ML23230A394

GNF-A Semi-Annual Effluent Monitoring Report

ML23230A394
Person / Time
Site:	07001113
Issue date:	08/18/2023
From:	Murray S Global Nuclear Fuel - Americas
To:	Office of Nuclear Material Safety and Safeguards, Document Control Desk
References
M230108
Download: ML23230A394 (1)

Text

Global Nuclear Fuel GNi= Global Nuclear Fuel Scott P. Murray Manager, Facility Licensing 3901 Castle Hayne Roi!d P.O. Box780 Wilmington, NC 28402 USA T (910) 819-5950 M230108 scort.inurray@ge.com August 18, 2023 Attn: Document Control Desk Director, Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20?55~gog_1__ _ _

Subject:

GNF-A Semi-Annual Effluent Monitoring Report

References:

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

2) NRe *Regulation 10 eFR- 70.59

Dear Sir or Madam:

With respect to activities authorized by NRG 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 January through June 2023.

If you have any questions regarding this report, please contact me at (91 O) 819-5950.

Sincerely, 0~

~ ~urray, Manager Facility Licensing

Attachment:

1) Semi-Annual Effluent Monitoring Report (January- June 2023) cc: NRC Region II Administrator, Atlanta, GA J. Rowley, USNRC/NMSS/DFM/FFLB J. Rivera Ortiz, USNRC/RII/DFFI J. Hall, NCDHHS D. Crowley, NCDHHS S. Breitmaier, ANI SPM 23-031

SEMI-ANNUAL EFFLUENT REPORT Global Nuclear Fuel - Americas, LLC Wilmington, North Carolina January 2023 - June 2023 NRC License SNM 1097, Docket # 70-1113 Fiscal Weeks 1-26 I. GASEOUS EFFLUENT-PARTICULATE 1

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

LIMIT (Ci) (uCi/cc) (uCi/cc) mrem mrem U234 7.94E-06 4.53E-15 5 E-12 0.09% 2.27E-02 1.90E-01 U235 3.32E-07 1.90E-16 6 E-12 0.00% 7.97E-04 6.64E-03 U236 3.70E-09 2.11E-18 6 E-12 0.00% 8.88E-06 7.40E-05 U238 1.07E-06 6.11E-16 6 E-12 0.01% 2.56E-03 2.14E-02 TOTAL 9.34E-06 --- --- --- 2.60E-02 2.18E-01 EXHAUST VOLUME = 1.75E+15 (cc) 1 2 QUANTITY CONCENTRATION APPENDIX B CEDE Nuclide  % of LIMIT (Ci) (Ci/cc) Limit (Ci/cc) (mrem)

H-3 3.95E-03 4.19E-11 1E-05 0.00% 1.05E-04 EXHAUST VOLUME = 9.44E+13 (cc)

II. LIQUID EFFLUENT 1

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

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

U234 3.76E-03 2.03E-08 3 E-07 6.76% 1.48E-06 9.34E-07 2.15E-05 U235 1.57E-04 8.49E-10 3 E-07 0.28% 8.83E-08 5.61E-08 1.28E-06 U236 1.75E-06 9.47E-12 3 E-07 0.00% 6.53E-10 4.17E-10 9.48E-09 U238 5.06E-04 2.73E-09 3 E-07 0.91% 1.80E-07 1.15E-07 2.62E-06 TOTAL U 4.42E-03 --- --- --- 1.75E-06 1.10E-06 2.54E-05 TOTAL VOLUME OF LIQUID EFFLUENT = 1.85E+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 2.03E-08 2.61E-02 2.19E-01 Limit 3.00E-07 25 25

% of Limit 6.76% 0.10% 0.87%

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.