ML031260677

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2002 Annual Radioactive Effluent Release Report
ML031260677
Person / Time
Site: Yankee Rowe
Issue date: 04/28/2003
From: Kay J
Yankee Atomic Electric Co
To:
Document Control Desk, NRC/FSME
References
-RFPFR, BYR 2003-035
Download: ML031260677 (49)
v • d • e


Text

Telephone (508) 721-7736 YANKEE A TOMIC ELECTRIC COMPANY Facsimile (508) 721 773 Suite 200, 19 Midstate Drive, Auburn, Massachusetts 01501 April 28, 2003 BYR 2003-035 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

References:

(a) License No. DPR-3 (Docket No. 50-29)

Subject:

2002 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the 2002 Annual Radioactive Effluent Release Report. This report summarizes the quantities of radioactive liquid and gaseous effluent and solid waste released from the Yankee Nuclear Power Station (YNPS) in Rowe, Massachusetts. This report also summarizes the estimated dose commitments from all radioactive liquids and gaseous effluents released during 2002. This information is submitted in accordance with YNPS Defueled Technical Specification 6.8.2.b and the YNPS Off-Site Dose Calculation Manual.

We trust this information is satisfactory; however, if you have any questions, please contact me at (978) 568-2302.

Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY James A. Kay Principal Licensing Engineer Enclosure c: J. Hickman, USNRC, Project Manager R. B. Bellamy, USNRC, Region I

L [.

L Li ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (ARERR)

YANKEE ROWE STATION JANUARY 1, 2002 - DECEMBER 31, 2002 DOCKET NO. 50-29 LICENSE NO. DPR-3 YANKEE ATOMIC ELECTRIC COMPANY Rowe, Massachusetts FRAMATOME ANP DOC I 47-5027090-00

NOTES:

1. Yankee Nuclear Power Station's last day at any power level was October 1, 1991.

The facility is permanently shut down and in the process of decommissioning. Due to ceased operations, short-lived nuclides have been deleted from the gaseous and liquid effluent tables. Their activity concentrations in the fuel inventory have decayed to zero values.

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TABLE OF CONTENTS

1.0 INTRODUCTION

..................................................................... 1 2.0 METEOROLOGICAL DATA .................................................................... 3 3.0 DOSE ASSESSMENT ..................................................................... 4 3.1 Doses From Liquid Effluents ..................................................................... 4 3.2 Doses From Noble Gases ..................................................................... 4 3.3 Doses From Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days ..................................................................... 5 3.4 Total Dose from Direct External Radiation, Plus Liquid and Gaseous Effluents .............. 6

4.0 REFERENCES

..................................................................... 7 Radioactive Liquid Effluent Monitoring Instrumentation ........................................................... A-1 Radioactive Gaseous Effluent Monitoring Instrumentation ...................................................... B-1 Liquid Holdup Tanks ......................................................................C-1 Radiological Environmental Monitoring Program .................................................................... D-1 Land Use Census .................................................................... E-1 Process Control Program (PCP) .................................................................... F-1 Off-Site Dose Calculation Manual (ODCM) .............................................................. ...... G-1 Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems ........................................ H-1 Supplemental Information .................................................................... 1-1 Sewage Sludge Disposal .................................................................... J-1

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LIST OF TABLES TABLE 1A: Gaseous Effluents - Summation of All Releases ................................................... 8 TABLE 1B: Gaseous Effluents - Elevated Releases ........................................................ 10 TABLE 1C: Gaseous Effluents - Ground Level Releases ....................................................... 12 TABLE 2A: Liquid Effluents - Summation of All Releases ...................................................... 14 TABLE 2B: Liquid Effluents - Routine Releases ......................................................... 16 TABLE 3: Solid Waste and Irradiated Fuel Shipments ........................................................ 18 TABLE 4: Maximum Off-Site Doses and Dose Commitments to Members of fhe Public....... 22 TABLE 5: Total Dose to Maximum Off-Site Individual (40CFR190) ...................................... 23 TABLE 6: 1992-1996 Meteorological Data Joint Frequency Distribution ............. ................. 24

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YANKEE ATOMIC ELECTRIC COMPANY, ROWE, MASSACHUSETTS 2002 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

1.0 INTRODUCTION

YNPS Technical Specification 6.8.2.b (a) requires that an Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted (to the NRC) before May 1 of each year. This report includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided is (1) consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP) for solid waste, and (2) is in conformance with 10CFR50.36a and Section IV.B.1 of Appendix I to 10CFR50. ODCM Control 7.2 details the specific information to be included in the annual report.

In June, 2002, the first dry spent fuel storage canister was placed on the Independent Spent Fuel Storage Installation (ISFSI) pad located within the plant's protected area. By design, there are no liquid or gaseous effluent release pathways from storage canisters once placed on the ISFSI pad.

Tables 1 through 3 lists the recorded radioactive gaseous and liquid effluents and solid waste, respectively, with data summarized on a quarterly basis for the year. Table 4 summarizes the estimated radiological dose commitments from all radioactive liquid and gaseous effluents released during the year 2002 along with the direct dose from station related activities. Table 5 summarizes the total dose to the maximum off-site individual from all station related sources for 2002.

As required by ODCM Control 7.2.b, dose commitments resulting from the release of radioactive materials in liquids and gases were estimated in accordance with the models and parameters identified in the ODCM (Reference 1). These dose estimates were made using a Method II analysis as described in the ODCM. A Method II analysis incorporates the methodology of Regulatory Guide 1.109 (Reference 2) using historic meteorological data. For gaseous releases, five years of historic (1992-1996) quarterly meteorological data were used for determining the gaseous pathway doses. As required by Control 7.2.b, this report also shall include an assessment of the radiation doses from radioactive effluents to member(s) of the public due to allowed recreational activities inside the site boundary during the year. However, for this reporting period, there were no recreational facilities open to the public inside the site boundary (on land), nor was permission granted for recreational use of plant property.

04125103

Shoreline activities associated with Sherman Pond and the Deerfield River were included in the dose assessments to the maximum individual. The dose impact for over-water activities, such as boating, are not significant due to the self shielding of water and the transient nature of the activity leading to low occupancy times. The limited use of the Information Center on-site is associated with educational activities as they pertain to the operation/decommissioning of the plant and as such, is not included under Control 7.2.b. Assessment of radiation doses (including direct radiation) to the most likely exposed real member(s) of the public for the calendar year for the purposes of demonstrating conformance with 40CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operations," also are included.

All calculated dose estimates for this reporting period are well below the regulatory dose criteria of 10CFR Part 50, Appendix I and 40CFR Part 190.

Appendices A through J indicate the status of reportable items per the requirements of the following documents:

Appendix Title Requirement Reference A Radioactive Liquid Effluent Monitoring Instrumentation ODCM Control 5.1 B Radioactive Gaseous Effluent Monitoring Instrumentation ODCM Control 5.2 C Liquid Holdup Tanks Technical Specification 3.40 0 Radiological Environmental Monitoring Program ODCM Control 4.1 E Land Use Census ODCM Control 4.2 F Process Control Program (PCP) PCP Control 2.0 G Offsite Dose Calculation Manual (ODCM) ODCM Control 7.2 H Radioactive Liquid, Gaseous, and Solid Waste Treatment ODCM Control 7.3, PCP System Control 3.0 I Supplemental Information Regulatory Guide 1.21 J Sewage Sludge Disposal ODCM Appendix A (a) With the incorporation of Amendment No. 157 the requirements of Technical Specifications 6 8.2.b and 3.4 will be relocated to the Yankee Decommissioning Quality Assurance Program.

-24ls3

2.0 METEOROLOGICAL DATA Five years of historic meteorological data (1992-1996) collected from the site's 200-foot meteorological tower, located approximately 180 meters north of the vapor container, were used to model the atmospheric dispersion of airborne effluents. The tower instrumentation was designed to meet the requirements of Regulatory Guide 1.23 (Reference 3) for meteorological monitoring. A summary of the 1992-1996 meteorological data is provided in Table 6 of this report.

