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{{#Wiki_filter:Nuclear Fuel Services, Inc.
{{#Wiki_filter:Nuclear Fuel Services, Inc.
Certified Mail 21 G-24-0032 Return Receipt Requested GOV-01-55 ACF-24-0033 February 14, 2024
Certified Mail Return Receipt Requested 21 G-24-0032 GOV-01-55 ACF-24-0033 February 14, 2024 Director Office of Nuclear Material Safety & Safeguards U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001  
 
Director Office of Nuclear Material Safety & Safeguards U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001


==Reference:==
==Reference:==
Docket No. 70-143; SNM License 124
Docket No. 70-143; SNM License 124  


==Subject:==
==Subject:==
Biannual Effluent Monitoring Report July to December 2023
Biannual Effluent Monitoring Report July to December 2023  


==Dear Director:==
==Dear Director:==
In accordance with the requirements set forth in 10 CFR Part 70.59, Nuclear Fuel Services, Inc. (NFS), submits the attached reports. Attachment 1 reports the Radioactivity in Effluent Liquid for the period July to December 2023. Attachment 2 reports the Radioactivity in Effluent Air for the period July to December 2023. Attachment 3 summarizes an evaluation of the dose and air activity concentrations for the maximally exposed offsite individual due to gaseous effluents during the period July to December 2023.
In accordance with the requirements set forth in 10 CFR Part 70.59, Nuclear Fuel Services, Inc. (NFS), submits the attached reports. Attachment 1 reports the Radioactivity in Effluent Liquid for the period July to December 2023. Attachment 2 reports the Radioactivity in Effluent Air for the period July to December 2023. Attachment 3 summarizes an evaluation of the dose and air activity concentrations for the maximally exposed offsite individual due to gaseous effluents during the period July to December 2023.
If you or your staff have any questions, require additional information, or wish to discuss this, please contact me or Mr. R. Jason Faddis, Deputy Environmental Protection and Industrial Safety Section Manager, at (423) 735-5438. Please reference our unique document identification number (21 G-24-0032) in any correspondence concerning this letter.
If you or your staff have any questions, require additional information, or wish to discuss this, please contact me or Mr. R. Jason Faddis, Deputy Environmental Protection and Industrial Safety Section Manager, at (423) 735-5438. Please reference our unique document identification number (21 G-24-0032) in any correspondence concerning this letter.
 
CJB/las Attachments Sincerely, NUCLEAR FUEL SERVICES, INC.  
Sincerely,
-J~~~
 
Tim Knowles Safety & Safeguards Director
NUCLEAR FUEL SERVICES, INC.
-J~~~ ~ms":,'2-0 Tim Knowles Safety & Safeguards Director lf:tD CJB/las Attachments [V/\\1\\SS
: 1) Report of Radioactivity in Effluent Liquid for the Period July to December 2023
: 1) Report of Radioactivity in Effluent Liquid for the Period July to December 2023
: 2) Report of Radioactivity in Effluent Air for the Period July to December 2023
: 2) Report of Radioactivity in Effluent Air for the Period July to December 2023  
: 3) Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed Off-Site Individual for the Release Period July to December 2023 Page 1 Of 14 P e o p l e S t r 6 n g 1205 Banner Hill Rd, Erwin, TN 37650 t: +1.423.743.9141 f: +1.423.743.0140 www.nuclearfuelserv1ces.com /NNDVAT/DN DR/VEN >
~ms":,'2-0 lf:tD
21 G-24-0032 GOV-01-55 ACF-24-0033
[V/\\1\\SS
: 3) Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed Off-Site Individual for the Release Period July to December 2023 Page 1 Of 14 P e o p l e S t r 6 n g 1205 Banner Hill Rd, Erwin, TN 37650 t: +1.423.743.9141 f: +1.423.743.0140 www.nuclearfuelserv1ces.com  
/NNDVAT/DN DR/VEN >  


Copy:
Copy:
Mr. Joel Rivera-Ortiz Senior Fuel Facility Inspector U. S. Nuclear Regulatory Commission Region II 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Regional Administrator U.S. Nuclear Regulatory Commission Region II 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Mr. James Downs Senior Project Manager Division of Fuel Management Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Two White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Dr. Robert Williams Chief, Projects Branch 1 U.S. Nuclear Regulatory Commission Region II 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Mr. Larry Harris Senior Resident Inspector U. S. Nuclear Regulatory Commission Page 2 of 14 21 G-24-0032 GOV-01-55 ACF-24-0033 To Letter Dated February 14, 2024 Report of Radioactivity in Effluent Liquid for the Period July to December 2023 (2 Pages to Follow)
Page 3 of 14 21 G-24-0032 GOV-01-55 ACF-24-0033


Mr. Joel Rivera-Ortiz Senior Fuel Facility Inspector U. S. Nuclear Regulatory Commission Region II 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257
Radioactivity in Effluent Liquid July 1, 2023 to December 31, 2023 Total Activity Error Quantity Volume Concentration Estimate LLD Released Location (I)
 
(µCi/ml)
Regional Administrator U.S. Nuclear Regulatory Commission Region II 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257
(µCi/ml)
 
(µCi/ml)
Mr. James Downs Senior Project Manager Division of Fuel Management Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Two White Flint North 11555 Rockville Pike Rockville, MD 20852-2738
(Ci)
 
Banner Spring Down Pu-238 393,789,000 2.45E-13 1.02E-10 2.43E-10 9.66E-08 Pu-239/240 393,789,000 O.OOE+OO 1.31E-10 2.89E-10 O.OOE+OO Tc-99 393,789,000 O.OOE+OO 3.59E-08 6.27E-08 O.OOE+OO Th-228 393,789,000 O.OOE+OO 1.54E-10 3.SSE-10 O.OOE+OO Th-230 393,789,000 4.25E-l l 1.79E-10 3.64E-l0 l.67E-05 Th-232 393,789,000 l.64E-1 I l.29E-10 2 SSE-10 6.47E-06 U-233/234 393,789,000 4.76E-10 3.09E-10 3.43E-10 l.88E-04 U-235/236 393,789,000 4.68E-11 l.53E-10 2.41E-IO l.84E-05 U-238 393,789,000 5.56E-l 1 1.44E-10 2.48E-10 2.19E-05 Sewer Pu-238 22,383,314 l.29E-11 l.26E-10 2.59E-10 2.89E-07 Pu-239/240 22,383,314 3.46E-12 9.99E-ll 2.16E-10 7.73E-08 Tc-99 22,383,314 7.SSE-10 3.88E-08 6.72E-08 l.69E-05 Th-228 22,383,314 4.52E-ll l.90E-10 3.73E-10 l.OIE-06 Th-230 22,383,314 6.0SE-11 2.02E-10 3.87E-10 l.36E-06 Th-232 22,383,314 2.SIE-12 l.lSE-10 2.43E-10 5.61E-08 U-232 22,383,314 O.OOE+OO l.47E-IO 3.56E-10 O.OOE+OO U-233/234 22,383,314 6.67E-09 8.23E-10 2.26E-IO 1.49E-04 U-235/236 22,383,314 3.09E-10 l.91E-10 1.51E-10 6.93E-06 U-238 22,383,314 7.42E-10 2.75E-10 i.44E-10 l.66E-05 West Ditch Pu-238 144,342,000 3.18E-11 1.03E-10 2.16E-10 4.59E-06 Pu-239/240 144,342,000 O.OOE+OO I.OSE-10 2.58E-10 O.OOE+OO Tc-99 144,342,000 2.07E-09 3.SOE-08 6.06E-08 2.99E-04 Th-228 144,342,000 4.62E-12 l.44E-10 3.27E-10 6.67E-07 Th-230 144,342,000 5.45E-l I 1.61E-!0 3.0SE-10 7.86E-06 Th-232 144,342,000 O.OOE+OO 9.42E-ll 2.12E-10 O.OOE+OO U-233/234 144,342,000 l.52E-08 l.56E-09 3.48E-10 2.19E-03 U-235/236 144,342,000 6.06E-10 3.65E-10 2.33E-10 8.75E-05 U-238 144,342,000 l.lSE-09 4.31E-10 2.54E-IO l.66E-04 WWTF Am-241 3,395,574 2.38E-ll 5.77E-l l l.12E-10 8.07E-08 Cs-137 3,395,574 0.00E+OO 1.82E-09 1.85E-09 O.OOE+OO Na-22 3,395,574 2.00E-11 8.75E-10 l.59E-09 6.79E-08 Np-237 3,395,574 5.20E-11 2.54E-10 4.81E-10 l.76E-07 Pb-212 3,395,574 1.93E-09 3.59E-09 2.94E-09 6.56E-06 Pu-238 3,395,574 l.18E-11 6.23E-1 I l.20E-10 4.0lE-08 ECV emuent Conoerrtrat1on Value from 10-CFR-20,Appendlx a Note: A valoe of "O" was substituted for negative analytical results.
Dr. Robert Williams Chief, Projects Branch 1 U.S. Nuclear Regulatory Commission Region II 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257
Printed: 02/05/2024 NFS-EDMS Page 4 of 14 Quantity Released (g) 5.65E-09 O.OOE+OO O.OOE+OO O.OOE+OO 8.28E-04 5.94E+Ol 3.0IE-02 8.53E+OO 6.54E+Ol Total:
 
l.69E-08 1.24E-06 l.OOE-03 1.23E-09 6.74E-05 5.lSE-01 O.OOE+OO 2.39E-02 3.21E+OO 4.96E+Ol Total:
Mr. Larry Harris Senior Resident Inspector U. S. Nuclear Regulatory Commission
2.68E-07 O.OOE+OO 1.77E-02 8.!SE-10 3.89E-04 O.OOE+OO 3.SlE-01 4.05E+Ol 4.96E+02 Total:
 
2.35E-08 O.OOE+OO 1.09E-11 2.SIE-04 4.74E-12 2.34E-09 21 G-24-0032 GOV-01-55 ACF-24-0033 Fraction of ECV 1
Page 2 of 14 21 G-24-0032 GOV-01-55 ACF-24-0033
1.23E-05 O.OOE+OO O.OOE+OO O.OOE+OO 4.25E-04 5.48E-04 l.59E-03 1.56E-04 1.85E-04 2.91E-03 6.45E-05 1.73E-05 1.26E-06 2.26E-05 6.0SE-05 8.35E-06 O.OOE+OO 2.22E-03 l.03E-04 2.47E-04 2.75E-03 l.59E-03 O.OOE+OO 3.45E-05 2.31E-05 5.45E-04 O.OOE+OO 5.06E-02 2.02E-03 3.83E-03 5.86E-02 l.19E-03 O.OOE+OO 3.33E-06 2.60E-03 9.66E-04 5.90E-04 Page I of2
 
Attachment 1 To Letter Dated February 14, 2024
 
Report of Radioactivity in Effluent Liquid for the Period July to December 2023
 
(2 Pages to Follow)
 
Page 3 of 14 21 G-24-0032 GOV-01-55 ACF-24-0033 Radioactivity in Effluent Liquid July 1, 2023 to December 31, 2023
 
