ML061230651

Annual Radioactive Effluent Release Report January-December 2005

ML061230651
Person / Time
Site:	Maine Yankee
Issue date:	12/31/2005
From:	Maine Yankee Atomic Power Co
To:	Document Control Desk, NRC/FSME
References
Download: ML061230651 (21)

Text

MAINE YANKEE ATOMIC POWER COMPANY ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January-December 2005

1.0 INTRODUCTION

Tables I and 2 summarizes the quantity of radioactive gaseous and liquid effluents, respectively, for each quarter of 2005. Table 3 states that waste was shipped off-site for burial or disposal during the year 2005. Table 4 contains supplementary information.

Appendices A through D, indicate the status of reportable items per the requirements of the Off-site Dose Calculation Manual (ODCM) sections 2.1.5, 2.2.6, 2.3.3, 2.3.4. 2.5 and Appendix C.

Changes to the ODCM made during the year 2005 are summarized in Appendix E. A complete copy of the revised manual is attached as well as the specific pages that changed.

I

TABLE IA Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters, 2005 Gaseous Effluents-Summation of All Releases I Unit Ist 2nd Est. Total Quarter Quarter Error, %

A. Fission and Activation Gases

1. Total Release Ci N/A* N/A* 2.50E+1

2. Average release rate for uCi/sec N/A* NWA*

period

3. Percent of regulatory limit  % NIA* N/A*

B. lodines

1. Total Iodine-131 Ci N/A* NIA* 2.50E+1

2. Average release rate for uCi/sec N/A* N/A*

period _

3. Percent of regulatory limit _ N/AI NIA*

C. Particulates

1. Particulates with T-1/2 > 8 Ci NIA* N/A* 3.50E+1 days

2. Average release rate for uCi/sec N/A* N/A*

period_

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* NIA* 2.50E+1

2. Average release rate for uCi/sec N/A* N/A*

period

3. Percent of regulatory limit _ _ _NA* N/A*

N/D*= Not Detected NJA*= Not Applicable

• • = Calculated for the time period in which the releases actually occurred. All others are calculated for the standard 91day period (particulate release is an unscheduled release, which is reported in Table 4) 2

TABLE 1A Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2005 Gaseous Effluents-Summation of All Releases Unit J O3' 4'I Est. Total IQuarter Quarter Error, %

A. Fission and Activation Gases

1. Total Release Ci J N/A* I NJA* J2.50E+1

2. Average release rate for uCi/sec NIA* N/A*

period 1 4 +

3. Percent of regulatory limit NJA* N/A*

B. lodines

1. Total Iodine-131 Ci NWA* N/A* 2.50E+1

2. Average release rate for uCi/sec N/A* N/A*

period__ _ _ _ _ _ _ _ __ _ _

3. Percent of regulatory limit I_ _ IN/A* N/A*

C. Particulates I

1. Particulates with T-1/2 > 8 Ci N/A* N/A* 3.50E+1 days

2. Average release rate for uCi/sec NJA* NIA*

period

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* NJA* 2.50E+1

2. Average release rate for uCi/sec N/A* NJA*

period

3. Percent of regulatory limit  % N/A* NJA*

NID*= Not Detected N/A*= Not Applicable 3

TABLE I B Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters, 2005 Gaseous Effluents-Elevated Release Continuous Mode Batch Mode Nuclides Released l Unit l 1 l 2n t l 2nd I Quarter I Quarter J Quarter j Quarter

1. Fisslon Gases = _

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

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

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

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

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

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

Xenon-135m Ci N/A* NJA* 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;lflieF Ii- - __ _ _ __ _ _ __ _ _

iodine-1 31 Ci NIA*! N/A* N/A* N/A*

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

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

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

3. Particulates Strontium-89 Ci N/A* N/A* N/A* N/A*

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

Cesium-134 Ci NJA* N/A* N/A* N/A*

Cesium-137 Ci N/A* N/A* N/A* N/A*

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

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

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*

N/D*= Not Detected N/A*= Not Applicable 4

TABLE 1B Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2005 Gaseous Effluents-Elevated Release Continuous Mode Batch Mode Nuclides Released Unit l 3rd 4th 3rd 4th Quarter Quarter Quarter Quarter i s soGasesA -_ _ _ _ _ _ _ _ __ _ _ _ _ _ _

