CY-07-072, Annual Radioactive Effluent Release Report for the Period of January Through December 2006

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Annual Radioactive Effluent Release Report for the Period of January Through December 2006
ML071240193
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 04/26/2007
From: Gerard van Noordennen
Connecticut Yankee Atomic Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CY-07-072
Download: ML071240193 (29)
v • d • e


Text

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

  • EAST HAMPTON, CT 06424-3099 April 26, 2007 Docket No. 50-213 CY-07-072 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 2.6.2 of Appendix C of the Quality Assurance Program (QAP) 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 2006. 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).

If you have any questions regarding this submittal, please call me at (860) 267-3196.

Sincerely, Gerard P. van Noordennen Date Director of Nuclear Safety/Regulatory Affairs

Attachment:

Annual Radioactive Effluent Report cc: S. J. Collins, NRC Region I Administrator T. B. Smith, NRC Project Manager, Haddam Neck Plant R. Lorson, Chief, Decommissioning Branch, NRC Region Dr. E. L. Wilds, Jr., Director, CT DEP Radiation Division E. Waterman, US EPA, Region 1

HADDAM NECK PLANT CONNECTICUT YANKEE ATOMIC POWER COMPANY Haddam, Connecticut ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January-December 2006 Docket No. 50-213 Prepared By:. Date -Al/~

Reviewed Date-//~/I/9k7

,Ec L'Darois (CHP) - '/ /

Approved BY: ,,e./ Date- y/z /?

Richard N. McGrath - Radiation Protection Manager

TABLE OF CONTENTS 1.0 Introduction 2.0 Summary 3.0 Supplemental Information 4.0 Related Information 4.1 Radiation Monitors Out of Service for Greater Than 30 Days 4.2 Radioactive Effluent Condition Reports 5.0 Summary of REMODCM Revisions in the Year 2006 1

LIST OF TABLES Table 1 First and Second Quarters, 2006 Gaseous Effluents -

Summation of all Releases Table 2 Third and Fourth Quarters, 2006 Gaseous Effluents -

Summation of all Releases Table 3 First and Second Quarters, 2006 Gaseous Effluents -

Elevated & Ground Releases Table 4 Third and Fourth Quarters, 2006 Gaseous Effluents -

Elevated & Ground Releases Table 5 January - December 2006 Gaseous Effluents - Ground Level Release Table 6 First and Second Quarters, 2006 Liquid Effluents -

Summation of all Releases Table 7 Third and Fourth Quarters, 2006 Liquid Effluents -

Summation of all Releases Table 8 First and Second Quarters, 2006 Liquid Effluents Table 9 Third and Fourth Quarters, 2006 Liquid Effluents Table 10 Maximum Off-site doses/dose commitments to Members of the Public From Liquid and Gaseous Effluents for 2006 (10CFR50, Appendix I)

Table 11 January 1 st - December 3 1 st 2006 Solid Waste and Irradiated Fuel Shipments Table 12 Radioactive Effluents Condition Reports 2

1,0 INTRODUCTION As required by the Connecticut Yankee Quality Assurance Program (QAP), this Annual Radioactive Effluent Release Report for the year 2006 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 Plant 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 2006. The radwaste system utilized filters and demineralizers to process radioactive liquid prior to controlled release to the environment. The RCA Yard Drain System which was categorized as a continuous release liquid pathway was removed in 2005. Therefore, all liquid releases in 2006 were batch releases. Non-radioactive or nominally contaminated ground water derived from construction related activities was treated to remove suspended solids and to adjust pH to meet non-radiological effluent release criteria. This water was also monitored for radiological contaminants through sample collection, compositing, and analysis.

Radionuclides detected above the Lower Limit of Detection (LLD) were included in the compilation of effluent releases presented in this 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 continue to be included in the gaseous effluent monitoring program until the second quarter of 2006 when decontamination of the spent fuel building for demolition was complete. The Alternate Containment Access, Alternate Containment, Containment Foyer, and Containment Tent are examples of miscellaneous pathways that were routinely monitored until the second quarter of 2006, after which decontamination of the containment for demolition was complete and demolition was in progress.

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2.0 Summary Tables 1 through 9 summarize the quantity of radioactive gaseous and liquid effluents, respectively, for each quarter of 2006. The gaseous release tables are a summation of all monitored release points in 2006 (i.e., Spent Fuel Building exhaust, CTMT Foyer, CTMT Lower Level Access, and CTMT Alternate Access Point). Due to the demolition of the Spent Fuel Building and Containment Structures in 2006, ventilation systems for these structures were only operable in the first two quarters of 2006. No gaseous effluents were generated in the 3rd and fourth quarters of 2006. Structures such as the Containment and Spent Fuel Building were decontaminated to levels below which radiological controls and environmental monitoring were not required during demolition.

