ML20136A016

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Annual Radioactive Effluent Report and Offsite Dose Calculation Manual
ML20136A016
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 05/15/2020
From: Sharp S
Northern States Power Co, Xcel Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-Pl-20-021, TS 5.6.3
Download: ML20136A016 (17)
v • d • e


Text

(l Xcel Energy*

RESPONSIBLE BY NATURE "' 1717 Wakonade Drive Welch, MN 55089 May 15, 2020 L-Pl-20-021 TS 5.6.3 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant, Units 1 and 2 Docket Nos. 50-282 and 50-306 Renewed Facility Operating License Nos. DPR-42 and DPR-60 2019 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual Pursuant to the applicable Prairie Island Nuclear Generating Plant (PINGP) Technical Specifications (TS), Appendix A to Renewed Operating Licenses DPR-42 and DPR-60, and the requirements of the Offsite Dose Calculation Manual (ODCM), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM") ,

submits the 2019 Annual Radioactive Effluent Report which is comprised of the following:

Enclosure 1 contains the Off-Site Radiation Dose Assessment for the period January 1, 2019, through December 31 , 2019, in accordance with ODCM section 8.1.1.

Enclosure 2 contains the Annual Radioactive Effluent Report, Supplemental Information, for the period January 1, 2019, through December 31, 2019 , in accordance with TS 5.6.3 and ODCM section 8.1.1 .

Summary of Commitments This letter makes no new commitments and no revisions to existing commitments .

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Scott Sharp Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (2) cc: Administrator, Region Ill , USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC Department of Health, State of Minnesota Pl Indian Community Environmental Coordinator

ENCLOSURE 1 OFF-SITE RADIATION DOSE ASSESSMENT January 1, 2019 - December 31, 2019 6 pages to follow

Page 1 of 6 PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFF-SITE RADIATION DOSE ASSESSMENT FOR January 1, 2019 - December 31, 2019 An Assessment of the 2019 radiation dose, due to operation of The Prairie Island Nuclear Generating Plant, was performed in accordance with the Offsite Dose Calculation Manual, and as required by Technical Specifications. Computed doses were well below the 40 CFR Part 190 Standards and 10 CFR Part 50 Appendix I Guidelines.

Off-site dose calculation formulas and historical meteorological data were used in making this assessment. Source terms were obtained from the Annual Radioactive Effluent and Waste Disposal Report and prepared for NRC review, for the year of 2019.

OFFSITE DOSES FROM GASEOUS RELEASE:

Computed doses due to gaseous releases are reported in Table 1. Critical receptor location and pathways for organ doses are reported in Table 2. Gaseous release doses are a small percentage of Appendix I Guidelines.

OFFSITE DOSES FROM LIQUID RELEASE:

Computed doses due to liquid releases are reported in Table 1. Critical receptor information is reported in Table 2. Liquid release doses, both whole body and organ, are a small percentage of Appendix I Guidelines.

DOSES TO INDIVIDUALS DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY:

Occasionally sportsmen enter the Prairie Island Site Boundary for recreational activities.

These individuals are not expected to spend more than a few hours per year within the site boundary. Commercial and recreational river traffic exists through this area.

For purposes of estimating the dose due to recreational and river water transportation activities within the site boundary it is assumed that the limiting dose within the site boundary would be received by an individual who spends a total of seven days per year on the river just off-shore from the plant buildings (ESE at 0.2 miles). The gamma and beta doses from noble gas releases and the maximum organ doses from the inhalation pathway due to Iodine 131, lodine-133, tritium, long-lived particulates and Carbon-14 were calculated for this location and occupancy time. These doses are reported in Table 1.

Critical Receptor location and pathways for organ doses are reported in Table 2.

Page 2 of 6 40 CFR 190 COMPLIANCE:

REMP environmental TLD results for 2019 were reviewed per ANSI/HPS N13.37-2014 methodology for determining any plant effect above ambient gamma radiation measurements. All measurements are considered to be within the range of variations in natural background radiation.

Neutron sky shine dose from the ISFSI was evaluated. The maximum neutron sky shine dose was determined to be 0.79 mrem, to the nearest resident, at 724 meters from the ISFSI. Neutron sky shine dose is greater than the effluent dose to the Critical Receptor, therefore, 40 CFR190 compliance was evaluated to the location of the maximum neutron sky shine dose.

