ML19123A203
| ML19123A203 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 04/18/2019 |
| From: | Southern Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19123A207 | List: |
| References | |
| NL-19-0486 | |
| Download: ML19123A203 (75) | |
Text
Edwin I. Hatch Nuclear Plant - Units 1 &2 Joseph M. Farley Nuclear Plant - Units 1 &2 Vogtle Electric Generating Plant - Units 1 &2 Annual Non-Radiological Environmental Operating Reports, Annual Radioactive Effluent Release Reports, and Offsite Dose Calculation Manual for 2018 Joseph M. Farley Nuclear Plant - Units 1 &2 Annual Radioactive Effluent Release Report for 2018
SOUTHERN NUCLEAR OPERATING COMPANY FARLEY NUCLEAR PLANT UNIT NO. ONE LICENSE NO. NPF-2 AND FARLEY NUCLEAR PLANT UNIT NO. TWO LICENSE NO. NPF-8 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CALENDAR YEAR 2018
ACKNOWLEDGEMENT OF OWNERSHIP The contents of this Annual Radioactive Effluent Release Report, contained herein, are true and accurate to the best of my knowledge. I understand that I am ultimately responsible for the information that has been captured within these pages.
Valencia Flowers Farley Chemistry Manager 5 ~
-")-/fl-! g Nuclear Chemist
___,~,4i,,,F'C;....:::;...__-....,.__::::~::..__--'-* ___
o_'i I 11 I rf Stephen Colvin Chemistry Support Superintendent
SECTION 1.0 1.1 1.1.1 1.1.2 1.2 1.3 1.3.1 1.3.2 1.4 1.5 1.6 1.7 2.0 2.1 2.1.1 2.1.2 2.1.3 2.2 2.2.1 FARLEY NUCLEAR PLANT ANNUAL RADI0AC11VE EFFLUENT RELEASE REPORT TITLE LIQUID EFFLUENTS Regulatory Requirements Concentration Limits Dose Limits Effluent Concentration Limit (ECL)
Measurements and Approximation of Total Radioactivity Total Radioactivity Determination Total Error Estimation Liquid Effluents - Release Data Radiological Impact Due to Liquid Releases Liquid Effluents - Batch Releases Liquid Effluents - Abnormal Releases GASEOUS EFFLUENTS Regulatory Requirements Dose Rate Limits Air Doses Due to Noble Gases in Gaseous Releases Doses to a Member of the Public Measurements and Approximation of Total Radioactivity Sample Collection and Analysis PAGE 1
1 1
1 1
2 2
3 3
3 3
3 25 25 25 25 25 26 26
SECTION 2.2.2 2.2.2.1 2.2.2.2 2.2.2.3 2.2.3 2.3 2.4 2.5 2.6 3.0 3.1 3.1.1 3.1.2 3.2 4.0 4.1 4.2 FARLEY NUCLEAR PLANT ANNUAL RADIOACITVE EFFLUENT RELEASE REPORT TITLE Total Quantities of Radioactivity, Dose Rates and Cumulative Doses Fission and Activation Gases Radioiodine, Tritium and Particulate Releases Gross Alpha Release Total Error Estimation Gaseous Effluent Release Data Radiological Impact Due to Gaseous Releases Gaseous Effluents - Batch Releases Gaseous Effluents - Abnormal Releases SOLID WASTE Regulatory Requirements Solid Radioactive Waste System Reporting Requirements Solid Waste Data DOSES TO MEMBERS OF THE PUBLIC INSIDE THE SITE BOUNDARY Regulatory Requirements Demonstration of Compliance PAGE 26 27 27 28 28 28 29 29 29 54 54 54 54 54 57 57 57
SECTION 5.0 5.1 5.2 6.0 7.0 7.1 7.1.1 7.1.2 7.2 7.2.1 7.2.2 7.3 7.3.1 7.3.2 8.0 8.1 8.2 FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TITLE TOTAL DOSE FROM URANIUM FUEL CYCLE (40CFR190)
Regulatory Requirements Demonstration of Compliance METEOROLOGICAL DATA PROGRAM DEVIATIONS Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation Regulatory Requirements Description of Deviations Effluent Sample Analysis Exceeding Minimum Detectable Concentration (MDC)
Regulatory Requirements Description of Deviations Incorrect Compositing of Liquid or Gaseous Effluent Samples Regulatory Requirements Description of Deviations CHANGES TO THE PLANT FARLEY ODCM Regulatory Requirements Description of Changes PAGE 61 61 61 61 61 61 61 61 62 62 62 62 62 62 62 62 62
SECTION 9.0 9.1 9.2 App.A App.B FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TITLE MAJOR CHANGES TO LIQUID, GASEOUS, OR SOLID RADWASTE TREATMENT SYSTEMS Regulatory Requirements Description of Major Changes Appendix A, Carbon-14 Supplement for 2018 Appendix B, Correction to 2018 Annual Radioactive Effluent Release Report PAGE 63 63 63 64 65
TABLE 1-lA 1-18 1-lC 1-2A 1-2B 1-2C 1-3A 1-3B 1-4 1-SA 1-SB 1-6A 1-6B FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIST OF TABLES Liquid Effluents - Summation of All Releases, Unit 1 (Quarters 1,2, 3 and
- 4)
Liquid Effluents - Summation of All Releases, Unit 2 (Quarters 1,2, 3 and
- 4)
Liquid Effluents - Summation of All Releases, Site (Quarters 1,2, 3 and 4)
Liquid Effluents, Unit 1 (Quarters 1,2, 3 and 4)
Liquid Effluents, Unit 2 (Quarters 1,2, 3 and 4)
Liquid Effluents, Site (Quarters 1,2, 3 and 4)
Doses to a MEMBER OF THE PUBLIC Due to Liquid Releases, Unit 1 (Quarters 1,2,3 and 4)
Doses to a MEMBER OF THE PUBLIC Due to Liquid Releases, Unit 2 (Quarters 1,2,3 and 4)
Minimum Detectable Concentration - Liquid Sample Analyses Liquid Effluents - Batch Release Summary, Unit 1 Liquid Effluents - Batch Release Summary, Unit 2 Liquid Effluents - Abnormal Release Summary, Unit 1 Liquid Effluents - Abnormal Release Summary, Unit 2 PAGE 4
5 6
7 10 14 18 19 20 21 22 23 24 J
TABLE 2-1A 2-1B 2-1C 2-2A 2-2B 2-2C 2-3A 2-3B 2-3C FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIST OF TABLES Gaseous Effluents - Summation of All Releases, Unit 1 (Quarters 1,2; 3 and 4)
Gaseous Effluents - Summation of All Releases, Unit 2 (Quarters 1,2, 3 and 4)
Gaseous Effluents - Summation of All Releases, Site (Quarters 1,2, 3 and
- 4)
Gaseous Effluents - Mixed Mode Level Releases, Unit 1 (Quarters 1,2, 3 and 4)
Gaseous Effluents - Mixed Mode Level Releases, Unit 2 (Quarters 1,2, 3 and 4)
Gaseous Effluents - Mixed Mode Level Releases, Site (Quarters 1,2, 3 and 4)
Gaseous Effluents - Ground Level Releases, Unit 1 (Quarters 1,2, 3 and
- 4)
Gaseous Effluents - Ground Level Releases, Unit 2 (Quarters 1,2, 3 and
- 4)
Gaseous Effluents - Ground Level Releases, Site (Quarters 1,2, 3 and 4)
PAGE 30 31 32 33 35 37 39 41 43
TABLE 2-4A 2-4B 2-SA 2-SB 2-6 2-7A 2-7B 2-8A 2-8B 3-1 4-1 FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIST OF TABLES Air Doses Due to Noble Gases in Gaseous Releases, Unit 1 (Quarters 1,2, 3 and 4)
Air Doses Due to Noble Gases in Gaseous Releases, Unit 2 (Quarters 1,2, 3 and 4)
Doses to a MEMBER OF THE PUBLIC Due to Radioiodines, Tritium, and Particulates in Gaseous Releases, Unit 1 (Quarters 1,2,3 and 4)
Doses to a MEMBER OF THE PUBLIC Due to Radioiodines, Tritium, and Particulates in Gaseous Releases, Unit 2 (Quarters 1,2,3 and 4)
Minimum Detectable Concentration - Gaseous Effluent Analyses Gaseous Effluents - Batch Release Summary, Unit 1 Gaseous Effluents - Batch Release Summary, Unit 2 Gaseous Effluents - Abnormal Release Summary, Unit 1 Gaseous Effluents - Abnormal Release Summary, Unit 2 Solid Waste and Irradiated Fuel Shipments Doses to a MEMBER OF THE PUBLIC Due to Activities Inside the Site Boundary, Site PAGE 45 46 47 48 49 so 51 52 53 55 58
1.0 LIQUID EFFLUENTS This section contains applicable ODCM limits for liquid effluents as well as the quantities of radioactive liquid effluents released during 2018. These quantities are summarized on a quarterly basis and include any unplanned releases. A tabulation of the total body and organ doses which were calculated in accordance with ODCM 2.4 are presented to show conformance with the limits of ODCM 2.1.3.
1.1 Regulatory Requirements 1.1.1 Concentration Limits Technical Specifications 5.5.4.b and 5.5.4.c state that the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see ODCM Figure 10-1) shall be limited at all times to ten times the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 1.0E-04 µCi/ml total activity.
1.1.2 Dose Limits Technical Specifications 5.5.4.d and 5.5.4.e state that the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see ODCM Figure 10-1) shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and
- b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
1.2 Effluent Concentration Limit (ECL)
ECL values used in determining allowable liquid radwaste release rates and concentrations, for principal gamma emitters, I-131, tritium, Sr-89, Sr-90, and Fe-55, are taken from 10CFR Part 20, Appendix B, Table 2, Column 2. A tolerance factor of 10 is utilized to allow flexibility in establishing practical monitor setpoints which can accommodate effluent releases at concentrations higher than the ECL values stated in 10CFR20, Appendix B, Table 2, Column 2.
For dissolved or entrained noble gases in liquid radwaste, the ECL is 1.0E-04 uCi/ml total activity.
For gross alpha in liquid radwaste, the ECL is 2.0E-09 1,.1Ci/ml.
Furthermore, for all the above radionuclides, or categories of radioactivity, the overall ECL fraction is determined in accordance with 10CFR Part 20, Appendix B.
1 -
1.3 Measurements and Approximation of Total Radioactivity The radionuclides listed below are specifically considered when evaluating liquid effluents:
MN-54 FE-59 C0-58 C0-60 ZN-65 SR-89 SR-90 1-131 CS-134 CS-137 CE-141 CE-144 M0-99 FE-55 H-3 1.3.1 Total Radioactivity Determination Batch Releases: Representative pre-release grab samples are obtained and analyzed in accordance with ODCM Table 2-3. Isotopic analyses are performed by the computerized pulse height analysis system utilizing high resolution germanium detectors. Isotopic radionuclide concentrations thus obtained are used for release rate calculations as specified in the ODCM. Only those nuclides that are detected are used in the calculations. All Gross Alpha, Strontium, and Iron-55, samples are sent offsite to the Georgia Power Environmental Laboratory for analysis. Gross beta determinations are made using 2 pi gas flow proportional counters. Tritium determinations are made using liquid scintillation techniques. Dissolved gases are determined employing grab sampling techniques and then counting on the gamma spectrometry system.
The sample analyses results are used along with the ECL values to determine the ECL fraction for the planned release. The ECL fraction is then used, with the appropriate safety factors, and the expected dilution stream flow, to calculate the maximum permissible release rate and a liquid effluent monitor setpoint. The monitor setpoint is calculated to assure that the limits of the ODCM are not exceeded. A monitor reading in excess of the calculated setpoint will result in automatic termination of the liquid radwaste discharge.
Radionuclide concentrations, safety factors, dilution stream flow rate, and liquid effluent radiation monitor calibration factors are used by the computer to generate a pre-release printout. If the release is not permissible, appropriate warnings will be displayed on the computer screen and on the printout. If the release is permissible, it is approved by a Chemistry Technician. The release permit is transferred from the Chemistry Department to the Operations Department for release.
When the release is completed, the actual release data are provided to the Chemistry Department.
These release data, including release rate and release duration, are input into the computer and a post-release printout is generated. This printout contains the actual release rates, radionuclide concentrations and quantities, dilution flow, and calculated doses to an individual.
Continuous Releases: Continuous releases are analogous to batch releases except that they are analyzed on a weekly composite basis in accordance with ODCM Table 2-3.
Typically achieved liquid effluent sample analyses minimum detectable concentrations are reported in Table 1-4.
2 -
1.3.2 Total Error Estimation The maximum error associated with volume and flow measurements, based upon plant calibration practice is estimated to be + or - 10%. The average error associated with counting is estimated to be less than + or - 15%.
1.4 Liquid Effluent Release Data Summaries of all radioactive liquid effluents released from Units 1 and 2 during 2018 are presented in accordance with Regulatory Guide 1.21 Tables 2A and 28. Information required by Table 2A is found in this report in Tables 1-lA, 1-18, and 1-lC; Table 2-8 information is presented in Tables 1-2A, 1-28, and 1-2C. Data is presented on a quarterly basis as required by Regulatory Guide 1.21 for all four quarters.
