Text

2018 Annual Monitoring Report
	ML19120A177
Person / Time
Site:	Point Beach
Issue date:	04/26/2019
From:	Schultz E; Point Beach
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NRC 2019-0014
	Download: ML19120A177 (451)
	v • d • e

{{#Wiki_filter:NEXTera ENERGY S POINT BEACH April 26, 2019 NRC 2019-0014 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 2018 Annual Monitoring Report Enclosed is the Annual Monitoring Report for PBNP Units 1 and 2, for the period January 1 through December 31, 2018. This letter contains no new regulatory commitments and no revisions to existing regulatory commitments. Sincerely,

     ~n~ach, LLC Eric Schultz Licensing Manager Enclosure cc:         Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW American Nuclear Insurers WI Division of Public Health, Radiation Protection Section Office of Nuclear Material Safety and Safeguards, US NRC NextEra Energy Point Beach, LLC 6610 Nuclear Road , Two Rivers, WI 54241

ENCLOSURE ANNUAL MONITORING REPORT 2018 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT DOCKETS 50-266 (UNIT 1), 50-301 (UNIT 2), 72-005 (ISFSI) RENEWED LICENSES DPR-24 and DPR-27 ~~~-_, January 1, 2018 through December 31, 2018

TABLE OF CONTENTS Summary 1 Part A: Effluent Monitoring 1.0 Introduction 4 2.0 Radioactive Liquid Releases 5 3.0 Radioactive Airborne Releases 12 4.0 Radioactive Solid Waste Shipments 18 5.0 Nonradioactive Chemical Releases 21 6.0 Circulating Water System Operation 22 Part 8: Miscellaneous Reporting Requirements 7.0 Additional Reporting Requirements 23 Part C: Radiological Environmental Monitoring 8.0 Introduction 25 9.0 Program Description 26 10.0 Results 38 11 .0 Discussion 43 12.0 REMP Conclusion 59 Part D: Groundwater Monitoring 13.0 Program Description 60 14.0 Results and Discussion 63 15.0 Groundwater Summary 69 Appendix 1: Environmental, Inc. Midwest Laboratory, "Final Report for Point Beach Nuclear Plant" Appendix 2: Offsite Dose Calculation Manual, Revision 20, issued 02/27/2018 ii

LIST OF TABLES Table 2-1 Comparison of 2018 Liquid Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives 5 Table 2-2 Summary of Circulating Water Discharge 8 Table 2-3 Isotopic Composition of Circulating Water Discharges 9 Table 2-4 Beach and Subsoil System Drains -Tritium Summary 10 Table 3-1 Comparison of 2018 Airborne Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives 15 Table 3-2 Radioactive Airborne Effluent Release Summary 15 Table 3-3 Isotopic Composition of Airborne Releases 16 Table 3-4 Comparison of Airborne Effluent Doses 17 Table 4-1 Quantities and Types of Waste Shipped from PBNP in 2018 18 Table 4-2 2018 PBNP Radioactive Waste Shipments 18 Table 4-3 2018 Estimated Solid Waste Major Radionuclide Composition 19 Table 4-4 Corrected Type A Radionuclide Values for the 2009 and 2014 AMRs 20 Table 6-1 Circulating Water System Operation for 2018 22 Table 9-1 PBNP REMP Sample Analysis and Frequency 29 Table 9-2 PBNP REMP Sampling Locations 30 Table 9-3 ISFSI Sampling Sites 34 Table 9-4 Minimum Acceptable Sample Size 34 Table 9-5 Deviations from Scheduled Sampling and Frequency During 2018 35 Table 9-6 Sample Collection for the State of Wisconsin 35 Table 10-1 Summary of Radiological Environmental Monitoring Results for 2018 40-41 Table 10-2 Feed Crops Grown on Point Beach Land 42 Table 10-3 Average ISFSI Fence TLD Results for 2018 42 Table 11-1 Average Indicator TLD Results from 1993-2018 43 Table 11-2 Average ISFSI Fence TLD Results (mR/7days) 44 Table 11-3 Average TLD Results Surrounding the ISFSI (mR/7days) 46 Table 14-1 Intermittent Streams and Bogs 63 Table 14-2 2018 Beach Drain Tritium 64 Table 14-3 2018 East Yard Area Manhole Tritium (pCi!L) 65 Table 14-4 2018 Fagade Well Water Tritium (pCi/L) 66 Table 14-5 2016-2018 Unit 2 Fagade SSD Sump H-3 (pCi/L) 67 Table 14-6 2018 Potable Well Water Tritium Concentration (pCi/L) 68 Table 14-7 2018 Quarterly Monitoring Well Tritium (pCi!L) 68 LIST OF FIGURES Figure 9-1 PBNP REMP Sampling Sites 31 Figure 9-2 Map of REMP Sampling Sites Located Around PBNP 32 Figure 9-3 Enhanced Map Showing REMP Sampling Sites Closest to PBNP 33 Figure 11-1 ISFSI Area TLD Results (1995- 2018) 46 Figure 11-2 Comparison of ISFSI Fence TLDs to Selected REMP TLDs 47 Figure 11-3 Sr-90 Concentration in Milk (1997- 2018) 48 Figure 11-4 Annual Average Air Gross ~ (1993- 2018) 49 Figure 11-5 2018 Airborne Gross Beta 49 Figure 11-6 2015 Airborne Gross Beta 50 Figure 11-7 E-01 Results 1971 - 2018 57 Figure 11-8 Comparison of E-03 and E-20 Results 1971-2018 57 iii

Figure 11-9 Comparison of E-01, E-02, E-03, and E-04 Results 1992 - 2018 58 Figure 11-10 E-03, E-31, and Background Site E-20 Results 1992- 2018 59 Figure 13-1 Groundwater Monitoring Locations 62 iv

I

SUMMARY

I The Annual Monitoring Report for the period from January 1, 2018, through December 31, 2018, 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 Renewed 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 2018, the following Curies (Ci) of radioactive material were released via the liquid and atmospheric pathways: Liquid Atmospheric Tritium (Ci) 981 94.1 1 Particulate (Ci) 0.0645 0.00003 Noble Gas (Ci) 0.0126 0.607 2 C-14 0.031 11.74 Atmosphenc partrculate rncludes radrorodrne (1-131 133) . 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 (MEl) 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) and comply with the EPA's limits in 40CFR190. The maximum annual calculated doses in millirem (mrem) or millirad (mrad) are shown below and compared to the corresponding design objectives of 10 CFR 50, Appendix I. LIQUID RELEASES Dose Category Calculated Dose Appendix I Dose %Appendix I Whole body dose 0.00224 mrem 6 mrem 0.037 Organ dose 0.00282 mrem 20 mrem 0.014 ATMOSPHERIC RELEASES Dose Category Calculated Dose Appendix I Dose %Appendix I Particulate organ dose 0.0116 mrem 30 mrem 0.039 Noble gas beta air dose 0. 0000383 m rad 40 mrad 0.00010 Noble gas gamma ray air dose 0.000101 mrad 20 mrad 0.00051 Noble gas dose to the skin 0.000140 mrem 30 mrem 0.00047 Noble gas dose to the whole body 0.0000952 mrem 10 mrem 0.00095 1

The results show that during 2018, the doses from PBNP effluents were =s;Q.039% of the Appendix I design objectives. This is slightly lower than the 2017 results of 0.061 °/o. Therefore, operation of the PBNP radwaste treatment system continues to be ALARA. A survey of land use with respect to the location of dairy cattle was made pursuant to Section 12.2.5 of the PBNP ODCM. As in previous years, no dairy cattle were found to be grazing at the site boundary. Therefore, the assumption that cattle graze at the site boundary used in the evaluation of doses from PBNP effluents remains conservative. Of the sixteen compass sectors around PBNP, six are over Lake Michigan. A land use census (LUC) of the remaining ten sectors over land identifies any changes in the closest garden, occupied dwelling, and dairy in each sector. The 2017 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 2018 Radiological Environmental Monitoring Program (REMP) collected 767 individual samples for radiological analyses. Quarterly composites of weekly air particulate filters generated an additional 24 samples and quarterly composites of monthly lake water samples resulted in a further 16 samples. This yielded a total of 807 samples. The ambient radiation measurements in the vicinity of PBNP and the ISFSI were conducted using 145 sets of thermoluminescent dosimeters (TLDs). Air monitoring from six different sites did not reveal any effect from Point Beach effluents. Terrestrial monitoring consisting of soil, vegetation, crops, and milk found no influence from PBNP. Similarly, samples from the aquatic environment, consisting of lake and well water, and fish revealed no buildup of PBNP radionuclides released in liquid effluents. (No algae were available in 2018). Therefore, the data shows no environmental effect from plant operation. Six new, loaded dry storage units were added to the ISFSI in 2018. The total number now is 50 dry storage casks: 16 ventilated, vertical storage casks (VSC-24) and 34 NUHOMS, horizontally stacked storage modules. The subset of the PBNP REMP samples used to evaluate the environmental impact of the PBNP ISFSI showed no environmental impact from its operation. The environmental monitoring conducted during 2018 confirmed that the effluent control program at PBNP ensured a minimal impact on the environment. One-hundred-fifty-seven (157) samples were analyzed for tritium as part of the groundwater protection program (GWPP). These samples came from drinking water wells, monitoring wells, yard drain outfalls, yard manholes, surface water on site, the sump for the subsurface drainage system (SSD - located under the plant foundation), and four groundwater foundation integrity monitoring wells located in the facades. The results for all but the fagade wells show no substantial change in tritium from previous years. In May 2018 increased tritium concentration was observed in three of the four fagade wells. The tritium increased to 911 - 4486 pCi/L from the normal range of -200 pCi/L. No gamma emitters were found in the elevated tritium samples. Further analyses found no Sr-90, Fe-55, or Ni-63 in the high tritium samples. No drinking water wells (depth > 100 feet) have any detectable tritium. 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 tritium whereas none was detectable in the wells monitoring the potential offsite tritium movement. 2

Gamma scans of groundwater samples originating within the power block found no plant related gamma emitters. Fagade well samples obtained in March before the increase, and then again in July, August, and October had tritium results within the expected ranges (-200 pCi/L). The results of GWPP monitoring indicate no significant change from previous years for all but the increase observed in the fagade wells in May 2018. 3

I Part A EFFLUENT MONITORING I

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. The appropriate portions of the radwaste treatment systems are used as required to keep both liquid and atmospheric 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 ISFSI annual reporting requirement pursuant to 10 CFR 72.44(d)(3) is no longer applicable (

Reference:

64 FR 33178). Any release of radioactive materials from the operation of the ISFSI must comply with the limits of Part 20 and Part 50 Appendix I design objectives. The dose criteria for effluents and direct radiation specified by 10 CFR 72.104 states that during normal operations and anticipated occurrences, the annual dose equivalent to any real individual beyond the controlled area must not exceed 25 mrem to the whole body, 75 mrem to the thyroid, and 25 mrem to any other organ. The dose from naturally occurring radon and its decay products are exempt. Because the loading of the storage casks occurs within the primary auxiliary building of PBNP, the doses from effluents due to the loading process will be assessed and quantified as part of the PBNP Radiological Effluent Control Program. 4

2.0 RADIOACTIVE LIQUID RELEASES The radioactive liquid release path to the environment is via the circulating water discharge. A liquid waste treatment system in conjunction with administrative controls is used to minimize the impact on the environment and maintain doses to the public ALARA from the liquid releases. 2.1 Doses From Liquid Effluent Doses from liquid effluent are calculated using the methodology of the Offsite Dose Calculation Manual (ODCM). These calculated doses use parameters such as the amount of radioactive material released, the total volume of liquid, the total volume of dilution water, and usage factors (e.g., water and fish consumption, shoreline and swimming factors). These calculations produce a conservative estimation of the dose. For compliance with 10 CFR 50, Appendix I design objectives, the annual dose is calculated to the hypothetical maximally exposed individual (MEl). The MEl 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 MEl 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 MEl is a very small fraction of the Appendix I design objective. Table 2-1 Comparison of 2018 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) 0.00224 0.037 20 (any organ) 0.00282 0.014 2.2 2018 Circulating Water Radionuclide Release Summary Radioactive liquid releases via the circulating water discharge are summarized by individual source and total curies released on a monthly basis, semi-annual and annual totals (Table 2-2). These releases are composed of processed waste, wastewater effluent, and blowdown from Units 1 and 2. The wastewater effluent consists of liquid from turbine hall sumps, plant well house backwashes, sewage treatment plant effluent, water treatment plant backwashes, the Unit 1 and 2 facade sumps and the subsurface drainage system sump. 2.3 2018 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. 5

The 2018 processed waste volume (Table 2-2) decreased from 2017 (9.89E+05 gallons to 9.21 E+05 gallons). However, there was an increase in the total isotopic curie distribution of gamma emitters plus hard-to-detects from 7.36E-02 Ci to 9.56E-02 Ci, which is similar to what was observed in 2016 (9.98E-02 Ci). The total antimony in 2018 increased to 3.49E-02 Ci from 5.87E-03 Ci in 2017, which is comparable to the concentration of antimony (1.30E-02 Ci) discharged in 2016. The higher Sb in 2018 is attributable to post outage water processing. By contrast, Zr-Nb decreased about 77°/o from 3.19E-03 in 2017 to 7.30E-04 Ci in 2018. The tin isotopes Sn-113/117m also decreased from 7.97E-03 in 2017 to 1.93E-03 Ci in 2018. The 2018 C-14 increased to 3.1 OE-02 Ci from 2.22E-02 Ci in 2017. No strontium isotopes (Sr-89, Sr-90, Sr-92) were discharged in 2018. Tritium increased from 887 Ci in 2017 to 981 Ci in 2018, a roughly 10% increase. The increase in tritium is attributable to each unit reaching their peak RCS tritium concentration during 2018 and increased dilutions during online operation. 2.4 Beach Drain System Releases Tritium Summary Beach drain is the term used to describe the point at which the site yard drainage system empties onto the beach of Lake Michigan. Six of these outfalls carry yard and roof drain runoff to the beach. A seventh outfall drains a small portion of the grassy area on top of the bluff overlooking the lake. The plant foundation has a subsurface drainage system (SSD) around the external base of the foundation. This SSD relieves hydrostatic pressure on the foundation by draining water away from the foundation. The drainage pipes empty out onto the beach. In 2014, the SSD outfalls, designated as S-12 and S-13, were added to the beach drain sampling program. Their quarterly results are presented with the other beach drains. The quarterly results from the monthly beach drain and SSD samples are presented in Table 2-4. The total monthly flow is calculated assuming that the flow rate at the time of sampling persists for the whole month. In 2018, no tritium was observed at the effluent LLDs. Tritium found in the beach drains is not included in the effluent totals unless it can be shown to be the result of a spill or similar event. Because the source of beach drain tritium has been determined to be recapture, including beach drain tritium in the effluent totals would be double counting (NRC RIS 2008-03, Return/re-use of previously discharged radioactive effluents). The principle source of water for the beach drains is the yard drain system. Yard drain water sources are rain and snow melt containing recaptured tritium. During the winter natural melting is the principle source. (Additionally, various roof drains connect to the yard drain system. In addition to precipitation, the roof drains also carry condensate from various building AC units. A secondary source may be groundwater in leakage. This is evidenced by flow during periods of no precipitation. Because there are no external storage tanks or piping that carries radioactive liquids, the main source of radioactivity for this system is recapture/washout of airborne tritium discharges via the yard drain system. Because of these various recapture sources, the beach drains also are sampled as part of the groundwater 6

monitoring program. These results and other groundwater monitoring results are presented in Part D of this Annual Monitoring Report. 7

Table 2-2 Summary of Circulating Water Discharge January 1, 2018 through December 31, 2018 I I Total Annual I Jan I Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec Total Total Activity Released (Ci) Gamma ~can(+H 1Ds) 2.12E-03 3.23E-03 5.77E-04 3.19E-04 7.33E-03 4.46E-04 1.40E-02 1.98E-03 2.23E-03 1.03E-02 3.04E-02 6.91E-03 2.98E-02 9.56E-02 Gross Alpha ND ND ND ND ND ND ND ND ND ND ND ND ND ND Tritium 4.09E+01 1.13E+02 7.78E+OO 1.57E+01 1.74E+02 1.07E+01 3.62E+02 8.66E+01 1.65E+02 1.47E+02 5.73E+01 7.36E+OO 1.56E+02 9.81E+02 Strontium (89/90/92) ND ND ND ND ND ND ND ND ND ND ND ND ND ND Noble Gases 6.90E-04 1.29E-03 ND ND 7.89E-04 ND 2.77E-03 3.83E-04 1.62E-03 2.28E-03 1.99E-03 4.46E-04 3.09E-03 1.26E-02 Total Vol Released (gal) Processed Waste 4.47E+04 4.42E+04 3.24E+04 4.17E+04 6.36E+04 4.20E+04 2.69E+05 7.12E+04 7.77E+04 1.38E+05 1.55E+05 1.02E+05 1.10E+05 9.21E+05 Waste Water Effluent 3.49E+06 3.38E+06 3.66E+06 3.69E+06 3.35E+06 3.17E+06 2.07E+07 3.67E+06 3.32E+06 3.47E+06 3.70E+06 3.65E+06 3.43E+06 4.20E+07 U1 SG Slowdown 2.68E+06 2.41 E+06 2.68E+06 2.65E+06 2.66E+06 2.59E+06 1.57E+07 2.68E+06 2.75E+06 2.65E+06 2.61E+06 2.58E+06 3.22E+06 3.22E+07 U2 SG Slowdown 2.66E+06 2.42E+06 2.68E+06 2.58E+06 2.60E+06 2.59E+06 1.55E+07 2.67E+06 2.68E+06 2.56E+06 1.59E+06 4.43E+06 2.83E+06 3.23E+07 Total Gallons 8.88E+06 8.26E+06 9.05E+06 8.96E+06 8.67E+06 8.40E+06 5.22E+07 9.08E+06 8.82E+06 8.82E+06 8.06E+06 1.08E+07 9.60E+06 1.07E+08 Total cc 3.36E+10 3.12E+10 3.42E+10 3.39E+10 3.28E+10 3.18E+10 1.98E+11 3.44E+10 3.34E+10 3.34E+10 3.05E+10 4.07E+10 3.63E+10 4.06E+11 UIIUtion VOI(CC}" 7.91E+13 7.14E+13 7.91E+13 7.65E+13 1.25E+14 1.23E+14 5.53E+14 1.27E+14 1.27E+14 1.23E+14 9.05E+13 1.23E+14 7.53E+13 1.22E+15 Avg diluted discharge cone (~Ci/cc) Gamma ~can (+HTDS) 2.68E-11 4.52E-11 7.30E-12 4.17E-12 5.88E-11 3.63E-12 1.56E-11 1.76E-11 8.39E-11 3.36E-10 5.63E-11 3.95E-10 Gross Alpha ND ND ND ND ND ND ND ND ND ND ND ND Tritium 5.17E-07 1.58E-06 9.84E-08 2.05E-07 1.40E-06 8.71 E-08 6.82E-07 1.30E-06 1.20E-06 6.33E-07 5.99E-08 2.07E-06 Strontium (89/90/92) ND ND ND ND ND ND ND ND ND ND ND ND Noble Gases 8.72E-12 1.81E-11 ND ND 6.33E-12 ND 3.02E-12 1.28E-11 1.85E-11 2.20E-11 3.63E-12 4.10E-11 Max Batch Discharge Cone (IJCi/cc) Tritium 2.46E-05 3.29E-05 5.96E-06 5.75E-06 3.25E-05 3.44E-06 3.31E-05 4.02E-05 3.88E-05 3.58E-05 1.63E-06 3.72E-05 Gamma Scan I 1.45E-1 0 2.42E-10 8.55E-11 1.07E-11 1.10E-10 3.37E-11 2.49E-1 0 3.85E-10 1.53E-09 5.50E-09_ '---?.11 E-09 6.19E-09 1 HTDs include Fe-55, C-14, Ni-63, and Tc-99. Does not include strontium which is totaled separately. 2 Circulating water discharge from both units. ND: means that the radionuclide was not identified in any samples and all analyses were performed with instrumentation meeting the lower limit of detection as required by the PBNP Offsite Dose Calculation Manual. 8

Table 2-3 Isotopic Composition of Circulating Water Discharges (Ci) January, 2018 through December 31, 2018 Total Total Nuclide Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec Jan-Dec H-3 4.09E+01 1.13E+02 7.78E+OO 1.57E+01 1.74E+02 1.07E+01 3.62E+02 8.66E+01 1.65E+02 1.47E+02 5.73E+01 7.36E+OO 1.56E+02 9.81E+02 C-14 1.69E-03 2.34E-03 ND ND 3.13E-03 ND 7.16E-03 1.46E-03 6.47E-04 3.96E-03 4.04E-03 1.77E-03 1.20E-02 3.11 E-02 F-18 1.57E-04 ND 4.82E-04 3.07E-04 5.35E-04 4.22E-04 1.90E-03 2.48E-04 3.74E-04 7.57E-04 1.30E-04 5.54E-04 4.88E-04 4.45E-03 Cr-51 ND ND ND ND ND ND ND ND ND ND 3.03E-03 5.83E-05 ND 3.09E-03 Mn-54 ND ND ND ND ND ND ND ND ND 2.11 E-05 6.40E-05 ND ND 8.51E-05 Fe-55 ND ND ND ND ND ND ND ND ND 5.21E-04 ND ND ND 5.21 E-04 Fe-59 ND ND ND ND ND ND ND ND ND ND 2.20E-05 ND ND 2.20E-05 Co-57 ND ND ND ND ND ND ND ND 1.15E-06 ND ND ND ND 1.15E-06 Co-58 5.89E-05 2.48E-04 3.38E-05 1.21 E-05 2.14E-05 4.40E-06 3.79E-04 3.42E-05 4.19E-05 1.58E-05 5.03E-03 9.35E-05 9.94E-05 5.69E-03 Co-60 1.58E-05 3.31 E-05 5.69E-06 ND 3.52E-05 1.99E-05 1.10E-04 4.86E-05 8.61E-05 6.80E-04 2.16E-03 1.31 E-04 6.79E-04 3.89E-03 Ni-63 ND 6.02E-05 2.56E-05 ND 3.13E-03 ND 3.22E-03 3.50E-05 ND ND 6.44E-04 ND 7.47E-05 3.97E-03 Zn-65 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Se-75 ND ND ND ND ND ND ND ND ND ND ND ND 6.37E-06 6.37E-06 As-76 ND ND ND ND ND ND ND ND ND ND 1.11 E-03 1.01 E-04 ND 1.21 E-03 Sr-90 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Sr-92 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Nb-95 ND ND ND ND ND ND ND ND ND ND 4.31 E-04 5.45E-06 ND 4.36E-04 Nb-97 ND ND ND ND ND ND ND ND ND ND 6.02E-05 ND ND 6.02E-05 Zr-95 ND ND ND ND ND ND ND ND ND ND 2.33E-04 ND ND 2.33E-04 Tc-99 3.55E-06 1.04E-05 ND ND 9.39E-06 ND 2.33E-05 5.93E-06 1.23E-05 6.77E-05 5.56E-05 1.00E-05 3.24E-03 3.41 E-03 Ag-11 Om ND ND ND ND ND ND ND ND 2.78E-06 1.68E-04 2.86E-04 ND 2.68E-05 4.84E-04 Sn-113 ND ND ND ND ND ND ND ND ND ND 2.01 E-05 ND ND 2.01E-05 Sn-117m 7.38E-05 7.03E-05 ND ND 1.23E-05 ND 1.56E-04 ND ND 3.21 E-06 1.48E-03 2.60E-04 1.48E-05 1.91 E-03 Sb-122 ND ND ND ND ND ND ND ND ND ND 1.47E-05 ND ND 1.47E-05 Sb-124 2.71 E-05 1.47E-04 2.86E-06 ND 7.27E-05 ND 2.50E-04 1.48E-05 7.80E-05 2.04E-04 5.50E-04 1.56E-04 7.34E-03 8.59E-03 Sb-125 9.06E-05 3.12E-04 2.57E-05 ND 3.82E-04 ND 8.10E-04 1.38E-04 9.86E-04 3.90E-03 1.10E-02 3.77E-03 5.70E-03 2.63E-02 1-131 ND ND ND ND ND ND ND ND ND ND ND ND ND ND 1-132 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Te-132 NO ND ND ND ND ND ND ND ND ND ND ND ND ND Cs-136 ND ND ND ND ND ND ND ND ND 5.09E-06 ND ND ND 5.09E-06 Cs-137 ND 4.77E-06 1.35E-06 ND ND ND 6.12E-06 ND ND ND ND ND ND 6.12E-06 Cs-138 ND ND ND ND ND ND ND ND ND ND ND ND 6.83E-05 6.83E-05 Xe-131m ND ND ND ND ND ND ND ND ND ND ND ND ND ND Xe-133 6.85E-04 1.28E-03 ND ND 7.85E-04 ND 2.75E-03 3.83E-04 1.59E-03 2.25E-03 1.92E-03 4.11 E-04 3.07E-03 1.24E-02 Xe-133m ND ND ND ND ND ND ND ND ND ND ND ND ND ND Xe-135 4.65E-06 1.57E-05 ND ND 3.85E-06 ND 2.42E-05 ND 3.57E-05 2.53E-05 6.83E-05 3.50E-05 1.93E-05 2.08E-04 ND: means that the radionuclide was not identified in any samples and all analyses were performed with instrumentation meeting the lower limit of detection as required by the PBNP Offsite Dose Calculation Manual. 9

Table 2-4 Beach and Subsoil System Drains -Tritium Summary January 1, 2018, through December 31, 2018 S-1 S-3 S-7 S-8 S-9 S-10 S-11 S-12 S-13 1st Qtr H-3 (Ci) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Flow (gal) 1.27E+05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2nd Qtr H-3 (Ci) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Flow (gal) 5.21E+05 3.08E+05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.32E+04 2.23E+04 3rd Qtr H-3 (Ci) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NS O.OOE+OO O.OOE+OO Flow (gal) 4.91 E+05 3.35E+04 O.OOE+OO 1.79E+05 O.OOE+OO O.OOE+OO NS O.OOE+OO O.OOE+OO 4th Qtr H-3 (Ci) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NS O.OOE+OO O.OOE+OO Flow (gal) 3.57E+05 2.68E+05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NS O.OOE+OO O.OOE+OO NS- No sample due to sample location no longer bemg mcluded m the sampling program (See Sect1on 13.0 for explanation). 2.6 Land Application of Sewage Sludge and Wastewater In 1988, pursuant to 10 CFR 20.302(a), Point Beach received NRC approval for the disposal of sewage sludge, which may contain trace amounts of radionuclides, by land application on acreage within the site. Land application of sewage sludge is regulated by the Wisconsin Department of Natural Resources. Point Beach has not land applied sewage sludge for over a decade. Therefore, Point Beach has not renewed its WI DNR permit to dispose of sewage sludge in this manner. There were no sludge or equalization basin disposals by land application during 2018. All disposals from the PBNP sewage treatment plant (STP) were done at the Manitowoc Sewage Treatment Plant. A total of 210,200 gallons in 35 shipments were made to Manitowoc. All sludge and equalization basin discharges were analyzed to environmental LLDs. Naturally occurring radionuclides such as Ra-226 and K-40 were present in all samples. For the 35 shipments in 2018 the total Ra-226 and K-40 were 126 !JCi and 158 !JCi, respectively. Small concentrations of H-3 (not detectable- 591 pCi/L) were found in seventeen (17) of the shipments for a total of 69.9 j.JCi. Based on the daily flow at the Manitowoc plant, the H-3 discharge concentration would be on the order of 0.21 pCi/L or 90,000 times lower than the EPA drinking water limit of 20,000 pCi/L. The STP H-3 is attributable to groundwater in-leakage at the STP lift station whose volume is known to increase after a heavy rain or snow melt event. The STP is in the groundwater flow path from the retention pond area and the lake. The STP H-3 concentrations are comparable to those found in the retention pond area monitoring wells. 10

2.7 Carbon-14 Carbon-14 (C-14) is a naturally occurring radionuclide. Nuclear weapons testing in 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 occurs naturally. Based on information from the NRC obtained at industry sponsored workshops, Point Beach began evaluating C-14 liquid discharges in 2009, prior to the issuance of Regulatory Guide 1.21 [RG 1.21 ], Rev 2 in June of 2009. Point Beach continues to analyze batch liquid waste discharges for C-14 and reporting the results in the Annual Monitoring Report. The NRC requested that all nuclear plants report C-14 emissions beginning with the 2010 monitoring reports. Pursuant to NRC guidance in RG 1.21 (Rev 2), evaluation of C-14 in liquid wastes is not required because the quantity released via this pathway is much less than that contributed by gaseous emissions. However, as stated above, Point Beach began C-14 analyses and reporting prior to the issuance of RG 1.21 (Rev 2). RG 1.21 states that a radionuclide is a principal effluent component if it contributes greater than 1% of the Appendix I design objective dose compared to the other radionuclides in the effluent type, or, if it is greater than 1%> of the activity of all radionuclides in the effluent type. In this case, C-14 is compared to other (non-tritium or noble gases) radionuclides discharged in liquids. For 2018, the monthly and total C-14 (3.11 E-02 Ci) in liquid discharges is documented in Table 2-3. The 2018 amount of C-14 released makes up about 28% of the non-tritium radionuclides released in liquids (3.11 E-02/1.08E-01). The liquid C-14 dose contribution is included in the doses calculated for the hypothetically, maximally exposed individual (Table 2-1). Under the parameters and pathways used for the dose calculations, the C-14 dose contribution to the infant age group ranges from 0.101 to 0.102% of the dose to the whole body and the applicable organs except for bone, for which C-14 contributes 22.3%> of the total dose. For the remaining age groups, the C-14 contributes roughly 88.5% of the bone dose and 6 - 16% of the dose to the whole body and to other organs specified in RG 1.1 09. 11

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 (MEl) 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 MEl doses, the energy deposited in the air by noble gas beta particles and gamma rays is calculated and compared to the corresponding Appendix I design objectives. A comparison of the annual Appendix I design objectives for atmospheric effluents to the highest organ dose and the noble gas doses calculated using ODCM methodology is listed in Table 3-1. C-14 is not included in the Appendix I calculations because it is not an Appendix I radionuclide. The C-14 dose calculation has been required since 2010 (see Sections 3.4 through 3.6, below, for a more detailed description) and is treated separately. The comparison between airborne effluent doses with and without C-14 is shown in Table 3-4. The highest Appendix I dose is 1.16E-02 mrem for the child age group thyroid. Had C-14 been included, the child-bone dose would have been the highest at 2.43E-01 mrem. Even with the inclusion of C-14 the doses demonstrate that releases from PBNP to the atmosphere continue to be ALARA at 0.8% of the dose objective. 3.2 Radioactive Airborne Release Summary Radioactivity released in airborne effluents for 2018 is summarized in Table 3-2. The particulate total decreased from 2.33E-04 Ci in 2017 to 3.27E-05 Ci in 2018. H-3 decreased from 148 Ci to 94.1 Ci. Noble gases decreased 6.15E-01 Ci to 6.07E-01 Ci in 2018. 3.3 Isotopic Airborne Releases The monthly isotopic airborne releases for 2018, from which the airborne doses were calculated, are presented in Table 3-3. Carbon-14 is not included in Table 3-3 because it was calculated and not measured. C-14 is discussed in the following sections. As in previous years the outage impact of the isotopic mixture is demonstrated in the comparison of the non-outage particulate releases. During October, four different particulates were identified in the airborne effluent whereas in the non-outage months, at most one was found. Most were released via the open hatch on the 66-foot elevation of containment. The convective flow through the open hatch during purge is unfiltered. Although the flow is into the fagade, there are two circumferential gaps around the fagade. It is assumed that the release into 12

fac;ade is transferred to the outside and therefore is treated as a release to the environment. 3.4 Carbon-14 C-14 is a naturally occurring radionuclide. Nuclear weapons testing of the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Small amounts of C-14 also are produced by nuclear reactors as neutrons interact with the dissolved oxygen and nitrogen in the primary coolant. However, the amount produced by nuclear reactors is much less than that produced by weapons testing or that occur naturally. The NRC has requested that nuclear plants report C-14 emissions. C-14 is a hard-to-detect radionuclide. It is not a gamma emitter and must be chemically separated from the effluent stream before it can be measured. Because nuclear plants currently are not equipped to perform this type of sampling, RG 1.21 allows for calculating C-14 discharges based on fission rates. The Electric Power Research Institute (EPRI) developed the methodology for calculating C-14 generation and releases for the nuclear industry. The results were published as Technical Report 1021106 (December 201 0), "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents." In addition to neutron flux, the percent oxygen and nitrogen in the VCTs is used in the C-14 calculation as both gases contribute to the generation of C-14. Pursuant to NRC guidance (Regulatory Guide 1.21, Rev 2, p. 16, June 2009), most of the C-14 emissions from nuclear plant occur in the gaseous phase. The Point Beach C-14 generation for 2018 was calculated using the EPRI guidance and the current core parameters resulting from the power uprate. The calculated amounts were 5.88 Ci for Unit 1 and 5.86 Ci for Unit 2 yielding a total of 11.74 Ci which is the same as 2016 and 2017. The 2018 calculated total11.74 Ci is roughly 400 times higher than the 3.1 OE-02 Ci of C-14 determined by analyses of composites from liquid waste batch discharges, steam generator blowdown, and other waste streams. 3.5 C-14 Airborne Effluent Dose Calculation The dose from the airborne C-14 is dependent on its chemical form. The C-14 released to the atmosphere consists of both organic and inorganic species. Both the inorganic and organic C-14 contribute to the inhalation dose. Only the inorganic 14C02 species contributes to the dose from the ingestion of photosynthetically incorporated C-14. The organic forms such as methane, CH 4 , are not photosynthetically active. For PWRs such as PBNP most of the gaseous C-14 occurs as methane, 14CH 4 , not as carbon dioxide, 14C02. The amount of 14C02 present in the PBNP airborne effluent has not been measured. However, such measurements have been made at a comparable PWR sites similar to the PBNP design. The Ginna nuclear generating station is of similar design to PBNP. It is a Westinghouse 2-loop PWR of the same vintage as PBNP and approximately the same power (prior to the PBNP power uprate). Measurements at Ginna for 18 months in 1980- 1981 (Kunz, "Measurement of 13

14 C Production and Discharge From the Ginna Nuclear Power Reactor," 1982) found that ten percent of the C-14 was discharged as 14 C0 2 . Therefore, 10°/o of the 11.74 Ci of the calculated C-14 for PBNP will be used in the ingestion dose calculations. C-14 dose calculations were made using the dose factors and the methodology of Regulatory Guide 1.1 09. The inhalation dose factors were updated for the 2018 calculation due to a change in the x/Q that is stated in the Point Beach ODCM Rev. 20. 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 14C0 2 or one of the organic forms, such as CH 4 , both would be inhaled and contribute to a lung dose. For the other existing pathways, milk, meat, and produce, the dose depends upon the amount incorporated into biomass consumed by cattle and people: forage for cattle and produce for humans. Incorporation only occurs via photosynthesis. Photosynthesis only incorporates 14C0 2 and hence the use only of the 10°/o 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 MEl as explained in Section 2.1. This approach utilizes all the pathways that are applicable to a hypothetical person residing at the site boundary. Because C-14 is present as a gas, the pathways are milk, meat, and produce (vegetables, fruit, and grain) and the Regulatory Guide 1.1 09, Table E-5 usage factors applied to the calculation. As such, the resulting dose will be conservative in that the produce usage factor includes grain and fruit and these pathways do not exist in the vicinity of the point for which the C-14 doses are calculated. Furthermore, because leafy vegetables are included in the produce pathway, they are not used as a separate pathway because that would result in double accounting for leafy vegetable dose contribution. Carbon-14 is not an Appendix I radionuclide. Therefore, airborne C-14 is not summed with the other airborne radioactive effluents for comparison of airborne effluent dose to the Appendix I dose objectives. However, the C-14 doses are presented and compared to the other radionuclide doses in Table 3-4. 3.6 C-14 Measurements No C-14 measurements were made of PBNP airborne effluents. In 2010, C-14 was measured in crops grown on fields in the owner controlled area located in the highest x/Q sector at the site's south boundary. One field is leased for feed corn by a dairy south of the plant. That dairy is part of the REMP. In an adjacent field soybeans are grown by another farmer. These two crops were sampled in this sector and as well as in a background location about 17 miles SW of the plant. Based on the measurement error, there was no statistical difference between the results obtained on site in the highest x/Q sector as compared to the background site some 17 miles away (2013 AMR, Table 10-3). These results demonstrated that the dose from C-14 in Point Beach airborne effluents should not measurably increase the C-14 dose compared to that received from naturally occurring C-14 in plants (1 mrem: NCRP Report 93, Ionizing Radiation Exposure of the Population of the United States, 1987, p.12). 14

Table 3-1 Comparison of 2018 Airborne Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives Annual Appendix I Design January-December Percent of Appendix I Category Objective Calculated Dose Design Objective Particulate 30 mrem/organ 0.0116 mrem 0.039 Noble gas 40 mrad (beta air) 0.0000383 mrad 0.00010 Noble gas 20 mrad (gamma air) 0.000101 mrad 0.00051 Noble gas 30 mrem (skin) 0.000140 mrem 0.00047 Noble_gas 10 mrem (whole body) 0.0000952 mrem 0.00095 Table 3-2 Radioactive Airborne Effluent Release Summary January 1, 2018, through December 31, 2018 Total Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec Total 1 Total Noble Gas (Ci) 5.95E-02 5.10E-02 5.39E-02 6.57E-02 4.02E-02 4.44E-02 3.15E-01 5.17E-02 5.37E-02 5.37E-02 3.82E-02 4.61 E-02 4.85E-02 6.07E-01 2 Total Radioiodines (Ci) ND ND ND ND ND ND ND ND ND ND ND ND ND ND 3 Total Particulate (Ci) 1.55E-06 ND ND ND ND ND 1.55E-06 4.95E-07 ND ND 2.49E-05 6.73E-07 5.16E-06 3.27E-05 Alpha (Ci) ND ND ND ND ND ND ND ND ND ND ND ND ND ND Strontium(Ci) ND ND ND ND ND ND ND ND ND ND ND ND ND ND All other beta + gamma (Ci) 1.55E-06 ND ND ND ND ND 1.55E-06 4.95E-07 ND ND 2.49E-05 6.73E-07 5.16E-06 3.27E-05 Total Tritium (Ci) 1.24E+01 1.02E+01 1.32E+01 1.04E+01 6.68E+OO 4.17E+OO 5.71E+01 3.56E+OO 6.28E+OO 4.38E+OO 6.92E+OO 7.38E+OO 8.55E+OO 9.41 E+01 Max NG H'rly Rei.(Cilsec) _ 5.89E-08 5.90E-08 5.28E-08 S.SOE-08 4.25E-08 5.73E-08 5.32E-08 5.17E-08 S.SOE-08 5.52E-08 4.74E-08 5.40E-08 1 Total noble gas (airborne releases) and activation gas Ar-41. It does not include the activation gas F-18 because of its short T 112 and because it is not an Appendix I radionuclide. 2 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. 3 Total Particulate is the sum of alpha, strontium, and others. It does not include radioiodines or C-14. C-14 was calculated for the year and no monthly values are available. ND: means that the radionuclide was not identified in any samples and all analyses were performed with instrumentation meeting the lower limit of detection as required by the PBNP Offsite Dose Calculation Manual. 15

TABLE 3-3 Isotopic Composition of Airborne Releases January 1, 2018 through December 31, 2018 Jan Feb Mar Apr May Jun Semi- Jul Aug Sep Oct Nov Dec Total Nuclide (Ci) (Ci) (Ci) (Ci) (Ci) (Ci) Annual (Ci) (Ci) (Ci) (Ci) (Ci) (Ci) (Ci) H-3 1.24E+01 1.02E+01 1.32E+01 1.04E+01 6.68E+OO 4.17E+OO 5.71E+01 3.56E+OO 6.28E+OO 4.38E+OO 6.92E+OO 7.38E+OO 8.55E+OO 9.41 E+01 F-18 1.55E-06 ND ND ND ND ND 1.55E-06 4.95E-07 ND ND 2.39E-05 6.73E-07 5.16E-06 3.18E-05 Ar-41 4.90E-02 4.31E-02 4.22E-02 4.94E-02 3.01E-02 3.38E-02 2.48E-01 3.80E-02 4.10E-02 3.74E-02 2.75E-02 4.02E-02 3.99E-02 4.72E-01 Kr-85 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Kr-85m ND ND ND ND ND ND ND ND ND ND ND ND ND ND Kr-87 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Kr-88 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Xe-131m ND ND ND ND ND ND ND ND ND ND ND ND ND ND Xe-133 1.04E-02 7.80E-03 1.18E-02 1.63E-02 1.01 E-02 1.06E-02 6.70E-02 1.37E-02 1.28E-02 1.62E-02 1.07E-02 5.96E-03 8.60E-03 1.35E-01 Xe-133m ND ND ND ND ND ND ND ND ND ND ND ND ND ND Xe-135 5.86E-05 ND ND ND ND ND 5.86E-05 ND ND 1.34E-04 ND ND ND 1.93E-04 Xe-135m ND ND ND ND ND ND ND ND ND ND ND ND ND ND Xe-138 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Cr-51 ND ND ND ND ND ND ND ND ND ND 2.94E-07 ND ND 2.94E-07 Mn-54 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Fe-59 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Co-57 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Co-58 ND ND ND ND ND ND ND ND ND ND 3.24E-07 ND ND 3.24E-07 Co-60 ND ND ND ND ND ND ND ND ND ND 1.43E-07 ND ND 1.43E-07 Zn-65 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Nb-95 ND ND ND ND ND ND ND ND ND ND 2.01E-07 ND ND 2.01E-07 Zr-95 ND ND ND ND ND ND ND ND ND ND ND ND ND ND 1-131 ND ND ND ND ND ND ND ND ND ND ND ND ND ND 1-132 ND ND ND ND ND ND ND ND ND ND ND ND ND ND 1-133 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Sb-124 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Sb-125 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Cs-137 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Fe-55 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Ni-63 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Tc-99 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Sr-89 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Sr-90 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Sn-113 ND ND ND ND ND ND ND ND ND ND ND ND ND ND Sn-117m ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND: means that the radionuclide was not identified in any samples and all analyses were performed with instrumentation meeting the lower limit of detection as required by the PBNP Offsite Dose Calculation Manual. 16

Table 3-4 Comparison of Airborne Effluent Doses (Appendix I and C-14) 2018 Appendix I (Airborne Particulate + Tritium) Dose (mrem) Bone Liver T-WB Thyroid Kidney Lung GI-LLI Skin Adult 1.46E-05 7.46E-03 7.45E-03 7.43E-03 7.46E-03 7.43E-03 7.45E-03 4.27E-09 Teen 1.80E-05 8.23E-03 8.21 E-03 8.19E-03 8.22E-03 8.19E-03 8.21 E-03 4.27E-09 Child 3.01 E-05 1.16E-02 1.16E-02 1.16E-02 1.16E-02 1.16E-02 1.16E-02 4.27E-09 Infant 2.87E-05 5.09E-03 5.05E-03 5.01 E-03 5.05E-03 5.01 E-03 5.08E-03 4.27E-09 2018 Carbon-14 Dose (mrem) Bone Liver T.Body Thyroid Kidney Lungs GI-LLI Skin Adult 6.76E-02 1.34E-02 1.34E-02 1.34E-02 1.34E-02 1.34E-02 1.34E-02 O.OOE+OO Teen 1.06E-01 2.10E-02 2.10E-02 2.10E-02 2.10E-02 2.10E-02 2.1 OE-02 O.OOE+OO Child 2.43E-01 4.85E-02 4.85E-02 4.85E-02 4.85E-02 4.85E-02 4.85E-02 O.OOE+OO Infant 1.24E-01 2.64E-02 2.64E-02 2.64E-02 2.64E-02 2.64E-02 2.64E-02 O.OOE+OO 2018 Total Airborne Non-Noble Gas Dose [Particulate+ H-3 + C-14 (mrem)] Bone Liver T-WB Thyroid Kidney Lung GI-LLI Skin Adult 6.76E-02 2.09E-02 2.09E-02 2.09E-02 2.09E-02 2.09E-02 2.09E-02 4.27E-09 Teen 1.06E-01 2.93E-02 2.92E-02 2.92E-02 2.93E-02 2.92E-02 2.92E-02 4.27E-09 Child 2.43E-01 6.01E-02 6.01E-02 6.01E-02 6.01E-02 6.01 E-02 6.01 E-02 4.27E-09 Infant 1.24E-01 3.15E-02 3.14E-02 3.14E-02 3.14E-02 3.14E-02 3.15E-02 4.27E-09 The percent of limit is calculated using the highest total dose, the Child Age Group. 17

4.0 RADIOACTIVE SOLID WASTE SHIPMENTS 4.1 Types, Volumes, and Activity of Shipped Solid Waste The following types, volumes, and activity of solid waste were shipped from PBNP for offsite disposal or burial during 2018. No Types C or D wastes were shipped. No irradiated fuel was shipped offsite. The volume, activity and type of waste are listed in Table 4-1. Table 4-1 Quantities and Types of Waste Shipped from PBNP in 2018 3 A. Spent resins, filter sludge, evaporator bottoms, etc. 5.9 m 7.630 Ci 2o1.4 te 3 B. Dry compressible waste, contaminated equipment, etc 208.2 m 0.391 Ci 7354.2 te 3 C. Irradiated components, control rods, etc. 0.00 m N/A Ci te3 D. Other 0.0 m N/A Ci o te 4.2 Solid Waste Disposition There were five solid waste shipments from PBNP during 2018. The dates and destinations are shown in Table 4-2. Table 4-2 2018 PBNP Radioactive Waste Shipments Date Destination 01/30/18 Oak Ridge, TN 04/05/18 Oak Ridge, TN 05/09/18 Clive, UT 10/19/18 Oak Ridge, TN 11/07/18 Oak Ridge, TN 4.3 Major Nuclide Composition (by Type of Waste) The major radionuclide content of the 2018 solid waste was determined by gamma isotopic analysis and the application of scaling factors for certain indicator radionuclides based on the measured isotopic content of representative waste stream samples. The estimated isotopic content is presented in Table 4-3. Only those radionuclides with detectable activity are listed. 18

Table 4-3 2018 Estimated Solid Waste Major Radionuclide Composition TYPE A TYPES Activity Percent Activity Percent Nuclide (mCi) Abundance Nuclide (mCi) Abundance Total 7.63E+03 100.00% Total 3.90E+02 100.00% Co-60 9.43E+02 12.35% Co-60 9.51 E+01 24.40% Co-58 2.85E+03 37.33% Zr-95 7.29E+01 18.71% Ni-63 2.68E+03 35.10% Fe-55 6.15E+01 15.79% Sb-125 4.25E+02 5.57% Cr-51 4.24E+01 10.88% Cs-137 1.17E+02 1.53% Co-58 3.79E+01 9.73% Fe-55 9.67E+01 1.27% Nb-95 3.10E+01 7.95% H-3 9.11 E+01 1.19% Ni-63 1.70E+01 4.37% C-14 8.58E+01 1.12% Sb-125 7.17E+OO 1.84% Co-57 5.98E+01 0.78% Mn-54 4.57E+OO 1.17% Mn-54 4.92E+01 0.64% Sn-113 3.84E+OO 0.99% Nb-95 4.36E+01 0.57% Sb-124 3.46E+OO 0.89% Ni-59 3.80E+01 0.50% Fe-59 2.81E+OO 0.72% Sb-124 2.46E+01 0.32% Zn-65 2.22E+OO 0.57% Ce-144 2.36E+01 0.31% Ni-59 1.71E+OO 0.44% Zr-95 2.32E+01 0.30% Ag-110m 1.45E+OO 0.37% Ag-110m 2.07E+01 0.27% Ce-144 1.30E+OO 0.33% Pu-241 2.03E+01 0.27% Co-57 9.00E-01 0.23% Cr-51 1.46E+01 0.19% Sn-117m 7.88E-01 0.20% Zn-65 1.41E+01 0.18% Tc-99 3.50E-01 0.09% Sn-113 8.28E+OO 0.11% Cs-137 3.31E-01 0.08% Tc-99 3.98E+OO 0.05% H-3 2.50E-01 0.06% Sr-90 1.36E+OO 0.02% Te-123m 2.47E-01 0.06% Am-241 1.80E-01 0.00% Nb-94 1.83E-01 0.05% Pu-238 7.55E-02 0.00% Pu-241 1.14E-01 0.03% Pu-239 6.90E-02 0.00% Sr-90 5.51E-02 0.01% Cm-243 6.72E-02 0.00% C-14 5.27E-02 0.01% Cm-242 3.95E-02 0.00% Am-241 1.50E-02 0.00% Pu-239 8.65E-03 0.00% Pu-238 7.85E-03 0.00% Cm-243 5.30E-03 0.00% Cm-242 2.78E-03 0.00% 4.4 Corrections to Previous AMRs A review of radwaste shipments has discovered that errors were made in transcribing the radwaste shipment data from the manifests to the data tables of the TYPE A radionuclides in the 2009 and 2014 Annual Monitoring Reports. Below are the corrected tables for the TYPE A radionuclide quantities and percentages. 19

Table 4-4 Corrected Type A Radionuclide Values for the 2009 and 2014 AMRs CORRECTED 2009 TYPE A CORRECTED 2014 TYPE A Percent Activity Percent Activity Nuclide Abundance (mCi) Nuclide Abundance (mCi) Total l.OOE+02 1.84E+05 Total l.OOE+02 8.49E+04 Ni-63 5.87E+01 1.08E+05 Ni-63 5.74E+01 4.87E+04 Co-60 2.25E+01 4.14E+04 Co-60 2.46E+01 2.09E+04 Co-58 7.20E+OO 1.32E+04 Cs-137 4.85E+OO 4.12E+03 Fe-55 3.22E+OO 5.92E+03 Co-58 4.62E+OO 3.92E+03 Sb-125 2.34E+OO 4.31E+03 Sb-125 3.35E+OO 2.85E+03 Cs-137 2.27E+OO 4.18E+03 Mn-54 1.48E+OO 1.26E+03 Mn-54 1.94E+OO 3.56E+03 Fe-55 1.09E+OO 9.29E+02 Ni-59 6.73E-01 1.24E+03 H-3 6.52E-01 5.54E+02 Pu-241 3.84E-01 7.06E+02 Ni-59 5.07E-01 4.30E+02 Ce-144 3.07E-01 5.64E+02 Co-57 3.57E-01 3.03E+02 Co-57 2.14E-01 3.94E+02 Ag-110m 1.85E-01 1.57E+02 Ag-110m 1.21E-01 2.23E+02 Nb-95 1. 77E-01 1.50E+02 C-14 9.46E-02 1.74E+02 Ce-144 1.33E-01 1.13E+02 Sr-90 4.51E-02 8.30E+01 C-14 1.16E-01 9.81E+01 H-3 2.25E-02 4.15E+01 Zr-95 8.50E-02 7.22E+01 Zn-65 1.08E-02 1.98E+01 Sb-124 7.46E-02 6.33E+01 Tc-99 1.96E-03 3.60E+OO Pu-241 6.69E-02 5.68E+01 Cm-243 1.14E-03 2.09E+OO Sr-90 6.02E-02 5.12E+01 Pu-239 6.00E-04 1.10E+OO Sn-117m 5. 75E-02 4.88E+01 Pu-238 5.16E-04 9.49E-01 Cr-51 5.69E-02 4.83E+01 Am-241 3.08E-04 5.66E-01 Zn-65 1. 77E-02 1.50E+01 Cm-244 8.82E-05 1.62E-01 Sn-113 1.17E-02 9.92E+OO Pu-240 7.39E-05 1.36E-01 Am-241 1.91E-03 1.62E+OO Cm-242 1.88E-05 3.46E-02 Pu-238 1.89E-03 1.60E+OO Pu-239 1.23E-03 1.05E+OO Cm-243 5.24E-04 4.45E-01 Cm-242 1.22E-04 1.04E-01 20

5.0 NONRADIOACTIVE CHEMICAL RELEASES 5.1 Scheduled Chemical Waste Releases There were no scheduled chemical releases of neutralized wastewater to the circulating water system from January 1, 2018, to June 30, 2018. There were no scheduled chemical releases of neutralized wastewater to the circulating water system from July 1, 2018, to December 31, 2018. 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, 2018, to June 30, 2018, included 2.1 OE+07 gallons of clarified effluent. The wastewater contained 2.51 E+03 lbs. of suspended solids. Miscellaneous chemical waste releases from the wastewater effluent (based on effluent analyses) to the circulating water for July 1, 2018, to December 31, 2018, included 2.21 E+07 gallons of clarified effluent. The wastewater contained 1.86E+03 lbs. of suspended solids. Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from January 1, 2018, to June 30, 2018, included 5.67E+05 lbs. of sodium bisulfite solution (2.16E+05 lbs. sodium bisulfite), 6.19E+05 lbs. of Sodium Hypochlorite Solution (7.73E+04 lbs. sodium hypochlorite), 2.55E+041bs. Acti-Brom 1338 (1.15E+041bs. sodium bromide). 4.23E+03 lbs. of biodetergent, and 5.94E+04 lbs. of silt dispersant. Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from July 1, 2018, to December 31, 2018, included 7.87E+05 lbs. of sodium bisulfite solution (2.99E+05 lbs. sodium bisulfite), 9.47E+05 lbs. Sodium Hypochlorite Solution (1.18+05 lbs. sodium hypochlorite),

2. 79E+04 lbs. Acti-Brom 1338 (1.26E+04 lbs. sodium bromide), 4.00E+03 lbs. of biodetergent, and 5.25E+05 lbs. of silt dispersant.

21

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 2018 UNIT JAN FEB MAR APR MAY JUN Average Volume Cooling 1 346.7 346.7 346.7 346.7 539.9 549.7 Water Discharge [million gal/day]* 2 346.7 346.7 346.7 346.7 541.2 551.1 Average Cooling Water 1 37 38 39 41 48 57 Intake Temperature [°F] 2 37 39 40 42 49 58 Average Cooling Water 1 70 72 73 75 69 78 Discharge Temperature [°F] 2 67 69 70 72 65 74 Average Ambient Lake Temperature [°F] 34 35 36 38 45 53

For days with cooling water discharge flow.

Table 6-1(continued) Circulating Water System Operation for 2018 UNIT JUL AUG SEP OCT** NOV DEC Average Volume Cooling* 1 549.7 549.7 549.7 558.6 549.7 353.6 Water Discharge [million gal/day] 2 551.1 551.1 551.1 231.9 551.1 366.7 Average Cooling Water 1 57 64 58 52 43 40 Intake Temperature [°F] 2 57 64 59 51 43 41 Average Cooling Water 1 77 84 78 71 62 68 Discharge Temperature [°F] 2 73 81 76 60 60 69 Average Ambient Lake Temperature [°F] 52 58 62 49 44 37

For days with cooling water discharge flow.

**U2 outage October 6 - October 26 22

Part B Miscellaneous Reporting Requirements 7.0 ADDITIONAL REPORTING REQUIREMENTS 7.1 Revisions to the PBNP Effluent and Environmental Programs The ODCM (attached) was revised in 2018. ODCM changes included updates to the Radiological Environmental Monitoring Program (REMP) sampling frequencies, analysis, and addition of a new TLD location. All REMP changes were evaluated and compared to NUREG-0472 and NUREG-1301, along with several other applicable NUREGs and Reg. Guides, and years of historical site data to ensure the efficacy of the program would not be impacted by the changes that were implemented. Changes included reducing the sampling frequencies for algae, soil, and shoreline sediment to an annual frequency from either biannual or tri-annual frequency. Fish sampling was changed to quarterly or as available from semi-annually to standardize the sampling/analysis process at the station. The gross beta analysis that was performed on Vegetation (Grass and Weeds), Algae, Fish, Soil, and Shoreline Sediment was removed since PBNP analyzes all of the recommended nuclides for these samples, and the gross beta analysis was a remnant from the pre-operational program. Additionally, a new TLD at location E-44 was added to increase the monitoring of the REMP and the ISFSI. There are dry fuel cask storage additions planned for the future and this is a proactive addition to the program to ensure PBNP is monitoring near the closest dwelling. As well, the guidance for entrained noble gas accountability in liquid discharges was updated to change the process of quantifying noble gases in liquid effluents as airborne noble gas effluents. Several documents such as 10 CFR 50.34a, 10CFR 50.36a, 10 CFR 50, Appendix I, Regulatory Guide 1.1 09, NUREG-0472, NUREG-1301, and NUREG/CR-5569, Generic Letter 89-01, and site Technical Specifications were reviewed for requirements and guidance for entrained noble gas accountability in liquid discharges. It was determined that limiting the concentration of dissolved and entrained noble gases to 2.0E-04 11CilmL total activity, ensures that the noble gas released in liquid effluents remains negligible for dose calculations, therefore removing the need to account for entrained noble gases in liquid discharges as airborne effluents. 7.2 Interlaboratory Comparison Program ATI Environmental, Inc, Midwest Laboratory, the analytical laboratory contracted to perform the radioanalyses of the PBNP environmental samples, participated in the Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP) as well as in the interlaboratory comparison studies administered by Environmental Resources Associates (ERA) during 2018. The ERA environmental crosscheck program replaces the Environmental Measurements Laboratory (EML) Quality Assessment Program which was discontinued. The 23

results of these comparisons can be found in Appendix A of the attached final report for 2018, January- December 2018 from ATI Environmental Inc. 7.3 Special Circumstances No special circumstances to report regarding operation of the explosive gas monitor for the waste gas holdup system was needed during 2018. 24

Part C RADIOLOGICAL ENVIRONMENTAL MONITORING

8.0 INTRODUCTION

The objective of the PBNP Radiological Environmental Monitoring Program (REMP) is to determine whether the operation of PBNP or the ISFSI has radiologically impacted the environment. To accomplish this, the REMP collects and analyzes air, water, milk, soil, vegetation (grasses, weeds, and crops), and fish samples for radionuclides and uses thermoluminescent dosimeters (TLDs) to determine the ambient radiation background. The analyses of the various environmental media provide data on measurable levels of radiation and radioactive materials in the principal pathways of environmental exposure. These measurements also serve as a check of the efficacy of PBNP effluent controls. The REMP fulfills the requirements of 10 CFR 20.1302, PBNP General Design Criterion (GDC) 17, GDC 64 of Appendix A to 10 CFR 50, and Sections IV.B.2 and IV.B.3 of Appendix I to 10 CFR 50 for the operation of the plant. A subset of the PBNP REMP samples, consisting of air, soil and vegetation also fulfills 10 CFR 72.44(d)(2) for operation of the ISFSI. Additionally, TLDs provide the means to measure changes in the ambient environmental radiation levels at sites near the ISFSI and at the PBNP site boundary to ensure that radiation levels from the ISFSI are maintained within the dose limits of 10 CFR 72.104. Because the ISFSI is within the PBNP site boundary, radiation doses from PBNP and the ISFSI, combined, must be used to assess compliance with 10 CFR 72.122 and 40 CFR 190. Therefore, radiological environmental monitoring for the ISFSI is provided by selected sampling sites, which are part of the PBNP REMP. For the aquatic environment, the samples include water as well as the biological integrators, such as fish and filamentous algae. Because of their migratory behavior, fish are wide area integrators. In contrast, the filamentous algae periphyton is attached to shoreline rocks and concentrate nuclides from the water flowing by their point of attachment. Grab samples of lake water provide a snapshot of radionuclide concentrations at the time the sample is taken; whereas analysis of fish and filamentous algae yield concentrations integrated over time. The air-grass-cow-milk exposure pathway unites the terrestrial and atmospheric environments. This pathway is important because of the many dairy farms around PBNP. Therefore, the REMP includes samples of air, general grasses, and milk from the PBNP environs. An annual land use survey is made to determine whether the assumptions on the location of dairy cattle remain conservative with respect to dose calculations for PBNP effluents. The dose calculations assume that the dairy cattle are located at the south site boundary, the highest depositional sector. In addition, soil samples are collected and analyzed in order to monitor the potential for long-term buildup of radionuclides in the vicinity of PBNP. 25

For the measurement of ambient environmental radiation levels that may be affected by direct radiation from PBNP or by noble gas effluents, the REMP employs a series of TLDs situated around PBNP and the ISFSI. 9.0 PROGRAM DESCRIPTION 9.1 Results Reporting Convention The vendor used by PBNP to analyze the environmental samples is directed to report analysis results as measured by a detector, which can meet the required lower limit of detection (LLD) as specified in Table 12-1 of the ODCM 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" (NO), 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 26

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 +/- 90. One hundred minus 90 yields a positive result and therefore may be considered to be present. However, this may be a false positive. If the radionuclide was not in the plant effluent, this result would fall into that category which 5%> of the time it is falsely concluded that the radionuclide is present when in actuality it is not. This usually happens at low concentrations at or near the LLD where fluctuations in the background during the counting process skew the results to produce a positive result. In interpreting the data, effects due to the plant must be distinguished from those due to other sources. A key interpretive aid in assessment of these effects is the design of the PBNP REMP, which is based upon the indicator-control concept. Most types of samples are collected at both indicator locations and at control locations. A plant effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuation in radiation levels arising from other sources. 9.2 Sampling Parameters Samples are collected and analyzed at the frequency indicated in Table 9-1 from the locations described in Table 9-2 and shown in Figures 9-1, 9-2 and 9-3. (The latter two figures show sampling locations not shown in preceding figures due to space limitations. The location of the former retention pond, retired and remediated to NRC unrestricted access criteria, is indicated in Figure 9-3). The list of PBNP REMP sampling sites used to determine environmental impact around the ISFSI is found in Table 9-3. The minimum acceptable sample size is found in Table 9-4. In addition, Table 9-1 indicates the collection and analysis frequency of the ISFSI fence TLDs. 9.3 Deviations from Required Collection Frequency Deviations from the collection frequency given in Table 9-1 are allowed because of hazardous conditions, automatic sampler malfunction, seasonal unavailability, and other legitimate reasons (Section 12.2.2.e of the ODCM). 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 collect certain environmental samples (Table 9-6) for the State from sites that are near PBNP sampling sites, or are co-located. 27

9.5 Program Modifications Changes to the Radiological Environmental Monitoring Program (REMP) including updated sampling frequencies, analysis, and addition of a new TLD location occurred in 2018. All REMP changes were evaluated and compared to NUREG-0472 and NUREG-1301, along with several other applicable NUREGs and Reg. Guides, and years of historical site data to ensure the efficacy of the program would not be impacted by the changes that were implemented. Changes included reducing the sampling frequencies for algae, soil, and shoreline sediment to an annual frequency from either biannual or tri-annual frequency. Fish sampling was changed to quarterly or as available from semi-annually to standardize the sampling/analysis process at the station. The gross beta analysis that was performed on Vegetation (Grass and Weeds), Algae, Fish, Soil, and Shoreline Sediment was removed since PBNP analyzes all of the recommended nuclides for these samples, and the gross beta analysis was a remnant from the pre-operational program. Additionally, a new TLD at location E-44 was added to increase the monitoring of the REMP and the ISFSI. There are dry fuel cask storage additions planned for the future and this is a proactive addition to the program to ensure PBNP is monitoring near the closest dwelling. 28

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

                   -14, -15, -16B, -17, -18, 20, -22, -23, -24,
                   -25, -26B, -27, -28
                   -29, -30, 31' -32, -38,
                    -39,-41' -42,-43, -44
                   -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               1x/yr as available Gamma Isotopic Analysis Fish               E-13                       Gross Beta               Quarterly as available Gamma Isotopic Analysis (Analysis of edible portions only)

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

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

Gamma Isotopic Analysis Quarterly (on composite

                                                                      !particulate filters)

Soil E-01, -02, -03, -04, Gross Beta 1x/yr

                  -06, -08, -09, -20,        Gamma Isotopic Analysis Shoreline Sediment E-01, -05, -06, -12, -33, Gross Beta                 1x/yr Gamma Isotopic Analysis ISFSI Ambient      North, East, South, Radiation Exposure West Fence Sections        TLD                      Quarterly 29

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 Telephone E-06 pole E-07 WPSC Substation on County V, about 0.5 Miles West of Hwy 42 E-08 G.J. Francar Property at Southeast Corner of the Intersection of Cty. B and Zander Road E-09 Nature Conservancy E-10 PBNP Site Well E-11 Dairy Farm about 3. 75 Miles West of Site E-12 Discharge Flume/Pier E-13 Pumphouse E-14 South Boundary, about 0.2 miles East of Site Boundary Control Center E-15 Southwest Corner of Site E-16B WSW, Hwy 42, a residence about 0.25 miles North of Nuclear Road E-17 North of Mishicot, Cty. B and Assman Road, Northeast Corner of Intersection E-18 Northwest of Two Creeks at Zander and Tannery Roads E-20 Reference Location, 17 miles Southwest, at Silver Lake College E-21 Local Dairy Farm just South of Site on Lakeshore and Irish Roads E-22 West Side of Hwy 42, about 0.25 miles North of Johanek Road E-23 Greenfield Lane, about 4.5 Miles South of Site, 0.5 Miles East of Hwy 42 E-24 North Side of County Rt. V, near intersection of Saxonburg Road E-25 South Side of County Rt. BB, about 0.5 miles West of Norman Road E-26B 804 Tapawingo Road, about 0.4 miles East of Cty. B, North Side of Road E-27 Intersection of Saxonburg and Nuclear Roads, Southwest Corner, about 4 Miles WSW E-28 TLD site on western most pole between the 2nd and 3rd parking lots. E-29 Area of North Meteorological Tower. E-30 NE corner at Intersection of Tapawingo and Lakeshore Roads. E-31 On utility pole North side of Tapawingo Road closest to the gate at the West property line. E-32 On a tree located at the junction of property lines, as indicated by trees and shrubs, about 500 feet east of the west gate on Tapawingo Road and about 1200 feet south of Tapawingo Road. The location is almost under the power lines between the blue and gray transmission towers. Lake Michigan shoreline accessed from theSE 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 utility pole south of Elmwood) E-44 Utility Pole N Side of Tapawingo Rd near house at 5011 E-TC Transportation Control; Reserved for TLDs 30

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ENV!RONMENT;LLEA~ON!TORJNG TLD A* OTHER STATIONS II CGS FILE 1074&

Figure 9-2 Map of REMP Sampling Sites Located Around PBNP 32

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Figure 9-3 Enhanced Map Showing REMP Sampling Sites Closest to PBNP 33

Table 9-3 ISFSI Sampling Sites Ambient Radiation Monitoring (TLD) Soil, Vegetation and Airborne Monitoring E-03 E-02 E-28 E-03 E-29 E-04 E-30 E-31 E-32 E-44 Table 9-4 Minimum Acceptable Sample Size Sample Type Size Vegetation 100-1000 grams Lake Water 8 liters Air Filters 250 m3 (volume of air) Well Water 8 liters Milk 8 liters Algae 100-1 000 grams Fish (edible portions) 1000 grams Soil 500-1000 grams Shoreline Sediment 500-1 000 grams 34

Table 9-5 Deviations from Scheduled Sampling and Frequency During 2018 Scheduled Sample Reason for not conducting Plans for Preventing Location Collection Type RSVJP as required Recurrence Date LW E-01 1/11/2018 Icy Conditions at the Shore Natural Occurrence LW E-06 1/11/2018 Icy Conditions at the Shore Natural Occurrence LW E-05 2/14/2018 Icy Conditions at the Shore Natural Occurrence LW E-06 2/14/2018 Icy Conditions at the Shore Natural Occurrence LW E-33 2/14/2018 Icy Conditions at the Shore Natural Occurrence TLD E-15 4/4/2018 TLD Lost in field New TLD Holders SL E-05 8/16/2018 None Grow ing Natural Occurrence SL E-12 8/16/2018 None Grow ing Natural Occurrence TLD E-7 10/2/2018 TLD Lost in field Fence Removed - New TLD Holder TLD E-28 10/2/2018 TLD Lost in field Sa111Jie shipment validation Table 9-6 Sample Collections for State of Wisconsin Sample Type Location Frequency Lake Water E-01 Monthly Air Filters E-07 Weekly E-08 Fish E-13 Quarterly, As Available Precipitation E-04 Twice a month, E-08 As Available Milk E-11 Monthly E-21 Well Water E-10 Twice per year 35

9.6 Analytical Parameters The types of analyses and their frequencies are given in Table 9-1. The LLDs for the various analyses are found in Section 10 (Table 10-1) with the summary of the REMP results. All environmental LLDs listed in Table 12-1 of the ODCM (also in Table 10-1) were achieved during 2018. 9.7 Description of Analytical Parameters in Table 9-1 9.7.1 Gamma isotopic analysis Gamma isotopic analysis consists of a computerized scan of the gamma ray spectrum from 80 keV to 2048 keV. Specifically included in the scan are Mn-54, Fe-59, Co-58, Co-60, Zr-95, Nb-95, Ru-103, Ru-106, 1-131, Ba-La-140, Cs-134, Cs-137, Ce-141, and Ce-144. However, other detected nuclear power plant produced radionuclides also are noted. The above radionuclides detected by gamma isotopic analysis are decay corrected to the time of collection. Frequently detected, but not normally reported in the Annual Monitoring Report, are the naturally occurring radionuclides Ra-226, Bi-214, Pb-212, Tl-208, Ac-228, Be-7, and K-40. 9.7.2 Gross Beta Analysis Gross beta analysis is a non-specific analysis that consists of measuring the total beta activity of the sample. No individual radionuclides are identifiable by this method. Gross beta analysis is a quick method of screening samples for the presence of elevated activity that may require additional, immediate analyses. 9.7.3 Water Samples Water samples include both Lake Michigan and well water. The Lake Michigan samples are collected along the shoreline at two locations north and two locations south of PBNP. The well water is sampled from the on-site PBNP well. Gross beta measurements are made on the solids remaining after evaporation of the unfiltered sample to dryness. Gamma isotopic analyses are performed using 1-liter liquid samples. Strontium is determined by chemical separation and beta counting. 9.7.4 Air Samples Particulate air filters are allowed to decay at least 72 hours before gross beta measurements are made in order for naturally occurring radionuclides to become a negligible part of the total activity. Gross beta measurements serve as a quick check for any unexpected activity that may require immediate investigation. Quarterly composites of the particulate air filters are analyzed for long-lived radionuclides such as Cs-134 and Cs-137. Charcoal cartridges for radioiodine are counted as soon as possible so the 1-131 will undergo only minimal decay prior to analyses. The weekly charcoal cartridges are screened for 1-131 by 36

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 2018. 9.7.6 Environmental Radiation Exposure The 2018 environmental radiation exposure measurements were made using TLD cards. The TLD card is a small passive detector, which integrates radiation exposure. Each TLD consists of a Teflon sheet coated with a crystalline, phosphorus material (calcium sulfate containing dysprosium) which absorbs the gamma ray energy deposited in them. Each TLD is read in four distinct areas to yield four exposure values which are averaged. Prior to the third quarter of 2001, exposure data was obtained using three lithium fluoride (LiF) TLD chips sealed in black plastic. The difference in material types can impact the amount of exposure measured. An evaluation of the response difference between the two types of TLD in 2001 demonstrated that the TLD cards produced a 14% higher response than the LiF chips (2011 AMR, Table 9-7, p. 36). The reported field exposure is the arithmetic average of the measured exposure values at each location minus the exposure transportation control TLD (exposure received while the field TLD is in storage and transit). The gamma rays may originate from PBNP produced radionuclides or from naturally occurring radionuclides. The TLDs remain at the monitoring site for roughly three months prior to analyses and the results are reported as mrem per seven days. Because the TLDs are constantly bombarded by naturally occurring gamma radiation, even during shipment to and from PBNP, the amount of exposure during transportation is measured using transportation controls with each shipment of TLDs to and from the laboratory. The doses recorded on the transportation controls are subtracted from the monitoring TLDs in order to obtain the net in situ dose. 37

9.7.7 ISFSI Ambient Radiation Exposure The ISFSI fence TLDs are part of the 10CFR72.44 monitoring and are not considered part of the REMP. However, their results can be used indirectly to determine whether the operation of the ISFSI is having an impact on the ambient environmental radiation beyond the site boundary. Impacts are determined by comparison of fence TLD results to the results of the monitoring at PBNP site boundary and other selected locations. These results are used as part of the 40CFR 190 compliance demonstration. 10.0 RESULTS 10.1 Summary of 2018 REMP Results Radiological environmental monitoring conducted at PBNP from January 1, 2018, through December 31, 2018, consisted of analysis of air filters, milk, lake water, well water, soil, fish, shoreline sediments, and vegetation as well as TLDs (No algae obtained in 2018). The results are summarized, averages and high values, in Table 10-1 which contain the following information: Sample: Type of the sample medium

Description:

Type of measurement N: Number of samples analyzed LLD: a priori lower limit of detection Average: Average value +/-the standard deviation of N samples High: Highest measured value +/- it's associated 2 sigma counting error Units: Units of measurement For certain analyses, an LLD, which is lower than that required by REMP, is used because the lower value derives from the counting time required to obtain the LLDs for radionuclides that are more difficult to detect. For these analyses, both LLDs are listed with the technical specification required REMP LLD given in parentheses. The results are discussed in the narrative portion of this report (Section 11 ). Blank values have not been subtracted from the results presented in Table 10-1. A listing of all the individual results obtained from the contracted analytical laboratory and the laboratory's radioanalytical quality assurance results and Interlaboratory Crosscheck Program results are presented in the Appendix. In Table 10-1 no results are reported as less than LLD (<LLD). All results are reported to Point Beach by the contracted radioanalytical laboratory "as measured" whether positive or negative (see Section 9-1 ). Based on these results, a radionuclide is considered detected if it meets the criterion that the measured value minus its 2a counting error is greater than zero (x-2a >0). An "ND" entry in Table 10-1 means that for this radionuclide the criterion was not satisfied for any of the measurements. If one analysis fulfilled the criterion, then all of the reported results, both positive and negative, were used in calculating the average shown in Table 10-1. 38

The method of determining averages based on "as measured" results follows the recommendations made in NUREG-0475 (1978), "Radiological Environmental Monitoring by NRC Licensees for Routine Operations of Nuclear Facilities Task Force Report," and in Health Physics Society Committee Report HPSR-1 (1980)

 "Upgrading Environmental Radiation Data" released as document EPA 520/1   012 and in more recent documents such as ANSI N42.23-1996, "Instrument Quality Assurance for Radioassay Laboratories;" ANSI N13.30-1996, "Performance Criteria for Radiobioassay;" DE91-013607, "Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance" and NUREG-1576, "Multi-Agency Radiological Laboratory Analytical Protocols Manual."

In addition to the required radionuclides for each medium analyzed, Table 10-1 also has an additional radionuclide listed known to originate with nuclear power plants. This radionuclide is either Co-60, Ru-1 03, or any other radionuclide which has the lowest LLD based on the analytical parameters needed to meet the LLDs required for radionuclides specified for the medium being analyzed. The radionuclide is identified by parentheses. During the analyses for those radionuclides specifically required to be identified, naturally occurring radionuclides such as Ra-226, Be-7 and K-40 are detected in many samples. Their concentrations are presented in Table 10-1 for a comparison to those radionuclides for which specific analyses are required by the regulations. There are no regulatory required LLDs for naturally occurring radionuclides. Finally, Point Beach reports the results for soil analyses. There is no regulatory requirement for soil analyses in standard RETS (NUREG-0472 and NUREG-1301 ). Point Beach includes soil analyses in the REMP to be able to compare current results to the historical record. The crop sampling initiated in 2015 continued in 2018 and is incorporated into the REMP via HPIP 3.58.1. Approximately 60% of the 1260 acres (FSAR 2.1) comprising the NextEra Point Beach site is leased to farmers who use the land to grow various crops. These crops consist of corn, alfalfa, and soy beans and appear to be for cattle feed. Ten samples were obtained from the nine separate plots and gamma scanned for radionuclides representative of Point Beach effluents and for naturally occurring radionuclides. Results are reported in Table 10-2. Table 10-3 contains the ISFSI fence TLD results. 39

Table 10-1 Summary of Radiological Environmental Monitoring Results for 2018 Average+/- 1 sta. Sample Description N LLD (a) Deviation (b) High +/- 2 sigma Units TLD Environmental Radiation 125 1 mrem 1.11 +/- 0.17 1.51 +/- 0.08 mR/7days Control (E-20) 4 1 mrem 1.19 +/- 0.17 1.46 +/- 0.14 mR/7days Air Gross Beta 260 0.01 0.024 +/- 0.008 0.053 +/- 0.005 pCi/m3 Control (E-20) Gross beta 52 0.01 0.025 +/- 0.008 0.053 +/- 0.005 pCi!m3 1-131 260 0.030 (0.07) NO - pCi/m3 Control (E-20) 1-131 52 0.030 (0.07) NO - pCi!m3 Cs-134 20 0.01(0.05) NO - pCi/m3 Control (E-20) Cs-134 4 0.01 (0.05) NO - pCi/m3 Cs-137 20 0.01(0.06) 0.0000 +/- 0.0004 0.0007 +/- 0.0006 pCi/m3 Control (E-20) Cs-137 4 0.01(0.06) NO - pCi/m3 Other v emitters (Co-60) 20 0.1 0.0001 +/- 0.0004 0.0008 +/- 0.0006 pCi/m3 Control (E-20) Other (Co-60) 4 0.1 NO - pCi/m3 Natural Be-7 20 - 0.069 +/- 0.018 0.095 +/- 0.016 pCi!m3 Control (E-20) Natural Be-7 4 - 0.071 +/- 0.015 0.088 +/- 0.012 pCi/m3 Milk Sr-89 36 5 NO - pCi!L Sr-90 36 1 0.4 +/- 0.2 0.8 +/- 0.3 pCi/L 1-131 36 0.5 NO - pCi!L Cs-134 36 5 (15) -0.2 +/- 1 3.2 2.2 pCi/L Cs-137 36 5 (18) 0.4 +/- 1.3 3.2 +/- 2.0 pCi/L Ba-La-140 36 5 (15) NO pCi/L Other gamma emitters(Co-60) 36 15 -0.2 +/- 1.2 1.9 +/- 2.4 pCi/L Natural K-40 36 - 1356 +/- 71 1485 +/- 111 pCi/L Well Gross beta 4 4 1.8 +/- 1.1 2.9 +/- 1.2 pCi/L Water H-3 4 200 (3000) NO - pCi/L Sr-89 4 5(10) NO - pCi/L Sr-90 4 1 (2) NO - pCi/L 1-131 4 0.5 (2) NO - pCi/L Mn-54 4 10 (15) NO - pCi/L Fe-59 4 30 NO - pCi/L Co-58 4 10(15) NO - pCi/L Co-60 4 10(15) NO - pCi/L Zn-65 4 30 NO - pCi/L Zr-Nb-95 4 15 NO - pCi/L Cs-134 4 10(15) NO - pCi/L Cs-137 4 10(18) NO - pCi/L Ba-La-140 4 15 -0.7 +/- 2 1.9 +/- 1.8 pCi/L Other gamma emitters(Ru-1 03) 4 30 NO - pCi/L Algae Co-58 0 0.25 NS - pCi/g Co-60 0 0.25 NS pCi/g Cs-134 0 0.25 NS pCi/g Cs-137 0 0.25 NS pCi/g Natural Be-7 0 - NS pCi/g Natural K-40 0 - NS pCi!g NS =No Sample obtained during the year 40

Table 10-1 (continued) Summary of Radiological Environmental Monitoring Results for 2018 Average +/- 1 Std. Sample Description N LLD (a) Deviation (b) High +/- 2 sigma Units Lake Water Gross beta 43 4 1.3 +/- 0.4 2.3 +/- 1.0 pCi/L 1-131 43 0.5 (2) NO - pCi/L Mn-54 43 10 (15) 0.2 +/- 1.0 3.4 +/- 2.4 pCi!L Fe-59 43 30 -1.0 +/- 2.2 5.5 +/- 3.8 pCi/L Co-58 43 10(15) 0.0 +/- 1.4 2.6 +/- 1.6 pCi/L Co-60 43 10(15) 0.0 +/- 0.9 1.3 +/- 1.0 pCi/L Zn-65 43 30 -1.2 +/- 2.9 3.9 +/- 3.4 pCi/L Zr-Nb-95 43 15 -0.9 +/- 1.6 3.0 +/- 1.6 pCi!L Cs-134 43 10 (15) -0.2 +/- 0.8 2.0 +/- 1.8 pCi/L Cs-137 43 10 (18) 0.0 +/- 1.1 2.2 +/- 1.9 pCi/L Ba-La-140 43 15 -0.9 +/- 3.0 5.6 +/- 1.6 pCi/L Other gamma (Ru-1 03) 43 30 -0.2 +/- 1.1 2.3 +/- 1.3 pCi/L Sr-89 16 5(10) NO - pCi/L Sr-90 16 1 (2) 0.22 +/- 0.08 0.36 +/- 0.30 pCi!L H-3 16 200 (3000) 2012 +/- 7765 31129 +/- 527 pCi/L Fish Mn-54 13 0.13 0.005 +/- 0.005 0.013 +/- 0.011 pCi/g Fe-59 13 0.26 NO - pCi/g Co-58 13 0.13 0.005 +/- 0.009 0.018 +/- 0.007 pCi/g Co-60 13 0.13 0.003 +/- 0.006 0.012 +/- 0.009 pCi/g Zn-65 13 0.26 NO - pCi/g Cs-134 13 0.13 0.001 +/- 0.006 0.013 +/- 0.008 _pCilg Cs-137 13 0.15 0.028 +/- 0.026 0.083 +/- 0.020 pCi/g Other gamma (Ru-1 03) 13 0.5 0.002 +/- 0.009 0.012 +/- 0.009 pCi/g Natural K-40 13 - 2.68 +/- 0.84 3.85 +/- 0.5 pCi/g Shoreline Cs-134 5 0.18 NO - pCi!g Sediment Cs-137 5 0.15 0.006 +/- 0.008 0.020 +/- 0.010 pCi/g Natural Be-7 5 - 0.025 +/- 0.082 0.244 +/- 0.138 pCi!g Natural K-40 5 - 2.61 +/- 2.94 7.73 +/- 0.40 pCi/g Natural Ra-226 5 - 0.20 +/- 0.22 0.51 +/- 0.18 pCi/g Soil Cs-134 8 0.15 NO pCi/g Cs-137 8 0.15 0.06 +/- 0.07 0.20 +/- 0.03 pCi/g Natural Be-7 8 - -0.004 +/- 0.08 0.09 +/- 0.08 _2Ci/g Natural K-40 8 - 8.66 +/- 9.19 20.46 +/- 0.76 pCi/g Natural Ra-226 8 - 0.46 +/- 0.53 1.40 +/- 0.28 pCi/g Vegetation 1-131 24 0.06 -0.001 +/- 0.011 0.026 +/- 0.007 pCi/g Cs-134 24 0.06 -0.001 +/- 0.004 0.009 +/- 0.007 pCilg Cs-137 24 0.08 0.011 +/- 0.041 0.184 +/- 0.028 pCi/g Other gamma emitters (Co-60) 24 0.25 NO - pCi/g Natural Be-7 24 - 2.56 +/- 1.54 7.40 +/- 0.46 pCi/g Natural K-40 24 - 5.43 +/- 1.35 8.92 +/- 0.44 pCilg (a) When two LLD values are listed, the required LLD per the PBNP REMP rs enclosed m the parentheses. Whenever possible, PBNP uses the lower value to obtain greater sensitivity. (b) "NO" indicates that the sample result is Not Detectable, i.e., sample concentrations were statistically equal to zero or <MDA. 41

Table 10-2 Feed Crops Grown on Point Beach Land Average Max Number pCilg 1cr pCi/g 2a Be-7 10 1.64 +/- 0.73 2.82 +/- 0.26 K-40 10 3.33 +/- 1.41 6.52 +/- 0.50 Co-60 10 NO - 1-131 10 NO - Cs-134 10 NO 1 - Cs-137 10 NO - NO = Not detected Table 10-3 Average ISFSI Fence TLD Results for 2018 Fence Location Average +/- Standard Deviation Units North 2.24 +/- 0.21 mR/7 days East 4.21 +/- 0.35 mR/7 days South 1.49 +/- 0.28 mR/7 days West 4.32 +/- 0.39 mR/7 days 42

11.0 DISCUSSION 11 . 1 TLD Cards The ambient radiation was measured in the general area of the site boundary, at an outer ring 4 to 5 miles from the plant, at special interest areas, and at one control location, roughly 17 miles southwest of the plant. The average indicator TLD is 1.11

            +/- 0.17 mR/7-days compared to 1.19 +/- 0.17 mR/7-days at the background location.

These two values are not significantly different from each other. Neither are the indicator TLD values significantly different from those observed from 2001 through 2018 for the same type of TLD (tabulated below in Table 11-1 ). Prior to third quarter of 2001 TLD LiF chips were used versus the current TLD cards, see Section 9.7.6 for additional information. The response difference between the two types of TLDs is evident in Table 11-1. Prior to 2001 all of the annual averages are <1 mrem/7-days. Beginning in 2001, all are >1 mrem/7-days. Table 11-1 Average Indicator TLD Results from 1993-2018 Year Average mR/7-days +/- St. Dev* 1993 0.82 +/- 0.15 1994 0.90 +/- 0.12 1995 0.87 +/- 0.13 1996 0.85 +/- 0.12 1997 0.87 +/- 0.11 1998 0.79 +/- 0.13 1999 0.79 +/- 0.21 2000 0.91 +/- 0.15 2001 1.06 +/- 0.19 2002 1.17 +/- 0.21 2003 1.10 +/- 0.20 2004 1.10 +/- 0.22 2005 1.04 +/- 0.21 2006 1.14 +/- 0.21 2007 1.08 +/- 0.20 2008 1.05 +/- 0.17 2009 1.08 +/- 0.17 2010 1.11 +/- 0.15 2011 1.14 +/- 0.25 2012 1.17 +/- 0.17 2013 1.14 +/- 0.20 2014 1.07 +/- 0.19 2015 1.18 +/- 0.20 2016 1.19 +/- 0.21 2017 1.11 +/- 0.17 2018 1.11 +/- 0.17

                               *St. Dev = Standard Deviation In 2018, the REMP TLD E-15 was found missing in the 1st quarter of 2018, and in the 3rd quarter of 2018 the TLDs at locations E-07 and E-28 (Figure 9-1) were also 43

missing and/or lost prior to shipment. An analysis of each of the missing TLD was made by comparing the quarterly REMP TLD data to TLDs that surrounded the missing TLD. As well, the TLDs used in the analysis were looked at over an eight year period to ensure the surrounding TLDs trended as expected when compared to historical data. Analyses of all 3 missing TLDs found that there was no unmonitored impact in the area surrounding the missing TLD. Six new casks were added to the East side of the ISFSI in 2018. The west fence TLDs continue to record higher exposures followed by the east, north, and south fence locations (Table 11-2). This sequence has been observed for the last nine years. The East TLD fence location shows an increase in mR/7 days due to the dry fuel storage campaign that occurred in June-July 2018. Table 11-2 Average ISFSI Fence TLD Results (mR/7 days) TLD FENCE LOCATION YEAR North East South West 1995 1.29 1.28 1.10 1.26 1996 2.12 1.39 1.10 1.68 1997 2.05 1.28 1.00 1.66 1998 2.08 1.37 1.02 1.86 1999 2.57 1.84 1.11 3.26 2000 2.72 2.28 1.25 5.05 2001 2.78 2.54 1.36 6.08 2002 2.79 2.74 1.42 6.46 2003 2.70 2.60 1.50 6.88 2004 2.61 2.12 1.41 6.50 2005 2.54 2.05 1.44 5.63 2006 2.73 2.35 1.38 5.80 2007 2.72 2.73 1.34 5.47 2008 2.64 2.37 1.36 5.36 2009 2.36 2.35 1.20 4.63 2010 2.64 3.02 1.41 5.05 2011 2.44 2.62 1.31 4.75 2012 2.59 3.27 1.40 4.92 2013 2.57 3.66 1.15 4.28 2014 2.45 3.35 1.14 4.24 2015 2.31 3.24 1.17 4.36 2016 2.30 3.34 1.33 4.35 2017 2.21 3.84 1.30 4.25 2018 2.24 4.21 1.49 4.32 There is no significant change in the exposure on the TLD monitoring locations around the ISFSI (Table 11-3). The results at E-03 and E-31 0fV of the ISFSI) and E-32 (SW of the ISFSI) are similar to previous years (1.34, 1.16, and 1.46 respectively) and continue to be higher than E-30 (1.02) on the east side and closest to the ISFSI. E-03, about equidistant between the ISFSI and the site 44

boundary location E-31, continues to be slightly higher than the site boundary location but the difference is not statistically different. (See Figs. 9-1 and 9-2 for locations). Although the mR/7 -day results for the three TLD locations nearest the site boundary (E-03 1.34 +/- 0.11; E-31, 1.16 +/- 0.15; E-32, 1.46 +/- 0.09) are higher than at the background site E-20 (1.19 +/- 0.36), they are comparable at the 95% confidence level, indicating a small, but not significant, increase in ambient gamma radiation at the site boundary due to the operation of the ISFSI. In 2018, a TLD monitoring location was added at location E-44 TLD, directly west of E-03 and E-31, but prior to the nearest resident. After one year of monitoring the average reading at E-44 is lower (1.04 +/- 0.23) than the observed readings at E-03, E-31, and background location E-20 (1.34, 1.16, and 1.19 respectively). Further data supporting this conclusion is the comparison of the TLD results at selected locations around the ISFSI before and after the storage of spent fuel at the ISFSI (Figure 11-1). As stated in Section 9.7.6, the TLD values increased by about 14% in the second half of 2001 when the TLD monitoring devices were changed from LiF chips in the first half of the 2001 to calcium sulfate impregnated TLD cards. After that initial change, the measured radiation exposure, as measured by the TLD cards, has remained fairly constant with a slight increase with the addition of stored fuel at the ISFSI. Each year the variations in the TLD results appear to move in concert with each other and with the background site, E-20, which is 17 miles south west of the ISFSI. Comparing the ISFSI TLD results to results from surrounding REMP indicator and background TLDs reveals minimal impact of the ISFSI on the surrounding radiation levels (Figure 11-2). As previously discussed, the small increase is more related to the switch from the LiF chips to the calcium sulfate impregnated Teflon TLD cards as evidenced by the synchronicity with E-20, the background site. LiF TLD chips were replaced with calcium sulfate impregnated Teflon TLD cards in the third quarter of 2001 resulting in a higher measured background values. 45

Figure 11 -1 ISFSI AREA TLD RESULTS 1995 - 2018 ISFSI AREA TLD RESULTS 1.8 1.6 1.4 1.2 1/) + E-03 ca "C

    ......                                                                                    E-29 a: 0.8                                                                               X E-30 E

e:: E-31 0.6 e E-32 0.4 + E-20

E-44 0.2 0

1990 1995 2000 2005 2010 2015 2020 2025 YEAR Table 11-3 Average TLD Resu Its S urroun d"mg th e ISFSI (m R/7 days E-03 E-28 E-29 E-30 E-31 E-32 E-44 E-20 *** Pre-Operation* 0.93 0.87 0.87 0.81 0.93 0.98 0.88 1996 0.87 0.78 0.81 0.79 0.93 1.00 0.78 1997 0.91 0.89 0.84 0.84 0.89 0.97 0.79 1998 0.82 0.68 0.80 0.82 0.91 0.85 0.77 1999 0.88 0.83 0.76 0.80 0.90 0.99 0.78 2000 0.98 0.88 0.92 0.99 0.98 1.06 0.90 2001 1.31 0.95 1.07 1.02 1.10 1.04 1.03 2002 1.45 0.91 1.22 1.10 1.26 1.25 1.14 2003 1.29 0.82 0.94 1.02 1.20 1.15 0.99 2004 1.35 0.80 0.96 1.05 1.23 1.18 1.06 2005 1.30 0.72 0.96 0.98 1.15 1.04 1.00 2006 1.44 0.80 1.19 1.07 1.21 1.07 1.11 2007 1.37 0.78 1.07 1.05 1.18 0 .97 1.05 2008 1.33 0.75 0.81 1.00 1.12 1.03 1.00 2009 1.39 0.82 0.85 1.01 1.17 1.05 1.09 2010 1.41 0.84 0.89 1.07 1.21 1.24 1.10 2011 1.46 0.85 0.90 1.06 1.25 1.32 1.12 2012 1.54 0.87 0.91 1.10 1.21 1.39 1.14 2013 1.23 0.87 0.77 1.00 1.40 1.38 1.22 2014 1.23 0.77 0.79 0.97 1.25 1.25 1.15 2015 1.36 0.86 0.78 1.07 1.24 1.40 1.20 2016 1.35 0.85 0.81 1.06 1.28 1.50 1.25 2017 1.36 0.79 0.80 1.01 1.21 1.44 1.21 2018 1.34 0.77 0.8 1.02 1.16 1.46 1.04 1.19

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.
    - E-44 Added in 2018 46

Figure 11-2 Comparison of ISFSI Fence TLDs to Selected REMP TLDs Comparison of Fence and REMP TLDS - . . - North

                                                                                   ~ Eas t 8_00 , - - - - - - - - - - - - - - - - - - - - - - - - -
                                                                                  - . -so uth 7.00 V)                                                                           -       west
     ~ 6 .00 +----------:1<:----~..-y-----------
    "'C t:. 5.00   --t----------,1<.;:------------'~~~------
                                                                                  -       E-D3 0::                                                                           - . . - E-28 E 4.00    --t---------+-----------==--~...o...:...._~---

g.o - E-29 r-----=~-:;~*lliii~~~lj~~,.*~~::~- 3

    <t 2 2.00.oo +--------w~    ....-L___--~~--==~-:....__-~~~~-                            E-30 L-_____j~'-\ih~      ~~""'?f'~~~~
    <t 1.00                                                                     -       E-31 0.00                                                                     ~ E-32 1990     1995      2000      2005       2010      2015       2020 E-44 YEAR
                                                                                  --.-- E-20 11.2 Milk Naturally occurring potassium-40 (1356 +/- 71 pCi/1) continues to be the most prevalent radionuclide measured in milk at concentrations roughly 1300 times higher than the only potential plant related radionuclide, Sr-90 (0.8 +/- 0.3 pCi/1),

detected in milk. The annual average Sr-90 concentrations in milk continue to be similar to previous years. No positive results for Ba-La-140, 1-131, or Sr-89 were obtained in 2018. Some low positive Cs-137 (3 of 36) results were obtained. In the last three years, Cs-137 was discharged from PBNP only in March 2016 and October 2017. All the Cs-137 values also are <MDC limit and therefore may be false positive. Another possibility is residual Cs-137 recycling through the environment from the 1960's atmospheric weapons tests and events such as Chernobyl and Fukushima. As well , no Cs-134 was discharged, and only one positive Cs-134 result that was

    <MDC was obtained .

One positive Co-60 value (<MDC) was obtained from site E-11 west of the plant. The Co-60 value occurred in January when the cattle would not be on pasture. It is concluded that the Co-60 result is a false positive. No 1-131 was detected in any of the milk samples. The 2018 average Sr-90 concentrations have not changed much over the last few years (Figure 11 -3) . Over the past twenty years, the average has decreased from 1.2 +/- 0.5 pCi/L in 1997 to 0.4 +/- 0.2 pCi/L in 2018. The graph of the annual averages displays a logarithmic decrease over time. The annual averages are from the monthly Sr-90 measurements from three different dairies (Figure 9-1). The only dairy that has been in the monitoring program over 47

the entire 1997- 2018 timespan under consideration is located at site E-21. It is located south of the plant. The other two, E-40 and E-11, are replacements for dairies which had dropped out of the program at various times during this time interval. The replacements were chosen to maintain, to the extent possible, the former sampling sites west and north of Point Beach. The decrease by about one-half from 1997 to 2018 indicates a Sr-90 removal half-life of about 20 years which is lower than its radiological half-life of 28.6 years. However, given the standard deviation of the annual averages, the actual decrease probably is not much different from the radiological half-life. Point Beach discharged no airborne Sr-90 in 2018. Since 1997, PBNP has discharged airborne Sr-90 only in 3 years: 1999, 2.4E-08 Ci; 2004, 3.2E-08 Ci; and 2011, 1.6 E-08 Ci. It is interesting to note that six of highest Sr-90 results occur at E-11 located about 4.4 miles west of PBNP (Fig. 9-1 ). If the observed Sr-90 activity were from Point Beach the highest Sr-90 concentrations would occur at E-21, the dairy south of the site boundary in the highest X/Q and 0/Q.meteorological sector. This dairy grows feed corn on site and in a field across the road from the site boundary in the highest 0/Q sectors. Feed crops are the dominant source of food for dairy cattle. No cattle have been seen grazing for many years. The major Sr-90 input to the environment is from fallout from atmospheric weapons testing during the early 1960s with minor inputs during the 50's, 70's and later contributions from the Chernobyl accident in the late 1980s and from Fukushima in 2011. The Sr-90 in milk persists due to its 28.6 year half-life and to cycling in the biosphere. With little or no atmospheric input to the environment, the mode of entry into cattle feed must be root uptake by forage crops and transfer into the milk. Over the time period of this graph (1997- 2018), these low discharges do not appear to impact the decreasing concentrations as they continue to decrease over time. It is concluded that the milk data for 2018 show no radiological effects of the plant operation. Figure 11-3 Sr-90 Concentration in Milk (1997- 2018) Sr-90 in MILK 10 ~----------------------------------- 0.1 - ' - - - - - - - - - - - - - - - - - - - - - - - - - - - 1995 2000 2005 2010 2015 2020 2025 YEAR 48

11 .3 Air The average annual gross beta concentrations (plus/minus the 2a uncertainty) in weekly airborne particulates at the indicator and control locations were 3 0.024 +/- 0.017 pCi/m and 0.025 +/- 0.016 pCi/m 3 , respectively, and are similar to levels observed from 1993 through 2018 (Figure 11-4). The 2018 weekly gross beta concentrations reveal higher winter values and lower summer values (Figure 11-5). This is a repeat of the patterns seen in 2006 - 2017. The slight August- September peak is similar to what was observed in 2015 (Figure 11-6). The August-September peak is observed throughout the US and believed to result from weather patterns impacting with naturally occurring airborne radionuclides . This would explain why the control and indicators are moving in concert. Therefore, a plant effect can be ruled out. Figure 11-4 Annual Average Air Gross~ (1993- 2018) Gross J3 Concentration in Air 0.03 - , - - - - - - - - - - - - - - - - - - - - - s~ u 0.025 +----~~~~.--..----r~--.:~5"--- 0.02 _j__:'!~~~~=--=--=--_J~_:'!~~~=-----

                   ..:: 0.015     4--------------------
                    ~     0.01    4--------------------

e o.oo5 111

                    ~
                                  -+--------------------

0 -~-~--~--~-~--~-~--~ 1990 1995 2000 2005 2010 2015 2020 2025 YEAR Figure 11-5 2018 Airborne Gross Beta 2018 Airborne Gross Beta (pCifmAJ) vs. Time 0.060

E-02 M' 0.050 E I + E-01

0.040

() E:: E-03 ca. 0.030 tn X E-04 tn 0 0.020 I.. (!) ;K E-08 e E-20 0.000 ------.-----.---~r------r---.-----,---.,.----..J 1/1/18 2/20/ 18 4/ 11 / 18 5/31/18 7/20/ 18 9/8/ 18 10/28/18 12/17/18 DATE 49

Figure 11-6 2015 Airborne Gross Beta 2015Airborne Gross Beta (pCi/m"3) vs. Time 0 .070 -.---- - - - - - - - - - - - - - - - - - , 0 .0 60 + - - - - - - - - - - - - - - - - , - - - - - - - ; (") 0 .0 50 + - - - - - -* *- - - - -

u 0 .0 4 0 -t-------7 !~-----~-----==--------1

E-0 1

a. 0 .0 30 -----411!1~~------JI--:;::.~~, ._,.__--1 E -03 0 .020 + - - - - -------f!I:IIIIIIRI 0 .010 +--- - - - - - - - - ' x E-04 0 .000 + - - - - - - , - - - - - . - - - - - . - - - - - , - - - - - - ;

c E-08 9/ 18/ 14 12 /2711 4 4/6/15 7/ 15/ 15 10/23/1 5 1/31 / 16

E -20 DATE No 1-131 was detected during 2018. 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 0.0.021 pCilm 3 . Because the analysis LLD is based on counting only *one cartridge, the use of six cartridges or roughly six times the sample volume with the same count time as would be needed to achieve the desired LLD for only one sample, the actual LLD is about six times lower than the programmatic value given in Table 10-1. Similarly, the actual MDA is about one-sixth of that reported, in the range of 0.001 to 0.003 pCilm 3 .

At each sampling location, the particulate filters are composited quarterly and analyzed for Cs-134, Cs-137 and any other (Co-60) detectable gamma emitters. As summarized in Table 10-1, several gamma emitters were detected and all were <MDC, except for one Co-60 result at E-08 in the 4th quarter of 2018. E-08 is west of the plant, and the only Co-60 released was in October 2018 during the Unit 2 refueling outage. However, E-03, which is west of the plant, but closer to the plant than E-08, showed no positive Co-60 results during the 4th quarter of 2018. As, well, location E-01, which is in the highest X/Q and 0/Q meteorological sector, showed no positive Co-60 value in the 4th quarter 2018. While the low positive Co-60 result at E-08 may be attributable to Point Beach, based on the location and results when compared to the results at E-03 and E-01, E-08 is likely a false positive. By contrast, naturally occurring Beryllium-? was found in all of the quarterly composites at concentrations ranging from 0.040 to 0.095 pCilm 3 . Be-7 (T 112 =53.3 days) is produced in the atmosphere by the interaction of cosmic rays with oxygen and nitrogen nuclei. Its half-life is long enough to allow for it to be detected in the quarterly composited filters . 50

In summary, the 2018 air gamma data from quarterly composites do not indicate an environmental impact from the operation of PBNP. 11.4 Lake Water For the REMP-specified gamma emitting radionuclides listed in Table 10-1, the reported concentrations continue to occur as small, negative and positive values scattered around zero, indicating no radiological impact from the operation of PBNP. Only 24 of the results were positive, of which, nine are from north of the plant, sites E-33 and E-05 (see Figure 9-1 ). Only two of the 24 slightly positive results are >MDC. Both occurrences were for Zn-65 and occurred south of the site at E-01 and E-06 in different months. Both are concluded to be false positives because PBNP did not discharge any Zn-65 in 2018. Therefore, based on this, it is concluded that the positive results are false positives and not indications of PBNP effluents in Lake Michigan during 2018. A false positive is concluding an isotope is present when it isn't. False positives occur most often at the detection limit when the random fluctuations of the background result in lower than normal background activity. The result is a higher net count and hence falsely concluding an isotope is present when it isn't because the value is statistically above zero. In conclusion, based on the results of the gamma scans of Lake Michigan water, there is no measureable impact on the lake from PBNP discharges. Aliquots of the monthly samples are com posited quarterly and analyzed for Sr-89/90 and for tritium. Small amounts of Sr-90 were detected in four of the sixteen quarterly composites, three north and one south of the plant. All the results were below their statistically calculated minimum detectable concentrations (MDCs). No Sr-90 was discharged in 2018 or in 2012-2015 and 2017. A small amount was discharged in March of 2016. Sr-90 has a 28.6 year half-life and, like Cs-137, is a remnant of atmospheric weapons testing in the '50s and '60s. Therefore, positive Sr-90 concentrations could be indicative of fallout being recycled in Lake Michigan. However, because the concentrations are below their MDCs, they most likely are false positives and there for unlikely to be the result of past PBNP discharges. Tritium, in addition to being produced by water-cooled reactors such as PBNP, also is a naturally occurring radionuclide. It also was produced by atmospheric weapons testing. However, due to its mobility, any tritium now found in Lake Michigan at the concentrations typically found in monitoring programs cannot be from that time period. It is the result of power plant discharges. Point Beach discharges on the order of 700 - 1000 Ci of tritium per year. Sixteen quarterly lake water composites were generated from the monthly samples. Out of the sixteen quarterly composites, five had positive tritium indications, and of those five only two were greater than the MDC. Both of these occurred in the samples obtained at the site of the shut-down Kewaunee nuclear plant. Analysis of the individual monthly samples and date of sampling when compared to date of releases indicated that PBNP sampled shortly after a Kewaunee discharge in March and April. 51

The first quarter composite results from location E-33 contained the high tritium value. The tritium concentration was 31129 +/- 527 at E-33 (the Kewaunee site 5 miles north of PBNP), 123 +/- 90 at E-05 (Two Creeks boat ramp 3 miles north of PBNP), 129 +/-90 at E-01 (PBNP met tower -0.7 miles south of the plant), and 77 +/- 88 pCi!L at E-06 (Rawley Point light house six miles south of PBNP). Based on these results, the individual March samples were analyzed for tritium. The March sample from E-33 had 58778 +/- 715 pCi/1. At E-05 about 3 miles north of PBNP the tritium concentration was 353 +/- 91 pCi/L. Although Kewaunee is retired from service, it still makes discharges. Kewaunee made two tritium discharges on March 13th and 14th_ Point Beach had two tritium discharges on March ih and 9th, about six days prior to the obtaining the lake water samples. The concentrations of the Point Beach discharges were 1.85E+03 pCi/L-3.01 E+03 pCi!L. Point Beach sampled the lake water on March 15th right after Kewaunee began their discharge. The results at E-05 and E-01 directly south of Kewaunee showed positive tritium results that were both below the MDC of 160, and the result at E-06, six miles south of PBNP showed a result that was not statistically different than zero. Based on these results, it is unlikely that PBNP discharges had an impact on the observed elevated H-3 concentrations. The second quarter composite from location E-33 at the Kewaunee site had slightly elevated tritium at 377 +/- 82 pCi/L. The other location composites had H-3 concentrations ranging from -5 +/- 79 to 51 +/- 82 pCi/1, all below the MDC of 160 pCi/L. Kewaunee made four tritium discharges from April ih-11th. During that time Point Beach had one tritium discharge on April 8th. The concentration of the Point Beach discharge was 5.14+03 pCi!L. Point Beach samrled the lake water on April 11th after Kewaunee performed a discharge on April 1ot . None of the other three sites south of Kewaunee had detectable tritium in their second quarter composite sample. Based on the location of the higher lake water H-3 concentrations, it is concluded that the higher concentrations north of PBNP are not the result of PBNP effluent. 11.5 Algae Filamentous algae attached to rocks along the Lake Michigan shoreline are known to concentrate radionuclides from the water. Samples are obtained at Two Creeks Park and at the PBNP discharge (locations 5 and 12 in Figure 9-1). In order to allow the algae time to grow, typically samples are collected in August, and if none is available at that time, then a second attempt is made in October. In 2018 no algae samples were obtained. There either were no algae present or it was located in an inaccessible location. When no algae was available during the first sampling attempt, a second attempt was made to collect the sample during a different month. Again, none was available. Algae sampling is not called for in either NUREG-0472 or 1301 the standard RETS documents. However, PBNP has continued to collect algae as a good practice to provide continuity between the current REMP and the pre-operational REMP. 52

11.6 Fish Thirteen fish were analyzed in 2018 with twelve exhibiting detectable amounts of plant related activity. Of these, eleven were positive for Cs-137 with 5 Cs-137 results >MDC. No other radionuclide has a positive result >MDC. The positive Cs-137 concentrations ranged from 0.014 +/- 0.010 to 0.083 +/- 0.020 pCi/g. In 2018 PBNP released !JCi amounts of Cs-137 from February- March. This may be a source of the Cs-137 in the fish. The other Cs-137 source is the recycling of Cs-137 that entered Lake Michigan as fallout from atmospheric weapons testing in the

      '50s and '60s with lesser amounts from events at Chernobyl and Fukushima.

Positive results below their MDCs were found also for Mn-54, Co-58, Co-60, Ru-1 03 and Cs-134. It is concluded that these results are false positives. The highest radionuclide concentration in fish is naturally occurring K-40 with an average concentration of 2.68 +/- 0.84 pCi!g. Based on these results, it is concluded that there is little impact of PBNP discharges on Lake Michigan fish. 11.7 Well Water Small, positive values of Ba-La-140 were detected in the main plant well water (E-

10) during 2018. The value was below its minimum detectable concentrations 2.3 pCi/L. It is concluded that this slightly positive value is a false positives. Therefore, there is no evidence of PBNP effluents getting into the aquifer supplying drinking water to PBNP.

11.8 Soil Cs-137 is present in the soils throughout North America and the world resulting from the atmospheric nuclear weapons testing in the 1950s, 1960s, and 1970s and from the 1986 Chernobyl accident, and more recently, from the Fukushima event. Soil is an integrating sample media, in that it is a better indicator of long term buildup of Cs-137 as opposed to current deposition for local sources. In addition to erosion and radioactive decay, human activities can modify the soil Cs-137 concentrations. In 2018, Cs-137 was detected in all 8 soil samples obtained in October. The concentrations ranged from 0.04 +/- 0.02 to 0.20 +/- 0.03 and all were >MDC. The highest values for Cs-137 were found at E-08, E-02, and E-06, with concentrations of 0.20 +/- 0.027, 0.187 +/- 0.033, 0.15 +/- 0.019 respectively. No airborne release of Cs-137 occurred in 2018, with the most recent release of airborne Cs-137 occurring approximately one year prior in October 2017 for a total of 0.237 !JCi at a concentration of 1.96E-08 pCi/cc. Therefore, it seems unlikely that the observed soil Cs-137 is attributable to PBNP effluent. The most likely source is recycling of fallout from atmospheric weapons testing in the 50s and 60 as well as the Chernobyl and Fukushima events and subsequently being bound to the soil. 53

The soil samples from the remaining locations (E-01, -03, -04, -09, -20) Cs-137 results range from 0.04 +/- 0.02 to 0.122 +/- 0.032 pCilg. Based on the rather uniform distribution of Cs-137 in soils at various locations, no plant based effect is indicated. By comparison to naturally occurring radionuclides, Cs-137 continues to be present in soil samples at well below the levels of naturally occurring Be-7, K-40, and Ra-226 (see Table 10-1 ). 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. Four of the five samples have Cs-137 concentrations statistically different from zero with three results being >MDC. Shoreline sediment Cs-137 concentrations continue to be about one-tenth of that found in soils (Table 10-1 ). This is expected because Cs-137 in the geological media is bound to fine particles, such as clay, as opposed to the sand found on the beach. Lake Michigan sediments are a known reservoir of fallout Cs-137. Wave action suspends lake sediments depositing them on the beach. The fine particles deposited on the beach eventually are winnowed from the beach leaving the heavier sand; hence the lower Cs-137 concentrations in beach samples. In contrast to Cs-137, K-40, which is actually part of the minerals making up the clay and sand, is at a concentration about several hundred times higher than the Cs-137 that is attached to particle surfaces. Therefore, it is not surprising that Cs-137 is present at concentrations 1°/o or less of the naturally occurring concentrations of K-40. The most likely source of the observed Cs-137 is the cycling of fallout from atmospheric weapons tests and event such as Chernobyl and Fukushiima in the Lake Michigan environment and not current PBNP discharges. As with soil, the naturally occurring radionuclides such as K-40, and Ra-226 are found in the shoreline sediment samples. Therefore, the shoreline sediment data indicate no radiological effects from current plant operation. 11.10 Vegetation and Crops The REMP collects two general types of vegetation within the site. The first consists of general vegetation, non-cultivated plants which would be consumed by grazing cattle. The second consists of crops grown on site acreage licensed to farmers, about half the site's 1400 acres, for growing feed crops for cattle. Ten samples of cultivated crops (corn, hay, alfalfa, and soybeans) grown on this acreage were obtained for analyses. The naturally occurring radionuclides Be-7 and K-40 were found in all of the general vegetation and crop samples (Tables 10-1 and 10-2). The source of Be-7 is atmospheric deposition. It is continuously formed in the atmosphere by cosmic ray spallation of oxygen, carbon, and nitrogen atoms. (Spallation is a process whereby a cosmic ray breaks up the target atom's nucleus producing a radionuclide of lower mass.) Be-7 was lower in the crop samples with an average of 1.64 +/- 0.73 pCi/g, when compared to the vegetation samples that had an average of 2.56 +/- 1.54 pCi/g. In general vegetation Be-7 concentrations were higher and ranged from 0. 79 54

 +/- 0.15 to 7.40 +/- 0.46 pCilg, in comparison to the concentrations in the crop samples that range from 0. 74 +/- 0.16 to 2.82 +/- 0.26 pCi/g. The average concentrations in the vegetation increased from May (1.84 +/- 1.13 pCi/g) to September (4.07 +/- 1.96), and when compared to the crops that were obtained in September shows that the vegetation is about 2.5 times higher than the crop samples for Be-7. In contrast, K-40 is a primordial radionuclide which is incorporated into vegetation from the soil during the growing process. By not being dependent upon seasonal atmospheric variations and plant surface to capture deposition, the vegetation K-40 concentrations from root uptake are more uniform with a range of 3.34 +/- 0.40 to 8.92 +/- 0.44. In crops, similar to vegetation, the K-40 is higher than Be-7. Similar to Be-7 as well, the crops K-40 average of 3.33 +/- 1.41 pCi/g is lower than the average vegetation K-40 average of 5.43 +/- 1.35 pCi/g.

Cs-137 can be present in vegetation via both pathways. Fresh Cs-137 fallout is associated, like Be-7, with deposition on the plant surface. Old fallout from the '50s and '60s is now being incorporated into growing plants in the same manner as potassium because it is in the same chemical family as potassium. This fallout Cs-137 has been found in firewood ash at many locations in the United States that are far from any nuclear plants (S. Farber, "Cesium-137 in Wood Ash, Results of a Nationwide Survey," 5th Ann. Nat. Biofuels Conf., 10/21/1992). No Cs-137 was detected in the crop samples. In 2018 three of the twenty-four vegetation samples had a positive indication for Cs-137 and only E-06 had two results in May (0.084 +/- 0.022) and September (0.184 +/- 0. 0.028) that were above the MDC of 0.019 and 0.022 respectively. The other positive result was below the MDC and was found at the control location E-20. 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. The positive results from 2016 and 2017 were from E-

06. These occurrences were attributed to the above described mechanism. The only 2016 airborne Cs-137 discharged by PBNP occurred in March when there was no fresh vegetation. In 2017 the airborne Cs-137 release occurred in October after the vegetation and crops were collected, and in 2018 there was no airborne Cs-137 released in plant effluents. Therefore, the Cs-137 has to be the result of uptake via roots. Therefore, it is unlikely that the Cs-137 results indicate an impact from PBNP releases.

No Cs-134 or 1-131 were detected in the crop samples. In the vegetation samples one positive Cs-134 (below the MDC) result was obtained in May 2018 at location E-08. Since no Cs-134 was released in 2018, this result is likely a false positive. The only other radionuclide having a positive indication was 1-131, however all results were below the MDC value. In the vegetation, the 1-131 was identified in July at E-09, and in September at E-01, E-09, and the control location E-20. The control location had the highest concentration of 0.026 +/- 0.007 and was still below the MDC of 0.040 pCi/g. No 1-131 was released from the site in 2018. Therefore the 1-131 results are considered to be false positives. Based on the 2018 crop and general vegetation sampling results, it is concluded that there is little or no effect from PBNP effluents. 55

11.11 Land Use Census In accordance with the requirements of Section 12.2.5 of the ODCM, a visual verification of animals grazing in the vicinity of the PBNP site boundary was completed in 2018. No significant change in the use of pasturelands or grazing herds was noted. Therefore, the existing milk-sampling program continues to be acceptable. The nearest dairy (E-21) lies in the SSE sector and it is one of the Point Beach REMP milk sampling sites. This dairy leases land in the S and SSE sectors at the PBNP site boundary for growing feed corn. Also, the highest x/Q (1.09E-06) and D/Q (6.23E-09) values occur in these sectors. As demonstrated from the analyses of feed crops, there is no measureable plant impact on the crops grown on site by this dairy. 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. The 2017 LUC revealed no changes that would necessitate changes to the current REMP, such as the addition of new sampling locations. 11.12 Long Term TLD Trending To put the 2018 REMP TLD results in perspective, it is instructive to look at long term trends. The following examines the TLD results from 1971 to 2018. The ANSI standard (ANSIIHPS N13.37-2014 "Environmental Dosimetry) states that the data from early vintage dosimetry systems (c. 1970 - 1990) should not be considered comparable to current dosimetry systems in establishing a baseline for environmental TLD results. These problems are evident from the review of our early data as discussed below. The pre-operational data, 1968- 1970, are not included. The pre-operational ambient radiation monitoring sites were E-01 (the met tower area) through E-04 (the north boundary). They were monitored using TLDs and ionization chambers. E-04 was used as a background location until E-08 (see Figure 9-1) was added for the operational REMP in 1971. Prior to 1975, a control TLD stored in a lead pig was used for a comparison to those placed in the field. In the pre-operational data, the control TLD could be equal to or higher than the field results and both the field and control TLD results appear erratic compared to the ion-chamber results. Also, the reported TLD results do not have transportation exposures from New Mexico to Wisconsin subtracted. Therefore, only the TLD results beginning in 1971, with the transportation caveat, are used in this analysis of long-term trends. The trend at E-01 (Figure 11-7) shows slowly decreasing trend from 1971 to 1979. This is may be an artifact. The cause is not known. As previously mentioned, no transportation controls were used until the 4th quarter of 1975 so no transport dose corrections were made prior to that quarter. There is a small increase in 1980 when the current contracted REMP lab began. A slowly decreasing exposure rate occurs from 1980 - 1992 except for the 1984 - 1988 time segments. The erratic results from 1984- 1988 were traced to a faulty connection in the TLD reader. 56

Figure 11-7 E-01 Results 1971 - 2018 E-01 (mR/ 7-days) 3.00 2.50 1

       ~ 2.oo      I "C
     ,.:.. 1.50
     ~             l w*~~~r-E    1.00    I I

0.50 I 0.00 1/1/71 6/23/76 12/14/81 6/ 6/8 7 11/26/92 5/19/98 11/9/03 5/1/09 10/22/14 DATE The TLD package from 1980 to 2001 consisted of three LiF chips sealed in a black plastic bag. The magnitude of the error bars indicates the degree of variability of the 1984 - 1988 results from the three chips due to a fault in the TLD reader. The results appear much the same for the E-03 and E-20 results (Figure 11-8). Note that E-20 did not begin until 1976. Again, there is an increase in both the E-20 (the background site) and E-03 (the location nearest the ISFSI) which coincides with the switch from the LiF chips to the Teflon TLD cards. Given that the first twelve casks were loaded December 1995 to September 2000 in which there were no increases in the TLD results, the increase in 2001 indicates that this change is the result of the different response of the new TLDs and not of any effluents or shine from the plant. Figure 11-8 Comparison of E-03 and E-20 Results 1971 - 2018 3.50 ' 3.00 VI 2.50 , res I

  "C 2.00 I
   .....         I i:2' 1.so      I E      1.oo 0.50  I 0.00 1/1/71    6/23/76   12/14/81   6/6/87    11/ 26/92  5/19/ 98 11/9/03   5/1/09  10/ 22/14 DATE
                          -+- E-03 _._, E-20 -+- ......._ -....- -+- -+- -         -    -+-

Narrowing the time window for the TLD results from 1992 to the present allows for a comparison among the original four TLD locations since the introduction of the ISFSI (Figure 11-9) without the interference by the faulty TLD reader in the mid-1980s. Sites E-01 and E-02 are about 1 mile south of the ISFSI. E-03 is 1200 feet west and E-04 is 4300 feet north. 57

Figure 11-9 Comparison of E-01, E-02, E-03 and E-04 (1992 -2018) 2.00 1.80 1.60 tl) 1.40

"'  1.20

-c ,.!. 1.00 ~ 0.80 E o.6o 0.40 0.20 0 .00 1/1/92 9/27/94 6/23/97 3/19/00 12/14/02 9/9/05 6/5/08 3/2/11 11/26/13 8/22/16 DATE _._ E-01 _._ E-02 --.- E-03 E-04 ~ __._ ~ - -- ~ The comparison shows a definite difference between E-01 and the other three locations. E-01, although approximately the same distance from the ISFSI as E-02 and further away than either E-03 or E-04, is lower than the other three sites. Therefore, distance is not the determining factor in the difference among the measured exposures. There are two factors which could cause the observed difference. The first difference is that E-02, E-03, and E-04 are surrounded by plowed fields whereas the area around E-01 is uncultivated. Second, E-01 is within 100 feet of the lake. Therefore, about 50% of the area contributing natural radiation to the location is a combination of sandy soil, beach sand, and lake water. As seen from the REMP soil and beach analyses, the soil at E-01 has lower Ra-226 content (1.08 pCi/g) than the soil at E-02 (1.33 pCi/g). Results obtained for K-40 show a lower concentration at E-01 verse E-02 and E-04. Concentrations of K-40 are 18.55 pCi!g at E-01 vs.19.4 pCi/g (E-02 and E-04). E-03 soil was lower in Ra-226 (0.66 pCi!g) and K-40 (15.36 pCilg) in 2018, than was observed at locations E-01, E-02, and E-04. As seen from the REMP soil and beach sediment analyses, the beach sands at E-01 have lower Ra-226 (0.29 pCi/g) and K-40 (3. 73 pCi/g) concentrations than the soil at E-01. However, since E-01 has a combination of different natural radiation contributors (beach sand, lake water, and soil), that could explain the lower results that are observed at E-01. The impact of the ISFSI on the ambient radiation levels at its nearest site boundary, the west boundary is shown in Figure 11-10. The ISFSI impact on ambient exposure levels was addressed briefly in Section 11.1 (see Figure 11-2). 58

Figure 11-10 E-03, E-31, E-44 and Background Site E-20 Results 1992 to 2018 2.50 2.oo I

tD 1.50 "C I

       '  .r:::.       I 0::: 1.00 E

0.50 I 0.00 1/1/92 9/27/94 6/23/97 3/19/00 12/14/02 9/9/05 6/5/08 3/2/11 11/26/13 8/22/16 DATE

                           ---- E - - E-20      E-31     E-44   --   _._   -e- -

Figure 11-2 shows that beginning with the use of the Teflon TLD cards in the fourth quarter of 2000, the measured exposure levels at E-03 are 2 - 5 mR/7 -days lower than the exposures at the west fence of the ISFSI. Figure 11-10 shows that although their individual 95% confidence levels overlap indicating no statistical difference, the quarterly exposures at E-03 (about 1200 feet from the ISFSI) are consistently higher than the exposure at E-31 (at the site boundary about 1400 feet west of E-03). Therefore, the lower values at E-31 compared to E-03 appear to be a real difference as the distance from the ISFSI increases at the west boundary. Because land usage and location are similar at E-03 and E-31, the cause of the previously identified response differences between E-03 and E-01 are not applicable. Therefore, the lower results at the site boundary location E-31 show that the exposures from the ISFSI are dropping off and approaching the lower readings found at the background site E-20. 12.0 REMP CONCLUSION Based on the analytical results from the 807 environmental samples (767 individual samples with an additional 24 quarterly air particulate composites and 16 quarterly lake water composites) together with 129 REMP + 16 ISFSI sets of TLDs that comprised the PBNP REMP for 2018, PBNP effluents had no discernable effect on the surrounding environs. The calculated effluent doses are below the 10 CFR 50, Appendix I dose objectives demonstrate that PBNP continues to have good controls on effluent releases. The control of effluents from PBNP continues to be acceptable pursuant to the ALARA criteria of 10 CFR 50.34a. Additionally, when the TLD results are factored in to the overall exposure, the resulting doses are lower than the ISFSI (1 0 CFR 72.1 04) and EPA (40 CFR 190) limits of 25 mrem whole body, 75 mrem thyroid, and 25 mrem any other organ. From the long-term analysis of TLD results, there is no evidence of elevated ambient radiation levels from the operation of Point Beach and the ISFSI except for the slightly higher exposures measured at the site boundary (E-31) compared to the background reference site (E-20) [see Figure 11-1 0]. 59

I Part D GROUNDWATER MONITORING I 13.0 PROGRAM DESCRIPTION PBNP monitors groundwater for tritium as part of the Groundwater Protection Program (GWPP). The GWPP supports NEI 07-07, the nuclear industry's groundwater protection initiative. The GWPP also fulfills the requirement of 10 CFR 20.1501 (a) to make surveys of areas, including to subsurface in order to comply with Part 20. During 2018 the sampling program consisted of beach drains, intermittent stream and bog locations, drinking water wells, fagade wells, yard electrical manholes, ground water monitoring wells, and the subsurface drainage (SSD) system sump located in the U-2 fagade. 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 tritium 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 tritium, the beach drains are monitored as part of the groundwater monitoring program. In addition to tritium, groundwater beach drain samples also are gamma scanned for the same suite of radio nuclides as lake water using the lake water LLDs. Three intermittent stream locations and the Energy Information Center (EIC) well were added to the groundwater monitoring program in the late 1990s when it was discovered that tritium diffusion from the then operable, earthen retention pond was observable in the intermittent streams which transverse the site in a NW to SE direction. A fourth stream location closer to the plant was added in 2008. These streams pass on the east and west sides of the former retention pond and empty into Lake Michigan about half a mile south of the plant near the meteorological tower. The intermittent stream samples track tritium in the surface groundwater. The groundwater monitoring program also includes two bogs I ponds on site. One is located about 400 feet SSE of the former retention pond; the other, about 1500 feet N between Warehouses 6 and 7. In addition to the main plant well, four other drinking water wells are monitored. The Site Boundary Control Center well, located at the plant entrance, the Warehouse 6 well, on the north side of the plant, and the EIC well, located south of the plant. In 2012, a new building (Warehouse 7) was constructed for radwaste. The well for this building was added to the GWPP. These wells do not draw water from the top 20 - 30 feet of soil which is known to contain tritium. These wells monitor the deeper (200 - 600 feet), drinking water aquifer from 60

which the main plant well draws its water. The two soil layers are separated by a gray, very dense till layer of low permeability identified by hydrological studies. Manholes in the plant yard and for the subsurface drainage (SSD) system under the plant are available for obtaining ground water samples. The plant yard manholes for accessing electrical conduits are susceptible to ground water in-leakage. Therefore, a number of these were sampled. The SSD system was designed to lessen hydrostatic pressure on the foundation by controlling the flow of water under the plant and around the perimeter of the foundation walls. The SSD system flows to a sump in the Unit 2 facade. The sump was sampled twelve times during 2018. Due to flooding concerns, man-holes and clean-outs for the SSD were sealed in 2014. Therefore, only the SSD sump now is used for sampling. In the 1990s, two wells were sunk in each unit's fagade to monitor the groundwater levels and look for evidence of concrete integrity as part of the lSI IWE Containment Inspection Program. These wells are stand pipes which are sampled periodically for chemical analyses. Fagade well sampling has been part of the GWPP since 2007. These wells are sampled quarterly. Rising lake levels and rip-rap added for flooding protection have impacted beach drain sampling. Beach drain S-1 has been sampled most frequently, ten out of twelve months. High lake levels have washed away the access to beach drain S-3 south of the U2 discharge allowing sampling only six times during 2018. S-7 and S-10 were available but had no flow. S-8 and S-9 were each available once during 2018, and at other times when accessible the locations had no flow. S-12 and S-13 are impacted by high lake levels and rip-rap. However, two samples were available from both S-12 and S-13 in 2018. Although one sample was obtained at S-11 in 2018, high lake levels and rip-rap made sampling impossible during the rest of the year. S-11 was removed from the GWPP sampling program in May 2018 after it was evaluated and determined that sampling at the location was a safety concern. Beach Drain location S-11 was documented as a background runoff location from the beach bluff. The principle source of water for this drain, in addition to rain, is snow melt. It has been determined, based on a study performed at Point Beach in 2010-2011 that the main source of radioactivity that would be observed in this system is recapture/washout of airborne tritium discharges. The recapture/washout study stated that based on the tritium concentrations observed in the rainwater collected close to the plant, recapture of tritium in airborne effluents are sufficient to account for the concentrations seen in the beach drains. Removing S-11 from the sampling schedule does not have a negative impact on the GWPP, as the location shows a lower level of tritium than is observed in nearby beach drain outfalls. There are also two groundwater monitoring wells and a bog location that are monitored upstream of this beach drain outfall that could provide early detection of radioactivity that is not caused by recapture/washout. The groundwater sampling sites (other than the beach drains, SSDs and manholes) are shown in Figure 13.1. 61

62 14.0 RESULTS AND DISCUSSION 14.1 Streams and Bogs The results from the surface groundwater monitoring associated with the former retention pond are presented in Table 14-1. For the most part, the creek results are barely above the detection level and less than the MDC. The highest averages are for the East Creek and STP which are in the groundwater flow path from the retention pond area to Lake Michigan. The West Creek is west of the former retention pond, an upstream location with respect to the groundwater flow. The tritium concentration at GW-08, close to the former retention pond, is about one-tenth of the tritium concentrations it had prior to the remediation of the retention pond. Table 14-1 Intermittent Streams and Bogs H-3 Concentration (pCi/1) Month GW-01 (E-01) GW-02 GW-03 GW-17 BOGS MDC Creek Confluence E. Creek W. Creek STP GW-07 GW-08 Jan NS +/- NS +/- NS +/- NS +/- 156 Feb NO +/- NS +/- NS +/- NS +/- 151 Mar NS +/- NS +/- NS +/- NS +/- 153 Apr 142 +/- 82 245 +/- 88 92 +/- 80 211 +/- 86 155 May 129 +/- 81 151 +/- 82 NO +/- 270 +/- 88 164 +/- 82 263 +/- 88 158 Jun NO +/- 186 +/- 88 NO +/- 138 +/- 85 157 Jul NO +/- 227 +/- 85 90 +/- 78 181 +/- 82 156 Aug NO +/- NO +/- NO +/- 80 +/- 77 152 Sep NO +/- 99 +/- 76 91 +/- 76 NO +/- 150 Oct NO +/- 110 +/- 76 NO +/- 241 +/- 83 150 Nov NS +/- NS +/- NS +/- NS +/- 153 Dec NS +/- NS +/- NS +/- NS +/- 157 Average 69 +/- 46 154 +/- 70 53 +/- 41 166 +/- 83 A blank indicates no sample was scheduled. Streams are sampled monthly; bogs, annually. NS = no sample due to dry or frozen. Values are presented as the measured value and the 95% confidence level counting

                      =                =

error. The LLD 200 pCi/1. ND measured value minus 2o is less than zero and <MDC. To be statistically correct, the measured, actual values for the NOs are used in calculating the average (i.e. 64+/-77, the 64 is used to calculate the average). STP is the north end of the E. Creek at the SE corner of the sewage treatment plant. The analyses of these surface water samples show low concentrations of tritium. Although 2 small positive tritium concentrations occur in samples from the confluence of the two creeks (GW-01 ), none of the concentrations are above the MDC. None of the West Creek (GW-03) samples had tritium above its MDC. In contrast, there are more positive results from GW-02 (south end of the East Creek) and GW-17 (located at the north end of the East Creek). GW-17 is east of the former retention pond area in the groundwater flow path to Lake Michigan. The STP and East Creek concentrations are generally lower than the 300 - 350 pCi/1 found before the retention pond was remediated in 2002. The bog (GW-08) SE of the former retention pond is higher than the bog at GW-07 north of the former retention pond. The lower tritium value at GW-07 indicates that 63

the impact of groundwater flow from the retention pond area is not to the north. These results are in conformance with the west to east groundwater flow described in the Site Conceptual Model and the FSAR. The GW-08 bog result is down from the 3200 - 3900 pCi/1 seen in 1999 before the retention pond was remediated and the 297 +/- 89 pCi/L seen in 2012. 14.2 Beach Drains The 2018 results for the beach drains that were sampled are presented in Table 14-

2. S-1 collects yard drainage from the north part of the site yard; S-3, from the south. Drains S-8 and S-9 carry water from the lake side yard drains whereas drains S-7 and S-1 0 are from the turbine building roof. S-11 is not connected to any yard drain system and mainly carries groundwater flow and runoff from a small lawn area south of the plant. S-12 is a drain from the external SSD which run along the outside northern half of the foundation wall, and S-13 is the south external SSD drain. They are not connected to the internal SSD under the plant which drains to a sump in the U2 fagade.

