ML051260097

Attachment 1, Millstone, Units 1 2, and 3 - 2004 Radioactive Effluent Release Report, Volume I

ML051260097
Person / Time
Site:	Millstone, 05000203
Issue date:	04/30/2005
From:	Dominion Nuclear Connecticut
To:	Document Control Desk, NRC/FSME
References
Download: ML051260097 (98)

Text

Serial No.05-203 Docket Nos. 50-245 50-336 50-423 License Nos. DPR-21 DPR-65 NPF-49 Attachment 1 2004 Radioactive Effluent Release Report Volume I Millstone Power Station Units 1, 2, and 3 Dominion Nuclear Connecticut, Inc. (DNC)

Millstone Power Station 2004 Radioactive Effluent Release Report Volume I Dominion Nuclear Connecticut, Inc.

MILLSTONE UNIT LICENSE DOCKET 1 DPR-21 50-245 2 DPR-65 50-336 0Dominion 3 NPF49 50-423

Table of Contents Volume I List of Tables References Introduction Operating History 1.0 Doses 1.1 Dose Calculations 1.2 Dose Results 2.0 Radioactivity 2.1 Airborne Effluents 2.2 Liquid Effluents 2.3 Solid Waste 3.0 REMODCM Changes 4.0 Inoperable Effluent Monitors > 30 days 5.0 Errata Volume 11 2004 REMODCM Revision 24 -01

List of Tables Table 1-1 Off-Site Dose Summary from Airborne Effluents - Units 1,2,3 Table 1-2 Off-Site Dose Summary from Liquid Effluents - Units 1,2,3 Table 1-3 Off-Site Dose Comparison to Limits - Units 1,2,3 Table 1-4 Off-Site Dose Comparison - Units 1,2,3 Table 2.1-Al Unit I Airborne Effluents - Release Summary Table 2.1-A2 Unit 1 Airborne Effluents - Elevated Continuous Table 2.1-A3 Unit 1 Airborne Effluents - Ground Continuous - Balance of Plant Vent

& Spent Fuel Pool Island Vent Table 2.1-L1 Unit 1 Liquid Effluents - Release Summary Table 2.1-L2 Unit I Liquid Effluents - Batch Table 2.2-Al Unit 2 Airborne Effluents - Release Summary Table 2.2-A2 Unit 2 Airborne Effluents - Mixed Continuous - Aux Bldg Vent, SGBD Tank Vent

& Spent Fuel Pool Evaporation Table 2.2-A3 Unit 2 Airborne Effluents - Mixed Batch - Containment Purges Table 2.2-A4 Unit 2 Airborne Effluents - Elevated Batch - WGDT Table 2.2-A5 Unit 2 Airborne Effluents - Elevated Continuous - Containment Vents/Site stack Table 2.2-A6 Unit 2 Airborne Effluents - Ground Batch - Containment Equipment Hatch Table 2.2-A7 Unit 2 Airborne Effluents - Ground Batch - RWST Vent Table 2.2-L1 Unit 2 Liquid Effluents - Release Summary - Quarry Table 2.2-L2 Unit 2 Liquid Effluents - Continuous - SGBD Table 2.2-L3 Unit 2 Liquid Effluents - Batch - LWS Table 2.2-L4 Unit 2 Liquid Effluents - Continuous - Turbine Building Sump - Yard Drain DSN 006 Table 2.3-Al Unit 3 Airborne Effluents - Release Summary Table 2.3-A2 Unit 3 Airborne Effluents - Mixed Continuous - Vent & Spent Fuel Pool Evaporation Table 2.3-A3 Unit 3 Airborne Effluents - Ground Continuous - ESF Building Ventilation Table 2.3-A4 Unit 3 Airborne Effluents - Mixed Batch - Containment Drawdowns Table 2.3-A5 Unit 3 Airborne Effluents - Mixed Batch - Containment Purges Table 2.3-A6 Unit 3 Airborne Effluents - Elevated Continuous - Gaseous Waste System & Containment Vents Table 2.3-A7 Unit 3 Airborne Effluents - Ground Batch - Containment Equipment Hatch Table 2.3-A8 Unit 3 Airborne Effluents - Ground Batch- RWST Vent Table 2.3-L1 Unit 3 Liquid Effluents - Release Summary - Quarry Table 2.3-L2 Unit 3 Uquid Effluents - Continuous - SGBD, SW & TK2 Table 2.3-L3 Unit 3 Liquid Effluents - Batch - LWS Table 2.3-L4 Unit 3 Liquid Effluents - Batch - CPF Waste Neutralization Sumps & Hotwell Discharge Table 2.3-L5 Unit 3 Liquid Effluents - Release Summary - Yard Drain DSN 006 Table 2.3-L6 Unit 3 Liquid Effluents - Continuous - Turbine Building Sump Table 2.3-L7 Unit 3 Liquid Effluents - Continuous - WTT Berm Water Table 2.1-S Unit 1 Solid Waste & Irradiated Component Shipments Table 2.2-S Unit 2 Solid Waste & Irradiated Component Shipments Table 2.3-S Unit 3 Solid Waste & Irradiated Component Shipments

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. Intentionally left blank

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. Intentionally left blank

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, ORNUNUREG/TDMC-1 User's Manual for LADTAP II - A Computer Program for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liqiuid 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 Ener r, Part 50 Domestic Licensing of Production and Utilization Facilities, Appendix I Numerical Guides for Design Obiectives 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 Environmental Protection Agency, Part 190 Environmental Radiation Protection Standard for Nuclear Power Operation.

9. Memo No. MP-HPO-05-016, 2004 Report on Solid Waste and Irradiated Component Shipments, March 18, 2005.

10. DOSLIQ-Dose Excel Code for Liquid EffluentsSoftware Document File, Rev 1, February 2002

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

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

Introduction This report, for the period of January through December of 2004, is being submitted by Dominion Nuclear Connecticut, Inc. for Millstone Power Station's 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 I contains radiological and volumetric information on airborne and liquid effluents and 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 any corrections to previous reports. Volume II contains a full copy of each of the complete revisions to the REMODCM effective during the calendar year.

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

The annual capacity factor for Unit 1 was 0.0%. Unit 1 was shut down November 11, 1995 with a cessation of operation declared in July 1998.

The annual capacity factor for Unit 2 was 97.6% based on Design Electrical Rating (DER).

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1.0 Doses This report provides a summary of the 2004 off-site radiation doses for releases of radioactive materials in airborne and liquid effluents from Millstone 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 with the regulatory limits and with the annual average dose a member of the public could receive from natural background and other sources.

1.1 Dose Calculations The off-site dose to humans from radioactive airborne and liquid effluents have been calculated using measured radioactive effluent data, measured meteorological data, and dose computer models DOSAIR and DOSLIQ, which were developed by Millstone. 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.

1.1.1 Maximum Individual Dose The 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 due to inhalation and ingestion, taking into account radioactive decay and biological elimination of the radioactive materials.

Maximum Individual dose is defined as the dose to the individual within the 50 mile population 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 these three types of input: radioactive source term, site-specific data, and generic factors. The radioactive source terms (Curies) are characterized in the Radioactivity section of this report. The site specific data includes:

meteorological data (e.g. wind speed, direction, 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.

1.1.1.1 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 (X/Q) and average relative deposition (D/Q) used in the DOSAIR code were generated using EDAN 3, a meteorological computer code which implements the assumptions cited in NRC Regulatory Guide 1.111 (Reference 5), Section C. The annual summary of hourly meteorological data (in 15-minute increments), which includes wind speed, direction, atmospheric stability, and joint frequency distribution, is not provided in the report but can be retrieved from computer storage.

Millstone Stack (375 ft) releases are normally considered elevated 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 for elevated releases from the Millstone Stack prior to touchdown. All three units had the ability to discharge effluents to the Millstone Stack, however, in March 2001, Unit 1 was separated from releasing to the stack and modifications were made to add two new release points, the Spent Fuel Pool Island Vent (SFPI) and the Balance of Plant Vent (BOP).

Unit 1 Spent Fuel Pool Island Vent (73 ft) and the Balance of Plant Vent (80 ft) releases are considered ground level and DOSAIR was used to calculate doses using 33 ft meteorology. Continuous ventilation of the spent fuel pool island and evaporation from the spent fuel pool water (H-3) release to 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.

Each of these doses were summed to determine the total Unit 1 airborne effluent dose.

Unit 2 Vent (159 ft) releases are considered mixed mode (partially elevated and partially ground) releases; and, Pasquill stability classes are determined based upon the temperature gradient between the 33 ft and 142 ft meteorological tower levels.

DOSAIR was used to calculate doses for Unit 2 mixed mode continuous releases (Auxiliary Building Ventilation and the Steam Generator Blowdown Tank flashed gases) and mixed mode batch releases (Containment Purge) through the Unit 2 Vent, and elevated batch releases (Waste Gas Decay Tanks and Containment Vents) through the Millstone Stack. The doses for these elevated batches were conservatively calculated using mixed mode 142 ft meteorology. Each of these doses were summed to determine the total Unit 2 airborne effluent dose. The Containment Equipment Hatch and the RWST Tank Vent releases are considered ground level and DOSAIR was used to calculate doses using 33 ft meteorology.

Unit 3 (142.5 ft) Vent releases are considered mixed mode (partially elevated and partially ground) releases; and, Pasquill stability classes are determined based upon the temperature gradient between the 33 ft and 142 ft meteorological tower levels.

DOSAIR was used to calculate doses for Unit 3 mixed mode continuous releases through the Unit 3 Vent (Auxiliary Building Ventilation), mixed mode batch releases (Containment Purge) through the Unit 3 Vent, and "initial' Containment Drawdown through the roof of the Auxiliary Building. Gaseous waste and containment drawdowns are released through the Unit 3 SLCRS system to the Millstone Stack (375 ft). The doses for these elevated releases were conservatively calculated using mixed mode 142 ft meteorology. In addition, the Engineered Safety Features Building (ESF) Vent releases are considered ground level and doses are calculated using 33 ft meteorology Each of these doses were summed to determine the total Unit 3 airborne effluent dose.

1.1.1.2 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).

1.1.2 Gamma and Beta Air Doses Maximum gamma and beta air doses from the release of noble gases are calculated using DOSAIR.

1.2 Dose Results 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 the plume and from ground deposition, inhalation, and ingestion of vegetation, cow and 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 except for the case when only tritium is released in which the maximum individual dose is calculated at the vegetable garden with the highest XIQ. 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.

For the 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).

The air dose includes only the dose from noble gases in the plume.

The off-site doses from airborne effluents are presented in Table 1-1. These are the calculated maximum off-site doses.

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).

The off-site doses from liquid effluents are presented in Table 1-2. These are the calculated maximum off-site doses.

1.2.3 Analysis of Results Table 1-3 provides a quantitative dose comparison with limits specified in the REMODCM.

The data indicates that the total whole body and organ doses to the maximum offsite individual from Millstone Station including all sources of the fuel cycle are well within the limits of 40CFR190 (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 0.14 mrem/yr. The doses from airborne and liquid effluents were added to the estimated dose from on-site radioactive waste storage to show compliance with 40CFR190.

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

Table 1-1 2004 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+0O Max Individual (mrem) (mrem) (mrem) (mrem) (mrem)

Whole Body 7.59E-04 3.41 E-04 6.76E-04 6.40E-04 2.42E-03 Skin 8.68E-04 3.41 E-04 6.87E-04 7.39E-04 2.64E-03 Thyroid 7.58E-04 3.41 E-04 6.35E-04 6.38E-04 2.37E-03 Max organ+ 7.75E-04 3.41 E-04 9.13E-04 6.42E-04 2.67E-03 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Total Max Air (mrad) (mrad) (mrad) (mrad) (mrad)

Beta 3.07E-04 1.28E-04 1.36E-03 1.33E-03 3.12E-03 Gamma 2.10E-04 1.18E-04 1.12E-04 1.38E-04 5.78E-04 Max Individual (mrem) (mrem) (mrem) (mrem) (mrem)

Whole Body 3.81 E-04 7.03E-04 5.94E-04 2.61 E-04 1.94E-03 Skin 5.89E-04 7.53E-04 1.27E-03 1.19E-03 3.81 E-03 Thyroid 8.51 E-04 8.31 E-03 9.09E-04 2.72E-03 1.28E-02 Max organ+ 3.84E-04 7.45E-04 6.03E-04 2.77E-04 2.01 E-03 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Total Max Air (mrad) (mrad) (mrad) (mrad) (mrad)

Beta 1.44E-04 1.40E-05 7.06E-06 4.52E-06 1.70E-04 Gamma 3.75E-05 1.85E-05 1.80E-05 1.20E-05 8.59E-05 Max Individual (mrem) (mrem) (mrem) (mrem) (mrem)

Whole Body 4.67E-04 9.99E-03 9.29E-03 2.04E-03 2.18E-02 Skin 5.42E-04 1.01E-02 9.29E-03 2.1OE-03 2.20E-02 Thyroid 4.67E-04 9.95E-03 9.29E-03 2.04E-03 2.17E-02 Max organ+ 4.68E-04 1.03E-02 9.302-03 2.04E-03 2.21 E-02

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

Table 1-2 2004 Off-Site Dose Commitments from Liquid Effluents Millstone Units 1, 2, 3 1st Quarter I 2nd Quarter I 3rd Quarter I 4th Quarter I Annual Total Max Individual (mrem) (mrem) (mrem) (mrem) (mrem)

Whole Body O.OOE+OO 3.39E-06 1.62E-06 4.12E-07 5.42E-06 Thyroid O.OOE+OO 1.48E-06 7.08E-07 1.41 E-07 2.33E-06 Max Organ O.OOE+OO 4.40E-06 2.10E-06 5.65E-07 7.07E-06 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Total Max Individual (mrem) (mrem) (mrem) (mrem) (mrem)

Whole Body 4.17E-05 6.73E-05 4.05E-05 8.1OE-05 2.30E-04 Thyroid 1.81 E-05 3.75E-05 1.85E-05 5.19E-05 1.26E-04 Max Organ 1.19E-04 1.91 E-04 1.59E-04 2.14E-04 6.83E-04 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Total Max Individual (mrem) (mrem) (mrem) (mrem) (mrem)

Body 4.82E-04 7.44E-04 1.75E-04 1.12E-04 1.51 E-03 Thyroid 3.72E-04 2.51 E-04 2.81 E-05 3.74E-05 6.89E-04 Max Organ 6.93E-04 2.52E-03 8.65E-04 5.12E-04 4.59E-03

Table 1-3 2004 Off-Site Dose Comparison to Limits Millstone Units 1, 2, 3 Airborne Effluents Max Individual Dose vs REMODCM Limits Whole Body Thyroid Max Organ Skin Beta Air Gamma Air (mrem) (mrem) (mrem) (mrem) (mrad) (mrad)

Unit I 2.42E-03 2.37E-03 2.67E-03 2.64E-03 O.OOE+00 O.OOE+00 Unit 2 1.94E-03 1.28E-02 2.01 E-03 3.81 E-03 3.12E-03 5.78E-04 Unit 3 2.18E-02 2.17E-02 2.21E-02 2.20E-02 1.70E-04 8.59E-05 Millstone Station 2.61 E-02 3.69E-02 2.68E-02 2.84E-02 3.29E-03 6.64E-04 A #'n--_

Liquid Effluents Max Individual Dose vs REMODCM Limits Whole Body Thyroid Max Organ (mrem) (mrem) (mrem)

Unit 1 5.42E-06 2.33E-06 7.07E-06 Unit 2 2.30E-04 1.26E-04 6.83E-04 Unit 3 1.51 E-03 6.89E-04 4.59E-03 Millstone Station 1.75E-03 8.17E-04 5.28E-03

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Millstone Station Max Individual Dose vs 40CFRI90 Limits Whole Body Thyroid Max Organ (mrem) (mrem) (mrem)

Airborne Effluents 2.61 E-02 3.69E-02 2.68E-02 Liquid Effluents 1.75E-03 8.17E-04 5.28E-03 Radwaste Storage 1.40E-01 1.40E-01 1.40E-01 Millstone Station 1.68E-01 1.78E-01 1.72E-01

• 10CFR50. Appendix I Guidelines Maximum of the following organs (not Including Thyroid): Bone. GI-LLI. Kidney. Liver. Lung

Table 1-4 2004 Offsite Dose Comparison Natural Background vs. Millstone Station Average Resident Natural Background Radiation Dose (NCRP 94)

Cosmic 27 mrem Cosmogenic 1 mrem Terrestial (Atlantic and Gulf Coastal Plain) 16 mrem Inhaled 200 mrem In the Body 40 mrem I. . - 284 mrem l Maximum Offsite Individual Millstone Station Whole Body Dose Airborne Effluents 0.0261 mrem Liqud Effluents 0.0017 mrem On site RadWaste Storage 0.1400 mrem 0.17 mrem

2.0 Radioactivity 2.1 Airborne Effluents 2.1.1 Measurement of Radioactivity 2.1.1.1 Millstone Stack The MP2 Wide Range Gas Monitor (WRGM) and MP3 Secondary Leak Collection and Recovery System (SLCRS) continuously monitor the effluent activity concentration and flow rate to the Millstone Stack. Monthly gaseous grab samples are taken and analyzed for isotopic content. The isotopic concentrations at the release point are multiplied by the total flow to the stack to obtain the total activity released for each isotope.

