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| number = ML17130A969
| number = ML17130A969
| issue date = 05/08/2017
| issue date = 05/08/2017
| title = Prairie Island, Units 1 and 2, Submittal of 2016 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual
| title = Submittal of 2016 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual
| author name = Northard S
| author name = Northard S
| author affiliation = Northern States Power Company, Minnesota, Xcel Energy
| author affiliation = Northern States Power Company, Minnesota, Xcel Energy
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:1717 Wakonade Drive Welch, MN 55089 800.895.4999 xcelenergy.com MAY 0 8 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Prairie Island Nuclear Generating Plant, Units 1 and 2 Docket Nos. 50-282 and 50-306 Renewed Operating License Nos. DPR-42 and DPR-60 (},, Xcel Energy* R ES P 0 NS I B LE B Y NAT U R E L-Pl-17-018 TS 5.5.1.c TS 5.6.3 2016 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"),
{{#Wiki_filter:1717 Wakonade Drive Welch, MN 55089
submits the 2016 Annual Radioactive Effluent Report which is comprised of the following:
(},, Xcel Energy*
Enclosure 1 contains the Off-Site Radiation Dose Assessment for the period January 1, 2016, through December 31, 2016, in accordance with ODCM sections 8.1.1c, d, e, f, g, h, i, j, k, m and n. ' Enclosure 2 contains the Annual Radioactive Effluent Report, Supplemental Information, for the period January 1, 2016, through December 31, 2016, in accordance with TS 5.6.3 and ODCM section 8.1.1 b. Enclosure 3 contains a complete and legible copy of the entire ODCM revision 30, issued on 2/27 /2016, in accordance with ODCM section 8.1.11. Enclosure 4 contains a complete and legible copy of the entire ODCM revision 31, issued on 10/13/2016, in accordance with ODCM section 8.1.11. On May 4, 2016, PINGP identified a potential issue regarding the operability of the Waste Gas Holdup System Gas (Oxygen)
R ES P 0 NS I B LE B Y NAT U R E 800.895.4999 xcelenergy.com L-Pl-17-018 MAY 0 8 2017                                                           TS 5.5.1.c TS 5.6.3 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Prairie Island Nuclear Generating Plant, Units 1 and 2 Docket Nos. 50-282 and 50-306 Renewed Operating License Nos. DPR-42 and DPR-60 2016 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"),
Monitors listed in ODCM Table 3.2. This issue has been entered into the PINGP Corrective Action Program for evaluation.
submits the 2016 Annual Radioactive Effluent Report which is comprised of the following: contains the Off-Site Radiation Dose Assessment for the period January 1, 2016, through December 31, 2016, in accordance with ODCM sections 8.1.1c, d, e, f, g, h, i, j, k, m and n.
Evaluation identified errata data for 2014 and 2015 Annual Radioactive Effluent  
                            ' contains the Annual Radioactive Effluent Report, Supplemental Information, for the period January 1, 2016, through December 31, 2016, in accordance with TS 5.6.3 and ODCM section 8.1.1 b. contains a complete and legible copy of the entire ODCM revision 30, issued on 2/27/2016, in accordance with ODCM section 8.1.11. contains a complete and legible copy of the entire ODCM revision 31, issued on 10/13/2016, in accordance with ODCM section 8.1.11.
: Reports, in the form of omission of reporting of operability, in accordance with ODCM section 8.1.1 h. The errata data is reported with this submittal and in accordance with ODCM section 8.7 guidance for reporting of errata data.
On May 4, 2016, PINGP identified a potential issue regarding the operability of the Waste Gas Holdup System Gas (Oxygen) Monitors listed in ODCM Table 3.2. This issue has been entered into the PINGP Corrective Action Program for evaluation. Evaluation identified errata data for 2014 and 2015 Annual Radioactive Effluent Reports, in the form of omission of reporting of operability, in accordance with ODCM section 8.1.1 h. The errata data is reported with this submittal and in accordance with ODCM section 8.7 guidance for reporting of errata data.
* Document Control Desk Page 2 Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
* Document Control Desk Page 2 Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
Scott Northard Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company -Minnesota Enclosures (4) cc: Regional Administrator, USNRC, Region Ill Project Manager, Prairie Island Nuclear Generating Plant, USN RC, NRR NRC Resident Inspector  
&ritJ~
-Prairie Island Nuclear Generating Plant Department of Health, State of Minnesota Pl Dakota Community Environmental Coordinator ENCLOSURE 1 OFF-SITE RADIATION DOSE ASSESSMENT January 1, 2016 -December 31, 2016 7 pages to follow PRAIRIE ISLAND NUCLEAR GENERA TING PLANT OFF-SITE RADIATION DOSE ASSESSMENT FOR January 1, 2016-December31, 2016 Page 1of7 An Assessment of the radiation dose due to releases from Prairie Island Nuclear Generating Plant during 2016 was performed, in accordance with the Offsite Dose Calculation Manual, arid as required by Technical Specifications.
Scott Northard Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (4) cc:   Regional Administrator, USNRC, Region Ill Project Manager, Prairie Island Nuclear Generating Plant, USN RC, NRR NRC Resident Inspector - Prairie Island Nuclear Generating Plant Department of Health, State of Minnesota Pl Dakota Community Environmental Coordinator
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.
ENCLOSURE 1 OFF-SITE RADIATION DOSE ASSESSMENT January 1, 2016 - December 31, 2016 7 pages to follow
Source terms were obtained from the Annual Radioactive Effluent and Waste Disposal Report and prepared for NRG review, for the. year of 2016. OFFSITE DOSES FROM GASEOUS RELEASE:
 
Page 1of7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFF-SITE RADIATION DOSE ASSESSMENT FOR January 1, 2016- December31, 2016 An Assessment of the radiation dose due to releases from Prairie Island Nuclear Generating Plant during 2016 was performed, in accordance with the Offsite Dose Calculation Manual, arid 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 NRG review, for the. year of 2016.
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.
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:
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.
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:  
DOSES TO INDIVIDUALS DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY:
*
*
* Occasionally sportsmen enter the Prairie Island Site Boundary for recreational activities.
* Occasionally sportsmen enter the Prairie Island Site Boundary for recreational activities.
These individuals are not expeded to spend more than a few hours per year within the site boundary.
These individuals are not expeded 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 dose from noble gas releases and the whole body and 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.
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 dose from noble gas releases and the whole body and 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.
* Critical Receptor location and pathways for organ doses are reported in Table 2.
Page 2of7 ABNORMAL RELEASES  
 
*There were no (0) abnormal releases for 2016. 40 CFR 190 COMPLIANCE REMP environmental TLD results for 2016 were reviewed  
Page 2of7 ABNORMAL RELEASES
'perANSl/HPS N13.37-2014 methodology for determining any plant effect above ambient gamma radiation measurements.
*There were no (0) abnormal releases for 2016.
All measurements considered to be within the range of variations in natural background radiation.
40 CFR 190 COMPLIANCE REMP environmental TLD results for 2016 were reviewed 'perANSl/HPS N13.37-2014 methodology for determining any plant effect above ambient gamma radiation measurements. All measurements ar~ considered to be within the range of variations in natural background radiation.
Neutron sky shine dose from the ISFSI was evaluated.
Neutron sky shine dose from the ISFSI was evaluated. The maximum sky shine dose was determined to be 0.71 mrem; to the nearest resident, at 724 meters from the ISFS(
The maximum sky shine dose was determined to be 0.71 mrem; to the nearest resident, at 724 meters from the ISFS( Neutron sky shine dose is greater than the effluent dose to the Critical  
Neutron sky shine dose is greater than the effluent dose to the Critical Receptor, therefore, 40 CFR 190 compliance was evaluated to the location of the maximum neutron sky shine dose.
: Receptor, therefore, 40 CFR 190 compliance was evaluated to the location of the maximum neutron sky shine dose. The 40CFR190 evaluation location was determined to be 0.7 miles west ofthe plant. Dose due to gaseous effluents were calculated to the 40 CFR 190 evaluation location.
The 40CFR190 evaluation location was determined to be 0.7 miles west ofthe plant.
Gamma Direct Radiation Dose: Neutron sky shine Dose: Garrima Air Dose: Beta Air Dose: lodrne, particulate, H-3 and C-14 Dose: O.OOE+OO MREM 7.10E-01 MREM 2.0SE-12 MREM 1.37E-11 MREM 1.04E-02 MREM* *Calculated values identical for Whole Body, Thyroid and Maximum "Other" Organs 40CFR190 DOSE EVALUATION:
Dose due to gaseous effluents were calculated to the 40 CFR 190 evaluation location.
40CFR190 LIMIT 40CFR 190 DOSE " (MREM) (MREM) WHOLE BODY 25 7.20E-01 THYROID 75 7.20E-01 OTHER ORGANS 25 7.20E-01 (TEEN -WHOLE BODY) I . SAMPLING, ANALYSIS AND LLD REQUIREMENTS The lower limit of detection (LLD) requirements, as specified in ODCM Table 2.11 and 3.1 were met for 2016. The minimum sampling frequency requirements, as specified in ODCM Table 2.1 and 3.1 were met for 2016.
Gamma Direct Radiation Dose:             O.OOE+OO MREM Neutron sky shine Dose:                 7.10E-01 MREM Garrima Air Dose:                       2.0SE-12 MREM Beta Air Dose:                           1.37E-11 MREM lodrne, particulate, H-3 and C-14 Dose:   1.04E-02 MREM*
.Page 3 of 7 . MONITORING INSTRUMENTATION For 2016, 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. From 1/24/16 to 4/14/16, less than the minimum channels required for Explosive Gas Monitoring Instrumentation were available, as specified in H4, Offsite Dose Calculation Manual. Special Report L-16-058 was submitted to NRG on July22, 2016. An apparent cause evaluation was initiated.
*Calculated values identical for Whole Body, Thyroid and Maximum "Other" Organs 40CFR190 DOSE EVALUATION:
. . .
40CFR190 LIMIT                 40CFR 190 DOSE (MREM)                           (MREM)
* The apparent cause evaluation found that a lack of clarity between the ODCM, Administrative Work 1.nstructions and Operations Procedures was the cause. Actions were initiated to clarify requirements.
WHOLE BODY               "                                              7.20E-01 25 THYROID                                   75                           7.20E-01 OTHER ORGANS                             25                           7.20E-01 (TEEN - WHOLE BODY)
DOSES TO INDIVIDUALS DUE TO EFFLUENT RELEASES FROM THE INDEPENDENT SPENT FUEL STORAGE FACILITY (ISFSI):
I                                 .
Zero (0) fuel casks were loaded and placed in the storage facility during the 2016 calendar year. The total number of casks in the ISFSI, as of 12/31/16, was forty (40) . . There were no (0) releases of radioactive effluents from the ISFSI. CURRENT OFFSITE DOSE CALCULATIONS MANUAL (ODCM) REVISION:
SAMPLING, ANALYSIS AND LLD REQUIREMENTS The lower limit of detection (LLD) requirements, as specified in ODCM Table 2.11 and 3.1 were met for 2016. The minimum sampling frequency requirements, as specified in ODCM Table 2.1 and 3.1 were met for 2016.
 
