ML23128A092

2022 Annual Radioactive Effluent Report

ML23128A092
Person / Time
Site:	Prairie Island
Issue date:	05/08/2023
From:	Borgen T Northern States Power Co, Xcel Energy
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
L-Pl-23-008
Download: ML23128A092 (1)

Text

fl Xcel Energy May 08, 2023 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 2022 Annual Radioactive Effluent Report 1717 Wakonade Drive Welch, MN 55089 L-Pl-23-008 10 CFR 50.36a Tech Spec 5.6.3 Pursuant to 10 CFR 50.36a, "Technical specifications on effluents from nuclear power reactors," paragraph (a)(2), and in accordance with Prairie Island Nuclear Generating Plant (PINGP) Technical Specification (TS) 5.6.3 "Radioactive Effluent Report," the Northern States Power Company (NSPM), a Minnesota corporation, d/b/a Xcel Energy, is submitting the following enclosures: - Radioactive Effluent Report. - Radioactive Effluent Report, Supplemental Information.

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



Timothy P. Borgen Plant Manager, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (2)

Document Control Desk L-PI-23-008 Page 2 cc:

Administrator, Region III, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC Department of Health, State of Minnesota PI Dakota Community Environmental Coordinator

ENCLOSURE 1 RADIOACTIVE EFFLUENT REPORT JANUARY 1, 2022 - DECEMBER 31, 2022 7 pages to follow

Page 1 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFF-SITE RADIATION DOSE ASSESSMENT FOR January 1, 2022 - December 31, 2022 An Assessment of the 2022 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 2022.

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 7 40 CFR 190 COMPLIANCE:

REMP environmental TLD results for 2022 were reviewed per ANSI/HPS N13.37-2014 methodology for determining any plant effect above ambient gamma radiation measurements. All measurements are 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 0.93 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 location was determined to be 0.7 miles west of the plant.

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

Gamma Direct Radiation Dose:

Neutron Sky Shine Dose:

Noble Gas Gamma Dose:

Noble Gas Beta Dose:

Iodine, particulate, H-3 and C-14 Dose:

MREM 0.00E+00 9.30E-01 1.69E-06 3.55E-06 3.41E-03*

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

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

WHOLE BODY 25 9.33E-01 THYROID 75 9.33E-01 OTHER ORGANS (TEEN - WHOLE BODY) 25 9.33E-01

Page 3 of 7 ABNORMAL RELEASES:

There were zero (0) abnormal releases in 2022.

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 2022 The minimum sampling frequency requirements, as specified in ODCM Tables 2.1 and 3.1, were met for 2022.

MONITORING INSTRUMENTATION:

For 2022, there was one (1) occurrence 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.

1R22, Unit One Shield Building Stack Monitor, was out of service from 07/03/2022 at 21:55 to 10/07/2022 at 13:15. It was out of service for a total of 95.6 days. Waning vendor support for aging radiation monitor has caused parts availability challenges. Additionally, improper classification of 1R22 as safety related precluded the prompt use of site available parts.

Reclassification of 1R22 allowed the use of available parts and restoration of the monitor.

The ultimate resolution is to replace the Radiation Monitor. 1R22 is part of the Radiation Monitor Replacement Project, now underway.

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

Three (3) fuel casks were loaded and placed in the ISFSI during the 2022 calendar year.

The total number of casks in the ISFSI, as of 12/31/2022, was fifty (50). 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 2022. Revision 32 is dated May 25, 2018. Revision 33 was approved on 3/10/2023 and will be submitted with the 2023 Annual Radioactive Effluent Report.

PROCESS CONTROL PROGRAM:

D59, The Process Control Program for Solidification/Dewatering of Radioactive Waste from Liquid Systems, was not revised in 2022. Revision 12 is the current revision. Revision 12 is dated January 26, 2018.

INDUSTRY INITIATIVE ON GROUND WATER PROTECTION:

For 2022, there was zero (0) events for inclusion in the Annual Effluent Report, as part of the NEI Ground Water Initiative.

Page 4 of 7 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.

HISTORICAL METEOROLOGICAL DATA ASSESSMENT:

Prairie Islands current in-use meteorological data set is 2012-2016. Prairie Island submitted the 2017-2021 meteorological data set to a certified meteorologist in 2022, for assessment. Submitted data set was found to be a quality data set representative of local meteorology. The submitted data set (2017-2021) did NOT vary from in-use data set (2012-2016) to a degree requiring updating the current in-use data set. Current in-use data set is conservative in dispersion factors generated.

Determination was to continue the use of the in-use data set (2012-2016).

