ML18051A577
| ML18051A577 | |
| Person / Time | |
|---|---|
| Site: | 07200001 |
| Issue date: | 02/20/2018 |
| From: | Mcfadden A GE-Hitachi Nuclear Energy Americas |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, NRC/RGN-III |
| References | |
| M180037 | |
| Download: ML18051A577 (2) | |
Text
HITACHI M180037 February 20, 2018 A TIN: Document Control Desk Director, Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Regional Administrator U.S. Nuclear Regulatory Commission, Region Ill 2443 Warrenville Road, Ste 210 Lisle, IL 60532-4352
Subject:
2017 GEH Morris Operation Effluent Report
References:
- 1) NRC License SNM-2500, Docket 72-01
- 2) NRC Regulation 1 OCFR72.44
Dear Sir or Madam,
GE Hitachi Nuclear Energy GEH Morris Operation 7555 East Collins Rd Morris, IL 60450 In accordance with 10CFR72.44(d)(3) and SNM-2500 license condition 8.2.1, this report documents an estimate of quantities of principal radionuclides released to the environment by the GE-Hitachi Morris Operation in 2017. This report also provides an estimate of the maximum potential dose to the pubic resulting from GE-Hitachi Morris Operation effluents for2017.
Particulate and gaseous radionuclides above minimum detectable levels were used in calculations. Particulates present on the stack monitor filters were Ni-63, Co-60 and Cs-137.
Gaseous radionulides evaluated were H-3 and Kr-85. The quantity of tritium released was calculated by multiplying basin water evaporative losses, by the average tritium levels in the fuel basins. The amount of Kr-85 released was calculated by multiplying the concentration found in samples taken directly over the basin water, by the airflow through the basin area.
COMPLY V1.7.1 (the EPA software program) was used to calculate the Committed Effective Dose Equivalent from the release of principle radionuclides. The quantities released and the estimated dose to the public is shown in the following table.
Nuclide Cs-137 Co-60 Ni-63 H-3 Kr-85 Activity Discharged (Ci) 4.938E-7 8.079E-8 3.032E-7 7.022E-3 1.260E-O Committed Effective Dose Equivalent:
3.1 E-7 mRem/year
U.S. NRC February 20, 2018 Page 2 of 2 There are no liquid effluents from the site. Surface and groundwater water tritium levels were below minimum detectable levels and therefore, reported as zero.
The maximum potential Committed Effective Dose Equivalent to the public that could occur from surface water was calculated to be 0 mRem - based on a person consuming water all year from the Sanitary Lagoons (<MDA pCi/1 H-3).
The maximum potential Committed Effective Dose Equivalent to the public that could occur from groundwater was calculated to be 0 mRem - based on a person consuming water all year from any of the following wells: DM-1, 2, 3, 4, 5, 6, 7, and 8 (<MDA pCi/1 H-3).
Measurement of direct radiation at the GE-Hitachi Morris Operation owner control boundary is accomplished using TLDs prepared and processed by a NVLAP certified laboratory using direct measurement techniques. The calculated maximum potential Deep Dose Equivalent to the public that could occur from direct radiation at the boundary of the owner controlled area was calculated to be 0.383 mRem assuming the maximum time spent at the boundary is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per year.
The maximum potential radiation dose to the public, for 2017, would result from the sum of the stack effluent releases, the dose from drinking surface water from the Sanitary Lagoons, ground water from monitoring wells DM-1, 2, 3, 4, 5, 6, 7, and 8, and from direct radiation at the owner controlled boundary. The maximum potential Total Effective Dose Equivalent (TEDE) to the public estimated from these sources for 2017 is 0.38 mRem.
Sincerely,
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