ML111250247

Submittal of 2010 Radioactive Effluent Release Report

ML111250247
Person / Time
Site:	Millstone
Issue date:	04/28/2011
From:	Macmanus R Dominion Nuclear Connecticut
To:	Document Control Desk, NRC/FSME, Office of Nuclear Reactor Regulation
References
11-227
Download: ML111250247 (77)

Text

'Dominions Dominion Nuclear Connecticut, Inc.

Millstone Power Station Rope Ferry Road Waterford, CT 06385 APR 2 8 2011 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Serial No.

MPS Lic/GJC Docket Nos.

License Nos.11-227 RO 50-245 50-336 50-423 DPR-21 DPR-65 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNITS 1, 2, AND 3 2010 RADIOACTIVE EFFLUENT RELEASE REPORT In accordance with 10 CFR 50.36a, this letter transmits the annual Radioactive Effluent Release Report (RERR) for the period January 2010 through December2010. This report meets the provisions of Section 5.7.3 of the Millstone Power Station Unit 1 Permanently Defueled Technical Specifications (PDTS), and Sections 6.9.1.6b and 6.9.1.4 of the Millstone Power Station Units 2 and 3 Technical Specifications, respectively. transmits the 2010 RERR, in accordance with Regulatory Guide 1.21.

The RERR contains information regarding airborne, liquid, and solid radioactivity released from Millstone Power Station, off-site dose from airborne and liquid effluents.

If you have any questions or require additional information, please contact Mr. William D. Bartron at (860) 444 4301.

Sincerely, R. K. MacManus Director, Nuclear Station Safety and Licensing tJýtB

'Serial No.11-227 2010 Radioactive Effluent Release Report Page 2 of 4 Attachments:

1 Commitments made in this letter:

1. None.

cc:

U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 S. J. Giebel NRC Project Manager Millstone Unit 1 U.S. Nuclear Regulatory Commission Two White Flint North, Mail Stop T-8 F5 11545 Rockville Pike Rockville, MD 20852-2738 L. A. Kauffman NRC Inspector U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 T. A. Moslak NRC Inspector U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 J. D. Hughey NRC Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-BlA 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director Bureau of Air Management Monitoring & Radiation Division Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127

Serial No.11-227 2010 Radioactive Effluent Release Report Page 3 of 4 A. Honnellio Regional Radiation Representative (EPA Region 1, Boston)

U. S. Environmental Protection Agency (Region 1) 5 Post Office Square Suite 100 Boston, MA 02109 G. Allen Jr.

Department of Health and Human Services U. S. Food and Drug Administration 90 Madison St. Room 402 Worcester, MA 01608 R. Stein Chairman Connecticut Siting Council 10 Franklin Square New Britain, CT 06051 P. Kelley Waterford-East Lyme Shellfish Commission Waterford Town Hall Waterford, CT 06385 J. A. Martinez American Nuclear Insurers 95 Glastonbury Blvd.

Glastonbury, CT 06033 D. Carey Connecticut Department of Agriculture Aquaculture Division P. 0. Box 97 Millford, CT 06460 D. Steward First Selectman Town of Waterford Waterford Town Hall Waterford, CT 06385 P. Formica First Selectman Town of East Lyme PO Box 519 Niantic, CT 06357

Serial No.11-227 2010 Radioactive Effluent Release Report Page 4 of 4 D. M. Rose City Manager 181 State Street New London, CT 06320 University Of Connecticut Library Serials Department Storrs, CT 06268

Serial No.11-227 Docket Nos. 50-245 50-336 50-423 License Nos. DPR-21 DPR-65 NPF-49 ATTACHMENT 1 2010 RADIOACTIVE EFFLUENTS RELEASE REPORT MILLSTONE POWER STATION UNITS 1, 2, AND 3 DOMINION NUCLEAR CONNECTICUT, INC. (DNC)

Millstone Power Station 2010 Radioactive Effluents Release Report Dominion Dominion Nuclear Connecticut, Inc.

MILLSTONE UNIT LICENSE DOCKET 1

DPR-21 50-245 2

DPR-65 50-336 3

NPF-49 50-423

Table of Contents Table of Contents...........................................................................................................................................

I List of Tables..................................................................................................................................................

2 References......................................................................................................................................................

3 Introduction....................................................................................................................................................

4 1.0 Off-Site Doses.........................................................................................................................................

5 1.1 Dose Calculations............................................................................................................................

5 1.1.1 Airborne Effluents.......................................................................................................

5 1.1.2 Liquid Effluents........................................................................................................

6 1.2 Dose Results....................................................................................................................................

7 1.2.1 A irborne Effluents.......................................................................................................

7 1.2.2 Liquid Effluents........................................................................................................

7 1.2.3 Analysis of Results........................................................................................................

7 2.0 Effl uent Radioactivity...........................................................................................................................

12 2.1 Airborne Effluents.........................................................................................................................

12 2.1.1 M easurem ent of Airborne Radioactivity......................................................................

12 2.1.2 Estim ate of Carbon-14................................................................................................

13 2.1.3 Estim ate of Errors.......................................................................................................

14 2.1.4 A irborne Batch Release Statistics..............................................................................

14 2.1.5 Abnorm al Airborne Releases.......................................................................................

14 2.1.6 Airborne Release Tables..............................................................................................

14 2.2 Liquid Effl uents.............................................................................................................................

33 2.2.1 M easurem ent of Liquid Radioactivity.......................................................................

33 2.2.2 Estim ate of Errors.......................................................................................................

33 2.2.3 Liquid Batch Release Statistics...................................................................................

34 2.2.4 Abnorm al Liquid Releases..........................................................................................

34 2.2.5 Liquid Release Tables.................................................................................................

34 2.3 Solid W aste....................................................................................................................................

49 2.4 Groundwater M onitoring...............................................................................................................

61 3.0 Inoperable Effluent M onitors................................................................................................................

67 4.0 Operating H istory..................................................................................................................................

68 5.0 E rrata.....................................................................................................................................................

7 1 6.0 REM ODCM Changes............................................................................................................................

71 1

List of Tables Table 1-1 Off-Site Dose Summary from Airborne 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 - Units 1, 2, 3...................................................................................................

I I Table 2. 1-A l Unit I Airbome Effluents - Release Summary................................................................................................

15 Table 2.1 -A2 Unit I Airborne Effluents - Ground Continuous - BOP Vent & SFPI Vent...............................................................

16 Table 2.2-A l Unit 2 Airborne Effluents - Release Summary................................................................................................

17 Table 2.2-A2 Unit 2 Airborne Effluents - Mixed Continuous - Aux Bldg Vent, SGBD Tank Vent & Spent Fuel Pool Evaporation.............. 18 Table 2.2-A3 Unit 2 Airborne Effluents - Mixed / Elevated Batch - Containment Purges...............................................................

19 Table 2.2-A4 Unit 2 Airborne Effluents - Elevated Batch - WGDT........................................................................................

20 Table 2.2-A5 Unit 2 Airborne Effluents - Elevated Continuous - Containment Vents/Site stack.....................................................

21 Table 2.2-A6 Unit 2 Airborne Effluents - Ground Batch - Containment Equipment Hatch............................................................ 22 Table 2.2-A7 Unit 2 Airborne Effluents - Ground Batch - RWST Vent....................................................................................

23 Table 2.3-A l Unit 3 Airborne Effluents - Release Summary................................................................................................

24 Table 2.3-A2 Unit 3 Airborne Effluents - Mixed Continuous - Nonnal Ventilation & Spent Fuel Pool Evaporation................................ 25 Table 2.3-A3 Unit 3 Airborne Effluents - Ground Continuous - ESF Building Ventilation............................................................ 26 Table 2.3-A4 Unit 3 Airborne Effluents - Mixed Batch - Containment Drawdowns.................................................................... 27 Table 2.3-A5 Unit 3 Airborne Effluents - Mixed Batch - Containment Purges............................................................................. 28 Table 2.3-A6 Unit 3 Airborne Effluents - Elevated Continuous - Gaseous Waste System............................................................ 29 Table 2.3-A7 Unit 3 Airborne Effluents - Elevated Batch - Containment Vents........................................................................ 30 Table 2.3-A8 Unit 3 Airborne Effluents - Ground Batch - Containment Equipment Hatch............................................................ 31 Table 2.3-A9 Unit 3 Airborne Effluents - Ground Batch-RWST Vent..................................................................................

32 Table 2. I-LI Unit I Liquid Effluents - Release Summary - (Release Point - Quarry)................................................................... 35 Table 2. 1-L2 Unit I Liquid Effluents - Batch - (Release Point - Quany)................................................................................... 36 Table 2.2-L1 Unit 2 Liquid Effluents - Release Summary - (Release Point - Quarry)..................................................................... 37 Table 2.2-L2 Unit 2 Liquid Effluents - Continuous - SGBD, SW, RBCCW - (Release Point - Quarry)................................................ 38 Table 2.2-L3 Unit 2 Liquid Effluents - Batch - LWS - (Release Point - Quarry)........................................................................ 39 Table 2.2-L4 Unit 2 Liquid Effluents - Release Summary - (Release Point - Yard Drain DSN 006)................................................ 40 Table 2.2-L5 Unit 2 Liquid Effluents - Continuous - Turbine Building Sump - (Release Point - Yard Drain DSN 006)........................ 41 Table 2.3-L1 Unit 3 Liquid Effluents - Release Summary - (Release Point - Quarry)................................................................... 42 Table 2.3-L2 Unit 3 Liquid Effluents - Continuous - SGBD, SW - (Release Point - Quarry)............................................................ 43 Table 2.3-L3 Unit 3 Liquid Effluents - Batch-LWS - (Release Point - Quarry)........................................................................

44 Table 2.3-L4 Unit 3 Liquid Effluents - Batch - CPF Waste Neut Sumps, Hotwell, S/G Bulk - (Release Point - Quany)........................ 45 Table 2.3-L5 Unit 3 Liquid Effluents - Release Summary - (Release Point - Yard Drain DSN 006)................................................

46 Table 2.3-L6 Unit 3 Liquid Effluents - Continuous - T B Sump, WTT Benn - (Release Point - Yard Drain DSN 006).......................... 47 Table 2.3-L7 Unit 3 Liquid Effluents - Continuous - Foundation Drain Sumps - (Release Point - Yard Drain DSN 006)........................ 48 Table 2. 1-S Unit I Solid Waste & Iradiated Component Shipments...................................................................................

50 Table 2.2-S Unit 2 Solid Waste & Irradiated Component Shipments.................................................................................... 53 Table 2.3-S Unit 3 Solid Waste & Irradiated Component Shipments...................................................................................

57 Table 2.4-GWI Environmental Well Monitoring Results......................................................................................................... 62 Table 2.4-GW2 Catch Basin/Underdmin Monitoring Results.................................................................................................... 63 Table 2.4-GW3 Foundation Drains Monitoring Results.......................................................................................................... 64 Table 2.4-GW4 Manhole and WTT Benn Results................................................................................................................. 65 Table 2.4-G W 5 Special W ell Sam ples..............................................................................................................................

66 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-I 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.

DOSLIQ-Dose Excel Code for Liquid Effluents, Software Document File, Rev 1, February 2002.

10. DOSAIR-Dose Excel Code for Airborne Effluents, Software Document File, Rev 0, February 2002.

11. GASPAR II - Technical Reference and User Guide (NUREG/CR-4653), March 1987.

12. NEI 07-07 Industry Ground Water Protection Initiative - Final Guidance Document, August 2007.

13. Memo - MP-HPO-1 1019, 2010 Report on Solid Waste and Irradiated Component Shipments, March 15, 2011.

3

Introduction This report, for the period of January through December of 2010, is being submitted by Dominion Nuclear Connecticut, Inc. for Millstone Power Station Units 1, 2, and 3, in accordance with 10CFR50.36a, the REMODCM, and the Station's Technical Specifications. A combined report, written in the US NRC Regulatory Guide 1.21 format, is submitted for all three units.