Krypton-85 Ci N/A* N/A* NIA* NiA*

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

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

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

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

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

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

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

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

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

2 I6. .. . .. _ ._. _ . . _ _ _ _ _ _ _ _ _ _

_odine-131 Ci NIA* NIA* I NIA* N/A*

_odine-133 Ci NJA* NIA* l N/A* N/A*

_odine-135 Ci N/A* N/A* l N/A* NIA*

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

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

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

Cesium-134 Ci N/A* N/A* NIA* N/A*

Cesium-137 Ci N/A* NIA* N/A* N/A*

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

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

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

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

Thonum-232 Ci N/A* N/A* N/A* N/A*

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

N/D*= Not Detected N/A*= Not Applicable 5

TABLE 1C Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report January-December 2005 Gaseous Effluents-Ground Level Release There were no gaseous effluent releases from Maine Yankee during the year 2005.

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TABLE 2A Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters, 2005 Liquid Effluents-Summation of All Releases I Unit I aSt 2na l Est. Total I l Quarter Quarter Error, %

A. Fission and Activation Products

1. Total Release (not including Ci 1.50E+1 tritium, gases,alpha) 1.15E-4 1.06E-5

2. Average diluted concentration .uCiml 8.5E8 5.5E dunn period _

3. Percent of applicable limit  % 8.3E-3 6.46E4 B. Tritium 1.Total Release Ci 2.44E-2 3.18E-2 1.50E+1

2. Average diluted concentration .uCi/ml 1.56E-6 1.99E-6 during period

3. Percent of applicable limit %_I 3.5E-3 3.43E-3 I C. Dissolved and Entrained Gases 1.Total Release Ci N/D* N/D* 1.50 E+1

2. Average diluted concentration .uCi/ml N/A* NJA*

during period

3. Percent of applicable limit _ INJA*_I N/A*

D. Gross Alpha Radioactivity 1.Total release Ci NID N/D 1.50E+1

2. Average diluted concentration .uCiml N/A* N/A during period E. Volume of Waste Released (prior Liters 7.OOE+6 9.27E+6 to dilution) 1.OE+1 F. Volume of Dilution Water Used Liters O.OOE+0 O.OOE+0 During Period 1.OE+I N/D*= Not Detected NIA*= Not Applicable 7

TABLE 2A Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2005 Liquid Effluents-Summation of All Releases I Unit 3rd 4th Est. Total Quarter Quarter Error, %

A. Fission and Activation Products 1.Total Release (not including Ci NIA N/A N/A tritium, gases,alpha)

2. Average diluted concentration .uCiml NIA NIA during period

3. Percent of applicable limit  % N/A NIA B. Tritium 1.Total Release Ci WA N/A N/A

2. Average diluted concentration .uCVml NIA N/A during period

3. Percent of applicable limit  % N/A N/A C. Dissolved and Entrained Gases 1.Total Release Ci NIA N/A N/A

2. Average diluted concentration .uCiml NIA N/A during period

3. Percent of applicable limit %JI N/A I N/A I D. Gross Alpha Radioactivity 1.Total release Ci N/A NIA N/A

2. Average diluted concentration .uCi/ml N/A N/A during period E. Volume of Waste Released (prior Liters N/A N/A N/A to dilution)

F. Volume of Dilution Water Used Liters N/A N/A N/A During Period II N/D*= Not Detected N/A*= Not Applicable TABLE 2B 8

Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters, 2005 Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit IlSt 2nds 2 Quarter Quarter Quarter Quarter Strontium-89 Ci N/A* N/D* N/D* N/D*

Strontium-90 Ci NIA* N/D* N/D* N/D*

Cesium-134 Ci N/A* N/D* N/D* NID*

Cesium-137 Ci N/A* N/D* 2.66E-5 3.67E-6 lodine-I 31 Ci N/A* N/D* N/D* N/D*

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

Cobaft-60 Ci NIA* N/D 8.82E-5 6.95E-6 Iron-59 Ci N/A* N/D* N/D* N/D*

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

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 NIA* N/D* N/D* N/D*

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

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

Unidentified Ci NJA* N/D* N/D* N/D*

Total for period (above) Ci N/A* N/D* 1.15EA I.06E-5 Xenon-133 Ci N/A* N/D* N/D* N/D*