The main release point for gases discharged from the plant is via the 150-foot primary vent stack, located between the vapor container and the primary auxiliary building. The primary vent stack is treated as a mixed mode elevated release point dependent upon wind speed, as described in Regulatory Guide 1.111 (Reference 4).

Atmospheric diffusion was calculated using quarterly historical data along with the recorded quarterly effluent information. CHI/Q and D/Q values were derived for all receptor points using a straight-line airflow model. All dispersion and deposition factors have been calculated employing appropriate source configuration considerations and removal mechanism (e.g., dry deposition) described in Regulatory Guide 1.111 (Reference 4). Terrain elevations, including downwind valley flow corrections for the surrounding area, were factored into the calculation of CHI/Q and D/Q values at each receptor location.

04125/03

3.0 DOSE ASSESSMENT 3.1 Doses From Liquid Effluents Control 3.1 limits total body (1.5 mrem per quarter and 3 mrem per year) and organ (5 mrem per quarter and 10 mrem per year) doses from liquid effluents to a member of the public to those specified in 10CFR Part 50, Appendix I. By implementing the requirements of 10CFR Part 50, Appendix I, Control 3.1 assures that the release of radioactive material in liquid effluents will be kept 'as low as is reasonably achievable.'

Exposure pathways that could exist as a result of liquid effluents are fish, direct exposure from river shoreline sedimentation, milk and meat via animal ingestion of the Deerfield River water, and meat, milk, and vegetable pathways via crop irrigation with water withdrawn from the Deerfield River. Drinking water and aquatic invertebrate pathways do not exist downriver of the Yankee plant at Rowe. The dose analysis for the liquid pathways assumes a dilution based on the monthly average flow at the Sherman Dam.

The whole body and organ doses due to liquid effluents were determined by summing the contributions from all pathways. The whole body and organ doses to a member of the public from liquid effluents are given in Table 4. The estimated quarterly and annual doses due to liquid effluents are well below the 10CFR Part 50, Appendix I dose criteria of Control 3.1.

3.2 Doses From Noble Gases Control 3.4 limits the gamma air (5 mrad per quarter and 10 mrad per year) and beta air (10 mrad per quarter and 20 mrad per year) doses from noble gases released in gaseous effluents from the site to areas at and beyond the site boundary to those specified in IOCFR Part 50, Appendix I. By implementing the requirements of 10CFR Part 50, Appendix I, Control 3.4 assures that the release of radioactive noble gases in gaseous effluents will be kept "as low as is reasonably achievable."

If noble gases are determined to be present in effluent discharge, the dose estimates are calculated at the site boundary, nearest resident, nearest vegetable garden, and nearest milk animal in each of the sixteen principle compass directions, as well as the point of highest off-site ground level air concentrations of radioactive materials. Gamma and beta air doses, as well as whole body and skin doses, are calculated at each of the above locations.

04J25/03

To determine the beta contribution to the skin dose, a semi-infinite cloud model is utilized. The whole body gamma dose is calculated using a finite cloud sector average model with a Gaussian distribution of activity in the vertical plane. The gamma radiation received from the cloud at a point of interest is determined by integrating the contribution from a differential volume over the entire cloud, taking into account the geometry of the cloud, variation in concentration, attenuation by the interaction of photons with matter in the path between the source and receptor point, and scattering of radiation from material outside the direct path to the point of interest. No additional credit is taken for decay of radionuclides in transit to the receptor point.

The estimated quarterly and annual gamma and beta air doses at the point of highest off-site exposure are listed in Table 4. The estimated gamma and beta air doses due to noble gases released in gaseous effluents are well below the 10CFR Part 50, Appendix I dose criteria of Control 3.4.

3.3 Doses From Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days Control 3.5 limits the organ doses to a member of the public from tritium and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the site to areas at and beyond the site boundary to those specified in 10CFR Part 50, Appendix I (7.5 mrem per quarter and 15 mrem per year). By implementing the requirements of 10CFR Part 50, Appendix I, Control 3.5 assures that the releases of tritium and particulates in gaseous effluents will be kept "as low as is reasonably achievable." It should be noted that due to the permanent shutdown of the plant (last power operation was in October 1991); the lodine-131 source term has decayed away and no longer has the potential to affect dose assessment.

Exposure pathways that could exist as a result of the release of particulates and tritium to the atmosphere include external irradiation from activity deposited onto the ground surface, inhalation, and ingestion of vegetables, meat, and milk. Dose estimates for 2002 were made at the site boundary, nearest resident, nearest vegetable garden, and nearest meat animal in each of the sixteen principle compass directions. The nearest resident, vegetable garden and milk animal in each sector were searched for by the most recent Land Use Census, as required by, Control 4.2. Doses were calculated for pathways that were determined by the field survey to actually exist. Conservatively, a vegetable garden is assumed to exist at each milk animal location when the milk pathway is included. Furthermore, the meat pathway is assumed to exist at locations where identified in the past (a meat animal inventory is not required by the annual Land Use Census) and at each milk animal location (when milk is identified). Meat and milk 0425

animals are assumed to receive their entire intake from pasture during the second and third quarters. This assumption is conservative since most dairy operations utilize supplemental feeding of animals when on pasture or actually restrict animals to full time silage feeding throughout the entire year.

The organ doses were determined after adding the contributions from all pathways at each location. Doses were calculated for the whole body, GI-tract, bones, liver, kidneys, thyroid, lungs, and skin for adults, teenagers, children, and infants. The maximum estimated quarterly and annual organ doses due to tritium and particulates at any of the off-site receptor locations are reported in Table 4. The doses to all other organs at all other locations for all other age groups are less than the doses reported in Table 4. The estimated organ doses from tritium and particulates in gaseous effluents are well below the 10CFR Part 50, Appendix I dose criteria of Control 3.5.

3.4 Total Dose from Direct External Radiation, Plus Liquid and Gaseous Effluents The annual total dose or dose commitment to any member of the public due to releases of radioactivity and direct radiation from fixed sources are limited to the EPA's radiation protection standards for the uranium fuel cycle (40CFR1 90). The dose limits are set to less than or equal to 25 mrem per year to the total body or any organ, except the thyroid, which is limited to less than or equal to 75 mrem per year.

Direct external dose from fixed sources of radioactive materials, such as spent fuel in the on-site ISFSI, and from within other plant structures was evaluated by comparing Yankee Rowe's 2002 TLD data for indicator stations versus the control locations. Since there was no distinguishable difference between the indicator measurements and the control measurements, it was concluded that there is no station-related direct radiation dose for 2002.

Table 5 shows that the total dose to the maximum off-site individual for 2002 is well below the EPA dose limit criteria.

04.25/03

4.0 REFERENCES

1. YNPS Offsite Dose Calculation Manual (ODCM), Revision No. 15.
2. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance With 10CFR Part 50, Appendix I,` U.S. Nuclear Regulatory Commission, Office of Standards Development, Revision 1, October 1977.
3. Regulatory Guide 1.23, 'On-Site Meteorological Programs (Safety Guide 23),"

U.S. Nuclear Regulatory Commission, Office of Standards Development, February 1972.

4. Regulatory Guide 1.1 11, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light - Water - Cooled Reactors," U.S. Nuclear Regulatory Commission, Office of Standards Development, Revision 1, October 1977.

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TABLE 1A

, (Sheet 1 of 2)

Yankee Atomic Electric Company, Rowe, Massachusetts 2002 Annual Radioactive Effluent Release Report Gaseous Effluents - Summation of All Releases

[ l l l lEst. Totall Unit U Quarter 1 I Quarter 2 l Error, %Tt A. Fission and Activation Gases

1. Total Release Ci ND 3.65E-02 +/-5.00E+01
2. Average Release Rate for Period ilCi/sec ND 4.64E-03
3. Percent of Control Limita)  % 0.OOE+00 5.36E_04 B. lodines 1' C.. Particulates 1.

2.

3.

Particulates with Half-lives > 8 days Average Release Rate for Period Percent of Control Limit(c) 1lCUsec Ci 8.07E-08 1.04E-08 2.84E-04 3.02E-08 3.84E-08 6.01 E-04

+/-3.OOE+01

4. Gross Alpha Radioactivity Ci ND ND D. Tritium
1. Total Release Ci 1.01 E-02 1.80E-02 +/-3.OOE+01 I
2. Average Release Rate for Period uxCi/sec 1.30E-03 _ 2.29E-03
3. Percent of Control Limit .