The 40 CFR 190 evaluation locations were determined to be 0.7 miles west of the plant.

Dose due to gaseous effluents was calculated to the 40 CFR 190 evaluation locations.

MREM Gamma Direct Radiation Dose: 0.00E+00 Neutron Sky Shine Dose: 7.90E-01 Noble Gas Gamma Dose: 7.94E-06 Noble Gas Beta Dose: 1.23E-05 Iodine, particulate, H-3 and C-14 Dose: 4.49E-03*

  • Calculated values were identical for Whole Body, Thyroid and Maximum "Other" Organs SUMMATION OF 40 CFR 190 DOSE:

40 CFR 190 LIMIT 40 CFR 190 DOSE (MREM) (MREM)

WHOLE BODY 25 7.95E-01 THYROID 75 7.95E-01 OTHER ORGANS 25 7.95E-01 (TEEN - WHOLE BODY)

Page 3 of 6 ABNORMAL RELEASES:

There were zero (0) abnormal releases in 2019.

SAMPLING, ANALYSIS AND LLD REQUIREMENTS:

The lower limit of detection (LLD) requirements, as specified in ODCM Tables 2.1 and 3.1, were met for 2019. The minimum sampling frequency requirements, as specified in ODCM Tables 2.1 and 3.1, were met for 2019.

MONITORING INSTRUMENTATION:

For 2019, there were zero (0) occurrences, when less than the minimum required radioactive liquid and/or gaseous effluent monitoring instrumentation channels were operable, as required by ODCM Tables 2.2 and 3.2.

DOSES TO INDIVIDUALS DUE TO EFFLUENT RELEASES FROM THE INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI):

Zero (0) fuel casks were loaded and placed in the ISFSI during the 2019 calendar year. The total number of casks in the ISFSI, as of 12/31/19, was forty-four (44). There were zero (0) releases of radioactive effluents from the ISFSI.

CURRENT OFFSITE DOSE CALCULATIONS MANUAL (ODCM) REVISION:

The Offsite Dose Calculation Manual was not revised in 2019. Revision 32, is the current revision. Revision 32 is dated May 25, 2018.

PROCESS CONTROL PROGRAM:

D59, The Process Control Program for Solidification/Dewatering of Radioactive Waste from Liquid Systems, was not revised in 2019. Revision 12 is the current revision. Revision 12 is dated January 26, 2018.

INDUSTRY INITIATIVE ON GROUND WATER PROTECTION:

For 2019, there was zero (0) events for inclusion in the Annual Effluent Report, as part of the NEI Ground Water Initiative.

CRITICAL RECEPTOR:

Based on the Annual Land Use Census, the critical receptor did not change. The critical receptor is defined as The Suter Residence, at 0.6 miles, in the SSE sector.

Page 4 of 6 LOW LEVEL WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED COMPONENTS SHIPMENTS PERIOD: 1/1/19 TO 12/31/19 LICENSE NUMBER: DPR-42/60 SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL):

