ML25055A042

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Westinghouse Electric Company, LLC - NRC Semi-Annual Discharge Report (July-December 2024)
ML25055A042
Person / Time
Site: Westinghouse
Issue date: 02/19/2025
From: Ferguson J
Westinghouse
To:
Office of Nuclear Material Safety and Safeguards, NRC/RGN-II, Document Control Desk
References
LTR-RAC-25-12
Download: ML25055A042 (1)
v • d • e


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 July-December 2024

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-25-12 February 19, 2025 The following report fulfills regulatory requirements as listed in 1 0 CFR 40.65 and 1 0 CFR 70.59, "Effluent Monitoring Reporting Requirements." For the six-month period of July 1, 2024, through December 31, 2024, 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 (1,1Ci)

Concentration Limit Gaseous 132.2 Uranium (analyzed as 9.7 E-11 µCi/ml*

5 E-14 µCi/ml gross alpha) 1284 U-234 Liquid 53 U-235 1.97 E-08 µCi/ml 3 E-07 µCi/ml Effluent#

241 U-238 438 Tc-99 5.45 E-09 uCi/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 (85.17% U-234, 3.38% U-235, and 11.45% 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 2024 was 8.03 E+1o milliliters (ml).

© 2024 Westinghouse Electric Company LLC All Rights Reserved

Page 2 of 2 Our ref: L TR-RAC-25-12 February 19, 2025 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-25-07, "2024 Annual Assessment of Public Dose due to Liquid and Gaseous Effluents" is attached.

Sincerely, Jeff,!~

Manager, Environment, Health and Safety

Attachment:

L TR-EHS-25-07, "2024 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

© 2025 Westinghouse Electric Company LLC All Rights Reserved To: Diana Joyner Date: February 17, 2025 cc: Jeff Ferguson, Stephen Subosits, Nancy Parr, Anna Miller From: David Wagoner Your ref:

Phone: 803.465.5088 Our ref: LTR-EHS-25-07 Fax: 803.695.4158

Subject:

2024 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 #1247 (Hot Oil Room Ex), the measured release quantity, and the dose conversion factors from Federal Guidance Report No 11, Limiting Values of Radionuclide Intake and Air concentration Factors for Inhalation, Submersion, and Ingestion (FGR 11).

Dose due to Liquid Effluents by Ingestion of Potable Water 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-25-07 February 17, 2025 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 41 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 2024:

311.4 µCi of Uranium in gaseous effluent 4,248 µCi of Uranium in liquid effluent 1,048 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 2024 resulted in a potential whole body dose of 0.16 mrem, 1.10 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 0.5 mrem ALARA goal for a member of the public.

Table 1. 2024 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 4.16E-03 1.10 Liquid Effluents Potable Water 1.01E-04 1.49E-03 Aquatic Food (Fish) 5.88E-06 8.58E-05 Shoreline Deposition 3.99E-09 Total (mrem) 0.16 5.73E-03 1.10

  • Assumes 80 % residence time

Westinghouse Non-Proprietary Class 3 Page 3 of 3 Our ref: LTR-EHS-25-07 February 17, 2025 There were no changes in source material and no release points were added during 2024. The stack height for location #1230 and #1247 was increased by 8 and locations #1212 and #1213 were increased by 3 to support the gaseous effluent sample probe upgrade. One gaseous effluent release point was removed (sample location #1231, Dev Lab Ex #2). This system was no longer operational, so the fan, stack, and effluent sample were demolished. The attachments below illustrate the method used to calculate each result listed in Table 1. :

2024 Gaseous Effluent Discharges :

Lung/Bone Organ Dose due to Gaseous Effluent :

2024 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 :

2024 Isotopic Fractions 0:

Comply Results David Wagoner, CHP Radiation Safety Engineer EH&S Operations Review by: Anna Miller Manager, RSO EH&S Operations 2024 Gaseous Effluent Discharges Sampling Location Stack Height Gross Alpha Concentration*

1st Half (Jan-Jun) 2nd Half (Jan-Jun)

Total Station Description (m)

