ML21238A011: Difference between revisions
StriderTol (talk | contribs) (StriderTol Bot insert) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:Nuclear Fuel Services, Inc. | {{#Wiki_filter:Nuclear Fuel Services, Inc. | ||
21G-21-0103 Certified Mail | 21G-21-0103 Certified Mail GOV-01-55 Return Receipt Requested ACF-21-0182 August 16, 2021 Director Office of Nuclear Material Safety & Safeguards U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 | ||
==Reference:== | ==Reference:== | ||
Line 26: | Line 26: | ||
==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 January to June 2021. Attachment 2 reports the Radioactivity in Effluent Air for the period January to June 2021. 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 January to June 2021. | |||
If you or your staff have any questions, require additional information, or wish to discuss this, please contact me or Mr. R. Jason Faddis, Environmental Safety Unit Manager, at (423) 735-5438. Please reference our unique document identification number (21G 0103) 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, Environmental Safety Unit Manager, at (423) 735-5438. Please reference our unique document identification number (21G | |||
Sincerely, NUCLEAR FUEL SERVICES, INC. | Sincerely, | ||
IE4? | |||
NUCLEAR FUEL SERVICES, INC. IE4? | |||
,:J~/~ !lflvj552D | |||
Tim Knowles | |||
Tim Knowles jl}Jv/55 Safety & Safeguards Director CJB/pj/smd Attachments | |||
: 1) Report of Radioactivity in Effluent Liquid for the Period January to June 2021 | : 1) Report of Radioactivity in Effluent Liquid for the Period January to June 2021 | ||
: 2) Report of Radioactivity in Effluent Air for the Period January to June 2021 | : 2) Report of Radioactivity in Effluent Air for the Period January to June 2021 | ||
: 3) Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed Off-Site Individual for the Release Period January to June 2021 | : 3) Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed Off-Site Individual for the Release Period January to June 2021 | ||
1205 Banner Hill Rd, Erwin, TN 37650 Page 1 of 13 People Strong | |||
t: +1.423.743.9141 f: +1.423.743.0140 www.nuclearfuelservices.com INNOVATION DRIVEN > | |||
21G-21-0103 GOV-01-55 ACF-21-0182 | |||
Copy: | |||
Mr. Joel Rivera-Ortiz | 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 Fire Protection Engineer 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 13 | *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 Fire Protection Engineer 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 13 21G-21-0103 GOV-01-55 ACF-21-0182 | |||
Attachment 1 To Letter Dated August 16, 2021 | |||
Report of Radioactivity in Effluent Liquid for the Period January to June 2021 | |||
(2 Pages to Follow) | |||
Page 3 of 13 21 G-21-01 03 GOV-01-55 ACF-21-0182 Radioactivity in Effluent Liquid January 1, 2021 to June 30, 2021 | |||
Total Activity Error Quantity Quantity Fraction Volume Concentration Estimate LLD Released Released of Location (I) (µCi/ml) (µCi/ml) (µCi/ml) (Ci) (g) ECV1 Banner Spring Down Pu-238 472,037,000 0.00E+OO 8.57E-l l 2.28E-10 0.00E+OO O.OOE+OO O.OOE+OO Pu-239/240 472,037,000 O.OOE+OO 9.4JE-l l 2.40E-10 O.OOE+OO O.OOE+OO O.OOE+OO Tc-99 472,037,000 O.OOE+OO 3.44E-08 6.1 OE-08 0.00E+OO O.OOE+OO O.OOE+OO Th-228 472,037,000 1.08E-11 1.43E-IO 2.99E-10 5.IOE-06 6.22E-09 5.40E-05 Th-230 472,037,000 3.59E-l I l.81E-10 3.66E-10 l.70E-05 8.40E-04 3.59E-04 Th-232 472,037,000 O.OOE+OO l.OOE-10 2.67E-10 O.OOE+OO O.OOE+OO O.OOE+OO U-233/234 472,037,000 2.73E-10 2.SIE-10 3.43E-10 1.29E-04 2.07E-02 9.llE-04 U-235/236 472,037,000 1.90E-ll 1.42E-10 2.89E-10 8.96E-06 4.ISE+OO 6.33E-05 U-238 472,037,000 5.64E-l l l.58E-IO 2.82E-10 2.66E-05 7.95E+Ol 1.88E-04 | |||
Total: 1.58E-03 Sewer Pu-238 25,036,000 O.OOE+OO l.l lE-10 2.41E-10 O.OOE+OO O.OOE+OO O.OOE+OO Pu-239/240 25,036,000 O.OOE+OO 1.22E-10 2.92E-10 O.OOE+OO O.OOE+OO O.OOE+OO Tc-99 25,036,000 3.62E-09 3.74E-08 6.SSE-08 9.05E-05 5.36E-03 6.03E-06 Th-228 25,036,000 l.88E-l l 2.43E-IO 4.88E-10 4.71E-07 5.75E-10 9.41E-06 Th-230 25,036,000 l.58E-10 3.08E-IO 4.97E-10 3.97E-06 l.96E-04 l.58E-04 Th-232 2s,0J6,poo O.OOE+OO l.68E-IO 3.93E-10 O.OOE+OO O.OOE+OO O.OOE+OO U-232 25,036,000 3.03E-ll l.83E-IO 3.74E-10 7.59E-07 3.55E-08 5.0SE-05 U-233/234 25,036,000 l.8 !E-08 1.40E-09 2.9!E-10 4.54E-04 7.27E-02 6.04E-03 U-235/236 25,036,000 7.02E-10 3.03E-10 2.56E-10 l.76E-05 8.14E+OO 2.34E-04 U-238 25,036,000 2.57E-09 5.38E-IO 2.SSE-10 6.44E-05 l.92E+02 8.58E-04 | |||
Total: 7.36E-03 West Ditch Pu-238 169,304,000 O.OOE+OO l.12E-10 2.79E-10 O.OOE+OO O.OOE+OO O.OOE+OO Pu-239/240 169,304,000 O.OOE+OO l.22E-10 3.45E-10 O.OOE+OO O.OOE+OO O.OOE+OO Tc-99 169,304,000 5.83E-09 3.48E-08 6.06E-08 9.87E-04 5.84E-02 9.72E-05 Th-228 169,304,000 l.17E-ll l.76E-10 3.92E-10 l.98E-06 2.4!E-09 5.84E-05 Th-230 169,304,000 7.71E-ll 2.ISE-10 4.03E-10 l.30E-05 6.46E-04 7.71E-04 Th-232 169,304,000 O.OOE+OO 1.25E-IO 2.76E-10 O.OOE+OO 0.00E+OO O.OOE+OO U-233/234 169,304,000 l.SIE-08 l.40E-09 3.14E-10 2.56E-03 4.l lE-01 5.0SE-02 U-235/236 169,304,000 7.09E-10 3.SIE-10 2.SIE-10 l.20E-04 5.56E+O! 2.36E-03 U-238 169,304,000 l.53E-09 4.SIE-10 2.33E-10 2.59E-04 7.72E+02 5.09E-03 | |||
