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{{#Wiki_filter:Nuclear Fuel Servi.ces, 1nc. | {{#Wiki_filter:Nuclear Fuel Servi.ces, 1nc. | ||
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 21 G-21-0029 GOV-01-55 ACF-21-0042 February 12, 2021 | ||
==Subject:== | ==Subject:== | ||
Biannual Effluent Monitoring Report July to December 2020 | Biannual Effluent Monitoring Report July to December 2020 | ||
==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 2020. Attachment 2 reports the Radioactivity in Effluent Air for the period July to December 2020. Attachment 3 summarizes an evaluation of the dose and air activity concentrations for the maximally exposed offsite indMdual due to gaseous effluents during the period July to December 2020. | 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 2020. Attachment 2 reports the Radioactivity in Effluent Air for the period July to December 2020. Attachment 3 summarizes an evaluation of the dose and air activity concentrations for the maximally exposed offsite indMdual due to gaseous effluents during the period July to December 2020. | ||
If you or your staff have any questions, require additional infom,ation, 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 (21 G | If you or your staff have any questions, require additional infom,ation, 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 (21 G 0029) in any correspondence concerning this 1etter. | ||
Sincerely, NUCLEAR FUEL SERVICES, INC. | CJB/pj | ||
.Attachments Sincerely, NUCLEAR FUEL SERVICES, INC. | |||
j~~~ | |||
Tim Knowles Safety &- Safeguards Director | |||
)ZEf?'J Nf/55ZD fi)f1_SS | |||
: 1) Report *of Radioactivity in Effluent Liquid for the Period July to December 2020 | : 1) Report *of Radioactivity in Effluent Liquid for the Period July to December 2020 | ||
: 2) Report of Radioactivity in Effluent Air for the Period July to December 2020 | : 2) Report of Radioactivity in Effluent Air for the Period July to December 2020 | ||
: 3) Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed* Off-Site Individual for the Release Period July to December 2020 | : 3) Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed* Off-Site Individual for the Release Period July to December 2020 1206 Banner Hdl Rd, Erwin, TN 37650 Page 1 of 14 t +1.423 743 9141 I +1423743 0140 wwwnuclerui1Jelservices com People Strong INNDVATIDN DRIVEN > | ||
21 G-21-0029 GOV-01-55 ACF-21-0042 | Copy: | ||
Page 3 of 14 | 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 Br:anch 1 U. S. Nuclear Regulatory Commission Region II 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Mr. Larry Hanis Senior Resident :Inspector U.S. Nuclear Regulatory Commission Page 2 of14 21 G-21-0029 GOV-01-55 ACF-21-0042 To Letter Dated February 12, 2021 Report of Radioactivity in Effluent Liquid for the Period July to December 2020 (2 Pages to Follow) | ||
Page 3 of 14 21 G-21-0029 GOV-01-55 ACF-21-0042 | |||
Radioactivity in Effluent Liquid July 1, 2020 to December 31, 2020 Total | Radioactivity in Effluent Liquid July 1, 2020 to December 31, 2020 Total Activity Error Quantity Volume Concentration Estimate LLD Released Location (I) | ||
Location | (µCi/ml) | ||
(µCi/ml) | |||
(µCi/ml) | |||
(Ci) | |||
Banner Spring Down Pu-238 444,874,000 O.OOE+OO l.22E-10 2.79E-10 O.OOE+OO Pu-239/240 444,874,000 J.32E-l l I.SIE-1 0 3.07E-1 0 S.89E-06 Tc-99 444,874,000 O.OOE+OO 3.83E-08 6.78E-08 O.OOE+OO Th-228 444,874,000 S.14E-12 1.S2E-I 0 3.33E-l 0 2.28E-06 Th-230 444,874,000 | |||
: 3. 17E-12 l.62E-10 3.52E-10 1.41 E-06 Th-232 444,874,000 O.OOE+OO l.02E-l 0 | |||
: 2. 14E-l 0 O.OOE+OO U-233/234 444,874,000 2.34E-l 0 2.35E-IO 3.26E-IO l.04E-04 U-235/236 444,874,000 2.06E-l l l.39E-10 2.82E-1 0 9.14E-06 U-238 444,874,000 O.OOE+OO I.ISE-1 0 2.66E-IO O.OOE+OO Sewer Pu-238 33,721,400 O.OOE+OO l.29E-IO 3.27E-l 0 O.OOE+OO Pu-239/240 33,721,400 O.OOE+OO 1.26E-l 0 3.S6E-I O O.OOE+OO Tc-99 33,721,400 O.OOE+OO | |||
: 4. I 7E-08 7.46E-08 O.OOE+OO Th-228 33,721,400 O.OOE+OO 1.91E-10 4.37E-l 0 O.OOE+OO Th-230 33,72 1,400 7.28E-11 2.2 1E-10 4.29E-10 2.4SE-06 Th-232 33,721,400 O.OOE+OO l.17E-I O 2.66E-l 0 O.OOE+OO U-232 33,721,400 4.07E-l l l.13E-J O 2.09E-l 0 l.37E-06 U-233/234 33,721,400 | |||
: 1. l 7E-08 1.0 I E-09 I.84E-l 0 3.94E-04 U-23S/236 33,72 1,400 4.S9E-I 0 2.04E-I O 1.06E-IO I.SSE-OS U-238 33,72 1,400 I.S3E-09 3.66E-IO l.3SE-10 S. l 6E-OS West Ditch Pu-238 143, 7S3,000 O.OOE+OO l.29E-I O 3.35E-JO O.OOE+OO Pu-239/240 143,7S3,000 O.OOE+OO 1.41 E-10 3.65E-IO O.OOE+OO Tc-99 143,7S3,000 O.OOE+OO 3.93E-08 6.95E-08 O.OOE+OO Th-228 143,7S3,000 O.OOE+OO l.76E-l 0 3.87E-l 0 O.OOE+OO Th-230 143,753,000 7.68E-l l l.94E-10 3.49E-IO 1.1 OE-OS Th-232 143,7S3,000 2.79E-ll 1.3 I E-10 2.38E-10 4.0IE-06 U-233/234 143,753,000 I.52E-08 l.44E-09 2.86E-1 0 | |||
: 2. l 8E-03 U-23S/236 143,7S3,000 6.07E-10 3.3SE-10 2.16E-IO 8.72E-OS U-238 143,753,000 I.24E-09 4.20E-IO 2.14E-10 1.78E-04 WWTF Am-24 1 3,6 I S,678 3.20E-l l I.06E-l 0 I.91E-JO 1.1 6E-07 Cs-137 3,6 l S,678 O.OOE+OO l.OSE-09 l.S4E-09 O.OOE+OO Na-22 3,61S,678 2.58E-10 8.13E-IO l.52E-09 9.32E-07 Np-237 3,61 S,678 O.OOE+OO 1.70E-10 4.61E-10 O.OOE+OO Pb-212 3,615,678 9.SOE-10 | |||