Resins, Filters and Evaporator Volume Curies Shipped Bottoms Waste Class FT3 M3 Curies A 2.21E+02 6.25E+00 6.44E+00 B 2.91E+02 8.25E+00 1.69E+02 C 0.00+00 0.00E+00 0.00E+00 ALL 5.12E+02 1.45E+01 1.75E+02 Major Nuclides H-3, C-14, Mn-54, Fe-55, Co-58, Co-60, Ni-59, Ni-63, Sr-90, Nb-94, Nb-95, Tc-99,Ag-110m, Sb-125, I-129, Cs-137, Ce-144, Pu-238, Pu-239, Pu-240, Pu-241, Am-241, Cm-242, Cm-243, Cm-244 Dry Active Waste Volume Curies Shipped Waste Class FT3 M3 Curies A 1.54E+04 4.36E+02 4.95E-01 B 0.00E+00 0.00E+00 0.00E+00 C 0.00E+00 0.00E+00 0.00E+00 ALL 1.54E+04 4.36E+02 4.95E-01 Major Nuclides H-3, C-14, Cr-51, Mn-54, Fe-55, Co-58, Co-60, Ni-59, Ni-63, Sr-90, Zr-95, Nb-94, Nb-95, Tc-99, Ag-110m, Sn-113, Sb-125, I-129, Cs-137, Ce-144, Pu-238, Pu-239, Pu-240, Pu-241, Am-241, Cm-242, Cm-243, Cm-244 Irradiated Components Volume Curies Shipped Waste Class FT3 M3 Curies A 0.00E+00 0.00E+00 0.00E+00 B 0.00E+00 0.00E+00 0.00E+00 C 0.00E+00 0.00E+00 0.00E+00 ALL 0.00E+00 0.00E+00 0.00E+00 Major Nuclides Other Waste Volume Curies Shipped Waste Class FT3 M3 Curies A 0.00E+00 0.00E+00 0.00E+00 B 0.00E+00 0.00E+00 0.00E+00 C 0.00E+00 0.00E+00 0.00E+00 ALL 0.00E+00 0.00E+00 0.00E+00 Major Nuclides Sum of All Low Level Waste Volume Curies Shipped Shipped from Site Waste Class FT3 M3 Curies A 1.56E+04 4.42E+02 6.94E+00 B 2.91E+02 8.25E+00 1.69E+02 C 0.00E+00 0.00E+00 0.00E+00 ALL 1.59E+04 4.50E+02 1.76E+02 Major Nuclides H-3, C-14, Cr-51, Mn-54, Fe-55, Co-58, Co-60, Ni-59, Ni-63, Sr-90, Zr-95, Nb-94, Nb-95, Tc-99, Ag-110m, Sn-113, Sb-125, I-129, Cs-137, Ce-144, Pu-238, Pu-239, Pu-240, Pu-241, Am-241, Cm-242, Cm-243, Cm-244 Total curie quantity and principal radionuclides identification are calculated estimates determined for packaged waste using gross gamma radiation measurements, direct sample data or swipe data within WMGs Radman Suite Software. Characterization of radioactive waste is performed in accordance with 10 CFR 20, 10 CFR 61, and NRCs Branch Technical Positions.

Page 5 of 6 TABLE 1 OFF-SITE RADIATION DOSE ASSESSMENT JANUARY 2019 THROUGH DECEMBER 2019 DOSE LIMIT*

Gaseous Releases Maximum Site Boundary Gamma Air Dose (mrad) 2.28E-05 20 Maximum Site Boundary Beta Air Dose (mrad) 1.43E-05 40 Maximum Off-site Dose to any Organ (mrem)** 6.51E-02 30 Organ Child - bone Offshore Location Maximum Site Boundary Gamma Air Dose (mrad) 1.76E-07 20 Maximum Site Boundary Beta Air Dose (mrad) 1.10E-07 40 Maximum Off-site Dose to any Organ (mrem)** 5.01E-04 30 Organ Teen - Total Body Liquid Releases Maximum Off-site Dose Total Body (mrem) 1.55E-03 6 Maximum Off-site Dose to any Organ (mrem) 1.69E-03 20 Organ Adult - Gi-LLi

  • 10 CFR part 50, Appendix I Guidelines (2-unit site per year)

Page 6 of 6 TABLE 2 OFF-SITE RADIATION DOSE ASSESSMENT- PRAIRIE ISLAND SUPPLEMENTAL INFORMATION January 1, 2019 - December 31, 2019 Gaseous Releases Maximum Site Boundary Dose Location (From Building Vents)

Sector W Distance (miles) 0.36 Offshore Location Within Site Boundary Sector ESE Distance (miles) 0.2 Pathway Inhalation Critical Receptor Location Sector SSE Distance (miles) 0.60 Pathways Ground Inhalation Vegetable Age Group Child Liquid Releases Maximum Off-site Dose Location Sector SSE Distance (miles) 0.43 Pathway Fish

ENCLOSURE 2 ANNUAL RADIOACTIVE EFFLUENT REPORT SUPPLEMENTAL INFORMATION January 1, 2019 - December 31, 2019 8 pages to follow

Page 1 of 8 ANNUAL RADIOACTIVE EFFLUENT REPORT SUPPLEMENTAL INFORMATION 01-JAN-19 THROUGH 31-DEC-19 Facility: Prairie Island Nuclear Generating Plant Licensee: Northern States Power Company License Numbers: DPR-42 & DPR-60 A. Regulatory Limits

1. Liquid Effluents:
a. The dose or dose commitment to an individual from radioactive materials in liquid effluents released from the site shall be limited to:

for the quarter 3.0 mrem to the total body 10.0 mrem to any organ for the year 6.0 mrem to the total body 20.0 mrem to any organ

