ML18243A480
| ML18243A480 | |
| Person / Time | |
|---|---|
| Site: | Erwin |
| Issue date: | 08/24/2018 |
| From: | Freudenberger R Nuclear Fuel Services |
| To: | Office of Nuclear Material Safety and Safeguards |
| References | |
| 21G-18-0098, ACF-18-0188, GOV-01-55 | |
| Download: ML18243A480 (13) | |
Text
\\
Nuclear Fuel Services, Inc.
21 G-18-0098 GOV-01-55 ACF-18-0188 August24,2018 Director Office of Nuclear Material Safety & Safeguards U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001
Reference:
Docket No.70-143; SNM License 124
Subject:
Biannual Effluent Monitoring Report January to June 2018 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 2018. Attachment 2 reports the Radioactivity in Effluent Air for the period January to June 2018. 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 2018.
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 0098) in any correspondence concerning this letter.
Sincerely,.
NUCLEAR FUEL SERVICES, INC.
CJB/pj Richard J. FrelJdenberger Safety & Safeguards Director J:)::/4J
/Jf-1>520 Attachments
- 1) Report of Radioactivity in Effluent Liquid for the Period January to June 2018
- 2) Report of Radioactivity in Effluent Air for the Period January to June 2018
- 3) Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed Off-Site Individual for the Release Period January to June 2018 tJrvf55 Page 1 of13 1205 Banner Hill Rd, Erwin, TN 37650 t: +1.423.743.9141 f: +1.423.743.0140 www.nuclearfuelservices.com People Strong INNOVATION DRIVEN >
Copy:
Mr. Leonard Pitts-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 Ms. Leira Cuadrado Project Manager Fuel Manufacturing Branch Division of Fuel Cycle Safety, Safeguards, and Environmental Review Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Two White Flint North 11555 Rockville' Pike Rockville, MD 20852-2738 Mr. Larry Harris Senior Resident Inspector U. S. Nuclear Regulatory Commission Page 2 of13 21 G-18-0098 GOV-01-55 ACF-18-0188 To Letter Dated August 24, 2018 Report of Radioactivity in Effluent Liquid for the Period January to June 2018 (2 Pages to Follow)
Page3 of13 21 G-18-0098 GOV-01-55 ACF-18-0188
'}
Radioactivity in Effluent Liquid January 1, 2018 to June 30, 2018 Total Activity Error Quantity Quantity Fraction Volume Concentration Estimate LLD Released Released of Location (I)
(µCi/ml)
(µCi/ml)
(µCi/ml)
(Ci)
(g)
ECV 1
Banner Spring Down Pu-238 461,080,000 O.OOE+OO l.OSE-10 2.61E-10 O.OOE+OO O.OOE+OO O.OOE+OO Pu-239/240 461,080,000 O.OOE+OO l.36E-10 3.17E-10 O.OOE+OO O.OOE+OO O.OOE+OO Tc-99 461,080,000 l.77E-11 3.58E-08 6.23Es08 8.l 7E-06 4.84E-04 2.95E-07 Th-228 461,080,000 5.07E-l l l.85E-10 3.69E-10 2.34E-05 2.85E-08 2.54E-04 Th-230 461,080,000 3.61E-ll l.99E-10 3.93E-10 l.67E-05 8.25E-04 3.61E-04 Th-232 461,080,000 l.76E-ll l.29E-10 2.39E-10 8.llE-06 7.44E+Ol 5.86E-04 U-233/234 461,080,000 3.75E-10
