ML071270276

Radioactive Effluent Report, Release Report, Volume 1

ML071270276
Person / Time
Site:	Millstone
Issue date:	12/31/2006
From:	Dominion Nuclear Connecticut
To:	NRC/FSME
References
07-0244
Download: ML071270276 (89)

Text

Serial No. 07-0244 Docket Nos. 50-245 50-336 50-423 License Nos. DPR-21 DPR-65 NPF-49 ATTACHMENT 1 2006 RADIOACTIVE EFFLUENT RELEASE REPORT VOLUME I MILLSTONE POWER STATION UNITS 1, 2, AND 3 DOMINION NUCLEAR CONNECTICUT, INC. (DNC)

19r JilJJcE~1DLI? I 2006 Radioactive Effluent Report Release Report Volume 1 Gasedu*..ffiuents

• Dominion Nuclear Connecticut, Inc.

MILLSTONE UNIT LICENSE DOCKET I DPR-21 50-245 2-----1001wRww 2 3

DPR-65 NPF-49 50-336 50-A23

Table of Contents Volume 1 Table of Contents ......................................................................................................................... 1 List of Tables ................................................................................................................................ 2 References ................................................................................................................................... 3 Introduction ............................................................................................................... .................. 4 1.0 Off-Site Doses ....................................................................................................................... 5 1.1 Dose Calculations ...................................................................................................... 5 1.1.1 Airborne Effluents .......................................................................................... 5 1.1.2 Liquid Effluents ............................................................................................. 6 1.2 Dose Results .................................................................................................................. 7 1.2.1 Airborne Effluents .......................................................................................... 7 1.2.2 Liquid Effluents ............................................................................................. 7 1.2.3 Analysis of Results ........................................................................................ 7 2.0 Effluent Radioactivity ........................................................................................................... 12 2.1 Airborne Effluents ..................................................................................................... 12 2.1.1 Measurement of Airborne Radioactivity ......................................................... 12 2.1.2 Estimate of Errors ....................................................................................... 14 2.1.3 Airborne Batch Release Statistics ............................................................... 15 2.1.4 Abnormal Airborne Releases ........................................................................ 15 2.2 Liquid Effluents .................................................................................................................... 33 2.2.1 Measurement of Liquid Radioactivity ........................................................... 33 2.2.1.1 Continuous Liquid Releases ............................................................... 33 2.2.1.2 Liquid Tanks/Sum ps .......................................................................... 33 2.2.2 Estimate of Errors ....................................................................................... 33 2.2.3 Liquid Batch Release Statistics ................................................................... 34 2.2.4 Abnormal Liquid Releases .......................................................................... 34 2.2.5 Liquid Release Tables ................................................................................. 34 2.3 Solid W aste .......................................................................................................................... 47 2.4 Groundwater Monitoring .................................................................................................. 76 3.0 Inoperable Effluent Monitors ............................................................................................ 77 4.0 Operating History ................................................................................................................ 78 5.0 Errata .................................................................................................................................. 80 6.0 REMODCM Changes .......................................................................................................... 81 6.1 REMODCM Rev 25 Description of Changes .................................................. 82 Volume 2 2006 REMODCM Revision 25-02 1

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

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

& Spent Fuel Pool Evaporation Table 2.2-A3 Unit 2 Airborne Effluents - Mixed / Elevated Batch - Containment Purges Table 2.2-A4 Unit 2 Airborne Effluents - Elevated Batch - WGDT Table 2.2-A5 Unit 2 Airborne Effluents - Elevated Continuous - Containment Vents/Site stack Table 2.2-A6 Unit 2 Airborne Effluents - Ground Batch - Containment Equipment Hatch Table 2.2-A7 Unit 2 Airborne Effluents - Ground Batch - RWST Vent Table 2.2-L1 Unit 2 Liquid Effluents - Release Summary - Quarry Table 2.2-L2 Unit 2 Liquid Effluents - Continuous - SGBD Table 2.2-L3 Unit 2 Liquid Effluents - Batch - LWS Table 2.2-L4 Unit 2 Liquid Effluents - Continuous - Turbine Building Sump - Yard Drain DSN 006 Table 2.3-Al Unit 3 Airborne Effluents - Release Summary Table 2.3-A2 Unit 3 Airborne Effluents - Mixed Continuous - Vent & Spent Fuel Pool Evaporation Table 2.3-A3 Unit 3 Airborne Effluents - Ground Continuous - ESF Building Ventilation Table 2.3-A4 Unit 3 Airborne Effluents - Mixed Batch - Containment Drawdowns Table 2.3-A5 Unit 3 Airborne Effluents - Mixed Batch - Containment Purges Table 2.3-A6 Unit 3 Airborne Effluents - Elevated Continuous - Gaseous Waste System & Containment Vents Table 2.3-A7 Unit 3 Airborne Effluents - Ground Batch - Containment Equipment Hatch Table 2.3-A8 Unit 3 Airborne Effluents - Ground Batch- RWST Vent Table 2.3-L1 Unit 3 Liquid Effluents - Release Summary - Quarry Table 2.3-L2 Unit 3 Liquid Effluents - Continuous - SGBD, SW & TK2 Table 2.3-L3 Unit 3 Liquid Effluents - Batch - LWS Table 2.3-L4 Unit 3 Liquid Effluents - Batch - CPF Waste Neutralization Sumps & Hotwell Discharge Table 2.3-L5 Unit 3 Liquid Effluents - Release Summary - Yard Drain DSN 006 Table 2.3-L6 Unit 3 Liquid Effluents - Continuous - Turbine Building Sump Table 2.3-L7 Unit 3 Liquid Effluents - Batch - WTT Berm Water Table 2.1-S Unit 1 Solid Waste & Irradiated Component Shipments Table 2.2-S Unit 2 Solid Waste & Irradiated Component Shipments Table 2.3-S Unit 3 Solid Waste & Irradiated Component Shipments Table 2.4-GW Groundwater Monitoring Results 2

References

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

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

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

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

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

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

12. Memo No. MP-HPO-07024, 2006 Report on Solid Waste and Irradiated Component Shipments, April 9, 2007.

13. Memo No. NAF-07-035, 40CFR1 90 Offsite Dose Estimate for 2006, April 9, 2007.

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Introduction This report, for the period of January through December of 2006, is being submitted by Dominion Nuclear Connecticut, Inc. for Millstone Power Station's Units 1, 2, and 3, in accordance with 10CFR50.36a, the REMODCM, and the Station's Technical Specifications. A combined report, written in the US NRC Regulatory Guide 1.21 format, is submitted for all three units.

Volume 1 contains radiological and volumetric information on airborne and liquid effluents, shipments of solid waste & irradiated components, calculated offsite radiological doses, all changes to the REMODCM, information on effluent monitors inoperable for more than 30 consecutive days, and corrections to previous reports. Volume 2 contains a full copy of each of the complete revisions to the REMODCM effective during the calendar year.

Nesting Ospreys 4

1.0 Off-Site Doses This report provides a summary of the 2006 off-site radiation doses from releases of radioactive materials in airborne and liquid effluents from Millstone Units 1, 2, and 3. This includes the annual maximum dose (mrem) to any real member of the public as well the maximum gamma and beta air doses.

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

1.1 Dose Calculations The off-site dose to humans from radioactive airborne and liquid effluents have been calculated using measured radioactive effluent data, measured meteorological data, and the dose computer models DOSAIR and DOSLIQ, which were developed by Millstone. The methodology and input parameters for DOSAIR are those used in GASPAR II (Reference 12) and NRC Regulatory Guide 1.109 (Reference 3). The methodology and input parameters for DOSLIQ are those used in LADTAP II (Reference 6) and NRC Regulatory Guide 1.109 (Reference 3). The calculated doses generally tend to be conservative due to the conservative model assumptions. More realistic estimates of the off-site dose can be obtained by analysis of environmental monitoring data. A comparison of doses estimated by each of the above methods is presented in the Annual Radiological Environmental Operating Report.

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

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

The dose calculations are based upon three types of input: radioactive source term, site-specific data, and generic factors. The radioactive source terms (Curies) are characterized in Section 2, Effluent Radioactivity, of this report. The site-specific data includes: meteorological data (e.g. wind speed, wind direction, atmospheric stability, etc.) to calculate the transport and dispersion of airborne effluents, and dilution factors for liquid effluents. The generic factors include the average annual consumption rates (for inhalation of air and ingestion of fruits, vegetables, leafy vegetables, grains, milk, poultry, meat, fish, and shellfish) and occupancy factors (for air submersion and ground irradiation, shoreline activity, swimming, boating, etc.). All these inputs are used in the appropriate dose models to calculate the maximum individual dose from radioactive airborne and liquid effluents.

1.1.1 Airborne Effluents Maximum individual doses due to the release of noble gases, radioiodines, and particulates were calculated using the computer code DOSAIR (Reference 11). This is equivalent to the NRC code, GASPAR II, which uses a semi-infinite cloud model to implement the NRC Regulatory Guide 1.109 (Reference 3) dose models.

The values of average relative effluent concentration (X/Q) and average relative deposition (D/Q) used in the DOSAIR code were generated using EDAN 3, a meteorological computer code which implements the assumptions cited in NRC Regulatory Guide 1.111 (Reference 5), Section C. The annual summary of hourly meteorological data (in 15-minute increments), which includes wind speed, 5

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. The doses were conservatively calculated using mixed mode 142 ft meteorology since DOSAIR may underestimate the plume exposure (prior to plume touchdown) for elevated releases from the Millstone Stack. All three units previously 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, therefore these doses were calculated using the 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. Doses from these release points were summed to determine the total Unit 1 airborne effluent dose.

Unit 2 Auxiliary Building Ventilation, Steam Generator Blowdown Tank Vent, and Containment Purge (through the Unit 2 Vent)(1 59 ft) releases are considered mixed mode (partially elevated and partially ground) continuous releases. The first two of these are continuous releases while the Containment Purge is typically a batch release. Some Containment Purges are released via the Millstone Stack.

Because doses for releases from the Unit 2 Vent and from the Millstone Stack are calculated using the same meteorology, the Containment Purge releases are not divided between Unit 2 Vent and Millstone Stack. Batch releases from the Waste Gas Decay Tanks and Containment Vents are typically discharged via the Millstone Stack. The doses for these elevated releases were conservatively calculated using mixed mode 142 ft meteorology for which the Pasquill stability classes are determined based upon the temperature gradient between the 33 ft and 142 ft meteorological tower levels. The Containment Equipment Hatch and the RWST Tank Vent releases are considered ground level where the 33 ft meteorology was used for the dose calculations. Each of the doses for the various release points were summed to determine the total Unit 2 airborne effluent dose.

The Unit 3 Vent (142.5 ft) is considered a mixed mode (partially elevated and partially ground) release point. The Pasquill stability classes are determined based upon the temperature gradient between the 33 ft and 142 ft meteorological tower levels. Auxiliary Building Ventilation is a mixed mode continuous release while Containment Purge and "initial" Containment Drawdown (through the roof of the Auxiliary Building) are considered mixed mode batch releases. Gaseous waste and operational containment drawdowns (also called containment vents) are released through the Unit 3 SLCRS system to the Millstone Stack (375 ft). The doses for these elevated releases were conservatively calculated using mixed mode 142 ft meteorology. The Engineered Safety Features Building (ESF)

Ventilation, the Containment Equipment Hatch, and RWST Vent releases are considered ground level where the doses were calculated using 33 ft meteorology. Similar to Unit 2, each of the doses for the various release points were summed to determine the total Unit 3 airborne effluent dose.

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

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

1.2.1 Airborne Effluents For the dose to the maximum individual, DOSAIR calculates the dose to the whole body, GI-tract, bone, liver, kidney, thyroid, lung, and skin from each of the following pathways: direct exposure from noble gases in the plume and from ground deposition, inhalation, and ingestion of vegetation, cow or goat milk, and meat. The values presented are a total from all pathways. However, only the whole body, skin, thyroid and maximum organ (other than thyroid) doses are presented.

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

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

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

To determine compliance with 10CFR50, Appendix I (Reference 7), the maximum individual whole body and organ doses include all applicable external pathways (i.e. plume and ground exposure) as well as the internal pathways (inhalation and ingestion).

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

1.2.3 Analysis of Results Table 1-3 provides a quantitative dose comparison with the limits specified in the REMODCM. The data indicates that the total whole body and organ doses to the maximum offsite individual from Millstone Station including all sources of the fuel cycle are well within the limits of 40CFR190 (Reference 8). On-site radioactive waste storage during this year was within storage criteria and the maximum dose to a member of the public was approximately 0.22 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 dose to the maximum individual received from Millstone Station is small in comparison to the dose received from natural background radiation.

