ML031270082

Radioactive Effluent Release Report. Volume 1. Enclosure 1 Through Table 2.3-11

ML031270082
Person / Time
Site:	Millstone
Issue date:	12/31/2002
From:	Dominion Nuclear Connecticut
To:	NRC/FSME
References
B18875
Download: ML031270082 (88)

Text

Docket Nos. 50-245 50-336 50-423 B18875 Enclosure 1 Millstone Power Station, Unit Nos. 1, 2 and 3 2002 Radioactive Effluent Release Report, Volume I

Millstone Power Station 2002 Radioactive Effluent Release Report Volume I

<Gaseous Effluentsd r7..

Liquid t) -'-:A oEffluents Dominion Nuclear Connecticut, Inc.

MILLSTONE UNIT LICENSE DOCKET I DPR-2 1 50-245 2 DPR-65 50-336

~Dominiow 3 NPF-49 50-423

Millstone Power Station 2002 Radioactive Effluent Release Report Volume I Nesting Ospreys Dominion Nuclear Connecticut, Inc.

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

Table of Contents Volume I List of Tables References Introduction 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 5.0 Errata Volume II 2002 REMODCM Revision 23

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 2.1-1 Unit 1 Airborne Effluents - Release Summary Table 2.1-2 Unit 1 Airborne Effluents - Elevated Continuous Table 2.1-3 Unit 1 Airborne Effluents - Ground Continuous - Balance of Plant Vent (BOP)

& Spent Fuel Pool Island Vent (SFPI)

Table 2.1-4 Unit 1 Liquid Effluents - Release Summary Table 2.1-5 Unit 1 Liquid Effluents - Batch Table 2.1-6 Unit 1 Solid Waste & Irradiated Component Shipments Table 2.2-1 Unit 2 Airborne Effluents - Release Summary Table 2.2-2 Unit 2 Airborne Effluents - Mixed Continuous-Aux Bldg Vent & SGBD Tank Vent

& Spent Fuel Pool Evaporation Table 2.2-3 Unit 2 Airborne Effluents - Mixed Batch-Containment Purges Table 2.2-4 Unit 2 Airborne Effluents - Elevated Batch-WGDT Table 2.2-5 Unit 2 Airborne Effluents - Elevated-Containment Vents Table 2.2-6 Unit 2 Liquid Effluents - Release Summary Table 2.2-7 Unit 2 Liquid Effluents - Continuous-SGBD Table 2.2-8A Unit 2 Liquid Effluents - Batch-LWS Table 2.2-8B Unit 2 Liquid Effluents - Continuous -Turbine Building Sump Table 2.2-9 Unit 2 Solid Waste & Irradiated Component Shipments Table 2.3-1 Unit 3 Airborne Effluents - Release Summary Table 2.3-2 Unit 3 Airborne Effluents - Mixed Continuous-Vent & Spent Fuel Pool Evaporation Table 2.3-3 Unit 3 Airborne Effluents - Ground Continuous-ESF Building Ventilation Table 2.3-4 Unit 3 Airborne Effluents - Mixed Batch-Containment Drawdowns Table 2.3-5 Unit 3 Airborne Effluents - Mixed Batch-Containment Purges Table 2.3-6 Unit 3 Airborne Effluents - Elevated Continuous - GWS & Containment Vents Table 2.3-7 Unit 3 Liquid Effluents - Release Summary - Quarry Table 2.3-8 Unit 3 Liquid Effluents - Continuous - SGBD & SW & TK2 Table 2.3-9 Unit 3 Liquid Effluents - Batch - LWS Table 2.3-10A Unit 3 Liquid Effluents - Batch -CPF Waste Neutralization Sumps & Hotwell Discharge Table 2.3-1OB Unit 3 Liquid Effluents - Release Summary- DSN 006 Table 2.3-1OC Unit 3 Liquid Effluents - Continuous -Turbine Building Sump Table 2.3-1 OD Unit 3 Liquid Effluents - WTT Berm Water Table 2.3-11 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, ORNLINUREG/TDMC-1 User's Manual for LADTAP II - A Computer Program for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents, DB Simpson, BL McGill, prepared by Oak Ridge National Laboratory, Oak Ridge, TN 37830, for Office of Administration, US Nuclear Regulatory Commission, manuscript completed 17 March 1980.

7. 10 CFR Energq, 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 ReasonablV 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. MPWS-03-006, Solid Waste and Irradiated Component Shipments, March 11, 2003.

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

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

12. GASPAR 1i- Technical Reference and User Guide (NUREG/CR-4653), March 1987.

-n Introduction This report, for the period of January through December of 2002, 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 isbeing submitted for all three units because they share some common effluent facilities.

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 any 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.

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

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

The annual capacity factor for Unit 2 was 81.25% based on Design Electrical Rating (DER). Unit 2 was shutdown in the first quarter for 2R14 refueling and maintenance. In August, Unit 2 was temporarily shutdown due to a leak in the charging system.

MP2 - CYCLE 14 & 15 POWER HISTORY YEAR 2002 Note. Data at 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> intervals 80 -

70 - . _ , K 2SHUTDOWN FOR REFUELING-21R14 40 -3CYCLE15 STARTUP B0TURBINE CONTROL VALVE TESTING-

7. MANUAL SHUTDOWN DUE TO PIN HOLE LEAK IN CHARGING f HEADER 20 8 PLANTTRIPDUETOLOWSGLEVELWHEN2-FW-lBCHECK VALVE STUCK OPEN 9 DOWNPOWER TO BACKFLUSH MAIN CONDENSERS -

10 iin POWER REnDUCEDTO gat TO SECURE I CW PUMP FOR

The annual capacity factor for Unit 3 was 86.35% based on Design Electrical Rating (DER). Unit 3 was shutdown in the third quarter for refueling (3R8) and restarted in October 2002. In December, Unit 3 was temporarily shutdown due to a ground fault in the Turbine Main Generator.

MP3 - CYCLE 8 & 9 POWER HISTORY YEAR 2002 Note: Data at 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Intervals 110 - _ia , 0 24gz runa AW 100 90 70 PUM~P 'ABELLOWS JOINT-W FEED PUMP FROM SERVICE DUE TO OIL LEAM WITH TH1E' wu 60 TDFW PUMP ALREADY SECURED FOR SEAL REPLACEME" 0 3. MS REHEAT ISOLATED WHEN PERFORMING A' REHEA

.0TEMPERATURE LOOP CAUIBRATION -POWER REDUCEDIO9/

- BY AUTO ROD INSERTION CONTROL-40 -FLOW BASED 2o9 DOWNPOWER DUE TO MOISTURE SEPARATOR DRAIN PP A 10 GENERATOR GROUND FAULT 0 I N N N N N N N N NNN N N N NNN N N N NNN N N N N N . N N N N N NNN N N oo o o oO o o oo C o O .oor- O)

O O ) .oo O CO O. OU O OO 2 -N N N 2 _ _ 2C _ _ _ ?i 2 C _ C _ _ ° 000 - - - N 0 0 0 O O OO0O00 0 0 0 0O O0 O0 O 0O OO00 0 0 O O O__00

1.0 Doses This report provides a summary of the 2002 off-site radiation doses for releases of radioactive materials in airborne and liquid effluents from Millstone Unit 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. Input parameters for DOSAIR are those used in GASPAR II (Reference 12) and NRC Regulatory Guide 1.109 (Reference 3).

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, dilution factors for liquid effluents, the population distribution and demographic profile surrounding the site by compass sector. 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 (XIQ) and average relative deposition (DIQ) 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.

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). In addition, the Engineered Safety Features Building (ESF) Vent releases are considered as ground level and doses are calculated using 33 ft meteorology.

The doses for these elevated releases were conservatively calculated using mixed mode 142 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), which uses the dose models and parameters cited in NRC Regulatory Guide 1.109 and site specific inputs and produces 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, Gl-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 y/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 XIQ 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 DIQ 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.

Doses were calculated at the cow farm and goat farm of maximum deposition.

To determine compliance with 10CFR50, Appendix I (Reference 7), the maximum individual whole body and organ doses includes 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 In the first quarter of 2002, Unit 2 shutdown for 2R14 refueling and maintenance. As a consequence of small fuel pin leakage, the noble gas and iodine activity concentration in the primary coolant was higher than normal. When the primary systems were opened inside containment during the shutdown period, higher than normal levels of noble gas and iodine were released during containment purging (Table 2.2-3). In addition, Unit 2 shutdown in August due to a pinhole leak in the charging system resulting in higher than normal releases via the Unit 2 Vent. Although offsite doses were higher than normal during these two periods of time, the doses are well below the permissible levels in the REMODCM and the applicable sections of 10CFR50. The quarterly doses are presented in Tables 1-1 and 1-2.

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 40CFRI90 (Reference 8). On-site radioactive waste storage during this year was within storage criteria and the maximum dose to a member of the public was approximately 0.05 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 40CFR1 90.

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 2002 Off-Site Dose Commitments from Airborne Effluents Millstone Units 1, 2, 3 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Max Air (mrad) (mrad) (mrad) (mrad)

Beta O.OOE+00 O.OOE+00 0.002+00 O.OOE+00 Gamma O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Max Individual (mrem) (mrem) (mrem) (mrem)

Whole Body 2.00E-04 6.39E-04 7.79E-04 8.66E-05 Skin 2.11 E-04 6.43E-04 8.64E-04 1.01E-04 Thyroid 1.99E-04 6.26E-04 7.60E-04 8.63E-05 Max organ+ 2.08E-04 7.16E-04 1.41 E-03 8.69E-05 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Max Air (mrad) (mrad) (mrad) (mrad)

Beta 3.76E-02 1.24E-02 1.1 OE-02 7.86E-03

-Gamma 1.19E-02 1.31 E-03 2.14E-03 3.50E-03 Max Individual (mrem) (mrem) (mrem) (mrem)

Whole Body 7.69E-03 1.33E-03 2.48E-03 4.67E-03 Skin 2.29E-02 8.89E-03 7.84E-03 8.45E-03 Thyroid 3.26E-02 7.12E-02 1.34E-01 1.56E-02 Max organ+ 8.03E-03 1.66E-03 2.86E-03 4.74E-03 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Max Air (mrad) (mrad) (mrad) (mrad)

Beta 9.70E-06 5.33E-06 1.51 E-05 2.65E-04 Gamma 2.38E-05 1.21 E-05 1.94E-05 6.63E-05 Max Individual (mrem) (mrem) (mrem) (mrem)

Whole Body 7.51 E-04 2.36E-03 5.20E-03 1.81 E-03 Skin 7.61 E-04 2.36E-03 5.30E-03 1.96E-03 Thyroid 7.51 E-04 2.36E-03 5.15E-03 1.82E-03 Max organ+ 7.51 E-04 2.36E-03 5.27E-03 1.82E-03

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

Table 1-2 2002 Off-Site Dose Commitments from Liquid Effluents Millstone Units 1, 2, 3 1st Quarter I 2nd Quarter 3rd(mrm)

Quarter l 4th(re.

