ML081140672

From kanterella
Jump to navigation Jump to search
Maine Yankee Atomic Power Company Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report, January-December 2007
ML081140672
Person / Time
Site: Maine Yankee, 07100465
Issue date: 04/30/2008
From: Mercer E L
Radiological Safety & Control Services
To:
Office of Nuclear Material Safety and Safeguards
References
MN-08-008, RA-08-015
Download: ML081140672 (19)
v • d • e


Text

License No. DPR-36 Maine Yankee Atomic Power Company Independent Spent Fuel Storage Installation ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January-December 2007 ,RSIIlfStlnCuWSrtfl April 2008 Prepared by: Edward L. Mercer Radiological Safety & Control Services 91 Portsmouth Avenue Stratham, NH 03885-2468 Tables 1 and 2 summarizes the quantity of radioactive gaseous and liquid effluents, respectively, for each quarter of 2007. Table 3 states the quantity of solid radioactive waste shipped off-site for burial or disposal during the year 2007. 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).Changes to the ODCM made during the year 2007 are summarized in Appendix E. A complete copy of the revised manual is attached as well as the specific pages that changed.1 TABLE 1A Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters, 2007 Gaseous Effluents-Summation of All Releases I... ..........

... ........ ...............

1 N/D*= Not Detected N/A*= Not Applicable There are no gaseous effluents associated the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI)2 TABLE 1A Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2007 Gaseous Effluents-Summation of All Releases-Unit 3 3St.TotalFormatted:

Font: 14 pt A. Fission and Activation Gases _ ____________

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*B. lodines _,____. ....._____ ____-1. Total Iodine-131 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*C. Particulates

______ _____,______

1. Particulates with T-1/2 > 8 Ci N/A* N/A* N/A 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 I N/A* N/A*D .T ritium __:,__. .__... ........ ....... ______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 Detected N/A*= Not Applicable There are no gaseous effluents associated the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI)3 TABLE 1B Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters, 2007 Gaseous Effluents-Elevated Release Continuous Mode Batch Mode Nuclides Released Unit Ist 2"c Ist ,2nd 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-133 Ci N/A* N/A* N/A* N/A*Xenon-135 Ci N/A* N/A* N/A* N/A*Xenon-1 35m 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 N/A* N/A* N/A* N/A*2. Ibdiiies ~ ~ _______ _______Iodine-131 Ci N/A* N/A* N/A* N/A*Iodine-133 Ci N/A* N/A* N/A* N/A*Iodine-135 Ci N/A* N/A* N/A* N/A*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 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 Detected N/A*= Not Applicable There are no gaseous effluents associated the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI)4 TABLE 1 B Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2007 Gaseous Effluents-Elevated Release N/D*= Not Detected N/A*= Not Applicable There are no gaseous effluents associated the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI)5 TABLE 1C Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report January-December 2007 Gaseous Effluents-Ground Level Release There are no gaseous effluents associated the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI)6 TABLE 2A Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters, 2007 Liquid Effluents-Summation of All Releases~Unit Quarter Quarter Est Total Formatte:

Font: 14 pt Error, : -A. Fission and Activation Products 1. Total Release (not including Ci N/A* N/A* N/A tritium, gasesalpha)

2. Average diluted concentration uCi/ml N/A* N/A*during period 3. Percent of applicable limit % N/A* N/A*B. Tritium 1. Total Release Ci N/A* N/A* N/A 2. Average diluted concentration uCi/ml N/A* N/A*during period 3. Percent of applicable limit % N/A* N/A*C. Dissolved and Entrained Gases 1. Total Release Ci N/A* N/A* N/A 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 N/A N/A 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*to dilution)F. Volume of Dilution Water Used Liters N/A* N/A*During Period N/D*= Not Detected N/A*= Not Applicable 7

TABLE 2A Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2007 Liquid Effluents-Summation of All Releases unit 3rd 4.Est. Total Quarter Quarter Error, %A. Fission and Activation Products 1. 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 period 3. Percent of applicable limit % N/A N/A B. Tritium 1. Total Release Ci N/A N/A N/A 2. Average diluted concentration uCi/ml N/A N/A during period 3. Percent of applicable limit % N/A N/A C. Dissolved and Entrained Gases 1. Total Release Ci N/A N/A N/A 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 N/A N/A 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 N/D*= Not Detected N/A*= Not Applicable 8