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Table 1-1 2006 Off-Site Dose Commitments from Airborne Effluents Millstone Units 1, 2, 3 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Total Max Air (mrad) (mrad) (mrad) (mrad) (mrad)

Beta 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Gamma 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.002+00 Max Individual (mrem) (mrem) (mrem) (mrem) (mrem)

Whole Body 3.09E-04 2.60E-04 2.60E-04 1.49E-04 9.78E-04 Skin 3.46E-04 2.64E-04 2.62E-04 1.49E-04 1.02E-03 Thyroid 3.08E-04 2.46E-04 2.51 E-04 1.49E-04 9.54E-04 Max organ+ 3.10E-04 3.41E-04 3.11 E-04 1.49E-04 1.11 E-03 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Total Max Air (mrad) (mrad) (mrad) (mrad) (mrad)

Beta 1.66E-03 4.02E-03 1.32E-03 8.03E-03 1.50E-02 Gamma 2.30E-03 2.51E-04 2.41E-04 9.92E-04 3.79E-03 Max Individual (mrtem) (inrem) (mrem) (mrem) (mrem)

Whole Body 2.59E-03 5.20E-03 8.12E-04 1.51 E-03 1.1E-02 Skin 4.05E-03 7.41 E-03 1.47E-03 2.83E-03 1.58E-02 Thyroid 3.71 E-03 1.20E-02 2.06E-02 2.18E-02 5.81 E-02 Max organ+ 2.60E-03 5.25E-03 8.84E-04 2.48E-03 1.12E-02 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Total Max Air (mrad) (mrad) (mrad) (mrad) (mrad)

Beta 5.49E-06 6.20E-06 8.89E-06 3.10E-06 2.37E-05 Gamma 1.07E-05 1.54E-04 2.21 E-05 8.09E-06 1.95E-04 Max Individual (mrem) (mrem) (mrem) (mrem) (mrem)

Whole Body 1.87E-03 2.51 E-03 7.23E-03 6.79E-04 1.23E-02 Skin 1.87E-03 2.51 E-03 7.23E-03 6.84E-04 1.23E-02 Thyroid 1.87E-03 2.51 E-03 7.22E-03 6.79E-04 1.23E-02 Max organ+ 1.87E-03 2.51 E-03 7.23E-03 6.79E-04 1.23E-02

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

Table 1-2 2006 Off-Site Dose Commitments from Liquid Effluents Millstone Units 1, 2, 3 F- Unit 1 1 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Total Max Individu (mrem) (mrem) (mrem) (mrem) (mrem)

Whole Body O.OOE+00 2.66E-07 O.OOE+00 O.OOE+00 2.66E-07 Thyroid O.OOE+00 7.63E-08 O.OOE+00 O.OOE+00 7.63E-08 Max Organ O.OOE+00 3.78E-07 O.OOE+00 O.OOE+00 3.78E-07 L A.IA.A Max Individual 1st(mrem)

Quarter 2nd(mrem)

Quarter 3rd(mrem)

Quarter 4th (mrem)

Quarter Annual Total (mrem)

Whole Body 9.93E-05 7.63E-05 8.78E-05 1.30E-04 3.93E-04 Thyroid 6.83E-05 6.43E-05 7.1OE-05 4.20E-05 2.46E-04 Max Organ 2.73E-04 3.16E-04 5.22E-04 1.75E-03 2.86E-03 IMax Individual 1st Quarter (mrem) 2nd Quarter (mrem) 3rd Quarter (mrem) 4th Quarter (mrem)

Annual Total (mrem)

Whole Body 4.96E-05 1.13E-04 6.90E-05 1.21 E-04 3.53E-04 Thyroid 2.87E-05 4.23E-05 2.94E-05 1.03E-04 2.03E-04 Max Organ 1.93E-04 7.15E-04 2.88E-04 1.76E-04 1.37E-03 9

Table 1-3 2006 Off-Site Dose Comparison to Limits Millstone Units 1, 2, 3 Airborne Effluents Max Individual Dose vs REMODCM Limits 1 T T T T Whole Body Thyroid Max Organ** Skin Beta Air Gamma Air (mrem) (mrero) (mrem) (mrem) (mrad) (mrad)

Unit 1 9.78E-04 9.54E-04 1.11E-03 1.02E-03 O.OOE+00 Q.OOE+00 Unit 2 1.01E-02 5.81E-02 1.12E-02 1.58E-02 1.50E-02 3.79E-03 Unit 3 1.23E-02 1.23E-02 1.23E-02 1.23E-02 2.37E-05 1.95E-04 Millstone Station 2.34E-02 7.14E-02 2.46E-02 2.91 E-02 1.51 E-02 3.98E-03

- 0 D PJJB l-=it-* JL ________ L 1~a ______, _ 1 __________

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

Unit I 2.66E-07 7.63E-08 3.78E-07 Unit 2 3.93E-04 2.46E-04 2.86E-03 Unit 3 3.53E-04 2.03E-04 1.37E-03 Millstone Station 7.46E-04 4.49E-04 4.23E-03

%0 w Max Individual Dose vs 40CFRI90 Limits Whole Body Thyroid, Max Organ **

(mrem) (mrem) (mrem)

Airborne Effluents 2.34E-02 7.14E-02 2.46E-02 Liquid Effluents 7.46E-04 4.49E-04 4.23E-03 Radwaste Storage 2.20E-01 2.20E-01 2.20E-01 Millstone Station 2.44E-01 2.92E-01 2.49E-01

....... - j -j

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

Table 1-4 2006 Offsite Dose Comparison Natural Background vs. Millstone Station Average Resident Natural Background Radiation Dose (NCRP 94)

Cosmic 27 mrem Cosmogenic 1 mrem Terrestial (Atlantic and Gulf Coastal Plain) 16 mrem Inhaled 200 mrem In the Body 40 mrem

-24 mrern Maximum Off-Site Individual Millstone Station Whole Body Dose Airborne Effluents 0.023 mrem Liquid Effluents 0.001 mrem On site RadWaste Storage 0.220 mrem 11

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

Unit 1 Spent Fuel Pool (SFPI) Island (no charcoal cartridge)

Unit 1 Balance of Plant (BOP) Vent (no charcoal cartridge)

Unit 2 Ventilation Vent Unit 2 Wide Range Gas Monitor (WRGM)

Unit 3 Ventilation Vent Unit 3 Supplementary Leak Collection and Recovery System (SLCRS)

Unit 3 Emergency Safeguards Facility (ESF) Building Vent Charcoal cartridges and particulate filters are used to collect iodines and particulates, respectively.

These filters are periodically replaced (typically weekly, except every two weeks for Unit 1) and then analyzed for isotopic content using a gamma spectrometer. Particulate filters are also analyzed for Sr-89 (for all but Unit 1), Sr-90 and gross alpha. At least monthly, gaseous grab samples are taken and analyzed for noble gasses and tritium. The gas washing bottle (bubbler) method is utilized for tritium collection. This sample is counted on a liquid scintillation detector. Isotopic concentrations at the release point are multiplied by the total flow to obtain the total activity released for each isotope.

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

Another continuous airborne pathway is the Unit 2 Steam Generator Blowdown Tank Vent. A decontamination factor (DF) across the SGBD Tank vent was determined for iodines by comparing the results of gamma spectrometry, HPGe, analysis of the Steam Generator Blowdown water and grab samples of the condensed steam exiting the vent. This DF was applied to the total iodine releases via the Steam Generator Blowdown water to calculate the iodine release out the vent. An additional factor of 0.33 was utilized to account for the fraction of blowdown water actually flashing to steam in the Steam Generator Blowdown Tank.

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

Unit 1 Reactor Building Evaporator (via BOP Vent)

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

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

Unit 2 and 3 Containment Equipment Hatch Openings Unit 2 and 3 Refueling Water Storage Tank (RWST) Vents Unit 3 Containment Drawdown 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 determine the total activity released.

Waste Gases from the Unit 2 Gaseous Waste Processing System are held for decay in waste gas decay tanks (6) prior to discharge through the Millstone Site Stack. Each gas decay tank is analyzed prior to discharge for noble gas and tritium. Calculated volume discharged is multiplied by the isotopic concentrations (noble gas and tritium) from the analysis of grab samples to determine the total activity released.

Containment air is sampled periodically for gamma and tritium to determine the activity released from containment venting. The measured concentrations are multiplied by the containment vent volume to obtain the total activity released. Unit 2 typically performs this process of discharging air from containment to maintain pressure approximately once per week while at Unit 3 it is more often (typically at least daily).

Containment air is sampled prior to each purge for gamma and tritium to determine the activity released from containment purging. Similar to containment venting, the measured concentrations are multiplied by the containment vent volume to obtain the total activity released.

Samples of air near the Containment Equipment Hatch openings are analyzed for particulates and iodines, during refueling outages for the period that the equipment hatch is open. An estimated flow out of the hatch and sample results are used to determine the radioactivity released.

When water is transferred to Refueling Water Storage Tank (RWST) there is a potential for a release of radioactivity through the tank vent. In previous years a decontamination factor (DF) was applied to the total iodine transferred from the water that is transferred to the RWST water to estimate the iodine released. Starting with the 2R17 outage, actual measurements were performed by suction on the tank. lodines and particulates were reduced prior to release by HEPA and charcoal filtration. All noble gases are assumed to be released through the tank vent.

Unit 3 containment is initially drawn down prior to startup. This is accomplished by using the containment vacuum steam jet ejector which releases through an unmonitored vent on the roof of the Auxiliary Building. Grab samples are performed prior to drawdown to document the amount of radioactivity released during these evolutions.

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

Sampling/Data Collection 10% Variation in data collection Sample Line Loss 20% Deposition of some nuclides Calibration 10% Calibration to NBS standards Sample Counting 10% Error for counting statistics Flow & Level Measurements 10% Error for release volumes 14

2.1.3 Airborne Batch Release Statistics Unit I - None Unit 2 Ctmt Purges Ctmt Vents WGDT Number of Batches 1 36 16 Total Time (min) 492 5569 8688 Maximum Time (min) 492 320 717 Average Time (min) 492 155 543 Minimum Time (min) 492 65 306 Unit 3 Ctmt Purges Ctmt Vents Drawdowns Number of Batches 0 278 0 Total Time (min)

• Maximum Time (min)

• Average Time (min)

• Minimum Time (min) *

• ~ 2-3 hrs per Vent 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.

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

15

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

1. Total Activity ci Released IC E. Tritium dash "-" denotes less than Minimum Detectable Activity (MDA) 16

Table 2.1-A2 Millstone Unit 1 Airborne Effluents Ground Continuous - Balance of Plant Vent & Spent Fuel Pool Island Vent I Nuclides 11[

0 I Released I Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total A. Fission & Activation Gases lKr-85 c- - I I - I Total Activity Ci - - -

B. lodines11-131 1 Ci I - I - - I - I -

Total Activity Ci - - I C. Particulates ICs-137 I Ci I 6.37E-06 I 2.07E-06 I 8.44E-07 I9.E06 Total Activity Ci 6.37E-06 2.07E-06 8.44E-07 I 9.29E-06 D. Gross Alpha IGross Alpha I C I - - - I E. Tritium HN-3 Ci I 2.86E-01 I 1.28E-01 I 1.25E-01 6.1OE-01 I 1.15E+001 dash "-" denotes less than Minimum Detectable Activity (MDA) 17

Table 2.2-Al Millstone Unit No. 2 Airborne Effluents - Release Summary Units i1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total A. Fission & Activation D. Gross Alpha

1. Total Activity Ci Released dash "-" denotes less than Minimum Detectable Activity (MDA) 18

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

& Spent Fuel Pool Evaporation Nuclides S I Released Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total A. Fission & Activation Gases Ar-41 Ci 1.17E+00 2.07E-02 2.56E-01 1.45E+00 Xe-1 33 Ci 5.23E-01 6.94E-01 2.34E-02 2.53E+00 3.77E+00 Xe-135 Ci 5.1OE-01 - 1.54E-02 1.30E-01 6.55E-01 Total Activity Ci 2.20E+00 6.94E-01 5.96E-02 2.92E+00 5.87E+00 B. lodines 1-131 Ci 2.12E-04 1.30E-04 2.23E-04 6.65E-04 1.23E-03 1-132 Ci 1.27E-04 8.24E-05 3.31E-04 7.25E-04 1.27E-03 1-133 Ci 7.46E-04 4.66E-04 7.56E-04 2.15E-04 2.18E-03 1-134 Ci ....

