ML23240A508
| ML23240A508 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 08/28/2023 |
| From: | Ferguson J Westinghouse |
| To: | Office of Nuclear Material Safety and Safeguards, NRC/RGN-II, Document Control Desk |
| References | |
| LTR-RAC-23-54 | |
| Download: ML23240A508 (1) | |
Text
8) Westinghouse Document Control Desk, Director Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 cc:
USNRC, Region II 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, Georgia 30303-1257
Subject:
SNM-1107/70-1151 NRC Semi-Annual Discharge Report January - June 2023
Dear Sir:
Page 1 of 2 Westinghouse Electric Company LLC Nuclear Fuel Columbia Fuel Site 5801 Bluff Road Hopkins, South Carolina 29061 USA Direct tel: 803-647-1000 Our ref: L TR-RAC-23-54 August28,2023 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 of January 1, 2023, through June 30, 2023, the following quantities of radionuclides were released to the unrestricted area by the Westinghouse Electric Company's Columbia, South Carolina Nuclear Fuel Plant:
Total Total Regulatory 6-month 6-month Discharge emissions Parameter Measured Concentration (uCi)
Concentration Limit Gaseous 121.4 Uranium (analyzed as 9.0E-17 µCi/ml*
5 E-14 µCi/ml Qross alpha) 1,084 U-234 Liquid 66 U-235 1.SE-08 µCi/ml 3 E-07 µCi/ml Effluent#
210 U-238 1,032 Tc-99 1.4E-08 µCi/ml 6 E-05 uCi/ml
- Includes a dispersion factor of 1000 to account for dilution between the release point and the nearest site boundary.
- Sum of fractions (SOF) equates to less than 1.0.
As shown above, the effluent releases are within the NRC's regulatory limits designed to protect 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 (85.21 % U-234, 3.32% U-235, and 11.47% U-238). Tc-99 is not reported for gaseous effluents as the quantities of Tc-99 detected during benchmark testing of gaseous emissions were below the thresholds that would necessitate reporting.
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 first half of 2023 was 7.48 E+ 10 milliliters (ml).
({::J 2023 Westinghouse Electric Company LLC All Rights Reserved
Page 2 of 2 Our ref: L TR-RAC-23-54 August 28, 2023 Calculated values have been reported for all results, due to variability of minimum detection concentrations (MDC). Negative values are reported as zero.
To meet the requested dosage information outlined in Regulatory Guide 4.16, Section 6.1, L TR-EHS-23-43, "2023 Semi-Annual Assessment of Public Dose due to Liquid and Gaseous Effluents" is attached.
Sincerely, Je£t1r-Manager, Environment, Health and Safety
Attachment:
L TR-EHS-23-43, "2023 Semi-Annual Assessment of Public Dose due to Liquid and Gaseous Effluents"
Westinghouse Non-Proprietary Class 3 Page 1 of 3 Westinghouse Electric Company Nuclear Fuel Columbia Fuel Site 5801 Bluff Rd Hopkins, South Carolina 29061 USA
© 2023 Westinghouse Electric Company LLC All Rights Reserved To: Diana Joyner Date: August 14, 2023 cc: Jeff Ferguson, Stephen Subosits, Nancy Parr, Anna Miller From: David Wagoner Your ref:
Ext: 1919 Our ref: LTR-EHS-23-43 Fax: 803.695.4158
Subject:
2023 Semi-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 models developed by the NRC and EPA to estimate the potential dose to the public.
The whole body and organ dose via the following pathways is determined in this assessment:
Dose due to Gaseous Effluents by Direct Inhalation The whole body dose was estimated using EPAs COMPLY Code at level 2 complexity.
The organ dose was estimated by calculating the X/Q factor using the results of the COMPLY analysis for stack #1248 (ERBIA Furnace Exh), 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 Estimated using equations and recommended values in Regulatory Guide 1.109, Doses from Liquid Effluent Pathways (RG 1.109). Dose conversion factors are referenced from FGR 11.
Dose due to Liquid Effluents by Ingestion of Fish Estimated using equations and recommended values in RG 1.109. Dose conversion factors are referenced from FGR 11.
Dose due to Liquid Effluents by Irradiation from Shoreline Deposition Estimated using equations and recommended values in RG 1.109. Dose conversion factors are referenced from Federal Guidance report No 12, External Exposure to Radionuclides in Air, Water, and Soil.