Total: 5.89E-02 WWTF Am-241 3,947,307 O.OOE+OO 9.48E-11 2.19E-10 O.OOE+OO O.OOE+OO O.OOE+OO Cs-137 3,947,307 O.OOE+OO l.24E-09 l.43E-09 O.OOE+OO O.OOE+OO O.OOE+OO Na-22 3,947,307 8.95E-11 8.13E-10 l.39E-09 3.53E-07 5.66E-11 l.49E-05 Np-237 3,947,307 2.61E-l l 2.74E-IO 5.62E-IO l.03E-07 1.46E-04 l.3 IE-03 Pb-212 3,947,307 1.20E-09 3.35E-09 3.02E-09 4.72E-06 3.41E-12 5.98E-04 Pu-238 3,947,307 l.33E-l l 5.35E-l l l.07E-10 5.27E-08 3.08E-09 6.67E-04 | |||
1 ECV: Effluent Concentration Value from 10-CFR-20, Appendix B. | |||
Note: A value of "a~ was substituted for negative analytical results. | |||
Printed: 08/04/2021 NFS-EDMS Page I of2 | |||
Page 4 of 13 21G-21-0103 GOV-01-55 ACF-21-0182 Radioactivity in Effluent Liquid January 1, 2021 to June 30, 2021 | |||
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 WWTF Pu-239/240 3,947,307 O.OOE+OO 6.32E-l 1 I.57E-IO O.OOE+OO O.OOE+OO O.OOE+OO Pu-241 3,947,307 4.56E-IO I.OIE-08 I. 74E-08 l.SOE-06 1.75E-08 4.56E-04 Ra-224 3,947,307 l.20E-08 6.69E-09 l.20E-08 4.73E-05 2.98E-IO 5.99E-02 Tc-99 3,947,307 4.75E-09 l.30E-07 2.24E-07 1.87E-05 I.I IE-03 7.91E-05 Th-228 3,947,307 O.OOE+OO I.SIE-10 3.74E-IO O.OOE+OO O.OOE+OO O.OOE+OO Th-230 3,947,307 l.16E-10 2.23E-IO 3.87E-10 4.60E-07 2.28E-05 l.16E-03 Th-231 3,947,307 O.OOE+OO 3.98E-08 3.89E-08 O.OOE+OO O.OOE+OO O.OOE+OO Th-232 3,947,307 3.63E-II l.33E-IO 2.37E-IO 1.43E-07 1.3 IE+OO l.21E-03 U-232 3,947,307 O.OOE+OO I.ISE-10 2.45E-IO O.OOE+OO O.OOE+OO O.OOE+OO U-233/234 3,947,307 l.34E-08 9.28E-IO 1.75E-IO 5.30E-05 8.50E-03 4.48E-02 U-235/236 3,947,307 5.96E-IO 2.06E-IO l.06E-IO 2.35E-06 l.09E+OO l.99E-03 U-238 3,947,307 9.75E-l l l.02E-10 l.34E-IO 3.85E-07 I.ISE+OO 3.25E-04 | |||
Total: 1.IJE-01 | |||
ECV: Effluent Concentration Value from 10-CFR-20, Appendix B. | ECV: Effluent Concentration Value from 10-CFR-20, Appendix B. | ||
Note: A value of "O" was substituted for negative analytical results. | Note: A value of "O" was substituted for negative analytical results. | ||
Printed: 08/04/2021 | Printed: 08/04/2021 NFS-EDMS Page 2 of2 | ||
21G-21-0103 GOV-01-55 ACF-21-0182 | Page 5 of 13 21G-21-0103 GOV-01-55 ACF-21-0182 | ||
21G-21-0103 GOV-01-55 ACF-21-0182 | Attachment 2 To Letter Dated August 16, 2021 | ||
(µCi/ml) | |||
Report of Radioactivity in Effluent Air for the Period January to June 2021 | |||
(3 Pages to Follow) | |||
Page 6 of 13 21G-21-0103 GOV-01-55 ACF-21-0182 Radioactivity in Effluent Air January 1, 2021 to June 30, 2021 | |||
Total Activity Error Quantity Quantity Fraction Volume Concentration Estimate LLD Released Released of Location (mJ) (µCi/ml) (µCi/ml) (µCi/ml) (Ci) (g) ECV1 Main Stack 416 1070.66 m 3/min 17.84 m3tsec Th-228 282,139,411 6.58E-16 l.50E-16 8.16E-I 7 I.86E-07 2.27E-10 3.29£-02 Th-230 282,139,411 6.58E-16 l.50E-16 8. 16E-l 7 l.86E-07 9.19E-06 3.29E-02 Th-232 282,139,411 4.94E-16 1.13E-16 6.12E-17 l.39E-07 l.28E+00 l.23E-0l U-234 282,139,411 l.55E-13 3.54E-14 l.92E-l 4 4.38E-05 7.02E-03 3.I0E+00 U-235 282,139,411 5.92E-15 l.35E-15 7.35E-16 I.67E-06 7.74E-0l 9.87E-02 U-238 282,139,411 l.65E-15 3.76E-16 2.04E-16 4.64E-07 l.39E+00 2.74E-02 | |||
Total: 3.42E+00 Stack 185 Bldg. 131 112.74 m 3/min 1.88 m3tsec Pu-241 29,384,273 4.92E-16 9.20E-16 l.62E-15 l.45E-08 l.40E-10 6.!6E-04 Tc-99 29,384,273 l.59E-14 2.98E-14 5.23E-14 4.68E-07 2.77E-05 1.77£-05 U-234 29,384,273 2.42E-16 7.61E-15 l.93E-14 7.12E-09 l.14E-06 4.85E-03 U-235 29,384,273 7.50E-18 2.36E-16 5.98E-16 2.20E-I0 l.02E-04 l.25E-04 | |||
Total: 5.61E-03 Stack 234 Bldg. 234 328.49 m 3/min 5.47 m3tsec Am-241 85,678,107 5.83E-l 7 2.63E-17 4.34E-l 7 5.00E-09 I.46E-09 2.92E-03 Pu-238 85,678,107 7.13E-l 7 3.22E-l7 5.30E-17 6.I IE-09 3.57E-10 3.56E-03 Pu-239/240 85,678,107 2.53E-16 l.14E-16 l.88E-l6 2.16E-08 3.48E-07 l.26E-02 Pu-241 85,678,107 4.78E-15 4.34E-15 7.l3E-15 4.09E-07 3.98E-09 5.97E-03 Th-228 85,678,107 3.89E-l 7 l.75E-l 7 2.89E-17 3.33E-09 4.07E-12 l.94E-03 Th-230 85,678,107 4.86E-16 2.19E-16 3.62E-l6 4.16E-08 2.06E-06 2.43E-02 Th-232 85,678,107 6.15E-l6 2.78E-16 4.58E-16 5.27E-08 4.84E-0I 1.54E-0l U-234 85,678,107 l.33E-15 5.99E-l6 9.89E-l6 l.14E-07 1.82E-05 2.66E-02 U-238 85,678,107 3.89E-16 l.75E-16 2.89E-l6 3.33E-08 9.94E-02 6.48E-03 | |||
Total: 2.38E-0l Stack 327 Bldg. 330 1036.36 m 3/min 17.27 m3tsec Pu-241 270,157,102 2.50E-15 5.19E-l6 7.28E-16 6.75E-07 6.55E-09 3.12E-03 Tc-99 270,157,102 8.08E-14 l.68E-14 2.35E-l4 2.18E-05 l.29E-03 8.98E-05 U-234 270,157,102 1.40E-13 l.3 IE-14 8.78E-15 3.77£-05 6.05E-03 2.79E+00 U-235 270,157,102 4.32E-15 4.05E-16 2.71E-l6 l.l 7E-06 5.40E-01 7.20E-02 | |||
Total: 2.87E+00 Stack 421 Bldg. 100 32.96 m 3/min 0.55 m3tsec Pu-241 8,590,906 3.61E-l5 l.28E-15 l.95E-15 3. I0E-08 3.0IE-10 4.51E-03 Tc-99 8,590,906 1.17E-13 4.15E-14 6.30E-14 I.00E-06 5.93E-05 l.30E-04 U-234 8,590,906 1.26E-l4 1.29E-14 2.12E-14 1.08E-07 l.74E-05 2.52E-0l U-235 8,590,906 3.90E-16 3.98£-16 6.55E-16 3.35E-09 l.55E-03 6.50E-03 | |||
Total: 2.63E-0l Stack 424 Bldg. 100 32.62 m 3/min 0.54 m 3/sec Pu-241 8,502,340 1.29E-15 l.02E-15 1.57E-l 5 l.09E-08 l.06E-10 l.6 IE-03 Tc-99 8,502,340 4.16E-14 3.31E-14 5.0SE-14 3.54E-07 2.09E-05 4.62E-05 | |||
ECV: Effluent Concentralion Value from 10-CFR-20, Appendix B. Fraction o*f ECV at the stack is provided for rererence only. Concentrations at off-site significantly less than those reported here (at stack) due to the atmospheric dispersion that occurs before the effluent locations are exits the site. | |||