Page 5 of 7 LOW LEVEL WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED COMPONENTS SHIPMENTS PERIOD: 1/1/22 TO 12/31/22 LICENSE NUMBER: DPR-42/60 SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL):

Resins, Filters and Evaporator Bottoms Volume Curies Shipped Waste Class ft3 m3 Curies A

2.06E+02 5.82E+00 6.14E+00 B

3.75E+01 1.06E+00 7.30E+00 C

7.50E+00 2.12E-01 2.30E+00 ALL 2.51E+02 7.10E+00 1.57E+01 Major Nuclides H-3, C-14, Cr-51, Mn-54, Fe-55, Fe-59, Co-58, Co-60, Ni-59, Ni-63, Sr-90, Zr-95, 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

1.02E+04 2.90E+02 2.77E-01 B

0.00E+00 0.00E+00 0.00E+00 C

0.00E+00 0.00E+00 0.00E+00 ALL 1.02E+04 2.90E+02 2.77E-01 Major Nuclides H-3, C-14, Cr-51, Mn-54, Fe-55, Co-58, Co-60, Ni-63, Sr-90, Zr-95, Nb-94, Nb-95, Tc-99, 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 n/a 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 n/a Sum of All Low Level Waste Shipped from Site Volume Curies Shipped Waste Class ft3 m3 Curies A

1.04E+04 2.96E+02 6.41E+00 B

3.75E+01 1.06E+00 7.30E+00 C

7.50E+00 2.12E-01 2.30E+00 ALL 1.05E+04 2.97E+02 1.60E+01 Major Nuclides H-3, C-14, Cr-51, Mn-54, Fe-55, Fe-59, 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 6 of 7 Table 1 OFF-SITE RADIATION DOSE ASSESSMENT JANUARY 2022 THROUGH DECEMBER 2022 DOSE LIMIT*

Gaseous Releases Maximum Site Boundary Gamma Air Dose (mrad) 4.88E-06 20 Maximum Site Boundary Beta Air Dose (mrad) 7.26E-06 40 Maximum Off-site Dose to any Organ (mrem)**

6.41E-02 30 Organ Child - bone Offshore Location Maximum Site Boundary Gamma Air Dose (mrad) 3.70E-07 20 Maximum Site Boundary Beta Air Dose (mrad) 5.07E-07 40 Maximum Off-site Dose to any Organ (mrem)**

6.06E-04 30 Organ Teen - Total Body Liquid Releases Maximum Off-site Dose Total Body (mrem) 2.57E-03 6

Maximum Off-site Dose to any Organ (mrem) 2.57E-03 20 Organ Adult - Lung

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

• • Long Lived Particulate, I-131, I-133, Tritium and C-14

Page 7 of 7 Table 2 OFF-SITE RADIATION DOSE ASSESSMENT-PRAIRIE ISLAND SUPPLEMENTAL INFORMATION January 1, 2022 - December 31, 2022 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 RADIOACTIVE EFFLUENT REPORT SUPPLEMENTAL INFORMATION JANUARY 1, 2022 - DECEMBER 31, 2022 8 pages to follow

Page 1 of 8 ANNUAL RADIOACTIVE EFFLUENT REPORT SUPPLEMENTAL INFORMATION 01-JAN-22 THROUGH 31-DEC-22 Facility:

Licensee:

Prairie Island Nuclear Generating Plant 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 in gaseous releases:

Nuclide

2.

Iodines in gaseous releases:

Total HPGe Nuclide

3.

Particulates in gaseous releases:

Total HPGe Nuclide

4.

Liquid effluents Total HPGe Nuclide

+/-25%

+/-25%

+/-25%

+/-25%

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 2022 Annual Release Summary Batch Release Summary Liquid Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Number of Releases:

24 17 28 49 118 Total Time for All Releases (Minutes):

2153.0 1271.0 2117.0 4162.7 9703.7 Maximum Time for All Releases (Minutes):

312.0 104.0 115.0 166.7 312.0 Average Time for All Releases (Minutes):

89.7 74.8 75.6 85.0 82.2 Minimum Time for All Releases (Minutes):

66.0 38.0 54.0 52.0 38.0 Gaseous Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Number of Releases:

0 0

1 20 21 Total Time for All Releases (Minutes):

0.0 0.0 132480.0 22933.0 155413.0 Maximum Time for All Releases (Minutes):

0.0 0.0 132480.0 1440.0 132480.0 Average Time for All Releases (Minutes):

0.0 0.0 132480.0 1146.7 7400.6 Minimum Time for All Releases (Minutes):

0.0 0.0 132480.0 131.0 131.0 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 2022 Annual Release Summary Gaseous Effluents-Summation of All Releases Type of Effluent Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Total Error, %

