ML19059A323
| ML19059A323 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse (SNM-1107) |
| Issue date: | 02/27/2019 |
| From: | Wills E Westinghouse |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| LTR-RAC-19-15 | |
| Download: ML19059A323 (21) | |
Text
Page 1 of 2 Westinghouse Electric Company LLC Nuclear Fuel Columbia Fuel Site 5801 Bluff Road Hopkins, South Carolina 29061 USA
© 2019 Westinghouse Electric Company LLC All Rights Reserved Document Control Desk, Director Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Direct tel: 803-647-1000 Our ref: LTR-RAC-19-15
Subject:
SNM-1107/70-1151 NRC Semi-Annual Discharge Report July - December 2018 February 27, 2019
Dear Sir:
The following report fulfills regulatory requirements as listed in 10 CFR 40.65 and 10 CFR 70.59 "Effluent Monitoring Reporting Requirements." For the six-month period July 1, 2018, through December 31, 2018, the following quantities of radionuclides were released to the unrestricted area by the Westinghouse Electric Company's Columbia, South Carolina Nuclear Fuel Plant:
Discharge Total 6-month emissions (uCi)
Parameter Total 6-month Measured Concentration Regulatory Concentration Limit Gaseous 204.5 Uranium (analyzed as gross alpha) 7.4 E-15 uCi/mL*
5 E-14 uCi/mL Liquid Effluent 1,342.2 U-234 2.1 E-8 uCi/mL 3 E-7 uCi/mL 47.4 U-235 222.1 U-238 629.6 Tc-99 8.0 E-9 uCi/mL 6 E-5 uCi/mL
- Includes a dispersion factor of 1000 to account for dilution between the release point and the nearest site boundary As shown above, the effluent releases are within the NRCs regulatory limits designed to protect the public health and safety.
Gaseous effluent results were obtained from point source gross alpha analysis of stack gas effluent, and the individual radionuclide activity composition is inferred from the calculated average enrichment (85.04% U-234, 3.38% U-235, and 11.43% U-238). Tc-99 is not reported for gaseous effluents, as significant quantities of Tc-99 were not detected during benchmark testing of gaseous emissions.
Liquid effluent values were obtained by analysis of composite proportional samples prior to discharge to the Congaree River and basing the activity on the calculated average enrichment. All liquid discharges are pumped through a single discharge line to the Congaree River. Liquid effluent composites were analyzed by alpha spectroscopy, and significant quantities of U-236 were not detected using this method. The total liquid effluent volume released to the Congaree River during the second half of 2018 was 7.84E+07 liters.
Calculated values have been reported for all results, due to variability of minimum detection
Page 2 of2 Our ref: LTR-RAC-19-15 February 27, 2019 To meet the requested dosage information outlined in Regulatory Guide 4.16, section 6.1, the internal Westinghouse letter LTR-EHS-19-17 entitled "Annual Assessment of Public Dose due to Liquid and Gaseous Effluents" is attached.
Sincerely,
/;t,.,Yc:J wdle}
Edward Wills Manager, Environment, Health and Safety cc:
USNRC, Region II 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, Georgia 30303-1257
© 2019 Westinghouse Electric Company LLC All Rights Reserved
- Electronically approved records are authenticated in the Electronic Document Management System.
To: Cynthia Logsdon, Diana Joyner Date: February 22, 2019 cc: Ed Wills, Nancy Parr, Anna Pearson, Ed Byrd From: David Wagoner Your ref:
Ext: 1919 Our ref: LTR-EHS-19-17 Fax: 803.695.4158
Subject:
Annual Assessment of Public Dose due to Liquid and Gaseous Effluents Effluents released from plant operations are monitored to determine the quantities of radionuclides discharged into the environment. The cumulative radioactivity released is summarized semi-annually and annually and input into dose models developed by the NRC and EPA to estimate the dose to the public.
The whole body and organ dose via the following pathways were determined in this assessment:
Dose due to Gaseous Effluents by Direct Inhalation o The whole body dose was estimated using the EPAs COMPLY Code at level 2 complexity. The organ dose was estimated using the calculated X/Q factor for stack number 1210 (Conv. 1-A Ex.), the measured release quantity, and the dose conversion factors from Federal Guidance Report No 11, Limiting Values of Radionuclide Intake and Air concentration Factors for Inhalation, Submersion, and Ingestion (FGR 11).
Dose due to Liquid Effluents by Ingestion of Potable Water o Estimated using equations and recommended values in Regulatory Guide 1.109, Doses from Liquid Effluent Pathways (RG1.109). Dose conversion factors were taken from FGR 11.
Dose due to Liquid Effluents by Ingestion of Fish o Estimated using equations and recommended values in RG 1.109. Dose conversion factors were taken from FGR 11.
Dose due to Liquid Effluents by Irradiation from Shoreline Deposition o Estimated using equations and recommended values in RG 1.109. Dose conversion factors were taken from Federal Guidance report No 12, External Exposure to Radionuclides in Air, Water, and Soil The inhalation dose is determined at the nearest site boundary at a distance of 595 meters.
The ingestion dose from liquid effluent and external dose from sediment deposition is determined at the point where the liquid effluent leaves the diffuser in the Congaree River.
Page 2 of 3 Our ref: LTR-EHS-19-17 February 22, 2019 The release rates for gaseous effluent are determined by gross alpha measurements performed on daily air samples, one per stack for 47 stacks (Attachment 1). The release rates for liquid effluent are determined by isotopic analysis of composite liquid effluent samples taken monthly (Attachment 3). Based on these results, the following quantities were released in calendar year 2018:
366.92 µCi of Uranium in gaseous effluent 3.43 mCi of Uranium in liquid effluent 1.12 mCi of Technetium in liquid effluent Using these results and the methods previously mentioned the whole body dose, dose to the bone, and dose to the lung were determined for an individual present at the nearest site boundary.