(d)

\-,

(d)

A_,

ND Not detected in gaseous effluents.

(a) ODCM Control 3.4.b for beta-air dose. Percent of limits are calculated using ODCM Method II dose equations.

(b) lodine-131 (and 1-133,1-135) data have been deleted. These nuclides have decayed below any practicable level for detection in effluents due to permanent plant shutdown.

(c) Per ODCM Control 3.5, the percentage of the limit Is based on the combined dose contribution from iodines, tntium, and particulates with half-lives greater than 8 days. Percent of limits are calculated using ODCM Method II dose equations.

(d) Per ODCM Control 3.5, percentage dose contnbution from tritium is included in Part C.3.

04f5iV3

TABLE 1A (Sheet 2 of 2)

Yankee Atomic Electric Company. Rowe, Massachusetts 2002 Annual Radioactive Effluent Release Report Gaseous Effluents - Summation of All Releases ll l l Est. Total l

[ I UnitQuarter 3 Quarter 4 Error, %

A. Fission and Activation Gases _ _ 1_______ __________

1. Total Release Ci 1.83E-02 7.44E-03 5.00E+01
2. Average Release Rate for Period iCi/sec 2.33E-03 9.36E-04
3. Percent of Control Limit(a) _ 2.87E-04 9.98E-05 B. lodines(b)

C. Particulates

1. Particulates with Half-lives > 8 days Ci 8.63E-08 8.32E-08 Zt3.OE+01
2. Average Release Rate for Period gCVsec 1.10E-08 1.05E-08
3. Percent of Control Limit(  % 6.07E-04 3.32E-04
4. Gross Alpha Radioactivity Ci ND 1.47E-09 D. Tritium
1. Total Release I Ci 1.72E-02 1.15E-02 I3.OOE+01 I
2. Average Release Rate for Period
3. Percent of Control Limit I pCi/sec I  %

__-*.4..

2.19E-03 (d) 1.45E-03 (d)

I ND Not detected in gaseous effluents.

(a) ODCM Control 3.4.b for beta-air dose. Percent of limits are calculated using ODCM Method II dose equations.

(b) lodine-1 31 (and 1-133.1-135) data have been deleted. These nuclides have decayed below any practicable level for detection in effluents due to permanent plant shutdown.

(c) Per ODCM Control 3.5, the percentage of the limit Is based on the combined dose contribution from iodines, tritum, and particulates with half lives greater than 8 days. Percent of limits are calculated using ODCM Method II dose equations.

(d) Per ODCM Control 3.5, percentage dose contribution from trittum is included in Part C.3.

_ 9 _ O43

TABLE 1B (Sheet 1 of 2)

Yankee Atomic Electric Company, Rowe, Massachusetts 2002 Annual Radioactive Effluent Release Report Gaseous Effluents - Elevated Releases Continuous Mode Batch Modema)

Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission Gases Krypton-85 l Ci l ND l 3.65E-02 l - l Total for Period Ci ND 3.65E-02 - l
2. lodines(b)
3. Particulates Strontium-89 Ci ND ND l l Strontium-90 Ci ND ND Cesium-134 Ci ND ND Cesium-137 Ci ND ND Zinc-65 Ci ND ND Cobalt-58 Ci ND ND Cobalt-60 Ci 8.07E-08 3.02E-08 Cerium-144 Ci ND ND Manganese-54 Ci ND ND Total for Period Ci 8.07E-08 3.02E-08 ND Not detected in gaseous effluents.

(a) There are no longer any batch mode gaseous releases.

(b) lodine-131,1-133 and 1-135 data have been deleted. These nuclides have decayed below any practicable level for detection in effluents due to permanent plant shutdown.

- Dash indicates no release of this type.

- 10 - 04/25W0

TABLE 1B (Sheet 2 of 2)

Yankee Atomic Electric Company. Rowe. Massachusetts 2002 Annual Radioactive Effluent Release Report Gaseous Effluents - Elevated Releases Continuous Mode Batch Mode(a)

Nuclides Released Unit Quarter 3 QuuarterS Quarter4l

1. Fission Gases Krvpton-85 Ci 1.83E-02 7.44E-03 Total for Period Ci 1.83E-02 7.44E-03
2. lodines(b)
3. Particulates Strontium-89 Ci ND ND Strontium-90 Ci ND ND Cesium-134 Ci ND ND Cesium-1 37 Ci ND ND Zinc-65 Ci ND ND Cobalt-58 Ci ND ND Cobalt-60 Ci 8.63E-08 8.32E-08 Cerium-144 Ci ND ND Manganese-54 Ci ND ND Total for Period Ci 8.63E-08 8.32E-08 ND Not detected in gaseous effluents.

(a) There are no longer any batch mode gaseous releases.

(b) Iodine-131,1-133 and 1-135 data have been deleted. These nuclides have decayed below any practicable level for detection in effluents due to permanent plant shutdown.

- Dash indicates no release of this type.

-11 - 042S/0

TABLE 1C (Sheet 1 of 2)

Yankee Atomic Electric Company, Rowe, Massachusetts 2002 Annual Radioactive Effluent Release Rerort Gaseous Effluents - Ground Level Releases Continuous Mode Batch Mode(a)

Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission Gases Krvpton-85&b) Ci l 7.30E-06 l -

Total for Period Ci - 7.30E-06 -

2. Iodines(C)
3. Particulates Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Zinc-65 Ci Cobalt-58 Ci Cobalt-60 Ci Cerium-144 Ci .

Manganese-54 Ci Total for Period Ci ND Not detected in gaseous effluents.

(a) There are no longer any batch mode gaseous releases.

(b) Krypton-85 laboratory QC gas source diffused over a 3-month period.

(c) lodine-131,1-133 and 1-135 data have been deleted. These nuclides have decayed below any practicable level for detection in effluents due to permanent plant shutdown.

- Dash indicates no release of this type.

04r25M03

TABLE 1C (Sheet 2 of 2)

Yankee Atomic Electric Company, Rowe, Massachusetts 2002 Annual Radioactive Effluent Release Report Gaseous Effluents - Ground Level Releases Continuous Mode Batch Mode(a)

Nuclides Released Unit Quarter 3 Quarter 4l Quarter 3 Q

1. Fission Gases l Krypton-85 l Ci l l l l l Total for Period Ci - - - -
2. lodinesb)
3. Particulates Strontium-89 Ci l l l l Strontium-90 Ci .
  • l
  • Cesium-1 34 Ci Cesium-1 37 Ci . . .

Zinc-65 Ci . .

Cobalt-58 Ci . .

Cobalt-60 Ci - -

Cerium-144 Ci Manganese-54 Ci .

Total for Period Ci . . -

ND Not detected in gaseous effluents.

(a) There are no longer any batch mode gaseous releases.

(b) lodine-131,1-133 and 1-135 data have been deleted. These nuclides have decayed below any practicable level for detection in effluents due to permanent plant shutdown.

- Dash indicates no release of this type.

- 13 -13 04125W

TABLE 2A (Sheet 1 of 2)

Yankee Atomic Electric Company, Rowe. Massachusetts 2002 Annual Radioactive Effluent Release Report Liquid Effluents - Summation of All Releases I l I TEst. Total I Unit Quarter 1 Quarter 2 l Error, %

A. Fission and Activation Products

1. Total Release (not including tritium, gases, alpha) Ci *2.E+01 l
2. Average Diluted Concentration During Period £ fCiml 3; Percent of Applicable UImitca)  %

B. Tritium

1. Total Release Ci  :-1.i0E+01
2. Average Diluted Concentration During Period giCiml
3. Percent of Applicable Limitca) _

C. Dissolved and Entrained Gases ,.

1. Total Release Ci ll2.E+01l
2. Average Diluted Concentration During Period iiCiml
3. Percent of Applicable Limite)  % J D. Gross Alpha Radioactivity
1. Total Release C, -3.50E+O1 E. Volume of Waste Release (prior to dilution) Liters 0.OOE+00 O.OOE+00 +/-1 .00E+01 F. Volume of Dilution Water Used Dunng Period Liters 5.05E+07 5.01 E+07 l1.50E+01 ND Not detected in liquid effluents.

