Radiological Safety & Control Services 91 …tritium, gases,alpha) 2. Average diluted concentration .uCi/ml N/A* N/A* during period 3. Percent of applicable limit % N/A* N/A* B. Tritium

License No. DPR-36Maine Yankee Atomic Power Company

Independent Spent Fuel Storage Installation

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

January-December 2006

April 2007Prepared by:

Edward L. Mercer

Radiological Safety & Control Services91 Portsmouth Avenue

Stratham, NH 03885-2468

1.0 INTRODUCTION

Tables 1 and 2 summarizes the quantity of radioactive gaseous and liquid effluents,respectively, for each quarter of 2006: Table 3 states that waste was shipped off-site for burial ordisposal during the year 2006. Tabie 4 contains supplementary information.

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

Changes to the ODCM made during the year 2006 are summarized in Appendix E. Acomplete copy of the revised manual is attached as well as the specific pages that changed.

1

TABLE 1A

Maine Yankee Atomic Power StationEffluent and Waste Disposal Annual Report

First and Second Quarters, 2006Gaseous Effluents-Summation of All Releases

'i. i otai Keiease U; NI/- lIVA IN•M

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

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

B. lodines _________ __ _ _ _ _ __ _ _ _ _ ______ ____ ____

1. Total Iodine-131 Ci N/A* N/A* N/A2. Average release rate for uCi/sec N/A* N/A*

period3. Percent of regulatory limit % N/A* N/A*

C.Prticulates ___

1. Particulates with T-1/2 > 8 Ci N/A* N/A* N/A

days2. Average release rate for uCi/sec N/A* N/A*


4. Gross alpha radioactivity Ci N/A* N/A*

~D. T~ritiumn_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1. Total release Ci N/A* N/A* N/A



N/D*= Not DetectedN/A*= Not Applicable** = Calculated for the time period in which the releases actually occurred. Allothers are calculated for the standard 91day period

(particulate release is an unscheduled release, which is reported in Table 4)

2

TABLE 1A


Third and Fourth Quarters, 2006Gaseous Effluents-Summation of All Releases

'i. I oTai Keiease2. Average release rate for

period

I 1 4 4

NIA* NIA*uCi/sec N/A* N/A*

3. Percent of regulatory limiti i

%/ N/A* N/A*

B. Iodines~ _ _ _ __ _ _ _ _ _ _

1. Total Iodine-131 Ci N/A* N/A* N/A2. Average release rate for uCi/sec N/A* N/A*

period3. Percent of regulatory limit % N/A* N/A*1. Particulates.withT-1, 2"> ..N/A1. Particulates with T-1/2 > 8

daysCi N/A* N/A* N/A



4. Gross alpha radioactivity Ci N/A* N/A*

1. Total release Ci N/A* N/A* N/A__2. Average release rate for uCi/sec N/A* N/A*


N/D*= Not DetectedN/A*= Not Applicable

3

TABLE 1B


First and Second Quarters, 2006Gaseous Effluents-Elevated Release

Continuous Mode Batch ModeNuclides Released Unit Ist 2n Ist 2n

Quarter Quarter Quarter Quarter

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-1 33 Ci N/A* N/A* N/A* N/A*Xenon-1 35 Ci N/A* N/A* N/A* N/A*

Xenon-1 35m 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*I odine-NNIodine-131 Ci N/A* N/A* N/A* N/A*Iodine-133 Ci N/A* N/A* N/A* N/A*lodine-135 Ci NIA* N/A* N/A* NIA*Total for period Ci N/A* N/A* N/A* N/A*S rticulates-89 Ci N/ I /

Strontium-89 Ci N/A* N/A* N/A* N/A*Strontium-90 Ci NIA* NIA* NIA* NIA*Cesium-I134 Ci NIA* NIA* NIA* NIA*Cesium-137 Ci N/A* N/A* N/A* N/A*

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


21

TABLE 1B


Third and Fourth Quarters", 2006Gaseous Effluents-Elevated Release

Continuous Mode Batch ModeNuclides Released Unit 3rd 4th 3rd 4th

__ IQuarter Quarter Quarter J Quarter1. Fisi ion Gas $ ' .. I • .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-1 33 Ci N/A* N/A* N/A* N/A*Xenon-1 35 Ci N/A* N/A* N/A* N/A*Xenon-1 35m 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.Iodines C NAN*/*AIodine-133 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 NIA* NIA* NIA* NIA*Total for period Ci N/A* N/A* N/A* N/A*3. Partic~ulates/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 N/A* N/A* N/A* N/A*Cesium-137 Ci N/A* N/A* N/A* N/A*Cobalt-60 Ci N/A* N/A* 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*