: 3. l lE-09 2.93E-09 3.43E-06 Pu-238 3,615,678 O.OOE+OO 7.78E-l l | |||
: 2. 13E-1 0 O.OOE+OO ECV: Effluent Concentrallon Value rrom 10-CFR-20, Appendix 8. | |||
Note: A value of *o* was substituted for negative analytical results. | Note: A value of *o* was substituted for negative analytical results. | ||
Printed: 02/09/202 1 | Printed: 02/09/202 1 NFS - EDMS Page 4 of 14 Quantity Fraction Released of 1 | ||
(g) | |||
ECV O.OOE+OO O.OOE+OO 9.47E-OS 6.62E-04 O.OOE+OO O.OOE+OO 2.79E-09 2.57E-05 6.97E-05 | |||
: 3. I 7E-05 O.OOE+OO O.OOE+OO l.67E-02 7.81E-04 4.23E+OO 6.85E-05 O.OOE+OO O.OOE+OO Total: | |||
l.57E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.21E-04 7.28E-OS O.OOE+OO O.OOE+OO 6.42E-08 6.79E-OS 6.3 IE-02 3.89E-03 | |||
: 7. 17E+OO l.53E-04 I.S4E+02 S.IOE-04 Total: | |||
4.70E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO S.46E-04 7.68E-04 3.68E+Ol 9.31E-04 3.SOE-01 S.06E-02 4.04E+Ol 2.02E-03 5.3 IE+02 4.13E-03 Total: | |||
S.84E-02 3.38E-08 l.60E-03 O.OOE+OO O.OOE+OO l.49E-l 0 4.29E-OS O.OOE+OO O.OOE+OO 2.48E-1 2 4.75E-04 O.OOE+OO O.OOE+OO Page I of2 | |||
Radioactivity in Effluent Liquid July 1, 2020 to December 31, 2020 Total Activity Volume Concentration Location (I) | |||
Page 6 of 14 | (µCi/ml) | ||
WWTF Pu-239/240 3,615,678 0.00E+00 Pu-241 3,615,678 0.00E+00 Ra-224 3,615,678 9.46E-09 Tc-99 3,615,678 0.00E+00 Th-228 3,615,678 0.00E+00 Th-230 3,615,678 4.38E-l l Th-23 1 3,615,678 l.06E-08 Th-232 3,615,678 0.00E+00 U-232 3,615,678 0.00E+00 U-233/234 3,615,678 9.72E-09 U-235/236 3,615,678 3.68E-10 U-238 3,615,678 9.23E-l 1 ECV: Effluent Concentration Value from 10*CFR*20, Appendix 8. | |||
Note: A value of "O" was substituted for negative analytical results. | |||
Printed: 02/09/2021 Error Quantity Estimate LLD Released | |||
(µCi/ml) | |||
(µCi/ml) | |||
(Ci) 7.25E-ll 2.00E-10 0.00E+00 l.20E-08 2.0SE-08 0.00E+00 4.80E-09 8.67E-09 3.42E-05 l.53E-07 2.64E-07 0.00E+00 l.42E-I0 3.20E-10 0.00E+00 I. 70E-l 0 3.31E-10 l.59E-07 | |||
: 4. l lE-08 3.82E-08 3.82E-05 l.08E-10 2.47E-I0 0.00E+00 9.78E-l l 2.I0E-10 0.00E+00 8.77E-I0 l.SI E-10 3.51 E-05 l.80E-10 l.14E-10 1.33E-06 l.06E-10 l.31E-10 3.34E-07 NFS-EDMS Page 5 of 14 Quantity Fraction Released of (g) | |||
ECV 1 | |||
0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.ISE-10 4.73E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.85E-06 4.38E-04 | |||
: 7. l 7E-l l 2.l lE-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.63E-03 3.24E-02 6.16E-01 1.23E-03 9.96E-0I 3.08E-04 Total: | |||
8.40E-02 Page 2 of2 To Letter Dated February 12, 2021 Report of Radioactivity in Effluent Air for the Period July to December 2020 (3 Pages to Follow) | |||
Page 6 of 14 21G-21-0029 GOV-01-55 ACF-21-0042 | |||
Radioactivity in Effluent Air July 1, 2020 to December 31, 2020 | Total Volume Location (ml ) | ||
Ma in Stack 416 Th-228 274,100,738 Th-230 274, I 00,738 U-234 274,100,738 U-235 274, I 00,738 U-238 274,100,738 Stack 185 Bldg. 131 Pu-24 1 29,936,302 Tc-99 29,936,302 U-234 29,936,302 U-235 29,936,302 Stack 234 Bldg. 234 Am-241 80,728,684 Pu-238 80,728,684 Pu-239/240 80,728,684 Pu-241 80,728,684 Th-228 80,728,684 Th-230 80,728,684 Th-232 80,728,684 U-234 80,728,684 U-238 80,728,684 Stack 327 Bldg. 330 Pu-241 274,993,820 Tc-99 274,993,820 U-234 274,993,820 U-235 274,993,820 Stack 421 Bldg. 100 Pu-24 1 8,861,131 Tc-99 8,861,131 U-234 8,861,131 U-235 8,861,131 Stack 424 Bldg. 100 Pu-24 1 8,692,072 Tc-99 8,692,072 U-234 8,692,072 Radioactivity in Effluent Air July 1, 2020 to December 31, 2020 Activity Error Quantity Concentration Estimate LLD Released | |||
(µCi/ml) | |||
(µCi/ml) | |||
(µCi/ml) | |||
(Ci) 1033.76 ml/min 17.23 ml/sec 5.04E-1 6 l.04E-l 6 5.74E-17 l.38E-07 6.72E-16 l.38E-16 7.65E-17 I.84E-07 l.58E-1 3 3.26E-14 1.81E-14 4.34E-05 6.38E-15 l.31E-15 7.27E-16 l.75E-06 l.85E-1 5 3.80E-16 | |||
: 2. I0E-1 6 5.06E-07 112.98 ml/min 1.88 m3/sec 6.67E-16 9.00E-16 l.5SE-1 5 2.00E-08 2.16E-14 2.91E-14 5.00E-14 6.45E-07 3.63E-15 8.82E-l 5 l.85E-14 l.09E-07 1.12E-1 6 2.73E-16 5.72E-16 3.36E-09 308.03 ml/min 5.13 ml/sec 0.00E+00 2.07E-17 4.49E-17 0.00E+00 0.00E+00 2.53E-17 5.49E-17 0.00E+00 0.00E+00 8.96E-17 l.95E-16 0.00E+00 l.35E-l 5 4.24E-I S 7.48E-1 5 l.09E-07 0.00E+00 l.38E-l 7 3.00E-1 7 0.00E+00 0.00E+00 1.72E-16 3.74E-16 0.00E+00 0.00E+00 2.18E-16 4.74E-16 0.00E+00 0.00E+00 4.7 1E-16 1.02E-15 0.00E+00 0.00E+00 l.38E-l 6 3.00E-16 0.00E+00 1037.87 ml/min 17.30 ml/sec 2.0SE-1 5 4.77E-1 6 7.02E-16 S.63E-07 6.63E-14 l.54E-14 2.27E-14 l.82E-05 8.90E-14 I.0SE-14 8.58E-15 2.45E-05 2.75E-15 3.26E-16 2.65E-l 6 7.57E-07 33.41 ml/min 0.56 ml/sec 5.48E-l 5 l.38E-l S 1.92E-l S 4.8SE-08 I. 77E-l 3 4.46E-14 6.22E-14 l.57E-06 S.16E-14 l.76E-1 4 | |||
: 2. 14E-14 4.58E-07 l.60E-15 S.45E-16 6.62E-16 I.42E-08 32.79 ml/min 0.55 ml/sec l.2SE-15 9.85E-1 6 1.55E-15 l.09E-08 4.0SE-14 3.19E-1 4 5.00E-14 3.52E-07 2.0SE-1 4 l.24E-14 l.86E-l 4 I. 78E-07 Quantity Released (g) l.69E-1 0 9.11 E-06 6.96E-03 | |||
: 8. I0E-0 1 1.51 E+00 Total: | |||
l.94E-10 3.82E-05 I.74E-05 I.56E-03 Total: | |||
0.00E+00 0.00E+00 0.00E+00 l.06E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total: | |||
5.47E-09 l.08E-03 3.92E-03 3.S0E-01 Total: | |||
4.7 1E-10 9.29E-05 7J3E-0S 6.55E-03 Total: | |||