(a) Concentration limits specified in Appendix B to 10CFR20.1-20.602, Table II, Column 2 (ODCM Control 2.1). The percent of applicable limit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentration limit.

(b) Concentration limits for dissolved and entrained noble gases is 2.OOE-04 [tCVml (ODCM Control 2.1).

The percent of applicable limit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentration limit.

- Dash indicates no release of this type.

04/25M0

TABLE 2A (Sheet 2 of 2)

Yankee Atomic Electric Company. Rowe, Massachusetts 2002 Annual Radioactive Effluent Release Report Liquid Effluents - Summation of All Releases Est. Total Unit Quarter 3 Quarter 4 Error, %

A. Fission and Activation Products

1. Total Release (not including tritium, gases, alpha) Ci ND jj2.OE+01jl
2. Average Diluted Concentration During Period ACVml . ND
3. Percent of Applicable Umit(a)  % - ND B. Tritium
1. Total Release Ci - 5.31E-04 1.00&E+01
2. Average Diluted Concentration During Period J4CVml - 1.13E-08
3. Percent of Applicable Limit(a)  % - 3.77E-04 C. Dissolved and Entrained Gases
1. Total Release Ci - ND jt2.OE+01
2. Average Diluted Concentration During Period 4CVml - ND
3. Percent of Applicable Limite' - ND D. Gross Alpha Radioactivity
1. Total Release Ci - ND l+/-3.50E+01 E. Volume of Waste Release (prior to dilution) Liters O.OOE+00 2.46E+04 +/- .OOOE+01 F. Volume of Dilution Water Used During Period Liters 4.77E+07 4.72E+07 l 1.50E+01 ND Not detected in liquid effluents.

(a) Concentration limits specified in Appendix B to 10CFR20.1-20.602, Table II, Column 2 (ODCM Control 2.1). The percent of applicable limit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentration limit.

(b) Concentration limits for dissolved and entrained noble gases is 2.OOE-04 pCVml (ODCM Control 2.1).

The percent of applicable limit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentration limit.

- Dash indicates no release of this type.

OUl25M0

TABLE 2B (Sheet 1 of 2)

Yankee Atomic Electric Company, Rowe, Massachusetts 2002 Annual Radioactive Effluent Release Report Liquid Effluents - Routine Releases Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Strontium-89 Ci l Strontium-90 Ci.

Cesium-1 34 Ci Cesium-137 Ci--

Cobalt-58 Ci Cobalt-60 Ci Zinc-65 Ci Manganese-54 Ci Cerium-144 Ci Carbon-14 Ci Iron-55 - Ci Unidentified Ci Total for Period (above) Ci - - - l Kwton-85 Ci - - - l ND Not detected in liquid effluents.

- Dash indicates no release of this type.

04-1 -25=

TABLE 2B (Sheet 2 of 2)

Yankee Atomic Electric Company. Rowe, Massachusetts 2002 Annual Radioactive Effluent Release Report Liquid Effluents - Routine Releases Continuous Mode Batch Mode Nuclides Released Unit Quarter 3 Quarter4 Quarter 3 Quarter4 Strontium-89 Ci - l ND Strontium-90 Ci l ND Cesium-134 Ci ND Cesium-137 Ci 1 ND Cobalt-58 Ci l - l ND Cobalt-60 Ci ND Zinc-65 Ci ND Manganese-54 Ci ND Cerium-144 l Ci _l -l l ND Carbon-14 _ Ci l ND Iron-55 Ci ND Unidentified Ci ND Total for Period (above) Ci - - l ND Krypton-85 Ci l l ND l ND Not detected in liquid effluents.

- Dash indicates no release of this type.

04/25/03

TABLE 3 (Sheet 1 of 4)

Yankee Atomic Electric Companv, Rowe, Massachusetts 2002 Annual Radioactive Effluent Release ReDort Solid Waste and Irradiated Fuel Shipments

1. First and Second Quarters A. SOLID WASTE SHIPPED FOR BURIAL OR DISPOSAL (not irradiated fuel) 6-month Est. Total
1. Type of Waste Unit Period Error, %
a. Bead Resin: Class B m3 3.4 30 Containers: (8-120 Poly HIC) Ci (est.) 1.9E1
b. Mechanical Filters: Class A m3 2.2 30 Containers: (medium overpack HIC) Ci (est.) 4.3E-2
c. Dry Active Waste: Class A m3 36.3 50 Containers: (a) Ci (est.) 3.8E-3
2. Estimate of Nuclide Composition > 1 % (by type of waste)
a. Iron-55 I_%_ _ 8.8 Cobalt-60  % 46.6 Nickel-63  % 26.6 Cesium-1 37  % 15.9
b. Iron-55 %__ 41.6 Cobalt-60  % 17.6 Nickel-63 _ 37.2 Plutonium-241  % 1.5
c. Iron-55 %__ 32.7 Cobalt-60 20.4 Nickel-63  % 41.6 Cesium-1 37  % 3.8
3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 1(b) Truck Oak Ridge, TN 2 Truck Barnwell, SC (a) Partial shipments by the processor to disposal.

(b) Waste shipments to processor.

m4nim

TABLE 3 (Sheet 2 of 4)

Yankee Atomic Electric Companv, Rowe. Massachusetts 2002 Annual Radioactive Effluent Release Report Solid Waste and Irradiated Fuel Shipments

1. First and Second Quarters (continued)

B. IRRADIATED FUEL SHIPMENTS (Disposition): None OV225103

TABLE 3 (Sheet 3 of 4)

Yankee Atomic Electric Company, Rowe, Massachusetts 2002 Annual Radioactive Effluent Release Report Solid Waste and Irradiated Fuel Shipments II. Third and Fourth Quarters A. SOLID WASTE SHIPPED FOR BURIAL OR DISPOSAL (not irradiated fuel) 6-month Est. Total

1. Type of Waste Unit Period Error, %

3

a. Dry Active Waste: Class A in 72.5 50 Containers: (a) Ci (est.) 5.2E-3 I
b. Radioactive/PCB Debris: Class A m38.2 30 Containers (steel box) Ci (est.) 2.9E-3. I
c. Dry Active Waste: Class A m3 72.5 50 Containers: (a) Ci (est.) 1.9E-1
2. Estimate of Nuclide Composition > 1% (by type of waste)
a. Iron-5S I % 1 34.8 Cobalt-60  % 20.5 Nickel-63  % 39.6 Cesium-1 37  % 3.6
b. Tritium (H-3) _ 3.2 Iron-55  % 31.9 Cobalt-60  % 18.8 Nickel-63  % 32.6 Cesium-137  % 13.0
c. Iron-55 I  % 1 82.6 I Cobalt-60 f  % 14.2 Nickel-63 I  % 1 2.0 1
3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 3 Truck Clive, UT 2(b) Truck Oak Ridge, TN (a) Partial shipments by the processor to disposal.

(b) Waste shipments to processor.

04/25/03

TABLE 3 (Sheet 4 of 4)

Yankee Atomic Electric Company, Rowe, Massachusetts 2002 Annual Radioactive Effluent Release Report Solid Waste and Irradiated Fuel Shipments II. Third and Fourth Quarters (continued)

B. IRRADIATED FUEL SHIPMENTS (Disposition): None 04125/3

TABLE 4 (Sheet 1 of 1)

Yankee Atomic Electric ComDanv, Rowe, Massachusetts 2002 Annual Radioactive Effluent Release Report Maximum(a) Off-Site Doses and Dose Commitments to Members of the Public(b)

Source Unit 1S'Quarter 2"dQuarter 3 rdQuarter 4' Quarter __Year(C)

E

1. Liquid Effluents Whole Body Critical Organ mreml O.OOE+00(') l O.OOE+O0(d) l O.OOE+00(d) l 3.32E-07(e) jmiremn O.OOE+00(ci) jO.O0E+00(d) O.OOE+00(ci) 3.32E-07()

I 3.32E-07 l 3.32E-07q

2. Airborne Effluents Tritium and Particulates mrem 2.13E-05(9 ) 4.51 E-05(h) 4.55E-051) 2.49E-05(9) 1.37E-04 Noble Gases (Beta Air) mrad O.OOE+00 0 5.36E-05() 2 . 8 7 E-0 5 (k) 9.98E-06(k) 9.23E-05 Noble Gases (Gamma Air) mrad O.OOE+00 0 1.42E-07(") 8.18E-08(_) 2.83E-08'(' 2.52E-07
3. Direct Dose Direct External Dose mrem I O.00E+00t1 O.OOE+00t ') I O.OOE+00 0) I O.OOE+00t 1' O.OOE+00 (a) 'Maximum' means the largest fraction of corresponding 10 CFR Part 50, Appendix I, dose design objective.

