ML23244A028
| ML23244A028 | |
| Person / Time | |
|---|---|
| Site: | Erwin |
| Issue date: | 08/17/2023 |
| From: | Knowles T BWXT Nuclear Fuel Services |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| 21G-23-0116, GOV-01-55, ACF-23-0229 | |
| Download: ML23244A028 (1) | |
Text
i Nuclear Fuel Services, Inc.
I' I'
I I : :
Certified Mail Return Receipt Requested 21G-23-0116 GOV-01-55 ACF-23-0229 August 17, 2023 Director Office of Nuclear Material Safety & Safeguards U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Reference:
Docket No.70-143; SNM License 124
Subject:
Biannual Effluent Monitoring Report January to June 2023
Dear Director:
In accordance with the requirements* set forth in 10 CFR Part 70.59, Nuclear Fuel Services, Inc. (NFS), submits the attached reports. Attachment 1 reports the Radioactivity in Effluent Liquid for the period January to June 2023. Attachment 2 reports the Radioactivity in Effluent Air for the period January to June 2023. 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 2023.
If you or your staff have any questions, require additional inf6rrnati~n, or wish to discuss this, please contact me or Mr. R. Jason Faddis, Deputy Environmental Protection and Industrial Safety Section Manager, at (423) 735-5438. Please reference our unique document identification number (21 G-23-0116} in any _correspondence concerning this letter.
Sincerely, NUCLEAR FUEL *sERVICES, INC.
reJJ-i f\\)"fSSZiJ CJB/las Attachments
- J~;f'~.
Tim Knowles.
- Safety & Safeig uards Director
- 1) Report of Radioactivity in Effluent Liquid for the Period*January to June 2023
- 2) Report of Radioactivity in Effluent Air for the Period January to June 2023
- 3) Report of Gaseous Effluent Dose and Activity ConGentrati9ns for the Maximally Exposed Off-Site Individual for the Release Period January to June 2023
/V/l-f S-5 1205 Banner Hill Rd, Erwin, TN 37650 Page 1 of 13 p e D p l e s t r D n g t: +1.423.743.9141 f: +1.423.743.0140 www.nuclearfuelservices.com
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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 Senior Project Manager Division of Fuel Management Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Two White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Dr. Robert Williams Chief, Projects Branch 1 U. S. Nuclear Regulatory Commission Region II 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Mr. Larry Harris Senior Resident Inspector U.S. Nuclear Regulatory Commission Page 2 of 13 21G-23-0116 GOV-01-55 ACF-23-0229 To Letter Dated August 17, 2023 Report of Radioactivity in Effluent Liquid for the Period January to June 2023 (2 Pages to Follow)
Page 3 of 13 21G-23-0116 GOV-01-55 ACF-23-0229
I j:
21 G-23-0116 GOV-01-55 ACF-23-0229 Radioactivity in Effluent Liquid January 1, 2023 to June 30, 2023 Total Activity Error Quantity Quantity Fraction Volume Concentration Estimate LLD Released Released of Location (I)
(11Ci/ml)
(11Ci/ml)
(11Ci/ml)
(Ci)
(g)
ECV 1
Banner Spring Down Pu-238 446,416,000 2.198-11 1.098-10 2.098-10 9;808-06, 5.738-07 1.108-03 Pu-239/240 446,416,000 1.958-11 1.18E-10 2.398-10 8.7IE-06 l.40E-04 9.76E-04 Tc-99 446,416,000 0.008+00 3.598-08 6.278-08 O.OOE+OO 0.008+00 0.008+00 Th-228 446,416,000 1.168-11 l.35E-10 2.95E-10 5.178-06 6.31E-09 S.79E-OS Th-230 446,416,000 2.228-10 2.05E-10 2.86E-10 9.928-05 4.91E-03 2.228-03 Th-232 446,416,000 2.29E-11 9.408-11 1.79E-IO 1.028-05, 9.38E+Ol 7.638-04 U-233/234 446,416,000 1.208-09 3.73E-IO 2.978-10 5.33E-04 8.558-02 3.988-03 U-235/236 446,416,000 9.78E-ll 1.728-10 2.548-10 4.378-05 2.028+01 3.268-04 U-238 446,416,000 l.15E-IO l.66E-IO 2.43E-IO 5.i3E-05 LS3E+02.