Quarter ndivdua Max (mrm) (rem Max Individual (mrem) (mrem) (mrem) (mrem)

Whole Body 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Thyroid 0,00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Max Oman O.OOF+00 ()-ooF=+nn n nn;:+nn n nn;=.nn 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Max Individual (mrem) (mrem) (mrem) (mrem)

Whole Body 2.78E-04 2.05E-04 3.86E-05 2.69E-05 Thyrld 1.05E-04 3.48E-05 2.74E-05 2.25E-05 Max Organ 3.61 E-03 2.97E-03 2.16E-04 5.15E-05 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Max Individual (mrem) (mrem) (mrem) (mrem)

Whole Body 1.23E-04 2.25E-04 7.31 E-04 4.02E-04 Thyroid 7.62E-05 1.72E-04 3.65E-04 7.20E-05 Max Organ 3.52E-04 3.88E-04 2.89E-03 4.34E-03

Table 1-3 2002 Off-Site Dose Comparison to Limits Millstone Units 1, 2, 3 Airborne Effluents Max Individual Dose vs REMODCM Limits

• .T Whole Body Thyroid Max Organ Skin Beta Air Gamma Air (mrem) (mrem) (mrem) (mrem) (mrad) I (mrad)

Unit I 1.70E-03 1.67E-03 2.42E-03 1.82E-03 O.OOE+00 O.OOE+00 Unit 2 1.62E-02 2.53E-01 1.73E-02 4.81 E-02 6.88E-02 1.88E-02 Unit 3 1.01E-02 1.01E-02 1.02E-02 1.04E-02 2.95E-04 1.22E-04 Millstone Station 2.80E-02 2.65E-01 2.99E-02 6.03E-02 6.91 E-02 1.89E-02

- e-I. I I Liquid Effluents Max Individual Dose vs REMODCM Limits Whole Body Thyroid Max Organ' (mrem) (mrem) (mrem)

Unit I 0.OOE+00 O.OOE+00 0.OOE+00 Unit 2 5.49E-04 1.89E-04 6 85E-03 Unit 3 1.48E-03 6.85E-04 7.98E-03 Millstone Station 2.03E-03 8.74E-04 1.48E-02 F.

Millstone Station Max Individual Dose vs 40CFR190 Limits Whole Body Thyroid Max Organ (mrem) (Mrem) (mrem)

Airborne Effluents 2.80E-02 2.65E-01 2.99E-02 Liquid Effluents 2.03E-03 8.74E-04 1.48E-02 Radwaste Storage 5.OE-02 4.80E-02 4.80E-02 Millstone Station 0.080 0.314 0.09 I }- '

' 10CFR50, Appendix I Guidelines Maximum of the following organs (not including Thyroid) Bone. Gl-LLI, Kidney, Uver, Lung

Table 1-4 2002 Offsite Dose Comparison Millstone Units 1, 2, 3 Natural Background Radiation Dose vs. Radiation Dose from Millstone Station Average Resident Natural Background Radiation Dose * .

Cosmic 27 mrem Cosmogenic 1 mrem Terrestial (Atlantic and Gulf Coastal Plain) 16 mrem Inhaled 200 mrem In the Body .

40 mrem .

Effective Whole Body Dose from Natural Background 284 mrem Maximum Offsite Individual .

Millstone Station Whole Body Dose 0.080 mrem Thyroid Dose 0.314 mrem Effective Whole Body Dose from Millstone Station < 0.1 mrem

• NCRP94

2.0 Radioactivity 2.1 Airborne Effluents 2.1.1 Measurement of Radioactivity 2.1.1.1 Millstone Stack Millstone Stack monitors, MP2 WRGM and MP3 SLCRS continuously record 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.

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. This amount was added to the amount measured by the grab sample technique.

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 I 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 (Noble Gas & Tritium) are taken and are analyzed on a HPGe gamma spectrometer 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 (Noble Gas & Tritium) are taken and are analyzed on a HPGe gamma spectrometer 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 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. This amount was added to the amount measured by the grab sample technique.

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.

2.1.1.9 Unit 3 Containment Drawdown and Purge Unit 3 containment is initially drawn down 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. Purges and drawdowns are intermittent and are therefore considered batch releases. 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

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.

2.1.1.10 Unit 3 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, when applicable. 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.

2.1.2 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

2.1.3 Batch Releases - Airborne Effluents Unit 1-None Unit 2 Ctmt Purge WGDT Number of Batches 3 15 Total Time (min) 1080 5688 Maximum Time (min) 600 590 Average Time (min) 360 379 Minimum Time (min) 240 15 Unit 3 Ctmt Purge Drawdown Number of Batches 2 1 Total Time (min) 249 59 Maximum Time (min) 217 59 Average Time (min) 125 59 Minimum Time (min) 217 59 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 2002, the following abnormal airborne releases occurred:

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

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

Unit I None (All liquid processed by the Reactor Building Evaporator)

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.

2.2.1.3 Unit 2 and Unit 3 Continuous Liquid Releases Grab samples are 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 1 Unit 2 Unit 3 Number of Batches 0 50 294 Total Time (min) 0 6453 31973 Maximum Time (min) 0 542 206 Average Time (min) 0 129 109 Minimum Time (min) 0 42 7 Average Stream Flow Not Applicable - Ocean Site 2.2.4 Abnormal Liquid Releases An abnormal release of radioactivity is the discharge of a volume of liquid radioactive material to the environment that was unplanned or uncontrolled.

In 2002, 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

Table 2.1-1 Millstone Unit No. 1 Airborne Effluents - Release Summary I II __I__________________Total___

l Units 1stQtr lntr_ 3r t  ; t t oa D. Gross Alpha l . Total Activity : c j NID i NID I NID I NID I N/D I Released I - No ActivitY Detected I NID = Not Detected

Table 2.1-2 Millstone Unit No. I Airborne Effluents - Elevated Continuous

<< No Activity Detected >>

Note: MPI ventilation releases were seperated from elevated Millstone stack after 1st Quarter 2001 clides Released I Units lst Qtr 1 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases B.-- Iodin Total Activity Ci lNID B. lodines11-131 ICiI ITotal Activity Ci ---- NID C. Particulates I Cil Total Activity I Ci I - l l l N;D D. Gross Alpha GrossAlpha I Ci I - I - - i - N/D E. Tritium IH-3 Ci I I - - I NID N/D = Not Detected

Table 2.1-3 Millstone Unit No. 1 Airborne Effluents - Ground Continuous -Balance of Plant Vent (BOP) and Spent Fuel Pool Island Vent (SFPI)

Nuclides [

Released I Units 1st Qtr 2nd Qtr 3rd Qtr th Qtr Total A. Fission & Activation Gases Total Activity

! ci I I Ci I

- i -

- I - I -

N/D B. lodines11-131 Ci _

Total Activity , Ci I _ t- NID l C. Particulates Sr-90 1 Ci 1.06E-06 - I l 1.06E-06 Cs-137 I Ci I 1.39E-06 1.17E-06 I 8.24E-06 I 2.74E-06 1.35E-05 Total Activity I Ci 2.45E-06 1.17E-06 8.24E-06 2.74E-06 1.46E-05 D. Gross Alpha Gross Alpha I Ci I - - - l NID E. Tritium H-3 Ci j 3.40E-01 I 3.92E-01 1.69E-01 4.13E-03 9.05E-01 N/D = Not Detected

Table 2.1-4 Millstone Unit No. I Liquid Effluents - Release Summary (Release Point - Quany)

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

1. Total Activity I Released

2. Average Period I Diluted Activity B. Tritium I1.

12.

C. Dissolved and Entrained Gases

1. Total Acbvity Ci I N/D I NID N/D ND NID Released I _ No Activity Detected

2. Average Period uCi/ml - - [ - l _ l Diluted Activity l I ,

D. Gross Alpha I1. Total Activity Ci N/D N/D j NID 1 N/D NID Released No Activity Detected E. Volume

1. Released Waste Liters O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.00E+00 Volume _

2. Dilution Volume Liters O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+0O During Releases L

3. Dilution Volume Liters O.OOE+0O I O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 During Period _ _

N/D = Not Detected

Table 2.1-5 Millstone Unit No. 1 Liquid Effluents - Batch

<< No Activity Defected >>

Nuclides 2]I l Released lIUnits I 1st Qtr I 2ndQtr 3rdQtr I 4th Qtr Total A. Fission & Activation Products Ag-1 Om lCi Co-58 Ci Co-60 Ci Cs-137 _ Ci Fe-55 Ci Mn-54 Ci Sr-89 _ Ci Sr-90 Ci Zn-65 'Ci - I - i Total Activity; Ci j - - - l - NID B. Tritium H-3 Ci - - I - i NID C. Dissolved & Entrained Gases Total Activity.i - I _  ! - I - N/D D. Gross Alpha lGrossAlpha 1 Ci I - - - -  ! N/D N/D = Not Detected

Table 2.2-1 Millstone Unit No. 2 Airborne Effluents - Release Summary Ii I Units lstQtr I -2ndQtr I 3rdQtr I '4thQtr I Total I A. Fission & Activation Gases D. Gross Alpha

1. Total Activity I Ci l NID I N/D I NID I N/D NID I Released I I No Activity Detected N/D = Not Detected

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

& Spent Fuel Pool Evaporation I Nuclides - 1I I IReleased I Units liwst Qt77 I 2nd Otr I a1rd Otr In Ash Qftr

_,, I l Trnfn vtaa I I

I TnfI A. Fission & Activation Gases Ar-41 Ci 3.09E-02 9.52E-04 5.74E-02 8.92E-02 Kr-85m Ci 5.92E-01 5.92E-01 Xe-131m Ci Xe-133 Ci 1.95E+01 6.87E+00 1.53E+01 4.05E+01 8.22E+01 Xe-133m Ci 3.76E-02 3.76E-02 Xe-135 Ci 3.38E-01 3.62E-01 1.42E-01 4.91E+00 5.75E+00 Xe-135m Ci - - 7.15E-02 7.15E-02 Total Activity Ci 1.99E+01 7.23E+00 1.54E+01 4.61E+01 8.87E+01 B. lodines 1-131 Ci 9.93E-04 7A 1E-04 1.59E-03 2.83E-04 3.60E-03 1-132 Ci 1.72E-04 2.71 E-04 6.25E-04 1.28E-04 1.20E-03 1-133 Ci 3.73E-04 1.91 E-03 1.01E-03 4.75E-04 3.77E-03 1-135 Ci 3.31 E-04 2.67E-04 6.34E-04 2.65E-04 1.50E-03

,Total Activity Ci 1.87E-03 3.19E-03 3.86E-03 1.15E-03 I 1.01E-02 C. Particulates 1-131 Ci I Co-8 Ci 6.99E-07 1.88E-06 2.30E-06 4.88E-06 Co-60 Ci - -- I -

Mn-54 Ci - _ .

