radiological safety & control services 91 …tritium, gases,alpha) 2. average diluted...
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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.
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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*
period3. Percent of regulatory limit % 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
2. Average release rate for uCi/sec N/A* N/A*period
3. Percent of regulatory limit % 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)
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TABLE 1A
Maine Yankee Atomic Power StationEffluent and Waste Disposal Annual Report
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
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*
1. Total release Ci N/A* N/A* N/A__2. Average release rate for uCi/sec N/A* N/A*
period3. Percent of regulatory limit % N/A* N/A*
N/D*= Not DetectedN/A*= Not Applicable
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TABLE 1B
Maine Yankee Atomic Power StationEffluent and Waste Disposal Annual Report
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*
N/D*= Not DetectedN/A*= Not Applicable
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TABLE 1B
Maine Yankee Atomic Power StationEffluent and Waste Disposal Annual Report
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*
N/D*= Not DetectedN/A*= Not Applicable
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TABLE 1C
Maine Yankee Atomic Power StationEffluent and Waste Disposal Annual Report
January-December 2006Gaseous Effluents-Ground Level Release
There are no gaseous effluents associated with the Maine Yankee IndependentSpent Fuel Storage Installation (ISFSI)
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TABLE 2A
Maine Yankee Atomic Power StationEffluent and Waste Disposal Annual Report
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
N/D*= Not DetectedN/A*= Not Applicable
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TABLE 2A
Maine Yankee Atomic Power StationEffluent and Waste Disposal Annual Report
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
N/D*= Not DetectedN/A*= Not Applicable
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TABLE 2B
Maine Yankee Atomic Power StationEffluent and Waste Disposal Annual Report
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*
N/D*= Not DetectedN/A*= Not Applicable
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TABLE 2B
Maine Yankee Atomic Power StationEffluent and Waste Disposal Annual Report
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*
N/D*= Not DetectedN/A*= Not Applicable
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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
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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
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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
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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
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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