3.83E-04 Total:
9.81E-03 Sewer Pu-238 16,925,000 6.608-11 l.2S8-10 2.36E-l0 1.128-06
<i.53E-08 3.308-04 Pu-239/240 16,925,000 O.OOE+OO 1.098-10
,2.648-10 0,008+00 O.OOE+OO 0.008+o0 Tc-99 16,925,000 1.09E-08 3.868-08 6.648-08 1.848-04 1.09E-02 1.818-0S Th-228 16,925,000 S.97E-11 1.91E-10 3.698-10.
1.018-06 1.238-09 2.99E-OS Th-230 16,925,000 9.92E-II 2.12E-IO 3.75E-10 1.68E-06 8.3IE-05 9.92E-05 Th-232 16,925,000 3.86E-11 *.
l.3SE-IO 2.36E-10 6.54E-07 6.008+00 1.29E-04 U-232 16,925,000 3.29E-II l.44E-10 2.888-10 5.578-07 2.608-08 S.48E-05 U-233/234 16,925,000 1.43E-08 l.lIE-09 1.528-10 2.41E-04 3.878-02 4.75E-03 U-235/236 16,925,000 6.71E-10 2.46E-10 1.20E-10 1.148-05, S.26E+OO 2.248-04 U-238 16,925,000 l.49E-09 3:588-10 l.30E-IO 2.52E-05 '
7.53E+OI 4.97E-04 Total:
6.13E-03 West Ditch Pu-238 159,000,000 5.l5E-ll 8.13E-11 1.448-10 8.l9E-06 4.798-07 2.58E-03 Pu-239/240 159,000,000 l.75E-ll 9.56E-ll 1.86E-IO 2.788-06 4.478-05 8.748-04 Tc-99 159,000,000 2.998-09 3.678-08 6.34E-08 4.75E-04 2.81E-02 4.98E-05 Th-228 159,000,000 7.528-11 1.758-10 2.998-10 1.208-05 1.468-08 3.76E-04 Th-230 159,000,000 2.168-10 2.37E-IO 3.388-10 3.448-05 1.70E-03 2.168-03 Th-232 159,000,000 I.ISE-11 l.02E-10 2.138-10 l.83E-06 I.68E+OI 3.838-04 U-233/234 159,000,000 1.848-08 1.6IE-09 3.098-10 2.938-03 4.708-01 6.158-02 U-235/236 159,000,000 7.52E-IO 3.76E-IO
!.97E-10 1.208-04 5.54E+Ol 2.518-03 U-238 159,000,000 l.37E-09 4.49E-10 2.25E-10 2.188-04 6.508+02 4.568-03 Total:
7.S0E-02 WWTF Am-241 3,775,331 1.30E-ll 7.99E-1 I l.67E-IO 4.89E-08:
1.438-08 6.48E-04 Cs-137 3,775,331 O.OOE+OO l.59E-09 1.54E-09 O.OOE+OO O.OOE+OO O.OOE+OO Na-22 3,775,331 2.12E-12 7.72E-10 l.36E-09 7.99E-09.
1.28E-12 3.53E-07 Np-237 3,775,331 9.288-11 2.63E-IO 5.22E-10 3.508-07 4.988-04 4.64E-Q3 Pb-212 3,775,331 2.02E-09 2.86E-09 2.90E-09 7.64E-06:
5.52E-12 1.0IE-03 Pu-238 3,775,331 2.99E-11 9.108-11 1.728-10 1.138-07 6.6IE-09 1.508-03 ECV: Effluenl ConcenlraUon Value from 10-CFR-20, Appendix B.
Nole: A value ~r *o* was subsllluled for negaUve analytical results..
