ML22059B021

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Westinghouse, NRC Semi-Annual Discharge Report July - December 2021
ML22059B021
Person / Time
Site: Westinghouse
Issue date: 02/24/2022
From: Ferguson J
Westinghouse, Westinghouse
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
LTR-RAC-22-17
Download: ML22059B021 (24)
v • d • e


Text

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-22-17 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, Georgia 30303-1257

Subject:

SNM-1107/70-1151 NRC Semi-Annual Discharge Report February 24, 2022 July - December 2021

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 July 1, 2021, through December 31, 2021, 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 (Ci) Concentration Uranium (analyzed as Gaseous 293 1.9E-16 Ci/mL* 5 E-14 Ci/mL gross alpha) 1,164 U-234 Liquid 66 U-235 2.0E-08 Ci/mL 3 E-07 Ci/mL Effluent # 203 U-238 1,302 Tc-99 1.8E-08 Ci/mL 6 E-05 Ci/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 NRCs 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 (85.23% U-234, 3.29% 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 2021 was 7.22 E+10 milliliters (mL).

© 2022 Westinghouse Electric Company LLC All Rights Reserved

Page 2 of 2 Our ref: LTR-RAC-22-17 February 24, 2022 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-22-09, 2021 Annual Assessment of Public Dose due to Liquid and Gaseous Effluents is attached.

Sincerely, Jeff Ferguson Manager, Environment, Health and Safety

Attachment:

LTR-EHS-22-09, 2021 Annual Assessment of Public Dose due to Liquid and Gaseous Effluents

Westinghouse NonProprietary Class 3 Page 1 of 3 Westinghouse Electric Company Nuclear Fuel Columbia Fuel Site 5801 Bluff Rd Hopkins, South Carolina 29061 USA To: Cynthia Teague, Diana Joyner Date: February 21, 2022 cc: Jeff Ferguson, Patrick Donnelly, Nancy Parr, Anna Miller From: David Wagoner Your ref:

Ext: 1919 Our ref: LTR-EHS-22-09 Fax: 803.695.4158

Subject:

2021 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 #1210 (Conv 1-A Ex), the measured release quantity, and the dose conversion factors from Federal Guidance Report No 11, Limiting Values of Radionuclide Intake and Air concentration Factors for Inhalation, Submersion, and Ingestion (FGR 11).

Dose due to Liquid Effluents by Ingestion of Potable Water 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

© 2022 Westinghouse Electric Company LLC All Rights Reserved

Westinghouse NonProprietary Class 3 Page 2 of 3 Our ref: LTR-EHS-22-09 February 21, 2022 boundary (595 meters) for twelve 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 46 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 2021:

528.5 µCi of Uranium in gaseous effluent 3,064 µCi of Uranium in liquid effluent 3,310 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 a hypothetical 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 2021 resulted in a potential whole body dose of 0.24 mrem, 0.008 mrem to the bone, and 1.89 mrem to the lung 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. 2021 Annual Dose to the Public from Liquid and Gaseous Effluents Whole Body Dose Organ Dose - Bone Organ Dose - Lung (mrem) (mrem) (mrem)

Gaseous Effluents Direct inhalation* 0.24 7.17E-03 1.89 Liquid Effluents Potable Water 7.33E-05 1.07E-03 -

Aquatic Food (Fish) 4.37E-06 6.18E-05 -

Shoreline Deposition 2.92E-09 - -

Total (mrem) 0.24 8.30E-03 1.89

  • Assumes 80 % residence time There were no changes in source material and no release points were added during 2021. Gaseous effluent sample locations 1240, 1242, 1243, and 1246 were removed from the sampling program in the 2nd half of 2021 because these ventilation systems are outside the scope of the effluent monitoring program. All four systems are recirculating comfort air systems that are non-process related and do not exhaust to the atmosphere.