1.5 Radiological Impact Due to Liquid Releases The total body and organ doses for Units 1 and 2 are provided in the following tables in order to show conformance with the limits of ODCM 2.1.3:
Unit 1 2018 Doses to a Member of the Public due to Liquid Releases: Table 1-3A Unit 2 2018 Doses to a Member of the Public due to Liquid Releases: Table 1-38 1.6 Liquid Effluents - Batch Releases Batch release information for Units 1 and 2 is summarized in the following tables:
Unit 1 2018 Liquid Effluents - Batch Release Summary: Table 1-SA Unit 2 2018 Liquid Effluents - Batch Release Summary: Table 1-58 1.7 Liquid Effluents -Abnormal Releases There were no abnormal releases during 2018.
Abnormal release information for Units 1 and 2 is summarized in the following tables:
Unit 1 2018 Liquid Effluents - Abnormal Release Summary: Table 1-6A Unit 2 2018 Liquid Effluents - Abnormal Release Summary: Table 1-6 3 -
Type of Effluent A. Fission And Activation Products
- 1. Total Release (not including tritium, gases, alpha)
- 2. Average diluted concentration during period
- 3. Percent of Applicable Limit B. Tritium
- 1. Total Release
- 2. Average diluted Concentration during period
- 3. Percent of Applicable Limit C. Dissolved and Entrained Gases
- 1. Total Release
- 2. Average diluted Concentration during period
- 3. Percent of Applicable Limit D: Gross Alpha Radioactivity
- 1. Total Release E: Waste Vol Release (Pre-Dilution)
F. Volume of Dilution Water Used Units Curies uCi/mL Curies uCi/mL Curies uCi/mL Curies Liters Liters Table 1-lA Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Liquid Effluents - Summation of All Releases Unit:
1 Starting: 1-Jan-2018 Ending: 31-Dec-2018 1ST Quarter l.94E-02 l.OOE-08 4.56E+02 2.35E-04 9.42E-03 4.87E-09 0.00E+OO 2.27E+06 l.93E+09 2ND Quarter 2.52E-02 2.06E-08 3.51E+Ol 2.87E-05 2.48E-03 2.03E-09 0.00E+OO l.25E+06 1.22E+09 3RD Quarter 5.66E-02 2.97E-08 7.59E+Ol 3.98E-05 9.86E-05 5.18E-ll O.OOE+OO 2.95E+06 l.90E+09
- Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.
4 -
4TH Quarter 4.6IE-02 l.23E-08 2.76E+02 7.34E-05 9.29E-05 2.47E-11 O.OOE+OO 1.2IE+06 3.76E+09
Type of Effluent A. Fission And Activation Products
- 1. Total Release (not including tritium, gases, alpha)
- 2. Average diluted concentration during period
- 3. Percent of Applicable Limit B. Tritium I. Total Release
- 2. Average diluted Concentration during period
- 3. Percent of Applicable Limit C. Dissolved and Entrained Gases
- 1. Total Release
- 2. Average diluted Concentration during period
- 3. Percent of Applicable Limit D: Gross Alpha Radioactivity
- 1. Total Release E: Waste Vol Release (Pre-Dilution)
F. Volume of Dilution Water Used Units Curies uCi/mL Curies uCi/mL Curies uCi/mL Curies Liters Liters Table 1-IB Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Liquid Effluents - Summation of All Releases Unit:
2 Starting: 1-Jan-2018 Ending: 31-Dec-2018 1ST Quarter l.77E-02 7.97E-09 l.85E+02 8.30E-05 8.54E-03 3.84E-09 O.OOE+OO 2.38E+06 2.22E+09 2ND Quarter l.98E-02 l.57E-08 7.99E+Ol 6.35E-05 4.15E-03 3.30E-09 O.OOE+OO l.33E+06 l.26E+09 3RD Quarter 3.25E-02 3.52E-08 8.12E+Ol 8.79E-05 l.99E-05 2.ISE-11 O.OOE+OO 8.91E+05 9.23E+08
- Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.
5 -
L --
4TH Quarter 4.86E-02 3.71E-08 3.94E+02 3.0lE-04 8.80E-05 6.72E-ll O.OOE+OO l.04E+06 l.31E+09
Type of Effluent A. Fission And Activation Products I. Total Release (not including tritium, gases, alpha)
- 2. Average diluted concentration during period
- 3. Percent of Applicable Limit B. Tritium
- 1. Total Release
- 2. Average diluted Concentration during period
- 3. Percent of Applicable Limit C. Dissolved and Entrained Gases
- 1. Total Release
- 2. Average diluted Concentration during period
- 3. Percent of Applicable Limit D: Gross Alpha Radioactivity
- 1. Total Release E: Waste Vol Release (Pre-Dilution)
F. Volume of Dilution Water Used Units Curies uCi/mL Curies uCi/mL Curies uCi/mL Curies Liters Liters Table I-IC Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -
2018 Liquid Effluents - Summation of All Releases Unit:
Site Starting: I -Jan-2018 Ending: 31-Dec-2018 1ST Quarter 2ND Quarter 3RD Quarter 3.7IE-02 4.49E-02 8.9IE-02 8.9IE-09 l.8IE-08 3.15E-08 6.40E+02 1.15E+02 1.57E+02 l.54E-04 4.63E-05 5.55E-05 l.80E-02 6.63E-03 1.18E-04 4.32E-09 2.67E-09 4.19E-11 O.OOE+OO O.OOE+OO O.OOE+OO 4.65E+06 2.58E+06 3.84E+06 4.16E+09 2.48E+09 2.82E+09
- Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-38 of this report.
6 -
4TH Quarter 9.47E-02 l.87E-08 6.70E+02 1.32E-04 1.8 IE-04 3.57E-11 O.OOE+OO 2.25E+06 5.07E+09
Nuclides Released Fission & Activation Products No Nuclides Found Tritium No Nuclides Found Dissolved And Entrained Gases No Nuclides Found Gross Alpha Radioactivity No Nuclides Found Units Curies Curies Curies Curies Table l-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Liquid Effluents Unit:
Starting: 1-Jan-2018 Ending: 31-Dec-2018 Continuous Mode 1ST Quarter 2ND Quarter 3RD Quarter O.OOE+OO 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO 0.00E+OO O.OOE+OO Zeroes in this table indicate that no radioactivity was present at detectable levels.
See Table 1-4 for typical minimum detectable concentrations.
7 -
4TH Quarter O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
Table l-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Liquid Effluents Unit:
1 Starting: 1-Jan-2018 Ending: 31-Dec-2018 Batch Mode Nuclides Released Units 1ST Quarter
. 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Nb-97 Curies l.51E-06 3.90E-05 2.57E-05 4.91E-06 Y-88 Curies 9.53E-07 0.00E+OO O.OOE+OO 5.71E-07 Co-57 Curies 3.04E-06 3.32E-06 6.37E-07 O.OOE+OO Y-93 Curies O.OOE+OO 0.00E+OO 4.80E-05 O.OOE+OO Nb-95 Curies l.64E-04 l.65E-03 2.24E-04 8.80E-05 Te-132 Curies 0.00E+OO 4.56E-07 4.84E-05 2.43E-05 Ru-103 Curies 0.00E+OO 4.39E-06 0.00E+OO 0.00E+OO Mn-54 Curies l.77E-05 l.02E-04 2.40E-05 2.76E-05 Te-129M Curies 0.00E+OO 2.54E-05 0.00E+OO 0.00E+OO Fe-55 Curies 9.92E-04 l.02E-03' l.47E-03 7.64E-04 Ba-139 Curies l.23E-06 0.00E+OO 0.00E+OO 0.00E+OO I-131 Curies O.OOE+OO 0.00E+OO 2.05E-06 3.73E-06 I-133 Curies 1.49E-06 0.00E+OO O.OOE+OO 2.26E-06 Rh-105 Curies 5.63E-06 6.27E-04 5.77E-06 0.00E+OO Ni-56 Curies 2.49E-05 9.46E-06 l.12E-05 O.OOE+OO Co-60 Curies 3.89E-03 4.50E-03 1.54E-03 2.09E-03 Sr-92 Curies O.OOE+OO 3.5IE-06 O.OOE+OO 0.00E+OO Sr-89 Curies O.OOE+OO 0.00E+OO l.29E-05 3.61E-05 Fe-59 Curies 7.87E-06 5.79E-05 0.00E+OO 7.04E-07 Te-131 Curies O.OOE+OO 2.39E-06 0.00E+OO O.OOE+OO Cr-51 Curies l.03E-03 7.18E-03 1.68E-03 l.27E-03 Co-58 Curies 4.97E-03 5.99E-03 l.30E-03 8.46E-04 In-115M Curies 0.00E+OO 0.00E+OO O.OOE+OO l.13E-06 Ce-141 Curies 2.82E-06 l.05E-05 O.OOE+OO 0.00E+OO Sb-124 Curies O.OOE+OO 2.29E-05 4.13E-04 3.02E-04 Br-84 Curies 0.00E+OO 0.00E+OO l.20E-04 0.00E+OO As-76 Curies l.73E-04 6.21E-06 O.OOE+OO 0.00E+OO Te-127 Curies 2.60E-05 O.OOE+OO 0.00E+OO O.OOE+OO Hg-203 Curies 0.00E+OO 0.00E+OO 0.00E+OO 4.40E-07 Sn-113 Curies 6.74E-07 2.32E-05 O.OOE+OO O.OOE+OO 8 -
Ag-108M Curies 5.06E-06 l.93E-05 8.06E-06 3.24E-07 Zr-95 Curies 5.16E-05 9.20E-04 9.52E-05 4.57E-05 Zn-65 Curies 8.82E-06 4.08E-05 4.41E-06 6.62E-06 Te-125M Curies 7.60E-03 1.85E-03 l.95E-03 8.22E-04 Te-127M Curies 2.38E-04 1.75E-04 O.OOE+OO 6.32E-05 Pr-144 Curies O.OOE+OO 1.21E-04 O.OOE+OO O.OOE+OO Te-129 Curies 8.0lE-06 l.17E-05 O.OOE+OO 3.l lE-06 Zr-97 Curies O.OOE+OO 1.62E-06 O.OOE+OO O.OOE+OO Cd-115 Curies O.OOE+OO O.OOE+OO O.OOE+OO l.09E-06 Eu-154 Curies O.OOE+OO 1.97E-06 O.OOE+OO O.OOE+OO Sb-125 Curies 1.06E-04 5.44E-04 4.34E-02 3.95E-02 Be-7 Curies O.OOE+OO 2.98E-05 3.50E-05 O.OOE+OO La-140 Curies O.OOE+OO 8.31E-06 3.18E-06 O.OOE+OO Ce-139 Curies 3.14E-07 O.OOE+OO 0.00E+OO O.OOE+OO Cs-137 Curies 3.50E-05 1.37E-06 3.75E-05 2.23E-04 Sn-117M Curies 8.84E-07 2.15E-06 2.98E-06 O.OOE+OO Ag-1 lOM Curies O.OOE+OO 1.63E-04 6.19E-05 3.37E-06 Tc-99M Curies O.OOE+OO O.OOE+OO O.OOE+OO 3.53E-06 Cs-138 Curies O.OOE+OO O.OOE+OO 2.26E-06 O.OOE+OO Na-24 Curies O.OOE+OO O.OOE+OO 2.88E-06 O.OOE+OO Total For Period Curies l.94E-02 2.52E-02 5.25E-02 4.61E-02 Tritium H-3 Curies 4.56E+02 3.51E+Ol 7.54E+Ol 2.76E+02 Dissolved And Entrained Gases Xe-133 Curies 9.30E-03 2.46E-03 9.69E-05 7.75E-05 Xe-133M Curies 2.72E-05 5.28E-06 O.OOE+OO l.33E-05 Ar-41 Curies 3.94E-05 l.19E-05 O.OOE+OO O.OOE+OO Xe-135M Curies O.OOE+OO 0.00E+OO O.OOE+OO 2.lOE-06 Xe-127 Curies O.OOE+OO 2.27E-07 O.OOE+OO O.OOE+OO Xe-135 Curies 4.58E-05 1.90E-06 1.67E-06 O.OOE+OO Kr-87 Curies 8.07E-07 O.OOE+OO O.OOE+OO O.OOE+OO Total For Period Curies 9.42E-03 2.48E-03 9.86E-05 9.29E-05 Gross Alpha Radioactivity No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zeroes in this table indicate that no radioactivity was present at detectable levels.
See Table 1-4 for typical minimum detectable concentrations.
9 -
Nuclides Released Fission & Activation Products No Nuclides Found Tritium No Nuclides Found Dissolved And Entrained Gases No Nuclides Found Gross Alpha Radioactivity No Nuclides Found Units Curies Curies Curies Curies Table l-2B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Liquid Effluents Unit:
2 Starting: 1-Jan-2018 Ending: 31-Dec-2018 Continuous Mode 1ST Quarter 2ND Quarter 3RD Quarter O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO 0.00E+OO 0.00E+OO 0.00E+OO Zeroes in this table indicate that no radioactivity was present at detectable levels.
See Table 1-4 for typical minimum detectable concentrations.
