10 E-42 91 18.5 k 0.7

• 14.8 0.8 18.5 It 0.7 *

1. I 4 0.06 E-43 91 17.7 0.7

• 14.0 0.8

• 17.7 0.7

• 1.08 0.06 Control E-20 91 19.0

• 1.3 15.3

• 1.3 19.0

• 1.3 1.I8

• 0.10 In-Transit Exposure Date Annealed 09-16-11 12-19-11 Date Read 10-18-11 01-12-12 Total mR ITC-1

• 4.5 0.2

• 3.0 0.2 ITC-2

• 4.5 0.1

• 2.9 0.2 Annual Indicator Mean1s.d. 19.5 f 3.6 14.9 f 3.4 19.2 f 2.6 1.1 10.3 Annual Control Meanfs.d. 19.5 f 1.1 14.9 f 0.7 19.4 + 1.0 1.1 10.0 Annual IndicatorIControl Mean+s.d. 19.5 3.5 14.9 + 3.4 19.2 + 2.6 1.1 k0.3

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

Intermittent Streams Sample ID GW-01 GW-02 Collection MDC Collection MDC Date Lab Code Tritium (pCilL) @cn) Date Lab Code Tritium (pCilL) (pci) 01-27-11 NSa 01-27-11 NSa 02-23-11 NSa 02-23-11 NSa 03-02-11 NS~ 03-02-11 NS~

04-26-11 EWW- 2487 72 f 86 c 166 04-26-11 EWW- 2488 322 f 97 c 166 05-23-11 EWW- 3169 94 f 78 c 140 05-23-11 EWW- 3190 130 i80 < 140 06-29-11 EWW- 4229 53f81 ~ 1 4 9 06-29-11 EWW- 4230 217 f 89 c 149 07-28-11 EWW- 5161 99 f 89 < 171 07-28-1 1 EWW- 5162 88 f 89 , c 171 08-30-11 EWW- 5817 85 f 95 < 150 08-30-11 EWW- 5818 133 f 97 c 150 09-28-11 EWW- 6565 63575 <I44 09-28-11 EWW- 6566 156 f 80 c 144 10-27-11 EWW-7516 191f84 <I42 10-27-11 EWW-7518 185f84 el42 12-01-11 EWW- 8431 89 f 89 c 162 12-01-11 EWW- 6433 214 f 95 c 162 12-28-11 EWW- 8969 39f78 <I44 12-28-11 EWW- 8990 259 f 88 < 144 Mean + s.d. 94 i 46 Mean + s.d. 176 f 77 Sample ID GW-03 GW-17 Collection MDC Collection MDC Date Lab Code Tritium (pCilL) (~CIIL) Date Lab Code Tritium (pCilL) (pci) 01-27-1 1 NSa 01-27-11 NSa 02-23-11 NSa 02-23-11 NSa 03-02-11 NS~ 03-02-11 NS~

04-26-11 EWW- 2489 179 f 91 c 166 0330-11 EWW- 1449 422 f 96 c 146 05-23-11 EWW- 3191 85 f 78 c 140 04-26-11 EWW- 2491 393 f 100 c 166 06-29-11 EWW-4231 109 f 84 < 149 05-23-11 EWW- 3193 132 f 80 c 140 07-28-11 EWW- 5163 -21 f 84 c 171 06-29-11 EWW- 4233 184 f 88 c 149 0830-1 1 EWW- 5619 17fQ2 <I50 07-28-11 EWW- 5165 70 f 88 c 171 09-28-11 EWW- 6567 80 f 76 c 144 08-30-11 EWW- 5821 110 f 96 c 150 10-27-11 EWW-7519 122281 <I42 09-28-11 EWW- 6569 71 f 75 < 144 12-01-11 EWW- 8434 14 f 86 c 162 10-27-11 EWW- 7521 251 f 87 c 142 12-28-11 EWW- 8991 80f80 <I44 12-01-11 EWW-8436 269 f 97 c 162 12-28-11 EWW- 8993 142 f 83 < 144 Mean + s.d. 73 f 66 Mean + s.d. 204 f 139 Wells Sample ID GW-04 (EIC Well) GW-11 (MW-1)

Collection MDC Collection MDC Date Lab Code Tritium (pCilL) (pcvl) Date Lab Code Tritium (pCilL) (pcin) 01-27-11 EWW-408 -33 f 66 c 138 01-27-11 EWW- 548 31f73 <I44 03-02-11 EWW- 895 62f76 c152 02-23-11 EWW- 896 102 f 79 c 152 0330-1 1 EWW- 1448 47 f 79 c 146 03-27-11 EWW- 1443 168 f 85 c 146 04-26-11 EWW- 2490 35f84 <I66 04-09-11 EWW- 3194 95 f 79 < 141 05-23-1 1 EWW- 3192 18f75 el40 05-08-11 EWW- 2978 105 f 80 c 141 06-29-11 EWW-4232 -43 f 76 149 06-28-11 EWW- 4314 116 f 78 < 144 07-28-1 1 EWW- 5164 -5284 ~ 1 7 1 07-19-11 EWW-4743 22 f 77 c 144 08-30-11 EWW- 5620 -27 f 90 < 150 08-24-11 EWW-5774 18 f 73 c 150 09-28-1 1 EWW- 6568 19 i 72 < 144 09-25-11 EWW- 6570 90 _+ 91 c 166 10-27-11 EWW- 7520 33f76 <I42 10-09-11 EWW- 7102 31 f 79 c 147 12-01-11 EWW- 6435 51 f 88 c 162 11-25-11 EWW- 8437 101 f 90 c 162 12-28-11 EWW- 8992 23 i 77 c 144 12-23-11 EWW- 8994 60 f 79 c 144 Mean + s.d. 14 f 36 Mean + s.d. 80 f 48 a "NS" = no sample; not sent.

"NS" = no sample; water frozen.

CDuplicateresult = 224i86 pCilL.

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

Wells fcont.)

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

Collection MDC Collection MDC Date Lab Code Tritium (pCilL) (pctk) Date Lab Code Trilium (pCiL) (~CVL) 01-27-11 EWW-549 66f75 <I44 01-27-1 1 EWW- 550 92 f 76 4 144 02-23-11 EWW- 897 12f74 <I52 02-23-1 1 EWW- 898 86 f 78 < 152 03-27-11 EWW- 1444 39f79 <I46 03-27-11 EWW- 1445 114 f 82 < 146 04-09-11 EWW- 3195 Of74 <I41 04-09-11 EWW- 3196 103 f 79 < 141 05-08-11 EWW- 2979 2f74 <I41 05-08-1 1 EWW- 2980 86 f 79 < 141 06-28-1 1 EWW- 431 5 46 f 74 c 144 06-28-1 1 EWW-4316 15 f 72 c 144 07-19-11 EWW- 4745 -26 f 74 c 144 07-19-1 1 EWW- 4746 22 f 77 c 144 08-24-11 EWW- 5776 78 f 81 < 146 08-24-1 1 EWW- 5777 105 f 78 c 150 09-25-1 1 EWW- 6571 -23 f 86 < 166 09-25-1 1 EWW- 6572 15 f 88 c 166 10-09-11 EWW- 7103 5f77 <I47 10-09-11 EWW- 7104 -7 f 77 < 147 11-25-1 1 EWW- 8438 69 f 89 < 162 11-25-11 EWW- 8439 69 f 89 c 162 12-23-11 EWW- 8996 37f76 <I44 12-23-1 1 EWW- 8997 82 f 80 c 144 Mean + s.d. 24 f 37 Mean + s.d. 64 f 44 Sample ID GW-14 (MW-5) GW-15 (MW-4)

Collection MDC Collection MDC Date Lab Code Tritium (pCilL) (pcin) Date Lab Code Tritium (pCilL) (pcfi) 01-27-1 1 EWW- 551 16f72 <I44 01-27-1 1 NSa 02-23-11 EWW- 899 126f80 <I52 02-23-11 EWW- 900 424 f 95 c 152 03-27-11 EWW- 1446 144 f 84 < 146 03-27-1 1 EWW- 1447 394 f 95 < 146 04-09-11 EWW- 3197 24 f 75 < 141 04-09-11 EWW- 3199 313 f 89 < 141 05-08-11 EWW- 2981 26f76 <I41 05-08-1 1 EWW- 2983 263 f 87 < 141 06-28-1 1 EWW- 4317 81 f 76 < 144 06-28-11 EWW- 4318 282 f 86 < 144 07-19-11 EWW- 4747 110 f 81 < 144 07-19-1 1 EWW- 4748 274 f 89 < 144 08-24-1 1 EWW- 5778 18 f 73 < 150 08-24-11 EWW- 5779 230 f 84 c 150 09-25-11 EWW- 6573 134 f 93 c 166 09-25-1 1 EWW- 6574 367 f 103 < 166 10-09-11 EWW- 7105 31 f 79 c 147 10-09-11 EWW- 7106 209 87+ < 147 11-25-11 EWW- 8440 67f88 <I62 11-25-1 1 EWW- 8441 31 1 f 99 < 162 12-23-1 1 EWW- 8998 96 f 81 c 144 12-23-11 EWW- 8999 298 f 90 < 144 Mean + s.d. 71 f 51 Mean + s.d. 307 2 70 Sample ID GW-16 (MW-3)

Collection MDC Date Lab Code Tritium (pCi1L) (pci) 01-27-11 NSa 02-23-1 1 NS~

03-27-11 NS~

04-09-11 EWW- 3200 244 f 86 c 141 05-08-1 1 NSa 06-28-11 EWW-4319 198 f 82 < 144 07-19-1 1 EWW- 4749 221 f 87 c 144 08-24-1 1 EWW- 5760 179 f 82 c 150 09-25-1 1 EWW- 6575 161 f 94 c 166 10-09-11 EWW- 7107 193 f 87 < 147 11-25-1 1 EWW- 8442 148 f 92 c 162 12-23-11 EWW- 9000 225 f 87 < 144 Mean + s.d. 192 f 33 a " N S = no sample; not sent.

b " ~ ~no' sample;

= location frozen.

POINT BEACH NUCLEAR PLANT Table 13. GroundwaterTritiurnMonitoring Program (Monthly Collections)

~ n i i=

s pCilL .

Beach Drains Sample ID Colleclion MDC Collection MDC Date Lab Code Tritium (pCi1L) (PCIK) Date Lab Code Tritium (pCilL) (~CVL) 01-06-11 EW- 65 322 i 97 < 137 EW- 67 282 f 96 c 137 02-16-11 EW- 625 408 f 97 < 147 EW- 626 1268f 130 <I47 03-10-11 EW- 1026 2360 f 164 c 154 EW- 1027 1382f 135 <I54 04-08-1 1 EW- 1921 391 f 95 ' < 145 EW- 1922 378f106 <I52 05-05-11 EW- 2697 333 f 91 < 143 EW- 2698 430 f 95 < 143 06-09-11 EW- 3673 237 k 88 < 144 EW- 3674 +

663 106 c 144 07-07-11 EW- 4312 224 f 83 c 144 EW- 4313 374 f 90 < 144 08-11-1 1 EW- 5445 221 f 98 c 145 EW- 5446 557f111 <I45 09-08-11 EW- 6059 220 f 98 < 145 EW- 6061 312 f 101 < 145 10-04-11 EW- 6680 197 f 82 < 144 EW- 6681 817 f 108 c 144 11-11-11 EW- 7941 123 f 79 < 147 EW- 7942 373 f 91 < 147 12-10-11 EWW- 8844 151 f 83 < 144 EWW- 8845 298 f 90 < 144 Mean + s.d. 432 f 614 Mean + s.d. 595 f 377

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

Units = pCilL Beach U r a ~ n s Sample ID S-7 5-8 Collection MDC Collection MDC Date Lab Code Tritium (pCiR) (pcii) Date Lab Code Tritium (pCilL) (pci) 01-03-11 NSa 01-03-11 NSa 02-16-11 NSa 02-16-11 NSa 03-10-11 NSa 03-10-1 1 NSa 04-08-11 NSa 04-08-11 NSa 05-05-11 NSa 05-05-11 NSa 06-09-1 1 NSa 06-09-11 NSa 07-07-11 NSa 07-07-11 NSa 08-11-11 NSa 08-11-11 NSa 09-06-11 NSa 09-08-11 NSa 10-04-11 NSa 10-04-11 NSa 11-11-11 NSa 11-11-11 NSa 12-10-11 NSa 12-10-11 NSa Mean + s.d. Mean + s.d.

