ML23058A272
| ML23058A272 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 02/27/2023 |
| From: | Ferguson J Westinghouse, Westinghouse |
| To: | Office of Nuclear Material Safety and Safeguards, NRC/RGN-II, Document Control Desk |
| References | |
| LTR-RAC-23-19 | |
| Download: ML23058A272 (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 Semiannual Discharge Report July - December 2022
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-23-19 February 27, 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 July 1, 2022, through December 31, 2022, 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
&-month Discharge emissions Parameter Measured Concentration (UCO Concentration Limit Gaseous 124 Uranium (analyzed as 9.1 E*17 µCi/ml*
5 E*14 µCi/ml gross alpha) 1,033 U-234 Uquid 49 U-235 2.0E-08 µCi/ml 3 E*07 µCi/ml Effluent*
153 U-238 1,453 Tc-99 2.3E-08 µCi/ml 6 E*05 µCi/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 second half of 2022 was 6.30 E+10 milliliters {ml).
© 2023 Westinghouse Electric Company LLC All Rights Reserved
Page 2 of 2 Our ref: L TR-RAC-23-19 February 27, 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-23-13, "2022 Annual Assessment of Public Dose due to Liquid and Gaseous Effluents" is attached.
Sincer;J/4 (111~
Jeff Ferguson Manager, Environment, Health and Safety
Attachment:
LTR-EHS-23-13, "2022 Annual Assessment of Public Dose due to Liquid and Gaseous Effluents"
WestinghouseNonProprietaryClass3 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: February 20, 2023 cc: Jeff Ferguson, Patrick Donnelly, Nancy Parr, Anna Miller From: David Wagoner Your ref:
Ext: 1919 Our ref: LTR-EHS-23-13 Fax: 803.695.4158
Subject:
2022 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 #1208 (Incinerator 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
WestinghouseNonProprietaryClass3 Page 2 of 3 Our ref: LTR-EHS-23-13 February 20, 2023 boundary (595 meters) for a calendar year. 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 calendar year 2022:
337.8 µCi of Uranium in gaseous effluent
3,333 µCi of Uranium in liquid effluent
5,556 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 2022 resulted in a potential whole body dose of 0.16 mrem, 1.21 mrem to the lung, and 0.006 mrem to the bone for an individual present at the nearest site boundary. The estimated whole body dose is well below the 25 mrem annual dose limit and the 1 mrem ALARA goal for a member of the public.
Table 1. 2022 Annual Dose to the Public from Liquid and Gaseous Effluents Whole Body Dose (mrem)
Organ Dose - Bone (mrem)
Organ Dose - Lung (mrem)
Gaseous Effluents Direct inhalation*
0.16 4.58E-03 1.21 Liquid Effluents Potable Water 8.02E-05 1.17E-03 Aquatic Food (Fish) 4.87E-06 6.75E-05 Shoreline Deposition 3.19E-09 Total (mrem) 0.16 5.82E-03 1.21
- Assumes 80 % residence time
WestinghouseNonProprietaryClass3 Page 3 of 3 Our ref: LTR-EHS-23-13 February 20, 2023 There were no changes in source material and no release points were added or removed during calendar year 2022. In May of 2022 the instrument used to analyze gaseous effluent samples was upgraded from a Tennelec to an iMatic. Both instruments measure gross alpha however the iMatic is equipped with a high-resolution detector and software that excludes naturally occurring Radon-Thoron from the results. As a result, the reported gaseous effluent discharges have decreased because residual naturally occurring radioactivity is no longer included in the final results. This provides a more accurate estimate of gaseous effluent releases and the subsequent dose to the public.
