ML23240A508

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Westinghouse Electric Company LLC - NRC Semi-Annual Discharge Report (January- June 2023)
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)
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Text

8) Westinghouse Page 1 of 2 Westinghouse Electric Company LLC Nuclear Fuel Columbia Fuel Site 5801 Bluff Road Hopkins, South Carolina 29061 USA Document Control Desk, Director Direct tel: 803-647-1000 Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 cc: USNRC, Region II Our ref: LTR-RAC-23-54 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, Georgia 30303-1257

Subject:

SNM-1107/70-1151 NRC Semi-Annual Discharge Report August28,2023 January - June 2023

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 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 Parameter Concentration emissions Measured Limit (uCi) Concentration Uranium (analyzed as 5 E- 14 µCi/ml Gaseous 121.4 9.0E- 17 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.
  1. 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: LTR-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, LTR-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:

LTR-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 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

© 2023 Westinghouse Electric Company LLC All Rights Reserved

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 Organ Dose - Bone Organ Dose - Lung (mrem/6 months) (mrem/6 months) (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 Review by: Anna Miller Radiation Safety Engineer Manager, RSO EH&S Operations EH&S Operations

Attachment 1 1st Half 2023 Gaseous Effluent Discharges Sampling Location Stack Height Gross Alpha Concentration* 1st Half (JanJun) Release Rate (Ci/s)

Station Description (m) (uCi/mL) uCi Uranium Released U234 U235 U238 1239 MAINT WELD EX 9 8.36E14 1.20 6.50E14 2.53E15 8.75E15 1223 CALC COMB GAS LN 2 10 3.88E13 0.96 5.20E14 2.03E15 7.00E15 1226 CALC COMB GAS LN 5 10 8.83E14 0.22 1.19E14 4.64E16 1.60E15 1230 DEV LAB EX #1 10 8.91E14 1.28 6.94E14 2.70E15 9.34E15 1247 HOT OIL RM EX 11 1.39E13 8.20 4.44E13 1.73E14 5.98E14 1206 NEW DECON ROOM 11 8.15E14 2.01 1.09E13 4.24E15 1.47E14 1221 DECON ROOM EX 11 1.11E13 2.38 1.29E13 5.02E15 1.74E14 1231 DEV LAB EX #2 11 9.03E14 1.30 7.04E14 2.74E15 9.48E15 1251 WATERGLASS SCR S1190 12 1.01E13 3.55 1.92E13 7.50E15 2.59E14 1217 CONV ENCL EX 4C 13 8.55E14 5.05 2.74E13 1.07E14 3.68E14 1218 CONV ENCL EX 4D 13 8.64E14 0.24 1.30E14 5.07E16 1.75E15 1219 CONV EMERG EX 4E 13 9.00E14 0.25 1.35E14 5.28E16 1.82E15 1250 ERBIA CHANGE ROOM 13 8.52E14 2.46 1.33E13 5.19E15 1.79E14 1207 MET LAB EXHAUST 13 8.52E14 0.72 3.90E14 1.52E15 5.25E15 1210 CONV 1A EX 13 1.13E13 6.84 3.71E13 1.44E14 4.99E14 1201 FURNACE EX LINE 1 13 8.06E14 3.38 1.83E13 7.14E15 2.47E14 1202 FURNACE EX LINE 2 13 8.00E14 3.38 1.83E13 7.14E15 2.47E14 1203 FURNACE EX LINE 3 13 8.01E14 3.32 1.80E13 7.01E15 2.42E14 1204 FURNACE EX LINE 4 13 8.04E14 3.38 1.83E13 7.14E15 2.47E14 1205 FURNACE EX LINE 5 13 8.01E14 3.38 1.83E13 7.14E15 2.47E14 1222 CALC COMB GAS LN 1 13 8.92E14 0.22 1.19E14 4.64E16 1.60E15 1224 CALC COMB GAS LN 3 13 9.77E14 0.24 1.30E14 5.07E16 1.75E15 1225 CALC COMB GAS LN 4 13 8.50E14 0.21 1.14E14 4.43E16 1.53E15 1237 ABF HOOD TORIT EX 13 8.14E14 1.75 9.48E14 3.69E15 1.28E14 1211 CONV 1B EX 13 8.58E14 0.26 1.41E14 5.49E16 1.90E15 1227 CHEM LAB EX #2 14 1.27E13 1.12 6.07E14 2.36E15 8.17E15 1229 HP LAB EX 14 8.07E14 0.72 3.90E14 1.52E15 5.25E15 1232 PELLET COMBINED EX 14 8.81E14 6.33 3.43E13 1.34E14 4.62E14 1233 SOLVENT EXT N EX 14 8.03E14 3.43 1.86E13 7.24E15 2.50E14 1234 SOLVENT EXT S EX 14 8.75E14 0.63 3.41E14 1.33E15 4.60E15 1244 AMMON FUME SCR 1008A 14 9.31E14 2.55 1.38E13 5.38E15 1.86E14 1209 SUPPL INCIN EX 15 8.45E14 1.20 6.50E14 2.53E15 8.75E15 1220 CHEM LAB FILT EX 15 8.04E14 6.79 3.68E13 1.43E14 4.95E14 1236 MAP COMBINED 15 8.80E14 3.72 2.02E13 7.85E15 2.71E14 1245 AMMON FUME SCR 1008B 15 9.24E14 0.13 7.04E15 2.74E16 9.48E16 1248 ERBIA FURNACE EX 16 8.43E14 10.47 5.67E13 2.21E14 7.64E14 1249 ERBIA SCRUBBER EX 16 8.16E14 5.38 2.92E13 1.14E14 3.92E14 1208 INCINERATOR EX 16 1.20E13 3.44 1.86E13 7.26E15 2.51E14 1212 S1030 A 17 8.79E14 9.62 5.21E13 2.03E14 7.02E14 1213 S1030 B 17 9.73E14 0.53 2.87E14 1.12E15 3.87E15 1238 IFBA EXHAUST 19 8.05E14 5.78 3.13E13 1.22E14 4.22E14 1241 PELLET LINE 6 20 8.07E14 3.41 1.85E13 7.20E15 2.49E14 Total 121.43 6.58E12 2.56E13 8.86E13