Note: A value of "O~ was substituted for negative analytical results. | Note: A value of "O~ was substituted for negative analytical results. | ||
Printed: 08/04/2021 | Printed: 08/04/2021 NFS-EDMS Page 1 of3 | ||
Page 7 of 13 21G-21-0103 GOV-01-55 ACF-21-0182 Radioactivity in Effluent Air January 1, 2021 to June 30, 2021 | |||
Total Activity Error Quantity Quantity Fraction Volume Concentration Estimate LLD Released Released of Location (m3) (µCi/ml) (µCi/ml) (µCi/ml) (Ci) (g) ECV1 Stack 424 Bldg. 100 32.62 m 3/min 0.54 m3/sec U-234 8,502,340 8.14E-15 l.09E-14 1.88E-14 6.92E-08 l.llE-05 l.63E-01 U-235 8,502,340 2.52E-16 3.38E-16 5.SIE-16 2.14E-09 9.91E-04 4.20E-03 | |||
Total: l.69E-0l Stack 573 Bldg 306-W 120.88 m 3/min 2.01 m3/sec Pu-241 31,507,371 3.97E-16 8.ISE-16 l.49E-15 l.25E-08 l.21E-10 4.96E-04 Tc-99 31,507,371 1.28E-14 2.64E-14 4.SIE-14 4.04E-07 2.39E-05 l.43E-05 U-234 31,507,371 1.78E-16 6.65E-15 1.SOE-14 5.60E-09 8.98E-07 3.56E-03 U-235 31,507,371 5.SOE-18 2.06E-16 5.57E-16 l.73E-10 8.02E-05 9.16E-05 | |||
Total: 4.16E-03 Stack 600 Bldg. 110 319.61 m 3/min 5.33 m 3/sec Pu-241 83,303,746 1.23E-15 5.93E-16 9.73E-16 l.03E-07 9.99E-IO 1.54E-03 Tc-99 83,303,746 3.99E-14 l.92E-14 3.ISE-14 3.33E-06 l.97E-04 4.44E-05 U-234 83,303,746 2.46E-14 8.07E-15 1.22E-14 2.0SE-06 3.29E-04 4.92E-01 U-235 83,303,746 7.61E-16 2.SOE-16 3.78E-16 6.34E-08 2.94E-02 l.27E-02 | |||
Total: 5.06E-01 Stack 615 Bldg. 306-W 48.41 m 3/min 0.81 m 3/sec Pu-241 12,618,460 3.07E-16 8.62E-16 l.57E-15 3.88E-09 3.77E-ll 3.84E-04 Tc-99 12,618,460 9.94E-15 2.79E-14 5.0SE-14 1.25E-07 7.42E-06 l.lOE-05 U-234 12,618,460 3.02E-16 7.32E-15 1.88E-14 3.SIE-09 6.IOE-07 6.03E-03 U-235 12,618,460 9.33E-18 2.26E-16 5.SIE-16 l.lSE-10 5.45E-05 l.55E-04 | |||
Total: 6.58E-03 Stack 646 Bldg. 110 37.49 m 3/min 0.62 m 3/sec Pu-241 9,771,787 5.32E-16 9.0IE-16 l.57E-15 5.20E-09 5.0SE-ll 6.65E-04 Tc-99 9,771,787 l.72E-14 2.91E-14 5.07E-14 l.68E-07 9.94E-06 l.91E-05 U-234 9,771,787 9.59E-16 7.68E-15 l.88E-14 9.38E-09 l.SOE-06 l.92E-02 U-235 9,771,787 2.97E-17 2.38E-16 5.SOE-16 2.90E-10 l.34E-04 4.95E-04 | |||
Total: 2.04E-02 Stack 701 Bldg. 307 119.13 m 3/min 1.99 m 3/sec Pu-241 31,049,779 3.58E-!6 9.91E-16 I.SOE-IS l.llE-08 I.OSE-10 4.47E-04 Tc-99 31,049,779 l.16E-14 3.20E-14 5.84E-14 3.59E-07 2.13E-05 l.29E-05 U-234 31,049,779 2.60E-15 9.65E-15 2.16E-14 8.07E-08 l.29E-05 5.20E-02 U-235 31,049,779 8.04E-17 2.99E-16 6.67E-16 2.SOE-09 l.16E-03 l.34E-03 | |||
Total: 5.38E-02 Stack 702 Bldg. 307 158.63 m 3/min 2.64 m 3/sec Pu-241 41,345,582 3.63E-16 8.72E-16 l.57E-15 l.SOE-08 l.46E-IO 4.53E-04 Tc-99 41,345,582 I.I 7E-14 2.82E-14 5.0SE-14 4.85E-07 2.87E-05 1.30E-05 U-234 41,345,582 2.35E-15 8.30E-15 l.88E-14 9.7IE-08 l.56E-05 4.70E-02 | |||
ECV: Effluent Concentration Value from 10-CFR-20, Appendix B. Fraction of ECV at the stack Is provided for reference only. Concentrations at off-site 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. | Note: A value of "O" was substituted for negative analytical results. | ||
Printed: 08/04/2021 | Printed: 08/04/2021 NFS-EDMS Page 2 of3 | ||
Page 8 of 13 21G-21-0103 GOV-01-55 ACF-21-0182 Radioactivity in Effluent Air January 1, 2021 to June 30, 2021 | |||
Total Activity Error Quantity Quantity Fraction Volume Coucentratiou Estimate LLD Released Released of Location (ml) (µCi/ml) (µCi/ml) (µCi/ml) (Ci) (g) ECV1 Stack 702 Bldg. 307 158.63 ml/min 2.64 m3tsec U-235 41,345,582 7.27E-l 7 2.57E-16 5.81E-!6 3.00E-09 l.39E-03 l.21E-03 | |||
Total: 4.87E-02 Stack 703 Exhaust Room Air 776.96 ml/min 12.95 m3tsec Pu-241 202,506,263 9.09E-15 2.57E-14 4.69E-14 l.84E-06 l.79E-08 l.14E-02 Th-228 202,506,263 l.76E-16 7.41E-16 1.72E-15 3.56E-08 4.35E-ll 8.S0E-03 Th-230 202,506,263 l.0!E-16 4.26E-16 9.SSE-16 2.05E-08 l.02E-06 5.06E-03 Th-232 202,506,263 1.44E-16 6.06E-16 1.40E-15 2.91E-08 2.67E-0l 3.60E-02 U-234 202,506,263 1.!0E-15 4.64E-15 1.07E-14 2.23E-07 3.58E-05 2.20E-02 U-235 202,506,263 l.14E-16 4.79E-!6 1.l lE-15 2.30E-08 l.07E-02 l.90E-03 U-238 202,506,263 l.39E-16 5.84E-16 l.35E-15 2.SIE-08 8.38E-02 2.3 !E-03 | |||
Total: 8.74E-02 Stack 773 Bldg. 440 166.92 ml/min 2.78 m3tsec Pu-241 43,576,819 2.!0E-14 3.53E-14 6. !SE-14 9. l 7E-07 8.90E-09 2.63E-02 Th-228 43,576,819 1.98E-16 1.31E-15 3.23E-15 8.61E-09 l.05E-ll 9.88E-03 Th-230 43,576,819 2.54E-!6 l.68E-!5 4.15E-15 1.llE-08 5.48E-07 l.27E-02 Th-232 43,576,819 1.69E-16 l.12E-15 2.76E-15 7.38E-09 6.77E-02 4.23E-02 U-234 43,576,819 5.22E-16 3.46E-15 8.52E-15 2.28E-08 3.65E-06 1.04E-02 U-235 43,576,819 9.18E-17 6.07E-!6 1.50E-15 4.00E-09 l.85E-03 l.53E-03 U-238 43,576,819 !.84E-16 l.21E-15 2.99E-15 8.00E-09 2.39E-02 3.06E-03 | |||
Total: l.06E-0l Stack 774 Bldg. 301 319.16 ml/min 5.32 m3tsec Th-228 83,185,658 5.43E-18 1.71E-!6 4.29E-16 4.52E-10 5.5!E-13 2.71E-04 Th-230 83,185,658 1.85E-l 7 5.SIE-16 1.46E-15 l.54E-09 7.62E-08 9.25E-04 Th-232 83,185,658 l.l0E-17 3.45E-16 8.67E-16 9.12E-10 8.37E-03 2.74E-03 U-234 83,185,658 4.94E-l 7 l.55E-15 3.91E-15 4. llE-09 6.59E-07 9.SSE-04 U-235 83,185,658 3.21E-18 1.0IE-16 2.54E-!6 2.67E-10 l.24E-04 5.35E-05 U-238 83,185,658 2.33E-l 7 7.31E-!6 1.84E-15 l.94E-09 5.78E-03 3.SSE-04 | |||
