CY-05-117, Annual Radioactive Effluent Release Report

Annual Radioactive Effluent Release Report

ML051230454
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	04/27/2005
From:	Gerard van Noordennen Connecticut Yankee Atomic Power Co
To:	Document Control Desk, NRC/FSME
References
CY-05-117
Download: ML051230454 (44)

Text

3 CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD

• EAST HAMPTON, CT 06424-3099 APR 2 7 2005 Docket No. 50-213 CY-05-117 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Haddam Neck Plant Annual Radioactive Effluent Release Report In accordance with the requirements of 10CFR50.36a and Section 5.6.2 of Appendix F of the Connecticut Yankee Quality Assurance Program (CYQAP) for the Haddam Neck Plant (HNP), a copy of the Annual Radioactive Effluent Release Report is included as Attachment 1. It covers the period of January through December 2004. This report includes a summary of the quantities of solid radioactive waste and liquid and gaseous effluents, as well as a summary of the assessment of maximum individual and population dose resulting from routine radioactive airborne and liquid effluents.

Additionally, this report is submitted to the Connecticut Department of Environmental Protection in accordance with Section 4(D) of the NPDES Permit (Permit ID: CT0003123).

Revisions 16 and 17 of the Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM) and a list of the associated changes are included as Attachment 2 and Attachment 3 respectively.

If you have any questions regarding this submittal, please call me at (860) 267-3938.

Sincerely, GLalA,14'VO Gerard P. van Noordennen Date Regulatory Affairs Manager Attachments: (1) Annual Radioactive Effluent Report (2) Revision 16 to Radiological Effluent Monitoring and Offsite Dose Calculation Manual, and List of Changes (3) Revision 17 to Radiological Effluent Monitoring and Offsite Dose Calculation Manual, and List of Changes cc: S. J. Collins, NRC Region I Administrator T. B. Smith, NRC Project Manager, Haddam Neck Plant R. R. Bellamy, Chief, Decommissioning and Laboratory Branch, NRC Region I Dr. E. L. Wilds, Jr., Director, CT DEP Monitoring and Radiation Division M. Rosenstein, US EPA, Region 1

Docket No. 50-213 CY-05-1 17 ATTACHMENT 1 Annual Radioactive Effluent Report April 2005

ANNUAL RADIOACTIVE EFFLUENT REPORT HADDAM NECK STATION RADIOLOGICAL EFFLUENT CONTROLS PROGRAM JANUARY 1, 2004 - DECEMBER 31,2004 DOCKET NO. 50-213 LICENSE NO. DPR-61 CONNECTICUT YANKEE ATOMIC POWER COMPANY Haddam, Connecticut

TABLE OF CONTENTS 1.0 Introduction 2.0 Summary 3.0 Supplemental Information 3.1 Overview of the Radioactive Effluent Controls Program 3.2 Maximum Permissible Concentration 3.2.1 Gaseous Effluents 3.2.2 Liquid Effluents 3.3 Measurements and Approximation of Total Activity 3.3.1 Gaseous Radioactive Effluents 3.3.2 Liquid Radioactive Effluents 3.4 Batch Releases 3.4.1 Airborne Effluents 3.4.2 Liquid Effluents 3.5 Abnormnal Releases 4.0 Dose Calculation Methodology 4.1 Airborne Effluents 4.2 Liquid Effluents 5.0 Evaluation of Results 5.1 Total Offsite Dose 5.2 Gaseous Effluents 5.3 Liquid Effluents 5.4 Solid Wastes 6.0 Related Information 6.1 Radiation Monitors Out of Service for Greater than Thirty Days 6.2 Radioactive Effluent Condition Reports 7.0 Health Physics Technical Support Document 8.0 REMODCM Revisions in the Year 2004 2 of 42

LIST OF TABLES Table 1 2004 Off-Site Dose Commitments from Airborne Effluents Table 2 2004 Off-Site Dose Commitments from Liquid Effluents Table 3 2004 Off-Site Dose Summary Table 4 2004 Off-Site Dose Comparison Table 5 Airborne Effluents - Total Release Summary Table 6 Airborne Effluents - Mixed Mode Continuous (Main Stack)

Table 7 Airborne Effluents - Ground Continuous (Spent Fuel Building Exhaust)

Table 8 Airborne Effluents - Ground Continuous (Spent Fuel Spray Cooling)

Table 9 Airborne Effluents - Ground Continuous (Miscellaneous potential release points)

Table 10 Liquid Effluents - Total Release Summary Table 11 Liquid Effluents - Batch (FRAC Temporary Tank)

Table 12 Liquid Effluents - Continuous (RCA Yard Drains, GWTT Effluent, Groundwater)

Table 13 2004 Liquid Effluent Release Volumes Table 14 2004 Solid Waste and Irradiated Fuel Shipments LIST OF FIGURES Figure 1 Liquid Dose 2004 Figure 2 FRAC Temporary Tank Activity Released 2004 Figure 3 RCA Yard Drain H-3, Co-60, Sr-90 and Cs-137 Activity Released 2004 Figure 4 Noble Gas Kr-85 Effluent Dose 2004 Figure 5 Gaseous Effluent Maximum Organ Dose 2004 Figure 6 Miscellaneous Gaseous Pathway Activity 2004 Figure 7 Spent Fuel Building Activity Released 2004 Figure 8 Spray Cooling Release Rates During 2004 System Operation (uCi'hr.)

Figure 9 Total Dose 2004 for 10 CFR Part 190 3 of 42

1.0 Introduction As required by the Connecticut Yankee Quality Assurance Program (CYQAP),

Appendix F, Section 5.6.2, this Annual Radioactive Effluent Release Report for the year 2004 is submitted in accordance with 10 CFR 50.36a, "Technical Specifications on effluents from nuclear power reactors." A summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the Haddam Neck Facility is presented in this document. The material provided is consistent with the objectives outlined in the Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM). The information submitted is formatted to the general outline described in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants."

Haddam Neck is currently in the process of decommissioning. In support of the decommissioning effort, radioactive liquid was processed and batch released from Temporary FRAC Tanks in 2004. The radwaste system utilized filters and demineralizers to process radioactive liquid prior to controlled release to the environment. The RCA Yard Drain System is categorized as a continuous release liquid pathway. The major contributors to this release point during 2004 were the External Containment Sump, dewatering wells used for groundwater extraction, groundwater processing system effluent and rainwater.

The transfer of nuclear fuel from the Spent Fuel Pool (SFP) to storage casks commenced in 2004. The loaded storage casks were then transported to the Independent Spent Fuel Storage Installation (ISFSI) for storage until transferred to the Department of Energy for final internment. During the preparation of canisters for the movement of the spent fuel, elevated Kr-85 concentrations were detected in the effluent of the Spent Fuel Building ventilation. The duration and quantity of Noble Gas (Kr-85) released was quantified and included in this annual report.