Total Activity Error Quantity Quantity Fraction Volume Concentration Estimate LLD Released Released of 1 Location (I) (µCi/ml) (µCi/ml) (µCi/ml) (Ci) (g) ECV Banner Spring Down Pu-238 393,789,000 2.45E-13 1.02E-10 2.43E-10 9.66E-08 5.65E-09 1.23E-05 Pu-239/240 393,789,000 O.OOE+OO 1.31E-10 2.89E-10 O.OOE+OO O.OOE+OO O.OOE+OO Tc-99 393,789,000 O.OOE+OO 3.59E-08 6.27E-08 O.OOE+OO O.OOE+OO O.OOE+OO Th-228 393,789,000 O.OOE+OO 1.54E-10 3.SSE-10 O.OOE+OO O.OOE+OO O.OOE+OO Th-230 393,789,000 4.25E-l l 1.79E-10 3.64E-l0 l.67E-05 8.28E-04 4.25E-04 Th-232 393,789,000 l.64E-1 I l.29E-10 2 SSE-10 6.47E-06 5.94E+Ol 5.48E-04 U-233/234 393,789,000 4.76E-10 3.09E-10 3.43E-10 l.88E-04 3.0IE-02 l.59E-03 U-235/236 393,789,000 4.68E-11 l.53E-10 2.41E-IO l.84E-05 8.53E+OO 1.56E-04 U-238 393,789,000 5.56E-l 1 1.44E-10 2.48E-10 2.19E-05 6.54E+Ol 1.85E-04 Total: 2.91E-03 Sewer Pu-238 22,383,314 l.29E-11 l.26E-10 2.59E-10 2.89E-07 l.69E-08 6.45E-05 Pu-239/240 22,383,314 3.46E-12 9.99E-ll 2.16E-10 7.73E-08 1.24E-06 1.73E-05 Tc-99 22,383,314 7.SSE-10 3.88E-08 6.72E-08 l.69E-05 l.OOE-03 1.26E-06 Th-228 22,383,314 4.52E-ll l.90E-10 3.73E-10 l.OIE-06 1.23E-09 2.26E-05 Th-230 22,383,314 6.0SE-11 2.02E-10 3.87E-10 l.36E-06 6.74E-05 6.0SE-05 Th-232 22,383,314 2.SIE-12 l.lSE-10 2.43E-10 5.61E-08 5.lSE-01 8.35E-06 U-232 22,383,314 O.OOE+OO l.47E-IO 3.56E-10 O.OOE+OO O.OOE+OO O.OOE+OO U-233/234 22,383,314 6.67E-09 8.23E-10 2.26E-IO 1.49E-04 2.39E-02 2.22E-03 U-235/236 22,383,314 3.09E-10 l.91E-10 1.51E-10 6.93E-06 3.21E+OO l.03E-04 U-238 22,383,314 7.42E-10 2.75E-10 i.44E-10 l.66E-05 4.96E+Ol 2.47E-04 Total: 2.75E-03 West Ditch Pu-238 144,342,000 3.18E-11 1.03E-10 2.16E-10 4.59E-06 2.68E-07 l.59E-03 Pu-239/240 144,342,000 O.OOE+OO I.OSE-10 2.58E-10 O.OOE+OO O.OOE+OO O.OOE+OO Tc-99 144,342,000 2.07E-09 3.SOE-08 6.06E-08 2.99E-04 1.77E-02 3.45E-05 Th-228 144,342,000 4.62E-12 l.44E-10 3.27E-10 6.67E-07 8.!SE-10 2.31E-05 Th-230 144,342,000 5.45E-l I 1.61E-!0 3.0SE-10 7.86E-06 3.89E-04 5.45E-04 Th-232 144,342,000 O.OOE+OO 9.42E-ll 2.12E-10 O.OOE+OO O.OOE+OO O.OOE+OO U-233/234 144,342,000 l.52E-08 l.56E-09 3.48E-10 2.19E-03 3.SlE-01 5.06E-02 U-235/236 144,342,000 6.06E-10 3.65E-10 2.33E-10 8.75E-05 4.05E+Ol 2.02E-03 U-238 144,342,000 l.lSE-09 4.31E-10 2.54E-IO l.66E-04 4.96E+02 3.83E-03 Total: 5.86E-02 WWTF Am-241 3,395,574 2.38E-ll 5.77E-l l l.12E-10 8.07E-08 2.35E-08 l.19E-03 Cs-137 3,395,574 0.00E+OO 1.82E-09 1.85E-09 O.OOE+OO O.OOE+OO O.OOE+OO Na-22 3,395,574 2.00E-11 8.75E-10 l.59E-09 6.79E-08 1.09E-11 3.33E-06 Np-237 3,395,574 5.20E-11 2.54E-10 4.81E-10 l.76E-07 2.SIE-04 2.60E-03 Pb-212 3,395,574 1.93E-09 3.59E-09 2.94E-09 6.56E-06 4.74E-12 9.66E-04 Pu-238 3,395,574 l.18E-11 6.23E-1 I l.20E-10 4.0lE-08 2.34E-09 5.90E-04
 
ECV emuent Conoerrtrat1on Value from 10-CFR-20,Appendlx a Note: A valoe of "O" was substituted for negative analytical results.
Printed: 02/05/2024 NFS-EDMS Page I of2
 
Page 4 of 14 21 G-24-0032 GOV-01-55 ACF-24-0033 Radioactivity in Effluent Liquid July 1, 2023 to December 31, 2023
 
Total Activity Error Quantity Quantity Fraction Volume Concentration Estimate LLD Released Released of Location (I) (µCi/ml) (µCi/ml) (µCi/ml) (Ci) (g) ECV1 WWTF Pu-239/240 3,395,574 3.14E-12 5.69E-ll l.23E-10 1.07E-08 l.72E-07 l.57E-04 Pu-241 3,395,574 0.00E+OO 1.19E-08 2.07E-08 O.OOE+OO O.OOE+OO O.OOE+OO Ra-224 3,395,574 l.46E-08 9.21E-09 l.73E-08 4.97E-05 3.13E-l0 7.32E-02 Tc-99 3,395,574 2.lSE-09 3.79E-08 6.56E-08 7.30E-06 4.32E-04 3.58E-05 Th-228 3,395,574 O.OOE+OO l.12E-l0 3.00E-10 O.OOE+OO O.OOE+OO O.OOE+OO Th-230 3,395,574 1.03E-10 l.89E-10 3.22E-10 3.SlE-07 1.74E-05 l.03E-03 Th-231 3,395,574 8.42E-09 4.76E-08 4.93E-08 2.86E-05 5.37E-ll l.68E-04 Th-232 3,395,574 3.20E-12 9.78E-ll 2.l lE-10 l.09E-08 9.98E-02 l.07E-04 U-232 3,395,574 O.OOE+OO l.l2E-10 2.64E-10 O.OOE+OO O.OOE+OO O.OOE+OO U-233/234 3,395,574 7.87E-09 6.95E-10 l.36E-10 2.67E-05 4.28E-03 2.62E-02 U-235/236 3,395,574 3.62E-l0 l.58E-10 l.l7E-JO l.23E-06 5.68E-Ol I.21E-03 U-238 3,395,574 6.llE-11 7.66E-ll l.02E-10 2.07E-07 6.19E-Ol 2.04E-04 Total: 1.0SE-01


ECV: Efflueol Coocenlratlon value from 10-CFR-20, Appendix B.
Radioactivity in Effluent Liquid July 1, 2023 to December 31, 2023 Total Activity Volume Concentration Location (I)
(µCi/ml)
WWTF Pu-239/240 3,395,574 3.14E-12 Pu-241 3,395,574 0.00E+OO Ra-224 3,395,574 l.46E-08 Tc-99 3,395,574 2.lSE-09 Th-228 3,395,574 O.OOE+OO Th-230 3,395,574 1.03E-10 Th-231 3,395,574 8.42E-09 Th-232 3,395,574 3.20E-12 U-232 3,395,574 O.OOE+OO U-233/234 3,395,574 7.87E-09 U-235/236 3,395,574 3.62E-l0 U-238 3,395,574 6.llE-11 ECV: Efflueol Coocenlratlon value from 10-CFR-20, Appendix B.
Note A value of "O~ was substttuted for negallve analytical results.
Note A value of "O~ was substttuted for negallve analytical results.
Printed: 02/05/2024 NFS-EDMS Page2 of2
Printed: 02/05/2024 Error Quantity Estimate LLD Released
 
(µCi/ml)
Page 5 of 14 21 G-24-0032 GOV-01-55 ACF-24-0033
(µCi/ml)
 
(Ci) 5.69E-ll l.23E-10 1.07E-08 1.19E-08 2.07E-08 O.OOE+OO 9.21E-09 l.73E-08 4.97E-05 3.79E-08 6.56E-08 7.30E-06 l.12E-l0 3.00E-10 O.OOE+OO l.89E-10 3.22E-10 3.SlE-07 4.76E-08 4.93E-08 2.86E-05 9.78E-ll 2.l lE-10 l.09E-08 l.l2E-10 2.64E-10 O.OOE+OO 6.95E-10 l.36E-10 2.67E-05 l.58E-10 l.l7E-JO l.23E-06 7.66E-ll l.02E-10 2.07E-07 NFS-EDMS Page 5 of 14 Quantity Released (g) l.72E-07 O.OOE+OO 3.13E-l0 4.32E-04 O.OOE+OO 1.74E-05 5.37E-ll 9.98E-02 O.OOE+OO 4.28E-03 5.68E-Ol 6.19E-Ol Total:
Attachment 2 To Letter Dated February 14, 2024
21 G-24-0032 GOV-01-55 ACF-24-0033 Fraction of ECV 1
 
l.57E-04 O.OOE+OO 7.32E-02 3.58E-05 O.OOE+OO l.03E-03 l.68E-04 l.07E-04 O.OOE+OO 2.62E-02 I.21E-03 2.04E-04 1.0SE-01 Page2 of2 To Letter Dated February 14, 2024 Report of Radioactivity in Effluent Air for the Period July to December 2023 (3 Pages to Follow)
Report of Radioactivity in Effluent Air for the Period July to December 2023
Page 6 of 14 21 G-24-0032 GOV-01-55 ACF-24-0033  
 
(3 Pages to Follow)
 
Page 6 of 14 21 G-24-0032 GOV-01-55 ACF-24-0033 Radioactivity in Effluent Air July 1, 2023 to December 31, 2023
 
Total Activity Error Quantity Quantity Fraction Volume Concentration Estimate LLD Released Released of 1 Location (ma) (µCi/ml) (µCi/ml) (µCi/ml) (Ci) (g) ECV Main Stack416 1013.64 mo/min 16.89 m3/sec Th-228 265,683,538 l.09E-15 l.84E-16 7.86E-17 2.91E-07 3.SSE-10 5.47E-02 Th-230 265,683,538 l.09E-15 l.84E-16 7.86E-17 2.91E-07 1.44E-05 5.47E-02 Th-232 265,683,538 8.21E-16 l.38E-16 5.89E-17 2.18E-07 2.00E+OO 2.0SE-01 U-234 265,683,538 2.58E-13 4.34E-14 1.85E-14 6.86E-05 l.IOE-02 5.16E+OO U-235 265,683,538 9.85E-15 1.66E-15 7.0?E-16 2.62E-06 l.21E+OO 1.64E-OI U-238 265,683,538 2.74E-15 4.60E-!6 l.96E-!6 7.27E-07 2.17E+OO 4.56E-02 Total: 5.69E+00 Stack 234 Bldg. 234 315.90 m 3/min 5.27 m3!sec Am-241 83,246,700 4.65E-I 7 2.83E-17 4.25E-17 3.87E-09 1.13E-09 2.32E-03 Pu-238 83,246,700 5.68E-17 3.46E-17 5.19E-!7 4.73E-09 2.77E-IO 2.84E-03 Pu-239/240 83,246,700 2.0lE-16 l.23E-16 1.84E-16 l.68E-08 2.?0E-07 l.OIE-02 Pu-241 83,246,700 9.59E-15 3.59E-15 4.62E-15 7.98E-07 7.75E-09 l.20E-02 Th-228 83,246,700 3.lOE-17 l.89E-17 2.83E-17 2.SSE-09 3.lSE-12 I SSE-03 Th-230 83,246,700 3.87E-16 2.36E-16 3.54E-16 3.22E-08 1.60E-06 I.94E-02 Th-232 83,246,700 4.91E-16 2.98E-16 4.48E-16 4.0SE-08 3.75E-OI l.23E-O I U-234 83,246,700 l.06E-15 6.44E-16 9.67E-16 8.SIE-08 l.41E-05 2.12E-02 U-238 83,246,700 3.IOE-16 l.89E-16 2.83E-16 2.58E-08 7 ?OE-02 5.l6E-03 Total: l.97E-0l Stack 327 Bldg. 330 974.04 m 3/min 16.23 m3/sec Pu-241 255,277,191 2.89E-15 4.17E-16 4.99E-16 7.37E-07 7.16E-09 3.61E-03 Tc-99 255,277,191 9.34E-14 1.35E-14 l.61E-14 2.38E-05 l.41E-03 l.04E-04 U-234 255,277,191 5.79E-14 9.77E-15 8.42E-15 1.48E-05 2.37E-03 l.16E+OO U-235 255,277,191 1.79E-15 3.02E-16 2.60E-16 4.57E-07 2 12E-OI 2.99E-02 Total: l.19E+00 Stack 421 Bldg. 100 35.68 mo/min 0.59 m3/sec Pu-241 9,345,920 6.98E-15 l.22E-15 1.30E-15 6.52E-08 6.33E-10 8.72E-03 Tc-99 9,345,920 2.26E-13 3.96E-14 4.21E-14 2.I IE-06 l.25E-04 2.SIE-04 U-234 9,345,920 2.88E-14 1.66E-14 2.27E-14 2.69E-07 4.31E-05 S.76E-Ol U-235 9,345,920 8.9IE-16 S.14E-16 7.0IE-16 8.33E-09 3.86E-03 l.49E-02 Total: 6.00E-01 Stack 424 Bldg. 100 34.38 m3/min 0.57 m3/sec Pu-241 9,006,009 2.4SE-15 9.l!E-16 9.57E-16 2.20E-08 2.14E-l0 3.06E-03 Tc-99 9,006,009 7.91E-14 2.94E-14 3.09E-14 7.12E-07 4.21E-05 8.79E-05 U-234 9,006,009 2.00E-14 l.16E-14 J.76E-14 l.SOE-07 2.89E-05 4.00E-01 U-235 9,006,009 6.ISE-16 3.SSE-16 5.46E-16 S.57E-09 2.SSE-03 1.03E-02 Total: 4.13E-01 Stack 573 Bldg 306-W 114.37 m 3/min 1.91 m3/sec Pu-241 29,974,550 1.27E-15 7.3 IE-16 l.OIE-15 3.82E-08 3.71E-IO l.59E-03 Tc-99 29,974,550 4.12E-14 2.37E-14 3.25E-14 l.23E-06 7.30E-05 4.SSE-05
 