Sample ID S-9 S-10 Collection MDC Collection MDC Date Lab Code Tritium (pCilL) (pcn) Date Lab Code Tritium (pCilL) (pcm) 01-03-1 1 NSa 01-03-1 1 NSa 02-16-11 EW- 628 651f107 <I47 02-16-11 NSa 03-10-1 1 EW-1028 199f.87 <I54 03-10-11 NSa 0408-11 NSa 04-08-11 NSa 05-05-1 1 NSa 05-05-11 NSa 06-09-1 1 NSa 06-09-11 NSa 07-07-11 NSa 07-07-11 NSa 08-1 1-11 NSa 08-11-11 NSa 09-08-11 NSa 09-08-11 NSa 10-04-11 NSa 10-04-11 NSa 11-11-11 NSa 11-11-11 NSa 12-10-11 NSa 12-10-11 NSa Mean + s.d. Mean + s.d.

Sample ID S-I I Collection MDC Date Lab Code Tritium (pCi1L) (pcm)

NSa NSa NSa EW- 1923 96f96 <I52 NSa NSa NSa NSa EW- 6062 117 f. 93 < 145 EW- 7943 122 f 80 < 148 NSa 12-10-11 NS' Mean + s.d. 111 f 14 Mean + s.d a ,*

NS"= no sample; not sent.

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program Units = pCilL U2 F a ~ a d eSubsurface Drain Sump Collection Collection Date Lab Code Tritium (pCiIL) MDC Date Lab Code Tritium (pCilL) MDC (pCilL) (PCIL) 01-03-11 EW- 105

• 631 110 c 138 01-10-11 EW-106 605f109 el38 01-17-11 EW- 409 663 4 97 c 138 01-24-11 EW-410 411f87 <I38 01-31-11 EW- 693

• 550 101 < 141 02-07-11 EW- 694 628 f 104 < 141 02-14-11 EW- 700 719 i 108 c 141 02-21-11 EW- 701 661 f 105 < 141 02-28-11 EW-1023 591f106 <I54 03-07-11 EW-1024 490f101 el54 03-14-11 EW-3185 557i100 <I42 03-21-11 EW- 2142 654 i 104 < 141 03-28-11 EW- 2143 536 f 99 < 141 04-04-11 EW- 2145 683 f 105 c 141 04-11-1I EW- 2146 584 f 101 < 141 04-18-1 1 EW- 3186 528 i 98 c 141 04-25-11 EW- 3187 508 f 97 c 141 05-02-11 EW- 3188 666 f 103 < 140 05-09-11 EW-3120 450i101 el38 05-16-11 EW- 3121 658 f 108 < 138 05-22-11 EW- 3862

• 504 101 < 147 05-30-11 EW- 3863 641 f 106 < 146 06-06-11 EW- 3864 499 f 100 c 146 06-13-11 EW- 3866 540 f 102 c 146 06-20-11 EW- 4911 183 90* < 155 06-27-11 EW-4912 570f107 <I54 07-04-11 EW- 4913 715 f 112 < 154 07-11-11 EW- 4914 576 i 110 c 164 07-18-11 EW- 5537 650 f 105 c 144 07-25-11 EW- 5539 839 i112 c 144 08-01-11 EW- 5540 505 f 99 < 144 08-08-11 EW- 5541 371 5 93 < 143 08-15-11 EW- 6143 463 f 106 < 142 08-22-11 EW- 6144 513 f 108 c 142 08-29-11 EW- 6145 446 f 105 < 142 09-05-11 EW- 6146

• 488 107 < 142 09-12-11 EW- 7097 567 f 102 < 146 09-19-11 EW- 7098 587 i 103 c 146 09-26-11 EW- 7100 603 f 104 < 147 10-03-11 EW- 7101 467 f 99 < 147 10-10-1 1 EW- 7751 545 f 102 c 147 10-17-11 EW- 7752

• 394 96 c 147 10-24-11 EW- 7753 596 f 104 < 147 10-31-11 EW- 7754

• 592 104 < 147 11-07-11 EW- 8304 404 96* < 146 11-14-11 EW- 8305 479 f 99 < 146 11-21-11 EW- 8853 321 f 92 < 145 11-28-11 EW- 8854 545 f 101 < 144 12-16-11 EW- 9104 437 5 98 < 148 Mean + s.d. 538 f 137

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program Manholes Sample ID MH Z-065A MH 2-0658 Collection Collection Date Lab Code Tritium (pCilL) ~ o c Date Lab Code Tritium (pCi1L) MDC

( P C ~ (PCW Mean + s.d. Mean + s.d.

Sample ID MH 2-065C MH 2-065D Collection Lab Code Tritium (pCi,L) MDC Collection Lab Code Tritium (pCi1L) MDC Date (PciiL) Date ( P C ~

Mean + s.d. Mean + s.d Sample ID MH 2-066A MH 2-066B Collection Lab Code Tritium (pCilL) MDC Lab Code Tritium (pCilL) M E Date (PCW Date (PC~L) 04-05-11 EW- 1913 258 f 89 c 145 04-06-11 EW- 1914 711 f 108 c 145 09-28-11 EW- 6576 116 f 92 c 166 09-27-11 EW- 6577

• 108 92 c 166 12-02-11 EW- 8846

• 114 81 < 152 12-02-11 NSa Mean + s.d. Mean -+ s.d. 410 f 426 Sample ID MH Z-066C MH 2-066D Collection Lab Code Collection Lab Code Tritium (pCilL) MDC Tritium (pCilL) MDC Date (PCI/L) Date (PC"'-)

04-06-11 EW- 1915 242 f 88 < 145 04-06-11 EW-1916 485+99 <I45 09-27-11 EW- 6578

• 62 90 < 166 09-27-11 EW- 6579

• 288 100 c 166 12-02-11 NS~ 12-02-1I NS~

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

Sample ID MH Z-067A MH 2-0678 Collection Lab Code Tritium (pCilL) MDC Collection Lab Code Tritium (pCilL) MoC Date (PCW Date (PCW 04-06-11 EW- 1917 160 f 84 c 145 04-06-11 EW-1918 456*97 c145 09-28-11 EW- 6581

• 90 91 < 166 09-27-11 EW- 6582 90 f 91 c 166 12-02-11 EW- 8847

• 117 82 c 144 12-02-11 NSa Mean + s.d. Mean + s.d. 273 f 259 a "NS" = NOsample; not sent.

POINT BEACH NUCLEAR PLANT Manholes (cont.)

Sample ID MH 2-067C MH 2-067D Collection Lab Code Tritium (pCiIL) MDc Collection Lab Code Tritium (pCilL) MDc Date (PCW Date (pcln) 04-06-11 EW-1919 287*90 <I45 04-06-11 NSa 09-27-11 EW- 6583 62 90* < 166 09-27-11 EW- 6584

• 280 99 c 166 12-02-11 NSa 12-02-11 NSa Mean + s.d. 174

• 159 Mean + s.d.

Sample ID MH 2-068 MH-3 Colleclion , -, ,-,-

LdU ClUUG

'ilium I

(-P:,I

,p,IfLJ

\ ~ ~ n r Collection , -,,-,- Tritium (pCi1L) MDc Date (PC~IL) Date (PCW 04-06-11 EW- 1920 454

• 97 < 145 04-06-11 09-27-11 EW- 6585 199

• 82 < 144 09-27-11 12-02-11 EW- 8848 253

• 88 < 144 12-02-11 Mean + s.d. 302 5 134 Mean + s.d.

Sample ID MH-4 MH-6 Coliection Lab Code Tritium (pCilL)

Collection Lab Code MDC Tritium'(pCi1L) MDC Date (pCi/L) Date (PC'~

NSB NSa NS" Mean + s.d. Mean + s.d.

Sample ID MH-7 MH-8 Collection Lab Code Tritium (pCi1L) MDC Collection Lab Code Tritium (pCIIL) MDC Date (pCi/L) Date (PC'W Mean + s.d. Mean + s.d.

I llllUlll (pl Date Mean + s.d. Mean + s.d.

Sample ID MH-5A MH-9 Collection Collection Lab Code Tritium (pCL li) MDC Lab 'Ode Tritium (pClIL) MDC Date (PC'~ Date (PC'~

04-06-11 09-27-11 12-02-11 Mean + s.d. Mean + s.d.

a " N S = No sample; not sent.

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

Units = pCilL Quarterly Wells Sample ID GW-05 (WH 6 Well) GW-06 (SBCC Well)

Collection MDC Collection MDC Date Lab Code Tritium (pCilL) (pci/L) Date Lab Code Tritium (pCilL) (pCi/L) 01-12-11 EWW- 124 -28 i 82 < 138 01-12-11 EWW- 125 -14 i 83 < 138 04-19-11 EWW- 2232 -18 i 74 < 142 04-19-11 EWW- 2233 -4 i 75 < 142 07-14-11 EWW-4617 5i73 ~ 1 4 8 07-14-11 EWW- 4619 41 i 75 < 148 10-13-11 EWW- 7095 2 i 76 < 145 10-13-1 1 EWW- 7096 -63 f 73 < 145 Mean + s.d. -10 f 16 Mean + s.d. -10 t 43 Sample ID GW-09 1Z-361A GW-09 12-3618 Collection MDC Collection MDC Date Lab Code Tritium (pCilL) (pCi/L) Date Lab Code Tritium (pCi1L) (pCi/L)

EWW- 697 EWW- 698 EWW- 2970 EWW- 2971 EWW- 2974 EWW- 2975 EWW- 3122 EWW- 3123 EWW- 4751 EWW- 4752 EWW- 5447 EWW- 5449 EWW- 6139 EWW- 6140 EWW- 7755 EWW- 7757 EWW- 8849 EWW- 8850 Mean + s.d. 256 k 73 Mean + s.d. 106 i 64 Sample ID GW-10 2Z-361A GW-10 22-361B Collection MDC Collection MDC Date Lab Code Tritium (pCi1L) (pcu~) Date Lab Code Tritium (pCilL) (pci/~)

EWW- 699 EWW- 2972 EWW- 2973 EWW- 2976 EWW- 2977 EWW- 3124 EWW- 3125 EWW- 4753 EWW- 4754 EWW- 5450 EWW- 5451 EWW- 6141 EWW- 6142 EWW- 7758 EWW- 7759 EWW- 8851 EWW- 8852 Mean + s.d. 20 f 36 Mean + s.d. 107 i 43 Groundwater Tritium Monitoring Program (Annual Collections)

Collection MDC Collection MDC Date Lab Code Tritium (pCi1L) (pCi/L) Date Lab Code Tritium (pCilL) (~c~IL) 05-05-11 EWW- 2762 160 f 84 < 145 05-05-11 EWW- 2763 331 f 92 < 145

'"NS" = No sample; not sent.

Environmental, Inc.

Midwest Laboratory Road NMhbrooR, IL 60062-2310 phone (847) 564-0700 fax (647) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January through December, 2011

Appendix A Interlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems.

Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.

Results in Table A-I were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.

Table A-2 lists results for thermoluminescent dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters, when available, and internal laboratory testing.

Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NlST traceable sources. Data for previous years available upon request.

Table A-4 lists results of the analyses on in-house "blank samples for the past twelve months. Data for previous years available upon request.

Table A-5 lists REMP specific analytical results from the in-house "duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors.

Complete analytical data for duplicate analyses is available upon request.

The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.

Results in Table A-7 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).

Attachment A lists the laboratory precision at the 1 sigma level for various analyses. The acceptance criteria

+

in Table A-3 is set at 2 sigma.

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

Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One standard deviation Analysis Level for single determination Gamma Emitters 5 to 100 pcilliter or kg 5.0 pcilliter

> 100 pcilliter or kg 5% of known value 5.0 pcilliter 10% of known value 5.0 pcilliter 10% of known value Potassium-40 2 0.1 glliter or kg 5% of known value Gross alpha 5.0 pcilliter 25% of known value Gross beta 5.0 pcilliter 5% of known value Tritium *lo,=

169.85 x 10% of known value Radium-226,-228 s 0.1 pcilliter 15% of known value Plutonium s 0.1 pcilliter, gram, or sample 10% of known value 6 pcilliter 10% of known value 6 pcilliter 15% of known value 10 pcilliter 10% of known value Other Analyses , --- 20% of known value a From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-60014-81-004.

Laboratory limit.

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

Concentration (pCilL)

Lab Code Date Analysis Laboratory ERA Control Result Result Limits Acceotance Sr-89 Pass Sr-90 Pass Ba-133 Pass CO-60 Pass Cs-I 34 Pass CS-137 Pass 211-65 Pass Gr. Alpha Pass Gr. Beta Pass 1-131 Pass Ra-226 Pass Ra-228 Pass Uranium Pass H-3 Pass Sr-89 Pass Sr-90 Pass Ba-133 Pass Co-60 Pass CS-134 Fail CS-137 Pass Zn-65 Pass Gr. Alpha Pass Gr. Beta Pass 1-131 Pass Ra-226 Pass Ra-228 Pass Uranium Pass H-3 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

Unless otherwise indicated, the laboratory result is given as the mean f standard deviation for three determinations.

Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.

The sample was reanalyzed. Result of reanalysis was acceptable, 32.9 f 7.4 pCilL.

TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaSO,: Dy Cards).