Bounding dose assessments for direct inhalation and for ingestion are performed using conservative assumptions to determine the maximum potential dose to a hypothetical individual member of the public. The inhalation dose is determined for the hypothetical individual standing at the nearest site
Westinghouse Non-Proprietary Class 3 Page 2 of 3 Our ref: LTR-EHS-23-43 August 14, 2023 boundary (595 meters) for six months. The ingestion dose from liquid effluent and external dose from sediment deposition is determined at the point at which the liquid effluent leaves the diffuser in the Congaree River.
The release rates for gaseous effluent are determined by gross alpha measurements performed on daily air samples, one per stack for 42 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 the 1st half of calendar year 2023:
121.4 µCi of Uranium in gaseous effluent 1,360 µCi of Uranium in liquid effluent 1,032 µCi 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 the 1st half of 2023 resulted in a potential whole body dose of 0.04 mrem, 0.42 mrem to the lung, and 0.002 mrem to the bone for an individual present at the nearest site boundary. The estimated whole body dose is well below the 12.5 mrem annual dose limit (1/2 of the 25 mrem annual dose limit) and the 0.5 mrem ALARA goal (1/2 of 1 mrem annual ALARA goal) for a member of the public.
Table 1. 2023 Semi-Annual Dose to the Public from Liquid and Gaseous Effluents Whole Body Dose (mrem/6 months)
Organ Dose - Bone (mrem/6 months)
Organ Dose - Lung (mrem/6 months)
Gaseous Effluents Direct inhalation*
0.04 1.61E-03 0.42 Liquid Effluents Potable Water 1.62E-05 2.38E-04 Aquatic Food (Fish) 9.58E-07 1.37E-05 Shoreline Deposition 7.57E-10 Total (mrem/6 months) 0.04 1.86E-03 0.42
- Assumes 80 % residence time There were no changes in source material and no release points were added or removed during the 1st half of 2023. The attachments below illustrate the method used to calculate each result listed in Table 1. The annual dose calculation will be completed when the data is available for the entire calendar year.
Westinghouse Non-Proprietary Class 3 Page 3 of 3 Our ref: LTR-EHS-23-43 August 14, 2023 1st Half 2023 Gaseous Effluent Discharges :
Lung/Bone Organ Dose due to Gaseous Effluent :
1st Half 2023 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 :
2023 Isotopic Fractions 0:
Comply Results David Wagoner, CHP Radiation Safety Engineer EH&S Operations Review by: Anna Miller Manager, RSO EH&S Operations 1stHalf2023GaseousEffluentDischarges Sampling Location StackHeight GrossAlphaConcentration*
1stHalf(JanJun)
Station Description (m)
(uCi/mL) uCiUraniumReleased U234 U235 U238 1239 MAINTWELDEX 9
