ML19247C069
| ML19247C069 | |
| Person / Time | |
|---|---|
| Site: | Erwin (SNM-0124) |
| Issue date: | 08/26/2019 |
| From: | Freudenberger R BWXT Nuclear Fuel Services |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| 21G-19-0107, ACF-19-0183, GOV-01-55 | |
| Download: ML19247C069 (13) | |
Text
Nuclear Fuel Services, Inc.
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 21G-19-0107 GOV-01-55 ACF-19~0183 August 26, 2019
Subject:
Biannual Effluent Monitoring Report January to June 2019
Dear Sir:
In accordance with the re*quirements 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 2019. Attachment 2 reports the Radioactivity in Effluent Air for the period January to June 2019. 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 2019.
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 (21 G 0107) in any correspondence concerning this letter.
CJB/pj Attachments Sincerely, NUCLEAR FUEL SERVICES, INC.
Richard J. Freude.nberger Safety & Safeguar9s Director
- 1) Report of Radioactivity in Effluent Liquid for the-Period January to June 2019
- 2) Report of Radioactivity in Effluent Air for the Period January to June 2019
- 3) Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed Off-Site Individual for the Release Period January to June 2019 1205 Banner Hill Rd, Erwin, TN 37650 Page 1 of 13 t: +1.423.743.9141 f: +1.423.743.0140 www.nuclearfuelservices.com People Strong INNOVATION 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. Kevin Ramsey 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. Robert Williams Chief, Projects Branch 1 U. S. Nuclear Regulatory Commission Region II 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Mr. Larry Harris Senior Resident Inspector U.S. Nuclear Regulatory Commission Page 2 of13 21 G-19-0107 GOV-01-55 ACF-19-0183 To Letter Dated August 26, 2019 Report of Radioactivity in Effluent Liquid for the Period January to June 2019 (2 Pages to Follow)
Page 3 of13 21G-19-0107 GOV-01-55 ACF-19-0183
Radioactivity in Effluent Liquid January 1, 2019 to June 30, 2019 Total Activity Error Quantity Quantity Fraction Volume Concentration Estimate LLD Released Released of Location (1)
(µCi/ml)
(µCi/ml)
(µCi/ml)
(Ci)
(g)
ECV 1
Banner Spring Down Pu-238 546,768,000 O.OOE+OO l.33E-10 3.47E-10 O.OOE+OO O.OOE+OO O.OOE+OO Pu-239/240 546,768,000 O.OOE+OO l.51E-10 3.74E-IO O.OOE+OO 0.00E+OO O.OOE+OO Tc-99 546,768,000 O.OOE+OO 3.55E-08 6.26E-08 O.OOE+OO 0.00E+OO O.OOE+OO Th-228 546,768,000 O.OOE+OO l.51E-IO 3.54E-IO O.OOE+OO O.OOE+OO O.OOE+OO Th-230 546,768,000 3.IOE-11 l.62E-10 3.43E-IO 1.70E-05 8.40E-04 3.IOE-04 Th-232 546,768,000 4.23E-ll l.26E-IO 2.32E-10 2.3 IE-05 2.12E+02 l.41E-03 U-233/234 546,768,000 4.84E-10 2.97E-10 3.29E-IO 2.65E-04 4.24E-02 1.61E-03 U-235/236 546,768,000 6.05E-l l l.51E-10 2.35E-IO 3.JIE-05