10 -
4TH Quarter O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
Table l-2B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -
2018 Liquid Effluents Unit:
2 Starting: 1-Jan-2018 Ending: 31-Dec-2018 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Te-133 Curies O.OOE+OO O.OOE+OO 5.69E-06 O.OOE+OO Cr-51 Curies l.31E-03 5.23E-03 3.59E-04 l.IOE-03 Te-125M Curies 3.27E-03 2.36E-03 2.42E-03 2.21E-03 Mn-56 Curies 2.00E-06 O.OOE+OO O.OOE+OO O.OOE+OO Te-129 Curies O.OOE+OO 4.12E-05 O.OOE+OO O.OOE+OO Na-22 Curies O.OOE+OO 8.04E-07 O.OOE+OO 7.71E-07 Ag-1 IOM Curies O.bOE+OO l.33E-04 2.31E-05 2.85E-05 I-131 Curies O.OOE+OO O.OOE+OO O.OOE+OO 5.27E-06 In-I ISM Curies O.OOE+OO 7.77E-07 O.OOE+OO O.OOE+OO Br-84 Curies 5.30E-06 O.OOE+OO O.OOE+OO O.OOE+OO Sr-93 Curies O.OOE+OO 9.92E-06 O.OOE+OO O.OOE+OO Cd-109 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.67E-05 I-133 Curies O.OOE+OO O.OOE+OO O.OOE+OO 1.81E-05 Hg-203 Curies 2.37E-07 6.90E-07 O.OOE+OO O.OOE+OO Zr-95 Curies l.36E-04 5.81E-04 2.92E-05 1.35E-04 Mn-54 Curies 6.23E-05 7.47E-05 2.49E-05 l.76E-04 Ru-103 Curies
- l. l 7E-06 8.91E-06 O.OOE+OO O.OOE+OO Ce-141 Curies O.OOE+OO 2.35E-06 O.OOE+OO O.OOE+OO Te-134 Curies O.OOE+OO l.41E-07 O.OOE+OO O.OOE+OO Sn-l 17M Curies O.OOE+OO 3.24E-06 O.OOE+OO O.OOE+OO r
La-140 Curies O.OOE+OO l.80E-06 O.OOE+OO O.OOE+OO Cl-38 Curies O.OOE+OO O.OOE+OO O.OOE+OO 2.18E-06 Rh-105 Curies 4.71E-05 7.08E-04 3.06E-06 O.OOE+OO Ag-I08M Curies l.80E-06 6.71E-06 4.21E-06 7.SOE-06 Co-60 Curies 4.85E-03 3.58E-03 l.44E-03 8.IOE-03 Ni-56 Curies 7.35E-06 l.OlE-05 l.29E-05 O.OOE+OO Te-132 Curies
- O.OOE+OO O.OOE+OO l.21E-05 2.19E-05 11 -
L__
Eu-152 As-76 Tc-99M Sr-89 Nb-95 Y-93 Sb-125 Cs-136 Mo-99 Y-92 Y-94 Fe-55 Te-131 Cs-137 Na-24 Sr-92 Te-129M Fe-59 Zn-69M Co-58 Sb-124 Sb-122 Pr-144 Zr-97 Zn-65 Pm-149 Ru-105 Nb-97 Y-91M Co-57 Sr-90 Eu-154 Sn-113 Cd-115 Total For Period Tritium H-3 Curies O.OOE+OO l.38E-06 Curies 3.48E-04 l.69E-05 Curies O.OOE+OO 2.82E-07 Curies O.OOE+OO O.OOE+OO Curies 3.35E-04 l.05E-03 Curies O.OOE+OO l.82E-05 Curies 7.55E-05 2.85E-04 Curies O.OOE+OO 6.56E-07 Curies O.OOE+OO O.OOE+OO Curies O.OOE+OO l.49E-05 Curies O.OOE+OO O.OOE+OO Curies l.35E-03 l.42E-03 Curies 1.35E-06 O.OOE+OO Curies 3.17E-07 O.OOE+OO Curies O.OOE+OO O.OOE+OO Curies O.OOE+OO O.OOE+OO Curies O.OOE+OO 6.66E-05 Curies 9.98E-06 5.31E-05 Curies 2.37E-06 1.39E-06 Curies 5.86E-03 3.67E-03 Curies 2.51E-07 l.20E-05 Curies 5.94E-07 l.31E-06 Curies O.OOE+OO 3.33E-04 Curies O.OOE+OO 6.74E-07 Curies 6.27E-05 2.08E-05 Curies O.OOE+OO 5.62E-06 Curies O.OOE+OO 5.52E-07 Curies 5.09E-06 2.55E-05 Curies O.OOE+OO 6.51E-07 Curies 6.19E-06 1.49E-06 Curies O.OOE+OO O.OOE+OO Curies O.OOE+OO 9.70E-07 Curies O.OOE+OO 1.77E-05 Curies O.OOE+OO l.83E-06 Curies l.77E-02 l.98E-02 Curies l.85E+02 7.99E+Ol Zeroes in this table indicate that no radioactivity was present at detectable levels.
See Table 1-4 for typical minimum detectable concentrations.
12 -
0.00E+OO O.OOE+OO 0.00E+OO O.OOE+OO 0.00E+OO 3.26E-05 2.18E-04 4.29E-05 7.72E-05 3.0lE-04 O.OOE+OO O.OOE+OO 1.49E-02 3.21E-02 0.00E+OO O.OOE+OO 0.00E+OO l.58E-05 0.00E+OO O.OOE+OO l.02E-06 O.OOE+OO l.22E-02 1.47E-03 0.00E+OO O.OOE+OO l.15E-05 4.65E-04 0.00E+OO 2.75E-05 2.91E-06 5.89E-07 O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO 0.00E+OO l.85E-06 5.93E-04 l.87E-03 1.24E-04 l.72E-04 0.00E+OO O.OOE+OO 0.00E+OO 0.00E+OO 3.02E-07 O.OOE+OO l.20E-05 l.41E-04 0.00E+OO O.OOE+OO 0.00E+OO O.OOE+OO 5.12E-05
- 6.39E-05 0.00E+OO O.OOE+OO 2.70E-06 7.59E-06 6.23E-06 O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO 3.25E-02 4.86E-02 8.12E+Ol 3.94E+02
Dissolved And Entrained Gases Ar-41 Curies l.85E-05 8.04E-07 Xe-133M Curies 1.35E-05 5.23E-06 Xe-135 Curies 4.90E-05 2.0lE-06 Xe-135M Curies O.OOE+OO 7.79E-07 Kr-85M Curies 6.54E-07 O.OOE+OO Xe-133 Curies 8.46E-03 4.14E-03 Total For Period Curies 8.54E-03 4.15E-03 Gross Alpha Radioactivity No Nuclides Found Curies O.OOE+OO O.OOE+OO Zeroes in this table indicate that no radioactivity was present at detectable levels.
See Table 1-4 for typical minimum detectable concentrations.
13 -
8.54E-06 2.35E-06 0.00E+OO O.OOE+OO 7.42E-07 O.OOE+OO 0.00E+OO O.OOE+OO 0.00E+OO O.OOE+OO 1.06E-05 8.56E-05 l.99E-05 8.80E-05 0.00E+OO O.OOE+OO
Nuclides Released Fission & Activation Products No Nuclides Found Tritium No Nuclides Found Dissolved And Entrained Gases No Nuclides Found Gross Alpha Radioactivity No Nuclides Found Units Curies Curies Curies Curies Table l-2C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Liquid Effluents Unit:
Site Starting: 1-Jan-2018 Ending: 31-Dec-2018 Continuous Mode 1ST Quarter 2ND Quarter 3RD Quarter O.OOE+OO 0.00E+OO 0.00E+OO 0.00E+OO 0.00E+OO 0.00E+OO 0.00E+OO 0.00E+OO 0.00E+OO 0.00E+OO 0.00E+OO 0.00E+OO Zeroes in this table indicate that no radioactivity was present at detectable levels.
See Table 1-4 for typical minimum detectable concentrations.
14 -
L___..
4TH Quarter O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
Table l-2C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -
2018 Liquid Effluents Unit:
Site Starting: 1-Jan-2018 Ending: 31-Dec-2018 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission & Activation Products Zr-95 Curies l.88E-04 l.SOE-03 l.24E-04 1.80E-04 Zn-65 Curies 7.ISE-05 6.16E-05 l.64E-05 l.47E-04 Te-132 Curies O.OOE+OO 4.56E-07 6.0SE-05 4.62E-05 1-133 Curies l.49E-06 O.OOE+OO 0.00E+OO 2.03E-05 Ba-139 Curies l.23E-06 O.OOE+OO 0.00E+OO O.OOE+OO Te-131 Curies l.35E-06 2.39E-06 0.00E+OO O.OOE+OO Rh-105 Curies 5.27E-05 l.33E-03 8.83E-06 O.OOE+OO Co-58 Curies l.08E-02 9.65E-03 l.89E-03 2.72E-03 As-76 Curies 5.21E-04 2.31E-05 0.00E+OO O.OOE+OO Te-129 Curies 8.0lE-06 5.29E-05 O.OOE+OO 3.1 lE-06 Sn-l 17M Curies 8.84E-07 5.39E-06 2.98E-06 O.OOE+OO Pr-144 Curies O.OOE+OO 4.54E-04 0.00E+OO O.OOE+OO Ce-139 Curies 3.14E-07 O.OOE+OO 0.00E+OO O.OOE+OO Y-92 Curies O.OOE+OO 1.49E-05 O.OOE+OO O.OOE+OO Te-134 Curies O.OOE+OO l.41E-07 O.OOE+OO O.OOE+OO Y-94 Curies O.OOE+OO O.OOE+OO l.02E-06 O.OOE+OO Co-57 Curies 9.24E-06 4.81E-06 3.33E-06 7.59E-06 1-131 Curies O.OOE+OO O.OOE+OO 2.0SE-06 9.00E-06 Sn-113 Curies 6.74E-07 4.09E-05 O.OOE+OO O.OOE+OO Tc-99M Curies O.OOE+OO 2.82E-07 O.OOE+OO 3.61E-05 Mo-99 Curies O.OOE+OO O.OOE+OO O.OOE+OO l.58E-05 Fe-59 Curies l.79E-05 l.1 lE-04 0.00E+OO 7.04E-07 Sb-125 Curies l.81E-04 8.28E-04 5.82E-02 7.16E-02 Be-7 Curies O.OOE+OO 2.98E-05 3.SOE-05 O.OOE+OO Ce-141 Curies 2.82E-06 l.29E-05 0.00E+OO O.OOE+OO Ni-56 Curies 3.22E-05 1.95E-05 2.41E-05 O.OOE+OO Nb-97 Curies 6.60E-06 6.45E-05 7.69E-05 6.88E-05 Fe-55 Curies 2.34E-03 2.44E-03 1.37E-02 2.23E-03 Cr-51 Curies 2.33E-03 l.24E-02 2.04E-03 2.37E-03 15 -
Sb-124 Sb-122 Cl-38 Cd-109 Zr-97 Nb-95 Cd-115 Zn-69M Te-127 Sr-90 Eu-152 Cs-136 Mn-56 Na-24 Cs-137 Sr-93 Sr-92 Ru-103 Hg-203 Pm-149 Sr-89 Te-I29M Te-I27M Br-84 Eu-154 In-I ISM Ru-105 La-140 Mn-54 Ag-1 IOM Y-93 Na-22 Te-133 Y-9IM Ag-I08M Co-60 Te-125M Y-88 Cs-138 Total For Period Tritium H-3 Curies 2.SIE-07 Curies 5.94E-07 Curies O.OOE+OO Curies O.OOE+OO Curies O.OOE+OO Curies 4.99E-04 Curies O.OOE+OO Curies 2.37E-06 Curies 2.60E-05 Curies O.OOE+OO Curies O.OOE+OO Curies O.OOE+OO Curies 2.00E-06 Curies O.OOE+OO Curies 3.53E-05 Curies O.OOE+OO Curies O.OOE+OO Curies l.17E-06 Curies 2.37E-07 Curies O.OOE+OO Curies O.OOE+OO Curies O.OOE+OO Curies 2.38E-04 Curies 5.30E-06 Curies O.OOE+OO Curies O.OOE+OO Curies O.OOE+OO Curies O.OOE+OO Curies 8.00E-05 Curies O.OOE+OO Curies O.OOE+OO Curies O.OOE+OO Curies O.OOE+OO Curies O.OOE+OO Curies 6.86E-06 Curies 8.74E-03 Curies l.09E-02 Curies 9.53E-07 Curies O.OOE+OO Curies 3.7IE-02 Curies 6.40E+02 16 -
3.49E-05 5.37E-04 4.74E-04 l.3 lE-06 0.00E+OO O.OOE+OO 0.00E+OO 0.00E+OO 2.I8E-06 0.00E+OO 0.00E+OO 2.67E-05 2.29E-06 3.02E-07 O.OOE+OO 2.70E-03 3.0IE-04 3.89E-04 l.83E-06 0.00E+OO l.09E-06 l.39E-06 0.00E+OO l.85E-06 0.00E+OO 0.00E+OO O.OOE+OO 0.00E+OO 6.23E-06 0.00E+OO l.38E-06 0.00E+OO O.OOE+OO 6.56E-07 O.OOE+OO 0.00E+OO O.OOE+OO 0.00E+OO 0.00E+OO O.OOE+OO 2.88E-06 2.75E-05 l.37E-06 4.90E-05 6.88E-04 9.92E-06 0.00E+OO 0.00E+OO 3.SIE-06 2.9IE-06 5.89E-07 1.33E-05 0.00E+OO 0.00E+OO 6.90E-07 0.00E+OO 4.40E-07 5.62E-06 0.00E+OO O.OOE+OO O.OOE+OO 2.3IE-04 7.90E-05 9.19E-05 O.OOE+OO 0.00E+OO l.75E-04 O.OOE+OO 6.32E-05 O.OOE+OO L20E-04 0.00E+OO 2.94E-06 0.00E+OO O.OOE+OO 7.77E-07 0.00E+OO l.I3E-06 5.52E-07 o.ooE+oo*
0.00E+OO l.OIE-05 3.1 SE-06 0.00E+OO l.77E-04 4.89E-05 2.03E-04 2.96E-04 8.SOE-05 3.19E-05 l.82E-05 4.SOE-05 O.OOE+OO 8.04E-07 0.00E+OO 7.7IE-07 O.OOE+OO 5.69E-06 O.OOE+OO 6.SIE-07 0.00E+OO 0.00E+OO 2.60E-05 l.23E-05 7.82E-06 8.0SE-03 2.98E-03 1.02E-02 4.2IE-03 4.37E-03 3.03E-03 O.OOE+OO O.OOE+OO 5.7IE-07 O.OOE+OO 2.26E-06 O.OOE+OO 4.49E-02 8.SIE-02 9.47E-02 l.15E+02 l.57E+02 6.70E+02
Dissolved And Entrained Gases Kr-85M Xe-135 Kr-87 Ar-41 Xe-133M Xe-127 Xe-133 Xe-135M Total For Period Gross Alpha Radioactivity No Nuclides Found Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies 6.54E-07 O.OOE+OO 9.48E-05 3.92E-06 8.07E-07 O.OOE+OO 5.78E-05 l.27E-05 4.07E-05 1.05E-05 O.OOE+OO 2.27E-07 l.78E-02 6.60E-03 O.OOE+OO 7.79E-07 l.80E-02 6.63E-03 O.OOE+OO O.OOE+OO Zeroes in this table indicate that no radioactivity was present at detectable levels.