Total: 5.37E-03 Stack 796 Bldg. 100 19.37 ml/min 0.32 m3tsec Pu-241 5,048,265 8.86E-16 9.59E-!6 l.57E-15 4.47E-09 4.34E-11 l.l lE-03 Tc-99 5,048,265 2.87E-14 3.I0E-14 5.0SE-14 1.45E-07 8.56E-06 3.ISE-05 U-234 5,048,265 0.00E+00 7.14E-15 l.88E-14 0.00E+00 0.00E+00 0.00E+00 U-235 5,048,265 0.00E+00 2.21E-16 5.SIE-16 0.00E+00 0.00E+00 0.00E+00 | |||
Total: l.14E-03 | |||
ECV: Effluent concentration Value from 10-CFR-20, Appendix B. Fraction of ECV at the stack is provided for reference only. Concentrations at off-site locations are significantly less than those reported here (al 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. | Note: A value of "O" was substituted for negative analytical results. | ||
Printed: 08/04/2021 | Printed: 08/04/2021 NFS-EDMS Page 3 of3 | ||
Page 9 of 13 21G-21-0103 GOV-01-55 ACF-21-0182 | |||
Attachment 3 To Letter Dated August 16, 2021 | |||
Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed Off-Site Individual for the Release Period January to June 2021 | |||
(3 Pages to Follow) | |||
21G-21-0103 GOV-01-55 ACF-21-0182 | Page 10 of 13 21G-21-0103 GOV-01-55 ACF-21-0182 | ||
Report of Potential Gaseous Effluent Dose to the Maximally Exposed Offsite Individual and on the Maximum Radionuclide Concentrations for the Period: | |||
January to June 2021 | |||
Introduction During this biannual period, NRC License SNM-124, Section 9.1.1.3, required 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 sixteen (16) radiological stacks during the first half of 2021. 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 sixteen (16) radiological stacks during the first half of 2021. 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. | 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. | ||
21G-21-0103 GOV-01-55 ACF-21-0182 Table 1 summarizes the six-month dose to a hypothetical individual at the MEI location, which was determined to be approximately 550 meters North-Northeast from the center of the plant site. The TEDE to the MEI was estimated to be 3.2E-03 mrem for gaseous effluents released during the first half of 2021. The highest organ committed dose equivalent (COE) to the MEI was estimated to be 1.7E-02 mrem to the lungs. These MEI doses are well below the Environmental Radiological Monitoring Program action levels and applicable regulatory limits/ALARA constraints. | Page 11 of 13 21G-21-0103 GOV-01-55 ACF-21-0182 | ||
Table 1. Organ Doses and Total Effective Dose Equivalent at the MEI Location Organ | |||
Adrenals | Table 1 summarizes the six-month dose to a hypothetical individual at the MEI location, which was determined to be approximately 550 meters North-Northeast from the center of the plant site. The TEDE to the MEI was estimated to be 3.2E-03 mrem for gaseous effluents released during the first half of 2021. The highest organ committed dose equivalent (COE) to the MEI was estimated to be 1.7E-02 mrem to the lungs. These MEI doses are well below the Environmental Radiological Monitoring Program action levels and applicable regulatory limits/ALARA constraints. | ||
Table 1. Organ Doses and Total Effective Dose Equivalent at the MEI Location | |||
Organ Committed Dose Equivalent (mrem per first half of 2021) | |||
Adrenals 2.2E-04 Urinary Bladder Wall 2.6E-04 Bone Surface 9.2E-03 Brain 2.2E-04 Breasts 2.3E-04 Stomach Wall 3.7E-03 Small Intestine 2.5E-04 Upper Large Intestine Wall 1.1 E-03 Lower Large Intestine Wall 2.SE-03 Kidneys 2.SE-03 Liver 8.0E-04 Muscle 2.3E-04 Ovaries 2.4E-04 Pancreas 2.2E-04 Red Bone Marrow 1.2E-03 Skin 4.5E-04 Spleen 2.2E-04 Testes 2.5E-04 Thymus 2.2E-04 Thyroid 1.9E-03 Gall Bladder Wall 2.2E-04 Heart Wall 2.2E-04 Uterus 2.2E-04 Extra-thoracic 1.5E-02 Lungs 1.7E-02 | |||
Total Effective Dose Equivalent 3.2E-03 mrem Location of MEI: 550 meters North-Northeast | |||
Page 12 of 13 21G-21-0103 GOV-01-55 ACF-21-0182 | |||
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 5.SE-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 | Table 2. Maximum Predicted Airborne Concentrations at or Beyond the Site Boundary | ||
Maximum Predicted Airbome Concentrations at or Beyond the Site: Boundary l\1aximum | ~ | ||
Maximum Predicted Airbome Concentrations at | |||
(l,ICi/mL) | |||
'. or Beyond the Site: Boundary '. ' ' | |||
l\\1aximum Concenµ-~tion 10 CFR 20, App. B, Ratio of Maximum | |||
,* Nuclide Concentration Location Table 2, Col. 1 Value Concentration to. | |||
(l,ICi/mL) Sector Dist(m). (IJCi/mL) 10 CFR20 Value | |||
99Tc l.5E-17 NNE 450 9.E-10 l.6E-08 22sTh 5.5E-20 NNE 650 2.E-14 2.8E-06 230Th 8.lE-20 NNE 400 2.E-14 4.0E-06 -* | |||
232Th 9.3E-20 NNE 300 4.E-15 2.3E-05 234u 2.6E-17 NNE 550 5.E-14. 5.3E-04 23s 0 8.7E-19 NNE 550 6.E-14 l.5E-05 | |||
23su l.2E-19 NNE 650 6.E-14 2.0E-06 | |||
23sPu 9.0E-21 NNE 250 2.E-14 4.5E-07 239Pu 3.2E-20 NNE 250 2.E-14 l.6E-06 | |||
241Pu 2.5E-18 NNE 400 8.E-13 3.2E-06 241Am 7.4E-21 NNE 250 2.E-14 3.7E-07 | |||
Sum of Fractions: 5.8Fr04 | |||
Page 13 of 13}} |
Latest revision as of 23:38, 19 November 2024
ML21238A011 | |
Person / Time | |
---|---|
Site: | Erwin |
Issue date: | 08/16/2021 |
From: | Knowles T Nuclear Fuel Services |
To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
References | |
21G-21-0103, ACF-21-0182, GOV-01-55 | |
Download: ML21238A011 (13) | |
Text
Nuclear Fuel Services, Inc.
