ML18121A167

Annual Radioactive Effluent Release Report

ML18121A167
Person / Time
Site:	Callaway
Issue date:	05/01/2018
From:	Ameren Missouri
To:	Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
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ML18121A165	List: ML18121A167 ULNRC-06430, Submittal of 2017 Annual Radioactive Effluent Release Report
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Download: ML18121A167 (111)

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Callaway Energy Center 2017 Annual Radioactive Effluent Release Report Callaway Energy Center 2017 Annual Radioactive Effluent Release Report Renewed Facility Operating License NPF-30 Docket Numbers 50-483 and 72-1045 AffletBll Callaway MISSOURI Energy Center

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report Callaway Energy Center 2017 Annual Ahstract The Annual Radioactive Radio active Effluent R&ase Report covers the opertio of Effluent Release the Callaway Energy Center during the ear 2O17 The report Report Includes a summary of the quantities of Renewed Facility Operating License NPF-30 radioacthe liquid and Docket Numbers 50-483 and 72-1045 gaseous effluents and solid waste released

1. Introduction This Annual Radioactive Effluent Release Report (ARERR) is submitted from the unit. The by Union Electric Co., Uba Ameren Missouri, in accordance with the

, report also includes an requirements of 10 CER 50.36a and 10 CFR 72.44fd)(3), Callaway annual summaryof Energy Center Technical Specification 5.6.3, and HI-STORM UMAX Certificate of Compliance Section Sic. This report is for the period hourly meteorological January 1, 2017 to December 31, 2017. data collected during the The doses to the Member of the Public from all liquid and gaseous year and an assessment effluents discharged during the reporting period were small fractions of radiation dose to the of the NRC and EPA regulatory limits and the Radioactive Effluent Control limits in the Offsite Dose Calculation Manual. Member of the Public from hquid and gaseous Radionuclide concentrations in liquid and gaseous effluents were obtained by effluent sampling and radiological analysis in accordance with the requirements of FSAR-SP/ODCM Radiological Effluent Control C 1 (REC) Table 16.11-1 and Table 16.11-4. Gamma spectroscopy was the

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report primary analysis technique used to determine the radionuclide composition and concentration of liquid and gaseous effluents. Composite samples were analyzed for the hard to detect nuclides by an independent laboratory. Tritium and gross alpha were measured for both liquid and gaseous effluents using liquid scintillation counting and gas flow proportional counting techniques, respectively. The total radioactivity in effluent releases was determined from the measured concentrations of each radionuclide present and the total volume of effluents discharged.

The concept of average energy is not applicable to the Callaway Plant radiological effluent monitoring program since the release rate limits for fission and activation gases in gaseous effluent are not based on the average energy of the radionuclide mixture.

The Radiological Effluent Control (REC) limits applicable to the release of radioactive material in liquid and gaseous effluents are provided below.

Regulatory LInlits The Callaway regulatory limits are provided in the Radiological Effluent Controls in FSAR SPJODCM Chapter 16.11.

Fission and Activation Gases (Noble Gases]

The dose rate due to radioactive noble gases released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin.

The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the site boundary 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.

Radioiodine, Tritium, and Particulates The dose rate due to lodine-131 and lodine-133, tritium and all radionuclides in particulate form with half-lives greater than eight (8) days released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 1500 mrem/yr to any organ.

The dose to a Member of the Public from lodine-131 and lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than eight (8) days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report

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.

Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to 10 times the concentrations specified in 10 CFR 20 Appendix B To Part 20, Table 2, Column 2 (Effluent Concentrations) for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.OE-04 l.iCi/mL total activity.

The dose or dose commitment to an Individual from radioactive materials in liquid effluents released to unrestricted areas shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and 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 whole body and to less than or equal to 10 mrem to any organ.

Uranium Fuel Cycle Sources The annual (calendar year) dose or dose commitment to any Member of the Public 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 any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.

2. Gaseous Effluents The quantity of radioactive material released in gaseous effluents during the reporting period is summarized in Table A-i. The quarterly and annual sums of all radionuclides discharged in gaseous effluents are reported in Tables A-lA and A-lB. All gaseous effluent releases are considered to be ground level.

Gaseous Batch Releases Qi & Q2 Q3 & Q4 Number of batch releases: 29 23 Total time period for batch releases: minutes 1773 9031 Max time period for a batch release: minutes 435 6519 Avg time period for a batch release minutes 61 393 Mm. time period for a batch release: minutes 19 31

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report The quantity of C released in gaseous effluents was calculated as described in EPRI Technical Report 1021106.

There were no radioactive effluents from the Independent Spent Fuel Storage Installation (ISFSI).

The HI-STORM UMAX Canister Storage System does not create any radioactive materials or have any radioactive waste treatment systems. Specification 3.1.1, Multi-Purpose Canister (MPC),

provides assurance that there are no radioactive effluents from the SF51.

3. Liquid Etiluents The quantity of radioactive material released in liquid effluents during the reporting period is summarized in Table A-2. The quarterly and annual sums of all radionuclides discharged in liquid effluents are reported in Table A-2A. All liquid effluents were discharged in batch mode; there were no continuous liquid discharges for the reporting period. Dilution by the Missouri River, in the form of the near- field dilution factor, is utilized in the ODCM dose calculation methodology.

Liquid Batch Relea5es 01 & 02 03 & 04 Number of batch releases 22 38 Total time period for batch releases minutes 10218 16925 Max time period for a batch release minutes 873 806 Avg. time period for a batch release: minutes 464 445 Mm. time period for a batch release: minutes 255 224

4. Solid Waste Storage and Shipments The volume and activity of solid waste shipped for disposal is provided in Table A-3.

5. Dose Assessments The annual evaluation of dose to the Member of the Public is calculated in accordance with the methodology and parameters in the ODCM and is reported in Tables A-4 and A-5.

Estimation of Carbon- 14 in Nuclear Power Plant Gaseous Effluents, Technical Report 1021106, Electric Power Research Institute, December, 2010.

Certificate of Compliance No. 1040, Appendix A, Technical Specifications for the HI STORM UMAX Canister Storage System, Specification 5,1,

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report 5.1 Table A-4, Dose Assessments, 10 CFR 50, Appendix I The dose assessments reported in Table A-4 were calculated using the methodology and parameters in the ODCM and demonstrate compliance with 10 CFR 50, Appendix I. The gamma air dose and beta air dose were calculated at the nearest Site Boundary location with the highest value of X/Q. as described in the ODCM. The maximum organ dose from gaseous effluents was calculated for the ingestion, inhalation, and ground plane pathways at the location of the nearest resident with the highest value of D/Q, as described in the ODCM. The organ dose does not include the dose from 14C, which is listed separately.

5.2 Table A-5, EPA 40 CFR 190 Individual in the Unrestricted Area The dose assessments reported in Table A-5 are the doses to the Member of the Public from activities within the Site Boundary plus the doses at the location of the Nearest Residence. A large portion of the residual land of the Callaway Site is managed by the State of Missouri Conservation Department as the Reform Wildlife Management Area. Pursuant to the guidance provided in Regulatory Guide 1.21, rev.2, the dose reported in Table A-S is the sum of the dose from gaseous effluents (at the Nearest Resident location and within the Site Boundary), plus the dose contribution due to activities within the Site Boundary and the organ dose from inhalation of 4C (at the Nearest Resident location and within the Site Boundary). The dose assessments in Table A-5 demonstrate compliance with 10 CFR 20.1301(e) and 40 CFR 190.

6. Supplemental Information 6.1 Abnormal Releases or Abnormal Discharges There were no abnormal releases or abnormal discharges during the reporting period.

6.2 Non- routine Planned Discharges There were no non- routine planned discharges during the reporting period.

6.3 Radioactive Waste Treatment System Changes There were no major changes to the liquid or gaseous radwaste treatment system during the reporting period.

6.4 Annual Land Use Census Changes There were no changes identified in the locations for dose calculation. Changes in sample locations identified in the Land Use Census are described in the Annual Radioactive Environmental Operating Report.

6.5 Elfluent Monitoring System Non functionality BM-RE-52, Steam Generator Blowdown Discharge Monitor, has been non- functional since 2010 when the surveillances were changed to on- demand. The procedures for performing discharges

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report by this pathway were voided in 2007. The last discharge via this pathway was Q2 1986, therefore the associated action statement has been met since BMRE52 became non- functional.

Callaway Energy Center is in the process of removing BM-RE-52 from ODCM/ FSAR-SP Table 16.11-2, Radioactive Effluent Monitoring Instrumentation the associated discharge point from ODCM/FSAR-SP Table 16.11-1, Radioactive Liquid Waste Sampling and Analysis Program.

While operating in mode 1, GTRE22, Noble Gas Activity Monitor, was non- functional for 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> due to equipment malfunction between 7/2/17 10:14:00 7/3/17 21:20:00. During this time, there was a containment vent in progress on 7/2/17 until 12:29, which is an overlap of 2:15 his. The associated action statement requires that the purge be suspended within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, therefore the requirements of the associated action statement were met.

6.6 Offsite Dose Calculation Manual Changes APA-ZZ-01003, Callaway Plant Offsite Dose Calculation Manual was revised during the reporting period. The changes are described in detail in Appendix B to APA-ZZ-01003. A complete copy of APA-ZZ-01003 rev. 22 with revision bars showing the areas of change is attached.

6.7 Process Control Program Changes There were no changes to APA-ZZ-01011, Process Control Program during the reporting period.

6.8 Corrections to Previous Reports The condition discussed in Section 6.5 for BM-RE-52 affects all reports 2010- 2016.

6.9 Other Information Related to Radioactive Effluents Meteorological dispersion parameters, data recovery rate, and Joint Frequency Tables for the monitoring period are attached as Appendix B.

Callaway Plant Semiannual Radioactive Effluent Release Report, January- June 1986, Table 2B.

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report Appendix A Tables of Quantities Released in Liquid and Gaseous Radioactive Effluents and in Solid Radioactive Waste Shipments Tables of Doses from the Discharge of Liquid and Gaseous Radioactive Effluents

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report Table A-i: Gaseous Effluents-_Summation of All Releases Summation of Estimated

• Quarter Quarter Quarter Quarter All Releases Unit Total Uncertainty I 3 ioi4 j_/0,1 Fission &

Activation Ci 533E-2 4.06E-2 108E-1 495E-1 697E-1 20 Gases Aseldu]L iCi/s 6.85E-3 5.16E-3 1.36E-2 6.22E-2 2.20E-2 Relea.ce Rate

%of Limit  % N/A N/A N/A N/A N/A 31lodine Ci 0 0 0 0 0 23 Average Release Rate

% oJ Limit  % N/A N/A N/A N/A N/A Particulates Ci 0 0 0 0 0 30 tlverage Ci/s 0 0 0 0 0 Release Rate

% of Limit  % N/A N/A N/A N/A N/A Gross Alpha Ci 1.57E-7 2.96E-7 1.58E-7 1.29E-7 740E-7 3H Ci 5.75E0 9.02E0 1.O1E1 1.82E1 4.31E1 14 Atei age

&Ci/s 740E-1 1.15E0 1.28E0 2.29E0 1.37E0 Release Rate

% of Limit  % N/A N/A N/A N/A N/A 4C Ci 2.60E0 26OEO 2.60E0 2.60E0 1.04E1 Safety Analysis calculation 87-063-00, January 6, 1988 14C activity is estimated based on EPRI report TR-1021106, Estimation of 14C in Nuclear Power Plant Effluents, December 2010.

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report Table A-lA: Gaseous Effluents- Ground Level Release- Batch Mode Fission &

. Quarter Quarter Quarter Quarter Total for Activation Units 1 2 3 4 theyear Gases 41Ar Ci 4.30E-2 4.06E-2 1.08E-1 4.90E-1 6.82E-1 851(r Ci 1.03E-2 0 0 4.65E-3 1.50E-2 133Xe Ci 0 0 0 4.86E-5 4.86E-5 Total Ci 5.33E-2 4.06E-2 1.08E-1 4.95E4 6.97E-1 lodines & Quarter Quarter Quarter Quarter Total for ni Halogens 1 2 3 4 the year l Ci 0 0 0 0 0

. Quarter Quarter Quarter Quarter Total for Particulates Units 1 2 3 4 theyear Ci 0 0 0 0 0 3H Ci 1.49E-1 2.31E-1 5.84E-1 1.92E0 2.85E0 Grossa Ci 0 0 0 0 0 14C Ci 4.28E-1 4.28E-1 428E-1 4.28E-1 1.71E0

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report Table A-1B: Gaseous Effluents- Ground Leve) Release- Continuous Mode Fission &

• Quarter Quarter Quarter Quarter Total for Activation Units 1 2 3 4 theyear Gases Ci 0 0 0 0 0 lodines & Quarter Quarter Quarter QuarteJ Total for Units Halogens 1 2 3 4 the year Ci 0 0 0 0 0

. Quarter Quarter Quarter Quarter Total for Particulates Units 1 2 3 4 theyear Ci 0 0 0 0 0 3H Ci Ci 5.60E0 1.57E-7 8.79E0 9.56E0

] 1.63E1 403E1 Gross a 2.96E-7 1.S8E-7 1.29E-7 7.40E-7 14C Ci

[ 2.17E0 2.17E0 2.17E0 2.17E0 8.68E0

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report Table A-2: Liquid Effluents- Summation of All Releases Est.

Summation of All Quarter Quarter Quarter Quarter

. Units Total Uncert.

Liquid Releases 1 2 3 4 (%)6 Fission and Activation Ci 4.97E-3 7.94E-3 5.14E-3 2.82E-2 4.62E-2 20 Products7 AegDilutedCoiic sCi/ml 4.96E-8 5.24E-8 2.09E-8 1.72E-7 6.98E-8

% of Limit  % N/A N/A N/A N/A N/A 3H Ci 1.30E2 431E2 6.73E2 1.24E2 1.42E3 14 Avg Diluted Co,ic iCi/mI 1.30E-3 2.85E-3 2.73E-3 1.12E-3 2.14E-3

% of Limit  % N/A N/A N/A N/A N/A Dissolved &

Ci 0.OOEO 0.OOEO 3.03E-4 L57E-3 1.$7E-3 27 Entrained Gases Avg Diluted Conc ilCi/mI 0.OOEO 0.OOEO 1.23E-9 9.57E-9 4.56E-09

% of Limit  % N/A N/A N/A N/A N/A Gross a Ci 0.OOEO 1.29E-4 5.29E-5 0.OOEO 1.82E-4 29 Avg Diluted Couc jCi/ml 0.OOEO 8.52E-10 2.15E-10 0.OOEO 457E-10 Vol Liquid Liters 3.13E6 3.39E6 5.07E6 5.15E6 1.67E7 Effluent8 Dilution Volume9 Liters 9.69E7 1.48E8 2.41E8 1.59E8 6.45E8 Avg river flow10 m3/s 1.50E3 4.69E3 2.44E3 1.77E3 2.60E3 Time period for hrs 6.68E1 1.04E2 1.70E2 1.12E2 4.52E2 releases 6

Safety Analysis calculation 87-063-00, January 6, 1928 Excludes 3H, noble gases, and gross alpha.

8 Primary system liquid effluent plus secondary liquid effluent, prior to dilution.

Does not include Missouri River dilution.

Average Missouri River flow for the year at the Hermann, MO monitoring station as reported by the USGS.

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report

[ission & Activation te4otforth I Products 5.06E-4 706E-4 9.85E-4 3.14E-4 251E-3 1.97E-4 1.43E-4 1.03E-4 7.63E-6 4.51E-4 9.08E-5 1.86E-3 1.52E-4 8.77E-5 2.19E-3 4.16E-3 5.12E-3 3.88E-3 2.27E-2 3.59E-2 2.66E-6 1.17E-S 0 9.34E-5 1.08E-4 9.89E-6 0 2.43E-5 3.58L-3 3.61E-3 0 9.57E-5 0 7.30E-4 8.26E-4 0 0 4.70E-6 0 4.70E-6 0 0 0 3.15E-4 3.15E-4 0 0 0 3.30E-4 3.30E-4 0 0 0 3.36E-5 3.36E-5 0 0 0 177E-5 1.77E-5 4.97E-03 794E-03 5.15E-03 2.82E-02 4.63E-2 Quarter Quartet Quarter Quarter Total for the 1 2 3 4 year 3.03E-4 1.57E-3 1.87E-3 1.30E2 4.31E2 6.73E2 1.84E2 142E3 Gross a 0 L29E-4 5.29E-5 0 1.82E-4

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report Table A-3: Low Level Waste Resins, Filters, And Evaporator Bottoms Waste Volume Curies Class ft3 m3 Shipped A 1 .60E+02 4.52E+00 1 .79E+00 B 0.OOE÷00 0.OOE+00 0.OOE÷00 C 7.50E+00 2.12E-01 1.74E+00 Unclassified 5.OOE÷00 1 .42E-01 2.03 E+00 All 1.67E+02 4.73E+00 3.53E+00 Major Nuclides for the Above Table: j-t---+i9-r H-3, C-14, Cr-51, Fe-55, Co-58, Co-60, Ni-59, Ni-63, Sr-90, Zr-95, Nb-94, Nb-95, Tc 99, Sn-117m, 1-129, Cs-134, Cs-137, Ce-144, Pu-238, Pu-239, Pu-240, Pu-241, Pu-Dry Active Waste (DAW)

Waste Volume 1 f1 Curles Class tV m3 Shipped

/f A 1 .06E÷04 *.. 3.01 E÷02 1.41 E-01 B 0.OOE÷00 ( 0.OOE÷00 0.OOE+00 C 0.OOE÷00 0.OOE÷00 0.OOE÷00 Unclassified 0.OOE+00 0.OOE+00 0.OOE+00 All 1.06E+04 3.O1E÷02 1.41E-01 Major Nuclides for the Above Table:

H-3, C-14, Cr-51, Mn-54, Fe-55, Co-58, Co-60, Ni-59, Ni-63, Zn-65, Sr-90, Nb-94, Nb-95, Tc-99, Ru-106, Sb-125, 1-129, Cs-134, Cs-137, Pu-238, Pu-239, Pu-240, Pu Irradiated Components Waste Volume Curies Class ft3 m3 Shipped A 0.OOE÷00 0.OOE+00 0.OOE÷00 B 0.OOE÷00 0.OOE+00 0.OOE+00 C 0.OOE÷00 0.OOE+00 0.OOE+00 Unclassified 0.OOE÷00 0.OOE÷00 0.OOE+00 All 0.OOE+00 0.OOE+00 0.OOE÷00 Major Nuclides for the Above Table:

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report Other Waste Waste Volume Curies Class W m3 Shipped A 0.OOE+00 0OOE÷00 0.OOE÷00 B 0.OOE÷00 0.OOE+00 O.OOE÷0O C 0.OOE÷00 0.OOE+O0 0.OOE÷00 Unclassified O.OOE+00 0.OOE÷00 0OOE+00 All 0.OOE+0O 0.OOE÷00 0.OOE÷00 Major Nuclides for the Above Table:

Sum Of All Low-Level Waste Shipped From Site Waste Volume Curles Class ft3 m3 Shipped A 1.08E÷04 3.06E+02 1.93E+00 B 0.OOE+00 0.OOE÷00 OOOE+00 C 7.50E+00 2.12E-01 1.74E÷00 Unclassified 5.OOE÷00 1 .42E-01 2.03E+0Q All 1 .08E+04 3.06E÷02 3.67E+00 Major Nuclides for the Above Table:

H-3, 0-14, Cr-51, Mn-54, Fe-55, Co-58, Co-60, Ni-59, Ni-63, Zn-65, Sr-90, Zr-95, Nb-94, Nb-95Tc-99, Ru-106, Sn-117m, Sb-125, 1-129, Cs-134, Cs-137, Ce-144, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Am-241 Cm-242, Cm-243, Cm-244

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report Table A-4: Dose Assessments, 10 CFR 50, Appendix I Quarter Quarter Quarter Quarter Yearly 1 2 3 4 total Liquid Effluent Dose Limit, 1.5 1.5 1.5 1.5 3 Total Body (mrem)

Total Body Dose (mrem) 7.23E-4 1.13E-3 1.45E-3 3.42E-4 3.65E-3

% Limit (%) 0.05% 0.08% 0.10% 0.02% 0.12%

Liquid Effluent Dose Limit, 5 10 Maximum Organ (mrem)

Maximum Organ Dose (mrem) 9.86E-4 1.34E-3 1.59E-3 5.30E-4 4.28E-3 3/4 Limit (%) 0.02% 0.03% 0.03% 0.01% 0.04%

Gaseous Effluent Dose Limit, 5 5 10 Gamma Air (mrem)

Gamma Air Dose (mrad) 2.04E-5 1.93E-5 5.13E-5 2.33E-4 3.24E-4

% Limit f%) 0.00% 0.00% 0.00% 0.00% 0.00%

Gaseous Effluent Dose Limit, 10 10 10 10 20 Beta Air fmrem)

Beta Air Dose (mrad) 8.22E-6 6.80E-6 1.81E-5 8.25E-5 1.16E-4

% Limit (%) 0.00% 0.00% 0.00% 0.00% 0.00%

Gaseous Effluent Dose Limit, 7.5 7.5 7.5 15 Maximum Organ (mrem)

Maximum organ dose (mrem) 1.50E-3 2.35E-3 2.63E-3 4.75E-3 1.13E-2 3/4 Limit f%) 0.02% 0.03% 0.04% 0.06% 0.07%

4C Maximum organ dose 3.25E-3 3.25E-3 3.25E-3 3.25E-3 1.30E-2 (mrem)2

Iodine, 3h, and particulates with greater than an 8 day half- life.