!.53E+Ol 2.02E-04 U-238 546,768,000 l.33E-IO l.88E-IO 2.83E-IO 7.28E-05 2.17E+02 4.44E-04 Total:
3.98E-03 Sewer Pu-238 31,394,000 O.OOE+OO l.49E-10 3.26E-IO O.OOE+OO O.OOE+OO O.OOE+OO Pu-239/240 31,394,000 O.OOE+OO l.16E-IO 2.74E-IO O.OOE+OO O.OOE+OO O.OOE+OO Tc-99 31,394,000 O.OOE+OO 4.04E-08 7.02E-08 O.OOE+OO O.OOE+OO O.OOE+OO Th-228 31,394,000 2.24E-l l l.99E-IO 4.19E-IO 7.02E-07 8.57E-IO 1.12E-05 Th-230 31,394,000 8.SOE-11 2.0SE-10 3.71E-IO 2.76E-06
!.37E-04 8.SOE-05 Th-232 31,394,000 3.27E-ll l.57E-IO 3.04E-IO l.OJE-06 9.43E+OO l.09E-04 U-232 31,394,000 5.18E-l l 1.46E-10 2.72E-10 l.63E-06 7.60E-08 8.63E-05 U-233/234 31,394,000 l.73E-08 l.22E-09 l.79E-IO 5.44E-04 8.71E-02 5.77E-03 U-235/236 31,394,000 9.76E-10 2.98E-10 1.52E-IO 3.06E-05 1.42E+Ol 3.25E-04 U-238 31,394,000 2.35E-09 4.53E-10 l.56E-IO 7.37E-05 2.20E+02 7.83E-04 Total:
7.lSE-03 West Ditch Pu-238 181,889,000 5.23E-12 l.28E-10 2.89E-10 9.SIE-07 5.56E-08 2.61E-04 Pu-239/240 181,889,000 6.60E-12 l.34E-10 3.00E-10 l.20E-06 l.93E-05 3.JOE-04 Tc-99 181,889,000 O.OOE+OO 3.61E-08 6.37E-08 O.OOE+OO O.OOE+OO O.OOE+OO Th-228 181,889,000 4.73E-12 1.64E-10 3.52E-IO 8.60E-07 l.05E-09 2.36E-05 Th-230 181,889,000 2.42E-ll L72E-IO 3.66E-10 4.40E-06 2.ISE-04 2.42E-04 Th-232 181,889,000 4.98E-l l l.27E-IO 2.22E-IO 9.06E-06 8.31E+Ol l.66E-03 U-233/234 181,889,000 l.76E-08 l.77E-09 3.97E-IO 3.19E-03 5.12E-01 5.85E-02 U-235/236 181,889,000 8.SIE-10 4.47E-IO 2.33E-IO l.55E-04 7.16E+Ol 2.84E-03 U-238 181,889,000 2.24E-09 6.43E-IO 2.84E-IO 4.07E-04 l.22E+03 7.46E-03 Total:
7.14E-02 WWTF Am-241 4,149,746 l.52E-ll 7.07E-ll l.27E-10 6.32E-08 1.84E-08 7.61E-04 Cs-137 4,149,746 7.37E-IO l.09E-09 l.55E-09 3.06E-06 3.52E-08 7.37E-04 Na-22 4,149,746 O.OOE+OO 8.24E-10 l.47E-09 O.OOE+OO O.OOE+OO O.OOE+OO Np-237 4,149,746 O.OOE+OO l.41E-IO 3.28E-10 O.OOE+OO O.OOE+OO O.OOE+OO Pb-212 4,149,746 O.OOE+OO 3.0SE-09 2.85E-09 O.OOE+OO O.OOE+OO O.OOE+OO Pu-238 4,149,746 3.12E-l l 8.36E-ll 1.54E-10 l.JOE-07 7.58E-09 1.56E-03 ECV: Effluent Concentration Value from 10-CFR-20, Appendix B.
Note: A value of Qon was substituted for negative analytical results.
Printed: 08/19/2019 NFS-EDMS Page I of2 Page 4 of13
Radioactivity in Effluent Liquid January 1, 2019 to June 309 2019 Total Activity Volume Concentration Location (I)
(µCi/ml)
WWTF Pu-239/240 4,149,746 O.OOE+OO Pu-241 4,149,746 O.OOE+OO Ra-224 4,149,746 l.3IE-08 Tc-99 4,149,746 6.62E-09 Th-228 4,149,746 O.OOE+OO Th-230 4,149,746 7.15E-1I Th-231 4,149,746 5.3 IE-09 Th-232 4,149,746 O.OOE+OO U-232 4,149,746 O.OOE+OO U-233/234 4,149,746 3.37E-08 U-235/236 4,149,746 I.70E-09 U-238 4,149,746 4.77E-10 ECV: Effluent Concentration Value from 10*CFR-20, Appendix B.
Note: A value of *o* was substituted for negative analytical results.