The mixed mode elevated gaseous release pathway from the Main Stack was removed during 2004. The temporary ventilation units that replaced the former stack were included in the gaseous effluent monitoring program. As the decommissioning project creates new potential gaseous release pathways, baseline data will be collected and, if necessary, the release point will be added to the monitoring program. The Alternate Containment Access, Alternate Containment and PAB Ventilation, Cable Vault, Containment Foyer, Tank Farm Tent and Terry Turbine are examples of miscellaneous pathways that were routinely monitored.

2.0 Summary The radioactive effluent monitoring program for 2004 was conducted in accordance with CYQAP section 5.4. The results of the monitoring program indicate that the 4 of 42

Haddam Neck Plant was successful in maintaining radioactive effluent releases to the environment as low as reasonably achievable.

A general overview of the radioactive gaseous releases to the environment during 2004 is summarized below:

• The total whole body dose due to gaseous radioactivity released was 2.32E-02 mrem. This is approximately 0.46 % of the allowable limit.

• The maximum organ dose due to gaseous radioactivity was 1.29E-01 mrem.

This is approximately 0.86 % of the allowable limit.

• The calculated beta air dose due to noble gases was 2.47 mrad. This is approximately 12.35 % of the allowable limit.

• The calculated gamma air dose due to noble gases was 2.18E-02 mrad. This is approximately 0.22 % of the allowable limit.

• The total gaseous tritium released was 1.65 curies.

• The total gaseous particulate activity released was 1.14E-04 curies.

• The total gaseous gross alpha activity released was 5.22E-07 curies.

• The total gaseous Sr-90 activity released was 3.52E-06 curies.

A general overview of the radioactive liquid releases to the environment during 2004 is summarized below:

• The total whole body dose due to liquid radioactivity released was 3.02E-01 mrem. This is approximately 10.1 % of the allowable limit.

• The maximum organ dose due to liquid radioactivity released was 4.73E-01 mrem. This is approximately 4.7 % of the allowable limit.

• The total volume of radioactive liquid processed and batch released was 254,694 gallons. The estimated total volume of radioactive liquid released from the RCA Yard Drain System was 15,711,491 gallons.

• The total amount of radioactivity from liquids released to the environment was 9.74E-01 curies.

• Of the total curies released, 9.66E-01 were attributed to tritium and 7.94E-03 curies from all other nuclides.

The effluent dose contributions for this report period are significantly less than regulatory limits and natural background dose contributions.

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A review of the radioactive waste program showed 3.46E+04 cubic meters of solid waste containing 3.74E+02 curies of radioactivity was shipped offsite for processing or disposal.

3.0 Supplemental Information 3.1 Overview of the Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the dose to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program shall be contained in the REMODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation, including surveillance tests and set point determinations, in accordance with the methodology described in the REMODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to the pre-1994 concentration values in 10 CFR Part 20, Appendix B (to 20.1 to 20.602), Table II, Column 2;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters described in the REMODCM;

d. Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the facility to unrestricted areas, conforming to 10 CFR Part 50, Appendix I;

e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters described in the REMODCM (performed at least every 92 days);

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2%

of the guidelines for the annual dose or dose commitment, conforming to 10 CFR Part 50, Appendix I; 6 of 42

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY shall be as follows;

1. for noble gases: less than or equal to a dose rate of 500 mrem/yr to the total body and less than or equal to a dose of 3000 mrem/yr to the skin; and

2. for tritium and all radionuclides in particulate form with half-lives greater than 8 days: less than or equal to a dose rate of 1500 mrem/yr. to any organ;

h. Limitations on the annual and quarterly air doses from noble gases released in gaseous effluents from the unit to areas beyond the SITE BOUNDARY, conforming to 10 CFR Part 50, Appendix I;

i. Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each facility to areas beyond the SITE BOUNDARY, conforming to 10 CFR Part 50, Appendix I; and

j. Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC at points beyond the SITE BOUNDARY due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR Part 190.

3.2 Maximum Permissible Concentration 3.2.1 Gaseous Effluents The applicable limits for gaseous effluents are expressed in terms of dose rate at the site boundary.

3.2.2 Liquid Effluents The values specified in 10 CFR Part 20, Appendix B, Table 2, Column 2, (pre-1994 edition), were used as the limits for radioactive effluents released to unrestricted areas.

3.3 Measurements and Approximation of Total Activity 3.3.1 Gaseous Radioactive Effluents Gaseous effluent release pathways were sampled and analyzed weekly for tritium, particulates and noble gas, as required. During spent fuel transfer evolutions the noble gas effluent release was accounted for by 7 of 42

integrating the Spent Fuel Exhaust Radiation Monitor chart recordings.

Particulate release pathways were continuously sampled using air filters.

The particulate filters were analyzed weekly for gamma radioactivity, monthly for gross alpha and gross beta activity. Particulate filters exhibiting a positive gross beta were saved for quarterly Sr-90 analysis.

The results for radioactivity from gaseous effluents and the effluent flow rate were used to determine the total amount of activity released.

The following estimates for the uncertainty associated with gaseous sample analysis stem from a composite of variances in effluent flow rates, instrumentation tolerances and low level counting statistics.

Tritium 25%

Fission and Activation Products 25%

Gross Alpha, Sr-90 25%

Noble Gas 25%

3.3.2 Liquid Radioactive Effluents Each batch release was sampled and analyzed for gamma emitting radionuclides prior to release. Composite samples were analyzed monthly for gross alpha and quarterly for Fe-55 and Sr-90. The results of the composite analyses from the previous month or quarter were used to estimate the quantities of these radionuclides in liquid effluents during the current month or quarter. The total radioactivity in liquid effluent releases was determined from the measured concentrations of each radionuclide present and the total volume of the effluent released during periods of discharge.

The RCA Yard Drain continuous release pathway was sampled at the Yard Drain 6 sample point with an automatic composite sampler or by obtaining daily grab samples. As necessary, grab samples were obtained from individual release sources to the RCA Yard Drain system and a separate composite generated in order to properly account for the radioactivity released. Composites were analyzed each week for gamma emitting radionuclides and tritium. Analyses were performed to the minimum detection levels for environmental media. Composite samples were analyzed monthly for gross alpha and quarterly for Fe-55 and Sr-

90. The results of the composite analyses from the previous month or quarter were used to estimate the quantities of these radionuclides in liquid effluents during the current month or quarter. The total radioactivity in liquid effluent releases was determined from the measured concentrations of each radionuclide present and the total volume of the effluent released during the period of discharge.

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The following estimates for the uncertainty associated with liquid sample analysis stem from a composite of variances in effluent flow rates, instrumentation tolerances and low level counting statistics.