12 Not included in above totals

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report Table A-5: EPA LLQ CFR 190 Individual in the Unrestricted Area Whole Body Thyroid Max Other Organ Dose Limit 25 mrem 75 mrem 25 mrem Dose 1.66E-02 1.64E-02 2.79E-02 3/4 Limit 0.07% 0.02% 0.11%

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report Appendix B Meteorological Para meters for the Reporting Period Joint Frequency Tables; Totals of Hours at Each Wind Speed &

Direction for the period January 1, 2017- December 31, 201 7

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report Meteorological Parameters for the Reporting Period Nearest Resident Dispersion Parameters Direction: NNW Distance: 2913 meters X/Q, Undecayed and Undepleted: 9.75E-07 sec/rn3 X/Q Decayed and Undepleted: 9.63E-07 sec/rn3 X/Q Decayed and Depleted: 812E-07 sec/rn3 D/QDeposition rate: 2.76E-09 m2 Site Boundary Dispersion Parameters Direction: SSW Distance: 1400 meters X/Q, Undecayed and Undepleted: 1.62E-06 sec/rn3 X/Q Decayed and Undepleted: 161E-06 sec/rn3 X/Q Decayed and Depleted: 1.43 E-06 sec/rn3 D/Q Deposition rate: 5.35E09 m2 Meteorological Data Recovery Rate 10 meters elevation Hours of valid data: 8723 Total hours in period: 8760 Recovery rate: 99.6%

60 meters elevation Hours of valid data: 8723 Total hours in period: 8760 Recovery rate: 99.6%

Joint Frequency Distribution: Hours at Wind Speed and Direction January- December, 2017 All Stabilities Elevations: Winds lOm Stability 6Gm Wind Speed Range (mis)

Wind Direction Sector <0.50 OS- 1 1.1- 1.5 1.6- 2 2.1-3 3.1-4 4.1-5 5.1-6 6.1-8 8.1- 10 >10.00 Total 3 19 65 66 164 118 89 42 23 6 0 595 N

NNE 0 47 65 69 163 119 51 14 3 1 0 532 6 43 54 52 116 86 49 19 4 0 0 429 NE 5 20 47 43 63 49 28 5 2 0 0 262 ENE 5 28 38 36 109 48 20 14 2 0 0 300 E

4 31 43 56 111 68 18 5 2 0 0 338 ESE 5 24 125 139 243 130 25 1 0 0 0 692 4 44 76 129 408 178 68 30 18 1 0 956 SSE 0 39 60 76 246 228 143 85 100 9 2 988 4 23 46 74 159 124 105 38 37 3 1 614 SSW 1 24 63 79 185 115 67 42 12 1 0 589 SW 3 28 50 48 103 69 27 15 6 2 0 351 WSW 6 35 33 41 88 95 68 29 27 1 0 423 w

2 24 52 54 134 77 88 31 26 0 0 488 WNW 0 21 72 82 149 130 81 28 8 0 0 571 NW 1 39 43 85 140 135 80 40 24 2 0 589 NNW 49 489 932 1129 2581 1769 1007 438 294 26 3 8717 Tot Hours of Calm 6 Hours of Variable Direction 0 Hours of Valid Data 8723 Hours of Missing Data 37 Hours in Period 8760

Joint Frequency Distribution. Hours at Wind Speed and Direction January- December, 2017 Class A Extremely Unstable based on lapse rate Elevations: Winds 1Dm Stability 6Dm Wind Speed Range tm/c)

Wind Direction Sector <0.50 0.5- 1 1,1- 1.5 1.6- 2 2 1-3 3.1-4 4.1-5 5.1-6 6.1-8 8.1-10 >10.00 Total N 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 1 1 0 0 0 2 E 0 0 0 0 0 0 0 2 0 0 0 2 ESE 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 2 9 5 0 0 0 0 16 SSE 0 0 0 0 4 8 8 1 0 0 0 21 S 0 0 0 1 1 12 12 3 11 0 0 40 SSW 0 0 0 0 0 4 7 3 5 0 0 19 SW 0 0 0 0 0 3 11 17 4 0 0 35 WSW 0 0 0 0 0 6 3 1 0 0 0 10 W 0 0 0 0 0 1 9 1 0 0 0 11 WNW 0 0 0 0 1 2 15 9 2 0 0 29 NW 0 0 0 0 0 0 16 0 1 0 0 17 NNW 0 0 0 0 0 0 2 0 0 0 0 2 Tot 0 0 0 1 8 45 89 38 23 0 0 204 Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data 204 Hours of Missing Data 37 Hours in Period 8760

Joint Frequency Distribution: Flours at Wind Speed and Direction January- December, 2017 Class B Moderately Unstable based on lapse rate Elevations: Winds 1Gm Stability 6Gm Wind Speed Range tmls)

Wind Direction Sector <0.50 0.5- 1 1.1- 1.5 1.6-2 2.1-3 3.1-4 4.1-5 5.1- 6 6.1-8 8.1-10 >10.00 Total N 0 0 0 0 0 0 0 0 2 0 0 2 NNE 0 0 0 1 1 2 1 0 0 0 0 5 NE 0 0 0 0 0 0 0 1 0 0 0 1 ENE 0 0 0 0 0 2 3 0 1 0 0 6 E 0 0 0 0 1 2 1 1 0 0 0 5 ESE 0 0 0 0 2 3 1 0 0 0 0 6 SE 00 0 2 9 13 5 0 0 0 0 29 SSE 0 0 0 3 16 15 4 4 1 0 0 43 5 0 0 1 1 iS 13 5 7 5 0 0 47 55W 0 0 0 1 8 14 12 4 10 0 0 49 SW 0 0 0 0 7 15 11 7 2 0 0 42 WSW 0 0 0 0 2 6 1 2 1 0 0 12 W 0 0 0 0 3 6 8 2 5 0 0 24 WNW 0 0 0 0 3 9 8 1 3 0 0 24 NW 0 0 0 0 3 6 5 1 1 0 0 16 NNW 0 0 0 0 2 1 4 1 3 0 0 11 Tot 0 0 1 8 72 107 69 31 34 0 0 322 Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data 322 Hours of Missing Data 37 Hours in Period 8760

Joint Frequency Distribution: Hours at Wind Speed and Direction January- December, 2017 Clasa C Slightly Unstable based on lapse rate Elevations: Winds 1Dm Stability 6Dm Wind Speed Range (mis)

Wind Direction Sector <D.5D D.5- 1 1.1- iS 1.6-2 2 1-3 3.1-4 4 1-5 5.1-6 6.1-8 8.1- tD >1D.DD Total N D D 1 1 9 9 3 4 3 1 D 31 NNE D D 0 1 7 8 2 2 D D D 20 NE D D D 1 3 3 3 2 2 D D 14 ENE 0 0 1 1 5 5 1 1 D D D 14 E D D D 2 3 3 2 2 D D D 12 ESE D D D 2 7 9 2 D D D D 2D SE DO 1 8 28 13 3 D D D D 53 SSE D D D 3 23 7 4 D 1 D D 38 S 0 0 1 9 13 11 13 7 13 2 0 69 SSW 0 0 0 6 19 12 21 7 5 0 0 70 SW 0 0 1 6 16 18 5 5 0 0 D 51 WSW 0 0 1 6 14 8 2 1 D 0 0 32 W 0 0 0 0 6 5 3 4 2 0 0 20 WNW 0 D 0 1 17 116 2 3 0 0 40 NW 0 0 1 2 12 16 4 2 2 0 0 39 NNW 0 0 0 2 4 11 9 5 7 0 D 38 Tot 0 0 7 51 186 149 83 44 38 3 0 561 Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data 561 Hours of Missing Data 37 Hours in Period 8760

Joint Frequency Distribution: Hours at Wind Speed and Direction january- December, 2017 Class D Neutral based on lapse rate Elevations: Winds 1Dm Stability 60m Wind Speed Range (mis)

Wind Direction Sector <0.50 0.5-1 1.1- 1.5 1.6-2 2.1-3 3.1-4 4.1-5 5.1-6 6.1-8 8.1-10 >10.00 Total N 0 1 17 29 87 82 80 36 16 4 0 352 NNE 0 1 15 19 92 97 43 12 3 1 0 283 Nt 0 2 15 15 79 67 46 16 2 0 0 242 ENE 1 0 13 16 33 39 22 3 1 0 0 128 E 0 3 9 7 68 34 15 8 2 0 0 146 tSE 0 1 14 22 51 35 13 4 2 0 0 142 SE 0 1 22 35 100 5610 0 0 0 0 224 SSE 0 3 13 23 61 47 25 17 11 1 D 201 S 0 7 11 25 53 53 44 41 62 6 2 304 SSW 0 3 9 13 41 40 29 15 14 3 1 168 SW 0 3 17 23 70 36 27 9 6 1 0 192 WSW 0 4 14 15 40 29 12 11 5 2 0 132 W 0 4 12 12 52 47 19 21 20 1 0 188 WNW 0 2 5 26 74 39 52 17 13 0 0 228 NW 0 3 10 30 73 77 51 22 4 0 0 270 NNW 0 4 11 29 66 98 55 25 14 2 0 304 Tot 1 42 207 339 1040 876 543 257 175 21 3 3504 Hours of Calm 1 Hours of Variable Direction 0 Hours of Valid Data 3505 Hours of Missing Data 37 Hours in Period 8760

Joint Frequency Distribution. Hours at Wind Speed and Direction January- December, 2017 Class E Slightly Stable based on lapse rate Elevations: Winds 1Dm Stability GOrn Wind Speed Range (m/s)

Wind Direction Sector <0.50 0.5-1 1.1- 1.5 1.6-2 2.1-3 3.1-4 4.1-5 5,1-6 6.1-8 8.1-10 >10.00 Total N 0 6 19 26 44 27 6 2 2 1 0 133 NNE 0 11 17 27 49 12 5 0 0 0 0 121 NE 0 9 6 22 26 16 0 0 0 0 0 79 ENE 0 3 12 16 22 3 1 0 0 0 0 57 E 0 11 15 19 33 9 2 1 0 0 0 90 ESE 0 7 9 21 44 21 2 1 0 0 D 105 SE 0 5 45 45 82 35 2 1 0 0 0 215 SSE 0 4 16 38 105 69 27 8 5 0 0 272 S 0 5 8 10 63 111 64 27 9 1 0 298 55W 1 5 12 17 45 44 35 9 3 0 0 171 SW 0 3 18 28 46 34 12 4 0 0 0 145 WSW 0 6 19 19 35 17 9 0 0 0 0 105 W 2 9 7 22 24 36 29 1 0 0 0 130 WNW 0 6 12 11 34 16 7 2 5 0 0 93 NW 0 5 21 25 42 30 5 3 0 0 0 131 NNW 0 6 6 25 59 24 10 9 0 0 0 139 Tot 3 101 242 371 753 504 216 68 24 2 0 2284 Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data 2284 Hours of Missing Data 37 Hours in Period 8760

Joint Frequency Distribution: Hours at Wind Speed and Direction January- December, 2017 Class F Moderately Stable based on lapse rate Elevations: Winds lOm Stability 6Gm Wind Speed Range (m/s)

Wind Direction Sector <0.50 D.S- 1 1.1- 1.5 1.6-2 2.1-3 3.1-4 4.1-5 5.1-6 6.1-8 8.1-iD >10.00 Total N 0 8 12 8 19 0 0 0 0 0 0 47 NNE 0 17 20 15 11 0 0 0 0 0 0 63 NE 2 12 17 13 7 0 0 0 0 0 0 51 ENE 1 10 18 10 3 0 0 0 0 0 0 42 E 1 8 11 8 4 0 0 0 0 0 0 32 6SF 2 13 18 11 7 0 0 0 0 0 0 51 SE 2 7 43 45 20 4 0 0 0 0 0 121 SSE 1 12 17 44 157 22 0 0 0 0 0 253 S 0 10 17 15 78 24 5 0 0 0 0 149 SSW 1 5 15 26 40 10 1 0 0 0 0 98 SW 1 5 18 19 39 9 1 0 0 0 0 93 WSW 2 11 15 8 11 3 0 0 0 0 0 50 W 2 9 9 7 3 0 D 0 0 0 0 30 WNW 1 9 18 8 5 0 0 0 0 0 0 41 NW D 7 29 18 13 1 0 0 0 0 0 68 NNW 0 12 13 23 7 1 0 0 0 0 0 56 Tot 16 156 290 278 424 74 7 0 0 0 0 1245 Hours of Calm 1 Hours of Variable Direction 0 Hours of Valid Data 1246 Hours of Missing Data 37 Hours in Period 8760

Joint Frequency Distribution: Hours at Wind Speed and Direction January- December, 2017 Class 6 Extremely Stable based on lapse rate Elevations: Winds 1Dm Stability 6Dm Wind Speed Range (m/s)

Wind Direction Sector <0,50 0.5- 1 1.1- 1.5 1.6-2 2.1- 3 3.1-4 4.1-5 5.1- 6 6.1-8 8.1- 10 >10.00 Total N 3 4 16 2 5 00 0 0 0 0 30 NNE 0 18 13 6 3 0 0 0 0 0 0 40 NE 4 20 16 1 1 0 0 0 0 0 0 42 ENE 3 7 3 0 0 0 0 0 0 0 0 13 E 4 6 3 0 0 0 0 0 0 0 0 13 ESE 2 10 2 0 0 0 0 0 0 0 0 14 SE 3 11 14 4 2 0 0 0 0 0 0 34 SSE 3 25 30 18 42 10 0 0 0 0 D 128 5 0 17 22 15 23 4 0 0 0 0 0 81 55W 2 10 10 11 6 0 0 0 0 0 0 39 SW 0 12 9 3 7 0 0 0 0 0 0 31 WSW 1 7 1 0 1 0 0 0 0 0 0 10 W 2 13 5 0 0 0 0 0 0 0 0 20 WNW 1 7 17 8 0 0 0 0 0 0 0 33 NW 0 6 11 7 6 0 0 0 0 0 0 30 NNW 1 17 13 6 2 0 0 0 0 0 0 39 Tot 29 190 185 81 98 14 0 0 0 0 0 597 Hours of Calm 4 Hours of Variable Direction .... 0 Hours of Valid Data 601 Hours of Missing Data 37 Hours in Period 8760

Joint Frequency Distribution: Hours at Wind Speed and Direction January- December, 2017 All Stabilities Elevations: Winds 6Dm Stability 6Dm Wind Speed Range (mis)

Wind Direction Sector <050 0.5- 1 1.1- 1.5 1.6-2 2.1-3 3.1-4 4.1-5 5.1-6 6.1-8 8.1-10 >10.00 Total N 0 3 16 15 56 108 110 120 72 20 6 526 NNE 0 3 11 18 67 109 120 108 38 5 1 480 NE 0 3 15 23 58 102 117 118 69 2 0 507 ENE 0 5 4 14 42 81 76 59 26 2 0 309 E 1 3 15 14 43 76 90 46 27 3 0 318 ESE 0 2 8 17 45 65 94 62 21 3 0 317 SE 0 4 17 71 226 189 108 28 2 3 0 648 5SF 0 6 11 29 135 168 136 130 117 20 3 755 5 0 4 9 20 90 93 151 195 289 133 26 1010 SSW 0 1 12 21 57 96 117 147 241 57 9 758 SW 0 3 10 14 75 94 106 129 214 52 6 703 WSW 0 2 13 19 55 51 72 73 75 19 9 388 W 0 3 9 12 SD 54 5S 76 129 43 18 449 WNW 0 3 8 4 38 66 62 92 149 49 31 502 NW 0 1 6 15 38 72 127 146 166 48 5 624 NNW 0 1 4 12 50 61 91 92 86 17 13 427 Tot 1 47 168 318 1125 1485 1632 1621 1721 476 127 8721 Hours of Calm 2 Hours of Variable Direction . 0 Hours of Valid Data 8723 Hours of Missing Data 37 Hour5 in Period 8760

Joint Frequency Distribution: Hours at Wind Speed and Direction January- December, 2017 Class A Extremely Unstable based on lapse rate Elevations: Winds 6Dm Stability 6Dm Wind Speed Range (mis)

Wind Direction 1 1-Sector <050 0.5-1 1.6- 2 2.1-3 3.1-4 4.1-3 5.1- 6 6.1-8 8.1-10 >10.D0 Total 1.5 N 0 D 0 0 0 0 0 0 D 0 0 0 NNE D 0 0 0 D 0 0 0 0 0 D 0 NE D 0 D 0 0 0 0 0 D 0 0 0 ENE 0 0 0 0 0 0 0 2 0 0 0 2 E 0 D D D 0 0 0 1 1 0 0 2 ESE 0 0 0 D 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 4 6 1 0 0 0 11 SSE 0 0 0 0 3 5 8 7 1 0 0 24 S 0 0 0 0 2 2 9 9 6 8 1 37 SSW 0 0 0 0 0 0 5 5 7 6 1 24 SW 0 0 0 0 0 0 1 5 18 10 1 35 WSW 0 0 0 0 0 0 2 4 2 1 0 9 W 0 0 0 0 0 0 0 3 7 1 0 11 WNW 0 0 0 0 0 1 0 1 19 7 4 32 NW 0 0 0 0 0 0 0 2 13 1 0 16 NNW 0 0 0 0 0 0 0 0 1 0 0 1 Tot 0 0 0 0 5 12 31 40 75 34 7 204 Hours of Calm 0 Hours of Variable Direction 0 Hour5 of Valid Data 204 Hours of Missing Data 37 Hours in Period 8750

Joint Frequency Distribution: Hours at Wind Speed and Direction January December, 2017 Class B Moderately Unstable based on lapse rate Elevations: Winds 60m Stability 60m Wind Speed Range (mis)

Wind Direction Sector <0.50 0.5- 1 1.1- 1.5 1 6- 2 2.1-3 3.1-4 4.1-S 5.1-6 6.1-8 8.1-10 >10.00 Total N 0 0 0 0 0 0 0 0 1 0 0 1 NNE 0 0 0 1 0 1 1 1 0 1 0 5 NE 0 0 0 0 0 0 1 0 1 0 0 2 EN E 0 0 0 D 0 0 2 2 0 1 0 5 E 0 D 0 0 0 1 1 2 1 0 0 5 ESE 0 D 0 0 0 2 2 0 0 0 0 4 SE 0 0 0 1 3 14 5 5 0 0 0 28 5SF 0 0 0 0 11 17 10 0 6 1 0 45 5 0 0 0 1 8 7 9 8 7 4 1 4S 55W 0 0 0 1 2 9 9 12 7 9 0 49 SW 0 0 0 0 0 9 8 6 13 6 1 43 WSW 0 0 0 0 0 2 2 5 5 2 1 17 W 0 0 0 0 0 3 2 4 8 4 2 23 WNW 00 0 0 0 5 3 8 7 1 3 27 NW 0 0 0 0 0 3 2 5 5 2 0 17 NNW 0 0 0 0 0 1 0 2 0 1 2 6 Tot 0 0 0 4 24 74 57 60 61 32 10 322 Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data 322 Hours of Mis5ing Data 37 Hours in Period 8760

Joint Frequency Distribution Hours at Wind Speed and Direction January- December, 2017 Class C Slightly Unstable based on lapse rate Elevations: Winds 60m Stability 6Dm Wind Speed Range (mis)

Wind Direction Sector <050 0.5- 1 1 1- 1.5 1.6- 2 2.1-3 3.1-4 4.1-5 5.1-6 6.1- g 8.1- 10 >10 OD Total N 0 D D 06 5 5 2 6 1 1 26 NNE 0 1 0 0 0 7 6 1 1 0 0 16 NE 0 0 1 0 2 4 3 1 5 1 0 17 ENE 0 0 0 1 3 6 1 2 0 0 0 13 t 0 0 1 04 3 1 3 1 0 0 13 ESE 0 0 0 14 2 7 2 0 0 0 16 SE 0 0 0 6 17 18 6 1 0 0 0 48 SSE 0 0 0 018 15 2 5 0 1 0 41 S 0 0 0 1 17 9 7 7 10 11 4 66 SSW 0 0 1 2 g 17 9 12 15 6 0 70 SW 0 0 0 1 11 13 9 11 13 3 0 61 WSW 0 0 0 37 5 7 6 2 0 0 3D W 0 0 0 0 4 5 1 2 9 3 1 25 WNW 00 0 0 4 9 9 4 10 2 3 41 NW 0 0 0 0 4 6 14 11 8 3 1 47 NNW 0 0 0 2 4 1 7 6 4 6 1 31 Tot 0 1 3 17 113 125 94 76 84 37 11 561 HoursofCalm 0 Hours of Variable Direction 0 Hours of Valid Data 561 Hours of Missing Data 37 Hours in Period 8760

Joint Frequency Distribution: Hours at Wind Speed end Direction January- December, 2017 Class D Neutral based on lap5e rate Elevations: Winds 6Dm Stability 60m Wind Speed Range tm/s)

Wind Direction Sector <0.50 0.5- 1 1.1- 1.5 16- 2 21-3 3.1-4 41-S 5.1-6 6.1-8 8.1- 10 >10.00 Total N 0 1 7 12 36 56 62 69 52 17 4 316 NNE 0 0 10 8 43 69 67 59 22 4 1 283 NE 0 1 9 11 26 69 57 52 38 1 0 264 ENE 0 1 3 5 21 38 27 14 19 1 0 129 E 1 2 7 9 25 38 28 7 15 3 0 135 ESE 0 0 4 8 25 29 27 15 12 3 0 123 SE 0 1 4 19 74 67 38 9 1 1 0 214 5Sf 0 2 7 17 44 36 34 36 21 10 2 209 S 0 0 6 11 35 32 24 39 73 66 18 304 55W 0 0 5 9 23 35 30 23 32 16 8 181 SW 0 0 5 8 28 29 45 33 35 19 3 205 WSW 0 0 9 9 23 22 18 25 19 11 8 144 W 0 2 3 6 29 24 24 26 36 25 14 189 WNW 0 1 3 2 23 29 31 44 68 32 16 249 NW 0 1 3 10 26 40 64 55 76 36 3 314 NNW 0 1 3 8 38 40 48 42 48 7 10 245 Tot 1 13 88 152 519 653 624 548 567 252 87 3504 Hours of Calm 1 Hours of Variable Direction 0 Hours of Valid Data 3505 Hours of Missing Data 37 Hours in Period 8760

Joint Frequency Distribution: Hours at Wind Speed and Direction January- December, 2017 Class E Slightly Stable based on lapse rate Elevations: Winds 6Dm Stability 6Dm Wind Speed Range (mis)

Wind Direction Sector <D50 D.5- 1 1.1- 1.5 1.6- 2 2.1-3 3.1-4 4.1-5 5.1-6 6.1-8 8.1- 10 >10.00 Total N D 1 4 1 10 33 31 31 9 2 1 123 NNE D 1 0 6 14 29 28 3D 6 D D 114 NE 0 1 3 7 12 15 28 36 8 D D 110 ENE D 1 1 5 10 12 23 13 3 D D 68 F D D 2 36 21 39 1D 6 D D 87 ESE D D 4 66 14 39 25 5 D D 99 SE D D 2 16 6D 57 4D 9 1 2 D 187 SSE D 2 D S 27 41 44 49 56 7 1 232 S D 2 1 3 12 16 34 53 135 40 2 298 SSW 0 1 5 1 9 13 25 34 115 14 D 217 SW 0 1 2 2 16 17 21 35 60 11 1 166 WSW 0 1 1 1 11 13 25 22 29 2 0 105 W 0 1 2 1 8 13 17 21 65 10 1 139 WNW 0 0 1 1 7 13 13 23 35 7 5 lOS NW 0 0 3 3 2 14 28 38 40 6 1 135 NNW 0 0 0 2 5 9 24 33 22 3 0 98 Tot 0 12 31 63 215 330 459 462 595 104 12 2283 Hours of Calm 1 Hours of Variable Direction 0 Hours of Valid Data 2284 Hours of Missing Data 37 Hours in Period 8760