Table 14-2 2018 Beach Drain H-3 Concentration (pCi/1) Month S-1 S-12 S-8 S-9 S-13 S-3 S-11 MDC Jan NS +/- NS +/- NS +/- NS +/- NS +/- NS +/- NS +/- Feb NS +/- NS +/- NS +/- NS +/- NS +/- NS +/- NS +/- Mar 423 +/- 99 NF +/- NF +/- NF +/- NF +/- NF +/- NF +/- 158 Apr 190 +/- 85 426 +/- 96 NF +/- NF +/- NF +/- 491 +/- 99 157 +/- 83 156 May 199 +/- 84 NF +/- NF +/- NF +/- 287 +/- 89 382 +/- 93 D +/- 158 Jun 255 +/- 88 322 +/- 92 NF +/- NF +/- NF +/- NF +/- D +/- 159 Jul 236 +/- 85 NF +/- NF +/- NF +/- NF +/- NF +/- D +/- 154 Aug 184 +/- 81 NF +/- ND +/- NF +/- NF +/- 321 +/- 87 D +/- 151 Sep ND +/- NF +/- NF +/- ND +/- 113 +/- 79 82 +/- 77 D +/- 156 Oct 158 +/- 79 NF +/- NF +/- NF +/- NF +/- 238 +/- 83 D +/- 150 Nov 310 +/- 88 NF +/- NF +/- NF +/- NF +/- 238 +/- 84 D +/- 149 Dec 258 +/- 85 NF +/- NF +/- NF +/- NF +/- NF +/- D +/- 153 Avg = 223 +/- 105 374 +/- 73 ND +/- ND +/- 200 +/- 123 292 +/- 140 157 +/- 83

NO not detected and ~MDC NS = no sample NF =no sample due to no flow D = Discontinued from sampling program The tritium concentrations at S-1 and S-3 are consistent with results from previous years. Because high lake levels and the addition of rip-rap around some of the beach drains to prevent shoreline erosion and to address flooding concerns, it is not possible to sample from the other beach drains most of the year. However, the results from available samples are consistent with other groundwater results from various streams and manholes. Gamma scans were performed on the beach drain samples at the LLD used for lake water. A few indications of small, positive concentration values below their MDCs were found for Ba-La-140, Co-58, Co-60, Fe-59, Mn-54, and Cs-137, and Zr-Nb-95. No Ba-La-140 was released via liquid or airborne effluents in 2018. Also, all the positive results were below their MDCs. Therefore, it is concluded that all the 64

gamma results are false positives. This leaves tritium as the only PBNP radionuclide positively found in the beach drains. 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 tritium concentrations (Table 14-3). Z-065A and Z-065B are located on the west side of the pump house. Manholes, Z-066A and Z-067A through Z-0660 and Z-0670 are between the pump house and the turbine building and run in parallel in the NE section of the yard beginning just north of the Unit 2 truck bay and run from the Unit 2 truck bay north to the EDG building. Z-068 is located just west of the EDG building and north of Z-066/0670. Each of the two A, B, C, and D vaults is side by side. Based on being side-by-side, it is expected that the each pair of manholes 66A/67A, etc. would have similar tritium concentrations. This is appears to hold for all the paired vaults. The similarity of the May and September Z-068 tritium values is similar to the S-1 beach tritium values. Table 14-3 2018 East Yard Area Manhole Tritium (pCi/1) MH 5/7/2018 9/12/2018 Z-065A(M-1 )* NS +/- 240 +/- 84 Z-0658(M-2)* NS +/- 215 +/- 83 Z-066A 331 +/- 91 165 +/- 80 Z-067A 465 +/- 97 236 +/- 84 Z-0668 247 +/- 87 213 +/- 83 Z-0678 197 +/- 84 243 +/- 84 Z-066C 376 +/- 93 415 +/- 93 Z-067C 210 +/- 85 137 +/- 79 Z-0660 361 +/- 92 158 +/- 80 Z-0670 123 +/- 80 217 +/- 83 Z-068 240 +/- 87 ND +/- MDC 159 154

                      *Sample Date 9/13/2018 14.4  Facade Wells and Subsurface Drainage System There are two methods of sampling the groundwater under the plant foundation.

The first is a set of four shallow wells, two in each fac;ade. The other is a subsurface drainage system (SSD). The fac;ade wells were installed to monitor for groundwater conditions which may affect the integrity of the concrete and rebar of each unit's foundation. The SSD was designed to relieve hydrostatic pressure on each unit's foundation as well as the Auxiliary and Turbine buildings. The fagade wells are not located symmetrically in the two units. The Unit 1 fac;ade wells are east of the containment in theSE (1Z-361A) and NE (1Z-361 B) corners of the fagade. However, in Unit 2, there is one well in the NW corner (2Z-361A) and the other rotated approximately 180° in the SW corner (2Z-361 B). In each the well cap is level with the floor. 65

The 2018 fagade well results are shown in Table 14-4. The Unit 1 wells continue to have higher tritium concentrations than the U2 wells with 1Z-361A, in theSE corner of the Unit 1 fagade, having the highest tritium concentrations. An increase in tritium was observed in both Unit 1 fagade wells (1Z-361A and 1Z-361 B) and Unit 2 fagade well 2Z-361A in late May 2018. Reanalysis of the tritium from the May 2018 samples show that the results were valid and repeatable. The gamma scans on all four of the fagade wells from May 2018 trended as usual with no radionuclides above the minimum detectable concentration (MDC). Hard-to-detect (HTD) radionuclides (Fe-55, Ni-63, Sr-89, Sr-90, and Tc-99) were analyzed for in the May 2018 samples and all results were not detectable. Follow up samples from the fagade wells in early July and August 2018 showed that the tritium concentrations returned back to the normal trend values, with gamma scans also trending as expected. It is unknown as to why there was an increase in tritium in three of the four fagade wells in May 2018. There are no known system leaks. Results from the SSD and groundwater monitoring wells, as described below, show that there were no other increased tritium values during the time that the increase was observed in the fagade wells. Table 14-4 2018 Facade Well Water Tritium (pCi/1) UNIT1 UNIT2 Month 1Z-361A 1Z-361B 2Z-361A 2Z-361B MDC March 150 +/- 104 NO +/- NO +/- NO +/- 161 May 911 +/- 114 4486 +/- 210 2742 +/- 170 168 +/- 82 151 July 182 +/- 82 130 +/- 79 NO +/- NO +/- 153 August 176 +/- 80 113 +/- 77 NO +/- 113 +/- 77 151 October 199 +/- 81 104 +/- 76 NO +/- 127 +/- 77 150 NO =Not Detected and <MDC To relieve hydrostatic pressure on the foundation, Point Beach has an external and an internal subsurface drainage system (SSD) to drain groundwater away from the foundation. The internal SSD consist of perforated piping which drains groundwater by gravity to a sump located in the Unit 2 fagade. A comparison of the 2016 through 2018 SSD results is presented in Table 14-5. In 2018, the tritium concentrations returned the normal concentrations of tritium observed in 2016. Why the tritium concentration increased by an order of magnitude in October 2017 is not known. There were no known system leaks. The SSD system and the fagade wells sample the groundwater under the plant foundation. Again in 2018, as in 2016 and 2017, the SSD sump has higher tritium concentrations than the fagade wells, with the exception of the three fagade wells in May 2018. Why the fagade wells typically have lower tritium is not known. The difference, however, does illustrate that the groundwater tritium was not uniformly distributed under the foundation. This was demonstrated by the SSD sump tritium increase that was observed in October 2017 (8772 pCi/L), while the four fagade wells in October 2017 remained at tritium values that ranged from 83 - 271 pCi/L. 66

Table 14-5 2016 - 2018 Unit 2 Facade SSD Sump H-3 (pCi/1) 2016 2017 2018 Date pCi/1 20' pCi/1 20' pCi/1 2a Jan 499 +/- 102 1058 +/- 122 2634 +/- 168 Feb 510 +/- 102 776 +/- 107 2721 +/- 169 Mar 507 +/- 99 765 +/- 111 2217 +/- 169 Apr 572 +/- 102 1635 +/- 142 1107 +/- 122 May 1018 +/- 133 1503 +/- 134 389 +/- 98 Jun 1230 +/- 125 854 +/- 112 890 +/- 113 Jul 1333 +/- 128 907 +/- 115 1225 +/- 127 Aug 929 +/- 116 1035 +/- 115 1056 +/- 119 Sep 615 +/- 104 737 +/- 105 803 +/- 110 Oct 966 +/- 119 8772 +/- 284 1022 +/- 116 Nov 1616 +/- 140 7478 +/- 265 852 +/- 111 Dec 1523 +/- 136 4165 +/- 203 634 +/- 106 Average 943 +/- 410 2474 +/- 2815 1296 +/- 781 The SSD sump samples are scanned for gamma emitters. A few slightly positive values were found for Co-58, Cs-134, Cs-137, and Ba-La-140, all results were below the MDC. The H-3 in the SSD system sump is discharged via the wastewater effluent system. The external SSD system runs along the external foundation walls for the Unit 1 and Unit 2 facades, the Auxiliary Building, the North Service Building, and the Turbine Hall. It is not connected to the internal SSD system. During 2014, work to mitigate the possibility of external flooding events uncovered the N (S-12) and S (S-13) external SSD outfalls. Both the north and south halves of the external SSD system drain toward the beach. Two samples each from SSD S-12 and S-13 were obtained in 2018. The results ranged from 113- 426 pCi/L, which is comparable to the concentrations found in various manholes (Table 14-3) on the east side of the plant during 2018. In addition to H-3 analysis, the fagade wells were gamma scanned. As in lake water samples, small positive values below their calculated, minimum detectable concentrations were found for Co-58, Zr-Nb-95, Cs-134, Cs-137, and Ba-La-140. Because all values were less than or equal to the MDC, it is concluded that these results are false positives. 14.5 Potable Water and Monitoring Wells Outside of the protected area, ten wells, in addition to the main plant well (Section

11. 7), are used for monitoring tritium in groundwater: the four potable water wells, GW-04 (Energy Information Center or EIC), GW-05 (Warehouse 6), GW-18 (Warehouse 7), GW-06 (Site Boundary Control Center), and six tritium 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 67

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, clay layer with very low permeability. The potable water wells had no detectable tritium (Table 14-6). Table 14-6 2018 Potable Well Water Tritium Concentration (pCi/1) t:.IC Warehouse SBCC GW-05, EIC WELL MDC 6Well Well WH7 06, 18 Month GW-04 GW-05 GW-06 GW-18 MDC Jan NO 156 NO NO NO 154 Feb NO 151 Mar NO 153 Apr NO 155 NO NO NO 161 May NO 158 Jun NO 157 Jul NO 156 NO NO NO 156 Aug NO 152 Sep NO 150 Oct NO 150 NO NO NO 150 Nov NO 153 Dec NO 157 ND= not detected The monitoring well results are similar to those obtained in 2017. The two monitoring wells showing higher and consistently detectable tritium (GW-15, GW-

16) are in the flow path from the retention pond area to the lake (Table 14-7).

Similar results were obtained in 2016. Table 14-7 2018 Quarterly Monitoring Well Tritium (pCi/1) MW-01 MW-02 MW-06 MW-05 MW-04 MW-03 Q GW-11 GW-12 GW-13 GW-14 *GW-15 *GW-16 MDC 1 ND +/- ND +/- 84 +/- 77 ND +/- 139 +/- 80 NS +/- 154 2 222 +/- 86 ND +/- ND +/- 188 +/- 84 145 +/- 82 227 +/- 86 158 3 ND +/- ND +/- ND +/- 77 +/- 76 209 +/- 83 129 +/- 79 152 4 197 +/- 81 ND +/- ND +/- ND +/- ND +/- 264 +/- 84 150 ND= not stat1st1cally different from zero and <MDC. NS =no sample available

Duplicate samples taken, highest value reported.

In summary, the results from monitoring wells GW-15 and GW-16 as well as results from the nearby surface water sample locations (GW-03, the east creek; GW-08, the bog to theSE of the former pond; and GW-17, the surface water on theSE corner of the STP) show that the area around and in the groundwater flow path from the former retention pond remain impacted by the tritium that diffused from the pond into the soil while it was in use. 68

15.0 GROUNDWATER

SUMMARY

Groundwater monitoring indicates that low levels of tritium continue to occur in the upper soil layer but not in the deep, drinking water aquifer. These results also indicate that the low levels of tritium are restricted to a small, well defined area close to the plant. Results from precipitation analyses (2011 AMR) show that airborne tritium concentrations are higher close to the plant as compared to results at the site boundaries. The observed tritium concentrations in the yard manholes can be explained by the higher tritium in precipitation close to the plant. In addition to tritium captured by precipitation, the beach drains also receive the tritium captured in the AC condensate because the condensate drainage is connected to the yard drain system. Tritium continues in the soil below the plant foundation as evidenced by results from the subsurface drainage system and from the fagade wells. In conclusion, the groundwater tritium 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 tritium 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 two monitoring wells west of the plant (GW-12 and GW-13, Figure 13-1 ). Additionally, because no tritium is detected in either of the four on-site drinking water wells close to the power block or from the drinking water well at the site boundary, none of the tritium observed in the upper soil layer has penetrated into the drinking water aquifer to impact either on-site or off-site personnel. 69

APPENDIX 1 Environmental, Inc. Midwest Laboratory Final Report for the Point Beach Nuclear Plant and Other Analyses Reporting Period: January- December 2018 97 pages follow

   ~*L_ ATI                EQvironmental, Inc.
     "+~J-\1               M1dwest Laboratory 700 Landwellr Road

Northllrook. IL 60062-2310 phone (847) 564-0700
fax (847) 564-4517 MONTHLY PROGRESS 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, 2018 Reviewed and Approved by-----~~----:-:-~::-~--*--- oJJJ. Date _ 1_,..,1_3_ 1...,../_*_CJ_ __ anavali, PhD. Laboratory Manager Distribution: S. Bartels, 1 hardcopy, 1 email

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

1.0 INTRODUCTION

..                                                   ... iv 2.0     LISTING OF MISSED SAMPLES ..                                           v 3     DATA TABLES                                                .......... vi A     Interlaboratory Comparison Program Results .............          . .. A-1 B     Data Reporting Conventions .                             ********** B-1 c     Sampling Program and Locations ...                        .......... C-1 D     Graphs of Data Trends                                     .......... D-1 E      Supplemental Analyses .............                        .. ...... E-1 F      Special Analyses                                         .......... F-1 ii

POINT BEACH NUCLEAR PLANT LIST OF TABLES Airborne Particulates and lodine-131 Location E-01, Meteorological Tower.............................................. 1-1 Location E-02, Site Boundary Control Center .. .. ... .. . ... .. ... .... . .. .. .. .. ... 1-2 Location E-03, West Boundary...................................................... 1-3 Location E-04, North Boundary...................................................... 1-4 Location E-08, G. J. Francar Residence ......................................... 1-5 Location E-20, Silver Lake College................................................. 1-6 Airborne Particulates, Gamma Isotopic Analyses....................................... 2-1 Milk ........ .. ............... ..... ............. ............................................................. 3-1 Well Water............................................................................................. 4-1 Lake Water............................................................................................. 5-1 Lake Water, Analyses on Quarterly Composites ............................................... 6-1 Fish .................................................................................................................... 7-1 Shoreline Sediments .......................................................................................... 8-1 Soil ..................................................................................................................... 9-1 Vegetation (Grass) .............................................................................................. 10-1 Aquatic Vegetation ............................................................................................. 11-1 Gamma Radiation, as Measured by TLDs ........................................................ 12-1 Groundwater Monitoring Program ...................................................................... 13-1 Vegetation (Corn/Alfalfa) .................................................................................... 14-1 iii

POINT BEACH NUCLEAR PLANT

1.0 INTRODUCTION

The following constitutes the current Monthly Progress Report for the Environmental Radiological Monitoring Program conducted at the Point Beach Nuclear Plant, Two Rivers, Wisconsin. Results of completed analyses are presented in the attached tables. Missing entries indicate analyses that are not completed. These results will appear in subsequent reports. 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 all gamma isotopic analyses, the spectrum is computer scanned from 80 to 2048 KeV. Specifically included are Mn-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95, Nb-95, Ru-103, Ru-106, 1-131, Ba-La-140, Cs-134, Cs-137, Ce-141, and Ce-144. Naturally occurring gamma-emitters, such as K-40 and Ra daughters, are frequently detected in soil and sediment samples. Specific isotopes listed are K-40, Tl-208, Pb-212, Bi-214, Ra-226 and Ac-228. The results reported under "Other Gammas" may be Co-60, Ru-1 03 or any other radionuclide which is indicative of other gammas for the sample type. "Other Gammas" do not include naturally occuring radionuclides. All concentrations, except gross beta, are decay corrected. All samples were collected within the scheduled period unless noted otherwise in the Listing of Missed Samples. iv

POINT BEACH NUCLEAR PLANT 2.0 LISTING OF MISSED SAMPLES Expected Collection Sample Type Location Date Reason LW E-001 01-11-18 No sample due to icy conditions. LW E-006 01-11-18 No sample due to icy conditions. LW E-005 02-14-18 No sample due to icy conditions. LW E-006 02-14-18 No sample due to icy conditions. LW E-033 02-14-18 No sample due to icy conditions. TLD E-15 04-04-18 TLD lost in field. SL E-05 08-16-18 None growing. SL E-12 08-16-18 None growing . TLD E-7 10-02-18 TLD lost in field. TLD E-28 10-02-18 TLD lost in field. v

POINT BEACH NUCLEAR PLANT 3.0 Data Tables vi

POINT BEACH NUCLEAR PLANT Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131. Location: E-01, Meteorological Tower Units: pCi/m 3 Collection: Continuous, weekly exchange. Date Vol. Date Vol. Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-10-18 307 0.036 +/- 0.004 < 0.005 07-11-18 336 0.025 +/- 0.003 < 0.007 01-17-18 315 0.016 +/- 0.003 < 0.010 07-18-18 305 0.023 +/- 0.003 < 0.010 01-24-18 292 0.045 +/- 0.005 < 0.010 07-25-18 302 0.023 +/- 0.004 < 0.010 01-31-18 301 0.028 +/- 0.004 < 0.007 08-01-18 299 0.022 +/- 0.003 < 0.011 02-07-18 315 0.029 +/- 0.004 < 0.007 08-08-18 303 0.036 +/- 0.004 < 0.014 02-14-18 305 0.034 +/- 0.004 < 0.007 08-15-18 299 0.034 +/- 0.004 < 0.006 02-21-18 300 0.036 +/- 0.004 < 0.005 08-22-18 303 0.031 +/- 0.004 < 0.010 02-27-18 251 0.024 +/- 0.004 < 0.012 08-29-18 294 0.029 +/- 0.004 < 0.012 03-08-18 394 0.028 +/- 0.003 < 0.005 09-05-18 294 0.014 +/- 0.003 < 0.008 03-14-18 260 0.025 +/- 0.004 < 0.008 09-11-18 258 0.016 +/- 0.003 < 0.009 03-21-18 299 0.028 +/- 0.004 < 0.010 09-19-18 320 0.024 +/- 0.003 < 0.005 03-28-18 304 0.023 +/- 0.003 < 0.009 09-26-18 296 0.018 +/- 0.003 < 0.006 10-02-18 253 0.025 +/- 0.004 < 0.013 1st Quarter 3rd Quarter Mean+/- s.d. 0 .029 +/- 0 .008 < 0.008 Mean+/- s.d. 0.025 +/- 0.007 < 0.009 04-04-18 308 0 .025 +/- 0.004 < 0.008 10-10-18 337 0.015 +/- 0.003 < 0.009 04-12-18 341 0.032 +/- 0.004 < 0.012 10-17-18 305 0.017 +/- 0.003 < 0.021 04-18-18 268 0.021 +/- 0.004 < 0.008 10-24-18 304 0.015 +/- 0.003 < 0.009 04-25-18 307 0.028 +/- 0.004 < 0.008 10-31-18 302 0.019 +/- 0.003 < 0.010 05-02-18 295 0.019 +/- 0.004 < 0.008 11-07-18 289 0.016 +/- 0.004 < 0.006 05-09-18 314 0.018 +/- 0.003 < 0.010 11-14-18 303 0.020 +/- 0.003 < 0.009 05-16-18 300 0.016 +/- 0.003 < 0.008 11-21-18 299 0.026 +/- 0.004 < 0.010 05-23-18 296 0.017 +/- 0.003 < 0.007 11-28-18 301 0.020 +/- 0.004 < 0.010 05-30-18 295 0.032 +/- 0.004 < 0.008 12-05-18 305 0.017 +/- 0.003 < 0.014 06-06-18 311 0.012 +/-0.003 < 0.011 12-12-18 302 0.053 +/- 0.005 < 0.010 06-13-18 301 0.021 +/- 0.003 < 0.007 12-19-18 301 0.048 +/- 0.005 < 0.006 06-20-18 302 0.018 +/- 0.003 < 0.011 12-26-18 308 0.027 +/- 0.004 < 0.011 06-27-18 311 0.020 +/- 0.003 < 0.007 01-02-19 307 0.022 +/- 0.004 < 0.006 07-03-18 255 0.026 +/- 0.004 < 0.010 2nd Quarter 4th Quarter Mean+/- s.d. 0.022 +/- 0.006 < 0.009 Mean+/- s.d. 0.024 +/- 0.012 < 0.010 Cumulative Average 0.025 +/- 0.009 < 0.009 1-1

POINT BEACH NUCLEAR PLANT Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131. Location: E-02, Site Boundary Control Center 3 Units: pCilm Collection: Continuous, weekly exchange. Date Vol. Date Vol. Collected (m3) Gross Beta [-131 Collected (m3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-10-18 315 0.025 +/- 0.004 < 0.005 07-11-18 336 0.023 +/- 0.003 < 0.007 01-17-18 310 0.020 +/- 0.003 < 0.011 07-18-18 305 0.022 +/- 0.003 < 0.010 01-24-18 293 0.045 +/- 0.005 < 0.010 07-25-18 302 0.020 +/- 0.003 < 0.010 01-31-18 298 0.026 +/- 0.004 < 0.008 08-01-18 299 0.021 +/- 0.003 < 0.011 02-07-18 317 0.027 +/- 0.004 < 0.007 08-08-18 307 0.037 +/- 0.004 < 0.014 02-14-18 306 0.032 +/- 0.004 < 0.007 08-15-18 300 0.035 +/- 0.004 < 0.006 02-21-18 301 0.034 +/- 0.004 < 0.005 08-22-18 303 0.032 +/- 0.004 < 0.010 02-27-18 260 0.021 +/- 0.004 < 0.012 08-29-18 307 0.028 +/- 0.003 < 0.012 03-08-18 300 0. 033 +/- 0 .004 < 0.006 09-05-18 299 0.013 +/- 0.003 < 0.007 03-14-18 267 0.026 +/- 0.004 < 0.008 09-11-18 262 0.014 +/- 0.003 < 0.008 03-21-18 305 0.027 +/- 0.004 < 0.010 09-19-18 337 0.025 +/- 0.003 < 0.005 03-28-18 306 0.024 +/- 0.003 < 0.009 09-26-18 320 0.019 +/- 0.003 < 0.006 10-02-18 257 0.024 +/- 0.004 < 0.013 1st Quarter 3rd Quarter Mean+/- s.d. 0.028 +/- 0.007 < 0.008 Mean+/- s.d. 0.024 +/- 0.007 < 0.009 04-04-18 311 0.026 +/- 0.004 < 0.008 10-10-18 319 0.017 +/- 0.003 < 0.010 04-12-18 344 0.032 +/- 0.004 < 0.011 10-17-18 306 0.016 +/- 0.003 < 0.021 04-18-18 266 0.017 +/- 0.004 < 0.008 10-24-18 298 0.016 +/- 0 003 < 0.009 04-25--18 307 0.024 +/- 0.004 < 0.008 10-31-18 302 0.022 +/- 0.003 < 0.010 05-02-18 302 0.019 +/- 0.004 < 0.008 11-07-18 304 0.011 +/- 0.003 < 0.006 05-09-18 301 0.020 +/- 0.003 < 0.010 11-14-18 310 0.019 +/- 0.003 < 0.008 05-16-18 299 0.016 +/- 0.003 < 0.008 11-21-18 304 0.024 +/- 0.004 < 0.010 05-23-18 302 0.016 +/- 0.003 < 0.007 11-28-18 301 0.022 +/- 0 004 < 0.010 05-30-18 295 0.036 +/- 0.004 < 0.008 12-05-18 305 0.019 +/- 0.003 < 0.014 06-06-18 312 0.013 +/- 0.003 < 0.011 12-12-18 282 0.048 +/- 0 005 < 0.011 06-13-18 300 0.019 +/- 0.003 < 0.008 12-19-18 300 0.044 +/- 0.004 < 0.006 06-20-18 256 0.022 +/- 0.004 < 0.014 12-26-18 300 0.027 +/- 0.004 < 0.011 06-27-18 300 0.017 +/- 0.003 < 0.007 01-02-19 306 0.021 +/- 0.004 < 0.006 07-03-18 258 0.025 +/- 0.004 < 0.010 2nd Quarter 4th Quarter Mean+/- s.d. 0.022 +/- 0.007 < 0.009 Mean+/- s.d. 0.024 +/- 0.011 < 0.010 Cumulative Average 0.024 +/- 0.008 < 0.009 f-I. (:- [';

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1-2 f.

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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/m 3 Collection: Continuous, weekly exchange. Date VoL Date Vol. Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Reguired LLD 0.010 0.030 Reguired LLD 0.010 0.030 01-10-18 308 0.025 +/- 0.004 < 0.005 07-11-18 345 0.021 +/- 0.003 < 0.007 01-17-18 310 0.020 +/- 0.003 < 0.010 07-18-18 302 0.023 +/- 0.003 < 0.010 01-24-18 294 0.048 +/- 0.005 < 0.010 07-25-18 302 0.019 +/- 0.003 < 0.010 01-31-18 303 0 .025 +/- 0 .004 < 0.007 08-01-18 299 0.023 +/- 0.004 < 0.011 02-07-18 327 0.025 +/- 0.003 < 0.007 08-08-18 306 0.031 +/- 0.004 < 0.014 02-14-18 307 0.036 +/- 0.004 < 0.007 08-15-18 301 0.030 +/- 0.004 < 0.006 02-21-18 305 0.034 +/- 0.004 < 0.005 08-22-18 303 0.032 +/- 0.004 < 0.010 02-27-18 257 0.023 +/- 0.004 < 0.012 08-29-18 297 0.029 +/- 0.004 < 0.012 03-08-18 307 0.040 +/- 0.004 < 0.006 09-05-18 299 0.011 +/- 0.003 < 0.007 03-14-18 266 0.026 +/- 0.004 < 0.008 09-11-18 262 0.014 +/- 0.003 < 0.008 03-21-18 308 0.023 +/- 0.004 < 0.010 09-19-18 337 0 .025 +/- 0 .003 < 0.005 03-28-18 309 0.020 +/- 0.003 < 0.009 09-26-18 305 0.020 +/- 0.003 < 0.006 10-02-18 260 0.020 +/- 0.004 < 0.012 1st Quarter 3rd Quarter Mean+/- s.d. 0.029 +/- 0.009 < 0.008 Mean+/- s.d. 0.023 +/- 0.006 < 0.009 04-04-18 309 0.024 +/- 0.004 < 0.008 10-10-18 343 0.015 +/- 0.003 < 0.009 04-12-18 344 0.034 +/- 0.004 < 0.011 10-17-18 317 0.016 +/- 0.003 < 0.021 04-18-18 267 0.019 +/- 0.004 < 0.008 10-24-18 298 0.017 +/- 0.003 < 0.009 04-25-18 301 0.023 +/- 0.004 < 0.008 10-31-18 300 0.020 +/- 0.003 < 0.010 05-02-18 300 0.018 +/- 0.004 < 0.008 11-07-18 301 0 016 +/- 0.003 < 0.006 05-09-18 305 0.021 +/- 0.003 <0.010 11-14-18 317 0.021 +/- 0.003 < 0.008 05-16-18 300 0.018 +/- 0.003 < 0.008 11-21-18 296 0.025 +/- 0.004 < 0.010 05-23-18 300 0.017 +/- 0.003 < 0.007 11-28-18 302 0.024 +/- 0.004 < 0.010 05-30-18 292 0.033 +/- 0.004 < 0.008 12-05-18 305 0.019 +/- 0.003 < 0.014 06-06-18 313 0.013 +/- 0.003 < 0.011 12-12-18 302 0.048 +/- 0.005 < 0.010 06-13-18 307 0.017 +/- 0.003 < 0.007 12-19-18 301 0.045 +/- 0.004 < 0.006 06-20-18 314 0.019 +/- 0.003 < 0.011 12-26-18 311 0.026 +/- 0.004 < 0.011 06-27-18 313 0.017 +/- 0.003 < 0.007 01-02-19 312 0.021 +/- 0.004 < 0.006 07-03-18 258 0.031 +/- 0.004 < 0.010 2nd Quarter 4th Quarter Mean+/- s.d. 0.022 +/- 0.007 < 0.009 Mean+/- s.d. 0.024 +/- 0.011 < 0.010 Cumulative Average 0.024 +/- 0.008 < 0.009 1-3

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/m 3 Collection: Continuous, weekly exchange. Date Vol. Date Vol. Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-10-18 310 0.031 +/- 0. 004 < 0.005 07-11-18 344 0.025 +/- 0.003 < 0.007 01-17-18 314 0.019 +/- 0.003 < 0.010 07-18-18 303 0. 022 +/- 0.003 < 0.010 01-24-18 295 0.044 +/- 0.004 < 0.010 07-25-18 302 0.021 +/- 0.003 < 0.010 01-31-18 297 0.030 +/- 0.004 < 0.008 08-01-18 299 0.021 +/- 0.003 < 0.011 02-07-18 319 0.024 +/- 0.003 < 0.007 08-08-18 307 0.035 +/- 0.004 < 0.014 02-14-18 311 0.035 +/- 0.004 < 0.007 08-15-18 335 0.037 +/- 0.004 < 0.006 02-21-18 307 0.033 +/- 0.004 < 0.005 08-22-18 304 0.029 +/- 0.004 < 0 010 02-27-18 258 0.021 +/- 0.004 < 0.012 08-29-18 305 0.030 +/- 0.004 < 0.012 03-08-18 393 0.027 +/- 0.003 < 0.005 09-05-18 299 0.012 +/- 0.003 < 0.007 03-14-18 262 0. 032 +/- 0 .004 < 0.008 09-11-18 262 0.016 +/- 0.003 < 0.008 03-21-18 302 0.027 +/- 0.004 < 0.010 09-19-18 353 0.027 +/- 0.003 < 0.005 03-28-18 307 0.022 +/- 0.003 < 0.009 09-26-18 304 0.018 +/- 0.003 < 0.006 10-02-18 255 0.019 +/- 0.004 < 0.013 1st Quarter 3rd Quarter Mean+/- s.d. 0.029 +/- 0.007 < 0.008 Mean+/- s.d. 0.024 +/- 0.007 < 0.009 04-04-18 315 0.027 +/- 0.004 < 0.008 10-10-18 344 0.016 +/- 0.003 < 0.009 04-12-18 343 0.031 +/- 0.003 < 0.012 10-17-18 315 0.015 +/- 0 003 < 0.021 04-18-18 266 0.018 +/- 0.004 < 0.008 10-24-18 299 0.017 +/- 0.003 < 0.009 04-25-18 309 0.027 +/- 0.004 < 0.008 10-31-18 306 0.020 +/- 0.003 < 0.010 05-02-18 301 0.021 +/- 0.004 < 0.008 11-07-18 303 0.013 +/- 0.003 < 0.006 05-09-18 307 0.017 +/- 0.003 < 0.010 11-14-18 320 0.020 +/- 0.003 < 0.008 05-16-18 295 0.015 +/- 0.003 < 0.008 11-21-18 302 0.026 +/- 0.004 < 0.010 05-23-18 300 0.018 +/- 0.003 < 0.007 11-28-18 301 0.023 +/- 0.004 < 0.010 05-30-18 294 0.033 +/- 0.004 < 0.008 12-05-18 304 0.021 +/- 0.003 < 0.014 06-06-18 306 0.010 +/- 0.003 < 0.011 12-12-18 302 0.052 +/- 0.005 < 0.010 06-13-18 302 0.018 +/- 0.003 < 0.007 12-19-18 301 0.047 +/- 0.004 < 0.006 06-20-18 302 0.017 +/- 0.003 < 0.011 12-26-18 309 0.024 +/- 0.004 < 0.011 06-27-18 304 0.019 +/- 0.003 < 0.007 01-02-19 310 0.023 +/- 0.004 < 0.006 07-03-18 260 0.026 +/- 0.004 < 0.010 2nd Quarter 4th Quarter Mean+/- s.d. 0.021 +/- 0.007 < 0.009 Mean+/- s.d. 0.024 +/- 0.012 < 0.010 Cumulative Average 0.024 +/- 0.009 < 0.009 1-4

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/m 3 Collection: Continuous, weekly exchange. Date Vol. Date Vol. Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0 010 0.030 01-10-18 313 0.026 +/- 0.004 < 0.005 07-11-18 344 0.024 +/- 0.003 < 0.007 01-17-18 358 0.019 +/- 0.003 < 0.009 07-18-18 303 0.022 +/- 0.003 < 0.010 01-24-18 256 0.045 +/- 0.005 < 0.011 07-25-18 302 0.021 +/- 0.003 < 0.010 01-31-18 295 0.027 +/- 0.004 < 0.008 08-01-18 299 0.020 +/- 0.003 < 0.011 02-07-18 319 0.026 +/- 0.004 < 0.007 08-08-18 303 0.031 +/- 0.004 < 0.014 02-14-18 307 0 .035 +/- 0 .004 < 0.007 08-15-18 302 0.029 +/- 0.004 < 0.006 02-21-18 301 0 .037 +/- 0.004 < 0.005 08-22-18 300 0.033 +/- 0.004 < 0.010 02-27-18 255 0.023 +/- 0.004 < 0.012 08-29-18 295 0.027 +/- 0.004 < 0.012 03-08-18 387 0.030 +/- 0.003 < 0.005 09-05-18 302 0.014 +/-0.003 < 0.007 03-14-18 267 0.025 +/- 0.004 < 0.008 09-11-18 260 0.015 +/- 0.003 < 0.008 03-21-18 300 0.027 +/- 0.004 < 0.010 09-19-18 346 0.022 +/- 0.003 < 0.005 03-28-18 307 0.023 +/- 0.003 < 0.009 09-26-18 306 0.017 +/-0.003 < 0.006 10-02-18 256 0.020 +/- 0.004 < 0.013 1st Quarter 3rd Quarter Mean+/- s.d. 0.029 +/- 0.007 < 0.008 Mean+/- s.d. 0 .023 +/- 0.006 < 0.009 04-04-18 311 0.026 +/- 0.004 < 0.008 10-10-18 342 0.012 +/- 0.003 < 0.009 04-12-18 341 0.030 +/- 0.003 < 0.012 10-17-18 318 0.015 +/- 0.003 < 0.021 04-18-18 267 0.019 +/- 0.004 < 0.008 10-24-18 299 0.014 +/- 0.003 < 0.009 04-25-18 297 0.023 +/- 0.004 < 0.008 10-31-18 298 0.019 +/- 0.003 < 0.010 05-02-18 292 0.019 +/- 0.004 < 0.008 11-07-18 307 0.017 +/- 0.003 < 0.006 05-09-18 301 0.017 +/- 0.003 < 0.010 11-14-18 309 0.019 +/- 0.003 < 0.008 05-16-18 308 0.019 +/- 0.003 < 0.008 11-21-18 310 0.022 +/- 0.003 < 0.010 05-23-18 296 0.016 +/- 0.003 < 0.007 11-28-18 294 0.021 +/- 0.004 < 0.010 05-30-18 288 0.035 +/- 0.004 < 0.008 12-05-18 295 0 018 +/- 0.003 < 0.014 06-06-18 314 0.011 +/- 0.003 < 0.011 12-12-18 298 0.048 +/- 0.005 < 0.010 06-13-18 292 0.021 +/- 0.003 < 0.008 12-19-18 300 0.042 +/- 0.004 < 0.006 06-20-18 294 0.018 +/- 0.003 < 0.012 12-26-18 302 0.022 +/- 0.004 < 0.011 06-27-18 301 0.017 +/- 0.003 < 0.007 01-02-19 302 0.021 +/- 0.004 < 0.006 07-03-18 259 0.024 +/- 0.004 < 0.010 2nd Quarter 4th Quarter Mean+/- s.d. 0.021 +/- 0.006 < 0.009 Mean+/- s.d. 0.022 +/- 0.010 < 0.010 Cumulative Average 0.023 +/- 0.008 < 0.009 Indicator Locations Annual Mean +/- s.d. 0.025 +/- 0.007 < 0.009 1-5

POINT BEACH NUCLEAR PLANT Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131. Location: E-20, Silver Lake 3 Units: pCi/m Collection: Continuous, weekly exchange. Date Vol. Date Vol. Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-10-18 305 0.031 +/- 0.004 < 0.005 07-11-18 344 0.025 +/- 0.003 < 0.007 01-17-18 316 0.016 +/- 0.003 < 0.010 07-18-18 304 0.024 +/- 0.003 < 0.010 01-24-18 295 0.044 +/- 0.004 < 0.010 07-25-18 303 0.021 +/- 0.003 <0.010 01-31-18 305 0.025 +/- 0.004 < 0.007 08-01-18 297 0.020 +/- 0.003 < 0.011 02-07-18 318 0.026 +/- 0.004 < 0.007 08-08-18 307 0 029 +/- 0.004 < 0.014 02-14-18 308 0.034 +/- 0.004 < 0.007 08-15-18 296 0.033 +/- 0.004 < 0.006 02-21-18 303 0.035 +/- 0.004 < 0.005 08-22-18 301 0.035 +/- 0.004 < 0.010 02-27-18 252 0.025 +/- 0.004 < 0.012 08-29-18 296 0.031 +/- 0.004 < 0.012 03-08-18 394 0.030 +/- 0.003 < 0.005 09-05-18 294 0.013 +/- 0.003 < 0.008 03-14-18 273 0.026 +/- 0.004 < 0.008 09-11-18 258 0.022 +/- 0.004 < 0.009 03-21-18 307 0.030 +/- 0.004 < 0.010 09-19-18 346 0.024 +/- 0.003 < 0.005 03-28-18 307 0.023 +/- 0.003 < 0.009 09-26-18 306 0.022 +/- 0.003 < 0.006 10-02-18 256 0.023 +/- 0.004 < 0.013 1st Quarter 3rd Quarter Mean+/- s.d. 0.029 +/- 0.007 < 0.008 Mean+/- s.d. 0.025 +/- 0.006 < 0.009 04-04-18 315 0.025 +/- 0.004 < 0.008 10-10-18 342 0.013 +/- 0.003 < 0.009 04-12-18 347 0.031 +/- 0.003 < 0.011 10-17-18 314 0.019 +/- 0.003 < 0.021 04-18-18 264 0.018 +/- 0.004 < 0.008 10-24-18 300 0.017 +/- 0.003 < 0.009 04-25-18 301 0.025 +/- 0.004 < 0.008 10-31-18 301 0.023 +/- 0.003 < 0.010 05-02-18 299 0.021 +/- 0.004 < 0.008 11-07-18 304 0.015 +/- 0.003 < 0.006 05-09-18 302 0.019 +/- 0.003 < 0.010 11-14-18 313 0.019 +/- 0.003 < 0.008 05-16-18 296 0.016 +/- 0.003 < 0.008 11-21-18 302 0.025 +/- 0.004 < 0.010 05-23-18 296 0.019 +/- 0.003 < 0.007 11-28-18 302 0.021 +/- 0.004 < 0.010 05-30-18 298 0.034 +/- 0.004 < 0.008 12-05-18 298 0.020 +/- 0.003 < 0.014 06-06-18 311 0.013 +/- 0.003 < 0.011 12-12-18 302 0.053 +/- 0.005 < 0.010 06-13-18 303 0.019 +/- 0.003 < 0.007 12-19-18 300 0.046 +/- 0.004 < 0.006 06-20-18 307 0.019 +/- 0.003 < 0.011 12-26-18 315 0.029 +/- 0.004 < 0.010 06-27-18 315 0.017 +/- 0.003 < 0.006 01-02-19 314 0.021 +/- 0.004 < 0.006 07-03-18 257 0.024 +/- 0 .004 < 0.010 2nd Quarter 4th Quarter Mean+/- s.d. 0.021 +/- 0.006 < 0.009 Mean+/- s.d. 0.025 +/- 0.012 < 0.010 0.022 Cumulative Average 0.025 +/- 0.008 < 0.009 Control Annual Mean+/- s.d. 0.025 +/- 0.008 < 0.009 I l 1-6 I

POINT BEACH NUCLEAR PLANT Table 2. Gamma emitters in quatterly composites of air particulate filters 3 Un1ts: pCi/m (Other) (Other) Locat1on 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- 1304 0.079 +/- 0015 -0.0001 +/- 0.0004 < 0.0008 0.0001 +/- 0.0006 < 0.0009 -0.0001 +/- 0.0005 < 0.0005 3642 E-02 - 1305 0.092 +/- 0.017 0.0002 +/- 0.0005 < 0.0009 0.0002 +/- 0.0006 < 0.0006 0.0002 +/- 0.0006 < 0.0008 3578 E-03 - 1306 0.088 +/- 0.015 -0.0002 +/- 0.0005 < 0.0007 -0.0004 +/- 0.0004 < 0.0004 0.0004 +/- 0 0005 < 0.0007 3602 E-04 - 1307 0.062 +/- 0.018 0.0000 +/- 0.0005 < 0.0010 0.0005 +/- 0.0006 < 0.0010 -0.0001 +/- 0.0003 < 0.0005 3676 E-08 - 1308 0.064 +/- 0.019 -0.0013 +/- 0.0008 < 0.0013 0.0002 +/- 0.0008 < 0.0015 0.0006 +/- 0.0007 < 0.0008 3665 E-20 - 1309 0.074 + 0.013 -0.0001 +/- 0.0004 < 0.0006 -0.0003 + 0.0004 < 0.0005 0.0000 + 0 0003 < 0.0004 3681 2nd Quarter E-01 2955 0.090 +/- 0.013 -0.0001 +/- 0.0004 < 0.0008 -0.0004 +/- 0.0005 < 0.0006 0.0000 +/- 0 0006 < 0.0005 4204 E-02 2956 0.095 +/- 0.014 0.0002 +/- 0.0004 < 0.0006 -0.0005 +/- 0.0005 < 0.0007 -0.0001 +/- 0.0005 < 0.0003 4153 E-03 2957 0095 +/-0.016 -0.0005 +/- 0.0005 < 0.0008 0.0001 +/- 0.0005 < 0.0005 -0.0001 +/- 0.0006 < 0.0006 4221 E-04 2958 0.089 +/- 0.015 -0.0008 +/- 0.0006 < 0.0010 -0.0002 +/- 0.0006 < 0.0009 0.0004 +/- 0 0007 < 0.0011 4204 E-08 2960 0.088 +/- 0.012 -0.0002 +/- 0.0004 < 0.0007 -0.0003 +/- 0.0005 < 0.0006 -0.0002 +/- 0 0004 < 0.0004 4161 E-20 2961 0.088 +/- 0.012 0.0002 +/- 0.0003 < 0.0007 -0.0001 +/- 0.0004 < 0.0005 0.0002 +/- 0.0004 < 0.0003 4210 3rd Quarter E-01 EAP- 4452 0.069 +/- 0.012 -0.0001 +/- 0.0005 < 0.0009 0.0007 +/- 0.0006 < 0.0008 -0.0008 +/- 0 0007 < 0.0008 3862 E-02 - 4454 0083 +/- 0.015 -0.0001 +/- 0.0004 < 0.0009 -0.0002 +/- 0.0006 < 0.0006 0.0003 +/- 0.0005 < 0.0004 3934 E-03 - 4455 0.067 +/- 0.013 -0.0004 +/- 0.0005 < 0.0011 0.0005 +/- 0.0005 < 0.0007 0.0001 +/- 0. 0007 < 0.0005 3919 E-04 - 4456 0.065 +/- 0.012 0. 0001 +/- 0.0005 < 0.0009 -0.0003 +/- 0.0005 < 0.0004 0.0003 +/- 0. 0005 < 0.0008 3971 E-08 - 4457 0.067 +/-0012 0.0001 +/- 0.0005 < 0.0011 -0.001 0 +/- 0.0006 < 0.0004 0.0002 +/- 0 0005 < 0.0004 3916 E-20 -4458 0.070 + 0.014 0.0003 + 0.0005 < 0.0009 -0.0004 +/- 0.0006 < 0.0007 -0.0003 +/- 0.0006 < 0.0007 3908 4th Quarter E-01 EAP- 5577 0.047 +/- 0018 -0 0007 +/- 0.0006 < 0.0011 -0.0002 +/- 0.0007 < 0.0008 0.0005 +/- 0.0008 < 0.0007 3963 E-02 5578 0.054 +/- 0.013 0.0001 +/- 0.0004 < 0.0007 0.0001 +/- 0.0005 < 0.0008 -0.0006 +/- 0.0006 < 0.0003 3936 E-03 5579 0.040 +/-0012 -0.0004 +/- 0 0004 < 0.0007 -0.0003 +/- 0.0004 < 0.0005 -0.0003 +/- 0.0004 < 0.0004 4004 E-04 5580 0.052 +/- 0.016 -0.0003 +/- 0.0006 < 0.0009 00002 +/- 0.0005 < 0.0003 0. 0002 +/- 0.0006 < 0.0006 4014 E-08 5581 0.051 +/- 0.017 -0.0002 +/- 0.0006 < 0.0011 0.0002 +/- 0.0007 < 0.0010 0.0008 +/- 0.0006 < 0.0006 3973 E-20 5582 0.052 +/- 0.012 -0.0003 +/- 0.0004 < 0.0008 0.0003 +/- 0.0004 < 0.0006 0.0000 +/- 0.0004 < 0 0004 4007 Annual Mean+/-s.d. 0.072 +/- 0.017 *0.0002 :f; 0.0004 < 0.0009 -0.0001 +/- 0.0004 < 0.0007 0.0001 +/- 0.0004 < 0.0006 2-1

POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L) E-11 Lambert Dai!Y Farm MDC MDC MDC Required Collection Date 01-10-18 02-14-18 03-14-18 LLD Lab Code EMI- 88 EMI- 490 EMI- 881 Sr-89 -0.2 +/- 0.7 < 0.7 0.2 +/- 0.6 < 0.6 0.0 +/- 0.7 < 0.7 5.0 Sr-90 0.6 +/- 0.3 < 0.5 0.3 +/- 0.3 < 0.5 0.6 +/- 0 3 < 0.5 1.0 1-131 0.11+/-0.15 < 0.26 0.14 +/- 0.14 < 0.25 0.07 +/- 0.21 < 0.41 0.5 K-40 1302 +/- 113 1278 +/- 94 1292 +/- 105 Cs-134 -0.2 +/- 2.0 < 3.9 1.0+/-1.6 < 2.8 0.8 +/- 1.8 < 3.5 5.0 Cs-137 -1.6 +/- 2.4 < 3.2 0.2 +/- 1.8 < 2.9 -0.5 +/- 2.3 < 3.3 5.0 Ba-La-140 0.3 +/- 2.2 < 2.6 -1.6 +/- 1.8 < 1.6 0.2 +/- 1.7 < 1. 7 5.0 Other (Co-60) 1.9 +/- 2.4 < 3.3 -1 1 +/- 2.3 < 2.8 -0.2 +/- 2.3 < 3.3 15.0 Collection Date 04-11-18 05-09-18 06-13-18 Lab Code EMI- 1156 EMI- 1733 EMI- 2295 Sr-89 0.4 +/- 0.8 < 0.9 -0.6 +/- 0.7 < 0.7 0.6 +/- 0.7 < 0.7 5.0 Sr-90 0.5 +/- 0.3 < 0.6 0.8 +/- 0.3 c:: 0.5 0.3 +/- 0.3 < 0.6 1.0 1-131 -0.05 +/- 0.14 < 0.25 0.02 +/- 0.17 < 0.31 0.01 +/- 0.12 < 0.22 05 K-40 1281 +/- 113 1410+/-101 1311 +/- 107 Cs-134 0.9 +/- 2.0 < 3.6 0.2 +/- 1.6 < 2.9 -0.3 +/- 1.9 < 3.5 5.0 Cs-137 -1.7 +/- 2.3 < 2.4 1.6 +/- 1.9 < 3.9 0.5 +/- 2.2 < 2.9 5.0 Ba-La-140 -2.3 +/- 2.4 < 2.6 -0.4 +/- 1.3 < 2.5 -2.9 +/- 1.8 < 3.2 5.0 Other (Co-60) 0.8 +/- 2.4 < 3.2 -0.7 +/- 2.1 < 2.3 0.7 +/- 22 <40 15.0 3-1

POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L) E-11 Lambert Dai(Y Farm MDC MDC MDC Required Collection Date 07-11-18 08-08-18 09-12-18 LLD Lab Code EMI- 2600 EMI- 3190 EMI- 3742 Sr-89 0.3 +/- 0.7 < 0.7 -0.2 +/- 0.9 < 0.9 -0.2 +/- 0.7 < 0.7 5.0 Sr-90 0.4 +/- 0.3 < 0.5 0.7 +/- 0.3 < 0.6 0.6 +/- 0.3 < 0.5 1.0 1-131 0.04+/-0.15 < 0.26 0.11 +/- 0.22 < 0.45 0.10 +/- 0.20 < 0.38 0.5 K-40 1159 +/- 105 1354 +/- 91 1431 +/- 122 Cs-134 -1.3+/-2.0 < 3.6 -0.4 +/- 1.6 < 2.6 -0.5 +/- 2.3 < 4.3 5.0 Cs-137 0.9 +/- 2.1 < 29 1.7 +/- 1.8 < 3.5 0.8 +/- 2.6 < 4.4 5.0 Ba-La-140 -0.5+/-2.1 < 1.4 -1.0 +/- 1.3 < 1.1 0.6 +/- 1.9 < 1.3 5.0 Other (Co-60) -2.4 +/- 2.4 < 2.5 0.7 +/- 1.6 < 2.4 -0.5 +/- 2.7 < 3.2 15.0 Collection Date 10-17-18 11-14-18 12-12-18 Lab Code EMI- 4329 EMI- 4847 EMI- 5273 Sr-89 -0.5 +/- 0.7 < 0.7 0.3 +/- 0.6 < 0.7 0.8 +/- 0.9 < 0.8 5.0 Sr-90 0.8 +/- 0.3 < 0.5 0.3 +/- 0.3 < 0.5 0.3 +/- 0.4 < 0.8 1.0 1-131 -0.02 +/- 0.14 < 0.26 0.07 +/- 0.15 < 0.27 -0.19 +/- 0.17 < 0.33 0.5 K-40 1460 +/- 116 1301 +/- 117 1267 +/- 107 Cs-134 -1.3 +/- 2.2 < 4.5 -1.8 +/- 2.2 < 4.5 -1.1 +/- 1.8 < 3.0 5.0 Cs-137 2.3 +/- 2.7 < 4.2 0.8 +/- 2.6 < 4.0 0.6 +/- 2.2 < 3.8 5.0 Ba-La-140 -1.4 +/- 2.1 < 1.7 -1.0 +/- 2.3 < 2.9 -0.6 +/- 2.2 < 4.9 5.0 Other (Co-60) -1.6 +/- 2.5 < 3.7 -1.6 +/- 2.5 < 3.3 0.1 +/- 2.7 < 3.7 15.0 3-2

POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L) E-21 Strutz D9i£Y Farm MDC MDC MDC Required Collection Date 01-10-18 02-14-18 03-14-18 LLD Lab Code EMI- 89 EMI- 491 EMI- 882 Sr-89 0.2 +/- 0.8 < 0.8 -0.4 +/- 0.7 < 0.7 0.2 +/- 0.6 < 0.7 5.0 Sr-90 0.2 +/- 0.3 < 0.7 0.4 +/- 0.3 < 0.6 0.1 +/- 0.2 < 0.5 1.0 l-131 0.01 +/- 0.13 < 0.24 0.21 +/- 0.25 < 0.48 0.03 +/- 0.13 < 0.24 0.5 K-40 1382 +/- 115 1449 +/- 98 1265 +/- 107 Cs-134 -0.4 +/- 1.8 < 3.0 -0.6 +/- 1.7 < 2.8 0.3 +/- 2.0 < 3.4 5.0 Cs-137 -0.8 +/- 2.1 < 2.4 -1.5 +/- 2.0 < 2.8 1.1 +/- 2.2 < 2.0 5.0 Ba-La-140 -0.7 +/- 1.8 < 1.9 0.1 +/- 1.5 < 1.0 -1.2 +/- 1.9 < 2.0 5.0 Other (Co-60) -0.6 +/- 2.2 < 2.0 0.5 +/- 1.7 < 2.8 -0.7 +/- 2.5 < 2.4 15.0 Collection Date 04-11-18 05-09-18 06-13-18 Lab Code EMI- 1157 EMI- 1734 EMI- 2296 Sr-89 0.5 +/- 0.6 < 0.7 0.0 +/- 0.7 < 0.8 0.6 +/- 0.7 < 0.8 5.0 Sr-90 0.1 +/- 0.3 < 0.5 0.5 +/- 0.3 < 0.5 0.2 +/- 0.3 < 0.6 1.0 l-131 -0.04 +/- 0.14 < 0.26 0.10 +/- 0.25 < 0.48 0.00 +/- 0.13 < 0.24 0.5 K-40 1407 +/- 103 1365 +/- 103 1297 +/- 112 Cs-134 -0.2 +/- 1.8 < 3.2 0.8 +/- 1.7 < 3.2 -0.4 +/- 2.2 <4.4 5.0 Cs-137 0.4 +/- 2.0 < 3.2 3.2 +/- 2.0 < 3.6 -0.5 +/- 2.3 < 3.6 5.0 Ba-La-140 -0.5 +/- 1.5 < 1.0 0.3 +/- 1.7 < 1.9 -2.2 +/- 2.0 < 3.5 5.0 Other (Co-60) -0.7 +/- 2.1 < 2.1 -0.3 +/- 2.0 < 2.3 0.6 +/- 2.4 < 2.8 15.0 3-3

POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L) E-21 Strutz Dairy Farm MDC MDC MDC Required Collection Date 07-11-18 08-08-18 09-12-18 LLD Lab Code EMI- 2601 EMI- 3191 EMI- 3743 Sr-89 0.2 +/- 0.7 < 0.9 0.4 +/- 0 7 < 0.8 0.0 +/- 0.7 < 0.8 5.0 Sr-90 0.2 +/- 0.3 < 0.5 0.6 +/- 0.3 < 0.5 0.3 +/- 0.3 < 0.5 1.0 1-131 0.03 +/- 0.15 < 0.27 0.06 +/- 0.14 < 0.25 0.13 +/- 0.14 < 0.25 0.5 K-40 1387 +/- 111 1309 +/- 88 1369 +/- 110 Cs-134 0.0 +/- 2.0 < 3.1 -0.6 +/- 1.4 < 2.8 -0.1 +/- 1.8 < 3.4 5.0 Cs-137 0.2 +/- 2.5 < 4.1 1.9 +/- 1.8 < 3.5 2.7 +/- 2.2 < 4.1 5.0 Ba-La-140 0.1 +/- 1.9 < 2.5 -1.2 +/- 1.6 < 3.1 0.4 +/- 2.3 < 3.3 5.0 Other (Co-60) -0.2 +/- 2.4 < 3.3 0.1 +/- 1.6 < 2.3 0.4 +/- 2.3 < 3.4 15.0 Collection Date 10-17-18 11-14-18 12-12-18 Lab Code EMI- 4330 EMI- 4848 EMI- 5274 Sr-89 0.0 +/- 0.7 < 0.8 0.2 +/- 0.6 < 0.8 0.4 +/- 0.7 < 0.8 5.0 Sr-90 0.5 +/- 0.3 < 0.6 0.2 +/- 0.3 < 0.5 0.3 +/- 0.3 < 0.5 1.0 1-131 0.11 +/- 0.13 < 0.22 0.10 +/- 0.14 < 0.24 -0.16 +/- 0.16 < 0.30 0.5 K-40 1358 +/- 118 1298 +/- 115 1391 +/- 116 Cs-134 -0.4 +/- 2.1 < 3.9 3.2 +/- 2.2 < 4.5 1.2 +/- 2.1 < 3.8 5.0 Cs-137 1.0 +/- 2.6 < 4.7 0.4 +/- 2.3 < 3.3 1.5 +/- 2.0 < 3.9 5.0 Ba-La-140 -1.0 +/- 1.7 < 1.3 -2.8 +/- 1.6 < 1.6 -1.9 +/- 1.7 < 1. 7 5.0 Other (Co-60) 1.1 +/- 2.3 < 3.3 0.4 +/- 2.5 < 2.6 1.3 +/- 2.2 < 3.0 15.0 3-4

POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L) E-40 Barta MDC MDC MDC Required Collection Date 01-10-18 02-14-18 03-14-18 LLD Lab Code EMI- 90 EMI- 492 EMI- 883 Sr-89 -0.4 +/- 0.8 < 0.8 -0.5 +/- 0.6 < 0.6 -0.6 +/- 0.7 < 0.6 5.0 Sr-90 0.4 +/- 0.4 < 0.7 0.6 +/- 0.3 < 0.5 0.7 +/- 0.3 < 0.5 1.0 1-131 -0.04 +/- 0.10 < 0.18 -0.01 +/- 0.19 < 0.39 -0.09 +/- 0.15 < 0.28 0.5 K-40 1411 +/- 104 1324 +/- 100 1365 +/- 104 Cs-134 -3.0 +/- 2.0 < 3.4 -0.3 +/- 1.7 < 3.1 0.0 +/- 1.7 < 3.0 5.0 Cs-137 -1.2 +/- 2.0 < 3.6 -2.2 +/- 1.9 < 2.6 -0.8 +/- 2.0 < 2.5 5.0 Ba-La-140 -0.9 +/- 2.0 < 1.5 1.3 +/- 1.9 < 3.5 0.5 +/- 1.5 < 1.7 5.0 Other (Co-60) 1.4 +/- 2.2 < 2.8 0.8 +/- 1.9 < 3.2 0.1 +/- 21 < 31 15.0 Collection Date 04-11-18 05-09-18 06-13-18 Lab Code EMI- 1158 EMI- 1735 EMI- 2297 Sr-89 0.4 +/- 0.7 < 0.8 0.2 +/- 0.7 < 0.6 0.6 +/- 0.6 < 0.6 5.0 Sr-90 0.5 +/- 0.3 < 0.5 0.4 +/- 0.3 < 0.5 0.2 +/- 0.3 < 0.5 1.0 1-131 -0.01 +/- 0.13 < 0.24 0.09 +/- 0.25 < 0.48 0.10 +/- 0.14 < 0.24 0.5 K-40 1421 +/- 112 1367 +/- 107 1335 +/- 115 Cs-134 -0.7+/-1.9 < 3.6 -0.5 +/- 1.5 < 2.9 0.3 +/- 1.8 < 3.3 5.0 Cs-137 1.3 +/- 2.0 < 3.3 -0.8 +/- 2.1 < 2.5 1.1 +/- 2.4 < 4.2 5.0 Ba-La-140 -0.6 +/- 1.5 < 1.8 0.3 +/- 1.4 < 2.6 -3.8 +/- 1.8 < 2.4 5.0 Other (Co-60) 1.9 +/- 2.0 < 3.3 -0.9 +/- 2.1 < 2.3 -0.7 +/- 2.5 < 3.7 15.0 3-5

POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L) E-40 Barta MDC MDC MDC Required Collection Date 07-11-18 08-08-18 09-12-18 LLD Lab Code EMI- 2602 EMI- 3192 EMI- 3744 Sr-89 0.0 +/- 0.6 < 0.7 -0.3 +/- 0.7 < 0.7 -0.6 +/- 0.7 < 0.7 5.0 Sr-90 0.3 +/- 0.2 < 0.4 0.5 +/- 0.3 < 0.5 0.6 +/- 0.3 < 0.5 1.0 1-131 0.01 +/- 0.16 < 0.29 0.08 +/- 0.14 < 0.24 0.06 +/- 0.15 < 0.26 0.5 K-40 1482 +/- 116 1370 +/- 116 1361 +/- 110 Cs-134 -0.8 +/- 2.1 < 3.7 0.5 +/- 2.0 < 3.7 0.6 +/- 1.8 < 3.5 5.0 Cs-137 0.5 +/- 2.3 < 4.2 -0.7 +/- 2.2 < 3.3 2.1 +/- 2.1 < 3.6 5.0 Ba-La-140 -2.0 +/- 2.3 < 2.8 -0.3 +/- 1.5 < 1.9 -1.2 +/- 1.5 < 2.6 5.0 Other (Co-60) -0.9 +/-23 < 1.9 -0.6 +/- 2.0 < 1.6 -3.9 +/- 2.8 < 2.1 15.0 Collection Date 10-17-18 11-14-18 12-12-18 Lab Code EMI- 4331 EMI- 4849 EMI- 5275 Sr-89 -0.2 +/- 0.7 < 0.7 0.3 +/- 0.7 < 0.7 0.0 +/- 0.7 < 0.7 5.0 Sr-90 0.6 +/- 0.3 < 0.5 0.4 +/- 0.3 < 0.5 0.4 +/- 0.3 < 0.5 1.0 1-131 0.03 +/- 0.13 < 0.22 0.20 +/- 0.22 < 0.41 -0.09 +/- 0.19 < 0.36 0.5 K-40 1485 +/- 111 1462 +/- 109 1326 +/- 111 Cs-134 -1.9 +/- 1.8 < 3.1 0.0 +/-20 < 4.2 -0.4 +/- 2.1 < 3.7 5.0 Cs-137 -0.8 +/- 2.0 < 2.4 -1.2 +/- 2.3 < 3.0 1.4 +/- 2.4 < 4.0 5.0 Ba-La-140 -0 8 +/- 1. 7 < 17 -2.2 +/- 2.6 < 4.1 -2.4 +/- 1.8 < 3.0 5.0 Other (Co-60) 0.6 +/- 2.0 < 3.1 -0.6 +/- 2.5 < 3.8 -2.1 +/- 2.4 < 2.9 15.0 Sr-89 Annual Mean + s.d. 0.1 +/- 0.4 Sr-90 Annual Mean + s.d. 0.4 +/-0.2 1-131 Annual Mean+ s.d. 0.04 +/-0.09 K-40 Annual Mean+ s.d. 1356 +/- 71 Cs-134 Annual Mean+ s.d. -0.2 +/- 1.0 Cs-137 Annual Mean+ s.d. 0.4 +/- 1.3 Ba-La Annual Mean+ s.d. -0.9 +/- 1.1 Co-60 Annual Mean + s.d. -0.2 +/- 1.2 3-6

POINT BEACH NUCLEAR PLANT Table 4. Radioactivity in Well Water Samples, E-10 Collection: Quarterly Units: pCi/L 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Req. Annual LLD Mean +/-s.d Collection Date 02-01-18 04-11-18 07-17-18 10-17-18 Lab Code E\M/11- 346 E\M/11- 1194 E\M/11- 2760 E\M/11- 4500 Gross Beta 2.9 +/- 1.2 2.7 +/- 1.4 0.7 +/- 1.1 1.1 +/- 0.7 4.0 1.8 +/- 1.1 H-3 -45 +/- 70 -86 +/- 94 27 +/- 74 +/- 70 500 -25.6 +/- 50.1 Sr-89 0.0 +/- 0.3 -0.3 +/- 0.4 -0.3 +/- 0.6 0.2 +/- 0.4 5.0 -0.1 +/- 0.2 Sr-90 0.1 +/- 0.2 0.2 +/- 0.2 0.3 +/- 0.4 -0.1 +/- 0.2 1.0 0.1 +/- 0.2 1-131 0.22 +/- 0.22 -0.01 +/- 0.14 -0.02 +/- 0.18 0.13 +/- 0.17 0.5 0.08 +/- 0.12 Mn-54 0.7 +/- 1.8 2.0 +/- 2.1 0.6 +/- 1.4 0.7 +/- 1.9 10 1.0 +/-0.7 Fe-59 -0.7 +/- 3.2 -3.8 +/- 4.0 -1.5 +/- 2.5 -1.4 +/-3.1 30 -1.9 +/- 1.3 Co-58 0.2 +/- 1.6 -0.7 +/- 1.9 0.0 +/- 1.3 -0.2 +/- 1.7 10 -0.2 +/- 0.4 Co-60 1.4 +/- 2.2 0.5 +/- 2.1 0.8 +/- 1.5 -1.7 +/- 2.2 10 0.3 +/-1.3 Zn-65 0.2 +/- 4.5 -2.7 +/- 4.4 -2.4 +/- 2.4 0.5 +/- 3.6 30 -1.1 +/- 1.7 Zr-Nb-95 -4.7 +/- 2.5 -0.2 +/- 2.1 -0.9 +/- 1.4 -0.3 +/- 2.1 15 -1.5 +/- 2.2 Cs-134 0.4 +/- 2.0 -2.3 +/- 2.1 0.0 +/- 1.4 -0.5 +/- 1.8 10 -0.6 +/- 1.2 Cs-137 1.1 +/- 2.0 0.9 +/- 2.1 -0.6 +/- 1.6 0.9 +/- 2.0 10 0.6 +/- 0.8 Ba-La-140 1.9 +/- 1.8 -1.6 +/-2.5 -0.1 +/- 1.3 -2.9 +/- 2.4 15 -0.7 +/- 2.0 Other (Ru-103) 1.4 +/- 1.9 -1.5 +/- 2.0 -0.5 +/- 1.3 -1.1 +/- 1.6 30 -0.4 +/- 1.3 MDC Data Collection Date 02-01-18 04-11-18 07-17-18 10-17-18 Lab Code E\M/11- 346 E\M/11- 1194 E\M/11- 2760 E\M/11- 4500 Gross Beta < 1.9 < 1.9 < 2.0 < 1.2 4.0 < 1.7 H-3 < 154 < 161 < 156 < 150 500 < 155.3 Sr-89 < 0.5 < 0.5 < 0.5 < 0.6 5.0 < 0.5 Sr-90 < 0.4 < 0.4 < 0.8 < 0.4 1.0 < 0.5 i-131 < 0.41 < 0.26 < 0.33 < 0.30 0.5 < 0.32 Mn-54 < 3.1 < 3.4 < 2.5 < 3.1 10 < 3.0 Fe-59 < 2.2 < 4.1 < 3.1 < 5.3 30 < 3.7 Co-58 < 2.5 < 2.7 < 2.0 < 2.3 10 < 2.4 Co-60 < 3.8 < 2.3 < 2.3 < 2.3 10 < 2.7 Zn-65 < 7.4 < 5.9 < 1.7 < 7.0 30 < 5.5 Zr-Nb-95 < 4.0 < 3.4 < 1.4 < 3.7 15 < 3.1 Cs-134 < 3.7 < 3.8 < 1.6 < 3.5 10 < 3.1 Cs-137 < 3.0 < 4.0 < 2.2 < 3.4 10 < 3.1 Ba-La-140 < 2.3 < 2.8 < 1.7 < 4.2 15 < 2.8 Other (Ru-1 03) < 3.2 < 2.8 < 1.7 < 2.8 30 < 2.6 4-1

POINT BEACH Table 5. Lake water, analyses for gross beta, iodine-131 and gamma emitting isotopes. Location: E-01 (Meteorological Tower) Collection: Monthly composites Units: pCi/L MDC MDC MDC MDC Lab Code NSa ELW- 513 ELW- 915 ELW- 1190 Date Collected 01-11-18 02-14-18 03-14-18 04-11-18 Req. LLD Gross beta 1.9 +/- 0.6 < 0.9 2.0 +/- 0.6 < 0.9 1.6 +/- 0.6 < 0.9 4.0 1-131 0.13 +/- 0.17 < 0.29 0.06 +/- 0.19 < 0.34 0.03 +/- 0.18 < 0.32 0.5 Be-7 -10.8 +/- 17.4 < 21.4 -2.1 +/- 17.0 < 23.9 -6.4 +/- 10.2 < 19.1 Mn-54 0.2 +/- 1.8 < 2.3 0.5 +/- 1.6 < 2.7 0.6 +/- 1.3 < 2.3 10 Fe-59 -4.1 +/- 3.0 < 3.5 0.2 +/- 3.3 < 5.7 -1.6 +/- 2.3 < 3.6 30 Co-58 -1.3 +/- 1.6 < 2.0 0.2 +/- 1.7 < 2.7 -1.0 +/- 1.2 < 1.7 10 Co-60 -1.4 +/- 1.6 < 1.9 -0.2 +/- 2.0 < 2.3 -0.1 +/- 1.1 < 1.2 10 Zn-65 -1.4 +/- 3.4 < 3.6 -4.6 +/- 3.2 < 1.5 0.3 +/- 2.6 < 4.4 30 Zr-Nb-95 -0.8 +/- 1.8 < 1.6 -1.1 +/- 1.9 < 3.1 -1.2+/-1.4 < 1.6 15 Cs-134 2.0 +/- 1.8 < 3.9 -0.6 +/- 2.0 < 3.4 -0.1 +/- 1.5 < 2.7 10 Cs-137 -0.8 +/- 1.6 < 1.8 0.4 +/- 1.8 < 2.6 00 +/- 1.6 < 3.0 10 Ba-La-140 -1.3 +/- 1.5 < 1.3 2.2 +/- 1.5 < 2.6 -0.2 +/- 1.8 < 4.7 15 Other (Ru-103) 0.1 +/- 2.1 < 3.4 1.0 +/- 1.7 < 3.6 -0.8 +/- 1.3 < 3.5 30 Lab Code ELW- 1782 ELW- 2315 ELW- 2704 ELW- 3228 Date Collected 05-09-18 06-13-18 07-11-18 08-09-18 Gross beta 1.3 +/- 0.5 < 0.9 0.9 +/- 0.5 < 0.9 0.5 +/- 0.5 < 0.8 0.9 +/- 0.5 < 0.9 4.0 1-131 -0.03 +/- 0.16 < 0.29 0.13 +/- 0.23 < 0.46 0.12 +/- 0.16 < 0.28 -0.13 +/- 0.19 < 0.35 0.5 Be-7 -1.9 +/- 12.7 < 38.4 -5.4 +/- 23.2 < 45.3 -2.4 +/- 11.3 < 23.8 7.7 +/- 13.0 < 37.6 Mn-54 1.0 +/- 1.6 < 3.3 1.3 +/- 2.7 < 3.4 0.3 +/- 1.2 < 1.9 -0.6 +/- 1.5 < 2.1 10 Fe-59 -2.4 +/- 3.0 < 5.8 -1.0+/-4.1 < 7.2 -0.5 +/- 2.6 < 3.7 -0.6 +/- 3.3 < 7.7 30 Co-58 0.8 +/- 1.4 < 3.3 -3.5 +/- 2.2 < 2.5 0.2 +/- 1.5 < 2.7 1.5 +/- 1.8 < 3.7 10 Co-60 1.2 +/- 1.7 < 1.9 1.3 +/- 2.8 < 3.9 0.4 +/- 1.4 < 1.7 -1.1 +/- 1.5 < 1.2 10 Zn-65 0.4 +/- 2.3 < 2.3 -1.4 +/- 5.8 < 9.2 0.6 +/- 2.6 < 3.4 1.4 +/- 3.4 < 4.9 30 Zr-Nb-95 -0.2 +/- 1.8 < 6.1 -0.3 +/- 2.6 < 5.3 -0.4 +/- 1.3 < 2.3 -1.1 +/- 1.6 < 3.5 15 Cs-134 -0.4 +/- 1.6 < 3.0 -1.4 +/- 2.4 < 4.8 0.5 +/- 1.3 < 2.5 0.8 +/- 1.6 < 3.2 10 Cs-137 -0.3 +/- 1.5 < 2.2 -3.1 +/- 2.8 < 3.1 -1.9 +/- 1.5 < 1.8 -0.2 +/- 1.8 < 2.8 10 Ba-La-140 -2.7 +/- 1.6 < 8.4 2.0 +/- 3.0 < 6.8 0.6 +/- 1.0 < 2.5 -0.6 +/- 2.1 < 3.8 15 Other (Ru-1 03) 1.3 +/- 1.5 < 5.1 0.1 +/- 2.5 < 5.0 -0.3 +/- 1.2 < 2.4 1.0 +/- 1.7 < 4.0 30 Lab Code ELW- 3758 ELW- 4496 ELW- 4875 ELW- 5269 Date Collected 09-11-18 10-17-18 11-14-18 12-11-18 Gross beta 1.6 +/- 0.6 < 0.9 2.0 +/- 0.6 < 0.9 1.5 +/- 0.6 < 0.9 1.2 +/- 0.6 < 0.9 4.0 1-131 -0.04 +/- 0.16 < 0.30 -0.09 +/- 0.21 < 0.38 -0.06 +/- 0.15 < 0.27 -0.08 +/- 0.18 < 0.33 0.5 Be-7 -1.0 +/- 4.9 < 13.6 -12.5 +/- 21.3 < 30.6 -4.9 +/- 11.6 < 26.7 20.1 +/- 27.5 < 57.8 Mn-54 0.5 +/- 0.6 < 1.2 -0.4 +/- 2.2 < 4.1 0.6 +/- 1.3 < 1.9 -2.3 +/- 3.3 < 4.6 10 Fe-59 1.0 +/- 10 < 3.1 -1.1 +/-4.0 < 5.7 -5.5 +/- 2.5 < 3.7 -7.4 +/- 5.4 < 6.5 30 Co-58 0.6 +/- 0.6 < 1.2 -0.5 +/- 2.1 < 2.5 -0.1 +/- 1.3 < 1.6 0.3 +/- 2.7 < 3.3 10 Co-60 0.1 +/- 0.7 < 1.2 -1.5 +/- 2.1 < 2.0 0.5 +/- 1.7 < 1.5 -2.0 +/- 3.8 < 3.7 10 Zn-65 0.9 +/- 1.1 < 2.0 -0.6 +/- 4.6 < 6.9 3.1 +/- 2.7 < 1.9 -10.2 +/- 7.4 < 10.6 30 Zr-Nb-95 0.8 +/- 0.6 < 2.3 -2.0 +/- 2.0 < 4.9 -1.5+/-1.6 < 3.2 -3.7 +/- 3.9 < 3.8 15 Cs-134 -0.2 +/- 0.6 < 1.3 -0.4 +/- 1.9 < 3.3 0.2 +/- 1.5 < 2.7 -0.3 +/- 3.2 < 6.0 10 Cs-137 0.0 +/- 0.7 < 1.1 0.4 +/- 2.0 < 2.8 -0.3 +/- 1.8 < 2.2 -1.0 +/- 3.1 < 4.8 10 Ba-La-140 -3.2 +/- 0.7 < 4.3 -1.5 +/- 1.6 < 3.5 -1.9+/-1.4 < 4.3 -2.8 +/- 3.7 < 4.7 15 Other (Ru-103) 0.1 +/- 0.6 < 1.8 -1.5 +/- 2.4 < 4.7 -0.8 +/- 1.5 < 3.2 -3.7 +/- 3.0 < 3.1 30 ""NS" =No sample; see Table 2.0. Listing of Missed Samples. 5-1

POINT BEACH Table 5. Lake water, analyses for gross beta. iodine-131 and gamma emitting isotopes. Location: E-05 (Two Creeks Park} Collection: Monthly composites Units: pCi/L MDC MDC MDC MDC 3 Lab Code ELW- 106 NS ELW- 916 ELW- 1191 Date Collected 01-11-18 02-14-18 03-15-18 04-11-18 Req. LLD Gross beta 0.9 +/- 0.5 < 0.8 1.2 +/- 0.5 < 0.8 1.2 +/- 0.5 < 0.8 4.0 1-131 -0.07 +/- 0.18 < 0.37 0.00 +/- 0.12 < 0.18 0 17 +/- 0.19 < 0.33 0.5 Be-7 1.1 +/- 12.7 < 20.7 2.6 +/- 12.9 < 29.9 -5.1 +/- 120 < 29.8 Mn-54 0.0 +/- 1.9 < 3.5 0.5 +/- 1.6 < 1.8 -0.7 +/- 1.4 < 2.0 10 Fe-59 -1.1 +/- 2.9 < 4.1 -2.5 +/- 2.9 < 2.5 0.2 +/- 3.1 < 6.4 30 Co-58 -2.9 +/- 1.5 < 1.0 0.1 +/- 1.3 < 1.8 0.2 +/- 1.4 < 2.4 10 Co-60 -0.3 +/- 1.5 < 2.2 -0.1 +/- 1.6 < 2.4 0.2 +/- 1.4 < 1.7 10 Zn-65 -2.1 +/- 3.2 < 3.0 -0.9 +/- 2.9 < 3.1 -3.5 +/- 2.8 < 1.7 30 Zr-Nb-95 -2.5 +/- 1.9 < 2.8 3.0 +/- 1.6 < 3.0 -1.8 +/- 1.4 < 2.5 15 Cs-134 0.5 +/- 1.7 < 2.6 -0.5 +/- 1.5 < 3.3 -0.1 +/- 1.6 < 2.9 10 Cs-137 1.9 +/- 2.1 < 3.9 0.6 +/- 1.8 < 28 0.8 +/- 1.7 < 2.8 10 Ba-La-140 0.3 +/- 2.2 < 5.9 -0.4 +/- 1.7 < 2.7 3.6+/- 1.7 < 6.0 15 Other (Ru-103} -1.1 +/- 1.7 < 3.9 0.4 +/- 1.4 < 3.1 2.3 +/- 1.3 < 3.7 30 Lab Code ELW- 1783 ELW- 2316 ELW- 2658 ELW- 3229 Date Collected 05-11-18 06-13-18 07-12-18 08-09-18 Gross beta 2.0 +/- 1.0 < 1.6 1.2 +/- 0.5 < 0.8 1.5 +/- 0.6 < 0.9 1.1 +/- 0.5 < 0.8 4.0 1-131 0.06 +/- 0.14 < 0.24 -0.01 +/- 0.21 < 0.45 0.15 +/- 0.24 < 0.48 0.14 +/- 0.18 < 0.31 0.5 Be-7 5.2 +/- 11.8 < 24.7 -26.1 +/- 22.8 < 39.0 -6.2 +/- 23.8 < 36.7 6.7 +/- 13.4 < 37.1 Mn-54 0.9 +/- 1.5 < 2.5 1.9 +/- 3.0 < 5.0 1.6 +/- 2.9 < 4.4 1.6+/-1.6 < 2.8 10 Fe-59 0.1 +/- 3.0 < 4.6 -3.1 +/- 4.9 < 10.7 -5.5 +/- 5.2 < 4.2 -0.2 +/- 2.8 < 6.3 30 Co-58 1.1 +/- 1.9 < 3.4 0 0 +/- 2.4 < 3.5 -3.5 +/- 2.7 < 3.1 -0.8 +/- 1.6 < 1.9 10 Co-60 -0.8 +/- 1.7 < 1.9 -1.9 +/- 3.0 < 4.3 -0.1 +/- 2.9 < 3.9 1.6 +/- 1.8 < 2.0 10 Zn-65 -4.1 +/- 3.2 < 3.1 -8.8 +/- 6.3 <88 -9.3 +/- 6.8 < 8.3 -1.7 +/- 3.0 < 3.0 30 Zr-Nb-95 -0.3 +/- 1. 7 < 4.2 -4.2 +/- 3.0 < 5.0 -0.6 +/- 3.1 < 6.6 0.7 +/- 2.0 < 4.6 15 Cs-134 -0.1 +/- 1.8 < 3.4 -1.3 +/- 2.5 < 5.1 -1.5 +/- 2.9 < 5.3 0.9+/-1.7 < 3.0 10 Cs-137 1.7 +/- 1.8 < 3.0 1.1 +/- 3.2 < 5.3 -0.5 +/- 3.0 < 5.1 1.5 +/- 1.9 < 2.9 10 Ba-La-140 2.0 +/- 2.1 < 12.7 -8.1 +/- 3.6 < 6.6 2.1 +/- 3.5 < 6.5 -1.0 +/- 1. 7 < 7.0 15 Other (Ru-103} -1.8 +/- 1.4 < 2.4 -0.9 +/- 2.6 < 4.3 -0.2 +/- 2.7 < 4.4 -0.3 +/- 1.7 < 4.0 30 Lab Code ELW- 3759 ELW- 4497 ELW, 4876 ELW- 5270 Date Collected 09-11-18 10-19-18 11-14-18 12-11-18 Gross beta 1.5 +/- 0.6 < 0.8 1.6 +/- 0.6 < 0.9 1.1 +/- 0.5 < 0.8 1.5 +/- 0.6 < 0.9 4.0 1-131 0.01 +/- 0.23 < 0.46 -0.10 +/- 0.17 < 0.31 0.14 +/- 0.20 < 0.38 0.08 +/- 0.17 < 0.31 0.5 Be-7 4.1 +/- 5.2 < 16.3 7.6 +/- 14.5 < 36.1 -19.9 .!: 15.3 < 31.5 -10.8 +/- 20.1 < 24.7 Mn-54 0.2 +/- 0.6 < 1.2 -0.2 +/- 1.5 < 1.8 0.3 +/- 2.0 < 4.0 -0.3 +/- 1.9 < 3.1 10 Fe-59 0.1 +/- 1.1 < 2.1 -1.2 +/- 3.1 < 6.7 0.4 +/- 3.2 < 4.6 1.9 +/- 4.3 < 5.3 30 Co-58 -0.3 +/- 0.6 < 0.8 1.2 +/- 1.7 < 3.2 -1.7 +/- 2.0 < 4.1 -1.6 +/- 2.0 < 1.8 10 Co-60 0.4 +/- 0.7 < 1.3 -0.5 +/- 2.0 < 3.1 1.9 +/- 2.0 < 2.8 0.2 +/- 1.8 < 2.3 10 Zn-65 -0.7 +/- 1.2 < 2.2 -1.1 +/- 3.5 < 3.7 -1.6 +/- 4.4 < 7.5 -2.5 +/- 5.0 < 3.8 30 Zr-Nb-95 -0.1 +/- 0.7 < 2.4 -2.3 +/- 1.8 < 2.5 -4.0 +/- 2.4 < 6.6 -1.2 +/- 1.8 < 2.5 15 Cs-134 0.2 +/- 0.6 < 1.2 -0.9 +/- 1.7 < 3.3 -1.0 +/- 2.1 < 3.7 -1.1 +/- 2.1 < 4.5 10 Cs-137 0.2 +/- 0.7 < 1.3 -0.6 +/- 2.1 < 3.6 -2.4 +/- 2.1 < 3.4 0.8 +/- 1.8 < 2.5 10 Ba-La-140 0.1 +/- 0. 7 < 4.0 -2.8 +/- 1. 9 < 6.9 5.6 +/- 1.6 < 6.2 -1.0 +/- 2.5 < 3.3 15 Other (Ru-103} -0.1 +/- 0.6 < 1.4 -0.7 +/- 1.6 < 4.0 0.6 +/- 1.9 < 5.8 -1.9 +/- 2.3 < 3.4 30 3

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

5-2

POINT BEACH Table 5. Lake water, analyses for gross beta, iodine-131 and gamma emitting isotopes. Location: E-06 (Coast Guard Station) Collection: Monthly composites Units: pCi/L MDC MDC MDC MDC Lab Code NSa NSa ELW- 917 ELW- 1192 Date Collected 01-11-18 02-14-18 03-15-18 04-11-18 Req. LLD Gross beta 1.1 +/- 0.6 < 0.9 0.7 +/- 0.5 < 0.9 4.0 1-131 0.05 +/- 0.13 < 0.19 -0.14 +/- 0.17 < 0.32 0.5 Be-7 6.4 +/- 16.7 < 22.8 -6.2 +/- 12.3 < 30.2 Mn-54 -0.1 +/- 1.7 < 2.8 1.2 +/- 1.6 < 3.1 10 Fe-59 -0.3 +/- 3.0 < 5.0 -1.3 +/- 4.0 < 5.8 30 Co-58 -1.1 +/- 1.7 < 1.7 2.6 +/- 1.6 < 3.0 10 Co-60 0.4 +/- 1.4 < 2.0 -0.1 +/- 1.7 < 2.0 10 Zn-65 0.5 +/- 3.1 < 4.2 1.3 +/- 2.7 < 2.3 30 Zr-Nb-95 -0.7 +/- 2.0 < 3.2 -1.5+/- 1.6 < 3.8 15 Cs-134 0.0 +/- 1.7 < 3.2 -0.2 +/- 1.7 < 3.1 10 Cs-137 0.7 +/- 2.0 < 3.4 0.7 +/- 1.9 < 3.2 10 Ba-La-140 0.7 +/- 1.7 < 3.1 -3.5 +/- 2.3 < 4.9 15 Other (Ru-103) 0.1 +/- 1.9 < 3.7 0.7 +/- 1.7 < 5.2 30 Lab Code ELW- 1784 ELW- 2317 ELW- 2659 ELW- 3230 Date Collected 05-11-18 06-13-18 07-12-18 08-09-18 Gross beta 0.6 +/- 0.5 < 0.9 1 2 +/- 0.5 < 0.9 1.2 +/- 0.6 < 0.9 1.2 +/- 0.5 < 0.9 4.0 1-131 -0.01 +/-0.13 < 0.24 0.01 +/- 0.12 < 0.21 0.14 +/- 0.18 < 0.34 0.13 +/- 0.20 < 0.35 0.5 Be-7 -5.1 +/- 13.2 < 35.3 21.0 +/- 19.4 < 39.2 18.0 +/- 21.6 < 41.3 1.0 +/- 19.5 < 47.1 Mn-54 0.3 +/- 1.4 < 2.0 0.5 +/- 2.0 < 3.3 3.4 +/- 2.4 < 3.7 0.7 +/- 1.8 < 3.1 10 Fe-59 -1.4 +/- 3.0 < 2.9 0.9 +/- 3.8 < 8.5 0.6 +/- 4.9 < 9.1 5.5 +/- 3.8 < 7.6 30 Co-58 -0.1 +/- 1.6 < 2.0 0.4 +/- 2.0 < 3.2 0.8 +/- 2.1 < 3.2 -1.1 +/- 1.5 < 1.3 10 Co-60 ~0.8 +/- 1.5 < 2.2 -0.4 +/- 2.3 < 2.6 0.3 +/- 2.4 < 3.0 -1.5 +/- 1.5 < 1.5 10 Zn-65 1.2 +/- 3.2 < 3.8 3.9 +/- 3.4 < 3.5 0.9 +/- 4.4 < 5.7 -2.4 +/- 4.0 < 4.6 30 Zr-Nb-95 -2.5 +/- 1.5 < 2.3 1.3 +/- 1.8 < 4.2 -1.5 +/- 2.4 < 2.6 1.0+/-1.9 < 4.3 15 Cs-134 -0.9 +/- 1.7 < 3.1 -0.5 +/- 1.8 < 3.4 1.4 +/- 2.3 < 4.8 -0.4 +/- 2.0 < 4.0 10 Cs-137 0.8 +/- 2.0 < 3.2 0.4+/- 1.9 < 3.1 -1.4 +/- 2.8 < 2.7 0.1 +/- 1.7 < 2.8 10 Ba-La-140 5.2 +/- 1.5 < 10.3 -3.6 +/- 2.1 < 4.9 -0.8 +/- 2.7 < 3.5 1.0+/-1.9 < 7.0 15 Other (Ru-103) 0.7 +/- 1.5 < 4.7 -0.5 +/- 2.0 < 2.9 -1.3 +/- 2.4 < 3.4 -1.9 +/- 2.1 < 3.2 30 Lab Code ELW- 3760 ELW- 4498 ELW- 4877 ELW- 5271 Date Collected 09-11-18 10-19-18 11-14-18 12-11-18 Gross beta 1.4 +/- 0.6 < 0.9 1.7 +/- 0.6 < 0.9 1.1 +/- 0.5 < 0.9 1.9 +/- 0.6 < 0.9 4.0 1-131 0.12 +/- 0.16 < 0.28 -0.01 +/- 0.15 < 0.27 0.10 +/- 0.16 < 0.28 -0 06 +/- 0.15 < 0.27 0.5 Be-7 -3.8 +/- 8.3 < 22.7 16.5 +/- 17.2 < 40.7 10.1 +/- 13.8 < 43.4 4.1 +/- 14.4 < 33.8 Mn-54 0.6 +/- 0.9 < 1.7 0.6 +/- 1.8 < 2.8 -0.4 +/- 1.7 < 2.3 0.2 +/- 1.7 < 3.1 10 Fe-59 -0.9 +/- 1.8 < 3.1 -0.2 +/- 3.7 < 6.0 0.1 +/- 3.3 <58 -2.1 +/- 3.1 < 4.4 30 Co-58 1.2 +/- 0.8 < 2.0 0.8 +/- 1.9 < 3.8 -3.3 +/- 1.9 < 1.2 1.6 +/- 1.5 < 2.5 10 Co-60 1.3 +/- 1.0 < 1.7 0.6 +/- 2.0 < 3.2 0.1 +/- 1.9 < 2.2 0.2 +/- 1.9 < 1.8 10 Zn-65 1.0+/-1.7 < 2.7 -1.9 +/- 4.3 < 5.5 0.6 +/- 3.2 < 5.4 -1.6 +/- 3.0 < 2.8 30 Zr-Nb-95 -0.3 +/- 0.8 < 2.8 0.0 +/- 2.1 < 5.1 -3.8 +/- 2.0 < 4.8 -0.4 +/- 2.0 < 3.3 15 Cs-134 0.0 +/- 0.9 < 1.8 -0.3 +/- 1.7 < 3.7 -0.5 +/- 1.8 < 3.4 -1.1 +/- 1.8 < 3.2 10 Cs-137 0.6 +/- 1.0 < 1.9 0.1 +/- 2.4 < 2.3 -0.2 +/- 2.1 < 3.7 -1.6 +/- 2.0 < 2.4 10 Ba-La-140 -6.5 +/- 1.1 < 6.8 1.1 +/- 1.8 < 7.3 -1.5 +/- 2.1 < 12.8 -2.1 +/- 1.9 < 2.2 15 Other (Ru-103) -1.1 +/- 0.9 < 2.0 -0.1 +/- 2.0 < 4.3 2.2 +/- 1.7 < 5.2 0.4+/-1.9 < 4.1 30 a"NS" = No sample; see Table 2.0, Listing of Missed Samples. 5-3

POINT BEACH Table 5. Lake water, analyses for gross beta, iodine-131 and gamma emitting isotopes. Location: E-33 (Kewaunee) Collection: Monthly composites Units: pCi/L MDC MDC MDC MDC Lab Code ELW- 107 NSa ELW~ 918 ELW- 1193 Date Collected 01-11-18 02-14-18 03-15-18 04-11-18 Req. LLD Gross beta 1.3 +/- 0.6 < 0.9 1.9 +/- 0.6 < 0.8 0.6 +/- 0.5 < 0.8 4.0 1-131 0.15 +/- 0.20 < 0.39 -0.07 +/- 0.12 < 0.17 -0.02 +/- 0.15 < 0.26 0.5 Be-7 -3.9 +/- 13.0 < 23.4 -0.7 +/- 14.0 < 29.6 -9.5 +/- 12.2 < 25.7 Mn-54 -1.0 +/- 1.5 < 2.5 -1.3 +/- 1.7 < 1.9 0.3 +/- 1.5 < 2.2 10 Fe-59 -1.4 +/- 2.6 < 5.1 0.6 +/- 2.7 < 3.6 0.8 +/- 2.5 < 3.4 30 Co-58 -0.5 +/- 1.4 < 2.2 1.4 +/- 1.4 < 2.8 1.2 +/- 1.6 < 2.9 10 Co-60 0.3 +/- 1.4 < 1.9 1.1 +/- 2.0 < 2.5 -0.5 +/- 1.3 < 1.2 10 Zn-65 -0.1 +/- 3.3 < 5.3 0.2 +/- 3.0 < 4.6 0.5 +/- 3.1 < 4.3 30 Zr-Nb-95 -0.1 +/- 1.8 < 2.6 0.2 +/- 1.3 < 2.1 1.8 +/- 1.8 < 4.8 15 Cs-134 -0.6 +/- 1.6 < 3.0 -1.1 +/- 1.4 < 2.3 -1.0 +/- 1.6 < 2.7 10 Cs-137 1.1 +/- 2.0 < 3.7 -0.8 +/- 1.7 < 1.8 1.0 +/- 1.8 < 2.8 10 Ba-La-140 -1.7 +/- 1.8 < 3.3 -1.8 +/- 1.7 < 2.6 -8.1 +/- 2.1 < 6.8 15 Other (Ru-103) 0.4 +/- 1.5 < 2.4 -0.5 +/- 1.4 < 2.9 -0.3 +/- 1.6 < 3.8 30 Lab Code ELW- 1785 ELW- 2318 ELW- 2660 ELW- 3231 Date Collected 05-11-18 06-13-18 07-12-18 08-09-18 Gross beta 2.3 +/- 1.0 < 1.6 1.1 +/-0.5 < 0.8 1.2 +/- 0.5 < 0.9 1.4 +/- 0.5 < 0.8 4.0 1-131 -0.08 +/- 0.14 < 0.25 0.08 +/- 0.13 < 0.22 0.08 +/- 0.24 < 0.50 0.13 +/- 0.20 < 0.34 0.5 Be-7 10.1 +/- 17.7 < 45.6 19.6 +/- 14.5 < 40.5 -5.4 +/- 11.7 < 27.4 8.3 +/- 20.2 < 46.7 Mn-54 0.8 +/- 1.9 < 3.3 -1.6 +/- 1.5 < 2.1 -0.4 +/- 1.4 < 1.2 -0.5 +/- 2.9 < 4.5 10 Fe-59 2.7 +/- 3.5 < 7.2 -2.8 +/- 2.6 < 2.7 -0.6 +/- 2.7 < 3.9 -3.5 +/- 4.3 < 6.9 30 Co-58 1.2 +/- 1.6 < 4.0 1.2 +/- 1.7 < 4.0 -0.2 +/- 1.1 < 1.1 1.3 +/- 2.2 < 4.8 10 Co-60 -0.6 +/- 1.5 < 1.4 0.4 +/- 1.7 < 1.7 -0.5 +/- 1.6 < 1.3 -0.6 +/- 2.5 < 2.8 10 Zn-65 0.4 +/- 3.8 < 3.3 -2.2 +/- 3.5 < 3.9 0.9 +/- 2.7 < 3.8 -2.5 +/- 5.4 < 6.1 30 Zr-Nb-95 -1.1 +/- 1.9 < 3.5 -1.8 +/- 1.6 < 3.1 -1.9 +/- 1.8 < 2.8 0.4 +/- 2.4 < 5.7 15 Cs-134 0.8 +/- 1.7 < 3.6 0.4 +/- 1.7 < 3.0 0.2 +/- 1.5 < 1.9 1.9 +/- 2.2 < 4.3 10 Cs-137 -0.1 +/- 2.0 < 3.0 -1.0 +/- 2.0 < 2.4 1.4 +/- 1. 7 < 2.8 0.1 +/- 2.8 < 3.9 10 Ba-La-140 2.2+/-2.1 < 10.3 2.7+/-1.8 < 8.6 0.6 +/- 1.9 < 2.0 -4.0 +/- 3.2 < 8.1 15 Other (Ru-103} -0.9 +/- 1.9 < 5.8 -0.5+/- 1.5 < 2.5 1.3 +/- 1.4 < 3.0 -0.1 +/- 2.2 < 5.0 30 Lab Code ELW- 3761 ELW- 4499 ELW- 4878 ELW- 5272 Date Collected 09-12-18 10-19-18 11-14-18 12-11-18 Gross beta 1.8 +/- 0.6 < 0.8 0.8 +/- 0.5 < 0.9 0.8 +/- 0.5 < 0.9 0.8 +/- 0.5 < 0.8 4.0 1-131 0.02 +/- 0.14 < 0.24 0.11 +/- 0.16 < 0.29 0.13+/-0.15 < 0.26 -0.07 +/- 0.14 < 0.27 0.5 Be-7 -1.3 +/- 6.2 < 15.6 6.0 +/- 12.2 < 31.2 -6.6 +/- 20.5 < 31.6 -9.8 +/- 14.4 < 17.8 Mn-54 -0.4 +/- 0.6 < 1.2 -0.5 +/- 1.6 < 2.3 0.2 +/- 1.9 < 3.0 02 +/- 1.8 < 2.6 10 Fe-59 -0.6 +/- 1.3 < 2.0 -1.2 +/- 2.9 < 5.7 -3.9 +/- 4.3 < 8.9 -1.2 +/- 2.5 < 4.2 30 Co-58 0.0 +/- 0.6 < 1.6 0.8 +/- 1.7 < 2.7 0.2 +/- 2.0 < 3.3 0.5 +/- 1.9 < 2.7 10 Co-60 0.8 +/- 0.7 < 1.2 0.2 +/- 1.8 < 2.1 1.4 +/- 2.0 < 2.1 1.0 +/- 1.9 < 2.4 10 Zn-65 0.4 +/- 1.3 < 2.0 -1.4 +/- 3.2 < 3.7 -0.4 +/- 4.4 < 6.8 -1.4 +/- 3.3 < 3.5 30 Zr-Nb-95 -1.3 +/- 0.7 < 2.3 1.7+/-1.8 < 4.4 -3.9 +/-20 < 4.9 0.3 +/- 1.8 < 3.3 15 Cs-134 -0.1 +/- 0.7 < 1.3 -0.9 +/- 1.8 < 3.0 0.2 +/- 2.1 < 4.3 -0.5 +/- 1.? < 2.9 10 Cs-137 -0.1 +/- 0.7 < 1.4 0.8 +/- 1.7 < 3.6 0.8 +/- 2.5 < 5.0 2.2 +/- 1.9 < 3.3 10 Ba-La-140 -0.4 +/- 0.7 < 3.4 -5.3 +/- 2.0 < 4.4 -2.9 +/- 2.2 < 7.6 1.5 +/- 1.9 < 5.8 15 Other (Ru-103) -0.8 +/- 0.7 < 1.6 -0.5 +/- 1.8 < 48 0.1 +/- 2.3 < 5.5 -0.3 +/- 1.6 < 3.6 30 3

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

Annual Annual A II locations Mean +/-S.d. Mean +/- s.d. Mean +/-S.d. Gross Beta 1.3 +/- 0.4 1-131 0.03 +/- 0.09 Co-58 0.0 +/- 1.4 Cs-134 -0.2 +/- 0.8 Be-7 0.2 +/- 10.2 Co-60 0.0 +/- 0.9 Cs-137 0.0 +/- 1.1 Mn-54 0.2 +/- 1.0 Zn-65 -1.2 +/- 2.9 Ba-La-140 -0.9 +/- 3.0 Fe-59 -1.0 +/- 2.2 Zr-Nb-95 -0.9 +/- 1.6 Ru-103 -0.2 +/- 1.1 5-4

POINT BEACH NUCLEAR PLANT Table 6. Lake water, analyses for tritium. strontium-89 and strontium-90. Collection: Quarterly composites of weekly grab samples Units: pCi/L Location E-01 (Meteorolo~ical Tower) Period 1st Qtr. MDC 2nd Qtr. MDC 3rd Qtr. MDC 4th Qtr. MDC Lab Code ELW- 926 ELW- 2336 ELW- 3834 ELW- 5314 H-3 129 +/- 90 < 160 51 +/- 82 < 160 46 +/- 78 < 152 36 +/-75 < 157 Sr-89 0.55 +/- 0.68 < 0.86 -0.07 +/- 0.46 < 0.57 0.17 +/- 0.66 < 0.81 0.25 +/- 0.63 < 0.73 Sr-90 0.00 +/- 0.21 < 0.46 0.22 +/- 0.24 < 0.47 0.16 +/-0.27 < 0.54 0.23 +/- 0.26 < 0.51 Location E-05 (Two Creeks Park) Period 1st Qtr. 2nd Qtr. 3nd Qtr. 4th Qtr. Lab Code ELW- 927 ELW- 2337 ELW- 3835 ELW- 5315 H-3 123 +/- 90 < 160 21 +/-80 < 160 124 +/- 82 < 152 11 +/- 73 < 157 Sr-89 0.38 +/- 0.82 < 1.03 0.05 +/- 0.51 < 0.65 -0.24 +/- 0.71 < 0.86 027 +/- 0.62 < 0.79 Sr-90 0.13+/-0.26 < 0 53 0.18 +/- 0.26 < 0.52 0.36 +/- 0.30 < 0.56 0.17 +/-0.26 < 0.52 Location E-06 (Coast Guard Station~ Period 1st Qtr. 2nd Qtr. 3nd Qtr. 4th Qtr. Lab Code ELW- 928 ELW- 2338 ELW- 3836 ELW- 5316 H-3 77 +/-88 < 160 -5 +/- 79 < 160 46 +/- 78 < 152 -23 +/- 71 < 157 Sr-89 0.03 +/- 0.78 < 0.93 -0.21 +/- 0.45 < 0.51 -0.14 +/- 0.60 < 0.71 0.04 +/- 0.57 < 0.69 Sr-90 0.23 +/- 0.26 < 0.50 0.26 +/- 0.31 < 0.59 0.28 +/- 026 < 0.48 0.23 +/- 0.25 < 0.47 Location E-33 (Kewaunee) Period 1st Qtr. 2nd Qtr. 3nd Qtr. 4thQtr. Lab Code ELW- 929 ELW- 2339 ELW- 3837 ELW- 5317 a H-3 31129 +/- 527 < 160 377 +/- 82 < 160 73 +/- 80 < 152 -21 +/- 71 < 157 Sr-89 -0.16 +/- 0.70 < 0.84 0 50+/- 0.57 < 0.71 0.25 +/- 0.64 < 0 75 0.09 +/- 0.69 < 0.81 Sr-90 0.23 +/- 0.23 < 0.44 0.28 +/-0.23 < 0.42 0.27 +/- 0.26 < 0.48 0.27 +/- 0.29 < 0.55 a Tritium repeated with a result of 31056+/-522 pCi/l. March sample analysis at E-05 and E-33 requested by station: March result at E-05 = 353+/-91 pCi/L; E-33 result =58778+/-715 pCi/L. Tritium Annual Mean +/- s.d. 2012 +/-7765 Sr-89 Annual Mean +/- s.d. 0.11 +/-0.24 Sr-90 Annual Mean +/- s.d. 0.22 +/-0.08 6-1

POINT BEACH NUCLEAR PLANT Table 7. Fish, analyses for gamma emitt1ng isotopes Location: E-13 Collection: Quarterly Units: pCi/g wet Sample Description and Concentration Req. MDC MDC MDC LLD Collection Date 01-12-18 01-14-18 02-05-18 Lab Code EF- 1018 EF- 1019 EF- 1020 Type Lake Herring Salmon Yellow Perch K-40 3.85 +/- 0.50 2.86 +/- 0.31 2.61 +/- 0.34 Mn-54 0.013 +/- 0.011 < 0027 0.005 +/- 0.007 < 0 017 -0.001 +/- 0.007 < 0.015 0.13 Fe-59 -0 039 +/- 0.022 < 0.174 -0.014 +/- 0.013 < 0 071 -0.033 +/- 0.015 < 0.062 0.26 Co-58 0.010 +/- 0.012 < 0.037 0.018 +/- 0.007 < 0.034 0.010 +/- 0.008 < 0.028 0.13 Co-60 0.001 +/- 0.013 < 0.015 0.010 +/- 0.006 < 0.005 0.002 +/- 0.010 < 0.015 0.13 Zn-65 -0.026 +/- 0.023 < 0.018 -0.001 +/- 0.014 < 0 023 -0.005 +/- 0.017 < 0.033 0.26 Cs-134 0.000 +/- 0.010 < 0.021 -0.003 +/- 0.006 < 0.012 -0.004 +/- 0.008 < 0.016 0.13 Cs-137 0.014 +/- 0.014 < 0.021 0.015 +/- 0.008 < 0.014 0.083 +/- 0.020 < 0.020 0.15 Other (Ru-103) 0.007 +/- 0.010 < 0.109 -0.010 +/- 0.006 < 0.069 0.006 +/- 0.007 < 0.045 0.5 Collection Date 02*23-18 04-16-18 04-29-18 Lab Code EF- 1021 EF- 2331 EF- 2332 Type Freshwater Drum King Salmon Burbot K-40 2.18 +/- 0.36 3.46 +/- 0.41 1.41 +/- 1.41 Mn-54 0.005 +/- 0.008 < 0.015 0.006 +/- 0.009 < 0.016 0.009 +/- 0.008 < 0.012 0.13 Fe-59 0.004 +/- 0.015 < 0.059 -0.037 +/- 0.019 < 0.074 -0.011 +/- 0.017 < 0.040 0.26 Co-58 -0.017 +/- 0.008 < 0.018 0.002 +/- 0.008 < 0.025 0.004 +/- 0.009 < 0.016 0.13 Co-60 0.012 +/- 0.009 < 0.017 0 009 +/- 0.009 < 0.013 0.002 +/- 0.010 < 0.008 0.13 Zn-65 -0 038 +/- 0.019 < 0.012 0.008 +/- 0.023 < 0.045 0.002 +/- 0.018 < 0.030 0.26 Cs-134 -0.001 +/- 0.009 < 0 016 -0.003 +/- 0 008 < 0.017 0.006 +/- 0.008 < 0.015 0.13 Cs-137 0.050 +/- 0.022 < 0.021 0 016 +/- 0.012 < 0.024 0.025 +/- 0.012 < 0.018 0.15 Other (Ru-103) 0.005 +/- 0.007 < 0.047 0.012 +/- 0.009 < 0.056 0.011 +/- 0.009 < 0.031 0.5 7-1

POINT BEACH NUCLEAR PLANT Table 7. Fish, analyses for gamma emitting isotopes. Location: E-13 Collection: Quarterly Units: pCi/g wet Sample Description and Concentration (pCi/g wet) Req. MDC MDC MDC LLD Collection Date 05-02-18 07-27-18 08-13-18 Lab Code EF- 2333 EF- 3943 EF- 3944 Type Lake Trout Coho Salmon Burbot K-40 2.51 +/- 0.32 3.46 +/- 0.40 1.41 +/- 0.30 Mn-54 0.004 +/- 0.007 < 0.013 -0.004 +/- 0.010 < 0.020 0.009 +/- 0.008 < 0.015 0.13 Fe-59 0.008 +/- 0.015 < 0.051 -0.031 +/- 0.022 < 0.063 -0.011 +/- 0.017 < 0.039 0.26 Co-58 0.005 +/- 0.009 < 0.024 -0.003 +/- 0.011 < 0.024 0.004 +/- 0.009 < 0.017 0.13 Co-60 -0 007 +/- 0.010 < 0.013 -0.002 +/- 0.008 < 0.009 0.002 +/- 0.010 < 0.009 0.13 Zn-65 -0.026 +/- 0.018 < 0.034 -0.003 +/- 0.025 < 0.034 0.002 +/- 0.018 < 0.023 0.26 Cs-134 -0 002 +/- 0.008 < 0.015 0.013 +/- 0.008 < 0.019 0.006 +/- 0.008 < 0.015 0.13 Cs-137 0.014 +/- 0.010 < 0.020 0.014 +/- 0.012 < 0.020 0.025 +/- 0.012 < 0.018 0.15 Other (Ru-103) 0.005 +/- 0.007 < 0.031 -0.009 +/- 0.010 < 0.058 0.011 +/- 0.009 < 0.043 0.5 Collection Date 09-03-18 10-27-18 11-25-18 Lab Code EF- 3945 EF* 5362 EF- 5363 Type Catfish Burbot Lake trout K-40 1.54 +/- 0.33 2.46 +/- 0.36 2.98 +/- 0.37 Mn-54 0.000 +/- 0.010 < 0.018 0.009 +/- 0.008 < 0.012 0.004 +/- 0.009 < 0.016 0.13 Fe-59 0.009 +/- 0.021 < 0.054 -0.013 +/- 0.015 < 0.045 0.002 +/- 0.016 < 0.041 0.26 Co-58 -0.002 +/- 0.009 < 0.019 -0.001 +/- 0.007 < 0.023 0.010 +/- 0.008 < 0.021 0.13 Co-60 0.001 +/- 0.012 < 0.012 0.011 +/- 0.008 < 0.012 -0 003 +/- 0.011 < 0.019 0.13 Zn-65 0.009 +/- 0.018 < 0.032 -0.023 +/- 0.020 < 0.025 0.007 +/- 0.019 < 0.037 0.26 Cs-134 0.000 +/- 0.009 < 0.015 0.002 +/- 0.008 < 0.015 -0.002 +/- 0.009 < 0.016 013 Cs-137 0.022 +/- 0.013 < 0.022 0.015 +/- 0.010 < 0.017 0.017 +/- 0.011 < 0.018 0.15 Other (Ru-1 03) -0.001 +/- 0.008 < 0.024 -0.007 +/- 0.006 < 0 034 0 000 +/- 0.007 < 0.024 0.5 7-2

POINT BEACH NUCLEAR PLANT Table 7. Fish, analyses for gross beta and gamma emitting isotopes. Location: E-13 Collection: Quarterly Units: pCi!g wet Sample Description and Concentration (pCi/g wet) Req. MDC MDC MDC LLD Collection Date 12-06-18 Lab Code EF- 5364 Annual Type Lake herring Ratio (wet/dry wt.) Mean +/- s.d. Gross Beta 0.00 +/- 0.00 0.5 K-40 3.01 +/- 0.39 2.68 +/- 0.84 Mn-54 -0.001 +/- 0.008 < 0.013 0.005 +/- 0.005 0.13 Fe-59 0.006 +/- 0.016 < 0.032 -0.011 +/- 0.018 0.26 Co-58 0.003 +/- 0.008 < 0.018 0.005 +/- 0.009 0.13 Co-60 -0.005 +/- 0.009 < 0.010 0.003 +/- 0.006 0.13 Zn-65 -0.020 +/- 0.018 < 0.031 -0.008 +/- 0.016 0.26 Cs-134 -0.004 +/- 0.009 < 0.016 0.001 +/- 0.006 0.13 Cs-137 0.000 +/- 0.012 < 0.020 0.028 +/- 0.026 0.15 Other (Ru-1 03) -0.010 +/- 0.007 < 0.017 0.002 +/- 0.009 0.5 7-3

POINT BEACH NUCLEAR PLANT Table 8. Radioactivity in shoreline sediment samples Collection: Annual Sample Description and Concentration (pCi/g dry) MDC MDC MDC Collection Date 10/12/2018 10/12/2018 10/12/2018 Lab Code ESS- 4512 ESS- 4513 ESS- 4514 LLD Location E-01 E-05 E-06 Be-7 0.064 +/- 0.043 < 0.14 -0.057 +/- 0.083 < 0.15 0.244 +/- 0.138 < 0.16 K-40 3.73 +/- 0.31 4.75 +/- 0.41 7.73 +/- 0.40 Cs-134 -0.001 +/- 0.005 < 0.007 -0.008 +/- 0.010 < 0.018 -0.001 +/- 0.006 < 0.011 0.15 Cs-137 0.011 +/- 0.007 < 0.013 -0.002 +/- 0.010 < 0.020 0.020 +/- 0.010 < 0.014 0.15 Tl-208 0.041 +/- 0.013 0.067 +/- 0.027 0.056 +/- 0.016 Pb-212 0.09 +/- 0.017 0.16 +/- 0.023 0.17 +/- 0.020 Bi-214 0.162 +/- 0.029 1.81 +/-0.073 0.14 +/- 0.025 Ra-226 0.29 +/- 0.11 < 0.24 0.44+/-0.19 < 0.37 0.51 +/- 0.18 Ac-228 0.12 +/- 0.035 0.23 +/- 0.093 0.19 +/- 0.043 Collection Date 10/12/2018 10/12/2018 Lab Code ESS- 4515 ESS- 4517 Annual Location E-12 E-33 Mean +/-s.d. 0.0 0.0 Be-7 -0.004 +/- 0.038 < 0.12 0.001 +/- 0.063 < 0.16 0.025 0.082 K-40 4.36 +/- 0.31 5.54 +/- 0.42 2.61 2.94 Cs-134 -0.002 +/- 0.005 < 0.008 0.007 +/- 0.007 < 0.015 0.15 0.00 0.00 Cs-137 0.017 +/- 0.007 < 0.013 0.015 +/- 0.009 < 0.014 0.15 0.006 0.008 Tl-208 0.039 +/- 0.012 0.045 +/- 0.020 0.025 0.03 Pb-212 0.09 +/- 0.017 0.105 +/- 0.020 0.06 0.07 Bi-214 0.096 +/- 0.023 0.152 +/- 0.029 0.24 0.56 Ra-226 0.44 +/- 0.11 < 0.23 0.33+/-0.16 < 0.30 0.20 0.22 Ac-228 0.14 +/- 0.034 0.10 +/- 0.042 0.08 0.09 8-1

POINT BEACH NUCLEAR PLANT Table 9. Radioactivity in soil samples Collection: Annual Sample Description and Concentration (pCi/g dry) MDC MDC MDC Collection Date 10/12/2018 10/12/2018 10/12/2018 Req. Lab Code ESO- 4504 ESO- 4505 ESO- 4506 LLD Location E-01 E-02 E-03 Be-7 -0.039 +/- 0.09 < 0.23 -0.07 +/- 0.09 < 0.25 0.077 +/- 0.079 < 0.24 K-40 18.55 +/- 0.73 19.33 +/- 0.83 15.36 +/- 0.73 Cs-134 -0.010 +/- 0.011 < 0.021 -0.011 +/- 0.012 < 0.018 -0.004 +/- 0.010 < 0.016 0.15 Cs-137 0.04 +/- 0.020 < 0.023 0.187 +/- 0.033 < 0.030 0.122 +/- 0.032 < 0.030 0.15 Tl-208 0.21 +/- 0.030 0.18+/-0.027 0.16+/-0.034 Pb-212 0.56 +/- 0.038 0.48 +/- 0.037 0.42 +/- 0.034 Bi-214 0.53 +/- 0.049 0.58 +/- 0.059 0.38 +/- 0.049 Ra-226 1.08 +/- 0.29 1.33 +/- 0.29 0.66 +/- 0.26 Ac-228 0.61 +/- 0.095 0.53 +/- 0.124 0.54 +/- 0.11 Collection Date 10/12/2018 10/12/2018 10/12/2018 Lab Code ESO- 4507 ESO- 4508 ESO- 4509 Location E-04 E-06 E-08 Be-7 -0.054 +/- 0.117 < 0.31 0.082 +/- 0.072 < 0.26 0.082 +/- 0.062 < 0.19 K-40 19.45 +/- 0.87 11.97 +/- 0.58 14.04 +/- 0.65 Cs-134 -0.020 +/- 0.013 < 0.019 -0.002 +/- 0.008 < 0.015 -0.006 +/- 0.008 < 0.011 0.15 Cs-137 0.09 +/- 0.027 < 0.028 0.15 +/- 0.019 < 0.018 0.20 +/- 0.027 < 0.021 0.15 Tl-208 0.22 +/- 0.047 0.065 +/- 0.021 0.081 +/- 0.020 Pb-212 0.50 +/- 0.040 0.18 +/- 0.025 0.22 +/- 0.027 Bi-214 1.15 +/- 0.072 0.12 +/- 0.030 0.23 +/- 0.036 Ra-226 0.92 +/- 0.32 0.51 +/- 0.22 0.40 +/- 0.23 Ac-228 0.59 +/- 0.083 0.24 +/- 0.067 0.20 +/- 0.066 Collection Date 10/12/2018 10/12/2018 Lab Code ESO- 4510 ESO- 4511 Annual Location E-09 E-20 Mean +/- s.d. Be-7 0.086 +/- 0.077 < 0.29 -0.23 +/- 0.1 09 < 0.35 -0.004 +/- 0.08 K-40 20.46 +/- 0.76 19.33 +/- 0.91 8.66 +/- 9.19 Cs-134 -0.037 +/- 0.011 < 0.017 0.009 +/- 0.012 < 0.020 -0.006 +/- 0.01 0.15 Cs-137 0.09 +/- 0.024 < 0.024 0.117 +/- 0.024 < 0.030 0.06 +/- 0.07 0.15 Tl-208 0.22 +/- 0.028 0.21 +/- 0.039 0.08 +/- 0.10 Pb-212 0.63 +/- 0.037 0.57 +/- 0.042 0.22 +/- 0.26 Bi-214 0.41 +/- 0.049 0.49 +/- 0.057 0.24 +/- 0.33 Ra-226 1.40 +/- 0.28 1.00 +/- 0.33 0.46 +/- 0.53 Ac-228 0.68 +/- 0.07 0.62 +/- 0.100 0.25 +/- 0.29 9-1

POINT BEACH NUCLEAR PLANT Table 10. Radioactivity in vegetation samples Collection: Tri-annual Sample Description and Concentration (pCi/g wet) MDC MDC MDC Location E-01 E-02 E-03 Collection Date 05-16-18 05-16-18 05-17-18 Lab Code EG- 1909 EG- 1910 EG-1911 Req. LLD Be-7 2.46 +/- 0.20 0.79 +/- 0.15 0.96 +/- 0.15 K-40 5.53 +/- 0.38 4.86 +/- 0.36 7.35 +/- 0.41 1-131 -0.007 +/- 0.006 < 0.014 0.001 +/- 0.005 < 0.021 0.003 +/- 0.005 < 0.023 0.060 Cs-134 0.002 +/- 0.006 < 0.011 0.000 +/- 0.006 < 0.009 0.001 +/- 0.006 < 0.010 0.060 Cs-137 -0.002 +/- 0.008 < 0.014 0.002 +/- 0.006 < 0.011 -0.003 +/- 0.007 < 0.009 0.080 Other (Co-60) 0.003 +/- 0.007 < 0.008 0.003 +/- 0.006 < 0.006 0.002 +/- 0.007 < 0.010 0.060 Location E-04 E-06 E-08 Collection Date 05-17-18 05-16-18 05-17-18 Lab Code EG- 1912 EG- 1913 EG- 1914 Req. LLD Be-7 1.57 +/- 0.17 4.31 +/- 0.33 1.64 +/- 0.23 K-40 5.92 +/- 0 38 4.52 +/- 0.44 7.07 +/- 0.53 1-131 0.002 +/- 0 005 < 0.022 -0.015 +/- 0.007 < 0.020 -0.005 +/- 0.008 < 0.022 0.060 Cs-134 0.001 +/- 0 005 < 0.010 0.004 +/- 0.008 < 0.014 0.009 +/- 0.007 < 0.013 0.060 Cs-137 0.004 +/- 0.006 < 0.008 0.084 +/- 0.022 < 0.019 -0.001 +/- 0.009 < 0.016 0.080 Other (Co-60) 0.004 +/- 0.007 < 0.012 -0.005 +/- 0.008 < 0.008 0.001 +/- 0.008 < 0.010 0.060 Location E-09 E-20 Collection Date 05-17-18 05-16-18 Lab Code EG- 1915 EG- 1916 Req. LLD Be-7 1.18 +/- 0.14 1.77 +/- 0.30 K-40 6.44 +/- 0.37 6.08 +/- 0.52 1-131 -0.002 +/- 0.006 < 0.025 0.002 +/- 0.009 < 0.033 0.060 Cs-134 0.002 +/- 0.006 < 0.011 -0.005 +/- 0.008 < 0.015 0.060 Cs-137 -0.002 +/- 0.007 < 0.007 0.012 +/- 0.010 < 0.018 0.080 Other (Co-60) 0.004 +/- 0.006 < 0.010 -0.006 +/- 0.008 < 0.009 0.060 10-1