See Table 1-4 for typical minimum detectable concentrations.
17 -
O.OOE+OO O.OOE+OO 2.41E-06 O.OOE+OO O.OOE+OO O.OOE+OO 8.54E-06 2.35E-06 O.OOE+OO l.33E-05 O.OOE+OO O.OOE+OO l.07E-04 l.63E-04 O.OOE+OO 2.lOE-06 l.18E-04 l.81E-04 O.OOE+OO O.OOE+OO
Table l-3A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -
2018 Doses to a member of the public due to Liquid Releases Unit:
1 Starting: 1-Jan-2018 Ending: 31-Dec-2018 Cumulative Doses Per Quarter Organ ODCM Units 1ST Qtr
%0DCM 2ND Qtr
%0DCM 3RD Qtr
%0DCM 4TH Qtr
%0DCM Lmt Liver 5.00E+OO mRem 8.33E-03 l.67E-Ol 1.16E-03 2.31E-02 2.02E-03 4.03E-02 3.05E-03 6.1 IE-02 Thyroid 5.00E+OO mRem 7.67E-03 l.53E-OI 7.00E-04 I.40E-02 I.OlE-03 2.03E-02 2.62E-03 5.23E-02 Lung 5.00E+OO mRem 7.15E-03 l.43E-Ol 3.59E-03 7.17E-02 2.24E-Ol 4.49E+OO l.46E-OI 2.92E+OO Kidney 5.00E+OO mRem 2.26E-02 4.51E-Ol 4.50E-03 9.00E-02 3.70E-03 7.40E-02 3.96E-03 7.92E-02 Total Body 5.00E+OO mRem 7.33E-03 l.47E-OI 8.69E-04 l.74E-02 1.73E-03 3.46E-02 3.09E-03 6.19E-02 Total Body l.50E+OO mRem 7.33E-03 4.89E-OI 8.69E-04 5.79E-02 l.73E-03 1.15E-Ol 3.09E-03 2.06E-Ol Total Body 5.00E+OO mRem 7.33E-03 l.47E-Ol 8.69E-04 l.74E-02 1.73E-03 3.46E-02 3.09E-03 6.19E-02 Total Body l.50E+OO mRem 7.33E-03 4.89E-Ol 8.69E-04 5.79E-02 1.73E-03 l.15E-Ol 3.09E-03 2.06E-Ol GI-Lli 5.00E+OO mRem 2.41E-02 4.81E-OI 7.96E-03 l.59E-Ol 2.47E-02 4.94E-Ol l.71E-02 3.41E-Ol Bone 5.00E+OO mRem 4.33E-03 8.66E-02 l.38E-03 2.76E-02 4.65E-03 9.29E-02 2.I IE-03 4.22E-02 Cumulative Doses per Year Organ ODCMLmt Units Year to Ending Date
%0DCM Rece12tor Limit Total Body 3.00E+OO mRem l.30E-02 4.34E-Ol Maximum Individual Liquid Liquid Effluent TB Annual Bone 1.00E+Ol mRem 1.25E-02 l.25E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+Ol mRem 1.46E-02 l.46E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Total Body 1.00E+Ol mRem l.30E-02 l.30E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid l.OOE+Ol mRem l.20E-02 1.20E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual Kidney l.OOE+OI mRem 3.47E-02 3.47E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Lung l.OOE+Ol mRem 3.81E-Ol 3.81E+OO Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli l.OOE+Ol mRem 7.38E-02 7.38E-Ol Maximum Individual Liquid Liquid Effluent Organ Annual 18 -
L
Table 1-3B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -
2018 Doses to a member of the public due to Liquid Releases Unit:
2 Starting: 1-Jan-2018 Ending: 31-Dec-2018 Cumulative Doses Per Quarter Organ ODCM Units 1ST Qtr
%0DCM 2ND Qtr
%0DCM 3RD Qtr
%0DCM 4TH Qtr
%0DCM Lmt Thyroid 5.00E+OO mRem 2.38E-03 4.76E-02 1.21E-03 2.41E-02 l.lOE-03 2.20E-02 4.09E-03 8.17E-02 Total Body 5.00E+OO mRem 2.46E-03 4.92E-02 l.26E-03 2.53E-02 1.56E-03 3.12E-02 5.0lE-03 1.00E-01 Total Body l.50E+OO mRem 2.46E-03 I.64E-01 I.26E-03 8.43E-02 l.56E-03 1.04E-0I 5.0lE-03 3.34E-Ol Total Body 5.00E+OO mRem 2.46E-03 4.92E-02 l.26E-03 2.53E-02 l.56E-03 3.I2E-02 5.0lE-03 1.00E-01 Total Body 1.50E+OO mRem 2.46E-03 1.64E-01 l.26E-03 8.43E-02 1.56E-03 1.04E-01 5.0lE-03 3.34E-01 Liver 5.00E+OO mRem 2.84E-03 5.68E-02 1.67E-03 3.34E-02 2.81E-03 5.61E-02 5.22E-03 l.04E-01 Bone 5.00E+OO mRem 1.69E-03 3.37E-02 1.60E-03 3.21E-02 4.15E-03 8.31E-02 2.66E-03 5.32E-02 GI-Lli 5.00E+OO mRem 9.44E-03 1.89E-01 8.lOE-03 1.62E-01 1.22E-02 2.43E-01 l.93E-02 3.86E-Ol Lung 5.00E+OO mRem 2.49E-03 4.98E-02 2.54E-03 5.09E-02 7.34E-02 1.47E+OO 1.26E-Ol 2.51E+OO Kidney 5.00E+OO mRem 7.26E-03 1.45E-01 5.62E-03 l.12E-Ol 4.46E-03*
8.92E-02 6.41E-03 l.28E-01 Cumulative Doses per Year Organ ODCMLmt Units Year to Ending Date
%0DCM Rece12tor Limit Total Body 3.00E+OO mRem l.03E-02 3.43E-01 Maximum Individual Liquid Liquid Effluent TB Annual Bone 1.00E+Ol mRem 1.0lE-02 1.0lE-01 Maximum Individual Liquid Liquid Effluent Organ Annual Liver 1.00E+Ol mRem 1.25E-02 1.25E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Total Body l.OOE+Ol mRem l.03E-02 1.03E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Thyroid 1.00E+Ol mRem 8.77E-03 8.77E-02 Maximum Individual Liquid Liquid Effluent Organ Annual Kidrtey 1.00E+Ol mRem 2.38E-02 2.38E-01 Maximum Individual Liquid Liquid Effluent Organ Annual Lung 1.00E+Ol mRem 2.04E-01 2.04E+OO Maximum Individual Liquid Liquid Effluent Organ Annual GI-Lli l.OOE+Ol mRem 4.90E-02 4.90E-01 Maximum Individual Liquid Liquid Effluent Organ Annual 19 -
TABLE 1-4 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-2018 MINIMUM DETECTABLE CONCENTRATION - LIQUID SAMPLE ANALYSES The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of liquid radwaste samples.
Nuclide MDC(pCi/ML)
Mn-54 4.SBE-08 Co-58 4.21E-08 Fe-59 7.88E-08 Co-60 3.78E-08 Zn-65 6.SBE-08 Mo-99 2.56E-07 1-131 2.99E-08 Cs-134 3.12E-08 Cs-137 4.23E-08 Ce-141 3.82E-08 Ce-144 2.69E-07 20 -
Table l-5A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Liquid Releases I. Number of batch releases
- 2. Total time period for Batch releases
- 3. Maximum time period for a batch release
- 4. Average time period for a batch release
- 5. Minimum time period for a batch release
- 6. Average stream flow during periods of release of liquid effluent into Units (Minutes)
(Minutes)
(Minutes)
(Minutes) a flowing stream *
( CFS )
Replace this text in the Station Parameters Liquid Effluents - Batch Release Summary Unit:
1 Starting: 1-Jan-2018 Ending: 31-Dec-2018 1ST Quarter 2ND Quarter 3RD Quarter 171 95
- 57.
l.99E+04 l.17E+04 7.35E+03 2.04E+02 1.55E+02 l.57E+02 l.16E+02 l.23E+02 l.29E+02 8.90E+Ol l.04E+02 I.OOE+02 9.12E+03 l.02E+04 6.02E+03
- Average River Flow Rate, taken at Walter F. George Lock and Dam, located 30.7 miles above Farley Nuclear Plant.
21 -
4TH Quarter Year Totals 92 415 l.23E+04 5.12E+04 2.00E+02 2.04E+02 1.34E+02 l.23E+02 8.60E+Ol 8.60E+Ol 4.40E+03 7.44E+03
Table 1-5B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Liquid Releases
- 1. Number of batch releases
- 2. Total time period for Batch releases
- 3. Maximum time period for a batch release
- 4. Average time period for a batch release
- 5. Minimum time period for a batch release
- 6. Average stream flow during periods of release of liquid effluent into Units (Minutes)
(Minutes)
(Minutes)
(Minutes) a flowing stream *
( CFS )
Replace this text in the Station Parameters Liquid Effluents - Batch Release Summary Unit:
2 Starting: 1-Jan-2018 Ending: 31-Dec-2018 1ST Quarter 2ND Quarter 3RD Quarter 179 100 67 1.96E+04 1.IOE+04 7.78E+03 1.5IE+02 l.50E+02 1.42E+02 1.10E+02 1.IOE+02 1.16E+02 3.00E+OO 8.60E+Ol 9.50E+Ol 9.12E+03 1.02E+04 6.02E+03
- Average River Flow Rate, taken at Walter F. George Lock and Dam, located 30.7 miles above Farley Nuclear Plant.
22 -
L_
4TH Quarter Year Totals 78 424 9.9IE+03 4.83E+04 1.70E+02 1.70E+02 1.27E+02 l.14E+02 l.OOE+02 3.00E+OO 4.40E+03 7.44E+03
Table l-6A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Liquid Effluents - Abnormal Release Summary Unit:
Starting: 1-Jan-2018 Ending: 31-Dec-2018 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals
- 1. Number of Releases 0
0 0
0 0
- 2. Total Time For All Releases (Minutes)
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 3. Maximum Time For A Release (Minutes)
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 4. Average Time For A Release (Minutes)
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 5. Minimum Time For A Release (Minutes)
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 6. Total activity for all releases (Curies)
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 23 -
Table l-6B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Liquid Effluents - Abnormal Release Summary Unit:
2 Starting: 1-Jan-2018 Ending: 31-Dec-2018 Liquid Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals
- 1. Number of Releases 0
0 0
0 0
- 2. Total Time For All Releases (Minutes) 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 3. Maximum Time For A Release (Minutes) 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 4. Average Time For A Release (Minutes) 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 5. Minimum Time For A Release (Minutes)
O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 6. Total activity for all releases (Curies)
O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO 24 -
L
2.0 GASEOUS EFFLUENTS This section contains applicable ODCM limits for gaseous effluents as well as the quantities of radioactive gaseous effluents released during 2018. These quantities are summarized on a quarterly basis and include any unplanned releases. Tabulations are provided of the offsite air doses calculated in accordance with ODCM 3.4.2 to show conformance with the limits of ODCM 3.1.3, and the offsite organ doses to a member of the public calculated in accordance with ODCM 3.4.3 to show conformance with ODCM 3.1.4.
2.1 Regulatory Requirements The requirements presented in this section are for Unit 1 and Unit 2.
2.1.1 Dose Rate Limits The dose rates due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:
- a.
For noble gases: Less than or equal to 500 mrem/yr. to the whole body and less than or equal to 3000 mrem/yr. to the skin, and
- b.
For lodine-131, lodine-133, tritium and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr. to any organ.
2.1.2 Air Doses Due to Noble Gases in Gaseous Releases Technical Specifications 5.5.4.e and 5.5.4.h state that the air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see ODCM Figure 10-1) shall be limited to the following:
- a.
During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and
- b.