The attachments below illustrate the method used to calculate each result listed in Table 1. :
2022 Gaseous Effluent Discharges :
Lung/Bone Organ Dose due to Gaseous Effluent :
2022 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 :
2022 Isotopic Fractions 0:
Comply Results David Wagoner, CHP Radiation Safety Engineer EH&S Operations Review by: Anna Miller Manager, RSO EH&S Operations 2022GaseousEffluentDischarges Sampling Location StackHeight GrossAlphaConcentration*
1stHalf(JanJun) 2ndHalf(JulyDec)
TotaluCi Station Description (m)
(uCi/mL)
Released U234 U235 U238 1239 MAINTWELDEX 9
1.06E13 1.72 1.36 3.08 8.32E14 3.24E15 1.12E14 1223 CALCCOMBGASLN2 10 2.45E13 0.47 0.77 1.24 3.35E14 1.31E15 4.51E15 1226 CALCCOMBGASLN5 10 1.20E13 0.39 0.21 0.60 1.62E14 6.32E16 2.18E15 1230 DEVLABEX#1 10 1.24E13 2.29 1.32 3.61 9.75E14 3.80E15 1.31E14 1247 HOTOILRMEX 11 1.70E13 11.18 9.2 20.38 5.51E13 2.15E14 7.41E14 1206 NEWDECONROOM 11 8.77E14 2.39 2.03 4.42 1.19E13 4.65E15 1.61E14 1221 DECONROOMEX 11 2.06E13 6.54 2.43 8.97 2.42E13 9.44E15 3.26E14 1231 DEVLABEX#2 11 1.50E13 2.88 1.49 4.37 1.18E13 4.60E15 1.59E14 1251 WATERGLASSSCRS1190 12 1.69E13 7.52 4.59 12.11 3.27E13 1.27E14 4.40E14 1217 CONVENCLEX4C 13 9.64E14 5.96 5.57 11.53 3.12E13 1.21E14 4.19E14 1218 CONVENCLEX4D 13 1.27E13 0.46 0.26 0.72 1.95E14 7.58E16 2.62E15 1219 CONVEMERGEX4E 13 1.44E13 0.55 0.27 0.82 2.22E14 8.63E16 2.98E15 1250 ERBIACHANGEROOM 13 8.08E14 2.35 2.35 4.70 1.27E13 4.95E15 1.71E14 1207 METLABEXHAUST 13 1.40E13 1.60 0.81 2.41 6.51E14 2.54E15 8.77E15 1210 CONV1AEX 13 1.44E13 11.63 6.05 17.68 4.78E13 1.86E14 6.43E14 1201 FURNACEEXLINE1 13 8.07E14 3.45 3.46 6.91 1.87E13 7.27E15 2.51E14 1202 FURNACEEXLINE2 13 8.06E14 3.43 3.46 6.89 1.86E13 7.25E15 2.51E14 1203 FURNACEEXLINE3 13 8.42E14 3.70 3.5 7.20 1.95E13 7.58E15 2.62E14 1204 FURNACEEXLINE4 13 8.02E14 3.38 3.45 6.83 1.85E13 7.19E15 2.48E14 1205 FURNACEEXLINE5 13 8.01E14 3.42 3.42 6.84 1.85E13 7.20E15 2.49E14 1222 CALCCOMBGASLN1 13 8.42E14 0.22 0.2 0.42 1.13E14 4.42E16 1.53E15 1224 CALCCOMBGASLN3 13 9.73E14 0.24 0.25 0.49 1.32E14 5.16E16 1.78E15 1225 CALCCOMBGASLN4 13 9.02E14 0.24 0.21 0.45 1.22E14 4.74E16 1.64E15 1237 ABFHOODTORITEX 13 8.60E14 1.85 1.9 3.75 1.01E13 3.95E15 1.36E14 1211 CONV1BEX 13 1.39E13 0.56 0.29 0.85 2.30E14 8.95E16 3.09E15 1227 CHEMLABEX#2 14 2.46E13 3.18 1.26 4.44 1.20E13 4.67E15 1.61E14 1229 HPLABEX 14 8.32E14 0.76 0.73 1.49 4.03E14 1.57E15 5.42E15 1232 PELLETCOMBINEDEX 14 8.32E14 6.17 5.94 12.11 3.27E13 1.27E14 4.40E14 1233 SOLVENTEXTNEX 14 8.28E14 3.59 3.62 7.21 1.95E13 7.59E15 2.62E14 1234 SOLVENTEXTSEX 14 1.33E13 1.25 0.7 1.95 5.27E14 2.05E15 7.09E15 1244 AMMONFUMESCR1008A 14 1.01E13 3.08 2.51 5.59 1.51E13 5.88E15 2.03E14 1209 SUPPLINCINEX 15 1.30E13 2.55 1.22 3.77 1.02E13 3.97E15 1.37E14 1220 CHEMLABFILTEX 15 8.35E14 7.33 6.97 14.30 3.86E13 1.51E14 5.20E14 1236 MAPCOMBINED 15 1.11E13 5.40 4.13 9.53 2.57E13 1.00E14 3.47E14 1245 AMMONFUMESCR1008B 15 1.39E13 0.24 0.14 