Volume 1 contains radiological and volumetric information on airborne and liquid effluents, shipments of solid waste &

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

4

1.0 Off-Site Doses This report provides a summary of the 2010 off-site radiation doses from releases of radioactive materials in airborne and liquid effluents from Millstone Power Station Units 1, 2, and 3. This includes the annual maximum dose (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.

Regulatory Guide 1.21 Revision 2 was issued in June 2009. This guide specifically states that C-14 needs to be reported in airborne effluents from US nuclear power plants. This reporting requirement became effective beginning with reporting year 2010. C-14 is not a new power plant emission. Because the overall quantity of radioactive releases has steadily decreased due to improvements in power plant operations, C-14 now qualifies as a "principle radionuclide" per the revised regulatory guide.

1.1 Dose Calculations The off-site dose to humans from radioactive airborne and liquid effluents have been calculated using measured radioactive effluent data, measured meteorological data, and the dose computer models DOSAIR and DOSLIQ, which were developed by Millstone Power Station. The methodology and input parameters for DOSAIR are those used in GASPAR II (Reference 12) and NRC Regulatory Guide 1.109 (Reference 3). The methodology and input parameters for DOSLIQ are those used in LADTAP II (Reference 6) and NRC Regulatory Guide 1.109 (Reference 3). The calculated doses generally tend to be conservative due to the conservative model assumptions.

More realistic estimates of the off-site dose can be obtained by analysis of environmental monitoring data. A comparison of doses estimated by each of the above methods is presented in the Annual Radiological Environmental Operating Report.

Doses are based upon exposure to the airborne 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 airborne 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, etc.) to calculate the transport and dispersion of airborne effluents, and dilution factors for liquid effluents. The generic factors include the average annual consumption rates (for inhalation of air and ingestion of fruits, vegetables, leafy vegetables, grains, milk, poultry, meat, fish, and shellfish) and occupancy factors (for air submersion and ground irradiation, shoreline activity, swimming, boating, etc.). All these inputs are used in the appropriate dose models to calculate the maximum individual dose from radioactive airborne and liquid effluents.

1.1.1 Airborne Effluents Maximum individual doses due to the release of noble gases, radioiodines, and particulates were calculated using the computer code DOSAIR (Reference 11). This is equivalent to the NRC code, GASPAR II, 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 (XIQ) and average relative deposition (D/Q) used in the DOSAIR code were generated using EDAN4, a meteorological computer code which implements the 5

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 can be retrieved from computer storage.

Millstone Power Station Stack releases are elevated (375 ft) with Pasquill stability classes determined based upon the temperature gradient between the 33 ft and 374 ft meteorological tower levels. However, the doses were conservatively calculated using mixed mode 142 ft meteorology since DOSAIR may underestimate the plume exposure (prior to plume touchdown) for elevated releases from the Millstone Power Station Stack. Only Millstone Power Station Units 2 and 3 discharge to the Millstone Power Station Stack. In March 2001, Millstone Power Station 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.

Unit I Spent Fuel Pool Island Vent (73 ft) and the Balance of Plant Vent (80 ft) releases are considered ground level; therefore these doses were calculated using the 33 ft meteorology. Continuous ventilation of the Spent Fuel Pool Island including H-3 releases due to evaporation from the spent fuel pool water release through the Spent Fuel Pool Island Vent. Continuous ventilation from other Unit 1 buildings and airborne releases from the reactor building evaporator are discharged to the BOP Vent. Doses from these release points were summed to determine the total Unit I airborne effluent dose.

Unit 2 Auxiliary Building Ventilation, Steam Generator Blowdown Tank Vent and Containment Purge releases via the Unit 2 Vent at 159 ft 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. Because doses for releases from the Unit 2 Vent and from the Millstone Power Station Stack are calculated using the same meteorology, the Containment Purge releases are not divided between the Unit 2 Vent and Millstone Power Station Stack. Batch releases from the Waste Gas Decay Tanks and Containment Vents are discharged via the Millstone Power Station Stack. The doses for these elevated releases were conservatively calculated using mixed mode 142 ft meteorology for which the Pasquill stability classes are determined based upon the temperature gradient between the 33 ft and 142 ft meteorological tower levels.

The Containment Equipment Hatch and the RWST Tank Vent releases are considered ground level where the 33 ft meteorology was used for the dose calculations. Each of the doses for the various release points were summed to determine the total Unit 2 airborne effluent dose.

The Unit 3 Vent (142.5 ft) 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 ft and 142 ft 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 ft). The doses for these elevated releases were conservatively calculated using mixed mode 142 ft meteorology. The Engineered Safety Features Building (ESF) Ventilation, the Containment Equipment Hatch, and Refueling Water Storage Tank (RWST) Vent releases are considered ground level where the doses were calculated using 33 ft meteorology. Each of the doses for the various release points were summed to determine the total Unit 3 airborne effluent dose.

1.1.2 Liquid Effluents Maximum individual doses from the release of radioactive liquid effluents were calculated using the DOSLIQ program (Reference 10). This program uses the dose models and parameters cited in NRC Regulatory Guide 1.109 with site-specific inputs to produce results similar to the LADTAP II code, (Reference 6).

6

1.2 Dose Results The calculated maximum off-site doses are presented in Table 1-1 for airborne effluents and Table 1-2 for liquid effluents.

1.2.1 Airborne Effluents For the dose to the maximum individual, DOSAIR calculates the dose to the whole body, GI-tract, 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, 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.

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.

To determine compliance with 10CFR50, 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 The DOSLIQ code 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-LLI, 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 40CFRI90 (Reference 8). On-site radioactive waste 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 airborne and liquid effluents were added to the estimated dose from on-site radioactive waste storage to show compliance compared to 40CFR190.

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.

7

Table 1-1 2010 Off-Site Dose Commitments from Airborne 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 1.04E-04 5.OOE-05 1.20E-04 8.96E-05 3.64E-04 Skin 1.18E-04 5.OOE-05 1.37E-04 8.96E-05 3.94E-04 Thyroid 1.04E-04 5.OOE-05 1.20E-04 8.96E-05 3.64E-04 Max organ+

1.05E-04 5.OOE-05 1.96E-04 8.96E-05 4.40E-04 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Total Max Air mrad mrad mrad mrad mrad Beta 1.16E-05 2.04E-03 4.58E-04 5.71E-05 2.56E-03 Gamma 3.14E-05 1.27E-04 7.19E-05 2.40E-05 2.54E-04 Max Individual mrem mrem mrem mrem mrem Whole Body 2.36E-03 7.81 E-02 9.18E-02 4.93E-03 1.77E-01 Skin 2.38E-03 7.95E-02 9.22E-02 4.97E-03 1.79E-01 Thyroid 2.39E-03 7.86E-02 9.24E-02 5.04E-03 1.78E-01 Max organ+

1.18E-02 3.91 E-01 4.58E-01 2.37E-02 8.84E-01 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Total Max Air mrad mrad mrad mrad mrad Beta 1.44E-04 8.23E-03 9.06E-05 5.09E-05 8.51E-03 Gamma 2.28E-05 2.91 E-03 8.34E-06 1.07E-05 2.96E-03 Max Individual mrem mrem mrem mrem mrem Whole Body 2.09E-03 6.24E-02 5.78E-02 8.09E-03 1.30E-01 Skin 2.18E-03 6.61E-02 5.78E-02 8.13E-03 1.34E-01 Thyroid 2.09E-03 1.74E-01 5.78E-02 8.09E-03 2.42E-01 Max organ+

9.17E-03 2.90E-01 2.77E-01 3.68E-02 6.13E-01

+ Maximum of the following organs (not including thyroid): Bone, GI-LLI, Kidney, Liver, Lung 8

Table 1-2 2010 Off-Site Dose Commitments from Liquid Effluents Millstone Power Station Units 1, 2,3 IITt Max Individual I Whole Body I Thyroid I Max Organ 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter I

Annual Total (mrem)

O.OOE+00 0,OOE+00 O.OOE+00 (mrem) 2.12E-07 6.08E-08

3. 01 E-07 (mrem)

O.OOE+00 O.OOE+00 O.OOE+00 (mrem)

O.OOE+00 O.OOE+00 O.OOE+00 (mrem) 2.12E-07 6.08E-08 3.01 E-07 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Total Max Individual (mrem)

(mrem)

(mrem)

(mrem)

(mrem)

Whole Body 3.68E-05 5.81 E-05 3.19E-05 1.49E-04 2.76E-04 Thyroid 7.11 E-06 3.39E-05 1.45E-05 1.31 E-04 1.87E-04 Max Organ 6.20E-04 1.39E-03 4.35E-03 2.67E-03 9.04E-03 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Total Max Individual (mrem)

(mrem)

(mrem)

(mrem)

(mrem)

Whole Body 2.00E-04 3.17E-04 3.21 E-04 1.28E-04 9.66E-04 Thyroid 1.67E-04 3.44E-04 1.32E-04 9.58E-05 7.39E-04 Max Organ 6.79E-04 5.21 E-04 1.89E-03 2.24E-04 3.31 E-03 9

Table 1-3 2010 Off-Site Dose Comparison to Limits Millstone Power Station Units 1, 2, 3 Airborne Effluents Dose Max Individual Dose vs REMODCM & 10CFR50 Appendix I Limits Whole Body (mrem)

Thyroid (mrem)

Max Organ*

(mrem)

Skin (mrem)

Beta Air (mrad)

Gamma Air (mrad)

Unit 1 3.64E-04 3.64E-04 4.40E-04 3.94E-04 0.00E+00 0.OOE+00 Unit 2 1.77E-01 1.78E-01 8.84E-01 1.79E-01 2.56E-03 2.54E-04 Unit 3 1.30E-01 2.42E-01 6.13E-01 1.34E-01 8.51E-03 2.96E-03 Millstone Power Station 3.08E-01 4.21 E-01 1.50E+00 3.14E-01 1.11 E-02 3.21 E-03 I

-Li-it-

-5i-1-20

-1 Liquid Effluents Dose Whole Body (mrem)

Thyroid (mrem)

Max Organ*

(Mrem)

Unit I 2.12E-07 6.08E-08 3.01 E-07 Unit 2 2.76E-04 1.87E-04 9.04E-03 Unit 3 9.66E-04 7.39E-04 3.31 E-03 Millstone Power Station 1.24E-03 9.26E-04 1.24E-02

~-I iis3 01 Max Individual Dose vs REMODCM & 40CFRI90 Limits Whole Body (mrem)

Thyroid (mrem)

Max Organ *

(mrem)

Airborne Effluents 3.08E-01 4.21 E-01 1.50E+00 Liquid Effluents 1.24E-03 9.26E-04 1.24E-02 Radwaste Storage 1.90E-01 1.90E-01 1.90E-01 Millstone Power Station 4.99E-01 6.12E-01 1.70E+00 I

Limits 25 75 25

-1 Note: REMODCM limits are listed in 1 OCFR50, Appendix I which contains additional limits not listed in the REMODCM

• Maximum of the following organs (not including Thyroid): Bone, GI-LLI, Kidney, Liver, Lung 10

Table 1-4 2010 Offsite Dose Comparison Natural Background vs. Millstone Power Station Average Resident Cosmic Cosmogenic Terrestial (Atlantic and Gulf Coastal Plain)

Inhaled In the Body Natural Background Radiation Dose 27 mrem 1 mrem 16 mrem 200 mrem 40 mrem I

~- 284 mrem I Courtesy NCRP Report 94 (1987)

Maximum Off-Site Individual Airborne Effluents Liquid Effluents On-site RadWaste Storage Millstone Power Station Whole Body Dose 0.3297 mrem 0.0012 mrem 0.1900 mrem 1

0.5209 mrem I I1

2.0 Effluent Radioactivity 2.1 Airborne Effluents 2.1.1 Measurement of Airborne 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 Spent Fuel Pool (SFPI) Island (no charcoal cartridge)

Unit 1 Balance of Plant (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 Supplementary Leak Collection and Recovery System (SLCRS) to Site Stack Unit 3 Emergency Safeguards Facility (ESF) Building Vent Charcoal cartridges and particulate filters are used to collect iodines and particulates, respectively. These filters are periodically replaced (typically weekly, except every two weeks for Unit 1) and then analyzed for isotopic content using a gamma spectrometer. Particulate filters are also analyzed for Sr-89 (for all but Unit 1), Sr-90 and gross alpha. At least monthly, gaseous grab samples are taken and analyzed for noble gasses and tritium.

