ML16118A303

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Maine Yankee Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report, Annual Radiological Environmental Operating Report, and Changes to the Off-Site Dose Calculation Manual for 2015
ML16118A303
Person / Time
Site: Maine Yankee
Issue date: 04/20/2016
From: Brown J S
Maine Yankee Atomic Power Co
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
OMY-16-021
Download: ML16118A303 (47)
v • d • e


Text

MAINE YANKEE 321 Old Ferry Road, Wiscasset; Maine 04578 April 20, 2016 OMY-16-021 10 CFR 50.4 and 10 CFR 50.36a(a)(2) ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 -0001 Maine Yankee Atomic Power Company Maine Yankee Independent Spent Fuel Storage Installation NRC License No. DPR-36 CNRC Docket No. 50-309)

Subject:

Annual Radioactive Effluent Release Report, Annual Radiological Environmental Operating Report, and Changes to the Off-Site Dose Calculation Manual for 2015 10 CFR 50.36a(a)(2), Section 2)b) of Appendix C of the Maine Yankee Atomic Power Company (Maine Yankee) Quality Assurance Program (QAP) for the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) and Section 2 of Appendix A of the Off-Site Dose Calculation Manual (ODCM) for the Maine Yankee ISFSI require Maine Yankee to submit an Annual Radioactive Effluent Release Report. Enclosure 1 provides the report for the period of January 1 through December 31, 2015. Section 2)a) of Appendix C of the Maine Yankee QAP for the Maine Yankee ISFSI and Section 1 of Appendix A of the ODCM for the Maine Yankee ISFSI require the submittal of an Annual Radiological Environmental Operating Report. Enclosure 2 provides the report for the period ofJanuary 1 through December 31, 2015. Section l)c)(4) of Appendix C of the Maine Yankee QAP for the Maine Yankee ISFSI requires that any changes to the ODCM to be submitted as part of or concurrent with the Annual Radiological Environmental Operating Report. No revisions to the Maine Yankee ISFSI ODCM were issued in 2015. If you have any questions regarding this submittal, please do not hesitate to contact me at (207) 882-1303. Respectfully, / iSFsr Manager Maine Yankee Atomic Power Company OMY-16-021/April 20, 2016/Page 2

Enclosures:

1. Maine Yankee Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report, January-December 2015. 2. Maine Yankee Independent Spent Fuel Storage Installation, Annual Radiological Environmental Operating Report, January-December 2015. cc: D. Dorman, NRC Region I Administrator R. Powell, Chief, Decommissioning Branch, NRC, Region 1 J. Goshen, NRC Project Manager P. J. Dostie, SNSI, State of Maine J. Hyland, State of Maine ENCLOSURE 1 MAINE YANKEE INDEPENDENT SPENT FUEL STORAGE INSTALLATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -DECEMBER 2015 OMY-16-021 MAINE YANKEE INDEPENDENT SPENT FUEL STORAGE INSTALLATION License Nos. DPR-36 and SFGL-14 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January -December 2015 Radiation &toty & Control Services April 2016 Prepared by: Radiation Safety & Control Services 91 Portsmouth Avenue Stratham, NH 03885-2468 EXECUTIVE SUMMARY Tables 1 and 2 summarize the quantity of radioactive gaseous and liquid effluents, respectively, for each quarter of 2015. There were no gaseous or liquid releases in 2015. Table 3 summarizes waste shipped off-site for disposal for each half year of 2015. There was no waste shipped for disposal in 2015. Appendices A and B indicate the status of reportable items per the requirements of the Off-site Dose Calculation Manual (ODCM). There were no reportable items in 2015. Appendix C presents any changes in the ODCM. The ODCM was not revised in 2015. MY 2015 Annual RER Report Page 2 of 15 Table 1 MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2015 Gaseous Effluents-Summation of All Releases Nuclides Released
  • Units 1st 2nd 3rd .. 4th Quarter* *.Quarter Quarter Quarter A. Fission and Activation Gases .... . ,;. *"'. '* .. ;. Total Release Ci N/A* N/A* N/A* N/A* Average release rate µCi/s N/A* N/A* N/A* N/A* Percent of regulatory limit % N/A* N/A* N/A* N/A* B. Iodines ,... * .. ;;c .... M. ..... :* * '.p..' . ,._, .*' ... J,_<r.:.. ' .. Total Iodines released Ci N/A* N/A* N/A* N/A* Average release rate µCi/s N/A* N/A* N/A* N/A* Percent of regulatory limit % N/A* N/A* N/A* N/A* C .. Particulates ... ' '.?f * . ' .:-;* < :-. ;.-,_' .. *-.. ' ' Particulates Released Ci N/A* N/A* N/A* N/A* Averaqe release rate µCi/s N/A* N/A* N/A* N/A* Percent of requlatory limit % N/A* N/A* N/A* N/A* Gross alpha radioactivity Ci N/A* N/A* N/A* N/A* ... .. . .*. . , .. "* . Error .. -I N/A* .. N/A* -:* N/A* ., ' D. Tritium .* -: ; :.*_.. ,: *. : ?:./ >"i *;:*.'{* . _,, "" I*-"._ *' J.. ' -"i r. * . V, .?.' . ,.;:._, , -.* .. . -.. .* *-.: Total release Ci N/A* N/A* N/A* N/A* N/A* Average release rate µCi/s N/A* N/A* N/A* N/A* Percent of regulatory limit % N/A* N/A* N/A* N/A* *-N/A*= Not Applicable There are no gaseous effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) MY 2015 Annual RER Report Page 3 of 15 Table 1A MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2015 Gaseous Effluents -Ground Level Releases -Batch Mode Nuclides Released s pton-85 Ci N/A* N/A* N/A* N/A* N/A* Kr ton-85m Ci N/A* N/A* N/A* N/A* N/A* Kr pton-87 Ci N/A* N/A* N/A* N/A* N/A* K pton-88 Ci N/A* N/A* N/A* N/A* N/A* Xenon-133 Ci N/A* N/A* N/A* N/A* N/A* Xenon-135 Ci N/A* N/A* N/A* N/A* N/A* Xenon-135m Ci N/A* N/A* N/A* N/A* N/A* Xenon-138 Ci N/A* N/A* N/A* N/A* N/A* Unidentified Ci N/A* N/A* N/A* N/A* N/A* Total for period Ci N/A* N/A* N/A* N/A* N/A* *_ . -. c-. __ ,_ -** -.. --.-... --.* lodine-131 Ci N/A* N/A* N/A* N/A* N/A* lodine-133 Ci N/A* N/A* N/A* N/A* N/A* lodine-135 Ci N/A* N/A* N/A* N/A* N/A* Total for period Ci N/A* N/A* N/A* N/A* N/A* . *,:i ':' '"" ;(' ' .. -----. -. ---' -,,. --. r, -_,*_,, .. . . . -. ----L ... Strontium-89 Ci N/A* N/A* N/A* N/A* N/A* Strontium-90 Ci N/A* N/A* N/A* N/A* N/A* Cesium-134 Ci N/A* N/A* N/A* N/A* N/A* Cesium-137 Ci N/A* N/A* N/A* N/A* N/A* Cobalt-60 Ci N/A* N/A* N/A* N/A* N/A* Barium-Lanthanum-140 Ci N/A* N/A* N/A* N/A* N/A* Others-Plutonium-238 Ci N/A* N/A* N/A* N/A* N/A* Curium-243,244 Ci N/A* N/A* N/A* N/A* N/A* Uranium-234 Ci N/A* N/A* N/A* N/A* N/A* Uranium-238 Ci N/A* N/A* N/A* N/A* N/A* Thorium-232 Ci N/A* N/A* N/A* N/A* N/A* Radium-226 Ci N/A* N/A* N/A* N/A* N/A* N/A*= Not Applicable There are no gaseous effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) MY 2015 Annual RER Report Page 4 of 15 -. *-

Table 18 MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2015 Gaseous Effluents -Ground Level Releases -Continuous Mode Nuclides Released pton-85 NIA* NIA* NIA* pton-85m NIA* NIA* NIA* NIA* ton-87 NIA* NIA* NIA* NIA* ton-88 NIA* NIA* NIA* NIA* Xenon-133 NIA* NIA* NIA* NIA* Xenon-135 NIA* NIA* NIA* NIA* Xenon-135m NIA* NIA* NIA* NIA* NIA* Xenon-138 Ci NIA* NIA* NIA* NIA* NIA* Unidentified Ci NIA* NIA* NIA* NIA* NIA* Total for period Ci NIA* NIA* NIA* NIA* NIA* a ir.oXHliW.:3 _ -* * *-r ...., ...,, -1 , * -" * ' ... . _* ... ...... ;..:. ___ .. -..... * ._ ___ --.... -------. lodine-131 Ci NIA* NIA* NIA* NIA* NIA* lodine-133 Ci NIA* NIA* NIA* NIA* NIA* lodine-135 Ci NIA* NIA* NIA* NIA* NIA* Total for period Ci NIA* NIA* NIA* NIA* NIA* :.;. I fu\Q . .. . --,. ... -.. ., ... -------. ----,, . Strontium-89 Ci NIA* NIA* NIA* NIA* NIA* Strontium-90 Ci NIA* NIA* NIA* NIA* NIA* Cesium-134 Ci NIA* NIA* NIA* NIA* NIA* Cesium-137 Ci NIA* NIA* NIA* NIA* NIA* Cobalt-60 Ci NIA* NIA* NIA* NIA* NIA* Barium-Lanthanum-140 Ci NIA* NIA* NIA* NIA* NIA* Others-Plutonium-238 Ci NIA* NIA* NIA* NIA* NIA* Curium-243,244 Ci NIA* NIA* NIA* NIA* NIA* Uranium-234 Ci NIA* NIA* NIA* NIA* NIA* Uranium-238 Ci NIA* NIA* NIA* NIA* NIA* Thorium-232 Ci NIA* NIA* NIA* NIA* NIA* Radium-226 Ci NIA* NIA* NIA* NIA* NIA* NIA*= Not Applicable There are no gaseous effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) MY 2015 Annual RER Report Page 5of15 ' '

