ML21064A071

BWXT Nuclear Fuel Services, Inc. Biannual Effluent Monitoring Report July to December 2020

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.

21 G-21-0029 GOV-01-55 ACF-21-0042 February 12, 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 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.

Sincerely, NUCLEAR FUEL SERVICES, INC.

)ZEf?'J j~~~ Nf/55ZD Tim Knowles Safety &- Safeguards Director fi)f1_SS CJB/pj

.Attachments

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 People Strong 1206 Banner Hdl Rd, Erwin, TN 37650 Page 1 of 14 t +1.423 743 9141 I +1423743 0140 wwwnuclerui1Jelservices com INNDVATIDN DRIVEN >

21 G-21-0029 GOV-01-55 ACF-21-0042 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 Attachment 1 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

Radioactivity in Effluent Liquid July 1, 2020 to December 31, 2020 Total Activity Error Quantity Quantity Fraction Volume Concentration Estimate LLD Relea sed Released of 1

Location (I) (µCi/ml) (µCi/ml) (µCi/ml ) (Ci) (g) ECV Banner Spring Down Pu-238 444,874,000 O.OOE+OO l .22E-10 2.79E- 10 O.OOE+OO O.OOE+OO O.OO E+OO Pu-239/240 444,874,000 J .32E-l l I. SIE-1 0 3.07E-1 0 S.89E-06 9.47E-OS 6.62E-04 Tc-99 444,874,000 O.OOE+OO 3.83E-08 6.78E-08 O.OOE+OO O.OOE+OO O.OOE+OO Th-228 444,874,000 S.14E-12 1.S2E-I 0 3.33E-l 0 2.28E-06 2.79E-09 2.57E-05 Th-230 444,874,000 3. 17E-12 l.62 E- 10 3.52E- 10 1.41 E-06 6.97E-05 3. I 7E-05 Th-232 444,874,000 O.OOE+OO l.02E-l 0 2. 14E-l 0 O.OOE+OO O.OOE+OO O.OOE+OO U-233/234 444,874,000 2.34E- l 0 2.35E-IO 3.26E- IO l .04E-04 l .67E-02 7.81E-04 U-235/236 444,874,000 2.06E- l l l.39 E-10 2.82E-1 0 9.14E-06 4.23E+OO 6.85E-05 U-238 444,874,000 O.OOE+OO I.IS E-1 0 2.66E- IO O.OOE+OO O.OOE+OO O.OOE+OO Total: l.57E-03 Sewer Pu-238 33,721 ,400 O.OOE+OO l.29 E- IO 3.27E- l 0 O.OOE+OO O.OO E+OO O.OOE+OO Pu-239/240 33,721,400 O.OOE+OO 1.26E-l 0 3.S6E-I