                                                                                    .Page 3 of 7
. MONITORING INSTRUMENTATION For 2016, 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.
From 1/24/16 to 4/14/16, less than the minimum channels required for Explosive Gas Monitoring Instrumentation were available, as specified in H4, Offsite Dose Calculation Manual.
Special Report L-16-058 was submitted to NRG on July22, 2016. An apparent cause evaluation was initiated.
* The apparent cause evaluation found that a lack of clarity between the ODCM, Administrative Work 1.nstructions and Operations Procedures was the cause.
Actions were initiated to clarify requirements.
DOSES TO INDIVIDUALS DUE TO EFFLUENT RELEASES                                 FROM     THE INDEPENDENT SPENT FUEL STORAGE FACILITY (ISFSI):
Zero (0) fuel casks were loaded and placed in the storage facility during the 2016 calendar year. The total number of casks in the ISFSI, as of 12/31/16, was forty (40) .
. There were no (0) releases of radioactive effluents from the ISFSI.
CURRENT OFFSITE DOSE CALCULATIONS MANUAL (ODCM) REVISION:
The Offsite Dose Calculation Manual was revised two (2) times in 2016. Revision 30 is dated February 27, 2016. Revision 31 is dated October 13, 2016. Both revisions are
The Offsite Dose Calculation Manual was revised two (2) times in 2016. Revision 30 is dated February 27, 2016. Revision 31 is dated October 13, 2016. Both revisions are
* submitted with this report: CRITICAL RECEPTOR Based on the Annual Land Use Census*,
* submitted with this report:
the critical receptor did change. The critical receptor is defined as The Suter Residence, at 0.6 miles, in fhe SSE sector. 2016 is evaluated using the Critical Receptor identification of the Glazier Residence,.
CRITICAL RECEPTOR Based on the Annual Land Use Census*, the critical receptor did change. The critical receptor is defined as The Suter Residence, at 0.6 miles, in fhe SSE sector.
at 0.6 miles in the NNW sector. 2017 will .be evaluated using the newly identified Critical Receptor identification of the Suter Residence, at 0.6 miles in the SSE direction.
2016 is evaluated using the Critical Receptor identification of the Glazier Residence,. at 0.6 miles in the NNW sector.
. Page 4of7 ERRATA DATA: For 2014, 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. For 2015, there was one (1) occurrence, when less than the minimum reqLJired radioactive liquid and/or gaseous effluent monitoring instrumentation channels were operable, as required by ODCM Tables 2.2 and 3.2. These out of service periods were incorrectly omitted from their respective annual reports.
2017 will .be evaluated using the newly identified Critical Receptor identification of the Suter Residence, at 0.6 miles in the SSE direction.
From 9/25/14 to 10/26/14 and from 7/12/15 to 8/18/15, less than the minimum channels required for Explosive Gas Monitoring Instrumentation were available, as specified in H4, Offsite Dose Calculation Manual. Special Report L-16-058 was submitted to NRC on July 22, 2016. An apparent cause evaluation was initiated.
 
The apparent cause evaluation found that a lack of clarity between the ODCM, Administrative Work Instructions and Operations Procedures was the cause. Actions were initiated to clarify requirements.
                                                                              . Page 4of7 ERRATA DATA:
* ERRATA DATA: The volume fdr the geometry employed in the evaluation of noble gas samples was
For 2014, ~here was one (1) occurrence, when less than the minimum required radioactive liquid and/or gaseous effluent monitoring instrumentation channels were
* inaccurate.
.operable, as required by ODCM Tables 2.2 and 3.2.
This value is canned in the software and the inaccuracy went undetected for an extended period of time.
For 2015, there was one (1) occurrence, when less than the minimum reqLJired radioactive liquid and/or gaseous effluent monitoring instrumentation channels were operable, as required by ODCM Tables 2.2 and 3.2.
These out of service periods were incorrectly omitted from their respective annual reports.
From 9/25/14 to 10/26/14 and from 7/12/15 to 8/18/15, less than the minimum channels required for Explosive Gas Monitoring Instrumentation were available, as specified in H4, Offsite Dose Calculation Manual.
Special Report L-16-058 was submitted to NRC on July 22, 2016. An apparent cause evaluation was initiated.
The apparent cause evaluation found that a lack of clarity between the ODCM, Administrative Work Instructions and Operations Procedures was the cause.
Actions were initiated to clarify requirements.
* ERRATA DATA:
The volume fdr the geometry employed in the evaluation of noble gas samples was
* inaccurate. This value is canned in the software and the inaccuracy went undetected for an extended period of time.
* The inaccuracy would have generated results with a conservatively high bias. No underreporting occurred.
* The inaccuracy would have generated results with a conservatively high bias. No underreporting occurred.
Inaccurate reporting of dose equated to significantly less than 1 % of the applicable 10 CFR 50 Appendix I design objectives and significantly less than 1 % of the EPA public dose criterion.
Inaccurate reporting of dose equated to significantly less than 1% of the applicable 10 CFR 50 Appendix I design objectives and significantly less than 1% of the EPA public dose criterion. Over reporting did NOT impede Prairie Island's ability to adequately assess the information supplied.
Over reporting did NOT impede Prairie Island's ability to adequately assess the information supplied.
Corrective actions have been implemented.
Corrective actions have been implemented.
INDUSTRY INITIATIVE ON GROUND WATER PROTECTION:
INDUSTRY INITIATIVE ON GROUND WATER PROTECTION:
There was zero (0) events for inclusion in the Annual Effluent Report, as part of the NEI Ground Water Initiative.
There was zero (0) events for inclusion in the Annual Effluent Report, as part of the NEI Ground Water Initiative.
Page 5of7 LOW LEVEL WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED COMPONENTS SHIPMENTS PERIOD: 1/1/16 TO 12/31/16 LICENSE NUMBER: DPR-42/60 SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL): Resins, Filters and Volume Evaporator Bottoms Waste Class FT3 . M3 A 2.91E+02 8.25E+OO B 4.37E+02 1.24E+01 c O.OOE+OO O.OOE+OO ALL 7.29E+02 2.06E+01 Major Nuclides.
 
H-3, Mn-54, Fe-55, Co-57, Co-58, Co-60, Ni-63, Sb-125, Cs-137 Dry Active Waste Volume Waste Class FT3 M3 A 2.82E+04 7.97E+02 8 O.OOE+OO O.OOE+OO c O.OOE+OO O.OOE+OO ALL 2.82E+04 7.97E+02 Major Nuclides Fe-55, Co-58, Co-60,.Ni-63, Zr-95, Nb-95 Irradiated Components Volume Waste Class FT3 M3 A O.OOE+OO O.OOE+OO 8 O.OOE+OO O.OOE+OO c O.OOE+OO O.OOE+OO ALL O.OOE+OO O.OOE+OO Major Nuclides Other Waste Volume Waste Class FT3 M3 A O.OOE+OO O.OOE+OO 8 O.OOE+OO O.OOE+OO c O.OOE+OO O.OOE+OO ALL O.OOE+OO O.OOE+OO Major Nuclides Sum of All Low Level Waste Volume Shipped from Site Waste Class FT3 M3 A 2.85E+04 8.06E+02 8 4.37E+02 1.24E+01 c O.OOE+OO O.OOE+OO ALL 2.89E+04 8.18E+02 Major Nuclides Mn-54, Fe-55, Co-58, Co-60, Ni-63, Zr-95, Nb-95, Sb-125, Cs-137 PROCESS CONTROL PROGRAM Curies Shipped Curies 1.93E-01 2.00E+02 O.OOE+OO 2.00E+02 Curies Shipped Curies 2.76E-01 O.OOE+OO O.OOE+OO 2.76E-01 Curies Shipped Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Curies Shipped Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Curies Shipped Curies 4.68E-01 2.00E+02 O.OOE+OO 2.00E+02 The Process Control Program for Solidification/Dewatering of Radioactive Waste from Liquid Systems (D 59) was not revised in 2016. Current manual revision is 11. The revision date is October 23, 2014. Revision 11 was submitted with the 2014 report.
Page 5of7 LOW LEVEL WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED COMPONENTS SHIPMENTS PERIOD: 1/1/16 TO 12/31/16 LICENSE NUMBER: DPR-42/60 SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL):
Page 6of7 Table 1 OFF-SITE RADIATION DOSE ASSESSMENT  
Resins, Filters and                                   Volume                                     Curies Shipped Evaporator Bottoms Waste Class                             FT3                           . M3                           Curies A                         2.91E+02                         8.25E+OO                       1.93E-01 B                         4.37E+02                         1.24E+01                       2.00E+02 c                         O.OOE+OO                         O.OOE+OO                        O.OOE+OO ALL                       7.29E+02                         2.06E+01                       2.00E+02 Major Nuclides.           H-3, Mn-54, Fe-55, Co-57, Co-58, Co-60, Ni-63, Sb-125, Cs-137 Dry Active Waste                                     Volume                                     Curies Shipped Waste Class                             FT3                             M3                           Curies A                         2.82E+04                         7.97E+02                       2.76E-01 8                         O.OOE+OO                        O.OOE+OO                       O.OOE+OO c                         O.OOE+OO                        O.OOE+OO                       O.OOE+OO ALL                       2.82E+04                         7.97E+02                       2.76E-01 Major Nuclides             Fe-55, Co-58, Co-60,.Ni-63, Zr-95, Nb-95 Irradiated Components                                 Volume                                     Curies Shipped Waste Class                             FT3                               M3                           Curies A                         O.OOE+OO                         O.OOE+OO                      O.OOE+OO 8                         O.OOE+OO                         O.OOE+OO                      O.OOE+OO c                         O.OOE+OO                         O.OOE+OO                      O.OOE+OO ALL                       O.OOE+OO                        O.OOE+OO                       O.OOE+OO Major Nuclides Other Waste                                           Volume                                     Curies Shipped Waste Class                             FT3                               M3                         Curies A                         O.OOE+OO                         O.OOE+OO                      O.OOE+OO 8                         O.OOE+OO                        O.OOE+OO                       O.OOE+OO c                         O.OOE+OO                         O.OOE+OO                      O.OOE+OO ALL                       O.OOE+OO                         O.OOE+OO                      O.OOE+OO Major Nuclides Sum of All Low Level Waste                           Volume                                     Curies Shipped Shipped from Site Waste Class                             FT3                             M3                           Curies A                         2.85E+04                         8.06E+02                       4.68E-01 8                         4.37E+02                         1.24E+01                       2.00E+02 c                         O.OOE+OO                        O.OOE+OO                       O.OOE+OO ALL                       2.89E+04                         8.18E+02                      2.00E+02 Major Nuclides             Mn-54, Fe-55, Co-58, Co-60, Ni-63, Zr-95, Nb-95, Sb-125, Cs-137 PROCESS CONTROL PROGRAM The Process Control Program for Solidification/Dewatering of Radioactive Waste from Liquid Systems (D 59) was not revised in 2016. Current manual revision is 11. The revision date is October 23, 2014. Revision 11 was submitted with the 2014 report.
-PRAIRIE ISLAND PERIOD: JANUARY 2016 through DECEMBER 2016. Gaseous Releases Maximum Site Boundary Gamma Air Dose (mrad} Maximum Site Boundary Beta Air Dose (mrad) Maximum Off-site Dose to any Organ (mrem}* Organ:. Offshore Location Gamma Dose (mrad} Total Body-(mrem) Maximum Off-site Dose to any Organ (mrem)* Organ: Liquid Releases Maximum Off-site Dose Total Body (mrem) Maximum Off-site Dose to any Organ (mrem) Organ 2.48E-05 1.65E-04 8.03E-02 Child -bone 4.97E-07 4.15E-07 6.90E-03 Teen -Lung 1.64E-03 10 CFR Part 50 Appendix I Guidelines (2-unit site per year) 20 40 30 20 10 30 .6 2.13E-03 Adult -Gi-LLi 20
 