The liquid release tables are a summation of continuous and batch releases from all monitored release points for 2006. Table 10 provides the quarterly and annual doses from liquids, particulate and gaseous effluents to the whole body and maximally exposed organ. Table 11 summarizes the waste that was shipped off-site for burial or disposal during the year 2006.

The radioactive effluent monitoring program for 2006 was conducted in accordance with QAP Appendix C, Section 2.5. The results of the monitoring program indicate that the Haddam Neck Plant was successful in maintaining radioactive effluent releases to the environment as low as reasonably achievable.

The effluent dose contributions for this report are significantly less than regulatory limits.

3.0 Supplemental Information 3.1 Regulatory Limits 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 is 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 (from 20.1 to 12

20.602), Table II, Column 2;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 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 dose contributions from radioactive effluents for the current calendar year in accordance with the methodology and parameters described in the REMODCM performed at least every 92 days. A determination of projected dose contributions from radioactive effluents in accordance with the methodology 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;
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 7 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 12

sources, confirming to 40 CFR Part 190.

3.2 Maximum Permissible Effluent Concentrations

a. Fission and activation gases Pre-1994 concentration values in 10 CFR Part 20, Appendix B (from 20.1 to 20.602), Table II, Column 1
b. lodines Pre-1994 concentration values in 10 CFR Part 20, Appendix B (from 20.1 to 20.602), Table II, Column 1
c. Particulates, (half lives>8 days) Pre-1994 concentration values in 10 CFR Part 20, Appendix B (from 20.1 to 20.602), Table II, Column 1
d. Liquid Effluents Pre-1994 concentration values in 10 CFR Part 20, Appendix B (from 20.1 to 20.602), Table II, Column 2

. Total noble gas concentration Pre-1994 concentration values in 10 CFR Part 20, Appendix B (from 20.1 to 120.602), Table II, Column 1 3.3 Average Energy - Not Applicable 3.4 Measurements and Approximations of Radioactivity

a. Fission and Activation Gases Continuous Discharge - The Fuel Building Exhaust Vent, samples are analyzed monthly. Alternate Containment Access, Alternate Containment, Containment Foyer, and Containment Tent are examples of miscellaneous pathways that were routinely monitored. Activity levels determined are assumed constant for the surveillance interval.

Batch Discharges - There were no batch releases via this pathway in 2006.

There are no gaseous effluent release pathways associated with ISFSI Operations.

b. Iodine's Iodine surveillance no longer applies due to the elapsed time since final plant shutdown from power operations.
c. Particulates 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 12

from gaseous effluents and the effluent flow rate were used to determine the total amount of activity released. Detected particulate activity is reported in Tables 1 through 4.

There are no gaseous effluent release paths associated with ISFSI operations.

d. Liquid Effluents Continuous Discharges The RCA Yard Drain was removed in 2005. There were no continuous liquid releases in 2006.

Batch Releases Each batch release was sampled and analyzed for tritium and gamma emitting radionuclides prior to release. Composite samples were analyzed monthly for gross alpha and quarterly for Fe-55 and Sr-90. There was no detectable Fe-55 in the liquid release samples in 2006. The results of the composite analyses from the previous month or quarter were used to estimate the quantities of these radionuclides in liquid effluent during the current month or quarter in which discharges were conducted.

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 Spent Fuel Pool was decontaminated and drained in 2006 using the Alternate Radioactive Water Processing System and batch releases from Temporary FRAC Tanks with 20,000 gallon capacity. In addition, construction activity derived ground water was collected and released using the Groundwater Treatment System which also used 20,000 gallon FRAC Tanks. Due to this the number and duration of liquid effluent batch releases increased significantly in 2006 in comparison to 2005.

Groundwater treatment system releases were also sampled and analyzed as described above.

There are no liquid effluent release paths associated with ISFSI operations.

e. Total Noble Gas Concentration Refer to Table 5. Spent Fuel was removed from the Spent Fuel Pool and placed in dry cask storage in 2005. The 2005 releases of Kr-85 were associated with dry cask storage process. Since this process was complete and the spent fuel had been removed to the ISFSI, there were no noble gas releases in 2006.

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3.5 Batch Releases

a. Liquids
1. Number of Batch Releases: 48
2. Total time period for batch releases: 45,950 minutes
3. Maximum time period for a batch release: 5,519 minutes
4. Average time period for batch releases: 957 minutes
5. Minimum time period for a batch release: 30 minutes
6. Average stream flow during periods of release of effluents into a flowing stream: 15,500
7. Maximum gross release concentration (uCi/ml): 1,.83E-3 of H-3
b. Gaseous
1. Number of batch releases: 0
2. Total time period for batch releases: Not Applicable
3. Maximum time period for a batch release: Not Applicable
4. Average time period for batch releases: Not Applicable
5. Minimum time period for batch release: Not Applicable
6. Maximum gross release rate (uCi/sec): Not Applicable 3.6 Unplanned Releases
a. Liquid - There were no unplanned releases in 2006
b. Gaseous - There were no unplanned releases in 2006 4.0 Related Information.