- 3. lSE-10 3.77E-10 l.73E-04 2.77E-02 l.25E-03 U-235/236 461,080,000 l.81E-10 2.14E-10 2.66E-10 8.36E-05 3.87E+Ol 6.04E-04 U-238 461,080,000 1.74E-10 2.24E-10 2.SlE-10 8.00E-05 2.39E+02 5.78E-04 Total:
3.63E-03 Sewer Pu-238 29,946,000 7.86E-11 l.40E-IO 2.57E-10 2.35E-06 l.38E-07 3.93E-04 Pu-239/240 29,946,000 6.86E-12 l.04E-10 2.22E-10 2.0SE-07 3.JOE-06 3.43E-05 Tc-99 29,946,000 7.69E-09 3.66E-08 6.34E-08 2.JOE-04 l.36E-02 1.28E-05 Th-228 29,946,000 4.08E-l l l.90E-10 3.46E-10 l.22E-06 l.49E-09 2.04E-05 Th-230 29,946,000 l.37E-10 2.57E-10 4.38E-10 4.IOE-06 2.0JE-04 l.37E-04 Th-232 29,946,000 2.08E-l l l.63E-IO 3.IOE-10 6.22E-07 5.71E+OO 6.92E-05 U-232 29,946,000 5.92E-l l l.39E-IO 2.47E-10 l.77E-06 8.29E-08 9.87E-05 U-233/234 29,946,000 l.23E-08 l.09E-09 2.IIE-10 3.68E-04 5.90Ea02 4.lOE-03 U-235/236 29,946,000 5.84E-IO 2.45E-10 l.49E-10 l.75E-05 8.09E+OO l.95E-04 U-238 29,946,000 l.87E-09 4.29E-10 1.47E-10 5.59E-05 l.67E+02 6.22E-04 Total:
S.68E-03 West Ditch Pu-238 154,049,000 6.71E-ll l.54E-IO 2.60E-10 l.OJE-05 6.04E-07 3.35E-03 Pu-239/240 154,049,000 O.OOE+OO l.32E-10 2.62E-10 O.OOE+OO O.OOE+OO O.OOE+OO Tc-99 154,049,000 O.OOE+OO 3.SIE-08 6.18E-08 O.OOE+OO O.OOE+OO O.OOE+OO Th-228 154,049,000 l21E-11 l.37E-10 2.61E-10 4.95E-06 6.04E-09 l.61E-04 Th-230 154,049,000 l.45E-10 2.0SE-10 3.18E-10 2.24E-05 l.l lE-03 l.45E-03 Th-232 154,049,000 l.07E-10 l.57E-10 2.0SE-10 l.65E-05 l.51E+02 3.56E-03 U-233/234 154,049,000 l.82E-08 l.89E-09 4.72E-10 2.81E-03 4.SOE-01 6.08E-02 U-235/236 154,049,000 l.OSE-09 5.24E-IO 3.SOE-10 l.62E-04 7.SOE+Ol 3.SOE-03 U-238 154,049,000 2.16E-09 6.72E-10 3.60E-10 3.33E-04 9.94E+02 7.20E-03 Total:
8.00E-02 WWTF Am-241 3,762,141 2.93E-ll 8.12E-l 1 l.43E-10 l.lOE-07 3.21E-08 1.46E-03 Cs-137 3,762,141 2.71E-IO 8.43E-10 l.SIE-09 l.02E-06 l.17E-08 2.71E-04 Na-22 3,762,141 l.95E-IO 8.32E-IO l.5 lE-09 7.35E-07 l.18E-IO 3.26E-05 Np-237 3,762,141 9.0lE-11 2.12E-10 4.25E-10 3.39E-07 4.82E-04 4.SlE-03 Pb-212 3,762,141 9.36E-10 3.38E-09 3.IJE-09 3.52E-06 2.SSE-12 4.68E-04 Pu-238 3,762,141 l.62E-l l 9.76E-ll l.93E-10 6.08E-08 3.SSE-09 8.08E-04 ECV: Effluent Concentration Value from 10-CFR-20, Appendix B.
Note: A value of Ro~ was substituted for negative analytical results.
Printed: 08/14/2018 NFS-EDMS Page I of2 Page 4 ofl3
')
Radioactivity in Effluent Liquid January 1, 2018 to June 30, 2018 Total Activity Volume Concentration Lo*cation (I)
(µCi/ml)
WWTF Pu-239/240 3,762,141 2.29E-Il Pu-241 3,762,141 3.67E-09 Ra-224 3,762,141 9.14E-09 Tc-99 3,762,141 l.49E-08 Th-228 3,762,141 l.l lE-11 Th-230 3,762,141 9.ISE-11 Th-231 3,762,141 O.OOE+OO Th-232 3,762,141 2.ISE-11 U-232 3,762,141 1.74E-ll U-233/234 3,762,141 3.48E-08 U-235/236 3,762,141 l.77E-09 U-238 3,762,141 6.68E-10 ECV: Effluent Concentration Value from 10-CFR-20, Appendix B.
Note: A value of *o" was substituted for negative analytical results.