8.36E14 1.20 6.50E14 2.53E15 8.75E15 1223 CALCCOMBGASLN2 10 3.88E13 0.96 5.20E14 2.03E15 7.00E15 1226 CALCCOMBGASLN5 10 8.83E14 0.22 1.19E14 4.64E16 1.60E15 1230 DEVLABEX#1 10 8.91E14 1.28 6.94E14 2.70E15 9.34E15 1247 HOTOILRMEX 11 1.39E13 8.20 4.44E13 1.73E14 5.98E14 1206 NEWDECONROOM 11 8.15E14 2.01 1.09E13 4.24E15 1.47E14 1221 DECONROOMEX 11 1.11E13 2.38 1.29E13 5.02E15 1.74E14 1231 DEVLABEX#2 11 9.03E14 1.30 7.04E14 2.74E15 9.48E15 1251 WATERGLASSSCRS1190 12 1.01E13 3.55 1.92E13 7.50E15 2.59E14 1217 CONVENCLEX4C 13 8.55E14 5.05 2.74E13 1.07E14 3.68E14 1218 CONVENCLEX4D 13 8.64E14 0.24 1.30E14 5.07E16 1.75E15 1219 CONVEMERGEX4E 13 9.00E14 0.25 1.35E14 5.28E16 1.82E15 1250 ERBIACHANGEROOM 13 8.52E14 2.46 1.33E13 5.19E15 1.79E14 1207 METLABEXHAUST 13 8.52E14 0.72 3.90E14 1.52E15 5.25E15 1210 CONV1AEX 13 1.13E13 6.84 3.71E13 1.44E14 4.99E14 1201 FURNACEEXLINE1 13 8.06E14 3.38 1.83E13 7.14E15 2.47E14 1202 FURNACEEXLINE2 13 8.00E14 3.38 1.83E13 7.14E15 2.47E14 1203 FURNACEEXLINE3 13 8.01E14 3.32 1.80E13 7.01E15 2.42E14 1204 FURNACEEXLINE4 13 8.04E14 3.38 1.83E13 7.14E15 2.47E14 1205 FURNACEEXLINE5 13 8.01E14 3.38 1.83E13 7.14E15 2.47E14 1222 CALCCOMBGASLN1 13 8.92E14 0.22 1.19E14 4.64E16 1.60E15 1224 CALCCOMBGASLN3 13 9.77E14 0.24 1.30E14 5.07E16 1.75E15 1225 CALCCOMBGASLN4 13 8.50E14 0.21 1.14E14 4.43E16 1.53E15 1237 ABFHOODTORITEX 13 8.14E14 1.75 9.48E14 3.69E15 1.28E14 1211 CONV1BEX 13 8.58E14 0.26 1.41E14 5.49E16 1.90E15 1227 CHEMLABEX#2 14 1.27E13 1.12 6.07E14 2.36E15 8.17E15 1229 HPLABEX 14 8.07E14 0.72 3.90E14 1.52E15 5.25E15 1232 PELLETCOMBINEDEX 14 8.81E14 6.33 3.43E13 1.34E14 4.62E14 1233 SOLVENTEXTNEX 14 8.03E14 3.43 1.86E13 7.24E15 2.50E14 1234 SOLVENTEXTSEX 14 8.75E14 0.63 3.41E14 1.33E15 4.60E15 1244 AMMONFUMESCR1008A 14 9.31E14 2.55 1.38E13 5.38E15 1.86E14 1209 SUPPLINCINEX 15 8.45E14 1.20 6.50E14 2.53E15 8.75E15 1220 CHEMLABFILTEX 15 8.04E14 6.79 3.68E13 1.43E14 4.95E14 1236 MAPCOMBINED 15 8.80E14 3.72 2.02E13 7.85E15 2.71E14 1245 AMMONFUMESCR1008B 15 9.24E14 0.13 7.04E15 2.74E16 9.48E16 1248 ERBIAFURNACEEX 16 8.43E14 10.47 5.67E13 2.21E14 7.64E14 1249 ERBIASCRUBBEREX 16 8.16E14 5.38 2.92E13 1.14E14 3.92E14 1208 INCINERATOREX 16 1.20E13 3.44 1.86E13 7.26E15 2.51E14 1212 S1030A 17 8.79E14 9.62 5.21E13 2.03E14 7.02E14 1213 S1030B 17 9.73E14 0.53 2.87E14 1.12E15 3.87E15 1238 IFBAEXHAUST 19 8.05E14 5.78 3.13E13 1.22E14 4.22E14 1241 PELLETLINE6 20 8.07E14 3.41 1.85E13 7.20E15 2.49E14 Total 121.43 6.58E12 2.56E13 8.86E13
- ConcentrationLLDis8E14uCi/mL ReleaseRate(Ci/s)
O:\\Regulatory\\EH&SOperations\\Environment\\Environment2023\\GaseousEffluent1sthalf.xlsx Lung/BoneOrganDoseduetoGaseousEffluents 1st half (Jan-Jun) 2nd half (Jul-Dec)