During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
2.1.3 Doses to a Member of the Public Technical Specifications 5.5.4.e and 5.5.4.i state that the dose to a MEMBER OF THE PUBLIC from 1-131, 1-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see ODCM Figure 10-1) shall be limited to the following:
- a.
During any calendar quarter: Less than or equal to 7.5 mrem to any organ, and
- b.
During any calendar year: Less than or equal to 15 mrem to any organ.
25 -
2.2 Measurements and Approximation of Total Radioactivity The following noble gases are specifically considered in evaluating gaseous effluents:
KR-87 XE-133 KR-88 XE-135 XE-133M XE-138 The following radioiodines and radioactive materials in particulate form are specifically considered in evaluating gaseous effluents:
MN-54 FE-59 C0-58 C0-60 ZN-65 SR-89 SR-90 M0-99 I-131 CS-134 CS-137 CE-141 CE-144 H-3 2.2.1 Sample collection and Analysis Periodic grab samples from plant effluent streams are analyzed by a computerized pulse height analyzer system utilizing high resolution germanium detectors. Samples are obtained and analyzed in accordance with ODCM Table 3-3. Isotopic values thus obtained are used for release rate calculations as specified in ODCM 3.4.2 and ODCM 3.4.3. Only those nuclides which are detected are used in calculations. For radioiodines and particulates, in addition to the nuclides listed above other nuclides with half-lives greater than 8 days which are identified are also considered.
Continuous Releases: Continuous sampling is performed on the continuous release points (i.e. the Plant Vent Stack, Containment Purge when in continuous mode, and the Turbine Building Vent).
Particulate material is collected by filtration. At least weekly, these filters are removed and analyzed on the pulse height analyzer to identify and quantify radioactive materials collected on the filters.
Particulate filters are then analyzed for gross alpha and strontium as required. All gross alpha, Sr-89 and Sr-90 samples are sent offsite to the Georgia Power Environmental Laboratory for analysis.
Batch Releases: The processing of batch type releases (from Containment when in batch mode, or Waste Gas Decay Tanks) is analogous to continuous releases, except that the release is not commenced until samples have been obtained and analyzed. Containment Purge batch releases were commenced at FNP beginning in 2006 in order to take advantage of additional decay time for short lived radionuclides.
Typically achieved minimum detectable concentrations for gaseous effluent sample analyses are reported in Table 2-6.
2.2.2 Total Quantities of Radioactivity, Dose Rates, and Cumulative Doses 26 -
The methods for determining release quantities of radioactivity, dose rates, and cumulative doses follow:
2.2.2.1 Fission and Activation Gases The released radioactivity is determined using sample analyses results collected as described in section 2.2.1 and the average release flow rates over the period represented by the collected sample.
Dose rates due to noble gases, radioiodines, tritium, and particulates are calculated (with computer assistance). The calculated dose rates are compared to the dose *rate limits specified in ODCM 3.1.2 for noble gases, radioiodine, tritium, and particulates. Dose rate calculation methodology is presented in the ODCM.
Beta and gamma air doses due to noble gases are calculated for the location in the unrestricted area with the potential for the highest exposure due to gaseous releases. Air doses are calculated for each release period and cumulative totals are kept for each unit for the calendar quarter and year.
Cumulative air doses are compared to the dose limits specified in ODCM 3.1.3. The current percent of the ODCM limits are shown on the printout for each release period. Air dose calculation methodology is presented in the ODCM.
2.2.2.2 Radioiodine, Tritium, and Particulate Releases Released quantities of radioiodines are determined using the weekly samples and release flow rates for the applicable release points. Radioiodine concentrations are determined by gamma spectroscopy.
Release quantities of particulates are determined using the weekly (filter) samples and release flow rates for the applicable release points. Gamma spectroscopy is used to quantify the concentrations of principal gamma emitters.
After each quarter, the particulate filters from each applicable vent (plant vent stack and containment purge) are combined, fused, and a strontium separation is performed. Since sample flows and vent flows are almost constant over each quarterly period the filters from each vent can be dissolved together. Decay corrections are performed back to the middle of the quarterly collection period. If Sr-89 or Sr-90 is not detected, MDCs are calculated. Strontium concentrations are input into the composite file of the computer and used for release dose rate and individual dose calculations.
Tritium samples are obtained monthly from the Plant Vent Stack, the Containment Purge when in batch mode, and the Turbine Building Vent (and weekly for Containment Purge when in continuous mode) by passing the sample stream through a cold trap or by using the bubble method. The grams of water vapor/cubic meter are measured upstream of the cold trap in order to alleviate the difficulties in determining water vapor collection efficiencies. The tritium samples are analyzed onsite and the results furnished in µCi/ml of water. The tritium concentration in water is converted to the tritium concentration in air and this value is input into the composite file of the computer and used in release, dose rate, and individual dose calculations.
27 -
Dose rates due to radioiodine, tritium and particulates are calculated for a hypothetical child exposed to the inhalation pathway at the location in the unrestricted area where the potential dose rate is expected to be the highest. Dose rates are calculated, for each release point for each release period, and the dose rates from each release point is compared to the dose rate limits specified in ODCM 3.1.2, allocated for each release point as described in ODCM 3.3.2.
Doses to a Member of the Public (individual doses) due to radioiodine, tritium and particulates are calculated for the controlling receptor, which is described in the ODCM. Individual doses are calculated for each release period, and cumulative totals are kept for each unit, for the current calendar quarter and year. Cumulative individual doses are compared to the dose limits specified in ODCM 3.1.4. The current percent of ODCM limits are shown on the printout for each release period.
2.2.2.3 Gross Alpha Release The gross alpha release is computed each month by counting the particulate filters, for each week for gross* alpha activity in a proportional counter. The highest concentration calculated for any of these weeks is used for the monthly value. This value is input into the composite file of the computer and used for release calculations.
2.2.3 Total Error Estimation The maximum errors associated with monitor readings, sample flow, vent flow, sample collection, monitor calibration and laboratory procedure are collectively estimated to be:
Fission and Activation Gases Iodine Particulates Tritium 75%
60%
50%
45%
The average error associated with counting is estimated to be:
Fission and Activation Gases Iodine* Particulates Tritium 19%
28%
20%
8%
2.3 Gaseous Effluent Release Data Regulatory Guide 1.21 Tables lA, 18 and lC are found in this report as Tables 2-lA, 2-lB, 2-lC, 2-2A, 2-2B, 2-2C, 2-3A, 2-3B, and 2-3C. Data are presented on a quarterly basis as required by Regulatory Guide 1.21.
To complete Tables 2-lA and 2-lB, the total release for each of the four categories (fission and activation gases, radioiodines, particulates and tritium) was divided by the number of seconds in the quarter to obtain a release rate in µCi/second for each category. However, the percent of the ODCM limits are not applicable because FNP has no curie limit for gaseous releases. Applicable limits are expressed in terms of dose. Noble gases are limited as specified in ODCM 3.1.2. The other three categories (tritium, radioiodines, and particulates) are limited as a group as specified in ODCM 3.1.2.
Dose rates due to noble gas releases and due to radioiodines, tritium and particulate releases were calculated as part of the pre-release and post-release permits. No limits were exceeded for this reporting period.
28 -
Gross alpha radioactivity is reported in Tables 2-lA, 2-18 and 2-lC as curies released in each quarter.
Limits for cumulative beta and gamma air doses due to noble gases are presented in Tables 2-4A and 2-48 along with the percent of ODCM limits.
Limits for cumulative doses to an individual due to radioiodines, tritium and particulates are specified in ODCM 3.1.4. Cumulative individual doses are presented in Tables 2-5A and 2-58 along with percent of ODCM limits.
2.4 Radiological Impact Due to Gaseous Releases The air doses due to noble gases and doses to a Member of the Public due to radioiodines, tritium and particulates in gaseous effluents for Units 1 and 2 are provided in the following tables in order to show conformance with the limits of ODCM 3.1.3 and ODCM 3.1.4:
Unit 1 2018 Air Doses Due to Noble Gases in Gaseous Releases: Table 2-4A Unit 2 2018 Air Doses Due to Noble Gases in Gaseous Releases: Table 2-48 Unit 1 2018 Doses to a Member of the Public Due to Radioiodines, Tritium, and Particulates in Gaseous Releases:
Table 2-5A Unit 2 2018 Doses to a Member of the Public Due to Radioiodines, Tritium, and Particulates in Gaseous Releases:
Table 2-58 2.5 Gaseous Effluents - Batch Releases Batch release information for Units 1 and 2 is summarized in the following tables:
Unit 1 2018 Gaseous Effluents - Batch Release Summary: Table 2-7A Unit 2 2018 Gaseous Effluents - Batch Release Summary: Table 2-78 2.6 Gaseous Effluents - Abnormal Releases There were no abnormal releases on Unit 1 or Unit 2 during 2018.
Abnormal release information for Units 1 and 2 is summarized in the following tables:
Unit 1 2018 Gaseous Effluents - Abnormal Release Summary: Table 2-8A Unit 2 2018 Gaseous Effluents - Abnormal Release Summary: Table 2-88 29 -
Type of Effluent A. Fission And Activation Gases
- 1. Total Release
- 2. Average Release rate for period
- 3. Percent of Applicable Limit B. Radioiodines I. Total Iodine-131
- 2. Average Release rate for period
- 3. Percent of Applicable Limit C. Particulates
- 1. Particulates ( Half-Lives > 8 Days )
- 2. Average Release rate for period
- 3. Percent of Applicable Limit D. Tritium
- 1. Total Release
- 2. Average Release rate for period
- 3. Percent of Applicable Limit E. Gross Alpha Units Curies uCi/sec Curies uCi/sec Curies uCi/sec Curies uCi/sec Table 2-lA Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Gaseous Effluents - Summation Of All Releases Unit:
1 Starting: 1-Jan-2018 Ending: 31-Dec-2018 1 ST Quarter 2ND Quarter 3RD Quarter 7.44E+OO 9.43E-01 O.OOE+OO 0.00E+OO 6.16E-08 7.81E-09 2.69E+OO 3.42E-01 l.35E+OO l.72E-01 1.03E-04 l.30E-05 4.91E-07 6.23E-08 5.00E+OO 6.35E-01 8.23E-01 l.04E-01 4.44E-05 5.63E-06 l.31E-07 1.66E-08 4.60E+OO 5.83E-OI
- 1. Total Release Curies 2.0lE-06 7.50E-07 l.57E-06
- 2. Average Release rate for period uCi/sec 2.55E-07 9.52E-08 l.99E-07
- Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-SA, 2-SB of this report.
30 -
4TH Quarter 4.3 lE-01 5.47E-02 4.62E-07 5.86E-08 5.99E-07 7.602E-08 3.69E+OO 4.68E-01 2.20E-06 2.79E-07
Type of Effluent A. Fission And Activation Gases
- 1. Total Release
- 2. Average Release rate for period
- 3. Percent of Applicable Limit B. Radioiodines
- 1. Total Iodine-131
- 2. Average Release rate for period
- 3. Percent of Applicable Limit C. Particulates I. Particulates ( Half-Lives > 8 Days )
- 2. Average Release rate for period
- 3. Percent of Applicable Limit D. Tritium
- 1. Total Release
- 2. Average Release rate for period
- 3. Percent of Applicable Limit E. Gross Alpha
- 1. Total Release
- 2. Average Release rate for period Units Curies uCi/sec Curies uCi/sec Curies uCi/sec Curies uCi/sec Curies uCi/sec Table 2-lB Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Gaseous Effluents - Summation Of All Releases Unit:
2 Starting: 1-Jan-2018 Ending: 31-Dec-2018 I ST Quarter 2ND Quarter 3RD Quarter 5.69E-OI 7.22E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.32E+OI l.67E+OO 2.44E-06 3.09E-07 l.65E-OI 2.09E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.16E+OI l.47E+OO 1.38E-06 l.75E-07 3.61E-OI 4.58E-02 O.OOE+OO 0.00E+OO 0.00E+OO 0.00E+OO 7.17E+OO 9.IOE-01 1.35E-06 l.71E-07
- Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-48, 2-SA, 2-58 of this report.
31 -
4TH Quarter 2.18E-OI 2.76E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOOE+OO l.27E+OI 1.62E+OO l.67E-06 2.12E-07
Table 2-IC Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -
2018 Gaseous Effluents - Summation Of All Releases Unit:
Site Starting: 1-Jan-2018 Ending: 31-Dec-2018 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission And Activation Gases I. Total Release Curies 8.0lE+OO l.52E+OO l.18E+OO 6.49E-Ol
- 2. Average Release rate for period uCi/sec l.02E+OO l.93E-01 l.SOE-01 8.23E-02
- 3. Percent of Applicable Limit B. Radioiodines I. Total Iodine-131 Curies O.OOE+OO l.03E-04 4.44E-05 4.62E-07
- 2. Average Release rate for period uCi/sec O.OOE+OO l.30E-05 5.63E-06 5.86E-08
- 3. Percent of Applicable Limit C. Particulates I. Particulates ( Half-Lives > 8 Days )
Curies 6.16E-08 4.91E-07 1.31E-07 5.99E-07
- 2. Average Release rate for period uCi/sec 7.81E-09 6.23E-08 l.66E-08 7.602E-08
- 3. Percent of Applicable Limit D. Tritium I. Total Release Curies l.59E+Ol l.66E+Ol l.18E+Ol l.64E+Ol
- 2. Average Release rate for period uCi/sec 2.0IE+OO 2.llE+OO 1.49E+OO 2.08E+OO
- 3. Percent of Applicable Limit E. Gross Alpha
- 1. Total Release Curies 4.45E-06 2.13E-06 2.92E-06 3.87E-06
- 2. Average Release rate for period uCi/sec 5.64E-07 2.70E-07 3.70E-07 4.91E-07
- Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-SA, 2-SB of this report.