Table 1C MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2015 Gaseous Effluents -Elevated Releases -Batch Mode Nuclides Released N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* Xenon-133 N/A* N/A* N/A* N/A* Xenon-135 N/A* N/A* N/A* N/A* Xenon-135m N/A* N/A* N/A* N/A* N/A* Xenon-138 Ci N/A* N/A* N/A* N/A* N/A* Unidentified Ci N/A* N/A* N/A* N/A* N/A* Total for period Ci N/A* N/A* N/A* N/A* N/A* _* :_ --,_......._. ; *--. -* -. ... -. . -. -. -.. .. -; -.. *-. __ -jL lodine-131 Ci N/A* N/A* N/A* N/A* N/A* lodine-133 Ci N/A* N/A* N/A* N/A* N/A* lodine-135 Ci N/A* N/A* N/A* N/A* N/A* Total for period Ci N/A* N/A* N/A* N/A* N/A* *1 . . . " . .v-,iv,*M' *---" Strontium-89 Ci N/A* N/A* N/A* N/A* N/A* Strontium-90 Ci N/A* N/A* N/A* N/A* N/A* Cesium-134 Ci N/A* N/A* N/A* N/A* N/A* Cesium-137 Ci N/A* N/A* N/A* N/A* N/A* Cobalt-60 Ci N/A* N/A* N/A* N/A* N/A* Bari um-Lanthanum-140 Ci N/A* N/A* N/A* N/A* N/A* Others-Plutonium-238 Ci N/A* N/A* N/A* N/A* N/A* Curium-243,244 Ci N/A* N/A* N/A* N/A* N/A* Uranium-234 Ci N/A* N/A* N/A* N/A* N/A* Uranium-238 Ci N/A* N/A* N/A* N/A* N/A* Thorium-232 Ci N/A* N/A* N/A* N/A* N/A* Radium-226 Ci N/A* N/A* N/A* N/A* N/A* N/A*= Not Applicable There are no gaseous effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) MY 2015 Annual RER Report Page 6of15 :

Table 10 MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2015 Gaseous Effluents -Elevated Releases -Continuous Mode Nuclides Released N/A* N/A* N/A* ton-85m N/A* N/A* N/A* N/A* N/A* N/A* Ci 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* N/A* Xenon-135m Ci N/A* N/A* N/A* N/A* N/A* Xenon-138 Ci N/A* N/A* N/A* N/A* N/A* Unidentified Ci N/A* N/A* N/A* N/A* N/A* Total for period Ci N/A* N/A* N/A* N/A* N/A* _ .. __ .... --:.: ... ' **--.. ___ . * *_. ** J_ lodine-131 Ci N/A* N/A* N/A* N/A* N/A* lodine-133 Ci N/A* N/A* N/A* N/A* N/A* lodine-135 Ci N/A* N/A* N/A* N/A* N/A* Total for period Ci N/A* N/A* N/A* N/A* N/A* Strontium-89 Ci N/A* N/A* N/A* N/A* N/A* Strontium-90 Ci N/A* N/A* N/A* N/A* N/A* Cesium-134 Ci N/A* N/A* N/A* N/A* N/A* Cesium-137 Ci N/A* N/A* N/A* N/A* N/A* Cobalt-60 Ci N/A* N/A* N/A* N/A* N/A* Barium-Lanthanum-140 Ci N/A* N/A* N/A* N/A* N/A* Others-Plutonium-238 Ci N/A* N/A* N/A* N/A* N/A* Curium-243,244 Ci N/A* N/A* N/A* N/A* N/A* Uranium-234 Ci N/A* N/A* N/A* N/A* N/A* Uranium-238 Ci N/A* N/A* N/A* N/A* N/A* Thorium-232 Ci N/A* N/A* N/A* N/A* N/A* Radium-226 Ci N/A* N/A* N/A* N/A* N/A* N/A*= Not Applicable There are no gaseous effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) MY 2015 Annual RER Report Page 7 of 15 Table 2 MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2015 Liquid Effluents -Summation of All Releases Nuclides Released Unit * *2nd . * ** *. 3rd Quarter . . ,_., *-***** Quarter-.: Quarter. A. Fission and Activation Products Total Release (not including Ci N/A* N/A* N/A* tritium, Qases, alpha) Average diluted concentration µCi/ml N/A* N/A* N/A* during period Percent of applicable limit % N/A* N/A* N/A* 8. Tritium Total Release Ci N/A* N/A* N/A* Average diluted concentration µCi/ml N/A* N/A* N/A* during period Percent of applicable limit % N/A* N/A* N/A* C. Dissolved and Entrained Gases Total Release Ci N/A* N/A* N/A* Average diluted concentration µCi/ml N/A* N/A* N/A* during period Percent of applicable limit % N/A* N/A* N/A* D. Gross Alpha Radioactivity Total release Ci N/A* N/A* N/A* Average diluted concentration µCi/ml N/A* N/A* N/A* during period E. Volume of Waste Released Liters N/A* N/A* N/A* (prior to dilution) F. Volume of Dilution Water Liters N/A* N/A* N/A* Used During Period N/A*= Not Applicable ***4th Error "Quarter N/A* N/A* N/A* N/A* . N/A* N/A* N/A* . N/A* N/A* N/A* N/A* .{ N/A* .**t:.: N/A* N/A* N/A* N/A* N/A* ' : ';,:_ There are no liquid effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) MY 2015 Annual RER Report Page 8 of 15 Table 2A MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2015 Liquid Effluents -Batch Mode NuFliaes. * , 1: . ; *.::.

  • f_nd: * ** . ** .\;. * . 't'ZY' Quarter Strontium-89 Strontium-90 Cesium-134 Cesium-137 lodine-131 Cobalt-58 Cobalt-60 lron-59 Zinc-65 ManQanese-54 Chromium-51 Zirconium-Niobium-95 Molybdenum-99 Technetium-99m Barium-Lathanium-140 Cerium-141 Others-lron-55 Antimony-125 Unidentified Total for period (above) Dissolved and Entrained Gasses Tritium Gross Alpha N/A*= Not Applicable Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* ,, , 3rd Quarter* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A*

N/A* N/A*

N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* , 4th Totals 14 ' *' N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* There are no liquid effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) MY 2015 Annual RER Report Page 9 of 15 I Nuclides Released ,ti: -Strontium-89 Strontium-90 Cesium-134 Cesium-137 lodine-131 Cobalt-58 Cobalt-60 lron-59 Zinc-65 Manganese-54 Chromium-51 Zirconium-Niobium-95 Molybdenum-99 Technetium-99m Barium-Lathanium-140 Cerium-141 Others-lron-55 Antimony-125 Unidentified Total for period (above) Dissolved and Entrained Gasses Tritium Gross Alpha Table 28 MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2015 Liquid Effluents -Continuous Mode Unit 1st* 2nd 3rd Quarter Quarter Quarter ' Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* NIA*= Not Applicable 4th Totals * ' _Quader* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* There are no liquid effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) MY 2015 Annual RER Report Page 10 of 15 Table 3 MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report First Half 2015 Low Level Waste Shipments Resins, Filters and Evaporator Bottoms Volume Waste Class Solidifying Agent ft,j m,j A 0 0 B 0 0 c 0 0 All 0 0 Major radionuclides for above data: ' Dry Active Waste Volume Waste Class Solidifying Agent ft3 m3 A 0 0 B 0 0 c 0 0 All 0 0 Major radionuclides for above data: Irradiated Components Volume >: ,.. . Waste Class Solidifying Agent ft3 m3 A 0 0 B 0 0 c 0 0 All 0 0 Major radionuclides for above data: *. *. * .. ' .. Other Waste Volume . ' .. Waste Class Solidifying Agent ft,j m,j A 0 0 B 0 0 c 0 0 All 0 0 Major radionuclides for above data: MY 2015 Annual RER Report ! Curies Shipped Curies 0 0 0 0 Curies Shipped Curies 0 0 0 0 Curies Shipped Curies 0 0 0 0 Curies' *. Shipped Curies 0 0 0 0 Page 11 of 15 Table 3A MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report Second Half 2015 Low Level Waste Shipments Resins, Filters and Evaporator Volume Bottoms Waste Class Solidifying Agent ft3 m3 A 0 0 B 0 0 c 0 0 All 0 0 Major radionuclides for above data: . " ,, Dry Active Waste ' Volume0 ' . iF . Waste Class Solidifying Agent ft3 m3 A 0 0 B 0 0 c 0 0 All 0 0 Major radionuclides for above data: : . , . ,volume ., . > -*S5"* , , *. ,* *:" I>:' . *-" Waste Class Solidifying Agent ft3 m3 A 0 0 B 0 0 c 0 0 All 0 0 Major radionuclides for above data: 0the.r Waste . .. ."'.:' ,.,,. Volume ,* .. ,,. ... , ,* **,' .. ;_: ... ..,. (; .,. -. Waste Class Solidifying Agent ft3 m3 A 0 0 B 0 0 c 0 0 All 0 0 Major radionuclides for above data: MY 2015 Annual RER Report Curies Shipped* Curies 0 0 0 0 Curies Shipped .,, Curies 0 0 0 0 Curies , Shipped . ' Curies 0 0 0 0 Curies Shipped Curies 0 0 0 0 Page 12 of 15 Appendix A Radiation Dose Assessment There were no gaseous or liquid effluent releases in 2015. Therefore, an assessment of radiation doses to the most likely exposed member(s) of the public to show compliance with 40CFR190 or 1OCFR72.104 from effluents was not required. MY 2015 Annual RER Report Page 13of15 Appendix B Unplanned Releases There were no unplanned releases of radioactive materials from the site in 2015. MY 2015 Annual RER Report Page 14of15 Appendix C Off-site Dose Calculation Manual Changes There were no changes to the Off-site Dose Calculation Manual in 2015. MY 2015 Annual RER Report Page 15 of 15 OMY-16-021 ENCLOSURE2 MAINEY ANKEE INDEPENDENT SPENT FUEL STORAGE INSTALLATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY -DECEMBER 2015 MAINE YANKEE INDEPENDENT SPENT FUEL STORAGE INSTALLATION License Nos. DPR-36 and SFGL-14 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January -December 2015 Radiotion Safety & Controi Services April 2016 Prepared by: Radiation Safety & Control Services 91 Portsmouth Avenue Stratham, NH 03885-2468 EXECUTIVE SUMMARY The Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) has been in operation since 2001. All fuel has been transferred into dry storage casks and placed at the Independent Spent Fuel Storage Installation. The Radiological Environmental Monitoring Program (REMP) for the Maine Yankee ISFSI located in Wiscasset, ME was continued for the period January through December 2015 in compliance with the Maine Yankee Offsite Dose Calculation Manual (ODCM). By design, there are no liquid or gaseous effluents associated with the operation of the ISFSI. Therefore, the ODCM only requires monitoring of direct exposure from the facility. TLDs were used to measure direct gamma exposure at nine locations in the vicinity of the ISFSI and one control location 5.2 kilometers away. The results of these measurements showed no significant change in exposure rates and potential doses to members of the public during the monitoring period. The results of the monitoring performed in 2015 also show that operating the Maine Yankee ISFSI results in only a small fraction of the 40 CFR Part 190 and 1 O CFR Part 72.104 direct radiation dose limit of 25 mrem/year to members of the public. MY 2015 Annual REO Report Page 2of28 TABLE OF CONTENTS Section