0.38 1.03E14 4.00E16 1.38E15 1248 ERBIAFURNACEEX 16 8.00E14 9.99 10.05 20.04 5.41E13 2.11E14 7.29E14 1249 ERBIASCRUBBEREX 16 8.05E14 5.36 5.31 10.67 2.88E13 1.12E14 3.88E14 1208 INCINERATOREX 16 1.08E12 59.56 3.71 63.27 1.71E12 6.66E14 2.30E13 1212 S1030A 17 1.14E13 15.99 9.33 25.32 6.84E13 2.67E14 9.21E14 1213 S1030B 17 1.38E13 0.98 0.55 1.53 4.13E14 1.61E15 5.56E15 1238 IFBAEXHAUST 19 8.00E14 5.84 5.81 11.65 3.15E13 1.23E14 4.24E14 1241 PELLETLINE6 20 8.49E14 3.57 3.66 7.23 1.95E13 7.61E15 2.63E14 Total 213.26 124.49 337.75 9.13E12 3.56E13 1.23E12
- ConcentrationLLDis8E14uCi/mL ReleaseRate(Ci/s) uCiUraniumReleased O:\\Regulatory\\EH&SOperations\\Environment\\Environment2022\\Annual\\Gaseouseffluent2022.xlsx 2022GaseousEffluentDischarges Building Nearest Ht Width Receptor Meter MeterMeter Height (m U234 U235 U238 9
8.32E14 3.24E15 1.12E14 9
137 595 10 1.47E13 5.74E15 1.98E14 9
137 595 11 1.03E12 4.02E14 1.39E13 9
137 595 12 3.27E13 1.27E14 4.40E14 9
137 595 13 2.12E12 8.26E14 2.85E13 9
137 595 14 8.86E13 3.45E14 1.19E13 9
137 595 15 7.56E13 2.95E14 1.02E13 9
137 595 16 2.54E12 9.89E14 3.42E13 9
137 595 17 7.25E13 2.83E14 9.77E14 9
137 595 19 3.15E13 1.23E14 4.24E14 9
137 595 20 1.95E13 7.61E15 2.63E14 9
137 595 Ci/s O:\\Regulatory\\EH&SOperations\\Environment\\Environment2022\\Annual\\Gaseouseffluent2022.xlsx Lung/BoneOrganDoseduetoGaseousEffluents 1st half (Jan-Jun) 2nd half (Jul-Dec)
Total EPA STACK IDENTIFICATION uCi Uranium uCi Uranium uCi released Comply Run Results Incinerator Ex 59.56 3.71 63.27 Dose (mrem/yr) 3.40E-02 use highest release to calculate X/Q used by COMPLY Stack height (m) 16 U-234 U-235 U-238 Dose from comply 0.03400 mrem/yr 1.71E-12 6.66E-14 2.30E-13 release quantity 63.27 uCi 6.33E-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 85.21%
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) 1.62E-05 X/Q Estimate Lung Dose using X/Q and annual releases for 2022 Estimate Bone Dose using X/Q and annual releases for 2022 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 337.75 uCi/yr 337.75 uCi/yr 3.38E-04 Ci/yr 3.38E-04 Ci/yr Lung
- 1.21 mrem/yr Bone
- 4.58E-03 mrem/yr assume 80% residence Release Rate (Ci/s)
O:\\Regulatory\\EH&SOperations\\Environment\\Environment2022\\Annual\\Gaseouseffluent2022.xlsx
2022 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 2752.693 2,752,693 17.2 1.36 2.77 21 14 35 179 14 29 146 2.01 0.644 0.820 2.49 21 7
9 26 February 2883.249 2,883,249 16.0 0.723 2.44 19 15 34 175 8
27 165 1.52 0.372 0.596 6.45 17 4
7 70 March 2957.058 2,957,058 26.1 1.15 4.65 32 7
39 292 13 52 79 1.82 0.440 0.775 2.36 20 5
9 26 April 2042.303 2,042,303 23.2 1.27 4.65 29 134 163 179 10 36 1036 1.70 0.450 0.765 6.26 13 3
6 48 May 2927.395 2,927,395 34.0 1.25 6.17 41 157 198 377 14 68 1740 2.04 0.442 0.873 6.96 23 5
10 77 June 2428.678 2,428,678 56.4 2.93 8.73 68 102 170 518 27 80 938 2.92 0.750 1.16 4.74 27 7
11 44 July 3267.386 3,267,386 23.5 1.16 3.58 28 49 77 291 14 44 604 1.98 0.503 0.781 3.12 24 6