32 -
Nuclides Released Fission Gases Ar-41 Total For Period iodines I-131 I-133 I-135 Total For Period Particulates Co-58 Co-60 Sr-89 Sr-90 Total For Period Tritium H-3 Gross Alpha G-Alpha Total For Period Units Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Table 2-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Gaseous Effluents - Mixed Mode Level Releases Unit:
I Starting: 1-Jan-2018 Ending: 31-Dec-2018 Continuous Mode 1ST Quarter O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.16E-08 6.16E-08 2.55E+OO 2.0IE-06 2.0IE-06 2ND Quarter l.07E+OO l.07E+OO l.18E-05 9.08E-05 7.44E-05 l.77E-04 l.36E-07 l.48E-07 2.06E-07 O.OOE+OO 4.90E-07 5.00E+OO 7.SOE-07 7.SOE-07 3RD Quarter O.OOE+OO 0.00E+OO 3.48E-06 4.09E-05 O.OOE+OO 4.44E-05 O.OOE+OO 0.00E+OO l.31E-07 0.00E+OO l.31E-07 4.44E+OO l.57E-06 l.57E-06 4TH Quarter O.OOE+OO O.OOE+OO 4.62E-07 O.OOE+OO O.OOE+OO 4.62E-07 O.OOE+OO O.OOE+OO 5.99E-07 O.OOE+OO 5.99E-07 3.63E+OO 2.20E-06 2.20E-06
- If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
33 -
Table 2-2A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Gaseous Effluents - Mixed Mode Level Releases Unit:
1 Starting: 1-Jan-2018 Ending: 31-Dec-2018 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 6.90E+OO 7.95E-02 8.18E-Ol 4.30E-Ol Kr-85M Curies O.OOE+OO 3.52E-04 O.OOE+OO O.OOE+OO Kr-88 Curies O.OOE+OO l.67E-04 O.OOE+OO O.OOE+OO Xe-131M Curies O.OOE+OO l.19E-03 O.OOE+OO O.OOE+OO Xe-133M Curies O.OOE+OO 3.60E-03 0.00E+OO O.OOE+OO Xe-133 Curies 3.56E-Ol l.90E-01 4.98E-03 3.07E-04 Xe-135 Curies l.80E-Ol 1.31E-02 0.00E+OO 8.38E-04 Total For Period Curies 7.44E+OO 2.88E-01 8.23E-Ol 4.31E-Ol Iodines I-131 Curies O.OOE+OO 6.14E-08 0.00E+OO O.OOE+OO I-133 Curies O.OOE+OO 3.1 lE-08 O.OOE+OO O.OOE+OO Total For Period Curies O.OOE+OO 9.25E-08 O.OOE+OO O.OOE+OO Particulates Y-88 Curies O.OOE+OO l.07E-09 0.00E+OO O.OOE+OO Total For Period Curies O.OOE+OO l.07E-09 0.00E+OO O.OOE+OO Tritium H-3 Curies l.44E-01 4.37E-03 l.57E-Ol 6.31E-02 Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO
- If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
34 -
Nuc!ides Released Fission Gases No Nuclides Found Iodines No Nuclides Found Particulates No Nuclides Found Tritium H-3 Gross Alpha G-Alpha Total For Period Units Curies Curies Curies Curies Curies Curies Table 2-2B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -
2018 Gaseous Effluents - Mixed Mode Level Releases Unit:
2 Starting: 1-Jan-2018 Ending: 31-Dec-2018 1ST Quarter O.OOE+OO O.OOE+OO O.OOE+OO l.32E+Ol 2.44E-06 2.44E-06 Continuous Mode 2ND Quarter O.OOE+OO O.OOE+OO O.OOE+OO l.16E+Ol l.38E-06 l.38E-06 3RD Quarter 0.00E+OO O.OOE+OO 0.00E+OO 7.12E+OO l.35E-06 l.35E-06 4TH Quarter O.OOE+OO O.OOE+OO O.OOE+OO l.27E+Ol 1.67E-06 l.67E-06
- If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
35 -
Table 2-2B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Gaseous Effluents - Mixed Mode Level Releases Unit:
2 Starting: 1-Jan-2018 Ending: 31-Dec-2018 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 5.69E-01 l.65E-01 3.61E-Ol 2.18E-01 Kr-88 Curies O.OOE+OO O.OOE+OO 0.00E+OO l.91E-04 Xe-133 Curies 3.44E-04 O.OOE+OO O.OOE+OO O.OOE+OO Xe-135 Curies 4.53E-04 O.OOE+OO O.OOE+OO O.OOE+OO Total For Period Curies 5.69E-Ol l.65E-01 3.61E-01 2.18E-01 Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium H-3 Curies 4.95E-03 l.04E-02 5.55E-02 l.37E-02 Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
36 -
Nuclides Released Fission Gases Ar-41 Total For Period Iodines I-131 I-133 I-135 Total For Period Particulates Co-58 Co-60 Sr-89 Sr-90 Total For Period Tritium H-3 Gross Alpha G-Alpha Total For Period Units Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Table 2-2C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -
2018 Gaseous Effluents - Mixed Mode Level Releases Unit:
Site Starting: 1-Jan-2018 Ending: 31-Dec-2018 Continuous Mode 1ST Quarter O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.16E-08 6.16E-08 1.57E+Ol 4.45E-06 4.45E-06 2ND Quarter l.07E+OO 1.07E+OO l.18E-05 9.08E-05 7.44E-05 l.77E-04 l.36E-07 l.48E-07 2.06E-07 O.OOE+OO 4.90E-07 l.66E+Ol 2.13E-06 2.13E-06 3RD Quarter O.OOE+OO O.OOE+OO 3.48E-06 4.09E-05 O.OOE+OO 4.44E-05 O.OOE+OO O.OOE+OO l.31E-07 O.OOE+OO l.31E-07 1.16E+Ol 2.92E-06 2.92E-06 4TH Quarter O.OOE+OO O.OOE+OO 4.62E-07 O.OOE+OO O.OOE+OO 4.62E-07 O.OOE+OO O.OOE+OO 5.99E-07 O.OOE+OO 5.99E-07 1.64E+Ol 3.87E-06 3.87E-06
- If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
37 -
Table 2-2C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -
2018 Gaseous Effluents - Mixed Mode Level Releases Unit:
Site Starting: 1-Jan-2018 Ending: 31-Dec-2018 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases Ar-41 Curies 7.47E+OO 2.44E-01 1.18E+OO 6.48E-01 Kr-85M Curies O.OOE+OO 3.52E-04 O.OOE+OO O.OOE+OO Kr-88 Curies O.OOE+OO l.67E-04 O.OOE+OO l.9IE-04 Xe-131M Curies O.OOE+OO 1.19E-03 O.OOE+OO O.OOE+OO Xe-133M Curies O.OOE+OO 3.60E-03 O.OOE+OO O.OOE+OO Xe-133 Curies 3.56E-01 l.90E-01 4.98E-03 3.07E-04 Xe-135 Curies 1.81E-01 1.3IE-02 O.OOE+OO 8.38E-04 Total For Period Curies 8.0IE+OO 4.52E-01 l.18E+OO 6.49E-Ol Iodines I-131 Curies O.OOE+OO 6.14E-08 0.00E+OO O.OOE+OO I-133 Curies O.OOE+OO 3.l IE-08 0.00E+OO O.OOE+OO Total For Period Curies O.OOE+OO 9.25E-08 0.00E+OO O.OOE+OO Particulates Y-88 Curies O.OOE+OO l.07E-09 0.00E+OO O.OOE+OO Total For Period Curies O.OOE+OO l.07E-09 O.OOE+OO O.OOE+OO Tritium H-3 Curies l.49E-01 l.47E-02 2.12E-01 7.68E-02 Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
38 -
Table 2-3A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Gaseous Effluents - Ground Level Releases Unit:
Starting: 1-Jan-2018 Ending: 31-Dec-2018 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO Iodines No Nuclides Found Curies 0.00E+OO O.OOE+OO 0.00E+OO 0.00E+OO Particulates No Nuclides Found Curies O.OOE+OO 0.00E+OO 0.00E+OO O.OOE+OO Tritium No Nuclides Found Curies 0.00E+OO O.OOE+OO 0.00E+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO
- If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
39 -
Table 2-3A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Gaseous Effluents - Ground Level Releases Unit:
1 Starting: 1-Jan-2018 Ending: 31-Dec-2018 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
40 -
L Table 2-3B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Gaseous Effluents - Ground Level Releases Unit:
2 Starting: 1-Jan-2018 Ending: 31-Dec-2018 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO 0.00E+OO 0.00E+OO 0.00E+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO Particulates No Nuclides Found Curies 0.00E+OO 0.00E+OO 0.00E+OO 0.00E+OO Tritium No Nuclides Found Curies 0.00E+OO O.OOE+OO 0.00E+OO O.OOE+OO Gross Alpha No Nuclides Found Curies 0.00E+OO O.OOE+OO 0.00E+OO 0.00E+OO
- If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
41 -
Table 2-3B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -
2018 Gaseous Effluents - Ground Level Releases Unit:
2 Starting: 1-Jan-2018 Ending: 31-Dec-2018 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
42 -
Table 2-3C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -
2018 Gaseous Effluents - Ground Level Releases Unit:
Site Starting: 1-Jan-2018 Ending: 31-Dec-2018 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO Iodines No Nuclides Found Curies O.OOE+OO 0.00E+OO 0.00E+OO O.OOE+OO Particulates No Nuclides Found Curies 0.00E+OO 0.00E+OO 0.00E+OO O.OOE+OO Tritium No Nuclides Found Curies 0.00E+OO 0.00E+OO 0.00E+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO 0.00E+OO 0.00E+OO O.OOE+OO
- If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
43 -
Table 2-3C Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -
2018 Gaseous Effluents - Ground Level Releases Unit:
Site Starting: 1-Jan-2018 Ending: 31-Dec-2018 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO Tritium No Nuclides Found Curies O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO
- If Not Detected, Nuclide is Not Reported. Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.