Tritium 25%

Fission and Activation Products 25%

Gross Alpha 25%

Sr-90, Fe-55 25%

3.4 Batch Releases 3.4.1 Airborne Effluents None 3.4.2 Liquid Effluents Number of Batches: 19 Total Time (min.): 5019 Maximum Time (min.): 425 Average Time (min.): 264 Minimum Time (min.): 1 Average dilution flow during releases: 34.5 cfs Tidal Flow 3.5 Abnormal Releases None 4.0 Dose Calculation Methodology 4.1 Airborne Effluents Maximum individual doses and population doses due to the release of noble gases and particulates were calculated using the computer program GASPAR II. GASPAR II is used by the staff of the NRC to perform environmental dose analyses for releases of radioactive effluents from nuclear power plants into the atmosphere. The program estimates radiation dose to individuals and population groups from inhalation, ingestion (terrestrial foods), and external-exposure (ground and plume) pathways. Additional information related to the GASPAR II program is in NUREG/CR-4653, "GASPAR II -Technical Reference and User Guide".

The values of average relative effluent concentration (X/Q) and average relative deposition (D/Q) used in GASPAR II to determine -population doses were generated using a meteorological computer code which implements the assumptions cited in Section C, NRC Regulatory Guide 1.111. These values were generated in 1999, the last year that real time data was collected. The X/Q 9 of 42

and D/Q values used in the GASPAR II program to determine maximum individual doses were obtained from Appendix F of the REMODCM. Separate values were used for the growing season (defined as April-December) and non-growing season (defined as January-March).

While in operation, continuous mixed mode releases from the Main Stack (175 fi) included the Reactor Containment, temporary tent enclosing the tank farm and the Primary Auxiliary Building Ventilation. After the Main Stack was removed from service, individual temporary ventilation units were installed at individual release points and included in the monitoring program for ground level releases. The Spent Fuel Pool Spray Cooling, Spent Fuel Building Exhaust and other miscellaneous monitored release points were also considered continuous ground level releases.

GASPAR II calculates the maximum individual and population doses to the whole body, GI-tract, bone, liver, kidney, thyroid, lung, and skin from each of the following pathways: direct exposure from the plume and ground deposition, inhalation, and ingestion of vegetation, cow's milk, and meat. The doses are calculated for adults, teenagers, children, and infants separately.

To determine compliance with IOCFR50, Appendix I, the maximum whole body dose to an individual only includes the external pathways (i.e. plume and ground exposure) while the maximum organ dose to an individual only includes the internal pathways (inhalation and ingestion). All applicable pathways were included for the population doses.

The off-site dose commitments from airborne effluents are presented in Table 1.

4.2 Liquid Effluents Maximum individual and population doses from the release of radioactive liquid effluents were calculated using the computer program LADTAP II. LADTAP II is a NRC computer program, which performs environmental dose analyses for releases of radioactive effluents from nuclear power plants into surface waters.

The program estimates radiation dose to individuals, population groups, and biota from ingestion (aquatic foods, water, and terrestrial irrigated foods) and external exposure (shoreline, swimming, and boating) pathways. Additional information relating to the LADTAP II program is in NUREG/CR-4013, "LADTAP II -Technical Reference and User Guide".

At Haddam Neck, the algae, drinking water, and irrigated food pathways do not exist; and therefore were not included in the totals. Doses are calculated for the whole body, skin, thyroid, GI-LLI, bone, liver, kidney, and lung. Calculations are performed separately for adults, teenagers, and children.

The off-site dose commitments from liquid effluents are presented in Table 2.

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5.0 Evaluation of Results 5.1 Total Offsite Dose The dose commitments calculated using the release data for this report period are compared to 10 CFR Part 50, Appendix I, in Table 3, and compared to 40 CFR Part 190 limits in Table 4.

The whole body and maximum organ total doses for each month in this report period are presented in Figure 9. The contributions shown were calculated using Method 1 in the REMODCM for gaseous and liquid contributions. As expected, the total dose increased in the months corresponding to larger volumes of liquid being released and spent fuel transfer operations.

The effluent dose contributions for this report period are significantly less than regulatory limits and natural backgrounds dose contribution.

5.2 Gaseous Effluents The total activity released from all gaseous effluent pathways is summarized in Table 5. Each pathway's contribution to the total activity released is shown in Tables 6-9. The figures described below were used to identify trends for this report period:

• The monthly air dose from the release of Kr-85 is presented in Figure 4.

Health Physics Technical Support Document CY-HP-0176, Rev. 0, "Evaluation for Spent Fuel Building Radiation Monitors Set-points during Cask Movement and Kr-85 releases during Vacuum Drying System Operation", provides the technical bases for method used to calculate the amount of Kr-85 released to the environment. The dose calculations were performed in accordance with the REMODCM

• The monthly maximum organ dose compared to the total year to date dose is presented in Figure 5. The calculations were performed using Method 1 in the REMODCM. The contribution for each month remained consistent throughout this report period.

• The activity released for each month from miscellaneous gaseous pathways is presented in Figure 6.

• The activity released for each month from the Spent Fuel Building pathway is presented in Figure 7.

• The release rates (uCi/hr) for specific nuclides from the Spray Cooling System are shown in Figure 8. The release rates are consistent for this report period.

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The monthly maximum organ dose calculated using Method 1 in the REMODCM were conservatively higher than the calculations using GASPAR II for this report. The REMODCM includes adjustment factors for Method 1 that if used, would have corrected the monthly organ dose calculations to be within 6%

of the dose calculated for this report (GASPAR II).

The monthly noble gas dose for gamma and beta radiation was calculated in accordance with the REMODCM. The monthly results were within 8% of the dose calculated for this report (GASPAR II) for the air dose offsite from beta and gamma radiation..

This indicates the methodology currently used in the monthly calculations includes the necessary conservatism to ensure limitations are not exceeded.

5.3 Liquid Effluents The total activity released from all liquid effluent pathways is summarized in Table 10. Each pathway's contribution to the total activity released is presented in Tables 11 and 12. The volume released from batch and RCA Yard Drain discharges for this report period is presented in Table 13. The figures described below were used to identify trends for this report period:

• The monthly whole body and maximum organ doses compared against the total year to date is presented in Figure 1. The calculations were performed using Method 1 in the REMODCM. As expected, the doses increase for the periods corresponding to large volumes of liquid waste being discharged.

• Specific contributions from individual nuclides released to the environment from batch discharges are presented in Figure 2. As expected, increases in radioactivity released corresponded to larger volumes of water being discharged.

• Specific contributions from individual nuclides released to the environment from the RCA Yard Drain System are presented in Figure 3. The major contributors to this release point during 2004 were the External Containment Sump, dewatering wells used for groundwater extraction, groundwater processing system effluent and rainwater. As shown on Figure 3, the total Cs-137 activity released shows a substantial increase during the fourth quarter. The increase was due to the significant groundwater dewatering operations performed to support the excavation of contaminated soil. A conservative estimate for the effluent volume is used in release calculations for this pathway.