Westinghouse NonProprietary Class 3 Page 3 of 3 Our ref: LTR-EHS-22-09 February 21, 2022 In addition, the height and diameter for each gaseous effluent stack were physically verified during the 2nd half of 2021. Several stack heights were identified to be incorrect, and SEPS-009-16 was revised to reflect the actual field measurements. Neither of these parameters are used for calculating release concentrations so there is no impact to the calculations performed by the Personnel Exposure System. Stack height is used by the Comply code to estimate dose to a member of the public, however, the impact on historical results was determined to be negligible based on re-runs of the Comply code using the revised stack heights.

The attachments below illustrate the method used to calculate each result listed in Table 1. : 2021 Gaseous Effluent Discharges : Lung/Bone Organ Dose due to Gaseous Effluent : 2021 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 : 2021 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 2021 Gaseous Effluent Discharges Sampling Location Stack Height Gross Alpha Concentration* 1st Half (JanJun) 2nd Half (JulyDec) Total uCi Release Rate (Ci/s)

Station Description (m) (uCi/mL) uCi Uranium Released Released U234 U235 U238 1239 MAINT WELD EX 9 4.74E13 3.07 5.48 8.55 2.31E13 8.92E15 3.11E14 1223 CALC COMB GAS LN 2 10 3.47E13 0.60 0.59 1.19 3.22E14 1.24E15 4.33E15 1226 CALC COMB GAS LN 5 10 2.74E13 0.57 0.42 0.99 2.68E14 1.03E15 3.60E15 1230 DEV LAB EX #1 10 4.92E13 3.35 5.62 8.97 2.42E13 9.36E15 3.26E14 1247 HOT OIL RM EX 11 5.73E13 13.95 28.16 42.11 1.14E12 4.39E14 1.53E13 1206 NEW DECON ROOM 11 1.50E13 2.21 2.74 4.95 1.34E13 5.16E15 1.80E14 1221 DECON ROOM EX 11 9.85E13 9.43 17.17 26.60 7.19E13 2.78E14 9.67E14 1231 DEV LAB EX #2 11 6.85E13 4.46 7.92 12.38 3.35E13 1.29E14 4.50E14 1243 AC8 11 1.35E13 5.19 3.59 8.78 2.37E13 9.16E15 3.19E14 1251 WATERGLASS SCR S1190 12 4.75E13 8.48 13.33 21.81 5.89E13 2.28E14 7.93E14 1217 CONV ENCL EX 4C 13 2.24E13 7.39 9.95 17.34 4.69E13 1.81E14 6.31E14 1218 CONV ENCL EX 4D 13 4.49E13 0.66 0.97 1.63 4.41E14 1.70E15 5.93E15 1219 CONV EMERG EX 4E 13 5.71E13 0.79 1.26 2.05 5.54E14 2.14E15 7.46E15 1250 ERBIA CHANGE ROOM 13 1.57E13 2.99 3.19 6.18 1.67E13 6.45E15 2.25E14 1207 MET LAB EXHAUST 13 5.74E13 2.19 3.91 6.10 1.65E13 6.36E15 2.22E14 1210 CONV 1A EX 13 7.87E13 17.49 40.25 57.74 1.56E12 6.02E14 2.10E13 1201 FURNACE EX LINE 1 13 1.37E13 3.69 4.13 7.82 2.11E13 8.16E15 2.84E14 1202 FURNACE EX LINE 2 13 1.42E13 4.86 3.72 8.58 2.32E13 