\\ ECV. Effluent concentration \\/alue from 10~CFR~20, Appendix B Fraction of ECV al the stack ls provided for reference only. concentrations at off~site locations are
 
s1gmficantly less than those reported here (at stack) due to the atmospherfc dispersion that occurs before lhe effluent exits the site, Note* A value of "O" was substituted for negatlve analytical results.
Printed: 02/05/2024 NFS-EDMS Page I of3
 
Page 7 of 14 21 G-24-0032 GOV-01-55 ACF-24-0033 Radioactivity in Effluent Air July 1, 2023 to December 31, 2023
 
Total Activity Error Quantity Quantity Fraction Volume Concentration Estimate LLD Released Released of 1 Location (m3) (µCi/ml) (µCi/ml) (µCi/ml) (Ci) (g) ECV Stack 573 Bldg 306-W 114.37 m3/min 1.91 m 3/sec U-234 29,974,550 l.35E-15 7.12E-15 l.79E-14 4.04E-08 6.47E-06 2.70E-02 U-235 29,974,550 4. l 7E-17 2.20E-16 5.53E-16 l.2SE-09 5.78E-04 6.95E-04 Total: 2.93E-02 Stack 600 Bldg. 110 295.54 m 3/min 4.93 m3/sec Pu-241 77,455,900 3.398-15 5.76E-16 6.62E-16 2.63E-07 2.55E-09 4.24E-03 Tc-99 77,455,900 1.IOE-13 1.868-14 2.14E-14 8.SOE-06 5.03E-04 l.22E-04 U-234 77,455,900 1.268-13 1.198-14 l.lSE-14 9.79E-06 l.57E-03 2.53E+OO U-235 77,455,900 3.91E-15 3.68E-16 3.668-16 3.03E-07 l.40E-Ol 6.SIE-02 Total: 2.60E+00 Stack 615 Bldg. 306-W 48.03 m 3/min 0.80 m3tsec Pu-241 12,586,491 l.29E-15 7.26E-16 9.SOE-16 l.63E-08 l.58E-10 l.62E-03 Tc-99 12,586,491 4.l8E-14 2.35E-l4 3.07E-14 5.278-07 3.!2E-05 4,658-05 U-234 12,586,491 l.67E-l5 7.29E-15 l.75E-14 2.IOE-08 3.36E-06 3.338-02 U-235 12,586,491 5.158-17 2.26E-16 S.42E-l6 6.488-10 3.00E-04 8.59E-04 Total: 3.58E-02 Stack 646 Bldg. 110 33.30 m 3/min 0.56 m3/sec Pu-241 8,727,425 1.46E-15 7.60E-16 9.60E-16 1.28E-08 I 24E-10 l.83E-03 Tc-99 8,727,425 4.738-14 2.46E-14 3.IOE-14 4.13E-07 2.44E-05 S.26E-OS U-234 8,727,425 2.258-15 7.68E-IS 1.758-14 l.96E-08 3.14E-06 4.498-02 U-235 8,727,425 6.948-17 2.378-16 S.43E-16 6.06E-l0 2.818-04 1.16E-03 Total: 4.79E-02 Stack 701 Bldg. 307 130.71 m 3/min 2.18 m3/sec Pu-241 34,256,629 1.528-15 8.358-16 1.098-15 5.2IE-08 5.068-10 1.908-03 Tc-99 34,256,629 4.928-14 2.708-14 3.538-14 1.688-06 9.97E-05 5.47E-05 U-234 34,256,629 3.908-15 9.27E-15 2.008-14 1.348-07 2.148-05 7.808-02 U-235 34,256,629 l.21E-16 2.87E-16 6.19E-16 4.138-09 1.918-03 2.018-03 Total: 8.19E-02 Stack 702 Bldg. 307 153.00 m 3/min 2.55 m 3/sec Pu-241 40,097,176 l.62E-15 7.778-16 9.518-16 6.SIE-08 6.328-10 2.03E-03 Tc-99 40,097,176 5.258-14 2.SlE-14 3 078-14 2.1 IE-06 1.258-04 S.83E-05 U-234 40,097,176 l.46E-14 1.058-14 l.75E-14 5.848-07 9.368-05 2.91E-OI U-235 40,097,176 4.SOE-16 3.24E-16 5.428-16 1.818-08 8.36E-03 7.SIE-03 Total: 3.0tE-01 Stack 703 Exhaust Room Air 476.58 m 3/min 7,94 m3/sec Pu-241 125,899,447 4.04E-14 2.438-14 3.258-14 5.0SE-06 4.93E-08 5.058-02 Th-228 125,899,447 7.41E-16 9.13E-16 l.83E-15 9.33E-08 1.148-10 3.70E-02 Th-230 125,899,447 4.278-16 5.25E-16 1.058-15 S.37E-08 2.66E-06 2.13E-02 Th-232 125,899,447 6.06E-16 7.47E-16 1.498-15 7.63E-08 7.00E-01 1.52E-01 U-234 125,899,447 4.64E-15 5.728-15 1.148-14 5.84E-07 9.36E-05 9.288-02
 
I ECV: Effluent Concentration Value from 10-CFR-20, Appendix: 8. Fraction of ECV at the stack is provided for reference only Concentrations al off-site locations are s1gnlflcant1y less than those reported here (at stack) due to the atmospheric dispersion that occurs before the effluent exits the site.
Note. A value of 110"' was substituted for negative analytical results Printed: 02/05/2024 NFS-EDMS Page 2 of3
 
Page 8 of 14 21 G-24-0032 GOV-01-55 ACF-24-0033 Radioactivity in Effluent Air July 1, 2023 to December 31, 2023
 
Total Activity Error Quantity Quantity Fraction Volume Concentration Estimate LLD Released Released of 1 Location (ml) (µCi/ml) (µCi/ml) (µCi/ml) (Ci) (g) ECV Stack 703 Exhaust Room Air 476.58 m 3/min 7.94 m3/sec U-235 125,899,447 4.79E-16 5.90E-16 l.lSE-15 6.03E-08 2.79E-02 7.98E-03 U-238 125,899,447 S.84E-16 7.19E-16 1.44E-IS 7.35E-08 2.19E-Ol 9.73E-03 Total: 3.71E-01 Stack 773 Bldg. 440 174.69 m 3/min 2.91 m 3/sec Pu-241 45,781,877 5.07E-14 3,04E-14 3.93E-14 2.32E-06 2.26E-08 6.34E-02 Th-228 45,781,877 l.89E-16 l.30E-15 3.16E-IS 8.67E-09 l.06E-ll 9.47E-03 Th-230 45,781,877 2.44E-l6 l.67E-15 4.06E-15 l.12E-08 5.52E-07 l.22E-02 Th-232 45,781,877 l.62E-16 l.lIE-15 2.71E-15 7.43E-09 6.82E-02 4.06E-02 U-234 45,781,877 5.0IE-16 3.43E-15 8.35E-15 2.29E-08 3.67E-06 I.OOE-02 U-235 45,781,877 8.79E-17 6.02E-16 l.47E-15 4.03E-09 l.86E-03 1.47E-03 U-238 45,781,877 l.76E-16 l.20E-15 2.93E-15 8.0SE-09 2.40E-02 2.93E-03 Total: l.40E-Ol Stack 774 Bldg. 301 214.25 m 3/min 3.57 m3/see Tc-99 29,000,242 3.49E-13 2.56E-14 2.31E-l4 l.OlE-05 5 98E-04 3.87E-04 Th-228 29,000,242 l.62E-16 2.SIE-16 6.0IE-16 4.68E-09 5.72E-12 8.0SE-03 Th-230 29,000,242 5.SlE-16 9.56E-16 2.0SE-15 l.60E-08 7.90E-07 2.75E-02 Th-232 29,000,242 3.26E-16 5.67E-16 l.21E-15 9.47E-09 8.68E-02 8.16E-02 U-234 29,000,242 l.47E-IS 2.SSE-15 5.47E-15 4.26E-08 6 83E-06 2.94E-02 U-235 29,000,242 9.56E-17 l.66E-16 3.56E-16 2.77E-09 l.28E-03 I.59E-03 U-238 29,000,242 6.92E-16 l.20E-15 2.58E-15 2.0lE-08 5.99E-02 l.lSE-02 Total: 1.60E-01 Stack 796 Bldg. 100 16.35 m 3/min 0.27 m3/sec Pu-241 4,287,257 l.88E-15 8.24E-16 9.52E-l6 8.04E-09 7.SIE-11 2.34E-03 Tc-99 4,287,257 6.07E-14 2.67E-14 3.0SE-14 2.60E-07 l.54E-05 6.74E-05 U-234 4,287,257 3.00E-15 8.16E-15 l.76E-14 l.29E-08 2.06E-06 6.00E-02 U-235 4,287,257 9.28E-17 2.52E-16 5.44E-16 3.98E-10 l.84E-04 l.55E-03 Total: 6.40E-02
 
I ECV; Effluent Concentration Value from 1 *CFR-20, Appendix a. Fracl!On of ecv at the slack 1s provided for reference only. Concentrations at off~slte locations are
 
significantly less than those reported here (at stack) due to the atmospheric dispersion that occurs before the effluent exits the site.
Note: A value of "O~ was substituted for negative analytical results Printed: 02/05/2024 NFS-EDMS Page 3 of3
 
Page 9 of 14 21 G-24-0032 GOV-01-55 ACF-24-0033
 
Attachment 3 To Letter Dated February 14, 2024
 
Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed Off-Site Individual for the Release Period July to December 2023