* Long-Lived Particulate, 1-131, 1-133, Tritium and C-14 Page 7of7 Table 2 OFF-SITE RADIATION DOSE ASSESSMENT  
Page 6of7 Table 1 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND PERIOD: JANUARY 2016 through DECEMBER 2016.
-PRAIRIE ISLAND SUPPLEMENTAL INFORMATION January 1, 2016 -December 31, 2016 Gaseous Releases Maximum Site Boundary Dose Location (From Building Vents) Sector Distance (miles) Offshore Location Within Site Boundary Sector Distance (miles) Pathway Maximum Off-site Sector Distance (miles) Pathways Age Group Liquid Releases  
10 CFR Part 50 Appendix I Guidelines (2-unit site per year)
. . Maximum Off-site Dose Location Downstream Pathway w 0.36 ESE 0.2 Inhalation NNW 0.60 Ground, Inhalation Vegetable Child Fish ENCLOSURE 2 ANNUAL RADIOACTIVE EFFLUENT REPORT SUPPLEMENTAL INFORMATION January 1, 2016 -December 31, 2016 8 pages to follow ANNUAL RADIOACTIVE EFFLUENT REPORT 01-JAN-16 THROUGH 31-DEC-16 SUPPLEMENTAL INFORMATION Facility:
Gaseous Releases Maximum Site Boundary Gamma Air Dose (mrad}                 2.48E-05                  20 Maximum Site Boundary Beta Air Dose (mrad)                 1.65E-04                  40 Maximum Off-site Dose to any Organ (mrem}*                   8.03E-02                  30 Organ:.                               Child - bone Offshore Location Gamma Dose (mrad}                   4.97E-07                    20 Total Body- (mrem)                 4.15E-07                    10 Maximum Off-site Dose to any Organ (mrem)*               6.90E-03                    30 Organ:                             Teen -Lung Liquid Releases Maximum Off-site Dose Total Body     (mrem)               1.64E-03                    .6 Maximum Off-site Dose to any Organ (mrem)                   2.13E-03                   20 Organ                                Adult - Gi-LLi
Prairie Island Nuclear Generating Plant Licensee:
* Long-Lived Particulate, 1-131, 1-133, Tritium and C-14
Northern States Power Company License Numbers:
 
DPR-42 & DPR-60 A. Regulatory Limits i. Liquid Effluents:  
Page 7of7 Table 2 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND SUPPLEMENTAL INFORMATION January 1, 2016 - December 31, 2016 Gaseous Releases Maximum Site Boundary Dose Location (From Building Vents)
: 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 for the year 2. Gaseous Effluents:
Sector                               w Distance (miles)                     0.36 Offshore Location Within Site Boundary Sector                               ESE Distance (miles)                   0.2 Pathway                             Inhalation Maximum Off-site Sector                               NNW Distance (miles)                     0.60 Pathways                             Ground, Inhalation Vegetable Age Group                           Child Liquid Releases .
3.0 mrem to the total body 10.0 mrem to any organ 6.0 mrem to the total body 20.0 mrem to any organ 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 $1500 mrem/year to any organ b. The dose due to radioactive gaseous effluents released from the site shall be limited to: noble gases I-131, I-133,.H-3, LLP $10 mrad/quarter gamma $20 mrad/quarter beta $20 mrad/year gamma $40 mrad/year beta $15 mrem/quarter to any organ $30 mrem/year to any organ Page 1 of 8 B. Effluent Concentration  
. Maximum Off-site Dose Location Downstream Pathway                             Fish
 
ENCLOSURE 2 ANNUAL RADIOACTIVE EFFLUENT REPORT SUPPLEMENTAL INFORMATION January 1, 2016 - December 31, 2016 8 pages to follow
 
Page 1 of 8 ANNUAL RADIOACTIVE EFFLUENT REPORT 01-JAN-16 THROUGH 31-DEC-16 SUPPLEMENTAL INFORMATION Facility:         Prairie Island Nuclear Generating Plant Licensee:       Northern States Power Company License Numbers: DPR-42 & DPR-60 A. Regulatory Limits
: i. 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   $1500 mrem/year to any organ
: b. The dose due to radioactive gaseous effluents released from the site shall be limited to:
noble gases               $10 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
                                      $30 mrem/year to any organ
 
Page 2 of 8.
B. Effluent Concentration
: 1. Fission and activation gases in gaseous releas.es:
: 1. Fission and activation gases in gaseous releas.es:
10 CFR 20, Appendix B, Table 2, Column 1 2. Iodine and particulates with half lives greater than 8 days in gaseous releas.es  
10 CFR 20, Appendix B, Table 2, Column 1
: 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: 2.0E-04 uCi/ml Total Activity C. Average Energy Not applicable to Prairie Island regulatory limits. D. Measurements and approximations of total activity  
: 2. Iodine and particulates with half lives greater than 8 days in gaseous releas.es :
: 1. Fission and activation gases Total Gem in gaseous releases:
10 CFR 20, Appendix B, Table 2, Column 1
Nuclide Gem 2. Iodines in gaseous releases:
: 3. Liquid effluents for radionuclides other than dissolved or entrained gases:
Total Gem Nuclide Gem 3. Particulates in gaseous releases:
10 CFR 20, Appendix B., Table 2, Column 2
Total Gem Nuclide Gem 4. Liquid effluents Total Gem Nuclide Gem E. Manual Revisions  
: 4. Liquid effluent dissolved and entrained gases:
: 1. Offsite Dose Calculations Manual: Latest Revision number: 31 Revision date October 13, 2016 Page 2 of 8. +/-25% +/-25% +/-25% +/-25%
2.0E-04 uCi/ml Total Activity C. Average Energy Not applicable to Prairie Island regulatory limits.
Liquid Releases Total Time for All Maximum Time for All Average Time for All Minimum Time for All Gaseous Releases Total Time for All Maximum Time for All Average Time for All Minimum Time for All Liquid Releases Number of Total Activity for Gaseous Releases Number of Total Activity for Prairie Island Nuclear Generating Station 2016 Annual. Release Summary Batch Release Surnniary Qtr 1 Qtr 2 Number of Releases:
D. Measurements and approximations of total activity
21 21 Releases (Minutes):
: 1. Fission and activation gases         Total     Gem +/-25%
1607.0 1624. 0 Releases (Minutes):
in gaseous releases:                 Nuclide   Gem
117. 0 103.0 Releases (Minutes):
: 2. Iodines in gaseous releases:         Total     Gem +/-25%
76.5 77.3 Releases (Minutes):
Nuclide   Gem
50.0 62. 0 Qtr 1 Qtr 2 Number of Releases:
: 3. Particulates in gaseous releases:     Total     Gem +/-25%
65 5 Releases (Minutes):
Nuclide   Gem
90055.0 1070.0 Releases (Minutes):
: 4. Liquid effluents                     Total     Gem  +/-25%
1440.0 300.0 Releases (Minutes):
Nuclide  Gem E. Manual Revisions
1385.5 214.0 Releases (Minutes):  
: 1. Offsite Dose Calculations Manual:
: 71. 0 71. 0 Abnormal Release Summary Abnormal Releases:
Latest Revision number:   31 Revision date             October 13, 2016
0 Abnormal Releases:
 
O.OOE+OO Curies Abnormal Releases:
Page 3 of 8 Prairie Island Nuclear Generating Station 2016 Annual. Release Summary Batch Release Surnniary Liquid Releases                                                Qtr 1      Qtr 2    Qtr 3      Qtr 4      Year Number of Releases:              21            21    35        48      125 Total Time for All Releases (Minutes):        1607.0      1624. 0  2516.0  4156.0    9903.0 Maximum Time for All Releases (Minutes):          117. 0      103.0    -89.0      140.0    140.0 Average Time for All Releases (Minutes):            76.5        77.3    71. 9      86.6      79.2 Minimum Time for All Releases (Minutes):            50.0        62. 0  61. 0      63.0      50.0 Gaseous Releases                                              Qtr 1       Qtr 2   Qtr 3      Qtr 4    Year Number of Releases:             65            5      1  c*    18        89 Total  Time  for All Releases (Minutes):       90055.0      1070.0     60.0 21472.0   112657.0 Maximum  Time  for All Releases (Minutes):         1440.0        300.0     60.0   1660.0     1660.0 Average  Time  for All Releases (Minutes):         1385.5        214.0     60.0   1192.9    12 65. 8.
0 Abnormal Releases:
Minimum  Time  for All Releases (Minutes):           71. 0       71. 0  60.0      220.0      60.0 Abnormal Release Summary Liquid Releases Number of Abnormal Releases:                 0 Total Activity for Abnormal Releases:         O.OOE+OO Curies Gaseous Releases Number of Abnormal Releases:                   0 Total Activity for Abnormal Releases:         O.OOE+OO Curies
O.OOE+OO Curies Page 3 of 8 Qtr 3 Qtr 4 Year 35 48 125 2516.0 4156.0 9903.0 -89.0 140.0 140.0 71. 9 86.6 79.2 61. 0 63.0 50.0 Qtr 3 Qtr 4 Year 1 c* 18 89 60.0 21472.0 112657.0 60.0 1660.0 1660.0 60.0 1192.9 12 65. 8. 60.0 220.0 60.0 Prairie Island Nuclear Generating Station 2016 Annual Release Summary Gaseous Effluents-Sununation of All Releases Type of Effluent Units Qtr l Qtr 2 A. Fission & Activation Gases 1. Total Release Curies 9.42E-04 5.00E-'04
 