The monthly doses calculated using Method I in the REMODCM was consistent with the calculations using LADTAP II for this report. The summed monthly 12 of 42

doses calculated using Method 1 were within approximately 6% of the Whole Body and Maximum Organ calculations using LADTAP II for the year 2004.

This indicates the methodology currently used in the monthly calculations includes the necessary conservatism to ensure limitations are not exceeded.

5.4 Solid Wastes The quantities of radioactive material shipped offsite for processing or disposal are summarized in Table 14.

6.0 Related Information 6.1 Radiation Monitors Out of Service for Greater than Thirty Days.

6.1.1 The liquid effluent radiation monitor R-22 was placed out of service on June 14, 2004 due to system modifications on the radwaste treatment system. The processing system was dismantled and moved to the Radwaste Reduction Facility (RRF). The system modifications were completed in August 2004. There were no batch liquid releases performed while the system modifications were being performed.

Condition Report 04-0905 was generated to document the radiation monitor was not available for greater than thirty days.

6.2 Radioactive Effluent Condition Reports 6.2.1 The sample flow alarm for the Main Stack R-2 particulate monitor was found disabled on March 11, 2004. The alarm was disabled by a technician performing the weekly sample collection for particulate activity. After the sample was obtained and the particulate filter replaced the technician did not verify the alarm was left in the enabled condition. The flow rate is checked every four hours and was not outside of the acceptable sample flow rate during the time without the alarm. Condition Report 04-0342 was generated to document this condition. An enhancement to the procedure was performed to ensure this would not occur in future sampling events.

6.2.2 An environmental air sampler monitoring the Terry Turbine area was found out of calibration. The air sampler was in service for three days past the expired calibration. The RASP pump was changed out for one with a satisfactory expiration date. The "as found" calibration data on the pump showed that the pump was within calibration acceptance criteria. Condition Report 04-0688 was generated to document this condition.

6.2.3 An environmental air sampler was not started after a planned electrical outage. Temporary power was supplied until a reliable supply was 13 of 42

available. No releases occurred during the outage and other environmental air samplers were maintained operational. Condition Report 04-0708 was generated to document this condition. As a precaution to ensure this was not overlooked during future planned electrical outages the sampler was added to the power recovery checklist.

6.2.4 An environmental air sample was not analyzed for particulate activity within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> as required by the REMODCM. This particulate sample location was normally changed out by a Chemistry Technician.

Due to a power interruption the filter was obtained by a Health Physics Technician and not delivered to the count room in a timely manner for analysis. Condition Report 04-0932 was generated to document this condition. Technicians were informed to deliver environmental air samples directly to the count room for timely analysis.

6.2.5 The beta radiation dose result logged in the May 2004 Offsite Dose Tracking worksheet was incorrect. The dose was calculated correctly but an error occurred in the transposition to the worksheet. The entry was corrected and submitted for review. Condition Report 04-0934 was generated to document this condition.

6.2.6 A planned noble gas release during spent fuel transfer operations resulted in the R-1 effluent monitor reading exceeding a procedural limit. The release was terminated by the control room operators. The procedure was found to be misleading on reporting requirements surrounding a planned release. The release did not exceed regulatory release rate limits and the spent fuel transfer operations were restarted.

Condition Report 04-0991 was generated to document this condition.

The procedure was revised to clarify the control room operator actions for R-1 readings during spent fuel transfer operations.

6.2.7 During the start of the first liquid release from the RRF, liquid effluent radiation monitor R-22 alarmed and secured the release. A total of 4 gallons was released before being secured. The FRAC Tank was re-sampled and the results compared well to the concentrations reported prior to release. A sample was collected from the radiation monitor and the results showed significantly higher concentrations of radioactivity than the FRAC Tank being released. The cause of the alarm was determined to be residual activity in the hoses from past operations. The hoses were the same ones that had been used before the system was moved to the RRF. The hoses were flushed and the release continued without alarms. The sample from the radiation monitor was saved for composite and included in the monthly and 14 of 42

quarterly analyses. Condition Report 04-1120 was generated to document this condition.

6.2.8 Radiation Monitor R-22 alarmed and secured the release from a FRAC Tank. The FRAC Tank was re-sampled and the concentrations compared well with the results reported prior to release. To investigate the spurious alarm, Maintenance Department personnel performed the quarterly electronic checks on the monitor and it was found to be in good operating condition. Steady state readings were obtained over a few days with no deficiencies noted. The FRAC Tank release was restarted and was completed without alarming R-22. It is suspected that outgoing radwaste or the transfer of the casks to the ISFSI may have influenced the sudden increase during transit by the RRF. Operations were informed to be aware of this possibility during future releases. Condition Report 04-1302 was generated to document this condition.

6.2.9 The method of accounting for the radioactivity being released through the RCA Yard Drain system was found to be inadequate when the waste characteristics changed on the effluent of the groundwater treatment system. The groundwater treatment system was releasing liquid waste containing only tritium and the results compared well with other release sources to the Yard Drains. When gamma activity was identified on the effluent of the groundwater treatment system, the method for compositing based upon only tritium releases became invalid. Samples were saved and a procedure revision was completed to account for the radioactivity released from the groundwater treatment system separate from other Yard Drain sources. Condition Report 04-1653 was generated to document this condition.

6.2.10 An environmental air sample was not obtained while performing work in an area with the potential for an effluent release. As a conservative measure, the air sample from the work location covering the job activity was used to bound the potential unmonitored release. The work location filter was included in the monthly and quarterly analyses and included in calculated doses. Condition Report 04-1662 was generated to document this condition.

7.0 Health Physics Technical Support Document Health Physics Technical Support Document, HP-CY-0204, "Radioactivity Effluent Analysis for the Year 2004", was generated to document the calculations performed for this report. Site specific, environmental information and other input data that was necessary to complete this report are listed and discussed in the technical support document.

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8.0 REMODCM Revisions in the Year 2004 Revision 17 to the REMODCM was issued January 26, 2004. A copy of revision 17 and the information to support the changes have been included with the submission of this annual report.

