ML14128A039

Attachment 1 - 2013 Radioactive Effluents Release Report - Volume 1

ML14128A039
Person / Time
Site:	Millstone
Issue date:	04/30/2014
From:	Dominion Nuclear Connecticut
To:	NRC/FSME
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14-189
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Serial No.14-189 Docket Nos. 50-245 50-336 50-423 License Nos. DPR-21 DPR-65 NPF-49 ATTACHMENT I 2013 RADIOACTIVE EFFLUENTS RELEASE REPORT VOLUME I MILLSTONE POWER STATION UNITS 1, 2, AND 3 DOMINION NUCLEAR CONNECTICUT, INC. (DNC)

Millstone Power Station 2013 Radioactive Effluents Release Report Volume 1 Gaseous Effluents aI NI Dominion Nuclear Connecticut, Inc.

Unit License Docket 1 DPR-21 50-245 7`Dominion 2 DPR-65 50-336 3 NPF-49 50-423

Table of Contents Table of Contents............................................................................................................................................. 1 List of Tables................................................................................................................................................... 2 References....................................................................................................................................................... 3 Introduction..................................................................................................................................................... 4 1.0 Off-Site Doses .......................................................................................................................................... 5 1.1 Dose Calculations............................................................................................................................ 5 1.1.1 Gaseous Effluents ...................................................................................................... 5 1.1.2 Liquid Effl uents................................................................................................................... 6 1.2 Dose Results ..................................................................................................................................... 6 1.2.1 Gaseous Effluents ...................................................................................................... 6 1.2.2 Liquid Effl uents................................................................................................................... 7 1.2.3 Analysis of Results ...................................................................................................... 7

2. 0 Effl uent Radioactivity............................................................................................................................. 12 2.1 Gaseous Effluents ........................................................................................................................... 12 2.1.1 Measurement of Gaseous Radioactivity..................................................................... 12 2.1.2 Estimate of Errors........................................................................................................ 14 2.1.3 Gaseous Batch Release Statistics ................................................................................. 14 2.1.4 Abnormal Gaseous Releases........................................................................................ 14 2.1.5 Gaseous Release Tables .............................................................................................. 14 2.2 Liquid Effl uents .............................................................................................................................. 31 2.2.1 Measurement of Liquid Radioactivity........................................................................... 31 2.2.2 Estimate of Errors......................................................................................... 31 2.2.3 Liquid Batch Release Statistics................................................................................... 32 2.2..4 Abnormal Liquid Releases.......................................................................................... 32 2.2.5 Liquid Release Tables ................................................................................................. 32 2.3 Solid Waste ..................................................................................................................................... 41 2.4 GroundwaterMonitoring............................................................................................................... 53 3.0 Inoperable Effl uent Monitors................................................................................................................. 55 4.0 OperatingH istory.................................................................................................................................. 56

5. 0 Errata..................................................................................................................................................... 59 I

List of Tables Table 1-1 Off-Site Dose Summary from Gaseous Effluents - Units 1, 2,3 ............................................................................ 8 Table 1-2 Off-Site Dose Summary from Liquid Effluents - Units 1, 2,3 .............................................................................. 9 Table 1-3 Off-Site Dose Comparison to Limits - Units 1, 2, 3........................................................................................... 10 Table 1-4 Off-Site Dose Comparison to Background - Units 1, 2, 3.................................................................................... II Table 2. 1-A l Unit I Gaseous Effluents - Release Summary ................................................................................................ 15 Table 2.1 -A2 Unit 1 Gaseous Effluents - Ground Continuous - BOP Vent & SFPI Vent .............................................................. 16 Table 2.2-Al Unit 2 Gaseous Effluents - Release Summary ................................................................................................. 17 Table 2.2-A2 Unit 2 Gaseous Effluents - Mixed Continuous - Aux Bldg Vent, SGBD Tank Vent & Spent Fuel Pool Evaporation .............. 18 Table 2.2-A3 Unit 2 Gaseous Effluents - Mixed Batch - Containment Purges, Liquid Radwaste System Gas Space .............................. 19 Table 2.2-A4 Unit 2 Gaseous Effluents - Elevated Batch - Containment Vents/Purges, WGDT ...................................................... 20 Table 2.2-A5 Unit 2 Gaseous Effluents - Elevated Continuous - Condenser Air Ejector, Containment Enclosure, C-14 ......................... 21 Table 2.2-A6 Unit 2 Gaseous Effluents - Ground Batch - Reactor Water Storage Tank Vent ......................................................... 22 Table 2.3-Al Unit 3 Gaseous Effluents - Release Summary ................................................................................................. 23 Table 2.3-A2 Unit 3 Gaseous Effluents - Mixed Continuous - Aux Bldg Ventilation & Spent Fuel Pool Evaporation ............................ 24 Table 2.3-A3 Unit 3 Gaseous Effluents - Ground Continuous - ESF Building Ventilation, RWST, Containment Equipment Hatch .............. 25 Table 2.3-A4 Unit 3 Gaseous Effluents - Mixed Batch - Containment Purge .............................................................................. 26 Table 2.3-A5 Unit 3 Gaseous Effluents - Ground Batch - Containment Drawdown ..................................................................... 27 Table 2.3-A6 Unit 3 Gaseous Effluents - Elevated Continuous - Gaseous Waste System .............................................................. 28 Table 2.3-A7 Unit 3 Gaseous Effluents - Elevated Batch - Containment Vents .......................................................................... 29 Table 2.3-A8 Unit 3 Gaseous Effluents - Ground Batch - Containment Equipment Hatch .............................................................. 30 Table 2. 1-LI Unit 1 Liquid Effluents - Release Summary .................................................................................................. 33 Table 2. 1-L2 Unit 1 Liquid Effluents - Batch ................................................................................................................. 34 Table 2.2-LI Unit 2 Liquid Effluents - Release Summary .................................................................................................. 35 Table 2.2-L2 Unit 2 Liquid Effluents - Continuous - SGBD, SW, RBCCW, Turbine Building Sumps ............................................. 36 Table 2.2-L3 Unit 2 Liquid Effluents - Batch - Liquid Radwaste System .................................................................................. 37 Table 2.3-LI Unit 3 Liquid Effluents - Release Summary .................................................................................................. 38 Table 2.3-L2 Unit 3 Liquid Effluents - Continuous - SGBD, SW, TB sump, W Tl berm, Foundation Drain Sump ............................... 39 Table 2.3-L3 Unit 3 Liquid Effluents - Batch - Liquid Radwaste System ................................................................................. 40 Table 2.1 -S Unit I Solid Waste & Irradiated Component Shipments .................................................................................... 42 Table 2.2-S Unit 2 Solid Waste & Irradiated Component Shipments ....................................................................................... 45 Table 2.3-S Unit 3 Solid Waste & Irradiated Component Shipments .................................................................................... 49 Table 2.4-GWI Additional Well Sanmples..: ............................................................................ ....................... 53 Table 2.4-G W 2 Well M W-7D R esults ............................................................................................................................. 54 2

References

1. NUREG-0597 User Guide to GASPAR Code, KF Eckerman, FJ Congel, AK Roecklien, WJ Pasciak, Division of Site Safety and Environmental Analysis, Office of Nuclear Reactor Regulation, US Nuclear Regulatory Commission, Washington, DC 20555, manuscript completed January 1980, published June 1980.

2. EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power Plants Gaseous Effluents, December, 2010.

3. NRC Regulatory Guide 1.109 Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977.

4. Technical Evaluation M3-EV-09-0003, "Impact of Faulty Flow Indication from HVR-FTIO on Radiation Monitors," March 29, 2010.

5. NRC Regulatory Guide 1.111 Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977.

6. NUREG/CR-1276, ORNL/NUREG/TDMC-1 User's Manual for LADTAP II - A Computer Program for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents, DB Simpson, BL McGill, prepared by Oak Ridge National Laboratory, Oak Ridge, TN 37830, for Office of Administration, US Nuclear Regulatory Commission, manuscript completed 17 March 1980.

7. 10 CFR Part 50 Domestic Licensing of Production and Utilization Facilities, Appendix I Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion "As Low As Reasonably Achievable" for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents.

8. 40 CFR Part 190 Environmental Radiation Protection Standard for Nuclear Power Operation.

9. SQA-OpenEMS-20140130, OpenEMS vl.l Code File, January 6,2014.

10. NEI 07-07, Nuclear Energy Institute, Industry Ground Water Protection Initiative - Final Guidance Document, August 2007.

11. Memo - MP-HPO-14012, 2013 Report on Solid Waste and Irradiated Component Shipments, March 15, 2014.

12. NRC Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste, Revision 2, October 2008.

13. SQA-DOSAIR-2011013 1, DOSAIR v2 Code File, January 6,2014.

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Introduction This report, for the period of January through December of 2013, is being submitted by Dominion Nuclear Connecticut, Inc. for Millstone Power Station Units 1, 2, and 3, in accordance with 10 CFR 50.36a, the Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM), and the Station's Technical Specifications.

This report contains radiological and volumetric information on gaseous and liquid effluents, shipments of solid waste &

irradiated components, calculated offsite radiological doses, information on effluent monitors inoperable for more than 30 consecutive days, and corrections to previous reports.

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1.0 Off-Site Doses This report provides a summary of the 2013 off-site radiation doses from releases of radioactive materials in gaseous and liquid effluents from Units 1, 2 and 3. This includes the annual maximum dose in millirem (mrem) to any real member of the public as well the maximum gamma and beta air doses.

To provide perspective, these doses are compared to the regulatory limits and to the annual average dose that a member of the public could receive from natural background and other sources.

1.1 Dose Calculations The off-site dose to humans from radioactive material in liquid effluents have been calculated using measured radioactive effluent data and the dose computation algorithm in OpenEMS, an effluent tracking program (Reference 9). The off-site dose to humans from radioactive materials in gaseous effluents have been calculated using measured radioactive effluent data, measured meteorological data, and the dose computation algorithm in DOSAIR (Reference 13). OpenEMS and DOSEAIR give doses equal to doses calculated using the methodology of NRC Regulatory Guide 1.109 (Reference 3). The calculated doses generally tend to be conservative due to the conservative model assumptions.

Doses are based upon exposure to radioactivity in gaseous and liquid effluents over a one-year period and an associated dose commitment over a 50-year period from initial exposure. The portion of the doses due to inhalation and ingestion take into account radioactive decay and biological elimination of the radioactive materials.

Maximum individual dose is defined as the dose to the individual who would receive the maximum dose from releases of gaseous and liquid effluents. Although the location of the maximum individual may vary each quarterly period, the annual dose is the sum of these quarterly doses. This conservatively assumes that the individual is at the location of maximum dose each quarter.

The dose calculations are based upon three types of input: radioactive source term, site-specific data, and generic factors. The radioactive source terms (Curies) are characterized in Section 2, Effluent Radioactivity, of this report. The site-specific data includes: meteorological data (e.g. wind speed, wind direction, atmospheric stability) to calculate the transport and dispersion of gaseous effluents, and dilution factors for liquid effluents.

The generic factors include the average annual consumption rates (for inhalation of air and ingestion of vegetables, produce, milk, meat, fish, and shellfish) and occupancy factors (for air submersion, ground irradiation, shoreline activity, swimming, boating, etc.).

1.1.1 Gaseous Effluents Maximum individual doses due to the release of noble gases, radioiodines, radioactive particulates, tritium (H-

3) and Carbon-14 were calculated using DOSAIR. This is equivalent to the NRC code, GASPAR II (Reference 1), which uses a semi-infinite cloud model to implement the NRC Regulatory Guide 1.109 (Reference 3) dose models.

The values of average relative effluent concentration (X/Q) and average relative deposition (D/Q) used in DOSAIR were generated using EDAN4, a meteorological computer code which implements the assumptions cited in NRC Regulatory Guide 1.111 (Reference 5), Section C. The annual summary of hourly meteorological data (in 15-minute increments), which includes wind speed, direction, atmospheric stability, and joint frequency distribution, is not provided in the report but are available.

Millstone Power Station stack releases are elevated (375 foot) with Pasquill stability classes determined based upon the temperature gradient between the 33 foot and 374 foot meteorological tower levels. Only Unit 2 and Unit 3 discharge to the Millstone Power Station Stack. In March 2001, Unit 1 was separated from the stack and two new release points were added to Unit 1, the Spent Fuel Pool Island (SFPI) Vent and the Balance of Plant (BOP) Vent.