The gas washing bottle method accomplishes tritium collection. The sample is counted on a liquid scintillation detector. Concentration is multiplied by volume to get the total activity released.

Charcoal cartridges and particulate filters are used to collect iodines and particulates, respectively. These filters are then analyzed for isotopic content using a gamma spectrometer. Particulate filters are also analyzed for Sr-89, Sr-90 and gross alpha.

Isotopic concentrations are multiplied by the release flow rate and sampling time to determine the total amount of activity released.

2.1.1.2 Unit 1 Spent Fuel Pool Island (SFPI) Vent The SFPI monitor continuously records the effluent activity concentration and flow rate. Monthly gaseous grab samples are taken and analyzed for isotopic content.

The isotopic concentrations at the release point are multiplied by the total flow to the stack to obtain the total activity released for each isotope.

The gas washing bottle method accomplishes tritium collection. The sample is counted on a liquid scintillation detector. Concentration is multiplied by volume to get the total activity released.

Particulate filters are used to collect particulates. These filters are then analyzed for isotopic content using a gamma spectrometer. Particulate filters are also analyzed for Sr-90 and gross alpha. Isotopic concentrations are multiplied by the release flow rate and sampling time to determine the total amount of activity released.

2.1.1.3 Unit 1 Balance of Plant (BOP) Vent The BOP monitor continuously records the effluent activity concentration and flow rate. Monthly gaseous grab samples are taken and analyzed for isotopic content.

The isotopic concentrations at the release point are multiplied by the total flow to the stack to obtain the total activity released for each isotope.

The gas washing bottle method accomplishes tritium collection. Prior to processing each batch from the Reactor Building Evaporator a sample is collected and counted on a liquid scintillation detector. Concentration is multiplied by volume to get the total activity released.

Particulate filters are used to collect particulates. These filters are then analyzed for isotopic content using a gamma spectrometer. Particulate filters are also analyzed for Sr-90 and gross alpha. Isotopic concentrations are multiplied by the release flow rate and sampling time to determine the total amount of activity released.

2.1.1.4 Unit 2 Vent Effluent volume from the Unit 2 vent is multiplied by the isotopic concentrations as measured by gamma spectrometer HPGe analysis for gases and liquid scintillation analysis for tritium to obtain the total activity released from the vent. The gas washing bottle method accomplishes tritium collection.

Since a major source of tritium is evaporation of water from the spent fuel pool, tritium releases were also estimated based upon amount of water lost and measured concentrations of the pool water. When the grab samples from the Unit 2 Vent are less than detectable, the measured evaporation technique is used to determine the amount of tritium released. If the grab samples from the Unit 2 Vent are detectable, the higher amount from either the vent or from the measured evaporation technique is used to determine the amount of tritium released.

Charcoal cartridges and particulate filters are used to collect iodines and particulates, respectively. These filters are then analyzed for isotopic content using a gamma spectrometer. Particulate filters are also analyzed for Sr-89, Sr-90 and gross alpha.

Isotopic concentrations are multiplied by the release flow rate and sampling time to determine the total amount of activity released.

2.1.1.5 Unit 2 Containment Purges / Vents A purge is the process of discharging air from containment to maintain temperature, humidity, pressure, concentration, etc., where air is replaced. Purges are considered batch releases and are filtered by HEPA and normally released through the Unit 2 vent. If necessary, the purge may be filtered by charcoal in the EBFS system and discharged to the Millstone Stack.

Gaseous grab samples are taken and are analyzed on a HPGe gamma spectrometer for noble gas and liquid scintillation detector for tritium. Computed concentrations are then multiplied by the calculated purge volume to obtain the total activity released. The gas washing bottle method accomplishes tritium collection.

A vent is the process of discharging air from containment usually once per week to maintain temperature, humidity, pressure, concentration without supplying replacement air. Weekly gaseous grab samples are taken and are analyzed on a HPGe gamma spectrometer for noble gas and liquid scintillation detector for tritium.

Computed concentrations are then multiplied by the calculated containment vent volume to obtain the total activity released. The gas washing bottle method accomplishes tritium collection.

2.1.1.6 Unit 2 Waste Gas Decay Tanks Waste Gases from the Gaseous Waste Processing System are held for decay in waste gas decay tanks (6) prior to discharge through the Unit 1 Stack. Calculated volume discharged is multiplied by the isotopic concentrations from the analysis of grab samples to determine the total activity released.

2.1.1.7 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.

2.1.1.8 Unit 2 Radwaste Storage Tank (RWST) Vent When reactor water is transferred to radwaste storage tank there is a potential for a release of radioactivity out the tank vent. A decontamination factor (DF) of 100 is applied to the total iodine transferred from the RCS to the RWST water to estimate the iodine released. All noble gases are assumed to be released through the tank vent.

2.1.1.9 Unit 2 Containment Equipment Hatch Opening Samples of air near the opening are analyzed for particulates, iodines, during refueling outages for the period that the equipment hatch is open. An estimated flow out of the hatch together with the sample results are used to determine the radioactivity released. These samples of air near the opening are analyzed for particulates, and iodines, during refueling outages for the period that the equipment hatch is open.

2.1.1.10 Unit 3 Vent and ESF Building Vent Effluent volume from the Unit 3 ventilation vent is multiplied by the isotopic concentrations as measured by gamma spectrometer HPGe analysis for gases and liquid scintillation analysis for tritium to obtain the total activity released from the vent.

The gas washing bottle method accomplishes tritium collection.

Since a major source of tritium is evaporation of water from the spent fuel pool, tritium releases were also estimated based upon amount of water lost and measured concentrations of the pool water. When the grab samples from the Unit 3 Vent are less than detectable, the measured evaporation technique is used to determine the amount of tritium released. If the grab samples from the Unit 3 Vent are detectable, the higher amount from either the vent or from the measured evaporation technique is used to determine the amount of tritium released.

The Unit 3 Engineered Safety Features (ESF) building vent collects gas streams from the ESF building ventilation system.

Total effluent volume is multiplied by isotopic concentrations from the analysis of grab samples and composites to obtain the total activity released. These samples are obtained monthly for fission gases, weekly composites of filters for iodines and particulates, monthly composites of particulate filters for gross alpha and strontium.

2.1.1.11 Unit 3 Containment Drawdown and Purge Unit 3 containment is initially drawn down prior to startup and purged typically during outages. The initial drawdown is accomplished by using the containment vacuum steam jet ejector and releases through an unmonitored vent on the roof of the auxiliary building. The containment vacuum pump discharge, which maintains subatmospheric pressure following initial drawdown, is released through the Millstone Stack.

The purge is the process of discharging air from containment to maintain temperature, humidity, pressure, concentration, etc., where air is replaced. Purges are normally released through the Unit 3 Vent. Intermittent purges and drawdowns are considered continuous releases since they occur usually 1 or 2 times a week.

For initial drawdowns and purges, the calculated volume discharged is multiplied by isotopic concentrations from the analysis of grab samples to obtain total activity released. These are considered as batch releases.

2.1.1.12 Unit 3 Radwaste Storage Tank (RWST) Vent When reactor water is transferred to radwaste storage tank there is a potential for a release of radioactivity out the tank vent. A decontamination factor (DF) of 100 is applied to the total iodine transferred from the RCS to the RWST water to estimate the iodine released. All noble gases are assumed to be released through the tank vent.

2.1.1.13 Unit 3 Containment Equipment Hatch Opening A ground level release of radioactivity may occur during outages from the containment building through the open equipment hatch. The calculated volume discharged is multiplied by isotopic concentrations from the analysis of grab samples to obtain total activity released. These samples of air near the opening are analyzed for particulates, and iodines, during refueling outages for the period that the equipment hatch is open.

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

Sampling/Data Collection 10% Variation in data collection Sample Line Loss 10% Deposition of some nuclides Calibration 10% Calibration to NBS standards Sample Counting 10% Error for counting statistics Flow & Level Measurements 10% Error for release volumes 2.1.3 Batch Releases - Airborne Effluents Unit I - None Unit 2 Ctmt Purges WGDT Number of Batches 0 13 Total Time (min) 0 4,754 Maximum Time (min) 0 711 Average Time (min) 0 367 Minimum Time (min) 0 88 Unit 3 Ctmt Purges Drawdowns Number of Batches 2 6 Total Time (min) 258 68 Maximum Time (min) 258 68 Average Time (min) 258 68 Minimum Time (min) 258 68 2.1.4 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.

In 2004, the following abnormal airborne releases occurred:

2.1.4.1 Unit I - None 2.1.4.2 Unit 2 - None 2.1.4.3 Unit 3 - None

2.2 Liquid Effluents 2.2.1 Measurement of Radioactivity 2.2.1.1 Liquid TankslSumps There are numerous tanks & sumps that are used to discharge liquids containing radioactivity to the environs; they are:

Unit I Reactor Cavity Water Unit 2 Clean Waste Monitor Tanks (2)

Aerated Waste Monitor Tank 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 for individual radionuclide composition. Isotopic concentrations are multiplied by the volume released to obtain 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.

2.2.1.2 Unit 2 and Unit 3 Steam Generator Blowdown Steam generator blowdown water grab samples are taken and analyzed on the HPGe gamma spectrometer and liquid scintillation detector if required by the conditional action requirements of the REMODCM. Total volume of blowdown is multiplied by the isotopic concentrations (if any) to determine the total activity released via blowdown. 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. Tritium is determined through liquid scintillation counting. Unit 2 is a continuous release while Unit 3 recycles blowdown except for periodic open cycle blowdown.

2.2.1.3 Unit 2 and Unit 3 Continuous Liquid Releases Grab samples are taken for continuous liquid release pathways and analyzed on the HPGe gamma spectrometer and liquid scintillation detector. 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. Tritium is determined through liquid scintillation

counting. Pathways for continuous liquid effluent releases include, Steam Generator Blowdown, Service Water Effluent, and Turbine Building Sump discharge from Units 2&3.

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

Sampling/Data Collection 10% Variation in data collection Calibration 10% Calibration to NBS standards Sample Counting 10% Error for counting statistics Flow & Level Measurements 10% Error for release volumes 2.2.3 Batch Releases - Liquid Effluents Unit I Unit 2 Unit 3 Number of Batches 7 48 380 Total Time (min) 995 4,236 43,841 Maximum Time (min) 157 206 310 Average Time (min) 142 88 115 Minimum Time (min) 109 5 30 Average Stream Flow Not Applicable - Ocean Site 2.2.4 Abnormal Liquid Releases An abnormal release of radioactivity isthe discharge of a volume of liquid radioactive material to the environment that was unplanned or uncontrolled.

In2004, 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

Table 2.1-Al Millstone Unit 1 Airborne Effluents Release Summary I_

I Units I 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Totall A. Fission & Activation Gases

1. Total Activity Ci Released

2. Average Period uCi/sec - _ _

Release Rate B. Iodine-131

1. Total Activity Ci Released

2. Average Period uCi/sec l _

Release Rate C. Particulates

1. Total Activity Ci 1.37E-05 4.25E-06 2.02E-05 3.82E-05 Released

2. Average Period uCilsec 1 .75E-06 5.35E-07 2.54E-06 1.21 E-06 Release Rate D. Gross Alpha

1. Total Activity ci Released Ci I-n = Not Detected

Table 2.1-A2 Millstone Unit I Airborne Effluents Elevated Continuous

<< No Radioactivity Released >>

l Nuclides Released I Units P

• 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr I Total 1 A. Fission & Activation Gases I c i I I - I - -I - I lTotal Activity I Ci I - - -

B. lodines11-131 Ci II lI l I ITotal Activity Ci I C. Particulates11-131 1l C l - I - - I lTotal Activity I Ci - - - I I I D. Gross Alpha lGross Alpha Ci - - - I -

E. Tritium H-3 Deece Ci I

- = Not Detected

Table 2.1-A3 Millstone Unit 1 Airborne Effluents Ground Continuous - Balance of Plant Vent & Spent Fuel Pool Island Vent Nucl ides*

Released I Units l 1st Qtr l 2nd Qtr I 3rd Qtr l 4th Qtr l Total l A. Fission & Activation Gases I ci I - . I - I Total Activity I Ci - - - -

B. lodines11-131 l Cii - - - - - I ITotal Activity Ci - - - -

C. Particulates Co-58 Ci Co-60 Ci 5.83E-06 8.58E-07 6.69E-06 iCs-137 Ci 7.89E-06 4.25E-06 1.93E-05 3.15E-05 Total Activity Ci 1.37E-05 4.25E-06 2.02E-05 3.82E-05 D. Gross Alpha IGross Alpha Ci - - j - I -

E. Tritium IH-3 I Ci 5.07E-01 1.97E-01 2.84E-01 1.88E-01 1.18E+0l

"-" = Not Detected

Table 2.1-LI Millstone Unit No. I Liquid Effluents - Release Summary (Release Point - Quarry)

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

1. Total Activity Ci - 1.95E-04 1.12E-04 3.28E-05 3.40E-04 Released

2. Average Period uCi/ml - 6.31 E-13 2.98E-13 8.84E-14 9.09E-13 Diluted Activity (1)

B. Tritium

1. Total Activity i - 2.01 E+OO 1.17E+00 1.07E-01 3.29E+OO Released

2. Average Period uCi/mi - 6.50E-09 3.10E-09 2.84E-10 8.72E-09 Diluted Activity (1)

C. Dissolved and Entrained Gases

1. Total Activity Ci Released I

2. Average Period uCi/mI _

Diluted Activity l D. Gross Alpha l1. Total Activity lCi Released l l l l l E. Volume _

1. Released Waste Liters 0 1 .04E+06 7.47E+05 1.20E+05 1.91 E+06 Volume

2. Dilution Volume Liters 0 1.86E+09 1.33E+09 2.1 OE+08 3.40E+09 During Releases

3. Dilution Volume Liters 0 0 0 0 0 During Period (2) axo = Not Detected (1)Diluted activity concentration for each batch discharge was a function of available dilution flow from Units 2 and/or 3. Therefore the reported average diluted activity is based on an average of dilution volumes from Unit 2 (see Table 2.2-LI)

(2) Unit I provided no dilution water flow during discharge, however, there was flow from Units 2 and 3 which diluted Unit I discharges prior to release to Long Island Sound.