Sections 4.1.1 through 4.1.4 provide the status of reportable items per requirements of the ODCM.

4.1.1 Radioactive Effluent Monitoring Instrumentation Requirement: Radioactive effluent monitoring instrumentation channels are required to be operable in accordance with the ODCM.

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, the ODCM requires an explanation for the delay in correcting the inoperability in the next Annual Effluent Release Report.

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Response: No radioactive effluent monitoring instrumentation was out of service for more than 30 consecutive days during the reporting period when required to be operable by the Offsite Dose Calculation Manual.

4.1.2 Liquid Radwaste Treatment System Requirement: With radioactive liquid waste being discharged without treatment, with estimated doses in excess of the limits in ODCM, a report must be submitted to the Commission in the Annual Effluent Release Report for the period.

Response: The above requirements of ODCM were met during this period, and therefore, no report is required.

4.1.3 Gaseous Radwaste Treatment System Requirement: With radioactive gaseous waste being discharged without treatment with doses in excess of the limits in ODCM, a report must be submitted to the Commission in the Annual Effluent Release Report for the period.

Response: The above requirements of ODCM were met during this period, and therefore no report is required.

4.1.4 Lower Limit of Detection for Radiological Analysis Requirement: ODCM requires that when unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Annual Radioactive Effluent Release Report.

Response: All samples were counted in such a manner as to satisfy the specified a priori lower limits of detection.

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4.2 Radioactive Effluent Condition Reports Table 12 lists the condition reports generated during the year 2006 and actions taken to resolve the individual issues.

Condition report 06-0149 describes problems with 2005 liquid composite samples that were not re-analyzed for gross alpha. The samples were to be re-analyzed to ensure issues associated with an alpha source had not effected the reported 2005 results.

Although these samples were not reanalyzed, it is unlikely to have significantly affected the data reported in the 2005 effluent report.

Positive liquid alpha results were reported in the first and second quarter of 2006. As opposed to no positive results in 2005. The positive results in 2006 are attributable to the processing and discharge of Spent Fuel Pool water which had significantly higher alpha emitting radionuclide concentrations than previously released water at CY. The 2006 data shows that alpha radioactivity accounts for a small fraction of the dose from a liquid pathway as shown in the table below.

Alpha Total Total Alpha Total Body Body Organ Organ 2006 Ci mrem mrem mrem mrem Q1 1.40E-05 1.31 E-05 1.17E-01 1.37E-04 1.85E-01 Q2 1.03E-05 9.70E-06 1.34E-02 7.85E-05 2.04E-02 Therefore, if activity was released, it would not change the reported dose total in 2006. It is unlikely that the water released in 2005 had the alpha radionuclide concentration of the spent fuel pool water released in 2006.

5.0 Summary of REMODCM Revisions in the Year 2006 5.1 There were no changes to the REMODCM in 2006.

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TABLE 1 Connecticut Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters, 2006 Gaseous Effluents-Summation of All Releases

1. I otal Release SI N/L) I NIL) I.OUt+l
2. Average release rate for period uCi/sec N/D N/D FB.
3. Percent of regulatory limit lodines
1. Total Iodine-131

. _N/D %

Ci N/A*

l N/D N/A* 2.50E+1

2. Average release rate for period uCi/sec N/A* N /A*
3. Percent of regulator limit %______ NIA* NIA* ______

C. Particulates______________ _______________

1. Particulates with T-1/2 > 8 days Ci 9.42E-06 1.36E-06 2.50E+1
2. Average release rate for period uCi/sec 1.23E-06 1.74E-07
3. Percent of regulatory limit  % 6.95E-02 2.67E-05
4. Gross alpha radioactivity Ci 3.6E-07 N/D

~D. Tritiumn~

1. Total release Ci N/D* i N/D* 2.50E+1
2. Average release rate for period uCi/sec N/D* N/D*
3. Percent of regulatory limit  % N/D* N/D* _

N/D*= Not Detected N/A*= Not Applicable 12

TABLE 2 Connecticut Yankee Atomic Power Station Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2006 Gaseous Effluents-Summation of All Releases

2. Average release rate for period uCi/sec N/A
  • N/A*
3. Percent of regulatory limit _ %__ N/A* N/A*

~B. lodin~es~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1. Total Iodine-131 Ci N/A
  • N/A* 2.50E+1
2. Average release rate for period uCi/sec N/A* N/A*
3. Percent of regulatory limit  % N/A* N/A*