1.0 INTRODUCTION

............................................................................................ 6 2.0 GENERAL ISFSI AND SITE INFORMATION ................................................ 7 3.0 PROGRAM DESIGN ............................................................. -......................... 7 3.1 MONITORING ZONES ........................................................................................... 7 3.2 PATHW_AYS MONITORED ...................................................................................... 8 3.3 DESCRIPTION OF MONITORING PROGRAM ............................................................ 8 4.0 RADIOLOGICAL DATA SUMMARY TABLES ............................. .............. 13 5.0 ANALYSIS OF ENVIRONMENTAL RES UL TS ............................................ 27 5.1 SAMPLING PROGRAM DEVIATIONS ..................................................................... 27 5.2 DIRECT RADIATION PATHWAY ............................................................................ 27

6.0 REFERENCES

............................................................................................. 28 MY 2015 Annual REO Report Page 3of28 LIST OF TABLES 3.1 Radiological Environmental Monitoring Program ..................................... 9 3.2 Radiological Environmental Monitoring* Locations ................................. 10 4.1 TLD Measurements by Half-Year ............................................................... 14 4.2 TLD Data Summary .................................................................................... 15 4.3 Direct Dose from ISFSI Operations ........................................................... 16 MY 2015 Annual REO Report Page 4 of 28 LIST OF FIGURES Figure 3.1 Radiological Environmental Monitoring Locations (within 0.28 km) ..... 11 3.2 Direct Radiation Monitoring Locations (outside 1 km) ........................... 12 4.1 Annual Dose Trend at TL-1-02 .................................................................... 18 4.2 Annual Dose Trend at TL-1-04 ..................................................................... 19 4.3 Annual Dose Trend at TL-1-06 .................................................................... 20 4.4 Annual Dose Trend at TL-1-08 .................................................................... 21 4.5 Annual Dose Trend at TL-1-10 .................................................................... 22 4.6 Annual Dose Trend at TL-1-12 .................................................................... 23 4.7 Annual Dose Trend at TL-1-14 .................................................................... 24 4.8 Annual Dose Trend at TL-1-15 .................................................................... 25 4.9 Annual Dose Trend at TL-1-16 .................................................................... 26 MY 2015 Annual REO Report Page 5of28

1.0 INTRODUCTION

This report summarizes the findings of the Radiological Environmental Monitoring Program (REMP) conducted by Maine Yankee in the vicinity of the Independent Spent Fuel Storage Installation in Wiscasset, Maine during the calendar year 2015. It is submitted annually in compliance with Appendix A, of the Offsite Dose Calculation Manual (ODCM). The remainder of this report is organized as . follows: Section 2: Provides a brief description of the Maine Yankee site and its environs. Section 3: Provides a description of the overall REMP design. Included is a summary of the requirements for REMP sampling, tables listing routine TLD monitoring locations with compass sectors and distances from the ISFSI, and maps showing the location of each of the TLD monitoring locations. Section 4: Provides a complete set of TLD data showing measured results (mR) and calculated doses (mrem per year). This section also provides the summarized exposure rate data in the format specified by the NRG Branch Technical Position on Environmental Monitoring (Reference 1 ). Section 5: Provides the results of the monitoring program. The performance of the program in meeting ODCM requirements is discussed, and the data acquired during the year is analyzed. Section 6: References MY 2015 Annual REO Report Page 6of28 2.0 GENERAL ISFSI AND SITE INFORMATION The Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) is located in the town of Wiscasset, Lincoln County, Maine, approximately six miles northeast of Bath, Maine. The site vicinity is rural and lightly populated. The ISFSI site is located near Bailey Point, a peninsula bounded to the east by the Back River and to the west by a shallow inlet known as Bailey Cove, both of which are part of the Montsweag Bay-Sheepscot River Estuary. Bailey point is an elongated bedrock ridge with flat or gently rolling topography rising to an average elevation of about 25 feet above sea level. The Radiological Environmental Monitoring Program (REMP) for the ISFSI began pre-operational measurements in the 4th quarter of 1999, approximately 2 years prior to the initial spent fuel transfer to the ISFSI. The ISFSI REMP has been in continuous operation since this transfer began. 3.0 PROGRAM DESIGN The Radiological Environmental M0nitoring Program (REMP) for the Maine Yankee ISFSI was designed to provide assurance to regulatory agencies and the public that the station's environmental impact is known and within anticipated limits. The direct dose limit for members of the public from operation of the ISFSI is 25 mrem per year (References 3 and. 4 ). The detailed sampling requirements of the REMP are given in the ODCM. The sampling requirements specified in the ODCM are summarized in Table 3.1 of this report. Details of the monitored locations are shown in Table 3.2, as well as Figures 3.1 and 3.2 of this report. 3.1 Monitoring Zones The REMP is designed to allow comparison of levels of radioactivity in samples from the area possibly influenced by the ISFSI to levels found in areas not influenced by the ISFSI. The first area is called "indicator stations". The second area is called "control stations". The distinction between the two is based on relative direction from the facility and distance. Analysis of survey data from the two zones aids in determining if there is a. sigRificant difference between the two areas. It can also help in differentiating between radioactivity or radiation due to releases and that due to other fluctuations in the environment, such as seasonal variations in the natural background. MY 2015 Annual REO Report Page 7of28 3.2 Pathways Monitored Based on the design of the ISFSI, only the direct radiation exposure pathway is monitored by the REMP. This pathway is monitored by the collection of thermoluminescent dosimeters (TLDs}which are described in more detail below. 3.3 Description of Monitoring Program 3.3.1 Direct Radiation Direct gamma radiation exposure was continuously monitored during 2015. with the use of thermoluminescent dosimeters (TLDs). At each monitoring location, these TLDs are sealed in plastic bags and attached to an object such as a tree, fence or utility pole. The TLDs are posted and retrieved on a semi-annual basis. All TLDs are provided and processed by a National Voluntary Laboratory Accreditation Program (NVLAP) certified vendor. The TLDs are placed at various locations around the Independent Spent Fuel Storage Installation (ISFSI). Table 3.2 lists the Station ID Codes, distances and direction of the TLDs from the ISFSL 3.3.2 Special Monitoring Special samples can be taken that are not required in the ODCM. The sample locations do not appear in Table 3.1 or 3.2 of this report. For this monitoring period, no special samples were collected as part of the Maine Yankee ISFSI Radiological Environmental Monitoring Program. MY 2015 Annual REO Report Page 8of28 Table 3.1 Radiological Environmental Monitoring Program Exposure Collection Analysis Pathway Number of Routine and/or Collection Analysis Analysis Sample Sample Sampling Frequency Type Frequency Media Locations Mode Direct Total Continuous Semi-Gamma Semi-Radiation Locations: 1 0 annual dose annual (TLD) (9 around perimeter of the site and 1 offsite control location) MY 2015 Annual REO Report Page 9of28 Table 3.2 Radiological Environmental Monitoring Locations Station Distance Direction Station Description Zone . Code From ISFSI From ISFSI (km) TL-1-02 Spent Fuel Storage (I)** 1 <0.28 N TL-1-04 Spent Fuel Storage (I)** 1 < 0.28 NE TL-1-06 Spent Fuel Storage (I)** 1 < 0.28 E TL-1-08 Spent Fuel Storage (I)** 1 <0.28 SE TL-1-10 Spent Fuel Storage (I)** 1 < 0.28 s TL-1-12 Spent Fuel Storage (I)** 1 < 0.28 SW TL-1-14 Spent Fuel Storage (I)** 1 < 0.28 w TL-1-15 Spent Fuel Storage (I)** 1 < 0.28 WNW TL-1-16 Spent Fuel Storage (I)** 1 < 0.28 NW TL-0-36 *Wiscasset Fire Station (0) 2 5.2 NW *2 =Control TLD; 1 =Indicator TLD **I = Inner Ring TLD; 0 = Outer Ring TLD MY 2015 Annual REO Report Page 10 of 28 Figure 3.1 Radiological Environmental Monitoring Locations (within 0.28 km) LITTLE OAK ISLAND Moine Yankee ISFSI SITE Plan with 25 nramlyr Boundary Baseo on 8760 Har Annuo I Oecwaney MY 2015 Annual REO Report CIUPHIC SCALE: Page 11 of 28 Figure 3.2 Direct Radiation Monitoring Locations (outside 1 km) MY 2015 Annual REO Report Page 12 of 28 4.0 RADIOLOGICAL DATA SUMMARY TABLES This section summarizes the analytical results of the environmental samples, which were collected during the monitoring period.