1-135 Ci 4.42E-04 2.08E-04 5.02E-04 1.45E-04 1.30E-03 Total Activity Ci 1.53E-03 8.87E-04 1 .81 E-03 1.75E-03 5.98E-03 C. Particulates 1-131 Ci Br-82 Ci - -

Co-58 Ci - 2.90E-07 2.90E-07 Co-60 Ci - -

Ru-1 03 Ci - -

Ru-1 06 Ci - 4.35E-06 4.35E-06 Cs-1 37 Ci - -

Sr-89 Ci - -

Sr-90 Ci - -

Total Activity Ci - 4.64E-06 4.64E-06 D. Gross Alpha IGross Alpha Ci I - - I E. Tritium

• IH-3 Ci 7.43E+00 1.33E+01I 1.03E+00 7.53E+00 2.93E+0I

• includes estimated spent fuel pool evaporation dash "-" denotes less than Minimum Detectable Activity (MDA) 19

Table 2.2-A3 Millstone Unit No. 2 Airborne Effluents - Mixed Batch - Containment Purges N11uc1id s I 0 Released I Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total A. Fission & Activation Gases Kr-85 Ci N/A N/A N/A 2.19E+00 2.19E+00 Xe-1 33 Ci N/A N/A N/A 1.08E+01 1.08E+01 Xe-135 Ci N/A N/A N/A 2.12E-03 2.12E-03 Total Activity Ci N/A N/A N/A 1.30E+01 1.30E+01 B. lodines

• 11-131 Ci I N/A I N/A I N/A I - -

Total Activity Ci N/A N/A N/A C. Particulates

• 1-131 Ci N/A N/A N/A Cs-137 Ci N/A I N/A N/A Total Activity Ci N/A N/A N/A D. Gross Alpha*

IGross Alpha I Ci N/A I N/A I N/A I E. Tritium IH-3 Ci N/A N/A N/A 6.99E-03 6.99E-03

• lodines, Particulates and Gross a included in Table 2.2-A2 or 2.2-A5 dash "-" denotes less than Minimum Detectable Activity (MDA) 20

Table 2.2-A4 Millstone Unit No. 2 Airborne Effluents - Elevated Batch - WGDT INuclidesle,200I Released I Units 1 1st Qtr I 2nd Qtr 3rd Qtr 4th Qtr I Total A. Fission & Activation Gases Kr-85 Ci 5.35E-01 1.39E+00 4.OOE-01 1.26E+00 3.59E+00 Xe-131m Ci 5.03E-03 6.80E-03 5.03E-03 8.07E-03 2.49E-02 Xe-133 Ci 1.10E-01 1.05E-01 1.82E-01 1.OOE-01 4.97E-01 Xe-133m Ci 3.22E-05 - 7.01 E-05 - 1.02E-04 Xe-i 35 Ci 5.05E-05 2.00E-05 - 7.05E-05 Total Activity Ci 6.50E-01 1.50E+00 5.87E-01 1.37E+00 4.11 E+O B. lodines

• 11-131 1 a i Total Activity Ci I I I C. Particulates

• 1-131 Ci-Cs-137 Ci Total Activity Ci D. Gross Alpha*

IGross Alpha I Ci I I -

E. Tritium H-3 Ci I 6.79E-04 2.75E-03 3.51 E-04 4.33E-04 4.21 E-03

• lodines, Particulates and Gross a included in Table 2.2-A2 or 2.2-A5 dash "-" denotes less than Minimum Detectable Activity (MDA) 21

Table 2.2-A5 Millstone Unit No. 2 Airborne Effluents - Elevated - Containment Vents/Site Stack Nuclides Released I Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th QtrI Total A. Fission & Activation Gases Ar-41 Ci 2.07E-02 2.1OE-02 2.60E-02 1.20E-02 7.96E-02 Kr-85 Ci 6.06E-01 9.40E-01 1.20E+00 7.36E-02 2.82E+00 Kr-87 Ci 7.45E-04 7.45E-04 Kr-88 Ci 1.40E-03 1.40E-03 Xe-1 33 Ci 1.37E-01 8.01 E-02 4.92E-02 1.41 E-02 2.80E-01 Xe-1 33m Ci 4.83E-04 4.83E-04 Xe-I 35 Ci 6.80E-03 7.68E-04 2.40E-04 2.77E-04 8.08E-03 Total Activity Ci 7.71 E-01 1.04E+00 1.28E+00 1.01 E-01 3.19E+00 B. lodines 1-131 Ci 7.19E-08 7.19E-08-]

1-133 2.52E-07 2.52E-07 Total Activity Ci 3.24E-07 3.24E-07 C. Particulates 1-131 Ci Br-82 Ci 1.47E-07 1.47E-07 Co-58 Ci 1.81E-07 1.81E-07 Co-60 Ci Ru-103 Ci Ru-i 06 Ci Cs-137 Ci Sr-89 Ci Sr-90 Ci Total Activity Ci 3.28E-07 3.28E-07 D. Gross Alpha Gross Alpha Ci - 1 - I E. Tritium H-3 Ci 3.01E-01I 4.15E-01i 5.91E-02 i1.05E-01i 8.79E-0I dash "-" denotes less than Minimum Detectable Activity (MDA) 22

Table 2.2-A6 Millstone Unit No. 2 Airborne Effluents - Ground Batch - Containment Equipment Hatch 2Nuclides 06 Released I Units 1 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total A. Fission & Activation Gases Ir-85 Ci N/A N/A N/A -

Xe-1 33 Ci N/A N/A N/A -

Total Activity Ci N/A N/A N/A -

B. lodines 1-131 Ci N/A N/A N/A 2.75E-05 2.75E-05 1-132 Ci N/A N/A N/A 7.49E-06 7.49E-06 Total Activity Ci N/A N/A N/A 3.50E-05 3.50E-05 C. Particulates 1-131 Ci N/A N/A N/A Go-58 Ci N/A N/A N/A 1.86E-06 1.86E-06 Co-60 Ci N/A N/A N/A 2.12E-07 2.12E-07 Zr-95 Ci N/A N/A N/A 5.16E-07 5.16E-07 Nb-95 Ci N/A N/A N/A 6.51E-07 6.51E-07 Cs-137 Ci N/A N/A N/A 1.01 E-07 1.01E-07 Ru-105 Ci N/A N/A N/A 2.41E-07 2.41E-07 Total Activity Ci N/A N/A N/A 3.58E-06 3.58E-06

0. Gross Alpha

[Gross Alpha I C l N/A I N/A I N/A I I E. Tritium H-3 Ci N/A N/A N/A - I dash "-" denotes less than Minimum Detectable Activity (MDA) 23

Table 2.2-A7 Millstone Unit No. 2 Airborne Effluents - Ground Batch - RWST Vent Nuclides Released I Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total A. Fission & Activation Gases Kr-85 Ci - - - 1.38E-01 1.38E-01 Kr-85m Ci - - - 5.04E-06 5.04E-06 Xe-131m Ci - - - 1.42E-02 1.42E-02 Xe-1 33 Ci - - - 1.97E+00 1.97E+00 Xe-1 33m Ci - - - 2.88E-02 2.88E-02 Xe-1 35 Ci - 1.59E-02 1.59E-02 Total Activity Ci I 2.17E+00 2.17E+00 B. Iodines 1-131 Ci N/A N/A N/A 5.81E-06 5.81E-06 1-133 Ci N/A N/A N/A 4.OOE-07 4.OOE-07 Total Activity Ci N/A N/A N/A 6.21 E-06 6.21 E-06 C. Particulates 11-[1 iI N/Al N/Al N/Al Total Activity N/A N/A N/A -

D. Gross Alpha "Gross Alpha I ci N/A I N/A I N/A I - I E. Tritium H-3 Ci N/A N/A N/A I dash "-" denotes less than Minimum Detectable Activity (MDA) 24

Table 2.3-Al Millstone Unit No. 3 Airborne Effluents - Release Summary Units 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total D. Gross Alpha

1. Total Activity Ci R

Rlease dash "-" denotes less than Minimum Detectable Activity (MDA) 25

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

Spent Fuel Pool Evaporation Nuciides I I0 Released Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total A. Fission & Activation Gases IXe-133 CiI - I - I Total Activity I - - -

B. lodines 1-131 Ci-1-133 Ca Total Activity I Ci C. Particulates 1-131 Ci -

Be-7 Ci - - 1.27E-05 1.27E-05 Co-58 Ci - - -

Co-60 Ci - - -

Cr-51 Ci - -

Mn-54 Ci - - -

Nb-95 Ci -- -

Ba-140 Ci --

Ce-141 Ci -

Ce144 Ci -

Sr-89 Ci -

Sr-90 Ci -

Total Activity Ci - 1.27E-05 1.27E-05 D. Gross Alpha IGrossAlpha I Ci - I - - I E. Tritium

[H-3 I Ci 1.74E+01 1.03E+01 1.54E+01 7.76E+0015.09E+01 dash "-" denotes less than Minimum Detectable Activity (MDA) 26

Table 2.3-A3 Millstone Unit No. 3 Airborne Effluents - Ground Continuous - ESF Building Ventilation Nuclides ,,2 .

Released I Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total A. Fission & Activation Gases IXe-133 Ci I - - - - I -

Total Activity Ci - - - -

B. lodines 1-131 Ci--

1-133 Ci--

To t al Activity Ci - -

C. Particulates 1-131 Ci - -

Be-7 Ci 3.96E-07 3.15E-07 7.11E-07 Co-58 Ci -- -

Cr-51 Ci -- -

Sr-89 Ci -- -

Sr-90 Ci -- -

Total Activity Ci 3.96E-07 3.15E-07 7.11E-07 D. Gross Alpha IGross Alpha I Ci - I  ! I E. Tritium H-3 Ci - 2.32E-01

. 1.62E-01 3.94E-01 dash "-" denotes less than Minimum Detectable Activity (MDA) 27

Table 2.3-A4 Millstone Unit No. 3 Airborne Effluents - Mixed Batch - Containment Drawdowns

<< No Release >>

SNuclides I *Ill[

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

3Ci I N/A I N/A I N/A I N/A I N/A Total Activity Ci N/A N/A N/A N/A N/A B. lodines 1-131 Ci N/A N/A N/A N/A N/A

-133 Ci N/A N/A N/A N/A --N/A Total Activity Ci N/A N/A N/A N/A N/A C. Particulates 11111Ci N/A N/A N/A N/A N/A Total Activity N/A N/A I N/A I N/A I N/A D. Gross Alpha IGross Alpha I Ci I N/A I N/A I N/A I N/A I N/A E. Tritium H-3 Ci N/A N/A N/A N/A N/A dash "-" denotes less than Minimum Detectable Activity (MDA) 28

Table 2.3-A5 Millstone Unit No. 3 Airborne Effluents - Mixed Batch - Containment Purges

<< No Release >>

I~

q 2006s Released Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total A. Fission & Activation Gases Xe-1 33 -1 Ci N/A N/A N/A N/A N/A Xe-1 35 Ci N/A N/A N/A N/A N/A Total Activity Ci N/A N/A N/A N/A N/A B. lodines *

[1-131 Ci N/A N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A N/A ITotal Activity Ci N/A N/A N/A N/A N/A C. Particulates

• 1-131 Ci N/A N/A N/A N/A N/A Br-82 Ci N/A N/A N/A N/A N/A Total Activity Ci N/A N/A N/A N/A N/A D. Gross Alpha

• IGross Alpha 1 Ci N/A I N/A I N/A I N/A N/A E.Tritium 1--3 Ci N/A I N/A N/A N/A N/A

• lodines, Particulates and Gross at included in Table 2.3-A2 or 2.3-A6 dash "-" denotes less than Minimum Detectable Activity (MDA) 29

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

& Containment Vents Nuclides Released Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total A. Fission & Activation Gases Ar-41 Ci 7.45E-03 6.85E-03 7.59E-03 8.23E-03 3.01 E-02 Xe-1 33 Ci 1.22E-02 3.38E-03 3.22E-03 2.02E-03 2.08E-02 Xe-1 35 Ci 2.21E-04 6.51E-05 3.17E-04 2.87E-04 8.90E-04 Kr-85m Ci - -

Xe-1 35m Ci Total Activity Ci 1.99E-02 1.03E-02 1 1.11E-02 1.05E-02 5.18E-02 B. lodines L,-1 I - I Total Activity Ci - I C. Particulates 1-131 Ci -- -

Ce-141 Ci - 2.56E-08 - 2.56E-08 Ce-144 Ci - 1.28E-07 - 1.28E-07 Sn-117m Ci 1.50E-08 1.98E-08 3.48E-08 Br-82 Ci 4.41E-06 3.30E-06 3.93E-06 3.43E-06 1.51E-05 Co-60 Ci - 4.01 E-07 1.73E-07 5.24E-08 6.26E-07 Sr-89 Ci -

Sr-90 Ci - - -

Total Activity Ci 4.43E-06 3.70E-06 4.28E-06 3.48E-06 1.59E-05 D. Gross Alpha IGross Alpha I Ci I - - "

E. Tritium IH-3 Ci I 2.67E-01 3.57E-01 3.26E-01 5.91E-01 1.54E+00 dash "-" denotes less than Minimum Detectable Activity (MDA) 30

Table 2.3-A7 Millstone Unit No. 3 Airborne Effluents - Ground Batch - Containment Equipment Hatch