(uCi/mL) uCi Released U234 U235 U238 1239 MAINT WELD EX 9

1.09E-13 1.51 1.66 3.17 8.56E-14 3.40E-15 1.15E-14 1223 CALC COMB GAS LN 2 10 2.52E-13 1.03 0.26 1.29 3.48E-14 1.38E-15 4.68E-15 1226 CALC COMB GAS LN 5 10 1.47E-13 0.34 0.4 0.74 2.00E-14 7.93E-16 2.69E-15 1206 NEW DECON ROOM 11 8.06E-14 2.06 2.03 4.09 1.10E-13 4.38E-15 1.48E-14 1221 DECON ROOM EX 11 1.27E-13 2.66 2.89 5.55 1.50E-13 5.95E-15 2.02E-14 1231 DEV LAB EX #2 11 1.08E-13 1.65 0.99 2.64 7.13E-14 2.83E-15 9.59E-15 1251 WATERGLASS SCR S1190 12 1.38E-13 4.38 5.66 10.04 2.71E-13 1.08E-14 3.65E-14 1217 CONV ENCL EX 4-C 13 9.18E-14 5.71 5.36 11.07 2.99E-13 1.19E-14 4.02E-14 1218 CONV ENCL EX 4-D 13 8.99E-14 0.24 0.27 0.51 1.38E-14 5.47E-16 1.85E-15 1219 CONV EMERG EX 4E 13 8.73E-14 0.24 0.25 0.49 1.32E-14 5.25E-16 1.78E-15 1250 ERBIA CHANGE ROOM 13 8.20E-14 2.38 2.4 4.78 1.29E-13 5.12E-15 1.74E-14 1207 MET LAB EXHAUST 13 1.34E-13 0.93 1.37 2.30 6.21E-14 2.47E-15 8.35E-15 1210 CONV 1-A EX 13 1.22E-13 7.24 7.76 15.00 4.05E-13 1.61E-14 5.45E-14 1230 DEV LAB EX #1 13 9.97E-14 1.47 1.43 2.90 7.83E-14 3.11E-15 1.05E-14 1247 HOT OIL RM EX 13 4.03E-13 42.62 6.47 49.09 1.33E-12 5.26E-14 1.78E-13 1201 FURNACE EX LINE 1 13 8.11E-14 3.52 3.46 6.98 1.89E-13 7.48E-15 2.53E-14 1202 FURNACE EX LINE 2 13 8.04E-14 3.48 3.45 6.93 1.87E-13 7.43E-15 2.52E-14 1203 FURNACE EX LINE 3 13 8.02E-14 3.46 3.43 6.89 1.86E-13 7.38E-15 2.50E-14 1204 FURNACE EX LINE 4 13 8.01E-14 3.48 3.42 6.90 1.86E-13 7.40E-15 2.51E-14 1205 FURNACE EX LINE 5 13 8.10E-14 3.48 3.5 6.98 1.89E-13 7.48E-15 2.53E-14 1222 CALC COMB GAS LN 1 13 9.54E-14 0.22 0.27 0.49 1.32E-14 5.25E-16 1.78E-15 1224 CALC COMB GAS LN 3 13 1.23E-13 0.36 0.27 0.63 1.70E-14 6.75E-16 2.29E-15 1225 CALC COMB GAS LN 4 13 8.33E-14 0.21 0.21 0.42 1.13E-14 4.50E-16 1.52E-15 1237 ABF HOOD TORIT EX 13 8.21E-14 1.76 1.83 3.59 9.70E-14 3.85E-15 1.30E-14 1211 CONV 1-B EX 13 8.58E-14 0.26 0.27 0.53 1.43E-14 5.68E-16 1.92E-15 1229 HP LAB EX 14 8.40E-14 0.74 0.77 1.51 4.08E-14 1.62E-15 5.48E-15 1232 PELLET COMBINED EX 14 8.26E-14 6.23 5.84 12.07 3.26E-13 1.29E-14 4.38E-14 1233 SOLVENT EXT N EX 14 8.13E-14 3.55 3.59 7.14 1.93E-13 7.65E-15 2.59E-14 1234 SOLVENT EXT S EX 14 9.62E-14 0.69 0.73 1.42 3.84E-14 1.52E-15 5.16E-15 1244 AMMON FUME SCR 1008A 14 3.69E-13 16.28 2.32 18.60 5.02E-13 1.99E-14 6.75E-14 1209 SUPPL INCIN EX 15 1.10E-13 1.47 1.75 3.22 8.70E-14 3.45E-15 1.17E-14 1220 CHEM LAB FILT EX 15 8.03E-14 6.99 6.84 13.83 3.74E-13 1.48E-14 5.02E-14 1236 MAP COMBINED 15 9.14E-14 3.79 4.09 7.88 2.13E-13 8.45E-15 2.86E-14 1245 AMMON FUME SCR 1008B 15 1.10E-13 0.13 0.16 0.29 7.83E-15 3.11E-16 1.05E-15 1248 ERBIA FURNACE EX 16 8.09E-14 10.45 10.05 20.50 5.54E-13 2.20E-14 7.44E-14 1249 ERBIA SCRUBBER EX 16 8.11E-14 5.52 5.35 10.87 2.94E-13 1.17E-14 3.95E-14 1208 INCINERATOR EX 16 3.04E-13 8.19 9.69 17.88 4.83E-13 1.92E-14 6.49E-14 1212 S1030 A 18 9.96E-14 10.59 11.59 22.18 5.99E-13 2.38E-14 8.05E-14 1213 S1030 B 18 1.03E-13 0.53 0.61 1.14 3.08E-14 1.22E-15 4.14E-15 1238 IFBA EXHAUST 19 8.22E-14 5.91 6.06 11.97 3.23E-13 1.28E-14 4.35E-14 1241 PELLET LINE 6 20 8.04E-14 3.44 3.45 6.89 1.86E-13 7.38E-15 2.50E-14 Total 179.19 132.20 311.39 8.41E-12 3.34E-13 1.13E-12

