CY-06-062, Annual Radioactive Effluent Release Report for 2005
| ML061280257 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 05/01/2006 |
| From: | Connecticut Yankee Atomic Power Co |
| To: | Document Control Desk, NRC/FSME |
| References | |
| CY-06-062 | |
| Download: ML061280257 (31) | |
Text
Docket No. 50-213 CY-06-062 Attachment 1 Annual Radioactive Effluent Release Report May 2006
HADDAM NECK PLANT CONNECTICUT YANKEE ATOMIC POWER COMPANY Haddam, Connecticut ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January-December 2005 Docket No. 50-213 LICENSE NUMBER DPR-61
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 2005 1
LIST OF TABLES Table 1 First and Second Quarters, 2005 Gaseous Effluents -
Summation of all Releases Table 2 Third and Fourth Quarters, 2005 Gaseous Effluents -
Summation of all Releases Table 3 First and Second Quarters, 2005 Gaseous Effluents -
Elevated & Ground Releases Table 4 Third and Fourth Quarters, 2005 Gaseous Effluents -
Elevated & Ground Releases Table 5 January - December 2005 Gaseous Effluents - Ground Level Release Table 6 First and Second Quarters, 2005 Liquid Effluents -
Summation of all Releases Table 7 Third and Fourth Quarters, 2005 Liquid Effluents -
Summation of all Releases Tab-le 8 First and Second Quarters, 2005 Liquid Effluents Table 9 Third and Fourth Quarters, 2005 Liquid Effluents Table 10 Maximum Off-site doses/dose commitments to Members of the Public From Liquid and Gaseous Effluents for 2005 (10CFR50, Appendix I)
Table 11 January 1 st - December 3 1 st 2005 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 2005 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 2005. 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 2005 were the External Containment Sump, Groundwater Processing System effluent and rainwater.
The transfer of nuclear fuel from the Spent Fuel Pool (SFP) to storage casks was completed in March 2005. The loaded storage casks were 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 concentration; were detected in the effluent of the Spent Fuel Building ventilation. The duration and quantity of noble gas (Kr-85) released was quantified and include 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 continue to be 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, Containment Foyer, and Tank Farm TeIt are examples of miscellaneous pathways that were routinely monitored.
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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 2005. The gaseous release tables are a summation of all monitored release points in 2005 (i.e., Spent Fuel Pool exhaust, CTMT Foyer, CTMT Lower Level Access, and CTMT Alternate Access Point). The liquid release tables are a summation of continuous and batch release from all monitored release points for 2005. 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 2005.
The radioactive effluent monitoring program for 2005 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 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 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; 4
- 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 l;
- 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 l; 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, confirming to 40 CFR Part 190.
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3.2 Maximum Permissible Effluent Concentrations a Fission and activation gases Pre-1994 concentration values in 1(0 CFR Part 20, Appendix B (from 20.1 to 20.602), Table II, Column 1
- b. lodines Pre-1994 concentration values in 11 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 1I)
CFR Part 20, Appendix B (from 20.1 to 20.602), Table II, Column 2 e Total noble gas concentration Pre-1994 concentration values in 1)
CFR Part 20, Appendix B (from 20.-1 to 20.602), Table II, Column 1 3.3 Average Energy - Not Applicable 3.4 Measurements and Approximations of Radioactivity
- a. Fission and Activation Gases During spent fuel transfer evolutions the noble gas effluent release was accounted for by integrating the Spent Fuel Exhaust Radiation Monitor chart recordings. The results for radioactivity from gaseous effluents and the effluent flow rate were used to determine the total amount of activity released.
Continuous Discharge - The Fuel Building Exhaust Vent samples are analyzed monthly. Activity levels determined are assumed constant for the surveillance interval.
Batch Discharges - There were no batch releases via this pathway in 2005.
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.
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- 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 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 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.
Batch Releases 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 effluent 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.
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There are no liquid effluent release paths associated with ISFSI operations.