POINT BEACH NUCLEAR PLANT Table 10. Radioactivity in vegetation samples Collection: Tri-annual Sample Description and Concentration (pCi/g wet) MDC MDC MDC Location E-01 E-02 E-03 Collection Date 07-24-18 07-24-18 07-24-18 Lab Code EG- 2994 EG- 2995 EG- 2996 Req. LLD Be-7 2.53 +/- 0.25 1.69 +/- 0.24 2.35 +/- 0.19 K-40 5.16 +/- 0.43 6.55 +/- 0.51 8.92 +/- 0.44 1-131 -0.010 +/- 0.008 < 0.019 0.007 +/- 0.008 < 0.026 -0.004 +/- 0.006 < 0.015 0.060 Cs-134 0.000 +/- 0.008 < 0.013 0.000 +/- 0.008 < 0.015 -0.001 +/- 0.007 < 0.011 0.060 Cs-137 0.006 +/- 0.010 < 0.020 -0.003 +/- 0.009 < 0.013 -0 006 +/- 0.006 < 0.008 0.080 Other (Co-60) -0.004 +/- 0.009 < 0.008 0.006 +/- 0.010 < 0.013 0.001 +/- 0.007 < 0.006 0.060 Location E-04 E-06 E-08 Collection Date 07-24-18 07-24-18 07-24-18 Lab Code EG- 2997 EG- 2998 EG- 2999 Req. LLD Be-7 1.82 +/- 0.18 2.37 +/- 0.29 2.13 +/- 0.22 K-40 4.12 +/- 0.33 3.61 +/- 0.38 6.12 +/-0.44 1-131 0.002 +/- 0.006 < 0.026 0.001 +/- 0.009 < 0.023 -0.011 +/- 0.006 < 0.020 0.060 Cs-134 0.005 +/- 0.006 < 0.010 -0.009 +/- 0.008 < 0.014 -0 002 +/- 0.007 < 0.013 0.060 Cs-137 0.000 +/- 0.007 < 0.011 0.001 +/- 0.010 < 0.015 -0.001 +/- 0.007 < 0.011 0.080 Other (Co-60) 0.000 +/- 0.006 < 0.006 0.003 +/- 0.008 < 0.005 -0.004 +/- 0.009 < 0.006 0.060 Location E-09 E-20 Collection Date 07-24-18 07-25-18 Lab Code EG- 3000 EG- 3002 Req. LLD 0.25 Be-7 3.24 +/- 0.26 1.03 +/- 0.17 K-40 5.06 +/- 0.41 4.82 +/- 0.38 i-131 0.008 +/- 0.007 < 0.035 -0.010 +/- 0.006 < 0.020 0.060 Cs-134 -0.005 +/- 0.008 < 0.015 0.003 +/- 0.006 < 0.012 0.060 Cs-137 -0.001 +/- 0.008 < 0.009 -0.004 +/- 0.007 < 0.012 0.080 Other (Co-60} -0.004 +/- 0.008 < 0.007 0.005 +/- 0.007 < 0.005 0.060 10-2

POINT BEACH NUCLEAR PLANT Table 10. Radioactivity in vegetation samples Collection: Tri-annual Sample Description and Concentration (pCi/g wet) MDC MDC MDC Location E-01 E-02 E-03 Collection Date 09-28-18 09-27-18 09-27-18 Lab Code EG- 4001 EG- 4002 EG- 4003 Req. LLD 0.25 Be-7 2.14 +/- 0.16 3.90 +/- 0.23 3.66 +/- 0.18 K-40 5.20 +/- 0.28 4.98 +/- 0.31 7.04 +/- 0.30 1-131 0.006 +/- 0.005 < 0.022 -0.006 +/- 0.007 < 0.022 0.001 +/- 0.005 < 0.014 0.060 Cs-134 0. 003 +/- 0.005 < 0.008 -0.003 +/- 0.006 < 0.012 -0.004 +/- 0.004 < 0.008 0.060 Cs-137 0.002 +/- 0.005 < 0.008 0.001 +/- 0.006 < 0.013 -0.002 +/- 0.005 < 0.006 0.080 Other (Co-60) -0.005 +/- 0.005 < 0.005 0.004 +/- 0.006 < 0.010 0.005 +/- 0.005 < 0.009 0.060 Location E-04 E-06 E-08 Collection Date 09-27-18 09-27-18 09-28-18 Lab Code EG- 4005 EG- 4006 EG- 4007 Req. LLD 0.25 Be-7 3.32 +/- 0.30 7.40 +/- 0.46 5.42 +/- 0.36 K-40 5.54 +/- 0.47 3.34 +/- 0.40 3.71 +/- 0.38 1-131 0.008 +/- 0.010 < 0.031 -0.034 +/- 0.013 < 0.051 -0.002 +/- 0.008 < 0.038 0.060 Cs-134 -0.001 +/- 0.007 < 0.014 -0.008 +/- 0.011 < 0.021 -0.009 +/- 0.008 < 0.015 0.060 Cs-137 -0 003 +/- 0.009 < 0.010 0.184 +/- 0.028 < 0.022 0.001 +/- 0.009 < 0.015 0.080 Other (Co-60) -0.002 +/- 0.010 < 0.009 -0.003 +/- 0.010 < 0.008 0.004 +/- 0.009 < 0.015 0.060 Location E-09 E-20 Collection Date 09-28-18 09-27-18 Lab Code EG- 4008 EG- 4009 Req. LLD 0.25 Be-7 2.67 +/- 0.29 1.16 +/- 0.20 K-40 4.31 +/- 0.41 4.21 +/- 0.35 1-131 0.010 +/- 0.008 < 0.034 0.026 +/- 0.007 < 0.040 0.060 Cs-134 -0.004 +/- 0.008 < 0.015 -0.002 +/- 0.007 < 0.013 0.060 Cs-137 0.002 +/- 0.009 < 0.011 -0.001 +/- 0.008 < 0.012 0.080 Other (Co-60) 0.005 +/- 0.009 < 0.013 0.003 +/- 0.007 < 0.010 0.060 Be-7 Annual Mean +/- s.d. 2.56 +/- 1.54 K-40 Annual Mean +/- s.d. 5.43 +/- 1.35 1-13*1 Annual Mean+/- s.d. -0.001 +/- 0.011 Cs-134 Annual Mean+/- s.d. -0.001 +/- 0.004 Cs-137 Annual Mean+/- s.d. 0.011 +/- 0.041 Co-60 Annual Mean +/- s.d. 0.003 +/- 0.004 10-3

POINT BEACH NUCLEAR PLANT Table 11. Aquatic Vegetation, analyses for gross beta and gamma emitting isotopes. Collection: Annual Units: pCi/g wet Sample Description and Concentration Collection Date 08-16-18 MDC 08-16-18 MDC Req. 8 8 Lab Code NS NS LLD Location E-05 E-12 Be-7 K-40 Co-58 0.25 Co-60 0.25 Cs-134 0.25 Cs-137 0.25 Annual Mean+/- s.d. 8 "NS" =No sample. See Table 2.0, Listing of Missed Samples. 11-1

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation a LLD/7days: < 1mR/TLD 1st. Quarter, 2018 Date Annealed: 12-06-17 Days in the field 89 Date Placed: 01-05-18 Days from Annealing Date Removed: 04-04-18 to Readout 128 Date Read: 04-13-18 Days in mR/Stnd Qtr Location Field Total mR NetmR (91 days) Net mR per 7 days Indicator E-1 89 17.8 +/- 0.3 12.1 +/-0.9 12.3 +/- 0.9 0.95 +/- 0.07 E-2 89 24.1 +/- 1.3 18.4 +/- 1.4 18.8 +/- 1.4 1.45 +/- 0.11 E-3 89 22.5 +/- 1.8 16.8+/-1.8 17.2+/-1.9 1.32+/-0.14 E-4 89 18.1+/-1.4 12.4 +/- 1.5 12.7 +/- 1.5 0.98 +/- 0.12 E-5 89 19.5 +/- 0.6 13.8 +/- 0.7 14.1 +/-07 1 09 +/- 0.05 E-6 89 17.7 +/-08 12.0 +/- 0.9 12.2 +/- 0 9 0 94 +/- 0.07 E-7 89 17.4 +/- 1.0 11.7+/-11 12.0 +/- 1.1 0.92 +/- 0.08 E-8 89 18.5 +/- 1.2 12.8 +/- 1.2 13 0 +/- 1.3 1.00 +/-0.10 E-9 89 20.4 +/- 1. 1 14.7 +/- 1 1 15.0 +/- 1.2 1.15 +/- 0.09 E-12 89 17.1 +/- 0.7 11.4+/-08 11.6 +/- 0 9 0.89 +/- 0.07 E-14 89 18.9 +/- 0.5 13.2 +/-06 13.5 +/- 0.7 1.04 +/- 0.05 E-15 NDIJ E-168 89 20.4 +/- 0 8 14.6 +/- 0 9 15.0 +/- 1.0 1.15 +/- 0 08 E-17 89 20.8 +/- 1.2 15.1 +/- 1.3 15.4 +/- 1.3 1.19+/-0.10 E-18 89 21.2 +/- 1.0 15.5 +/- 1.1 15.8 +/- 1.1 1.22 +/- 0.09 E-22 89 22.1 +/- 1.3 16.4 +/- 1.4 16.8+/-1.4 1.29 +/- 0.11 E-23 89 20.2 +/- 0 5 14.5 +/- 0.6 14.8 +/- 0 7 1.14 +/- 0.05 E-24 89 20 0 +/- 1.3 14.3 +/- 1.3 14.6 +/- 1.4 1.13 +/- 0.10 E-25 89 19.0 +/-0.4 13.3 +/- 0.6 13.5 +/- 0.6 1.04 +/- 0 04 E-268 89 19.2 +/- 0 9 13.5 +/- 1.0 13.8+/-1.0 1.06 +/- 0.08 E-27 89 23 9 +/- 0 5 18.2 +/- 0 7 18.6 +/- 0.7 1.43 +/- 0.05 E-28 89 15.0 +/- 0 6 9.3 +/- 0.7 95 +/-0 7 0.73 +/- 0.06 E-29 89 16.2+/-1.0 10.5 +/- 1 1 10.7 +/- 1.1 0.82 +/- 0.09 E-30 89 19.0 +/- 1.0 13.3 +/- 1.1 13.6+/-1.1 1.04 +/- 0.08 E-31 89 19.4 +/- 0.6 13 7 +/- 0.7 14.0 +/- 0.8 1.08 +/- 0.06 E-32 89 23.6 +/- 0.9 17.8 +/- 0.9 18.2 +/- 1.0 1.40 +/- 0.07 E-38 89 21.0 +/- 1.5 15.3 +/- 1.6 15.6 +/- 1 6 1.20 +/- 0.13 E-39 89 20.9 +/- 0.8 15.2 +/- 0.9 15.5 +/- 0 9 1.19 +/- 0.07 E-41 89 17.8 +/- 0.7 12.1 +/- 0.8 12.4 +/- 0.8 0.95 +/- 0.06 E-42 89 21.1 +/-0.8 15.3 +/- 0.9 15.7 +/- 0.9 1.21 +/- 0.07 E-43 89 18.9 +/- 11 13.2 +/- 1.2 13.5 +/- 1.2 1.04 +/- 0 09 E-44 89 17.0 +/- 0.5 11.2 +/- 0.6 11.5 +/-0.7 0.88 +/- 0.05 Control E-20 89 19.8 +/- 1.2 14.1 +/- 1.2 14.4+/-1.3 1.11 +/- 0.10 Mean+/-s.d. 19.6 +/- 2.2 13.9 +/- 2.2 14.2 +/- 2.2 1.09+/-0.16 In-Transit Ex1;2osure Date Annealed Date Read ITC-1 ITC-2 12-06-17 01-10-18 5.1 +/- 0.3 5.4 +/- 0.5 03-07-18 04-13-18 5.1 +/- 0.2 5.5 +/- 0.5 a The CaS0 4 :0y dosimeter cards provide four separate readout areas. Values listed represent the mean and standard deviat1on of the average of the four readings. b "NO" = No data; see Table 2.0, Listing of Missed Samples. 12-1

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation a LLD/7days: < 1 mR/TLD 2nd Quarter, 2018 Date Annealed: 03-07-18 Days in the field 89 Date Placed: 04-04-18 Days from Annealing Date Removed: 07-02-18 to Readout 124 Date Read: 07-09-18 Days in mR/Stnd Qtr Location Field Total mR NetmR (91 days) Net mR per 7 days Indicator E-1 89 17.6 +/- 0.4 12.8 +/- 0.8 13.1 +/-0.8 1.01 +/- 0.06 E-2 89 21.0 +/- 1.3 16.2 +/- 1.5 16.5 +/- 1.5 1.27 +/- 0.12 E-3 89 22.8 +/- 1.5 18.0 +/- 1.7 18.4 +/- 1.7 1.42+/-0.13 E-4 89 19.1 +/-0.9 14.3 +/- 1.2 14.6 +/- 1.2 1.13 +/- 0 09 E-5 89 18.9 +/- 0.5 14.1 +/- 0.8 14.4 +/- 0.9 1.11 +/- 0.07 E-6 89 17.0 +/- 0.5 12.2 +/- 0.8 12.5 +/- 0.9 0.96 +/- 0.07 E-7 89 17.9+/-09 13.1+/-1.2 13.4 +/- 1.2 1.03 +/- 0.09 E-8 89 18.2 +/- 1.2 13.4 +/- 1.4 13.7 +/- 1.4 1.05 +/- 0.11 E-9 89 19.7 +/-0.7 15.0 +/- 1.0 15.3 +/- 1.0 1.18 +/- 0.08 E-12 89 15.3 +/- 1.2 10.5 +/- 1.4 10.7 +/-1.4 0.83 +/- 0.11 E-14 89 20.9 +/- 0.9 16.1 +/- 1.2 16.5 +/- 1.2 1.27 +/- 0 09 E-15 89 20.3 +/- 1.8 15.5 +/- 2.0 15.9 +/-2.0 1.22 +/- 0.16 E-168 89 18.9 +/- 0.7 14.1 +/- 1.0 14.4 +/- 1.0 1.11 +/- 0.08 E-17 89 21.3 +/- 0.4 16.5 +/- 0.8 16.9 +/- 0.8 1.30 +/- 0.06 E-18 89 21.2 +/-0.9 16.5 +/- 1.1 16.8 +/- 1.1 1.29 +/- 0 09 E-22 89 19.7 +/- 1.5 15.0 +/- 1.6 15.3+/-1.7 1.18 +/-0.13 E-23 89 21.0 +/- 0.5 16.2 +/- 0.8 16.6 +/- 0.9 1.28 +/- 0.07 E-24 89 19.8 +/- 0.8 15.0 +/- 1.1 15.3 +/- 1 1 1.18 +/-0.09 E-25 89 19.1 +/- 0.1 14.3 +/- 0.7 14.6 +/- 0.7 1.13 +/-0.06 E-268 89 17.7 +/- 0.9 12.9 +/- 1.1 13.2 +/- 1.1 1.01 +/- 0 09 E-27 89 21.1 +/- 1.2 16.4 +/- 1.4 16.7 +/- 1.5 1.29 +/- 0.11 E-28 89 14.9 +/- 0.5 10.1 +/-0.9 10.3 +/- 0.9 0.79 +/- 0.07 E-29 89 15.4 +/- 0.8 10.6 +/- 1.0 10.8 +/- 1.1 0.83 +/- 0.08 E-30 89 16.8 +/- 0.8 12.0 +/- 1.0 12.3 +/- 1.0 0.94 +/- 0.08 E-31 89 19.2 +/- 1.1 14.4 +/- 1.3 14.7 +/- 1.3 1.13 +/- 0.10 E-32 89 23.7 +/-0.7 18.9 +/- 1.0 19.4 +/- 1.0 1.49 +/- 0.08 E-38 89 18.9 +/-0.7 14.2 +/- 1.0 14.5 +/- 1.0 1.11 +/- 0 08 E-39 89 18.7 +/- 0.9 14.0 +/- 1.1 14.3+/-1.1 1.10+/-0.09 E-41 89 18.1 +/-0.3 13.3 +/- 0.8 13.6 +/- 0.8 1.05 +/- 0.06 E-42 89 21 1 +/- 1 0 16.3 +/- 1.2 16.7 +/- 1.3 1.28 +/- 0.10 E-43 89 18.8+/-0.7 14.0 +/- 1.0 14.3 +/- 1 0 1.10 +/- 0.08 E-44 89 19.4 +/- 0.4 14.6 +/- 0.8 14.9 +/- 0 8 1.15 +/- 0.06 QQ!lliQ! E..20 89 19.0+/-0.7 14.2 +/- 1 0 14.5 +/- 1.0 1.12 +/- 0.08 Mean+/-s.d. 19.2 +/- 2.0 14.4 +/- 2.0 14.7 +/- 2.1 1.13 +/-0.16 In-Transit ExQosure Date Annealed Date Read ITC-1 ITC-2 03-07-18 04-13-18 51 +/- 0.2 5.5 +/- 0.5 06-07-18 07-09-18 4.3 +/- 0.2 4.3 +/- 0.4

The CaSO ~:Dy dosimeter cards provide four separate readout areas. Values listed represent the mean and standard deviat1on of the average of the four readings 12-2

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation a LLD/7days: < 1mR/TLD 3rd Quarter. 2018 Date Annealed: 06-07-18 Days in the field 92 Date Placed: 07-02-18 Days from Annealing Date Removed: 10-02-18 to Readout: 123 Date Read: 10-08-18 Days in mR/Stnd Qtr Location Field Total mR NetmR (91 days) Net mR per 7 days Indicator E-1 92 15.7 +/- 0.2 11.0 +/-0.7 10.9 +/- 0.7 0.84 +/- 0.05 E-2 92 21.9 +/- 0.8 17.3+/-1.1 17.1+/-1.1 1.31 +/- 0.08 E-3 92 21.6 +/- 1.4 16.9 +/- 1.5 16.7 +/- 1.5 1.29 +/-0.12 E-4 92 18.0 +/- 0.9 13.4+/-1.1 13.3 +/- 1.1 1.02 +/- 0.08 E-5 92 18.5 +/- 0.8 13.9+/-1.1 13.7 +/- 1.1 1 06 +/- 0.08 E-6 92 16.7 +/- 0.7 12.1 +/-0.9 12.0 +/- 0.9 0.92 +/- 0.07 E-7 92 NOb E-8 92 17.3 +/- 1.0 12.6 +/- 1.2 12.5+/-1.2 0.96 +/- 0.09 E-9 92 19.8 +/- 1.0 15.1+/-1.2 15.0+/-1.2 1.15 +/-0.09 E-12 92 14.7 +/- 0.9 10.1 +/- 1 1 10.0+/-1.1 0.77 +/-008 E-14 92 17.7 +/-0.4 13.0 +/- 0.8 12.9 +/- 0.8 0.99 +/- 0.06 E-15 92 20.3 +/- 0.5 15.6 +/- 0.8 15.4 +/- 0.8 1.19 +/- 0.06 E-168 92 19.2 +/- 0.8 14.6 +/- 1.0 14.4 +/- 1.0 1.11 +/-0.08 E-17 92 19.3 +/- 0.9 14.7+/-1.1 14.5 +/- 1 1 1.12 +/- 0.08 E-18 92 20.9 +/- 0.9 16.3+/-1.1 161 +/-1.1 1.24 +/- 0.08 E-22 92 21.6 +/- 1.5 16.9 +/- 1.6 16.8 +/- 1.6 1.29 +/-0.12 E-23 92 20.2 +/- 0.5 15.6 +/- 0.9 15.4 +/- 0.8 1.19 +/- 0.06 E-24 92 18.6 +/- 0.8 14.0 +/- 1.0 13.8+/-1.0 1.06 +/- 0.08 E-25 92 18.3 +/- 0.3 13.7 +/-0.7 13.5 +/- 0.7 1.04 +/- 0.05 E-268 92 18.8 +/- 1.0 14.2 +/- 1.2 14.0 +/- 1.2 1.08 +/- 0.09 E-27 92 23.1 +/- 0.5 18.4 +/- 0.8 18.2 +/- 0.8 1.40 +/- 0 06 E-28 92 NOb E-29 92 14.7 +/- 0.9 10.0+/-1.1 9.9+/-1.1 0.76 +/- 0.08 E-30 92 18.1 +/-1.3 13.4 +/- 1.5 13.3 +/- 1.5 1.02 +/- 0.11 E-31 92 19.9 +/- 0.7 15.3 +/- 1.0 15.1 +/-1.0 1.16 +/- 0.07 E-32 92 24.4 +/- 0.8 19.8 +/- 1.0 19.6+/-1.0 1.51 +/- 0.08 E-38 92 18.7 +/- 1.2 14.0 +/- 1.3 13.9+/-1.3 1 07 +/- 0.10 E-39 92 21.4 +/- 0.9 16.8 +/- 1.1 16.6 +/- 1.1 1.28 +/- 0.09 E-41 92 18.9 +/- 0.8 14.3 +/- 1.0 14.1 +/- 1.0 1.09 +/- 0.08 E-42 92 20.6 +/- 0.8 16.0 +/- 1.1 15.8 +/- 1.1 1.22 +/- 0.08 E-43 92 19.9 +/- 1.3 15.3 +/- 1.5 15.1 +/- 1.5 1.16 +/- 0.11 E-44 92 18.5 +/- 0.8 13.9 +/- 1.0 13.7 +/- 1.0 1.06 +/- 0.08 Control E-20 92 18.8 +/- 1.3 14.1 +/- 1.5 14.0 +/- 1.5 1.07 +/- 0.11 Mean+/-s.d. 19.2 +/- 2.2 14.6 +/- 2.2 14.4 +/- 2.2 1.11 +/- 0.16 In-Transit Exgosure Date Annealed Date Read ITC-1 ITC-2 06-07*18 07-09-18 4.3 +/- 0.2 4 3 +/- 0.4 09-07-18 10-09-18 4.8 +/-0.3 5.3 +/- 0.4 "The CaSO~:Dy dos1meter cards provide four separate readout areas. Values listed represent the mean and standard deviation of the average of the four readings. ~"NO"= No data, see Table 2.0, listing of Missed Samples 12-3

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation a LLD/7days: < 1mR/TLD 4th Quarter, 2018 Date Annealed: 09-07-18 Days in the field 100 Date Placed: 10-02-18 Days from Annealing Date Removed: 01-10-19 to Readout 126 Date Read: 01-11-19 Days in mR/Stnd Qtr Location Field Total mR NetmR (91 days) Net mR per 7 days Indicator E-1 100 17.5 +/- 0.3 12.3 +/- 0.8 11.2 +/- 0.7 0.86 +/- 0.05 E-2 100 21.8 +/- 1.3 16.6 +/- 1.5 15.1 +/-1.4 1.16 +/-0.11 E-3 100 24.4 +/- 1.6 19.2+/-1.7 17.5 +/- 1.6 1.34 +/- 0.12 E-4 100 20.7 +/- 1.2 15.5 +/- 1.4 14.1 +/-1.3 1.09 +/- 0.10 E-5 100 20.7 +/- 0.5 15.5 +/- 0.8 14.1+/-0.8 1.08 +/- 0.06 E-6 100 17.6 +/- 0.2 12.4 +/- 0.7 11.3 +/-0.7 0.87 +/-0.05 E-7 100 18.6 +/- 0.7 13.3 +/- 1.0 12.1 +/-09 0.93 +/- 0.07 E-8 100 19.2 +/- 1.1 14.0 +/- 1.3 12.7 +/- 1.2 0.98 +/- 0.09 E-9 100 21.1 +/- 1.0 15.9 +/- 1.2 14.5 +/- 1.1 1.11 +/- 0.08 E-12 100 17.2 +/- 1.4 11.9+/-1.6 10 9 +/- 1.5 0.84 +/- 0.11 E-14 100 23.2 +/- 1.3 17.9+/-1.4 16.3 +/- 1.3 1.26 +/- 0.10 E-15 100 26.7 +/- 2.3 21.5 +/- 2.4 19.5 +/- 2.2 1.50 +/-0.17 E-168 100 20.4 +/- 0.5 15.2 +/- 0.9 13.8 +/- 0.8 1.06 +/- 0.06 E-17 100 23.0 +/- 0.7 17.7 +/- 1.0 16.1 +/- 0.9 1.24 +/- 0.07 E-18 100 23.3 +/- 0.9 18.1 +/- 1.1 16.5 +/- 1.0 1.27 +/- 0.08 E-22 100 22.3 +/- 0.8 17.1 +/- 1.1 15.5 +/- 1.0 1.20 +/- 0.08 E-23 100 24.7 +/- 0.8 19.5 +/- 1.1 17.7 +/- 1.0 1.36 +/- 0.08 E-24 100 21.7 +/-1.5 16.5 +/- 1.6 15.0 +/- 1.5 1.15 +/- 0.11 E-25 100 21.8 +/- 1.0 16.5 +/- 1.2 15.0 +/- 1.1 1.16 +/- 0.08 E-268 100 18.7 +/-0.6 13.5 +/- 0.9 12.3 +/- 0.8 0.95 +/- 0.06 E-27 100 23.2+/-1.3 17.9 +/- 1.4 16.3 +/- 1.3 1.26 +/- 0.10 E-28 100 16.6 +/- 0.3 11.4+/-0.8 10.4 +/- 0.7 0.80 +/- 0.05 E-29 100 16.2 +/- 1.6 11.0 +/- 1.7 10.0 +/- 1.6 0.77 +/- 0.12 E-30 100 20.6 +/- 1.1 15.4 +/- 1.3 14.0 +/- 1.2 1.08 +/- 0.09 E-31 100 23.2 +/- 0 9 18.0 +/- 1.1 16.4 +/- 1.0 1.26 +/- 0.08 E-32 100 25.9 +/- 0.8 20.7 +/- 1.1 18.8 +/- 1.0 1.45 +/- 0.08 E-38 100 21.1 +/-0.2 15.9 +/- 0.7 14.5 +/- 0.7 1.11 +/- 0.05 E-39 100 21.0 +/- 0.8 15.8 +/- 1.0 14.4 +/- 0.9 1.11 +/- 0.07 E-41 100 19.9 +/-0.3 14.7 +/- 0.8 13.4 +/- 0.7 1.03 +/- 0.05 E-42 100 22.8 +/- 0.9 17.6+/-1.1 16.0 +/- 1.0 1.23 +/- 0.08 E-43 100 21.6 +/- 0.8 16.4 +/- 1.0 14.9 +/- 1.0 1.15 +/- 0.07 E-44 100 20.4 +/- 0.4 15.1 +/-0.8 13.8+/-0.7 1.06 +/- 0.05 Contra! E-20 100 26.1 +/- 1.8 20.9 +/- 2.0 19.0 +/- 1.8 1.46 +/- 0.14 Mean+/-s.d. 21.3 +/- 2.7 16.1 +/-2.7 14.64 +/- 2.44 1.13 +/-0.19 In-Transit Exposure Date Annealed Date Read ITC-1 IIC-2 09-07-18 10-09-18 4.8 +/- 0.3 5.3 +/- 0.4 12-06-18 01-11-19 5.6 +/- 0.2 5.3 +/-0.5 a The CaS0 4 :0y dosimeter cards provide four separate readout areas. Values listed represent the mean and standard deviation of the average of the four readmgs Annual Indicator Mean+/-s.d. 19.8 +/- 2.4 14.8 +/- 2.4 14.5 +/- 2.2 1.1 +/- 0.2 Annual Control Mean+/-s.d. 20.9 +/- 3.5 15.8 +/- 3.4 15.5 +/- 2.4 1.2 +/-0.2 Annual Indicator/Control Mean+/-s.d. 19.9 +/- 2.4 14.8 +/- 2.4 14.5 +/- 2.2 1.1 +/- 0.2

POINT BEACH NUC!.EAR PLANT Table 13. Groundwater H3Data Monitoring Program (Monthly Collections) Units =pCi/L Intermittent Streams Sample ID GW-01 GW-02 Collection Collection Date Lab Code H3Data MDC Date Lab Code H3Data MDC 01-18-18 NSa 01-18-18 NS 3 02-21-18 EWW-610 60:!:: 75 < 151 02-21-18 NSa 03-22-18 NS 3 03-22-18 NSa 04-18-18 EWW-1370 142 :!:: 82 < 155 04-18-18 EWW- 1371 245 :!:: 88 < 155 05-22-18 EWW-1974 129:!:: 81 < 158 05-22-18 EWW-1975 151 :!:: 82 < 158 06-20-18 EWW-2399 80 :!:: 82 < 157 06-20-18 EWW-2400 186 +/- 88 < 157 07-17-18 EWW-2766 42 +/- 75 < 156 07-17-18 EWW-2767 227 :!:: 85 < 156 08-29-18 EWW-3553 46 +/- 75 < 156 08-29-18 EWW-3554 56 :!:: 76 < 156 09-21-18 EWW- 3913 13 :!:: 71 < 150 09-21-18 EWW-3914 99:!:: 76 < 150 10-22-18 EWW-4555 37:!:: 72 < 150 10-22-18 EWW-4556 110 :!:: 76 < 150 11-27-18 NSa 11-27-18 NS 3 12-20-18 NSa 12-20-18 NS 3 Mean+/- s.d. 69:!:: 46 Mean+/- s.d 154 :!:: 70 Sample ID GW-03 GW-17 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 8 01-18-18 NS 3 01-18-18 NS 3 02-21-18 NS 8 02-21-18 NS 03-22-18 NS 3 03-22-18 NS" 04-18-18 EWW-1372 92:!:: 80 < 155 04-18-18 EWW-1374 211 :!:: 86 < 155 05-22-18 EWW- 1976 56+/- 77 < 158 05-22-18 EWW- 1978 270 +/- 88 < 158 06-20-18 EWW-2402 43 :!:: 80 < 157 06-20-18 EWW-2404 138 :!:: 85 < 157 07-17-18 EWW-2768 90 +/- 78 < 156 07-17-18 EWW-2770 181 +/- 82 < 156 08-29-18 EWW-3555 4 +/- 73 < 156 08-29-18 EWW-3556 80:!:: 77 < 156 09-21-18 EWW-3915 91 +/- 76 < 150 09-21-18 EWW-3917 45 +/- 73 < 150 10-22-18 EWW-4557 -5 +/- 69 < 150 10-22-18 EWW-4559 241 +/- 83 < 150 11-27-18 NSa 11-27-18 NS 8 8 3 12-20-18 NS 12-20-18 NS Mean+/- s d 53+/- 41 Mean+/- s.d 166 +/- 83 Wells Samele ID GW-04 (EIC Well~ Collection Date Lab Code Tritium MDC 01-26-17 EWW-18*1 26 +/- 76 < 156 02-21-18 EWW-611 39 +/- 73 < 151 03-22-18 EWW-962 82 +/- 85 < 153 04-18-18 EWW-1373 40 +/- 77 < 155 05-22-18 EWW-1977 -11 +/- 73 < 158 06-20-18 EWW-2403 38 +/- 80 < 157 07-17-18 EWW-2769 34 +/- 74 < 156 08-29-18 EWW-3448 -23 +/- 69 < 152 09-21-18 EWW- 3916 -2 +/- 70 < 150 10-22-18 EWW-4558 18 +/- 71 < 150 11-27-18 EWW-5030 -7 +/- 71 < 153 12-20-18 EWW-5359 34 t 75 < 157 Mean+/- sd 22 +/- 29

"NS" =No sample; creeks frozen 13-1

EQINT BEACH NUCLEAR PLANT Table 13 Groundwater Tritium Monitoring Program (Monthly Collections) Units = pCi/L Beach Drains SamPle ID S-1 S-3 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 3 3 01-18-18 NF 01-18-18 NF 3 02-21-18 NF" 02-21-18 NF 3 03-09-18 EWW-842 423 +/- 99 < 158 03-09-18 NF 04-25-18 EWW-1536 190 +/- 85 < 156 04-25-18 EWW-1537 491 +/- 99 < 156 05-15-18 EWW-1924 199 +/- 84 < 158 05-15-18 EWW-1925 382 +/- 93 < 158 06-07-18 EWW-2252 255 +/- 88 < 159 06-07-18 NFa 3 07-03-18 EWW-2489 236 +/- 85 < 154 07-03-18 NF 08-14-18 EWW-3294 184 +/- 81 < 152 08-14-18 EWW-3295 321 +/- 87 < 152 09-04-18 EWW- 3619 18 +/- 73 < 156 09-04-18 EWW-3620 82 +/- 77 < 156 10-01-18 EWW-4081 158 +/- 79 < 150 10-01-18 EWW-4082 238 +/- 83 < 150 11-07-18 EWW-4781 310 +/- 88 < 149 11-07-18 EWW-4782 238 +/- 84 < 149 3 12-04-18 EWW-5089 258 +/- 85 < 153 12-04-18 NF Mean+/- s.d 223 +/- 105 Mean+/- s.d. 292 +/- 140 SampleiD S-7 S-8 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 3 01-18-18 NF" 01-18-18 NF 3 02-21-18 NF 3 02-21-18 NF 03-09-18 NF 3 03-09-18 NF" 3 04-25-18 NF 04-25-18 NF" 05-15-18 NFa 05-15-18 NF 3 3 3 06-07-18 NF 06-07-18 NF 3 07-03-18 NF 07-03-18 NF" 3 08-14-18 NF 08-14-18 EWW-3296 63 +/- 74 < 151 3 09-04-18 NF" 09-04-18 NF 10-01-18 NF" 10-01-18 NF" 3 3 11-07-18 NF 11-07-18 NF 3 3 12-04-18 NF 12-04-18 NF Mean+/- s.d Mean+/- s.d Sample ID S-9 S-10 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 3 01-18-18 NF 01-18-18 NF" 3 02-21-18 NF" 02-21-18 NF 03-09-18 NF" 03-09-18 NF" 8 04-25-18 NF 04-25-18 NF" 05-15-18 NF" 05-15-18 NF~ 06-07-18 NF" 06-07-18 NF" 07-03-18 NFa 07-03-18 NFa 3 08-14-18 NF" 08-14-18 NF 09-04-18 EWW-3621 33 +/- 74 < 156 09-04-18 NFa 3 3 10-01-18 NF 10-01-18 NF 8 3 11-07-18 NF 11-07-18 NF 12-04--18 NF 8 12-04-18 NF" Mean+/- s.d Mean+/- s.d. a "NF" = No flow 13-2

POINT BEACH NUCLEAR PLA..~I Table 13. Groundwater Tritium Monitoring Program (Monthly Collections) Units= Ci/L Beach Drains (cont.) Samele !D S-11 S-12 Collection Collect1on Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-18-18 NFa 01-18-18 NFa 02-21-18 NFa 02-21-18 NFa 03-09-18 NFa 03-09-18 NFa 04-25-18 EWW-1538 157 +/- 83 < 156 04-25-18 EWW-1539 426 +/- 96 < 156 05-15-18 NFa 05-15-18 NFa 06-07-18 NFa 06-07-18 EWW-2253 322 +/- 92 < 159 07-03-18 NFa 07-03-18 NFa 08-14-18 NFa 08-14-18 NFa 09-04-18 NFa 09-04-18 NFa 10-01-18 NFa 10-01-18 NFa 11-07-18 NFa 11-07-18 NFa 12-04-18 NFa 12-04-18 NFa Mean+/- s.d. Mean+/- s.d 374 +/- 73 Sample ID S-13 U2 Fac;ade Subsurface Drain Sump Collection Collection Date lab Code Date Lab Code Tritium MDC Tritium MDC 05-15-18 EWW- 1926 287 +/- 89 < 158 01-31-18 EW- 443 2634 +/- 168 < 156 06-07-18 NFa 02-28-18 EW- 837 2721 +/- 169 < 156 07-03-18 NFa 03-31-18 EW- 1075 2217 +/- 169 < 161 08-14-18 NFa 04-30-18 EW- 1767 1107 +/- 122 < 155 09-04-18 EWW-3622 113 +/- 79 < 156 05-31-18 EW- 2299 389 +/- 98 < 158 10-01-18 NFa 06-30-18 EW- 2661 890 +/- 113 < 157 11-07-18 NFa 07-31-18 EW- 3198 1225 +/- 127 < 154 12-04-18 NF" 08-31-18 EW- 3745 1056 +/- 119 < 156 09-30-18 EW- 4195 803 +/- 110 < 154 10-31-18 EW- 4879 1022 +/- 116 < 151 11-30-18 EW- 5161 852 +/- 111 < 153 12-31-18 EW- 5537 634 +/- 106 < 177 Mean+/- s.d 200 +/- 123 Mean+/- s.d 1296 +/- 781 0

 "NF" =No flow 13-3

POINT BEACH NUCLEAR PLANT Beach Drains Units: = pCi/L Gamma isotopic analysis Location S-1 S-3 S-7 S-8 Collection Date 01-18-18 01-18-18 01-18-18 01-18-18 Lab Code NFa MDC NFa MDC NFa MDC NF 3 MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-9 S-10 S-11 S-12 Collection Date 01-18-18 01-18-18 01-18-18 01-18-18 3 Lab Code NFa NFa NFa NF Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-1 S-3 S-7 S-8 Collection Date 02-21-18 02-21-18 02-21-18 02-21-18 3 3 Lab Code NF 3 MDC NF MDC NF MDC NFa MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 a "NF" = No flow 13-4

POINT BEACH NUCLEAR PLANT Beach Drains (cont.) Units: = pCi\L Gamma isotopic analysis Location S-9 S-10 S-11 S-12 Collection Date 02-21-18 02-21-18 02-21-18 02-21-18 Lab Code NFa MDC NFa MDC NFa NFa MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-1 S-3 S-7 S-8 Collection Date 03-09-18 03-09-18 03-09-18 03-09-18 8 8 8 Lab Code EW- 842 NF NF NF Be-7 -4.5 +/- 13.7 < 27.1 Mn-54 0.7 +/- 1.4 < 2.5 Fe-59 0.2 +/- 3.3 < 6.4 Co-58 0.9 +/- 1.6 < 2.9 Co-60 0.2 +/- 1.6 < 1.8 Zn-65 1.0 +/- 3.4 < 5.1 Zr-Nb-95 0.4 +/- 1.9 < 4.2 Cs-134 -1.0 +/- 1.7 < 2.8 Cs-137 0.0 +/- 2.0 < 2.1 Ba-La-140 -0.9 +/- 1.7 < 1.5 Location S-9 S-10 S-11 S-12 Collection Date 03-09-18 03-09-18 03-09-18 03-09-18 3 3 Lab Code NFa NFa NF NF Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 a "NF" = No flow. 13-5

POINT BEACH NUCLEAR PLANT Beach Drains (cont.) Units: = pCi\L Gamma isotopic analysis Location S-1 S-3 S-7 S-8 Collection Date 04-25-18 04-25-18 04-25-18 04-25-18 Lab Code EW- 1536 MDC EW- 1537 MDC NFa NFa MDC Be-7 8.9 +/- 17.3 < 41.5 9.8 +/- 11.2 < 39.8 Mn-54 0.1+/-1.4 < 2.3 -1.4 +/- 1.8 < 1.9 Fe-59 -5.1 +/- 3.5 < 4.4 1.5 +/- 2.7 < 5.9 Co-58 0.5 +/- 1. 7 < 2.8 -0.9 +/- 1.5 < 2.1 Co-60 -0.5 +/- 2.0 < 1.6 -0.7 +/- 1.4 < 1.4 Zn-65 -4.1 +/- 4.1 < 3.4 1.4 +/- 2.7 < 2.8 Zr-Nb-95 -1.5 +/- 1.8 < 2.5 0.2 t 1.8 < 3.1 Cs-134 -0.3 +/- 1.9 < 3.4 1.3 +/- 1.5 < 3.1 Cs-137 0.3 +/- 2.0 < 3.5 2.0 +/- 1.5 < 2.8 Ba-La-140 -1.1 +/- 2.2 < 9.8 -1.6 +/- 1.8 < 3.9 Location S-9 S-10 S-11 S-12 Collection Date 04-25-18 04-25-18 04-25-18 04-25-18 Lab Code NFa NFa EW- 1538 EW- 1539 Be-7 -15.7 +/- 13.0 < 19.4 -0.3 +/- 12.2 < 38.4 Mn-54 2.3 +/- 1.5 < 2.8 0.5 +/- 1.4 < 2.3 Fe-59 -3.7 +/- 3.0 < 3.8 1.1 +/- 2.8 < 5.8 Co-58 0.3 +/- 1.5 < 3.2 -1.9 +/- 1.5 < 0.9 Co-60 -0.3 +/- 1. 7 < 2.8 -0.7 +/- 1.4 < 1.6 Zn-65 1.9 +/- 3.4 < 5.4 0.1 +/- 2.9 < 3.0 Zr-Nb-95 -1.4 +/- 1.5 < 2.8 -1.4 +/- 1.5 < 2.8 Cs-134 -0.4 +/- 1.6 < 2.6 0.7 +/- 1.6 < 2.8 Cs-137 0.6 +/- 1.8 < 2.6 0.6 +/- 1.6 < 3.3 Ba-La-140 3.9 +/- 1.8 < 9.2 1.0 +/- 1.5 < 8.3 Location S-1 S-3 S-7 S-8 Collection Date 05-15-18 05-15-18 05-15-18 05-15-18 Lab Code EW- 1924 MDC EW- 1925 MDC NFa NFa Be-7 -11.1 +/- 13.3 < 32.4 -1.4 +/- 13.7 < 25.1 Mn-54 0.1 +/- 1. 8 < 3 3 1.6 +/- 1.6 < 2.4 Fe-59 2.6 +/- 2.9 < 4.0 2.8 +/- 2.7 < 4.7 Co-58 -0.1 +/- 1.4 < 2.5 0.2 +/- 1.5 < 1.8 Co-60 -1.0 +/- 2.1 < 2.0 1.8 +/- 1.5 < 2.2 Zn-65 -3.1 +/- 2.6 < 2.3 -1.2 +/- 2.7 < 3.3 Zr-Nb-95 1.7 +/- 1.8 < 4.6 -0.6 +/- 1. 7 < 2.7 Cs-134 0.2 +/- 1.8 < 3.4 0.9 +/- 1.4 < 30 Cs-137 0.5 +/- 1.8 < 3.2 0.9 +/- 1.8 < 3.4 Ba-La-140 5.3 +/-2 1 < 7.5 7.7 +/- 1.9 < 10.3 a "NF" = No flow 13-6

POINT BEACH NUCLEAR PLANT Beach Drains (cont.) Units: = pCi\L Gamma isotopic analysis Location S-9 S-10 S-11 S-12 Collection Date 05-15-18 05-15-18 05-15-18 05-15-18 Lab Code NFa MDC NFa MDC MDC MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-13 S-1 S-3 S-7 Collection Date 05-15-18 06-07-18 06-07-18 06-07-18 Lab Code EW- 1926 MDC EW- 2252 MDC NFa NFa Be-7 2.9 +/- 16.5 < 30.7 7.2 +/- 13.5 < 32.6 Mn-54 -0.1 +/- 1.7 < 1.6 -1.5 +/- 1.9 < 2.5 Fe-59 -2.2 +/- 3.2 < 2.8 -1.8 +/- 3.1 < 6.3 Co-58 0.4 +/- 1.8 < 3.6 2.0 +/- 1.7 < 3.0 Co-60 -0.3 +/- 1.6 <1.4 -0.6 +/- 1.9 <28 Zn-65 0.3 +/- 3.4 < 4.6 2.9 +/- 3.3 < 5.9 Zr-Nb-95 3.3 +/- 1.8 < 3.8 -0.7 +/- 1.8 < 2.6 Cs-134 0.9+/-1.7 < 3.0 1.0 +/- 1.8 < 3.3 Cs-137 2.1 +/- 2.1 < 3.6 1.3 +/- 1.9 < 2.7 Ba-La-140 4.1 +/- 1.6 < 6.2 -3.0 +/- 1.4 < 5.4 Location S-8 S-9 S-10 S-11 Collection Date 06-07-18 06-07-18 06-07-18 06-07-18 Lab Code NFa NFa NFa NFa Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 a "NF" =No flow. 13-7

POINT BEACH NUCLEAR PLANT Beach Drains (cont.) Units: =pCi\L Gamma isotopic analysis Location S-12 S-13 S-1 S-3 Collection Date 06-07-18 06-07-18 07-03-18 07-03-18 Lab Code EW- 2253 MDC NFa MDC EWW- 2489 MDC NFa MDC Be-7 0.9 +/- 14.8 < 35.1 4.8 +/- 17.1 < 34.4 Mn-54 -0.4 +/- 1.4 < 2.7 -1.0 +/- 1.7 < 1. 7 Fe-59 -1.6 +/- 2.3 < 2.1 1.2 +/- 2.9 < 4.8 Co-58 0.1 +/- 1.4 < 3.1 -0.2 +/- 1.5 < 2.2 Co-60 0.2 +/- 1. 7 < 2.2 -0.1 +/- 1.8 < 1. 7 Zn-65 -2.3 +/- 3.0 < 4.1 -0.1 +/- 3.2 < 4.3 Zr-Nb-95 -1.3+/-1.5 < 3.1 0.4 +/- 1.7 < 2.7 Cs-134 0.7+/-1.4 < 2.9 -1.6 +/- 1.7 < 3.5 Cs-137 -0.3 +/- 1.8 < 3.3 1.4 +/- 1.7 < 3.5 Ba-La-140 1.2+/-1.4 < 8.1 0.6 +/- 1.4 < 2.2 Location S-7 S-8 S-9 S-10 Collection Date 07-03-18 07-03-18 07-03-18 07-03-18 Lab Code NFa NFa NFa NFa Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-11 S-12 S-13 S-1 Collection Date 07-03-18 07-03-18 07-03-18 08-14-18 Lab Code NFa NFa NFa EWW- 3294 Be-7 -18.6 +/- 23.7 < 46.8 Mn-54 1.3 +/- 2.4 < 2.5 Fe-59 3.6 +/- 4.5 < 8.4 Co-58 -1.6 +/- 2.3 < 3.8 Co-60 -1.7 +/- 2.4 < 2.2 Zn-65 -5.5 +/- 4.8 < 2.5 Zr-Nb-95 0.0 +/- 2.5 < 3.9 Cs-134 -0.2 +/- 2.5 < 4.9 Cs-137 -2.6 +/- 2.6 < 2.3 Ba-La-140 -5.0 +/- 3.4 < 2.8 13-8

POINT BEACH NUCLEAR PLANT Beach Drains (cont.) Units: =pCi\L Gamma isotopic analysis Location S-3 S-7 S-8 S-9 Collection Date 08-14-18 08-14-18 08-14-18 08-14-18 Lab Code EWVV- 3295 MDC NFa MDC EWVV- 3296 MDC NFa MDC Be-7 15.4 +/- 23.9 < 43.5 6.4 +/- 27.6 < 49.0 Mn-54 0.1 +/- 2.6 < 4.9 0.2 +/- 3.2 < 3.0 Fe-59 0.8 +/- 3.8 < 6.4 -2.7 +/- 6.1 < 10.4 Co-58 -0.4 +/- 2.1 < 3.3 -0.2 +/- 2.9 < 5.5 Co-60 -2.2 +/- 2.8 < 2.8 -1.9 +/- 3.8 < 5.7 Zn-65 1.9 +/- 5.5 < 8.1 -14.1 +/- 8.8 < 13.9 Zr-Nb-95 -2.4 +/- 2.5 < 4.1 -8.4 +/- 4.0 < 7.1 Cs-134 -0.6 +/- 2.3 < 4.3 1.2 +/- 3.1 < 5.6 Cs-137 -1.8 +/- 2.8 < 3.1 -0.9 +/- 3.5 < 3.6 Ba-La-140 -2.1 +/- 3.4 < 6.7 3.5 +/- 3.7 < 8.1 Location S-10 S-11 S-12 S-13 Collection Date 08-14-18 08-14-18 08-14-18 08-14-18 Lab Code NFa NFa NFa NFa Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-1 S-3 S-7 S-8 Collection Date 09-04-18 09-04-18 09-04-18 09-04-18 Lab Code EWW- 36" MDC EWVV- 3620 MDC NFa MDC NFa MDC Be-7 -6.4 +/- 25.7 < 47.1 13.2 +/- 16 1 < 40.3 Mn-54 2.4 +/- 2.8 < 5.4 -0.7 +/- 1.8 < 2.9 Fe-59 -1.0+/-4.1 < 7.3 -3 7 +/- 3.1 < 4.2 Co-58 -0.1 +/- 2.4 < 2.6 -0.4 +/- 1.3 < 2.4 Co-60 -0.7 +/- 3.4 < 3.4 -0.2 +/- 2.0 < 2.8 Zn-65 -8.0 +/- 5.3 < 4.7 -3.7 +/- 3.6 < 3.6 Zr-Nb-95 -0.9 +/- 2.7 < 4.7 -2.3 +/- 1.8 < 3.5 Cs-134 -1.6 +/- 2.7 < 5.0 -0.2 +/- 1.7 < 3.3 Cs-137 -1.1 +/-2.9 < 3.0 -03 +/- 1.8 < 3.0 Ba-La-140 0.1 +/- 3.1 < 3.2 -5.0 +/- 1.9 < 3.2 a NF" =No flow. 13-9

POINT BEACH NUCLEAR PLANT Location S-9 S-10 S-11 S-12 Collection Date 09-04-18 09-04-18 09-04-18 09-04-18 Lab Code EWW- 3621 MDC NFa MDC NFa MDC NFa MDC Be-7 6.5 +/- 14.3 < 34.8 Mn-54 0.6 +/- 1.3 < 2.1 Fe-59 0.3 +/- 2.8 < 3.4 Co-58 0.9 +/- 1.3 < 2.1 Co-60 1.1 +/- 1.5 < 2.0 Zn-65 2.4 +/- 2.5 < 1.4 Zr-Nb-95 2.1 +/- 1.7 < 4.1 Cs-134 -1.5 +/- 1.5 < 3.0 Cs-137 -0.4 +/- 1. 7 < 2.8 Ba-La-140 0.9 +/- 1.8 < 4.5 Location S-13 S-1 S-3 S-7 Collection Date 09-04-18 10-01-18 10-01-18 10-01-18 Lab Code EWW- 3622 MDC EWW- 4081 MDC EWW- 4082 MDC NFa Be-7 -6.9 +/- 12.0 < 22.0 -6.1 +/- 22.1 < 53.5 0.6 +/- 15.1 < 37.6 Mn-54 2.0 +/- 1.3 < 2.2 ~0.7 +/- 2.0 < 1.9 0.3 +/- 1.6 < 3.1 Fe-59 -0.9 +/- 2.7 < 5.0 -0.5 +/- 4.0 < 5.3 4.0 +/- 3.3 < 8.2 Co-58 0.1 +/-1.3 < 2.3 -0.2 +/- 2.0 < 2.7 -0.3 +/- 1.6 < 2.6 Co-60 0.6 +/- 1.4 < 2.6 -0.8 +/- 1.8 < 2.0 1.3 +/- 1.8 < 1.7 Zn-65 0.9 +/- 2.6 < 3.7 -3.2 +/- 5.1 < 3.2 0.3 +/- 3.4 < 7.0 Zr-Nb-95 -2.6 +/- 1.5 < 2.1 -1.7 +/-2.5 < 6.0 1.2 +/- 1.7 < 4.0 Cs-134 0.8 +/- 1.3 < 2.6 -2.7 +/- 2.3 < 4.4 0.0 +/- 1.5 < 2.5 Cs-137 -0.7+/-1.7 < 2.3 -1.4+/-2.1 < 2.3 1.5 +/- 1.7 < 2.7 Ba-La-140 1.1 +/-1.4 < 4.0 1.6 +/- 2.3 < 7.5 -3.1 +/- 1.8 < 4.6 Location S-8 S-9 S-10 S-11 Collection Date 10-01-18 10-01-18 10-01-18 10-01-18 Lab Code NFa NFa NFa NFa Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 13-10

POINT BEACH NUCLEAR PLANT Units: =pCi\L Gamma isotopic analysis Location S-12 S-13 S-1 S-3 Collection Date 10-01-18 10-01-18 11-07-18 11-07-18 Lab Code NFa NFa EWW- 4781 MDC EWW- 4782 MDC Be-7 -4.7 +/- 14.0 < 26.4 10.9 +/- 13.8 < 30.1 Mn-54 0.2 +/- 1.8 < 2.9 -1.0 +/- 1.6 < 1.6 Fe-59 -1.0 +/- 2.8 < 3.9 -1.9 +/- 2.3 < 3.4 Co-58 1.4 +/- 1.8 < 3.4 0.8 +/- 1.5 < 2.7 Co-60 -0.9 +/- 1.8 < 1. 7 0.7 +/- 1.4 < 2.3 Zn-65 1.4 +/- 3.6 < 4.1 -0.4 +/- 2.7 < 2.9 Zr-Nb-95 -0.1 +/- 2.2 < 3.2 -1.2 +/- 1. 7 < 2.4 Cs-134 0.4 +/- 1.8 < 3.2 01 +/- 1.8 < 3.3 Cs-137 0.7 +/- 2 1 < 2.6 -0.4 +/- 2.0 < 2.7 Ba-La-140 0.5 +/- 2.2 < 2.7 -0 7 +/- 1.5 < 4.1 Location S-7 S-8 S-9 S-10 Collection Date 11-07-18 11-07-18 11-07-18 11-07-18 Lab Code NFa NFa NFa NFa Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-11 S-12 S-13 S-1 Collection Date 11-07-18 11-07-18 11-07-18 12-04-18 Lab Code NFa NFa NFa EWN- 5089 Be-7 -9.3 +/- 12.0 < 24.3 Mn-54 1.1 +/- 1.3 < 2.1 Fe-59 1.5 +/- 3.2 < 5.4 Co-58 0.8 +/- 1.5 < 2.7 Co-60 1.2+/-1.7 < 1.5 Zn-65 0.1 +/- 3.2 < 4.5 Zr-Nb-95 -0.4 +/- 1.9 < 3.2 Cs-134 0.0 +/- 1.8 < 3.2 Cs-137 1.0 +/- 2.1 < 4.0 Ba-La-140 -2.2 +/- 2.2 < 3.6 13-11

POINT BEACH NUCLEAR PLANT Beach Drains (cont.) Units: = pCi\L Gamma isotopic analysis Location S-3 S-7 S-8 S-9 Collection Date 12-04-18 12-04-18 12-04-18 Lab Code NFa NFa NFa MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-10 S-11 S-12 S-13 Collection Date 12-04-18 12-14-18 12-04-18 12-04-18 Lab Code NFa NFa NFa NFa Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 13-12

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Quarterly Collections) Units = pCi/L Quarterl~ Wells Sample ID GW-05 {WH 6 Well} GW-06 (SBCC Well) Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-31-18 EWW- 347 -47 +/- 69 < 154 01-31-18 EWW- 349 -22 +/- 71 < 154 04-11-18 EWW- 1195 -4 +/- 97 < 161 04-11-18 EWW- 1196 -45 +/- 95 < 161 07-17-18 EWW- 2761 -15 +/- 72 < 156 07-17-18 EWW- 2762 29 +/-74 < 156 10-19-18 EWW- 4501 -33 +/- 68 < 150 10-19-18 EWW- 4502 -14 +/- 69 < 150 Mean+/- s.d. -25 +/- 19 Mean+/- s.d. -13 +/- 31 Sample ID GW-11 {MW-1) GW-12 (MW-2) Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-25-18 EWW- 351 73 +/- 77 < 154 01-25-18 EWW- 352 -16 +/- 71 < 154 05-15-18 EWW- 1917 222 +/- 86 < 158 05-15-18 EWW- 1918 -28 +/- 72 < 158 07-18-18 EWW- 2978 64 +/- 75 < 152 07-18-18 EWW- 2979 32 +/- 74 < 152 10-14-18 EWW-4383 197 +/- 81 < 150 10-14-18 EWW- 4384 12 +/- 70 < 150 Mean+/- s.d. 139 +/- 82 Mean+/- s.d. 0 +/-27 Sample ID GW-13 (MW-6) GW-14A (MW-05A) Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-25-18 EWW- 353 84 +/- 77 < 154 01-25-18 EWW- 354 67 +/- 76 < 154 05-15-18 EWW-1919 78 +/- 78 < 158 05-15-18 EWW- 1920 188 +/- 84 < 158 07-18-18 EWW- 2981 20 +/- 73 < 152 07-18-18 EWW- 2982 77 +/- 76 < 152 10-14-18 EWW- 4385 16 +/- 71 < 150 10-14-18 EWW- 4386 56+/- 73 < 150 Mean+/- s.d. 49 +/- 37 Mean+/- s.d. 97 +/- 61 SameleiD GW-15A {MW-4~ GW-158 (MW-4) Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-25-18 EWW- 355 52+/- 75 < 154 01-25-18 EWW- 356 139 +/- 80 < 154 05-15-18 EWW- 1921 123 +/- 80 < 158 05-15-18 EWW- 1922 145 +/- 82 < 158 07-18-18 EWW- 2983 104 +/- 78 < 152 07-18-18 EWW- 2984 209 +/- 83 < 152 10-14-18 EWW- 4387 66 +/- 74 < 150 10-14-18 EWW- 4388 60 +/- 73 < 150 Mean+/- s.d. 86 +/- 33 Mean+/- s.d. 138 +/- 61 Sample ID GW-16A (MW-3) GW-168 (MW-3) Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-25-18 NSa 01-25-18 NSa 05-15-18 EWW-1923 227 +/- 86 < 158 07-18-18 EWW- 2985 129 +/- 79 < 152 10-14-18 EWW-4389 264 +/- 84 < 150 Mean+/- s.d. a "NS" =No sample; well cap frozen. 13- 13

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Quarterly Collections) Units = pCi/L Quarterly Wells (cont.) Sample ID GW-18 (WH 7 Well) Collection Date Lab Code Tritium MDC 01-31-18 EWW- 350 -37 +/- 70 < 154 04-11-18 EWW-1197 -88 +/- 93 < 161 07-18-18 EWW- 2763 -13 +/- 72 < 156 10-19-18 EWW-4503 64 +/- 73 < 150 Mean+/- s.d. -18 +/- 63 Fac;ade Wells Sample ID GW-09 1 Z-361A GW-09 1Z-361 8 Collection MDC Collection MDC Date Lab Code Tritium Date Lab Code Tritium 03-16-18 EWW-1081 150 +/- 104 < 161 03-16-18 EWW- 1083 -13 +/- 97 < 161 05-27-18 EWW- 2078 911 +/- 114 < 151 05-27-18 EWW- 2079 4486 +/- 210 < 151 07-11-18 EWW- 2700 182 +/- 82 < 153 07-11-18 EWW- 2701 130 +/- 79 < 153 08-09-18 EWW- 3301 176 +/- 80 < 151 08-09-18 EWW- 3302 113+/-77 < 151 10-13-18 EWW- 4377 199 +/- 81 < 150 10-13-18 EWW- 4378 104 +/- 76 < 150 Mean+/- s.d. 324 +/- 329 Mean+/- s.d. 964 +/- 1970 Sample ID GW-10 2Z-361A GW-10 2Z-361 B Collection MDC Collection MDC Date Lab Code Tritium Date Lab Code Tritium 03-16-18 EWW-1084 9 +/- 98 < 161 03-16-18 EWW- 1085 -19 +/- 97 < 161 05-27-18 EWW- 2080 2742 +/- 170 < 151 05-27-18 EWW- 2081 168 +/- 82 < 151 07-11-18 EWW- 2702 36 +/- 74 < 153 07-11-18 EWW- 2703 56+/- 75 < 153 08-09-18 EWW- 3304 33 +/- 72 < 151 08-09-18 EWW- 3305 113 +/- 77 < 151 10-*13-18 EWW- 4379 7 +/- 70 < 150 10-13-18 EWW-4380 127 +/- 77 < 150 Mean+/- s.d. 565 +/- 1217 Mean+/- s.d. 89 +/-73 {Annual Collections) Units = pCi/L Bogs Sample ID GW-07 (North Bog~ GW-08 EIC Boa Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 05-22-18 EWW- 1979 164 +/- 82 < 158 05-22-18 EWW-1980 263 +/- 88 < 158 a Repeat result = 786 +/- 109 pCi/L b Repeat result = 4197 +/- 202 pCi/L c Repeat result= 2731 +/-168 pCi/L I 13- 14 I

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program Units = pCi/L Manholes Sample ID MH Z-065A MH Z-0658 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCill) Date (pCi/L) 05-07-18 NSa 05-07-18 NS 8 09-13-18 EWW-3859 240 +/- 84 < 154 09-13-18 EWW- 3860 215 +/- 83 < 154 Mean+/- s.d. Mean+/- s.d. Samele ID MH Z-065C MH Z-065D Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 05-07-18 NSa 05-07-18 NSa 09-13-18 NSa 09-13-18 NSa Mean+/- s.d. Mean+/- s.d. samele ID MH Z-066A MH Z-0668 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCill) Date (pCi/L) 05-07-18 EWW- 1770 331 +/- 91 < 159 05-07-18 EWW- 1771 247 +/- 87 < 159 09-12-18 EWW- 3861 165 +/- 80 < 154 09-12-18 EWW- 3862 213 +/- 83 < 154 Mean+/- s.d. 248 +/- 118 Mean+/- s.d. 230 +/- 24 Sample ID MH Z-066C MH Z-066D Collection MDC Collection MDC Lab Code Tritium (pCi/L) Lab Code Tritium Date Date (pCi/L) 05-07-18 EWW- 1772 376 +/- 93 < 159 05-07-18 EWW- 1773 361 +/- 92 < 159 09-12-18 EWW- 3863 415 +/- 93 < 154 09-12-18 EWW- 3864 158 +/- 80 < 154 Mean +/-s.d. 396 +/- 27 Mean+/- s.d. 260 +/- 143 samere ID MH Z-067A MH Z-0678 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 05-07-18 EWW- 1774 465 +/- 97 < 159 05-07-18 EWW-1775 197 +/- 84 < 159 09-12-18 EWW- 3865 236 +/- 84 < 154 09-12-18 EWW- 3866 243 +/- 84 < 154 Mean+/- s.d. 351 +/- 162 Mean+/- s.d. 220 +/- 32 a "NS" = No sample; not sent. 13-15

POINT BEACH NUCLEAR PLANT Manholes (cont.) Sam121e ID MH Z-067C MH Z-067D Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 05-07-18 EWW- 1776 210 +/- 85 < 159 05-07-18 EWW- 1777 123 +/- 80 < 159 09-12-18 EWW- 3867 137 +/- 79 < 154 09-12-18 EWW- 3868 217 +/- 83 < 154 Mean+/- s.d. 174 +/-51 Mean+/- s.d. 170 +/-67 Sample ID MH Z-068 MH-1 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 8 05-07-18 EWW- 1778 240 +/- 87 < 159 05-07-18 NS 8 09-12-18 EWW- 3869 32 +/- 73 < 154 09-12-18 NS Mean+/- s.d. 136 +/- 147 Mean+/- s.d. Sample ID MH-4 MH-6 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 05-07-18 NS 8 05-07-18 NSa 8 8 09-12-18 NS 09-12-18 NS Mean+/- s.d. Mean+/- s.d. Samele ID MH-7 MH-8 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 8 8 05-07-18 NS 05-07-18 NS 8 8 09-12-18 NS 09-12-18 NS Mean+/- s.d. Mean+/- s.d. Sample ID MH-16 MH-2 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date {pCi/L) 8 8 05-07-18 NS 05-07-18 NS 8 8 09-12-18 NS 09-12-18 NS Mean+/- s.d. Mean+/- s.d. f Samele ID MH-SA MH-9 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium I Date (pCi/L) Date (pCi/L) 8 8 05-07-18 NS 05-07-18 NS 09-12-18 NSa 09-12-18 NSa r Mean+/- s.d. Mean+/- s.d a "NS" = No sample; not sent.

~=

13-16 ,,

POINT BEACH NUCLEAR PLANT Table 14. Radioactivity in vegetation samples Collection: Annual Sample Description and Concentration (pCi/g wet) MDC MDC MDC Location E-F1A E-F1B E-F2 Collection Date 09-10-18 09-10-18 09-10-18 Lab Code EVE- 3717 EVE- 3718 EVE- 3719 Req. LLD Type Alfalfa Soybeans Corn Be-7 2.398 +/- 0.272 2.01 +/- 0.22 1.32 +/- 0.16 K-40 6.52 +/- 0.50 3.49 +/- 0.37 2.44 +/- 0.25 1-131 0.002 +/- 0.008 < 0.017 -0.005 +/- 0.008 < 0.028 -0 008 +/- 0.005 < 0.019 0.060 Cs-134 0.002 +/- 0.008 < 0.015 0.000 +/- 0.007 < 0.014 -0 003 +/- 0.005 < 0.009 0.060 Cs-137 0.000 +/- 0.010 < 0.020 0.004 +/- 0.009 < 0.016 -0.003 +/- 0.006 < 0.007 0.080 Other (Co-60) -0.010 +/- 0.011 < 0.008 0.007 +/- 0.009 < 0.011 0.001 +/- 0.005 < 0.005 0.060 Location E-F3 E-F4 E-F5 Collection Date 09-10-18 09-10-18 09-10-18 Lab Code EVE- 3720 EVE- 3721 EVE- 3722 Req. LLD Type Corn Corn Soybeans Be-7 1.26 +/- 0.17 1.172 +/- 0.157 2.535 +/- 0.237 K-40 2.39 +/- 0.25 2.32 +/- 0.24 3.07 +/- 0.30 1-131 -0.007 +/- 0.007 < 0.014 -0.006 +/- 0.005 < 0.014 0.001 +/- 0.006 < 0.025 0.060 Cs-134 -0.002 +/- 0.005 < 0.010 0.000 +/- 0.005 < 0.009 -0.002 +/- 0.006 < 0.011 0.060 Cs-137 -0 002 +/- 0.006 < 0.010 0.004 +/- 0.005 < 0.009 0.003 +/- 0.007 < 0.012 0.080 Other (Co-60) 0.003 +/- 0.006 < 0.008 0.003 +/- 0.006 < 0.004 0.001 +/- 0.007 < 0.009 0.060 Location E-F6 E-F7 E-F8 Collection Date 09-10-18 09-10-18 09-10-18 Lab Code EVE- 3723 EVE- 3724 EVE- 3726 Req. LLD Type Soybeans Corn Alfalfa Be-7 2.820 +/- 0.264 0.737 +/- 0.164 0.92 +/- 0.14 K-40 3.27 +/- 0.32 3.00 +/- 0.30 4.96 +/- 0.35 1-131 -0.015 +/- 0.008 < 0.033 0.005 +/- 0.006 < 0.025 0.005 +/- 0.005 < 0.022 0.060 Cs-134 -0.003 +/- 0.006 < 0.013 0.003 +/- 0.007 < 0.014 0.002 +/- 0.005 < 0.009 0.060 Cs-137 -0.004 +/- 0.007 < 0.010 0.001 +/- 0.007 < 0.008 0.007 +/- 0.007 < 0.012 0.080 Other (Co-60) 0.001 +/- 0.007 < 0.006 -o.oo*1 +/- o.oo7 < 0.006 0.003 +/- 0.006 < 0.008 0.060 a Gross beta reanalyzed. 14-1

POINT BEACH NUCLEAR PLANT Table 14. Radioactivity in vegetation samples Collection: Annual Sample Description and Concentration (pCi/g wet) MDC MDC MDC Location E-F9 Collection Date 09-10-18 Lab Code EVE- 3727 Req. LLD Type Corn Be-7 1.266 +/- 0 146 K-40 1.89 +/- 0.21 1-131 -0.015 +/- 0.004 < 0.015 0.060 Cs-134 -0.002 +/- 0.005 < 0.007 0.060 Cs-137 0.004 +/- 0.005 < 0.008 0.080 Other (Co-60) 0.001 +/- 0.005 < 0.008 0.060 Beta Annual Mean +/- s.d. 0.00 +/- 0.00 Be- 7 Annual Mean +/- s.d. 1.64 +/- 0.73 K-40 Annual Mean +/- s.d. 3.33 +/- 1.41 1-131 Annual Mean +/- s.d. -0.004 +/- 0.007 Cs-134 Annual Mean +/- s.d. -0.001 +/- 0.002 Cs-137 Annual Mean+/- s.d. 0.001 +/- 0.003 Co-60 Annual Mean +/- s.d. 0.001 +/- 0.004 14-2

.ll+L A.

7+"'"'1 II Midwest Environmental, Inc. Laboratory 700 Landwehr Road

Northbrook. IL 60082*2310 p/)(JnfJ (847) 564*0700
fax (847) 564*4f.i17 APPENDIX A INTERLABORATORY AND INTRALABORATORY COMPARISON PROGRAM RESULTS NOTE: Appendix A is updated four times a year. The complete appendix is included in March, June, September and December monthly progress reports only.

January, 2018 through December, 2018

Appendix A Interlaboratory/ lntralaboratorv 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 radio nuclides 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. Table A-1 lists results that were obtained through participation in the RAD PT Study Proficiency Testing Program administered by Environmental Resource 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 irradiation and evaluation by the University of Wisconsin-Madison Radiation Calibration Laboratory at the University of Wisconsin Medical Radiation Research Center. Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Acceptance criteria is detailed on Attachment A page A2. 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 analytical results from the in-house "duplicate" program for the past twelve months. The Precision Acceptance limit is +/-25% of the mean for Sr-89,90, Gross Alpha and Gross Beta or the 2-sigma uncertainty overlaps the mean value. For all other analytes the precision acceptance limit is +/-20% of the mean or the 2-sigma uncertainty overlaps the mean value. Complete analytical data for duplicate analyses is available upon request. Table A-6 list results that were obtained through pa1iicipation in the Mixed Analyte Performance Evaluation Program. Table A-7 lists results that were obtained through participation in the MRAD PT Study Proficiency Testing Progra1 administered by Environmental Resource Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML). Out-of-limit results are explained directly below the result. A1

Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES Analysis Ratio of lab result to known value. Gamma Emitters 0.8 to 1.2 Strontium-89, 0.8 to 1.2 Strontium-90 Potassium-40 0.8 to 1.2 Gross alpha 0.5 to 1.5 Gross beta 0.8 to 1.2 Tritium 0.8 to 1.2 Radium-226, 0.7 to 1.3 Radium-228 Plutonium 0.8 to 1.2 lodine-129, 0.8 to 1.2 lodine-131 Nickel-63, 0.7to 1.3 Technetium-99, Uranium--238 0.8to1.2 Other Analyses 0.8 to 1.2 A2

8 TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) . RAD study Concentration (pCi/L) Lab Code Reference Analysis Laboratory ERA Control Date Result Result Limits Acceptance ERW-52 1/8/2018 Sr-89 61.6 +/- 5.8 65.2 52.9 -73.2 Pass ERW-52 1/8/2018 Sr-90 39.7 +/- 2.3 39.2 28.2 -45.1 Pass ERW-54 1/8/2018 Ba-133 89.7 +/- 4.7 95.1 80.2 -105 Pass ERW-54 1/8/2018 Cs-134 62.1 +/- 5.4 65.6 53.4-72.2 Pass ERW-54 1/8/2018 Cs-137 111.2 +/- 6.1 112 101 -126 Pass ERW-54 1/8/2018 Co-60 115.8 +/- 4.7 114.0 103.0 - 128.0 Pass ERW-54 1/8/2018 Zn-65 292.2 +/- 14.0 277.0 249 -324 Pass ERW-52 1/8/2018 Gr. Alpha 70.1 +/- 3.0 72.4 38.1 -89.2 Pass ERW-52 1/8/2018 Gr. Beta 47.4 +/- 1.4 54.8 37.5 -61.7 Pass ERW-58 1/8/2018 1-131 25.3 +/- 1.0 28.1 23.4-33.0 Pass ERW-61 1/8/2018 Ra-226 12.4 +/- 0.4 14.20 10.60 - 16.30 Pass ERW-60 1/8/2018 Ra-228 4.9 +/- 0.8 4.21 2.43 - 5.81 Pass ERW-60 1/8/2018 Uranium 52.2 +/- 0.9 58.6 47.8-64.5 Pass ERW-62 1/8/2018 H-3 21,780 +/- 437 21,200 18,600 - 23,300 Pass ERW-2555 7/9/2018 Sr-89 62.8 +/- 4.0 62.7 50.7-70.6 Pass ERW-2555 7/9/2018 Sr-90 40.1 +/- 1.3 40.1 29.5 -46.1 Pass ERW-2557 7/9/2018 Ba-133 23.1 +/-2.3 25.6 19.9 -29 Pass ERW-2557 7/9/2018 Cs-134 15.2+/-1.7 15.7 11.4 -18.2 Pass ERW-2557 7/9/2018 Cs-137 22.3 +/- 4.9 192 173-213 Failb ERW-2557 7/9/2018 Co-60 110.4 +/-3.7 119.0 107 - 133 Pass ERW-2557 7/9/2018 Zn-65 189.5 +/-7.5 177.0 159-208 Pass ERW-2559 7/9/2018 Gr. Alpha 13.5 +/- 0.7 16.0 7.79 - 22.6 Pass ERW-2559 7/9/2018 Gr. Beta 41.1 +/- 0.9 49.0 33.2 -56.1 Pass ERW-2561 7/9/2018 1-131 24.9 +/- 0.9 28.1 23.4 -33.0 Pass ERW-2563 7/9/2018 Ra-226 9.0 +/- 0.3 9.08 6.81 - 10.6 Pass ERW-2563 7/9/2018 Ra-228 3.2 +/- 0.4 2.28 1.07 -3.60 Pass ERW**2563 7/9/2018 Uranium 38.2 +/- 1.4 51.8 42.2 -57.1 Faile ERW-2565 7/9/2018 H-3 21,039 +/- 302 20,400 17,900 - 22,400 Pass ERW-3832b 10/7/2016 Ba-i33 57.0 +/- 3.1 54.9 45- 6*1 Pass ERW-3832b 10/7/2016 Cs-*134 79.2 +/- 3.0 81.8 67-90 Pass ERW-3832b 10/7/2016 CS**'137 222.4 +/- 4.5 210 189-233 Pass ERW-3832b 10/7/2016 Co~60 67.7 +/- 3.5 64.5 58 -73 Pass ERW-3832b 10/7/2016 Zn-65 274.1 +/- 3.0 245 220-287 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 Resource Associates (ERA). b A transcription error caused the Cs-137 result submitted to be understated by a factor of 10. The actual result obtained was slightly higher than the acceptance criteria for the study. A "Quick Response" proficiency test was analyzed to help determine the cause of the high result. (See ERW-3832 above) No definitive cause for the previous high Cs-137 result was determined. c An investigation is underway to determine the reason for the unacceptable Uranium PT result. Al-l

a TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaS0 4: Dy Cards). mrem Lab Code Irradiation Delivered Reported Performance c Date Description Dose Dose Quotient (P) Environmental. Inc. Group 1 2018-1 11/15/2018 Spike 1 97.0 81.6 -0.16 2018-1 11/15/2018 Spike 2 97.0 88.5 -0.09 2018-1 11/15/2018 Spike 3 97.0 87.9 -0.09 2018-1 11/15/2018 Spike 4 97.0 85.6 -0.12 2018-1 11/15/2018 Spike 5 97.0 86.5 -0.11 2018-1 11/15/2018 Spike 6 97.0 89.0 -0.08 2018-1 11/15/2018 Spike 7 97.0 85.1 -0.12 2018-1 11/15/2018 Spike 8 97.0 90.6 -0.07 2018-1 11/15/2018 Spike 9 97.0 91.3 -0.06 2018-1 11/15/2018 Spike 10 97.0 84.5 -0.13 2018-1 11/15/2018 Spike 11 97.0 90.8 -0.06 2018-1 11/15/2018 Spike 12 97.0 93.8 -0.03 2018-1 11/15/2018 Spike 13 97.0 85.3 -0.12 2018-1 11/15/2018 Spike 14 97.0 85.5 -0.12 2018-1 11/15/2018 Spike 15 97.0 86.9 -0.10 2018-1 11/15/2018 Spike 16 97.0 88.6 -0.09 2018-1 11/15/2018 Spike 17 97.0 83.1 -0.14 2018-1 11/15/2018 Spike 18 97.0 85.4 -0.12 2018-1 11/15/2018 Spike 19 97.0 83.3 -0.14 2018-1 11/15/2018 Spike 20 97.0 85.5 -0.12 Mean (Spike 1-20) 86.9 -0.10 Passd Standard Deviation (Spike 1-20) 3.1 0.03 Passd a TLD's were irradiated by the Univeisity of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose. b Reported dose was converted from exposure (R) to Air Kerma (cGy) using a conversion of 0.876. Conversion from air kerma to ambient dose equivalent for Cs-137 at the reference dose point H*(1 O)Ka = 1.20 . mrem/cGy = 1000. c Performance Quotient (P) is calculated as ((reported dose- conventially true value) + conventially true value) where the conventially true value is the delivered dose. d Acceptance is achieved when neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15. A2-1

a TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaS0 4 : Dy Cards). mrem b Lab Code Irradiation Delivered Reported Performance c Date Description Dose Dose Quotient (P) Environmental. Inc. Group 2 2018-2 11/15/2018 Spike 21 143.0 130.3 -0.09 2018-2 11/15/2018 Spike 22 143.0 128.1 -0.10 2018-2 11/15/2018 Spike 23 143.0 134.4 -0.06 2018-2 11/15/2018 Spike 24 143.0 129.0 -0.10 2018-2 11/15/2018 Spike 25 143.0 132.5 -0.07 2018-2 11/15/2018 Spike 26 143.0 126.1 -0.12 2018-2 11/15/2018 Spike 27 143.0 126.2 -0.12 2018-2 11/15/2018 Spike 28 143.0 122.4 -0.14 2018-2 11/15/2018 Spike 29 143.0 118.8 -0.17 2018-2 11/15/2018 Spike 30 143.0 123.2 -0.14 2018-2 11/15/2018 Spike 31 143.0 137.2 -0.04 2018-2 11/15/2018 Spike 32 143.0 144.4 0.01 2018-2 11/15/2018 Spike 33 143.0 137.8 -0.04 2018-2 11/15/2018 Spike 34 143.0 140.2 -0.02 2018-2 11/15/2018 Spike 35 143.0 143.8 0.01 2018-2 11/15/2018 Spike 36 143.0 146.7 0.03 2018-2 11/15/2018 Spike 37 143.0 150.0 0.05 2018-2 11/15/2018 Spike 38 143.0 126.1 -0.12 2018-2 11/15/2018 Spike 39 143.0 136.2 -0.05 2018-2 11/15/2018 Spike 40 143.0 144.8 0.01 Mean (Spike 21-40) 133.9 -0.06 Passd Standard Deviation (Spike 21-40) 9.0 0.06 Passd a TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13.37

 !Jrotocol from a known air karma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-l'v1adison Radiation Calibration Laboratory for comparison to the delivered dose.

b Reported dose was convetied from exposure (R} to Air Kerma (cGy} using a conversion of 0.876. Conversion from air kerma to ambient dose equivalent for Cs-137 at the reference dose point H*(10)Ka = 1.20. mrem/cGy =1000. c Performance Quotient (P} is calculated as ((reported dose- conventially true value} + conventially true value} where the conventially true value is the delivered dose. d Acceptance is achieved when neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15. A2-2

TABLE A-3. In-House "Spiked" Samples Concentration a Lab Code b Date Analysis Laboratory results Known Control Ratio 2s, n=1 c Activity Limits d Acceptance Lab/Known SPW-1749 4/21/2016 Fe-55 1,576 +/-81 1,482 1,186 -1,778 Pass 1.06 SPW-95 1/11/2018 H-3 16,457 +/- 381 16,507 13,206 - 19,808 Pass 1.00 SPW-109 1/12/2018 Sr-90 18.9 +/- 1.7 17.9 14.3-21.5 Pass 1.06 SPW-175 1/19/2018 H-3 16,261 +/- 382 16,507 13,206- 19,808 Pass 0.99 SPW-210 1/23/2018 H-3 16,461 +/- 382 16,507 13,206 - 19,808 Pass 1.00 SPW-212 1/10/2018 Ra-226 12.9 +/- 0.4 12.3 8.6 - 16.0 Pass 1.05 SPW-272 1/30/2018 H-3 16,607 +/- 384 16,507 13,206 - 19,808 Pass 1.01 W-013118 4/29/2016 Cs-134 33.9 +/- 7.4 36.2 29.0 -43.4 Pass 0.94 W-013118 4/29/2016 Cs-137 80.0 +/- 7.9 71.9 57.5 -86.3 Pass 1.11 SPW-330 2/1/2018 Ni-63 168 +/- 2 198 139-258 Pass 0.85 SPW-338 2/2/2018 H-3 16,512 +/- 381 16,507 13,206- 19,808 Pass 1.00 SPW-384 2/6/2018 H-3 16,429 +/- 380 16,507 13,206 - 19,808 Pass 1.00 W-020618 4/29/2016 Cs-134 39.0 +/- 12.0 36.2 29.0 -43.4 Pass 1.08 W-020618 4/29/2016 Cs-137 81.0+/-15.7 71.9 57.5-86.3 Pass 1.13 SPW-461 2/13/2018 H-3 16,799 +/- 385 16,507 13,206 - 19,808 Pass 1.02 SPW-516 2/19/2018 H-3 16,323 +/- 382 16,507 13,206 - 19,808 Pass 0.99 SPW-556 2/8/2018 Ra-226 12.2 +/- 0.3 12.3 8.6- 16.0 Pass 0.99 SPW-582 2/22/2018 H-3 16,200 +/- 380 16,507 13,206 - 19,808 Pass 0.98 SPW-609 2/23/2018 H-3 16,467 +/- 383 16,507 13,206 - 19,808 Pass 1.00 SPW-650 2/21/2018 Ra-226 11.8 +/- 0.5 12.3 8.6 - 16.0 Pass 0.96 SPW-666 2/28/2018 Gr. Alpha 67.1 +/- 2.8 72.4 36.2 - 108.6 Pass 0.93 SPW-666 2/28/2018 Gr. Beta 48.1 +/- 1.4 54.8 43.8-65.8 Pass 0.88 W-022818 4/29/2016 Cs-134 32.7 +/- 8.5 36.2 29.0 -43.4 Pass 0.90 W-022818 4/29/2016 Cs-137 73.8 +/- 9.3 71.9 57.5-86.3 Pass 1.03 SPW-748 3/6/2018 H-3 16,209 +/- 381 16,507 13,206 - 19,808 Pass 0.98 SPW-787 3/8/2018 H-3 16,934 +/- 388 16,507 13,206 - 19,808 Pass 1.03 W-030718 4/29/2016 Cs-134 33.4 +/- 7.9 36.2 29.0 -43.4 Pass 0.92 W-030718 4/29/2016 Cs-137 78.9 +/- 9.6 71.9 57.5 - 86.3 Pass 1.10 SPW-885 3/15/2018 H-3 16,475 +/-384 16,507 13,206- 19,808 Pass 1.00 SPW-931 3/20/2018 H-3 16,467 +/- 384 16,507 13,206 - 19,808 Pass 1.00 SPW-957 3/12/2018 Ra-226 11.4 +/-0.4 12.3 8.6- 16.0 Pass 0.93 SPW-969 3/23/2018 Ni-63 260 +/- 12 329 230-428 Pass 0.79 W-031418 4/29/2016 Cs-134 36.9 +/- 11.2 36.2 29.0 - 43.4 Pass 1.02 W-031418 4/29/2016 Cs-137 82.3 +/- 15.5 71.9 57.5 - 86.3 Pass 1.14 SPW-985 3/27/2018 H-3 16,544 +/- 386 16,507 13,206 - 19,808 Pass 1.00 SPW-1037 4/4/20'18 H-3 16,298 +/- 384 16,507 13,206 - 19,808 Pass 0.99 SPW-1149 4/12/2018 H-3 16,361 +/- 383 16,507 13,206 - 19,808 Pass 0.99 SPW-1200 4/13/2018 u..238 44.2 +/- 2.3 41.7 29.2 - 54.2 Pass 1.06 SPW-1426 4/20/2018 H-3 16,573 +/- 390 16,507 13,206 -19,808 Pass 1.00 SPW-1454 4/24/20'18 H-3 16,495 +/- 384 16,507 13,206 - 19,808 Pass 1.00 SPW-1493 4/26/2018 Ra-228 4.59 +/- 1.10 4.21 2.95 - 5.47 Pass 1.09 SPW-1518 4/27/2018 H-3 16,483 +/- 382 16,507 13,206 - 19,808 Pass 1.00 SPW-1522 4/27/2018 Tc-99 105 +/-2 108 75- 140 Pass 0.98 W-050118 4/29/2016 Cs-134 35.2 +/- 9.9 36.2 29.0 -43.4 Pass 0.97 W-050118 4/29/2016 Cs-137 82.4 +/- 7.7 71.9 57.5- 86.3 Pass 1.15 A3-1

TABLE A-3. In-House "Spiked" Samples Concentration a Lab Code b Date Analysis Laboratory results Known Control Ratio 2s, n=1 c Activity Limits d Acceptance Lab/Known SPW-1573 5/2/2018 Gr. Alpha 25.2 +/- 0.5 20.1 10.1 -30.2 Pass 1.25 SPW-1573 5/2/2018 Gr. Beta 28.2 +/- 0.3 27.5 22.0 -33.0 Pass 1.03 SPW-1618 5/3/2018 H-3 14,834 +/- 366 16,507 13,206 - 19,808 Pass 0.90 W-050318 4/29/2016 Cs-134 32.9 +/- 7.6 36.2 29.0 - 43.4 Pass 0.91 W-050318 4/29/2016 Cs-137 83.1 +/- 8.5 71.9 57.5 - 86.3 Pass 1.16 SPW-1644 5/4/2018 Sr-90 20.0 +/- 1.3 17.9 14.3-21.5 Pass 1.12 W-050718 4/29/2018 Cs-134 42.4 +/- 8.5 36.2 29.0 -43.4 Pass 1.17 W-050718 4/29/2018 Cs-137 80.6 +/- 13.6 71.9 57.5 - 86.3 Pass 1.12 SPW-1695 5/8/2018 H-3 16,450 +/- 384 16,507 13,206 - 19,808 Pass 1.00 W-050818 4/29/2016 Cs-134 32.3 +/- 6.9 36.2 29.0 - 43.4 Pass 0.89 W-050818 4/29/2016 Cs-137 73.0 +/- 8.2 71.9 57.5 -86.3 Pass 1.02 SPW-1780 5/11/2018 H-3 16,784 +/- 388 16,507 13,206- 19,808 Pass 1.02 W-051518 4/29/2016 Cs-134 33.0 +/- 6.7 36.2 29.0 -43.4 Pass 0.91 W-051518 4/29/2016 Cs-137 76.0 +/- 7.4 71.9 57.5 -86.3 Pass 1.06 W-051718 4/29/2016 Cs-134 35.1 +/- 5.7 36.2 29.0 - 43.4 Pass 0.97 W-051718 4/29/2016 Cs-137 73.7 +/- 6.7 71.9 57.5-86.3 Pass 1.03 SPW-1897 5/18/2018 H-3 16,650 +/- 387 16,507 13,206 - 19,808 Pass 1.01 SPW-1899 5/18/2018 H-3 16,754 +/- 365 16,507 13,206 - 19,808 Pass 1.01 W-052418 4/29/2016 Cs-134 33.9 +/- 6.2 36.2 29.0 -43.4 Pass 0.94 W-052418 4/29/2016 Cs-137 78.8 +/- 7.4 71.9 57.5-86.3 Pass 1.10 SPW-1994 5/24/2018 H-3 16,488 +/- 384 16,507 13,206 - 19,808 Pass 1.00 W-053118 4/29/2016 Cs-134 38.9 +/- 9.5 36.2 29.0 -43.4 Pass 1.07 W-053118 4/29/2016 Cs-137 74.0 +/- 7.5 71.9 57.5-86.3 Pass 1.03 SPW-2042 5/31/2018 H-3 16,901 +/- 390 16,507 13,206 - 19,808 Pass 1.02 W-060518 4/29/2016 Cs-134 33.0+/-10.1 36.2 29.0 -43.4 Pass 0.91 W-060518 4/29/2016 Cs-137 83.3 +/- 8.7 71.9 57.5-86.3 Pass 1.16 SPW-2186 6/6/2018 H-3 16,551 +/- 385 16,507 13,206 -19,808 Pass 1.00 SPW-2914 6/19/2018 Ra-226 12.7 +/- 0.4 12.3 8.6 - 16.0 Pass 1.03 SPW-2437 6/27/2018 Sr-90 18.0 +/- 1.1 17.9 14.3-21.5 Pass 1.00 SPW-2447 6/29/2018 H-3 16,595 +/- 387 16,507 13,206 - 19,808 Pass 1.01 W-070518 4/29/2016 Cs-134 38.9 +/- 8.1 36.2 29.0 - 43.4 Pass 1.08 W-070518 4/29/2016 Cs-137 73.4 +/- 9.4 ?1.9 57.5-86.3 Pass 1.02 SPW-2546 7/10/2018 H-3 15,949 +/- 373 16,507 13,206 - 19,808 Pass 0.97 W-071218 4/29/2016 Cs-134 33.1+/-7.7 36.2 29.0 - 43.4 Pass 0.91 W-071218 4/29/2016 Cs-137 74.5 +/- 7.7 71.9 57.5- 86.3 Pass 1.04 SPW-2706 7116/2018 H*3 15,474.7 +/- 366.6 16,507 '13,206 - 19,808 Pass 0.94 SPVV-2772 7/19/2018 H-3 15,994.0 +/- 314.0 16,507 13,206 - 19,808 Pass 0.97 SPW-2811 7/20/2018 Gr. Alpha 21.1 +/- 0.4 20.1 10.1 - 30.2 Pass 1.05 SPVIJ-2811 7/20/2018 Gr. Beta 26.9 +/- 0.3 27.5 22.0-33.0 Pass 0.98 W-0"/2118 4/29/2016 Cs-134 33.6 +/- 7.3 36.2 29.0 -43.4 Pass 0.93 W-072118 4/29/2016 Cs-137 80.3 +/- 7.9 71.9 57.5-86.3 Pass 1.12 SPW-3689 7/23/2018 Ra-226 12.7 +/- 0.3 12.3 8.6 -16.0 Pass 1.03 W-072718 2/1/2017 U-234 26.8 +/- 3.4 31.4 22.0-40.8 Pass 0.85 W-072718 2/1/2017 U-238 24.1 +/- 3.2 32.4 22.7-42.1 Pass 0.74 SPW-3018 7/31/2018 H-3 16,166 +/- 376 16,507 13,206 - 19,808 Pass 0.98 SPW-3154 8/6/2018 H-3 15,686 +/- 370 16,507 13,206 - 19,808 Pass 0.95 W-081218 4/29/2016 Cs-134 38.6 +/- 11.5 36.2 29.0 -43.4 Pass 1.07 W-081218 4/29/2016 Cs-137 83.7 +/- 13.4 71.9 57.5 -86.3 Pass 1.16 A3-2

TABLE A-3. In-House "Spiked" Samples Concentration a Lab Code b Date Analysis Laboratory results Known Control Ratio 2s, n=1 c Activity Limits d Acceptance Lab/Known SPW-3278 8/16/2018 H-3 15,587 +/- 370 16,507 13,206 -19,808 Pass 0.94 SPW-3378 8/23/2018 Ni-63 378 +/- 44 465 325 -604 Pass 0.81 SPW-3420 8/23/2018 H-3 15,536 +/- 368 16,507 13,206 - 19,808 Pass 0.94 SPW-3691 8/23/2018 Ra-226 15.5 +/- 0.4 12.3 8.6 -16.0 Pass 1.26 SPW-3477 8/27/2018 Ra-228 11.3 +/- 1.6 15.1 10.6-19.7 Pass 0.75 W-082818 4/29/2016 Cs-134 33.0 +/- 2.7 36.2 29.0 -43.4 Pass 0.91 W-082818 4/29/2016 Cs-137 80.7 +/- 3.0 71.9 57.5 - 86.3 Pass 1.12 SPW-3648 9/7/2018 H-3 15,876 +/- 371 16,507 13,206 - 19,808 Pass 0.96 SPW-4755 9/7/2018 Ra-226 11.2 +/- 0.3 12.3 8.6 -16.0 Pass 0.91 W-091118 4/29/2016 Cs-134 35.3 +/- 2.7 36.2 29.0 -43.4 Pass 0.98 W-091118 4/29/2016 Cs-137 80.7 +/- 3.2 71.9 57.5 - 86.3 Pass 1.12 SPW-3843 9/19/2018 H-3 15,759 +/- 372 16,507 13,206 - 19,808 Pass 0.95 W-092818 4/29/2016 Cs-134 36.1 +/- 10.0 36.2 29.0 -43.4 Pass 1.00 W-092818 4/29/2016 Cs-137 73.6 +/- 9.9 71.9 57.5 -86.3 Pass 1.02 SPW-3991 10/1/2018 H-3 15,614 +/- 369 16,507 13,206 -19,808 Pass 0.95 SPW-4105 10/5/2018 H-3 15,669 +/- 370 16,507 13,206 - 19,808 Pass 0.95 W-101118 4/29/2016 Cs-134 33.5 +/- 3.1 36.2 29.0 -43.4 Pass 0.92 W-101118 4/29/2016 Cs-137 79.7 +/- 3.2 71.9 57.5-86.3 Pass 1.11 SPW-4205 10/12/2018 H-3 15,821 +/- 372 16,507 13,206 - 19,808 Pass 0.96 SPW-4274 10/17/2018 H-3 15,575 +/- 369 16,507 13,206 - 19,808 Pass 0.94 SPW-4596 10/31/2018 H-3 15,650 +/- 369 16,507 13,206 - 19,808 Pass 0.95 SPW-4682 11/1/2018 H-3 15,742 +/- 371 16,507 13,206 - 19,808 Pass 0.95 SPW-4684 11/1/2018 Sr-90 19.1 +/- 1.2 17.9 14.3-21.5 Pass 1.07 SPW-4790 11/9/2018 H-3 15,887 +/- 373 16,507 13,206 - 19,808 Pass 0.96 SPW-4839 11/13/2018 Ni-63 381 +/- 43 465 326-605 Pass 0.82 SPW-4863 11/16/2018 H-3 15,610 +/-370 16,507 13,206 - 19,808 Pass 0.95 W-111618 4/29/2016 Cs-134 38.0 +/- 12.4 36.2 29.0 -43.4 Pass 1.05 W-111618 4/29/2016 Cs-137 83.8 +/- 13.8 71.9 57.5 - 86.3 Pass 1.17 SPW-5049 11/30/2018 H-3 15,370 +/- 366 16,507 13,206 - 19,808 Pass 0.93 SPW-5148 12/7/2018 H-3 15,522 +/- 368 16,507 13,206 - 19,808 Pass 0.94 W-121118 4/29/2016 Cs-134 39.4 +/- 7.9 36.2 29.0 - 43.4 Pass 1.09 W-121118 4/29/2016 Cs-*137 78.5 +/- 7.7 71.9 57.5 - 86.3 Pass 1.09 W-121218 4/29/2016 Cs-134 42.0 +/- 13.8 36.2 29.0-43.4 Pass 1.16 W-121218 4/29/2016 CS**137 79.2 +/- 13.1 71.9 57.5 - 86.3 Pass 1.10 VV-121318 4/29/2016 Cs-134 35.1 +/- 7.8 36.2 29.0 - 43.4 Pass 0.97 W-121318 4/29/2016 Cs-137 77.5 +/- 8.4 71.9 57.5 - 86.3 Pass 1.08 SPW-5279 12/14/2018 H-3 15,686 +/- 370 16,507 13,206 - 19,808 Pass 0.95 W-i 21418 4/29/2016 Cs-134 34.5 +/- 8.2 36.2 29.0 - 43.4 Pass 0.95 W**121418 4/29/2016 Cs-137 82.7 +/- 8.0 71.9 57.5 - 86.3 Pass 1.15 W-121718 4/29/2016 Cs-134 34.9 +/- 10.5 36.2 29.0 - 43.4 Pass 0.96 W-121718 4/29/2016 Cs-137 80.3 +/- 8.1 71.9 57.5 -86.3 Pass 1.12 SPW-5351 12/19/2018 H-3 15,855 +/- 375 16,507 13,206 - 19,808 Pass 0.96 SPW-5404 12/31/2018 H-3 15,179 +/- 365 16,507 13,206 - 19,808 Pass 0.92 a Liquid sample results are reported in pCi/Liter, air filters ( pCi/m3), charcoal (pCi/charcoal canister), and solid samples (pCi/kg). b Laboratory codes : W (Water), Ml (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine). c Results are based on single determinations. d Control limits are listed in Attachment A of this report. NOTE: For fish, gelatin is used for the spike matrix. For vegetation, cabbage is used for the spike matrix. A3-3

TABLE A-4. In-House "Blank" Samples Concentration a Lab Code Sample Date Analysisb LaboratO!}: results (4.66cr) Acceptance Type LLD Activityc Criteria (4.66 cr) SPW-94 Water 1/11/2018 H-3 154 1 +/- 74 200 SPW-108 Water 1/12/2018 Sr-89 0.63 0.41 +/- 0.53 5 SPW-108 Water 1/12/2018 Sr-90 0.55 0.05 +/- 0.26 1 SPW-174 Water 1/19/2018 H-3 152 23 +/- 73 200 SPW-209 Water 1/23/2018 H-3 154 78 +/-78 200 SPW-211 Water 1/10/2018 Ra-226 0.03 0.19 +/- 0.03 2 SPW-213 Water 1/23/2018 1-131 0.23 -0.05 +/- 0.13 1 SPW-271 Water 1/30/2018 H-3 156 -36 +/- 77 200 SPW-329 Water 2/1/2018 Ni-63 74 -13 +/- 45 200 SPW-337 Water 2/2/2018 H-3 154 -16 +/- 71 200 SPW-385 Water 2/6/2018 H-3 150 -19 +/- 71 200 SPW-461 Water 2/13/2018 H-3 156 56+/- 80 200 SPW-515 Water 2/19/2018 H-3 153 -1 +/- 80 200 SPW-555 Water 2/8/2018 Ra-226 0.04 0.14 +/- 0.03 2 SPW-581 Water 2/22/2018 H-3 156 43 +/- 77 200 SPW-608 Water 2/23/2018 H-3 151 58+/- 75 200 SPW-649 Water 2/21/2018 Ra-226 0.04 0.17 +/- 0.03 2 SPW-665 Water 2/28/2018 Gr. Alpha 0.43 0.70 +/- 0.36 2 SPW-665 Water 2/28/2018 Gr. Beta 0.68 0.86 +/- 0.51 4 SPW-747 Water 3/6/2018 H-3 154 11 +/- 82 200 SPW-786 Water 3/8/2018 H-3 156 62 +/- 76 200 SPW-865 Water 3/14/2018 1-131 0.18 0.07 +/- 0.10 1 SPW-930 Water 3/20/2018 H-3 155 44 +/- 84 200 SPW-956 Water 3/12/2018 Ra-226 0.03 0.18 +/- 0.03 2 SPW-984 Water 3/27/2018 H-3 153 32 +/- 82 200 SPW-1036 Water 4/4/2018 H-3 162 14 +/- 77 200 SPW-1148 Water 4/12/2018 H-3 159 -15 +/- 73 200 SPW-1202 Water 4/13/2018 U-234 0.15 0.00 +/- 0.09 1 SPW-1202 Water 4/13/2018 U-238 0.15 0.06 +/- 0.13 1 SPW-1425 Water 4/20/2018 H-3 159 45 +/- 98 200 SPW-1453 Water 4/24/2018 H-3 155 43 +/- 77 200 SPW-1492 Water 4/26/2018 Ra-228 0.68 0.25 +/- 0.35 2 SPW-15"17 Water 4/27/2018 H-3 150 54+/- 75 200 SPW-1521 Water 4/27/2018 Tc-99 5.38 2.64 +/- 3.31 10 SPW*-1572 Water 5/2/2018 Gr.l\lpha 0.41 -0.23 +/- 0.26 2 SPW-1572 Water 5/2/20'18 Gr. Beta 0.69 -0.28 +/- 0.47 4 SPW-1617 Water 5/3/2018 H-3 155 -113 +/- 68 200 SPVV-1643 Water 5/4/2018 Sr-89 0.66 0.36 +/- 0.50 5 SPVV-1643 Water 5/4/2018 Sr-90 0.57 -0.07 +/- 0.25 1 a Liquid sample results are reported in pCi/Liter, air filters ( pCilm\ charcoal (pCi/charcoal canister), and solid samples (pCilg). b I-131(G); iodine-131 as analyzed by gamma spectroscopy. c Activity reported is a net activity result. A4-1

TABLE A-4. In-House "Blank" Samples Concentration a Lab Code Sample Date Analysisb Laboratory results (4.66cr) Acceptance Type LLD Activityc Criteria (4.66 cr) SPW-1694 Water 5/8/2018 H-3 157 86 +/- 80 200 SPW-1779 Water 5/11/2018 H-3 156 11 +/- 74 200 SPW-1895 Water 5/17/2018 1-131 0.12 0.00 +/- 0.08 SPW-1896 Water 5/18/2018 H-3 155 46 +/- 75 200 SPW-1898 Water 5/18/2018 H-3 186 2 +/- 92 200 SPW-1993 Water 5/24/2018 H-3 158 103 +/- 79 200 SPW-2041 Water 5/31/2018 H-3 156 115 +/- 81 200 SPW-2185 Water 6/6/2018 H-3 150 29 +/- 74 200 SPW-2383 Water 6/6/2018 Ra-226 0.03 0.20 +/- 0.02 2 SPW-2264 Water 6/11/2018 Gr. Alpha 0.39 -0.02 +/- 0.27 2 SPW-2264 Water 6/11/2018 Gr. Beta 0.73 -0.35 +/- 0.50 4 SPW-2913 Water 6/19/2018 Ra-226 0.02 0.18+/-0.02 2 SPW-2436 Water 6/27/2018 Sr-89 0.66 0.00 +/- 0.46 5 SPW-2436 Water 6/27/2018 Sr-90 0.61 -0.10 +/- 0.27 1 SPW-2447 Water 6/29/2018 H-3 160 -6 +/- 79 200 SPW-2545 Water 7/10/2018 H-3 154 20 +/- 74 200 SPW-2705 Water 7/16/2018 H-3 153 15 +/- 73 200 SPW-2771 Water 7/19/2018 H-3 156 -27 +/- 71 200 SPW-2810 Water 7/20/2018 Gr. Alpha 0.42 -0.09 +/- 0.29 2 SPW-2810 Water 7/20/2018 Gr. Beta 0.70 0.31 +/- 0.50 4 SPW-3688 Water 7/23/2018 Ra-226 0.02 0.21 +/- 0.02 2 SPW-3017 Water 7/31/2018 H-3 157 -5 +/- 74 200 SPW-3153 Water 8/6/2018 H-3 152 13 +/- 72 200 SPW-3377 Water 8/23/2018 Ni-63 66 18 +/- 40 200 SPW-3446 Water 8/27/2018 H-3 151 -15 +/- 69 200 SPW-3476 Water 8/27/2018 Ra-228 0.77 0.05 +/- 0.36 2 SPW-3648 Water 9/7/2018 H-3 148 89 +/- 75 200 SPW-4754 Water 9/7/2018 Ra-226 0.03 0.13+/-0.08 2 SPW-3842 Water 9/19/2018 H-3 156 29 +/- 74 200 SPW-3990 Water 10/1/2018 H-3 153 -6 +/- 71 200 SPW-4105 Water 10/5/2018 H-3 150 7 +/- 71 200 SPW-4565 Water 10/11/2018 Ra-228 0.86 -0.26 +/- 0.36 2 SPW-4205 Water 10/12/2018 H-3 154 -9 +/- 71 200 SPW-4273 Water 10/17/2018 H-3 153 67 +/- 76 200 SPW-4595 Water 10/30/2018 H-3 150 75 +/- 74 200 SPW-4681 Water '11/1/2018 H-3 152 19 +/- 72 200 SPW-4789 Water 11/9/2018 H-3 148 27 +/- 73 200 SPW-4862 Water 11/16/2018 H-3 154 15 +/- 77 200 SPW-5048 Water 11/30/2018 H-3 151 -6 +/- 69 200 a Liquid sample results are reported in pCi/Liter, air filters ( pCilm\ charcoal (pCi/charcoal canister), and solid samples (pCi/g). b 1-131 (G); iodine-131 as analyzed by gamma spectroscopy. c Activity reported is a net activity result. A4-2

TABLE A-4. In-House "Blank" Samples Concentration a Lab Code Sample Date Analysisb Laboratory results (4.66cr) Acceptance T~pe LLD Activitt Criteria (4.66 cr) SPW-4681 Water 11/1/2018 H-3 152 19 +/- 72 200 SPW-4683 Water 11/1/2018 Sr-89 0.64 0.25 +/- 0.45 5 SPW-4683 Water 11/1/2018 Sr-90 0.51 -0.10 +/- 0.22 SPW-4799 Water 11/9/2018 1-131 0.43 -0.01 +/- 0.20 SPW-4838 Water 11/13/2018 Ni-63 62 34 +/-38 200 SPW-5028 Water 11/19/2018 Ra-226 0.04 -0.14 +/- 0.03 2 SPW-5028 Water 11/19/2018 Ra-228 0.96 -0.11 +/- 0.43 2 SPW-5147 Water 12/7/2018 H-3 151 14 +/- 71 200 SPW-5278 Water 12/14/2018 H-3 153 83 +/- 76 200 SPW-5350 Water 12/19/2018 H-3 153 71 +/- 75 200 SPW-5403 Water 12/31/2018 H-3 156 51 +/- 75 200 a Liquid sample results are reported in pCi/Liter, air filters ( pCi!m\ charcoal (pCi/charcoal canister), and solid samples (pCi/g). b I-131(G); iodine-131 as analyzed by gamma spectroscopy. c Activity reported is a net activity result. A4-3

TABLE A-5. In-House "Duplicate" Samples Concentration a Averaged Lab Code Date Anal;tsis First Result Second Result Result Acceptance AP-010218 1/2/2018 Gr. Beta 0.048 +/- 0.004 0.057 +/- 0.004 0.052 +/- 0.003 Pass AP-010218 1/2/2018 Be-7 0.073 +/- 0.008 0.073 +/- 0.007 0.073 +/- 0.005 Pass AP-010318 1/3/2018 Gr. Beta 0.039 +/- 0.005 0.034 +/- 0.005 0.037 +/- 0.003 Pass AP-6846,6847 1/3/2018 Be-7 0.058 +/- 0.010 0.062 +/- 0.010 0.060 +/- 0.007 Pass AP-010318 1/3/2018 Be-7 0.059 +/- 0.009 0.059 +/- 0.007 0.059 +/- 0.006 Pass AP-010818 1/8/2018 Gr. Beta 0.053 +/- 0.007 0.055 +/- 0.007 0.054 +/- 0.005 Pass WW-164,165 1/11/2018 Gr. Beta 21.9 +/-2.2 20.4 +/- 2.1 21.1 +/- 1.5 Pass WW-189,190 1/11/2018 H-3 501 +/- 100 498 +/- 100 499 +/- 71 Pass AP-011518 1/15/2018 Gr. Beta 0.032 +/- 0.005 0.033 +/- 0.005 0.032 +/- 0.003 Pass AP-012318 1/23/2018 Gr. Beta 0.031 +/- 0.005 0.032 +/- 0.005 0.031 +/- 0.003 Pass LW-280,281 1/25/2018 Gr. Beta 1.10 +/-0.52 1.19 +/- 0.55 1.15 +/-0.38 Pass AP-013018 1/30/2018 Gr. Beta 0.024 +/- 0.005 0.023 +/- 0.005 0.024 +/- 0.003 Pass SG-301,302 1/30/2018 Ac-228 3.01 +/- 0.49 3.11 +/- 0.71 3.06 +/- 0.43 Pass SG-301,302 1/30/2018 Pb-214 2.47 +/- 0.31 2.22 +/- 0.35 2.34 +/- 0.23 Pass SG-301,302 1/30/2018 K-40 7.44 +/- 1.93 6.52 +/- 2.25 6.98 +/- 1.48 Pass SWU-322,323 1/30/2018 Gr. Beta 1.48 +/- 1.10 3.06 +/- 1.31 2.27 +/- 0.85 Pass P-391,392 2/2/2018 H-3 428 +/- 94 332 +/- 89 380 +/- 65 Pass S-433,434 2/7/2018 Pb-214 0.16 +/- 0.04 0.13 +/-0.05 0.15 +/- 0.03 Pass S-433,434 2/7/2018 Ac-228 0.24 +/- 0.06 0.26 +/- 0.07 0.25 +/- 0.05 Pass S-433,434 2/7/2018 K-40 6.45 +/- 0.58 6.50 +/- 0.59 6.48 +/- 0.41 Pass AP-454,455 2/8/2018 Be-7 0.233 +/- 0.102 0.271 +/- 0.111 0.252 +/- 0.075 Pass AP-021218 2/12/2018 Gr. Beta 0.037 +/- 0.005 0.035 +/- 0.005 0.036 +/- 0.004 Pass CF-477,478 2/12/2018 Be-7 0.31 +/- 0.17 0.21 +/- 0.08 0.26 +/- 0.09 Pass AP-021918 2/19/2018 Gr. Beta 0.036 +/- 0.005 0.033 +/- 0.008 0.035 +/- 0.005 Pass AP-022118 2/21/2018 Gr. Beta 0.030 +/- 0.003 0.025 +/- 0.003 0.028 +/- 0.002 Pass SWU-704,705 2/27/2018 Gr. Beta 2.50 +/- 0.65 1.72+/-0.58 2.11 +/- 0.44 Pass W-849,850 2/28/2018 H-3 567 +/- 105 730 +/- 112 649 +/- 77 Pass AP-030518 3/5/2018 Gr. Beta 0.024 +/- 0.005 0.025 +/- 0.005 0.024 +/- 0.004 Pass DW-90026,90027 3/7/2018 Gr. Alpha 55.4 +/- 2.5 60.3 +/- 2.6 57.8 +/- 1.8 Pass DW-90026,90027 3/7/2018 Gr. Beta 28.0 +/- 1.2 27.4 +/- 1.2 27.7 +/- 0.8 Pass S-800,801 3/8/2018 Ra-226 1.06 +/- 0.15 1.17 +/-0.17 1.12 +/-0.11 Pass S-800,801 3/8/2018 Ra**228 1.08 +/- 0.19 1.05 +/- 0.20 1.07 +/- 0.14 Pass S-800,801 3/8/2018 K-40 15.5 +/- 1.3 15.7+/-1.4 15.6 +/- 0.9 Pass SG-863,864 3/8/2018 Ra-226 5.56 +/- 0.28 5.92 +/- 0.27 5.74 +/- 0.19 Pass SG-863,864 3/8/2018 Ra-228 7.77 +/- 0.44 8.19 +/-0.53 7.98 +/- 0.34 Pass SG-863,864 3/8/2018 K-40 10.75 +/- 1.29 12.28 +/- 1.39 11.52 +/- 0.95 Pass WW-842,843 3/9/2018 H-3 415 +/- 99 423 +/- 99 419 +/- 70 Pass AP-030918 3/9/2018 Gr. Beta 0.027 +/- 0.004 0.021 +/- 0.004 0.024 +/- 0.003 Pass AP-031318 3/13/2018 Gr. Beta 0.030 +/- 0.004 0.031 +/- 0.004 0.031 +/- 0.003 Pass AP-031318 3/13/2018 Gr. Beta 0.026 +/- 0.005 0.024 +/- 0.005 0.025 +/- 0.003 Pass WW-934,935 3/13/2018 H-3 266 +/- 95 294 +/- 96 280 +/- 68 Pass S-972,973 3/20/2018 K-40 23.1 +/- 3.3 19.8 +/- 2.5 21.4 +/- 2.1 Pass AS-1

TABLE A-5. In-House "Duplicate" Samples Concentration a Averaged Lab Code Date Anallsis First Result Second Result Result Acceptance AP-032018 3/20/2018 Gr. Beta 0.021 +/- 0.005 0.023 +/- 0.005 0.022 +/- 0.004 Pass WW-1016,1017 3/22/2018 H-3 716 +/- 110 790 +/- 113 753 +/- 79 Pass SW-995,996 3/26/2018 H-3 14,538 +/- 364 14,647 +/- 365 14,593 +/- 258 Pass WW-1900,1901 3/30/2018 H-3 863 +/- 123 865 +/- 123 864 +/- 87 Pass AP-1299,1300 4/3/2018 Be-7 0.075 +/- 0.017 0.073 +/- 0.014 0.07 4 +/- 0.011 Pass SG-1470,1471 4/3/2018 Pb-214 1.45 +/- 0.14 1.39 +/- 0.12 1.42 +/- 0.09 Pass SG-1470,1471 4/3/2018 Ac-228 2.39 +/- 0.31 2.55 +/- 0.31 2.47 +/- 0.22 Pass WW-1123,1124 4/5/2018 H-3 11,266 +/- 319 11,175 +/- 320 11,220 +/- 226 Pass DW-90035,90036 4/6/2018 Ra-226 1.04 +/-0.13 0.88 +/- 0.14 0.96 +/- 0.10 Pass DW-90035,90036 4/6/2018 Ra-228 0.84 +/- 0.13 1.08 +/- 0.42 0.96 +/- 0.22 Pass AP-041018 4/10/2018 Gr. Beta 0.023 +/- 0.004 0.019 +/- 0.004 0.021 +/- 0.003 Pass SS-1611,1612 4/18/2018 K-40 10.01 +/- 0.54 8.93 +/- 0.56 9.47 +/- 0.39 Pass SW-1427,1428 4/18/2018 H-3 180 +/- 84 114 +/- 81 147 +/-58 Pass WW-1494,1495 4/20/2018 H-3 326 +/- 84 270 +/- 89 298 +/- 61 Pass AP-042518 4/25/2018 Gr. Beta 0.028 +/- 0.004 0.023 +/- 0.004 0.026 +/- 0.003 Pass S0-1634, 1635 4/25/2018 K-40 5.72 +/-0.51 6.36 +/- 0.56 6.04 +/- 0.38 Pass BS-1546,1547 4/26/2018 K-40 8.35 +/- 0.53 8.54 +/- 0.57 8.44 +/- 0.39 Pass AP-042618 4/26/2018 Gr. Beta 0.023 +/- 0.004 0.021 +/- 0.004 0.022 +/- 0.003 Pass DW-90043,90044 4/27/2018 Gr. Alpha 11.9 +/- 1.1 11.3 +/- 1.1 11.6 +/- 0.8 Pass AP-050118 5/1/2018 Gr. Beta 0.020 +/- 0.006 0.022 +/- 0.006 0.021 +/- 0.004 Pass AP-050218 5/2/2018 Gr. Beta 0.020 +/- 0.002 0.019 +/- 0.002 0.020 +/- 0.002 Pass F-2333,2334 5/2/2018 Cs-137 2.53 +/- 0.34 2.51 +/- 0.32 2.52 +/- 0.24 Pass DW-90048,90049 5/2/2018 Ra-226 0.18 +/- 0.11 0.14 +/- 0.08 0.16 +/- 0.07 Pass DW-90048,90049 5/2/2018 Ra-228 0.86 +/- 0.60 0.78 +/- 0.60 0.82 +/- 0.42 Pass WW-1833,1834 5/8/2018 H-3 182 +/- 83 304 +/- 98 243 +/- 64 Pass SG-1747,1748 5/8/2018 Pb-214 13.0+/-0.6 13.0 +/- 0.6 13.0 +/- 0.4 Pass SG-1747,1748 5/8/2018 Ac-228 21.0 +/- 1.2 21.1 +/- 1.4 21.0 +/- 0.9 Pass AP-050818 5/8/2018 Gr. Beta 0.027 +/- 0.005 0.025 +/- 0.004 0.026 +/- 0.003 Pass F-1812,1813 5/9/2018 K-40 4.30 +/- 0.47 3.40 +/- 0.47 .3.85 +/- 0.33 Pass SG-'1767, 1768 5/9/2018 Pb-214 0.96 +/- 0.24 0.72 +/- 0.24 0.84 +/- 0.17 Pass SG-1767,1768 5/9/2018 Ac-228 1.28 +/- 0.34 1.15 +/- 0.37 1.22 +/- 0.25 Pass AP-051418 5i14/2018 Gr. Beta 0.038 +/- 0.006 0.033 +/- 0.005 0.036 +/- 0.004 Pass DW-90061,90062 5/17/2018 Ra-226 1.53 +/- 0.13 '1.78 +/- 0.15 1.66 +/- 0.10 Pass DW--90061,90062 5/17/2018 Ra-228 0.82 +/- 0.45 0.87 +/- 0.44 0.85 +/- 0.31 Pass F-2201,2202 5/18/2018 K-40 2.73 +/- 0.40 2.68 +/- 0.45 2.71 +/- 0.30 Pass AP-051818 5/18/2018 Gr. Beta 0.020 +/- 0.004 0.026 +/- 0.004 0.023 +/- 0.003 Pass WW-2050,2051 5/22/2018 H-3 28,404 +/- 502 28,666 +/- 504 28,535 +/- 356 Pass AP-0522'18 5/22/2018 Gr. Beta 0.024 +/- 0.004 0.021 +/- 0.004 0.023 +/- 0.003 Pass AP-052918 5/29/2018 Gr. Beta 0.028 +/- 0.004 0.024 +/- 0.004 0.026 +/- 0.003 Pass AP-052918 5/29/2018 Gr. Beta 0.023 +/- 0.005 0.025 +/- 0.005 0.024 +/- 0.003 Pass AS-2

TABLE A-5. In-House "Duplicate" Samples Concentration a Averaged Lab Code Date Anal~sis First Result Second Result Result Acceptance G-2133,2134 6/4/2018 Be-7 0.55 +/- 0.64 0.32+/-0.16 0.43 +/- 0.33 Pass G-2133,2134 6/4/2018 K-40 7.12 +/- 0.64 6.53 +/- 0.58 6.82 +/- 0.43 Pass WW-2270,2271 6/8/2018 H-3 90 +/- 84 71 +/- 83 80 +/-59 Pass VE-2312,2313 6/11/2018 K-40 6.06 +/-0.17 5.50 +/- 0.46 5.78 +/- 0.24 Pass AP-2375,2376 6/14/2018 Be-7 0.310+/-0.134 0.240 +/-0.100 0.275 +/- 0.084 Pass AP-2893,2894 6/27/2018 Be-7 0.111 +/- 0.016 0.111 +/-0.016 0.111 +/- 0.011 Pass SG-24511 ,2512 7/2/2018 Gr. Alpha 19.60 +/- 3.08 19.55 +/- 3.06 19.58 +/- 2.17 Pass SG-2469,2470 7/2/2018 Pb-214 9.16 +/- 0.48 9.46 +/- 0.37 9.31 +/- 0.30 Pass SG-2469,2470 7/2/2018 Ac-228 9.94 +/- 0.87 10.00 +/- 0.64 9.97 +/- 0.54 Pass SG-2511 ,2512 7/2/2018 Pb-214 4.46 +/- 0.31 4.57 +/- 0.34 4.52 +/- 0.23 Pass SG-2511 ,2512 7/2/2018 Ac-228 6.15 +/- 0.57 5.83 +/- 0.66 5.99 +/- 0.44 Pass VE-261 0,2611 7/9/2018 K-40 6.52 +/- 0.75 5.92 +/- 0.75 6.22 +/- 0.53 Pass F-2851 ,2852 7/11/2018 K-40 2.93 +/- 0.38 2.83 +/- 0.32 2.88 +/- 0.25 Pass AP-071218 7/12/2018 Gr. Beta 0.021 +/- 0.003 0.024 +/- 0.004 0.023 +/- 0.002 Pass AP-2721 ,2722 7/12/2018 Be-7 0.204 +/- 0.100 0.275 +/- 0.127 0.240 +/- 0.081 Pass WW-2742,2743 7/12/2018 H-3 253 +/- 86 278 +/- 97 265 +/- 65 Pass DW-90123,90124 7/24/2018 Ra-226 0.97 +/- 0.18 1.06+/-0.12 1.02 +/- 0.11 Pass DW-90123,90124 7/24/2018 Ra-228 3.61 +/- 0.74 4.05 +/- 0.80 3.83 +/- 0.54 Pass G-3000,3001 7/24/2018 Be-7 3.29 +/- 0.25 3.24 +/- 0.26 3.26 +/-0.18 Pass G-3000,3001 7/24/2018 K-40 4.98 +/- 0.40 5.06 +/-0.41 5.02 +/- 0.29 Pass S-2916,2917 7/24/2018 Pb-214 1.00 +/- 0.51 0.94 +/- 0.53 0.97 +/- 0.37 Pass S-2916,2917 7/24/2018 Ac-228 0.98 +/- 0.11 0.98 +/- 0.09 0.98 +/- 0.07 Pass AP-073018 7/30/2018 Gr. Beta 0.029 +/- 0.004 0.022 +/- 0.004 0.026 +/- 0.003 Pass DW-90133,90134 8/7/2018 Ra-228 2.34 +/- 0.68 3.28 +/- 0.73 2.81 +/- 0.50 Pass DW-90138,90139 8/10/2018 Gr. Alpha 4.02 +/- 0.68 3.87 +/- 0.66 3.95 +/- 0.51 Pass VE-3281 ,3282 8/14/2018 K-40 11.40 +/- 0.831 11.39 +/- 0.524 11.39 +/- 0.491 Pass VE-3323,3324 8/14/2018 K-40 3.41 +/- 0.227 3.67 +/- 0.262 3.54 +/- 0.173 Pass VE-3323,3324 8/14/2018 Be**? 0.25 +/- 0.069 0.33 +/- 0.092 0.29 +/- 0.058 Pass AP-081518 8/'15/2018 Gr. Beta 0.022 +/- 0.003 0.028 +/- 0.003 0.025 +/- 0.002 Pass PM-3365,3366 8/16/2018 K-40 14.77 +/- 0.76 14.19 +/- 0.69 14.48 +/- 0.51 Pass S-3478,3479 8/27/2018 Pb-214 0."10 +/- 0.05 0.70 +/- 0.05 0.70 +/- 0.04 Pass S-3478,3479 8/27/2018 Ac-228 0.84 +/- 0.11 0.89 +/- 0.08 0.87 +/- 0.07 Pass SWT-3501 ,3502 8/27/2018 Gr. Beta 0.64 +/- 0.48 1.42 +/- 0.56 1.03 +/- 0.37 Pass VE-*3522,3523 8/28/2018 K-40 2.51 +/- 0.20 2.63 +/- 0.20 2.57 +/- 0.14 Pass WW-3745,3746 8/31/2018 H-3 1035 +/- 119 1056 +/- 99 1045 +/- 77 Pass S-3542,3543 8/30/2018 K-40 6.10+/-0.72 5.69 +/- 0.63 5.90 +/- 0.48 Pass W-3703,3704 9/11/2018 Gr. Alpha 0.71 +/- 0.80 1.03 +/- 0.81 0.87 +/- 0.57 Pass W-3703,3704 9/11/2018 Gr. Beta 1.67 +/- 1.08 0.53 +/- 1.00 1.10+/-0.74 Pass SG-3796,3797 9/14/2018 Gr. Alpha 42.3 +/- 3.6 50.9 +/- 3.8 46.6 +/- 2.6 Pass AS-3

TABLE A-5. In-House "Duplicate" Samples Concentration a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SG-3796,3797 9/14/2018 Gr. Beta 43.9 +/- 1.9 44.1 +/- 1.8 44.0 +/- 1.3 Pass SG-3796,3797 9/14/2018 Pb-214 10.4 +/- 0.6 14.2 +/- 0.5 12.3 +/- 0.4 Pass SG-3796,3797 9/14/2018 Ac-228 15.8 +/- 1.2 15.7+/-1.2 15.8 +/- 0.8 Pass DW-90173,90174 10/24/2018 Ra-226 1.13 +/-0.15 1.38 +/- 0.17 1.26 +/- 0.11 Pass DW-90173,90174 10/24/2018 Ra-228 5.09 +/- 0.84 6.59 +/- 0.89 5.84 +/- 0.61 Pass SW-4782,4783 11/7/2018 H-3 192 +/- 82 238 +/- 84 215 +/-59 Pass WW-4959,4960 11/13/2018 H-3 330 +/- 88 286 +/- 86 308 +/- 61 Pass SG-4850,4851 11/14/2018 Pb-214 15.0 +/- 0.4 14.7 +/- 0.4 14.9 +/- 0.3 Pass SG-4850,4851 11/14/2018 Ac-228 17.5 +/- 0.7 16.7 +/- 0.6 17.1+/-0.5 Pass VE-4917,4918 11/20/2018 K-40 4.54 +/- 0.45 4.05 +/- 0.46 4.30 +/- 0.32 Pass VE-4917,4918 11/20/2018 Be-7 9.42 +/- 0.45 9.42 +/- 0.46 9.42 +/- 0.32 Pass SG-5046,5047 11/21/2018 K-40 8.65 +/- 1.18 9.12 +/- 1.02 8.88 +/- 0.32 Pass SG-5046,5047 11/21/2018 Cs-137 0.18 +/- 0.06 0.10 +/- 0.05 0.14 +/- 0.78 Pass SG-5046,5047 11/21/2018 Gr. Alpha 22.8 +/- 5.6 17.5 +/-4.8 20.2 +/- 0.0 Pass SG-5046,5047 11/21/2018 Gr. Beta 31.8 +/- 3.5 26.8 +/- 3.1 29.3 +/- 3.7 Pass SG-6286,6287 12/1/2018 Pb-214 11.3 +/-0.4 10.7 +/- 0.5 11.0 +/- 0.3 Pass SG-6286,6287 12/1/2018 Ac-228 13.5 +/- 0.9 13.2 +/- 1.0 13.4 +/- 0.7 Pass SWU-5132 ,5133 12/4/2018 H-3 159 +/- 82 204 +/- 80 181 +/-57 Pass SWU-5132 ,5133 12/4/2018 Gr. Beta 1.32 +/- 0.56 1.33 +/- 0.57 1.32 +/- 0.40 Pass XAP-5499,5500 1/2/2019 Fe-55 941 +/- 220 1027 +/-226 984 +/- 158 Pass XAP-5499,5500 1/2/2019 Sr-89 20.2 +/- 7.3 14.9 +/- 5.7 17.5 +/- 4.7 Pass XAP-5499,5500 1/2/2019 Ni-63 12.1 +/- 8.5 15.6 +/- 8.5 13.8 +/- 6.0 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD. a Results are reported in units of pCi!L, except for air filters (pCi/Filter or pCi/m3), food products, vegetation, soil and sediment (pCi/g). AS-4

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentration a Reference Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAS0-765 2/1/2018 Am-241 1.57 +/- 4.46 0 NA c Pass MAS0-765 2/1/2018 Cs-137 4.69 +/- 2.59 4.6 NA ct Pass MAS0-765 2/1/2018 Co-57 886 +/- 7 826 578 -1074 Pass MAS0-765 2/1/2018 Co-60 579 +/- 7 560 392 -728 Pass MAS0-765 2/1/2018 Mn-54 1135 +/- 15 1010 707 - 1313 Pass MAS0-765 2/1/2018 K-40 653 +/- 47 577 404-750 Pass MAS0-765 2/1/2018 Zn-65 1096 +/- 19 960 672 - 1248 Pass MAS0-765 2/1/2018 Pu-238 54.4 +/- 5.6 45.2 31.6 -58.8 Pass MAS0-765 2/1/2018 Pu-239/240 58.9 +/- 5.6 50.8 35.6 -66.0 Pass MAS0-765 2/1/2018 Sr-90 1.07 +/- 1.15 0 NA c Pass MAAP-769 2/1/2018 Am-241 0.070 +/- 0.021 0.067 0.047 - 0.087 Pass MAAP-769 2/1/2018 Cs-134 0.55 +/- 0.04 0.675 0.473 - 0.878 Pass MAAP-769 2/1/2018 Cs-137 0.01 +/- 0.01 0 NA c Pass MAAP-769 2/1/2018 Co-57 1.06 +/- 0.04 1.18 0.83 - 1.53 Pass MAAP-769 2/1/2018 Co-60 0.01 +/- 0.01 0 NA c Pass MAAP-769 2/1/2018 Mn-54 1.01 +/- 0.05 1.03 0.72 - 1.34 Pass MAAP-769 2/1/2018 Zn-65 1.37 +/- 0.11 1.33 0.93 -1.73 Pass MAAP-769 2/1/2018 Pu-238 0.042 +/- 0.017 0.0445 0.0312 -0.0579 Pass MAAP-769 2/1/2018 Pu-239/240 -0.001 +/- 0.006 0 NA c Pass MAAP-769 2/1/2018 Sr-90 1.12 +/-0.13 1.01 0.71-1.31 Pass MAAP-769 2/1/2018 U-234/233 0.117 +/-0.023 0.124 0.087 - 0.161 Pass MAAP-769 2/1/2018 U-238 0.126 +/- 0.023 0.128 0.090 - 0.166 Pass MAVE-767 2/1/2018 Cs-134 3.03 +/- 0.10 3.23 2.26-4.20 Pass MAVE-767 2/1/2018 Cs-137 3.86 +/- 0.05 3.67 2.57-4.77 Pass MAVE-767 2/1/2018 Co-57 4.86 +/- 0.09 4.42 3.09-5.75 Pass MAVE-767 2/1/2018 Co-60 2.24 +/- 0.06 2.29 1.60-2.98 Pass MAVE-767 2/1/2018 Mn-54 2.75 +/- 0.08 2.66 1.86 - 3.46 Pass MAVE-767 211/2018 Zn-65 0.02 +/- 0.05 0 NA c Pass MAW-656 2/1/2018 1-129 1.66 +/- 0.07 1.93 1.35 - 2.51 Pass MAW-662 2/1/2018 Arn-241 0.581 +/- 0.050 0.709 0.496 - 0.922 Pass MAW-662 211/2018 Cs-134 9.35 +/- 0.38 10.2 7.1 -13.3 Pass MAW-662 2/1/2018 Cs-137 13.0 +/- 0.2 12.2 8.5 - 15.9 Pass MAW-662 2/1/20'18 co. 57 0.003 +/- 0.039 0 NA c Pass MAW-662 2/1/2018 Co-60 11.73 +/- 0.19 11.5 8.1-15.0 Pass MAW-662 2/1/2018 Mn-54 0.060 +/- 0.019 0 NA c Pass MAW-662 2/1/2018 Zn-65 15.85 +/- 0.27 14.3 10.0-18.6 Pass MAW-662 2/1/2018 Fe-55 10.7 +/- 11.7 11.1 7.80- 14.40 Pass MAW-662 2/1/2018 Ni-63e 11.0 +/- 1.4 14.0 9.8 - 18.2 Warning MAW-662 2/1/2018 Ni-63e 12.9 +/- 1.7 14.0 9.8 - 18.2 Pass MAW-662 2/1/2018 H-3 -0.3 +/- 3.0 0 NA c Pass MAW-662 2/1/2018 Pu-238 0.02 +/- 0.01 0.023 NA ct Pass MAW-662 2/1/2018 Pu-239/240 0.585 +/- 0.056 0.600 0.420 - 0. 780 Pass MAW-662 2/1/2018 Ra-226f 0.340 +/- 0.040 0.257 0.180 - 0.334 Fail MAW-662 2/1/2018 Ra-226f 0.297 +/- 0.048 0.257 0.180 - 0.334 Pass A6-1

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentration a Reference Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAW-662 2/1/2018 Sr-90 9.92 +/- 0.75 11.4 8.0 - 14.8 Pass MAW-662 2/1/2018 Tc-99 4.9 +/- 0.4 4.37 3.06 -5.68 Pass MAW-662 2/1/2018 U-233/234 0.404 +/- 0.041 0.430 0.301 - 0.559 Pass MAW-662 2/1/2018 U-238 0.396 +/- 0.041 0.437 0.306 - 0.568 Pass MAS0-3638 8/1/2018 Cs-134 688.7 +/- 26.2 781 547- 1015 Pass MAS0-3638 8/1/2018 Cs-137 605.9 +/- 22.7 572 400-744 Pass MAS0-3638 8/1/2018 Co-57 976.7 +/- 37.6 958 671 - 1245 Pass MAS0-3638 8/1/2018 Co-60 604.5 +/- 24.9 608 426 -790 Pass MAS0-3638 8/1/2018 Mn-54 5.2 +/- 5.2 0 NA c Pass MAS0-3638 8/1/2018 K-40 630 +/- 31 566 396- 736 Pass MAS0-3638 8/1/2018 Zn-65 556.4 +/- 26.8 500 350 -650 Pass MAAP-3636 8/1/2018 Cs-134 0.37 +/- 0.04 0.444 0.311 - 0.577 Pass MAAP-3636 8/1/2018 Cs-137 0.34 +/- 0.05 0.345 0.242 - 0.449 Pass MAAP-3636 8/1/2018 Co-57 0.56 +/- 0.04 0.592 0.414 - 0.770 Pass MAAP-3636 8/1/2018 Co-60 0.28 +/- 0.03 0.294 0.206 - 0.382 Pass MAAP-3636 8/1/2018 Mn-54 0.26 +/- 0.05 0.266 0.186 - 0.346 Pass MAAP-3636 8/1/2018 Zn-65 0.22 +/- 0.07 0.201 NA d Pass MAVE-3640 8/1/2018 Cs-134 1.87 +/-0.10 1.94 1.36-2.52 Pass MAVE-3640 8/1/2018 Cs-137 2.69 +/- 0.15 2.36 1.65 - 3.07 Pass MAVE-3640 8/1/2018 Co-57 3.90 +/- 0.12 3.31 2.32-4.30 Pass MAVE-3640 8/1/2018 Co-60 1.76 +/- 0.09 1.68 1.18 - 2.18 Pass MAVE-3640 8/1/2018 Mn-54 2.91 +/- 0.16 2.53 1.77- 3.29 Pass MAVE-3640 8/1/2018 Zn-65 1.53 +/- 0.21 1.37 0.96 - 1.78 Pass MAW-3480 8/1/2018 H-3 336.0 +/- 10.7 338 237-439 Pass MAW-3480 8/1/2018 Cs-134 7.86 +/- 0.31 8.7 6.1 - 11.3 Pass MAW-3480 8/1/2018 Cs-137 7.55 +/- 0.33 6.9 4.8- 9.0 Pass MAW-3480 8/1/2018 Co-57 15.67 +/- 0.36 14.9 10.4- 19.4 Pass MAW-3480 8/1/2018 Co-60 0.12+/-0.12 0 NA c Pass MAW-3480 8/1/2018 Mn-54 13.38 +/- 0.44 12.5 8.8 - 16.3 Pass MAW-3480 8/1/2018 Zn-65 7.80 +/- 0.53 7.53 5.27 - 9.79 Pass MAW-3634 8/1/2018 1-129 1.32 +/- 0.08 1.62 1.13-2.11 Pass " Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation). b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil) and MAVE (vegetation). c 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. d Provided in the series for "sensitivity evaluation". MAPEP does not provide control limits. e The lab was in the "warning zone" on this study(biased low). The sample was rerun applying an aggressive oxidation technique to remove a complexing agent that is utilized in the early steps of the procedure. Reanalysis was acceptable with this enhanced technique. fAn investigation was performed to determine reason for the failure of the Ra-226 result. A backup solution was reanalyzed with acceptable results. The current study as well as a past study were reanalyzed with acceptable results. No conclusion has been currently drawn from the results of this investigation. A6-2

TABLE A-7. Interlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA) 8 . MRAD-28 Stud~ Concentration a Lab Code b Date Analysis Laboratory ERA Control Result Result Limits c Acceptance ERAP-942 3/19/2018 Am-241d 24.6 7.86 5.61 - 10.5 Fail ERAP-942 3/19/2018 Am-241d 7.30 7.86 5.61 - 10.5 Pass ERAP-942 3/19/2018 Cs-134 174 204 132 -250 Pass ERAP-942 3/19/2018 Cs-137 969 865 710 - 1130 Pass ERAP-942 3/19/2018 Co-60 672 665 565 -845 Pass ERAP-942 3/19/2018 Fe-55 701 771 281 - 1230 Pass ERAP-942 3/19/2018 Mn-54 <50 < 50.0 0.00 - 50.0 Pass ERAP-942 3/19/2018 Zn-65 594 668 548 - 1020 Pass ERAP-942 3/19/2018 Pu-238 56.8 55.6 42.0 -68.3 Pass ERAP-942 3/19/2018 Pu-239 54.4 52.3 39.1 -63.1 Pass ERAP-942 3/19/2018 Sr-90 113 124 78.4-169 Pass ERAP-942 3/19/2018 U-234 22.8 24.6 18.2 -28.8 Pass ERAP-942 3/19/2019 U-238 22.7 24.4 18.4 - 29.1 Pass ERAP-944 3/19/2018 Gross Alpha 49.1 43.4 22.7 - 71.5 Pass ERAP-944 3/19/2018 Gross Beta 44.8 52.0 31.5 -78.6 Pass ERS0-946 3/19/2018 Ac-228 1,480 1,240 818 - 1560 Pass ERS0-946 3/19/2018 Am-241 48 74.7 40.3-106 Pass ERS0-946 3/19/2018 Bi-212e 1,980 1,240 355 - 1,850 Fail ERS0-946 3/19/2018 Bi-212e 11,220 1,240 355- 1,850 Pass ERS0-946 3/19/2018 Bi-214 2,180 1,760 845-2,620 Pass ERS0-946 3/19/2018 Cs-134 5,230 5,330 3,640 - 6,370 Pass ERS0-946 3/19/2018 Cs-137 4,820 4,210 3,180 - 5,320 Pass ERS0-946 3/19/2018 Co-60 8,390 8,060 6,350 - 9,950 Pass ERS0-946 3/19/2018 K-40e 14,100 10,600 7,300 - 12,700 Fail ERS0-946 3/19/2018 K-40e 12160 10,600 7,300- 12,700 Pass ERS0-946 3/19/2018 Mn-54 < 1000 < 1000 0 - 1,000 Pass ERS0-946 3/19/2018 Pb-212 1,140 1,240 865- 1,570 Pass ERS0-946 3/19/2018 Pb-214 2330 1850 777-2910 Pass ERS0-946 3/19/2018 Pu-238 1,830 1,470 733 -2230 Pass ERS0-946 3/19/2018 Pu-239 1,520 1,330 725 - 1910 Pass ERS0-946 3!-19/2018 Sr-90 3,500 4,500 1,400 - 7,010 Pass ERS0-946 3/19/2018 Th-234 1,800 1,800 680 -3,080 Pass ERS0-946 3/19/2018 U-234 1,610 1,820 853 - 2,380 Pass ERS0-946 3/19/2018 U-238 1,800 1,800 988-2,420 Pass ERS0-946 3/19/2018 Zn-65 2,440 1,990 1,590-2,710 Pass ERW-952 3/19/2018 Gr. Alpha 25.3 29.0 10.6 -40.0 Pass ERW-952 3/19/2018 Gr. Beta 61.3 73.1 36.6 - 101 Pass ERW-954 3/19/2018 H-3 22,300 21,700 16,400 - 26,400 Pass A7-1

TABLE A-7. Interlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA) a. MRAD-28 Study Concentration a Lab Code b Date Analysis Laboratory ERA Control Result Result Limits c Acceptance ERVE-948 3/19/2018 Am-241 3,800 3,880 2,400 - 5,480 Pass ERVE-948 3/19/2018 Cm-244 2,490 2,630 1,480 - 3,270 Pass ERVE-948 3/19/2018 Co-60 579 491 385 -642 Pass ERVE-948 3/19/2018 Cs-134 2,090 1,950 1,290 - 2,600 Pass ERVE-948 3/19/2018 Cs-137 2,640 2,160 1,660 - 2,910 Pass ERVE-948 3/19/2018 K-40 34,000 30,900 23,200 - 39,100 Pass ERVE-948 3/19/2018 Mn-54 < 300 < 300 0.00 -300 Pass ERVE-948 3/19/2018 Zn-65 3,080 2,400 1'790 - 3,560 Pass ERVE-948 3/19/2018 Pu-238 2,400 2,020 1,400 - 2,600 Pass ERVE-948 3/19/2018 Pu-239 5,140 4,160 2,880 - 5,270 Pass ERVE-948 3/19/2018 Sr-90 3,570 3,330 1,880 -4340 Pass ERVE-948 3/19/2018 U-233/234 4,130 4,050 2,850 - 5,170 Pass ERVE-948 3/19/2018 U-238 4,190 4,010 2,830 - 5,020 Pass ERW-950 3/19/2018 Am-241 72.5 103 70.7- 132 Pass ERW-950 3/19/2018 Co-60 1,550 1,480 1,280 - 1,700 Pass ERW-950 3/19/2018 Cs-134 1,280 1,330 1,000- 1460 Pass ERW-950 3/19/2018 Cs-137 343 328 281 -373 Pass ERW-950 3/19/2018 Mn-54 < 100 < 100 0.00 -100 Pass ERW-950 3/19/2018 Pu-238 59.8 66.1 39.7 - 85.6 Pass ERW-950 3/19/2018 Pu-239 84.8 91.8 56.8 - 113 Pass ERW-950 3/19/2018 U-234 111 132 100 - 151 Pass ERW-950 3/19/2018 U-238 113 131 102- 154 Pass ERW-950 3/19/2018 Zn-65 1450 1300 1160 - 1640 Pass ERW-950 3/19/2018 Fe-55 533 445 261 -647 Pass ERW-950 3/19/2018 Sr-90 754 781 562-965 Pass a Results obtained by Environmental, inc., Midwest Laboratory (EIML) as a participant in the crosscheck program for proficiency testing administered by Environmental Resource Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML). b Laboratory codes as follows: ERW (water), ERAP (air filter), ERSO (soil), ERVE (vegetation). Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCi/kg). c Results are presented as the known values, expected laboratory precision (2 sigma, 1 determination) and control limits as provided by ERA. d Reported result was higher than ERA's upper acceptance limit. An investigation was initiated. The sample was run with a pre-treatment technique. Rerunning the analysis with this pre-treatment gave a result of 7.30 pCi/total. Going forward all samples for Am-241 will be analyzed utilizing this pre-treatment. e The ERA results for K-40 and Bi-212 were outside the acceptable limits. The sample analysis was rerun utilizing a different library with acceptable results. The gamma software vendor will be consulted for the differences between the two libraries. In the meantime EIML will occasionally be counting a standard with known activity to ensure reported values are within the laboratory's acceptance criteria. A7-2

APPENDIX 8 DATA REPORTING CONVENTIONS B-1

Daja Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period. 2.0, Single Measurements Each single measurement is reported as follows: x +/-s where: x :::: value of the measurement; s = 2CJ counting uncertainty (corresponding to the 95% confidence level). In cases where the activity is less than the lower limit of detection L, it is reported as: <: L, where L = the lower limit of detection based on 4.66a uncertainty for a background sample. 3.0. Duplicate analyses If duplicate analyses ~re reported, the convention is as follows. : 3.1 Individual r~sults: For two analysis results; x1 :;t s 1 and x2 +/- s2

                      &mQtted result          ~ +/- s:  where x = (1/2) (x1 + x~) and s = (1/2)    ~ s~ +    s; 3.2.       Individual results*     < L 1 * < L2         Repgrted result: < L, where L    = lower of L, and L2 3.3.        lndividua! result§:     x +/- s, < L          Repofjed result:        x :;t s if x $! L; < L otheiWise.