21G-21-0103 Certified Mail GOV-01-55 Return Receipt Requested ACF-21-0182 August 16, 2021 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 January to June 2021
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 January to June 2021. Attachment 2 reports the Radioactivity in Effluent Air for the period January to June 2021. 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 January to June 2021.
If you or your staff have any questions, require additional information, or wish to discuss this, please contact me or Mr. R. Jason Faddis, Environmental Safety Unit Manager, at (423) 735-5438. Please reference our unique document identification number (21G 0103) in any correspondence concerning this letter.
Sincerely,
NUCLEAR FUEL SERVICES, INC. IE4?
,:J~/~ !lflvj552D
Tim Knowles jl}Jv/55 Safety & Safeguards Director CJB/pj/smd Attachments
- 1) Report of Radioactivity in Effluent Liquid for the Period January to June 2021
- 2) Report of Radioactivity in Effluent Air for the Period January to June 2021
- 3) Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed Off-Site Individual for the Release Period January to June 2021
1205 Banner Hill Rd, Erwin, TN 37650 Page 1 of 13 People Strong
t: +1.423.743.9141 f: +1.423.743.0140 www.nuclearfuelservices.com INNOVATION DRIVEN >
21G-21-0103 GOV-01-55 ACF-21-0182
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 Fire Protection Engineer 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 13 21G-21-0103 GOV-01-55 ACF-21-0182
Attachment 1 To Letter Dated August 16, 2021
Report of Radioactivity in Effluent Liquid for the Period January to June 2021
(2 Pages to Follow)
Page 3 of 13 21 G-21-01 03 GOV-01-55 ACF-21-0182 Radioactivity in Effluent Liquid January 1, 2021 to June 30, 2021
Total Activity Error Quantity Quantity Fraction Volume Concentration Estimate LLD Released Released of Location (I) (µCi/ml) (µCi/ml) (µCi/ml) (Ci) (g) ECV1 Banner Spring Down Pu-238 472,037,000 0.00E+OO 8.57E-l l 2.28E-10 0.00E+OO O.OOE+OO O.OOE+OO Pu-239/240 472,037,000 O.OOE+OO 9.4JE-l l 2.40E-10 O.OOE+OO O.OOE+OO O.OOE+OO Tc-99 472,037,000 O.OOE+OO 3.44E-08 6.1 OE-08 0.00E+OO O.OOE+OO O.OOE+OO Th-228 472,037,000 1.08E-11 1.43E-IO 2.99E-10 5.IOE-06 6.22E-09 5.40E-05 Th-230 472,037,000 3.59E-l I l.81E-10 3.66E-10 l.70E-05 8.40E-04 3.59E-04 Th-232 472,037,000 O.OOE+OO l.OOE-10 2.67E-10 O.OOE+OO O.OOE+OO O.OOE+OO U-233/234 472,037,000 2.73E-10 2.SIE-10 3.43E-10 1.29E-04 2.07E-02 9.llE-04 U-235/236 472,037,000 1.90E-ll 1.42E-10 2.89E-10 8.96E-06 4.ISE+OO 6.33E-05 U-238 472,037,000 5.64E-l l l.58E-IO 2.82E-10 2.66E-05 7.95E+Ol 1.88E-04
Total: 1.58E-03 Sewer Pu-238 25,036,000 O.OOE+OO l.l lE-10 2.41E-10 O.OOE+OO O.OOE+OO O.OOE+OO Pu-239/240 25,036,000 O.OOE+OO 1.22E-10 2.92E-10 O.OOE+OO O.OOE+OO O.OOE+OO Tc-99 25,036,000 3.62E-09 3.74E-08 6.SSE-08 9.05E-05 5.36E-03 6.03E-06 Th-228 25,036,000 l.88E-l l 2.43E-IO 4.88E-10 4.71E-07 5.75E-10 9.41E-06 Th-230 25,036,000 l.58E-10 3.08E-IO 4.97E-10 3.97E-06 l.96E-04 l.58E-04 Th-232 2s,0J6,poo O.OOE+OO l.68E-IO 3.93E-10 O.OOE+OO O.OOE+OO O.OOE+OO U-232 25,036,000 3.03E-ll l.83E-IO 3.74E-10 7.59E-07 3.55E-08 5.0SE-05 U-233/234 25,036,000 l.8 !E-08 1.40E-09 2.9!E-10 4.54E-04 7.27E-02 6.04E-03 U-235/236 25,036,000 7.02E-10 3.03E-10 2.56E-10 l.76E-05 8.14E+OO 2.34E-04 U-238 25,036,000 2.57E-09 5.38E-IO 2.SSE-10 6.44E-05 l.92E+02 8.58E-04
Total: 7.36E-03 West Ditch Pu-238 169,304,000 O.OOE+OO l.12E-10 2.79E-10 O.OOE+OO O.OOE+OO O.OOE+OO Pu-239/240 169,304,000 O.OOE+OO l.22E-10 3.45E-10 O.OOE+OO O.OOE+OO O.OOE+OO Tc-99 169,304,000 5.83E-09 3.48E-08 6.06E-08 9.87E-04 5.84E-02 9.72E-05 Th-228 169,304,000 l.17E-ll l.76E-10 3.92E-10 l.98E-06 2.4!E-09 5.84E-05 Th-230 169,304,000 7.71E-ll 2.ISE-10 4.03E-10 l.30E-05 6.46E-04 7.71E-04 Th-232 169,304,000 O.OOE+OO 1.25E-IO 2.76E-10 O.OOE+OO 0.00E+OO O.OOE+OO U-233/234 169,304,000 l.SIE-08 l.40E-09 3.14E-10 2.56E-03 4.l lE-01 5.0SE-02 U-235/236 169,304,000 7.09E-10 3.SIE-10 2.SIE-10 l.20E-04 5.56E+O! 2.36E-03 U-238 169,304,000 l.53E-09 4.SIE-10 2.33E-10 2.59E-04 7.72E+02 5.09E-03
Total: 5.89E-02 WWTF Am-241 3,947,307 O.OOE+OO 9.48E-11 2.19E-10 O.OOE+OO O.OOE+OO O.OOE+OO Cs-137 3,947,307 O.OOE+OO l.24E-09 l.43E-09 O.OOE+OO O.OOE+OO O.OOE+OO Na-22 3,947,307 8.95E-11 8.13E-10 l.39E-09 3.53E-07 5.66E-11 l.49E-05 Np-237 3,947,307 2.61E-l l 2.74E-IO 5.62E-IO l.03E-07 1.46E-04 l.3 IE-03 Pb-212 3,947,307 1.20E-09 3.35E-09 3.02E-09 4.72E-06 3.41E-12 5.98E-04 Pu-238 3,947,307 l.33E-l l 5.35E-l l l.07E-10 5.27E-08 3.08E-09 6.67E-04