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Unit 1 SFPI Vent (73 foot) and the BOP Vent (80 foot) releases are considered ground level; therefore these doses were calculated using the 33 foot meteorology. Continuous ventilation of the SFPI includes tritium (H-

3) releases due to evaporation from the spent fuel pool water release through the SFPI Vent. Continuous ventilation from other Unit 1 buildings is discharged to the BOP Vent. Doses from these release points were summed to determine the total Unit 1 gaseous effluent dose.

Unit 2 Auxiliary Building Ventilation, Steam Generator Blowdown Tank Vent and Containment Purge release via the Unit 2 Vent at 159 foot are considered mixed mode (partially elevated and partially ground) releases.

The first two of these are continuous releases while the Containment Purge is a batch release. Containment Purges can also be released via the Millstone Power Station Stack. Batch releases from the Waste Gas Decay Tanks and Containment Vents are discharged via the Millstone Power Station Stack. The Containment Equipment Hatch and the Reactor Water Storage Tank (RWST) Tank Vent releases are considered ground level where the 33 foot meteorology was used for the dose calculations. Each of the doses for the various release points were summed to determine the total Unit 2 gaseous effluent dose.

The Unit 3 Vent (142.5 foot) is considered a mixed mode (partially elevated and partially ground) release point.

The Pasquill stability classes are determined based upon the temperature gradient between the 33 foot and 142 foot meteorological tower levels. Auxiliary Building Ventilation is a mixed mode continuous release while Containment Purge and the "initial" Containment Drawdown (released at the roof of the Auxiliary Building) are considered mixed mode batch releases. Gaseous waste and operational containment drawdowns (also called containment vents) are released through the Unit 3 Supplementary Leak Collection and Recovery System (SLCRS) system to the Millstone Power Station Stack (375 foot). The Engineered Safety Features Building (ESF) Ventilation, the Containment Equipment Hatch, and RWST Vent releases are considered ground level where the doses were calculated using 33 foot meteorology. Each of the doses for the various release points were summed to determine the total Unit 3 gaseous effluent dose.

Based on Reference 2, it was conservatively assumed that 30% of the C-14 exists as carbon dioxide (CO 2 )

which may be deposited on surfaces. Thus only 30% of C-14 released yielded dose via ingestion pathways of milk, meat, produce and vegetation.

1.1.2 Liquid Effluents Maximum individual doses from the release of radioactive liquid effluents were calculated using OpenEMS which gives dose results equal to dose results calculated using NRC Regulatory Guide 1.109.

1.2 Dose Results The calculated maximum off-site doses are presented in Table 1-1 for gaseous effluents and Table 1-2 for liquid effluents. The units 'mrad' and 'mrem' used in this report are units of radiation dose. The letter 'in' is for 'milli', or one-thousandth of a 'rad' or a 'rem.' The word 'rad' is an acronym for radiation absorbed dose. One rad is equal to the absorption of 100 ergs of energy per gram of tissue. The word 'rem' is an acronyn for roentgen equivalent man. One rem is equal to a rad multiplied by factors to account for type of radiation and distribution within the body.

1.2.1 Gaseous Effluents For the dose to the maximum individual, DOSAIR calculates the dose to the whole body, gastrointestinal (GI),

bone, liver, kidney, thyroid, lung, and skin from each of the following pathways: direct exposure from noble gases in the plume and from ground deposition, inhalation, and ingestion of vegetation, produce, cow or goat milk, and meat. The values presented are a total from all pathways. However, only the whole body, skin, thyroid and maximum organ (other than thyroid) doses are presented.

For the plume and inhalation pathways, the maximum individual dose is calculated at the off-site location of the highest decayed x/Q where a potential for dose exists.

For ground deposition, the maximum individual dose is calculated at both the off-site maximum land location of the highest x/Q and highest D/Q where a potential for dose exists.

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For the vegetation pathway, the maximum individual dose is calculated at the vegetable garden of the highest D/Q. For the vegetation pathway, the calculated dose is included in the maximum individual's dose only at locations and times where these pathways actually exist. Similarly, for meat, cow's milk, and goat's milk pathways, the calculated dose is included in the maximum individual's dose only at locations and times where these pathways actually exist.

Beginning with the 2012 report, doses are reported with and without dose from C-14.

To determine compliance with 10 CFR 50, Appendix I (Reference 7), the maximum individual whole body and organ doses include all applicable external pathways (i.e., plume and ground exposure) as well as the internal pathways (inhalation and ingestion).

1.2.2 Liquid Effluents OpenEMS performs calculations for the following pathways: fish, shellfish, shoreline activity, swimming, and boating. Doses are calculated for the whole body, skin, thyroid, and maximum organ (GI, bone, liver, kidney, and lung).

1.2.3 Analysis of Results Table 1-3 provides a quantitative dose comparison with the limits specified in the REMODCM. The data indicates that the total whole body and organ doses to the maximum offsite individual from Millstone Power Station including all sources of the fuel cycle are well within the limits of 40 CFR 190 (Reference 8). On-site radioactive waste and spent fuel storage during this year was within storage criteria and the maximum dose to a member of the public was approximately 0.19 mrem/yr. The doses from gaseous and liquid effluents were added to the estimated dose from on-site radioactive waste storage to show compliance compared to 40 CFR 190.

The Offsite Dose Comparison, Table 1-4, provides a perspective on the maximum offsite individual dose received from Millstone Power Station with the natural background radiation dose received by the average Connecticut resident. The total dose to the maximum individual received from Millstone Power Station is small

(< 0.1%) in comparison to the dose received from natural background radiation.

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Table 1-1 2013 Off-Site Dose Commitments from Gaseous Effluents Millstone Units 1,2, 3 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Total Max Air mrad mrad mrad mrad mrad Beta O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Gamma O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Max Individual mrem mrem mrem mrem mrem Whole Body 6.02E-06 3.59E-05 5.32E-04 6.08E-04 1.18E-03 Skin 6.02E-06 3.59E-05 5.46E-04 6.08E-04 1.20E-03 Thyroid 6.02E-06 3.59E-05 4.81 E-04 6.08E-04 1.13E-03 Max organ3 6.02E-06 3.59E-05 8.24E-04 6.08E-04 1.47E-03 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Total Max Air mrad mrad mrad mrad mrad Beta 1.93E-07 1.14E-04 3.24E-05 3.24E-05 1.79E-04 Gamma 2.59E-07 3.24E-04 6.19E-07 6.19E-07 3.25E-04 Max Individual mrem mrem mrem mrem Whole Body' 1.83E-04 1.61 E-03 5.14E-04 2.22E-03 4.53E-03 Whole Body' 7.75E-04 1.49E-02 1.07E-02 1.34E-03 2.77E-02 Skin 1 1.84E-04 1.66E-03 5.30E-04 2.24E-03 4.62E-03 Skin 2 7.76E-04 1.50E-02 1.09E-02 1.34E-03 2.80E-02 Thyroid1 2.94E-04 3.79E-03 1.99E-03 2.37E-03 8.44E-03 Thyroid 2 9.06E-04 1.71 E-02 1.24E-02 1.49E-03 3.18E-02 Max organ1,3 1.84E-04 1.09E-02 5.20E-04 1.08E-02 2.24E-02 Max organZ3 3.27E-03 6.68E-02 5.21E-02 6.33E-03 1.29E-01 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Total Max Air mrad mrad mrad mrad mrad Beta 1.85E-07 1.87E-06 6.15E-07 3.84E-07 3.06E-06 Gamma 4.36E-08 8.23E-07 5.36E-08 4.08E-08 9.61 E-07 Max Individual mrem mrem mrem mrem mrem Whole Body' 5.71E-04 1.51 E-02 1.91 E-03 1.04E-03 1.86E-02 Whole Body2 5.97E-04 1.50E-02 2.59E-03 9.79E-04 1.92E-02 Skin' 5.72E-04 1.51 E-02 1.91 E-03 1.07E-03 1.87E-02 Skin 2 5.98E-04 1.50E-02 2.59E-03 9.79E-04 1.91 E-02 Thyroid' 5.71 E-04 1.50E-02 1.91 E-03 1.04E-03 1.86E-02 Thyroid 2 5.97E-04 1.50E-02 2.59E-03 9.79E-04 1.91 E-02 Max organ1 3, 5.71 E-04 1.53E-02 1.92E-03 1.04E-03 1.88E-02 Max organ2 3 6.60E-04 1.57E-02 4.14E-03 1.34E-03 2.19E-02 NOTES:

1 - Dose without C-14 2 - Dose with C-14 3 - Maximum of the following organs (not including thyroid): Bone, GI-LLI, Kidney, Liver, Lung 8

Table 1-2 2013 Off-Site Dose Commitments from Liquid Effluents Millstone Units 1, 2, 3 1st Quarter 2nd Quarter I 3rd Quarter 4th Quarter I Annual Total B

Max I divdual (mrem) (mrem) (mrem) (mrem) (mrem)

IWhole Body 4.78E-06 6.25E-06 5.06E-06 1. 61 E-05 IThyroid 1.39E-06 1.81E-06 1.47E-06 4.67E-06 IMax Organ 6.77E-06 8.86E-06 7.18E-06 2.28E-05

• No releases in 4th Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Total Max Individual (mrem) (mrem) (mrem) (mrem) (mrem)

Whole Body 1.42E-05 2.57E-05 4.09E-05 5.84E-05 1.39E-04 Thyroid 1.03E-05 2.03E-05 2.03E-05 5.38E-05 1.05E-04 Max Organ 6.14E-05 1.53E-04 1.98E-03 9.56E-04 3.15E-03 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Total Max IndMdual (mrem) (mrem) (mrem) (mrem) (mrem)

Whole Body 4.14E-04 5.39E-04 1.52E-04 1.94E-04 1.30E-03 Thyroid 2.07E-04 2.46E-04 6.80E-05 1.16E-04 6.37E-04 Max Organ 2.28E-03 4.53E-03 1.22E-03 6.13E-04 8.64E-03 9

Table 1-3 2013 Off-Site Dose Comparison to Limits Millstone Units 1,2, 3 Gaseous Effluents Dose (without C-14)

Whole Body Thyroid Max Organ* Skin Beta Air Gamma Air (mrem) (mrem) (mrem) (mrem) (mrad) (mrad)

Unit I 1.18E-03 1.13E-03 1.47E-03 1.20E-03 O.OOE+00 O.OOE+00 Unit 2 4.53E-03 8.44E-03 2.24E-02 4.62E-03 1.79E-04 3.25E-04 Unit 3 1.86E-02 1.86E-02 1.88E-02 1.87E-02 3.06E-06 9.61 E-07 Millstone Station 2.43E-02 2.81 E-02 4.27E-02 2.45E-02 1.82E-04 3.26E-04 Limits - 1 - 15 20I -0 Gaseous Effluents Dose (with C-14)

Whole Body Thyroid Max Organ* Skin Beta Air Gamma Air (mrem) (mrem) (mrem) (mrem) (mrad) (mind)

Unit 1 1.18E-03 1.13E-03 1.47E-03 1.20E-03 0.OOE+00 0.OOE+00 Unit 2 2.77E-02 3.18E-02 1.29E-01 2.80E-02 1.79E-04 3.25E-04 Unit 3 1.92E-02 1.91E-02 2.19E-02 1.91 E-02 3.06E-06 9.61E-07 Millstone Station 4.81E-02 5.21E-02 1.52E-01 4.83E-02 I 1.82E-04 3.26E-04 Liit 5 51 5 01 Liquid Effluents Dose Whole Body Thyroid Max Organ*

(mrem) (mrem) (mrem)

Unit 1 1.61 E-05 4.67E-06 2.28E-05 Unit 2 1.39E-04 1.05E-04 3.15E-03 Unit 3 1.30E-03 6.37E-04 8.64E-03 Millstone Station 1.45E-03 7.46E-04 I.18E-02 Total Off-Site Dose from Millstone Station Whole Body Thyroid Max Organ (mrem) (mrem) (mrem)

Gaseous without C-14 2.43E-02 2.81E-02 4.27E-02 Gaseous with C-14 4.81 E-02 5.211E-02 1.52E-01 Liquid 1.45E-03 7.46E-04 1.18E-02 Direct Shine*" 1.90E-01 1.90E-01 1.90E-01 Millstone Station 2.40E-01 2.43E-01 3.54E-01 Li-t -5 -5 2

• Maximum of the following organs (not including Thyroid): Bone, GI-LLI, Kidney, Liver, Lung

• • Direct shine is radiation exposure from onsite storage of radwaste and spent fuel.