8.95E15 3.12E14 1203 FURNACE EX LINE 3 13 1.28E13 3.59 3.78 7.37 1.99E13 7.69E15 2.68E14 1204 FURNACE EX LINE 4 13 1.27E13 3.74 3.68 7.42 2.01E13 7.74E15 2.70E14 1205 FURNACE EX LINE 5 13 1.26E13 3.53 3.71 7.24 1.96E13 7.55E15 2.63E14 1222 CALC COMB GAS LN 1 13 2.22E13 0.54 0.3 0.84 2.27E14 8.76E16 3.06E15 1224 CALC COMB GAS LN 3 13 2.21E13 0.34 0.4 0.74 2.00E14 7.72E16 2.69E15 1225 CALC COMB GAS LN 4 13 1.66E13 0.30 0.28 0.58 1.57E14 6.05E16 2.11E15 1237 ABF HOOD TORIT EX 13 1.35E13 2.14 1.92 4.06 1.10E13 4.24E15 1.48E14 1211 CONV 1B EX 13 2.53E13 0.68 0.44 1.12 3.03E14 1.17E15 4.07E15 1227 CHEM LAB EX #2 14 8.85E13 5.66 5.28 10.94 2.96E13 1.14E14 3.98E14 1229 HP LAB EX 14 2.14E13 0.93 1.49 2.42 6.54E14 2.52E15 8.80E15 1232 PELLET COMBINED EX 14 1.58E13 8.03 7.65 15.68 4.24E13 1.64E14 5.70E14 1233 SOLVENT EXT N EX 14 1.30E13 3.72 3.96 7.68 2.08E13 8.01E15 2.79E14 1234 SOLVENT EXT S EX 14 5.89E13 1.94 3.43 5.37 1.45E13 5.60E15 1.95E14 1244 AMMON FUME SCR 1008A 14 3.88E13 6.73 7.56 14.29 3.86E13 1.49E14 5.20E14 1209 SUPPL INCIN EX 15 2.46E13 2.13 2.58 4.71 1.27E13 4.91E15 1.71E14 1220 CHEM LAB FILT EX 15 1.86E13 8.81 11.75 20.56 5.56E13 2.14E14 7.48E14 1236 MAP COMBINED 15 3.22E13 7.88 10.05 17.93 4.85E13 1.87E14 6.52E14 1245 AMMON FUME SCR 1008B 15 3.76E13 0.17 0.44 0.61 1.65E14 6.36E16 2.22E15 1240 AC3 15 1.51E13 5.48 4.14 9.62 2.60E13 1.00E14 3.50E14 1246 AC4 15 1.49E13 5.96 4.06 10.02 2.71E13 1.05E14 3.64E14 1248 ERBIA FURNACE EX 16 1.39E13 14.84 10.39 25.23 6.82E13 2.63E14 9.18E14 1249 ERBIA SCRUBBER EX 16 1.25E13 5.41 5.81 11.22 3.03E13 1.17E14 4.08E14 1208 INCINERATOR EX 16 7.32E13 16.84 13.22 30.06 8.12E13 3.14E14 1.09E13 1242 AC5 17 1.22E13 4.90 3.18 8.08 2.18E13 8.43E15 2.94E14 1212 S1030 A 17 2.36E13 17.95 17.64 35.59 9.62E13 3.71E14 1.29E13 1213 S1030 B 17 6.76E13 1.61 3 4.61 1.25E13 4.81E15 1.68E14 1238 IFBA EXHAUST 19 1.31E13 6.08 6.63 12.71 3.44E13 1.33E14 4.62E14 1241 PELLET LINE 6 20 1.40E13 3.91 4.14 8.05 2.18E13 8.40E15 2.93E14 Total 235.21 293.31 528.52 1.43E11 5.51E13 1.92E12

  • Concentration LLD is 8E14 uCi/mL O:\Regulatory\EH&S Operations\Environment\Environment 2021\Annual\Gaseous Effluent.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 Conv 1-A Ex 17.49 40.25 57.74 Dose (mrem/yr) 3.10E-02 use highest release to calculate X/Q used by COMPLY Stack height (m) 13 U-234 U-235 U-238 Release Rate (Ci/s)

Dose from comply 0.03100 mrem/yr 1.56E12 6.02E14 2.10E13 release quantity 57.74 uCi 5.77E-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 85.23%