A. Fission & Activation Gases

1. Total Release

2. Average Release Rate for Period

3. Percent of Applicable Limit Curies

µCi/sec 0.00E+00 0.00E+00 1.19E-03 2.00E-02 2.50E+01 0.00E+00 0.00E+00 1.50E-04 2.52E-03 0.00E+00 0.00E+00 4.22E-06 4.59E-05 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 0.00E+00 7.59E-07 2.50E+01

2. Average Release Rate for Period

µCi/sec 0.00E+00 0.00E+00 0.00E+00 9.55E-08

3. Percent of Applicable Limit 0.00E+00 0.00E+00 0.00E+00 1.61E-05

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 8.34E+00 8.52E+00 4.99E+00 1.83E+01 2.50E+01

2. Average Release Rate for Period

µCi/sec 1.07E+00 1.08E+00 6.27E-01 2.30E+00

3. Percent of Applicable Limit 1.53E-02 1.56E-02 9.17E-03 3.54E-02 E. Carbon-14

1. Total Release Curies 2.76E+00 2.80E+00 2.82E+00 2.39E+00 2.50E+01

Page 5 of 8 Prairie Island Nuclear Generating Station PI 2022 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 0.00E+00 6.38E-04 Kr-85 Curies 0.00E+00 0.00E+00 0.00E+00 9.44E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 Curies 0.00E+00 0.00E+00 0.00E+00 9.92E-03 0.00E+00 0.00E+00 1.17E-03 0.00E+00 Xe-133m Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.45E-05 0.00E+00 Xe-135 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.29E-06 0.00E+00 Total for Period Curies 0.00E+00 0.00E+00 0.00E+00 1.94E-02 0.00E+00 0.00E+00 1.19E-03 6.38E-04

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 0.00E+00 2.76E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 Curies 0.00E+00 0.00E+00 0.00E+00 4.61E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 Curies 0.00E+00 0.00E+00 0.00E+00 2.80E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Curies 0.00E+00 0.00E+00 0.00E+00 1.06E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 Curies 0.00E+00 0.00E+00 0.00E+00 2.88E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 Curies 0.00E+00 0.00E+00 0.00E+00 2.27E-08 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 7.59E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00

4.

Tritium H-3 Curies 8.34E+00 8.52E+00 4.98E+00 1.80E+01 0.00E+00 0.00E+00 3.99E-03 2.68E-01

5. Carbon-14 C-14 Curies 2.76E+00 2.80E+00 2.82E+00 2.39E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 6 of 8 Prairie Island Nuclear Generating Station PI 2022 Annual Release Summary Liquid Effluents - Summation of All Releases Type of Effluent Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Total Error, %

A. Fission & Activation Products

1. Total Release (not including Tritium, Curies 2.81E-03 4.88E-05 9.91E-05 5.04E-04 2.50E+01 Gases, and Alpha)

2. Average Diluted Concentration During

µCi/ml 3.74E-11 6.12E-13 1.36E-12 6.03E-12 Period

3. Percent of Applicable Limit 5.62E-02 9.75E-04 1.98E-03 1.01E-02 B. Tritium

1. Total Release

2. Average Diluted Concentration During Period Curies

µCi/ml 1.98E+02 1.22E+02 1.82E+02 3.08E+02 2.50E+01 2.64E-06 1.53E-06 2.49E-06 3.69E-06

3. Percent of Applicable Limit 2.64E-01 1.53E-01 2.49E-01 3.69E-01 C. Dissolved and Entrained Gases

1. Total Release Curies 1.88E-05 3.14E-05 9.67E-05 9.85E-05 2.50E+01

2. Average Diluted Concentration During Period

3. Percent of Applicable Limit

µCi/ml 2.51E-13 3.93E-13 1.32E-12 1.18E-12 1.25E-07 1.97E-07 6.62E-07 5.90E-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 3.38E+07 3.81E+07 3.07E+07 4.35E+07 2.50E+01 F. Volume of Dilution Water Used Liters 7.50E+10 7.97E+10 7.30E+10 8.35E+10 2.50E+01

Page 7 of 8 Prairie Island Nuclear Generating Station PI 2022 Annual Release Summary Liquid Effluents Continuous Mode Batch Mode Nuclides R Eleased 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 0.00E+00 0.00E+00 2.61E-06 0.00E+00 As-76 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.99E-06 Co-58 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.59E-05 5.18E-06 8.19E-06 4.19E-05 Co-60 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.38E-05 2.75E-05 5.25E-05 1.88E-05 Cr-51 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.11E-05 0.00E+00 0.00E+00 0.00E+00 Fe-55 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.85E-04 0.00E+00 0.00E+00 0.00E+00 H-3 Curies 2.45E-01 2.74E-01 3.31E-01 2.35E-01 1.98E+02 1.22E+02 1.81E+02 3.08E+02 Mn-54 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.42E-07 0.00E+00 0.00E+00 Nb-95 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.35E-06 Nb-97 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.03E-06 0.00E+00 0.00E+00 Sb-124 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.93E-06 0.00E+00 0.00E+00 0.00E+00 Sb-125 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.91E-03 1.40E-05 3.58E-05 2.04E-04 Te-123M Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.61E-06 4.61E-07 0.00E+00 2.21E-04 Te-132 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.49E-07 Xe-133 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.88E-05 3.14E-05 9.45E-05 9.59E-05 Xe-135 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.20E-06 2.53E-06 Zr-95 Curies 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.65E-06 2022 TOTAL Curies 2.45E-01 2.74E-01 3.31E-01 2.35E-01 1.98E+02 1.22E+02 1.81E+02 3.08E+02

