SVPLTR 21-0027, Radioactive Effluent Release Report and Offsite Dose Calculation Manual
| ML21321A286 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/22/2021 |
| From: | Karaba P Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| SVPLTR 21-0027 | |
| Download: ML21321A286 (59) | |
Text
Exelon Generation Dresden Nuclear Power Station 6500 North Dresden Road Morris, IL 60450 10 CFR 50.36a (a)(2)
April 22, 2021 SVPLTR: #21-0027 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 1, 2 and 3 Facility Operating License No. DPR-2 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos.50-010. 50-237, and 50-249
Subject:
Dresden Nuclear Power Station 2020 Radioactive Effluent Release Report and Offsite Dose Calculation Manual The Radioactive Effluent Release Report for January through December 2020 for Dresden Nuclear Power Station (DNPS) is submitted in accordance with Sections 6.9.A.4 and 5.6.3, "Radioactive Effluent Release Report," of the DNPS Unit 1 and Units 2 and 3 Technical Specifications, respectively and 10 CFR 50.36a, "Technical specifications on effluents from nuclear power reactors."
Should you have any questions concerning this letter, please contact DJ Walker, Regulatory Assurance Department, at (815) 416-2812.
Respectfully,
~-
Peter J. Karaba Site Vice President Dresden Nuclear Power Station
Attachment:
DNPS 2020 Annual Radioactive Effluent Release Report
cc: Regional Administrator- NRC Region Ill NRC Senior Resident Inspector, DNPS Senior Environmental Chemist - Dresden
Dresden Nuclear Power Station 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (ARERR)
Docket Numbers: 50-010/50-237/50-249 Units 1, 2, 3
DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT DOCKET NUMBER: 505-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table of Contents EXECUTIVE
SUMMARY
.......................................................................................................................... 1 BACKGROUND ........................................................................................................................................... 2 REGULTORY LIMITS ............................................................................................................................... 2 EFFLUENT MONITORING ....................................................................................................................... 4 RELEASE
SUMMARY
................................................................................................................................ 7 RADIOLOGICAL IMPACT ON MAN .................................................................................................... 29 CHANGES TO THE PROCESS CONTROL PROGRAM .................................................................... 31 DIRECT RADIATION ............................................................................................................................... 31 Attachment 1 ............................................................................................................................................... 38 RADIOACTIVE GROUNDWATER PROTECTION PLAN (RGPP) .................................................. 38
DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT DOCKET NUMBER: 505-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2 and 3 License: Exelon Nuclear
DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT DOCKET NUMBER: 505-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC EXECUTIVE
SUMMARY
The Radiological Eflluent Controls (REC) Program monitors and records all radioactive effluents released from the plant for the purpose of calculating a dose to a member of the public. The results are recorded in this report for the Dresden Nuclear Power Station from January 1 through December 31, 2020. The Radiological Environmental Monitoring Program (REMP) is a separate program that serves as a backup or independent verification of the REC Program. The REMP samples are analyzed for radioactivity associated with the operation of Dresden Nuclear Power Station by an outside vendor and the results are compared against historical REMP data as well as the calculations from the REC Program. The REMP results and comparisons are contained within the Annual Radiological Environmental Operating Report (AREOR) for the Site.
There were no regulatory effluent limit exceedances in 2020 and the resultant calculated dose to a member of the public for 2020 due to the uranium fuel cycle was 7.40E+00 mRem, which is 29.6% of the regulatory limit of25 mRem/year. The annual organ dose from all effluent sources is 7.91E-02 mRem/yr which is l .05E-0 I% of the 75 mRem/yr (Thyroid) limit. Additionally, the Annual Radiological Environmental Operating Report (AREOR) supported the effluent dose calculation and indicates that Units 1, 2, and 3 of the Dresden Nuclear Power Station did not result in any adverse environmental impact.
The total dose to the nearest member of the public is a calculation of the sum of the gaseous and liquid eflluents, the direct radiological dose from all sources including; IFSFI pad, storage tanks, skyshine, and Carbon-14 based upon Equivalent Full-Power Operation in days. There are many variables to consider, and in all cases, the most conservative factors were used to ensure there is sufficient margin to maintain regulatory compliance.
Table 1: Summation of Total Dose:
Liquid Effluents (All Units):
Total Body 5.79E-08 mRem Noble Gas (All Units):
Total Body 2.67E-03 mRem Radioiodines, tritium and Particulate (All units):
Total Body 1.42E-03 mRem Direct Radiation GE Facility l.20E-01 mRem Skyshine 4.40E+00 mRem ISFSI/ CST 2.87E+00 mRem C-14 l.03E-02 mRem Total 7.40E+00 mrem Page I of38
DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT DOCKET NUMBER: 505-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC BACKGROUND Dresden Nuclear Power Station, located in rural Grundy County in Northern Illinois, is home to the nation's first full-scale, privately financed nuclear power plant, which began operation in 1960. Capable of generating 210 megawatts of electricity before its retirement in 1978, Dresden Unit I is designated a Nuclear Historic Landmark by the American Nuclear Society. Dresden Units 2 and 3 began commercial operation in June 1970 and November 1971, respectively. In October of 2004, the Nuclear Regulatory Commission (NRC) renewed the operating licenses for both units for an additional 20 years, extending them to 2029 and 2031. Both units contain boiling water reactors designed by General Electric. The units generate a combined 1,845 net megawatts of electricity (MWe), which is enough power to support the electricity needs of more than I million average American homes.
Part of the regulatory requirements of nuclear operation is to maintain a Radiological Effluent Control (REC) Program to track and record all radioactive effluent releases to the environment and calculate a dose to the public from all uranium fuel sources to include direct doses from storage tanks and off-site facilities. This requires a knowledge not only of plant operation but of plant design and potential sources of radioactive effluent releases. There are two forms of releases; gaseous and liquid and these can be released continuously or by a batch process. Particulate and iodine monitors are installed on plant ventilation system effluents and are monitored continuously and analyzed weekly. The normal gaseous effluent release points are the 2/3 Chimney (a 300' elevated stack) and the 2/3 Reactor Building Ventilation Stack (150' mixed mode stack). These are examples of a continuous gaseous release point.
A discrete volume that is released over a specific time period with a defined start and stop time is an example of a batch release. Effluent releases that are not typical or expected are categorized as "abnormal". These are documented in a Dresden Abnormal Release (DAR) report.
REGUL TORY LIMITS The NRC sets a Total Effective Dose Equivalent (TEDE) in I 0CFR Part 20 Subpart D-Radiation Dose Limits for the Individual Members of the Public of I 00 mRem/year. In 1977 the Environmental Protection Agency enacted 40 CFR Part 190 "Environmental Radiation Protection Standards for Nuclear Power Operations" which sets the annual dose equivalent to any member of the public at 25 millirem (0.25 millisievert (mSv)) to the whole body, 75 millirem (0.75 mSv) to the thyroid and 25 millirem (0.25 mSv) to any other organ.
These limits are incorporated into the site's Offsite Dose Calculation Manual (ODCM) which sets limits of:
Fission and activation gases:
A. Dose Rate {site)
(I) Less than 500 mRem/year to the whole body.
(2) Less than 3000 mRem/year to the skin Page 2 of38
DRESDEN NUCLEAR POWER STA TION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC B. Gamma Air Dose (each unit)
(1) Less than or equal to 5 mrad/quarter.
(2) Less than or equal to 10 mrad/year.
C. Beta Air Dose (each unit)
(I) Less than or equal to l 0 mrad/quarter.
(2) Less than or equal to 20 mrad/year.
lodine-131, Iodine-I 33, and all radionuclides in particulate form with half-lives greater than 8 days:
A. Dose Rate (site)
(I) Less than 1500 mRem/year to any organ.
B. Dose (each unit)
(I) Less than or equal to 7.5 mRem/quarter to any organ.
(2) Less than or equal to 15 mRem/year to any organ.
Liquid effluents (each unit):
(I) Less than or equal to 1.5 mRem to the whole body during any calendar quarter.
(2) Less than or equal to 5 mRem to any organ during any calendar quarter.
(3) Less than or equal to 3 mRem to the whole body during any calendar year.
(4) Less than or equal to l 0 mRem to any organ during any calendar year.
40CFR190 and l 0CFR72 (all uranium fuel cycle operations in the region):
(1) Less than or equal to 25 mRem annual whole body dose.
(2) Less than or equal to 75 mRem annual thyroid dose.
(3) Less than or equal to 25 mRem annual dose to any other critical organ.
EFFLUENT CONCENTRATION LIMITS Dose rates, rather than effluent concentrations, are used to calculate permissible release rates for gaseous effluents. The maximum permissible dose rates for gaseous releases are defined in Dresden Offsite Dose Calculation Manual (ODCM) Radiological Effluent Control (REC) Section 12.4.1.
Liquid effluent concentrations are limited per ODCM REC Sectionl2.3.1 to IO times the concentration specified in l 0CFR20 Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases and 2.00E-04 µCi/mL total activity for all dissolved or entrained noble gases.
The ODCM limits dose rates at or beyond the site boundary due to the release of noble gases to less than or equal to 500 mRem per year to the1total body and less than or equal to 3,000 mRem per year to the Page 3 of38
DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC skin, and average energy is not used to determine dose to the public. Compliance with these limits is demonstrated based on dose calculations using measured isotopic concentrations of effluent streams and not based on gross count rate measuring systems. Therefore, the average beta and gamma energies ~) for gaseous effluents as described in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," are not applicable.
EFFLUENT MONITORING The 2/3 Chimney (elevated}, 2/3 Reactor Building Vent (mixed mode), and the Unit I Chemical Cleaning Building (mixed mode) effluents are continuously sampled for iodine and particulates. These samples are changed weekly and analyzed by gamma spectroscopy. The particulate filters are composited and sent to a vendor for gross alpha, Sr-89, Sr-90, Ni-63 and Fe-55 analysis quarterly. Noble gas grab samples of the 2/3 Chimney and 2/3 Reactor Building Vent are obtained weekly and analyzed by gamma spectroscopy.
Contributing streams of the 2/3 Chimney and 2/3 Reactor Building Vent are also sampled and analyzed by gamma spectroscopy. Tritium samples of the 2/3 Chimney and 2/3 Reactor Building Vent are obtained monthly and analyzed by liquid scintillation.
For the 2/3 Chimney and 2/3 Reactor Building Vent eflluents, the resultant activity concentration and measured flowrate at the release points is used to calculate the curies released. For the Chemical Cleaning Building effluent, the design basis flows are used to calculate curies released.
The Unit I Main Turbine Floor is used as an area to work on contaminated equipment. The Unit I Fuel Building is used as a storage area and potentially as a work area. The ventilation systems to these areas are no longer operational and the areas are at ambient pressure with the outside environment. The potential exists for airborne activity to be released to the environment through various points. Based on the work normally performed in these areas, an estimated 6.00E-06 Ci of Cs-137 was released via this path per month for a total of 7.20E-05 Ci during 2020.
The Chemistry Laboratory exhausts directly into the environment via its ventilation system and is not monitored. Based on an evaluation of activities performed in the area, the estimated activity released to the environment from the Chemistry laboratory from Unit 2 was: 3.360E-05 Ci and Unit 3: 3.846E-06 Ci.
The East Turbine Building Ventilation System exhausts directly into the environment. This release path is not monitored. Low-level removable contamination has been detected in the system in the past. A radiological survey was performed in August 2020 of the ventilation system and found no detectable isotopic contamination. This will continue to be surveyed annually and release permits generated for that year if activity is found.
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DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Carbon-14 Carbon-14 activity released is determined using Electric Power Research Institute Report 1021106 Boiling Water Reactor proxy value of 5.1 Ci per GWth year, gaseous release fraction of 0. 99%, a carbon dioxide fraction of 0.95, a reactor power rating of2957 MWt for Units 2 and 3. The resultant dose due to C-14 was calculated using the EPRI approved C-14 worksheet. The equivalent full power days (EFPD) of operation of Unit 2 was: 359.45 EFPD and Unit 3 was: 341.76, which resulted in 14.851 Ci ofC-14 from Unit 2 and 14.120 Ci from Unit 3 being produced in 2020. The calculated dose from C-14 produced from Unit 2 was:
5.296E-03 mrem/yr (Total Body-Child) and 5.035E-03 mrem/yr (Total Body-Child) for Unit 3 for a Station total of: l .033E-02 mrem/yr.
Liquid Effluents The Waste Surge Tank (WST) utilized for river discharges is analyzed for gamma-emitting nuclides by gamma spectroscopy and for tritium by liquid scintillation prior to discharge. A representative portion of this sample is saved and composited with other discharges that occur during the calendar month. The composite is sent to a vendor for analyses of gross alpha, Sr-89, Sr-90, Ni-63 and Fe-55. The tank volumes and activities are used to calculate the diluted activity released at the discharge point from batch discharges. There were no discharges from the Waste Surge Tank in 2020. Batch release data can be found in Table 4 of this report.