Ba-140 Ci l l Cs-137 Ci I Total Activity I Ci 6.99E-07 1.88E-06 2.30E-06 4.88E-06 D. Gross Alpha lGross Alpha I Ci - - _

- N/D E. Tritium lH-3 I Ci 1.24E+00 I 1.22E+00 1 2.70E+00 2.39E+01 I 2.91E+01 N/D = Not Detected

Table 2.2-3 Millstone Unit No. 2 Airborne Effluents - Mixed Batch - Containment Purges Nuclides Released Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases Kr-85 Ci 1.72E+00 - 1.72E+00 Xe-133 Ci 2.67E+01 1.89E-02 - - 2.67E+01 Xe-131m Ci 1.17E-01 - - 1.17E-01 Xe-133m Ci 1.20E-01 - - 1.20E-01 Xe-135 Ci 2.40E-01 1.09E-02 - - 2.51 E-01

• Total Activity Ci I 2.89E+01 2.97E-02 I - 2.89E+01 B. lodines 1-131 Ci 1.28E-03 1.64E-06 - 1.28E-03 1-132 Ci 5.27E-05 - 5.27E-05 1-133 Ci 1.10E-04 6.29E-06 1.16E-04 Total Activity Ci j 1.44E-03 I 7.92E-06 - 1.45E-03 C. Particulates 1-131 Br-82 Ci -

Ci l 6.97E-06

[

6.97E-06 Cs-137 Ci, - _

Total Activity Ci I 6.97E-06 6.97E-06 D. Gross Alpha Gross Alpha Ci I - - - - NtD E. Tritium 1H-3 Ci I 1.77E-01 I 2.89E-02 - 2.06E-O1 l NtD = Not Detected

Table 2.2-4 Millstone Unit No. 2 Airborne Effluents - Elevated Batch - WGDT Nuclides-I Released l Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases Ar-41 Ci -

Kr-85 Ci 8.36E-01 4.87E+00 8.81 E-01 3.06E-01 6.90E+00 Kr-85m Ci _

Kr-87 Ci Kr-88 Ci Xe-131m Ci 4.48E-03 5.51 E-02 5.96E-02 Xe-133 Ci 7.73E-02 1.07E-01 1.84E-01 Xe-133m Ci 2.37E-04 _ 2.37E-04 Xe-135 Ci _ _

Xe-135m Ci _ _

Total Activity Ci j 9.18E-01 5.04E+00 8.81 E-01 3.06E-01 N/D B. lodines 1-131 ____ -  :  :

Total Activity l Ci - - l _ l N/D N-O C. Particulates 1-131 Ci l - __l_l___l _

TotalActivity j Ci - - _

- - NID NO D. Gross Alpha lGross Alpha I Ci I - _ NOD E. Tritium H-3 Ci I 1.85E-04 7.44E-04 2.14E-04 7.98E-05 1 .22E-03 NID = Not Detected

Table 2.2-5 Millstone Unit No. 2 Airborne Effluents - Elevated - Containment Vents Nuclides Released I Units I 1st Qtr I 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. Fission & Activation Gases Ar-41 Ci 4.31 E-02 2.24E-02 2.04E-02 2.43E-02 1.1OE-01 Kr-85 Ci 4.18E-01 1.64E-01 5.53E-01 1.13E+OO Kr-85m Ci 4.53E-04 3.84E-05 4.91 E-04 Xe-131 m Ci 1.90E-02 7.59E-04 1.12E-02 4.84E-03 3.58E-02 Xe-133 Ci 1.35E+00 1.03E-01 2.57E-01 1.97E-01 1.91 E+OO Xe-1 33m Ci 8.85E-03 8.38E-04 _ 8.38E-04 Xe-135 Ci 1.97E-02 2.41 E-03 7.46E-04 8.51 E-04 2.37E-02 Total Activity Ci 11.86E+00 1.29E-01 I 4.54E-01 7.80E-01 3.22E+OO B. lodines

• 1-131 Ci I 1.65E-06 ' 3.13E-07 - 1.40E-05 1.59E-05 1-133 Ci l 5.37E-07 _ 3.82E-07 _ 9.19E-07 Total Activity I Ci 2.18E-06 3.13E-07 l 1.44E-05 1.68E-05 C. Particulates 1-131 ICil - I - I _

Co-58 Ci r 3.85E-07 - 3.85E-07 Cs-137 Ci I Total Activity I Ci , - 3.85E-07 _ 3.85E-07 D. Gross Alpha Gross Alpha I Ci I - - - l N/D E. Tritium H-3 I Ci I 3.90E-01 3.47E-02 2.08E-01 1.25E+00 1.88E+OO NID = Not Detected

• Prior to charcoal filtration

Table 2.2-6 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 I A. Fission and Activation Products

1. Total Activity Ci 3.23E-02 I Released I

2. Average Period uCi/ml 1.67E-10 I Diluted Activity I I D. Gross Alpha

1. Total Activity Ci j N/D l NOD l NID l NOD l N/D Released F } No Activity Detected E. Volume

1. Released Waste Liters 7.03E+05 8.24E+05 3.20E+05 3.16E+07 3.34E+07 Volume

2. Dilution Volume Liters 2.40E+09 2.29E+09 1.05E+09 1.25E+09 6.99E+09 During Releases

3. Dilution Volume Liters 1.93E+1 1 2.60E+1 1 2.78E+11 2.86E+11 1.02E+12 During Period L N/D = Not Detected

Table 2.2-7 Millstone Unit No. 2 Liquid Effluents - Continuous - SGBD Nuclides l Released I Units l 1st Qtr I 2nd Qtr 3rd Qtr l 4th Qtr Total A. Fission & Activation Products 1 ciI - I l l I  ;

ITotal Activity ICi I - -- NID B. Tritium IH-3 Ci l - I 6.91E-02 l 6.91E-02 C. Dissolved & Entrained Gases Ii Cil ITotal Activity I Ci --- I - I NID-L D. Gross Alpha Gross Alpha c C - I I I N/D i N/D = Not Detected

Table 2.2-8A Millstone Unit No. 2 Liquid Effluents - Batch - LWS i .

Nuclides I Released I UnitsI 1st QrIr - 2nd Qtr I 3rdQtr I 4th Qtr I Total I A. Fission & Activation Products Ba-140 Ci 7.64E-05 I - - 7.64E-05 Ag-1i1m Ci 5.19E-04 l 3.21E-05 l 2.39E-05 2.07E-06 5.77E-04 Cr-51 Ci 3.92E-03 l 9.53E-03 1.35E-02 Co-57 Ci 2.43E-05 3.77E-05 6.20E-05 Co-58 Ci 6.75E-03 1.98E-02 1.OOE-03 2.02E-04 2.77E-02 Co-60 Ci 8.30E-03 1.85E-03 3.79E-04 2.27E-04 1.08E-02 Cs-134 Ci 4.84E-04 1.15E-03 6.26E-05 1.70E-03 Cs-137 Ci 4.56E-04 8.04E-04 5.24E-05 1.75E-05 1.33E-03 Fe-55 Ci 9.24E-03 l 5.81 E-03 6.47E-04 3.47E-04 1.60E-02 Fe-59 Ci 3.68E-04  ! 7.96E-04 1.16E-03 1-131 Ci 8.23E-05 15.58E-05 9.70E-07 5.68E-05 La-140 Ci 9.68E-05 j - 2.32E-06 9.91 E-05 Mn-54 Ci 5.29E-04 1 4.30E-04 6.40E-06 3.53E-06 9.69E-04 Nb-95 l_Ci f5.32E-04 i.17E-03 I 3.59E-05 1.63E-06 1.74E-03 Nb-97 CiT - ;7.09E-06 6.13E-06 1.32E-05 Ru-103 Ci i 4.94E-06  ;- - - 4.94E-06 Ru-105 Ci 1.17E-04 1.47E-04 2.63E-04 Sb-122 4 Ci - 4.69E-05l - 4.69E-05 Sb-1 24 I Ci I - _ 3.83E-05 2.111 E-05 5.93E-05 Sb-125 I Ci i 5.29E-04 2.98E-04 1.67E-03 8.78E-04 3.38E-03 Sn-113 Ci , 2.91E05 1.54E-04 - 1.83E-04 Sr-89 Ci 3.97E-05 - 6.94E-05 6.52E-05 1.74E-04 Sr-90 t Ci I - j_2.33E-06 2.33E-06 Sr-92 , Ci - 2.48E-06 _ 2.48E-06 Zr-95 i Ci 2.25E-04 1 6.69E-04 8.94E-04 Total Activity I Ci 3.23E-02 1 4.28E-02 ; 3.98E-03 1.75E-03 8.08E-02 B. Tritium lH-3 I Ci I 6.07E+01 I 1.80E+01 6.75E+01 6.11E+O 1 2.07E+02 C. Dissolved & Entrained Gases Kr-85 Ci 2.07E-01 2.80E-41 6.04E-02 3.97E-02 l 5.87E-01 Xe-131m Ci 1.65E-02 4.29E-03 j 7.38E-03 2.81 E-02 Xe-133 Ci 4.47E-01 j 1.35E-01 1.25E-01 1.57E-03 7.09E-01 Xe-133m Ci i.1 7E-03 1.98E-03 i 2.84E-04 - 3.44E-03 Xe-1 35 __ Ci t. 1 E-04 2.10E-04 -4.3E02E__ 3 __ __

Total Activity J Ci 6.72E-01  ; 4.22E-01 1.93E-01 _4.13E-02 I 1.33E+O0 D. Gross Alpha GrossAlpha I Ci N!D NID = Not Detected

Table 2.2-8B Millstone Unit No. 2 Liquid Effluents -Continuous-Turbine Building Sump (Release Point - Yard Drain - DSN 006)

Nuclides Released I UnitsI 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total1 A. Fission & Activation Products Total Activity Ci - j - N/D B. Tritium H-3 Ci 2.48E-02 8.34E-03 2.33E-05 4.72E-03 3.78E-02 Average Period uCI/ml 1.01E-06 3.36E-07 9.29E-10 1.88E-07 3.80E-07 Diluted Activity C. Dissolved & Entrained Gases I Cil I - I - - I -

lTotal Activity I Ci - l - - RD D. Gross Alpha lGross Alpha I Ci ! - I I I l N/D

• from Yard Drains N/D = Not Detected

Table 2.3-1 Millstone Unit No. 3 Airborne Effluents - Release Summary IUnits 1stQtr I 2ndQtr I 3rd Qtr l 4thQtr I Total D. Gross Alpha

• . Total Activity Ci N/D I N/D l NID l ND l I Released I No Activity Detected I E. Tritium NID = Not Detected

Table 2.3-2 Millstone Unit No.3 Airborne Effluents - Mixed Continuous - Normal Ventilation &

Spent Fuel Pool Evaporation Nuclides Released I Units I 1st Qtr 2nd Qtr 3rd Qtr 4thQtr Total A. Fission & Activation Gases Xe-131m Ci 2.17E+00 2.17E+00 Xe-133 Ci Xe-135 Ci 1.18E-01 1.18E-01 Total Activity Ci J - 2.29E+00 2.29E+00 B. lodines; 1-131 ] Ci [ - 1.27E-06 1.27E-06 1-133 l Ci - 9.15E-06 9.15E-06 Total Activity l Ci I - - 1.04E-05 1.04E-05 C. Particulates 1-131 j Ci f__ _ _ _ _ --

Cr-51 j Ci L - 1.66E-05 - 1.66E-05 Mn-54 Ci I -- 4.28E-06 - 4.28E-06 Co-58 Ci - 2.17E-05 - 2.17E-05 Co-60 - Ci I - 1.21 E-05 - 1.21 E-05 Nb-95 Ci1 - j -

Sr-89 Ci Sr-90 Ci Ru-106 Ci Total Activity Ci [ 5.47E-05 5.47E-05 D. Gross Alpha lGross Alpha Ci - _

- _ N/D E. Tritium IH-3 Ci 4.92E+00 5.89E+00 9.01 E+00 2.47E+01 - 4.45E+01 N/D = Not Detected

Table 2.3-3 Millstone Unit No. 3 Airborne Effluents - Ground Continuous - ESF Building Ventilation Nuclides A Released I Units l 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr - Total A. Fission & Activation Gases IXe-131m I Cil - I - - l -

Total Activity i Ci - - - NID B. lodines 1-131 Cil - I - - l - 7 1-133 Tci - 1 - T - T - T - I Total Activity Ci l - - T _ NID C. Particulates 1-131 Ci -

Co-58 Ci j 1.82E-07 1.82E-07 Mn-54 i i Hf-1 81 Ci: - 3.06E-08 3.06E-08 Cr-51 Ci - -T -

Sr-89 Ci I -I _ -

Sr-90 Ci - I I  !