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Table 1-4 2013 Offsite Dose Comparison Natural Background vs Millstone Station Average Resident Natural Background Radiation Dose Cosmic 27 mrem Cosmogenic 1 mrem Terrestial (Atlantic and Gulf Coastal Plain) 16 mrem Inhaled 200 mrem In the Body 40 mrem

- 284 mrem Courtesy NCRP Report 94 (1987)

Maximum Off-Site Individual Millstone Station Whole Body Dose Gaseous Effluents 0.0481 mrem Liquid Effluents 0.0015 mrem Direct Shine 0.1900 mrem 0.2395 mrem I1

2.0 Effluent Radioactivity 2.1 Gaseous Effluents 2.1.1 Measurement of Gaseous Radioactivity 2.1.1.1 Continuous Releases The following pathways have continuous radiation monitors that include particulate filters and, except for Unit 1, charcoal cartridges for monitoring the activity being released:

Unit 1 SFPI Island (no charcoal cartridge)

Unit 1 BOP Vent (no charcoal cartridge)

Unit 2 Ventilation Vent Unit 2 Wide Range Gas Monitor (WRGM) to Site Stack Unit 3 Ventilation Vent Unit 3 SLCRS to Site Stack Unit 3 ESF Building Vent Unit 2 and Unit 3 Containment Equipment Hatch Openings Charcoal cartridges and particulate filters are used to collect iodines and particulates, respectively. These filters are replaced weekly (except every two weeks for Unit I) and then analyzed for isotopic content using a gamma spectrometer. Particulate filters are also analyzed for Strontium-89 (Sr-89) (except for Unit 1), Strontium-90 (Sr-90) and gross alpha. At least monthly, gaseous grab samples are taken and analyzed for noble gasses and H-3. The gas washing bottle (bubbler) method is utilized for H-3 collection. This sample is counted on a liquid scintillation detector. Isotopic concentrations at the release point are multiplied by the total flow to obtain the total activity released for each isotope.

Since a major source of H-3 is evaporation of water from the spent fuel pools, H-3 releases were also estimated based upon amount of water lost and measured concentrations of H-3 in the pool water. Grab samples from the Unit 1 SFPI Vent and the Unit 2 and Unit 3 Vents are compared to the measured evaporation technique and the higher amount from either the vent or the measured evaporation technique is used to determine the amount of H-3 released.

Another continuous airborne pathway is the Unit 2 Steam Generator Blowdown (SGBD) tank vent. A decontamination factor (DF) across the SGBD tank vent was determined for iodines by comparing the results of gamma spectrometry, analysis of the SGBD water and grab samples of the condensed steam exiting the vent.

This DF was applied to the total iodine releases via the SGBD water to calculate the iodine release out the vent.

An additional factor of 0.33 was utilized to account for the fraction of blowdown water actually flashing to steam in the SGBD tank.

When water is transferred to RWST there is a potential for a release of radioactivity through the tank vent.

During the Unit 3 outage in the second quarter, releases of noble gases, iodines, particulates and H-3 from the RWST were estimated. A DF was applied to the total particulates and iodines contained in the water transferred to the RWST to estimate the releases. All noble gases are assumed to be released through the tank vent. For quarters when Unit 2 and Unit 3 were at power releases of H-3 were estimated from both RWSTs and releases of particulates were estimated from Unit 3 RWST based on known concentrations in RWST water.

Samples of air near the containment equipment hatch openings are analyzed for particulates and iodines, during refueling outages for the period that the equipment hatch is open. An estimated flow out of the hatch and sample results are used to determine the radioactivity released. Small releases from the Unit 3 hatch opening were measured during the second quarter of 2013 but were insignificant relative to other continuous ground level releases during the quarter.

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During the first quarter there was a small release from the Millstone Radwaste Reduction Facility (MRRF).

The radioactivity was measured using portable monitors and the volume released estimated based on an estimate air flow from the MRRF.

C-14 has always been released from the plant but, previous to 2010, was not reported because it was not a significant release relative to other radioactive releases. This nuclide is not monitored because of its difficulty in measurement and analysis. Because the overall quantity of other radioactive releases has steadily decreased due to improvements in power plant operations, C-14 now qualifies as a principle radionuclide. The amount of C-14 released is calculated using the guidance given in Regulatory Guide 1.21 (Reference 12) and the methodology of Reference 2. According to the regulatory guidance, releases of C-14 are reported in gaseous effluents but not in liquid effluents and the amount released is calculated based on a normalized source term.

The calculation is for an annual source term which is then divided evenly between quarters in the year. It is assumed that C-14 is released from the Millstone Stack and each unit's main ventilation vent in the same relative proportion as noble gases released.

2.1.1.2 Batch Releases The following pathways have releases that are considered batches:

Unit 2 Waste Gas Decay Tanks (WGDT) (via Unit 2 WRGM to Millstone Power Station Stack)

Unit 2 Radwaste processing tank vents.

Unit 2 and Unit 3 Containment Purges (via Unit Ventilation Vents, except for Unit 2 if using Enclosure Building Filtration System (EBFS) via WRGM to Millstone Power Station)

Unit 2 and Unit 3 Containment Vents (via EBFS to Millstone Power Station Stack for Unit 2 and via SLCRS to Millstone Power Station Stack for Unit 3)

Unit 3 Containment Drawdown Waste Gases from the Unit 2 Gaseous Waste Processing System are held for decay in waste gas decay tanks prior to discharge through the Millstone Power Station Site Stack. Each gas decay tank is analyzed prior to discharge for noble gas and H-3. Calculated volume discharged is multiplied by the isotopic concentrations (noble gas and H-3) from the analysis of grab samples to determine the total activity released.

During 2013 there were four batch releases from Unit 2 radwaste processing tank vents. These were released via the Unit 2 vent.

Containment air is sampled periodically for gamma and H-3 to determine the activity released from containment venting. The measured concentrations are multiplied by the containment vent volume to obtain the total activity released. Unit 2 typically performs this process of discharging air from containment to maintain pressure approximately once per week while at Unit 3 it is more often (typically at least daily). Any iodines and particulates discharged would be detected by the continuous monitoring discussed in Section 2.1.1.1.

Containment air is sampled prior to each purge for gamma and H-3 to determine the activity released from containment purging. Similar to containment venting, the measured concentrations are multiplied by the containment vent volume to obtain the total activity released. Any iodines and particulates discharged would be detected by the continuous monitoring discussed in section 2.1.1.1.

Unit 3 containment is initially drawn down prior to startup. This is accomplished by using the containment vacuum steam jet ejector which releases through an unmonitored vent on the roof of the Auxiliary Building.

Grab samples are performed prior to drawdown to document the amount of radioactivity released during these evolutions.

13

2.1.2 Estimate of Errors Estimates of errors associated with radioactivity measurements were made using the following guidelines:

Radioactivity Measurement Calibration 10% Calibration to NIST* standards Sampling/Data Collection 10% - 20% Variation in sample collection Sample Line Loss 20% - 40% Deposition of some nuclides Sample Counting 10% - 30% Error for counting statistics Flow & Level Measurements 10% - 20% Error for release volumes

• National Institute of Standards and Technology 2.1.3 Gaseous Batch Release Statistics Unit 1 -None Unit 2 Ctmt Purges Ctmt Vents WGDT Radwaste Vents Number of Batches 0 57 4 3 Total Time (min) NA 8638 1347 170 Maximum Time (min) NA 229 570 125 Average Time (min) NA 152 337 57 Minimum Time (min) NA 61 153 15 Unit 3 Ctmt Purges Ctmt Vents* Ctmt Drawdowns Number of Batches 1 -350 1 Total Time (min) 166 40 Maximum Time (min) 166 40 Average Time (min) 166 40 Minimum Time (min) 166 40

• 3 hrs per Vent 2.1.4 Abnormal Gaseous Releases An abnormal gaseous release of radioactivity is defined as an increase in gaseous radioactive material released to the environment that was unplanned or uncontrolled due to an unanticipated event. These do not include normal routine effluent releases from anticipated operational and maintenance occurrences such as power level changes, reactor trip, opening primary system loops, degassing, letdown of reactor coolant or transferring spent resin and do not include non-routine events such as minor leakages from piping, valves, pump seals, tank vents, etc.

2.1.4.1 Unit 1 - None 2.1.4.2 Unit 2 - None 2.1.4.3 Unit 3 - None 2.1.5 Gaseous Release Tables The following tables provide the details of the gaseous radioactivity released from each of the Millstone Power Station units. They are categorized by type of release, source(s), and by release point of discharge to the environment.

14

Table 2.1-Al Millstone Unit 1 Gaseous Effluents - Release Summary Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases D. Gross Alpha

1. TotalaActivity Ic Released

"-" denotes less than Minimum Detectable Activity (MVDA)

"na" denotes not required to be analyzed 15

Table 2.1-A2 Millstone Unit 1 Gaseous Effluents - Ground Continuous - BOP Vent & SFPI Vent Nuclides Released UnitsI 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total A. Fission & Activation Gases

[r85Cii l Activity Ci B. lodinesl Halogens 1-131 Ci na na na na na 1-133 Ci na na na na na Other y Emitters Ci na na na na na Total Activity Ci na na na na na C. Particulates Cs-137 Ci - 4.31 E-06 4.31 E-06 Other y Eritters Ci -

Sr-90 Ci ---

Total Activity Ci - 4.31 E-06 - 4.31 E-06 D. Gross Alpha IGross Alpha I c l I- II - I E. Tritium H-3 I Ci 2.47E-02 1.77E-02 2.02E-01 2.52E+00 1 2.76E+00

"-" denotes less than Mnirnum Detectable Activity (MDA)

"na" denotes not required to be analyzed 16

Table 2.2-Al Millstone Unit 2 Gaseous Effluents - Release Summary Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total C. Particulates D. Gross Alpha

1. TotalActivity Ci

%" denotes less than Minimum Detectable Activity (MDA)

-Calculated value per "Estimation of Carbon-14 in Nuclear Power Rant Gaseous Effluents" EPRI Final Report, 12/2010.

17

Table 2.2-A2 Millstone Unit 2 Gaseous Effluents - Mixed Continuous Aux Bldg Ventilation, SG Blowdown Tank Vent & Spent Fuel Pool Evaporation Release Point - Unit 2 Ventilation Vent Nuclides Released I Units I 1st Qtr I 2nd Qtr I 3rd Qtr 4th Qtr Total A. Fission & Activation Gases Ar-41 Ci - 9.37E-02 9.37E-02 Other y Ermitters Ci -- - - -

Total Activity Ci - 9.37E-02 9.37E-02 B. lodines/Halog ens 1-131 Ci 3.02E-05 2.77E-05 1.64E-05 1.89E-05 9.32E-05 1-132 Ci 2.1OE-05 2.1OE-05 1-133 Ci 1.22E-04 1.09E-04 7.77E-05 7.78E-05 3.87E-04 1-135 Ci 2.27E-05 2.27E-05 Other y Emitters Ci _ -

Total Activity Ci 1.96E-04 1.37E-04 9.41E-05 9.67E-05 5.23E-04 C. Particulates Nb-95 Ci 1.16E-06 1.16E-06 Other y Emitters Ci -

Sr-89 Ci -

Sr-90 Ci_-

Total Activity _ Ci 1.16E-06 1.16E-06 D. Gross Alpha lGross Alpha I Ci I - - -

E. Tritium H-3 Ci I 1.82E+00 2.79E+00 1.22E+00 1.40E+00 7.23E+0 i F. C-14 IC-14 I Ci 6.70E-01 I 6.70E-01 I 6.70E-01 I 6.70E-01 I 2.68E+00I

"-" denotes less than Minirum Detectable Activity (MDA) 18

Table 2.2-A3 Millstone Unit 2 Gaseous Effluents - Mixed Batch Containment Purges, Liquid Radwaste System Gas Space Release Point - Unit 2 Ventilation Vent Nuclides Released I Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases Kr-85 Ci *

• 1.22E-02 3.16E-02 4.38E-02 Ye-133 Ci *

• 9.58E-05 5.35E-04 6.31E-04 Xe-133m Ci *

• 1.1OE-05 1.1OE-05 Other y Emitters Ci Q

• Total Activity Ci *

• 1.23E-02 3.21E-02 4.44E-02 B. lodinesl Halogens 1-131 Ci *

• 1-133 Ci

• _

Br-82 Ci *

• Other y Bmitters Ci

• Total Activity Ci *

• C. Particulates yEmitters I Ci I I*

Total Actity Ci *

• D. Gross Alpha IGrossAlpha I Ci na na na na na E. Tritium IH-3 I Ci l No activity released