Table 1 provides a summary of the results for each pathway. The gaseous and liquid effluents released during 2018 resulted in a potential whole body dose of 0.16 mrem to an individual present at the nearest site boundary. This dose is significantly less than the 25 mrem annual whole body dose limit for a member of the public.
Table 1. 2018 Annual Dose to the Public from Liquid and Gaseous Effluents Whole Body Dose (mrem/yr)
Organ Dose - Bone (mrem/yr)
Organ Dose - Lung (mrem/yr)
Gaseous Effluents Direct inhalation*
0.16 4.9E-03 1.3 Liquid Effluents Potable Water 8.2E-05 1.2E-03 Aquatic Food (Fish) 4.8E-06 6.9E-05 Shoreline Deposition 3.0E-08 Total (mrem) 0.16 6.2E-03 1.3
- Assumes 80 % residence time No effluent release points were added or removed from the effluent monitoring program in 2018.
The attachments below illustrate the method used to calculate each result listed in Table 1.
Page 3 of 3 Our ref: LTR-EHS-19-17 February 22, 2019 2018 Gaseous Effluent Discharges :
Lung/Bone Organ Dose due to Gaseous Effluent :
2018 Liquid Effluent Discharges :
Whole Body Dose from Liquid Effluent Pathways - Potable Water :
Dose to the Bone Surface from Liquid Effluent Pathways - Potable Water :
Whole Body Dose from Liquid Effluent Pathways - Aquatic Foods :
Dose to the Bone Surface from Liquid Effluent Pathways - Aquatic Foods :
Whole Body Dose from Liquid Effluent Pathways - Shoreline Deposits :
2018 Isotopic Fractions 0:
Comply Results David Wagoner, CHP Radiation Safety Engineer EH&S Operations Anna Pearson Manager, RSO EH&S Operations 2018GaseousEffluentDischarges Sampling Location StackHeight GrossAlphaConcentration*
1stHalf 2ndHalf TotaluCi Station Description (m)
(uCi/mL)
Released U234 U235 U238 1207 METLABEXHAUST 10 1.96E13 1.69 1.70 3.39 9.18E14 3.65E15 1.23E14 1238 IFBAEXHAUST 10 8.13E14 5.98 7.11 13.09 3.54E13 1.41E14 4.77E14 1239 MAINTWELDEX 11 1.76E13 2.59 2.31 4.90 1.33E13 5.28E15 1.78E14 1243 AC8 11 8.01E14 4.70 4.83 9.53 2.58E13 1.03E14 3.47E14 1222 CALCCOMBGASLN1 12 3.06E13 0.77 0.30 1.07 2.90E14 1.15E15 3.90E15 1223 CALCCOMBGASLN2 12 5.08E13 1.30 0.42 1.72 4.66E14 1.85E15 6.26E15 1224 CALCCOMBGASLN3 12 1.28E13 0.33 0.36 0.69 1.87E14 7.44E16 2.51E15 1225 CALCCOMBGASLN4 12 1.13E13 0.29 0.34 0.63 1.71E14 6.79E16 2.29E15 1226 CALCCOMBGASLN5 12 1.26E13 0.32 0.24 0.56 1.52E14 6.04E16 2.04E15 1228 CHEMLABEX#3 12 8.68E14 0.43 0.45 0.88 2.38E14 9.49E16 3.20E15 1231 DEVLABEX#2 12 1.99E13 2.93 3.00 5.93 1.61E13 6.39E15 2.16E14 1237 ABFHOODTORITEX 12 8.64E14 1.91 2.02 3.93 1.06E13 4.24E15 1.43E14 1241 PELLETLINE6 12 8.12E14 3.51 3.57 7.08 1.92E13 7.63E15 2.58E14 1247 HOTOILRMEX 12 1.65E13 9.99 16.24 26.23 7.10E13 2.83E14 9.55E14 1201 FURNACEEXLINE1 13 8.44E14 3.65 3.60 7.25 1.96E13 7.81E15 2.64E14 1202 FURNACEEXLINE2 13 8.09E14 3.49 3.56 7.05 1.91E13 7.60E15 2.57E14 1203 FURNACEEXLINE3 13 8.00E14 3.45 3.54 6.99 1.89E13 7.53E15 2.54E14 1204 FURNACEEXLINE4 13 8.01E14 3.46 3.58 7.04 1.91E13 7.59E15 2.56E14 1205 FURNACEEXLINE5 13 8.34E14 3.60 3.50 7.10 1.92E13 7.65E15 2.58E14 1206 NEWDECONROOM 13 9.21E14 2.35 10.19 12.54 3.40E13 1.35E14 4.57E14 1208 INCINERATOREX 13 1.36E13 4.00 15.24 19.24 5.21E13 2.07E14 7.00E14 1209 SUPPLINCINEX 13 3.16E13 4.65 3.51 8.16 2.21E13 8.80E15 2.97E14 1217 CONVENCLEX4C 13 1.01E13 6.09 7.92 14.01 3.79E13 1.51E14 