Lab Code Date Known Lab Result Control Description Value f 2 sigma Limits Acceptance Environmental, Inc.

100 cm. Pass 110 cm. Pass 120 cm. Pass 150 cm. Pass 180 cm. Pass 40 cm. Pass 50 cm. Pass 60 cm. Pass 60 cm. Pass 80 cm. Pass 90 cm. Pass Environmental, Inc.

100 cm. Pass 110 cm. Pass 120 cm. Pass 150 cm. Pass 180 cm. Pass 40 cm. Pass 45 cm. Pass 50 cm. Pass 60 cm. Pass 70 cm. Pass 80 cm. Pass 90 cm. Pass

TABLE A-3. In-House "Spike" Samples Concentration (oCi/Lla Lab Code Date Analysis Laboratory results Known Control 2s, n = l Activity Limits Acceptance SPW-202 U-238 Pass w-20111 Ra-226 Pass W-20711 Gr. Alpha Pass W-20711 Gr. Beta Pass XWW-33 1 Ba-133 Pass XWW-331 Cs-134 Pass XWW-331 Cs-137 Pass XWW-331 H-3 Pass SPAP-567 Gr. Beta Pass SPAP-569 Cs-134 Pass SPAP-569 Cs-137 Pass SPAP-571 H-3 Pass SPW-581 Cs-134 Pass SPW-581 Cs-137 Pass SPW-581 Sr-89 Pass SPW-581 Sr-90 Pass SPMI-583 Cs-I 37 Pass SPMI-583 Sr-90 Pass SPW-602 U-238 Pass SPW-686 Ni-63 Pass SPF-1113 Cs-137 Pass XWW-1602 Ba-133 Pass XWW-1602 CS-134 Pass XWW-I 602 Cs-137 Pass XWW-1602 H-3 Pass Ba-133 Pass Cs-134 Pass Cs-137 Pass H-3 Pass Ra-228 Pass Cs-134 Pass Cs-137 Pass Sr-89 Pass Sr-90 Pass Ra-226 Pass Gr. Alpha Pass Gr. Beta Pass SPAP-4167 7/7/2011 Cs-I 34 6.92 + 1.45 6.57 0.00 - 16.57 Pass SPAP-4167 7/7/2011 Cs-137 108.02 + 2.84 105.80 95.22 - 116.38 Pass SPW-4169 7/7/2011 Cs-134 34.52 + 4.79 32.84 22.84 -42.84 Pass SPW-4169 7/7/2011 Cs-137 58.29 + 6.19 52.92 42.92 - 62.92 Pass

TABLE A-3. In-House "Spike" Samples Concentration ( P C ~ I L ) ~

Lab Code Date Analysis Laboratory results Known Control 2s, n = l Activity Limits Acceptance Sr-89 Pass Sr-90 Pass H-3 Pass Tc-99 Pass Ra-228 Pass Ni-63 Pass Tc-99 Pass C-14 Pass Fe-55 Pass Gr. Alpha Pass Gr. Beta Pass Tc-99 Pass Ra-226 Pass Gr. Alpha Pass Gr. Beta Pass Ra-226 Pass Ba-I33 Pass Cs-134 Pass Cs-137 Pass Ra-226 Pass Gr. Alpha Pass Gr. Beta Pass Ra-228 Pass Cs-I 34 Pass Cs-137 Pass Cs-134 Pass Cs-137 Pass Gr. Beta Pass Cs-134 Pass Cs-137 Pass H-3 Pass Ni-63 Pass Tc-99 Pass Cs-134 Pass Cs-137 Pass a Liquid sample results are reported in pCilLiter, air filters( pcilfilter), charcoal (p~ilm3),and solid samples (pCiIg).

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

CH (charcoal canister), F (fish), U (urine).

Results are based on single determinations.

Control limits are established from the precision values listed in Attachment A of this report, adjusted to *2 (J.

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

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

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

Water U-238 Water Ra-226 Water Gr. Alpha Water Gr. Beta Air Filter Gr. Beta Air Filter Cs-134 Air Filter Cs-137 Air Filter H-3 Water CS-134 Water CS-I37 Water Sr-89 Water Sr-90 Milk cs-134 Milk Cs-137 Milk 1-131(G)

Milk Sr-89 Milk Sr-90 Water U-238 Water Ni-63 Fish Cs-134 Fish Cs-137 Water 1-131 Water Co-60 Water Cs-134 Water Cs-I 37 Water Ra-228 Water Ra-226 Water Gr. Alpha Water Gr. Beta SPAP-4164 Air Filter 717/2011 Gr. Beta 0.72 1.04 + 0.48 3.2 SPW-4168 Water 71712011 CS-134 3.41 10 SPW-4168 Water 7/7/2011 CS-I37 2.45 10 SPW-4168 Water 7/7/2011 Sr-89 0.72 0.40 f 0.50 5 SPW-4168 Water 71712011 Sr-90 0.51 +

-0.19 0.21 1 SPW-4171 Water 71712011 H-3 152.00 +

37.10 81.80 200 SPW-41811 Water 71712011 Ra-228 0.77 0.51 f 0.42 2

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

Lab Code Sample Date ~nalysis~ Laboratory results ( 4 . 6 6 ~ ) Acceptance Type LLD ActivityC Criteria (4.66 G)

Water Ni-63 Water Tc-99 Water C-I4 Water Fe-55 Water Gr. Alpha Water Gr. Beta Water Tc-99 Water Ra-226 Water Gr.Alpha Water Gr. Beta Water Ra-226 Water Ra-226 Water Gr. Alpha Water Gr. Beta Water Ra-228 Milk CS-I34 Milk Cs-I 37 Milk 1-131(G)

Water CS-134 Water Cs-137 Water I-131(G)

Air Filter Gr. Beta Air Filter Cs-134 Air Filter Cs-137 Water H-3 Water Ni-63 Water Tc-99 Fish CS-134 Fish CS-137 a Liquid sample results are reported in pCilLiter, air filters( pcilfilter), charcoal (pcilcharcoal canister), and solid samples (pcilkg).

I-131(G); iodine-131 as analyzed by gamma spectroscopy.

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

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

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance CF-20, 21 Be-7 0.24 f 0.14 0.34 f 0.17 0.29 k 0.11 Pass CF-20,21 K-40 10.37 f 0.43 +

9.76 0.68 10.07 f 0.40 Pass CF-20, 21 Sr-90 0.01 f 0.01 0.01 k 0.01 0.01 -1: 0.00 Pass WW-65, 66 H-3 321.91 f 97.19 345.76 k 98.16 333.83 k 69.06 Pass BS-165, 166 Cs-137 0.13 f 0.02 0.15 f 0.02 0.14 f 0.01 Pass BS-165, 166 H-3 +

286.00 80.00 284.00 f 80.00 285.00 f 56.57 Pass BS-165, 166 K-40 14.11 f 0.52 13.79 k 0.60 13.95 k 0.40 Pass BS-176, 177 H-3 391.00 f 92.00 332.00 f 89.00 361.50 f 64.00 Pass BS-176, 177 K-40 9.06 f 0.44 8.28 f 0.81 8.67 f 0.46 Pass BS-197, 198 CS-137 0.14 _C 0.03 0.15 k 0.04 +

0.15 0.03 Pass BS-197, 198 H-3 +

459.00 103.00 283.00 f 95.00 371.OO f 70.06 Pass BS-197, 198 K-40 +

14.40 0.77 14.16 f 1.23 14.28 f 0.73 Pass WW-358, 359 H-3 331.44 It 93.05 407.65 k 95.91 , 369.55 k 66.81 Pass DW-20009,20010 Ra-226 +

3.66 0.57 2.74 f 0.43 3.20 f 0.36 Pass DW-20009,20010 Ra-228 1.51 k 0.64 1.36 f 0.60 1.44 f 0.44 Pass WW-337,338 H-3 21986 f 402 21896 k 401 21941 k284 Pass W-49 1,492 Ra-226 6.70 f 0.50 6.10 k 0.50 6.40 k 0.35 Pass W-491,492 Ra-228 6.60 k 1.30 +

8.40 1.40 7.50 f 0.96 Pass DW-20014,20015 Gr. Alpha 1.91 f 0.71 2.34 f 0.80 2.13 k 0.53 Pass SWU-447,448 Gr. Beta 7.42 f 1.17 6.85 f 1.11 7.14 k 0.81 Pass W-694,695 H-3 628.26 f 104.30 +

692.37 106.89 660.32 f 74.67 Pass DW-20022,20023 Ra-228 0.71 k 0.47 +

1.13 0.54 0.92 f 0.36 Pass SW-626,627 H-3 1268.17k129.52 1144.65+125.39 1206.41k90.14 Pass LW-825, 826 Gr. Beta 2.65 f 0.82 2.45 f 0.74 2.55 f 0.55 Pass SW-845, 846 Gr. Beta 1.11 k0.39 0.80 k 0.37 0.96 k 0.27 Pass MI-998, 999 K-40 1760.10 f 127.50 1708.50 k 131.60 1734.30 f 91.62 Pass W-1024, 1025 H-3 489.83 f 101.09 +

581.39 105.06 535.61 f 72.90 Pass WW-1156, 1157 Gr. Beta 1.79 f 0.78 0.47 f 0.66 +

1.13 0.51 Pass P-1198, 1199 H-3 504.00 k 133.00 597.00 k 136.00 550.50 k 95.1 1 Pass SW-1434, 1435 H-3 15523 f 359 15968 f 364 +

15746 256 Pass WW-1588, 1589 Gr. Beta 1.81 f 1.23 2.81 k 1.38 2.31 f 0.92 Pass SG-1714, 1715 Gr. Alpha 8.82 k 0.81 8.58 f 0.74 8.70 k 0.55 Pass SG-1714, 1715 Gr. Beta 13.78 k 0.65 +

12.76 0.58 +

13.27 0.44 Pass AP-1862, 1863 Be-7 0.09 f 0.02 0.08 k 0.02 0.08 k 0.01 Pass W-2143,2144 H-3 536.40 k 99.37 466.79 f 96.46 501.59 f 69.25 Pass AP-2269, 2270 Be-7 0.07 k 0.01 0.08 f 0.01 0.07 k 0.01 Pass DW-20061,20062 Gr. Alpha 2.82 f I.33 3.89 f I.26 3.36 f 0.92 Pass SWU-1455, 1456 Gr. Beta 2.50 k 0.75 2.75 k 0.83 2.62 k 0.56 Pass SWU-I 522, 1523 Gr. Beta 1.36 k 0.87 2.14 f 0.96 1.75 k 0.65 Pass PM-1543, 1544 Gr. Beta 13.81 k 0.26 13.67 f 0.27 13.74 k 0.19 Pass PM-1543, 1544 Sr-90 8.12 f 3.20 7.71 f 3.25 7.91 f 2.28 Pass

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

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SWT-5885, 5886 3/29/2011 Gr. Beta +

1.21 0.54 0.77 + 0.54 0.99 2 0.38 Pass AP-1883, 1884 3/30/2011 Be-7 0.07 + 0.01 0.09 + 0.02 +

0.08 0.01 Pass AP-2248, 2249 3/30/2011 Be-7 +

0.06 0.01 0.06 + 0.01 0.06 + 0.01 Pass OW-20066, 20067 3/30/2011 Ra-226 +

2.14 0.16 2.10

• 0.16 +

2.12 0.11 Pass DW-20066, 20067 3/30/2011 Ra-228 +

2.55 0.65 I.78 + 0.62 +

2.17 0.45 Pass H-3 Pass 1-131 Pass K-40 Pass Sr-90 Pass A6228 Pass Pb-214 Pass Be-7 Pass Cs-137 Pass 1-131(G) Pass A6228 Pass Pb-214 Pass H-3 Pass K-40 Pass Sr-90 Pass H-3 Pass H-3 Pass K-40 Pass U-23314 Pass U-238 Pass H-3 Pass H-3 Pass H-3 Pass U-23314 Pass U-238 Pass K-40 Pass K-40 Pass U-23314 Pass U-238 Pass U-23314 Pass U-238 Pass Cs-134 Pass Cs-137 Pass K-40 Pass H-3 Pass H-3 Pass

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

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance A~228 Pass Pb-214 Pass K-40 Pass K-40 Pass Be-7 Pass H-3 Pass Be-7 Pass Gr. Beta Pass K-40 Pass Be-7 Pass Ac-228 Pass Bi-212 Pass Bi-214 Pass CS-137 Pass K-40 Pass Pb-212 Pass Pb-214 Pass Th-232 Pass U-23314 Pass U-238 Pass K-40 Pass Cs-137 Pass K-40 Pass U-23314 Pass U-238 Pass Gr. Beta Pass K-40 Pass Gr. Beta Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass

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

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance Be-7 Pass K-40 Pass U-23314 Pass U-235 Pass U-238 Pass U-23314 Pass U-238 Pass U-23314 Pass U-238 Pass K-40 Pass H-3 Pass Gr. Beta Pass Be-7 Pass Be-7 Pass Gr. Beta Pass K-40 Pass Be-7 Pass Gr. Beta Pass K-40 Pass U-23314 Pass U-238 Pass Ac-228 Pass Bi-212 Pass K-40 Pass Pb-214 Pass TI-208 Pass K-40 Pass Gr. Alpha Pass Gr. Beta Pass Ra-228 Pass Be-7 Pass K-40 Pass Ac-228 Pass K-40 Pass Pb-212 Pass Pb-214 Pass TI-208 Pass U-235 Pass Gr. Alpha Pass Gr. Beta Pass K-40 Pass

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

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance 91612011 Be-7 Pass 91612011 Gr. Beta Pass 9/6/2011 K-40 Pass 91712011 9-90 Pass 91812011 H-3 Pass 911312011 Be-7 Pass 911312011 Gr. Beta Pass 911312011 H-3 Pass 911312011 K-40 Pass 911912011 H-3 Pass 912012011 Ra-228 Pass 9/27/2011 K-40 Pass 912712011 H-3 Pass 9/27/2011 Be-7 Pass 9/28/2011 Be-7 Pass 912812011 Gr. Beta Pass 9/29/2011 Be-7 Pass 101312011 Be-7 Pass 101312011 Gr. Beta Pass 101312011 K-40 Pass 101312011 Be-7 Pass 101312011 Be-7 Pass 101412011 K-40 Pass 101612011 Be-7 Pass 101912011 H-3 Pass 1011012011 Cs-137 Pass 1011012011 K-40 Pass 1011312011 K-40 Pass 1011312011 Be-7 Pass 1011312011 U-23314 Pass 1011312011 U-238 Pass 1011912011 H-3 Pass 1012112011 H-3 Pass 1012612011 K-40 Pass 1012712011 H-3 Pass 1012812011 K-40 Pass 1013112011 K-40 Pass 1013112011 U-23314 Pass 1013112011 U-238 Pass 11/1/2011 Gr. Beta Pass

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

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance Gr. Alpha Pass Gr. Beta Pass U-23314 Pass U-235 Pass U-238 Pass U-238 Pass U-23314 Pass U-238 Pass A~228 Pass K-40 Pass Pb-212 Pass Pb-214 Pass Cs-137 Pass Gr. Beta Pass Be-7 Pass Cs-137 Pass Gr. Beta Pass K-40 Pass u-23314 Pass U-238 Pass Gr. Beta Pass Be-7 Pass Gr. Alpha Pass Gr. Beta Pass Ra-226 Pass K-40 Pass Be-7 Pass Be-7 Pass Gr. Beta Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.

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

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a Concentration Known Control Lab Code Date Analvsis Laboratory result Activity Limits Acceptance Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STW-1238 02/01/11 Gr. Alpha 0.82 f 0.07 1.14 0.34 - 1.93 Pass STW-1238 02/01/11 Gr. Beta 2.82 f 0.07 2.96 1.48 - 4.44 Pass 11.27 f 0.21 9.94 6.96 - 12.92 Pass 4.95 f 0.16 4.91 -

3.44 6.38 Pass

+

5.18 0.19 5.50 -

3.85 7.15 Pass

< 0.09 0.00 Pass 6.91 f 0.25 6.40 4.48 - 8.32 Pass 3.10 f 0.32 2.99 2.09 - 3.89 Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass 0.00 f 0.01 0.00 -0.10 - 0.10 Pass 3.48 + 0.06 3.33 2.33 - 4.33 Pass 0.00 f 0.02 0.00 -0.10 - 0.10 Pass 3.44 f 0.27 3.49 2.44 - 4.54 Pass 2.46 f 0.27 2.28 1.60 - 2.96 Pass

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a Concentration Known Control Lab Code Date Analysis Laboratory result Activity Limits Acceptance Gr. Alpha Pass Gr. Beta Pass Mn-54 Pass Pu-238 Pass Pu-239140 Pass Sr-90 Fail U-23314 Pass U-238 Pass Zn-65 Pass 9.50 6.70 - 12.40 Pass 0.00 Pass 3.38 2.37 - 4.39 Pass 0.00 -0.10 - 0.10 Pass 4.71 3.30 - 6.12 Pass 5.71 4.00 -,7.42 Pass 6.39 4.47 - 8.31 Pass STSO-1251 Pass STSO-1251 Pass STSO-1251 Pass STSO-1251 Pass STSO-1251 Pass STSO-1251 Pass STSO-1 251 Pass STSO-1251 Pass STSO-1251 Pass STSO-1251 Fail STSO-1251 ' Fail STSO-1251 Pass STSO-I 251 Pass STSO-1251 Pass Pass Pass Pass Pass Pass Pass Pass Pass

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

Concentration Known Control Lab Code Date Analysis Laboratory result Activity Limits Acceptance STAP-1252 08/01/11 U-23314 0.17 k 0.02 0.16 0.1 1 - 0.21 Pass STAP-1252 08/01/11 U-238 0.17 f 0.02 0.17 0.12 - 0.22 Pass STAP-1252 08/01/11 Zn-65 +

4.46 0.23 4.1 1 2.88 - 5.34 Pass CO-57 Pass CO-60 Pass CS-134 Pass CS-137 Pass H-3 Pass K-40 Pass Mn-54 Pass Ni-63 Pass Pu-238 Pass Pu-239140 Pass Sr-90 Pass Tc-99 Pass u-23314 Pass U-238 Pass Zn-65 Pass Gr. Alpha Pass Gr. Beta Pass a Results obtained by Environmental. Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, ldaho Operations office, ldaho Falls, ldaho Results are reported in units of Bqlkg (soil), BqlL (water) or Bqltotal sample (filters, vegetation).

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

MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.

Result of a repeat analysis was still unacceptable. ERA crosschecks for Am-241 were acceptable, but biased low.

Matrix spikes were prepared, ( 5.17 and 51.7 pCilL), to verify method; results were acceptable, 4.4 and 47.5 pCilL.

Am-241 has been added to the internal spike and blank program for 2012.

' An error in percent recovery was found, result of recalculation, 427.3 + 18.8 Bqlkg dry.

No errors found in calculation or procedure, results of reanalysis; 1.73 Bqlfilter.

The analyses were repeated through a strontium column; mean result of triplicate analyses, 304.2 Bqlkg.

'The lab does not currently analyze soil for Tc-99, but is evaluating the procedure. After consultation with Eichrom, the analysis was repeated using a matrix spike correction. Mean result of triplicate reanalyses; 183.3 Bqlkg.

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

Concentration (pCilL)

Lab Code Date Analysis Laboratory ERA Control Result Result

• Limits Acceptance Am-241 Pass CO-60 Pass Cs-134 Pass Cs-137 Pass Mn-54 Pass Pu-238 Pass Pu-239140 Pass Sr-90 Pass U-23314 Pass U-238 Pass Uranium Pass Zn-65 Pass Gr. Alpha 38.5 - 112 Pass Gr. Beta 42.8 - 102 Pass Ac-228 Pass Am-241 Pass Bi-212 Pass Bi-214 Pass Co-60 Pass CS-134 Pass Cs-137 Pass K-40 Pass Mn-54 Pass Pb-212 Pass Pb-214 Pass Pu-238 Pass Pu-239140 Pass Sr-90 Pass Th-234 Pass U-23314 Pass U-238 Pass Uranium Pass Zn-65 Pass

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

Lab Code Date Analysis Laboratory ERA Control Result Result Limits Acceptance STVE-1233 Am-241 Pass STVE-1233 Cm-244 Pass STVE-1233 Co-60 Pass STVE-1233 CS-134 Pass STVE-I 233 CS-137 Pass STVE-1233 K-40 Pass STVE-1233 Mn-54 Pass STVE-1233 Pu-238 Pass STVE-I 233 Pu-239140 Pass STVE-1233 Sr-90 Pass STVE-1233 U-23314 Pass STVE-1233 U-238 Pass STVE-1233 Uranium Pass STVE-1233 Zn-65 Pass Am-241 Pass CO-60 Pass Cs-134 Pass CS-137 Pass Mn-54 Pass Pu-238 Pass Pu-239140 Pass Sr-90 Pass U-23314 Pass U-238 Pass Uranium Pass Zn-65 Pass STW-1235 03/21/11 Gr. Alpha +

97.6 2.9 112.0 49.7 - 166.0 Pass STW-1235 03/21/11 Gr. Beta 99.6 f 2.0 99.8 58.4 - 146.0 Pass STW-1236 03/21/11 H-3 16307.0 + 377.0 15200.0 9900.0 - 22500.0 Pass Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, sewing as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

Laboratory codes as follows: STW (water). STAP (air filter), STSO (soil), STVE (vegetation). Results are reported in units of pCilL, except for air filters (pCilFilter), vegetation and soil (pcilkg).

Unless otherwise indicated, the laboratory result is given as the mean i: standard deviation for three determinations.

Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". Control limits are not provided.

APPENDIX B DATA REPORTING CONVENTIONS

Data Reportinn Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.

2.0. Sinale Measurements Each single measurement is reported as follows: 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. Du~licateanalvses If duplicate analyses are reported, the convention is as follows. :

3.1 Individual results: For two analysis results; x,

• s, and x, f s, Reoorted result: x f s; where x = (112) (x, + x,) and s = (112) dm 3.2. Individual results: < L, , < L, Reported result: < L, where L = lower of L, and L, 3.3. Individual results: x + s, < L Reported result: +

x s if x 2 L; < L otherwise.

4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, - an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation "s"of a set of n numbers x,, x, . . . 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 ~ y p e ) ~ (and Frequencylb (and Frequencylb Airborne Filters 6 E-1-4,8,20 Weekly GB, GS, on QC for each location Airborne Iodine 6 E-1-4, 8, 20 Weekly 1-131 Ambient Radiation 22 E-1-9, 12, 14-18,20, Quarterly Ambient Gamma (TLD's) 22-32, 34-36,38,39 Lake Water 5 E-1, 5, 6, 33 Monthly GB, GS, 1-131 on MC H-3, Sr-89-90 on QC Well Water 1 E-10 Quarterly GB, GS, H-3, Sr-89-90, 1-131 Vegetation 8 E-1-4,6, 9,20 3x I year GB, GS as available Shoreline Silt 5 E-1, 5, 6, 12, 33 2x / year GB, GS Soil 8 E-1-4,6,8,9,20 2x l year GB, GS Milk 3 E-I 1,40,21 Monthly GS, 1-131, Sr-89-90 Algae 3x 1 year GB, GS as available Fish 1 E-13 2x 1 year GB, GS (in edible portions) as available a Locations codes are defined in Table 2. Control Stations are indicated by (C). All other stations are indicators.

Analysis type is coded as follows: GB = gross beta, GA= gross alpha, GS = gamma spectroscopy, H-3 = tritium, Sr-89 = strontium-89, Sr-90 = strontium-90, 1-131 = iodine-131. Analysis frequency is coded as follows:

MC = monthly composite, QC =quarterly composite.

POINT BEACH NUCLEAR PLANT APPENDIX D Graphs of Data Trends

POINT BEACH Air Particulates - Gross Beta Location E-I , monthly averages 2007-201I 0.050 0.040

?