C. Particulates \~______________

1. Particulates with T-1/2 > 8 days Ci N/A
  • N/A* 2.50E+1
2. Average release rate for period uCi/sec N/A
  • N/A*
3. Percent of regulatory limit  % N/A
  • N/A*
4. Gross alpha radioactivity Ci N/A
  • N/A* _

D. Tritium_ _ _ _ _ _ _ __ _ _ _ _ _ _ _

1. Total release Ci N/A* N/A* 2.50E+1
2. Average release rate for period uCi/sec N/A
  • N/A*
3. Percent of regulatory limit  % N/A
  • N/A*

N/D*= Not Detected N/A*= Not Applicable 13

TABLE 3 Connecticut Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters, 2006 Gaseous Effluents-Elevated & Ground Releases Continuous Mode Batch Mode Nuclides Released Unit 1st 2no st 2 nd Quarter Quarter Quarter Quarter Krypton-85 Ci N/A* NHA* NIA* NIA*

Krypton-85m Ci N/A* N/A* N/A* N/A*

Krypton-87 Ci N/A* N/A* N/A* N/A*

Krypton-88 Ci N/A* N/A* N/A* N/A*

Xenon-133 Ci N/A* N/A* N/A* N/A*

Xenon-135 Ci N/A* N/A* N/A* N/A*

Xenon-135m Ci N/A* N/A* N/A* N/A*

Xenon-1 38 Ci N/A* N/A* N/A* N/A*

Unidentified Ci N/A* N/A* N/A* N/A*

Total for period Ci N/A* N/A* N/A* N/A*

2. odine- CA*

Iodine-I 31 Ci N/A* N/A* N/A* N/A*

Iodine-1 33 Ci N/A* N/A* N/A* N/A*

Iodine-i 35 Ci N/A* jN/A* NIA* NIA*

Total for period Ci N/A* N/A* N/A* N/A*

Strontium-89 Ci N/A* N/A* N/A* N/A*

Strontium-90 Ci 1.06E-06 8.60E-08 N/A* N/A*

Cesium-1 34 Ci N/A* N/A* N/A* N/A*

Cesium-1 37 Ci 1.25E-06 N/D* N/A* N/A*

Cobalt-60 Ci 6.75E-06 1.27E-06 N/A* N/A*

Barium-Lanthanum-140 Ci N/A* N/A* N/A* N/A*

Others-Plutonium-238 Ci N/A* N/A* N/A* N/A*

Curium-243,244 Ci N/A* N/A* N/A* N/A*

Uranium-234 Ci N/A* N/A* N/A* N/A*

Uranium-238 Ci N/A* N/A* N/A* N/A*

Thorium-232 Ci N/A* N/A* N/A* N/A*

Radium-226 Ci N/A* N/A* N/A* N/A*

Gross Alpha Ci 3.64E-07 N/D* N/A* N/A*

N/D*= Not Detected N/A*= Not Applicable 14

TABLE 4 Connecticut Yankee Atomic Power Station Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2006 Gaseous Effluents-Elevated & Ground Releases Continuous Mode Batch Mode Nuclides Released Unit 3rd 4th 3rd 4th Quarter Quarter Quarter Quarter 1.rFiss7on Ci CAR" Krypton-85 Ci N/A* N/A* N/A* N/A*

Krypton-85m Ci N/A* N/A* N/A* N/A*

Krypton-87 Ci N/A* N/A* N/A* N/A*

Krypton-88 Ci N/A* N/A* N/A* N/A*

Xenon-133 Ci N/A* N/A* N/A* N/A*

Xenon-1 35 Ci N/A* N/A* N/A* NiA*

Xenon-1 35m Ci N/A* N/A* N/A* N/A*

Xenon-I 38 Ci NIA* NIA* NJ]A* NIA*

Unidentified Ci N/A* N/A* N/A* N/A*

Total for period Ci NIA* N/A* NIA* NIA*

Iodine-I131 Ci NIA* NIA* NIA* NIA*

Iodine-133 Ci N/A* N/A* N/A* N/A*

Iodine-1 35 Ci N/A* N/A* N/A* N/A*

Total for period Ci N/A* N/A* N/A* N/A*

3. Pariclt'es Strontium-89 Ci N/A* N/A* N/A* N/A*

Strontium-90 Ci N/A* N/A* N/A* N/A*

Cesium-1 34 Ci N/A* N/A* N/A* N/A*

Cesium-1 37 Ci N/A* N/A* N/A* N/A*

Cobalt-60 Ci N/A* N/A* N/A* N/A*

Barium-Lanthanum-1 40 Ci N/A* N/A* N/A* N/A*

Others-Plutonium-238 Ci N/A* N/A* N/A* N/A*

Curium-243,244 Ci N/A* N/A* N/A* N/A*

Uranium-234 Ci N/A* N/A* N/A* N/A*

Uranium-238 Ci N/A* N/A* N/A* N/A*

Thorium-232 Ci N/A* N/A* N/A* N/A*

Radium-226 Ci N/A* N/A* N/A* N/A*

Gross Alpha Ci N/D* N/D* N/A* N/A*

N/D*= Not Detected N/A*= Not Applicable 15

TABLE 5 Connecticut Yankee Atomic Power Station Effluent and Waste Disposal Annual Report January-December 2006 Gaseous Effluents-Ground Level Release Plant; The Main Stack was demolished in 2004. Therefore, the gaseous / particulates released from the facility are considered as a ground level release.