Containment Cooling Service Water (CCSW) is sampled from the Low-Pressure Coolant Injection (LPCI) heat exchangers monthly and analyzed for gamma-emitting nuclides by gamma spectroscopy.
These samples are composited quarterly and analyzed for tritium, gross alpha, Sr-89, Sr-90, Fe-55, and Ni-63. Results from the quarter are conservatively applied for each month of the quarter. Batch release volume is based on LPCI heat exchanger volume. There were no releases from this system in 2020.
On-site storm sewers are sampled and analyzed for tritium content. The CBG well tritium concentration measured during each month of 2020 was used to calculate the released activity for each month via the storm sewers. The volume was based on the monthly rain fall over a 100,000 sqft area of the Site. Low level tritium was detected throughout the 2020 year, and the total estimated tritium activity released via the storm sewers in 2020 was 3.955E-03 Ci in 6.787E+05 gallons of rain water.
Water in the Sewage Treatment Plant (STP) effluent is routinely sampled and analyzed for tritium, gross alpha, Sr-89, Sr-90, Fe-55, and Ni-63. Tritium was sampled monthly and was below the minimum detectable activity each month in the 2020 year.
The Unit 2/3 Heating Steam System has been contaminated in the past and has occasionally contained low-level contamination. During normal operation, the condensate is converted to steam, a portion of which gets vented to the atmosphere. Three were no nuclides identified above minimum detectable activity in 2020. This will continue to be monitored when the system is running.
Beginning in September 2019, groundwater from the West Tritium Remediation Well was monitored via
' the 2/3 Discharge Tunnel. Although this is a planned continuous release it is being mentioned here due to Page 5 of38
DRESDEN NUCLEAR POWER ST ATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC its relatively short duration over this life of the plant. An estimated 9.499E-03 Ci of tritium was released via this source in 2020 in 8.875E+05 gallons of ground water.
The estimated calculated dose from all of these releases was well below the regulatory limit of 25 mRem/yr for the whole body/ 75 mRem/yr Thyroid as well as all quarterly dose limits.
Estimated Total Errors The estimated total errors were calculated as the square root of the sum of the squares of significant errors present in the sampling and analysis process.
Less than the Lower Limit of Detection (<LLD)
Samples are analyzed such that the ODCM LLD requirements are met. When a nuclide is not detected, then "<LLD" is reported.
Abnormal Releases None Changes to the ODCM None Errata None Page 6 of38
DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC RELEASE
SUMMARY
Table 2.1(1): Gaseous Effluents-Summation of All Effluent Releases Unit 1 1st 2nd 3rd 4th Est. Total Units Quarter Quarter Quarter Quarter Error %
A Fission & Activation Gases 1 Total Release Ci NIA NIA NIA NIA 1.31E+01 I 2 Averaae release rate for oeriod uCi/sec NIA NIA NIA NIA Percent of ODCM Quarterly dose % Gamma 1 NIA NIA NIA NIA 3
limit (site)
% Beta 2 NIA NIA NIA NIA B. lodine-131 1 Total release Ci NIA NIA NIA NIA 2.60E+01 I 2 Averaae release rate for oeriod uCi/sec NIA NIA NIA NIA Percent of ODCM Quarterly dose 3 limit(*)
% NIA NIA NIA NIA C. Particulates 1 Particulates with half-life >8 davs Ci NIA NIA NIA 7.20E-05 2.94E+01 I 2 Averaae release rate for period uCi/sec NIA NIA NIA 9.13E-06 Percent of ODCM Quarterly dose 3 limit(*)
% NIA NIA NIA 1.38E-02 D Tritium 1 Total release Ci NIA NIA NIA NIA 7.56E+00 I 2 Averaae release rate far oeriod uCi/sec NIA NIA NIA NIA Percent of ODCM Quarterly dose 3 limit/*)
% NIA NIA NIA NIA E. Gross Aloiha 1 Total release Ci NIA NIA NIA NIA 2.94E+01 I 2 Averaae release rate for oeriod uCi/sec NIA NIA NIA NIA F Carbon14 1 Total release Ci NIA NIA NIA NIA 2 Averaae release rate for oeriod uCi/sec NIA NIA NIA NIA
- 1. Based upon a quarterly dose limit of 5.00 mRad/yr for the Site
- 2. Based upon a quarterly dose limit of 10.00 mRad/yr for the Site
- "Percent of ODCM annual dose limit" indicates combined total of lodine-131, Particulates, and Tritium Page 7 of38
DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table 2.1 (2): Gaseous Effluents- Summation of All Effluent Releases Unit2 1st 2nd 3rd 4th Est. Total Units Quarter Quarter Quarter Quarter Error %
A. Fission & Activation Gases 1 Total Release Ci 1.94E+01 1.75E+01 1.78E+01 1.74E+01 1.31E+01 I 2 Averaae release rate for period uCi/sec 2.45E+00 2.22E+00 2.26E+00 2.20E+0O 1.82E-02 1.62E-02 1.57E-02 1.73E-02 3
Percent of ODCM Quarterly dose Gamma 1 limit (site)
% Beta2 3.71E-04 3.37E-04 3.40E-04 1.40E-03 B . lodine-131 1 Total release Ci 6.52E-04 4.36E-03 5.96E-03 2.99E-03 2.60E+01 I 2 Averaae release rate for period uCi/sec 8.27E-05 5.53E-04 7.56E-04 3.79E-04 Percent of ODCM Quarterly dose
% 2.30E-03 2.61 E-03 2.14E-03 6.13E-03 3 limit(*)
C. Particulates 1 Particulates with half-life >8 days Ci 1.89E-04 4.36E-03 5.66E-04 7.07E-04 2.94E+01 I 2 Averaae release rate for Period uCi/sec 2.39E-05 5.52E-05 7.17E-05 8.97E-05 Percent of ODCM Quarterly dose
% 2.30E-03 2.61 E-03 2.14E-03 6.13E-03 3 limit(*)
D. Tritium 1 Total release Ci 4.42E+00 8.04E+00 6.41E+0O 4.87E+00 7.56E+00 I 2 Averaae release rate for Period uCi/sec 5.61E-01 1.02E+00 8.13E-01 6.18E-01 Percent of ODCM Quarterly dose
% 2.30E-03 2.61 E-03 2.14E-03 6.13E-03 3 limit(*)
E. Gross AlIPIha 1 Total release Ci O.00E+00 0.00E+00 0.00E+00 0.00E+00 2.94E+01 I 2 Averaae release rate for period uCi/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F. Carbon14 1 Total release Ci 5.28E+00 3.66E+00 3.76E+00 3.75E+00 2 Averaae release rate for oeriod uCi/sec 6.79E-01 4.66E-01 4.73E-01 4.72E-01 1 . Based upon a quarterly dose limit of 5. 00 mRad/yr for the Site
- 2. Based upon a quarterly dose limit of 10.00 mRad/yr for the Site
- "Percent of ODCM annual dose limit" indicates combined total of lodine-131, Particulates, and Tritium Page 8 of38
DRESDEN NUCLEAR POWER STA TION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table 2.1 (3): Gaseous Effluents- Summation of All Effluent Releases Unit3 1st 2nd 3rd 4th Est. Total Units Quarter Quarter Quarter Quarter Error %
A. Fission & Activation Gases 1 Total Release Ci 3.40E+00 3.71E+O0 4.04E+00 2.14E+00 1.31E+01 j 2 Averaoe release rate for period uCilsec 4.31E-01 4.71E-01 5.12E-01 2.72E-01 Percent of ODCM Quarterly dose 3.25E-03 3.66E-03 3.86E-03 2.06E-03 3 Gamma 1 limit (site)
% Beta 2 6.62E-05 7.16E-05 7.11E-05 4.15E-05 B lodine-131 1 Total release Ci 5.37E-04 1.45E-03 1.11E-03 2.85E-04 2.60E+01 j 2 Averaoe release rate for period uCilsec 6.81E-05 1.84E-04 1.40E-04 3.61 E-05 Percent of ODCM Quarterly dose
% 1.51E-03 9.38E-04 8.39E-04 1.48E-03 3 limit(*)
C Particulates 1 Particulates with half-life >8 davs Ci 1.51E-04 1.53E-04 1.16E-04 7.98E-05 2 .94E+01 I 2 Averaoe release rate for period uCilsec 1.91E-05 1.94E-05 1.47E-05 1.01E-05 Percent of ODCM Quarterly dose
% 1.51E-03 9.38E-04 8.39E-04 1.48E-03 3 limit(*)
D Tritium 1 Total release Ci 3.20E+00 2.82E+00 1.13E+00 3.57E-01 7.56E+00 I 2 Average release rate for period uCilsec 4.06E-01 3.57E-01 1.44E-01 4.53E-02 Percent of ODCM Quarterly dose
% 1.51E-03 9.38E-04 8.39E-04 1.48E-03 3 limit(*)
E Gross AlIP ha 1 Total release Ci NIA NIA NIA NIA 2 .94E+01 I 2 Averaoe release rate for period uCilsec NIA NIA NIA NIA F Carbon14 1 Total release Ci 5.28E+00 3.72E+OO 3.49E+0O 3.05E+00 2 Averaoe release rate for period uCilsec 6.79E-01 4.73E-01 4.40E-01 3.84E-01
- 1. Based upon a quarterly dose limit of 5.00 mRad/yr for the Site
- 2. Based upon a quarterly dose limit of 10.00 mRad/yr for the Site
- "Percent of ODCM annual dose limit" indicates combined total of lodine-131 , Particulates, and Tritium Page 9 of38
DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Lower Limits of Detectability for Gaseous Effluents Fission / Activation Gases µCi/cc Kr-87 l.00E-04 Kr-88 l.00E-04 Xe-133 1.00E-04 Xe-133m l.00E-04 Xe-135 1.00E-04 Xe-138 l.00E-04 Iodines 1-131 1.00E-12 1-133 l .00E-10 Particulates Sr-89 1.00E-11 Sr-90 l .00E-11 Mn-54 l .0OE-11 Co-58 l .00E-11 Fe-59 1.00E-11 Co-60 l .00E-11 Zn-65 l.00E-11 Mo-99 l.00E-11 Cs-134 l .00E-11 Cs-137 l .00E-11 Ce-141 1.00E-11 Ce-144 l .OOE-11 Other H-3 1.00E-06 Gross Alpha l.00E-11 The above limits are the ODCM required Lower Limits of Detection (LLD).