Total Activity Ci - - 3.06E-08 7 1.82E-07 2.13E-07 D. Gross Alpha Gross Alpha Ci I - I - - N/D E. Tritium H-3 Ci - - I 3.31E-01 I - 3.31E-01l N/D = Not Detected

Table 2.3-4 Millstone Unit No. 3 Airborne Effluents - Mixed Batch - Containment Drawdowns Nucilides Released I Units I 1st Qtr - 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases IXe-131m Ci -

Total Activity Ci - NID B. lodines 1-131 Ci_ _ _

1-1333 Ci ll l lTotal Activity Ci - l - - l NID C. Particulates 1-131 Ci 2 2 Nb-97 Ci 2.21 E-08 2.21 EI08 Total Activity Ci 2.21 E_-8 2.21 E-08 D. Gross Alpha Gross Alpha Ci - - - l NID E. Tritium IH-3 Ci - l 6.31 E-04 I l 6.31E04 N/D = Not Detected

Table 2.3-5 Millstone Unit No. 3 Airborne Effluents - Mixed Batch - Containment Purges Nuclides fill l Released I Units I 1stQtr 2ndQtr 3rd Qtr I 4th Qtr I Total A. Fission & Activation Gases Xe-133 Ci 4.12E-03 I - 4.12E-03 Xe-135 Ci 2.01 E-03 - 2.01 E-03 Total Activity Ci - 6.13E-03 - 6.13E-03 B. lodines 1-131 Ci _ [ ]

Total Activity j Ci - t - I - [ N/D C. Particulates 1-133 Total Activity Ci Ci _ - _ NID D. Gross Alpha lGross Alpha I Ci - - - i NID E. Tritium IH-3 Ci - l 6.51 E-02 - 6.51E-02 NID = Not Detected

Table 2.3-6 Millstone Unit No. 3 Airborne Effluents - Elevated Continuous - Gaseous Waste System

& Containment Vents Nuclides I Released I Units 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr l Total A. Fission & Activation Gases Ar-41 Ci 1.47E-02 5.54E-03 6.51 E-03 1.29E-02 3.97E-02 Kr-85m Ci Kr-87 Ci -

Xe-133 Ci 5.12E-03 3.59E-03 6.37E-03 2.29E-04 1.53E-02 Xe-1 35 Ci 1.72E-03 8.01 E-04 2.35E-03 - 4.87E-03 Kr-85 Ci 9.93E-02 9.93E-02 Total Activity I Ci 2.15E-02 9.93E-03 I 1.52E-02 1.12E-01 l 1.59E-01 B. lodines 1-131

_ Ci - j - 2.50E-07 l - 2.50E-07 1-133 Ci 5.34E-07 5.34E-07 Total Activity J Ci I - 7.84E-07 7.84E-07 C. Particulates 1-131 Ci Cr-51 Ci 2.64E-06 1.75E-07 2.82E-06 Mn-54 Ci 5.19E-08 5.19E-08 Co-58 Ci 1.92E-06 4.82E-07 2.40E-06 Co-60 Ci 1.03E-07 4.83E-07 5.86E-07 Nb-95 Ci Ru-106 Ci Cs-I 37 Ci Br-82 Ci Zr-95 Ci Total Activity Ci I - - 4.66E-06 11.19E-06 1 5.85E-06 D. Gross Alpha Gross Alpha I Ci I - I - - I N/D E. Tritium H-3 Ci 1.13E+00 5.98E-01 4.99E-01 11.57E-01 2.38E+00 NID = Not Detected

Table 2.3-7 Millstone Unit No. 3 Liquid Effluents - Release Summary (Release Point - Quarry)

I __

I Units l 1st Qtr- 2nd Qtr I 3rd Qtr I 4th Qtr Total l D. Gross Alpha

1. Total Activity I Ci NID NID  ; NID NID I NI Released I T E. Volume

1. Released Waste Liters 5.65E+06 3.59E+06 1 5.36E+06 3.20E+06 1.78E+07 Volume I I

2. Dilution Volume Liters 2.94E+1 0 1 1.21 E+10 1 1.77E+10 9.09E+09 6.83E+10 During Releases iLe

3. Dilution Volume Liters 4.60E+11 4.66E+11 3.84E+11 4.30E+11 1.74E+12 During Period N/D = Not Detected

Table 2.3-8 Millstone Unit No. 3 Liquid Effluents - Continuous - SGBD & SW & TK2 Nuclides ow l Released lUnitsl 1stQtr I 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Products IC:i I - I - I - I - -

lTotalActivity I Ci I - -lIl D l B. Tritium H-3 I Ci I 2.09E-01 I 1.77E-01 I 9.28E-02 4.01E-02 I 5.19E-O1 C. Dissolved & Entrained Gases I CiI - I -- I -

ITotalActivity I Ci I - - l l /D D. Gross Alpha

[Gross Alpha I Ci I - - I - - N/D N/D = Not Detected

Table 2.3-9 Millstone Unit No. 3 Liquid Effluents - Batch - LWS Nuclides il l Released lUnitsl 1st Qtr I 2nd Qtr I 3rd r I 4th Qtr Total A. Fission & Activation Products Ag-110m Ci I Co-57 Ci 2.27E-06 6.44E-05 1.81 E-05 8.48E-05 Co-58 Ci 5.27E-04 1.90E-04 5.12E-03

• 1.07E-02 1.65E-02 Co-60 Ci 1.1OE-03 1.14E-03 1.78E-02 6.59E-03 2.66E-02 Cr-51 Ci 6.18E-03 1.33E-02 1.95E-02 Cs-134 Ci -

Cs-137 Ci 2.94E-04 8.42E-04 2.02E-03 3.16E-03 Fe-55 Ci 3.96E-03 4.69E-03 2.40E-02 2.04E-02 5.31 E-02 Fe-59 Ci _ 2.46E-04 5.31 E-04 7.77E-04 1-131 Ci 1-133 Ci Mn-54 Ci 4.59E-04 1.25E-04 3.09E-03 1.60E-03 5.27E-03 Mo-99 Ci _ - _ _

Na-24 Ci -

Nb-95 Ci 1.96E-05 - l_5.19E-04 1.86E-03 2.40E-03 Nb-97 Ci 3.35E-05 - I 2.26E-05 i j 5.61 E-05 Rb-88 Ci - _ - - -

Ru-105 ICi _ - 8.71 E-05 j 8.71 E-05 Sb-124 Ci _ - -  !

Sb-125 Ci 1.52E-03 3.52E-03 6.55E-03 8.OOE-03 1.96E-02 Sr-91 Ci - 1.60E-05 - 1.60E-05 Sn-113 Ci - I 2.72E-05 3.33E-05 6.05E05 Tc-99m Ci -  ! -  ! -

Tc-101 Ci I - - i Zr-95 Ci - 3.19E-04 9.12E-04 j 1.23E-03 Ba-140 Ci - 8.12E-05 8.12E-05 Y-91m Ci Total Activity Ci 7.92E-03 1.05E-02 1 6.61 E-02  ! 6.40E-02 1.49E-01 B. Tritium

[lHZ3 lCi I 1.69E+02 I 4.90E+02 I 6.25E+02 4.29E+01 i 1.33E+03 C. Dissolved & Entrained Gases__

Xey133 Ci 1.26E-05 L - - 1.26E-05 Xej135m Ci 2.54E-05 - . 2.54E-05 Xe135 Ci 1.53E-05 r - , 1.53E-05 1

Total Activity Ci 4.07E-05 -1.26E-05 j - - 5.33E-05 D. Gross Alpha lGross Alpha I Ci I - - . I N/D N/D = Not Detected

Table 2.3-10A Millstone Unit No. 3 Liquid Effluents - Batch - CPF Waste Neutralization Sumps & Hotwell Discharge

<< No Activity Detected >>

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

lTotal Activity I Ci I - I - N/D B. Tritium IH-3 Ci I 2.56E-02 2.39E-02 8.28E-03 5.08E-03 NID C. Dissolved & Entrained Gases Xe-1m31 m C - I - I Xe-1 35 C - - -CC!,

Total Activity - j - - - N/D D. Gross Alpha lGross Alpha ' Ci - - - - N/D NID = Not Detected

Table 2.3-1OB Millstone Unit No. 3 Liquid Effluents - Release Summary (Release Point - Yard Drain - DSN 006)

I Units I 1st Qtr . 2nd Qtr 3rd Qtr 4th Qtr TotalI D. Gross Alpha

1. TotalActivity Ci N/D l NID I l I/D NO ' NO I Released lI I N N N N E. Volume N/D = Not Detected

Table 2.3-1OC Millstone Unit No. 3 Liquid Effluents - Continuous - Turbine Building Sump (Release Point - Yard Drain - DSN 006)

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

TotalActivity i- I N/D B. Tritium H-3 I Ci 3.72E-02 4.03E-02 I 1.16E-02 9.42E-03 9.85E-02 Average Period uC/ml 1.52E-06 1.63E-06 4.56E-07 3.68E-07 9.73E-07 Diluted Activity l _ I I C. Dissolved & Entrained Gases ITotalActivity i I -C I I NtD D. Gross Alpha lGross Alpha Ci I - - - I I NID -

E. Volume ReleasedWaste I Liters I 4.15E+05 4AOE+05 3.77E+05 5.09E+05 1 1.74E+06 Volume I I I I Dilution Volume ILiters 2.45E+07 2.48E+07 2.51 E+07 2.51 E+07 i 9.95E+07 DuringPeriod' l I i

' from Yard Drains N/D = Not Detected

Table 2.3-1OD Millstone Unit No. 3 Liquid Effluents - Continuous - WTT Berm Water (Release Point - Yard Drain - DSN 006)

Nuclides Released_ Units I1 st Qtr 2nd Qtr 3rd Qtr I 4th Qtr Total A. Fission & Activation Products Total Activity I ci I I - I Ci ND B. Tritium H-3 Cil - 2.46E-03 1.89E-04 5.51E-04 3.20E-03 Average Period uC/mi O.OOE+00 9.94E-08 7.54E-09 2.20E-08 3.22E-08 Diluted Activity I I I C. Dissolved & Entrained Gases lTotal Activity I Ci I - - l l NID D. Gross Alpha jGross Alpha I Ci I - I - - i N/D

• from Yard Drains NID = Not Detected

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

Table 2.1-6 Unit I Solid Waste and Irradiated Component Shipments Table 2.2-9 Unit 2 Solid Waste and Irradiated Component Shipments Table 2.3-11 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 2002 Containers routinely used for radioactive waste shipment include:

55-gal Steel Drum DOT 17-H container 7.5 ft3 Steel Boxes 45 ff3 87 ff3 95 ft3 122 ff3 Steel Container 202.1 ff3 Steel "Sea Van" 1280 ff3 Polyethylene High Integrity Containers 120.3 ft3 132.4 ft3 173.4 ff3 202.1 ff3

Table 2.1-6 Solid Waste and Irradiated Component Shipments Millstone Unit 1 January 1, 2002 through December 31, 2002 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of Waste

a. Spent resins, filter sludges, evaporator bottoms, etc.

I t. id I-From Millstone Nuclear Power Station to IChem-Nuclear Services LLC, Bamwell SC for burial

b. Dry compressible waste, contaminated equipment, etc.

From Millstone Nuclear Power Station to Duratek Inc., 1 .45E+01 Oak Ridge TN for Super-Compaction, Incineration, etc. I eI 1 .33E+00 25%

C. Irradiated components, control rods, etc.

- No shipments during this repofl period - -aB y__________

i:~-Rn/a n/a

d. Other - (Mixed Waste)

d. Other - (Water)

From Millstone Nuclear Power Station to Duratek Inc. - 6.27E+00 Oak Ridge. TN for Incineration 1.91 E-02 25%

d. Other - (Grease, oil, oily waste) jrFm M.li.sflone Nuciear Power SoUon to Muralel Inc.,

Oak Ridge, TN for Super-Compacton, Incineration, etc.