O O.OOE+OO O.OO E+OO O.OOE+OO Tc-99 33,721 ,400 O.OOE+OO 4. I 7E-08 7.46E-08 O.OOE+OO O.OOE+OO O.OOE+OO Th-228 33,721,400 O.OOE+OO 1.91E-10 4.37E-l 0 O.OOE+OO O.OOE+OO O.OO E+OO Th-230 33 ,72 1,400 7.28E- 11 2.2 1E- 10 4.29E-10 2.4SE-06 l .2 1E-04 7.28E-OS Th-232 33,721,400 O.OOE+OO l.17 E-I O 2.66E-l 0 O.OOE+OO O.OOE+OO O.OOE+OO U-232 33,721 ,400 4.07E- l l l.13 E-J O 2.09E-l 0 l. 37E-06 6.42E-08 6.79E-OS U-233/234 33,721 ,400 1. l 7E-08 1.0 I E-09 I. 84E-l 0 3.94E-04 6.3 IE-02 3.89E-03 U-23S/236 33,72 1,400 4.S9E- I 0 2.04E-I O 1.06E-IO I .SSE-OS 7. 17E+OO l.53E-04 U-238 33,72 1,400 I .S3E-09 3.66E-IO l .3 SE-10 S. l 6E-OS I.S4E+02 S.IOE-04 Total : 4.70E-03 West Ditch Pu-238 143,7S3,000 O.OOE+OO l.29E-I O 3.35E- JO O.OOE+OO O.OOE+OO O.OOE+OO Pu-239/240 143,7S3,000 O.OOE+OO 1.4 1E-10 3.65E-IO O.OOE+OO O.OOE+OO O.OOE+OO Tc-99 143,7S3,000 O.OOE+OO 3.93E-08 6.95E-08 O.OOE+OO O.OOE+OO O.OOE+OO Th-228 143,7S3 ,000 O.OOE+OO l.76E-l 0 3.87E- l 0 O.OOE+OO O.OOE+OO O.OOE+OO Th-230 143,753,000 7.68E-l l l.94E-10 3.49E- IO 1.1OE-OS S.46E-04 7.68E-04 Th-232 143,7S3,000 2.79E-ll 1.3 I E-10 2.38E-10 4.0IE-06 3.68E+Ol 9.31E-04 U-233/234 143,753,000 I.52E-08 l .44E-09 2.86E-1 0 2. l 8E-03 3.SOE-01 S.06E-02 U-23S/236 143,7S3,000 6.07E- 10 3.3SE-10 2.16E-IO 8.72E-OS 4.04E+Ol 2.02E-03 U-238 143,753,000 I.24E-09 4.20E- IO 2.14E- 10 1.78E-04 5.3 IE+02 4.13E-03 Total: S.84E-02 WWTF Am-24 1 3,6 I S,678 3.20E-l l I.06E-l 0 I.91E-JO 1.1 6E-07 3.38E-08 l .60E-03 Cs- 137 3,6 l S,678 O.OOE+OO l .OSE-09 l .S4E-09 O.OOE+OO O.OOE+OO O.OOE+OO Na-22 3,61S,678 2.58E-10 8.13E-IO l .52E-09 9.32E-07 l.49E- l 0 4.29E-OS Np-237 3,61S,678 O.OOE+OO 1.70E-10 4.6 1E- 10 O.OOE+OO O.OOE+OO O.OOE+OO Pb-212 3,615,678 9.SOE-10 3. l l E-09 2.93E-09 3.43E-06 2.48E-1 2 4.75E-04 Pu-238 3,6 15,678 O.OOE+OO 7.78E-l l 2. 13 E-1 0 O.OOE+OO O.OOE+OO 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 I of2 Page 4 of 14