Page 8 of 8 Prairie Island Nuclear Generating Station 2022 Annual Dose Summary Gaseous Effluents Parameter Location Dose Dose Limit

% of Limit Qtr 1 Gamma Air Dose (mrad) 0.58 km W 0.00E+00 1.00E+01 0.00 Beta Air Dose (mrad) 0.58 km W 0.00E+00 2.00E+01 0.00 Total Body Dose (mrem) 0.58 km W 0.00E+00 5.00E+00 0.00 Skin Dose (mrem) 0.58 km W 0.00E+00 1.50E+01 0.00 Max Organ Dose (mrem) 0.97 km SSE 2.29E-03 1.50E+01 0.02 Child - Liver Qtr 2 Gamma Air Dose (mrad) 0.58 km W 0.00E+00 1.00E+01 0.00 Beta Air Dose (mrad) 0.58 km W 0.00E+00 2.00E+01 0.00 Total Body Dose (mrem) 0.58 km W 0.00E+00 5.00E+00 0.00 Skin Dose (mrem) 0.58 km W 0.00E+00 1.50E+01 0.00 Max Organ Dose (mrem) 0.97 km SSE 2.56E-02 1.50E+01 0.17 Child - Bone Qtr 3 Gamma Air Dose (mrad) 0.58 km W 2.88E-07 1.00E+01 0.00 Beta Air Dose (mrad) 0.58 km W 8.44E-07 2.00E+01 0.00 Total Body Dose (mrem) 0.58 km W 2.41E-07 5.00E+00 0.00 Skin Dose (mrem) 0.58 km W 5.74E-07 1.50E+01 0.00 Max Organ Dose (mrem) 0.97 km SSE 3.85E-02 1.50E+01 0.26 Child - Bone Qtr 4 Gamma Air Dose (mrad) 0.58 km W 4.59E-06 1.00E+01 0.00 Beta Air Dose (mrad) 0.58 km W 6.42E-06 2.00E+01 0.00 Total Body Dose (mrem) 0.58 km W 4.29E-06 5.00E+00 0.00 Skin Dose (mrem) 0.58 km W 8.93E-06 1.50E+01 0.00 Max Organ Dose (mrem) 0.97 km SSE 5.31E-03 1.50E+01 0.04 Child - Kidney Year Gamma Air Dose (mrad) 0.58 km W 4.88E-06 2.00E+01 0.00 Beta Air Dose (mrad) 0.58 km W 7.26E-06 4.00E+01 0.00 Total Body Dose (mrem) 0.58 km W 4.53E-06 1.00E+01 0.00 Skin Dose (mrem) 0.58 km W 9.50E-06 3.00E+01 0.00 Max Organ Dose (mrem) 0.97 km SSE 6.41E-02 3.00E+01 0.21 Child - Bone Liquid Effluents Parameter Max Receptor Dose Dose Limit

% of Limit Qtr 1 Max Organ Dose (mrem)

Adult - Lung 5.48E-04 1.00E+01 0.01 Total Body Dose (mrem)

Adult - Total Body 5.35E-04 3.00E+00 0.02 Qtr 2 Max Organ Dose (mrem)

Adult - Gi-LLi 5.08E-04 1.00E+01 0.01 Total Body Dose (mrem)

Adult - Total Body 5.07E-04 3.00E+00 0.02 Qtr 3 Max Organ Dose (mrem)

Adult - Gi-LLi 3.67E-04 1.00E+01 0.00 Total Body Dose (mrem)

Adult - Total Body 3.64E-04 3.00E+00 0.01 Qtr 4 Max Organ Dose (mrem)

Adult - Gi-LLi 1.16E-03 1.00E+01 0.01 Total Body Dose (mrem)

Adult - Total Body 1.17E-03 3.00E+00 0.04 Year Max Organ Dose (mrem)

Adult - Lung 2.57E-03 2.00E+01 0.01 Total Body Dose (mrem)

Adult - Total Body 2.57E-03 6.00E+00 0.04