  • Data from direct radiation measurements made by TLDs are presented in Table 4.1.
  • The summarized TLD measurements, shown in Table 4.2, are presented in a forrriat similar to that prescribed in the NRC's Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 1 ).
  • Table 4.3 presents the estimated direct dose from ISFSI operations as determined by TLD data shown in Table 4.1. MY 2015 Annual REO Report Page 13 of 28 Table 4.1 TLD Measurements by Half-Year (mR} Station ID Direction 1st Half-Year 2nd Half-Year TL-1-02 N 42 51 TL-1-04 NE 39 43 TL-1-06 E 61 69 TL,.1-08 SE 45 51 TL-1-10 s 46 56 TL-1-12 . SW 44 55 TL-1-14 w 55 54 TL-1-15 WNW 50 51 TL-1-16 NW 45 58 TL-0-36 Control 44 49 TL-0-36a Control Backup. 46 51 MY 2015 Annual REO Report Page 14 of 28 Indicator TLDs Mean (Range) (No. Measurements)* 50.8 (39 -69) (18) Table 4.2 TLD Data Summary {mR) Co.ntrol TLDs Indicator Station With Highest Mean Mean Mean (Range) Station# (Range) (No. Measurements)* (No. Measurements)* 47.5 TL-1-06 65.0 (44-51) (61 -69) (4) (2)
  • Each "measurement" is based on semi-annual readings. MY 2015 Annual REO Report Page 15 of28 Station ID TL-1-02 TL-1-04 TL-1-06 TL-1-08 TL-1-10 TL-1-12 TL-1-14 TL-1-15 TL-1-16 Note: Table 4.3 Direct Dose from ISFSI Operations (mrem) 1st Half-Year 2"d Half-Year NetTLD Calculated Net TLD Calculated Result Dose Result Dose 0.00 0.00 1.00 0.04 0.00 0.00 0.00 0.00 16.00 0.59 19.00 0.70 0.00 0.00 1.00 0.04 1.00 0.04 6.00 0.22 0.00 0.00 5.00 0.19 10.00 0.37 4.00 0.15 5.00 0.19 1.00 0.04 0.00 0.00 8.00 0.30 Max Dose=> Annual Dose 0.04 0.00 1.30 0.04 0.26 0.19 0.52 0.22 0.30 1.30 Doses based on a 162.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> occupancy in both of the first and second half-years. MY 2015 Annual REO Report Page 16 of 28 Radiological Environmental Monitoring Program Trending A series of graphs of REMP TLD data have been developed and are provided for trending purposes. The trending is developed for each of the indicator locations based on the annual historical doses. The trending is provided for the "real members of the public" based on the guidance provided in the ODCM. The analysis of the trends and ' associated data shows very small annual doses with minor fluctuations in the data. In this report, the uncorrected TLD results have been summarized and the annual doses, calculated for "real members of the public" based upon guidance in the ODCM, have been plotted for trending. MY 2014 Annual REO Report Page 17 of 28 0 Figure 4.1 Annual Dose Trend at TL-1-02 TL-1-02 30.00 -.---------------------25.00 +------------------------20.00 -15.00 +----------------------... -+-TL-1-02 E 10.00 +------------------------limit 5.00 0.00 ........ --.....,,----------, 2007 2008 2009 2010 2011 2012 2013 2014 2015 Year Annual Doses (mrem/yr) Location 2007 2008 2009 2010 2011 2012 2013 2014 2015 TL-1-02 0.17 0.55 0.08 0.30 0.00 0.14 0.07 0.00 0.04 MY 2014 Annual REO Report Page 18 of 28 Figure 4.2 Annual Dose Trend at TL-1-04 c TL-1-04 30.00 25.00 !;. 20.00 -15.00 ...,._TL-1-04 ... E 10.00 -=-limit 5.00
  • A .. 0.01 0.12 0.10 0.09 0.13 0.06 0.00 0.00 0.00 2007 2008 2009 2010 2011 2012 2013 2014 2015 Year Annual Doses (mrem/yr) Location 2007 2008 2009 2010 2011 2012 2013 2014 2015 TL-1-04 0.01 0.12 0.10 1.45 0.09 0.13 0.06 0.00 0.00 MY 2014 Annual REO Report Page 19of28 Cl Figure 4.3 Annual Dose Trend at TL-1-06 TL-1-06 30.00 25.00 +-----------------------20.00 -15.00 +----------------------... -+-TL-1-06 E 10.00 -i----------------------5.00 H::-21:---1..,98 2 04 1.65 1 74 0.00 .....,._limit 1.6-5--1:+/-5--(T,99-1:-;3-8-2007 2008 2009 2010 2011 2012 2013 2014 2015 Vear Annual Doses (mrem/yr) Location 2007 2008 2009 2010 2011 2012 2013 2014 2015 TL-1-06 1.21 1.68 2.04 1.65 1.74 1.65 1.15 0.99 1.30 MY 2014 Annual REO Report Page 20 of 28 0 Figure 4.4 Annual Dose Trend at TL-1-08 TL-1-08 30.00 ......----------------------25.00 +-----------------------!;. 20.00 -15.00 +----------------------... -¢-TL-1-08 E 10.00 +-----------------------limit 5.00 -i--,U....,,j..--!:>--n-. U. /n-U"""'U ...... /.,...._ /-n--U-0.,.....0..,..4,.....-""'0""'.2"""o-0..,.. . ..,..04.,..-0.00 2007 2008 2009 2010 2011 2012 2013 2014 2015 Year Annual Doses (mrem/yr) Location 2007 2008 2009 201 O 2011 2012 2013 2014 2015 TL-1-08 0.35 0.70 0.38 0.70 0.48 0.70 0.04 0.26 0.04 MY 2014 Annual REO Report Page 21of28 Cl Figure 4.5 Annual Dose Trend at TL-1-10 TL-1-10 30.00 -.---------------------25.00 ;-----------------------!>. 20.00 -15.00 +----------------------... .....,_TL-1-10 E 10.00 +-----------------------limit 5.00 0.00 2007 2008 2009 2010 2011 2012 2013 2014 2015 Year Annual Doses (mrem/yr) Location 2007 2008 2009 201 O 2011 2012 2013 2014 2015 TL-1-10 0.48 0.49 0.26 0.85 0.53 0.41 0.23 0.21 0.26 MY 2014 Annual REO Report Page 22of28 0 Figure 4.6 Annual Dose Trend at TL-1-12 TL-1-12 30.00 ....---------------------25.00 +---------------------20.00 -15.00 +---------------------... ....,_TL-1-12 E 10.00 +---------------------=-limit 5.00 0.05 u.19 0.10 0.61 0.25 0.41 0.13 CJ.80 0.19 0.00 2007 2008 2009 2010 2011 2012 2013 2014 2015 Year Annual Doses (mrem/yr) Location 2007 2008 2009 2010 2011 2012 2013 2014 2015 TL-1-12 0.05 0.79 0.10 0.61 0.25 0.41 0.13 0.80 0.19 MY 2014 Annual REO Report Page 23of28 c Figure 4.7 Annual Dose Trend at TL-1-14 TL-1-14 30.00 25.00 -t----------------------!;.. 20.00 -15.00 -!---------------------... E 10.00 +----------------------limit 5.00 0.30 0.55 0.23 0.40 0.67 0.22 0.28 0.37 0.52 0.00 2007 2008 2009 2010 2011 2012 2013 2014 2015 Year Annual Doses (mrem/yr) Location 2007 2008 2009 2010 2011 2012 2013 2014 2015 TL-1-14 0.30 0.55 0.23 0.40 0.67 0.22 0.28 0.37 0.52 MY 2014 Annual REO Report Page 24of28 0 Figure 4.8 Annual Dose Trend at TL-1-15 TL-1-15 30.00 25.00 +-----------------------5. 20.00 -15.00 +--------------------... '""4-TL-1-15 E 10.00 +---------------------limit 5 .oo o .oo 2007 2008 2009 2010 2011 2012 2013 2014 2015 Year Annual Doses (mrem/yr) Location 2007 2008 2009 201 O 2011 2012 2013 2014 2015 TL-1-15 0.30 0.67 0.76 0.87 0.57 0.66 0.50 0.41 0.22 MY 2014 Annual REO Report Page 25of28 c Figure 4.9 Annual Dose Trend at TL-1-16 TL-1-16 30.00 ...----------------------25.00 +----------------------!;. 20.00 -15.00 -!----------------------... E 10.00 +----------------------limit 5.oo ...... o.oo 2007 2008 2009 2010 2011 2012 2013 2014 2015 year Annual Doses (mrem/yr) Location 2007 2008 2009 2010 2011 2012 2013 2014 2015 TL-1-16 0.44 0.77 0.36 0.89 0.66 0.45 0.34 0.59 0.30 MY 2014 Annual REO Report Page 26of28 5.0 ANALYSIS OF ENVIRONMENTAL RES UL TS 5.1 Sampling Program Deviations A sampling program deviation is defined as samples that are unobtainable due to hazardous conditions or to malfunction of sampling equipment. Such deviations do not compromise the program's effectiveness and in fact are considered insignificant with respect to what is normally anticipated for this Radiological Environmental Monitoring Program. There were two deviations of the sampling program in 2015. 1. The TLD at location TL-1-06 was not found for retrieval at the end of the first half of the year .. A condition report was written to document the finding. A follow-up investigation the next day located the missing TLD. The TLD was then sent in for processing. 2. Results from TL-1-14 were missing from the first half 2015 report from the vendor. Two condition reports were written to document the finding. The subsequent investigation concluded that the TLD was not lost but simply not included in the shipment to the vendor for processing. The TLD was then sent in for processing. 5.2 Direct Radiation Pathway 5.2.1 Annual Dose Trends Direct radiation is continuously measured at 9 indicator locations surrounding the Maine Yankee ISFSI, along with 1 control location (Wiscasset Fire Station) using thermoluminescent dosimeters (TLDs). These dosimeters are collected every six months for readout at the NVLAP certified dosimetry services vendor. Review of the data in Figures 4.1 through 4.9 shows no significant difference in annual doses over time at the indicator locations and their relation to the 25 mrem/yr limit. 5.2.2 Direct Doses from ISFSI Operations A dose estimate is the potential dose to any real member of the public that could use portions of the site or be present adjacent to the site for recreational activities MY 2014 Annual REO Report Page 27of28 throughout the year. Direct exposure above background can be estimated by subtracting the average TLD value of the control station from the indicator location measurements. As in previous years, the 2015 dose estimate assumes a total of 325 hours0.00376 days <br />0.0903 hours <br />5.373677e-4 weeks <br />1.236625e-4 months <br /> occupancy for the dose calculation; of which 162.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> are used in both the first and second half-years. The most likely location for exposure to a member of the public from the ISFSI is along the Back River, Bailey Cove or Montsweag Bay for boating and fishing and the mud flats in the Cove or Bay exposed at low tides which is worked by clam diggers and worm diggers; however, the time estimates are conservatively applied to all monitoring locations. Table 4.3 presents the results of the dose calculations. The highest calculated dose is at Station ID number TL-1-06. The maximum calculated annual dose at that location is 1.30 mrem. This value is only 5 percent of the 25 mrem per year limit. It is noted that most of the mud flat region in Bailey Cove that is used by the public is situated further away from this Station. As a result, actual exposures from direct radiation would be much less than the maximum calculated value.