- e. Total Noble Gas Concentration Refer to Table 5.
3.5 Batch Releases
- a. Liquids
- 1. Number of Batch Releases: 9
- 2. Total time period for batch releases: 2347 minutes
- 3. Maximum time period for a batch release: 405 minutes
- 4. Average time period for batch releases: 261 minutes
- 5. Minimum time period for a batch release: 46 minutes
- 6. Average stream flow during periods of release of effluents into a flowing stream: 15,500
- 7. Maximum gross release concentration (uCi/ml): 2.82E-3 (2.82E-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 2005
- b. Gaseous - There were no unplanned releases in 2005 4 Related Information Sections 4.1.1 through 4.1.4 provide the status of reportable items per requirements of the ODCM.
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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.
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 the 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 ir 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.
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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.
4.2 Radioactive Effluent Condition Reports Table 12 lists the condition reports generated during the year 2005 and actions taken to resolve the individual issues.
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5.0 Summary of REMODCM Revisions in the Year 2005 5.1 Revision number: Change #2005-01 Date: 3/29/05 Summary:
This change was performed to replace "Technical Specifications" with "QAP". The ODCM requirements have been relocated to the Quality Assurance Program. Additionally, the change removed all release pathways, instrumentation and associated analysis for release paths that no longer exists due to the transfer of fuel to long term storage, and the progress of the decommissioning (i.e., noble gas release path, spent fuel pool exhaust, rad-monitor R-22) and added some flexibility to the "point of discharge" for liquid releases to accommodate the decommissioning progress. An example of additional discharge points is the use of the next manhole or catch basin associated with Yard Drain 6 as the previous section is isolated to support decommissioning. Other changes either reduced or eliminated some of the REMP sampling locations that are no longer applicable due to the stage of the decommissioning (i.e., particulate, vegetation and milk).
5.2 Revision number: Change #2005-02 Date: 12/21/05 Summary:
Table E Changed items 2, 4, and 5 to an annual schedule and coordinated the sample collection period to be performed once bulk water of the spent fuel pool had been released. Additional changes replaced the "Unit Manager" with "Designated Manager" to be consistent with the QAP.
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TABLE 1 Connecticut Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters, 2005 Gaseous Effluents-Summation of All Releases
- Unit 1 1st 2n1 Est. Total V Quarter _Quarter Error, %
A. Fissiorn and Activation Gases
- 1. Total Release Ci 2.37E+1 N/A* 2.50E+ I
- 2. Average release rate for period uCi/sec 3.01 E+00 N/A*
- 3. Percent of regulatory limit % 3.1OE-1 N/A*
B. lodines _ -
- 1. Total lodine-131 Ci N/A* N/A* 2.50E+i
- 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 9.15E-6 2.27E-6 2.50E+I
- 2. Average release rate for period uCi/sec 1.19E-6 2.88E-7
- 3. Percent of regulatory limit % 3.56E-4 8.93E-5
- 4. Gross alpha radioactivity Ci 5.87E-8 N/D*
D. Tritium - -_ _ _ _ _
- 1. Total release Ci 3.76E-1 9.70E-2 2.50E+1
- 2. Average release rate for period uCi/sec 4.78E-2 1.23E-2
- 3. Percent of regulatory limit % 7.38E-3 1.90E-3 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, 2005 Gaseous Effluents-Summation of All Releases 1 Unit 3r l Est.Total l l Quarter l_Quarter Error, %
A. Fission and Activation Gases __
- 1. Total Release Ci J N/A* I N/A* 2.50E+I
- 2. Average release rate for period uCi/sec N/A* N/A*
I I
- 3. Percent of regulatory limit N/A* N/A*
B. lodines E - - -_-_.
- 1. Total lodine-131 Ci N/A
- N/A* 2.50E+ i
- 2. Average release rate for period uCi/sec N/A* N/A*
- 3. Percent of regulatory limit C. Particulates ; .