Total EPA STACK IDENTIFICATION uCi Uranium uCi Uranium uCi released Comply Run Results ERBIA Furnace Ex 10.47 N/A 10.47 Dose (mrem/yr) 1.10E-02 use highest release to calculate X/Q used by COMPLY Stack height (m) 16 U-234 U-235 U-238 Dose from comply 0.00550 mrem/6 mo 5.67E-13 2.21E-14 7.64E-14 release quantity 10.47 uCi 1.05E-05 Ci App E table E-5 4000.00 m3/6 mo Effective Dose conversion EPA FGR 11 p150-151 U-234 3.58E-05 Sv/Bq 85.21%
U-235 3.32E-05 Sv/Bq 3.32%
U-238 3.20E-05 Sv/Bq 11.47%
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) 3.17E-05 X/Q Estimate Lung Dose using X/Q and semi-annual releases for 2023 Estimate Bone Dose using X/Q and semi-annual releases for 2023 App E table E-5 Lung Organ Dose conversion EPA FGR 11 p150-151 U-234 2.98E-04 Sv/Bq 85.21%
1.13E-06 Sv/Bq U-235 2.76E-04 Sv/Bq 3.32%
1.05E-06 Sv/Bq U-238 2.66E-04 Sv/Bq 11.47%
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 121.43 uCi/6 mo 121.43 uCi/6 mo 1.21E-04 Ci/6 mo 1.21E-04 Ci/6 mo Lung
- 0.42 mrem/6 mo Bone
- 1.61E-03 mrem/6 mo assume 80% residence Release Rate (Ci/s)
O:\\Regulatory\\EH&SOperations\\Environment\\Environment2023\\GaseousEffluent1sthalf.xlsx
2023 Tc-99 Measured Concentrations Sum U & Tc-99 Month Actual kgal/month Actual gal/month U234 pCi/L U235 pCi/L U238 pCi/L Total U pCi/L Tc-99 pCi/L Total U & Tc-99 pCi/L U234 U-235 U-238 Tc-99 U234 pCi/L U235 pCi/L U238 pCi/L Tc-99 pCi/L U234 uCi U-235 uCi U-238 uCi Tc-99 uCi January 3491.811 3,491,811 9.49 0.665 1.72 11.875 12.1 23.975 125.425 8.789 22.732 159.920 1.20 0.369 0.522 2.65 15.860 4.877 6.899 35.024 February 3415.569 3,415,569 14.3 1.03 2.61 17.94 9.45 27.39 184.869 13.316 33.742 122.169 1.53 0.471 0.659 2.60 19.780 6.089 8.520 33.613 March 3270.860 3,270,860 17.5 0.864 4.04 22.404 24.7 47.104 216.654 10.696 50.016 305.791 1.60 0.411 0.773 3.06 19.808 5.088 9.570 37.883 April 2834.219 2,834,219 16.9 1.04 2.98 20.92 7.62 28.54 181.295 11.157 31.968 81.744 1.43 0.405 0.606 2.54 15.340 4.345 6.501 27.248 May 3126.968 3,126,968 17.9 1.04 3.13 22.07 11.8 33.87 211.857 12.309 37.045 139.660 1.32 0.359 0.553 2.96 15.623 4.249 6.545 35.033 June 3609.918 3,609,918 12.0 0.680 2.54 15.22 16.3 31.52 163.962 9.291 34.705 222.716 1.19 0.323 0.549 2.85 16.260 4.413 7.501 38.941 Total (Jan-Jun) 19749.345 19,749,345 1084.062 65.558 210.209 1031.999 103 29 46 208 Liters (L) 7.48E+07 Milliliters (ml) 7.48E+10 FIRST HALF LIQUID DISCHARGES Radionuclide Quantity Released (uCi)
U234 1084.1
+/-
103 U235 65.6
+/-
29 U238 210.2
+/-
46 Total U 1359.8 Tc-99 1032.0
+/-
208 Total (Jan-Jun) 2391.8 NOTE: Values reported by GEL as "nondetect" with a U qualifier have been reported here at the value given, due to scattered MDCs.