U-235 3.32E-05 Sv/Bq 3.29%

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 semi-annual releases for 2021 Estimate Bone Dose using X/Q and semi-annual releases for 2021 App E table E-5 Lung Organ Dose conversion EPA FGR 11 p150-151 U-234 2.98E-04 Sv/Bq 85.23% 1.13E-06 Sv/Bq U-235 2.76E-04 Sv/Bq 3.29% 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 1.0862 mrem/pCi 4.12E-03 mrem/pCi release quantity 528.52 uCi/yr 528.52 uCi/yr 5.29E-04 Ci/yr 5.29E-04 Ci/yr Lung

  • 1.89 mrem/yr Bone
  • 7.17E-03 mrem/yr assume 80% residence O:\Regulatory\EH&S Operations\Environment\Environment 2021\Annual\Gaseous Effluent.xlsx

2021 Attachment 3 - 2021 LIQUID EFFLUENT RADIOACTIVITY DISCHARGES Tc-99 Isotopic Uranium Total uCi/month Released Measurement Uncertainty / Error Uncertainty / Error Liquid Effluent Discharges Measured Sum U & Tc-Measured Concentrations (based on monthly GEL discharge samples)

Concentrations 99 Total U & Tc-Actual Actual U234 U235 U238 Total U Tc-99 U234 U235 U238 Tc-99 U234 U-235 U-238 Tc-99 Month 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 2945.861 2,945,861 34.0 1.77 6.37 42.1 28.0 70.1 379 20 71 312 1.62 0.419 0.699 3.27 18 5 8 36 February 3711.259 3,711,259 4.44 0.258 4.04 8.74 59.0 67.7 62 4 57 829 0.778 0.224 0.741 4.95 11 3 10 70 March 3275.019 3,275,019 20.9 0.868 3.29 25.1 36.2 61.3 259 11 41 449 1.20 0.281 0.505 3.75 15 3 6 46 April 1812.059 1,812,059 19.1 0.493 3.53 23.1 18.6 41.7 131 3 24 128 1.59 0.325 0.711 2.39 11 2 5 16 May 2544.166 2,544,166 31.1 1.23 5.77 38.1 18.8 56.9 299 12 56 181 1.64 0.386 0.736 3.47 16 4 7 33 June 3231.978 3,231,978 13.3 0.712 2.59 16.6 8.93 25.5 163 9 32 109 1.58 0.438 0.704 2.17 19 5 9 27 July 3539.662 3,539,662 14.7 0.912 2.89 18.5 7.28 25.8 197 12 39 98 0.953 0.277 0.429 2.27 13 4 6 30 August 4536.226 4,536,226 15.1 0.895 2.92 18.9 4.84 23.8 259 15 50 83 1.28 0.355 0.565 2.41 22 6 10 41 September 3231.769 3,231,769 14.2 0.696 2.57 17.5 24.8 42.3 174 9 31 303 1.40 0.358 0.604 2.67 17 4 7 33 October 2764.638 2,764,638 13.7 0.591 2.31 16.6 30.2 46.8 143 6 24 316 1.43 0.348 0.596 3.14 15 4 6 33 November 2225.996 2,225,996 16.3 0.854 2.45 19.6 34.6 54.2 137 7 21 292 0.919 0.241 0.359 3.56 8 2 3 30 December 2785.661 2,785,661 24.0 1.57 3.59 29.2 20.0 49.2 253 17 38 211 1.62 0.465 0.627 2.20 17 5 7 23 Total 36604.293 36,604,293 2457 124 483 3310 182 47 84 419 Liters (L) 1.39E+08 3064 Milliliters (ml) 1.39E+11 uCi Uranium 6374 uCi Uranium & Tc-99 LIQUID DISCHARGES Quantity Average Concentration Radionuclide LLD (uCi/ml) Released Error Released (uCi/ml)

(uCi)

