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{{#Wiki_filter:8 Westinghouse                                                                      Page 1 of 2 Westinghouse Electric Company LLC Nuclear Fuel Columbia Fuel Site 5807 Bluff Road Hopkins, South Carolina 29067 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-22-45 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, Georgia 30303-1257
{{#Wiki_filter:Page 1 of 2 8 Westinghouse Westinghouse Electric Company LLC Nuclear Fuel Columbia Fuel Site 5807 Bluff Road Hopkins, South Carolina 29067 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: L TR-RAC-22-45 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, Georgia 30303-1257


==Subject:==
==Subject:==
SNM-1107/70-1151 NRC Semi-Annual Discharge Report                                                   August16,2022 January - June 2022
SNM-1107/70-1151 NRC Semi-Annual Discharge Report August16,2022 January - June 2022


==Dear Sir:==
==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, 2022, through June 30, 2022, the following quantities of radionuclides were released to the unrestricted area by the Westinghouse Electric Company's Columbia, South Carolina Nuclear Fuel Plant:
Total Total Regulatory Discharge emissions Parameter Measured Concentration 6-month 6-month


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, 2022, through June 30, 2022, the following quantities of radionuclides were released to the unrestricted area by the Westinghouse Electric Company's Columbia, South Carolina Nuclear Fuel Plant:
(µCi) Concentration Limit Gaseous 213.3 Uranium (analyzed as 1.6E-16 µCi/ml* 5 E-14 µCi/ml gross alpha) 1,720 U-234 Liquid 86 U-235 3.5E-08 µCi/ml 3 E-07 µCi/ml Effluent# 292 U-238 4,102 Tc-99 6.SE-08 µCi/ml 6 E- 05 µCi/ml
Total                                                  Total Regulatory 6-month                                                6-month Discharge                                Parameter                                                Concentration emissions                                              Measured Limit
(µCi)                                             Concentration Uranium (analyzed as Gaseous                213.3                                        1.6E-16 µCi/ml*               5 E- 14 µCi/ml gross alpha) 1,720               U-234 Liquid                   86             U-235                     3.5E- 08 µCi/ml               3 E-07 µCi/ml Effluent#                 292               U-238 4,102               Tc-99                     6.SE-08 µCi/ml               6 E- 05 µCi/ml
* Includes a dispersion factor of 1000 to account for dilution between the release point and the nearest site boundary.
* Includes a dispersion factor of 1000 to account for dilution between the release point and the nearest site boundary.
  # Sum of fractions (SOF) equates to less than 1.0.
# 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.
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.
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.
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 2022 was 6.05 E+ 10 milliliters (ml).
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 2022 was 6.05 E+ 10 milliliters (ml).
                          © 2022 Westinghouse Electric Company LLC All Rights Reserved


Page 2 of 2 Our ref: LTR-RAC-22-45 August 16, 2022 Calculated values have been reported for all results, due to variability of minimum detection concentrations (MDC). Negative values are reported as zero.
© 2022 Westinghouse Electric Company LLC All Rights Reserved Page 2 of 2 Our ref: L TR-RAC-22-45 August 16, 2022
To meet the requested dosage information outlined in Regulatory Guide 4.16, Section 6.1, LTR-EHS-22-39, "2022 Semi-Annual Assessment of Public Dose due to Liquid and Gaseous Effluents" is attached.
 
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-22-39, "2022 Semi-Annual Assessment of Public Dose due to Liquid and Gaseous Effluents" is attached.
 
Sincerely, Jeffllt~
Sincerely, Jeffllt~
Manager, Environment, Health and Safety
Manager, Environment, Health and Safety


==Attachment:==
==Attachment:==
L TR-EHS-22-39, "2022 Semi-Annual Assessment of Public Dose due to Liquid and Gaseous Effluents" WestinghouseNonProprietaryClass3 Page 1 of 3


LTR-EHS-22-39, "2022 Semi-Annual Assessment of Public Dose due to Liquid and Gaseous Effluents"
Westinghouse Electric Company Nuclear Fuel Columbia Fuel Site 5801 Bluff Rd Hopkins, South Carolina 29061 USA


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:   August 11, 2022 cc: Jeff Ferguson, Patrick Donnelly, Nancy Parr, Anna Miller From: David Wagoner                                                     Your ref:
To: Cynthia Teague, Diana Joyner Date: August 11, 2022
Ext: 1919                                                               Our ref:   LTR-EHS-22-39 Fax: 803.695.4158
 
cc: Jeff Ferguson, Patrick Donnelly, Nancy Parr, Anna Miller
 
From: David Wagoner Your ref:
Ext: 1919 Our ref: LTR-EHS-22-39 Fax: 803.695.4158


==Subject:==
==Subject:==
2022 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.
2022 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:
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.
Dose due to Gaseous Effluents by Direct Inhalation The whole body dose was estimated using EPAs COMPLY Code at level 2 complexity.
The organ dose was estimated by calculating the X/Q factor using the results of the COMPLY analysis for stack #1208 (Incinerator Exh), the measured release quantity, and the dose conversion factors from Federal Guidance Report No 11, Limiting Values of Radionuclide Intake and Air concentration Factors for Inhalation, Submersion, and Ingestion (FGR 11).
The organ dose was estimated by calculating the X/Q factor using the results of the COMPLY analysis for stack #1208 (Incinerator Exh), the measured release quantity, and the dose conversion factors from Federal Guidance Report No 11, Limiting Values of Radionuclide Intake and Air concentration Factors for Inhalation, Submersion, and Ingestion (FGR 11).
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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 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.
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
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-22-39 August 11, 2022 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.
© 2022 Westinghouse Electric Company LLC All Rights Reserved WestinghouseNonProprietaryClass3
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 2022:
Page 2 of 3 Our ref: LTR-EHS-22-39 August 11, 2022
213.3 µCi of Uranium in gaseous effluent 2,098 µCi of Uranium in liquid effluent 4,102 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 2022 resulted in a potential whole body dose of 0.08 mrem, 0.76 mrem to the lung, and 0.003 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. 2022 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*                  0.08                  2.89E-03                    0.76 Liquid Effluents Potable Water                    2.53E-05                  3.69E-04                      -
Aquatic Food (Fish)              1.55E-06                  2.12E-05                      -
Shoreline Deposition              1.02E-09                      -                          -
Total (mrem/6 months)                0.08                  3.28E-03                    0.76
* Assumes 80 % residence time There were no changes in source material and no release points were added or removed during the 1st half of 2022. 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 NonProprietary Class 3 Page 3 of 3 Our ref: LTR-EHS-22-39 August 11, 2022 :        1st Half 2022 Gaseous Effluent Discharges :        Lung/Bone Organ Dose due to Gaseous Effluent :        1st Half 2022 Liquid Effluent Discharges :        Whole Body Dose from Liquid Effluent Pathways - Potable Water :        Dose to the Bone Surface from Liquid Effluent Pathways - Potable Water :        Whole Body Dose from Liquid Effluent Pathways - Aquatic Foods :        Dose to the Bone Surface from Liquid Effluent Pathways - Aquatic Foods :        Whole Body Dose from Liquid Effluent Pathways - Shoreline Deposits :        2022 Isotopic Fractions 0:      Comply Results David Wagoner, CHP                              Review by: Anna Miller Radiation Safety Engineer                      Manager, RSO EH&S Operations                                EH&S Operations
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.