: 2. Average Release Rate for Period µCi/sec 1. 20E-04 6.35E-05
Page 4 of 8 Prairie Island Nuclear Generating Station 2016 Annual Release Summary Gaseous Effluents-Sununation of All Releases Est. Tota)-
: 3. Percent of Applicable Limit % 2.65E-05 l.39E-05 B. Iodines 1. Total Iodine-131 Curies O.OOE+OO O.OOE+OO  
Type of Effluent                                      Units    Qtr l    Qtr 2    Qtr 3     Qtr 4   Error, .%
: 2. Average Release Rate for Period µCi/sec O.OOE+OO O.OOE+OO  
A. Fission & Activation Gases
: 3. Percent of Applicable Limit % O.OOE+OO O.OOE+OO
: 1. Total Release                                  Curies  9.42E-04  5.00E-'04 3.88E-02 O.OOE+OO  2.SOE+Ol
: c. Particulates
: 2. Average Release Rate for Period              µCi/sec  1. 20E-04 6.35E-05  4.89E-03 0.00E+OO
: 1. Total Particulates (Half-lives
: 3. Percent of Applicable Limit                      %      2.65E-05  l.39E-05  7.87E-04 O.OOE+OO B. Iodines
> 8 days) Curies O.OOE+OO O.OOE+OO
: 1. Total Iodine-131                              Curies  O.OOE+OO  O.OOE+OO  O.OOE+OO 2.09E-07  2.50E+Ol
: 2. Average Release Rate for Period µCi/sec O.OOE+OO O.OOE+OO  
: 2. Average Release Rate for Period               µCi/sec   O.OOE+OO  O.OOE+OO  O.OOE+OO 2.62E-08
: 3. Percent of Applicable.
: 3. Percent of Applicable Limit                     %     O.OOE+OO  O.OOE+OO O.OOE+OO 2.09E-05
Limit % 0.00E+OO O.OOE+OO  
: c. Particulates
: 4. Gross Alpha Activity Curies O.OOE+OO O.OOE+OO D. Tritium 1. Total Release Curies 5.13E+OO 5.51E+OO  
: 1. Total Particulates (Half-lives > 8 days)      Curies  O.OOE+OO O.OOE+OO O.OOE+OO 2.42E-06  2.50E+Ol
: 2. Average Release Rate for Period µCi/sec 6.52E-01 7.0lE-01  
: 2. Average Release Rate for Period               µCi/sec   O.OOE+OO O.OOE+OO  O.OOE+OO 3.04E-07
: 3. Percent of Applicable Limit % 3.64E-02 3.83E-02 E. carbon-14  
: 3. Percent of Applicable. Limit                     %     0.00E+OO O.OOE+OO  O.OOE+OO 2.46E-05
: 1. Total Release Curies 2.02E+OO 2.89E+OO Page 4 of 8 Est. Tota)-Qtr 3 Qtr 4 Error, .% 3.88E-02 O.OOE+OO 2.SOE+Ol 4.89E-03 0.00E+OO 7.87E-04 O.OOE+OO O.OOE+OO 2.09E-07 2.50E+Ol O.OOE+OO 2.62E-08 O.OOE+OO 2.09E-05 O.OOE+OO 2.42E-06 2.50E+Ol O.OOE+OO 3.04E-07 O.OOE+OO 2.46E-05 O.OOE+OO O.OOE+OO 2.50E+Ol 6.99E+OO  
: 4. Gross Alpha Activity                           Curies   O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO  2.50E+Ol D. Tritium
: 1. 09E+Ol 2.50E+Ol 8.79E-01 1.37E+OO 4.86E-02 7.70E-02 2.93E+00 2.32E+OO 2.SOE+Ol Nuclides Released Units Qtr Prairie Island Nuclear Generating Station 2016 Annual Release Summary Gaseous Effluents
: 1. Total Release                                 Curies   5.13E+OO   5.51E+OO 6.99E+OO 1. 09E+Ol 2.50E+Ol
-Ground Level Releases Continuous Mode 1 Qtr 2 Qtr 3 Qtr 4 Qtr. 1 1. Fission and Activation Gases Kr-85 Curies O.OOE+OO O.OOE+OO  
: 2. Average Release Rate for Period               µCi/sec   6.52E-01 7.0lE-01 8.79E-01 1.37E+OO
: 1. 43E-02 O.OOE+OO 9.42E-04 Xe-133 Curies 0.00E+OO O.OOE+OO 2.36E-02 O.OOE+OO O.OOE+OO Total for Period Curies O.OOE+OO O.OOE+OO 3.79E-02 O.OOE+OO 9.42E-04
: 3. Percent of Applicable Limit                     %     3.64E-02   3.83E-02  4.86E-02 7.70E-02 E. carbon-14
: 2. Iodines I-131 Curies 0.00E+OO O.OOE+OO 0.00E+OO 2.09E-07 O.OOE+OO Total for Period Curies O.OOE+OO O.OOE+OO 0.00E+OO 2.09E-07 O.OOE+OO  
: 1. Total Release                                 Curies   2.02E+OO   2.89E+OO 2.93E+00 2.32E+OO 2.SOE+Ol
: 3. Particulates Cd-109 Curies O.OOE+OO O.OOE+OO O.OOE+OO 4.93E-07 O.OOE+OO  
 
. Co-58 Curies O.OOE+OO O.OOE+OO O.OOE+OO 1.34E-06 O.OOE+OO Co-60 Curies O.OOE+OO O.OOE+OO O.OOE+OO 3.27E-07 O.OOE+OO Cr-51 Curies O.OOE+OO O.OOE+OO O.OOE+OO  
Page 5 of 8 Prairie Island Nuclear Generating Station 2016 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. 72E-07 O.OOE+OO Mn-54 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.50E-08 O.OOE+OO Nb-95 Curies O.OOE+OO O.OOE+OO O.OOE+OO 3.59E-08 O.OOE+OO Zr-95 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.32E-08 O.OOE+OO Total for Period Curies O.OOE+OO O.OOE+OO.
: 1. Fission and Activation Gases Kr-85            Curies  O.OOE+OO   O.OOE+OO   1. 43E-02 O.OOE+OO   9.42E-04 4.89E-04  9.80E-04 0.00E+OO Xe-133            Curies  0.00E+OO   O.OOE+OO   2.36E-02  O.OOE+OO   O.OOE+OO l.07E-05  0.00E+OO O.OOE+OO Total for Period        Curies  O.OOE+OO  O.OOE+OO    3.79E-02  O.OOE+OO   9.42E-04 5.00E-04  9.80E-04 O.OOE+OO
O.OOE+OO 2.42E-06 O.OOE+OO  
: 2. Iodines I-131            Curies  0.00E+OO  O.OOE+OO    0.00E+OO 2.09E-07    O.OOE+OO O.OOE+OO   O.OOE+OO O.OOE+OO Total for Period        Curies   O.OOE+OO   O.OOE+OO   0.00E+OO  2.09E-07    O.OOE+OO O.OOE+OO   O.OOE+OO O.OOE+OO
: 4. Tritium H-3 Curies 5.09E+OO 5.51E+OO 6.99E+OO  
: 3. Particulates Cd-109            Curies  O.OOE+OO   O.OOE+OO   O.OOE+OO 4.93E-07   O.OOE+OO O.OOE+OO   O.OOE+OO O.OOE+OO
: 1. 09E+Ol 3.36E-02
    . Co-58            Curies   O.OOE+OO   O.OOE+OO   O.OOE+OO 1.34E-06    O.OOE+OO O.OOE+OO   O.OOE+OO O.OOE+OO Co-60             Curies   O.OOE+OO   O.OOE+OO   O.OOE+OO 3.27E-07   O.OOE+OO O.OOE+OO   O.OOE+OO O.OOE+OO Cr-51            Curies  O.OOE+OO   O.OOE+OO   O.OOE+OO 1. 72E-07  O.OOE+OO O.OOE+OO   O.OOE+OO O.OOE+OO Mn-54            Curies   O.OOE+OO   O.OOE+OO   O.OOE+OO 2.50E-08   O.OOE+OO O.OOE+OO   O.OOE+OO O.OOE+OO Nb-95            Curies  O.OOE+OO   O.OOE+OO    O.OOE+OO 3.59E-08    O.OOE+OO O.OOE+OO   O.OOE+OO O.OOE+OO Zr-95            Curies   O.OOE+OO  O.OOE+OO   O.OOE+OO 2.32E-08    O.OOE+OO O.OOE+OO   0.00E+OO O.OOE+OO Total for Period        Curies  O.OOE+OO   O.OOE+OO. O.OOE+OO    2.42E-06    O.OOE+OO O.OOE+OO   O.OOE+OO O.OOE+oo*
: 5. Carbon-14 C-14 Curies 2.02E+00 2.89E+OO 2.93E+OO 2.32E+OO O.OOE+OO Page 5 of 8 Batch Mode Qtr 2 Qtr 3 Qtr 4 4.89E-04 9.80E-04 0.00E+OO l.07E-05 0.00E+OO O.OOE+OO 5.00E-04 9.80E-04 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 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+oo*
: 4. Tritium H-3              Curies  5.09E+OO   5.51E+OO     6.99E+OO 1. 09E+Ol  3.36E-02  1. 09E-04  1.lOE-03 4.90E-02
: 1. 09E-04 1.lOE-03 4.90E-02 O.OOE+OO O.OOE+OO O.OOE+OO 
: 5. Carbon-14 C-14              Curies  2.02E+00  2.89E+OO     2.93E+OO 2.32E+OO   O.OOE+OO O.OOE+OO   O.OOE+OO O.OOE+OO
*Prairie Island Nuclear Generating Station 2016 Annual Release Summary Liquid Ef.fluerits
 