ISFSI; There are no gaseous or particulate release pathways associated with ISFSI operations.

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TABLE 6 Connecticut Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters, 2006 Liquid Effluents-Summation of All Releases

1. Total Release (not Ci 1.90E-03 9.08E-04 2.50E+01 including tritium, gases,alpha)
2. Average diluted .uCi/ml 5.60E-08 8.16E-08 concentration during period
3. Percent of applicable limit  % 7.34E-01 8.84E-01 B. Tritium
1. Total Release Ci 3.86E+00 1.26E+00 2.50E+01
2. Average diluted .uCi/ml 1.13E-04 1.13E-04 concentration during period
3. Percent of applicable limit  % 3.78E+00 3.78E+00 C. Dissolved and Entrained Gases
1. Total Release Ci N/A* N/A* 2.50E+01
2. Average diluted .uCi/ml N/A* N/A*

concentration during period

3. Percent of applicable limit  % N/A* N/A*

D. Gross Alpha Radioactivity

1. Total release Ci 1.40E-05 1.03E-05 2.50E+01
2. Average diluted .uCi/ml 4.1OE-10 9.26E-10 concentration during period
3. Percent of applicable limit  % 1.03E-02 2.32E-02 E. Volume of Waste Liters 3.25E+06 4.73E+05 1.OOE+01 Released (prior to dilution)

F. Volume of Dilution Water Liters 3.08E+07 1.07E+07 1.OOE+01 Used During Period N/D*= Not Detected N/A*= Not Applicable 17

TABLE 7 Connecticut Yankee Atomic Power Station Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2006 Liquid Effluents-Summation of All Releases I A. Fission and Activation Products

1. Total Release (not including Ci 2.50E+01 tritium, gases, alpha) 4.75E-04 3.06E-06
2. Average diluted concentration .uCi/ml 2.54E-06 2.43E-08 during period
3. Percent of applicable limit  % 2.65E+01 9.28E-01 B. Tritium
1. Total Release Ci 6.82E-02 8.79E-04 2.50E+01
2. Average diluted concentration .uCi/ml 3.64E-04 6.98E-06 during period
3. Percent of applicable limit  % 1.21 E+01 2.33E-01 C. Dissolved and Entrained Gases
1. Total Release Ci N/A* N/A* 2.50E+01
2. Average diluted concentration .uCi/ml N/A* N/A*

during period

3. Percent of applicable limit  % N/A* N/A*

D. Gross Alpha Radioactivity

1. Total release Ci 0.OOE+00 0.OOE+00 2.50E+01
2. Average diluted concentration .uCi/ml 0.OOE+00 0.OOE+00 during period
3. Percent of applicable limit  % 0.OOE+00 0.OOE+00 E. Volume of Waste Released Liters 1.53E+05 1.26E+05 1.OOE+01 (prior to dilution)

F. Volume of Dilution Water Used Liters 8.81 E+05 8.59E+05 1.O0E+01 During Period N/D*= Not Detected N/A*= Not Applicable 18

TABLE 8 Connecticut Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters, 2006 Liquid Effluents

£~nntinunu~ Mode Batch Mode o ....

n in ... u. ... ... . ...... .

Nuclides Released Unit ISt 2nd Ist 2nd Quarter Quarter Quarter Quarter Strontium-89 Ci N/A* N/A N/D* N/D*

Strontium-90 Ci N/A* N/A 5.04E-05 2.OOE-05 Cesium-1 34 Ci N/A* N/A N/D* N/D*

Cesium-137 Ci N/A* N/A 1.19E-03 1.20E-04 Iodine-1 31 Ci N/A* N/A N/D* N/D*

Cobalt-58 Ci N/A* N/A N/D* N/D*

Cobalt-60 Ci N/A* N/A 6.65E-04 7.68E-04 Iron-55 Ci N/A* N/A N/D* N/D*

Zinc-65 Ci N/A* N/A N/D* N/D*

Manganese-54 Ci N/A* N/A N/D* N/D*

Chromium-51 Ci N/A* N/A N/D* N/D*

Zirconium-Niobium-95 Ci N/A* N/A N/D* N/D*

Molybdenum-99 Ci N/A* N/A N/D* N/D*

Technetium-99m Ci N/A* N/A N/D* N/D*

Barium-Lathanium-1 40 Ci N/A* N/A N/D* N/D*

Cerium-141 Ci N/A* N/A N/D* N/D*

Others- Iron-55 Ci N/A* N/A N/D N/D*

Antimony- 125 Ci N/A* N/A N/D* N/D*

Unidentified Ci N/A* N/A N/D* N/D*

Total for period (above) Ci N/A* N/A 1.90E-03 9.08E-04 Xenon-1 33 Ci N/A* N/A N/D* N/D*