Millstone Unit 1 Page 1 of 25

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, Barnwell, SC for Burial

__. _.____li_ CrieiI H-3 0.11 8.63E-03 C-1 4 1.92 1.57E-01 Na-22 Cr-51 <0.01 7.91 E-09 Mn-54 0.92 7.54E-02 Fe-55 56.48 4.61 E+00 Fe-59 <0.01 1.70E-07 Co-57 0.02 1.94E-03 Co-58 0.05 3.98E-03 Co-60 22.59 1.85E+00 Ni-63 16.73 1.37E+00 Zn-65 <0.01 1.50E-04 Rb-83 Sr-89 <0.01 4.91 E-06 Sr-90 <0.01 5.08E-04 Nb-95 <0.01 2.39E-05 Zr-95 <0.01 2.28E-04 Tc-99 <0.01 9.65E-06 Ru-1 03 <0.01 3.40E-1 0 Ru-1 06 <0.01 8.23E-05 Ag-11Om 0.01 8.36E-04 Sn-1 13 <0.01 2.69E-04 Sb-124 <0.01 1.1 OE-07 Sb-125 0.41 3.39E-02 1-129 <0.01 1.48E-04 Cs-1 34 0.10 7.91 E-03 Cs-1 37 0.44 3.63E-02 Ce-144 <0.01 9.77E-08 U-234 U-235 U-238 Pu-238 <0.01 3.62E-04 Pu-239 <0.01 1.97E-04 Pu-241 0.18 1.47E-02 Am-241 <0.01 4.13E-04 Pu-242 <0.01 - 2.60E-07 Cm-242 <0.01 2.50E-05 Cm-244 <0.01 4.82E-04 Z 8.17E+00 Millstone Unit 1 Page 2 of 25

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.

H-3 0.20 2.63E-03 C-14 Na-22 Cr-51 Mn-54 Fe-55 63.25 8.38E-01 Fe-59 Co-57 Co-58 Co-60 24.22 3.21 E-01 Ni-63 3.24 4.29E-02 Zn-65 Rb-83 Sr-89 Sr-90 0.59 7.87E-03 Nb-95 Zr-95 Tc-99 Ru-i 03 Ru-i 06 Ag-1i1 Om Sn-113 Sb-124 Sb-1 25 1-129 Cs-1 34 Cs-137 8.50 1.13E-01 Ce-I44 _ _

U-234 U-235 U-238 Pu-238 Pu-239 Pu-241 _ _

Am-241 Pu-242 Cm-242 Cm-244

__ _ _5 _ _ 1.33E+00 Millstone Unit 1 Page 3 of 25

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

d. Other - (Mixed Waste)

From Millstone Nuclear Power Station to Perma-Fix Environrmental Services, Gainesville FL for Stabilization, Fuel Blending, etc.

Qdff6-tD-HV H-3 1.41 4.95E-05 C-14 0.20 7.17E-06 Na-22 Cr-51 Mn-54 Fe-55 40.73 '1.43E-03 Fe-59 Co-57 Co-58 0.55 1.91 E-05 Co-60 27.62 9.66E-04 Ni-63 5.72 2.OOE-04 Zn-65 Rb-83 Sr-89 Sr-90 <0.01 2.22E-07 Nb-95 Zr-95 Tc-99 Ru-1 03 Ru-1 06 Ag-110m Sn-113 Sb-1 24 Sb-1 25 1-129 Cs-1 34 Cs-137 23.76 8.31 E-04 Ce-1 44 U-234 U-235 U-238 Pu-238 Pu-239 Pu-241 Am-241 Pu-242 Cm-242 Cm-244

_____ ___3.50E-03 Millstone Unit 1 Page 4 of 25

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

d. Other - (Water)

From Millstone Nuclear Power Stabon to Duratek Inc.. Oak Ridge. TN for Incineration 03aampubum ravotip-pe-sm-11i I H-3 93.92 1.79E-02 C-14 Na-22 Cr-51 0.23 4.46E-05 Mn-54 0.12 2.37E-05 Fe-55 2.24 4.27E-04 Fe-59 Co-57 -<0.01 1.76E-06 Co-58 1.83 3.48E-04 Co-60 0.77 1.48E-04 Ni-63 0.58 1.11 E-04 Zn-65 <0.01 5.67E-07 Rb-83 <0.01 3.33E-08 Sr-89 Sr-90 Nb-95 0.14 2.58E-05 Zr-95 0.07 1.43E-05 Tc-99 Ru-103 0.01 2.13E-06 Ru-1 06 Ag-1 Om Sn-113 Sb-1 24 Sb-125 0.03 5.53E-06 1-129 Cs-134 Cs-137 -0.03 6.11 E-06 Ce-144 U-234 <0.01 6.67E-07 U-235 U-238 Pu-238 Pu-239 Pu-241 Arn-241 <0.01 3.33E-08 Pu-242 Cm-242 Cm-244

___ __ -1.91E-02 Millstone Unit 1 Page 5 of 25

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.

r RddRqYtFcFiddr,11-0.0W.W WWA if I H-3 _ _ _ _ _

C-t4 Na-22 Cr-51 Mn-54 1.46 1.98E-07 Fe-55 46.63 6.30E-06 Fe-59 Co-57 0.12 1.66E-08 Co-58 9.05 1.22E-06 Co-60 15.57 2.1 OE-06 Ni-63 12.16 1.64E-06 Zn-65 Rb-83 Sr-89 Sr-90 0.32 4.37E-08 Nb-95 Zr-95 Tc-99 Ru-103 Ru-106 Ag-1i1 Om Sn-113 Sb-1 24 Sb-125 1-129 Cs-1 34 0.79 1.07E-07 Cs-137 13.89 -1.88E-06 Ce-144 U-234 U-235 U-238 Pu-238 Pu-239 Pu-241 Am-241 Pu-242 Cm-242 Cm-244 1.35E-05 Millstone Unit 1 Page 6 of 25

3. Solid Waste Disposition (Shipments from Millstone)

I lb9U'iBii .D bisa

,;fEi M.Apapr bspo 1 2 l Truck (Sole Use Vehicle) lChem-Nuclear Services LLC, Barnwell, SC I 5 I Truck (Sole Use Vehicle) lDuratek Inc. - Oak Ridge, TN l 1 l Truck (Sole Use Vehicle) lPerma-Fix Environmental Services - Gainesville FL. I B. IRRADIATED FUEL SHIPMENTS (Disposition)

Ib-Tfipetsin-0Mb02 1 N/A I NiA I No Shipments in 2002 lN/A lN/Al Millstone Unit 1 Page 7 of 25

Table 2.2-9 Solid Waste and Irradiated Component Shipments Millstone Unit 2 January 1, 2002 through' December 31, 2002 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of Waste

a. Spent resins, filter sludges, evaporator bottoms, etc.

g e Md fi*-,

l s From Millstone Nuclear Power Station to Studsvik M2.35E+0 Processing Facirdy for Thermal Destruction A 2.14E+01 25%

From Millstone Nuclear Power Station to Duratek Inc., 7.45E-01 l 1 1Oak Ridge, TN for Super-Compaction, Incineration, etc. a 1.19E+00 25% l From Millstone Nudear Power Station to Bajal 1.88E+00 l 1 lChem-Nuclear Services LLC, Bamwell, SC for Burial 9.13E+00 25% l

b. Dry compressible waste, contaminated equipment, etc.

From Millstone Nuclear Power Station to Duratek Inc. A l 3.17E+02 Oak Ridge. TN for Super-Compaction. Incineration, etc. - CAi li 3.43E+00 25%

c. Irradiated components, control rods, etc.

d. Other - (Mixed Waste)

d. Other - (Water)

From Millstone Nuclear Power Station to Duratek Inc. - - 1.61 E+01 Oak Ridge. TN for Super-Compaction, Incineration, etc. A l 2.56E-02 25%

d. Other - (Grease, oil, oily waste)

Millstone Unit 2 Page 8 of 25

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 Facility for Thermal Destruction

,, _ . - ~~~  :*wimos,44 ,>t _t"Oul H-3 <0.01 3.01 E-04 C-14 2.96 6.34E-01 Na-22 Cr-51 Mn-54 0.10 2.14E-02 Fe-55 8.58 1.84E+00 Fe-59 Co-57 0.01 2.49E-03 Co-58 0.01 2.34E-03 Co-60 14.45 3.1 OE+O0 Ni-63 66.97 1.44E+01 Zn-65 Rb-83 Sr-89 Sr-90 0.19 4.01 E-02 Nb-95 Zr-95 Tc-99 <0.01 5.43E-05 Ru-1 03 Ru-106 Ag-1 1 Om Sn-113 Sb-124 Sb-125 0.13 2.86E-02 1-129 -

Cs-134 0.59 1.27E-01 Cs-137 5.98 1.28E+00 Ce-144 U-234 U-235 U-238 Pu-238 <0.01 2.18E-04 Pu-239 -<0.01 9.97E-05 Pu-241 0.03 5.81 E-03 Am-241 <0.01 8.34E-05 Pu-242 Cm-242 <0.01 6.16E-06 Cm-244 <0.01 9.22E-05

-_ 2.14E+01 Millstone Unit 2 Page 9 of 25

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.

IIFN6-1CIia11002-f r  ;-Ciiii

-u S-iax H-3 2.02 2.40E-02 C-14 1.37 1.63E-02 Na-22 Cr-51 Mn-54 0.24 2.91 E-03 Fe-55 47.78 5.69E-01 Fe-59 Co-57 0.05 6.41 E-04 Co-58 0.05 6.47E-04 Co-60 25.81 3.07E-01 Ni-63 20.51 2.44E-01 Zn-65 Rb-83 Sr-89 Sr-90 Nb-95 Zr-95 Tc-99 Ru-103 Ru-106 Ag-110m Sn-113 Sb-124 Sb-125 0.58 6.88E-03 1-129 Cs-134 Cs-137 1.20 1.43E-02 Ce-144 U-234 U-235 U-238 Pu-238 <0.01 9.54E-05 Pu-239 <0.01 3.84E-05 Pu-241 0.35 4.14E-03 Am-241 <0.01 7.08E-05 Pu-242 Cm-242 <0.01 5.24E-05 Cm-244 0.01 1.33E-04 QTAt 1.1 9E+00 Millstone Unit 2 Page 10 of 25

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, Barnwell, SC for Burial IRSdfcrfiq--dIjdT-R r~ ~ ~ IIW&-qVMrdW Ififf GUHw6MR-HE s,________________sZz E s d73~x H-3 0.13 1.14E-02 C-14 2.40 2.19E-01 Na-22 Cr-51 <0.01 7.91 E-09 Mn-54 0.83 7.61 E-02 Fe-55 53.93 4.92E+00 Fe-59 <0.01 1.70E-07 Co-57 0.02 1.95E-03 Co-58 0.04 3.98E-03 Co-60 23.29 2.13E+00 Ni-63 17.78 1.62E+00 Zn-65 <0.01 1.50E-04 Rb-83 Sr-89 <0.01 4.91 E-06 Sr-90 - <0.01 7.49E-04 Nb-95 -<0.01 2.39E-05 Zr-95 <0.01 2.28E-04 Tc-99 <0.01 9.65E-06 Ru-103 - <0.01 3.40E-10 Ru-1 06 <0.01 8.23E-05 Ag-11 Om <0.01 8.73E-04 Sn-1 13 <0.01 - 2.69E-04 Sb-124 <0.01 1.1 OE-07 Sb-125 0.40 3.65E-02 1-129 <0.01 1.51 E-04 Cs-134 0.10 9.16E-03 Cs-137 0.84 7.67E-02 Ce-1 44 <0.01 9.77E-08 U-234 U-235 U-238 Pu-238 <0.01 4.53E-04 Pu-239 <0.01 2.44E-04 Pu-241 0.20 1.83E-02 Am-241 <0.01 4.62E-04 Pu-242 <0.01 2.60E-07 Cm-242 <0.01 2.51 E-05 Cm-244 <0.01 5.64E-04

- - 9.13E+00 Millstone Unit 2 Page 11 of 25

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-Compacbon, Incineration, etc.