Printed: 08/19/2019 Error Quantity Estimate LLD Released
(µCi/ml)
(µCi/ml)
(Ci) 6.74E-1I l.57E-I0 O.OOE+OO 9.SIE-09 l.65E-08 O.OOE+OO 8.72E-09 l.6IE-08 5.45E-05 8.SOE-08 l.47E-07 2.75E-05 l.49E-10 3.3IE-10 O.OOE+OO l.87E-I0 3.27E-I0 2.97E-07 4.07E-08 3.99E~08 2.20E-05 l.l 7E-I0 2.53E-I0 O.OOE+OO l.03E-I0 2.32E-I0 O.OOE+OO l.65E-09 l.75E-I0 l.40E-04 3.66E-I0 I.SOE-IO 7.0SE-06 l.94E-10 l.57E-10 l.98E-06 NFS-EDMS Page 5 of13 Quantity Fraction Released of (g)
ECV 1
0.00E+OO O.OOE+OO 0.00E+OO O.OOE+OO 3.43E-I0 6.56E-02 1.62E-03 1.IOE-04 0.00E+OO O.OOE+OO l.47E-05 7.15E-04 4.14E-ll I.06E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.24E-02 1.12E-0I 3.26E+OO 5.66E-03 5.91E+OO 1.59E-03 Total:
1.89E-Ol Page 2 of2 To Letter Dated August 26, 2019 Report of Radioactivity in Effluent Air for the Period January to June 2019 (3 Pages to Follow)
Page 6 ofl3 21G-19-0107 GOV-01-55 ACF-19-0183
Total Volume Location (ma)
Main Stack 416 Th-230 272,250,800 U-234 272,250,800 U-235 272,250,800 U-238 272,250,800 Stack 185 Bldg. 131 Pu-241 28,104,061 Tc-99 28,104,061 U-234 28,104,061 U-235 28,104,061 Stack 234 Bldg. 234 Am-241 74,535,748 Pu-238 74,535,748 Pu-239/240 74,535,748 Pu-241 74,535,748 Th-228 74,535,748 Th-230 74,535,748 Th-232 74,535,748 U-234 74,535,748 U-238 74,535,748 Stack 327 Bldg. 330 Pu-241 267,024,629 Tc-99 267,024,629 U-234 267,024,629 U-235 267,024,629 Stack 421 Bldg. 100 Pu-241 8,554,371 Tc-99 8,554,371 U-234 8,554,371 U-235 8,554,371 Stack 424 Bldg. 100 Pu-241 8,612,762 Tc-99 8,612,762 U-234 8,612,762 Radioactivity in Effluent Air January 1, 2019 to June 30, 2019 Activity Error Quantity Concentration Estimate LLD Released
(µCi/ml)
(µCi/ml)
(µCi/ml)
(Ci) 1056.22 m3/min 17.60 m3/sec 4.77E-16 J.27E-16 8.83E-l 7 l.30E-07 l.09E-13 2.90E-14 2.0IE-14 2.96E-05 6.68E-15 l.78E-15 l.24E-15 l.82E-06 3.34E-15 8.91E-16 6.18E-16 9.09E-07 109.03 m3/min 1.82 m3tsec O.OOE+OO 8.73E-16 l.78E-15 O.OOE+OO O.OOE+OO 2.82E-14 5.74E-14 O.OOE+OO O.OOE+OO 7.16E-15 2.16E-14 O.OOE+OO O.OOE+OO 2.21E-16 6.67E-16 O.OOE+OO 293.87 m3/min 4.90 m 3/sec l.18E-16 3.14E-17 5.04E-17 8.77E-09 l.44E-16 3.83E-l 7 6.16E-17 l.07E-08 5.!0E-16 l.36E-16 2.18E-16 3.80E-08 O.OOE+OO 4.34E-15 8.!SE-15 O.OOE+OO 7.84E-l 7 2.09E-l 7 3.36E-17 5.85E-09 9.SOE-16 2.61E-16 4.20E-16 7.31E-08 1.24E-15 3.31E-16 5.32E-16 9.26E-08 2.68E-15 7.15E-16 l.15E-15 2.00E-07 7.84E-16 2.09E-16 3.36E-16 5.85E-08 1035.87 m3/min 17.26 m3tsec l.22E-15 4.SSE-16 7.73E-16 3.25E-07 3.93E-14 l.58E-14 2.SOE-14 l.05E-05 8.83E-14 l.14E-14 9.44E-15 2.36E-05 2.73E-15 3.52E-16 2.92E-16 7.29E-07 33.19 m3/min 0.55 m3tsec 2.23E-I5 l.48E-15 2.27E-15 l.91E-08 7.22E-14 4.78E-14 7.35E-14 6.18E-07 l.29E-13 2.86E-14 2.61E-14 l.l IE-06 4.00E-15 8.84E-16 8.06E-16 3.42E-08 33.41 m3/min 0.56 m3tsec 3.72E-16 9.93E-16 l.79E-15 3.20E-09 l.20E-14 3.21E-14 5.79E-14 1.04E-07 8.66E-15 l.25E-14 2.18E~l4 7.46E-08 Quantity Released (g) 6.43E-06 4.75E-03 8.42E-Ol 2.71E+OO Total:
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total:
2.56E-09 6.27E-IO 6.l IE-07 O.OOE+OO 7.14E-12 3.62E-06 8.49E-Ol 3.20E-05 l,75E-Ol Total:
3.l 5E-09 6.21E-04 3.78E-03 3.38E-Ol Total:
l.86E-10 3.66E-05 l.77E-04 l.58E-02 Total:
3.l !E-11 6.13E-06 l.20E-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 exits the site.
Note: A value of *o" was substituted for negative analytical results.
Printed: 08/19/2019 NFS-EDMS Page 7 of 13 Fraction of ECV 1
2.39E-02 2.18E+OO I.IIE-01 5.57E-02 2.37E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.88E-03 7.19E-03 2.55E-02 O.OOE+OO 3.92E-03 4.90E-02 3.!0E-01 5.36E-02 l.3 !E-02 4.69E-Ol l.52E-03 4.37E-05 l.77E+OO 4.SSE-02 I.8IE+OO 2.79E-03 8.02E-05 2.58E+OO 6.66E-02 2.65E+OO 4.65E-04 l.34E-05 l.73E-Ol Page I of3
Total Volume Location (m3)
Stack 424 Bldg. 100 U-235 8,612,762 Stack 573 Bldg 306-W Pu-241 20,860,403 Tc-99 20,860,403 U-234 20,860,403 U-235 20,860,403 Stack 600 Bldg. 110 Pu-241 79,653,455 Tc-99 79,653,455 U-234 79,653,455 U-235 79,653,455 Stack 615 Bldg. 306-W Pu-241 12,546,082 Tc-99 12,546,082 U-234 12,546,082 U-235 12,546,082 Stack 646 Bldg. 110 Pu-241 9,955,770 Tc-99 9,955,770 U-234 9,955,770 U-235 9,955,770 Stack 701 Bldg. 307 Pu-241 31,757,737 Tc-99 31,757,737 U-234 31,757,737 U-235 31,757,737 Stack 702 Bldg. 307 Pu-241 41,567,527 Tc-99 41,567,527 U-234 41,567,527 U-235 41,567,527 Radioactivity in Effluent Ai.r January 1, 2019 to June 30, 2019 Activity Error Quantity Concentration Estimate LLD Released
(µCi/ml)
(µCi/ml)
(µCi/ml)
(Ci) 33.41 m3/min 0.56 m3/sec 2.68E-16 3.86E-16 6.73E-16 2.31E-09 80.93 m3/min 1.35 m3tsec O.OOE+OO 8.08E-16 l.66E-15 O.OOE+OO O.OOE+OO 2.61E-14 5.36E-14 O.OOE+OO O.OOE+OO 7.09E-15 2.02E-14 O.OOE+OO O.OOE+OO 2.19E-16 6.25E-16 O.OOE+OO 309.02 m3/min 5.15 m3tsec 4.80E-16 5.79E-16 l.04E-15 3.82E-08 l.55E-14 l.87E-14 3.37E-14 l.24E-06 2.42E-14 7.86E-15 l.32E-14 l.93E-06 7.48E-16 2.43E-16 4.07E-16 5.96E-08 48.67 m3/min 0.81 m3/sec O.OOE+OO 8.48E-16 l.78E-15 O.OOE+OO O.OOE+OO 2.74E-14 5.75E-14 O.OOE+OO O.OOE+OO 6.49E-15 2.16E-14 O.OOE+OO O.OOE+OO 2.0IE-16 6.68E-16 O.OOE+OO 38.62 m3/min 0.64 m3tsec O.OOE+OO 8.45E-16 l.78E-15 O.OOE+OO O.OOE+OO 2.73E-14 5.75E-14 O.OOE+OO O.OOE+OO 6.64E-15 2.16E-14 O.OOE+OO O.OOE+OO 2.0SE-16 6.68E-16 O.OOE+OO 123.21 m3/min 2.05 m3/sec O.OOE+OO 9.6IE-16 2.02E-15 O.OOE+OO O.OOE+OO 3.l !E-14 6.53E-14 O.OOE+OO O.OOE+OO 7.48E-15 2.45E-14 O.OOE+OO O.OOE+OO 2.3IE-16 7.58E-16 O.OOE+OO 161.26 m3/min 2.69 m3tsec O.OOE+OO 8.29E-16 l.78E-15 O.OOE+OO O.OOE+OO 2.68E-14 5.74E-14 O.OOE+OO O.OOE+OO 7.21E-15 2.16E-14 O.OOE+OO O.OOE+OO 2.23E-16 6.68E-16 O.OOE+OO Quantity Released (g) l.07E-03 Total:
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total:
3.7IE-10 7.3 IE-05 3.09E-04 2.76E-02 Total:
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 Total:
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 Total:
ECV: Effluent Concentration Value from 1 O-CFR-20, Appendix B. Fraction of ECV at the stack is provided for reference only. concentrations at off-site lo cations are slgnificantry less than those reported here (at stack) due to the atmospheric dispersion that occurs before the effluent exits the site.
Note: A value of no* was substituted for negative analytical results.
Printed: 08/19/2019 NFS-EDMS Page 8 of 13 Fraction of ECV 1
4.47E-03 1.78E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.99E-04 l.72E-05 4.84E-01 l.25E-02 4.97E-01 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 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO Page 2 of3
Total Volume Location (m3)
Stack 703 Exhaust Room Air Pu-241 210,349,903 Th-228 210,349,903 Th-230 210,349,903 Th-232 210,349,903 U-234 210,349,903 U-235 210,349,903 U-238 210,349,903 Stack 773 Bldg. 440 Pu-241 46,914,845 Th-228 46,914,845 Th-230 46,914,845 Th-232 46,914,845 U-234 46,914,845 U-235 46,914,845 U-238 46,914,845 Stack 774 Bldg. 301 Th-228 82,380,001 Th-230 82,380,001 Th-232 82,380,001 U-234 82,380,001 U-235 82,380,001 U-238 82,380,001 Stack 796 Bldg. 100 Pu-241 4,817,308 Tc-99 4,817,308 U-234 4,817,308 U-235 4,817,308 Radioactivity in Effluent Afr January 1, 2019 to June 30, 2019 Activity Error Quantity Concentration Estimate LLD Released
(µCi/ml)
(µCi/ml)
(µCi/ml)
(Ci) 816.07 m3/min 13.60 m 31sec O.OOE+OO 2.51E-14 5.30E-14 O.OOE+OO O.OOE+OO 7.89E-16 l.97E-15 O.OOE+OO O.OOE+OO 4.54E-16 l.14E-15 O.OOE+OO O.OOE+OO 6.45E-16 l.61E-15 O.OOE+OO O.OOE+OO 4.94E-15 l.24E-14 O.OOE+OO O.OOE+OO 5.I OE-16 1.28E-15 O.OOE+OO O.OOE+OO 6.21E-16 l.SSE-15 O.OOE+OO 182.40 m3/min 3.04 m3/sec O.OOE+OO 3.45E-14 6.91E-I4 O.OOE+OO O.OOE+OO 1.26E-15 3.64E-I5 O.OOE+OO O.OOE+OO 1.62E-15 4.69E-15 O.OOE+OO O.OOE+OO 1.0SE-15 3.12E-15 O.OOE+OO O.OOE+OO 3.33E-15 9.63E-15 O.OOE+OO O.OOE+OO 5.86E-16 l.69E-15 O.OOE+OO O.OOE+OO 1.17E-15 3.38E-15 O.OOE+OO 319.70 m3/min 5.33 m3/sec O.OOE+OO 1.63E-16 4.54E-16 O.OOE+OO O.OOE+OO 5.56E-16 l.55E-15 O.OOE+OO O.OOE+OO 3.30E-16 9.IBE-16 O.OOE+OO O.OOE+OO l.49E-15 4.13E-15 O.OOE+OO O.OOE+OO 9.66E-I7 2.69E-16 O.OOE+OO O.OOE+OO 7.00E-16 l.95E-15 O.OOE+OO 18.69 m3/min 0.31 m3/sec l.04E-16 9.40E-16 l.78E-15 5.0IE-10 3.36E-15 3.04E-14 5.74E-14 l.62E-08 O.OOE+OO 7.32E-15 2.16E-14 O.OOE+OO O.OOE+OO 2.26E-16 6.67E-16 O.OOE+OO Quantity Released (g)