6.0 REFERENCES

1. USNRC Radiological Assessment Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979. 2. Maine Yankee Offsite Dose Calculation Manual, Revision 36. 3. 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation". 4. 10 CFR Part 72.104, "Criteria for Radioactive Materials in Effluents and Direct Radiation from an ISFSI or MRS". MY 2014 Annual REO Report Page 28 of 28 MAINE YANKEE 321 Old Ferry Road, Wiscasset; Maine 04578 April 20, 2016 OMY-16-021 10 CFR 50.4 and 10 CFR 50.36a(a)(2) ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 -0001 Maine Yankee Atomic Power Company Maine Yankee Independent Spent Fuel Storage Installation NRC License No. DPR-36 CNRC Docket No. 50-309)

Subject:

Annual Radioactive Effluent Release Report, Annual Radiological Environmental Operating Report, and Changes to the Off-Site Dose Calculation Manual for 2015 10 CFR 50.36a(a)(2), Section 2)b) of Appendix C of the Maine Yankee Atomic Power Company (Maine Yankee) Quality Assurance Program (QAP) for the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) and Section 2 of Appendix A of the Off-Site Dose Calculation Manual (ODCM) for the Maine Yankee ISFSI require Maine Yankee to submit an Annual Radioactive Effluent Release Report. Enclosure 1 provides the report for the period of January 1 through December 31, 2015. Section 2)a) of Appendix C of the Maine Yankee QAP for the Maine Yankee ISFSI and Section 1 of Appendix A of the ODCM for the Maine Yankee ISFSI require the submittal of an Annual Radiological Environmental Operating Report. Enclosure 2 provides the report for the period ofJanuary 1 through December 31, 2015. Section l)c)(4) of Appendix C of the Maine Yankee QAP for the Maine Yankee ISFSI requires that any changes to the ODCM to be submitted as part of or concurrent with the Annual Radiological Environmental Operating Report. No revisions to the Maine Yankee ISFSI ODCM were issued in 2015. If you have any questions regarding this submittal, please do not hesitate to contact me at (207) 882-1303. Respectfully, / iSFsr Manager Maine Yankee Atomic Power Company OMY-16-021/April 20, 2016/Page 2

Enclosures:

1. Maine Yankee Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report, January-December 2015. 2. Maine Yankee Independent Spent Fuel Storage Installation, Annual Radiological Environmental Operating Report, January-December 2015. cc: D. Dorman, NRC Region I Administrator R. Powell, Chief, Decommissioning Branch, NRC, Region 1 J. Goshen, NRC Project Manager P. J. Dostie, SNSI, State of Maine J. Hyland, State of Maine ENCLOSURE 1 MAINE YANKEE INDEPENDENT SPENT FUEL STORAGE INSTALLATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -DECEMBER 2015 OMY-16-021 MAINE YANKEE INDEPENDENT SPENT FUEL STORAGE INSTALLATION License Nos. DPR-36 and SFGL-14 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January -December 2015 Radiation &toty & Control Services April 2016 Prepared by: Radiation Safety & Control Services 91 Portsmouth Avenue Stratham, NH 03885-2468 EXECUTIVE SUMMARY Tables 1 and 2 summarize the quantity of radioactive gaseous and liquid effluents, respectively, for each quarter of 2015. There were no gaseous or liquid releases in 2015. Table 3 summarizes waste shipped off-site for disposal for each half year of 2015. There was no waste shipped for disposal in 2015. Appendices A and B indicate the status of reportable items per the requirements of the Off-site Dose Calculation Manual (ODCM). There were no reportable items in 2015. Appendix C presents any changes in the ODCM. The ODCM was not revised in 2015. MY 2015 Annual RER Report Page 2 of 15 Table 1 MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2015 Gaseous Effluents-Summation of All Releases Nuclides Released
  • Units 1st 2nd 3rd .. 4th Quarter* *.Quarter Quarter Quarter A. Fission and Activation Gases .... . ,;. *"'. '* .. ;. Total Release Ci N/A* N/A* N/A* N/A* Average release rate µCi/s N/A* N/A* N/A* N/A* Percent of regulatory limit % N/A* N/A* N/A* N/A* B. Iodines ,... * .. ;;c .... M. ..... :* * '.p..' . ,._, .*' ... J,_<r.:.. ' .. Total Iodines released Ci N/A* N/A* N/A* N/A* Average release rate µCi/s N/A* N/A* N/A* N/A* Percent of regulatory limit % N/A* N/A* N/A* N/A* C .. Particulates ... ' '.?f * . ' .:-;* < :-. ;.-,_' .. *-.. ' ' Particulates Released Ci N/A* N/A* N/A* N/A* Averaqe release rate µCi/s N/A* N/A* N/A* N/A* Percent of requlatory limit % N/A* N/A* N/A* N/A* Gross alpha radioactivity Ci N/A* N/A* N/A* N/A* ... .. . .*. . , .. "* . Error .. -I N/A* .. N/A* -:* N/A* ., ' D. Tritium .* -: ; :.*_.. ,: *. : ?:./ >"i *;:*.'{* . _,, "" I*-"._ *' J.. ' -"i r. * . V, .?.' . ,.;:._, , -.* .. . -.. .* *-.: Total release Ci N/A* N/A* N/A* N/A* N/A* Average release rate µCi/s N/A* N/A* N/A* N/A* Percent of regulatory limit % N/A* N/A* N/A* N/A* *-N/A*= Not Applicable There are no gaseous effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) MY 2015 Annual RER Report Page 3 of 15 Table 1A MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2015 Gaseous Effluents -Ground Level Releases -Batch Mode Nuclides Released s pton-85 Ci N/A* N/A* N/A* N/A* N/A* Kr ton-85m Ci N/A* N/A* N/A* N/A* N/A* Kr pton-87 Ci N/A* N/A* N/A* N/A* N/A* K pton-88 Ci N/A* N/A* N/A* N/A* N/A* Xenon-133 Ci N/A* N/A* N/A* N/A* N/A* Xenon-135 Ci N/A* N/A* N/A* N/A* N/A* Xenon-135m Ci N/A* N/A* N/A* N/A* N/A* Xenon-138 Ci N/A* N/A* N/A* N/A* N/A* Unidentified Ci N/A* N/A* N/A* N/A* N/A* Total for period Ci N/A* N/A* N/A* N/A* N/A* *_ . -. c-. __ ,_ -** -.. --.-... --.* lodine-131 Ci N/A* N/A* N/A* N/A* N/A* lodine-133 Ci N/A* N/A* N/A* N/A* N/A* lodine-135 Ci N/A* N/A* N/A* N/A* N/A* Total for period Ci N/A* N/A* N/A* N/A* N/A* . *,:i ':' '"" ;(' ' .. -----. -. ---' -,,. --. r, -_,*_,, .. . . . -. ----L ... Strontium-89 Ci N/A* N/A* N/A* N/A* N/A* Strontium-90 Ci N/A* N/A* N/A* N/A* N/A* Cesium-134 Ci N/A* N/A* N/A* N/A* N/A* Cesium-137 Ci N/A* N/A* N/A* N/A* N/A* Cobalt-60 Ci N/A* N/A* N/A* N/A* N/A* Barium-Lanthanum-140 Ci N/A* N/A* N/A* N/A* N/A* Others-Plutonium-238 Ci N/A* N/A* N/A* N/A* N/A* Curium-243,244 Ci N/A* N/A* N/A* N/A* N/A* Uranium-234 Ci N/A* N/A* N/A* N/A* N/A* Uranium-238 Ci N/A* N/A* N/A* N/A* N/A* Thorium-232 Ci N/A* N/A* N/A* N/A* N/A* Radium-226 Ci N/A* N/A* N/A* N/A* N/A* N/A*= Not Applicable There are no gaseous effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) MY 2015 Annual RER Report Page 4 of 15 -. *-

Table 18 MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2015 Gaseous Effluents -Ground Level Releases -Continuous Mode Nuclides Released pton-85 NIA* NIA* NIA* pton-85m NIA* NIA* NIA* NIA* ton-87 NIA* NIA* NIA* NIA* ton-88 NIA* NIA* NIA* NIA* Xenon-133 NIA* NIA* NIA* NIA* Xenon-135 NIA* NIA* NIA* NIA* Xenon-135m NIA* NIA* NIA* NIA* NIA* Xenon-138 Ci NIA* NIA* NIA* NIA* NIA* Unidentified Ci NIA* NIA* NIA* NIA* NIA* Total for period Ci NIA* NIA* NIA* NIA* NIA* a ir.oXHliW.:3 _ -* * *-r ...., ...,, -1 , * -" * ' ... . _* ... ...... ;..:. ___ .. -..... * ._ ___ --.... -------. lodine-131 Ci NIA* NIA* NIA* NIA* NIA* lodine-133 Ci NIA* NIA* NIA* NIA* NIA* lodine-135 Ci NIA* NIA* NIA* NIA* NIA* Total for period Ci NIA* NIA* NIA* NIA* NIA* :.;. I fu\Q . .. . --,. ... -.. ., ... -------. ----,, . Strontium-89 Ci NIA* NIA* NIA* NIA* NIA* Strontium-90 Ci NIA* NIA* NIA* NIA* NIA* Cesium-134 Ci NIA* NIA* NIA* NIA* NIA* Cesium-137 Ci NIA* NIA* NIA* NIA* NIA* Cobalt-60 Ci NIA* NIA* NIA* NIA* NIA* Barium-Lanthanum-140 Ci NIA* NIA* NIA* NIA* NIA* Others-Plutonium-238 Ci NIA* NIA* NIA* NIA* NIA* Curium-243,244 Ci NIA* NIA* NIA* NIA* NIA* Uranium-234 Ci NIA* NIA* NIA* NIA* NIA* Uranium-238 Ci NIA* NIA* NIA* NIA* NIA* Thorium-232 Ci NIA* NIA* NIA* NIA* NIA* Radium-226 Ci NIA* NIA* NIA* NIA* NIA* NIA*= Not Applicable There are no gaseous effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) MY 2015 Annual RER Report Page 5of15 ' '