N/A*
N/A*
r ,r
- 1. Particulates with T-1/2 > 8 days Ci 1.09E-6 1.22E-6 2.50E+I
- 2. Average release rate for period uCi/sec 1.38E-7 1.55E-7
- 3. Percent of regulatory limit _ 7.79E-5 2.62E-5
- 4. Gross alpha radioactivity Ci N/D* NID*
D. Tritiuni _ : __::_i_.__;_L_-_
- 1. Total release Ci 7.84E-2 5.56E-2 2.50E+1
- 2. Average release rate for period uCi/sec 9.97E-3 7.07E-3
- 3. Percent of regulatory limit _ 1.54E-3 1.09E-3 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, 2005 Gaseous Effluents-Elevated & Ground Releases Continuous Mode Batch Mode Nuclides Released Unit l 2 s 2 Quarter Quarter Quarter Quarter
'1Fissoi~o[G=a-se,,s. --- Ci .. _- - - 0 ...... -E Krypton-85 Ci 2.37E+1 N/A* N/A* N/A*
Krypton-85m Ci N/A* N/A* N/A* N/A*
eryton-87 Ci N/A* N/A* N/A* N/A*
X -toI n-88 Ci N/A* N/A* N/A* N/A*
Xenion-133 Ci N/A* N/A* N/A* N/A*
Xenon-1 35 Ci N/A* N/A* N/A* N/A*
XUnien-1e35m Ci N/A* N/A* N/A* N/A*
Xerion-1 38 Ci N/A* N/A* N/A* N/A*
Unidentified Ci N/A* N/A* N/A* N/A*
Total for neriod Ci N/A* N/A* N/A* N/A*
lodine-131 Ci NIA* _ N/A* N/A* NIA*
lodine-133 Ci N/A* N/A* N/A* N/A*
lodi ne-135 Ci N/A* N/A* N/A* NiA*
Total for period Ci N/A* N/A* N/A* N/A*
~.Pticulafes -~:00_=-0 Strontium-89 Ci N/A* N/A* N/A* N/A*
Strontium-90 Ci 1.29E-6 5.82E-7 N/A* N/A*
Cesium-1 34 Ci N/A* N/A* N/A* N/A*
Cesium-137 Ci 1.54E-6 8.35E-7 N/A* N/A*
Cobalt-60 Ci 6.32E-6 8.54E-7 N/A* N/A*
Barium-Lanthanum-140 Ci N/A* N/A* N/A* N/A*
Others-Plutonium-238 Ci N/A* NIA* N/A* N/A*
Curium-243,244 Ci N/A* N/A* NIA* 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* NiA*
Radium-226 Ci N/A* N/A* N/A* N/A*
Gross Alpha Ci 5.87E-8 N/D* N/D* N/D*
N/DF= Not Detected N/AI= Not Applicable 14
TABLE 4 Connecticut Yankee Atomic Power Station Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2005 Gaseous Effluents-Elevated & Ground Releases Continuous Mode Batch Mode Nuclides Released Unit 3rd 4th 3rd 4th
_ Quarter Quarter Quarter Quarter i Fi E 7s10 ses 10 Ci N/A*
N/A*
= _ -___,___
N/A* N/A*
Krypton-85 Kypton-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-1 33 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-138 Ci N/A* N/A* N/A* N/A*
Unidentified Ci N/A* N/A* N/A* N/A*
Total for period Ci NIA* N/A* N/A* N/A*
lodine-131 Ci N/A* N/A* NIA* N/A*
lodine-133 Ci N/A* N/A* N/A* N/A*
lodine-135 Ci N/A* N/A* N/A* N/A*
Total for period Ci N/A* N/A* N/A* N/A*
Strc ntium-89 Ci N/A* N/A* N/A* NIA*
Strcntium-90 Ci 5.86E-7 1.23E-7 N/A* N/A*
Cesium-1 34 Ci N/A* N/A* N/A* N/A*
Cesium-1 37 Ci 2.89E-7 5.43E-7 N/A* N/A*
Cobalt-60 Ci 2.20E-7 5.50E-7 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 NIA* N/A* N/A* N/A*
Uranium-234 Ci N/A* N/A* N/A* N/A*
Urarnium-238 Ci N/A* N/A* N/A* N/A*
Thorium-232 Ci N/A* N/A* N/A* N/A*
Raclium-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 2005 Gaseous Effluents-Ground Level Release Plant; Connecticut Yankee processed several Transportable Storage Canisters in the first quarter of 2005, which contained spent fuel element assemblies. The processing of these canisters resulted in 23.7 Curies of Krypton-85 being released to the environment. This activity was released through the Spent Fuel Pool Exhaust.