  • Concentration LLD is 8E-14 uCi/mL Release Rate (Ci/s) uCi Uranium Released O:\\Regulatory\\EH&S Operations\\Environment\\Environment 2024\\Annual\\2024 Gaseous Effluent Report.xlsx 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 Hot Oil Room 42.62 6.47 49.09 Dose (mrem/yr) 2.60E-02 use highest release to calculate X/Q used by COMPLY Stack height (m) 13 U-234 U-235 U-238 Dose from comply 0.02600 mrem/yr 1.33E-12 5.26E-14 1.78E-13 release quantity 49.09 uCi 4.91E-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 85.17%

U-235 3.32E-05 Sv/Bq 3.38%

U-238 3.20E-05 Sv/Bq 11.45%

weighted dose conversion 3.53E-05 Sv/Bq conversion factor 3700.00 mrem/pCi= factor* Sv/Bq weighted dose conversion 0.1305 mrem/pCi equations Dose (mrem) = R(a)*3.17e4*Q*(X/Q)*effective Dose conversion see RG1.109-25 Dose (mrem)/(R(a)*3.17e4*Q*effective Dose conversion)=(X/Q) 1.60E-05 X/Q Estimate Lung Dose using X/Q and annual releases for 2024 Estimate Bone Dose using X/Q and annual releases for 2024 App E table E-5 Lung Organ Dose conversion EPA FGR 11 p150-151 U-234 2.98E-04 Sv/Bq 85.17%

1.13E-06 Sv/Bq U-235 2.76E-04 Sv/Bq 3.38%

1.05E-06 Sv/Bq U-238 2.66E-04 Sv/Bq 11.45%

1.01E-06 Sv/Bq weighted dose conversion 2.94E-04 Sv/Bq 1.11E-06 Sv/Bq conversion factor 3700.00 mrem/pCi= factor* Sv/Bq 3700.00 mrem/pCi= factor* Sv/Bq weighted dose conversion 1.0863 mrem/pCi 4.12E-03 mrem/pCi release quantity 311.39 uCi/yr 311.39 uCi/yr 3.11E-04 Ci/yr 3.11E-04 Ci/yr Lung