l.06E-I 0 2.09E-0S 2.85E-05 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 exi1s the site. | |||
Note: A value of ~ a~ was substituted for negative analytical results. | Note: A value of ~ a~ was substituted for negative analytical results. | ||
Printed: 02/09/202 1 | Printed: 02/09/202 1 NFS-EDMS Page 7 of 14 Fraction of ECV 1 | ||
2.52E-02 3J6E-02 | |||
: 3. I 7E+00 l.06E-0I 3.08E-02 3.37E+00 8.33E-04 2.40E-05 7.27E-02 l.87E-03 7.54E-02 0.00E+00 0.00E+00 0.00E+00 l.69E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l.69E-03 2.56E-03 7.36E-0S l.78E+00 4.59E-02 1.83E+00 6.8SE-03 l.97E-04 l.03E+00 2.66E-02 1.07E+00 I.57E-03 4.S0E-05 4.I0E-01 Page I of3 | |||
Radioactivity in Effluent Air July 1, 2020 to December 31, 2020 | Total Volume Location (m3) | ||
Stack 424 Bldg. 100 U-235 8,692,072 Stack 573 Bldg 306-W Pu-241 19,390,581 Tc-99 19,390,581 U-234 19,390,581 U-235 19,390,581 Stack 600 Bldg. 110 Pu-241 83,150,468 Tc-99 83,150,468 U-234 83,150,468 U-235 83,150,468 Stack 615 Bldg. 306-W Pu-241 12,814,838 Tc-99 12,814,838 U-234 12,814,838 U-235 12,814,838 Stack 646 Bldg. ll0 Pu-241 10,28 1,735 Tc-99 10,28 1,735 U-234 10,281,735 U-235 10,281,735 Stack 701 Bldg. 307 Pu-241 3 1,183,240 Tc-99 31, I 83,240 U-234 31,183,240 U-235 31,183,240 Stack 702 Bldg. 307 Pu-241 42,358,587 Tc-99 42,358,587 U-234 42,358,587 U-235 42,358,587 Radioactivity in Effluent Air July 1, 2020 to December 31, 2020 Activity Error Quantity Concentration Estimate LLD Released | |||
(µCi/ml) | |||
(µCi/ml) | |||
(µCi/ml) | |||
(Ci) 32.79 m3/min 0.55 m3/sec 6.33E-l 6 3.84E-16 5.75E-16 5.51 E-09 72.10 m3/min 1.20 m3/sec 3.60E-16 7.97E-16 l.48E-l 5 6.97E-09 l.l6E-14 2.58E-14 4.79E-14 2.25E-07 l.29E-14 8.89E-l 5 1.79E-14 2.51 E-07 4.00E-16 2.75E-16 5.SSE-16 7.76E-09 313.96 m3/min 5.23 m3/sec l.5SE-15 5.96E-16 9.SlE-16 l.29E-07 5.0lE-14 l.93E-14 3.07E-14 4.16E-06 4.69E-14 8.82E-15 l.21 E-14 3.90E-06 l.45E-l 5 2.73E-16 3.76E-16 l.21E-07 48.37 m3/min 0.81 m3Jsec 1.88E-l 6 8.lSE-16 1.53E-15 2.4 1 E-09 6.08E-15 2.64E-14 4.95E-14 7.79E-08 2.25E-16 7.23E-15 1.83E-14 2.88E-09 6.96E-18 2.24E-16 5.67E-16 8.91E-l l 38.71 m3/min 0.65 m3/sec 4.1 2E-16 8.65E-16 ISSE-15 4.24E-09 l.33E-14 2.80E-14 5.02E-14 l.37E-07 4.l8E-16 7.31E-15 1.85E-14 4.30E-09 l.29E-17 2.26E-16 5.72E-16 l.33E-IO 117.79 m3/min l.96 m3/sec 3.39E-16 9.58E-l 6 l.76E-15 l.06E-08 I.IOE-14 3.IOE-14 5.70E-14 3.42E-07 9.81E-15 l.03E-14 2.l lE-14 3.06E-07 3.03E-16 3.19E-16 6.53E-16 9.46E-09 159.78 m3/min 2.66 m3/sec 3.03E-16 8.SlE-16 1.56E-15 I.28E-08 9.78E-l5 2.75E-14 5.06E-14 4.l4E-07 3.95E-15 8.77E-l5 l.87E-14 l.67E-07 l.22E-16 2.71E-16 5.80E-16 | |||
: 5. l 8E-09 Quantity Released (g) 2.SSE-03 Total: | |||
6.77E-l l l.33E-05 4.02E-05 3.59E-03 Total: | |||
l.25E-09 2.46E-04 6.25E-04 5.58E-02 Total: | |||
2.34E-l l 4.61 E-06 4.62E-07 4.13E-05 Total: | |||
4.12E-ll 8.l lE-06 6.89E-07 6.16E-05 Total: | |||
l.03E-10 2.02E-05 4.90E-05 4.38E-03 Total: | |||
1.24E-l 0 2.45E-05 2.68E-05 2.40E-03 Total: | |||
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 resuNs. | Note: A value of *o* was substituted for negative analytical resuNs. | ||
Printed: 02/09/2021 | Printed: 02/09/2021 NFS - EDMS Page 8 of 14 Fraction of ECV 1 | ||
l.06E-02 4.22E-0l 4.SOE-04 l.29E-05 2.59E-01 6.67E-03 2.66E-0l l.94E-03 5.56E-05 9.37E-Ol 2.42E-02 9.64E-0l 2.35E-04 6.75E-06 4.SOE-03 l.16E-04 4.86E-03 | |||
: 5. l SE-04 1.48E-05 8.37E-03 2.16E-04 9.llE-03 4.23E-04 l.22E-05 l.96E-Ol 5.06E-03 2.02E-0l 3.78E-04 l.09E-05 7.90E-02 2.04E-03 8.15E-02 Page 2 of3 | |||
Radioactivity in Effluent Air July 1, 2020 to December 31, 2020 | Total Volume Location (ml) | ||
Stack 703 Exhaust Room Air Pu-241 205,862,720 Th-228 205,862,720 Th-230 205,862,720 Th-232 205,862,720 U-234 205,862,720 U-235 205,862,720 U-238 205,862,720 Stack 773 Bldg. 440 Pu-241 45,204,566 Th-228 45,204,566 Th-230 45,204,566 Th-232 45,204,566 U-234 45,204,566 U-235 45,204,566 U-238 45,204,566 Stack 774 Bldg. 301 Th-228 84,762,558 Th-230 84,762,558 Th-232 84,762,558 U-234 84,762,558 U-235 84,762,558 U-238 84,762,558 Stack 796 Bldg. 100 Pu-241 5,129,613 Tc-99 5,129,6 13 U-234 5,129,613 U-235 5,129,613 Radioactivity in Effluent Air July 1, 2020 to December 31, 2020 Activity Error Quantity Concentration Estimate LLD Released | |||
(µCi/ml) | |||
(µCi/ml) | |||
(µCi/ml) | |||
(Ci) 776.96 m3/min 12.95 m3/scc 8.15E-15 2.48E-14 4.58E-14 l.68E-06 2.06E-16 7.58E-16 l.68E-15 4.24E-08 | |||
: l. l 9E-t 6 4.36E-16 9.65E-16 2.44E-08 l.68E-I 6 6.20E-l 6 l.37E-15 3.47E-08 I.29E-15 4.74E-15 l.05E-14 2.65E-07 l.33E-l 6 4.90E-16 1.0SE-15 2.74E-08 1.62E-16 5.97E-16 l.32E-l 5 3.34E-08 170.61 m3/min 2.84 m3/scc 3.59E-15 3.41 E-14 6.53E-14 l.62E-07 O.OOE+OO l.26E-l 5 3.36E-15 O.OOE+OO O.OOE+OO 1.62E-15 4.32E-15 O.OOE+OO O.OOE+OO l.OSE-15 2.88E-15 O.OOE+OO O.OOE+OO 3.32E-l 5 8.88E-15 O.OOE+OO O.OOE+OO 5.84E-16 1.56E-15 O.OOE+OO O.OOE+OO 1.17E-15 3.12E-15 O.OOE+OO 319.87 m 3/min 5.33 m 3/sec 7.36E-l 7 2.02E-16 4.54E-16 6.24E-09 2.51E-16 6.SSE-16 t.55E-l 5 2.13E-08 l.49E-16 4.0SE-16 9.17E-16 I.26E-08 6.70E-16 l.84E-15 4.13E-15 5.68E-08 4.36E-l 7 l.20E-16 2.69E-16 3.69E-09 | |||