Table 2.1-L2 Millstone Unit No. 1 Liquid Effluents - Batch (Release Point - Quarry)

Nuclides Released IUnits 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total A. Fission & Activation Products Ag-11Om Ci -

Co-58 Ci - - - _

Co-60 Ci -

Cs-1 37 Ci 1.95E-04 1.1 2E-04 3.28E-05 3.40E-04 Fe-55 Ci Mn-54 Ci Sr-89 Ci Sr-90 Ci Zn-65 Ci Total Activity Ci 1.95E-04 j 1.12E-04 3.28E-05 3.40E-04 B. Tritium H-3 Ci - 2.01E+00 1.17E+00 1.07E-01 3.29E+OO C. Dissolved & Entrained Gases I ci I - I - 1 - I lTotalActivity C ci I - - - - -

D. Gross Alpha lGross Al pha Ci - - - - I

"!' = Not Detected

Table 2.2-Al Millstone Unit No. 2 Airborne Effluents - Release Summary I Units l 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total A. Fission & Activation Gases

1. Total Activity Ci 1.37E+00 1.38E+00 3.35E+00 1.15E+00 7.25E+00 Released

2. Average Period uCi/sec 1 .75E-01 1.76E-01 4.21 E-01 1.44E-01 2.29E-01 Release Rate B. Iodine-131

1. Total Activity Ci 1.1 5E-04 1.06E-04 4.06E-06 1.01 E-04 3.26E-04 Released

2. Average Period uCi/sec 1 .47E-05 1.34E-05 5.11 E-07 1.27E-05 1.03E-05 Release Rate C. Particulates

1. Total Activity Ci 7.25E-07 1.43E-06 1.28E-07 5.89E-07 2.87E-06 Released

2. Average Period uCilsec 9.22E-08 1.81 E-07 1.62E-08 7.40E-08 9.07E-08 Release Rate D. Gross Alpha

1. Total Activity Released1 n-n = Not Detected

Table 2.2-A2 Millstone Unit No. 2 Airborne Effluents - Mixed Continuous - Aux Bldg Vent & SGBD Tank Vent

& Spent Fuel Pool Evaporation Nuclides I Released I Units l st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total I A. Fission & Activation Gases Ar-41 Ci Kr-85 Ci 1.26E+00 1.26E+00 Kr-85m Ci Xe-131m Ci Xe-1 33 Ci 7.45E-01 7.95E-03 7.53E-01 Xe-133m Ci Xe-1 35 Ci 4.98E-01 2.25E-01 7.23E-01 Total Activity Ci I 1.24E+00 1.27E+00 2.25E-01 2.74E+00 B. lodines 1-131 Ci 1.15E-04 1.06E-04 J 4.06E-06 l1.01E-04 3.26E-04 I-132 Ci 5.07E-05 1.41 E-04 1.91 E-04 1-133 Ci 4.14E-04 4.27E-04 1.76E-05 4.90E-04 1.35E-03 1_135 Ci 1.34E-04 1.57E-04 4.54E-04 7.45E-04

,Total Activity Ci 6.62E-04 7.41E-04 2.17E-05 1.19E-03 2.61E-03 C. Particulates 1-131 Ci l - - -

Co-58 Ci Co-60 Ci Sr-89 Ci Sr-90 Ci Cs-137 Ci 6.94E-07 5.79E-07 _ - 1.27E-06 Total Activity Ci 6.94E-07 5.79E-07 1.27E-06 D. Gross Alpha Gross Alpha I Ci -

E. Tritium IH-3 I Ci 2.04E+00 1.09E+00 I9.78E-01 8.25E-01 4.93E+00

"_n = Not Detected

Table 2.2-A3 Millstone Unit No. 2 Airborne Effluents - Mixed Batch - Containment Purges

<< No Radioactivity Released >>

Nuclides Released I Units 1Ist Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total I A. Fission & Activation Gases Ar-41 Ci Kr-85 Ci Kr-85m Ci Xe-131 m Ci .

Xe-133 Ci Xe-1 33m Ci Xe-135 Ci Xe-1 35m Ci Total Activity Ci .

B. lodines, 1-131 Ci 1-132 Ci 1-133 Ci .

Total Activity Ci C. Particulates 1-131 Ci Sr-89 Ci Sr-90 Ci Total Activity Ci D. Gross Alpha lGross Al pha I Ci I -

E. Tritium IH-3 Ci -

"-" = Not Detected

Table 2.2-A4 Millstone Unit No. 2 Airborne Effluents - Elevated Batch - WGDT Nuclides VI*S Released I Units I 1st Qtr 2nd Qtr I3rd Qtr l 4th Qtr l Total A. Fission & Activation Gases Ar-41 Ci ----

Kr-85 Ci 1.25E+00 1.91E+00 6.04E-01 3.76E+00 Kr-85m Ci Xe-131 m Ci _ - 5.04E-04 - 5.04E-04 Xe-1 33 Ci - 1.89E-02 - 1.89E-02 Xe-133m Ci - 1.12E-04 - 1.12E-04 Xe-1 35 Ci - 7.96E-06 - 7.96E-06 Xe-135m Ci Total Activity Ci 1.25E+00 1.93E+00 6.04E-01 3.78E+oo B. lodines 1-131 Ci - _______ _

1-133 Ci - _ - T - I - I Total Activity Ci - t - J - j - -

C. Particulates 1-131 Ci Sr-89 Ci Sr-9o Ci Total Activity I Ci D. Gross Alpha Gross Alpha Ci - - I -

E. Tritium H-3 Ci - 1.65E-04 7.69E-04 1.38E-04 1 .07E-03 II-" = Not Detected

Table 2.2-A5 Millstone Unit No. 2 Airborne Effluents - Elevated - Containment Vents/Site Stack Nuclides I Released I Units I1st tr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total I A. Fission & Activation Gases Ar-41 Ci 2.74E-02 2.95E-02 3.23E-02 3;85E-02 1.28E-01 Kr-85 Ci 1.07E-01 1.07E-01 Kr-85m Ci Xe-131 m Ci Xe-133 Ci 1.01E-01 9.92E-02 1.16E-01 1.71 E-01 4.88E-01 Xe-133m Ci 2.36E-04 3.57E-04 3.13E-04 9.06E-04 Xe-135 Ci 4.90E-04 6.04E-04 9.08E-04 1.20E-03 3.21 E-03 Total Activity Ci 1.29E-01 1.30E-01 1.49E-01 3.18E-01 7.26E-01 B. lodines

• 1-131 Ci 1.72E-07 - ] - l 1.72E-07 1-133 r Ci 2.32E-07 5.10E-07 1.59E-07 9.01 E-07 Total Activity I Ci 1 4.04E-07 5.10E-07 j 1.59E-07 1.07E-06 C. Particulates 1-131 Ci - - - -

Co-58 Ci 8.05E-07 1.28E-07 9.34E-07 Co-60 Ci 5.89E-07 5.89E-07 Cs-137 Ci 3.09E-08 4.21 E-08 7.31 E-08 Sr-89 Ci Sr-90 Ci Total Activity Ci 3.09E-08 8.47E-07 1.28E-07 5.89E-07 1.60E-06 D. Gross Alpha Gross Alpha Ci I E. Tritium 1H-3 Ci I 1.15E-01 1.14E-01 2.11E-01 2.89E-01 1 7.292-01

• Prior to charcoal filtration

"-' = Not Detected

Table 2.2-A6 Millstone Unit No. 2 Airborne Effluents - Ground Batch - Containment Equipment Hatch

<< No Radioactivity Released >>

Nuclides I Released I Units 1st Qtrl 2nd Qtr I 3rd Qtr I 4th Qtr I Total I A. Fission & Activation Gases Ar-41 Ci Kr-85 Ci Kr-85m Ci ----

Kr-87 Ci Kr-88 Ci Xe-131 m Ci Xe-1 33 Ci Xe-1 33m Ci - - - -

Xe-135 Ci Xe-I 35m Ci Total Activity Ci B. lodines 1-131 1-133 Ci Ci j - - _ _

Total Activity j Ci C. Particulates 1-131 l Ci l - l Co-58 Ci Cs-i 37 j Ci - - - -

Total Activity l Ci - - - - I -

D. Gross Alpha Gross Alpha I Ci I - - - - I E. Tritium H-3 Ci - -

"-n = Not Detected

Table 2.2-A7 Millstone Unit No. 2 Airborne Effluents - Ground Batch - RWST Vent

<< No Radioactivity Released >>

Nuclides I Released I Units 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total I A. Fission & Activation Gases Ar-41 Ci Kr-85 Ci ----

Kr-85m Ci Xe-131m Ci - -

Xe-1 33 Ci Xe-1 33m Ci Xe-1 35 Ci Total Activity ICi B. lodines 1-131 Ci -

1-132 Ci-- --

1-133 Ci -

Total Activity Ci C. Particulates 1-131 Ci Co-58 Ci ----

Co-60 Ci Cs-1 34 Ci  ;

Cs-i 36 Ci Cs-I 37 Ci -

Sb-124 Ci -

Total Activity I Ci I - -

D. Gross Alpha IGross Alpha Ci I -

E. Tritium IH-3 I Ci I-n!n = Not Detected

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

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

1. Total Activity Ci 7.74E-03 4.86E-03 3.71 E-03 5.79E-03 2.21 E-02 Released

2. Average Period uCi/ml 2.80E-11 1.75E-11 1.31 E-1 1 2.07E-11 1.98E-1 1 Diluted Activity B. Tritium

1. Total Activity Ci 7.41 E+oo 8.19E+01 4.22E+01 1.34E+02 2.65E+02 Released

2. Average Period uCi/ml 2.68E-08 2.94E-07 1.49E-07 4.79E-07 2.37E-07 Diluted Activity C. Dissolved and Entrained Gases

1. Total Activity Ci 2.56E-01 3.30E-01 7.43E-02 1.22E-01 7.81 E-01 Released

2. Average Period uCi/ml 9.27E-10 1.19E-09 2.63E-10 4.36E-10 7.OOE-10 Diluted Activity D. Gross Alpha

11. Total Activity C Released Ci E. Volume

1. Released Waste Liters 3.43E+05 1.39E+06 4.05E+07 2.06E+07 6.28E+07 Volume

2. Dilution Volume Liters 1.94E+09 1.32E+09 1.31 E+09 1.86E+09 6.42E+09 During Releases

3. DilutionVolume Liters 2.76E+11 2.78E+11 l 2.83E+11 2.79E+11 1.12E+12 During Period I I I I I

"-" = Not Detected

Table 2.2-L2 Millstone Unit No. 2 Liquid Effluents - Continuous - SGBD, SW, RBCCW (Release Point - Quarry)

Nuclides l Released I Units r 1st Qtr I 2nd Qtr 7 3rd Qtr l 4th Qtr 7 Total A. Fission & Activation Products I Ci I - I - - I - I -

Total Activity I Ci - - - - -

B.Tritium lH-3 I Ci I 1.23E-04 I 3.32E-04 I 4.36E-02 I 3.61E-02l 8.01E-02 C. Dissolved & Entrained Gases II ci I - I - I - I - -

'TotalActivity Ci I -

D. Gross Alpha Gross Alpha I Ci I -

"-' = Not Detected

Table 2.2-L3 Millstone Unit No. 2 Liquid Effluents - Batch - LWS (Release Point - Quarry)

Nuclides I Released I Units"I st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total I A. Fission & Activation Products Ag-11Om Ci 1.36E-04 7.40E-05 8.04E-05 2.12E-05 3.12E-04 Co-57 Ci 4.11 E-08 6.58E-07 6.99E-07 Co-58 Ci 1.19E-03 2.49E-04 5.47E-05 3.52E-05 1.53E-03 Co-60 Ci 1.46E-03 7.65E-04 6.91 E-04 6.89E-04 3.61 E-03 Cs-I 34 Ci 1.04E-04 1.72E-04 4.65E-05 8.42E-05 4.06E-04 Cs-I 37 Ci 1.38E-04 1.72E-04 6.63E-05 1.46E-04 5.22E-04 Fe-55 Ci 1.40E-03 2.01 E-03 2.07E-03 2.74E-03 8.22E-03 1-133 Ci 1.75E-06 - 1.75E-06 Ba-1 41 Ci 4.59E-06 4.59E-06 Mn-54 Ci 1.59E-04 2.46E-05 2.23E-05 1.05E-05 2.17E-04 Nb-95 Ci 1.73E-04 6.04E-05 2.33E-06 2.35E-04 Mo-99 Ci 1.97E-06 1.97E-06 Tc-99m Ci 2.13E-06 2.13E-06 Ru-103 Ci 1.69E-05 1.69E-05 Ru-105 Ci 5.85E-05 5.85E-05 Sb-1 24 Ci 1.88E-04 2.39E-05 2.12E-04 Sb-125 Ci 2.57E-03 1.19E-03 6.78E-04 2.06E-03 6.49E-03 Sn-1 13 Ci 7.44E-05 5.43E-05 1.29E-04 Sn-117m Ci 3.11 E-08 3.11 E-08 Sr-89 Ci 1.83E-05 7.27E-05 9.10E-05 Sr-90 Ci Zr-95 Ci 5.12E-05 5.12E-05 Total Activity Ci 7.74E-03 I 4.86E-03 3.71 E-03 5.79E-03 2.21 E-02 B. Tritium IH-3 I Ci l 7.41E+00 I 8.19E+01 1 4.22E+01 1.34E+02 I 2.65E+02 C. Dissolved & Entrained Gases Kr-85 Ci 2.54E-01 3.15E-01 7.39E-02 1.14E-01 7.58E-01 Xe-131m Ci 9.98E-04 9.98E-04 Xe-133 Ci 3.21 E-04 1.47E-02 4.21 E-04 7.16E-03 2.26E-02 Xe-1 35 Ci 9.48E-06 9.48E-06 Total Activity CiI 2.56E-01 3.30E-01 7.43E-02 1.22E-01 7.81E-01 D. Gross Alpha JGrossAlpha Ci - - - - -

%- = Not Detected

Table 2.2-L4 Millstone Unit No. 2 Liquid Effluents -Continuous-Turbine Building Sump (Release Point - Yard Drain - DSN 006)

Nuclides Released I Units 1st Qtr 1 I 2nd Qtr I 3rd Qtr I 4th Qtr l Total A. Fission & Activation Products Total Activity Ci Released Average Period uCi/ml Diluted Activity B. Tritium Total Activity Ci 1 .24E-02 1.55E-03 1.44E-02 2.83E-02 Released Average Period uCi/mI 5.05E-07 6.19E-08 5.74E-07 2.85E-07 Diluted Activity C. Dissolved & Entrained Gases Total Activity Ci Released _ _

Average Period uCi/mi Diluted Activity D. Gross Alpha Gross Alpha I Ci E. Volume Released Waste Liters 1.71 E+06 O.OOE+00 2.19E+05 2.18E+06 4.11E+06 Volume I I I I Dilution Volume Liters Dilution Volumes cannot be accurately determined for yard drain releases During Releases l Dilution Volume Liters 2.45E+07 2.48E+07 2.51 E+07 2.51 E+07 9.95E+07 During Period l t-' = Not Detected

Table 2.3-Al Millstone Unit No. 3 Airborne Effluents - Release Summary I Units l 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total I A. Fission & Activation Gases

1. Total Activity Ci 4.21 E-01 3.51 E-02 1.47E-02 1.35E-02 4.84E-01 Released

2. Average Period luCi/sec 5.35E-02 4.47E-03 1.84E-03 1.70E-03 1.53E-02 Release Rate B. Iodine-131

1. Total Activity Ci 1.33E-06 1.33E-06 Released

2. Average Period uCilsec 1.69E-07 4.21 E-08 Release Rate C. Particulates

1. Total Activity Ci 1.26E-05 3.53E-04 1.01 E-06 1.84E-05 3.85E-04 Released

2. Average Period uCi/sec 1.61 E-06 4.49E-05 1.26E-07 2.32E-06 1.22E-05 Release Rate D. Gross Alpha l1. Total Activity Ci l - l - l - l - - l l Released I E. Tritium

%"= Not Detected

Table 2.3-A2 Millstone Unit No. 3 Airborne Effluents - Mixed Continuous - Normal Ventilation &

Spent Fuel Pool Evaporation Nuclides lU I Released I Units l 1sQtr I 2ndQtr I 3rd Qtr I 4thQtr I Total I A. Fission & Activation Gases Xe-131m Ci Xe-i 33 Ci l _

Xe-135 Ci Total Activity Ci - -

B. lodines 1-131 Ci - 1.33E-06 1.33E-06 1-133 Ci -

Total Activity Ci - 1.33E-06 - j 1.33E-06 C. Particulates 1-131 Ci Co-58 Ci 1.20E-04 9.73E-07 1.21 E-04 Co-60 Ci 1.77E-05 4.83E-06 2.25E-05 Cr-51 Ci 1.72E-04 1.72E-04 Mn-54 Ci 1.12E-05 1.12E-05 Nb-95 Ci - 6.12E-06 6.12E-06 Zr-95 Ci - 1.75E-05 1.75E-05 Be-7 Ci - 1.33E-05 1.33E-05 Sr-89 Ci ----

Sr-90 Ci -

Total Activity Ci 3.45E-04 9.73E-07 I 1.81 E-05 3.64E-04 D. Gross Alpha lGross Alpha Ci I - - I E. Tritium lH-3 I Ci I 4.90E+00 2.53E+01 1 2.46E+01 1 .95E+01 7.43E+01 l]

"2'= Not Detected

Table 2.3-A3 Millstone Unit No. 3 Airborne Effluents - Ground Continuous - ESF Building Ventilation Nuclides I a1!!.