The gas washing bottle (bubbler) method is utilized for tritium 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 tritium is evaporation of water from the spent fuel pools, tritium releases were also estimated based upon amount of water lost and measured concentrations of the pool water. Grab samples from the Unit I SFPI Vent and the Unit 2 and 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 tritium released.

Another continuous airborne pathway is the Unit 2 Steam Generator Blowdown Tank Vent.

A decontamination factor (DF) across the SGBD Tank vent was determined for iodines by comparing the results of gamma spectrometry, HPGe, analysis of the Steam Generator Blowdown water and grab samples of the condensed steam exiting the vent. This DF was applied to the total iodine releases via the Steam Generator Blowdown 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 Steam Generator Blowdown Tank.

12

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

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

Unit 2 and 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 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 2 and 3 Containment Equipment Hatch Openings Unit 2 and 3 Refueling Water Storage Tank (RWST) Vents Unit 3 Containment Drawdown Waste Gases from the Unit 2 Gaseous Waste Processing System are held for decay in waste gas decay tanks (6) prior to discharge through the Millstone Power Station Site Stack. Each gas decay tank is analyzed prior to discharge for noble gas and tritium. Calculated volume discharged is multiplied by the isotopic concentrations (noble gas and tritium) from the analysis of grab samples to determine the total activity released.

Containment air is sampled periodically for gamma and tritium 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 tritium 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.

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.

When water is transferred to Refueling Water Storage Tank (RWST) there is a potential for a release of radioactivity through the tank vent. A decontamination factor (DF) was applied to the total iodine contained in the water transferred to the RWST to estimate the iodine released. All noble gases are assumed to be released through the tank vent.

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.

2.1.2 Estimate of Carbon-14 Beginning in 2011 U. S. nuclear utilities are required to report airborne releases of C-14. This nuclide is not typically monitored because of its difficulty in measurement and analysis but the amount released can be estimated based upon its production rate. Reference 2 provides a method for this calculation. Also a key factor in the dose assessment is the percentage of C-14 that is in the form of carbon dioxide. Based on Reference 2, it was conservatively assumed that 30% of the C-14 exists as carbon dioxide (CO 2).

13

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

Radioactivity Measurement Calibration Sampling/Data Collection Sample Line Loss Sample Counting Flow & Level Measurements 10%

Calibration to NBS standards 10% - 20%

Variation in sample collection 20% - 40%

Deposition of some nuclides 10% - 30%

Error for counting statistics 10% - 20%

Error for release volumes 2.1.4 Airborne Batch Release Statistics Unit 1 - None Unit 2 Ctmt Purges Ctmt Vents Number of Batches Total Time (min)

Maximum Time (min)

Average Time (min)

Minimum Time (min)

Unit 3 Number of Batches Total Time (min)

Maximum Time (min)

Average Time (min)

Minimum Time (min) 0 0

0 0

0 52 8313 224 160 77 WGDT 5

2278 965 456 25 Ctmt Purges Ctmt Vents* Ctmt Drawdowns 1

274 1

108 108 108 108 79 79 79 79

• 3 hrs per Vent 2.1.5 Abnormal Airborne Releases An abnormal airborne release of radioactivity is defined as an increase in airborne 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.

2.1.5.1 Unit 1 - None 2.1.5.2 Unit 2 - None 2.1.5.3 Unit 3 - None 2.1.6 Airborne Release Tables The following tables provide the details of the airborne radioactivity released from each of the Millstone Power Station units obtained from Reference 2. They are categorized by type of release, source(s), and by release point of discharge to the environment.

14

Table 2.1-Al Millstone Power Station Unit 1 Airborne Effluents - Release Summary Units ------------

I 1lst Otr 2nd Otr 3rd Otr 4th Otr Total I

A. Fission & Activation Gases D. Gross Alpha

1.

Total Activity Ci Released "na" denotes Not Required to be Analyzed

+ "Total Activity Released". Seconds in Quarter measurements below detectable levels 15

Table 2.1-A2 Millstone Power Station Unit 1 Airborne Effluents - Ground Continuous - BOP Vent & SFPI Vent Nuclides Released Units lst tr I

2nd tr I

3rd tr 4th tr 2Total A. Fission & Activation Gases Kr-85 Ci Other y Emitters Ci Total Activity Ci B. lodines / Halogens Total Activity Ci na na na na na C. Particulates Cs-137 Ci 1.07E-06 1.91 E-06 Other y Emitters Ci Sr-90 Ci Total Activity Ci 1.07E-06 1.91 E-06 D. Gross Alpha Gross Alpha Ci I

E. Tritium H-3 Ci 2.97E-01 5.20E-02 4.10E-02 6.59E-01 1.05E+00 "na" denotes Not Required to be Analyzed measurements below detectable levels 16

Table 2.2-Al Millstone Power Station Unit 2 Airborne Effluents - Release Summary 1st Qtr 2nd tr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases D. Gross Alpha I.

Total Activity Ci Released

+ "Total Activity Released" + Seconds in Quarter

"-" measurements below detectable levels

• Calculated value per "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents" EPRI Final Report, 12/2010. Calculated value is for the year; quarterly releases were not required to be calculated.

17

Table 2.2-A2 Millstone Power Station Unit 2 Airborne Effluents - Mixed Continuous - Aux Bldg Vent & SGBD Tank Vent

& Spent Fuel Pool Evaporation Nuclides 1

Released Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases y Emitters Ci[

Total Activity Ci B. lodines / Halo ens 1-131 Ci 7.22E-06 9.41 E-06 7.86E-06 4.77E-05 7.22E-05 1-132 Ci 1.21E-04 1.21E-04 1-133 Ci 4.62E-05 2.09E-05 3.62E-05 2.24E-04 3.28E-04 1-135 Ci 2.29E-04 2.29E-04 Total Activity Ci 5.34E-05 3.03E-05 4.41 E-05 6.22E-04 7.50E-04 C. Particulates 1-131 Ci Other y Emitters Ci Sr-89 Ci Sr-90 Ci Total Activity Ci D. Gross Alpha Gross Al ha Ci I

E. Tritium H-3 Ci 1.78E+00 9.74E-01 1.75E+00 6.42E+00 1.09E+01 measurements below detectable levels 18

Table 2.2-A3 Millstone Power Station Unit 2 Airborne Effluents - Mixed Batch - Containment Purges There were no containment purges during 2010.

Nuclides Released Units 2010 I

I st Qtr I 2nd Qtr I

3rd Qtr I

4th Qtr I

Total I

A. Fission & Activation Gases Y Emitters Ci Total Activity Ci B. lodines / Halog ens 1-131 Ci 1-133 Ci Total Activity Ci C. Particulates TotalActivity Ci D. Gross Alpha Gross Alpha Ci E. Tritium H-3 Ci

• No activity released 19

Table 2.2-A4 Millstone Power Station Unit 2 Airborne Effluents - Elevated Batch - WGDT Nuclides U slj Released Units 1st Qtr 2nd Qtr 3rd Qtr I

4th Qtr Total A. Fission & Activation Gases Kr-85 Ci 9.50E-01 5.38E-01 6.27E-01 2.11E+00 Other y Emitters Ci Total Activity Ci 9.50E-01 5.38E-01 6.27E-01 2.11E+00 B. lodines / Halogens Total Activity Ci na na na na na C. Particulates Total Activit Ci na na na na na D. Gross Alpha Gross Alpha Ci na na I

na na na E. Tritium H-3 Ci 2.53E-04 2.13E-04 T 2.98E-04 7.64E-04

• No activity released "na" denotes Not Required to be Analyzed measurements below detectable levels 20

Table 2.2-A5 Millstone Power Station Unit 2 Airborne Effluents - Elevated Continuous - Containment Vents/Site Stack N u c l i d e s U t 4 h tT a

Released Units 1st Qtr I 2nd Qtr 1=3rd Qtr I 4th Qtr Total A. Fission & Activation Gases Ar-41 Ci 2.82E-02 3.48E-02 3.12E-02 3.56E-02 1.30E-01 Xe-133 Ci 4.16E-03 5.68E-03 5.70E-03 9.45E-03 2.50E-02 Xe-133m Ci Xe-135 Ci 4.17E-04 4.84E-04 4.81E-04 8.61E-04 2.24E-03 Xe-138 Ci 6.63E-05 6.63E-05 Other y Emitters Ci Total Activity Ci 3.28E-02 4.09E-02 3.74E-02 4.59E-02 1.57E-01 B. lodines / Halogens 1-131 Ci 1-133 Ci Other y Emitters Ci Total Activity Ci C. Particulates y Emitters Cii I

Total Activity Ci D. Gross Alpha Gross Alpha Ci na na na na na E. Tritium H-3 Ci 1.42E-01 2.39E-01 2.25E-01 11.80E-01 7.86E-01 measurements below detectable levels "na" denotes Not Required to be Analyzed 21

Table 2.2-A6 Millstone Power Station Unit 2 Airborne Effluents - Ground Batch - Containment Equipment Hatch There were no equipment hatch releases during 2010.

Nuclides Released Units s234 r

I lst Qtr I 2nd Qtr I 3rd Qtr 1 4th Qtr Total A. Fission & Activation Gases y yEmitters I

Cii Total Activity Ci B. lodines / Halo ens 1-131 Ci 1-133 Ci Other y Emitters Ci Total Activity Ci C. Particulates y Emitters Ci Total Activity Ci D. Gross Alpha Gross Alpha Ci E. Tritium H-3 Ci

• No activity released 22

Table 2.2-A7 Millstone Power Station Unit 2 Airborne Effluents - Ground Batch - RWST Vent There were no RWST releases during 2010.

Nuclides Released Units

ý1111 11 I lstQtr I 2ndQtr I 3rdQtr I

4th Qtr I

Total I

A. Fission & Activation Gases y Emiiers Total Activity B. lodines / Halo gens 1-131 Ci 1-133 Ci Other y Emitters Ci Total Activity Ci C. Particulates IyEmitters Cii Total Activity D. Gross Alpha GrossAlpha Ci E. Tritium H-3 Ci

• No activity released 23

Table 2.3-Al Millstone Power Station Unit 3 Airborne Effluents - Release Summary Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases D. Gross Alpha

1.

Total Activity Ci Released

+ "Total Activity Released" - Seconds in Quarter measurements below detectable levels

• Calculated value per "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents" EPRI Final Report, 12/2010 Calculated value is for the year; quarterly releases were not calculated.