: 3. 16E-16 8.66E-16 1.94E-15 2.68E-08 19.36 m3/min 0.32 m3tscc 8.71E-16 9.29E-16 I.SSE-15 4.47E-09 2.82E-14 3.00E-14 5.01 E-14 1.44E-07 2.79E-16 7.38E-15 l.86E-14 I.43E-09 8.64E-l 8 2.28E-16 5.74E-16 4.43E-ll Quantity Released (g) | |||
I.63E-08 | |||
: 5. I 7E-1 I l.21E-06 3.ISE-01 4.25E-05 l.27E-02 9.97E-02 Total: | |||
I.57E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total: | |||
7.62E-12 l.05E-06 I.I 6E-O I | |||
: 9. II E-06 1.71 E-03 7.99E-02 Total: | |||
4.34E-I I 8.SSE-06 2.30E-07 2 OSE-05 Total: | |||
ECV: Effluent Concentration Value from 10-CFR-20, Appendix B. Fradion 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 or *o* was substituted for negative analytical resutts. | Note: A value or *o* was substituted for negative analytical resutts. | ||
Printed: 02/09/2021 | Printed: 02/09/2021 NFS-EDMS Page 9 of 14 Fraction of ECV 1 | ||
1.02E-02 l.03E-02 5.93E-03 4.21E-02 2.58E-02 2.22E-03 2.70E-03 9.92E-02 4.48E-03 O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.48E-03 3.68E-03 l.25E-02 3.72E-02 l.34E-02 7.26E-04 5.26E-03 7.28E-02 l.09E-03 3.13E-05 5.59E-03 l.44E-04 6.8SE-03 Page 3 of3 To Letter Dated February 12, 2021 21 G-21-0029 GOV-01-55 ACF-21-0042 Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed Off-Site Individual for the Release Period July to December 2020 (4 Pages to Follow) | |||
21 G-21-0029 GOV-01-55 ACF-21-0042 | Page 10 of14 | ||
Page 10 of14 | |||
21 G-21-0029 GOV-01-55 ACF-21-0042 Report of Potential Gaseous Effluent Dose to the Maximally Exposed Offsite Individual and on the Maximum Radionuclide Concenb'ations for the Period: | 21 G-21-0029 GOV-01-55 ACF-21-0042 Report of Potential Gaseous Effluent Dose to the Maximally Exposed Offsite Individual and on the Maximum Radionuclide Concenb'ations for the Period: | ||
| Line 77: | Line 141: | ||
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 second hatf of 2020. 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 ~he 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 second hatf of 2020. 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 ~he 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 | 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. | ||
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. | ||
Page 11 of 14 | Page 11 of 14 f r | ||
21 G-21-0029 GOV-01-55 ACF-21-0042 Table 1 summarizes the six-month dose to a hypothetical individual at the MEI location, which was determined to be approximately 450 meters Northeast from the center of the plant site. The TEDE to the MEI was estimated to be 3.4E-03 mrem for gaseous effluents released during the second half of 2020. The highest organ committed dose equivalent (COE) to the MEI was estimated to be 1.8E-02 mrem to the lungs. These MEI doses are well below the Environmental Radiological Monitoring Program action levels and applicable regulatory limits/ALARA constraints. | 21 G-21-0029 GOV-01-55 ACF-21-0042 Table 1 summarizes the six-month dose to a hypothetical individual at the MEI location, which was determined to be approximately 450 meters Northeast from the center of the plant site. The TEDE to the MEI was estimated to be 3.4E-03 mrem for gaseous effluents released during the second half of 2020. The highest organ committed dose equivalent (COE) to the MEI was estimated to be 1.8E-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 | 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 2020) 2.3E-04 2.7E-04 8.7E-03 2.3E-04 2.4E-04 4.4E-03 2.6E-04 1,3E-03 3.3E-03 2.9E-03 7.6E-04 2.4E-04 2.4E-04 2.3E-04 1.1 E-03 4.7E-04 2.3E-04 2.5E-04 2.3E-04 2.3E-03 2.3E-04 2.3E-04 2.3E-04 1.5E-02 1.8E-02 3.4E-03 mrem 450 meters Northeast Page 12 of14 | |||
21 G-21-0029 GOV-01-55 ACF-21-0042 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 5.7E-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. | 21 G-21-0029 GOV-01-55 ACF-21-0042 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 5.7E-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. | ||
T~ble 2. Maximum Predicted Airborne Concentrations at or Beyond the Site Boundary | T~ble 2. Maximum Predicted Airborne Concentrations at or Beyond the Site Boundary i ** n:,....,... | ||
**-**..r* | |||
~ | |||
* 10. CFR20~._i'i; _* Rati:c{of~ ._ | *1.. **, | ||
.:~- ._N~l1~-~\ , ~celljrau,on*.-. -:*: .. ,*::, '.~on:::-., , . ~~~e"2, Col~} :V~u~ | .. ~ | ||
* l~~c~~tta'tioµ tQ **. | *: -'": *. :* * * *-.:Ma,ximii'm'_'1* * '*. *.eon:~*entratio~ ' _.*> | ||
*.:*' _.', t ~*-,~'-r *--:,'~~r:*:: * | * 10. CFR20~._i'i; _* Rati:c{of~._ | ||
99Tc | .:~-._N~l1~-~\\, ~celljrau,on*.-. -:*:..,*::, '.~on:::-.,,. ~~~e"2, Col~} :V~u~ | ||
* l~~c~~tta'tioµ tQ **. | |||
*.:*' _.', t ~*-,~'-r *--:,'~~r:*:: * :**s.~~~:,. ~:~qm);. :/-:' 0:'91~): *... * '._"J~-~,20.y~ue::~- | |||
Sum QfF'ractions: | 99Tc 1.SE-17 NE 400 9.E-10 20E-08 z2sTh 5.4E-20 NE (j(X) 2E-14 27E-06 230Th 6.lE-20 NE 650 2E-14 3.0E-06 732Th 2.6E-20 NE 450 4.E-15 6.4E--06 234u 27E-17 NE 500 5.E-14 5.4E-04 235u 9.lE-19 NE 550 6.E-14 1.5E-05 238u 1.4E-19 NE 650 6.E-14 2.3E-06 238Pu 0.0E+OO NIA NIA 2.E-14 0.0E+oo 23_9Pu 0.0E+-00 NIA NIA 2E-14 0.0E+oo 241Pu 1.8E-}8 NE 400 8.E-13 23E-06 2-41Am 22E-26 NE 650 2E-14 l.lE-12 | ||
., -~ | |||
NIA: Not Applicable | ~ | ||
Page 13 of14 | '~. | ||
Sum QfF'ractions: | |||