Radioactivity in Effluent Liquid July 1, 2020 to December 31, 2020 Total Activity Error Quantity Quantity Fraction Volume Concentration Estimate LLD Released Released of 1

Location (I) (µCi/ml) (µCi/ml) (µCi/m l) (Ci) (g) ECV WWTF Pu-239/240 3,615 ,678 0.00E+00 7.25E-ll 2.00E-10 0.00E+00 0.00E+00 0.00E+00 Pu-241 3,615,678 0.00E+00 l .20E-08 2.0SE-08 0.00E+00 0.00E+00 0.00E+00 Ra-224 3,615,678 9.46E-09 4.80E-09 8.67E-09 3.42E-05 2. IS E-10 4.73E-02 Tc-99 3,615,678 0.00E+00 l .53E-07 2.64E-07 0.00E+00 0.00E+00 0.00E+00 Th-228 3,615,678 0.00E+00 l.42E-I0 3.20E-10 0.00E+00 0.00E+00 0.00E+00 Th-230 3,615,678 4.38E-l l I. 70E-l 0 3.31E-10 l.59E-07 7.85E-06 4.38E-04 Th-23 1 3,615,678 l.06E-08 4. l l E-08 3.82E-08 3.82E-05 7. l 7E-l l 2.l l E-04 Th-232 3,615,678 0.00E+00 l.08E-10 2.47E-I0 0.00E+00 0.00E+00 0.00E+00 U-232 3,615,678 0.00E+00 9.78E-l l 2.I0E-10 0.00E+00 0.00E+00 0.00E+00 U-233/234 3,615,678 9.72E-09 8.77E-I0 l.SI E- 10 3.51 E-05 5.63E-03 3.24E-02 U-235/236 3,615,678 3.68E- 10 l.80E-10 l.14E-10 1.33E-06 6.16E-01 1.23E-03 U-238 3,615,678 9.23E-l 1 l.06E-10 l.31E-10 3.34E-07 9.96E-0I 3.08E-04 Total: 8.40E-02 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 NFS-EDMS Page 2 of2 Page 5 of 14