<< No Release >>

Nuclides 2 Released I Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total A. Fission & Activation Gases JXe-i 33 ICi I N/A I N/A I N/A I N/A I N/A ITotal Activity I Ci N/A N/A N/A N/A N/A B. lodines 1-131 Ci N/A N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A N/A Total Activity Ci N/A N/A N/A N/A N/A C. Particulates 1-131 Ci N/A N/A N/A N/A N/A Cr-51 Ci N/A N/A N/A N/A N/A Co-58 Ci N/A N/A N/A N/A N/A Co-60 Ci N/A N/A N/A N/A N/A Mn-54 Ci N/A N/A N/A N/A N/A Nb-95 Ci N/A N/A N/A N/A N/A Zr-95 Ci N/A N/A N/A N/A N/A Ru-1 05 Ci N/A N/A N/A N/A N/A Sn-117m Ci N/A N/A N/A N/A N/A Cs-137 Ci N/A N/A N/A N/A N/A Total Activity Ci N/A N/A N/A N/A N/A D. Gross Alpha IGrossAlpha I Ci I N/A I N/A I N/A I N/A I N/A E. Tritium IH-3 Ci N/A N/A N/A N/A N/A dash "-" denotes less than Minimum Detectable Activity (MDA) 31

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

<< No Release >>

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

3 1Ci I N/A I N/A N/A I N/A I N/A Total Activity Ci N/A N/A N/A N/A N/A B. lodines 1-131 Ci N/A N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A N/A Total Activity Ci N/A N/A N/A N/A N/A C. Particulates 11111Cii N/A I N/A I N/A I N/A I N/A Total Activity N/A N/A N/A N/A N/A D. Gross Alpha iGross Alpha I CiI N/A N/A I N/A I N/A I N/A E. Tritium H-3 I Ci N/A N/A N/A N/A N/A dash "-" denotes less than Minimum Detectable Activity (MDA) 32

2.2 Liquid Effluents 2.2.1 Measurement of Liquid Radioactivity 2.2.1.1 Continuous Liquid Releases Grab samples are taken for continuous liquid release pathways and analyzed on the HPGe gamma spectrometer and liquid scintillation detector (for tritium) if required by the conditional action requirements of the REMODCM. Total estimated volume is multiplied by the isotopic concentrations (if any) to determine the total activity released. A proportional aliquot of each discharge is retained for composite analysis for Sr-89, Sr-90, Fe-55 and gross alpha if required by the conditional action requirements of the REMODCM. Pathways for continuous liquid effluent releases include, Steam Generator Blowdown, Service Water Effluent, and Turbine Building Sump discharge from Units 2 & 3.

2.2.1.2 Liquid Tanks/Sumps There are numerous tanks & sumps that are used to discharge liquids containing radioactivity to the environs; they are:

Unit 1 Reactor Cavity Water Unit 2 Clean Waste Monitor Tanks (2)

Aerated Waste Monitor Tanks (2)

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

Low Level Waste Drain Tanks (2)

Boron Test Tanks CPF Waste Neutralization Sump &Turbine Building Sump Steam Generator Bulk Prior to release, a tank is re-circulated for two equivalent tank volumes, a sample is drawn and then analyzed on the HPGe gamma spectrometer and liquid scintillation detector (H-3) for individual radionuclide composition. Isotopic concentrations are multiplied by the volume released to obtain the total activity released. For bulk releases, several samples are taken during the discharge to verify the amount of radioactivity released. A proportional aliquot of each discharge is retained for composite analysis for Sr-89, Sr-90, Fe-55, Ni-63, and gross alpha.

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 33

2.2.3 Liquid Batch Release Statistics Unit I Unit 2 Unit 3 Number of Batches 0 55 297 Total Time (min) 0 6140 35,026 Maximum Time (min) 0 287 370 Average Time (min) 0 112 118 Minimum Time (min) 0 11 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 2006, the following abnormal liquid releases occurred:

2.2.4.1 Unit I - None 2.2.4.2 Unit 2 - None 2.2.4.3 Unit 3 - None 2.2.5 Liquid Release Tables The following tables provide the details of the liquid radioactivity released from each of the Millstone units. They are categorized by type of release, source(s), and by release point of discharge to the environment.

34

Table 2.1-L1 Millstone Unit No. 1 Liquid Effluents - Release Summary (Release Point - Quarry)

I 206.

1Units 11st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Toa D. Gross Alpha

1. Total Activity Ci N/A N/A N/A N/A ReleasedN/N/NANA E. Volume

1. Released Waste Liters O.OOE+00 8.32E+04 O.OOE+00 O.OOE+00 8.32E+04 Volume

2. Dilution Volume Liters N/A 9.09E+08 N/A N/A 9.09E+08 During Releases

3. Dilution Volume Liters N/A 3.70E+1 1 N/A N/A 3.70E+1 1 During Period)1) _ _ _ _ _

dash "-" denotes less than Minimum Detectable Activity (MDA) 35

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

Units 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total A. Fission and Activation Products D. Gross Alpha 1 . Total Activity Ci - - - -

Released E. Volume

1. Released Waste Liters 7.95E+06 4.08E+05 7.25E+05 4.58E+05 9.54E+06 Volume

2. Dilution Volume Liters 2.40E+09 1.82E+09 3.56E+09 1.56E+09 9.34E+09 During Releases

3. Dilution Volume Liters 2.69E+1 1 2.73E+1 1 2.87E+1 1 1.86E+1 1 1.02E+12 During Period I I I I II_ I dash "-" denotes less than Minimum Detectable Activity (MDA) 36

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

Nuclides so Released I Units ,1st Qtr I 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Products ITotal Activity I C! I -I B. Tritium IH-3 Ci I 1.13E-02 7.85E-05 - 5.80E-04 1.20E-02 C. Dissolved & Entrained Gases ITotal Activity I Ci I - - -

D. Gross Alpha lGross Alpha I Ci I N/A N/A N/A N/A N/A dash "-" denotes less than Minimum Detectable Activity (MDA),

or that an MDA is not specified.

37

Table 2.2-L3 Millstone Unit No. 2 Liquid Effluents - Batch - LWS Released Nuclides I 1nts" st Qt~r 2nd Qtr I 3rd Qtr I 4th Qtr I Total I A. Fission & Activation Products Ag-1 1Om Ci 4.85E-05 5.36E-05 1.29E-04 1.42E-04 3.73E-04 Ce-141 Ci - -

Ce-144 Ci - -

Co-57 Ci 3.57E-06 7.68E-07 2.91 E-06 3.76E-05 4.48E-05 Co-58 Ci 2.15E-04 1.65E-04 1.35E-04 1.85E-03 2.37E-03 Co-60 Ci 6.02E-04 1.14E-03 1.84E-03 1.90E-03 5.48E-03 Cr-51 Ci 1.05E-05 - 1.34E-03 1.35E-03 Ni-63 Ci 2.40E-03 3.51 E-04 7.63E-04 1.39E-03 4.90E-03 Cs-1 34 Ci 5.12E-04 1.89E-06 7.30E-06 2.05E-04 7.26E-04 Cs-1 37 Ci 9.25E-04 2.01 E-05 4.82E-05 3.02E-04 1.30E-03 Fe-55 Ci 9.33E-04 7.08E-04 7.93E-04 4.32E-03 6.76E-03 Fe-59 Ci - 2.46E-04 2.46E-04 La-1 40 Ci 4.70E-08 - - 4.70E-08 Mn-54 Ci 2.05E-05 6.69E-05 1.20E-04 1.95E-04 4.02E-04 MO-99 Ci - -

Nb-95 Ci 5.85E-06 2.48E-05 4.70E-04 5.01 E-04 Ru-1 03 Ci - 3.60E-05 3.60E-05 Sb-124 Ci - 4.35E-05 4.35E-05 Sb-1 25 Ci 1.02E-03 6.65E-04 1.24E-03 2.53E-03 5.46E-03 Sn-113 Ci 9.04E-06 1.95E-07 3.06E-04 3.15E-04 Sn-117m Ci - 3.79E-05 3.79E-05 Sr-89 Ci 1.05E-05 - 1.05E-05 Sr-90 Ci - 4.16E-06 4.16E-06 Zn-65 Ci - -

Zr-95 Ci 4.1OE-06 - 2.39E-04 2.43E-04 Zr-97 Ci - 6.05E-06 6.05E-06 Total Activity Ci 6.72E 3.19E-03 5.08E-03 1.56E-02 3.06E-02 B. Tritium H-3 Ci 1.79E+02 1.84E+02 1.97E+02 4.23E+01i 6.02E+O2 C. Dissolved & Entrained Gases Kr-85 Ci 2.83E-02 5.04E-02 1.88E-01 1.13E-01 3.80E-01 Xe-1 31m Ci - 2.29E-03 3.85E-04 2.67E-03 Xe-133 Ci 4.72E-03 4.54E-04 1.17E-01 1.94E-02 1.41E-01 Xe-i 33m Ci - 2.59E-04 2.59E-04 Xe-135 Ci 9.88E-05 1.35E-05 1.12E-04 Total Activity Ci 3.30E-02 5.08E-02 3.08E-01 1.33E-01 5.24E-01 D. Gross Alpha GrossAlpha I Ci I - - -

dash "-" denotes less than Minimum Detectable Activity (MDA),

or that an MDA is not specified. 38

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

Nuclides * ° Released Units In1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Products ITotal Activity I ci I B. Tritium H-3 Ci 1.75E-02 8.08E-03 2.23E-04 2.75E-02 5.33E-02 Average Period uCi/mi 6.91 E-07 2.31 E-07 4.66E-09 1.34E-06 4.14E-07 Diluted Activity C. Dissolved & Entrained Gases ITotal Activity I ci I I I - I D. Gross Alpha IGross Alpha I oi N/A I N/A I N/A I N/A I N/A dash "-" denotes less than Minimum Detectable Activity (MDA),

or that an MDA is not specified.

• Dilution Volume During Period is an approximation of actual dilution flow to DSNO06.

39

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

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

1. TotalaActivity Ci - - -

Released E. Volume

1. Released Waste Liters 4.66E+06 4.82E+06 7.91E+06 4.32E+06 2.17E+07 Volume

2. Dilution Volume Liters 5.23E+09 7.79E+09 8.68E+09 6.67E+09 2.84E+10 During Releases

3. Dilution Volume Liters 4.38E+11 4.66E+11 4.72E+11 4.69E+11 1.85E+12 During Period I I I I _II dash "-" denotes less than Minimum Detectable Activity (MDA),

or that an MDA is not specified.

40

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

Nuclides Released Units 11st Qtr I 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Products Activit I C -Total - -

B. Tritium H-3 1 Ci I 1.86E-02 6.87E-02 1.46E-01 4.95E-02 2.83E-01 C. Dissolved & Entrained Gases IXe-1 33 Cii Total Activity Ci I D. Gross Alpha IGross Alpha Ci N/A N/A N/A N/A N/A dash "-" denotes less than Minimum Detectable Activity (MDA),

or that an MDA is not specified.

41

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

Nuclides Released 1st Qtr 1Units 2nd Qtr I 3rd Qtr 4th Qtr Total A. Fission & Activation Products Ag-110m Ci - 1.19E-04 2.42E-05 1.43E-04 Ce-141 Ci - -

Ce-144 Ci - - -

Co-58 Ci 2.93E-04 3.68E-05 1.24E-05 3.42E-04 Co-60 Ci 6.56E-04 2.07E-03 2.19E-03 1.05E-03 5.97E-03 Cs-134 Ci - - -

Cs-137 Ci 4.61E-05 4.55E-05 8.50E-05 1.25E-04 3.02E-04 Fe-55 Ci 1.82E-03 5.40E-03 3.34E-03 1.1 5E-03 1.17E-02 Fe-59 Ci - - -

Mn-54 Ci 7.48E-05 2.63E-04 1.93E-04 1.94E-05 5.50E-04 Mo-99 Ci - - -

Nb-95 Ci 1.50E-05 1.09E-05 2.59E-05 Ni-63 Ci 6.26E-04 4.11E-03 3.73E-04 4.13E-04 5.52E-03 Sb-1 24 Ci - 3.95E-05 3.95E-05 Sb-125 Ci 6.92E-04 7.29E-03 8.25E-03 1.35E-03 1.76E-02 Sn-113 Ci 11.14E-05 1.14E-05 Sn-117m Ci - 4.15E-05 8.17E-06 4.97E-05 Te-132 Ci 5.92E-06 5.92E-06 Sr-89 Ci -

Sr-90 Ci -

Sr-92 Ci - 1.35E-05 Zn-65 Ci -

Total Activity Ci 4.23E-03 1.94E-02 1.45E-02 4.11E-03 4.22E-02 B. Tritium 1H-3 1 Ci I4.54E+01 I2.39E+01 I2.53E+01 2.32E+02 3.27E+02 C. Dissolved & Entrained Gases IKr-85 I ci I - I5.16E-03 - I 5.16E-03 D. Gross Alpha lGross Alpha I ci - - I --

dash "-" denotes less than Minimum Detectable Activity (MDA),

or that an MDA is not specified.

42

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

Nuclides Unt .

Released I Units 1st Qtr I 2nd Qtr I 3rd Qtr 4th Qtr ITotal A. Fission & Activation Products ITotal Activity Ci -- -

B. Tritium JH-3 Ci 1.74E-02 2.83E-02 3.42E-02 2.46E-02 1 .05E-01 C. Dissolved & Entrained Gases ITotal Activity I Ci I - - - -

D. Gross Alpha lGross Alpha I Ci I N/A N/A N/A N/A N/A dash "-" denotes less than Minimum Detectable Activity (MDA),

or that an MDA is not specified.