(4 Pages to Follow)
Total Volume Location (ma)
Main Stack416 Th-228 265,683,538 Th-230 265,683,538 Th-232 265,683,538 U-234 265,683,538 U-235 265,683,538 U-238 265,683,538 Stack 234 Bldg. 234 Am-241 83,246,700 Pu-238 83,246,700 Pu-239/240 83,246,700 Pu-241 83,246,700 Th-228 83,246,700 Th-230 83,246,700 Th-232 83,246,700 U-234 83,246,700 U-238 83,246,700 Stack 327 Bldg. 330 Pu-241 255,277,191 Tc-99 255,277,191 U-234 255,277,191 U-235 255,277,191 Stack 421 Bldg. 100 Pu-241 9,345,920 Tc-99 9,345,920 U-234 9,345,920 U-235 9,345,920 Stack 424 Bldg. 100 Pu-241 9,006,009 Tc-99 9,006,009 U-234 9,006,009 U-235 9,006,009 Stack 573 Bldg 306-W Pu-241 29,974,550 Tc-99 29,974,550
\\
Radioactivity in Effluent Air July 1, 2023 to December 31, 2023 Activity Error Quantity Concentration Estimate LLD Released
(µCi/ml)
(µCi/ml)
(µCi/ml)
(Ci) 1013.64 mo/min 16.89 m3/sec l.09E-15 l.84E-16 7.86E-17 2.91E-07 l.09E-15 l.84E-16 7.86E-17 2.91E-07 8.21E-16 l.38E-16 5.89E-17 2.18E-07 2.58E-13 4.34E-14 1.85E-14 6.86E-05 9.85E-15 1.66E-15 7.0?E-16 2.62E-06 2.74E-15 4.60E-!6 l.96E-!6 7.27E-07 315.90 m3/min 5.27 m3!sec 4.65E-I 7 2.83E-17 4.25E-17 3.87E-09 5.68E-17 3.46E-17 5.19E-!7 4.73E-09 2.0lE-16 l.23E-16 1.84E-16 l.68E-08 9.59E-15 3.59E-15 4.62E-15 7.98E-07 3.lOE-17 l.89E-17 2.83E-17 2.SSE-09 3.87E-16 2.36E-16 3.54E-16 3.22E-08 4.91E-16 2.98E-16 4.48E-16 4.0SE-08 l.06E-15 6.44E-16 9.67E-16 8.SIE-08 3.IOE-16 l.89E-16 2.83E-16 2.58E-08 974.04 m3/min 16.23 m3/sec 2.89E-15 4.17E-16 4.99E-16 7.37E-07 9.34E-14 1.35E-14 l.61E-14 2.38E-05 5.79E-14 9.77E-15 8.42E-15 1.48E-05 1.79E-15 3.02E-16 2.60E-16 4.57E-07 35.68 mo/min 0.59 m3/sec 6.98E-15 l.22E-15 1.30E-15 6.52E-08 2.26E-13 3.96E-14 4.21E-14 2.I IE-06 2.88E-14 1.66E-14 2.27E-14 2.69E-07 8.9IE-16 S.14E-16 7.0IE-16 8.33E-09 34.38 m3/min 0.57 m 3/sec 2.4SE-15 9.l!E-16 9.57E-16 2.20E-08 7.91E-14 2.94E-14 3.09E-14 7.12E-07 2.00E-14 l.16E-14 J.76E-14 l.SOE-07 6.ISE-16 3.SSE-16 5.46E-16 S.57E-09 114.37 m3/min 1.91 m3/sec 1.27E-15 7.3 IE-16 l.OIE-15 3.82E-08 4.12E-14 2.37E-14 3.25E-14 l.23E-06 21 G-24-0032 GOV-01-55 ACF-24-0033 Quantity Fraction Released of (g)
ECV 1
3.SSE-10 5.47E-02 1.44E-05 5.47E-02 2.00E+OO 2.0SE-01 l.IOE-02 5.16E+OO l.21E+OO 1.64E-OI 2.17E+OO 4.56E-02 Total:
5.69E+00 1.13E-09 2.32E-03 2.77E-IO 2.84E-03 2.?0E-07 l.OIE-02 7.75E-09 l.20E-02 3.lSE-12 I SSE-03 1.60E-06 I.94E-02 3.75E-OI l.23E-O I l.41E-05 2.12E-02 7 ?OE-02 5.l6E-03 Total:
l.97E-0l 7.16E-09 3.61E-03 l.41E-03 l.04E-04 2.37E-03 l.16E+OO 2 12E-OI 2.99E-02 Total:
l.19E+00 6.33E-10 8.72E-03 l.25E-04 2.SIE-04 4.31E-05 S.76E-Ol 3.86E-03 l.49E-02 Total:
6.00E-01 2.14E-l0 3.06E-03 4.21E-05 8.79E-05 2.89E-05 4.00E-01 2.SSE-03 1.03E-02 Total:
4.13E-01 3.71E-IO l.59E-03 7.30E-05 4.SSE-05 ECV. Effluent concentration \\/alue from 10~CFR~20, Appendix B Fraction of ECV al the stack ls provided for reference only. concentrations at off~site locations are s1gmficantly less than those reported here (at stack) due to the atmospherfc dispersion that occurs before lhe effluent exits the site, Note* A value of "O" was substituted for negatlve analytical results.
Printed: 02/05/2024 NFS-EDMS Page I of3 Page 7 of 14


Page 10 of 14 21 G-24-0032 GOV-01-55 ACF-24-0033
Total Volume Location (m3)
Stack 573 Bldg 306-W U-234 29,974,550 U-235 29,974,550 Stack 600 Bldg. 110 Pu-241 77,455,900 Tc-99 77,455,900 U-234 77,455,900 U-235 77,455,900 Stack 615 Bldg. 306-W Pu-241 12,586,491 Tc-99 12,586,491 U-234 12,586,491 U-235 12,586,491 Stack 646 Bldg. 110 Pu-241 8,727,425 Tc-99 8,727,425 U-234 8,727,425 U-235 8,727,425 Stack 701 Bldg. 307 Pu-241 34,256,629 Tc-99 34,256,629 U-234 34,256,629 U-235 34,256,629 Stack 702 Bldg. 307 Pu-241 40,097,176 Tc-99 40,097,176 U-234 40,097,176 U-235 40,097,176 Stack 703 Exhaust Room Air Pu-241 125,899,447 Th-228 125,899,447 Th-230 125,899,447 Th-232 125,899,447 U-234 125,899,447 I
Radioactivity in Effluent Air July 1, 2023 to December 31, 2023 Activity Error Quantity Concentration Estimate LLD Released
(µCi/ml)
(µCi/ml)
(µCi/ml)
(Ci) 114.37 m3/min 1.91 m3/sec l.35E-15 7.12E-15 l.79E-14 4.04E-08
: 4. l 7E-17 2.20E-16 5.53E-16 l.2SE-09 295.54 m3/min 4.93 m3/sec 3.398-15 5.76E-16 6.62E-16 2.63E-07 1.IOE-13 1.868-14 2.14E-14 8.SOE-06 1.268-13 1.198-14 l.lSE-14 9.79E-06 3.91E-15 3.68E-16 3.668-16 3.03E-07 48.03 m3/min 0.80 m3tsec l.29E-15 7.26E-16 9.SOE-16 l.63E-08 4.l8E-14 2.35E-l4 3.07E-14 5.278-07 l.67E-l5 7.29E-15 l.75E-14 2.IOE-08 5.158-17 2.26E-16 S.42E-l6 6.488-10 33.30 m3/min 0.56 m3/sec 1.46E-15 7.60E-16 9.60E-16 1.28E-08 4.738-14 2.46E-14 3.IOE-14 4.13E-07 2.258-15 7.68E-IS 1.758-14 l.96E-08 6.948-17 2.378-16 S.43E-16 6.06E-l0 130.71 m3/min 2.18 m3/sec 1.528-15 8.358-16 1.098-15 5.2IE-08 4.928-14 2.708-14 3.538-14 1.688-06 3.908-15 9.27E-15 2.008-14 1.348-07 l.21E-16 2.87E-16 6.19E-16 4.138-09 153.00 m3/min 2.55 m3/sec l.62E-15 7.778-16 9.518-16 6.SIE-08 5.258-14 2.SlE-14 3 078-14 2.1 IE-06 l.46E-14 1.058-14 l.75E-14 5.848-07 4.SOE-16 3.24E-16 5.428-16 1.818-08 476.58 m3/min 7,94 m3/sec 4.04E-14 2.438-14 3.258-14 5.0SE-06 7.41E-16 9.13E-16 l.83E-15 9.33E-08 4.278-16 5.25E-16 1.058-15 S.37E-08 6.06E-16 7.47E-16 1.498-15 7.63E-08 4.64E-15 5.728-15 1.148-14 5.84E-07 21 G-24-0032 GOV-01-55 ACF-24-0033 Quantity Fraction Released of (g)
ECV 1
6.47E-06 2.70E-02 5.78E-04 6.95E-04 Total:
2.93E-02 2.55E-09 4.24E-03 5.03E-04 l.22E-04 l.57E-03 2.53E+OO l.40E-Ol 6.SIE-02 Total:
2.60E+00 l.58E-10 l.62E-03 3.!2E-05 4,658-05 3.36E-06 3.338-02 3.00E-04 8.59E-04 Total:
3.58E-02 I 24E-10 l.83E-03 2.44E-05 S.26E-OS 3.14E-06 4.498-02 2.818-04 1.16E-03 Total:
4.79E-02 5.068-10 1.908-03 9.97E-05 5.47E-05 2.148-05 7.808-02 1.918-03 2.018-03 Total:
8.19E-02 6.328-10 2.03E-03 1.258-04 S.83E-05 9.368-05 2.91E-OI 8.36E-03 7.SIE-03 Total:
3.0tE-01 4.93E-08 5.058-02 1.148-10 3.70E-02 2.66E-06 2.13E-02 7.00E-01 1.52E-01 9.36E-05 9.288-02 ECV: Effluent Concentration Value from 10-CFR-20, Appendix: 8. Fraction of ECV at the stack is provided for reference only Concentrations al off-site locations are s1gnlflcant1y less than those reported here (at stack) due to the atmospheric dispersion that occurs before the effluent exits the site.
Note. A value of 110"' was substituted for negative analytical results Printed: 02/05/2024 NFS-EDMS Page 2 of3 Page 8 of 14


Report of Potential Gaseous Effluent Dose to the Maximally Exposed Offsite Individual and on the Maximum Radionuclide Concentrations for the Period:
Total Volume Location (ml)
July to December 2023
Stack 703 Exhaust Room Air U-235 125,899,447 U-238 125,899,447 Stack 773 Bldg. 440 Pu-241 45,781,877 Th-228 45,781,877 Th-230 45,781,877 Th-232 45,781,877 U-234 45,781,877 U-235 45,781,877 U-238 45,781,877 Stack 774 Bldg. 301 Tc-99 29,000,242 Th-228 29,000,242 Th-230 29,000,242 Th-232 29,000,242 U-234 29,000,242 U-235 29,000,242 U-238 29,000,242 Stack 796 Bldg. 100 Pu-241 4,287,257 Tc-99 4,287,257 U-234 4,287,257 U-235 4,287,257 I
Radioactivity in Effluent Air July 1, 2023 to December 31, 2023 Activity Error Quantity Concentration Estimate LLD Released
(µCi/ml)
(µCi/ml)
(µCi/ml)
(Ci) 476.58 m3/min 7.94 m3/sec 4.79E-16 5.90E-16 l.lSE-15 6.03E-08 S.84E-16 7.19E-16 1.44E-IS 7.35E-08 174.69 m3/min 2.91 m3/sec 5.07E-14 3,04E-14 3.93E-14 2.32E-06 l.89E-16 l.30E-15 3.16E-IS 8.67E-09 2.44E-l6 l.67E-15 4.06E-15 l.12E-08 l.62E-16 l.lIE-15 2.71E-15 7.43E-09 5.0IE-16 3.43E-15 8.35E-15 2.29E-08 8.79E-17 6.02E-16 l.47E-15 4.03E-09 l.76E-16 l.20E-15 2.93E-15 8.0SE-09 214.25 m 3/min 3.57 m3/see 3.49E-13 2.56E-14 2.31E-l4 l.OlE-05 l.62E-16 2.SIE-16 6.0IE-16 4.68E-09 5.SlE-16 9.56E-16 2.0SE-15 l.60E-08 3.26E-16 5.67E-16 l.21E-15 9.47E-09 l.47E-IS 2.SSE-15 5.47E-15 4.26E-08 9.56E-17 l.66E-16 3.56E-16 2.77E-09 6.92E-16 l.20E-15 2.58E-15 2.0lE-08 16.35 m3/min 0.27 m3/sec l.88E-15 8.24E-16 9.52E-l6 8.04E-09 6.07E-14 2.67E-14 3.0SE-14 2.60E-07 3.00E-15 8.16E-15 l.76E-14 l.29E-08 9.28E-17 2.52E-16 5.44E-16 3.98E-10 21 G-24-0032 GOV-01-55 ACF-24-0033 Quantity Fraction Released of (g)
ECV 1
2.79E-02 7.98E-03 2.19E-Ol 9.73E-03 Total:
3.71E-01 2.26E-08 6.34E-02 l.06E-ll 9.47E-03 5.52E-07 l.22E-02 6.82E-02 4.06E-02 3.67E-06 I.OOE-02 l.86E-03 1.47E-03 2.40E-02 2.93E-03 Total:
l.40E-Ol 5 98E-04 3.87E-04 5.72E-12 8.0SE-03 7.90E-07 2.75E-02 8.68E-02 8.16E-02 6 83E-06 2.94E-02 l.28E-03 I.59E-03 5.99E-02 l.lSE-02 Total:
1.60E-01 7.SIE-11 2.34E-03 l.54E-05 6.74E-05 2.06E-06 6.00E-02 l.84E-04 l.55E-03 Total:
6.40E-02 ECV; Effluent Concentration Value from 1 *CFR-20, Appendix a. Fracl!On of ecv at the slack 1s provided for reference only. Concentrations at off~slte locations are significantly less than those reported here (at stack) due to the atmospheric dispersion that occurs before the effluent exits the site.
Note: A value of "O~ was substituted for negative analytical results Printed: 02/05/2024 NFS-EDMS Page 3 of3 Page 9 of 14 To Letter Dated February 14, 2024 21 G-24-0032 GOV-01-55 ACF-24-0033 Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed Off-Site Individual for the Release Period July to December 2023 (4 Pages to Follow)
Page 10 of 14