,v, denotes less than Mnimnunm Detectable Activity (MDA)

"na" denotes not required to be analyzed 19

Table 2.2-A4 Millstone Unit 2 Gaseous Effluents - Elevated Batch Containment Vents and Purges, Waste Gas Decay Tanks Discharges Release Point - Millstone Site Stack Nuclides Released I UnitsI 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total A. Fission & Activation Gases Ar-41 Ci 4.22E-02 4.54E-02 2.41E-02 2.57E-02 1.37E-01 Kr-85 Ci 7.68E-02 - 7.68E-02 Xe-133 Ci 6.13E-03 7.43E-03 3.94E-03 4.18E-03 2.17E-02 Xe-135 Ci 5.60E-04 5.81E-04 3.32E-04 1.69E-04 1.64E-03 Other y Enitters Ci - -

Total Activity Ci 1.26E-01 5.34E-02 2.84E-02 3.OOE-02 2.38E-01 B. lodinesl Halogens 1-131 Ci -_-

1-133 Ci--

Other y Emitters - -

Total Activity - -

C. Particulates y Emitters ICi -

Total Activit, I C-y -

D. Gross Alpha jGrossAlpha I Ci I na na na na E. Tritium H-3 Ci 2.45E-01 3.28E-01 I 2.56E-01 I 2.36E-01 1.07E+00

,v, denotes less than Minimum Detectable Activity (MDA)

"na" denotes not required to be analyzed 20

Table 2.2-A5 Millstone Unit 2 Gaseous Effluents - Elevated Continuous Condenser Air Ejector, Ventilation of Containment Enclosure, C-14 Release Point - Millstone Site Stack Nuclides "i Released IUnits I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total A. Fission & Activation Gases Tota Act [Cty I -

B. lodines/Halogens Br-82 Ci -

1-131 Ci -

1-133 Ci -

Other y Emitters Ci -

Total Activity Ci -

C. Particulates IvEmitters Ci----

Total Act itty Ci D. Gross Alpha IGross Alpha Ci I E. Tritium IH-3 Ci - 1.80E-02 1.80E-02 F. C-14 IC-14 I Ci I 1.81E+00 I 1.81E+00 I 1.81E+00 I 1.81E+00 1 7.24E+00

"-"denotes less than IMninuJm Detectable Activity (IVDA) 21

Table 2.2-A6 Millstone Unit 2 Gaseous Effluents - Ground Continuous Reactor Water Storage Tank, Radwaste Reduction Facility (MRRF)

Release Point - Reactor Water Storage Tank Vent, MRRF Doors Nuclides I *%w Released UnitsI 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total A. Fission & Activation Gases y Emitters Ci na na na na na Total Actvity Ci na na na na na B. lodines/Halogens 1-131 Ci - na na na 1-133 Ci - na na na -

Other y Emitters Ci - na na na -

Total Acthiity Ci - na na na C. Particulates Co-58 Ci 9.80E-10 na na na 9.80E-10 Co-60 Ci 1.OOE-09 na na na 1.OOE-09 Other y Entters Ci na na na -

Total Activity Ci 1.98E-09 na na na 1.98E-09 D. Gross Alpha IGross Alpha I Ci I na na na na na E. Tritium IH-3 I Ci 6.24E-04 I 6.24E-04 6.24E-04 6.24E-04 2.50E-03

"-" denotes less than Mnimum Detectable Activity (MDA)

"na" denotes Not Required to be Analyzed 22

Table 2.3-Al Millstone Unit 3 Gaseous Effluents - Release Summary Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total D. Gross Alpha

1. TotallActivity Ci Released

-Calculated value per "Estimation of Carbon-14 in Nuclear Power Rant Gaseous Effluents" EPRI Final Report, 12/2010.

23

Table 2.3-A2 Millstone Unit 3 Gaseous Effluents - Mixed Continuous Aux Bldg Ventilation & Spent Fuel Pool Evaporation Release Point - Unit 3 Ventilation Vent Nuclides Released UnitsI 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total A. Fission & Activation Gases Total Actiuty Ci B. eodiness Halo ens 1-131 Ci .....

1-133 Ci -....

Other y En-tters Ci -....

Total Activity Ci -....

C. Particulates Cr-51 Ci - 7.54E-05 - - 7.54E-05 Mn-54 Ci - 2.77E-06 - - 2.77E-06 Co-58 Ci - 1.42E-04 - - 1.42E-04 Nb-95 Ci - 2.50E-06 - - 2.50E-06 Ru-1 03 Ci - - 8.22E-07 - 8.22E-07 Ba-131 Ci - - 1.87E-06 - 1.87E-06 Other y Emitters Ci .....

Sr-89 Ci ....

Sr-90 Ci .....

Total ActiAty Ci - 2.23E-04 2.69E-06 - 2.25E-04 D. Gross Alpha IGross Alpha I Ci I - I--

E. Tritium IH-3 I Ci I 7.93E+00 I 4.32E+01 7.22E+00 I1.12E+01 F 6.95E+01 F. C-14 IC-14 I Ci I 3.30E-02 I 1.30E-02 1 3.1OE-02 3.30E-02 I1.10E-01

"-" denotes less than Mnimum Detectable Activity (MDA) 24

Table 2.3-A3 Millstone Unit 3 Gaseous Effluents - Ground Continuous Engineered Safeguards Building (ESF), Reactor Water Storage Tank (RWST)

Containment (during outage)

Release Points - ESF Building Vent, RWST Vent Open containment equipment hatch (during outage)

NuclidesI Released IUnits I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr !T!o6t al I A. Fission & Activation Gases ly Emitters lou = = - I - I - I -

Total ActiAty Ci - - - - -

B. lodines/Halogens 1-131 Ci -

1-133 Ci -

Other VEmitters Ci Total Actiiaty Ci I

C. Particulates Be-7 Ci - 3.12E-07 3.12E-07 Cr-51 Ci - 1.01E-05 1.18E-08 1.01E-05 Mn-54 Ci 9.55E-09 2.38E-06 3.06E-08 2.12E-07 2.63E-06 Co-57 Ci 7.90E-08 1.15E-08 9.05E-08 Co-58 Ci 5.77E-09 4.86E-05 2.80E-07 1.03E-06 4.99E-05 Co-60 Ci 2.27E-08 1.60E-06 2.11E-08 1.77E-07 1.82E-06 Zr-95 Ci 1.21E-07 1.21 E-07 Nb-95 Ci 3.08E-07 8.35E-1O0 3.09E-07 Ag-110m Ci 2.12E-08 9.96E-1O0 2.22E-08 Sb-125 Ci 6.21E-08 1.75E-07 1.01E-08 7.66E-08 3.24E-07 Cs-137 Ci 9.91E-09 1.09E-07 2.61E-09 1.95E-08 1.41E-07 Ta-182 Ci 2.56E-07 2.56E-07 Other y Emitters Ci Total Actiity Ci 1.1OE-07 6.38E-05 6.14E-07 1.53E-06 6.61 E-05 D. Gross Alpha IGross Alpha I Ci I I -I -I -I E. Tritium IH-3 I Ci I 8.90E-03 I 2.89E-02 1.68E-03 I 1.73E-02 I 5.68E-02

,v, denotes less than Mnimum Detectable Activity (MDA) 25

Table 2.3-A4 Millstone Unit 3 Gaseous Effluents - Mixed Batch Containment Purge Release Point - Aux Building Roof Vent Nuclides Released Units I1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases Xe-133 Ci

• 4.11E-03 *

• 4.11E-03 Xe-135 Ci

• 9.97E-04 *

• 9.97E-04 Other y Emitters Ci * * * -

Total Activity Ci

• 5.11E-03 *

• 5.11E-03 B. lodinesl Halogens Br-82 Ci

• 1.24E-07 *

• 1.24E-07 1-131 Ci * * * -

1-133 Ci * * * -

Other y Emitters Ci * * * -

Total Activity Ci

• 1.24E-07 *

• 1.24E-07 C. Particulates Co-60 Ci

• 5.75E-08 *

• 5.75E-08 Other y Emitters Ci * * * -

Total Activity Ci

• 5.75E-08 *

• 5.75E-08 D. Gross Alpha IGrossAlpha I Ci I

• na *

• na E. Tritium IH-3 I Ci

• 5.21E-03 *

• 5.21E-03

• No activity released

,v, denotes less than rnimurm Detectable Activity (MCEA)

"na" denotes not required to be analyzed 26

Table 2.3-A5 Millstone Unit 3 Gaseous Effluents - Ground Batch Containment Drawdown Nuclides i Released Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases yEm~ittersIJ i I[

[

i Ci Total Activity *

• ymters I B. Iodinesl Halogens III"II Total Acti.[ty**

• C. Particulates yEmitters Ci *

• I

• Total ActiAty Ci

• 1

• D. Gross Alpha jGross Alpha I Ci I - *I *---

E. Tritium H-3 Ci

• 6.17E-04 I

• 6.17E-04

"-" denotes less than Mnimum Detectable Activity (M)DA)

• No activity released 27

Table 2.3-A6 Millstone Unit 3 Gaseous Effluents - Elevated Continuous Gaseous Waste System Release Point - Millstone Site Stack Nuclides Released IUnits 11st Qtr 2nd Qtr 3rdl Qtr 4th Qtr Total A. Fission & Activation Gases Kr-85 Ci 1.33E-01 9.17E-02 2.39E-01 2.63E-01 7.27E-01 Kr-85m Ci - 9.80E-06 - - 9.80E-06 Kr-88 Ci - 1.70E-07 - - 1.70E-07 Xe-1 33 Ci - 8.64E-03 - - 8.64E-03 Xe-135 Ci - 3.10E-03 - - 3.1OE-03 Other y Emitters Ci - - - - -

Total Activity Ci 1.33E-01 1.03E-01 2.39E-01 2.63E-01 7.38E-01 B. eodines/Halo ns 1-131 Ci 2.15E-07 - - 2.15E-07 1-133 Ci 5.20E-06 - 5.20E-06 1-135 Ci 3.96E-06 - 3.96E-06 Br-82 Ci 2.87E-06 6.33E-06 8.53E-07 1.62E-06 1.17E-05 Other V Enitters Ci - - -

Total Activity Ci 2.87E-06 1 1.17E-05 4.81 E-06 1.62E-06 2.1OE-05 C. Particulates Co-57 Ci - 7.51E-09 - - 7.51E-09 Co-58 Ci - 3.54E-06 - 3.54E-06 Co-60 Ci - 9.48E-08 - 9.48E-08 Other VEmitters Ci -- -

Total Activity Ci - 3.64E-06 - 3.64E-06 D. Gross Alpha IGrossAlpha I Ci -I I I I E. Tritium IH-3 Ci 1.03E+00 I 2.20E+00I 8.42E-01 I 8.93E-01 I 4.97E+00 F. C-14 IC-14 I Ci I 3.30E+00 I 1.32E+00 I 3.08E+00 I 3.30E+00I 1.10E+01

"-" denotes less than Mnimum Detectable Activity (MDA) 28

Table 2.3-A7 Millstone Unit 3 Gaseous Effluents - Elevated Batch Containment Vents Release Point - Millstone Site Stack Nuclides Released I Units I 1st Qtr 2nd Qtr I 3rd Qtr 4th Qtr Total A. Fission & Activation Gases Ar-41 Ci 6.86E-03 1.39E-03 4.02E-03 5.57E-03 1.78E-02 Xe-133 Ci 1.22E-03 - 1.04E-03 3.72E-04 2.63E-03 Xe-135 Other y Enitters Total Activity Ci Ci Ci 1.26E-04 8.21 E-03

1. 39E-03 F -

5.06E-03 5.94E-03 1.26E-04 2.06E-02 B. lodinesl Halogens 1-131 Ci - -

O-133 Ci - -

Other y Emitters Ci -_-

Total Activity Ci - -

C. Particulates yEmitters I Ci - - - -

Total Activity Ci I - I -

D. Gross Alpha IGross Alpha Ci I I - - I E. Tritium IH-3 Ci 4.58E-03 2.47E-03 2.61 E-03 4.95E-03 1.46E-02

"-" denotes less than Minimum Detectable Activity (MDA) 29

Table 2.3-A8 Millstone Unit 3 Gaseous Effluents - Ground Batch Containment Air Containment Equipment Hatch Nuclides 0 Released Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases IVEmitters ICi I na I na Total Act ity Ci

• na na B. lodines/ Halogens IVEmitters Ci I Total Activity Ci C. Particulates Cr-51 Ci

• 1.90E-10 *

• 1.90E-10 Co-58 Ci

• 1.60E-10 *

• 1.60E-10 Co-60 Ci

• 4.50E-1 1 *

• 4.50E-1 1 Nb-95 Ci

• 7.20E-12 *

• 7.20E-12 Other y Emitters Ci * * *

• Total Activity Ci

• 4.02E-10 *

• 4.02E-10 D. Gross Alpha IGrossAlpha I Ci

• na na E. Tritium IH-3 I Ci

• na I na

• No activity released

"-" denotes less than Minimunm Detectable Activity (MBA)

"na" denotes not required to be analyzed 30

2.2 Liquid Effluents 2.2.1 Measurement of Liquid Radioactivity 2.2.1.1 Continuous Liquid Releases Water containing radioactivity is continuously released through one of two pathways - the Millstone Quarry or DSNO06. DSNO06 is next to the Unit 3 intake structure (DSN is an acronym for 'discharge serial number.')