1'XVWA-feTAYA-I1;W tbrQr-v-Mv-K-W0 H-3 0.27 9.17E-03 C-14 0.06 2.18E-03 Na-22 Cr-51 0.14 4.79E-03 Mn-54 0.76 2.62E-02 Fe-55 34.64 1.19E+O0 Fe-59 <0.01 5.55E-08 Co-57 <0.01 3.62E-05 Co-58 4.66 1.60E-01 Co-60 20.68 7.09E-01 Ni-63 27.75 9.52E-01 Zn-65 _

Rb-83 Sr-89 -<0.01 5.45E-09 Sr-90 <0.01 8.12E-06 Nb-95 0.10 3.45E-03 Zr-95 0.07 2.26E-03 Tc-99 <0.01 4.37E-09 Ru-103 Ru-106 Ag-1 1Om <0.01 2.26E-04 Sn-1 13 <0.01 8.75E-06 Sb-1 24 <0.01 2.40E-08 Sb-1 25 0.01 3.91 E-04 1-129 Cs-134 3.54 1.22E-01 Cs-137 7.30 2.51 E-01 Ce-144 _ __

U-234 _

U-235 U-238 Pu-238 <0.01 3.39E-06 Pu-239 <0.01 1.48E-06 Pu-241 <0.01 1.47E-04 Am-241 <0.01 2.64E-06 Pu-242 Cm-242 <0.01 2.95E-06 Cm-244 - <0.01 4.98E-06

___M - -3.43E+00 Millstone Unit 2 Page 12 of 25

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

d. Other - (Mixed Waste)

From Millstone Nuclear Power Station to Perma-Fix Environmental Services, Gainesville FL for Stabilization, Fuel Blending, etc.

R-Ad6 il __c________________

H-3 11.39 1.34E-04 C-I4 1.42 1.67E-05 Na-22 Cr-51 Mn-54 0.06 7.11 E-07 Fe-55 37.97 4.47E-04 Fe-59 Co-57 Co-58 -2.84 3.34E-05 Co-60 14.69 1.73E-04 Ni-63 14.79 1.74E-04 Zn-65 Rb-83 Sr-89 Sr-90 0.02 2.22E-07 Nb-95 Zr-95 Tc-99 Ru-1 03 Ru-106 Ag- 1Om Sn-113 Sb-i 24 Sb-1 25 i-129 Cs-1 34 0.30 3.49E-06 Cs-137 16.52 1.94E-04 Ce-144 U-234 _

U-235 _

U-238 Pu-238 Pu-239 Pu-241 -

Am-241 Pu-242 Cm-242 Cm-244 _

___ ________ 1.1 8E-03 Millstone Unit 2 Page 13 of 25

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

I d. Other- (Water)

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

ir-H-3 90.75 2.33E-02 C-14 Na-22 <0.01 6.40E-07 Cr-51 0.17 4.46E-05 Mn-54 0.18 4.49E-05 Fe-55 3.36 8.61 E-04 Fe-59 Co-57 <0.01 1.77E-06 Co-58 1.51 3.86E-04 Co-60 0.93 2.38E-04 Ni-63 0.73 1.88E-04 Zn-65 0.05 1.31 E-05 Rb-83 <0.01 3.33E-08 Sr-89 Sr-90 Nb-95 0.12 - 3.13E-05 Zr-95 0.07 1.78E-05 Tc-99 Ru-103 <0.01 2.13E-06 Ru-1 06 Ag-11 Om Sn-113 Sb-1 24 Sb-1 25 0.02 5.53E-06 1-129 Cs-134 <0.01 1.42E-06 Cs-137 2.07 5.31 E-04 Ce-144 U-234 <0.01 2.28E-06 U-235 <0.01 1.16E-08 U-238 <0.01 1.18E-07 Pu-238 <0.01 1.81 E-07 Pu-239 <0.01 1.OOE-07 Pu-241 Am-241 <0.01 1.68E-07 Pu-242 Cm-242 _

Cm-244

_ 2.56E-02 Millstone Unit 2 Page 14 of 25

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.

'ALR~d fl6-i-fhIfdf I, M.12,2X0.9F I H-3 70.06 4.67E-05 C-14 -

Na-22 Cr-51 Mn-54 0.30 1.98E-07 Fe-55 9.45 6.30E-06 Fe-59 Co-57 0.02 1.66E-08 Co-58 2.54 1.69E-06 Co-60 11.74 7.82E-06 Ni-63 2.47 1.64E-06 Zn-65 _

Rb-83 Sr-89 Sr-90 0.07 4.37E-08 Nb-95 Zr-95 Tc-99 Ru-1 03 Ru-106 Ag-1 Om Sn-i 1 3__ _ _ _ _

Sb- 124 Sb-125 1-129 _ _ _ _ _ _ _ _ _ _

Cs-1 34 0.16 1.07E-07 Cs-137 3.19 .2.13E-06 Ce-144 U-234 U-235 U-238 Pu-238 Pu-239 Pu-241 Am-241 Pu-242 Cm-242 Cm-244

________ WI __ I6.66E-05 Millstone Unit 2 Page 15 of 25

3. Solid Waste Disposition (Shipments from Millstone) 3 f Truck (Sole Use Vehicle) IChem-Nuclear Services - Barnwell, SC 14 Truck (Sole Use Vehicle) lDuratek Inc. - Oak Ridge, TN 2 Truck (Sole Use Vehicle) Perma-Fix Environmental Services - Gainesville FL 1 Truck (Sole Use Vehicle) JStudsvik Processing Facility, LLC - Erwin, TN B. IRRADIATED FUEL SHIPMENTS (Disposition) lNo Shipments in 2002 lNA N/A Millstone Unit 2 Page 16 of 25

Table 2.3-11 Solid Waste and Irradiated Component Shipments Millstone Unit 3 January 1, 2002 through December 31, 2002 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of Waste

a. Spent resins, filter sludges, evaporator bottoms, etc.

DRat r140-From Millstone Nuclear Power Station to 2.76E+00 ChefmNuclear Services U1C, Bamwell, SC for Burial 2.30 E+01 25%

From Millstone Nuclear Power Station to Duratek Inc., 4.28E-01 1 akRidge,TNforSuper-paction,Incineration,etc. 1 .76E+0 l 25% J From Millstone Nuclear Power Station to Studsvik I l 4.09E+00 Il Processing Facility for Thermal Destruction - G o I 4.96E+01 l 25% l

b. Dry compressible waste, contaminated equipment, etc.

From Millstone Nuclear Power Station to Duratek Inc , _ 1 .98E+02 Oak Ridge, TN for Super-Compaction, Incineration. etc. 1.1 3E+00 25%

C. Irradiated components, control rods, etc.

d. Other - (Mixed Waste)

_ _ § %LI _f" From Millstone Nuclear Power Station to Perma-Fix Environmental H i 4.51 E-01 Services, Gainesville FL for Stabilization, Fuel Blending, etc. 4.24E-04 25%

d. Other- (Water)

From Millstone Nuclear Power Station to Duratek Inc.,

1Oak Ridge, TN for Super-Compaction, Incineration, etc.

d. Other - (Grease, oil, oily waste)

Millstone Unit 3 Page 17 of 25

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. Bamwell. SC for Bunal H-3 0.06 1.29E-02 C-14 0.97 2.23E-01 Na-22 Cr-51 <0.01 7.91 E-09 Mn-54 1.45 3.33E-01 Fe-55 56.03 1.29E+01 Fe-59 <0.01 1.70E-07 Co-57 0.03 7.31 E-03 Co-58 - 0.04 8.52E-03 Co-60 24.18 5.56E+00 Ni-63 16.11 3.71 E+00 Zn-65 <0.01 1.50E-04 Rb-83 Sr-89 <0.01 4.91 E-06 Sr-90 <0.01 9.04E-04 Nb-95 <0.01 3.80E-05 Zr-95 <0.01 4.94E-04 Tc-99 <0.01 9.65E-06 Ru-1 03 <0.01 3.40E-1 0 Ru- 06 <0.01 8.23E-05 Ag-11 Om <0.01 8.73E-04 Sn-1 13 <0.01 3.63E-04 Sb-124 <0.01 1.1OE-07 Sb-125 0.60 1.37E-01 1-129 <0.01 1.25E-03 Cs-1 34 0.04 9.16E-03 Cs-137 -0.37 8.52E-02 Ce-144 <0.01 9.77E-08 U-234 U-235 U-238 Pu-238 -<0.011 5.60E-04 Pu-239 <0.01 2.82E-04 Pu-241 -0.10 2.25E-02 Am-241 <0.01 4.85E-04 Pu-242 <0.01 2.60E-07 Cm-242 <0.01 3.04E-05

- Cm-244 -- <0.01 -- - 5.84E-04

_____ ____ _ 2.30E+01 Millstone Unit 3 Page 18 of 25

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.

NEW1 idn-TdUd ffEFWWq-f gr6ra MIN IOW6WH90-Z"'

H-3 1.83 3.22E-02 C-1 4 0.03 5.33E-04 Na-22 Cr-51 Mn-54 0.17 2.95E-03 Fe-55 77.17 1.36E+00 Fe-59 Co-57 Co-58 Co-60 - -10.73 1.89E-01 Ni-63 9.30 1.64E-01 Zn-65 Rb-83 Sr-89 Sr-90 Nb-95 Zr-95 Tc-99 Ru-103 Ru-106 Ag-1I Om Sn-113 Sb-1 24 -

Sb-1 25 -0.31 - 5.55E-03 1-129 Cs-134

'Cs-137 - 0.45 7.93E-03 Ce-144 .

U-234 U-235 U-238 Pu-238 <o.01 2.37E-06 Pu-239 <0.01 1.90E-06 Pu-241 0.01 1.83E-04 Am-241 <0.01 2.79E-06 Pu-242 _

Cm-242 <0.01 5.92E-06 Cm-244 <0.01 9.96E-06 a _1 - 1.76E+OO Millstone Unit 3 Page 19 of 25

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 Facility for Thermal Destruction 4

IR; Fr9drd nifd IidQ- HT16farN rOffCQ-deR.W:v H-3 0.11 5.62E-02 C-14 0.07 3.59E-02 Na-22 Cr-51 Mn-54 2.14 t.06E+OO Fe-55 19.86 9.85E+00 Fe-59 Co-57 Co-58 0.32 1.57E-01 Co-60 12.83 6.36E+00 Ni-63 61.02 3.03E+01 Zn-65 Rb-83 Sr-89 Sr-90 0.02 1.06E-02 Nb-95 Zr-95 Tc-99 Ru-1 03 Ru-1 06 Ag-11 Om Sn-1 13 Sb-124 Sb-125 1.11 5.48E-01 1-129 Cs-134 Cs-137 2.51 1.24E+00 Ce-i44 U-234 U-235 U-238 Pu-238 <0.01 2.36E-04 Pu-239 <0.01 2.28E-05 Pu-241 <0.01 3.82E-03 Am-241 <0.01 1.06E-04 Pu-242 Cm-242 <0.01 5.25E-05 Cm-244 <0.01 2.25E-04 (I____InWV 4.96E+01 Millstone Unit 3 Page 20 of 25

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.

rIF3d-dj-0-JjddrWt-L'SM.", Wmr&NIM-MI-M,(;0W4VI H-3 1.96 2.22E-02 C-14 0.09 1.03E-03 Na-22 Cr-51 0.17 1.88E-03 Mn-54 4.23 4.79E-02 Fe-55 50.78 5.74E-01 Fe-59 <0.01 5.55E-08 Co-57 <0.01 1.10E-04 Co-58 6.49 7.33E-02 Co-60 10.55 1.19E-01 Ni-63 8.96 1.01E-01 Zn-65 Rb-83 Sr-89 <0.01 5.45E-09 Sr-90 <0.01 8.12E-06 Nb-95 <0.01 8.01 E-02 Zr-95 - <0.01 3.74E-02 Tc-99 <0.01 4.37E-09 Ru-1 03 Ru-106 Ag-11 Om Sn-I 13 <0.01 8.75E-06 Sb-1 24 <0.01 2.40E-08 Sb-125 0.07. 7.41 E-04 1-129 Cs-134 <0.01 5.76E-05 Cs-137 6.29 7.11 E-02 Ce-144 U-234 U-235 U-238 Pu-238 <0.01 1.36E-06 Pu-239 <0.01 7.21 E-07 Pu-241 <0.01 6.20E-05 Am-241 <0.01 1.19E-06 Pu-242 -

Cm-242 <0.01 1.19E-06

- Cm-244 <0.01 2.50E-06

___________ __ 1.13E+00 Millstone Unit 3 Page 21 of 25

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

d. Other - (Mixed Waste)

From Millstone Nuclear Power Station to Perma-Fix Environmental Services, Gainesville FL for Stabilization, Fuel Blending, etc.