Attachment 1 2022 Gaseous Effluent Discharges Sampling Location                        Stack Height Gross Alpha Concentration*    1st Half (JanJun)         Release Rate (Ci/s)
The release rates for gaseous effluent are determined by gross alpha measurements performed on daily air samples, one per stack fo r 42 stacks (Attachment 1). The release rates for liquid effluent are determined by isotopic analysis of composite liquid effluent samples taken monthly (Attachment 3).
Station Description                          (m)              (uCi/mL)          uCi Uranium Released    U234        U235            U238 1239  MAINT WELD EX                          9              1.18E13                    1.72        9.32E14    3.63E15        1.25E14 1223  CALC COMB GAS LN 2                    10              1.85E13                    0.47        2.55E14    9.92E16        3.43E15 1226  CALC COMB GAS LN 5                    10              1.57E13                    0.39        2.11E14    8.23E16        2.84E15 1230  DEV LAB EX #1                        10              1.57E13                    2.29        1.24E13    4.83E15        1.67E14 1247  HOT OIL RM EX                        11              1.86E13                    11.18        6.06E13    2.36E14        8.15E14 1206  NEW DECON ROOM                        11              9.45E14                    2.39        1.30E13    5.05E15        1.74E14 1221  DECON ROOM EX                        11              3.00E13                    6.54        3.54E13    1.38E14        4.77E14 1231  DEV LAB EX #2                        11              1.98E13                    2.88        1.56E13    6.08E15        2.10E14 1251  WATERGLASS SCR S1190                  12              2.06E13                    7.52        4.07E13    1.59E14        5.49E14 1217  CONV ENCL EX 4C                      13              9.97E14                    5.96        3.23E13    1.26E14        4.35E14 1218  CONV ENCL EX 4D                      13              1.62E13                    0.46        2.49E14    9.71E16        3.36E15 1219  CONV EMERG EX 4E                      13              1.94E13                    0.55        2.98E14    1.16E15        4.01E15 1250  ERBIA CHANGE ROOM                    13              8.04E14                    2.35        1.27E13    4.96E15        1.71E14 1207  MET LAB EXHAUST                      13              1.87E13                    1.60        8.67E14    3.38E15        1.17E14 1210  CONV 1A EX                          13              1.90E13                    11.63        6.30E13    2.46E14        8.48E14 1201  FURNACE EX LINE 1                    13              8.03E14                    3.45        1.87E13    7.28E15        2.52E14 1202  FURNACE EX LINE 2                    13              8.07E14                    3.43        1.86E13    7.24E15        2.50E14 1203  FURNACE EX LINE 3                    13              8.60E14                    3.70        2.00E13    7.81E15        2.70E14 1204  FURNACE EX LINE 4                    13              8.00E14                    3.38        1.83E13    7.14E15        2.47E14 1205  FURNACE EX LINE 5                    13              8.01E14                    3.42        1.85E13    7.22E15        2.49E14 1222  CALC COMB GAS LN 1                    13              8.78E14                    0.22        1.19E14    4.64E16        1.60E15 1224  CALC COMB GAS LN 3                    13              9.48E14                    0.24        1.30E14    5.07E16        1.75E15 1225  CALC COMB GAS LN 4                    13              9.57E14                    0.24        1.30E14    5.07E16        1.75E15 1237  ABF HOOD TORIT EX                    13              8.49E14                    1.85        1.00E13    3.91E15        1.35E14 1211  CONV 1B EX                          13              1.84E13                    0.56        3.03E14    1.18E15        4.08E15 1227  CHEM LAB EX #2                        14              3.53E13                    3.18        1.72E13    6.71E15        2.32E14 1229  HP LAB EX                            14              8.49E14                    0.76        4.12E14    1.60E15        5.54E15 1232  PELLET COMBINED EX                    14              8.49E14                    6.17        3.34E13    1.30E14        4.50E14 1233  SOLVENT EXT N EX                      14              8.22E14                    3.59        1.95E13    7.58E15        2.62E14 1234  SOLVENT EXT S EX                      14              1.70E13                    1.25        6.77E14    2.64E15        9.12E15 1244  AMMON FUME SCR 1008A                  14              1.11E13                    3.08        1.67E13    6.50E15        2.25E14 1209  SUPPL INCIN EX                        15              1.75E13                    2.55        1.38E13    5.38E15        1.86E14 1220  CHEM LAB FILT EX                      15              8.58E14                    7.33        3.97E13    1.55E14        5.35E14 1236  MAP COMBINED                          15              1.26E13                    5.40        2.93E13    1.14E14        3.94E14 1245  AMMON FUME SCR 1008B                  15              1.75E13                    0.24        1.30E14    5.07E16        1.75E15 1248  ERBIA FURNACE EX                      16              8.00E14                    9.99        5.41E13    2.11E14        7.29E14 1249  ERBIA SCRUBBER EX                    16              8.09E14                    5.36        2.90E13    1.13E14        3.91E14 1208  INCINERATOR EX                        16              2.04E12                    59.56        3.23E12    1.26E13        4.34E13 1212  S1030 A                              17              1.44E13                    15.99        8.66E13    3.38E14        1.17E13 1213  S1030 B                              17              1.78E13                    0.98        5.31E14    2.07E15        7.15E15 1238  IFBA EXHAUST                          19              8.00E14                    5.84        3.16E13    1.23E14        4.26E14 1241  PELLET LINE 6                        20              8.35E14                    3.57        1.93E13    7.54E15        2.60E14 Total                                                                213.26        1.16E11    4.50E13        1.56E12
Based on these results, the following quantities were released in the 1 st half of calendar year 2022:
        *Concentration LLD is 8E14 uCi/mL O:\Regulatory\EH&S Operations\Environment\Environment 2022\Gaseous effluent 1st half 2022.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 Incinerator Ex                            59.56                          N/A                    59.56        Dose (mrem/yr)                        6.40E-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)
213.3 µCi of Uranium in gaseous effluent 2,098 µCi of Uranium in liquid effluent 4,102 µCi of Technetium in liquid effluent
Dose from comply                                  0.03200            mrem/6 mo                                                                      3.23E-12      1.26E-13 4.34E-13 release quantity                                    59.56                uCi 5.96E-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) 3.25E-05                X/Q Estimate Lung Dose using X/Q and semi-annual releases for 2022                                                Estimate Bone Dose using X/Q and semi-annual releases for 2022 App E table E-5 Lung Organ Dose conversion EPA FGR 11 p150-151 U-234                                            2.98E-04              Sv/Bq                        85.21%                        1.13E-06          Sv/Bq U-235                                            2.76E-04              Sv/Bq                        3.32%                        1.05E-06          Sv/Bq U-238                                            2.66E-04              Sv/Bq                        11.47%                        1.01E-06          Sv/Bq weighted dose conversion                          2.94E-04              Sv/Bq                                                      1.11E-06          Sv/Bq conversion factor                                3700.00      mrem/pCi= factor* Sv/Bq                                                3700.00 mrem/pCi= factor* Sv/Bq weighted dose conversion                          1.0863              mrem/pCi                                                      4.12E-03        mrem/pCi release quantity                                  213.26              uCi/6 mo                                                        213.26        uCi/6 mo 2.13E-04              Ci/6 mo                                                      2.13E-04        Ci/6 mo Lung
* 0.76            mrem/6 mo            Bone
* 2.89E-03      mrem/6 mo assume 80% residence O:\Regulatory\EH&S Operations\Environment\Environment 2022\Gaseous effluent 1st half 2022.xlsx