Xenon-1 35 Ci N/A* N/A N/D* N/D*

N/D*= Not Detected N/A*= Not Applicable 19

TABLE 9 Connecticut Yankee Atomic Power Station Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2006 Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit 3rd 4th 3rd 4th Quarter Quarter Quarter Quarter Strontium-89 Ci N/A* N/A* N/D* N/D*

Strontium-90 Ci N/A* N/A* 7.97E-06 3.16E-07 Cesium-1 34 Ci N/A* N/A* N/D* N/D*

Cesium-137 Ci N/A* N/A* 4.12E-04 1.42E-06 Iodine-131 Ci N/A* N/A* N/D* N/D*

Cobalt-58 Ci N/A* N/A* N/D* N/D*

Cobalt-60 Ci N/A* N/A* 4.81 E-05 1.32E-06 Iron-59 Ci N/A* N/A* N/D* N/D*

Zinc-65 Ci N/A* N/A* N/D* N/D*

Manganese-54 Ci N/A* N/A* N/D* N/D*

Chromium-51 Ci N/A* N/A* N/D* N/D*

Zirconium-Niobium-95 Ci N/A* N/A* N/D* N/D*

Molybdenum-99 Ci N/A* N/A* N/D* N/D*

Technetium-99m Ci N/A* N/A* N/D* N/D*

Barium-Lathanium-140 Ci N/A* N/A* N/D* N/D*

Cerium-1 41 Ci N/A* N/A* N/D* N/D*

Others- Iron-55 Ci N/A* N/A* N/D N/D*

Antimony-125 Ci N/A* N/A* N/D* N/D*

Unidentified Ci N/A* N/A* N/D* N/D*

Total for period (above) Ci N/A* N/A* 4.68E-04 3.06E-06 Xenon-1 33 Ci N/A* N/A* N/D* N/D*

Xenon-1 35 Ci N/A* N/A* N/D* N/D*

N/D*= Not Detected N/A*= Not Applicable 20

TABLE 10 Connecticut Yankee Maximum Off-Site Doses/Dose Commitments to Members of the Public from Liquid and Gaseous Effluents for 2006 (10CFR50, Appendix I)

II Dose (mrem) 1 st 2nd 3rd 4th Source Quarter Quarter Quarter Quarter Year)

________________________KLiquidEffluents ____ ________

Total Body Dose 1.17E-01 1.34E-02 4.17E-02 1.52E-04 1.72E-01 Organ Dose** 1.85E-01 2.04E-02 6.53E-02 2.45E-04 2.71 E-01

_________ _______ Airborne lEffiutents,. _ _ _ _ _ _ _ __ _ _ _ _

Organ Dose (Tritium + Part.)** 6.81 E-02 1.71 E-03 N/A N/A 6.98E-02

/ K__Nobl~eGses--____

Beta Air (mrad) N/A N/A N/A N/A N/A Gamma Air (mrad) N/A N/A N/A N/A N/A

_ _ _ _ _ _ _ _ _ _ _ _ __I_ I_ I I_ _ I _ I _ _

    • Maximum of the following age groups and organs; Adult, Teen, Child, and Bone, GI-LLI, Kidney, Liver, Lung, Thyroid 21

TABLE 11 Connecticut Yankee Atomic Power Station Effluent and Waste Disposal Report January 1 st - December 3 1 st 2006 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel)

1. Type of Waste A. Spent Resins, Filter, Sludge, etc SFP Filters Legacy Sludge in 8-120 Waste Class Unit  % Error (Ci)

A m3 2.24E-01 +/- 25%

Ci 4.98E-02 m3 +/-25%

B 0.OOE+00 Ci 0.OOE+00 C m3 4.75E+00 +/- 25%

Ci 3.22E+00 m3 +/-25%

Total 4.97E+00 Ci 3.27E+00 B. Dry Active Waste DAW in Intermodal DAW in B-25 DAW in 55 gal drum FP/TRU in 20' S/L CTMT Conc in Inter NST pieces in Inter CTMT Exterior in Gondo Septic Sludge Boxes Insitu Liner DAW in 80 gal drum DAW in 35 gal drum DAW in 5 gal drum Waste Class Unit  % Error (Ci) m3 A 8.94E+04 +/- 25%