Released I Units I 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. Fission & Activation Gases IXe-131m I Ci I 3.44E-01 - I - I - l 3.44E-01 l lTotal Activity j Ci 3.44E-01 - - - 3.44E-01 B. lodines 1-131 Cil - j -

1-133 lCi - 1 -

Total Activity lCil - -ir -

C. Particulates 1-131 Ci Co-58 Ci - 6.47E-08 6.47E-08 Cr-51 Ci -

Ru-106 Ci - 2.32E-07 2.32E-07 Hf-1 81 Ci - 3.23E-08 3.23E-08 Sr-89 Ci -

Sr-90 Ci _

Total Activity I Ci 2.97E-07 3.23E-08 3.29E-07 D. Gross Alpha Gross Alpha Ci I -

E. Tritium IH-3 Ci I - l 1.14E+00 I 1.77E-01 1.32E+00

"-" = Not Detected

Table 2.3-A4 Millstone Unit No. 3 Airborne Effluents - Mixed Batch - Containment Drawdowns Nuclides Released I Units P 1st Qtr T

.'*O i 2nd Qtr l 3rd Qtr r 4th Qtr l Total I

A. Fission & Activation Gases IXe-131m Ci I - - - - I jTotal Activity Ci - - - -

B. lodines 1-131 Ci -

1-133 ci - r -- T - I - I Total Activity Ci - - - I - T - 1 C. Particulates 1-131 Ci  ;

Nb-97 Ci Total Activity Ci D. Gross Alpha Gross Alpha I Ci I - - -

E. Tritium H-3 Ci - l .07E-03 - - l .07E-03

%" = Not Detected

Table 2.3-A5 Millstone Unit No. 3 Airborne Effluents - Mixed Batch - Containment Purges Nuclides 's! !.

Released I Units I 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. Fission & Activation Gases Xe-I 33 Ci 5.77E-03 5.77E-03 Xe-I 35 Ci 1.99E-03 1.99E-03 Total Activity Ci - 7.76E-03 - 7.76E-03 B. lodines 1-131 Ci T -

1-133 Ci -

Total Activity Ci C. Particulates 1-133 l Ci I - l l l lTotai Activity I Ci - - - - -

D. Gross Alpha lGross Alpha Ci - i E. Tritium H-3 Ci - 6.70E-02 - l 6.70E-02

"-" = Not Detected

Table 2.3-A6 Millstone Unit No. 3 Airborne Effluents - Elevated Continuous - Gaseous Waste System

& Containment %tents Nuclides I Released l Units I stQtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total I A. Fission & Activation Gases Ar-41 Ci 1.61 E-02 5.66E-03 1.06E-02 1.13E-02 4.36E-02 Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-133 Ci 4.70E-02 1.31 E-02 3.81 E-03 1.91 E-03 6.59E-02 Xe-135 Ci 1.37E-02 8.62E-03 2.54E-04 3.57E-04 2.29E-02 Xe-1 35m Ci Xe-1 38 Ci Total Activity Ci 7.68E-02 2.74E-02 1.47E-02 1.35E-02 1.32E-01 B. lodines 1-131 Ci 1-132 Ci 1.45E-05 - 1.45E-05 1

Total Activity I Ci 1.45E-05 - 1.45E-05 1

C. Particulates 1-131 Ci -

Co-58 Ci 2.16E-06 2.16E-06 Co-60 Ci 1.41 E-07 1.41 E-07 Cr-51 Ci - 1.23E-06 1.23E-06 Ba-1 40 Ci - 2.72E-07 2.72E-07 Mn-54 Ci - 1.16E-08 1.16E-08 Nb-95 Ci - 5.98E-08 5.98E-08 Co-57 Ci - 7.62E-08 7.62E-08 Zr-95 Ci - 1.58E-08 1.58E-08 Br-82 Ci 1.25E-05 4.01 E-06 1.65E-05 Total Activity Ci 1.26E-05 7.56E-06 I 2.72E-07 2.05E-05 D. Gross Alpha Gross Alpha I Ci - - - -

E. Tritium 1H-3 Ci 1.17E+00 4.40E-01 3.69E-01 6.59E-01 2.64E+00 n~n = Not Detected

Table 2.3-A7 Millstone Unit No. 3 Airborne Effluents - Ground Batch - Containment Equipment Hatch l Nuclides I i _

I Released I Units l 1st Mar l 2nd Qtr I 3rd Qtr I 4th Qtr I Total A. Fission & Activation Gases Ar-41 Ci Kr-85 Ci Kr-85m Ci --

Kr-87 Ci Kr-88 Ci Xe-131m Ci Xe-133 Ci Xe-1 33m Ci Xe-1 35 Ci Xe-135m Ci _ -

Total Activity Ci B. lodines 1-131 Ci _

1-133 lCi Total Activity Cij - - I C. Particulates 1-131 Ci Cr-51 Ci - 3.79E-07 3.79E-07 Co-58 Ci - 5.52E-07 5.52E-07 Co-60 Ci - 2.91 E-08 2.91 E-08 Mn-54 Ci - 3.21 E-08 3.21 E-08 Zr-95 Ci - 3.18E-08 3.18E-08 Total Activity Ci 1-1.02E-06 I- 1.02E-06 D. Gross Alpha Gross Alpha I Ci I - II E. Tritium H-3 Ci I - I I I I

' = Not Detected

Table 2.3-A8 Millstone Unit No. 3 Airborne Effluents - Ground Batch - RWST Vent

<< No Radioactivity Released >>

Nuclides I Released I Units l stQtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total I A. Fission & Activation Gases Ar-41 Ci Kr-85 Ci Kr-85m Ci Xe-131m Ci Xe-1 33 Ci Xe-1 33m Ci Xe-1 35 Ci Total Activity Ci - I B. lodines 1-131 Ci 1-132 Ci 1-133 Ci Total Activity Ci C. Particulates 1-131 Ci Co-58 Ci Co-60 Ci Cs-1 34 Ci Cs-1 36 Ci Cs-1 37 Ci Sb-124 Ci Total Activity Ci I D. Gross Alpha lGross Alpha Ci E. Tritium lH-3 Ci - - - - I

"!' = Not Detected

Table 2.3-L1 Millstone Unit No. 3 Liquid Effluents - Release Summary (Release Point - Quarry)

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

1. Total Activity Ci 2.85E-02 7.32E-02 1.79E-02 9.24E-03 1.29E-01 Released

2. Average Period uCi/mi 6.45E-11 2.15E-10 3.79E-11 2.OOE-11 7.51 E-11 Diluted Activity B. Tritium

1. Total Activity Ci 9.43E+02 2.43E+02 6.17E+01 3.48E+01 1.28E+03 Released

2. Average Period uCi/ml 2.13E-06 7.15E-07 1.31 E-07 7.53E-08 7.48E-07 Diluted Activity C. Dissolved and Entrained Gases

1. Total Activity Ci 5.53E-04 5.53E-04 Released _

2. Average Period uCi/ml 1.25E-12 3.22E-13 Diluted Activity D. Gross Alpha

1. TotalActivity Ci 1 Released E. Volume

1. Released Waste Liters 1 .32E+07 3.69E+06 9.42E+06 1.06E+07 3.69E+07 Volume

2. Dilution Volume Liters 1 .25E+10 7.62E+09 8.89E+09 5.97E+09 3.50E+10 During Releases

3. DilutionVolume Liters 4.42E+11 3.40E+11 4.71 E+11 4.62E+11 1.72E+12 During Period I _ I_ I I I I _I

"_n = Not Detected

Table 2.3-L2 Millstone Unit No. 3 Liquid Effluents - Continuous - SGBD & SW & TK2 (Release Point - Quarry)

Nclides uReleased Units I 1st Qtr I 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. Fission & Activation Products Cii - I I I

[Total Activity Ci - T - - - -

B. Tritium H-3 Ci I 9.16E-02 1.52E-02 8.09E-02 1.30E-01 3.18E-01 C. Dissolved & Entrained Gases LI ci I - I - I - I - I1 ITotalActivity I Ci I - T- I 1 D. Gross Alpha Gross Alpha I Ci I - - I i

• -_ = Not Detected

Table 2.3-L3 Millstone Unit No. 3 Liquid Effluents - Batch - LWS (Quany Release Point)

Nuclides l Units l r 7 dQtr 1 3rd Qtr I 4th Qtr I

Total I

I A. Fission& Activation Products Be-7 Ci I -- 1.15E-04 1.15E-04 Ag-11 Om Ci 6.26E-05 5.71 E-04 6.84E-06 6.40E-04 Co-57 Ci 1.55E-05 1.55E-05 Co-58 Ci 7.60E-04 7.86E-03 2.74E-03 7.30E-04 1.21 E-02 Co-60 Ci 9.17E-03 1.87E-02 1.1 6E-03 8.39E-04 2.99E-02 Cr-51 Ci 1.64E-04 1.04E-02 3.84E-04 1.09E-02 Cs-134 Ci Cs-137 Ci 1.76E-05 5.30E-06 2.29E-05 Fe-55 Ci 7.70E-03 2.57E-02 1.14E-02 6.73E-03 5.15E-02 Fe-59 Ci 9.32E-04 1.03E-04 1.04E-03 1-131 Ci -

1-133 Ci Mn-54 Ci 1.45E-03 2.63E-03 3.47E-04 1.35E-04 4.56E-03 Na-24 Ci Nb-95 Ci 1.16E-05 1.11 E-03 3.84E-04 2.48E-05 1.53E-03 Nb-97 Ci 1.43E-04 1.05E-04 2.48E-04 Ru-105 Ci 2.97E-05 9.36E-05 1.23E-04 Sb-1 24 Ci 3.29E-05 3.29E-05 Sb-125 Ci 8.99E-03 4.38E-03 1.1 5E-03 6.62E-04 1.52E-02 Sr-89 Ci -

Sr-90 Ci -

Sn-117m Ci - 3.57E-05 _ 3.57E-05 Zr-95 Ci - 3.34E-04 1.04E-04 4.38E-04 Ba-140 Ci Ba-1 42 Ci 9.36E-05 9.36E-05 Y-91m Ci Total Activity Ci 2.85E-02 7.29E-02 1.79E-02 9.24E-03 1.28E-01 B. Tritium H-3 lCi I 9.43E+02 I 2.43E+02 I 6.16E+01 3.46E+01 1.28E+03 C. Dissolved & Entrained Gases Xe-133 Ci I 4.86E-04 l - - l 4.86E-04 Xe-1 35m Ci -

Xe-135 Ci 6.69E-05 6.69E-05 Total Activity Ci 5.53E-04 - - - 5.53E-04 D. Gross Alpha Gross Alpha I Ci - - T - I

• @_n= Not Detected

Table 2.3-L4 Millstone Unit No. 3 Liquid Effluents - Batch - CPF Waste Neutralization Sumps, Hotwell, SIG Bulk (Quarry Release Point)

Nuclides l Released I Unitsl 1st Qtr I 2nd Qtr l 3rd Qtr I 4th Qtr I Total A. Fission& Activation Products Co-58 Ci - 2.96E-04 l - - l 2.96E-04 Nb-95m Ci 9.97E-05 - 9.97E-05 Sn-117m Ci 1.22E-05 - 1.22E-05 Total Activity Ci 2.96E-04 l - 4.08E-04 B. Tritium H-3 l Ci l1.67E-02 I 5.15E-03 3.57E-02 5.14E-02 1.09E-01 C. Dissolved & Entrained Gases Xe-131 m l Ci Xe-1-35 --

Total Activity Ci I - - --

D. Gross Alpha Gross Alpha Ci --

"-" = Not Detected

Table 2.3-L5 Millstone Unit No. 3 Liquid Effluents - Release Summary (Release Point - Yard Drain - DSN 006)

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

1. Total Activity Ci Released

2. Average Period uCi/mI _ _ _

Diluted Activity _

B. Tritium

1. Total Activity Ci 3.77E-02 7.52E-03 1.46E-02 5.94E-02 1.19E-01 Released

2. Average Period uCi/ml 1 .43E-06 3.03E-07 5.38E-07 2.21 E-06 1.1 3E-06 Diluted Activity _

C. Dissolved and Entrained Gases

1. Total Activity Ci Released

2. Average Period uClml _ _

Diluted Activity D. Gross Alpha

1. Total Activity Ci _ _ _ _ l Released l E. Volume

1. Released Waste Uters 1.78E+06 3.97E+05 2.16E+06 1 .75E+06 6.08E+06 Volume l_ l__I I I l

2. Dilution Volume Liters Dilution Volumes cannot be accurately determined for yard drain releases During Releases l I I

3. Dilution Volume lUters 2.45E+07 2.48E+07 2.51 E+07 2.51 E+07 9.95E+07 During Period I I lIlll I

%" = Not Detected

Table 2.3-L6 Millstone Unit No. 3 Liquid Effluents - Continuous - Turbine Building Sump (Release Point - Yard Drain - DSN 006)

Nuclides '

I Released IUnits l 1st Qtr I 2nd Qtr I 3rd Qtr l 4th Qtr r Total A. Fission& Activation Products I I Ci I - I - I - I - I lTotal Activity I Ci - I - T -

B. Tritium H-3 Ci 3.72E-02 l 4.59E-03 1.16E-02 I 5.93E-02 1.13E-01 Average Period uClmi 1.52E-06 1.85E-07 4.27E-07 2.21 E-06 1.07E-06 Diluted Activity C. Dissolved & Entrained Gases I

lTotalActivity I ci I ICi -

7 -

[

l I - 71 - I D. Gross Alpha Gross Alpha I Ci - - - -

n= Not Detected

Table 2.3-L7 Millstone Unit No. 3 Liquid Effluents - Continuous - WTT Berm Water (Release Point - Yard Drain - DSN 006)

Nuclides  !

l Released I Units I 1st Qtr I 2nd Qtr 7 3rd Qtr l 4th Qtr I Total A. Fission & Activation Products ITotalActivity I Ci I - I -

B. Tritium H-3 I Ci 4.60E-04 2.93E-03 3.04E-03 9.19E-05 6.52E-03 Average Period uCi/ml 1.88E-08 1.18E-07 1.21 E-07 3.67E-09 6.55E-08 Diluted Activity C. Dissolved & Entrained Gases I Icia I - - -

ITotalActivity Ci D. Gross Alpha lGross Alpha Ci I -

E. Volume

"-_= Not Detected

2.2 Liquid Effluents 2.2.1 Measurement of Radioactivity 2.2.1.1 Liquid TankslSumps There are numerous tanks & sumps that are used to discharge liquids containing radioactivity to the environs; they are:

Unit I Reactor Cavity Water Unit 2 Clean Waste Monitor Tanks (2)

Aerated Waste Monitor Tank 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 for individual radionuclide composition. Isotopic concentrations are multiplied by the volume released to obtain 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.