Printed: 08/14/2018 Error Quantity Estimate LLD Released
(µCi/ml)
(µCi/ml)
(Ci) 8.25E-ll l.58E-10 8.60E-08
- l.22E-08 2.IOE-08 l.38E-05 3.38E-09 6.49E-09 3.44E-05 1.26E-07 2.ISE-07 5.62E-05 9.17E-ll 2.16E-10 4.18E-08 1.72E-10 3.02E-10 3.44E-07 4.0SE-08 3.95E-08 O.OOE+OO 9.80E-ll 1.72E-10 8.08E-08 8.59E-l l l.80E-10 6.SSE-08 1.65E-09 l.47E-10 l.31E-04 3.79E-10 l.27E-10 6.65E-06 2.36E-IO l.31E-IO 2.SIE-06 NFS-EDMS Page 5 of13 Quantity Fraction Released of (g) 1 ECV l.38E-06 1.14E-03 l.34E-07 3.67E-03 2.16E-10 4.57E-02 3.33E-03 2.49E-04 5.llE-11 5.56E-05 L70E-05 9.ISE-04 O.OOE+OO O.OOE+OO 7.42E-Ol 7.16E-04 3.06E-09 2.90E-04 2.lOE-02 1.16E-Ol 3.08E+OO 5.89E-03 7.SIE+OO 2.23E-03 Total:
I.SSE-01 Page 2 of2
To Letter Dated August 24, 2018 Report of Radioactivity in Effluent Air for the Period January to June 2018 (3 Pages to Follow)
Page 6 ofl3 21 G-18-0098 GOV-01-55 ACF-18-0188
Total
- Volume, Location (m3)
Main Stack 416 Th-230 280,984,505 U-234 280,984,505 U-235 280,984,505 U-238 280,984,505 Stack 185 Bldg. 131 Pu-241 26,718,117 Tc-99 26,718,117 U-234 26,718,117 U-235 26,718,117 Stack 234 Bldg. 234 Am-241 78,726,040 Pu-238 78,726,040 Pu-239/240 78,726,040 Pu-241 78,726,040 Th-228 78,726,040 Th-230 78,726,040 Th-232 78,726,040 U-234 78,726,040 U-238 78,726,040 Stack 327 Bldg. 330 Pu-241 267,374,122 Tc-99 267,374,122 U-234 267,374,122 U-235 267,374,122 Stack 421 Bldg. 100 Pu-241 9,603,136 Tc-99 9,603,136 U-234 9,603,136 U-235 9,603,136 Stack 424 Bldg. 100 Pu-241 8,579,000 Tc-99 8,579,000 U-234 8,579,000 Radioactivity in Effluent Air January 1, 2018 to June 30, 2018 Activity Error Quantity Concentration Estimate LLD Released
(µCi/ml)
(µCi/ml)
(µCi/ml)
(Ci) 1072.13 m3/min 17.87 m3/sec 5.44E-16 1.34E-16 8.42E-17 l.53E-07 1.24E-13 3.0SE-14 1.92E-14 3.48E-05 7.61E-15 1.87E-15 l.18E-15 2.14E-06 3.SIE-15 9.36E-16 5.90E-16 1.07E-06 101.95 m3/min 1.70 m3tsec O.OOE+OO 8.56E-16 l.76E-15 O.OOE+OO O.OOE+OO 2.77E-14 5.68E-14 O.OOE+OO O.OOE+OO 7.58E-15 2.04E-14 O.OOE+OO O.OOE+OO 2.34E-16 6.32E-16 O.OOE+OO 298.59 m3/min 4.98 m3tsec 2.24E-17 2.57E-l 7 4.72E-17 1.77E-09 2.74E-17 3.ISE-17 5.77E-17 2.16E-09 9.72E-17 1.12E-16 2.0SE-16 7.65E-09 O.OOE+OO 4.14E-15 7.84E-15 O.OOE+OO l.SOE-17 l.72E-l 7 3.ISE-17 1.ISE-09 1.87E-16 2.14E-16 3.94E-16 l.47E-08 2.37E-16 2.72E-16 4.99E-16 l.86E-08 5.llE-16 5.86E-16 1.0SE-15 4.02E-08 l.SOE-16 1.72E-16 3.ISE-16 1.ISE-08 1020.01 m3/min 17.00 m3tsec 2.28E-15 5.46E-16 7.67E-16 6.l lE-07 7.39E-14 1.77E-14 2.48E-14 1.98E-05 1.80E-13 l.SOE-14 9.12E-15 4.81E-05 5.57E-15 4.64E-16 2.82E-16 1.49E-06 36.64 m3/min 0.61 m3/sec l.39E-15 l.33E-15 2.21E-15 1.34E-08 4.SOE-14 4.3 IE-14 7.16E-14 4.32E-07 6.48E-14 2.0SE-14 2.40E-14 6.22E-07 2.00E-15 6.35E-16 7.42E-16 1.92E-08 32.73 m3/min 0.55 m3tsec 4.75E-16 9.84E-16 l.76E-15 4.08E-09 l.54E-14 3.18E-14 5.68E-14 1.32E-07 l.46E-14 l.37E-14 2.04E-14 1.25E-07 Quantity Released (g) 7.56E-06 5.58E-03 9.90E-01 3.19E+OO Total:
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total:
5.ISE-10 1.26E-10 1.23E-07 O.OOE+OO 1.44E-12 7.28E-07 1.71E-01 6.45E-06 3.SIE-02 Total:
5.93E-09 l.17E-03 7.71E-03 6.89E-Ol Total:
I.30E-10 2.56E-05 9.97E-05 8.91E-03 Total:
3.96E-11 7.80E-06 2.0IE-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 ere si.gnificantly 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: 08/14/2018 NFS-EDMS Page 7 of 13 Fraction of ECV 1
2.72E-02 2.48E+OO 1.27E-01 6.34E-02 2.70E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.12E-03 l.37E-03 4.86E-03 O.OOE+OO 7.48E-04 9.35E-03 5.92E-02 1.02E-02 2.49E-03 8.93E-02 2.86E-03 8:21E-05 3.60E+OO 9.28E-02 3.70E+OO l.74E-03 5.00E-05 1.30E+OO 3.34E-02 l.33E+OO 5.94E-04 l.71E-05 2.92E-01 Page I of3
Total Volume Location (ml)
Stack 424 Bldg. 100 U-235 8,579,000 Stack 573 Bldg 306-W Pu-241 20,647,143 Tc-99 20,647,143 U-234 20,647,143 U-235 20,647,143 Stack 600 Bldg. 110 Pu-241 78,049,602 Tc-99 78,049,602 U-234 78,049,602 U-235 78,049,602 Stack 615 Bldg. 306-W Pu-241 10,115,205 Tc-99 10,115,205 U-234 10,115,205 U-235 10,115,205 Stack 646 Bldg. 110 Pu-241 10,768,277 Tc-99 10,768,277 U-234 10,768,277 U-235 10,768,277 Stack 701 Bldg. 307 Pu-241 30,805,733 Tc-99 30,805,733 U-234 30,805,733 U-235 30,805,733 Stack 702 Bldg. 307 Pu-241 44,134,352 Tc-99 44,134,352 U-234 44,134,352 U-235 44,134,352 Radioactivity in* Effluent Air January 1, 2018 to June 30, 2018 Activity Error Quantity Concentration Estimate LLD Released
(µCi/ml)
(µCi/ml)
(µCi/ml)
(Ci) 32.73 m3/min 0.55 m3/sec 4.52E-16 4.24E-16 6.32E-16 3.87E-09 78.87 m3/min 1.31 m3tsec O.OOE+OO 7.93E-16 l.64E-15 O.OOE+OO O.OOE+OO 2.56E-14 5.29E-14 O.OOE+OO O.OOE+OO 6.26E-15 l.93E-14 O.OOE+OO O.OOE+OO l.94E-16 5.96E-16 O.OOE+OO 297.81 m3/min 4.96 m3tsec 6.99E-16 5.83E-16 l.03E-15 5.46E-08 2.26E-14 l.89E-14 3.32E-14 l.77E-06 3.42E-14 9.08E-15 l.27E-14 2.67E-06 1.06E-15 2.81E-16 3.93E-16 8.26E-08 38.60 m3/min 0.64 m3tsec O.OOE+OO 8.63E-16 1.77E-15 O.OOE+OO O.OOE+OO 2.79E-14 5.73E-14 O.OOE+OO 2.71E-15 9.65E-15 2.06E-14 2.74E-08 8.39E-17 2.98E-16 6.37E-16 8.49E-10 41.09 m3/min 0.68 m3/sec O.OOE+OO 8.82E-16 l.80E-15 O.OOE+OO O.OOE+OO 2.85E-14 5.82E-14 O.OOE+OO O.OOE+OO 7.llE-15 2.09E-14 O.OOE+OO O.OOE+OO 2.20E-16 6.47E-16 O.OOE+OO 117.54 m3/min 1.96 m3tsec O.OOE+OO 9.75E-16 2.0lE-15 O.OOE+OO O.OOE+OO
- 3. ISE-14 6.49E-14 O.OOE+OO O.OOE+OO 8.36E-15 2.33E-14 O.OOE+OO O.OOE+OO 2.59E-16 7.22E-16 O.OOE+OO 168.40 m3/min 2.81 m3/sec O.OOE+OO 8.55E-16 l.76E-15 O.OOE+OO O.OOE+OO 2.77E-14 5.68E-14 O.OOE+OO 1.80E-15 8.94E-15 2.04E-14 7.97E-08 5.58E-17 2.76E-16 6.32E-16 2.46E-09 Quantity Released (g) l.79E-03 Total:
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total:
5.30E-10 l.04E-04 4.28E-04 3.82E-02 Total:
O.OOE+OO O.OOE+OO 4.40E-06 3.93E-04 Total:
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total:
O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO Total:
O.OOE+OO O.OOE+OO 1.28E-05 1.14E-03 Total:
ECV: Effluent Concentration Value from 1 O-CFR-20, Appendix B. Fraction of ECV at the stack is provided for reference ollly. 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: 08/14/2018 NFS-EDMS Page 8 of13 Fraction or ECV 1
7.53E-03 3.00E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 8.74E-04 2.SIE-05 6.84E-Ol 1.76E-02 7.03E-Ol O.OOE+OO O.OOE+OO 5.43E-02 l.40E-03 5.57E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.61E-02 9.30E-04 3.70E-02 Page 2 of3
Total Volume Location (m3)
Stack 703 Exhaust Room Air Pu-241 202,577,866 Th-228 202,577,866 Th-230 202,577,866 Th-232 202,577,866 U-234 202,577,866 U-235 202,577,866 U-238 202,577,866 Stack 773 Bldg. 440 Pu-241 47,707,984 Th-228 47,707,984 Th-230 47,707,984 Th-232 47,707,984 U-234 47,707,984 U-235 47,707,984 U-238 47,707,984 Stack 774 Bldg. 301 Th-228 87,971,854 Th-230 87,971,854 Th-232 87,971,854 U-234 87,971,854 U-235 87,971,854 U-238 87,971,854 Stack 796 Bldg. 100 Pu-241 5,313,637 Tc-99 5,313,637 U-234 5,313,637 U-235 5,313,637 1
Radioactivity in Effluent Air January 1, 2018 to June 30, 2018 Activity Error Quantity Concentration Estimate LLD Released
(µCi/ml)
(µCi/ml)
(µCi/ml)
(Ci) 772.96 m3/min 12.88 m 3/sec O.OOE+OO 2.SOE-14 5.2IE-14 O.OOE+OO 3.03E-I7 7.45E-I6 1.85E-I5 6.ISE-09 1.75E-I7 4.29E-I6 1.07E-I5 3.54E-09 2.48E-l 7 6.lOE-16 1.52E-15 5.03E-09 1.90E-16 4.67E-15 l.16E-14 3.85E-08 1.96E-17 4.82E-16 1.20E-15 3.97E-09 2.39E-l 7 5.87E-16 L46E-I5 4.84E-09 181.73 m3/min 3.03 m3tsec 7.67E-16 3.SIE-14 6.85E-14 3.66E-08 O.OOE+OO 1.20E-15 3.47E-15 O.OOE+OO O.OOE+OO l.54E-15 4.46E-15 O.OOE+OO O.OOE+OO l.03E-15 2.97E-15 O.OOE+OO O.OOE+OO 3.16E-15 9.17E-15 O.OOE+OO O.OOE+OO 5.56E-16 1.6IE-15 O.OOE+OO O.OOE+OO l.lIE-15 3.22E-15 O.OOE+OO 335.67 m3/min 5.59 m3/sec O.OOE+OO l.57E-16 4.39E-16 O.OOE+OO O.OOE+OO 5.35E-16 l.SOE-15 O.OOE+OO O.OOE+OO 3.l 7E-16 8.88E-16 O.OOE+OO O.OOE+OO 1.43E-15 4.00E-15 O.OOE+OO O.OOE+OO 9.29E-17 2.60E-16 O.OOE+OO O.OOE+OO 6.73E-16 1.88E-15 O.OOE+OO 20.27 m3/min 0.34 m3tsec 1.70E-16 9.36E-16 1.76E-15 9.02E-10 5.49E-15 3.03E-14 5.68E-14 2.92E-08 O.OOE+OO 6.88E-15 2.04E-14 O.OOE+OO O.OOE+OO 2.13E-16 6.32E-16 O.OOE+OO Quantity Released (g)
O.OOE+OO 7.SIE-12 1.75E-07 4.62E-02 6.l 7E-06 1.84E-03 1.45E-02 Total:
3.SSE-10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total:
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total:
8.75E-12 1.72E-06 O.OOE+OO O.OOE+OO 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 "On was substituted for negative analytical results.