2. Gaseous Effluents:
a. The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to:

noble gases 500 mrem/year total body 3000 mrem/year skin I-131, I-133, H-3, LLP, C-14 l500 mrem/year to any organ

b. The dose due to radioactive gaseous effluents released from the site shall be limited to:

noble gases l0 mrad/quarter gamma 20 mrad/quarter beta 20 mrad/year gamma 40 mrad/year beta I-131, I-133, H-3, LLP, 15 mrem/quarter to any organ C-14 30 mrem/year to any organ

Page 2 of 8 B. Effluent Concentration

1. Fission and activation gases in gaseous releases:

10 CFR 20, Appendix B, Table 2, Column 1

2. Iodine and particulates with half-lives greater than 8 days in gaseous releases:

10 CFR 20, Appendix B, Table 2, Column 1

3. Liquid effluents for radionuclides other than dissolved or entrained gases:

10 CFR 20, Appendix B, Table 2, Column 2

4. Liquid effluent dissolved and entrained gases:

Offsite Dose Calculation Manual C. Average Energy Not applicable to Prairie Island regulatory limits.

D. Measurements and approximations of total activity

1. Fission and activation gases Total HPGe +/-25%

in gaseous releases: Nuclide

2. Iodines in gaseous releases: Total HPGe +/-25%

Nuclide

3. Particulates in gaseous releases: Total HPGe +/-25%

Nuclide

4. Liquid effluents Total HPGe +/-25%

Nuclide E. Manual Revisions

1. Offsite Dose Calculations Manual:

Latest Revision number: 32 Revision date May 25, 2018

Page 3 of 8 Prairie Island Nuclear Generating Station PI 2019 Annual Release Summary Batch Release Summary Liquid Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Number of Releases: 25 36 43 58 162 Total Time for All Releases (Minutes): 1846.0 2807.0 3409.0 4552.0 12614.0 Maximum Time for All Releases (Minutes): 95.0 120.0 207.0 122.0 207.0 Average Time for All Releases (Minutes): 73.8 78.0 79.3 78.5 77.9 Minimum Time for All Releases (Minutes): 52.0 66.0 64.0 46.0 46.0 Gaseous Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Number of Releases: 1 1 10 19 31 Total Time for All Releases (Minutes): 129600.0 131040.0 132480.0 152903.0 546023.0 Maximum Time for All Releases (Minutes): 129600.0 131040.0 132480.0 132480.0 132480.0 Average Time for All Releases (Minutes): 129600.0 131040.0 132480.0 8047.7 24819.3 Minimum Time for All Releases (Minutes): 129600.0 131040.0 132480.0 14.0 14.0 Abnormal Release Summary Liquid Releases Number of Abnormal Releases: 0 Total Activity for Abnormal Releases: 0.00E+00 Curies Gaseous Releases Number of Abnormal Releases: 0 Total Activity for Abnormal Releases: 0.00E+00 Curies

Page 4 of 8 Prairie Island Nuclear Generating Station PI 2019 Annual Release Summary Gaseous Effluents-Summation of All Releases Est. Total Type of Effluent Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Error, %

A. Fission & Activation Gases

1. Total Release Curies 1.64E-04 1.94E-04 2.08E-04 1.29E-02 2.50E+01
2. Average Release Rate for Period µCi/sec 2.10E-05 2.43E-05 2.62E-05 1.62E-03
3. Percent of Applicable Limit  % 5.83E-07 6.85E-07 7.57E-07 2.26E-04 B. Iodines
1. Total Iodine-131 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.50E+01
2. Average Release Rate for Period µCi/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00
3. Percent of Applicable Limit  % 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C. Particulates
1. Total Particulates (Half-lives > 8 days) Curies 0.00E+00 0.00E+00 3.27E-06 4.93E-07 2.50E+01
2. Average Release Rate for Period µCi/sec 0.00E+00 0.00E+00 4.11E-07 6.21E-08
3. Percent of Applicable Limit  % 0.00E+00 0.00E+00 4.83E-05 6.42E-07
4. Gross Alpha Activity Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.50E+01 D. Tritium
1. Total Release Curies 9.16E+00 1.01E+01 7.23E+00 7.12E+00 2.50E+01
2. Average Release Rate for Period µCi/sec 1.16E+00 1.29E+00 9.09E-01 8.96E-01
3. Percent of Applicable Limit  % 1.68E-02 1.85E-02 1.32E-02 1.37E-02 E. Carbon-14
1. Total Release Curies 2.87E+00 2.87E+00 2.84E+00 2.30E+00 2.50E+01