Printed: 08/07/2023 NFS-EDMS Page I of2 Page 4 of 13
Radioactivity in Effluent Liquid January 1, 2023 to June 30, 2023 Total Activity Volume Concentration Location (I)
(µCi/ml)
WWTF Pu-239/240 3,775,331 2.46E-ll Pu-241 3,775,331 O.OOE+OO Ra-224 3,775,331 1.38E-08 Tc-99 3,775,331 O.OOE+OO Th-228 3,775,331 4.20E-12 Th-230 3,775,331 l.66E-10 Th-231 3,775,331 O.OOE+OO Th-232 3,775,331 5.87E-11 U-232 3,775,331 O.OOE+OO U-233/234 3,775,331 6.78E-09 U-235/236 3,775,331 3.62E-10 U-238 3,775,331 8.00E-11 ECV; Effluent Concentration VBlue rrom 10..cFR-20, Appendix B~
Nole: A value of *o* was substituted for negaUve analytical results.
Printed: 08/07/2023 Error Quantity Estimate LLD Released
(µCi/ml)
(µCi/ml)
(Ci) 9.SIE-11 1.SIE-10 9.28E-08 1.26E-08 2.17E-08 O.OOE+OO 7.84E-09 1.39E-08 5.21E-05 4.67E-08 8.13E-08 O.OOE+OO l.43E-10 3.12E-10 l.SSE-08 2.17E-10 3.32E-10 6.25E-07 4.12E-08 3.83E-08 O.OOE+OO l.47E-IO 2.46E-10 2.22E-07 l.94E-10 4.28E-10 O.OOE+OO 7.lOE-10 l.29E-10 2.56E-05 I.70E-10 l.02E-10 l.37E-06 8.98E-11 I.OSE-10 3.02E-07 NFS-EDMS Page 5 of 13 21 G-23-0116 GOV-01-55 ACF-23-0229 Quantity Fraction Released of (g)
ECV 1
l.49E-06 l.23E-03 O.OOE+OO O.OOE+OO 3.28E-10 6.90E-02 O.OOE+OO O.OOE+OO l.93E-ll 2.IOE-05 3.09E-05 l.66E-03 O.OOE+OO 0.00E+OO 2.03E+OO 1.96E-03 O.OOE+OO O.OOE+OO 4.lOE-03 2.26E-02 6.32E-01 l.2IE-03 9.0IE-01 2.67E-04 Total:
1.06E-01 Page2 of2 To Letter Dated August 17, 2023 Report of Radioactivity in Effluent Air for the Period January to June_2023 (3 Pages to Follow)
Page 6 of 13 21 G-23-0116 GOV-01-55 ACF-23-0229
Total Volume Location (m3)
Main Stack 416 Th-228 276,561,993 Th-230 276,561,993 Th-232 276,561,993 U-234 276,561,993 U-235 276,561,993 U-238 276,561,993 Stack 234 Bldg. 234 Am-241 77,449,539 Pu-238 77,449,539 Pu-239/240 77,449,539 Pu-241 77,449,539 Th-228 77,449,539 Th-230 77,449,539 Th-232 77,449,539 U-234 77,449,539 U-238 77,449,539 Stack 327 Bldg. 330 Pu-241 257,963,368 Tc-99 257,963,368 U-234 257,963,368 U-235 257,963,368 Stack42l Bldg.100 Pu-241 8,794,217 Tc-99 8,794,217 U-234 8,794,217 U-235 8,794,217 Stack 424 Bldg. 100 Pu-241 8,252,463 Tc-99 8,252,463 U-234 8,252,463 U-235 8,252,463 Stack 573 Bldg 306-W Pu-241 28,919,138 Tc-99 28,919,138 1
Radioactivity in Effluent Aiir January 1, 2023 to June 30, 2023 Activity Error Quantity Concentration Estimate LLD Released