O.OOE+OO 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 O.OOE+OO Total:
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total:
4.86E-I2 9.58E-07 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 slgnJficantly 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: 08/19/2019 NFS-EDMS Page 9 of 13 Fraction of 1
ECV 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 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 l.30E-04 3.73E-06 O.OOE+OO O.OOE+OO l.34E-04 Page 3 of3 To Letter Dated August 26, 2019 21 G-19-0107 GOV-01-55 ACF-19-0183 Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed Off-Site Individual for the Release Period January to June 2019 (3 Pages to Follow)
Page 10 of13
~-
21G-19-0107 GOV-01-55 ACF-19-0183 Report of Potential Gaseous Effluent Dose to the Maximally Exposed Offsite Individual and on the Maximum Radionuclide Concentrations for the Period:
January to June 2019 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 2019. Based on effluent types and ~tack 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.
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21G-19-0107 GOV-01-55 ACF-19-0183 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 1.4E-03 mrem for gaseous effluents released during the first half of 2019. The highest organ committed dose equivalent (COE) to the MEI was estimated to be 7.7E-03 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 first half of 2019) 9.6E-05 1.1 E-04 4.5E-03 9.7E-05 1.0E-04 1.2E-03 1.1 E-04 4.1E-04 1.0E-03 1.3E-03 3.BE-04 1.0E-04 1.1 E-04 9.6E-05 5.7E-04 3.0E-04 9.7E-05 1.2E-04 9.7E-05 6.3E-04 9.6E-05 9.7E-05 9.6E-05 6.6E-03 7.7E-03 1.4E-03 mrem 400 meters North-Northeast Page 12 ofl3
21G-19-0107 GOV-01-55 ACF-19-0183 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 2.BE-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 Maximurµ Concentration 10 CFR20,App.B; Ratio ofMaxiJnum Nuclide.
.Concentration Location Table 2, Col. 1 Value Concentration to
. (µCi/mL)
- sector J)ist. (m)
(IJCi/mL) 10 CFR20 Value 99Tc 4.7E-I8 NNE 400 9.E-10 5.2E-09 228Tb 6.4E-2I NNE 200 2.E-14 3.2E-07 230Th 7.9E-20 NNE 200 2.E-14 4.0E-06 232Th l.OE-19 NNE 200 4.E-15 2.SE-05 234u l.2E-I7 NNE 450 5.E-14 2.4E-04 23su 4.5E-I9 NNE 500 6.E-14 7.4E-06 23su 1.2E-I9 NNE 650 6.E-14 2.IE-06 238Pu l.2E-20 NNE 200 2.E-14 5.8E-07 239Pu 4.IE-20 NNE 200 2.E-14 2.IE-06 241Pu 1.4E-I9 NNE 350 8.E-13 l.8E-07 241Am 9.5E-2I NNE 200 2.E-14 4.8E-07 Sum of Fractions:
2.8E-04 Page 13 ofl3