Grab samples are taken for continuous liquid release pathways and analyzed on the gamma spectrometer and liquid scintillation detector (for H-3) if required by the conditional action requirements of the REMODCM. Total estimated volume is multiplied by the isotopic concentrations (if any) to determine the total activity released. A proportional aliquot of each discharge is retained for composite analysis for Sr-89, Sr-90, Fe-55 and gross alpha if required by the conditional action requirements of the REMODCM.

Pathways for continuous liquid effluent releases via the Millstone Quarry include Steam Generator Blowdown for Unit 3, Service Water Effluent for Unit 2 and Unit 3 and Reactor Building Closed Cooling Water (RBCCW) Sump for Unit 2. Pathways for continuous liquid effluent releases via DSNO06 include Turbine Building Sump discharge from Unit 2 and Unit 3.

2.2.1.2 Batch Liquid Releases from Tanks and Sumps Batch liquid releases are made via both the Millstone Quarry and DSNO06. There are numerous sources from which batches of liquids containing radioactivity are discharged to the environs. Except for three sources from Unit 3 to DSNO06 they are discharged via the Millstone Quarry. The sources are:

Unit I Radwaste Processing System - Includes sources from:

1. Reactor Building Sumps

2. Underground Ventilation Duct

3. Site Stack Sump Unit 2 Radwaste Processing System:

1. Clean Waste Monitor Tanks (2)

2. Aerated Waste Monitor Tanks Other Radwaste Sources:

1. CPF Waste Neutralization Sump

2. Steam Generator

3. Other Systems' Bulk Discharges Unit 3 Radwaste Processing

1. Waste Test Tanks (2)

Other Radwaste Sources:

1. CPF Waste Neutralization Sump

2. Steam Generator Bulk

3. Boron and Waste Test Tanks Berm (via DSNO06)

4. Foundation Drains Sumps (via DSNO06)

5. Systems' Bulk Discharges (via DSNO06)

Prior to release, a tank is re-circulated for two equivalent tank volumes, a sample is drawn and then analyzed on the HPGe gamma spectrometer and liquid scintillation detector (H-3) for individual radionuclide composition. Isotopic concentrations are multiplied by the volume released to obtain the total activity released. For bulk releases, several samples are taken during the discharge to verify the amount of radioactivity released. A proportional aliquot of each discharge is retained for composite analysis for Sr-89, Sr-90, Fe-55, and gross alpha.

31

2.2.2 Estimate of Errors Estimates of errors associated with radioactivity measurements were made using the following guidelines:

Radioactivity Measurement Calibration 10% Calibration to NIST* standards Sampling/Data Collection 10% - 20% Variation in sample collection Sample Counting 10% - 30% Error for counting statistics Flow & Level Measurements 10% - 20% Error for release volumes

• National Institute of Standards and Technology 2.2.3 Liquid Batch Release Statistics Unit 1 Unit 2 Unit 3 Radwaste Processing System:

Number of Batches 5 41 48 Total Time (min) 187 12,824 6,380 Maximum Time (min) 39 8,690 156 Average Time (min) 37 120 110 Minimum Time (min) 36 15 17 Unit I Unit 2 Unit 3 Other Radwaste Sources:

Number of Batches NA 16 191 Total Time (min) NA 2,442 762,000 Maximum Time (min) NA 400 44,600 Average Time (min) NA 1,530 4,320 Minimum Time (min) NA 17 156 2.2.4 Abnormal Liquid Releases An abnormal release of radioactivity is the discharge of a volume of liquid radioactive material to the environment that was unplanned or uncontrolled.

In 2013, the following abnormal liquid releases occurred:

2.2.5.1 Unit I - None 2.2.5.2 Unit 2 - None 2.2.5.3 Unit 3 - None 2.2.5 Liquid Release Tables The following tables provide the details of the liquid radioactivity released from each of the Millstone Power Station units. They are categorized by type of release, source(s), and by release point of discharge to the environment.

32

Table 2.1-L1 Millstone Unit 1 Liquid Effluents - Release Summary Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total B. Tritium D. Gross Alpha

1. Total Activity CI I - I

• Released I E. Volume

1. Released Waste Liters 5.89E+04 3.20E+04 5.83E+04 1.49E+05 Volume

2. Dilution Volume Liters 3.50E+08 2.01E+08 3.80E+08 9.31E+08 During Releases

3. Dilution Volume Liters 2.52E+11 2.36E+11 2.85E+11 7.73E+11 During Period++

No activity released denotes less than Mnimum Detectable Activity (MDA)

+ "Total Activity Released" + ("Released Waste Volume" + "Dilution Volume During Period")

++ Unit 2 Dilution Volume During Period used because there is no Unit 1 dilution 33

Table 2.1-L2 Millstone Unit I Liquid Effluents - Batch Release to Quarry: Liquid Radwaste Processing System Nuclides ] 1o1i Released Units I 1st Qtr 2nd Qtr I 3rd Qtr 4th Qtr Total A. Fission & Activation Products Cs-137 Ci 3.43E-04 4.94E-04 3.99E-04

• 1.24E-03 Other y Emitters Ci -

• Sr-90 Ci -

• Fe-55 Ci -

• Total Actiity Ci 3.43E-04 4.94E-04 3.99E-04

• 1.24E-03 B. Tritium

[H-3 I Ci I 2.30E-03 7.69E-04 8.58E-04 [ I 3.93E-03 C. Dissolved & Entrained Gases Kr-85 Ci -

• Other y Enitters Ci -

• Total Activity Ci -

• D. Gross Alpha IGross Alpha ci I* I -

No activity released denotes less than Mnirnum Detectable Activity (MDA) 34

Table 2.2-L1 Millstone Unit No. 2 Liquid Effluents - Release Summary Units 1 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total A. Fission and Activation Products

1. Total Activity Ci 4.34E-03 6.41E-04 5.25E-03 1.06E-03 1.13E-02 Released

2. Average Period uCi/rd 1.72E-11 2.71E-12 1.84E-11 4.10E-12 1.09E-11 Diluted Activity*

B. Tritium

1. TotalActivity Ci 1.52E+01 3.34E+01 3.35E+01 1.38E+02 2.20E+02 Released

2. Average Period uCi/ni 6.04E-08 1.42E-07 1.18E-07 5.35E-07 2.14E-07 Diluted Activity

• C. Dissolved and Entrained Gases

1. Total Activity Ci 1.31E-07 4.94E-03 1.76E-02 2.25E-02 Released

2. Average Period uCi/mrn 5.55E-16 1.73E-11 6.82E-11 2.19E-11 Diluted Activity

• D. Gross Alpha

1. Total Activity i 6.15E-06 6.15E Released E. Volume

1. Released Waste Volume Primary Liters 1.19E+04 1.09E+05 1.74E+05 4.14E+05 7.09E+05 Secondary Liters 2.46E+06 3.31 E+05 3.94E+04 1.75E+06 4.58E+06

2. Dilution Volume During Releases Primary Liters 5.16E+09 3.31E+09 6.27E+09 1.46E+10 2.93E+10 Secondary Liters 1.93E+09 1.78E+09 8.71 E+08 4.05E+08 4.99E+09

3. Dilution Volume During Period I Liters I 2.52E+11 I 2.36E+11 I 2.85E+11 I 2.58E+11 I 1.03E+12 "Total Activity Released" - (Primary "Released Waste Volume" + "Dilution Volume During Period")

denotes less than Minimum Detectable Activity (MDA) 35

Table 2.2-L2 Millstone Unit 2 Liquid Effluents - Continuous

1. Release to Quarry: Steam Generator Blowdown, Service Water and Reactor Building Closed Cooling Water

2. Release to DSNO06: Turbine Building Sumps and Tendon Gallery Nuclides Released I UnitsI 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total A. Fission & Activation Products Mn-54 Ci 2.30E-06 - 2.30E-06 Co-58 Ci 1.46E-05 - 1.46E-05 Co-60 Ci 4.32E-06 - - 4.32E-06 Cs-137 Ci 4.45E-06 4.65E-05 1.85E-05 - 6.95E-05 Other y Emitters Ci - -

Sr-89 Ci - -

Sr-90 Ci - -

Fe-55 Ci - -

Total Activity Ci 4.45E-06 6.77E-05 1.85E-05 - 9.07E-05 B. Tritium

[H-3 I Ci I 1.75E-02 1 5.31 E-03 3.69E-03 [ 6.81E-03 J 3.33E-02 I C. Dissolved & Entrained Gases Xe-133 Ci - 1.31E-07 - 1.31E-07 Other y Emitters Ci -

Total ActiAty Ci - 1.31E-07 - 1.31 E-07 D. Gross Alpha IGross Alpha I ci I -I I

"-" denotes less than rnimum Detectable Activity (MDA)

"na" denotes Not Analyzed 36

Table 2.2-L3 Millstone Unit 2 Liquid Effluents - Batch Release to Quarry: Liquid Radwaste Processing System Nuclides Released Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total A. Fission & Activation Products Mn-54 Ci - 3.22E-05 4.37E-06 3.66E-05 Co-57 Ci - 2.1OE-05 2.1OE-05 Co-58 Ci 1.98E-04 7.02E-05 9.28E-04 2.53E-05 1.22E-03 Co-60 Ci 1.69E-05 1.80E-05 9.92E-04 2.39E-04 1.27E-03 Sr-92 Ci - 3.47E-05 - 3.47E-05 Nb-95 Ci - 2.03E-05 - 2.03E-05 Zr-95 Ci - 1.21 E-05 - 1.21 E-05 Nb-97 Ci 6.58E-06 - 6.58E-06 Ag-1I1m Ci 8.49E-06 1.51E-05 5.77E-04 2.67E-04 8.68E-04 Sn-113 Ci 2.38E-04 1.45E-05 2.87E-05 2.81E-04 Sb-124 Ci 5.26E-04 - - 5.26E-04 Sb-125 Ci 2.86E-03 1.27E-04 2.14E-04 6.79E-05 3.27E-03 1-131 Ci - - 7.50E-06 7.50E-06 Cs-1 34 Ci 5.05E-06 - - 5.05E-06 Cs-137 Ci 7.OOE-05 1.83E-05 2.20E-05 1.50E-05 1.25E-04 La-141 Ci 1.74E-04 - - 1.74E-04 Other y Emitters Ci - -

Fe-55 Ci 2.36E-04 2.05E-04 9.1OE-04 2.33E-04 1.58E-03 Ni-63 Ci 6.86E-05 1.43E-03 1.94E-04 1.69E-03 Sr-89 Ci - 9.69E-06 4.27E-06 1.40E-05 Sr-90 Ci - - -

Total Activity Ci 4.33E-03 5.43E-04 5.23E-03 1.06E-03 1.12E-02 B. Tritium

[H-3 I Ci 11.52E+01 J 3.34E+01 J 3.35E+01 1.38E+02 2.20E*02 C. Dissolved & Entrained Gases Kr-85 Ci 4.94E-03 1.72E-02 2.21E-02 Xe-133 Ci - 3.98E-04 3.98E-04 Other y Emritters Ci -

Total ActivAty Ci 4.94E-03 1.76E-02 2.25E-02 D. Gross Alpha IGross Alpha I Ci I 6.15E-06 - - 6.15E-06