2.2.1.2 Unit 2 and Unit 3 Steam Generator Blowdown Steam generator blowdown water grab samples are taken and analyzed on the HPGe gamma spectrometer and liquid scintillation detector if required by the conditional action requirements of the REMODCM. Total volume of blowdown is multiplied by the isotopic concentrations (if any) to determine the total activity released via blowdown. 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. Tritium is determined through liquid scintillation counting. Unit 2 is a continuous release while Unit 3 recycles blowdown except for periodic open cycle blowdown.

2.2.1.3 Unit 2 and Unit 3 Continuous Liquid Releases Grab samples are taken for continuous liquid release pathways and analyzed on the HPGe gamma spectrometer and liquid scintillation detector. 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. Tritium is determined through liquid scintillation

counting. Pathways for continuous liquid effluent releases include, Steam Generator Blowdown, Service Water Effluent, and Turbine Building Sump discharge from Units 2 & 3.

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

SamplingfData Collection 10% Variation in data collection Calibration 10% Calibration to NBS standards Sample Counting 10% Error for counting statistics Flow & Level Measurements 10% Error for release volumes 2.2.3 Batch Releases - Liquid Effluents Unit 1 Unit 2 Unit 3 Number of Batches 7 48 380 Total Time (min) 995 4,236 43,841 Maximum Time (min) 157 206 310 Average Time (min) 142 88 115 Minimum Time (min) 109 5 30 Average Stream Flow Not Applicable - Ocean Site 2.2.4 Abnormal Liquid Releases An abnormal release of radioactivity isthe discharge of a volume of liquid radioactive material to the environment that was unplanned or uncontrolled.

In2004, the following abnormal liquid releases occurred:

2.2.4.1 Unit I - None 2.2.4.2 Unit 2 - None 2.2.4.3 Unit 3 - None

2.3 Solid Waste 2004 Solid waste shipment radioactivity summaries for each unit are given in the following tables:

Table 2.1-S Unit 1 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 for 2004 Containers routinely used for radioactive waste shipment include:

55-gal Steel Drum DOT 17-H container 7.5 ft3 Steel Boxes 45 ft3 87 ft3 95 ft3 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

Table 2.1-S Solid Waste and Irradiated Component Shipments Millstone Unit 1 January 1, 2004 through December 31, 2004 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of Waste

a. Spent resins, Filter sludges, Evaporator bottoms, etc.

Di0position ,-5 Units  : tAnnual Totals:. Est.-Total t - "

A.r C;~lft~~ 2 Nso r' .-

Error-i%

t _%,-,'j.'

.'S'P, From Millstone Nuclear PowerStatlon to - m3 ' 6.4161 E+00 Chem-Nucdear Services LLC, DCSF. Bamwell, SC for De-watering Ci 2.8909E+01 25%

From Millstone Nuclear Power Station to Duratek Inc.,. *.*4 m , 2.0400E-01 j Oak Ridge.,TN for Super-Compactlon I

?,.C's CiY ~ 9.951 7E-02 9957-2 J l25% 25 From Millstone Nuclear Power Stailon to Studsvik *-3 i 9.8672E-02 Processing Center LLC, Erwin, TN for Incineration l J;i 9 3.4912E+00 25%

b. Dry compressible waste, Contaminated equipment, etc.

Dip osit 'i;- ,s.tY'AnnuaI Totas E l From Millstone Nuclear Power Station to *-" m3 r 3.9791 E-01 25%

[

Chem-Nuclear Services LLC, DCSF, Bamwell, SC for De-watering {' Ci 2.7591 E-01 From Millstone Nuclear Power Station to Duratek inc., m. 3.0528E+01 I

lngston,TN for Super-Compacgon. Incineration,_etc._ 3.1940E-02 25%

From Millstone Nuclear Power station to DuratekInc., -2.5424E+01 2-Oak Ridge, TN for Super-Compaction,lIncineration, etc. I--Ci: 2.9896E+00 l 25% 1 C. Irradiated components, Control rods, etc.

Disposition . -. S+ J - s Units_ l -Annual Totals !:'r- Est.'.Total Chem-Nuclear From Millstone Services Nuclear Pow Sta tion toSC LLC,erBarnwell. for Burial "C

4i'_ m i __ - _

__ 3 _1.6260E +00l 4.8665E+0325

d. Other - (Water)

Disposition ^¢T- *.;- -, Units " '.Annual Totals ,; j Est.Total

[M~

ri;,,>a:~ ,*',,r8, -, G ..

From Millstone Nuclear Power Station to Duratek Inc.,

Oak Ridge, TN for Incineration m-Ci 2.3355E+00-3 6.0720E-02

- Error..%.'.>

25%

d. Other - (Mixed Waste)

Dipoiio ~ *- ""'- -Units ,%

-- ,Annual TotalsS' EStbjotal 1 XI~its~iS~l 1rr-or o-/

From Millstone Nuclear Power Station to Perma-Fix of Florida, Inc.. l_____ 1.3333E-02 Gainesville. FL for Stabilization, Fuel Blending. etc. Ci .; 2.5268E-05 25%

Dominion Nuclear Connecticut Millstone Power Station Page 1 of 11 Unit 1 Section

2. Estimate of major nuclide composition (by type of waste)

a. Spent resins, Filter sludges, Evaporator bottoms, etc.

From Millstone Nuclear Power Station to Chem-Nuclear Services LLC, DCSF, Bamwell, SC for De-watering

r. .._

I nlnnrlrP~:T/ nf.TntnI I .-- li~riPQ,--

H-3 <0.01 1.8011 E-03 C-14 Cr-51 Mn-54 0.07 1.9801 E-02 Fe-55 79.28 2.2918E+01 Fe-59 Co-57 <0.01 3.2056E-05 Co-58 Co-60 17.29 4.9985E+00 Ni-59 Ni-63 2.42 6.9949E-01 Zn-65 0.01 3.9320E-03 Sr-89 _ _ _ _

Sr-90 <0.01 7.9430E-04 Nb-94 _ _ _ _

Zr-95 Nb-95 Tc-99 Ru-103 _ _

Ru-1 06 Ag-108m Ag-11 Om Sn-113 Sb-124 Sb-125 0.04 1.0172E-02 1-129 <0.01 2.2800E-05 1-131 Cs-1 34 Cs-1 37 0.68 1.9727E-01 Ba-140 _ _

Ce-141 __ __ __ _

Ce-144 0.05 1.4135E-02 U-234 U-235 U-238 Pu-238 _ <0.01 1.3197E-03 Pu-239 <0.01 6.5587E-04 Pu-241 0.12 3.4743E-02 Am-241 0.02 5.2448E-03 Cm-242 <0.01 1.0718E-06 Cm-244 <0.01 2.2495E-03 A!X--;',.CURIES ITOTAL) ' . .2.8909E+01 Dominion Nuclear Connecticut Millstone Power Station Page 2 of 11 Unit 1 Section

2. Estimate of major nuclide composition (by type of waste)

a. Spent resins, Filter sludges, Evaporator bottoms, etc.

From Millstone Nuclear Power Station to Duratek Inc.. Oak Ridge. TN for Super-Compaction 1 ......

l R_ saionul

.i sa . of.4Total :.:3 1r-. (tripq<-I aI i ideP IO/W%

H-3 1.60 1.5920E-03 C-14 <0.01 8.25OOE-06 Cr-51 Mn-54 0.09 8.5200E-05 Fe-55 68.73 6.8400E-02 Fe-59 Co-57 Co-58 Co-60 19.31 1.9220E-02 Ni-59 Ni-63 5.04 5.0200E-03 Zn-65 Sr-89 Sr-90 0.02 1.4970E-05 Nb-94 Zr-95 Nb-95 Tc-99 Ru-1 03 Ru-1 06 Ag-108m Ag-11 Om <0.01 1.3630E-06 Sn-113 Sb-124 Sb-125 1-129 1-131 Cs-1 34 Cs-i 37 4.54 4.5200E-03 Ba-140 Ce-141 Ce-1 44 <0.01 1.7590E-06 U-234 U -235 ____________

U-238 Pu-238 0.02 2.15O0E-05 Pu-239 0.01 1.0880E-05 Pu-241 0.40 4.0300E-04 Am-241 0.14 1.391 OE-04 Cm-242 <0.01 8.1500E-10 Cm-244 0.08 7.8600E-05 GT JCURIES (TOTAL) - 9.9517E-02 Dominion Nuclear Connecticut Millstone Power Station Page 3 of 11 Unit 1 Section

2. Estimate of major nuclide composition (by type of waste)

a. Spent resins, Filter sludges, Evaporator bottoms, etc.

From Millstone Nuclear Power Station to Studsvik Processing Center LLC. Erwin, TN for Incineration Fl :Radionuclidel i.°/.%nof.TotalWI .- Curies. ,.

H-3 0.05 1.6977E-03 C-14 0.71 2.4899E-02 Cr-51 <0.01 5.4738E-17 Mn-54 0.60 2.1092E-02 Fe-55 45.98 1.6051 E+00 Fe-59 <0.01 1.9549E-1 2 Co-57 0.05 1.8623E-03 Co-58 0.05 1.6360E-03 Co-60 18.60 6.4924E-01 Ni-59 _

Ni-63 25.29 8.8280E-01 Zn-65 Sr-89 <0.01 8.8074E-07 Sr-90 0.02 6.3175E-04 Nb-94 Zr-95 <0.01 9.4145E-05 Nb-95 <0.01 2.9529E-07 Tc-99 <0.01 1.9446E-07 Ru-103 <0.01 1.1627E-16 Ru-106 Ag-108m Ag-1 1Om <0.01 2.9941 E-05 Sn-113 0.01 4.8873E-04 Sb-124 <0.01 3.6835E-11 Sb-1 25 0.24 8.3238E-03 1-129 <0.01 5.6384E-05 1-131 Cs-134 3.21 1.1215E-01 Cs-1 37 4.86 1.6977E-01 Ba-140 Ce-141 Ce-144 0.10 3.6629E-03 U-234 U-235 U-238 Pu-238 <0.01 1.6771 E-04 Pu-239 <0.01 9.0852E-05 Pu-241 0.20 6.8834E-03 Am-241 <0.01 2.1504E-04 Cm-242 <0.01 3.6217E-05 Cm-244 <0.01 2.6237E-04 2K<CURIES (TOTAL) 3.491 2E+00 Dominion Nuclear Connecticut Millstone Power Station Page 4 of 11 Unit I Section

2. Estimate of major nuclide composition (by type of waste)

b. Dry compressible waste, Contaminated equipment, etc.

From Millstone Nuclear Power Station to Chem-Nuclear Services LLC. DCSF. Bamwell, SC for De-watering

, .Radionuclide,

.. I' %ofTotalI J. _:__ _II :V: CCuries H-3 <0.01 2.9239E-06 C-1 4 Cr-51 Mn-54 0.06 1.7902E-04 Fe-55 80.32 2.2160E-01 Fe-59 Co-57 <0.01 8.4382E-07 Co-58 Co-60 15.06 4.1550E-02 Ni-59 Ni-63 2.36 6.5146E-03 Zn-65 <0.01 7.9509E-06 Sr-89 Sr-90 <0.01 1.6697E-05 Nb-94 Zr-95 Nb-95 Tc-99 Ru-1 03 Ru-1 06 Ag-1 08m Ag-1 1 Om Sn-113 Sb-1 24 Sb-125 0.01 2.7700E-05 1-129 <0.01 6.0017E-07 1-131 Cs-1 34 Cs-137 1.86 5.1296E-03 Ba-140 Ce-141 Ce-144 0.13 3.7190E-04 U-234 U-235 U-238 Pu-238 <0.01 1.4337E-05 Pu-239 <0.01 7.1302E-06 Pu-241 0.13 3.5651 E-04 Am-241 0.03 8.5152E-05 Cm-242 <0.01 2.8213E-08 Cm-244 0.02 4.1550E-05

..w CURIES.(TOTAL) i- U;' 2.7591 E-01 Dominion Nuclear Connecticut Millstone Power Station Page 5 of 11 Unit I Section

2. Estimate of major nuclide composition (by type of waste)

b. Dry compressible waste, Contaminated equipment, etc.

From Millstone Nuclear Power Station to Duratek Inc., Kingston, TN for Super-Compaction, Incineration, etc.

IRadionuclide'I ,.;Oof

> ZTotal ' Curies r H-3 - 1 C-14 4 4 Cr-51 Mn-54 Fe-55 54.51 1.7410E-02 Fe-59 Co-57 Co-58 Co-60 23.47 7.4950E-03 Ni-59 Ni-63 7.88 2.5180E-03 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 Nb-95 Tc-99 Ru-103 Ru-1 06 Ag-108m Ag-110m Sn-113 Sb-1 24 Sb-1 25 1-129 1-131 Cs-1 34 Cs-1 37 12.85 4.1030E-03 Ba-140 Ce-1 41 Ce-144 0.15 4.6570E-05 U-234 U-235 U-238 Pu-238 0.04 1.1 969E-05 Pu-239 0.02 6.2930E-06 Pu-241 0.99 3.1660E-04 Am-241 0.07 2.1529E-05 Cm-242 Cm-244 0.03 1.1172E-05

~ ,;iCURIES (TOTAL)Yv 3.1940E-02 Dominion Nuclear Connecticut Millstone Power Station Page 6 of 11 Unit 1 Section

2. Estimate of major nuclide composition (by type of waste)

b. Dry compressible waste, Contaminated equipment, etc.

From Millstone Nuclear Power Station to Duratek Inc., Oak Ridge, TN for Super-Compaction, Incineration, etc.