43

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

IUnits 1 1st Qtr I 2nd Qtr I3rd Qtr I 4th Qtr I Total D. Gross Alpha

1. Total Activity Ci N/A j N/A N/A N/A N/A I Released I E. Volume dash "-" denotes less than Minimum Detectable Activity (MDA),

or that an MDA is not specified.

44

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

Nuclides 1 Released IUnits 1st Qtr I 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Products Activity Ci- iTotal - i - -

B. Tritium IH-3 ICi 3.66E-02 1 8.51 E-02 4.61 E-03 4.95E-02 1.76E-01 C. Dissolved & Entrained Gases ITotal Activity I Ci- - L " -

D. Gross Alpha IGross Alpha I Ci I N/A I N/A I N/A I N/A I N/A dash "-" denotes less than Minimum Detectable Activity (MDA),

or that an MDA is not specified.

45

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

Nuclides I g Released I Units 1 1st Qtr I 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Products ITotal Activity Ci N/A N/A N/A B. Tritium H-3 Ci 2.OOE-04 N/A N/A N/A 2.OOE-04 C. Dissolved & Entrained Gases ITotal Activity I Ci I N/A I N/A I N/S I D. Gross Alpha IGross Alpha ! Ci I N/A I N/A I N/A I N/A I N/A I dash "-" denotes less than Minimum Detectable Activity (MDA),

or that an MDA is not specified.

46

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

Table 2.1-S Unit 1 Solid Waste and Irradiated Component Shipments Table 2.2-S Unit 2 Solid Waste and Irradiated Component Shipments Table 2.3-S Unit 3 Solid Waste and Irradiated Component Shipments The principal radionuclides in these tables were from shipping manifests.

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

55-gal Steel Drum DOT 17-H container 7.5 ft3 Steel Boxes 45 ft3 87 ft33 95 ft 122 ft 3 Steel Container 202.1 ft 3 Steel "Sea Van;' 1280 ft 3 Polyethylene High Integrity Containers 120.3 ft33 132.4 ft 173.4 ft3 202.1 ft3 47

Table 2.1-S Solid Waste and Irradiated Component Shipments Millstone Unit 1 January 1, 2006 through December 31, 2006 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of Waste

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

Disposition Units Annual Totals t Total

_ _ T E rro r I None b.

C.

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

d. Other - (Mixed Waste)

Disposition None I-Units I Annual I

Totals I Est.

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

d.

48

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..

Radionuclide  % of Total Curies H-3 0.74 2.7898E-05 C-1 4 Cr-51 0.03 1.3115E-06 Mn-54 Fe-55 54.13 2.0311E-03 Fe-59 Co-57 Co-58 1.19 4.4730E-05 Co-60 11.38 4.2705E-04 Ni-59 Ni-63 6.56 2.4612E-04 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 Nb-95 Tc-99 Ru-1 03 Ru-1 06 Ag-11 Oin Sn-113 Sn-117m Sb-1 24 Sb-125 1-129 1-131 Cs-134 2.08 7.8112E-05 Cs-136 Cs-1 37 23.82 8.9363E-04 Ba-140 La-140 Ce-141 Ce-1 44 Eu-154 Hf-1 81 Pu-238 0.01 4.3842E-07 Pu-239 <0.01 3.0189E-07 Pu-241 Am-241 0.03 1.0894E-06 Pu-242 Cm-242 Cm-243 Cm-244 0.01 4.6107E-07 CURIES (TOTAL) 3.7522E-03 49

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

d. Other - (Mixed Waste)

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

Radionuclide  % of Total Curies H-3 1.40 6.0896E-06 C-14 Cr-51 0.75 3.2793E-06 Mn-54 Fe-55 49.47 2.1503E-04 Fe-59 Co-57 Co-58 5.71 2.4835E-05 Co-60 10.40 4.5201E-05 Ni-59 Ni-63 9.55 4.1532E-05 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 Nb-95 Tc-99 Ru-1 03 Ru-106 A m-110m Sn-113 Sn-117m Sb-1 24 Sb-1 25 1-129 1-131 Cs-134 4.22 1.8353E-05 Cs-136 Cs-137 18.45 8.0188E-05 Ba-140 La-140 -_

Ce-1 41 Ce-144 Eu-154 Hf-1 81 Pu-238 0.01 4.9965E-08 Pu-239 <0.01 3.9932E-08 Pu-241 Am-241 0.02 8.7060E-08 Pu-242 Cm-242 Cm-243 _

Cm-244 <0.01 2.3622E-08 CURIES (TOTAL) 4.3471 E-04 50

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

d. Other - (Water)

From Millstone Nuclear Power Station to Duntek Inc_ Oak Ridne TN for Incineratinn Radionuclide  % of Total [ Curies H-3 95.56 1.1256E-03 C-14 <0.01 8.9895E-09 Cr-51 Mn-54 0.02 2.2579E-07 Fe-55 0.93 1.1 007E-05 Fe-59 Co-57 Co-58 0.17 1.9939E-06 Co-60 0.32 3.7564E-06 Ni-59 Ni-63 0.65 7.6305E-06 Zn-65 Sr-89 <0.01 7.7641 E-08 Sr-90 <0.01 1.0378E-07 Nb-94 <0.01 2.6436E-09 Zr-95 Nb-95 <0.01 8.2036E-08 Tc-99 <0.01 8.0282E-09 Ru-1 03 Ru-1 06 Ag-110m Sn-113 Sn-1 17m Sb-124 Sb-125 0.04 5.2261E-07 1-129 1-131 Cs-1 34 0.04 4.3330E-07 Cs-136 Cs-1 37 2.03 2.3963E-05 Ba- 140 La-140 Ce-141 Ce-1 44 <0.01 9.5663E-09 Eu-154 <0.01 1.8934E-09 Hf-1 81 Pu-238 <0.01 8.8690E-08 Pu-239 <0.01 3.7440E-08 Pu-241 0.18 2.1576E-06 Am-241 <0.01 1.0881 E-07 Pu-242 <0.01 6.7301E-10 Cm-242 <0.01 6.3870E-10 Cm-243 <0.01 2.0520E-08 Cm-244 CURIES (TOTAL) 1.1778E-03 51

3. Solid Waste Disposition (Shipments from Millstone)

INumber of Shipments* Mode of TransportationI Destination 3 Truck (Sole Use Vehicle) IDuratek, Inc., Oak Ridge, TN 2 Truck Sole Use Vehicle) jPerma-Fix of Florida, Inc., Gainesville, FL

• Indicates the num-ber-of ship*ments in th is category which contained any unit-i waste.

(Example: A shipment containing wastes from units 1, 2 and 3 will be counted once on each of the three unit-specific sectionsof this report.) 31 physical shipments were made from this station in 2006.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination No Shipments in 2006 N/A N/A 52

Table 2.2-S Solid Waste and Irradiated Component Shipments Millstone Unit 2 January 1, 2006 through December 31, 2006 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of Waste

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

Disposition Units I J Annual Totals Est.

Es Total ot Systems, LLC, Barnwell, m 3.406gE+00 From Millstone Nuclear Power Station to Chem-Nuclear m 34069+00 25%

SC fr Buial sc for Buria. Ci 2.0047E+02 From Millstone Nuclear Power StationIm= to Duratek, Inc., Kingston, TN for Super- 5.0976E+002 0 25%

Compaction, Incineration, etc.. j Ci 2.3207E-03 1 25%____

From Millstone Nuclear Power Station to Duratek, Inc., Oak Ridge, TN for Super- M 3(

l 9.7524E+00 25 Compaction, Incineration, etc.. " Ci 4.0877E-01 From Millstone Nuclear Power Station to Studsvik Processing Facility, Erwin, TNL m3 5.3569E+00 for Thermal Destruction, Incineration, etc.. Ci 1.0516E+02 25%

b. Dry compressible waste, Contaminated equipment, etc.

i I IEst. Total Error Disposition Units Annual Totals Error From Millstone Nuclear Power Station to Duratek, Inc., Kingston, TN for Super- m.3 1.3359E+02 Compaction, Incineration, etc.. Ci 4.4353E-02 25%

From Millstone Nuclear Power Station to Duratek, Inc., Oak Ridge, TN for Super- m3 2.8574E+02 Compaction, Incineration, etc.. 1 Ci 2.7485E-01 .

From Millstone Nuclear Power Station to Energy Solutions. LLC, Clive, UT for __m3__ 1.8428E+02 25%1 IBurial. I Ci I 1.9502E+01 1 C. Irradiated components, Control rods, etc.

r Disposition Units T

Annual Totals JEst.Error Total 1.008E+02 Error From Millstone Nuclear Power Station to Energy Solutions, LLC, Clive, UT for m 1.0082E+02 Burial. Ci 6.6065E+01 25%

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

Units Annual Totals EE oral Disposition Error From Millstone Nuclear Power Station to Duratek, Inc., Oak Ridge, TN for Super- m3 6.2446E-01 25 Compaction, Incineration, etc..

Ci 6.1083E-05

d. Other- (Mixed Waste)

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

d. Other - (Water) 53

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 Systems, LLC, Barnwell, SC for Burial.

Radionuclide  % of Total Curies H-3 C-1 4 Cr-51 Mn-54 0.30 5.9172E-01 Fe-55 5.03 1.0077E+01 Fe-59 Co-57 Co-58 <0.01 1.6420E-03 Co-60 1.63 3.2701 E+00 Ni-59 Ni-63 15.28 3.0635E+01 Zn-65 Sr-89 Sr-90 0.12 2.4595E-01 Nb-94 Zr-95 Nb-95 Tc-99 Ru-1 03 Ru-106 Ag-I 10Om Sn-113 Sn-117m Sb-124 Sb-125 1-129 1-131 Cs-134 27.53 5.5193E+01 Cs-136 Cs-1 37 50.10 1.0043E+02 Ba-140 La-140 Ce-141 Ce-144 Eu-154 Hf-181 Pu-238 <0.01 8.5083E-04 Pu-239 <0.01 2.1471 E-04 Pu-241 <0.01 1.5475E-02 Am-241 <0.01 7.7075E-05 Pu-242 Cm-242 <0.01 .1.2676E-04 Cm-243 Cm-244 <0.01 6.5148E-04 CURIES (TOTAL) 2.0047E+02 54

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

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

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

Radionuclide  % of Total Curies H-3 C-14 Cr-51 Mn-54 Fe-55 27.49 6.3799E-04 Fe-59 Co-57 Co-58 5.94 1.3788E-04 Co-60 7.90 1.8325E-04 Ni-59 Ni-63 12.84 2.9788E-04 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 Nb-95 Tc-99 Ru-1 03 Ru-1 06 Ag-I 10 m Sn-113 Sn-117m Sb-1 24 Sb-125 1-129 I-131 Cs-1 34 17.41 4.0403E-04 Cs-136 Cs-1 37 28.37 6.5838E-04 Ba-140 La-140 Ce-1 41 Ce-144 Eu-154 Hf-1 81 Pu-238 0.02 4.3699E-07 Pu-239 0.02 3.8887E-07 Pu-241_

Am-241 0.02 4.9796E-07 Pu-242 Cm-242 Cm-243 Cm-244 CURIES (TOTAL) 2.3207E-03 55

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..

Radionuclide  % of Total Curies H-3 1.27 5.1740E-03 C-14 0.07 2.9248E-04 Cr-51 1.07 4.3728E-03 Mn-54 0.65 2.6443E-03 Fe-55 43.62 1.7829E-01 Fe-59 0.04 1.5556E-04 Co-57 0.16 6.5833E-04 Co-58 12.51 5.1140E-02 Co-60 12.65 5.1708E-02 Ni-59 Ni-63 20.48 8.3708E-02 Zn-65 <0.01 9.9811 E-06 Sr-89 <0.01 1.0219E-05 Sr-90 0.02 7.5739E-05 Nb-94 <0.01 1.0800E-05 Zr-95 2.85 1.1644E-02 Nb-95 1.76 7.2080E-03 Tc-99 <0.01 2.4710E-07 Ru-103 <0.01 2.1727E-05 Ru-106 Ag-11Orn 0.08 3.3548E-04 Sn-113 0.17 6.8227E-04 Sn-1 17m Sb-124 0.02 1.0081 E-04 Sb-1 25 0.57 2.3266E-03 1-129 1-131 Cs-134 0.66 2.7113E-03 Cs-136 Cs-1 37 0.97 3.9583E-03 Ba-1 40 <0.01 3.2926E-06 La-140 Ce-141 <0.01 4.7541E-06 Ce-1 44 0.15 6.0688E-04 Eu-1 54 Hf-1 81 0.01 4.7923E-05 Pu-238 <0.01 2.1128E-05 Pu-239 <0.01 9.6661 E-06 Pu-241 0.19 7.8853E-04 Am-241 <0.01 1.1569E-05 Pu-242 Cm-242 <0.01 1.3274E-05 Cm-243 Cm-244 <0.01 2.5143E-05 CURIES (TOTAL) 4.0877E-01 56

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, Erwin, TN for Thermal Destruction, Incineration, etc..