44 -
Table 2-4A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Air Doses Due to Gaseous Releases Unit:
1 Starting: 1-Jan-2018 Ending: 31-Dec-2018 Cumulative Doses Per Quarter Tyge of ODCM Units 1ST Qtr
%0DCM 2ND Qtr
%0DCM 3RD Qtr
%0DCM 4TH Qtr
%0DCM Radiation Lmt Gamma Air 5.00E+OO mRad 2.21E-03 4.43E-02 3.69E-04 7.37E-03 2.61E-04 5.21E-03 l.37E-04 2.74E-03 Beta Air I.OOE+Ol mRad 8.03E-04 8.03E-03 1.37E-04 l.37E-03 9.21E-05 9.21E-04 4.84E-05 4.84E-04 Cumulative Doses Per Year Tyge of ODCM Units Year to End Date
%0DCM Recegtor Limit Radiation Lmt Gamma Air l.OOE+Ol mRad 2.98E-03 2.98E-02 Site Boundary SSE Mixed Mode R Air Dose Gamma Annual Beta Air 2.00E+Ol mRad l.08E-03 5.40E-03 Site Boundary SSE Mixed Mode R Air Dose Beta Annual 45 -
Cumulative Doses Per Quarter TyQe of ODCM Radiation Lmt Gamma Air 5.00E+OO Beta Air l.OOE+Ol Cumulative Doses Per Year TyQe of Radiation Gamma Air Beta Air Lmt ODCM l.OOE+Ol 2.00E+Ol Units mRad mRad Units mRad mRad Table 2-4B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Air Doses Due to Gaseous Releases Unit:
2 Starting: 1-Jan-2018 Ending: 31-Dec-2018 1ST Qtr
%0DCM 1.8IE-04 3.62E-03 6.39E-05 6.39E-04 Year to End Date 4.18E-04 1.48E-04 2ND Qtr
%0DCM 3RD Qtr 5.25E-05 l.05E-03 1.15E-04 1.85E-05 1.85E-04 4.06E-05
%0DCM ReceQtor 4.18E-03 7.38E-04 Site Boundary SSE Mixed Mode R Site Boundary SSE Mixed Mode R 46 -
%0DCM 4TH Qtr 2.30E-03 6.94E-05 4.06E-04 2.45E-05 Limit Air Dose Gamma Annual Air Dose Beta Annual
%0DCM l.39E-03 2.45E-04
Table 2-SA Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit:
1 Starting: 1-Jan-2018 Ending: 31-Dec-2018 Cumulative Doses Per Quarter Organ ODCMLmt Units 1ST Qtr
%0DCM 2ND Qtr
%0DCM 3RD Qtr
%0DCM 4TH Qtr
%0DCM Liver 7.SOE+OO mRem 3.69E-04 4.91E-03 6.56E-04 8.75E-03 6.29E-04 8.39E-03 5.0SE-04 6.73E-03 Total Body 7.SOE+OO mRem 3.75E-04 5.00E-03 6.56E-04 8.74E-03 6.29E-04 8.39E-03 5.0SE-04 6.73E-03 Bone 7.SOE+OO mRem 2.58E-05 3.44E-04 4.SlE-06 6.02E-05 l.90E-06 2.54E-05 7.32E-06 9.76E-05 GI-Lli 7.SOE+OO mRem 3.69E-04 4.92E-03 6.SSE-04 8.74E-03 6.29E-04 8.39E-03 5.0SE-04 6.73E-03 Thyroid 7.SOE+OO mRem 3.69E-04 4.91E-03 9.03E-04 l.20E-02 7.07E-04 9.43E-03 5.13E-04 6.84E-03 Kidney 7.SOE+OO mRem 3.69E-04 4.91E-03 6.56E-04 8.75E-03 6.30E-04 8.40E-03 5.0SE-04 6.73E-03 Lung 7.SOE+OO mRem 3.69E-04 4.92E-03 6.SSE-04 8.73E-03 6.29E-04 8.39E-03 5.0SE-04 6.73E-03 Cumulative Doses per Year Organ ODCM Units Year to Ending Date
%0DCM Recegtor Limit Lmt Bone l.SOOE+Ol mRem 3.952E-05 2.634E-04 Gas Controlling Receptor Iodine/Part Dose Annual Liver l.SOOE+Ol mRem 2.159E-03 l.439E-02 Gas Controlling Receptor Iodine/Part Dose Annual Total Body l.SOOE+Ol mRem 2.165E-03 l.443E-02
- Gas Controlling Receptor Iodine/Part Dose Annual Thyroid l.SOOE+Ol mRem 2.492E-03 l.661E-02 Gas Controlling Receptor Iodine/Part Dose Annual Kidney l.SOOE+Ol mRem 2.159E-03 1.440E-02 Gas Controlling Receptor Iodine/Part Dose Annual Lung l.SOOE+Ol mRem 2.158E-03 l.438E-02 Gas Controlling Receptor Iodine/Part Dose Annual GI-Lli l.SOOE+Ol mRem 2.159E-03 1.439E-02 Gas Controlling Receptor Iodine/Part Dose Annual 47 -
Table 2-SB Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Doses To A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases Unit:
2 Starting: 1-Jan-2018 Ending: 31-Dec-2018 Cumulative Doses Per Quarter Organ ODCMLmt Units 1ST Qtr
%0DCM 2ND Qtr
%0DCM 3RD Qtr
%0DCM 4TH Qtr
%0DCM GI-Lli 7.50E+OO mRem 1.80E-03 2.40E-02 l.59E-03 2.12E-02 9.81E-04 l.31E-02 l.74E-03 2.32E-02 Liver 7.50E+OO mRem l.80E-03 2.40E-02 l.59E-03 2.12E-02 9.81E-04 l.3 lE-02 1.74E-03 2.32E-02 Total Body 7.50E+OO mRem l.80E-03 2.40E-02 l.59E-03 2.12E-02 9.81E-04 l.31E-02 l.74E-03 2.32E-02 Kidney 7.50E+OO mRem l.80E-03 2.40E-02 l.59E-03 2.12E-02 9.81E-04 l.3 lE-02 l.74E-03 2.32E-02 Thyroid 7.50E+OO mRem l.80E-03 2.40E-02 l.59E-03 2.12E-02 9.81E-04 l.31E-02 1.74E-03 2.32E-02 Lung 7.50E+OO mRem l.80E-03 2.40E-02 1.59E-03 2.12E-02 9.8IE-04 l.31E-02 1.74E-03 2.32E-02 Cumulative Doses per Year Organ ODCM Units Year to Ending Date
%0DCM Recegtor Limit Lmt Liver l.500E+0I mRem 6.Il3E-03 4.075E-02 Gas Controlling Receptor Iodine/Part Dose Annual Total Body l.500E+Ol mRem 6.113E-03 4.075E-02 Gas Controlling Receptor Iodine/Part Dose Annual Thyroid l.500E+0I mRem 6.l 13E-03 4.075E-02 Gas Controlling Receptor Iodine/Part Dose Annual Kidney l.500E+Ol mRem 6.113E-03 4.075E-02 Gas Controlling Receptor Iodine/Part Dose Annual Lung l.500E+Ol mRem 6.l 13E-03 4.075E-02 Gas Controlling Receptor Iodine/Part Dose Annual GI-Lli l.500E+Ol mRem 6.113E-03 4.075E-02 Gas Controlling Receptor Iodine/Part Dose Annual 48 -
TABLE 2-6 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-2018 MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS EFFLUENT ANALYSES The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of gaseous radwaste samples.
Nuclide
. MDC(uCi/ML)
Nuclide MDC(uCi/ML).
MN-54 1.67E-14 KR-87 5.76E-08 C0-58 1.37E-14 KR-88 3.89E-08 FE-59 2.39E-14 XE-133 4.54E-08 C0-60 2.82E-14 XE-133M 1.19E-07 ZN-65 3.81E-14 XE-135 1.82E-08 M0-99 1.41E-13 XE-138 8.46E-08 CS-134 8.35E-15 1-131 1.68E-14 CS-137 8.38E-15 1-133 7.21E-14 CE-141 1.03E-14 CE-144 3.03E-14 49 -
Table 2-7A Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Gaseous Effluents - Batch Release Summary Unit:
1 Starting: 1-Jan-2018 Ending: 31-Dec-2018 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals I. Number of batch releases 159 22 73 91 345
- 2. Total time period for batch releases (Minutes) 6.38E+04 4.41E+03 1.03E+04 5.72E+03 8.43E+04
- 3. Maximum time period for a batch release (Minutes) 2.82E+03 8.33E+02 2.44E+03 1.43E+03 2.82E+03
- 4. Average time period for a batch release (Minutes) 4.02E+02 2.00E+02 1.41E+02 6.29E+Ol 2.44E+02
- 5. Minimum time period for a batch release (Minutes) 5.00E+OO 5.00E+OO 1.00E+OO 1.00E+OO l.OOE+OO
- so -
Table 2-7B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Gaseous Effluents - Batch Release Summary Unit:
2 Starting: 1-Jan-2018 Ending: 31-Dec-2018 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals
- 1. Number of batch releases 35 38 38 47 158
- 2. Total time period for batch releases (Minutes) 5.55E+03 l.7IE+03 3.88E+03 2.34E+03 l.35E+04
- 3. Maximum time period for a batch release (Minutes) 2.69E+03 l.02E+02 2.l 1E+03 3.10E+02 2.69E+03
- 4. Average time period for a batch release (Minutes) l.59E+02 4.49E+Ol 1.02E+02 4.97E+Ol 8.53E+Ol
- 5. Minimum time period for a batch release (Minutes) 2.00E+OO l.OOE+OO 4.00E+OO 2.00E+OO l.OOE+OO 51 -
Gaseous Releases
- 1. Number of Releases
- 2. Total Time For All Releases
- 3. Maximum Time For A Release
- 4. Average Time For A Release
- 5. Minimum Time For A Release
- 6. Total activity for all releases Table 2-SA Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT -
2018 Units (Minutes)
(Minutes)
(Minutes)
(Minutes)
(Curies)
Gaseous Effluents - Abnormal Release Summary Unit:
Starting: 1-Jan-2018 Ending: 31-Dec-2018 1ST Quarter 2ND Quarter 3RD Quarter 0
0 0
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO 52 -
4TH Quarter Year Totals 0
0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
Gaseous Releases I. Number of Releases
- 2. Total Time For All Releases
- 3. Maximum Time For A Release
- 4. Average Time For A Release
- 5. Minimum Time For A Release
- 6. Total activity for all releases Table 2-8B Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT-2018 Units (Minutes)
(Minutes)
(Minutes)
(Minutes)
(Curies)
Gaseous Effluents - Abnormal Release Summary Unit:
2 Starting: 1-Jan-2018 Ending: 31-Dec-2018 1ST Quarter 2ND Quarter 3RD Quarter 0
0 0
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 53 -
4TH Quarter Year Totals 0
0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
r-3.0 SOLID WASTE 3.1 Regulatory Requirements 3.1.1 Solid Radioactive Waste System FNP-0-M-30, PROCESS CONTROL PROGRAM, step B.3.1 states that the radwaste solidification system shall be OPERABLE and used, as applicable in accordance with a PROCESS CONTROL PROGRAM, for the SOLIDIFICATION and packaging of radioactive wastes to ensure meeting the requirements of 10 CFR Part 20 and 10 CFR Part 71 prior to shipment of radioactive wastes from the site.
3.1.2 Reporting Requirements FNP-0-M-30, PROCESS CONTROL PROGRAM, step B.5.1 states that the Annual Radioactive Effluent Release Report, submitted in accordance with Technical Specifications 5.6.2 and 5.6.3, shall include a summary of the quantities of solid radwaste released from the units as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste," Revision 2, issued June 2009, with data summarized on an annual basis following the format of Table A-3 thereof.
3.2 Solid Waste Data Regulatory Guide 1.21 Revision 2 Table A-3 is found in the report as Table 3-1.
54 -
TABLE 3-1 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-2018 SOLID RADIOACTIVE WASTE SHIPPED FOR PROCESSING OR DISPOSAL Starting 01-Jan-2018 Ending 31-Dec-2018 Resins, Filters, and Evaporator Bottoms Waste Class ft3 A
2.76E+02 B
7.70E+Ol C
6.11E+Ol ALL 4.14E+02 Major Nuclides for the Above Table:
Waste Class "A":
C-14 6.98%
Ni-63 32.39%
Waste Class "B":
Fe-55 20.13%
Waste Class "C":
H-3 1.28%
Co-60 35.65%
Nb-95 2.42%
ALL:
C-14 1.04%
Sb-125 1.72%
Dry Active Waste Waste Class ft3 A
1.07E+04 B
O.OOE+OO C
O.OOE+OO ALL 1.07E+04 Major Nuclides for the Above Table:
Waste Class "A":
Waste Class "B" N/ A Waste Class "C" N/ A ALL:
H-3 10.26%
Co-58 13.45%
Nb-95 12.53%
H-3 10.26%
Co-58 13.45%
Nb-95 12.53%
Irradiated Components Waste Class A
B C
ALL Major Nuclides for the Above Table:
Waste Class "A" N/ A Waste Class "B" N/ A Waste Class "C" N/ A ALL N/A ft3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Volume Fe-55 8.57%
Sb-125 7.53%
Co-60 41.03%
C-14 7.64%
Ni-63 8.94%
Sb-125 1.39%
Fe-55 19.65%
Volume C-14 3.95%
Co-60 19.55%
Tc-99 1.48%
C-14 3.95%
Co-60 19.55%
Tc-99 1.48%
Volume 55 -
m3 7.82E+OO 2.lBE+OO 1.73E+OO 1.17E+Ol Co-58 8.74%
Ni-63 36.12%
Fe-55 30.43%
Zn-65 1.06%
Co-60 40.11%
m3 3.03E+02 O.OOE+OO O.OOE+OO 3.03E+02 m3 Cr-51 2.83%
Ni-63 8.20%
Cr-51 2.83%
Ni-63 8.20%
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Curies Shipped 1.27E+01 1.39E+02 6.BBE+OO 1.58E+02 Co-60 32.47%
Sb-125 1.20%
Co-58 6.19%
Zr-95 1.18%
Ni-63 34.64%
Curies Shipped 1.79E+OO O.OOE+OO O.OOE+OO 1.79E+OO Fe-55 16.85%
Zr-95 8.40%
Fe-55 16.85%
Zr-95 8.40%
Curies Shipped O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
Other Waste Waste Class ft3 A
1.87E+04 B
O.OOE+OO C
O.OOE+OO ALL 1.87E+04 Major Nuclides for the Above Table:
Waste Class "A":
Waste Class "B":
Waste Class "C":
ALL:
Sum of All Low-Level Waste Shipped from Site Waste Class A
B C
ALL H-3 11.18%
Co-58 14.58%
Nb-95 17.99%
N/A N/A H-3 11.18%
Co-58 14.58%
Nb-95 17.99%
ft3 2.97E+04 7.70E+01 6.11E+01 2.98E+04 Major Nuclides for the Above Table:
Waste Class "A":
H-3 1.54%
Co-60 30.88%
Sb-125 6.62%
Waste Class "B":
Fe-55 20.13%
Waste Class "C" :
H-3 1.28%
Co-60 35.65%
Nb-95 2.42%
ALL:
C-14 1.07%
Ni-63 34.35%
{Continued)
Volume C-14 1.43%
Co-60 13.52%
Tc-99 2.28%
C-14 1.43%
Co-60 13.52%
Tc-99 2.28%
Volume C-14 6.61%
Fe-55 9.58%
Co-60 41.03%
C-14 7.64%
Ni-63 8.94%
Sb-125 1.39%
Fe-55 19.62%
Sb-125 1. 70%
56 -
m3 5.29E+02 O.OOE+OO O.OOE+OO 5.29E+02 m3 Cr-51 4.77%
Ni-63 6.94%
Cr-51 4.77%
Ni-63 6.94%
8.40E+02 2.18E+OO 1.73E+OO 8.44E+02 Ni-63 29.43%
Zr-95 1.03%
Ni-63 36.12%
Fe-55 30.43%
Zn-65 1.06%
Co-58 1.11%
Curies Shinned 2.59E-02 O.OOE+OO O.OOE+OO 2.59E-02 Fe-55 11.49%
Zr-95 12.10%
Fe-55 11.49%
Zr-95 12.10%
Curies Shipped 1.45E+01 1.39E+02 6.88E+OO 1.60E+02 Co-58 9.32%
Nb-95 1.74%
Sb-125 1.20%
Co-58 6.19%
Zr-95 1.18%
Co-60 39.88%
4.0 DOSES TO MEMBERS OF THE PUBLIC INSIDE THE SITE BOUNDARY 4.1 Regulatory Requirements Current FNP effluent controls as established by ODCM 6.1 do not require assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (ODCM Figure 10-1).