(b) The numbered footnotes Indicate the location of the dose receptor, age group, and organ, where appropriate.

(c) 'Maximum' dose for the year Is the sum of the maximum doses for each quarter. This results In a conservative yearly dose estimate, but still within the limits of 10 CFR Part 50.

(d) There were no liquid releases dunng the first and second and third quarters of 2002.

(e) Child.

(Of) Liver, kidney, lung, GI-LLI. and thyroid of child.

(g) SW and WSW, 1300 meters; lung and GI-LLI of child.

(h) SW and WSW, 1300 meters; lung, GI-LLI and whole body of child.

(i) SW and WSW, 1300 meters; lung of child

0) There were no noble gases released during the first quarter of 2002.

(k) SSE and S, 800 meters; site boundary.

(I) 2002 TLD data for Indicator and control stations were compared No statistical difference which could be attributed to station sources was identified

- 22 - 04125=0

TABLE 5 (Sheet 1 of 1)

Yankee Atomic Electric Company, Rowe. Massachusetts 2002 Annual Radioactive Effluent Release Report Total Dose to Maximum Off-Site Individual (40CFR1 90)

Pathway Total Body Maximum Organ(a)

(mrem) (mrem)

Direct External 0.0 0.0 Liquids 3.32E-07 3.32E-07 Gases 1.36E-04 1.37E-04 Annual Total 1.36E-04 1.37E-04 (a) Maximum organ includes consideration of the thyroid.

04/25M0

I I f r - -- I - f 1- I ' 1---'

TABLE 6 (Sheet 1 of 8)

Yankee Atomic Electric Company. Rowe, Massachusetts 2002 Annual Radioactive Effluent Release Report 1992-1996 Meteorological Data Joint Frequency Distribution

1. 199.0 FT WIND DATA STABILITY CLASS A CLASS FREQUENCY (PERCENT) = .09 WIND DIRECTION FROM SPEED(MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 0 0 1 2 0 0 0 0 0 0 0 0 0 0 0 1 0 4 (1) .00 .00 2.56 5.13 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 2.56 .00 10.26 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 4-7 0 0 0 0 0 0 0 1 0 2 0 0 0 0 0 0 0 3 (1) .00 .00 .00 .00 .00 .00 .00 2.56 .00 5.13 .00 .00 .00 .00 .00 .00 .00 7.69 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 8-12 0 1 0 0 0 0 0 0 2 3 13 6 1 0 0 0 0 26 (1) .00 2.56 .00 .00 .00 .00 .00 .00 5.13 7.69 33.33 15.38 2.56 .00 .00 .00 .00 66.67 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .03 .01 .00 .00 .00 .00 .00 .06 13-18 0 0 0 0 0 0 0 0 0 0 5 1 0 0 0 0 0 6 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 12.82 2.56 .00 .00 .00 .00 .00 15.38 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .01 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 0 1 1 2 0 0 0 1 2 5 18 7 1 0 0 1 0 39 (1) .00 2.56 2.56 5.13 .00 .00 .00 2.56 5.13 12.82 46.15 17.95 2.56 .00 .00 2.56 .00 100.00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .04 .02 .00 .00 .00 .00 .00 .09 (1)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C=CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)

- 24 04M5/03

F I- , - I- ( -- - 1- -- 1- - I II I , I- I TABLE 6 (Sheet 2 of 8)

Yankee Atomic Electric Company, Rowe, Massachusetts 2002 Annual Radioactive Effluent Release Report 1992-1996 Meteorological Data Joint Frequency Distribution

2. 199.0 FT WIND DATA STABILITY CLASS B CLASS FREQUENCY (PERCENT) = .36 WIND DIRECTION FROM SPEED(MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 5 (1) .68 .68 .68 .68 .68 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 3.42 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 4-7 1 0 0 0 0 0 0 2 11 5 6 3 1 0 0 0 0 29 (1) .68 .00 .00 .00 .00 .00 .00 1.37 7.53 3.42 4.11 2.05 .68 .00 .00 .00 .00 19.86 (2) .00 .00 .00 .00 .00 .00 .00 .00 .03 .01 .01 .01 .00 .00 .00 .00 .00 .07 8-12 0 1 0 0 0 0 0 3 6 14 49 20 0 0 0 0 0 93 (1) .00 .68 .00 .00 .00 .00 .00 2.05 4.11 9.59 33.56 13.70 .00 .00 .00 .00 .00 63.70 (2) .00 .00 .00 .00 .00 .00 .00 .01 .01 .03 .12 .05 .00 .00 .00 .00 .00 .23 13-18 0 1 0 0 0 0 0 0 0 0 12 6 0 0 0 0 0 19 (1) .00 .68 .00 .00 .00 .00 .00 .00 .00 .00 8.22 4.11 .00 .00 .00 .00 .00 13.01 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .03 .01 .00 .00 .00 .00 .00 .05 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .0p .00 .00 .00 .00 ALL SPEEDS 2 3 1 1 1 0 0 5 17 19 67 29 1 0 0 0 0 146 (1) 1.37 2.05 .68 .68 .68 .00 .00 3.42 11.64 13.01 45.89 19.86 .68 .00 .00 .00 .00 100.00 (2) .00 .01 .00 .00 .00 .00 .00 .01 .04 .05 .16 .07 .00 .00 .00 .00 .00 .36 (1)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C=CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 0425/03

I [ ( {

I~ I- I I 1 TABLE 6 (Sheet 3 of 8)

Yankee Atomic Electric Company. Rowe. Massachusetts 2002 Annual Radioactive Effluent Release Report 1992-1996 Meteorological Data Joint Frequency Distribution

3. 1990 FT WIND DATA STABILITY CLASS C CLASS FREQUENCY (PERCENT) = 1.24 WIND DIRECTION FROM SPEED(MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 1 1 5 3 0 0 0 1 1 0 0 0 0 0 1 0 0 13 (1) .20 .20 .98 .59 .00 .00 .00 .20 .20 .00 .00 .00 .00 .00 .20 .00 .00 2.55 (2) .00 .00 .01 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .03 4-7 0 3 2 0 1 3 2 17 24 21 22 16 6 3 1 0 0 121 (1) .00 .59 .39 .00 .20 .59 .39 3.33 4.71 4.12 4.31 3.14 1.18 .59 .20 .00 .00 23.73 (2) .00 .01 .00 .00 .00 .01 .00 .04 .06 .05 .05 .04 .01 .01 .00 .00 .00 .29 8-12 1 4 1 0 0 0 2 7 17 42 122 107 10 2 1 2 0 318 (1) .20 .78 .20 .00 .00 .00 .39 1.37 3.33 8.24 23.92 20.98 1.96 .39 .20 .39 .00 62.35 (2) .00 .01 .00 .00 .00 .00 .00 .02 .04 .10 .30 .26 .02 .00 .00 .00 .00 .77 13-18 2 2 0 0 0 0 0 0 1 4 20 27 2 0 0 0 0 58 (1) .39 .39 .00 .00 .00 .00 .00 .00 .20 .78 3.92 5.29 .39 .00 .00 .00 .00 11.37 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .05 .07 .00 .00 .00 .00 .00 .14 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 4 10 8 3 1 3 4 25 43 67 164 150 18 5 3 2 0 510 (1) .78 1.96 1.57 .59 .20 .59 .78 4.90 8.43 13.14 32.16 29.41 3.53 .98 .59 .39 .00 100.00 (2) .01 .02 .02 .01 .00 .01 .01 .06 .10 .16 .40 .36 .04 .01 .01 .00 .00 1.24 (1)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C=CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 04/25/03

r .- - I' ( I- I'-

T I 1F---- I 1' [ , I- 1 f I I ( I 1 TABLE 6 (Sheet 4 of 8)