24

Table 2.3-A2 Millstone Power Station Unit 3 Airborne Effluents - Mixed Continuous - Normal Ventilation & Spent Fuel Pool Evaporation Nuclides Released Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases Xe-1 33 Ci 1.52E+01 1.52E+01 Other y Emitters Ci Total Activity Ci 1.52E+01

-1.52E+01 B. lodines I Halo ens 1-131 Ci 2.09E-03 2.09E-03 1-133 Ci 6.91E-05 6.91E-05 Other*y Emitters Ci Total Activity Ci 2.16E-03 2.16E-03 C. Particulates Cr-51 Ci 1.56E-05 1.56E-05 Co-58 Ci 1.24E-05 1.24E-05 Nb-95 Ci 1.87E-06 1.87E-06 Sb-1 24 Ci 1.27E-06 1.27E-06 Cs-1 34 Ci 1.02E-06 1.02E-06 Ba-140 Ci 8.11E-06 8.11E-06 Other y Emitters Ci Sr-89 Ci Sr-90 Ci Total Activity Ci D. Gross Alpha Gross Alpha Ci E. Tritium H-3 Ci 7.OE+00 I1.30E+01 i1.44E+01 1.42E+01i 4.86E+0i measurements below detectable levels 25

Table 2.3-A3 Millstone Power Station Unit 3 Airborne Effluents - Ground Continuous - ESF Building Ventilation Nuclides Released Units 2010 I

lstQtr I

2nd Qtr I

3rd Qtr I

4th Qtr I

Total I

A. Fission & Activation Gases Xe-1 33 Ci 1.22E-02 1.22E-02 Xe-135 Ci 5.81E-03 5.81 E-03 Other y Emitters Ci Total Activity Ci 1.80E-02 1.80E-02 B. lodines / Halogens 1-131 Ci 5.52E-06 5.52E-06 1-133 Ci 2.13E-06 2.13E-06

-Other y Emitters Ci Total Activity Ci

-7.65E-06 7.65E-06 C. Particulates Be-7 Ci 5.82E-07 5.95E-07 7.30E-07 1.91 E-06

-Other y Emitters Ci Sr-89 Ci Sr-90 Ci Total Activity Ci 5.82E-07 5.95E-07 7.30E-07 1.91 E-06 D. Gross Alpha Gross Alpha Ci I

I E. Tritium H-3 Ci 2.26E-02 1.32E-01 5.68E-02 1.14E-01 3.25E-01 measurements below detectable levels 26

Table 2.3-A4 Millstone Power Station Unit 3 Airborne Effluents - Mixed Batch - Containment Drawdowns Nuclides l

Released Units I

1stQtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases Xe-133 Ci*

1.31E-04 I 1.31 E-04 Other y Emitters Ci I

Total Activity Ci 1.31 E-04 1.31 E-04 B. lodines / Halogens 1-131 Ci*

2.07E-07 2.07E-07 1-133 Ci Other y Emitters Ci Total Activity Ci 2.07E-07 2.07E-07 C. Particulates y Emitters Ci I

Total Activity Ci D. Gross Alpha Gross Alpha Ci na na E. Tritium H-3 Ci 3.OOE-03 3.005-03 measurements below detectable levels "na" denotes Not Required to be Analyzed

• No activity released 27

Table 2.3-A5 Millstone Power Station Unit 3 Airborne Effluents - Mixed Batch - Containment Purges Nuclides Released Units 1

2010 I

1 st Qtr I

2nd Qtr I

3rd Qtr I

4th Qtr I

Total I

A. Fission & Activation Gases Ar-41 Ci 7.55E-04 7.55E-04 Xe-133 Ci 1.42E-01 1.42E-01 Xe-1 35 Ci 4.54E-03 4.54E-03 y Emitters Ci Total Activity Ci 1.47E-01 1.47E-01 B. lodines / Halog ens 1-131 Ci 1-133 Ci Other y emitters Ci Total Activity Ci C. Particulates y Emitters Ci Total Activity Ci D. Gross Alpha Gross Alpha Ci na na na na na E. Tritium H-3 Ci 1.10E-02 1.10E-02

- measurements below detectable levels "na" denotes Not Required to be Analyzed

• No activity released 28

Table 2.3-A6 Millstone Power Station Unit 3 Airborne Effluents - Elevated Continuous - Gaseous Waste System Nuclides Released Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total I

A. Fission & Activation Gases Ar-41 Ci 2.89E-04 2.08E-04 4.97E-04 Kr-85 Ci 6.29E-01 9.84E-01 2.96E-01 2.50E-01 2.16E+00 Kr-85m Ci 2.19E-02 2.19E-02 Kr-88 Ci 1.26E-02 1.26E-02 Xe-131 m Ci 1.09E-03 1.09E-03 Xe-133 Ci 4.50E-01 6.90E+00 6.17E-03 7.36E+00 Xe-133m Ci 1.39E-01 1.39E-01 Xe-1 35 Ci 6.39E-05 8.89E-01 8.89E-01 Other y Emitters Ci Total Activity Ci 1.08E+00 8.95E+00 3.02E-01 2.50E-01 1.06E+01 B. lodines / Halo ens 1-131 Ci 2.20E-07 3.57E-05 3.59E-05 1-133 Ci 1.44E-06 1.44E-06 Br-82 Ci 4.23E-06 1.53E-06 1.69E-06 8.21 E-06 1.57E-05 Other y Emitters Ci Total Activity I Ci 4.45E-06 3.87E-05 1.69E-06 8.21 E-06 5.30E-05 C. Particulates Be-7 Ci 2.47E-07 2.47E-07 Co-58 Ci 7.04E-07 2.23E-08 7.26E-07 Co-60 Ci 3.90E-08 3.90E-08 Ba-140 Ci 1.08E-07 1.08E-07 Other y Emitters Ci Sr-89 Ci Sr-90 Ci Total Activity Ci 3.90E-08 7.04E-07 2.69E-07 1.08E-07 1.12E-06 D. Gross Alpha IGross Alpha I ci-I I

E. Tritium JH-3 I ci 5

S.49E-01 I3.04E-O1 I3.16E-01 6.85E-01 I 1.85E+O0 measurements below detectable levels 29

Table 2.3-A7 Millstone Power Station Unit 3 Airborne Effluents - Elevated Batch - Containment Vents Nuclides Released Units 1

2010 I

1 st Qtr I 2nd Qtr I

3rd Qtr I

4th Qtr Total I

A. Fission & Activation Gases Ar-41 Ci 9.14E-03 2.90E-03 5.06E-03 1.12E-02 2.83E-02 Xe-1 33 Ci 7.14E-02 1.02E-02 2.06E-03 2.38E-03 8.60E-02 Xe-1 33m Ci 1.44E-04 1.36E-04 2.80E-04 Xe-1 35 Ci 1.60E-03 3.40E-04 2.86E-04 6.33E-04 2.86E-03 Xe-135m Ci 9.21E-05 6.14E-05 1.54E-04 Other y Emitters Ci Total Activity Ci 8.24E-02 1.36E-02 7.41 E-03 1.42E-02 1.18E-01 B. lodines / Halo gens 1-131 Ci 1-133 Ci Other y Emitters Ci Total Activity Ci C. Particulates y Emitters Ci Total Activity Ci D. Gross Alpha Gross Alpha Ci na na na na na E. Tritium H-3 Ci 2.06E-02 1.94E-02 8.25E-02 1.57E-02 1.38E-01 "na" denotes Not Required to be Analyzed measurements below detectable levels 30

Table 2.3-A8 Millstone Power Station Unit 3 Airborne Effluents - Ground Batch - Containment Equipment Hatch Nuclides Released Units 1

2010 i

1 st Qtr I 2nd Qtr I

3rd Qtr I

4th Qtr I

Total A. Fission & Activation Gases Xe-133 Ci 2.1OE+00 2.1OE+00 Other y Emitters Ci Total Activity Ci B. lodines / Halo~

ens 1-131 Ci 3.70E-05 3.70E-05 1-132 Ci 3.87E-06 3.87E-06 1-133 Ci 2.04E-07 2.04E-07 Total Activity Ci 4.11E-05 4.11E-05 C. Particulates Cr-51 Ci 8.05E-06 8.05E-06 Mn-54 Ci 1.75E-06 1.75E-06 Co-58 Ci 8.57E-06 8.57E-06 Fe-59 Ci 2.15E-07 2.15E-07 Co-60 Ci 3.37E-06 3.37E-06 Nb-95 Ci 1.54E-06 1.54E-06 Zr-95 Ci 8.78E-07 8.78E-07 Other y Emitters Ci Total Activity Ci 2.44E-05 2.44E-05 D. Gross Alpha Gross Alpha Ci na na na na na E. Tritium H-3 Ci na na na na I

na I

measurements below detectable levels No activity released "na" denotes Not Required to be Analyzed 31

Table 2.3-A9 Millstone Power Station Unit 3 Airborne Effluents - Ground Batch - RWST Vent Nuclides Released Units 1 st Qtr t 2nd Qtr 3rd Qtr I

4th Qtr Total A. Fission & Activation Gases Xe-1 33 Ci na 8.42E-02 na na 8_42e-02 Other y Emitters Ci na na na Total Activity Ci na 8.42E-02 na na 1.18E-01 B. lodines / Halogens 1-131 Ci na 2.07E-04 na na 2.07E-04 Other y Emitters Ci na na na Total Activity Ci na 2.07E-04 na na 2.07E-04 C. Particulates Cr-51 Ci na 2.18E-05 na na 2.18E-05 Mn-54 Ci na 3.22E-06

_na na 3.22E-06_

Co-57 Ci na 1.66E-07 na na 1.66E-07 Co-58 Ci na 7.35E-05 na na 7.35E-05 Fe-59 Ci na 5.24E-07 na na 5.24E-07 Co-60 Ci na 2.77E-06 na na 2.77E-06 Zr-95 Ci na 1.32E-06 na na 1.32 E-06_

Nb-95 Ci na 1.91 E-06 na na 1.91 E-06 Ag -1n......................

C..........................

..................... _7.1 9 E -0 7.._

n n....

I....................................

1..-oan a

_1 Sb-i 24 Ci na 7.65E-08 na na 7.65E-08 Sb-125 Ci na 1.77E-06 na na

_1.77E-06_

Cs-1 34 Ci na 7.33E-06 na na 7.33E-06 Cs-i136------Ci

~na 2.43E-07 na na 2.43E-07 Cs-137 Ci na 4.77E-06 na na 4.71E-06 La-140 Ci na 7.12E-07 na na 7.32E-07

_O

~t~

e r y

.E m.!.t e rs.....................

C !...........

.........n........................

.....a...................................

I...................

n a...........

I-. I.....-

Othry miter Ci na 1.2-0 na na 1.2-0 Total Activity Ci na 1.20E-04 na na 1.20E-04 D. Gross Alpha Gross Alpha Ci na na na na na E. Tritium H-3 Ci na na na na na "na" denotes not required to be analyzed measurements below detectable levels 32

2.2 Liquid Effluents 2.2.1 Measurement of Liquid Radioactivity 2.2.1.1 Continuous Liquid Releases Grab samples are taken for continuous liquid release pathways and analyzed on the HPGe gamma spectrometer and liquid scintillation detector (for tritium) 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 include, Steam Generator Blowdown, Service Water Effluent, and Turbine Building Sump discharge from Units 2 & 3.

2.2.1.2 Liquid Tanks/Sumps There are numerous sources from which liquids containing radioactivity are discharged to the environs; they are:

Unit 1 Underground ventilation duct Unit 2 Clean Waste Monitor Tanks (2)

Aerated Waste Monitor Tanks CPF Waste Neutralization Sump & Turbine Building Sump Steam Generator Bulk Unit 3 High Level Waste Test Tanks (2)

Low Level Waste Drain Tanks (2)

Boron Test Tanks CPF Waste Neutralization Sump & Turbine Building Sump Steam Generator Bulk 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.

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 NBS 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 33

2.2.3 Liquid Batch Release Statistics Number of Batches Total Time (min)

Maximum Time (min)

Average Time (min)

Minimum Time (min)

Average Stream Flow Unit 1 1

330 330 330 330 Unit 2 51 4438 244 87 2

Unit 3 57 7670 272 135 66 Not Applicable - Ocean Site 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 2010, the following abnormal liquid releases occurred:

2.2.4.1 Unit 1 - None 2.2.4.2 Unit 2 - None 2.2.4.3 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 obtained from Reference 2. They are categorized by type of release, source(s),

and by release point of discharge to the environment.

34

Table 2.1-Li Millstone Power Station Unit 1 Liquid Effluents - Release Summary (Release Point - Quarry)

Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total j

A. Fission and Activation Products D. Gross Alpha I. Total Activity Ci Released E. Volume I.

Released Waste Liters 1.16E+05 1.16E+05 Volume

2.

Dilution Volume Liters 6.49E+08 6.49E+08 During Releasesý++

3.

Dilution Volume Liters 2.55E+1 1 2.55E+1 1 During Period-_

measurements below detectable levels No activity released

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

++ Unit 2 E.3 quarterly dilution used because there is no more Unit I dilution

.++ E.3 quarterly dilution x (Total release time - Total quarter time) 35

Table 2.1-L2 Millstone Power Station Unit 1 Liquid Effluents - Batch (Release Point - Quarry)

Nuclides U

Released Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Products Cs-137 Ci 1.37E-05 1.37E-05 Sr-90 Ci Fe-55 Ci Total Activity Ci 1.37E-05 1.37E-05 B. Tritium H-3 I CiI C. Dissolved & Entrained Gases Kr-85 Ci-Total Activity Ci D. Gross Alpha Gross Alpha Ci measurements below detectable levels

• No activity released 36

Table 2.2-L1 Millstone Power Station Unit No. 2 Liquid Effluents - Release Summary (Release Point - Quarry)

I=

2010

[ Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I

Total I

D. Gross Alpha

1.