  • Concentration LLD is 8E14 uCi/mL O:\Regulatory\EH&S Operations\Environment\Environment 2023\Gaseous Effluent 1st half.xlsx

Attachment 2 Lung/Bone Organ Dose due to Gaseous Effluents 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 Release Rate (Ci/s)

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 O:\Regulatory\EH&S Operations\Environment\Environment 2023\Gaseous Effluent 1st half.xlsx

2023 Attachment 3 - 1st Half 2023 Liquid Effluent Discharges Tc-99 Isotopic Uranium Total uCi/month Released Measurement Uncertainty / Error Uncertainty / Error Liquid Effluent Discharges Measured Sum Measured Concentrations (based on monthly GEL discharge samples)

Concentrations U & Tc-99 Total Actual Actual U234 U235 U238 Total U Tc-99 U234 U235 U238 Tc-99 U234 U-235 U-238 Tc-99 Month U & Tc-99 U234 U-235 U-238 Tc-99 kgal/month gal/month pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L uCi uCi uCi uCi pCi/L 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 1359.8 uCi Uranium for 6-month period Milliliters (ml) 7.48E+10 (all types) 2391.8 uCi Uranium & Tc-99 for 6-month period FIRST HALF LIQUID DISCHARGES Quantity Average Concentration Radionuclide LLD (uCi/ml) Released Error Released (uCi/ml)

(uCi)

U234 6.00E-10 1084.1 +/- 103 1.45E-08 U235 6.00E-10 65.6 +/- 29 8.77E-10 U238 6.00E-10 210.2 +/- 46 2.81E-09 Total U 1359.8 1.82E-08 Tc-99 6.00E-10 1032.0 +/- 208 1.38E-08 Total (Jan-Jun) 2391.8 5.02E-08 NOTE: Values reported by GEL as "nondetect" with a U qualifier have been reported here at the value given, due to scattered MDCs.

