ML24219A263
| 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
GNii=
Global Nuclear Fuel M240162 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:
Global Nuclear Fuel Scott P. Murray Manager, Facility Licensing 3901 Castle Hayne Road P.O. Box 780 Wilmington, NC 28402 USA T (910) 819-5950 scott.murray@ge.com 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 questions regarding this report, please contact me at (910) 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/DFM/FFLB C. Ubben, USNRC/RII/DFFI J. Hall, NCDHHS D. Crowley, NCDHHS S. Breitmaier, ANI SPM 24-036
SEMI-ANNUAL EFFLUENT REPORT Global Nuclear Fuel - Americas, LLC Wilmington, North Carolina NRC License SNM 1097, Docket# 70-1113 I.
GASEOUS EFFLUENT-PARTICULATE NUCLIDES QUANTITY CONCENTRATION ICil (uCi/cc)
U234 9.15E-06 5.17E-15 U235 3.63E-07 2.05E-16 U236 1.79E-09 1.01E-18 U238 1.21 E-06 6.84E-16 TOTAL 1.07E-05 1 APPENDIXB LIMIT (uCi/cc) 5 E-12 6 E-12 6 E-12 6 E-12 EXHAUST VOLUME =
1.77E+15 (cc) 2 Nuclide QUANTITY CONCENTRATION 1 APPENDIX B (Ci)
(µCi/cc)
Limit (µCi/cc)
H-3 4.19E-03 4.43E-11 1E-05 EXHAUST VOLUME =
9.44E+13 (cc)
II. LIQUID EFFLUENT NUCLIDES QUANTITY CONCENTRATION 1 APPENDIXB LIMIT
!Cil luCi/ccl luCi/cc\\
U234 6.83E-03 3.04E-08 3 E-07 U235 2.71E-04 1.20E-09 3 E-07 U236 1.33E-06 5.93E-12 3 E-07 U238 9.04E-04 4.02E-09 3 E-07 TOTAL U 8.01E-03 3/4of LIMIT 0.10%
0.00%
0.00%
0.01%
3/4of LIMIT 0.00%
3/4of LIMIT 10.12%
0.40%
0.00%
1.34%
TOTAL VOLUME OF LIQUID EFFLUENT=
2.25E+08 (liters)
Ill. ABNORMAL RELEASES Air Water Total
- 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%
CEDE mrem 2.58E-02 8.60E-04 4.23E-06 2.87E-03 2.96E-02 CEDE (mrem) 1.11 E-04 CEDE lmrem) 2.22E-06 1.25E-07 4.09E-10 2.65E-07 2.61E-06 January 2024 - June 2024 Fiscal Weeks 1-26 CDE (Lung) mrem 2.17E-01 7.16E-03 3.53E-05 2.39E-02 2.48E-01 CDE (Lung) CDE (Bone Surface)
(mrem)
(mrem) 1.40E-06 3.22E-05 7.94E-08 1.81 E-06 2.61E-10 5.93E-09 1.69E-07 3.85E-06 1.65E-06 3.78E-05 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.