5.7E-04 | |||
~ | |||
. ~. | |||
NIA: Not Applicable we to 0.0 max. concentration. | |||
Page 13 of14 | |||
21 G-21-0029 GOV-01-55 ACF-21-0042 The TEDE to the MEI for gaseous effluents released during 2020 is provided in Table 3. | |||
The results for the 1st half of 2020 were previously reported in Biannual Effluent Monitoring Report January to June 2020 (21G-20-0084). The annual dose is well below the Environmental Radiological Monitoring Program action levels and applicable regulatory limits/ALARA constraints. | The results for the 1st half of 2020 were previously reported in Biannual Effluent Monitoring Report January to June 2020 (21G-20-0084). 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 2020 Period | Table 3. Annual Dose to the MEI for Gaseous Effluents Released During 2020 Period Direction Distance TEDE Covered (m) | ||
(mrem) 2nd Half NE 450 3.4E-03 1st Half NE 500 2.6E-03 Annual Total 6.0E-03 Page 14 of 14}} | |||
Latest revision as of 10:43, 29 November 2024
| ML21064A071 | |
| Person / Time | |
|---|---|
| Site: | Erwin |
| Issue date: | 02/12/2021 |
| From: | Knowles T BWXT Nuclear Fuel Services |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| 21G-21-0029, ACF-21-0042, GOV-01-55 | |
| Download: ML21064A071 (14) | |
Text
Nuclear Fuel Servi.ces, 1nc.
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 21 G-21-0029 GOV-01-55 ACF-21-0042 February 12, 2021
Subject:
Biannual Effluent Monitoring Report July to December 2020
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 2020. Attachment 2 reports the Radioactivity in Effluent Air for the period July to December 2020. Attachment 3 summarizes an evaluation of the dose and air activity concentrations for the maximally exposed offsite indMdual due to gaseous effluents during the period July to December 2020.
If you or your staff have any questions, require additional infom,ation, 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 (21 G 0029) in any correspondence concerning this 1etter.
CJB/pj
.Attachments Sincerely, NUCLEAR FUEL SERVICES, INC.
j~~~
Tim Knowles Safety &- Safeguards Director
)ZEf?'J Nf/55ZD fi)f1_SS
- 1) Report *of Radioactivity in Effluent Liquid for the Period July to December 2020
- 2) Report of Radioactivity in Effluent Air for the Period July to December 2020
- 3) Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed* Off-Site Individual for the Release Period July to December 2020 1206 Banner Hdl Rd, Erwin, TN 37650 Page 1 of 14 t +1.423 743 9141 I +1423743 0140 wwwnuclerui1Jelservices com People Strong INNDVATIDN DRIVEN >
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 Br:anch 1 U. S. Nuclear Regulatory Commission Region II 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Mr. Larry Hanis Senior Resident :Inspector U.S. Nuclear Regulatory Commission Page 2 of14 21 G-21-0029 GOV-01-55 ACF-21-0042 To Letter Dated February 12, 2021 Report of Radioactivity in Effluent Liquid for the Period July to December 2020 (2 Pages to Follow)
Page 3 of 14 21 G-21-0029 GOV-01-55 ACF-21-0042
Radioactivity in Effluent Liquid July 1, 2020 to December 31, 2020 Total Activity Error Quantity Volume Concentration Estimate LLD Released Location (I)
(µCi/ml)
(µCi/ml)
(µCi/ml)
(Ci)
Banner Spring Down Pu-238 444,874,000 O.OOE+OO l.22E-10 2.79E-10 O.OOE+OO Pu-239/240 444,874,000 J.32E-l l I.SIE-1 0 3.07E-1 0 S.89E-06 Tc-99 444,874,000 O.OOE+OO 3.83E-08 6.78E-08 O.OOE+OO Th-228 444,874,000 S.14E-12 1.S2E-I 0 3.33E-l 0 2.28E-06 Th-230 444,874,000
- 2. 14E-l 0 O.OOE+OO U-233/234 444,874,000 2.34E-l 0 2.35E-IO 3.26E-IO l.04E-04 U-235/236 444,874,000 2.06E-l l l.39E-10 2.82E-1 0 9.14E-06 U-238 444,874,000 O.OOE+OO I.ISE-1 0 2.66E-IO O.OOE+OO Sewer Pu-238 33,721,400 O.OOE+OO l.29E-IO 3.27E-l 0 O.OOE+OO Pu-239/240 33,721,400 O.OOE+OO 1.26E-l 0 3.S6E-I O O.OOE+OO Tc-99 33,721,400 O.OOE+OO
- 4. I 7E-08 7.46E-08 O.OOE+OO Th-228 33,721,400 O.OOE+OO 1.91E-10 4.37E-l 0 O.OOE+OO Th-230 33,72 1,400 7.28E-11 2.2 1E-10 4.29E-10 2.4SE-06 Th-232 33,721,400 O.OOE+OO l.17E-I O 2.66E-l 0 O.OOE+OO U-232 33,721,400 4.07E-l l l.13E-J O 2.09E-l 0 l.37E-06 U-233/234 33,721,400
- 1. l 7E-08 1.0 I E-09 I.84E-l 0 3.94E-04 U-23S/236 33,72 1,400 4.S9E-I 0 2.04E-I O 1.06E-IO I.SSE-OS U-238 33,72 1,400 I.S3E-09 3.66E-IO l.3SE-10 S. l 6E-OS West Ditch Pu-238 143, 7S3,000 O.OOE+OO l.29E-I O 3.35E-JO O.OOE+OO Pu-239/240 143,7S3,000 O.OOE+OO 1.41 E-10 3.65E-IO O.OOE+OO Tc-99 143,7S3,000 O.OOE+OO 3.93E-08 6.95E-08 O.OOE+OO Th-228 143,7S3,000 O.OOE+OO l.76E-l 0 3.87E-l 0 O.OOE+OO Th-230 143,753,000 7.68E-l l l.94E-10 3.49E-IO 1.1 OE-OS Th-232 143,7S3,000 2.79E-ll 1.3 I E-10 2.38E-10 4.0IE-06 U-233/234 143,753,000 I.52E-08 l.44E-09 2.86E-1 0
- 2. l 8E-03 U-23S/236 143,7S3,000 6.07E-10 3.3SE-10 2.16E-IO 8.72E-OS U-238 143,753,000 I.24E-09 4.20E-IO 2.14E-10 1.78E-04 WWTF Am-24 1 3,6 I S,678 3.20E-l l I.06E-l 0 I.91E-JO 1.1 6E-07 Cs-137 3,6 l S,678 O.OOE+OO l.OSE-09 l.S4E-09 O.OOE+OO Na-22 3,61S,678 2.58E-10 8.13E-IO l.52E-09 9.32E-07 Np-237 3,61 S,678 O.OOE+OO 1.70E-10 4.61E-10 O.OOE+OO Pb-212 3,615,678 9.SOE-10
- 3. l lE-09 2.93E-09 3.43E-06 Pu-238 3,615,678 O.OOE+OO 7.78E-l l
- 2. 13E-1 0 O.OOE+OO ECV: Effluent Concentrallon Value rrom 10-CFR-20, Appendix 8.