Joint Frequency Distribution: Hours at Wind Speed and Direction January- December, 2017 Class F Moderately Stable based on lapse rate Elevations Winds 60m Stability 60m Wind Speed Range (m/s)

Wind Direction Sector <0.50 0.5-1 Li- 1.5 1.6- 2 2,1-3 3.1-4 4.1- 5 5.1-6 6.1-8 8.1- 10 >10.00 Total N 0 0 3 0 3 11 12 12 2 0 0 43 NNE 0 1 0 2 6 1 13 13 6 0 0 42 NE 0 0 2 4 10 7 20 21 11 0 0 75 ENE 0 1 0 3 3 13 15 12 1 0 0 48 E 0 1 4 2 4 8 9 20 3 0 0 51 ESE 0 1 0 2 8 8 10 18 4 0 0 51 SE 0 2 4 18 55 20 13 3 0 0 0 115 5SF 0 2 2 3 21 37 30 31 26 1 0 1S3 5 0 1 1 2 7 11 52 57 48 4 0 183 SSW 0 0 0 4 5 8 23 41 47 4 0 132 SW 0 1 1 0 11 8 15 29 61 3 0 129 WSW 0 1 2 2 7 5 ii 9 15 3 0 55 W 0 0 1 4 4 6 10 18 4 0 0 47 WNW 0 1 2 0 1 5 4 9 7 0 0 29 NW 0 0 0 1 3 4 17 30 17 0 0 72 NNW 0 0 0 0 3 3 5 5 5 0 0 21 Tot 0 12 22 47 151 155 259 328 257 15 0 1246 Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data 1246 Hours of Missing Data 37 Hours in Period 8760

Joint Frequency Distribution: Hours at Wind Speed and Direction January- December, 2017 Class 0 Estremely Stable based on lapse rate Elevations: Winds 6Dm Stability 6Dm Wind Speed Range (mis)

Wind Direction Sector <050 D.5- 1 1.1- 1.5 1.6-2 2.1-3 3.1-4 4.1-5 5.1-6 6.1-8 8.t- 10 >10.00 Total N 0 1 2 2 1 3 0 6 2 0 0 17 NNE 0 0 1 14 2 5 4 3 0 0 20 NE 0 1 0 1 8 7 8 8 6 0 0 39 ENE 0 2 0 0 5 12 8 14 3 0 0 44 E 0 0 1 0 4 5 12 3 0 0 0 25 ESE 0 1 0 0 2 10 9 2 0 0 0 24 SE 0 1 7 11 17 90 0 0 0 0 45 SSE 0 0 2 4 11 17 8 2 7 0 0 51 S 0 1 1 2 9 16 16 22 10 0 0 77 SSW 0 0 1 4 10 14 16 20 18 2 0 85 SW 0 1 2 3 9 18 7 10 14 0 0 64 WSW 0 0 1 4 7 4 7 2 3 0 0 28 W 0 0 3 1 5 3 1 2 0 0 0 15 WNW 0 1 2 1 3 4 2 3 3 0 0 19 NW 0 0 0 1 3 5 2 5 7 0 0 23 NNW 0 0 1 00 7 7 4 6 0 0 25 Tot 0 9 24 35 98 136 108 107 82 2 0 601 HoursofCalm 0 Hours of Variable Direction 0 Hours of Valid Data - 601 Hours of Missing Data - 37 Hours in Period 8760

Appendix C Callaway Enerqy Center Offsite Dose Calculation Man ttal

Ameren MISSOURI Callaway Energy Center APA-ZZ-O1 003 OFF-SITE DOSE CALCULATION MANUAL MINOR Revision 022 Page 1 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Contents

1. PURPOSEANDSCOPE 5

2. LIQUID EFFLUENTS 5 2.1. Liquid Effluent Monitors 5 2.1 .1. Continuous Liquid Effluent Monitors 7 2.2. Calculation of Liquid Effluent Monitor Setpoints 7 2.2.1. CALCULATION OF THE ECV SUM 7 2.2.2. CALCULATION OF THE MAXIMUM PERMISSIBLE LIQUID EFFLUENT DISCHARGE FLOW RATE 8 2.2.3. CALCULATION OF LIQUID EFFLUENT MONITOR SETPOINT 9 2.3. Liquid Effluent Concentration Measurements 10 2.4. Dose due to Liquid Effluents 10 2.4.1. THE MAXIMUM EXPOSED INDIVIDUAL 10 2.4.2. CALCULATION OF DOSE FROM LIQUID EFFLUENTS 11 2.4.3.

SUMMARY

, CALCULATION OF DOSE DUE TO LIQUID EFFLUENTS 13 2.5. Liquid Radwaste Treatment System 13 2.6. Liquid Effluents Dose Factors 13

3. GASEOUS EFFLUENTS 13 3.1. Gaseous Effluent Monitors 13 3.1.1. CONTINUOUS RELEASE GASEOUS EFFLUENT MONITORS 14 3.1.2. BATCH RELEASE GASEOUS EFFLUENT MONITORS 15 3.2. Gaseous Effluent Monitor Setpoints 16 3.2.1. TOTAL BODY DOSE RATE SETPOINT CALCULATIONS 16 3.2.2. SKIN DOSE RATE SETPOINT CALCULATION 17 3.3. Calculation of Dose and Dose Rate from Gaseous Effluents 18 3.3.1. DOSE RATE FROM GASEOUS EFFLUENTS 1$

3.3.2. DOSE DUE TO GASEOUS EFFLUENTS 20 3.4. Gaseous Radwaste Treatment System 22 3.5. Gaseous Effluents Dose Factors 23

4. DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES 23 Page 2 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 4.1. Calculation of Dose and Dose Commitment from Uranium Fuel Cycle Sources 23 4.1.1. IDENTIFICATION OF THE MEMBER OF THE PUBLIC 24 4.1.2. TOTAL DOSE TO THE NEAREST RESIDENT 24 4.1.3. TOTAL DOSE TO THE CRITICAL RECEPTOR WITHIN THE SITE BOUNDARY 24

5. RADIOLOGICAL ENVIRONMENTAL MONITORING 27 5.1. Description Of The Radiological Environmental Monitoring Program 27 5.2. Performance Testing Of Environmental Thermoluminescence Dosimeters 27

6. ANNUAL AVERAGE ATMOSPHERIC DISPERSION PARAMETERS 27 6.1. Annual Atmospheric Dispersion Parameters 27 6.1.1. Determination of Dispersion Estimates for Special Receptor Locations 23 6.1 .2. Atmospheric Dispersion Parameters for Farming Areas within the Site Boundary 28 6.2. Annual Meteorological Data Processing 28

7. REPORTING REQUIREMENTS 29 7.1. Annual Radiological Environmental Operating Report 29 7.2. Annual Radioactive Effluent Release Report 29

8. RADIOACTIVE EFFLUENT CONTROLS (REC) 29

9. ADMINISTRATIVE CONTROLS 29 9.1. Major Changes to Liquid and Gaseous Radwaste Treatment Systems 29 9.2. Changes to the Offsite Dose Calculation Manual (ODCM) 30

10. BIBLIOGRAPHY 30 Table 1: Ingestion Dose Commitment Values (A) for Adult Age Group 35 Table 2: Bioaccumulation Factor (Bf) 38 Table 3: Dose Factor for Exposure to a Semi- Infinite Cloud of Noble Gases 39 Table 4: Ground Plane Pathway Dose Factors (R) 40 Table 5: Child Inhalation Pathway Dose Factors (R) 41 Table 6: Child Grass- Cow Milk Pathway Dose Factors (R,) 43 Table 7: Child Grass- Goat Milk Pathway Dose Factors (R,) 45 Page 3 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Table 8: Child Meat Pathway Dose Factors (R) 47 Table 9: Child Vegetation Pathway Dose Factors (R) 49 Table 10: Highest Annual Average Atmospheric Dispersion Parameters 51 Table 11: Application of Atmospheric Dispersion Parameters for Release Permits 52 Table 12: Application of Atmospheric Dispersion Parameters Annual Radioactive Effluent Release Report 53 Table 13: Meteorological Data Selection Hierarchy 54 Appendix A: Methodology for Calculating Dose from 14C in Gaseous Effluents 55 Appendix B: Record of Revisions 68 Page 4 of 75 IN FORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 OFF-SITE DOSE CALCULATION MANUAL

1. Purpose and Scope The Oftsite Dose Calculation Manual (ODCM) describes the methodology and parameters used in the calculation of oft-site doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM also contains the Radioactive Effluent Controls and Radiological Environmental Monitoring Program required by T/S 5.5.4 and FSAR-SP Chapter 16.1 1.4, and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Effluent Release Reports required by T/S 5.6.2 and T/S 5.6.3 Compliance with the Radiological Effluent Controls limits demonstrates compliance with the limits of 10 CFR 20.1301.1.2.3 The ODCM consists of two parts: FSAR-SP Chapter 16.11 which contains the Radiological Effluent Controls (REC5), and APA-ZZ-01003, which contains the methodology and parameters used to implement the RECs.

2. Liquid Effluents 2.1. Liquid Effluent Monitors Gross radioactivity monitors which provide for automatic termination of liquid effluent releases are present on the liquid effluent lines. Flow rate measurement devices are present on the liquid effluent lines and the discharge line (cooling tower blowdown). Setpoinls, precautions, and limitations applicable to the operation of the Callaway Plant liquid effluent monitors are provided in the appropriate Plant Procedures. Setpoint values are calculated to assure that alarm and trip actions occur prior to exceeding ten times the Effluent Concentration Values (ECV) limits in 1 0 CFR Part 20 at the release point to the Unrestricted Area. The calculated alarm and trip action setpoints for the liquid effluent line monitors and flow measuring devices must satisfy the following equation:

cf F+f Eq. 1 Where:

Statements of Consideration, Federal Register, Vol. 56, No. 98, Tuesday, May 21, 1991, Subpart D, page 23374 2

10 CFR 50.36 a (b)

Letter, F. J. Congel to J. F. Schmidt, dated April 23, 1991 Page 5 of 75 INFORMATION USE March, 2017

p j APA-ZZ-01 003 Rev. 022 C is the liquid effluent concentration value (ECV) implementing REC 16.11.1.1 for the site in iCi/ml; c is the setpoint, in (tiCi/mi), of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release. The setpoint, which is inversely related to the volumetric flow of the effluent line and directly related to the volumetric flow of the dilution stream plus the effluent steam, represents a value, which, it exceeded, would result in concentrations exceeding ten times the values of 1 0 CFR Part 20 Appendix B, Table 2, Column 2, in the Unrestricted Area; f is the undiluted waste flow rate as measured at the radiation monitor location, in volume per unit time, but in the same units as F, below; and F is the dilution water flow rate setpoint as measured prior to the release point, in volume per unit time. If F is large compared to f, then F + t F.4 If no dilution is provided then c C.

The radioactive liquid waste stream is diluted by the plant discharge line prior to entry into the Missouri River. Normally, the dilution flow is obtained from the cooling tower blowdown, but should this become unavailable, the plant water treatment facility supplies the necessary dilution flow via a bypass line.

The limiting concentration which corresponds to the liquid radwaste effluent monitor setpoint is to be calculated using methodology from the expression above. Thus, the expression for determining the setpoint of the liquid radwaste effluent line monitor becomes:

(pCi/mi)

Eq. 2 The alarm/trip setpoint calculations are based on the minimum dilution flow rate (corresponding to the dilution flow rate setpoint), the maximum effluent stream flow rate, and the actual isotopic analysis. Due to the possibility of a simultaneous release from more than one release pathway, a portion of the total site release limit is allocated to each pathway. The determination and usage of the allocation factor is discussed in Section 2.2. In the event the alarm/trip selpoint is reached, an evaluation will be performed using actual dilution and effluent flow values and actual isotopic analysis to ensure that REC 16.11.1.1 limits were not exceeded.

NUREG-0133, pages AA-1 thru AA-3 Page 6 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 2.1.1. Continuous Liquid Effluent Monitors The radiation detection monitor associated with continuous liquid effluent releases is:56 Monitor ID. Description BM-RE-52 Steam Generator Blowdown Discharge Monitor The Steam Generator Blowdown discharge is not considered to be radioactive unless radioactivity has been detected by the associated effluent radiation monitor or by laboratory analysis. The sampling frequency, minimum analysis frequency, and type of analysis performed are Per FSAR-SP Table 16.1 1-1.

2.1.2. Radioactive Liquid Batch Release Effluent Monitors The radiation monitor associated with the liquid effluent batch release system is:7 Monitor l.D. Description HB-RE-1 8 Liquid Radwaste Discharge Monitor This effluent stream is normally considered to be radioactive. The sampling frequency, minimum analysis frequency, and the type of analysis performed are per FSAR-SP Table 16.11-1.

2.2. Calculation of Liquid Effluent Monitor Setpoints The dependence of the setpoint, c, on the radionuclide distribution, yields, calibration, and monitor parameters, requires that several variables be considered in setpoint calculations.8 2.2.1. Calculation of the ECV Sum The isotopic concentration of the release(s) being considered must be determined. This is obtained from the analyses required per FSAR-SP Table 16.11 -1, and is used to calculate an ECV sum (ECVSUM):

ECVSUM = ( (c)/(Ecv))

= g, Q,s, t, I Eq. 3 Where:

Cg is the concentration of each measured gamma emitting nuclide observed by gamma-ray spectroscopy of the waste sample; FSAR-SP, Section 11.5.2.2.3.1 FSAR-SP, Section 11.5.2.2.3.4 FSAR-SP, Section 11.5.2.2.3.2 NUREG-0133, pages AA-1 thru AA-3 Page 7 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Ca is the concentration of 237Np, 238Pu, 2391240Pu, 241Pu, 241Am, 242Cm, & 243244Cm, in the quarterly composite sample based on previous composite sample analyses; C is the measured concentrations of 89Sr and 90Sr as determined by analysis of the quarterly composite sample based on previous composite sample analyses; C is the measured concentration of 3H in the waste sample; and C is the measured concentration of 55Fe & 63Ni as determined by analysis of the quarterly composite sample based on previous composite sample analyses.

ECVg, ECV, ECVa, ECV,, and ECV are ten times the limiting concentrations of the appropriate radionuclides from 10 CFR 20, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2x104 liCi/mI total activity.

For the case ECVSUM 1, the monitor tank effluent concentration meets the limits of REC 16.11.1 .1 without dilution and the effluent may be released at any desired flow rate. If ECVSUM> 1 then dilution is required to ensure compliance with the concentration limits of REC 16.11.1.1. If simultaneous releases are occurring or are anticipated, an allocation fraction, N, must be applied so that available dilution flow may be apportioned among simultaneous discharge pathways. The value of N may be any value between 0 and 1 for a particular discharge point, provided that the sum of the allocation fractions for all discharge points must be 1.

2.2.2. Calculation of the Maximum Permissible Liquid Effluent Discharge Flow Rate The maximum permissible liquid effluent discharge flow rate is calculated by:

fmox (F+f)-SF.N+/-(ECVSUM)

Eq. 4 Where:

fmax is the maximum permissible liquid effluent discharge flow rate, (in gallons/minute);

f is the expected undiluted liquid effluent flow rate, in gpm; N is the allocation fraction which apportions dilution flow among simultaneous discharge pathways (see discussion above); and SF is the safety factor; an administrative factor used to compensate for statistical fluctuations and errors of measurements. This factor also provides a margin of safety in the calculation of the maximum liquid effluent discharge flow rate max The value of SF should be 1.

F and ECVSUM are previously defined.

The dilution water supply is furnished with a flow monitor which isolates the liquid effluent discharge if the dilution flow rate falls below its setpoint value.

Page $ of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 In the event that fmax is less than f, then the value of fm< is substituted into the equation for f, and a new fmax value is calculated. This substitution is performed for three iterations in order to calculate the correct value of fmax.

2.2.3. Calculation of Liquid Effluent Monitor Setpoint The liquid effluent monitors are Nal(Tl) based systems and respond primarily to gamma radiation. Accordingly, their setpoint is based on the total concentration of gamma emitting nuclides in the effluent:

c_O.95.[bkg+[(Cg)+/-SFJ]

Eq. 5 Where:

c is the monitor setpoint as previously defined, in pCi/mi; bkg is the monitor background prior to discharge, in l.iCi/ml, adjusted for monitor response:

and 0.95 is a factor for conservatism to ensure the monitor trips prior to exceeding the limits of REC 16.11.1.1 Z Cg and SF are as previously defined.

The monitors background is controlled at an appropriate limit to ensure adequate sensitivity.

Utilizing the methodology of ANSI N13.10-1974, the background must be maintained at a value of less than or equal to 9x106 pCi/mi (relative to 137Cs) in order to detect a change of 4x107 pCi/mI of 137Cs.9 In the event that there is no detectable gamma activity in the effluent or if the value of

{ (ç)÷SF} is less than the background of the monitor, then the monitor setpoint will be set at twice the current background of the monitor.

As previously stated, the monitors response is dependent on the gamma emitting radionuclide distribution of the effluent. Accordingly, a database conversion factor is calculated for each release based upon the results of the gamma spectrometric analysis of the effluent sample and the measured response of the monitor to National Institute of Standards and Technology (N 1ST) traceable calibration sources:

DBCFC =((Cg))+(CMR)X(ECF)

Eq. 6 HPCI 96-005, Calculation of Maximum Background Value for HB-RE-18 Page 9 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 DBCFC is the monitor data base conversion factor which converts count rate into concentration (uiCi/mD; CMR is the calculated response of the radiation monitor to the liquid effluent; ECF is the conversion factor for 137Cs, which converts count rate into concentration (iiCi/ml).

Cg is as previously defined.

The new value of the DBCFC is calculated and entered into the monitor data base prior to each discharge. A more complete discussion of the derivation and calculation of the CMR is given in HPCI 87-10.

2.3. Liquid Effluent Concentration Measurements Liquid batch releases are discharged as a discrete volume and each release is authorized based upon the sample analysis and the dilution flow rate existing in the discharge line at the time of release. To assure representative sampling, each liquid monitor tank is isolated and thoroughly mixed by recirculation of tank contents prior to sample collection. The methods for mixing, sampling, and analyzing each batch are outlined in applicable plant procedures. The allowable release rate limit is calculated for each batch based upon the pre-release analysis, dilution flow-rate, and other procedural conditions, prior to authorization for release. The liquid effluent discharge is monitored prior to entering the dilution discharge line and will automatically be terminated if the pre-selected alarm/trip setpoint is exceeded. Concentrations are determined primarily from the gamma isotopic and 3H analyses of the liquid batch sample.

For 89Sr, 90Sr, 55Fe, 63Ni, 237Np, 238Pu, 2391240Pu, 241Pu, 241Am, 242Cm, & 243244Cm, the measured concentrations from the previous quarterly composite analyses are used until laboratory results become available. Composite samples are collected for each batch release and analyzed in accordance with FSAR-SP Table 16.11 -1 .The dose from liquids discharged as continuous releases is calculated by utilizing the last measured values of samples in accordance with FSAR-SP Table 16.11-1.

2.4. Dose due to Liquid Effluents 2.4.1. The Maximum Exposed Individual The cumulative dose determination considers the dose contributions from the maximum exposed individuals consumption of fish and potable water, as appropriate. Normally, the adult is considered to be the maximum exposed individual.10 The Callaway Plants liquid effluents are discharged to the Missouri River. As there are no potable water intakes within 10 miles of the discharge point,1112 this pathway does not require routine evaluation. Therefore, the dose contribution from fish consumption is expected to account for more than 95% of the total man-rem dose from discharges to the Missouri River.

10 NUREG-0133, Section 4.3 Environmental Report, OLS, Table 2.1-19 12 I FSAR-SA Section 11.2.3.3.4 Page 10 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Dose from recreational activities is expected to contribute the additional 5%, which is considered to be negligible.13 2.4.2. Calculation of Dose from Liquid Effluents The dose contributions for the total time period are calculated at least once each 31 days and a cumulative summation of the total body and individual organ doses is maintained for each calendar quarter. Dose is calculated for all radionuclides identified in liquid effluents released to Unrestricted Areas using the following expression:14 Dr = t1 C11 Eq. 7 Where:

D is the cumulative dose commitment to the total body or any organ, t, from the liquid effluents for the total period r1t, in mrem.

/h t1 is the length of the time period over which C, and F1 are averaged for all liquid releases, in hours. At1 corresponds to the actual duration of the release(s).

C1,1 is the average measured concentration of radionuclide, i, in undiluted liquid effluent during the time period At from any liquid release, in (liCi/mI).

A, is the site- related ingestion dose commitment factor to the total body or any organ t for each identified principal alpha, gamma and beta emitter listed in FSAR-SP Table 16.11-1 in (mrem/hr) per (iCi/ml).

F1 is the near field average dilution factor for C1, during any liquid effluent release:

F, fmox (F+fmoj89.77 Eq. 8 Where:

Fmax is the maximum undiluted effluent flow rate during the release; F is the average dilution flow; and 13 FSAR-SA, Section 11.2.3.4.3 14 NUREG-0133, Section 4.3 Page 11 of 75 INFORMATION USE March, 2017

I APA-ZZ-01 003 Rev. 022 89.77 is site specific applicable factor for the mixing effect of the discharge structure.51617 The term C,1 is the undiluted concentration of radioactive material in liquid waste at the common release point determined in accordance with REC 16.11 .1.1, Table 16.11-1, Radioactive Liquid Waste Sampling and Analysis Program. All dilution factors beyond the sample point(s) are included in the F1 term.

As there are currently no potable water intakes within 10 river miles of the discharge point, the drinking water pathway is not included in dose estimates to the maximally exposed individual.

Should future potable water intakes be constructed within 10 river miles downstream of the discharge point, then this manual will be revised to include this pathway in dose estimates.8 The A1 values given in Table 1 were calculated according to:19 A1 = k0 (U/D + UEBFI ÷ U1BI)DF Eq. 9 Since there are no drinking water pathways, and CEC is a freshwater site, the terms for drinking water consumption (U/D) and invertebrate consumption (U1BI) go to zero and the equation simplifies to:

A1 = k0 UFBFI DF Eq. 10 Where:

k0 is a constant of units conversion, 1 .14x1 5 = (106 pCi/pCi 1 mi/kg / 8760 hr/yr)

UF is the adult fish consumption, 21 kg/yr 20 BF is the bioaccumulation factor for nuclide, i, in fresh water fish, pCi/kg per pCi/L.2122 DF is the dose conversion factor for nuclide, i, for adults for organ, T, in mrem/pCi.