Radionuclide  % of Total Curies H-3 0.56 5.8797E-01 C-14 0.02 2.1019E-02 Cr-51 0.03 3.4000E-02 Mn-54 1.06 1.1154E+00 Fe-55 23.18 2.4376E+01 Fe-59 <0.01 3.5607E-03 Co-57 0.05 4.8872E-02 Co-58 0.40 4.2454E-01 Co-60 4.69 4.9282E+00 Ni-59 Ni-63 28.29 2.9750E+01 Zn-65 <0.01 1.1300E-03 Sr-89 <0.01 3.2828E-03 Sr-90 0.18 1.8853E-01 Nb-94 Zr-95 0.05 5.5333E-02 Nb-95 0.04 4.5701 E-02 Tc-99 Ru-1 03 <0.01 8.7500E-04 Ru-1 06 <0.01 4.0900E-03 Ag-11Om <0.01 3.9850E-03 Sn-113 0.03 3.5579E-02 Sn-117m Sb-1 24 <0.01 4.4400E-04 Sb-125 0.23 2.3921E-01 1-129 1-131 Cs-134 16.06 1.6884E+01 Cs-136 Cs-1 37 24.98 2.6270E+01 Ba-140 <0.01 2.4339E-20 La-140 Ce-141 <0.01 1.3600E-04 Ce-1 44 0.06 6.5932E-02 Eu-154 Hf-1 81 <0.01 2.6493E-07 Pu-238 <0.01 1.5083E-03 Pu-239 <0.01 6.9768E-04 Pu-241 0.06 6.2845E-02 Am-241 <0.01 8.2932E-04 Pu-242 Cm-242 <0.01 3.6848E-04 Cm-243 Cm-244 <0.01 1.7305E-03 CURIES (TOTAL) 1.0516E+02 57

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

b. Dry compressible waste, Contaminated equipment, etc.

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

Radionuclide  % of Total Curies H-3 0.64 2.8456E-04 C-14 Cr-51 0.75 3.3326E-04 Mn-54 0.63 2.7863E-04 Fe-55 35.08 1.5557E-02 Fe-59 Co-57 Co-58 8.41 3.7302E-03 Co-60 8.55 3.7908E-03 Ni-59 Ni-63 12.13 5.3812E-03 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 Nb-95 Tc-99 Ru-103 Ru-1 06 Ag-1 1Om Sn-1 13 Sn-117m Sb-1 24 Sb-1 25 1-129 1-131 Cs-134 12.54 5.5632E-03 Cs-1 36 Cs-137 21.22 9.4134E-03 Ba-140 La-1 40 Ce-141 Ce-144 Eu-154 Hf-181 Pu-238 0.02 6.7487E-06 Pu-239 0.01 5.9860E-06 Pu-241 Am-241 0.02 7.8058E-06 Pu-242 Cm-242 Cm-243 Cm-244 <0.01 9.1732E-08 CURIES (TOTAL) 4.4353E-02 58

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..

Radionuclide  % of Total Curies H-3 0.04 9.7843E-05 C-14 Cr-51 0.02 4.1905E-05 Mn-54 0.02 4.4007E-05 Fe-55 28.25 7.7642E-02 Fe-59 Co-57 Co-58 5.71 1.5692E-02 Co-60 8.06 2.2151 E-02 Ni-59 Ni-63 12.93 3.5542E-02 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 Nb-95 Tc-99 Ru-1 03 Ru-1 06 Ag-110m Sn-113 Sn-117m Sb-1 24 Sb-1 25 1-129 1-131 Cs-134 17.05 4.6873E-02 Cs-136 Cs-1 37 27.87 7.6608E-02 Ba-140 La-140 Ce-141 Ce-144 Eu-154 Hf-1 81 Pu-238 0.02 5.1127E-05 Pu-239 0.02 4.5342E-05 Pu-241 <0.01 1.7385E-05 Am-241 0.02 4.6581 E-05 Pu-242 Cm-242 Cm-243 Cm-244 <0.01 2.1747E-07 CURIES (TOTAL) 2.7485E-01 59

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

b. Dry compressible waste, Contaminated equipment, etc.

From Millstone Nuclear Power Station to Energy Solutions, LLC, Clive, UT for Burial.

Radionuclide  % of Total Curies H-3 0.58 1.1400E-01 C-14 1.24 2.4200E-01 Cr-51 <0.01 3.41OOE-07 Mn-54 1.16 2.2700E-01 Fe-55 53.33 1.0400E+01 Fe-59 <0.01 2.3500E-07 Co-57 0.15 2.8800E-02 Co-58 1.05 2.0500E-01 Co-60 15.13 2.9500E+00 Ni-59 Ni-63 24.36 4.7500E+00 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 0.09 1.7800E-02 Nb-95 0.17 3.3700E-02 Tc-99 0.93 1.8100E-01 Ru-1 03 <0.01 6.3300E-09 Ru-106 0.78 1.5300E-01 Ag-11Om <0.01 2.7100E-08 Sn-113 0.09 1.7100E-02 Sn-i 17m <0.01 2.8800E-09 Sb-1 24 <0.01 5.0700E-09 Sb-125 0.67 1.3100E-01 1-129 0.03 5.7800E-03 1-131 <0.01 8.2200E-08 Cs-1 34 <0.01 2.3550E-05 Cs-136 <0.01 2.2400E-08 Cs-1 37 <0.01 2.8965E-05 Ba-140 <0.01 1.8800E-07 La-140 <0.01 1.8800E-07 Ce-141 <0.01 2.5500E-09 Ce-144 0.13 2.4600E-02 Eu-1 54 Hf-181 <0.01 5.7800E-09 Pu-238 0.04 6.9800E-03 Pu-239 0.03 6.2000E-03 Pu-241 Am-241 0.04 7.9500E-03 Pu-242 Cm-242 Cm-243 Cm-244 CURIES (TOTAL) 1.9502E+01 60

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

c. Irradiated components, Control rods, etc.

From Millst'one Nuclear Power Station to Energy Solutions, LLC, Clive, LJT for Burial.

Radionuclide %of Total Curies H-3 <0.01 2.6600E-04 C-14 0.11 7.3700E-02 Cr-51 <0.01 1.3500E-05 Mn-54 2.13 1.4100E+00 Fe-55 81.89 5.4100E+01 Fe-59 <0.01 4.6600E-04 Co-57 <0.01 3.9200E-03 Co-58 0.03 2.2000E-02 Co-60 12.47 8.2400E+00 Ni-59 0.01 6.6900E-03 Ni-63 3.24 2.1400E+00 Zn-65 <0.01 2.2400E-03 Sr-89 Sr-90 Nb-94 <0.01 2.2900E-05 Zr-95 <0.01 4.2700E-03 Nb-95 <0.01 3.2200E-05 Tc-99 <0.01 6.0500E-06 Ru-1 03 <0.01 9.6500E-06 Ru-106 Ag-110m _ _

Sn-113 <0.01 2.3000E-03 Sn-1 17m Sb-1 24 Sb-125 0.07 4.7000E-02 1-129 1-131 Cs-1 34 Cs-1 36 Cs-137 <0.01 2.9100E-03 Ba-140 La-140 Ce-141 <0.01 4.0600E-07 Ce-144 Eu-154 Hf-1 81 <0.01 2.5300E-06 Pu-238 <0.01 2.0500E-03 Pu-239 <0.01 1.8400E-03 Pu-241 Am-241 <0.01 2.3639E-03 Pu-242 Cm-242 Cm-243 <0.01 3.2600E-03 Cm-244 CURIES (TOTAL) 6.6065E+01 61

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..

Radionuclide  % of Total Curies H-3 0.46 2.8391 E-07 C-14 Cr-51 Mn-54 4.23 2.5847E-06 Fe-55 52.77 3.2235E-05 Fe-59 Co-57 Co-58 11.77 7.1865E-06 Co-60 11.54 7.0518E-06 Ni-59 Ni-63 14.95 9.1301E-06 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 Nb-95 0.12 7.3124E-08 Tc-99 Ru-1 03 Ru-1 06 Ag-1 10 m Sn-113 Sn-117m Sb-1 24 Sb-125 1-129 1-131 Cs-1 34 Cs-1 36 Cs-137 4.11 2.5118E-06 Ba-140 La-140 Ce-1 41 Ce-1 44 Eu-154 Hf-1 81 Pu-238 0.01 8.6784E-09 Pu-239 0.01 7.7499E-09 Pu-241 Am-241 0.02 9.9450E-09 Pu-242 Cm-242 Cm-243 Cm-244 CURIES (TOTAL) 6.1083E-05 62

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

d. Other - (Mixed Waste)

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

Radionuclide  % of Total Curies H-3 1.40 6.0896E-06 C-14 Cr-51 0.75 3.2793E-06 Mn-54 Fe-55 49.47 2.1503E-04 Fe-59 Co-57 Co-58 5.71 2.4835E-05 Co-60 10.40 4.5201 E-05 Ni-59 Ni-63 9.55 4.1532E-05 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 Nb-95 Tc-99 Ru-1 03 Ru-1 06 Ag-I 10m Sn-113 Sn-117m Sb-1 24 Sb-125 1-129 1-131 Cs-1 34 4.22 1.8353E-05 Cs-1 36 Cs-137 18.45 8.0188E-05 Ba-140 La-140 Ce-141 Ce-144 Eu-1 54 Hf-181 Pu-238 0.01 4.9965E-08 Pu-239 <0.01 3.9932E-08 Pu-241 Am-241 0.02 8.7060E-08 Pu-242 Cm-242 Cm-243 Cm-244 <0.01 2.3622E-08 CURIES (TOTAL) 4.3471 E-04 63

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

d. Other- (Water)

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

Radionuclide  % of Total Curies H-3 91.34 2.5173E-02 C-14 <0.01 9.8165E-08 Cr-51 Mn-54 0.07 1.8396E-05 Fe-55 2.62 7.2190E-04 Fe-59 Co-57 <0.01 1.2696E-06 Co-58 0.57 1.5730E-04 Co-60 2.03 5.5979E-04 Ni-59 Ni-63 1.30 3.5798E-04 Zn-65 Sr-89 <0.01 8.4784E-07 Sr-90 <0.01 1.1 333E-06 Nb-94 <0.01 2.8868E-08 Zr-95 Nb-95 0.02 5.8562E-06 Tc-99 <0.01 8.7668E-08 Ru-1 03 Ru-106 Ag-I 10Om Sn-113 <0.01 2.3582E-06 Sn-117m Sb-i 24 Sb-1 25 0.07 2.0517E-05 1-129 1-131 Cs-134 0.11 3.1662E-05 Cs-136 Cs-1 37 1.74 4.7826E-04 Ba-140 La-140 Ce-1 41 Ce-144 <0.01 1.0446E-07 Eu-i 54 <0.01 2.0676E-08 Hf-181 Pu-238 <0.01 1.3708E-06 Pu-239 <0.01 7.6651 E-07 Pu-241 0.09 2.3561 E-05 Am-241 <0.01 1.6464E-06 Pu-242 <0.01 7.3492E-09 Cm-242 <0.01 6.9746E-09 Cm-243 <0.01 2.2407E-07 Cm-244 I CURIES (TOTAL) 2.7558E-02 64

3. Solid Waste Disposition (Shipments from Millstone)

Number of Shipments* Mode of Transportation Destination 1 *..Truck(Sole Use Vehicle) JChem-Nuclear Systems, LLC, Barnwell, SC 8 Truck (Sole Use Vehicle) IDuratek, Inc., Kingston, TN 13 7Truck (Sole Use Vehicle) TDuratek, Inc., Oak Ridge, TN 1 I Rail-Car (Sole Use Vehicle) IEnergy Solutions, LLC, Clive, UT 1"** ' Barge (Sole Use Vehicle) jEnergy Solutions, LLC, Clive, UT 2 Truck (Sole Use Vehicle) IPerma-Fix of Florida, Inc., Gainesville, FL 4 Truck (Sole Use Vehicle) JStudsvik Processing Facility, Erwin, TN

• Indicates the number of shipments in this category which contained any unit-2 waste.

(Example: A shipment containing wastes from units 1, 2 and 3 will be counted once on each of the three unit-specific sections of this report.) 31 physical shipments were made from this station in 2006.

• • One physical Barge shipment was made, holding three separately manifested components.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination No Shipments in 2006 N/A I N/A 65

Table 2.3-S Solid Waste and Irradiated Component Shipments Millstone Unit 3 January 1, 2006 through December 31, 2006 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of Waste

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

Disposition Units Annual Totals Est. Total Error From Millstone Nuclear Power Station to Duratek. Inc., Kingston, TN for Super- m3 1.2744E+01 Compaction, Incineration, etc.. Ci 1.1532E-02 25%

From Millstone Nuclear Power Station to Duratek, Inc., Oak Ridge, TN for Super-I m3 J 7.1887E+00 25%

Compaction, Incineration, etc.. Ci 2.0762E+00 From Millstone Nuclear Power Station to Studsvik Processing Facility, Erwin, TN m3 j 2.7557E+00 for Thermal Destruction, Incineration, etc.. 125%

Ci 7.3485E+01

b. Dry compressible waste, Contaminated equipment, etc.