Note: A value of *o* was substituted for negative analytical results.
Printed: 02/09/202 1 NFS - EDMS Page 4 of 14 Quantity Fraction Released of 1
(g)
ECV O.OOE+OO O.OOE+OO 9.47E-OS 6.62E-04 O.OOE+OO O.OOE+OO 2.79E-09 2.57E-05 6.97E-05
- 3. I 7E-05 O.OOE+OO O.OOE+OO l.67E-02 7.81E-04 4.23E+OO 6.85E-05 O.OOE+OO O.OOE+OO Total:
l.57E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.21E-04 7.28E-OS O.OOE+OO O.OOE+OO 6.42E-08 6.79E-OS 6.3 IE-02 3.89E-03
- 7. 17E+OO l.53E-04 I.S4E+02 S.IOE-04 Total:
4.70E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO S.46E-04 7.68E-04 3.68E+Ol 9.31E-04 3.SOE-01 S.06E-02 4.04E+Ol 2.02E-03 5.3 IE+02 4.13E-03 Total:
S.84E-02 3.38E-08 l.60E-03 O.OOE+OO O.OOE+OO l.49E-l 0 4.29E-OS O.OOE+OO O.OOE+OO 2.48E-1 2 4.75E-04 O.OOE+OO O.OOE+OO Page I of2
Radioactivity in Effluent Liquid July 1, 2020 to December 31, 2020 Total Activity Volume Concentration Location (I)
(µCi/ml)
WWTF Pu-239/240 3,615,678 0.00E+00 Pu-241 3,615,678 0.00E+00 Ra-224 3,615,678 9.46E-09 Tc-99 3,615,678 0.00E+00 Th-228 3,615,678 0.00E+00 Th-230 3,615,678 4.38E-l l Th-23 1 3,615,678 l.06E-08 Th-232 3,615,678 0.00E+00 U-232 3,615,678 0.00E+00 U-233/234 3,615,678 9.72E-09 U-235/236 3,615,678 3.68E-10 U-238 3,615,678 9.23E-l 1 ECV: Effluent Concentration Value from 10*CFR*20, Appendix 8.
Note: A value of "O" was substituted for negative analytical results.
Printed: 02/09/2021 Error Quantity Estimate LLD Released
(µCi/ml)
(µCi/ml)
(Ci) 7.25E-ll 2.00E-10 0.00E+00 l.20E-08 2.0SE-08 0.00E+00 4.80E-09 8.67E-09 3.42E-05 l.53E-07 2.64E-07 0.00E+00 l.42E-I0 3.20E-10 0.00E+00 I. 70E-l 0 3.31E-10 l.59E-07
- 4. l lE-08 3.82E-08 3.82E-05 l.08E-10 2.47E-I0 0.00E+00 9.78E-l l 2.I0E-10 0.00E+00 8.77E-I0 l.SI E-10 3.51 E-05 l.80E-10 l.14E-10 1.33E-06 l.06E-10 l.31E-10 3.34E-07 NFS-EDMS Page 5 of 14 Quantity Fraction Released of (g)
ECV 1
0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.ISE-10 4.73E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.85E-06 4.38E-04
- 7. l 7E-l l 2.l lE-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.63E-03 3.24E-02 6.16E-01 1.23E-03 9.96E-0I 3.08E-04 Total:
8.40E-02 Page 2 of2 To Letter Dated February 12, 2021 Report of Radioactivity in Effluent Air for the Period July to December 2020 (3 Pages to Follow)
Page 6 of 14 21G-21-0029 GOV-01-55 ACF-21-0042
Total Volume Location (ml )
Ma in Stack 416 Th-228 274,100,738 Th-230 274, I 00,738 U-234 274,100,738 U-235 274, I 00,738 U-238 274,100,738 Stack 185 Bldg. 131 Pu-24 1 29,936,302 Tc-99 29,936,302 U-234 29,936,302 U-235 29,936,302 Stack 234 Bldg. 234 Am-241 80,728,684 Pu-238 80,728,684 Pu-239/240 80,728,684 Pu-241 80,728,684 Th-228 80,728,684 Th-230 80,728,684 Th-232 80,728,684 U-234 80,728,684 U-238 80,728,684 Stack 327 Bldg. 330 Pu-241 274,993,820 Tc-99 274,993,820 U-234 274,993,820 U-235 274,993,820 Stack 421 Bldg. 100 Pu-24 1 8,861,131 Tc-99 8,861,131 U-234 8,861,131 U-235 8,861,131 Stack 424 Bldg. 100 Pu-24 1 8,692,072 Tc-99 8,692,072 U-234 8,692,072 Radioactivity in Effluent Air July 1, 2020 to December 31, 2020 Activity Error Quantity Concentration Estimate LLD Released
(µCi/ml)
(µCi/ml)
(µCi/ml)
(Ci) 1033.76 ml/min 17.23 ml/sec 5.04E-1 6 l.04E-l 6 5.74E-17 l.38E-07 6.72E-16 l.38E-16 7.65E-17 I.84E-07 l.58E-1 3 3.26E-14 1.81E-14 4.34E-05 6.38E-15 l.31E-15 7.27E-16 l.75E-06 l.85E-1 5 3.80E-16
- 2. I0E-1 6 5.06E-07 112.98 ml/min 1.88 m3/sec 6.67E-16 9.00E-16 l.5SE-1 5 2.00E-08 2.16E-14 2.91E-14 5.00E-14 6.45E-07 3.63E-15 8.82E-l 5 l.85E-14 l.09E-07 1.12E-1 6 2.73E-16 5.72E-16 3.36E-09 308.03 ml/min 5.13 ml/sec 0.00E+00 2.07E-17 4.49E-17 0.00E+00 0.00E+00 2.53E-17 5.49E-17 0.00E+00 0.00E+00 8.96E-17 l.95E-16 0.00E+00 l.35E-l 5 4.24E-I S 7.48E-1 5 l.09E-07 0.00E+00 l.38E-l 7 3.00E-1 7 0.00E+00 0.00E+00 1.72E-16 3.74E-16 0.00E+00 0.00E+00 2.18E-16 4.74E-16 0.00E+00 0.00E+00 4.7 1E-16 1.02E-15 0.00E+00 0.00E+00 l.38E-l 6 3.00E-16 0.00E+00 1037.87 ml/min 17.30 ml/sec 2.0SE-1 5 4.77E-1 6 7.02E-16 S.63E-07 6.63E-14 l.54E-14 2.27E-14 l.82E-05 8.90E-14 I.0SE-14 8.58E-15 2.45E-05 2.75E-15 3.26E-16 2.65E-l 6 7.57E-07 33.41 ml/min 0.56 ml/sec 5.48E-l 5 l.38E-l S 1.92E-l S 4.8SE-08 I. 77E-l 3 4.46E-14 6.22E-14 l.57E-06 S.16E-14 l.76E-1 4
- 2. 14E-14 4.58E-07 l.60E-15 S.45E-16 6.62E-16 I.42E-08 32.79 ml/min 0.55 ml/sec l.2SE-15 9.85E-1 6 1.55E-15 l.09E-08 4.0SE-14 3.19E-1 4 5.00E-14 3.52E-07 2.0SE-1 4 l.24E-14 l.86E-l 4 I. 78E-07 Quantity Released (g) l.69E-1 0 9.11 E-06 6.96E-03
- 8. I0E-0 1 1.51 E+00 Total:
l.94E-10 3.82E-05 I.74E-05 I.56E-03 Total:
0.00E+00 0.00E+00 0.00E+00 l.06E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total:
5.47E-09 l.08E-03 3.92E-03 3.S0E-01 Total:
4.7 1E-10 9.29E-05 7J3E-0S 6.55E-03 Total:
l.06E-I 0 2.09E-0S 2.85E-05 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 exi1s the site.