Page 10 of38
DRESDEN NUCLEAR POWER ST ATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-0 I 0/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table 2.2.A(1) Gaseous Effluents Release Point: Unit 1 Ground Level Nuclldes Released Continuous Mode Batch Mode 1st 2nd 3rd 4th 1st 2nd 3rd 4th Units Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter
- 1. Fission gases Kr-85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-85m Cl <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-133 Cl <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135 Cl <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ar-41 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Cl <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
- 2. Iodines 1-131 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
- 3. Particulates Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD 7.20E-05 <LLD <LLD <LLD <LLD Ba-140 Cl <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD cr-51 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ag-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD 7.20E-05 <LLD <LLD <LLD <LLD
- 5. Gross Alpha Gross Alpha Total Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table 2.2.A (2) Gaseous Effluents Release Point: Unit 2 Ground Level Nuclldes Released Continuous Mode Batch Mode 1st 2nd 3rd 4th 1st 2nd 3rd 4th Units Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter
- 1. Fission gases Kr-85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-85m Ci <LLD <LLD <LLD 5.45E-07 <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD 3.0BE-06 <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD 2.0BE-06 <LLD <LLD <LLD <LLD Xe-131m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD 1.76E-07 <LLD <LLD <LLD <LLD Xe-133m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135 Ci <LLD <LLD <LLD 2.47E-06 <LLD <LLD <LLD <LLD Xe-135m Ci <LLD <LLD <LLD 4.84E-06 <LLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD <LLD 2.03E-05 <LLD <LLD <LLD <LLD Ar-41 Ci <LLD <LLD <LLD 1.28E-07 <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD 3.36E-05 <LLD <LLD <LLD <LLD
- 2. Iodines 1-131 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-132 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
- 3. Particulates Br-82 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ba-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cr-51 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-57 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ag-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Te-123m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Hf-181 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zn-65 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zr-95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Nb-95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sn-117m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sb-124 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Page 12 of38
DRESDEN NUCLEAR POWER ST ATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Sb-125 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
- 5. Gross Alpha Gross Alpha Total Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table 2.2.A(3} Gaseous Effluents Release Point: Unit 3 Ground Level Nuclldes Released Continuous Mode Batch Mode 1st 2nd 3rd 4th 1st 2nd 3rd 4th Units Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter
- 1. Fission gases Kr-85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-85m Ci <LLD <LLD <LLD 1.20E-07 <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD 7.02E-07 <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD 4.36E-07 <LLD <LLD <LLD <LLD Xe-131m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD 4.93E-08 <LLD <LLD <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135m Ci <LLD <LLD <LLD 7.59E-07 <LLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD <LLD 1.59E-06 <LLD <LLD <LLD <LLD Ar-41 Ci <LLD <LLD <LLD 1.90E-07 <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD 3.BSE-06 <LLD <LLD <LLD <LLD
- 2. Iodines 1-131 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
- 3. Particulates Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ba-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cr-51 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-57 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ag-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Te-123m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Hf-181 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zn-65 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zr-95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Nb-95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sn-117m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sb-124 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sb-125 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Page 14 of38
DRESDEN NUCLEAR POWER ST ATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-0l0/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC
- 5. Gross Alpha Gross Alpha Total Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table 2.2.8(1) Gaseous Effluents Release Point: Unit 1 Elevated Nuclldes Released Continuous Mode Batch Mode 1st 2nd 3rd 4th 1st 2nd 3rd 4th Units Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter
- 1. Fission gases Kr-85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-85m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ar-41 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
- 2. Iodines 1-131 Cl <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-133 Cl <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-135 Cl <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
- 3. Partlculates Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-137 Cl <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ba-140 Cl <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cr-51 Cl <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ag-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-141 Cl <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-144 Cl <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
- 5. Gross Alpha Gross Alpha Total Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table 2.2.8(2) Gaseous Effluents Release Point: Unit 2 Elevated Nuclldes Released Continuous Mode Batch Mode 1st 2nd 3rd 4th 1st 2nd 3rd 4th Units Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter
- 1. Fission gases Kr-85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-85m Ci 1.42E+00 1.0SE+00 2.73E-01 2 .77E-01 <LLD <LLD <LLD <LLD Kr-87 Ci 5.60E-01 5.37E-01 5.S0E-01 5.81E-01 <LLD <LLD <LLD <LLD Kr-88 Ci 1.03E+00 6.91E-01 3.82E-01 6 .89E-01 <LLD <LLD <LLD <LLD Xe-133 Ci 9.20E-01 1.49E+00 2.79E+00 8.03E-01 <LLD <LLD <LLD <LLD Xe-135 Ci 1.70E+00 7.89E-01 7.44E-01 7.67E-01 <LLD <LLD <LLD <LLD Xe-135m Ci 2.08E+00 2.12E+00 2.02E+00 2.44E+00 <LLD <LLD <LLD <LLD Xe-138 Ci 1.04E+01 1.02E+01 1.09E+01 1.15E+01 <LLD <LLD <LLD <LLD Ar-41 Ci 1.21E+00 6.34E-01 1.69E-01 2.78E-01 <LLD <LLD <LLD <LLD Total for Period Ci 1.94E+01 1.75E+01 1.78E+01 1.74E+01 <LLD <LLD <LLD <LLD
- 2. Iodines 1-131 Ci 9 .SBE-05 2.72E-04 3.48E-04 3.15E-04 <LLD <LLD <LLD <LLD 1-133 Ci 5.56E-04 1.73E-03 2.40E-03 1.66E-03 <LLD <LLD <LLD <LLD 1-135 Ci <LLD 2.36E-03 3.21E-03 1.00E-03 <LLD <LLD <LLD <LLD Total for Period Ci 6 .52E-04 4.36E-03 5.96E-03 2.98E-03 <LLD <LLD <LLD <LLD
- 3. Particulates Zn-65 Ci <LLD <LLD 3.28E-05 <LLD <LLD <LLD <LLD <LLD Sr-89 Ci 1.31E-05 1.0SE-04 2.19E-04 1.52E-04 <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ba-140 Ci 9.20E-05 2.24E-04 2.28E-04 2.56E-04 <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cr-51 Ci 6.57E-07 <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mn-54 Ci 3.38E-06 3.37E-06 1.19E-05 <LLD <LLD <LLD <LLD <LLD Co-58 Ci 1.43E-07 4.76E-06 <LLD <LLD <LLD <LLD <LLD <LLD Co-60 Ci 4 .37E-05 7.45E-05 6.37E-05 1.35E-04 <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ag-110m Ci 5.31E-07 9.96E-06 8.86E-06 2.06E-05 <LLD <LLD <LLD <LLD Sn-117m Ci 1.93E-05 6.16E-06 7 .77E-07 5.51E-05 <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci 1.73E-04 4.28E-04 5.66E-04 6.18E-04 <LLD <LLD <LLD <LLD
- 5. Gross Alpha Gross Alpha Total Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
- 6. Carbon 14 C-14 Total for Period Ci 5.28E+00 3.66E+00 3.76E+00 3.75E+00 <LLD <LLD <LLD <LLD Page 17of38
DRESDEN NUCLEAR POWER ST ATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table 2.2.8(3) Gaseous Effluents Release Point: Unit 3 Elevated Nuclide& Released Continuous Mode Batch Mode 1st 2nd 3rd 4th 1st 2nd 3rd 4th Units Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter
- 1. Fission gases Kr-85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-85m Ci 3.36E-02 7.01E-02 5.28E-02 3.35E-02 <LLD <LLD <LLD <LLD Kr-87 Ci 8.05E-02 8.50E-02 7.14E-02 5.26E-02 <LLD <LLD <LLD <LLD Kr-88 Ci 4 .40E-02 5.59E-02 3.82E-02 4.49E-02 <LLD <LLD <LLD <LLD Xe-133 Ci 1.25E-01 2.27E-01 5.77E-01 1.72E-01 <LLD <LLD <LLD <LLD Xe-135 Ci 2.SOE-01 8.16E-02 6.64E-02 4.74E-02 <LLD <LLD <LLD <LLD Xe-135m Ci 5.44E-01 5.88E-01 4 .78E-01 3.37E-01 <LLD <LLD <LLD <LLD Xe-138 Ci 2.0SE+OO 2.22E+OO 1.81E+OO 1.34E+OO <LLD <LLD <LLD <LLD Ar-41 Ci 2 .18E-01 3.91E-01 9.45E-01 1.20E-01 <LLD <LLD <LLD <LLD Total for Period Ci 3.40E+OO 3.71E+OO 4.04E+OO 2.14E+OO <LLD <LLD <LLD <LLD
- 2. Iodines 1-131 Ci 6.58E-05 9.71E-05 6.48E-05 2.78E-05 <LLD <LLD <LLD <LLD 1-133 Ci 4 .71E-04 6.01E-04 4.44E-04 1.47E-04 <LLD <LLD <LLD <LLD 1-135 Ci <LLD 7.55E-04 5.99E-04 1.07E-04 <LLD <LLD <LLD <LLD Total for Period Ci 5.37E-04 1.45E-03 1.11 E-03 2.82E-04 <LLD <LLD <LLD <LLD
- 3. Partlculates Zn-65 Ci <LLD <LLD 7.22E-06 <LLD <LLD <LLD <LLD <LLD Sr-89 Ci 9.41E-06 3.71E-05 4.01E-05 1.26E-05 <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ba-140 Ci 8.85E-05 7.88E-05 4 .93E-05 2.09E-05 <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cr-51 Ci 2 .41E-07 <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mn-54 Ci 1.24E-06 1.04E-06 1.50E-06 <LLD <LLD <LLD <LLD <LLD Co-58 Ci 5.26E-08 1.38E-06 <LLD <LLD <LLD <LLD <LLD <LLD Co-60 Ci 2.95E-05 2.69E-05 9.41E-06 1.21E-05 <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ag-110m Ci 7 .92E-07 3.12E-06 9.72E-07 1.44E-06 <LLD <LLD <LLD <LLD Sn-117m Ci 1.42E-05 1.79E-06 8.53E-08 4.78E-06 <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci 1.44E-04 1.50E-04 1.09E-04 5.18E-05 <LLD <LLD <LLD <LLD
- 5. Gross Alpha Gross Alpha Total Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
- 6. Carbon 14 C-14 Total for Period Ci 5.28E+OO 3.72E+OO 3.49E+OO 3.05E+OO <LLD <LLD <LLD <LLD Page 18 of38
DRESDEN NUCLEAR POWER ST ATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table 2.2.C(l) Gaseous Effluents Release Point: Unit 1 Mixed Mode Nuclides Released Continuous Mode Batch Mode 1st 2nd 3rd 4th 1st 2nd 3rd 4th Units Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter I. Fission gases Kr-85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-85m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ar-41 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
- 2. Iodines 1-131 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
- 3. Particulates Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ba-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cr-51 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ag-ll0m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
- 4. Tritium H-3 Total for Period Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD S. Gross Alpha Gross Alpha Total Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
DRESDEN NUCLEAR POWER ST ATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table 2.2.C(2) Gaseous Effluents Release Point: Unit 2 Mixed Mode Nuclldes Released Continuous Mode Batch Mode 1st 2nd 3rd 4th 1st 2nd 3rd 4th Units Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter
- 1. Fission gases Kr-85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-85m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135 Ci <LLD <LLD <LLD 9.92E-06 <LLD <LLD <LLD <LLD Xe-135m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ar-41 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD 9.92E-06 <LLD <LLD <LLD <LLD
- 2. Iodines 1-131 Ci <LLD <LLD 1.09E-06 1.09E-06 <LLD <LLD <LLD <LLD 1-133 Ci <LLD <LLD <LLD 5.64E-06 <LLD <LLD <LLD <LLD 1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD 1.09E-06 6.72E-06 <LLD <LLD <LLD <LLD
- 3. Particulates Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ba-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cr-51 Ci <LLD <LLD <LLD 3.87E-05 <LLD <LLD <LLD <LLD Mn-54 Ci 1.74E-06 <LLD <LLD 3.98E-06 <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD 2.11E-06 <LLD <LLD <LLD <LLD Co-60 Ci 1.43E-05 7.67E-06 <LLD 4.42E-05 <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ag-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sn-117m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci 1.60E-05 7.67E-06 <LLD 8.90E-05 <LLD <LLD <LLD <LLD
- 5. Gross Alpha Gross Alpha Total Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table 2.2.C(3) Gaseous Effluents Release Point: Unit 3 Mixed Mode Nuclldes Released Continuous Mode Batch Mode 1st 2nd 3rd 4th 1st 2nd 3rd 4th Units Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter
- 1. Fission gases Kr-85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-85m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135 Ci <LLD <LLD <LLD 1.31 E-06 <LLD <LLD <LLD <LLD Xe-135m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ar-41 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD 1.31E-06 <LLD <LLD <LLD <LLD
- 2. Iodines 1-131 Ci <LLD 6.30E-07 <LLD 8.25E-07 <LLD <LLD <LLD <LLD 1-133 Ci <LLD <LLD <LLD 2.44E-06 <LLD <LLD <LLD <LLD 1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD 6.30E-07 <LLD 3.27E-06 <LLD <LLD <LLD <LLD
- 3. Particulates Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ba-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cr-51 Ci <LLD <LLD <LLD 8.11E-06 <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD 1.43E-06 <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD 1.43E-07 <LLD <LLD <LLD <LLD Co-60 Ci 6.65E-06 2.81E-06 7.45E-06 1.83E-05 <LLD <LLD <LLD <LLD M<r99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ag-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sn-117m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci 6 .65E-06 2.81E-06 7.45E-06 2.B0E-05 <LLD <LLD <LLD <LLD
- 5. Gross Alpha Gross Alpha Total Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table 3.1(1) Liquid Effluents-Summation of All Releases: Unit 1 1st 2nd 3rd 4th Est. Total Units Quarter Quarter Quarter Quarter Error,%
A. Fission & Activation Gases 1 Total Release Ci NIA NIA NIA NIA 1.95E+01 I 2 Average Concentration uCi/mL NIA NIA NIA NIA Percent of ODCM Quarterly 3
dose limit NIA NIA NIA NIA B. Tritium 1 Total release Ci NIA NIA NIA NIA 2.37E+00 I 2 Averaae Concentration uCi/mL NIA NIA NIA NIA 3 Percent of ODCM Quarterly % NIA NIA NIA NIA dose limit C. Dissolved and Entrained Gases 1 Total release Ci NIA NIA NIA NIA 2.03E+01 I 2 Averaae Concentration uCi/mL NIA NIA NIA NIA 3 Percent of ODCM Quarterly % NIA NIA NIA NIA dose limit D. Gross Alpha 1 Total release Ci NIA NIA NIA NIA 2.00E+01 2 Avera e Concentration Ci/ml NIA NIA NIA NIA E. Liquid Release Volume I II 1 Total Release Liters NIA NIA NIA NIA F. Dilution Volume 1
II Total Release Liters NIA NIA NIA NIA Page 22 of38
DRESDEN NUCLEAR POWER ST ATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table 3.1(2) Liquid Effluents-Summation of All Releases: Unit 2 1st 2nd 3rd 4th Est. Total Units Quarter Quarter Quarter Quarter Error, %
A. Fission & Activation Gases 1 Total Release Ci NIA NIA NIA NIA 1.95E+01 I 2 Average Concentration uCi/mL NIA N/A NIA NIA Percent of ODCM Quarterly 3
dose limit NIA N/A NIA NIA B. Tritium 1 Total release Ci 2.48E-03 2.69E-03 1.21E-03 3.40E-04 2.37E+00 I 2 Averaae Concentration uCi/mL 1.57E-12 1.37E-12 7.65E-13 2.15E-13 3 Percent of ODCM Quarterly % 2.30E-03 2.61E-03 2.14E-03 6.13E-03 dose limit C. Dissolved and Entrained Gases 1 Total release Ci NIA NIA NIA NIA 2.03E+01 I 2 AveraQe Concentration uCi/mL NIA NIA NIA NIA 3 Percent of ODCM Quarterly % NIA N/A NIA NIA dose limit D. Gross Alpha 1 Total release Ci NIA NIA NIA NIA 2.00E+01 I 2 Avera!le Concentration uCi/mL NIA NIA NIA NIA E. Liquid Release Volume Total Release Liters 9.01 E+05 1.19E+06 6.65E+05 2.1 0E+05 F. Dilution Volume Total Release Liters 1.58E+12 1.97E+12 1.58E+12 1.58E+12 Page 23 of38
DRESDEN NUCLEAR POWER ST ATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table 3.1 (3) Liquid Effluents- Summation of All Releases: Unit3 1st 2nd 3rd 4th Est. Total Units Quarter Quarter Quarter Quarter Error %
A. Fission & Activation Gases 1 Total Release Ci NIA NIA NIA NIA 1.95E+01 I 2 Average Concentration uCi/mL NIA NIA NIA NIA Percent of ODCM Quarterly 3
dose limit NIA NIA NIA NIA B. Tritium 1 Total release Ci 2.48E-03 2.69E-03 1.21E-03 3.40E-04 2.37E+00 I 2 Averaae Concentration uCi/mL 1.57E-12 1.37E-12 7.65E-13 2.15E-13 Percent of ODCM Quarterly 3
dose limit
% 1.51E-03 9.38E-04 8.39E-04 1.48E-03 C. Dissolved and Entrained Gases 1 Total release Ci NIA NIA NIA NIA 2.03E+01 I 2 Averaae Concentration uCi/mL NIA NIA NIA NIA Percent of ODCM Quarterly 3
dose limit
% NIA NIA NIA NIA D. Gross Alpha 1 Total release Ci NIA NIA NIA NIA 2.00E+01 j 2 Averaae Concentration uCi/mL NIA NIA NIA NIA E. Liquid Release Volume Total Release Liters 9.01E+05 1.19E+06 6.65E+05 2.10E+05 F. Dilution Volume Total Release Liters 1.58E+12 1.97E+12 1.58E+12 1.58E+12 Page 24 of38
DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-0I0/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Lower Limits of Detection for Liquid Effluents Fission and Activation Gase µCi/mL Kr-87 l.00E-05 Kr-88 l.00E-05 Xe-133 l.00E-05 Xe-133m l.00E-05 Xe-135 l.00E-05 Xe-138 l.00E-05 Iodines 1-131 l.00E-06 Particulates Fe-55 l.00E-06 Sr-89 5.00E-08 Sr-90 5.00E-08 Mn-54 5.00E-07 Co-58 5.00E-07 Fe-59 5.00E-07 Co-60 5.00E-07 Zn-65 5.00E-07 Mo-99 5.00E-07 Cs-134 5.00E-07 Cs-137 5.00E-07 Ce-141 5.00E-07 Ce-144 5.00E-06 Other H-3 l.00E-05 Gross Alpha l.00E-07 The above limits are the ODCM required Lower Limits of Detection (LLD).