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Table 1 2004 Off-Site Dose Commitments from Airborne Effluents Haddam Neck CY 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Max Air (mrad) (mrad) (mrad) (mrad)

Beta 0 1.72E-01 2.13E+00 1.71E-01 Gamma 0 1.52E-03 1.88E-02 1.51E-03 Max Individual (mrem) (rnrem) (mrem) (mrem)

Whole Body4 1.33E-04 3.81E-03 1.62E-02 3.02E-03 Skin+ 1.56E-04 1.23E-01 1.48E+00 1.20E-01 Thyroid 1.03E-02 1.65E-02 1.37E-02 5.29E-03 Max OrganH 1.15E-02 3.95E-02 5.12E-02 2.66E-02 Population (person-rem) (person-rem) (person-rem) (person-rem)

Whole Body 1.23E-03 3.76E-03 1.03E-02 1.90E-03 Skin 1.21E-03 5.59E-02 8.60E-01 5.57E-02 Thyroid 1.21E-03 3.56E-03 9.04E-03 1.60E-03 Max Organ+ 1.25E-03 4.48E-03 3.31E-02 7.94E-03 Avg Individual (mrem) (mrem) (mrem) (mrem)

Whole Body 3.20E-07 9.81E-07 2.68E-06 4.96E-07 Skin 3.16E-07 1.46E-05 2.24E-04 1.45E-05 Thyroid 3.15E-07 9.29E-07 2.36E-06 4.17E-07 Max Organ+ 3.26E-07 1.17E-06 8.64E-06 2.07E-06

+ External doses only

++Maximum of the following organs: Bone, GI-LLI, Kidney, Liver, Lung, Thyroid 17 of 42

Table 2 2004 Off-Site Dose Commitments from Liquid Effluents Haddam Neck CY 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Max Individual (mrem) (mrem) (mrem) (mrem)

Whole Body 1.20E-01 9.35E-02 3.52E-03 8.53E-02 Thyroid 1.71E-03 2.31E-03 6.34E-05 1.1OE-03 Max Organ 1.84E-01 1.49E-01 7.64E-03 1.32E-01 Population (person-rem) (person-rem) (person-rem) (person-rem)

Whole Body 2.16E+00 1.68E+00 6.70E-02 1.53E+00 Thyroid 7.58E-04 1.07E-03 5.38E-04 8.68E-04 Max Organ 3.88E+00 2.88E+00 1.66E-01 2.80E+00 Avg Individual (mrem) (mrem) (mrem) (mrem)

Whole Body 5.64E-04 4.38E-04 1.75E-05 3.99E-04 Thyroid 1.98E-07 2.79E-07 1.40E-07 2.26E-07 Max Organ 1.01E-03 7.51E-04 4.33E-05 7.30E-04 18 of 42

Table 3 2004 Off-Site Dose Summary Haddam Neck Airborne Effluents Population Dose Commitments (total person-rem within 50 miles) l Whole Body l Thyroid l Max Organ l 1.71E-02 I 1.54E-02 I 4.68E-02 Max Individual Dose/Dose Commitments vs 10CFR50, Appendix I Gamma Beta Air Whole Body Max Organ Skin Air Dose Dose (mrem) (mrem) (mrem) (mrad) (mrad)

I.B andICLimits 5 15 15 10 20 Haddam Neck Total 2.32E-02 1.29E-01 I 1.73E+00 12.18E-02 2.47 Liquid Effluents Population Dose Commitments (total person-rem within 50 miles) l Whole Body I Thyroid l Max Organ l 5.44 l 3.23E-03 l 9.73 l Max Individual Dose/Dose Commitments vs 10CFR50, Appendix I I.

Whole Body Max Organ (mrem) (mrem)

II.A Limits 3 1 10 Haddam Neck Total 3.02E-01 I_4.73_-01 19 of 42

Table 4 2004 Off-Site Dose Comparison Haddam Neck Max Individual Annual Dose vs 40CFR190 Limits Whole Body Any Organ Thyroid (mrem) (mrem) (mrem) 40CFR190 Limit 25 25 75 Airborne Effluents 2.32E-02 1.29E-01 4.58E-02 Liquid Effluents 3.02E-01 4.73E-01 5.18E-03 Haddam Neck Total 3.26E-01 6.01E-01 5.10E-02 Whole Bod' Dose from Hladdam Neck Plant vs. Background Radiation Sources of Background Radiation:

Cosmic 26 Cosmogenic 1 Terrestial (Atlantic and Gulf Coastal Plain) 23 Inhaled 200 In the Bodv 40 l CT Resident Whole Body Dose from Backgrund l 290 mrem I ICT Resident (within 50 miles) Whole Body Dose from l l IHaddam Neck Plant Airbome and Liquid Effluents I 1.42E-03 mrem I IMaximum Individual (within 50 miles) Whole Body Dose from l l IHaddam Neck Plant Airbome and Liquid Effluents I 3.26E-01 mrem I 20 of 42

Table 5 Haddam Neck Airborne Effluents - Total Release Summary I 2004 l Units I 1st Qtr T 2nd Qtr I 3rd Qtr I 4th Qtr I Total A. Fission & Activation Gases

1. Total Activity Ci Released

2. Average juCi/se J -

9.03E+00 1.15E+OO 1.12E+02 1.40E+01 8.94E+00 1.30E+02 1.12E+00 4.1OE+OO Release Rate B. lodines

1. Total Activity Ci - -

Released

2. Average uCi/sec Release Rate C. Particulates

1. Total Activity Ci 2.78E-06 3.27E-05 6.66E-05 1.36E-05 1.16E-04 Released

2. Average uCi/sec 3.53E-07 4.16E-06 8.38E-06 1.71E-06 3.66E-06 Release Rate .

D. Gross Alpha

1. Total Activity Ci - 9.54E-07 2.OOE-07 1.15E-06 Released

2. Average uCi/sec 1.20E-07 2.52E-08 3.65E-08 Release Rate E. Tritium

1. Total Activity Ci 3.76E-01 5.97E-01 4.85E-01 1.93E-01 1.65E+OOl Released I j I

2. Average uCi/sec 4.78E-02 7.60E-02 6.10E-02 2.42E-02 5.22E-02 Release Rate 21 of 42

Table 6 Haddam Neck Airborne Effluents - Mixed Mode Continuous Main Stack Nuclides l l 2004 Released I Units I1st Qtr 2nd Qtr T 3rd Qtr 4th Qtr Total J A. Fission & Activation Gases II 7 T otalAc t ivit yl ci I Ci I [ 1] -

I I

I I I

I I J I

B. lodines II lTotal Activityl Ci IIIIII Ci IlI -  :

C. Particulates Co-60 Ci l - 1.59E-06 11.09E-05 - 1.25E-05 Sr-90 Ci J 2.69E-08 - - - l 2.69E-08 Cs-137 Ci 7 1.63E-06 4.48E-06 l 2.52E-05 7 - 3.13E-05 Total Activity, Ci J 1.65E-06 6.07E-06 l 3.61E-05 7 - 4.38E-05 D. Gross Alpha lGross Alpha I Ci - 6.33E-07 I - 6.33E-07 E. Tritium H-3 I Ci I I

- (For Fission & Act Gas) = Not Required to be analyzed.

- (For lodine's) = Not Required to be analyzed.