Est. Total Disposition Units Annual Totals Error From Millstone Nuclear Power Station to Duratek, Inc., Kingston, TN for Super- m3 8.0429E+01 Compaction, Incineration, etc.. Ci 3.1317E-02 25%

From Millstone Nuclear Power Station to Duratek, Inc., Oak Ridge, TN for Super- m3 1.3590E+02 Compaction, Incineration, etc.. [25%

Ci 1.130 7E+00

c. Irradiated components, Control rods, etc.

Disposition Units Annual Totals Est. Total Error None d.

66

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

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

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

Radionuclide  % of Total Curies H-3 0.50 5.8103E-05 C-14 Cr-51 3.59 4.1438E-04 Mn-54 2.40 2.7715E-04 Fe-55 57.05 6.5793E-03 Fe-59 Co-57 Co-58 14.38 1.6580E-03 Co-60 9.57 1.1041 E-03 Ni-59 Ni-63 8.39 9.6742E-04 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 0.94 1.0783E-04 Nb-95 0.97 1.1161E-04 Tc-99 Ru-1 03 Ru-1 06 Ag-110m Sn-113 Sn-117m Sb-1 24 Sb-125 1-129 1-131 Cs-134 Cs-1 36 Cs-1 37 2.20 2.5423E-04 Ba-140 La-140 Ce-1 41 Ce-1 44 Eu-154 Hf-1 81 Pu-238 Pu-239 Pu-241 Am-241 Pu-242 Cm-242 Cm-243 Cm-244 CURIES (TOTAL) 1.1532E-02 67

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..

Radionuclide  % of Total Curies H-3 0.42 8.6712E-03 C-14 <0.01 1.5500E-05 Cr-51 <0.01 1.6334E-05 Mn-54 1.90 3.9471 E-02 Fe-55 65.66 1.3632E+00 Fe-59 Co-57 0.04 7.8103E-04 Co-58 0.17 3.5560E-03 Co-60 18.03 3.7438E-01 Ni-59 Ni-63 13.28 2.7573E-01 Zn-65 Sr-89 Sr-90 <0.01 4.0000E-06 Nb-94 Zr-95 <0.01 5.6231 E-05 Nb-95 0.01 2.7481 E-04 Tc-99 Ru-1 03 Ru-1 06 Ag-1 1Om <0.01 2.2500E-05 Sn-113 Sn-117m Sb-1 24 Sb-125 0.38 7.8546E-03 1-129 1-131 Cs-134 <0.01 1.1700E-04 Cs-1 36 Cs-137 0.07 1.5065E-03 Ba-1 40 La-140 Ce-141 Ce-144 <0.01 1.3609E-04 Eu-154 Hf-1 81 Pu-238 <0.01 9.7344E-06 Pu-239 <0.01 2.9559E-06 Pu-241 0.02 3.5250E-04 Am-241 <0.01 5.2061E-06 Pu-242 Cm-242 <0.01 3.1021 E-06 Cm-243 Cm-244 <0.01 1.9121 E-05 CURIES (TOTAL) 2.0762E+00 68

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, Erwin, TN for Thermal Destruction, Incineration, etc..

Radionuclide  % of Total Curies H-3 0.05 3.4297E-02 C-14 0.01 7.3570E-03 Cr-51 0.80 5.8600E-01 Mn-54 4.33 3.1806E+00 Fe-55 51.88 3.8125E+01 Fe-59 0.06 4.5300E-02 Co-57 0.12 8.9427E-02 Co-58 4.05 2.9732E+00 Co-60 13.95 1.0253E+01 Ni-59 Ni-63 22.92 1.6841E+01 Zn-65 0.03 2.0488E-02 Sr-89 <0.01 4.3715E-04 Sr-90 <0.01 1.9569E-03 Nb-94 Zr-95 0.44 3.2302E-01 Nb-95 0.59 4.3500E-01 Tc-99 Ru-103 <0.01 3.3400E-03 Ru-106 <0.01 3.1400E-03 Ag-11Orn 0.05 3.4810E-02 Sn-1 13 0.04 3.2687E-02 Sn-1 17m Sb-124 <0.01 3.1401 E-03 Sb-125 0.53 3.8689E-01 1-129 <0.01 1.6429E-05 1-131 Cs-1 34 <0.01 3.0500E-03 Cs-136 Cs-137 0.06 4.0443E-02 Ba-140 La-140 Ce-141 <0.01 1.0400E-04 Ce-144 0.05 3.6621E-02 Eu-154 Hf-1 81 Pu-238 <0.01 5.5000E-04 Pu-239 <0.01 2.0839E-04 Pu-241 0.03 2.2476E-02 Am-241 <0.01 3.5685E-04 Pu-242 Cm-242 <0.01 1.0622E-03 Cm-243 Cm-244 <0.01 9.1509E-04 CURIES (TOTAL) 7.3485E+01 69

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

b. Dry compressible waste, Contaminated equipment, etc.

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

Radionuclide  % of Total Curies H-3 1.10 3.4368E-04 C-14 Cr-51 2.16 6.7736E-04 Mn-54 1.77 5.5366E-04 Fe-55 49.56 1.5522E-02 Fe-59 Co-57 Co-58 11.37 3.56001E-03 Co-60 9.59 3.0038E-03 Ni-59 Ni-63 10.49 3.2863E-03 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 0.31 9.8223E-05 Nb-95 0.30 9.5400E-05 Tc-99 Ru-1 03 Ru-106 Ag-I 10Om Sn-113 Sn-117m Sb-124 Sb-125 1-129 1-131 Cs-134 4.19 1.3129E-03 Cs-136 Cs-137 9.12 2.8569E-03 Ba-1 40 La-140 Ce-141 Ce-144 Eu-154 Hf-181 Pu-238 <0.01 2.2285E-06 Pu-239 <0.01 1.9652E-06 Pu-241 Am-241 <0.01 2.6566E-06 Pu-242 Cm-242 Cm-243 Cm-244 <0.01 9.1732E-08 CURIES (TOTAL) 3.1317E-02 70

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..

Radionuclide  % of Total Curies H-3 0.62 6.9945E-03 C-1 4 Cr-51 0.60 6.7636E-03 Mn-54 2.28 2.5808E-02 Fe-55 64.81 7.3281 E-01 Fe-59 Co-57 Co-58 6.54 7.3912E-02 Co-60 11.34 1.2824E-01 Ni-59 Ni-63 10.38 1.1738E-01 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 0.38 4.3431 E-03 Nb-95 0.22 2.4610E-03 Tc-99 Ru-1 03 Ru-1 06 Ag-I 10m_ _

Sn-113 Sn-117m Sb-1 24 Sb-125 1-129 1-131 Cs-1 34 0.03 3.5466E-04 Cs-136 Cs-1 37 2.80 3.1607E-02 Ba-140 La-140 Ce-1 41 Ce-144 Eu-154 Hf-181 Pu-238 <0.01 7.9206E-07 Pu-239 <0.01 6.6357E-07 Pu-241 Am-241 <0.01 1.1836E-06 Pu-242 Cm-242 Cm-243 Cm-244 <0.01 2.1747E-07 CURIES (TOTAL) 1.1307E+00 71

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..

Radionuclide  % of Total Curies H-3 0.46 2.8391 E-07 C-1 4 Cr-51 Mn-54 4.23 2.5847E-06 Fe-55 52.77 3.2235E-05 Fe-59 Co-57 Co-58 11.77 7.1865E-06 Co-60 11.54 7.0518E-06 Ni-59 Ni-63 14.95 9.1301E-06 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 Nb-95 0.12 7.3124E-08 Tc-99 Ru-103 Ru-106 Ag-1i1m Sn-113 Sn-117m Sb-i24 Sb-125 1-129 1-131 Cs-1 34 Cs-136 Cs-137 4.11 2.5118E-06 Ba-140 La-1 40 Ce-141 Ce-144 Eu-154 Hf-181 Pu-238 0.01 8.6784E-09 Pu-239 0.01 7.7499E-09 Pu-241 Am-241 0.02 9.9450E-09 Pu-242 Cm-242 Cm-243 Cm-244 CURIES (TOTAL) 6.1083E-05 72

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..

Radionuclide O/%of Total Curies H-3 0.46 2.8391 E-07 C-14 Cr-51 Mn-54 4.23 2.5847E-06 Fe-55 52.77 3.2235E-05 Fe-59 Co-57 Co-58 11.77 7.1865E-06 Co-60 11.54 7.0518E-06 Ni-59 Ni-63 14.95 9.1301E-06 Zn-65 Sr-89 Sr-90 Nb-94 Zr-95 Nb-95 0.12 7.3124E-08 Tc-99 Ru-1 03 Ru-1 06 Ag-1 1Om Sn-113 Sn-117m Sb-1 24 Sb-125 1-129 1-131 Cs-134 Cs-1 36 Cs-137 4.11 2.5118E-06 Ba-140 La-1 40 Ce-1 41 Ce-144 Eu-154 Hf-1 81 Pu-238 0.01 8.6784E-09 Pu-239 0.01 7.7499E-09 Pu-241 Am-241 0.02 9.9450E-09 Pu-242 Cm-242 Cm-243 Cm-244 CURIES (TOTAL) 6.1083E-05 73

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

d. Other- (Water)

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

Radionuclide  % of Total Curies H-3 96.95 1.6451 E-02 C-14 <0.01 7.9827E-08 Cr-51 Mn-54 0.02 3.1079E-06 Fe-55 0.61 1.0286E-04 Fe-59 Co-57 Co-58 0.11 1.7979E-05 Co-60 0.21 3.5210E-05 Ni-59 Ni-63 0.41 6.9101E-05 Zn-65 Sr-89 <0.01 6.8945E-07 Sr-90 <0.01 9.2157E-07 Nb-94 <0.01 2.3475E-08 Zr-95 Nb-95 <0.01 7.2848E-07 Tc-99 <0.01 7.1290E-08 Ru-1 03 Ru-1 06 Ag-I 10Om Sn-113 Sn-1 17m Sb-1 24 Sb-1 25 0.03 4.6407E-06 1-129 1-131 Cs-134 0.07 1.1300E-05 Cs-1 36 Cs-137 1.47 2.4987E-04 Ba-140 La-1 40 Ce-141 Ce-144 <0.01 8.4949E-08 Eu-154 <0.01 1.6813E-08 Hf-1 81 Pu-238 <0.01 7.8884E-07 Pu-239 <0.01 3.3360E-07 Pu-241 0.11 1.9160E-05 Am-241 <0.01 9.6767E-07 Pu-242 <0.01 5.9763E-09 Cm-242 <0.01 5.6717E-09 Cm-243 <0.01 1.8221 E-07 Cm-244 CURIES (TOTAL) 1.6969E-02 74

3. Solid Waste Disposition (Shipments from Millstone)

Number of Shipments* Mode of Transportation Destination 5 Truck (Sole Use Vehicle) IDuratek, Inc., Kingston, TN 9 Truck (Sole Use Vehicle) IDuratek, Inc., Oak Ridge, TN 2 Truck (Sole Use Vehicle Perma-Fix of Florida, Inc., Gainesville, FL 3 Truck (Sole Use Vehicle) IStudsvik Processing Facility, Erwin, TN

• Indicates the number of shipments in this category which contained any unit-3 waste.

(Example: A shipment containing wastes from units 1, 2 and 3 will be counted once on each of the three unit-specific sections of this report.) 31 physical shipments were made from this station in 2006.