0.030 E

4 0, 0.020 0.010 0.000 2007 2008 2009 - 2010 201 1 Year Location E-2, monthly averages 2007-2011 0.050 -

0.040 --

0.010 -

0.000 : :  : : ~ ~ : : : ~ : l : : : ! ~ ! t : ~ : : ~ : : : : : : ~ I ~ : : i l I : : : : : : I I : : I : : : : : : ! : I : I 2007 2008 2009 2010 201 1 Year

POINT BEACH Air Particulates - Gross Beta Location E-3, monthly averages 2007-2011 2007 2008 2009 2010 201 1 Year Location E-4, monthly averages 2007-2011 0.000  !:l::::r::::l:t::::1:1:!1:1!11:1::+1  ! ~ 1 : ~ : : : 1 : I : : : : : I I : I I : I H 2007 2008 2009 2010 201 1 Year

POINT BEACH Air Particulates - Gross Beta Location E-8, monthly averages 2007-2011 0.000 ! : I : : : : : : : I : I : ! : ~ ~ ! ! ! i ! : I ~ I : : i r I : f : t t c + - H t r t + t t : I ! i ~ : i ! : ! I I 2007 2008 2009 2010 201 1 Year Location E-20, monthly averages 2007-2011 2007 2008 2009 2010 201 1 Year

POINT BEACH NUCLEAR PLANT APPENDIX E Supplemental Analyses

POINT BEACH NUCLEAR PLANT APPENDIX F Special Analyses

POINT BEACH NUCLEAR PLANT Special Analyses Precipitation samples Units = pCilL Location E-01 Collection Date 03-22-11 03-22-11 03-22-11 Lab Code EP- 1172 MDC EP- 1173 MDC EP- 1174 MDC Gross Beta 1.2

• 0.7

-0.59 f 0.87 124 f 101 11.7 f 3.8 40.9 f 13.7

-0.1 f 1.5

-4.1 f 2.7

-0.5 f 1.4

-0.6 f 1.6

-1.6 f 3.2

-1.0 f 1.6 0.7 f 1.5

-0.3 f I.6 1.5 f 1.2 Location E-02 Collection Date 03-25-11 03-25-11 03-25-11 Lab Code EP- 1292 MDC EP- 1293 MDC EP- 1294 MDC Gross Beta 3.1

• 0.6 < 0.8

-0.04

• 0.33 < 0.71 47 f 96 < 154 24.4 f 4.9 < 3.7 72.5 + 29.4 0.4 f 1.2 < 2.0 0.6 f 2.7 < 3.2

-0.6 f 1.4 < 1.2 0.7 f 1.7 < 2.4

-0.9 f 2.7 < 2.4

-2.8 f 1.6 7 <1.6 0.3 f 1.4 < 2.7 1.8 f 1.8 < 3.7 0.2 f 1.7 < 3.2

POINT BEACH NUCLEAR PLANT Special Analyses Weekly Composiites of airborne partic1ulates Collection Start 02-23-11 03-02-11 03-10-11 Co[lection End 03-02-11 03-10-11 03-16-11 Lab Code EAP- 1169 MDC EAP- 1170 MDC EAP- 1171 MDC Volume (m3) 1809 1869 1602 Collection Sfart 03-16-11 03-24-11 03-30-11 Collection End 03-24-1 1 03-30-11 04-06-11 Lab Code EAP- 1288 MDC EAP- 1466 MDC EAP- 1704 MDC Volume (m3) 2054 1374 1809

POINT BEACH NUCLEAR PLANT Special Analyses Weekly Composites of airborne particulates Units = pCilm" Collection Start 04-06-11 04-13-11 04-20-11 Collection End 04-13-11 04-20-11 04-27-1 1 Lab Code EAP- 2045 MDC EAP- 2439 MDC EAP- 2501 MDC Volume (m3) 1849 1912 1912 Collection Start 04-27-1 1 05-04-11 Collection End 05-04-11 05-1 1-11 Lab Code ' EAP- 2699 MDC EAP- 2867 MDC Volume (m3) 2085 1860

POINT BEACH NUCLEAR PLANT Air particulate and air iodine cartridges for gross beta and gamma emitting isotopes Units = pcilm3 Location WHSE # I WHSE # I Collection Date 03-27-11 03-27-1 1 Lab Code EAP- 1407 MDC ECH- 1408 MDC Volume (m3) 121.5 121.5 Gross Beta 0.040

• 0.007 < 0.008 Location lSFSl lSFSl Collection Date 03-31-11 03-31-11 Lab Code EAP- 1467 MDC ECH- 1468 MDC Volume (m3) 288.7 288.7 Gross Beta 0.028

• 0.004 < 0.003

POINT BEACH NUCLEAR PLANT Special Analyses Air particulate and air iodine cartridges for gross beta and gamma emitting isotopes Units = p ~ i l m 3 Location ISFSl lSFSl Collection Date 04-06-11 04-06-11 Lab Code EAP- 1702 MDC ECH- 1703 MDC Volume (m3) 266.5 266.5 Gross Beta 0.030 f 0.004 c 0.003 Location ISFSl ISFSl Collection Date 04-14-11 04-14-11 Lab Code EAP- 2025 MDC ECH- 2026 MDC Volume (m3) 338.6 338.6 Gross Beta 0.023 f 0.003 c 0.003

POINT BEACH NUCLEAR PLANT Special Analyses Air particulate and air iodine cartridges for gross beta and gamma emitting isotopes Units = pcilm3 Location ISFSl ISFSl Collection Date 04-21-11 04-21-11 Lab Code EAP- 2299 MDC ECH- 2298 MDC Volume (m3) 301.4 301.4 Gross Beta 0.024 f 0.003 < 0.003

POINT BEACH NUCLEAR PLANT Special Analyses Precipitation samples Units = pCilL Location E-02 E-03 E-04 Collection Date 04-06-11 04-06-11 04-06-11 Lab Code EP- 1706 MDC EP- 1707 MDC EP- 1708 MDC Gross Beta 2.9 i 1.9 < 3.6 1.9

• 1.7 < 3.1 3.5

• 1.9 < 3.5

-0.27

• 0.56 < 1.28 -0.15

• 0.69 < 1.53 -0.17 S 0.49 < 1.11 48 + 89 4 143 28 + 88 < 143 72 + 90 < 143 12.6 f 1.6 < 13.6 13.6 i 1.5 < 11.4 10.8 + 1.5 < 11.2

-7.4 f 14.7 < 22.5 2.5 f 11.0 < 30.5 11.4 r 11.0 < 27.5 1.0 + 1.5 < 3.5 +

0.6 1.3 < 2.6 0.4 f 1.3 < 2.4 0.3 f 2.4 < 4.8 3.6 f 2.3 < 5.8 -2.3 f 2.5 < 4.1 1.8 + 1.4 < 2.5 +

-1.3 1.2 < 1.6 -0.3 + 1.2 < 2.6

-0.6 + 1.5 < 2.6 +

-0.1 1.4 < 2.4 0.4 + 1.5 < 2.7

-2.5 + 2.9 < 4.4 +

0.5 2.5 < 4.2 1.3 f 2.5 < 4.7 0.3 f 1.4 < 3.9 +

0.6 1.4 < 3.8 -1.6 f 1.4 < 2.5

-0.3 r 1.5 < 2.8 +

-0.5 1.4 < 1.8 0.4 + 1.4 < 2.4

-0.4 f 1.7 < 1.7 +

0.8 1.4 < 2.7 -0.2 f 1.5 < 2.5

-3.5 f 1.5 < 5.3 +

-2.2 1.5 c 4.5 -4.3 + 1.4 < 4.0 Location E-02 E-03 E-04 Collection Date 04-19-11 04-19-11 04-19-11 Lab Code EP- 2229 MDC EP- 2230 MDC EP- 2231 MDC Gross Beta 1.7 i 1.6 < 3.1 2.8

• 1.8 < 3.4 1.7 i 0.6 < 0.8

-0.09 i 0.25 < 0.56 -0.03 -1: 0.31 < 0.67 -0.09 -1: 0.33 < 0.75 a 1-131 analyzed by column.

POINT BEACH NUCLEAR PLANT Special Analyses Precipitation samples Units = pCilL Location E-02 E-03 E-04 Collection Date 04-21-11 04-21-11 04-21-11 Lab Code EP- 2368 MDC EP- 2369 MDC EP- 2370 MDC Gross Beta ' -0.5

• 1.2 < 2.2 0.7 5 1.1 Location Composite of PBNP-3-22 Onsite Samples Composite Collection Date 04-19-11 04-20-11 Lab Code EP- 2367 MDC EP- 2492 MDC Gross Beta 8.8 k 1.3 < 1.5 -0.4 k 0.6 a 1-131 analyzed by column.

b Tritium analysis not requested.

POINT BEACH NUCLEAR PLANT Special Analyses Precipitation samples Units = pCilL Collection Date Lab Code Tritium MDC Location EP- 2008 Precip 1 EP- 2009 Precip 2 EP- 2010 Precip 3 EP- 201 1 Precip 4 EP- 2013 Precip 5 EP- 2014 Precip 6 EP- 2015 Precip 7 EP- 2016 Precip 8 EP- 2017 Precip 9 EP- 2018 Precip 10 EP- 2019 Precip 11 EP- 2020 Precip 12 Special Analyses Lake water samples Required LLD = 1E-06 pCilmL Units = pCilL Collection Date Lab Code carbon-14 Location 09-13-1 1 ELW- 6278 09-13-1 1 ELW- 6279

Environmental, Inc.

Midwest Laboratory 700 Landwehr Road. Norlhbrook. IL 60062-2310 phone (8471 564-0700. fax (847) 564-4517 Mr. Daniel Craine LABORATORY REPORT NO.: 8006-100-972 Radiation Protection Mgr. DATE: 04-15-11 Point Beach Nuclear Plant SAMPLES RECEIVED: 04-08-11 NextEraEnergy PURCHASE ORDER NO.:

6610 Nuclear Road Two Rivers, WI 54241 Below are the results of the readout of supplemental TLDs deployed during the first quarter, 201 1 Period: 1st Quarter, 2011 Date Annealed: 12113110 Date Placed: 01/06/11 Date Removed: 04/05/11 Date Read: 04113111 Days in the Field: 89 Days from Annealing to Readout: 121 In-transit exposure: +

4.78 0.44 Net mR Location Total mR Net mR per 7 days Control I

SA Coorlim, Quality Assurance APPROVED cc: K. Johansen

+:~ATIEnvironmental, Midwest Laboratory Inc.

- TOO Landwehr Road phone (847) 564-0700 -

Northbrook, IL 60062-2370-fax (847) 564-4577 Mr. Daniel Craine LABORATORY REPORT NO.: 8006-100-990 Radiation Protection Mgr. DATE: 08-04-11 Point Beach Nuclear Plant SAMPLES RECEIVED: 07-11-1I NextEraEnergy PURCHASE ORDER NO.:

6610 Nuclear Road Two Rivers, W I 54241 Below are the results of the readout of supplemental TLDs deployed during the second quarter, 201 1.

Period: 2nd Quarter, 201 1 Date Annealed: 0311011 1 Date Placed: 04105111 Date Removed: 07108111 Date Read: 07115111 Days in the Field: 94 Days from Annealing to Readout: 127 In-transit exposure: 4.44 f 0.37 Net mR Net mR Location Total mR Net mR Std Qtr per 7 days Control SA Coorlim, Quality Assurance APPROVED cc: K. Johansen

Environmental, lnc.

Midwest Labomtory 7 0 0 L a n M h r R w d Nahhmoh IL 60082-2310 phMa (817) 66C0700. fax (W7J 544-4517 Mr. Daniel Craine LABORATORY REPORT NO.:

Radiation Protection Mgr. DATE:

Polnt Beach Nuclear Plant SAMPLES RECEIVED:

NextEraEnergy PURCHASE ORDER NO.:

6610 Nuclear Road Two Rivers, WI 54241 Below are the results of the readout of supplemental TLDs deployed during the third quarter, 2011.

Period: 3rd Quarter, 2011 Date Annealed: 06/03/11 Date Placed: 07/08/11 Date Removed: 10/07/11 Date Read: I011911I Days in the Field: 91 Days from Annealing to Readout: 138 '

In-transit exposure: 7.5 f 0.6 Net rnR Net mR Location Total mR Net rnR Std Qtr . per 7 days Control I ..

SA Coorlim,

'Quality Assurance APPROVED cc: K. Johansen REC'D NOV 0 2 2011

Environmental, Inc.

Midwest Laboratory 7QOL a n k h r Road NuUIbrooh IL 60062-2510 phoM (847) MCO7Od. far (847) S 4 - 4 5 1 7 Mr. Daniel Craine LABORATORY REPORT NO.: 8006-100-1010 Radiation Protection Mgr. DATE: 02-01-12 Point Beach Nuclear Plant SAMPLES RECEIVED: 01-09-12 NextEraEnergy PURCHASE ORDER NO.:

6610 Nuclear Road Two Rivers, W I 54241 Below are the resulisof the readout of supplemental TLDs deployed during the fourth quarter, 2011. . .

Period: .:4th Quarter, 2011 Date Annealed: 09116111 Date Placed: 10107111 Date Removed: 0 1106112 Date Read: 01112112 ,

Days in the Field: .90 :

Days from Annealing to Readout: . ... . 118:

In-transit exposure: ' 5.01 ,f0.48 Net mR ',. . NetmR Location Total mR Net mR Std Qtr ... .. per 7 days Control a Date removed 01-05-12.

1 SA Coorlirn,

~ u a l i tAssurance

'~ . .

APPROVED cc: K. Johansen

APPENDIX 2 University of Waterloo (Ontario)

Environmental Isotope Laboratory Precipitation Monitoring Results for the Point Beach Nuclear Plant Reporting Period: January - December 201 1

Client: Johansen . lSO# 201 1032 Environmental Isotope Lab NextEra Energy Point Beach Location: T-8 71612011 Contract #:' 25473 3 for 3H 1 of I NPL 201 1-0006 El Conductivity Tritium is reported in Tritium Units.

1TU = 3.221 PicocurriesIL per IAEA, 2000 Repod.

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

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

Client: Johansen ]SO# 201 1 1 30 Environmental Isotope Lab NextEra Energy Point Beach Location: T-8 311912012 Contract #: 25473 3 for 3H ?of1 NPL 201 1-0054 F l Conductivity Tritium is reported in Tritium Units.

I T U = 3.221 Picocurries/L per IAEA, 2000 Report.