Total Activity Ci Released E. Volume I.

Released Waste Volume Primary Liters 2.82E+05 2.57E+05 1.35E+05 6.81 E+05 1.35E+06 Secondary Liters 4.05E+03 5.52E+07 4.08E+10 6.48E+03 4.08E+10

2.

Dilution Volume During Releases Primary Liters 1.63E+09 1.61E+09 1.72E+09 3.01E+09 7.96E+09 Secondary Liters

3.

Dilution Volume During Period Liters 2.23E+11 2.55E+11 2.58E+11 2.54E+11 9.90E+11 measurements below detectable levels

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

++ No release of secondary waste 37

Table 2.2-L2 Millstone Power Station Unit 2 Liquid Effluents - Continuous - SGBD, SW, RBCCW (Release Point - Quarry)

Nuclides Unis lil Released Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Products y Emitters Ci Sr-89 Ci na na na na na Sr-90 Ci na na na na na Fe-55 Ci na na na na na Total Activity Ci B. Tritium H-3

] Ci I 1.40E-05 7.04E-03 4.02E-03 3.74E-04 1.14E-02 C. Dissolved & Entrained Gases y Emitters Ci Total ActivityH Ci D. Gross Alpha Gross Alpha I Ci na na na na.

na measurements below detectable levels "na" denotes not required to be analyzed 38

Table 2.2-L3 Millstone Power Station Unit 2 Liquid Effluents - Batch - LWS (Release Point - Ouarrv)

Nuclides Released Units I st Otr I

2nd Otr I

3rd Otr I 4th Otr I

Total A. Fission & Activation Products Cr-51 Ci 1.41 E-05 1.41 E-05 Mn-54 Ci 2.68E-05 4.02E-05 4.96E-05 3.39E-06 1.20E-04 Co-57 Ci 4.12E-06 4.12E-06 Co-58 Ci 6.62E-04 2.77E-04 6.82E-05 2.30E-04 1.24E-03 Co-60 Ci 1.97E-04 5.71 E-04 6.55E-04 1.86E-03 3.29E-03 Nb-95 Ci 1.31 E-04 1.44E-04 2.75E-04 Zr-95 Ci 4.37E-05 8.38E-05 6.85E-06 1.34E-04 Ru-106 Ci 3.37E-05 3.37E-05 Ag-I 10in Ci 9.28E-05 2.58E-04 1.37E-03 7.71 E-04 2.49E-03 Sn-113 Ci 7.83E-06 7.83E-06 Sn-1171n Ci 5.29E-06 5.29E-06 Sb-124 Ci 8.45E-06 9.71 E-06 1.82E-05 Sb-125 Ci 3.50E-04 4.OOE-04 1.92E-04 8.78E-04 1.82E-03 1-131 Ci 1.89E-05 1.89E-05 Cs-134 Ci 3.48E-05 3.05E-05 3.32E-05 9.84E-05 Cs-136 Ci 1.18E-07 1.18E-07 Cs-137 Ci 1.44E-04 8.68E-05 2.06E-06 1.89E-04 4.22E-04 Fe-55 Ci 1.76E-03 7.25E-04 8.45E-04 2.17E-04 3.54E-03 Ni-63 Ci 1.37E-03 5.09E-04 8.30E-05 1.80E-03 3.76E-03 Sr-89 Ci 4.63E-06 4.63E-06 Sr-90 Ci Total Activity Ci 4.85E-03 3.13E-03 3.28E-03 6.04E-03 1.73E-02 B. Tritium IH-3 I Ci

[ 1.10E+01 I 5.67E+01 1 2.31 E+01 I 3.36E+02

4.27E+02 C. Dissolved & Entrained Gases Ar-41 Ci 3.27E-05 3.27E-05 Kr-85 Ci 6.99E-02 5.78E-02 1.83E-01 3.11E-01 Kr-85m Ci 4.77E-05 4.77E-05 Xe-131in Ci 6.1OE-03 6.1OE-03 Xe-133 Ci 2.OOE-04 1.59E-04 1.40E-01 1.40E-01 Xe-1331n Ci 9.15E-04 9.15E-04 Xe-135 Ci 1.92E-05 5.20E-03 5.22E-03 Total Activity Ci 7.01 E-02 5.79E-02 3.35E-01 4.63E-01 D. Gross Alpha Gross Alpha Ci

-a measurements below detectable levels 39

Table 2.2-L4 Millstone Power Station Unit 2 Liquid Effluents - Release Summary (Release Point - Yard Drain - DSN 006) t 2010 I Units I 1st Otr I 2nd Otr I 3rd Otr I 4th Otr I

Total I

Tritium Total Activity Ci 3.65E-03 1.36E-03 9.32E-04 1.25E-02 1.84E-02 Released Average Period uCi/mi 8.25E-08 4.03E-08 4.31 E-08 3.38E-07 1.35E-07 Diluted Activity +

Dissolved and Entrained Gases Total Activity Ci Released Average Period uCi/ml Diluted Activity +

Gross Alpha Total Activity Ci

-1 Released Volume Released Waste Liters 1.43E+06 8.81 E+04 4.37E+05 1.55E+06 3.50E+06 Volume

+/

+

I

+/-4-++

44-+

Dilution Volume Liters During Releases Dilution Volume Liters 4.28E+07 3.35E+07 2.12E+07 3.55E+07 1.33E+08 During Period ++

measurements below detectable levels

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

H-Includes all station dilution sources via Yard Drain - DSN 006

... Continuous "Dilution Volume During Releases" is not quantified 40

Table 2.2-L5 Millstone Power Station Unit 2 Liquid Effluents -Continuous-Turbine Building Sump/Totes (Release Point - Yard Drain - DSN 006)

Nuclides Unis l1l1ý Released Units I 1st Qtr 2nd Qtr I 3rd Qtr I 4th Qtr Total A. Fission & Activation Products Co-60 Ci 1.37E-06 1.37E-06 Cs-137 Ci 3.83E-07 3.67E-08 4.20E-07 Other y Emitters Ci Sr-89 Ci na na na na na Sr-90 Ci na na na na na Fe-55 Ci na na na na na Total Activity Ci B. Tritium H-3 I Ci I 3.65E-03 1.36E-03 9.32E-04 1.25E-02 1.84E-02 C. Dissolved & Entrained Gases y Emitters rCI Total Activity C

j D. Gross Alpha Gross Alpha Ci na na na na na measurements below detectable levels "na" denotes Not Required to be Analyzed 41

Table 2.3-L1 Millstone Power Station Unit 3 Liquid Effluents - Release Summary (Release Point - Quarry)

Units 1 st Qtr 2nd Qtr 3rtd Qtr 4th Qtr Total D. Gross Alpha I.

Total Activity Ci Released E. Volume I.

Released Waste Volume Primary Liters 7.87E+05 1.33E+06 1.06E+06 7.37E+05 3.91E+06 Secondary Liters 4.37E+06 3.44E+06 6.88E+06 5.77E+06 2.05E+07

2.

Dilution Volume During Releases Primary Liters 3.08E+09 2.33E+09 4.45E+09 3.39E+09 1.33E+10 Secondary Liters 7.72E+09 4.59E+08 1.32E+10 1.41E+10 3.55E+10

3.

Dilution Volume During Period Liters 4.01E+11 2.94E+11 4.25E+11 4.17E+11 1.54E+12 measurements below detectable levels

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

42

Table 2.3-L2 Millstone Power Station Unit 3 Liquid Effluents - Continuous - SGBD & SW (Release Point - Quarry)

Nuclides MlýL Released Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr I

Total A. Fission & Activation Products y Emitters Ci Sr-89 Ci na na na na na Sr-90 Ci na na na na na Fe-55 Ci na na na na na Total Activity Ci B. Tritium H-3 Ci [ 1.38E-02 1.16E-02 4.70E-02 6.59E-02 1.38E-01 C. Dissolved & Entrained Gases y Emitters cCi [

Total Activity Ci D. Gross Alpha Gross Alpha Ci na na na na na measurements below detectable levels "na" denotes Not Required to be Analyzed 43

Table 2.3-L3 Millstone Power Station Unit 3 Liquid Effluents - Batch - LWS (Release Point - Quarry)

Nuclides Il 1

Released Units Ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Products Mn-54 Ci 1.65E-04 1.58E-04 1.05E-03 4.43E-05 1.42E-03 Co-58 Ci 1.57E-04 1.08E-03 3.01 E-03 4.30E-04 4.68E-03 Fe-59 Ci 3.57E-05 1.30E-04 2.86E-05 1.94E-04 Co-60 Ci 1.92E-03 8.99E-04 8.OOE-03 8.85E-04 1.17E-02 As-76 Ci 6.53E-06 6.53E-06 Nb-95 Ci 9.41 E-05 5.08E-04 6.02E-04 Zr-95 Ci 2.67E-04 2.67E-04 Ag-110m Ci 1.10E-04 5.94E-05 1.69E-04 Sb-122 Ci 7.17E-05 7.17E-05 Sb-124 Ci 3.61 E-05 2.91 E-05 6.52E-05 Sb-125 Ci 3.91E-03 1.29E-02 2.39E-03 2.93E-03 2.21E-02 1-131 Ci 1.81 E-03 1.81 E-03 1-133 Ci 2.94E-05 2.94E-05 Cs-134 Ci 7.96E-05 6.34E-03 1.68E-03 3.05E-05 8.13E-03 Cs-136 Ci 6.81 E-05 6.81 E-05 Cs-137 Ci 8.26E-05 4.23E-03 1.15E-03 4.22E-05 5.50E-03 Fe-55 Ci 2.01E-03 2.99E-03 1.03E-02 2.53E-03 1.78E-02 Ni-63 Ci 2.12E-03 2.12E-03 Sr-89 Ci Sr-90 Ci Total Activity Ci 8.43E-03 3.07E-02 3.07E-02 6.96E-03 7.68E-02 B. Tritium H-3 J Ci 4.04E+02 1.12E+02 1.62E+02 2.15E+02 8.93E+02 C. Dissolved & Entrained Gases Xe-133 Ci 2.16E-05 9.81E-05 1.20E-04 Other y Emitters Ci Total Activity Ci 2.16E-05 9.81E-05 1.20E-04 D. Gross Alpha Gross Alpha Ci measurements below detectable levels 44

Table 2.3-L4 Millstone Power Station Unit 3 Liquid Effluents - Batch - CPF Waste Neutralization Sumps, Hotwell, S/G Bulk (Release Point - Quarry)

Nuclides i

Released Units 1st Qtr I 2nd Qtr I 3rdQtr I 4th Qtr Total I

A. Fission & Activation Products y Emitters Ci Fe-55 Ci na na na na na Sr-89 Ci na na na na na Sr-90 Ci na na na na na Total Activity Ci B. Tritium H-3 3 Ci I 3.24E-03 4.15E-03 6.12E-03 1.10E-02 2.45E-02 C. Dissolved & Entrained Gases Y Emitters Cii I

Total Activity Ci D. Gross Alpha Gross Alpha Ci na na na na na measurements below detectable levels "na" denotes Not Required to be Analyzed 45

Table 2.3-L5 Millstone Power Station Unit 3 Liquid Effluents - Release Summary (Release Point - Yard Drain - DSN 006)

Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total D. Gross Alpha Total Activity Ci Released E. Volume Released Waste Liters 6.08E+06 1.95E+06 5.23E+06 6.91 E+06 2.02E+07 Volume Dilution Volume Liters During Releases I

Dilution Volume Liters 3.81 E+07 3.17E+07 1.64E+07 3.01 E+07 1.16E+08 During Period ++

measurements below detectable levels

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

++ Includes all station dilution sources via Yard Drain - DSN 006 Continuous "Dilution Volume During Releases" is not quantified 46