2022                                                              Attachment 3 - 1st HALF 2022 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)
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 2022 resulted in a potential whole body dose of 0.08 mrem, 0.76 mrem to the lung, and 0.003 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.
Concentrations        99 Total U & Tc-Actual          Actual    U234    U235        U238      Total U      Tc-99                                                                            U234        U235        U238  Tc-99 U234 Month                                                                                              99          U234        U-235        U-238      Tc-99                                                      U-235 (uCi) U-238 (uCi) Tc-99 (uCi) kgal/month      gal/month    pCi/L  pCi/L      pCi/L      pCi/L        pCi/L                                                                            pCi/L        pCi/L      pCi/L pCi/L (uCi) pCi/L January    2752.693          2,752,693 17.2    1.36      2.77      21.3          14.0         35.3                179            14        29          146    2.01        0.644        0.820  2.49      21          7            9        26 February    2883.249          2,883,249 16.0    0.723      2.44      19.2          15.1          34.3                175              8        27          165    1.52        0.372        0.596  6.45      17          4            7        70 March    2957.058          2,957,058 26.1    1.15      4.65      31.9          7.02          38.9                292            13        52            79    1.82        0.440        0.775  2.36      20          5             9        26 April    2042.303          2,042,303 23.2    1.27      4.65      29.1          134          163.1              179            10        36          1036    1.70        0.450        0.765  6.26      13          3            6        48 May      2927.395          2,927,395 34.0    1.25       6.17      41.4          157          198.4              377            14        68          1740    2.04        0.442        0.873  6.96      23          5           10        77 June      2428.678          2,428,678 56.4    2.93      8.73      68.1           102          170.1              518            27        80          938    2.92        0.750        1.16  4.74      27          7          11        44 Total (Jan-Jun)   15991.376      15,991,376                                                                                1720            86        292          4102                                            120          31          50        292 Liters (L)                          6.05E+07                                                                                        2098 uCi Uranium for 6-month period Milliliters (ml)                    6.05E+10                                                                                    (all types) 6200 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              1720          +/-        120                    2.84E-08 U235                6.00E-10                  86          +/-          31                    1.41E-09 U238                6.00E-10                292          +/-          50                    4.83E-09 Total U                                      2098                                              3.47E-08 Tc-99              6.00E-10              4102          +/-        292                    6.78E-08 Total (Jan-Jun)                                6200                                              1.37E-07 O:\Regulatory\EH&S Operations\Environment\Environment 2022\Liquid effluent 1st half 2022.xlsx


Attachment 4 Whole Body Dose from Liquid Effluent Pathways - Potable Water Whole Body-Ingestion 5
Table 1. 2022 Semi-Annual Dose to the Public from Liquid and Gaseous Effluents
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 1.720E-03 U-234 release fraction  Ci                                                                                                                              ICRP 69    Comparison 8.600E-05 U-235 release fraction  Ci 2.920E-04 U-238 release fraction  Ci                                                                                                                                            Sv/Bq  Rem/Bq    mRem/pCi 4.102E-03 Tc-99 release fraction  Ci adult      5.00E-08      0.005    1.85E-04 check U sum                          0.00210                                                                                                                                  infant      3.70E-07      0.037    1.37E-03 bone-adult 7.90E-07      0.079    2.92E-03 4.87E-07 U-234                  release fraction *dose factor*exp(-*tp) 2.29E-08 U-235                  release fraction *dose factor*exp(-*tp) 7.43E-08 U-238                  release fraction *dose factor*exp(-*tp) 6.00E-09 Tc-99                  release fraction *dose factor*exp(-*tp) 5.91E-07 all nuclides            sum of nuclides 42.76736 usage                  1100*(usage*dilution)/flow 2.53E-05 mRem                    see regulatory guide 1.109 page 1.109-2 and 1.109-3 for formula and definition of terms.
O:\Regulatory\EH&S Operations\Environment\Environment 2022\Liquid effluent 1st half 2022.xlsx