Note: A value of ~ a~ was substituted for negative analytical results.
Printed: 02/09/202 1 NFS-EDMS Page 7 of 14 Fraction of ECV 1
2.52E-02 3J6E-02
- 3. I 7E+00 l.06E-0I 3.08E-02 3.37E+00 8.33E-04 2.40E-05 7.27E-02 l.87E-03 7.54E-02 0.00E+00 0.00E+00 0.00E+00 l.69E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l.69E-03 2.56E-03 7.36E-0S l.78E+00 4.59E-02 1.83E+00 6.8SE-03 l.97E-04 l.03E+00 2.66E-02 1.07E+00 I.57E-03 4.S0E-05 4.I0E-01 Page I of3
Total Volume Location (m3)
Stack 424 Bldg. 100 U-235 8,692,072 Stack 573 Bldg 306-W Pu-241 19,390,581 Tc-99 19,390,581 U-234 19,390,581 U-235 19,390,581 Stack 600 Bldg. 110 Pu-241 83,150,468 Tc-99 83,150,468 U-234 83,150,468 U-235 83,150,468 Stack 615 Bldg. 306-W Pu-241 12,814,838 Tc-99 12,814,838 U-234 12,814,838 U-235 12,814,838 Stack 646 Bldg. ll0 Pu-241 10,28 1,735 Tc-99 10,28 1,735 U-234 10,281,735 U-235 10,281,735 Stack 701 Bldg. 307 Pu-241 3 1,183,240 Tc-99 31, I 83,240 U-234 31,183,240 U-235 31,183,240 Stack 702 Bldg. 307 Pu-241 42,358,587 Tc-99 42,358,587 U-234 42,358,587 U-235 42,358,587 Radioactivity in Effluent Air July 1, 2020 to December 31, 2020 Activity Error Quantity Concentration Estimate LLD Released
(µCi/ml)
(µCi/ml)
(µCi/ml)
(Ci) 32.79 m3/min 0.55 m3/sec 6.33E-l 6 3.84E-16 5.75E-16 5.51 E-09 72.10 m3/min 1.20 m3/sec 3.60E-16 7.97E-16 l.48E-l 5 6.97E-09 l.l6E-14 2.58E-14 4.79E-14 2.25E-07 l.29E-14 8.89E-l 5 1.79E-14 2.51 E-07 4.00E-16 2.75E-16 5.SSE-16 7.76E-09 313.96 m3/min 5.23 m3/sec l.5SE-15 5.96E-16 9.SlE-16 l.29E-07 5.0lE-14 l.93E-14 3.07E-14 4.16E-06 4.69E-14 8.82E-15 l.21 E-14 3.90E-06 l.45E-l 5 2.73E-16 3.76E-16 l.21E-07 48.37 m3/min 0.81 m3Jsec 1.88E-l 6 8.lSE-16 1.53E-15 2.4 1 E-09 6.08E-15 2.64E-14 4.95E-14 7.79E-08 2.25E-16 7.23E-15 1.83E-14 2.88E-09 6.96E-18 2.24E-16 5.67E-16 8.91E-l l 38.71 m3/min 0.65 m3/sec 4.1 2E-16 8.65E-16 ISSE-15 4.24E-09 l.33E-14 2.80E-14 5.02E-14 l.37E-07 4.l8E-16 7.31E-15 1.85E-14 4.30E-09 l.29E-17 2.26E-16 5.72E-16 l.33E-IO 117.79 m3/min l.96 m3/sec 3.39E-16 9.58E-l 6 l.76E-15 l.06E-08 I.IOE-14 3.IOE-14 5.70E-14 3.42E-07 9.81E-15 l.03E-14 2.l lE-14 3.06E-07 3.03E-16 3.19E-16 6.53E-16 9.46E-09 159.78 m3/min 2.66 m3/sec 3.03E-16 8.SlE-16 1.56E-15 I.28E-08 9.78E-l5 2.75E-14 5.06E-14 4.l4E-07 3.95E-15 8.77E-l5 l.87E-14 l.67E-07 l.22E-16 2.71E-16 5.80E-16
- 5. l 8E-09 Quantity Released (g) 2.SSE-03 Total:
6.77E-l l l.33E-05 4.02E-05 3.59E-03 Total:
l.25E-09 2.46E-04 6.25E-04 5.58E-02 Total:
2.34E-l l 4.61 E-06 4.62E-07 4.13E-05 Total:
4.12E-ll 8.l lE-06 6.89E-07 6.16E-05 Total:
l.03E-10 2.02E-05 4.90E-05 4.38E-03 Total:
1.24E-l 0 2.45E-05 2.68E-05 2.40E-03 Total:
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 resuNs.