Introduction During this biannual period, NRC License SNM-124, Section 9.1.1.3, requires NFS to
21 G-24-0032 GOV-01-55 ACF-24-0033 Report of Potential Gaseous Effluent Dose to the Maximally Exposed Offsite Individual and on the Maximum Radionuclide Concentrations for the Period:
July to December 2023 Introduction During this biannual period, NRC License SNM-124, Section 9.1.1.3, requires NFS to  
'* assess the total effective dose equivalent (TEDE) to the maximally exposed offsite receptor and the maximum radioactive air concentrations at the site boundary attributable to NFS' air effluents. The required biannual assessment has been completed and the details of the assessment are provided in the subsequent sections.
'* assess the total effective dose equivalent (TEDE) to the maximally exposed offsite receptor and the maximum radioactive air concentrations at the site boundary attributable to NFS' air effluents. The required biannual assessment has been completed and the details of the assessment are provided in the subsequent sections.
Summary of Methods In accordance with SNM-124, Section 9.1.1.4, and internal procedure NFS-HS-A-27, the U.S. Department of Energy's CAP88-PC computer program was used to estimate off-site doses and activity concentrations for gaseous effluents. NFS operated fifteen (15) radiological stacks during the second half of 2023. Based on effluent types and stack physical characteristics, releases from these stacks were grouped into effective stacks for modeling purposes. To accommodate the co-location limitation of the model, the effective stacks were taken to be at the approximate center of the plant site. The distance to the site boundary (nearest model receptor distance) was conservatively taken to be 150 meters for all sectors.
Summary of Methods In accordance with SNM-124, Section 9.1.1.4, and internal procedure NFS-HS-A-27, the U.S. Department of Energy's CAP88-PC computer program was used to estimate off-site doses and activity concentrations for gaseous effluents. NFS operated fifteen (15) radiological stacks during the second half of 2023. Based on effluent types and stack physical characteristics, releases from these stacks were grouped into effective stacks for modeling purposes. To accommodate the co-location limitation of the model, the effective stacks were taken to be at the approximate center of the plant site. The distance to the site boundary (nearest model receptor distance) was conservatively taken to be 150 meters for all sectors.
Meteorological data was based on the average wind speed and direction frequencies from the onsite meteorological tower covering the time period for this report.
Meteorological data was based on the average wind speed and direction frequencies from the onsite meteorological tower covering the time period for this report.
Atmospheric stability class D (neutral atmosphere) was used for all releases (default value recommended by the U.S. Environmental Protection Agency in "User's Guide for COMPLY"). The most conservative inhalation class was assumed for each radionuclide released. A particle size (activity median aerodynamic diameter or AMAD) of 1.0 micron was assumed for modeling purposes since no information on actual particle sizes exists.
Atmospheric stability class D (neutral atmosphere) was used for all releases (default value recommended by the U.S. Environmental Protection Agency in "User's Guide for COMPLY"). The most conservative inhalation class was assumed for each radionuclide released. A particle size (activity median aerodynamic diameter or AMAD) of 1.0 micron was assumed for modeling purposes since no information on actual particle sizes exists.
Because CAP88-PC models releases over an entire year, the six-month source term (i.e., total curies of each radionuclide released over the period, given in Attachment 2) was annualized (i.e., transformed into a 12-month release) so that airborne activity concentrations would not be under-estimated during the release period.
Because CAP88-PC models releases over an entire year, the six-month source term (i.e., total curies of each radionuclide released over the period, given in Attachment 2) was annualized (i.e., transformed into a 12-month release) so that airborne activity concentrations would not be under-estimated during the release period.
Summary of Results Doses are reported in Table 1 below and are derived from the CAP88-PC "Synopsis Report." These doses are at the location of the maximally exposed (off-site) individual (MEI). The results include an adjustment (using the normalization factor mentioned above) to convert the "annualized" doses back to those doses that were actually received in the six-month release period. Activity concentrations reported in Table 2 come directly from the CAP88-PC "Concentration Tables" report; no adjustments are needed for these concentrations. The CAP88-PC output reports are available for review at NFS.
Page 11 of 14


Summary of Results Doses are reported in Table 1 below and are derived from the CAP88-PC "Synopsis Report." These doses are at the location of the maximally exposed (off-site) individual (MEI). The results include an adjustment (using the normalization factor mentioned above) to convert the "annualized" doses back to those doses that were actually received in the six-month release period. Activity concentrations reported in Table 2 come directly from the CAP88-PC "Concentration Tables" report; no adjustments are needed for these concentrations. The CAP88-PC output reports are available for review at NFS. Page 11 of 14 21 G-24-0032 GOV-01-55 ACF-24-0033
21 G-24-0032 GOV-01-55 ACF-24-0033 Table 1 summarizes the six-month dose to a hypothetical individual at the MEI location, which was determined to be approximately 600 meters North-Northeast from the center of the plant site. The TEDE to the MEI was estimated to be 5.2E-03 mrem for gaseous effluents released during the second half of 2023. The highest organ committed dose equivalent (COE) to the MEI was estimated to be 2.3E-02 mrem to the lungs. These MEI doses are well below the Environmental Radiological Monitoring Program action levels and applicabl~ regulatory limits/ALARA constraints.
 
Table 1. Organ Doses and Total Effective Dose Equivalent at the MEI Location Organ Adrenals Urinary Bladder Wall Bone Surface Brain Breasts Stomach Wall Small Intestine Upper Large Intestine Wall Lower Large Intestine Wall Kidneys Liver Muscle Ovaries Pancreas Red Bone Marrow Skin Spleen Testes Thymus Thyroid Gall Bladder Wall Heart Wall Uterus Extra-thoracic Lungs Total Effective Dose Equivalent Location of MEI:
Table 1 summarizes the six-month dose to a hypothetical individual at the MEI location, which was determined to be approximately 600 meters North-Northeast from the center of the plant site. The TEDE to the MEI was estimated to be 5.2E-03 mrem for gaseous effluents released during the second half of 2023. The highest organ committed dose equivalent (COE) to the MEI was estimated to be 2.3E-02 mrem to the lungs. These MEI doses are well below the Environmental Radiological Monitoring Program action levels and applicabl~ regulatory limits/ALARA constraints.
Committed Dose Equivalent (mrem per second half of 2023 )
 
3.9E-04 4.8E-04 1.4E-02 3.9E-04 4.0E-04 9.0E-03 4.4E-04 2.4E-03 6.3E-03 4.1E-03 1.3E-03 4.0E-04 4.3E-04 3.8E-04 1.9E-03 8.7E-04 3.9E-04 4.5E-04 3.9E-04 4.6E-03 3.8E-04 3.9E-04 3.9E-04 2.0E-02 2.3E-02 5.2E-03 mrem 600 meters North-Northeast Page 12 of 14  
Table 1. Organ Doses and Total Effective Dose Equivalent at the MEI Location
 
Organ Committed Dose Equivalent (mrem per second half of 2023 )
Adrenals 3.9E-04 Urinary Bladder Wall 4.8E-04 Bone Surface 1.4E-02 Brain 3.9E-04 Breasts 4.0E-04 Stomach Wall 9.0E-03 Small Intestine 4.4E-04 Upper Large Intestine Wall 2.4E-03 Lower Large Intestine Wall 6.3E-03 Kidneys 4.1E-03 Liver 1.3E-03 Muscle 4.0E-04 Ovaries 4.3E-04 Pancreas 3.8E-04 Red Bone Marrow 1.9E-03 Skin 8.7E-04 Spleen 3.9E-04 Testes 4.5E-04 Thymus 3.9E-04 Thyroid 4.6E-03 Gall Bladder Wall 3.8E-04 Heart Wall 3.9E-04 Uterus 3.9E-04 Extra-thoracic 2.0E-02 Lungs 2.3E-02
 
Total Effective Dose Equivalent 5.2E-03 mrem Location of MEI: 600 meters North-Northeast
 
Page 12 of 14 21 G-24-0032 GOV-01-55 ACF-24-0033
 
Table 2 summarizes the maximum radioactive air concentrations at or beyond the site boundary, as determined by CAP88-PC, for the radionuclides released. The total sum of fractions was estimated to be 7.8E-04 and indicates that exposures to the offsite public from gaseous effluents were much less than 1 % of the 10 CFR 20, Appendix B, Table 2, Col. 1 values for all offsite receptors including the site boundary. It is noted that the location of the maximum airborne concentration for a given radionuclide does not necessarily correspond to the MEI location. This is due primarily to the fact that the maximum concentrations for individual nuclides can vary due to differences in values input into the dispersion model for each of the effective stacks - such inputs include stack height, stack diameter, flow rate, and total radionuclide activities released per stack. Another reason for the disparity is the fact that the MEI dose includes both inhalation and ingestion pathways.
 
Table 2. Maximum Predicted Airborne Concentrations at or Beyond the Site Boundary
 
Maximum Predicted Ajrbome Concentrations at. ''
or Beyond the Site :Boundary
,i' ','
* Maximum Concentratfon* 10 CFR 20, App; B, Ratio of Maximum Nuclide Concentration ', Location Tabl~ 2, Col. 1 Value Concentration to :.*
((JCi/mL).Sector*
* Dist(m), (fJCi/mL) ).0 CJJ'R20 Value..
 