15 NEO-54 16 UOTH 83-58

CAR 200700053- Attachments: Phase 1 final draft 18 FSAR-SP, Section 1 1.2.3.3.4 19 NUREG-0133, Section 4.3.1 20 NUREG-0133, Section 4.3.1, pp. 16 21 UCRL- 50564, Table 6 22 NUREG/CR-4013, pp. 3.17 Page 12 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 2.4.3. Summary, Calculation of Dose Due to Liquid Effluents The dose contribution for the total time period is determined by calculation at least once per 31 days and a cumulative summation of the total body and organ doses is maintained for each calendar quarter. The projected dose contribution from liquid effluents for which radionuclide concentrations are determined by periodic composite and grab sample analysis may be approximated by using the last measured value. Dose contributions are determined for all radionuclides identified in liquid effluents released to Unrestricted Areas.

Nuclides which are not detected in the analyses are reported as less than the Minimum Detectable Activity (MDA) and are not reported as being present at the Lower Limit of Detection (LLD) for that nuclide. The less than values are not used in the dose calculations.

2.5. Liquid Radwaste Treatment System The Liquid Radwaste Treatment System is described in FSAR-SP Chapter 11 .2.

The Operability of the Liquid Radwaste Treatment System ensures this system wifl be available for use when liquids require treatment prior to their release to the environment.

Operability is demonstrated through compliance with REC 16.11.1.1. and 16.11.1.2.

Projected doses due to liquid releases to Unrestricted Areas are determined each 31 days.

The prior 31 day period is used to calculate compliance. This may be modified as appropriate to account for changes in radwaste treatment which may have a significant effect on the projected doses.

2.6. Liquid Effluents Dose Factors The dose conversion factors provided in Table 1 were derived from the appropriate dose conversion factors of Regulatory Guide 1 .109, Table 2.2 and other sources as necessary.2324

3. Gaseous Effluents 3.1. Gaseous Effluent Monitors Noble gas activity monitors are present on the containment building ventilation system, plant unit ventilation system, and radwaste building ventilation system.

The alarm/trip (alarm & trip) setpoint for any gaseous effluent radiation monitor is determined based on the instantaneous noble gas total body and skin dose rate limits of REC 16.11 .2.1, at the Site Boundary location with the highest annual average X.IQ value.

Each gaseous monitor channel is provided with a two level system which provides sequential alarms on increasing radioactivity levels. These setpoints are designated as alert setpoints and alarm/trip setpoints.25 23 HPCI 04-06, rev. 1 24 HPCI 16-04 Page 13 of 75 INFORMATION USE March, 2017

, I APA-ZZ-01 003 Rev. 022 The radiation monitor alarm/trip setpoints for each release point are based on the radioactive noble gases in gaseous effluents. It is not considered practicable to apply instantaneous alarm/trip setpoints to integrating radiation monitors sensitive to radioiodines, radioactive materials in particulate form and radionuclides other than noble gases. The exception is GL RE-202. The only effluent released from the Laundry Decon Facility Dryer Exhaust is in the particulate form. Conservative assumptions may be necessary in establishing setpoints to account for system variables, such as the measurement system efficiency and detection capabilities during normal, anticipated, and unusual operating conditions, variability in release flow and principal radionuclides, and the time lag between alarm/trip action and the final isolation of the radioactive effluent.26 FSAR-SP Table 16.11-6 provides the instrument surveillance requirements, such as calibration, source checks, functional tests, and channel checks.

3.1.7. Continuous Release Gaseous Effluent Monitors The radiation detection monitors associated with continuous gaseous effluent releases are:2728 Monitor l.D. Description GT-RE-21 Unit Vent GH-RE-1 0 Radwaste Building Vent GL-RE-202 Laundry Decon Facility Dryer Exhaust Monitor Each of the above continuously monitors gaseous radioactivity concentrations downstream of the last point of potential influent, and therefore measures effluents and not inplant concentrations.

The unit vent monitor continuously monitors the effluent from the unit vent for gaseous radioactivity. The unit vent, via ventilation exhaust systems, continuously purges various tanks and sumps normally containing low-level radioactive aerated liquids that can potentially generate airborne activity. The exhaust systems which supply air to the unit vent are from the fuel building, auxiliary building, the access control area, the containment purge, and the condenser air discharge.

The unit vent monitor provides alarm functions only, and does not terminate releases from the unit vent.

The Radwaste Building ventilation effluent monitor continuously monitors for gaseous radioactivity in the effluent duct downstream of the exhaust filter and fans. The flow path provides ventilation exhaust for all parts of the building structure and components within the building and provides a discharge path for the waste gas decay tank release line. These 25 FSAR-SP Section 1 1.5.2.1.2 26 NUREG- 0133, section 5.1.1 27 FSAR-SP Section 11.5.2.3.3.1 28 FSAR-SP Section 1 1.5.2.3.3.2 Page 14 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 components represent potential sources for the release of gaseous and air particulate and iodine activities in addition to the drainage sumps, tanks, and equipment purged by the waste processing system.

This monitor will isolate the waste gas decay tank discharge line upon a high gaseous radioactivity alarm.

The Laundry Decon Facility Dryer Exhaust Monitor continuously monitors the effluent of the dryer exhaust for particulate radioactivity during operation of the dryers. This effluent point is designed to release an insignificant quantity of radioactivity. The items to be placed in the dryers are typically washed before drying removing most of the radioactive material. The dryer effluent then passes through a HEPA filter before being sampled and released.

The Laundry Decon Facility Dryer Exhaust Monitor will secure the dryers and exhaust fans and isolate the dryer effluent upon a high radioactivity alarm or for a monitor failure.

The continuous Unit Vent and Radwaste Building Vent gaseous effluent monitor setpoints are established using the methodology described in Section 3.2. Since there are two continuous gaseous effluent release points, a fraction of the total dose rate limit (DRL) will be allocated to each release point. Neglecting the batch releases, the plant Unit Vent monitor has been allocated 0.7 DRL and the Radwaste Building Vent monitor has been allocated 0.3 DRL.

These allocation factors may be changed as required to support plant operational needs, but shall not be allowed to exceed unity (i.e., 1.0). Therefore, a particular monitor reaching the setpoint would not necessarily mean the dose rate limit at the Site Boundary is being exceeded; the alarm only indicates that the specific release point is contributing a greater fraction of the dose rate limit than was allocated to the associated monitor, and will necessitate an evaluation of both systems.

For a loss of all isokinetic sampling and/or all heat tracing for the Unit Vent or Radwaste Building Vent grab samplers, one hour is allowed to restore a sampler to service. If sampling cannot be restored within one hour, all batch releases and ventilation not required for the operation of the plant should be secured. The best available sampling should be maintained during this period and normal sampling returned to service as soon as possible.

3.1.2. Batch Release Gaseous Effluent Monitors The radiation monitors associated with batch release gaseous effluents are:293031 Monitor ID. Descriijtion Gf-RE-22, GT-RE-33 Containment Purge System GH-RE-10 Radwaste Building Vent 29 FSAR-SP Section 11.5.2.3.3.2

° FSAR-SP Section 11.5.2.3.2.3 31 FSAR-SP Section 11.5.23.2.2 Page 15 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 The Containment Purge System continuously monitors the containment purge exhaust duct during purge operations for gaseous radioactivity. The primary purpose of these monitors is to isolate the containment purge system on high gaseous activity via the ESFAS.

The sample points are located outside the containment between the containment isolation dampers and the containment purge filter adsorber unit.

The Radwaste Building Vent monitor was previously described.

A pre-release isotopic analysis is performed for each batch release to determine the identity and quantity of the principal radionuclides. The alarm/trip setpoint(s) is adjusted accordingly to ensure that the limits of REC 16.1 1 .2.1 are not exceeded.

3.2. Gaseous Effluent Monitor Setpoints The alarm/trip setpoint for the Unit Vent and Radwaste Building Vent gaseous effluent monitors is determined based on the more restrictive of the total body dose rate (Eq. 11) and skin dose rate (Eq. 13) as calculated for the Site Boundary. In the event there is no noble gas activity in the sample, then the high alarm setpoint is set to the default value of 2.2E-02 pCi/cc.

This corresponds to 50% of the 500 mrem/yr limit of REC 16.11.2.1.32 Each monitor is allocated only 50% of the limit such that the sum total of the two monitors cannot exceed the limit.

The alarm! trip setpoint for the Laundry Decon Facility Exhaust Monitor is set to less than or equal to 2,000 cpm above equilibrium background. The maximum allowed background is 2,000 cpm as discussed in HPCI 99-05.

3.2.7. Total Body Dose Rate Setpoint Calculations To ensure that the limits of REC 16.11.2.1 are met, the alarm/trip setpoint based on the total body dose rate is calculated according to:

5th DbRtbFSFQ Eq. 11 Where:

Stb is the alarm/trip setpoint based on the total body dose rate (pCi/cc);

Dtb is the REC 16.11 .2.1 dose rate limit of 500 mrem/yr, conservatively interpreted as a continuous release over a one year period; F is the safety factor; a conservative factor used to compensate for statistical fluctuations and errors of measurement. (For example, Fs = 0.5 corresponds to a 100% variation.) Default value is F = 0.1.

32 HPCI 8403, page 9 Page 16 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Fa is the allocation factor which will modify the required dilution factor such that simultaneous gaseous releases may be made without exceeding the limits of REC 1 6.1 1 .2.1.

Rtb is a factor used to convert dose rate to the effluent concentration as measured by the effluent monitor, in (tCi/cc) per (mrem/yr) to the total body, determined according to:

Rb=C [t) (KQ)1 Eq. 12 Where:

C is the reading of a noble gas monitor corresponding to the sample radionuclide concentrations for the release. Concentrations are determined in accordance with FSAR SP Table 16.11-4.The mixture of radionuclides determined via grab sampling of the effluent stream or source is correlated to a calibration factor to determine monitor response. The monitor response is based on concentration, not release rate, and is in units of (pCi/cc);

X/Q is the highest calculated annual average relative concentration for any area at or beyond the Site Boundary in (sec/m3) (Table 10, Table 11, and Table 12);

K1 is the total body dose factor due to gamma emissions for each identified noble gas radionuclide, in (mrem/yr) per (pCi/rn3) (Table 3); and Q is the rate of release of noble gas radionuclide, i, in (pCi/sec).

0 is calculated as the product of the ventilation path flow rate and the measured activity of the effluent stream as determined by sampling.

3.2.2. Skin Dose Rate Setpoint Calculation To ensure that the limits of REC 16.11 .2.1 are met, the alarm/trip setpoint based on the skin dose rate is calculated according to:

55 D5R5F5FQ Eq. 13 Where:

F5 and Fa are as previously defined; S5 is the alarm/trip setpoint based on the skin dose rate; O is the REC 16.11.2.1 dose rate limit of 3000 mrem/yr, conservatively interpreted as a continuous release over a one year period; and R5 is the factor used to convert dose rate to the effluent concentration as measured by the effluent monitor, in (i.iCi/cc) per (mrem/yr) to the skin, determined according to:

Page 17 of 75 IN FORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 R=C÷[(X/Q) (L,÷1.1M,) ]

Eq. 14 Where:

L is the skin dose factor due to beta emissions for each identified noble gas radionuclide, in (mrem/yr) per (pCi/rn3);

7.1 is a factor of units conversion; 1 mrad air dose = 1.1 mrem skin dose; and M1 is the air dose factor due to gamma emissions for each identified noble gas radionuclide, in (mrad/yr) per (iiCilm3).

C, (x/q) and Q are previously defined.

3.3. Calculation of Dose and Dose Rate from Gaseous Effluents 3.3.1. Dose Rate from Gaseous Effluents The following methodology is applicable to the location (Site Boundary or beyond) characterized by the values of the parameter X/Q which results in the maximum total body or skin dose rate. In the event that the analysis indicates a different location for the total body and skin dose limitations, the location selected for consideration is that which minimizes the allowable release values.33 The factors K, L, and M1 relate the radionuclide airborne concentrations to various dose rates, assuming a semi-infinite cloud model.

3.3.1.7. Dose Rate from Noble Gases The release rate limit for noble gases is determined according to the following general relationships Db = [KQ ((7))] 500 mrem/yr Eq. 15 D5 =Z[(L +1.1 M)((X/Q)Q1)]3000mrem/yr Eq. 16 Where:

NUREG-0133. Section 5.1.2

NUREG-0133, Section 5.1.2 Page 18 of 75 IN FORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Q1 is the release rate of noble gas radionuclides, i, in gaseous effluents, from all vent releases in (tCi/sec); and 1.1 is a factor of units conversion factor; 1 mrad air dose = 1 .1 mrem skin dose.

L1, M, K, (X/Q), Db and D5are as previously identified.

3.3.72. Dose Rate from Radionuclides Other than Noble Gases The release rate limit for 1311 and 1331 for 3H, and for all radioactive materials in particulate form with half-lives greater than 8 days is determined according to:35 D0_R1[X/Q1 Q 1500 mrem/yr Eq. 17 Where:

D0 is the dose rate to any critical organ, in (mrem/yr);

R1 is the dose parameter for radionuclides other than noble gases for the inhalation pathway for the child, based on the critical organ, in (mrem/yr) per (tiCi/m3); and Q is the release rate of radionuclides other than noble gases, i, in gaseous effluents, from all vent releases in (j.tCi/sec).

(x/q) is as previously defined.

The dose parameter (R,) includes the internal dosimetry of radionuclide, i, and the receptors breathing rate, which are functions of the receptors age. The child age group has been selected as the limiting age group. All radiodines are assumed to be released in elemental form.36 R values were calculated according to:37 R = K(BR)DFAJ Eq. 18 Where:

K is a factor of units conversion factor: 1x106 pCi/jiCi; BR is the breathing rate from Regulatory Guide 1.109, Table E-5 (m3/yr);

NUREG-0133, Section 5.2.1 NURE&-0133, Section 5.2.1 NuREG-o133, Section 5.2.1.1 Page 19 of 75 IN FORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 DFA1 is the maximum organ inhalation dose factor for the i radionuclide, in (mrem/pCi). The total body is considered as an organ in the selection of DFA.3839 The results of periodic tritium, iodine and particulate samples of the Unit Vent and Radwaste Vent are used to verify the dose rate limit was not exceeded for the period during which the samples or composite samples were obtained.

3.3.2. Dose Due to Gaseous Effluents 3.3.2.7. Air Dose Due to Noble Gases The air dose at the Site Boundary due to noble gases is calculated according to the following methodology :° During any calendar quarter, for gamma radiation:

Dq = 3.17E-08 [M (k,) ,] 5 mrad Eq. 19 During any calendar quarter, for beta radiation:

Db =3.17E-O8 [N,

() ] lOmraU Eq. 20 During any calendar year, for gamma radiation:

Dg _-3.17E-O8[M, () Q] lOmrad Eq. 21 During any calendar year, for beta radiation:

Db =3.17EO8[N, (X/Q) Q,

] 2Omrad Eq. 22 Where:

°g is the air dose in mrad, from gamma radiation due to noble gases released in gaseous effluent;

°b is the air dose in mrad, from beta radiation due to noble gases released in gaseous effluents; Regulatory Guide 1.109, Appendix E, Table [-9 ZZ-48 40 NUREG-0133, Section 5.3.1 Page 20 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 N1 is the air dose factor due to beta emissions for each identified noble gas radionuclide, i, in (mrad/yr) per (tCi/m3);

0 is the releases of noble gas radionuclides, I, in gaseous effluents, for all gaseous releases in QiCi). Releases are cumulative over the calendar quarter or year as appropriate. 0 is calculated as the product of the ventilation flow rate and the measured activity of the effluent stream as determined by sampling; and 3.17x108 is the inverse of the number of seconds per year.

X/Q & M1 are as previously defined.

3.3.2.2. Dose Due to Radionuclides Other than Noble Gases The dose to a Member of the Public from 1311 and 1331, for 3H, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the Site Boundary, is calculated according to the following expressions:

During any calendar quarter:

0,, 7.5 mrem Eq. 23 During any calendar year:

D,,f5mrem Eq. 24 For each pathway, j, (i.e., for inhalation, ground plane, meat, cow- milk, goat- milk, and vegetation) D1, is calculated according to the expression:

D, 3.; 7E 8R,,1 [w,Q,1 Eq. 25 Where:

is the dose in mrem, to a Member of the Public from radionuclides other than noble gases, from pathway j, received by organ I (including total body);

R is the dose factor for each identified radionuclide, i, in m2 (mrem/yr) per (l.tCi/sec) or (mrem/yr) per (pCi/rn3) as appropriate, for the pathway1, and exposed organ I, appropriate to the age group of the critical Member of the Public receptor; W1 is the X/Q for the inhalation and tritium pathways, in sec/m3 and is the D/Q for the food and ground plane pathways, in meters2.

Page 21 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 D/Q is the average relative deposition of the effluent at or beyond the Site Boundary, considering depletion of the plume during transport; Q is the release of radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases, i, in gaseous effluents, for all gaseous releases in .tCi. Releases are cumulative over the calendar quarter or year as appropriate. 0 is calculated as the product of ventilation flow rate and the measured activity of the effluent stream as determined by sampling; and 3.17x7O8 is the inverse of the number of seconds per year.

X/Q is as previously defined. Refer to Table 10, Table 11, and Table 12 for applicability; Although the annual average relative concentrationX/Q and the average relative deposition rate D/Q are generally considered to be at the approximate receptor location in lieu of the Site Boundary for these calculations, it is acceptable to consider the ingestion, inhalation, and ground plane pathways to coexist at the location of the nearest residence with the highest value otX/Q *41 The Total Body dose from ground plane deposition is added to the dose for each individual organ.42 3.4. Gaseous Radwaste Treatment System The gaseous radwaste treatment system and the ventilation exhaust system are available for use whenever gaseous effluents require treatment prior to being released to the environment.

The gaseous radwaste treatment system is designed to allow for the retention of all gaseous fission products to be discharged from the reactor coolant system. The retention system consists of eight (8) waste gas decay tanks. Normally, waste gases will be retained for at least 60 days prior to discharge. When practicable, waste gas decay tanks are discharged outside the growing season or at night such that 14C released from the waste gas system will not be incorporated into the ingestion pathways and will result in a lower dose to the Member of the Public. For this purpose, the growing season is defined as April 1 through November 1 These systems will provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept ALARA.

The Operability of the gaseous radwaste treatment system ensures this system will be available for use when gases requite treatment prior to their release to the environment.

Operability is demonstrated through compliance with REC 16.11 .2.1, 16.1 1 .2.2, and 1 6.1 1.2.3.

Projected doses (gamma air, beta air, and organ dose) due to gaseous effluents at or beyond the Site Boundary are determined each 31 days. The prior 31 day period is used to calculate 41 NuREG-0133, Section 5.3.1 42 Regulatory Guide 1.109, Appendix C, Section 1 Hammer, Gregory, R., Climate of Missouri, monograph available from the National Climatic Data Center (NCDC) of the National Oceanic and Atmospheric Administration (NOAA), January, 2006.

Page 22 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 compliance. This may be modified as appropriate to account for changes in radwaste treatment which may have a significant effect on the projected doses.

3.5. Gaseous Effluents Dose Factors The dose conversion factors were derived from the appropriate dose conversion factors in Regulatory Guide 1 .109 and other sources as necessary.4445 Particulate nuclides with a half-life of less than 8 days are not considered.46 90Y, 140La, and 144Pr are included because the parent half-life is greater than 8 days, and equilibrium is assumed.

4. Dose and Dose Commitment from Uranium Fuel Cycle Sources 4.1. Calculation of Dose and Dose Commitment from Uranium Fuel Cycle Sources The annual dose or dose commitment to a Member of the Public for Uranium Fuel Cycle Sources is determined as:

• Dose to the total body and internal organs due to gamma ray exposure from submersion in a cloud of radioactive noble gases, ground plane exposure, and direct radiation from the Unit, onsite storage of low-level radioactive waste, and outside storage tanks;

• Dose to skin due to beta radiation from submersion in a cloud of radioactive noble gases, and ground plane exposure;

• Thyroid dose due to inhalation and ingestion of radioiodines; and

• Organ dose due to inhalation and ingestion of radioactive material.

It is assumed that total body dose from sources of gamma radiation irradiates internal body organs at the same numerical rate.47 The dose from gaseous effluents is considered to be the summation of the dose at the individuals residence and the dose to the individual from activities within the Site Boundary.

Since the doses via liquid releases are very conservatively evaluated, there is reasonable assurance that no real individual will receive a significant dose from radioactive liquid release pathways. Therefore, only doses to individuals via airborne pathways and doses resulting from direct radiation are considered in determining compliance to 40 CFR 190.48 There are no other Uranium Fuel Cycle Sources within 8 km of the Callaway Plant.

ZZ-78

ZZ-250 46 Inspection Report 50-483/92002 (DRSS)

NUREG-0543,Section III, page 8 48 NUREG-0543,Section IV, page 9 Page 23 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 4.1.1. Identification of the Member of the Public The Member of the Public is considered to be a real individual, including all persons not occupationally associated with the Callaway Plant, but who may use portions of the plant site for recreational or other purposes not associated with the plant.49 Accordingly, it is necessary to characterize this individual with respect to his utilization of areas both within and at or beyond the Site Boundary and identify, as far as possible, major assumptions which could be reevaluated if necessary to demonstrate continued compliance with 40 CFR 1 90 through the use of more realistic assumptions.5051 The evaluation of Total Dose from the Uranium Fuel Cycle should consider the dose to two Critical Receptors: (a) The Nearest Resident, and (b) The Critical Receptor within the Site Boundary.

4.7.2. Total Dose to the Nearest Resident The dose to the Nearest Resident is due to plume exposure from noble gases, ground plane exposure, and inhalation and ingestion pathways. It is conservatively assumed that each ingestion pathway (meat, milk, and vegetation) exists at the location of the Nearest Resident.

It is assumed that direct radiation dose from operation of the Unit and storage of radioactive material, and dose from gaseous effluents due to activities within the Site Boundary is negligible for the Nearest Resident. The total Dose from the Uranium Fuel Cycle to the Nearest Resident is calculated using the methodology discussed in Section 3, using concurrent meteorological data for the location of the Nearest Resident with the highest value of X/Q.

The location of the Nearest Resident in each meteorological sector is determined from the Annual Land Use Census conducted in accordance with the Requirements of REC 16.11.4.2.