I T U = 0.1 1919 BecquerelsJL per IAEA, 2000 Report.

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

Client: Johansen ISO# 201 1182 Environmental Isotope Lab NextEra Energy Point Beach Location: T-8 3121/2012 Contract #25473 3 for 3H Iof I NPL 201 1-0096 Tritium is reported in Tritium Units.

1TU = 3.221 PicocurriesIL per IAEA, 2000 Report.

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

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

Client: Johansen 1SO# 201 1217 Environmental Isotope Lab NextEra Energy Point Location: T - 8 3/21/2012 Beach 3 for 3H 1 of I Contract #25473 NPL 201 1-0107 El Conductivity Tritium is reported in Tritium Units.

1TU = 3.221 PicocurriesIL per IAEA, 2000 Report.

I T U = 0.1 1919 BecquerelsIL per IAEA, 2000 Report.

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

Client: Johansen ISO# 201 1234 Environmental Isotope Lab NextEra Energy Point Beach Location: T-8 3/21/2012 Contract #25473 3 for 3H Io f 1 NPL 201 1-0111 El Conductivity Tritium is reported in Tritium Units.

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

1TU = 0.11919 BecquerelsJL per IAEA, 2000 Report.

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

Client: Johansen ISO# 2011264 Environmental Isotope Lab NextEra Energy Point Beach Location: T - 8 3/21/2012 Contract #: 25473 3 for 3H lofl NPL 2011-0123 El Conductivity Tritium.is reported in Tritium Units.

I T U = 3.221 Picocurries/L per IAEA, 2000 Report.

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

Rick Heemskerk uwElLAB Manager To Contact uwEILAB: rkhmskrk@uwaterloo.ca 5 19 888 4732 519 888 4567 ext 35838

Client: Johansen ISO# 2011295 Environmental Isotope Lab NextEra Energy Point Beach Location: T - 8 3/21/2012 Contract #25473 3 for 3H 1 of 1 NPL 2011-0144 k

Conductivity Tritium is reported in Tritium Units.

1TU = 3.221 PicocurriesIL per IAEA, 2000 Report.

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

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

Client: Johansen /SO# 2011297 Environmental Isotope Lab NextEra Energy Point Beach Location: T - 8 3/21/2012 Contract #25473 , 3 for 3H lofl NPL 2011-0153 El Conductivity Tritium is reported in Tritium Units.

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

I T U = 0.1 1919 BecquerelsIL per IAEA, 2000 Repori.

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

Client: Johansen lSO# 2011339 Environmental Isotope Lab NextEra Energy Point Beach Location: T - 8 311912012 Contrac t#25473 3 for 3H . Iofl NPL 2011-0169 El Conductivit Tritium is reported in Tritium Units.

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

ITU = 0.11919 BecquerelsIL per IAEA, 2000 Report.

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

Client: Johansen 1SO# 201 1384 Environmental Isotope Lab NextEra Energy Point Beach Location: T - 8 311912012 Contract #25473 3 for 3H Iof I NPL 2011-0214 Tritium is reported in Tritium Units.

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

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

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

Client: Johansen ISO# 2011465 Environmental Isotope Lab NextEra Energy Point Beach Location: T - 8 3119/2012 Contract #: 25473 3 for 3H lofl NPL 201 1-0237 Tritium is reported in Tritium Units.

1TU = 3.221 PicocurriesIL per IAEA, 2000 Report.

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

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

Client: Johansen ISO# 2011530 Environmental Isotope Lab NextEra Energy Point Beach Location: T - 8 311912012 Contract #: 25473 3 for 3H Iof I NPL 2011-0290 Tritium is reported in Tritium units.

1TU = 3.221 PicocurriesIL per IAEA, 2000 Report.

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

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

Client: Johansen [SO# 201 1586 Environmental Isotope Lab NextEra Energy Point Beach Location: T - 8 311 912012 Contract #: 25473 3 for 3H 1 of 1 NPL 201 1-0312 Tritium is reported in Tritium Units.

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

I T U = 0.1 1919 BecquerelsIL per IAEA, 2000 Report.

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

Client: Johansen ISO# 2011639 Environmental Isotope Lab NextEra Energy Point Beach Location: T-8 3/19/2012 Contract #25473 3 for 3H Iofl NPL 201 1-0343 Tritium is reported in Tritium Units.

1TU = 3.221 PicocurrieslL per IAEA, 2000 Report.

1TU = 0. I1919 BecquerelslL per IAEA, 2000 Report.

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

Client: Johansen ISO# 2011733 Environmental Isotope Lab Nextera Energy Point Beach Location: T-2 3120/2012 Contract #25473 3 for 3H lofl NPL 201 1-0398 Rainwater samples Tritium is reported in Tritium Units.

1TU = 3.221 PicocurriesIL per IAEA, 2000 Report.

I T U = 0.1 1919 BecquerelsIL per IAEA, 2000 Report.

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

Client: Johansen ISO# 2011796 Environmental Isotope Lab NextEra Energy Point Beach Location: 1-8 3120/2012 Conctract #25473 3 for 3H Iofl NPL 201 1-0426 Tritium is reported in Tritium Units.

1TU = 3.221 PicocurriesIL per IAEA, 2000 Report.

I T U = 0.1 1919 BecquerelsIL per IAEA, 2000 Report.

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

Client: Johansen 1SO# 2012012 Environmental Isotope Lab

~ e x t ~Energy ra Point Beach Location: T-8 311912012 Contract #25473 3 for 3H Iofl NPL 2012-009 Tritium is reported in Tritium Units.

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

I T U = 0,11919 BecquerelslL per IAEA, 2000 Report.

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

Client: Johansen ISO# 2010748 Environmental Isotope Lab FPL Energy Ponit Peach Location: 12/7/2010 Zontract #: 25473 12 for 3H lofl NPL.2010-0412 Client's Note:

We expect that some samples will have more H-3 than previous rain water samples, on the order of 400 800 T.U.

Tritium is reported in Tritium Units.

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

I T U = 0.1 1919 BecquerelslL per IAEA, 2000 Report.

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

Client: Johansen ISO# 201 1324 Environmental Isotope Lab NextEra Energy Point Beach Location: T - 8 4/27/20 12 Contract #25473 13 for 3H 1of1 NPL 201 1-0150

• sample taken 0411 1111 Tritium is reported in Tritium Units.

1TU = 3.221 PicocurriesIL per IAEA, 2000 Report.

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

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

Client: Johansen lSO# 201 1296 Environmental Isotope Lab NextEra Energy Point Beach Location: T - 8 4/27/2012 Contract #25473 11 for 3H 1 of 1 NPL 201 1-0145 F I Conductivity w

Tritium is reported in Tritium Units.

1TU = 3.221 PicocurriesIL per IAEA, 2000 Report.

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

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

ENCLOSURE 2 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 ENVIRONMENTAL MANUAL REVISION 23 MARCH 30,2011 34 pages follow

EM ENVIRONMENTAL MANUAL DOCUMENT TYPE: Controlled Reference CLASSIFICATION: N/A REVISION: 23 EFFECTIVE DATE: March 30,20 11 REVIEWER: Plant Operations Review Committee (PORC)

APPROVAL AUTHORITY: Plant Manager (PORC Chair)

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

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30. 201 1 ENVIRONMENTAL MANUAL TABLE OF CONTENTS SECTION TITLE PAGE 1.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ADMINISTRATION ................................................................................ 3 1.1 Definition and Basis .......................................................................................................3 1.2 Responsibilities for Program Implementation ............................................................... 4 1.3 Quality Assurance/Quality Control ................................................................................ 7 1.4 Program Revisions ......................................................................................................... 8 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING ........................................... 8 2.1 Program Overview ......................................................................................................... 8 2.2 Program Parameters ....................................................................................................... 9 2.3 Assistance to the State of Wisconsin............................................................................. 14 2.4 Specification of Sampling Procedures .......................................................................... 15 2.5 Milk Survey ..................................................................................................................

24 Table 2-1 Recommended Minimum Sample Sizes .......................................................................25 Table 2-2 Sample Types And Associated Lower Level Of Detection (Lld) And Notification Level Values ............................................................................................. 26 Table 2-3 Radiological Environmental Sampling Locations......................................................... 28 Table 2-4 PBNP Radiological Environmental Sample Collection And Analysis Frequency ....... 30 Table 2-5 Samples Collected For State Of Wisconsin .................................................................. 31 Figure 2-la Radiological Environmental Sampling Locations......................................................... 32 Figure 2-lb Radiological Environmental Sampling Locations......................................................... 33 Figure 2-lc Radiological Environmental Sampling Locations......................................................... 34 Page 2 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 3 0,20 11 ENVIRONMENTAL MANUAL 1.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ADMINISTRATION 1.1 Definition and Basis 1.1.1 Definition Radiological environmental monitoring is the measurement of radioactivity in samples collected from the atmospheric, aquatic and terrestrial environment around the Point Beach Nuclear Plant (PBNP). Monitoring radioactivity in effluent streams at or prior to the point of discharge to the environment is not part of the Radiological Environmental Monitoring Program (REMP).

1.1.2 Basis The REMP is designed to fulfill the requirements of 10 CFR 20.1302, PBNP GDC 17, and Sections IV.B.2 and IV.B.3 of Appendix I to 10 CFR 50.

Technical Specification 5.5.1.b requires the Offsite Dose Calculation Manual (ODCM) to contain the radiological environmental monitoring activities. A complete description of the PBNP radiological environmental monitoring program, including procedures and responsibilities, is contained in the Environmental Manual (EM). The EM is incorporated into the ODCM by reference (ODCM, Section 6.0).

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

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

Page 3 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,20 11 ENVIRONMENTAL MANUAL Water, periphyton, and fish are analyzed to monitor radionuclide levels in Lake Michigan in the vicinity of PBNP. Periphyton, attached algae, along with lake water samples, provide a means of detecting changes which may have a potential impact on the radionuclide concentrations in Lake Michigan fish. Because of the migratory behavior of fish, fish sampling is of minimal value for determining radiological impact specifically related to the operation of the Point Beach Nuclear Plant. However, fish sampling is carried out as a conservative measure with emphasis on species which are of intermediate trophic level and which exhibit minimal migration in order to monitor the status of radioactivity in fish.

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

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

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

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

Chemistry reviews the EM annually via the Annual Monitoring Report.

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

The vendors monthly reports are cumulative (e.g. The September report contains all the results from January-September). The cognizant Chemist reviews the current months results, signs and dates the cover page, and sends the reviewed report to plants records for retention.

Page 4 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,2011 ENVIRONMENTAL MANUAL

c. Data monitoring Chemistry reviews the monthly analytical results from the vendor.

Trends, if any, are noted. Any resulting corrections, modifications and additions to the data are made by Chemistry . The review is documented and sent to records, as noted in Section 1.2.1.b. Inconsistencies are investigated by Chemistry with the cooperation of Radiation Protection (RP) and contractor personnel, as required. Radioactivity levels in excess of administrative notification levels would be evaluated and notifications made, as appropriate, in accordance with the PBNP Reportability Manual and applicable fleet policies and procedures.

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

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

e. Contractor communications Communication with the contractor regarding data, analytical procedures, lower limits of detection, notification levels and contractual matters are normally conducted by Chemistry. Communication regarding sample shipment may be done by either RP or Chemistry as appropriate.

f. Reportable items

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

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

(c) New or relocated sampling locations and reason for change; Page 5 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 ENVIRONMENTAL MANUAL (d) LLDs that are higher than specified in Table 2-2 and factors contributing to inability to achieve specified LLDs; (e) Notification that the analytical laboratory does not participate in an interlaboratory comparison program and corrective action taken to preclude a recurrence; and (0 Results of the annual milk sampling program land use census "milk survey" to visually verify that the location of grazing animals in the vicinity of the PBNP site boundary so as to ensure that the milk sampling program remains as conservative as practicable.

(g) The annual results from the contracted REMP analytical laboratory as well as the laboratory's analytical QAIQC results, in-house blanks, interlaboratory comparisons, etc., shall be submitted to the NRC, via the Annual Monitoring Report.

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

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

a. Manual control and distribution The distribution of the PBNP Environmental Manual is the responsibility of Document Control.

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

1. Ensuring that samples are obtained in accordance with the type and frequency in Table 2-4 following procedures outlined in this manual; Page 6 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30, 20 11 ENVIRONMENTAL MANUAL

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

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

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

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

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

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

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

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

Page 7 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 ENVIRONMENTAL MANUAL 1.4 Program Revisions This manual describes the current scope of the PBNP Radiological Environmental Monitoring Program. Program items or procedures periodically may be updated or changed, consistent with good radiologically monitoring practices, either to reflect new conditions or to improve program effectiveness. Technical and program features described in this manual shall be reviewed by PORC pursuant to the requirements stated in the ODCM.

