ML23058A223

GNF-A Semi-Annual Effluent Monitoring Report

ML23058A223
Person / Time
Site:	07001113
Issue date:	02/27/2023
From:	Murray S Global Nuclear Fuel - Americas
To:	Office of Nuclear Material Safety and Safeguards, Document Control Desk
References
M230028
Download: ML23058A223 (1)

Text

Global Nuclear Fuel Scott P. Murray

~ Manager, Facility Licensing 3901 Castle Hayne Road Global Nuclear Fuel P.O. Box 780 Wilmington, NC 28402 USA T (910) 819-5950 M230028 scott.murray@ge.com February 27, 2023 Attn: Document Con_trol Desk Director, Offipe of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555-:0001

Subject:

GNF-A Semi-Annual Effluent Monitoring Report

References:

1) NRC License SNM-1097, Docket 70-1113

2) NRC Regulation 10 CFR 70.59

Dear Sir or Madam:

With respect to activities authorized by NRC License SNM-1097, the Global Nuclear Fuel-Americas, L.L.C. (GNF-A) facility in Wilmington, North Carolina hereby submits the semi-annual effluent monitoring report required by 10 CFR 70.59 for the period of July through December 2022.

If you hc:;tve any questions regarding this report, please contact me at (91 0) 819-5950.

Sincerely, g~aagar

• Facility Licensing

Attachment:

1) Semi-Annual Effluent Monitoring Report (July- December 2022) cc: NRC Region II Administrator, Atlanta, GA J. Rowley, USNRC;NMSS J. Rivera Ortiz, USNRC, Rll J. Hall, NCDHHS

p. ~rowley, NCDHHS

s. Breitmaier, ANI SPM 23-011

SEMI-ANNUAL EFFLUENT REPORT Global Nuclear Fuel - Americas, LLC Wilmington, North Carolina July 2022 - December 2022 NRC License SNM 1097, Docket # 70-1113 Fiscal Weeks 27-52 I. GASEOUS EFFLUENT-PARTICULATE 1

APPENDIX B NUCLIDES QUANTITY CONCENTRATION  % of LIMIT CEDE CDE (Lung)

LIMIT (Ci) (uCi/cc) (uCi/cc) mrem mrem U234 6.45E-06 4.49E-15 5 E-12 0.09% 2.25E-02 1.89E-01 U235 2.75E-07 1.92E-16 6 E-12 0.00% 8.06E-04 6.71E-03 U236 1.78E-09 1.24E-18 6 E-12 0.00% 5.21E-06 4.35E-05 U238 9.81E-07 6.84E-16 6 E-12 0.01% 2.87E-03 2.39E-02 TOTAL 7.70E-06 --- --- --- 2.61E-02 2.19E-01 EXHAUST VOLUME = 1.44E+15 (cc) 1 2 QUANTITY CONCENTRATION APPENDIX B CEDE Nuclide  % of LIMIT (Ci) (Ci/cc) Limit (Ci/cc) (mrem)

H-3 3.16E-03 3.31E-11 1E-05 0.00% 8.27E-05 EXHAUST VOLUME = 9.54E+13 (cc)

II. LIQUID EFFLUENT 1

APPENDIX B CDE (Bone NUCLIDES QUANTITY CONCENTRATION  % of LIMIT CEDE CDE (Lung)

LIMIT Surface)

(Ci) (uCi/cc) (uCi/cc) (mrem) (mrem) (mrem)

U234 5.63E-03 2.43E-08 3 E-07 8.11% 1.78E-06 1.12E-06 2.58E-05 U235 2.40E-04 1.04E-09 3 E-07 0.35% 1.08E-07 6.86E-08 1.57E-06 U236 1.56E-06 6.72E-12 3 E-07 0.00% 4.64E-10 2.96E-10 6.73E-09 U238 8.57E-04 3.70E-09 3 E-07 1.23% 2.44E-07 1.56E-07 3.54E-06 TOTAL U 6.73E-03 --- --- --- 2.13E-06 1.34E-06 3.09E-05 TOTAL VOLUME OF LIQUID EFFLUENT = 2.31E+08 (liters)

III. ABNORMAL RELEASES Air Water Total

1. Releases 0 0 0 Activity 0 0 0 Released (Ci)

IV.

SUMMARY

3 Max Release CEDE, total CDE (Lung), total (uCi/cc) (mrem) (mrem)

Value 2.43E-08 2.62E-02 2.19E-01 Limit 3.00E-07 25 25

% of Limit 8.11% 0.10% 0.88%

1 Limit from 10 CFR 20 Appendix B, Table 2, Columns 1 and 2. Air limit adjusted to reflect NRC License SNM-1097, Section 1.3.9.

2 This nuclide is included due to the the neutron generator licensed by the State of North Carolina.

3 From nuclide with release that is the largest percentage of its release limit.

Notes:

Air sampling is continuous. H-3 gaseous effluent is calculated. Water samples analyzed are representative, continuous composite samples of the process effluent stream.

Reported effluent concentration values are representative of the effluent concentration at the point of release and do not consider effects of dilution from point of release to the plant site boundary.