4.1.3. Total Dose to the Critical Receptor within the Site Boundary The Union Electric Company has entered into an agreement with the State of Missouri Department of Conservation for management of the residual lands surrounding the Callaway Plant, including some areas within the Site Boundary. Under the terms of this agreement, certain areas have been opened to the public for low intensity recreational uses (hunting, hiking, sightseeing, etc.) but recreational use is excluded in an area immediately surrounding the plant site (refer to Figure 4.1). Much of the residual lands within the Site Boundary are leased to area farmers by the Department of Conservation to provide income to support management and development costs. Activities conducted under these leases are primarily

NuREG-0133, Section 3.8 50 NuREG-o543,Section IV, page 9 51 NUREG-0543, section III, page 6 Page 24 of 75 IN FORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 comprised of farming (animal teed), grazing, and forestry. Crops for human consumption are specifically prohibited by the lease.525354 Based on the utilization of areas within the Site Boundary, it is reasonable to assume that the critical receptor within the Site Boundary is a farmer, and that his dose from activities within the Site Boundary is due to exposure incurred while conducting his farming activities. The previous tenant estimated that he spent approximately 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> per year working the farm plots of the Reform Conservation Area.55 Any reevaluation of assumptions should consider only real receptors and real pathways using realistic assumptions, and should include a reevaluation of the occupancy period at the locations of real exposure (e.g. a real individual would not simultaneously exist at each point of maximum exposure).

4.7.3.7. Total Dose to the Farmer from Gaseous Effluents The Total Dose to the farmer from gaseous effluents is calculated for the adult age group using the methodology discussed in Section 3, utilizing historical meteorological data from Table 10 for activities within the Site Boundary. The Reform Conservation Area farm plots are leased to several different farmers therefore there is no dose calculation for the farmers residence.

It is assumed that food ingestion pathways do not exist within the Site Boundary, therefore the gaseous effluents dose within the Site Boundary is due to plume exposure from Noble Gases and the ground plane and inhalation pathways.

4.1.3.1.1. Direct Radiation Dose The direct radiation dose to the Member of Public due to activities within the Site Boundary is insignificant.5657 52 Environmental Report, OLS, Section 2.1.2.3 Environmental Report, OLS, Section 2.1.3.3.4 Management Agreement for the Public Use of Lands, Exhibit A.

Private communication, H.C. Lindeman & B.F.Holderness, August 6, 1986 56 HPCI 12-06 HPCI 15-05 Page 25 of 75 INFORMATION USE March, 2017

c) U r Ll l 0 DO 0c.J C\1 I -

3_ 0)

<I un:

0 U

z z

Ln 4-C

.0 a) bC CD

APA-ZZ-01 003 Rev. 022

5. Radiological Environmental Monitoring 5.1. Description Of The Radiological Environmental Monitoring Program The Radiological Environmental Monitoring Program is intended to provide background data for pre- operation and to supplement the radiological effluent release monitoring program during plant operation. Radiation exposure to the public from the various specific pathways and direct radiation is evaluated by this program.

Some deviations from the sampling frequency may be necessary due to seasonal unavailability, hazardous conditions, or other legitimate reasons. Efforts are made to obtain all required samples within the required time frame. Any deviation(s) in sampling frequency or location is documented in the Annual Radiological Environmental Operating Report.

REMP sampling locations that use meteorological sectors and or distance from the plant site were verified as described in HPCI 99-01.

Sampling, reporting, and analytical requirements are given in FSAR-SP Tables 16.11-7, 16.11-8, and 16.11-9.

Airborne, waterborne, direct radiation, and ingestion samples collected under the monitoring program are analyzed by an independent, third-party laboratory. With the exception of direct radiation, the laboratory is required to participate in an Interlaboratory Analyses Program per Reg. Guide 4.15.58 The laboratory participates in an Interlaboratory crosscheck program administered by Environmental Resources Associates (ERA), Mixed Analyte Performance Evaluation Program (MAPEP), or equivalent program. This participation includes all of the determinations (sample medium radionuclide combination) that are both offered by ERA and/or MAPEP and are also included in the environmental monitoring program.

5.2. Performance Testing Of Environmental Thermoluminescence Dosimeters Dosimeters used for monitoring of direct radiation dose in the Radiological Environmental Monitoring Program are tested for accuracy and precision to demonstrate compliance with the applicable portions of Regulatory Guide 4.13.

6. Annual Average Atmospheric Dispersion Parameters 6.1. Annual Atmospheric Dispersion Parameters The dispersion values presented in Table 1 0 were determined through the analysis of five years of on-site meteorological data.59 The straight-line Gaussian dispersion model XOQDOQ6° was used for determination of the long-term atmospheric dispersion parameters.

A more detailed discussion of the methodology and input data utilized to calculate these parameters can be found in HPCI 1503.

Regulatory Guide 4.15, rev. 1, section 6.3.2 HPCI 1503 60 NUREG/CR2919 Page 27 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 6.1.1. Determination of Dispersion Estimates for Special Receptor Locations XOQDOQ is utilized to obtain dispersion paramters for 22 standard distances. Dispersion parameters at the Site Boundary and at special receptor locations are estimated by logarithmic interpolation according to:61 XX1 (U/U1)8 Eq. 26 Where:

(X2/X1)

B In (d2/d1)

Eq. 27 X1, X2 are the atmospheric dispersion parameters at distance d1and d2, respectively, from the source. The distances d1 and d2 are selected such that they satisfy the relationship d1<d<d2.

6.1.2. Atmospheric Dispersion Parameters for Farming Areas within the Site Boundary The dispersion parameters for farming areas within the Site Boundary are intended for a narrow scope application; that of calculating the dose to the current farmer62 from gaseous effluents while he conducts farming activities within the Site Boundary.

For the purpose of these calculations, it was assumed that all of the farmers time, approximately 1 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> per year, is spent on croplands of the Reform Conservation Area, including plots within the Site Boundary, and that his time is divided among the plots proportional to the acreage of each plot. Fractional acreage/time- weighted dispersion parameters were calculated for each plot as described in HPCI 1502. The weighted dispersion parameters for each plot were summed (according to type) in order to produce a composite value of the dispersion parameters which are presented in Table 10. These dispersion parameters therefore represent the distributed activities of the farmer within the Site Boundary and his estimated occupancy period.

6.2. Annual Meteorological Data Processing The annual atmospheric dispersion parameters utilized in the calculation of doses for demonstration of compliance with the numerical dose objectives of 10 CFR 50, Appendix I, are determined using XOQDOQ.63 Multiple sensors are utilized to ensure 90% valid data recovery for the wind speed, wind direction, and ambient air temperature parameters as required by Regulatory Guide 1.23. The selection hierarchy is presented in Table 13.

The input parameters to XOQDOQ are documented in HPCI 1503.

61 FSAR-SA 2.3.5.2.1.2 62 The farming plots are leased by the Missouri Department of Conservation to multiple farmers through a bidding process. This represents a composite of those persons farming the plots within the Site Boundary.

NUREG/CR-2919 Page 28 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 A quality check of the meteorological data is performed prior to processing to ensure the validity of the calculated dispersion parameters.

7. Reporting Requirements 7.1. Annual Radiological Environmental Operating Report The reporting requirements for the Annual Radiological Environmental Operating Report (AREOR) have been relocated to FSAR-SP 16.11 .5.1.

7.2. Annual Radioactive Effluent Release Report The reporting requirements for the Annual Radioactive Effluent Release Report (ARERR) have been relocated to FSAR-SP 16.11 .5.2. The application of atmospheric dispersion parameters in the ARERR is presented in Table 12.

8. Radioactive Effluent Controls (REC)

The Radioactive Effluent Controls were relocated to FSAR-SP Chapter 16.11 ,Offsite Dose Calculation Manual Radioactive Effluent Controls. The former ODCM REC numbers appear on each of the RECs in FSAR-SP Chapter 16.11,and may be used as a cross-reference between the previous and the current numbering system if necessary.

9. Administrative Controls 9.1. Major Changes to Liquid and Gaseous Radwaste Treatment Systems A summary of Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous) must be reported to the Commission in the Annual Radioactive Effluent Release Report (ARERR) for the period in which the evaluation was reviewed by the On-Site Review Committee (ORC). On site documentation must contain:

• A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

• Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

• A detailed description of the equipment, components and process involved and the interfaces with other plant systems;

• An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the License application and amendments thereto;

• An evaluation of the change, which shows the expected maximum exposures to a Member of the Public in the Unrestricted Area and to the general population that differ from those previously estimated in the License application and amendments thereto; Page 29 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022

• A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releases for the period prior to when the changes are to be made;

• An estimate of the exposure to plant operating personnel as a result of the change; and

• Documentation of the fact that the change was reviewed and found acceptable by the ORC.

Changes to the Radwaste Treatment Systems shall become effective upon review and approval by the ORC.

9.2. Changes to the Offsite Dose Calculation Manual (ODCM)

All changes to the ODCM shall be performed pursuant to I/S AC 5.5.1 Review for each revision of the ODCM must include the Radiation Protection Department.

10. Bibliography ANSI Ni 3.10-i 974, Specification & Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents. (1974)

CAR 200700053 Missouri River Low Flow Trend for 2006, Attachments: Phase 1 Final Draft CDP-ZZ-00200, Appendix B, Primary Plant Systems Tables, rev. 36. November, 2015.

Certificate of Compliance No. 1040, Appendix A, Technical Specifications for the HI-STORM UMAX Canister Storage System. April, 2015.

EGG-PHY-9703, Technical Evaluation Report for the evaluation of ODCM Revision 0 (May, 1990) Callaway Plant, Unit 1, transmitted via letter, Samuel J. Collins (USNRC) to D. F.

Schnell (UE), dated July 12, 1996.

EPRI YR-i 021106, Estimation of 14C in Nuclear Power Plant Effluents, December, 2010 Generic Letter 89-01, Guidance for the Implementation of Programmatic Controls for RETS in the Administrative Controls Section of Technical Specifications and the Relocation of Procedural Details of Current REIS to the Offsite Dose Calculation Manual or Process Control Program, US Nuclear Regulatory Commission. (1989)

Hammer, Gregory, R., Climate of Missouri, monograph available from the National Climatic Data Center (NCDC) of the National Oceanic and Atmospheric Administration (NOAA),

January, 2006 HPCI 8403, Setpoints and Associated Bases for Process and Effluent Radioactivity Monitors (SP System). June, 1984.

Page 30 of 75 IN FORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 HPCI 8710, Methodology for Calculating the Response of Gross Nal(Tl) Monitors to Liquid Effluent Streams, rev. 1, April2005.

HPCI 8902, Calculation of ODCM Dose Commitment Factors, rev. 0. September, 1989.

HPCI 9605, Calculation of Maximum Background Value for HB-RE-1 8, rev.0. September, 1996 HPCI 9901, Documentation of REMP Procedure Changes. Rev.0. January, 2000.

HPCI 9905, Calculation of Setpoint for GL-RE-202, rev.0. April, 1999.

HPCI 0406 Calculation of Liquid Effluent Dose Commitment Factors (A) for the Adult Age Group, rev. 1. November, 2004.

HPCI 0509, Radiological Environmental Monitoring Program (REMP) Calculation of Direct Dose from RAM Storage at Stores II, rev. 0. April, 2005.

HPCI 0510, Radiological Environmental Monitoring Program (REMP) Calculation of Direct Dose from RAM Storage in the Radwaste Yard, rev. 0. April, 2005.

HPC( 0601, Equipment Hatch Platform and Missile Shield Modification Direct,Dose Calculation to the Member of the Public, rev. 0. January2006.

HPCI 1003, Evaluation of the 2010 Land Use Census, rev. 0. December, 2010.

HPCI 1102, Dose to the Member of the Public from the Release of 14C in Gaseous Effluents for 2010, rev.0. July, 2011.

HPCI 1 206, Evaluation of Direct Radiation Dose to the Member of the Public Due to Activities within the site Boundary, rev. 0. August, 2012.

HPCI 1 502, Atmospheric Dispersion Parameters for Activities Inside the Site Boundary, rev.

0. February, 2015.

HPCI 1 503, Calculation of Long- Term Meteorological Dispersion Parameters, rev. 1. April, 2015 HPCI 1 504, Evaluation of the 2014 Annual Land Use Census, rev. 1. March, 2015 HPCI 1 505, Evaluation of Direct Radiation Dose to the Member of the Public from the Independent Spent Fuel Storage Facility, rev. 1. July, 2015.

HPCI 1508, Evaluation of the 2015 Land Use Census, rev.0. March, 2016.

HPCI 1 604, Calculation of 126Sb Ingestion Dose Commitment Factors (A1), rev. 0. April, 2016.

IAEA Technical Reports Series no. 421, Management of Waste Containing Tritium and Carbon- 14, 2004 Page 31 of 75 INFORMATION USE March, 2017

APA-ZZ-0i 003 Rev. 022 Internal USNRC memo, F.]. Congel to V. L. Miller, et al, dated April 17, 1992.

Kunz, C., Carbon-14 Discharge at Three Light- Water Reactors, Health Physics, vol. 49, pages 25-35, 1985 Letter, F.]. Congel to]. F. Schmidt, dated April 23, 1 992.

Letter, F. ]. Congel to J. F. Schmidt, dated December 9, 1991.

Letter, F. ]. Congel to]. F. Schmidt, dated ]une 8, 1993.

Letter, F. ]. Congel to]. F. Schmidt, dated September 14, 1992.

Management Agreement for the Public Use of Lands, Union Electric Company and the State of Missouri Department of Conservation, ]anuary 15, 2009.

Memo, F.]. Congel, Eigth Set of Questions and Answers on 10 CFR Part 20, May 26, 1994.

NCRP Report 81, Carbon-i 4 in the Environment, ]anuary 1985 Neeb, Karl- Heinz, The Radiochemistry of Nuclear Power Plants with Light Water Reactors, Walter de Gruyter, Berlin, 1997 NEO-54, memo, D. W. Capone to S. F. Miltenberger, dated ]anuary 5, 1983; Union Electric Company correspondence.

NUREG-0017, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors PWR-GALE Code, April, 1985 NUREG-0133, Preparation of Radiological Effluent Technical Specification for Nuclear Power Plants, U.S. Nuclear Regulatory Commission. (1978)

NUREG-0543, Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190), U.S. Nuclear Regulatory Commission. (1980)

NUREG-1 301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, Generic Letter 89-01, Supplement No. 1, April, 1991 NUREG/CR-2919, XOQDOQ, Computer Program For the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations, U.S. Nuclear Regulatory Commission. (1982)

NUREG/CR-6204, Questions and Answers Based on Revised 10 CFR 20, May, 1994 Regulatory Guide 1 .1 09, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, U. S. Nuclear Regulatory Commission. (1977)

Page 32 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Regulatory Guide 1 .1 11 Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, U. S.

Nuclear Regulatory Commission. (1977)

Regulatory Guide 1 .21, Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste, (Revision 2), U. S. Nuclear Regulatory Commission.

(2009)

Regulatory Guide 4.13, Performance, Testing, and procedural specifications for Thermoluminescence Dosimetry: Environmental Applications (Revision 1), U. S. Nuclear Regulatory Commission. (1977)

Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Normal Operations) Effluent Streams and the Environment (Revision 1), U. S. Nuclear Regulatory Commission (1979)

Statements of Consideration, Federal Register, Vol. 56, No. 98, Tuesday, May 21, 1991, Subpart D, page 23374.

Title 10, Energy, Chapter 1, Code of Federal Regulations, Part 20; U.S. Government Printing Office, Washington, D.C. 20402.

Title 10, Energy, Chapter 1, Code of Federal Regulations, Part 72, Subpart F; U.S.

Government Printing Office, Washington, D.C. 20402.

Title 10, Energy, Chapter 1, Code of Federal Regulations, Part 50, Appendix I; U.S.

Government Printing Office, Washington, D.C. 20402.

Title 40, Protection of Environment, Chapter 1, Code ol Federal Regulations, Part 190; U.S.

Government Print Office, Washington, D.C. 20402.

Union Electric Company Callaway Plant Environmental Report, Operating License Stage Union Electric Company Callaway Plant, Unit 1, Final Safety Analysis Report- Standard Plant UOTH 83-58, Documentation of ODCM Dose Factors and Parameters. (1983)

USNRC Inspection Report 50-483/92002(DRSS), Section 5, page 5.

Westinghouse Calculation Note CN-TA-02-1 35, Callaway (SCP) RSG IGOR/RETRAN Base Deck, May 16, 2003 ZZ-250, Rev. 0, ODCM Gaseous Pathway Dose Factors for Child Age Group and Ground Plane Dose Factors. (1992)

ZZ-48, Calculation of Inhalation and Ingestion Dose Commitment Factors for the Adult and Child. (1988)

ZZ-57, Dose Factors for Eu-i 54. (1989)

Page 33 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 ZZ-78, Rev. 2, ODCM Gaseous Pathway Dose Factors for Adult Age Group. (1992)

Page 34 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Table 1: Ingestion Dose Commitment Values (Aft) for Adult Age Group (mrem/hr) per (iiCi/mI)

. . Total Nuclide Bone Liver Thyroid Kidney Lung GI-LLI Body 3H O.OOE+OO 2.26E-O1 2.26E-O1 2.26E-O1 2.26E-O1 2.26E-O1 2.26E-O1 7Be 131E-02 2.98E-02 1.45E-02 O.OOE+OO 3.15E-02 O.OOE+OO S.17E+OO 24Na 4.07E÷02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 51Cr O.OOE+OO O.OOF÷OO 1.27E+OO 761EO1 2.81E-O1 1.69E+OO 3.20E+02 54Mn Q.OOE+OO 4.38E+03 8.35E+02 O.OOE÷OO 1.30L+03 O.OOE÷OO 1.34E+04 56Mn O.OOE+QO 11QE÷32 1,95E+O1 O.OOE+OO 1.40E÷02 O.OOE+QO 3.S1E+03 S5F 6.58E+02 4.55E+02 1.06E+02 O,00E÷OO OOOE+OO 2.54E+02 2.61E+02 59Fe 1.04E+03 2.44E+03 9.36E+02 O.OOE+OO O.OOE+OO 6.82E+02 8.14E+03 57Co O.OQE+OO 209E+O1 3.48E÷O1 Q.OOE+OO O.OOE-i-OO O.OOE+OO 5.31E+02 58Co O.OOE+OO 8.92E+O1 2.OOE+02 O.OOE÷OO O.OOE÷OO O.OOE+OO 1.81E+03 60Co O.OQE+OO 2.56E÷02 5.65E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.81E+03 63Ni 3.1E+04 2.16E+03 1.04E+03 O.OOE+OO O.OOE+OO O.OOE+OO 4.50E+02 65N 1.26E÷02 1.64E+O1 7.49E÷OO O.OOE+OO O.OOE÷OO O.OOE+OO 4.17E+02 Cu O.OOE+OO 9.97E+OO 4.68E+OO O.OOE÷OO 2.51E+O1 O.OOE+OO 8.SQE+02 65Zn 2.32E+04 7.37E+04 3.33E+04 OOOE+OO 4.93E+04 O.OOE+OO 4.64E+04 69Zn 4.93E+O1 9.43E+O1 6.56E+QO O.OOE+OO 6.13E+O1 O.OOE+OO 1.42E+O1 82Br O.OOE+OO O.OOE+OO 2.27E+03 O.OOE÷OO O.OOE+OO O.OOE+OO 2.60E+03 83Br O.OOE+OO OQQE+OO 4.04E+O1 O.OOE+OO O.QOE+OO O.OOE+OO 5.82E÷O1 4Br OOOE+OO OOOE+OO 5.24E+O1 O.OOE+OO O.OOE+OO O.OOE+OO 41E-04 as8 OOOE+OO O.OOE+OO 2.15E+DO O.OOE+OO O.OQE+OQ QQQE÷OO 1.O1E-15 86Rb O.OOE÷OO 1.OE+05 4.71E+04 O.ODE÷OO O.OOE+QO O.OOE+OO 1.99E+04 88Rb OOOE÷OO 2.90E+02 1.54E+02 O.OOE÷OO OOOE+OO O.OOE+OO 4.OOE-09 Rb O.OOE+OO 1.92E+02 1.35E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.12E-11 5r 2.21E÷04 O,00E÷OO 6.35E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.55E÷03 90Sr 5.44E+05 O.OOE+OO 1,34E÷05 O.OOE+OO O.OOE+OO O.OOE+OO t57E+04 915r 4.07E+02 O.OOE+OO 1.64E+O1 O.OOE+OO OOOE÷OO O.OOE+OO 1.94E÷03 925r 1.54E+02 O.OOE+OO 6.68E+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.06E+03 90Y 5.?6E-O1 O.OOE+OO 1.54E-02 O.OOE+OO O.OOE+OO O.OOE+OO 61OE÷03 9lmy 5.44E-03 Q.OO[÷OO 2.11E-04 O.OOE+OO O.OOE+OO O.OOE+OO 1.60E-02 Y 8.44E÷OO O.OOE÷OO 2.26E-O1 O.OOE÷OO O.OOE÷OO O.OOE+OO 4.64E+03 92, 5.06E-02 O.OOE+OO 1.48E-03 O.OOE+OO OOOE+OO O.OOE+OO 886E+02 93Y 160E-O1 O.OOE+OO 4.43E-03 O.OOE÷OO O.OOE+OO O.OOE+OO 5.09E+03 95Zr 2.40E-O1 7.70E-02 5.21E-02 O.OOE+OO 1.21E-O1 OOOE+OO 2.44E+02 97Zr 1,33E-02 2.68E-03 1.22E-03 O.OOE+OO 4.04E-03 O.OOE+OO 8.30E÷02 95Nb 4.47E+02 2.48E+02 1.34E+02 O.OOE+OO 2.46E+02 O.OOE+OO 1.51E+O6 99Mo O.OOE+OO 103E+02 1.96E+O1 O.OOE+OO 2,34E+02 O.OOE+OO 2.39E+02 99Tc 8.87E-03 2.51E-02 3.19E-O1 O.OOE+OO 3.81E-O1 123E-02 1.48E+O1 Page 35 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Table 1: Ingestion Dose Commitment Values (A1) for Adult Age Group (mrem/hr) per (liCi/mi)

. . Total -

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI Bod

°Ic 9.12E-03 1.31E-02 1.29E-O1 O.OOE+OO 2.37E-O1 6.72E-03 3.95E-14 113Ru 4.43E+OO O.OOE+OO 1.91E+OO O.OOE+GO 1.69E+U1 O.OOE+OO 5.17E+02 1DSR 3.69E-O1 O.OOE+OO 1.46E-O1 O.OOE+OO 4.76E+OO O.OOE÷OO 2.26E+02