Xenon-135 Ci NIA* N/D* N/D* N/D*

N/D*= Not Detected N/A*= Not Applicable TABLE 2B 9

Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2005 Liquid Effluents Confinuons Made Batch Mode Nuclides Released Unit 3rd 4th 3rd 4th Quarter Quarter Quarter Quarter Strontium-89 Ci NIA* N/A* N/A* NIA*

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

Cesium-134 Ci N/A* N/A* N/A* NIA*

Cesium-137 Ci NIA* NIA* N/A* N/A*

Iodine-131 Ci N/A* N/A* N/A* NIA*

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

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

Iron-59 Ci N/A* NIA* N/A* NIA*

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

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

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

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

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

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

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

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

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

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

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

Total for period (above) Ci N/A* NIA* NIA* NIA*

Xenon-1 33 Ci NIA* NIA* NIA* NIA*

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

N/D*= Not Detected N/A*= Not Applicable 10

TABLE 3 Maine Yankee Atomic Power Station Effluent and Waste Disposal Semiannual Report First Half. 2005 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel).

1. Type of Waste. Unit 6-Month Est. Total Error, Period

a. Spent resins, filter Cu. M. 0.0 sludges, etc. Ci. 0.0 +/-25

b. Dry compressible waste, Cu. M. 22900 contaminated equipment, DAW, Ci. 3.41 +/-25 cement.

c. Irradiated Hardware. Cu. M. 0.0 ci. 0.0 +/- 25

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

a. Co-60 0 0 Ni-63 0 0 Cs-137 0 0 Fe-55 0 0

b. Co-60 4.43% 1.51 E-1 Fe-55 0.87% 2.98E-2 Ni-63 8.63% 2.94E-1 Cs-1 37 85.21% 2.90E+00 Ce-144 0.16% 5.49E-3 Pu-241 .026% 9.01 E-4 C. Co-60 0 0 Fe-55 0 0 Ni-63 0 0

3. Solid Waste Disposition Number of Shipments Mode of Destination Transportation I Trucking over Duratek, Oakridge,TN highway 2 Trucking over Envirocare of Utah highway Clive, Utah 291 Rail Envirocare of Utah 11

Table 3 (Cont)

B. Irradiated Fuel Shipments (Disposition): None Shipped.

Additional ODCM Appendix C requirements.

Solid Waste Class Volume (Cu. M.) Est. Activity Est. Total (c) Error A 2.29E+04 3.41 E+00 +1-25%

B O.OOE+00 O.OOE+00 +1-25%

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

Container Package Volume (Cu. M.)

Gondola Car Strong 68.0 Tight Container B-25 Steel Box Strong Tight 2.9 Container 12

TABLE 3 Maine Yankee Atomic Power Station Effluent and Waste Disoosal Semiannual Report Second Half. 2005 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel).

1. Type of Waste. Unit 6-Month Est. Total Error, %

Period b Dry compressible waste, Cu. M. 16600 contaminated equipment, Ci 2.43 +1-25 DAW, cement.

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

b. Co-60 1.56% 3.8E-02 Ni-63 4.75% 1.16E-1 Cs-1 37 93.68% 2.28+00

3. Solid Waste Disposition Number of Shipments Mode of Destination Transportation 211 Rail Envirocare of Utah Clive, Utah 13

TABLE 3 (Continued)

B. Irradiated Fuel Shipments (Disposition):

None Shipped.

Additional ODCM Appendix C requirements.

Solid Waste Class Volume (Cu. Est. Activity Est. Total M.) ci) Error A 1.66E+04 2.43E+00 +1-25%

B O.OOE+00 O.OOE+00 +1-25%

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

Container IyPe Package Volume (Cu. M.)

Gondola Car Strong Tight 68.0 Container 14

TABLE 4 Supplemental Information

1. Regulatory Limits Effluent Concentrations

a. Fission and activation gases 10 CFR 20; Appendix B, Table 2, Column 1

b. lodines 10 CFR 20; Appendix B, Table 2, Column 1

c. Particulates, (with half lives greater than 8 days) 10 CFR 20; Appendix B, Table 2, Column 1

d. Liquid effluents: 10 CFR 20; Appendix B, Table 2, Column 2

e. Total noble gas concentration: 2.0 E-4 uCi/mi

2. Average Energy- Not Applicable

3. Measurements and Approximations of Radioactivity

a. Fission and Activation Gases Continuous Discharge-There were no continuous discharges via this effluent pathway in the year 2005. By the end of 2004, all site buildings within the radiologically controlled area were demolished and the only remaining activity associated with the Maine Yankee Decommissioning was soil remediation within the restricted area yard.