Printed: 02/09/2021 NFS - EDMS Page 8 of 14 Fraction of ECV 1
l.06E-02 4.22E-0l 4.SOE-04 l.29E-05 2.59E-01 6.67E-03 2.66E-0l l.94E-03 5.56E-05 9.37E-Ol 2.42E-02 9.64E-0l 2.35E-04 6.75E-06 4.SOE-03 l.16E-04 4.86E-03
- 5. l SE-04 1.48E-05 8.37E-03 2.16E-04 9.llE-03 4.23E-04 l.22E-05 l.96E-Ol 5.06E-03 2.02E-0l 3.78E-04 l.09E-05 7.90E-02 2.04E-03 8.15E-02 Page 2 of3
Total Volume Location (ml)
Stack 703 Exhaust Room Air Pu-241 205,862,720 Th-228 205,862,720 Th-230 205,862,720 Th-232 205,862,720 U-234 205,862,720 U-235 205,862,720 U-238 205,862,720 Stack 773 Bldg. 440 Pu-241 45,204,566 Th-228 45,204,566 Th-230 45,204,566 Th-232 45,204,566 U-234 45,204,566 U-235 45,204,566 U-238 45,204,566 Stack 774 Bldg. 301 Th-228 84,762,558 Th-230 84,762,558 Th-232 84,762,558 U-234 84,762,558 U-235 84,762,558 U-238 84,762,558 Stack 796 Bldg. 100 Pu-241 5,129,613 Tc-99 5,129,6 13 U-234 5,129,613 U-235 5,129,613 Radioactivity in Effluent Air July 1, 2020 to December 31, 2020 Activity Error Quantity Concentration Estimate LLD Released
(µCi/ml)
(µCi/ml)
(µCi/ml)
(Ci) 776.96 m3/min 12.95 m3/scc 8.15E-15 2.48E-14 4.58E-14 l.68E-06 2.06E-16 7.58E-16 l.68E-15 4.24E-08
- l. l 9E-t 6 4.36E-16 9.65E-16 2.44E-08 l.68E-I 6 6.20E-l 6 l.37E-15 3.47E-08 I.29E-15 4.74E-15 l.05E-14 2.65E-07 l.33E-l 6 4.90E-16 1.0SE-15 2.74E-08 1.62E-16 5.97E-16 l.32E-l 5 3.34E-08 170.61 m3/min 2.84 m3/scc 3.59E-15 3.41 E-14 6.53E-14 l.62E-07 O.OOE+OO l.26E-l 5 3.36E-15 O.OOE+OO O.OOE+OO 1.62E-15 4.32E-15 O.OOE+OO O.OOE+OO l.OSE-15 2.88E-15 O.OOE+OO O.OOE+OO 3.32E-l 5 8.88E-15 O.OOE+OO O.OOE+OO 5.84E-16 1.56E-15 O.OOE+OO O.OOE+OO 1.17E-15 3.12E-15 O.OOE+OO 319.87 m 3/min 5.33 m 3/sec 7.36E-l 7 2.02E-16 4.54E-16 6.24E-09 2.51E-16 6.SSE-16 t.55E-l 5 2.13E-08 l.49E-16 4.0SE-16 9.17E-16 I.26E-08 6.70E-16 l.84E-15 4.13E-15 5.68E-08 4.36E-l 7 l.20E-16 2.69E-16 3.69E-09
- 3. 16E-16 8.66E-16 1.94E-15 2.68E-08 19.36 m3/min 0.32 m3tscc 8.71E-16 9.29E-16 I.SSE-15 4.47E-09 2.82E-14 3.00E-14 5.01 E-14 1.44E-07 2.79E-16 7.38E-15 l.86E-14 I.43E-09 8.64E-l 8 2.28E-16 5.74E-16 4.43E-ll Quantity Released (g)
I.63E-08
- 5. I 7E-1 I l.21E-06 3.ISE-01 4.25E-05 l.27E-02 9.97E-02 Total:
I.57E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total:
7.62E-12 l.05E-06 I.I 6E-O I
- 9. II E-06 1.71 E-03 7.99E-02 Total:
4.34E-I I 8.SSE-06 2.30E-07 2 OSE-05 Total:
ECV: Effluent Concentration Value from 10-CFR-20, Appendix B. Fradion 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 or *o* was substituted for negative analytical resutts.
Printed: 02/09/2021 NFS-EDMS Page 9 of 14 Fraction of ECV 1
1.02E-02 l.03E-02 5.93E-03 4.21E-02 2.58E-02 2.22E-03 2.70E-03 9.92E-02 4.48E-03 O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.48E-03 3.68E-03 l.25E-02 3.72E-02 l.34E-02 7.26E-04 5.26E-03 7.28E-02 l.09E-03 3.13E-05 5.59E-03 l.44E-04 6.8SE-03 Page 3 of3 To Letter Dated February 12, 2021 21 G-21-0029 GOV-01-55 ACF-21-0042 Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed Off-Site Individual for the Release Period July to December 2020 (4 Pages to Follow)
Page 10 of14
21 G-21-0029 GOV-01-55 ACF-21-0042 Report of Potential Gaseous Effluent Dose to the Maximally Exposed Offsite Individual and on the Maximum Radionuclide Concenb'ations for the Period:
July to December 2020 Introduction During this biannual period, NRC License SNM-124, Sectibn 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 second hatf of 2020. 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 ~he 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 f r
21 G-21-0029 GOV-01-55 ACF-21-0042 Table 1 summarizes the six-month dose to a hypothetical individual at the MEI location, which was determined to be approximately 450 meters Northeast from the center of the plant site. The TEDE to the MEI was estimated to be 3.4E-03 mrem for gaseous effluents released during the second half of 2020. The highest organ committed dose equivalent (COE) to the MEI was estimated to be 1.8E-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 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 2020) 2.3E-04 2.7E-04 8.7E-03 2.3E-04 2.4E-04 4.4E-03 2.6E-04 1,3E-03 3.3E-03 2.9E-03 7.6E-04 2.4E-04 2.4E-04 2.3E-04 1.1 E-03 4.7E-04 2.3E-04 2.5E-04 2.3E-04 2.3E-03 2.3E-04 2.3E-04 2.3E-04 1.5E-02 1.8E-02 3.4E-03 mrem 450 meters Northeast Page 12 of14
21 G-21-0029 GOV-01-55 ACF-21-0042 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 5.7E-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.
T~ble 2. Maximum Predicted Airborne Concentrations at or Beyond the Site Boundary i ** n:,....,...
- -**..r*
~
- 1.. **,
.. ~
- -'": *. :* * * *-.:Ma,ximii'm'_'1* * '*. *.eon:~*entratio~ ' _.*>
- 10. CFR20~._i'i; _* Rati:c{of~._
.:~-._N~l1~-~\\, ~celljrau,on*.-. -:*:..,*::, '.~on:::-.,,. ~~~e"2, Col~} :V~u~
- l~~c~~tta'tioµ tQ **.
- .:*' _.', t ~*-,~'-r *--:,'~~r:*:: * :**s.~~~:,. ~:~qm);. :/-:' 0:'91~): *... * '._"J~-~,20.y~ue::~-
99Tc 1.SE-17 NE 400 9.E-10 20E-08 z2sTh 5.4E-20 NE (j(X) 2E-14 27E-06 230Th 6.lE-20 NE 650 2E-14 3.0E-06 732Th 2.6E-20 NE 450 4.E-15 6.4E--06 234u 27E-17 NE 500 5.E-14 5.4E-04 235u 9.lE-19 NE 550 6.E-14 1.5E-05 238u 1.4E-19 NE 650 6.E-14 2.3E-06 238Pu 0.0E+OO NIA NIA 2.E-14 0.0E+oo 23_9Pu 0.0E+-00 NIA NIA 2E-14 0.0E+oo 241Pu 1.8E-}8 NE 400 8.E-13 23E-06 2-41Am 22E-26 NE 650 2E-14 l.lE-12
., -~
~
'~.
Sum QfF'ractions:
5.7E-04
~
. ~.
NIA: Not Applicable we to 0.0 max. concentration.
Page 13 of14
21 G-21-0029 GOV-01-55 ACF-21-0042 The TEDE to the MEI for gaseous effluents released during 2020 is provided in Table 3.
The results for the 1st half of 2020 were previously reported in Biannual Effluent Monitoring Report January to June 2020 (21G-20-0084). 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 2020 Period Direction Distance TEDE Covered (m)
(mrem) 2nd Half NE 450 3.4E-03 1st Half NE 500 2.6E-03 Annual Total 6.0E-03 Page 14 of 14