The Main Stack was demolished in 2004. Therefore, the gaseous / particulates released from the facility are considered as a ground level release.
ISFS I; 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, 2005 Liquid Effluents-Summation of All Releases Unit 1 St 1 2n i 7 Est. Total l Quarter Quarter Error, %
A. Fission and Activation Products 1.Total Release (not including tritium, Ci 2.50E+1 gases,alpha) 9.42E-4 4.28E-4
- 2. Average diluted concentration during .uCi/ml 1.90E-6 perio _________ 9.72E-7
- 3. Percent of applicable limit °/0 9.21E-2 3.85E-2 B. Tritium 1.Total Release Ci 1.63E-1 1.34E-1 2.50E+'I
- 2. Average diluted concentration during .uCi/ml 5.75E-5 3.72E-5 period
- 3. Percent of applicable limit _ 1.91E-2 1.24E-2 C. Dissolved and Entrained Gases 1.Total Release Ci N/A* NIA* 2.50 E+1
- 2. Average diluted concentration during .uCi/ml N/A* N/A*
period
- 3. Percent of applicable limit _ _ N/A* NIA*
D. Gross Alpha Radioactivity 1.Total release Ci N/D N/D 2.50E+ I
- 2. Average diluted concentration during .uCi/ml N/A* N/A period E. Volume of Waste Released (prior Liters 1.58E+7 1.99E+7 to dilution) 1.OE+1 F. Volume of Dilution Water Used Liters N/A N/A During Period 1.OE+l 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, 2005 Liquid Effluents-Summation of All Releases
. Unit 1 3rd 4th Est.:Total
-_:_.. Quarter jQuarter Error, %
A. Fission and Activation Products
- 1. Total Release (not including tritium, Ci 1.69E-4 1.12E-4 N/A gases,alpha)
- 2. Average diluted concentration during .uCi/ml 1.75E-6 4.19E-7 period
- 3. Percent of applicable limit _ 3.39E-2 5.17E-2 B. Tritium
- 1. Total Release Ci 2.91 E-2 2.76E-2 N/A
- 2. Average diluted concentration during .uCi/ml 4.09E-5 2.90E-4 period
- 3. Percent of applicable limit %jI 1.36E-2 9.66E-2 I C. Dissolved and Entrained Gases
- 1. Total Release Ci N/A N/A l N/A
- 2. Average diluted concentration during .uCi/ml N/A N/A period
- 3. Percent of applicable limit J N/A N/A D. Gross Alpha Radioactivity
- 1. Total release Ci N/D N/D N/A
- 2. Average diluted concentration during .uCi/ml N/A N/A period E. Volume of Waste Released (prior Liters 3.95E+6 5.46E+6 N/A to dilution)
F. Volume of Dilution Water Used Liters N/A N/A N/A During Period N/D*= Not Detected N/Ak= Not Applicable 18
TABLE 8 Connecticut Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters, 2005 Liquid Effluents Conninunusq Mnda Batc-h ModA Nuclides Released Unit 12 2 Quarter Quarter Quarter Quarter Strontium-89 Ci N/A* N/D* N/D* N/D*
Strontium-90 Ci 3.66E-5 5.71 E-5 3.19E-5 N/D*
Cesium-1 34 Ci N/A* N/D* N/D* N/D*