Attachment 5 Dose to the Bone Surface from Liquid Effluent Pathways - Potable Water Bone Surface-Ingestion 5
Whole Body Dose Organ Dose - Bone Organ Dose - Lung (mrem/6 months) (mrem/6 months) (mrem/6 months)
365 liters                  Usage by adult/6 m U                10CFR20 7.3 x 10 (ml) which is the annual water intake of "Reference Man."
Gaseous Effluents Direct inhalation* 0.08 2.89E-03 0.76
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 1.720E-03 U-234 release fraction  Ci                                                                                                                                  Sv/Bq  Rem/Bq mRem/pCi 8.600E-05 U-235 release fraction  Ci 2.920E-04 U-238 release fraction  Ci                                                                                                                    adult      5.00E-08     0.005 1.85E-04 4.102E-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                          0.00210 7.19E-06 U-234                  release fraction *dose factor*exp(-*tp) 3.34E-07 U-235                  release fraction *dose factor*exp(-*tp) 1.09E-06 U-238                  release fraction *dose factor*exp(-*tp) 9.17E-10 Tc-99                  release fraction *dose factor*exp(-*tp) 8.62E-06 all nuclides            sum of nuclides 42.76736 usage                  1100*(usage*dilution)/flow 3.69E-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 2022\Liquid effluent 1st half 2022.xlsx


Attachment 6 Whole Body Dose from Liquid Effluent Pathways - Aquatic Foods Whole Body 10.5 Kg                      Usage by adult/6 moU                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 1.720E-03  U-234 release fraction  Ci 8.600E-05  U-235 release fraction  Ci                                                                                                                                                                  Sv/Bq    Rem/Bq mRem/pCi 2.920E-04  U-238 release fraction  Ci 4.102E-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                            0.00210                                                                                                                                                        bone-adult 7.90E-07        0.079 2.92E-03 bioaccumulation factor      BNWL-2075 9.75E-07  U-234                  release fraction *bioaccumulation factor*dose factor*exp(-*tp)                                        2            UC-11 4.58E-08  U-235                  release fraction *bioaccumulation factor*dose factor*exp(-*tp)                                        2            Methodology for Calculation of Radiation Doses 1.49E-07  U-238                  release fraction *bioaccumulation factor*dose factor*exp(-*tp)                                        2            in the Environs from Nuclear Fuel 8.99E-08  Tc-99                  release fraction *bioaccumulation factor*dose factor*exp(-*tp)                                        15            Cycle Facilities 1.26E-06 all nuclides            sum of nuclides 1.23029 usage                    1100*(usage*dilution)/flow 1.55E-06 mRem                    see regulatory guide 1.109 page 1.109-2 and 1.109-3 for formula and definition of terms.
Liquid Effluents Potable Water 2.53E-05 3.69E-04 -
O:\Regulatory\EH&S Operations\Environment\Environment 2022\Liquid effluent 1st half 2022.xlsx
Aquatic Food (Fish) 1.55E-06 2.12E-05 -
Shoreline Deposition 1.02E-09 - -
Total (mrem/6 months) 0.08 3.28E-03 0.76
* Assumes 80 % residence time


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 1.720E-03 U-234 release fraCi                                                                                                                                                          Sv/Bq  Rem/Bq mRem/pCi 8.600E-05 U-235 release fraCi 2.920E-04 U-238 release fraCi                                                                                                                                            adult      5.00E-08      0.005 1.85E-04 4.102E-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                    0.00210 bioaccumulation factor    BNWL-2075 1.44E-05 U-234            release fraction *bioaccumulation factor*dose factor*exp(-*tp)                                  2          UC-11 6.68E-07 U-235            release fraction *bioaccumulation factor*dose factor*exp(-*tp)                                  2          Methodology for Calculation of Radiation Doses 2.18E-06 U-238            release fraction *bioaccumulation factor*dose factor*exp(-*tp)                                  2          in the Environs from Nuclear Fuel 1.38E-08 Tc-99            release fraction *bioaccumulation factor*dose factor*exp(-*tp)                                  15          Cycle Facilities 1.72E-05 all nuclides      sum of nuclides 1.23029 usage            1100*(usage*dilution)/flow 2.12E-05 mRem              see regulatory guide 1.109 page 1.109-2 and 1.109-3 for formula and definition of terms.
There were no changes in source material and no release points were added or removed during the 1st half of 2022. 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.
O:\Regulatory\EH&S Operations\Environment\Environment 2022\Liquid effluent 1st half 2022.xlsx
WestinghouseNonProprietaryClass3


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 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)]
Page 3 of 3 Our ref: LTR-EHS-22-39 August 11, 2022
0.0000000147  U-235                    exp(-t-p)*[1-exp(-t-b)]
: 1st Half 2022 Gaseous Effluent Discharges : Lung/Bone Organ Dose due to Gaseous Effluent : 1st Half 2022 Liquid Effluent Discharges : Whole Body Dose from Liqui d Effluent Pathways - Potable Water : Dose to the Bone Surface fro m Liquid Effluent Pathways - Potable Water : Whole Body Dose from Liqui d Effluent Pathways - Aquatic Foods : Dose to the Bone Surface fro m Liquid Effluent Pathways - Aquatic Foods : Whole Body Dose from Liqui d Effluent Pathways - Shoreline Deposits : 2022 Isotopic Fractions 0: Comply Results
0.0000000023  U-238                    exp(-t-p)*[1-exp(-t-b)]
0.0000486679  Tc-99                    exp(-t-p)*[1-exp(-t-b)]
Activity Released 1.720E-03  U-234 release fraction    Ci 8.600E-05  U-235 release fraction    Ci 2.920E-04  U-238 release fraction    Ci 4.102E-03  Tc-99 release fraction    Ci check U sum                            0.00210 6.40E-11  U-234                    release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 6.40E-10  U-235                    release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 8.09E-12  U-238                    release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 1.61E-11  Tc-99                    release fraction *dose factor*exp(-t-p)*1-exp(-t-b)*t-i 7.28E-10 all nuclides              sum of nuclides 1.406050 usage                      11000*(usage*dilution*shore width factor)/flow 1.02E-09 mRem                      see regulatory guide 1.109 page 1.109-2 and 1.109-3 for formula and definition of terms.
see regulatory guide 1.109 page 1.109-40 table A-2,Shore width O:\Regulatory\EH&S Operations\Environment\Environment 2022\Liquid effluent 1st half 2022.xlsx


Attachment 9 2022 Isotopic Fractions Based on the plant nominal enrichment for 2022 Nuclide      Average      Specific Activity        Weighted            %
David Wagoner, CHP Review by: Anna Miller Radiation Safety Engineer Manager, RSO EH&S Operations EH&S Operations
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          95.66            3.360E-07            3.214E-07        11.47 Total          100.0                                  2.803E-06        100.00 O:\Regulatory\EH&S Operations\Environment\Environment 2022\Liquid effluent 1st half 2022.xlsx