Ci 5.94E+01 3

B m 0.OOE+00 +/-25%

Ci 0.00E+00 C m3 1.06E+01 +/-25%

Ci 1.18E+01 m3 +/- 25%

Total 8.95E+04 Ci 7.12E+01 22

C. Irradiated Hardware None Waste Class Unit  % Error (Ci)

A O.OOE+00 +/-25%

Ci O.OOE+00 B m3 O.OOE+00 +/- 25%

Ci O.OOE+00 C m3 O.OOE+00 +/- 25%

Ci O.OOE+00 m3 Total 0.00E+00 +/- 25%

Ci O.OOE+00 D. Other Waste N/A Combine Packages Demolition Rubble In FP/TRU in Intermodal SFP Conc South RCA Soil Liquid Waste 15 gal po Waste Class Unit  % Error (Ci).

A m3 1.36E+03 +/- 25%

Ci 8.38E-01 B m3 3.62E+01 +/- 25%

Ci 7.74E-01 m3 +/-25%

C 3.41 E+00 Ci 5.38E+00 m3 +/-25%

Total 1.40E+03 Ci 6.99E+00 E. Sum of all 4 Categories Above Waste Class Unit  % Error (Ci)

A m3 9.08E+04 +/- 25%

Ci 6.03E+01 B m3 3.62E+01 +/- 25%

Ci 7.74E-01 m3 C 1.87E+01 +/- 25%

Ci 2.04E+01 m3 Total 9.09E+04 +/- 25%

Ci 8.15E+01 23

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

A. Spent Resins, Filter, Sludge, etc (Class A, B & C Combined)

Nuclide  % Abundance Curies H-3 0.129 4.20E-03 C-14 0.577 1.89E-02 Mn-54 0.001 2.25E-05 Fe-55 30.826 1.01 E+00 Co-60 39.995 1.31 E+00 Ni-59 1.919 6.27E-02 Ni-63 19.840 6.49E-01 Sr-89 0.000 1.30E-07 Sr-90 0.057 1.85E-03 Nb-94 0.033 1.07E-03 Tc-99 0.001 2.31 E-05 1-129 0.000 1.55E-05 Cs-1 34 0.215 7.03E-03 Cs-137 3.018 9.87E-02 Ce-144 0.756 2.47E-02 Eu-1 54 0.100 3.28E-03 Np-237 0.001 3.75E-05 Pu-238 0.234 7.64E-03 Pu-239 0.017 5.54E-04 Pu-240 0.017 5.54E-04 Pu-241 2.104 6.88E-02 Am-241 0.119 3.88E-03 Am-243 0.001 6.06E-04 Cm-242 0.000 6.78E-06 Cm-243 0.021 6.90E-04 Cm-244 0.021 6.89E-04 B. Dry Active Waste Nuclide  % Abundance Curies H-3 14.923 1.06E+01 C-14 4.836 3.44E+00 Mn-54 0.000 2.21 E-04 Fe-55 21.497 1.53E+01 Co-60 21.830 1.55E+01 Ni-59 0.039 2.79E-02 Ni-63 21.824 1.55E+01 Sr-90 0.260 1.85E-01 Nb-94 0.015 1.06E-02 Tc-99 0.088 6.25E-02 1-129 0.006 3.97E-03 Cs-1 34 0.344 2.45E-01 Cs-1 37 6.565 4.67E+00 Ce-1 44 0.637 4.54E-01 Eu-152 0.156 1.11 E-01 Eu-154 0.145 1.03E-01 Pu-238 0.243 1.73E-01 24

Nuclide  % Abundance Curies Pu-239 0.053 3.80E-02 Pu-240 0.047 3.33E-02 Pu-241 6.106 4.35E+00 Am-241 0.240 1.71 E-01 Cm-242 0.000 1.35E-04 Cm-243 0.078 5.56E-02 Cm-244 0.068 4. 83E-02 C. Irradiated Hardware None Shipped D. Other Waste Nuclide  % Abundance Curies H-3 0.325 2.27E-02 C-14 0.781 5.46E-02 Mn-54 0.005 3.84E-04 Fe-55 18.857 1.32E+00 Co-60 27.098 1.89E+00 Ni-59 0.196 1.37E-02 Ni-63 21.249 1.49E+00 Kr-85 0.000 9.98E-06 Sr-90 0.457 3.20E-02 Tc-99 0.224 1.57E-02 Cd-109 0.000 9.96E-06 1-129 0.004 3.06E-04 Cs-1 34 0.289 2.02E-02 Cs-1 37 27.969 1.95E+00 Ce-1 44 0.493 3.45E-02 Eu-154 0.514 3.59E-02 Ra-226 0.000 2.50E-07 U-238 0.010 7.21 E-04 Pu-238 0.060 4.22E-03 Pu-239 0.012 8.67E-04 Pu-240 0.012 8.58E-04 Pu-241 1.313 9.17E-02 Am-241 0.101 7.04E-03 Cm-242 0.000 3.14E-06 Cm-243 0.013 9.33E-04 Cm-244 0.015 1.07E-03