Page 25 of38
DRESDEN NUCLEAR POWER ST ATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-0I0/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table 3.2(1) Liauid Effluents Release Point: Unit 1 Nuclldes Continuous Mode Batch Mode Released 1st 2nd 3rd 4th 1st 2nd 3rd 4th Units Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-131 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zn-65 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cr-51 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zr-95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Nb-95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD o-99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Tc-99m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ba-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ag-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-55 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD H-3 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ci Ci Total for Period Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Page 26 of38
DRESDEN NUCLEAR POWER ST ATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table 3.2{2) Liauld Effluents Release Point: Unit 2 Nuclldes Continuous Mode Batch Mode Released 1st 2nd 3rd 4th 1st 2nd 3rd 4th Units Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-131 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zn-65 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cr-51 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zr-95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Nb-95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Tc-99m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ba-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ag-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-55 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD H-3 Ci 2.48E-03 2.69E-03 1.21 E-03 3.40E-04 <LLD <LLD <LLD <LLD Ci Ci Total for Period Ci 2.48E-03 2.69E-03 1.21 E-03 3.40E-04 <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Page 27 of38
DRESDEN NUCLEAR POWER ST ATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-0I0/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table 3.2(3) Liauid Effluents Release Point: Unit3 Nuclldes Continuous Mode Batch Mode Released 1st 2nd 3rd 4th 1st 2nd 3rd 4th Units Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-131 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zn-65 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cr-51 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zr-95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Nb-95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Tc-99m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ba-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ag-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-55 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD H-3 Ci 2.48E-03 2.69E-03 1.21 E-03 3.40E-04 <LLD <LLD <LLD <LLD Ci Ci Total for Period Ci 2.48E-03 2.69E-03 1.21 E-03 3.40E-04 <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Page 28 of38
DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table 4. Batch and Abnormal Release Totals Site Batch Releases A. Liquid Releases Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual
- 1. Number of Batch Releases 0 0 0 0 0
- 5. Minimum batch release duration min NIA NIA NIA NIA NIA B. Gaseous Releases Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual
- 1. Number of Batch Releases 0 0 0 0 0
- 5. Minimum batch release duration min NIA NIA NIA NIA NIA Abnormal Releases AL". IQUI"dRe Ieases um"ts Annua
- 1. Number of Abnormal Releases 0
- 2. Total Activity Ci O.OOE+OO B. Gaseous Releases Units Annual
- 1. Number of Abnormal Releases 0
- 2. Total Activity Ci O.OOE+OO RADIOLOGICAL IMPACT ON MAN Table 5 Total Body Dose from Gaseous and Liquid Effluents Unit 1 Unit 2 Unit3 Site Liauid mRem NIA 2.89E-08 2.89E-08 5.79E-08 Gaseous mRad NIA 2.24E-03 4.27E-04 2.67E-03 Radioiodines, tritium and mRem 1.03E-03 9.85E-04 3.58E-04 1.42E-03 Particulates Page 29 of38
DRESDEN NUCLEAR POWER ST ATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-0l0/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC T a bl e 51 . 0 raan Dose f rom Gaseous an d L"IQUI"d Effl uents Unit 1 Unit2 Unit3 Site Liquid mRem N/A 2.89E-08 2.89E-08 5.79E-08 Gaseous (Skin) mRad NIA 3.81E-03 7.25E-04 4.54E-03 Radioiodines, tritium and 2.71E-03 5.959E-02 1.497E-02 7.456E-02 mRem Particulates (Liver) (Thyroid) (Thyroid) (Thyroid)
Table 6 Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)
. Tvoes ofWaste Total Quantity Total Activity Est. Total Types of Waste (m3) Period (Ci) Error%
- a. Spent resins, filter sludges, 1.55E+02 6.95E+01 01/01-12/31 +/-25 evaoorator bottoms etc.
- b. Dry compressible waste, 6.67E+02 5.50E-01 01/01-12/31 +/- 25 contaminated eauic. etc.
- c. Irradiated components, control 9.34E+02 1.33E+00 01/01-12/31 +/- 25 rods, etc.
- d. Other (describe) 6.14E+00 6.65E-03 01/01-12/31 +/-25 2- Estimate of maior nuclide comoosition (bv waste tvcel Major Nuclide Composition %
Resins, Filters, and Evap Bottoms
- a. Cs-137 (1 .14E+00 Ci) 1.64 Mn-54 (3.47E+00 Ci) 4.99 Fe-55 (2.75E+01 Ci) 39.49 Co-60 (2.73E+01 Ci) 39.28 Zn-65 (5.14E+00 Ci) 7.38 Ni-63 (1.73E+00 Ci) 2.49 Cr-51 (9.67E-01 Ci) 1.39 Dry Active Waste
- b. H-3 (1 .06E-01 Ci) 19.26 Mn-54 (2.20E-02 Ci) 3.99 Fe-55 (2.33E-01 Ci) 42 .31 Co-60 (1.54E-01 Ci) 28 .02 Zn-65 (1.16E-02 Ci) 2.11 Cr-51 (6.70E-03 Ci) 1.22 Irradiated Components
DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Co-60 (6.05E-01 Ci) 45.34 Other
- d. Mn-54 (3.31 E-04 Ci) 4.97 Fe-55 (3.48E-03 Ci) 52.30 Co-60 (2.30E-03 Ci) 34.57 Zn-65 (1.75E-04 Ci) 2.64 Cr-51 (1.04E-04 Ci) 1.61 3- Solid Waste Disposition Number of Shipments Mode of Transportation Destination 17 Ground Energy Solutions-Oak Ridge, TN 20 Ground Energy Solutions--Clive, UT CHANGESTOTHEPROCESSCONTROLPROGRAM The Process Control Program procedure (RW-AA-100) Rev 12 was revised last on 8/17/2017. There have been no new changes for the 2020 year.
DIRECT RADIATION There are five identified sources of direct radiation dose that meets the definition referenced in 10CFR72.104 and must be added to the gaseous and liquid effluents dose. They are:
- 1. Skyshine
- 2. West Independent Spent Fuel Storage Installation (ISFSI) Pad
- 3. East ISFSI Pad
- 4. Condensate Storage Tanks (CST)
- 5. General Electric Facility located south west of the plant on Collins Road.
Skyshine The radioactivity source that results in the most significant offsite radiation dose at the Dresden Station is skyshine resulting from 16N decay inside turbines and steam piping.
The 16N that produces the skyshine effect is formulated through neutron activation of the oxygen atoms in the reactor coolant as the coolant passes through the operating reactor core. The 16N travels with the steam produced in the reactor to the steam-driven turbine. While the 16N is in transport, it radioactively decays with a half-life of about 7 seconds and produces 6-7 Me V gamma rays. Typically, offsite dose points are shielded from a direct view of components containing 16N, but there can be skyshine at offsite locations due to scattering of gamma rays off the mass of air above the steam lines and turbine.
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DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC The dose rate due to skyshine has been found to have the following dependencies:
- 1. The dose rate decreases as distance from the station increases.
- 2. The dose rate increases non-linearly as the power production level increases.
- 3. The dose rate increases when hydrogen is added to the reactor coolant, an action taken to improve reactor coolant chemistry characteristics.
To calculate offsite dose due to skyshine in a given time period, Dresden Station must track the following parameters:
- 1. The total gross energy fa produced with hydrogen being added.
- 2. The total gross energy Eo produced without hydrogen being added.
The turbines at the site are sufficiently close to each other that energy generated by the two operating units may be summed. Because the hydrogen addition system is normally in-service during plant operation, the conservative assumption that all power is generated during hydrogen addition can be used.
An initial estimate of skyshine dose is calculated using equation 5-1 on page 11.5.4 in the Dresden Offsite Dose Calculation Manual with the following assumptions from Table 5.1 on page 11.5-11:
Table 6.1 Parameters for Calculations ofN-16 Skyshine Radiation from Dresden Units 2 and 3 Location Occupancy Occupancy Shielding NumberK Activitv Hours (OH) Factor (OF) Factor (SF) Distance (R)
I Living at Home 8344 0.95 0.7 800 2 Fishing 416 0.05 I 610 These parameters are used to obtain an initial estimate of skyshine dose to the maximally exposed member of the public using Equation 5-1. If desired, more realistic parameters could be used in place of these to refine the estimate. For example, one could determine whether the nearest resident really fishes the specified number of hours at the specified location.
- a. The amount of time in a year that a maximally exposed fisherman would spend fishing near the site is estimated as 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per week for 8 months per year. This yields an estimate of:
[12 hours/week] x [(8 months/yr)/(12 months/yr)] x [52 weeks/yr]= 416 hour0.00481 days <br />0.116 hours <br />6.878307e-4 weeks <br />1.58288e-4 months <br />s/yr The remaining time is assumed to be spent at the nearest residence.
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DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-0I0/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC
- b. Distance to nearest residence (See ODCM Table 4-1).
- c. Estimated from a drawing of the site.
- d. The OFk is the quotient of the number of hours a location is occupied and the number of hours in a year. Thus OHk/8760 hours= OFk rounded to the 0.01 digit.
A survey of the nearest residents revealed that as they do enjoy fishing, they spend far less time than the above estimate in Table 6.1 above. In addition, because they live on the Kankakee River, they enjoy fishing at their homes rather than the designated 610 meters from the plant. As such, these assumptions have been adjusted in order to calculate a more accurate dose to the nearest resident at 868 meters from the plant with 8000 occupancy hours per year. This yielded a dose from Unit 2 due to skyshine of 2.258 mRem and 2.14 7 mRem from Unit 3 for a total of 4.40 mRem for the Site.