21G-21-0029 GOV-01-55 ACF-21-0042 Attachment 2 To Letter Dated February 12, 2021 Report of Radioactivity in Effluent Air for the Period July to December 2020 (3 Pages to Follow)

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Radioactivity in Effluent Air July 1, 2020 to December 31, 2020 Total Acti vity Error Quanti ty Qu antity Fraction Volume Co nce ntration Estimate LLD Released Released of Location 1 (ml ) (µCi/ml) (µCi/ml) (µCi /ml) (Ci) (g) ECV Ma in Stac k 41 6 1033.76 ml/min 17 .23 ml/sec Th-228 274, 100,738 5.04E-1 6 l.04E- l 6 5.74E- 17 l .38E-07 l.69E-1 0 2.52E-02 Th-230 274, I 00,738 6.72E- 16 l.38E-16 7.65E- 17 I .84E-07 9.11 E-06 3J6E-02 U-234 274, 100,738 l. 58E-1 3 3.26E-14 1. 81E-14 4.34E-05 6.96E-03 3. I 7E+00 U-235 274, I 00,738 6.3 8E-15 l.31E-15 7.27E-16 l. 75E-06 8. I0E-0 1 l .06E-0I U-238 274,100,738 l.85E-1 5 3.80E-16 2. I0E-1 6 5.06E-07 1.51 E+00 3.08E-02 Total: 3.37E+00 Stack 185 Bldg. 131 112.98 ml/min 1.88 m3/sec Pu-24 1 29,936,302 6.67E- 16 9.00E- 16 l.5SE-1 5 2.00E-08 l.94E- 10 8.33E-04 Tc-99 29,936,302 2.16E- 14 2.91E- 14 5.00E-14 6.45E-07 3.82E-05 2.40E-05 U-234 29,936,302 3.63E- 15 8.82E-l 5 l.85E-14 l.09E-07 I .74E-05 7.27E-02 U-235 29,936,302 1.12E-1 6 2.73E- 16 5.72E-16 3.36E-09 I .56E-03 l .87E-03 Tota l: 7.54E-02 Stack 234 Bld g. 234 308.03 ml/min 5.13 ml/sec Am-241 80,728,684 0.00E+00 2.07E-17 4.49E- 17 0.00E+00 0.00E+00 0.00E+00 Pu-238 80,728,684 0.00E+00 2.53E-17 5.49E-17 0.00E+00 0.00E+00 0.00E+00 Pu-239/240 80,728,684 0.00E+00 8.96E-17 l.95E- 16 0.00E+00 0.00E+00 0.00E+00 Pu-241 80,728,684 l.35E- l 5 4.24E-I S 7.48E-1 5 l.09E-07 l .06E-09 l .69E-03 Th-228 80,728,684 0.00E+00 l.3 8E- l 7 3.00E-1 7 0.00E+00 0.00E+00 0.00E+00 Th-230 80,728,684 0.00E+00 1.72E-16 3.74E-16 0.00E+00 0.00E+00 0.00E+00 Th-232 80,728,684 0.00E+00 2.18E-16 4.74E-16 0.00E+00 0.00E+00 0.00E+00 U-234 80,728,684 0.00E+00 4.7 1E-16 1.02E-15 0.00E+00 0.00E+00 0.00E+00 U-238 80,728,684 0.00E+00 l.3 8E- l 6 3.00E-16 0.00E+00 0.00E+00 0.00E+00 Total : l.69E-03 Stack 327 Bldg. 330 1037.87 ml/min 17 .30 ml/sec Pu-24 1 274,993,820 2.0SE-1 5 4.77E-1 6 7.02E-16 S.63E-07 5.47E-09 2.56E-03 Tc-99 274,993,820 6.63E- 14 l.5 4E- 14 2.27E-14 l .82E-05 l .08E-03 7.36E-0S U-234 274,993,820 8.90E- 14 I.0SE- 14 8.58E-15 2.45E-05 3.92E-03 l.78E+00 U-235 274,993,820 2.75E- 15 3.26E-16 2.65E-l 6 7.57E-07 3.S0E-0 1 4.59E-02 Total: 1.83E+00 Stack 421 Bldg. 100 33.41 ml/min 0.56 ml/sec Pu-24 1 8,861 , 13 1 5.48E-l 5 l.3 8E- l S 1.92E- l S 4.8SE-08 4.7 1E- 10 6.8SE-03 Tc-99 8,861 , 13 1 I. 77E-l 3 4.46E- 14 6.22E- 14 l.57E-06 9.29E-05 l.97E-04 U-234 8,861 , 13 1 S.16E- 14 l.76E-1 4 2. 14E- 14 4.58E-07 7J3E-0S l .03E+00 U-235 8,861 , 131 l.60E- 15 S.45E- 16 6.62E-16 I .42E-08 6.55E-03 2.66E-02 Total : 1.07E+00 Stack 424 Bldg. 100 32.79 ml/min 0.55 ml/sec Pu-24 1 8,692,072 l.2SE- 15 9.85E-1 6 1. 55E- 15 l.09E-08 l.06E- I 0 I .57E-03 Tc-99 8,692,072 4.0SE- 14 3.19E-1 4 5.00E-14 3.52E-07 2.09E-0S 4.S0E-05 U-234 8,692,072 2.0SE-1 4 l.24E- 14 l. 86E- l 4 I. 78E-07 2.85E-05 4.I0E-01 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 efflue nt exi1s the site .