Cesium-137 Ci 5.05E-4 1.46E-4 1.27E-4 1.13E-5 lodine-131 Ci N/A* N/D* N/D* N/D*
Cobalt-58 Ci N/A* N/D* N/D* N/D*
Cobalt-60 Ci 7.23E-6 5.95E-6 9.83E-5 2.63E-5 Iron-55 Ci N/A* N/D* 1.36E-4 1.81 E-4 Zinc-65 Ci N/A* N/D* N/D* N/D*
Manganese-54 Ci N/A* N/D* N/D* N/D*
Chromium-51 Ci N/A* N/D* N/D* N/D*
Zirconium-Niobium-95 Ci N/A* N/D* N/D* N/D*
Molybdenum-99 Ci N/A* N/D* N/D* NID*
Technetium-99m Ci N/A* N/D* N/D* N/D*
Barium-Lathanium-140 Ci N/A* N/D* N/D* N/D*
Cerium-141 Ci N/A* N/D* N/D* N/D*
Others- Iron-55 Ci N/A* N/D* N/D N/D*
Antimony-1 25 Ci N/A* N/D* N/D* N/D*
Unidentified Ci N/A* N/D* N/D* N/D*
Total for period (above) Ci 5.49E-4 2.09E-4 3.93E-4 2.19E-4 Xenon-1 33 Ci N/A* N/D* N/D* N/D*
Xenon-1 35 Ci N/A* N/D* 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, 2005 Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit 3rd 4th 3rd 4th Quarter Quarter Quarter Quarter Strcntium-89 Ci N/A* N/A* N/A* N/A*
Strcntium-90 Ci 1.07E-5 1.36E-5 N/A* 8.93E-6 Cesium-134 Ci N/A* N/A* N/A* N/A*
Cesium-137 Ci 3.97E-5 5.74E-5 7.84E-6 3.95E-6 lodine-131 Ci N/A* N/A* N/A* N/A*
Cobalt-58 Ci N/A* N/A* N/A* N/A*
Cobalt-60 Ci N/A* N/A* N/A* 4.83E-6 Iron-59 Ci N/A* N/A* 1.11E-4 2.32E-5 Zinc-65 Ci N/A* N/A* N/A* N/A*
Manganese-54 Ci N/A* N/A* N/A* N/A*
Chromium-51 Ci N/A* N/A* N/A* N/A*
Zirconium-Niobium-95 Ci N/A* N/A* N/A* N/A*
Molybdenum-99 Ci N/A* N/A* N/A* N/A*
Technetium-99m Ci N/A* N/A* N/A* N/A*
Barium-Lathanium-140 Ci N/A* N/A* N/A* N/A*
Cerium-141 Ci N/A* N/A* N/A* N/A*
Others- Iron-55 Ci N/A* N/A* N/A* N/A*
Antimony-1 25 Ci N/A* NIA* N/A* N/A*
Unidentified Ci N/A* N/A* N/A* NIA*
Total for period (above) Ci 5.04E-5 7.1OE-5 1.19E-4 4.09E-5 Xenon-133 Ci N/A* N/A* NIA* N/A*
Xenon-135 Ci N/A* N/A* N/A* N/A*
N/[)*= Not Detected N/IA*= Not Applicable 20
TABLE 10 Connecticut Yankee Maximum Off-Site Doses/Dose Commitments to Members of the Public from Liquid and Gaseous Effluents for 2005 (10CFR50, Appendix I)
Dose (mrem) 1st 2nd 3rd 4th 1 Source Quarter Quarter Quarter Quarter J Year)
__ Liquid Effluents Total Body Dose 6.44E-2 1.77E-2 5.04E-3 6.89E-3 9.40EE-2 Organ Dose** 1.02E-1 3.09E-2 8.27E-3 1.54E-1 1.54E:-1
__ Airborne Effluents Organ Dose (Tritium + 5.11 E-2 1.47E-2 1.26E-2 5.89E-3 8.43E>-2 PArt.)**
__=_ Noble Gases =
Beta Air (mrad) 4.29E-1 N/A N/A N/A 4.29EE-1 Gamma Air (mrad) 3.78E-3 N/A N/A N/A 3.78EE-3
- Maximum of the following organs; Bone, GI-LLI, Kidney, Liver, Lung, Thyroid 21
TABLE 11 Connecticut Yankee Atomic Power Station Effluent and Waste Disposal Report January 1 5t- December 31 st 2005 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 HDLF WDB Sludge/Water Waste Class Unit % Error (Ci)