  • 1.10 mrem/yr Bone
  • 4.16E-03 mrem/yr assume 80% residence Release Rate (Ci/s)

O:\\Regulatory\\EH&S Operations\\Environment\\Environment 2024\\Annual\\2024 Gaseous Effluent Report.xlsx

2024 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 2752.834 2,752,834 16.4 0.749 2.77 19.919 12.4 32.319 170.879 7.804 28.862 129.202 1.51 0.378 0.630 3.23 15.733 3.939 6.564 33.655 February 2434.286 2,434,286 15.3 1.14 2.92 19.36 14.4 33.76 140.971 10.504 26.904 132.678 1.35 0.421 0.599 2.85 12.439 3.879 5.519 26.259 March 3383.892 3,383,892 14.3 0.671 2.70 17.671 4.73 22.401 183.155 8.594 34.582 60.582 1.04 0.254 0.455 2.97 13.320 3.253 5.828 38.040 April 2097.782 2,097,782 39.9 2.24 7.61 49.75 10.4 60.15 316.810 17.786 60.424 82.577 2.03 0.540 0.887 2.53 16.118 4.288 7.043 20.088 May 2729.006 2,729,006 66.5 3.88 10.5 80.88 10.3 91.18 686.898 40.078 108.458 106.392 2.81 0.760 1.12 2.35 29.025 7.850 11.569 24.274 June 2826.858 2,826,858 63.0 3.04 11.3 77.34 9.21 86.55 674.078 32.527 120.906 98.544 2.38 0.585 1.01 2.47 25.465 6.259 10.807 26.428 July 3512.862 3,512,862 26.7 0.973 4.71 32.383 11.9 44.283 355.008 12.937 62.625 158.225 1.94 0.427 0.822 2.44 25.795 5.677 10.929 32.443 August 4595.264 4,595,264 15.7 0.539 3.04 19.279 3.23 22.509 273.071 9.375 52.875 56.180 1.31 0.282 0.578 2.31 22.785 4.905 10.053 40.178 September 3330.432 3,330,432 16.6 0.557 3.26 20.417 3.44 23.857 209.254 7.021 41.095 43.364 1.31 0.277 0.588 2.69 16.513 3.492 7.412 33.909 October 3577.505 3,577,505 12.8 0.655 2.09 15.545 5.21 20.755 173.323 8.869 28.300 70.548 1.23 0.321 0.509 2.98 16.655 4.347 6.892 40.352 November 3446.821 3,446,821 10.3 0.552 2.14 12.992 5.01 18.002 134.376 7.202 27.919 65.362 1.10 0.294 0.503 2.70 14.351 3.836 6.562 35.225 December 2741.305 2,741,305 13.4 0.745 2.68 16.825 4.25 21.075 139.036 7.730 27.807 44.097 1.20 0.323 0.538 2.87 12.451 3.351 5.582 29.779 Total (Jan-Dec) 37428.847 37,428,847 3456.860 170.427 620.757 1047.749 221 55 95 381 Liters (L) 1.42E+08 Milliliters (ml) 1.42E+11 ANNUAL LIQUID DISCHARGES Radionuclide Quantity Released (uCi)

U234 3456.9

+/-

221 U235 170.4

+/-

55 U238 620.8

+/-

95 Total U 4248.0 Tc-99 1047.7

+/-

381 Total (Jan-Dec) 5295.8 2.44E-08 1.20E-09 4.38E-09 3.00E-08 - 2024 LIQUID EFFLUENT DISCHARGES 7.40E-09 6.74E-08 Measurement Uncertainty / Error 4248.0 uCi Uranium (all types)