A,Radionuclide I . %-of Total Il I-.' Curies IIl H-3 _ _ _ _ _ _ _ _ _ _

C-14 0.01 4.0689E-04 Cr-51 Mn-54 _

Fe-55 2.39 7.1520E-02 Fe-59 Co-57 Co-58 Co-60 1.05 3.1256E-02 Ni-59 Ni-63 0.35 1.0539E-02 Zn-65 Sr-89 Sr-90 3.03 9.0700E-02 Nb-94 Zr-95 Nb-95 Tc-99 Ru-1 03 Ru-1 06 Ag-1 08m Ag-11 Om Sn-113 Sb-124 _ _ __

Sb-125 1-129 1-131 Cs-1 34 Cs-137 93.10 2.7835E+00 Ba-140 Ce-141 Ce-144 <0.01 1.8165E-04 U-234 U-235 U-238 Pu-238 <0.01 5.0133E-05 Pu-239 <0.01 2.6329E-05 Pu-241 0.04 1.3203E-03 Am-241 <0.01 9.0051 E-05 Cm-242 Cm-244 <0.01 4.6620E-05

.-. :CURIES C (TOTAL)--. 2.9896E+00 Dominion Nuclear Connecticut Millstone Power Station Page 7 of I1 Unit 1 Section

2. Estimate of major nuclide composition (by type of waste)

c. Irradiated components, Control rods, etc.

From Millstone Nuclear Power Station to Chem-Nuclear Services LLC, Bamwell, SC for Burial H.RrdinniuclideA '1 0Ownf ,Tntal uix r, I 11 H-3 <0.01 1.4400E-04 C-14 0.01 5.2400E-01 Cr-51 <0.01 7.7300E-07 Mn-54 0.04 1.7600E+00 Fe-55 36.17 1.7600E+03 Fe-59 <0.01 2.3700E-06 Co-57 <0.01 2.0300E-04 Co-58 <0.01 4.1300E-05 Co-60 55.07 2.6800E+03 Ni-59 0.07 3.2000E+00 Ni-63 8.65 4.2100E+02 Zn-65 <0.01 9.0300E-03 Sr-89 <0.01 2.8400E-08 Sr-90 <0.01 3.9600E-04 Nb-94 <0.01 1.2800E-02 Zr-95 <0.01 7.0700E-06 Nb-95 <0.01 1.1300E-06 Tc-99 <0.01 5.7800E-05 Ru-1 03 <0.01 9.5800E-07 Ru-1 06 <0.01 2.5200E-03 Ag-1 08m <0.01 7.1400E-04 Ag-1 Om <0.01 4.8700E-04 Sn-113 Sb-124 <0.01 1.4000E-05 Sb-1 25 <0.01 6.7600E-04 1-129 <0.01 4.4700E-06 1-131 Cs-1 34 <0.01 4.4500E-04 Cs-137 <0.01 2.9100E-02 Ba-140 <0.01 2.0800E-12 Ce-141 <0.01 1.0100E-06 Ce-144 <0.01 5.9700E-04 U-234 _ _

U-235 <0.01 8.6000E-06 U-238 <0.01 1.3300E-06 Pu-238 <0.01 7.2600E-05 Pu-239 <0.01 3.4800E-05 Pu-241 <0.01 1.81 OOE-03 Am-241 <0.01 3.8400E-04 Cm-242 <0.01 3.3200E-07 Cm-244 <0.01 2.21 OOE-04 f SCURIES (TOTAL)'-,.- 4.8665E+03 Dominion Nuclear Connecticut Millstone Power Station Page 8 of 11 Unit 1 Section

2. Estimate of major nuclide composition (by type of waste)

d. Other - (Water)

From Millstone Nuclear Power Station to Duratek Inc., Oak Ridge, TN for Incineration Radionuclide-. 7% of Total :;..i XaCuries'-.,.I H-3 99.47 6.0396E-02 C-14 <0.01 1.3923E-07 Cr-51 Mn-54 <0.01 3.3714E-06 Fe-55 0.07 4.4263E-05 Fe-59 Co-57 <0.01 9.3233E-07 Co-58 0.02 1.4355E-05 Co-60 0.05 2.7923E-05 Ni-59 Ni-63 0.05 3.2216E-05 Zn-65 Sr-89 Sr-90 _ __ _ __ _ _

Nb-94 Zr-95 <0.01 5.1209E-08 Nb-95 <0.01 1.4524E-07 Tc-99 _

Ru-1 03 Ru-1 06 Ag-1 08m Ag-11iOm Sn-113 <0.01 6.0340E-08 Sb-1 24 Sb-1 25 <0.01 4.3944E-07 1-129 1-131 Cs-134 0.12 7.1965E-05 Cs-1 37 0.16 9.9364E-05 Ba-1 40 Ce-141 Ce-144 <0.01 1.0705E-08 U-234 <0.01 8.0405E-07 U-235 U-238 Pu-238 <0.01 4.7745E-08 Pu-239 <0.01 8.4546E-08 Pu-241 <0.01 3.3856E-07 Am-241 0.05 2.8014E-05 Cm-242 Cm-244 <0.01 6.9327E-09

.=<-CURIES (TOTAL) t 6.0720E-02 Dominion Nuclear Connecticut Millstone Power Station Page 9 of 11 Unit 1 Section

2. Estimate of major nuclide composition (by type of waste)

d. Other - (Mixed Waste)

From Millstone Nuclear Power Station to Perma-Fix of Florida, Inc., Gainesville, FL for Stabilization, Fuel Blending, etc.

nI Rndinni it-liricaI-:A.,/nf Tntnl <1.. I (irie.:

C I

-II H-3 0.22 5.5000E-08 C-14 0.05 1.2600E-08 Cr-51 Mn-54 Fe-55 54.09 1.3667E-05 Fe-59 Co-57 Co-58 Co-60 26.78 6.7667E-06 Ni-59 Ni-63 18.86 4.7667E-06 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 Nb-95 Tc-99 Ru-103 Ru-1 06 Ag-1 08m Ag-110m Sn-1 13 Sb-1 24 Sb-125 1-129 1-131 Cs-134 Cs-1 37 <0.01 3.3333E-13 Ba-1 40 Ce-141 Ce-1 44 U-234 U-235 U-238 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-244

.'^;>CURIES(TOTAL)u! tt'.' 2.5268E-05 Dominion Nuclear Connecticut Millstone Power Station Page 10 of 11 Unit 1 Section

3. Solid Waste Disposition (Shipments from Millstone) l1Number of Shipments*. 1;.Mode.of Transportation:-,;c) ,i ,-- r z [ Destination ., i 3 Truck (Sole Use Vehicle) IChem-Nuclear Services LLC, Barnwell, SC 2 Truck (Sole Use Vehicle) lDuratek Inc. - Kingston, TN 9 Truck (Sole Use Vehicle) lDuratek Inc. - Oak Ridge, TN I Truck (Sole Use Vehicle) lPerma-Fix of Florida Inc. - Gainesville FL 1 Truck (Sole Use Vehicle) lStudsvik Processing Center LLC, Erwin, TN

-'=:ndicatesthe nulmber offshipm6entsin iTIiiiich ontainedany.,unit-I 'wastes; -

,(Exam~ple-,'A hiprent 'cotahinr g ste'sfromnhits'i-2dn3 wili be cou'nted once oneac'ahof'the f ' :.-i three unit-specific sections'of,this eport.3 i h nts were a20defrmt stationin2004 B. IRRADIATED FUEL SHIPMENTS (Disposition)

I Number ofShipments- -. Mode of.Transportation - - , Destination jNo Shipments in 2004 1 N/A l NIA I Dominion Nuclear Connecticut Millstone Power Station Page 11 of 11 Unit I Section

Table 2.2-S Solid Waste and Irradiated Component Shipments Millstone Unit 2 January 1, 2004 through December 31, 2004 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Tvye of Waste

a. Spent resins, Filter sludges, Evaporator bottoms, etc.

From Millstone Nuclear Power Station to Duratek Inc., 2.5490E+00 _

Kingston, TN for Super-Compaction, Incineration. etc. N i N>.1 1.0682E-03 l 25%

From Millstone Nuclear Power Station to Duratek Inc.. le e r 2.0800E-01 l Oak Ridge. TN for Super-Compaction. Incineration, etc. I 4.2787E-02 25% l From Millstone Nuclear Power Station to Studsvik 2.3358E+00 lProcessingCenterLLC,Erwin,TNforThermalDestructionIncineration. etc. l 8.6391 E+01 _ _25%_l

b. Dry compressible waste, Contaminated equipment, etc.

From Millstone Nudear Power Station to Duratek Inc., 1.2745E+01 Kingston, TN for Super-Compaction, Incineration, etc. 5.0602E-03 25%

lFrom Millstone Nudlear Power Station to Duratek Inc., lr- l 1095E+02 ll 1Oak Ridge. TN for Super-Compaction. Incineration, etc. l C,. I, 1.2313E+00 25%

c. Irradiated components, Control rods, etc.

From Millstone Nuclear Power Station to Duratek Inc., 4.3600E-01 Oak Ridge. TN for Super-Compaction, Metal Melt, etc. `eCi f..0 2.6262E+00 25%

d. Other - (Grease, Oil, Oily waste)

From Millstone Nuclear Power Station to Duratek Inc., . l 96.2450E-01 l Kingston, TN for Super-Compaction. Incineration, etc. Ah Fl1.1 243E-03 25%

.From Millstone Nucear Power Station to Duratek Inc., 1.2490E+00 lOak Ridge, TNfor Super-Compaction. Incineration, etc. Ifi 3.651 1E-03 t...v . . l ..25%l

d. Other - (Water)

From Millstone Nuclear Power Station to Duratek Inc., 4a.9149E+01 Oak Ridge, TN for Incineration  ! i 1.4820E+00 l 25%

d. Other - (Mixed Waste)

From Millstone Nuclear Power Station to Perma-Fix of Florida, Inc., 1 33L-021 IGainesville, FL for Stabilization, Fuel Blending, etc. 2 68E-05 l25% -

tminion Nuclear Connecticut Millstone Power Station Page 1 of 12 Unit 2 Section

2. Estimate of major nuclide composition (by type of waste) -

a. Spent resins, Filter sludges, Evaporator bottoms, etc.

From Millstone Nuclear Power Station to Duratek Inc., Kingston, TN for Super-Compaction, Incineration, etc.

._ . . 1 H-3 0.61 6.4700E-06 C-14 0.11 1.1800E-06 Cr-51 Mn-54 Fe-55 29.02 3.1 OOOE-04 Fe-59 Co-57 Co-58 3.38 3.61OOE-05 Co-60 19.47 2.0800E-04 Ni-59 Ni-63 24.43 2.61 0OE-04 Zn-65 Sr-89 Sr-90 Nb-94 ______

Zr-95 Nb-95 Tc-99 ______

Ru-1 03 Ru-106 Ag-108m Ag-110m Sn-113 Sb-124 _

Sb-125 1-129 1-131 Cs-134 10.30 1.1 OOOE-04 Cs-1 37 11.98 1.2800E-04 Ba-140 Ce-141 Ce-144 0.39 4.1400E-06 U-234 U-235-U-238 Pu-238 <0.01 4.8500E-08 Pu-239 <0.01 3.8300E-08 Pu-241 0.29 3.0500E-06 Am-241_ <0.01 7.1200E-08 Cm-242 Cm-244 <0.01 6.2600E-08 t t 11.0682E-03 Dominion Nuclear Connecticut Millstone Power Station Page2of 12 Unit 2 Section

2. Estimate of major nuclide composition (by type of waste)

a. Spent resins, Filter sludges, Evaporator bottoms, etc.

From Millstone Nuclear Power Station to Duratek Inc., Oak Ridge. TN for Super-Compaction, Incineration, etc.

FRAd

[I rob IkJI W IRdUflfW 1 ;.t ulet Ž!. jl H-3 1.09 4.6500E-04 C-14 1.28 5.4600E-04 Cr-51 Mn-54 0.73 3.1100E-04 Fe-55 49.31 2.1100E-02 Fe-59 Co-57 __ _ _ _ _

Co-58 Co-60 25.24 1.0800E-02 Ni-59 _ _ _ _ _ _

Ni-63 19.12 8.1800E-03 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 _ _ _ _ _ _

Nb-95 Tc-99 Ru-103 Ru-1 06 Ag-108m Ag-t1Om 0.74 3.1500E-04 Sn-113 Sb-1 24 Sb-125 1-129 <0.01 1.21 OOE-06 1-131 Cs-134 0.62 2.6700E-04 Cs-1 37 0.68 2.9000E-04 Ba-140 Ce-1 41 Ce-144 0.83 3.5600E-04 U-234 _

U-235 U-238 Pu-238 <0.01 3.1900E-06 Pu-239 <0.01 1.2800E-06 Pu-241 0.33 1.41 OOE-04 Am-241 <0.01 2.3600E-06 Cm-242 <0.01 3.2000E-06 Cm-244 0.01 4.4900E-06 W,3.1:1J3IESW,ATA. 4.2787E-02 Dominion Nuclear Connecticut Millstone Power Station Page 3 of 12 Unit 2 Section

2. Estimate of major nuclide composition (by type of waste)

a. Spent resins, Filter sludges, Evaporator bottoms, etc.

From Millstone Nuclear Power Station to Studsvik Processing Center LLC, Erwin. TN for Thermal Destruction, Incineration, etc.

I .RA556656 s1b~otbiij tes.:1 jqCu H-3 0.02 1.8524E-02 C-14 0.16 1.4100E-01 Cr-51 <0.01 3.0997E-1 6 Mn-54 0.57 4.9245E-01 Fe-55 14.33 1.2379E+01 Fe-59 <0.01 1.1071E-11 Co-57 0.01 1.0546E-02 Co-58 0.06 5.0964E-02 Co-60 9.27 8.0066E+00 Ni-59 Ni-63 34.26 2.9599E+01 Zn-65 Sr-89 <0.01 4.9876E-06 Sr-90 0.04 3.0878E-02 Nb-94 Zr-95 <0.01 5.3313E-04 Nb-95 <0.01 1.6722E-06 Tc-99 <0.01 1.1012E-06 Ru-103 <0.01 6.5840E-16 Ru-106 Ag-108m Ag-11 Om <0.01 1.6955E-04 Sn-113 <0.01 2.7676E-03 Sb-124 <0.01 2.0859E-10 Sb-125 0.99 8.5114E-01 1-129 <0.01 3.1930E-04 1-131 Cs-1 34 15.55 1.3435E+01 Cs-137 24.38 2.1061 E+01 Ba-1 40 Ce-141 Ce-144 0.30 2.5874E-01 U-234 U-235 U-238 Pu-238 <0.01 1.2207E-03 Pu-239 <0.01 6.1649E-04 Pu-241 0.05 4.6290E-02 Am-241 <0.01 1.3528E-03 Cm-242 <0.01 2.1790E-04 Cm-244 <0.01 1.6958E-03

, WBIE% .B qi 8.6391 E+01 Dominion Nuclear Connecticut Millstone Power Station Page 4 of 12 Unit 2 Section

2. Estimate of major nuclide composition (by type of waste)

b. Dry compressible waste, Contaminated equipment, etc.

From Millstone Nuclear Power Station to Duratek Inc., Kingston, TN for Super-Compaction, Incineration, etc.

si, . 1 H-3 0.60 3.0370E-05 C-14 0.11 5.5190E-06 Cr-51 Mn-54 Fe-55 29.03 1.4690E-03 Fe-59 Co-57 Co-58 3.83 1.9380E-04 Co-60 19.41 9.8200E-04 Ni-59 _ __ _ __ _ _

Ni-63 24.21 1.2250E-03 Zn-65 _

Sr-89 Sr-90 Nb-94 Zr-95 _

Nb-95 Tc-99 Ru-1 03 Ru-1 06 Ag-108m Ag-11Om Sn-113 Sb-1 24 Sb-125 1-129 1-131 Cs-134 10.28 5.201 OE-04 Cs-1 37 11.84 5.9900E-04 Ba-140 Ce-141 Ce-1 44 0.40 2.0080E-05 U-234 U-235 U-238 Pu-238 <0.01 2.2750E-07 Pu-239 <0.01 1.7960E-07 Pu-241 0.28 1.431 OE-05 Am-241 <0.01 3.3370E-07 Cm-242 Cm-244 <0.01 2.9360E-07 4,1..-181,j Ii fQ,4A. 4.)n 5.0602E-03 Dominion Nuclear Connecticut Millstone Power Station Page 5 of 12 Unit 2 Section

2. Estimate of major nuclide composition (by type of waste)

b. Dry compressible waste, Contaminated equipment, etc.