Table 2.3-L6 Millstone Power Station Unit 3 Liquid Effluents - Continuous - TB Sump, WTT Berm (Release Point - Yard Drain - DSN 006)

Nuclides Released Units lstQtr I 2ndQtr I 3rdQtr I 4thQtr Total A. Fission & Activation Products y Emitters Ci Sr-89 Ci na na na na na Sr-90 Ci na na na na na Fe-55 Ci na na na na na Total Activity Ci B. Tritium H-3

[

Ci 1 2.21 E-021.85E-03 3.69E-02 9.23E-02 1.53E-01 C. Dissolved & Entrained Gases yEmitters

]Cir Total Activity Ci D. Gross Alpha Gross Alpha Ci na na na na na measurements below detectable levels "na" denotes Not Required to be Analyzed 47

Table 2.3-L7 Millstone Power Station Unit 3 Liquid Effluents - Continuous - Foundation Drain Sumps (Release Point - Yard Drain - DSN 006)

Nuclides I

Released lUnits 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Products y Emitters Ci Sr-89 Ci na na na na na Sr-90 Ci na na na na na Fe-55 Ci na na na na na Total Activity Ci B. Tritium H-3 I

Ci ] 3.93E-02 4.02E-03 6.44E-03 3.98E-03 5.37E-02 C. Dissolved & Entrained Gases

-y Emitters Cii Total Activity

-C D. Gross Alpha Gross Alpha Ci na na na na na measurements below detectable levels "na" denotes Not Required to be Analyzed 48

2.3 Solid Waste Solid waste shipment summaries for each unit are given in the following tables (Reference 13):

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 fW 3

122 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 49

Table 2.1-S Solid Waste and Irradiated Component Shipments Millstone Power Station Unit 1 January 1, 2010 through December 31, 2010 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

Fitrs*ri E apba&

Battoms VPlumeeAboveTable A

N/A N/A N/A B

N/A N/A N/A C.

N/A N/A N/A AL*

N-A.NA N/A Major Nuclides for the Above Table:

"'CUIES 1,(TOTAL)

'0 DiVAciveWateVolume, Cuiries Shp~

Wate Class f 3 ii'N

,'Cure Fe55' 5.2 2119E0 A

1.8500E+02 5.2392E+00 4.6123E-03 B.'

N~'N N/A N/A N/A C

/A N/A N/A ALL

.0 5.2392E0 4.6123E-03 Major Nuclides for the Above Table:-________

Fe-55 45.92%

2.1179E-03 Co-60 13.91%

6.4154E-004 Ni-63'

.17.65%

8.1412E-04 Csý-137 22.36%

1.0311 E-03 Pu-238

-C0.01 %

3.3164E-07.

Pu-239

< 0.01 %

1.7755E-07 Pu-241 0.13%

6.1511E-06.,

Am-241 0.02%.7.4245E-07 Cm-244

< 0.01R%

2.4953E-07 CURISN~TTAL)

I 4.6123E-03 50

Table 2.1-S (continued)

Solid Waste and Irradiated Component Shipments Millstone Power Station Unit 1

,,a,

.,,om on nt,

Volurne Curios Shi~pp Waste Cla~ss rn C'

t uries' A

N/A N/A N/A BN/A N/A N/A C 'N/A N/A N/A ALL N/A N/A NI/A Major Nuclides for the Above Table:

PCUR1E!S-TTAT 0

h e r ste Volum Nur~les Shipped Waste Class, ft3 Cuie 1.1092E+02 3.1414E+00 4.2182E-03 BN/A N/A N/A CN/A N/A N/A AL1.1 092E+02 3.1414E+00 4.21 82E-03 Major Nuclides for the Above Table:

,,,Rad~ionuclidi[

W%-o~K~j7i'ii~~

H-3 77.34%

3.2623E-03 Cr-51

< 0.01%

8.3212E-08 Mn-54 0.08%

3.4447E-06 Fe-55 3.32%

1.4019E-04 Fe-59

< 0.01%

2.3828E-09 Co-58 0.06%

2.5846E-06 Co-60...

0.98%

4.1246E-05.

Ni-63 1.57%

6.6310E-05..

Zr-95

< 0.01%

3.7255E-08 Nb-95

< 0.01%

5.1558E-08 Sb-124

< 0.01%

2.5894E-09 Sb-125 0.04%

1.5919E-06 Cs-134 0.06%.

2.7052E-06 Cs-137 16.54%

6.9764E-04 Pu-238

< 0.01%

7.1357E-09 Arn-241

< 0.01%

1.0353E-08 CJES: (TOTA L*.

4.2182E-03 51

Table 2.1-S (continued)

Solid Waste and Irradiated Component Shipments Millstone Power Station Unit 1 Sum,,,A.vw"Le -,=!.Waste...........**

o*,*:*

i.2.9592E+02 8.3806E+00 8.8305E-03 N/A N/A N/A bN/A N/A N/A ALL:

2.9592E+02 8.3806E+OO 8.8305E-03 Major Nuclides for the Above Table:

d

,,,,d, RadouclIde J fTtal J

Cre H-3 36.94%

3.2623E-03 Cr-51

" <'0.01t%

8.3212E-08 Mn-54 0.04%

3.4447E-06 Fe-55 25.57%

2.2581 E-03 Fe-59 e<,0.01%

2.3828E-09 Co-58 0.03%

2.5846E-06....

Co-60 7.73%

6.8279E-04..

Ni-63 9.97%

8.8043E-04.

Zr-95

< 0.01%

3.7255E-08 Nb-95

< 0.01%

5,1558E-08 Sb-124

< 0.01%

2.5894E-09 Sb-125 0.02%

1.5919E-06 Cs-134 0.03%

2.7052E-06 Cs-137 19.58%

1.7288E-03 Pu-238

< 0.01%

3.3878E-07 Pu-239

<"0.01%

1.7755E-07 Pu-241 0.07%

6.1511E-06 Am-241"

<0.01%

7.5280E-07 Cm-244

< 0.01%

2.4953E-07

-CURIES(TOTAL);

88305E-03 52

Table 2.2-S Solid Waste and Irradiated Component Shipments Millstone Power Station Unit 2 January 1, 2010 through December 31, 2010 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

~Curies Shipped, WseClas ft3.

m

.Curi1es 7.3500E+01 2.0815E+00 1.3262E-01 2.4060E+02 6.8138E+00 5.4368E+01 8.9632E+01 2.5384E+o0 6.960E+00 ALL4.0373E+02 1.1434E+01 6.0697E+01 Major Nuclides for the Above Table:

• Radionuclide.'.

% of.Total

]

Curies H-3 0.14%

8.7107E702 C-14

< 0.01%

5.1132E-03 Cr-51

< 0.01%

3.9156E-04 Mn-54 1.89%

1.1473E+00 Fe-55 14.83%

9.0001EE+00 Fe-59

<0.01%

3.1310E-04 Co-57 0.27%

1.6547E-01 Co-58 1.11%

6.7526E-01 Co-60 9.14%

5.5464E+00 Ni-63 60.64%

3.6809E+01 Zn-65

< 0.01%

4.9324E-04.

Sr-89

< 0.01%

4.0883E-04 Sr-90 0.03%

1.9967E-02 Nb-94

< 0.01%

3.9142E-04 Zr-95

< 0,01%

3.5842E-03 Nb-95

< 0.01%

3.3718E-03 Ru-103

< 0.01%

5.7491E-15 Ru-1 06

<.0.01%

9.1738E-04.

Ag-110m

< 0.01%

4.7262E-03 Sn-113u

< 0.01%

1.5022E-03 Sb-124

< 0.01%

1.6837E-04 Sb-125 4.24%

2.5715E+00 Cs-134 2.36%

1.4344E+00 Cs-137 5.27%

3.1994E+00 Ce-141

< 0.01%

1.7864E-17 Ce-144

< 0.01%

1.3012E-04 Hf-181

< 0.01%

9.2337E-06 Pu-238

< 0.01%

6.2105E-04 Pu-239

< 0.01%

2.3653E-04 Pu-241 0.03%

1.7590E-02 Am-241

< 0.01%

4.0275E-04 Cm-242

< 0.01%

. 8.0932E-05 Cm-244

< 0.01%

8.3436E-04 CURIESTOTA):

6.0697E+01 53

Table 2.2-S (continued)

Solid Waste and Irradiated Component Shipments Millstone Power Station Unit 2 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

Dry~~~C Aciv ase

& Volme' uries Shpped A(

2.9815E+03 8.4436E+01 3.3978E-01 B

N/A N/A N/A C

.N/A N/A N/A ALL,:

2.9815E+03 8.4436E+01 3.3978E-01 Major Nuclide s for the Above Table:

Radionuclide% :%"f.Total..

i i

H-3 0.09%

3.0846E-04 Mn-54 0.42%

1.4198E-03 Fe-55.

43.73%

1.4860E-01 C0-58 3.17%

1.0780E-02 Co-60.

• 9.52%

3.2332E-02 Ni-63 36.35%

1.2352E-01 Zr-95 0.067%

2.2911 E-03 Nb-95 0.95%

3.2275E-03 Ag-11Om 0.38%

1

,.2995E-03......

Sb-125 1.12%

3.7918E-03 Cs-134 0.57%

1.9229E-03 Cs-137 2.99%

1.0151E-02 Pu-238

< 0.01%

3.7233E-06

• Pu-239

<0.01%

4.8878E-08 Pu-241 0.04%

1.1952E-04 Am-241

< 0.01%

2.8997E-06 Cm-244

< 0.01%

' 4.2732E-06 CURIES :TOTAL) 3 3978E-01 O T..

54

Table 2.2-S (continued)

Solid Waste and Irradiated Component Shipments Millstone Power Station Unit 2

,.,,volime Curies Shipped N

Waste Class 3

t Cr~

A N/A N/A N/A BN/A N/A N/A CN/A N/A N/A ALL N/A N/A N/A Major Nuclides for the Above Table:.

II.

Radionuclide I

%/of Tota I

Curies CUR14

-0(TO TA 0

Oither Waste Volume C uries Shipped Waste Class W.

3 M3 Curies A

2.1871E+03 6.1938E+01 33511E-02 B

N/A N/A N/A Cý N/A N/A N/A ALL 2.1871E.03 6.1938E+01 3.35111-02 Major Nuclides for the Above Table:

Rdould tof:Total: 4 -7 Curies H-3 88.91%

2.9793E-02 C-14

<0.01%

1.02OOE-08 Cr-58

<0.01%

3.5885E-07 Mn-54 0.02%

6.3825E-06 Fe-55 0.67%

2.2495E-04 Fe-59

< 0.01%

1.0276E-08 Co-58

< 0.03%

1.0667E-05

• N-60 0.19%

6.2421E-05 Ni-63 0.34%

1.1529E-04 Zn-65

< 0.01%

4.7087E-08 Zr-95

< 0.01%

8.7266E-07 Nb-95

<0.01%

1.3323E-06 Tc-99

< 0.01%

1.9712E-09 Ag-13rn

<0.01%

1.3105E-08 Sb-124

<0.01%

3.1655E-07 Sb-I 25 0.03%

1.0999E-05 1-129

< 0.01%

2.8473E-10 Cs-134 0.02%

7.2583E-06 Cs-137 9.78%

3.2767E-03 Pu-238

< 0.01%

7.8303E-09 Pu-239

< 0.01%

9.1989E-12 Am-241

< 0.01%

1.0870E-08 Cm-242

< 0.01%

2.6346E-1 1 Cm-244

< 0.01%

8.3261E-10

.CURI.ES.(TOTA 3.3511E-02 55

Table 2.2-S (continued)

Solid Waste and Irradiated Component Shipments Millstone Power Station Unit 2 Suimof. Afll LowLevel Waste.

Shpe rat ieVolume Curies Shippe'd Waste Cla S' f 3 i 3 Cre A

5.2421 E+03 1.4846E+02 5.0591 E-0 1 B

2.4060E+02 6.8138E+00 5.4368E+01 C

8.9632E+01 2.5384E+00 6.1960E+00 AýLLL 5.5723E+03 1.5781E+02 6.t070E+01 Major Nuclides for the Above Table:

Radionuclide f +Total Curies.