O:\Regulatory\EH&S Operations\Environment\Environment 2023\liquid-effluent-2023-1.xlsx

Attachment 4 Whole Body Dose from Liquid Effluent Pathways - Potable Water Whole Body-Ingestion 5

365 liters Usage by adult/6 moU 10CFR20 7.3 x 10 (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/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 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

Attachment 5 Dose to the Bone Surface from Liquid Effluent Pathways - Potable Water Bone Surface-Ingestion 5

365 liters Usage by adult/6 m U 10CFR20 7.3 x 10 (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 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

Attachment 6 Whole Body Dose from Liquid Effluent Pathways - Aquatic Foods Whole Body 10.5 Kg Usage by adult/6 m 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 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

Attachment 7 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/pCi mRem/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 fra 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 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

Attachment 8 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

Attachment 9 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

Attachment 10 - COMPLY Results COMPLY: V1.7. 8/14/2023 2:31 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 V1.7.

Prepared by:

Westinghosue Electric Co.

Columbia Fuel Fabrication Facility 5801 Bluff Rd. Hopkins, SC 29061 David Wagoner 803.465.5088

Prepared for:

U.S. Environmental Protection Agency Office of Radiation and Indoor Air Washington, DC 20460 2023 SemiAnnual Dose to Public due to Gaseous Effluents

SCREENING LEVEL 2

DATA ENTERED:

RELEASE RATES FOR STACK 1.

Release Rate Nuclide (curies/SECOND)

U234 Y 6.500E14

U235 Y 2.530E15 U238 Y 8.750E15 RELEASE RATES FOR STACK 2.

Release Rate Nuclide (curies/SECOND)

U234 Y 1.330E13 U235 Y 5.190E15 U238 Y 1.790E14 RELEASE RATES FOR STACK 3.

Release Rate Nuclide (curies/SECOND)

U234 Y 7.530E13 U235 Y 2.930E14 U238 Y 1.010E13 RELEASE RATES FOR STACK 4.

Release Rate

Nuclide (curies/SECOND)

U234 Y 1.920E13 U235 Y 7.500E15 U238 Y 2.590E14 RELEASE RATES FOR STACK 5.

Release Rate Nuclide (curies/SECOND)

U234 Y 1.900E12 U235 Y 7.410E14 U238 Y 2.560E13 RELEASE RATES FOR STACK 6.

Release Rate Nuclide (curies/SECOND)

U234 Y 8.010E13 U235 Y 3.120E14 U238 Y 1.080E13

RELEASE RATES FOR STACK 7.

Release Rate Nuclide (curies/SECOND)

U234 Y 6.420E13 U235 Y 2.500E14 U238 Y 8.640E14 RELEASE RATES FOR STACK 8.

Release Rate Nuclide (curies/SECOND)

U234 Y 1.050E12 U235 Y 4.070E14 U238 Y 1.410E13 RELEASE RATES FOR STACK 9.

Release Rate Nuclide (curies/SECOND)

U234 Y 5.500E13

U235 Y 2.140E14 U238 Y 7.400E14 RELEASE RATES FOR STACK 10.

Release Rate Nuclide (curies/SECOND)

U234 Y 3.130E13 U235 Y 1.220E14 U238 Y 4.220E14 RELEASE RATES FOR STACK 11.

Release Rate Nuclide (curies/SECOND)

U234 Y 1.850E13 U235 Y 7.200E15 U238 Y 2.490E14 SITE DATA FOR STACK 1.

Release height 9 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 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 3.

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 4.

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 5.

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 6.

Release height 14 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 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 8.

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 9.

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 10.

Release height 19 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 11.

Release height 20 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: 0.1 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: V1.7. 8/14/2023 11:59 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 V1.7.

Prepared by:

Westinghouse Electric Co.

Columbia Fuel Fabrication Facility 5801 Bluff Rd. Hopkins, SC 29061 David Wagoner 803.465.5088

Prepared for:

U.S. Environmental Protection Agency Office of Radiation and Indoor Air Washington, DC 20460 ERBIA Furnace Ex

SCREENING LEVEL 2

DATA ENTERED:

Release Rate Nuclide (curies/SECOND)

U234 Y 5.670E13 U235 Y 2.210E14

U238 Y 7.640E14 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: 1.1E02 mrem/yr.

      • Comply at level 2.
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