4.2 Demonstration of Compliance However, this assessment has been performed for 2018 using the methods described in ODCM 6.2 and is included in this section as Table 4-1.
57 -
Location Name:
Distance (kilometers):
Sector:
Occupancy Factor:
Age Group:
Mixed Mode Release Mixed Mode Release Ground Level Release Ground Level Release Lung Bone Thyroid Liver GI-Lli Kidney Total Body Skin Table 4-1 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2018 Doses to a Member of the Public Due to Activities Inside the Site Boundary Visitor Center 3.06E-Ol N
l.37E-03 Child Noble Gas Starting: 1-Jan-2018 Ending: 31-Dec-2018 Unit: Site Particulate and Radioiodine Particulate and Radioiodine Noble Gas X/Q (sec/m3): 8.80E-06 X/Q (sec/m3): 8.80E-06 X/Q (sec/m3): 1.04E-04 X/Q (sec/m3): l.04E-04 D/Q (m-2): 6.20E-08 D/Q (m-2): 4.80E-07 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year mRem 6.80E-08 7.04E-08 5.05E-08 7.05E-08 2.59E-07 mRem 2.38E-l l l.07E-10 7.85E-12 l.67E-12 1.40E-I0 mRem 6.80E-08 7.24E-08 5.13E-08 7.05E-08 2.62E-07 mRem 6.80E-08 7.04E-08 5.05E-08 7.05E-08 2.59E-07 mRem 6.80E-08 7.04E-08 5.05E-08 7.05E-08 2.59E-07 mRem 6.80E-08 7.04E-08 5.05E-08 7.05E-08 2.59E-07 mRem 6.80E-08 7.04E-08 5.05E-08 7.05E-08 2.59E-07 mRem O.OOE+OO l.16E-I0 5.24E-12 2.60E-13 l.22E-10 58 -
Location Name:
Distance (kilometers):
Sector:
Occupancy Factor:
Age Group:
Mixed Mode Release Mixed Mode Release Ground Level Release Ground Level Release Thyroid Lung Bone Skin GI-Lli Kidney Liver Total Body Table 4-1 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2018 Doses to a Member of the Public Due to Activities Inside the Site Boundary Starting: 1-Jan-2018 Ending: 31-Dec-2018 Service Water Pond 9.66E-Ol N
7.57E-03 Child Noble Gas Unit: Site Particulate and Radioiodine Noble Gas Particulate and Radioiodine X/Q (sec/m3): 9.75E-07 X/Q (sec/m3): 9.75E-07 X/Q (sec/m3): 4.74E-05 X/Q (sec/m3): 4.74E-05 D/Q (m-2): 2.78E-08 D/Q (m-2): l.3 IE-07 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year mRem 4.I6E-08 4.45E-08 3.I4E-08 4.32E-08 1.6IE-07 mRem 4.I6E-08 4.33E-08 3.09E-08 4.3IE-08 1.59E-07 mRem l.46E-11 2.49E-10 1.29E-l 1 1.42E-12 2.78E-10 mRem O.OOE+OO 2.89E-10 1.30E-1I 6.45E-I3 3.02E-10 mRem 4.I6E-08 4.33E-08 3.09E-08 4.3IE-08 1.59E-07 mRem 4.I6E-08 4.33E-08 3.09E-08 4.3IE-08 l.59E-07 mRem 4.16E-08 4.33E-08 3.09E-08 4.3IE-08 1.59E-07 mRem 4.16E-08 4.33E-08 3.09E-08 4.3IE-08 l.59E-07 59 -
Location Name:
Distance (kilometers):
Sector:
Occupancy Factor:
Age Group:
Ground Level Release Mixed Mode Release Mixed Mode Release Ground Level Release Kidney Total Body GI-Lli Thyroid Liver Lung Bone Skin Table 4-1 Joseph M Farley Nuclear Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2018 Doses to a Member of the Public Due to Activities Inside the Site Boundary Starting: 1-Jan-2018 Ending: 31-Dec-2018 River Water Discharge - Air 1.64E+OO N
1.14E-02 Child Noble Gas Noble Gas Unit: Site Particulate and Radioiodine Particulate and Radioiodine X/Q (sec/m3): l.63E-05 X/Q (sec/m3): 7.05E-07 X/Q (sec/m3): 7.05E-07 X/Q (sec/m3): 1.63E0 05 D/Q (m-2): l.39E-08 D/Q (m-2): 4.55E-08 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year mRem 4.53E-08 4.70E-08 3.37E-08 4.70E-08 1.73E-07 mRem 4.53E-08 4.70E-08 3.37E-08 4.70E-08 1.73E-07 mRem 4.53E-08 4.70E-08 3.37E-08 4.70E-08 l.73E-07 mRem 4.53E-08 4.84E-08 3.42E-08 4.70E-08 l.75E-07 mRem 4.53E-08 4.70E-08 3.37E-08 4.70E-08 l.73E-07 mRem 4.53E-08 4.70E-08 3.37E-08 4.70E-08 l.73E-07 mRem l.59E-l l l.90E-10 1.04E-l 1 l.37E-12 2.17E-10 mRem O.OOE+OO 2.17E-10 9.78E-12 4.86E-13 2.28E-10 60 -
5.0 TOTAL DOSE FROM URANIUM FUEL CYCLE (40CFR190) 5.1 Regulatory Requirements Technical Specification 5.5.4.j states that the dose or dose commitment to any MEMBER OF THE PUBLIC over a calendar year, due to releases of radioactivity and to radiation from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or to any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem (as stated in ODCM 5.1).
With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of ODCM 2.1.3, 3.1.3, or 3.1.4, calculations shall be made according to ODCM 5.2 methods to determine whether the above (ODCM 5.1) limits have been exceeded (as stated in ODCM 5.1.2).
5.2 Demonstration of Compliance Since none of the ODCM 2.1.3, 3.1.3, or 3.1.4 limits were exceeded during 2018, no calculations were required.
6.0 METEOROLOGICAL DATA Meteorological data are retained onsite; these data are available to the NRC upon request. The meteorological data include annual summaries of hourly measurements of wind speed, wind direction and atmospheric stability in the form of joint frequency distribution tables.
7.0 PROGRAM DEVIATIONS 7.1 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 7.1.1 Regulatory Requirements ODCM 7.2.2.6 states in part that the Annual Radioactive Effluent Release Report (the report) shall include deviations from the liquid and gaseous effluent monitoring instrumentation operability requirements included in Sections 2.1.1 and 3.1.1 of the ODCM. The report must also include an explanation as to why the inoperability was not corrected in a timely manner.
7.1.2 Description of Deviations SGBD low service water dilution flow trip inoperable for greater than 30 days. The low dilution flow trip could not be removed due to the circulating water canal level compensatory measures being in place to cycle N2P26V550 in order to maintain that level based on the failure of the normal level control valve N2P26LCV560 to control in automatic. Anytime N2P26V550 is cycled, service water must be recirculated back to the wet pit. Under this configuration, enough dilution flow cannot be obtained, even with an additional service water pump started, to warrant re-instating the low dilution flow trip without tripping SGBD.
U2 RE-15 "SJAE AIR EJECTOR MONITOR" Inoperable for > 30 days due to parts unavailability.
U2 R-23A failed low sporadically locking control room annunciator FH2 into alarm causing all ODCM rad monitors to be declared inoperable for> 30days. U2 RE-23A is not required per the ODCM, it 61 -
serves as a backup to RE-238 which monitors SGBD effluent. Control Room annunciator issues have since been resolved to ensure no future occurrences of this nature.
Unit-2 RE-06 "Sample Room Radiation Monitor" declared inoperable for excessive background counts. This caused control room annunciator FH2 to become locked into alarm causing all ODCM rad monitors to be declared inoperable for> 30days. Several attempts were made to repair the radiation monitor without success. It was determined to be a parts issue that was not available in stock.
U2 RE-298 "Plant Vent Stack Radiation Monitor" inoperable for > 30 days. Due to equipment issues encountered during the performance of maintenance and parts unavailability.
Ul RE-298 "Plant Vent Stack Radiation Monitor" inoperable for > 30 days. During a calibration the detector failed requiring parts not in stock.
Unit 1 RE18 Inoperable for > 30 days due to inadequate communication and scheduling errors.
7.2 Effluent Sample Analysis Exceeding Minimum Detectable Concentration (MDC) 7.2.1 Regulatory Requirements ODCM 7.2.2.6 states in part that the report shall include deviations from the MDC requirements included in ODCM Tables 2-3 and 3-3.
7.2.2 Description of Deviations There were no deviations during 2018.
7.3 Incorrect Compositing of Liquid or Gaseous Effluent Samples 7.3.1 Regulatory Requirements ODCM 7.2.2.6 states in part that the report shall include deviations from composite sampling requirements included in ODCM Tables 2-3 and 3-3.
7.3.2 Description of Deviations There were no deviations during 2018.
8.0 CHANGES TO THE PLANT FARLEY ODCM 8.1 Regulatory Requirements Pursuant to Technical Specification 5.5.1.c and ODCM 7.2.2.5, licensee initiated changes to the ODCM shall be submitted to the Nuclear Regulatory Commission as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period in which any changes were made. Included are changes to the radiological environmental monitoring program sampling locations or dose calculation locations or pathways, including any changes made pursuant to ODCM 4.1.2.2.2 (land use census).
8.2 Description of Changes ODCM updated to Version 26.0 Per LDCR 2018-026 and 2017-044 62 -
- 1. Removed all references to radiation monitors RE-14 and RE-22 and replaced them with RE-29B and RE-29C to reflect recent radiation monitor replacements.
2.Removed the requirement for on-site groundwater monitoring which is not required per NUREG 1301 at Farley.
9.0 MAJOR CHANGES TO LIQUID, GASEOUS, OR SOLID RADWASTE TREATMENT SYSTEMS 9.1 Regulatory Requirements ODCM 7.2.2.7 states in part that, as required by ODCM 2.1.5 and 3.1.6, licensee initiated MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (liquid and gaseous) shall be reported to the Nuclear Regulatory Commission in the Annual Radioactive Effluents Release Report covering the period in which the change was reviewed and accepted for implementation.
Process Control Program (PCP) B.5.1.2 states that licensee initiated major changes to the solid radioactive waste treatment system shall be reported to the Nuclear Regulatory Commission in the Annual Radioactive Effluent Release Report for the period in which the change was implemented. The discussion of each change shall include the information specified in PCP B.4.1.
9.2 Description of Major Changes There were no changes to the Process Control Program during 2018.
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L Farley Nuclear Plant Appendix A CARBON-14 Carbon-14 (C-14) is a naturally-occurring radionuclide with a 5730 year half-life. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere.
Nuclear power plants also produce C-14, but the amount is infinitesimal compared to what has been distributed in the environment due to weapons testing and what is produced by natural cosmic ray interactions.
As nuclear plants have improved gaseous waste processing systems and improved fuel performance, the percentages of "principal radionuclides" in gaseous effluents have changed, and C-14 has become a larger percentage. "Principal radionuclides" are determined based on public dose contribution or the amount of activity discharged compared to other radionuclides of the same effluent type. In Revision 2 (June 2009) of Regulatory Guide 1.21 (RG 1.21), "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste,"
the NRC recommended re-evaluating "principal radionuclides" and reporting C-14 as appropriate.
In 2010 Radioactive Effluent Release Reports, virtually all U. S. nuclear power plants started reporting C-14 amounts released and resulting doses to the maximally exposed member of the public.
Because C-14 is considered a hard-to-detect radionuclide which must be chemically separated from the effluent stream before it can be measured, RG 1.21 provides the option of calculating the C-14 source term based on power generation. The Electric Power Research Institute (EPRI) developed an accepted methodology for calculating C-14, and published the results in Technical Report 1021106 (December 2010), "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents."
Evaluation of C-14 in radioactive liquid effluents is not required because the quantity and dose contribution has been determined to be insignificant.
At Plant Farley, the annual quantity of C-14 released in gaseous effluents was estimated to be 9.28 Curies (per unit). Approximately 30% of the C-14 released is in the form of 14C02 and is incorporated into plants through photosynthesis. Ingestion dose results from this pathway. The remaining 70% is estimated to be organic. Both the organic and inorganic forms of C-14 contribute to inhalation dose. A child is the maximally exposed individual, and bone dose is the highest organ dose. Using the dose calculation methodology from the Farley ODCM, the resulting bone dose to a child located at the controlling rec::eptor location would be 4.llE-01 mrem in a year which is 2.74% of the regulatory limit of 15 mrem per year (per unit) to any organ due to gaseous effluents. The resulting total body dose to a child located at the controlling receptor location would be 8.21E-02 mrem in a year which is 0.54% of the regulatory limit of 15 mrem per year (per unit) total body dose due to gaseous effluents.
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Farley Nuclear Plant Appendix B Correction to 2017 Annual Radioactive Effluent Release Report On page 64, Section 3.0, A typographical error is present in the 2017 Report.
Typographical error discovered in the 2017 1.21 report. The error is present in Table 3-1 "Solid Radioactive Waste Shipped for Processing or Disposal". The error displays an inaccurate volume of 1.79E+01 cubic feet when the correct value should be 1.79 E+02 cubic feet. Th~ volume was displayed accurately in the summation section of Table 3-1.
This was a typographical error that occurred during transcription that did not effect the reported summation of releases.
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