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

2.1.2 Samples Samples for the REMP are obtained from the aquatic, terrestrial and atmospheric environment. The sample types represent key indicators or critical pathways which have been identified by applying radiological principles from NRC and other guidance documents to the PBNP environment.

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

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 ENVIRONMENTAL MANUAL 2.2 Program Parameters 2.2.1 Contamination avoidance Contamination prevents the accurate quantification of environmental radioactivity and the correct differentiation between fluctuating background radioactivity and levels of radioactivity attributable to the operation of PBNP.

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

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

b. Store sampling equipment in radiologically clean areas only;

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

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

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

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

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

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

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 2.2.3 Lower limit of detection The sensitivity required for a specific analysis of an environmental sample is defined in terms of the lower limit of detection (LLD). The LLD is the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with a 95% probability and have only a 5% probability of falsely concluding that a blank observation represents a real signal. Mathematically, the LLD is defined by the formula 4.66 Sb LLD =

E x V x 2.22 x Y x EXP(-hAT)

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

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

sample size in units of volume or mass, as applicable; 2.22 number of disintegrations per minute per picocurie; Y the fractional chemical yield as applicable; h the radioactive decay constant for the particular radionuclide; and AT the elapsed time between sample collection, or the end of the collection period, and the time of counting.

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

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

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

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 Notification levels The Notification Level (NL) is that measured quantity of radioactivity in an environmental sample which, when exceeded, requires a notification of such an occurrence be made to the appropriate party. Regulatory and administrative notification levels are listed in Table 2-2.

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

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

The weighted sum is calculated as follows:

concentration (I) concentration (2)

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

If the calculated weighted sum is equal to or greater than 1, resampling and/or reanalysis for confirmation shall be completed within 30 days of the determination of the anomalous result. If the confirmed calculated weighted sum remains equal to or greater than 1, see Section 1.2.1.c for notification guidance. This calculation requirement and report is not required if the measured level of radioactivity was not the result of plant effluents.

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

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 ENVIRONMENTAL MANUAL 2.2.5 Sampling locations A list of sampling locations and the corresponding location codes appear in Table 2-3. The locations also are shown in Figures 2-la, 2-lb, and 2-lc. It is conceivable that samples may become unavailable from specified sample locations. If this were to occur, new locations for obtaining replacement samples shall be identified and added to the Radiological Environmental Monitoring Program. If milk or vegetation samples become unavailable from the specified sampling locations, new sampling locations will be identified within 30 days. The specific locations where samples were unavailable may be deleted from the monitoring program in accordance with established provisions for assessing changes. Any significant changes in existing sampling location and the criteria for the change shall be reported in the Annual Monitoring Report for the period in which the change occurred.

Additional sampling locations may be designated if deemed necessary by cognizant company personnel. Figures and tables in this manual shall be revised to reflect the changes.

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

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

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 ENVIRONMENTAL MANUAL 2.2.7 Sample labeling All samples must be properly labeled to ensure that the necessary information is conveyed to the analytical contractor and that the results are associated with the correct geographical location. Each label (PBF-4026) must contain the following:

a. Sample type;

b. Sample location from Table 2-3;

c. Date and time (as appropriate) collected;

d. Air samples must show the total volume in m3; volumes for water and milk are in gallons; vegetation, sediment, soil, and algae are indicated as

<1000 grams; and fish 21000 grams;

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

f. Name of person collecting the sample.

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

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

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

2.2.8 Sample shipping All environmental samples are shipped to a contractor for analysis. The samples shall be packaged and shipped in such a way as to minimize the possibility of cross-contamination, loss, spoilage and leakage. Each sample shipment shall have a typed cover letter and, when appropriate, a contractor data collection sheet. Included in the letter shall be the same information required for the sample labels as well as the specific analyses required. The original cover letter and data collection sheet shall be sent to the contractor under separate cover; one copy of each is to be used as a packing list and a copy of each shall be kept in the appropriate PBNP file. The data collection sheet (PBF-4140a) also serves as the Chain of Custody form, so it is required that the collector, packer, and shipper sign the form.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 ENVIRONMENTAL MANUAL 2.2.9 Sample analyses and frequency The PBNP REMP samples shall be analyzed for designated parameters at the frequency listed in Table 2-4. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to effluents from PBNP. Typically, this entails the scanning of the spectrum from 80 to 2048 keV and decay correcting identified radionuclides to the time of collection. The analysis specifically includes, but is not limited to, Mn-54, Fe-59,Zn-65, Co-58, Co-60,Zr-Nb-95, Ru-103,I-13 1, Cs-134, Cs-137, Ba-La-140, Ce-141, and Ce-144.

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

Environmental Incorporated Midwest Laboratory 700 Landwehr Road Northbrook, IL 60062-45 17 (847) 564-0700 This laboratory performs the analyses in such a manner as to attain the desired LLDs. The contracted laboratory participates in an inter-laboratory comparison crosscheck program.

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

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

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

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 ENVIRONMENTAL MANUAL Samples obtained for the State of Wisconsin are either given directly to state personnel or shipped as required. The department address is:

State Lab of Hygiene Radiochemistry Unit 2601 Agriculture Dr.

PO Box 7996 Madison, Wisconsin 53707-7996 2.4 Specification of Sampling Procedures General radiological environmental sampling procedures follow the directives presented in Sections 2.1 and 2.2. Specific information for handling individual sample types follow.

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

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

2.4.2 Thermoluminescent dosimeters (TLDs)

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

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

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 ENVIRONMENTAL MANUAL Environmental TLDs should never be brought into the plant RCA or any other area with elevated radiation, but may be stored for brief periods in a shielded enclosure in the RP Office Area or other low background area, such as the Energy Information Center or the Site Boundary Control Center. The contractor is to time shipments to coincide as closely as possible with the beginning of a calendar quarter. TLDs should be shipped back to the contractor immediately 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 samples immediately upon receipt. The contractor shall report removal data and cumulative readings in mR for all locations and control, correct for in-transit exposure and express results in net mR17 days.

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

2.4.3 Lake water Lake water samples are obtained monthly at specified locations. The contractor is responsible for the compositing for quarterly analyses. Collect approximately 8000 rnl(2 gallons) of lake water in the required number of cubitainers, or other appropriate containers, at each location and label as directed in Section 2.2.7.

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

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

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

Sample should be obtained from PW-80, T-90 Hydro-pneumatic Tank Drain.

After purging 8 gallons, collect approximately 8000 ml(2 gallons) of well water using the required number of cubitainers or other appropriate containers. Label as directed in Section 2.2.7.

2.4.5 Air

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

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 ENVIRONMENTAL MANUAL Both particulate filters and charcoal cartridges are employed at each sampling location. Particulate filters are analyzed for gross beta activity after waiting for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to allow for the decay of short-lived radon and thoron daughter products. The contractor makes quarterly composites of the weekly particulate samples for gamma isotopic analyses.

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

Pertinent air sampling data for each location is recorded on PBF-4078, Air Sampling Data Sheet. At a normal filter change, the following procedure will apply:

NOTE: Environmental flow rates should be approximately 30 lpm.

NOTE: The correction factor for the digital flow meter is always 1.0 similar to that of a Hi Vol air sampler.

1. Ensure unit is in flow mode.

2. Read and record the current flow rate (R2).

3. Press the RESET button while the pump is operating. This turns the pump OFF and preserves the elapsed time and total time values.

4. Record Date Off and time off (t2).

5. Press the UNITS button to read elapsed time (T) and total volume (m3) and record.

NOTE: Always write data on the envelope before inserting the particulate filter in the envelope.

6. Label the sample envelope as directed in Section 2.2.7. Also enter any other pertinent information at this time.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30, 201 1 ENVIRONMENTAL MANUAL NOTE: Do NOT fold filter. Folding and unfolding may dislodge material from the filter and make a reproducible geometry impossible to achieve.

7. Remove particulate filter being careful to handle it only by the edges and place in the glassine envelope.

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

NOTE: Check the charcoal cartridge for breaks and the particulate filter for holes in the filter surface prior to installation.

Discard unacceptable filter media.

9. Install new charcoal cartridge and particulate filter.

10. Press the UNITS button until the time is displayed and time indicator is lit up.

11. Press the RESET button to zero the time.

12. Press the UNITS button until the total volume is displayed and total volume indicator is lit up.

13. Press the RESET button to zero the total volume.

14. Press the UNITS button until the flow is displayed and the flow indicator is lit up.

15. Press the RESET button to start the sample pump.

16. Record Date On and time on (tl).

17. Perform the weekly gross check by blocking the air flow with a large rubber stopper and verifying the displayed flow reads zero. Record test result.

18. Read and record the current flow rate (RI).

19. Compare current flow rate (RI) to previous ending flow rate (R2).

NOTE: The regulator will generally maintain a constant flow regardless of filter loading.

(a) If a substantial difference is found, investigate and identify cause. If condition can not be resolved, take the unit out of service and replace.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 ENVIRONMENTAL MANUAL

20. Calculate total volume for the sampling period and record, if required.

21. Record any unusual conditions or observations in the space provided at the bottom of the form.

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

Label and forward all applicable air samples to the State of Wisconsin.

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

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

c. Calibration Calibrate the pump flow meters at initial installation and at yearly intervals thereafter by connecting a laboratory-qualityreference flow meter with NIST traceable calibration to the filter face with the particulate filter and charcoal cartridge in position. Upon completion, a calibration sticker is affixed to, or near, the flow meter. The results are recorded on Form PBF-4020.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 ENVIRONMENTAL MANUAL

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

For normal operation, the regulators should be adjusted to maintain a true flow rate of 28-30 liters per minute. Adjustments are made by turning the screw marked FLOW ADJ located on the side of the regulator body:

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

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

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

2.4.6 Milk Because of iodine decay and protein binding of iodine in aging milk samples, speed is imperative in processing and samples must be kept cool to avoid degradation and spoilage of the samples. Milk samples are obtained monthly in conjunction with the State of Wisconsin Milk Sampling Program from three individual dairy farmers located north, south, and west of the site. Milk sampling data can also be obtained from the Kewaunee Power Station (KPS),

whose radiological environmental monitoring program includes samples taken from a dairy in Green Bay, WI. This location could act as a control location.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30, 201 1 ENVIRONMENTAL MANUAL Because two of the three sites are co-located, the PBNP pickup is coordinated to coincide with the State arranged schedule. The pickup usually will be the second Wednesday of the month.

The following sequence should be followed:

a. After verifying the State milk pickup date with the Manitowoc Public Health Department (Mr. Mark Chatenka, phone number 683-4454), notify dairies of pickup date.

b. Because the milk must be kept cool, but not frozen, fill enough cubitainers, or other appropriate containers, with water and freeze to be able to put one in each shipping container. Fill the containers with water and freeze the day preceding the pickup or use ice packs.

c. The milk from the Strutz farm (E-21) must be picked up before 0900 because that is the time the Strutz milk is shipped. A late arrival may mean a missed sample. Milk from sites E-1 1 and E-40 may be picked up any time after the Strutz pickup.

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

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

If shipment cannot occur on the collection day, store the milk in the environmental refrigerator at the SBCC overnight. DO NOT FREEZE.

e. Complete a PBNP sample tag according to Section 2.2.7 for each gallon sample and place in the box with the sample and ice or ice packs. Do not seal the box. Place the samples in insulated containers and turn them over to Ready Stores personnel for shipment. Make sure that the cover letter and, as appropriate, the contractor data collection sheets are sent according to Section 2.2.8 of this manual.

2.4.7 Algae Filamentous algae are collected from pilings or rocks three times per year, as available, from two locations. The long, grassy, dark green algae can normally be cut with scissors. The shorter, light green algae normally must be scraped from rocks or pilings. When scraping algae, be careful not to include pieces of rock in the sample. The sample can be lightly rinsed in the same medium in which it is growing. This rinse will help rid the sample of pieces of rock and gravel that may have been inadvertently collected with the sample. Because rocks and sediment contain naturally occurring radioactive materials, their inclusion may give false sample results. Collect between 100 and 1000 gm of algae. A sample greater than 500 gm is preferred. Place the algae in a wide-mouth poly bottle or other appropriate container and label the container as director in Section 2.2.7. The algae must be kept cool to prevent spoilage.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30, 201 1 ENVIRONMENTAL MANUAL 2.4.8 Fish The fish for the Point Beach REMP are obtained from either the traveling screens as washed into the fish baskets or by other methods, as required. The two-fold objective of fish sampling is to obtain commercially and recreationally important fish (game fish) that occur in the vicinity of the plant and to determine if there is evidence of PBNP released radionuclides in the fish.

There are three confounding factors affecting this objective. The first is the recycling of non-PBNP sources such as fallout from atmospheric weapons testing in the 1950s and 1960s and subsequent Chinese tests, fallout from the Chernobyl accident, and release from other plants on Lake Michigan. Due to the long residence time of water in Lake Michigan (about 200 years),

radionuclides entering Lake Michigan remain in the lake for a long time. This means that a long half life radionuclide such as Cs- 137 is still present in the lake and in the fish.