-Summation of All Releases Type of Effluent A. Fission & Activation Products
Page 6 of 8
: 1. Total Release (not including
                                      *Prairie Island Nuclear Generating Station 2016 Annual Release Summary Liquid Ef.fluerits - Summation of All Releases Est. Total Type of Effluent                                    Units      Qtr 1    Qtr 2    Qtr 3    Qtr 4    Error~ %
: Tritium, Gases, and Alpha) 2. Average Diluted Concentration During Period 3. Percent of Applicable Limit B. Tritium 1. Total.Release
A. Fission & Activation Products
: 2. Average Diluted Concentration During Period 3. Percent of Applicable Limit C. Dissolved and Entrained Gases 1. Total Release 2. Average Diluted Concentration During Period 3. Percent of Applicable Limit D. Gross Alpha Radioactivity L Total Release E. Waste Volume Released (Pre-Dilution)
: 1. Total Release (not including Tritium,        *Curies  7.09E-03   2.41E-03  l.43E-03  7.34E-03    2.50E+Ol Gases, and Alpha)
F. Volume of Dilution Water Used Units *Curies µCi/ml % Curies µCi/ml % Qtr 1 Qtr 2 Qtr 3 Qtr 4 7.09E-03 2.41E-03 l.43E-03 7.34E-03 7.29E-ll 3.05E-ll l.94E-ll 7.73E-ll l.42E-01 4.82E-02 2.87E-02 l.47E-01 l.02E+02 l.20E+02 l.06E+02 6.85E+Ol l.05E-06 l.52E-06 l.44E-06 7.21E-07 I°. 05E-02 1. 52E-02 1. 44E-02 7. 21,_E-03 Curies O.OOE+OO 5.95E-05 4.34E-05 3.41E-05
: 2. Average Diluted Concentration During          µCi/ml  7.29E-ll  3.05E-ll  l.94E-ll  7.73E-ll Period
µCi/sec O.OOE+OO 7.52E-13 5.BBE-13 3.59E-13
: 3. Percent of Applicable Limit                     %    l.42E-01  4.82E-02  2.87E-02  l.47E-01 B. Tritium
% O.OOE+OO 3.76E-07 2.94E-07 l.79E-07 Curies O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO Liters 5.67E+07 4.03E+07 5.94E+08 5.38E+07  
: 1. Total.Release                                 Curies  l.02E+02  l.20E+02  l.06E+02  6.85E+Ol  2.SOE+Ol
.Liters 9.72E+l0 7.90E+l0 7.32E+l0 9.49E+l0 Page 6 of 8 Est. Total
: 2. Average Diluted Concentration During         µCi/ml  l.05E-06  l.52E-06  l.44E-06  7.21E-07 Period
% 2.50E+Ol 2.SOE+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol Nuclides Released Units Ag-110m Curies Ar-41 Curies As-76 Curies Co-57 Curies Co-58 Curies Co-60 Curies Cr-51 Curies Fe-55 Curies Fe-59 Curies H-3 Curies Mn-54 Curies Nb-95 Curies Nb-97 Curies Ni-63 Curies Sb-124 Curies Sb-125 Curies Sn-113 Curies Sr-92 Curies Te-123M Curies W-187 Curi.es Xe-127 Curies Xe-133 Curies Xe-135 Curies Zr-95 Curies Total for Period Curies. Prairie Island Nuclear Generating Station 2016 Annual Release Summary Liquid Effluents Continuous Mode Qtr 1 Qtr 2 Qtr 3 Qtr 4 Qtr 1 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.20E-04 0.00E+OO o*.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+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 3.41E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.41E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.60E-05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.88E-03 O.OOE+OO  
: 3. Percent of Applicable Limit                      %   I°. 05E-02 1. 52E-02 1. 44E-02 7. 21,_E-03 C. Dissolved and Entrained Gases
.0. OOE+OO O.OOE+OO O.OOE+OO 2.14E-06 1.45E-01 1.60E-01 2.99E+OO 1.46E-01 1.02E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.26E-05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.49E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.87E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.97E-03 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 6.30E-05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
: 1. Total Release                                Curies  O.OOE+OO  5.95E-05  4.34E-05  3.41E-05    2.50E+Ol
: 1. 71E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO
: 2. Average Diluted Concentration During        µCi/sec  O.OOE+OO  7.52E-13  5.BBE-13  3.59E-13 Period
: 0. OOE+o*o O.OOE+OO O.OOE+OO O.OOE+OO 3.24E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.50E-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 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 2.32E-06  
: 3. Percent of Applicable Limit                      %    O.OOE+OO  3.76E-07  2.94E-07  l.79E-07 D. Gross Alpha Radioactivity L  Total Release                                Curies  O.OOE+OO  O.OOE+OO  0.00E+OO  O.OOE+OO    2.50E+Ol E. Waste Volume Released (Pre-Dilution)              Liters  5.67E+07  4.03E+07  5.94E+08  5.38E+07   2.50E+Ol F. Volume of Dilution Water Used                    .Liters  9.72E+l0  7.90E+l0  7.32E+l0  9.49E+l0    2.50E+Ol
: 1. 45E-01 1.60E-01 2.99E+OO  
 
: 1. 4 6E-01 1.02E+02 Page 7 of 8 Batch Mode Qtr 2 Qtr 3 Qtr 4 9.39E-05 2.61E-05 2.73E-05 7.62E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.47E-06 O.OOE+OO O.OOE+OO 6.35E-06 2.67E-04 4.95E-05 3.05E-03 2.33E-04 2.83E-04 3.38E-04 7.95E-06 O.OOE+OO 5.40E-05
Page 7 of 8 Prairie Island Nuclear Generating Station 2016 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  O.OOE+OO     O.OOE+OO    O.OOE+OO O.OOE+OO   1.20E-04  9.39E-05  2.61E-05    2.73E-05 Ar-41          Curies  0.00E+OO     o*.OOE+OO   O.OOE+OO  O.OOE+OO    O.OOE+OO  7.62E-07   O.OOE+OO    O.OOE+OO As-76          Curies  O.OOE+OO    O.OOE+OO    O.OOE+OO  0.00E+OO    O.OOE+OO  O.OOE+OO  O.OOE+OO    1.47E-06 Co-57           Curies O.OOE+OO    O.OOE+OO    O.OOE+OO  O.OOE+OO    O.OOE+OO  O.OOE+OO  O.OOE+OO    6.35E-06 Co-58           Curies O.OOE+OO    O.OOE+OO    O.OOE+OO  o:ooE+oo    3.41E-04  2.67E-04  4.95E-05    3.05E-03 Co-60          Curies O.OOE+OO    O.OOE+OO    O.OOE+OO  O.OOE+OO    6.41E-04  2.33E-04  2.83E-04    3.38E-04 Cr-51          Curies O.OOE+OO    O.OOE+OO    O.OOE+OO  O.OOE+OO    1.60E-05  7.95E-06  O.OOE+OO    5.40E-05 Fe-55          Curies O.OOE+OO     O.OOE+OO   O.OOE+OO O.OOE+OO   3.88E-03  1. 44E-03  9.49E-04   1. 49E-03 Fe-59          Curies  O.OOE+OO   .0. OOE+OO   O.OOE+OO O.OOE+OO   2.14E-06  5.50E-06  O.OOE+OO   O.OOE+OO H-3            Curies  1.45E-01    1.60E-01    2.99E+OO 1.46E-01    1.02E+02  1.20E+02  1.03E+02    6.83E+01 Mn-54          Curies  O.OOE+OO     O.OOE+OO   O.OOE+OO O.OOE+OO   1.26E-05  1.47E-05  2.90E-05    2.06E-05 Nb-95          Curies  O.OOE+OO     O.OOE+OO   O.OOE+OO O.OOE+OO   3.49E-06  3.76E-05  O.OOE+OO   4 .. 04E-06 Nb-97          Curies  O.OOE+OO     O.OOE+OO   O.OOE+OO O.OOE+OO   6.87E-06  6.48E-06  1. 37E-05  1. 09E-05 Ni-63          Curies  O.OOE+OO     O.OOE+OO   O.OOE+OO O.OOE+OO   1.97E-03 1. 22E-04  O.OOE+OO   7.35E-04 Sb-124          Curies  O.OOE+OO     O.OOE+OO   O.OOE+OO O.OOE+OO   O.OOE+OO 6.45E-07  O.OOE+OO   1.65E-06 Sb-125          Curies  O.OOE+OO     O.OOE+OO   O.OOE+OO O.OOE+OO   6.30E-05  1. 23E-04  s .15E-0*5 1. 55E-03 Sn-113          Curies  O.OOE+OO     O.OOE+OO   O.OOE+OO O.OOE+OO   1. 71E-06 3.32E-05  O.OOE+OO   2.0lE-06 Sr-92          Curies  O.OOE+OO     O.OOE+OO   O.OOE+OO O.OOE+OO   0.00E+OO 1. 32E-06  1. llE-06  1.65E-06 Te-123M        Curies  0. OOE+o*o  O.OOE+OO   O.OOE+OO O.OOE+OO   3.24E-06  O.OOE+OO   1. 46E-06  *4. 73E-05 W-187          Curi.es O.OOE+OO     O.OOE+OO   O.OOE+OO O.OOE+OO   2.50E-05  4.64E-06  O.OOE+OO   O.OOE+OO Xe-127          Curies  O.OOE+OO     O.OOE+OO   O.OOE+OO O.OOE+OO   O.OOE+OO O.OOE+OO   O.OOE+OO   2.95E-06 Xe-133          Curies  O.OOE+OO     O.OOE+OO   O.OOE+OO O.OOE+OO   O.OOE+OO 5.48E-05  4.28E-05  2.99E-05 Xe-135          Curies  O.OOE+OO     O.OOE+OO   O.OOE+OO O.OOE+OO   O.OOE+OO 3.BBE-06  5.17E-07  1.27E-06 Zr-95          Curies  O.OOE+OO     O.OOE+OO   O.OOE+OO O.OOE+OO   2.32E-06 1.77E-05  O.OOE+OO  O.OOE+OO Total for Period  Curies. 1. 45E-01   1.60E-01     2.99E+OO 1. 4 6E-01 1.02E+02   1. 20E+02  1.03E+02  6.83E+01
: 1. 44E-03 9.49E-04
 