Note: A value of ~ a~ was substituted for negative analytical results.

Printed: 02/09/202 1 NFS-EDMS Page I of3 Page 7 of 14

Radioactivity in Effluent Air July 1, 2020 to December 31, 2020 Total Activity Error Quantity Quantity Fraction Volume Concentration Estimate LLD Released Released of 1

Location (m3) (µCi/ml) (µCi/ml) (µCi/ml) (Ci) (g) ECV Stack 424 Bldg. 100 32.79 m 3/min 0.55 m3/sec U-235 8,692,072 6.33E-l 6 3.84E-16 5.75E-16 5.51 E-09 2.SSE-03 l.06E-02 Total: 4.22E-0l Stack 573 Bldg 306-W 72.10 m 3/min 1.20 m3/sec Pu-241 19,390,581 3.60E-16 7.97E-16 l.48 E- l 5 6.97E-09 6.77E-l l 4.SOE-04 Tc-99 19,390,581 l.l6E-14 2.58E-14 4.79E-14 2.25E-07 l .33E-05 l .29E-05 U-234 19,390,581 l.29E-14 8.89E-l 5 1.79E- 14 2.51E-07 4.02E-05 2.59E-01 U-235 19,390,581 4.00E-16 2.75E-16 5.SSE-16 7.76E-09 3.59E-03 6.67E-03 Total: 2.66E-0l Stack 600 Bldg. 110 313.96 m3/min 5.23 m3/sec Pu-241 83,150,468 l.5SE-15 5.96E-16 9.SlE-16 l .29E-07 l.25E-09 l .94E-03 Tc-99 83,150,468 5.0lE-14 l.93E-14 3.07E-14 4. 16E-06 2.46E-04 5.56E-05 U-2 34 83, 150,468 4.69E-14 8.82E-15 l.21 E-14 3.90E-06 6.25E-04 9.37E-Ol U-235 83, 150,468 l.45 E- l 5 2.73E-16 3.76E-16 l .21E-07 5.58E-02 2.42E-02 Total: 9.64E-0l Stack 615 Bldg. 306-W 48.37 m 3/min 0.81 m3Jsec Pu-241 12,814,838 1.88E-l 6 8.lSE-16 1.53E-15 2.4 1E-09 2.34E-l l 2.3 5E-04 Tc-99 12,814,838 6.08E-15 2.64E-14 4.95E-14 7.79E-08 4.61 E-06 6.75E-06 U-234 12,814,838 2.25E-16 7.23E-15 1.83E-14 2.88E-09 4.62E-07 4.SOE-03 U-235 12,814,838 6.96E-18 2.24E-16 5.67E-16 8.91E-l l 4. 13E-05 l .16E-04 Total: 4.86E-03 Stack 646 Bldg. ll0 38.71 m 3/min 0.65 m3/sec Pu-241 10,28 1,735 4.1 2E-16 8.65E-16 ISSE-15 4.24E-09 4.12E-ll 5. l SE-04 Tc-99 10,28 1,735 l.33E-14 2.80E-14 5.02E-14 l .37E-07 8. l lE-06 1.48E-05 U-234 10,281 ,735 4.l8E-16 7.31E-15 1.85 E-14 4.30E-09 6.89E-07 8.37E-03 U-235 10,281 ,735 l .29E-17 2.26E-16 5.72E-16 l.33E-IO 6.16E-05 2.16E-04 Total: 9.llE-03 Stack 701 Bldg. 307 117.79 m3/min l.96 m3/sec Pu-241 3 1, 183,240 3.39E-16 9.58E-l 6 l.76E-15 l.06E-08 l.03E-10 4.23E-04 Tc-99 31, I 83,240 I.IO E-14 3.IOE-14 5.70E-14 3.42E-07 2.02E-05 l.22 E-05 U-234 31 , 183,240 9.81E-15 l.03E-14 2.l lE-14 3.06E-07 4.90E-05 l.96E-Ol U-235 31,183 ,240 3.03E-16 3.19E-16 6.53E-16 9.46E-09 4.38E-03 5.06E-03 Total: 2.02E-0l Stack 702 Bldg. 307 159.78 m3/min 2.66 m3/sec Pu-241 42,358,587 3.03E-16 8.SlE-16 1.56E- 15 I .28E-08 1.24E- l 0 3.78E-04 Tc-99 42,358,587 9.78E-l5 2.75E-14 5.06E-14 4.l4E-07 2.45E-05 l .09E-05 U-234 42,358,587 3.95E-15 8.77E-l5 l.87E-14 l .67E-07 2.68E-05 7.90E-02 U-235 42,358,587 l.22E-16 2.71E-16 5.80E-16 5. l 8E-09 2.40E-03 2.04E-03 Total: 8.15E-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 resuNs.

Printed: 02/09/2021 NFS - EDMS Page 2 of3 Page 8 of 14

Radioactivity in Effluent Air July 1, 2020 to December 31, 2020 Total Activity Error Quantity Quantity Fraction Volume Concentration Estimate LLD Released Released of 1

