ML24219A263

GNF-A Semi-Annual Effluent Monitoring Report

ML24219A263
Person / Time
Site:	07001113
Issue date:	08/06/2024
From:	Murray S Global Nuclear Fuel
To:	Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk
References
M240162
Download: ML24219A263 (1)

Text

Global Nu clear Fuel Scott P. Murray Manager, Facility Licensing GNii= 3901 Castle Hayne Road Global Nuclear Fuel P.O. Box 780 Wilmington, NC 28402 USA

T (910) 819-5950 M240162 scott.murray@ge.com

August 6, 2024

Attn: Document Control Desk Director, Office 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 January through June 2024.

If you have any question s regarding this report, please cont ac t me at (9 10) 819-5950.

Sincerely, s!.~I!l~

Facility Licensing

Attachment:

1) Semi-Annual Effluent Monitoring Report (January- June 2024)

cc: NRC Region II Administrator, Atlanta, GA J. Rowley, USNRC/NMSS/DF M/F FLB C. Ubben, USN RC/R II/DFFI J. Hall, NCDHHS D. Crowley, NCD HH S S. Breitmaier, ANI SPM 24-036 SEMI-ANNUAL EFFLUENT REPORT

Global Nuclear Fuel - Americas, LLC Wilmington, North Carolina January 2024 - June 2024 NRC License SNM 1097, Docket# 70-1113 Fiscal Weeks 1-26

I. GASEOUS EFFLUENT-PARTICULATE

1 APPENDIXB NUCLIDES QUANTITY CONCENTRATION LIMIT 3/4of LIMIT CEDE CDE (Lung)

ICil (uCi/cc) (uCi/cc) mrem mrem U234 9.15E-06 5.17E-15 5 E-12 0.10% 2.58E-02 2.17E-01 U235 3.63E-07 2.05E-16 6 E-12 0.00% 8.60E-04 7.16E-03 U236 1.79E-09 1.01E-18 6 E-12 0.00% 4.23E-06 3.53E-05 U238 1.21 E-06 6.84E-16 6 E-12 0.01% 2.87E-03 2.39E-02 TOTAL 1.07E-05 ---- --- 2.96E-02 2.48E-01

EXHAUST VOLUME = 1.77E+15 (cc)

2 Nuclide QUANTITY CONCENTRATION 1 APPENDIX B 3/4of LIMIT CEDE (Ci) (µCi/cc) Limit (µCi/cc) (mrem)

H-3 4.19E-03 4.43E-11 1E-05 0.00% 1.11 E-04

EXHAUST VOLUME = 9.44E+13 (cc)

II. LIQUID EFFLUENT

1 APPENDIXB NUCLIDES QUANTITY CONCENTRATION LIMIT 3/4of LIMIT CEDE CDE (Lung) CDE (Bone Surface)

!Cil luCi/ccl luCi/cc\\ lmrem) (mrem) (mrem)

U234 6.83E-03 3.04E-08 3 E-07 10.12% 2.22E-06 1.40E-06 3.22E-05 U235 2.71E-04 1.20E-09 3 E-07 0.40% 1.25E-07 7.94E-08 1.81 E-06 U236 1.33E-06 5.93E-12 3 E-07 0.00% 4.09E-10 2.61E-10 5.93E-09 U238 9.04E-04 4.02E-09 3 E-07 1.34% 2.65E-07 1.69E-07 3.85E-06 TOTAL U 8.01E-03 -- ------2.61E-06 1.65E-06 3.78E-05

TOTAL VOLUME OF LIQUID EFFLUENT= 2.25E+08 (liters)

Ill. 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 3.04E-08 --- ______ 2.97E-02 2.48E-01 _____

Limit 3.00E-07 25 25

% of Limit 10.12% 0.12% 0.99%

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.