5.10E14 1218 CONVENCLEX4D 13 2.00E13 0.00 0.00 0.00 0.00E+00 0.00E+00 0.00E+00 1219 CONVEMERGEX4E 13 2.20E13 0.64 0.78 1.42 3.85E14 1.53E15 5.17E15 1221 DECONROOMEX 13 2.90E13 6.39 7.09 13.48 3.65E13 1.45E14 4.91E14 1230 DEVLABEX#1 13 2.04E13 3.00 2.76 5.76 1.56E13 6.21E15 2.10E14 1232 PELLETCOMBINEDEX 13 8.14E14 5.98 6.22 12.20 3.30E13 1.32E14 4.44E14 1233 SOLVENTEXTNEX 13 8.49E14 3.77 3.95 7.72 2.09E13 8.32E15 2.81E14 1234 SOLVENTEXTSEX 13 2.06E13 1.53 1.70 3.23 8.75E14 3.48E15 1.18E14 1229 HPLABEX 15 8.22E14 0.74 0.83 1.57 4.25E14 1.69E15 5.72E15 1236 MAPCOMBINED 15 1.07E13 0.00 0.00 0.00 0.00E+00 0.00E+00 0.00E+00 1240 AC3 15 8.06E14 4.74 4.94 9.68 2.62E13 1.04E14 3.52E14 1246 AC4 15 8.34E14 5.05 5.06 10.11 2.74E13 1.09E14 3.68E14 1251 WATERGLASSSCRS1190 15 8.14E14 2.99 3.05 6.04 1.64E13 6.51E15 2.20E14 1210 CONV1AEX 16 9.92E14 6.42 20.19 26.61 7.21E13 2.87E14 9.69E14 1211 CONV1BEX 16 1.97E13 0.00 0.00 0.00 0.00E+00 0.00E+00 0.00E+00 1212 S1030A 16 1.09E13 12.16 11.15 23.31 6.31E13 2.51E14 8.49E14 1213 S1030B 16 2.24E13 1.25 1.68 2.93 7.93E14 3.16E15 1.07E14 1227 CHEMLABEX#2 16 2.49E13 2.26 2.60 4.86 1.32E13 5.24E15 1.77E14 1220 CHEMLABFILTEX 17 8.71E14 7.53 8.35 15.88 4.30E13 1.71E14 5.78E14 1242 AC5 17 8.24E14 4.84 5.21 10.05 2.72E13 1.08E14 3.66E14 1244 AMMONFUMESCR1008A 17 8.89E14 2.61 2.92 5.53 1.50E13 5.96E15 2.01E14 1245 AMMONFUMESCR1008B 17 1.38E13 0.00 0.00 0.00 0.00E+00 0.00E+00 0.00E+00 1248 ERBIAFURNACEEX 18 8.51E14 10.81 10.27 21.08 5.71E13 2.27E14 7.67E14 1249 ERBIASCRUBBEREX 18 8.46E14 5.70 5.69 11.39 3.08E13 1.23E14 4.15E14 1250 ERBIACHANGEROOM 18 8.56E14 2.53 2.53 5.06 1.37E13 5.45E15 1.84E14 Total 162.42 204.50 366.92 9.94E12 3.96E13 1.34E12
- MinimumDetectableConcentrationis8E14uCi/mL 0.2 Assume80%residencetime=
0.16 uCiUraniumReleased ReleaseRate(Ci/s)
TotaloffsitedosecalculatedbyComply(mrem/y)=
O:\\Regulatory\\EH&SOperations\\Environment\\Environment2018\\Annual\\Gaseouseffluent2018.xlsx Lung/BoneOrganDoseduetoGaseousEffluents 1st half (Jan-Jun) 2nd half (Jul-Dec)
Total EPA STACK IDENTIFICATION uCi Uranium uCi Uranium uCi released Comply Run Results Conv 1-A Ex 6.42 20.19 26.61 Dose (mrem/yr) 1.40E-02 use highest release to calculate X/Q used by COMPLY Stack height (m) 16 U-234 U-235 U-238 Dose from comply 0.01400 mrem/yr 7.21E-13 2.87E-14 9.69E-14 release quantity 26.61 uCi 2.66E-05 Ci App E table E-5 8000.00 m3/yr Effective Dose conversion EPA FGR 11 p150-151 U-234 3.58E-05 Sv/Bq 85.16%
U-235 3.32E-05 Sv/Bq 3.39%
U-238 3.20E-05 Sv/Bq 11.45%
weighted dose conversion 3.53E-05 Sv/Bq conversion factor 3700.00 mrem/pCi= factor* Sv/Bq weighted dose conversion 0.1305 mrem/pCi equations Dose (mrem) = R(a)*3.17e4*Q*(X/Q)*effective Dose conversion see RG1.109-25 Dose (mrem)/(R(a)*3.17e4*Q*effective Dose conversion)=(X/Q) 1.59E-05 X/Q Estimate Lung Dose using X/Q and annual releases for 2018 Estimate Bone Dose using X/Q and annual releases for 2018 App E table E-5 Lung Organ Dose conversion EPA FGR 11 p150-151 U-234 2.98E-04 Sv/Bq 85.16%
1.13E-06 Sv/Bq U-235 2.76E-04 Sv/Bq 3.39%
1.05E-06 Sv/Bq U-238 2.66E-04 Sv/Bq 11.45%
1.01E-06 Sv/Bq weighted dose conversion 2.94E-04 Sv/Bq 1.11E-06 Sv/Bq conversion factor 3700.00 mrem/pCi= factor* Sv/Bq 3700.00 mrem/pCi= factor* Sv/Bq weighted dose conversion 1.0863 mrem/pCi 4.12E-03 mrem/pCi release quantity 366.92 uCi/yr 366.92 uCi/yr 3.67E-04 Ci/yr 3.67E-04 Ci/yr Lung