Yankee Atomic Electric Company, Rowe, Massachusetts 2002 Annual Radioactive Effluent Release Report 1992-1996 Meteorological Data Joint Frequency Distribution

4. 199 0 FTWIND DATA STABILITY CLASS D CLASS FREQUENCY (PERCENT) = 46.68 WIND DIRECTION FROM SPEED(MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .01 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 299 588 303 121 89 87 85 80 81 132 224 161 97 79 99 124 0 2649 (1) 1.56 3.07 1.58 .63 .46 .45 .44 .42 .42 .69 1.17 .84 .51 .41 .52 .65 .00 13.81 (2) .73 1.43 .74 .29 .22 .21 .21 .19 .20 .32 .55 .39 .24 .19 .24 .30 .00 6.45 4-7 786 1407 437 174 174 183 237 322 561 795 1107 761 509 358 376 454 0 8641 (1) 4.10 7.33 2.28 .91 .91 .95 1.24 1.68 2.92 4.14 5.77 3.97 2.65 1.87 1.96 2.37 .00 45.05 (2) 1.91 3.42 1.06 .42 .42 .45 .58 .78 1.36 1.93 2.69 1.85 1.24 .87 .91 1.10 .00 21.02 8-12 935 1264 163 35 37 32 39 82 162 525 792 942 569 258 241 441 0 6517 (1) 4.87 6.59 .85 .18 .19 .17 .20 .43 .84 2.74 4.13 4.91 2.97 1.34 1.26 2.30 .00 33.97 (2) 2.27 3.08 .40 .09 .09 .08 .09 .20 .39 1.28 1.93 2.29 1.38 .63 .59 1.07 .00 15.86 13-18 216 446 19 3 0 2 1 1 11 39 172 265 68 13 11 47 0 1314 (1) 1.13 2.32 .10 .02 .00 .01 .01 .01 .06 .20 .90 1.38 .35 .07 .06 .25 .00 6.85 (2) .53 1.09 .05 .01 .00 .00 .00 .00 .03 .09 .42 .64 .17 .03 .03 .11 .00 3.20 19-24 12 28 1 0 0 0 0 0 0 2 5 10 2 0 0 1 0 61 (1) .06 .15 .01 .00 .00 .00 .00 .00 .00 .01 .03 .05 .01 .00 .00 .01 .00 .32 (2) .03 .07 .00 .00 .00 .00 .00 .00 .00 .00 .01 .02 .00 .00 .00 .00 .00 .15 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 2248 3733 923 333 300 304 362 485 815 1493 2300 2139 1245 709 727 1067 0 19183 (1) 11.72 19.46 4.81 1.74 1.56 1.58 1.89 2.53 4.25 7.78 11.99 11.15 6.49 3.70 3.79 5.56 .00 100.00 (2) 5.47 9.08 2.25 .81 .73 .74 .88 1.18 1.98 3.63 5.60 5.20 3.03 1.73 1.77 2.60 .00 46.68 (1)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C=CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)

- 27 04/25/03

I- - I f 1- ' I TABLE 6 (Sheet 5 of 8)

Yankee Atomic Electric Company, Rowe. Massachusetts 2002 Annual Radioactive Effluent Release Report 1992-1996 Meteorological Data Joint Frequencv Distribution

5. 199.0 FTWIND DATA STABILITY CLASS E CLASS FREQUENCY (PERCENT) = 40.08 WIND DIRECTION FROM SPEED(MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 999 2950 1363 527 310 271 231 250 295 401 523 315 191 171 204 309 0 9310 (1) 6.06 17.91 8.27 3.20 1.88 1.65 1.40 1.52 1.79 2.43 3.17 1.91 1.16 1.04 1.24 1.88 .00 56.51 (2) 2.43 7.18 3.32 1.28 .75 .66 .56 .61 .72 .98 1.27 .77 .46 .42 .50 .75 .00 22.65 4-7 455 2014 392 83 66 59 74 168 242 501 730 340 172 92 151 164 0 5703 (1) 2.76 12.23 2.38 .50 .40 .36 .45 1.02 1.47 3.04 4.43 2.06 1.04 .56 .92 1.00 .00 34.62 (2) 1.11 4.90 .95 .20 .16 .14 .18 .41 .59 1.22 1.78 .83 .42 .22 .37 .40 .00 13.88 8-12 121 331 52 2 1 4 2 17 38 238 176 122 55 22 22 33 0 1236 (1) .73 2.01 .32 .01 .01 .02 .01 .10 .23 1.44 1.07 .74 .33 .13 .13 .20 .00 7.50 (2) .29 .81 .13 .00 .00 .01 .00 .04 .09 .58 .43 .30 .13 .05 .05 .08 .00 3.01 13-18 16 64 7 2 0 0 0 0 4 40 37 26 6 0 1 4 0 207 (1) .10 .39 .04 .01 .00 .00 .00 .00 .02 .24 .22 .16 .04 .00 .01 .02 .00 1.26 (2) .04 .16 .02 .00 .00 .00 .00 .00 .01 .10 .09 .06 .01 .00 .00 .01 .00 .50 19-24 0 7 0 0 0 0 0 0 0 0 9 2 0 0 0 0 0 18 (1) .00 .04 .00 .00 .00 .00 .00 .00 .00 .00 .05 .01 .00 .00 .00 .00 .00 .11 (2) .00 .02 .00 .00 .00 .00 .00 .00 .00 .00 .02 .00 .00 .00 .00 .00 .00 .04 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .0p .00 .00 .00 .00 ALL SPEEDS 1591 5366 1814 614 377 334 307 435 579 1180 1475 805 424 285 378 510 0 16474 (1) 9.66 32.57 11.01 3.73 2.29 2.03 1.86 2.64 3.51 7.16 8.95 4.89 2.57, 1.73 2.29 3.10 .00 100.00 (2) 3.87 13.06 4.41 1.49 .92 .81 .75 1.06 1.41 2.87 3.59 1.96 1.03 .69 .92 1.24 .00 40.08 (1)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C=CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)

- 2 04/25/03

TABLE 6 (Sheet 6 of 8)

Yankee Atomic Electric Company, Rowe. Massachusetts 2002 Annual Radioactive Effluent Release Report 1992-1996 Meteorological Data Joint Frequencv Distribution

6. 199.0 FTWIND DATA STABILITY CLASS F CLASS FREQUENCY (PERCENT) - 8.76 WIND DIRECTION FROM SPEED(MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 156 433 448 220 148 132 112 86 105 133 152 99 92 50 71 83 0 2520 (1) 4.33 12.02 12.44 6.11 4.11 3.67 3.11 2.39 2.92 3.69 4.22 2.75 2.55 1.39 1.97 2.30 .00 69.98 (2) .38 1.05 1.09 .54 .36 .32 .27 .21 .26 .32 .37 .24 .22 .12 .17 .20 .00 6.13 4-7 69 257 83 27 17 10 25 39 54 100 144 68 38 32 34 26 0 1023 (1) 1.92 7.14 2.30 .75 .47 .28 .69 1.08 1.50 2.78 4.00 1.89 1.06 .89 .94 .72 .00 28.41 (2) .17 .63 .20 .07 .04 .02 .06 .09 .13 .24 .35 .17 .09 .08 .08 .06 .00 2.49 8-12 4 13 0 0 0 0 0 0 2 6 14 7 4 1 0 0 0 51 (1) .11 .36 .00 .00 .00 .00 .00 .00 .06 .17 .39 .19 .11 .03 .00 .00 .00 1.42 (2) .01 .03 .00 .00 .00 .00 .00 .00 .00 .01 .03 .02 .01 .00 .00 .00 .00 .12 13-18 1 5 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 7 (1) .03 .14 .00 .00 .00 .00 .00 .00 .00 .00 .03 .00 .00 .00 .00 .00 .00 .19 (2) .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .02 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .0, .00 .00 .00 .00 ALL SPEEDS 230 708 531 247 165 142 137 125 161 239 311 174 134 83 105 109 0 3601 (1) 6.39 19.66 14.75 6.86 4.58 3.94 3.80 3.47 4.47 6.64 8.64 4.83 3.72 2.30 2.92 3.03 .00 100.00 (2) .56 1.72 1.29 .60 .40 .35 .33 .30 .39 .58 .76 .42 .33 .20 .26 .27 .00 8.76 (1)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C=CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 04/25103