Independent Spent Fuel Storage Installation There are currently two ISFSI pads (east and west) located within the Protected area of the Dresden station. These casks contain the spent fuel from the reactor, and the pad is designed to store the spent fuel until a more suitable location is available. Optically stimulated luminescence dosimeters (OSLO) are placed on the fence around the pads and exchanged semi-annually to measure the direct dose from the ISFSI pad. The dose from each location is summed to acquire an annual dose for that specific location a known distance from the casks.
The equation for a point source is used (DR1*Di2= DR2*Di2) to calculate the annual dose to the nearest member of the public. The OSLO with the highest annual reading was used because they have a lesser contribution by percent of background radiation lending to more accuracy in the dose attributable only to the ISFSI pad Table 7: West ISFSI Pad Dose Calculations West ISFSI Pad DR2 Ql Q2 (mrem)
(mrem) (mrem) DR1 (ft) D1 (ft) D2 (ft) 36 322.3 343.4 665 .7 136 2640 1.77 37 647.1 884.1 1531.2 91 2640 1.82 38 616.0 898.7 1514.7 98 2640 2.09 39 182.8 245.4 428.2 90 2640 0.50 40 465.1 633.6 1098.7 61 2640 0.59 41 285.0 352 637 117 2640 1.25 Page 33 of38
DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Figure 1: West ISFSI Pad Table 7.1: East ISFSI Pad Dose Calculations Ql Q2 DR1 D1 D2 DR2 (mrem) (mrem) (mrem/yr) (ft) (ft) (mrem/yr) 17 88.3 113.8 202.1 88.8 2660 0.23 18 73.3 88.1 161.4 99.4 2660 0.23 19 66.4 97.4 163.8 102.3 2660 0.24 20 83.2 116.3 199.5 117.0 2660 0.39 21 219.2 309 528.2 118.4 2660 1.05 22 94.1 111.8 205.9 97.4 2660 0.28 Page 34 of38
DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Figure 2: East ISFSI Pad The highest annual dose received from the ISFSI pads were location 21 and 37. These results and distances from the center of the pad was used to calculate a dose of l.82E+00 mRem/yr for the West pad and l .05E+00 mRem/yr for the East pad. This resulted in a combined annual dose of 2.87E+00 mRem/
yr. due to direct radiation from storage of spent fuel on the IFSFI pads.
Condensate Storage Tank (CST)
The Condensate Storage Tanks (A and B) are a source of make-up water and has become contaminated through the operation of the plant. Although the level of contamination of the water inside the tank isn't at a level to produce a measurable dose rate, tanks are specifically listed in 40CFR 190 and a calculation of the annual dose to the nearest resident must be performed.
A direct radiation dosimeter (07), was placed on the northeast perimeter fence of the 2/3 Condensate Storage Tank identical to those on the ISFSI pad, and as such will use the same methodology to calculate an annual dose.
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DRESDEN NUCLEAR POWER STATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Table 7.2: CST Dose Calculations Ql Q2 DR1 D1 D2 DR2 (mrem) (mrem) (mrem/yr) (ft) (ft) (mrem/yr) 20 1 148 170.8 318.8 17 2540 0.014 Figure 3: 2/3 Condensate Storage Tanks Figure 4: Distance to Nearest Resident The approximate distance from the dosimeter on the fence to the edge of the tank is 17 ft. Using the same equation and the distance to the nearest residence (2543 ft.) DR1 *Di2=DR2*Dz2 it yields an annual dose of l .40E-02 mRem/year. These calculations are very conservative because the measured dose is almost entirely from background and not from the plant or storage tanks.
GE Hitachi Nuclear Energy Facility This facility is located southwest of the Dresden Nuclear Power Station on Collins Rd and is the location of a de facto high-level radioactive waste storage site that holds 772 tons of spent nuclear fuel. The used fuel from various nuclear generating sites across the country are stored in a spent fuel pool. The following table was taken from the NRC Technical Specifications for Safety Renewed License SNM-2500 for the GE Hitachi Energy Americas LLC Appendix A:
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DRESDEN NUCLEAR POWER ST ATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-0 l 0/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Since the source of radiation from the site is from the Uranium fuel cycle, the site is also required to ensure that the requirements of 40CFR 190 and 10CFR72 are met. Therefore, an Annual Operating Report is generated and submitted to the NRC to demonstrate that the regulatory limits are not exceeded to members of the public.
40CFR 190 states that the annual whole-body dose to a member of the public shall not exceed 25 mRem/yr from all sources of the uranium fuel cycle. This distinction dictates that the sum of the dose from the operation of the Dresden Nuclear Power Station and the GE Hitachi Nuclear Energy site cannot cause a member of the public to exceed a whole-body dose of25 mRem/year. As a result, communication from the two sites is necessary to exchange the calculated dose contributions to ensure this requirement is met. The dose contribution from the GE Hitachi site for the 2020 year was: 1.20E-01 mRem/yr.
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DRESDEN NUCLEAR POWER ST ATION 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Numbers: 50-010/50-237/50-249 Dresden Nuclear Power Station Units 1,2, 3 Licensee: Exelon Generation Company, LLC Attachment 1 RADIOACTIVE GROUNDWATER PROTECTION PLAN (RGPP)
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Digitally signed by Ahmed, Ahmed, Anjum S.
Date: 2021.02.25 875 North Easton Road Suite 10 Anjum S. 15:05:22-06'00' AMO Environmental Doylestown, PA 18902 Decisions 215-230-8282 (Phone) 215-230-8283 (Fax) Geologists Hydrogeologlsts www.amoed.com GIS Analysts Environmental Scientists Earth & E11l'iro11111e11tal Resour('e ,\/111111ge111e111 Cv11s11/ta11/\
Security-Related Information : Withhold From Public Disclosure Under 10 CFR 2.390 and S ILCS 140/7 (l)(a) & (mm)
February 16, 2021 Exelon Generation Company, LLC Dresden Generating Station 6500 North Dresden Road Morris, IL 60450-9709
Subject:
2020 Annual RGPP Monitoring Report Summary of Results and Conclusions Dresden Generating Station Morris, Illinois This letter report presents the summary of Radiologic Groundwater Protection Plan (RGPP) results for the 2020 groundwater and surface water monitoring rounds conducted at the Exelon Dresden Generating Station. RGPP data for previous monitoring rounds is summarized in AMO's semi-annual/quarterly reports.
Background
In 2006, Conestoga-Rovers & Associates (CRA) was retained by Exelon Nuclear to perform a hydrogeologic investigation at the Dresden Generating Station to evaluate whether groundwater at or near the Station has been impacted by releases of radionuclides. Prior to performing the investigation, CRA evaluated available information concerning historic releases, as well as components, structures, and areas of the facility that have the potential to release radioactive liquid to the environment.
The results of the 2006 investigation for groundwater samples collected within the protected area identified that almost half of the 39 wells showed measurable concentrations of tritium. This tritium comes from historic spills from above ground tanks and leaks of underground lines within the protected area. Groundwater samples collected outside the protected area showed no detectable tritium for 24 of the 26 wells. The two exceptions for the wells outside the protected area include wells DSP 149(R) and DSP-159-I (M).
The results of the fleet wide study for the Dresden Generating Station (the Station) are presented in the report, entitled Hydrogeologic Investigation Report, Fleetwide Assessment, Dresden Generating Station, Braceville, Illinois (Conestoga-Rovers & Associates, September 2006). The referenced report also provides detailed descriptions of the Station's location, surrounding features and land use, subsurface geology and hydrogeology, and a summary of groundwater use in the area of the Station.
GHD completed three five-year update hydrogeologic investigation reports for the Station (NE/ 07-07, Hydrogeologic Investigation Report, dated May 2011, December 2015, and December 2020). The reports summarized station activities since the 2006 hydrogeologic investigation report, including changes at the Station as well as RGPP sampling activities and groundwater flow. Relevant conclusions from the 2020 report are:
Letter Report 2020 RGPP Monitoring Report Dresden Generating Station
- Tritium is not migrating off the Station at concentrations greater than the State of Illinois criteria of200 pCi/L.
- Tritium concentrations in groundwater were detected at concentrations greater than the USEPA drinking water standard. The maximum tritium concentration at the end of 2019 was 33,850 pCi/L (MD-11).
Tritium concentrations greater than the USEPA drinking water standard were limited to the "B" CST, south of the Unit 3 and 3 Turbine Building.
- No gamma-radionuclides associated with licensed plant operations were detected at concentrations greater than their respective LLDs.
- Select transuranics U-233/234 and U-238 were occasionally detected in several wells since 2016. The concentrations are considered background.
- In 2019, Ni-63 was consistently detected in monitoring well MW-DN-1011 and MW-DN-1191. Per revision 9 of the RGPP, and to investigate Ni-63 in groundwater, the Station includes Ni-63 and Fe-55 analysis for all Source wells and all Long-Term Shutdown wells currently sampled as part of the RGPP.
- In 2019, multiple Sr-90 concentrations were detected above its LLD. Sr-90 was detected in samples collected from MW-DN-105S three of the four sampling rounds in 2019. Sr-90 was also detected in DSP-108 during the second quarter 2019 RGPP sampling round.
- AFE-1 remains an ongoing tritium source to groundwater. No new AFEs were identified based on results between 2006 and 2015.
- Extraction well RW-DN-l00S continued to withdraw tritiated water from the "B" CST area. Up until August/September 2019, groundwater withdrawal from RW-DN-l00S was on an intermittent basis.
Continuous groundwater extraction of RW-DN-lO0S began in September 2019. As of the date of the report, over one million gallons of groundwater was extracted from RW-DN-lO0S. The extracted groundwater is discharged to the Kankakee River through a permitted outfall (Outfall 002).
The next hydrogeologic investigation update is due by the end of 2025.
"B" Condensate Storage Tank Elevated tritium concentrations in surface water (Sewage Treatment Plant (STP) samples and RGPP surface water samples), shallow aquifer samples, and intermediate aquifer samples were detected during the 2nd quarter 2014 RGPP sampling round. The source of the tritiated groundwater was determined to be the "B" Condensate Storage Tank (CST) south of the Turbine Buildings. The groundwater sample collected from shallow aquifer well MD-11, which is in the immediate vicinity of the CST, had a tritium concentration of approximately 1.5 million pCi/L. Subsequent samples collected from MD-11 have had a maximum tritium concentration of approximately 2.3 million pCi/L (June 27, 2014). The CST was taken out of service and water from the CST removed. The CST was inspected and subsequently repaired in August 2015.
A tritium monitoring plan was developed and implemented in June 2014, with weekly sampling of surface water, storm sewer water, sewer treatment plant water, shallow aquifer groundwater, and intermediate aquifer groundwater to evaluate and delineate the tritium plume. A modified tritium monitoring plan was implemented in November 2014. Based on tritium data collected, the plume was relatively small and only encompassed the area between the CST and Turbine Building.
Two groundwater extraction wells (RW-DN-1 00S and RW-DN-101 S) were installed in January 2015 to assist in the mitigation of tritiated groundwater in the area of the CST. Aquifer testing was completed on the two AMO Environmental Decisions Page 2 of9
Letter Report 2020 RGPP Monitoring Report Dresden Generating Station extraction wells near the end of 2015. Results of the aquifer test concluded that only RW-DN-100S produced sufficient water to operate as a viable groundwater extraction well. RW-DN-1 0OS began intermittent operation during the 1st quarter 2016 and continued operating intermittently through August 2019. In August 2019, the extraction well began pumping groundwater on a continuous basis. The extracted water is discharged to the Kankakee River through NPDES permitted Outfall 002. Overall, tritium concentrations in the area of the CST continue to decrease since the CST was repaired.
As of the end of 2020, the maximum tritium concentration in the area of the CST was approximately 15,600 pCi/L (MD-11).
MW-DN-1191 Nickel 63 The sample collected from monitoring well MW-DN-1191, was analyzed for for tritium, gamma-radionuclides, gross-alpha and beta (dissolved and suspended), and strontium 89 and 90. Gross-beta (dissolved) was the only parameter detected at a concentration greater than their respective LLDs (detected at 124 pCi/L). Prior to the 2nd quarter 2017 sampling round, gross-beta (dissolved) concentrations in samples collected from MW-DN-1191 ranged between 19.6 pCi/L and 28.9 pCi/L.
Due to the elevated gross-beta detection, the sample was analyzed for hard-to detects. Hard-to-detect radionuclide Nickel-63 was detected at a concentration over 50 pCi/L. An investigation into the source of the Nickel-63 was completed and additional samples collected from MW-DN-1191 and surrounding wells. Results and recommendations of the evaluation are included in AMO's Evaluation ofNickel -63 detections in MW-DN-119/ Update (March 28, 2018). As a result of the detection ofNickel-63, samples collected from MW-DN-1191 are analyzed for hard-to-detects quarterly.
As of the end of 2020, the Ni-63 concentration in MW-DN-1191 showed a decreasing trend.