Batch Discharges- There were no batch releases via this pathway in 2005. The waste gas hold-up drums were purged and removed from service in 1997 in preparation for decommissioning. At that time, containment purge operations were no longer required and containment ventilation was directed to the Primary Vent Stack, and sampled until it was removed in 2004 as part of the decommissioning process.

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

b. lodines Iodine surveillance no longer applies due to the elapsed time since final plant shutdown from power operations.

c. Particulates There were no discharges via this effluent pathway in the year 2005. By the end of 2004, all site buildings within the radiologically controlled area were demolished and the only remaining activity associated with the Maine Yankee Decommissioning was soil remediation within the restricted area yard.

There are no gaseous effluent release paths associated with ISFSI Operations

d. Uquid Effluents Continuous Discharges Normally, continuous discharges were not performed as part of the decommissioning mode. However, in the second quarter of 2005 the process was added to the station's Offsite 15

Dose Calculation Manual or a one-time release to de-water a deep exaction in the restricted area yard to allow Final Status Survey (FSS) to be performed. The activity was performed once remediation activities were largely completed.

Batch Releases Each batch of potentially radioactive liquid is analyzed for gross alpha, tritium, dissolved gases, and gamma emitting isotopes prior to discharge.

Composite samples are made of liquid effluents for a quarterly analysis of Strontium-89, Strontium-90, and Iron-55.

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

4. Batch Releases

a. Liquids

1. Number of Batch release: 210 Number of Continuous Release: 1

2. Total time period for batch releases: 20898 minutes Total time period for continuous release: 955 minutes

3. Maximum time period for a batch release: 810 minutes

4. Average time period for batch releases: 99.5 minutes

5. Minimum time period for a batch release: 65 minutes

6. Average stream flow during periods of release of effluents into a flowing stream:

N!A

7. Maximum gross release concentration (uCi/ml): 1.37E-5 (1.36E-5 of H-3)

b. Gaseous

1. Number of batch release: 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 a batch release: Not Applicable

6. Maximum gross release rate (uCitsec): Not Applicable

5. Unplanned Releases

a. Liquid- There were no unplanned releases in 2005

b. Gaseous- There were no unplanned releases in 2005 APPENDIX A 16

Radioactive Effluent Monitoring Instrumentation Requirement Radioactive effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Sections 2.3.3 and 2.3.4. With less than the minimum number of channels operable and reasonable efforts to return the instrument(s) to operable status within 30 days of being unsuccessful, ODCM Sections 2.3.3 and 2.3.4 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.

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APPENDIX B Liquid Radwaste Treatment System Requirement With radioactive liquid waste being discharged without treatment, with estimated doses in excess of the limits in ODCM Section 2.1.5, a report must be submitted to the Commission in the Annual Effluent Release Report for the period.

Response: The requirements of ODCM Section 2.1.5 were met during this period and, therefore, no report is required.

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APPENDIX C Gaseous Radwaste Treatment System Requirement With radioactive gaseous waste being discharged without treatment with doses in excess of the limits in ODCM Section 2.2.6, a report must be submitted to the Commission in the Annual Effluent Release Report for the period.

Response: The requirements of ODCM Section 2.2.6 were met during this period and, therefore, no report is required.

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APPENDIX D Lower Limit of Detection for Radiological Analysis Requirement: ODCM Section 2.5 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 priori lower limits of detection.

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APPENDIX E Summary of Off-site Dose Calculation Manual Revisions Revision number Change # 30 Date: 04105 Summary; This ODCM Change added the radioactive liquid waste sampling and analysis requirements for a continuous discharge. The revision was made to allow for a one-tmne continuous discharge of groundwater from a deep excavation within the restricted area yard to allow Final Status Survey (FSS) to be performed. Radiological remediation activities were largely completed prior to implementation of the continuous release activity.

Revision number: Change # 31 Date: 08/05 Summary:

With the decommissioning I dismantlement of the former Maine Yankee plant complete, all decommissioning sections of the ODCM were removed as part of this revision. However, all section numbers remained the same to allow for ease of filing the 2005 annual reports required by the ODCM.

Appendix A of the ODCM pertained to effluent and direct dose calculations. This appendix was deleted and the subsequent appendices (B & C) were relabled as A & B.

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