H-3 0.19%

1.1721 E-01 C-14

< 0.01%

5.1133E-03 Cr-51

< 0.01%

3.9192E-04 Mn-54 1.88%

1.1488E+00 Fe-55 14.98%

9.1489E+00 Fe-59

< 0.01%

3.1311 E-04 Co-57 0.27%

1.6547E-01 Co-58 1.12%

6.8605E-01 Co-60 9.14%

.5.5788E+00.

Ni-63 60.48%

3.6932E+01 Zn-65

< 0.01%

4.9329E-04 Sr-89

< 0.01%

4.0883E-04 Sr-90 0.03%

1.9967E-02 Nb-94

< 0.01%

3.9142E-04 Zr-95

< 0.01%

5.8762E-03 Nb-95 0.01%

6.6007E-03 Tc-99

< 0.01%

1.9712E-09 Ru-103

< 0.01%

5.7491E-15 Ru-106

< 0.01%

9.1738E-04 Ag-110m

< 0.01%

6.0257E-03 Sn-113

< 0.01%

1.5022E-03 Sb-124

< 0.01%

1.6869E-04 Sb-125 4.22%

2.5753E+00 1-129

< 0.01%.

2.8473E-10 Cs-134 2.35%

1.4363E+00 Cs-137 5.26%

3.2129E+00 Ce-141

< 0.01%

1.7864E-17 Ce-144

< 0.01%

1.3012E-04 Hf-181

< 0.01%

9.2337E-06 Pu-238

< 0.01%

6.2478E-04 Pu-239

< 0.01%

2.3658E-04 Pu-241 0.03%

1.7710E-02 Am-241

< 0.01%

4.0566E-04 Cm-242

< 0.01%

8.0932E-05 Cm-244

<0.01%

8.3863E%04

'CUjRI~~TT 6.1 070E+01 56

Table 2.3-S Solid Waste and Irradiated Component Shipments Millstone Power Station Unit 3 January 1, 2010 through December 31, 2010 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

116SIC, rs-ad 'Evaiporator Volume CuresSh ed WateClas t-uis 2.4500E+02 6.9384E+00 2.7214E-01 N/A N/A N/A 1.1247E+02 3.1851E+00 1.4758E+01 ALL:

3.5747E+02 1.0124E+01 1.5030E+01 Major Nuclides for the Above Table:

:::RAdionuclide6

,:o. --,df Total Curies H-3 1.22%

1.8312E-01 C-14 0.08%

1.1785E-02 Cr-51

< 0.01%

2.3928E-06 Mn-54 0.61%

9.0977E-02 Fe-55 54.72%

8.2245E+00 Fe-59

< 0.01%

6.2770E-04 Co-57 0.02%

2.5999E-03 Co-58 0.20%

3.0612E-02 Co-60 17.54%

2.6362E+00 NI-63 24.25%

3.6440E+00 Zn-65

< 0.01%

1.1750E-03 Sr-89

< 0.01%

2.0280E-06 Sr-90

< 0.01%

9.2662E-04 Nb-94

< 0.01%

9.7033E-04 Zr-95 0.02%

2.4160E-03 Nb-95 0.02%

2.8866E-03 Ru-103

< 0.01%

1.3693E-14 Ru-106.

0.01%

2.1850E-03 Ag-11Om 0.07%

1.0229E-02 Sn-113 0.02%

2.6105E-03 Sb-124

< 0.01%

2.4329E-04 Sb-125 0.65%

9.7076E-02 Cs-134 0.06%

9.3419E-03 Cs-137 0.33%

4.9019E-02 Ce-141

< 0.01%

4.2549E-17 Ce-144

< 0.01%

3.1046E-04 Pu-238

< 0.01%

6.3027E-04 Pu-239 0.01%

. 2.9361E-04 Pu-241 0.15%

2.3289E-02 Am-241

< 0.01%

6.3561E-04 Cm-242

< 0.01%

6.0920E-05 Cm-244

<0.01%

1.1574E-03

CURIES, 1TOTAL)

I

.5030E+0 57

Table 2.3-S (continued)

Solid Waste and Irradiated Component Shipments Millstone Power Station Unit 3

'Volume Cu,,ie~s-.,ipped Waste Class 3

~

Cft un

~

9r io A

9.8850E+03 2.7994E+02 7.6138E-01 i

'N/A N/A N/A CN/A N/A N/A AL9.8850E+03 2.7994E+02 7.6138E-01 Major Nuclides for the Above Table:.

Radiocli~de.[

-%'of TotalC~t*l.

.ies-H-3 4.76%

3.6243E-02 Mn-54 1.76%

1.3414E-02 Fe-55 52.10%

3.9670E-01 Co-58 2.48%

1.8852E-02 Co-60 14.79%

1.1260E-01 Ni-63 19.16%

1.4584E-01 Nb-95

< 0.01%

3.0416E-05 Cs-134 2.24%

1.7032E-02 Cs-137

.2.71%

2.0664E-02 Pu-238

< 0.01%

1.3453E-07 Pu-239

< 0.01%

4.8878E-08 Pu-241

< 0.01%

3.0960E-06 Am-241

< 0.01%

2.3648E-07 R TOTA L):'

7.6138E,01 Irra.diate C mp*nt

....ý h.e* t

Vollume, Curies.Shipped Waste class ft3

'Cu ries~'<

A N/A N/A N/A B

N/A N/A N/A C

N/A N/A N/A ALLN.

N/A N/A N/A Major Nuclides for the Above Table:

Radionclide Of Totl -

,.Cure CVRlES,.TOTAL).%

58

Table 2.3-S (continued)

Solid Waste and Irradiated Component Shipments Millstone Power Station Unit 3 Volume Curies Shipped

-Waste Class ft 3 mr 3

'Curies A

3.7900E+03 1.0733E+02 3.7915E-02 B

N/A N/A N/A N/A N/A N/A ALL 3.7900E+03 1.0733E+02 3.7915E-02 Major Nuclides for the Above Table:

Radionuclide [

% of Total

[

Curiesi H-3 96.29%

3.6509E-02 C-14

< 0.01%

1.6809E-08 Cr-51

< 0.01%

8.8413E-08 Mn-54 0.02%

7.4813E-06 Fe-55 0.56%

2.1380E-04 Fe-59

< 0.01%

2.5318E-09 Co-58 0.02%

8.9364E-06 Co-60 0.17%

6.2909E-05 Ni-63 0.28%

1.0652E-04 Zn-65

<0.01%

5.2205E-08 Zr-95

< 0.01%

3.9584E-08 Nb-95

< 0.01%

9.7209E-07 Tc-99

< 0.01%

3.2618E-07 Ag-1I0m

< 0.01%

1.4529E-08 Sb-124

< 0.01%

1.5017E-07 Sb-125 0.03%

9.5101E-06 1-129

< 0.01%

1.4615E-08 Cs-1 34 0.04%

1.3327E-05 Cs-1 37 2.48%

9.4089E-04 Th-232

< 0.01%

2.9301E-11 U (nat) 0.03%

1.1900E-05 Pu-238 0.02%

7.7066E-06 Pu-239 0.04%

1.3700E-05 Am-241 0.02%

7.3106E-06 Cm-242

< 0.01%

2.9209E-1 I Cm-244

< 0.01%

9.5926E-10

.CURIES(TOTAL

).

3.7915E-02 59

Table 2.3-S (continued)

Solid Waste and Irradiated Component Shipments Millstone Power Station Unit 3 Sumii of AllLoWLeel Waste Shiped rom iteVolume C~uries Shipped Waste Class ft3 m 3 Curies A

1.3920E+04 3.9421E+02 1.0714E+00 B

NlA N/A N/A C

1.1 247E+02 3.1851 E+00 1.4758E+01 ALL 1.4032E+04 3.9740E+02 1.5829E+01 Major Nuclides for the Above Table:

Radionuclide

, %of Total Curies H-3 1.62%

2.5587E-01 C-14 0.07%

1.1785E-02 Cr-51

< 0.01%

2.4812E-06 Mn-54 0.66%

1.0440E-01 Fe-55 54.47%

8.6214E+00 Fe-59

< 0.01%

6.2770E-04 Co-57 0.02%

2.5999E-03 Co-58 0.31%

4.9473E-02 Co-60 17.37%

2.7488E+00 Ni-63 23.94%

3.7900E+00 Zn-65

< 0.01%

1.1750E-03 Sr-89

< 0.01%

2.0280E-06 Sr-90

< 0.01%

9.2662E-04 Nb-94

< 0.01%

9.7033E-04 Zr-95 0.02%

2.4160E-03 Nb-95 0.02%

2.9180E-03 Tc-99

< 0.01%

3.2618E-07 Ru-103

< 0.01%

1.3693E-14 Ru-106 0.01%

2.1850E-03 Ag-110rn 0.06%

1.0230E-02 Sn-1 13 0.02%

2.6105E-03 Sb-124

< 0.01%

2.4344E-04 Sb-125 0.61%

9.7086E-02 1-129

< 0.01%

1.4615E-08 Cs-134 0.17%

2.6387E-02 Cs-137 0.45%

7.0624E-02 Ce-141

< 0.01%

4.2549E-17 Ce-144

< 0.01%

3.1046E-04 Th-232

< 0.01%

2.9301E-11 U (nat)

< 0.01%

1.1900E-05 Pu-238

< 0.01%

6.3811E-04 Pu-239

< 0.01%

3.0735E-04 Pu-241 0.15%

2.3292E-02 Am-241

< 0.01%

6.4316E-04 Cm-242

<0.01%

6.0920E-05 Cm-244

< 0.01%

1.1574E-03 CURIES O

1.5829E+01 I~*;:::'!

• i" k4;*,

7d!)'

60

2.4 Groundwater Monitoring The Groundwater Protection Program (GPP) describes the means by which Millstone Power Station implements the actions cited in the Nuclear Energy's Institute's (NEI) Groundwater Protection Initiative. The purpose of the GPP 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 GPP is on-site groundwater monitoring.

The results of the onsite monitoring programs required by the Radiological Environmental Monitoring Program are documented in the Annual Radiological Environmental Monitoring Report; the remaining monitoring programs are documented on the following pages (Tables 2.4-GWI - 2.4-GW5).

Another key element in the GPP is site hydrological characterization. The general trend of groundwater flow at the station is toward the Long Island Sound. Although positive measurements of plant related activity are noted in the Tables 2.4-GW 2.4-GW5, there are no pathways to any offsite drinking water supplies.

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.

The consequences of these measurements have been used to determine releases listed in Section 2.2 and the dose calculations listed in Section 1.0.

61

Table 2.4-GWl Environmental Well Monitoring Results Laboratory Analysis Location WellIID March-10 June-10 Sept.-10 Dec.-10 MW-9B TI - Unit I Tank Farm MW-9D Ti-MW-I T5 - Abandoned Heating Oil UST -

T5-MW-1 Building 512 T5-MW-2 T7-MW-1 T7 - Former Stone & Webster USTs T7-MW-2 T7-MW-3 S 1-Unit 1 Transformer Switchyard S1-MW-i MW-7C S2 - Unit 2 Transformer Switchyard

_MW-7D S2-MW-i ME-9 S5 - Former Batch Plant S5-MW-1 MW-I 1 -F u l n S t t o..

S I-MW-2*

S13-MW-1 S13 - Recycling Area Waste Oil AST Si3-MW-2 MW-6B M2 - Settling Pond ME-2 M5-MW-7 M5-MW-8 M5 - Excavation Pile M5-MW-9S M5-MW-9D

• sampled, gamma and H-3 (tritium) were LLD (Wells are typically sampled for chemical pollutants; they are also analyzed for radioactivity.)