A m3 0.00E+00 +I- 25%
Ci 0.OOE+00 B m3 5.OOE+00 +/- 25%
Ci 1.85E+01 C m3 1.14E+01 +/- 25%
Ci 4.14E+01 Total m3 6.14E+01 +/- 25%
Ci 5.99E+01 B. Dry Active Waste Dry Active Waste 20" DAW in Intermodal DAW in B-25 Dry Active Waste 4 DAW in 20' High Top FP/TRU in 20' S/L Barge Spoils Soil DAW Super Sack FP/TRU in B-25 Waste Class Unit % Error (Ci)
A m3 5.62E+04 +/- 25%
Ci 4.79E+01 B m3 0.OOE+00 +/- 25%
Ci 0.OOE+00 C m3 6.82E+00 +/- 25%
Ci 6.33E+00 Total m3 5.63E+04 +/-25%
Ci 5.43E+01 22
C. Irradiated Hardware NST IN-SITU NST Wide Mouth 195 Waste Class Unit % Error (Ci)
A m3 1.23E+02 +I- 25%
Ci 2.59E+01 B m3 O.OOE+00 +I- 25%
Ci O.OOE+00 C m3 4.13E-01 +/-25%
Ci 9.78E+01 Total m3 1.24E+02 +I- 25%
Ci 1.24E+02 D. Other Waste Combined Packages Demolition Rubble Waste Class Unit % Error (Ci)
A mn3 2.55E+04 +/- 25%
Ci 1.79E+01 B m3 3.73E+01 +I- 25%
Ci 1.79E+01 C m3 1.41 E+01 +I- 25%
Ci 6.99E+01 Total m3 2.55E+04 +/-25%
Ci 1.06E+02 E. Sum of all 4 Categories Above Waste Class Unit % Error (Ci)
A m3 8.18E+04 +/- 25%
Ci 9.17E+01 B m3 4.23E+01 +/- 25%
3.64E+01 Ci C 3.27E+01 +/- 25%
Ci 2.15E+02 Total m3 8.19E+04 +/-25%
Ci 3.44E+02 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 0.748 4.49E-01 C-14 0.451 2.71 E-01 Fe-55 4.705 2.82E--00 Co-57 0.010 6.02E-03 CO-60 16.493 9.89E--00 Ni-59 0.097 5.81 E-02 Ni-63 14.661 8.79E-400 Sr-90 0.706 4.23E-01 Cs-1 34 0.676 4.05E-01 Cs-I 37 59.740 3.58E+01 Ce-144 0.356 2.14E-01 Eu-I 54 0.014 8.34E-03 Np-237 0.000 1.15E-04 Pu-238 0.054 3.23E-02 Pu-239 0.011 6.39E-03 Pu-240 0.011 6.39E-03 Pu-241 1.115 6.69E-01 Am-241 0.112 6.71 E-02 Am-243 0.001 6.06E-04 Cm-242 0.000 2.21 E-04 Cm-243 0.019 1.16E-02 Cm-244 0.019 1.16E-02 B. Dry Active Waste Nuclide % Abundance Curies H-3 6.398 3.47E+00 C-14 4.227 2.29E+00 Mn-54 0.000 7.92E-05 Fe-55 13.864 7.52E+00 Co-60 16.358 8.88E+00 Ni-59 0.111 6.01 E-02 Ni-63 21.885 1.19E+01 Sr-89 0.000 1.52E-04 Sr-90 2.398 1.30E+00 Nb-94 0.000 2.59E-04 Tc-99 10.182 5.53E+00 1-129 0.204 1.11E-01 Cs-1 34 0.760 4.13E-01 Cs-137 13.797 7.49E+00 Ce-144 1.545 8.39E-01 Eu-I 52 0.055 2.97E-02 Eu-1 54 0.091 4.93E-02 U-233 0.001 3.82E-04 U-234 0.001 3.82E-4 U-238 0.001 7.27E-04 Np-237 0.000 2.13E-05 24
Pu-238 0.269 1.46E-01 Pu-239 0.067 3.64E-02 Pu-240 0.063 3.42E-02 Pu-241 7.313 3.97E+00 Am-241 0.291 1.58E-01 Cm-242 0.000 1.18E-04 Cm-243 0.055 2.99E-02 Cm-244 0.048 2.58E-02 C. Irradiated Hardware Nuclide % Abundance Curies H-3 0.003 3.1,6E-03 C-14 0.003 4.09E-03 Mn-54 0.003 3.1 2E-03 Fe-55 32.641 4.04E+01 CO-60 48.051 5.94E+01 Ni-59 0.126 1.55E-01 Ni-63 16.787 2.03E+01 Sr-90 0.001 1.27E-03 Nb-94 0.000 4.56E-04 Tc-99 0.000 9.82E-05 Ag-108m 