"-" denotes less than Mnirnum Detectable Activity (MDA) 37

Table 2.3-LI Millstone Unit 3 Liquid Effluents- Release Summary UVOI*

IUnits I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total A. Fission and Activation Products

1. Total Activity Ci 3.26E-02 8.19E-02 1.97E-02 2.57E-02 1.60E-01 Released

2. Average Period uCi/nI 7.42E-1 1 2.58E-1 0 4.23E-1 1 5.64E-1 1 9.53E-1 1 Diluted Act"vt B. Tritium

1. Total Activity Ci 4.02E+02 1.99E+02 1.20E+02 9.21E+01 8.14E+02 Released

2. Average Period uCi/rd 9.14E-07 6.26E-07 2.58E-07 2.02E-07 4.85E-07 Diluted Act"vt

• C. Dissolved and Entrained Gases

1. Total Activity Released

2. Average Period Diluted Activity

• Ci uCi/ml I_

D. Gross Alpha

1. T°RtalaAsctivity C Released Ci -----

E. Volume

1. Released Waste Volume Primary Liters 8.23E+05 8.70E+05 7.96E+05 9.51 E+05 3.44E+06 Secondary Liters 2.52E+07 1.61E+07 3.25E+07 2.87E+07 1.03E+08

2. Dilution Volume During Releases Primary Liters 7.99E+09 6.95E+09 8.02E+09 9.15E+09 3.21E+10 Secondary Liters 3.55E+11 1.37E+11 1.88E+11 1.68E+11 8.48E+11

3. Dilution Volume During Period I Liters 4.40E+11 3.18E+11 4.65E+11 4.55E+11 1.68E+12 denotes less than Mnimrnum Detectable Activity (MDA)

"Total Activity Released" + (Primary "Released Waste Volume" + "Dilution Volume During Period")

38

Table 2.3-L2 Millstone Unit 3 Liquid Effluents - Continuous

1. Release to Quarry: Steam Generator Blowdown & Service Water

2. Release to DSNO06: Turbine Building Sump, Waste Test Tank Berm and Foundation Drain Sumps, Nuclides Released I Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total A. Fission & Activation Products y Emitters Ci - -

Sr-89 Ci - -

Sr-90 Ci - -

Fe-55 Ci - -

,Total Actihity Ci - -

B. Tritium H-3 Ci 1.70E-01 [ 6.05E-02 1.85E-01 3.07E-01 7.23E C. Dissolved & Entrained Gases E mitters Ci I - I Total ActivAty I I -

D. Gross Alpha IGross Alpha I ciI I I

"-" denotes less than vnimum Detectable Activity (MDA)

"na" denotes Not Analyzed 39

Table 2.3-L3 Millstone Unit 3 Liquid Effluents - Batch Release to Quarry: Liquid Radwaste Processing System, CPF Waste Neutralization Sumps, Hotwell and Steam Generator Bulk I Nuclides I*'i Released Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total A. Fission & Activation Products Cr-51 Ci 9.86E-03 5.80E-04 1.04E-02 Mn-54 Ci 6.52E-04 7.79E-04 6.70E-04 2.57E-04 2.36E-03 Co-58 Ci 2.61 E-04 6.20E-03 2.30E-03 5.60E-04 9.32E-03 Fe-59 Ci 6.25E-04 - 6.25E-04 Co-60 Ci 9.23E-03 5.44E-03 2.92E-03 1.61 E-03 1.92E-02 Nb-95 Ci 9.74E-04 5.09E-04 6.64E-05 1.55E-03 Zr-95 Ci 5.19E-04 1.79E-04 3.43E-05 7.32E-04 Nb-97 Ci 4.84E-05 1.29E-04 - 1.77E-04 Ag-11Om Ci 4.08E-04 6.09E-05 - 8.68E-06 4.78E-04 Sn-117m Ci - -

Sb-122 Ci 4.86E-05 - 4.86E-05 Sb-124 Ci 4.47E-05 - 4.47E-05 Sb-125 Ci 4.14E-03 4.58E-02 4.88E-03 1.56E-02 7.04E-02 Te-132 Ci - 4.04E-05 - 4.04E-05 1-132 Ci - 5.42E-05 - 5.42E-05 Cs-134 Ci - 1.54E-05 - 4.30E-05 5.84E-05 Cs-1 37 Ci - - 3.66E-04 3.66E-04 Hf-181 Ci - 1.40E-05 - 1.40E-05 W-187 Ci - 5.23E-05 - 5.23E-05 Other y Emitters Ci - -

Ni-63 Ci 3.03E-04 6.82E-04 5.03E-04 3.78E-04 1.87E-03 Sr-89 Ci - -

Sr-90 Ci - -

Fe-55 Ci 1.76E-02 1.06E-02 7.15E-03 6.75E-03 4.21 E-02 Total Activity Ci 3.26E-02 8.19E-02 1.97E-02 2.57E-02 1.60E-01 B. Tritium H-3 Ci 4.02E+02 1.99E+02 1.20E+02 9.18E+01 8.13E+02 C. Dissolved & Entrained Gases y Emitters Ici I - I -- -

Total Actvihty Ci I - - -

D. Gross Alpha IGross Alpha I ci I - I "

"-" denotes less than Minimum Detectable Activity (MDA) 40

2.3 Solid Waste Solid waste shipment summaries for each unit are given in the following tables (Reference 11):

Table 2.1-S Unit I Solid Waste and Irradiated Component Shipments Table 2.2-S Unit 2 Solid Waste and Irradiated Component Shipments Table 2.3-S Unit 3 Solid Waste and Irradiated Component Shipments The principal radionuclides in these tables were from shipping manifests.

Solidification Agent(s): No solidification on site Containers routinely used for radioactive waste shipment include:

55-gal Steel Drum DOT* 17-H container 7.5 ft3 Steel Boxes 45 ft3 87 ft3 95 ft3 Steel Container 202.1 ft3 Steel "Sea Van" 1280 ft3 Polyethylene High Integrity Containers 120.3 ft3 132.4 ft3 173.4 ft3 202.1 ft3

• United States Department of Transportation 41

Table 2.1-S Solid Waste and Irradiated Component Shipments Millstone Unit I January 1, 2013 through December 31, 2013 I I Btos I

Major Nuclides for Resins, Filters and Evaporator Bottoms:

%P I

Major Nuclides for Dry Active Waste:

Radionuclide %of Total Cuiesk Fe-55 34.80% 1.68E-03 Co-60 13.85% 6.69E-04 Ni-63 23.08% 1.11E-03 Cs-1 37 28.23% 1.36E-03 Pu-238 < 0.01% 4.53E-07 Pu-239 < 0.01% 2.47E-07 Am-241 0.02% 1.03E-06 Cm-244 < 0.01% 3.19E-07 CURIES (TOTAL) 4.83E-03 42

Table 2.1 -S (continued)

Solid Waste and Irradiated Component Shipments Millstone Unit 1 January 1, 2013 through December 31, 2013 Major Nuclides for the Irradiated Components:

Radionuclide I %of Tota Curies CURIES (TOTAL) 0 Shipped Major Nuclides for Other Wastes:

IRadionuiclide I %of TotalI Curi*s CURIES (TOTAL) 0 1 43

Table 2.1-S (continued)

Solid Waste and Irradiated Component Shipments Millstone Unit 1 January 1, 2013 through December 31, 2013 Major Nuclides for All Low-Level Waste:

Radionucide %of Total Curies Fe-55 34.80% 1.68E-03 Co-60 13.85% 6.69E-04 Ni-63 23.08% 1.11E-03 Cs-1 37 28.23% 1.36E-03 Pu-238 < 0.01% 4.53E-07 Pu-239 < 0.01% 2.47E-07 Am-241 0.02% 1.03E-06 Cm-244 < 0.01% 3.19E-07 CURIES (TOTAL) 4.83E-03 44

Table 2.2-S Solid Waste and Irradiated Component Shipments Millstone Unit 2 January 1, 2013 through December 31, 2013 Major Nuclides for Resins, Filters and Evaporator Bottoms:

Radionuclide %of Total Curles H-3 0.44% 1.55E-01 C-14 0.67% 2.34E-01 Cr-51 < 0.01% 4.65E-04 Mn-54 1.65% 5.78E-01 Fe-55 13.16% 4.61E+00 Co-57 0.02% 7.41 E-03 Co-58 < 0.01% 1.48E-03 Co-60 6.57% 2.30E+00 Ni-59 0.20% 7.06E-02 Ni-63 20.89% 7.33E+00 Zn-65 < 0.01% 2.23E-05 Sr-89 < 0.01% 9.90E-04 Sr-90 0.04% 1.53E-02 Zr-95 < 0.01% 1.04E-04 Nb-95 < 0.01% 9.73E-05 Tc-99 < 0.01% 2.43E-04 Ag-110m 0.01% 3.87E-03 Sn-113 < 0.01% 2.27E-03 Sb-124 < 0.01% 2.59E-06 Sb-125 1.64% 5.75E-01 Cs-134 10.79% 3.78E+00 Cs-137 43.81% 1.54E+01 Pu-238 < 0.01% 7.09E-05 Pu-239 < 0.01% 2.15E-05 Pu-241 0.10% 3.42E-02 Am-241 < 0.01% 2.28E-05 Cm-242 < 0.01% 1.32E-07 Cm-244 < 0.01% 2.59E-05 CURIES (TOTAL) 3.51 E+01 45

Table 2.2-S (continued)

Solid Waste and Irradiated Component Shipments Millstone Unit 2 January 1,2013 through December 31, 2013 Major Nuclides for Dry Active Waste:

Radionuclide %of Total Curies C-14 0.02% 1.35E-04 Mn-54 0.64% 5.04E-03 Fe-55 20.76% 1.63E-01 Co-58 0.37% 2.89E-03 Co-60 20.09% 1.58E-01 Ni-63 47.85% 3.75E-01 Zr-95 0.47% 3.70E-03 Nb-95 0.54% 4.21 E-03 Tc-99 0.26% 2.06E-03 Ag-110m 0.05% 4.OOE-04 Sb-125 2.25% 1.76E-02 Cs-137 6.68% 5.24E-02 Pu-238 < 0.01% 2.27E-05 Pu-239 < 0.01% 6.98E-06 Pu-241 0.02% 1.92E-04 Am-241 < 0.01% 1.57E-05 Cm-244 < 0.01% 7.18E-06 CURIES (TOTAL) 7.84E-01 r Irradiated Components:

46

Table 2.2-S (continued)

Solid Waste and Irradiated Component Shipments Millstone Unit 2 January 1,2013 through December 31, 2013 Radionuclide  % of Total Curies H-3 95.07% 3.38E-01 C-14 < 0.01% 1.91E-06 Cr-51 < 0.01% 6.74E-06 Mn-54 0.08% 2.67E-04 Fe-55 0.27% 9.64E-04 Fe-59 < 0.01% 1.04E-05 Co-57 0.02% 5.54E-05 Co-58 3.21% 1.14E-02 Co-60 0.43% 1.54E-03 Ni-63 0.69% 2.46E-03 Zn-65 < 0.01% 5.42E-08 Sr-89 < 0.01% 1.85E-07 Sr-90 < 0.01% 8.33E-10 Zr-95 < 0.01% 2.64E-05 Nb-95 0.01% 5.32E-05 Tc-99 < 0.01% 1.62E-05 Ag-11Om < 0.01% 1.89E-05 Sn-113 < 0.01% 1.65E-06 Sb-124 0.01% 4.49E-05 Sb-125 0.06% 2.19E-04 Cs-134 < 0.01% 3.15E-05 Cs-137 0.11% 4.07E-04 Ce-144 < 0.01% 4.12E-09 Pu-238 < 0.01% 1.60E-07 Pu-239 < 0.01% 6.66E-08 Pu-241 < 0.01% 6.11E-07 Am-241 < 0.01% 1.04E-07 Cm-242 < 0.01% 1.85E-07 Cm-244 < 0.01% 2.57E-08 CURIES (TOT) 3.56E-01 47

Table 2.2-S (continued)