{µCi/ml)
(µCi/ml)
(µCi/ml)
(Ci) 1055.26 m3/min 17.59 m 3/sec 8.09E-16 l.76E-16 8.45E-17 2.24E-07 8.09E-16 l.76E-16 8.45E-17 2.24E-07 6.07E-16 1.32E-16 6.33E-17 1.68E-07 1.91E-13 4.ISE-14 1.99E-14 5.27E-05 7.28E-15 l.58E-15 7.60E-16 2.0IE-06 2.02E-15 4.40E-16 2.IIE-16 5.59E-07 295.47 m3/min 4.92 m3/sec 5.33E-17 3.08E-17 4.14E-17 4.13E-09 6.SIE-17 3.77E-l 7 5.06E-17 5.04E-09 2.31E-16 1.34E-16 1.79E-16 1.79E-08 1.04E-14 3.60E-15 4.45E-15 8.0SE-07 3.SSE-17 2.06E-l 7 2.76E-17 2.75E-09 4.44E-16 2.57E-16 3.45E-16 3.44E-08 5.63E-16 3.25E-16 4.37E-16 4.36E-08 1.21E-15 7.02E-16 9.43E-16 9.40E-08 3.SSE-16 2.06E-16 2.76E-16 2.75E-08 984.42 m3/min 16.41 m3/sec 2.93E-15 4.25E-16 4.88E-16 7.57E-07 9.49E-14 l.37E-14 1.58E-14 2.45E-05 9.43E-14 l.lSE-14 8.0SE-15 2.43E-05 2.92E-15 3.56E-16 2.SOE-16 7.53E-07 33.56 mo/min 0.56 m3/sec 6.0SE-15 1.19E-15 l.31E-15 5.35E-08 1.97E-13 3.SSE-14 4.23E-14 1.73E-06 2.ISE-14 1.63E-14 2.35E-14 1.92E-07 6.75E-16 5.03E-16 7.27E-16 5.93E-09 31.49 m3/min 0.52 m3/sec 2.0IE-15 8.SIE-16 9.4BE-16 1.66E-OB 6.SIE-14 2.BSE-14 3.06E-14 5.38E-07 S.29E-IS 9.67E-15 l.83E-14 4.36E-08 1.63E-16 2.99E-16 5.66E-16 1.3SE-09 110.20 mo/min 1.84 m3/scc 1.37E-15 7.20E-16 9.45E-16 3.96E-08 4.43E-14 2.33E-14 3.06E-14 1.2BE-06 21 G-23-0116 GOV-01-55 ACF-23-0229 Quantity Fraction Released of
{g)
ECV 1
2.73E-10 4.04E-02 l.l lE-05 4.04E-02 l.54E+OO l.52E-01 8.45E-03 3.81E+OO 9.32E-01 1.21E-01 1.67E+OO 3.37E-02 Total:
4.20E+OO 1.20E-09 2.66E-03 2.95E-10 3.26E-03 2.88E-07 l.lSE-02 7.82E-09 1.30E-02 3.36E-12 l.78E-03 l.70E-06 2.22E-02 4.00E-01 1.41E-01 1.SIE-05 2.43E-02 8.21E-02 5.92E-03 Total:
2.25E-Ol 7.35E-09 3.67E-03 1.45E-03 l.OSE-04 3.90E-03 l.89E+OO 3.48E-Ol 4.86E-02 Total:
l.94E+OO 5.19E-10 7.60E-03 l.02E-04 2.19E-04 3.07E-05 4.36E-01 2.75E-03 1.12E-02 Total:
4.55E-01 1.61E-10 2.52E-03 3.ISE-05 7.24E-05 6.99E-06 l.06E-01 6.25E-04 2.72E-03 Total:
l.llE-01 3.85E-10 1.71E-03 7.SSE-05 4.92E-05 EC\\t. Effluent Concentration Value from 10-CFR-20, Appendix B, Fractlun or CCV at the stack Is provided for reference only. concenlrallons al off-sHe locations are slgnlricantly less then those reported here (at stack) due lo the atmospherfc dlsperslan lhal occurs berore the effluent exits tne site.
Note: A value of "O* was substituted fer negative analytical rasulls.