Attachment 10 - Comply Results COMPLY: V1.7.                                        8/10/2022 1:19 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.
Attachment 9 2022 Isotopic Fractions
Prepared by:
Westinghouse Electric Co.
Columbia Fuel Fabrication Facility 5801 Bluff Rd. Hopkins, SC 29061 David Wagoner 803.647.1919 Prepared for:
U.S. Environmental Protection Agency Office of Radiation and Indoor Air Washington, DC 20460


2022 SemiAnnual Dose to Public due to Gaseous Effluents
Based on the plant nominal enrichment for 2022


SCREENING LEVEL 2
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 95.66 3.360E-07 3.214E-07 11.47


DATA ENTERED:
Total 100.0 2.803E-06 100.00
RELEASE RATES FOR STACK  1.
Release Rate Nuclide    (curies/SECOND)
U234    Y 9.320E14 U235    Y 3.630E15 U238    Y 1.250E14 RELEASE RATES FOR STACK  2.
Release Rate Nuclide    (curies/SECOND)
U234    Y 1.710E13 U235    Y 6.650E15 U238    Y 2.300E14 RELEASE RATES FOR STACK  3.
Release Rate Nuclide    (curies/SECOND)
U234    Y 1.250E12 U235    Y 4.850E14 U238    Y 1.680E13 RELEASE RATES FOR STACK  4.
Release Rate Nuclide    (curies/SECOND)


U234    Y 4.070E13 U235    Y 1.590E14 U238    Y 5.490E14 RELEASE RATES FOR STACK  5.
O:\\Regulatory\\EH&S Operations\\Environment\\Environment 2022\\Liquid effluent 1st half 2022.xlsx Attachment 10 - Comply Results
Release Rate Nuclide    (curies/SECOND)
U234    Y 2.330E12 U235    Y 9.090E14 U238    Y 3.140E13 RELEASE RATES FOR STACK  6.
Release Rate Nuclide    (curies/SECOND)
U234    Y 9.770E13 U235    Y 3.810E14 U238    Y 1.320E13 RELEASE RATES FOR STACK  7.
Release Rate Nuclide    (curies/SECOND)
U234    Y 8.410E13 U235    Y 3.280E14 U238    Y 1.130E13 RELEASE RATES FOR STACK  8.
Release Rate Nuclide    (curies/SECOND)
U234    Y 4.060E12 U235    Y 1.580E13 U238    Y 5.460E13 RELEASE RATES FOR STACK  9.
Release Rate Nuclide    (curies/SECOND)


U234    Y 9.200E13 U235    Y 3.580E14 U238    Y 1.240E13 RELEASE RATES FOR STACK  10.
COMPLY:V1.7. 8/10/20221:19
Release Rate Nuclide    (curies/SECOND)
U234    Y 3.160E13 U235    Y 1.230E14 U238    Y 4.260E14 RELEASE RATES FOR STACK  11.
Release Rate Nuclide    (curies/SECOND)
U234    Y 1.930E13 U235    Y 7.540E15 U238    Y 2.600E14 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.
40 CFRPart61 NationalEmissionStandards forHazardousAirPollutants
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.
REPORTON COMPLIANCEWITH
Building height 9 meters.
 
The source and receptor are not on the same building.
THECLEANAIRACTLIMITSFORRADIONUCLIDEEMISSIONS
Distance from the source to the receptor is 595 meters.
 
Building width 137 meters.
FROMTHECOMPLYCODEV1.7.
SITE DATA FOR STACK 8.
 
Release height 16 meters.
Preparedby:
Building height 9 meters.
 
The source and receptor are not on the same building.
WestinghouseElectricCo.
Distance from the source to the receptor is 595 meters.
ColumbiaFuelFabricationFacility 5801BluffRd.Hopkins,SC 29061
Building width 137 meters.
 
SITE DATA FOR STACK 9.
DavidWagoner 803.647.1919
Release height 17 meters.
 
Building height 9 meters.
Preparedfor:
The source and receptor are not on the same building.
 
Distance from the source to the receptor is 595 meters.
U.S.EnvironmentalProtectionAgency Officeof RadiationandIndoorAir Washington,DC20460 2022SemiAnnualDosetoPublicduetoGaseousEffluents
Building width 137 meters.
 
SITE DATA FOR STACK 10.
SCREENINGLEVEL2
Release height 19 meters.
 
Building height 9 meters.
DATAENTERED:
The source and receptor are not on the same building.
 
Distance from the source to the receptor is 595 meters.
RELEASERATESFORSTACK1.
Building width 137 meters.
 
SITE DATA FOR STACK 11.
ReleaseRate Nuclide(curies/SECOND)
Release height 20 meters.
 
U234Y9.320E14 U235Y3.630E15 U238Y1.250E14
 
RELEASERATESFORSTACK2.
 
ReleaseRate Nuclide(curies/SECOND)
 
U234Y1.710E13 U235Y6.650E15 U238Y2.300E14
 
RELEASERATESFORSTACK3.
 
ReleaseRate Nuclide(curies/SECOND)
 
U234Y1.250E12 U235Y4.850E14 U238Y1.680E13
 
RELEASERATESFORSTACK4.
 
ReleaseRate Nuclide(curies/SECOND)
 
U234Y4.070E13 U235Y1.590E14 U238Y5.490E14
 
RELEASERATESFORSTACK5.
 
ReleaseRate Nuclide(curies/SECOND)
 
U234Y2.330E12 U235Y9.090E14 U238Y3.140E13
 
RELEASERATESFORSTACK6.
 
ReleaseRate Nuclide(curies/SECOND)
 
U234Y9.770E13 U235Y3.810E14 U238Y1.320E13
 
RELEASERATESFORSTACK7.
 
ReleaseRate Nuclide(curies/SECOND)
 
U234Y8.410E13 U235Y3.280E14 U238Y1.130E13
 
RELEASERATESFORSTACK8.
 
ReleaseRate Nuclide(curies/SECOND)
 
U234Y4.060E12 U235Y1.580E13 U238Y5.460E13
 
RELEASERATESFORSTACK9.
 
ReleaseRate Nuclide(curies/SECOND)
 
U234Y9.200E13 U235Y3.580E14 U238Y1.240E13
 
RELEASERATESFORSTACK10.
 
ReleaseRate Nuclide(curies/SECOND)
 
U234Y3.160E13 U235Y1.230E14 U238Y4.260E14
 
RELEASERATESFORSTACK11.
 
ReleaseRate Nuclide(curies/SECOND)
 
U234Y1.930E13 U235Y7.540E15 U238Y2.600E14
 
SITEDATAFORSTACK1.
 
Releaseheight9meters.
 
Buildingheight9meters.
 