Current RGPP Summary In 2020, Exelon modified the corporate RGPP to include modified sample location designations and modified analytical procedural requirements. The newly adapted RGPP sample location designations include Background, Long-Tenn Shutdown, Mid-Field, Perimeter, and Source wells. Sample frequency and analyses are outlined below:
- Background - Annually for tritium; and every two years for gamma-radionuclide analyses.
- Long-Tenn Shutdown-Quarterly for tritium; annually for Fe-55, Ni-63, Sr-89, and Sr-90 analyses; and every two years for gamma-radionuclide and gross-alpha ( dissolved and suspended).
- Mid-Field - Semi-annually for tritium, and every two years for gamma-radionuclide analysis.
- Perimeter - Annually for tritium, and every two years for gamma-radionuclide analyses.
- Source - Quarterly for tritium; annually for Sr-89 & Sr-90 analyses; every two years for gamma-radionuclide and gross-alpha (dissolved and suspended); and every five years for Fe-55 and Ni-63, starting in 2021 .
Dresden Generating Station had a total of 59 wells (20 Background wells, 18 Source wells, six Mid-Field wells, ten Long-Tenn Shutdown wells, and five perimeter wells), that are sampled as part of the Station RGPP (EN-DR-408-4160 Revision 9) in 2020. Figure la shows the shallow aquifer RGPP sample locations and Figure lb shows the intermediate aquifer RGPP sample locations.
AMO Environmental Decisions Page 3 of9
Letter Report 2020 RGPP Monitoring Report Dresden Generating Station RGPP sampling at the Station is performed by A TI, under contract to Exelon. Laboratory testing is performed by Teledyne Brown Engineering. The laboratory data, field data, and depth to water readings are uploaded to the RACER website, which is a data repository for the RGPP sampling rounds. The uploaded data is used by AMO to evaluate the quarterly RGPP data.
Gross-Alpha Alert Level At Dresden Generating Station, gross-alpha (dissolved and suspended fractions) was analyzed annually from 2011 through 2019. In 2020, gross-alpha data was evaluated to establish an Alert Level for the dissolved and suspended gross-alpha fractions. The gross alpha data was evaluated by looking at the average concentration for each gross-alpha fraction for each well. Statistical outlier results were considered during the gross-alpha evaluation. An outlier is a value that is significantly higher or lower than most of the results, that can skew the results and not reflect the true dataset. Therefore, outlier results are not factored into the average gross-alpha concentrations. Outliers were established using methods an online website such as wikihow.com/Calculate-Outliers. Additional websites identified similar statistical models for removing outlier data.
EN-DR-408-4160 (Revision 9) established an Alert Level of three times the ongoing average gross-alpha concentration for each RGPP monitoring well that had gross-alpha analyzed more than one time and that will continue to be monitored for during future RGPP sampling rounds. According to the EN-DR-408-4160 (Revision 9), samples from the eighteen Source designated sample points and ten Long-Term Shutdown designated wells will be analyzed once every two years for gross alpha dissolved and suspended fraction in the future. The Alert Level will be able to account for fluctuations in naturally occurring alpha activity in the area of wells, while identifying an outlier that may be indicative of a potential release. Beginning in 2021, select transuranics will be analyzed if a gross alpha concentration exceeds the Alert Level in a particular well, to ensure that licensed material is not present in groundwater. If the results of the select transuranics analysis show no unusual activity, the gross-alpha result that triggered the select transuranics analysis, will be incorporated into the ongoing average concentration for that well.
Table 1 provides a gross-alpha ( dissolved and suspended) results summary as well as the average concentration and Alert Level for each well, respectively. Gross-alpha analysis was most recently performed on Source and Long-Term Shutdown designated wells, in 2019. Therefore, samples collected from Source and Long-Term Shutdown designated wells will be analyzed in 2021.
Gamma-Radionuclides Gamma-radionuclide analysis has been performed on RGPP samples (quarterly to annually) at Dresden Generating Station since 2006. This extensive sampling and analysis produced over 16,800 data records for the Station. Gamma-radionuclides have not been detected at concentrations greater than their respective LLDs, in RGPP samples submitted to the vendor laboratory since 2006. Therefore, in the 2020 RGPP, gamma-radionuclide analysis frequency was reduced from annual to every two years.
Gamma-radionuclide analysis was most recently performed in 2019. Gamma radionuclides were not detected at concentrations exceeding their respective LLDs in 2020. The next time gamma-radionuclide analysis will be performed is 2021.
Select Transuranics Select tran~uranics analysis is procedurally required annually for RGPP sample locations that were identified as AMO Environmental Decisions Page 4 of9
Letter Report 2020 RGPP Monitoring Report Dresden Generating Station Elevated designated wells in the historic EN-DR-408-4160 revisions and continued additional evaluation is warranted. Additionally, as part of the current EN-DR-408-4160 (Revision 9), select transuranics analysis is also warranted if a gross alpha concentration exceeds the Alert Level in a particular well.
Select transuranics analysis was performed on former Elevated designated wells MD-11, MW-DN-124S, and MW-DN-124I, during the 4th quarter 2020 RGPP sampling round. Additionally, select transuranics analysis was performed on MW-DN-1011 and MW-DN-119I during the 1st, 3rc1, and 4th, quarter 2020 RGPP sampling rounds.
Minor detections ofU-233/234 and U-238 were reported for MW-DN-1011 at 0.2971 pCi/L and 0.1755 pCi/L, respectively, during the 1st quarter 2020 RGPP sampling round. Table 2 provides a summary of select transuranics results (U-233/234 and U-238) since 2006.
Hard-to-Detects (fe-55 and Ni-63)
Hard-to-detect analysis (Fe-55 and Ni-63) is procedurally required annually for RGPP sample locations that were identified as Elevated designated wells in the historic EN-DR-408-4160 revisions and continued additional evaluation is warranted, as well as Long-Term Shutdown designated wells. Additionally, as part of the current EN-DR-408-4160 (Revision 9), hard-to-detect analysis is warranted on samples collected from Source designated wells once every 5 years, starting in 2021.
In 2020, samples collected from the nine Long-Term Shutdown designated wells and the former Elevated designated wells were analyzed for hard-to-detects (Fe-55 and Ni-63). Ni-63 was detected in the samples collected from Long-Term Shutdown well MW-DN-1 l 9I during the 1st, 3"1, and 4th, quarter 2020 RGPP sampling rounds with a maximum concentration of 26.6 pCi/L. Ni-63 was detected in the 1st quarter sample collected from Long-Tenn Shutdown well MW-DN-1011 at 9.61. Ni-63 was not detected in the samples collected from the former Elevated designated wells in 2020.
Sr-89 and Sr-90 Sr-89 and Sr-90 have been an annual procedurally required analysis on Detection, Long-Term Shutdown, and Elevated designated wells since sample point designations became part of the RGPP in 2010. EN-DR-408-4160 (Revision 9) states that Sr-89 and 90 analysis should be performed annually for Source and Long-Term Shutdown designated sample locations. In 2020, samples collected from the eighteen Source designated wells, nine Long-Term Shutdown designated wells, and one Mid-Field designated well (former Elevated designation) were analyzed for Sr-89 and Sr-90.
In 2020, Sr-90 was detected in the samples collected from MW-DN-105S and DSP-108 at 1.64 pCi/L and 2.39 pCi/L, respectively.
Summary of 2020 RGPP Sampling Rounds March 2020 RGPP Sampling Round Activities (1 st Quarter 2020)
Data Summary A total of 29 groundwater samples were collected during the 1st quarter 2020 sampling round. Per the RGPP, the Background, Perimeter, and Mid-Fielq designated wells were not sampled during the pt quarter 2020 RGPP sampling round. All samples were analyzed for tritium. Additionally, the samples collected from MW-DN-101 I and MW-DN-1191 were analyzed for select transuranics, hard-to-detects, and Sr-89 and Sr-90.
AMO Environmental Decisions Page 5 of9
Letter Report 2020 RGPP Monitoring Report Dresden Generating Station Tritium was detected in four shallow aquifer samples with a maximum tritium concentration of 17,800 pCi/L (MD-11 ). Tritium was detected in five intermediate aquifer samples with a maximum tritium concentration of 16,700 pCi/L (MW-DN-1241).
Ni-63 was detected in the groundwater sample collected from MW-DN-1011 and MW-DN-1191 at 9 .61 pCi/L and 12.4 pCi/L, respectively. The samples collected from MW-DN-1011 and MW-DN-1191 were also analyzed for select transuranics during the 1st quarter 2020. Detections of U-233/234 and U-238 were reported in the sample collected from MW-DN-1011 at 0.2971 pCi/L and 0.1755 pCi/L, respectively. Minor detections ofU-233/234 have been detected across the station at concentrations ranging between 0.1647 pCi/L and 1.091 pCi/L.
Minor detections ofU-238 have been detected across the station at concentrations ranging between 0.1465 pCi/L and 0.845 pCi/L.
The Station continued to implement the tritium monitoring plan for the "B" Condensate Storage Tank (CST).
The tritium concentrations in the area of the CST showed a decreasing trend at the Station. While the tritium concentration in MD-11 decreased from its maximum reported tritium concentration of approximately 2.29 million pCi/L, an elevated concentration persists in the area of the CST. As of March 25, 2020, the tritium concentration in groundwater at MD-11 was approximately 17,800 pCi/L. Tritium concentrations in samples collected from wells (other than MD-11) used to monitor the CST leak have decreased to less than 2,000 pCi/L, indicating the extent of the CST leak is confined to a small geographic area south of the Turbine Building.
AMO concluded that since the CST responsible for the release was repaired, there does not appear to be an active source of tritium to groundwater at the Station. Note that high existing tritium concentrations present a masking effect for detections of a new leak in the area of the CST.
Water Elevations All groundwater sample locations had depth to water measurements collected during the I st quarter 2020 sampling round. The 1st quarter 2020 groundwater elevation data was compared to the I st quarter 2019 sampling round to evaluate if changes in groundwater elevations occurred that may have an effect on groundwater flow direction. The variations in groundwater elevations have no significant effect on groundwater flow direction.
Based on comparison of groundwater elevations, the wells sampled effectively monitored groundwater conditions at the Station.
April - June 2020 RGPP Sampling Round Activities (2"d Quarter 2020)
The 2nd quarter 2020 RGPP sampling round was cancelled due to the Covid-19 pandemic. However, wells associated with the "B" CST monitoring plan were collected in the 2nd quarter 2020.
Data Summary Groundwater samples were collected from MD- I 1, MW-DN-107S, MW-DN-126S, and DSP-125 monthly during the second quarter 2020. Each sample was analyzed for tritium at the Station laboratory. As of the end of the 2nd quarter 2020, the tritium concentration in MD-11 was 12,600 pCi/L. Additionally, the tritium concentrations in MW-DN-126S increased to 11,700 pCi/L and the tritium concentration in MW-DN-107S increased to 14,700 pCi/L during the June 2020 sampling. The MW-DN-126S and MW-DN-107S are hydrogeologically downgradient from MD-11 and the CST. The increased activity is likely due to plume movement from MD-11 .
AMO Environmental Decisions Page 6 of9
Letter Report 2020 RGPP Monitoring Report Dresden Generating Station July 2020 RGPP Sampling Round Activities (3 rd Quarter 2020)
Data Summary A total of 27 groundwater samples were collected during the yd quarter 2020 sampling round. Per the RGPP, the Background, Perimeter, and Mid-Field designated wells were not sampled during the 3rd quarter 2020 RGPP sampling round. Additionally, samples could not be collected from MW-DN-1171 and MW-DN-140S due to inaccessibility. All samples were analyzed for tritium. In addition, the Long-Term Shutdown-designated well samples were analyzed for hard-to-detects, and Sr-89 and Sr-90. Source wells were also analyzed for Sr-89 and Sr-90. The sample collected from MW-DN-1191 was also analyzed for select transuranics.
Tritium was detected in seven shallow aquifer samples with a maximum concentration of 13,600 pCi/L (MD-11 ).
Tritium was detected in eleven intermediate aquifer samples with a maximum concentration of 16,100 pCi/L (MW-DN-1241).
During the 3rd quarter 2020 RGPP sampling round, Ni-63 was detected in the samples collected from MW-DN-1191 at 17.8 pCi/L). The sample collected from MW-DN-1011 was also analyzed for select transuranics during the 3 rd quarter 2020. No transuranics were detected at concentrations greater than their LLD during the 3rd quarter 2020 RGPP sampling round.
Sr-90 was detected in the samples collected from DSP-108 and MW-DN-105S at 2.39 pCi/L and 1.64 pCi/L, respectively.
The Station continued to implement the tritium monitoring plan for the "B" Condensate Storage Tank (CST).
The tritium concentrations in the area of the CST showed a decreasing trend at the Station. As of September 29, 2020, the tritium concentration in groundwater at MD-11 was approximately 12,700 pCi/L. Tritium concentrations in samples collected from MW-DN-107S and MW-DN-126S, which increased to over 10,000 pCi/L during the 2nd quarter 2020, decreased to less than 500 pCi/L during the 3 rd quarter 2020.