Isotopic Uranium Measured Concentrations 5295.8 uCi Uranium & Tc-99 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 2024\\Annual\\liquid-effluent-2024.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 3.457E-03 U-234 release fraction Ci ICRP 69 Comparison 1.704E-04 U-235 release fraction Ci 6.208E-04 U-238 release fraction Ci Sv/Bq Rem/Bq mRem/pCi 1.048E-03 Tc-99 release fraction Ci adult 5.00E-08 0.005 1.85E-04 check U sum 0.00425 infant 3.70E-07 0.037 1.37E-03 bone-adult 7.90E-07 0.079 2.92E-03 9.80E-07 U-234 release fraction *dose factor*exp(-*tp) 4.53E-08 U-235 release fraction *dose factor*exp(-*tp) 1.58E-07 U-238 release fraction *dose factor*exp(-*tp) 1.53E-09 Tc-99 release fraction *dose factor*exp(-*tp) 1.18E-06 all nuclides sum of nuclides 85.53473 usage 1100*(usage*dilution)/flow 1.01E-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 2024\\Annual\\liquid-effluent-2024.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 3.457E-03 U-234 release fraction Ci Sv/Bq Rem/Bq mRem/pCi 1.704E-04 U-235 release fraction Ci 6.208E-04 U-238 release fraction Ci adult 5.00E-08 0.005 1.85E-04 1.048E-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 0.00425 1.45E-05 U-234 release fraction *dose factor*exp(-*tp) 6.62E-07 U-235 release fraction *dose factor*exp(-*tp) 2.32E-06 U-238 release fraction *dose factor*exp(-*tp) 2.34E-10 Tc-99 release fraction *dose factor*exp(-*tp) 1.74E-05 all nuclides sum of nuclides 85.53473 usage 1100*(usage*dilution)/flow 1.49E-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 2024\\Annual\\liquid-effluent-2024.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 3.457E-03 U-234 release fraction Ci 1.704E-04 U-235 release fraction Ci Sv/Bq Rem/Bq mRem/pCi 6.208E-04 U-238 release fraction Ci 1.048E-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 0.00425 bone-adult 7.90E-07 0.079 2.92E-03 bioaccumulation factor BNWL-2075 1.96E-06 U-234 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 UC-11 9.07E-08 U-235 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 Methodology for Calculation of Radiation Doses 3.16E-07 U-238 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 in the Environs from Nuclear Fuel 2.30E-08 Tc-99 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 15 Cycle Facilities 2.39E-06 all nuclides sum of nuclides 2.46059 usage 1100*(usage*dilution)/flow 5.88E-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 2024\\Annual\\liquid-effluent-2024.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 3.457E-03 U-234 release fraCi Sv/Bq Rem/Bq mRem/pCi 1.704E-04 U-235 release fraCi 6.208E-04 U-238 release fraCi adult 5.00E-08 0.005 1.85E-04 1.048E-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 0.00425 bioaccumulation factor BNWL-2075 2.89E-05 U-234 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 UC-11 1.32E-06 U-235 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 Methodology for Calculation of Radiation Doses 4.64E-06 U-238 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 in the Environs from Nuclear Fuel 3.51E-09 Tc-99 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 15 Cycle Facilities 3.49E-05 all nuclides sum of nuclides 2.46059 usage 1100*(usage*dilution)/flow 8.58E-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 2024\\Annual\\liquid-effluent-2024.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 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 3.457E-03 U-234 release fraction Ci 1.704E-04 U-235 release fraction Ci 6.208E-04 U-238 release fraction Ci 1.048E-03 Tc-99 release fraction Ci check U sum 0.00425 1.29E-10 U-234 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 1.27E-09 U-235 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 1.72E-11 U-238 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 4.11E-12 Tc-99 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 1.42E-09 all nuclides sum of nuclides 2.812101 usage 11000*(usage*dilution*shore width factor)/flow 3.99E-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 2024\\Annual\\liquid-effluent-2024.xlsx 2024 Isotopic Fractions Based on the plant nominal enrichment for 2024 Nuclide Average Specific Activity Weighted wt%

Ci/g Activity Activity U-234 0.04 6.220E-03 2.388E-06 85.17 U-235 4.39 2.160E-06 9.487E-08 3.38 U-238 95.57 3.360E-07 3.211E-07 11.45 Total 100.0 2.804E-06 100.00 O:\\Regulatory\\EH&S Operations\\Environment\\Environment 2024\\Annual\\liquid-effluent-2024.xlsx

40CFRPart61 NationalEmissionStandards forHazardousAirPollutants REPORTONCOMPLIANCEWITH THECLEANAIRACTLIMITSFORRADIONUCLIDEEMISSIONS FROMTHECOMPLYCODEV1.7.