Printed: 08/14/2018 NFS-EDMS Page 9 of13 Fraction of ECV 1
O.OOE+OO 1.52E-03 8.74E-04 6.2IE-03 3.80E-03 3.27E-04 3.99E-04 1.31E-02 9.59E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.59E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.12E-04 6.lOE-06 O.OOE+OO O.OOE+OO 2.18E-04 Page 3 of3 To Letter Dated August 24, 2018 21 G-18-0098 GOV-01-55 ACF-18-0188 Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed Off-Site Individual for the Release Period January to June 2018 (3 Pages to Follow)
Page 10 ofl3
21 G-18-0098 GOV-01-55 ACF-18-0188 Report of Potential Gaseous Effluent Dose to the Maximally Exposed Offsite Individual and on the Maximum Radionuclide Concentrations for the Period January to June 2018 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 2018. 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 five-year average wind speed and direction frequencies as presented in NFS' 1996 Environmental 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 of13
21 G-18-0098 GOV-01-55 ACF-18-0188 Table 1 summarizes the six-month dose to a hypothetical individual at the MEI location, which was determined to be approximately 400 meters North-Northeast from the center of the plant site. The TEDE to the MEI was estimated to be 2.2E-03 mrem for gaseous effluents released during the first half of 2018. The highest organ committed dose equivalent (COE) to the MEI was estimated to be 1.3E-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 E~ra-thoracic Lungs Total Effective Dose Equivalent Location of MEI:
Committed Dose Equivalent (mrem per first half of 2018) 1.4E-04 1.6E-04 5.9E-03 1.4E-04 1.5E-04 2.0E-03 1.7E-04 6.7E-04 1.7E-03
- 2.0E-03 4.9E-04 1.5E-04 1.5E-04 1.4E-04 7.4E-04 3.5E-04 1.4E-04 1.6E-04 1.4E-04 1.1E-03 1.4E-04.
1.4E-04 1.4E-04 1.1E-02 1.3E-02 2.2E-03 mrem 400 meters North-Northeast Page 12 of13
21 G-18-0098 GOV-01-55 ACF-18-0188 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 offractions was estimated to be 4.3E-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 Airborne *concentrations at or Beyond the Site Boundary Maximwn Concentration 10 CFR 20, App. B, Ratio of Maxbnmn Nuclide Concentrati9n Location. *
- Table 2,.Col. 1 Value Concentration to
. (IJCi/inL)
Sector Dist. (m)
(IJCi/inL) 10 CFR 20.Value
- 99Tc 7.8E-18 NNE 400 9.E-10 8.7E-09 228111 2.8E-21 NNE 350 2.E-14 l.4E-07 230Th 2.4E-20 NNE 600 2.E-14 l.2E-06 231Th l.OE-21 NNE 850 9.E-09 l.lE-13 232Th 2.lE-20 NNE 200
- 4.E-15 5.lE-06 234u 2.0E-17 NNE 450 5.E-14 4.lE-04 mu 7.lE-19 NNE 500 6.E-14 1.2£-05 23su 1.3E-19 NNE 700 6.E-14 2.lE-06 238Pti 2.3£-21 NNE 200 2.E-14 l.2E-07 239Pti 8.2£-21 NNE 200 2.E-14 4.lE-07 241Pu 2.6E-19.
NNE 400 8.E-13 3.2£-07 241Am l.9E-21 NNE 200 2.E-14
- 9.SE-08 Swn of Fractions:
4.3E-04 Page 13 of13