1.45E-08 8.77E-10 2.81E-09 1.82E-08 - 1st Half 2023 Liquid Effluent Discharges 1.38E-08 5.02E-08 Measurement Uncertainty / Error 1359.8 uCi Uranium for 6-month period (all types)
Isotopic Uranium Measured Concentrations 2391.8 uCi Uranium & Tc-99 for 6-month period 6.00E-10 6.00E-10 6.00E-10 6.00E-10 Average Concentration Released (uCi/ml)
Error Uncertainty / Error Total uCi/month Released (based on monthly GEL discharge samples)
LLD (uCi/ml)
Liquid Effluent Discharges O:\\Regulatory\\EH&S Operations\\Environment\\Environment 2023\\liquid-effluent-2023-1.xlsx Whole Body Dose from Liquid Effluent Pathways - Potable Water Whole Body-Ingestion 365 liters Usage by adult/6 moU 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 for comaprison only URANIUM238 4.47E+09 3.91E+13 1.77E-14 0.9999999961 U-234 exp(-t-p)
TC-99 2.13E+05 1.87E+09 3.71E-10 Part 20 table 2 1.0000000000 U-235 exp(-t-p)
Dose Conversion soluble forms 1.0000000000 U-238 exp(-t-p) uCi/ml milliters uCi pCi mRem mRem/pCi 0.9999999955 Tc-99 exp(-t-p)
U-234 3.00E-07 7.30E+05 2.19E-01 2.19E+05 50 2.28E-04 U-235 3.00E-07 7.30E+05 2.19E-01 2.19E+05 50 2.28E-04 Activity Released 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 1.084E-03 U-234 release fraction Ci ICRP 69 Comparison 6.560E-05 U-235 release fraction Ci 2.102E-04 U-238 release fraction Ci Sv/Bq Rem/Bq mRem/pCi 1.032E-03 Tc-99 release fraction Ci adult 5.00E-08 0.005 1.85E-04 check U sum 0.00136 infant 3.70E-07 0.037 1.37E-03 bone-adult 7.90E-07 0.079 2.92E-03 3.07E-07 U-234 release fraction *dose factor*exp(-*tp) 1.75E-08 U-235 release fraction *dose factor*exp(-*tp) 5.35E-08 U-238 release fraction *dose factor*exp(-*tp) 1.51E-09 Tc-99 release fraction *dose factor*exp(-*tp) 3.80E-07 all nuclides sum of nuclides 42.76736 usage 1100*(usage*dilution)/flow 1.62E-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 2023\\liquid-effluent-2023-1.xlsx Dose to the Bone Surface from Liquid Effluent Pathways - Potable Water Bone Surface-Ingestion 365 liters Usage by adult/6 m 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/pCimRem/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 Part 20 table 2 3.71407E-10 Tc-99 decay const
URANIUM235 7.04E+08 6.17E+12 1.12E-13 Dose Conversion soluble forms URANIUM238 4.47E+09 3.91E+13 1.77E-14 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 ICRP 69 Comparison 1.084E-03 U-234 release fraction Ci Sv/Bq Rem/Bq mRem/pCi 6.560E-05 U-235 release fraction Ci 2.102E-04 U-238 release fraction Ci adult 5.00E-08 0.005 1.85E-04 1.032E-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 0.00136 4.53E-06 U-234 release fraction *dose factor*exp(-*tp) 2.55E-07 U-235 release fraction *dose factor*exp(-*tp) 7.86E-07 U-238 release fraction *dose factor*exp(-*tp) 2.31E-10 Tc-99 release fraction *dose factor*exp(-*tp) 5.57E-06 all nuclides sum of nuclides 42.76736 usage 1100*(usage*dilution)/flow 2.38E-04 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 2023\\liquid-effluent-2023-1.xlsx Whole Body Dose from Liquid Effluent Pathways - Aquatic Foods Whole Body 10.5 Kg Usage by adult/6 mU 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 ICRP 69 Comparison 1.084E-03 U-234 release fraction Ci 6.560E-05 U-235 release fraction Ci Sv/Bq Rem/Bq mRem/pCi 2.102E-04 U-238 release fraction Ci 1.032E-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 0.00136 bone-adult 7.90E-07 0.079 2.92E-03 bioaccumulation factor BNWL-2075 6.15E-07 U-234 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 UC-11 3.49E-08 U-235 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 Methodology for Calculation of Radiation Doses 1.07E-07 U-238 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 in the Environs from Nuclear Fuel 2.26E-08 Tc-99 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 15 Cycle Facilities 7.79E-07 all nuclides sum of nuclides 1.23029 usage 1100*(usage*dilution)/flow 9.58E-07 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 2023\\liquid-effluent-2023-1.xlsx Dose to the Bone Surface from Liquid