U234 6.00E-10 2457 +/- 182 1.77E-08 U235 6.00E-10 124 +/- 47 8.96E-10 U238 6.00E-10 483 +/- 84 3.49E-09 Total U 3064 2.21E-08 Tc-99 6.00E-10 3310 +/- 419 2.39E-08 Total 6374 6.81E-08 O:\Regulatory\EH&S Operations\Environment\Environment 2021\Annual\2021 liquid effluent.xlsx

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

730 liters Usage by adult/yr 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 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 2.457E-03 U-234 release fraction Ci ICRP 69 Comparison 1.240E-04 U-235 release fraction Ci 4.830E-04 U-238 release fraction Ci Sv/Bq Rem/Bq mRem/pCi 3.310E-03 Tc-99 release fraction Ci adult 5.00E-08 0.005 1.85E-04 check U sum 0.00306 infant 3.70E-07 0.037 1.37E-03 bone-adult 7.90E-07 0.079 2.92E-03 6.96E-07 U-234 release fraction *dose factor*exp(-*tp) 3.30E-08 U-235 release fraction *dose factor*exp(-*tp) 1.23E-07 U-238 release fraction *dose factor*exp(-*tp) 4.84E-09 Tc-99 release fraction *dose factor*exp(-*tp) 8.57E-07 all nuclides sum of nuclides 85.53473 usage 1100*(usage*dilution)/flow 7.33E-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 2021\Annual\2021 liquid effluent.xlsx

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

730 liters Usage by adult/yr 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 2.457E-03 U-234 release fraction Ci Sv/Bq Rem/Bq mRem/pCi 1.240E-04 U-235 release fraction Ci 4.830E-04 U-238 release fraction Ci adult 5.00E-08 0.005 1.85E-04 3.310E-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 0.00306 1.03E-05 U-234 release fraction *dose factor*exp(-*tp) 4.82E-07 U-235 release fraction *dose factor*exp(-*tp) 1.80E-06 U-238 release fraction *dose factor*exp(-*tp) 7.40E-10 Tc-99 release fraction *dose factor*exp(-*tp) 1.26E-05 all nuclides sum of nuclides 85.53473 usage 1100*(usage*dilution)/flow 1.07E-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 2021\Annual\2021 liquid effluent.xlsx

Attachment 6 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 2.457E-03 U-234 release fraction Ci 1.240E-04 U-235 release fraction Ci Sv/Bq Rem/Bq mRem/pCi 4.830E-04 U-238 release fraction Ci 3.310E-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 0.00306 bone-adult 7.90E-07 0.079 2.92E-03 bioaccumulation factor BNWL-2075 1.39E-06 U-234 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 UC-11 6.60E-08 U-235 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 Methodology for Calculation of Radiation Doses 2.46E-07 U-238 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 in the Environs from Nuclear Fuel 7.26E-08 Tc-99 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 15 Cycle Facilities 1.78E-06 all nuclides sum of nuclides 2.46059 usage 1100*(usage*dilution)/flow 4.37E-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 2021\Annual\2021 liquid effluent.xlsx

Attachment 7 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/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 2.457E-03 U-234 release fraCi Sv/Bq Rem/Bq mRem/pCi 1.240E-04 U-235 release fraCi 4.830E-04 U-238 release fraCi adult 5.00E-08 0.005 1.85E-04 3.310E-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 0.00306 bioaccumulation factor BNWL-2075 2.05E-05 U-234 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 UC-11 9.63E-07 U-235 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 Methodology for Calculation of Radiation Doses 3.61E-06 U-238 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 2 in the Environs from Nuclear Fuel 1.11E-08 Tc-99 release fraction *bioaccumulation factor*dose factor*exp(-*tp) 15 Cycle Facilities 2.51E-05 all nuclides sum of nuclides 2.46059 usage 1100*(usage*dilution)/flow 6.18E-05 mRem see regulatory guide 1.109 page 1.109-2 and 1.109-3 for formula and definition of terms.