4.0. Qomputation of Av~rages and Standarc:j Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual mea~?ur~ments over the period averaged; for exa~ple, an annual stand~rd deviation would not be the average of quarterly standard deviations. The average x and standard deviation **s" of a set of n numbers x1* x2 .*. xr. ~re defined a~ follows: x =n1 Lx --~ s~ '\j~ 4.2 Values below the highest lower limit of detection are not included in the average. 4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported. 4.4 If all but one of the values are Jess than the highest LLD, the single value x and associated two sigma error is reported. 4.5 In rounding off, the foll*wing rules are followed: 4.5.1. If th~ 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 round~d off to 11.44. 4.5.2. If the number following those to be retained is equal to or greater than 5, th~ number is dropped and the last retained numb~r is raised by 1. As an example, 11 ,445 is rounded off to 11.45. B-2

POINT BEACH NUCLEAR PLANT APPENDIX C Sampling Program and Locations C-1

POINT BEACH NUCLEAR PLANT Locations Collection Type Analysis Sample Type No. Codes (and Type)a (and Frequency)b (and Frequency)b Airborne Filters 6 E-1-4, 8, 20 Weekly GB, GS, on QC for each location Airborne Iodine 6 E-1-4, 8, 20 Weekly 1-131 Ambient Radiation 34 E-1-9, 12, 14, 15, 16b, Quarterly Ambient Gamma (TLD's) 178, 18, 20, 22-25, 26b, 27-32 Lake Water 5 E-1, 5, 6, 33 Monthly GB. GS, 1-131 on MC H-3, Sr-89-90 on Q C Well Water E-10 Quarterly GB. GS, H-3, Sr-89-90, 1-131 Vegetation 8 E-1-4, 6, 9, 20 3x I year GS (Grasses) as available Shoreline Silt 5 E-1. 5. 6, 12, 33 1x I year GS Soil 8 E-1-4, 6, 8, 9, 20 1x I year GS Milk 3 E-11, 40,21 Monthly GS, 1-131, Sr-89-90 Algae 2 E-5, 12 1x I year GS as available Fish E-13 Quarterly GS (in edible portions) as available Vegetation (Crops) 10 E-Fla, -F1b,-F2, -F3, Annual GS

                                         -F4, -F5, -F6, -F7, -F8,
                                         -F9 a   Locations codes are defined in Table 2. Control Stations are indicated by (C). All other stations are indicators.

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

      =                         =

MC monthly composite. QC quarterly composite. C-2

POINT BEACH NUCLEAR PLANT APPENDIX D Graphs of Data Trends D-1

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POINT BEACH Air Particulates - Gross Beta Location E-8, monthly averages 2014-2018

0.050 ' 0.040

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0.01 0 -;---- ..............______________________. _______ ---- ------.. -*--------------*--------------- I 0.000 ++--+--;-+-H--1 1--T*i*t--h-H-*H-i-+-H--;**H 4-i*H-:-1++++++H*h-*;--l*-H-+-i~-+-;.-,-;-H-+H-i*H-~ 2014 2015 2016 2017 2018 2019 Year 0-4

POINT BEACH NUCLEAR PLANT APPENDIX E Supplemental Analyses E-1

POINT BEACH NUCLEAR PLANT Facade Wells Units: =pCi\L Gamma isotopic analysis Location GW-09 1Z-361A GW-09 1Z-3618 GW-10 2Z-361A GW-10 2Z-3618 Collection* Date 03-16-18 03-16-18 03-16-18 03-16-18 Lab Code EWW- 1081 MDC EWW- 1083 MDC EWW- 1084 MDC EWW- 1085 MDC 8e-7 1.0 +/- 13.2 < 44.7 7.7 +/- 12.3 < 30.4 6.3 +/- 15.2 < 34.1 -0.7 +/- 11.4 < 36.6 Mn-54 0.2 +/- 1.6 < 3.7 1.4 +/- 1.5 < 3.2 0.6 +/- 1.6 < 3.1 1.0 +/- 1.4 < 2.7 Fe-59 -1.8 +/- 3.1 < 9.2 0.5 +/- 2.7 < 7.8 -4.0 +/- 3.1 < 7.2 1.1 +/- 2.4 < 6.3 Co-58 -0.8 +/- 1.6 < 3.0 0.2 +/- 1.4 < 3.9 -1.6 +/- 1.5 < 3.7 -1.1 +/- 1.4 < 3.7 Co-60 1.4 +/-1.7 < 3.5 -0.5 +/- 1.5 < 2.3 -1.1 +/- 1.8 < 3.1 0.1 +/- 1.5 < 1.7 Zn-65 -2.2 +/- 3.3 < 5.6 1.9 +/- 2.9 < 5.6 0.3 +/- 3.6 < 5.7 0.3 +/- 3.0 < 6.5 Zr-Nb-95 -2.1 +/- 1.7 < 3.8 2.2 +/- 1.5 < 5.3 1.7+/-1.7 < 6.0 0.3 +/- 1.5 < 4.1 Cs-134 -1.7 +/- 1.8 < 3.5 -0.6 +/- 1.5 < 3.0 -0.1 +/- 1.6 < 3.1 -0.1 +/-1.4 < 2.8 Cs-137 2.4 +/- 1.9 < 3.6 1.1 +/-1.7 < 3.7 -0.3 +/- 1.8 < 3.7 1.6+/-1.6 < 2.7 8a-La-140 -0.2 +/-1.9 < 14.1 -3.3 +/- 1.8 < 13.6 0.7 +/- 1.7 < 13.5 -1.6+/-1.7 < 11.6 Location GW-09 1Z-361A GW-09 1Z-361 8 GW-10 2Z-361A GW-10 2Z-361 8 Collection Date 05-27-18 05-27-18 05-27-18 05-27-18 Lab Code EWW- 2078 EWW- 2079 EWW- 2080 EWW- 2081 8e-7 -6.9 +/- 10.9 < 26.3 6.7 +/- 11.2 < 28.8 -12.8+/-11.8 < 27.5 -9.3 +/- 12.1 < 19.8 Mn-54 1.3 +/- 1.3 < 2.7 0.5 +/- 1.5 < 2.6 0.3 +/- 1.5 < 3.0 -0.8 +/- 1.5 < 2.1 Fe-59 -3.4 +/- 2.4 < 5.1 -0.4 +/- 2.8 < 5.4 1.5 +/- 2.8 < 7.8 -2.4 +/- 2.6 < 7.9 Co-58 0.0 +/- 1.3 < 2.4 1.7 +/- 1.5 < 3.6 0.9 +/- 1.5 < 3.0 0.6 +/- 1.4 < 2.9 Co-60 0.2 +/- 1.6 < 2.5 1.6 +/- 1.8 < 2.7 0.1 +/- 1.7 < 1.7 -0.6 +/- 1.6 < 3.1 Zn-65 -1.2 +/- 2.6 < 4.3 0.2 +/- 2.9 < 6.1 -0.6 +/- 2.8 < 2.8 2.0 +/-3.1 < 5.6 Zr-Nb-95 -1.4 +/- 1.5 < 4.3 -1.1 +/- 1.6 < 4.6 -3.1 +/- 1.5 < 2.7 0.4 +/- 1.6 < 5.0 Cs-134 0.1 +/-1.4 < 2.7 0.1+/-1.6 < 2.9 -0.3 +/- 1.5 < 2.7 0.0 +/- 1.5 < 2.7 Cs-137 0.0+/-1.7 < 3.3 -0.7 +/- 1.7 < 3.1 3.0 +/- 1.7 < 3.6 0.3 +/- 1.8 < 3.0 8a-La-140 0.4 +/- 1.6 < 9.6 -2.0 +/- 1.8 < 8.4 -1.9 +/- 1.8 < 10.7 -7.7 +/- 1.7 < 8.5 Location GW-09 1Z-361A GW-0912 .. 3618 GW-10 2Z-361A GW-10 2Z-3618 Collection Date 07-11-18 07-11-18 07-11-18 07-11-18 Lab Code EWW- 2700 EWW- 2701 EWW- 2702 EWW- 2703 8e-7 -2.0 +/- 14.8 < 26.6 -1.7 +/- 14.0 < 22.0 8.1 +/- 11.1 < 30.7 -5.8 +/- 10.2 < 20.1 Mn-54 -0.4 +/- 1.5 < 2.9 1.3 +/- 1.4 < 2.7 -0.3 +/- 1.4 < 2.3 0.9 +/- 1.4 < 2.8 Fe-59 1.6 +/-3.2 < 6.1 -1.8 +/- 3.2 < 5.8 -1.4 +/- 2.5 < 2.7 -0.9 +/- 2.3 < 3.9 Co-58 0.6 +/- 1.4 < 2.5 1.0 +/- 1.4 < 2.8 -0.5 +/- 1.3 < 2.2 -0.5 +/- 1.2 < 2.2 Co-60 -0.5 +/- 1.7 < 3.0 1.2 +/- 1.5 < 2.4 0.1+/-1.4 < 2.2 0.2 +/- 1.4 < 2.7 Zn-65 -1.0 +/- 3.4 < 6.0 0.2 +/- 3.3 < 5.4 -3.4 +/- 2.8 < 4.7 -1.3 +/-2.7 < 4.4 Zr-Nb-95 0.3 +/- 1.5 < 3.0 -0.1 +/- 1.5 < 2.9 .. 2.7 +/- 1.5 < 3.2 -1.1 +/- 1.3 < 2.3 Cs-134 -0.8 +/- 1.6 < 3.4 0.5 +/- 1.5 < 3.2 -0.4 +/- 1.4 < 2.5 -0.2 +/- 1.4 < 2.4 Cs-137 -0.2 +/- 1.8 < 3.0 0.9 +/- 1.7 < 3.2 0.8 +/- 1.5 < 2.4 1.1 +/- 1.5 < 2.5 8a-La-140 -1.4+/-1.7 < 2.8 -0.6 +/- 1.6 < 3.5 0.1 +/- 1.4 < 3.6 -2.7+/-1.6 < 3.6 E-2

POINT BEACH NUCLEAR PLANT Facade Wells Units: = pCi\L Gamma isotopic analysis Location GW-09 1Z-361A GW-091Z-361B GW-10 2Z-361A GW-10 2Z-361B Collection Date 08-09-18 08-09-18 08-09-18 08-09-18 Lab Code EWW- 3301 MDC EWW- 3302 MDC EWW- 3304 MDC EWW- 3305 MDC Be-7 -3.3 +/- 13.4 < 27.9 -5.8 +/- 13.0 < 23.8 -8.9 +/- 9.8 < 18.7 -2.2 +/- 10.1 < 23.2 Mn-54 0.0 +/- 1.4 < 3.2 -0.3 +/- 1.3 < 2.3 1.0 +/- 1.3 < 2.8 0.7 +/- 1.3 < 2.5 Fe-59 0.3 +/- 2.9 < 6.8 2.2 +/- 2.5 < 5.5 0.7 +/- 2.4 < 5.4 0.2 +/- 2.2 < 3.8 Co-58 1.5 +/- 1.3 < 2.9 -0.4 +/- 1.3 < 2.8 0 9 +/- 1.3 < 2.9 1.0 +/- 1.2 < 2.7 Co-60 0.4 +/- 1.6 < 2.9 1.3 +/- 1.3 < 2.4 -1.0 +/- 1.3 < 1.6 -0.7 +/- 1.4 < 2.5 Zn-65 -1.6 +/- 3.0 < 4.6 -5.3 +/- 3.0 < 3.8 -0.7 +/- 2.6 < 4.6 1.1 +/- 2.5 < 4.8 Zr-Nb-95 0.0 +/- 1.5 < 4.4 -0.9 +/- 1.5 < 3.5 -1.7 +/- 1.4 < 3.1 -0.3 +/- 1.3 < 3.3 Cs-134 -0.7 +/- 1.4 < 3.0 ~1 9 +/- 1.3 < 2.7 0.2 +/- 1.3 < 2.3 1.4 +/- 1.3 < 2.3 Cs-137 -1.0 +/- 1.6 < 3.0 -0.3 +/- 1.5 < 2.6 0.4 +/- 1.5 < 2.6 1.8 +/- 1.5 < 2.6 Ba-La-140 -0.3 +/- 1.5 < 2.7 -0.8 +/- 1.5 < 3.9 -1.4+/-15 < 3.4 -2.8 +/- 1.6 . < 4.3 Location GW-09 1Z-361A GW-09 1Z-361 B GW-10 2Z-361A GW-10 2Z-3618 Collection Date 10-13-18 10-13-18 10-13-18 10-13-18 Lab Code EWW- 4377 MDC EWW- 4378 MDC EWW- 4379 MDC EWW- 4380 MDC Be-7 -2.6 +/- 10.5 < 31.2 5.7 +/- 10.0 < 27.1 -20.2 +/- 13.8 < 16.0 8.6 +/- 10.3 < 28.3 Mn-54 0.2 +/- 1.3 < 2.0 -0.4 +/- 1.2 < 1.6 0.9 +/- 1.4 < 3.0 0.3 +/- 1.4 < 2.8 Fe-59 1.3 +/- 2.2 < 3.7 0.8 +/- 2.1 < 4.0 1.0 +/-29 < 5.7 -1.5 +/- 2.5 < 4.6 Co-58 -1.9 +/- 1.3 < 1.7 -0.6 +/- 1.2 < 2.1 -0.4 +/- 1.4 < 3.0 -1.1 +/- 1.3 < 2.0 Co-60 0.3+/-1.3 < 2.0 -0.3 +/- 1.2 < 1.6 -0.1 +/- 1.4 < 2.2 -0.4 +/- 1.5 < 3.2 Zn-65 -0.4 +/- 2.5 < 5.1 0.1 +/-2.2 < 4.3 -3.0 +/- 3.5 < 6.2 -2.0 +/- 2.6 < 4.3 Zr-Nb-95 1.4 +/- 1.3 < 3.3 -0.2 +/- 1.3 < 3.4 -0.4 +/- 1.5 < 3.9 -2.3 +/- 1.5 < 3.6 Cs-134 -0.6 +/- 1.3 < 2.3 0.1 +/- 1.3 < 2.4 -1.8 +/- 1.6 < 3.1 -2.1 +/-1.3 < 2.5 Cs-137 0.7 +/- 1.5 < 2.1 0.2 +/- 1.4 < 2.6 0.8 +/- 1.7 < 3.2 -0 9 +/- 1.5 < 1.9 Ba-La~140 -0.1 +/-1.4 < 4.1 -0.2 +/- 1.4 < 2.5 1.7 +/- 1.6 < 2.6 1.3 +/- 1.5 < 5.2 Annual Average All Locations Be-7 -1.9 +/- 7.7 Mn-54 0.4 +/- 0.6 Fe-59 -0.3 +/- 1.7 Co-58 0.0 +/- 1.0 Co*-60 0.1 +/- 0.8 Zn-65 -0.8 +/- 1.8 Zr-Nb-95 -0.6 +/- 1.4 Cs-134 -0.4 +/- 0.9 Cs-137 0.6 +/- 1.1 Ba-La-140 -1.14 +/- 2.04 E-3

POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: =pCi/L Gamma isotopic analysis Location U2FSSDS GW-04 GW-15A,B Collection Date 01-31-18 01-18-18 01-25-18 Lab Code EW- 443 MDC EW- 181 MDC EW- 358 MDC Be-7 -0.8 +/- 9.7 < 21.6 4.3 +/- 13.5 < 21.7 -0.2 +/- 11.6 < 33.6 Mn-54 1.0 +/- 1.3 < 2.5 0.2 +/- 1.7 < 3.0 1.4+/-1.4 < 3.0 Fe-59 1.4+/-2.2 < 5.5 1.5 +/- 3.1 < 4.2 1.3 +/- 2.6 < 5.3 Co-58 0.6 +/- 1.1 < 1.7 -0.6 +/- 1.7 < 1.8 0.4 +/- 1.3 < 3.2 Co-60 0.4 +/- 1.5 < 3.1 -1.8 +/- 1.5 < 2.1 2.6 +/- 1.5 < 3.2 Zn-65 0.4 +/- 2.4 < 4.8 -1.1 +/- 3.5 < 3.5 0.0 +/- 2.9 < 5.6 Zr-Nb-95 0.3 +/- 1.3 < 2.9 -1.7 +/- 1.7 < 2.1 0.0 +/- 1.5 < 4.4 Cs-134 0.2 +/- 1.2 < 2.3 0.7+/-1.6 < 2.9 -1.5+/-1.5 < 2.8 Cs-137 0.1 +/- 1.5 < 2.6 1.3 +/- 1.8 < 2.5 -0.4 +/- 1.7 < 2.9 Ba-La-140 0.7 +/- 1.6 < 4.9 0.7 +/- 2.1 < 3.4 -4.7 +/- 1.6 < 3.7 Location U2FSSDS GW-04 GW-04 Collection Date 02-28-18 02-21-18 03-22-18 Lab Code EW- 837 EW- 611 EW- 962 Be-7 -7.1 +/- 9.6 < 26.3 23.2 +/- 16.0 < 34.0 -7.3 +/- 14.4 < 22.6 Mn-54 0.1 +/- 1.3 < 2.1 0.4 +/- 2.0 < 3.8 0.8 +/- 1.7 < 3.1 Fe-59 -0.2 +/- 2.5 < 6.3 -1.2 +/- 3.6 < 5.6 -0.6 +/- 2.8 < 4.5 Co-58 0.8 +/- 1.2 < 2.7 -0.7 +/- 2.0 < 2.6 0.2 +/- 1.5 < 2.3 Co-60 0.5 +/- 1.4 < 2.2 -2.0 +/- 2.0 < 2.2 -0.8 +/- 1.6 < 1.6 Zn-65 -1.0 +/- 2.4 < 2.8 -2.6 +/- 4.3 < 7.4 -0.5 +/- 3.3 < 4.3 Zr-Nb-95 -1.2 +/- 1.3 < 3.4 -4.2 +/- 2.4 < 2.0 -5.4 +/- 2.1 < 3.2 Cs-134 1.6 +/- 1.3 < 2.5 -1.3+/-2.1 < 3.4 -0.3 +/- 1.8 < 3.4 Cs-137 0.8 +/- 1.5 < 2.9 -0.5 +/- 2.0 < 2.2 1.3 +/- 1.8 < 3.6 Ba-La-140 -4.2 +/- 1.5 < 3.8 1.9 +/- 2.0 < 2.1 0.2 +/- 1.9 < 3.3 Location U2FSSDS GW-04 U2FSSDS Collection Date 03-31-18 04-18-18 04-30-18 Lab Code EW- 1075 EW- 1373 EWW- 1767 Be-7 9.1 +/- 16.1 < 40.0 10.9 +/- 17.1 < 32.5 4.4 +/- 10.1 < 20.6 Mn-54 1.2 +/- 1.7 < 4.1 -1.0+/-1.7 < 2.6 0.6 +/- 1.2 < 2.6 Fe-59 0.6 +/- 3.2 < 8.0 -3.7 +/- 3.7 < 3.8 -0.3 +/- 2.4 < 5.9 Co-58 0.1 +/- 1.7 < 3.4 0.4 +/- 1.7 < 3.3 -0.9 +/- 1.2 < 2.0 Co-60 0.9 +/- 1.9 < 3.7 -0.6 +/- 2.1 < 1.9 0.0 +/- 1.3 < 1.9 Zn-65 2.5 +/- 3.8 < 7.4 0.4 +/- 3.7 < 5.8 1.3 +/- 2.4 < 5.0 Zr-Nb-95 1.1 +/- 1.7 < 4.3 1.4 +/- 1.8 < 3.8 -0.6 +/- 1.3 < 3.4 Cs-134 -0.6 +/- 1.7 < 3.4 -1.6 +/- 1.8 < 3.6 -0.3 +/- 1.3 < 2.3 Cs-137 2.3 +/- 2.0 < 4.1 -0.5 +/- 1.9 < 3.0 -0.1 +/- 1.4 < 1.9 Ba-La-140 -9.1 +/- 2.2 < 2.9 4.1 +/- 2.1 < 7.3 -2.6 +/- 1.5 < 4.0

POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: = pCi\L Gamma isotopic analysis Location U2FSSDS GW-15A.B GW-04 Collection Date 05-31-18 05-15-18 05-22-18 Lab Code EW- 2299 MDC EW- 2062 MDC EW- 1977 MDC Be-7 -16.6 +/- 17.0 < 34.6 -0.5 +/- 11.3 < 30.5 -16.7 +/- 17.0 < 29.2 Mn-54 1.5 +/- 2.1 < 4.0 1.4+/-1.4 < 2.7 1.4 +/- 1.3 < 2.0 Fe-59 -2.6 +/- 3.6 < 10.2 0.7 +/- 2.3 < 6.2 -1.5 +/- 2.8 < 4.2 Co-58 -0.4 +/- 1.7 < 3.0 -0.5 +/- 1.4 < 2.9 -0.5 +/- 1.4 < 2.4 Co-60 1.2 +/- 2.0 < 3.7 0.2 +/- 1.5 < 2.4 -0.4 +/- 1.5 < 1.9 Zn-65 -3.5 +/- 4.0 < 7.3 2.4 +/- 2.6 < 5.5 -1.6 +/- 3.9 < 4.3 Zr-Nb-95 -0.4 +/- 1.7 < 4.8 -1.1 +/- 1.5 < 3.6 1.4 +/- 1.5 < 2.7 Cs-134 0.8+/-1.8 < 3.6 -0.4 +/- 1.4 < 2.7 -1.8 +/- 1.6 < 3.1 Cs-137 -0.4 +/- 2.0 < 3.2 1.0 +/- 1.5 < 3.1 -0.7 +/- 1.8 < 2.6 Ba-La-140 -1.6 +/- 2.3 < 4.3 -1.3 +/- 1.4 < 9.8 -2.0 +/- 2.6 < 8.0 Location GW-04 U2FSSDS GW-04 Collection Date 06-20..18 06-30-18 07-17-18 Lab Code EWW- 2403 EW- 2661 EW- 2769 Be-7 21.2 +/- 27.3 < 52.6 4.1 +/- 10.5 < 29.1 7.0 +/- 19.6 < 37.5 Mn~54 0.3 +/- 3.3 < 5.6 1.1 +/- 1.2 < 2.5 -1.9 +/- 1.9 < 1.8 Fe-59 4.3 +/- 6.5 < 9.8 -2.0 +/- 2.2 < 3.6 0.5 +/- 3.7 < 7.6 Co-58 1.2 +/- 3.1 < 3.8 0.4+/-1.3 < 3.0 -2.0 +/- 1.8 < 3.2 Co-60 -2.6 +/- 3.5 < 3.2 0.1 +/- 1.3 < 1.9 -1.0 +/- 2.3 < 2.5 Zn-65 -4.7 +/- 8.7 < 6.5 1.7 +/- 2.6 < 5.0 -1.2 +/- 3.9 < 3.4 Zr-Nb-95 1.8 +/- 3.8 < 5.3 0.5 +/- 1.4 < 3.1 -1.8 +/- 2.0 < 5.0 Cs-134 -4.4 +/-4.1 < 6.6 1.4 +/- 1.3 < 2.4 0.2 +/- 1.9 < 4.0 Cs-137 1.3 +/- 3.7 < 5.6 -0.8 +/- 1.4 < 1.7 0.9 +/- 2.2 < 2.7 Ba-La-140 -8.4 +/- 3.9 < 3.3 -0.8 +/- 1.5 < 4.9 -0.9 +/- 1. 7 < 4.2 Location GW-15A,B U2FSSDS GW-04 Collection Date 07-18-18 07-31-18 08-22-18 Lab Code EW- 2986 EW- 3198 EW- 3448 Be~7 -1.0 +/- 12.2 < 38.5 -7.0 +/- 12.2 < 22.7 8.0 +/- 21.1 < 41.4 Mn-54 0.9 +/- 1.5 < 3.1 0.3 +/- 1.8 < 3.0 2.9 +/- 2.6 < 4.1 Fe-59 4.1 +/- 2.5 < 10.2 0.3 +/- 3.2 < 6.7 -3.6 +/- 5.0 < 6.5 Co-58 -0.8 +/- 1.5 < 3.7 -0.7+/-1.4 < 2.0 -1.3 +/- 2.0 < 2.2 Co-60 0.1 +/- 1.6 < 2.7 0.1 +/- 1.6 < 2.6 -1.4 +/- 2.8 < 3.1 Zn-65 0.8 +/- 2.8 < 5.2 -0.4 +/- 3.2 < 7.1 -1.8 +/- 3.9 < 2.1 Zr-Nb-95 -3.2 +/- 1.6 < 6.2 0.5 +/- 1.6 < 3.4 1.4 +/- 2.4 < 4.3 Cs-134 0.5 +/- 1.5 < 2.8 -1.0+/-1.7 < 3.2 1.2 +/- 2.0 < 4.6 Cs-137 -0.9 +/- 1.8 < 3.6 -0.2 +/- 2.0 < 2.6 -2.3 +/- 2.7 < 3.8 Ba-La-140 -20.9 +/- 1.8 < 31.0 -1.5 +/- 2.0 < 2.8 -5.0 +/- 2.9 < 2.6 "LLD not met due to the low volume of the sample. E-5

POINT BEACH NUCLEAR PLANT Supplemental Analyses

Units: pCi\L Gamma isotopic analysis Location U2FSSDS U2FSSDS GW-04 Collection Date 08-31-18 09-30-18 09-21-18 Lab Code EW- 3745 MDC EW- 4195 MDC EW- 3916 MDC Be-7 11.3+/-9.7 < 23.6 11.7 +/- 12.3 < 28.4 4.2 +/- 6.2 < 20.3 Mn-54 -0.7 +/- 1.2 < 1.8 -0.1 +/- 1.3 < 2.6 -0.7 +/- 0.6 < 1.0 Fe-59 2.1 +/- 2.1 < 3.8 0.7 +/- 2.7 < 4.7 0.1 +/- 1.3 < 5.5 Co-58 0.6 +/- 1.2 < 2.8 0.0 +/- 1.2 < 2.0 0.1 +/- 0.6 < 1.7 Co-60 0.7 +/- 1.3 < 2.6 0.0 +/- 1.5 < 2.4 1.2 +/- 0.6 < 1.3 Zn-65 0.3 +/- 2.5 < 4.8 -5.3 +/- 3.2 < 5.1 0.8 +/- 1.3 < 2.7 Zr-Nb-95 0.9 +/- 1.4 < 3.6 -1.0 +/- 1.4 < 3.3 1.3 +/- 0.7 < 3.5 Cs-134 0.3 +/- 1.2 < 2.4 -1.8+/-1.3 < 2.6 -0.8 +/- 0.6 <1.4 Cs-137 1.0 +/- 1.4 < 2.6 -0.5 +/- 1.4 < 2.4 0.1 +/- 0.7 < 1.1 Ba-La-140 2.0 +/- 1.5 < 4.8 -0.4 +/- 1.5 < 7.7 -8.9 +/- 0.8 < 14.5 Location U2FSSDS GW-15A,B GW-04 Collection Date 10-31-18 10-14-18 10-22-18 Lab Code EW- 4879 MDC EW- 4391 MDC EW- 4558 MDC Be-7 -1.3 +/- 10.0 < 24.0 -9.2 +/- 14.2 < 19.2 6.1 +/- 14.3 < 35.3 Mn-54 -0.8 +/- 1.3 < 1.9 0.5 +/- 1.6 < 3.1 1.1 +/- 1.7 < 2.8 Fe-59 -2.9 +/- 2.2 < 4.9 -2.0 +/- 3.1 < 4.0 1.6 +/- 2.7 < 3.4 Co-58 1.4 +/- 1.3 < 3.0 0.1 +/- 1.5 < 3.0 0.4 +/- 1.4 < 1.6 Co-60 -0.6 +/- 1.4 < 2.2 -0.2 +/- 1.5 < 1.3 0.3 +/- 1.6 < 2.0 Zn-65 1.5 +/-2.6 < 4.6 -7.0 +/- 3.7 < 5.9 0.5 +/- 3.5 < 3.4 Zr-Nb-95 -0.6 +/- 1.3 < 3.8 -1.6 +/- 1.7 < 4.5 -0.6 +/- 1.8 < 4.0 Cs-134 -1.5 +/- 1.3 < 2.3 -1.3 +/- 1.6 < 3.0 0.5 +/- 1.8 < 3.4 Cs-137 1.3 +/- 1.5 < 2.8 0.1 +/- 1.8 < 3.5 0.0 +/- 2.1 < 3.6 Ba-La-140 1.7 +/- 1.4 < 5.9 -1.5 +/- 1.9 < 6.7 -0.3 +/- 1.8 < 6.7 Location U2FSSDS GW-04 GW-04 Collection Date 11-30-18 11-27-18 12-20-18 Lab Code EW- 5161 MDC EW- 5030 MDC EW- 5359 MDC Be-7 -16.6 +/- 13.4 < 15.6 -7.8 +/- 18.4 < 39.2 2.8 +/- 19.8 < 36.3 Mn-54 0.7+/-1.4 < 3.2 0.4 +/- 1.8 < 2.8 1.1 +/- 1.9 < 3.1 Fe-59 2.4 +/- 2.8 < 4.9 0.5 +/- 3.6 < 6.0 0.4 +/- 3.6 < 5.1 Co-58 -0.3 +/- 1.4 < 2.4 0.9 +/- 1.7 < 2.5 -0.4 +/- 1. 7 < 2.0 ff Co-60 1.4 +/- 1.5 < 2.7 1.2 +/- 2.0 < 3.4 0.1 +/- 1.9 < 2.7 Zn-65 1.9 +/- 3.0 < 5.7 3.3 +/- 3.9 < 6.3 -1.7 +/- 4.2 < 5.2 r-~ Zr-Nb-95 -1.2 +/- 1.6 < 3.0 -1.8 +/- 1. 7 < 3.8 -2.1 +/- 2.3 < 3.2 Cs-134 -0.8 +/- 1.4 < 2.9 1.4 +/- 1.9 < 3.8 -2.0 +/- 1.9 < 3.5 Cs-137 -0.3 +/- 1.5 < 2.5 1.0 +/- 2.0 < 3.9 0.3 +/- 2.3 < 3.7 Ba-La-140 -1.0 +/- 1.6 < 3.7 -2.1 +/- 2.0 < 9.0 1.6 +/- 2.3 < 4.2 f

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POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: = pCi\L Gamma isotopic analysis Location U2FSSDS Collection Date 12-31-18 Lab Code EW- 5537 MDC Be-7 -8.2 +/- 10.5 < 26.5 Mn-54 -0.4 +/- 1.3 < 2.1 Fe-59 -1.2 +/- 2.4 < 5.4 Co-58 1.3 +/- 1.3 < 2.8 Co-60 0.1 +/- 1.5 < 2.6 Zn-65 -2.7 +/- 2.6 < 4.6 Zr-Nb-95 -2.3 +/- 1.5 < 3.8 Cs-134 0.5 +/- 1.3 < 2.5 Cs-137 -0.6 +/- 1.5 < 2.7 Ba-La-140 2.6 +/- 1.6 < 6.3 Be-7 2.9 +/- 10.7 Mn-54 0.6 +/- 1.0 Fe-59 0.1 +/- 2.2 Co-58 *0.2 +/- 0.8 Co-60 -0.2 +/- 1.2 Zn-65 w0.7 +/- 2.1 Zr-Nb-95 -0.7 +/- 1.9 Cs-134 *0.4 +/- 1.4 Cs-137 0.0 t 2.6 Ba-La-140 w2.4 +/- 5.5 E-7

POINT BEACH NUCLEAR PLANT APPENDIX F Special Analyses F-1

POINT BEACH NUCLEAR PLANT Special Analyses Precipitation samples Units = pCi/L Location GW-09 1Z-361A GW-09 12-3618 GW-10 2Z-361A Collection Date 05-27-18 05-27-18 05-27-18 Lab Code EWW- 2078 MDC EWW- 2079 MDC EWW- 2080 MDC Fe-55 -21.517 +/- 401.396 < 663.220 -85.537 +/- 395.46 < 659.13 -10.759 +/- 401.97 < 663.22 Ni-63 -0.029 +/- 0 041 < 0.068 0.001 +/- 0.043 < 0.070 -0.032 +/- 0.041 < 0.069 Sr-89 -0.838 +/- 4.429 < 4.524 1.519 +/- 3.984 < 4.653 0.46795 +/- 4.293 < 4.349 Sr-90 1.376 +/- 1.614 < 3.130 0.071 +/- 1.408 < 3.018 0.962 +/- 1.574 < 3.121 Tc-99 0 350 +/- 3.334 < 5.482 -0.759 +/- 3.314 < 5.482 1.021 +/- 3.345 < 5.482 F-2

~~L A"ll Environmental, Inc.

7flll .r'\.1 Midwest Laboratory 700 Landl.w!hr l?aBd

N<>rrhbrool<, JL 60062-23 10 phone (847) 564-0700. fB* (847) 564-4517 Jerri Walters LABORATORY REPORT NO.: 8006-100-1281 Radiation Protection Mgr. DATE: 05-14-18 Point Beach Nuclear Plant SAMPLES RECEIVED: 04-09-18 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, 2018. Period: 1st Quarter, 2018 Date Annealed: 12106/17 Date Placed: 01/05/18 Date Removed: 04/04/18 Date Read: 04/13/18 Days in the Field: 89 Days from Annealing to Readout: 128 In-transit exposure: 5.84 +/- 0.73 NetmR NetmR Location Total mR NetmR Std Qtr per 7 days SGSF-North 19.1 +/- 0.9 13.3+/-1.1 13.6 +/- 1.2 1.04 +/- 0.09 SGSF-East 20.1 +/- 1.2 14.2 +/- 1.4 14.5+/-1.4 1.12 +/- 0.11 SGSF-South 19.8 +/- 0.6 14.0 +/- 1.0 14.3 +/- 1.0 1.10 +/-0.08 SGSF-West 18.6 +/- 0.6 12.8 +/- 0.9 13.0 +/- 1.0 1.00 +/- 0.07 ISFSI-North 37.0 +/-1.0 31.2 +/- 1.2 31.9 +/- 1.3 2.45 +/- 0.10 ISFSI-East 55.3 +/- 1.4 49.5 +/- 1.6 50.6 +/-1.6 3.89 +/- 0.13 ISFSI-South 22.0 +/- 0.9 16.1 +/- 1.2 16.5 +/- 1.2 1.27 +/- 0.09 ISFSI*West 57.2 +/- 2.7 51.3 +/- 2.8 52.5 +/- 2.9 4.04 +/-0.22 Control 24.6 +/- 0.9 18.8 +/- 1.2 19.2 +/- 1.2 1.48 +/- 0.09

                                                                                                               .---...uY'-.;/?sf~J ~~

Ashok Banavali, Ph.D. Quality Assurance Laboratory Manager

   ~*J!l A-rJ Er}vir-onmental,lnc.

7/~r-\.1 Mrdwest: La.borat:ory 700 Lsndwehr RolJd

Norrnbrook. /L 60062-2310 phone (Bill) 564-0700 * '"" (847) SS4-4517 Jerri Walters LABORATORY REPORT NO.: 8006-100-1291 Radiation Protection Mgr. SAMPLES RECEIVED: 07-05-18 Point Beach Nuclear Plant PURCHASE ORDER NO.:

NextEraEnergy 6610 Nuclear Road Two Rivers, WI 54241 Below are the results of the readout of supplemental TLDs deployed during the second quarter, 2018. Period: 2nd Quarter, 2018 Date Annealed: 03/07/18 Date Placed: 04/04/18 Date Removed: 07/02/18 Date Read: 07/05/18 Days in the Field: 89 n Days from Annealing to Readout: 120 II In-transit exposure: 4.31 +/- 0.43 j NetmR NetmR Location Total mR NetmR Std Otr per 7 days SGSF-North 15.8 +/- 0.5 11.5+/-0.7 11.7 +/- 0.7 0.90 +/-0.05 SGSF-East 16.8 +/- 0.4 12.5 +/- 0.6 12.8 +/-0.6 0.98 +/- 0.05 SGSF-South 16.7 +/- 0.3 12.4 +/-0.5 12.7 +/- 0.5 0.97 +/- 0.04 SGSF-West 16.1 +/- 0.5 11.8 +/- 0.6 12.0 +/-0.7 0.93 +/- 0.05 ISFSI-North 30.0 +/- 1.6 25.7 +/- 1.7 26.2 +/- 1.7 2.02 +/- 0.13 ISFSI*East 56.6 +/- 0.9 52.3 +/- 1.0 53.5 +/- 1.0 4.11 +/- 0.08 ISFSI*South 22.0 +/- 1.1 17.7 +/- 1.2 18.1 +/- 1.2 1.40 +/-0.09 ISFSI-West 58.6 +/- 2.6 54.3 +/- 2.6 55.5 +/- 2.7 4.27 +/-0.20 Control 20.5 +/- 0.7 16.2 +/- 0.8 16.5 +/- 0.8 1.27 +/- 0.06 APPROVED

                                                                                                    ~~c.NJ?
                                                                                                         ~.r.~.o. ~ /II~                 f1 Quality Assurance                                                                      Laboratory Manager

~~L A '~I Environmental. Inc.

7f" .1"""\1 Midwest Laboratory 700 Lendwenr Ro&d

Northbrook. !L 60062-2310 phone (847) S64-070D. '"" (847) 564-4517 Jerri Walters LABORATORY REPORT NO.: 8006-100-1300 Radiation Protection Mgr. SAMPLES RECEIVED: 10-08-18 Point Beach Nuclear Plant PURCHASE ORDER NO.:

NextEraEnergy 661 0 Nuclear Road Two Rivers, WI 54241 Below are the results of the readout of supplemental TLDs deployed during the third quarter, 2018. Period: 3rd QuaJter, 2018 Date Annealed: 06/07/18 Date Placed: 07/02/18 Date Removed: 10/01/18 Date Read: 10/08/18 Days in the Field: 91 Days from Annealing to Readout: 123 In-transit exposure: 4.56 +/- 0.34 NetmR NetmR Location Total mR NetmR Std Otr per7 days SGSF-N01th 18.1 +/- 0.3 13.5 +/- 0.4 13.5 +/- 0.4 1.04 +/- 0.03 SGSF-East 18.0 +/- 1.2 13.4 +/- 1.2 13.4 +/- 1.2 1.03 +/-0.09 SGSF-South 18.2 +/- 1.4 13.6 +/- 1.4 13.6 +/- 1.4 1.05 +/-0.11 SGSF-West 16.6 +/- 0.7 12.1 +/- 0.8 12.1 +/- 0.8 0.93 +/- 0.06 JSFSJ-North 35.5 +/-0.9 30.9 +/- 0.9 30.9 +/- 0.9 2.38 +/-0.07 JSFSI-East 58.0 +/- 1.4 53.5 +/- 1.5 53.5 +/- 1.5 4.11 +/- 0.11 JSFSI-South 22.7 +/- 1.2 18.1 +/-1.2 18.1 +/- 1.2 1.39 +/- 0.09 ISFSI-West 57.7 +/- 3.0 53.2 +/- 3.0 53.2 +/- 3.0 4.09 +/- 0.23 Control 23.0 +/- 1.2 18.5 +/- 1.3 18.5 +/- 1.3 1.42 +/- 0.10 APPROVED I Forrest G. Shaw Ill Ashok Banavali, Ph.D. I Quality Assurance laboratory Manager

A-rl EQvironrnent:al, Inc.

       ~I           M1dwest: Laborat:ory 700 Landwehr Road

Northbcook., IL 60062-2310 ph<Jne (847) 564-0700
fex (847) 564-4517 Jerri Walters LABORATORY REPORT NO.: 8006-100-1319 Radiation Protection Mgr. SAMPLES RECEIVED: 01-11-19 Point Beach Nuclear Plant PURCHASE ORDER NO.:

NextEra Energy 6610 Nuclear Road Two Rivers, WI 54241 Below are the results of the readout of supplemental TLDs deployed during the fourth quarter, 2018. Period: 4th Quarter, 2018 Date Annealed: 09/07/18 Date Placed: 10/01/18 Date Removed: 01/08/19 Date Read: 01/14/19 Days in the Field: 99 Days from Annealing to Readout: 129 In-transit exposure: 4.67 +/- 0.39 NetmR NetmR Location Total mR Net mR Std Qtr per 7 days SGSF-North 18.1 +/- 1.1 13.5 +/- 1.2 12.4 +/- 1.1 0.95 +/- 0.08 SGSF-East 21.1 +/- 0.7 16.4 +/- 0.8 15.1+/-0.7 1.16 +/- 0.06 SGSF-South 21.7+/-0.5 17.1 +/- 0.7 15.7 +/- 0.6 1.21 +/- 0.05 SGSF-West 18.5+/-0.4 13.8 +/- 0.6 12.7 +/- 0.5 0.97 +/- 0.04 ISFSI-North 34.2 +/- 2.0 29.6 +/- 2.0 27.2 +/- 1.8 2.09 +/- 0.14 ISFSI-East 71.2 +/- 2.2 66.6 +/- 2.2 61.2 +/- 2.1 4.71 +/- 0.16 ISFSI-South 31.5+/-2.1 26.8 +/- 2.1 24.7 +/- 1.9 1.90 +/- 0.15 lSFSI-West 73.9 +/- 3.8 69.2 +/- 3.9 63.6 +/- 3.6 4.89 +/- 0.27 Control 26.5 +/- 0.9 21.9+/-1.0 20.1 +/- 0.9 1.55 +/- 0.07 yJdft#t 'ir-- J./<t/t 1 Forrest G. Shaw Ill Ashok Banavali, Ph.D. Quality Assurance Laboratory Manager

APPENDIX 2 NextEra Energy Point Beach, LLC Offsite Dose Calculation Manual Revision 20 Issued 02/27/2018 278 pages follow

ODCM OFFSITE DOSE CALCULATION MANUAL DOCUMENT TYPE: Controlled Reference CLASSIFICATION: N/A REVISION: 20 REVIEWER: Onsite Review Group APPROVAL AUTHORITY: Plant Manager PROCEDURE OWNER (title): Group Head OWNER GROUP: Chemistry Verified Current Copy: Signature Date Time List pages used for Partial Performance Controlling Work Document Numbers

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS SECTION TITLE PAGE 1.0 RECORD OF REVISIONS ............................................................................................ 7

2.0 INTRODUCTION

.......................................................................................................... 8 2.1   Purpose ............................................................................................................................ 8 2.2   Guidance ......................................................................................................................... 8 2.3  General Responsibilities ................................................................................................. 9 2.4  Audits .............................................................................................................................. 9 2.5  Definitions ....................................................................................................................... 9 3.0        REPORTING REQUIREMENTS ................................................................................. 14 3.1  Annual Monitoring Report ............................................................................................. 14 3.2  Record Retention Requirements .................................................................................... 16 4.0        RADIATION MONITORING SYSTEM AND RELEASE ACCOUNTING .............. 17 5.0        SPECIFICATIONS AND SURVEILLANCE REQUIREMENTS ............................... 22 5.1  Specifications ................................................................................................................. 22 5.2  Surveillance Requirements ............................................................................................ 22 6.0        LIQUID EFFLUENT SPECIFICATIONS AND SURVEILLANCE REQUIREMENTS ......................................................................................................... 23 6.1   Concentration ................................................................................................................. 23 6.2   Dose ............................................................................................................................... 26 6.3   Liquid Radwaste Treatment System .............................................................................. 27 6.4   Liquid Effluent Monitoring Instrumentation ................................................................. 28 7.0        GASEOUS EFFLUENT SPECIFICATIONS AND SURVEILLANCE REQUIREMENTS ......................................................................................................... 32 7.1   Dose Rate ....................................................................................................................... 32 7.2   Dose- Noble Gases ....................................................................................................... 35 7.3   Dose- I-131, I-133, H-3 and Radionuclides in Particulate Form ................................. 36 7.4   Gaseous Radwaste Treatment System ........................................................................... 38 7.5   Gaseous Effluent Monitoring Instrumentation ............................................................. .40 Page 2 of278                                                    REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS SECTION TITLE PAGE 8.0 TOTAL DOSE ............................................................................................................... 44 8.1 Specification .................................................................................................................. 44 8.2 Applicability .................................................................................................................. 44 8.3 Action ............................................................................................................................. 44 8.4 Surveillance Requirements ............................................................................................ 44 9.0 LIQUID EFFLUENT CALCULATIONS .................................................................... .46 9.1 Monitor Alarm Setpoint Determination ........................................................................ .46 9.2 Liquid Dose Calculations ............................................................................................... 51 9.3 Dose Projections ................. ,.......................................................................................... 55 10.0 GASEOUS EFFLUENT CALCULATIONS ................................................................ 56 10.1 Monitor Alarm Setpoint Determination ......................................................................... 56 10.2 Carbon-14 ...................................................................................................................... 61 10.3 Dose Rate Calculations- Noble Gases .......................................................................... 63 10.4 Dose Rate Calculations- Radioiodine, Tritium, Particulates ........................................ 64 10.5 Dose Calculations -Noble Gases .................................................................................. 65 10.6 Dose Calculations -Radioiodine, Tritium, Particulates ................................................ 66 10.7 Gaseous Dose Projection ............................................................................................... 67 11.0 DETERMINATION OF TOTAL DOSE ...................................................................... 120 12.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ..................... 121 12.1 REMP Administration .................................................................................................. 121 12.2 REMP Implementation ................................................................................................. 126 13.0 RADIOLOGICAL EFFLUENT CONTROLS PROGRAM ........................................ 140 13.1 Radiological Effluent Controls Program ...................................................................... 140 13.2 Radioactive Effluent Control and Accountability ......................................................... 144 13.3 Radioactive Effluent Monitoring Instrumentation Functionality Requirements .......... 145 13.4 Solid Radioactive Waste ............................................................................................... 146

14.0 REFERENCES

............................................................................................................. 147 Page 3 of278                                                   REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS SECTION TITLE PAGE Appendix A Liquid Pathway EMEC For Use In Setpoint Calculations .......................................... .148 Appendix B Liquid Dose Factors Technical Basis ........................................................................... 153 Appendix C Gaseous Pathway Setpoint Calculations ....................................................................... 15 8 Appendix D Gaseous Dose Factors Technical Basis ......................................................................... 162 Appendix E Derivation of Dilution Factors Using Regulatory Guide 1.113 .................................... 177 Appendix F Radiological Impact Of Sewage Treatment Sludge Disposal ....................................... 182 Appendix G ....................................................................................................................................... 187 Appendix H Modification #1 To NRC Submittal ............................................................................ .239 Appendix I Modification #2 To NRC Submittal ............................................................................. 241 Appendix J Modification #3 To NRC Submittal ............................................................................. 244 Appendix K Liquid Effluent Dose Conversion Factors .................................................................... 246 Appendix L Gaseous Effluent Dose Conversion Factors ................................................................. 262 TABLES Table 4-1 Radioactive Liquid Waste Effluent Monitors ................................................................ 18 Table 4-2 Radioactive Gaseous Waste Effluent Monitors ............................................................. 19 Table 6-1 Radioactive Liquid Waste Sampling And Analysis Program ........................................ 25 Table 6-2 Radioactive Liquid Effluent Monitoring Instrumentation ............................................. 30 Table 6-3 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements ................................................................................................................. 31 Table 7-1 Radioactive Gaseous Waste Sampling And Analysis Program ..................................... 34 Table 7-2 Gaseous Effluent Monitoring Instrumentation ............................................................. .42 Table 7-3 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements ................................................................................................................. 43 Page 4 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS SECTION TITLE PAGE Table 9-1 Liquid Effluent Pathways .............................................................................................. 50 Table 9-2 Liquid Effluent Sub-Pathways ............................................................... ,....................... 52 Table 9-3 PBNP Site-Specific Liquid Dose Commitment Factors, Aio ......................................... 53 Table 10-1 Gaseous Effluent Pathways ............................................................................................ 59 Table 10-2 Controlling Locations, Pathways And Atmospheric Dispersion For Dose Calculations .................................................................................................................... 60 Table 10-3 Dose Factors For Noble Gases ....................................................................................... 64 Table 10-4 RioJ Inhalation Pathway Dose Factors- Adult .............................................................. 68 Table 10-5 RioJ Inhalation Pathway Dose Factors- Teen ............................................................... 71 Table 10-6 RioJ Inhalation Pathway Dose Factors- Child .............................................................. 74 Table 10-7 RioJ Inhalation Pathway Dose Factors- Infant ............................................................. 77 Table 10-8 RioJ Grass-Cow-Milk Pathway Dose Factors- Adult ................................................... 80 Table 10-9 RioJ Grass-Cow-Milk Pathway Dose Factors- Teen .................................................... 83 Table 10-10 RioJ Grass-Cow-Milk Pathway Dose Factors- Child ................................................... 86 Table 10-11 RioJ Grass-Cow-Milk Pathway Dose Factors- Infant. .................................................. 89 Table 10-12 RioJ Grass-Cow-Meat Pathway Dose Factors- Adult .................................................. 92 Table 10-13 RioJ Grass-Cow-Meat Pathway Dose Factors -Teen .................................................... 95 Table 10-14 RioJ Grass-Cow-Meat Pathway Dose Factors- Child ................................................... 98 Table 10-15 RioJ Produce Pathway Dose Factors- Adult ................................................................ 101 Table 10-16 RioJ Produce Pathway Dose Factors- Teen ................................................................. 104 Table 10-17 RioJ Produce Pathway Dose Factors - Child ................................................................ 107 Table 10-18 RioJ Leafy Vegetable Pathway Dose Factors -Adult. .................................................. 11 0 Table 10-19 RioJ Leafy Vegetable Pathway Dose Factors- Teen .................................................... 113 Table 10-20 RioJ Leafy Vegetable Pathway Dose Factors- Child ................................................... 116 Table 10-21 RioJ Ground Plane Pathway Dose Factors .................................................................... 119 Table 12-1 Sample Types And Associated Lower Level Of Detection (LLD) And Notification Level Values ............................................................................................. 132 Table 12-2 Radiological Environmental Sampling Locations ........................................................ 134 Table 12-3 PBNP Radiological Environmental Sample Collection And Analysis Frequency ....... 136 Page 5 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS SECTION TITLE PAGE Table A-1 Liquid Effluent Volumes .............................................................................................. 149 Table A-2 Liquid Effluent Releases ............................................................................................... 149 Table A-3 Liquid Effluent Concentrations ..................................................................................... 151 Table A-4 Beta Corrected Setpoints ............................................................................................... 152 Table C-1 Noble Gas Releases ....................................................................................................... 159 Table C-2 Average Annual Discharge Volume ............................................................................. 159 Table C-3 Noble Gas Setpoint Parameter Calculation ................................................................... 160 Table C-4 RMS AIRBORNE ALARM SETPO INTS ................................................................... 161 Table E-1 Surface Dilution Factors For Liquid Effluents In A Large Lake ................................. .177 Table E-2 Dilution Factors ............................................................................................................ 181 FIGURES Figure 4-1 Radioactive Liquid Waste Effluent Monitors ................................................................ 20 Figure 4-2 Radioactive Gaseous Waste Effluent Monitors ............................................................. 21 Figure 12-1 Radioactive Environmental Sampling Locations .......................................................... 137 Figure 12-2 Radiological Environmental Sampling Locations ........................................................ 13 8 Figure 12-3 Radiological Environmental Sampling Locations ........................................................ 139 Page 6 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 1.0 RECORD OF REVISIONS Per TS 5.5.1.C, licensee initiated changes to the Offsite Dose Calculation Manual (ODCM) shall be documented and records of reviews performed shall be retained. This documentation shall contain sufficient information to support the changes(s) together with the appropriate analyses or evaluations justifying the changes( s), and a determination that the change( s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations. These changes shall become effective after receiving concurrence from the Onsite Review Group (ORG)* and approval of the Plant General Manager, and shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Monitoring Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e. month and year) the change was implemented.

    *NOTE: Pursuant to the Procedure, Plan and Program Review Matrix approved by the Plant General Manager, changes that have been determined to be editorial do not need ORG approval.

Page 7 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

2.0 INTRODUCTION

2.1 Purpose The PBNP Offsite Dose Calculation Manual contains the current methodology and parameters for the calculation of offsite doses due to radioactive gaseous and liquid effluents. This manual describes a methodology for demonstrating compliance with 10 CFR 50, Appendix I dose limits. Compliance with Appendix I is demonstrated by periodic calculation of offsite doses based on actual plant releases and comparison to Appendix I dose limits. The manual also details the methodology for the determination of gaseous and liquid effluent monitor alarm setpoints. The PBNP Radiation Monitoring System (RMS) effluent monitor alarm setpoints are established to ensure that controlled releases of liquid and gaseous radioactive effluents are maintained as low as is reasonably achievable. The setpoints also are established to ensure that the dose rate from radioactive material released in effluents to the atmosphere do not exceed 500 mrem/yr at the site boundary and to ensure that the concentrations of radioactive materials released in liquid effluents to the unrestricted area conform to (do not exceed) 10 times the concentration values in Table 2, Column 2 of Appendix B to 10 CFR 20 as specified in TS 5.5.4.g. The manual also details the methodology for evaluating the radiological impact of sewage treatment sludge disposal. This methodology addresses the commitments made to the United States Nuclear Regulatory Commission in our application dated October 8, 1987 (NRC-87-104) and accepted by the USNRC in a letter dated January 13, 1988 (NPC-30260). This application was submitted in accordance with the provisions of 10 CFR 20.302(a). Dose limits are established in the application to ensure the health and safety of the maximally exposed member of the general public and the inadvertent intruder. 10 CFR 50, Appendix I dose limits do not apply to sewage treatment sludge disposal. 2.2 Guidance The following sources provided guidance for this document: U. S. Nuclear Regulatory Commission, Regulatory Guide 1.1 09, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I", Revision 1, October 1977. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I", Revision 1, Apri11977. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste", Revision 2, June 2009. Page 8 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL U.S. Nuclear Regulatory Commission, NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", Revision 2, May 1982. U.S. Nuclear Regulatory Commission, NUREG-1301, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors", April1991. 2.3 General Responsibilities The primary responsibility for the implementation of the PBNP offsite dose calculation program and for any actions required by the program resides with Chemistry. Chemistry will provide the technical, regulatory, licensing, and administrative support necessary to fulfill the requirements of this manual. The calculation of offsite doses and analysis of data are Chemistry responsibilities. The Plant General Manager, PBNP is responsible for assuring that Radiation Monitoring System alarm setpoints are established and maintained in accordance with the methodologies outlined in this manual. The Plant General Manager, PBNP is also responsible for assuring the performance of periodic release summaries for the purpose of demonstrating compliance with PBNP effluent release limits. 2.4 Audits Audits of the activities encompassed by the ODCM, the Radiological Effluent Control Program (Section 13.0 of this manual), and the Radiological Environmental Monitoring Program (Section 12.0 of this manual) and its implementing procedures shall be scheduled, performed, and reported in accordance with the Quality Assurance Topical Report. 2.5 Definitions ABNORMAL RELEASE An ABNORMAL RELEASE is an unplanned or uncontrolled emission of an effluent containing plant related, licensed radioactive material. ACTION ACTION shall be that part of a specification that prescribes remedial measures required under designated conditions. BATCH RELEASE A BATCH RELEASE is a release of a discrete liquid volume from a tank or any isolatable containment containing radionuclide(s) whose inputs to the volume were secured prior to sampling for discharge and remains secured until the discharge is completed. Page 9 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL CHANNEL CALIBRATION A CHANNEL CALIBRATION is the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input. The CHANNEL CALIBRATION SHALL encompass the entire channel including the sensors and alarm, interlock and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated. CHANNEL CHECK CHANNEL CHECK is a qualitative determination of acceptable FUNCTIONALITY made by observing channel behavior during operation. This shall include, where possible, comparison of the channel with other independent instrumentation channels measuring the same parameter. CONTINUOUS RELEASE A CONTINUOUS RELEASE is a discharge of liquid or gaseous radioactive effluents of a non-discrete volume from a source containing radionuclide(s) that usually has make-up flow during the release. DISCHARGE A DISCHARGE is a radioactive effluent that enters an unrestricted area. FUNCTIONAL- FUNCTIONALITY FUNCTIONALITY is an attribute of an SSC(s) that is not controlled by TSs. An SSC not controlled by TSs is FUNCTIONAL or has FUNCTIONALITY when it is capable of performing its function(s) as set forth in the CLB. These CLB function(s) may include the capability to perform a necessary and related support function for an SSC(s) controlled by TSs. FUNCTIONAL TEST FUNCTIONAL TEST is the injection of a simulated signal into the channel to verify that it is FUNCTIONAL, including alarm and/or trip initiating action. This shall include, where possible, a comparison of the channel with other independent channels measuring the same variable. Page 10 of 278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL GASEOUS RADWASTE TREATMENT SYSTEM The GASEOUS RADWASTE TREATMENT SYSTEM consists ofthose components or devices utilized to reduce radioactive material in effluents released to the atmosphere. The system consists of the following:

Gas decay tanks,
Drumming area ventilation exhaust duct filter assembly (F-26),
Unit 1 and 2 containment purge exhaust filter assemblies (1/2 F-IlA/B),
Air ejector decay duct filter assembly (F-30),
Auxiliary building ventilation filter assembly (F-25, nominal11,214 CFM exhaust pathway),
Chemistry laboratory exhaust duct filter assembly (F -21 ),
Service building ventilation exhaust duct filter assembly (F-20),
Auxiliary building ventilation filter assemblies (F-23, F-29, nominal34,150 CFM exhaust pathway).

LIQUID RADWASTE TREATMENT SYSTEM The LIQUID RADWASTE TREATMENT SYSTEM consists ofthose components or devices used to reduce radioactive material in liquid effluent. The system consists of the following:

Waste evaporator,
Polishing demineralizers,
Advanced Liquid Processing System (ALPS)
Boric acid evaporator feed and condensate demineralizers MEMBER OF THE PUBLIC (10 CFR 20)

MEMBER OF THE PUBLIC as defined by 10 CFR 20.1003: Means any individual except when that individual is receiving an occupational dose. (TRM 4.1) MEMBER OF THE PUBLIC (40 CFR 190) MEMBER OF THE PUBLIC as defined by 40 CFR 190.02: Means any individual that can receive a radiation dose in the general environment, whether he may or may not also be exposed to radiation in an occupation associated with a nuclear fuel cycle. However, an individual is not considered a member of the public during any period in which the individual is engaged in carrying out any operation which is part of the nuclear fuel cycle. (TRM4.1) Page 11 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL NUCLEARFUELCYCLE NUCLEAR FUEL CYCLE as defined by 40 CFR 190.02: Means the operations defined to be associated with the production of electrical power for public use by any fuel cycle through the use of nuclear energy. OPERABLE-OPERABILITY A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety functions{s), and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling or seal water, lubrication and other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its specified safety function(s) are also capable of performing their related support function(s). PURGE-PURGING PURGE or PURGING is any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement. RELEASE A RELEASE is an effluent from the plant regardless of where the effluent is deposited. SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity. SPECIFIED FUNCTION/SPECIFIED SAFETY FUNCTION The definition of operability refers to the capability to perform the "specified function" at non-improved TSs plants or "specified safety function" at improved TSs plants. The specified safety function(s) in the CLB for the facility. In addition to providing the specified safety function, an SSC is expected to perform as designed, tested and maintained. When system capability is degraded to a point where it cannot perfmm with reasonable expectation or reliability, the SSC should be judged inoperable, even if at this instantaneous point in time the SSC(s) could provide the specified safety function. Page 12 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL UNRESTRICTED AREA An UNRESTRICTED AREA is any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials. (TRM4.I) URANIUM FUEL CYCLE The URANIUM FUEL CYCLE is defined in 40 CFR Part 190.02(b) as: "The operation of milling of uranium ore, chemical conversion of uranium, isotopic enrichment of uranium, fabrication of uranium fuel, generation of electricity by a light-water-cooled nuclear power plant using uranium fuel, and reprocessing of spent uranium fuel, to the extent that these directly support the production of electrical power for public use utilizing nuclear energy, but excludes mining operations, operations at wasted disposal sites, transportation of any radioactive material in support of these operations, and the use of recovered non-uranium special nuclear and by-product materials from the cycle". VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. VENTING VENTING is the controlled process of discharging air or gas form a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process. Page 13 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 3.0 REPORTING REQUIREMENTS 3.1 Annual Monitoring Report In accordance with TS 5.6.2 and 5.6.3, the Annual Monitoring Report covering the operation of the units shall be submitted in accordance with 10 CFR 50.36a. The annual monitoring report shall be submitted by April30 of each calendar year to the administrator of the appropriate Regional NRC office or designee and shall include:

a. A summary of the quantities of radioactive liquid and gaseous effluents released from the plant with data summarized on a semi-annual basis. The material provided shall be consistent with the objectives outlined in Sections 6.2, 7.2 and 7.3 of the ODCM and in conformance with 10 CFR 50, Appendix I, Section IV.B.l. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as an addendum in the next Annual Monitoring Report.

b. An assessment of the radiation doses from radioactive effluents released from the plant during the previous calendar year. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in the report.

c. The air doses and the doses to the hypothetical maximum exposed individual calculated following the ODCM methodology shall be reported.

d. The following information for solid waste shipped offsite during the report period:

Total amount of solid waste shipped, buried or stored (in cubic feet)
Estimated total isotopic content (in curies) determined by scaling factors, gamma isotopic and/or other suitable analyses
Dates of shipment and burial site, if applicable quantity
Type ofwaste (e.g., spent resin, dry activated waste, evaporator bottoms, filters, scrap metal, asbestos, etc.),
Type of container (e.g., LSA, Type A, Type B, Large Quantity), and
Solidification agent (e.g., cement, urea formaldehyde), if applicable

e. The following information for liquid releases during the report period.

Total radioactivity in curies released and average diluted discharge concentrations of the following release categories: gamma isotopic, gross alpha, tritium, and strontium (beta emitters other than tritium).
Total volume (in gallons) of liquid waste released into circulating water discharge.

Page 14 of 278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

Total volume (in gallons) of dilution water used.
The maximum concentration of tritium and gross gamma radioactivity released (averaged over the period of a single release).
Estimated monthly total radioactivity in curies of individual radionuclides released based on representative isotopic analyses.
Semiannual and annual totals of monthly quantities of individual radionuclides, as determined by isotopic analyses.

f. The following information for gaseous releases during the report period.

Total gross radioactivity (in Curies), by month, released of:

o Noble Gases o Halogens o Particulates, subdivided into beta emitters (strontium, etc.), gross alpha, and gamma emitters o Tritium o Maximum release rate (for any one-hour period).

Estimated monthly total radioactivity (in Curies) released, by nuclide, for I-131, I-133, H-3, and radioactive particulates with half-lives greater than eight days, based on representative analyses performed by beta and by gamma isotopic analyses.
Semiannual and annual totals of monthly isotopic radionuclide quantities.

g. Identification of ABNORMAL RELEASES from the site in gaseous and liquid effluents in the AMR.

h. Summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in ODCM Section 12.0 and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C. See Section 12.1.2.a.6 for REMP specific reporting requirements.

1. If the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeds twice the limits of 10 CFR 50, Appendix I, the Annual Monitoring Report shall also include an assessment of radiation doses to the most likely exposed member of the general public from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show compliance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

Page 15 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

j. A description (including cause, response and prevention of reoccurrence) of occurrences and circumstances when fewer than the sampling frequency, minimum analysis frequency, or lower limit of detection requirement specified in Table 6-2 and Table 7-1are met.

k. The Annual Monitoring Report shall include a description of all deviations from the radiological environmental sample collection and analysis frequency contained in Table 12-3.

1. The Annual Monitoring Report shall include a description of occurrences when fewer than the minimum required radioactive liquid and/or gaseous effluent monitoring instrumentation channels were FUNCTIONAL OR OPERABLE as required in Table 6-2 and Table 7-2.

m. The quantity of each of the principal radionuclides released to the environment in liquid and gaseous effluents during the previous 12 months of operation for the ISFSI. Other information required by the Commission to estimate maximum potential radiation dose commitment to the public resulting from effluent releases should be included in the report.

n. Licensee initiated changes to the ODCM in the form of a complete legible copy of the entire ODCM as a part of or concurrent with the Annual Monitoring Report for the period of the report in which the change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages clearly indicating the area of the page that was changed.

3.2 Record Retention Requirements Records of reviews performed for changes made to the ODCM shall be kept for the duration of the operating licenses ofUnits 1 and 2 of the Point Beach Nuclear Plant. (TS 5.5.1) Meteorological data shall be kept on file, on site for review by the NRC, upon request. The data available will include wind speed, wind direction and atmospheric stability. The data will be in the form of hour-by-hour averages stored in electronic form for each of the parameters. Page 16 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 4.0 RADIATION MONITORING SYSTEM AND RELEASE ACCOUNTING A computerized Radiation Monitoring System (RMS) is installed at Point Beach Nuclear Plant (PBNP). The RMS includes area, process, and effluent monitors. A description of those monitors used for liquid and gaseous effluents is presented in Table 4-1 and Table 4-2. The liquid and gaseous waste processing flow paths, equipment, and monitoring systems are depicted in Figure 4-1 and Figure 4-2. Calibration of the RMS detectors is accomplished in accordance with the PBNP instrument and control procedures. The setpoint methodology is described in Section 9.1 and Section 10.1 ofthe ODCM. The RMS is designed to detect and measure liquid and gaseous releases from the plant effluent pathways. The RMS will initiate isolation and control functions on certain effluent streams identified in Table 4-1 and Table 4-2. Complete monitoring and accounting of nuclides released in liquid and gaseous effluents is accomplished with the RMS together with the characterization of nuclide distributions by laboratory analysis of grab samples. Sampling frequencies and analysis requirements are described for liquids in Table 6-1 and gases in Table 7-1. The RMS is not used for normal operational release quantification. Release quantification is based on the analysis of actual samples and the known discharge rate. The main liquid releases (Ci) occur via batch releases. The continuous releases via SGBD and waste water effluents have a greater volume but very little licensed material. The major continuous release points are the vents from the Auxiliary Building, the Drumming Area, and the Gas Stripper. The Combined Air Ejector is a minor release source in terms of activity and volume during normal operation. The batch releases from the gas decay tanks occur through the Aux. Building vent stack. Page 17 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 4-1 RADIOACTIVE LIQUID WASTE EFFLUENT MONITORS CHANNEL NAME CONTROL FUNCTION DETECTOR NUMBER TYPE Containment Fan Coolers 1 (2) RE-216 None Scintillation Liquid Monitors Waste Disposal System Liquid RE-218 Shuts waste liquid overboard Scintillation Monitor Shuts steam generator Steam Generator Blowdown blowdown isolation valves, 1 (2) RE-219 Scintillation Line Liquid Monitors blowdown tank outlet valves and steam generator sample valves RE-220 Spent Fuel Pool Liquid Monitor None Scintillation Shuts steam generator Steam Generator Blowdown 1 (2) RE-222 blowdown isolation valves and GMTube Tank Outlet Monitor blowdown tank outlet valves Waste Distillate Overboard Shuts waste distillate overboard RE-223 Scintillation Liquid Monitor isolation valve Service Water Discharge 1 (2) RE-229 None Scintillation Monitors RE-230 Waste Water Effluent Monitor None Scintillation Page 18 of 278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 4-2 RADIOACTIVE GASEOUS WASTE EFFLUENT MONITORS CHANNEL NAME CONTROL FUNCTION DETECTOR NUMBER TYPE Containment Noble Gas Actuates containment ventilation I (2) RE-2I2 Scintillation Monitor isolation Shuts gas release valve and Auxiliary Building Exhaust RE-2I4 shifts auxiliary building exhaust Scintillation Ventilation Noble Gas Monitor through carbon filters Condenser Air Ejector Noble 1 (2) RE-2IS None Scintillation Gas Monitors Drumming Area Vent Noble RE-221 None Scintillation Gas Monitor Gas Stripper Building Exhaust RE-224 None Scintillation Noble Gas Monitor Combined Air Ejector RE-22S None Scintillation Low-Range Noble Gas Monitor Unit I and 2 Purge Exhaust Noble Gas Monitors (ChannelS Containment ventilation I (2) RE-30S Scintillation on SPING Units No. 2I and isolation No. 22) Auxiliary Building Exhaust Ventilation Noble Gas Monitor RE-31S None Scintillation (Channel S on SPING Unit No. 23) Drumming Area Ventilation RE-32S Noble Gas Monitor (ChannelS None Scintillation on SPING Unit No. 24) Page I9 of 278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL FIGURE 4-1 RADIOACTIVE LIQUID WASTE EFFLUENT MONITORS Page 20 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL FIGURE 4-2 RADIOACTIVE GASEOUS WASTE EFFLUENT MONITORS Radioactive Gaseous Waste Effluent Monitors Unll1

               ~                I                      ...........

Rm*ghlng Flltllr Page 21 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 5.0 SPECIFICATIONS AND SURVEILLANCE REQUIREMENTS 5.1 Specifications Compliance with the specifications contained in the succeeding text is required during the conditions specified therein. Upon failure to meet the specification, either during the performance of the surveillance, or between performances, the associated ACTION requirement shall be met. Noncompliance with a specification shall exist when its requirements and associated ACTION requirements are not met within the specified time period. If the specification is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required. 5.2 Surveillance Requirements Surveillance Requirements shall be met during the conditions specified for individual specifications unless otherwise stated in an individual surveillance requirement. The provisions ofSR 3.0.2 and 3.0.3 are applicable to the surveillance frequency of the Radioactive Effluent Controls Program in accordance with TS 5.5.4. Page 22 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 6.0 LIQUID EFFLUENT SPECIFICATIONS AND SURVEILLANCE REQUIREMENTS 6.1 Concentration 6.1.1 Specifications In accordance with PBNP TS 5.5.4.b, the concentration of radioactive materials in liquid effluents to the unrestricted area is limited to ten times the concentration value in Appendix B, Table 2, Column 2 to 10 CFR 20. For dissolved and entrained noble gases, the concentration shall be limited to 2.0 E-04 J.LCi/mL total activity. 6.1.2 Applicability At all times 6.1.3 Action

a. During release of radioactive liquid effluents, at least one condenser circulating water pump shall be in operation and the service water return header shall be lined up only to the unit whose circulating water pump is operating.

b. When the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeds the limits identified in Section 6 .1.1, immediately restore the concentration to within the above limits.

c. Report all deviations in the Annual Monitoring Report 6.1.4 Surveillance Requirement

a. The concentration of radioactivity in liquid waste shall be determined by sampling and analysis in accordance with Table 6-1.

b. The results of radioactive analysis shall be used in accordance with the methodology of Section 9.1 to assure that the concentrations at the point of release are maintained within the limits of Section 6.1.1.

Page 23 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 6.1.5 Basis This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to UNRESTRICTED AREAS will be less than 1OX the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures exceeding (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.1301(a)(l) to the population. The concentration limit for dissolved or entrained noble gases is based upon the NRC's evaluation and assumption that Xe-135 is the controlling radioisotope and its limit in air (submersion) has been converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in Currie, L. A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984). Note: Hard-to-detect (HTD) radionuclides are radionuclides, such as alpha emitters and pure beta emitters which can be detected only by chemical extraction followed by alpha or beta counting, and therefore cannot be detected before a release using gamma spectroscopy. Analyses for HTDs are accomplished by obtaining aliquots of sample streams and sending the samples to a contracted laboratory for analyses. Their release quantities and doses are assessed after analytical results are obtained and then included in the monthly effluent quantification. The HTDs specifically identified by the Point Beach RETS were Sr-89/90 and alpha emitters. Fe-55 identified in NUREG-04 72 was not included in the Point Beach RETS. Pursuant to regulatory guidance, reviews of the Part 61 analyses have been undertaken and, as a good practice, the following HTDs (other than the ones specifically required) have been added to the analytical list: C-14, Fe-55, Ni-63, and Tc-99. NRC guidance (Reg Guide 1.21, Rev 2, June 2009) does not require analysis for C-14 in liquids because the airborne C-14 far outweighs the amount discharged in liquids. Therefore, C-14 analyses may be discontinued in the future based on the results from the Part 61 analyses. The list of required radionuclides and the additional HTDs are listed in Table 6-1. Page 24 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 6-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE SAMPLING MINIMUM TYPE OF LOWER TYPE 5 FREQUENCY .. ANALYSIS ACTIVITY LEVEL OF FREQUENGY ANALYSIS DETECTION1 (JlCI/CC) Gamma emitters 5 E-07 2 Prior to release I-131 1 E-06 I. Batch Releases Tritium 1 E-05

a. Waste Condensate Tank Monthly on composites Gross alpha 1 E-07

b. Waste Distillate obtained from batches Tank Prior to release released during the Fe-55, Ni-63, 1E-06

c. Monitor Tanks current month Tc-99, C-14 1E-06

d. Other tanks containing Quarterly on radioactivity to be composites obtained discharged from batches released Sr-89/90 5 E-08 during the current quarter Gamma emitters 5E-07 Twice weekly I-131 1E-06 3 5

2. Continuous Releases ' Tritium IE-05

a. Steam Generator Grab samples Gross alpha 1E-07 Blowdown twice weekly Monthly on grab Fe-55, Ni-63, Tc-99, 1E-06 composites

b. Service Water C-14 1E-06 Quarterly on grab Sr-89/90 5E-08 composites Gamma emitters 5E-07 Weekly I-131 1E-06 Tritium 1E-05 Continuous Gross alpha

3. Waste Water Effluent composrte . 4 1E-07 Monthly on weekly Fe-55, Ni-63, Tc-99, 1E-06 composite C-14 1E-06 Quarterly on monthly Sr-89/90 5E-08 composite NOTE 1: The principal gamma emitter for which the gamma isotopic LLD applies is Cs-137. Because gamma isotopic analyses are performed, the LLDs for all other gamma emitters are inherently determined by the operating characteristics of the counting system. All positively identified gamma emitters will be reported in the Annual Monitoring Report NOTE2: A BATCH RELEASE is defined in Section 2.5. Prior to sampling for analysis, each batch shall be isolated and mixed to assure representative sampling.

NOTE3: A CONTINUOUS RELEASE is defined in Section 2.5. NOTE4: A continuous composite is one in which the method of sampling employed results in a specimen that is representative of the liquids released. NOTES: For compensatory analyses required by Table 6-2 only the analyses performed by the out-of-service monitor need to be performed. Page 25 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 6.2 Dose 6.2.1 Specifications In accordance with PBNP TS 5.5.4.d, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS shall not exceed:

a. 3 mrem to the total body or 10 mrem to any organ, total from both units, during any calendar quarter, and

b. 6 mrem to the total body or 20 mrem to any organ, total from both units, during any calendar year.

6.2.2 Applicability At all times 6.2.3 Action If the calculated dose from radioactive material actually released in liquid effluents exceeds any of the above limits, a special report shall be prepared and submitted to the Commission within 30 days of determination of the release quantity. The report shall include, as appropriate:

The cause( s) for exceeding the limits,
The corrective action(s) taken to reduce the release, and
The proposed corrective action(s) to be taken to assure that subsequent releases will be in compliance with the above limits.

If the dose to any MEMBER OF THE PUBLIC exceeds 75 mrem to the thyroid or 25 mrem to the whole body or an organ other than the thyroid, pursuant to 40 CPR 190, the report shall also contain a request for a variance from this standard pursuant to 40 CPR 190.11. 6.2.4 Surveillance Requirement Cumulative dose contributions from radioactive effluents shall be determined for the current calendar quarter and current calendar year in accordance with the methodology described in Section 9.2 at least once every 31 days. Page 26 of 278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 6.2.5 Basis This specification is provided to implement the requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable". Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodology in Section 9.2 implements the requirements of Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in Section 9.2 for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109 and Regulatory Guide 1.113. 6.3 Liquid Radwaste Treatment System 6.3.1 Specifications In accordance with PBNP TS 5.5.4.f, the LIQUID RADWASTE TREATMENT SYSTEM shall be used to reduce the radioactive materials in liquid wastes prior to discharge when the projected doses, due to the liquid effluent, to UNRESTRICTED AREAS would exceed 0.12 mrem to the total body or 0.4 mrem to any organ (2% of the annual Appendix I dose objective) in a 31 day period. 6.3.2 Applicability At all times Page 27 of 278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 6.3.3 Action With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the LIQUID RADWASTE TREATMENT SYSTEM not in operation, prepare and submit to the Commission within 30 days a special report that includes the following information:

Identification of the non-functional equipment or subsystem and the reason for non-functionality.
Actions taken to restore the non-functional equipment to FUNCTIONAL status.
Summary description of actions taken to prevent a recurrence.

6.3.4 Surveillance Requirement Doses due to liquid releases shall be projected at least once per 31 days in accordance with the methodology and parameters in Section 9.3. 6.3.5 Basis The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 1o CFR Part 50. The specified limits governing the use of appropriate portions of the LIQUID RADWASTE TREATMENT SYSTEM were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents. 6.4 Liquid Effluent Monitoring Instrumentation 6.4.1 Specifications

a. In accordance with PBNP TS 5.5 .4, the radioactive liquid monitoring instrumentation channels listed in Table 6-2 shall be FUNCTIONAL and alarm or trip setpoints established such that effluent releases do not exceed the values described in Section 6.1.1.

b. The alarm or trip setpoints of the monitoring instrumentation channels shall be determined in accordance with the methodology in Section 9 .1.

Page 28 of 278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 6.4.2 Applicability During releases using the monitored pathway 6.4.3 Action

a. If a radioactive effluent monitoring instrumentation channel alarm or trip setpoint is found less conservative than required by Section 6.4.1, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel non-functional, or change the setpoint so it is acceptably conservative.

b. If fewer than the minimum number of radioactive effluent monitoring channels is FUNCTIONAL, the appropriate ACTION should be taken for the instrument as listed in Table 6-2. Best effort shall be made to return the non-functional channel to a FUNCTIONAL status within 30 days. If this cannot be accomplished, the circumstances of the instrument failure and schedule for repair shall be reported in the Annual Monitoring Report.

c. Report all deviations in the Annual Monitoring Report.

6.4.4 Surveillance Requirement Each radioactive effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, calibration, FUNCTIONAL TEST, and SOURCE CHECK at the frequencies described in Table 6-3. 6.4.5 Basis The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alarm/Trip Setpoint for these instruments SHALL be calculated and adjusted in accordance with the methodologies and parameters in Section 9.1 of the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of TS 5.5.4.6. The FUNCTIONALITY and use of the instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CPR Part 50 and Point Beach General Design Criteria 17 and 70. Page 29 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 6-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Liquid Radwaste System

a. RE-223, Waste Distillate Tank Discharge Note 1

b. RE-218, Waste Condensate Tank Discharge 1 Note 1

c. Waste Condensate Tank Discharge Flow Meter 1 Note2

d. Waste Distillate Tank Flow Rate Recorder 1 Note2

2. Steam Generator Blowdown System

a. For each unit: RE-219, Steam Generator Blowdown Liquid 1 Note 3 Discharge, or RE-222, Blowdown Tank Monitor, or RE-229, Service Water Discharge

b. Steam Generator Blowdown Flow Indicating Transmitters 1 Note 4

( 1 per steam generator)

3. Service Water System

a. RE-229, Service Water Discharge (for applicable unit) 1 Note 5

b. For each unit: RE-216, Containment Cooling Fan Service 1 Note 5 Water Return, or RE-229, Service Water Discharge

c. RE-220, Spent Fuel Pool Heat Exchanger Service Water Outlet 1 Note 5 or RE-229, Service Water Discharge (for applicable unit)

4. Waste Water Effluent

a. RE-230, Waste Water Effluent 1 Note 5

b. Waste Water Effluent Composite Sampler Note 6

c. Waste Water Effluent Flow Determination NIA Note 7 NOTE 1: If the number of channels FUNCTIONAL is fewer than the minimum required, effluent releases via this pathway shall be discontinued immediately (reference TRM 3.3.1).

NOTE 2: If the number of channels FUNCTIONAL is fewer than the minimum required, effluent releases via this pathway may continue provided the flow rate is estimated at least once every four hours during actual liquid batch releases. NOTE 3: If the number of channels FUNCTIONAL is fewer than the minimum required, effluent releases via this pathway may continue provided grab samples are analyzed for gamma radioactivity in accordance with Table 6-1 at least once every 24 hours when the secondary coolant specific activity is less than 0.01 J!Cilcc dose equivalent 1-131 or once every 12 hours when the activity is greater than 0.01 JICi/cc dose equivalent 1-131. NOTE 4: If the number of channels FUNCTIONAL is fewer than the minimum required, effluent releases via this pathway may continue provided the flow is estimated or determined with auxiliary indication at least once every 24 hours. NOTE 5: If the number of channels FUNCTIONAL is fewer than the minimum required, effluent releases via this pathway may continue provided that at least once every 12 hours grab samples are collected and analyzed in accordance with Table 6-1. NOTE 6: If the number of channels FUNCTIONAL is fewer than the minimum required, effluent releases via this pathway may continue provided grab samples are collected twice per week and analyzed in accordance with Table 6-1. NOTE 7: Waste water effluent flow may be determined from the waste water effluent flow meter Page 30 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 6-3 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 1 I*'

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1. Liquid Radwaste System

a. RE-223, Waste Distillate Tank D R Q p

b. RE-218, Waste Condensate Tank Discharge D R Q p

c. Waste Condensate Tank Discharge Flow Meter P/D R N/A N/A

d. Waste Distillate Tank Flow Rate Recorder P/D R N/A N/A

2. Steam Generator Blowdown System

a. RE-219, Steam Generator Blowdown Liquid D R Q M Discharge (1 per unit)

b. RE-222, Blowdown Tank Monitor (1 per unit) D R Q M

c. Steam Generator Blowdown Flow Indicating D R N/A N/A Transmitters (1 per steam generator)

3. Service Water System

a. RE-229, Service Water Discharge (1 per unit) D R Q M

b. RE-216, Containment Cooling Fan Service D R Q M Water Return

c. RE-220, Spent Fuel Pool Heat Exchanger D R Q M Service Water Outlet

4. Waste Water Effluent

a. RE-230, Waste Water Effluent D R Q M

b. Waste Water Effluent Composite Sampler w N/A N/A N/A

c. Waste Water Effluent Flow Meter w R N/A N/A Legend: D Daily w Weekly M Monthly Q Quarterly R Once per 18 months, typically during refueling P/D Prior to or immediately upon initiation of a release or daily if a release continues for more than one day N/A Not applicable Page 31 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 7.0 GASEOUS EFFLUENT SPECIFICATIONS AND SURVEILLANCE REQUIREMENTS 7.1 Dose Rate 7 .1.1 Specifications In accordance with PBNP TS 5.5.4.g, the dose rate resulting from radioactive material released in gaseous effluents from the site areas at or beyond the SITE BOUNDARY shall be limited to the following:

a. For noble gases: a dose rate::::; 500 mrem/yr to the whole body and a dose rate::=:: 3000 mrem/yr to the skin, and

b. For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days: a dose rate::::; 1500 mrem/yr to any organ.

7.1.2 Applicability At all times. 7 .1.3 Action With the dose rate(s) exceeding the above limits, immediately restore the release rate within the above limit(s). 7 .1.4 Surveillance Requirement

a. The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in Section 10.3 of this manual.

b. The dose rate due to iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in Section 10.4 of this manual by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 7-1.

Page 32 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 7.1.5 Basis This specification is provided to ensure that the dose rate at the SITE BOUNDARY averaged over a time period of no greater than one hour due to gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10 CFR Part 20. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/yr to the total body or to less than or equal to 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to less than or equal to 1500 mrem/year. The required detection capabilities for radioactive material in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in Currie, L. A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984). Hard-to-detect (HTD) radionuclides are radionuclides, such as alpha emitters and pure beta emitters which can be detected only by chemical extraction followed by alpha or beta counting. HTD analyses are accomplished by a contracted laboratory on representative waste stream samples. Their release quantities and doses are assessed after analytical results are obtained and then included in the monthly effluent quantification. The HTDs specifically identified by the Point Beach RETS were Sr-89/90 and alpha emitters. Fe-55 identified in NUREG-0472 was not included in the Point Beach RETS. Pursuant to regulatory guidance, reviews of the Part 61 analyses have been undertaken, and, as a good practice, the following HTDs (other than the ones specifically required) have been added to the analytical list: Fe-55, Ni-63, and Tc-99. Airborne C-14 is calculated. The list of required radionuclides and the additional HTDs are listed in Table 7-1. Page 33 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 7-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM

1. Gas Decay Tank Prior to release Prior to release Gamma emitters 1E-04

2. Containment Purge or Pri~r to Purge Prior to purge or Gamma emitters 1E-04 Continuous Vent or vent vent Tritium 1E-06

3. Continuous Releases Continuous Weekly analysis of Gamma emitters 1E-11

a. Unit 1 Containment charcoal and I-131 1E-12 Purge and Vent particulate samples

b. Unit 2 Containment Monthly Gross alpha 1E-11 Purge and Vent composite of

c. Drumming Area vent particulate sample

d. Gas Stripper Building Quarterly Sr-89/90 1E-11 Vent composite of Fe-55, Ni-63, Per industry particulate sample Tc-99 standards5

e. Auxiliary Building Vent Noble gas monitor Noble gases- 1E-06 gross beta or gamma Monthly4 (grab) Monthly Gamma emitters 1E-04 Tritium 1E-06 NOTE 1: The principal gamma emitters for which LLD specification applies are Cs-137 in particulates and Xe-133 in gases. Because gamma isotopic analyses are performed, the LLDs for all other gamma emitters are inherently determined by the operating characteristics ofthe counting system. All identifiable gamma emitters will be reported in the Annual Monitoring Report.

NOTE 2: Tritium grab samples will be taken every 24 hours when the refueling cavity is flooded. NOTE 3: The ratio of the sample flow rate to the release flow rate shall be known or estimated for the time period covered by each sampling interval. (Reference RAM 5.2) NOTE 4: Tritium grab samples will be taken every seven days from the drumming area ventilation exhaust/spent fuel pool area whenever there is spent fuel in the spent fuel pool. NOTE 5: LLDs for Fe-55, Ni-63 and Tc-99 are not prescribed in NUREG 1301. LLDs should be consistent with laboratory capabilities and industry standards for nuclide detection. Page 34 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 7.2 Dose- Noble Gases 7.2.1 Specifications In accordance with PBNP TS 5.5.4.e & 5.5.4.h, the air dose from noble gases released in gaseous effluents to areas beyond the SITE BOUNDARY shall not exceed:

a. 10 mrad for gamma radiation or 20 mrad for beta radiation, per calendar quarter, and

b. 20 mrad for gamma radiation or 40 mrad for beta radiation, per calendar year.

7.2.2 Applicability At all times. 7.2.3 Action If the calculated air dose from radioactive noble gases actually released in gaseous effluents exceeds any of the above limits, a special report shall be prepared and submitted to the Commission within 30 days of determination of the release quantity. The report shall include, as appropriate:

The cause( s) for exceeding the limits,
The corrective action(s) taken to reduce the release, and
The proposed corrective action(s) to be taken to assure that subsequent releases will be in compliance with the above limits.

If the dose to any MEMBER OF THE PUBLIC exceeds 75 mrem to the thyroid or 25 mrem to the whole body or an organ other than the thyroid, pursuant to 40 CFR 190, the report shall also contain a request for a variance from this standard pursuant to 40 CFR 190.11. 7.2.4 Surveillance Requirement Cumulative dose contributions from noble gases in radioactive effluents shall be determined for the current calendar quarter and current calendar year in accordance with the methodology described in Section 10.5, at least every 31 days. Page 35 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 7.2.5 Basis This specification is provided to implement the requirements of Section li.B, liLA and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation implement the guides set forth in Section li.B of Appendix I. The ACTION statement provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the release of radioactive material in gaseous effluents will be kept "as low as reasonably achievable". The Surveillance Requirements implement the requirements of Section liLA of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology of Section 10.3 for calculating the doses due to the actual release rate of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109 and Regulatory Guide 1.111. The equations of Section 10.5 provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. Consistent with the approach for limiting gaseous effluents in 10CFR50 App. I, meeting the air dose limits for gamma and beta radiation under most all site conditions provides a de facto compliance with the total body (5 mrem per unit) and skin (15 mrem per unit) dose limits. For PBNP, the air dose limits are met at the site boundary at the location with the highest x/Q, which is a very conservative assessment when compared to the location of any real person. Furthermore, PBNP TS section 5.5.4.h. requires compliance with only the air dose limits. Therefore, compliance with the gamma and beta air dose limits provides for compliance with the total body and skin dose limits. 7.3 Dose - I-131, I-13 3, H-3 and Radionuclides in Particulate Form 7.3 .1 Specifications In accordance with PBNP TS 5.5 .4.i, the annual or quarterly dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents release to areas beyond the SITE BOUNDARY shall be limited to:

a. :::; 15 mrem to any organ per calendar quarter, and

b. :::; 30 mrem to any organ per calendar year.

7.3.2 Applicability At all times. Page 36 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 7.3.3 Action If the calculated dose from the release of iodine-131, iodine-13 3, tritium, and radionuclides in particulate form with half-lives greater than eight days, in gaseous effluents exceeds any of the above limits, a special report shall be prepared and submitted to the Commission within 30 days of determination of the release quantity. The report shall include, as appropriate:

The cause( s) for exceeding the limits,
The corrective action( s) taken to reduce the release, and
The proposed corrective action(s) to be taken to assure that subsequent releases will be in compliance with the above limits.

If the dose to any MEMBER OF THE PUBLIC exceeds 75 mrem to the thyroid or 25 mrem to the whole body or an organ other than the thyroid, pursuant to 40 CFR 190, the report shall also contain a request for a variance from this standard pursuant to 40 CFR 190.11. 7.3 .4 Surveillance Requirement Cumulative dose contributions from iodine-131, iodine-13 3, tritium, and particulates with half-lives greater than eight days in radioactive effluents shall be determined for the current calendar quarter and current calendar year in accordance with the methodology described in Section 10.6, at least every 31 days. Page 37 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 7.3.5 Basis This specification is provided to implement the requirements of Section li.C, liLA and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section li.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the release of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable". The Surveillance Requirements implement the requirements of Section liLA of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology of Section 10.4 for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.1 09 and Regulatory Guide 1.111. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for iodine-131, iodine-13 3, tritium, and radionuclides in particulate form with half-lives greater than eight days are dependent upon the existing radionuclide pathways to man at and beyond the SITE BOUNDARY. The pathways that were examined in the development of the calculations were: ( 1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man. 7.4 Gaseous Radwaste Treatment System 7.4.1 Specifications In accordance with PBNP TS 5.5.4.f, the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to discharge when the 31-day projected gaseous effluent air doses due to the gaseous effluents to UNRESTRICTED AREAS would exceed 0.4 mrad from noble gas gamma radiation, 0.8 mrad from noble gas beta radiation, and 0.6 mrem to any organ from I-131, I-133, H-3 and radioactive material in particulate form whose half-life is> 8 days, from both units (2% of the Appendix I annual dose objectives). 7.4.2 Applicability At all times. Page 38 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 7.4.3 Action If radioactive gases are being discharged for a period of 31 consecutive days without use of the effluent treatment system to meet the release limits specified above, a special report shall be prepared and submitted to the Commission within thirty days which includes the following information:

Identification of the non-functional equipment or subsystem and the reason for non-functionality.
Actions taken to restore the non-functional equipment to FUNCTIONAL status.
Summary description of actions taken to prevent a recurrence.

The following portions of the gaseous radioactive effluent treatment system shall be used to reduce the release of radioactivity:

For noble gases, a gas decay tank(s) (GDTs) shall be operated when required to maintain gaseous releases within the specified limits, described above.
During a GDT discharge through the Auxiliary Building vent, at least one exhaust fan shall be in operation (FSAR 11.2.3).
For iodine-131, iodine-133, tritium, and particulates with half-lives greater than eight days, the auxiliary building ventilation exhaust charcoal filter and/or air ejector charcoal filter shall be operated when required to maintain gaseous releases within the specified limits, described above.

7.4.4 Surveillance Requirement Projected dose contributions from radioactive effluents shall be determined for the current calendar quarter and current calendar year in accordance with the methodology described Sections 9.3 and 10.7 at least every 31 days. 7.4.5 Basis The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the release of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". This specification implements the requirements ofPBNP GDC 70, 10 CPR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CPR Part 50 and the design objective given in Section II.D of Appendix I to 1o CFR Part 50. The specified limits governing the use of appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM were specified as a suitable fraction (2%) of the annual dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents. Page 39 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 7.5 Gaseous Effluent Monitoring Instrumentation 7.5 .1 Specification

a. In accordance with PBNP TS 5.5.4.a, the radioactive gaseous monitoring instrumentation channels listed in Table 7-2 shall be FUNCTIONAL and alarm or trip setpoints established such that effluent releases do not exceed the values described in Section 7 .1.1.

1. All monitors are defined by the term FUNCTIONAL-FUNCTIONALITY, EXCEPT 1(2) RE-212 Containment Noble Gas Monitor which is defined by the term OPERABLE -

OPERABILITY.

2. IF the ability of 1(2) RE-212, Containment Noble Gas Monitor, to perform its function is questioned, THEN the Operability Determination process is applicable.

(LCO 3.4.15, RCS Leakage Detection Instrumentation)

b. The alarm or trip setpoints of the monitoring instrumentation channels shall be determined in accordance with the methodology in Section 10.1 of the ODCM.

7.5.2 Applicability During releases via the monitored pathway. 7.5 .3 Action

a. If a radioactive effluent monitoring instrumentation channel alarm or trip setpoint is found less conservative than required by Section 7.5 .1, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel non-functional, or change the setpoint so it is acceptably conservative.

b. If fewer than the minimum number of radioactive effluent monitoring channels is FUNCTIONAL, the appropriate ACTION should be taken for the instrument as listed in. Best effort shall be made to return the non-functional channel to a FUNCTIONAL status within 30 days. If the number of channels FUNCTIONAL is not restored to the minimum required for any release pathway within 30 days, the circumstances of the instrument failures and schedule for repair shall be reported in the Annual Monitoring Report.

c. Report all deviations in the Annual Monitoring Report Page 40 of 278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 7.5.4 Surveillance Requirement Each radioactive effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, calibration, FUNCTIONAL TEST, and SOURCE CHECK at the frequencies described in Table 7-3. 7.5.5 Basis The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm/Trip Setpoint for these instruments SHALL be calculated and adjusted in accordance with the methodologies and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The FUNCTIONALITY and use of the instrumentation is consistent with the requirements of Point Beach General Design Criteria 17 and 70 and General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. Page 41 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 7-2 GASEOUS EFFLUENT MONITORING INSTRUMENTATION

.~

(J~~~ FUNCTIQN.A11' ACTION

1. Gas Decay Tank System

a. RE-214, Noble Gas (Auxiliary Building Vent Stack), or RE-315, Noble Gas Note 1 (Auxiliary Building Vent SPING)

b. Gas Decay Tank Flow Measuring Meter Note 2

2. Auxiliary Building Ventilation

a. RE-214, Noble Gas (Auxiliary Building Vent Stack), or RE-315, Noble Gas Note 3 (Auxiliary Building Vent SPING)

b. Isokinetic Iodine and Particulate Continuous Air Sampling System or SPING 23 Note 4

3. Condenser Air Ejector System

a. RE-225, Noble Gas (Combined Air Ejector Discharge Monitor), or RE-215, Note 3 Noble Gas (Air Ejector Monitors- 1 per unit), or RE-214, Noble Gas (Auxiliary Building Vent Stack); or RE-315, Noble Gas (Auxiliary Building Vent SPIN G)

b. Flow Rate Monitor Air Ejectors NoteS

4. Containment Purge and Vent System

a. RE-212, Noble Gas Monitors (1 per unit); or RE-305, Noble Gas (Purge Exhaust Note 3 SPING- 1 per unit)

b. 30 cfm Forced Vent Path Flow Indicators NoteS

c. Iodine and Particulate- Continuous Air Samplers Note4

d. Sampler Flow Rate Measuring Device NoteS

5. Fuel Storage and Drumming Area Ventilation

a. RE-221, Noble Gas (Drumming Area Stack), or RE-325, Noble Gas (Drumming Note 3 Area SPING)

b. Isokinetic Iodine and Particulate Continuous Air Sampling System or SPING 24 Note4

6. Gas Stripper Building Ventilations

a. RE-224, Noble Gas (Gas Stripper Building), or RE-305, Unit 2 Purge Exhaust Note 3 SPING

b. Iodine and Particulate- Continuous Air Sampler or SPING 22 Note4

c. Sampler Flow Rate Measuring Device NoteS NOTE 1: If the number of channels FUNCTIONAL is fewer than the minimum required, effluent releases via this pathway may continue provided that prior to initiating a release, two separate samples are analyzed by two technically qualified people in accordance with the applicable part of Table 7-1 and the release rate is reviewed by two technically qualified people.

NOTE 2: If the number of channels FUNCTIONAL is fewer than the minimum required, effluent releases via this pathway may continue provided the flow rate is estimated at least once every four hours during actual gaseous releases. NOTE 3: lfthe number of channels FUNCTIONAL is fewer than the minimum required, effluent releases via this pathway may continue provided grab samples are collected at least once per 12 hours and are analyzed in accordance with Table 7-1. (Reference Step 7.S.1 for additional information regarding RE-212) NOTE 4: If the number of channels FUNCTIONAL is fewer than the minimum required, effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment, (e.g., any low volume sampler which meets the requirements of Table 7-1). NOTES: If the number of channels FUNCTIONAL is fewer than the minimum required, effluent releases via this pathway may continue provided the flow is estimated or determined with auxiliary indication at least once every 24 hours. Page 42 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 7-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ~~~;~t~;,~~~-:~TlE.,d *. *. *' < ~t'FX~ . .'*

                                                ~IIJ':I'II                         ~~~'                 ~eT. Sf'~9J¥ 1 ""';
                                     '~     'T

c:' '"

                                                                    *~
                                                                                   ; CHECK  P.AJ:1:IJ3*  TEST
                                                                                                         ... elmcK~"

1. Gas Decay Tank System

a. RE-214, Noble Gas (Auxiliary Building Vent Stack) D R Q M

b. Gas Decay Tank Flow Measuring Device p R N/A N/A

2. Auxiliary Building Ventilation System

a. RE-214, Noble Gas (Auxiliary Building Vent Stack D R Q M

b. RE-315, Noble Gas (Auxiliary Building SPING) D R Q M

c. Isokinetic Iodine and Particulate Continuous Air w R N/A N/A Sampling System

3. Condenser Air Ejector System

a. RE-225, Noble Gas (Combined Air Ejector D R Q M Discharge)

b. RE-215, Noble Gas (Air Ejectors- 1 per unit) D R Q M

c. Flow Rate Monitor- Air Ejectors (1 per unit) D R N/A N/A

4. Containment Purge and Vent System

a. RE-212, Noble Gas (1 per unit) D R Q MI

b. 30 cfm Vent Path Flow Indication P/D R N/A N/A

c. RE-305, Noble Gas (Purge Exhaust SPING- 1 per D R Q Ml unit)

d. Iodine and Particulate Continuous Air Sampler P/W N/A N/A N/A

e. Sampler Flow Rate Measuring Device P/D R N!A N/A

5. Fuel Storage and Drumming Area Ventilation Stack

a. RE-221, Noble Gas (Drumming Area Vent Stack) D R Q M

b. RE-325, Noble Gas (Drumming Area SPIN G) D R Q M

c. Isokinetic Iodine and Particulate Continuous Air w R N/A N/A Sampling System

6. Gas Stripper Building Ventilation System

a. RE-224, Noble Gas D R Q M

b. Iodine and Particulate Continuous Air Sampler w NIA N/A N/A

c. Sampler Flow Rate Measuring Device w R N/A N/A Legend: D =Daily R = Once per 18 months, typically during refueling W =Weekly P/D(W) =Prior to or immediately upon initiation of a release or daily (weekly) if a release continues for more than one day (week)

M =Monthly Q =Quarterly N/A =Not applicable NOTE 1: SOURCE CHECK required prior to containment purge Page 43 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 8.0 TOTALDOSE 8.1 Specification The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from URANIUM FUEL SOURCES shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. 8.2 Applicability At all times. 8.3 Action

a. With the calculated doses from the release or radioactive materials in liquid or gaseous effluents exceeding twice the limits of Sections 6.2.1, 7.2.1, or 7.3.1, calculations should be made including direct radiation contributions from the site to determine whether the above limits have been exceeded. If the limits are exceeded, a special report shall be prepared and submitted to the Commission within 30 days in lieu of a License Event Report, that includes the following:

the corrective action(s) taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits.
An analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from URANIUM FUEL CYCLE sources, including all effluent pathways and direct radiation, for the calendar year that includes the release( s) covered by this report, as defined in 10 CFR 20.2203.
A description of the levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

b. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CPR Part 190 has not already been corrected, a request for a variance in accordance with the provisions of 40 CPR Part 190 shall be made.

Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. 8.4 Surveillance Requirements 8.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Surveillance Requirements 6.2.4, 7.2.4, and 7.3.4 and in accordance with the methodology of Sections 9.2, 10.5, and 10.6, respectively. Page 44 of 278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 8.4.2 Cumulative dose contributions from direct radiation from the reactor units shall be determined using the procedure outlined in Section 11.0. This application is applicable only under the conditions set forth in ACTION 7.1.3. 8.5 Basis This specification is provided to meet the dose limitations of 40 CPR Part 190 that have been incorporated into 10 CPR Part 20 by 46 FR 18525. The specification requires the preparation and submittal of a special report whenever the calculated doses due to releases of radioactivity and to radiation from the URANIUM FUEL CYCLE sources exceed 25 mrem to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CPR 190 if the individual reactors remain within twice the dose design objectives of Appendix I and if direct radiation doses from the units (including outside storage tanks, the ISFSI, etc.) are kept small. The special report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within 40 CPR 190 limits. For the purposes of the special report, it may be assumed that the dose commitment to a MEMBER OF THE PUBLIC from other URANIUM FUEL CYCLE sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. The Kewaunee Nuclear Power Plant (KNPP) is within a radius of 8 Km of Point Beach. KNPP is now shut down. However, should there be any stored licensed material on that site which is released to the environment; the dose contribution from that release would have to be considered when evaluating Point Beach compliance with 40 CPR 190 limits. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40CFR190, the special report with a request for a variance (provided the release conditions resulting in violation of 40CFR190 have not already been corrected), in accordance with the provisions of 40CFR190.11 and 10CFR20.2203(a)(4), is considered to be a timely request and fulfills the requirements of 40CFR 190 until NRC staff action is completed. The variance only relates to the limits of 40CFR190, and does not apply in any way to the other requirements for dose limitation of 10CFR20, as addressed in Sections 6.2, 7.2 and 7.3. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. Page 45 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 9.0 LIQUID EFFLUENT CALCULATIONS 9.1 Monitor Alarm Setpoint Determination The effluent monitor setpoints are established to ensure that controlled releases of liquid radioactive effluents are maintained as low as is reasonably achievable, to ensure releases result in concentrations to unrestricted areas within the limits specified in Section 6.1 and to ensure that the dose limits of 10 CFR 50, Appendix I are not exceeded. The computerized PBNP Radiation Monitoring System (RMS) permits each effluent radiation monitor to be programmed to alarm at two distinct setpoints. The alert setpoint, typically twice the steady-state reading, is intended to delineate a changing plant condition, and is established for evaluation purposes only. The high alarm or trip setpoint either will actuate a control function as applicable or will require corrective action to be initiated. Alert Setpoint Guidelines The alert setpoint of each effluent monitor normally will be set to alarm at two times the established steady-state reading. The alert setpoint is normally set at concentrations well below the alarm setpoint value and is never to be set in excess of the alarm setpoint. Certain situations during the course of plant operations may require a deviation from the two times steady-state value. The intent of this setpoint is to warn of changing plant conditions, which may warrant an evaluation to determine the cause of the increased reading. If the increased level is actually due to an increased radiation inventory within the system being monitored, as opposed to an increased background radiation field in the vicinity of the detector, an evaluation should be made to determine the impact of the release. The alert setpoint may be adjusted with prior approval. Alert setpoint adjustments are to be made in accordance with the PBNP RMS Alarm Setpoint and Response Book (Ref. OM 4.1.7). High Alarm or Trip Setpoint Guidelines In accordance with TS 5.5.4 and as stated in Section 6.1, the high alarm or trip setpoint for effluent monitors shall be established to annunciate at concentrations that would result in an UNRESTRICTED AREA concentration equal to or greater than 1Ox the applicable maximum effluent concentration (MEC) for a single radionuclide. For a mixture of radionuclides, the setpoint shall be established so that the sum of fractions (SOF), as defined in Appendix B of 10 CFR 20, is less than or equal to one. If the setpoints listed in Table 9-1 exceed the monitor's saturation or fail high level, the setpoint may be set at a value :s;70% of the fail high level (MSSM No. 93-01). These monitors are indicated by an asterisk (*) in Table 9-1. The appropriate detailed response to an effluent alarm is described in the PBNP RMS Alarm Setpoint and Response Book. The effluent monitor setpoints are established to ensure that controlled releases of liquid radioactive effluent are maintained as low as is reasonably achievable, to ensure releases result in concentrations to UNRESTRICTED AREAS within the specified limits described in Section 6.1.1 and to ensure that the dose limits of 10 CFR50, Appendix 1 are not exceeded. Page 46 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL The following equation must be satisfied to meet the liquid effluent restriction: C(F +f) [ _] c::s; f 9 1 Where: c = The setpoint of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, which is inversely proportional to the volumetric flow of the dilution stream plus the effluent stream, represents a value which, if exceeded, would result in concentration exceeding the TS limits of 1 Ox the 10 CFR 20 values in the UNRESTRICTED AREA (f.1Ci/mL) C 1 Ox the effluent concentration limit from 10 CFR 20, Appendix B, Table 2 Column 2 (see section 6.1.1) (f.1Ci/mL) f the flow rate at the radiation monitor location (volume/time) F The dilution water flow rate as measured prior to the release point (volume/time) Note: If no dilution is provided, then c :S C. Also ifF is large compared to f, then (F +f) ~F The liquid monitor setpoints are based on 1Ox the 10CFR20, Appendix B, Table 2, Column 2 maximum effluent concentration (MEC) values as allowed by the Point Beach TS. For a mixture ofradionuclides, the setpoint is calculated so that the summation of fractions (SOF) will not exceed unity, i.e. [. SOF = I _l_< 1 MECi- [9-2] Where: Ci = The concentration of radio nuclide i in the liquid effluent (J.LCi/mL) MECi = 10 times the Maximum Effluent Concentration value corresponding to radionuclide "i"from 10 CFRPart 20, Appendix B, Column 2 (J.LCi/mL), The SOF meeting the :Sl criterion means that the discharge concentration could have been higher by a factor of 1/SOF such that the effective maximum effluent concentration (EMEC) for the mixture could have been EMEC =

"C.

LA l [. [9-3] LMEC. l The setpoints for liquid effluent monitors are determined by the following equation: [9-4] Page 4 7 of 278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL EMEC x CW SP:::;; RR {Jcf [9-5] Setpoint of the radiation monitor (cpm or JLCi/mL, depending upon Where: SP = the specific monitor), The effective MEC value for the mixture ofradio nuclides in the EMEC = effluent stream (JLCi/mL) the circulating water flow rate (dilution water flow) at the time of the cw = release (gpm)

                      =     The concentration of radio nuclide i in the liquid effluent (uCi/mL)

RR = The liquid effluent release rate (gpm) Beta correction factor to account for pure beta emitters such as H-3 jJcf = which are not detected by the monitors Note: The EMEC includes pure beta emitting radionuclides that may are not be detected by the monitors (i.e., non-gamma emitters). See Appendix Afar a discussion of this factor. If the nuclide specific sensitivity is unavailable, the default sensitivity based upon system calibration should be used. The default sensitivity is based upon the monitor response to the 2000 - 2010 average liquid isotopic distribution, as presented in Appendix A.