Effluent Pathways - Aquatic Foods Bone Surface 10.5 Kg Usage by adult/6 mU 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 ICRP 69 Comparison 1.084E-03 U-234 release fraCi Sv/Bq Rem/Bq mRem/pCi 6.560E-05 U-235 release fraCi 2.102E-04 U-238 release fraCi adult 5.00E-08 0.005 1.85E-04 1.032E-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 0.00136 bioaccumulation factor BNWL-2075 9.07E-06 U-234 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 UC-11 5.10E-07 U-235 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 Methodology for Calculation of Radiation Doses 1.57E-06 U-238 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 in the Environs from Nuclear Fuel 3.46E-09 Tc-99 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 15 Cycle Facilities 1.11E-05 all nuclides sum of nuclides 1.23029 usage 1100*(usage*dilution)/flow 1.37E-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 2023\\liquid-effluent-2023-1.xlsx Whole Body Dose from Liquid Effluent Pathways - Shoreline Deposits Whole Body 6 hr Usage by adult/6 mo 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 198 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 3.23557E-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 1.084E-03 U-234 release fraction Ci 6.560E-05 U-235 release fraction Ci 2.102E-04 U-238 release fraction Ci 1.032E-03 Tc-99 release fraction Ci check U sum 0.00136 4.03E-11 U-234 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 4.88E-10 U-235 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 5.82E-12 U-238 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 4.05E-12 Tc-99 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 5.38E-10 all nuclides sum of nuclides 1.406050 usage 11000*(usage*dilution*shore width factor)/flow 7.57E-10 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 1.109-40 table A-2,Shore width O:\\Regulatory\\EH&S Operations\\Environment\\Environment 2023\\liquid-effluent-2023-1.xlsx 2023 Isotopic Fractions Based on the plant nominal enrichment for 2023 Nuclide Average Specific Activity Weighted wt%
Ci/g Activity Activity U-234 0.04 6.220E-03 2.388E-06 85.21 U-235 4.31 2.160E-06 9.307E-08 3.32 U-238 95.65 3.360E-07 3.214E-07 11.47 Total 100.0 2.803E-06 100.00 O:\\Regulatory\\EH&S Operations\\Environment\\Environment 2023\\liquid-effluent-2023-1.xlsx
COMPLY:V1.7.8/14/20232:31
40CFRPart61 NationalEmissionStandards forHazardousAirPollutants
REPORTONCOMPLIANCEWITH
THECLEANAIRACTLIMITSFORRADIONUCLIDEEMISSIONS
FROMTHECOMPLYCODEV1.7.
Preparedby:
WestinghosueElectricCo.
ColumbiaFuelFabricationFacility
5801BluffRd.Hopkins,SC29061
DavidWagoner
803.465.5088
0 - COMPLY Results
Preparedfor:
U.S.EnvironmentalProtectionAgency
OfficeofRadiationandIndoorAir
Washington,DC20460
2023SemiAnnualDosetoPublicduetoGaseousEffluents
SCREENINGLEVEL2
DATAENTERED:
RELEASERATESFORSTACK1.
ReleaseRate
Nuclide(curies/SECOND)
U234Y6.500E14
U235Y2.530E15
U238Y8.750E15
RELEASERATESFORSTACK2.
ReleaseRate
Nuclide(curies/SECOND)
U234Y1.330E13
U235Y5.190E15
U238Y1.790E14
RELEASERATESFORSTACK3.
ReleaseRate
Nuclide(curies/SECOND)
U234Y7.530E13
U235Y2.930E14
U238Y1.010E13
RELEASERATESFORSTACK4.
ReleaseRate
Nuclide(curies/SECOND)
U234Y1.920E13
U235Y7.500E15
U238Y2.590E14
RELEASERATESFORSTACK5.
ReleaseRate
Nuclide(curies/SECOND)
U234Y1.900E12
U235Y7.410E14
U238Y2.560E13
RELEASERATESFORSTACK6.
ReleaseRate
Nuclide(curies/SECOND)
U234Y8.010E13
U235Y3.120E14
U238Y1.080E13
RELEASERATESFORSTACK7.
ReleaseRate
Nuclide(curies/SECOND)
U234Y6.420E13
U235Y2.500E14
U238Y8.640E14
RELEASERATESFORSTACK8.
ReleaseRate
Nuclide(curies/SECOND)
U234Y1.050E12
U235Y4.070E14
U238Y1.410E13
RELEASERATESFORSTACK9.
ReleaseRate
Nuclide(curies/SECOND)
U234Y5.500E13
U235Y2.140E14
U238Y7.400E14
RELEASERATESFORSTACK10.
ReleaseRate
Nuclide(curies/SECOND)
U234Y3.130E13
U235Y1.220E14
U238Y4.220E14
RELEASERATESFORSTACK11.
ReleaseRate
Nuclide(curies/SECOND)
U234Y1.850E13
U235Y7.200E15
U238Y2.490E14
SITEDATAFORSTACK1.
Releaseheight9meters.
Buildingheight9meters.
Thesourceandreceptorarenotonthesamebuilding.