- 1.29 mrem/yr Bone
- 4.87E-03 mrem/yr
- assume 80% residence Release Rate (Ci/s)
O:\\Regulatory\\EH&SOperations\\Environment\\Environment2018\\Annual\\Gaseouseffluent2018.xlsx
2018 Tc-99 Measured Concentrations Sum U & Tc-99 Month Average kgal/day Actual kgal/month Actual gal/month U234 pCi/L U235 pCi/L U238 pCi/L Total U pCi/L Tc-99 piC/L Total U & Tc-99 pCi/L U234 U-235 U-238 Tc-99 U234 piC/L U235 piC/L U238 piC/L Tc-99 piC/L U234 (uCi)
U-235 (uCi)
U-238 (uCi)
Tc-99 (uCi)
January 93.639 2902.795 2,902,795 20.8 2.04 4.34 27.180 4.73 31.910 228.531 22.414 47.684 51.969 2.13 0.814 1.00 19.5 23.402 8.943 10.987 214.248 February 87.617 2453.288 2,453,288 15.1 0.857 2.63 18.587 4.62 23.207 140.214 7.958 24.421 42.900 1.16 0.315 0.490 20.5 10.771 2.925 4.550 190.357 March 89.909 2787.174 2,787,174 18.4 1.22 3.19 22.810 3.08 25.890 194.110 12.870 33.653 32.492 1.48 0.432 0.623 26.9 15.613 4.557 6.572 283.780 April 86.267 2588.010 2,588,010 31.0 1.65 5.51 38.160 9.33 47.490 303.664 16.163 53.974 91.393 2.48 0.646 1.05 26.0 24.293 6.328 10.285 254.686 May 92.394 2864.223 2,864,223 36.1 1.13 6.21 43.440 12.8 56.240 391.363 12.250 67.323 138.766 3.02 0.614 1.27 26.6 32.740 6.656 13.768 288.373 June 115.012 3450.345 3,450,345 16.3 0.755 2.62 19.675 10.5 30.175 212.871 9.860 34.216 137.125 1.05 0.264 0.438 25.0 13.713 3.448 5.720 326.489 July 123.373 3824.560 3,824,560 14.3 0.522 2.19 17.0 0.0 17.0 207.006 7.556 31.702 0.000 1.94 0.467 0.784 24.9 28.083 6.760 11.349 360.451 August 117.849 3535.467 3,535,467 11.9 0.378 1.91 14.2 10.8 25.0 159.243 5.058 25.559 144.523 1.28 0.269 0.519 23.0 17.129 3.600 6.945 307.780 September 117.801 3534.026 3,534,026 14.7 0.517 2.42 17.6 14.2 31.8 196.631 6.916 32.371 189.943 1.42 0.312 0.584 21.0 18.994 4.173 7.812 280.902 October 116.834 3388.172 3,388,172 17.1 0.528 2.85 20.5 0.247 20.7 219.294 6.771 36.549 3.168 1.53 0.325 0.635 20.0 19.621 4.168 8.143 256.485 November 120.969 3024.228 3,024,228 21.1 0.867 3.42 25.4 13.0 38.4 241.525 9.924 39.148 148.807 1.79 0.412 0.736 23.7 20.490 4.716 8.425 271.287 December 121.681 3407.058 3,407,058 24.7 0.868 4.40 30.0 11.1 41.1 318.524 11.193 56.741 143.142 1.83 0.401 0.775 20.8 23.599 5.171 9.994 268.231 Total 37759.346 37,759,346 2812.978 128.934 483.341 1124.229 248 61 105 3303 Liters (L) 1.43E+08 Milliliters (ml) 1.43E+11 LIQUID DISCHARGES Radionuclide Quantity Released (uCi)
U234 2813.0
+/-
248 U235 128.9
+/-
61 U238 483.3
+/-
105 Total U 3425.3 Tc-99 1124.2
+/-
3303 Total 4549.5 Uncertainty / Error - 2018 Liquid Effluent Discharges Total uCi/month Released (based on monthly GEL discharge samples)
LLD (uCi/ml) 7.87E-09 3.18E-08 Measurement Uncertainty / Error Liquid Effluent Discharges 3425.3 uCi Uranium (all types)
Isotopic Uranium Measured Concentrations 4549.5 uCi Uranium & Tc-99 6.00E-10 6.00E-10 6.00E-10 6.00E-10 Average Concentration Released (uCi/ml)
Error 1.97E-08 9.02E-10 3.38E-09 2.40E-08 O:\\Regulatory\\EH&S Operations\\Environment\\Environment 2018\\Annual\\2018 Liquid Effluent.xlsx Whole Body Dose from Liquid Effluent Pathways - Potable Water Whole Body-Ingestion 730 liters Usage by adult/yr U
10CFR20 7.3 x 105 (ml) which is the annual water intake of "Reference Man."