1 ECV: Effluent Concentration Value from 10-CFR-20, Appendix B.
Note: A value of "a~ was substituted for negative analytical results.
Printed: 08/04/2021 NFS-EDMS Page I of2
Page 4 of 13 21G-21-0103 GOV-01-55 ACF-21-0182 Radioactivity in Effluent Liquid January 1, 2021 to June 30, 2021
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 WWTF Pu-239/240 3,947,307 O.OOE+OO 6.32E-l 1 I.57E-IO O.OOE+OO O.OOE+OO O.OOE+OO Pu-241 3,947,307 4.56E-IO I.OIE-08 I. 74E-08 l.SOE-06 1.75E-08 4.56E-04 Ra-224 3,947,307 l.20E-08 6.69E-09 l.20E-08 4.73E-05 2.98E-IO 5.99E-02 Tc-99 3,947,307 4.75E-09 l.30E-07 2.24E-07 1.87E-05 I.I IE-03 7.91E-05 Th-228 3,947,307 O.OOE+OO I.SIE-10 3.74E-IO O.OOE+OO O.OOE+OO O.OOE+OO Th-230 3,947,307 l.16E-10 2.23E-IO 3.87E-10 4.60E-07 2.28E-05 l.16E-03 Th-231 3,947,307 O.OOE+OO 3.98E-08 3.89E-08 O.OOE+OO O.OOE+OO O.OOE+OO Th-232 3,947,307 3.63E-II l.33E-IO 2.37E-IO 1.43E-07 1.3 IE+OO l.21E-03 U-232 3,947,307 O.OOE+OO I.ISE-10 2.45E-IO O.OOE+OO O.OOE+OO O.OOE+OO U-233/234 3,947,307 l.34E-08 9.28E-IO 1.75E-IO 5.30E-05 8.50E-03 4.48E-02 U-235/236 3,947,307 5.96E-IO 2.06E-IO l.06E-IO 2.35E-06 l.09E+OO l.99E-03 U-238 3,947,307 9.75E-l l l.02E-10 l.34E-IO 3.85E-07 I.ISE+OO 3.25E-04
Total: 1.IJE-01
ECV: Effluent Concentration Value from 10-CFR-20, Appendix B.
Note: A value of "O" was substituted for negative analytical results.
Printed: 08/04/2021 NFS-EDMS Page 2 of2
Page 5 of 13 21G-21-0103 GOV-01-55 ACF-21-0182
Attachment 2 To Letter Dated August 16, 2021
Report of Radioactivity in Effluent Air for the Period January to June 2021
(3 Pages to Follow)
Page 6 of 13 21G-21-0103 GOV-01-55 ACF-21-0182 Radioactivity in Effluent Air January 1, 2021 to June 30, 2021
Total Activity Error Quantity Quantity Fraction Volume Concentration Estimate LLD Released Released of Location (mJ) (µCi/ml) (µCi/ml) (µCi/ml) (Ci) (g) ECV1 Main Stack 416 1070.66 m 3/min 17.84 m3tsec Th-228 282,139,411 6.58E-16 l.50E-16 8.16E-I 7 I.86E-07 2.27E-10 3.29£-02 Th-230 282,139,411 6.58E-16 l.50E-16 8. 16E-l 7 l.86E-07 9.19E-06 3.29E-02 Th-232 282,139,411 4.94E-16 1.13E-16 6.12E-17 l.39E-07 l.28E+00 l.23E-0l U-234 282,139,411 l.55E-13 3.54E-14 l.92E-l 4 4.38E-05 7.02E-03 3.I0E+00 U-235 282,139,411 5.92E-15 l.35E-15 7.35E-16 I.67E-06 7.74E-0l 9.87E-02 U-238 282,139,411 l.65E-15 3.76E-16 2.04E-16 4.64E-07 l.39E+00 2.74E-02
Total: 3.42E+00 Stack 185 Bldg. 131 112.74 m 3/min 1.88 m3tsec Pu-241 29,384,273 4.92E-16 9.20E-16 l.62E-15 l.45E-08 l.40E-10 6.!6E-04 Tc-99 29,384,273 l.59E-14 2.98E-14 5.23E-14 4.68E-07 2.77E-05 1.77£-05 U-234 29,384,273 2.42E-16 7.61E-15 l.93E-14 7.12E-09 l.14E-06 4.85E-03 U-235 29,384,273 7.50E-18 2.36E-16 5.98E-16 2.20E-I0 l.02E-04 l.25E-04
Total: 5.61E-03 Stack 234 Bldg. 234 328.49 m 3/min 5.47 m3tsec Am-241 85,678,107 5.83E-l 7 2.63E-17 4.34E-l 7 5.00E-09 I.46E-09 2.92E-03 Pu-238 85,678,107 7.13E-l 7 3.22E-l7 5.30E-17 6.I IE-09 3.57E-10 3.56E-03 Pu-239/240 85,678,107 2.53E-16 l.14E-16 l.88E-l6 2.16E-08 3.48E-07 l.26E-02 Pu-241 85,678,107 4.78E-15 4.34E-15 7.l3E-15 4.09E-07 3.98E-09 5.97E-03 Th-228 85,678,107 3.89E-l 7 l.75E-l 7 2.89E-17 3.33E-09 4.07E-12 l.94E-03 Th-230 85,678,107 4.86E-16 2.19E-16 3.62E-l6 4.16E-08 2.06E-06 2.43E-02 Th-232 85,678,107 6.15E-l6 2.78E-16 4.58E-16 5.27E-08 4.84E-0I 1.54E-0l U-234 85,678,107 l.33E-15 5.99E-l6 9.89E-l6 l.14E-07 1.82E-05 2.66E-02 U-238 85,678,107 3.89E-16 l.75E-16 2.89E-l6 3.33E-08 9.94E-02 6.48E-03
Total: 2.38E-0l Stack 327 Bldg. 330 1036.36 m 3/min 17.27 m3tsec Pu-241 270,157,102 2.50E-15 5.19E-l6 7.28E-16 6.75E-07 6.55E-09 3.12E-03 Tc-99 270,157,102 8.08E-14 l.68E-14 2.35E-l4 2.18E-05 l.29E-03 8.98E-05 U-234 270,157,102 1.40E-13 l.3 IE-14 8.78E-15 3.77£-05 6.05E-03 2.79E+00 U-235 270,157,102 4.32E-15 4.05E-16 2.71E-l6 l.l 7E-06 5.40E-01 7.20E-02
Total: 2.87E+00 Stack 421 Bldg. 100 32.96 m 3/min 0.55 m3tsec Pu-241 8,590,906 3.61E-l5 l.28E-15 l.95E-15 3. I0E-08 3.0IE-10 4.51E-03 Tc-99 8,590,906 1.17E-13 4.15E-14 6.30E-14 I.00E-06 5.93E-05 l.30E-04 U-234 8,590,906 1.26E-l4 1.29E-14 2.12E-14 1.08E-07 l.74E-05 2.52E-0l U-235 8,590,906 3.90E-16 3.98£-16 6.55E-16 3.35E-09 l.55E-03 6.50E-03
Total: 2.63E-0l Stack 424 Bldg. 100 32.62 m 3/min 0.54 m 3/sec Pu-241 8,502,340 1.29E-15 l.02E-15 1.57E-l 5 l.09E-08 l.06E-10 l.6 IE-03 Tc-99 8,502,340 4.16E-14 3.31E-14 5.0SE-14 3.54E-07 2.09E-05 4.62E-05
ECV: Effluent Concentralion Value from 10-CFR-20, Appendix B. Fraction o*f ECV at the stack is provided for rererence only. Concentrations at off-site significantly less than those reported here (at stack) due to the atmospheric dispersion that occurs before the effluent locations are exits the site.