- (For Particulates) = < Lower Limit of Detection as specified in the REMODCM

- (For Gross Alpha) = < Lower Limit of Detection as specified in the REMODCM 22 of 42

Table 7 Haddam Neck Airborne Effluents - Ground Continuous Spent Fuel Building Exhaust E Nuclides Released l

I Units l 1st Qtr 2nd Qtr 2004 3rd Qtr I 4th Qtr Total A. Fission & Activation Gases Kr-85 j Ci I - l9.03E+00 l 1.12E+02 I 8.94E+00 1.30E+02 ITotal Activityl Ci I - l9.03E+00 l 1.12E+02 8.94E+00 I 1.30E+02l B. lodines lTotal Activityl Ci I lI - l I C. Particulates Co-60 Ci l - - 2.22E-06 1.60E-06 3.82E-06 sr-917 Ci - 4.71--7 5.45E-08 5.45E-08 Cs-137 Ci - 4.71E-07 1.27E-06 1.07E-07 1.85E-06 Total Activity, Ci - 4.71E-07 3.49E-06 1.76E-06 5.72E-06 D. Gross Alpha lGross Alpha I Ci - 2.24E-08 I 4.04E-08 6.28E-08 E. Tritium lH-3 I Ci I 3.76E-01 I 5.97E-01 I 4.82E-01 I 1.93E-01 I1.65E+00 (For Fission & Act Gas) = < Lower Limit of Detection as specified in the REMODCM (For lodine's) = Not Required to be analyzed (For Particulates) = < Lower Limit of Detection as specified in the REMODCM (For Gross Alpha) = < Lower Limit of Detection as specified in the REMODCM 23 of 42

Table 8 Haddam Neck Airborne Effluents - Ground Continuous Spent Fuel Spray Cooling lNuclides l l2004l uReleased Units 1st Qtr 2nd Qtr 3rdQtr 4th Qtr Total A. Fission & Activation Gases GiIL-- ]j I j B. lodines lTotal Activityl Ci I C. Particulates Co-60 Ci 1.05E-06 7.30E-07 2.08E-08 1.80E-06 Cs-134 Ci 6.91E-08 - - 6.91E-08 Cs-137 Ci 7.76E-06 6.83E-06 1.57E-07 1.47E-05 Total Activity Ci 8.88E-06 7.56E-06 1.78E-07 1.66E-05 D. Gross Alpha Gross Alpha Ci -- --

E. Tritium 1H-3 Ci - 4.95E-04 I 2.67E-03 I 2.19E-05 3.19E-03 (For Fission & Act Gas) = Not Required to be analyzed.

(For lodine's) = Not Required to be analyzed.

(For Particulates) = < Lower Limit of Detection as specified in the REMODCM (For Gross Alpha) = < Lower Limit of Detection as specified in the REMODCM 24 of 42

Table 9 Haddam Neck Airborne Effluents - Ground Continuous Miscellaneous potential release points (Alternate Access, Containment Foyer, Cable Vault, Terry Turbine, Alternate Containment, SRF, etc.)

lNuclides l 2004 lReleased I Units I Idst Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases

[Total Activityl Ci I - - I I I B. Iodines II

[To t al Ac t ivit yl Ci ci IIIIII J

- ] I j j C. Particulates Co-60 Ci 1.80E-07 3.50E-06 1.05E-05 1.02E-05 l 2.44E-05 Sr-90 Ci 5.97E-08 3.97E-07 2.46E-06 5.16E-07 3.44E-06 Cs-137 Ci 8.85E-07 1.34E-05 6.46E-06 9.90E-07 2.17E-05 Eu-154 Ci - - - 8.06E-09 8.06E-09 Total Activity Ci 1.12E-06 1.73E-05 1.95E-05 1.17E-05 4.95E-05 D. Gross Alpha Gross Al ha Ci - - 2.99E-07 1.60E-07 4.59E-07 I E. Tritium H-3 I Ci I

- (For Fission & Act Gas) = Not Required to be analyzed.

- (For lodine's) = Not Required to be analyzed.

- (For Particulates) = < Lower Limit of Detection as specified in the REMODCM

- (For tritium) = Not Required to be analyzed.

- (For Gross Alpha) = < Lower Limit of Detection as specified in the REMODCM 25 of 42

Table 10 Haddam Neck Liquid Effluents - Total Release Summary 1 2004

[Unitsl 1stQtr I 2ndQtr I3rd Qtr I 4th Qtr I Total I A. Fission and Activation Products

1. Total Activity Ci I 2.98E-03 2.90E-03 l 1.81E-04 I 1.85E-03 T 7.91E-03 l Released

2. Average Period Diluted Activity C. Dissolved and Entrained Gases

1. Total Activity Ci -

Released

2. Average Diluted Ci/ml -

Activity D. Gross Alpha

1. Total Activity Ci - 1.1 E-05 1.76E-05 2.87E-05 Released

2. Average Diluted Ci/ml - 1.4413-12 - 2.27-12 9.2813-13 Activity E. Volume

1. Released Waste Liters 1.20E+07 1.79E+07 1.43E+07 1.6213+07 6.0413+07 Volume

2. Dilution Volum Liters 7.69E+09 7.69E+09 7.77E+09 7.77E+09 3.09E+10 During Releases

3. Dilution Volum Liters 7.69E+09 7.69E+09 7.77E+09 7.77E+09 3.09E+10 During Period I 26 of 42

Table 11 Haddam Neck Liquid Effluents - Batch (FRAC Temporary Tank)

[ Nuclides Released l

Units 2004 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total 1

I A. Fission & Activation Products Am-241 Ci 7.29E-06 1.65E-05 1.16E-08 2.38E-05 Co-60 Ci 1.05E-03 1.83E-03 2.44E-05 5.58E-04 3.46E-03 Cs-134 Ci 1.1 E-05 9.17E-06 - 8.27E-06 2.85E-05 Cs-137 Ci 1.16E-03 8.36E-04 1.56E-05 6.47E-04 2.66E-03 Fe-55 Ci 6.1 OE-04 1.O1E-04 3.14E-04 1.03E-03 Sr-90 Ci 3.56E-05 1.38E-04 1.74E-04 Sb-125 Ci 5.02E-05 - - 5.02E-05 Total Activity Ci 2.92E-03 I 2.83E-03 1.41 E-04 1.53E-03 7.42E-03 B. Tritium lH-3 Ci I 4.19E-02 I 9.50E-02 l3.43E-01 I 2.46E-01 I 7.26E-O1 C. Dissolved & Entrained Gases Ici I - I - I - - I -

lTotal Activity I Ci I - - - - -

D. Gross Alpha lGross Alpha I Ci l - 1 lE-05 - 1.76E-05 2.87E-05

- (For Fission & Act Products) = < Lower Limit of Detection as specified in the REMODCM

- (For Dissolved & Entrained Gases) = < Lower Limit of Detection as specified in the REMODCM

- (For Gross Alpha)= <Lower Limit of Detection as specified in the REMODCM 27 of 42