Table 1C MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2015 Gaseous Effluents -Elevated Releases -Batch Mode Nuclides Released N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* Xenon-133 N/A* N/A* N/A* N/A* Xenon-135 N/A* N/A* N/A* N/A* Xenon-135m N/A* N/A* N/A* N/A* N/A* Xenon-138 Ci N/A* N/A* N/A* N/A* N/A* Unidentified Ci N/A* N/A* N/A* N/A* N/A* Total for period Ci N/A* N/A* N/A* N/A* N/A* _* :_ --,_......._. ; *--. -* -. ... -. . -. -. -.. .. -; -.. *-. __ -jL lodine-131 Ci N/A* N/A* N/A* N/A* N/A* lodine-133 Ci N/A* N/A* N/A* N/A* N/A* lodine-135 Ci N/A* N/A* N/A* N/A* N/A* Total for period Ci N/A* N/A* N/A* N/A* N/A* *1 . . . " . .v-,iv,*M' *---" Strontium-89 Ci N/A* N/A* N/A* N/A* N/A* Strontium-90 Ci N/A* N/A* N/A* N/A* N/A* Cesium-134 Ci N/A* N/A* N/A* N/A* N/A* Cesium-137 Ci N/A* N/A* N/A* N/A* N/A* Cobalt-60 Ci N/A* N/A* N/A* N/A* N/A* Bari um-Lanthanum-140 Ci N/A* N/A* N/A* N/A* N/A* Others-Plutonium-238 Ci N/A* N/A* N/A* N/A* N/A* Curium-243,244 Ci N/A* N/A* N/A* N/A* N/A* Uranium-234 Ci N/A* N/A* N/A* N/A* N/A* Uranium-238 Ci N/A* N/A* N/A* N/A* N/A* Thorium-232 Ci N/A* N/A* N/A* N/A* N/A* Radium-226 Ci N/A* N/A* N/A* N/A* N/A* N/A*= Not Applicable There are no gaseous effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) MY 2015 Annual RER Report Page 6of15 :

Table 10 MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2015 Gaseous Effluents -Elevated Releases -Continuous Mode Nuclides Released N/A* N/A* N/A* ton-85m N/A* N/A* N/A* N/A* N/A* N/A* Ci 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* N/A* Xenon-135m Ci N/A* N/A* N/A* N/A* N/A* Xenon-138 Ci N/A* N/A* N/A* N/A* N/A* Unidentified Ci N/A* N/A* N/A* N/A* N/A* Total for period Ci N/A* N/A* N/A* N/A* N/A* _ .. __ .... --:.: ... ' **--.. ___ . * *_. ** J_ lodine-131 Ci N/A* N/A* N/A* N/A* N/A* lodine-133 Ci N/A* N/A* N/A* N/A* N/A* lodine-135 Ci N/A* N/A* N/A* N/A* N/A* Total for period Ci N/A* N/A* N/A* N/A* N/A* Strontium-89 Ci N/A* N/A* N/A* N/A* N/A* Strontium-90 Ci N/A* N/A* N/A* N/A* N/A* Cesium-134 Ci N/A* N/A* N/A* N/A* N/A* Cesium-137 Ci N/A* N/A* N/A* N/A* N/A* Cobalt-60 Ci N/A* N/A* N/A* N/A* N/A* Barium-Lanthanum-140 Ci N/A* N/A* N/A* N/A* N/A* Others-Plutonium-238 Ci N/A* N/A* N/A* N/A* N/A* Curium-243,244 Ci N/A* N/A* N/A* N/A* N/A* Uranium-234 Ci N/A* N/A* N/A* N/A* N/A* Uranium-238 Ci N/A* N/A* N/A* N/A* N/A* Thorium-232 Ci N/A* N/A* N/A* N/A* N/A* Radium-226 Ci N/A* N/A* N/A* N/A* N/A* N/A*= Not Applicable There are no gaseous effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) MY 2015 Annual RER Report Page 7 of 15 Table 2 MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2015 Liquid Effluents -Summation of All Releases Nuclides Released Unit * *2nd . * ** *. 3rd Quarter . . ,_., *-***** Quarter-.: Quarter. A. Fission and Activation Products Total Release (not including Ci N/A* N/A* N/A* tritium, Qases, alpha) Average diluted concentration µCi/ml N/A* N/A* N/A* during period Percent of applicable limit % N/A* N/A* N/A* 8. Tritium Total Release Ci N/A* N/A* N/A* Average diluted concentration µCi/ml N/A* N/A* N/A* during period Percent of applicable limit % N/A* N/A* N/A* C. Dissolved and Entrained Gases Total Release Ci N/A* N/A* N/A* Average diluted concentration µCi/ml N/A* N/A* N/A* during period Percent of applicable limit % N/A* N/A* N/A* D. Gross Alpha Radioactivity Total release Ci N/A* N/A* N/A* Average diluted concentration µCi/ml N/A* N/A* N/A* during period E. Volume of Waste Released Liters N/A* N/A* N/A* (prior to dilution) F. Volume of Dilution Water Liters N/A* N/A* N/A* Used During Period N/A*= Not Applicable ***4th Error "Quarter N/A* N/A* N/A* N/A* . N/A* N/A* N/A* . N/A* N/A* N/A* N/A* .{ N/A* .**t:.: N/A* N/A* N/A* N/A* N/A* ' : ';,:_ There are no liquid effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) MY 2015 Annual RER Report Page 8 of 15 Table 2A MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2015 Liquid Effluents -Batch Mode NuFliaes. * , 1: . ; *.::.

  • f_nd: * ** . ** .\;. * . 't'ZY' Quarter Strontium-89 Strontium-90 Cesium-134 Cesium-137 lodine-131 Cobalt-58 Cobalt-60 lron-59 Zinc-65 ManQanese-54 Chromium-51 Zirconium-Niobium-95 Molybdenum-99 Technetium-99m Barium-Lathanium-140 Cerium-141 Others-lron-55 Antimony-125 Unidentified Total for period (above) Dissolved and Entrained Gasses Tritium Gross Alpha N/A*= Not Applicable Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* Ci N/A* N/A* ,, , 3rd Quarter* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A*

N/A* N/A*

N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* , 4th Totals 14 ' *' N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* N/A* There are no liquid effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) MY 2015 Annual RER Report Page 9 of 15 I Nuclides Released ,ti: -Strontium-89 Strontium-90 Cesium-134 Cesium-137 lodine-131 Cobalt-58 Cobalt-60 lron-59 Zinc-65 Manganese-54 Chromium-51 Zirconium-Niobium-95 Molybdenum-99 Technetium-99m Barium-Lathanium-140 Cerium-141 Others-lron-55 Antimony-125 Unidentified Total for period (above) Dissolved and Entrained Gasses Tritium Gross Alpha Table 28 MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2015 Liquid Effluents -Continuous Mode Unit 1st* 2nd 3rd Quarter Quarter Quarter ' Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* Ci NIA* NIA* NIA* NIA*= Not Applicable 4th Totals * ' _Quader* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* NIA* There are no liquid effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) MY 2015 Annual RER Report Page 10 of 15 Table 3 MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report First Half 2015 Low Level Waste Shipments Resins, Filters and Evaporator Bottoms Volume Waste Class Solidifying Agent ft,j m,j A 0 0 B 0 0 c 0 0 All 0 0 Major radionuclides for above data: ' Dry Active Waste Volume Waste Class Solidifying Agent ft3 m3 A 0 0 B 0 0 c 0 0 All 0 0 Major radionuclides for above data: Irradiated Components Volume >: ,.. . Waste Class Solidifying Agent ft3 m3 A 0 0 B 0 0 c 0 0 All 0 0 Major radionuclides for above data: *. *. * .. ' .. Other Waste Volume . ' .. Waste Class Solidifying Agent ft,j m,j A 0 0 B 0 0 c 0 0 All 0 0 Major radionuclides for above data: MY 2015 Annual RER Report ! Curies Shipped Curies 0 0 0 0 Curies Shipped Curies 0 0 0 0 Curies Shipped Curies 0 0 0 0 Curies' *. Shipped Curies 0 0 0 0 Page 11 of 15 Table 3A MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report Second Half 2015 Low Level Waste Shipments Resins, Filters and Evaporator Volume Bottoms Waste Class Solidifying Agent ft3 m3 A 0 0 B 0 0 c 0 0 All 0 0 Major radionuclides for above data: . " ,, Dry Active Waste ' Volume0 ' . iF . Waste Class Solidifying Agent ft3 m3 A 0 0 B 0 0 c 0 0 All 0 0 Major radionuclides for above data: : . , . ,volume ., . > -*S5"* , , *. ,* *:" I>:' . *-" Waste Class Solidifying Agent ft3 m3 A 0 0 B 0 0 c 0 0 All 0 0 Major radionuclides for above data: 0the.r Waste . .. ."'.:' ,.,,. Volume ,* .. ,,. ... , ,* **,' .. ;_: ... ..,. (; .,. -. Waste Class Solidifying Agent ft3 m3 A 0 0 B 0 0 c 0 0 All 0 0 Major radionuclides for above data: MY 2015 Annual RER Report Curies Shipped* Curies 0 0 0 0 Curies Shipped .,, Curies 0 0 0 0 Curies , Shipped . ' Curies 0 0 0 0 Curies Shipped Curies 0 0 0 0 Page 12 of 15 Appendix A Radiation Dose Assessment There were no gaseous or liquid effluent releases in 2015. Therefore, an assessment of radiation doses to the most likely exposed member(s) of the public to show compliance with 40CFR190 or 1OCFR72.104 from effluents was not required. MY 2015 Annual RER Report Page 13of15 Appendix B Unplanned Releases There were no unplanned releases of radioactive materials from the site in 2015. MY 2015 Annual RER Report Page 14of15 Appendix C Off-site Dose Calculation Manual Changes There were no changes to the Off-site Dose Calculation Manual in 2015. MY 2015 Annual RER Report Page 15 of 15 OMY-16-021 ENCLOSURE2 MAINEY ANKEE INDEPENDENT SPENT FUEL STORAGE INSTALLATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY -DECEMBER 2015 MAINE YANKEE INDEPENDENT SPENT FUEL STORAGE INSTALLATION License Nos. DPR-36 and SFGL-14 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January -December 2015 Radiotion Safety & Controi Services April 2016 Prepared by: Radiation Safety & Control Services 91 Portsmouth Avenue Stratham, NH 03885-2468 EXECUTIVE SUMMARY The Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) has been in operation since 2001. All fuel has been transferred into dry storage casks and placed at the Independent Spent Fuel Storage Installation. The Radiological Environmental Monitoring Program (REMP) for the Maine Yankee ISFSI located in Wiscasset, ME was continued for the period January through December 2015 in compliance with the Maine Yankee Offsite Dose Calculation Manual (ODCM). By design, there are no liquid or gaseous effluents associated with the operation of the ISFSI. Therefore, the ODCM only requires monitoring of direct exposure from the facility. TLDs were used to measure direct gamma exposure at nine locations in the vicinity of the ISFSI and one control location 5.2 kilometers away. The results of these measurements showed no significant change in exposure rates and potential doses to members of the public during the monitoring period. The results of the monitoring performed in 2015 also show that operating the Maine Yankee ISFSI results in only a small fraction of the 40 CFR Part 190 and 1 O CFR Part 72.104 direct radiation dose limit of 25 mrem/year to members of the public. MY 2015 Annual REO Report Page 2of28 TABLE OF CONTENTS Section