5

TABLE 1C


January-December 2006Gaseous Effluents-Ground Level Release

There are no gaseous effluents associated with the Maine Yankee IndependentSpent Fuel Storage Installation (ISFSI)

6

TABLE 2A


First and Second Quarters, 2006Liquid Effluents-Summation of All Releases

A. Fission and Activation Products1. Total Release (not including Ci N/A* N/A* N/A

tritium, gases,alpha)2. Average diluted concentration .uCi/ml N/A* N/A*

during period3. Percent of applicable limit % N/A* N/A*

B. Tritium1. Total Release2. Average diluted concentration

during period3. Percent of applicable limi

C. Dissolved and Entrained Gases1. Total Release2. Average diluted concentration

during period3. Percent of applicable limit

D. Gross Alpha Radioactivity1. Total release Ci N/A N/A N/A2. Average diluted concentration .uCi/ml N/A* N/A

during periodE. Volume of Waste Released (prior Liters N/A* N/A*to dilution)F. Volume of Dilution Water Used Liters N/A* N/A*During Period I


7

TABLE 2A


Third and Fourth Quarters, 2006Liquid Effluents-Summation of All Releases

->-z~-~A. I-ission ana Activation Proaucts

1. Total Release (not including Ci N/A N/A N/Atritium, gases,alpha)

2. Average diluted concentration .uCi/ml N/A N/Aduring period

3. Percent of applicable limit % N/A N/AB. Tritium

1. Total Release Ci N/A N/A N/A2. Average diluted concentration .uCi/ml N/A N/A

during period3. Percent of applicable limit 1 % N/A N/A

C. Dissolved and Entrained Gases1. Total Release Ci N/A N/A N/A2. Average diluted concentration .uCi/ml N/A N/A

during period3. Percent of applicable limit % N/A N/A

D. Gross Alpha Radioactivity1. Total release Ci N/A N/A N/A2. Average diluted concentration .uCi/ml N/A N/A

during periodE. Volume of Waste Released (prior Liters N/A N/A N/Ato dilution)F. Volume of Dilution Water Used Liters N/A N/A N/ADuring Period


8

TABLE 2B


First and Second Quarters, 2006Liquid Effluents

Continuous Mode Batch ModeNuclides Released Unit ISt 2n Ist 2 nd

Quarter Quarter Quarter QuarterStrontium-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*Iodine-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* N/A*Iron-59 Ci N/A* N/A* N/A* N/A*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-125 Ci N/A* N/A* N/A* N/A*Unidentified Ci N/A* N/A* N/A* N/A*Total for period (above) Ci N/A* N/A* N/A* N/A*Xenon-1 33 Ci N/A* N/A* N/A* N/A*Xenon-1 35 Ci N/A* N/A* N/A* N/A*


9

TABLE 2B


Third and Fourth Quarters, 2006Liquid Effluents

Continuous Mode Batch ModeNuclides Released Unit 3rd 4th 3rd 4th

Quarter Quarter Quarter QuarterStrontium-89 Ci N/A* N/A* N/A* N/A*Strontium-90 Ci N/A* N/A* N/A* N/A*Cesium-134 Ci N/A* N/A* N/A* N/A*Cesium-137 Ci N/A* N/A* N/A* N/A*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* N/A*Iron-59 Ci N/A* N/A* N/A* N/A*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-125 Ci N/A*. N/A* N/A* N/A*Unidentified Ci N/A* N/A* N/A* N/A*Total for period (above) Ci N/A* N/A* N/A* N/A*Xenon-1 33 Ci N/A* N/A* N/A* N/A*Xenon-1 35 Ci N/A* N/A* N/A* N/A*


10

TABLE 3Maine Yankee Atomic Power Station

Effluent and Waste Disposal Semiannual ReportFirst Half, 2006

Solid Waste and Irradiated Fuel Shipments

A. Solid Waste Shipped Off-Site for Burial or Disposal (NotIrradiated Fuel).

1. Type of Waste.

a. Spent resins, filtersludges, etc.

b. Dry compressible waste,contaminated equipment, DAW,cement.

c. Irradiated Hardware.

Unit 6-MonthPeriod

Cu. M. 0.0Ci. 0.0

Cu. M. 0.0Ci. 0.00

Est. Total Error,

+/- 25

+/- 25

+/- 25Cu. M.

Ci.0.0

0.0

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

a. Co-60 0

b.

C.

Ni-63Cs-137Fe-55Co-60Fe-55Ni-63

Cs-137Ce-144Pu-241Co-60Fe-55

00000000000

0

000000000000

0Ni-63

3. Solid Waste Disposition

Number of Shipments

0

Mode ofTransportationTrucking overhighway

Trucking overhighwayRail

Destination

Duratek, Oakridge,TN

Envirocare of UtahClive, UtahEnvirocare of Utah

0

0

11

Table 3 (Cont.)B. Irradiated Fuel Shipments (Disposition): NoneShipped.