31293 mixing - dilution Dilution at difuser M
Congaree Flow 9388 cubic feet/sec see Nureg-1118 Environmental Assessment for renewam SNM-1107 May 1985 0.3 cubic ft/sec Average discharge F Effluent Flow 3.00E-01 cubic feet/sec effective bone effective bone 2.83E-04 U-234 mRem/pCi D
EPA Limiting Values of Radioanuclide Intake Sv/Bq Sv/Bq mRem/pCimRem/pCi 2.66E-04 U-235 mRem/pCi D
FRG no 11 1988 U-234 7.66E-08 1.13E-06 2.83E-04 4.18E-03 2.55E-04 U-238 mRem/pCi D
Exposure-to-dose conversion factors for ingestion U-235 7.19E-08 1.05E-06 2.66E-04 3.88E-03 1.46E-06 Tc-99 mRem/pCi D
U-238 6.88E-08 1.01E-06 2.55E-04 3.74E-03 Tc-99 3.95E-10 6.04E-11 1.46E-06 2.23E-07 12 hrs transit time t-p reg guide 1.109 table E-15 3.23557E-10 U-234 decay const
1.12404E-13 U-235 decay const
Nuclide T(1/2) yr T(1/2) hr
1.77058E-14 U-238 decay const
URANIUM234 2.45E+05 2.14E+09 3.24E-10 3.71407E-10 Tc-99 decay const
URANIUM235 7.04E+08 6.17E+12 1.12E-13 URANIUM238 4.47E+09 3.91E+13 1.77E-14 for comaprison only 0.9999999961 U-234 exp(-t-p)
TC-99 2.13E+05 1.87E+09 3.71E-10 1.0000000000 U-235 exp(-t-p)
Part 20 table 2 soluble forms 1.0000000000 U-238 exp(-t-p)
Dose Conversion 0.9999999955 Tc-99 exp(-t-p) uCi/ml milliters uCi pCi mRem mRem/pCi U-234 3.00E-07 7.30E+05 2.19E-01 2.19E+05 50 2.28E-04 Activity Released U-235 3.00E-07 7.30E+05 2.19E-01 2.19E+05 50 2.28E-04 3.425E-03 total uranium(Ci)
Q U-238 3.00E-07 7.30E+05 2.19E-01 2.19E+05 50 2.28E-04 Tc-99 6.00E-05 7.30E+05 4.38E+01 4.38E+07 50 1.14E-06 2.813E-03 U-234 release fraction Ci 1.289E-04 U-235 release fraction Ci ICRP 69 Comparison 4.833E-04 U-238 release fraction Ci 1.124E-03 Tc-99 release fraction Ci Sv/Bq Rem/Bq mRem/pCi check U sum 0.00343 Ci adult 5.00E-08 0.005 1.85E-04 infant 3.70E-07 0.037 1.37E-03 7.97E-07 U-234 release fraction *dose factor*exp(-*tp) bone-adult 7.90E-07 0.079 2.92E-03 3.43E-08 U-235 release fraction *dose factor*exp(-*tp) 1.23E-07 U-238 release fraction *dose factor*exp(-*tp) 1.64E-09 Tc-99 release fraction *dose factor*exp(-*tp) 9.56E-07 all nuclides sum of nuclides 85.53473 usage 1100*(usage*dilution)/flow 8.18E-05 mRem see regulatory guide 1.109 page 1.109-2 and 1.109-3 for formula and definition of terms.
O:\\Regulatory\\EH&S Operations\\Environment\\Environment 2018\\Annual\\2018 Liquid Effluent.xlsx Dose to the Bone Surface from Liquid Effluent Pathways - Potable Water Bone Surface-Ingestion 730 liters Usage by adult/yr U
10CFR20 7.3 x 105 (ml) which is the annual water intake of "Reference Man."
31293 mixing - dilution Dilution at difuser M
Congaree Flow 9388 cubic feet/sec see Nureg-1118 Environmental Assessment for renewam SNM-1107 May 1985 0.3 cubic ft/sec Average discharge F Effluent Flow 3.00E-01 cubic feet/sec effective bone effective bone 4.18E-03 U-234 mRem/pCi D-bone EPA Limiting Values of Radioanuclide Intake Sv/Bq Sv/Bq mRem/pCi mRem/pCi 3.88E-03 U-235 mRem/pCi D-bone FRG no 11 1988 U-234 7.66E-08 1.13E-06 2.83E-04 4.18E-03 3.74E-03 U-238 mRem/pCi D-bone Exposure-to-dose conversion factors for ingestion U-235 7.19E-08 1.05E-06 2.66E-04 3.88E-03 2.23E-07 Tc-99 mRem/pCi D-bone U-238 6.88E-08 1.01E-06 2.55E-04 3.74E-03 Tc-99 3.95E-10 6.04E-11 1.46E-06 2.23E-07 12 hrs transit time t-p reg guide 1table E-15 3.23557E-10 U-234 decay const
1.12404E-13 U-235 decay const
Nuclide T(1/2) yr T(1/2) hr
1.77058E-14 U-238 decay const
URANIUM234 2.45E+05 2.14E+09 3.24E-10 3.71407E-10 Tc-99 decay const
URANIUM235 7.04E+08 6.17E+12 1.12E-13 Part 20 table 2 soluble forms URANIUM238 4.47E+09 3.91E+13 1.77E-14 Dose Conversion 0.9999999961 U-234 exp(-t-p)
TC-99 2.13E+05 1.87E+09 3.71E-10 uCi/ml milliters uCi pCi mRem mRem/pCi 1.0000000000 U-235 exp(-t-p)
U-234 3.00E-07 7.30E+05 2.19E-01 2.19E+05 50 2.28E-04 1.0000000000 U-238 exp(-t-p)
U-235 3.00E-07 7.30E+05 2.19E-01 2.19E+05 50 2.28E-04 0.9999999955 Tc-99 exp(-t-p)
U-238 3.00E-07 7.30E+05 2.19E-01 2.19E+05 50 2.28E-04 Tc-99 6.00E-05 7.30E+05 4.38E+01 4.38E+07 50 1.14E-06 Activity Released 3.425E-03 total uranium(Ci)
Q ICRP 69 Comparison 2.813E-03 U-234 release fraction Ci Sv/Bq Rem/Bq mRem/pCi 1.289E-04 U-235 release fraction Ci 4.833E-04 U-238 release fraction Ci adult 5.00E-08 0.005 1.85E-04 1.124E-03 Tc-99 release fraction Ci infant 3.70E-07 0.037 1.37E-03 bone-adult 7.90E-07 0.079 2.92E-03 check U sum 0.00343 1.18E-05 U-234 release fraction *dose factor*exp(-*tp) 5.01E-07 U-235 release fraction *dose factor*exp(-*tp) 1.81E-06 U-238 release fraction *dose factor*exp(-*tp) 2.51E-10 Tc-99 release fraction *dose factor*exp(-*tp) 1.41E-05 all nuclides sum of nuclides 85.53473 usage 1100*(usage*dilution)/flow 1.20E-03 mRem see regulatory guide 1.109 page 1.109-2 and 1.109-3 for formula and definition of terms.