62

Table 2.4-GW2 Catch Basin/Underdrain Monitoring Results Type Location Identification Frequency Results Yard Drains Catch Basin 1-3 CB 1-3 Monthly Gamma and H-3 < LLD Catch Basin 1-5 GB 1-5 Monthly Gamma and H-3 < LLD Catch Basin 1-7 CB 1-7 Monthly Gamma and H-3 < LLD Catch Basin 1-13 CB 1-13 Monthly Gamma and H-3 < LLD Catch Basin 1-14 CB 1-14 Monthly Gamma and H-3 < LLD Catch Basin 1-22 GB 1-22 Monthly Gamma and H-3 < LLD Catch Basin 2-9 CB 2-9 Monthly Gamma and H-3 < LLD Gamma < LLD and, NPDES Discharge DSN 006 Monthly occasionally H-3 at -2000 pCi/liter

• ROB Yard Drain Monthly Gamma and H-3 < LLD ISFSI Yard Drain DMH#1 I Monthly Gamma and H-3 < LLD Sumps Unit 3 Containment Underdrains Weekly Gamma and H-3 < LLD Unit 3 Foundation Underdrains**

3 SRW Sump 2 Quarterly***

See next page 3 SRW Sump 3 Quarterly***

See next page

• Turbine building sumps are discharged via DSN-006. These sumps normally have detectable H-3 (tritium),

which is monitored and reported in the effluent section of this report. Unit 3 Foundation Underdrains (3SRW sumps 2 & 3) are also discharged via DSN-006

• • New locations added in 2007. See Table 2.3 - L7 for the effluent release results for these locations.

• • • Minimum frequency 63

Table 2.4-GW3 Foundation Drains Monitoring Results Sump 2 Sump3 Tritium Tritium Tritium Date (pCi/liter)

Date (pCi/liter)

Date (pCi/liter) 1/1/10

<1730 1/1/10 2,240 8/23/10 4,930 2/23/10 3590 2/24/10

<1730 8/28/10 7,870 2/23/10 3300 2/25/10

<1730 9/1/10 7,070 2/24/10 3600 3/4/10 1,840 9/4/10 4,050 2/25/10 3440 3/9/10 2,820 9/7/10 7,210 2/26/010 5780 3/9/10 2,410 9/8/10 6,520 2/27/10 5720 3/11/10 2,660 9/11/10 5,580 2/28/10 4680 3/16/10 2,310 9/13/10 6,280 3/1/10 3790 4/5/10 2,340 9/21/10 7,930 3/2/10 5720 4/8/10 2,600 9/22/10 6,510 3/2/10 8700 5/10/10

<1730 9/25/10 5,710 3/3/10 14200 5/11/10

<1730 9/27/10 3,770 3/4/10 21900 6/7/10 3,500 9/28/10 5,650 3/5/10 25700 6/10/10 3,040 9/29/10 4,040 3/6/10 26500 7/1/10 5,290 9/30/10 5,190 3/7/10 26700 7/14/10 9,100 10/4/10 5,520 3/8/10 25300 7/16/10 9,830 10/6/10 5,490 3/9/10 26400 7/21/10 10,300 10/12/10 5,560 3/10/10 23400 7/22/10 6,150 10/14/10 4,950 3/11/10 23200 7/23/10 7,030 10/18/10 4,990 3/12/10 22400 7/24/10 10,600 10/20/10 4,900 3/13/10 20800 7/25/10 10,800 10/23/10 4,960 3/14/10 20400 7/27/10 9,120 10/26/10 4,610 3/15/10 14900 7/28/10 12,500 10/30/10 4,080 3/16/10 16000 7/29/10 13,100 11/1/10 5,060 3/17/10 11000 7/30/10 10,300 11/2/10 3,730 3/18/10 7580 7/31/10 10,000 11/6/10 4,610 3/19/10 5810 8/1/10 10,600 11/9/10 5,240 3/20/10 4220 8/3/10 9,120 11/13/10 4,710 3/21/10 3710 8/4/10 11,000 11/15/10 4,620 3/22/10 3850 8/6/10 9,710 11/18/10 3,690 3/23/10 3300 8/7/10 14,000 11/20/10 5,280 3/24/10 3460 8/8/10 9,920 11/22/10 4,810 3/29/10

<1730 8/10/10 8,370 11/29/10 4,450 4/1/10

<1730 8/11/10 8,600 12/1/10 4,090 4/5/10

<1730 8/12/10 8,680 12/7/10 3,660 5/12/10

<1730 8/13/10 8,760 12/14/10 4,780 6/7/10 1910 8/14/10 7,800 12/21/10 3,090 6/10/10

<1730 8/16/10 10,500 6/10/10

<1780 8/17/10 6,730 7/1/10

<1730 8/18/10 7,520 7/19/10

<1730 8/19/10 5,970 12/9/10

<1730 8/20/10 7,260 12/13/10

<1730 8/21/10 6,470 64

Table 2.4-GW4 Manhole and WTT Berm Results Manhole D4 WTT Berm

....r-iti u m........

T r t u.*

G m a Tritium Tritium Gamma*

Date (pCi/L)

Date I

(pCi/L)

(pCi/L) 2/25/10 1 15600 2/23/10 1050000 43 2/26/10 1 21600 2/23/10 1740000 2/27/10 20800 2/24/10 18700 2/28/10 15400 2/25/10 120000 29.3 3/1/10 12000 2/26/10 33700 3/2/10 28500 2/27/10 46100 21.7 3/3/10 68700 2/28/10 52600 3/4/10 106000 3/1/10 952000 158 3/5/10 1 113000 3/1/10 103 3/6/10 7121000 3/2/10 909000 3/7/10 T 110000 3/3/10 848000 3/8/10 102000 3/4/10 158000 58.5 3/9/10 99600 3/5/10 150000 68.9 3/10/10 96600 3/7/10 209000 161 3/11/10 90600 3/8/10 191000 104.3 3/12/10 183300 3/9/10 169000 107.0 3/13/10 76300 3/10/10 165000 74.1 3/14/10 70300 3/11/10 159000 96.4 3/15/10 66900 3/12/10 142000 89.8 3/16/10 54700 3/13/10 97900 72.3 3/17/10 39900 3/14/10 15900 3/18/10 25100 3/15/10 8300 3/19/10 13900 3/17/10 26900 3/20/10 13300 3/23/10 5500 3/21/10 10300 7/1/10 4150 3/22/10 10500 8/18/10

<1.73E-6 3/23/10 11600 9/3/10

<1.73E-6 3/24/10 12200 9/17/10

<1.73E-6 3/29/10 3280 9/29/10

<1.73E-6 4/1/10 1 2290 10/6/10

<1.73E-6 4/5/10 2160 10/17/10

<1.73E-6 5/12/10

<1730

.i i........

1 2590 wasSb-25 notepln lad uiesdnifd

• Gamma activity was Sb-125; no other plant related nuclides identified.

65

Table 2.4-GW5 Special Well Samples Tritium Tritium Name Date (pCiIL)

Name Date (pCilL)

MW-6A 3/16/10

<1,780 DP-003A 7/26/10 10,300 MW-6A 9/15/10

<1,730 DP-003A 8/23/10 12,100 MW-6B 3/16/10

<1,780 DP-003A 9/2/10 10,500 MW-6B 9/15/10

<1,730 DP-003A 10/21/10 3,350 MW-7A 7/27/10

<1,730 DP-004A 7/26/10 2,900 MW-7A 7/27/10

<1,730 DP-004A 9/2/10 2,480 MW-7A 11/9/10

<1,780 DP-004A 10/21/10 2,710 MW-7B (Note 1) 7/27/10

<1,730 DP-007 7/28/10 2,180 MW-7C 7/27/10

<1,730 DP-007 10/21/10 4,920 MW-7C 7/27/10

<1,730 MW-GPI-1 9/15/10

<1,780 MW-7C 11/9/10 2,680 MW-GPI-2 8/5/10

<1,780 MW-7C (Note 2) 11/9/10 2,740 MW-GPI-2 9/15/10

<1,780 MW-7C 11/15/10

<1,730 MW-GPI-3 9/15/10

<1,780 MW-7D 7/27/10

<1,730 MW-GPI-4 9/20/10

<1,780 MW-7D 11/9/10

<1,780 MW-GPI-5 8/5/10

<1,730 S2-MW-1 9/20/10

<1,780 MW-GPI-5 9/2/10 1,900 S12-MW-1 8/5/10

<1,780 MW-GPI-5 9/8/10

<1,730 S12-MW-2 8/5/10

<1,780 MW-GPI-5 9/16/10

<1,730 S13-MW-1 3/16/10

<1,780 MW-GPI-5 9/22/10

<1,730 S13-MW-2 3/16/10

<1,780 MW-GPI-5 10/21/10

<1,730 DP-001B (Note 2) 7/26/10 5,420 MW-GPI-6 2/24/10

<1,730 DP-002A 7/26/10 5,890 MW-GPI-6 9/2/10

<1,730 DP-002A 9/2/10 6,030 MW-GPI-8 9/20/10

<1,780 DP-002A 10/21/10 5,250 M3-MW-1 9/15/10

<1,780 1MW-XFMR-03 9/20/10

<1,780 Notes:

1. Well dry on 11/9/10

2. Filtered sample

3. No longer in service 66

3.0 Inoperable Effluent Monitors During the period January 1 through December 31, 2010, the following effluent monitors were inoperable for more than 30 consecutive days:

3.1 Unit 1 - None 3.2 Unit 2 - CPF liquid radwaste flow rate measurement instrument (FR-246)

On November 18, 2010 at 11:45 the flow rate measurement instrument was declared inoperable because the CPF Flow Recorder was not responding during discharge. Although repairs to FR-246 were completed on 12/15/2010 under Work Order 53102395259, the flow recorder could not be declared operable until a successful retest of the recorder. The post maintenance testing required that a channel check be done during an actual CPF discharge. The next CPF discharge did not occur until 12/22/2010 which started at 10:34 and ended at 13:13. Based on data from the actual discharge on 12/22/2010, the retest requirement was met and FR-246 was declared operable at 16:00 on 12/22/2010. Best efforts were made to restore the flow rate instrument within 30 days, but the instrument could not be declared operable until an actual CPF discharge was performed. The actual discharge occurred 4 days after the 30 day window.

Unit 2 - Waste Gas noble gas radiation monitor On August 3, 2010 at 12:29 Radiation Monitor RM-9095 was taken out of service to perform a modification to the detector assembly. During the modification there was a problem discovered with the extender module which delayed the work for over a week. Subsequently, the qualified I&C technician was utilized to perform higher priority work. After completion of the modification, the radiation monitor could not be declared operable until a discharge was performed to verify the relationship between the sampled activity and the indicated activity.

This was accomplished and the radiation monitor was restored to operability on September 8, 2010.

3.3 Unit 3 - None 67

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 96.4% and Unit 3 operated with a capacity factor of 87.5%

The power histograms for 2010 are on the following pages.

68

Millstone Power Station Unit 2 - Cycle 20 Power History Year 2010 12 3

4 S6 100 80 60 cosR o

TRVEIN SCRENDPWIH THVCW AP O

2*. DO OE O

REMOV YCODNE WTRO 60

3. DOWN POWER O0RMVEso.

TH FCNENER WAERBO.

VALVE P(SITIONER AND CONDUCT TRINE VALVE TESIN

7. UNIT REOVEFOM SEVIE I 19110)TOREPAIR 20 W CWPP SHUT DOMWTH S'HCWP OFCO BACKF.LUSOR 0

78 9

69

21 Millstone Power Station Unit 3 Cycle 14 Power History - 2010 002 3

4 5

90 1.,CONTINUATION OF FORCED OUT4 80 -

TRIP (12/19) FROM 100% POWER 3R 13 MAIN GENERATOR GROUND FAULT

2. SHUTDOWN-R13 REFUELING OU 70 (4/10) 3.AUTOMATICRXTRIP (5/17) DUE1 60 LO SG LEVEL 4, UNITTAKEN OFF-UNE(FORCED O0 50 8/14TO REPAIRRCS LEAK IN CTIT

5. DOWN POWERTO 93% (9/18/10)'

REMOVETHE'B' HEATER DRAIN PUIh SERVICETO REPLACELEAKING VALV V3T7 30

~6.DOWN POWERTO 93% (12/3/10) 6 20 -

10 0 -

70 a

U 5.0 Errata None 6.0 REMODCM Changes In 2010, there were no revisions made to the Millstone Power Station REMODCM.

71