AMO concluded that since the CST responsible for the release was repaired, there does not appear to be an active source of tritium to groundwater at the Station. Note that high existing tritium concentrations present a masking effect for detections of a new leak in the area of the CST.
Water Elevations All groundwater sample locations had depth to water measurements collected during the 3rd quarter 2020 sampling round. The 3rd quarter 2020 sampling round groundwater elevation data was compared to the 3 rd quarter 2019 sampling round to evaluate if changes in groundwater elevations occurred that may have an effect on groundwater flow direction. The variations in groundwater elevations have no significant effect on groundwater flow direction. Based on comparison of groundwater elevations, the wells sampled effectively monitored groundwater conditions at the facility.
November 2020 RGPP Sampling Round Activities (4th Quarter 2020)
Data Summary A total of 56 groundwater samples were collected during the 4 th quarter 2020 sampling round. Samples could not be collected from MW-DN-106S and MW-DN-1081 due to the wells being damaged. Additionally, a sample could not collected from MW-DN-1171 due to the well being inaccessible at the time of the 4th quarfer 2020 AMO Environmental Decisions Page 7 of9
Letter Report 2020 RGPP Monitoring Report Dresden Generating Station RGPP sampling. All samples were analyzed for tritium; all Source designated wells, as well as MW-DN-119S, and MW-DN-1241, were also analyzed for SR-89 and Sr-90; samples collected from MD-11, MW-DN-1011, MW-DN-119S, MW-DN-1191, MW-DN-124S, and MW-DN-1241 were analyzed for hard-to-detects; and samples collected from MD-11, MW-DN-124S, and MW-DN-1241 were analyzed for select transuranics.
Tritium was detected in seven shallow aquifer samples with a maximum concentration of 12,600 pCi/L (MD-11 ).
Tritium was detected in fifteen intermediate aquifer samples with a maximum concentration of 15,000 pCi/L (MW-DN-1241).
During the 4th quarter 2019 RGPP sampling round, Ni-63 was detected in the sample collected from MW-DN-MW-DN-1191 at 26.6 pCi/L. Select transuranics and SR-89 and Sr-90 were not detected in the samples collected during the 4 th quarter 2020 RGPP sampling round.
The Station continued to implement the tritium monitoring plan for the "B" CST. Extraction well RW-DN-IO0S was not operational from the end of September to the middle of December 2020 due to pump and totalizer issues.
The extraction well became operational again the week of December 14, 2020. As of December 8, 2020, the tritium concentration in groundwater at MD-11 was 15,600 pCi/L. Tritium concentrations in samples collected from wells (other than MD-11) used to monitor the CST leak have generally decreased to less than 1,000 pCi/L, indicating the extent of the CST leak is confined to a small geographic area south of the Turbine Building.
AMO concluded that since the CST responsible for the release was repaired, there does not appear to be an active source of tritium to groundwater at the Station. Note that high existing tritium concentrations present a masking effect for detections of a new leak in the area of the CST.
Water Elevations All sampled groundwater locations had depth to water measurements collected during the 4th quarter 2020 sampling round. Groundwater elevations and groundwater flow direction for the shallow aquifer are provided on Figure 2a and groundwater elevations and groundwater flow direction for the intermediate aquifer are provided on Figure 2b. Based on the groundwater flow depicted on figures 2a and 2b, the wells sampled effectively monitored groundwater conditions at the facility.
2021 RGPP Sample Locations The 2020 RGPP sample locations effectively monitored Systems, Structures, and Components of the Station.
Therefore, RGPP sample locations identified in Attachment I ofEN-DR-408-4160 (Revision 9) should continue to be sampled in accordance with Attachment 2 ofEN-DR-408-4160 (Revision 9).
Summary of 2020 RGPP Conformance The Station conformed with its RGPP with respect to sampling protocol for 2020.
AMO Environmental Decisions Page 8 of9
Letter Report 2020 RGPP Monitoring Report Dresden Generating Station Conclusions Based on the review of the data collected during the 2020 RGPP sampling rounds AMO concludes:
- The 2nd quarter 2020 RGPP sampling round was cancelled due to the Covid-19 pandemic. However, wells associated with the "B" CST monitoring plan were collected to continue monitoring groundwater in the area of the CST.
- The Station continued to implement the tritium monitoring plan for the "B" CST. The tritium concentrations in the area of the CST showed a decreasing trend at the Station through 2020. While the tritium concentration in MD-11 decreased from its maximum reported tritium concentration of approximately 2.29 million pCi/L, an elevated concentration persists in the area of the CST. However, tritium concentrations in samples collected from wells (other than MD-11) used to monitor the CST leak have generally decreased to less than 1,000 pCi/L, indicating the extent of the CST leak is confined to a small geographic area south of the Turbine Building.
- There does not appear to be an active source of tritium to groundwater at the Station since the repair of the CST. Note that high existing tritium concentrations present a masking effect for detections of a new leak in the area of the CST.
- The Station continued to monitor Ni-63 concentrations in intermediate aquifer wells MW-DN-1191 and MW-DN-1011. 'The Ni-63 concentration in MW-DN-1191 have been decreasing since first detected in 2017. The Ni-63 concentration in MW-DN-1011 is slowly increasing. MW-DN-1011 is hydraulically downgradient from MW-DN-1191.
- Based on analytical data collected in 2020, there does not appear to be an active source of tritium to groundwater.
- Based on the evaluation of groundwater flow direction, the wells sampled effectively monitored groundwater conditions at the facility.
AMO Environmental Decisions Page 9 of9
Dresden Generating Station Table 1 Exelon Corporation Summary of Gross-Alpha Results a-Alpha*--
IITE I -ID DSP-105 DSP-108 DSP-107 VIIIIA-1.71 1.27 1.n ALl!RT LEVEL 5.14 3.80 5.15 Foll 1.05 ID1Z 0.811 1.04 D.147 1.15 D.744 1.03
.hd
.,.Jun 3.08 2.14 2.18 1.9 1.81 1.74 2.n Jun 2.5 1.77 21111 Oct Foll 21117 1.79 1.53 2.73 Foll Jun 1.31 1.07 1.17 21111 1.39 1.1 1.21 I
DSP-108 3.85 11.54 1.05 1.37 7.87 12.A 5.79 2.95 3.84 4.71 3.2 DSP-122 flOl\//01 IOIV/UI 8.93 -- - - - - -
DSP-123 2.00 8.00 D.193 - 1.99 1.71 2.45 2.11 U3 1.7 1.16 1.95 DSP-124 DSP-125
,OIV/01 1.21 IOIV/01 24.83 0.11
- 4.13 -
9.1 -- - -
8.14
- 8.81
- 35.4
-- 12.S --
10.7
- 5.11
- - u Ml).11 1.23 3.70 - - 5.17 - - - - - - - - - - D.977 - - - 1.22 1.87 - 1.22 1.21 -4.8 - 0.978 0.918 1 1.59 MW-OM-1DU 2.89 I.GI 2.39 1.25 2.32 1.26 3.05 - 4.81 1.INI MW-ON-101-S 5.11 15.32 8.2 1.54 5.18 4.33 1.7 6.55 4.21 3.3 MWDN-102~ 2.30 1.89 - - D.875 -- - 1.48 -- 1.29 -- - 3.03 4.GI - 2.63 - - - 13.& - U8 - D.751 MWDN-102-S 19.59 51.71 - - 9.44 - - 13.9 15.8 - 19.9 21.3 - 51.1 - - - 35.2 - - 20.2 - - 14.2 MWDN-104-s ,OIV/01 IOIV/01 2.44 - -
MWDN-108-s IOIV/01 IOIV/01 - -- 1.42 MWDN-107-S 8.12 24.35 -
- -- 8.37 9.88
- - - u, - -- --
MW-OM 1.53 4.58 1.39 1.13 D.821 1.73 1.87 -- 222 3.35 MW-ON-IO!M MW-ON-109-s 2.76 4.AD 8.29 13.21 1.04 3.74 --
D.499 2.74 D.936 4.01
- 1.97
- 1.53 4.29 8.52 4.0Z 5.93 3.71 5.15 3.71 5.17 D- MWDN-11~
MW-ON-113-s MW-ON-11~
2.31 2.24 3.GI 8.t3 8.71 9.04 D.415 2.34 3.31 D.531 1.78 3.17 2.58 1.14 3.G1 1.54 2.DI us 4.18 u
3.02 3.77 3.91 3.16 3.79 3.18 2.1 1.81 2.95 1.65 2.74 MW-OM-116-s 3.09 1.21 2.53 3.55 1.15 5.21 4.13 3.12 1.57 2.08 MW-ON-117~ 1.06 3.11 1.24 U14 1 1.13 MW-ON-11&-s 1.25 3.74 - - - 0.745 - 1.24 - 1.14 D.197 - u, - - - 2.34 - - 0.551 - - I.II I -
MWDN-11~
MWDN-119-s 3.41 3.49 10.23 10A8
- 1.41- -
-- --- 1.16 2.35 3.82 1.55 2.42 4.23 3.11 us
-- -- 4.44 7.23 z.a.t 1.57 1.25 2.95 3.03 3.15 2.24 2.91 l 3.29 MW-ON-122~
MWDN-12~
IOIV/01 3.99 IDIV/01 11.91 2.13 -- - -
- -2 -
3.35 -
9.99 4.DI - -
5.33 7.19
-- -- 3.74 4.15 MW-ON-124-s 4.21 12.112 2.83 1.71 4.74 5.71 5.77 6.35 3.n 2.18 MWDN-125-s 3.G3 I.DI 2.152 1.13 4.13 1.31 3.63 JO 5.32 1.8 MW-ON-12&-S 7.50 22.50 - - - - 11 .5 12.7 - - 13.1 8.88 - 4.11 - - - 6.15 - 1.56 3.48 MW-ON-127-S 2.45 7.35 - -
2.1
- 2.38
- 5.27 1.01
- 2.03 - -
- - 5.19 -- -
0.478 -- -
0.313 MW-ON-I 34-s 2.71 1.33 - 1.15 2.82 3.65 3.77 4.31 - 1.G6 2.11 2.21 11'1111-DM-135-s 2.41 7.44 - - - - - - 2.11 4.2 - - 1.64 1.7 - 3.21 - - - 2.08 - - 1.5 - - 2.71 MW-OM-136-s s.az 15.GB - - - - - - - 2.31 3.21 - - 4.51 BM - 7.55 - -- - - 3.65 - - 3.27 - - 1.14 MW-ON-137-S UI 14.83 1.52 1.51 4.9 5.57 6.65 - 5.48 3.43 - 2.81 MW-ON-140-s IOIV/01 IDIV/01 - -- - -- - - 6.59 - - - - - - - - - - - - - - - -