Additional ODCM Appendix Crequirements.

Solid Waste Class Volume (Cu. M.) Est. Activity(ci)

Est. TotalError

ABC

O.OOE+000.OOE+000.OOE+00

0.OOE+000.00E+000.00E+00

+/- 25%+/- 25%+/- 25%

Container

Gondola Car

B-25 Steel Box

Type Package Volume(Cu. M.)

StrongTightContainer

Strong TightContainer

68.0

2.9

12

TABLE 3Maine Yankee Atomic Power Station

Effluent and Waste Disposal Semiannual ReportSecond Half, 2006

Solid Waste and Irradiated Fuel Shipments

A. Solid Waste Shipped Off-Site for Burial or Disposal (NotIrradiated Fuel).

1. Type of Waste.

b Dry compressible waste,contaminated equipment,DAW, cement.

Unit 6-MonthPeriod

Cu. M. 0Ci 0

Est. Total Error, %

+/- 25

2. Estimate of major nuclide composition (bytype of waste).

b. Co-60Ni-63

Cs-1 37

0.000.000.00

0.000.000.00

3. Solid Waste Disposition

Number of Shipments Mode ofTransportation

Destination

0 Rail Envirocare of UtahClive, Utah

13

TABLE 3(Continued)

B. Irradiated Fuel Shipments (Disposition):

None Shipped.

Additional ODCM Appendix Crequirements.

Solid Waste Class Volume (Cu.m.)

Est. Activity

0.OOE+000.OOE+000.OOE+00

Est. TotalError

+/- 25%+/- 25%+/- 25%

ABC

Container

Gondola Car

0.OOE+000.OOE+000.00E+00

PackageVolume (Cu. M.)

Strong TightContainer

68.0

14

TABLE 4

Supplemental Information

1. Regulatory Limits

Effluent Concentrationsa. Fission and activation gasesb. lodinesc. Particulates, (with half

lives greater than 8 days)d. Liquid effluents:

e. Total noble gas concentration:

10 CFR 20; Appendix B, Table 2, Column 110 CFR 20; Appendix B, Table 2, Column 1

10 CFR 20; Appendix B, Table 2, Column 110 CFR 20; Appendix B, Table 2, Column 2

2.0 E-4 uCi/ml

2. Average Energy- Not Applicable

3. Measurements and Approximations of Radioactivity

a. Fission and Activation GasesThere are no gaseous effluent release paths associated with ISFSI Operations.

b. lodinesThere are no gaseous effluent release paths associated with ISFSI Operations

c. Particulates

There are no particulate release paths associated with ISFSI Operations

d. Liquid Effluents

Continuous DischargesThere are no liquid effluent release paths associated with ISFSl Operations.

4. Batch Releasesa. Liquids

1. Number of Batch release: N/ANumber of Continuous Release: N/A

2. Total time period for batch releases: N/ATotal time period for continuous release: N/A

3. Maximum time period for a batch release: N/A4. Average time period for batch releases: N/A5. Minimum time period for a batch release: N/A6. Average stream flow during periods of release of effluents into a flowing stream:

N/A7. Maximum gross release concentration (uCi/ml): N/A

b. Gaseous1. Number of batch release: N/A2. Total time period for batch releases: Not Applicable3. Maximum time period for a batch release: Not Applicable4. Average time period for batch releases: Not Applicable5. Minimum time period for a batch release: Not Applicable6. Maximum gross release rate (uCi/sec): Not Applicable

5. Unplanned Releases -N/A

15

APPENDIX A

Radioactive Effluent Monitoring Instrumentation

There are no gaseous or liquid effluent release pathways associated with ISFSI Operations.Therefore, effluent monitoring instrumentation is not required.

16

APPENDIX B

Liquid Radwaste Treatment System

There are no liquid release pathways associated with ISFSI Operations. Therefore, a radwastetreatment system is not required.

17

APPENDIX C

Gaseous Radwaste Treatment System

There are no gaseous effluent release pathways associated with ISFSI Operations. Therefore, agaseous waste treatment system is not required.

18

APPENDIX D

Lower Limit of Detection for Radiological Analysis

There are no liquid or gaseous sampling requirements associated with ISFSI Operations sinceeffluent release pathways do not exist.

19

APPENDIX E

Summary of Off-site Dose Calculation Manual Revisions

There were no changes to the Offsite Dose Calculation in 2006.

20

Documents

Radiological Safety & Control Services 91 …tritium, gases,alpha) 2. Average diluted concentration .uCi/ml N/A* N/A* during period 3. Percent of applicable limit % N/A* N/A* B. Tritium