: 1. 49E-03 5.50E-06 O.OOE+OO O.OOE+OO 1.20E+02 1.03E+02 6.83E+01 1.47E-05 2.90E-05 2.06E-05 3.76E-05 O.OOE+OO 4 .. 04E-06 6.48E-06
Page 8 of 8 Prairie Island Nuclear Generating Station 2016 Annual Dose Summary Gaseous Effluents Parameter                Location                        Dose  Dose Limit  % of Limit Qtr 1 Gamma Air Dose (mrad)      0.58    km w                4.67E-08    1. OOE+Ol        0.00 Beta Air Dose (mrad)      0.58    km w                5.30E-06    2.00E+Ol        0.00 Total Body Dose (mrem)    0.58    km w                4.37E-08    5.00E+OO         0.00 Skin Dose (mrem)          0.58    km w                3.69E-06 *1.50E+Ol          0.00 1
: 1. 37E-05 1. 09E-05 1. 22E-04 O.OOE+OO 7.35E-04 6.45E-07 O.OOE+OO 1.65E-06
Max Organ Dose (mrem)      0.97    km NNW              5.76E-03   1. 50E+Ol        0.04 Child - Liver Qtr 2 Gamma Air Dose (mrad)      0.58    km w                3.51E-08    1.00E+Ol        0.00 Beta Air Dose (mrad)      0.58  km  w                2.78E-06   2.00E+Ol        0.00 Total Body Dose (mrem)    0.58  km w                  3.18E-08    5.00E+OO       0.00 Skin Dose (mrem)          0.58  km w                  1.94E-.06  1. 50E+Ol      0.00 Max Organ Dose (mrem)      0.97  km NNW                3.20E-02    1. 50E+Ol      0.21 Child - Bone Qtr*3 Gamma Air.Dose (mrad)      0.58  km  w                2.47E-05   1. OOE+Ol      0.00 Beta Air Dose (mrad)      0.58  km  w                1.57E-04    2 .*00E+o1      0.00 Total Body Dose (mrem)    0.58  km  w                2.07E-05   5.00E+OO       0.00 Skin Dose (mrem)          0.58  km W                  l.07E-04    1. 50E+Ol      0.00 Max Organ Dose (mrem)      0.97  km NNW                4.83E-02  1.50E+Ol        0.32 Child - Bone Qtr 4 Gamma Air Dose (mrad)      0.58  km  w                O.OOE+OO   1.00E+Ol        0.00 Beta Air Dose (mrad)      0.58  km  w                O.OOE+OO   2.00E+Ol        0.00 Total Body Dose (mrem)    0.58  km  w                O.OOE+OO   5.00E+OO         0.00 Skin Dose (mrem)          0.58  km W                  O.OOE+OO   l.50E+Ol        0.00 Max Organ Dose (mrem)      0.97  km NNW                1.22E-02  1.50E+Ol        0.08 Child - Thyroid Year  Gamma Air Dose (mrad)      0.58  km  w                2.48E-05   2.00E+Ol        0.00 Beta Air Dose (mrad)      0.58  km W                  1.65E-04  4.00E+Ol        0.00 Total Body Dose (mrem)     0.58  km w                  2.08E-05  1.00E+Ol        0.00 Skin Dose (mrem)           0.58  km w                  1.13E-04  3.00E+Ol        0.00 Max Organ Dose (mrem)     0.97  km NNW              8.03E-02    3.00E+Ol        0.27 Child - Bone Liquid Effluents Parameter              Max Receptor                      Dose    Dose Limit  % of Limit Qtr 1 Max Organ Dose (mrem) Adult - Bone                    1. 21E-03  1.00E+Ol        0.01 Total Body Dose (mrem) Adult ~ Total Body              4.64E-04    3.00E+OO        0.02 Qtr 2 Max Organ Dose (mrem) Adult - Gi-LLi                  9.17E-04    1. OOE+Ol        0.01 Total Body Dose (mrem) Adult - Total Body               6.15E-04  3.00E+OO        0.02 Qtr 3 Max Organ Dose .(mrem) Adult - Gi-LLi                  2.49E-04    l.OOE+Ol        0.00 Total Body Dose (mrem) Adult - Total Body              2.34E-04    3.00E+OO        0.01 Qtr 4 Max Organ Dose (mrem) Adult - Bone                    5.23E-04    1. OOE+Ol        0.01 Total Body Dose (mrem) Adult - Total Body              3.23E-04    3.00E+OO        0.01 Year  Max Organ Dose (mrem) Adult - Gi-LLi                  2.13E-03    2.00E+Ol        0.01 Total Body Dose (mrem) Adult - Total Body              l.64E-03    6.00E+OO         0.03}}
: 1. 23E-04 s .15E-0*5
: 1. 55E-03 3.32E-05 O.OOE+OO 2.0lE-06
: 1. 32E-06 1. llE-06 1.65E-06 O.OOE+OO  
: 1. 46E-06 *4. 73E-05 4.64E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.95E-06 5.48E-05 4.28E-05 2.99E-05 3.BBE-06 5.17E-07 1.27E-06 1.77E-05 O.OOE+OO O.OOE+OO
: 1. 20E+02 1.03E+02 6.83E+01 Parameter Qtr 1 Gamma Air Dose (mrad) Beta Air Dose (mrad) Total Body Dose (mrem) Skin Dose (mrem) Max Organ Dose (mrem) Child -Liver Qtr 2 Gamma Air Dose (mrad) Beta Air Dose (mrad) Total Body Dose (mrem) Skin Dose (mrem) Max Organ Dose (mrem) Child -Bone Qtr*3 Gamma Air.Dose (mrad) Beta Air Dose (mrad) Total Body Dose (mrem) Skin Dose (mrem) Max Organ Dose (mrem) Child -Bone Qtr 4 Gamma Air Dose (mrad) Beta Air Dose (mrad) Total Body Dose (mrem) Skin Dose (mrem) Max Organ Dose (mrem) Child -Thyroid Year Gamma Air Dose (mrad) Beta Air Dose (mrad) Total Body Dose (mrem) Skin Dose (mrem) Max Organ Dose (mrem) Child -Bone Parameter Qtr 1 Max Organ Dose (mrem) Total Body Dose (mrem) Qtr 2 Max Organ Dose (mrem) Total Body Dose (mrem) Qtr 3 Max Organ Dose .(mrem) Total Body Dose (mrem) Qtr 4 Max Organ Dose (mrem) Total Body Dose (mrem) Year Max Organ Dose (mrem) Total Body Dose (mrem) Prairie Island Nuclear Generating Station 2016 Annual Dose Summary Gaseous Effluents Location Dose 0.58 km w 4.67E-08 0.58 km w 5.30E-06 0.58 km w 4.37E-08 0.58 km w 3.69E-06 0.97 km NNW 5.76E-03 0.58 km w 3.51E-08 0.58 km w 2.78E-06 0.58 km w 3.18E-08 0.58 km w 1.94E-.06 0.97 km NNW 3.20E-02 0.58 km w 2.47E-05 0.58 km w 1.57E-04 0.58 km w 2.07E-05 0.58 km W l.07E-04 0.97 km NNW 4.83E-02 0.58 km w O.OOE+OO 0.58 km w O.OOE+OO 0.58 km w O.OOE+OO 0.58 km W O.OOE+OO 0.97 km NNW 1.22E-02 0.58 km w 2.48E-05 0.58 km W 1.65E-04 0.58 km w 2.08E-05 0.58 km w 1.13E-04 0.97 km NNW 8.03E-02 Liquid Effluents Max Receptor Dose Adult -Bone 1. 21E-03 Adult Total Body 4.64E-04 Adult -Gi-LLi 9.17E-04 Adult -Total Body 6.15E-04 Adult -Gi-LLi 2.49E-04 Adult -Total Body 2.34E-04 Adult -Bone 5.23E-04 Adult -Total Body 3.23E-04 Adult -Gi-LLi 2.13E-03 Adult -Total Body l.64E-03 Page 8 of 8 Dose Limit % of Limit 1. OOE+Ol 0.00 2.00E+Ol 0.00 5.00E+OO 0.00 *1.50E+Ol 0.00 1 1. 50E+Ol 0.04 1.00E+Ol 0.00 2.00E+Ol 0.00 5.00E+OO 0.00 1. 50E+Ol 0.00 1. 50E+Ol 0.21 1. OOE+Ol 0.00 2 .*00E+o1 0.00 5.00E+OO 0.00 1. 50E+Ol 0.00 1.50E+Ol 0.32 1.00E+Ol 0.00 2.00E+Ol 0.00 5.00E+OO 0.00 l.50E+Ol 0.00 1.50E+Ol 0.08 2.00E+Ol 0.00 4.00E+Ol 0.00 1.00E+Ol 0.00 3.00E+Ol 0.00 3.00E+Ol 0.27 Dose Limit % of Limit 1.00E+Ol 0.01 3.00E+OO 0.02 1. OOE+Ol 0.01 3.00E+OO 0.02 l.OOE+Ol 0.00 3.00E+OO 0.01 1. OOE+Ol 0.01 3.00E+OO 0.01 2.00E+Ol 0.01 6.00E+OO 0.03}}

Latest revision as of 18:14, 4 February 2020

Submittal of 2016 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual
ML17130A969
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 05/08/2017
From: Northard S
Northern States Power Company, Minnesota, Xcel Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML17130A980 List:
References
L-Pl-17-018
Download: ML17130A969 (19)
v • d • e


Text

1717 Wakonade Drive Welch, MN 55089

(},, Xcel Energy*

R ES P 0 NS I B LE B Y NAT U R E 800.895.4999 xcelenergy.com L-Pl-17-018 MAY 0 8 2017 TS 5.5.1.c TS 5.6.3 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Prairie Island Nuclear Generating Plant, Units 1 and 2 Docket Nos. 50-282 and 50-306 Renewed Operating License Nos. DPR-42 and DPR-60 2016 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 2016 Annual Radioactive Effluent Report which is comprised of the following: contains the Off-Site Radiation Dose Assessment for the period January 1, 2016, through December 31, 2016, in accordance with ODCM sections 8.1.1c, d, e, f, g, h, i, j, k, m and n.

' contains the Annual Radioactive Effluent Report, Supplemental Information, for the period January 1, 2016, through December 31, 2016, in accordance with TS 5.6.3 and ODCM section 8.1.1 b. contains a complete and legible copy of the entire ODCM revision 30, issued on 2/27/2016, in accordance with ODCM section 8.1.11. contains a complete and legible copy of the entire ODCM revision 31, issued on 10/13/2016, in accordance with ODCM section 8.1.11.

On May 4, 2016, PINGP identified a potential issue regarding the operability of the Waste Gas Holdup System Gas (Oxygen) Monitors listed in ODCM Table 3.2. This issue has been entered into the PINGP Corrective Action Program for evaluation. Evaluation identified errata data for 2014 and 2015 Annual Radioactive Effluent Reports, in the form of omission of reporting of operability, in accordance with ODCM section 8.1.1 h. The errata data is reported with this submittal and in accordance with ODCM section 8.7 guidance for reporting of errata data.

  • Document Control Desk Page 2 Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.

&ritJ~

Scott Northard Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (4) cc: Regional Administrator, USNRC, Region Ill Project Manager, Prairie Island Nuclear Generating Plant, USN RC, NRR NRC Resident Inspector - Prairie Island Nuclear Generating Plant Department of Health, State of Minnesota Pl Dakota Community Environmental Coordinator

ENCLOSURE 1 OFF-SITE RADIATION DOSE ASSESSMENT January 1, 2016 - December 31, 2016 7 pages to follow

Page 1of7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFF-SITE RADIATION DOSE ASSESSMENT FOR January 1, 2016- December31, 2016 An Assessment of the radiation dose due to releases from Prairie Island Nuclear Generating Plant during 2016 was performed, in accordance with the Offsite Dose Calculation Manual, arid 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 NRG review, for the. year of 2016.

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 expeded 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 dose from noble gas releases and the whole body and 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 2of7 ABNORMAL RELEASES

  • There were no (0) abnormal releases for 2016.

40 CFR 190 COMPLIANCE REMP environmental TLD results for 2016 were reviewed 'perANSl/HPS N13.37-2014 methodology for determining any plant effect above ambient gamma radiation measurements. All measurements ar~ considered to be within the range of variations in natural background radiation.

Neutron sky shine dose from the ISFSI was evaluated. The maximum sky shine dose was determined to be 0.71 mrem; to the nearest resident, at 724 meters from the ISFS(

Neutron sky shine dose is greater than the effluent dose to the Critical Receptor, therefore, 40 CFR 190 compliance was evaluated to the location of the maximum neutron sky shine dose.

The 40CFR190 evaluation location was determined to be 0.7 miles west ofthe plant.