°6Ru 6.58E+O1 O.OOE+OO $.33E+OO O.OOE+OO 1.27E+02 O.OOE+OO 4.26E÷03 09cd O.OOE+OO 5.55E+02 t94E÷O1 O.OOE+OO 5.31E+02 O.OOE+OO 5.60E+03 liomAg 8.$5E-O1 8.18E-O1 4.86E-O1 O.OOE+OO 1.61E+OO O.OOE+OO 3.34E+02 13Sn 5.67E÷04 1.61E+03 3.26E÷03 9.19E+02 O.OOE+OO O.OOE+OO 169E+05 225b 5.48E-O1 1.12E-02 1.66E-O1 7.73E-03 O.OOE+OO 2.94E-O1 O.OOE+OO 124Sb 6.70E+OO 1.27E-O1 2.66E÷OO 163E-02 O.OOE+OO 5.22E÷OO 1.90E÷02 1255b 4.29E÷OO 4.79F-02 1.02E+OO 4.36E-03 O.OOE+OO 3.30E+OO 472E+O1 265b 2.75E+OO 5.59E-02 9.92E-O1 1.68E-02 O.OOE+OO 1.68E+OO 2.25E÷02 27Te 6.48E÷03 2.32E+03 7.90E+02 1.66E+03 2.63F+04 O.OOE+OO 2.17E+04 27Te 1.OSE+02 3.78E+O1 2.28E+O1 7.80E+O1 4.29E+02 O.OOE+OO 8.31E+03 129mTC 1.1OE+04 4.11E--O3 1.74E+03 3,78E+03 4.60E+04 O.OOE+OO 5.54E+04 29Te 3.O1E÷O1 1.13E+O1 7.33E+OO 2.31E÷O1 126E÷02 O.OOE+OO 2.27E÷O1 13Te 1.66E+03 8.1OE+02 6.75E+02 1.2$E+03 8.21E+03 O.OOE+OQ 8.04E+04 31m 1.89E+O1 7.88E+OO 5.96E+OO 1.55E+O1 8.26E+Q1 O.OOE+OO 2.67E+OO 1321e 2.41E+03 1.56E+03 1.47E÷03 1.72E+03 1.50E+04 O.OOE+OO 7.38E+04

°t 2.71E+O1 $.O1E+O1 3.16E+O1 6.79E+03 1.25E+02 O.OOE+OO 6.89E+O1 1311 1.49E+02 2.14E+02 1.22E+02 7.OOE+04 366E+02 O.OOE+OO 5.&4E÷O1 1321 7.29E+OO 1.95E+O1 6.82E+OO 6.82E+02 3.11E+O1 O.OOE+OO 3.66E+OO I 5.14E+O1 8.87E+O1 2.70E+O1 1.30E+04 1.SSE+02 O.OOE+OO 7.97E+O1 34i 3.81E+OO 1.03E+O1 3.70E+OO 1.79E+02 1.64E+O1 O.OOE+OO 9.O1E-03 I 1.59E+Q1 4.17E+O1 1.54E+O1 2.ThE÷03 6.68E÷O1 O.OOE+OO 4.70E+O1 134Cs 2.98E+05 7.09E+05 5.79E+OS O.OOE+OO 2.29E+O5 7.61E+04 1.24E+04 36Cs 3.12E÷04 1.23E÷05 8.86E+04 O.OOE+OO 6.85E+04 9.38E+03 1.40E+04 37Cs 3.82E+05 5.22E+05 3.42E+05 O.OOE+OO 1,77E+05 5.89E+04 1.O1E+04 38Cs 2.64E+02 5.22E+02 2.59E+02 O.OOE+OO 3.84E+02 3.79E+O1 2.23E-03 39Ba 9.29E-O1 6.62E-04 2.72E-02 O,00E+OO 6.19E-04 3.75E-04 1.65E+OO 140Ba 1.94E+02 2.44E-O1 1.27E+O1 O.OOE+OO 8.30E-02 1.40E-O1 4.QOE+02 141Ba 4.51E-O1 3.41E-04 t52E-02 O.OOE÷OO 3.17E-04 1.93E-04 2.13E-1O 142Ba 2.04E-O1 2.1OE-04 1.28E-02 O.OOE+OO 1.77E-04 1.19E-04 2.87E-19 40La 1.50E-O1 7.54E-02 1.99E-02 O.OOE+OO O.OOE+OO O.OOE+OO 5.54E+03 142La 7.66E-03 3.48F-03 8.6$E-04 O.OOE+OO O.OOE÷OO O.OOE+OO 2.54E+O1 141Ce 2.24E-02 1.52E-02 1.72E-03 O.OOE+OO 7.04E-03 O.OOE+OO 5.79E+Q1 143Ce 3.95E-03 2.92E+OO 3.23E-04 O.OOE+OO 1.29E-03 O.OOE+OO 1.09E+02 44Ce 1.17E+OO 4.88E-O1 6.27E-02 O.OOE÷OO 2.90E-O1 O.OOE+OO 3.95E+02 Page 36 of 75 IN FORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Table 1: Ingestion Dose Commitment Values (A) for Adult Age Group (mrem/hr) per (iCi/ml)

. . Total Nuclide Bone Liver Thyroid Kidney Lung GI-LU Body 4Pr 5.51E-O1 2.21E-O1 2.73E-02 O.OOE+OO 1.27E-O1 O.OOE+OO 2.41E+03 44Pr 1.80E-03 7.48E-04 916E-05 O.OOE+O0 4.22E-04 O.OOE+O0 2.59E-1O 147Nd 3.76E-O1 435E-01 2.60E-02 O.OOE+OO 2.54E-O1 0.OOE÷OO 2.09E+03 4Eu 3.68E÷O1 4.52E÷OO 3.22E+OO 0OOE+OO 2.17E+O1 O.OOE+OO 3.28E+03 81Hf 4OOE-02 1.94E-O1 1.80E-02 Q.OOE+OO 418E-02 0.OOE+OO 2,21E+02 187W 2.96E+02 2.47E+02 8.65E+01 OOOE+0O O.OOE+0O O.OOE+OO 81OE+04 237Np 3.28E÷04 2.85E+03 1.33E+03 000E+OO 9.86E+03 O.OOE+0O 1.90E+03 239Np 2.85E-02 2.80E-03 1.54E-03 O.OOE+0O 8.74E-03 0.OOE÷OO 5.75E+02 238Pu 5.70E+03 8.03E+02 1.43E+02 O.OOE+00 6.13E+02 O.OOE+00 6.12E+02 239Pu* 6.59E+03 8.88E+02 1.60E+02 0.OOE÷OO 6.80E+02 O.OOE+OO 5.68E+02 2Pu 1.38E+02 7.07E+OO 2.78E+00 O.OOE÷OO 128E+O1 O.OOE+OO 1.17E+O1 241Am 4.90E+04 1.72E+04 324E+03 O.ODE+OO 2.44E+04 O.OOE÷OO 4.44E+03 242Cm 123E+03 1.26E÷03 8.20E÷O1 O.OOE+0O 3.72E+02 O.OOE+OO 4.74E+03 243Cm** 3.82E+04 1.44E+04 2.24E+03 0.OOE+QQ 1.OSE+Q4 O.OOE+OO 4.67E+03

• IncIudes Pu-240 contribution

• • IncIudes Cm-244 contribution Page 37 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Table 2: Bioaccumulation Factor (Bf,)

(pCi/kg) per (pCi/liter)

Element Bf1 Fish (Freshwater) Element Bf, Fish (Freshwater)

H 9.OE-01 Rh 1.OE÷01 Be 2.OE÷00 Ag 2.3E÷00 Na 1.OE+02 Cd 2.OE÷02 Cr 2.OE+02 Sn 3.OE+03 Mn 4.OE+02 Sb 1.OE+00 Fe 1.OE+02 Te 4.OE+02 Co 5.OE+01 I 1.5E+01 Ni 1.OE÷02 Cs 2.OE+03 Cu 5.OE+01 Ba 4.OE+00 Zn 2.OE+03 La 2.5E+01 Br 4.2E+02 Ce 1.OE+00 Rb 2.OE+03 Pr 2.5E+01 Sr 3.OE+01 Nd 2.5E÷01 Y 2.5E÷01 Eu 2.5E+01 Zr 3.3E+00 Hf 3.3E÷00 Nb 3.OE÷04 W 1.2E+03 Mo 1,OE÷01 Np 1.OE÷01 Ic 1.SE+01 Pu 3.5E+00 Ru 1.OE÷01 Am 2.5E+01 Cm 2.5E+01 (a)

Values from Regulatory Guide 1.109, Rev. 1, Table A-i and HPCI 04-06.

Page 38 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Table 3: Dose Factor for Exposure to a Semi- Infinite Cloud of Noble Gases Total Body Dose Factor Skin Dose Factor Gamma Air Dose Factor Beta Air Dose Factor Radionuclide K L1 M1 Ni (mrem/yr) per (jiCi/m3) (mrem/yr) per (j.ICi/m3) fmrad/yr) per (jiCi/m3) (mrad/yr) per fj.tCi/m3) s3mKr 7.56 E-02 1.93 E+0]. 2.8$ E+02 85mKr 1.17E+03 1.46E+03 1.23 E÷03 1.97 E+03 85Kr 1.61 E+01 1.34 E+03 1.72 E+01 1.95 E+03 87Kr 5.92 E+03 9.73 E+03 6.17 E+03 1.03 E+04 88Kr 1.47 E+04 2.37 E+03 1.52 E+04 2.93 E+03 89Kr 1.66 E+04 1.01 E+04 1.73 E+04 1.06 E+04 90Kr 1.56 E+04 7.29 E+03 1.63 E+04 7.83 E+03 l3lmXe 9.15 E+01 4.76 E÷02 1.56 E+02 1.11 E+03 a33mXe 2.51 E+02 9.94 E+02 3.27 E+02 1.48 E+03 33Xe 2.94 E+02 3.06 E+02 3.53 E+02 1.05 E+03 l3smXe 3.12 E÷03 7.11 E+02 3.36 E÷03 7.39 E+02 35Xe 1.81 E+03 1.86 E+03 1.92 E+03 2.46 E+03 37Xe 1.42 E+03 1.22 E+04 1.51 E÷03 1.27 E+04 138Xe 8.83 E+03 4.13 E÷03 9.21 E+03 4.75 E+03 41Ar 8.84 E÷03 2.69 E+03 9.30 E+03 3.28 E+03 Page 39 of 75 IN FORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Table 4: Ground Plane Pathway Dose Factors (R1) fm2mrem/yr) per (pCi/sec)

Nuclide Total Body Skin Nuclide Total Body Skin 3H 0.OOE+OO O.OOE+OO 1135n 1.43E+07 409E+07 7Be 2.24E+07 321E+07 24Sb 8.74E+08 1.23E+09 51Cr 4.66E÷06 5.51E+06 25Sb 3.57E+09 5.19E+09 54Mn 1.39E+09 163E÷09 12?mle 9.17E+04 1.08E+05 55Fe O.OOE+00 0.OOE+OO lz9mTe 1.98E+07 2.31E+07 59Fe 2.73E+08 3.21E+O8 1301 5.51E+06 6.69E+06 57Co 2.98E+08 4.37E+08 1311 1.72E+07 2.09E+07 58Co 3.79E+08 4.44E+08 1321 1.25E+06 1.47E+06 60Co 2.15E÷1O 2.53E+1O i 2.45E+06 2.98E÷06 63Ni O.OOE+O0 0.OOE÷0O 1341 4.47E+05 5.31E+05 65Z 747E÷08 8.59E+O8 1351 2.53E+06 2.95E+06 86Rb 8.99E+06 1.03E+07 134Cs 6.85E+09 8.OOE+09 89Sr 2.16E÷04 2.51E÷04 3Cs 1.51E+08 1.71E+08 90Sr O.DOE+OO 0.OOE+00 137Cs 1.03E+1O 1.20E+1O 90Y 5.36E+06 6.32E+06 43Ba 2.05E+07 2.35E+07 91Y 1.07E+06 1.21E+06 140La 1.47E+08 1.66E+08 95Zr 2.45E+O8 2.84E+08 41Ce 1.37E+07 154E+07 95Nb 2.50E+08 2.94E+O$ 144Ce 6.96E+07 8.04E+07

°3Ru 1.08E÷08 1.26E+08 43Pr O.OOE+OO O.OOE+OO

°6Ru 4.22E÷08 S.07E+08 44Pr 435E+07 5.OOE÷07 ilomAg 344E+09 4.O1E+09 47Nd 8.39E+06 1.O1E+07 109Cd 3.76E+07 1.54E÷08 154Eu 2.21E+10 3.15E+1O 81H1 1.97E+08 2.82E÷08 Page 40 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Table 5: Child Inhalation Pathway Dose Factors (R)

(mrem/yr) per (iiCi/m3)

Nuclide Bone Liver Total Body Thyroid Kidney Lung GI-LLI 3H 0.OOE÷OO 1.12E+03 1.12E+03 1.12E+03 1.12E÷03 1.12E+03 1.12E÷03 7Be 8.47E+02 1.44E+03 9.25E÷02 0.OOE+00 O.OOE+0O 6.47E+04 2.55E+03 51Cr 0.OOE÷00 0.OOE+00 1.54E+02 8.55E+01 2.43E+01 1,70E+04 1.08E÷03 54Mn 0.OOE÷00 4.29E+04 9.51E÷03 0.OOE÷00 1.OOE÷04 1.58E÷06 2.29E+04 55Fe 4.74E+04 2.52E+04 7.77E+03 0.OOE+00 0.OOE÷0O 1.1E+05 2.87E+03 59Fe 2.07E+04 3.34E+04 1.67E+04 0.OOE÷O0 0.OOE+00 1.27E÷06 7.07E+04 57Co 0.OOE+0O 9.03E÷02 1.07E+03 0.OOE+0O 0.OOE+0O 5.07E÷05 1.32E÷04 58Co O.OOE+00 1.77E+03 3.16E÷03 0.OOE+0O O.OOE÷0O 1.11E+06 3.44E+04 60Co 0.OOE÷0O 1.31E+04 2.26[÷04 0.OOE+0O 0.OOE+O0 7.07E+06 9.62E+04 63Ni 8.21E÷05 4.63E+04 2.8OE÷04 0.OOE÷0O O.OOE+0O 2.75E÷05 6.33E+03 65Zn 4.25E+04 1.13E÷05 7.03E+04 O.OOE+00 7.14E+04 9.95E+05 1.63E÷04 86Rb O.OOE÷00 1.98E+05 1.14E÷05 0.OOE÷00 0.OOE÷0O 0.OOE+00 7.99E+03 89Sr 5.99E+05 0.OOE+00 1.72E÷04 0.OOE+00 0.OOE+00 2.16E+06 1.67E+05 90Sr 1.O1E÷08 O.OOE+OO 6.44E+06 0.OOE+00 O.OOE+0O 1.48E÷07 3.43E+05 90Y 4.11E+03 0.OOE+0O 1.1E+02 O.OOE÷00 0.OOE+00 2.62E÷05 2.68E÷05 91Y 9.14E+05 O.OOE÷00 2,44E+04 0.OOE+0O 0.OOE+0O 2.63E+06 1.84E+05 95Zr 1.90E+05 4.18E+04 3.70E+04 O.OOE+O0 5.96E+04 2.23E+06 6.1E+04 95Nb 2.35E÷04 9.18E+03 6.55E+03 0.OOE+00 8.62E+03 6.14E÷05 3.70E+04

°3Ru 2.79E÷03 0.OOE+O0 1.07E+03 O.OOE+00 7.03E+03 6.62E+05 4.48E+04

°Ru 1.36E+05 0.OOE+00 1.69E÷04 0.OOE+O0 1.84E+05 1.43E+07 4.29E+05 liomAg 1.69E+04 1.14E+04 9.14E+03 0.OOE+00 2.12E+04 5.48E+06 1.OOE+05 109Cd 0.OOE+O0 5.48E÷05 2.59E+04 0.OOE÷00 4.96E+05 1.05E+06 2.78E+04 13Sn 1.13E+05 3.12E+03 8.62E+03 2.33E÷03 0.OOE+00 1.46E+06 2.26E÷05 24Sb 5.74E+04 7.40E÷02 2.OOE÷04 1.26E+02 O.OOE+0O 3.24E+06 1.64E÷05 25Sb 9.84E÷04 7.59E+02 2.07E+04 9.1OE÷01 O.OOE÷00 2.32E+06 4.03E÷04 12?mle 2.49E÷04 8.55E+03 3.02L÷03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 l29mTe 1.92E+04 6.85E+03_[ 3.04E+03 6.33E÷03 5.03E+04 1.76E+06 1.82E+05 Page 41 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Table 5: Child Inhalation Pathway Dose Factors (R) fmrem/yr) per (tCi/m3)

Nuclide Bone Liver Total Body Thyroid Kidney Lung GI-LLI 130) 818E+03 1.64E+04 8.44E+03 1.85E+06 2.45E+04 O.OOE+00 5.IIE÷03 i 4.81E÷04 4.81E+04 2.73E+04 1.62E+07 7.88[+04 0.OOE÷00 2.84E+03 132 2.12E+03 4.07E+03 1.88E+03 1.94E+05 6.25E+03 O.OOE+O0 3.20E+03 l 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.OOE+00 5.48E+03 l 1.17E÷03 2.16E+03 9.95E+02 5.07E÷04 3.30E÷03 0.OOE+00 9.55E+02 l 4.92E÷03 8.73E+03 4.14E+03 7.92E+05 1.34E+04 0.OOE+OO 4.44E+03 34Cs 6.51E+05 1.O1E+06 2.25E÷05 0.OOE+00 3.30E÷05 1.21L÷05 3.85E+03 36Cs 6.51E+04 1.71E+05 1.16E+05 O.OOE+00 9.55E÷04 145E+04 4.1$E+03 37Cs 9.07E+05 8.25E+05 1.28E+05 0.OOE+00 2.82E+05 ].04E+05 3.62E+03 140Ba 7.40E÷04 6.4$E+01 4.33E+03 O.OOE+OO 2.11E÷01 1.74E+06 1.02E+05 40La 644E÷02 2.25E÷02 7.55E+O1 O.OOE÷O0 0.OOE+O0 1,83E÷05 2.26E+05 141Ce 3.92E+04 1.95E+04 2.90E+03 0.OOE+00 8.55E+03 5.44E+05 5.66E+04 44Ce 6.77E÷06 2.12E+06 3.61E÷05 0.OOE+00 1.17E+06 1.20E÷07 3.89E+05 143Pr 1.85E+04 5.55E+03 9.14E÷02 0.OOE+00 3.OOE+03 4.33E+05 9.73E+04 44Pr 5.96E-02 1.85E-02 3.OOE-03 0.OOE+00 9.77E-03 157E+03 1.97E+02 147Nd 1.08E+04 8.73E+03 6.81E÷02 0.OOE+00 4.81E+03 3.28E+05 8.21E+04 54Eu 1.O1E÷07 9.21E+05 8.40E+05 O.OOE÷00 4.03E+06 6.14E+06 1.OE+05 81Hf 2.78E+04 1.O1E+05 1.25E+04 0.OOE+0O 2.05E+04 1.06E+06 6.62E+04 Page 42 of 75 IN FORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Table 6: Child Grass- Cow Milk Pathway Dose Factors (R1)

(m2mrem/yr) per (pCi/sec)

Nuclide Bone Liver Total Body Thyroid Kidney Lung GI-LLI 3H O.OOE+OO 1.57E+03 1.57E+03 1.57E+03 1.57E+03 157E+03 1.57E+03 7Be 7.50E+03 1.2$E+04 8.20E+03 O.OOE+00 1.25E+04 0.OOE+00 7.12E+05 51Cr 0.OOE+00 0.OOE÷00 1.02E+05 5.66E+04 1.55E+04 103E+05 5.40E+06 54Mn 0.OOE+00 2.1OE+07 5.59E+O6 0.OOE+00 5.89E÷06 0.OOE+O0 1.76E+07 55Fe 1.12E+08 5.94E+07 1.84E÷07 0.OOE÷00 0OOE÷0O 3.36E+07 1.1OE÷07 S9Fe 1.20E+08 1.95E+O$ 9.70E+07 0.OOE+00 0.OOE+00 5.64E+07 2.03E÷08 57Co 0.OOE÷O0 3.$4E+06 7.78E+06 0.OOE+00 0.OOE+00 0.OOE+00 3.15E+07 58Co 0.OOE+OO 1.21E÷07 3.72E+07 0.OOE+00 0.OOE+00 O.OOE÷00 7.OSE+07 60Co O.OOE÷00 4.32E+07 1.27E+08 0.OOE÷00 0.OOE÷00 0.OOE+OO 2.39E÷08 63N 2.97E+1O 1.59E÷09 1.O1E+09 0.OOE+0O O.OOE+00 0.OOE÷00 1.07E+08 65Zn 4.14E+09 1.1OE÷10 6.86E+09 0.OOE+00 6.95E+09 0.OOE+00 1.94E+09 86Rb 0OOE+OO 8.78E+09 5.40E+09 O.OOE÷0O 0.OOE+00 0.OOE+OO 5.65E+08 895r 6.63E+09 O.OOE+00 1.89E+08 0.OOE+00 0.OOE+00 0.OOE+O0 2.57E+08 90Sr 1.12E+11 0.OOE+00 2.84E+10 0.OOE+0O 0.OOE+0O O.OOE÷0O 1.51E+09 90Y 3.38E+03 0.OOE+00 9.05E+01 O.OOE+00 0.OOE+OO O.OOE+00 962E+06 9Y 3.91E+04 0.OOE+OO 1.04E+03 0.OOE+OO OOOE+0O 0.OOE+00 5.20E÷06 95Zr 3.84E+03 843E+02 7.51E+02 0.OOE÷00 1.21E+03 0.OOE+0O 880E+05 95Nb 3.72E+05 1.45E+05 1.03E+05 0.OOE+O0 1.36E+05 0.OOE+0O 2.68E÷0$

°3Ru 4.29E+03 0.OOE÷00 1.65E+03 O.OOE+00 1.O8E+04 O.OOE+OO 1.11E÷05

°6Ru 9.25E+04 O.OOE+00 1,15E+04 O.OOE+OD 1.25E+05 O.OOE+00 144E+06 IlomAg 2.09E+08 1.41E+08 1.13E+08 O.OOE+O0 2.63E+08 0.OOE+00 1.68E+10

°Cd 0.OOE+O0 3.86E÷06 179E+05 0.OOE+00 3.45E÷06 0OOE÷00 1.25E+07 113Sn 6.11E+08 1.26E+07 3.48E÷07 9.29E+08 0.OOE+00 0.OOE+0O 4.32E+O8 24Sb 1.09E+08 1.41E+06 3.S1E÷07 2.40E÷05 0.OOE+0O 6.03E+07 6.80E÷0$

255b 8.71E÷07 6.72E+05 1.83E÷07 8.07E+04 OOOE÷00 4.86E+07 2.08E+08 l27mTe 2.08E+08 561E+07 2.47E+07 4.98E+07 5.94E+O8 O.OOE÷O0 1.69E+08 129m1e 2.72E+08 7.59E+07 4.22E+07 8.76E+07 7.98E+08 O.OOE+0O 3.31E+08 Page 43 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Table 6: Child Grass- Cow Milk Pathway Dose Factors (R)