1.0 INTRODUCTION

............................................................................................ 6 2.0 GENERAL ISFSI AND SITE INFORMATION ................................................ 7 3.0 PROGRAM DESIGN ............................................................. -......................... 7 3.1 MONITORING ZONES ........................................................................................... 7 3.2 PATHW_AYS MONITORED ...................................................................................... 8 3.3 DESCRIPTION OF MONITORING PROGRAM ............................................................ 8 4.0 RADIOLOGICAL DATA SUMMARY TABLES ............................. .............. 13 5.0 ANALYSIS OF ENVIRONMENTAL RES UL TS ............................................ 27 5.1 SAMPLING PROGRAM DEVIATIONS ..................................................................... 27 5.2 DIRECT RADIATION PATHWAY ............................................................................ 27

6.0 REFERENCES

............................................................................................. 28 MY 2015 Annual REO Report Page 3of28 LIST OF TABLES 3.1 Radiological Environmental Monitoring Program ..................................... 9 3.2 Radiological Environmental Monitoring* Locations ................................. 10 4.1 TLD Measurements by Half-Year ............................................................... 14 4.2 TLD Data Summary .................................................................................... 15 4.3 Direct Dose from ISFSI Operations ........................................................... 16 MY 2015 Annual REO Report Page 4 of 28 LIST OF FIGURES Figure 3.1 Radiological Environmental Monitoring Locations (within 0.28 km) ..... 11 3.2 Direct Radiation Monitoring Locations (outside 1 km) ........................... 12 4.1 Annual Dose Trend at TL-1-02 .................................................................... 18 4.2 Annual Dose Trend at TL-1-04 ..................................................................... 19 4.3 Annual Dose Trend at TL-1-06 .................................................................... 20 4.4 Annual Dose Trend at TL-1-08 .................................................................... 21 4.5 Annual Dose Trend at TL-1-10 .................................................................... 22 4.6 Annual Dose Trend at TL-1-12 .................................................................... 23 4.7 Annual Dose Trend at TL-1-14 .................................................................... 24 4.8 Annual Dose Trend at TL-1-15 .................................................................... 25 4.9 Annual Dose Trend at TL-1-16 .................................................................... 26 MY 2015 Annual REO Report Page 5of28

1.0 INTRODUCTION

This report summarizes the findings of the Radiological Environmental Monitoring Program (REMP) conducted by Maine Yankee in the vicinity of the Independent Spent Fuel Storage Installation in Wiscasset, Maine during the calendar year 2015. It is submitted annually in compliance with Appendix A, of the Offsite Dose Calculation Manual (ODCM). The remainder of this report is organized as . follows: Section 2: Provides a brief description of the Maine Yankee site and its environs. Section 3: Provides a description of the overall REMP design. Included is a summary of the requirements for REMP sampling, tables listing routine TLD monitoring locations with compass sectors and distances from the ISFSI, and maps showing the location of each of the TLD monitoring locations. Section 4: Provides a complete set of TLD data showing measured results (mR) and calculated doses (mrem per year). This section also provides the summarized exposure rate data in the format specified by the NRG Branch Technical Position on Environmental Monitoring (Reference 1 ). Section 5: Provides the results of the monitoring program. The performance of the program in meeting ODCM requirements is discussed, and the data acquired during the year is analyzed. Section 6: References MY 2015 Annual REO Report Page 6of28 2.0 GENERAL ISFSI AND SITE INFORMATION The Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) is located in the town of Wiscasset, Lincoln County, Maine, approximately six miles northeast of Bath, Maine. The site vicinity is rural and lightly populated. The ISFSI site is located near Bailey Point, a peninsula bounded to the east by the Back River and to the west by a shallow inlet known as Bailey Cove, both of which are part of the Montsweag Bay-Sheepscot River Estuary. Bailey point is an elongated bedrock ridge with flat or gently rolling topography rising to an average elevation of about 25 feet above sea level. The Radiological Environmental Monitoring Program (REMP) for the ISFSI began pre-operational measurements in the 4th quarter of 1999, approximately 2 years prior to the initial spent fuel transfer to the ISFSI. The ISFSI REMP has been in continuous operation since this transfer began. 3.0 PROGRAM DESIGN The Radiological Environmental M0nitoring Program (REMP) for the Maine Yankee ISFSI was designed to provide assurance to regulatory agencies and the public that the station's environmental impact is known and within anticipated limits. The direct dose limit for members of the public from operation of the ISFSI is 25 mrem per year (References 3 and. 4 ). The detailed sampling requirements of the REMP are given in the ODCM. The sampling requirements specified in the ODCM are summarized in Table 3.1 of this report. Details of the monitored locations are shown in Table 3.2, as well as Figures 3.1 and 3.2 of this report. 3.1 Monitoring Zones The REMP is designed to allow comparison of levels of radioactivity in samples from the area possibly influenced by the ISFSI to levels found in areas not influenced by the ISFSI. The first area is called "indicator stations". The second area is called "control stations". The distinction between the two is based on relative direction from the facility and distance. Analysis of survey data from the two zones aids in determining if there is a. sigRificant difference between the two areas. It can also help in differentiating between radioactivity or radiation due to releases and that due to other fluctuations in the environment, such as seasonal variations in the natural background. MY 2015 Annual REO Report Page 7of28 3.2 Pathways Monitored Based on the design of the ISFSI, only the direct radiation exposure pathway is monitored by the REMP. This pathway is monitored by the collection of thermoluminescent dosimeters (TLDs}which are described in more detail below. 3.3 Description of Monitoring Program 3.3.1 Direct Radiation Direct gamma radiation exposure was continuously monitored during 2015. with the use of thermoluminescent dosimeters (TLDs). At each monitoring location, these TLDs are sealed in plastic bags and attached to an object such as a tree, fence or utility pole. The TLDs are posted and retrieved on a semi-annual basis. All TLDs are provided and processed by a National Voluntary Laboratory Accreditation Program (NVLAP) certified vendor. The TLDs are placed at various locations around the Independent Spent Fuel Storage Installation (ISFSI). Table 3.2 lists the Station ID Codes, distances and direction of the TLDs from the ISFSL 3.3.2 Special Monitoring Special samples can be taken that are not required in the ODCM. The sample locations do not appear in Table 3.1 or 3.2 of this report. For this monitoring period, no special samples were collected as part of the Maine Yankee ISFSI Radiological Environmental Monitoring Program. MY 2015 Annual REO Report Page 8of28 Table 3.1 Radiological Environmental Monitoring Program Exposure Collection Analysis Pathway Number of Routine and/or Collection Analysis Analysis Sample Sample Sampling Frequency Type Frequency Media Locations Mode Direct Total Continuous Semi-Gamma Semi-Radiation Locations: 1 0 annual dose annual (TLD) (9 around perimeter of the site and 1 offsite control location) MY 2015 Annual REO Report Page 9of28 Table 3.2 Radiological Environmental Monitoring Locations Station Distance Direction Station Description Zone . Code From ISFSI From ISFSI (km) TL-1-02 Spent Fuel Storage (I)** 1 <0.28 N TL-1-04 Spent Fuel Storage (I)** 1 < 0.28 NE TL-1-06 Spent Fuel Storage (I)** 1 < 0.28 E TL-1-08 Spent Fuel Storage (I)** 1 <0.28 SE TL-1-10 Spent Fuel Storage (I)** 1 < 0.28 s TL-1-12 Spent Fuel Storage (I)** 1 < 0.28 SW TL-1-14 Spent Fuel Storage (I)** 1 < 0.28 w TL-1-15 Spent Fuel Storage (I)** 1 < 0.28 WNW TL-1-16 Spent Fuel Storage (I)** 1 < 0.28 NW TL-0-36 *Wiscasset Fire Station (0) 2 5.2 NW *2 =Control TLD; 1 =Indicator TLD **I = Inner Ring TLD; 0 = Outer Ring TLD MY 2015 Annual REO Report Page 10 of 28 Figure 3.1 Radiological Environmental Monitoring Locations (within 0.28 km) LITTLE OAK ISLAND Moine Yankee ISFSI SITE Plan with 25 nramlyr Boundary Baseo on 8760 Har Annuo I Oecwaney MY 2015 Annual REO Report CIUPHIC SCALE: Page 11 of 28 Figure 3.2 Direct Radiation Monitoring Locations (outside 1 km) MY 2015 Annual REO Report Page 12 of 28 4.0 RADIOLOGICAL DATA SUMMARY TABLES This section summarizes the analytical results of the environmental samples, which were collected during the monitoring period.