Table 12 Haddam Neck Liquid Effluents - Continuous (RCA Yard Drains, GWTT Effluent, Groundwater)

Nuclides 2004 l Released Units 1st Qtr 2nd Qtr I 3rd Qtr I 4th Qtr l Total A. Fission & Activation Products Sr-90 Ci 5.85E-05 7.27E-05 3.32E-05 3.70E-05 2.01E-04 Mn-54 Ci - - - 4.70E-05 4.70E-05 Co-60 Ci 4.80E-05 4.80E-05 Cs-137 Ci 6.93E-06 1.89E-04 1.96E-04 Total Activity Ci 5.85E-05 7.27E-05 4.01E-05 3.21E-04 4.92E-04 B. Tritium lH-3 Ci 2.54E-02 I 3.60E-02 I 6.78E-02 I l.1lE-01 I 2.40E-01l C. Dissolved & Entrained Gases I Ci I - I I - I I lTotal Activity I Ci - - - - -

D. Gross Alpha lGross Alpha Ci - - - - -

- (For Fission & Act Products) = < Lower Limit of Detection as specified in thc REMODCM

- (For Dissolved & Entrained Gases) = Not Required to be analyzed

- (For Gross Alpha) = < Lower Limit of Detection as specified in the REMODCM 28 of 42

Table 13 2004 Liquid Effluent Release Volumes FRAC Tanks RCA Yard Drain Month Volume Released Volume Released (gallons) (gallons)

January 13,800 1,184,840 February 47,133 966,640 March 9,725 955,420 r

I April 44,365 1,231,500 May 16,600 1,880,200 June 19,550 1,527,580 r

July 0 1,319,253 August 17,760 1,184,621 September 36,381 1,224,986 October 0 1,477,057 November 12,200 1,151,079 December 37,180 1,608,315 Totals: 254,694 15.711,491 29 of 42

Table 14 Haddam Neck 2004 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream

1. Type of Waste

a. Waste Stream: Resins, Filters, and Evap Bottoms SFP HDLF WDB Sludge/Water Waste Volume Curies %Error Class MA3 Shipped (Ci)

A 7.13E+00 1.30E+00 +/-25%

B 5.32E-01 2.711E+00 +/-25%

C 6.98E+00 6.98E+00 +/-25%

All 1.46E+01 1.10E+01 +/-25%

b. Waste Stream : Dry Active Waste Dry Active Waste 20' DAW in Intermodal DAW in B-25 Dry Active Waste 40 DAW in 20' High Top FP/TRU in 20' S/L Barge Spoils Soil DAW Super Sack FP/TRU in B-25 Waste Volume Curies %Error Class MA3 Shipped (Ci)

A 2.87E+04 7.91E+01 +/-25%

B 5.32E-01 5.42E+00 +/-25%

C 6.00E-01 9.18E-01 +/-25%

All 2.87E+04 8.54E+01 +/-25%

30 of 42

Table 14 (continued)

c. Waste Stream : Irradiated Components NST IN-SITU NST Wide Mouth 195 Waste Volume Curies % Error Class MA3 Shipped (Ci)

A 4.78E+02 2.29E+02 +/-25%

B O.OOE+OO O.OOE+OO -

C O.OOE+OO O.OOE+OO I All 4.78E+02 2.29E+02 +/-25%

d. Waste Stream : Other Waste Combined Packages Demolition Rubble Waste Volume Curies % Error Class MA3 Shipped (Ci)

A 5.41E+03 3.3513-01 +/-25%

B 1.2813+01 6.42E+00 +/-25%

C 4.10E+00 4.1513+01 +/-25%

All 5.43E+03 4.83E+01 +/-25%

e. Waste Stream : Sum of all 4 Waste Streams Waste Volume Curies % Error Class MA3 Shipped (Ci)

A 3.A6E+04 3.IOE+02 +/-25%

B 1.3913+01 1.45E+01 +/-25%

C 1.17E+01 4.94E+01 +/-25%

All 3.46E+04 3.74E+02 +/-25%

31 of 42

Table 14 (continued)

2. Estimate of Major Nuclide Composition (by waste stream)

Composition In % for each waste stream Total Nuclide a. b. c. d. e. Curies H-3 0.865% 0.136% 0.000% 0.862% 0.168% 6.28E-0I C-14 0.911% 0.668% 0.004% 0.012% 0.183% 6.85E-01 Cr-SI 0.000% 0.000% 0.000% 0.107% 0.014% 5.18E-02 Mn-54 0.000% 7.562% 5.373% 0.293% 5.058% 1.89E+0O Fe-55 12.774% 16.705% 80.117% 14.315% 55.134% 2.06E+02 Fe-59 0.000% 0.000% 0.000% 0.089% 0.011% 4.29E-02 Co-S7 0.000% 0.000% 0.001% 0.000% 0.001% 2.64E-03 Co-58 0.000% 0.000% 0.000% 0.156% 0.020% 7.52E-02 Co-60 18.048% 30.756% 13.310% 27.433% 19.264% 7.20E+01 Ni-59 0.025% 0.398% 0.093% 0.067% 0.157% 5.88E-01 Ni-63 12.938% 22.520% 0.998% 7.952% 7.168% 2.68E+01 Zn-65 0.000% 0.000% 0.000% 0.333% 0.043% 1.61E-0I Sr-89 0.000% 0.000% 0.000% 0.009% 0.001% 4.69E-03 Sr-90 0.921% 0.551% 0.004% 0.124% 0.171% 6.40E-01 Nb-94 0.000% 0.020% 0.002% 0.000% 0.006% 2.13E-02 Zr-95 0.000% 0.000% 0.000% 0.007% 0.001% 3.32E-03 Tc-99 2.416% 0.156% 0.000% 0.000% 0.107% 3.99E-01 Ag-i lOnm 0.000% 0.000% 0.000% 0.166% 0.021% 8.OOE-02 Sb-124 0.002% 0.000% 0.000% 0.008% 0.001% 4.16E-03 1-129 0.048% 0.000% 0.000% 0.000% 0.001% 5.49E-03 Cs-134 0.158% 0.126% 0.000% 4.608% 0.629% 2.35E+00 Cs-137 45.715% 11.240% 0.008% 43.088% 9A89% 3.55E+01 Cc-141 0.000% 0.000% 0.000% 0.001% 0.000% 3.47E-04 Cc-144 1.050% 0.223% 0.026% 0.307% 0.137% 5.13E-01 Eu-154 0.030% 0.143% 0.000% 0.000% 0.034% 1.26E-01 Eu-155 0.001% 0.017% 0.000% 0.000% 0.004% 1.47E-02 Np-237 0.000% 0.003% 0.000% 0.000% 0.001% 2.51 E-03 Pu-238 0.149% 0.404% 0.003% 0.004% 0.099% 3.71E-01 Pu-239 0.032% 0.069% 0.001% 0.001% 0.017% 6.42E-02 Pu-240 0.032% 0.068% 0.001% 0.000% 0.017% 6.27E-02 Pu-241 3.618% 7.593% 0.056% 0.046% 1.882% 7.03E+00 Am-241 0.202% 0.4 87% 0.003% 0.006% 0.120% 4.48E-0I Cm-242 0.000% 0.000% 0.000% 0.000% 0.000% 1.75E-04 Cm-243 0.033% 0.078% 0.001% 0.003% 0.020% 7.34E-02 Cm-244 0.033% 0.075% 0.001% 0.003% 0.019% 7.07E-02 32 of 42