Thesourceandreceptorarenotonthesamebuilding.
 
Distancefromthesourcetothereceptoris595meters.
 
Buildingwidth137meters.
 
SITEDATAFORSTACK2.
 
Releaseheight10meters.
 
Buildingheight9meters.
 
Thesourceandreceptorarenotonthesamebuilding.
 
Distancefromthesourcetothereceptoris595meters.
 
Buildingwidth137meters.
 
SITEDATAFORSTACK3.
 
Releaseheight11meters.
 
Buildingheight9meters.
 
Thesourceandreceptorarenotonthesamebuilding.
 
Distancefromthesourcetothereceptoris595meters.
 
Buildingwidth137meters.
 
SITEDATAFORSTACK4.
 
Releaseheight12meters.
 
Buildingheight9meters.
 
Thesourceandreceptorarenotonthesamebuilding.
 
Distancefromthesourcetothereceptoris595meters.
 
Buildingwidth137meters.
 
SITEDATAFORSTACK5.
 
Releaseheight13meters.
 
Buildingheight9meters.
 
Thesourceandreceptorarenotonthesamebuilding.
 
Distancefromthesourcetothereceptoris595meters.
 
Buildingwidth137meters.
 
SITEDATAFORSTACK6.
 
Releaseheight14meters.
 
Buildingheight9meters.
 
Thesourceandreceptorarenotonthesamebuilding.
 
Distancefromthesourcetothereceptoris595meters.
 
Buildingwidth137meters.
 
SITEDATAFORSTACK7.
 
Releaseheight15meters.
 
Buildingheight9meters.
 
Thesourceandreceptorarenotonthesamebuilding.
 
Distancefromthesourcetothereceptoris595meters.
 
Buildingwidth137meters.
 
SITEDATAFORSTACK8.
 
Releaseheight16meters.
 
Buildingheight9meters.
 
Thesourceandreceptorarenotonthesamebuilding.
 
Distancefromthesourcetothereceptoris595meters.
 
Buildingwidth137meters.
 
SITEDATAFORSTACK9.
 
Releaseheight17meters.
 
Buildingheight9meters.
 
Thesourceandreceptorarenotonthesamebuilding.
 
Distancefromthesourcetothereceptoris595meters.
 
Buildingwidth137meters.
 
SITEDATAFORSTACK10.
 
Releaseheight19meters.
 
Buildingheight9meters.
 
Thesourceandreceptorarenotonthesamebuilding.
 
Distancefromthesourcetothereceptoris595meters.
 
Buildingwidth137meters.
 
SITEDATAFORSTACK11.
 
Releaseheight20meters.
 
Buildingheight9meters.
 
Thesourceandreceptorarenotonthesamebuilding.
 
Distancefromthesourcetothereceptoris595meters.
 
Buildingwidth137meters.
 
Defaultmeanwindspeedused(2.0m/sec).


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:
NOTES:
Input parameters outside the "normal" range:
 
Building (width) is unusually WIDE.
Inputparametersoutsidethe"normal"range:
Receptor is unusually FAR.
 
Building(width)isunusuallyWIDE.
ReceptorisunusuallyFAR.
 
RESULTS:
RESULTS:
Effective dose equivalent:        0.2 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.                                         8/10/2022 1:09 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.
Effectivedoseequivalent:0.2mrem/yr.
Prepared by:
 
Westinghouse Electric Co.
***Complyatlevel2.
Columbia Fuel Fabrication Facility 5801 Bluff Rd. Hopkins, SC 29061 David Wagoner 803.647.1919 Prepared for:
 
U.S. Environmental Protection Agency Office of Radiation and Indoor Air Washington, DC 20460
ThisfacilityisinCOMPLIANCE.
 
ItmayormaynotbeEXEMPTfromreportingtotheEPA.
 
YoumaycontactyourregionalEPAofficeformoreinformation.
 
**********ENDOFCOMPLIANCEREPORT**********
 
COMPLY:V1.7. 8/10/20221:09
 
40CFRPart61 NationalEmissionStandards forHazardousAirPollutants
 
REPORTONCOMPLIANCEWITH
 
THECLEANAIRACTLIMITSFORRADIONUCLIDEEMISSIONS
 
FROMTHECOMPLYCODEV1.7.
 
Preparedby:
 
WestinghouseElectricCo.
ColumbiaFuelFabricationFacility 5801BluffRd.Hopkins,SC29061
 
DavidWagoner 803.647.1919
 
Preparedfor:
 
U.S.EnvironmentalProtectionAgency OfficeofRadiationandIndoorAir Washington,DC20460
 
IncineratorExh
 
SCREENINGLEVEL2
 
DATAENTERED:
 
ReleaseRate Nuclide(curies/SECOND)
 
U234Y3.230E12 U235Y1.260E13 U238Y4.340E13
 
Releaseheight16meters.
 
Buildingheight9meters.
 
Thesourceandreceptorarenotonthesamebuilding.


Incinerator Exh
Distancefromthesourcetothereceptoris595meters.


SCREENING LEVEL 2
Buildingwidth137meters.
 
Defaultmeanwindspeedused(2.0m/sec).


DATA ENTERED:
Release Rate Nuclide      (curies/SECOND)
U234      Y 3.230E12 U235      Y 1.260E13 U238      Y 4.340E13 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:
NOTES:
Input parameters outside the "normal" range:
 
Building (width) is unusually WIDE.
Inputparametersoutsidethe"normal"range:
Receptor is unusually FAR.
 
Building(width)isunusuallyWIDE.
ReceptorisunusuallyFAR.
 
RESULTS:
RESULTS:
Effective dose equivalent:      6.4E02 mrem/yr.
    *** Comply at level 2.


This facility is in COMPLIANCE.
Effectivedoseequivalent:6.4E02mrem/yr.
It may or may not be EXEMPT from reporting to the EPA.
 
You may contact your regional EPA office for more information.
***Complyatlevel2.
********** END OF COMPLIANCE REPORT **********}}
 
ThisfacilityisinCOMPLIANCE.
 
ItmayormaynotbeEXEMPTfromreportingtotheEPA.
 
YoumaycontactyourregionalEPAofficeformoreinformation.
 