Distancefromthesourcetothereceptoris595meters.
Buildingwidth137meters.
SITEDATAFORSTACK2.
Releaseheight10meters.
Buildingheight9meters.
Thesourceandreceptorarenotonthesamebuilding.
Distancefromthesourcetothereceptoris595meters.
Buildingwidth137meters.
SITEDATAFORSTACK3.
Releaseheight11meters.
Buildingheight9meters.
Thesourceandreceptorarenotonthesamebuilding.
Distancefromthesourcetothereceptoris595meters.
Buildingwidth137meters.
SITEDATAFORSTACK4.
Releaseheight12meters.
Buildingheight9meters.
Thesourceandreceptorarenotonthesamebuilding.
Distancefromthesourcetothereceptoris595meters.
Buildingwidth137meters.
SITEDATAFORSTACK5.
Releaseheight13meters.
Buildingheight9meters.
Thesourceandreceptorarenotonthesamebuilding.
Distancefromthesourcetothereceptoris595meters.
Buildingwidth137meters.
SITEDATAFORSTACK6.
Releaseheight14meters.
Buildingheight9meters.
Thesourceandreceptorarenotonthesamebuilding.
Distancefromthesourcetothereceptoris595meters.
Buildingwidth137meters.
SITEDATAFORSTACK7.
Releaseheight15meters.
Buildingheight9meters.
Thesourceandreceptorarenotonthesamebuilding.
Distancefromthesourcetothereceptoris595meters.
Buildingwidth137meters.
SITEDATAFORSTACK8.
Releaseheight16meters.
Buildingheight9meters.
Thesourceandreceptorarenotonthesamebuilding.
Distancefromthesourcetothereceptoris595meters.
Buildingwidth137meters.
SITEDATAFORSTACK9.
Releaseheight17meters.
Buildingheight9meters.
Thesourceandreceptorarenotonthesamebuilding.
Distancefromthesourcetothereceptoris595meters.
Buildingwidth137meters.
SITEDATAFORSTACK10.
Releaseheight19meters.
Buildingheight9meters.
Thesourceandreceptorarenotonthesamebuilding.
Distancefromthesourcetothereceptoris595meters.
Buildingwidth137meters.
SITEDATAFORSTACK11.
Releaseheight20meters.
Buildingheight9meters.
Thesourceandreceptorarenotonthesamebuilding.
Distancefromthesourcetothereceptoris595meters.
Buildingwidth137meters.
Defaultmeanwindspeedused(2.0m/sec).
NOTES:
Inputparametersoutsidethe"normal"range:
Building(width)isunusuallyWIDE.
ReceptorisunusuallyFAR.
RESULTS:
Effectivedoseequivalent:0.1mrem/yr.
- Complyatlevel2.
ThisfacilityisinCOMPLIANCE.
ItmayormaynotbeEXEMPTfromreportingtotheEPA.
YoumaycontactyourregionalEPAofficeformoreinformation.
- ENDOFCOMPLIANCEREPORT**********
COMPLY:V1.7.8/14/202311:59
40CFRPart61 NationalEmissionStandards forHazardousAirPollutants
REPORTONCOMPLIANCEWITH
THECLEANAIRACTLIMITSFORRADIONUCLIDEEMISSIONS
FROMTHECOMPLYCODEV1.7.
Preparedby:
WestinghouseElectricCo.
ColumbiaFuelFabricationFacility
5801BluffRd.Hopkins,SC29061
DavidWagoner
803.465.5088
Preparedfor:
U.S.EnvironmentalProtectionAgency
OfficeofRadiationandIndoorAir
Washington,DC20460
ERBIAFurnaceEx
SCREENINGLEVEL2
DATAENTERED:
ReleaseRate
Nuclide(curies/SECOND)
U234Y5.670E13
U235Y2.210E14
U238Y7.640E14
Releaseheight16meters.
Buildingheight9meters.
Thesourceandreceptorarenotonthesamebuilding.
Distancefromthesourcetothereceptoris595meters.
Buildingwidth137meters.
Defaultmeanwindspeedused(2.0m/sec).
NOTES:
Inputparametersoutsidethe"normal"range:
Building(width)isunusuallyWIDE.
ReceptorisunusuallyFAR.
RESULTS:
Effectivedoseequivalent:1.1E02mrem/yr.
- Complyatlevel2.