TABLE 6 (Sheet 7 of 8)

Yankee Atomic Electric Company. Rowe, Massachusetts 2002 Annual Radioactive Effluent Release Report 1992-1996 Meteorological Data Joint Frequency Distribution

7. 199.0 FT WIND DATA STABILITY CLASS G CLASS FREQUENCY (PERCENT) = 2.79 WIND DIRECTION FROM SPEED(MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 30 88 83 54 60 41 47 46 44 41 52 31 15 13 16 16 0 677 (1) 2.62 7.68 7.24 4.71 5.24 3.58 4.10 4.01 3.84 3.58 4.54 2.71 1.31 1.13 1.40 1.40 .00 59.08 (2) .07 .21 .20 .13 .15 .10 .11 .11 .11 .10 .13 .08 .04 .03 .04 .04 .00 1.65 4-7 14 54 27 16 12 9 18 38 26 73 86 29 14 10 10 4 0 440 (1) 1.22 4.71 2.36 1.40 1.05 .79 1.57 3.32 2.27 6.37 7.50 2.53 1.22 .87 .87 .35 .00 38.39 (2) .03 .13 .07 .04 .03 .02 .04 .09 .06 .18 .21 .07 .03 .02 .02 .01 .00 1.07 8-12 0 3 0 0 0 0 0 0 3 8 8 4 2 0 0 0 0 28 (1) .00 .26 .00 .00 .00 .00 .00 .00 .26 .70 .70 .35 .17 .00 .00 .00 .00 2.44 (2) .00 .01 .00 .00 .00 .00 .00 .00 .01 .02 .02 .01 .00 .00 .00 .00 .00 .07 13-18 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .09 .00 .00 .00 .00 .00 .00 .09 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 44 145 110 70 72 50 65 84 73 122 147 64 31 23 26 20 0 1146 (1) 3.84 12.65 9.60 6.11 6.28 4.36 5.67 7.33 6.37 10.65 12.83 5.58 2.71 2.01 2.27 1.75 .00 100.00 (2) .11 .35 .27 .17 .18 .12 .16 .20 .18 .30 .36 .16 .08 .06 .06 .05 .00 2.79 (1)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C=CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 04125/03

rr- I - I , l - 1--- ' I- V;-- r--- F [-- I-- I-- , ~ , 1- -1 I - r-TABLE 6 (Sheet 8 of 8)

Yankee Atomic Electric Company. Rowe. Massachusetts 2002 Annual Radioactive Effluent Release Report 1992-1996 Meteorological Data Joint Frequency Distribution

8. 199.0 FT WIND DATA STABILITY CLASS ALL CLASS FREQUENCY (PERCENT) = 100 00 WIND DIRECTION FROM SPEED(MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 1486 4061 2204 928 608 531 475 463 526 707 951 606 395 313 391 533 0 15178 (1) 3.62 9.88 5.36 2.26 1.48 1.29 1.16 1.13 1.28 1.72 2.31 1.47 .96 .76 .95 1.30 .00 36.93 (2) 3.62 9.88 5.36 2.26 1.48 1.29 1.16 1.13 1.28 1.72 2.31 1.47 .96 .76 .95 1.30 .00 36.93 4-7 1325 3735 941 300 270 264 356 587 918 1497 2095 1217 740 495 572 648 0 15960 (1) 3.22 9.09 2.29 .73 .66 .64 .87 1.43 2.23 3.64 5.10 2.96 1.80 1.20 1.39 1.58 .00 38.83 (2) 3.22 9.09 2.29 .73 .66 .64 .87 1.43 2.23 3.64 5.10 2.96 1.80 1.20 1.39 1.58 .00 38.83 8-12 1061 1617 216 37 38 36 43 109 230 836 1174 1208 641 283 264 476 0 8269 (1) 2.58 3.93 .53 .09 .09 .09 .10 .27 .56 2.03 2.86 2.94 1.56 .69 .64 1.16 .00 20.12 (2) 2.58 3.93 .53 .09 .09 .09 .10 .27 .56 2.03 2.86 2.94 1.56 .69 .64 1.16 .00 20.12 13-18 235 518 26 5 0 2 1 1 16 83 248 325 76 13 12 51 0 1612 (1) .57 1.26 .06 .01 .00 .00 .00 .00 .04 .20 .60 .79 .18 .03 .03 .12 .00 3.92 (2) .57 1.26 .06 .01 .00 .00 .00 .00 .04 .20 .60 .79 .18 .03 .03 .12 .00 3.92 19-24 12 35 1 0 0 0 0 0 0 2 14 12 2 0 0 1 0 79 (1) .03 .09 .00 .00 .00 .00 .00 .00 .00 .00 .03 .03 .00 .00 .00 .00 .00 .19 (2) .03 .09 .00 .00 .00 .00 .00 .00 .00 .00 .03 .03 .00 .00 .00 .00 .00 .19 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .0p .00 .00 .00 .00 ALL SPEEDS 4119 9966 3388 1270 916 833 875 1160 1690 3125 4482 3368 1854 1105 1239 1709 0 41099 (1) 10.02 24.25 8.24 3.09 2.23 2.03 2.13 2.82 4.11 7.60 10.91 8.19 4.51 2.69 3.01 4.16 .00 100.00 (2) 10.02 24.25 8.24 3.09 2.23 2.03 2.13 2.82- 4.11 7.60 10.91 8.19 4:51 *2.69 3.01 4.16 .00 100.00 (1)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C=CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 04/25103

APPENDIX A Radioactive Liquid Effluent Monitorinq Instrumentation Requirement: Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Control 5.1. With less than the minimum number of channels operable and reasonable efforts to return the instrument(s) to operable status within 30 days being unsuccessful, ODCM Control 5.1 requires an explanation for the delay in correcting the inoperability in the next Annual Radioactive Effluent Release Report.

Response: The requirements of ODCM Control 5.1 governing the operability of radioactive liquid effluent monitoring instrumentation were met for this reporting period.

A-1 042523

APPENDIX B Radioactive Gaseous Effluent Monitoring Instrumentation Requirement: Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Control 5.2. With less than the minimum number of channels operable and reasonable efforts to return the instrument(s) to operable status within 30 days being unsuccessful, ODCM Control 5.2 requires an explanation for the delay in correcting the inoperability in the next Annual Radioactive Effluent Release Report.

Response: The requirements of ODCM Control 5.2 governing the operability of radioactive gaseous effluent monitoring instrumentation were met for this reporting period.

B-1 04D253

APPENDIX C Liquid Holdup Tanks Requirement: Defueled Technical Specification 3.4(a) limits the quantity of radioactive material contained in any outside temporary tank. With the quantity of radioactive material in any outside temporary tank exceeding the limits of Technical Specification 3.4, a description of the events leading to this condition is required in the next Annual Radioactive Effluent Release Report.

Response: The limits of Technical Specification 3.4 were not exceeded during this reporting period.

(a) With the incorporation of Amendment No. 157 the requirements of Technical Specification 3 4 will be relocated to the Yankee Decommissioning Quality Assurance Program.

C-1 04125W3

APPENDIX D Radiological Environmental Monitoring Program Requirement: The Radiological Environmental Monitoring Program is conducted in accordance with ODCM Control 4.1. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 4.1, ODCM Control 4.1 requires a description of the reasons for not conducting the program as required and that plans for preventing a recurrence be included in the next Annual Radioactive Effluent Report.