Page 5 of 8 Prairie Island Nuclear Generating Station PI 2019 Annual Release Summary Gaseous Effluents - Ground Level Releases Continuous Mode Batch Mode Nuclides Released Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Qtr 1 Qtr 2 Qtr 3 Qtr 4

1. Fission and Activation Gases Ar-41 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.71E-07 3.29E-03 Xe-133 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.59E-04 1.87E-04 2.00E-04 9.62E-03 Xe-133m Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.00E-06 0.00E+00 3.58E-06 5.39E-07 Xe-135 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.49E-06 3.88E-06 3.74E-06 1.61E-07 Total for Period Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.64E-04 1.91E-04 2.08E-04 1.29E-02
2. Iodines I-131 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total For Period Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
3. Particulates Cd-109 Curies 0.00E+00 0.00E+00 3.18E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.50E-09 Co-58 Curies 0.00E+00 0.00E+00 8.16E-08 4.90E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for Period Curies 0.00E+00 0.00E+00 3.27E-06 4.90E-07 0.00E+00 0.00E+00 0.00E+00 3.50E-09
4. Tritium H-3 Curies 9.16E+00 1.01E+01 7.23E+00 7.03E+00 3.34E-05 1.19E-04 2.72E-05 8.84E-02
5. Carbon-14 C-14 Curies 2.87E+00 2.87E+00 2.84E+00 2.30E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 6 of 8 Prairie Island Nuclear Generating Station PI 2019 Annual Release Summary Liquid Effluents - Summation of All Releases Est. Total Type of Effluent Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Error, %

A. Fission & Activation Products

1. Total Release (not including Tritium, Curies 1.90E-04 1.68E-04 1.91E-04 4.76E-03 2.50E+01 Gases, and Alpha)
2. Average Diluted Concentration During µCi/ml 2.63E-12 2.41E-12 2.35E-12 6.01E-11 Period
3. Percent of Applicable Limit  % 3.81E-03 3.37E-03 3.81E-03 9.52E-02 B. Tritium
1. Total Release Curies 1.24E+02 1.09E+02 8.08E+01 1.19E+02 2.50E+01
2. Average Diluted Concentration During µCi/ml 1.71E-06 1.56E-06 9.97E-07 1.50E-06 Period
3. Percent of Applicable Limit  % 1.71E-01 1.56E-01 9.97E-02 1.50E-01 C. Dissolved and Entrained Gases
1. Total Release Curies 1.91E-05 5.20E-05 1.20E-05 6.56E-05 2.50E+01
2. Average Diluted Concentration During µCi/ml 2.63E-13 7.43E-13 1.48E-13 8.28E-13 Period
3. Percent of Applicable Limit  % 1.32E-07 3.72E-07 7.40E-08 4.14E-07 D. Gross Alpha Radioactivity
1. Total Release Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.50E+01 E. Waste Volume Released (Pre-Dilution) Liters 2.30E+07 2.61E+07 2.76E+07 3.73E+07 2.50E+01 F. Volume of Dilution Water Used Liters 7.25E+10 6.99E+10 8.10E+10 7.92E+10 2.50E+01

Page 7 of 8 Prairie Island Nuclear Generating Station PI 2019 Annual Release Summary Liquid Effluents Continuous Mode Batch Mode Nuclides Released Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ag-110m Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.30E-05 8.59E-06 3.42E-05 1.26E-04 Co-57 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.08E-06 Co-58 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.46E-05 6.85E-05 3.16E-05 3.62E-03 Co-60 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.78E-05 6.31E-05 8.27E-05 1.70E-04 Cr-51 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.38E-06 0.00E+00 0.00E+00 2.88E-04 Fe-59 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.90E-05 H-3 Curies 2.65E-02 4.11E-02 7.67E-02 1.21E-01 1.24E+02 1.09E+02 8.07E+01 1.19E+02 Mn-54 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.33E-06 Nb-95 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.33E-06 0.00E+00 0.00E+00 1.41E-04 Nb-97 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.69E-06 1.97E-05 2.20E-05 2.17E-05 Sb-125 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.59E-06 9.24E-07 4.97E-06 2.44E-04 Sc-46 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.33E-07 Sn-113 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.42E-06 Sr-92 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.73E-07 1.79E-06 1.34E-06 1.72E-06 Te-123M Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.42E-05 5.95E-06 1.37E-05 3.59E-05 Xe-133 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.91E-05 4.82E-05 1.20E-05 6.50E-05 Xe-135 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 3.80E-06 0.00E+00 5.85E-07 Zr-95 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.09E-05 Total for Period Curies 2.65E-02 4.11E-02 7.67E-02 1.21E-01 1.24E+02 1.09E+02 8.07E+01 1.19E+02