2.371 2.93E+00 1-129 0.000 2.34E-04 Cs-137 0.003 3.61 E-03 Ce-144 0.008 9.5OE-03 Pu-238 0.000 1.17E-04 Pu-239 0.000 2.82E-05 Pu-240 0.000 2.8 3E-05 Pu-241 0.004 4.58E-03 Am-241 0.000 1.91 E-04 Cm-243 0.000 1.'2E-05 Cm-244 0.000 1.U2E-05 D. Other Waste Nuclide % Abundance Curies H-3 1.551 1.08E+00 C-14 0.145 1.01E-01 Cl-36 0.000 1.00E-07 Mn-54 0.000 1.31 E-04 Fe-55 5.453 3.81 E+00 Co-60 7.267 5.07E+00 Ni-59 0.199 1.39E-01 Ni-63 6.425 4.49E+00 Zn-65 0.000 1.69E-06 Kr-85 0.003 2.37E-03 Sr-89 0.000 1.12E-06 Sr-90 0.247 1.73E-01 Nb-94 0.002 1.32E-03 25
Tc-99 0.032 2.24E-02 1-129 0.001 4.70E-04 Cs-134 0.052 3.(S2E-02 Cs-1 37 77.875 5.44E+01 Ba-133 0.000 7.98E-07 Ce-144 0.213 1.49E-01 Eu-154 0.080 5.!;8E-02 Eu-155 0.000 3.98E-06 Po-210 0.000 4.131 E-07 Np-237 0.000 2.f37E-05 Pu-238 0.020 1.43E-02 Pu-239 0.004 2..47E-03 Pu-240 0.004 2.87E-03 Pu-241 0.405 2.83E-01 Am-241 0.032 2.21 E-02 Cm-242 0.000 1.48E-05 Cm-243 0.005 3.76E-03 Cm-244 0.006 4.13E-03
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation(Truck/Rail) Destination 26 Ameritech Environmental / CSXT ALARON Corporation 318 RACE Logistics, LLC ALARON Corporation 3 Hittman Transport Barnwell Waste Mgml: Facility 2 R&R Trucking Barnwell Waste Mgml: Facility 1 Hittman Transport Diversified Scientific 'Services 3 Hittman Transport Duratek, Inc. (BCO) 377 Hittman Transport Duratek, Inc. (GR) 15 Interstate Freight Duratek, Inc. (GR) 6 R&R Trucking Duratek, Inc. (GR) 396 RACE Logistics, LLC Duratek, Inc. (GR) 3 RSB Logistics Duratek, Inc. (GR) 51 Southern Freight Duratek, Inc. (GR) 161 Ameritech Environmental / CSXT Energy Solutions (Bulk) 125 RACE Logistics, LLC Energy Solutions (Bulk) 1 RSB Logistics Energy Solutions (Containerized) 54 Ameritech Environmental / CSXT RACE, LLC 1206 RACE Logistics, LLC RACE, LLC 1 R&R Trucking Toxco Material Mgml. Center 1 RACE Logistics, LLC Toxco Material MgmI. Center B. Irradiated Fuel Shipments (Disposition): None Shipped C. Additional Requirements; Summation of all Shipment Types Waste Class 3 Volume (m ) Curies Shipped %/.Error (Ci)
A 8.18E+04 9.17E+01 +/- 25%
B 4.23E+01 3.64E+01 +/- 25%
C 3.27E+01 2.15E+02 +/- 25%
Total 8.19E+04 3.44E+02 +/- 25%
26
Table 12 Radioactive Effluent Condition Reports Condition Ies,,m nDrinfinn Date of InitioI Crrnr-tint Artionn Tnknn Finni Corronmtivp Arntinnc Thkpn Report# Discovery ......
Contacted the DEMCO foreman and the electricians. After the breaker 1. Attached identification tags on the was reset and the air sampler was ends of the extension cord to still not on, the extension cord was prevent inadvertent de-HP environmental air sampler found off found unplugged inside the air lock energizing.