O:\\Regulatory\\EH&S Operations\\Environment\\Environment 2018\\Annual\\2018 Liquid Effluent.xlsx Whole Body Dose from Liquid Effluent Pathways - Aquatic Foods Whole Body 21 Kg Usage by adult/yr U
see regulatory guide 1.109 page 1.109-40 table E-5, Recommended Values for U(ap) 31293 mixing - dilution Dilution at difuser M
Congaree Flow 9388 cubic feet/sec see Nureg-1118 Environmental Assessment for renewam SNM-1107 May 1985 0.3 cubic ft/sec Average discharge F Effluent Flow 3.00E-01 cubic feet/sec effective bone effective bone 2.83E-04 U-234 mRem/pCi D
EPA Limiting Values of Radioanuclide Intake Sv/Bq Sv/Bq mRem/pCi mRem/pCi 2.66E-04 U-235 mRem/pCi D
FRG no 11 1988 U-234 7.66E-08 1.13E-06 2.83E-04 4.18E-03 2.55E-04 U-238 mRem/pCi D
Exposure-to-dose conversion factors for ingestion U-235 7.19E-08 1.05E-06 2.66E-04 3.88E-03 1.46E-06 Tc-99 mRem/pCi D
U-238 6.88E-08 1.01E-06 2.55E-04 3.74E-03 Tc-99 3.95E-10 6.04E-11 1.46E-06 2.23E-07 24 hrs transit time t-p reg guide 1table E-15 3.23557E-10 U-234 decay const
1.12404E-13 U-235 decay const
Nuclide T(1/2) yr T(1/2) hr
1.77058E-14 U-238 decay const
URANIUM234 2.45E+05 2.14E+09 3.24E-10 for comaprison only 3.71407E-10 Tc-99 decay const
URANIUM235 7.04E+08 6.17E+12 1.12E-13 URANIUM238 4.47E+09 3.91E+13 1.77E-14 Part 20 table 2 soluble forms 0.99999999223 U-234 exp(-t-p)
TC-99 2.13E+05 1.87E+09 3.71E-10 Dose Conversion 1.00000000000 U-235 exp(-t-p) uCi/ml milliters uCi pCi mRem mRem/pCi 1.00000000000 U-238 exp(-t-p)
U-234 3.00E-07 7.30E+05 2.19E-01 2.19E+05 50 2.28E-04 0.99999999109 Tc-99 exp(-t-p)
U-235 3.00E-07 7.30E+05 2.19E-01 2.19E+05 50 2.28E-04 U-238 3.00E-07 7.30E+05 2.19E-01 2.19E+05 50 2.28E-04 Activity Released Tc-99 6.00E-05 7.30E+05 4.38E+01 4.38E+07 50 1.14E-06 3.425E-03 total uranium(Ci)
Q ICRP 69 Comparison 2.813E-03 U-234 release fraction Ci 1.289E-04 U-235 release fraction Ci Sv/Bq Rem/Bq mRem/pCi 4.833E-04 U-238 release fraction Ci 1.124E-03 Tc-99 release fraction Ci adult 5.00E-08 0.005 1.85E-04 infant 3.70E-07 0.037 1.37E-03 check U sum 0.00343 bone-adult 7.90E-07 0.079 2.92E-03 bioaccumulation factor BNWL-2075 1.59E-06 U-234 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 UC-11 6.86E-08 U-235 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 Methodology for Calculation of Radiation Doses 2.46E-07 U-238 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 in the Environs from Nuclear Fuel 2.46E-08 Tc-99 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 15 Cycle Facilities 1.93E-06 all nuclides sum of nuclides 2.46059 usage 1100*(usage*dilution)/flow 4.76E-06 mRem see regulatory guide 1.109 page 1.109-2 and 1.109-3 for formula and definition of terms.
O:\\Regulatory\\EH&S Operations\\Environment\\Environment 2018\\Annual\\2018 Liquid Effluent.xlsx Dose to the Bone Surface from Liquid Effluent Pathways - Aquatic Foods Bone Surface 21 Kg Usage by adult/yr U see regulatory guide 1.109 page 1.109-40 table E-5, Recommended Values for U(ap) 31293 mixing - dilution Dilution at difuser M
Congaree Flow 9388 cubic feet/sec see Nureg-1118 Environmental Assessment for renewam SNM-1107 May 1985 0.3 cubic ft/sec Average discharge F Effluent Flow 3.00E-01 cubic feet/sec effective bone effective bone 4.18E-03 U-234 mRem/pCi D
EPA Limiting Values of Radioanuclide Intake Sv/Bq Sv/Bq mRem/pCimRem/pCi 3.88E-03 U-235 mRem/pCi D
FRG no 11 1988 U-234 7.66E-08 1.13E-06 2.83E-04 4.18E-03 3.74E-03 U-238 mRem/pCi D
Exposure-to-dose conversion factors for ingestion U-235 7.19E-08 1.05E-06 2.66E-04 3.88E-03 2.23E-07 Tc-99 mRem/pCi D
U-238 6.88E-08 1.01E-06 2.55E-04 3.74E-03 Tc-99 3.95E-10 6.04E-11 1.46E-06 2.23E-07 24 hrs transit time t-p reg guide 1.109 table E-15 3.23557E-10 U-234 decay const
1.12404E-13 U-235 decay const
Nuclide T(1/2) yr T(1/2) hr
for comaprison only 1.77058E-14 U-238 decay const
URANIUM234 2.45E+05 2.14E+09 3.24E-10 3.71407E-10 Tc-99 decay const
URANIUM235 7.04E+08 6.17E+12 1.12E-13 Part 20 table 2 soluble forms URANIUM238 4.47E+09 3.91E+13 1.77E-14 Dose Conversion 0.99999999223 U-234 exp(-t-p)
TC-99 2.13E+05 1.87E+09 3.71E-10 uCi/ml milliters uCi pCi mRem mRem/pCi 1.00000000000 U-235 exp(-t-p)