Printed: 08/07/2023 NFS-EDMS Page I of3 Page 7 of 13
Total Volume Location (m3)
Stack S73 Bldg 306-W U-234 28,919,138 U-235 28,919,138 Stack 600 Bldg. 110 Pu-241 79,415,281 Tc-99 79,415,281 U-234 79,415,281 U-235 79,415,281 Stack 61S Bldg. 306-W Pu-241 12,732,266 Tc-99 12,732,266 U-234 12,732,266 U-235 12,732,266 Stack 646 Bldg. 110 Pu-241 8,800,986 Tc-99 8,800,986 U-234 8,800,986 U-235 8,800,986 Stack 701 Bldg. 307 Pu-241 31,452,241 Tc-99 31,452,241 U-234 31,452,241 U-235 31,452,241 Stack 702 Bldg. 307 Pu-241 40,423,019 Tc-99 40,423,019 U-234 40,423,019 U-235 40,423,019 Stack 703 Exhaust Room Air Pu-241 153,675,300 Th-228 153,675,300 Th-230 153,675,300 Th-232 153,675,300 U-234 153,675,300
'*1 I
Radioactivity in Effluent Air January 1, 2023 to June 30, 2023 Activity Error Quantity Concentration Estimate LLD Released (11Ci/ml)
(11Ci/ml)
(11C_i/ml)
(Ci)
U0.20 m3/min 1,84 m3tsec 7.61E-18 6.43E-15 l.77E-14 2.20E-10 2.35E-19 1.99E-16 5.46E-16 6.81E-12 303.16 m 3/min 5.0S m3/sec 2.38E-1S 5.23E-16 6.JOE-16 l.89E-07 7.69E-14 l.69E-14 2.04E-14 6.IOE-06 7.92E-14 l.09E-14 l.l6E-14 6.298-06 2.45E~l5 3.36E-16 3.57E-16 l.95E-07 48,S8 m3/min 0.81. *m3/sec
- l.21E-15 7.40E-16 9.47E-16 l.SSE-08 3.93E-14 2.39E-14 3.06E-14 5.00E-07 O.OOE+OO 6.63E-15 l.83E-14 O.OOE+OO O.OOE+OO 2.0SE-16 5.66E-16 O.OOE+OO 33.58 m3/min O.S6 m3/sec l.48E-15 7.90E-16 9.46E-16 l.30E-08 4.79E-14 2.56E-14 3.06E-14 4.22E-07 3.44E-16 6.99E-15 l.83E-14 3.03E-09 l.06E-l 7 2.16E-16
- 5.66E-16 9.36E-11 120.01 m3/min 2.00 m3/sec l.40E-15 8.SOE-16 l.08E-15 4-41E-08 4.53E-14 2.75E-14 3.SOE-14 l.43E-06 l.70E-15 8.61E-15 2.IOE-14 5.33E-08 5.24E-17 2.66E-16 6.49E-16 l.65E-09 1S4.24 m3/min 2.S7 m3tsec 1.35E-1S 7.65E-16 9.46E-16 5.46E-08 4.36E-14 2.47E-14 3.06E-14 l.76E-06 3.89E-IS 8.78E-15 1.83E-14 1.57E-07 l.20E-16 2.71E-16 5.66E-16.
4.87E-09 586.37 m 3/min 9.77 m'lsec 3.SSE-14 2.18E~14 2.80E-14 5.46E-06 O.OOE+OO 6.25E-16 l.67E-15 O.OOE+OO 0.00E+OO 3.60E-16 9.60E-16 O.OOE+OO O.OOE+OO 5.12E-16 l.36E-15 O.OOE+OO O.OOE+OO 3_92E-15 l.04E-14 O.OOE+OO 21 G-23-0116 GOV-01-55 ACF-23-0229 Quantity Fraction Released of (g)
ECV 1
3.53E-08 l.52E-04 3.lSE-06 3-92E-06 Total:
l.92E-03 I.83E-09 2.97E-03 3.61E-04 8.54E-05 l.OlE-03 l.SBE+OO 9.0lE-02 4.09E-02 Total:
l.63E+OO l.SOE-10 l.52E-03 2.96E-05 4.36E-05 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO Total:
l.56E-03 1.27E-10 l.85E-03 2.SOE-05 5.33E-05 4.85E-07 6.88E-03 4.33E-05 l.77E-04 Total:
8.96E-03 4.28E-10 l.75E-03 8.44E-05 5.04E-05 8.SSE-06
~,39E-02 7.64E-04 8.74E-04 Total:
3.66E-02 5.30E-10 1.69E-03 1.04E-04 4.85E-05 2.52E-05 7.79E-02 2.25E-03 2.0IE-03 Total:
8.16E-02 5.30E-08 4.44E-02 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
' ECV; Effluent concentration Value from 10.CFR...20, Appendix B. Fraction of ecv at the stack Is provided ror reference only. concentratlons at off-slle locatlons are slgnlncantly less !hen !hose reported here (et slack) due 10 the atmosphedo dlsper.;lon lhet occur.; before lhe effluent OJClts the slle.