K4ljMd Oh fib Ircr&., M--PV -qffTd't5TR-'II0-%KQVff 0`1W.

H-3 5.83 2.47E-05 C-14 1.35 5.71 E-06 Na-22 Cr-51 Mn-54 <0.01 1.36E-10 Fe-55 - 40.26 1.71 E-04 Fe-59 -

Co-57 Co-58 4.51 - 1.91 E-05 Co-60 19.15 8.13E-05 Ni-63 18.18 7.72E-05 Zn-65 _

Rb-83 .

Sr-89 Sr-90 0.05 2.22E-07 Nb-95 Zr-95 _

Tc-99 Ru-1 03 -

Ru-1 06 Ag-1r1 Om Sn-113 Sb-124 Sb-125 _

1-129 Cs-134 Cs-137 10.67 4.53E-05 Ce-144 U-234 U-235 U-238 Pu-238 Pu-239 Pu-241 Am-241 _

Pu-242 Cm-242 Cm-244 -

4.24E-04 Millstone Unit 3 Page 22 of 25

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

d. Other - (Water)

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

a a Onuld to o FqUofa IV, 1g Uaff-es:mI H-3 97.91 1.33E-01 C-14 <0.01 1.81 E-06 Na-22 <0.01 1.23E-06 Cr-51 0.03 4.46E-05 Mn-54 0.04 5.04E-05 Fe-55 0.69 9.44E-04 Fe-59 <0.01 1.90E-06 Co-57 <0.01 2.13E-06 Co-58 -0.29 3.91 E-04 Co-60 0.20 2.75E-04 Ni-63 0.15 2.08E-04 Zn-65 0.01 1.47E-05 Rb-83 <0.01 3.33E-08 Sr-89 Sr-90 =

Nb-95 0.02 3.24E-05 Zr-95 0.01 1.78E-05 Tc-99 Ru-103 <0.01 2.13E-06 Ru-1 06 .

Ag-11 Om Sn-113 Sb-1 24 - _

Sb-1 25 <0.01 5.53E-06 1-129 Cs-134 0.08 1.06E-04 Cs-137 0.55 7.46E-04 Ce-144 _

U-234 <0.01 2.28E-06 U-235 <0.01 - 1.16E-08 U-238 -<0.01 1.18E-07 Pu-238 <0.01 - 1.81 E-07 Pu-239 <0.01 1.OOE-07 Pu-241 Am-241 - <0.01 1.68E-07 Pu-242 Cm-242 Cm-244

_OT___ __ 1.36E-01 Millstone Unit 3 Page 23 of 25

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.

jj-F.U#djft-04.W M-,Wb. ff-qtaM'jW-H-3 I.

4 C-14 Na-22 1-4 Cr-51 Mn-54 1.46 - 1.98E-07 Fe-55 46.63 6.30E-06 Fe-59 Co-57 0.12 1.66E-08 Co-58 9.05 1.22E-06 Co-60 15.57 2.1 OE-06 Ni-63 -12.16 - 1.64E-06 Zn-65 Rb-83 _ _

Sr-89 Sr-90 0.32 4.37E-08 Nb-95 Zr-95 Tc-99 Ru-103 Ru-106 Ag-11 Om Sn-113 Sb-124 Sb-1 25 1-129 Cs-1 34 0.79 1.07E-07 Cs-137 13.89 1.88E-06 Ce-144 _

I U-234 U-235 U-238 Pu-238 Pu-239 Pu-241 Am-241 Pu-242 Cm-242 Cm-244 _

____T ___ ___ 1.35E-05 Millstone Unit 3 Page 24 of 25

3. Solid Waste Disposition (Shipments from Millstone) 1I 070iS1i9iiII ti9. a-4 =

4 - Truck (Sole Use Vehicle) Chem-Nuclear Services - Barnwell, SC 13 lTruck (Sole Use Vehicle) Duratek Inc. - Oak Ridge, TN

- 1 Truck (Sole Use Vehicle) Perma-Fix Environmental Services - Gainesville FL 1 Truck (Sole Use Vehicle) lStudsvik Processing Facility, LLC - Erwin, TN B. IRRADIATED FUEL SHIPMENTS (Disposition)

No Shipments in 2002 NIA N/A Millstone Unit 3 Page 25 of 25

3.0 REMODCM Changes In 2002, the following changes were made to the Millstone REMODCM:

Chance # Rev Effective Date 01-03 23 January 8, 2002 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 2002 is provided to the Nuclear Regulatory Commission as Volume II of this report.

REMODCM Rev 23 Description of Changes and Radiological Environmental Review

I REMODCM Change Request - Routing and Cover Sheet Change Request #: 01-03 I. Description of changes (include markup pages) and implementing documents IA Originator name (Print): Claude Flory Section/Page Section Title and Description of Change with Basis Documents Lb& Kadiological Environmental Monitoring - Sampling and Analysis I.E.1/I.1E-2 I. Corrected references: None from - IV.E.lb, IV.E.2.b, IV.E.2.c, V.E.L.b, V.E.2.b, and V.E.2.c to IV.D.L.b, IV.D.2.b, IV.D.2.c, V.D..l.b, V.D.2.b, and V.D.2.c

-I.E. 1/I.E-3,5 2. Increased the total number of environmental TLDs from 36 to 40 None by adding four TLDs used to support the Millstone Emergency Plan. As part of this change-the footnote at bottom of Table I.E-2 was revised so that it no longer states that there are additional TLDs which are used in the emergency plan. With the addition of the four TLDs, all TLDs will now be listed in this table. This makes the REMODCM consistent with the Millstone Emergency Plan.

I.E. 1fI.E-4,5 3. Added "Onsite" to names for locations #5, 6, 7, 8, 9, 44 and 45 to None be consistent with other onsite location names:

I.E.1/I.E-5 4. Changed name of location 44 from "Old Schoolhouse" to None "Schoolhouse" and of location 53 from "Rt. 156&Gardiners Wood Rd" to "Gardiners Wood Rd" for the convenience of a shorter name.

I.E.1/I.E-5 5. Changed name of location 45 from "North Access Point" to None "Access Road" to be more accurate in describing the location.

II.E Liquid Monitor Setpoints II.E.4/II.E-4 Condensate Polishing Facility Waste Neutralization Sump Effluent CP2809E Line - CND245 SP2864 Revised setpoint based on background from two times to ten times monitor background to avoid an unnecesarily low setpoint. A setpoint of two times background was tripping on normal instrumentation signal flucations. An upper limit on background based setpoint of 1.7E-4 uCi/ml is added to guard against unacceptable increses in monitor background: This upper limits ensures that Specification IV.D.I.a is not exceeded.

If more space is needed, use MP-13-REM-SAP01-002 Yes fl No 3 Originator ' Date: - /

signature: '{/lo /

MP-13-REM-SAPO1-001 Rev. 000 I of 2

REMM Revision 23 I.E. RADIOLOGICAL ENVIRONMENTAL MONITORING (Cont'd)

When radionuclides other than those in Table L.E-3 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the appropriate calendar year limit of the RadiologicalEffluent Controls (Sections II.D. L.b, IlI.D.2.b, or lII.D.2.cfor Unit I; Sections IV.ED.Ib, V.D.2. b, orlV.ED.2.cfor Unit 2; andSections V ED.l.b, 1'.ED.2.b, or VED.2.cfor Unit 3). This report is not required if the measured level of radioactivity was not the result of plant effluents, however, in such an event, the condition shall be reported and described in the Annual RadiologicalEnvironmental OperatingReport.

The detection capabilities required by Table L.E-4 are state-of-the-art for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. All analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual RadiologicalEnvironmental OperatingReport.

I.E-26 I

REMM Revision 23 TABLE I.E-1 MILLSTONE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Number of Sampling and Collection Type and Frequency of Analysis Sample Locations Frequency

1. Gamma Dose - 634 f ' Quarterly Gamma Dose - Quarterly

- Environmental TLD I 2.Airborne Particulate 8 Continuous sampler - Gross Beta - Weekly weekly filter change Gamma Spectrum - Quarterly on composite (by location), and on individual sample if gross beta is greater than 10 times the mean of the weekly control station's gross beta results

3. Airborne Iodine 8 Continuous sampler - 1-131 - Weekly weekly canister change

4. Vegetation 5 One sample near middle Gamma Isotopic on each sample and one near end of growing season

5. Milk 3 Semimonthly when Gamma Isotopic and 1-131 on each animals are on pasture; sample; Sr-89 and Sr-90 on Quarterly monthly at other times. Composite 5a.Pasture Grass 3 Sample as necessary to Gamma Isotopic and 1-131 substitute for unavailable milk

6. Sea Water 2 Continuous sampler with a Gamma Isotopic and Tritium on each monthly collection at sample.

indicator location.

Quarterly at control location - Composite of 6 weekly grab samples

7. Bottom Sediment 5 Semiannual Gamma Isotopic on each sample 7a. Soil 3 Quarterly- Gamma Isotopic on each sample

8. Fin Fish-Flounder and 2 Quarterly Gamma Isotopic on each sample one other type of edible fin fish (edible portion)

9. Mussels (edible portion) 2 Quarterly -Gamma Isotopic on each sample 90.Oysters (edible portion) 4 Quarterly ' - Gamma Isotopic on each sample 1 .Clamrs (edible portion) 2 Quarterly - Gamma Isotopic on each sample 12Lobsters (edible 2 Quarterly Gamma Isotopic on each sample-portion)

(a) Two or more TLDs or TLD with two or more elements per location.

1.E-34 I

REMM Revision 23 TABLE I.E-2 ENVIRONMENTAL MONITORING PROGRAM Sampling Locations The following lists the environmental sampling locations and the types of samples obtained at each location.