U-234 3.00E-07 7.30E+05 2.19E-01 2.19E+05 50 2.28E-04 1.00000000000 U-238 exp(-t-p)
U-235 3.00E-07 7.30E+05 2.19E-01 2.19E+05 50 2.28E-04 0.99999999109 Tc-99 exp(-t-p)
U-238 3.00E-07 7.30E+05 2.19E-01 2.19E+05 50 2.28E-04 Tc-99 6.00E-05 7.30E+05 4.38E+01 4.38E+07 50 1.14E-06 Activity Released 3.425E-03 total uranium(CiQ ICRP 69 Comparison 2.813E-03 U-234 release fraCi Sv/Bq Rem/Bq mRem/pCi 1.289E-04 U-235 release fraCi 4.833E-04 U-238 release fraCi adult 5.00E-08 0.005 1.85E-04 1.124E-03 Tc-99 release fraCi infant 3.70E-07 0.037 1.37E-03 bone-adult 7.90E-07 0.079 2.92E-03 check U sum 0.00343 bioaccumulation factor BNWL-2075 2.35E-05 U-234 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 UC-11 1.00E-06 U-235 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 Methodology for Calculation of Radiation Doses 3.61E-06 U-238 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 in the Environs from Nuclear Fuel 3.77E-09 Tc-99 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 15 Cycle Facilities 2.81E-05 all nuclides sum of nuclides 2.46059 usage 1100*(usage*dilution)/flow 6.92E-05 mRem see regulatory guide 1.109 page 1.109-2 and 1.109-3 for formula and definition of terms.
O:\\Regulatory\\EH&S Operations\\Environment\\Environment 2018\\Annual\\2018 Liquid Effluent.xlsx Whole Body Dose from Liquid Effluent Pathways - Shoreline Deposits Whole Body 12 hr Usage by adult/yr U
see regulatory guide 1.109 page 1.109-40 table E-5, Recommended Values for U(ap) 31293 mixing - dilution Dilution at difuser M
Congaree Flow 9388 cubic feet/sec see Nureg-1118 Environmental Assessment for renewam SNM-1107 May 0.3 cubic ft/sec Average discharge F
Effluent Flow 3.00E-01 cubic feet/sec Sv/s:Bq/m^2 mrem/hr:pCi/m^2 9.86E-12 U-234 mRem*m^2/pCi*hr D
U-234 7.40E-19 9.86E-12 EPA FRG 12 Dose Coeff for exposure to contaminated ground surface 1.97E-09 U-235 mRem*m^2/pCi*hr D
U-235 1.48E-16 1.97E-09 7.34E-12 U-238 mRem*m^2/pCi*hr D
U-238 5.51E-19 7.34E-12 1.04E-12 Tc-99 mRem*m^2/pCi*hr D
Tc-99 7.80E-20 1.04E-12 12 hrs transit time t-p see regulatory guide 1.109 page 1.109-69 table E-15, Recommended Values 131040 hrs xposure time of sedime t-b page 1.109-68 t-i 3.24E-10 U-234 decay const
Nuclide T(1/2) yr T(1/2) hr
T(1/2) day 1.12404E-13 U-235 decay const
URANIUM234 2.45E+05 2.14E+09 3.24E-10 8.90E+07 1.77058E-14 U-238 decay const
URANIUM235 7.04E+08 6.17E+12 1.12E-13 2.56E+11 3.71407E-10 Tc-99 decay const
URANIUM238 4.47E+09 3.91E+13 1.77E-14 1.63E+12 TC-99 2.13E+05 1.87E+09 3.71E-10 7.75E+07 0.0000423980 U-234 exp(-t-p)*[1-exp(-t-b)]
0.0000000147 U-235 exp(-t-p)*[1-exp(-t-b)]
0.0000000023 U-238 exp(-t-p)*[1-exp(-t-b)]
0.0000486679 Tc-99 exp(-t-p)*[1-exp(-t-b)]
Activity Released 3.425E-03 total uranium(Ci)
Q 2.813E-03 U-234 release fraction Ci 1.289E-04 U-235 release fraction Ci 4.833E-04 U-238 release fraction Ci 1.124E-03 Tc-99 release fraction Ci check U sum 0.00343 1.05E-10 U-234 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 9.59E-10 U-235 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 1.34E-11 U-238 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 4.41E-12 Tc-99 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 1.08E-09 all nuclides sum of nuclides 28.121006 usage 110000*(usage*dilution*shore width factor)/flow 3.04E-08 mRem see regulatory guide 1.109 page 1.109-2 and 1.109-3 for formula and definition of terms.
see regulatory guide 1.109 page 1.109-15 table A-2,Shore width O:\\Regulatory\\EH&S Operations\\Environment\\Environment 2018\\Annual\\2018 Liquid Effluent.xlsx 2018 Isotopic Fractions Based on the plant nominal enrichment for 2018 Nuclide Average Specific Activity Weighted wt%
Ci/g Activity Activity U-234 0.04 6.220E-03 2.388E-06 85.16 U-235 4.40 2.160E-06 9.504E-08 3.39 U-238 95.57 3.360E-07 3.211E-07 11.45 Total 100.0 2.805E-06 100.00 O:\\Regulatory\\EH&SOperations\\Environment\\Environment2018\\Annual\\Gaseouseffluent2018.xlsx
Attachment 10 - Comply Results COMPLY: V1.6. 2/22/2019 1:35 40 CFR Part 61 National Emission Standards for Hazardous Air Pollutants REPORT ON COMPLIANCE WITH THE CLEAN AIR ACT LIMITS FOR RADIONUCLIDE EMISSIONS FROM THE COMPLY CODE - V1.6.