99Tc 3.9E-17 NNE 450 9.E-10 4.4E-08
 
22sTh l.5E-19 NNE 600 2.E-14 7.4E-06 230Th l.6E-19 NNE 550 2.E-14 7.9E-06
 
232Th l.7E-19 NNE 450 4.E-15 4.2E-05 234u 3.4E-17 NNE 650 5.E-14 6.9E-04 --
 
23su l.2E-18 NNE 650 6.E-14 2.0E-05
 
23su 2.7E-19 NNE 700 6.E-14 4.5E-06
 
238Pu 8.9E-21 NNE 250 2.E-14 4.5E-07
 
239Pu 3.2E-20 NNE 250 2.E-14 l.6E-06 241Pu 9.7E-18 NNE 400 8.E-13 l.2E-05
 
~- w- ~~-w-= -*
241Am 7.3E-21 NNE 250 2.E-14 3.7E-07 t.,
Sum of Fractions: 7.SE-04


Page 13 of 14 21 G-24-0032 GOV-01-55 ACF-24-0033
21 G-24-0032 GOV-01-55 ACF-24-0033 Table 2 summarizes the maximum radioactive air concentrations at or beyond the site boundary, as determined by CAP88-PC, for the radionuclides released. The total sum of fractions was estimated to be 7.8E-04 and indicates that exposures to the offsite public from gaseous effluents were much less than 1 % of the 10 CFR 20, Appendix B, Table 2, Col. 1 values for all offsite receptors including the site boundary. It is noted that the location of the maximum airborne concentration for a given radionuclide does not necessarily correspond to the MEI location. This is due primarily to the fact that the maximum concentrations for individual nuclides can vary due to differences in values input into the dispersion model for each of the effective stacks - such inputs include stack height, stack diameter, flow rate, and total radionuclide activities released per stack. Another reason for the disparity is the fact that the MEI dose includes both inhalation and ingestion pathways.
Table 2. Maximum Predicted Airborne Concentrations at or Beyond the Site Boundary Maximum Predicted Ajrbome Concentrations at.
or Beyond the Site :Boundary
,i'
'
* Maximum Concentratfon*
10 CFR 20, App; B, Ratio of Maximum Nuclide Concentration Location Tabl~ 2, Col. 1 Value Concentration to.*
((JCi/mL)
.Sector*
* Dist(m),
(fJCi/mL)
).0 CJJ'R20 Value..
99Tc 3.9E-17 NNE 450 9.E-10 4.4E-08 22sTh l.5E-19 NNE 600 2.E-14 7.4E-06 230Th l.6E-19 NNE 550 2.E-14 7.9E-06 232Th l.7E-19 NNE 450 4.E-15 4.2E-05 234u 3.4E-17 NNE 650 5.E-14 6.9E-04 23su l.2E-18 NNE 650 6.E-14 2.0E-05 23su 2.7E-19 NNE 700 6.E-14 4.5E-06 238Pu 8.9E-21 NNE 250 2.E-14 4.5E-07 239Pu 3.2E-20 NNE 250 2.E-14 l.6E-06 241Pu 9.7E-18 NNE 400 8.E-13 l.2E-05
~- w- ~~-w-= -*
241Am 7.3E-21 NNE 250 2.E-14 3.7E-07 t
Sum of Fractions:
7.SE-04 Page 13 of 14


The TEDE to the MEI for gaseous effluents released during 2023 is provided in Table 3.
21 G-24-0032 GOV-01-55 ACF-24-0033 The TEDE to the MEI for gaseous effluents released during 2023 is provided in Table 3.
The results for the 1st half of 2023 were previously reported in Biannual Effluent
The results for the 1st half of 2023 were previously reported in Biannual Effluent
* Monitoring Report January to June 2023 (21 G-23-0116). The annual dose is well below the Environmental Radiological Monitoring Program action levels and applicable regulatory limits/ALARA constraints.
* Monitoring Report January to June 2023 (21 G-23-0116). The annual dose is well below the Environmental Radiological Monitoring Program action levels and applicable regulatory limits/ALARA constraints.
 
Table 3. Annual Dose to the MEI for Gaseous Effluents Released During 2023  
Table 3. Annual Dose to the MEI for Gaseous Effluents Released During 2023
.JEDE Period Direction
 
* Distance Coyered *
,,.JEDE Period Direction
<ni)
* Distance
{mrem):
,. {mrem):
2nd Half NNE 600 5.2E-03 1st Half NE 450 4.2E-03
Coyered * <ni) 2nd Half NNE 600 5.2E-03
* Annual Total 9.4E-03 Page 14 of 14}}
 
1st Half NE 450 4.2E-03
* Annual Total 9.4E-03
 
Page 14 of 14}}

Latest revision as of 19:53, 24 November 2024

Nuclear Fuel Services, Inc. (NFS) Biannual Effluent Monitoring Report July to December 2023
ML24060A064
Person / Time
Site: Erwin
Issue date: 02/14/2024
From: Knowles T
BWXT Nuclear Fuel Services, Nuclear Fuel Services
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
21G-24-0032, GOV-01-55, ACF-24-0033
Download: ML24060A064 (1)
v • d • e


Text

Nuclear Fuel Services, Inc.

Certified Mail Return Receipt Requested 21 G-24-0032 GOV-01-55 ACF-24-0033 February 14, 2024 Director Office of Nuclear Material Safety & Safeguards U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Reference:

Docket No.70-143; SNM License 124

Subject:

Biannual Effluent Monitoring Report July to December 2023

Dear Director:

In accordance with the requirements set forth in 10 CFR Part 70.59, Nuclear Fuel Services, Inc. (NFS), submits the attached reports. Attachment 1 reports the Radioactivity in Effluent Liquid for the period July to December 2023. Attachment 2 reports the Radioactivity in Effluent Air for the period July to December 2023. Attachment 3 summarizes an evaluation of the dose and air activity concentrations for the maximally exposed offsite individual due to gaseous effluents during the period July to December 2023.

If you or your staff have any questions, require additional information, or wish to discuss this, please contact me or Mr. R. Jason Faddis, Deputy Environmental Protection and Industrial Safety Section Manager, at (423) 735-5438. Please reference our unique document identification number (21 G-24-0032) in any correspondence concerning this letter.

CJB/las Attachments Sincerely, NUCLEAR FUEL SERVICES, INC.

-J~~~

Tim Knowles Safety & Safeguards Director

1) Report of Radioactivity in Effluent Liquid for the Period July to December 2023
2) Report of Radioactivity in Effluent Air for the Period July to December 2023

~ms":,'2-0 lf:tD

[V/\\1\\SS

3) Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed Off-Site Individual for the Release Period July to December 2023 Page 1 Of 14 P e o p l e S t r 6 n g 1205 Banner Hill Rd, Erwin, TN 37650 t: +1.423.743.9141 f: +1.423.743.0140 www.nuclearfuelserv1ces.com

/NNDVAT/DN DR/VEN >

Copy:

Mr. Joel Rivera-Ortiz Senior Fuel Facility Inspector U. S. Nuclear Regulatory Commission Region II 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Regional Administrator U.S. Nuclear Regulatory Commission Region II 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Mr. James Downs Senior Project Manager Division of Fuel Management Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Two White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Dr. Robert Williams Chief, Projects Branch 1 U.S. Nuclear Regulatory Commission Region II 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Mr. Larry Harris Senior Resident Inspector U. S. Nuclear Regulatory Commission Page 2 of 14 21 G-24-0032 GOV-01-55 ACF-24-0033 To Letter Dated February 14, 2024 Report of Radioactivity in Effluent Liquid for the Period July to December 2023 (2 Pages to Follow)

Page 3 of 14 21 G-24-0032 GOV-01-55 ACF-24-0033

Radioactivity in Effluent Liquid July 1, 2023 to December 31, 2023 Total Activity Error Quantity Volume Concentration Estimate LLD Released Location (I)

(µCi/ml)

(µCi/ml)

(µCi/ml)

(Ci)

Banner Spring Down Pu-238 393,789,000 2.45E-13 1.02E-10 2.43E-10 9.66E-08 Pu-239/240 393,789,000 O.OOE+OO 1.31E-10 2.89E-10 O.OOE+OO Tc-99 393,789,000 O.OOE+OO 3.59E-08 6.27E-08 O.OOE+OO Th-228 393,789,000 O.OOE+OO 1.54E-10 3.SSE-10 O.OOE+OO Th-230 393,789,000 4.25E-l l 1.79E-10 3.64E-l0 l.67E-05 Th-232 393,789,000 l.64E-1 I l.29E-10 2 SSE-10 6.47E-06 U-233/234 393,789,000 4.76E-10 3.09E-10 3.43E-10 l.88E-04 U-235/236 393,789,000 4.68E-11 l.53E-10 2.41E-IO l.84E-05 U-238 393,789,000 5.56E-l 1 1.44E-10 2.48E-10 2.19E-05 Sewer Pu-238 22,383,314 l.29E-11 l.26E-10 2.59E-10 2.89E-07 Pu-239/240 22,383,314 3.46E-12 9.99E-ll 2.16E-10 7.73E-08 Tc-99 22,383,314 7.SSE-10 3.88E-08 6.72E-08 l.69E-05 Th-228 22,383,314 4.52E-ll l.90E-10 3.73E-10 l.OIE-06 Th-230 22,383,314 6.0SE-11 2.02E-10 3.87E-10 l.36E-06 Th-232 22,383,314 2.SIE-12 l.lSE-10 2.43E-10 5.61E-08 U-232 22,383,314 O.OOE+OO l.47E-IO 3.56E-10 O.OOE+OO U-233/234 22,383,314 6.67E-09 8.23E-10 2.26E-IO 1.49E-04 U-235/236 22,383,314 3.09E-10 l.91E-10 1.51E-10 6.93E-06 U-238 22,383,314 7.42E-10 2.75E-10 i.44E-10 l.66E-05 West Ditch Pu-238 144,342,000 3.18E-11 1.03E-10 2.16E-10 4.59E-06 Pu-239/240 144,342,000 O.OOE+OO I.OSE-10 2.58E-10 O.OOE+OO Tc-99 144,342,000 2.07E-09 3.SOE-08 6.06E-08 2.99E-04 Th-228 144,342,000 4.62E-12 l.44E-10 3.27E-10 6.67E-07 Th-230 144,342,000 5.45E-l I 1.61E-!0 3.0SE-10 7.86E-06 Th-232 144,342,000 O.OOE+OO 9.42E-ll 2.12E-10 O.OOE+OO U-233/234 144,342,000 l.52E-08 l.56E-09 3.48E-10 2.19E-03 U-235/236 144,342,000 6.06E-10 3.65E-10 2.33E-10 8.75E-05 U-238 144,342,000 l.lSE-09 4.31E-10 2.54E-IO l.66E-04 WWTF Am-241 3,395,574 2.38E-ll 5.77E-l l l.12E-10 8.07E-08 Cs-137 3,395,574 0.00E+OO 1.82E-09 1.85E-09 O.OOE+OO Na-22 3,395,574 2.00E-11 8.75E-10 l.59E-09 6.79E-08 Np-237 3,395,574 5.20E-11 2.54E-10 4.81E-10 l.76E-07 Pb-212 3,395,574 1.93E-09 3.59E-09 2.94E-09 6.56E-06 Pu-238 3,395,574 l.18E-11 6.23E-1 I l.20E-10 4.0lE-08 ECV emuent Conoerrtrat1on Value from 10-CFR-20,Appendlx a Note: A valoe of "O" was substituted for negative analytical results.

Printed: 02/05/2024 NFS-EDMS Page 4 of 14 Quantity Released (g) 5.65E-09 O.OOE+OO O.OOE+OO O.OOE+OO 8.28E-04 5.94E+Ol 3.0IE-02 8.53E+OO 6.54E+Ol Total:

l.69E-08 1.24E-06 l.OOE-03 1.23E-09 6.74E-05 5.lSE-01 O.OOE+OO 2.39E-02 3.21E+OO 4.96E+Ol Total:

2.68E-07 O.OOE+OO 1.77E-02 8.!SE-10 3.89E-04 O.OOE+OO 3.SlE-01 4.05E+Ol 4.96E+02 Total:

2.35E-08 O.OOE+OO 1.09E-11 2.SIE-04 4.74E-12 2.34E-09 21 G-24-0032 GOV-01-55 ACF-24-0033 Fraction of ECV 1

1.23E-05 O.OOE+OO O.OOE+OO O.OOE+OO 4.25E-04 5.48E-04 l.59E-03 1.56E-04 1.85E-04 2.91E-03 6.45E-05 1.73E-05 1.26E-06 2.26E-05 6.0SE-05 8.35E-06 O.OOE+OO 2.22E-03 l.03E-04 2.47E-04 2.75E-03 l.59E-03 O.OOE+OO 3.45E-05 2.31E-05 5.45E-04 O.OOE+OO 5.06E-02 2.02E-03 3.83E-03 5.86E-02 l.19E-03 O.OOE+OO 3.33E-06 2.60E-03 9.66E-04 5.90E-04 Page I of2

Radioactivity in Effluent Liquid July 1, 2023 to December 31, 2023 Total Activity Volume Concentration Location (I)

(µCi/ml)

WWTF Pu-239/240 3,395,574 3.14E-12 Pu-241 3,395,574 0.00E+OO Ra-224 3,395,574 l.46E-08 Tc-99 3,395,574 2.lSE-09 Th-228 3,395,574 O.OOE+OO Th-230 3,395,574 1.03E-10 Th-231 3,395,574 8.42E-09 Th-232 3,395,574 3.20E-12 U-232 3,395,574 O.OOE+OO U-233/234 3,395,574 7.87E-09 U-235/236 3,395,574 3.62E-l0 U-238 3,395,574 6.llE-11 ECV: Efflueol Coocenlratlon value from 10-CFR-20, Appendix B.