Solid Waste and Irradiated Component Shipments Millstone Unit 2 January 1, 2013 through December 31, 2013 Radionuclide  % of Total Curies H-3 1.36% 4.93E-01 C-14 0.65% 2.34E-01 Cr-51 < 0.01% 4.72E-04 Mn-54 1.61% 5.83E-01 Fe-55 13.20% 4.78E+00 Fe-59 < 0.01% 1.04E-05 Co-57 0.02% 7.46E-03 Co-58 0.04% 1.58E-02 Co-60 6.80% 2.46E+00 Ni-59 0.19% 7.06E-02 Ni-63 21.28% 7.70E+00 Zn-65 < 0.01% 2.23E-05 Sr-89 < 0.01% 9.90E-04 Sr-90 0.04% 1.53E-02 Zr-95 0.01% 3.83E-03 Nb-95 0.01% 4.36E-03 Tc-99 < 0.01% 2.31E-03 Ag-110m 0.01% 4.29E-03 Sn-113 < 0.01% 2.27E-03 Sb-124 < 0.01% 4.75E-05 Sb-125 1.64% 5.93E-01 Cs-134 10.45% 3.78E+00 Cs-137 42.57% 1.54E+01 Ce-144 < 0.01% 4.12E-09 Pu-238 < 0.01% 9.37E-05 Pu-239 < 0.01% 2.85E-05 Pu-241 0.10% 3.44E-02 Am-241 < 0.01% 3.86E-05 Cm-242 < 0.01% 3.17E-07 Cm-244 < 0.01% 3.31E-05 SCURIES (TOTA) 3.62E+01 48

Table 2.3-S (continued)

Solid Waste and Irradiated Component Shipments Millstone Unit 3 January 1, 2013 through December 31, 2013 Major Nuclides for Resins, Filters and Evaporator Bottoms:

Radionuclide  % of Total Curie H-3 < 0.01% 4.87E-03 C-14 0.04% 3.80E-02 Cr-51 < 0.01% 1.00E-05 Mn-54 7.10% 7.58E+00 Fe-55 7.62% 8.14E+00 Fe-59 < 0.01% 1.58E-06 Co-57 0.29% 3.11E-01 Co-58 3.44% 3.67E+00 Co-60 9.06% 9.68E+00 Ni-59 0.76% 8.11E-01 Ni-63 63.95% 6.83E+01 Sr-89 < 0.01% 2.95E-03 Sr-90 0.04% 4.60E-02 Nb-94 < 0.01% 9.25E-06 Zr-95 < 0.01% 2.67E-05 Nb-95 < 0.01% 1.16E-05 Tc-99 < 0.01% 1.61 E-03 Ag-110m < 0.01% 1.42E-04 Sn-113 < 0.01% 1.64E-06 Sn-117m < 0.01% 5.92E-10 Sb-124 < 0.01% 6.92E-08 Sb-125 0.71% 7.59E-01 Cs-134 2.26% 2.41E+00 Cs-1 37 4.70% 5.02E+00 Hf-181 < 0.01% 8.36E-08 Pu-238 < 0.01% 1.20E-04 Pu-239 < 0.01% 3.24E-05 Pu-241 0.04% 4.15E-02 Am-241 < 0.01% 4.95E-05 Cm-242 < 0.01% 2.74E-05 Cm-244 < 0.01% 9.97E-05 CURIES (TOTAL 1.07E+02 49

Table 2.3-S (continued)

Solid Waste and Irradiated Component Shipments Millstone Unit 3 January 1, 2013 through December 31, 2013 Major Nuclides for Dry Active Waste:

Radionuclide  % of Total Curies H-3 3.43% 3.31 E-02 Cr-51 0.51% 4.96E-03 Mn-54 2.34% 2.26E-02 Fe-55 30.80% 2.98E-01 Co-58 2.22% 2.14E-02 Co-60 37.81% 3.65E-01 Ni-63 17.60% 1.70E-01 Sb-125 0.89% 8.59E-03 Cs-134 1.25% 1.20E-02 Cs-1 37 3.16% 3.06E-02 CURIES (TOTAL) 9.66E-01 50

Table 2.3-S (continued)

Solid Waste and Irradiated Component Shipments Millstone Unit 3 January 1, 2013 through December 31, 2013 Major Nuclides for Other Waste:

Radionuclide %of Total Cre H-3 97.05% 4.98E-02 C-14 < 0.01% 1.13E-07 Mn-54 0.03% 1.69E-05 Fe-55 0.21% 1.08E-04 Fe-59 < 0.01% 3.06E-08 Co-57 0.02% 9.23E-06 Co-58 1.57% 8.06E-04 Co-60 0.50% 2.54E-04 Ni-63 0.46% 2.36E-04 Zr-95 < 0.01% 4.26E-08 Nb-95 < 0.01% 8.87E-08 Tc-99 < 0.01% 1.19E-06 Ag-110m < 0.01% 4.15E-08 Sb-124 < 0.01% 9.95E-08 Sb-125 0.04% 1.96E-05 Cs-1 34 0.01% 5.42E-06 Cs-137 0.11% 5.62E-05 Pu-238 < 0.01% 1.42E-08 Pu-239 < 0.01% 6.04E-09 Am-241 < 0.01% 9.48E-09 CURIES (TAL5.13E-02 51

Table 2.3-S (continued)

Solid Waste and Irradiated Component Shipments Millstone Unit 3 January 1, 2013 through December 31, 2013 Major Nuclides for All Low-Level Waste:

Radionuclide %of Total Curies H-3 0.08% 8.78E-02 C-14 0.04% 3.80E-02 Cr-51 < 0.01% 4.97E-03 Mn-54 7.05% 7.61 E+00 Fe-55 7.82% 8.44E+00 Fe-59 < 0.01% 1.61 E-06 Co-57 0.29% 3.11E-01 Co-58 3.43% 3.70E+00 Co-60 9.31% 1.OOE+01 Ni-59 0.75% 8.11E-01 Ni-63 63.50% 6.85E+01 Sr-89 < 0.01% 2.95E-03 Sr-90 0.04% 4.60E-02 Nb-94 < 0.01% 9.25E-06 Zr-95 < 0.01% 2.67E-05 Nb-95 < 0.01% 1.17E-05 Tc-99 < 0.01% 1.61 E-03 Ag-1I1m < 0.01% 1.42E-04 Sn-113 < 0.01% 1.64E-06 Sn-117m < 0.01% 5.92E-10 Sb-124 < 0.01% 1.69E-07 Sb-125 0.71% 7.68E-01 Cs-1 34 2.25% 2.42E+00 Cs-1 37 4.68% 5.05E+00 Hf-181 < 0.01% 8.36E-08 Pu-238 < 0.01% 1.20E-04 Pu-239 < 0.01% 3.24E-05 Pu-241 0.04% 4.15E-02 Am-241 < 0.01% 4.95E-05 Cm-242 < 0.01% 2.74E-05 Cm-244 < 0.01% 9.97E-05 CURIES (TOTAL) 1.08E+02 52

2.4 Groundwater Monitoring With the Groundwater Protection Program (GWPP) Millstone Power Station implements the actions cited in the Nuclear Energy's Institute's (NEI) Groundwater Protection Initiative (Reference 10). The purpose of the GWPP is to establish a program to assure timely and effective management of situations involving potential releases of radioactive material to groundwater. A key element in the GWPP is on-site groundwater monitoring. The results of the GWPP are documented in the Annual Radiological Environmental Operating Report (AREOR). Additional wells were sampled and the results are documented in tables below.

Another key element in the GWPP is site hydrological characterization. The general trend of groundwater flow at the station is toward the Long Island Sound. The underdrain system effectively captures groundwater in the area around Unit 3 and channels this water via the storm drain system to Long Island Sound.

Table 2.4-GW1 Additional Well Samples H-31 H-3' Name Date (pCi/L) I Name Date (pCilL)

MW-7A' 1/3/13 1,777 DP-003AP 2/26/13 6,930 2/26/13 1,775 3/26/13 5,970 3/27/13 1,775 4/2/13 8,350 4/29/13 1,775 4/8/13 6,350 5/28/13 1,775 4/16/13 5,190 6/24/13 1.775 4/22/13 <1,750 MW-7C' 6/10/13 2,110 4/29/13 2,820 6/17/13 <1,560 5/6/13 3,850 6/24/13 2,240 5/13/13 2,170 9/24/13 1,100 5/28/13 41,500 9/30/13 1,960 6/24/13 3,550 10/7/13 1,690 DP-004A' 1/3/13 <1,770 10/14/13 2,340 1/10/13 <1,770 10/22/13 2,050 1/17/13 <1,770 10/28/13 1,720 2/26/13 3,510 11/4/13 2,130 3/26/13 3,890 11/13/13 1,320 DP-102' 1/2/13 <1,770 11/14/13 <1,100 1/10/13 2,190 12/2/13 <1,220 1/17/13 2,490 12/11/13 <1,440 2/26/13 4,210 MW-GPI-5 3/13/13 <1770 3/13/13 6,320 DP-002A2 1/3/13 7,790 3/18/13 5,270 1/10/13 7,720 3/26/13 4,530 2/26/13 65,100 4/2/13 5,340 3/5/13 48,500 4/8/13 2,920 6/24/13 44,000 4/16/13 2,660 DP-003A2 1/3/13 3,050 4/22/13 3,260 1/10/13 9,550 4/29/13 4,050 1/17/13 9,230 5/6/13 2,830 5/13/13 3,010 5/28/13 3,100 6/24/13 2,040 Notes: I - There was no gamma radioactivity detected in these samples.

2 - These wells are located near the Unit 3 RWST. All or some of the H-3 detected in these wells is from releases out of the RWST vent. Gaseous releases from the RWST vent are reported in Table 2.3-A3. Any releases from RWST vent which reach the groundwater are captured in sumps and underground vaults, measured before release to the environment and reported in Table 2.3-L2. There has been no communication with offsite groundwater. During 2012, an investigation was initiated to determine if there are additional sources of H-3 to onsite groundwater at Well MW-7D.

53

Table 2.4-GW2 Well MW-7D 2 Results H.3 H-3' H-3' Date (pCi/L) Date Date DpCi/L) L) 1/3/13 3420 4/4/13 2620 5/15/13 1570 1/7/13 3030 4/8/13 3380 5/16/13 1550 1/17/13 2840 4/9/13 2330 5/17/13 1360 1/22/13 4410 4/10/13 2510 5/18/13 1600 1/24/13 4660 4/11/13 3020 5/20/13 1320 1/28/13 4330 4/14/13 2830 5/22/13 1170 1/31/13 3570 4/15/13 3650 5/23/13 1190 2/4/13 4090 4/16/13 3360 5/28/13 1500 2/7/13 4190 4/17/13 2630 5/29/13 1570 2/14/13 3900 4/18/13 2220 6/3/13 199 2/18/13 2400 4/19/13 3390 6/10/13 834 2/19/13 2230 4/20/13 1560 6/17/13 1440 2/20/13 2820 4/21/13 1750 6/24/13 1930 2/21/13 2290 4/22/13 2110 7/1/13 820 2/25/13 2310 4/23/13 1390 7/8/13 587 2/26/13 2270 4/24/13 2190 7/15/13 1450 3/4/13 1450 4/25/13 1330 7/29/13 813 3/5/13 2020 4/26/13 1880 8/4/13 1750 3/6/13 1820 4/27/13 1740 8/12/13 1350 3/7/13 2190 4/28/13 2360 8/20/13 425 3/7/13 2150 4/29/13 1860 8/26/13 875 3/8/13 2230 4/30/13 1060 9/3/13 1120 3/11/13 1750 5/1/13 1660 9/9/13 961 3/13/13 2470 5/2/13 1400 9/16/13 981 3/14/13 2540 5/3/13 1770 9/23/13 2330 3/15/13 3610 5/4/13 1170 9/30/13 1960 3/18/13 2920 5/5/13 889 10/7/13 2300 3/20/13 2610 5/6/13 1140 10/14/13 2650 3/21/13 2710 5/7/13 1310 10/22/13 2780 3/22/13 2460 5/8/13 1170 10/28/13 1960 3/25/13 1720 5/9/13 996 11/4/13 2620 3/27/13 2350 5/10/13 928 11/13/13 1500 3/28/13 2300 5/11/13 1620 11/14/13 2510 3/29/13 2250 5/13/13 1030 12/2/13 2140 4/1/13 2900 5/14/13 1040 12/11/13 1570 4/3/13 1750 Notes: I - There was no gamma radioactivity detected in these samples.

2 - This well is located near the Unit 3 RWST. All or some of the H-3 detected in this well is from releases out of the RWST vent. Gaseous releases from the RWST vent are reported in Table 2.3-A3. Any releases from RWST vent which reach the groundwater are captured in sumps and underground vaults, measured before release to the environment and reported in Table 2.3-L2. There has been no communication with offsite groundwater. During 2012, an investigation was initiated to determine if there are additional sources of H-3 to onsite groundwater at Well MW-7D.