Page 8 of 8 Prairie Island Nuclear Generating Station 2019 Annual Dose Summary Gaseous Effluents Parameter Location Dose Dose Limit  % of Limit Qtr 1 Gamma Air Dose (mrad) 0.58 km W 3.99E-08 1.00E+01 0.00 Beta Air Dose (mrad) 0.58 km W 1.17E-07 2.00E+01 0.00 Total Body Dose (mrem) 0.58 km W 3.34E-08 5.00E+00 0.00 Skin Dose (mrem) 0.58 km W 8.02E-08 1.50E+01 0.00 Max Organ Dose (mrem) 0.97 km SSE 2.52E-03 1.50E+01 0.02 Child - Liver Qtr 2 Gamma Air Dose (mrad) 0.58 km W 4.89E-08 1.00E+01 0.00 Beta Air Dose (mrad) 0.58 km W 1.37E-07 2.00E+01 0.00 Total Body Dose (mrem) 0.58 km W 4.13E-08 5.00E+00 0.00 Skin Dose (mrem) 0.58 km W 9.67E-08 1.50E+01 0.00 Max Organ Dose (mrem) 0.97 km SSE 2.63E-02 1.50E+01 0.18 Child - Bone Qtr 3 Gamma Air Dose (mrad) 0.58 km W 5.74E-08 1.00E+01 0.00 Beta Air Dose (mrad) 0.58 km W 1.51E-07 2.00E+01 0.00 Total Body Dose (mrem) 0.58 km W 4.88E-08 5.00E+00 0.00 Skin Dose (mrem) 0.58 km W 1.12E-07 1.50E+01 0.00 Max Organ Dose (mrem) 0.97 km SSE 3.88E-02 1.50E+01 0.26 Child - Bone Qtr 4 Gamma Air Dose (mrad) 0.58 km W 2.26E-05 1.00E+01 0.00 Beta Air Dose (mrad) 0.58 km W 1.39E-05 2.00E+01 0.00 Total Body Dose (mrem) 0.58 km W 2.12E-05 5.00E+00 0.00 Skin Dose (mrem) 0.58 km W 3.27E-05 1.50E+01 0.00 Max Organ Dose (mrem) 0.97 km SSE 2.05E-03 1.50E+01 0.01 Child - Kidney Year Gamma Air Dose (mrad) 0.58 km W 2.28E-05 2.00E+01 0.00 Beta Air Dose (mrad) 0.58 km W 1.43E-05 4.00E+01 0.00 Total Body Dose (mrem) 0.58 km W 2.14E-05 1.00E+01 0.00 Skin Dose (mrem) 0.58 km W 3.30E-05 3.00E+01 0.00 Max Organ Dose (mrem) 0.97 km SSE 6.51E-02 3.00E+01 0.22 Child - Bone Liquid Effluents Parameter Max Receptor Dose Dose Limit  % of Limit Qtr 1 Max Organ Dose (mrem) Adult - Gi-LLi 3.39E-04 1.00E+01 0.00 Total Body Dose (mrem) Adult - Total Body 3.36E-04 3.00E+00 0.01 Qtr 2 Max Organ Dose (mrem) Adult - Liver 7.11E-04 1.00E+01 0.01 Total Body Dose (mrem) Adult - Total Body 7.02E-04 3.00E+00 0.02 Qtr 3 Max Organ Dose (mrem) Adult - Gi-LLi 1.61E-04 1.00E+01 0.00 Total Body Dose (mrem) Adult - Total Body 1.58E-04 3.00E+00 0.01 Qtr 4 Max Organ Dose (mrem) Adult - Gi-LLi 4.80E-04 1.00E+01 0.00 Total Body Dose (mrem) Adult - Total Body 3.54E-04 3.00E+00 0.01 Year Max Organ Dose (mrem) Adult - Gi-LLi 1.69E-03 2.00E+01 0.01 Total Body Dose (mrem) Adult - Total Body 1.55E-03 6.00E+00 0.03

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