10 39 August 2968.522 2,968,522 15.3 0.676 2.10 18 21 39 172 8
24 231 1.39 0.343 0.552 3.28 16 4
6 37 September 2794.735 2,794,735 11.0 0.364 1.45 13 17 30 116 4
15 181 1.09 0.235 0.415 2.76 12 2
4 29 October 2847.662 2,847,662 8.88 0.461 1.74 11 17 28 96 5
19 179 1.07 0.291 0.487 2.95 12 3
5 32 November 2588.582 2,588,582 11.0 0.516 1.56 13 19 32 108 5
15 184 1.35 0.346 0.518 2.71 13 3
5 27 December 2166.044 2,166,044 30.6 1.59 4.32 37 9
46 251 13 35 74 2.21 0.568 0.837 2.95 18 5
7 24 Total 32624.307 32,624,307 2754 134 445 5556 215 55 87 479 Liters (L) 1.23E+08 Milliliters (ml) 1.23E+11 ANNUAL LIQUID DISCHARGES Radionuclide Quantity Released (uCi)
U234 2754
+/-
215 U235 134
+/-
55 U238 445
+/-
87 Total U 3333 Tc-99 5556
+/-
479 Total 8889 Uncertainty / Error Total uCi/month Released (based on monthly GEL discharge samples)
LLD (uCi/ml)
Liquid Effluent Discharges 2022 ANNUAL LIQUID EFFLUENT RADIOACTIVITY DISCHARGES 4.50E-08 7.20E-08 Measurement Uncertainty / Error 3333 uCi Uranium Isotopic Uranium Measured Concentrations 8889 uCi Uranium & Tc-99 6.00E-10 6.00E-10 6.00E-10 6.00E-10 Average Concentration Released (uCi/ml)
Error 2.23E-08 1.09E-09 3.60E-09 2.70E-08 O:\\Regulatory\\EH&S Operations\\Environment\\Environment 2022\\Annual\\liquid-effluent-2022-2.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 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 2.754E-03 U-234 release fraction Ci ICRP 69 Comparison 1.340E-04 U-235 release fraction Ci 4.450E-04 U-238 release fraction Ci Sv/Bq Rem/Bq mRem/pCi 5.556E-03 Tc-99 release fraction Ci adult 5.00E-08 0.005 1.85E-04 check U sum 0.00333 infant 3.70E-07 0.037 1.37E-03 bone-adult 7.90E-07 0.079 2.92E-03 7.81E-07 U-234 release fraction *dose factor*exp(-*tp) 3.56E-08 U-235 release fraction *dose factor*exp(-*tp) 1.13E-07 U-238 release fraction *dose factor*exp(-*tp) 8.12E-09 Tc-99 release fraction *dose factor*exp(-*tp) 9.38E-07 all nuclides sum of nuclides 85.53473 usage 1100*(usage*dilution)/flow 8.02E-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 2022\\Annual\\liquid-effluent-2022-2.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/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 2.754E-03 U-234 release fraction Ci Sv/Bq Rem/Bq mRem/pCi 1.340E-04 U-235 release fraction Ci 4.450E-04 U-238 release fraction Ci adult 5.00E-08 0.005 1.85E-04 5.556E-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 0.00333 1.15E-05 U-234 release fraction *dose factor*exp(-*tp) 5.21E-07 U-235 release fraction *dose factor*exp(-*tp) 1.66E-06 U-238 release fraction *dose factor*exp(-*tp) 1.24E-09 Tc-99 release fraction *dose factor*exp(-*tp) 1.37E-05 all nuclides sum of nuclides 85.53473 usage 1100*(usage*dilution)/flow 1.17E-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 2022\\Annual\\liquid-effluent-2022-2.