54

3.0 Inoperable Effluent Monitors During the period January 1 through December 31, 2013, the following effluent monitors were inoperable for more than 30 consecutive days:

3.1 Unit 1 - None 3.2 Unit 2- None 3.3 Unit 3 - None 55

4.0 Operating History The operating history of the Millstone Power Station Units during this reporting period was as follows:

Unit 1 was shut down November 11, 1995 with a cessation of operation declared in July 1998.

Unit 2 operated with a capacity factor of 98.3% and Unit 3 operated with a capacity factor of 88.2%

The power histograms for 2013 are on the following pages.

56

MP2 - CYCLE 22 POWER HISTORY YEAR 2013 110 100 90 80 70 60 0

0. 50 2 40 C1L 30 20 10 0

cy) (V) ce) cf) ce) cl) cf) ce) cf) ce) cf) ce) mV mV C-1 mV co) mV co) cV) c) cf) co) mV CM - u~) NV I-- M CI--

ND W -n Co MD 10 - 10 C- C0 0M t C0 o- cv) 0> C= C> V MV MV V N N\ CV) Ce) 1ý 't 1o 10 CD Co 1l- r~- r- 00 00 m) m) 0D 0D N CN C) ) C0 0) C0 0) 0) C0 C0 0) C0 C0 0 0 0o 0D 0 0D 0C 57

MP3 - CYCLE 16 POWER HISTORY 110 100 90 80 70

_6o 0

Il 3550 30 m~ ce) m~ m~ m~ m~ c'r) m' m' or) cf) cy) c') C')

m' C) m' ') C ') ce) ce) C') c') C')

-0 - -t -N I- - -D -N I- - C- - C ) - U ) 0 ~ 0 o M)0 LO; N P, N W 0 1ý 0) W C M LO O C: LO C) It M 'I

-- - (N m' Cy) ql qt Lo Lo Co co r- I,- t- 00 co 0) a) 0 C0 04 N o Co o 0 0 C0 0 C) 0 C0 C 0 0) 0) C0 0) C0 0) 0C - -

58

5.0 Errata Section 1.2.3 and Tables 1-3, 2.2-Al, 2.2-A4, 2.3-Al and 2.3-A3 of the 2012 Radioactive Effluents Release Report are resubmitted. A new first paragraph is added to Section 1.2.3 to discuss the C-14 dose and to explain why airborne doses in 2012 were lower than prior years.

Revisions to the tables were made to correct the following errors:

1) In Table 1-3, the Total Off-Site Dose from Millstone Station was revised for Direct Shine and totals with and without C-14. This was a transcription error on the entry for Direct Shine dose.

2) In Tables 2.2-Al and 2.2-A4, the total activity of Fission & Activation Gases were revised for all four quarters because the activity for Ar-41 was not included in each quarter. The annual total activity for Fission & Activation Gases was correct and did not need revision.

3) In Table 2.2-Al, the total activity of Iodines/Halogens were revised for the third and fourth quarters because the activity for Br-82 was not included for those quarters. The annual total activity for lodines/Halogen was correct and did not need revision.

4) In Table 2.3-Al, the total activity of Tritium was revised for the third and fourth quarter because of a transcription error. The annual total activity for Tritium was correct and did not need correction.

5) In Tables 2.3-Al and 2.3-A3, the particulates in 3rd quarter were revised because activity for Sc-46 was not included.

Errata to 2012 Millstone Radioactive Effluent Release Report 1.2.3 Analysis of Results There are two general changes in doses from airborne effluents shown in Table 1-1 compared to doses given in prior years. This year, for the first time, the increment in dose due to C-14 is shown. This was done because of the significance of the dose from C-14. The second change is a significant reduction in airborne dose compared to previous years. This reduction is due to using more accurate meteorological parameters for elevated releases from the Millstone Stack. In prior years, doses due to releases from the Millstone Stack were calculated using rooftop meteorology which was gave conservatively higher doses.

Table 1-3 provides a quantitative dose comparison with the limits specified in the REMODCM. The data indicates that the total whole body and organ doses to the maximum offsite individual from Millstone Power Station including all sources of the fuel cycle are well within the limits of 40 CFR 190 (Reference 8). On-site radioactive waste and spent fuel storage during this year was within storage criteria and the maximum dose to a member of the public was approximately 0.18 mrem/yr. The doses from airborne and liquid effluents were added to the estimated dose from on-site radioactive waste storage to show compliance compared to 40 CFR 190.

The Offsite Dose Comparison, Table 1-4, provides a perspective on the maximum offsite individual dose received from Millstone Power Station with the natural background radiation dose received by the average Connecticut resident. The total dose to the maximum individual received from Millstone Power Station is small (< 0.1%) in comparison to the dose received from natural background radiation.

59

Errata to 2012 Millstone Radioactive Effluent Release Report Table 1-3 2012 Off-Site Dose Comparison to Limits Millstone Units 1,2, 3 Airborne Effluents Dose (without C-14)

Whole Body Thyroid Max Organ* Skin Beta Air Gamma Air (mrem) (mrem) (mrem) (mrem) (mrad) (mrad)

Unit 1 5.31 E-05 5.31E-05 5.31 E-05 4.08E-05 O.OOE+00 O.OOE+00 Unit 2 3.14E-03 1.20E-02 3.15E-03 2.09E-03 8.72E-05 4.18E-05 Unit 3 1.24E-02 1.24E-02 1.67E-02 7.69E-03 1.85E-05 1.92E-06 Millstone Station 1.56E-02 2.44E-02 1.99E-02 9.81E-03 1.06E-04 4.38E-05 Airborne Effluents Dose (with C-14)

Whole Body Thyroid Max Organ* Skin Beta Air Gamma Air (m"rn) (mt"ern) (totem) (memm) (mrad) (mrad)

Unit 1 5.31 E-05 5.31E-05 5.31 E-05 4.08E-05 O.OOE+00 O.OOE+00 Unit 2 5.34E-02 6.24E-02 2.52E-01 2.09E-03 8.72E-05 4.18E-05 Unit 3 1.36E-02 1.36E-02 1.67E-02 7.69E-03 1.85E-05 1.92E-06 Millstone Station 6.71 E-02 7.60E-02 2.69E-01 9.81E-03 1.06E-04 4.38E-05

... I -p5 15 -. -

Liquid Effluents Dose Whole Body Thyroid Max Organ*

(mrem) (mrem) (intem)

Unit I 1.66E-05 3.69E-06 5.13E-05 Unit 2 1.28E-03 2.47E-04 1.72E-02 Unit 3 9.1OE-04 5.64E-04 3.23E-03 Millstone Station 2.21E-03 8.14E-04 2.04E-02

-OC5 App. I Lit 3 10 1I Total Off-Site Dose from Millstone Station Whole Body Thyroid Max Organ *

(mr) I (mrem) I (mrem)

Airborne without C-14 1.56E-02 2.44E-02 1.99E-02 Airborne with C-14 6.71 E-02 7.60E-02 2.69E-01 Liquid 2.21E-03 8.14E-04 2.04E-02 r

EI. L

~ &.6S IIIII no I

I I

Qnrl ni_ 1 Or= l_

- I i anc: ni I,_u__ ,,.-__,__I Total without C-14 1.98E-01 2.05E-01 I 2.20E-01 Total with C-14 2.49E-01 2.57E-01 4.70E-01

• Maximum of the following organs (not including Thyroid): Bone, GI-LLI, Kidney, Liver, Lung Direct shine is radiation exposure from onsite storage of radw aste and spent fuel 60

Errata to 2012 Millstone Radioactive Effluent Release Report Table 2.2-Al Millstone Unit 2 Airborne Effluents- Release Summary Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total D. Gross Alpha

1. Total Activity--

I Released

%" denotes less than Minimum Detectable Activity (MDA)

-Calculated value per "Estimation of Carbon-14 in Nuclear Power Rant Gaseous Effluents" EP:RI Final Report, 12/2010.

61

Errata to 2012 Millstone Radioactive Effluent Release Report Table 2.2-A4 Millstone Unit 2 Airborne Effluents - Elevated Batch Containment Vents and Purges, Waste Gas Decay Tanks Discharges Release Point - Millstone Site Stack Nuclides Released I Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases Ar-41 Ci 4.51E-02 4.84E-02 4.29E-02 2.14E-02 1.58E-01 Kr-85 Ci 2.86E-01 6.01 E-02 2.82E-02 3.47E-01 7.21 E-01 Kr-85m Ci 8.53E-06 - - - 8.53E-06 Xe-131 m Ci 6.20E-04 1.64E-04 - - 7.84E-04 Xe-133 Ci 1.19E-01 6.19E-02 3.64E-02 2.92E-03 2.20E-01 Xe-133m Ci 1.38E-03 4.49E-05 1.42E-03 Xe-135 Ci 4.82E-03 1.38E-03 1.31 E-03 2.46E-04 7.76E-03 Other y Emitters Ci Total Activity Ci 4.57E-01 1.72E-01 1.09E-01 3.72E-01 1.11E+00 B. lodinesl Halogens 1-131 Ci -

1-133 Ci -

Other V Emitters Ci -

Total Activity Ci -

C. Particulates yEmitters I Ci I Total ActivtyI Ci I D. Gross Alpha IGross Alpha I Ci I na na na I na na E. Tritium IH-3 I Ci 2.46E-01 I 3.60E-01 I 1.43E-01 I 1.42E-02 7.63E-01

"-" denotes less than Mnirmurm Detectable Activity (MDA)

"na" denotes not required to be analyzed 62

Errata to 2012 Millstone Radioactive Effluent Release Report Table 2.3-Al Millstone Unit 3 Airborne Effluents- Release Summary Units 1 1st Qtr I 2nd Qtr I 3rd Qtr 4th Qtr Total D. Gross Alpha

1. T ivity F. C-14

1. Total Activity Ci 3.10E+00 3.10E+00 3.10E+00 3.10E+00 1.24E+01 Released**

2. Average Period uC/sec 3.99E-01 3.94E-01 3.90E-01 3.90E-01 3.93E-01 Release Rate

%" denotes less than Mnirium Detectable Activity (MDA)

-Calculated value per "Estimnation of Carbon-14 in Nuclear Power Rant Gaseous Effluents" EPRI Final Report, 12/2010.

63

Errata to 2012 Millstone Radioactive Effluent Release Report Table 2.3-A3 Millstone Unit 3 Airborne Effluents- Ground Continuous ESF Building Ventilation, Reactor Water Storage Tank (RWST)

Release Point - ESF Building Vent, RWST Vent Nuclides Released Units I 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases y Emitters IQ I I Total ActivAty Ci -

B. eodinesl ah gens 1-131 Ci -

1-133 Ci -

Other y Emitters Ci Total Activity Ci C. Particulates Sc-46 Ci 5.63E-08 5.63E-08 Cr-51 Ci 5.27E-12 1.18E-12 5.90E-13 2.56E-13 7.30E-12 Mn-54 Ci 2.45E-12 9.90E-13 1.22E-12 1.29E-12 5.95E-12 Fe-59 Ci 1.60E-12 4.60E-13 3.30E-13 2.14E-13 2.60E-12 Co-58 Ci 2.52E-11 8.50E-12 7.90E-12 6.10E-12 4.77E-11 Co-60 Ci 4.18E-12 1.77E-12 2.34E-12 2.63E-12 1.09E-11 Zr-95 Ci 6.25E-13 2.06E-13 1.82E-13 1.37E-13 1.15E-12 Nb-95 Ci 4.97E-13 1.27E-13 7.90E-14 4.28E-14 7.46E-13 Sb-125 Ci 2.40E-12 1.02E-12 1.34E-12 1.48E-12 6.24E-12 Cs-134 Ci 1.46E-12 6.1OE-13 8.1OE-13 8.90E-13 3.77E-12 Cs-137 Ci 1.72E-12 7.50E-13 1.00E-12 1.15E-12 4.62E-12 Other y Emitters Ci -

Total Activity Ci 4.54E-11 1.56E-11 5.63E-08 1.42E-1 1 5.64E-08 D. Gross Alpha IGross Alpha I Ci I - II - I E. Tritium IH-3 I Ci 1.24E-04 I 7.50E-05 1.01E-04 I 9.90E-05 3.99E-04

"-" denotes less than Minimum Detectable Activity (MDA) 64