From Millstone Nuclear Power Station to Duratek Inc., Oak Ridge, TN for Super-Compaction, Incineration, etc.

_oi~i~ldgbt~l>.-;k  :. cr~iea...Trl H-3 0.61 7.4908E-03 C-14 0.11 1.3701 E-03 Cr-51 Mn-54 <0.01 2.5750E-05 Fe-55 28.88 3.5559E-01 Fe-59 Co-57 Co-58 3.30 4.0656E-02 Co-60 19.54 2.4062E-01 Ni-59 Ni-63 24.68 3.0392E-01 Zn-65 Sr-89 Sr-90 Nb-94 _

Zr-95 Nb-95 Tc-99 Ru-103 Ru-106 Ag-108m Ag-110m Sn-113 Sb-1 24 Sb-125 1-129 1-131 Cs-1 34 10.15 1.2495E-01 Cs-137 12.04 1.4830E-01 Ba-140 Ce-141 Ce-1 44 0.38 4.6338E-03 U-234 U-235 U-238 Pu-238 <0.01 5.6740E-05 Pu-239 <0.01 4.4704E-05 Pu-241 0.29 3.5370E-03 Am-241 <0.01 8.3320E-05 Cm-242 __ ___

Cm-244 <0.01 7.2885E-05

YI 1.2313E+00 Dominion Nuclear Connecticut Millstone Power Station Page 6 of 12 Unit 2 Section

2. Estimate of major nuclide composition (by type of waste)

c. Irradiated components, Control rods, etc.

From Millstone Nuclear Power Station to Duratek Inc., Oak Ridge. TN for Super-Compaction, Metal Melt, etc.

lNt:'.Rid idn'tilid& Y/0'1f1'Tbit'A Li,;

< t.S9~tes.7.>-I G I I H-3 <0.01 9.9080E-05 C-14 <0.01 9.1 840E-05 Cr-51 1.70 4.4660E-02 Mn-54 0.60 1.5693E-02 Fe-55 17.21 4.5203E-01 Fe-59 0.05 1.2199E-03 Co-57 Co-5B 15.58 4.0914E-01 Co-60 4.15 1.0889E-01 Ni-59 0.49 1.2903E-02 Ni-63 59.95 1.5744E+0O Zn-65 Sr-89 Sr-90 Nb-94 <0.01 1.5600E-06 Zr-95 Nb-95 Tc-99 Ru-103 Ru-106 Ag-1 08m Ag-11 Om Sn-113 Sb-1 24 Sb-1 25 1-129 1-131 _

Cs-134 Cs-137 0.25 6.6390E-03 Ba-1 40 Ce-141 Ce-144 <0.01 2.2159E-04 U-234 U-235 _

U-238 Pu-238 <0.01 2.5112E-06 Pu-239 <0.01 1.9849E-06 Pu-241 <0.01 1.5842E-04 Am-241 <0.01 3.6875E-06 Cm-242 Cm-244 <0.01 3.2639E-06

_IE __ ,______

_ ____ 2.6262E+00 Dominion Nuclear Connecticut Millstone Power Station Page 7 of 12 Unit 2 Section

2. Estimate of major nuclide composition (by type of waste)

d. Other - (Grease, Oil, Oily waste)

From Millstone Nuclear Power Station to Duratek Inc., Kingston, TN for Super-Compaction, Incineration, etc.

IIt at> ttCrihes - L I H-3 0.20 2.2500E-06 C-14 0.04 4.8600E-07 Cr-51 Mn-54 1.39 1.5650E-05 Fe-55 46.25 5.2000E-04 Fe-59 Co-57 Co-58 1.45 1.6300E-05 Co-60 23.04 2.5900E-04 Ni-59 Ni-63 16.37 1.8400E-04 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 Nb-95 Tc-99 Ru-1 03 Ru-1 06 Ag-i 08m Ag-1 10Om Sn-113 Sb-1 24 Sb-125 1-129 1-131 Cs-1 34 2.79 3.1350E-05 Cs-137 7.87 8.8500E-05 Ba-140 _

Ce-1 41 Ce-144 0.16 1.7850E-06 U-234 U-235 U-238 __ _ __ _ _

Pu-238 0.01 1.5500E-07 Pu-239 <0.01 8.3500E-08 Pu-241 0.39 4.3550E-06 Am-241 0.02 2.7650E-07 Cm-242 Cm-244 0.01 1.4750E-07 lL 01! 1.1243E-03 Dominion Nuclear Connecticut Millstone Power Station Page 8 of 12 Unit 2 Section

2. Estimate of major nuclide composition (by type of waste)

d. Other - (Grease, Oil, Oily waste)

From Millstone Nuclear Power Station to Duratek Inc., Oak Ridge, TN for Super-Compaction, Incineration, etc.

• _lr::s.4. ._.A H-3 0.63 2.31 OOE-05 C-14 0.12 4.2700E-06 Cr-51 Mn-54 Fe-55 28.76 1.0500E-03 Fe-59 Co-57 Co-58 1.43 5.21 OOE-05 Co-60 20.05 7.3200E-04 Ni-59 Ni-63 25.80 9.4200E-04 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 Nb-95 Tc-99 Ru-103 Ru-106 _

Ag-1 08m Ag-110m Sn-i133 Sb-124 Sb-125 1-129 1-131 Cs-134 9.97 3.6400E-04 Cs-137 12.60 4.6000E-04 Ba-140 Ce-141 Ce-144 0.33 1.1900E-05 U-234 U-235 _

U-238 Pu-238 <0.01 1.7500E-07 Pu-239 <0.01 1.3900E-07 Pu-241 0.30 1.09OOE-05 Am-241 <0.01 2.5700E-07 Cm-242 Cm-244 <0.01 2.2400E-07 QU PIS OLq 3.6511 E-03 Dominion Nuclear Connecticut Millstone Power Station Page 9 of 12 Unit 2 Section

2. Estimate of major nuclide composition (by type of waste)

d. Other -(Water)

From Millstone Nuclear Power Station to Duratek Inc., Oak Ridge, TN for Incineration IIIRH; r r-I I2 ,f'-Tnfr ~ I r~. .An i1 H-3 98.74 1.4633E+00 C-14 <0.01 1.8896E-05 Cr-51 Mn-54 0.01 2.1829E-04 Fe-55 0.35 5.1345E-03 Fe-59 Co-57 <0.01 7.4338E-05 Co-58 0.03 5.1396E-04 Co-60 0.23 3.4030E-03 Ni-59 Ni-63 0.28 4.2055E-03 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 <0.01 1.9333E-07 Nb-95 <0.01 5.4867E-07 Tc-99 Ru-1 03 Ru-106 Ag-1 08m Ag-11 Om <0.01 1.9890E-05 Sn-113 <0.01 2.2792E-07 Sb-124 Sb-125 0.01 1.9813E-04 1-129 1-131 <0.01 1.3005E-04 Cs-1 34 0.13 1.9288E-03 Cs-1 37 0.18 2.6694E-03 Ba-140 Ce-1 41 Ce-1 44 <0.01 6.2653E-08 U-234 <0.01 5.6807E-06 U-235 U-238 Pu-238 <0.01 1.1445E-06 Pu-239 <0.01 1.1165E-06 Pu-241 <0.01 4.9236E-05 Am-241 <0.01 1.2887E-04 Cm-242 Cm-244 <0.01 1.0157E-06

-,1M13 S t3LFj: 1.4820E+00 Dominion Nuclear Connecticut Millstone Power Station Page 10 of 12 Unit 2 Section

2. Estimate of major nuclide composition. (by type of waste)

d. Other -(Mixed Waste)

From Millstone Nuclear Power Station to Perma-Fix of Florida. Inc., Gainesville. FL for Stabilization, Fuel Blending, etc.

If .z Curies":4i ,

H-3 0.22 5.5000E-08 C-14 0.05 1.2600E-08 Cr-51 Mn-54 Fe-55 54.09 1.3667E-05 Fe-59 Co-57 Co-58 Co-60 26.78 6.7667E-06 Ni-59 __ _ _ _ _

Ni-63 18.86 4.7667E-06 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 Nb-95 Tc-99 Ru-103 Ru-106 Ag-1 08m Ag-11iOm Sn-113 Sb-124 Sb-1 25 1-129 __ _ _ _

1-131 Cs-1 34 Cs-137 <0.01 3.3333E-13 Ba-140 Ce-1 41 .

Ce-1 44 U-234 U-235 U-238 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-244 __

- .2.5268E-05 Dominion Nuclear Connecticut Millstone Power Station Page 11 of 12 Unit 2 Section

3. Solid Waste Disposition (Shipments from Millstone) 1[Numbertof;Shipments1 1 AMode tf4rTfats dtIVdT,-fF '-. -

77A, 4:, tDestinationlt

• M>.5$

1 2 l Truck (Sole Use Vehicle) lDuratek Inc. - Kingston, TN 12 Truck (Sole Use Vehicle) TDuratek Inc. - Oak Ridge, TN 1 Truck (Sole Use Vehicle) lPerma-Fix of Florida Inc. - Gainesville FL 2 Truck (Sole Use Vehicle) lStudsvik Processing Center LLC - Erwin, TN l r,t'"' cat Xrt~i

§"7'ai b'eF;Q'coui~ES t.d§ Mef th

= Q

^:this #>&:..'^.-'9}~t~',i'"it..'5.'r"pi-;st;."X'V<-a.<.'t<ettb..n*'~i'~ltt;.

B. IRRADIATED FUEL SHIPMENTS (Disposition) l*Number~ofShi nmentshx`'ModeoffTransp rS - t.;--Destirnatior ri -i2 No Shipments in 2004 l N/A I N/A I Dominion Nuclear Connecticut Millstone Power Station Page 12 of 12 Unit 2 Section

Table 2.3-S Solid Waste and Irradiated Component Shipments Millstone Unit 3 January 1, 2004 through December 31, 2004 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of Waste

a. Spent resins, Filter sludges, Evaporator bottoms, etc.

Dsp6 niti a Tbttils~!,'A Est---6tW

- ~ p~Fl$Ttals'~'EsITo From Millstone Nuclear Power Station to Duratek Inc.. - F,, 4.9870E+00 KinstonTN for Super.Compaction. Incineration. etc. ;fCif5~(z 3.9111 E-01 1 25%

From Millstone Nuclear Power Station to Duratek Inc., lim? 4.2130E+00 Jl 1Oak Ridge, TN for Super-Compaction. Incineration, etc. l3-Ci 4.4648E+00 1 25%

From Millstone Nuclear Power Station to Studsvik m 4.5386E+00 Processing Center LLC, Erwin. TN for Thermal Destruction. Incineration, etc. r.-1Ci 2: i 6.6401 E+01 l 25%_ _

b. Dry compressible waste, Contaminated equipment, etc.

From Millstone Nuclear Power Station to Duratek Inc.,

Kingston, TN for Super-Compaction, Incineration. etc.

From Millstone Nuclear Power Station to Duratek Inc.,

1.4r l

fasfl

>-Wl 2.2941 E+01 1.2168E-02 1.5293E+02 l

J 25%

0 1Oak Ridge. TN for Super-Compaction, Incineration, etc. lC~'i1 2.8663E+00 l 25%

c. Irradiated components, Control rods, etc.

- No shipments during this report period - _______ n/a

_ _ _ _ _ _ _ _ _ _ _ _n/a n/a

d. Other - (Grease, Oil, Oily waste)

From Millstone Nuclear Power Station to Duratek Inc..,a?4Mae> 6.2450E-01 Kingston, TNlforSuper-Compaction,lIncineration. etc. ti tI~o; 1.1243E-03 25%

d. Other - (Water)

From Millstone Nuclear Power Station to Duratek Inc., rZfM 31W 4.6548E+01 Oak Pidge, TN for Incineration I$3Gm1 3.1411 E-01 25%

d. Other - (Mixed Waste)

From Millstone Nulear Power Station to Pemia-x of Florda, Inc., Ci 1.3333E-02 2 Gainesville, FL for Stabilization, Fuel Blending, etc. - 3i 2.5268E-05 l 25%

Dominion Nuclear Connecticut Millstone Power Station Page 1 of 10 Unit 3 Section

2. Estimate of major nuclide composition (by type of waste)

a. Spent resins, Filter sludges, Evaporator bottoms, etc.

From Millstone Nuclear Power Station to Duratek Inc., Kinston. TN for Super-Compaction, Incineration, etc.

H-3 1.12 4.3868E-03 C-14 0.03 1.0200E-04 Cr-51 Mn-54 2.90 1.1347E-02 Fe-55 74.33 2.9073E-01 Fe-59 Co-57 0.07 2.5900E-04 Co-58 2.44 9.5444E-03 Co-60 9.85 3.8528E-02 Ni-59 Ni-63 8.13 3.1780E-02 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 0.17 6.7800E-04 Nb-95 0.36 1.3900E-03 Tc-99 Ru-103 _ _

Ru-106 Ag-108m Ag-110m Sn-1 13 Sb-124 Sb-125 0.33 1.2746E-03 1-129 1-131 Cs-134 Cs-1 37 0.06 2.2742E-04 Ba-140 Ce-141 Ce-144 0.21 8.2700E-04 U-234 U-235 _

U-238 Pu-238 <0.01 4.5600E-07 Pu-239 <0.01 3.6500E-07 Pu-241 <0.01 3.5800E-05 Am-241 <0.01 5.3500E-07 Cm-242 <0.01 2.11 OOE-06 Cm-244 <0.01 1.9400E-06 EW.O-_U:ta 3.9111 E-01 Dominion Nuclear Connecticut Millstone Power Station Page 2 of 10 Unit 3 Section

2. Estimate of major nuclide composition (by type of waste)

a. Spent resins, Filter sludges, Evaporator bottoms, etc.

From Millstone Nuclear Power Station to Duratek Inc., Oak Ridge, TN for Super-Compaction. Incineration, etc.

NE R d i Al l ii H-3 0.40 1.7892E-02 C-14 <0.01 1.6870E-04 Cr-51 Mn-54 2.52 1.1231E-01 Fe-55 69.00 3.0806E+00 Fe-59 Co-57 0.04 1.9630E-03 Co-58 0.47 2.0969E-02 Co-60 14.21 6.3450E-01 Ni-59 Ni-63 12.61 5.6316E-01 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 0.02 7.9500E-04 Nb-95 0.04 1.9619E-03 Tc-99 Ru-103 Ru-106 Ag-108m Ag-11 Om Sn-113 Sb-124 Sb-1 25 0.42 1.8689E-02 1-129 1-131 Cs-134 Cs-137 0.05 2.3728E-03 Ba-140 Ce-1 41 Ce-144 0.18 8.241 OE-03 U-234 U-235 U-238 Pu-238 <0.01 1.9486E-05 Pu-239 <0.01 5.71OOE-06 Pu-241 0.02 1.0743E-03 Am-241 <0.01 1.2735E-05 Cm-242 <0.01 8.3330E-06 Cm-244 <0.01 3.5845E-05

,FQ.WlSIEST LISMiN 4.4648E+00 Dominion Nuclear Connecticut Millstone Power Station Page 3 of 10 Unit 3 Section

2. Estimate of major nuclide composition (by type of waste)

a. Spent resins, Filter sludges, Evaporator bottoms, etc.