                                       . . .       Monitor Response SensztlVlty     =     "' (!lc*;

L.. l cci

                                                                    )                               [9-6]

Where: Monitor = the counts per minute registered by the monitor exposed to Response a calibration source l:(J.1Ci/ccJ = total concentration of radionuclides in the 2000- 2010 average liquid effluent isotopic distribution. In the event that an alarm setpoint, based upon the concentration limits of Section 6.1.1, is exceeded during any release of liquid effluents, an evaluation of compliance with the concentration limits may be performed using the following equation:

                                          ~[ C*          RR]

L M~cixcw:::;; 1 [9-7] Where: ci = the concentration of radio nuclide "i" in the liquid effluent (JLCi/mL), RR = the liquid effluent release rate (gpm) cw = the circulating water flow rate (dilution water flow) at the time of the release (gpm), Page 48 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Default Monitor Setpoints A default alarm setpoint for each liquid monitor is based upon the 2000 - 2010 average radionuclide concentration in the effluent discharged to the UNRESTRICTED AREA. The concentration in the release is calculated assuming a minimum circulating water flow rate of243,000 gpm and the physical maximum flow rate of the individual liquid effluent waste stream. Maximum waste discharge flow rates, the monitors associated with each liquid effluent pathway and the maximum TS default setpoints are listed in Table 9-1. The isotopic distribution of the waste system is obtained from the historical PBNP release data for the eleven years mentioned above. This information can be found in Appendix A. As indicated in Table 9-1, several liquid RMS monitors fail high before reaching the TS high alarm setpoint. For these monitors, as described above, the:::; 70% of the fail high value will be applied to the monitor in lieu of the calculated default setpoint. Additionally, RE-230, Waste Water Effluent Monitor, is impacted by a PBNP EP requirement for EAL declaration, therefore the application of the :::;70% of the fail high value is not an acceptable option. To fulfill the EAL requirement, RE-230 must be capable of reading 2x the ODCM setpoint on the liquid radiation monitor. As a result, the alarm setpoint as described in this section cannot be implemented for RE-230, Waste Water Effluent Monitor. Therefore, instead of utilizing the TS limit of 1Ox the 10 CFR 20, Appendix B, Table 2, Column 2, concentrations, the ODCM (Revision 18) RE-230 setpoint of 1.03E-03 J.!Ci/cc value will be used as the basis for the new setpoint. This setpoint is based on 1x the current 10 CFR 20, Appendix B, Table 2, Column 2, concentrations AND the old circulating water minimum flow rate of 206 Kgal/min. The ODCM (Revision 18) setpoint will be modified by the ratio of the current minimum circulating water flow rate of 243 Kgal/min to the old minimum circulating water flow rate. The flow augmentation factor is 1.18E+OO (243/206 = 1.18E+OO). The application of this flow factor results in an RE-230 setpoint of 1.22E-03 J.!Ci/cc. Page 49 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 9-1 LIQUID EFFLUENT PATHWAYS CALCULATED LIQUID DISCHARGE PATHWAY DEFAULT EFFLUENT FLOWRATE MONI1'0R3 SETPOINT 1 PATHWAY (GPIVI) {1tCi!cc)

                                              . . . . . . . . . . . . . . . . .!.. . P~~P'-. . ~!!.~.~E. ~~.i.!.. . . . . . . . . . . .~.4.}.'-.9..9..9                                                               N/A
                                              . . . . . . . . . . . . . . ~. . P~~ps, either u~it . . . . . . . . . . . ...?..?..4..'-.9..9..9.                                                                       N/A Recirculation Water       None                                         . . . . . . .!.. . P~~P'-. . ~~~h. .~~!!. . . . . . . . . . . . 4.. ?..4..'-.9..9..9. . . ..                                                  N/A 1 pump, one unit &                                                               ,

619 000 N/A

                                                                         . . ?.. . P~~P.~.'-. ..9.!.~.~t.Y..~.i..!.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

2 pumps, each unit 744,000 N/A

                                                 . . . . . . .?.. .P~~P.~. . @. . ?..?...9.9.. . gP~. . . . . . . . . . . . .J. ?..'-.9..9..9........................ . . . . . . .. . .. .. . . . . . . . . . . . . . . . .                                 .

Service Water ..................?.....P~~P~. . @. . ~.?...Q..Q. . gp!!l.. . . . . . . . . . . . . . J. ?..'-.?..9..9. . . . Return (normal cool 1(2)RE-229 . . . . . . .4.. .P~~P.~. . @. . ?.. .!...9.9.. . gp!!l.. . . . . . . . . . . . . . .~.9..'-.4..9.9. . . . . . . . . . . . ............................................ down per pump) . . . . . . . . . ?.. . P~~P.~. . @. . 4..~..9..Q. . gp!!l.. . . . . . . . . . . . . . .~J. '-.?..9..9. . . . . . . . . . . . . .................... 6 pumps@ 3700 gprn 22,200 1.14E-03 1(2)RE-219* Steam Generator

                           &                                                               Max Flow Rate                                              200                                                 1.26E-01 Blowdown 1 (2)RE-222 Max Flow Rate (both Waste Water RE-230                                 filter skids running in                                                             700                                                  1.22E-03 Effluent2 parallel)

Spent Fuel Pool RE-220* Max Flow Rate 700 3.61E-02 Waste Distillate & RE-218* & Condensate Storage Max Flow Rate 100 2.53E-01 RE-223* Tank Discharge Containment Fan Max Flow Rate (per 1(2)RE-216* 4000 6.32E-03 Cooler Return Containment) NOTE 1: Setpoints except for RE-230 are based on lOx the MEC values listed in 10CFR20, Appendix B, Table 2, Column 2. PBNP TS Section 5.5.4.b allows concentrations of radioactive material released to unrestricted areas to be 1Ox the MEC values. NOTE 2: RE-230 setpoint explanation can be found in Section 9.1, Default Monitor Setpoints. NOTE 3: Monitors marked with an asterisk(*) have a calculated default alarm setpoint above the monitors fail high or saturation level. See Section 9.1, High Alarm or Trip Setpoint Guidelines for further explanation. Page 50 of 278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 9.2 Liquid Dose Calculations Section 6.2.1 establishes dose or dose commitment limits to members of the public from radioactive materials in liquid effluents. The following equation may be used to determine the dose or dose commitment to members of the public due to these releases: Where: Do= 1.67E- 02 *Vol cw *I * (Ci Aio) dose or dose commitment for the release or release [9-8] Do = period evaluated, to organ o ", including total body (mrem) Vol = volume of liquid effluent released for the release or release period evaluated (gal), cw = average circulating water discharge rate during the release period (gpm) ci = average concentration ofradionuclide "i", in undiluted liquid effluent representative of the waste volume Vol (JLCi/mL), Aio = ingestion dose factor to the total body or any organ "o" for radio nuclide "i" (mrem/hr per JLCi/mL) 1.67E-02 = Conversion factor (hrlmin) The default PBNP site-specific liquid dose commitment factors (Aia), presented in Table 9-3, have been derived using guidance from Regulatory Guide 1.109 and NUREG-0133. NUREG-0133 states that the maximum exposed individual's cumulative dose contribution should consider consumption of fish, invertebrates (not applicable to Point Beach) and potable water as appropriate. The NUREG goes on to state that the adult is normally the maximum exposed individual. Therefore, the default factors contained in Table 9-3 are based on adult dose conversion factors, fish consumption from Lake Michigan plus potable water consumption from the Two Rivers facility. The derivation of these factors is described in detail in Appendix B. Dose conversion factors for other age ranges are provided in Appendix K. A summary of the liquid effluent sub-pathways applicable to Point Beach is described below in Table 9-2. Page 51 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 9-2 LIQUID EFFLUENT SUB-PATHWAYS LIQUID EFFLUENT APPLICABLE JUSTIFICATION LOCATION SUB-PATHWAY Fish assumed to be caught at Aquatic Foods (fish) Yes PBNP discharge PBNP discharge Aquatic Foods No invertebrates are consumed No N/A (invertebrates) from Lake Michigan In the area ofPBNP, only well Irrigated Foods (meat water is used to irrigate crops or No N/A from watered cattle) water animals. Lake Michigan water is not used. In the area ofPBNP, only well Irrigated Foods (milk water is used to irrigate crops or No N/A from watered cattle) water animals. Lake Michigan water is not used. Assumed drinking water obtained Potable Water Yes from Two Rivers facility, 11 Two Rivers miles south ofPBNP. Although shoreline deposits could be considered, NUREG-0 13 3 Shoreline Deposits No provides guidance that the dose N/A consequence of this pathway is generally negligible. Page 52 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 9-3 PBNP SITE-SPECIFIC LIQUID DOSE COMMITMENT FACTORS, Aio (mrem/hr per J.tCi/mL) I NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 2.06E-01 2.06E-01 2.06E-01 2.06E-01 2.06E-01 2.06E-01 C-14 3.56E+03 7.13E+02 7.13E+02 7.13E+02 7.13E+02 7.13E+02 7.13E+02 F-18 1.80E-02 O.OOE+OO 2.00E-03 O.OOE+OO O.OOE+OO O.OOE+OO 5.34E-04 Na-22 5.29E+02 5.29E+02 5.29E+02 5.29E+02 5.29E+02 5.29E+02 5.29E+02 Na-24 2.71E+01 2.71E+01 2.71E+01 2.71E+01 2.71E+01 2.71E+01 2.71E+01 P-32 5.13E+06 3.19E+05 1.98E+05 O.OOE+OO O.OOE+OO O.OOE+OO 5.76E+05 Sc-46 2.03E-02 3.95E-02 1.15E-02 O.OOE+OO 3.68E-02 O.OOE+OO 1.92E+02 Cr-51 O.OOE+OO O.OOE+OO 1.51E-01 9.03E-02 3.33E-02 2.00E-Ol 3.80E+01 Mn-54 O.OOE+OO 5.11E+02 9.76E+Ol O.OOE+OO 1.52E+02 O.OOE+OO 1.57E+03 Mn-56 O.OOE+OO 4.97E-01 8.82E-02 O.OOE+OO 6.31E-01 O.OOE+OO 1.59E+Ol Fe-55 8.36E+Ol 5.78E+01 1.35E+01 O.OOE+OO O.OOE+OO 3.22E+01 3.31E+Ol Fe-59 1.31E+02 3.07E+02 1.18E+02 O.OOE+OO O.OOE+OO 8.58E+Ol 1.02E+03 Co-57 O.OOE+OO 2.93E+OO 4.88E+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.45E+Ol Co-58 O.OOE+OO 1.24E+01 2.78E+Ol O.OOE+OO O.OOE+OO O.OOE+OO 2.52E+02 Co-60 O.OOE+OO 3.60E+01 7.93E+01 O.OOE+OO O.OOE+OO O.OOE+OO 6.75E+02 Ni-63 3.95E+03 2.74E+02 1.33E+02 O.OOE+OO O.OOE+OO O.OOE+OO 5.72E+01 Ni-65 5.28E-Ol 6.85E-02 3.13E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.74E+OO Cu-64 O.OOE+OO 6.08E-01 2.86E-Ol O.OOE+OO 1.53E+OO O.OOE+OO 5.18E+01 Zn-65 2.65E+03 8.42E+03 3.80E+03 O.OOE+OO 5.63E+03 O.OOE+OO 5.30E+03 Zn-69m 5.06E+Ol 1.21E+02 1.11E+01 O.OOE+OO 7.35E+01 O.OOE+OO 7.41E+03 Zn-69 7.56E-04 1.45E-03 l.OOE-04 O.OOE+OO 9.39E-04 O.OOE+OO 2.17E-04 As-76 8.45E+OO 2.46E+Ol 1.23E+02 7.37E+OO 3.00E+Ol 7.68E+OO 1.08E+03 Br-82 O.OOE+OO O.OOE+OO 2.07E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.37E+02 Br-83 O.OOE+OO O.OOE+OO 1.44E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.07E-Ol Br-84 O.OOE+OO O.OOE+OO 9.10E-07 O.OOE+OO O.OOE+OO O.OOE+OO 7.14E-12 Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.13E+04 5.28E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.23E+03 Rb-88 O.OOE+OO 1.87E-11 9.93E-12 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO 1.84E-13 1.29E-13 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 3.46E+03 O.OOE+OO 9.92E+01 O.OOE+OO O.OOE+OO O.OOE+OO 5.54E+02 Sr-90 9.90E+04 O.OOE+OO 1.33E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.49E+03 Sr-91 1.98E+Ol O.OOE+OO 8.01E-01 O.OOE+OO O.OOE+OO O.OOE+OO 9.44E+01 Sr-92 8.15E-Ol O.OOE+OO 3.53E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.62E+01 Y-90 7.58E-02 O.OOE+OO 2.03E-03 O.OOE+OO O.OOE+OO O.OOE+OO 8.04E+02 Y-91m 2.84E-08 O.OOE+OO 1.10E-09 O.OOE+OO O.OOE+OO O.OOE+OO 8.36E-08 Y-91 1.39E+OO O.OOE+OO 3.73E-02 O.OOE+OO O.OOE+OO O.OOE+OO 7.67E+02 Y-92 5.49E-04 O.OOE+OO 1.60E-05 O.OOE+OO O.OOE+OO O.OOE+OO 9.61E+OO Y-93 8.40E-03 O.OOE+OO 2.32E-04 O.OOE+OO O.OOE+OO O.OOE+OO 2.66E+02 Zr-95 1.22E-Ol 3.92E-02 2.65E-02 O.OOE+OO 6.15E-02 O.OOE+OO 1.24E+02 Zr-97 1.66E-03 3.35E-04 1.53E-04 O.OOE+OO 5.06E-04 O.OOE+OO 1.04E+02 Page 53 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 9-3 PBNP SITE-SPECIFIC LIQUID DOSE COMMITMENT FACTORS, Aio NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Nb-95 5.03£+01 2.80£+01 1.50£+01 O.OOE+OO 2.77£+01 O.OOE+OO 1.70£+05 Nb-97 4.93£-04 1.25£-04 4.55£-05 O.OOE+OO 1.45£-04 O.OOE+OO 4.60£-01 Mo-99 O.OOE+OO 1.87£+01 3.55£+00 O.OOE+OO 4.23£+01 O.OOE+OO 4.33£+01 Tc-99m 2.56£-04 7.23£-04 9.21£-03 O.OOE+OO l.lOE-02 3.54£-04 4.28£-01 Tc-99 9.10£-01 1.35£+00 3.65£-01 O.OOE+OO 1.70£+01 1.15£-01 4.43£+01 Te-l 01 5.94£-19 8.56£-19 8.39£-18 O.OOE+OO 1.54£-17 4.37£-19 O.OOE+OO Ru-103 1.07£+00 O.OOE+OO 4.61£-01 O.OOE+OO 4.08£+00 O.OOE+OO 1.25£+02 Ru-105 6.46£-03 O.OOE+OO 2.55£-03 O.OOE+OO 8.35£-02 O.OOE+OO 3.95£+00 Ru-106 1.62£+01 O.OOE+OO 2.05£+00 O.OOE+OO 3.14£+01 O.OOE+OO 1.05£+03 Rh-105 4.12£-01 3.01£-01 1.98£-01 O.OOE+OO 1.28£+00 O.OOE+OO 4.80£+01 Ag-llOm 6.09£-01 5.63£-01 3.34£-01 O.OOE+OO 1.11£+00 O.OOE+OO 2.30£+02 Sn-113 7.87£+02 1.33£+02 2.21£+03 6.96£+01 1.82£+02 8.17£+01 2.42£+04 Sn-117m 1.48£+03 5.03£+01 2.10£+03 1.01£+01 7.69£+01 1.60£+01 2.37£+04 Sb-122 1.44£+00 7.92£-01 1.36£+01 1.68£-01 5.60£-01 2.16£-01 1.44£+02 Sb-124 9.51£+00 1.80£-01 3.77£+00 2.31£-02 O.OOE+OO 7.40£+00 2.70£+02 Sb-125 6.20£+00 6.93£-02 1.48£+00 6.31£-03 O.OOE+OO 4.78£+00 6.83£+01 Te-125m 2.98£+02 1.08£+02 4.00£+01 8.97£+01 1.21£+03 O.OOE+OO 1.19£+03 Te-127m 7.56£+02 2.70£+02 9.21£+01 1.93£+02 3.07£+03 O.OOE+OO 2.53£+03 Te-127 4.95£+00 1.78£+00 1.07£+00 3.67£+00 2.02£+01 O.OOE+OO 3.91£+02 Te-129m 1.27£+03 4.75£+02 2.02£+02 4.38£+02 5.32£+03 O.OOE+OO 6.42£+03 Te-129 2.63£-03 9.88£-04 6.40£-04 2.02£-03 1.10£-02 O.OOE+OO 1.98£-03 Te-131m 1.45£+02 7.07£+01 5.89£+01 1.12£+02 7.16£+02 O.OOE+OO 7.02£+03 Te-131 4.59£-09 1.92£-09 1.45£-09 3.77£-09 2.01£-08 O.OOE+OO 6.50£-10 Te-132 2.51£+02 1.63£+02 1.53£+02 1.80£+02 1.57£+03 O.OOE+OO 7.69£+03 I-130 1.74£+00 5.13£+00 2.02£+00 4.35£+02 8.00£+00 O.OOE+OO 4.41£+00 I-131 2.75£+01 3.93£+01 2.25£+01 1.29£+04 6.73£+01 O.OOE+OO 1.04£+01 I-132 2.16£-02 5.77£-02 2.02£-02 2.02£+00 9.19£-02 O.OOE+OO 1.08£-02 r--* I-133 4.80£+00 8.35£+00 2.55£+00 1.23£+03 1.46£+01 O.OOE+OO 7.51£+00 I-134 3.28£-05 8.91£-05 3.19£-05 1.54£-03 1.42£-04 O.OOE+OO 7.76£-08 I-135 5.19£-01 1.36£+00 5.01£-01 8.96£+01 2.18£+00 O.OOE+OO 1.53£+00 Cs-134 3.40£+04 8.10£+04 6.62£+04 O.OOE+OO 2.62£+04 8.70£+03 1.42£+03 Cs-134m 6.59£-01 1.39£+00 7.08£-01 O.OOE+OO 7.51£-01 1.18£-01 4.88£-01 Cs-136 3.47£+03 1.37£+04 9.86£+03 O.OOE+OO 7.62£+03 1.04£+03 1.56£+03 Cs-137 4.36£+04 5.97£+04 3.91£+04 O.OOE+OO 2.03£+04 6.73£+03 1.16£+03 Cs-138 5.58£-06 1.1 OE-05 5.46£-06 O.OOE+OO 8.10£-06 8.00£-07 4.70£-11 Ba-139 2.73£-04 1.94£-07 7.99£-06 O.OOE+OO 1.82£-07 1.10£-07 4.84£-04 Ba-140 7.97£+01 l.OOE-01 5.22£+00 O.OOE+OO 3.41£-02 5.73£-02 1.64£+02 Ba-141 7.35£-14 5.55£-17 2.48£-15 O.OOE+OO 5.16£-17 3.15£-17 O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 1.73£-02 8.74£-03 2.31£-03 O.OOE+OO O.OOE+OO O.OOE+OO 6.41£+02 La-142 3.93£-06 1.79£-06 4.45£-07 O.OOE+OO O.OOE+OO O.OOE+OO 1.30£-02 Page 54 of 278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 9-3 PBNP SITE-SPECIFIC LIQUID DOSE COMMITMENT FACTORS, Aia

           '  ~'

NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Ce-141 3.12E-02 2.11E-02 2.39E-03 O.OOE+OO 9.80E-03 O.OOE+OO 8.07E+01 Ce-143 2.28E-03 1.68E+OO 1.86E-04 O.OOE+OO 7.41E-04 O.OOE+OO 6.29E+01 Ce-144 1.69E+OO 7.05E-01 9.05E-02 O.OOE+OO 4.18E-01 O.OOE+OO 5.70E+02 Pr-143 8.76E-02 3.51E-02 4.34E-03 O.OOE+OO 2.03E-02 O.OOE+OO 3.84E+02 Pr-144 5.87E-17 2.44E-17 2.98E-18 O.OOE+OO 1.37E-17 O.OOE+OO O.OOE+OO Nd-147 5.92E-02 6.84E-02 4.09E-03 O.OOE+OO 4.00E-02 O.OOE+OO 3.28E+02 Eu-152 1.97E+OO 4.44E-01 3.90E-01 O.OOE+OO 2.75E+OO O.OOE+OO 2.56E+02 W-187 2.38E+01 1.99E+01 6.96E+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.52E+03 U-235 2.56E+03 O.OOE+OO 1.55E+02 O.OOE+OO 5.98E+02 O.OOE+OO 2.50E+02 U-238 2.45E+03 O.OOE+OO 1.45E+02 O.OOE+OO 5.60E+02 O.OOE+OO 1.76E+02 Np-239 4.91E-03 4.83E-04 2.66E-04 O.OOE+OO 1.51E-03 O.OOE+OO 9.90E+01 Am-241 8.19E+03 2.88E+03 5.41E+02 O.OOE+OO 4.07E+03 O.OOE+OO 7.42E+02 NOTE: Aio factors listed above are for the controlling (adult) age group, per NUREG-0133 guidance. The pathways included are fish and potable water, the only significant, applicable pathways present at Point Beach. 9.3 Dose Projections As required by TS 5.5.4.e and TS 5.5.4.f dose projections shall be made at least once every 31 days. As described in Section 6.3 .1, when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, appropriate portions of the liquid effluent treatment system should be used to reduce releases of radioactivity to within the allowable limits. The following equations should be used to perform dose projections: Dtbp = Dtb cdl) [9-9] 1 Dmaxp = Dmax cd ) [9-10] Where: Dtbp = total body dose projection for the current calendar month (mrem) Dtb = total body dose to date for the current calendar month as determined by Equation 9-7 (mrem) Dmaxp = maximum organ dose projection for the current calendar month (mrem) Dmax = maximum organ dose to date for the current calendar month as determined by Equation 9-7 (mrem) d = number of days to date for the current calendar month 31 = number of days in projection Page 55 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 10.0 GASEOUS EFFLUENT CALCULATIONS 10.1 Monitor Alarm Setpoint Determination The computerized PBNP radiation monitoring system permits each effluent radiation monitor to be programmed to alarm at two distinct setpoints. The alert setpoint, typically twice the steady state reading, is intended to delineate a changing plant condition, and is established for evaluation purposes only. The high alarm or trip setpoint either will actuate a control function as applicable or will require corrective action to be initiated. Alert Setpoint Guidelines The alert setpoint of each effluent monitor will normally be set to alarm at two times the established steady-state reading. The alert setpoint is normally set at concentrations well below the alarm setpoint value and is never to be set in excess of the alarm setpoint. Certain situations during the course of plant operations may require a deviation from the two times steady-state value. The intent of this setpoint is to warn of changing plant conditions, which may warrant an evaluation to determine the cause of the increased reading. If the increased level is actually due to an increased radiation inventory with the system being monitored, as opposed to an increased background radiation field in the vicinity of the detector, an evaluation should be made to determine the impact of the release. The alert setpoint may be adjusted with prior approval. Alert setpoint adjustments are to be made in accordance with the PBNP RMS Alarm Setpoint and Response Book (Ref. OM 4.1.7). The appropriate detailed response to an effluent alarm also is described in the PBNP RMS Alarm Setpoint and Response Book. High Alarm or Trip Setpoint Guidelines In accordance with PBNP TS 5.5 .4.a, alarm setpoints shall be established for the gaseous effluent monitoring instrumentation to ensure that the release rate of noble gases does not exceed the instantaneous dose rate limits of Section 7 .1.1. These limits correspond to a dose rate at or beyond the SITE BOUNDARY of 500 mrem/yr to the total body or 3000 mrem/yr to the skin. Certain airborne effluent monitors cannot reach the calculated setpoint because they fail high at a lower value. These monitors are indicated by an asterisk (*) in Table 10-1. It is plant operational practice to set these monitors at :S 70% of the fail high value (MSSM No. 93-01). The following mid-range SPINO monitors can read the calculated default setpoints: SPINO 21, 1RE-307; SPING22, 2RE-307; SPINO 23, RE-317; and SPINO 24, RE-327. Page 56 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL The radiation monitoring alarm setpoints are established using the following equations: L Ci

500 SPrs < *AF

                                  -  472

x/QNc
VF * 'LCCi
Ki)

L Ci

3000 SP5 < *AF [10-1]

                            - 472

x/QNc
VF
L[Ci * (Li + 1.1Mi)]

Where: SPrB = monitor setpoint corresponding to the release rate limit for the total body dose rate of 500 mrem/yr (JLCi/cc) SPs = monitor setpoint corresponding to the release rate limit for the skin dose rate of 3000 mremlyr (JLCi/cc) 500 = total body dose rate limit (mremlyr) 3000 = skin dose rate limit (mrem/yr) x/QNG = atmospheric dispersion for direct exposure to noble gas at or beyond the SITE BOUNDARY (sec/m 3see Table 10-2) VF = ventilation3flow rate for the applicable release point and monitor (ft /min) ci = concentration of noble gas radionuclide "i" as determined by radioanalysis ofgrab sample (JLCi/cc) Ki = total body dose conversion factor for noble gas radio nuclide

                         i" (mrem/yr per j.1Ci/m 3, see Table 10-3)

Li = beta skin dose conversion factor for noble gas radio nuclide "i" (mrem/yr per j.1Ci/m 3, see Table 10-3)

               ~   =    gamma     air dose conversion factor for noble gas radio nuclide "i" (mrad/yr per j.1Cilm 3, see Table 10-3) 1.1  =    mrem    skin dose per mrad gamma air dose (mrem/mrad),

472 = 28317 (cc/ft3) x 1/60 (min/sec) AF = additional reduction factor of 0.25 applied to the four release point monitors(RE-214,-221, -224, and -225) to ensure that the maximum allowable SITE BOUNDARY dose rates will not be exceeded in the event simultaneous release from these points occur The lesser value of SPTs and SPs is used to establish the monitor setpoint. Page 57 of 278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Default Monitor Setpoints Default setpoints are established to eliminate the potential of periodically having to adjust the setpoint to reflect slight variations in the radionuclide distribution and variations in release flow rates. Using activities obtained from the 2000-2010 average annual atmospheric releases (see Appendix C for a detailed discussion), the highest annual x/Q, and the maximum ventilation flow rates for each pathway, default setpoints can be determined using Equations 10-1 and 10-2. Gaseous effluent pathway discharge flow rates, the monitors associated with each pathway and default setpoints are listed in Table 10-1. If the default setpoints listed in Table 10-1 exceed the monitors' saturation or fail high levels, the MSS has approved (MSSM No. 93-01) the use of a setpoint which is set at~ 70% of that monitor's fail high level. The current alarm levels are recorded in the RMS Alarm Setpoint and Response Book. Adjustments may be made to the alarm setpoints for release periods if actual flow rates are reduced to less than the maximum values or the actual x/Q values are calculated. This is not typical under conditions with elevated levels in containment or the waste gas decay tank. Alarm setpoint adjustments which result in values higher than the default values are to be made in accordance with the provisions and methodologies of the PBNP RMS Alarm Setpoint and Response Book. To maintain the inequality of Equations 10-1 and 10-2 during the release, the release rate (or release of gaseous effluents) may be adjusted. If at any time the monitor response is greater than that anticipated for the gaseous release (i.e., above the alert alarm setpoint), the activity should be re-evaluated. This re-evaluation will may include resampling of the applicable waste stream. With the setpoints being calculated based on TS release limits, some monitors fail high below the calculated default alarm setpoint. This value is the TS limit that will be reached at the sector of the site boundary with the highest X/Q and D/Q values. For the current airborne monitors, one of the associated SPING monitors has the range required to encompass the default alarm setpoint. Page 58 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-1 GASEOUS EFFLUENT PATHWAYS GASEOUS.EFFLUENT MONITORS DISCHARGE CALCULATED PATHWAY FLOW RATE DEFAULT (cfm) SETPOINT 1*.. (JJ.Cilcc) 66,400

1. Auxiliary Building Vent RE-214* & SPING 23 1 6.75E-04 (1500 )

2. Combined Air Ejector RE-225* 20 2.24E+OO

3. Unit Air Ejector 1(2) RE-215* 10 1.79E+Ol

4. Containment PurgeN ent Unit 1 1RE-212* & SPING 21 25,000 2 7.17E-03 Unit2 2RE-212* & SPING 22 38,0003 4.72E-03 Unit 1(2) 1(2) RE-212* 35 4 5.12E+OO 13,000

5. Gas Stripper Building RE-224* 3.45E-03 (250 1) 43,100

6. Drumming Area Vent RE-221 * & SPING 24 1.04E-03 (500 1)

NOTE 1: From RAM 5.1, Radioactive Airborne Effluent Releases, Table 2, convective flow with fans off NOTE 2: Two fans of 12,500 cfm NOTE 3: Two fans+ 13,000 cfm from gas stripper bldg. NOTE 4: Forced vent with nominal 35 cfm flow rate NOTE 5: Monitors marked with an asterisk(*) have a calculated default alarm setpoint above the monitors fail high or saturation level. See Section 10.1, High Alarm or Trip Setpoint Guidelines for further explanation and designation of SPING monitors that can be set at the calculated default setpoint. Page 59 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-2 CONTROLLING LOCATIONS, PATHWAYS AND ATMOSPHERIC DISPERSION FOR DOSE CALCULATIONS ODCM LOCATION DISTANCE AND PATHWAY(S) x/Ql D/Q SECTION . DIRECTION 3 (m-2) (sec/m ) Noble gases 7.l.l.a Site boundary SSE, 1220 meters2 1.09E-06 N/A Direct exposure 7.l.l.b Site boundary SSE, 1220 meters Inhalation 1.09E-06 N/A Gamma-air 7.2.1 Site boundary SSE, 1220 meters 1.09E-06 N/A Beta-air Inhalation, milk, meat, produce, 7.3.1 Residence/dairy ssw, 1290 3 leafy vegetables 7.15E-07 5.90E-9 meters and ground plane. NOTE 1: Atmospheric dispersion and deposition data taken from Point Beaclt Annual Meteorological and Atmospheric Dispersion Report for 2009, Report No. R-2330244-001, December 2010. NOTE 2: Location corresponds to site boundary distance and sector with the greatest yJQ and D/Q values. NOTE 3: The nearest residence/dairy is in the SSW sector. The distance is conservatively assumed to be at the site boundary. Page 60 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 10.2 Carbon-14 Carbon-14 is a constituent of a nuclear power plants atmospheric effluent that requires specific attention and evaluation. 14C is a pure, low-energy beta emitter (0.156 MeV) that historically has not been a focus of ODCM and nuclear power plant radiological effluent evaluations. The low beta energy means that 14C is not detected by installed effluent monitors, and can only be quantified with sensitive, in-laboratory equipment. Historically, 14C has not been identified as a significant contributor to the effluent source term, on either an activity or dose basis. However, the continued reduction in total effluent releases has increased the relative importance of 14 C, with respect to both the activity released and dose consequence. The PBNP methodology for estimating the activity of 14C released and the dose consequence of the release is described in the sections below. 10.2.1 Carbon-14 Effluent Activity The annual release rate of 14C in gaseous effluents is calculated in accordance with the methodology described in EPRI Technical Report 1021106 "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents" (EPRI, 2010). 14C is primarily generated in a nuclear power plant by one of2 reactions: 17 0(n,a) 14C or I4N(n,p)I4c The 14C production rate is determined by the following equation: N X ( O"th X (/Jth + o-i+f X q;i+f) X l.OE- 24 X A [1 0-2] Prod. Rate = 3

                                                              .?E _

04 Where: Prod = Production rate of C-14 production (J1Ci/s-kgfrom 170 Rate and J1Cils-kg-ppm N from 14N) N = Atoms 17 0 = 1.27£+22 atoms 170/kg H20 14 N = 4.284E+ 19 atoms 14N/kg-ppm N (Jth = "effective" thermal cross-section (b) 17 0 = 0.121 14 N = 0.951 (from EPRJ TR-1021106) (/Jth = Thermal neutron flux (n/cm -s) 2 2

                                  =3.55£13 n/cm -s at BOC (from EPRJTR-1021106)

(Ji+f = "effective " intermediate +fast cross-section (b) 17 0 = 0.0479 14 N = 0.0392 (from EPRJ TR-1021106) 2 {/Ji+f = Intermediate +fast neutron flux (n/cm -s)

                                  =3.51£17 n/cm 2-s at BOC (from EPRJ TR-1021106) l.OE-24 = (cm 2/b)

A = 14C decay constant, 3.833£-12 s-1

3. 7E-04 = d/s-JlCi Page 61 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Using the above formula and example PWR data values (for neutron flux, water mass in the active core and nitrogen content) from the EPRI report, the calculated 14C generation rate is 0.349 JlCi/s from the 17 0 reaction and 2.96E-3 JlCi/s from the 14N reaction. This results in a total 14C production rate of 11.1 Ci/year. According to the EPRI report, the atmospheric release rate is approximately 90-98% of the production rate. The remainder is effectively released via solid waste. For PWRs virtually all ofthe released C-14 is in the non-C02 form, a form which does not contributes to ingestion dose. Based on measurements at Ginna (a Westinghouse plant the same vintage as PBNP), approximately 10% is release as C02 (Kunz, "Measurement of 14C Production and Discharge From the Ginna Nuclear Power Plant, June 1982, p. 20) The neutron flux values listed in the formulae above are based on an assumed 3548 MWth Westinghouse PWR operating continuously at full power. Annual 14 C production and release values can be determined based on actual reactor operating performance at PBNP. As needed, the neutron flux data are obtained from ENG-Fuel/JB each year to estimate the year's 14C production. An evaluation of plant conditions and operating data will be considered to determine if adjustments are needed to the assumed production rate of 14 C. 10.2.2 Carbon-14 Vegetation Concentration The concentration of 14C incorporated in vegetation from 14CO or 14C02 is calculated as described in Regulatory Guide 1.109 (Rev 1) Appendix C, equation C-8: v _ [X ] 0.11 [1 0-3] Cc-14(r, 8)- 3.17E + 07 X p X QC-14 IQ (r, e) 0.16 Where: Cvc-u(r, 8) = the concentration of carbon-14 in vegetation grown at location (r, 8) in pCi/kg 3.17E+07 = conversionfactorequivalent to (1E+12 pCi/Ci)(lx1 03 g/kg)/(3.15E+07 sec/year) p = the fractional equilibrium ratio defined as the total annual release time (for 14C atmospheric releases) to the total annual release time during which photosynthesis occurs (assumed to be 4400 hours) with p :S 1. 0. 0.11/0.16 = total plant mass as natural carbon (0.11) divided the concentration of natural carbon in the atmosphere (0.16 g/m 3) Qc-14 = the annual release rate of 14C (Ci/year) x!Q (r, 8) = the annual average atmospheric dispersion factor, in seclm 3 for the point of interest defined by (r, 8). The concentration calculated above is then used to determine the concentration in meat and milk, no different from other radionuclides. The resultant dose is calculated in the same fashion as listed in the applicable sections below. Page 62 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 10.3 Dose Rate Calculations- Noble Gases PBNP TS 5.5.4.g limits the instantaneous dose rate at the SITE BOUNDARY due to noble gas releases to:

                         *   :::; 500 mrem/yr to the total body
                         *   :::; 3 000 mrem/yr to the skin Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded. If the alarm setpoint is exceeded by any gaseous release from the station, and evaluation of the SITE BOUNDARY dose rate resulting from the release shall be performed using the following equations:

Dtb = x/Q

L(Ki
Qa [1 0-4]

i bs = x/Q

l:[CLi + 1.1Ma
Qi] [10-5]

i Where: btb = the total body dose rate (mrem/yr), Ds = the skin dose rate (mrem/yr), x!Q = the atmospheric dispersion to the controlling SITE BOUNDARY location (sec/m 3, see Table 10-2) Qi = the average release rate of radio nuclide "i" over the release period under evaluation, not to exceed one hour (uCi/sec) Ki = total body dose conversion factor for noble gas radio nuclide 3

                      "i" (mrem/yr per JLCi/m see Table 10-3)

Li = beta skin dose conversion factor for noble gas radio nuclide "i" (mrem/yr per JLCi/m 3 see Table 10-3) M = gamma air dose conversion factor for noble gas radionuclide "i" (mradlyr per JLCi/m 3 see Table 10-3) 1.1 = mrem skin dose per mrad gamma air dose (mrem/mrad) Page 63 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-3 DOSE FACTORS FOR NOBLE GASES TOTAL BODY SKIN DOSE GAMMA AIR BETA AIR DOSE FACTOR FACTOR DOSE FACTOR DOSE FACTOR RADIONUCLIDE ~ Li Mi Ni (mrem/yr per (mrelll/yr per (mrad/yr per (mrad/yr. per 3 J.tCi/m ) p,Ci!m3) p,Ci/m3) p,Ci/m3 ) Kr-83m 7.56E-02 --- 1.93 E+01 2.88 E+02 Kr-85m 1.17 E+03 1.46 E+03 1.23 E+03 1.97 E+03 Kr-85 1.61 E+01 1.34 E+03 1.72 E+01 1.95 E+03 Kr-87 5.92 E+03 9.73 E+03 6.17 E+03 1.03 E+04 Kr-88 1.47 E+04 2.37 E+03 1.52 E+04 2.93 E+03 Kr-89 1.66 E+04 1.01 E+04 1.73 E+04 1.06 E+04 Kr-90 1.56 E+04 7.29 E+03 1.63 E+04 7.83 E+03 Xe-131m 9.15 E+01 4.76 E+02 1.56 E+02 1.11 E+03 Xe-133m 2.51 E+02 9.94 E+02 3.27 E+02 1.48 E+03 Xe-133 2.94 E+02 3.06 E+02 3.53 E+02 1.05 E+03 Xe-135m 3.12 E+03 7.11 E+02 3.36 E+03 7.39 E+02 Xe-135 1.81 E+03 1.86 E+03 1.92 E+03 2.46 E+03 Xe-137 1.42 E+03 1.22 E+04 1.51 E+03 1.27 E+04 Xe-138 8.83 E+03 4.13 E+03 9.21 E+03 4.75 E+03 Ar-41 8.84 E+03 2.69 E+03 9.30 E+03 3.28 E+03 Source: Reg. Gmde 1.109, Table B-1 10.4 Dose Rate Calculations- Radioiodine, Tritium, Particulates PBNP TS 5.5.4.g limits the instantaneous dose rate to 1500 mrem/yr to any organ for I-131, I-133, tritium, and particulates with half-lives greater than eight days. To demonstrate compliance with this limit, an evaluation may be performed at a frequency no greater than that corresponding to the sampling and analysis time period for CONTINUOUS RELEASES and for BATCH RELEASES on the time period over which any BATCH RELEASE is to occur when conditions depart from bounding conditions of the previous year. The following equation shall be used for the dose rate evaluation: Jj 0 = X I Q

Ii (Rio *Qa [10-6]

Where: n* 0 the average organ dose rate over the sampling time period (mrem/yr) x!Q the atmospheric dispersion to the controlling SITE BOUNDARY location (sec/m 3, see Table 1 0-2) the dose parameter for radio nuclide "i ",for the child inhalation pathway (mrem/yr per J..LCi/m 3 see Table 1 0-6) the average release rate over the appropriate sampling period and analysis frequency for radio nuclide "i ", 1-131, 1-133, tritium, or other radio nuclide in particulate form with a half-life greater than 8 days (J..LCi/sec) Page 64 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 10.5 Dose Calculations- Noble Gases PBNP TS 5.5.4.h requires that dose contributions due to the release of noble gases should be determined at least once every 31 days in order to evaluate compliance with the quarterly dose limits of< 5 mrad, gamma-air and< 10 mrad, beta-air and annual dose limits of< 10 mrad, gamma-air and < 20 mrad, beta-air. The following equations shall be used to calculate the gamma-air and beta-air doses: Dy = 3.17£-08

x/Q
LcMi
Qi) [1 0-7]

i Dp = 3.17£- 08

x/Q
I (Ni
Qi) [10-8]

i Where: air dose due to gamma emissions for noble gas radionuclides (mrad), Dp air dose due to beta emissions for noble gas radionuclides (mrad), xiQ atmospheric dispersion to the controlling SITE BOUNDARY location (seclm 3 , see Table 10-2) cumulative release of noble gas radionuclide "i" over the period of interest (J-LCi) air dose factor due to gamma emissions form noble gas radionuclide "i" (mradlyr per J-LCi 1m 3, see Table 10-3) air dose factor due to beta emissions form noble gas radionuclide "i" (mradlyr per j.LCi 1m3, see Table 10-3) 3.17E-08 yrlsec Page 65 of 278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 10.6 Dose Calculations- Radioiodine, Tritium, Particulates PBNP TS 5.5.4.i requires that dose contributions due to the release ofi-131, I-133, tritium, and/or particulates with half-lives greater than eight days should be determined at least once every 31 days in order to evaluate compliance with the quarterly dose limit of

           < 7.5 mrem and annual dose limit of < 15 mrem to any organ, per unit. For the two unit PBNP site, the limit is 15 mrem per quarter and 30 mrem per year. The following equation shall be used to evaluate the maximum organ dose:

Daop = 3.17£-08 x W x L(Rio

Qi) [10-9]

i Where: Daop = dose for age group "a" to organ "o ", including the total body, via pathway "p" (mrem), W = atmospheric dispersion factor to the controlling location(s) as identified in Table 10-2

                               = x!Q (seclm 3) for inhalation pathway and C-14 or H-3 in food pathways
                               = D/Q (m- 2) for ground plane and food pathways (except C-14 and H-3).