(m2mrem/yr) per (iiCi/sec)

Nuclide Bone Liver Total Body Thyroid Kidney Lung GI-LLI

°i 173E+06 3.50E+06 1.80E+06 3.85E+08 5.23E÷06 O.OOE+OO 1.64E÷06 1311 1.30E+09 1.31E÷09 7.46E+08 4.34E+11 2.15E+09 O.OOE+0O 1.17E+03 1321 6.92E-O1 1.27E÷OO 5.85E-O1 5.90E+O1 1.95E+OO O.OOE+OO 1.50E+OO 1331 1.72E+07 2.13E+07 8.05E+06 3.95E+09 3.54E+07 O.OOE+0O 8.57E+06 1341 O.OOE+OO O.OOE÷OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE÷0O O.OOE+QO 13S1 5.41E+04 9.74E+04 4.61E÷04 8.63E+06 1.49E÷05 O.OOE÷OO 7.42E+04 34Cs 2.27E÷1O 3.72E÷1O 7.84E+O9 O.OOE+OO 1.15E+1O 4.14E+09 2.OOE+08 136Cs 1.O1E+09 2.78E+09 1.80E+09 O.OOE÷OO 1.48E+09 221E÷08 9.78E+07 37Cs 3.23E+1O 3.09E+1O 4.56E+09 O.OOE+00 1.O1E÷1O 3.62E+09 1.93E+08 40Ba 1.17E+08 1.03E+05 6.84E+06 0.OOE÷OO 3.34E+04 6.12E+04 5.94E+07 140La 1.78E+02 6.23E+O1 2.1OE+O1 0.OOE+OO O.OOE+OO O.OOE+OO 1.74E+06 141Ce 2.19E+04 1.09E+04 1.62E+03 O.OOE+OO 4.79E÷03 O.OOE+00 1.36E+07 44Ce 1.62E+06 5.09E+05 8.67E+04 O.DOE÷OO 2.82E÷05 O.OOE÷OO 1.33E÷08 43Pr 7.19E+02 2.16E+02 3.57E+O1 OOOE+OO 1.17E+02 O.OOE+OO 7.76E+05 43Pr 5.04E+OO 1.56E÷OO 2.53E-O1 0.OOE+OO 8.24E-O1 O.OOE÷OO 3.35E+03 47Nd 4.45E+02 3.61E+02 2.79E+O1 O.OOE+OO 1.98E+02 O.OOE+OO 5.71E+05 ls4E 9.43E÷04 8.48E+03 7.75E÷03 O.OOE+OO 3.73E+04 O.OOE+OO 1.97E+06 81Hf 6.44E+02 2.35E+03 2.91E+02 O.OOE+OO 4.76E÷02 O.OOE+OO $.66E+05 Page 44 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Table 7: Child Grass- Goat Milk Pathway Dose Factors fR1) fm2mrem/yr) per ([ICVsec)

Nuclide Bone Liver Total Body Thyroid Kidney Lung Gl-LLI 3H 0.OOE+0O 3,20E+03 3.20E÷03 3.20E+03 3.20E÷03 3.20[÷03 3.20E÷03 7Be 9.OOE+02 1.53E+03 9.84E+02 O.OOE+00 1.50E+03 0.OOE+00 8.55E+04 51Cr 0.OOE÷00 0.OOE+00 1.22[÷04 6.79E+03 1.85E÷03 1.24E÷04 648E÷05 54Mn 0.OOE+00 2.52E÷06 6.71E+05 O.OOE+00 7.06E+05 0OOE+00 21E+06 55Fe 1.45E+06 772E+05 2.39E+05 0.OOE+00 0.OOE÷00 4.36E+05 1.43E÷05 1.56E+06 2.53E+06 1.26E+06 0.OOE+00 0.OOE+OO 734E+05 2.64E+06 57Co 0.OOE+00 4.61E+05 9.33E+05 0.OOE÷00 0.OOE+00 0.OOE÷00 3.7$E+06 58Co 0.OOE+00 1.46E+06 4.46E+06 0.OOE+00 0.OOE+O0 0OOE+OO 8.50E+06 60Co 0.00E÷0O 5.19E+06 153E+07 0.OOE+OQ 0.OOE+0O 0.OOE+00 2.87E+07 63Ni 356E+09 1.91E+08 121E+08 O.OOE+O0 0.OOE+00 0OOE+00 1.28E+07 65Zn 4.97E+08 1.32E+09 8.23E+08 0.OOE+0O 834E÷08 0.OOE+00 2.32E+08 86Rb 0.OOE÷00 1.05E÷09 6.48E÷08 O.OOE+00 0.OOE+00 0.OOE+O0 6.78E+07 89Sr 139E÷10 0.OOE+00 3.97E+08 0.OOE÷OO O.OOE+0O O.OOE÷00 5.39E+08 905r 2.35E÷11 0.OOE÷0O 5.95E+1O O.OOE+00 0.OOE+00 0OOE+00 3.16E+09

°Y 4.06E+02 O.OOE÷00 1.09E+01 O.OOE+OO 0.OOE+00 0.OOE+00 1.15E+06 91Y 4.69E+03 0.OOE÷00 1.25E+02 0.OOE+00 O.OOE+00 0.OOE÷00 6.25E÷05 95Zr 4.60E+02 1.OE+02 9.O1E+01 Q.OOE÷0O 1.45E+02 0.OQE÷00 1.06E+05 95Nb 4.46E+04 1.74E+04 124E÷04 0.OOE÷00 1.63E+04 0.OOE+OO 3.21E+07

°3Ru 514E+02 0.OOE+O0 1.9$E+02 O.OOE÷OO 1.29E÷03 O.OOE+00 133E+04

°6Ru 1.1E+04 0.OOE+OO 1.38E÷03 O.OOE+00 1.50E+04 0.OOE+00 1.73E+05 alomAg 2.51E÷07 1.69E+07 1.35E÷07 0.00E+00 3.15E+07 0.OOE÷00 2.O1E+09

°9Cd O.OQE+00 4.64E+05 2.15E+04 0OOE+00 4.14E÷0S 0.OOE+00 1.50E+06 35n 733E+07 151E+06 4.18E+06 1.1E+08 0.OOE+00 O.OOE÷00 5.18E+07 1245b 1.30E÷07 1.69E+05 4.57E+06 2.88E+04 0.OOE+OO 724E÷06 8.16E+07 25Sb 1.05E+07 8.06E+04 219E÷06 9.68E+03 O.OOE+0O 5.83E÷06 2.50E+07 l27mTe 2.50E÷07 6.73E÷06 297E÷06 5.98E+06 7.13E+07 0.OOE÷00 2.02E+07 129m1 3.26E÷07 9.1OE+06 5.06E+06 1.OSE+07 9.57E÷07 0OOE+0O 3.98E+07 Page 45 of 75 IN FORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Table 7: Child Grass- Goat Milk Pathway Dose Factors fR1)

(m2mrem/yr) per (piCi/sec)

Nuclide Bone Liver Total Body Thyroid Kidney Lung GI-LLI 130p 2.O$E+06 4.20E+06 2.16E÷06 4.62E+02 6.27E÷06 0.OOE+00 1.96E+06 131p 1.57E+09 1.57E+09 8.95E+08 5.21[+11 2.58E+09 0.OOE÷00 1.40E+08 1321 8.30E-01 1.53E+00 7.02E-O1 7.08E+O1 2.34E+OO O.OOE÷OO 180E+0O I 2.06E+07 2.55E+07 9.66E+06 4.74E+09 4.25E+07 0.OOE÷00 1.03E+07 1341 0.OOE+00 0.OOE÷00 0.OOE÷00 0.OOE+00 0.OOE+00 0.OOE÷00 0.OOE+00 I 6.49E+04 1.17E÷05 5.53E+04 1.04E+07 1.79E÷05 0.OOE+00 8.90E+04 134Cs 6.80E+10 1.12E÷11 2.35E+10 0.OOE+00 3.46E+10 1.24E+10 6.O1E+08 136Cs 3.04E+09 8.35E+09 5.40E÷09 0.OOE+00 4.45E+09 6.63E+08 2.93E+08 37Cs 9.68E+10 9.27E+10 1.37E+1O 0.OOE+00 3.02L+1O 1.09E÷10 5.80E+08 40Ba 1.41E+07 1.23E+04 8.21E+05 0.OOE+O0 4.OE+03 7.35E+03 7.13E÷06 140La 2,14E+01 7.47E÷0O 2.52E+00 0.OOE+00 0.OOE÷00 0.OOE+00 2.O8E+05 141Ce 2.63E+03 1.31E+03 1.95E+02 0.OOE+00 5.75E+02 0.OOE+00 1.63E+06 144Ce 1.95E+05 6.11E+04 1.04E+04 0.OOE+00 3.38E+04 0.OOE+00 1.59E+07 43Pr 8.63E+01 2.59E+01 4.2$E+O0 0.OOE+0O 1.40E+O1 O.OOE+OO 9.31E+04 144Pr 6.05E-O1 1.87E-O1 3.04E-02 O.OOE÷O0 9.89E-02 0.OOE+00 4.03E÷02 47Nd 5.34E+01 4.33E+01 3.35E+00 0.OOE+00 2.37E+01 0.OOE+0O 6.85E÷04 54Eu 113E÷04 1.02E÷03 9.29E+02 0.OOE+00 4.47E÷03 0.OOE+00 2.37E+0S 181Hf 7.73E+01 2.81E+02 3.49E+01 0.OOE+00 5.]2E+01 O.OOE+00 1.04E+05 Page 46 of 75 INFORMATION USE March, 2017

APA-ZZ-O1 003 Rev. 022 Table 8: Child Meat Pathway Dose Factors (R)

(m2mrem/yr) per (iiCi/sec)

Nuclide Bone Liver Total Body Thyroid Kidney Lung GI-LLI 3H 0.OOE+00 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E÷02 2.34E+02 7Be 7.38E+03 1.26E+04 8.07E÷03 0.OOE÷OO 1.23E+04 0.OOE+0O 7.OOE+05 51Cr 0.OOE+00 O.OOE÷OO 8.80E+03 4.88E+03 1.33E+03 8.92E+03 4.67E+05 54Mn 0.OOE+0O 802E÷06 2.14E+06 0.OOE+O0 2.25E+06 0.OOE+0O 6.73E+06 55Fe 4.58E+08 2.43E+08 7.52E÷07 0.OOE+00 0.OOE+00 1.37E+08 4.50E÷07 59Fe 3.77E+08 6.1OE÷08 3.04E+08 0.OOE+0O 0.OOE+00 1.77E+08 6.35E÷08 57Co 0.OOE÷00 5.92E+06 1.20E+07 O.OOE÷00 0.OOE+0O 0.OOE+00 4.85E+07 58Co O.OOE+OO 1.64E+07 5.03E+07 0.OOE+0O 0.OOE+00 0.OOE+O0 9.59E÷07 50Co 0.OOE+00 6.94E+07 2.OSE÷08 O.OOE+00 0.OOE+00 0.OOE+00 3.84E+08 3Ni 2.92E+10 1.56E+09 9.92E+08 0.OOE+00 0.OOE÷00 0.OOE+00 1.05E+08 65Zn 3.76E÷08 1OOE+09 6.23E÷08 0.OOE+00 6.31E+08 0.OOE÷00 1.76E+08 86Rb 0.OOE+OO 5.77E+08 3.55E+08 0.OOE+0O O.OOE+0O 0.OOE+00 3.71E+07 895r 4.82E+0$ 0.OOE+OO 1.38E+07 O.OOE+00 0.OOE+OO 0.OOE+00 1.87E+07 905r 1.04E+10 0.OOE+00 2.64E+09 0.OOE+OO 0.OOE÷00 O.OOE+00 1.40E÷0$

°Y 1.93E+05 0.OOE+00 5.16E+03 0.OOE+00 0.OOE+00 0.OOE+0O 5.49E+0$

91y 1.80E+06 0.OOE+00 4.82E+04 0.OOE+00 0.OOE+00 O.OOE÷00 2.40E+08 95Zr 2.67E÷06 5.86E+05 5.22E+05 O.OOE÷00 8.39E+05 0.OOE+00 611E+08 95Nb 4.26E+06 1.66E+06 1.18E+O6 0.OOE+OO 1.56E÷06 0.OOE+00 3.07E÷09

°3Ru 1.55E+08 O.OOE+00 5.96E+07 O.OOE÷00 3.90E+08 0OOE+0O 4.O1E+09 106Ru 4.44E+09 0.OOE+00 5.54E+08 0.OOE+OO 6.OOE+09 0.OOE+00 6.91E÷1O 110Ag 8.40E+06 5.67E+06 4.53E+06 0.OOE÷00 1.06E+07 0.OOE+OO 6.75E+08 109Cd 0.OOE+00 1.91E÷06 8.84E+04 0.OOE+OO 1.70E+06 0.00E+00 6.18E+06 13Sn 2.18E+09 4.48E+07 1.24E+08 3.31E+09 0.OOE+00 0.OOE+00 1.54E+09 245b 2.93E+07 3.80E+05 1.03E+07 6.46E+04 0.OOE+00 1.62E÷07 1.83E÷08 255b 2.85E÷07 2.20E+05 5.97E+06 2.64E+04 0.OOE+00 1.59L+07 6.81E+07 12?mle 1.7$E+09 4.7$E+O$ 2.1E+08 4.25E+08 5.07E+09 0.OOE+00 1.44E+09 l29mTe 1.79E+09 5,00E+08 2.78E+08 5.78E÷08 5.26E÷09 O.OOE+D0 2.19E+09 Page 47 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Table 8: Child Meat Pathway Dose Factors (R)

(m2mrem/yr) per (IIC1/sec)

Nuclide Bone Liver Total Body Thyroid Kidney Lung GI-ILI 1301 3.06E-06 6.18E-06 3.18E-06 6.80E-04 9.23E-06 O.OOE+OO 2.89E-06 I 1.66E+07 1.67E÷07 9.47E+06 5.51E+09 2.74E+07 O.OOE+OO 1.48E+06 1321 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1331 5.70E-O1 7.05E-O1 2.67E-O1 1.31E+02 1.17E+OO O.OOE+OO 2.84E-01 I O.OOE+OO O.OOE+OO O.OOE+OO O.OOE÷OO O.OOE÷OO O.OOE+OO O.OOE÷OO 0.OOE+OO O.OOE÷O0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE÷OO O.OOE÷OO 34Cs 9.23E+08 1.51E+09 3.20E+08 O.OOE+OO 4.69E÷08 1.68E+08 8.17E+06 36Cs 1.62E+07 4.46E+07 2.89E÷07 O.OOE+OO 2.38E÷07 3.54E÷06 1.57E÷06 137Cs 133E+09 1.28E+09 1.89E+08 O.OOE+OO 4.16E+08 1.SOE+08 8.OOE+06 40Ba 4.39E+07 3.85E+04 2.56E+06 O.OOE+OO 1.25E+04 2.29E+04 2.22E+07 40La 3.33E+02 1.17E÷02 3.93E÷O1 O.OOE÷OO O.OOE÷OO O.OOE÷OO 3.25E÷06 41Ce 2.22E+04 1.1E÷04 1.65E+03 0.OOE+O0 4.86E+03 O.OOE+00 1.38E+07 44Ce 2.32E+06 7.27E+05 1.24E+05 O.OOE÷OO 4.02E÷05 O.OOE÷OO 1.89E+08 43Pr 3.34E+04 1.OOE+04 166E+03 O.OOE+OO 5.43E÷03 O.OOE+OO 3.61E+07 44Pr 5.63E+02 1.74E÷02 2.83E+O1 O.OOE+OO 9.21E+O1 O,00E+OO 375E+05 47Nd 1.17E÷04 9.48E+03 7.34E+02 O.OOE+OO 5.20E+03 O.OOE+OO 1.50E+07 154Eu 1.12E+07 1.O1E+06 9.20E+05 O.OOE+OO 4.43E÷06 O.OOE÷OO 2.34E+08 181Hf 4.77E+06 1.74E+07 2.15E+06 0.OOE+OO 3.53E+06 O.OOE+OO 6.41E+09 Page 48 of 75 IN FORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Table 9: Child Vegetation Pathway Dose Factors (R1)

(m2mrem/yr) per (iiCi/sec)

Nuclide Bone liver Total Body Thyroid Kidney Lung Gl-LLI 3H O.OOE+00 4O1E÷03 4.O1E÷03 4.O1E+03 4.O1E+03 4.O1E÷03 4.O1E+03 7Be 338E÷05 5.76E+05 3.70E+05 0.OOE+00 5.65E+05 0.OOE+00 3.21E+07 51Cr 0.OOE÷0O OOOE+00 1.17E+05 6.SOE+04 1.78E+04 1.19E+05 621E÷06 54Mn 0.OOE+00 6.65E+08 1.77E+08 0.OOE+00 1.$6E÷08 0.OOE+00 5.58E+08 55Fe 8.O1E+08 4.25E÷08 132E÷08 0.OOE+00 0.OOE+OO 2.40E+08 7.87E+07 59Fe 3.98E+08 6.43E+Og 3.20E+08 0.OOE+00 0.OOE+00 187E÷08 6.70E+08 57Co 0OOE÷00 2.99E+07 6.04E+07 0.OOE+00 0.OOE÷0O 0.OOE+0O 2.45E÷08 58Co O.OOE+O0 6.44E+07 1.97E+08 0.OOE+00 O.OOE÷00 O.OOE+00 376E+08 60Co 0.OOE+00 3.78E+08 1.12E+09 O.OOE+00 0.OOE+00 0.OOE+OO 2.1OE+09 63Ni 3.95E+10 2.11E+09 1,34E+09 0.OOE+O0 0OOE÷00 D.OOE+00 142E+08 65Zn 8.13E÷08 2.17E+09 1.35E÷09 0.OOE+00 1.36E+09 0.OOE+00 3.80E+08 86Rb O.OOE+OO 4.52E+08 2.78E+08 0.OOE+00 0.OOE÷00 0.OOE+00 2.91E÷07 895r 3.60E+10 O.OOE÷00 103E+09 0.OOE÷00 0.OOE÷00 0.OOE+OO 1.39E+09 905r 1.24E+12 0.OOE+00 3.15E+11 0.OOE+O0 0.OOE+00 O.OOE÷00 1,67E+10

°Y 3.O1E+06 0.OOE÷00 8.04E+04 000E+00 O.OOE+O0 0.OOE+O0 8.56E+09 Y 1.86E+07 0.OOE÷00 4.99E+05 0.OOE+O0 0.OOE+0O 0OOE+00 2.48E+09 95Zr 3.86E÷06 8.48E÷05 7.55E+05 O.OOE+00 1.21E+06 0.OOE+00 8.85E+08 9Nb 7.48E+05 2.91E+05 2.08E+05 0.OOE+OO 2.74E+05 0.OOE+00 5.39E+08 103Ru 1.53E+07 O.OOE+0O 5.90E+06 O.OOE+00 3.86E+07 0.OOE+OO 3.97E+O$

°6Ru 7.45E+08 0.OOE÷00 9.30E÷07 0.OOE+00 1.OE+09 0.OOE÷00 1.1GE+10 IlomAg 3.21E+07 2.17E+07 1.73E+07 0.OOE÷00 4.04E+07 0OOE+00 2.58E+09

°°Cd O.OOE+00 2.45E+08 1.14E÷07 0.OOE+O0 2.18E+0$ 0.OOE+00 7.94E+0$

113Sn 1.5$E+09 3.25E÷07 9OOE÷07 2.40E+09 0.OOE÷00 0.OOE÷0O 1.12E+09 24sb 3.52E+08 4.57E+06 123E+08 7.77E+05 0.OOE+00 1.95E÷0$ 2.20E÷09 255b 499E+08 3.85E+06 1.05E+08 4.63E+05 O.OOE+00 2.78E÷08 1.19E+09 27Te 1.32E+09 3.56E÷08 1.57E+08 3.16E÷08 3.77E÷09 0.OOE÷00 1.07E+09

29m1e 8.41E+08 2.35E+08 1.31E+08 2.71E+08 2.47E+09 0.00L+00 1.03E+09 Page 49 of 75 INFORMATION USE March, 2017

APA-ZZ-O1 003 Rev. 022 Table 9: Child Vegetation Pathway Dose Factors fR1)

(m2mrem/yr) per (pCi/sec)

Nuclide Bone Liver Total Body Thyroid Kidney Lung Gl-LLI 130i 6.16E+05 1.24E+06 6.41E+05 1.37E+08 1.86E+06 0.OOE+0O 5.82E+05 1311 143E+08 1.44E+08 8.17E+07 4.76E+1O 2.36E+08 0.OOE+00 1.28E+07 i 9.23E+O1 1.70E+02 7.$OE+01 7.87E+03 2.60E+02 O.OOE+OO 2.OOE+02 1331 3.53E÷06 4.37E+06 1.65E÷06 8.12E+08 7.28E+06 0.OOE÷00 1.76E+06 I 1.56E-04 2.89E-04 1.33E-04 6.65E-03 4.42E-04 0.OOE+00 t92E-04 I 6.26E+04 1.13E+05 5,33E÷04 9.98E+06 1.73E÷05 0,00E÷00 8.59E+04 134Cs 1.60E+10 2.63E+1O 5.55E+09 0.OOE+00 8.15E+09 2.93E+09 1.42E÷08 36Cs 8.24E+07 2.27E+08 1.47E+08 0.OOE+00 1.21E+08 1.80E+07 7.96E+06 37Cs 2.39E÷1O 2.29E+10 3.38E+09 0.OOE+00 7.46E+09 2.68E÷09 1.43E+08 40Ba 2.77E+0$ 2.43E÷05 1.62E+07 O.OOE÷OO 7.90E+04 1.45E÷05 1.40E+08 40La 3.36E+04 1.18E+04 3.96E+03 0.OOE÷00 0.OOE+00 0.OOE+00 3.28E+0$

41Ce 6.56E÷05 3.27E+05 4.$6E÷04 0.OOE÷00 1.43E+05 0.OOE+00 4.08E+08 144Ce 1.27E+0$ 3.98E+07 6.78E÷06 0.OOE+00 2.21E÷07 0.OOE÷00 1.04E÷10 43Pr 1.46E÷05 4.37E+04 7.23E+03 0.OOE+00 2.37E+04 0.OOE+OO 1.57E+0$

44Pr 7.88E+03 2.44E+03 3.97E+02 O.OOE÷00 1.29E+03 0.OOE÷00 5.25E+06 47Nd 7.15E+04 5.79E÷04 4.48E+03 0.OOE+00 3.18E+04 0.OOE+00 9.17E÷07 54Eu 1.66E÷08 1.50E+07 1.37E+07 0.OOE+00 6.57E+07 0.OOE÷0O 3.48E+09 81Hf 4.90E+05 1.79E+06 2.21E+05 0.OOE÷00 3.63E+05 0.OOE÷O0 6.59L÷08 Page 50 of 75 INFORMATION USE March, 2017

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APA-ZZ-01 003 Rev. 022 Table 11: Application of Atmospheric Dispersion Parameters for Release Permits Dose Pathway Dispersion Parameter Controlling Age Group REC Controlling Location Noble Gas, X/Q, decayed/undepleted Site Boundary N/A 16.11.2.2 Beta Air & Gamma Air (2.26 day half-life)

Noble Gas, X/Q, decayed/u ndepleted N/A 16.11.2.1 Site Boundary Total Body & Skin (2,26 day half-life)

X/Q, decayed/depleted 16.11.2.1 Nearest Resident Inhalation chId (8 day half-life) 16,11.2.3 Site Boundary Ground Plane Deposition N/A 16.11.2.3 Nearest Resident Ingestion pathways D/0* Child 16.11.2.3 Nearest Resident

• For si-i, X/Q decayed/depleted is used instead of D/Q.69 69 Regulatory Guide 1.109, Appendix C, Section 3.a Page 52 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Table 12: Application of Atmospheric Dispersion Parameters Annual Radioactive Effluent Release Report

• Controlling I . . 70 Dose Pathway Dispersion Parameter I Dispersion Values Controlling location Age Group Noble Gas, X/Q, decayed/undepleted Site Boundary

. N/A Concurrent Beta Air & Gamma Air Dose (2.26 day half-life) Nearest Resident Site Boundary Noble Gas X/Q decayed/undepleted Concurrent N/A Nearest Resident Total Body & Skin Dose (2.26 day half-life)

Historical Inside Site Boundary Site Boundary Concurrent Ground Plane Deposition Dose D/Q N/A Nearest Resident Historical Inside Site Boundary Site Boundary Child Concurrent

. X/Q, decayed/depleted Nearest Resident Inhalation Dose (2 day half-life) Concurrent Nearest Residence Adult Historical Inside Site Boundary D/Q Site Boundary Ingestion Dose Pathways (For [43, /Q. decayed/depleted Child Concurrent

. Nearest Resident is used instead of D/Q.) 73 Child Concurrent Nearest Resident C All Dose Pathways72 X/Q, undecayed/undepleted Adult Historical Inside Site Boundary 70 Historical, i.e., 5 year average, dispersion parameters for activities inside the Site Boundary are provided in Table 10.