Note: A value of -0" was substituted for negeUve analytical resul~
1 Printed: 08/07/2023 NFS-EDMS Page 2 of3 Page 8 of 13
21 G-23-0116 GOV-01-55 Radioactivity in Effluent Air ACF-23-0229 January 1, 2023 to June 30, 2023 Total Activity Error Quantity Quantity Fraction Volume Concentration Estimate LLD Released Released of Location (m*)
(µCi/ml)
(µCi/ml)
(µCi/ml)
(Ci)
(g)
ECV 1
Stack 703 Exhaust Room Air 586,37 m3tmin 9.77 m3tsec U-235 153,675,300 O.OOE+OO 4.04E-16 I.OSE-15 O.OOE+OO O.OOE+OO O.OOE+OO U-238 153,675,300 O.OOE+OO 4.93E-16 l.31E-l5 0.00E+OO O.OOE+OO O.OOE+OO Total:
4.44E-02 Stack 773 Bldg. 440 165.22 m3/min 2.75 m3tsec Pu-241 43,110,868 5.92E-14 3.06E-14 3.75E-14 2.SSE-06 2.48E-08 7.39E-02 Th-228 43,110,868 2.56E-16 1.25E-IS 3.12E-15
- l. llE-08 l.3SE-ll 1.28E-02 Th-230 43,110,868 3.30E-16 l.61E-15 4.0lE-15 l.42E-08 7.03E-07 J.65E-02 Th-232 43,110,868 2.20E-16 l.07E-15 2.67E-15 9.47E-09 8.69E-02 5.49E-02 U-234 43,110,868 6.77E-16 3.30E-15 8.24E-15 2.92E-08 4.68E-06 l.35E-02 U-235 43,110,868 l.19E-16 5.SOE-16 l.45E-15 5.13E-09 2.38E-03 l.98E-03 U-238 43,110,868 2.38E-16 l.16E-15 2.89E-IS l.03E-08 3.06E-02 3.97E-03 Total:
l.78E-Ol Stack 774 Bldg. 301 305.29 m3/min 5.09 m 3/sec Tc-99 79,999,115 2.25E-13 l.70E-14 l.59E-14 I.SOE-OS l.07E-03 2.SOE-04 Th-228 79,999,115 I.SSE-IS 2.21E-16 4.IJE-16 l.24E-07 l.SlE-10 7.75E-02 Th-230 79,999,115 5.28E-15 7.53E-16 l.41E-15 4.23E-07 2.09E-05 2.64E-01 Th-232 79,999,115 3.13E-15 4.47E-16 8.35E-16 2.SlE-07 2.30E+OO 7.83E-Ol U-234 79,999,115 l.41E-14 2.0lE-15 3.76E-15 l.13E-06 I.BlE-04 2.82E-01 U-235 79,999,115 9.IBE-16 l.31E-16 2.45E-16 7.34E-08 3.40E-02 l.53E-02 U-238 79,999,115 6.64E-15 9.47E-16 l.77E-15 S.32E-07 l.59E+OO l.l!E-01 Total:
1.53E+OO Stack 796 Bldg. 100 17.92 m3/min 0.30 m3/sec Pu-241 4,697,670 l.66E-15 8J9E-16 9.47E-16 7.78E-09 7.56E-ll 2.07E-03 Tc-99 4,697,670 5.36E-14 2.65E-14 3.06E-14 2.52E-07 1.49E-05 5.95E-05 U-234 4,697,670 6.65E-16 7.3 IE-15 l.83E-14 3.13E-09 5.0lE-07 l.33E-02 U-235 4,697,670 2.06E-17 2.26E-16 5.66E-16 9.67E-1 I 4.48E-05 3.43E-04 Total:
l.SBE-02 1
ECV: Effluent Concenlrallon Value from 1 O-CFR-20, Appendix B. Fraction or ECV al the stack is provided ror rererence only. concentrations et off-slte locations are significantly less than those reported here (al slack) due to the atmospheric dispersion that occurs before the effluent exits the site.