Rio = dose factor for radionuclide "i" to organ "o"for each age group "a" and the applicable pathway "p" (mremlyr per J.LCi 1m3 or m2 -mrem/yr per J.LCi/sec, see Table 10-4 through Table 10-21) Qi = cumulative release for radionuclide "i" (J.LCi), 3.17E-08 = conversion factor for yr/sec In general, the infant or child is expected to be the controlling age group for gaseous exposures. Page 66 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 10.7 Gaseous Dose Projection As required by TS 5.5.4.e and TS 5.5.4.f dose projections shall be made at least once every 31 days. As described in Section 7.4.1, when the projected doses in a period of31 days would exceed 2% of the guidelines for the annual dose or dose commitment, appropriate portions of the gaseous effluent treatment system should be used to reduce releases of radioactivity to within the allowable limits. The following equations should be used to perform dose projections: Dyp = Dy(31/d) [10-10] Dpp = Dp(31/d) [10-11] Dmaxp = Dmax (31 /d) [10-12] Where: Dyp = projected 31-day gamma-air dose (mrad) Dy = gamma-air dose for current calendar month (mrad) Dpp = projected 31-day beta-air dose (mrad) Dp = beta-air dose for current calendar month (mrad) Dmaxp = maximum organ dose projection for the current calendar month (mrem) d = number of days to date for the current month (days) 31 = number ofdays in projection (days) Page 67 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-4 Rio, INHALATION PATHWAY DOSE FACTORS- ADULT (mrem/yr per ~tCilm 3') NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 7.18E+02 7.18E+02 7.18E+02 7.18E+02 7.18E+02 7.18E+02 C-14 1.82E+04 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 F-18 3.77E+03 O.OOE+OO 4.15E+02 O.OOE+OO O.OOE+OO O.OOE+OO 7.39E+01 Na-22 1.04E+05 1.04E+05 1.04E+05 1.04E+05 1.04E+05 1.04E+05 1.04E+05 Na-24 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 Sc-46 4.41E+05 8.56E+05 2.49E+05 O.OOE+OO 7.99E+05 O.OOE+OO 2.15E+05 P-32 1.32E+06 7.71E+04 5.01E+04 O.OOE+OO O.OOE+OO O.OOE+OO 8.64E+04 Cr-51 O.OOE+OO O.OOE+OO 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 Mn-54 O.OOE+OO 3.96E+04 6.30E+03 O.OOE+OO 9.84E+03 1.40E+06 7.74E+04 Mn-56 O.OOE+OO 1.24E+OO 1.83E-01 O.OOE+OO 1.30E+OO 9.44E+03 2.02E+04 Fe-55 2.46E+04 1.70E+04 3.94E+03 O.OOE+OO O.OOE+OO 7.21E+04 6.03E+03 Fe-59 1.18E+04 2.78E+04 1.06E+04 O.OOE+OO O.OOE+OO 1.02E+06 1.88E+05 Co-57 O.OOE+OO 6.92E+02 6.71E+02 O.OOE+OO O.OOE+OO 3.70E+05 3.14E+04 Co-58 O.OOE+OO 1.58E+03 2.07E+03 O.OOE+OO O.OOE+OO 9.28E+05 1.06E+05 Co-60 O.OOE+OO 1.15E+04 1.48E+04 O.OOE+OO O.OOE+OO 5.97E+06 2.85E+05 Ni-63 4.32E+05 3.14E+04 1.45E+04 O.OOE+OO O.OOE+OO 1.78E+05 1.34E+04 Ni-65 1.54E+OO 2.26E-01 9.12E-02 O.OOE+OO O.OOE+OO 5.60E+03 1.23E+04 Cu-64 O.OOE+OO 1.46E+OO 6.15E-01 O.OOE+OO 4.62E+OO 6.78E+03 4.90E+04 Zn-65 3.24E+04 1.03E+05 4.66E+04 O.OOE+OO 6.90E+04 8.64E+05 5.34E+04 Zn-69m 8.16E+OO 1.96E+01 1.79E+OO O.OOE+OO 1.18E+01 1.90E+04 1.37E+05 Zn-69 3.38E-02 6.51E-02 4.52E-03 O.OOE+OO 4.22E-02 9.20E+02 1.63E+01 As-76 9.78E+02 2.61E+03 2.19E+04 9.48E+02 2.90E+03 1.01E+05 8.59E+04 Br-82 O.OOE+OO O.OOE+OO 1.35E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.04E+04 Br-83 O.OOE+OO O.OOE+OO 2.41E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.32E+02 Br-84 O.OOE+OO O.OOE+OO 3.13E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.64E-03 Br-85 O.OOE+OO O.OOE+OO 1.28E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.35E+05 5.90E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.66E+04 Rb-88 O.OOE+OO 3.87E+02 1.93E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.34E-09 Rb-89 O.OOE+OO 2.56E+02 1.70E+02 O.OOE+OO O.OOE+OO O.OOE+OO 9.28E-12 Sr-89 3.04E+05 O.OOE+OO 8.72E+03 O.OOE+OO O.OOE+OO 1.40E+06 3.50E+05 Sr-90 2.87E+07 O.OOE+OO 5.77E+05 O.OOE+OO O.OOE+OO 9.60E+06 7.22E+05 Sr-91 6.19E+01 O.OOE+OO 2.50E+OO O.OOE+OO O.OOE+OO 3.65E+04 1.91E+05 Sr-92 6.74E+OO O.OOE+OO 2.91E-01 O.OOE+OO O.OOE+OO 1.65E+04 4.30E+04 Y-90 2.09E+03 O.OOE+OO 5.61E+01 O.OOE+OO O.OOE+OO 1.70E+05 5.06E+05 Y-91m 2.61E-01 O.OOE+OO 1.02E-02 O.OOE+OO O.OOE+OO 1.92E+03 1.33E+OO Y-91 4.62E+05 O.OOE+OO 1.24E+04 O.OOE+OO O.OOE+OO 1.70E+06 3.85E+05 Page 68 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-4 Rio, INHALATION PATHWAY DOSE FACTORS -ADULT NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Y-92 1.03E+01 O.OOE+OO 3.02E-01 O.OOE+OO O.OOE+OO 1.57E+04 7.35E+04 Y-93 9.44E+01 O.OOE+OO 2.61E+OO O.OOE+OO O.OOE+OO 4.85E+04 4.22E+05 Zr-95 1.07E+05 3.44E+04 2.33E+04 O.OOE+OO 5.42E+04 1.77E+06 1.50E+05 Zr-97 9.68E+01 1.96E+01 9.04E+OO O.OOE+OO 2.97E+01 7.87E+04 5.23E+05 Nb-95 1.41E+04 7.82E+03 4.21E+03 O.OOE+OO 7.74E+03 5.05E+05 1.04E+05 Nb-97 2.22E-01 5.62E-02 2.05E-02 O.OOE+OO 6.54E-02 2.40E+03 2.42E+02 Mo-99 O.OOE+OO 1.21E+02 2.30E+01 O.OOE+OO 2.91E+02 9.12E+04 2.48E+05 Tc-99m 1.03E-03 2.91E-03 3.70E-02 O.OOE+OO 4.42E-02 7.64E+02 4.16E+03 Tc-99 2.50E+02 3.71E+02 1.00E+02 O.OOE+OO 4.68E+03 8.08E+05 6.03E+04 Tc-101 4.18E-05 6.02E-05 5.90E-04 O.OOE+OO l.OSE-03 3.99E+02 1.09E-11 Ru-103 1.53E+03 O.OOE+OO 6.58E+02 O.OOE+OO 5.83E+03 5.05E+05 1.10E+05 Ru-105 7.90E-01 O.OOE+OO 3.11E-01 O.OOE+OO 1.02E+OO 1.10E+04 4.82E+04 Ru-106 6.91E+04 O.OOE+OO 8.72E+03 O.OOE+OO 1.34E+05 9.36E+06 9.12E+05 Rh-105 7.39E+OO 5.38E+OO 3.54E+OO O.OOE+OO 2.29E+01 1.93E+04 8.72E+04 Ag-110m 1.08E+04 1.00E+04 5.94E+03 O.OOE+OO 1.97E+04 4.63E+06 3.02E+05 Sn-113 2.70E+04 1.01E+04 8.00E+04 5.63E+03 5.33E+03 5.63E+05 6.22E+04 Sn-117m 2.79E+04 1.48E+03 7.11E+04 7.11E+02 7.11E+02 5.63E+05 5.33E+04 Sb-122 1.90E+03 1.48E+03 2.96E+04 6.52E+02 7.70E+02 1.63E+05 1.16E+05 Sb-124 3.12E+04 5.89E+02 1.24E+04 7.55E+01 O.OOE+OO 2.48E+06 4.06E+05 Sb-125 5.34E+04 5.95E+02 1.26E+04 5.40E+01 O.OOE+OO 1.74E+06 1.01E+05 Te-125m 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 Te-127m 1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 Te-127 1.40E+OO 6.42E-01 3.10E-01 1.06E+OO 5.10E+OO 6.51E+03 5.74E+04 Te-129m 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 Te-129 4.98E-02 2.39E-02 1.24E-02 3.90E-02 1.87E-01 1.94E+03 1.57E+02 Te-131m 6.99E+01 4.36E+01 2.90E+01 5.50E+01 3.09E+02 1.46E+05 5.56E+05 Te-131 l.llE-02 5.95E-03 3.59E-03 9.36E-03 4.37E-02 1.39E+03 1.84E+01 Te-132 2.60E+02 2.15E+02 1.62E+02 1.90E+02 1.46E+03 2.88E+05 5.10E+05 I-130 4.58E+03 1.34E+04 5.28E+03 1.14E+06 2.09E+04 O.OOE+OO 7.69E+03 I-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 O.OOE+OO 6.28E+03 I-132 1.16E+03 3.26E+03 1.16E+03 1.14E+05 5.18E+03 O.OOE+OO 4.06E+02 I-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 O.OOE+OO 8.88E+03 I-134 6.44E+02 1.73E+03 6.15E+02 2.98E+04 2.75E+03 O.OOE+OO 1.01E+OO I-135 2.68E+03 6.98E+03 2.57E+03 4.48E+05 1.11E+04 O.OOE+OO 5.25E+03 Cs-134 3.73E+05 8.48E+05 7.28E+05 O.OOE+OO 2.87E+05 9.76E+04 1.04E+04 Cs-134m 1.27E+02 2.56E+02 1.38E+02 O.OOE+OO 1.46E+02 2.34E+01 6.34E+01 Cs-136 3.90E+04 1.46E+05 1.10E+05 O.OOE+OO 8.56E+04 1.20E+04 1.17E+04 Page 69 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-4 Rio, INHALATION PATHWAY DOSE FACTORS -ADULT NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Cs-137 4.78E+05 6.21E+05 4.28E+05 O.OOE+OO 2.22E+05 7.52E+04 8.40E+03 Cs-138 3.31E+02 6.21E+02 3.24E+02 O.OOE+OO 4.80E+02 4.86E+01 1.86E-03 Ba-139 9.36E-01 6.66E-04 2.74E-02 O.OOE+OO 6.22E-04 3.76E+03 8.96E+02 Ba-140 3.90E+04 4.90E+01 2.57E+03 O.OOE+OO 1.67E+01 1.27E+06 2.18E+05 Ba-141 l.OOE-01 7.53E-05 3.36E-03 O.OOE+OO 7.00E-05 1.94E+03 1.16E-07 Ba-142 2.63E-02 2.70E-05 1.66E-03 O.OOE+OO 2.29E-05 1.19E+03 1.57E-16 La-140 3.44E+02 1.74E+02 4.58E+01 O.OOE+OO O.OOE+OO 1.36E+05 4.58E+05 La-142 6.83E-01 3.10E-01 7.72E-02 O.OOE+OO O.OOE+OO 6.33E+03 2.11E+03 Ce-141 1.99E+04 1.35E+04 1.53E+03 O.OOE+OO 6.26E+03 3.62E+05 1.20E+05 Ce-143 1.86E+02 1.38E+02 1.53E+01 O.OOE+OO 6.08E+01 7.98E+04 2.26E+05 Ce-144 3.43E+06 1.43E+06 1.84E+05 O.OOE+OO 8.48E+05 7.78E+06 8.16E+05 Pr-143 9.36E+03 3.75E+03 4.64E+02 O.OOE+OO 2.16E+03 2.81E+05 2.00E+05 Pr-144 3.01E-02 1.25E-02 1.53E-03 O.OOE+OO 7.05E-03 1.02E+03 2.15E-08 Nd-147 5.27E+03 6.10E+03 3.65E+02 O.OOE+OO 3.56E+03 2.21E+05 1.73E+05 Eu-152 1.90E+06 4.33E+05 3.81E+05 O.OOE+OO 2.68E+06 2.74E+06 1.27E+05 W-187 8.48E+OO 7.08E+OO 2.48E+OO O.OOE+OO O.OOE+OO 2.90E+04 1.55E+05 U-235 8.00E+07 O.OOE+OO 4.86E+06 O.OOE+OO 1.87E+07 3.92E+08 3.87E+05 U-238 7.66E+07 O.OOE+OO 4.54E+06 O.OOE+OO 1.74E+07 3.66E+08 2.73E+05 Np-239 2.30E+02 2.26E+01 1.24E+01 O.OOE+OO 7.00E+01 3.76E+04 1.19E+05 Am-241 8.08E+09 2.87E+09 5.37E+08 O.OOE+OO 4.03E+09 4.85E+08 3.68E+05 Page 70 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-5 Rio, INHALATION PATHWAY DOSE FACTORS TEEN ( mrem/yr per p,Ci!m3') NUCLIDE BONE LIVER T.*BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 7.25E+02 7.25E+02 7.25E+02 7.25E+02 7.25E+02 7.25E+02 C-14 2.60E+04 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 F-18 5.22E+03 O.OOE+OO 5.68E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.11E+02 Na-22 1.04E+05 1.04E+05 1.04E+05 1.04E+05 1.04E+05 1.04E+05 1.04E+05 Na-24 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 Sc-46 5.79E+05 1.13E+06 3.34E+05 O.OOE+OO 1.08E+06 O.OOE+OO 2.38E+05 P-32 1.89E+06 1.10E+05 7.16E+04 O.OOE+OO O.OOE+OO O.OOE+OO 9.28E+04 Cr-51 O.OOE+OO O.OOE+OO 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.00E+03 Mn-54 O.OOE+OO 5.11E+04 8.40E+03 O.OOE+OO 1.27E+04 1.98E+06 6.68E+04 Mn-56 O.OOE+OO 1.70E+OO 2.52E-01 O.OOE+OO 1.79E+OO 1.52E+04 5.74E+04 Fe-55 3.34E+04 2.38E+04 5.54E+03 O.OOE+OO O.OOE+OO 1.24E+05 6.39E+03 Fe-59 1.59E+04 3.70E+04 1.43E+04 O.OOE+OO O.OOE+OO 1.53E+06 1.78E+05 Co-57 O.OOE+OO 9.44E+02 9.20E+02 O.OOE+OO O.OOE+OO 5.86E+05 3.14E+04 Co-58 O.OOE+OO 2.07E+03 2.78E+03 O.OOE+OO O.OOE+OO 1.34E+06 9.52E+04 Co-60 O.OOE+OO 1.51E+04 1.98E+04 O.OOE+OO O.OOE+OO 8.72E+06 2.59E+05 Ni-63 5.80E+05 4.34E+04 1.98E+04 O.OOE+OO O.OOE+OO 3.07E+05 1.42E+04 Ni-65 2.18E+OO 2.93E-01 1.27E-01 O.OOE+OO O.OOE+OO 9.36E+03 3.67E+04 Cu-64 O.OOE+OO 2.03E+OO 8.48E-01 O.OOE+OO 6.41E+OO 1.11E+04 6.14E+04 Zn-65 3.86E+04 1.34E+05 6.24E+04 O.OOE+OO 8.64E+04 1.24E+06 4.66E+04 Zn-69m 1.15E+01 2.71E+01 2.49E+OO O.OOE+OO 1.65E+01 3.14E+04 1.71E+05 Zn-69 4.83E-02 9.20E-02 6.46E-03 O.OOE+OO 6.02E-02 1.58E+03 2.85E+02 As-76 1.16E+03 3.26E+03 2.61E+04 1.10E+03 3.56E+03 1.19E+05 1.04E+05 Br-82 O.OOE+OO O.OOE+OO 1.82E+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO 3.44E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 4.33E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 1.83E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.90E+05 8.40E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.77E+04 Rb-88 O.OOE+OO 5.46E+02 2.72E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.92E-05 Rb-89 O.OOE+OO 3.52E+02 2.33E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.38E-07 Sr-89 4.34E+05 O.OOE+OO 1.25E+04 O.OOE+OO O.OOE+OO 2.42E+06 3.71E+05 Sr-90 3.31E+07 O.OOE+OO 6.66E+05 O.OOE+OO O.OOE+OO 1.65E+07 7.65E+05 Sr-91 8.80E+01 O.OOE+OO 3.51E+OO O.OOE+OO O.OOE+OO 6.07E+04 2.59E+05 Sr-92 9.52E+OO O.OOE+OO 4.06E-01 O.OOE+OO O.OOE+OO 2.74E+04 1.19E+05 Y-90 2.98E+03 O.OOE+OO 8.00E+01 O.OOE+OO O.OOE+OO 2.93E+05 5.59E+05 Y-91m 3.70E-01 O.OOE+OO 1.42E-02 O.OOE+OO O.OOE+OO 3.20E+03 3.02E+01 Y-91 6.61E+05 O.OOE+OO 1.77E+04 O.OOE+OO O.OOE+OO 2.94E+06 4.09E+05 Page 71 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-5 Rio, INHALATION PATHWAY DOSE FACTORS -TEEN NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Y-92 1.47E+01 O.OOE+OO 4.29E-01 O.OOE+OO O.OOE+OO 2.68E+04 1.65E+05 Y-93 1.35E+02 O.OOE+OO 3.72E+OO O.OOE+OO O.OOE+OO 8.32E+04 5.79E+05 Zr-95 1.46E+05 4.58E+04 3.15E+04 O.OOE+OO 6.74E+04 2.69E+06 1.49E+05 Zr-97 1.38E+02 2.72E+01 1.26E+01 O.OOE+OO 4.12E+01 1.30E+05 6.30E+05 Nb-95 1.86E+04 1.03E+04 5.66E+03 O.OOE+OO 1.00E+04 7.51E+05 9.68E+04 Nb-97 3.14E-01 7.78E-02 2.84E-02 O.OOE+OO 9.12E-02 3.93E+03 2.17E+03 Mo-99 O.OOE+OO 1.69E+02 3.22E+01 O.OOE+OO 4.11E+02 1.54E+05 2.69E+05 Tc-99m 1.38E-03 3.86E-03 4.99E-02 O.OOE+OO 5.76E-02 1.15E+03 6.13E+03 Tc-99 3.58E+02 5.26E+02 1.43E+02 O.OOE+OO 6.68E+03 1.39E+06 6.39E+04 Tc-101 5.92E-05 8.40E-05 8.24E-04 O.OOE+OO 1.52E-03 6.67E+02 8.72E-07 Ru-103 2.10E+03 O.OOE+OO 8.96E+02 O.OOE+OO 7.43E+03 7.83E+05 1.09E+05 Ru-105 1.12E+OO O.OOE+OO 4.34E-01 O.OOE+OO 1.41E+OO 1.82E+04 9.04E+04 Ru-106 9.84E+04 O.OOE+OO 1.24E+04 O.OOE+OO 1.90E+05 1.61E+07 9.60E+05 Rh-105 1.06E+01 7.58E+OO 4.99E+OO O.OOE+OO 3.23E+01 3.27E+04 9.84E+04 Ag-110m 1.38E+04 1.31E+04 7.99E+03 O.OOE+OO 2.50E+04 6.75E+06 2.73E+05 Sn-113 2.81E+04 1.24E+04 9.48E+04 6.52E+03 6.52E+03 6.81E+03 7.41E+04 Sn-117m 2.73E+04 1.87E+03 9.19E+04 8.59E+02 9.19E+02 7.11E+05 6.22E+04 Sb-122 2.01E+03 1.84E+03 3.85E+04 7.41E+02 9.48E+02 1.99E+05 1.39E+05 Sb-124 4.30E+04 7.94E+02 1.68E+04 9.76E+01 O.OOE+OO 3.85E+06 3.98E+05 Sb-125 7.38E+04 8.08E+02 1.72E+04 7.04E+01 O.OOE+OO 2.74E+06 9.92E+04 Te-125m 4.88E+03 2.24E+03 6.67E+02 1.40E+03 O.OOE+OO 5.36E+05 7.50E+04 Te-127m 1.80E+04 8.16E+03 2.18E+03 4.38E+03 6.54E+04 1.66E+06 1.59E+05 Te-127 2.01E+OO 9.12E-01 4.42E-01 1.42E+OO 7.28E+OO 1.12E+04 8.08E+04 Te-129m 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 Te-129 7.10E-02 3.38E-02 1.76E-02 5.18E-02 2.66E-01 3.30E+03 1.62E+03 Te-131m 9.84E+01 6.01E+01 4.02E+01 7.25E+01 4.39E+02 2.38E+05 6.21E+05 Te-131 1.58E-02 8.32E-03 5.04E-03 1.24E-02 6.18E-02 2.34E+03 1.51E+01 Te-132 3.60E+02 2.90E+02 2.19E+02 2.46E+02 1.95E+03 4.49E+05 4.63E+05 I-130 6.24E+03 1.79E+04 7.17E+03 1.49E+06 2.75E+04 O.OOE+OO 9.12E+03 I-131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 O.OOE+OO 6.49E+03 I-132 1.59E+03 4.38E+03 1.58E+03 1.51E+05 6.92E+03 O.OOE+OO 1.27E+03 I-133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 O.OOE+OO 1.03E+04 I-134 8.88E+02 2.32E+03 8.40E+02 3.95E+04 3.66E+03 O.OOE+OO 2.04E+01 I-135 3.70E+03 9.44E+03 3.49E+03 6.21E+05 1.49E+04 O.OOE+OO 6.95E+03 Cs-134 5.02E+05 1.13E+06 5.49E+05 O.OOE+OO 3.75E+05 1.46E+05 9.76E+03 Cs-134m 1.76E+02 3.48E+02 1.88E+02 O.OOE+OO 2.03E+02 3.65E+01 1.62E+02 Cs-136 5.15E+04 1.94E+05 1.37E+05 O.OOE+OO 1.10E+05 1.78E+04 1.09E+04 Page 72 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-5 Ria, INHALATION PATHWAY DOSE FACTORS- TEEN NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Cs-137 6.70E+05 8.48E+05 3.11E+05 O.OOE+OO 3.04E+05 1.21E+05 8.48E+03 Cs-138 4.66E+02 8.56E+02 4.46E+02 O.OOE+OO 6.62E+02 7.87E+01 2.70E-01 Ba-139 1.34E+OO 9.44E-04 3.90E-02 O.OOE+OO 8.88E-04 6.46E+03 6.45E+03 Ba-140 5.47E+04 6.70E+01 3.52E+03 O.OOE+OO 2.28E+01 2.03E+06 2.29E+05 Ba-141 1.42E-01 1.06E-04 4.74E-03 O.OOE+OO 9.84E-05 3.29E+03 7.46E-04 Ba-142 3.70E-02 3.70E-05 2.27E-03 O.OOE+OO 3.14E-05 1.91E+03 4.79E-10 La-140 4.79E+02 2.36E+02 6.26E+01 O.OOE+OO O.OOE+OO 2.14E+05 4.87E+05 La-142 9.60E-01 4.25E-01 1.06E-01 O.OOE+OO O.OOE+OO 1.02E+04 1.20E+04 Ce-141 2.84E+04 1.90E+04 2.17E+03 O.OOE+OO 8.88E+03 6.14E+05 1.26E+05 Ce-143 2.66E+02 1.94E+02 2.16E+01 O.OOE+OO 8.64E+01 1.30E+05 2.55E+05 Ce-144 4.89E+06 2.02E+06 2.62E+05 O.OOE+OO 1.21E+06 1.34E+07 8.64E+05 Pr-143 1.34E+04 5.31E+03 6.62E+02 O.OOE+OO 3.09E+03 4.83E+05 2.14E+05 Pr-144 4.30E-02 1.76E-02 2.18E-03 O.OOE+OO 1.01E-02 1.75E+03 2.35E-04 Nd-147 7.86E+03 8.56E+03 5.13E+02 O.OOE+OO 5.02E+03 3.72E+05 1.82E+05 Eu-152 2.37E+06 5.75E+05 5.04E+05 O.OOE+OO 2.67E+06 4.01E+06 1.08E+05 W-187 1.20E+01 9.76E+OO 3.43E+OO O.OOE+OO O.OOE+OO 4.74E+04 1.77E+05 U-235 1.14E+08 O.OOE+OO 6.94E+06 O.OOE+OO 2.67E+07 6.75E+08 4.10E+05 U-238 1.09E+08 O.OOE+OO 6.48E+06 O.OOE+OO 2.50E+07 6.31E+08 2.90E+05 Np-239 3.38E+02 3.19E+01 1.77E+01 O.OOE+OO l.OOE+02 6.49E+04 1.32E+05 Am-241 8.48E+09 3.26E+09 5.68E+08 O.OOE+OO 4.26E+09 8.40E+08 3.90E+05 Page 73 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-6 Rio, INHALATION PATHWAY DOSE FACTORS CHILD (mrem/yr Jer J.tCi/m 3') NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 6.40E+02 6.40E+02 6.40E+02 6.40E+02 6.40E+02 6.40E+02 C-14 3.59E+04 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 F-18 6.96E+03 O.OOE+OO 6.85E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.25E+03 Na-22 1.63E+05 1.63E+05 1.63E+05 1.63E+05 1.63E+05 1.63E+05 1.63E+05 Na-24 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 Sc-46 7.29E+05 9.99E+05 3.85E+05 O.OOE+OO 8.84E+05 O.OOE+OO 9.07E+04 P-32 2.60E+06 1.14E+05 9.88E+04 O.OOE+OO O.OOE+OO O.OOE+OO 4.22E+04 Cr-51 O.OOE+OO O.OOE+OO 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 Mn-54 O.OOE+OO 4.29E+04 9.51E+03 O.OOE+OO 1.00E+04 1.58E+06 2.29E+04 Mn-56 O.OOE+OO 1.66E+OO 3.12E-01 O.OOE+OO 1.67E+OO 1.31E+04 1.23E+05 Fe-55 4.74E+04 2.52E+04 7.77E+03 O.OOE+OO O.OOE+OO 1.11E+05 2.87E+03 Fe-59 2.07E+04 3.34E+04 1.67E+04 O.OOE+OO O.OOE+OO 1.27E+06 7.07E+04 Co-57 O.OOE+OO 9.03E+02 1.07E+03 O.OOE+OO O.OOE+OO 5.07E+05 1.32E+04 Co-58 O.OOE+OO 1.77E+03 3.16E+03 O.OOE+OO O.OOE+OO 1.11E+06 3.44E+04 Co-60 O.OOE+OO 1.31E+04 2.26E+04 O.OOE+OO O.OOE+OO 7.07E+06 9.62E+04 Ni-63 8.21E+05 4.63E+04 2.80E+04 O.OOE+OO O.OOE+OO 2.75E+05 6.33E+03 Ni-65 2.99E+OO 2.96E-01 1.64E-01 O.OOE+OO O.OOE+OO 8.18E+03 8.40E+04 Cu-64 O.OOE+OO 1.99E+OO 1.07E+OO O.OOE+OO 6.03E+OO 9.58E+03 3.67E+04 Zn-65 4.26E+04 1.13E+05 7.03E+04 O.OOE+OO 7.14E+04 9.95E+05 1.63E+04 Zn-69m 1.58E+01 2.69E+01 3.18E+OO O.OOE+OO 1.56E+01 2.72E+04 l.OOE+05 Zn-69 6.70E-02 9.66E-02 8.92E-03 O.OOE+OO 5.85E-02 1.42E+03 1.02E+04 As-76 1.64E+03 4.11E+03 3.01E+04 1.51E+03 4.11E+03 9.32E+04 1.64E+05 Br-82 O.OOE+OO O.OOE+OO 2.09E+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO 4.74E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 5.48E+05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 2.53E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.98E+05 1.14E+05 O.OOE+OO O.OOE+OO O.OOE+OO 7.99E+03 Rb-88 O.OOE+OO 5.62E+02 3.66E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.72E+01 Rb-89 O.OOE+OO 3.45E+02 2.90E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.89E+OO Sr-89 5.99E+05 O.OOE+OO 1.72E+04 O.OOE+OO O.OOE+OO 2.16E+06 1.67E+05 Sr-90 3.85E+07 O.OOE+OO 7.66E+05 O.OOE+OO O.OOE+OO 1.48E+07 3.43E+05 Sr-91 1.21E+02 O.OOE+OO 4.59E+OO O.OOE+OO O.OOE+OO 5.33E+04 1.74E+05 Sr-92 1.31E+01 O.OOE+OO 5.25E-01 O.OOE+OO O.OOE+OO 2.40E+04 2.42E+05 Y-90 4.11E+03 O.OOE+OO 1.11E+02 O.OOE+OO O.OOE+OO 2.62E+05 2.68E+05 Y-91m 5.07E-01 O.OOE+OO 1.84E-02 O.OOE+OO O.OOE+OO 2.81E+03 1.72E+03 Y-91 9.14E+05 O.OOE+OO 2.44E+04 O.OOE+OO O.OOE+OO 2.63E+06 1.84E+05 Page 74 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-6 Rio, INHALATION PATHWAY DOSE FACTORS -CHILD NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Y-92 2.04E+01 O.OOE+OO 5.81E-01 O.OOE+OO O.OOE+OO 2.39E+04 2.39E+05 Y-93 1.86E+02 O.OOE+OO 5.11E+OO O.OOE+OO O.OOE+OO 7.44E+04 3.89E+05 Zr-95 1.90E+05 4.18E+04 3.70E+04 O.OOE+OO 5.96E+04 2.23E+06 6.11E+04 Zr-97 1.88E+02 2.72E+01 1.60E+01 O.OOE+OO 3.89E+01 1.13E+05 3.51E+05 Nb-95 2.35E+04 9.18E+03 6.55E+03 O.OOE+OO 8.62E+03 6.14E+05 3.70E+04 Nb-97 4.29E-01 7.70E-02 3.60E-02 O.OOE+OO 8.55E-02 3.42E+03 2.78E+04 Mo-99 O.OOE+OO 1.72E+02 4.26E+01 O.OOE+OO 3.92E+02 1.35E+05 1.27E+05 Tc-99m 1.78E-03 3.48E-03 5.77E-02 O.OOE+OO 5.07E-02 9.51E+02 4.81E+03 Tc-99 4.96E+02 5.51E+02 1.98E+02 O.OOE+OO 6.48E+03 1.25E+06 2.87E+04 Tc-101 8.10E-05 8.51E-05 1.08E-03 O.OOE+OO 1.45E-03 5.85E+02 1.63E+01 Ru-103 2.79E+03 O.OOE+OO 1.07E+03 O.OOE+OO 7.03E+03 6.62E+05 4.48E+04 Ru-105 1.53E+OO O.OOE+OO 5.55E-01 O.OOE+OO 1.34E+OO 1.59E+04 9.95E+04 Ru-106 1.36E+05 O.OOE+OO 1.69E+04 O.OOE+OO 1.84E+05 1.43E+07 4.29E+05 Rh-105 1.45E+01 7.77E+OO 6.62E+OO O.OOE+OO 3.10E+01 2.89E+04 4.92E+04 Ag-110m 1.69E+04 1.14E+04 9.14E+03 O.OOE+OO 2.12E+04 5.48E+06 1.00E+05 Sn-113 3.56E+04 1.18E+04 7.95E+04 7.67E+03 6.99E+03 5.21E+05 1.12E+05 Sn-117m 4.11E+04 1.78E+03 6.30E+04 1.04E+03 1.06E+03 4.39E+05 9.87E+04 Sb-122 2.60E+03 2.06E+03 3.84E+04 8.63E+02 1.11E+03 1.37E+05 2.33E+05 Sb-124 5.74E+04 7.40E+02 2.00E+04 1.26E+02 O.OOE+OO 3.24E+06 1.64E+05 Sb-125 9.84E+04 7.59E+02 2.07E+04 9.10E+01 O.OOE+OO 2.32E+06 4.03E+04 Te-125m 6.73E+03 2.33E+03 9.14E+02 1.92E+03 O.OOE+OO 4.77E+05 3.38E+04 Te-127m 2.49E+04 8.55E+03 3.03E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 Te-127 2.77E+OO 9.51E-01 6.11E-01 1.96E+OO 7.07E+OO 1.00E+04 5.62E+04 Te-129m 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 Te-129 9.77E-02 3.50E-02 2.38E-02 7.14E-02 2.57E-01 2.93E+03 2.55E+04 Te-131m 1.34E+02 5.92E+01 5.07E+01 9.77E+01 4.00E+02 2.06E+05 3.08E+05 Te-131 2.17E-02 8.44E-03 6.59E-03 1.70E-02 5.88E-02 2.05E+03 1.33E+03 Te-132 4.81E+02 2.72E+02 2.63E+02 3.17E+02 1.77E+03 3.77E+05 1.38E+05 I-130 8.18E+03 1.64E+04 8.44E+03 1.85E+06 2.45E+04 O.OOE+OO 5.11E+03 I-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 O.OOE+OO 2.84E+03 I-132 2.12E+03 4.07E+03 1.88E+03 1.94E+05 6.25E+03 O.OOE+OO 3.20E+03 I-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 O.OOE+OO 5.48E+03 I-134 1.17E+03 2.16E+03 9.95E+02 5.07E+04 3.30E+03 O.OOE+OO 9.55E+02 I-135 4.92E+03 8.73E+03 4.14E+03 7.92E+05 1.34E+04 O.OOE+OO 4.44E+03 Cs-134 6.51E+05 1.01E+06 2.25E+05 O.OOE+OO 3.30E+05 1.21E+05 3.85E+03 Cs-134m 2.34E+02 3.30E+02 2.26E+02 O.OOE+OO 1.83E+02 3.09E+01 2.93E+02 Cs-136 6.51E+04 1.71E+05 1.16E+05 O.OOE+OO 9.55E+04 1.45E+04 4.18E+03 Page 75 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-6 Rio, INHALATION PATHWAY DOSE FACTORS -CHILD NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Cs-137 9.07E+05 8.25E+05 1.28E+05 O.OOE+OO 2.82E+05 1.04E+05 3.62E+03 Cs-138 6.33E+02 8.40E+02 5.55E+02 O.OOE+OO 6.22E+02 6.81E+01 2.70E+02 Ba-139 1.84E+OO 9.84E-04 5.37E-02 O.OOE+OO 8.62E-04 5.77E+03 5.77E+04 Ba-140 7.40E+04 6.48E+01 4.33E+03 O.OOE+OO 2.11E+01 1.74E+06 1.02E+05 Ba-141 1.96E-01 1.09E-04 6.36E-03 O.OOE+OO 9.47E-05 2.92E+03 2.75E+02 Ba-142 5.00E-02 3.60E-05 2.79E-03 O.OOE+OO 2.91E-05 1.64E+03 2.74E+OO La-140 6.44E+02 2.25E+02 7.55E+01 O.OOE+OO O.OOE+OO 1.83E+05 2.26E+05 La-142 1.30E+OO 4.11E-01 1.29E-01 O.OOE+OO O.OOE+OO 8.70E+03 7.59E+04 Ce-141 3.92E+04 1.95E+04 2.90E+03 O.OOE+OO 8.55E+03 5.44E+05 5.66E+04 Ce-143 3.66E+02 1.99E+02 2.87E+01 O.OOE+OO 8.36E+01 1.15E+05 1.27E+05 Ce-144 6.77E+06 2.12E+06 3.61E+05 O.OOE+OO 1.17E+06 1.20E+07 3.89E+05 Pr-143 1.85E+04 5.55E+03 9.14E+02 O.OOE+OO 3.00E+03 4.33E+05 9.73E+04 Pr-144 5.96E-02 1.85E-02 3.00E-03 O.OOE+OO 9.77E-03 1.57E+03 1.97E+02 Nd-147 1.08E+04 8.73E+03 6.81E+02 O.OOE+OO 4.81E+03 3.28E+05 8.21E+04 Eu-152 2.75E+06 5.07E+05 5.96E+05 O.OOE+OO 2.12E+06 3.33E+06 4.22E+04 W-187 1.63E+01 9.66E+OO 4.33E+OO O.OOE+OO O.OOE+OO 4.11E+04 9.10E+04 U-235 1.58E+08 O.OOE+OO 9.58E+06 O.OOE+OO 2.59E+07 6.03E+08 1.84E+05 U-238 1.51E+08 O.OOE+OO 8.95E+06 O.OOE+OO 2.42E+07 5.66E+08 1.30E+05 Np-239 4.66E+02 3.34E+01 2.35E+01 O.OOE+OO 9.73E+01 5.81E+04 6.40E+04 Am-241 6.44E+09 2.90E+09 4.59E+08 O.OOE+OO 2.82E+09 7.47E+08 1.75E+05 Page 76 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-7 Rio, INHALATION PATHWAY DOSE FACTORS -INFANT (mrem/yr per J.LCi/m 3') NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 3.68E+02 3.68E+02 3.69E+02 3.68E+02 3.68E+02 3.68E+02 C-14 2.65E+04 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 F-18 5.49E+03 O.OOE+OO 4.66E+02 O.OOE+OO O.OOE+OO O.OOE+OO 8.54E+02 Na-22 1.03E+05 1.03E+05 1.03E+05 1.03E+05 1.03E+05 1.03E+05 1.03E+05 Na-24 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 Sc-46 5.25E+05 7.57E+05 2.37E+05 O.OOE+OO 4.98E+05 O.OOE+OO 3.07E+04 P-32 2.03E+06 1.12E+05 7.74E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.61E+04 Cr-51 O.OOE+OO O.OOE+OO 8.92E+Ol 5.75E+01 1.32E+01 1.28E+04 3.57E+02 Mn-54 O.OOE+OO 2.53E+04 4.98E+03 O.OOE+OO 4.98E+03 l.OOE+06 7.06E+03 Mn-56 O.OOE+OO 1.54E+OO 2.21E-01 O.OOE+OO 1.10E+OO 1.25E+04 7.17E+04 Fe-55 1.97E+04 1.17E+04 3.33E+03 O.OOE+OO O.OOE+OO 8.69E+04 1.09E+03 Fe-59 1.36E+04 2.35E+04 9.48E+03 O.OOE+OO O.OOE+OO 1.02E+06 2.48E+04 Co-57 O.OOE+OO 6.51E+02 6.41E+02 O.OOE+OO O.OOE+OO 3.79E+05 4.86E+03 Co-58 O.OOE+OO 1.22E+03 1.82E+03 O.OOE+OO O.OOE+OO 7.77E+05 1.11E+04 Co-60 O.OOE+OO 8.02E+03 1.18E+04 O.OOE+OO O.OOE+OO 4.51E+06 3.19E+04 Ni-63 3.39E+05 2.04E+04 1.16E+04 O.OOE+OO O.OOE+OO 2.09E+05 2.42E+03 Ni-65 2.39E+OO 2.84E-01 1.23E-01 O.OOE+OO O.OOE+OO 8.12E+03 5.01E+04 Cu-64 O.OOE+OO 1.88E+OO 7.74E-01 O.OOE+OO 3.98E+OO 9.30E+03 1.50E+04 Zn-65 1.93E+04 6.26E+04 3.11E+04 O.OOE+OO 3.25E+04 6.47E+05 5.14E+04 Zn-69m 1.26E+01 2.58E+01 2.34E+OO O.OOE+OO 1.04E+01 2.67E+04 4.09E+04 Zn-69 5.39E-02 9.67E-02 7.18E-03 O.OOE+OO 4.02E-02 1.47E+03 1.32E+04 As-76 3.58E+03 9.33E+03 2.64E+04 3.58E+03 9.33E+03 7.78E+04 9.85E+04 Br-82 O.OOE+OO O.OOE+OO 1.33E+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO 3.81E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 4.00E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 2.04E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.90E+05 8.82E+04 O.OOE+OO O.OOE+OO O.OOE+OO 3.04E+03 Rb-88 O.OOE+OO 5.57E+02 2.87E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.39E+02 Rb-89 O.OOE+OO 3.21E+02 2.06E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.82E+01 Sr-89 3.98E+05 O.OOE+OO 1.14E+04 O.OOE+OO O.OOE+OO 2.03E+06 6.40E+04 Sr-90 1.55E+07 O.OOE+OO 3.12E+05 O.OOE+OO O.OOE+OO 1.12E+07 1.31E+05 Sr-91 9.56E+01 O.OOE+OO 3.46E+OO O.OOE+OO O.OOE+OO 5.26E+04 7.34E+04 Sr-92 1.05E+01 O.OOE+OO 3.91E-01 O.OOE+OO O.OOE+OO 2.38E+04 1.40E+05 Y-90 3.29E+03 O.OOE+OO 8.82E+Ol O.OOE+OO O.OOE+OO 2.69E+05 1.04E+05 Y-91m 4.07E-01 O.OOE+OO 1.39E-02 O.OOE+OO O.OOE+OO 2.79E+03 2.35E+03 Y-91 5.88E+05 O.OOE+OO 1.57E+04 O.OOE+OO O.OOE+OO 2.45E+06 7.03E+04 Page 77 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-7 Ria, INHALATION PATHWAY DOSE FACTORS- INFANT NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Y-92 1.64E+01 O.OOE+OO 4.61E-01 O.OOE+OO O.OOE+OO 2.45£+04 1.27E+05 Y-93 1.50E+02 O.OOE+OO 4.07E+OO O.OOE+OO O.OOE+OO 7.64£+04 1.67E+05 Zr-95 1.15E+05 2.79E+04 2.03E+04 O.OOE+OO 3.11E+04 1.75E+06 2.17E+04 Zr-97 1.50£+02 2.56E+01 1.17£+01 O.OOE+OO 2.59E+01 1.10E+05 1.40E+05 Nb-95 1.57E+04 6.43E+03 3.78E+03 O.OOE+OO 4.72E+03 4.79E+05 1.27E+04 Nb-97 3.42E-01 7.29£-02 2.63E-02 O.OOE+OO 5.70E-02 3.32£+03 2.69E+04 Mo-99 O.OOE+OO 1.65E+02 3.23£+01 O.OOE+OO 2.65E+02 1.35E+05 4.87E+04 Tc-99m 1.40E-03 2.88E-03 3.72E-02 O.OOE+OO 3.11£-02 8.11E+02 2.03E+03 Tc-99 2.93£+02 3.75E+02 1.24E+02 O.OOE+OO 3.49E+03 9.48E+05 1.09E+04 Tc-101 6.51E-05 8.23E-05 8.12E-04 O.OOE+OO 9.79E-04 5.84E+02 8.44E+02 Ru-103 2.02£+03 O.OOE+OO 6.79E+02 O.OOE+OO 4.24E+03 5.52£+05 1.61£+04 Ru-105 1.22E+OO O.OOE+OO 4.10E-01 O.OOE+OO 8.99£-01 1.57£+04 4.84E+04 Ru-106 8.68E+04 O.OOE+OO 1.09E+04 O.OOE+OO 1.07E+05 1.16E+07 1.64E+05 Rh-105 1.16E+01 7.57E+OO 5.08E+OO O.OOE+OO 2.10E+01 2.91E+04 1.92E+04 Ag-llOm 9.98E+03 7.22E+03 5.00E+03 O.OOE+OO 1.09E+04 3.67E+06 3.30E+04 Sn-113 2.80E+04 9.33E+03 6.74E+04 6.22E+03 6.22E+03 3.99E+05 1.45E+05 Sn-117m 3.27£+04 1.66E+03 5.19E+04 9.85E+02 1.09E+03 3.32E+05 1.35E+05 Sb-122 2.39E+03 2.13E+03 4.30E+04 8.30E+02 1.14E+03 1.14E+05 3.16E+05 Sb-124 3.79E+04 5.56E+02 1.20£+04 1.01E+02 O.OOE+OO 2.65£+06 5.91E+04 Sb-125 5.17E+04 4.77E+02 1.09E+04 6.23E+01 O.OOE+OO 1.64E+06 1.47E+04 Te-l 25m 4.76£+03 1.99E+03 6.58E+02 1.62E+03 O.OOE+OO 4.47E+05 1.29E+04 Te-127m 1.67£+04 6.90E+03 2.07E+03 4.87E+03 3.75E+04 1.31£+06 2.73E+04 Te-127 2.23E+OO 9.53£-01 4.89E-01 1.85E+OO 4.86E+OO 1.03E+04 2.44E+04 Te-129m 1.41E+04 6.09E+03 2.23£+03 5.47£+03 3.18E+04 1.68£+06 6.90E+04 Te-129 7.88E-02 3.47E-02 1.88E-02 6.75E-02 1.75E-01 3.00E+03 2.63E+04 Te-l 31m 1.07E+02 5.50E+01 3.63E+01 8.93E+01 2.65E+02 1.99E+05 1.19E+05 Te-131 1.74E-02 8.22£-03 5.00£-03 1.58£-02 3.99E-02 2.06E+03 8.22E+03 Te-132 3.72E+02 2.37E+02 1.76£+02 2.79E+02 1.03E+03 3.40£+05 4.41E+04 I-130 6.36E+03 1.39E+04 5.57E+03 1.60E+06 1.53E+04 O.OOE+OO 1.99E+03 I-131 3.79E+04 4.44E+04 1.96£+04 1.48E+07 5.18E+04 O.OOE+OO 1.06E+03 I-132 1.69E+03 3.54E+03 1.26£+03 1.69E+05 3.95E+03 O.OOE+OO 1.90E+03 I-133 1.32E+04 1.92E+04 5.60£+03 3.56E+06 2.24E+04 O.OOE+OO 2.16E+03 I-134 9.21E+02 1.88E+03 6.65£+02 4.45E+04 2.09E+03 O.OOE+OO 1.29E+03 I-135 3.86E+03 7.60E+03 2.77£+03 6.96E+05 8.47E+03 O.OOE+OO 1.83E+03 Cs-134 3.96E+05 7.03E+05 7.45E+04 O.OOE+OO 1.90E+05 7.97£+04 1.33E+03 Cs-134m 1.85E+02 2.94E+02 1.55£+02 O.OOE+OO 1.19E+02 2.80E+01 1.62E+02 Cs-136 4.83E+04 1.35E+05 5.29£+04 O.OOE+OO 5.64E+04 1.18E+04 1.43E+03 Page 78 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-7 Rio, INHALATION PATHWAY DOSE FACTORS- INFANT NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Cs-137 5.49E+05 6.12E+05 4.55E+04 O.OOE+OO 1.72E+05 7.13E+04 1.33E+03 Cs-138 5.05E+02 7.81E+02 3.98E+02 O.OOE+OO 4.10E+02 6.54E+01 8.76E+02 Ba-139 1.48E+OO 9.84E-04 4.30E-02 O.OOE+OO 5.92E-04 5.95E+03 5.10E+04 Ba-140 5.60E+04 5.60E+01 2.90E+03 O.OOE+OO 1.34E+01 1.60E+06 3.84E+04 Ba-141 1.57E-01 1.08E-04 4.97E-03 O.OOE+OO 6.50E-05 2.97E+03 4.75E+03 Ba-142 3.98E-02 3.30E-05 1.96E-03 O.OOE+OO 1.90E-05 1.55E+03 6.93E+02 La-140 5.05E+02 2.00E+02 5.15E+01 O.OOE+OO O.OOE+OO 1.68E+05 8.48E+04 La-142 1.03E+OO 3.77E-01 9.04E-02 O.OOE+OO O.OOE+OO 8.22E+03 5.95E+04 Ce-141 2.77E+04 1.67E+04 1.99E+03 O.OOE+OO 5.25E+03 5.17E+05 2.16E+04 Ce-143 2.93E+02 1.93E+02 2.21E+01 O.OOE+OO 5.64E+01 1.16E+05 4.97E+04 Ce-144 3.19E+06 1.21E+06 1.76E+05 O.OOE+OO 5.38E+05 9.84E+06 1.48E+05 Pr-143 1.40E+04 5.24E+03 6.99E+02 O.OOE+OO 1.97E+03 4.33E+05 3.72E+04 Pr-144 4.79E-02 1.85E-02 2.41E-03 O.OOE+OO 6.72E-03 1.61E+03 4.28E+03 Nd-147 7.94E+03 8.13E+03 5.00E+02 O.OOE+OO 3.15E+03 3.22E+05 3.12E+04 Eu-152 1.10E+06 2.48E+05 2.41E+05 O.OOE+OO 8.32E+05 2.07E+06 1.38E+04 W-187 1.30E+01 9.02E+OO 3.12E+OO O.OOE+OO O.OOE+OO 3.96E+04 3.56E+04 U-235 7.01E+07 O.OOE+OO 4.93E+06 O.OOE+OO 1.41E+07 4.59E+08 7.03E+04 U-238 6.71E+07 O.OOE+OO 4.61E+06 O.OOE+OO 1.32E+07 4.28E+08 4.96E+04 Np-239 3.71E+02 3.32E+Ol 1.88E+01 O.OOE+OO 6.62E+01 5.95E+04 2.49E+04 Am-241 2.58E+09 1.18E+09 1.83E+08 O.OOE+OO 1.11E+09 5.68E+08 6.69E+04 Page 79 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-8 Rio, GRASS-COW-MILK PATHWAY DOSE FACTORS -ADULT 3 3 14 {m 2-mrem/yr per J..t.Ci/s (mrem/yr per J!Cilm for Hand C)} NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 6.33E+02 6.33E+02 6.33E+02 6.33E+02 6.33E+02 6.33E+02 C-14 3.63E+05 7.26E+04 7.26E+04 7.26E+04 7.26E+04 7.26E+04 7.26E+04 F-18 1.16E-03 O.OOE+OO 1.28E-04 O.OOE+OO O.OOE+OO O.OOE+OO 3.43E-05 Na-22 4.18E+09 4.18E+09 4.18E+09 4.18E+09 4.18E+09 4.18E+09 4.18E+09 Na-24 6.05E+05 6.05E+05 6.05E+05 6.05E+05 6.05E+05 6.05E+05 6.05E+05 Sc-46 8.96E+01 1.74E+02 5.06E+01 O.OOE+OO 1.62E+02 O.OOE+OO 8.47E+05 P-32 4.34E+09 2.70E+08 1.68E+08 O.OOE+OO O.OOE+OO O.OOE+OO 4.88E+08 Cr-51 O.OOE+OO O.OOE+OO 8.39E+03 5.02E+03 1.85E+03 1.11E+04 2.11E+06 Mn-54 O.OOE+OO 5.80E+06 1.11E+06 O.OOE+OO 1.73E+06 O.OOE+OO 1.78E+07 Mn-56 O.OOE+OO 1.05E-03 1.86E-04 O.OOE+OO 1.33E-03 O.OOE+OO 3.35E-02 Fe-55 1.87E+07 1.29E+07 3.01E+06 O.OOE+OO O.OOE+OO 7.20E+06 7.40E+06 Fe-59 1.11E+07 2.60E+07 9.97E+06 O.OOE+OO O.OOE+OO 7.27E+06 8.67E+07 Co-57 O.OOE+OO 8.59E+05 1.43E+06 O.OOE+OO O.OOE+OO O.OOE+OO 2.18E+07 Co-58 O.OOE+OO 2.20E+06 4.93E+06 O.OOE+OO O.OOE+OO O.OOE+OO 4.46E+07 Co-60 O.OOE+OO 1.27E+07 2.80E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.38E+08 Ni-63 5.68E+09 3.94E+08 1.90E+08 O.OOE+OO O.OOE+OO O.OOE+OO 8.21E+07 Ni-65 9.23E-02 1.20E-02 5.47E-03 O.OOE+OO O.OOE+OO O.OOE+OO 3.04E-01 Cu-64 O.OOE+OO 5.99E+03 2.81E+03 O.OOE+OO 1.51E+04 O.OOE+OO 5.10E+05 Zn-65 1.03E+09 3.26E+09 1.47E+09 O.OOE+OO 2.18E+09 O.OOE+OO 2.05E+09 Zn-69m 4.52E+04 1.08E+05 9.91E+03 O.OOE+OO 6.56E+04 O.OOE+OO 6.62E+06 Zn-69 7.14E-13 1.36E-12 9.49E-14 O.OOE+OO 8.87E-13 O.OOE+OO 2.05E-13 As-76 9.68E+04 2.82E+05 1.41E+06 8.45E+04 3.43E+05 8.80E+04 1.23E+07 Br-82 O.OOE+OO O.OOE+OO 8.19E+06 O.OOE+OO O.OOE+OO O.OOE+OO 9.38E+06 Br-83 O.OOE+OO O.OOE+OO 2.66E-02 O.OOE+OO O.OOE+OO O.OOE+OO 3.83E-02 Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 6.67E+08 3.11E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.32E+08 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 5.78E+08 O.OOE+OO 1.66E+07 O.OOE+OO O.OOE+OO O.OOE+OO 9.27E+07 Sr-90 4.45E+10 O.OOE+OO 8.93E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.52E+09 Sr-91 7.26E+03 O.OOE+OO 2.93E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.46E+04 Sr-92 1.24E-01 O.OOE+OO 5.36E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.45E+OO Y-90 1.77E+01 O.OOE+OO 4.75E-01 O.OOE+OO O.OOE+OO O.OOE+OO 1.88E+05 Y-91m 1.55E-20 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.56E-20 Y-91 3.67E+03 O.OOE+OO 9.82E+01 O.OOE+OO O.OOE+OO O.OOE+OO 2.02E+06 Page 80 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-8 Rio, GRASS-COW-MILK PATHWAY DOSE FACTORS -ADULT NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Y-92 1.41E-05 O.OOE+OO 4.12E-07 O.OOE+OO O.OOE+OO O.OOE+OO 2.47E-01 Y-93 5.85E-02 O.OOE+OO 1.61E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.85E+03 Zr-95 4.21E+02 1.35E+02 9.13E+01 O.OOE+OO 2.12E+02 O.OOE+OO 4.28E+05 Zr-97 1.07E-01 2.15E-02 9.84E-03 O.OOE+OO 3.25E-02 O.OOE+OO 6.67E+03 Nb-95 2.72E+04 1.51E+04 8.12E+03 O.OOE+OO 1.49E+04 O.OOE+OO 9.17E+07 Nb-97 1.64E-12 4.16E-13 1.52E-13 O.OOE+OO 4.85E-13 O.OOE+OO 1.53E-09 Mo-99 O.OOE+OO 6.20E+06 1.18E+06 O.OOE+OO 1.40E+07 O.OOE+OO 1.44E+07 Tc-99m 8.30E-01 2.34E+OO 2.99E+01 O.OOE+OO 3.56E+01 1.15E+OO 1.39E+03 Tc-99 4.26E+07 6.33E+07 1.71E+07 O.OOE+OO 7.97E+08 5.38E+06 2.07E+09 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 3.57E+02 O.OOE+OO 1.54E+02 O.OOE+OO 1.36E+03 O.OOE+OO 4.16E+04 Ru-105 2.16E-04 O.OOE+OO 8.54E-05 O.OOE+OO 2.79E-03 O.OOE+OO 1.32E-01 Ru-106 1.45E+04 O.OOE+OO 1.84E+03 O.OOE+OO 2.81E+04 O.OOE+OO 9.42E+05 Rh-105 1.05E+05 7.70E+04 5.07E+04 O.OOE+OO 3.27E+05 O.OOE+OO 1.23E+07 Ag-llOm 4.05E+07 3.74E+07 2.22E+07 O.OOE+OO 7.36E+07 O.OOE+OO 1.53E+10 Sn-113 9.13E+06 1.54E+06 2.56E+07 8.07E+05 2.11E+06 9.48E+05 2.81E+08 Sn-117m 3.90E+06 1.33E+05 5.54E+06 2.65E+04 2.03E+05 4.21E+04 6.24E+07 Sb-122 1.89E+05 1.04E+05 1.78E+06 2.20E+04 7.34E+04 2.83E+04 1.89E+07 Sb-124 1.12E+07 2.11E+05 4.43E+06 2.71E+04 O.OOE+OO 8.69E+06 3.17E+08 Sb-125 1.54E+07 1.72E+05 3.67E+06 1.57E+04 O.OOE+OO 1.19E+07 1.70E+08 Te-125m 7.74E+06 2.80E+06 1.04E+06 2.33E+06 3.15E+07 O.OOE+OO 3.09E+07 Te-127m 3.02E+07 1.08E+07 3.68E+06 7.71E+06 1.23E+08 O.OOE+OO 1.01E+08 Te-127 1.71E+02 6.15E+01 3.70E+Ol 1.27E+02 6.97E+02 O.OOE+OO 1.35E+04 Te-129m 2.08E+07 7.77E+06 3.30E+06 7.16E+06 8.70E+07 O.OOE+OO 1.05E+08 Te-129 7.44E-11 2.79E-11 1.81E-11 5.71E-11 3.13E-10 O.OOE+OO 5.61E-11 Te-131m 1.07E+05 5.26E+04 4.38E+04 8.32E+04 5.32E+05 O.OOE+OO 5.22E+06 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 6.01E+05 3.89E+05 3.65E+05 4.29E+05 3.74E+06 O.OOE+OO 1.84E+07 I-130 5.27E+04 1.55E+05 6.13E+04 1.32E+07 2.42E+05 O.OOE+OO 1.34E+05 I-131 3.64E+07 5.20E+07 2.98E+07 1.70E+10 8.92E+07 O.OOE+OO 1.37E+07 I-132 1.82E-02 4.88E-02 1.71E-02 1.71E+OO 7.77E-02 O.OOE+OO 9.16E-03 I-133 4.85E+05 4.83E+05 2.57E+05 1.24E+08 1.47E+06 O.OOE+OO 7.58E+05 I-134 2.63E-13 7.16E-13 2.56E-13 1.24E-11 1.14E-12 O.OOE+OO 6.24E-16 I-135 1.56E+03 4.07E+03 1.50E+03 2.69E+05 6.53E+03 O.OOE+OO 4.60E+03 Cs-134 4.19E+09 9.97E+09 8.15E+09 O.OOE+OO 3.23E+09 1.07E+09 1.74E+08 Cs-134m 4.40E-02 9.25E-02 4.73E-02 O.OOE+OO 5.02E-02 7.91E-03 3.26E-02 Cs-136 6.44E+07 2.54E+08 1.83E+08 O.OOE+OO 1.42E+08 1.94E+07 2.89E+07 Page 81 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-8 Ria, GRASS-COW -MILK PATHWAY DOSE FACTORS -ADULT NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Cs-137 5.94E+09 8.12E+09 5.32E+09 O.OOE+OO 2.76E+09 9.16E+08 1.57E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 1.38E-08 9.86E-12 4.05E-10 O.OOE+OO 9.21E-12 5.89E-12 2.45E-08 Ba-140 6.56E+06 8.23E+03 4.30E+05 O.OOE+OO 2.80E+03 4.71E+03 1.35E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 l.llE+OO 5.70E-01 1.51E-01 O.OOE+OO O.OOE+OO O.OOE+OO 4.19E+04 La-142 2.34E-12 1.06E-12 2.65E-13 O.OOE+OO O.OOE+OO O.OOE+OO 7.76E-09 Ce-141 1.54E+03 1.04E+03 1.18E+02 O.OOE+OO 4.83E+02 O.OOE+OO 3.97E+06 Ce-143 1.04E+01 7.71E+03 8.54E-01 O.OOE+OO 3.40E+OO O.OOE+OO 2.88E+05 Ce-144 2.41E+05 1.01E+05 1.29E+04 O.OOE+OO 5.98E+04 O.OOE+OO 8.15E+07 Pr-143 3.87E+01 1.55E+01 1.92E+OO O.OOE+OO 8.96E+OO O.OOE+OO 1.70E+05 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 2.30E+01 2.66E+01 1.59E+OO O.OOE+OO 1.55E+01 O.OOE+OO 1.27E+05 Eu-152 5.87E+03 1.32E+03 1.16E+03 O.OOE+OO 8.20E+03 O.OOE+OO 7.63E+05 W-187 1.64E+03 1.37E+03 4.80E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.50E+05 U-235 2.43E+09 O.OOE+OO 1.47E+08 O.OOE+OO 5.66E+08 O.OOE+OO 2.36E+08 U-238 2.32E+09 O.OOE+OO 1.37E+08 O.OOE+OO 5.30E+08 O.OOE+OO 1.67E+08 Np-239 9.19E-01 9.03E-02 4.98E-02 O.OOE+OO 2.82E-01 O.OOE+OO 1.85E+04 Am-241 2.45E+07 8.62E+06 1.62E+06 O.OOE+OO 1.22E+07 O.OOE+OO 2.22E+06 Page 82 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-9 Ria, GRASS-COW-MILK PATHWAY DOSE FACTORS- TEEN 3 3 14 {m 2-mrem/yr per J..tCi/s (mrem/yr per 11Cilm for Hand C)} NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 8.23E+02 8.23E+03 8.23E+03 8.23E+03 8.23E+03 8.23E+03 C-14 6.70E+05 1.34E+05 1.34E+05 1.34E+05 1.34E+05 1.34E+05 1.34E+05 F-18 2.07E-03 O.OOE+OO 2.26E-04 O.OOE+OO O.OOE+OO O.OOE+OO 1.86E-04 Na-22 7.26E+09 7.26E+09 7.26E+09 7.26E+09 7.26E+09 7.26E+09 7.26E+09 Na-24 1.06E+06 1.06E+06 1.06E+06 1.06E+06 1.06E+06 1.06E+06 1.06E+06 Sc-46 1.52E+02 2.96E+02 8.77E+01 O.OOE+OO 2.83E+02 O.OOE+OO 1.01E+06 P-32 8.02E+09 4.97E+08 3.11E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.74E+08 Cr-51 O.OOE+OO O.OOE+OO 1.47E+04 8.14E+03 3.21E+03 2.09E+04 2.46E+06 Mn-54 O.OOE+OO 9.67E+06 1.92E+06 O.OOE+OO 2.88E+06 O.OOE+OO 1.98E+07 Mn-56 O.OOE+OO 1.86E-03 3.31E-04 O.OOE+OO 2.36E-03 O.OOE+OO 1.23E-01 Fe-55 3.31E+07 2.35E+07 5.48E+06 O.OOE+OO O.OOE+OO 1.49E+07 1.02E+07 Fe-59 1.93E+07 4.51E+07 1.74E+07 O.OOE+OO O.OOE+OO 1.42E+07 1.07E+08 Co-57 O.OOE+OO 1.51E+06 2.53E+06 O.OOE+OO O.OOE+OO O.OOE+OO 2.81E+07 Co-58 O.OOE+OO 3.71E+06 8.54E+06 O.OOE+OO O.OOE+OO O.OOE+OO 5.11E+07 Co-60 O.OOE+OO 2.15E+07 4.84E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.80E+08 Ni-63 9.98E+09 7.05E+08 3.38E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.12E+08 Ni-65 1.69E-01 2.16E-02 9.84E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.17E+OO Cu-64 O.OOE+OO 1.07E+04 5.02E+03 O.OOE+OO 2.70E+04 O.OOE+OO 8.27E+05 Zn-65 1.57E+09 5.47E+09 2.55E+09 O.OOE+OO 3.50E+09 O.OOE+OO 2.31E+09 Zn-69m 8.23E+04 1.94E+05 1.78E+04 O.OOE+OO 1.18E+05 O.OOE+OO 1.07E+07 Zn-69 9.70E-13 1.85E-12 1.29E-13 O.OOE+OO 1.21E-12 O.OOE+OO 3.41E-12 As-76 1.48E+05 4.65E+05 2.27E+06 1.36E+05 5.45E+05 1.36E+05 2.04E+07 Br-82 O.OOE+OO O.OOE+OO 1.42E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO 4.89E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.22E+09 5.71E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.80E+08 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 1.07E+09 O.OOE+OO 3.05E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.27E+08 Sr-90 6.72E+10 O.OOE+OO 1.34E+09 O.OOE+OO O.OOE+OO O.OOE+OO 2.08E+09 Sr-91 1.33E+04 O.OOE+OO 5.31E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.05E+04 Sr-92 2.27E-01 O.OOE+OO 9.66E-03 O.OOE+OO O.OOE+OO O.OOE+OO 5.78E+OO Y-90 3.25E+01 O.OOE+OO 8.77E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.68E+05 Y-91m 2.85E-20 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.34E-18 Y-91 6.76E+03 O.OOE+OO 1.81E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.77E+06 Y-92 2.61E-05 O.OOE+OO 7.54E-07 O.OOE+OO O.OOE+OO O.OOE+OO 7.15E-01 Page 83 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-9 Rio, GRASS-COW-MILK PATHWAY DOSE FACTORS -TEEN NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Y-93 1.08E-01 O.OOE+OO 2.96E-03 O.OOE+OO O.OOE+OO O.OOE+OO 3.29E+03 Zr-95 7.35E+02 2.32E+02 1.60E+02 O.OOE+OO 3.41E+02 O.OOE+OO 5.36E+05 Zr-97 1.94E-01 3.84E-02 1.77E-02 O.OOE+OO 5.82E-02 O.OOE+OO 1.04E+04 Nb-95 4.63E+04 2.57E+04 1.41E+04 O.OOE+OO 2.49E+04 O.OOE+OO 1.10E+08 Nb-97 3.00E-12 7.44E-13 2.72E-13 O.OOE+OO 8.70E-13 O.OOE+OO 1.78E-08 Mo-99 O.OOE+OO 1.12E+07 2.13E+06 O.OOE+OO 2.56E+07 O.OOE+OO 2.00E+07 Tc-99m 1.44E+OO 4.01E+OO 5.20E+01 O.OOE+OO 5.98E+01 2.23E+OO 2.63E+03 Tc-99 7.87E+07 1.16E+08 3.15E+07 O.OOE+OO 1.47E+09 1.20E+07 2.83E+09 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 6.34E+02 O.OOE+OO 2.71E+02 O.OOE+OO 2.24E+03 O.OOE+OO 5.30E+04 Ru-105 3.95E-04 O.OOE+OO 1.53E-04 O.OOE+OO 4.98E-03 O.OOE+OO 3.19E-01 Ru-106 2.68E+04 O.OOE+OO 3.37E+03 O.OOE+OO 5.16E+04 O.OOE+OO 1.28E+06 Rh-105 1.94E+05 1.40E+05 9.21E+04 O.OOE+OO 5.96E+05 O.OOE+OO 1.79E+07 Ag-llOm 6.69E+07 6.33E+07 3.85E+07 O.OOE+OO 1.21E+08 O.OOE+OO 1.78E+10 Sn-113 1.27E+07 2.54E+06 4.17E+07 1.22E+06 3.31E+06 1.49E+06 4.48E+08 Sn-117m 5.13E+06 2.21E+05 8.86E+06 4.13E+04 3.12E+05 7.55E+04 9.97E+07 Sb-122 2.57E+05 1.76E+05 2.84E+06 3.52E+04 1.15E+05 4.74E+04 2.98E+07 Sb-124 1.99E+07 3.67E+05 7.77E+06 4.52E+04 O.OOE+OO 1.74E+07 4.01E+08 Sb-125 2.76E+07 3.01E+05 6.44E+06 2.63E+04 O.OOE+OO 2.42E+07 2.14E+08 Te-125m 1.43E+07 5.14E+06 1.91E+06 3.99E+06 O.OOE+OO O.OOE+OO 4.21E+07 Te-127m 5.56E+07 1.97E+07 6.62E+06 1.32E+07 2.26E+08 O.OOE+OO 1.39E+08 Te-127 3.17E+02 1.12E+02 6.83E+01 2.19E+02 1.29E+03 O.OOE+OO 2.45E+04 Te-129m 3.81E+07 1.41E+07 6.03E+06 1.23E+07 1.59E+08 O.OOE+OO 1.43E+08 Te-129 1.37E-10 5.10E-11 3.33E-11 9.78E-11 5.74E-10 O.OOE+OO 7.49E-10 Te-131m 1.96E+05 9.38E+04 7.82E+04 1.41E+05 9.78E+05 O.OOE+OO 7.53E+06 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 1.07E+06 6.80E+05 6.40E+05 7.17E+05 6.52E+06 O.OOE+OO 2.15E+07 I-130 9.26E+04 2.68E+05 1.07E+05 2.18E+07 4.13E+05 O.OOE+OO 2.06E+05 I-131 6.60E+07 9.24E+07 4.96E+07 2.70E+10 1.59E+08 O.OOE+OO 1.83E+07 I-132 3.23E-02 8.46E-02 3.04E-02 2.85E+OO 1.33E-01 O.OOE+OO 3.69E-02 I-133 8.85E+05 1.50E+06 4.58E+05 2.10E+08 2.63E+06 O.OOE+OO 1.14E+06 I-134 4.68E-13 1.24E-12 4.46E-13 2.17E-11 1.96E-12 O.OOE+OO 1.64E-14 I-135 2.76E+03 7.12E+03 2.64E+03 4.58E+05 1.12E+04 O.OOE+OO 7.89E+03 Cs-134 7.27E+09 1.71E+10 7.94E+09 O.OOE+OO 5.44E+09 2.08E+09 2.13E+08 Cs-134m 7.84E-02 1.62E-01 8.34E-02 O.OOE+OO 9.03E-02 1.59E-02 1.08E-01 Cs-136 1.10E+08 4.32E+08 2.90E+08 O.OOE+OO 2.35E+08 3.70E+07 3.47E+07 Cs-137 1.08E+10 1.43E+10 4.99E+09 O.OOE+OO 4.87E+09 1.89E+09 2.04E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 84 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-9 Rio, GRASS-COW-MILK PATHWAY DOSE FACTORS -TEEN NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Ba-139 2.56E-08 1.80E-11 7.45E-10 O.OOE+OO 1.70E-11 1.24E-11 2.28E-07 Ba-140 1.18E+07 1.45E+04 7.63E+05 O.OOE+OO 4.92E+03 9.75E+03 1.83E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 2.03E+OO 9.99E-01 2.66E-01 O.OOE+OO O.OOE+OO O.OOE+OO 5.73E+04 La-142 4.22E-12 1.87E-12 4.66E-13 O.OOE+OO O.OOE+OO O.OOE+OO 5.70E-08 Ce-141 2.82E+03 1.88E+03 2.16E+02 O.OOE+OO 8.85E+02 O.OOE+OO 5.38E+06 Ce-143 1.92E+01 1.40E+04 1.56E+OO O.OOE+OO 6.26E+OO O.OOE+OO 4.19E+05 Ce-144 4.43E+05 1.84E+05 2.38E+04 O.OOE+OO 1.10E+05 O.OOE+OO 1.12E+08 Pr-143 7.11E+01 2.84E+01 3.54E+OO O.OOE+OO 1.65E+01 O.OOE+OO 2.34E+05 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 4.42E+01 4.81E+01 2.88E+OO O.OOE+OO 2.82E+01 O.OOE+OO 1.73E+05 Eu-152 9.42E+03 2.27E+03 2.00E+03 O.OOE+OO 1.05E+04 O.OOE+OO 8.35E+05 W-187 3.00E+03 2.45E+03 8.58E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.63E+05 U-235 4.45E+09 O.OOE+OO 2.71E+08 O.OOE+OO 1.04E+09 O.OOE+OO 3.23E+08 U-238 4.26E+09 O.OOE+OO 2.54E+08 O.OOE+OO 9.77E+08 O.OOE+OO 2.28E+08 Np-239 1.75E+OO 1.65E-01 9.19E-02 O.OOE+OO 5.19E-01 O.OOE+OO 2.66E+04 Am-241 3.33E+07 1.27E+07 2.22E+06 O.OOE+OO 1.66E+07 O.OOE+OO 3.04E+06 Page 85 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-10 Ria, GRASS-COW-MILK PATHWAY DOSE FACTORS -CHILD {m 2-mrem/yr per J..LCi/s (mrem/yr per ~tCi/m 3 for 3Hand 14 C)} NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 1.30E+03 1.30E+03 1.30E+03 1.30E+03 1.30E+03 1.30E+03 C-14 1.65E+06 3.29E+05 3.29E+05 3.29E+05 3.29E+05 3.29E+05 3.29E+05 F-18 4.91E-03 O.OOE+OO 4.87E-04 O.OOE+OO O.OOE+OO O.OOE+OO 1.33E-03 Na-22 1.50E+10 1.50E+10 1.50E+10 1.50E+10 1.50E+10 1.50E+10 1.50E+10 Na-24 2.20E+06 2.20E+06 2.20E+06 2.20E+06 2.20E+06 2.20E+06 2.20E+06 Sc-46 3.41E+02 4.67E+02 1.80E+02 O.OOE+OO 4.14E+02 O.OOE+OO 6.84E+05 P-32 1.98E+10 9.25E+08 7.62E+08 O.OOE+OO O.OOE+OO O.OOE+OO 5.46E+08 Cr-51 O.OOE+OO O.OOE+OO 2.99E+04 1.66E+04 4.54E+03 3.03E+04 1.59E+06 Mn-54 O.OOE+OO 1.45E+07 3.85E+06 O.OOE+OO 4.05E+06 O.OOE+OO 1.21E+07 Mn-56 O.OOE+OO 3.25E-03 7.33E-04 O.OOE+OO 3.93E-03 O.OOE+OO 4.71E-01 Fe-55 8.31E+07 4.41E+07 1.37E+07 O.OOE+OO O.OOE+OO 2.49E+07 8.17E+06 Fe-59 4.48E+07 7.25E+07 3.61E+07 O.OOE+OO O.OOE+OO 2.10E+07 7.55E+07 Co-57 O.OOE+OO 2.58E+06 5.21E+06 O.OOE+OO O.OOE+OO O.OOE+OO 2.11E+07 Co-58 O.OOE+OO 5.66E+06 1.73E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.30E+07 Co-60 O.OOE+OO 3.34E+07 9.85E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.85E+08 Ni-63 2.50E+10 1.34E+09 8.51E+08 O.OOE+OO O.OOE+OO O.OOE+OO 9.02E+07 Ni-65 4.13E-01 3.89E-02 2.27E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.77E+OO Cu-64 O.OOE+OO 1.87E+04 1.13E+04 O.OOE+OO 4.53E+04 O.OOE+OO 8.80E+05 Zn-65 3.09E+09 8.23E+09 5.12E+09 O.OOE+OO 5.19E+09 O.OOE+OO 1.45E+09 Zn-69m 2.01E+05 3.42E+05 4.05E+04 O.OOE+OO 1.99E+05 O.OOE+OO 1.11E+07 Zn-69 3.23E-12 4.67E-12 4.31E-13 O.OOE+OO 2.83E-12 O.OOE+OO 2.94E-10 As-76 3.37E+05 9.37E+05 5.43E+06 3.18E+05 1.03E+06 3.18E+05 4.87E+07 Br-82 O.OOE+OO O.OOE+OO 2.91E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO 1.20E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.26E+09 1.39E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.45E+08 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 2.64E+09 O.OOE+OO 7.53E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E+08 Sr-90 1.39E+11 O.OOE+OO 2.80E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.24E+09 Sr-91 3.27E+04 O.OOE+OO 1.24E+03 O.OOE+OO O.OOE+OO O.OOE+OO 7.23E+04 Sr-92 5.54E-01 O.OOE+OO 2.22E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.05E+01 Y-90 8.06E+01 O.OOE+OO 2.16E+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.29E+05 Y-91m 6.95E-20 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.36E-16 Y-91 1.67E+04 O.OOE+OO 4.46E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.22E+06 Y-92 6.40E-05 O.OOE+OO 1.83E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.85E+OO Page 86 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-10 Ria, GRASS-COW-MILK PATHWAY DOSE FACTORS -CHILD NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Y-93 2.65E-01 O.OOE+OO 7.27E-03 O.OOE+OO O.OOE+OO O.OOE+OO 3.95E+03 Zr-95 1.71E+03 3.76E+02 3.34E+02 O.OOE+OO 5.38E+02 O.OOE+OO 3.92E+05 Zr-97 4.72E-01 6.83E-02 4.03E-02 O.OOE+OO 9.80E-02 O.OOE+OO 1.03E+04 Nb-95 1.05E+05 4.07E+04 2.91E+04 O.OOE+OO 3.82E+04 O.OOE+OO 7.53E+07 Nb-97 7.28E-12 1.31E-12 6.14E-13 O.OOE+OO 1.46E-12 O.OOE+OO 4.06E-07 Mo-99 O.OOE+OO 2.04E+07 5.04E+06 O.OOE+OO 4.35E+07 O.OOE+OO 1.68E+07 Tc-99m 3.30E+OO 6.47E+OO 1.07E+02 O.OOE+OO 9.40E+01 3.29E+OO 3.68E+03 Tc-99 1.94E+08 2.16E+08 7.76E+07 O.OOE+OO 2.54E+09 1.91E+07 2.27E+09 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 1.50E+03 O.OOE+OO 5.77E+02 O.OOE+OO 3.78E+03 O.OOE+OO 3.88E+04 Ru-105 9.64E-04 O.OOE+OO 3.50E-04 O.OOE+OO 8.47E-03 O.OOE+OO 6.29E-01 Ru-106 6.59E+04 O.OOE+OO 8.22E+03 O.OOE+OO 8.90E+04 O.OOE+OO 1.02E+06 Rh-105 4.76E+05 2.56E+05 2.19E+05 O.OOE+OO 1.02E+06 O.OOE+OO 1.58E+07 Ag-llOm 1.45E+08 9.80E+07 7.83E+07 O.OOE+OO 1.83E+08 O.OOE+OO 1.17E+ 10 Sn-113 2.95E+07 6.35E+06 9.71E+07 2.54E+06 6.73E+06 3.18E+06 1.08E+09 Sn-117m 1.33E+07 6.31E+05 2.08E+07 9.97E+04 6.40E+05 1.83E+05 2.41E+08 Sb-122 6.14E+05 3.69E+05 6.81E+06 8.04E+04 2.23E+05 1.05E+05 7.37E+07 Sb-124 4.71E+07 6.11E+05 1.65E+07 1.04E+05 O.OOE+OO 2.61E+07 2.95E+08 Sb-125 6.56E+07 5.06E+05 1.37E+07 6.08E+04 O.OOE+OO 3.66E+07 1.57E+08 Te-125m 3.51E+07 9.50E+06 4.67E+06 9.84E+06 O.OOE+OO O.OOE+OO 3.38E+07 Te-127m 1.37E+08 3.69E+07 1.63E+07 3.28E+07 3.91E+08 O.OOE+OO 1.11E+08 Te-127 7.80E+02 2.10E+02 1.67E+02 5.40E+02 2.22E+03 O.OOE+OO 3.05E+04 Te-129m 9.39E+07 2.62E+07 1.46E+07 3.03E+07 2.76E+08 O.OOE+OO 1.15E+08 Te-129 3.38E-10 9.43E-11 8.02E-11 2.41E-10 9.88E-10 O.OOE+OO 2.10E-08 Te-131m 4.76E+05 1.65E+05 1.75E+05 3.39E+05 1.59E+06 O.OOE+OO 6.68E+06 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 2.56E+06 1.13E+06 1.37E+06 1.65E+06 1.05E+07 O.OOE+OO 1.14E+07 I-130 2.17E+05 4.38E+05 2.25E+05 4.82E+07 6.564E+05 O.OOE+OO 2.05E+05 I-131 1.60E+08 1.61E+08 9.15E+07 5.32E+10 2.64E+08 O.OOE+OO 1.43E+07 I-132 7.65E-02 1.41E-01 6.46E-02 6.52E+OO 2.15E-01 O.OOE+OO 1.65E-01 I-133 2.15E+06 2.66E+06 1.01E+06 4.94E+08 4.43E+06 O.OOE+OO 1.07E+06 I-134 l.llE-12 2.06E-12 9.47E-13 4.73E-11 3.15E-12 O.OOE+OO 1.36E-12 I-135 6.54E+03 1.18E+04 5.57E+03 1.04E+06 1.81E+04 O.OOE+OO 8.97E+03 Cs-134 1.68E+10 2.75E+10 5.81E+09 O.OOE+OO 8.53E+09 3.06E+09 1.48E+08 Cs-134m 1.86E-01 2.75E-01 1.79E-01 O.OOE+OO 1.45E-01 2.39E-02 3.47E-01 Cs-136 2.48E+08 6.80E+08 4.40E+08 O.OOE+OO 3.62E+08 5.40E+07 2.39E+07 Cs-137 2.59E+10 2.48E+10 3.66E+09 O.OOE+OO 8.09E+09 2.91E+09 1.55E+08 Page 87 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-10 Rio, GRASS-COW-MILK PATHWAY DOSE FACTORS - CHILD NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI~LLI Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 6.29E-08 3.36E-11 1.82E-09 O.OOE+OO 2.93E-11 1.97E-11 3.63E-06 Ba-140 2.86E+07 2.50E+04 1.67E+06 O.OOE+OO 8.15E+03 1.49E+04 1.45E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 4.87E+OO 1.70E+OO 5.73E-01 O.OOE+OO O.OOE+OO O.OOE+OO 4.74E+04 La-142 1.02E-11 3.25E-12 1.02E-12 O.OOE+OO O.OOE+OO O.OOE+OO 6.43E-07 Ce-141 6.94E+03 3.46E+03 5.14E+02 O.OOE+OO 1.52E+03 O.OOE+OO 4.32E+06 Ce-143 4.70E+01 2.55E+04 3.69E+OO O.OOE+OO 1.07E+01 O.OOE+OO 3.74E+05 Ce-144 1.09E+06 3.43E+05 5.84E+04 O.OOE+OO 1.90E+05 O.OOE+OO 8.94E+07 Pr-143 1.76E+02 5.28E+01 8.73E+OO O.OOE+OO 2.86E+01 O.OOE+OO 1.90E+05 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 1.08E+02 8.79E+01 6.80E+OO O.OOE+OO 4.82E+01 O.OOE+OO 1.39E+05 Eu-152 1.95E+04 3.55E+03 4.22E+03 O.OOE+OO 1.50E+04 O.OOE+OO 5.84E+05 W-187 7.28E+03 4.31E+03 1.94E+03 O.OOE+OO O.OOE+OO O.OOE+OO 6.06E+05 U-235 1.10E+10 O.OOE+OO 6.67E+08 O.OOE+OO 1.81E+09 O.OOE+OO 2.59E+08 U-238 1.05E+10 O.OOE+OO 6.25E+08 O.OOE+OO 1.69E+09 O.OOE+OO 1.82E+08 Np-239 4.32E+OO 3.10E-01 2.18E-01 O.OOE+OO 8.96E-01 O.OOE+OO 2.29E+04 Am-241 4.55E+07 2.04E+07 3.25E+06 O.OOE+OO 1.98E+07 O.OOE+OO 2.43E+06 Page 88 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-11 Rio, GRASS-COW-MILK PATHWAY DOSE FACTORS- INFANT {m 2-mrem/yr per J.(.Ci/s (mrem/yr per J.tCi/m3 for 3Hand 14 C)} NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 1.98E+03 1.98E+03 1.98E+03 1.98E+03 1.98E+03 1.98E+03 C-14 3.23E+06 6.89E+05 6.89E+05 6.89E+05 6.89E+05 6.89E+05 6.89E+05 F-18 1.02E-02 O.OOE+OO 8.74E-04 O.OOE+OO O.OOE+OO O.OOE+OO 2.41E-03 Na-22 2.52E+10 2.52E+10 2.52E+10 2.52E+10 2.52E+10 2.52E+10 2.52E+10 Na-24 3.83E+06 3.83E+06 3.83E+06 3.83E+06 3.83E+06 3.83E+06 3.83E+06 Sc-46 6.49E+02 9.36E+02 2.93E+02 O.OOE+OO 6.16E+02 O.OOE+OO 6.11E+05 P-32 4.07E+10 2.40E+09 1.58E+09 O.OOE+OO O.OOE+OO O.OOE+OO 5.51E+08 Cr-51 O.OOE+OO O.OOE+OO 4.74E+04 3.09E+04 6.75E+03 6.01E+04 1.38E+06 Mn-54 O.OOE+OO 2.69E+07 6.10E+06 O.OOE+OO 5.96E+06 O.OOE+OO 9.88E+06 Mn-56 O.OOE+OO 7.96E-03 1.37E-03 O.OOE+OO 6.84E-03 O.OOE+OO 7.23E-01 Fe-55 1.00E+08 6.49E+07 1.73E+07 O.OOE+OO O.OOE+OO 3.17E+07 8.24E+06 Fe-59 8.36E+07 1.46E+08 5.76E+07 O.OOE+OO O.OOE+OO 4.32E+07 6.98E+07 Co-57 O.OOE+OO 6.01E+06 9.77E+06 O.OOE+OO O.OOE+OO O.OOE+OO 2.05E+07 Co-58 O.OOE+OO 1.13E+07 2.82E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.82E+07 Co-60 O.OOE+OO 6.82E+07 1.61E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.62E+08 Ni-63 2.95E+10 1.82E+09 1.02E+09 O.OOE+OO O.OOE+OO O.OOE+OO 9.07E+07 Ni-65 8.75E-01 9.90E-02 4.51E-02 O.OOE+OO O.OOE+OO O.OOE+OO 7.54E+OO Cu-64 O.OOE+OO 4.66E+04 2.16E+04 O.OOE+OO 7.88E+04 O.OOE+OO 9.57E+05 Zn-65 4.15E+09 1.42E+10 6.56E+09 O.OOE+OO 6.90E+09 O.OOE+OO 1.20E+ 10 Zn-69m 4.24E+05 8.66E+05 7.89E+04 O.OOE+OO 3.51E+05 O.OOE+OO 1.20E+07 Zn-69 6.88E-12 1.24E-11 9.22E-13 O.OOE+OO 5.15E-12 O.OOE+OO 1.01E-09 As-76 2.06E+06 5.43E+06 9.37E+06 2.06E+06 5.71E+06 2.06E+06 5.99E+07 Br-82 O.OOE+OO O.OOE+OO 4.90E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO 2.55E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 5.72E+09 2.83E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.46E+08 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 5.02E+09 O.OOE+OO 1.44E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.03E+08 Sr-90 1.54E+11 O.OOE+OO 3.12E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.26E+09 Sr-91 6.82E+04 O.OOE+OO 2.47E+03 O.OOE+OO O.OOE+OO O.OOE+OO 8.07E+04 Sr-92 1.18E+OO O.OOE+OO 4.37E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.27E+01 Y-90 1.70E+02 O.OOE+OO 4.57E+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.35E+05 Y-91m 1.47E-19 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.91E-16 Y-91 3.13E+04 O.OOE+OO 8.35E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.25E+06 Y-92 1.36E-04 O.OOE+OO 3.82E-06 O.OOE+OO O.OOE+OO O.OOE+OO 2.59E+OO Page 89 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-11 Rio, GRASS-COW-MILK PATHWAY DOSE FACTORS- INFANT NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Y-93 5.64E-01 O.OOE+OO 1.54E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.46E+03 Zr-95 3.03E+03 7.39E+02 5.24E+02 O.OOE+OO 7.97E+02 O.OOE+OO 3.68E+05 Zr-97 1.00E+OO 1.72E-01 7.84E-02 O.OOE+OO 1.73E-01 O.OOE+OO 1.09E+04 Nb-95 1.95E+05 8.04E+04 4.65E+04 O.OOE+OO 5.76E+04 O.OOE+OO 6.79E+07 Nb-97 1.54E-11 3.28E-12 1.18E-12 O.OOE+OO 2.57E-12 O.OOE+OO 1.04E-06 Mo-99 O.OOE+OO 5.21E+07 1.02E+07 O.OOE+OO 7.78E+07 O.OOE+OO 1.71E+07 Tc-99m 6.86E+OO 1.42E+01 1.82E+02 O.OOE+OO 1.52E+02 7.32E+OO 4.11E+03 Tc-99 3.92E+08 5.29E+08 1.65E+08 O.OOE+OO 4.46E+09 5.15E+07 2.29E+09 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 3.04E+03 O.OOE+OO 1.02E+03 O.OOE+OO 6.32E+03 O.OOE+OO 3.69E+04 Ru-105 2.03E-03 O.OOE+OO 6.84E-04 O.OOE+OO 1.49E-02 O.OOE+OO 8.08E-01 Ru-106 1.36E+05 O.OOE+OO 1.70E+04 O.OOE+OO 1.60E+05 O.OOE+OO 1.03E+06 Rh-105 1.01E+06 6.61E+05 4.44E+05 O.OOE+OO 1.83E+06 O.OOE+OO 1.64E+07 Ag-llOm 2.68E+08 1.96E+08 1.29E+08 O.OOE+OO 2.80E+08 O.OOE+OO 1.01E+10 Sn-113 1.08E+08 2.17E+07 2.91E+08 1.16E+07 2.17E+07 1.46E+07 3.21E+09 Sn-117m 4.73E+07 1.91E+06 6.40E+07 5.40E+05 1.66E+06 7.81E+05 7.31E+08 Sb-122 2.35E+06 1.56E+06 2.01E+07 4.69E+05 7.48E+05 5.36E+05 2.12E+08 Sb-124 9.08E+07 1.34E+06 2.81E+07 2.41E+05 O.OOE+OO 5.69E+07 2.80E+08 Sb-125 1.13E+08 1.09E+06 2.32E+07 1.41E+05 O.OOE+OO 7.08E+07 1.50E+08 Te-125m 7.16E+07 2.40E+07 9.69E+06 2.41E+07 O.OOE+OO O.OOE+OO 3.41E+07 Te-127m 2.78E+08 9.21E+07 3.36E+07 8.02E+07 6.84E+08 O.OOE+OO 1.12E+08 Te-127 1.66E+03 5.55E+02 3.56E+02 1.35E+03 4.04E+03 O.OOE+OO 3.48E+04 Te-129m 1.93E+08 6.61E+07 2.97E+07 7.41E+07 4.82E+08 O.OOE+OO 1.15E+08 Te-129 7.16E-10 2.47E-10 1.67E-10 6.00E-10 1.78E-09 O.OOE+OO 5.72E-08 Te-131m 1.01E+06 4.05E+05 3.34E+05 8.20E+05 2.78E+06 O.OOE+OO 6.81E+06 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 5.28E+06 2.61E+06 2.44E+06 3.86E+06 1.63E+07 O.OOE+OO 9.67E+06 I-130 4.45E+05 9.79E+05 3.93E+05 1.10E+08 1.08E+06 O.OOE+OO 2.10E+05 I-131 3.34E+08 3.94E+08 1.73E+08 1.29E+ 11 4.60E+08 O.OOE+OO 1.41E+07 I-132 1.59E-01 3.22E-01 1.15E-01 1.51E+01 3.59E-01 O.OOE+OO 2.61E-01 I-133 4.54E+06 6.61E+06 1.94E+06 1.20E+09 7.77E+06 O.OOE+OO 1.12E+06 I-134 2.30E-12 4.71E-12 1.67E-12 1.10E-10 5.26E-10 O.OOE+OO 4.87E-12 I-135 1.36E+04 2.71E+04 9.87E+03 2.43E+06 3.02E+04 O.OOE+OO 9.80E+03 Cs-134 2.70E+10 5.04E+10 5.09E+09 O.OOE+OO 1.30E+10 5.32E+09 1.37E+08 Cs-134m 3.87E-01 6.44E-01 3.25E-01 O.OOE+OO 2.48E-01 5.72E-02 5.10E-01 Cs-136 4.84E+08 1.42E+09 5.31E+08 O.OOE+OO 5.67E+08 1.16E+08 2.16E+07 Cs-137 4.14E+10 4.84E+10 3.43E+09 O.OOE+OO 1.30E+10 5.26E+09 1.51E+08 Page 90 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-11 Ria, GRASS-COW-MILK PATHWAY DOSE FACTORS- INFANT NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 1.34E-07 8.87E-ll 3.87E-09 O.OOE+OO 5.33E-11 5.38E-11 8.474E-06 Ba-140 5.88E+07 5.88E+04 3.03E+06 O.OOE+OO 1.40E+04 3.61E+04 1.44E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 1.02E+01 4.01E+OO 1.03E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.71E+04 La-142 2.14E-11 7.85E-12 1.88E-12 O.OOE+OO O.OOE+OO O.OOE+OO 1.33E-06 Ce-141 1.38E+04 8.39E+03 9.87E+02 O.OOE+OO 2.59E+03 O.OOE+OO 4.33E+06 Ce-143 9.96E+01 6.61E+04 7.54E+OO O.OOE+OO 1.92E+01 O.OOE+OO 3.86E+05 Ce-144 1.57E+06 6.41E+05 8.78E+04 O.OOE+OO 2.59E+05 O.OOE+OO 8.99E+07 Pr-143 3.64E+02 1.36E+02 1.80E+01 O.OOE+OO 5.06E+01 O.OOE+OO 1.92E+05 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 2.15E+02 2.21E+02 1.35E+01 O.OOE+OO 8.52E+01 O.OOE+OO 1.40E+05 Eu-152 2.14E+04 5.68E+03 4.79E+03 O.OOE+OO 1.59E+04 O.OOE+OO 5.05E+05 W-187 1.53E+04 1.07E+04 3.68E+03 O.OOE+OO O.OOE+OO O.OOE+OO 6.27E+05 U-235 1.51E+10 O.OOE+OO 1.15E+09 O.OOE+OO 3.20E+09 O.OOE+OO 2.61E+08 U-238 1.44E+10 O.OOE+OO 1.07E+09 O.OOE+OO 2.99E+09 O.OOE+OO 1.84E+08 Np-239 9.12E+OO 8.16E-01 4.61E-01 O.OOE+OO 1.63E+OO O.OOE+OO 2.36E+04 Am-241 4.87E+07 2.29E+07 3.47E+06 O.OOE+OO 2.09E+07 O.OOE+OO 2.45E+06 Page 91 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-12 Rio, GRASS-COW-MEAT PATHWAY DOSE FACTORS -ADULT {m 2-mrem/yr per J.t.Ci/s (mrem/yr per J.tCilm 3 for 3H and 14 C)} NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 2.69E+02 2.69E+02 2.69E+02 2.69E+02 2.69E+02 2.69E+02 C-14 3.33E+05 6.66E+04 6.66E+04 6.66E+04 6.66E+04 6.66E+04 6.66E+04 F-18 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-22 1.10E+09 1.10E+09 1.10E+09 1.10E+09 1.10E+09 1.10E+09 1.10E+09 Na-24 3.22E-04 3.22E-04 3.22E-04 3.22E-04 3.22E-04 3.22E-04 3.22E-04 Sc-46 8.77E+04 1.70E+05 4.95E+04 O.OOE+OO 1.59E+05 O.OOE+OO 8.29E+08 P-32 1.18E+09 7.36E+07 4.58E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.33E+08 Cr-51 O.OOE+OO O.OOE+OO 2.07E+03 1.24E+03 4.56E+02 2.75E+03 5.21E+05 Mn-54 O.OOE+OO 6.33E+06 1.21E+06 O.OOE+OO 1.88E+06 O.OOE+OO 1.94E+07 Mn-56 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Fe-55 2.18E+08 1.51E+08 3.51E+07 O.OOE+OO O.OOE+OO 8.41E+07 8.65E+07 Fe-59 9.89E+07 2.33E+08 8.91E+07 O.OOE+OO O.OOE+OO 6.50E+07 7.75E+08 Co-57 O.OOE+OO 3.78E+06 6.29E+06 O.OOE+OO O.OOE+OO O.OOE+OO 9.60E+07 Co-58 O.OOE+OO 8.51E+06 1.91E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.73E+08 Co-60 O.OOE+OO 5.82E+07 1.28E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.09E+09 Ni-63 1.59E+10 1.10E+09 5.34E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.30E+08 Ni-65 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cu-64 O.OOE+OO 7.00E-08 3.29E-08 O.OOE+OO 1.77E-07 O.OOE+OO 5.97E-06 Zn-65 2.66E+08 8.46E+08 3.82E+08 O.OOE+OO 5.66E+08 O.OOE+OO 5.33E+08 Zn-69m 4.37E-06 1.05E-05 9.58E-06 O.OOE+OO 6.34E-06 O.OOE+OO 6.39E-04 Zn-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO As-76 1.30E-01 3.78E-01 1.89E+OO 1.13E-01 4.61E-01 1.18E-01 1.65E+01 Br-82 O.OOE+OO O.OOE+OO 3.01E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.59E+02 Br-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.25E+08 5.84E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.47E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 1.20E+08 O.OOE+OO 3.45E+06 O.OOE+OO O.OOE+OO O.OOE+OO 1.93E+07 Sr-90 1.18E+10 O.OOE+OO 2.37E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.97E+08 Sr-91 3.96E-11 O.OOE+OO 1.60E-12 O.OOE+OO O.OOE+OO O.OOE+OO 1.88£-10 Sr-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-90 2.70E+01 O.OOE+OO 7.25E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.86E+05 Y-91m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-91 4.83E+05 O.OOE+OO 1.29E+04 O.OOE+OO O.OOE+OO O.OOE+OO 2.67E+08 Y-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 92 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-12 Ria, GRASS-COW-MEAT PATHWAY DOSE FACTORS -ADULT NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Y-93 1.70£-12 O.OOE+OO 4.69£-14 O.OOE+OO O.OOE+OO O.OOE+OO 5.39£-08 Zr-95 8.35£+05 2.68£+05 1.81£+05 O.OOE+OO 4.28£+05 O.OOE+OO 8.49£+08 Zr-97 4.67£-06 9.43£-05 4.31£-07 O.OOE+OO 1.42£-06 O.OOE+OO 2.92£-01 Nb-95 7.55£+05 4.20£+05 2.26£+05 O.OOE+OO 4.15£+05 O.OOE+OO 2.55£+09 Nb-97 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Mo-99 O.OOE+OO 2.50£+04 4.76£+03 O.OOE+OO 5.67£+04 O.OOE+OO 5.80£+04 Tc-99m O.OOE+OO O.OOE+OO 3.90£-20 O.OOE+OO 4.65£-20 O.OOE+OO 1.81£-18 Tc-99 2.42£+08 3.60£+08 9.71£+07 O.OOE+OO 4.52£+09 3.05£+07 1.18E+ 10 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 3.68£+07 O.OOE+OO 1.59£+07 O.OOE+OO 1.41£+08 O.OOE+OO 4.30£+09 Ru-105 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-106 2.00£+09 O.OOE+OO 2.53£+08 O.OOE+OO 3.86£+09 O.OOE+OO 1.29£+11 Rh-105 1.19£+00 8.69£-01 5.73£-01 O.OOE+OO 3.69£+00 O.OOE+OO 1.38£+02 Ag-110m 4.64£+06 4.30£+06 2.55£+06 O.OOE+OO 8.44£+06 O.OOE+OO 1.75£+09 Sn-113 9.30£+07 1.57£+07 2.61£+08 8.22£+06 2.15£+07 9.65£+06 2.86£+09 Sn-117m 1.77£+07 6.08£+05 2.51£+07 1.20£+05 9.20£+05 1.91£+05 2.83£+08 Sb-122 1.82£+03 1.00£+03 1.72£+04 2.12£+02 7.08£+02 2.73£+02 1.82£+05 Sb-124 8.59£+06 1.62£+05 3.40£+06 2.08£+04 O.OOE+OO 6.69£+06 2.44£+08 Sb-125 1.44£+07 1.61£+05 3.43£+06 1.46£+04 O.OOE+OO 1.11£+07 1.59£+08 Te-125m 1.71£+08 6.18£+07 2.28£+07 5.13£+07 6.94£+08 O.OOE+OO 6.81£+08 Te-127m 7.36£+08 2.63£+08 8.96£+07 1.88£+08 2.99£+09 O.OOE+OO 2.47£+09 Te-127 6.85£-11 2.46£-11 1.48£-11 5.07£-11 2.79£-10 O.OOE+OO 5.40£-09 Te-129m 3.93£+08 1.46£+08 6.21£+07 1.35£+08 1.64£+09 O.OOE+OO 1.98£+09 Te-129 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-131m 2.84£+02 1.39£+02 1.16£+02 2.20£+02 1.41£+03 O.OOE+OO 1.38£+04 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 3.33£+05 2.15£+05 2.02£+05 2.38£+05 2.07£+06 O.OOE+OO 1.02£+07 I-130 1.72£-07 8.02£-07 3.17£-07 6.80£-05 1.25£-06 O.OOE+OO 6.91£-07 I-131 1.32£+06 1.88£+06 1.08£+06 6.17£+08 3.23£+06 O.OOE+OO 4.97£+05 I-132 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-133 4.65£-02 8.09£-02 2.47£-02 1.19£+01 1.41£-01 O.OOE+OO 7.27£-02 I-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-135 4.29£-18 1.12£-17 4.15£-18 7.41£-16 1.80£-17 O.OOE+OO 1.27£-17 Cs-134 4.87£+08 1.16£+09 9.48£+08 O.OOE+OO 3.75£+08 1.25£+08 2.03£+07 Cs-134m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-136 2.95£+06 1.17£+07 8.39£+06 O.OOE+OO 6.49£+06 8.89£+05 1.32£+06 Cs-137 7.01£+08 9.59£+08 6.28£+08 O.OOE+OO 3.26£+08 1.08£+08 1.86£+07 Page 93 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-12 Ria, GRASS-COW-MEAT PATHWAY DOSE FACTORS -ADULT NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI~LLI Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-140 6.99E+06 8.79E+03 4.58E+05 O.OOE+OO 2.99E+03 5.03E+03 1.44E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 9.48E-03 4.78E-03 1.26E-03 O.OOE+OO O.OOE+OO O.OOE+OO 3.51E+02 La-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ce-141 4.46E+03 3.01E+03 3.42E+02 O.OOE+OO 1.40E+03 O.OOE+OO 1.15E+07 Ce-143 5.16E-03 3.81E+OO 4.22E-04 O.OOE+OO 1.68E-03 O.OOE+OO 1.43E+02 Ce-144 9.82E+05 4.11E+05 5.27E+04 O.OOE+OO 2.44E+05 O.OOE+OO 3.32E+08 Pr-143 5.15E+03 2.06E+03 2.55E+02 O.OOE+OO 1.19E+03 O.OOE+OO 2.26E+07 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 1.73E+03 2.00E+03 1.19E+02 O.OOE+OO 1.17E+03 O.OOE+OO 9.58E+06 Eu-152 2.00E+06 4.50E+05 3.95E+05 O.OOE+OO 2.79E+06 O.OOE+OO 2.59E+08 W-187 5.49E-03 4.59E-03 1.60E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.50E+OO U-235 5.85E+08 O.OOE+OO 3.55E+07 O.OOE+OO 1.37E+08 O.OOE+OO 5.71E+07 U-238 5.60E+08 O.OOE+OO 3.32E+07 O.OOE+OO 1.28E+08 O.OOE+OO 4.02E+07 Np-239 6.52E-02 6.41E-03 3.54E-03 O.OOE+OO 2.00E-02 O.OOE+OO 1.32E+03 Am-241 3.48E+08 1.22E+08 2.30E+07 O.OOE+OO 1.73E+08 O.OOE+OO 3.15E+07 Page 94 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-13 Rio, GRASS-COW-MEAT PATHWAY DOSE FACTORS -TEEN {m 2-mrem/yr per J.!Ci/s (mrem/yr per J.tCi/m 3 for 3Hand 14 C)} NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 1.60E+02 1.60E+02 1.60E+02 1.60E+02 1.60E+02 1.60E+02 C-14 2.81E+05 5.62E+04 5.62E+04 5.62E+04 5.62E+04 5.62E+04 5.62E+04 F-18 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-22 8.73E+08 8.73E+08 8.73E+08 8.73E+08 8.73E+08 8.73E+08 8.73E+08 Na-24 2.58E-04 2.58E-04 2.58E-04 2.58E-04 2.58E-04 2.58E-04 2.58E-04 Sc-46 6.81E+04 1.33E+05 3.93E+04 O.OOE+OO 1.27E+05 O.OOE+OO 4.51E+08 P-32 l.OOE+09 6.20E+07 3.88E+07 O.OOE+OO O.OOE+OO O.OOE+OO 8.41E+07 Cr-51 O.OOE+OO O.OOE+OO 1.66E+03 9.20E+02 3.63E+02 2.37E+03 2.78E+05 Mn-54 O.OOE+OO 4.83E+06 9.58E+05 O.OOE+OO 1.44E+06 O.OOE+OO 9.90E+06 Mn-56 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Fe-55 1.77E+08 1.26E+08 2.93E+07 O.OOE+OO O.OOE+OO 7.97E+07 5.44E+07 Fe-59 7.91E+07 1.85E+08 7.13E+07 O.OOE+OO O.OOE+OO 5.82E+07 4.36E+08 Co-57 O.OOE+OO 3.04E+06 5.10E+06 O.OOE+OO O.OOE+OO O.OOE+OO 5.67E+07 Co-58 O.OOE+OO 6.56E+06 1.51E+07 O.OOE+OO O.OOE+OO O.OOE+OO 9.05E+07 Co-60 O.OOE+OO 4.51E+07 1.02E+08 O.OOE+OO O.OOE+OO O.OOE+OO 5.88E+08 Ni-63 1.28E+10 9.06E+08 4.35E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.44E+08 Ni-65 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cu-64 O.OOE+OO 5.71E-08 2.69E-08 O.OOE+OO 1.45E-07 O.OOE+OO 4.43E-06 Zn-65 1.87E+08 6.49E+08 3.03E+08 O.OOE+OO 4.15E+08 O.OOE+OO 2.75E+08 Zn-69m 3.64E-06 8.59E-06 7.88E-07 O.OOE+OO 5.22E-06 O.OOE+OO 4.72E-04 Zn-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO As-76 9.08E-02 2.86E-01 1.40E+OO 8.35E-02 3.35E-01 8.38E-02 1.26E+01 Br-82 O.OOE+OO O.OOE+OO 2.49E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.05E+08 4.91E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.55E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 1.01E+08 O.OOE+OO 2.91E+06 O.OOE+OO O.OOE+OO O.OOE+OO 1.21E+07 Sr-90 8.18E+09 O.OOE+OO 1.64E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.87E+08 Sr-91 3.33E-11 O.OOE+OO 1.32E-12 O.OOE+OO O.OOE+OO O.OOE+OO 1.51E-10 Sr-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-90 2.27E+01 O.OOE+OO 6.12E-01 O.OOE+OO O.OOE+OO O.OOE+OO 1.88E+05 Y-91m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-91 4.08E+05 O.OOE+OO 1.09E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.67E+08 Page 95 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-13 Rio, GRASS-COW-MEAT PATHWAY DOSE FACTORS TEEN NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Y-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-93 1.43E-12 O.OOE+OO 3.93E-14 O.OOE+OO O.OOE+OO O.OOE+OO 4.38E-08 Zr-95 6.69E+05 2.11E+05 1.45E+05 O.OOE+OO 3.10E+05 O.OOE+OO 4.87E+08 Zr-97 3.90E-06 7.71E-07 3.55E-07 O.OOE+OO 1.17E-06 O.OOE+OO 2.09E-01 Nb-95 5.90E+05 3.27E+05 1.80E+05 O.OOE+OO 3.17E+05 O.OOE+OO 1.40E+09 Nb-97 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Mo-99 O.OOE+OO 2.07E+04 3.94E+03 O.OOE+OO 4.73E+04 O.OOE+OO 3.70E+04 Tc-99m O.OOE+OO O.OOE+OO 3.11E-20 O.OOE+OO 3.58E-20 O.OOE+OO 1.58E-18 Tc-99 2.05E+08 3.00E+08 8.19E+07 O.OOE+OO 3.82E+09 3.11E+07 7.36E+09 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 3.00E+07 O.OOE+OO 1.28E+07 O.OOE+OO 1.06E+08 O.OOE+OO 2.51E+09 Ru-105 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-106 1.68E+09 O.OOE+OO 2.12E+08 O.OOE+OO 3.24E+09 O.OOE+OO 8.07E+10 Rh-105 1.00E+OO 7.25E-01 4.76E-01 O.OOE+OO 3.08E+OO O.OOE+OO 9.23E+01 Ag-llOm 3.52E+06 3.33E+06 2.02E+06 O.OOE+OO 6.34E+06 O.OOE+OO 9.35E+08 Sn-113 5.92E+07 1.18E+07 1.94E+08 5.71E+06 1.54E+07 6.97E+06 2.09E+09 Sn-117m 1.07E+07 4.60E+05 1.84E+07 8.58E+04 6.48E+05 1.57E+05 2.07E+08 Sb-122 1.13E+03 7.76E+02 1.25E+04 1.55E+02 5.08E+02 2.09E+02 1.31E+05 Sb-124 7.01E+06 1.29E+05 2.74E+06 1.59E+04 O.OOE+OO 6.13E+06 1.41E+08 Sb-125 1.18E+07 1.29E+05 2.76E+06 1.13E+04 O.OOE+OO 1.04E+07 9.18E+07 Te-125m 1.44E+08 5.19E+07 1.93E+07 4.02E+07 O.OOE+OO O.OOE+OO 4.25E+08 Te-127m 6.21E+08 2.20E+08 7.38E+07 1.48E+08 2.52E+09 O.OOE+OO 1.55E+09 Te-127 5.81E-11 2.06E-11 1.25E-11 4.01E-11 2.35E-10 O.OOE+OO 4.49E-09 Te-129m 3.29E+08 1.22E+08 5.21E+07 1.07E+08 1.38E+09 O.OOE+OO 1.23E+09 Te-129 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-131m 2.37E+02 1.14E+02 9.48E+01 1.71E+02 1.19E+03 O.OOE+OO 9.12E+03 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 2.72E+05 1.72E+05 1.62E+05 1.82E+05 1.65E+06 O.OOE+OO 5.46E+06 I-130 2.19E-07 6.33E-07 2.53E-07 5.16E-05 9.76E-07 O.OOE+OO 4.87E-07 I-131 1.09E+06 1.53E+06 8.23E+05 4.47E+08 2.64E+06 O.OOE+OO 3.03E+05 I-132 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-133 3.89E-02 6.60E-02 2.01E-02 9.21E+OO 1.16E-01 O.OOE+OO 4.99E-02 I-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-135 3.49E-18 8.99E-18 3.33E-18 5.78E-16 1.42E-17 O.OOE+OO 9.96E-18 Cs-134 3.87E+08 9.12E+08 4.23E+08 O.OOE+OO 2.90E+08 1.11E+08 1.13E+07 Cs-134m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-136 2.30E+06 9.06E+06 6.08E+06 O.OOE+OO 4.93E+06 7.77E+05 7.29E+05 Cs-137 5.82E+08 7.75E+08 2.70E+08 O.OOE+OO 2.64E+08 1.02E+08 1.10E+07 Page 96 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-13 Rio, GRASS-COW-MEAT PATHWAY DOSE FACTORS- TEEN NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-140 5.78E+06 7.09E+03 3.73E+05 O.OOE+OO 2.40E+03 4.76E+03 8.92E+06 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 7.79E-03 3.83E-03 1.02E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.20E+02 La-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ce-141 3.74E+03 2.50E+03 2.87E+02 O.OOE+OO 1.18E+03 O.OOE+OO 7.15E+06 Ce-143 4.34E-03 3.16E+OO 3.53E-04 O.OOE+OO 1.42E-03 O.OOE+OO 9.50E+01 Ce-144 8.28E+05 3.43E+05 4.45E+04 O.OOE+OO 2.05E+05 O.OOE+OO 2.08E+08 Pr-143 4.33E+03 1.73E+03 2.16E+02 O.OOE+OO 1.01E+03 O.OOE+OO 1.43E+07 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 1.52E+03 1.65E+03 9.91E+01 O.OOE+OO 9.72E+02 O.OOE+OO 5.97E+06 Eu-152 1.47E+06 3.53E+05 3.11E+05 O.OOE+OO 1.64E+06 O.OOE+OO 1.30E+08 W-187 4.60E-03 3.75E-03 1.31E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.01E+OO U-235 4.92E+08 O.OOE+OO 3.00E+07 O.OOE+OO 1.15E+08 O.OOE+OO 3.57E+07 U-238 4.71E+08 O.OOE+OO 2.80E+07 O.OOE+OO 1.08E+08 O.OOE+OO 2.52E+07 Np-239 5.70E-02 5.38E-03 2.99E-03 O.OOE+OO 1.69E-02 O.OOE+OO 8.65E+02 Am-241 2.16E+08 8.26E+07 1.44E+07 O.OOE+OO 1.08E+08 O.OOE+OO 1.97E+07 Page 97 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFF SITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-14 Ria, GRASS-COW-MEATPATHWAYDOSE FACTORS CHILD 3 3 14 {m 2 -mrem/yr per J..LCi/s (mrem/ vr per p,Ci/m for H-3 and C)} NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 1.94E+02 1.94E+02 1.94E+02 1.94E+02 1.94E+02 1.94£+02 C-14 5.29E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 F-18 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-22 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 Na-24 4.10E-04 4.10E-04 4.10E-04 4.10E-04 4.10E-04 4.10E-04 4.10E-04 Sc-46 1.17E+05 1.60E+05 6.17E+04 O.OOE+OO 1.42E+05 O.OOE+OO 2.34E+08 P-32 1.89E+09 8.83E+07 7.27E+07 O.OOE+OO O.OOE+OO O.OOE+OO 5.21E+07 Cr-51 O.OOE+OO O.OOE+OO 2.58E+03 1.43E+03 3.92E+02 2.62E+03 1.37E+05 Mn-54 O.OOE+OO 5.52E+06 1.47E+06 O.OOE+OO 1.55E+06 O.OOE+OO 4.64E+06 Mn-56 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Fe-55 3.40E+08 1.80E+08 5.59E+07 O.OOE+OO O.OOE+OO 1.02E+08 3.34E+07 Fe-59 1.40E+08 2.27E+08 1.13E+08 O.OOE+OO O.OOE+OO 6.58E+07 2.36E+08 Co-57 O.OOE+OO 3.97E+06 8.04E+06 O.OOE+OO O.OOE+OO O.OOE+OO 3.26E+07 Co-58 O.OOE+OO 7.67E+06 2.35E+07 O.OOE+OO O.OOE+OO O.OOE+OO 4.47E+07 Co-60 O.OOE+OO 5.36E+07 1.58E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.97E+08 Ni-63 2.46E+10 1.32E+09 8.36E+08 O.OOE+OO O.OOE+OO O.OOE+OO 8.86E+07 Ni-65 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cu-64 O.OOE+OO 7.68E-08 4.64E-08 O.OOE+OO 1.86E-07 O.OOE+OO 3.60E-06 Zn-65 2.80E+08 7.47E+08 4.65E+08 O.OOE+OO 4.71E+08 O.OOE+OO 1.31E+08 Zn-69m 6.80E-06 1.16E-05 1.37E-06 O.OOE+OO 6.73E-06 O.OOE+OO 3.77E-04 Zn-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO As-76 1.59E-01 4.41E-01 2.56E+OO 1.50E-01 4.85E-01 1.50E-01 2.29E+01 Br-82 O.OOE+OO O.OOE+OO 3.90E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.48E+08 9.12E+07 O.OOE+OO O.OOE+OO O.OOE+OO 9.54E+06 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 1.92E+08 O.OOE+OO 5.48E+06 O.OOE+OO O.OOE+OO O.OOE+OO 7.43E+06 Sr-90 1.29E+10 O.OOE+OO 2.60E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.16E+08 Sr-91 6.24E-11 O.OOE+OO 2.36E-12 O.OOE+OO O.OOE+OO O.OOE+OO 1.38E-10 Sr-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-90 4.30E+01 O.OOE+OO 1.15E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.22E+05 Y-91m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-91 7.71E+05 O.OOE+OO 2.06E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.03E+08 Page 98 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-14 Ria, GRASS-COW-MEAT PATHWAY DOSE FACTORS- CHILD NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Y-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-93 2.69E-12 O.OOE+OO 7.39E-14 O.OOE+OO O.OOE+OO O.OOE+OO 4.02E-08 Zr-95 1.19E+06 2.61E+05 2.32E+05 O.OOE+OO 3.74E+05 O.OOE+OO 2.72E+08 Zr-97 7.25E-06 1.05E-06 6.18E-07 O.OOE+OO 1.50E-06 O.OOE+OO 1.59E-01 Nb-95 1.02E+06 3.97E+05 2.83E+05 O.OOE+OO 3.73E+05 O.OOE+OO 7.33E+08 Nb-97 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Mo-99 O.OOE+OO 2.88E+04 7.12E+03 O.OOE+OO 6.14E+04 O.OOE+OO 2.38E+04 Tc-99m O.OOE+OO O.OOE+OO 4.91E-20 O.OOE+OO 4.30E-20 O.OOE+OO 1.68E-18 Tc-99 3.86E+08 4.29E+08 1.54E+08 O.OOE+OO 5.06E+09 3.80E+07 4.50E+09 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 5.43E+07 O.OOE+OO 2.09E+07 O.OOE+OO 1.37E+08 O.OOE+OO 1.40E+09 Ru-105 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-106 3.17E+09 O.OOE+OO 3.95E+08 O.OOE+OO 4.28E+09 O.OOE+OO 4.93E+10 Rh-105 1.88E+OO 1.01E+OO 8.64E-01 O.OOE+OO 4.03E+OO O.OOE+OO 6.26E+01 Ag-llOm 5.83E+06 3.94E+06 3.15E+06 O.OOE+OO 7.33E+06 O.OOE+OO 4.68E+08 Sn-113 1.05E+08 2.27E+07 3.47E+08 9.06E+06 2.40E+07 1.13E+07 3.87E+09 Sn-117m 2.11E+07 1.00E+06 3.30E+07 1.58E+05 1.02E+06 2.90E+05 3.83E+08 Sb-122 2.07E+03 1.24E+03 2.30E+04 2.71E+02 7.54E+02 3.54E+02 2.49E+05 Sb-124 1.27E+07 1.65E+05 4.45E+06 2.80E+04 O.OOE+OO 7.04E+06 7.93E+07 Sb-125 2.15E+07 1.66E+05 4.50E+06 1.99E+04 O.OOE+OO 1.20E+07 5.13E+07 Te-125m 2.70E+08 7.33E+07 3.61E+07 7.59E+07 O.OOE+OO O.OOE+OO 2.61E+08 Te-127m 1.17E+09 3.15E+08 1.39E+08 2.84E+08 3.34E+09 O.OOE+OO 9.48E+08 Te-127 1.09E-10 2.95E-11 2.34E-11 7.56E-11 3.11E-10 O.OOE+OO 4.27E-09 Te-129m 6.20E+08 1.73E+08 9.62E+07 2.00E+08 1.82E+09 O.OOE+OO 7.56E+08 Te-129 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-131m 4.41E+02 1.53E+02 1.62E+02 3.14E+02 1.48E+03 O.OOE+OO 6.19E+03 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 4.97E+05 2.20E+05 2.66E+05 3.20E+05 2.04E+06 O.OOE+OO 2.21E+06 I-130 3.91E-07 7.91E-07 4.08E-07 8.71E-05 1.18E-06 O.OOE+OO 3.70E-07 I-131 2.03E+06 2.04E+06 1.16E+06 6.75E+08 3.35E+06 O.OOE+OO 1.82E+05 I-132 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-133 7.23E-02 8.94E-02 3.38E-02 1.66E+01 1.49E-01 O.OOE+OO 3.60E-02 I-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-135 6.32E-18 1.14E-17 5.38E-18 1.01E-15 1.74E-17 O.OOE+OO 8.67E-18 Cs-134 6.83E+08 1.12E+09 2.36E+08 O.OOE+OO 3.47E+08 1.25E+08 6.04E+06 Cs-134m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-136 3.97E+06 1.09E+07 7.07E+06 O.OOE+OO 5.82E+06 8.67E+05 3.84E+05 Page 99 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-14 Ria, GRASS-COW-MEAT PATHWAY DOSE FACTORS- CHILD NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Cs-137 1.07E+09 1.03E+09 1.52E+08 O.OOE+OO 3.34E+08 1.20E+08 6.43E+06 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-140 1.07E+07 9.35E+03 6.23E+05 O.OOE+OO 3.04E+03 5.57E+03 5.41E+06 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 1.43E-02 4.99E-03 1.68E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.39E+02 La-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ce-141 7.04E+03 3.51E+03 5.22E+02 O.OOE+OO 1.54E+03 O.OOE+OO 4.38E+06 Ce-143 8.15E-03 4.42E+OO 6.40E-04 O.OOE+OO 1.85E-03 O.OOE+OO 6.47E+01 Ce-144 1.56E+06 4.89E+05 8.33E+04 O.OOE+OO 2.71E+05 O.OOE+OO 1.28E+08 Pr-143 8.20E+03 2.46E+03 4.07E+02 O.OOE+OO 1.33E+03 O.OOE+OO 8.84E+06 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 2.86E+03 2.31E+03 1.79E+02 O.OOE+OO 1.27E+03 O.OOE+OO 3.66E+06 Eu-152 2.32E+06 4.23E+05 5.02E+05 O.OOE+OO 1.79E+06 O.OOE+OO 6.95E+07 W-187 8.52E-03 5.04E-03 2.26E-03 O.OOE+OO O.OOE+OO O.OOE+OO 7.09E-01 U-235 9.31E+08 O.OOE+OO 5.64E+07 O.OOE+OO 1.53E+08 O.OOE+OO 2.19E+07 U-238 8.90E+08 O.OOE+OO 5.28E+07 O.OOE+OO 1.43E+08 O.OOE+OO 1.54E+07 Np-239 1.07E-01 7.70E-03 5.41E-03 O.OOE+OO 2.23E-02 O.OOE+OO 5.70E+02 Am-241 2.26E+08 1.01E+08 1.61E+07 O.OOE+OO 9.86E+07 O.OOE+OO 1.21E+07 Page 100 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-15 Rio, PRODUCE PATHWAY DOSE FACTORS -ADULT {m 2-mrem/yr per J,.LCi/s (mrem/vr per J.tCilm 3 for 3H-3 and 14 C)} NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 1.60E+03 1.60E+03 1.60E+03 1.60E+03 1.60E+03 1.60E+03 C-14 7.72E+05 1.54E+05 1.54E+05 1.54E+05 1.54E+05 1.54E+05 1.54E+05 F-18 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-22 1.24E+09 1.24E+09 1.24E+09 1.24E+09 1.24E+09 1.24E+09 1.24E+09 Na-24 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sc-46 1.92E+05 3.73E+05 1.08E+05 O.OOE+OO 3.48E+05 O.OOE+OO 1.82E+09 P-32 3.98E+08 2.48E+07 1.54E+07 O.OOE+OO O.OOE+OO O.OOE+OO 4.48E+07 Cr-51 O.OOE+OO O.OOE+OO 2.69E+04 1.60E+04 5.92E+03 3.56E+04 6.75E+06 Mn-54 O.OOE+OO 2.60E+08 4.95E+07 O.OOE+OO 7.73E+07 O.OOE+OO 7.95E+08 Mn-56 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Fe-55 1.71E+08 1.18E+08 2.75E+07 O.OOE+OO O.OOE+OO 6.59E+07 6.78E+07 Fe-59 8.77E+07 2.06E+08 7.90E+07 O.OOE+OO O.OOE+OO 5.76E+07 6.87E+08 Co-57 O.OOE+OO 9.50E+06 1.58E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.41E+08 Co-58 O.OOE+OO 2.32E+07 5.21E+07 O.OOE+OO O.OOE+OO O.OOE+OO 4.71E+08 Co-60 O.OOE+OO 1.43E+08 3.15E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.68E+09 Ni-63 1.03E+10 7.15E+08 3.46E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.49E+08 Ni-65 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cu-64 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zn-65 3.36E+08 1.07E+09 4.84E+08 O.OOE+OO 7.16E+08 O.OOE+OO 6.74E+08 Zn-69m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zn-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO As-76 6.72E-11 1.96E-10 9.78E-10 5.87E-11 2.38E-10 6.11E-11 8.56E-09 Br-82 O.OOE+OO O.OOE+OO 8.08E-06 O.OOE+OO O.OOE+OO O.OOE+OO 9.26E-06 Br-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 9.00E+07 4.19E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.77E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 7.16E+09 O.OOE+OO 2.06E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.15E+09 Sr-90 6.64E+11 O.OOE+OO 1.33E+ 10 O.OOE+OO O.OOE+OO O.OOE+OO 1.67E+10 Sr-91 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-90 1.83E-02 O.OOE+OO 4.90E-04 O.OOE+OO O.OOE+OO O.OOE+OO 1.94E+02 Y-91m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-91 3.76E+06 O.OOE+OO 1.01E+05 O.OOE+OO O.OOE+OO O.OOE+OO 2.07E+09 Y-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 101 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-15 Ria, PRODUCE PATHWAY DOSE FACTORS- ADULT NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Y-93 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zr-95 8.75E+05 2.80E+05 1.90E+05 O.OOE+OO 4.40E+05 O.OOE+OO 8.89E+08 Zr-97 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.43E-18 Nb-95 9.19E+04 5.11E+04 2.75E+04 O.OOE+OO 5.06E+04 O.OOE+OO 3.10E+08 Nb-97 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Mo-99 O.OOE+OO 1.31E+01 2.49E+OO O.OOE+OO 2.97E+01 O.OOE+OO 3.03E+01 Tc-99m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tc-99 3.25E+07 4.84E+07 1.31E+07 O.OOE+OO 6.09E+08 4.11E+06 1.58E+09 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 3.23E+06 O.OOE+OO 1.39E+06 O.OOE+OO 1.23E+07 O.OOE+OO 3.77E+08 Ru-105 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-106 1.65E+08 O.OOE+OO 2.09E+07 O.OOE+OO 3.19E+08 O.OOE+OO 1.07E+ 10 Rh-105 7.23E-07 5.29E-07 3.48E-07 O.OOE+OO 2.25E-06 O.OOE+OO &.42E-05 Ag-llOm 9.51E+06 8.79E+06 5.22E+06 O.OOE+OO 1.73E+07 O.OOE+OO 3.59E+09 Sn-113 3.98E+07 6.74E+06 1.12E+08 3.52E+06 9.19E+06 4.14E+06 1.23E+09 Sn-117m 2.95E+06 1.00E+05 4.19E+06 2.01E+04 1.53E+05 3.19E+04 4.72E+07 Sb-122 1.71E+OO 9.42E-01 1.62E+01 2.00E-01 6.66E-01 2.57E-01 1.71E+02 Sb-124 7.67E+07 1.45E+06 3.04E+07 1.86E+05 O.OOE+OO 5.97E+07 2.18E+09 Sb-125 1.15E+08 1.28E+06 2.73E+07 1.17E+05 O.OOE+OO 8.86E+07 1.26E+09 Te-125m 9.11E+07 3.30E+07 1.22E+07 2.74E+07 3.71E+08 O.OOE+OO 3.64E+08 Te-127m 4.07E+08 1.46E+08 4.96E+07 1.04E+08 1.65E+09 O.OOE+OO 1.37E+09 Te-127 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-129m 1.90E+08 7.08E+07 3.01E+07 6.52E+07 7.93E+08 O.OOE+OO 9.56E+08 Te-129 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-131m 4.64E-07 2.27E-07 1.89E-07 3.60E-07 2.30E-06 O.OOE+OO 2.25E-05 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 7.82E+01 5.06E+01 4.75E+01 5.59E+01 4.87E+02 O.OOE+OO 2.39E+03 I-130 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-131 1.46E+06 2.09E+06 1.20E+06 6.86E+08 3.59E+06 O.OOE+OO 5.52E+05 I-132 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-133 2.06E-14 3.58E-14 1.09E-14 5.27E-12 6.26E-14 O.OOE+OO 3.22E-14 I-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-135 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-134 3.88E+09 9.24E+09 7.55E+09 O.OOE+OO 2.99E+09 9.93E+08 1.62E+08 Cs-134m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-136 9.22E+06 3.64E+07 2.62E+07 O.OOE+OO 2.02E+07 2.77E+06 4.13E+06 Cs-137 5.71E+09 7.81E+09 5.12E+09 O.OOE+OO 2.65E+09 8.82E+08 1.51E+08 Page 102 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-15 Rio, PRODUCE PATHWAY DOSE FACTORS -ADULT NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-140 2.55E+07 3.21E+04 1.67E+06 O.OOE+OO 1.09E+04 1.84E+04 5.26E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 3.18E-07 1.60E-07 4.23E-08 O.OOE+OO O.OOE+OO O.OOE+OO 1.18E-02 La-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ce-141 1.24E+05 8.37E+04 9.49E+03 O.OOE+OO 3.89E+04 O.OOE+OO 3.20E+08 Ce-143 7.79E-10 5.76E-07 6.37E-11 O.OOE+OO 2.53E-10 O.OOE+OO 2.15E-05 Ce-144 2.66E+07 1.11E+07 1.43E+06 O.OOE+OO 6.58E+06 O.OOE+OO 8.98E+09 Pr-143 1.45E+04 5.83E+03 7.21E+02 O.OOE+OO 3.37E+03 O.OOE+OO 6.37E+07 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 4.31E+03 4.99E+03 2.98E+02 O.OOE+OO 2.92E+03 O.OOE+OO 2.39E+07 Eu-152 1.30E+07 2.93E+06 2.58E+06 O.OOE+OO 1.82E+07 O.OOE+OO 'I.69E+09 W-187 3.44E-13 2.88E-13 1.01E-13 O.OOE+OO O.OOE+OO O.OOE+OO 9.42E-11 U-235 5.40E+ 10 O.OOE+OO 3.28E+09 O.OOE+OO 1.26E+10 O.OOE+OO 5.26E+09 U-238 5.17E+10 O.OOE+OO 3.06E+09 O.OOE+OO 1.18E+10 O.OOE+OO 3.71E+09 Np-239 2.53E-04 2.49E-05 1.37E-05 O.OOE+OO 7.76E-05 O.OOE+OO 5.10E+OO Am-241 5.37E+ 10 1.89E+10 3.55E+09 O.OOE+OO 2.67E+10 O.OOE+OO 4.87E+09 Page 103 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-16 Rio, PRODUCE PATHWAY DOSE FACTORS -TEEN 2 3 3 14 {m -mrem/yr per J.LCi/s (mrem/vr per ~tCi/m for H-3 and C)} NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 1.95E+03 1.95E+03 1.95E+03 1.95E+03 1.95E+03 1.95E+03 C-14 1.34E+06 2.67E+05 2.67E+05 2.67E+05 2.67E+05 2.67E+05 2.67E+05 F-18 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-22 2.02E+09 2.02E+09 2.02E+09 2.02E+09 2.02E+09 2.02E+09 2.02E+09 Na-24 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sc-46 3.06E+05 5.96E+05 1.77E+05 O.OOE+OO 5.70E+05 O.OOE+OO 2.03E+09 P-32 6.90E+08 4.27E+07 2.67E+07 O.OOE+OO O.OOE+OO O.OOE+OO 5.80E+07 Cr-51 O.OOE+OO O.OOE+OO 4.40E+04 2.45E+04 9.65E+03 6.29E+04 7.40E+06 Mn-54 O.OOE+OO 4.06E+08 8.05E+07 O.OOE+OO 1.21E+08 O.OOE+OO 8.33E+08 Mn-56 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Fe-55 2.85E+08 2.02E+08 4.71E+07 O.OOE+OO O.OOE+OO 1.28E+08 8.74E+07 Fe-59 1.44E+08 3.35E+08 1.29E+08 O.OOE+OO O.OOE+OO 1.06E+08 7.93E+08 Co-57 O.OOE+OO 1.56E+07 2.62E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.92E+08 Co-58 O.OOE+OO 3.67E+07 8.47E+07 O.OOE+OO O.OOE+OO O.OOE+OO 5.06E+08 Co-60 O.OOE+OO 2.27E+08 5.12E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.96E+09 Ni-63 1.70E+10 1.20E+09 5.77E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.91E+08 Ni-65 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cu-64 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zn-65 4.85E+08 1.68E+09 7.86E+08 O.OOE+OO 1.08E+09 O.OOE+OO 7.13E+08 Zn-69m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zn-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO As-76 9.62E-11 3.04E-10 1.48E-09 8.88E-11 3.55E-10 8.88E-11 1.33E-08 Br-82 O.OOE+OO O.OOE+OO 1.32E-05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.54E+08 7.24E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.28E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 1.24E+10 O.OOE+OO 3.55E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.48E+09 Sr-90 9.42E+ 11 O.OOE+OO 1.88E+10 O.OOE+OO O.OOE+OO O.OOE+OO 2.15E+10 Sr-91 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-90 3.15E-02 O.OOE+OO 8.49E-04 O.OOE+OO O.OOE+OO O.OOE+OO 2.60E+02 Y-91m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-91 6.49E+06 O.OOE+OO 1.74E+05 O.OOE+OO O.OOE+OO O.OOE+OO 2.66E+09 Y-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 104 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-16 Rio, PRODUCE PATHWAY DOSE FACTORS -TEEN NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Y-93 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zr-95 1.44E+06 4.53E+05 3.12E+05 O.OOE+OO 6.66E+05 O.OOE+OO 1.05E+09 Zr-97 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.96E-18 Nb-95 1.47E+05 8.17E+04 4.50E+04 O.OOE+OO 7.92E+04 O.OOE+OO 3.49E+08 Nb-97 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Mo-99 O.OOE+OO 2.22E+01 4.23E+OO O.OOE+OO 5.08E+01 O.OOE+OO 3.97E+01 Tc-99m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tc-99 5.65E+07 8.29E+07 2.26E+07 O.OOE+OO 1.05E+09 8.58E+06 2.03E+09 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 5.49E+06 O.OOE+OO 2.31E+06 O.OOE+OO 1.90E+07 O.OOE+OO 4.51E+08 Ru-105 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-106 2.86E+08 O.OOE+OO 3.60E+07 O.OOE+OO 5.51E+08 O.OOE+OO 1.37E+10 Rh-105 1.25E-06 9.05E-07 5.94E-07 O.OOE+OO 3.84E-06 O.OOE+OO 1.15E-04 Ag-110m 1.48E+07 1.40E+07 8.49E+06 O.OOE+OO 2.66E+07 O.OOE+OO 3.92E+09 Sn-113 5.20E+07 1.04E+07 1.71E+08 5.01E+06 1.35E+07 6.12E+06 1.84E+09 Sn-117m 3.65E+06 1.57E+05 6.29E+06 2.93E+04 2.22E+05 5.36E+04 7.08E+07 Sb-122 2.19E+OO 1.50E+OO 2.42E+01 3.00E-01 9.80E-01 4.04E-01 2.54E+02 Sb-124 1.28E+08 2.37E+06 5.01E+07 2.91E+05 O.OOE+OO 1.12E+08 2.59E+09 Sb-125 1.93E+08 2.11E+06 4.51E+07 1.84E+05 O.OOE+OO 1.70E+08 1.50E+09 Te-125m 1.58E+08 5.68E+07 2.11E+07 4.41E+07 O.OOE+OO O.OOE+OO 4.66E+08 Te-127m 7.05E+08 2.50E+08 8.38E+07 1.68E+08 2.86E+09 O.OOE+OO 1.76E+09 Te-127 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-129m 3.26E+08 1.21E+08 5.15E+07 1.05E+08 1.36E+09 O.OOE+OO 1.22E+09 Te-129 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-131m 7.93E-07 3.80E-07 3.17E-07 5.72E-07 3.97E-06 O.OOE+OO 3.05E-05 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 1.31E+02 8.31E+01 7.82E+01 8.76E+01 7.97E+02 O.OOE+OO 2.63E+03 I-130 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-131 2.49E+06 3.49E+06 1.87E+06 1.02E+09 6.01E+06 O.OOE+OO 6.90E+05 I-132 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-133 3.53E-14 6.00E-14 1.83E-14 8.37E-12 1.05E-13 O.OOE+OO 4.54E-14 I-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-135 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-134 6.33E+09 1.49E+10 6.91E+09 O.OOE+OO 4.74E+09 1.81E+09 1.85E+08 Cs-134m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-136 1.47E+07 5.80E+07 3.89E+07 O.OOE+OO 3.16E+07 4.97E+06 4.66E+06 Cs-137 9.73E+09 1.29E+10 4.51E+09 O.OOE+OO 4.40E+09 1.71E+09 1.84E+08 Page 105 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-16 Ria, PRODUCE PATHWAY DOSE FACTORS -TEEN NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-140 4.33E+07 5.30E+04 2.79E+06 O.OOE+OO 1.80E+04 3.57E+04 6.67E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 5.36E-07 2.63E-07 7.01E-08 O.OOE+OO O.OOE+OO O.OOE+OO 1.51E-02 La-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ce-141 2.13E+05 1.42E+05 1.63E+04 O.OOE+OO 6.70E+04 O.OOE+OO 4.07E+08 Ce-143 1.34E-09 9.78E-07 1.09E-10 O.OOE+OO 4.39E-10 O.OOE+OO 2.94E-05 Ce-144 4.59E+07 1.90E+07 2.47E+06 O.OOE+OO 1.13E+07 O.OOE+OO 1.15E+10 Pr-143 2.51E+04 1.00E+04 1.25E+03 O.OOE+OO 5.82E+03 O.OOE+OO 8.25E+07 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 7.80E+03 8.48E+03 5.08E+02 O.OOE+OO 4.98E+03 O.OOE+OO 3.06E+07 Eu-152 1.96E+07 4.72E+06 4.16E+06 O.OOE+OO 2.19E+07 O.OOE+OO 1.74E+09 W-187 5.91E-13 4.82E-13 1.69E-13 O.OOE+OO O.OOE+OO O.OOE+OO 1.30E-10 U-235 9.31E+10 O.OOE+OO 5.67E+09 O.OOE+OO 2.18E+10 O.OOE+OO 6.76E+09 U-238 8.90E+10 O.OOE+OO 5.30E+09 O.OOE+OO 2.04E+10 O.OOE+OO 4.76E+09 Np-239 4.53E-04 4.27E-05 2.37E-05 O.OOE+OO 1.34E-04 O.OOE+OO 6.88E+OO Am-241 6.85E+10 2.62E+10 4.57E+09 O.OOE+OO 3.43E+10 O.OOE+OO 6.26E+09 Page 106 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-17 Ria, PRODUCE PATHWAY DOSE FACTORS -CHILD {m 2-mrem/yr per f..lCi/s (mrem/vr per!!_Ci/m 3 for 3H-3 and 14 C)} NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG Gl-LLI H-3 O.OOE+OO 3.10E+03 3.10E+03 3.10E+03 3.10E+03 3.10E+03 3.10E+03 C-14 3.29E+06 6.58E+05 6.58E+05 6.58E+05 6.58E+05 6.58E+05 6.58E+05 F-18 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-22 4.20E+09 4.20E+09 4.20E+09 4.20E+09 4.20E+09 4.20E+09 4.20E+09 Na-24 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sc-46 6.87E+05 9.42E+05 3.63E+05 O.OOE+OO 8.33E+05 O.OOE+OO 1.38E+09 P-32 1.70E+09 7.96E+07 6.56E+07 O.OOE+OO O.OOE+OO O.OOE+OO 4.70E+07 Cr-51 O.OOE+OO O.OOE+OO 8.98E+04 4.99E+04 1.36E+04 9.10E+04 4.76E+06 Mn-54 O.OOE+OO 6.08E+08 1.62E+08 O.OOE+OO 1.70E+08 O.OOE+OO 5.10E+08 Mn-56 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Fe-55 7.15E+08 3.79E+08 1.17E+08 O.OOE+OO O.OOE+OO 2.14E+08 7.02E+07 Fe-59 3.33E+08 5.39E+08 2.69E+08 O.OOE+OO O.OOE+OO 1.56E+08 5.62E+08 Co-57 O.OOE+OO 2.68E+07 5.42E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.19E+08 Co-58 O.OOE+OO 5.62E+07 1.72E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.28E+08 Co-60 O.OOE+OO 3.53E+08 1.04E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.96E+09 Ni-63 4.27E+10 2.29E+09 1.45E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.54E+08 Ni-65 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cu-64 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zn-65 9.52E+08 2.54E+09 1.58E+09 O.OOE+OO 1.60E+09 O.OOE+OO 4.46E+08 Zn-69m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zn-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO As-76 2.20E-10 6.11E-10 3.54E-09 2.08E-10 6.72E-10 2.08E-10 3.18E-08 Br-82 O.OOE+OO O.OOE+OO 2.70E-05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.86E+08 1.76E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.84E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 3.07E+10 O.OOE+OO 8.77E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.19E+09 Sr-90 1.95E+12 O.OOE+OO 3.92E+10 O.OOE+OO O.OOE+OO O.OOE+OO 1.74E+10 Sr-91 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-90 7.81E-02 O.OOE+OO 2.09E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.22E+02 Y-91m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-91 1.61E+07 O.OOE+OO 4.29E+05 O.OOE+OO O.OOE+OO O.OOE+OO 2.14E+09 Y-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 107 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-17 Ria, PRODUCE PATHWAY DOSE FACTORS -CHILD NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Y-93 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zr-95 3.34E+06 7.34E+05 6.53E+05 O.OOE+OO 1.05E+06 O.OOE+OO 7.65E+08 Zr-97 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.92E-18 Nb-95 3.33E+05 1.29E+05 9.25E+04 O.OOE+OO 1.22E+05 O.OOE+OO 2.39E+08 Nb-97 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Mo-99 O.OOE+OO 4.04E+01 9.99E+OO O.OOE+OO 8.63E+01 O.OOE+OO 3.34E+01 Tc-99m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tc-99 1.39E+08 1.55E+08 5.55E+07 O.OOE+OO 1.83E+09 1.37E+07 1.63E+09 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 1.28E+07 O.OOE+OO 4.91E+06 O.OOE+OO 3.21E+07 O.OOE+OO 3.30E+08 Ru-105 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-106 7.04E+08 O.OOE+OO 8.78E+07 O.OOE+OO 9.50E+08 O.OOE+OO 1.09E+10 Rh-105 3.07E-06 1.65E-06 1.41E-06 O.OOE+OO 6.57E-06 O.OOE+OO 1.02E-04 Ag-llOm 3.20E+07 2.16E+07 1.73E+07 O.OOE+OO 4.03E+07 O.OOE+OO 2.57E+09 Sn-113 1.21E+08 2.60E+07 3.98E+08 1.04E+07 2.76E+07 1.30E+07 4.44E+09 Sn-117m 9.44E+06 4.48E+05 1.48E+07 7.08E+04 4.54E+05 1.30E+05 1.71E+08 Sb-122 5.23E+OO 3.14E+OO 5.81E+01 6.84E-01 1.80E+OO 8.95E-01 6.28E+02 Sb-124 3.04E+08 3.94E+06 1.07E+08 6.71E+05 O.OOE+OO 1.69E+08 1.90E+09 Sb-125 4.60E+08 3.54E+06 9.63E+07 4.26E+05 O.OOE+OO 2.56E+08 1.10E+09 Te-125m 3.88E+08 1.05E+08 5.17E+07 1.09E+08 O.OOE+OO O.OOE+OO 3.74E+08 Te-127m 1.74E+09 4.68E+08 2.06E+08 4.16E+08 4.96E+09 O.OOE+OO 1.41E+09 Te-127 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-129m 8.04E+08 2.25E+08 1.25E+08 2.59E+08 2.36E+09 O.OOE+OO 9.81E+08 Te-129 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-131m 1.93E-06 6.68E-07 7.11E-07 1.37E-06 6.47E-06 O.OOE+OO 2.71E-05 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 3.14E+02 1.39E+02 1.68E+02 2.02E+02 1.29E+03 O.OOE+OO 1.40E+03 I-130 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-131 6.05E+06 6.08E+06 3.46E+06 2.01E+09 9.99E+06 O.OOE+OO 5.42E+05 I-132 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-133 8.49E-14 1.06E-13 4.02E-14 1.97E-ll 1.77E-13 O.OOE+OO 4.28E-14 I-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-135 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-134 1.46E+10 2.40E+10 5.06E+09 O.OOE+OO 7.43E+09 2.67E+09 1.29E+08 Cs-134m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-136 3.33E+07 9.14E+07 5.92E+07 O.OOE+OO 4.87E+07 7.26E+06 3.21E+06 Cs-137 2.34E+10 2.24E+10 3.31E+09 O.OOE+OO 7.31E+09 2.63E+09 1.41E+08 Page 108 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-17 Rio, PRODUCE PATHWAY DOSE FACTORS -CHILD NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-140 1.05E+08 9.16E+04 6.10E+06 O.OOE+OO 2.98E+04 5.46E+04 5.29E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 1.28E-06 4.49E-07 1.51E-07 O.OOE+OO O.OOE+OO O.OOE+OO 1.25E-02 La-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ce-141 5.25E+05 2.62E+05 3.89E+04 O.OOE+OO 1.15E+05 O.OOE+OO 3.27E+08 Ce-143 3.30E-09 1.79E-06 2.59E-10 O.OOE+OO 7.51E-10 O.OOE+OO 2.62E-05 Ce-144 1.13E+08 3.55E+07 6.04E+06 O.OOE+OO 1.96E+07 O.OOE+OO 9.25E+09 Pr-143 6.21E+04 1.87E+04 3.08E+03 O.OOE+OO 1.01E+04 O.OOE+OO 6.70E+07 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 1.91E+04 1.55E+04 1.20E+03 O.OOE+OO 8.51E+03 O.OOE+OO 2.46E+07 Eu-152 4.06E+07 7.40E+06 8.78E+06 O.OOE+OO 3.12E+07 O.OOE+OO 1.22E+09 W-187 1.43E-12 8.49E-13 3.81E-13 O.OOE+OO O.OOE+OO O.OOE+OO 1.22E-10 U-235 2.30E+11 O.OOE+OO 1.39E+ 10 O.OOE+OO 3.78E+10 O.OOE+OO 5.41E+09 U-238 2.20E+ 11 O.OOE+OO 1.31E+10 O.OOE+OO 3.53E+10 O.OOE+OO 3.81E+09 Np-239 1.12E-03 8.01E-05 5.63E-05 O.OOE+OO 2.32E-04 O.OOE+OO 5.93E+OO Am-241 9.38E+10 4.20E+ 10 6.69E+09 O.OOE+OO 4.09E+10 O.OOE+OO 5.01E+09 Page 109 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-18 Rio, LEAFY VEGETABLE PATHWAY DOSE FACTORS- ADULT {m 2 -mrem/yr per J..LCi/s (mrem/~r per p,Ci/m 3 for 3H-3 and 14 C)} NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 2.61£+02 2.61£+02 2.61£+02 2.61£+02 2.61£+02 2.61£+02 C-14 1.25£+05 2.50£+04 2.50£+04 2.50£+04 2.50£+04 2.50£+04 2.50£+04 F-18 4.24£+00 O.OOE+OO 4.71£-01 O.OOE+OO O.OOE+OO O.OOE+OO 1.26£-01 Na-22 2.10£+08 2.10£+08 2.10£+08 2.10£+08 2.10£+08 2.10£+08 2.10£+08 Na-24 2.66£+05 2.66£+05 2.66£+05 2.66£+05 2.66£+05 2.66£+05 2.66£+05 Sc-46 5.07£+04 9.84£+04 2.86£+04 O.OOE+OO 9.19£+04 O.OOE+OO 4.79£+08 P-32 1.13£+09 7.03£+07 4.37£+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.27£+08 Cr-51 O.OOE+OO O.OOE+OO 1.90£+04 1.14£+04 4.19£+03 2.53£+04 4.79£+06 Mn-54 O.OOE+OO 4.79£+07 9.15£+06 O.OOE+OO 1.43£+07 O.OOE+OO 1.47£+08 Mn-56 O.OOE+OO 1.54£+01 2.74£+00 O.OOE+OO 1.96£+01 O.OOE+OO 4.92£+02 Fe-55 2.88£+07 1.99£+07 4.65£+06 O.OOE+OO O.OOE+OO 1.11£+07 1.14£+07 Fe-59 3.56£+07 8.36£+07 3.21£+07 O.OOE+OO O.OOE+OO 2.34£+07 2.79£+08 Co-57 O.OOE+OO 1.79£+06 2.97£+06 O.OOE+OO O.OOE+OO O.OOE+OO 4.54£+07 Co-58 O.OOE+OO 6.70£+06 1.50£+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.36£+08 Co-60 O.OOE+OO 2.36£+07 5.21£+07 O.OOE+OO O.OOE+OO O.OOE+OO 4.44£+08 Ni-63 1.67£+09 1.16£+08 5.61£+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.42£+07 Ni-65 5.91£+01 7.68£+00 3.51£+00 O.OOE+OO O.OOE+OO O.OOE+OO 1.95£+02 Cu-64 O.OOE+OO 9.19£+03 4.31£+03 O.OOE+OO 2.32£+04 O.OOE+OO 7.84£+05 Zn-65 6.44£+07 2.05£+08 9.26£+07 O.OOE+OO 1.37£+08 O.OOE+OO 1.29£+08 Zn-69m 2.27£+04 5.44£+04 4.98£+03 O.OOE+OO 3.30£+04 O.OOE+OO 3.32£+06 Zn-69 5.89£-06 1.13£-05 7.83£-07 O.OOE+OO 7.31£-06 O.OOE+OO 1.69£-06 As-76 1.76£+05 5.11£+05 2.55£+06 1.53£+05 6.22£+05 1.60£+05 2.23£+07 Br-82 O.OOE+OO O.OOE+OO 1.55£+06 O.OOE+OO O.OOE+OO O.OOE+OO 1.78£+06 Br-83 O.OOE+OO O.OOE+OO 3.21£+00 O.OOE+OO O.OOE+OO O.OOE+OO 4.62£+00 Br-84 O.OOE+OO O.OOE+OO 2.21£-11 O.OOE+OO O.OOE+OO O.OOE+OO 1.73£-16 Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.31£+08 6.09£+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.58£+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 2.61£+09 O.OOE+OO 7.48£+07 O.OOE+OO O.OOE+OO O.OOE+OO 4.18£+08 Sr-90 1.08£+11 O.OOE+OO 2.17£+09 O.OOE+OO O.OOE+OO O.OOE+OO 2.71£+09 Sr-91 3.02£+05 O.OOE+OO 1.22£+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.44£+06 Sr-92 4.15£+02 O.OOE+OO 1.79£+01 O.OOE+OO O.OOE+OO O.OOE+OO 8.22£+03 Y-90 1.33£+04 O.OOE+OO 3.56£+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.41£+08 Y-91m 4.74£-09 O.OOE+OO 1.83£-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.39£-08 Y-91 1.22£+06 O.OOE+OO 3.28£+04 O.OOE+OO O.OOE+OO O.OOE+OO 6.74£+08 Y-92 8.96£-01 O.OOE+OO 2.62£-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.57£+04 Page 110 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-18 Rio, LEAFY VEGETABLE PATHWAY DOSE FACTORS- ADULT NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Y-93 1.73E+02 O.OOE+OO 4.77E+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.48E+06 Zr-95 2.68E+05 8.60E+04 5.82E+04 O.OOE+OO 1.35E+05 O.OOE+OO 2.73E+08 Zr-97 3.32E+02 6.70E+01 3.06E+01 O.OOE+OO 1.01E+02 O.OOE+OO 2.07E+07 Nb-95 4.79E+04 2.67E+04 1.43E+04 O.OOE+OO 2.64E+04 O.OOE+OO 1.62E+08 Nb-97 2.84E-06 7.19E-07 2.63E-07 O.OOE+OO 8.39E-07 O.OOE+OO 2.65E-03 Mo-99 O.OOE+OO 6.17E+06 1.17E+06 O.OOE+OO 1.40E+07 O.OOE+OO 1.43E+07 Tc-99m 3.08E+OO 8.69E+OO 1.11E+02 O.OOE+OO 1.32E+02 4.26E+OO 5.14E+03 Tc-99 5.27E+06 7.84E+06 2.12E+06 O.OOE+OO 9.86E+07 6.66E+05 2.56E+08 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 1.48E+06 O.OOE+OO 6.38E+05 O.OOE+OO 5.66E+06 O.OOE+OO 1.73E+08 Ru-105 5.30E+01 O.OOE+OO 2.09E+01 O.OOE+OO 6.85E+02 O.OOE+OO 3.24E+04 Ru-106 2.99E+07 O.OOE+OO 3.78E+06 O.OOE+OO 5.77E+07 O.OOE+OO 1.94E+09 Rh-105 1.29E+05 9.41E+04 6.20E+04 O.OOE+OO 4.00E+05 O.OOE+OO 1.50E+07 Ag-110m 1.81E+06 1.68E+06 9.96E+05 O.OOE+OO 3.30E+06 O.OOE+OO 6.84E+08 Sn-113 9.20E+06 1.56E+06 2.58E+07 8.14E+05 2.12E+06 9.56E+05 2.83E+08 Sn-117m 9.66E+06 3.29E+05 1.37E+07 6.57E+04 5.03E+05 1.04E+05 1.55E+08 Sb-122 9.39E+05 5.17E+05 8.87E+06 1.10E+05 3.65E+05 1.41E+05 9.39E+07 Sb-124 2.45E+07 4.63E+05 9.71E+06 5.94E+04 O.OOE+OO 1.91E+07 6.96E+08 Sb-125 1.94E+07 2.17E+05 4.61E+06 1.97E+04 O.OOE+OO 1.49E+07 2.13E+08 Te-125m 2.99E+07 1.08E+07 4.00E+06 8.98E+06 1.21E+08 O.OOE+OO 1.19E+08 Te-127m 9.59E+07 3.43E+07 1.17E+07 2.45E+07 3.90E+08 O.OOE+OO 3.22E+08 Te-127 6.01E+03 2.16E+03 1.30E+03 4.46E+03 2.45E+04 O.OOE+OO 4.75E+05 Te-129m 1.04E+08 3.87E+07 1.64E+07 3.57E+07 4.33E+08 O.OOE+OO 5.23E+08 Te-129 7.52E-04 2.83E-04 1.83E-04 5.77E-04 3.16E-03 O.OOE+OO 5.68E-04 Te-131m 1.08E+06 5.27E+05 4.39E+05 8.34E+05 5.34E+06 O.OOE+OO 5.23E+07 Te-131 1.32E-15 5.49E-16 4.15E-16 l.OSE-15 5.76E-15 O.OOE+OO 1.86E-16 Te-132 4.50E+06 2.91E+06 2.73E+06 3.21E+06 2.80E+07 O.OOE+OO 1.38E+08 I-130 1.95E+05 5.75E+05 2.27E+05 4.87E+07 8.98E+05 O.OOE+OO 4.95E+05 I-131 3.88E+07 5.55E+07 3.18E+07 1.82E+10 9.51E+07 O.OOE+OO 1.46E+07 I-132 2.59E+01 6.93E+01 2.42E+01 2.42E+03 1.10E+02 O.OOE+OO 1.30E+01 I-133 1.04E+06 1.81E+06 5.51E+05 2.66E+08 3.15E+06 O.OOE+OO 1.62E+06 I-134 4.42E-05 1.20E-04 4.30E-05 2.08E-03 1.91E-04 O.OOE+OO 1.05E-07 I-135 1.89E+04 4.94E+04 1.82E+04 3.26E+06 7.92E+04 O.OOE+OO 5.58E+04 Cs-134 6.64E+08 1.58E+09 1.29E+09 O.OOE+OO 5.11E+08 1.70E+08 2.76E+07 Cs-134m 6.57E+OO 1.38E+01 7.06E+OO O.OOE+OO 7.50E+OO 1.18E+OO 4.87E+OO Cs-136 3.34E+07 1.32E+08 9.49E+07 O.OOE+OO 7.33E+07 1.00E+07 1.50E+07 Cs-137 9.29E+08 1.27E+09 8.32E+08 O.OOE+OO 4.31E+08 1.43E+08 2.46E+07 Page 111 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-18 Rio, LEAFY VEGETABLE PATHWAY DOSE FACTORS -ADULT NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Cs-138 3.39E-11 6.70E-11 3.32E-11 O.OOE+OO 4.92E-11 4.86E-12 2.86E-16 Ba-139 2.99E-02 2.13E-05 8.77E-04 O.OOE+OO 1.99E-05 1.21E-05 5.31E-02 Ba-140 1.02E+08 1.28E+05 6.70E+06 O.OOE+OO 4.36E+04 7.35E+04 2.10E+08 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 1.98E+03 9.97E+02 2.63E+02 O.OOE+OO O.OOE+OO O.OOE+OO 7.32E+07 La-142 1.33E-04 6.04E-05 1.50E-05 O.OOE+OO O.OOE+OO O.OOE+OO 4.41E-01 Ce-141 7.05E+04 4.77E+04 5.41£+03 O.OOE+OO 2.22E+04 O.OOE+OO 1.82E+08 Ce-143 9.98E+02 7.38E+05 8.16E+01 O.OOE+OO 3.25E+02 O.OOE+OO 2.76E+07 Ce-144 4.96£+06 2.08E+06 2.67E+05 O.OOE+OO 1.23E+06 O.OOE+OO 1.68E+09 Pr-143 4.80E+04 1.92E+04 2.38E+03 O.OOE+OO 1.11E+04 O.OOE+OO 2.10E+08 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 2.90E+04 3.35E+04 2.00E+03 O.OOE+OO 1.96E+04 O.OOE+OO 1.61E+08 Eu-152 2.12£+06 4.79E+05 4.21E+05 O.OOE+OO 2.97E+06 O.OOE+OO 2.76E+08 W-187 3.81£+04 3.19E+04 1.11E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.04E+07 U-235 8.74E+09 O.OOE+OO 5.30E+08 O.OOE+OO 2.04E+09 O.OOE+OO 8.52E+08 U-238 8.37£+09 O.OOE+OO 4.95E+08 O.OOE+OO 1.91E+09 O.OOE+OO 6.00E+08 Np-239 1.43E+03 1.40E+02 7.73E+01 O.OOE+OO 4.37E+02 O.OOE+OO 2.88E+07 Am-241 8.70E+09 3.06E+09 5.75E+08 O.OOE+OO 4.33E+09 O.OOE+OO 7.89E+08 Page 112 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-19 Rio, LEAFY VEGETABLE PATHWAY DOSE FACTORS- TEEN 3 for 3H-3 and 14 {m 2-mrem/yr per J..LCi/s (mrem/vr per ~tCilm C)} NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 1.73E+02 1.73E+02 1.73E+02 1.73E+02 1.73E+02 1.73E+02 C-14 1.17E+05 2.34E+04 2.34E+04 2.34E+04 2.34E+04 2.34E+04 2.34E+04 F-18 3.86E+OO O.OOE+OO 4.23E-01 O.OOE+OO O.OOE+OO O.OOE+OO 3.47E-01 Na-22 1.85E+08 1.85E+08 1.85E+08 1.85E+08 1.85E+08 1.85E+08 1.85E+08 Na-24 2.37E+05 2.37E+05 2.37E+05 2.37E+05 2.37E+05 2.37E+05 2.37E+05 Sc-46 4.37E+04 8.51E+04 2.52E+04 O.OOE+OO 8.15E+04 O.OOE+OO 2.90E+08 P-32 1.06E+09 6.57E+07 4.11E+07 O.OOE+OO O.OOE+OO O.OOE+OO 8.91E+07 Cr-51 O.OOE+OO O.OOE+OO 1.69E+04 9.39E+03 3.70E+03 2.41E+04 2.84E+06 Mn-54 O.OOE+OO 4.06E+07 8.05E+06 O.OOE+OO 1.21E+07 O.OOE+OO 8.33E+07 Mn-56 O.OOE+OO 1.39E+01 2.47E+OO O.OOE+OO 1.76E+01 O.OOE+OO 9.16E+02 Fe-55 2.60E+07 1.84E+07 4.30E+06 O.OOE+OO O.OOE+OO 1.17E+07 7.98E+06 Fe-59 3.16E+07 7.37E+07 2.85E+07 O.OOE+OO O.OOE+OO 2.32E+07 1.74E+08 Co-57 O.OOE+OO 1.60E+06 2.67E+06 O.OOE+OO O.OOE+OO O.OOE+OO 2.98E+07 Co-58 O.OOE+OO 5.74E+06 1.32E+07 O.OOE+OO O.OOE+OO O.OOE+OO 7.91E+07 Co-60 O.OOE+OO 2.04E+07 4.59E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.65E+08 Ni-63 1.50E+09 1.06E+08 5.07E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.68E+07 Ni-65 5.51E+01 7.03E+OO 3.21E+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.82E+02 Cu-64 O.OOE+OO 8.33E+03 3.92E+03 O.OOE+OO 2.11E+04 O.OOE+OO 6.46E+05 Zn-65 5.03E+07 1.75E+08 8.15E+07 O.OOE+OO 1.12E+08 O.OOE+OO 7.40E+07 Zn-69m 2.10E+04 4.96E+04 4.54E+03 O.OOE+OO 3.01E+04 O.OOE+OO 2.72E+06 Zn-69 5.51E-06 1.05E-05 7.35E-07 O.OOE+OO 6.86E-06 O.OOE+OO 1.93E-05 As-76 1.36E+05 4.29E+05 2.09E+06 1.26E+05 5.03E+05 1.26E+05 1.89E+07 Br-82 O.OOE+OO O.OOE+OO 1.37E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO 3.01E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 2.01E-11 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.21E+08 5.69E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.79E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 2.44E+09 O.OOE+OO 7.00E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.91E+08 Sr-90 8.29E+10 O.OOE+OO 1.66E+09 O.OOE+OO O.OOE+OO O.OOE+OO 2.57E+09 Sr-91 2.83E+05 O.OOE+OO 1.12E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.28E+06 Sr-92 3.86E+02 O.OOE+OO 1.65E+01 O.OOE+OO O.OOE+OO O.OOE+OO 9.84E+03 Y-90 1.24E+04 O.OOE+OO 3.34E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E+08 Y-91m 4.41E-09 O.OOE+OO 1.69E-10 O.OOE+OO O.OOE+OO O.OOE+OO 2.08E-07 Y-91 1.15E+06 O.OOE+OO 3.07E+04 O.OOE+OO O.OOE+OO O.OOE+OO 4.70E+08 Y-92 8.42E-01 O.OOE+OO 2.43E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.31E+04 Page 113 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-19 Ria, LEAFY VEGETABLE PATHWAY DOSE FACTORS -TEEN NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Y-93 1.62E+02 O.OOE+OO 4.44E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.95E+06 Zr-95 2.39E+05 7.53E+04 5.18E+04 O.OOE+OO 1.11E+05 O.OOE+OO 1.74E+08 Zr-97 3.07E+02 6.08E+01 2.80E+01 O.OOE+OO 9.22E+01 O.OOE+OO 1.65E+07 Nb-95 4.16E+04 2.31E+04 1.27E+04 O.OOE+OO 2.24E+04 O.OOE+OO 9.86E+07 Nb-97 2.64E-06 6.55E-07 2.39E-07 O.OOE+OO 7.65E-07 O.OOE+OO 1.56E-02 Mo-99 O.OOE+OO 5.67E+06 1.08E+06 O.OOE+OO 1.30E+07 O.OOE+OO 1.02E+07 Tc-99m 2.71E+OO 7.57E+OO 9.81E+01 O.OOE+OO 1.13E+02 4.20E+OO 4.97E+03 Tc-99 4.95E+06 7.28E+06 1.98E+06 O.OOE+OO 9.24E+07 7.52E+05 1.78E+08 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 1.34E+06 O.OOE+OO 5.73E+05 O.OOE+OO 4.73£+06 O.OOE+OO 1.12E+08 Ru-105 4.93E+01 O.OOE+OO 1.91E+01 O.OOE+OO 6.22E+02 O.OOE+OO 3.98E+04 Ru-106 2.80E+07 O.OOE+OO 3.52E+06 O.OOE+OO 5.39E+07 O.OOE+OO 1.34E+09 Rh-105 1.21E+05 8.73E+04 5.72E+04 O.OOE+OO 3.71E+05 O.OOE+OO 1.11E+07 Ag-110m 1.52E+06 1.44E+06 8.78E+05 O.OOE+OO 2.75E+06 O.OOE+OO 4.05E+08 Sn-113 6.50E+06 1.30E+06 2.14E+07 6.27E+05 1.70E+06 7.66E+05 2.30E+08 Sn-117m 6.47E+06 2.79E+05 1.12E+07 5.20E+04 3.93E+05 9.51E+04 1.26E+08 Sb-122 6.51E+05 4.45E+05 7.19£+06 8.90E+04 2.91E+05 1.20E+05 7.53E+07 Sb-124 2.22E+07 4.09E+05 8.67E+06 5.04E+04 O.OOE+OO 1.94E+07 4.48E+08 Sb-125 1.76E+07 1.93E+05 4.12E+06 1.68E+04 O.OOE+OO 1.55E+07 1.37E+08 Te-125m 2.80E+07 1.01E+07 3.74E+06 7.83E+06 O.OOE+OO O.OOE+OO 8.26E+07 Te-127m 8.99E+07 3.19E+07 1.07E+07 2.14E+07 3.65E+08 O.OOE+OO 2.24E+08 Te-127 5.67E+03 2.01E+03 1.22E+03 3.91E+03 2.30E+04 O.OOE+OO 4.38£+05 Te-129m 9.66E+07 3.59E+07 1.53E+07 3.12E+07 4.04E+08 O.OOE+OO 3.63E+08 Te-129 7.04E-04 2.63E-04 1.71E-04 5.03E-04 2.96E-03 O.OOE+OO 3.85E-03 Te-131m 9.97E+05 4.78E+05 3.99E+05 7.19E+05 4.99E+06 O.OOE+OO 3.84E+07 Te-131 1.22E-15 5.04E-16 3.82E-16 9.42E-16 5.34E-15 O.OOE+OO l.OOE-16 Te-132 4.09E+06 2.59E+06 2.44E+06 2.73E+06 2.48E+07 O.OOE+OO 8.20E+07 I-130 1.74E+05 5.04E+05 2.01E+05 4.11E+07 7.77E+06 O.OOE+OO 3.88E+05 I-131 3.58E+07 5.01E+07 2.69E+07 1.46E+10 8.63E+07 O.OOE+OO 9.92E+06 I-132 2.34E+01 6.11E+01 2.19E+01 2.06E+03 9.63E+01 O.OOE+OO 2.66E+01 I-133 9.65E+05 1.64E+06 4.99E+05 2.29E+08 2.87E+06 O.OOE+OO 1.24E+06 I-134 4.00E-05 1.06E-04 3.80E-05 1.77E-03 1.67E-04 O.OOE+OO 1.40E-06 I-135 1.70E+04 4.39E+04 1.63E+04 2.82E+06 6.93E+04 O.OOE+OO 4.86E+04 Cs-134 5.86E+08 1.38E+09 6.40E+08 O.OOE+OO 4.39E+08 1.67E+08 1.72E+07 Cs-134m 5.95E+OO 1.23E+01 6.34E+OO O.OOE+OO 6.86E+OO 1.20E+OO 8.20E+OO Cs-136 2.89E+07 1.14E+08 7.64E+07 O.OOE+OO 6.19E+07 9.76E+06 9.15E+06 Cs-137 8.56E+08 1.14E+09 3.97E+08 O.OOE+OO 3.88E+08 1.51E+08 1.62E+07 Page 114 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-19 Ria, LEAFY VEGETABLE PATHWAY DOSE FACTORS -TEEN NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Cs-138 3.13E-11 6.01E-11 3.01E-11 O.OOE+OO 4.44E-11 5.16E-12 2.73E-14 Ba-139 2.82E-02 1.98E-05 8.20E-04 O.OOE+OO 1.87E-05 1.37E-05 2.51E-01 Ba-140 9.38E+07 1.15E+05 6.05E+06 O.OOE+OO 3.90E+04 7.73E+04 1.45E+08 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 1.81E+03 8.88E+02 2.36E+02 O.OOE+OO O.OOE+OO O.OOE+OO 5.10E+07 La-142 1.22E-04 5.41E-05 1.35E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.65E+OO Ce-141 6.58E+04 4.39E+04 5.04E+03 O.OOE+OO 2.07E+04 O.OOE+OO 1.26E+08 Ce-143 9.32E+02 6.79E+05 7.58E+01 O.OOE+OO 3.04E+02 O.OOE+OO 2.04E+07 Ce-144 4.65E+06 1.92E+06 2.50E+05 O.OOE+OO 1.15E+06 O.OOE+OO 1.17E+09 Pr-143 4.48E+04 1.79E+04 2.23E+03 O.OOE+OO 1.04E+04 O.OOE+OO 1.47E+08 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 2.83E+04 3.08E+04 1.85E+03 O.OOE+OO 1.81E+04 O.OOE+OO 1.11E+08 Eu-152 1.73E+06 4.17E+05 3.68E+05 O.OOE+OO 1.94E+06 O.OOE+OO 1.54E+08 W-187 3.55E+04 2.89E+04 1.01E+04 O.OOE+OO O.OOE+OO O.OOE+OO 7.82E+06 U-235 8.16E+09 O.OOE+OO 4.97E+08 O.OOE+OO 1.91E+09 O.OOE+OO 5.93E+08 U-238 7.81E+09 O.OOE+OO 4.65E+08 O.OOE+OO 1.79E+09 O.OOE+OO 4.17E+08 Np-239 1.38E+03 1.31E+02 7.25E+01 O.OOE+OO 4.10E+02 O.OOE+OO 2.10E+07 Am-241 6.01E+09 2.29E+09 4.01E+08 O.OOE+OO 3.01E+09 O.OOE+OO 5.49E+08 Page 115 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-20 Rio, LEAFY VEGETABLE PATHWAY DOSE FACTORS -CHILD {m 2-mrem/yr per f.!Ci/s (mrem/vr per ,._ci/m 3 for 3H-3 and 14 C)} NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 2.06E+02 2.06E+02 2.06E+02 2.06E+02 2.06E+02 2.06E+02 C-14 2.16E+05 4.33E+04 4.33E+04 4.33E+04 4.33E+04 4.33E+04 4.33E+04 F-18 6.88E+OO O.OOE+OO 6.83E-01 O.OOE+OO O.OOE+OO O.OOE+OO 1.86E+OO Na-22 2.88E+08 2.88E+08 2.88E+08 2.88E+08 2.88E+08 2.88E+08 2.88E+08 Na-24 3.69E+05 3.69E+05 3.69E+05 3.69E+05 3.69E+05 3.69E+05 3.69E+05 Sc-46 7.36E+04 1.01E+05 3.89E+04 O.OOE+OO 8.93E+04 O.OOE+OO 1.48E+08 P-32 1.96E+09 9.18E+07 7.56E+07 O.OOE+OO O.OOE+OO O.OOE+OO 5.42E+07 Cr-51 O.OOE+OO O.OOE+OO 2.59E+04 1.44E+04 3.92E+03 2.62E+04 1.37E+06 Mn-54 O.OOE+OO 4.56E+07 1.21E+07 O.OOE+OO 1.28E+07 O.OOE+OO 3.83E+07 Mn-56 O.OOE+OO 1.82E+01 4.11E+OO O.OOE+OO 2.20E+01 O.OOE+OO 2.64E+03 Fe-55 4.90E+07 2.60E+07 8.05E+06 O.OOE+OO O.OOE+OO 1.47E+07 4.81E+06 Fe-59 5.50E+07 8.89E+07 4.43E+07 O.OOE+OO O.OOE+OO 2.58E+07 9.26E+07 Co-57 O.OOE+OO 2.05E+06 4.14E+06 O.OOE+OO O.OOE+OO O.OOE+OO 1.68E+07 Co-58 O.OOE+OO 6.58E+06 2.01E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.84E+07 Co-60 O.OOE+OO 2.37E+07 7.00E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.31E+08 Ni-63 2.81E+09 1.51E+08 9.57E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.01E+07 Ni-65 1.01E+02 9.51E+OO 5.55E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.16E+03 Cu-64 O.OOE+OO 1.10E+04 6.64E+03 O.OOE+OO 2.65E+04 O.OOE+OO 5.16E+05 Zn-65 7.41E+07 1.97E+08 1.23E+08 O.OOE+OO 1.24E+08 O.OOE+OO 3.47E+07 Zn-69m 3.85E+04 6.56E+04 7.75E+03 O.OOE+OO 3.81E+04 O.OOE+OO 2.14E+06 Zn-69 1.02E-05 1.47E-05 1.36E-06 O.OOE+OO 8.91E-06 O.OOE+OO 9.26E-04 As-76 2.33E+05 6.48E+05 3.76E+06 2.20E+05 7.13E+05 2.20E+05 3.37E+07 Br-82 O.OOE+OO O.OOE+OO 2.10E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO 5.55E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 3.41E-11 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.69E+08 1.04E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.08E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 4.54E+09 O.OOE+OO 1.30E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.76E+08 Sr-90 1.29E+11 O.OOE+OO 2.59E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.15E+09 Sr-91 5.20E+05 O.OOE+OO 1.96E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.15E+06 Sr-92 7.08E+02 O.OOE+OO 2.84E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.34E+04 Y-90 2.30E+04 O.OOE+OO 6.17E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.56E+07 Y-91m 8.09E-09 O.OOE+OO 2.940E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.58E-05 Y-91 2.12E+06 O.OOE+OO 5.68E+04 O.OOE+OO O.OOE+OO O.OOE+OO 2.83E+08 Y-92 1.55E+OO O.OOE+OO 4.44E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.48E+04 Page 116 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-20 Ria, LEAFY VEGETABLE PATHWAY DOSE FACTORS- CHILD NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Y-93 2.98E+02 O.OOE+OO 8.19E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.45E+06 Zr-95 4.16E+05 9.14E+04 8.14E+04 O.OOE+OO 1.31E+05 O.OOE+OO 9.54E+07 Zr-97 5.61E+02 8.11E+01 4.78E+01 O.OOE+OO 1.16E+02 O.OOE+OO 1.23E+07 Nb-95 7.05E+04 2.74E+04 1.96E+04 O.OOE+OO 2.58E+04 O.OOE+OO 5.07E+07 Nb-97 4.80E-06 8.68E-07 4.05E-07 O.OOE+OO 9.63E-07 O.OOE+OO 2.68E-01 Mo-99 O.OOE+OO 7.74E+06 1.91E+06 O.OOE+OO 1.65E+07 O.OOE+OO 6.40E+06 Tc-99m 4.67E+OO 9.16E+OO 1.52E+02 O.OOE+OO 1.33E+02 4.65E+OO 5.21E+03 Tc-99 9.16E+06 1.02E+07 3.66E+06 O.OOE+OO 1.20E+08 9.00E+05 1.07E+08 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 2.38E+06 O.OOE+OO 9.14E+05 O.OOE+OO 5.99E+06 O.OOE+OO 6.15E+07 Ru-105 9.02E+01 O.OOE+OO 3.27E+01 O.OOE+OO 7.93E+02 O.OOE+OO 5.89E+04 Ru-106 5.17E+07 O.OOE+OO 6.45E+06 O.OOE+OO 6.98E+07 O.OOE+OO 8.04E+08 Rh-105 2.22E+05 1.19E+05 1.02E+05 O.OOE+OO 4.75E+05 O.OOE+OO 7.39E+06 Ag-110m 2.48E+06 1.68E+06 1.34E+06 O.OOE+OO 3.12E+06 O.OOE+OO 1.99E+08 Sn-113 1.14E+07 2.44E+06 3.74E+07 9.78E+05 2.59E+06 1.22E+06 4.17E+08 Sn-117m 1.26E+07 5.97E+05 1.96E+07 9.42E+04 6.05E+05 1.73E+05 2.28E+08 Sb-122 1.17E+06 7.00E+05 1.29E+07 1.53E+05 4.24E+05 1.99E+05 1.40E+08 Sb-124 3.95E+07 5.12E+05 1.38E+07 8.71E+04 O.OOE+OO 2.19E+07 2.47E+08 Sb-125 3.15E+07 2.43E+05 6.60E+06 2.92E+04 O.OOE+OO 1.76E+07 7.52E+07 Te-125m 5.16E+07 1.40E+07 6.88E+06 1.45E+07 O.OOE+OO O.OOE+OO 4.98E+07 Te-127m 1.66E+08 4.48E+07 1.97E+07 3.98E+07 4.74E+08 O.OOE+OO 1.35E+08 Te-127 1.05E+04 2.82E+03 2.24E+03 7.24E+03 2.98E+04 O.OOE+OO 4.09E+05 Te-129m 1.79E+08 4.99E+07 2.77E+07 5.76E+07 5.25E+08 O.OOE+OO 2.18E+08 Te-129 1.30E-03 3.64E-04 3.09E-04 9.30E-04 3.81E-03 O.OOE+OO 8.12E-02 Te-131m 1.82E+06 6.30E+05 6.70E+05 1.30E+06 6.10E+06 O.OOE+OO 2.56E+07 Te-131 2.25E-15 6.86E-16 6.70E-16 1.72E-15 6.81E-15 O.OOE+OO 1.18E-14 Te-132 7.32E+06 3.24E+06 3.91E+06 4.72E+06 3.01E+07 O.OOE+OO 3.26E+07 I-130 3.06E+05 6.18E+05 3.19E+05 6.81E+07 9.24E+05 O.OOE+OO 2.89E+05 I-131 6.52E+07 6.56E+07 3.73E+07 2.17E+10 1.08E+08 O.OOE+OO 5.84E+06 I-132 4.15E+01 7.62E+01 3.50E+01 3.54E+03 1.17E+02 O.OOE+OO 8.97E+01 I-133 1.76E+06 2.18E+06 8.23E+05 4.04E+08 3.63E+06 O.OOE+OO 8.77E+05 I-134 7.10E-05 1.32E-04 6.07E-05 3.03E-03 2.02E-04 O.OOE+OO 8.74E-05 I-135 3.03E+04 5.45E+04 2.58E+04 4.83E+06 8.35E+04 O.OOE+OO 4.15E+04 Cs-134 1.01E+09 1.67E+09 3.51E+08 O.OOE+OO 5.16E+08 1.85E+08 8.98E+06 Cs-134m 1.06E+01 1.57E+01 1.02E+01 O.OOE+OO 8.26E+OO 1.37E+OO 1.98E+01 Cs-136 4.90E+07 1.35E+08 8.71E+07 O.OOE+OO 7.17E+07 1.07E+07 4.73E+06 Cs-137 1.55E+09 1.48E+09 2.19E+08 O.OOE+OO 4.83E+08 1.74E+08 9.28E+06 Cs-138 5.69E-ll 7.92E-11 5.02E-ll O.OOE+OO 5.57E-11 5.99E-12 3.65E-11 Page 117 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-20 Ria, LEAFY VEGETABLE PATHWAY DOSE FACTORS -CHILD NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Ba-139 5.19E-02 2.77E-05 1.50E-03 O.OOE+OO 2.42E-05 1.63E-05 3.00E+OO Ba-140 1.70E+08 1.49E+05 9.92E+06 O.OOE+OO 4.85E+04 8.88E+04 8.61E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 3.25E+03 1.13E+03 3.82E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.16E+07 La-142 2.21E-04 7.04E-05 2.20E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.39E+01 Ce-141 1.22E+05 6.06E+04 9.00E+03 O.OOE+OO 2.66E+04 O.OOE+OO 7.56E+07 Ce-143 1.72E+03 9.31E+05 1.35E+02 O.OOE+OO 3.91E+02 O.OOE+OO 1.36E+07 Ce-144 8.60E+06 2.69E+06 4.59E+05 O.OOE+OO 1.49E+06 O.OOE+OO 7.03E+08 Pr-143 8.32E+04 2.50E+04 4.13E+03 O.OOE+OO 1.35E+04 O.OOE+OO 8.97E+07 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 5.22E+04 4.23E+04 3.27E+03 O.OOE+OO 2.32E+04 O.OOE+OO 6.70E+07 Eu-152 2.69E+06 4.91E+05 5.83E+05 O.OOE+OO 2.07E+06 O.OOE+OO 8.06E+07 W-187 6.45E+04 3.82E+04 1.71E+04 O.OOE+OO O.OOE+OO O.OOE+OO 5.37E+06 U-235 1.52E+10 O.OOE+OO 9.18E+08 O.OOE+OO 2.49E+09 O.OOE+OO 3.56E+08 U-238 1.45E+10 O.OOE+OO 8.60E+08 O.OOE+OO 2.32E+09 O.OOE+OO 2.51E+08 Np-239 2.56E+03 1.84E+02 1.29E+02 O.OOE+OO 5.31E+02 O.OOE+OO 1.36E+07 Am-241 6.17E+09 2.76E+09 4.40E+08 O.OOE+OO 2.69E+09 O.OOE+OO 3.30E+08 Page 118 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 10-21 Rio, GROUND PLANE PATHWAY DOSE FACTORS (m 2-mrem/vrper j..t.Ci/s TOTAL TOTAL TOTAL NUCLIDE BODY NUCLIDE BODY NUCLIDE BODY AND AND AND ORGANS

ORGANS ORGANS H-3 O.OOE+OO Y-90 4.49E+03 I-132 1.24E+06 C-14 O.OOE+OO Y-91m l.OOE+05 I-133 2.45E+06 F-18 7.87E+05 Y-91 1.07E+06 I-134 4.47E+05 Na-22 2.00E+10 Y-92 1.81E+05 I-135 2.51E+06 Na-24 1.19E+07 Y-93 1.85E+05 Cs-134 6.88E+09 Sc-46 1.65E+09 Zr-95 2.45E+08 Cs-134m 3.19E+04 P-32 O.OOE+OO Zr-97 2.94E+06 Cs-136 1.51E+08 Cr-51 4.66E+06 Nb-95 1.36E+08 Cs-137 1.03E+ 10 Mn-54 1.38E+09 Nb-97 3.37E+05 Cs-138 3.59E+05 Mn-56 9.04E+05 Mo-99 3.99E+06 Ba-139 1.07E+05 Fe-55 O.OOE+OO Tc-99m 1.84E+05 Ba-140 2.05E+07 Fe-59 2.72E+08 Tc-99 3.02E+06 Ba-141 4.18E+04 Co-57 3.18E+08 Tc-101 2.04E+04 Ba-142 4.49E+04 Co-58 3.79E+08 Ru-103 1.08E+08 La-140 1.93E+07 Co-60 2.16E+10 Ru-105 6.37E+05 La-142 7.36E+05 Ni-63 O.OOE+OO Ru-106 4.27E+08 Ce-141 1.37E+07 Ni-65 2.97E+05 Rh-105 1.15E+06 Ce-143 2.32E+06 Cu-64 6.07E+05 Ag-110m 3.44E+09 Ce-144 6.97E+07 Zn-65 7.46E+08 Sn-113 2.50E+07 Pr-143 O.OOE+OO Zn-69m 2.41E+06 Sn-117m 2.09E+07 Pr-144 1.84E+03 Zn-69 O.OOE+OO Sb-122 1.21E+07 Nd-147 8.40E+06 As-76 4.74E+06 Sb-124 1.05E+09 Eu-152 2.98E+10 Br-82 3.83E+07 Sb-125 4.27E+09 W-187 2.36E+06 Br-83 4.90E+03 Te-125m 1.55E+06 U-235 5.72E+09 Br-84 2.03E+05 Te-127m 9.17E+04 U-238 2.13E+07 Br-85 O.OOE+OO Te-127 3.00E+03 Np-239 1.71E+06 Rb-86 8.99E+06 Te-129m 1.98E+07 Am-241 1.05E+09 Rb-88 3.29E+04 Te-129 2.62E+04 Rb-89 1.23E+05 Te-131m 8.67E+06 Sr-89 2.16E+04 Te-131 2.92E+04 Sr-90 9.24E+06 Te-132 4.16E+06 Sr-91 2.15E+06 I-130 5.51E+06 Sr-92 7.77E+05 I-131 1.72E+07 Page 119 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 11.0 DETERMINATION OF TOTAL DOSE The purpose of this section is to describe the method used to calculate the cumulative dose contributions from liquid and gaseous effluents in accordance with PBNP Technical Specifications for total dose. This method can also be used to demonstrate compliance with the Environmental Protection Agency (EPA) 40CFR190, "Environmental Standards for the Uranium Fuel Cycle". Compliance with the PBNP Technical Specification dose objectives for the maximum individual demonstrates compliance with the EPA limits to any MEMBER OF THE PUBLIC, since the design dose objectives from 10CFR50, Appendix I are much lower than the 40CFR190 dose limits to the general public. With the calculated doses from the releases of radioactive materials in liquid or gaseous effluents exceeding twice the limits outlined in Sections 6.2.1, 7.2.1 and 7.3.1, a special analysis shall be performed. The purpose of this analysis is to demonstrate if the total dose to any MEMBER OF THE PUBLIC (real individual) from all URANIUM FUEL CYCLE sources (including direct radiation contributions from the reactor units and from outside storage areas and from all real pathways) is limited to less than or equal to 25 mrem per year to the total body or any organ, except the thyroid, which is limited to 75 mrem per year. If required, the total dose to a MEMBER OF THE PUBLIC will be calculated for all significant effluent release points for all real pathways including direct radiation. As necessary, effluent releases from Kewaunee Nuclear Power Plant must also be considered due to its proximity. Calculations will be based on the equations in Sections 9.2, 10.5, 10.6 with the exception that usage factors and other site specific parameters may be modified using more realistic assumptions, where appropriate. The direct radiation component from the facility can be determined using environmental TLD results. These results will be corrected for natural background and for actual occupancy time of any areas accessible to the general public at the location of maximum direct radiation. It is recognized that by including the results from the environmental TLDs into the sum of total dose component, the direct radiation dose may be overestimated. The TLD measurements may include the exposure from noble gases, ground plane deposition, and shoreline deposition, which have already been included in the summation of the significant dose pathways to the general public. However, this conservative method can be used, if required, as well as any other method for estimating the direct radiation dose form contained radioactive sources within the facility. The methodology used to incorporate the direct radiation component into total dose estimates will be outlined whenever total doses are reported. Therefore, the total dose will be determined based on the most realistic site specific data and parameters to assess the real dose to any MEMBER OF THE PUBLIC. Page 120 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 12.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.1 REMP Administration 12.1.1 Definition and Basis 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). The REMP is designed to fulfill the requirements of 10 CPR 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.l.b requires the Offsite Dose Calculation Manual (ODCM) to contain the radiological environmental monitoring activities. 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 ofPBNP operations, and to monitor the efficacy of in plant effluent controls. The REMP, as outlined in Table 12-2 through Table 12-3 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 thermo luminescent 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. 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 offish, 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 in order to monitor the status of radioactivity in fish in the vicinity of Point Beach. 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. Page 121 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 12.1.2 Responsibilities

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

1. Program Scope The scope of the REMP is determined by the cognizant Chemist based on radiological principles for the fulfillment ofPBNP Technical Specifications (TS) and the applicable Federal Regulations. Based on the scope, the ODCM is written to accomplish the collection and analyses of the necessary environmental samples, and 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 ODCM. In order to verify compliance with TS, Nuclear Oversight arranges for program audits and Supplier Assessments of the contracted radioanalyticallaboratory. Chemistry reviews the REMP annually via the Annual Monitoring Report.

2. 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.

3. 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. 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 applicable fleet policies and procedures (LI-AA-102-1001). Page 122 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

4. Data Summary Pursuant toTS 5.6.2, 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.

5. 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.

6. Reportable Items 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 specific to the REMP 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 Table 12-3. (c) New or relocated sampling locations and reason for change; (d) LLDs that are higher than specified in Table 12-1 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 Page 123 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL (f) 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 QA/QC results, in-house blanks, interlaboratory comparisons, etc., shall be submitted to the NRC, via the Annual Monitoring Report.

b. 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.

1. Manual control and distribution The distribution of the PBNP Offsite Dose Calculation Manual is the responsibility of Document Control.

2. 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 functions required for the effective operation of the PBNP Radiological Environmental Monitoring Program. These administrative functions include the following:

(a) Ensuring that samples are obtained in accordance with the type and frequency in Table 12-3 following procedures outlined in this manual; (b) Ensuring adequate sampling supplies and calibrated, functional equipment are available at all times; (c) Ensuring that air sampling pumps are maintained, repaired and calibrated as required and that an adequate number of backup pumps are readily available at all times; Page 124 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL (d) Reporting lost or unavailable samples, as well as other potential deviations from the sampling regime in Table 12-3 will be documented via the radiological environmental sampling checklist forms and Corrective Action Program. Deviations are to be communicated to the cognizant Chemist. (e) As a courtesy to the State of Wisconsin, Point Beach assists in obtaining samples at co-located and other sampling sites (this is not a TS requirement); and (f) Assisting Chemistry, as necessary, with investigations into elevated radioactivity levels in environmental samples. 12.1.3 Quality Assurance I Quality Control Quality assurance is an integral part ofPBNP's Radiological Environmental Monitoring Program. The QATR commits PBNP to Reg. Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operation to License Termination) - Effluent Streams and the Environment. The REMP involves the interaction of Chemistry and the contracted analytical laboratory. 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 carrying out these procedures. An audit of the PBNP Radiological Environmental Monitoring Program and its results shall be completed periodically as a means of monitoring program effectiveness and assuring compliance with program directives. The audit shall be performed in accordance with Section 2.4. Page 125 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 12.2 REMP Implementation 12.2.1 Program Overview

a. 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.

b. 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.

c. Monitoring Sensitivity The effectiveness of the REMP in fulfilling 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.

12.2.2 Program Parameters

a. 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:

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

1. Equipment which has been in the radiologically controlled area, 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.

2. Store sampling equipment in radiologically clean areas only;

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

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

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

6. A void entering contaminated areas prior to collecting environmental samples.

b. 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: 4.66Sb LLD = EX V X 2.22 X Y X e-A.L1T [12-1] Where: LLD = The a priori lower limit of detection in picocuries per unit volume or mass, as applicable sb = The standard deviation of the background counting rate or 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; 2 = 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. Page 127 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Typical values ofE, V, Y, and L1T are used to calculate the LLD. As defined, the LLD is an a priori limit representing the capability of a measuring system and not an a posteriori limit for a particular measurement. The required analysis for each environmental sample and the highest acceptable LLD associated with each analysis are listed in Table 12-1. Whenever LLD values lower than those specified in Table 12-1 are reasonably achievable, the analytical contractor for the radiological environmental samples will do so. When the LLDs listed in Table 12-1 are not achieved, a description of the factors contributing to the higher LLD shall be reported in the next PBNP Annual Monitoring Report.

c. 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 12-1.

1. Regulatory notification levels The regulatory notification levels listed in Table 12-1 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 12-1, 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 12-1 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 of25% 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 12-1. The weighted sum is calculated as follows: concentration (1) concentration (2)

                            +                 l notification level (1) notification evel (2)
                                                        + ... =weighted sum                    [12-2]

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 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 12.1.2.a.3 for notification guidance. This calculation requirement and report is not required if the measured level of radioactivity was not the result of plant effluents.

2. 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.

d. Sampling Locations A list of sampling locations and the corresponding location codes appear in Table 12-2. The locations are shown in Figure 12-1 through Figure 12-3. If samples become unavailable from specified sample locations, 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.

e. Sampling Media and Frequency The minimum sampling frequency for the environmental media required by the PBNP REMP is found in Table 12-3. Additional samples may be collected in response to plant conditions as determined by the cognizant Chemistry Analyst. Included is algae which is not a NUREG-04 72 requirement. Additionally, the REMP also includes the sampling of soil and shoreline sediment, which were not part of the PBNP RETS but kept for continuity with the preoperational monitoring program.

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Samples are collected pursuant to HPIP 3.58.1, Radiological Environmental Sampling, which uses a monthly checklist to ensure that all the samples for the month are collected. The checklists also identify the schedule for the annual milk survey. 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 12-3 shall be documented in an AR and reported in the AMR.

f. Sample Analyses and Frequency The PBNP REMP samples shall be analyzed for designated parameters at the frequency listed in Table 12-3. Additional samples may be collected in response to plant conditions. 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-131, Cs-134, Cs-137, Ba/La-140, Ce-141, and Ce-144.

g. Analytical Laboratory The contracted 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 laboratory is responsible for providing prompt notification to the cognizant Chemist regarding any samples found to exceed the administrative notification levels as identified in Table 12-1. 12.2.3 Assistance to the State of Wisconsin (Non-Technical Specification Activity) 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. 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. Page 130 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 12.2.4 Specification of Sampling Procedures General radiological environmental sampling procedures follow the directives presented in Sections 12.1 and 12.2. Station procedures provide the specific information for the collection of the following samples:

Vegetation
Thermo luminescent Dosimeters (TLDs)
Lake water
Well water
Air
Milk
Algae (part ofPBNP RETS,10-3-1985)
Fish
Soil (not part ofPBNP RETS, 10-3-1985)
Shoreline sediment (not part ofPBNP RETS, 10-3-1985) 12.2.5 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. Page 131 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 12-1 SAMPLE TYPES AND ASSOCIATED LOWER LEVEL OF DETECTION (LLD) AND NOTIFICATION LEVEL VALUES NOTIFICATION LEVELS SAMPLE REPORTING PARAMETER LLD 1 PBNP2 TYPE UNIT NRC (ADMIN.) I Cs-137 0.08 2 0.40 Cs-134 0.06 1 0.20 Vegetation pCi/g (wet) I-131 0.06 0.1 0.06 Other3 0.25 --- 2.0 Shoreline I Sediment and pCi/g (dry) Cs-137/134 0.15/0.18 --- 20 Soil 5 Other3 0.15 --- 20 I Cs-137 0.25 10 1 Cs-134 0.25 10 1 Algae 5 pCi/g (wet) Co-58 0.25 10 1 Co-60 0.25 10 1 Other3 0.25 --- 1 I Cs-137 0.15 2 0.40 Cs-134 0.13 1 0.20 Co-58 0.13 30 3 Co-60 0.13 10 1 Fish pCi/g (wet) Mn-54 0.13 30 3 Fe-59 0.26 10 1 Zn-65 0.26 20 2 Other3 0.5 --- 6 Sr-89) 5 --- 100 Sr-90 5 1 --- 100 I-131 0.5 7 3 0.5 Milk pCi/L Cs-134 15 (5) 60 15 Cs-137 18 (5) 70 18 Ba-La-140 15 (5) 300 30 Other3 15 --- 30 Gross beta 0.01 --- 1.0 I-131 0.07 (0.03) 0.9 0.09 Air Filter6 pCi/m3 Cs-137 0.06 20 2.0 Cs-134 0.05 10 1.0 Other3 0.1 --- 1.0 TLDs mR/7 days Gamma 1mR/TLD --- 5mR/7 days Page 132 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 12-1 SAMPLE TYPES AND ASSOCIATED LOWER LEVEL OF DETECTION (LLD) AND NOTIFICATION LEVEL VALUES NOTIFICATION LEVELS SAMPLE REPORTING

                                        *PARAMETER                    LLD 1                                  PBNP2 TYPE                UNIT                                                              NRC (ADMIN.)_

pCi/L from I Total Solids Gross beta 4 --- 100 Cs-134 15 (10) 30 15 Cs-137 18 (1 0) 50 18 Fe-59 30 400 40 Zn-65 30 300 30 Zr-Nb-95 15 400 40 Ba-La-140 15 200 20 Co-58 15 (1 0) 1,000 100 Co-60 15 (10) 300 30 Lakewater4 and Mn-54 15 (10) 1,000 100 Well Water pCi/L I-131 1 (0.5) 2 2 Other3 30 --- 100 H-3 4 3,000 (200) 30,000 3,000 (Lakewater) H-3 (Well 2,000 (200) 20,000 3,000 Water) Sr-89 5 10 (5) --- 50 Sr-90:, 2 (1) --- 20 NOTE 1: The LLDs in this column are the maximum acceptable values. The values in parentheses are the administrative LLDs. NOTE 2: Values in this column are not technical specifications NOTE 3: "Other" refers to non-specified identifiable gamma emitters resulting from the operation of PBNP. Naturally occurring radionuclides are not included. NOTE 4: No drinking water NOTE 5: Items not required by PBNP RETS (10-3-1985) or NUREG-1301 but kept in the REMP for comparison to pre-operational and historical data. NOTE 6: All particulate filters shall be allowed to decay for at least 24 hours after sampling to allow for radon and radon-daughter decay prior to gross fl analysis. NOTE 7: Lower than NUREG-1301 value 1 pCi/L to support PBNP's sampling frequency. Page 133 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 12-2 RADIOLOGICAL ENVIRONMENTAL 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 Two Creeks Park, the TLD is on South side of Two Creeks Road, West of E-05 Lakeshore Road on first pole West of Lakeshore. Point Beach State Park - Water and shoreline sediment samples at the Coast Guard Station; soil and vegetation from the Point Beach State Park E-06 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. E-07 WPSC Substation on County Rt. V, about 0.5 Miles West ofHwy. 42 G. J. Francar Property, at theSE Comer of the Intersection ofCty. Band E-08 Zander Road Nature Conservancy, East side ofHwy 42. Comer ofHwy 42 and Cty. BB. E-09 On pole North side of Entrance. E-10 PBNP Site Well Lambert Dairy Farm, 1523 Tapawingo Road, 0.5 miles West of Saxonburg E-ll Road E-12 Discharge Flume I Pier, U-1 side E-13 Pump house E-14 South Boundary, about 0.2 miles East of Site Boundary Control Center E-15 SW Corner of Site, N side ofNuclear Rd at junction with Twin Elder Rd. Pole #2124 23Ll7, Third pole (beside white underground cable post) E-16b N of old E-16 pole at residence 14427 Hwy 42 E-17 North of Mishicot, Cty. Band Assman Road, NE Comer of Intersection E-18 NW of Two Creeks at Zander and Tannery Roads E-20 Reference Location, 17 miles SW, at Silver Lake College E-21 Local Dairy Farm just South of Site (R. Strutz) on Lakeshore and Irish Roads E-22 West Side ofHwy. 42, about 0.25 miles North of Johanek Road E-23 Greenfield Lane, about 4.5 Miles South of Site, 0.5 Miles East ofHwy. 42 E-24 North Side of County Rt. V, near intersection of Saxonburg Road South Side of County Rt. BB, about 0.5 miles West ofNorman/Saxonberg E-25 Road Page 134 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 12-2 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS LOCATION CODE LOCATION DESCRIPTION 804 Tapawingo Road, Pole #2124 18L17, Second Pole East ofCty. B. North E-26b Side of Road E-27 NE corner of Saxonburg and Nuclear Roads, about 4 Miles WSW E-28 TLD on westernmost pole between the 2nd and 3rd parking lots, E-29 On microwave tower fence E-30 NE corner at Intersection of Tapawingo and Lakeshore Roads. On utility pole North side ofTapawingo Road closest to the gate at the West E-31 property line On a conduit/pole 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 E-32 1200 feet south ofTapawingo Road. The location is almost under the power lines between the blue and gray transmission towers. (The conduit/pole is about 6 feet high). E-33 Lake Michigan shoreline accessed from area just S of KPS discharge. E-38 On tree West of former Retention Pond site E-39 On tree East of former Retention Pond site Local Dairy Farm (Barta), about 1.8 miles north of intersection of Highway E-40 42 and Nuclear Road (Manitowoc County), on West side of Highway 42. E-41 NW corner of Woodside and Nuclear Roads (Kewaunee Co.) E-42 NW corner of Church and Division, East of Mishicot E-43 West Side of Tannery Road South of Elmwood (7th pole South of Elmwood) I E-44 Utility PoleN side ofTapawingo Rd near house at 5011 E-TC Transportation Control; Reserved for TLDs E-F1a Field ENE ofE-14 E-F1b Field immediately N of SBCC E-F2 Field NW corner ofNuclear Rd and Lakeshore Rd, 200' W of Lakeshore Rd E-F3 Field approximately 400ft. E ofE-15 E-F4 Field approximately 600ft. W of Lakeshore Rd E-F5 Field approximately 600ft. W of Lakeshore Rd E-F6 Field approximately 600ft. W of Lakeshore Rd (West of marshy area) Field N ofiSFSI and W of Lakeshore Rd, approximately 600ft. W of E-F7 Lakeshore Rd E-F8 Field approximately 400 ft. NE ofE-31 E-F9 Field approximately 1000 ft. W ofE-04 Page 135 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE 12-3 PBNP RADIOLOGICAL ENVIRONMENTAL SAMPLE COLLECTION AND ANALYSIS FREQUENCY SAMPLE TYPE SAMPLE CODES ANALYSES FREQUENCY E-01, -02, -03, -04, -05, -06,

                          -07, -08, -09, -12, -14, -15, Environmental       -16b, -17,-18,-20,-22,-23, TLD                 Quarterly Radiation Exposure     -24, -25, -26b, -27, -28, -29
                        ' -30, -31, -32, -38, -39, -41, I                               -42, -43, -44, -TC Vegetation       E-01, -02,-03,-04,-06,-08, I  (Grass and Weeds)                 -09, -20, Gamma isotopic        3x/yr as available Vegetation       E-F1a, -F1 b, -F2, -F3, -F4, -       Gamma isotopic 1x/yr as available (Crops)             F5, -F6, -F7, -F8, -F9              analysis I         Algae                     E-05, -12                Gamma isotopic        1x/yr as available Fish (edible portions I         only)

E-13 Gamma isotopic 4x/yr as available Gross beta, H-3 Well Water E-10 Sr-89, 90, I-131 Quarterly Gamma isotopic Gross beta Monthly Quarterly composite H-3, Sr-89, 90 of monthly Lake Water E-01,-05, -06,-33 collections I-131 Monthly Gamma isotopic Monthly Sr-89, 90 Milk E-11, -21, -40 I-131 Monthly Gamma isotopic Gross beta Weekly (particulate) I-131 Weekly (charcoal) Air Filters E-01, -02,-03,-04,-08,-20 Quarterly (on Gamma isotopic composite particulate filters) E-01,-02,-03,-04,-06, -08, Soil Gamma isotopic 1x/yr

                                   -09, -20, Gamma isotopic Shoreline Sediment        E-01, -05,-06,-12,-33                                        1x/yr Analysis Page 136 of278                       REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL FIGURE 12-1 RADIOACTIVE ENVIRONMENTAL SAMPLING LOCATIONS FIGURE 2-1c KEY

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1 1MILE J'"' 1' " ' 11 KILOMETER MAY 2005 Page 137 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL FIGURE 12-2 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS FlGUP.E 2-lc SITE MAP POINT BEACH NUCLEAR PLANT 0 BOO 1600

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL FIGURE 12-3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS LAKE MICHIGAN

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 13.0 RADIOLOGICAL EFFLUENT CONTROLS PROGRAM 13.1 Radiological Effluent Controls Program 13.1.1 Basis The Radiological Effluent Control Program (RECP) shall conform to 10 CFR 50.36a for the control of radioactive effluents and maintaining doses to members of the public from radioactive effluents as low as reasonably achievable (ALARA). The RECP also is established to control the amount and concentrations of radioactivity in PBNP effluent pursuant to the following documents:

10 CFR 50.34a-Design objectives for equipment to control releases of radioactive material in effluents-nuclear power reactors,
10 CFR 50, Appendix A, Criterion 60-Control of releases of radioactive material to the environment,
10 CFR 50, Appendix A, Criterion 63-Monitoring fuel and waste storage,
10 CFR 50, Appendix A, Criterion 64-Monitoring radioactivity releases,
10 CFR 20.1302-Compliance with dose limits for individual members of the public,
10 CFR 20.1501-General,
PBNP General Design Criterion 17-Monitoring Radioactivity Releases, and
PBNP General Design Criterion 70-Control of releases of radioactivity to the environment 13.1.2 Basis Statement Liquid effluent from the radioactive waste disposal system is diluted by the circulating water system prior to release to Lake Michigan. With two pumps operating per unit, the flow of the circulating water system is approximately 390,000 gpm per unit. Operation of a single circulating water pump per unit reduces the nominal flow rate by about 35%. Liquid waste from the waste disposal system may be discharged to the circulating water system of either unit via the service water return header. Because of the low radioactivity levels in the circulating water discharge, the concentrations of liquid radioactive effluents at this point are not measured directly. Instead, the concentrations in the circulating water discharge are calculated from the measured concentration of the liquid effluent, the discharge flow rate of the effluent and the nominal flow in the circulating water system.

Page 140 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL The release of radioactive materials in liquid effluents to unrestricted areas is monitored and controlled to conform to the dose objectives in Section II.A of Appendix I to 10 CFR 50 and will be ALARA in accordance with the requirements of 10 CFR Parts 50.34a and 50.36a. The monitoring and control also is undertaken to keep the concentrations of radionuclides in PBNP liquid effluent released to unrestricted areas conforming to ten times the maximum effluent concentration (MEC) values specified in Table 2, Column 2 of Appendix B to 10 CFR 20. Furthermore, the appropriate portions of the liquid radwaste treatment systems will be used as required to keep the releases ALARA. These actions provide reasonable assurance that the resulting average annual dose or dose commitment from liquid effluent from each unit of the Point Beach Nuclear Plant for any individual in an unrestricted area from all pathways of exposure will not exceed the 10 CFR 50, Appendix I dose objectives. Thus, discharge of liquid wastes not exceeding these release limits will not result in significant exposure to members of the public because of consumption of drinking water from the lake, even if the effect of potable water treatment systems on reducing radioactive concentrations of the water supply is conservatively neglected. Prior to release to the atmosphere, gaseous wastes are mixed in the auxiliary building vent with the flow from at least one of two auxiliary building exhaust fans. Further dilution then occurs in the atmosphere. Release of radionuclides to the atmosphere is monitored and controlled so that effluents to unrestricted areas conform to the dose objectives of Sections II.B and C of Appendix I to 10 CFR 50. Monitoring and control also is undertaken to ensure that at the point of maximum ground concentration at the site boundary, the radionuclide concentrations in the atmosphere will conform to the limits specified in Table 2, Column 1 of Appendix B to 10 CFR 20. Furthermore, the appropriate portions of the gaseous radwaste treatment system are used as required to keep the radioactive releases to the atmosphere ALARA. In order to achieve the dose objectives of Appendix I to 10 CFR 50 and the aforementioned concentration limits, the setpoints for releases to the atmosphere and to Lake Michigan utilize the methodology found in the Offsite Dose Calculation Manual. Setpoints for releases to the atmosphere are based on conforming to the TS instantaneous dose rate limits using the dilution provided by building vents as well as the highest annual average x/Q at the site boundary. Setpoints for releases to Lake Michigan are based only on dilution by circulation water. Together, control and monitoring provide reasonable assurance that the annual dose from each unit's effluents, to an individual in an unrestricted area will not exceed the dose objectives of Appendix I to 10 CFR 50. Page 141 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Implementation of the RECP will keep average annual releases of radioactive material in PBNP effluents and their resultant committed effective dose equivalents at small percentages of the dose limits specified in 10 CFR 20.1301. At the same time, the methodology of implementing the RECP permits the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided with a dependable source of power even under unusual operating conditions which may temporarily result in releases higher than such numerical guides for design objectives set forth in Appendix I but still within levels that assure that the average population exposure is equivalent to small fractions of doses from natural background radiation. Compliance with the provisions of Appendix I to 10 CFR Part 50 constitutes adequate demonstration of conformance to the standards set forth in 40 CFR Part 190 regarding the dose commitment to individuals from the uranium fuel cycle. 13.1.3 Other RECP Reportable Events

a. Radioactive Effluent Non-Treatment If the effluent treatment system for radioactive liquids or for releases to the atmosphere is non-functional and effluents are being discharged for 31 consecutive days without the treatment required to meet the release limits specified in Section 6.1 and Section 7.1, a special report shall be prepared and submitted to the Commission within thirty days which includes the following information:

1. Identification of the non-functional equipment or subsystem and the reason for non-functionality.

2. Actions taken to restore the non-functional equipment to FUNCTIONAL status.

3. Summary description of actions taken to prevent a recurrence.

b. Exceeding Radioactive Effluent Release Limits If the quantity of radioactive material actually released in liquid or gaseous effluents during any calendar quarter exceeds twice the quarterly limit as specified in Sections 6.2, 7.2 or 7.3, a special report shall be prepared and submitted to the Commission within thirty days of determination of the release quantity.

Page 142 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL The report must describe the extent of exposure of individuals to radiation and radioactive material, including as appropriate:

1. corrective action( s) to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits, including the schedule for achieving conformance with applicable limits, ALARA constraints, generally applicable environmental standards, and associated license conditions,

2. estimates of exposures to a member of the public, including the dose from any external storage units, such as the ISFSI and the SGSF, for compliance with 40 CFR 190 limits,

3. levels of radiation and concentrations of radioactive materials involved, and

4. cause of the elevated exposures, dose rates, or concentrations.

If the dose to any member of the public exceeds 75 mrem to the thyroid or 25 mrem to the whole body or any organ other than the thyroid, pursuant to 40 CFR 190, the report shall also contain a request for a variance from this standard pursuant to 40 CFR 190.11.

c. Major Change to Radioactive Liquid, Gaseous and Solid Waste Treatment Systems Licensee initiated major changes to the radioactive waste treatment systems (liquid, gaseous, and solid) shall be reported to the U.S. Nuclear Regulatory Commission with the periodic update to the FSAR for the period for which the updates are submitted. The discussion of each change shall include:

1. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59;

2. Information necessary to support the reason for the change;

3. A description of the equipment, components and processes involved and the interfaces with other plant systems;

4. An evaluation of the change, which shows how the predicted releases of radioactive materials in liquid effluents and gaseous effluents and/or quantity of solid waste will differ from those previously predicted in the license application and amendments thereto; Page 143 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

5. An evaluation of the change, which shows the expected maximum exposures to an individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto;

6. An estimate of the exposure to plant operating personnel because of the change

d. Audits The activities of the Radiological Effluent Controls Program as described in this manual and its implementing procedures shall be audited in accordance with Section 2.4.