The second confounding factor is the migratory behavior of the fish. In addition to moving around the lake, fish move from deep water to the shallower, inshore areas. It is only when the fish are in the inshore area that they are susceptible to being drawn into the PBNP water intake. Therefore, the radioactivity in the fish so caught may not originate from PBNP but from any of the above named sources.

In addition to the migratory behavior of fish, fish sampling also is effected by the fish deterrent system used at the PBNP water intake. The purpose of this system is to prevent schools of fish from being sucked into the cooling water intake.

As a result of all these factors, the availability of fish is not uniform throughout the year. Based on experience, the period from late Spring to early Fall appears to be the best period for obtaining game fish. Therefore, fish for the PBNP REMP will be sent for analysis at least twice a year based on seasonal availability. Fish also are supplied to the State of Wisconsin at the same frequency. (Fish may be sent more frequently if available.)

Operations removes the fish from the fish basket pursuant to 01 38 Attachment D. Each game fish is identified, placed in a clear plastic bag and the bag sealed, and the collection date and fish name written on the bag. The fish are placed in the game fish freezer in the pump house. Trash fish, such as carp are bagged and placed in the trash fish freezer.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30, 201 1 ENVIRONMENTAL MANUAL Because individual fish are analyzed, emphasis is placed on large fish which will yield at least 1000 grams (2.2 Ibs.) of fillets in order to easily achieve the required LLD. Because of the aforementioned factors, it may not be possible to have enough large fish to fulfill the 1000 gram requirement. When this occurs, the lab will adjust count time on the available fish in order to achieve the required LLD.

1. Obtain the game fish from the freezer and package for shipment to the PBNP contracted radioanalytical lab and to the State. (If no game fish are available, trash fish from the larger freezer in the pump house may be used.)

2. Pack fish in an insulated container with ice or other similar cold media, as necessary, to prevent spoilage of the fish during transit. To aid in preventing the fish from thawing during transit, fish should be shipped so that they will arrive on or before Friday. If this is not possible, include enough cooling material so that the fish will not spoil if sitting on a loading dock over the weekend.

3. Send fish at the end of May and the end of August.

4. Divide the available fish approximately in half for shipment with PBNP contracted radioanalytical lab receiving the larger portion when an odd number of fish are available. If additional game fish are available later in the year, they will be sent during the fourth quarter.

5. The cognizant Chemist will make the final decision should fish sampling questions arise.

2.4.9 Soil Soil integrates atmospheric deposition and acts as a reservoir for long-lived radionuclides. Although soil sampling is a poor technique for assessing small incremental releases and for monitoring routine releases, it does provide a means of monitoring long-term trends in atmospheric deposition in the vicinity of PBNP. Therefore, soil samples are obtained two times per year from specified locations.

Clear the vegetation from a 6" x 6" area, being careful to leave the top layer of soil relatively intact. Remove root bound soil by shaking the soil onto the cleared area or into the sample container before discarding the roots. When necessary, it is preferable to leave some roots in the soil rather than to lose the top layer of soil.

Page 23 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30, 20 11 Remove the soil to a depth of three inches. If necessary, expand the area, instead of digging deeper, to obtain the required amount of sample. If an area larger than 6" x 6" is used, notify Chemistry of the area used. The minimum acceptable quantity is 500 grams. Place the entire soil sample in a wide-mouth poly bottle or another appropriate container. If a plastic bag is used, seal the bag with tape. Label the sample as directed in Section 2.2.7.

This procedure assumes that the samples are obtained from undisturbed land; land that has not been plowed within approximately the last 25 years. If the land has been plowed, the soil should be sampled to the plow depth which typically is eight inches. Place the soil in a clean bucket or appropriate size plastic bag, homogenize the soil and place 1000 grams of the well mixed soil sample in a plastic bag, or other appropriate container, and label as described above.

2.4.10 Shoreline Sediment Shoreline sediment consisting of sand and smaller grain size material is sampled two times per year from specified locations. The 1000 gram sample is collected, from beach areas near the water ridge. At each location collect representative samples of sediment types roughly in proportion to their occurrence. For example, at E-06 avoid collecting a sample which consists exclusively of the dark-brown to black sediments which occur in layers up to several inches thick. Package the sample in a wide-mouth poly bottle or other appropriate container and label as described in Section 2.2.7.

Milk Survey The milk sampling program is reviewed annually, including a visual verification of animal grazing in the vicinity of the site boundary, to ensure that sampling locations remain as conservative as practicable. The verification is conducted each summer by cognizant PBNP personnel. Because it is already assumed that milk animals may graze up to the site boundary, it is only necessary to verify that these animals have not moved onto the site. No animal census is required. Upon completion of the visual check, a memo will be generated to document the review and the memo sent to file. To ensure performance of the annual verification, "milk review" is identified on the sampling checklist (i.e., the PBF-4121a-1 series).

Page 24 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 ENVIRONMENTAL MANUAL TABLE 2-1 RECOMMENDED MINIMUM SAMPLE SIZES Sample Type Vegetation 100 -1000 gm Lake Water 8 liters (2 gal)

Air Filters 250 rn3 Well Water 8 liters (2 gal)

Milk 8 liters (2 gal)

Algae 100-1000 gm Fish (edible portions) 1000 gm Soil 500-1000 gm Shoreline Sediment 500-1000 gm Page 25 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 ENVIRONMENTAL MANUAL TABLE 2-2 SAMPLE TYPES AND ASSOCIATED LOWER LEVEL OF DETECTION (LLD) AND NOTIFICATION LEVEL VALUES NOTIFTCATION LEVELS WEIGHTED SAMPLE REPORTING NRC PB&~) SUM TYPE UNIT PARAMETER LLD(~) (Regulatory) (Admin.) ACTION LEVEL Vegetation pCi/g wet Gross Beta CS-137 CS-134 1-131 0

Shoreline pCi/g dry Gross Beta Sediment and CS-137 Soil other@)

Algae pCi/g wet Gross Beta CS-137 CS-134 CO-58 Co-60 other@)

Fish pCi/g wet Gross Beta CS-137 CS-134 CO-58 Co-60 Mn-54 Fe-59 Zn-65 other@)

TLDs m a 7 days Gamma Exposure 5 d 7 days

~akewater(~) p ~ i / ~ - ~ .Gross

~ . ( Beta d) and Well Water CS-134 CS-137 Fe-59 Zn-65 Zr-Nb-95 Ba-La-140 Co-58 Co-60 Page 26 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 ENVIRONMENTAL MANUAL TABLE 2-2 SAMPLE TYPES AND ASSOCIATED LOWER LEVEL OF DETECTION (LLD) AND NOTIFICATION LEVEL VALUES Lakewater p ~ Y L - ~ . ~ . ( dMn-54

) 15 (10) 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 Air Filter p~i/m3 Gross Beta 0.01 --- 1.O ---

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 1 .O 2.5 0ther'"' 0.1 --- 1.O ---

(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.

(c) Other refers to non-specified identifiable gamma emitters, resulting fi-om the operation of PBNP. Naturally occurring radionuclides are not included.

(d) T.S. =total solids.

(e) No drinking water Page 27 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30, 20 11 ENVIRONMENTAL MANUAL TABLE 2-3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Location Code Location Description E-0 1 Primary Meteorological Tower, South of the plant E-02 Site Boundary Control Center - East Side of Building E-03 Tapawingo Road, about 0.4 Miles West of Lakeshore Road E-04 North Boundary E-05 Two Creeks Park, the TLD is on South side of Two Creeks Road, West of Lakeshore Road on first pole West of Lakeshore.

E-06 Point Beach State Park - Water and shoreline sediment samples at the Coast Guard Station; soil and vegetation f?om the Point Beach State Park campground area N of the Coast Guard Station and on the West side of County Road 0 ; TLD located South of lighthouse on telephone pole.

WPSC Substation on County Rt. V, about 0.5 Miles West of Hwy. 42 G. J. Francar Property, at the SE Corner of the Intersection of Cty. B and Zander Road Nature Conservancy, East side of Hwy 42. Comer of Hwy 42 and Cty. BB. On pole North side of Entrance.

PBNP Site Well Lambert Dairy Farm, 1523 Tapawingo Road, 0.5 miles West of Saxonburg Road Discharge Flume 1 Pier, U-l side Pumphouse South Boundary, about 0.2 miles East of Site Boundary Control Center SW Comer of Site, N side of Nuclear Rd at junction with Twin Elder Rd.

WSW, Hwy. 42, Residence, about 0.25 miles North of Nuclear Road North of Mishicot, Cty. B and Assman Road, NE Comer of Intersection NW of Two Creeks at Zander and Tannery Roads Reference Location, 17 miles SW, at Silver Lake College Local Dairy Farm just South of Site (R. Strutz) on Lakeshore and Irish Roads West Side of Hwy. 42, about 0.25 miles North of Johanek Road Greenfield Lane, about 4.5 Miles South of Site, 0.5 Miles East of Hwy. 42 North Side of County Rt. V, near intersection of Saxonburg Road South Side of County Rt. BB, about 0.5 miles West of Norman/Saxonberg Road 804 Tapawingo Road, about 0.4 miles East of Cty. B. North Side of Road NE comer of Saxonburg and Nuclear Roads, about 4 Miles WSW TLD on westemmost pole between the 2nd and 3rd parking lots, On microwave tower fence NE comer at Intersection of Tapawingo and Lakeshore Roads.

On utility pole North side of Tapawingo Road closest to the gate at the West property line Page 28 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 ENVIRONMENTAL MANUAL TABLE 2-3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS On a conduitlpole located near the junction of property lines, about 500 feet east of the west gate in line with first designated treeline on Tapawingo Road and about 1200 feet south of Tapawingo Road. The location is almost under the power lines between the blue and gray transmission towers. (The conduit/pole is about 6 feet high).

Lake Michigan shoreline accessed fiom 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 1.8 miles north of intersection of Highway 42 and Nuclear Road (Manitowoc County), on West side of Highway 42.

E-4 1 NW corner of Woodside and Nuclear Roads (Kewaunee Co.)

E-42 NW comer of Church and Division, East of Mishicot E-43 West Side of Tannery Road South of Elmwood (7th pole South of Elmwood)

E-TC Transportation Control; Reserved for TLDs Page 29 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,20 11 ENVIRONMENTAL MANUAL TABLE 2-4 PBNP RADIOLOGICAL ENVIRONMENTAL SAMPLE COLLECTION AND ANALYSIS FREQUENCY Sample Type Sample Codes Analyses Frequency Environmental Radiation E-01, -02, -03, -04, -05, TLD Quarterly Exposure -06, -07, -08, -09, -12,

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

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

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

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

-42, -43, -TC Vegetation E-01, -02, -03, -04, -06, Gross Beta 3 x 1 as

~ available

-08, -09, -20, Gamma Isotopic Analysis Algae Gross Beta 3xIyr as available Gamma Isotopic Analysis Fish Gross Beta 2dyr as available Gamma Isotopic Analysis (Analysis of edible portions only)

Well Water Gross Beta, H-3 Quarterly Sr-89,90,I-131 Gamma Isotopic Analysis (on total solids)

Lake Water Gross Beta Monthly H-3, Sr-89,90 Quarterly composite of monthly collections 1-131 Monthly Gamma Isotopic Analysis Monthly (on total solids)

Milk Sr-89, 90 Monthly 1-13 1 Gamma Isotopic Analysis Air Filters E-01, -02, -03, -04, Gross Beta Weekly (particulate)

-08, -20 1-131 Weekly (charcoal)

Gamma Isotopic Analysis Quarterly (on composite particulate filters)

Soil E-01, -02, -03, -04, Gross Beta 2xj~r

-06, -08, -09, -20, Gamma Isotopic Analysis Shoreline Sediment E-01, -05, -06, -12, Gross Beta 2dyr

-33 Gamma Isotopic Analysis Page 30 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 ENVIRONMENTAL MANUAL TABLE 2-5 SAMPLES COLLECTED FOR STATE OF WISCONSIN Sample Type Location Frequency

1. Lake Water E-0 1 Monthly

2. Air Filters E-07 Weekly E-08

3. Fish Semiannually, As Available

4. Precipitation E-04 Twice a month, E-08 As Available

5. Milk E-2 1 Monthly E-40

6. Well Water E-10 2 timeslyear Page 3 1 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 ENVIRONMENTAL MANUAL FIGURE 2-1a RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Page 32 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,20 11 ENVIRONMENTAL MANUAL FIGURE 2-lb RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS FIGIRE 2-lb S l TE MAP POINT BEACH NUCLEAR PLANT 0 110 6 A I R CGI FILE 10141 Page 33 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 23 March 30,201 1 ENVIRONMENTAL MANUAL FIGURE 2- 1c RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Page 34 of 34 INFORMATION USE