Note A value of "O~ was substttuted for negallve analytical results.

Printed: 02/05/2024 Error Quantity Estimate LLD Released

(µCi/ml)

(µCi/ml)

(Ci) 5.69E-ll l.23E-10 1.07E-08 1.19E-08 2.07E-08 O.OOE+OO 9.21E-09 l.73E-08 4.97E-05 3.79E-08 6.56E-08 7.30E-06 l.12E-l0 3.00E-10 O.OOE+OO l.89E-10 3.22E-10 3.SlE-07 4.76E-08 4.93E-08 2.86E-05 9.78E-ll 2.l lE-10 l.09E-08 l.l2E-10 2.64E-10 O.OOE+OO 6.95E-10 l.36E-10 2.67E-05 l.58E-10 l.l7E-JO l.23E-06 7.66E-ll l.02E-10 2.07E-07 NFS-EDMS Page 5 of 14 Quantity Released (g) l.72E-07 O.OOE+OO 3.13E-l0 4.32E-04 O.OOE+OO 1.74E-05 5.37E-ll 9.98E-02 O.OOE+OO 4.28E-03 5.68E-Ol 6.19E-Ol Total:

21 G-24-0032 GOV-01-55 ACF-24-0033 Fraction of ECV 1

l.57E-04 O.OOE+OO 7.32E-02 3.58E-05 O.OOE+OO l.03E-03 l.68E-04 l.07E-04 O.OOE+OO 2.62E-02 I.21E-03 2.04E-04 1.0SE-01 Page2 of2 To Letter Dated February 14, 2024 Report of Radioactivity in Effluent Air for the Period July to December 2023 (3 Pages to Follow)

Page 6 of 14 21 G-24-0032 GOV-01-55 ACF-24-0033

Total Volume Location (ma)

Main Stack416 Th-228 265,683,538 Th-230 265,683,538 Th-232 265,683,538 U-234 265,683,538 U-235 265,683,538 U-238 265,683,538 Stack 234 Bldg. 234 Am-241 83,246,700 Pu-238 83,246,700 Pu-239/240 83,246,700 Pu-241 83,246,700 Th-228 83,246,700 Th-230 83,246,700 Th-232 83,246,700 U-234 83,246,700 U-238 83,246,700 Stack 327 Bldg. 330 Pu-241 255,277,191 Tc-99 255,277,191 U-234 255,277,191 U-235 255,277,191 Stack 421 Bldg. 100 Pu-241 9,345,920 Tc-99 9,345,920 U-234 9,345,920 U-235 9,345,920 Stack 424 Bldg. 100 Pu-241 9,006,009 Tc-99 9,006,009 U-234 9,006,009 U-235 9,006,009 Stack 573 Bldg 306-W Pu-241 29,974,550 Tc-99 29,974,550

\\

Radioactivity in Effluent Air July 1, 2023 to December 31, 2023 Activity Error Quantity Concentration Estimate LLD Released

(µCi/ml)

(µCi/ml)

(µCi/ml)

(Ci) 1013.64 mo/min 16.89 m3/sec l.09E-15 l.84E-16 7.86E-17 2.91E-07 l.09E-15 l.84E-16 7.86E-17 2.91E-07 8.21E-16 l.38E-16 5.89E-17 2.18E-07 2.58E-13 4.34E-14 1.85E-14 6.86E-05 9.85E-15 1.66E-15 7.0?E-16 2.62E-06 2.74E-15 4.60E-!6 l.96E-!6 7.27E-07 315.90 m3/min 5.27 m3!sec 4.65E-I 7 2.83E-17 4.25E-17 3.87E-09 5.68E-17 3.46E-17 5.19E-!7 4.73E-09 2.0lE-16 l.23E-16 1.84E-16 l.68E-08 9.59E-15 3.59E-15 4.62E-15 7.98E-07 3.lOE-17 l.89E-17 2.83E-17 2.SSE-09 3.87E-16 2.36E-16 3.54E-16 3.22E-08 4.91E-16 2.98E-16 4.48E-16 4.0SE-08 l.06E-15 6.44E-16 9.67E-16 8.SIE-08 3.IOE-16 l.89E-16 2.83E-16 2.58E-08 974.04 m3/min 16.23 m3/sec 2.89E-15 4.17E-16 4.99E-16 7.37E-07 9.34E-14 1.35E-14 l.61E-14 2.38E-05 5.79E-14 9.77E-15 8.42E-15 1.48E-05 1.79E-15 3.02E-16 2.60E-16 4.57E-07 35.68 mo/min 0.59 m3/sec 6.98E-15 l.22E-15 1.30E-15 6.52E-08 2.26E-13 3.96E-14 4.21E-14 2.I IE-06 2.88E-14 1.66E-14 2.27E-14 2.69E-07 8.9IE-16 S.14E-16 7.0IE-16 8.33E-09 34.38 m3/min 0.57 m 3/sec 2.4SE-15 9.l!E-16 9.57E-16 2.20E-08 7.91E-14 2.94E-14 3.09E-14 7.12E-07 2.00E-14 l.16E-14 J.76E-14 l.SOE-07 6.ISE-16 3.SSE-16 5.46E-16 S.57E-09 114.37 m3/min 1.91 m3/sec 1.27E-15 7.3 IE-16 l.OIE-15 3.82E-08 4.12E-14 2.37E-14 3.25E-14 l.23E-06 21 G-24-0032 GOV-01-55 ACF-24-0033 Quantity Fraction Released of (g)

ECV 1

3.SSE-10 5.47E-02 1.44E-05 5.47E-02 2.00E+OO 2.0SE-01 l.IOE-02 5.16E+OO l.21E+OO 1.64E-OI 2.17E+OO 4.56E-02 Total:

5.69E+00 1.13E-09 2.32E-03 2.77E-IO 2.84E-03 2.?0E-07 l.OIE-02 7.75E-09 l.20E-02 3.lSE-12 I SSE-03 1.60E-06 I.94E-02 3.75E-OI l.23E-O I l.41E-05 2.12E-02 7 ?OE-02 5.l6E-03 Total:

l.97E-0l 7.16E-09 3.61E-03 l.41E-03 l.04E-04 2.37E-03 l.16E+OO 2 12E-OI 2.99E-02 Total:

l.19E+00 6.33E-10 8.72E-03 l.25E-04 2.SIE-04 4.31E-05 S.76E-Ol 3.86E-03 l.49E-02 Total:

6.00E-01 2.14E-l0 3.06E-03 4.21E-05 8.79E-05 2.89E-05 4.00E-01 2.SSE-03 1.03E-02 Total:

4.13E-01 3.71E-IO l.59E-03 7.30E-05 4.SSE-05 ECV. Effluent concentration \\/alue from 10~CFR~20, Appendix B Fraction of ECV al the stack ls provided for reference only. concentrations at off~site locations are s1gmficantly less than those reported here (at stack) due to the atmospherfc dispersion that occurs before lhe effluent exits the site, Note* A value of "O" was substituted for negatlve analytical results.

Printed: 02/05/2024 NFS-EDMS Page I of3 Page 7 of 14

Total Volume Location (m3)

Stack 573 Bldg 306-W U-234 29,974,550 U-235 29,974,550 Stack 600 Bldg. 110 Pu-241 77,455,900 Tc-99 77,455,900 U-234 77,455,900 U-235 77,455,900 Stack 615 Bldg. 306-W Pu-241 12,586,491 Tc-99 12,586,491 U-234 12,586,491 U-235 12,586,491 Stack 646 Bldg. 110 Pu-241 8,727,425 Tc-99 8,727,425 U-234 8,727,425 U-235 8,727,425 Stack 701 Bldg. 307 Pu-241 34,256,629 Tc-99 34,256,629 U-234 34,256,629 U-235 34,256,629 Stack 702 Bldg. 307 Pu-241 40,097,176 Tc-99 40,097,176 U-234 40,097,176 U-235 40,097,176 Stack 703 Exhaust Room Air Pu-241 125,899,447 Th-228 125,899,447 Th-230 125,899,447 Th-232 125,899,447 U-234 125,899,447 I

Radioactivity in Effluent Air July 1, 2023 to December 31, 2023 Activity Error Quantity Concentration Estimate LLD Released

(µCi/ml)

(µCi/ml)

(µCi/ml)

(Ci) 114.37 m3/min 1.91 m3/sec l.35E-15 7.12E-15 l.79E-14 4.04E-08

4. l 7E-17 2.20E-16 5.53E-16 l.2SE-09 295.54 m3/min 4.93 m3/sec 3.398-15 5.76E-16 6.62E-16 2.63E-07 1.IOE-13 1.868-14 2.14E-14 8.SOE-06 1.268-13 1.198-14 l.lSE-14 9.79E-06 3.91E-15 3.68E-16 3.668-16 3.03E-07 48.03 m3/min 0.80 m3tsec l.29E-15 7.26E-16 9.SOE-16 l.63E-08 4.l8E-14 2.35E-l4 3.07E-14 5.278-07 l.67E-l5 7.29E-15 l.75E-14 2.IOE-08 5.158-17 2.26E-16 S.42E-l6 6.488-10 33.30 m3/min 0.56 m3/sec 1.46E-15 7.60E-16 9.60E-16 1.28E-08 4.738-14 2.46E-14 3.IOE-14 4.13E-07 2.258-15 7.68E-IS 1.758-14 l.96E-08 6.948-17 2.378-16 S.43E-16 6.06E-l0 130.71 m3/min 2.18 m3/sec 1.528-15 8.358-16 1.098-15 5.2IE-08 4.928-14 2.708-14 3.538-14 1.688-06 3.908-15 9.27E-15 2.008-14 1.348-07 l.21E-16 2.87E-16 6.19E-16 4.138-09 153.00 m3/min 2.55 m3/sec l.62E-15 7.778-16 9.518-16 6.SIE-08 5.258-14 2.SlE-14 3 078-14 2.1 IE-06 l.46E-14 1.058-14 l.75E-14 5.848-07 4.SOE-16 3.24E-16 5.428-16 1.818-08 476.58 m3/min 7,94 m3/sec 4.04E-14 2.438-14 3.258-14 5.0SE-06 7.41E-16 9.13E-16 l.83E-15 9.33E-08 4.278-16 5.25E-16 1.058-15 S.37E-08 6.06E-16 7.47E-16 1.498-15 7.63E-08 4.64E-15 5.728-15 1.148-14 5.84E-07 21 G-24-0032 GOV-01-55 ACF-24-0033 Quantity Fraction Released of (g)

ECV 1

6.47E-06 2.70E-02 5.78E-04 6.95E-04 Total:

2.93E-02 2.55E-09 4.24E-03 5.03E-04 l.22E-04 l.57E-03 2.53E+OO l.40E-Ol 6.SIE-02 Total:

2.60E+00 l.58E-10 l.62E-03 3.!2E-05 4,658-05 3.36E-06 3.338-02 3.00E-04 8.59E-04 Total:

3.58E-02 I 24E-10 l.83E-03 2.44E-05 S.26E-OS 3.14E-06 4.498-02 2.818-04 1.16E-03 Total:

4.79E-02 5.068-10 1.908-03 9.97E-05 5.47E-05 2.148-05 7.808-02 1.918-03 2.018-03 Total:

8.19E-02 6.328-10 2.03E-03 1.258-04 S.83E-05 9.368-05 2.91E-OI 8.36E-03 7.SIE-03 Total:

3.0tE-01 4.93E-08 5.058-02 1.148-10 3.70E-02 2.66E-06 2.13E-02 7.00E-01 1.52E-01 9.36E-05 9.288-02 ECV: Effluent Concentration Value from 10-CFR-20, Appendix: 8. Fraction of ECV at the stack is provided for reference only Concentrations al off-site locations are s1gnlflcant1y less than those reported here (at stack) due to the atmospheric dispersion that occurs before the effluent exits the site.