13.2 Radioactive Effluent Control and Accountability 13.2.1 Radiation Monitoring System

a. Description The computerized Radiation Monitoring System (RMS) at Point Beach Nuclear Plant consists of area and process monitors. The effluent monitors are those process monitors that are designed to detect and measure radioactivity in liquid and gaseous releases from PBNP. A description of the liquid and gaseous effluent monitors and associated isolation and control functions are presented in ODCM Sections 9.1 and 10.1.

b. Calibration Calibration of the RMS detectors is accomplished according to the PBNP instrument and control procedures.

c. Setpoints The methodology for determining effluent RMS detector setpoints is described in the ODCM Sections 9.1 and 10.1.

d. Alarms Response to alarms received from RMS effluent detectors is described in the PBNP RMS Alarm Setpoint and Response Book.

e. Effluent Detector Functionality and Surveillance Detector functionality and surveillance requirements are addressed in Sections 6.0 and 7.0 of this manual.

Page 144 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 13.2.2 Release Accountability Control and accountability of radioactivity in PBNP effluents is accomplished by the RMS in conjunction with the characterization of radionuclide distributions by laboratory analyses of grab samples from the various waste streams. Sampling frequencies and analysis requirements are set forth in Sections 6.1.4 and 7.1.4 of this manual. Additional aspects of grab sampling and release accountability are described in the PBNP Release Accountability Manual 13.3 Radioactive Effluent Monitoring Instrumentation Functionality Requirements 13.3.1 Objective The functionality of detectors is specified in order to ensure that liquid and gaseous radioactive effluents are adequately monitored and to ensure that alarm or trip setpoints are established such that effluent releases do not exceed the values cited in Sections 6.1.1, 6.2.1, 7.1.1, 7.2.1, 7.3.1 and 8.1. 13.3.2 Functionality Specifications

a. The radioactive effluent monitoring instrumentation channels listed in Table 6-2 and Table 7-2 shall be functional. The alarm or trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

1. All monitors are defined by the term FUNCTIONAL -

FUNCTIONALITY, EXCEPT 1(2) RE-212 Containment Noble Gas Monitor which is defined by the term OPERABLE-OPERABILITY.

2. IF the ability of 1(2) RE-212, Containment Noble Gas Monitor, to perform its function is questioned, THEN the Operability Determination process is applicable.

(LCO 3.4.15, RCS Leakage Detection Instrumentation)

b. If fewer than the minimum number of radioactive effluent monitoring channels are functional, the action statement listed in either Table 6-2 or Table 7-2 shall be taken. Best effort shall be made to return a non-functional channel to functional status within 30 days.

c. If the channel is not returned to a functional status within 30 days, the circumstances of the instrument failure and schedule for repair shall be reported to the NRC Resident Inspector.

Page 145 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

d. If a radioactive effluent monitoring instrumentation channel alarm or trip setpoint is found less conservative than required by the ODCM, the channel shall be declared non-functional OR the setpoint shall be changed to the ODCM value or a more conservative value.

13.4 Solid Radioactive Waste The solid radwaste system shall be used in accordance with the Process Control Program to process radioactive wastes to meet all shipping and burial ground requirements. If the provisions of the Process Control Program are not satisfied, shipments of defectively processed or defectively packaged radioactive waste from the site will be suspended. The Process Control Program shall be used to verify solidification of radwaste. Page 146 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

14.0 REFERENCES

14.1 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," U.S. Nuclear Regulatory Commission, Washington DC. 14.2 Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Demonstrating Compliance with 10 CFR Part 50, Appendix I," U.S. Nuclear Regulatory Commission, Washington, DC. 14.3 Regulatory Guide 1.113, "Estimating Aquatic Dispersion ofEffluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," U.S. Nuclear Regulatory Commission, Washington, DC. 14.4 Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste," U.S. Nuclear Regulatory Commission, Washington, DC. 14.5 NUREG-0133, "Preparation ofRadiological Effluent Technical Specifications for Nuclear Power Plants," October 1978. 14.6 NUREG-1301, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors," April1991. 14.7 EPRI Technical Report 1021106 "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents", 201 0. 14.8 Report No. R-2330244-001, Point Beach Annual Meteorological and Atmospheric Dispersion Report for 2009, December 2010. 14.9 Regulatory Guide 4.1, "Radiological Environmental Monitoring for Nuclear Power Plants," June 2008, Rev. 2, USNRC, Washington, DC. NOTE: The NRC documents (References 14.2 - 14.6, and 14.9) are presented for informational purposes and do not constitute a NextEra Energy Point Beach commitment to these documents. Page 147 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIX A LIQUID PATHWAY EMEC FOR USE IN SETPOINT CALCULATIONS The effective maximum effluent concentration (EMEC) is calculated from the annual liquid releases for the years 2000 through 2010 (Table A-1). The EMEC is the total concentration ofradionuclides which can be discharged without having the summation of concentration fractions exceed unity. To obtain this value, the average annual total radionuclide concentration is divided by the sum of the ratio of each average individual radionuclide concentration divided by 1Ox its maximum effluent concentration listed in 10CFR20, Appendix B, Table 2, Col2. The EMEC formula (Equation 9-3) is:

L ci :L ci EMEC = Ci or EMEC = SOF [A-1]

LMEC.l Where: SOF = Sum offractions Ci = Annual average concentration of radio nuclide "i" MECi = 1Ox the maximum ejjluent concentration from 10CFR20, Appendix B, Table 2, Column 2. Also referred to as the Ejjluent Concentration Limit (ECL) The 2000-2010 liquid effluent data are used for calculating the annual averages and EMEC (see Table A-1). C-14, Ni-63 and Tc-99 were added to the analytical requirements for liquid wastes in 2009, so each of these three radionuclides is averaged only over the two years of available data. The annual average concentration is based on the volume for all of the eleven years. In calculating the annual average concentrations, the annual liquid waste effluent volumes were not used because they were four orders of magnitude lower than the dilution volume and would have but a minor effect on the resulting concentrations. The calculated value for the EMEC is 9.89E-03 J!Ci/cc. The Nai detectors do not measure pure ~-emitters such as H-3, C-14, Fe-55, Ni-63, Sr-90, and Tc-99. Therefore, a ~-correction factor (~CF) is used to correct for these radionuclides to correct for these isotopes not being detected by the monitors. Additional conservatism is realized when calculating individual liquid effluent monitor setpoints because the minimum dilution flow is used. PBNP technical specifications allow liquid discharge concentrations at ten times the concentrations set forth in 10CFR20, Appendix B, Table 2, Column 2. The EMEC is the maximum concentration allowed at the point of discharge. Therefore, in addition to a ~CF, a dilution scaling factor (SF) is applied to determine the monitor setpoint which is the maximum allowable discharge concentration. The SF is the ratio of the eire water flow rate (CW) to the release rate (RR) [ODCM formula 9-5]. Therefore the SP = EMEC *SF* ~CF. The SF is calculated from the minimum eire water flow (243,000 gpm) and the maximum effluent release rate (Table 9-1). Page 148 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLEA-1 LIQUID EFFLUENT VOLUMES 2000 2001 .. 2002 2003 2004 2005 2006 2007 2008 2009 2010 TOTAL AVE. I '>* *. < Discharge Vol. (cc) 4.94E+!! 4.!5E+ll 4.72E+ll 3.96E+ll 4.15E+ll 3.59E+ll 3.77E+ll 3.84E+ll 4.12E+ll 4.80E+ll 6.24E+ll 4.83E+l2 4.39E+ll Dilution Vol. (cc) 1.06E+!5 1.04E+l5 1.03E+l5 l.OOE+l5 1.04E+l5 8.64E+l4 1.12E+l5 1.10E+l5 1.70E+!5 1.07E+l5 1.11E+l5 1.2!E+l6 1.103E+!5 TABLEA-2 LIQUID EFFLUENT RELEASES 2007 2008 2009 2010 Total Ave. (Ci/yr) (Ci/yr) (Ci/yr) (Ci/yr) (Ci) (Ci/yr) H-3 l.OOE-03 8.04E+02 5.88E+02 5.60E+02 7.48E+02 6.08E+02 5.53E+02 6.07E+02 5.88E+02 5.34E+02 6.37E+02 5.59E+02 6.79E+03 6.17E+02 C-14 3.00E-05 1.97E-02 3.39E-03 2.31E-02 1.15E-02 F-18 7.00E-04 2.26E-04 9.90E-04 3.31E-04 1.08E-03 1.30E-03 1.20E-03 2.52E-03 2.45E-03 1.97E-03 3.81E-03 5.66E-03 2.15E-02 1.96E-03 Na-22 6.00E-06 5.58E-06 5.58E-06 5.07E-07 Na-24 5.00E-05 5.50E-06 5.50E-06 5.00E-07 Cr-51 5.00E-04 8.24E-03 9.08E-03 1.41E-02 8.23E-03 4.25E-04 2.55E-03 7.82E-03 3.10E-03 2.06E-02 8.63E-03 4.88E-03 8.77E-02 7.97E-03 Mn-54 3.00E-05 4.53E-04 1.52E-03 4.42E-04 1.06E-03 1.21E-04 6.97E-04 4.39E-04 1.24E-04 6.62E-04 9.10E-04 1.42E-04 6.57E-03 5.97E-04 Mn-56 7.00E-05 1.92E-06 1.92E-06 1.75E-07 Fe-55 1.00E-04 1.12E-02 8.80E-03 6.82E-03 7.21E-03 3.85E-03 3.23E-03 3.06E-03 6.22E-03 5.50E-03 4.62E-03 4.92E-03 6.54E-02 5.95E-03 Fe-59 l.OOE-05 1.23E-04 2.18E-04 1.85E-03 3.11E-04 5.61E-05 1.04E-05 1.09E-04 1.93E-04 5.21E-04 1.49E-04 3.66E-04 3.91E-03 3.55E-04 Ni-63 l.OOE-04 9.94E-03 2.26E-03 1.22E-02 6.10E-03 Co-57 6.00E-05 1.29E-04 1.03E-03 1.11E-04 1.29E-04 1.06E-05 3.04E-05 5.50E-06 2.72E-04 9.13E-05 5.60E-05 1.86E-03 1.69E-04 Co-58 2.00E-05 5.56E-02 9.01E-02 3.39E-02 1.04E-01 4.12E-03 4.92E-03 3.58E-03 6.26E-03 3.70E-02 1.36E-02 4.28E-02 3.96E-01 3.60E-02 Co-60 3.00E-06 7.33E-03 1.35E-02 3.61E-03 1.27E-02 2.13E-03 8.02E-03 9.94E-03 5.45E-03 l.lOE-02 2.17E-02 3.96E-03 9.93E-02 9.03E-03 Zn-65 5.00E-06 1.44E-04 1.76E-04 4.57E-05 6.35E-05 3.73E-06 8.13E-05 4.38E-05 4.62E-06 1.55E-04 3.50E-04 9.33E-06 1.08E-03 9.79E-05 As-76 l.OOE-05 2.07E-05 1.27E-05 1.97E-05 1.84E-05 1.99E-05 7.09E-06 9.33E-05 8.59E-09 1.92E-04 1.74E-05 Sr-89 8.00E-06 3.41E-06 7.69E-05 8.03E-05 7.30E-06 Sr-90 5.00E-07 3.04E-04 8.79E-05 2.14E-04 1.57E-05 1.71E-06 9.36E-05 1.03E-05 1.95E-05 7.47E-04 6.79E-05 Sr-92 4.00E-05 1.36E-06 4.25E-05 5.54E-06 1.76E-06 1.61E-06 5.27E-05 4.79E-06 Nb-95 3.00E-05 1.07E-03 3.86E-03 1.67E-03 1.73E-03 1.83E-04 1.62E-03 9.38E-04 2.71E-04 3.92E-03 1.57E-03 6.09E-04 1.74E-02 1.59E-03 Nb-97 3.00E-04 2.93E-05 1.92E-05 9.20E-06 1.92E-05 1.50E-05 7.07E-06 9.10E-06 1.83E-06 1.50E-05 6.36E-06 1.13E-05 1.43E-04 1.30E-05 Page 149 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLEA-2 LIQUID EFFLUENT RELEASES MEC 2000 2001 2002 2003 . . 2004 .. 2005 2006 2007 2008 2009 2010 Total Ave. (rJ.Ci/cc) (Cilyr) (Cilyr) (Ci/yr) (Ci!yr) ** (Ci/yr) (Ci/yr) (Ci/yr) (Cilyr) (Cilyr) (Cilyr) (Cilyr) (Ci) (Ci/yr)

   *..           .**                                     ..                                        :_c.

Zr-95 2.00E-05 5.11E-04 1.69E-03 7.02E-03 8.89E-04 5.26E-05 6.85E-04 4.97E-04 4.53E-05 2.12E-03 8.17E-04 3.38E-04 1.47E-02 1.33E-03 Zr-97 9.00E-06 1.65E-06 5.31E-08 7.14E-06 O.OOE+OO O.OOE+OO 2.86E-06 6.67E-06 1.84E-05 1.67E-06 Mo-99 2.00E-05 1.96E-06 8.72E-06 1.07E-05 9.71E-07 Tc-99 6.00E-05 6.46E-04 6.60E-04 1.31E-03 6.53E-04 Tc-99m l.OOE-03 6.34E-06 8.45E-06 1.48E-05 1.34E-06 Ru-103 3.00E-05 9.58E-06 2.68E-06 2.05E-05 3.28E-05 2.98E-06 Ru-105 7.00E-05 1.68E-05 1.68E-05 1.52E-06 Ru-106 3.00E-06 2.31E-05 3.13E-05 2.49E-04 3.03E-04 2.76E-05 Ag-IIOm 6.00E-06 2.92E-03 4.66E-03 2.80E-03 3.85E-03 5.45E-04 3.29E-03 2.46E-03 4.74E-03 2.67E-03 1.06E-03 2.95E-03 3.19E-02 2.90E-03 Sn-113 3.00E-05 1.20E-04 3.51E-04 6.91E-04 4.17E-04 3.23E-05 1.64E-04 7.8!E-05 1.17E-04 1.22E-03 4.34E-04 2.88E-04 3.91E-03 3.56E-04 Sn-117m 3.00E-05 3.47E-04 5.83E-04 1.32E-03 1.45E-03 1.29E-03 2.45E-03 1.24E-03 2.27E-03 4.34E-03 3.68E-03 1.70E-03 2.07E-02 1.88E-03 Sb-122 l.OOE-05 5.90E-06 3.14E-06 4.25E-06 5.75E-06 3.49E-06 1.33E-05 5.66E-07 3.64E-05 3.31E-06 Sb-124 7.00E-06 2.03E-04 4.31E-04 6.09E-04 4.71E-04 1.76E-03 4.76E-05 2.01E-04 2.90E-04 1.20E-03 7.59E-04 1.06E-03 7.03E-03 6.39E-04 Sb-125 3.00E-05 5.70E-03 6.65E-04 2.06E-03 1.30E-02 6.69E-03 2.40E-02 9.15E-04 4.88E-02 2.64E-02 8.90E-03 1.57E-03 1.39E-OI 1.26E-02 Te-131 8.00E-05 3.49E-06 3.49E-06 3.17E-07 Te-132 9.00E-06 2.73E-05 3.73E-05 1.17E-04 1.07E-05 2.32E-05 1.38E-05 2.29E-04 2.09E-05 I-131 !.OOE-06 1.65E-04 9.30E-05 1.97E-06 2.50E-06 3.74E-05 9.32E-07 1.21E-05 3.13E-04 2.85E-05 I-132 l.OOE-04 l.IOE-05 l.IOE-05 l.OOE-06 I-133 7.00E-06 2.68E-06 1.74E-05 4.22E-05 2.06E-05 1.53E-06 2.10E-05 1.05E-04 9.58E-06 Cs-134 9.00E-07 2.70E-06 2.70E-06 2.45E-07 Cs-134m 2.00E-03 4.09E-06 4.09E-06 3.72E-07 Cs-136 6.00E-06 1.73E-05 1.60E-05 6.94E-06 6.83E-06 1.51E-06 5.67E-06 2.42E-06 5.67E-05 5.15E-06 Cs-137 l.OOE-06 9.15E-04 9.3!E-05 2.84E-05 7.83E-05 3.57E-05 2.62E-04 5.13E-04 1.04E-04 9.35E-05 2.45E-03 1.17E-05 4.58E-03 4.16E-04 Ba-139 2.00E-04 5.37E-07 5.37E-07 4.88E-08 Ba-140 8.00E-06 9.31E-06 3.66E-05 1.79E-05 6.38E-05 5.80E-06 La-140 9.00E-06 1.45E-04 8.21E-06 1.53E-04 1.39E-05 Ce-141 3.00E-05 O.OOE+OO 2.18E-06 2.18E-06 1.99E-07 W-187 3.00E-05 1.12E-05 1.12E-05 1.02E-06 Page 150 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLEA-3 LIQUID EFFLUENT CONCENTRATIONS (The pure ~ emitters are highlighted) MEC Ann~ Average CilOxMECi (p.tCilcc} (p.tCi/cc} H-3 l.OOE-03 5.59E-07 5.59E- 05 C-14 3.00E-05 1.05E-11 3.49E- 08 F-18 7.00E-04 1.77E-12 2.54E-10 Na-22 6.00E-06 4.60E-16 7.66E-12 Na-24 5.00E-05 4.53E-16 9.07E-13 Cr-51 5.00E-04 7.23E-12 1.45E-09 Mn-54 3.00E-05 5.41E-13 1.80E-09 Mn-56 3.00E-05 1.58E-16 2.26E-13 Fe-55 l.OOE-04 5.39E-12 5.39E-09 Fe-59 1.00E-05 3.22E-13 3.22E-09 Ni-63 1.00E-04 5.53E-12 5.53E-09 Co-57 6.00E-05 1.53E-13 2.56E-10 Co-58 2.00E-05 3.26E-11 1.63E-07 Co-60 3.00E-06 8.19E-12 2.73E-07 Zn-65 S.OOE-06 8.87E-14 1.77E-09 As-76 l.OOE-05 1.58E-14 1.58E-10 Sr-89 8.00E-06 6.62E-15 8.27E-11 Sr-90 5.00E-07 6.16E-14 1.23E-08 Sr-92 4.00E-05 4.35E-15 1.09E-11 Nb-95 3.00E-05 1.44E-12 4.79E-09 Nb-97 3.00E-04 1.18E-14 3.92E-12 Zr-95 2.00E-05 1.21E-12 6.04E-09 Zr-97 9.00E-06 1.51E-15 1.68E-11 Mo-99 2.00E-05 8.80E-16 4.40E-12 Tc-99 6.00E-05 5.92E-13 9.86E-10 Tc-99m 1.00E-03 1.22E-15 1.22E-13 Ru-103 3.00E-05 2.70E-15 9.00E-12 Ru-105 7.00E-05 1.38E-15 1.97E-12 Ru-106 3.00E-06 2.50E-14 8.33E-10 Ag-110m 6.00E-06 2.63E-12 4.39E-08 Sn-113 3.00E-05 3.22E-13 1.07E-09 Sn-117m 3.00E-05 1.70E-12 5.68E-09 Sb-122 1.00E-05 3.00E-15 3.00E-ll Sb-124 7.00E-06 5.80E-13 8.28E-09 Sb-125 3.00E-05 1.14E-ll 3.81E-08 Te-131 8.00E-08 2.88E-16 3.60E-13 Te-132 9.00E-06 1.89E-14 2.10E-10 I-131 l.OOE-06 2.58E-14 2.58E-09 I-132 l.OOE-04 9.07E-16 9.07E-13 Page 151 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE A-3(CONT'D) LIQUID EFFLUENT CONCENTRATIONS MEC Ann. Average Ci/lOxMECi (p.tCi!cc) (p.tCilcc) 1-133 7.00E-06 8.69E-15 1.24E-10 Cs-134 9.00E-07 2.23E-16 2.47E-11 Cs-134m 2.00E-03 3.37E-16 1.69E-14 Cs-136 6.00E-06 4.67E-15 7.79E-ll Cs-137 l.OOE-06 3.77E-13 3.77E-08 Ba-139 2.00E-04 4.43E-17 2.21E-14 Ba-140 8.00E-06 5.26E-15 6.57E-ll La-140 9.00E-06 1.26E-14 1.40E-10 Ce-141 3.00E-05 1.80E-16 6.00E-13 W-187 3.00E-05 9.23E-16 3.08E-12 TOTAL 5.59E-07 5.66E-05 TOTALy 7.07E-11 5.95E-07 Total p 5.59E-07 5.60E-05 The ~CF is based on the condition that the total summation of fraction or ~SOP :::; 1. Therefore, at the setpoint, the~ andy SOP fractions of the total SOP (~SOP) must satisfy the condition SOP~/ ~SOP + SOFy/~SOF. Because the monitors detect only the gamma fraction of the ~SOP, the EMEC is multiplied by the ratio SOFy/ ~SOP which is the ~CF. Using the above Table A-3 SOP values, the

                      ~CF   = SOFy/      ~SOP      = 5.95E-07/5 .66E-05       1.05E-02.

TABLEA-4 BETA CORRECTED SETPOINTS Beta Corrected Set Point= EMEC x SF x f3CF MAX SF J3-Corrected Monitor GPM (CW/RR) SP(f.l.Ci/cc) 1/2RE-229 22200 1.09E+01 1.14E-03 1/2RE-219/222 200 1.22E+03 1.26E-01 RE-230 700 3.47E+02 3.61E-02 RE-220 700 3.47E+02 3.61E-02 RE-218/223 100 2.43E+03 2.53E-01 1/2RE-216 4000 6.08E+01 6.32E-03 Page 152 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXB LIQUID DOSE FACTORS TECHNICAL BASIS TECHNICAL BASIS FOR PBNP SITE-SPECIFIC LIQUID DOSE FACTORS The site-specific liquid dose factors, presented in Table 9-2, have been extracted from the liquid dose equations outlined in Regulatory Guide 1.109, Section C.l, along with the guidance ofNUREG-0133. To obtain the liquid dose factors, all variables specific to each release of liquid effluents have been removed from the liquid dose equations ofRegulatory Guide 1.109, Section C. I. These include the dilution flow rate and the average release rate of the effluent. The dose factors for each liquid effluent pathway are calculated using the following equations: Aquatic Foods (Fish) Aio = 114000 X Mp X Uap X I i BipDaioe-A.itp [B-1] Where: Aio = Ingestion dose factor to the total body or any organ "o "for radionuclide "i" (mremlhr per j..LCi/mL) Mp = the mixing ratio (reciprocal of the dilution factor) at the point of harvest of aquatic food

                              = 0.1136 (Point ofharvest of the fresh fish is taken at a point 1 OOOm downstream. The plume centerline dilution factor at this location is 8.8 using RG 1.113 methodology.

The factor of 2 allowed for current reversals was not used. See Appendix E.) Uap = annual fish consumption rate for age group "a" and meat pathway "p" (kglyr)

                              = 0 kg/yr for infant
                             = 6. 9 kg/yr for child
                             = 16 kglyr for teen
                             = 21 kg/yr for adult (see RG 1.109, Table E-5 for maximum exposed individual)

Bip = the equilibrium bioaccumulation factor for radio nuclide "i" in pathway "p", expressed as the ratio ofthe concentration in biota (in pCi/kg) to the radionuclide concentration in water (pCi/1). (L/kg, see RG 1.1 09, Table A-1) Daio = ingestion dose factor for age group "a", radio nuclide "i" and organ "o",.from Reg. Guide 1.109 (mrem/pCi) 1 A.i = the radioactive decay constant of nuclide "i ", in day-tp = the average transit time required for nuclides to reach the point of exposure. For internal dose, tp is the total time elapsed between release of the nuclides and the ingestion of the water

                             = 0.5 d 114000 = conversion factor (pCi/J..LCi

mLIL per hr/yr)

Page 153 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Irrigated Foods (Meat From Watered Cattle) Aio = 114000 X Mp X Uap X QAw X Ii FtDaioe-Jt.its [B-2] Where: Mp = the mixing ratio (reciprocal of the dilution factor) at the point of harvest of aquatic food

                            = 0.1111 (Point at which water is taken from the lake is plume centerline I mile downstream. The plume centerline dilution factor at this location is 9 using RG 1.113 methodology. See Appendix E.)

Uap = annual meat consumption rate for age group "a" and meat pathway p" (kg/yr)

                            = 0 kg/yr for infant
                            = 41 kg/yr for child
                            = 65 kg/yr for teen
                            = 110 kglyr for adult (see RG 1.109, Table E-5 for maximum exposed individual)

QAw = consumption rate of contaminated water by an animal (Lid)

                           = 60 L/day (see RG 1.1 09, Table E-3)

Ff = stable element transfer coefficients (d/kg, see RG 1.1 09, Table E-1) Daio = ingestion dose factor for age group "a", radionuclide "i" and organ "o",from Reg. Guide 1.109 (mrem/pCi) li = the radioactive decay constant of nuclide "i ", in day- 1 ts = time .from slaughter to consumption (d)

                           = 20d (see RG 1.109, Table E-15) 114000   =   conversion factor (pCi/JLCi

mL/L per hrlyr)

Page 154 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Irrigated Foods (Milk From Watered Cattle) Aio = 114000 X Mp X Uap X QAw X I i FmDaioe-?t.itf [B-3] Where: Mp = the mixing ratio (reciprocal of the dilution factor) at the point of harvest of aquatic food;

                            = 0.1111 (Point at which water is taken as plume centerline 1 mile downstream. The plume centerline dilution factor at this location is 9 using RG 1.113 methodology. See Appendix E.)

Uap = annual cow's milk consumption rate for age group "a" and milk pathway p " (Liyr)

                            = 33 0 L/yr for infant
                            = 330 Llyr for child
                            = 400 Llyr for teen
                            = 310 Llyr for adult (from RG 1.109, Table E-5 for maximum exposed individual)

QAw = consumption rate of contaminated water by an animal (L/d)

                           = 60 L/day (see RG 1.1 09, Table E-3)

Fm = stable element transfer coefficients (d/L,from RG 1.109, Table E-1) Daio = ingestion dose factor for age group "a", radionuclide "i" and organ "o ",from Reg. Guide 1.109 (mremlpCi) Ai = the radioactive decay constant of nuclide "i", in day- 1 ft = transport time from pasture to cow, to milk, to receptor (d)

                           = 2 d (see RG 1.109, Table E-15) 114000 =     conversion factor (pCiiJLCi

mLIL per hrlyr)

Page 155 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Potable Water Aio = 114000 X Mp X Uap XL Daioe-A.itp [B-4] i Where: Mp = mixing ratio (reciprocal of the dilution factor) at the point ofwithdrawal of drinking water

                          = 0. 0384 (Withdrawal point is taken as the Two Rivers municipal water intake located a distance of 12 miles downstream. The plume centerline dilution factor at this location is 26 using RG 1.113 methodology.)

Uap = a usage factor that specifies the drinking water intake rate for an individual of age group "a" associated with pathway "p ";

                          = 330 Llyr for infant
                          = 510 Llyr for child
                          = 510 Llyr for teen
                          = 730 Llyr for adult (see RG 1.109, Table E-5)

Daio = ingestion dose factor for age group "a", radio nuclide "i" and organ "o ",from Reg. Guide 1.109 (mrem/pCi) 1 Ai = radioactive decay constant of nuclide "i", in day-tp = average transit time required for nuclides to reach the point of exposure. (d)

                         = 2 d (12.2 cm/s plus 12 hours to reflect the transport of the water through the water purification plant and distribution system) 114000  = conversion factor (pCi/jiCi

mLIL per hrlyr)

Page 156 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Shoreline Deposits Aio = 1.14£ + 07 X Mp X Uap X W XL TiDie-A.itp (1- e-A.itb) [B-5] i Where: Mp = the mixing ratio (reciprocal of the dilution factor) at the point of harvest of aquatic food;

                                    = 0.01821 (Point ofexposure is taken as the Point Beach State Park beach which is located 8000 meters downstream. The plume shoreline dilution factor at this location is 54.9 using RG 1.113 methodology. The factor of2 allowed for current reversals was not used.

See Appendix E) Uap = annual drinking water consumption for age group "a" and pathway "p" (L/yr)

                                    = 0 hr/yr for infant
                                    = 14 hr/yr for child
                                    = 67 hr/yr for teen
                                    = 12 hr/yr for adult (from RG 1.109, Table E-5 for maximum exposed individual) w   = the shoreline width factor;
                                   = 0.3 (from RG 1.109, Table A-2)

Ti = radioactive half-life ofradionuclide "i" (d) Di = the external dose factor for nuclide "i ", in mrem/hr per pCilm 2, taken from Table E-6 ofRG 1.109 1 A.i = the radioactive decay constant of nuclide "i ", in day-tp = the average transit time required for nuclides to reach the point of exposure (d)

                                   = 0.5 d tb  =  time  period of long-term buildup for activity in sediment or soil (d)
                                   = 5.47E+03 d (15 yr, see RG 1.1 09, Table E-15) 1.14E+07     =  conversion   factor (pCi/JLCi

mL/kg per hr/yr) and to account for the proportionality constant used in the sediment radioactivity model Following the guidance ofNUREG-0133, the adult age group represents the maximum exposed individual. Evaluation of doses for other age groups is not required for demonstrating compliance with the dose criteria of Section 6.2. To obtain a composite dose factor, the factors are summed for each liquid effluent pathway. (Reference Appendix K)

Page 157 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXC GASEOUS PATHWAY SETPOINT CALCULATIONS The calculation of the setpoints for airborne effluents is based on the tech spec requirement that the noble gas dose rate at the site boundary nearest the closest residence must be :=:;soo mrem/yr total body or:=:;; 3000 mrem/yr to the skin of the whole body. The calculation proceeds in a manner similar to the liquid EMEC calculation. First the average noble gas emission rate for each identified noble gas is calculated from the average annual effluent discharge. Next, the site boundary concentrations are calculated by multiplying the release rates by the dispersion coefficient, x!Q. Then the product of the individual noble gas concentrations and its dose factor is summed to determine the total dose rate from this noble gas mixture. Dividing this dose rate into the dose rate limit determines factor by which the average total site boundary noble concentration must be multiplied in order to achieve the concentration which will yield the limiting dose rate. Finally, based on the flow rate of an individual stack and applying the dispersion factor, the alarm setpoint for that stack monitor is calculated. The parameters for calculating the setpoints are shown in the spreadsheet below and the setpoints are calculated using either equation 10-1(total body) or equation 10-2 (skin). Page 158 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE C-1 NOBLE GAS RELEASES 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 Avg. (~i!yr} ;JCifyr} ((;il~r} JfWyr) (Cilyr) (Ci!yr) (Ci/yr) (Cilyr) (Cilyr) (Cilyr) (Cilyr) (Cilyr) .. Ar-41 1.35E+OO 9.28E-01 1.87E+OO 7.77E-01 8.47E-01 4.61E-01 5.45E-Ol 4.98E-01 1.55E+OO 7.67E-Ol 7.74E-Ol 8.52E-O! Kr-85 O.OOE+OO O.OOE+OO 4.87E-03 3.95E-04 O.OOE+OO 2.63E-04 O.OOE+OO O.OOE+OO 1.37E-03 8.66E-03 O.OOE+OO 1.41E-03 Kr-85m 1.47E-02 4.42E-04 4.67E-02 O.OOE+OO 2.84E-03 3.71E-03 1.43E-04 2.07E-04 8.47E-04 7.60E-03 9.73E-03 7.90E-03 Kr-87 3.51E-02 1.76E-03 !.68E-01 O.OOE+OO 7.27E-03 8.80E-03 O.OOE+OO 4.64E-04 2.10E-03 1.86E-02 2.35E-02 2.41E-02 Kr-88 3.52E-02 2.02E-03 1.61E-01 O.OOE+OO 7.62E-03 9.12E-03 O.OOE+OO 2.02E-02 6.50E-03 1.80E-02 2.33E-02 2.57E-02 Xe-13lm O.OOE+OO 1.15E-04 O.OOE+OO 7.00E-05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.70E-03 8.04E-04 O.OOE+OO 2.44E-04 Xe-133 9.86E-01 4.95E-Ol 2.37E-Ol 1.12E-01 3.70E-01 9.14E-02 4.13E-02 9.95E-02 3.32E-04 5.43E-02 2.83E-01 2.52E-01 Xe-133m 2.89E-03 4.72E-04 O.OOE+OO 8.37E-04 9.67E-04 5.19E-04 3.65E+OO 3.74E-04 2.77E-01 9.40E-04 2.11E-03 3.58E-01 Xe-135 1.75E-Ol 3.20E-02 4.10E-Ol 1.59E-04 1.97E-02 2.26E-02 9.32E-02 4.79E-03 4.05E-03 4.28E-02 6.14E-02 7.88E-02 Xe-135m 6.07E-02 O.OOE+OO 1.79E-Ol 3.46E-04 1.18E-02 1.74E-02 1.48E-02 9.53E-04 O.OOE+OO 3.36E-02 5.38E-02 3.38E-02 Xe-138 1.50E-Ol 8.77E-03 7.57E-Ol O.OOE+OO 3.25E-02 4.43E-02 3.89E-02 2.17E-03 1.14E-02 9.17E-02 1.16E-Ol 1.14E-01 TABLE C-2 AVERAGE ANNUAL DISCHARGE VOLUME RE-214 ABVS 66400 1.880E+09 9.883E+14 RE-225 CAE 20 5.663E+05 2.977E+ll l/2RE-215 CAE 10 2.832E+05 !.488E+ll IRE-212 U1 25,000 7.079E+08 2RE-212 U2 38,000 1.076E+09

                                     !12RE-212          Ul/2                35          9.911E+05        5.209E+ll RE-224           GSVS              13 000        3.681E+08        1.935E+14 RE-221           DAYS              43 100        1.220E+09        6.415E+14 Total cc r         1.823E+15 Page 159 of278                                                            REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL The average annual discharge volume is based on the flow from the four pathways monitored by RE-214, RE-221, RE-224, and RE-225. A random check of monthly effluent calculations show that over a span of one year, only the Aux. Bldg. Vent Stack, the Gas Stripper, and the Drumming Area Vent are important. The containment vents typically are about 35 cfm. The purges at 25,000 cfin occur during outages at a time when there no noble gas is detected in containment as all results are <MDA. Therefore, including the purge volumes would result in a less conservative calculated concentration by adding to the total volume at a time when no noble gases would be contributed to the total annual noble gas discharge. Also, not included are the GDT discharges. Their volumes are negligible in comparison to the main stack discharge volumes. TABLE C-3 NOBLE GAS SETPOINT PARAMETER CALCULATION

                                                 *                             ******. l\'{.I
                         *. Ayg.          Ci           Ki            L*
                                                                       . I                               CixKi ***.

9><(Li+

                       <;.   {Cilyr) *  (p.tCilcc) (Whole Body)      {skin) ..           {y.,.air)                    ~.1Mi)

Ar-41 8.52E-Ol 4.670E-10 8.84E+03 2.69E+03 9.30E+03 4.129E-06 6.034E-08 Kr-85 1.41E-03 7.758E-13 1.61E+Ol 1.34E+03 1.72E+Ol 1.249E-11 1.054E-09 Kr-85m 7.90E-03 4.335E-12 1.17E+03 1.46E+03 1.23E+03 5.072E-09 1.219E-08 Kr-87 2.41E-02 1.324E-11 5.92E+03 9.73E+03 6.17E+03 7.839E-08 2.187E-07 Kr-88 2.57E-02 1.411E-11 1.47E+04 2.37E+03 1.52E+04 2.074E-07 2.694E-07 Xe-131m 2.44E-04 1.341E-13 9.15E+Ol 4.76E+02 1.56E+02 1.227E-11 6.613E-ll Xe-133 2.52E-Ol 1.383E-10 2.94E+02 3.06E+02 3.53E+02 4.065E-08 9.600E-08 Xe-133m 3.58E-Ol 1.963E-10 2.51E+02 9.94E+02 3.27E+02 4.927E-08 2.657E-07 Xe-135 7.88E-02 4.319E-11 1.81E+03 1.86E+03 1.92E+03 7.818E-08 1.716E-07 Xe-135m 3.38E-02 1.857E-11 3.12E+03 7.11E+02 3.36E+03 5.792E-08 8.182E-08 Xe-138 1.14E-Ol 6.247E-11 8.83E+03 4.13E+03 9.21E+03 5.516E-07 8.909E-07 TOTAL 5.197E-06 8.042E-06 Inserting these calculated totals and this sector's x!Q into equations 10-1 and 10-2, the equations reduce to the following: SPTB O.JCi/cc) = 1.79E+02AFNF and SPs (!JCi/cc) = 6.95E+03AFNF , or SPTB (!JCi/cc) = 1.95E-04AF/(VF

x/Q) and SPs (!JCi/cc) = 7.58E-04AF/(VF* x/Q) .

From this it is seen that the limiting setpoints are derived using the total body dose rate restriction. The resulting setpoints are shown in Table C-4 where AF is applied only to RE-214, RE-221, RE-224, and RE-225. Page 160 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE C-4 RMS AIRBORNE ALARM SETPOINTS GASEOUS EFFLUENT MONITORS DISCHARGE DEFAULT PATHWAY FLOW RATE SETPOINT (cfm) (J.LCilcc) I. Auxiliary Building Vent RE-214 & SPINO 23 66,400 6.75E-04

2. Combined Air Ejector RE-225 20 2.24E+OO

3. Unit Air Ejector 1(2) RE-215 10 1.79E+01

4. Containment Purge Vent Unit 1 1RE-212 & SPINO 21 25,000 1 7.17E-03 Unit2 2RE-212 & SPINO 22 38,0002 4.72E-03 3

Unit 1(2) 1(2) RE-212 35 5.12E+OO

5. Gas Stripper Building RE-224 13,000 3.45E-03

6. Drumming Area Vent RE-221 & SPING 24 43,100 1.04E-03 Note 1: Two fans of 12,500 cfm Note 2: Two fans+ 13,000 cfm from gas stripper bldg.

Note 3: Forced vent with nominal 35 cfm flow rate Page 161 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXD GASEOUS DOSE FACTORS TECHNICAL BASIS TECHNICAL BASIS FOR PBNP SITE-SPECIFIC GASEOUS DOSE FACTORS The site-specific gaseous dose factors, presented in Chapter 10, have been extracted from the gaseous effluent dose equations outlined in Regulatory Guide 1.109, Section C.2, along with the guidance of NUREG-0133, Section 5.3. To obtain the gaseous dose factors, all variables specific to each release of gaseous effluents have been removed from the gaseous dose equations of Regulatory Guide 1.109. The dose factors for each gaseous effluent pathway are calculated using the following equations: Inhalation Pathway (see NUREG-0133, Section 5.3.1.1) Rio = 1 X 10 6 X BRa X Daio [D-1] Where: Rio = dose factor for each identified radionuclide "i" and organ "o" (m 2 (mrem/yr) per JLCi/s or mrem/yr per j.1Ci/m 3) BRa = breathing rate for age group "a"(m 3/yr): Infant= 1400 Child= 3700 Teen & Adult= 8000 (from RG 1.109, Table E-5 for maximum exposed individual) Daio = Inhalation dose factor for age group "a", radio nuclide "i" and organ "o ",from Reg. Guide 1.109 (mrem/pCi) 1E+06 = Conversion factor for pCi/Jl.Ci Ground Plane Pathway (see NUREG-0133, Section 5.3.1.2) (1- e-A.itb) Rio = 8.76 X 10 9 X SF X Daio X A* [D-2] L Where: Rio = dose factor for each identified radionuclide "i" and organ "o" (m 2 (mrem/yr) per JLCi/s or mremlyr per f.1Ci/m 3) Daio = ground plane dose factor for age group "a", radio nuclide "i" and organ "o ", (see RG 1.109, Table E-6) Ai = the radioactive decay constant of nuclide "i ", in sec- 1 tb = the exposure period (sec)

                                = 4.73E+08 s (15 yr,from RG 1.109, App. C.1) 8.76E+09      =  conversion factor for pCi/Jl.Ci and hrlyr SF =     shielding factor
                               = 0. 7 (see RG 1.1 09, Table E-15 for maximum exposed individual)

Page 162 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Grass-Cow-Milk Pathway The dose from the grass-cow-milk pathway is determined according to Equation 10-11. The produce Rio dose factor is calculated according to the following equation for all particulates and iodines, EXCEPT H-3 and C-14: Rio = 1£ + 06 X QfUapFmDaioe-A.itf X {fpfs + (1- {pfs)e-A.ith} X {r(l- e-(Ai+Aw)te + Biv(1- e-Aitb)} [D-3] Yv(A.i + A.w) PA.i Where: Rio = dose factor for each identified radio nuclide "i" and organ "o" (m 2 -mrem/yr per JLCi/s or mremlyr per 3 JLCi/m ) Qf = cow feed consumption rate (kg/d)

                                    = 50 kg/d (from RG 1.1 09, Table E-3)

Uap = annual cow's milk consumption rate for age group "a" and milk pathway p" (Liyr)

                                   = 330 Llyr for infant
                                   = 330 Llyr for child
                                   = 400 Llyr for teen
                                   = 310 Llyr for adult (from RG 1.109, Table E-5 for maximum exposed individual)

Fm = stable element transfer coefficients (d/L, from RG 1.109, Table E-1) Daio = ingestion dose factor for age group "a", radio nuclide "i" and organ "o ",from Reg. Guide 1.109 (mrem/pCl) Ai = decay constant of radio nuclide "i" (sec- 1) lj = transport time from pasture to cow, to milk, to receptor (sec)

                                   = 1.73£+05 s (2d,from RG 1.109, Table E-15) h   =  fraction of the year that cow is on pasture
                                   = 0.5 (from June 1976 Appendix I submittal to NRC.

Doc. Number NPC-27397) Is = fraction of cow feed that is pasture grass while cow is on pasture

                                  = 0.5 (from June 1976 Appendix I submittal to NRC.

Doc. Number NPC-27397) r = fraction of deposited activity retained on cow's feed grass

                                  = 1.0 for radioiodines
                                  = 0.2 for particulates (see RG 1.1 09, Table E-15) th  =   transport time from pasture, to harvest, to cow, to milk to receptor (sec)
                                  = 7.78£+06 s (90d, see RG 1.109, Table E-15)

Page 163 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Aw = decay constant for removal of activity on leaf and plant surfaces by weathering (sec- 1)

                          = 5. 73£-07 sec- 1(corresponds to a 14 day half-life, see RG 1.109, Table E-15)

Yv = agricultural productivity by unit area ofpasture feed grass (kg/m 2)

                          = 0.7 kg/m 2 (from RG 1.109, Table E-15) te =  time period that crops are exposed to contamination during the growing season (s)
                         = 2.59£+06 s (30d, see RG 1.109, Table E-15)

Biv = concentration factor for the uptake of radio nuclide

                          "!", expressed as the ratio of the concentration in biota (pCi/kg) to the concentration in water (pCi/L)

(see RG 1.109, Table E-1) tb = time period of long-term buildup for activity in sediment or soil (s)

                         = 4. 72£+8 s (15 yr, see RG 1.109, Table E-15)

P = effective surface density for soil (kg/m 2)

                         = 240 kg/m 2 (see RG 1.109, Table E-15) 1£+06   = conversion factor for pCi/Jl.Ci. This factor should be reduced to 5£+05 when calculating the dose factors for radioiodines. This accounts for the fraction of deposited elemental iodine that is accounted for in the dose modeling. See Reg. Guide 1.1 09, Appendix C, Section 3.a.

Page 164 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL For carbon-14, the milk pathway Rio dose factor is calculated according to the following equation: Rio = 1£ + 09 X 0.0.11 16 X FmUap X p X QtDaioe

                                                                            -kt t h                 [D-4]

Where: Rio = dose factor for radionuclide "i" (C-14) and organ "o" (mrem/yr per j1Ci/m 3) 0.11 = fraction ofplant mass that is natural carbon (see RG 1.109, eqn. C-8 0.16 = concentration of natural carbon in the atmosphere (see RG 1.109, eqn, C-8) Fm = stable element transfer coefficients (d/L, from RG 1.1 09, Table E-1) Uap = annual cow's milk consumption rate for age group "a" and milk pathway "p " (L/yr)

                               = 330 Llyr for infant
                               = 330 Llyr for child
                               = 400 L/yr for teen
                               = 310 L/yr for adult (from RG 1.1 09, Table E-5 for maximum exposed individual) p   =   Fractional equilibrium ratio
                              = 1 for continuous releases (from RG 1.1 09, page 26)

Daio = ingestion dose factor for age group "a", radionuclide "i" and organ "o ", (mremlpCi) (from Reg. Guide 1.1 09, Table E-ll) QJ = cow feed consumption rate (kg/d)

                              =50 kg/d (from RG 1.109, Table E-3) 1E+09    =   conversion factor for pCi/J1Ci and g/kg.

Ai = decay constant ofradionuclide "i"(C-14) (sec- 1)

                              = 3.84E-12 sec-1 th  =   time interval between harvest and consumption offood (sec)
                              = 1.73E+05 sec (2 d, RG 1.109, Table E-15)

Page 165 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL For hydrogen-3, the milk pathway Rio dose factor is calculated according to the following equation: 0.5 -A.*t Rio= 1E + 09 X 0.75 X HFmUapQfDaioe l h [D-5] Where: Rio = dose factor for radionuclide "i" (H-3) and organ "o" (mrem/yr per JLCi/m 3)

0. 75 = fraction ofplant mass that is water (see RG 1.1 09, eqn.

C-9)

0. 5 = ratio of tritium concentration in plant water to tritium concentration in atmospheric water (see RG 1.1 09, eqn, C-9)

H = absolute humidity at the location of interest (g/m 3)

                             = 5.5 g/m 3 (from E. L. Entier (1980), Health Physics 39:318-320)

Fm = stable element transfer coefficients (d/L, from RG 1.1 09, Table E-1) Uap = annual cow's milk consumption rate for age group "a" and milk pathway "p" (L/yr)

                             = 330 Llyr for infant
                             = 330 L/yr for child
                             = 400 L/yr for teen
                             = 310 L/yr for adult (from RG 1.109, Table E-5 for maximum exposed individuaV Qf =   cow feed consumption rate (kg/d)
                            =50 kgld (from RG 1.109, Table E-3)

Daio ingestion dose factor for age group "a", radionuclide "i" (H-3) and organ "o ", (mremlpCi) (from Reg. Guide 1.109, Table E-ll) 1E+09 = conversion factor for pCi/f.J.Ci and g/kg. Ai = decay constant ofradionuclide "i"(H-3) (sec- 1)

                            = 1. 78E-09 sec-1 th =  time interval between harvest and consumption of milk (sec)
                            = 1.73E+05 sec (2 d, RG 1.109, Table E-15)

Page 166 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Grass-Cow-Meat Pathway The dose from the grass-cow-meat pathway is determined according to Equation 10-11. The produce Rio dose factor is calculated according to the following equation for all particulates and iodines, EXCEPT H-3 and C-14: Rio = 1E + 06 X QfUapFfDaioe-A.its X {/pfs + (1- [pfs)e-A.ith} X {r(l - e-CA.i+A.w)te + Biv(l- e-A.itb)} [D-6] Yv(A.i + A.w) PA.i Where: Rio = dose factor for each identified radio nuclide "i" and organ "o" (m 2 (mrem/yr) per J1Cils or mrem/yr per 3 J1Ci/m ) Qf = cow's consumption rate (kg/day) . Uap = annual meat consumption rate for age group "a" and meat pathway "p" (kg/yr)

                                    = 0 kg/yr for infant
                                    = 41 kg/yr for child
                                    = 65 kg/yr for teen
                                   = 110 kg/yr for adult (see RG 1.1 09, Table E-5 for maximum exposed individual)

F1 = stable element transfer coefficients (d/kg, see RG 1.109, Table E-1) Daio = ingestion dose factor for age group ((a", radio nuclide "i" and organ ((o",from Reg. Guide 1.109 (mrem/pCi) Ai = decay constant of radio nuclide ((i" (sec- 1) ts = time from slaughter to consumption (sec)

                                   = 1. 73E+06 s (20d, see RG 1.109, Table E-15)
                          /p   =  fraction of the year that cow is on pasture
                                   = 0.5 (from June 1976 Appendix I submittal to NRC.

Doc. Number NPC-27397) Is = fraction of cow feed that is pasture grass while cow is on pasture

                                   = 0. 5 (from June 1976 Appendix I submittal to NRC.

Doc. Number NPC-27397) r = fraction of deposited activity retained on cow 's feed grass

                                   = 1. 0 for radio iodines
                                   = 0.2for particulates (see RG 1.109, Table E-15) th  =  transport time from pasture, to harvest, to cow, to milk to receptor (sec)
                                   = 7. 77E+06 s (90d, see RG 1.109, Table E-15)

Aw = decay constant for removal of activity on leaf and plant surfaces by weathering (sec- 1)

                                   = 5. 73E-07 sec-1 (corresponds to a 14 day half-life, see RG 1.109, Table E-15)

Page 167 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Yv = agricultural productivity by unit area ofpasture feed grass (kg/m 2)

                         = 0. 7 kg/m 2 (from RG 1.1 09, Table E-15) te = time period that crops are exposed to contamination during the growing season (s)
                        = 2.59E+06 s (30d, see RG 1.109, Table E-15)

Biv = concentration factor for the uptake of radionuclide

                         "!", expressed as the ratio of the concentration in biota (pCi/kg) to the concentration in water (pCi/L)

(see RG 1.109, Table E-1) tb = time period of long-term buildup for activity in sediment or soil (s)

                        = 4.72E+8 s (15 yr, see RG 1.109, Table E-15)

P = effective surface density for soil (kg/m 2)

                        = 240 kg/m 2 (see RG 1.1 09, Table E-15) 1E+06   = conversionfactor for pCi/jlCi Page 168 of278                           REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL For carbon-14, the meat pathway Rio dose factor is calculated according to the following equation: 0.11 -kt Rio = 1E + 09 X 0. X FfUap X p X QtDaioe l s [D-7] 16 Where: Rio = dose factor for radionuclide "i" (C-14) and organ "o" (mrem/yr per j1Ci/m 3) 0.11 = fraction ofplant mass that is natural carbon (see RG 1.1 09, eqn. C-8 0.16 = concentration of natural carbon in the atmosphere (see RG 1.109, eqn, C-8) Ff = stable element transfer coefficients (d/kg, see RG 1.1 09, Table E-1) Uap = annual meat consumption rate for age group "a" and meat pathway "p" (kg/yr)

                              = 0 kg/yr for infant
                              = 41 kg/yr for child
                              = 65 kg/yr for teen
                              = 110 kglyr for adult (see RG 1.1 09, Table E-5 for maximum exposed individual) p   =   Fractional equilibrium ratio
                              =I for continuous releases (from RG 1.109, page 26)

Daio = ingestion dose factor for age group "a", radio nuclide "i" and organ o ", (mrem/pCi) (from Reg. Guide 1.109, Table E-ll) Qf = cow feed consumption rate (kg/d)

                              =50 kg/d (from RG 1.109, Table E-3) 1E+09 =     conversion factor for pCi/J1Ci and g/kg.

i\i = decay constant ofradionuclide "i"(C-14) (sec- 1)

                                               -1
                              = 3.84E-12 sec ts  =  time from slaughter to consumption (sec)
                              = 1. 73E+06 s (20d, see RG 1.109, Table E-15)

Page 169 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL For hydrogen-3, the meat pathway Rio dose factor is calculated according to the following equation: 0.5 -A-t [D-8] Ria= 1E + 09 X 0.75 X HFfUapQfDaiae l s Where: Rio = dose factor for radio nuclide "i" (H-3) and organ "o" (mrem/yr per J1Ci!m 3) 0.75 = fraction ofplant mass that is water (see RG 1.1 09, eqn. C-9) 0.5 = ratio of tritium concentration in plant waer to tritium concentration in atmospheric water (see RG 1.1 09, eqn, C-9) 3 H = absolute humidity at the location of interest (g/m ) 3

                             = 5.5 g/m (from E. L. Entier (1980), Health Physics 39:318-320)

FJ = stable element transfer coefficients (d/kg, see RG 1.1 09, Table E-1) Uap = annual meat consumption rate for age group "a" and meat pathway "p" (kg/yr)

                             = 0 kg/yr for infant
                             = 41 kg/yr for child
                             = 65 kg/yr for teen
                             = 110 kglyr for adult (see RG 1.109, Table E-5 for maximum exposed individual)

Qf = cow feed consumption rate (kg/d)

                            =50 kg/d (from RG 1.109, Table E-3)

Daio = ingestion dose factor for age group "a", radio nuclide "i" (H-3) and organ "o ", (mremlpCi) (from Reg. Guide 1.109, Table E-ll) 1E+09 = conversion factor for pCi/jlCi and g/kg. Ai = decay constant ofradionuclide "i"(H-3) (sec- 1) 1

                            = 1. 78E-09 sec-ts =  time from slaughter to consumption (sec)
                            = 1.73E+06s (20d, see RG 1.109, Table E-15)

Page 170 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Fruit, Grain, Non-Leafy Vegetable (Produce) Pathway The dose from the fruit, grain, non-leafy vegetable (produce) pathway is determined according to Equation 10-11. The produce Rio dose factor is calculated according to the following equation for all particulates and iodines, EXCEPT H-3 and C-14: Rio = 1£ + 06 X t( 1 _ e-(A;+Aw)te) y: (It* It ) + B* ( 1- e-A;tb )} lv Pit* [gUapDaioe-A.ith [D-9] v l + w l Where: Rio = dose factor for each identified radio nuclide "i" and organ "o" (m 2 -mremlyr per jiCi/s or mremlyr per J1Ci/m 3) r = fraction of deposited activity remaining on crops

                                 = 1. 0 for iodines
                                 = 0.2for other particulates (from RG 1.109, Table E-15)
                        .Ai  = decay constant ofradionuclide "i"(sec- 1)

Aw = decay constant for removal of1 activity on leaf and plant surfaces by weathering, (sec- )

                                 = 5. 73E-07 sec-1 (14 day half-life, from RG 1.109, Table E-15)

Daio = ingestion dose factor for age group "a", radionuclide "i" and organ "o ", (mrem/pCi) (from Reg. Guide 1.1 09, Table E-ll) te = growing season (sec)

                                =5.18E+06 sec (60 days, from RG 1.109, Table E-15) tb      time that soil is exposed to the effluent (hr).
                                = 4.72E+08 sec (15 yr,from RG 1.109, Table E-15) th      time interval between harvest and consumption offood (sec)
                                = 5.18E+06 sec (60 d, RG 1.109, Table E-15)

Yv = agricultural productivity by unit area (kg/m 2) 2

                                = 2.0 kg/m (from RG 1.109, Table E-15) p   = effective surface      density of soil (kg/m 2) 2
                                = 240 kglm (from RG 1.109, Table E-15)

Biv = concentration factor for uptake of radio nuclide "i "from soil by edible parts of crops (pCi/kg, see RG 1.1 09, Table E-1)

                       /g   =  fraction    of ingestion taken from the garden of interest
                                = 0. 76 (from NUREG-0133, page 36)

Uap = annual produce usage rate (consumption rate) for age group "a" and produce pathway "p" (kg/yr)

                                = 0 kg/yr for infant
                                = 520 kglyr for child
                                = 63 0 kglyr for teen
                                = 520 kg/yr for adult (from RG 1.109, Table E-5 for maximum exposed individual) 1E+06     = conversion factor for pCi/J.l.Ci. This factor is reduced by 50% to 5E+05for iodines. (see RG 1.109, eqn. C-7)

Page 171 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL For carbon-14, the produce Rio dose factor is calculated according to the following equation: Rio = 1E + 09 X 0.0.1116 X [gUap X

                                                                         -A-t p X Daioe t h                 [D-10]

Where: Rio = dose factor for radionuclide "i" (C-14) and organ "o" (mrem/yr per J.1Ci/m 3) 0.11 = fraction ofplant mass that is natural carbon (see RG 1.1 09, eqn. C-8 0.16 = concentration of natural carbon in the atmosphere (see RG 1.109, eqn, C-8)

                       /g =   fraction of ingestion taken from the garden of interest
                               = 0. 76 (from NUREG-0133, page 36)

Uap = annual produce usage rate (consumption rate) for age group "a" and produce pathway p" (kg/yr)

                               = 0 kg/yr for infant
                               = 520 kg/yr for child
                               = 63 0 kg/yr for teen
                               = 520 kglyr for adult (from RG 1.109, Table E-5 for maximum exposed individual) p  =   Fractional equilibrium ratio
                              = 1 for continuous releases (from RG 1.109, page 26)

Daio = ingestion dose factor for age group "a", radio nuclide "i" and organ "o ", (mrem/pCi) (from Reg. Guide 1.1 09, Table E-ll) 1E+09 conversion factor for pCi/Jl.Ci and g/kg. Ai decay constant ofradionuclide "i"(C-14) (sec- 1)

                              = 3.84E-12 sec-1 th     time interval between harvest and consumption offood (sec)
                              = 5.18E+06 sec (60 d, RG 1.109, Table E-15)

Page 172 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL For hydrogen-3, the produce Rio dose factor is calculated according to the following equation: 0.5 -A.*t Ria = 1E + 09 X 0.75 X H f9 UapDaiae h l [D-11] Where: Rio = dose factor for radionuclide "i" (H-3) and organ "o" (mrem/yr per f1Ci!m 3) 0.75 = fraction ofplant mass that is water (see RG 1.1 09, eqn. C-9) 0.5 = ratio of tritium concentration in plant waer to tritium concentration in atmospheric water (see RG 1.1 09, eqn, C-9) 3 H = absolute humidity at the location of interest (g/m ) 3

                               = 5.5 g/m (from E. L. Entier (1980), Health Physics 39:318-320) h      fraction of ingestion taken from the garden of interest
                              = 0. 76 (from NUREG-0133, page 36)

Uap = annual produce usage rate (consumption rate) for age group "a" and produce pathway p" (kg/yr)

                              = 0 kg/yr for infant
                              = 52 0 kglyr for child
                              = 63 0 kglyr for teen
                              = 520 kglyr for adult (from RG 1.1 09, Table E-5 for maximum exposed individual)

Daio = ingestion dose factor for age group "a", radio nuclide "i" (H-3) and organ "o ", (mrem/pCi) (from Reg. Guide 1.109, Table E-ll) 1E+09 = conversion factor for pCi/Jl.Ci and g/kg.

                      .Ai =  decay constant ofradionuclide "i"(H-3) (sec- 1)
                              = 1. 78E-09 sec -I th =  time interval between harvest and consumption offood (sec)
                              = 5.18E+06 sec (60 d, RG 1.109, Table E-15)

Page 173 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Leafy Vegetable Pathway The dose from the leafy vegetable pathway is determined according to Equation 10-11. The leafy vegetable Rio dose factor is calculated according to the following equation for all particulates and iodines, EXCEPT H-3 and C-14: [D-12] Where: Rio = dose factor for each identified radio nuclide "i" and organ "o" (m 2 -mrem/yr per J1Ci/s or mrem/yr per J1Ci/m 3) r = fraction of deposited activity remaining on crops

                                 = 1. 0 for iodines
                                 = 0.2 for other particulates (from RG 1.1 09, Table E-15)

Ai = decay constant of radio nuclide "i "(sec- 1) Aw = decay constant for removal of activity on leaf and plant surfaces by weathering, (sec- 1)

                                 = 5. 73E-07 sec-1 (14 day half-life, from RG 1.109, Table E-15)

Daio = ingestion dose fact or for age group "a", radio nuclide "i" and organ "o",fromReg. Guide 1.109 te = growing season (sec)

                                =5.18E+06 sec (60 days, from RG 1.109, Table E-15) tb  =    time that soil is exposed to the effluent (hr).
                                = 4.72E+08 sec (15 yr,from RG 1.109, Table E-15) th =     time interval between harvest and consumption offood (sec)
                                = 8.64E+04 sec (1 d,from RG 1.109, Table E-15)

Yv = agricultural productivity by unit area (kg/m 2)

                                = 2.0 kg/m 2 (from RG 1.109, Table E-15) p   =    effective surface density of soil (kg/m 2)
                                = 240 kglm 2 Biv =      concentration factor for uptake of radio nuclide "i "from soil by edible parts of crops (pCi/kg) (from RG 1.1 09, Table E-1)
                      /g   =   fraction of ingestion taken from the garden of interest
                                = 1. 0 (from NUREG-0133, page 36)

Page 174 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Uap = annual produce usage rate (consumption rate) for age group "a" and produce pathway 'p" (kglyr)

                                = 0 kg/yr for infant
                                = 26 kglyr for child
                                = 42 kglyr for teen
                                = 64 kglyr for adult (from RG 1.109, Table E-5 for maximum exposed individual) 1E+06 = conversionfactor for pCi/jlCi. This factor is reduced by 50% to 5E+05 for iodines. (see RG 1.109, eqn. C-7)

For carbon-14, the leafy vegetable Rio dose factor is calculated according to the following equation: 0.11 -kt Rio = 1E + 09 X 0. 16 X [gUapDaioe r h [D-13] Where: Rio = dose factor for radionuclide "i" (C-14) and organ "o" 3 (mrem/yr per J1Ci/m ) 0.11 = fraction ofplant mass that is natural carbon (see RG 1.1 09, eqn. C-8 0.16 = concentration of natural carbon in the atmosphere (see RG 1.109, eqn. C-8)

                       /g =   fraction of ingestion taken from the garden of interest
                               = 1. 0 (from NUREG-0133, page 36)

Uap = annual produce usage rate (consumption rate) for age group "a" and produce pathway 'p" (kg/yr)

                               = 0 kglyr for infant
                               = 26 kg/yr for child
                               = 42 kg/yr for teen
                              = 64 kg/yr for adult (from RG 1.109, Table E-5 for maximum exposed individual)

Daio = ingestion dose factor for age group "a", radionuclide "i" and organ "o ", (mrem/pCi) (from Reg. Guide 1.109, Table E-ll) 1E+09 = conversion factor for pCi/jlCi and g/kg. Ai = decay constant of radio nuclide "i "(C-14) (sec- 1)

                              = 3.84E-12 sec-th =   time interval between harvest and consumption offood (sec)
                              = 8.64E+04 sec (1 d, RG 1.109, Table E-15)

Page 175 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL For hydrogen-3, the leafy vegetable Rio dose factor is calculated according to the following equation: 0.5 -A.*t Rio= 1E + 09 X 0.75 X H f9 UapDaioe h L [D-14] Where: Rio = dose factor for radio nuclide ai" (H-3) and organ ((o" (mrem/yr per jiCi/m 3) 0.75 = fraction ofplant mass that is water (see RG 1.1 09, eqn. C-9) 0.5 = ratio of tritium concentration in plant waer to tritium concentration in atmospheric water (see RG 1.1 09, eqn, C-9) H = absolute humidity at the location of interest (g/m 3) 3

                              = 5.5 g/m (from E. L. Entier (1980), Health Physics 39:318-320) h   =  fraction of ingestion taken from the garden of interest
                              = 1. 0 (from NUREG-0133, page 36)

Uap = annual produce usage rate (consumption rate) for age group ((a" and produce pathway 'p" (kg/yr)

                              = 0 kg/yr for infant
                             = 2 6 kg/yr for child
                             = 42 kg/yr for teen
                             = 64 kg/yr for adult (from RG 1.1 09, Table E-5 for maximum exposed individual)

Daio = ingestion dose factor for age group ((a", radio nuclide ((i" (H-3) and organ ao ", (mremlpCi) (from Reg. Guide 1.109, Table E-ll) 1E+09 = conversion factor for pCi/J1Ci and g/kg. Ai = decay constant ofradionuclide "i"(H-3) (sec- 1)

                             = 1. 78E-09 sec-1 th =  time interval between harvest and consumption offood (sec)
                             = 8.64E+04 sec (1 d, RG 1.109, Table E-15)

Page 176 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXE DERIVATION OF DILUTION FACTORS USING REGULATORY GUIDE 1.113 E.1 Liquid Effluent Dilution Factor Calculations E.1.1 Methodology The dilution factors used for calculating the doses from liquid effluent released to Lake Michigan were calculated using the methodology of Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I." The parameters used in the calculation and the results of the calculation are given in Table E-1. The results are presented graphically in Figure E-1. The centerline and shoreline values were calculated using Reg Guide 1.113 formulae 17 and 18 which apply to discharges to the Great Lakes. (The formulae are not presented here. See Section 5 of the PBNP FSAR for the formulae and origin of values used.) These results are applied as calculated for fish caught near PBNP. But for other pathways, an extra factor of two (2) is applied to account for current reversals which occur in Lake Michigan as described in the Appendix I, Section 5, of the PBNP FSAR. TABLE E-1 SURFACE DILUTION FACTORS FOR LIQUID EFFLUENTS IN A LARGE LAKE D9WN~~l\.M r,DJSTANGE ((n~t~rs5; 10 8.81 20 8.81 30 8.81 40 8.81 50 8.81 60 8.81 70 8.81 80 8.81 90 8.81 100 8.81 200 8.81 300 8.81 400 8.81 500 8.81 600 8.81 700 8.81 800 8.81 Page 177 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE E-1 SURFACE DILUTION FACTORS FOR LIQUID EFFLUENTS IN A LARGE LAKE DOWNSTREAM PLUME SHORELINE DISTANCE CENTERLINE (meters) 900 8.81 1000 8.81 122000 2000 8.86 1758 3000 9.01 401 4000 9.25 186 5000 9.53 116 6000 9.85 83.8 7000 10.2 65.9 8000 10.5 54.9 9000 10.8 47.4 10000 11.1 42.1 20000 14.0 24.0 30000 16.1 20.1 40000 17.7 18.7 50000 18.8 18.3 60000 19.6 18.2 70000 20.3 18.3 80000 20.9 18.6 90000 21.4 18.9 100000 21.9 19.2 200000 25.9 23.2 300000 29.2 26.9 400000 32.3 30.3 500000 35.2 33.3 600000 37.8 36.0 700000 40.2 38.6 800000 42.6 41.0 900000 44.8 43.3 1000000 46.9 45.5 NOTE 1: These values were calculated using the equation described in Section 5.2 of the PBNP FSAR and the following values: Ey 900 cm2/sec Zs 0 meters 2 Ez 2 cm /sec d 10 meters u 12.2 em/sec h 10 meters Ys 152.5 meters b 305 meters Discharge rate 42.2 m 3/sec Page 178 of278 REFERENCE USE

0"':rj 0'"0 Dilution Factor at Surface "':rj Vl

tnto Liquid Effluents in a Large Lake u 0 Vl om o> Vl(J tr1 tn~ n OF per Unit Release Rate r>

                                                                                                                                    ~2 rn 1.0E+06~----------------------------------------------~                                                       n     nr c      em epe(y}

900 om*vuo ~ ~~

                                                                                                                                    ~'"0 1.0E+05    ept(%.)

2 cm*ueec Shoreline ~

                                                                                                                                    ~r 0>

u

12.2 cm/aec u ~ Zz Yh}
1l52.C5 m

                                                                                                                 §
                                                                                                                              ~

Zf*}

0 m

~~

1.0E+04 d

10 m ~

                                                                                                                                    ~
                                                                                                                  ~

h

10 m

 '"0                       b

305 m

~.......... Olacharge rate .. 4Z..2 m-3/aec "':rj"':rj

>~

r r 1.0E+03 na

                                                                                                                  ~~
 ........:)
 \0 0

1--t) N Vlm

                                                                                                                  >~
 ........:)

00

Plume Centerline ~ 1.0E+O 1 ~-------------

                                                                                                                 ~>                 ~0 n                 ~      u tr1               ...... n 5*::s  ~

1.QE+QQI , I IIIII!! I I ll!l!f! I I Jill!!! I I 11!1111 I I 1"1 N 0 1.0E+01 1.0E+02 1.0E+03 tOE+04 1.0E+05 tOE+06

§                                          Downstream Distance (in meters)
 "':rj tr1 Area source, width 305 m and height 10 m n
 ~

tr1 cVl tr1

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL E.I.2 Dilution Factor Twelve Miles Downstream: Two Rivers Water Intake The dilution factors used at the Two Rivers water intake twelve miles downstream from PBNP included the factor of two described in Section DI.1. However, instead of using the straight centerline dilution factor shown in Table I, the weighted average dilution factor calculated over the width of the plume was used. The approach was used for the following reasons. First, the path that the current takes to reach the Two Rivers water intake is not straight. In order to reach Two Rivers, the water must flow southeast around Point Beach State Park, which juts into Lake Michigan, and then curves back 90 degrees towards Two Rivers. As a result of this deviation from straight line flow, any part of the plume or possibly none of the plume would impinge upon the intake structure. Second, there is a difference in the distance offshore of the PBNP discharge and the Two Rivers water intake. The Two Rivers water intake is located 5080 feet offshore. By contrast, PBNP discharges close to the shoreline through two flumes, one directed north and one directed south, and is modeled as a source that extends I 000 feet out into the lake from the shoreline. Based on these two considerations, it was concluded that the weighted average dilution across the width of the plume as it diverges while flowing south would constitute a better estimate of the dilution factor instead of the calculated for the centerline of an area source as is assumed for the FSAR calculation. The calculation and the values used are shown below. The average dilution factor at 12 miles downstream was calculated in the following manner: The standard deviation of the radionuclide concentration in the y direction at I2 miles downstream on the surface of the lake is 168.8 meters. This calculation used the following formula:

                                            ~y=J¥                                                    [E-1]

Where: (Jy = Standard deviation of the radio nuclide concentration in they direction By = Lateral turbulent diffusion coefficient (cm 2/sec)

                                = 900 cm2/sec X  =  Downstream distance (em)
                                =1.93E+06 em u  =   Current (em/sec)
                                = 12.2 em/sec At distances ofO.lcr, 0.2cr, etc. off the plume centerline, the dilution factor was calculated using the equation shown in Section 5.2 of the PBNP FSAR. The distances off the plume centerline, the calculated dilution factor, and the fraction of the area under the normal distribution curve is listed below.

Page I80 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL TABLE E-2 DILUTION FACTORS STANDARD DISTANCE FRACTION OF DILUTION DEVIATION (meters) AREA UNDER FACTOR CURVE1 O.lcr 16.9 0.080 13.8 0.2cr 33.8 0.080 14.0 0.3cr 50.6 0.078 14.3 0.4cr 67.5 0.075 14.7 0.5cr 84.4 0.072 15.2 0.6cr 101.3 0.068 15.8 0.7cr 118.1 0.065 16.6 0.8cr 135.0 0.060 17.6 0.9cr 151.9 0.056 18.8 I. Ocr 168.8 0.051 20.2 1.1cr 185.6 0.046 21.9 1.2cr 202.5 0.042 23.9 1.3cr 219.4 0.037 26.3 1.4cr 236.3 0.032 29.2 1.5cr 253.2 0.028 32.6 1.75cr 295.4 0.053 44.7 2.0cr 337.6 0.035 64.7 2.25cr 379.8 0.021 98.4 2.5cr 421.9 0.012 158.4 3.0cr 506.3 0.010 482 TOTAL 1.000 NOTE: It is assumed that the standard deviation of the radionuclide concentrations across the plume can be represented by a normal distribution curve. The fraction of the total area under the curve is that fraction of the area under the curve that lies between, for example, the interval O.lcr and 0.2cr which also includes the area of the curve in the interval-O.lcr and -0.2cr. The average dilution factor over the width of the plume was calculated by multiplying the dilution factor at each of the locations off of the plume centerline by the fraction of the total area of the curve occupied by that interval and then summing over all the intervals. An average dilution factor of 29 was calculated. Page 181 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXF RADIOLOGICAL IMPACT OF SEWAGE TREATMENT SLUDGE DISPOSAL NOTE: Appendix F is for historical reference. Land disposal of sewage sludge is no longer used at Point Beach The methodology for determining the radiological impact of land application of contaminated sewage treatment sludge is presented in this section. The evaluation must be made prior to every land application of sewage treatment plant (STP) sludge that contains licensed material. Sludge and other STP material which does not contain licensed material may be disposed of by any legal method without prior radiological analysis. F .1 Basis, Commitments and Actions F.1.1 Basis With the discovery that the PBNP STP sludge contained licensed material, Wisconsin Electric applied for NRC approval to dispose of the sludge by land application on land within the PBNP site boundary pursuant to 10 CPR 20.302(a). Wisconsin Electric committed to gamma isotopic analysis (GIA) of the sludge to measure the concentrations of licensed material in the STP sludge and to compare the results to concentration limits prior to each disposal [letter dated October 8, 1987 (VPNPD-87-430, NRC-87-104)] (See Appendix G). In addition, the dose to the maximally exposed individual of the general public and to the inadvertent intruder would be evaluated for the appropriate exposure pathways. F .1.2 Basis for NRC Commitment Modification Pursuant to NRC guidance, the sludge is clean if no licensed materials are found when analyzed under conditions necessary to achieve the environmental LLDs (NRC HPPOS 221 ). Clean sludge is not under NRC jurisdiction and may be disposed of by any legal method without prior radioanalyses. Therefore, if the sludge is clean and there is no pathway to the STP from the RCA, or pathways are administratively controlled to prevent the transfer of licensed materials to the STP, there is no need to analyze the sludge prior to any disposal. Since the 1987 commitment, engineering modifications and administrative controls have eliminated the pathways from the RCA to the STP. Three subsequent sludge GIAs (a total of eight STP samples) utilizing the analytical parameters required to achieve environmental lower limit of detection (LLD) found only naturally occurring radionuclides. In each analysis, the licensed materials were below the minimum detectable activity for the particular measurement and below the required LLDs. These results verify the efficiency of the modifications and administrative controls in eliminating pathways from the RCA to the STP. Therefore, because there is no longer any reason to believe that the PBNP STP sewage contains licensed material and there are no pathways from the RCA to the STP, the sewage may be disposed of by any legal method without GIA prior to each disposal. Page 182 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL F .1.3 Modification Periodic gamma isotopic analyses (GIA) of the STP sludge shall occur at a frequency set forth in the Chemistry Analytical Methods & Procedures (CAMP). This may include analyses prior to disposal depending on the results from the periodic analyses. The GIA of the STP sludge shall meet the LLD criteria of normal liquid effluents. The detection of any licensed material in the sludge during the periodic GIA shall necessitate returning to the GIA prior to disposal in order to evaluate the radiological consequences of the disposal. The GIA prior to each disposal shall continue until such time that the sludge can be shown, using environmental LLD criteria, not to contain licensed material. Also, re-initiation of the 1987 commitment to analyze the STP sludge prior to each disposal shall be required if plant conditions change in a manner which would lead one to believe that the STP sludge may be contaminated. An example of such a condition is the opening of valve STP-009 which is controlled by a tag. Again, reversion to a CAMP controlled frequency can occur only upon verification that no licensed material is in the sludge pursuant to the environmental LLD criteria. F .1.4 Exposure Evaluations If the sludge contains licensed material, the 1987 commitment requires that the appropriate exposure pathways be evaluated prior to each application of sludge to insure that the dose to the maximally exposed member of the general public is maintained at less than 1 mrem/year and that to the inadvertent intruder, at less than 5 mrem/year. Also, the measured concentration shall be compared to the liquid maximum effluent concentrations of Appendix B to 10 CFR 20. The exposure pathways evaluated for the maximally exposed individual are the following:

1. External whole body exposure due to a ground plane source of radionuclides.

2. Milk ingestion pathway from cows fed alfalfa grown on plot.

3. Meat ingestion pathway from cows fed alfalfa grown on plot.

4. Vegetable ingestion pathway from vegetables grown on plot.

5. Inhalation of radioactivity resuspended in air above plot.

6. Pathways associated with a release to Lake Michigan. These pathways are ingestion of potable water at the Two Rivers, Wisconsin municipal water supply, ingestion of fish from edge of initial mixing zone of radionuclide release, ingestion of fresh and stored vegetables irrigated with water from Lake Michigan, ingestion of milk and meat from cows utilizing Lake Michigan as drinking water source, swimming and boating activities at the edge of the initial mixing zone, and shoreline deposits.

The exposure pathways evaluated for the inadvertent intruder are the same as items 1, 4, 5, and 6 identified above for the maximally exposed individual. Page 183 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL F .2 Procedure The following steps are to be performed by the responsible Chemistry Specialist for each contaminated sewage treatment sludge disposal.

1. Determine the radionuclide concentrations in each representative sewage treatment sludge sample. The minimum number of representative samples required is three from each sludge storage tank. The average of all statistically valid concentration determinations will be utilized in determining the sludge storage tank concentration values.

2. Verify that the concentration of each radionuclide meets the concentration and activity limit criteria. The methodology for determining compliance with the concentration and activity limit criteria are contained in Wisconsin Electric letter VPNPD 87-430.

3. Verify that the proposed disposal of the sewage treatment sludge will maintain doses within the applicable limits. This calculation will include radionuclides disposed of in previous sludge applications. The activity from these prior disposals will be corrected for radiological decay prior to performing dose calculations for the meat, milk, and vegetable ingestion pathways, the inhalation of resuspended radionuclides, and all pathways associated with a potential release to Lake Michigan. The residual radioactivity will be corrected, if applicable, for the mixing of radionuclides in the soil prior to performing external exposure calculations.

Microshield, a nationally recognized computer code, will be used to calculate the dose rate due to standing on a plot of land utilized for sludge disposal in which the radionuclides from prior disposals have been incorporated into the plot by plowing. This calculated dose rate will be used to assess the radiological consequences from prior disposals with the consequences of proposed future disposals. The total radiological dose consequence of the past and the proposed disposal will be compared to the applicable limits to insure the dose is maintained at or below the limits. The methodology for calculating the radiological impact of the sewage treatment sludge disposal is contained in Wisconsin Electric letter VPNPD 87-430.

4. Inform the appropriate Chemistry Specialist that the sewage treatment sludge disposal may proceed after verifying that the sewage treatment sludge meets the concentration, activity, and dose limits.

5. All calculations shall be included with the sewage treatment sludge disposal record.

Page 184 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL F .3 Administrative Requirements The following steps are to be performed by the responsible Chemistry Specialist for each contaminated sewage treatment sludge disposal.

1. Complete records of each contaminated disposal shall be kept as follows:

a. Radionuclide concentration of the sludge

b. Total volume of the sludge disposed

c. The identity of the plot used for the disposal

d. Dose calculation results

e. Results of annual chemical composition determination

2. Modifications to the WE application as documented in the October 8, 1987, letter shall be processed in accordance with NP 5.1. 7, Regulatory Commitment Management.

(CCE 001-013)

a. Commitment Change - 1 Section 3.2 of Attachment II of the submittal states that physical and chemical properties of the sludge would be determined prior the each land application.

Pursuant to a change in the PBNP WPDES Permit, non-radiological properties are now determined annually instead of per application. The frequency for radiological characterization did not change. (See Appendix H and CCE 2002-002)

b. Commitment Change - 2 In Section 3.3 of Attachment II of the submittal letter, the annual disposal rate was ... "

limited to 4,000 gallons/acre, provided WDNR chemical composition, NRC dose guidelines and activity limits are maintained .... " Modification 2 removes the 4,000 gallon limit and makes the application unlimited provided the WDNR and NRC constraints are met. (See Appendix I and CCE 2002-004) Page 185 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

c. Commitment Change - 3 In Section 3.2 of Attachment II ofNRC submittal letter dated October 8, 1987, Wisconsin Electric committed to gamma isotopic analysis (GIA) to determine the concentration of licensed material in sewage treatment plant (STP) sludge prior to each disposal. Pursuant to NRC HPPOS-221 guidance, the sludge has been shown to be clean on three different occasions after pathways from the RCA to the STP were eliminated by plant modifications and administrative controls. Pursuant to HPPOS, the sludge analyses were done under the conditions necessary to achieve the environmental LLDs. Only naturally occurring radionuclides were found and licensed material was below the minimum detectable concentration. This indicates that the former pathways from the RCA to the STP had been eliminated. Therefore, there is no need to continue the analyses because there is no RCA to STP pathway and there is no reason to believe that the sewage contains licensed material. Hence, the commitment to analyze STP sludge prior to every disposal is modified and replaced with periodic analyses at a frequency set by CAMP 914. However, if plant conditions change in a manner which places the STP sewage outside the guidance parameters which allowed for the discontinuance of analyses, the sewage must be analyzed prior to each disposal until it again is shown not to contain licensed material. (See Appendix J and CCE-2002-3)

Page 186 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXG VPNPD-87-430, NRC-87-104 Wisconsin Electric submittal to the United States Nuclear Regulatory Commission, dated October 8, 1987 (VPNPD-87-430, NRC-87-104) The submittal consists of the letter and two Attachments. Attachment II contains Appendices A-G. Pursuant to the NRC letter of January 13, 1988 (NPC-30260), a copy of the submittal (VPNPD-87-430, NRC-87-104) must be permanently incorporated into the ODCM as an Appendix and future modifications of the letter be reported to the NRC in accordance with commitments regarding ODCM changes. Page 187 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL VPNPD-87-430 NRC-87-104 October s. 1987 U.S. NUCLEAR REGULATORY COMMISSION DOCUJ(tent Control Desk Washington, D.C. 20555 Gentlemen: DOCKET NOS. 50-ZGG AND S0-301 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR 10 CFR 20.302 APPLICATTON POINT BEACH NUCLEAR PLANT

On ~uly 14. 1987, Wisconsin Electri~ ~9wer company submitted an appl-ication, under the provisions o~,.~Q".,::;cFR 2.0-.3-02;,,;,.i.P!':;~PP,!i:9.V..:tl.-

of a proposed procedure to dispose of sewage treatment sludge containing minute quantities of radioactive materials. Sub-sequent to the application, Mr. Ted Quay of the NRC staff requested additional information regarding the environment*al characteristics of the area surrounding the Point Beach Nuclear Plant. The responses to this request were furnished in our submittal d~ted August &, 1987. By letter dated september 9. 1987, the NRC has requested Wisconsin ElecLtic s,upply ddditional information in order to complete the review of our application. This Request for Additional Information (RAI) contain~ ten specific items which require responses or commitments from Wisconsin Electric. In addition, the NRC rcqucctc the previously submitt~d information and the information supplied in response to the RAI be compiled into "one complete, extensive, and self-contained package". To facilitate your review, Attachment l is included to provide rlirf:"r.t: rf:"sponsf:"s to the ten it~ms.: c:ont.ained in the RAI. Attachment It is provided as the complete application, including the info~rnation from our letters dated ~uly 14, 1987, and August 6, 1987, and information supplied in response to the NRC RA!. _sr., J We request that you complete your review of this complete, self-contained package and issue an approval of our application RECElVEfl) OCT 12 1987 romT BfACH Page 188 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL NRC Document Control Desk Cctober 8, 1987 Page 2

as soon as po~5ible. ln order to facilitat~ you* ~eview anct to expedite processing, we would be pleased to discuss these matters or provide additional information by telephone. Please feel free to contact us.

Very truly yours,

c. w. Fay Vice President Nuclear Power bjm Attachments Copies to NRC Resident Inspector NRC Regional Administrator, Region III Blind copies to Britt/Gorske/Finke, Burstein; Charnoff, Fay, K~ieser, Lipke, Newton, z~

Page 189 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL ATTACHMENT I

                             * ('* ' * * *. '* ~ L

RESPONSES TO*QUESTIONS CO~TAINEO IN THE REQUEST FOR AOOITIONAL:INFORMATION (RAI)

ON POINT* BEACH 1 AND 2 .REQUEST FOR DISPOSAL OF LOW LEVEL RADIOACTIVITY CONTAMINATED SEWAGE SLUDGE BY lANO APPLICATION WISCONSINELECTRIC POWER COMPANY

                  *UNDER 10 CFR 20.302(a)

Page 190 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Tne numbering system used in these responses corresponds directly to numbering used in the NRC RAI, dated September 9. 1987.

1. a. This request is for multiple applications) approximately 2 to 4 per year.

b. This request is for multiple years, expiration to toincide with conclusion of decommissioning activities associated with retirement of PBNP Units 1 &2.

c. Please refer to the response to question number 10 .

      .2. The pathways used to determine doses to both the maximally exposed individual and the inadvertent intruder are documented in Attachment II. Ar?endices 0    a~d  E.

Due to the ~xtremely low concentrations of radionuclides in the sewage sludge and the associate low doses, Wisconsin Electric will control access to the disposal sites by conditions of use defined in lease agreements with the lease. Use of the land is* not controlled beyond the conditions of the leasep thereby not restraining a casual vi~itor from the disposal site. However continuous occupancy would be readily observed. and remedial action would be taken.

3. Information contained in previous .sub~~nittal5 has bct'n included in Att£chment II with modifications to provide specific commitments to the NRC. .

4. Please refer to the response to question number 10.

5. Site maps have been updated and are included in Attachment 11.

Appendix c.

Tne- dir~ct. orazina of catt.l~ on th~.rroposed disposal sites is controlled by restrictions containe'd(;."i:fr**the lease ~.?greement. . . . . i~

There will be no restrictions placed or. fishermen on Lake Michigan. Calculations of dose~ due ~o all pathways associated w~th a release to Lake Michigan (Attachment 11. Appendix E) do not indicate a need to apply rc~trictions to fishermen.

7. Please refer to revised site maps included in Attachment II~

Appendix C. Site number 5 is located on company owned land beyond the PBNP site boundary. All other sit~s are within the PRNP site boundary area.

8. a. Please refer to Attachment II~ Section 3.2, Disposal Procedure.

b. Please refer to Attachment II. Section 3.Z, Dispo~dl Pro~edure.

c. Please refer to Attacbment II, Section 3.2, Disposal Procedure.

d. Please refer to Attachment II, Appendix A.

9. Please refer to Attachment 11. including Appendix D and Appendix E for additional pathways analyzed for this subMittal. These identified pathways wi 11 be analyzed prior to all subsequent disposals to insure- :r="

doses are maintained within prescribed limits. i.e., 1 ~rem/year to the maximally exposed individual and 5 mrem/year to the inadvertent intruder.

10. A limiting concentration level for the sludge contained in the storage tank 1s discussed. in Attachment II. Appendix f. Since this application is for multiple applications over multiple years.

Attachment II, Appendix F also addresses an activity limit. Page 191 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL ATTACHMENT II COMPi.rETE ANA~VSIS AND EVALUATION POINT BEACH t~UCLEAR PLANT 10 CFR 20. 302(a) A'PPLICATION Page 192 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

1. 0 , Purpose _

By tn1s submittal W1scens1n Electric Power Company requests approval of the U~S. Nuclear Regulatory Commission for a proposed procedure to dispose of sewage treatment sludge containing trace quantities of radionuclides generated at the Point Beach Nuclear Plant. This request is submitted in accordance with the provisions of 10 CFR 20.302(a). 2.0 Waste De!cription The waste involved in this disposal process consists of the residual solids remaining in solution upon completion of the aerobic digestion sewage treat-ment process utilized at PBNP. The PBNP sewage treatment plant is used to pror.ess waste water from the plant sanitary and pot..:tble watEllr systems. These systems produce non-radioactive waste streams with the possible exception of wash basin~ located in the r~dio1ogica11y controll~d ~rea of the plant. These wash basins are believed to be the primary source of the t!!.xtrfllft@ly small quantities of radionuclfdes in the sludge. The sewage sludge generated at PBNP is allowed to accumulate in the sewage plant digestor and aeration basin. Two to four times annually, depending on work activitie; and corresponding work foree at PCNP, the volume of the sludge fn the digestor and aeration basin needs to be reduced to allow cor.tinued efficient operation of the treatflleot facility. The lolal volume of sludge removed during each disposal operation is typically on the order of 15,000 gallons.. The max~mum capacity for the entire PBNP treatment facility and hence the maximum disposal volume is about 30,000 ga~lons.

         *In .the**_case of. a maximum. capac i ty ..di spo:$4!1

doses wou:l.d,~.n9;t:.*OeJ:es~arily . , ...,.~

increase i o- proportion to the vo 1ume. sli.Ce more than 'One** d*i sposa 1 site may be used. Tt*ace amounts of rad'ionuclides have been ident'if1ed in PBNP sludge currently

       . be-ing stored awaiting. di-sposal. The radionucl ides identified and their concentrations in the sludge are summarized b*elow=

Nuclide Concentration (!JCi/cc} Co-60 2.33E-07 Cs-137 1. SOE-07 lhe total activity of the radionuclides in the storedslud\,!e. based on thE! identified concentrations and a total volume or 15,('00 gallons of sewage sludge. are as follows: NuclidP Activity (&JCi) Co-60 13.2 Cs-137 8.5 These concentrations and activities are consistent with expected values bas~d on prior analysea of sewage sludge. The redionu~lide concentration in thP sewage sludge has remained relatively constant during sampling

        *conducted       ~inc~ December 30, 1993.       A detailed summary of the r-e$ult.!t of this saw.pling program are contained in Appendix A for your review.

Page 193 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL In addition to monitoring for the radionuclide content of the sludge .. the WONR requires sever a 1 other phys tea 1 and chemical propet*l i e~ uf .,the . sludge to be determined. These properties are the percent total solids, percent total nitrogen. percent ammoni~m nitrogen, pH. percent total phosphorus, percent total potassium~ cadmium, copper, lead~ nickel~ mercury, zinc, and boron. An example *Of a typical sludge sa~~nple analysis is included in Appendix B 3.0 Olsgosal Me\hod

                                        ~, ' ,~'I"

In the context of thts application. Wisconsin Electric commits to the following methodology. No di~tinction is made or intended between nshallu or 11 wi11". as used in the de:s.criptions contained in this section.

3.1 Transport of Sludge Th~ method us~d to dispose of the sludga shall utililP ~ technique approved by the WDNR. The process of transporting the sewage sludge for disposal involves pumping the sludge from the PBNP 'ewage treatment plant storage tanks into a t~uck ~ounted tank. The truck mounted tank shall be required to be maintained tightly closed to prevent spillage while in transit to the disposal site~ The sludge shall be transported to one or more of the six sites approved by the WDNR for land application of the iewagc sludge from PBNP. 3.2 Disposal Procedure The radionuclide concentrations in the sludge shall be determined prior to.iea.ch. dtsposa} py 9bt~1.~.1_!l,Q. th_ree- representa~ive -~amR"l.~s.:f.J:_'?~*:,:~.:ach_, !.::..*_A of the sludge storage tan~s. *Tne* sludge conta11.ed in the sludge tanks is prevented tr~;m going septic by a process Known as complete mh: and continuous aera~ion~ This process completely mixes the sludge allowing for representat~vr samples to be obtatned. The samples shall ~e counted utilizing ~ Geli detect~r and multi-channel analyzer wi~h appropriate geometry? The detection system is routinely calibrated and checked to ensure the 1ower l in:i ts of detection are within values specified in the Radiological Effluent Technical Specificati~ns (RETS). To insure the samplef are representative of the overall ctncentration. in the storage tanks. the radionuclide concentration deter~lnation for each of the three samples s~a11 be analyzed to insure each sample is within t~o standard deviations of the.averaae value of tha three samples. If this criteria is not met. addiiional samples will be 6titaf~ed and*analyzed to insure a trtily repr~~~ntative radionuclide ccncentration is utilized for dose calculations and concentration limit determinations. 1he average of all statistically vali,q-:: . ,1:,. concentration determinntions will be utilized in determining the ttoragc tank conc~ntration value~. Page 194 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Prior to disposal the waste stream will be monitored to determine the physical and chem1cal properties or the sludge, a~ d,1scussed ..Jn l-h~ last paragraph of Section 2.0t Waste Description. The results will be compared to State of Wi~consin limits to insure the sludge does not pose a chemical hazard to people or to the environment. The ra~ionuclides identified in the slu~~e. along wit~ their respective conce~trations. will ba compared to concentration limits prior to dtsvosal. The methodology discussed in Appendix F will be used in determi n~ ~.9 ~OWP~.i ance w.i th the proposed concentrat i9n 1i.~it!....}.he... total activity of the proposed disposal will be compared to the"

proposed activity limit as described in Appt*ll:lix F.

If the concentration and activity limit criteri'a are met, the appropriate exposure pathways (as described in Appendix D) will be ev~luated prior to each app 1i cation of s 1udge. These exposures wi 11 be eva 'I uated to insure the do~~ to th~ maximally exposed individual will be maintained less than 1 mremlyear and the dose to the inadvertent intruder is maintained less than &mrem/year. The exposures will be calculated utilizing the meth-odology used in Appendix E, including the current activity to be landspread along with the activity from all prior disposal. The remaining radio-activity from prior disposals will be corrected for radiological decay prior to performing dose talculations for the meat, milk, and vegetable ingestion path :"ays. the inhalation of resuspended radionuclides, and all 1 pathways as so..: i a ted with a r*e lease to lake Michi gdn. The rt!'!l hh.ta 1 radio-activity will be corrected for radiological decay and, if appr*opriatea the mixing of the radionuclides in the soil by plowing prior to performing external exposure calculations.

       ' . , ... <   ' **    *   "* *"                         ,:            l !..~*;r The sewage sludge fs app 1fed on the des i ~nated area of 1and uti 1i z*i ng the - '

WONR approved technique and adhering to the following *requirements of WPOES Permit Number WI-0000957-3. 0 Discharge t.o the land disposal. system shall be limited so that during surface spreading all of the sludge and any precipitation* falling onto or flow*ng onto the disposal field shall not overflow the peri-meter of the system. 0 Sludge shall not be land spread on land with a slope greater than 12%. During the period from December 15 throuah March 31 sludae shall not be land spread on land with a slope greater than 6% unless the wastes are injected im~ediatQly into the soil. 0 Sludge shall not be surface ~pread closer than 500 feet from the nearest inhabited dwelling except that this distance may be reduced

       ..;..:;~::~::.:t',~"l:.fn~::o\iln~:t,;.s""wrft*te'f1"'~Qil$'0'nt~-=.c~:+/-.;;.....J.:.;;.;_'-::.:.:.....E:.::z..~.:. -    c:.~-.=**:*~ .:._

Sludge shall not be spread closer than 1,000 feet ft~Pm a public water supply well or 250 feet from a private water supply well. 0 Sludge shall not be land spread within 200 feet of any surf2ce water unless a egetative buff~r strip is maintained between the surface watercourse and the land spreading 1ystem, in which case a minimum separation distance of et least 100 feet is required between the system and the surface watercourse. Page 195 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL 0 Depth to groundwater and bedrock shall be greater than 3 feet from the land 5urface elevation during use of any site. 0

Sludge shall not be land spread in a floodway.

Sludge shall not be land spread within 50 feet of a property line road or ditGh unle~$ the sludge is incorporated with th~ SQil. in whi~h case a minimum separation distance of at least 25 feet is required. 0 The pH of the sl~dge-soil mixture shall be maint~ioed at 6.5 or higher.

  ;" *.r'TM' 0

low areas of the approved fields, subject* to seasC~na lly h.i gh ground-water levels, are excluded from the sludge application. Ct'ops for human consUfl!lption shall not be grown Of'i the land for up to one year following the application of the sludge. 0 The sludge shall be plowed, disked. injected or otherwise incorporat&d into th~ surface soil layer at appropriate intervals. Jhe ttexibility implied in the l~tter provision for so11 1ncorporat1on i~ intended to allow for crops which require more than a one year cycle. For the Point Beach disposal sites. alfalfa is a common crop which is l'arvested for several years after a single planting. Sludge disposal on an alfalfa plot constitutes good fertilizatioil, but the plot cannot be plowed without destroying th~ crop. Th~ alfalfa in this case aids in binding the layer of sludge on the surface of the plot. At a minimum. however, plowing (or diskfng or other ~ethod of injection and mixing to a nominal depth of 6 inches) shall be done prior to planting any new crop, r~p~rdlPss of the crop . 7

    .. ~- :rr7.!1Ti. 'j' id~T~i s"t,rat i ve Pr~~-ed~res c~~pleta   records of each disposal will     b~  maintained. These records will include the concentration of radionuclides in the sludge, the total volume of sl.~dge disposed. the total activity, the plot on which the sludge was applied, the results of the chemical composition determinations. and a-ll dose calculations.

The annual disposal rate for each of the approved land spread sites will be limited to 4,000 gallons/acre, pro\lided WONR chemical composi-tion. NRC dose guidelines, and concentrotion and activity limits arc maintained within the appropriate values. The farmer leasing the site used for the disposal will be notified of lhe appl h;able re!tt.ricticns plcu;.ed ou the !!tite due to the land spreading of sewage sludge. 4.0 Evaluation vf Environmental Impact 4.1 Site Characteristics

4. 1. 1 Site. TopograP._h.Y The disposal site~ are located in th~ Town of Two Creek~ in the northeast corner of M~nitowoc County. Wisconsin, or. the Page 196 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL west shore of lake Michigan about 30 miles southeast of the center of the city of Green Say, and 90 m11es NNt of Milwaukee. This site is located at longitude 87° 32.s~w and latitude 44° 11.o*r-L The six sites** a're on property owned and controlled* by Wisconsin £l~ctric and are within or directly adjacent to the Point Beach site boundary. lhe sites ~re described below and are outlined on the Map conta.im~d fn Appendix C as Figure 3. Site No. PB The approximately 15 acr~s located in thg NE 1/4 of the NE 1/4 of Section 23, T. 21N - R. 24E. Site No. PB The approximately 20 acres located in the SE 1/4 of the St 1/4 of Section 14. T. 21N - R. 24E. Site No. PB The approximately 5 acres located in the NW 1/4 of Secticn 24 T. 21N - R. 24E. 1 Site No. PB The approximately &acres located in the NW l/4 of the sw 1/4 of seetion 2~. T. 21N = R. 24E. Site No. PB-0!) - The approximately 5 acres located 1n the NE

                 *114 of the NW 1/4 of Section 25, T. 21N - R. 24E.

Site No. PB The approximately 5 acres located in the N[ 1/4 of the SW 1/4 of Section 14. T. 21N - R. 24E. The overall ground surface at the site of the Point Beach Nuclear Plant is gently rolling to f1at with elevations varying from 5 to 60 feet above the level of Lak~ Michigan. Subdued knob and .kettlE!! t,oP.oJJr:aphy ie; visibl~ fr:om aerial photographs. The

               ;<;land~sur;face,~s~ope$*."'gra'duaiiY toward *tn*e lake' fromi ttle ,*higher~ '*

glacial ~oraine areas west of the site. Higher ground adjacent to the lake. however, diverts the drainage to the north and south. The major surface drainage featur@& are two small creeks whieh drain to the north and south. One creek discharges into the loke about 1500 feet above the northern corner of the !;.ite and the other near the center of the site. During the spring. ponds of water may occupy the shallow depre~sion~. As mentioned in Section 3.2, Disposal Proc2dure, these low areas are excluded from the sludge application. A sile topogr~phi~ mdp ~ov~ring details out to a 5 mile radius may be found in the FSAR at figure 2.2-3 and is included in Appendix C as Figure 2. The disposal or sewage sludge at these s1x sites will hdv(:!' no impact on ~the ~~pography of this area. i* "-:'.:

4. L2 Sjte Geology Prior to cr,nst, .*ction of the Point Beach Nuclear Plant, an evaluation of the geological characteri~tics of the ar~a in and surrounding the site was made. The geologic structure of the region is essentially simple. Gently dipping sedimentary rock Page 197 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL strata of Paleoloic age outcrop in a horseshoe pattern around a shiQld of Precambrian crystalline rock which occupies the western part of the region. The site is located on the western flank of the Michigan Basin. which is a broad downwarp ringt>d by discontinuous outcrops of more resistant formations. The bedrock formations are principally limestonQs, dolomite,, aad sandstones with subor*dinate shale layers. The rocks form a succession of extensive layers that are relatively uniform in thickness. lhe bedrock strata dip very gently towards lake Michigan at rates from 15 to 35 feet per mile.

                         ~. ,,*.-'-;;,'- ~ft)f'                                                    d, \

The uppermost bedrock under the site is Niagara Dolomite. Bedrock does not outcrop on the site but is covered by glacial ttll and lake depos1ts. The soils conta1n e~pans1ve clay

                    ~inerals and have moderately high base exchange capacity.

ln the area of the site, the overburden soils are approximately 70 to 100 feet in thickness. Although the character of the glacfal deposit~ may vary greatly within relatively short distances, a generalized section through the overburden soils adjacent to take Michigan at the site consists of the following sequence:

1. An upper layer of brown clay silt topsoil underlain with several feet of brown silty clay with layar~ of ~ilty ~and;

2. A layer of 20 feet of reddish-brown silty clay with $Ome sand and gravel and occasional lenses of silt;

               , .. l.=A.. ,l.a~er;.,o~f~-~~fe~~ !J.:r. N!ddish:brown* 'silty cl~Y  w.i.t.ll ,tlaJI.er~~}_,.;

of s1lty sand and lenses of s1lt;

4. A layer or 50 feel cf reddish-brown s.ilty clay with some sand and gravel, the lower portion of which contains gravels, cobbles, and boulders resting on a glacial eroded surface of Niagara dolomite bedrock.

Site drainage is poor due to the high clay content of the soil combined with the pock-marked surface. Additional information on site geology may be found in Section 2.8 of the FSAR. The use of these sites for disposal of sewaQe sludge will not jmpact the geology of the area. 4.2 Area Characteristics

4. 2.1 Meteorology

                  . The ~li_mate of the site region is influenced by the general storms which move eastward along the north~rn t*ier of thij United States and by those which move northeastward from the south-western part of the country to tne Great Lakes. Thi:; conti-nental type of clillate is fJOdified by lake Michigan.. During
                    $pring, summer, and fall months the lake temperature differs markedly from the air temperature.               Wind shifts from westerly to  t=CI5 terly tl i reclions produce m<<:n*keti cooling of day-time Page 198 of278                        REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL temperatures in spring and summer. In autumn the relatively warm water to the la~e prevents night-time temperatures from falling as l~ as they do a few miles inland from the shorelinG. Summer time temperatures exceed 90°f for six days on the average. freeling temperatures occur 147 days and below zero on 14 days of the winter on the average. Rainfall averages Clbout 28 inches per yeer with S5 percent falling in the months of Hay through September. Snowfall averages about 45 inches per year. Sludge spreading shall be ~anaged such that the surface spreading together with any precipitation falling on

                   . ~the field shall not overflow the perimeter of the field.

Additional information on site meteorology may be found in Section 2.6 of the FSAR.

There will be no 1mpact on the meteorology ot the area due to the disposal of the sewage sludge. 4.2.2 Hydrology lhe dominant hydro1o$Jica1 feature of this site is Lake Michigan, one of the largest of the Great Lakes. The normal water level in Lake Michigan is approximately 580 feet above mean sea leve14 In the general vicinity of the site. the 30 foot depth contour is betweQn 1 and 1-1/2 miles offshore and the 60 foot contour is 3 to 3-1/2 miles off shore~ The disposal sites are twenty or more feet above the normal lake level. There is no record that the sites have been flooded by the lake during tRodern times. Ther* are no rivers or large streams whi~h ~ould ~r&ite

                     . a flood hazard at or near the sites.

Tlr~;,-sub,-urlate~*:IJal.er table .,~17 thP. Point Beach .si.te,. . h,s,f:~~:, .*:~*~:\~"~*.L** _.", ** .r definite slope eastward toward the lake. The gradient indi-cated by test drilling on the site is approximately 30 feet per mile. It is therefore extremely unlikely that any release of radioactivity on tbe site could spread inland. Furthermore, the rate uf !.ubsurface flow is smal i due Lo the telCitive impervious nature of the suil and will not promote the spread of releases *. further infcrmat1on on site hydrology is detailed in* the PBNP FS~R Section 2.5. There will be no adverse impact on hydrology of the area due to disposal of sewage stuage by land spreading. 4.3 Water usage 4.3.1 Surface Water lake Michigan is used as the source of potable water supplies in the vicinity of the site for the cities of Two Rivers (12 miles south), Manitowoc (16 miles sourth}; Sheboygan (40 miles south). and Green Bay (intake at Rostok 1 mile north of Kewaunee, 13 miles north). No other potable water use~ are recorded within 50 miles of the site along the lake shore. All public water suppli~~ drawn from lake Michigan are treated in puri~ iication plants. Th~ nP~rPst ~urfHc~ watPr uspd for drinking other tha~ Lake Michigan are the Fox River 30 miles NW and Page 199 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL LQk~ Winnebago 40 miles W of the site. lai;:e Michigan is. also uti1i2@d by various. rEH~rP.ational activities. i ncl udi ng fishing, swinrrming and boating. There will be no impact on surface water usage due to the disposal of sewage sludge. 4.3.2 Ground Water Ground water provides the remaining population with potable supplies. ?ublic ground water suppiies*within a 20 mile radius of the site are lhted in Table 2.5-3 of t.he fSAR. Additional wells for private use are in existence throughout the region. The location of private wells within a two mile radius of PBNP are indicated on Figure 3~ Appendix C. The potable water for use at the Point Beach Nuclear Plant is drawn fro~ a 257 feet deep well 1ocated at the southwest corner of the plant yard. Water from this well is routinely sampled as part of the environmental monitoring program. There will be no adverse impact on ground water usage due to the disposal of sewage sludge. 4.4 land U!i.~gP Manitowoc County, in which the site is located, and the adjacent counties of Kewaunee, Brown. Calu~tt and Sheboygan are predominantly

   .. * .. . ,~...,._.r:ur.a \* _ .f\srtcul tural purs.,.its. aeeount. for apg:rgxim.ately. ~0%_ ~f the 4
                 ~ *.to-tal county acreage.         Wit-h the exception of .. the K'ewaunee";*NtJCleai' Plant located 4.5 miles north, the region within a radius of five 111iles of the site is presently devoted exclusively to agriculture.

Dairy products and livestock account for 8S% of the counties 1 farm production, with field crops and vegetables accounting for most of the remaiode:, The principal crops are grain corn, 3ilage corn, oats, barley, hay. potatoes, green peas. lima beans. sna~ beans. IJ~et:s., cabbage, sweet corn, cucumbers, and cranberries. Within thc:!

     ** * * * **township of"*Two Creeks surrounding *the site {15 sq. miles), ther~

are about 800 producing cows on about 40 dairy farms. Some beef cattle are raised 2.5 miles north of the site. Cows are on pasture from the first of June to late September or early O~luber. During the winter. cows are fed on locally produced hay and silage. Of the milk produced 1n this area, about 2S percent 1s consumed a~ fiuid milk and 50 percent is converted to cheese, with the remainder being useu in butter making and other by-products. It has been the policy of W1sconsin Electric to permit the controlled use of crop land and pasture land on company owned property~ No direct grazing of dairy or beef cattle or other animals is permitted on these company owned properties. Crops intended for human consump-tion shall not be grown on the disposal sites for at least one year following the application of the sludQe. The proposed land application of sewage sludge will not have any direct effect on the adjaceot facilities. Additi~nal land use Page 200 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL information may be found in Section 2.4 of the FSAR. 4.5 Radiological Impact The rate of sewage s.ludge c:~pplicctt.ion on eac.h of the six proposed sites will be monitored to insure doses are maintained within applic~ able limits. These Hm1t~ are bas~d on NRC Nuclear Reactor Regulation (NRR) staff proposed guidance (described in AIF/t~ESP-037. August, 1986}. These limits require doses to the maximally exposed member of the general public to be maintained less than 1 mrem/year due to the disposal material. In addition, NRR guidance requires doses of less than 5 1wem/year to em inadvertent intruder. To assess the doses received by the maximally exposed individual and the inadv~rtent intruder, six credible pathways have been identified for the maximally exposed individual and four credible pathways for the inadvertent intruder. The id~ntified credible pathways are described in Appendix D. C~1culations detailed in Appendix E demon~trat~ the disposal of the currently stored PSNP sewas~ sludge would re~ain below these limits. The total annual exposure to the maximally ~~posPd individu~l b~s~d on the identified exposure pathways is equal to 0.072 mrem. The dose to a hypothetical intruder assuming an overly conservative occupancy factor of 100% is calculated to be 0.115 mrem/yar. By definition, the inadvertent intruder would not be expose~ to the processed food pathways (~eat and milk). The calculational methodology used in determinir.g doses for the proposed disposal of sludge store~:t;:il!t PBHP shall be utilh.ed p.r.io.r to each additional land application to insure doses are maintained *ltfss than those proposed by HRR. This calculation will include radio-nuclides disposed of in previous sludge applications. The activity from these prior disposals will be corrected for radiologi~al decoy prior to performing dose calculations for the meat, milk7 and vegetab!e ingestion pathways, the inhalation of resuspended radio-nuclides, and all pathways associated with a potential release to Lake

11.t~: ~.!g~a,n_. }he.~ re~1!!Y..aJ~.r~~.Lo~~~1~i.ty llftll_~e ~9.rret;ted for ra_9i_~~-- _

           '~--:nOVfe'al* 'tlecay. and~* 'lf *applic*ab le ;*the mixln~f Of . railionud ide~.*; n *ttitf soil prior to perfo~ing external exposure ~alculations. In addition, the dose to a farmer potentially leasing mo;*e than one application site will be addressed by summing the doses received from the extl:!rnal exposure from a ground plane source and resuspension inhalatio~

pathways for each leased site. In addition, the maximum site specific dose due to the other pathways identified in Appendix 0, will be utilized in the total exposure estimation. 5.0 Radiation Protection The disposal operation will follow the applicable PBNP procedures to maint.:tin (InS('$ as ll')w ~s r~.:tSO!!.l!lhly .ru;hiP.v~b1P, TPt;hnical review and guidance will be provided by the PBNP Superintendent - Health Physics. Page 201 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIX A

SUMMARY

OF RADIOLOGICAl ANALYSES OF SEWAGE SlUDGE SINCE DECEMBER 30, 1983 Page 202 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Sample Tank Tank Radionuclide Concentration Oat.P Volume (Gallons) (pCi/cc) 12-30-t$3 Digester 8400 co-sa 5.58E-07 Co ... 60 1+87E-06 cr-51 4. a*aE.-07 Cs-134 1. 59E-07 Cs-137 3a57E-07 4-05-84 Oi~ester 7560 Co-60 7.89E-07 Aeration 6667 Co-60 1.87E-07 12-05-84 Digf!~t~r 7560 Co . . S8 1.75E-07 Aeration 6667 Co-60 8.L9t-07 6-03-85 Digester 7560 Co-60 8.29E-07 Cs-137 2-46E-07 Aeration 6700 Co-60 3.27£-07 Cs-137 1.33£-07 4-10-86 Digester 75GO Co-60 6.79E--07 Cs-137 1.72E-07 >> Mn-54 Co-60 4~91E-08 1.6SE.. 07 11-04-86 Digest~r 7560 Co-58 8.04E-08 Aeration & Clarifier 25100 Co-58 1.37E-07 Co-60 2.18£-07 Cs-137 1. 64E-07 Page 203 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIX_B CHEMICAL COM~OSlTIOH ANALYSIS OF SEWAGE SLUDGE Page 204 of 278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL STAT£ OF WI$CON$1N llU.P,fl,fllMt.l't(f OF f<tATURAI.. f\I:;:IOVit<<:O SLUDGE CHARACTERISTIC Wisco!liin Statute 147 .02(1 l and Wiscon$in Admtni~tratid'Cad!: NR 110.27(61 FORM 3400-tt Fl£V.lCHIO Plt!lue complete thil form and send to the Deparun~nt of N*nura1 Resources iPPrOPTiatll Pinrk:t/Arl'a Offic:t. Kup one eoPV !Of vourr~ds. FOt additional forms, pluu contact your IPf'tos:wiate Dimic:t/Aru Office. l'fiRMITfl~ WPQO:'!'- RMIT NlJMAii"R

         'lUsconsin Elect-ric. ?ower Company                                                                                                               WI 00        L lL L      ..5_  .1..
     $'fl'lll£T OR ROUTE                                                                                               cnuk1"¥ 131         w. Yichi~~n Str~et                                                                               ?-tihmukee
     ~l"tV,!Ii'fATE,      ZII>COOE                                                                                     TFJ *EP~l'INE ..,H!'M~~ft}~Nii:.LUDE AREA CODE I
         )~i;.'~i~\!1;:-*~.           **~*!     5"5~~3                                                                    ** ,_ *:!
                                                                                                                               *~     I *' * ~ t, ::1*J

1. Please report labc\ratory testi~g results for the following parameters:

                        *f'aramenr                 ADDftviation                             Result                             "'P.aramtter                  Abbre'fllllcn             Result
               *r otal SOlids. l.                                                                                      CfiiOiniuM, ppm                            Cr l.t'                                                                      Co

!11)0 lotal Nitrogen, '5 TOTN (;oppet,ppm

Amti'l.onium:N!~'~~t,C, NH:-N r}. :i4 Ltad-,p~. 'I >~..... ..f;b, *~

Toul Ph~spharous, "Kl ,. " !l. ul Mercury, ppm H9 3.6 Total !"'otamum, 'Kt K fl.!S Nic:~el,pprn Ni l:! 1.0 :2~110 Ar$-enle, ppm As Zinc* ppm Ztl

12. pH 7.,. t1 C.dmiurn, ppm Cd

               *suw¢tttd enotnl* prootduru tot the ebol'l pttl!metera an bt found jn NR 219. *nalytil!id ttltl cnd fH'OCI!IIduru. Wi1oon*l~

Administrative Code. All parai'I1Cters other thin pl'retnt .Oiids and pH shall be npotttd on 1 dry weight bult. *

2. Whet is the n.tme of the llboratorv that did th.t analysts am when wn it periormtd1 Labofatorv Name ~Hsconsin Electric Power Co. Oatest.,ttolab April lZ, 1933 Laboratory SerYi~cs Divi~ion e'r~':": :;1~':!~~ hc!\H:':~ t~n!o: ~rio": to

     )         Whrr*atthetreatmentplantwastheAmp4uaken?

4. When wu the $ample uken1 _.:..:l\:.:..~....:l":...:i:..;l:.-.::.1.::.:!..:.*--::1:.:9;...;8;:;.;S:;.__ _ _ _ _ _ _ _ _ _ _ _ _.....;._ _ _ _ _ _ _ __

TtTU: CAT~

            ... /                                                                                               ~l:l't~r   (.!ual i    ~y 'i!:l!.~ i.:1eer Page 205 of278                                                                           REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIX C SITE MAPS Page 206 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

                            .I 1 f I
                                                                     ~.

(

                                                                  ~-**-
                                                         . SITt rtOT Page 207 of278             REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Page 208 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

S"l-rs. "t>out*.fi)A2.'i

                                                                                                                                           \N e   *-pi!of!'t:-2-ltt l"n.ltt
                                                                                                                                 *  ~RE~"'Itl~tJCE
        ............... t- . . . . . . . .

l

                                           ~ . . . _ ............. =....... ,. .... _.,., ""~$ ............ _ _

Page 209 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIX 0 EX~OSURE PATHWAYS Page 210 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

1. EXPOSURE PATHWAYS - MAXIMALLY EXPuSED lNDIVIDUAL

1. External whole body exposure due to a ground plane source of radicJnuclides.

2. M11t 1ngest1on pathway from cows ted alfalfa grown on plot.

3. Meat. ingestion pathway from cows fed alfalfa gro~*m on plot.

4. Vegetable ingestion pathway from vegetables grown on plot.

5. Inhalation of radioactivity resuspended in air above application site.

6. Pa~n~ays associated with a release to lake Michigan. Ingestion of potaule water at Two River*s, Wisconsin municipal water supply, ingestion of fish from edge of initial mixing zone of radionuclide release. ingestion of fresh and stored vegetables irrigated with w~t~r ~ourc@ AS Lake Mi~higan, ing~stion of milk and meat from cows utilizing Lake Michigan as drinking water source, swimming and boating activiti@s at edg@ of initial mi~ing lone~ and shoreline deposits.

II. EXPOSURE PATHWAYS - INADVERTENT INTRUDER

. *

1.. Externa.l .whole body.:.. expd.5ur.e due **ground Qlane. sourcer~ot:,::.::

radicnuclides.

2. Vegetable ingestion pathway fr~m vegetables grown on plot.

3. Inhalation of radioactivity rest..:spended in air abo'o'e .application site.

4. Pathways associated with a rel~ase to lake Michigan. Ingestion of potable water at Two Rf~ers, Wisconsin municipal water 5up~ly, ingestion of fish fr9m edge of initial mixing zone of radionuclide release, inge~tion of fresh and stored vegetables 1rr1gated with water source a~ Lake Michigan. inge!.tion of milk. and meat from cows ut111Z1ng Lake Michigan as drinking water so*rrce, sw1mm1ng and boating acti~iti~s at edge of 1nitial m~ving zone~ and shoreline deposits.

The milk and meat pathways are not included in calculating the dose to the inadvertent intruder~ The dcses due to these pathways are calculated based on feeding the cow:; alfalfa :rown on the sludge applied land. _ ~:h:tt;e: direct grazing on these l'nds is prohibited, the alfalfa must be cropped prior to being used as feed. Thts effectively removes the availability of these pathways to the inadvertent intruder. who by definition occupies the sludge appli~d land continuo~sly. Page 211 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Ill. ,GROUND WATER PATHWAY The ingestion of groundwater is not a credible exposure pathway. The two factors contributing l.o Lhh determination are as follows: L The site map 1n Appendix C1 Figure 3 details t.he spdtia.l n~latlon ship between the proposed disposal sites and the local ground water

                'Wel fS. 1he fJO'W gradient Of ground Water W'il$ determ1ned for the PBNP FSAR to be towards Lake Michigan. Reviewing the sites and local wells shows no private we11 lo~ated in thP. path of radionuclide migration towards lake Michigan.

The PBNP site well is located on the plant site. potentially in a path of radionuclide ffligration. The PBNP well is routinely sampled as a requirement of the PBNP environmental monitoring program.

2. The cation exchange capacity (CEC) of the soils at each site has been rtetermined.

Site Cation Exchange Capacity (HEQ/lOOgl 1 16 2 11 3 11 4 10 5 8 6 9 Jhe cation exchange capacity of soil is depe.ndent on the valance Of the radl011UClideS and ls determirff!)i by the rel.ati,:Ofl:,"'1r ;*A** ., . *'"'!; ~*1*( MEQ =ATOMIC WEIGHT

VALANCE l OE-Ol Rad1onuc11de Valance CEC ~MEg/lOOg) co-6o +l l.OOE"'02 Co-58 +2 2.90E-02 cs-13/ +l 1. 3/t:-01 Mn-54 +2 2.70E-02 Cr-51 +3 1.70E-02 Cs-134 * +1 1.34E-Ol Using the values for Cs-137 and site 5 which has the lowest CEC. the total exchange capacity of tht! soil is 1.10 grams of Cs-137 100 grams of soil Calculating th~ specific activity of Cs-137, SpP~ific Activity = 3.578E+05 = 3.578E+05 T112 (yrs.) *ATOMIC hASS 30
137

                                     = 87.1 Ci/gram Page 212 of278                                   REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL The cation exchange capacity of the soil expressed in the number uf c~ries of radionuclide per 100 gr&ms of soil is 9S.8 Ci Cs-137 100 grams of soil Since the proposed disposal of sewage ~ludge contains quantities of radionuclides on the order of 10*100 ~Ci the soil at each site has the capacity to effectively eliminate the migration of the rad1onuclide to ground water~ Page 213 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIX E EXPOSURE ANAJ..YSIS Page 214 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL GENERAL AS~UHPTIONS

1. Sewage sludge is uniformly applied over plot acreagea

2. Sewage sludge is applied to one of the S acre plots., site PB-03.

PB-r4. PB*OS~ or PB-06. (Assuming the smallest site size is conservative for the calculati_on methodology herein . ),~_.~ ... *.: ..

3. Based on the sewage sludge currently stored at PBNP. the following data is used in the calculations.

Ground Plane Sludge Volu111e Activity Concentration Concentration Radinnuclide (Gallons) (cm3) (pCi) (J!Ci/CD13 ) __ (uCi/cm2 ) Co .. 60 15,000 §.68£+07 1:3.2 2.33E-07 6+53E-OB Cs-137 15,000 5.6BE+07 8.5 l. 50E-07 4.21E-08 I. CALCULATION OF EXTERNAL EXPOSURES A. Specific Assumptions

1. Conservatively assume radioactivity remains on surfa'e of land plot.

Calculation ignores any plowing or mixing of radioactivity within

                  .soiL Calcula,tions for the propo~d disposal will.~ther.~fo.r..e Jgflp.r:~

el

             . - ~5-:e 1f. eb*s*orp*tton **or '"shi dt ng .. tr&m~oi 1.       : . .       ~ ,; !')1'1,_::,*; .-ir<f, ~"'r, ..._. :~I">;

The external exposure at the application site due to prior disposals will be calculated utilizing the methodology in Appendix G and added to that calculated for the proposed disposal.

2. The plots are owned by Wisconsin Electric and have been approved by the Wisconsin Depcn*tment of Nc:Jtuy*al Resout~ces (ONR) as disposal sites. The land is 1eased and potentially farmed. Occupancy of the land can be realistically expected only ~Jtn*ing plowing, planting and harvesting. Occupancy has been estimated to be 64 hours per year.

B. Summary ofCalculationa1 Methodo1ogy

1. calculate ground plane radionuclide concentrat1ons in pCi/cm 2 ~

2. The dose from a plane of uniformly deposited radionuclides is calculated using Regulatory Guide 1.109. Revision 1. AppQndix C, fonr.\11 a c- 2.

3. Dose rates were calculated assuming continuous occupancy then adjusted for r~alistic occupancy factors.

Page 215 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL C. External Exposure Rate Calculations The dose from a pla.ne of uniform1y deposited radionuclides is calculated using Regulatory Guide 1.109~ Revision 1, Appendix C't formula C-2 G G Dj(r"9) =. 8760 SF t* C1(r.6) DFGij where o; (r.e) =*yearly dose 8760 = hours per year

                                             = 1. 0..     ~i   nee no dosp 'reduct i .,n dul! t.o        r-~"i> i rb?*nt i a 1 sh;elding is applicable.

c~ (r.e) =ground plane radfonuclide concentration (pCi/m 2 ) OFG(i.j) =external dose factor for 1tanding on contaminated ground as given ir. Table E-6 of Regulatory Guide 1.109, Revision 1. Ground Plane Groun~ Plane 'Y Dose l Dose Factor Concentration Coneen~ration Rate (mrem/hr per ,!~iJmZ) ll!Cilcm22 (pCifm2) (mrem/yr) Co-60 1~70E-08 6~&3E-08 6aS3E+02 9,.72E-02 1 *"'c**-:i~*.. ~s~,;!).l~"' ,:L;r. *'

4 .. 20E-09!.~..;.,__." '=4~1E-08 ,.:._..,:. :t~4...~~~+9~. 1. 55£*02 .* L TOTAL: 1.13E*Ol mrem/year These calculated do~e rates assume continuous occupancy. In reality~ these sites will be occupied only during plowing, planting, and harvesting.

A~sut~~tino an oc-cupancy of 2 hours*ptir' day. 1 day per \JIE'ek. and 3? w~P.k!i (A month growing season) per year, the occupancy f1.ctor becomes Z hr/day

1 day/week
32 weeks/yr
1/8760 hours/yr = 7.3E--03~

E~!ERNAL ~)(~OS~RE OOSE ~ATE _(m!em(ye~r) Radi onuc 1ide Conti llU9!JS. Oc:t:ueancy_ Co-60 ~"72E-02 7 .. lUE-04 Cs-137 l.SSE-02 1.13£-04 TOTAL: l.l3E-Ol 8.23E-04 Page 216 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

11. CALCULATION OF MEAT AND .MilK IHGE?llON,J'AlHWAY. EXPOSURtS A. Specific Assumptions All feed consumed by cow is grown on slu~ge applied acreage4

2. All meat and milk consumed by human is from cattle e.xclus1vely fed feed from sludge applied land.

    . 3. Stable element transfer coefficients (B. ) are utilized fr,om Regulatory Guide 1.109 to estimate the t¥action ot radioactivity which is transferred from the soil to the feed~

Radi onuc l ide 8.1J Co-60 9.4E*03 Cs-137 1. OE-02

4. Alfalfa has typically been grown on the plots.. Soil tests have indi-cated a mini~um alfalfa yield of 4.1 tons per acre can be e~pected.

R Summary of Calculational Methodol~gy

1. Th9 concentration of radionuclid@s in feed grown on the disposal pl~ts is estimated. Transfer coefficients (B. ) from Table of Regulatory Guide 1.109 were used to estimate t~l fraction of radio-nuclide which may be expected to transfer to the feed from the soil.

                           "  "   't    '"i          ... -   "A"' *J'f.              '

Concentrati-ons of *radionuel i,des;,~tfi~ milk and. me*at:'were est*imatatL-using Formula A-ll from Regulatory Guide 1 . 109.

l. Ingestion do$e rates were estimated using Formula A-12 fr~

Regulatory Guide 1+109.

c. Milk and Meat*. Ingestion Pathway Dose Rate Calculation

1. Concentration in feed~

           *Activity in Feed      =B;v

Activity in Soil Concentration in feed= Activity in Feed/(kg ~~r:eed
5 Acres)

Radionuclide Activity in Activity in Concentration in Radionuclide Soil (pCi) Feed (HCi) Feed (RCi/kg)_ Co-60 13.2 1. 24E-Ol 6.67[+00 Cs-137 8.5 8~50E-02 4.S7E.+OO

2. Concentration 1n Milk ano Meat Calculate tohc*nttattons of rad1onucl1des in milk and n~at using Page 217 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL F.or.mula A-ll in Regulatory Guide 109, Revision 1 which .is CiA= FiA*CtF*Qf where CiA= radionuclide concentration of i in component A F1A = stable element transfer coefficient whose values are in Table E-1 of the Regulatory Guide C = radionuclid~ concentration in f2~d Q;f .= consumption rate of feed = SO kg/d (wet weight) from R~ou1atory Gu!de 1.109 Us@ th@ following R@gulatory Guide 1-109 values for F A 1 Elamgnt F1A=m (d/l) for milk F;A=Ff (d/kg) for meat CQ 1. OE>--03 l.JE-02 Cs 1.2E-02 4.0E-03 Concentration in Concentration in R~dioouclide Milk (pCi/1) Meat (pCi/kg) Co-60 3+ 34E-Ol . 4,. 34E-t-OO Cs-137 2+74E+OO 9. 14E-Ol 3~ Calculated Dose rates The formula for total dose from eating animal products fed vegeta-

        . t1on (alfalfa) grown on PBNP s,lugg.~ applied land 1s giv.e.n by ..