Nole: A value or ~o* was subslltuted for negeUve analytfcal reslllts, Printed: 08/07/2023 NFS-EDMS Page 3 of3 _
Page 9 of 13 To Letter Dated August 17, 2023 21G-23-0116 GOV-01-55 ACF-23-0229 Report of Gaseous Effluent Dose and Activity Concentrations for the Maximally Exposed Off-Site Individual for the Release Period January to June 2023 (3 Pages to Follow)
Page 10 of 13
21 G-23-0116 GOV-01-55 ACF-23-0229 Report of Potential Gaseous Effluent Dose to the Maximally Exposed Offsite Individual and on the Maximum Radionuclide Concentrations for the Period:
January to June 2023 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 fifteen
{15) radiological stacks during the first half of 2023. Based on effluent types and stack physical characteristics, releases from these stacks were grouped into effective stacks for modeling purposes. To accommodate the co-location limitation of the model, the effective stacks were taken to be at the approximate center of the plant site. The distance to the site boundary (nearest model receptor distance) was conservatively taken to be 150 meters for all sectors.
Meteorological data was based on the average wind speed and direction frequencies from the onsite meteorological tower covering the time period for this report.
Atmospheric stability class D (neutral atmosphere) was used for all releases (default value recommended by the U.S. Environmental Protection Agency in "User's Guide for COMPLY"). The most conservative inhalation class was assumed for each radionuclide released. A particle size (activity median aerodynamic diameter or AMAD) of 1.0 micron was assumed for modeling purposes since no information on actual particle sizes exists.
Because CAP88-PC models releases over an entire year, the six-month soun;:e 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-23-0116 GOV-01-55 ACF-23-0229 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 4.2E-03 mrem for gaseous effluents released during the first half of 2023. 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 first half of 2023) 3.2E-04 4.0E-04 1.2E-02 3.2E-04 3.4E-04 7.9E-03 3.6E-04 2.1E-03 5.4E-03 3.2E-03 1.1 E-03 3.3E-04 3.7E-04 3.2E-04 1.6E-03 8.4E-04 3.2E-04 3.9E-04 3.2E-04 4.1E-03 3.2E-04 3.2E-04 3.2E-04 1.5E-02 1.8E-02 4.2E-03 mrem 450 meters Northeast Page 12 of 13
I i
i*
21G-23-0116 GOV-01-55 ACF-23-0229 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 6.3E-04 an*d 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 JVlaxbnmµ Predicte.d Airborne Conce_~tratfoiis at
- or Beyond the S'ite BQundary
'\\
Ma:tjrilum Concentratio'}
10 CJRtO,App.B,.Ratio of Maximum
... *Nu~li~
- Concentration Location.
Table 2, Col. i Value Conc~ntration to.
(l.1Ci/mLY
- -Dis't (Di) 10 CFR20 Value
. Sect!>r*
(µCi/~).
-1 99Tc 3.lE-17 NE 400 9.E-10 3.4E-08 22sTh 9.9E-20 NE 600 2.E-14 4.9E-06 230Th 2.5E-19 NE 500 2.E-14 l.2E-05 232Th 1.7E-19 NE 450 4.E-15 4.4E-05 z34u 2.7E-17 NE 500 5.E-14 5.4E-04 23su 9.IE-19 NE 550 6.E-14 l.5E-05 23su 3.4E-19 NE 550 6.E-14 5.6E-06 238Pu 9.5E-21 NE 200 2.E-14 4.7E-07 239Pu 3.3E-20 NE 200 2.E-14 l.7E-06 241Pu 8.0E-18 NE 350 8.E-13 l.0E-05 241Am 7.7E-21 NE 200 2.E-14 3.9E-07 Sum of Fractions:
6.3E-04 Page 13 of 13