Note. A value of 110"' was substituted for negative analytical results Printed: 02/05/2024 NFS-EDMS Page 2 of3 Page 8 of 14

Total Volume Location (ml)

Stack 703 Exhaust Room Air U-235 125,899,447 U-238 125,899,447 Stack 773 Bldg. 440 Pu-241 45,781,877 Th-228 45,781,877 Th-230 45,781,877 Th-232 45,781,877 U-234 45,781,877 U-235 45,781,877 U-238 45,781,877 Stack 774 Bldg. 301 Tc-99 29,000,242 Th-228 29,000,242 Th-230 29,000,242 Th-232 29,000,242 U-234 29,000,242 U-235 29,000,242 U-238 29,000,242 Stack 796 Bldg. 100 Pu-241 4,287,257 Tc-99 4,287,257 U-234 4,287,257 U-235 4,287,257 I

Radioactivity in Effluent Air July 1, 2023 to December 31, 2023 Activity Error Quantity Concentration Estimate LLD Released

(µCi/ml)

(µCi/ml)

(µCi/ml)

(Ci) 476.58 m3/min 7.94 m3/sec 4.79E-16 5.90E-16 l.lSE-15 6.03E-08 S.84E-16 7.19E-16 1.44E-IS 7.35E-08 174.69 m3/min 2.91 m3/sec 5.07E-14 3,04E-14 3.93E-14 2.32E-06 l.89E-16 l.30E-15 3.16E-IS 8.67E-09 2.44E-l6 l.67E-15 4.06E-15 l.12E-08 l.62E-16 l.lIE-15 2.71E-15 7.43E-09 5.0IE-16 3.43E-15 8.35E-15 2.29E-08 8.79E-17 6.02E-16 l.47E-15 4.03E-09 l.76E-16 l.20E-15 2.93E-15 8.0SE-09 214.25 m 3/min 3.57 m3/see 3.49E-13 2.56E-14 2.31E-l4 l.OlE-05 l.62E-16 2.SIE-16 6.0IE-16 4.68E-09 5.SlE-16 9.56E-16 2.0SE-15 l.60E-08 3.26E-16 5.67E-16 l.21E-15 9.47E-09 l.47E-IS 2.SSE-15 5.47E-15 4.26E-08 9.56E-17 l.66E-16 3.56E-16 2.77E-09 6.92E-16 l.20E-15 2.58E-15 2.0lE-08 16.35 m3/min 0.27 m3/sec l.88E-15 8.24E-16 9.52E-l6 8.04E-09 6.07E-14 2.67E-14 3.0SE-14 2.60E-07 3.00E-15 8.16E-15 l.76E-14 l.29E-08 9.28E-17 2.52E-16 5.44E-16 3.98E-10 21 G-24-0032 GOV-01-55 ACF-24-0033 Quantity Fraction Released of (g)

ECV 1

2.79E-02 7.98E-03 2.19E-Ol 9.73E-03 Total:

3.71E-01 2.26E-08 6.34E-02 l.06E-ll 9.47E-03 5.52E-07 l.22E-02 6.82E-02 4.06E-02 3.67E-06 I.OOE-02 l.86E-03 1.47E-03 2.40E-02 2.93E-03 Total:

l.40E-Ol 5 98E-04 3.87E-04 5.72E-12 8.0SE-03 7.90E-07 2.75E-02 8.68E-02 8.16E-02 6 83E-06 2.94E-02 l.28E-03 I.59E-03 5.99E-02 l.lSE-02 Total:

1.60E-01 7.SIE-11 2.34E-03 l.54E-05 6.74E-05 2.06E-06 6.00E-02 l.84E-04 l.55E-03 Total:

6.40E-02 ECV; Effluent Concentration Value from 1 *CFR-20, Appendix a. Fracl!On of ecv at the slack 1s provided for reference only. Concentrations at off~slte locations are significantly less than those reported here (at stack) due to the atmospheric dispersion that occurs before the effluent exits the site.

Note: A value of "O~ was substituted for negative analytical results Printed: 02/05/2024 NFS-EDMS Page 3 of3 Page 9 of 14 To Letter Dated February 14, 2024 21 G-24-0032 GOV-01-55 ACF-24-0033 Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed Off-Site Individual for the Release Period July to December 2023 (4 Pages to Follow)

Page 10 of 14

21 G-24-0032 GOV-01-55 ACF-24-0033 Report of Potential Gaseous Effluent Dose to the Maximally Exposed Offsite Individual and on the Maximum Radionuclide Concentrations for the Period:

July to December 2023 Introduction During this biannual period, NRC License SNM-124, Section 9.1.1.3, requires NFS to

'* assess the total effective dose equivalent (TEDE) to the maximally exposed offsite receptor and the maximum radioactive air concentrations at the site boundary attributable to NFS' air effluents. The required biannual assessment has been completed and the details of the assessment are provided in the subsequent sections.

Summary of Methods In accordance with SNM-124, Section 9.1.1.4, and internal procedure NFS-HS-A-27, the U.S. Department of Energy's CAP88-PC computer program was used to estimate off-site doses and activity concentrations for gaseous effluents. NFS operated fifteen (15) radiological stacks during the second half of 2023. Based on effluent types and stack physical characteristics, releases from these stacks were grouped into effective stacks for modeling purposes. To accommodate the co-location limitation of the model, the effective stacks were taken to be at the approximate center of the plant site. The distance to the site boundary (nearest model receptor distance) was conservatively taken to be 150 meters for all sectors.

Meteorological data was based on the average wind speed and direction frequencies from the onsite meteorological tower covering the time period for this report.

Atmospheric stability class D (neutral atmosphere) was used for all releases (default value recommended by the U.S. Environmental Protection Agency in "User's Guide for COMPLY"). The most conservative inhalation class was assumed for each radionuclide released. A particle size (activity median aerodynamic diameter or AMAD) of 1.0 micron was assumed for modeling purposes since no information on actual particle sizes exists.

Because CAP88-PC models releases over an entire year, the six-month source term (i.e., total curies of each radionuclide released over the period, given in Attachment 2) was annualized (i.e., transformed into a 12-month release) so that airborne activity concentrations would not be under-estimated during the release period.

Summary of Results Doses are reported in Table 1 below and are derived from the CAP88-PC "Synopsis Report." These doses are at the location of the maximally exposed (off-site) individual (MEI). The results include an adjustment (using the normalization factor mentioned above) to convert the "annualized" doses back to those doses that were actually received in the six-month release period. Activity concentrations reported in Table 2 come directly from the CAP88-PC "Concentration Tables" report; no adjustments are needed for these concentrations. The CAP88-PC output reports are available for review at NFS.

Page 11 of 14

21 G-24-0032 GOV-01-55 ACF-24-0033 Table 1 summarizes the six-month dose to a hypothetical individual at the MEI location, which was determined to be approximately 600 meters North-Northeast from the center of the plant site. The TEDE to the MEI was estimated to be 5.2E-03 mrem for gaseous effluents released during the second half of 2023. The highest organ committed dose equivalent (COE) to the MEI was estimated to be 2.3E-02 mrem to the lungs. These MEI doses are well below the Environmental Radiological Monitoring Program action levels and applicabl~ regulatory limits/ALARA constraints.

Table 1. Organ Doses and Total Effective Dose Equivalent at the MEI Location Organ Adrenals Urinary Bladder Wall Bone Surface Brain Breasts Stomach Wall Small Intestine Upper Large Intestine Wall Lower Large Intestine Wall Kidneys Liver Muscle Ovaries Pancreas Red Bone Marrow Skin Spleen Testes Thymus Thyroid Gall Bladder Wall Heart Wall Uterus Extra-thoracic Lungs Total Effective Dose Equivalent Location of MEI:

Committed Dose Equivalent (mrem per second half of 2023 )

3.9E-04 4.8E-04 1.4E-02 3.9E-04 4.0E-04 9.0E-03 4.4E-04 2.4E-03 6.3E-03 4.1E-03 1.3E-03 4.0E-04 4.3E-04 3.8E-04 1.9E-03 8.7E-04 3.9E-04 4.5E-04 3.9E-04 4.6E-03 3.8E-04 3.9E-04 3.9E-04 2.0E-02 2.3E-02 5.2E-03 mrem 600 meters North-Northeast Page 12 of 14

21 G-24-0032 GOV-01-55 ACF-24-0033 Table 2 summarizes the maximum radioactive air concentrations at or beyond the site boundary, as determined by CAP88-PC, for the radionuclides released. The total sum of fractions was estimated to be 7.8E-04 and indicates that exposures to the offsite public from gaseous effluents were much less than 1 % of the 10 CFR 20, Appendix B, Table 2, Col. 1 values for all offsite receptors including the site boundary. It is noted that the location of the maximum airborne concentration for a given radionuclide does not necessarily correspond to the MEI location. This is due primarily to the fact that the maximum concentrations for individual nuclides can vary due to differences in values input into the dispersion model for each of the effective stacks - such inputs include stack height, stack diameter, flow rate, and total radionuclide activities released per stack. Another reason for the disparity is the fact that the MEI dose includes both inhalation and ingestion pathways.

Table 2. Maximum Predicted Airborne Concentrations at or Beyond the Site Boundary Maximum Predicted Ajrbome Concentrations at.

or Beyond the Site :Boundary

,i'

'

  • Maximum Concentratfon*

10 CFR 20, App; B, Ratio of Maximum Nuclide Concentration Location Tabl~ 2, Col. 1 Value Concentration to.*

((JCi/mL)

.Sector*

  • Dist(m),

(fJCi/mL)

).0 CJJ'R20 Value..

99Tc 3.9E-17 NNE 450 9.E-10 4.4E-08 22sTh l.5E-19 NNE 600 2.E-14 7.4E-06 230Th l.6E-19 NNE 550 2.E-14 7.9E-06 232Th l.7E-19 NNE 450 4.E-15 4.2E-05 234u 3.4E-17 NNE 650 5.E-14 6.9E-04 23su l.2E-18 NNE 650 6.E-14 2.0E-05 23su 2.7E-19 NNE 700 6.E-14 4.5E-06 238Pu 8.9E-21 NNE 250 2.E-14 4.5E-07 239Pu 3.2E-20 NNE 250 2.E-14 l.6E-06 241Pu 9.7E-18 NNE 400 8.E-13 l.2E-05

~- w- ~~-w-= -*

241Am 7.3E-21 NNE 250 2.E-14 3.7E-07 t

Sum of Fractions:

7.SE-04 Page 13 of 14

21 G-24-0032 GOV-01-55 ACF-24-0033 The TEDE to the MEI for gaseous effluents released during 2023 is provided in Table 3.

The results for the 1st half of 2023 were previously reported in Biannual Effluent

  • Monitoring Report January to June 2023 (21 G-23-0116). The annual dose is well below the Environmental Radiological Monitoring Program action levels and applicable regulatory limits/ALARA constraints.

Table 3. Annual Dose to the MEI for Gaseous Effluents Released During 2023

.JEDE Period Direction

  • Distance Coyered *

<ni)

{mrem):

2nd Half NNE 600 5.2E-03 1st Half NE 450 4.2E-03

  • Annual Total 9.4E-03 Page 14 of 14
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