Response: The requirements of ODCM Control 4.1 governing the conduction of the REMP were met for this reporting period.

Requirement: With milk samples no longer available from one or more of the required sample locations, ODCM Control 4.1 requires the identification of the new location(s) if available, for obtaining replacement sample(s) in the next Annual Radioactive Effluent Release Report and inclusion of revised Off-Site Dose Calculation Manual figure(s) and table(s) reflecting the new location(s).

Response: A total of two milk sampling locations are called for in the REMP; one indicator location and one control. The 2002 land use census did identify two locations with a limited number of goats within 5 miles of the Yankee site in the South sector, one at 2.0 miles and the other at 2.8 miles. Both owners have stated that milk would not be available on a regular basis due to the small number of goats and need for the milk for other purposes. As a consequence of the non-routine availability of milk from these locations, they could not be added to the Radiological Environmental Monitoring Program.

There are no other milk animal locations identified within 5 miles.

D-1 0425tM3

APPENDIX E Land Use Census Requirement: A land use census is conducted in accordance with ODCM Control 4.2. With a land use census identifying a location(s) which yields at least a 20 percent greater dose or dose commitment than the values currently being calculated in ODCM Control 3.5, ODCM Control 4.2 requires the identification of the new location(s) in the next Annual Radioactive Effluent Release Report.

Response: The land use census for this reporting period did not identify any locations yielding at least 20 percent greater dose or dose commitment than the values currently being calculated in ODCM Control 3.5.

Requirement: With a land use census identifying a location(s) which yields a calculated dose or dose commitment (via the same exposure pathway) at least 20 percent greater than at a location from which samples are currently being obtained in accordance with ODCM Control 4.1, ODCM Control 4.2 requires that the new location(s) be added to the Radiological Environmental Monitoring Program if permission from the owner to collect samples can be obtained and sufficient sample volume is available. Ifa new location is found, then it must be identified in the next Annual Radioactive Effluent Release Report.

Response: No new locations were added to the Radiological Environmental Monitoring Program as a result of the 2002 land use census.

E-1 M45/03

APPENDIX F Process Control Proaram (PCP)

Requirement: PCP Control 2.0 requires that licensee-initiated changes to the PCP be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change(s) was made.

Response: There were no licensee-initiated changes to the PCP during this reporting period.

F-1 F4W25/O3

APPENDIX G Off-Site Dose Calculation Manual (ODCM)

Requirement: ODCM Control 7.2 requires that licensee-initiated changes to the ODCM be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change(s) was made effective.

Response: There were no licensee-initiated changes to the ODCM during this reporting period.

G-1 04MS3

APPENDIX H Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems Requirement: ODCM Control 7.3 and PCP Control 3.0 require that licensee-initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Operation Review Committee.

Response: There were no licensee-initiated changes to the radioactive liquid, gaseous, or solid waste treatment systems during this reporting period.

H-1 04s5/03

APPENDIX I Supplemental Information

1. Control Limits - Dose and Dose Rate Control and Category Limit
a. Noble Gases Control 3.3, Total Body Dose Rate 500 mrem/year Control 3.3, Skin Dose Rate 3000 mrem/year Control 3.4, Gamma Air Dose 5 mrad/quarter Control 3.4, Gamma Air Dose 10 mrad/year Control 3.4, Beta Air Dose 10 mrad/quarter Control 3.4, Beta Air Dose 20 mrad/year
b. Iodine-1 31. Tritium. and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days Control 3.3, Organ Dose Rate 1500 mrem/year Control 3.5, Organ Dose 7.5 mrem/quarter Control 3.5, Organ Dose 15 mrem/year
c. Liquids Control 3.1, Total Body Dose 1.5 mrem/quarter Control 3.1, Total Body Dose 3 mrem/year Control 3.1, Organ Dose 5 mrem/quarter Control 3.1, Organ Dose 10 mrem/year
2. Control Limits - Concentration Control and Category Limit
a. Liquids Control 2.1, Total Sum of the Fraction of MPC (10CFR20, 1.0 Appendix B, Table II, Column 2), excluding Noble Gases less than:

Control 2.1, Total Noble Gas Concentration 2.OOE-4 [LCicc 1-1 i425/03

3. Measurements and Approximations of Total Radioactivity
a. Noble Gases. Krvpton-85 Continuous discharges are determined by direct measurements. A primary vent stack gas sample is taken monthly and analyzed for Krypton-85. A review of the weekly primary vent stack noble gas integrator readings for any increase in values above the background level also is used as a reference. There are no longer any batch discharges. Errors associated with the above measurements are estimated to be +/- 50 percent.

In the second quarter of 2002, a Kr-85 laboratory QC source routinely diffused over a three month period. This estimated ground release is listed in Table 1C. During fuel transfer to dry storage in the second half of 2002, it was assumed that small amounts of Kr-85 were released. Any amounts of Kr-85 that may have been released during vacuum drying of the fuel canisters or during fuel sipping were too low to quantify and were, therefore, conservatively estimated in Table 1B. These potential releases were treated as continuous type releases.

b. lodines, Particulates There are no longer any iodine isotopes available for discharge. The sampling system design requires the use of a charcoal cartridge as a support for the particulate filter during particulate collection. The sampling system continuously draws a sample from the primary vent stack through a filter and charcoal cartridge. The particulate filter is removed and analyzed weekly. The errors associated with the determination of particulate effluents are estimated to be +/-30 percent.
c. Liquid Effluents A gamma isotopic analysis is performed on a representative sample using a Marinelli Beaker geometry for both a batch or continuous discharge. Composite samples for batch and continuous discharges are analyzed for strontium-89, strontium-90, iron-55 and gross alpha activity.

Tritium analysis is performed on composite samples for continuous discharges and on each batch discharge. The errors associated with these measurements are as follows:

fission and activation products, +/-20 percent; tritium, +10 percent; dissolved fission gases, +/-20 percent; and alpha activity, +/-35 percent.

1-2 04,25,03

4. Batch Releases
a. Liquids Routine First Quarter Releases Number of batch releases 0 Total time period for batch releases (minutes)

Maximum time period for a batch release (minutes)

Average time period for batch releases (minutes)

Minimum time period for a batch release (minutes)

Average stream flow (Sherman Dam) during period (cfs) 637 Average discharge rate (gpm)

Routine Second Quarter Releases Number of batch releases 0 Total time period for batch releases (minutes)

Maximum time period for a batch release (minutes)

Average time period for batch releases (minutes)

Minimum time period for a batch release (minutes)

Average stream flow (Sherman Dam) during period (cfs) 846 Average discharge rate (gpm)

Routine Third Quarter Releases Number of batch releases 0 Total time period for batch releases (minutes)

Maximum time period for a batch release (minutes)

Average time period for batch releases (minutes)

Minimum time period for a batch release (minutes)

Average stream flow (Sherman Dam) during period (cfs) 303 Average discharge rate (gpm)

Routine Fourth Quarter Releases Number of batch releases 1 Total time period for batch releases (minutes) 1,415 Maximum time period for a batch release (minutes) 1,415 Average time period for batch releases (minutes) 1,415 Minimum time period for a batch release (minutes) 1,415 Average stream flow (Sherman Dam) during period (cfs) 547 Average discharge rate (gpm) 4.6 1-3 oo3

b. Gases There are no longer any batch-mode gaseous releases associated with plant systems.

Estimated Kr-85 releases during QC source diffusion, fuel transfer and fuel sipping operations were treated as continuous releases in the second half of 2002.

5. Abnormal Releases ODCM Control 7.2 requires the reporting of any unplanned releases from the site to the site boundary of radioactive material in gaseous and liquid effluents made during the reporting period.
a. Liquid There were no non-routine liquid releases during the reporting period.
b. Gases There were no non-routine gaseous releases during the reporting period.

1-4 O4M25dM3

APPENDIX J Sewage Sludge Disposal Requirement: For periods in which disposal of septage occurs, the licensee shall report in the Annual Radioactive Effluent Release Report, the volume discharged, liquid and solid fractions, and total activity discharged.

Response: There were no septage disposals for the year 2002.

J-1 04)25103

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