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

Gamma Direct Radiation Dose: O.OOE+OO MREM Neutron sky shine Dose: 7.10E-01 MREM Garrima Air Dose: 2.0SE-12 MREM Beta Air Dose: 1.37E-11 MREM lodrne, particulate, H-3 and C-14 Dose: 1.04E-02 MREM*

  • Calculated values identical for Whole Body, Thyroid and Maximum "Other" Organs 40CFR190 DOSE EVALUATION:

40CFR190 LIMIT 40CFR 190 DOSE (MREM) (MREM)

WHOLE BODY " 7.20E-01 25 THYROID 75 7.20E-01 OTHER ORGANS 25 7.20E-01 (TEEN - WHOLE BODY)

I .

SAMPLING, ANALYSIS AND LLD REQUIREMENTS The lower limit of detection (LLD) requirements, as specified in ODCM Table 2.11 and 3.1 were met for 2016. The minimum sampling frequency requirements, as specified in ODCM Table 2.1 and 3.1 were met for 2016.

.Page 3 of 7

. MONITORING INSTRUMENTATION For 2016, 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.

From 1/24/16 to 4/14/16, less than the minimum channels required for Explosive Gas Monitoring Instrumentation were available, as specified in H4, Offsite Dose Calculation Manual.

Special Report L-16-058 was submitted to NRG on July22, 2016. An apparent cause evaluation was initiated.

  • The apparent cause evaluation found that a lack of clarity between the ODCM, Administrative Work 1.nstructions and Operations Procedures was the cause.

Actions were initiated to clarify requirements.

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

Zero (0) fuel casks were loaded and placed in the storage facility during the 2016 calendar year. The total number of casks in the ISFSI, as of 12/31/16, was forty (40) .

. There were no (0) releases of radioactive effluents from the ISFSI.

CURRENT OFFSITE DOSE CALCULATIONS MANUAL (ODCM) REVISION:

The Offsite Dose Calculation Manual was revised two (2) times in 2016. Revision 30 is dated February 27, 2016. Revision 31 is dated October 13, 2016. Both revisions are

  • submitted with this report:

CRITICAL RECEPTOR Based on the Annual Land Use Census*, the critical receptor did change. The critical receptor is defined as The Suter Residence, at 0.6 miles, in fhe SSE sector.

2016 is evaluated using the Critical Receptor identification of the Glazier Residence,. at 0.6 miles in the NNW sector.

2017 will .be evaluated using the newly identified Critical Receptor identification of the Suter Residence, at 0.6 miles in the SSE direction.

. Page 4of7 ERRATA DATA:

For 2014, ~here 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.

For 2015, there was one (1) occurrence, when less than the minimum reqLJired radioactive liquid and/or gaseous effluent monitoring instrumentation channels were operable, as required by ODCM Tables 2.2 and 3.2.

These out of service periods were incorrectly omitted from their respective annual reports.

From 9/25/14 to 10/26/14 and from 7/12/15 to 8/18/15, less than the minimum channels required for Explosive Gas Monitoring Instrumentation were available, as specified in H4, Offsite Dose Calculation Manual.

Special Report L-16-058 was submitted to NRC on July 22, 2016. An apparent cause evaluation was initiated.

The apparent cause evaluation found that a lack of clarity between the ODCM, Administrative Work Instructions and Operations Procedures was the cause.

Actions were initiated to clarify requirements.

  • ERRATA DATA:

The volume fdr the geometry employed in the evaluation of noble gas samples was

  • inaccurate. This value is canned in the software and the inaccuracy went undetected for an extended period of time.
  • The inaccuracy would have generated results with a conservatively high bias. No underreporting occurred.

Inaccurate reporting of dose equated to significantly less than 1% of the applicable 10 CFR 50 Appendix I design objectives and significantly less than 1% of the EPA public dose criterion. Over reporting did NOT impede Prairie Island's ability to adequately assess the information supplied.

Corrective actions have been implemented.

INDUSTRY INITIATIVE ON GROUND WATER PROTECTION:

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

Page 5of7 LOW LEVEL WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED COMPONENTS SHIPMENTS PERIOD: 1/1/16 TO 12/31/16 LICENSE NUMBER: DPR-42/60 SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL):

Resins, Filters and Volume Curies Shipped Evaporator Bottoms Waste Class FT3 . M3 Curies A 2.91E+02 8.25E+OO 1.93E-01 B 4.37E+02 1.24E+01 2.00E+02 c O.OOE+OO O.OOE+OO O.OOE+OO ALL 7.29E+02 2.06E+01 2.00E+02 Major Nuclides. H-3, Mn-54, Fe-55, Co-57, Co-58, Co-60, Ni-63, Sb-125, Cs-137 Dry Active Waste Volume Curies Shipped Waste Class FT3 M3 Curies A 2.82E+04 7.97E+02 2.76E-01 8 O.OOE+OO O.OOE+OO O.OOE+OO c O.OOE+OO O.OOE+OO O.OOE+OO ALL 2.82E+04 7.97E+02 2.76E-01 Major Nuclides Fe-55, Co-58, Co-60,.Ni-63, Zr-95, Nb-95 Irradiated Components Volume Curies Shipped Waste Class FT3 M3 Curies A O.OOE+OO O.OOE+OO O.OOE+OO 8 O.OOE+OO O.OOE+OO O.OOE+OO c O.OOE+OO O.OOE+OO O.OOE+OO ALL O.OOE+OO O.OOE+OO O.OOE+OO Major Nuclides Other Waste Volume Curies Shipped Waste Class FT3 M3 Curies A O.OOE+OO O.OOE+OO O.OOE+OO 8 O.OOE+OO O.OOE+OO O.OOE+OO c O.OOE+OO O.OOE+OO O.OOE+OO ALL O.OOE+OO O.OOE+OO O.OOE+OO Major Nuclides Sum of All Low Level Waste Volume Curies Shipped Shipped from Site Waste Class FT3 M3 Curies A 2.85E+04 8.06E+02 4.68E-01 8 4.37E+02 1.24E+01 2.00E+02 c O.OOE+OO O.OOE+OO O.OOE+OO ALL 2.89E+04 8.18E+02 2.00E+02 Major Nuclides Mn-54, Fe-55, Co-58, Co-60, Ni-63, Zr-95, Nb-95, Sb-125, Cs-137 PROCESS CONTROL PROGRAM The Process Control Program for Solidification/Dewatering of Radioactive Waste from Liquid Systems (D 59) was not revised in 2016. Current manual revision is 11. The revision date is October 23, 2014. Revision 11 was submitted with the 2014 report.

Page 6of7 Table 1 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND PERIOD: JANUARY 2016 through DECEMBER 2016.

10 CFR Part 50 Appendix I Guidelines (2-unit site per year)

Gaseous Releases Maximum Site Boundary Gamma Air Dose (mrad} 2.48E-05 20 Maximum Site Boundary Beta Air Dose (mrad) 1.65E-04 40 Maximum Off-site Dose to any Organ (mrem}* 8.03E-02 30 Organ:. Child - bone Offshore Location Gamma Dose (mrad} 4.97E-07 20 Total Body- (mrem) 4.15E-07 10 Maximum Off-site Dose to any Organ (mrem)* 6.90E-03 30 Organ: Teen -Lung Liquid Releases Maximum Off-site Dose Total Body (mrem) 1.64E-03 .6 Maximum Off-site Dose to any Organ (mrem) 2.13E-03 20 Organ Adult - Gi-LLi

Page 7of7 Table 2 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND SUPPLEMENTAL INFORMATION January 1, 2016 - December 31, 2016 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 Maximum Off-site Sector NNW Distance (miles) 0.60 Pathways Ground, Inhalation Vegetable Age Group Child Liquid Releases .

. Maximum Off-site Dose Location Downstream Pathway Fish

ENCLOSURE 2 ANNUAL RADIOACTIVE EFFLUENT REPORT SUPPLEMENTAL INFORMATION January 1, 2016 - December 31, 2016 8 pages to follow

Page 1 of 8 ANNUAL RADIOACTIVE EFFLUENT REPORT 01-JAN-16 THROUGH 31-DEC-16 SUPPLEMENTAL INFORMATION Facility: Prairie Island Nuclear Generating Plant Licensee: Northern States Power Company License Numbers: DPR-42 & DPR-60 A. Regulatory Limits

i. 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 $1500 mrem/year to any organ

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

noble gases $10 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

$30 mrem/year to any organ

Page 2 of 8.

B. Effluent Concentration

1. Fission and activation gases in gaseous releas.es:

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

2. Iodine and particulates with half lives greater than 8 days in gaseous releas.es :

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:

2.0E-04 uCi/ml Total Activity C. Average Energy Not applicable to Prairie Island regulatory limits.

D. Measurements and approximations of total activity

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

in gaseous releases: Nuclide Gem

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

Nuclide Gem

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

Nuclide Gem

4. Liquid effluents Total Gem +/-25%

Nuclide Gem E. Manual Revisions

1. Offsite Dose Calculations Manual:

Latest Revision number: 31 Revision date October 13, 2016

Page 3 of 8 Prairie Island Nuclear Generating Station 2016 Annual. Release Summary Batch Release Surnniary Liquid Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Number of Releases: 21 21 35 48 125 Total Time for All Releases (Minutes): 1607.0 1624. 0 2516.0 4156.0 9903.0 Maximum Time for All Releases (Minutes): 117. 0 103.0 -89.0 140.0 140.0 Average Time for All Releases (Minutes): 76.5 77.3 71. 9 86.6 79.2 Minimum Time for All Releases (Minutes): 50.0 62. 0 61. 0 63.0 50.0 Gaseous Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Number of Releases: 65 5 1 c* 18 89 Total Time for All Releases (Minutes): 90055.0 1070.0 60.0 21472.0 112657.0 Maximum Time for All Releases (Minutes): 1440.0 300.0 60.0 1660.0 1660.0 Average Time for All Releases (Minutes): 1385.5 214.0 60.0 1192.9 12 65. 8.