Table 14 (continued)

3. Solid Waste Disposition Mode of Carriers Destination No.

Transport Shipments Rail Ameritech Environmental / CSXT Alaron 16 Truck RACE Logistics, LLC Bamwell Waste Management Facility 13 RSB Logistics Envirocare of Utah, Inc. 325 Hittman Transport D.S.S.I. 1 Priority Transport Service RA.C.E. 840 R&R Trucking GTS Duratek, Inc. 139 Southern Pines Trucking Landstar Systems B. Irradiated Fuel Shipments (disposition)

NONE 33 of 42

Figure 1 Liquid Dose 2004 Haddam Neck 1.60E-01 4.50E-01 1.40E-01 1.20E-01 I

0,1.OOE-O1 I 8.OOE-02 3

3 I6.OOE-02 4.00E-02 2.00E-02 0.OOE+00 3- I 1 0.00E+00 Jan-04 Feb-04 Mar-04 Apr-04 May-04 Jun-04 Jul-04 Aug-04 Sep-04 Oct-04 Nov-04 Dec-04 Month

+---WBDose _UMax. Organ Dose

• WB YTD X Max. Organ YTD I 34 of 42

(-p1

Figure 2 FRAC Temporary Tank Activity Released 2004 Haddam Neck IOOE 04 L - -- - - - - - - - - - - - - - - - - - - -- -

1.OOE-08 Jan-04 Feb-04 Mar-04 Apr-04 May-04 Jun-04 Jul-04 Aug-04 Sep-04 Oct-04 Nov-04 Dec-04 Month

-H-3 A*Gross Alpha -Cs-134 -*-Fe-55 -- 0Am-241 I-Sr-90 -- Co Sb-125 - Cs-137l 35 of 42

.-c -

Figure 3 RCA Yard Drain H-3, Co-60, Sr-90 and Cs-137 Activity Released 2004 Haddam Neck 1.20E-04 -

1.OOE-04 --

3 8.00E-05 -

I e..

j 6.OOE-05 - -

4.00E-05 -_

2.00E-05 !

O.OOE+00 I Jan-04 Feb-04 Mar-04 Apr-04 May-04 Jun-04 Jul-04 Aug-04 Sep-04 Oct-04 Nov-04 Dec-04 Month l_--Co-60 ACs-137 --

_-Sr-90 -*-Mn-54 -+-Tritium 36 of 42 C09O-~

Figure 4 Noble Gas Kr-85 Effluent Dose 2004 Haddam Neck 4.00E 2.OOE+00 1.80E+00 3.50E - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1.60E+00 3.GO E-02 -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - -

I 1.40E+00 2.50E - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1.20E+00 s

, 2.00E 1.OOE+00 8.OOE-01 1.50E -02 - - - - - - - - - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - -

-- 6.OOE-01 I.OOE-02 I f - t

-- 4.OOE-01 2.OOE-01 O.OOE+00 O.OOE+00 Jan-04 Feb-04 Mar-04 Apr-04 May-04 Jun-04 Jul-04 Aug-04 Sep-04 Oct-04 Nov-04 Dec-04 Month U Gamma Air Dose + Beta Air Dose 37 of 42

Figure 5 Gaseous Effluent Maximum Organ Dose 2004 Haddam Neck 2.50E-O1 2.OOE-O1 1.50E-O1 I

I .OOE-O1 5.OOE-02 O.OOE+OO Jan-04 Feb-04 Mar-04 Apr-04 May-04 Jun-04 Jul-04 Aug-04 Sep-04 Oct-04 Nov-04 Dec-04 Month

--- Max Organ -- YTD 38 of 42 co

Figure 6 Miscellaneous Gaseous Pathway Activity 2004 (Cable Vault, Containment Alternate Access, Containment Foyer, Terry Turbine, etc) 1.OOE-06 9.OOE-07

-______ __- 8.OOE-07 IU I

---

- 6.OOE-07 I

---

- 5.OOE-07

1. 4 U

~0

'I ------ ------------ 4.OOE-07 i

_ _ _- 3.OOE-07 2.OOE-07 I- - 1.OOE-07 O.00E+00 - O.OOE+00 Jan-04 Feb-04 Mar-04 Apr-04 May-04 Jun-04 Jul-04 Aug-04 Sep-04 Oct-04 Nov-04 Dec-04 Month Co-60 -U-Cs-137 AEu-154 A-Sr-90 -X-Gr. Alpha 39 of 42 CO&

Figure 7 Spent Fuel Building Activity Released 2004 Haddam Neck I.OOE+02- 1.80E-06 1.60E-06 1.40E-06 I.GOE+0 1 - - - -- - -- - - - -- - - -- - - -- - -- - - -- - -- - - -- - -- - - _ - -- _________-_-

5.20E-06 1.OOE-06 '

6.OOE-07 L.OOE-0 ------------- ------------------------------ ---------------------

4.OOE-07 2.OOE-07 L.OOE O.OOE+00 Jan-04 Feb-04 Mar-04 Apr-04 May-04 Jun-04 Jul-04 Aug-04 Sep-04 Oct-04 Nov-04 Dec-04 Month l Tritium -- Kr-85 -U-Co-60 A Cs-137 -*-Gr. Alpha + Sr-90 40 of 42 CD1

, I

Figure 8 Spray Cooling Release Rates During 2004 System Operation (uCi/hr)

Haddam Neck 1.OOE+01 ---

NUU

) - -\ /700 1.00E+00 l 600 I I.OOE-01 500 i I AA - 400 I Is

. 300 I

ILGOE-02

-- 200 I.OOE-04 LG0E105

\'-loo100 I A v

0

-It 0E a .0 0 0 o0 0

,It cz zI Month

-- H-3 -U-Co-60 ACs-134 -- Cs-137 -*-Run Times I 41 of 42

Figure 9 Total Dose 2004 for 40 CFR Part 190 Haddam Neck

.1.200E-01 I .OOOE-01 8.OOOE-02 I 6.OOOE-02 4.OOOE-02 2.OOOE-02 O.OOOE+00 4 0 1

Month/Year I_-M ax Organ Dose 0 Total Body Dose 42 of 42 Ctp cqcI