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 ICRP 69 Comparison 2.754E-03 U-234 release fraction Ci 1.340E-04 U-235 release fraction Ci Sv/Bq Rem/Bq mRem/pCi 4.450E-04 U-238 release fraction Ci 5.556E-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 0.00333 bone-adult 7.90E-07 0.079 2.92E-03 bioaccumulation factor BNWL-2075 1.56E-06 U-234 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 UC-11 7.13E-08 U-235 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 Methodology for Calculation of Radiation Doses 2.27E-07 U-238 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 in the Environs from Nuclear Fuel 1.22E-07 Tc-99 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 15 Cycle Facilities 1.98E-06 all nuclides sum of nuclides 2.46059 usage 1100*(usage*dilution)/flow 4.87E-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 2022\\Annual\\liquid-effluent-2022-2.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 ICRP 69 Comparison 2.754E-03 U-234 release fraCi Sv/Bq Rem/Bq mRem/pCi 1.340E-04 U-235 release fraCi 4.450E-04 U-238 release fraCi adult 5.00E-08 0.005 1.85E-04 5.556E-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 0.00333 bioaccumulation factor BNWL-2075 2.30E-05 U-234 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 UC-11 1.04E-06 U-235 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 Methodology for Calculation of Radiation Doses 3.33E-06 U-238 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 in the Environs from Nuclear Fuel 1.86E-08 Tc-99 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 15 Cycle Facilities 2.74E-05 all nuclides sum of nuclides 2.46059 usage 1100*(usage*dilution)/flow 6.75E-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 2022\\Annual\\liquid-effluent-2022-2.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 3.23557E-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 2.754E-03 U-234 release fraction Ci 1.340E-04 U-235 release fraction Ci 4.450E-04 U-238 release fraction Ci 5.556E-03 Tc-99 release fraction Ci check U sum 0.00333 1.02E-10 U-234 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 9.97E-10 U-235 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 1.23E-11 U-238 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 2.18E-11 Tc-99 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 1.13E-09 all nuclides sum of nuclides 2.812101 usage 11000*(usage*dilution*shore width factor)/flow 3.19E-09 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 2022\\Annual\\liquid-effluent-2022-2.xlsx 2022 Isotopic Fractions Based on the plant nominal enrichment for 2022 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 9.310E-08 3.32 U-238 95.66 3.360E-07 3.214E-07 11.47 Total 100.0 2.803E-06 100.00 O:\\Regulatory\\EH&S Operations\\Environment\\Environment 2022\\Annual\\liquid-effluent-2022-2.xlsx
COMPLY:V1.7.
2/20/20232:59 40CFRPart61 NationalEmissionStandards forHazardousAirPollutants REPORTONCOMPLIANCEWITH THECLEANAIRACTLIMITSFORRADIONUCLIDEEMISSIONS FROMTHECOMPLYCODEV1.7.
Preparedby:
WestinghouseElectricCo.