B. IRRADIATED FUEL SHIPMENTS (Disposition) 11Number of Shipments Mode of Transportation Destination No Shipments in 2006 N/A N/A 75

2.4 Groundwater Monitoring Per the voluntary requirements of the NEI Groundwater Monitoring Initiative:

Table 2.4-GW Groundwater Monitoring Results Well I Unit 1 Tank Farm MW-9A Semiannuallv Gamma and H-3 < LLD Unit 1 Tank Farm MW-9,B Semiannually Gamma and H-3 < LLD Unit 1 Tank Farm MW-9D Semiannually Gamma and H-3 < LLD Unit 1 Tank Farm Ti-MW-i Semiannually Gamma and H-3 < LLD Former Waste Oil UST T3-MW-1 Quarterly Gamma and H-3 < LLD Former ROB UST ME-5 Quarterly Gamma and H-3 < LLD Former S&W USTs T7MW-5 Semiannually Gamma and H-3 < LLD Former S&W USTs T7-MW-2 Semiannually Gamma and H-3 < LLD Former S&W USTs T7-MW-3 Semiannually Gamma and H-3 < LLD Fab Shop Area Ti 0-MW-i Semiannually Gamma and H-3 < LLD

-Fab Shop Area T1 0-MW-2 Semiannually Gamma and H-3 < LLD Fab Shop Area T1 0-MW-3 Semiannually Gamma and H-3 < LLD Fab Shop Area MW-4A Semiannually Gamma and H-3 < LLD Fab Shop Area MW-4B Semiannually Gamma and H-3 < LLD

-Fab Shop Area MW-4D Semiannually Gamma and H-3 < LLD Fab Shop Area T1O-MW-5A Semiannually Gamma and H-3 < LLD Fab Shop Area T10-MW-5C Semiannually Gamma and H-3 < LLD Fab Shop Area T10-MW-5D Semiannually Gamma and H-3 < LLD Transformer Switchyard bUnit 1MW-XMFR-03 Semiannually Gamma and H-3 < LLD Unit 1 Transformer Switchyard S1-MW-2 Semiannually Gamma and H-3 < LLD Unit 2 Transformer Switchyard MW-7B Semiannually Gamma and H-3 < LLD Unit 2 Transformer Switchyard MW-7C Semiannually Gamma and H-3 < LLD

-Unit 2 Transformer Switchyard MW-7D Semiannually Gamma and H-3 < LLD Unit 2 Transformer Switchyard S2-MW-7 Semiannually Gamma and H-3 < LLD Unit 3 Service Trans. Switchyard S3-MW-2 Quarterly Gamma and H-3 < LLD Fueling Station S11-MW-1 Semiannually Gamma and H-3 < LLD

-Fueling Station S11-MW-2 Semiannually Gamma and H-3 < LLD

-Unit 2 Fuel Oil AST S12-MW-1 Semiannually Gamma and H-3 < LLD Unit 2 Fuel Oil AST S12-MW-3 Semiannually Gamma and H-3 < LLD

-Recycling Area Waste Oil AST S13-MW-1 Semiannually Gamma and H-3 < LLD Recycling Area Waste Oil AST S13-MW-2 Semiannually Gamma and H-3 < LLD

-Recycling Area Waste Oil AST MW-6A Annual Gamma and H-3 < LLD Recycling Area Waste Oil AST MW-6B Annual Gamma and H-3 < LLD Yard Drains Catch Basin 1-3 CB 1-3 Monthly Gamma and H-3 < LLD Catch Basin 1-5 CB 1-5 Monthly Gamma and H-3 < LLD Catch Basin 1-7 CB 1-7 Monthly Gamma and H-3 < LLD Catch Basin 1-13 CB 1-13 Monthly Gamma and H-3 < LLD Catch Basin 1-14 CB 1-14 Monthly Gamma and H-3 < LLD Catch Basin 1-22 CB 1-22 Monthly Gamma and H-3 < LLD Catch Basin 2-9 CB 2-9 Monthly Gamma and H-3 < LLD NPDES Discharge DSN 006 Monthly Gamma < LLD and, occasionally*,

I H-3 at -2000 pCi/liter ROB Yard Drain Monthly Gamma and H-3 < LLD ISFSI Yard Drain DMH#1 1 Monthly Gamma and H-3 < LLD Sump Unit 3 Containment Underdrains Weekly Gamma and H-3 < LLD

• Note: Turbine building sumps normally have detectable H-3, which is monitored and reported in the effluent section of this report 76

3.0 Inoperable Effluent Monitors During the period January 1 through December 31, 2006, the following effluent monitors were inoperable for more than 30 consecutive days:

3.1 Unit I - None 3.2 Unit 2 - None 3.3 Unit 3 - None 77

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

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

Unit 2 operated with a DER capacity factor of 84.0% and the power history for 2006 is shown below.

MP2 - CYCLE 17 & 18 POWER HISTORY YEAR 2006 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 110 100 90 80 70 60, 0

• "50-40-30-

1. DOWN POWER TO REPLACE FAILED 1Y CW PP 20 2. MANUAL RX TRIP (2f23) DUE TO LOSS OF SG FEED PUMP AS A RESULT OF A BROKEN INSTRUMENT AIR LINE

3. DOWN POWER TO INSTALL EHC BACKUP TEMPORARY POWER 10 STWN (4/06) DUE TO TURBINE DRIVEN AUX FEED PUMP FAILURE 10- 5,((EOCCOA0TDOWN( 1017(......

0 0 0 0 0 0 0 0 0 0 0 0 0

0) Q 0;0 C)4 ( 40 SR 0

0 0

' 0 ' ' ~- (4 . '0 . ( O - (N ( O - ( ' ( .

78

Unit 3 operated with a DER capacity factor of 99.6% and the power history for 2006 is shown below.

MP3 - CYCLE 11 POWER HISTORY YEAR 2006 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 110 100 90 80 70 W 60 0

a- 50 40 30-20O 10 1. DOWN POWER DUE TO DEGRADED INTAKE CONDITIONS DURING STORM 0o-CD 0 0> 0n 0 0 0 0 0 0 0 0 02 0R 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0- 0 0 Q 0~ ~~~~

N 0. -( N 0 0 NC N 0 C) ( 0 - (NC 0 - (N (N - - (N 0 - (N0-(

79

5.0 Errata 5.1 The 2005 Radioactive Effluent Release Report had incorrect information for Reference 9. The corrected Reference 9:

Memo No. MP-HPO-06023, 2005 Report on Solid Waste and Irradiated Component Shipments, April 11, 2006.

80

6.0 REMODCM Changes In 2006, the following changes were made to the Millstone REMODCM:

Rev Effective Date 25 - 02 December 4, 2006 The description and the bases of the change(s) for each REMODCM revision are included here in Volume 1 of the Radioactive Effluent Release Report. In addition, a complete copy of the REMODCM revision(s) for the calendar year 2006 is provided to the Nuclear Regulatory Commission as Volume 2 of the Radioactive Effluent Release Report.

81

6.1 REMODCM Rev 25 Description of Changes 82

Approval 02/21/06 Effective 02/28/06 REMODCM Change Request - Routing and Cover Sheet Change Request #: 06-02 Page 1 of 2 I. Description of changes (include markup pages) and affected documents Originator name (Print): Claude Flory Section/Page Section Title and Description of Change with Basis Table I.D-3 Millstone Unit 2 Radioactive Gaseous Waste Sampling and Analysis Program Page 28 Correct title of table by changing "Unit 2" to "Unit 3."

Table I.E-1 1) Change sample type for #6 from "Well Water" to "Sea Water." This will correct Page 39 an error made during processing of a previous REMODCM change.

2) Change sample type for #6a from "Water" to "Well Water." This will correct an error made during processing of a previous REMODCM change.

3) Change numbering of samples #6a to #7, #7 to #8, #7a to #9, and #8-#12 to #10-

1. 14. This is an administrative change.

V.B.1/P. 140 REMODCM Unit Three Controls - Definitions The definition for DOSE EQUIVALENT 1-131 is changed for Unit 3.

This change supports the licensing change associated with the Alternate Source Term (AST). (See attached markup page for change.)

If more space is needed, Go To page 3 Yes D No 0 Originator signature: 1 2 'ZL Date: 19ý/:Lo/*

61 MP-22-REC-FAPO 1.1-001 Rev. 001 1 of 2

Millstone Unit 23 Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Release Sample Type and Minimum Analysis Type of Activity Analysis Lower Limit Source or Point Frequency Frequency of Detection (LLD)A (pCi/cc)

A. Containment and Fuel Building Release

1. Containment Gaseous, Particulate and Prior to Each Purge or Principal Gamma EmittersB Hogger Drawdown Charcoal Grab Prior to Drawdown; Weekly for Each Drawdown venting and prior to I x 10-1

2. Containment Purge venting for Footnote I Gaseous Grab prior to sample

3. Containment Vent each purgeH 1-131 1 x 10"12

4. Open Equipment Gaseous Grab every two 1-133 1 x 1040 Hatch during Outages weeks for venting' Prior to Each Drawdown Principal Particulate Gamma I x 10"11

5. Fuel Building Emitters 0 - (1-131, others with half lives greater than 8 days)

Monthly for all release H-3 Ix 10.6 sources except Equipment Hatch Continuous Particulate at Weekly Particulate Gamma emitters for NA Open Equipment Hatch Y/2hour count (]- 13 1, others with half-life greater than 8 days)

Continuous Charcoal at Weekly [-131 and 1-133 for one hour NA Equipment Hatch and Fuel count Building Rollup DoorsK Gaseous Grab at Daily Noble Gases-Gross Activity I x 104 Equipment Hatch and Fuel Building Rollup DoorsK B. Continuous Release I. Unit 3 Ventilation Monthly- Gaseous Grabcj Monthlyc.J Principal Gamma EmittersBB x 10-4 Vent (HVR-REIOB) H-3G I x 10.6

2. Engineered Continuous Charcoal Weekly 1-131 1 x 10.12 Safeguards SampleD'F 1-133 1 x 10"10 Building (HVQ-RE49)

3. Millstone Stack via Continuous Particulate Weekly Principal Particulate Gamma I x 10-11 SLCRS (HVR- Sampleo.F EmittersB - (1-13 1, others with RE19B) half lives greater than 8 days)

Continuous Particulate Quarterly Composite Sr-89, Sr-90 I x 10"11 SampleD Gross alpha I x 10"11 Continuous Noble GasD Continuous Monitor Noble Gases - Gross Activity I x 10.6 MP-22-REC-BAP01 Rev. 025-01 28 of 162

TABLB, a2LE-Millstone Rd i logical Environmental M* nitoring Program Exposure Pathway and/or No. of Sampling and Collection Type and Frequency of Sample Locations Frequency Analysis

1. Gamma Dose - 40(a) Quarterly Gamma Dose - Quarterly Environmental TLD

2. Airborne Particulate 8 Continuous sampler - weekly Gross Beta - 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 - weekly 1-131 - Weekly canister change

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

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

6. Wl-tSea Water 2 Continuous sampler with a Gamma Isotopic and Tritium on monthly collection at indicator each sample.

location. Quarterly at control location - Composite of 6 weekly grab samples 6a7. Well Water -2 Semiannually Gamma Isotopic and Tritium on each sample.

-78. Bottom Sediment 5 Semiannual Gamma Isotopic on each sample

'a9. Soil 3 Annually Gamma Isotopic on each sample 910. Fin Fish-Flounder and 2 Quarterly Gamma Isotopic on each sample one other type of edible fin fish (edible portion) 911. Mussels (edible portion) 2 Quarterly Gamma Isotopic on each sample 4G12.Oysters (edible portion) 4 Quarterly Gamma Isotopic on each sample 4413.Clams (edible portion) 2 Quarterly Gamma Isotopic on each sample 4a14.Lobsters (edible portion) 2 Quarterly Gamma Isotopic on each sample (a) Two or more TLDs or TLD with two or more elements per location.

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3. CHANNEL CALIBRATION - A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

4. CHANNEL CHECK - A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

5 DOSE EQUIVALENT 1-131 - DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microCurie/gram) which alone would produce the same CDE-thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Regulatey-Guide 14109 Rev'. 1, "Cclclation ef Annual Poses to Man frmRuioRl A~e f-Reactcr- Effluent for-the Por-pcse of Evaluating Complianee with 10 CFR Part 50 Appendix I under Inhalation in Federal Guidance Report No. 1 (FGR 11), "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion and Ingestion.

6. MEMBER(S) OF THE PUBLIC - MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors or its vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

The term "REAL MEMBER OF THE PUBLIC" means an individual who is exposed to existing dose pathways at one particular location.

7. MODE - Refers to Mode of Operation as defined in Safety Technical Specifications.

8. OPERABLE - OPERABILITY - An instrument shall be OPERABLE or have OPERABILITY when it is capable of performing its specified functions(s) and when all necessary attendant instrumentation, controls, electrical power, or other auxiliary equipment that are required for the instrument to perform its functions(s) are also capable of performing their related support function(s).

9. SITE BOUNDARY - The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee.

MP-22-REC-BAPO1 Rev 025-01 140 of 162

REMODCM Change Request - Routing and Cover Sheet Change Request Number #: 06-02 Page 2 of 2 II. Technical Reviews:

Approve [ 6 isapprove 0 Manager, - dii ' ,carotection and Chemistry Date Approve lYDisapprove E Supervisor - Rfdiol gical Engineering Date I1. SORC Revie' Meeting No.

Unreviewed Radiological Environmental Impact (Bases Attached) Yes [] No Approve 0 Disapprove F]

soRC Chailrma/ Date ))3*0 *[.t -. )*;

IV. Management Approval:

4 t. t 1e Vi-0 0 Approve Disapprove El S te ce President Date V. Implementation: Verify that the affected document changes have been Effective tate E ,DCM revision: q / &

Supervisor - ad logical Engineering Section (NFE) Date VI. Distribution:"-dhange sent to DocumentAntrol for distribution Supervisor - Radiol giga1 Engineering Section (NFE) Date VII. Documentation: In Annual ffluent epot(or separate submittal to NRC)

Supervisor - Radiolc Engineering Section (NFE) Date L/

MP-22-REC-FAPO 1.1-001 Rev. 001 2 of 2