Note: A value of "O~ was substituted for negative analytical results.
Printed: 08/04/2021 NFS-EDMS Page 1 of3
Page 7 of 13 21G-21-0103 GOV-01-55 ACF-21-0182 Radioactivity in Effluent Air January 1, 2021 to June 30, 2021
Total Activity Error Quantity Quantity Fraction Volume Concentration Estimate LLD Released Released of Location (m3) (µCi/ml) (µCi/ml) (µCi/ml) (Ci) (g) ECV1 Stack 424 Bldg. 100 32.62 m 3/min 0.54 m3/sec U-234 8,502,340 8.14E-15 l.09E-14 1.88E-14 6.92E-08 l.llE-05 l.63E-01 U-235 8,502,340 2.52E-16 3.38E-16 5.SIE-16 2.14E-09 9.91E-04 4.20E-03
Total: l.69E-0l Stack 573 Bldg 306-W 120.88 m 3/min 2.01 m3/sec Pu-241 31,507,371 3.97E-16 8.ISE-16 l.49E-15 l.25E-08 l.21E-10 4.96E-04 Tc-99 31,507,371 1.28E-14 2.64E-14 4.SIE-14 4.04E-07 2.39E-05 l.43E-05 U-234 31,507,371 1.78E-16 6.65E-15 1.SOE-14 5.60E-09 8.98E-07 3.56E-03 U-235 31,507,371 5.SOE-18 2.06E-16 5.57E-16 l.73E-10 8.02E-05 9.16E-05
Total: 4.16E-03 Stack 600 Bldg. 110 319.61 m 3/min 5.33 m 3/sec Pu-241 83,303,746 1.23E-15 5.93E-16 9.73E-16 l.03E-07 9.99E-IO 1.54E-03 Tc-99 83,303,746 3.99E-14 l.92E-14 3.ISE-14 3.33E-06 l.97E-04 4.44E-05 U-234 83,303,746 2.46E-14 8.07E-15 1.22E-14 2.0SE-06 3.29E-04 4.92E-01 U-235 83,303,746 7.61E-16 2.SOE-16 3.78E-16 6.34E-08 2.94E-02 l.27E-02
Total: 5.06E-01 Stack 615 Bldg. 306-W 48.41 m 3/min 0.81 m 3/sec Pu-241 12,618,460 3.07E-16 8.62E-16 l.57E-15 3.88E-09 3.77E-ll 3.84E-04 Tc-99 12,618,460 9.94E-15 2.79E-14 5.0SE-14 1.25E-07 7.42E-06 l.lOE-05 U-234 12,618,460 3.02E-16 7.32E-15 1.88E-14 3.SIE-09 6.IOE-07 6.03E-03 U-235 12,618,460 9.33E-18 2.26E-16 5.SIE-16 l.lSE-10 5.45E-05 l.55E-04
Total: 6.58E-03 Stack 646 Bldg. 110 37.49 m 3/min 0.62 m 3/sec Pu-241 9,771,787 5.32E-16 9.0IE-16 l.57E-15 5.20E-09 5.0SE-ll 6.65E-04 Tc-99 9,771,787 l.72E-14 2.91E-14 5.07E-14 l.68E-07 9.94E-06 l.91E-05 U-234 9,771,787 9.59E-16 7.68E-15 l.88E-14 9.38E-09 l.SOE-06 l.92E-02 U-235 9,771,787 2.97E-17 2.38E-16 5.SOE-16 2.90E-10 l.34E-04 4.95E-04
Total: 2.04E-02 Stack 701 Bldg. 307 119.13 m 3/min 1.99 m 3/sec Pu-241 31,049,779 3.58E-!6 9.91E-16 I.SOE-IS l.llE-08 I.OSE-10 4.47E-04 Tc-99 31,049,779 l.16E-14 3.20E-14 5.84E-14 3.59E-07 2.13E-05 l.29E-05 U-234 31,049,779 2.60E-15 9.65E-15 2.16E-14 8.07E-08 l.29E-05 5.20E-02 U-235 31,049,779 8.04E-17 2.99E-16 6.67E-16 2.SOE-09 l.16E-03 l.34E-03
Total: 5.38E-02 Stack 702 Bldg. 307 158.63 m 3/min 2.64 m 3/sec Pu-241 41,345,582 3.63E-16 8.72E-16 l.57E-15 l.SOE-08 l.46E-IO 4.53E-04 Tc-99 41,345,582 I.I 7E-14 2.82E-14 5.0SE-14 4.85E-07 2.87E-05 1.30E-05 U-234 41,345,582 2.35E-15 8.30E-15 l.88E-14 9.7IE-08 l.56E-05 4.70E-02
ECV: Effluent Concentration Value from 10-CFR-20, Appendix B. Fraction of ECV at the stack Is provided for reference only. Concentrations at off-site 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: 08/04/2021 NFS-EDMS Page 2 of3
Page 8 of 13 21G-21-0103 GOV-01-55 ACF-21-0182 Radioactivity in Effluent Air January 1, 2021 to June 30, 2021
Total Activity Error Quantity Quantity Fraction Volume Coucentratiou Estimate LLD Released Released of Location (ml) (µCi/ml) (µCi/ml) (µCi/ml) (Ci) (g) ECV1 Stack 702 Bldg. 307 158.63 ml/min 2.64 m3tsec U-235 41,345,582 7.27E-l 7 2.57E-16 5.81E-!6 3.00E-09 l.39E-03 l.21E-03
Total: 4.87E-02 Stack 703 Exhaust Room Air 776.96 ml/min 12.95 m3tsec Pu-241 202,506,263 9.09E-15 2.57E-14 4.69E-14 l.84E-06 l.79E-08 l.14E-02 Th-228 202,506,263 l.76E-16 7.41E-16 1.72E-15 3.56E-08 4.35E-ll 8.S0E-03 Th-230 202,506,263 l.0!E-16 4.26E-16 9.SSE-16 2.05E-08 l.02E-06 5.06E-03 Th-232 202,506,263 1.44E-16 6.06E-16 1.40E-15 2.91E-08 2.67E-0l 3.60E-02 U-234 202,506,263 1.!0E-15 4.64E-15 1.07E-14 2.23E-07 3.58E-05 2.20E-02 U-235 202,506,263 l.14E-16 4.79E-!6 1.l lE-15 2.30E-08 l.07E-02 l.90E-03 U-238 202,506,263 l.39E-16 5.84E-16 l.35E-15 2.SIE-08 8.38E-02 2.3 !E-03
Total: 8.74E-02 Stack 773 Bldg. 440 166.92 ml/min 2.78 m3tsec Pu-241 43,576,819 2.!0E-14 3.53E-14 6. !SE-14 9. l 7E-07 8.90E-09 2.63E-02 Th-228 43,576,819 1.98E-16 1.31E-15 3.23E-15 8.61E-09 l.05E-ll 9.88E-03 Th-230 43,576,819 2.54E-!6 l.68E-!5 4.15E-15 1.llE-08 5.48E-07 l.27E-02 Th-232 43,576,819 1.69E-16 l.12E-15 2.76E-15 7.38E-09 6.77E-02 4.23E-02 U-234 43,576,819 5.22E-16 3.46E-15 8.52E-15 2.28E-08 3.65E-06 1.04E-02 U-235 43,576,819 9.18E-17 6.07E-!6 1.50E-15 4.00E-09 l.85E-03 l.53E-03 U-238 43,576,819 !.84E-16 l.21E-15 2.99E-15 8.00E-09 2.39E-02 3.06E-03