TABLE 2B Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters, 2007 Liquid Effluents N/D*= Not Detected N/A*= Not Applicable 9

TABLE 2B Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report Third and Fourth Quarters, 2007 Liquid Effluents Cnntinunug MndA Raitrh ModA Nuclides Released Unit 3rd 4th 3rd 4th Quarter Quarter Quarter Quarter 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*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-133 Ci N/A* N/A* N/A* N/A*Xenon-1 35 Ci N/A* N/A* N/A* N/A*N/D*= Not Detected N/A*= Not Applicable 10 TABLE 3 Maine Yankee Atomic Power Station Effluent and Waste Disposal Semiannual Report First Half, 2007 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 Period N/A N/A Est. Total Error, N/A N/A 2, Estimate of major nuclide composition (by type of waste).N/A 3, Solid Waste Disposition Number of Shipments None Mode of Transportation N/A Destination N/A B. Irradiated Fuel Shipments (Disposition):

None Shipped.Additional ODCM Requirements.

Solid Waste Class A B C Volume (Cu. M.)0.00E+00 0.OOE+00 0.OOE+00 Est. Activity 0.OOE+00 0.OOE+00 0.OOE+00 Est. Total Error %+/- 25+/- 25+/- 25 Container Type Package Volume (Cu. M.)N/A N/A N/A 11 TABLE 3 Maine Yankee Atomic Power Station Effluent and Waste Disposal Semiannual Report Second Half, 2007 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 Period None 2. Estimate of major nuclide composition (by type of waste).None Est. Total Error, %3. Solid Waste Disposition Number of Shipments None Mode of Transportation N/A Destination N/A B. Irradiated Fuel Shipments (Disposition):

None Shipped.Additional ODCM Requirements.

Solid Waste Class Volume (Cu.M_)A 0.OOE+00 B 0.OOE+00 C 0.OOE+00 Est. Activity 0.OOE+00 0.OOE+00 0.OOE+00 Est. Total Error+/- 0%+/- 0%+/- 0%12 TABLE 4 Supplemental Information

1. Regulatory Limits Effluent Concentrations
a. Fission and activation gases b. lodines c. Particulates, (with half lives greater than 8 days)d. Liquid effluents:
e. Total noble gas concentration:

10 CFR 20; Appendix B, Table 2, Column 1 10 CFR 20; Appendix B, Table 2, Column 1 10 CFR 20; Appendix B,Table 2, Column 1 10 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 Gases There are no gaseous effluent release paths associated with ISFSI Operations.
b. lodines There 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 Discharges There are no liquid effluent release paths associated with ISFSI Operations.
4. Batch Releases a. Liquids 1. Number of Batch release: N/A Number of Continuous Release: N/A 2. Total time period for batch releases:

N/A Total time period for continuous release: N/A 3. Maximum time period for a batch release: N/A 4. Average time period for batch releases:

N/A 5. Minimum time period for a batch release: N/A 6. Average stream flow during periods of release of effluents into a flowing stream: N/A 7. Maximum gross release concentration (uCi/ml):

N/A b. Gaseous 1. Number of batch release: N/A 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 (uCi/sec):

Not Applicable

5. Unplanned Releases -N/A 13 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.14 APPENDIX B Liquid Radwaste Treatment System There are no liquid release pathways associated with ISFSI Operations.

Therefore, radwaste treatment systems were not required.15 APPENDIX C Gaseous Radwaste Treatment System There are no gaseous effluent release pathways associated with ISFSI Operations.

Therefore, gaseous waste treatment systems were not required.16 APPENDIX D Lower Limit of Detection for Radiological Analysis There are no liquid or gaseous sampling requirements associated with ISFSI Operations since effluent release pathways do not exist.17 APPENDIX E Summary of Off-site Dose Calculation Manual Revisions One change was made to the Offsite Dose Calculation in 2007.Description of Changes;Revise the Maine Yankee site boundary to be consistent with the license and the 72.212 Rad Evaluation for the Maine Yankee ISFSI. Additionally, the environmental TLD's locations were reduced from 16 to 9.18

Retrieved from "https://kanterella.com/w/index.php?title=ML081140672&oldid=1373047"