05-0013 (unplugged). 1/4/2005 roll up door. The air sampler was plugged back in, restarted and the 2. Evaluated and bounded the air sampler filter was changed out. potential release of radioactive Notified HP supervision. The air material.
sampler filter was dropped off at the HP count room for analysis.
Radioactive liquid was observed being 1. Unclogged the drain line released via an unmonitored pathway.
Since the water did not go to the YD-6, it Notified Management. CR CLOSED 05-0417 was not being monitored in accordance with 5/6/2005 TO CR05-0416 per MRT 5-9-05.
the REMODCM. The approved pathway is to YD-6 (CB-1 1) and not the ground outside GS-7.
- 1. Evaluation of activities 05-0442 Environmental Monitoring of HEPA Exhaust 5/16/2005 Started the environmental air determined that no release of sampler. Notified HP Supervision. radioactive material occurred.
- 1. Communicated to the craft through thee supervisors' safety Dug the RASP pump out from under meeting to contact Health a pile of hoses, checked power, Physics prior to moving sampling 05-0573 HP/Chemistry Environmental Air Sampling 7/27/2005 found another power cord, changed equipment.
out the air sampler filter and restarted the air sampler. HP 2. Evaluated activities and Supervision was notified. determined that no release ot radioactive material had
._ _ _ occurred.
27
Table 12 Radioactive Effluent Condition Reports
- 1. Re-powered R-1 from a more secure power supply.
CR05-0613: R-1 vent stack monitor- Ran another extension from an 2. Electrical safety was discussed 05-0613 sampling pump found de-energized 8/15/2005 existing power cord to sampler pump at the supervisors safety and re-energized pump. meeting for communication to the craft.
- 3. Evaluated effluents for potential release of radioactive material.
- 1. The fan, which shorted the breaker due to rainwater and called attention to the loss of Attempted to restart air sampler. power to the air sampler, was Informed oncoming shift of issue so taken out of service.
05-0614 CR05-0614: Environmental air sampler 8/15/2005 that remedial actions could be 2. Power was restored to the air performed which would allow sampler.
Chemistry to restart the environmental air sample 3. Electrical safety and the care of electrical equipment exposed to the elements were discussed at the supervisors' safety meeting
_ _ _ __ _ ___ _for communication to the craft.
28
Docket No. 50-213 CY-06-062 Attachment 2 Revision 18 to Radiological Effluent Monitoring and Offsite Dose Calculation Manual, and List of Changes May 2006