Total: l.06E-0l Stack 774 Bldg. 301 319.16 ml/min 5.32 m3tsec Th-228 83,185,658 5.43E-18 1.71E-!6 4.29E-16 4.52E-10 5.5!E-13 2.71E-04 Th-230 83,185,658 1.85E-l 7 5.SIE-16 1.46E-15 l.54E-09 7.62E-08 9.25E-04 Th-232 83,185,658 l.l0E-17 3.45E-16 8.67E-16 9.12E-10 8.37E-03 2.74E-03 U-234 83,185,658 4.94E-l 7 l.55E-15 3.91E-15 4. llE-09 6.59E-07 9.SSE-04 U-235 83,185,658 3.21E-18 1.0IE-16 2.54E-!6 2.67E-10 l.24E-04 5.35E-05 U-238 83,185,658 2.33E-l 7 7.31E-!6 1.84E-15 l.94E-09 5.78E-03 3.SSE-04
Total: 5.37E-03 Stack 796 Bldg. 100 19.37 ml/min 0.32 m3tsec Pu-241 5,048,265 8.86E-16 9.59E-!6 l.57E-15 4.47E-09 4.34E-11 l.l lE-03 Tc-99 5,048,265 2.87E-14 3.I0E-14 5.0SE-14 1.45E-07 8.56E-06 3.ISE-05 U-234 5,048,265 0.00E+00 7.14E-15 l.88E-14 0.00E+00 0.00E+00 0.00E+00 U-235 5,048,265 0.00E+00 2.21E-16 5.SIE-16 0.00E+00 0.00E+00 0.00E+00
Total: l.14E-03
ECV: Effluent concentration Value from 10-CFR-20, Appendix B. Fraction of ECV at the stack is provided for reference only. Concentrations at off-site locations are significantly less than those reported here (al 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: 08/04/2021 NFS-EDMS Page 3 of3
Page 9 of 13 21G-21-0103 GOV-01-55 ACF-21-0182
Attachment 3 To Letter Dated August 16, 2021
Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed Off-Site Individual for the Release Period January to June 2021
(3 Pages to Follow)
Page 10 of 13 21G-21-0103 GOV-01-55 ACF-21-0182
Report of Potential Gaseous Effluent Dose to the Maximally Exposed Offsite Individual and on the Maximum Radionuclide Concentrations for the Period:
January to June 2021
Introduction During this biannual period, NRC License SNM-124, Section 9.1.1.3, required 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 sixteen (16) radiological stacks during the first half of 2021. 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 13 21G-21-0103 GOV-01-55 ACF-21-0182
Table 1 summarizes the six-month dose to a hypothetical individual at the MEI location, which was determined to be approximately 550 meters North-Northeast from the center of the plant site. The TEDE to the MEI was estimated to be 3.2E-03 mrem for gaseous effluents released during the first half of 2021. The highest organ committed dose equivalent (COE) to the MEI was estimated to be 1.7E-02 mrem to the lungs. These MEI doses are well below the Environmental Radiological Monitoring Program action levels and applicable regulatory limits/ALARA constraints.
Table 1. Organ Doses and Total Effective Dose Equivalent at the MEI Location
Organ Committed Dose Equivalent (mrem per first half of 2021)
Adrenals 2.2E-04 Urinary Bladder Wall 2.6E-04 Bone Surface 9.2E-03 Brain 2.2E-04 Breasts 2.3E-04 Stomach Wall 3.7E-03 Small Intestine 2.5E-04 Upper Large Intestine Wall 1.1 E-03 Lower Large Intestine Wall 2.SE-03 Kidneys 2.SE-03 Liver 8.0E-04 Muscle 2.3E-04 Ovaries 2.4E-04 Pancreas 2.2E-04 Red Bone Marrow 1.2E-03 Skin 4.5E-04 Spleen 2.2E-04 Testes 2.5E-04 Thymus 2.2E-04 Thyroid 1.9E-03 Gall Bladder Wall 2.2E-04 Heart Wall 2.2E-04 Uterus 2.2E-04 Extra-thoracic 1.5E-02 Lungs 1.7E-02
Total Effective Dose Equivalent 3.2E-03 mrem Location of MEI: 550 meters North-Northeast
Page 12 of 13 21G-21-0103 GOV-01-55 ACF-21-0182
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 5.SE-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 Airbome Concentrations at
'. or Beyond the Site: Boundary '. ' '
l\\1aximum Concenµ-~tion 10 CFR 20, App. B, Ratio of Maximum
,* Nuclide Concentration Location Table 2, Col. 1 Value Concentration to.
(l,ICi/mL) Sector Dist(m). (IJCi/mL) 10 CFR20 Value
99Tc l.5E-17 NNE 450 9.E-10 l.6E-08 22sTh 5.5E-20 NNE 650 2.E-14 2.8E-06 230Th 8.lE-20 NNE 400 2.E-14 4.0E-06 -*
232Th 9.3E-20 NNE 300 4.E-15 2.3E-05 234u 2.6E-17 NNE 550 5.E-14. 5.3E-04 23s 0 8.7E-19 NNE 550 6.E-14 l.5E-05
23su l.2E-19 NNE 650 6.E-14 2.0E-06
23sPu 9.0E-21 NNE 250 2.E-14 4.5E-07 239Pu 3.2E-20 NNE 250 2.E-14 l.6E-06
241Pu 2.5E-18 NNE 400 8.E-13 3.2E-06 241Am 7.4E-21 NNE 250 2.E-14 3.7E-07
Sum of Fractions: 5.8Fr04
Page 13 of 13