  • Data from direct radiation measurements made by TLDs are presented in Table 4.1.
  • The summarized TLD measurements, shown in Table 4.2, are presented in a forrriat similar to that prescribed in the NRC's Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 1 ).
  • Table 4.3 presents the estimated direct dose from ISFSI operations as determined by TLD data shown in Table 4.1. MY 2015 Annual REO Report Page 13 of 28 Table 4.1 TLD Measurements by Half-Year (mR} Station ID Direction 1st Half-Year 2nd Half-Year TL-1-02 N 42 51 TL-1-04 NE 39 43 TL-1-06 E 61 69 TL,.1-08 SE 45 51 TL-1-10 s 46 56 TL-1-12 . SW 44 55 TL-1-14 w 55 54 TL-1-15 WNW 50 51 TL-1-16 NW 45 58 TL-0-36 Control 44 49 TL-0-36a Control Backup. 46 51 MY 2015 Annual REO Report Page 14 of 28 Indicator TLDs Mean (Range) (No. Measurements)* 50.8 (39 -69) (18) Table 4.2 TLD Data Summary {mR) Co.ntrol TLDs Indicator Station With Highest Mean Mean Mean (Range) Station# (Range) (No. Measurements)* (No. Measurements)* 47.5 TL-1-06 65.0 (44-51) (61 -69) (4) (2)
  • Each "measurement" is based on semi-annual readings. MY 2015 Annual REO Report Page 15 of28 Station ID TL-1-02 TL-1-04 TL-1-06 TL-1-08 TL-1-10 TL-1-12 TL-1-14 TL-1-15 TL-1-16 Note: Table 4.3 Direct Dose from ISFSI Operations (mrem) 1st Half-Year 2"d Half-Year NetTLD Calculated Net TLD Calculated Result Dose Result Dose 0.00 0.00 1.00 0.04 0.00 0.00 0.00 0.00 16.00 0.59 19.00 0.70 0.00 0.00 1.00 0.04 1.00 0.04 6.00 0.22 0.00 0.00 5.00 0.19 10.00 0.37 4.00 0.15 5.00 0.19 1.00 0.04 0.00 0.00 8.00 0.30 Max Dose=> Annual Dose 0.04 0.00 1.30 0.04 0.26 0.19 0.52 0.22 0.30 1.30 Doses based on a 162.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> occupancy in both of the first and second half-years. MY 2015 Annual REO Report Page 16 of 28 Radiological Environmental Monitoring Program Trending A series of graphs of REMP TLD data have been developed and are provided for trending purposes. The trending is developed for each of the indicator locations based on the annual historical doses. The trending is provided for the "real members of the public" based on the guidance provided in the ODCM. The analysis of the trends and ' associated data shows very small annual doses with minor fluctuations in the data. In this report, the uncorrected TLD results have been summarized and the annual doses, calculated for "real members of the public" based upon guidance in the ODCM, have been plotted for trending. MY 2014 Annual REO Report Page 17 of 28 0 Figure 4.1 Annual Dose Trend at TL-1-02 TL-1-02 30.00 -.---------------------25.00 +------------------------20.00 -15.00 +----------------------... -+-TL-1-02 E 10.00 +------------------------limit 5.00 0.00 ........ --.....,,----------, 2007 2008 2009 2010 2011 2012 2013 2014 2015 Year Annual Doses (mrem/yr) Location 2007 2008 2009 2010 2011 2012 2013 2014 2015 TL-1-02 0.17 0.55 0.08 0.30 0.00 0.14 0.07 0.00 0.04 MY 2014 Annual REO Report Page 18 of 28 Figure 4.2 Annual Dose Trend at TL-1-04 c TL-1-04 30.00 25.00 !;. 20.00 -15.00 ...,._TL-1-04 ... E 10.00 -=-limit 5.00
  • A .. 0.01 0.12 0.10 0.09 0.13 0.06 0.00 0.00 0.00 2007 2008 2009 2010 2011 2012 2013 2014 2015 Year Annual Doses (mrem/yr) Location 2007 2008 2009 2010 2011 2012 2013 2014 2015 TL-1-04 0.01 0.12 0.10 1.45 0.09 0.13 0.06 0.00 0.00 MY 2014 Annual REO Report Page 19of28 Cl Figure 4.3 Annual Dose Trend at TL-1-06 TL-1-06 30.00 25.00 +-----------------------20.00 -15.00 +----------------------... -+-TL-1-06 E 10.00 -i----------------------5.00 H::-21:---1..,98 2 04 1.65 1 74 0.00 .....,._limit 1.6-5--1:+/-5--(T,99-1:-;3-8-2007 2008 2009 2010 2011 2012 2013 2014 2015 Vear Annual Doses (mrem/yr) Location 2007 2008 2009 2010 2011 2012 2013 2014 2015 TL-1-06 1.21 1.68 2.04 1.65 1.74 1.65 1.15 0.99 1.30 MY 2014 Annual REO Report Page 20 of 28 0 Figure 4.4 Annual Dose Trend at TL-1-08 TL-1-08 30.00 ......----------------------25.00 +-----------------------!;. 20.00 -15.00 +----------------------... -¢-TL-1-08 E 10.00 +-----------------------limit 5.00 -i--,U....,,j..--!:>--n-. U. /n-U"""'U ...... /.,...._ /-n--U-0.,.....0..,..4,.....-""'0""'.2"""o-0..,.. . ..,..04.,..-0.00 2007 2008 2009 2010 2011 2012 2013 2014 2015 Year Annual Doses (mrem/yr) Location 2007 2008 2009 201 O 2011 2012 2013 2014 2015 TL-1-08 0.35 0.70 0.38 0.70 0.48 0.70 0.04 0.26 0.04 MY 2014 Annual REO Report Page 21of28 Cl Figure 4.5 Annual Dose Trend at TL-1-10 TL-1-10 30.00 -.---------------------25.00 ;-----------------------!>. 20.00 -15.00 +----------------------... .....,_TL-1-10 E 10.00 +-----------------------limit 5.00 0.00 2007 2008 2009 2010 2011 2012 2013 2014 2015 Year Annual Doses (mrem/yr) Location 2007 2008 2009 201 O 2011 2012 2013 2014 2015 TL-1-10 0.48 0.49 0.26 0.85 0.53 0.41 0.23 0.21 0.26 MY 2014 Annual REO Report Page 22of28 0 Figure 4.6 Annual Dose Trend at TL-1-12 TL-1-12 30.00 ....---------------------25.00 +---------------------20.00 -15.00 +---------------------... ....,_TL-1-12 E 10.00 +---------------------=-limit 5.00 0.05 u.19 0.10 0.61 0.25 0.41 0.13 CJ.80 0.19 0.00 2007 2008 2009 2010 2011 2012 2013 2014 2015 Year Annual Doses (mrem/yr) Location 2007 2008 2009 2010 2011 2012 2013 2014 2015 TL-1-12 0.05 0.79 0.10 0.61 0.25 0.41 0.13 0.80 0.19 MY 2014 Annual REO Report Page 23of28 c Figure 4.7 Annual Dose Trend at TL-1-14 TL-1-14 30.00 25.00 -t----------------------!;.. 20.00 -15.00 -!---------------------... E 10.00 +----------------------limit 5.00 0.30 0.55 0.23 0.40 0.67 0.22 0.28 0.37 0.52 0.00 2007 2008 2009 2010 2011 2012 2013 2014 2015 Year Annual Doses (mrem/yr) Location 2007 2008 2009 2010 2011 2012 2013 2014 2015 TL-1-14 0.30 0.55 0.23 0.40 0.67 0.22 0.28 0.37 0.52 MY 2014 Annual REO Report Page 24of28 0 Figure 4.8 Annual Dose Trend at TL-1-15 TL-1-15 30.00 25.00 +-----------------------5. 20.00 -15.00 +--------------------... '""4-TL-1-15 E 10.00 +---------------------limit 5 .oo o .oo 2007 2008 2009 2010 2011 2012 2013 2014 2015 Year Annual Doses (mrem/yr) Location 2007 2008 2009 201 O 2011 2012 2013 2014 2015 TL-1-15 0.30 0.67 0.76 0.87 0.57 0.66 0.50 0.41 0.22 MY 2014 Annual REO Report Page 25of28 c Figure 4.9 Annual Dose Trend at TL-1-16 TL-1-16 30.00 ...----------------------25.00 +----------------------!;. 20.00 -15.00 -!----------------------... E 10.00 +----------------------limit 5.oo ...... o.oo 2007 2008 2009 2010 2011 2012 2013 2014 2015 year Annual Doses (mrem/yr) Location 2007 2008 2009 2010 2011 2012 2013 2014 2015 TL-1-16 0.44 0.77 0.36 0.89 0.66 0.45 0.34 0.59 0.30 MY 2014 Annual REO Report Page 26of28 5.0 ANALYSIS OF ENVIRONMENTAL RES UL TS 5.1 Sampling Program Deviations A sampling program deviation is defined as samples that are unobtainable due to hazardous conditions or to malfunction of sampling equipment. Such deviations do not compromise the program's effectiveness and in fact are considered insignificant with respect to what is normally anticipated for this Radiological Environmental Monitoring Program. There were two deviations of the sampling program in 2015. 1. The TLD at location TL-1-06 was not found for retrieval at the end of the first half of the year .. A condition report was written to document the finding. A follow-up investigation the next day located the missing TLD. The TLD was then sent in for processing. 2. Results from TL-1-14 were missing from the first half 2015 report from the vendor. Two condition reports were written to document the finding. The subsequent investigation concluded that the TLD was not lost but simply not included in the shipment to the vendor for processing. The TLD was then sent in for processing. 5.2 Direct Radiation Pathway 5.2.1 Annual Dose Trends Direct radiation is continuously measured at 9 indicator locations surrounding the Maine Yankee ISFSI, along with 1 control location (Wiscasset Fire Station) using thermoluminescent dosimeters (TLDs). These dosimeters are collected every six months for readout at the NVLAP certified dosimetry services vendor. Review of the data in Figures 4.1 through 4.9 shows no significant difference in annual doses over time at the indicator locations and their relation to the 25 mrem/yr limit. 5.2.2 Direct Doses from ISFSI Operations A dose estimate is the potential dose to any real member of the public that could use portions of the site or be present adjacent to the site for recreational activities MY 2014 Annual REO Report Page 27of28 throughout the year. Direct exposure above background can be estimated by subtracting the average TLD value of the control station from the indicator location measurements. As in previous years, the 2015 dose estimate assumes a total of 325 hours0.00376 days <br />0.0903 hours <br />5.373677e-4 weeks <br />1.236625e-4 months <br /> occupancy for the dose calculation; of which 162.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> are used in both the first and second half-years. The most likely location for exposure to a member of the public from the ISFSI is along the Back River, Bailey Cove or Montsweag Bay for boating and fishing and the mud flats in the Cove or Bay exposed at low tides which is worked by clam diggers and worm diggers; however, the time estimates are conservatively applied to all monitoring locations. Table 4.3 presents the results of the dose calculations. The highest calculated dose is at Station ID number TL-1-06. The maximum calculated annual dose at that location is 1.30 mrem. This value is only 5 percent of the 25 mrem per year limit. It is noted that most of the mud flat region in Bailey Cove that is used by the public is situated further away from this Station. As a result, actual exposures from direct radiation would be much less than the maximum calculated value.

6.0 REFERENCES

1. USNRC Radiological Assessment Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979. 2. Maine Yankee Offsite Dose Calculation Manual, Revision 36. 3. 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation". 4. 10 CFR Part 72.104, "Criteria for Radioactive Materials in Effluents and Direct Radiation from an ISFSI or MRS". MY 2014 Annual REO Report Page 28 of 28
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