Preparedby:

WestinghouseElectricCo.

ColumbiaFuelFabricationFacility 5801BluffRd.Hopkins,SC29061 DavidWagoner 803.647.5088 Preparedfor:

U.S.EnvironmentalProtectionAgency OfficeofRadiationandIndoorAir Washington,DC20460 0 - Comply Results

2024AnnualDosetoPublicduetoGaseousEffluent

SCREENINGLEVEL2

DATAENTERED:

RELEASERATESFORSTACK1.

ReleaseRate Nuclide(curies/SECOND)

U234Y8.560E14 U235Y3.400E15 U238Y1.150E14 RELEASERATESFORSTACK2.

ReleaseRate Nuclide(curies/SECOND)

U234Y5.480E14 U235Y2.180E15 U238Y7.370E15 RELEASERATESFORSTACK3.

ReleaseRate Nuclide(curies/SECOND)

U234Y3.320E13 U235Y1.320E14 U238Y4.460E14 RELEASERATESFORSTACK4.

ReleaseRate Nuclide(curies/SECOND)

U234Y2.710E13 U235Y1.080E14 U238Y3.650E14

RELEASERATESFORSTACK5.

ReleaseRate Nuclide(curies/SECOND)

U234Y3.420E12 U235Y1.360E13 U238Y4.590E13

RELEASERATESFORSTACK6.

ReleaseRate Nuclide(curies/SECOND)

U234Y1.100E12 U235Y4.370E14 U238Y1.480E13

RELEASERATESFORSTACK7.

ReleaseRate Nuclide(curies/SECOND)

U234Y6.810E13 U235Y2.700E14 U238Y9.160E14

RELEASERATESFORSTACK8.

ReleaseRate Nuclide(curies/SECOND)

U234Y1.330E12 U235Y5.280E14 U238Y1.790E13

RELEASERATESFORSTACK9.

ReleaseRate Nuclide(curies/SECOND)

U234Y6.300E13 U235Y2.500E14 U238Y8.470E14

RELEASERATESFORSTACK10.

ReleaseRate Nuclide(curies/SECOND)

U234Y3.230E13 U235Y1.280E14 U238Y4.350E14

RELEASERATESFORSTACK11.

ReleaseRate Nuclide(curies/SECOND)

U234Y1.860E13 U235Y7.380E15 U238Y2.500E14

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.

Releaseheight18meters.

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**********

40CFRPart61 NationalEmissionStandards forHazardousAirPollutants

REPORTONCOMPLIANCEWITH

THECLEANAIRACTLIMITSFORRADIONUCLIDEEMISSIONS

FROMTHECOMPLYCODEV1.7.

Preparedby:

WestinghouseElectricCo.

ColumbiaFuelFabricationFacility 5801BluffRd.Hopkins,SC29061

DavidWagoner 803.647.5088

Preparedfor:

U.S.EnvironmentalProtectionAgency OfficeofRadiationandIndoorAir Washington,DC20460

HotOilRoomExh

SCREENINGLEVEL2

DATAENTERED:

ReleaseRate Nuclide(curies/SECOND)

U234Y1.330E12 U235Y5.260E14 U238Y1.780E13

Releaseheight13meters.

Buildingheight9meters.

Thesourceandreceptorarenotonthesamebuilding.

Distancefromthesourcetothereceptoris595meters.

Buildingwidth137meters.

Defaultmeanwindspeedused(2.0m/sec).

NOTES:

Inputparametersoutsidethe"normal"range:

Building(width)isunusuallyWIDE.

ReceptorisunusuallyFAR.

RESULTS:

Effectivedoseequivalent:2.6E02mrem/yr.

      • Complyatlevel2.

ThisfacilityisinCOMPLIANCE.

ItmayormaynotbeEXEMPTfromreportingtotheEPA.

YoumaycontactyourregionalEPAofficeformoreinformation.

                    • ENDOFCOMPLIANCEREPORT**********
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