O:\Regulatory\EH&S Operations\Environment\Environment 2021\Annual\2021 liquid effluent.xlsx

Attachment 8 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 2.457E-03 U-234 release fraction Ci 1.240E-04 U-235 release fraction Ci 4.830E-04 U-238 release fraction Ci 3.310E-03 Tc-99 release fraction Ci check U sum 0.00306 9.14E-11 U-234 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 9.22E-10 U-235 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 1.34E-11 U-238 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 1.30E-11 Tc-99 release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 1.04E-09 all nuclides sum of nuclides 2.812101 usage 11000*(usage*dilution*shore width factor)/flow 2.92E-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 2021\Annual\2021 liquid effluent.xlsx

Attachment 9 2021 Isotopic Fractions Based on the plant nominal enrichment for 2021 Nuclide Average Specific Activity Weighted  %

wt% Ci/g Activity Activity U-234 0.04 6.220E-03 2.388E-06 85.23 U-235 4.27 2.160E-06 9.223E-08 3.29 U-238 95.70 3.360E-07 3.216E-07 11.47 Total 100.0 2.802E-06 100.00 O:\Regulatory\EH&S Operations\Environment\Environment 2021\Annual\2021 liquid effluent.xlsx

Attachment 10 - Comply Results COMPLY: V1.7. 2/18/2022 3:51 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

2021 Annual Assessment of Dose to a Member of the Public

SCREENING LEVEL 2

DATA ENTERED:

RELEASE RATES FOR STACK 1.

Release Rate Nuclide (curies/SECOND)

U234 Y 2.310E13 U235 Y 8.920E15 U238 Y 3.110E14 RELEASE RATES FOR STACK 2.

Release Rate Nuclide (curies/SECOND)

U234 Y 3.010E13 U235 Y 1.160E14 U238 Y 4.060E14 RELEASE RATES FOR STACK 3.

Release Rate Nuclide (curies/SECOND)

U234 Y 2.560E12 U235 Y 9.890E14 U238 Y 3.450E13 RELEASE RATES FOR STACK 4.

Release Rate Nuclide (curies/SECOND)

U234 Y 5.890E13 U235 Y 2.280E14 U238 Y 7.930E14 RELEASE RATES FOR STACK 5.

Release Rate Nuclide (curies/SECOND)

U234 Y 3.700E12 U235 Y 1.430E13 U238 Y 4.980E13 RELEASE RATES FOR STACK 6.

Release Rate Nuclide (curies/SECOND)

U234 Y 1.520E12 U235 Y 5.880E14 U238 Y 2.050E13 RELEASE RATES FOR STACK 7.

Release Rate Nuclide (curies/SECOND)

U234 Y 1.710E12 U235 Y 6.620E14 U238 Y 2.310E13 RELEASE RATES FOR STACK 8.

Release Rate Nuclide (curies/SECOND)

U234 Y 1.800E12 U235 Y 6.940E14 U238 Y 2.420E13 RELEASE RATES FOR STACK 9.

Release Rate Nuclide (curies/SECOND)

U234 Y 1.300E12 U235 Y 5.040E14 U238 Y 1.760E13 RELEASE RATES FOR STACK 10.

Release Rate Nuclide (curies/SECOND)

U234 Y 3.440E13 U235 Y 1.330E14 U238 Y 4.620E14 RELEASE RATES FOR STACK 11.

Release Rate Nuclide (curies/SECOND)

U234 Y 2.180E13 U235 Y 8.400E15 U238 Y 2.930E14 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: 0.3 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. 2/18/2022 4:06 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

Conv. 1A Ex

SCREENING LEVEL 2

DATA ENTERED:

Release Rate Nuclide (curies/SECOND)

U234 Y 1.560E12 U235 Y 6.020E14 U238 Y 2.100E13 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.

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: 3.1E02 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 **********
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