ColumbiaFuelFabricationFacility 5801BluffRd.Hopkins,SC29061 DavidWagoner 803.647.1919 Preparedfor:
U.S.EnvironmentalProtectionAgency OfficeofRadiationandIndoorAir Washington,DC20460 0 - Comply Results
2022AnnualDosetoPublicduetoGaseousEffluents
SCREENINGLEVEL2
DATAENTERED:
RELEASERATESFORSTACK1.
ReleaseRate Nuclide(curies/SECOND)
U234Y8.320E14 U235Y3.240E15 U238Y1.120E14 RELEASERATESFORSTACK2.
ReleaseRate Nuclide(curies/SECOND)
U234Y1.470E13 U235Y5.740E15 U238Y1.980E14 RELEASERATESFORSTACK3.
ReleaseRate Nuclide(curies/SECOND)
U234Y1.030E12 U235Y4.020E14 U238Y1.390E13 RELEASERATESFORSTACK4.
ReleaseRate Nuclide(curies/SECOND)
U234Y3.270E13 U235Y1.270E14 U238Y4.400E14
RELEASERATESFORSTACK5.
ReleaseRate Nuclide(curies/SECOND)
U234Y2.120E12 U235Y8.260E14 U238Y2.850E13
RELEASERATESFORSTACK6.
ReleaseRate Nuclide(curies/SECOND)
U234Y8.860E13 U235Y3.450E14 U238Y1.190E13
RELEASERATESFORSTACK7.
ReleaseRate Nuclide(curies/SECOND)
U234Y7.560E13 U235Y2.950E14 U238Y1.020E13
RELEASERATESFORSTACK8.
ReleaseRate Nuclide(curies/SECOND)
U234Y2.540E12 U235Y9.890E14 U238Y3.420E13
RELEASERATESFORSTACK9.
ReleaseRate Nuclide(curies/SECOND)
U234Y7.250E13 U235Y2.830E14 U238Y9.770E14
RELEASERATESFORSTACK10.
ReleaseRate Nuclide(curies/SECOND)
U234Y3.150E13 U235Y1.230E14 U238Y4.240E14 RELEASERATESFORSTACK11.
ReleaseRate Nuclide(curies/SECOND)
U234Y1.950E13 U235Y7.610E15 U238Y2.630E14 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:0.2mrem/yr.
- Complyatlevel2.
ThisfacilityisinCOMPLIANCE.
ItmayormaynotbeEXEMPTfromreportingtotheEPA.
YoumaycontactyourregionalEPAofficeformoreinformation.
- ENDOFCOMPLIANCEREPORT**********
COMPLY:V1.7.
2/20/20234:07 40CFRPart61 NationalEmissionStandards forHazardousAirPollutants REPORTONCOMPLIANCEWITH THECLEANAIRACTLIMITSFORRADIONUCLIDEEMISSIONS FROMTHECOMPLYCODEV1.7.
Preparedby:
WestinghouseElectricCo.
ColumbiaFuelFabricationFacility 5801BluffRd.Hopkins,SC29061 DavidWagoner 803.647.1919 Preparedfor:
U.S.EnvironmentalProtectionAgency OfficeofRadiationandIndoorAir Washington,DC20460
IncineratorEx
SCREENINGLEVEL2
DATAENTERED:
ReleaseRate Nuclide(curies/SECOND)
U234Y1.710E12 U235Y6.660E14 U238Y2.300E13
Releaseheight16meters.
Buildingheight9meters.
Thesourceandreceptorarenotonthesamebuilding.
Distancefromthesourcetothereceptoris595meters.
Buildingwidth137meters.
Defaultmeanwindspeedused(2.0m/sec).
NOTES:
Inputparametersoutsidethe"normal"range:
Building(width)isunusuallyWIDE.
ReceptorisunusuallyFAR.
RESULTS:
Effectivedoseequivalent:3.4E02mrem/yr.
- Complyatlevel2.
ThisfacilityisinCOMPLIANCE.
ItmayormaynotbeEXEMPTfromreportingtotheEPA.
YoumaycontactyourregionalEPAofficeformoreinformation.
- ENDOFCOMPLIANCEREPORT**********