**********ENDOFCOMPLIANCEREPORT**********}}

Revision as of 05:14, 16 November 2024

Westinghouse, NRC Semi-Annual Discharge Report January - June 2022
ML22228A181
Person / Time
Site: Westinghouse
Issue date: 08/16/2022
From: Ferguson J
Westinghouse, Westinghouse
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
LTR-RAC-22-45
Download: ML22228A181 (24)
v • d • e


Text

Page 1 of 2 8 Westinghouse Westinghouse Electric Company LLC Nuclear Fuel Columbia Fuel Site 5807 Bluff Road Hopkins, South Carolina 29067 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: L TR-RAC-22-45 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, Georgia 30303-1257

Subject:

SNM-1107/70-1151 NRC Semi-Annual Discharge Report August16,2022 January - June 2022

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, 2022, through June 30, 2022, the following quantities of radionuclides were released to the unrestricted area by the Westinghouse Electric Company's Columbia, South Carolina Nuclear Fuel Plant:

Total Total Regulatory Discharge emissions Parameter Measured Concentration 6-month 6-month

(µCi) Concentration Limit Gaseous 213.3 Uranium (analyzed as 1.6E-16 µCi/ml* 5 E-14 µCi/ml gross alpha) 1,720 U-234 Liquid 86 U-235 3.5E-08 µCi/ml 3 E-07 µCi/ml Effluent# 292 U-238 4,102 Tc-99 6.SE-08 µCi/ml 6 E- 05 µCi/ml

  • Includes a dispersion factor of 1000 to account for dilution between the release point and the nearest site boundary.
  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 2022 was 6.05 E+ 10 milliliters (ml).

© 2022 Westinghouse Electric Company LLC All Rights Reserved Page 2 of 2 Our ref: L TR-RAC-22-45 August 16, 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, L TR EHS-22-39, "2022 Semi-Annual Assessment of Public Dose due to Liquid and Gaseous Effluents" is attached.

Sincerely, Jeffllt~

Manager, Environment, Health and Safety

Attachment:

L TR-EHS-22-39, "2022 Semi-Annual Assessment of Public Dose due to Liquid and Gaseous Effluents" WestinghouseNonProprietaryClass3 Page 1 of 3

Westinghouse Electric Company Nuclear Fuel Columbia Fuel Site 5801 Bluff Rd Hopkins, South Carolina 29061 USA

To: Cynthia Teague, Diana Joyner Date: August 11, 2022

cc: Jeff Ferguson, Patrick Donnelly, Nancy Parr, Anna Miller

From: David Wagoner Your ref:

Ext: 1919 Our ref: LTR-EHS-22-39 Fax: 803.695.4158

Subject:

2022 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 #1208 (Incinerator Exh), the measured release quantity, and the dose conversion factors from Federal Guidance Report No 11, Limiting Values of Radionuclide Intake and Air concentration Factors for Inhalation, Submersion, and Ingestion (FGR 11).

Dose due to Liquid Effluents by Ingestion of Potable Water Estimated using equations and recommended values in Regulatory Guide 1.109, Doses from Liquid Effluent Pathways (RG 1.109). Dose conversion factors are referenced from FGR 11.

Dose due to Liquid Effluents by Ingestion of Fish Estimated using equations and recommended values in RG 1.109. Dose conversion factors are referenced from FGR 11.

Dose due to Liquid Effluents by Irradiation from Shoreline Deposition Estimated using equations and recommended values in RG 1.109. Dose conversion factors are referenced from Federal Guidance report No 12, External Exposure to Radionuclides in Air, Water, and Soil.

Bounding dose assessments for direct inhalation and for ingestion are performed using conservative assumptions to determine the maximum potential dose to a hypothetical individual member of the public. The inhalation dose is determined for the hypothetical individual standing at the nearest site

© 2022 Westinghouse Electric Company LLC All Rights Reserved WestinghouseNonProprietaryClass3

Page 2 of 3 Our ref: LTR-EHS-22-39 August 11, 2022

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 fo r 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 1 st half of calendar year 2022:

213.3 µCi of Uranium in gaseous effluent 2,098 µCi of Uranium in liquid effluent 4,102 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 2022 resulted in a potential whole body dose of 0.08 mrem, 0.76 mrem to the lung, and 0.003 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. 2022 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* 0.08 2.89E-03 0.76

Liquid Effluents Potable Water 2.53E-05 3.69E-04 -

Aquatic Food (Fish) 1.55E-06 2.12E-05 -

Shoreline Deposition 1.02E-09 - -

Total (mrem/6 months) 0.08 3.28E-03 0.76

  • Assumes 80 % residence time

There were no changes in source material and no release points were added or removed during the 1st half of 2022. 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.

WestinghouseNonProprietaryClass3

Page 3 of 3 Our ref: LTR-EHS-22-39 August 11, 2022

1st Half 2022 Gaseous Effluent Discharges : Lung/Bone Organ Dose due to Gaseous Effluent : 1st Half 2022 Liquid Effluent Discharges : Whole Body Dose from Liqui d Effluent Pathways - Potable Water : Dose to the Bone Surface fro m Liquid Effluent Pathways - Potable Water : Whole Body Dose from Liqui d Effluent Pathways - Aquatic Foods : Dose to the Bone Surface fro m Liquid Effluent Pathways - Aquatic Foods : Whole Body Dose from Liqui d Effluent Pathways - Shoreline Deposits : 2022 Isotopic Fractions 0: Comply Results

David Wagoner, CHP Review by: Anna Miller Radiation Safety Engineer Manager, RSO EH&S Operations EH&S Operations

Attachment 9 2022 Isotopic Fractions

Based on the plant nominal enrichment for 2022

Nuclide Average Specific Activity Weighted %

wt% Ci/g Activity Activity U-234 0.04 6.220E-03 2.388E-06 85.21 U-235 4.31 2.160E-06 9.307E-08 3.32 U-238 95.66 3.360E-07 3.214E-07 11.47

Total 100.0 2.803E-06 100.00

O:\\Regulatory\\EH&S Operations\\Environment\\Environment 2022\\Liquid effluent 1st half 2022.xlsx Attachment 10 - Comply Results

COMPLY:V1.7. 8/10/20221:19

40 CFRPart61 NationalEmissionStandards forHazardousAirPollutants

REPORTON COMPLIANCEWITH

THECLEANAIRACTLIMITSFORRADIONUCLIDEEMISSIONS

FROMTHECOMPLYCODEV1.7.

Preparedby:

WestinghouseElectricCo.

ColumbiaFuelFabricationFacility 5801BluffRd.Hopkins,SC 29061

DavidWagoner 803.647.1919

Preparedfor:

U.S.EnvironmentalProtectionAgency Officeof RadiationandIndoorAir Washington,DC20460 2022SemiAnnualDosetoPublicduetoGaseousEffluents

SCREENINGLEVEL2

DATAENTERED:

RELEASERATESFORSTACK1.