Samppling locations are also shown on Figures I.E-I;-I.E-2, and I.E-3:

Location Direction &

Number* Name - Distance from Sample Types Release Point**

1-1 Onsite - Old Millstone Road 0.6 Mi, NNW TLD, Air Particulate, Iodine, Vegetation 2-1 Onsite - Weather Shack 0.3 Mi, S - TLD, Air Particulate, Iodine 3-I Onsite - Bird Sanctuary 0.3 Mi, NE - TLD, Air Particulate, Iodine, Soil 4-1 Onsite - Albacore Drive 1.0 Mi, N TLD, Air Particulate, Iodine, Soil 5-1 Onsite - MP3 Discharge 0.1 Mi, SSE TLD 6-I Onsite - Quarry Discharge 0.3 Mi, SSE - TLD 7-I Onsite - Environmental Lab Dock 0.3 Mi, SE TLD 8-I Onsite - Environmental Lab 0.3 Mi, SE - TLD 9-1 Onsite - Bay Point Beach - 0.4 Mi, W TLD 10-1 Pleasure Beach 1.2 Mi, E TLD, Air Particulate, Iodine, Vegetation 11-1 New London Country Club 1.6 Mi, ENE - - TLD, Air Particulate, Iodine C Fisher's Island, NY 8.0 Mi, ESE TLD 13-C Mystic, CT 11.5 Mi, ENE TLD 14-C Ledyard, CT 12.0 Mi, NE TLD, Soil I5-C - Norwich, CT 14.0 Mi, N TLD, Air Particulate, Iodine 16-C Old Lyme, CT 8.8 Mi, W TLD -

17-1 Site Boundary 0.5 Mi, NE Vegetation 21-1 Goat Location No. 1 2.0 Mi., N Milk 22-1 Goat Location No.2 - 5.2 Mi, NNE Milk -

24-C Goat Location No.3 29 Mi, NNW Milk 25-I Fruits & Vegetables Within 10 Miles Vegetation 26-C Fruits & Vegetables Beyond 10 Miles Vegetation 27-1 Niantic - 1.7 Mi, WNW TLD, Air Particulate, Iodine 28-1 Two Tree Island 0.8 Mi, SSE Mussels 29-1 West Jordan Cove 0.4 Mi, NNE Clams 30-1 Niantic Shoals 1.5 Mi, NNW Mussels 31-I Niantic Shoals - 1.8 Mi, NW - Bottom Sediment, Oysters 32-1 Vicinity of Discharge Bottom Sediment, Oysters, Lobster, Fish, Seawater -

33-1 Seaside Point - 1.8 Mi, ESE Bottom Sediment 34-1 Thames River Yacht Club - 4.0 Mi, ENE Bottom Sediment 35-1 Niantic Bay 0.3 Mi, WNW Lobster, Fish 36-I Black Point - 3.0 Mi, WSW - Oysters - -

37-C Giant's Neck - 3.5 Mi, WSW Bottom Sediment, Oysters, Seawater 38-1 Waterford Shellfish Bed No. I 1.0 Mi, NW - Clams

- I = Indicator; C = Control

• • = The release points are the Millstone Stack for terrestrial locations and the-end of the quarry for aquatic location.

I.E- 44 I

REMM Revision 23 TABLE I.E-2 (cont.)

ENVIRONMENTAL MONITORING PROGRAM Sampling Locations Location

- Direction &

Number* Name Distance from Sample Types Release Point**

41-1 Myrock Avenue 3.2 Mi, ENE -_TLD 42-1 Billow Road 2.4 Mi, WSW TLD-43-1 Black Point 2.6 Mi, SW - TLD ---

44-I Onsite O44-Schoolhouse 0.1 Mi, NNE TLD 45-I Nlorth Acocss PointOnsite Access 0.5 Mi, NNW TLD Road -

46-I Old Lyme - Hillcrest Ave. 4.6 Mi, WSW - TLD 47-I East Lyme - W. Main St. 4.5 Mi, W - TLD 48-I - East Lyme - Corey Rd.- 3.4 Mi, WNW TLD 49-1 East Lyme - Society Rd. 3.6 Mi, NW TLD 50-1 East Lyme - Manwaring Rd. 2.1 Mi, W TLD 51-I East Lyme - Smith Ave. 1.5 Mi, NW TLD 52-I Waterford - River Rd. 1.1 Mi, NNW TLD 53-1 Waterford - Rt-.156--Gardiners 1.4 Mi, NNE TLD Wood Rd. -

I 55-I Waterford - Magonk Point 1.8 Mi, ESE TLD 56-1 New London - Mott Ave. 3.7 Mi, E TLD 57-1 New London - Ocean Ave. 3.6 Mi, ENE TLD 59-1 Waterford -Miner Ave. 3.4 Mi, NNE TLD 60-1 Waterford - Parkway South 4.0 Mi, N TLD 61-1 Waterford - Boston Post Rd. 4.3 Mi, NNW TLD 62-1 East Lvme - Columbus Ave. 1.9 Mi,-WNW - TLD 63-1 Waterford - Jordon Cove Rd. 0.8 Mi. NE TLD 64-I Waterford - Shore Rd. - 1.1 Mi ENE TLD 65-1 Waterford - Bank St. 3.2 Mi, NE TLD

- I = inaicator; C = Control. -

• • = The release points are the Millstone Stack for terrestrial locations and the end of the quarry for aquatic location.

NOTE: Environmental TLDs also function as accident TLDs in support of the Millstone Emergency Plan. -The 36 listed lccationz for TLD- aro the number ofenvironmenta LD rquird by Table I.E 1. There are-additional TLDs aeplayeo in M Oeffircnment net listed in this table. including T-LDs necdez to- comrnph Aiht; Miltn Emer-geney Plai+ ---r L.E-55 I

IODCM Revision 23 II.E. LIQUID MONITOR SETPOINTS (Cont'd)

4. Condensate Polishing Facility Waste Neutralization Sump Effluent Line - CND245 When the grab sample prior to release required by Table I.C-2 is greater than 5 x 10' uCi/ml, the setpoint shall be determined as for the Clean and Aerated Liquid Monitors in Section II.E.3 except the CPF monitor has the capability to readout in CPM or pCitml. If the grab sample is less than 5 x 10-'uCi/ml, use a setpoint of the lower of tweten times background or the value as specified in II.E.3. A setpoint based on ten times background shall not exceed a reading corresponding to 1.7E4 uCi/ml. which is approximately 38,000 CPM based on recent calibration data.

5a. Unit 2 Steam Generator Blowdown - RM4262 Assumptions used in determining the Alarm setpoint for this monitor are:

a. Total S.G. blowdown flow rate 700 gpm.

b. Normal minimum possible circulating water dilution flow during periods of blowdown = 200,000 gpm (2 circulating water pumps) = 200,000 gpm.

c. The release rate limit is conservatively set at 10% of the IOCFRPart20 limit for 1-131 (0.1 x 3 x 10'7 PCi/ml = 3 x 10-' PCifml)*

d. Background can be added after above calculations are performed.

Therefore, the alarm setpoint corresponds to a concentration of:

Alarm (,uCi/ml) = 200,000 x 3 x I0 + background** - 8.5 x 10' pCilml + background 700 The latest monitor calibration curve shall be used to determine ihe alarm setpoint in cpm corresponding to 8.5 x 10' PCi/ml.

This setpoint may be adjusted (increased or decreased) through proper administrative controls if the steam generator blowdown rate is maintained other than 700 gpmn and/or other than 2 circulating water pumps are available.' The adjustment would correspond to the ratio of flows to those assumed above or.

Alarm (uCi /ml) = 8.5 x Io-6 Ci/Ml x circulating &service water flow (gpm) 700 200,000 SIG blowdown (gpm)

Background = 3xl-pCis/ml . circulating &service water flow(gpm)+ Background total S/G blowdown (gpm)

Note: The Steam Generator Blowdown alarm criteria is in practice based on setpoints required to detect allowable levels ofprimary to secondary leakage. This alarm criteria is typically more restrictive than that required to meet discharge limits.

This fact shall be verified, however, whenever the alarm setpoint is recalculated.

• In lieu of using the 1-131 MPC value, the identified MPC values for unrestricted area may be used. - -

• • Background of monitor at monitor location (i.e., indication provided by system monitor with no activity present in the monitored system).

II.E14

RADIOLOGICAL ENVIRONMENTAL REVIEW RER-02-001 Revision 0 for REMODCM Rev 23 January 8,- 2002 Total Number of Pages: 2 Claude Flory - a Xt I

Preparer , Date William Eakin Date

RER-02-001 Revision 0 REMODCM Revision 23

1.0 DESCRIPTION

OF CHANGE, List of changes for REMODCM Revision 23:

In Section L.E, 'Radiological Environmental Monitoring - Sampling and Analysis":

1. Corrected internal references from IV.E.1b, IV.E.2.b, IV.E.2.c, V.E.1.b, V.E.2.b, and V.E.2.c to IV.D.1.b, IV.D.2.b, IV.D.2.c, V.D.1.b, V.D.2.b, and V.D.2.c

2. Increased the total number of environmental TLDs from 36 to 40 by adding four TLDs. As part of this change the footnote at bottom of Table l.E-2 was revised so that it no longer states that there are additional TLDs which are used in the emergency plan.

3. Added "Onsite' to names for locations #5, 6,-7, 8, 9, 44 and 45 to be consistent with other onsite location names.

4. Changed name of location 44 from 'Old Schoolhouse" to "Schoolhouse" and of location 53 from 'Rt. 156&Gardiners Wood Rd" to Gardiners Wood Rd' for the convenience of a shorter name.

5. Changed name of location 45 from 'North Access Point' to 'Access Road" to be more accurate in describing the location.

In Section Il.E, "Liquid Monitor Setpoints":

Revised the setpoint for the Condensate Polishing Facility (CPF) Waste Neutralization Sump Effluent Line Radiation Monitor (CND245). The requirement was changed from two times background to ten times monitor background.

2.0 DISCUSSION Changes in Section I.E to correct wrong internal references and revise location names are self-explanatory or briefly explained in the Description of Change.

The increased in total number of environmental TLDs from 36 to 40 was done in support of the Millstone Emergency Plan. With the addition of the four TLDs, all TLDs used for both -

environmental monitoring and for accident assessment will now be listed in this table. This makes the REMODCM consistent with statements in the Millstone Emergency Plan.

The CPF Waste Neutralization Sump Radiation Monitor setpoint requirement was revised to avoid an unnecessarily low setpoint. -A setpoint of two times background was tripping on normal instrumentation signal fluctuations. An upper limit on background based setpoint of 1.7E-4 uCiml is added to guard against unacceptable increases in monitor background. This upper limits ensures that Specification IV.D.1.a is not exceeded and has the same basis as the limit on setpoint for the other liquid radwaste radiation monitors.

3.0 CONCLUSION

The changes in Revision 23 to the REMODCM would not cause an increase in release of radioactivity to the environment or of dose to the public and they do not deviate from any of the design bases for an effluent control program in the FSAR for Millstone Units 2 and 3 or in the DSAR for Millstone Unit 1. The changes will not affect the level of radioactive effluent control required by each unit's Technical Specifications and FSAR, 10CFR20, 40CFR190, IOCFR50.36a, and Appendix I of 10CFR50 and will not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations. The changes do not cause an Unreviewed Radiological Environmental Impact (UREI). '

4.0 Inoperable Effluent Monitors During the period January 1 through December 31, 2002,- the following effluent monitors were inoperable for more than 30 consecutive days:

4.1 Unit I -

The MPI BOP balance of plant sampler was declared inoperable from September 23

@ 10:03 to November 2 @ 09:00 for a total of 39 days due to a lightning strike which failed the sample flow control valve. The purchased replacement flow control valve did not arrive on site until October 31. The valve was installed and the monitor' declared operable on November 2. Operability was not restored within 30 days as required because there were no spares on site. Corrective actions include stocking a spare flow control valve for this application. During the period that the monitor was inoperable, periodic samples were collected and analyzed as required.

4.2 Unit 2-The MP2 WRGM wide range gas monitor was declared inoperable from September 20 @

03:32 to October 23 @ 11:13 for a total of 33 days due to a lightning strikeMwhich

- damaged several components of the monitor. The control room indication was'damaged such that it would loose communication with the monitor for 10 to 15 seconds at a time causing alarms. The power isolation card and the 1/O card were also replaced.

Operability was not restored within 30 days as required because the required troubleshooting exceeded our on site capability in experience and in spare parts. We were not prepared to diagnose the multiple failures caused by the lightning strike. We were forced to bring in the vendor and to wait several days as he was at another site when we called. Our supply of spare parts did not include the control room indication that failed.

Corrective actions include analysis of the failed components to identify the failure

- mechanism. During the period that the monitor was inoperable, samples were collected and analyzed, and flow rates were periodically estimated as required.

4.3 Unit 3- None

5.0 Errata None