Minimum Time for All Releases (Minutes): 71. 0 71. 0 60.0 220.0 60.0 Abnormal Release Summary Liquid Releases Number of Abnormal Releases: 0 Total Activity for Abnormal Releases: O.OOE+OO Curies Gaseous Releases Number of Abnormal Releases: 0 Total Activity for Abnormal Releases: O.OOE+OO Curies

Page 4 of 8 Prairie Island Nuclear Generating Station 2016 Annual Release Summary Gaseous Effluents-Sununation of All Releases Est. Tota)-

Type of Effluent Units Qtr l Qtr 2 Qtr 3 Qtr 4 Error, .%

A. Fission & Activation Gases

1. Total Release Curies 9.42E-04 5.00E-'04 3.88E-02 O.OOE+OO 2.SOE+Ol
2. Average Release Rate for Period µCi/sec 1. 20E-04 6.35E-05 4.89E-03 0.00E+OO
3. Percent of Applicable Limit  % 2.65E-05 l.39E-05 7.87E-04 O.OOE+OO B. Iodines
1. Total Iodine-131 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.09E-07 2.50E+Ol
2. Average Release Rate for Period µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO 2.62E-08
3. Percent of Applicable Limit  % O.OOE+OO O.OOE+OO O.OOE+OO 2.09E-05
c. Particulates
1. Total Particulates (Half-lives > 8 days) Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.42E-06 2.50E+Ol
2. Average Release Rate for Period µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO 3.04E-07
3. Percent of Applicable. Limit  % 0.00E+OO O.OOE+OO O.OOE+OO 2.46E-05
4. Gross Alpha Activity Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.50E+Ol D. Tritium
1. Total Release Curies 5.13E+OO 5.51E+OO 6.99E+OO 1. 09E+Ol 2.50E+Ol
2. Average Release Rate for Period µCi/sec 6.52E-01 7.0lE-01 8.79E-01 1.37E+OO
3. Percent of Applicable Limit  % 3.64E-02 3.83E-02 4.86E-02 7.70E-02 E. carbon-14
1. Total Release Curies 2.02E+OO 2.89E+OO 2.93E+00 2.32E+OO 2.SOE+Ol

Page 5 of 8 Prairie Island Nuclear Generating Station 2016 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 Kr-85 Curies O.OOE+OO O.OOE+OO 1. 43E-02 O.OOE+OO 9.42E-04 4.89E-04 9.80E-04 0.00E+OO Xe-133 Curies 0.00E+OO O.OOE+OO 2.36E-02 O.OOE+OO O.OOE+OO l.07E-05 0.00E+OO O.OOE+OO Total for Period Curies O.OOE+OO O.OOE+OO 3.79E-02 O.OOE+OO 9.42E-04 5.00E-04 9.80E-04 O.OOE+OO
2. Iodines I-131 Curies 0.00E+OO O.OOE+OO 0.00E+OO 2.09E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total for Period Curies O.OOE+OO O.OOE+OO 0.00E+OO 2.09E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
3. Particulates Cd-109 Curies O.OOE+OO O.OOE+OO O.OOE+OO 4.93E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

. Co-58 Curies O.OOE+OO O.OOE+OO O.OOE+OO 1.34E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-60 Curies O.OOE+OO O.OOE+OO O.OOE+OO 3.27E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cr-51 Curies O.OOE+OO O.OOE+OO O.OOE+OO 1. 72E-07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Mn-54 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.50E-08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-95 Curies O.OOE+OO O.OOE+OO O.OOE+OO 3.59E-08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zr-95 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.32E-08 O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO Total for Period Curies O.OOE+OO O.OOE+OO. O.OOE+OO 2.42E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+oo*

4. Tritium H-3 Curies 5.09E+OO 5.51E+OO 6.99E+OO 1. 09E+Ol 3.36E-02 1. 09E-04 1.lOE-03 4.90E-02
5. Carbon-14 C-14 Curies 2.02E+00 2.89E+OO 2.93E+OO 2.32E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

Page 6 of 8

  • Prairie Island Nuclear Generating Station 2016 Annual Release Summary Liquid Ef.fluerits - 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 7.09E-03 2.41E-03 l.43E-03 7.34E-03 2.50E+Ol Gases, and Alpha)
2. Average Diluted Concentration During µCi/ml 7.29E-ll 3.05E-ll l.94E-ll 7.73E-ll Period
3. Percent of Applicable Limit  % l.42E-01 4.82E-02 2.87E-02 l.47E-01 B. Tritium
1. Total.Release Curies l.02E+02 l.20E+02 l.06E+02 6.85E+Ol 2.SOE+Ol
2. Average Diluted Concentration During µCi/ml l.05E-06 l.52E-06 l.44E-06 7.21E-07 Period
3. Percent of Applicable Limit  % I°. 05E-02 1. 52E-02 1. 44E-02 7. 21,_E-03 C. Dissolved and Entrained Gases
1. Total Release Curies O.OOE+OO 5.95E-05 4.34E-05 3.41E-05 2.50E+Ol
2. Average Diluted Concentration During µCi/sec O.OOE+OO 7.52E-13 5.BBE-13 3.59E-13 Period
3. Percent of Applicable Limit  % O.OOE+OO 3.76E-07 2.94E-07 l.79E-07 D. Gross Alpha Radioactivity L Total Release Curies O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO 2.50E+Ol E. Waste Volume Released (Pre-Dilution) Liters 5.67E+07 4.03E+07 5.94E+08 5.38E+07 2.50E+Ol F. Volume of Dilution Water Used .Liters 9.72E+l0 7.90E+l0 7.32E+l0 9.49E+l0 2.50E+Ol

Page 7 of 8 Prairie Island Nuclear Generating Station 2016 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 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.20E-04 9.39E-05 2.61E-05 2.73E-05 Ar-41 Curies 0.00E+OO o*.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.62E-07 O.OOE+OO O.OOE+OO As-76 Curies O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.47E-06 Co-57 Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.35E-06 Co-58 Curies O.OOE+OO O.OOE+OO O.OOE+OO o:ooE+oo 3.41E-04 2.67E-04 4.95E-05 3.05E-03 Co-60 Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.41E-04 2.33E-04 2.83E-04 3.38E-04 Cr-51 Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.60E-05 7.95E-06 O.OOE+OO 5.40E-05 Fe-55 Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.88E-03 1. 44E-03 9.49E-04 1. 49E-03 Fe-59 Curies O.OOE+OO .0. OOE+OO O.OOE+OO O.OOE+OO 2.14E-06 5.50E-06 O.OOE+OO O.OOE+OO H-3 Curies 1.45E-01 1.60E-01 2.99E+OO 1.46E-01 1.02E+02 1.20E+02 1.03E+02 6.83E+01 Mn-54 Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.26E-05 1.47E-05 2.90E-05 2.06E-05 Nb-95 Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.49E-06 3.76E-05 O.OOE+OO 4 .. 04E-06 Nb-97 Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.87E-06 6.48E-06 1. 37E-05 1. 09E-05 Ni-63 Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.97E-03 1. 22E-04 O.OOE+OO 7.35E-04 Sb-124 Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.45E-07 O.OOE+OO 1.65E-06 Sb-125 Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.30E-05 1. 23E-04 s .15E-0*5 1. 55E-03 Sn-113 Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. 71E-06 3.32E-05 O.OOE+OO 2.0lE-06 Sr-92 Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 1. 32E-06 1. llE-06 1.65E-06 Te-123M Curies 0. OOE+o*o O.OOE+OO O.OOE+OO O.OOE+OO 3.24E-06 O.OOE+OO 1. 46E-06 *4. 73E-05 W-187 Curi.es O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.50E-05 4.64E-06 O.OOE+OO O.OOE+OO Xe-127 Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.95E-06 Xe-133 Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.48E-05 4.28E-05 2.99E-05 Xe-135 Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.BBE-06 5.17E-07 1.27E-06 Zr-95 Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.32E-06 1.77E-05 O.OOE+OO O.OOE+OO Total for Period Curies. 1. 45E-01 1.60E-01 2.99E+OO 1. 4 6E-01 1.02E+02 1. 20E+02 1.03E+02 6.83E+01

Page 8 of 8 Prairie Island Nuclear Generating Station 2016 Annual Dose Summary Gaseous Effluents Parameter Location Dose Dose Limit  % of Limit Qtr 1 Gamma Air Dose (mrad) 0.58 km w 4.67E-08 1. OOE+Ol 0.00 Beta Air Dose (mrad) 0.58 km w 5.30E-06 2.00E+Ol 0.00 Total Body Dose (mrem) 0.58 km w 4.37E-08 5.00E+OO 0.00 Skin Dose (mrem) 0.58 km w 3.69E-06 *1.50E+Ol 0.00 1

Max Organ Dose (mrem) 0.97 km NNW 5.76E-03 1. 50E+Ol 0.04 Child - Liver Qtr 2 Gamma Air Dose (mrad) 0.58 km w 3.51E-08 1.00E+Ol 0.00 Beta Air Dose (mrad) 0.58 km w 2.78E-06 2.00E+Ol 0.00 Total Body Dose (mrem) 0.58 km w 3.18E-08 5.00E+OO 0.00 Skin Dose (mrem) 0.58 km w 1.94E-.06 1. 50E+Ol 0.00 Max Organ Dose (mrem) 0.97 km NNW 3.20E-02 1. 50E+Ol 0.21 Child - Bone Qtr*3 Gamma Air.Dose (mrad) 0.58 km w 2.47E-05 1. OOE+Ol 0.00 Beta Air Dose (mrad) 0.58 km w 1.57E-04 2 .*00E+o1 0.00 Total Body Dose (mrem) 0.58 km w 2.07E-05 5.00E+OO 0.00 Skin Dose (mrem) 0.58 km W l.07E-04 1. 50E+Ol 0.00 Max Organ Dose (mrem) 0.97 km NNW 4.83E-02 1.50E+Ol 0.32 Child - Bone Qtr 4 Gamma Air Dose (mrad) 0.58 km w O.OOE+OO 1.00E+Ol 0.00 Beta Air Dose (mrad) 0.58 km w O.OOE+OO 2.00E+Ol 0.00 Total Body Dose (mrem) 0.58 km w O.OOE+OO 5.00E+OO 0.00 Skin Dose (mrem) 0.58 km W O.OOE+OO l.50E+Ol 0.00 Max Organ Dose (mrem) 0.97 km NNW 1.22E-02 1.50E+Ol 0.08 Child - Thyroid Year Gamma Air Dose (mrad) 0.58 km w 2.48E-05 2.00E+Ol 0.00 Beta Air Dose (mrad) 0.58 km W 1.65E-04 4.00E+Ol 0.00 Total Body Dose (mrem) 0.58 km w 2.08E-05 1.00E+Ol 0.00 Skin Dose (mrem) 0.58 km w 1.13E-04 3.00E+Ol 0.00 Max Organ Dose (mrem) 0.97 km NNW 8.03E-02 3.00E+Ol 0.27 Child - Bone Liquid Effluents Parameter Max Receptor Dose Dose Limit  % of Limit Qtr 1 Max Organ Dose (mrem) Adult - Bone 1. 21E-03 1.00E+Ol 0.01 Total Body Dose (mrem) Adult ~ Total Body 4.64E-04 3.00E+OO 0.02 Qtr 2 Max Organ Dose (mrem) Adult - Gi-LLi 9.17E-04 1. OOE+Ol 0.01 Total Body Dose (mrem) Adult - Total Body 6.15E-04 3.00E+OO 0.02 Qtr 3 Max Organ Dose .(mrem) Adult - Gi-LLi 2.49E-04 l.OOE+Ol 0.00 Total Body Dose (mrem) Adult - Total Body 2.34E-04 3.00E+OO 0.01 Qtr 4 Max Organ Dose (mrem) Adult - Bone 5.23E-04 1. OOE+Ol 0.01 Total Body Dose (mrem) Adult - Total Body 3.23E-04 3.00E+OO 0.01 Year Max Organ Dose (mrem) Adult - Gi-LLi 2.13E-03 2.00E+Ol 0.01 Total Body Dose (mrem) Adult - Total Body l.64E-03 6.00E+OO 0.03

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