Regulatory Guide 1.109. Revisioh~~l~ Formula A-12t page..r.1'1tl9*16*."'""C* t. But, as noted following equation A-13s it is necessary to compute separately the milk and meat portions of the dos~. DOSE= I(Uap*D;apg*exp(-A;t$)) where U = const.--npt ion rate of anima 1 produc't c;~ = cone nf radionuclide i in animal product A D ~ _ = dose factor tic~py 5

                          = average time between milking or slaughtering and consumption Uap by Age Group In*fant      Chi 1d     Teenager        Adult Milk (1/yr)         330          330            400 Moat {kg/yr) ci~:    ~  concentration calculated 3bovc f.* .'

0iapg Df whole body dose factors, RegulatOrY Guide 1.109, Revision 1.

Page 218 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

                                               -Whole Body.Oose Factors {mrem/pCi Ingested)

Infant Child Te*enager Adult Nuclide lngesticm Ingestion Ingestion Ingestion Co*60 2.55E-05 1. SGE~OS 6.33E-06 4.72E-06 cs-137 4.33E-05 4.62E-05 5.19E*05 7.14E-05 T s

                                         =020 for

=!.

milk (assume consumption on farm)

                                                 'itay~ for meat (Regul;rtDry Guide 1.109 ..             Revis;ion -1. Tablf:! E-15)

MilK lNGE~TlOH DOSE RATE (mrem/year) Radionuclide Infant Child Teenager Adult Co-60 2.81E-03 1.72E-03 8.46E-04 4.89E-04 Cs-137 3.92£-02 4.18E-02 5.69E-02 6.06£-02 TOTALS: 4.20E~o2 4.35(-02 5.77E-02 6.11£-02 MEAT INGESTION DOSE RATE (mrem/~ear) Radionuclide Infant Child Teenager Adult. Co-60 2.76£-03 1. 77E-03 2.24E-03 Cs-13/ 1.73~~~$ 3.08~*03 7.16E-:Jl3 _.

. --~ .,_, _,_ ..

_ .._.~-. *,;. ,""'** t~ .. t. ;:. .-; TOTALS: 4.49E-03 4.85E-03 9.42t-03 ME.AT AND MILK INGESTION PATHWAY DOSE RATES (rnrem(y~~r) Infant - 4.20E-02 Child - 4~80E-02 Teenager - 6.26E*02 Adult - 7.0SE-02 111. CALCUlATION OF VEGETABlE INGESTION PATHWAY EXPOSURES A. Seecific Assu~etions

1. The WPDES permit issued to PBNP for the disposal of sewage sludge prohibit' thQ growing of crop£ for human consumption for one year following t~e application of the sewage sludge.

Therefore, prior to planting.vegetables on the application site, the soil would be plowed. P1owing is assumed to uni-formly mix the t~~ 6 inches of soil. Page 219 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

2. The* soil density is assu~ed to be 1.3 grams/cm3.

3. All v~getables consumed by the individual of inte**est are grown on th* iludge ipplied acreage.

4. St~blc:~Qlcmcnt transfer coefficients (Biu).from Ragu~~tory Gu1de !.109 are used to estimate the fratt1on of radlo-activity transfered from the soil to the vegetable~ .

                            .-.** Radionucl idt!

Co-60 9. 4£:-0J Cs-137 l.OE-02

5. The consumption factors of food medium (U ) and the ~ass basis distributions from Regulatory Guide 1.109~PTable are used to determine annual consumption of vegetables.

Uap by Age Group* Infant Child Teen Adult .. 280 ft.g/yr 340 kg/yr 280 kg/yr

             *Based on 54% veg@table consumption by mass of fruit, vegetable, and grain .

6. Ttitf* ingestion Dose Factors by age group are from Regulatory**

Guide 1.109, Tables E*ll, E~12, E-13, and E-14~ Whole Body Ingestion Dose_ Factors (~&rem/pCi ingested) Radionuclide Infant Child Teen Adult Co-60 2.S5E-05 1.56E .. 05 6.33£-06 4"72E-06 Cs-137 4.33E-OS 4.62E-05 S.l9E-05 7.14£-05

7. Radi~logical decay of the radionucltdes applied to the plot is not taken into account in these calculations.

B. Summary of ~alculational Methodology

1. The radionuclide concentration in the soil is calculated in units of pCi/kg based on unifor~ application over 5 acre plott plowing to a depth of 6 inches, and a soil density of 1.3 g/cm 3 *

2. The B. values are applied to the soil concenlr~litm values to obtai~vthe radionuclide concentration in the vegetables.

3. The consumption factqrs (U ) for each age group are then used to determine the anm.1a ~1 ra8~ onuc 11 de intake t>y age gro*up due to eating these vegetables.

Page 220 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

4. Fina1'ly, the age d*ependent ingestion dose factors are used to obtain annual doses by age group.

C. Vegetable Pathway Ingestion Dose Rete Calculation!

1. Concentration in soil Concentration Activity Soil Volume Soil Mass In Soil Radionuclide Aeelied {~ill (cm 3 ~ {kg} ((!Ci/kg~

Co-60 13 .. 2 3 .. 08E+09 4+00E+06 3.30f+OO Cs-137 8.5 3.08E+09 4.00E+06 2.13E-+OO

2. Concentration in vegetables Concentration Concentration ln In Vegetables Radionuclide Soil (pCi/kg) 8 tv (pCi/kg)

Co-60 3.30E+OO 9.4£-03 3.10E-02 Cs-137 2.13£+00 l.Ot'""O~ 2.13E-02

3. Calculated Dose Rates The dose rate for direct ingestion of vegetables grown on the sludge

                ,.,.~,,.;

applied land is

,;~...._.~-.. ...

given equation DOSE RAlE =I Uap ~ Diapj

EXP (-A 1t)
C; where U = consumption rate of food medium o~P . = do5e factor for radionuclide. i AlapJ 1

                                          = rgdiologic~l dec~y constant t           =time between harvest and consumption C.          = concentration of            rad~onuclide~         i. in food 1

medium. t~ the time between harvest and ingestion, is assumf!d to be zero Jor ~his calculation~ VEGETABlE INGESTION DOSE RATE (mrem/year) Radionuclide Infant Child Teen Adult Co-60 1.3~E-04 6.67E~os 4.10E-OS Cs-137 2.76E-04 3.76E~04 4.26E-04 TOTAL 4.11£-04 4.43E-04 4.67E-04 Page 221 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

   !V. CAlCULATION    O~_INHALATION                 OF    RESUSP~NOEO   RADIONUCliDES PATHWAY          EX~OSURE A. Specific AssumRtions

1. The model used to detem1ne the radianuclide c:oncenlrdtiun in air above the sludge applied land is taken from WASH-1400)

USNRCt Reactor Safety Study ... An Assessml!nt of Accident Risks in Commercial Nuclear Power Plants. Appendix VI.

2. The radionuclide concentrati6n in air remains constant for year of interest, i.e., radiological decay and decrease i~a resuspension factor e.re not*taken into accourt for this calculation.

3. The maximally exposed member of the general public is assumed to be the farmer using the plot of land with an occupancy of 64 hours per year.

4. The inadvertent intruder is assumed to occupy the plot of land for thE' entire year.

5. The Inhal~tion Dose Factors by age group are from Regulatory de 109 *. Ta~}J~~ ~.::L, E-8, E-9, a-:l~~ E;:~.0;.

WHOLE BODY INHALATION DOSE FACTORS.(mrem{pCi inhaled) Radionue1ide Infant ChiJd ..* Te{l.n Adult

       -" .. ..                        *,; ,.,.. * ~ *. L
                                                                    ~J'
                                                                                                     ... --..It'~ ~~,.~-t-Co-GO          8.41£~06                    6.12£-06     2.48E:-OG       1 85E-06 Cs-137          3.25E ... OS               3.47E... OS  3 .. 89E-05     5.35E-05 LUNG INHALATION DOSE FACTORS {mrem/pCi                           inh~l~d}

Radionuclide Infant Child Teen Adult Co-~0 3.22E-03 *1.91E-03 1.09E-03 7.46E*04 cs~l37 5.09[-05 z.Bl[-05 1.51£-05 9.40E-06

6. The age dependent inh~lation rates are obtained from Regulatory Guide 1.109, Table E-5.

Inhalation Rates (m1 /yr) Infant Teen Adult 1400 3700 8000 8000 Page 222 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

8. Summarl ()f Calculational Methodology

1. The ground plane radionucli~e concentrations in pCi/m~.

2. Calculate the resuspension factor utilizing ~~uation gfven in WA~H-1400.

Obtain the radionuclide concentration in afr (pCi/m 3 ) above plot utilizing methodology i'n WASH-1400.

4. Using parameters contained in Regulatory Guide 1.109, calculate annual dose for continuous occupanc~ and for realistic occupancy.

C. Inhalation of Resusp~nded Radionuclides in Air PatJhway Dose Rate

        'Circulations ... Resus2ension of Radionuclide in Air 1~       Ground plane radionuclide concentration Ground Plane                    Ground Plane Radi cmuc 1ide       Concentration (uCi/cm2)         Concentration {pCi/m2)

Co-60 6.53E-08 6.53E+02 Cs*137 4.21E-08 4.21E+02

-I

2. Calculation of resuspension factor* K (m )

          , *, .* F-rom MASH-1400, ":-*** : .       .

K(t) = l.OE-09 + l.OE-05

EXP [-0.6769
t]

where t = time &ince radionuclides were depc~ited on gr~u~d ~urface. t is assumed to be 0 for these calculation;., thereby maximizing the resuspension factor. Therefore, K = l.OE-05 m.. 1

3. Calculate radionuclide concentration (pCi/*~' in air.

From WASH-1400, or -1 Air :.Com:ent.r.ation (pCi/m3) :::: surface depostt (pCi/m2 -) ~-,.K{m **)""* AIR CONCENTRATIONS Radionuclide Air Concentrations (pCi/*11 Co*60 6.53E-03 Cs.-137 4.21£-03 Page 223 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

4. Dose Rate Calculations Dose Rate (tnrem/yr) = Inhalation R~. :* ,.m3 /yr)

Air Cone. (pCi/m3 )
Dose Conversivn Factor (mrem/pCi)

WHOLE BODY INHALATION DOSE RI\JE (mrem/year) J,..;i'%. . *io* Radiooucli~ Infant Child Co-60 7~69E.-OS l .. 48E-04 l.JOE-04 9.66E-OS Cs-137 1.92£-04 5.41E-04 1.. 31E-03 l.SOE-03 TOTAL 2.69E ... 04 6.89t:-04 1.44E-03 1. 90E-03 LUNG lNHALATIOtf OOSE RATE (mrem/year) Radionuclide Infant Child Teen Adult Co-60 2. 94E-02 . 4.61E-02 5.69£... 02. 3.90E-02 cs-137 J.OOE-04 4.Jsl£-o4 5 .. 09E-04 3.17E... 04 TOTAL 2.97£-02 4.65£-02 5.74E-02 3.93t-OZ

                                          ~~OLE  BODY DOSE RATE          'mrem/~ear}
        *,  Occueanc~         ... ,.. lnf~nt               Child                 Teen             Adu"l t Continuous               2 .. 69E-04          6.89E-04           1.44E-03            1. 90E-03 RP.i\listic             1.<16F:-06            5 03E-06           l,O!if-05           1. 39E .... Q5 LUNG DOSE RATE           !mrem/~earl Occu(!anc~                 Infant              Child                  Teen            Adult Continuous              2.97E-02              4.. 65E*02         5.74E-02            3.93E-02 Re~listic:               2.17E-04             3.3~E-04           4.19E-04            2.87E-04

v. :cALCULATION OF WHOLE BODY EXPOSURES DUE TO RELEASE,rlo LAKE MICHIGAN A. SEecific Assumptions

1. The methodology contained in* the PBNP Offsite Dose Calculation Manual (OOtM) 1s used to perror~*tnts calculation.

Page 224 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

2. The entir~ activity contained in the sludge is released into Lake Michigan.

3. The exposure pathways addressed by the ODCM methodolcgy are ingestion of potable water from T-wo Rivers, Wl water supplyt ingestion of fish at edge of initial mixing zone, ingestion of fresh and stored vegetables. irrigated with Lake Michigan as

            ~*-~puree of water., ingestion of milk and 111eat        frof!l ,c;~ws utilizing
            ~-*lake Michigan as drinking water source. swimming arid boating activities at edge of initial mixing zor.e, and shoreline deposits.

B. Summar,y of Calculational Methodology L The activity released in the sludge is converted into Co-60 dose equivalent Curies.

2. Th@ annual dp~ign r@hHHiP. limit from the ODCH is 94.7 Co-60 equivalent curies.

3. The annual design release limit is based on a l~miting dose of 6 mrom adult whol~ body. Tha annual do'S@ dup to s~wage sludge is calculated !Jy a ratio of calculated release compared to release limit,

C. Whole BodyExposure Calculations Activity Co-60 Gq~

Radionuclide ~~ DF;/DFco-60 Activity (pCi) Co-60 13.2 l.OOE+OO 13.2 Cs-137 8.5 1.51E+Ol 128.4 TOTAl 14l.6~Ci Co-60 equivalent

2. Ratio of dose limit to annual design release limit 6 mrem 94.7 Cu-60 equivalent curies :,,

3. Whole Body Og~e C.:~h;ul c~t ion Dose 6 mrem 141. 61-1Ci 94. 1 xiO'\*C i Oos* 8.97E-06 mrem WHOLE SODV DOSE RATE (mrem/yea~L 8.97E-06 Page 225 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL DOSE

SUMMARY

Maximal]y Exposed Individual The identified credible exposure pathways for the maximally exposed individual are: f.) External exposure fr(!oJn groundplane source (realistic occupancy) 2.) Milk ingastion pathway 3.) Meat ingestion pathway-4.) Vegetable ingestion pathway 5.) R~suspension inhalation pathway (realistic occupancy)

64) Pttthway! identified due to release to lake Mic1ige.n.

AGE GROOP Pathway Infant Child Teen Adult External 8.23E-04 8.23E~04 8.23£-04 B. 231>04 Hi 1k. 4.20E-02 4.35E-02 5.77E-02 6.11E-02 Mec~l 4.49[-03 4.8SE-03 9.42E-03 Vegetal:le 4.11E*04 4.43E-04 4.67E-04 Inhalation 1.96E-06 5.03£-06 l.OSE-05 1.39E-OS Water 8.97E-06 a*.97E-o6 8.97E-06 8.97E... 06 TOTAL: 0.043 0.049 0.064 0.072 (mrem/yea.r) Inadvertent Intruder The identified credible exposure pathways for the inadvertent intruder are: 1.} txtornal exposure from gr~und plane source (continuous occupancy) 2.) Vegetable inge~tion pathway 3.) Resuspet,sion inhalation pathway (continuous occupancy) 4.) Pathways identified due to release to Lake Michigan. AGE GROUP Pathway Infant Child Teen Adult

            .~termt1            l.).j~~P~. 1.,13E~f)l     1.13E-Ol         l.l3E-Ol L. Vegetab 1e                        4.11E-o4       4.43E~04.        j4~67E.;.04.

Inhalation 2.96£-04 6.89E-04 1.44£-03 1.901::... 03 Water 8.97E.. 06 8 .. 97E-06 8.97E-06 8.97E.. 06 TOTAL: 0.113 ,0.114 0.115 0.115 (mrem/year) Reviewing these tables, the cftlculated limiting dose~ for both the maximally exposed individual and the inadvertent intruder oc~ur for the adult age group. These doses ar*: Maximally Expos*d Individual~ 0.072 ll'irerJ/year Inadvertent Intruder; 0.115 mrem/year Page 226 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIX F BASIS FOR SETTING CONCENTRATION liMITS AND ACTIVITY liMIT FOR_DISPOSAL~OF SLUDGE Page 227 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Ana lyses of previously disposed sewage s 1udge have i dent i *fi six different radionuclides in the sludge. All six radionuclides did not occur in each disposal. Therefore, it is difficult to dete~ine a single concentration limit for regulating the disposal of the sludge from the storage tanks. To provide a basis to regulate the disposal of the sewage sludge based on idP.ntifil2d radfonuclide concentrations1o following relation i!l proposed. N

C i

where N =number' .of rlifft:'rent 't";ulionuclides identified in th~ sewage. sludge. c.l = coneentration of the ith radfonucl in thP sewage sludge.

                    =  the MPC value of the ith rAdionuclid~ in th@

sewage sludge, as listed in 10 CFR Part 20* Appendix 8 1 Table II, Column 2. If thi& criteria is met, the sewage sludge may be di&pos.ed of by land spraad-i provided the dose calculations (as identified in Appendix E) indicate

dose rates within the prescribed limits.

The ftttachment to thi:; Appendi K details cal c:ul at ion::; performed. to determine- .... - doses fr.Onl fOil'r~ r*adionuclidffS 'identified in !the sluc:lge*: erhe* C'.alculatforfS (ir'Cf';:;,.. based on sn identified concentration equal to 10% of the 10 CFR Part 20, Appendix B, Table II, Column 2 valves. The ca1c~lations use the methodology in Appendix E along with the exposure pathway' identified in Appendix 0 to determine dose rates. These calculations indicate the use of this triethouology will r11aintaio radiation doses within the appropriate.limits. The maximum allowr;~ble cn.;livity disposed uf per* year* pea~ acre is calculated utilizing 10% of the MPC value, 10 CFR Part 20, Appendix B. Table. II, Column 2, for Co*58. Volume limit per acre ha& been prupo,ed at 4,000 gallons/acre/year.

Then, l.OE-05 ~Ci/cc

4,000 gallons/acre/year~ 3.785.43 cc/gallon

                     = 151.4  ~Ci/acre/year Page 228 of 278                      REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Cs-134 Concentration in Sludge~ 9.0£-07 mCi/mi Sludge Volume Concentration Activity Ground Plane (Gallons) ~I:;!C i /_t:t_~~) _ (pC i) Concentration (~Ci/cm2) 15000 5.68E+07 9.00E-07 5.11E+Ol . 2.53E-07 External Exposure y Dose Factor Ground Plane Concentration '/-Dose Rate (mre;n/nr. per pCi/m~) (mrem/year2

1. 20t-08 2.53t+03 2.bbE-Ul Continuous Occupancy: 2.66E-Ol mrem/year Realistic Occupancy: 1.94E-03 mrem/year Meat &Milk Pathway Activity in Activity in Concentration in Concentration in Concentration in Soil CuCi) Feed (pCtl. Feed {pCi/Kg) Milk (pCi/1} Meat (pCi/kg) 5.22E+Ol S.llE-01 2.75E+Ol t5.50E+CO Milk Dose Rates (mrem/lear)

Infant Child Teenager Adult 3.87E-Ol 4.41E*Ol 6.03E-Ol 6.19E-Ol Meat Doso Rata ~mrom/~oar) Infant Child Teenage-r _l.dult . 1.83£-02 3.27E-02 7.32E-02 Vegetable Pathwa;t Act ivi Soil Volume Soil Mass Concentration Concentration (Cml) (Kgl in Soilu'RCi/K9} in Vegetable~ (pCi/Ks) 3.oaE+o9 4.00E+06 1.28E-t-Ol 1. 28E-01 Cs-134-1 Page 229 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Vegetable Pathway Oose Rates (mre~/year) Infant Child Teenager Adult 2.90E-03 4.34E-03 Inhalation Pathway

                       . Ground Plane                                     Kl                   Air Concentration Conc.entl)lt ion (pCi /m2)                 (m- )                                (pCi/m'J}

2.53E+03 l.OE-05 2.53E-02 Inhalation Pathway Dose Rates (mrem/~ear) Infant Child Teenager Adult Continuous Occupancy 1. 88E-03 .5. 68E-03 1. 39E-02 l. S4E-02 Realistic Occupancy 1.38E-05 4.15E-OS l.OlE-04 1.35E-04 Release to lake Mithigan Activity Dfi/0fco-60 Co-60 eq. activity

                                  . (uCi l                                                              (JJCi) .

5.11E+Ol 2.56Et01 1. 31E+03

   !' *~ ;..: : ~:*r                               *.*,,  J.
                                                             .-~-"'"'       ' .

t".r:-,\,,;.*** ,

                                                                                 ~.
                                                                                          * *rr.. ,   . -:-;.

6 mrem

L31E+03
l.o£+U6 . l.Cl-*~ci -- 8 29E 05 mrem

                                                                                                           ~      -

94.7 ci Maximall~ Ex~osed Individual Infant Child Teenager Adult External 1. 94E-03 1.94E-03 1. 94E-03 1. 94E-03 Milk 3.87E-Ol 4.41E-Ol 6.03E-Ol 6.19E-Ol Heat 1.83E-02 3.27E-02 7.32E-02 Vegetable 2.90E-03 3.9SE-03 4.34[-03 lnha.1 at ion . 1. 38E-OS 4.15E-05 1. OlE-04 L35E-04 Water 8.29E-:-05 8:.29E-05 8.29£-0~ 8.29E-05 Totals.: 3.89E .. Ol 4.64E-Ol 6.42E""01 6.99E-Ol Child Teenager Adult External 2.66£-01 2.66E-Ol 2.66E-Ol 2.66E-Ol VPg~t.AhlP. 2.90E-03 3.9SE-03 4.34E-03 Inhalation L88E-03 5.68E-03 L39E-02 1. 84E-02 WAi'.l'r s_ 29E-*os 8.29[-05 8.29E-05 fL29F-05 Totals: . 2.68E-Ol 2.75E-Ol 2.84E-Ol 2.89E-Ol Cs-134-2 Page 230 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Cs-137 Concentration in Sludge: 2.0E-0£".JJCi/m1 Sludge Volume Concentration Activity Ground Plane (ctallons} (emS) (L!Ci /cml) {yCf) Concentration*(yCi/cm2) 1sooo *;5~. *tsE+o7 :?.OGf-06 1.14t+02 : :*.:s ~~2E~o.7 External Exeos~re y Dose Factor Ground Plane Concentration y Dose Rate

    ~rem/hr.         per pCi/m2)                              (pCi/m2)                         ( rnrem/;yea r}

4.20E-09 5~62E+03 2~07£-01 Continuous Occu'pancy: 2.07E-Ol mrem/ycar Realistic Occupancy: l~SlE-03 mrem/year Meat & Milk Pat.hwa.y Activity 1n Act1v1ty fn Concentration in Com::enlr*athm in Corn:entration in Sofl (J,JCi) Feed {b'Ci) Feed CeC1/Kg) Milk (pCi/£) Meat ~2Ci/kg)

    *.. 1~*146,..02~  <   'l"'l..-i4E+j09, :*,    . *". 6.13E+Gl              3. 6sE+rn.:.-.*. n*; .. , ,.*J_.L~l~#Jllr      ,i-:-**

Milk Dose Rates {mrem/year) Infant Child Teenager Adult 5.26E-OO 5.61E-Ol 7.64E-Ol B.lSE-01 Meat Dose Rate (mrem/yenr) Child Teenager Adult 2.33E-02 4.15E-02 9.66E:-02 Vegetable Pathwa~

   "*Aa-t i V*~:ty     Soil Volu111e            Soil Mass         Concentrat i.orr....  ~- ...,,. Concentration (pCi)   ~             {Cm3)                (Kg~

in Soil ([!Ci/K!J} in Vegetabl@S {~Ci/Kg)

1. 14£+02 l.OSt;+09 4.00E.J06 2.B5E+Ol 2. 85E*01 Cs-137-1 Page 231 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Vegetable Pathway Dose Rates (mtem/year) lnfa11t Child Teenager Adt,Jlt . 3~69E-03 5.03E~03 Inha1aqun Pathwi!l Ground Plane K... l Air Concentration

        *.Concentration (pCi/m2)               (M ) .                (pCi/m 3 )

5.62E+03 l.OE... OS 5.62E-02 Inhalation PathwaY Dose Rates (mrem/year) Infant Chi~ Teenager Adult Continuous Occupancy 2.56£-03 7.22E~03 1.7SE-02 2.41E-02 Realistic Occupancy 1. 87E*05 5. 27E-05 1. 28E-04 1. 76E-04 Release to lake Michigan Activity DFi/DFco-60 Co-60 eq. activity {HCi) (~Ci) 1..14E+02 1. 51E+Ol l./2t+U3

                                 ~ L72~+0~

1: O~+~!** pCi ~* 1. 09E-04

    .                  6 mrena 94.7 ci

mrem Haximall~ Exeoscd Individual Infant Child Teenager Adult*

Exterofll l.SlE-03 l.SlE-03 l.SlE-03 1.51E-03 Milk 5.26E-Ol 5.61E-Ol 7.64E-Ol 8+ 15E-Ol Meat 2.33E-02 4.15E-02 5.70E-03 Vegetable 3.69£-03 5.03E-03 5.70E-03 Inhalation 1.87E-05 5. 27E *05 . 1.28E...,04 1.76E-O~ Water 1. 09E-04 1.09E-04 1.09E-04 1.09[-04 Totals: 5.28E-Ol 5.90E-Ol 8.12E-Ol 9.19E-Ol Inadvertent Intruder Infant . cvi 1d Teenagf!: Adult fxternal 2.07E-Ol 2.07E-Ol £.07E-Ol 2.07E ... Ol Veg~table 3.69E-03 5.03E-03 5.70£-03 Inhalation 2.56E-:03 7.22E-03 1. 75E-02 2.41E-02 Water 1.09E-04 1.09E-04 1. 09E.-04 1.09E...,04 Totals! 2.10E~Ol 2.18E-Ol 2.30E-Ol 2.37£-01 Cs-137-2 Page 232 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Co-58 Concentration in Sludge; l.OOE-05 ~Ci/ml Sludge Volume Concentration Activity Ground Plan~ (Gallons) (clll~) (IJC tl.;m~) {..-Ci) Concentration (~Ci/cm~) 15000 5.68E+07 l.OOE*05 5.6BE+OZ l External E~posure

       'Y Dose Factor           Ground Plane Concentration                                    y  Dose Rate (mrem/hr. per pCi/mt)                        (pCi/m2 )                                     ~f!urem/year)

J.OOE-09 2.81E+04 1.72E+OO continuous occupancy: 1.7ZET00 mrem/year Realistic Occupancy: 1.26E-02 mrem/year Meat &Milk Pathwa~ Activity in Activity in Concentration in Concentration in concentration 1n Soil {~Ci) Feed (~Ci) feed (pCi/Kg) Milk (pCi/~) Meat {pCi/kgJ S.34E+OO 2.87E+02 ,..k,* * :

f-1.44E+Ol 1.87E+02

                                        .:..    ... ,- :t .. "'. .:.*

Milk Dose Rates (mrem/year) Infant Child Teenager Adult 4.27E-02 2.62E-02 1.29E-02 7.45E-03 Meat Dose Rate ~mre*/~ear} Infant Child Teenager Adult 4.22E-02 2 .. 72E-02 3. 44E-.02 Vegetable Pathwa~ Activity Soil Volume Soil Mass' Concentration Concentration {I*Ci) ~Cml~ {Kg} - in Soil (~Ci/K,g) in Vegetab 1es (~;!Ci /K~t-\ S.6SE+02 3.08E+09 4.00E+06 1_4~f-04 1.33[+00 Co-58-1 Page 233 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Vegetable Pathway Oos<i Rates (mrerm/year) Infant Te~nager Adult 2.nst:-o3 l .. OlE-03 6.22E-04 Inhalation Pathway Ground Plane Kl Air Concentration Concentration (pti/m2) {m- ) (pCi /m3 ) ....... * ~ ,, r.:tr.,: 2.81E+04 l.OE-05 2.81E*Ol

                                !~h~l~!tion   Pathway Dose Rates (mre11/year)

Child Teenager Adult Continuous Occupancy S.llE-04 8.89E-04 7.80E-04 5.82E-04 Realistic Occupancy 3.74E-06 6.49E-06 5.70E-OG 4.25E-06 Release to lake Michigan

Activity DF;/DFco-60 Co-60 eq. activity

                             ~J:!C1)                                          (t:JCi) 5.68E+02           3.54E-Ol                       2.01E+02
                 . : -:: ,:6r;:mrem .

z~ ~.~oz 94.7 ci ........ ~ ~

JJC 1 .lit ... Jlt ci *

1. OE+06 *tic1

                                                                                 =1 *..27 E~os  * -

Maximall~ Exf!OS@d Individual Infant Child Jeenaser Adult External 1.26E*02 1.26£-02 1.26F.-O? l.26E-02 Milk 4.27E*02 2.62E-02 L29E-02 7.45£-03 Meat 4.22E-02 2. 72E-,02 ~.44E-02 Vegetable 2.05E-03 1. OlE*OJ 6.22E*-04 Inhalation '3. 74£~06 6.49£-06 5.70£-06 4.2;F-06 Water 1.27E-05 1.27E-05 L27E-05 1.27E-OS Totals: 5.53E-02 8.31E-02 S.37E-02 5.51E .. 02

                                             !n~d~~rt~n~         Intruder
   ...                                     Infant               Child           TeenaJJer                 Adult External                1.72E+OO           1. 72E+OO           1.72E+OO                1.72E+OO Vegetable                                  2.05£-03            1. OlE-03               6.22E-04
                *Inha 1at ion            5.11E-04           8.89E-04            7.80£-04                5.82E-04 Water                   1. 27E~os          1.27E-05            1.27E-OS                1. ~7E-OS Totals:       1. 72E+OO          1. 72E+OO           1. 72E+OO               1. 72E+OO co-!Js~z Page 234 of278                                               REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

    .9?.:!?2 Concentr~t1on    in    Sludg~;   S.OE-06   ~Cf/ml Sludge Volume             concentration          Act1v1ty                    l';rc,mnd Plane iGallons) (cml)                  (pCi/c;;m!)           (pCi) .        Concentration (pCi/cm2}

15000 5.68E+07 S.OOE*06 2.84£+02 1.41E-06 External Exposure y Dose Factor Grc~nd Plane concentration y Oose Rate (mrem/hr. per pCi/m2) (eCi/m2) Jmrem/year) l.70E-08 1.41E+04 2.09E+OO Continuous Occupancy: 2.09E+OO mrem/year Realistic Occupancy: 1.53E-02 mrem/year Meat &Milk Pathwa~ Activity in Activity in Concentration in Concentration in Concentration in Soi 1 (JJCi) Feed (JJCi) . Feed {pCi/Kg) Milk (pCi /.t)_ Meat (pCi /kg)

      ;2. 84E+02      2.67E+OO             1.44E+02              7 .lS'Ei£00:: ;.: :

9:33E+Ol Milk Dose Rates(mrem/year)

Infant Child Teenager Adult fi. 04£-02 3.70E-02 1.82E-02 l.OSE-02 Meat Dose Rate (mre111/year} Infant Child Teenager Adult 5.97E-02 l.84E-02 4.84E-02 Vegetable Pathway Activity Soil Volum@ Soil Mass Concentration Concentrati6~ _ (IJCi} ~~ (Kgl_ in Soil (pCi/Kg) in Vegetables (pCi/Kg) 2.84E+02 3.08E+09 4.00E+06 7.10E+Ol 6.67E-Ol Co-60-l Page 235 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Vegetable Pat~!fa:t Dose Retes (mrern/year) Child_ Teenage~ Adult 2+91E-03 8.82E-01 lnhalation Pathway Ground Plane ~~ Air Con,entration Concentration (pC~Jm2) (m ) (pCi/m 3 }

1. 41E+04 l.OE-05 1.41E-Ol Inhalation Pathway Oose Rates (mrem/year)

Child Teenager _Bdult Continuous Occupancy 1.66E-03 3.19E-03 2.80E-03 2.09E-03 Realistic Occupancy 1.21E-05 2.33E-05 2.05E-05 1.53E-05

     *Release to lake Michigan Activity         DFi/Ofco-60            Co-60 eq. activity (lJCi)                                --.:u.<~o'.lli.~-~  --*-

6 mrem 94.7 Ci

Z.84ET0ZpCi
1 Ci L OE+06 tJC{

                                                                        =1* SOE-OS rn-em H

Maximally Exposed Individual Infant Child TPP.nager Adult External 1.53[-02 1.53E-02 1.53[-02 1. 53E-02 Milk 6.04£-02 3.70E-02 1. 82E-02 1. OSE-02 Meat 5.97£-02 1.84E-02 4.84F-02 Vegetable 2.91E-03 L44E-03 8.82E-04 Inhalation 1.21E .. 05 2.33E-05 2.05E-05 1. !"13f-05 Water 1.80E~o5 1. 80E-05

l.SOE-05 1. 80£-05 Totals: 7.57E-02 LlSE-01 7.34E-02 7.51E-02 Inadvertent Intruder Infaot l:hild Teenager Adult External 2.09E+OO 2.09f..-t00 2.09E+OO 2.09E+\l0 Vegetable 2. 91E~03* L44E~03 8.82£-04 Inhalation 1. 66E,Ol 3.19E-03 2.80E-03 2.09E*03 Water 1. 80E*05 !.SOE-05 1.80£-03 ~-u~

Totals: 2.09E+Ou 2.10E+OO 2.10E+OO 2.09£+00 Co-60-2 Page 236 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL CALCULATIONAL M§Tt19DOLOGV FOR OETERMINI_NG EXTERNAl DOSE RATES fROM RADIONUC~lDES AFTER INCORPORATIOH_lNTO SOIL Page 237 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL Wisconsin Electric utilizes QAD; a nationally recognized computer code, to perform shielding and dose rate analys~~- Th~ QAD computer code utilizes a point kernel methodology to calculate the dose rate at a specified point due to ~ given source of r~diation. QAD will be u5cd to calculate the dose rate du~ to ~t~nd~ng *on a plot of land utili2ed for sludge disposal after the radionuclide$ have been incorporated into the plot by plowing. The following parameters will be used in the calculation: The total activity from all previous disposals will be corrected for radiological decay and us~d as the radin-nuclide sour-ce term. Appropriate values will be used to represent the surface area of the plot. 0 The radionuclides will be assumed to be incorporated uniformly into the top six inches of soil. The dose rate will be calculated at a height of 1 meter above theground pltitne at a depth of 5 centimeter:; in tissue. (Regulatory Guide 1.109 values).

               ':ifh~ *aensity-of the sofl 'Wi'll b~*,*as:'sumed'-to be ~;i3"'gramsJ"',-.-,

cubtc centimeter. This calculated dose rate will be used to assess the rari1olQgical consequences of past disposals in conjunction with the consequences of proposed future disposals. The total radiological dose con~equenc.(! of 'Lhe p~$t and the pro-posed disposal will be compared to the applicable limits to insure the dose is maintained at or below the 11~1ts. Page 238 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXH MODIFICATION #1 TO NRC SUBMITTAL Modifications to the Wisconsin Electric submittal to the United States Nuclear Regulatory Commission dated October 8, 1987 (VPNPD-87-430, NRC-87-104), Disposal by Land Application of Sewage Sludge Containing Minute Quantities Of Radioactive Material. Page 239 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL MODIFICATION #1 TO NRC SUBMITTAL CHANGE TO ORIGINAL SUBMITTAL Section 3.2, Disposal Procedure (page 3) Section 3.3, Administrative Procedure (page 4) The requirements for sludge characterization (the determination of the chemical and physical properties of the sludge) contained in the sections referenced above are modified to allow characterization of the sludge on an annual basis. BASIS/EXPLANATION The October 8, 1987 submittal to the USNRC for permission to dispose of sewage treatment sludge containing minute quantities of radioactive material requires that, "prior to disposal the waste stream will be monitored to determine the physical and chemical properties of the sludge ... ". Subsequent to the submittal and the approval by the NRC, a new Wisconsin Pollutant Discharge Elimination System (WPDES) permit was issued to the Point Beach Nuclear Plant by the Wisconsin Department ofNatural Resources on November 30, 1988. Both the new WPDES permit and the Point Beach Nuclear Plant Sludge Management Plan specify an annual required frequency for the evaluation of the sludge characteristics. The original requirement to perform the characterization of the chemical and physical properties of the sewage sludge prior to each disposal has proven time consuming and costly for Wisconsin Electric Lab Services. Preparation of special analytical standards are required to complete the characterization study. The preparation of these standards, sample preparation, and the actual analyses are all manpower intensive and difficult to perform on a timely basis. This has led to requiring overtime for Lab Services personnel and support from outside companies. In order to better utilize the resources of Lab Services while maintaining the requirements of the WPDES permit, the frequency of sludge characterization in the October 8, 1987 submittal to the NRC should be changed to an annual requirement. This change in the required frequency for determination of the sludge characteristics does not change the requirement to analyze the sewage sludge for radionuclide content or perform dose evaluations prior to each disposal. Page 240 of 278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIX I MODIFICATION #2 TO NRC SUBMITTAL Modifications to the Wisconsin Electric submittal to the United States Nuclear Regulatory Commission dated October 8, 1987 (VPNPD-87-430, NRC-87-104), Disposal by Land Application of Sewage Sludge Containing Minute Quantities Of Radioactive Material. Page 241 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL MODIFICATION #2 CHANGE TO ORIGINAL SUBMITTAL Section 3.3, Administrative Procedures (Page E-1 0) The limitation on the annual volume of sludge disposal per acre contained in the section referenced above is modified to allow unlimited disposal provided the other requirements of this submittal are met. BASIS/EXPLANATION The October 8, 1987, submittal to the USNRC for permission to dispose of sewage treatment sludge containing minute quantities of radioactive material requires that "the annual disposal rate for each of the approved land spread sites will be limited to 4,000 gallons/acre, provided WDNR chemical composition, NRC dose guidelines, and concentration and activity limits are maintained with the appropriate values". The original requirement to limit sewage sludge disposal to 4, 000 gallons per acre is based on the assumption that the sewage sludge is contaminated with Co-58 at a concentration that is ten percent of the 10 CFR Part 20 Appendix B Table 2 Column 2 value. Past sewage sludge disposal experience has shown that the sludge may or may not be contaminated and, if it is, at concentrations far below ten percent of the performed prior to each sewage sludge disposal. With the removal of some of the land spread sites due to their use as a storage site for dry storage of spent fuel, this requirement is limiting our ability to dispose of the sewage sludge on the remaining approved land spread sites. This removal of the annual volume of sewage sludge that may be disposed of per acre on approved land spread sites does not change the requirement to analyze the sewage sludge for radionuclide content or perform dose evaluation prior to each disposal. This change was evaluation under SER 95-057, "Removal of licensee Commitment Involved With Sewage Sludge Disposal", 4/20/95. Page 242 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL

                                       ~tODIFICA TION        #2 Depth   ta grouncvater    and btdrru:; k s:ha 1 1 t>e the 1aod   s~rface *1ev~t1~               usu   ~f  any Sludge   $t~1l  net  b~ 1A~d spre~      in a flaQdway.

Sludge sh~ll not be 1*nd spr*tQ witn1n 50 fe~t ~t a property lin@ rcaQ or ditch unles$ the sludge is 1Rcorporated with the 1ailp tn which case a *ini~~ sepe~aticn di~tanca of at leait 2S f**t is r.quired. The pH of t.hre ~1udge-5oil 11ixtur* sha1 be 11aJnutruMt at 6.5 or higher. low ar@~J of the Approv@d field$, $ubject to 5eason*11J hi~h g~ound watar le~elsJ are eKcluae~ from the ,1udge ap~li~ation. Crops foT numan con~umption ~ha1 not be g~n on tn. land fQr up to ona year folhnr1ng the appHcat.icn of ~ .Gludgt .. The sludge 5ha1 be plowed. diske~. inJected or otherwise into the surfaee soil la~er At appropr1ate inter~als_ Tne ilexibility implied in ine latter p~o~isicn for soil incerporat1o~ is intended to allow for crops ~ich require ~re than a one y~a~ eyele. fo~ the Poi~t Beach d1spo$a1 site$. a1falf~ is a t~n crtp ~ich i~ haTYested to~ 5everal yea~& efte~ a s1~1e ~leoting~ Sludge dfs~osal en an elfalfa p1o~ eonstitutes good fertil1zation. but the plot cannot b* l)lC)~d wit.hout. de$tl"oyi,..g the tf'rtp. The a1 *ra1fa in ~fs ea5e lids 1n

          ~1~ding the lay*r of .GlU4gt on the Jurt*~* Of the ~loiH               At 1 ~iniaumw hc~~er; plowing (or disting o~ oth*r ~thod of injection and ~ixing to a ~omfna1 depth of 6 1nch&i) lht1 be done prior to planting ~ny new crop, ragardle11 of the crap.

3.3 Administrative frpcedures tOtDP l*te record1 of each di t.pos.a l wi ll be *a ~ nta faed. Tneit r.<<tcords will include ihe concentratign of r6dioouc1ides in the sludge, the total volu.i of sludg1 dis~os*d~ the total a~tiwit1 1 the plot en which the ~ludoe was appl~ed, the results of the che*ical coapa$ition determination!~ end all dose calculations. The ann~id~~sa1 ~ate for ea~ ~f the approved land sp~ead sites wi 11 bt "l~ "" -., oog .~i Orttflc .... I pro"" i O.d 'WD:NR ehRrt t C::ll COn'lp0$1-t ion

NRC dot..a gui del huts, and cone antl"at; on and act i v1 ty H*i t s are

               **intAinad within the *ppropriAte Vllues.

The f*nner lt.as~ng: tn. stu usld for the dhpt\511 lfnl tHt notified of the epp1iQI)1e re:5trietfon$ p1~ced Oil the site due to tl'tt l*nd tpf'U<Iirtg of itwafe sl~. 4.0 £valuation cf Enviranmenta1 Imeact

         ~-1   Site Chartsttrist1cs 4.1.1 Thrt dhprn..al :Sitits 1re lel!ated fn ttle Town of Two Crte:lt.s in tbe nort.heas.t corner 1)1    ~nitowr,x; County 3 Whe:onsi n, on thi li-10 Page 243 of278                                 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIX I MODIFICATION #3 TO NRC SUBMITTAL Modifications to the Wisconsin Electric submittal to the United States Nuclear Regulatory Commission dated October 8, 1987 (VPNPD-87-430, NRC-87-104), Disposal by Land Application of Sewage Sludge Containing Minute Quantities Of Radioactive Material. Page 244 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL MODIFICATION #3 TO NRC SUBMITTAL CHANGE TO ORIGINAL SUBMITTAL Section 3.2 of Attachment II of the October 8, 1987letter to the NRC contains the commitment to perform a gamma isotopic analysis of sewage sludge samples prior to every sludge disposal on land surrounding PBNP. The analytical results are to be used to evaluate the dose consequences of the radionuclides entering the environmental via this disposal pathway. As described in ODCM Section 7, the requirement for a radioisotopic analysis of the sewage sludge prior to every disposal on land surrounding PBNP is modified if the sludge has been shown to be clean and there is no reason to believe that the sludge is contaminated. BASIS/EXPLANATION Small ~Ci quantities ofPBNP licensed materials (Co-58/60, Cs-134/137, Cr-51, and Mn-54) were found in PBNP sewage treatment plant (STP) sludge. Pursuant to of 10 CFR 20.302(a), Wisconsin Electric applied to the NRC for permission to dispose of the licensed material by applying the sludge to Wisconsin Electric land surrounding PBNP. In the October 8, 1987 application letter, Wisconsin Electric committed to gamma isotopic analysis of the sludge prior to every disposal in order to evaluate the dose consequences of this disposal and to compare radionuclide concentrations to the 10 CFR 20, Appendix B, maximum effluent concentrations. However, such analysis are not required if the sludge does not contain licensed material. It there is no reason to believe that the sludge is contaminated and if there is no pathway from the RCA to the STP, then there is no reason to analyze the sludge for radionuclides once it has been shown to be clean. Administrative controls and engineering modifications to PBNP have removed the pathway from the RCA to the STP as verified by subsequent analyses of the sludge under conditions required to obtain the environmental LLDs. These analyses have not revealed radionuclides attributable to PBNP. Pursuant to NRC HPPOS-221, a substance is clean if analyses under analytical parameters necessary to achieve the environmental LLDs does not reveal any licensed material. These LLDs define how hard you have to look. Below this detection level, " ... the probability of undetected radioactivity is negligible and can be disregarded when considering the practicality of detecting such potential radioactivity from natural background ... " (Docket No. 50-206, letter to J. E. Dyer from L. J. Cunningham dated September 6, 1991). Therefore the NRC criteria are met and there is no longer any reason to believe that the STP sludge is contaminated. However if plant conditions should change in a manner compromising the NRC criteria, radiological analysis must be made prior to each STP sludge land application until such time that the clean criteria are satisfied pursuant to subsequent NRC guidance. Page 245 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXK LIQUID EFFLUENT DOSE CONVERSION FACTORS The tables below identify the expected dose to each of the four age ranges (adult, teen, child and infant) as a result of activity released via liquid effluents. These dose conversion factors are based on Reg. Guide 1.109 and NUREG-0133 assumptions. The pathways included in these DCFs are drinking water and fish. The other pathways (irrigated meat, irrigated milk, invertebrates and shoreline exposure) are either not applicable or contribute a negligible contribution to the dose. The dose conversion factors below assume a discharge flow of 6. 77E+05 gpm. If actual plant conditions are significantly different, revised DCFs should be calculated and used. Fji_3 Liquid release (mrem/Ci released) Bone Liver T.Body Thyroid Kidney Lung GI-LLI Adult O.OOE+OO 1.34E-06 1.34E-06 1.34E-06 1.34E-06 1.34E-06 1.34E-06

           '~
                           < ,.      *Teen          O.OOE+OO     9.51E-07      9.51E-07      9.51E-07         9.51E-07    9.51E-07   9.51E-07
            >              *. ;Cilitd               O.OOE+OO     1.75E-06       1.75E-06     1.75E-06         1.75E-06    1.75E-06   1.75E-06

_{*.~,..;;;>* O.OOE+OO 1.65E-06 1.65E-06 1.65E-06 1.65E-06 1.65E-06 1.65E-06 C-14 Liquid release (mrem/Ci released)

                      *      <           ~, * *
           . ~ *:        ** >>~* ** ' :         '.~,~ Bone   ~'   Liver,,  ~~,  T.Body   ~~ Thyroid    ', ~ ~ l(idney      Lung      GI-LLI
        * * <.            ~>         A.auit         2.32E-02    4.64E-03       4.64E-03     4.64E-03         4.64E-03    4.64E-03   4.64E-03
       *~~.     >*c. **Teirr         ~" . ...

2.52E-02 5.05E-03 5.05E-03 5.05E-03 5.05E-03 5.05E-03 5.05E-03 i *.~,* ~); ~. *** .... Child 3.25E-02 6.51E-03 6.51E-03 6.51E-03 6.51E-03 ~ 6.51E-03 6.51E-03

    **s *.
        ~ ~*~ ~ :; : ; ';           inr~~r          2.23E-04    4.76E-05       4.76E-05     4.76E-05         4.76E-05    4.76E-05   4.76E-05 1.35E-08     O.OOE+OO        O.OOE+OO     O.OOE+OO O.OOE+OO       1.52E-08     O.OOE+OO        O.OOE+OO     O.OOE+OO   4.16E-08 O.OOE+OO       5.27E-14     O.OOE+OO        O.OOE+OO     O.OOE+OO   1.45E-13 3.49E-03       3.49E-03     3.49E-03         3.49E-03    3.49E-03 4.27E-03      4.27E-03      4.27E-03         4.27E-03    4.27E-03   4.27E-03 9.23E-04       9.23E-04     9.23E-04         9.23E-04    9.23E-04   9.23E-04 l.SIE-04    l.SIE-04       l.SIE-04     l.SIE-04         l.SIE-04    l.SIE-04   l.SIE-04 2.02E-04      2.02E-04      2.02E-04        2.02E-04     2.02E-04   2.02E-04 1.03E-05    1.03E-05       1.03E-05     1.03E-05         1.03E-05    1.03E-05   1.03E-05 Page 246 of278                                      REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXK LIQUID EFFLUENT DOSE CONVERSION FACTORS P-32 Liquid release (mrem/Ci released) Bone Liver T.Body Thyroid Kidney Lung GI-LLI

                         ~~*'

Adult 3.33E+Ol 2.07E+OO 1.29E+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.75E+OO Teell 3.63E+Ol 2.25E+OO 1.41E+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.05E+OO

      / ,. ',.. '* Child                         4.68E+Ol   2.19E+OO   1.81E+OO         O.OOE+OO       O.OOE+OO    O.OOE+OO          1.29E+OO Infant           1.45E-02  8.53E-04   5.62E-04         O.OOE+OO      O.OOE+OO     O.OOE+OO           1.96E-04 Sc-46                                                          Liquid release (mrem/Ci released)

Bone Liver T.Body Thyroid Kidney Lung GI-LLI I A.afiit; 1.32E-07 2.57E-07 7.46E-08 O.OOE+OO 2.40E-07 O.OOE+OO 1.25E-03

                 *,:: }>,. (            ren       1.23E-07  2.39E-07   7.10E-08         O.OOE+OO       2.29E-07   O.OOE+OO           8.15E-04
   <         *.: . *          >*c 1ld            3.04E-07   4.17E-07   1.61E-07         O.OOE+OO      3.69E-07    O.OOE+OO           6.10E-04
    *           ***           <: ~'~       *;_
       >             * . . * .1.n ,ant           3.47E-07   5.00E-07   1.56E-07         O.OOE+OO      3.29E-07    O.OOE+OO           3.26E-04 I Cr-51                                                            Liquid release (mrem/Ci released)

Liver. 'i::Btidy .. *,**,,Thyroid

Kidney Lung ', GI-LLI O.OOE+OO 9.82E-07 5.87E-07 2.16E-07 1.30E-06 2.47E-04 O.OOE+OO l.OlE-06 5.60E-07 2.21E-07 1.44E-06 1.70E-04 O.OOE+OO 1.15E-06 6.36E-07 1.74E-07 1.16E-06 6.07E-05 O.OOE+OO 1.26E-07 8.23E-08 1.80E-08 1.60E-07 3.68E-06 Mn-54 Liquid release (mrem/Ci released)

Liver T:Bodjr Thyroid ** kiilll~Y ~, .tulie *,* * *** GJ..:LLI 3.33E-03 6.35E-04 O.OOE+OO 9.90E-04 O.OOE+OO 1.02E-02 3.26E-03 6.47E-04 O.OOE+OO 9.74E-04 O.OOE+OO 6.69E-03 2.64E-03 7.03E-04 O.OOE+OO 7.40E-04 O.OOE+OO 2.22E-03 1.86E-04 4.22E-05 O.OOE+OO 4.13E-05 O.OOE+OO 6.84E-05 Mn-56 Liquid release (mrem/Ci released) O.OOE+OO 4.28E-06 2.23E-04 3.08E-06 6.96E-07 O.OOE+OO 3.73E-06 O.OOE+OO 4.47E-04 1.91E-11 3.29E-12 O.OOE+OO 1.64E-11 O.OOE+OO 1.73E-09 Kidne O.OOE+OO 2.15E-04 4.00E-04 9.33E-05 O.OOE+OO O.OOE+OO 2.54E-04 1.73E-04 8.35E-04 4.43E-04 1.37E-04 O.OOE+OO O.OOE+OO 2.51E-04 8.21E-05 1.30E-04 8.43E-05 2.25E-05 O.OOE+OO O.OOE+OO 4.12E-05 1.07E-05 Page 247 of278 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXK LIQUID EFFLUENT DOSE CONVERSION FACTORS Fe-59 Liquid release (mrem/Ci released) Bone Liver T.Body Thyroid Kidney Lung GI-LLI Adult 8.50£-04 2.00£-03 7.66£-04 O.OOE+OO O.OOE+OO 5.58£-04 6.66£-03 Teen 8.68£-04 2.03£-03 7.82£-04 O.OOE+OO O.OOE+OO 6.39£-04 4.79£-03 Child 1.18£-03 1.92£-03 9.55£-04 O.OOE+OO O.OOE+OO 5.56£-04 2.00£-03 In.fant 2.81£-04 4.90£-04 1.93£-04 O.OOE+OO O.OOE+OO 1.45£-04 2.34£-04 Co-57 Liquid release (mrem/Ci released) Bone Liver T.Body Thyroid Kidne_y Lung GI~LLI

        -'-       .         . Adult                            O.OOE+OO     1.91£-05      3.17£-05     O.OOE+OO   O.OOE+OO    O.OOE+OO     4.84£-04
             '               * *.*  .1't~h~                   O.OOE+OO      1.95£-05      3.26£-05     O.OOE+OO   O.OOE+OO    O.OOE+OO     3.63£-04 I             .

Child O.OOE+OO 2.14£-05 4.34£-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.76£-04

                     .*h       <.*.*
                       ; . mfant                              O.OOE+OO      1.08£-05      1.75£-05     O.OOE+OO   O.OOE+OO    O.OOE+OO     3.67£-05 Co-58                                                                           Liquid release (mrem/Ci released)

Liver T.:Body ..* Thyroid Kidney Lun~ GJ..,LLI 8.08£-05 1.81£-04 O.OOE+OO O.OOE+OO O.OOE+OO 1.64£-03 7.91£-05 1.82£-04 O.OOE+OO O.OOE+OO O.OOE+OO 1.09£-03 7.77£-05 2.38£-04 O.OOE+OO O.OOE+OO O.OOE+OO 4.53£-04 3.32£-05 8.28£-05 O.OOE+OO O.OOE+OO O.OOE+OO 8.27£-05 Co-60 Liquid release (mrem/Ci released)

       . ; J~.:. ,:; . :~ ;;                                 *~~~iJ~ile Liver*****   TJJoC:If.   *fhirtiid. Kiilii~y ", 'I.,uitg  . GJ..,LLI I~
          '** >*<:*0A".:f, O.OOE+OO     2.34£-04      5.16£-04     O.OOE+OO   O.OOE+OO    O.OOE+OO     4.39£-03 I' : >f::*~.;.,,**. 'l'e~ ..*

O.OOE+OO 2.30£-04 5.19£-04 O.OOE+OO O.OOE+OO O.OOE+OO 3.00£-03

i;1 . *;;*;;;..:

               ~J.; *)~                        ~;     ,.
                ***   ;.;;p*       ...... ....,...,           O.OOE+OO     2.31£-04      6.80£-04     O.OOE+OO   O.OOE+OO    O.OOE+OO     1.28£-03
     . *.*. ;.*~.*~~* .:Tjl.fifil,*'                          O.OOE+OO     1.01£-04      2.40£-04     O.OOE+OO   O.OOE+OO    O.OOE+OO     2.41£-04 Ni-63 Kidne O.OOE+OO                 3.72£-04 1.87£-03      8.96£-04     O.OOE+OO   O.OOE+OO    O.OOE+OO     2.97£-04 2.09£-03      1.33£-03     O.OOE+OO   O.OOE+OO    O.OOE+OO     1.41£-04 3.69£-04      2.07£-04     O.OOE+OO   O.OOE+OO    O.OOE+OO     1.83£-05
                                                                                                                  *id.n.f O.OOE+OO    O.OOE+OO     1.13£-05 4.74£-07      2.16£-07     O.OOE+OO   O.OOE+OO    O.OOE+OO     2.57£-05 4.46£-07      2.60£-07     O.OOE+OO   O.OOE+OO    O.OOE+OO     5.47£-05 8.03£-11     9.09£-12      4.13£-12     O.OOE+OO   O.OOE+OO    O.OOE+OO     6.92£-10 Page 248 of278                              REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXK LIQUID EFFLUENT DOSE CONVERSION FACTORS Cu-64 Liquid release (mrem/Ci released) Bone Liver T.Body Thyroid Kidney Lun~ GI-LLI Adult O.OOE+OO 3.96E-06 1.86E-06 O.OOE+OO 9.97E-06 O.OOE+OO 3.37E-04

                      ... *.. Teen            O.OOE+OO    4.15E-06       1.95E-06    O.OOE+OO      l.OSE-05      O.OOE+OO       3.22E-04
          ...    *:            Child          O.OOE+OO    3.96E-06       2.39E-06    O.OOE+OO     9.57E-06       O.OOE+OO        1.86E-04 Infant          O.OOE+OO    4.17E-07       1.93E-07    O.OOE+OO     7.05E-07       O.OOE+OO       8.56E-06 Zn-65                                                       Liquid release (mrem/Ci released)
                                 ..             Bone        Liver        T.Body      Thyroid       Kidney          Lun~          GI-LLI Adult           1.72E-02    5.48E-02      2.47E-02     O.OOE+OO     3.66E-02      O.OOE+OO        3.45E-02 Teen         1.56E-02    5.42E-02      2.53E-02    O.OOE+OO      3.47E-02      O.OOE+OO        2.29E-02 Child           1.61E-02    4.29E-02      2.67E-02    O.OOE+OO      2.70E-02      O.OOE+OO        7.54E-03
                          .Infant             1.72E-04    5.90E-04      2.72E-04    O.OOE+OO      2.86E-04      O.OOE+OO        4.98E-04 Zn-69m                                                      Liquid release (mrem/Ci released)

i> ' *. *** *
Bone . I Liver ,. ** T.Body ... Thyroid.*. Kidney Lung GI-LLI

      * . *********<,'.')Adult                3.29E-04    7.90E-04      7.22E-05    O.OOE+OO     4.78E-04       O.OOE+OO        4.82E-02
   *.*. *}.

Te~il 3.54E-04 8.34E-04 7.65E-05 O.OOE+OO 5.07E-04 O.OOE+OO 4.59E-02

         *. : ',~~        .~*ciiilti          4.52E-04    7.70E-04      9.11E-05    O.OOE+OO     4.48E-04       O.OOE+OO        2.51E-02
    .. .            **' *'lil.fa.llt          1.26E-06   2.56E-06       2.34E-07    O.OOE+OO      1.04E-06      O.OOE+OO        3.55E-05 Zn-69                                                         Liquid release (mrem/Ci released)
  '~*C:~.1.t ..'\<1;(Iuff                    4.91E-09    9.40E-09       6.54E-10    O.OOE+OO     6.11E-09       O.OOE+OO        1.41E-09
   .*.***~*****. ;. /}*s.7. ~~-5._34_E_-0_9-+_1._02_E_-0_8-+_7_._12_E_-l_O-+_O_.O_O_E_+_00-+_6_.6_5_E_-0_9-+_0_.0_0_E_+0_0-+_1_._88_E_-0_8-11
  *~:;. *~~&T ~~~fin l* 6.87E-09                         9.92E-09      9.17E-10     O.OOE+OO     6.02E-09       O.OOE+OO       6.25E-07
       *t*..; ><*fiifaill                    2.89E-22    5.21E-22      3.88E-23     O.OOE+OO     2.17E-22       O.OOE+OO       4.25E-20 As-76 Liver        T.Bod 1.60E-04      7.99E-04                                                6.99E-03 1.55E-04      7.58E-04     4.55E-05     1.82E-04       4.55E-05       6.83E-03 1.72E-04      9.99E-04     5.85E-05     1.89E-04       5.85E-05       8.95E-03 9.83E-05     2.16E-05     5.99E-05       2.16E-05       6.29E-04 Kidne O.OOE+OO                      1.54E-03 O.OOE+OO    O.OOE+OO       O.OOE+OO        O.OOE+OO O.OOE+OO      l.SOE-03     O.OOE+OO    O.OOE+OO       O.OOE+OO        O.OOE+OO O.OOE+OO     4.65E-05      O.OOE+OO    O.OOE+OO       O.OOE+OO        O.OOE+OO Page 249 of278                                    REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXK LIQUID EFFLUENT DOSE CONVERSION FACTORS Br-83 Liquid release (mrem/Ci released)

                            *.                                                Bone       Liver      T.Body      Thyroid     Kidney       Lung      GI-LLI Adult                           O.OOE+OO   O.OOE+OO    9.34E-07    O.OOE+OO    O.OOE+OO    O.OOE+OO    1.35E-06 Teen                          O.OOE+OO   O.OOE+OO    1.02E-06    O.OOE+OO    O.OOE+OO    O.OOE+OO   O.OOE+OO
       *   *.*         * ..                 Child                           O.OOE+OO   O.OOE+OO    1.31E-06    O.OOE+OO    O.OOE+OO    O.OOE+OO   O.OOE+OO Infant                             O.OOE+OO  O.OOE+OO     3.25E-12    O.OOE+OO    O.OOE+OO    O.OOE+OO   O.OOE+OO Br-84                                                                                 Liquid release (mrem/Ci released)
                            .**...                                            Bone       Liver      T.Body     Thyroid [*. Kidney        Lung      GI-LLI Adult                             O.OOE+OO  O.OOE+OO     5.92E-12    O.OOE+OO    O.OOE+OO    O.OOE+OO   4.65E-17
                     .                       Teen                          O.OOE+OO   O.OOE+OO     6.25E-12    O.OOE+OO    O.OOE+OO   O.OOE+OO    O.OOE+OO ehild                           O.OOE+OO   O.OOE+OO     7.39E-12    O.OOE+OO    O.OOE+OO   O.OOE+OO   O.OOE+OO
       *.*      .....    *.          'Infant                               O.OOE+OO  O.OOE+OO     O.OOE+OO    O.OOE+OO     O.OOE+OO   O.OOE+OO   O.OOE+OO Br-85                                                                                   Liquid release (mrem/Ci released)
                  ..            .f<                                      .. *Bone    .. Live'r     T.Bo(ly .*  Thyroid      Kidney       Lun~      GI-LLI
                                                  . . . . . . . . . . .h
                     **** .....*.

Adult O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ji'] 7eei.. O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

    . . *.*****.:,z**~./ *..** ,.In r~ r1f
                                    .*:.::.,.;. ~  .                      O.OOE+OO   O.OOE+OO     O.OOE+OO    O.OOE+OO    O.OOE+OO    O.OOE+OO   O.OOE+OO 7.93E-02     3.73E-02    O.OOE+OO    O.OOE+OO                1.17E-02 7.74E-02     4.76E-02    O.OOE+OO    O.OOE+OO    O.OOE+OO   4.98E-03 1.48E-03     7.33E-04    O.OOE+OO    O.OOE+OO    O.OOE+OO   3.80E-05 Liquid release (mrem/Ci released)

Liver
T~Bod 1.22E-16 6.46E-17 O.OOE+OO 1.31E-16 6.96E-17 O.OOE+OO O.OOE+OO O.OOE+OO 1.12E-23 1.26E-16 8.73E-17 O.OOE+OO O.OOE+OO O.OOE+OO 6.16E-18 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kidne GJ..:LLI O.OOE+OO O.OOE+OO 1.25E-18 8.84E-19 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.15E-18 1.02E-18 O.OOE+OO O.OOE+OO O.OOE+OO l.OOE-20 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 250 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXK LIQUID EFFLUENT DOSE CONVERSION FACTORS Sr-89 Liquid release (mrem/Ci released)
~
Bone Liver T.Body Thyroid Kidney Lung GI-LLI Adult 2.25E-02 O.OOE+OO 6.45E-04 O.OOE+OO O.OOE+OO O.OOE+OO 3.60E-03 Teen 2.39E-02 O.OOE+OO 6.84E-04 O.OOE+OO O.OOE+OO O.OOE+OO 2.85E-03 I **~.**Child 4.15E-02 O.OOE+OO 1.19E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.61E-03 Infant 2.30E-02 O.OOE+OO 6.59E-04 O.OOE+OO O.OOE+OO O.OOE+OO 4.72E-04 Sr-90 Liquid release (mrem/Ci released) Bone Liver T.Body Thyroid Kidney Lung GI-LLI Adult 6.44E-01 O.OOE+OO 1.29E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.62E-02
.. "Teen 5.61E-Ol O.OOE+OO 1.12E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.28E-02 . . ...... * *cb.ua* ~ ; ~** 8.19E-O 1 O.OOE+OO 1.65E-02 O.OOE+OO O.OOE+OO O.OOE+OO 7.32E-03 Infant 2.66E-Ol O.OOE+OO 5.40E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.17E-03 GI-LLI 6.14E-04 O.OOE+OO 5.55E-06 O.OOE+OO O.OOE+OO 6.33E-04 1.85E-04 O.OOE+OO 6.98E-06 O.OOE+OO O.OOE+OO O.OOE+OO 4.08E-04 1.42E-05 O.OOE+OO 5.13E-07 O.OOE+OO O.OOE+OO O.OOE+OO 1.68E-05 Sr-92 Liquid release (mrem/Ci released) 1 ? ~;;}, ;;':t f ~
I **Bo'iie**** :.**tiver ;_'_
T.Body
Thyroid .. Kidney

i.un.~* GI-LLI I /,;;*\:A rl It 5.30E-06 O.OOE+OO 2.29E-07 O.OOE+OO O.OOE+OO O.OOE+OO l.OSE-04
'******* ..:**~~.;~; ... .. .. *~ *e n 5.73E-06 O.OOE+OO 2.44E-07 O.OOE+OO O.OOE+OO O.OOE+OO 1.46E-04 . :,~.. ; **~*"'Ci!! ***~ .. \.: 7.32E-06 O.OOE+OO 2.93E-07 O.OOE+OO O.OOE+OO O.OOE+OO 1.39E-04 ll u Irifab.t 8.41E-1 0 O.OOE+OO 3.12E-11 O.OOE+OO O.OOE+OO O.OOE+OO 9.06E-09 GJ.-LLI 5.23E-03 O.OOE+OO 1.41E-08 O.OOE+OO O.OOE+OO O.OOE+OO 4.32E-03 O.OOE+OO 2.36E-08 O.OOE+OO O.OOE+OO O.OOE+OO 2.51E-03 O.OOE+OO 1.30E-08 O.OOE+OO O.OOE+OO O.OOE+OO 6.71E-04 .. GI~'LLI' 5.15E-13 1.89E-13 O.OOE+OO 7.24E-15 O.OOE+OO O.OOE+OO O.OOE+OO 8.94E-12 O.OOE+OO 8.80E-15 O.OOE+OO O.OOE+OO O.OOE+OO 4.74E-10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.13E-23 Page 251 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXK LIQUID EFFLUENT DOSE CONVERSION FACTORS Y-91 Liquid release (mrem/Ci released) Bone Liver T.Body Thyroid Kidney Lung GI-LLI Adult 9.07E-06 O.OOE+OO 2.42E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.99E-03 Teen 9.59E-06 O.OOE+OO 2.57E-07 O.OOE+OO O.OOE+OO O.OOE+OO 3.93E-03
.*.... Child 1.72E-05 O.OOE+OO 4.61E-07 O.OOE+OO O.OOE+OO O.OOE+OO 2.30E-03 Infant 1.04E-05 O.OOE+OO 2.76E-07 O.OOE+OO O.OOE+OO O.OOE+OO 7.44E-04 Y-92 Liquid release (mrem/Ci released)
Bone Liver T.Body Thyroid Kidney Lung GI-LLI Adult 3.57E-09 O.OOE+OO 1.04E-10 O.OOE+OO O.OOE+OO O.OOE+OO 6.25E-05
< Teell 3.89E-09 O.OOE+OO 1.13E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.07E-04 .* Child S.OOE-09 O.OOE+OO 1.43E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.44E-04 '** IIifant 5.96E-12 O.OOE+OO 1.67E-13 O.OOE+OO O.OOE+OO O.OOE+OO 1.14E-07 Y-93 Liquid release (mrem/Ci released)
.. . *.* <c
.* . Bone Liver T.Body Thyroid Kidney Lung GJ;..LLI *.*.**.v:**************** ..... Adult 5.46E-08 O.OOE+OO 1.51E-09 O.OOE+OO O.OOE+OO O.OOE+OO 1.73E-03 > .* **.** ....**.*.* Teen ....*... .... 5.93E-08 O.OOE+OO 1.62E-09 O.OOE+OO O.OOE+OO O.OOE+OO l.SIE-03
. ...**~'*child 7.97E-08 O.OOE+OO 2.19E-09 O.OOE+OO O.OOE+OO O.OOE+OO 1.19E-03
*L **.. * \
Th'rant 8.76E-09 O.OOE+OO 2.38E-10 O.OOE+OO O.OOE+OO O.OOE+OO 6.92E-05 Zr-95 Liquid release (mrem/Ci released)
Lun~ GJ..;LLI *.
***:~ 1 ~;~Ali1{Jf. 7.95E-07 2.55E-07 1.73E-07 O.OOE+OO 4.00E-07 O.OOE+OO 8.09E-04 +.~;*.. *~:*.*f:~e f 7.68E-07 2.42E-07 1.67E-07 O.OOE+OO 3.56E-07 O.OOE+OO 5.59E-04 1*~~.;:: : :;;* 1.87E-06 4.11E-07 3.66E-07 O.OOE+OO 5.89E-07 O.OOE+OO 4.29E-04 ;t\, r/~ 1 ; ~
6
.. 1.90E-06 4.62E-07 3.28E-07 O.OOE+OO 4.98E-07 O.OOE+OO 2.30E-04 Zr-97 Bolle Liver l.OSE-08 2.18E-09 3.29E-09 6.75E-04 1.12E-08 2.21E-09 1.02E-09 O.OOE+OO 3.35E-09 5.99E-04 2.22E-08 3.21E-09 1.89E-09 O.OOE+OO 4.60E-09 O.OOE+OO 4.86E-04 1.92E-08 3.30E-09 1.51E-09 O.OOE+OO 3.32E-09 O.OOE+OO 2.10E-04 Nb-95 Liquid release (mrem/Ci released)
Liver**** Lung.** Gl-LLl . . 3.27E-04 1.82E-04 9.78E-05 O.OOE+OO l.SOE-04 O.OOE+OO l.IOE+OO 3.29E-04 1.83E-04 l.OIE-04 O.OOE+OO 1.77E-04 O.OOE+OO 7.81E-01 3.89E-04 1.51E-04 l.OSE-04 O.OOE+OO 1.42E-04 O.OOE+OO 2.80E-Ol 3.80E-07 1.56E-07 9.04E-08 O.OOE+OO 1.12E-07 O.OOE+OO 1.32E-04 Page 252 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXK LIQUID EFFLUENT DOSE CONVERSION FACTORS Kidne GI-LLI 9.46E-10 2.99E-06 8.56E-10 3.13E-10 O.OOE+OO l.OOE-09 O.OOE+OO 2.04E-05 7.91E-10 3.69E-10 O.OOE+OO 8.78E-10 O.OOE+OO 2.44E-04 1.65E-21 5.94E-22 O.OOE+OO 1.29E-21 O.OOE+OO 5.20E-16 1.85E-04 4.57E-05 O.OOE+OO 3.95E-04 O.OOE+OO 1.53E-04 1.93E-04 3.76E-05 O.OOE+OO 2.88E-04 O.OOE+OO 6.36E-05
; fc Kinlrt.t 7.14E-08 2.30E-09 2.78E-06 1.70E-09 4.75E-09 6.15E-08 O.OOE+OO 7.07E-08 2.63E-09 3.12E-06 2.07E-09 4.06E-09 6.73E-08 O.OOE+OO 5.90E-08 2.06E-09 2.31E-06 1.47E-1 0 1.89E-09 O.OOE+OO 1.58E-09 7.67E-11 4.26E-08 6.22E-06 9.14E-06 2.49E-06 O.OOE+OO 9.45E-07 2.24E-04 1.24E-05 1.39E-05 4.98E-06 O.OOE+OO 1.63E-04 1.23E-06 1.45E-04 1.02E-05 1.37E-05 4.28E-06 O.OOE+OO 1.16E-04 1.33E-06 5.93E-05 Page 253 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXK LIQUID EFFLUENT DOSE CONVERSION FACTORS Ru-105 Liquid release (mrem/Ci released)
>; *.**.****. ... B()ne
Liver T.Body Thyroid Kidney Lung.* GJ.,.LLI
*~. .... , ......... .Ad1lit . 4.20E-08 O.OOE+OO 1.66E-08 O.OOE+OO 5.43E-07 O.OOE+OO 2.57E-05 *.*. *; /*. .* .<t';i I:~:e*
j,; *~.;!** . i;rli;:~ ,J3
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4.53E-08 O.OOE+OO 1.76E-08 O.OOE+OO 5.72E-07 O.OOE+OO 3.66E-05 5.81E-08 O.OOE+OO 2.11E-08 O.OOE+OO 5.11E-07 O.OOE+OO 3.79E-05
* **** '* ;*J; ~~,f~*nf 7.12E-10 O.OOE+OO 2.40E-10 O.OOE+OO 5.23E-09 O.OOE+OO 2.83E-07 GI-LLI 3.12E-04 2.04E-06 O.OOE+OO 8.68E-06 O.OOE+OO 2.60E-04 5.28E-06 2.84E-06 2.42E-06 O.OOE+OO 1.13E-05 O.OOE+OO 1.76E-04 4.00E-06 2.62E-06 1.76E-06 O.OOE+OO 7.27E-06 O.OOE+OO 6.50E-05 Page 254 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXK LIQUID EFFLUENT DOSE CONVERSION FACTORS Sb-122 Liquid release (mrem/Ci released)
~.
Bone .. .Liver T.Bot:ly Thyroid Kidney Lun~ GI-LLI Adult 9.3 7E-06 5.15£-06 8.85E-05 1.09E-06 3.64£-06 1.41£-06 9.37£-04 4.77£-06 7.71£-05 9.55£-07 3.12£-06 1.29£-06 8.08£-04 1.13£-05 2.09£-04 2.46£-06 6.84£-06 3.22£-06 2.26£-03 2.93£-05 3.76£-04 8.78£-06 1.40£-05 l.OOE-05 3.97£-03 Sb-124 Liver GI-LLI 1.17£-06 1.76£-03 2.13£-06 5.75E-05 3.62E-07 O.OOE+OO 9.10£-05 1.03£-03 1.97E-04 2.89£-06 6.09£-05 5.22E-07 O.OOE+OO 1.23£-04 6.06£-04 1.08£-04 8.33£-07 2.26£-05 l.OOE-07 O.OOE+OO 6.02£-05 2.58£-04 1.15£-04 1.12£-06 2.38£-05 1.45E-07 O.OOE+OO 7.25£-05 1.54£-04 Page 255 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXK LIQUID EFFLUENT DOSE CONVERSION FACTORS Te-129m Liquid release (mrem/Ci released)
. : Bone Liver T.Bot!y Thyroid Kidney Lung GI-LLI >. , .... Adult 8.29E-03 3.09E-03 1.31E-03 2.85E-03 3.46E-02 O.OOE+OO 4.17E-02 < * * *.. *** ..* ~~en 8.93E-03 3.31E-03 1.41E-03 2.88E-03 3.74E-02 O.OOE+OO 3.35E-02 .... . ;t . :i"thild 1.19E-02 3.32E-03 1.85E-03 3.83E-03 3.49E-02 O.OOE+OO 1.45E-02 . Infant 9.02E-04 3.09E-04 1.39E-04 3.46E-04 2.26E-03 O.OOE+OO 5.39E-04 GI~LLI 1.29E-08 1.86E-08 6.93E-09 4.52E-09 1.33E-08 1.02E-07 6.69E-09 5.69E-09 1.71E-08 7.01E-08 O.OOE+OO 1.49E-06 3.22E-19 2.18E-19 7.82E-19 2.32E-18 O.OOE+OO 7.46E-17 GJ..,LLI 4.56E-02 l.OIE-03 4.84E-04 5.05E-03 O.OOE+OO 3.88E-02 1.30E-03 4.51E-04 4.80E-04 9.27E-04 4.36E-03 O.OOE+OO 1.83E-02 1.90E-05 1.57E-05 3.85E-05 1.31E-04 O.OOE+OO 3.19E-04 l.OIE-14 2.48E-14 1.41E-13 O.OOE+OO 2.64E-15 1.26E-14 1.23E-14 3.16E-14 1.25E-13 O.OOE+OO 2.17E-13 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.37E-05 1.35E-05 2.75E-03 5.19E-05 O.OOE+OO 2.59E-05 1.59E-05 3.22E-05 1.65E-05 3.53E-03 4.79E-05 O.OOE+OO l.SOE-05 3.82E-06 8.41E-06 3.38E-06 9.43E-04 9.24E-06 O.OOE+OO 1.80E-06 Page 256 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXK LIQUID EFFLUENT DOSE CONVERSION FACTORS 1-131 Liquid release (mrem/Ci released)
..* ** .. Bone Liver T.Body *. Thyroid Kidney Lung GI-LLI ,,Adult 1.79E-04 2.55E-04 1.46E-04 8.37E-02 4.38E-04 O.OOE+OO 6.74E-05 ......*.. .* Teen 1.85E-04 2.59E-04 1.39E-04 7.55E-02 4.45E-04 O.OOE+OO 5.12E-05 ... . . ..**.*..,*** ..Infant *~.* Child 3.54E-04 2.84E-04 3.56E-04 3.35E-04 2.02E-04 1.47E-04 1.18E-01 1.1 OE-01 5.84E-04 3.91E-04 O.OOE+OO O.OOE+OO 3.17E-05 1.19E-05 GJ.;.LLI 7.05E-08 1.82E-07 3.34E-07 1.54E-07 1.55E-05 5.11E-07 O.OOE+OO 3.93E-07 1.46E-11 5.19E-12 6.83E-10 1.63E-11 O.OOE+OO 1.18E-11 GJ.;.LLI 4.88E-05 5.62E-05 1.72E-05 7.85E-03 O.OOE+OO 4.25E-05 6.43E-05 2.43E-05 1.19E-02 1.07E-04 O.OOE+OO 2.59E-05 3.45E-05 1.01E-05 6.29E-03 4.06E-05 O.OOE+OO 5.85E-06 2.13E-10 9.88E-09 9.35E-10 O.OOE+OO 7.82E-12 2.77E-10 5.14E-10 2.37E-10 1.18E-08 7.86E-10 O.OOE+OO 3.41E-10 2.69E-22 5.51E-22 1.96E-22 1.29E-20 6.16E-22 O.OOE+OO 5.70E-22 O.OOE+OO 5.34E-01 2.48E-01 O.OOE+OO 1.70E-Ol 4.52E-Ol 9.53E-02 O.OOE+OO 1.40E-Ol 5.03E-02 2.44E-03 6.60E-03 6.66E-04 O.OOE+OO 1.70E-03 6.96E-04 1. 79E-05 Page 257 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXK LIQUID EFFLUENT DOSE CONVERSION FACTORS Cs-134m Liquid release (mrem/Ci released)
' Bone Liver T.Body Thyroid Kidney Lung GI-LLI Adult 4.28E-06 9.01E-06 4.60E-06 O.OOE+OO 4.89E-06 7.70E-07 3.18E-06 ,, <' Teen 4.50E-06 9.33E-06 4.79E-06 O.OOE+OO 5.19E-06 9.11E-07 6.20E-06 * ~*
C!hild 5.58E-06 8.26E-06 5.39E-06 O.OOE+OO 4.35E-06 7.20E-07 1.04E-05
'., *., ID.tallt 1.72E-ll 2.87E-11 1.45E-11 O.OOE+OO l.llE-11 2.54E-12 2.27E-11 Cs-136 8.92E-02 5.99E-02 O.OOE+OO 4.86E-02 7.66E-03 7.18E-03 7.40E-02 4.79E-02 O.OOE+OO 3.94E-02 5.88E-03 2.60E-03 1.14E-03 4.26E-04 O.OOE+OO 4.55E-04 9.31E-05 1. 73E-05 3.69E-Ol 5.44E-02 O.OOE+OO 1.20E-Ol 4.32E-02 2.31E-03 5.74E-03 4.07E-04 O.OOE+OO 1.54E-03 6.24E-04 1.80E-05 ;~Gtlif~ GI~LLI' 5.27E-11 5.20E-12 3.06E-16 7.46E-11 3.73E-11 O.OOE+OO 5.51E-11 6.41E-12 3.39E-14 6.85E-11 4.34E-11 O.OOE+OO 4.82E-11 5.18E-12 3.15E-11 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.94E-09 1.36E-12 5.65E-11 O.OOE+OO 1.29E-12 9.40E-13 1.73E-08 2.49E-09 1.33E-12 7.21E-11 O.OOE+OO 1.16E-12 7.81E-13 1.44E-07 3.69E-16 2.45E-19 1.07E-17 O.OOE+OO 1.47E-19 1.48E-19 2.34E-14 5.19E-04 6.36E-07 3.35E-05 O.OOE+OO 2.16E-07 4.28E-07 1.27E-03 l.llE-06 7.42E-05 O.OOE+OO 3.63E-07 6.64E-07 6.44E-04 1.44E-03 1.44E-06 7.43E-05 O.OOE+OO 3.42E-07 8.85E-07 3.54E-04 Page 258 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXK LIQUID EFFLUENT DOSE CONVERSION FACTORS Ba-141 Liquid release (mrem/Ci released)
..* .. Bone Liver T.Body Thyroid Kidney Lung GI-LLI
<. ..*.....*Adult 4.78E-19 3.61E-22 1.61E-20 O.OOE+OO 3.36E-22 2.05E-22 O.OOE+OO
. .**. rTeen 5.19E-19 3.87E-22 1.73E-20 O.OOE+OO 3.59E-22 2.65E-22 l.llE-24 '**; cllil..l 6.67E-19 3.73E-22 2.17E-20 O.OOE+OO 3.23E-22 2.19E-21 3.80E-19
J > Illfallt O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kid.ne GI-LLI O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kidne GJ...;LLI O.OOE+OO 4.17E-03 1.17E-07 1.54E-08 O.OOE+OO O.OOE+OO 3.32E-03 1.84E-07 6.42E-08 2.16E-08 O.OOE+OO O.OOE+OO O.OOE+OO 1.79E-03 3.42E-08 8.81E-09 O.OOE+OO O.OOE+OO O.OOE+OO 4.02E-04 GI~LLI 8.48E-08 1.21E-11 3.01E-12 O.OOE+OO O.OOE+OO O.OOE+OO 3.68E-07 l.lOE-11 3.43E-12 O.OOE+OO O.OOE+OO O.OOE+OO 2.17E-06 1.57E-18 3.77E-19 O.OOE+OO O.OOE+OO O.OOE+OO 2.67E-13 2.87E-07 4.26E-08 O.OOE+OO 1.26E-07 O.OOE+OO 3.58E-04 7.09E-07 4.32E-07 5.09E-08 O.OOE+OO 1.33E-07 O.OOE+OO 2.23E-04 1.21E-09 4.82E-09 O.OOE+OO 4.09E-04 1.49E-08 1.21E-09 O.OOE+OO 4.88E-09 O.OOE+OO 3.27E-04 2.18E-05 3.16E-09 O.OOE+OO 9.16E-09 O.OOE+OO 3.20E-04 3.37E-05 3.85E-09 O.OOE+OO 9.82E-09 O.OOE+OO 1.97E-04 Page 259 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXK LIQUID EFFLUENT DOSE CONVERSION FACTORS Ce-144 Liquid release (mrem/Ci released) Bone Liver T.Body Thyroid Kidney Lung GI-LLI
.. Adult 1.10E-05 4.58E-06 5.89E-07 O.OOE+OO 2.72E-06 O.OOE+OO 3.71E-03 Teen 1.1 OE-05 4.55E-06 5.91E-07 O.OOE+OO 2.72E-06 O.OOE+OO 2.77E-03 . . . ; Child 3.13E-05 9.81E-06 1.67E-06 O.OOE+OO 5.43E-06 O.OOE+OO 2.56E-03 . Illfant 2.79E-05 1.14E-05 1.56E-06 O.OOE+OO 4.61E-06 O.OOE+OO 1.60E-03 Pr-143 Liquid release (mrem/Ci released) '"*.* * .. <Bone ,Liver T.Body *.*.Thyroid Kidney Lung GI-LLI . Adult 5.70E-07 2.28E-07 2.82E-08 O.OOE+OO 1.32E-07 O.OOE+OO 2.49E-03 ****:.\\ *Teen 6.02E-07 2.40E-07 3.00E-08 O.OOE+OO 1.40E-07 O.OOE+OO 1.98E-03 .* **< Child> 1.07E-06 3.22E-07 5.32E-08 O.OOE+OO 1.74E-07 O.OOE+OO 1.16E-03 .*. . :;*s~/:****y:.:_~::..:..'.)1 6.90E-07 2.58E-07 3.42E-08 O.OOE+OO 9.59E-08 O.OOE+OO 3.64E-04 GI,;;LLI O.OOE+OO 1.70E-22 2.11E-23 O.OOE+OO 9.75E-23 4.58E-25 1.66E-22 2.70E-23 O.OOE+OO 8.79E-23 O.OOE+OO 3.58E-19 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO GPLCI 2.60E-07 2.14E-03 4.27E-07 4.64E-07 2.78E-08 O.OOE+OO 2.72E-07 O.OOE+OO 1.67E-03 7.50E-07 6.08E-07 4.71E-08 O.OOE+OO 3.33E-07 O.OOE+OO 9.63E-04 4.58E-07 4.71E-07 2.88E-08 O.OOE+OO 1.81E-07 O.OOE+OO 2.98E-04 1.18E-05 2.85E-06 2.51E-06 O.OOE+OO 1.32E-05 O.OOE+OO 1.05E-03 1.79E-05 3.26E-06 3.87E-06 O.OOE+OO 1.37E-05 O.OOE+OO 5.35E-04 6.33E-06 1.68E-06 1.42E-06 O.OOE+OO 4.72E-06 O.OOE+OO 1.49E-04 1.36E-04 4.78E-05 O.OOE+OO O.OOE+OO O.OOE+OO 3.69E-02 1.26E-04 5.66E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.77E-02 1.47E-06 5.07E-07 O.OOE+OO O.OOE+OO O.OOE+OO 8.62E-05 Page 260 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXK LIQUID EFFLUENT DOSE CONVERSION FACTORS U-235 Liquid release (mrem/Ci released) Bone l..iver T.Body Thyroid Kidney Lung GI-LLI
*.**.* Adult 1.67E-02 O.OOE+OO l.OIE-03 O.OOE+OO 3.89E-03 O.OOE+OO 1.62E-03 ,. ******Teen 1.66E-02 O.OOE+OO l.OIE-03 O.OOE+OO 3.88E-03 O.OOE+OO 1.20E-03 *** ..*~ .. . Child 4.97E-02 O.OOE+OO 3.01E-03 O.OOE+OO 8.15E-03 O.OOE+OO 1.17E-03 . . . Infant 4.39E-02 O.OOE+OO 3.35E-03 O.OOE+OO 9.34E-03 O.OOE+OO 7.62E-04 U-238 Liquid release (mrem/Ci released)
Bqlle .*. Liver T.Body Thyroid *. Kidney Lung GI-.LLI 1.60E-02 O.OOE+OO 9.44E-04 O.OOE+OO 3.64E-03 O.OOE+OO 1.14E-03 1.58E-02 O.OOE+OO 9.43E-04 O.OOE+OO 3.63E-03 O.OOE+OO 8.47E-04 4.75E-02 O.OOE+OO 2.82E-03 O.OOE+OO 7.61E-03 O.OOE+OO 8.22E-04 4.20E-02 O.OOE+OO 3.13E-03 O.OOE+OO 8.72E-03 O.OOE+OO 5.37E-04 3.27E-09 O.OOE+OO 1.03E-08 O.OOE+OO 5.26E-04 4.93E-09 3.46E-09 O.OOE+OO 1.43E-08 O.OOE+OO 3.65E-04 5.18E-09 2.93E-09 O.OOE+OO 1.03E-08 O.OOE+OO 1.50E-04 1.59E-02 2.77E-03 O.OOE+OO 2.08E-02 O.OOE+OO 3.80E-03 1.86E-02 2.96E-03 O.OOE+OO 1.81E-02 O.OOE+OO 2.22E-03 1.44E-02 6.75E-03 1.02E-03 O.OOE+OO 6.16E-03 O.OOE+OO 7.24E-04 Page 261 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXL GASEOUS EFFLUENT DOSE CONVERSION FACTORS The tables below identify the expected dose to each of the four age ranges (adult, teen, child and infant) as a result of activity released via gaseous effluents. These dose conversion factors are the summation of the expected exposures based on Reg. Guide 1.109 and NUREG-0133 assumptions. The pathways considered are inhalation, ground plane, milk, meat, leafy vegetables and produce. The assumed values for x/Q and D/Q are those referenced in Table 10-2. The total body, skin and air dose factors for noble gas releases are contained at the end of the tables below. H-3 Gaseous release (mrem/Ci released) Kidne GI-LLI 7.89£-05 7.89£-05 8.69£-05 8.69£-05 8.69£-05 8.69£-05 1.23£-04 1.23£-04 1.23£-04 1.23£-04 1.23£-04 1.23£-04 5.32£-05 5.32£-05 5.32£-05 5.32£-05 5.32£-05 5.32£-05 C-14 Gaseous release (mrem/Ci released)
~,;z~, ,~,J~<s" '";I'<Lkriri~." ~;. :t*:~:r::l'~:t~: !; *.... iT ih,*~. z
Tlijroid Kidney .* Lun~ .GJ:.:LLI ,
.::'.';,*~, ~Aaifif 3.65E-o2 7.3oE-o3 7.3oE-o3 7.3oE-o3 7.3oE-o3 7.3oE-o3 7.3oE-o3 ;< / ' , ..... -';~' 5.51£-02 1.10£-02 1.10£-02 1.10£-02 1.10£-02 1.10£-02 1.10£-02 I :" ;i-. H<<l 1.30£-01 2.59£-02 2.59£-02 2.59£-02 2.59£-02 2.59£-02 2.59£-02 ' .*~"'.c *w~~t** 7.37E-o2 I.57E-o2 L57E-o2 L57E-02 L57E-02 L57E-o2 L57E-o2 1.47£-04 1.60£-04 1.47E-04 1.47E-04 1.47E-04 1.63E-04 1.47£-04 1.47£-04 1.47£-04 1.75£-04
2. 72E-04 1.4 7E-04 1.58E-04 1.47E-04 1.47E-04 1.47E-04 1.67E-04 Kidile 5.00E+OO 5.00E+OO 5.00£+00 5.68E+OO 5.68£+00 5.68E+OO 5.68£+00 5.68E+OO 5.68£+00 7.66E+OO 7.66E+OO 7.66E+OO 7.66E+OO 7.66£+00 7.66E+OO 7.66£+00 8.45E+OO 8.45E+OO 8.45E+OO 8.45£+00 8.45E+OO 8.45E+OO Page 262 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXL GASEOUS EFFLUENT DOSE CONVERSION FACTORS Na-24 Gaseous release (mrem/Ci released)
*. Bone Liver T.Body Thyroid Kidney Lung GI-LLI Adult 2.62E-03 2.62E-03 2.62E-03 2.62E-03 2.62E-03 2.62E-03 2.62E-03 . . *** Teen 2.78E-03 2.78E-03 2.78E-03 2.78E-03 2.78E-03 2.78E-03 2.78E-03 Child .. 3.07E-03 3.07E-03 3.07E-03 3.07E-03 3.07E-03 3.07E-03 3.07E-03 bifari.t 3.18E-03 3.18E-03 3.18E-03 3.18E-03 3.18E-03 3.18E-03 3.18E-03 P-32 Gaseous release (mrem/Ci released) >; ; ... Bone . . Liver ;*
T.Body Thyroid Kidney Lun~ . . GI.:.LLI
.. *' Adult 3.18E-O 1 3.28E-Ol 3.14E-Ol 3.08E-Ol 3.26E-Ol 3.08E-Ol 8.98E-Ol t ..**** < 'l'eell 3.21E-Ol 3.34E-Ol 3.16E-Ol 3.08E-Ol 3.33E-Ol 3.08E-Ol 8.31E-Ol cliudt 3.25E-Ol 3.31E-Ol 3.17E-Ol 3.08E-01 3.28E-Ol 3.08E-Ol 6.39E-Ol
<:._.. ,:_.:.P.'j
;** 3.20E-Ol 3.25E-Ol 3.13E-Ol 3.08E-Ol 3.19E-Ol 3.08E-Ol 3.09E-Ol Sc-46 Gaseous release (mrem/Ci released)
Kidne GI-LLI O.OOE+OO 1.50E-Ol 1.27E-Ol 7.97E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.71E-Ol 2.24E-Ol 1.85E-Ol O.OOE+OO O.OOE+OO O.OOE+OO 1.32E-Ol 7.66E+OO 4.51E-Ol 2.97E-Ol O.OOE+OO O.OOE+OO O.OOE+OO 1.03E-Ol 8.72E-04 8.72E-04 8.82E-04 8.76E-04 1.37E-03 3.37E-03 8.72E-04 9.03E-04 8.89E-04 8. 77E-04 1.28E-03 2.37E-03
8. 72E-04 8.83E-04 8. 79E-04 8. 73E-04 1.17E-03 1.14E-03 3.46E-Ol 2.59E-Ol 2.85E-Ol 3.04E-Ol 4.37E-Ol 3.86E-Ol 2.93E-Ol 2.59E-Ol 2.95E-Ol 2.95E-Ol 3.65E-Ol 2.59E-Ol 2.65E-Ol 2.60E-Ol 2.59E-Ol 2.60E-Ol 2.82E-Ol 2.61E-Ol 1.69E-04 1.69E-04 1.69E-04 5.14E-04 1.47E-03 1.69E-04 1.69E-04 1.69E-04 1.69E-04 1.69E-04 4.67E-04 2.96E-03 1.69E-04 1.69E-04 1.69E-04 1.69E-04 1.69E-04 4.53E-04 1.79E-03 Page 263 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXL GASEOUS EFFLUENT DOSE CONVERSION FACTORS Fe-55 Gaseous release (mrem/Ci released)
*... . Bone Liver T.Body Thyroid Kidney Lung GI-LLI Adult 8.22E-02 5.68E-02 1.32E-02 O.OOE+OO O.OOE+OO 3.31E-02 3.25E-02 .. ... Teen 9.82E-02 6.96E-02 1.62E-02 O.OOE+OO O.OOE+OO 4.66E-02 3.00E-02 Ghild 2.23E-01 1.18E-O 1 3.67E-02 O.OOE+OO O.OOE+OO 6.91E-02 2.19E-02 Infant 1.92E-02 1.24E-02 3.32E-03 O.OOE+OO O.OOE+OO 7.91E-03 1.57E-03 Fe-59 Gaseous release (mrem/Ci released) **: ;. > ** ...... LiVer T.Body Thyroid Kidu,ey.******* Lung . GI-LLI 9.48E-02 1.54E-01 9.05E-02 5.09E-02 5.09E-02 1.03E-01 3.97E-01 1.02E-01 1.71E-01 9.74E-02 5.09E-02 5.09E-02 1.23E-01 3.37E-01 1.59E-01 2.25E-01 1.38E-01 5.09E-02 5.09E-02 1.30E-01 2.33E-01 6.69E-02 7.88E-02 6.19E-02 5.09E-02 5.09£-02 8.20E-02 6.46E-02 Co-57 1.36E-01 6.36E-02 6.63E-02 5.95E-02 5.95E-02 7.28E-02 1.36E-01 6.61E-02 7.29E-02 5.95E-02 5.95E-02 7.10£-02 1.14E-01 6.06E-02 6.13E-02 5.95E-02 5.95E-02 6.81E-02 6.34E-02 7.86E-02 8.81E-02 7.10E-02 7.10E-02 9.20E-02 2.28E-01 8.09E-02 9.38E-02 7.10E-02 7.10E-02 1.01E-01 2.09E-01 8.52E-02 1.15E-01 7.10E-02 7.10E-02 9.61E-02 1.55E-01 7.31E-02 7.63E-02 7.10E-02 7.10E-02 8.86E-02 7.65E-02 4.09E+OO 4.03E+OO 4.03E+OO 4.80E+OO 4.12E+OO 4.29E+OO 4.03E+OO 4.03E+OO 4.19E+OO 4.51E+OO 4.04E+OO 4.06E+OO 4.03E+OO 4.03E+OO 4.13E+OO 4.06E+OO *roaile O.OOE+OO 4.04E-03 9.12E-02 7.74E+OO 5.47E-01 2.62E-01 O.OOE+OO O.OOE+OO 6.96E-03 8.72E-02 1.78E+01 9.53E-01 6.06E-01 O.OOE+OO O.OOE+OO 6.23E-03 6.43E-02 3.41E-01 1.92E-01 O.OOE+OO O.OOE+OO 4.73E-03 1.70E-02 Page 264 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXL GASEOUS EFFLUENT DOSE CONVERSION FACTORS Ni-65 Gaseous release (mrem/Ci released)
! * <2* > ; Bone Liver T.Body_ Thyroid Kidney Lung GI':"LLI ; Adult 5.56E-05 5.55E-05 5.55E-05 5.55E-05 5.55E-05 1.82E-04 3.35E-04 .* ** ***.><"T~en 5.56E-05 5.55E-05 5.55E-05 5.55E-05 5.55E-05 2.68E-04 8.88E-04 .* . *........ L.:< 01::1~ 5.56E-05 5.55E-05 5.55E-05 5.55E-05 5.55E-05 2.41E-04 1.96E-03 'IDfant 5.56E-05 5.55E-05 5.55E-05 5.55E-05 5.55E-05 2.40E-04 1.19E-03 Cu-64 Gaseous release (mrem/Ci released) .~ ***~ .;;~t.r~; .* .* *; .* Bone Diver**** T.Body Thyroid .... Kidney Luni * *
GI.:.LLI I*** ;:~ "*~,;;:~~;AdUJf* 1.14E-04 1.16E-04 1.15E-04 1.14E-04 1.21E-04 2.67E-04 1.47E-03 1.14E-04 1.17E-04 1.15E-04 1.14E-04 1.23E-04 3.66E-04 1.78E-03
.., . ,., it 1.14E-04 1.19E-04 1.17E-04 1.14E-04 1.27E-04 3.31E-04 1.21E-03 1.14E-04 1.22E-04 1.18E-04 1.14E-04 1.28E-04 3.24E-04 6.32E-04 Zn-65 Gaseous release (mrem/Ci released)
GI~LLI 7.75E-Ol 1.40E-Ol 7.72E-Ol 2.33E+OO 1.50E+OO 1.40E-Ol 1.52E+OO 5.25E-Ol 2.80E+OO 1.37E+OO 1.40E-Ol 1.43E+OO 2.39E+O 4.81E-04 4.53E-04 4.50E-04 8.82E-04 5.41E-03 4.96E-04 4.54E-04 4.50E-04 4. 78E-04 1.16E-03 6.83E-03 5.27E-04 4.59E-04 4.50E-04 4.95E-04 1.07E-03 5.21E-03 6.12E-04 4.65E-04 4.50E-04 5.16E-04 1.06E-03 3.62E-03 1.1 OE-09 2.09E-09 1.46E-1 0 O.OOE+OO 3.59E-05 1.52E-09 2.19E-09 2.02E-1 0 O.OOE+OO 1.33E-09 3.22E-05 2.31E-04 1.22E-09 2.19E-09 1.63E-10 O.OOE+OO 9.11E-10 3.33E-05 3.00E-04 9.65E-04 1.13E-03 2.29E-03 1.16E-03 1.03E-03 1.28E-03 3.29E-03 1.02E-03 1.31E-03 3.1 OE-03 2.00E-02 1.35E-03 2.11E-03 3.24E-03 1.35E-03 2.17E-03 3.03E-03 1.43E-02 Page 265 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXL GASEOUS EFFLUENT DOSE CONVERSION FACTORS Br-82 Gaseous release (mrem/Ci released) Bone Liver T.Body Thyroid Kidney Lun~ GI-LLI Adult 7.15E-03 7.15E-03 9.28E-03 7.15E-03 7.15E-03 7.15E-03 9.48E-03
>": Teen 7.15E-03 7.15E-03 1.05E-02 7.15E-03 7.15E-03 7.15E-03 7.15E-03
I*>< .: cliild 7.15E-03 7.15E-03 1.35E-02 7.15E-03 7.15E-03 7.15E-03 7.15E-03
",*" " ". Infant 7.15E-03 7.15E-03 1.66E-02 7.15E-03 7.15E-03 7.15E-03 7.15E-03 Br-83 Gaseous release (mrem/Ci released) "*" *Bolle Kidney ...". ,. Lun~ GI~LLI "'. > ,, ;; "~?* ** Liver,." T!Body I,"""Thyroid .;;* \ ;" A.all1i 9.16E-07 9.16E-07 6.37E-06 9.16E-07 9.16E-07 9.16E-07 6.17E-06 i .I.~}:;.**(
T~~n~ 9.16E-07 9.16E-07 8.71E-06 9.16E-07 9.16E-07 9.16E-07 9.16E-07
*; J . >(gJiiid 9.16E-07 9.16E-07 1.17E-05 9.16E-07 9.16E-07 9.16E-07 9.16E-07 .,""*;. ".~;**lifr:ilt 9.16E-07 9.16E-07 9.55E-06 9.16E-07 9.16E-07 9.16E-07 9.16E-07 Br-84 Gaseous release (mrem/Ci released)
Kidlle GI-LLI 3.79E-05 3.79E-05 4.77E-05 3.79E-05 3.79E-05 3.79E-05 3.79E-05 3.79E-05 5.03E-05 3.79E-05 3.79E-05 3.79E-05 3.79E-05 3.79E-05 4.70E-05 3.79E-05 3.79E-05 3.79E-05 3.79E-05 O.OOE+OO 4.15E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.74E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.63E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.68E-03 3.04E-01 1.44E-Ol 1.68E-03 1.68E-03 1.68E-03 4.62E-02 1.68E-03 5.41E-Ol 3.33E-Ol 1.68E-03 1.68E-03 1.68E-03 3.62E-02 1.68E-03 1.08E+OO 5.32E-Ol 1.68E-03 1.68E-03 1.68E-03 2.91E-02 6.15E-06 1.86E-05 1.23E-05 6.15E-06 6.15E-06 6.15E-06 1.89E-05 1.45E-05 6.15E-06 6.15E-06 6.15E-06 6.55E-06 6.15E-06 1.88E-05 1.27E-05 6.15E-06 6.15E-06 6.15E-06 1.38E-05 Page 266 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXL GASEOUS EFFLUENT DOSE CONVERSION FACTORS Rb-89 Gaseous release (mrem/Ci released) Bone Liver T.Body Thyroid ,.. Kidney Lung GI-LLI
.. .......... Adult 2.29E-05 2.88E-05 2.68E-05 2.29E-05 2.29E-05 2.29E-05 2.29E-05 ..... .... Teeil 2.29E-05 3.09E-05 2.82E-05 2.29E-05 2.29E-05 2.29E-05 2.29E-05 .. *..*.... *:rt.i1~f* 2.29E-05 3.08E-05 2.95E-05 2.29E-05 2.29E-05 2.29E-05 2.30E-05 .. *.... *****Infant 2.29E-05 3.02E-05 2.76E-05 2.29E-05 2.29E-05 2.29E-05 2.45E-05 Kidne***
4.05E-06 3.23E-Ol 3.00E+OO 4.05E-06 4.05E-06 4.05E-06 5.48E-02 3.65E-Ol 4.05E-06 2.04E-Ol 4.05E-06 4.05E-06 4.89E-02 2.79E-Ol 4.05E-06 2.72E-02 4.05E-06 4.05E-06 4.60E-02 2.07E-02 4.13E+OO 1.73E-03 1.73E-03 3.75E-Ol 6.39E+OO 1.73E-03 8.41E+OO 1.73E-03 1.73E-03 3.36E-Ol 3.74E+OO 1.73E-03 5.92E-Ol 1.73E-03 1.73E-03 2.57E-Ol 2.39E-Ol 4.04E-04 4.02E-04 4.02E-04 1. 78E-03 6.53E-03 4.02E-04 4.06E-04 4.02E-04 4.02E-04 1.61E-03 4.57E-03 4.02E-04 4.03E-04 4.02E-04 4.02E-04 1.60E-03 2.08E-03 Page 267 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXL GASEOUS EFFLUENT DOSE CONVERSION FACTORS Y-91m Gaseous release (mrem/Ci released)
~~ ......** *. ~.. >
Bolle Liver T.Bod_y Thyroid Kidlley _:c_ Lun~ GI-LLI 1.88E-05 1.88E-05 1.88E-05 1.88E-05 1.88E-05 6.23E-05 1.88E-05 1.88E-05 1.88E-05 1.88E-05 1.88E-05 1.88E-05 9.13E-05 1.94E-05 1.88E-05 1.88E-05 1.88E-05 1.88E-05 1.88E-05 8.25E-05 5.77E-05 1.88E-05 1.88E-05 1.88E-05 1.88E-05 1.88E-05 8.19E-05 7.21E-05 Y-91 GI.::LLI 5.72E-01 1.67E-02 2.01E-04 6.42E-04 2.01E-04 2.01E-04 6.67E-02 6.27E-Ol 2.01E-04 8.48E-04 2.01E-04 2.01E-04 5.97E-02 4.77E-Ol 1.35E-02 2.01E-04 5.56E-04 2.01E-04 2.01E-04 5.57E-02 2.21E-03
.:Kicbie GI;,LLI 3.38E-05 1.70E-03 3.38E-05 3.38E-05 3.38E-05 3.38E-05 6.41E-04 3.77E-03 3.38E-05 3.38E-05 3.38E-05 3.38E-05 5.76E-04 5.46E-03 3.38E-05 3.38E-05 3.38E-05 3.38E-05 5.89E-04 2.90E-03 5.54E-04 5.51E-04 5.51E-04 5.51E-04 5.52E-04 3.49E-03 1.79E-02 5.55E-04 5.51E-04 5.51E-04 5.51E-04 5.52E-04 3.12E-03 l.OSE-02 5.54E-04 5.51E-04 5.51E-04 5.51E-04 5.51E-04 3.05E-03 3.73E-03 Page 268 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXL GASEOUS EFFLUENT DOSE CONVERSION FACTORS Nb-95 Gaseous release (mrem/Ci released) Bolle Liver T.Body Thyroid Kidney Lung Gl-:-LLI Adult 2.60E-02 2.58E-02 2.57E-02 2.55E-02 2.59E-02 3.70E-02 6.10E-Ol
". * *",,?r¢en 2.61E-02 2.59E-02 2.57E-02 2.55E-02 2.59E-02 4.25E-02 3.94E-Ol . :, :.*.~1;.,. cibiltl 2.63E-02 2.59E-02 2.58E-02 2.55E-02 2.59E-02 3.94E-02 2.32E-Ol ;f" /;,: ;*~**,*i;,"* > *cnnanr 2.59E-02 2.57E-02 2.56E-02 2.55E-02 2.56E-02 3.64E-02 3.85E-02 GI-LLI 6.85E-05 6.31E-05 6.31E-05 6.31E-05 6.31E-05 1.52E-04 1.12E-04 6.31E-05 6.31E-05 6.31E-05 6.31E-05 1.40E-04 6.94E-04 6.31E-05 6.31E-05 6.31E-05 6.31E-05 1.38E-04 6.72E-04 GI'""LLI, 1.17E-02 7.47E-04 1.35E-03 7.47E-04 7.98E-02 4.23E-03 1.25E-02 7.47E-04 6.01E-03 2.05E-03 7.4 7E-04 1.20E-02 3.82E-03 7.97E-03 7.47E-04 1.05E-02 2.65E-03 7.47E-04 1.53E-02 3.80E-03 5.06E-03 1.30E-04 3.44E-05 3.44E-05 3.44E-05 3.44E-05 3.44E-05 6.05E-05 1.75E-04 3.44E-05 3.44E-05 3.44E-05 3.44E-05 3.44E-05 5.59E-05 1.45E-04 3.44E-05 3.44E-05 3.44E-05 3.44E-05 3.44E-05 5.28E-05 8.12E-05 Page 269 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXL GASEOUS EFFLUENT DOSE CONVERSION FACTORS Ru-103 Gaseous release (mrem/Ci released)
c "' : cC ">> : ""cc:": Bone ', Liver T.Body Thyroid Kidney Lung "c" GI-LLI c"
/,~A:ilidt 2.80E-02 2.02E-02 2.36E-02 2.02E-02 S.OOE-02 3.17E-02 9.30E-Ol '.>>I" *,":rfeeit 2.71E-02 2.02E-02 2.32E-02 2.02E-02 4.46E-02 3.80E-02 5.97E-Ol I ; ..:~.~*~2?i,:Gblid""* 3.33E-02 2.02E-02 2.52E-02 2.02E-02 5.31E-02 3.52E-02 3.57E-Ol "'.*j'**.'/1'~~~~4- 2.03E-02 2.02E-02 2.02E-02 2.02E-02 2.03E-02 3.27E-02 2.06E-02 Ru-105 Gaseous release (mrem/Ci released) 1.22E-03 1.19E-04 1.19E-04 1.19E-04 1.19E-04 5.31E-04 2.18E-03 1.19E-04 1.19E-04 1.19E-04 1.19E-04 1.19E-04 4.80E-04 2.39E-03 1.19E-04 1.19E-04 1.19E-04 1.19E-04 1.19E-04 4.74E-04 1.22E-03 Gaseous release (mrem/Ci released)
Kidne GI-LLI 7.99E-02 1.32E-Ol 8.75E-Ol 2.66E+Ol 7.99E-02 1.27E-Ol 7.99E-02 8.04E-Ol 4.44E-01 1.80E+Ol 8.17E-Ol 7.99E-02 1.72E-Ol 7.99E-02 1.07E+OO 4.04E-01 1.15E+Ol 8.19E-02 7.99E-02 8.02E-02 7.99E-02 8.24E-02 3.42E-Ol 8.38E-02 3.52E-04 3.97E-04 7.86E-03 3.46E-04 2.85E-04 2.75E-04 2.15E-04 4.95E-04 8.71E-04 5.67E-03 4.04E-04 3.39E-04 2.98E-04 2.15E-04 5.59E-04 8.75E-04 3.72E-03 Page 270 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXL GASEOUS EFFLUENT DOSE CONVERSION FACTORS Sn-117m Gaseous release (mrem/Ci released) Bone.*. Liver -' 'f.Body .*.
Thyroid Kidney Lung . GI..,LLI*
1.09E-02 4.16E-03 1.46E-02 3.97E-03 4.26E-03 1.67E-02 l.OSE-01 9.38E-03 4.16E-03 1.44E-02 3.97E-03 4.23E-03 2.01E-02 9.94E-02 1.54E-02 4.45E-03 2.18E-02 4.01E-03 4.44E-03 1.40E-02 1.97E-01 1.35E-02 4.31E-03 1.70E-02 4.03E-03 4.25E-03 1.16E-02 1.44E-01 GI-LLI 2.60E-02 2.42E-03 5.02E-03 2.30E-03 2.36E-03 6.79E-03 2.51E-02 2.51E-03 6.83E-03 2.32E-03 2.41E-03 5.42E-03 4.75E-02 2.60E-03 7.00E-03 2.37E-03 2.43E-03 4.95E-03 4.91E-02
~: *~Kia.Vt. **
1.96E-01 2.70E-01 8.48E-01 2.31E-01 2.10E-01 1.96E-01 1.96E-01 3.13E-01 8.75E-01 2.73E-Ol 1.97E-01 2.23E-01 1.97E-01 1.96E-01 3.12E-01 6.72E-01 2.14E-01 1.97E-01 2.02E-01 1.96E-Ol 1.96E-01 2.77E-01 2.50E-01 7.98E-01 7.98E-01 8.61E-01 1.14E+OO 8.47E-01 7.99E-01 8.10E-01 7.98E-Ol 7.98E-01 9.01E-01 1.16E+OO 9.09E-01 7.99E-01 8.21E-01 7.98E-01 7.98E-01 9.11E-01 1.06E+OO 8.21E-Ol 7.98E-01 8.03E-Ol 7.98E-01 7.98E-01 8.32E-01 8.27E-01 Page 271 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXL GASEOUS EFFLUENT DOSE CONVERSION FACTORS Te-127 Gaseous release (mrem/Ci released)
. ******* Bone Liver T.Body Thyroid
Kidney Lung GI-LLI
> :Adult 1.75E-06 9.90E-07 8.18E-07 1.44E-06 5.39E-06 1.48E-04 1.39E-03 < .*~> Teen 1.73E-06 9.78E-07 S.llE-07 1.36E-06 5.26E-06 2.54E-04 1.92E-03 I :;./,**i*eh.illd> 2.73E-06 1.15E-06 1.02E-06 2.06E-06 6.70E-06 2.28E-04 1.36E-03 ........ J* .Th'r~TI:t 9.22E-07 6.86E-07 6.38E-07 8.54E-07 1.43E-06 2.35E-04 5.59E-04 Te-129m Gaseous release (mrem/Ci released)
Liver* T.Bod Kidne GI..:LLI 5.32E-02 2.47E-02 5.57E-Ol 6.78E-Ol 1.52E-Ol 5.87E-02 2.71E-02 5.15E-02 6.23E-Ol 5.67E-Ol 9.25E-02 5.30E-02 1.06E-Ol 9.37E-Ol 4.36E-02 3.95E-Ol 1.62E-02 9.31E-03 1.77E-02 9.46E-02 4.18E-02 2.68E-02
.* ffi.drt~'
4.91E-06 8.46E-06 4.91E-06 4.91E-06 4.91E-06 4.92E-06 7.96E-05 4.15E-05 4.91E-06 4.91E-06 4.91E-06 4.91E-06 7.14E-05 5.83E-04 4.91E-06 4.91E-06 4.91E-06 4.91E-06 7.28E-05 6.01E-04 Page 272 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXL GASEOUS EFFLUENT DOSE CONVERSION FACTORS 1-130 Gaseous release (mrem/Ci released)
.. . Bone Liver T.Body Thyroid Kidney LUB2 GJ..,LLI I* **. Adult 1.18E-03 1.47E-03 1.21E-03 3.84E-02 1.72E-03 1.03E-03 1.32E-03 < ... :reen 1.22E-03 1.58E-03 1.25E-03 4.65E-02 1.88E-03 1.03E-03 1.35E-03 ! ~* i ~. ;. Z>~; ChiJ d*** 1.31E-03 1.60E-03 1.32E-03 6.46E-02 1.88E-03 1.03E-03 1.24E-03 ** ** * *..... . *IItralit: * :>.. 1.26E-03 1.53E-03 1.23E-03 5.77E-02 1.58E-03 1.03E-03 1.12E-03 1-131 Gaseous release (mrem/Ci released) 3.19E-02 1.86E-02 8.39E+OO 5.26E-02 3.21E-03 8.82E-03 4.82E-02 2.88E-02 1.49E+Ol 7.71E-02 3.21E-03 7.18E-03 7.78E-02 3.60E-02 2.45E+Ol 9.04E-02 3.21E-03 5.86E-03 Gaseous release (mrem/Ci released) *~:~1:11*** 'oi(l Kidne 2.82E-03 3.49E-04 2.31E-04 2.40E-04 3.30E-04 2.67E-04 3.66E-03 3.88E-04 2.31E-04 2.60E-04 2.79E-04 3.23E-04 2.74E-04 4.62E-03 3.73E-04 2.31E-04 3.04E-04 2.69E-04 3.11E-04 2.60E-04 4.07E-03 3.21E-04 2.31E-04 2.74E-04 4.59E-04 l.llE-03 1.08E-03 1.51E-03 2.30E-03 4.59E-04 1.14E-03 1.57E-03 1.82E-03 9.75E-04 2.56E-Ol 2.73E-03 4.59E-04 9.47E-04 1.61E-03 2.13E-03 9.48E-04 3.06E-Ol 2.42E-03 4.59E-04 7.17E-04 Page 273 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXL GASEOUS EFFLUENT DOSE CONVERSION FACTORS Cs-134 Gaseous release (mrem/Ci released)
. . > Bone Liver T.Body 'I'hyroid . Kidney Lung GI-LLI .* Adult 3.02E+OO 5.41E+OO 4.66E+OO 1.29E+OO 2.62E+OO 1.73E+OO 1.36E+OO ....**;:. Teen 4.02E+OO 7.73E+OO 4.28E+OO 1.29E+OO 3.33E+OO 2.07E+OO 1.37E+OO I/. ,,*Child 7.49E+OO 1.15E+Ol 3.43E+OO 1.29E+OO 4.44E+OO 2.42E+OO 1.34E+OO ' .,( Infant 6.35E+OO 1.07E+Ol 2.24E+OO 1.29E+OO 3.72E+OO 2.28E+OO 1.31E+OO Cs-134m Gaseous release (mrem/Ci released)
I~*;E; ..:,;3 .*; 2*i ** Bone Liver .....* . *T.Body ** H'hyr6id. * 'Kidney I******* Lung* . GI..LLJ***.
.*~;
(~
;.{L* ~**.
8.85E-06 1.18E-05 9.08E-06 5.96E-06 9.28E-06 6.50E-06 7.40E-06 _B*~~:*;. *.;; ... 9.95E-06 1.39E-05 1.02E-05 5.96E-06 1.06E-05 6.79E-06 9.63E-06
';F; . . *. h ~* .. '~ . ***** ** ::.:5; '.:c;~';~\** ;*~.w:* 4:*
1.13E-05 1.34E-05 l.llE-05 5.96E-06 l.OIE-05 6.66E-06 1.26E-05 1.02E-05 1.26E-05 9.49E-06 5.96E-06 8.66E-06 6.60E-06 9.64E-06 GI-LLI 3.77E-02 5.85E-02 1.47E-Ol 2.82E-02 9.31E-02 3.85E-02 3.77E-02 9.21E-02 2.04E-Ol 1.42E-Ol 2.82E-02 1.22E-01 4.22E-02 3.44E-02 1.20E-01 2.97E-Ol 1.29E-Ol 2.82E-02 1.36E-Ol 5.02E-02 3.23E-02 2.31E+OO 3.84E+OO 1.93E+OO 3.79E+OO 2.65E+OO 2.01E+OO 1.17E+Ol 1.13E+Ol 3.31E+OO 1.93E+OO 4.97E+OO 3.02E+OO 1.99E+OO 9.68E+OO l.lOE+Ol 2.57E+OO 1.93E+OO 4.36E+OO 2.92E+OO 1.96E+OO Page 274 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXL GASEOUS EFFLUENT DOSE CONVERSION FACTORS Ba-140 Gaseous release (mrem/Ci released) Bone Liver T.Body Thyroid Kidney Lung GJ...:LLI Adult 3.11 E-02 3.86E-03 5.62E-03 3.83E-03 3.84E-03 3.27E-02 6.32E-02 3.87E-03 5.77E-03 3.83E-03 3.84E-03 4.99E-02 5.36E-02 3.88E-03 7.35E-03 3.83E-03 3.85E-03 4.34E-02 3.59E-02 3.84E-03 4.46E-03 3.83E-03 3.83E-03 4.00E-02 7.40E-03 Ba-141 Gaseous release (mrem/Ci released) Kidne GJ..;LLI 7.82E-06 7.82E-06 7.82E-06 7.82E-06 7.82E-06 7.82E-06 7.82E-06 7.82E-06 7.82E-06 7.82E-06 7.82E-06 7.82E-06 7.82E-06 7.40E-05 1.41E-05 7.82E-06 7.82E-06 7.82E-06 7.82E-06 7.82E-06 7.51E-05 1.15E-04
,.Kia~~
8.40E-06 8.40E-06 8.40E-06 8.40E-06 8.40E-06 5.17E-05 8.40E-06 8.40E-06 8.40E-06 8.40E-06 8.40E-06 4.56E-05 8.46E-06 8.40E-06 8.40E-06 8.40E-06 8.40E-06 8.40E-06 4.36E-05 2.41E-05 GI-LL:(. 2.77E-02 3.61E-03 3.61E-03 3.60E-03 3.60E-03 3.60E-03 8.46E-03 2.42E-02 3.62E-03 3.61E-03 3.60E-03 3.60E-03 3.60E-03 7.74E-03 1.46E-02 3.61E-03 3.61E-03 3.60E-03 3.60E-03 3.60E-03 7.41E-03 5.53E-03 Page 275 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXL GASEOUS EFFLUENT DOSE CONVERSION FACTORS Ce-143 Gaseous release (mrem/Ci released) Bone Liver T.Body Thyroid.** Kidney Lung GI~LLI
* . ,* *"*,* *
Adult 4.38E-04 5.76E-04 4.33E-04 4.33E-04 4.35E-04 2.24E-03 1.08E-02 r , .* ~., .:.;:feen
; 4.40E-04 5.67E-04 4.34E-04 4.33E-04 4.35E-04 3.39E-03 l.OIE-02 "? ~.~"'/ ** f';i.':J ".:~** 4.42E-04 6.17E-04 4.34E-04 4.33E-04 4.35E-04 3.05E-03 5.94E-03 ,.* . .,. ) . .};;i~i.t 4.40E-04 4.50E-04 4.34E-04 4.33E-04 4.35E-04 3.07E-03 1.63E-03 ."*.c.:.*****
Ce-144 1.34E-Ol 1.95E-02 4.28E-02 3.16E-Ol 2.47E+OO 1.90E-Ol 6.83E-02 2.25E-02 1.30E-02 4.37E-02 2.84E-Ol 1.92E+OO 8.57E-02 4.06E-02 1.70E-02 1.30E-02 2.53E-02 2.36E-Ol 3.32E-02 GI~LLI 6.00E-02 1.57E-05 O.OOE+OO 7.32E-05 l.IOE-02 5.06E-02 1.34E-04 2.21E-05 O.OOE+OO 7.27E-05 9.81E-03 3.32E-02 1.19E-04 1.58E-05 O.OOE+OO 4.48E-05 9.81E-03 8.80E-04 3.44E-07 3.43E-07 3.43E-07 3.45E-07 3.44E-07 3.43E-07 3.43E-07 3.44E-07 3.58E-05 4.80E-06 3.44E-07 3.44E-07 3.43E-07 3.43E-07 3.44E-07 3.68E-05 9.74E-05 Page 276 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL APPENDIXL GASEOUS EFFLUENT DOSE CONVERSION FACTORS W-187 Gaseous release (mrem/Ci released)
**. *..*~.* . ..
Bone Liver T.Body Thyroid Kidney .* Lung GI~LLI Adult 4.49E-04 4.48E-04 4.44E-04 4.42E-04 4.42E-04 l.IOE-03 6.00E-03 1
£*:~ \. *we~il 4.49E-04 4.48E-04 4.44E-04 4.42E-04 4.42E-04 1.52E-03 6.04E-03 *.*,~,~ :: . ~*7:~iBL:I.1** *. 4.55E-04 4.50E-04 4.45E-04 4.42E-04 4.42E-04 1.37E-03 3.62E-03 ~*iffir~nt 4.45E-04 4.44E-04 4.42E-04 4.42E-04 4.42E-04 1.34E-03 1.36E-03 2.44E+OO 1.07E+OO 6.33E+OO 1.64E+Ol 2.52E+OO 1.07E+OO 4.20E+OO 1.07E+OO 9.56E+OO 1.47E+Ol 2.21E+OO 1.07E+OO 1.40E+OO 1.07E+OO 1.99E+OO 1.15E+Ol 1.12E+OO Gaseous release (mrem/Ci released) *wli'?;'i!Jia~t~* . Idilli~
3.99E-03 3.09E+OO 8.54E-Ol 3.99E-03 1.28E+OO 3.99E-03 4.93E+OO 1.03E+OO 3.99E-03 2.94E+OO 3.99E-03 7.93E+OO 1.28E+Ol 8.04E-Ol 3.99E-03 3.09E-Ol 3.99E-03 8.62E-Ol 9.71E+OO 3.95E-02 3.21E-04 3.21E-04 3.20E-04 3.22E-04 1.64E-03 4.32E-03 3.21E-04 3.20E-04 3.20E-04 3.22E-04 1.67E-03 8.89E-04 Page 277 of278 REFERENCE USE
POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 20 OFFSITE DOSE CALCULATION MANUAL ACTIVITY RELEASED TO DOSE CONVERSION FACTORS FOR NOBLE GASES TOT~~L ]lpDY BETA AIR SKIN DOSE GAMMA AIR RADIONUCLIDE D()S:E .* DOSE DOSE
' (mrelll/Ci) (mrem/Ci) (mrad/Ci) (mradlCi)
Kr-83m 1.71E-09 4.81E-07 4.37E-07 6.53E-06 Kr-85m 2.65E-05 6.37E-05 2.79E-05 4.46E-05 Kr-85 3.65E-07 3.08E-05 3.90E-07 4.42E-05 Kr-87 1.34E-04 3.74E-04 1.40E-04 2.33E-04 Kr-88 3.33E-04 4.33E-04 3.44E-04 6.64E-05 Kr-89 3.76E-04 6.60E-04 3.92E-04 2.40E-04 Kr-90 3.53E-04 5.71E-04 3.69E-04 1.77E-04 Xe-131m 2.07E-06 1.47E-05 3.53E-06 2.51E-05 Xe-133m 5.69E-06 3.07E-05 7.41E-06 3.35E-05 Xe-133 6.66E-06 1.57E-05 8.00E-06 2.38E-05 Xe-135m 7.07E-05 9.98E-05 7.61E-05 1.67E-05 Xe-135 4.10E-05 9.00E-05 4.35E-05 5.57E-05 Xe-137 3.22E-05 3.14E-04 3.42E-05 2.88E-04 Xe-138 2.00E-04 3.23E-04 2.09E-04 1.08E-04 Ar-41 2.00E-04 2.93E-04 2.11E-04 7.43E-05 Page 278 of278 REFERENCE USE}}

NRC 2019-0014, 2018 Annual Monitoring Report

Contents

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SUMMARY

1.0 INTRODUCTION

Reference:

8.0 INTRODUCTION

Description:

SUMMARY

1.0 INTRODUCTION

1.0 INTRODUCTION

2.0 INTRODUCTION

14.0 REFERENCES

2.0 INTRODUCTION

14.0 REFERENCES

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SUMMARY

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NRC 2019-0014, 2018 Annual Monitoring Report

Text

SUMMARY

1.0 INTRODUCTION

Reference:

8.0 INTRODUCTION

Description:

SUMMARY

1.0 INTRODUCTION

1.0 INTRODUCTION

2.0 INTRODUCTION

14.0 REFERENCES

2.0 INTRODUCTION

14.0 REFERENCES

SUMMARY

SUMMARY

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