ReleaseRate Nuclide(curies/SECOND)

U234Y9.320E14 U235Y3.630E15 U238Y1.250E14

RELEASERATESFORSTACK2.

ReleaseRate Nuclide(curies/SECOND)

U234Y1.710E13 U235Y6.650E15 U238Y2.300E14

RELEASERATESFORSTACK3.

ReleaseRate Nuclide(curies/SECOND)

U234Y1.250E12 U235Y4.850E14 U238Y1.680E13

RELEASERATESFORSTACK4.

ReleaseRate Nuclide(curies/SECOND)

U234Y4.070E13 U235Y1.590E14 U238Y5.490E14

RELEASERATESFORSTACK5.

ReleaseRate Nuclide(curies/SECOND)

U234Y2.330E12 U235Y9.090E14 U238Y3.140E13

RELEASERATESFORSTACK6.

ReleaseRate Nuclide(curies/SECOND)

U234Y9.770E13 U235Y3.810E14 U238Y1.320E13

RELEASERATESFORSTACK7.

ReleaseRate Nuclide(curies/SECOND)

U234Y8.410E13 U235Y3.280E14 U238Y1.130E13

RELEASERATESFORSTACK8.

ReleaseRate Nuclide(curies/SECOND)

U234Y4.060E12 U235Y1.580E13 U238Y5.460E13

RELEASERATESFORSTACK9.

ReleaseRate Nuclide(curies/SECOND)

U234Y9.200E13 U235Y3.580E14 U238Y1.240E13

RELEASERATESFORSTACK10.

ReleaseRate Nuclide(curies/SECOND)

U234Y3.160E13 U235Y1.230E14 U238Y4.260E14

RELEASERATESFORSTACK11.

ReleaseRate Nuclide(curies/SECOND)

U234Y1.930E13 U235Y7.540E15 U238Y2.600E14

SITEDATAFORSTACK1.

Releaseheight9meters.

Buildingheight9meters.

Thesourceandreceptorarenotonthesamebuilding.

Distancefromthesourcetothereceptoris595meters.

Buildingwidth137meters.

SITEDATAFORSTACK2.

Releaseheight10meters.

Buildingheight9meters.

Thesourceandreceptorarenotonthesamebuilding.

Distancefromthesourcetothereceptoris595meters.

Buildingwidth137meters.

SITEDATAFORSTACK3.

Releaseheight11meters.

Buildingheight9meters.

Thesourceandreceptorarenotonthesamebuilding.

Distancefromthesourcetothereceptoris595meters.

Buildingwidth137meters.

SITEDATAFORSTACK4.

Releaseheight12meters.

Buildingheight9meters.

Thesourceandreceptorarenotonthesamebuilding.

Distancefromthesourcetothereceptoris595meters.

Buildingwidth137meters.

SITEDATAFORSTACK5.

Releaseheight13meters.

Buildingheight9meters.

Thesourceandreceptorarenotonthesamebuilding.

Distancefromthesourcetothereceptoris595meters.

Buildingwidth137meters.

SITEDATAFORSTACK6.

Releaseheight14meters.

Buildingheight9meters.

Thesourceandreceptorarenotonthesamebuilding.

Distancefromthesourcetothereceptoris595meters.

Buildingwidth137meters.

SITEDATAFORSTACK7.

Releaseheight15meters.

Buildingheight9meters.

Thesourceandreceptorarenotonthesamebuilding.

Distancefromthesourcetothereceptoris595meters.

Buildingwidth137meters.

SITEDATAFORSTACK8.

Releaseheight16meters.

Buildingheight9meters.

Thesourceandreceptorarenotonthesamebuilding.

Distancefromthesourcetothereceptoris595meters.

Buildingwidth137meters.

SITEDATAFORSTACK9.

Releaseheight17meters.

Buildingheight9meters.

Thesourceandreceptorarenotonthesamebuilding.

Distancefromthesourcetothereceptoris595meters.

Buildingwidth137meters.

SITEDATAFORSTACK10.

Releaseheight19meters.

Buildingheight9meters.

Thesourceandreceptorarenotonthesamebuilding.

Distancefromthesourcetothereceptoris595meters.

Buildingwidth137meters.

SITEDATAFORSTACK11.

Releaseheight20meters.

Buildingheight9meters.

Thesourceandreceptorarenotonthesamebuilding.

Distancefromthesourcetothereceptoris595meters.

Buildingwidth137meters.

Defaultmeanwindspeedused(2.0m/sec).

NOTES:

Inputparametersoutsidethe"normal"range:

Building(width)isunusuallyWIDE.

ReceptorisunusuallyFAR.

RESULTS:

Effectivedoseequivalent:0.2mrem/yr.

      • Complyatlevel2.

ThisfacilityisinCOMPLIANCE.

ItmayormaynotbeEXEMPTfromreportingtotheEPA.

YoumaycontactyourregionalEPAofficeformoreinformation.

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

COMPLY:V1.7. 8/10/20221:09

40CFRPart61 NationalEmissionStandards forHazardousAirPollutants

REPORTONCOMPLIANCEWITH

THECLEANAIRACTLIMITSFORRADIONUCLIDEEMISSIONS

FROMTHECOMPLYCODEV1.7.

Preparedby:

WestinghouseElectricCo.

ColumbiaFuelFabricationFacility 5801BluffRd.Hopkins,SC29061

DavidWagoner 803.647.1919

Preparedfor:

U.S.EnvironmentalProtectionAgency OfficeofRadiationandIndoorAir Washington,DC20460

IncineratorExh

SCREENINGLEVEL2

DATAENTERED:

ReleaseRate Nuclide(curies/SECOND)

U234Y3.230E12 U235Y1.260E13 U238Y4.340E13

Releaseheight16meters.

Buildingheight9meters.

Thesourceandreceptorarenotonthesamebuilding.

Distancefromthesourcetothereceptoris595meters.

Buildingwidth137meters.

Defaultmeanwindspeedused(2.0m/sec).

NOTES:

Inputparametersoutsidethe"normal"range:

Building(width)isunusuallyWIDE.

ReceptorisunusuallyFAR.

RESULTS:

Effectivedoseequivalent:6.4E02mrem/yr.

      • Complyatlevel2.

ThisfacilityisinCOMPLIANCE.

ItmayormaynotbeEXEMPTfromreportingtotheEPA.

YoumaycontactyourregionalEPAofficeformoreinformation.

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