From Millstone Nuclear Power Station to Studsvik Processing Center LLC, Erwin, TN for Thermal Destruction, Incineration, etc.

114Radiont clid6ll bfiThTa lt-akN.I uriesl ii H-3 0.09 5.7888E-02 C-14 0.12 7.7061 E-02 Cr-51 <0.01 1.6729E-16 Mn-54 5.40 3.5845E+00 Fe-55 25.76 1.7105E+01 Fe-59 <0.01 5.9746E-12 Co-57 0.22 1.4569E-01 Co-58 0.69 4.6000E-01 Co-60 13.55 8.9942E+00 Ni-59 Ni-63 49.09 3.2598E+01 Zn-65 Sr-89 <0.01 2.6917E-06 Sr-90 <0.01 4.9307E-03 Nb-94 Zr-95 <0.01 2.8772E-04 Nb-95 <0.01 9.0247E-07 Tc-99 <0.01 5.9431 E-07 Ru-103 <0.01 3.5533E-16 Ru-106 =

Ag-108m Ag-11Om <0.01 9.1505E-05 Sn-113 <0.01 1.4936E-03 Sb-1i24 <0.01 1.1 257E-1 0 Sb-125 3.20 2.1254E+00 1-129 <0.01 1.7232E-04 1-131 Cs-1 34 0.52 3.4275E-01 Cs-137 0.90 5.9654E-01 Ba-1 40 Ce-1 41 Ce-144 0.42 2.8119E-01 U-234 U-235 U-238 Pu-238 <0.01 5.3555E-04 Pu-239 <0.01 3.0076E-04 Pu-241 0.04 2.3257E-02 Am-241 <0.01 6.5720E-04 Cm-242 <0.01 1.2599E-04 Cm-244 <0.01 8.4595E-04

% j S111R 36.6401 E+01 Dominion Nuclear Connecticut Millstone Power Station Page 4 of 10 Unit 3 Section

2. Estimate of major nuclide composition (by type of waste)

b. Dry compressible waste, Contaminated equipment, etc.

From Millstone Nuclear Power Station to Duratek Inc., Kingston. TN for Super-Compaction, Incineration, etc.

il*RoHEml1lr84 1i;wt-tTI-<11 J¢ i.,..!s++*t

'II H-3 6.28 7.6470E-04 C-14 __ _

Cr-51 Mn-54 3.10 3.7720E-04 Fe-55 50.92 6.1960E-03 Fe-59 Co-57 Co-58 0.79 9.6698E-05 Co-60 23.44 2.8520E-03 Ni-59  ; -

Ni-63 13.12 1.5960E-03 Zn-65  ; -

Sr-89 Sr-90 Nb-94 Zr-95 Nb-95 Tc-99 Ru-103 Ru-106 Ag-1 08m Ag-1 1_Om Sn-113 ;_; -

Sb-124 Sb-125 1.73 2.1060E-04 1-129 1-131 Cs-134 Cs-137 0.61 7.4600E-05 Ba-140 Ce-141 Ce-144 U-234 U-235  ;

U-238 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-244 E .!3lL)

>Xf,<X+ .fl ri '1.2168 E-02 Dominion Nuclear Connecticut Millstone Power Station Page 5 of 10 Unit 3 Section

2. Estimate of major nuclide composition (by type of waste)

b. Dry compressible waste, Contaminated equipment, etc.

From Millstone Nuclear Power Station to Duratek Inc., Oak Ridge, TN for Super-Compaction. Incineration, etc.

Ii =Radionti1tid'I -t1Wobfi% 1TtAl t I H TIl H-3 5.82 1.6677E-01 C-14 <0.01 2.5819E-05 Cr-51 Mn-54 2.58 7.4068E-02 Fe-55 51.56 1.4778E+00 Fe-59 Co-57 <0.01 2.8600E-05 Co-58 0.32 9.0818E-03 Co-60 21.49 6.1605E-01 Ni-59 Ni-63 13.83 3.9653E-01 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 <0.01 1.3071 E-04 Nb-95 <0.01 3.11 OOE-06 Tc-99 Ru-1 03 Ru-106 Ag-108m .

Ag-11 Om Sn-113 Sb-1 24 Sb-125 1.31 3.7565E-02 1-129 1-131 Cs-134 <0.01 1.2045E-04 Cs-1 37 3.07 8.7955E-02 Ba-140 Ce-1 41 Ce-144 <0.01 1.0080E-04 U-234 U-235 U-238 __ __ __ _

Pu-238 <0.01 7.4950E-07 Pu-239 <0.01 4.3135E-07 Pu-241 <0.01 2.5930E-05 Am-241 <0.01 1.2730E-06 Cm-242 <0.01 1.4200E-07 Cm-244 <0.01 1.0440E-06 7 ' 3J S tL 2.8663E+00 Dominion Nuclear Connecticut Millstone Power Station Page 6 of 10 Unit 3 Section

2. Estimate of major nuclide composition (by type of waste)

d. Other - (Grease, Oil, Oily waste)

From Millstone Nuclear Power Station to Duratek Inc., Kingston, TN for Super-Compaction. Incineration, etc.

11'Rad iO tru Iid~l NW/.1f ffbtl l%4-4i--X I- Uribi 4.1;e.'tf H-3 0.20 2.2500E-06 C-1 4 0.04 4.8600E-07 Cr-51 Mn-54 1.39 1.5650E-05 Fe-55 46.25 5.2000E-04 Fe-59 Co-57 Co-58 1.45 1.6300E-05 Co-60 23.04 2.5900E-04 Ni-59 Ni-63 16.37 1.8400E-04 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 Nb-95 Tc-99 Ru-103 Ru-1 06 Ag-108m Ag-110Om Sn-113 Sb-1 24 Sb-125 1-129 1-131 Cs-134 2.79 3.1350E-05 Cs-1 37 7.87 8.8500E-05 Ba-140 Ce-141 Ce-144 0.16 1.7850E-06 U-234 U-235 U-238 Pu-238 0.01 1.5500E-07 Pu-239 <0.01 8.3500E-08 Pu-241 0.39 4.3550E-06 Am-241 0.02 2.7650E-07 Cm-242 Cm-244 0.01 1.4750E-07

• iCU~itE$5(WU)3 1.1 243E-03 Dominion Nuclear Connecticut Millstone Power Station Page 7 of 10 Unit 3 Section

2. Estimate of major nuclide composition (by type of waste)

d. Other - (Water)

From Millstone Nuclear Power Station to Duratek Inc., Oak Ridge, TN for Incineration

. i _ _ __ _.1__ _

l H-3 98.45 3.0924E-01 C-14 <0.01 3.5912E-06 Cr-51 Mn-54 0.02 7.2162E-05 Fe-55 0.36 1.1408E-03 Fe-59 Co-57 <0.01 1.4771 E-05 Co-58 0.06 2.0013E-04 Co-60 0.23 7.1887E-04 Ni-59 Ni-63 0.26 8.3090E-04 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 <0.01 7.1981 E-07 Nb-95 <0.01 2.0420E-06 Tc-99 Ru-1 03 Ru-106 Ag-108m Ag-11 Om <0.01 3.51 OOE-06 Sn-113 <0.01 8.4829E-07 Sb-124 Sb-125 0.01 4.6900E-05 1-129 _

1-131 <0.01 2.2950E-05 Cs-134 0.16 5.0451 E-04 Cs-137 0.26 8.0105E-04 Ba-140 Ce-141 Ce-144 <0.01 2.2822E-07 U-234 <0.01 2.0551 E-05 U-235 U-238 Pu-238 <0.01 1.4549E-06 Pu-239 <0.01 1.9371 E-06 Pu-241 <0.01 9.7075E-06 Am-241 0.15 4.7059E-04 Cm-242 Cm-244 <0.01 2.0971 E-07

'W I ;3.1411 E-01 Dominion Nuclear Connecticut Millstone Power Station Page 8 of 10 Unit 3 Section

2. Estimate of major nuclide composition (by type of waste)

d. Other - (Mixed Waste)

From Millstone Nuclear Power Station to Perma-Fix of Florida, Inc., Gainesville, FL for Stabilization, Fuel Blending, etc.

ll4Radion iclicdi btetrStak l^>Cur

_______ es; ;-I4 l H-3 0.22 5.5000E-08 C-1 4 0.05 1.2600E-08 Cr-51 Mn-54 Fe-55 54.09 1.3667E-05 Fe-59 Co-57 Co-58 Co-60 26.78 6.7667E-06 Ni-59 Ni-63 18.86 4.7667E-06 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 Nb-95 Tc-99 Ru-103 Ru-1 06 Ag-108m Ag-1i1 Om Sn-113 Sb-124 Sb-125 1-129 1-131 Cs-1 34 Cs-1 37 <0.01 3.3333E-13 Ba-1 40 Ce-141 Ce-1 44 U-234 U-235 U-238 Pu-238 Pu-239 Pu-241 Am-241 .

Cm-242 Cm-244 i.% 2.5268E-05 Dominion Nuclear Connecticut Millstone Power Station Page 9 of 10 Unit 3 Section

3. Solid Waste Disposition (Shipments from Millstone)

}gNm-e'f~ mefltst-.4aMode-'of;Trans otatoikn~ev~rD;Q^ >>wg^Detntin I2:,

2 Truck (Sole Use Vehicle) Duratek Inc. - Kingston, TN 13 Truck (Sole Use Vehicle) lDuratek Inc. - Oak Ridge, TN 1 Truck (Sole Use Vehicle) lPerma-Fix of Florida Inc. - Gainesville FL 2 Truck (Sole Use Vehicle) lStudsvik Processing Center LLC - Erwin, TN hree f repo) a shiICments were made from .this station B. IRRADIATED FUEL SHIPMENTS (Disposition)

I Numbe'r..of.DShipaentsi tItid i oMode6o4TlraZs INo Shipments in 2004 1 N/A I N/A I Dominion Nuclear Connecticut Millstone Power Station Page 10 of 10 Unit 3 Section

3.0 REMODCM Changes In 2004, the following changes were made to the Millstone REMODCM:

Rev Effective Date 24-02 April 1, 2004 (Non-intent administrative change)

The description and the bases of the change(s) for each REMODCM revision are included in Volume I of this report. In addition, a complete copy of the REMODCM revision(s) for the calendar year 2004 is provided to the Nuclear Regulatory Commission as Volume II of this report.

REMODCM Rev 24-02 Description of Changes

'OrDminion-Memo SORC Summary Unit: NA Document: REMODCM (MP-22-REC-BAP01)

Presenter: Claude Flory (ext. 2337)

Date: 3/11/04 Length: 10 minutes An administrative change is being made to the REMODCM to change the designation from MP-22-REM-BAP01 to MP-22-REC-BAPO1, to change references to documents which have had their designations changed, and to make the corrections listed below:

I) "Figure l.C-2" on Page 22 and in TOC is corrected to "Figure l.C-1 ",

2) Name of REMP sample location #72 is corrected from "Background Well" to "Onsite Well" on Page 43, and

3) Corrected title of reference on Page 68.

REMODCM Change Request - Routing and Cover Sheet Change Request Number #: Page _ of 3 II. Technical Reviews:

a- .Z/ / Approve E Disapprove [3 Man r, dical Protection and Chemistry Date

,/ ,y MO R-ad z,*&.zevee tepid n /tApprove 2/Disapprove E S sor - Radiological Engineering Date III. S&C Review: A Meeting No.

Unreviewed Radi logical nvironmental Impact (Bases Attached) Yes El No E 6 /1oy Approve [i3Disapprove El SORC Cairman Date IV. Management proval:

i/ 3~ / 6- £ 4 ApproveETapprove El Site V ce Resident -Millstone Date V. Imple tation: Verify that the affected document changes have been approved.

Effective date of REMODCM revisio Supervisor - Radi lo al Engineering Section (NFE) Date VI. Distribution: C an e sent to Docunnt trol distribution Supervisor - Radiological E ginering Section (NFE) Date VII. Documentation: In Annual flu t R VA (o eparate submittal to NRC)

Supervisor -Radiological Ynneering Section (NFE) Date MP-22-REC-FAPOl .1-001 Rev. 000 I 2 of 3

4.0 Inoperable Effluent Monitors During the period January 1 through December 31, 2004, the following effluent monitors were inoperable for more than 30 consecutive days:

4.1 Unit I -None 4.2 Unit 2- None 4.3 Unit 3 - None

5.0 Errata Unit 2 - Table 2.2-A6 - The Fission & Activation Gases Total Activity did not include Xe-1 33.

The corrected Total Activity is 3.1 5E-01. See attached corrected Table 2.2-A6.

Unit 3 - Table 2.3-A6 - The Table indicated 2002 rather than 2003. See attached corrected Table 2.3-A6.

Table 2.2-A6 Millstone Unit No. 2 Airborne Effluents - Ground Batch - Containment Equipment Hatch Nuclides I Released I Units r st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total I A. Fission & Activation Gases Ar-41 Ci --

Kr-85 Ci -

Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-131m Ci Xe-I 33 Ci 3.07E-01 3.07E-01 Xe-1 33m Ci Xe-1 35 Ci 7.53E-03 7.53E-03 Xe-135m Ci Total Activity I Ci I 3.15E-01 3.15E-01 B. lodines 1-131 Ci - l 6.94E-07 6.94E-07 1-133 aCi - - 9.22E-07 9.22E-07 Total Activity I Ci - - - J 1.62E-06 1.62E-06 C. Particulates 1-131 Ci - .

Co-58 Ci 9.99E-09 1.52E-08 Cs-I 37 Ci 9.97E-09 9.97E-09 Total Activity Ci I - - 2.OOE-08 1 2.52E-08 D. Gross Alpha lGross Alpha Ci - - - - N/D E. Tritium lH-3 ICi - - I - - N/D N/D = Not Detected

Table 2.3-A6 Millstone Unit No. 3 Airborne Effluents - Elevated Continuous - Gaseous Waste System

& Containment Vents Nuclides I Released I Units l stQtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total I A. Fission & Activation Gases Ar-41 Ci I 1.09E-02 1.63E-02 5.43E-04 1.87E-02 4.64E-02 Kr-85m Ci 3.53E-03 3.51 E-05 3.57E-03 Kr-87 Ci 5.18E-03 5.18E-03 Kr-88 Ci 6.89E-03 6.89E-03 Xe-133 Ci 4.33E-03 2.34E-03 1.80E-03 7.53E-03 1.60E-02 Xe-135 Ci 2.80E-03 8.81 E-04 1.49E-04 2.40E-03 6.23E-03 Xe-I 35m Ci 2.OOE-02 _ 2.OOE-02 Xe-I 38 Ci 8.40E-03 8.40E-03 Total Activity Ci I 6.20E-02 1.95E-02 1 2.49E-03 2.86E-02 1.13E-01 B. lodines 1-131 1-133

[

lCiI Ci l -

Total Activity I.Ci. I - I - I - T - NOD C. Particulates 1-131 Ci Co-58 Ci 1.74E-07 1.74E-07 Co-60 Ci 1.43E-07 2.79E-07 4.22E-07 Cr-51 Ci -

Cs-1 37 Ci Mn-54 Ci 5.68E-08 5.68E-08 Nb-95 Ci Ru-106 Ci Zr-95 Ci Br-82 Ci 9.43E-06 1.08E-05 2.02E-05 Total Activity Ci 3.74E-07 - I 9.43E-06 1.11 E-05 I 2.09E-05 D. Gross Alpha lGross Alpha I Ci I - - I N/D E. Tritium I H-3 Ci I 6.60E-01 1 2.43E+00 1 7.49E-01 1.27E+00 5.11E+0l N/D = Not Detected