3. Solid Waste Disposition Number of Shipments Mode of Transportation(Truck/Rail) Destination 67 STUDSVIK Logistics, LLC ALARON Corporation 3 R&R Trucking Barnwell Waste Mgmt Facility 1 STUDSVIK Logistics, LLC Barnwell Waste Mgmt Facility 2 Hittman Transport Diversified Scientific Services, Inc 25

Number of Shipments Mode of Transportation(Truck/Rail) Destination 7 Hittman Transport Duratek, Inc. (BCO) 1 R&R Trucking Duratek, Inc. (BCO) 5 Hittman Transport Duratek, Inc. (GR) 1 R&R Trucking Duratek, Inc. (GR) 9 STUDSVIK Logistics, LLC Duratek, Inc. (GR) 38 Ameritech Environmental / CSXT Energy Solutions, LLC (Bulk) 93 Manafort Brothers, Inc. Energy Solutions, LLC (Bulk) 84 SRS trucking Energy Solutions, LLC (Bulk) 861 STUDSVIK Logistics, LLC Energy Solutions, LLC (Bulk) 1 STUDSVIK Logistics, LLC Energy Solutions, LLC (Containerized))

1756 STUDSVIK Logistics, LLC STUDSVIK Logistics, LLC B. Irradiated Fuel Shipments (Disposition): None Shipped C. Additional Requirements; Summation of all Shipment Types Waste Class Volume (M3) Curies Shipped  % Error (Ci)

A 9.08E+04 6.03E+01 +/- 25%

B 3.62E+01 7'74E-01 +/- 25%

C 1.87E+01 2.04E+01 +/- 25%

Total 9.09E+04 8.15E+01 +/-25%

26

Table 12 Radioactive Effluent Condition Reports

~Date Issue Description Date of Initial Corrective Actions Taken Final Corrective ActionsTaken

~Discovery The remaining 1 - 2 ml that was not 1. MDA on remaining sample Technician at GELContinmet Laboratories Fyerdropped the ompoitespilled scalculated wasretrained for Sr-90.on analyzedtechnician to be 5.18E-14 uCi/ml.

Containment Foyer 4tthquarer quarter composite 2/23/2006 Laboratory 2CoprdtRE DC after digestion, resulting in the a loss of most of sample, ~~~~carrying carrying2. small samples in baskets to Compared to REMODCM reuedLDo1.0-.

the sample. required LLD of 1.00E-1 1.

prevent recurrence. Requirements of ODCM were met.

1. Monitor was unplugged despite do not unplug tag on cord.

SFB building particulate effluent monitor 2. Could not be determine by whom or when.

found unplugged. Chemistry technician Plugged monitor in, made 3. Reviewed HP Environmental air found RI unplugged when arriving at the 5/2/2006 notifications. samples for fuel building for time monitor to perform the weekly particulate faesneR1smlrwsls filtr chnge ut.frame since R-1 sampler was last filter change out. checked.

4. All results less than MDA.
5. R-1 no longer in use at time of CR closure o FRAC tank was put on 1. Detector replaced recirculation through the ion 2. Detector well replaced exchanger. 3. Pre-event background levels R-22 Liquid Rad Monitor Alarm trip during o Chemistry sampled the FRAC tank returned.

discharge of L-25. Approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to verify the original analysis 4. Cause was contaminated into the discharge of L-25, around 1400 on 06-0107 results for gamma emitting detector well Friday April, 2005, R-22 Liquid Monitor isotopes.

alarmed and shut down the discharge. o Decision was made to polish L-25 through the ion exchanger until Saturday morning.

_o Chemistry sampled L-25 for 27

Table 12 Radioactive Effluent Condition Reports gamma emitting isotopes and pH.

o Gamma activity dropped significantly and a new permit was issued on the remaining 15,000 gallons.

o R-22 original background number was slightly higher than normal; Operations flushed R-22 line prior to restarting the discharge.

1. Technician responsible for saving Informed management. Initiated and counting samples had left Some analysis results for 2005 monthly Initiated investigation into the extent site.

liquid composite gross alphas could not be 5/24/2006 of this issue. Contacted vendor lab 2. Personnel currently on site 06-0149 located. Saved samples could not be to determine if they had any sample analyzing such samples were located.anlznsuhsmlswr in storage in the event the results coached and counseled on and/or sample could not be located. importance of environmental I__

Isamples.

28

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