Prepared by:
Westinghouse Electric Company Columbia Fuel Fabrication Facility 5801 Bluff Rd. Hopkins, SC 29061 David Wagoner 803.647.1919 Prepared for:
U.S. Environmental Protection Agency Office of Radiation and Indoor Air Washington, DC 20460
2018 Annual Dose to the Public Due to Gaseous Effluents SCREENING LEVEL 2 DATA ENTERED:
RELEASE RATES FOR STACK 1.
Release Rate Nuclide (curies/SECOND)
U-234 Y 4.460E-13 U-235 Y 1.780E-14 U-238 Y 6.000E-14 RELEASE RATES FOR STACK 2.
Release Rate Nuclide (curies/SECOND)
U-234 Y 3.910E-13 U-235 Y 1.560E-14 U-238 Y 5.250E-14 RELEASE RATES FOR STACK 3.
Release Rate Nuclide (curies/SECOND)
U-234 Y 1.320E-12 U-235 Y 5.250E-14 U-238 Y 1.770E-13 RELEASE RATES FOR STACK 4.
Release Rate Nuclide (curies/SECOND)
U-234 Y 3.610E-12 U-235 Y 1.440E-13 U-238 Y 4.850E-13 RELEASE RATES FOR STACK 5.
Release Rate Nuclide (curies/SECOND)
U-234 Y 7.420E-13 U-235 Y 2.950E-14 U-238 Y 9.980E-14 RELEASE RATES FOR STACK 6.
Release Rate
Nuclide (curies/SECOND)
U-234 Y 1.560E-12 U-235 Y 6.220E-14 U-238 Y 2.100E-13 RELEASE RATES FOR STACK 7.
Release Rate Nuclide (curies/SECOND)
U-234 Y 8.520E-13 U-235 Y 3.390E-14 U-238 Y 1.150E-13 RELEASE RATES FOR STACK 8.
Release Rate Nuclide (curies/SECOND)
U-234 Y 1.020E-12 U-235 Y 4.050E-14 U-238 Y 1.370E-13 SITE DATA FOR STACK 1.
Release height 10 meters.
Building height 9 meters.
The source and receptor are not on the same building.
Distance from the source to the receptor is 595 meters.
Building width 137 meters.
SITE DATA FOR STACK 2.
Release height 11 meters.
Building height 9 meters.
The source and receptor are not on the same building.
Distance from the source to the receptor is 595 meters.
Building width 137 meters.
SITE DATA FOR STACK 3.
Release height 12 meters.
Building height 9 meters.
The source and receptor are not on the same building.
Distance from the source to the receptor is 595 meters.
Building width 137 meters.
SITE DATA FOR STACK 4.
Release height 13 meters.
Building height 9 meters.
The source and receptor are not on the same building.
Distance from the source to the receptor is 595 meters.
Building width 137 meters.
SITE DATA FOR STACK 5.
Release height 15 meters.
Building height 9 meters.
The source and receptor are not on the same building.
Distance from the source to the receptor is 595 meters.
Building width 137 meters.
SITE DATA FOR STACK 6.
Release height 16 meters.
Building height 9 meters.
The source and receptor are not on the same building.
Distance from the source to the receptor is 595 meters.
Building width 137 meters.
SITE DATA FOR STACK 7.
Release height 17 meters.
Building height 9 meters.
The source and receptor are not on the same building.
Distance from the source to the receptor is 595 meters.
Building width 137 meters.
SITE DATA FOR STACK 8.
Release height 18 meters.
Building height 9 meters.
The source and receptor are not on the same building.
Distance from the source to the receptor is 595 meters.
Building width 137 meters.
Default mean wind speed used (2.0 m/sec).
NOTES:
Input parameters outside the "normal" range:
Building (width) is unusually WIDE.
Receptor is unusually FAR.
RESULTS:
Effective dose equivalent: 0.2 mrem/yr.
- Comply at level 2.
This facility is in COMPLIANCE.
It may or may not be EXEMPT from reporting to the EPA.
You may contact your regional EPA office for more information.
- END OF COMPLIANCE REPORT **********
COMPLY: V1.6. 2/22/2019 1:49 40 CFR Part 61 National Emission Standards for Hazardous Air Pollutants REPORT ON COMPLIANCE WITH THE CLEAN AIR ACT LIMITS FOR RADIONUCLIDE EMISSIONS FROM THE COMPLY CODE - V1.6.
Prepared by:
Westinghouse Electric Company Columbia Fuel Fabrication Facility 5801 Bluff Rd. Hopkins, SC 29061 David Wagoner 803.647.1919 Prepared for:
U.S. Environmental Protection Agency Office of Radiation and Indoor Air Washington, DC 20460
Conv 1-A EX SCREENING LEVEL 2 DATA ENTERED:
Release Rate Nuclide (curies/SECOND)
U-234 Y 7.210E-13 U-235 Y 2.870E-14 U-238 Y 9.690E-14 Release height 16 meters.
Building height 9 meters.
The source and receptor are not on the same building.
Distance from the source to the receptor is 595 meters.
Building width 137 meters.
Default mean wind speed used (2.0 m/sec).
NOTES:
Input parameters outside the "normal" range:
Building (width) is unusually WIDE.
Receptor is unusually FAR.
RESULTS:
Effective dose equivalent: 1.4E-02 mrem/yr.
- Comply at level 2.
This facility is in COMPLIANCE.
It may or may not be EXEMPT from reporting to the EPA.
You may contact your regional EPA office for more information.
- END OF COMPLIANCE REPORT **********