Location (ml) (µCi/ml) (µCi/ml) (µCi/ml) (Ci) (g) ECV Stack 703 Exhaust Room Air 776.96 m 3/min 12.95 m3/scc Pu-241 205,862,720 8.15 E- 15 2.48E-14 4.58E-14 l .68E-06 I .63E-08 1.02E-02 Th-228 205,862,720 2.06E-16 7.58E-16 l.68 E- 15 4.24E-08 5. I 7E-1 I l.03E-02 Th-230 205,862,720 l. l 9E-t 6 4.36E-16 9.65E-16 2.44E-08 l.21E-06 5.93E-03 Th-232 205,862,720 l.68E-I 6 6.20E-l 6 l.37E-15 3.47E-08 3.IS E-01 4.21E-02 U-234 205,862,720 I .29E-15 4.74E-15 l.05 E- 14 2.65E-07 4.25E-05 2.58E-02 U-235 205,862,720 l.33E-l 6 4.90E-16 1.0SE-15 2.74E-08 l .27 E-02 2.22E-03 U-238 205,862,720 1.62E-16 5.97E-16 l.32E-l 5 3.34E-08 9.97E-02 2.70E-03 Total: 9.92E-02 3 3 Stack 773 Bldg. 440 170.61 m /min 2.84 m /scc Pu-241 45,204,566 3.59E-15 3.41 E-14 6.53E-14 l.62E-07 I .57E-09 4.48E-03 Th-228 45,204,566 O.OOE+OO l.26E-l 5 3.36E-15 O.OOE+OO O.OOE+OO O.OOE+OO Th-230 45,204,566 O.OOE+OO 1.62E-15 4.32E-15 O.OOE+OO O.OOE+OO O.OOE+OO Th-232 45,204,566 O.OOE+OO l.OS E- 15 2.88E-15 O.OOE+OO O.OOE+OO 0.00E+OO U-234 45,204,566 O.OOE+OO 3.32E-l 5 8.88E-15 O.OOE+OO O.OOE+OO O.OOE+OO U-235 45,204,566 O.OOE+OO 5.84E-16 1.56E-15 O.OOE+OO O.OOE+OO O.OOE+OO U-238 45,204,566 O.OOE+OO 1.17E-15 3.12E-15 O.OOE+OO O.OOE+OO O.OOE+OO Total: 4.48E-03 3 3 Stack 774 Bldg. 301 319.87 m /min 5.33 m /sec Th-228 84,762,558 7.36E-l 7 2.02E-16 4.54E-16 6.24E-09 7.62E-12 3.68E-03 Th-230 84,762,558 2.51E-16 6.SSE-16 t.55E-l 5 2.13E-08 l.05E-06 l .25E-02 Th-232 84,762,558 l.49E-16 4.0SE-16 9.17E-16 I .26E-08 I.I 6E-O I 3.72E-02 U-234 84,762,558 6.70E-16 l .84E-15 4.13E-15 5.68E-08 9. II E-06 l.34E-02 U-235 84,762,558 4.36E-l 7 l.20 E- 16 2.69E-16 3.69E-09 1.71 E-03 7.26E-04 U-238 84,762,558 3. 16E-16 8.66E-16 1.94E-15 2.68E-08 7.99E-02 5.26E-03 Total: 7.28E-02 3

Stack 796 Bldg. 100 19.36 m /min 0.32 m3tscc Pu-241 5,129,613 8.71E-16 9.29E-16 I.SSE-15 4.47E-09 4.34E-I I l .09E-03 Tc-99 5, 129,6 13 2.82E-14 3.00E-14 5.01 E- 14 1.44E-07 8.SSE-06 3.13E-05 U-234 5, 129,613 2.79E-16 7.38E-15 l.86E-14 I .43E-09 2.30E-07 5.59E-03 U-235 5,129,613 8.64E-l 8 2.28E-16 5.74E-16 4.43E-ll 2 OSE-05 l.44E-04 Total: 6.8SE-03 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 3 of3 Page 9 of 14

21 G-21-0029 GOV-01-55 ACF-21-0042 Attachment 3 To Letter Dated February 12, 2021 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)

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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 f r

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.

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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 Committed Dose Equivalent (mrem per second half of 2020)

Adrenals 2.3E-04 Urinary Bladder Wall 2.7E-04 Bone Surface 8.7E-03 Brain 2.3E-04 Breasts 2.4E-04 Stomach Wall 4.4E-03 Small Intestine 2.6E-04 Upper Large Intestine Wall 1,3E-03 Lower Large Intestine Wall 3.3E-03 Kidneys 2.9E-03 Liver 7.6E-04 Muscle 2.4E-04 Ovaries 2.4E-04 Pancreas 2.3E-04 Red Bone Marrow 1.1 E-03 Skin 4.7E-04 Spleen 2.3E-04 Testes 2.5E-04 Thymus 2.3E-04 Thyroid 2.3E-03 Gall Bladder Wall 2.3E-04 Heart Wall 2.3E-04 Uterus 2.3E-04 Extra-thoracic 1.5E-02 Lungs 1.8E-02 Total Effective Dose Equivalent 3.4E-03 mrem Location of MEI: 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.

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.... '.,. 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 Distance TEDE Direction 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