MW-ON-141-S 0.92 2.75 0.137 0.769 - 2.01 1.33 1.12 - 0.7B 0.722 0.152 MW-ON-142-S 4.51 13.87 - - - - - - - - - - - - - -- - -- 7.27 -- 2.91 - 4.31 - 3.66 MW-ON-143-s 3.10 t.31 - - - - - - - - - - - - - - 2.16 - 4.71 - 3.08 - - 2.41 MW-ON-144-s 3.16 10.97 - - - - - - - - - - - - - - - - 4.17 - - 4.78 - - 3.27 - - 2.43 R-lnpCl/l Page 1 of 2 AMO Enlll_,., 11<<:lMon*
Dresden Generating Station Table 1 Exelon Corporation Summary of Gross-Alpha Results lffE I DSP-105 DSP-108
-A-(.outllllSI 0.86 0.79 ALERT LEVEL 2.59 2.38 Felt 2111 Jun 21112 0.82 0.809 Jun llar 211S 0.793 0.793 Jul 21114 Jun 0.63 0.63 Jun 0.923 0.923
-AlpM*-...--
21111
-- -- 0.599 0.599 21111 A*
Oct Felt 2117 0.817 0.817 Felt 1.13 1.13 21111
-1.39 ua 2111t l
DSP-107 0.86 U7 0.345
- - -- - 0.349 - - 0.381 - - 0.63 0.911 - 4.7.f - - -- - 0.811 - - 1.13 -
0.898 OSP-108 0.71 2.13 - - - 0.348 - - 0.381 0.851 - 0.83 0.933 - 0.805 -- 0.819 - -- 1.14 - 0.897 DSP-122 DSP--123 10111/01 0.70 10111/01 2.10 0.245 0.814 0.347 0.601 1.9
- 0.923 - 0.808 - -
0.817 1.18 0.719 DSP-124 10111/01 IDIIIIIII 0.818 DSP-125 1.85 4.94 1.28 D.88 1.89 1.9 0.892 2.88 2.21 1.85 3.n
- - - - - - - - - 0.711 -- - - -
M0-11 0.70 2.10 0.839 - o.m 0.347 0.822 0.824 0.844 0.898 1 0.528 MW-ON-101~ 0.84 2.52 0.78 0.267 1.24 0.923 1.04 - 0.82 - 1.14 0.719 MW-ON-101-S 1.15 5.56 - -- - 1.12 - - 0.695 - 1.24 - 0.982 - 3.41 - - - 1.3 ..H - - 1.73 - 3.92
- - - -- 1.8 - - - -- - -- -
MW-ON-102~ 1.02 3.05 0.495 0.498 0.63 0.359 0.381 2.33 1.73 0.752 MW-ON-102-S 2.82 8.45 3.58 1.18 0.63 2.14 4.99 3.8 1.37 5.18 MW-ON-104-s IDIV/01 IOIV/01 0.82 MW-ON-106-S IOIV/01 IDIV/01 - - 1.17 MW-ON-107-S 4.73 14.19 - - - 2.5 8.91 MW-ON-1~ 2.12 8.37 0.84 - - - - 0.781 - - 0.808 - 1.24 - 1.15 - - - - 38.3 MW-ON-109-l 1.02 3.05 - - - 0.502 - - 0.804 - 1.24 - 0.51 - 0.357 - - - 1.84 - - 1.6 - - 1.48 MW-ON-109-s 1.20 3.81 -- -
0.398 - - 0.503 -
1.24
- 0.501 -- 2.05 -
1.84 -
- 1.6 1.48 MW-ON-11~ 2.70 1.09 1.18 - 0.499 1.3 1.21 0.381 20.18 1.15 7.89 7.27 MW-ON-113-s 4.70 14.10 -- - 0.849 - - 1.63 0.446 - 2.47 3.24 - 15.7 - - - 7.59 -- - 8.82 - 1.94 Drud*
MW-ON-11~ 0.70 2.11 1.02 0.503 1.24 0.503 0.374 0.823 0.827 0.728 MW-ON-119-s 0.79 2.37 -- -
0.89 0.502 1.24 -
0.508 0.748 -
- - 1.02
- - 0.871
- - 0.747 MW-DN-11 N 0.82 2.48 0.807 0.491 0.831 I 1.15 MW-DN-118-s 0.73 2.211 -
0.622 -
- 0.491 -
1.79 0.511 0.938 0 .809 - -
0.182 -
- - 0.192 I -
MW-DN-11M 0.89 2.IMI 0.82 1.03 Ul 0.515 0.912 2.78 0.85 0.501 0.911 1.54 I 1.03 MW-ON-119-5 2.35 7.08 - - 0.822 - 0.557 - 1.24 - 0.509 - - 2.38 - 3.73 - - 4.28 - - 5.52
- - - - 0.491 - - - - -
--- - - - -1.5 - - -
MW-ON-122~ IOIV/01 IOIV/01 3.2 - - -
MW-ON-12~ 1.09 3.27 0.345
- 0.358
- 0.382
- 0.665 -
1.21 1.21 -- 1.73 -
2.78 -
- 1.5 MW-ON-124-5 1.83 4.90 0.49 - 1.21 1.28 2.41 2.17 3.48 0.982
-- - - 1.33 - - - - - - -
MW-ON-125-s 1.14 3.43 0.798 1.21 1.14 0.739 2.17 1.51 1.44 MW-ON-126-S 1.75 5.24 1.5 1.21 1.29 1.79 2.77 1.5 2.57 MW-ON-127-S 0.92 2.77 0.817 0.488 1.21 1.34 0.731 D.815 0.182 1.13 MW-DN-134-5 MW-ON-135-s -
o.n 0.75 2.15 2.25 --- -- -- -- -
0.925 1.08 0.513 0.538 0.857 0.857 0.345 0.345 -
o.n 1 0.n1 0.807 0.143 -
0.1188 0.932 0.8116 0.814 MW-DN-138-5 1.13 3.39 0.4 0.545 - 0.857 0.348 2.55 - 1.78 1.35 1.43 MW-DN-137-S 1.41 4.24 - - - - - - 1.25 0.845 - - 1.1 - 0.351 2.5 - - - - 2.81 - - 1.42 - 1.44 MW-ON-140-5 MW-ON-141-S IOIV/01 0.86 IDIV/01 2.58 --- -
1.49 0.973 0.513
-- 1.24 0.504 0.894 0.83
-- 1.03 0.884 MIIV-DN-142-S 1.18 3.49 - 2.82 0.591 1.47 1.43 MIIV-DN-143-s 1.25 3.78 - - - - - - - - - D.819 - -- 1.61 - -- 1.43 -- 0.982 MIIV-DN-144-5 1.19 5.18 - - - - - - - - - - - - - - - - 3.23 - 1.15 - 1.44 - 1.02 Elqllanatlon:
2.13 - - . . - ,.,,..,.d from 1he caballon ol 1he average concennllon that- uaod ID ....,Jato Iha Alert i....et.
RHullalnpCUI. Pqe2 Df 2 AMOl!nlfl-u/ o.c,.,._
Dresden Generating Station Table 2 Exelon Corporation Summary of U-233/234
- DSP-107 DSl'-122 DSP-123 OSP-12
-D ,...
0.Dlllm o.m:s 0.1M7 0.03151121
- *11
... Doc
--... --... -... ... -- - - 0d ,... 1111'
.... ,... -... - 0d
- - -- Doc and U238 Results 0.1321 I DSP.125 Mtl-ll 0.DSII o., . 0.1011 0Jm41 0.1:ZSZ 0 .1154 0.1121 0- o.t:m 0.147 MWON-101-4 0.ll04 0Jl5172 0.&7 0.2IOS 0.527 um 0.2711 0.5173 U81'1 MWON-1D2"" 0.5114 MW-ON-1IJ2,.,S D.1111 MWON-104-$ 0.0508 I MW-ON-tQI.I 1.081 MW-ON-107....S o.:m 0.9135 M'#ON-1 1)-1 liM',ON-1'W 0.37IO I .......
MW-DN-111-1 0.MOI 0,0t171 0,1421 OJ>Z29 0.11217 o.- 0,1045 0.1441 0.11,a D.1117 o.-
MW-ON-122-1 0.:12<
MWON-12~ 0.05192 o.- 0.00071 0.1212 0.1'43 0- o.,m 0.104 0.1055 0.G3851 0.11*
MW-DN-124-S O.o5753 0.17CI 0.1171 o.- o.- D.113 0.02588 0.1175 0.1111 sw-DN-101 I 0.-
SW-ON-t CD I I
0,441 o.m7 I
sw-oN-104 0.7M sw-oN-105 0.553 SW-ON-tOI 0.411
- IDSP-107 DSP-122 DSP.123 DSP-124
-D 0.o71211, o.,eos 0.0743' 0.00005 Doc .., ... - -- ... - - -- - **
I 0d ,...
- -- - .. - Doc DSP.125 0.1171 o.,m 0.1252 0.1CNII o.oe111 0.11 24 IA'IJ.ON.101.a 0.lmlCI 0.1051 0.111531 0J157'7 0.1411 0.1ZS3 0""30I 0 ,1215 o.,m 02114 o., . 0.11113 0.124 0.17'55 MW-ON-102-S D.1111 UW-ON-tDW o.....
MWON-1084 o....
MW-DN-107.S 0.4338 o.....
UW.ON-1~ 02105 lifltl,,QN.ttl-1 o...... I IIWOH-113-S o..a, I IIW-ON-111-1 I 0.4422 0,1124 0-001* o.- 0.11217 0.011* O.Dl333 o.,sse O.tCD 0.1341 0.11 1
_,>4-1 MW-ON-1~
M\N-DN-124-S I 0.1415 0.:,512 0.0,405 .......
0.081 4 0.1811 0.1532 0J.15121 0.21121 0.207 o.,* . ..,,.
0.1141 OJIOIZI 0.1274 0.122 0.1111213 o.-
0.1191 sw.oN-101 0.5611 SWON-102 0.53112 SWON-10I 0.
_, sw-oN-104 SWON-106 SW.QN-101 Q.4112 0.3171 0.5152 1
- Ir* -mpll ... ~on p rlc:ultr dlt , 0/lft th l'IWI* conontnltlon II natd.
Results In pCIA. Pago 1 of 1 AMO Envlronnumtal DIM:bllon
MW-DN-143-S MW-ON-144-S
- MW-DN-142-S II MW-DN-134-S MW-ON-135-S MW-ON-136-S MW-DN-137-S *+
s MW-DN-106-S I
- *: (!) (!)
(!)
MW-ON-110-S MW-DN-104-S
- e*
MW-ON-140-S MW-DN-116-S MW-DN-101-S
(!)
- MW-ON-141-S (!)
(!)
MW-ON-119-8
. .* *'.*L.**,. * * (!)
- I MW-DN-109-8 e MW-DN-107-S MW-DN-111-S e *
- MW-DN-114-S MW-DN-118-S MW-DN-105-S MW-ON-112-S e RW-DN-101-S (!)
MW-DN-124-S RW-DN-100-S* "' MW-DN-115-S MW-DN-125-S
- e
- MD-11 MW-ON-127-S
- MW-DN-126-S MW-DN-102-S
- MW-DN-113-S MW-DN-122-S *
- MW-DN-103-S DSP-159S 0 500 1,000 Feet
- 0 400 800 Feet Explanation:
Shallow Aquifer RGPP Monitoring Location
- Background Figure 1a Long-Term Shutdown RGPP Sample Locations Mid-Field Shallow Aquifer
- Perimeter Exelon Corporation
- Source Dresden Generating Station
DSP-147
\
DSP-148 OSP-149R l
I
- I **
0 00 0 DSP-150 DSP-122
- MW.ON-116-1 DSP-123 0
MW.DN-101-1
- 0
~
- 0 MW-DN-119-1 0
- 0 MW-DN-117-1 MW.DN-108-I
- !e 0 0 DSP-108 MW.DN-109-I *
© DSP-107 DSP-126 DSP-124
- MW-DN-114-1
- DSP-106
- MW-DN-112-1
- MW-DN-124-1 MW-DN-115-1 DSP-125 DSP-154 MW.DN-122-I *
- MW.DN-103-I DSP-159M 0 500 1,000
- 0 400 800 Feet Feet Explanation:
lntennedlate Aquifer RGPP Monitoring Location
- Background Figure 1b 0 Long-Term Shutdown RGPP Sample Locations Mid-Field Intermediate Aquifer
- Perimeter Exelon Corporation
- Source Dresden Generating Station
- + s
, - "" ..., 2/3 Discharge MW-DN-104-S 2/3 Cribhouse
, _..., ""..., ~ 7. 508.03, , 505.01 MWON-116-S MW-ON-101-S MW-ON-110-S II \ * \ e e eMW-ON-140-S
-. e
- 504.99e 1 Cribhouse 505.31 505.44 510.50 I
- 508.16~= -----.:
I . MW-ON-141-S e - MW-ON-119-S I 509.05 506.43 "",
... "Sa
... ... ... II'*
MW.ON-109-S
- so8 _
.l 509.46 MW.ON-107-S MW.ON-111-S 513.00 ~
\
~ ---
511.21
- s,o .
MW-ON-112-S e e MW-ON-127-S 512.06
.!_ MW.ON-115-s 509.95 MW-ON-105-s 513.37 °MIW-CIN'\;~ e \_ 511.24
~
MWON-126-S __ - -
e 512.29 - - - - - - - -
- s12
- MW.ON-102-S ~
-- s~ \ * ', - - - -
'\ MW.ON-113-s
, , 515.n MW.ON-103-s 507.97
\
\ ' . '~....
~
~
0
% \
"'I \
0 500 1,000
====-----===::::::::,Feet Explanation:
Figure 2a
- 4th Qtr. 2020 RGPP Shallow Aquier MonHoring Location 4th Quarter 2020 RGPP Groundwater Elevation Contour Groundwater Elevations and Inferred Groundwater Elevation Contour Groundwater Elevation Contours
__. Groundwater Flow Direction Surface water and Shallow Aquifer 507.97 - Groundwater elevation wHh respect to mean sea level Exelon Corporation Dresden Generating Station
OSP-148 507.65 s
-~'o e OSP-149 (R) 505.51
- - T ..
DSP-123 MW.ON-101-1 504.85 504.43 e - MW-ON-119-1 506.69 * ._
e DSP-108 506.47
- sa~-
- * \
OSP-125\
e MW.ON-115-1 509.21 512.11 513.06 \ 509.56 '.s:i?c9
\ \
\
\
\
\
' *~)'o.
MW.ON-103-I * '~
507.05 ""*
' '~
~-
0 e 0 500 1,000 OSP-1~
508.48 ----======-----===:=:::::iFeet Explanation: Figure 2b
- 4th Qtr. 2020 RGPP Intermediate Aquifer Monitoring Location 4th Quarter 2020 RGPP Groundwater Elevation Contour Groundwater Elevations and Inferred Groundwater Elevation Contour Groundwater Elevation Contours
--+ Groundwater Flow Direction Intermediate Aquifer 507.97 - Groundwater elevation with respect to mean sea level Exelon Corporation Dresden Generating Station