Regulatory Guide 1.109, Appendix C, Section 3.a 72 See Appendix A Page 53 of 75 IN FORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Table 13: Meteorological Data Selection Hierarchy First Second Third Parameter Primary Alternate Alternate Alternate Wind Speed lOm A lOm B 60m A 60m B Wind Direction lOm A lOm B 60m A 60m B Air Temperature lOm A lOm B Wind Variability 1Dm A lOm B 60m A 60m B Temp Difference 60-lOm A 60-lOm B Dew point/Relative Humidity lOm A 60m B Precipitation im (a) A indicates Alpha train meteorological instrumentation.

(b) B indicates Bravo train meteorological instrumentation.

Page 54 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Appendix A: Methodology for Calculating Dose from 14C in Gaseous Elf I uents

1) Introduction The purpose of this Appendix is to provide methodology and parameters for calculating (1) the quantity of 14C released in gaseous effluents, (2) the dose to the Member of the Public at the neatest receptor location due to 140 released in gaseous effluents, and (3) the dose from 140 released in gaseous effluents to the Member of the Public due to activities within the Site Boundary.

The quantity of 14C discharged can be estimated73 by sample measurements, or by use of a normalized 140 source term and scaling factors based on power generation,74 or by use of the GALE code,75 or by use of the EPRI site specific or proxy methodologies.76 Any of these methodologies is acceptable for estimating the 14C discharged in gaseous effluents.

2) Assumptions

a. The total quantity of o produced during the year is assumed to be released during the year in which it was produced.

b. The quantity of 140 produced is determined using the methodology in EPRI TR-1 021106.

c. For conservatism, it is assumed that all 140 produced is released in gaseous effluents.

d. The dose contribution of 140 from liquid effluents is much less than that contributed by gaseous effluents, therefore evaluation of 140 in liquid effluents is not required.77

e. The dose to the Member of the Public is determined in accordance with the methodology and parameters in Regulatory Guide 1 .109.

f. 0 has a long half- life with respect to the plume transit time. 140 is discharged as OH4 or 002 gas and does not deplete or undergo chemical change before it reaches the receptor location. Therefore the appropriate dispersion parameter is XQ (undecayed and undepleted).

Regulatory Guide 1.21, rev. 2, Section 1.9 NCRP Report 81 NUREG- 0017 EPRI TR-1021106, Section 4.

Regulatory Guide 1.21, rev. 2, Section 1.9 Page55of75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022

g. The inhalation pathway is assumed to exist at the Nearest Residence location with the highest value of X!Q, undecayed! undepleted as determined by the annual Land Use Census.

h. The ingestion pathways are assumed to exist at the nearest receptor location with the highest value of X/Q, undecayed! undepleted as determined by the annual Land Use Census. For conservatism, the Nearest Residence location may be considered the highest nearest receptor location for the ingestion pathways.

The appropriate dispersion parameters for activities within the Site Boundary is provided in Table 10.

j. 1C is not a gamma- emitting nuclide; therefore the ground plane pathway is negligible.

k. As a first approximation, it is assumed that the child age group exists at the Nearest Residence and ingestion pathway locations.

Only 14C02 discharged during periods of photosynthesis is considered for the ingestion pathways.

m. All of the 4C produced is assumed to contribute to the inhalation dose pathway, regardless of chemical form.

3) Applicable Dose Limits 10 CFR 50, Appendix I, states, The calculated annual total quantity of all radioactive iodine and radioactive material in particulate form above background to be released from each light-water-cooled nuclear power reactor in effluents to the atmosphere will not result in an estimated annual dose or dose commitment from such radioactive iodine and radioactive material in particulate form for any individual in an unrestricted area from all pathways of exposure in excess of 15 millirems to any organ.78 Radiological Effluent Control (REC) 16.11.2.3 limits the annual dose to the Member of the Public from 1311, 3H, and particulates with half-lives greater than 8 days released in gaseous effluents to 15 mrem to any organ.79 14C is released as a gas in the form of CH4 or CO2 and is not a radioiodine, tritium, or particulate, therefore the design objectives in 1 0 CER 50, Appendix I and the limits of REC 16.11.2.3 do not apply to 14C.

10 CFR 20.1301(a)(1) limits the annual TEDE dose to the Member of the Public to 100 mrem.

78 10 CFR 50, Appendix I, section II, paragraph C NUREG-1301, REC3.11.2.3 Page5Gof7S INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 40 CER 190.10(a) limits the total annual dose tram the uranium fuel cycle to the Member of the Public to 25 mrem to the whole body or any organ. 40 CFR 190 is implemented by REC 16.11.3.1. This limit includes dose from the release of gaseous effluents to areas at or beyond the Site Boundary, the dose from gaseous effluents due to activities within the Site Boundary, and the dose from direct radiation. The methodology for calculating the total annual dose from the uranium fuel cycle is provided in Section 4.

10 CFR 72.104 requires that the annual dose equivalent to any real individual who is located beyond the controlled area must not exceed 25 mrem to the whole body, 75 mrem to the thyroid and 25 mrem to any other critical organ as a result of exposure to planned discharges at radioactive materials and direct radiation from Independent Spent Fuel Storage Installation (ISFSI) operations. There are no radioactive effluents from the ISFSI. The HI-STORM UMAX Canister Storage System does not create any radioactive materials or have any radioactive waste treatment systems. COC Specification 3.1 .1, Multi-Purpose Canister (MPC), provides assurance that there are no radioactive effluents from the ISFSI.8° 14C is a weak beta emitter and does not contribute to direct radiation dose.

4) Estimation of 14C in Gaseous Effluents 4C exists in all PWR systems, and any location or system that contains tritium most likely also will contain 14C in some chemical form. Measurements of 14C concentrations in various liquid systems have been performed, and some of the reported data are included in EPRI TR-1 021106.81 As a general rule, 14C in the primary coolant is essentially all organic with a significant traction as a gaseous species. If the RCS liquid or gas is exposed to an oxidizing environment, such as during the forced oxidation during the shutdown evolution and during refueling outages, a slow transformation from an organic to an inorganic chemical form can occur.

Dissolved nitrogen gas and ammonia in the RCS could contribute to the 14C source term.

The dissolved nitrogen could become significant in the latter stages of the fuel cycle due to the introduction of increased quantities of non-borated water for boron dilution.

Callaway maintains a hydrogen gas overpressure on the RCS which effectively eliminates dissolved nitrogen gas and ammonia in the RCS, therefore the RCS ammonia concentration is assumed to be 0.82 In general, 14C is produced in light water moderated nuclear power reactors by 14N(n,p)14C reactions with nitrogen impurities in the coolant and by 170(n,a)14C reactions in the coolant. 14C produced in a nuclear power reactor can be released directly to the environment from the coolant in a gaseous form or in much smaller quantities as liquid 80 Certificate of Compliance No. 1040, Appendix A, Specification 5.1.

EPRI TR-1021106, Section 4.1 p 82 CDP-ZZ-00200, Appendix B. Table 1 .1, Reactor Coolant System-MODES 1, 2, 3, and 4, page 6 of 23 Page 57 of 75 IN FORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 effluents.83 Kunz estimated the fraction of 14C in liquid and solid wastes at <5% of that in gaseous discharges84. Regulatory Guide 1 .21 states that the dose contribution from 4C in liquid discharges is insignificant and evaluation of 14C released in liquid effluents is not required.85 The release and removal pathways from the primary coolant include VCT venting, boron dilution, inventory buildup on the letdown demineralizers and filters, and reactor coolant leakage. Letdown system removal is approximately 1 Ci/yr.86 The 14C production balance is shown in Figure 1.

Source Term- 4C Production System Inventory Gaseous Release RCS Solid Release Waste Gase System Waste Gas System Liquid Release Fuel Pool Primary System IX resins &

Containment Vent RWST tillers Containment Purge Discharge Monitor Tanks Radwaste Systems Fuel pool IX resins & tilters Aux. Bldg. Ventilation IX resins Radwaste IX resins Fuel Bldg Ventilation Filters Charcoal SF51_Canisters Figure 1: 14C Production Balance

5) Chemical Form of 14c in Gaseous Effluents Since the PWR operates with a reducing chemical environment, most, if not all, of the l4 species initially produced are in the reduced, i.e., organic, form and contain only a single carbon atom. Possible species include methane (4CH4), methanol (14CH30H),

formaldehyde (H214C=O or the gem-diol H214C(OH)2), and formic acid (H14COOH). In theory, the only ionic species produced will be formic acid (H14CO2H) and some or all of the formic acid will be removed by the letdown demineralizers. Formaldehyde is soluble in water and may partially be chemisorbed on the ion exchange resin. A quasi-equilibrium is established in the coolant between the initially produced species and other possible species in the reactor coolant. The most chemically reduced species and probably the most prevalent species is 14CH4 which partitions between the liquid and gas phases in the VCT and pressurizer.87 The airborne 14C released from PWRs is predominantly hydrocarbons (7595%), mainly methane (CH4), with only a small fraction IAEA Report 421, Section 3.1.3 Kunz, 1985 85 Regulatory Guide 7.21 rev. 2, section 1.09 86 EPRITR-1021106, Section 4.1 EPRI TR-1021 106, Section 4.1 Page 58 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 in the form of 002.8889 Regulatory Guide 1 .21 states that 140 releases in PWRs occur primarily as a mix of organic carbon and 002 in gaseous waste from the waste gas system.9° NUREG-001 791 concludes that 16.4% of the 14C produced in a PWR will be released via the waste gas processing system, and the remainder, 83.6%, from the Reactor Building and the Auxiliary Building.

Due to the presence of high temperature hydrogen recombiners in the Callaway waste gas system, 100% of the 140 released through the waste gas system is assumed to be released from the waste gas decay tanks in the oxidized, i.e., inorganic form as 002.

The 140 released from the unit vent is assumed to be in the reduced (organic) form as CH4, therefore 16.4% of the c produced is released through the Waste Gas Decay tanks (WGDT) as 002, and 83.6% is released via the Unit Vent as CH4.

C in Gaseous Discharges 16.4% 636%

Plant Vents Waste Gas System Containment Vent Waste Gas Decay Tanks Containment Purge 2

Aux Bldg Ventilation Fuel Bldg Ventilation Figure 2: 14C Gaseous Discharge Balance

6) 14C Source Term Estimation The neutron absorption cross section for the 170(n,a)14C reaction is shown in Figure 3.

The 170(n,o)140 reaction has a 1/v region and a significant high energy neutron cross section. Given a constant neutron flux and target concentration, the rate of production of a species, Na, in atoms per second is given by:

Na NT {(a1 (Pr) + (C9 (Pe) + (a1 (p)}

Where:

Na S the rate of production, atoms/sec 88 IAEA Report 421, Section 3.1.3 89 Neeb, section 4.2.4 ao Regulatory Guide 1.21, rev. 2, section 1.09 NUREG-0017, Section 2.2.25.2 Page59of7S IN FORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 17 NTis the number of or 4N target atoms per kg of coolant UtIS the effective neutron cross section for thermal neutron absorption, cm2 tPt is the thermal neutron flux, n/cm2-sec GelS the effective neutron cross section for epithermal energy neutron absorption, cm2 q is the epithermal neutron flux, n/cm2-sec a, is the effective neutron cross section for fast neutron absorption, cm2 Cp, is the fast neutron flux, n/cm2-sec ENDF/B-Vll 0-17 Principal cross sections 10 10 C,,

(0 io° 0

• 101 U,

U, U,

2 9 10 ci Energy (MeV)

Figure 3: ENDF/B VII Cross Sections for 170 Table 14: Effective Cross Section for the 170(n,a)14C Reaction in the PWR as a Function of Neutron Energy92 Neutron Group Group Energy Effective Cross Section Thermal sQ.625 eV 0.121 barns Epithermal (E) >0.625 eV <1 MeV 0.0291 barns Fast (F) 1 MeV 0.1124 barns The source term of each species A, is given by:

A0 (Ups) = N0 92 EPRI TR-1021 106, Section 4.3.2.2 Page 60 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 N° A A(MC1)=

3.7E4 Where Aa is the activity of species a, Na is the number of atoms of species a, Aa is the decay constant of species a, in seconds. The 140 production rate from the 170(n,a)14C reaction is calculated for the three group flux distribution according to:93 (1E-24. A N {(a) + (ee) +(UfOf)]

C production rate =

3.7E4 Where:

14C Production rate is 140 rate of production, iCi/sec- kg l7j N is the number of target atoms per unit mass of coolant (1 .27E22 atoms kg H20);

GtIS the effective neutron cross section for thermal neutron absorption, in barns; cot is the thermal neutron flux, n/cm2-sec; Ge is the effective neutron cross section for epithermal energy neutron absorption, in barns; CPe is the epithermal neutron flux, n/cm2-sec; u, is the effective neutron cross section for fast neutron absorption, in barns:

(t is the fast neutron flux, n/cm2-sec; LOE-24 is a units conversion factor, 1 .OE-24 cm2/barn; A is the 14C decay constant, 3.833E-12/sec; and 3.7E4 is a units conversion factor, 3.7E4 d/(sec- iCi).

The activity of 140 produced is thus the product of the production rate, the coolant mass in the active core region, and time:

A Production rate coolant mass time Where:

Avis the activity of 140 produced, in iCi; The coolant mass is the mass of water in the active core region, in kg, corrected for core average temperature and pressure; The time is the time period of reactor operation, in sec; The Callaway reactor is a Westinghouse Model F, four loop Pressurized Water Reactor (PWR) rated at 3565 MWth. The fuel is Westinghouse Vantage+ OFA with 1 93 fuel EPRI TR-1021106, Section 432.1 Page 61 of 75 IN FORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 assemblies. The mass of coolant in the active core region is 12,925 kg.94 The hydrogen gas overpressure in the Volume Control Tank (VCT) effectively eliminates N2 and NH3 in the RCS, therefore 4C production from the 14N(n,p)14C reaction is insignificant.

The core average neutron flux, the Effective Full Power Years (EFPY), and the fuel burnup are specific to the reactor operation for the period.

7) Inhalation Dose at the Nearest Residence Location from 14C The child age group is the critical age group for an airborne release of 4C due to higher inhalation dose factors and higher ingestion dose factors.95 The inhalation dose for the child age group, D, is calculated according to the expression96:

D=3.17E4R0 .DFA .Q X/Q Where:

D is the dose in mrem, to a member of the public from 4C, from the inhalation pathway, received by organ j; 3.17 E4 is the number of pCi/Ci divided by the number of sec/yr; Ra is the breathing rate for the child age group (3700 m3/yr);97 DFA, is the 14C inhalation pathway dose factor for organ j, appropriate to the child age group (mrern/pCi). For 4C, the limiting organ is the bone. The DFAbofle for the child age group is 9.70E-6 mrem/pCi, and the DFAtotai body for the child age group is 1 .82E-6;98 0 is the quantity of 14C produced during the year (Ci/yr); and X/0 is the highest calculated annual average concentration at the nearest receptor location (sec/rn3).

The inhalation dose to the bone for the child age group at the Nearest Residence location is:

Db = 1138Q, .X/Q The inhalation dose to the total body for the child age group at the Nearest Residence location is:

D00, body = 213 . X/Q Westinghouse Calculation Note CN-TA-02-135, Callaway (SOP) RSG IGOR/RETRAN Base Deck, May 16, 2003 Regulatory Guide 1.109, Table E-9, and Table E-13 Regulatory Guide 1.109, equations 0-3 and 0-4.

Regulatory Guide 1.109, Table E-5 Regulatory Guide 1109, Table E-9.

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APA-ZZ-0l 003 Rev. 022

8) Dose from 4C in Fresh Leafy Vegetation The concentration of 140 in leafy vegetation is calculated by assuming that the 14C ratio to the natural carbon in the vegetation is the same as the ratio of 140 to natural carbon in the atmosphere surrounding the vegetation.99 Only 140 released in the oxide form (CO or 002) is incorporated into the plant material.100 All 140 released from the waste gas decay tanks is assumed to be in the organic form, as 002. The inorganic form, e.g., CH4, is not incorporated into plant material, therefore, only the organic form, e.g., 002 contributes to the ingestion dose pathway. 14002 released outside the growing season or at night is not incorporated into plant material and does not contribute to the dose from the ingestion pathway. 1400 released during the growing season in the daytime is assumed to be incorporated into the plant material and contributes to the ingestion dose pathway. The growing season in mid- Missouri is approximately April 1- November The concentration of 140 in leafy vegetation is given by:102 3.17E7Q, .X/Qo1; Conc =

0.16 Where:

Conc, is the concentration of 140 in leafy vegetation grown at the nearest receptor location (pCi/kg);

3.17E7 is equal to (1 El 2pCi/C)(l E3g/kg)/(3.l 5E7 sec/yr);

Q1 is the quantity of 140 released as 002 during periods of photosynthesis (Ci/yr);

X/Q is the highest calculated annual average concentration at the nearest receptor location (sec/rn3);

0.11 is the fraction of total plant mass that is natural carbon, dimensionless; and 0.16 is the concentration of natural carbon in the atmosphere (g/m3).

Substitution of constants yields:

Conç =2.2E7*Q X/Q The leafy vegetation ingestion dose for the Child age group at the nearest receptor location is given by:103 D =DFI.J *U0 Conç,

Regulatory Guide 1.109, Appendix C 100 Regulatory Guide 1.109, Appendix C 101 Hammer, G. R.

102 Regulatory Guide 1.109, equation C-8 103 Regulatory Guide 1.109, equation C-13 PageG3of75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Where:

D is the annual dose to the bone or total body for the child age group from ingestion of fresh leafy vegetation, (mrem/yr);

DFI is the ingestion dose conversion factor for the maximum exposed organ. For the child age group, the bone is the maximum exposed organ. The DFlbone 5 1 .21 E-5 mrem/pCi ingested and the DFltotai body is 2.42E-6 mrem/pCi ingested;104 t is the traction of leafy vegetation grown in the garden at the nearest receptor location. f1 1 0.105 and Ua is the ingestion rate of leafy vegetation. For the child age group, Ua = 26 kg/yr.106

9) Dose from 14C in Milk The concentration of 14C in milk is determined as107:

COflC ilk = Fm Conc .

Where:

COflCmiIk is the concentration of 14C in milk, in pCi/L; Fm is the average fraction of the animals daily intake of 14G which appears in each liter of milk, in days/L. For cow milk, Fm IS 1.2E-2 days/L.108 For goat milk, Fm is 0.10 days/L;109 Concv is the concentration of 14C in leafy vegetation grown at the receptor location (pCi/kg), as described above; QF is the amount of feed consumed by the animal per day, in kg/day. For cows, OF is equal to 50 kg/day and for goats OF is equal to 6 kg/day;11° t, is the average transport time of the 4C from the feed into the milk and to the receptor (a value of 2 days is assumed): and A is the radiological decay constant for 4C, 3.32E-7 days1.

The dose from 14C in milk is determined as:

D = DFI U0

. COflC uk Where:

104 Regulatory Guide 1.109, Table E-13 105 Regulatory Guide 1.109, Table E-15 106 Regulatory Guide 1.109, Table E-5

° Regulatory Guide 1.109, equation C-JO

° Regulatory Guide 1.109, Table E-1 Regulatory Guide 1.109, Table E-2 Regulatory Guide 1.109, Table E-3 Page 64 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 D is the annual dose to the bone or total body for the child age group trom milk ingestion, (mrem/yr);

DFI is the ingestion dose conversion factor for the maximum exposed organ. For the child age group, the bone is the maximum exposed organ. The DFIbofle 15 1 .21 E-5 mrem/pCi ingested and the DFItotai body is 2.42E-6 mrem/pCi ingested;111 and U3 is the ingestion rate for milk. For the child age group, U3 =330 L/yr (for both cow and goat milk).112

10) Dose from 4C in Meat The concentration of C in meat is determined as113:

332E-7)

Conc01 = 3.1E-2Conc *50e2° Where:

COflCmeat is the concentration of 14C in meat, in pCi/kg; 3.1E-02 is the stable element transfer factor, in days/kg, for beef 114 COflCv is the concentration of 14C in leafy vegetation grown at the receptor location (pCi/kg), as described above; 50kg/day is the amount of feed consumed by the beef animal per day;115 20 days is the average time from slaughter to consumption116: and 3.32E-7days1 is the radiological decay constant for 14C.

The dose from 14C in meat is determined as:

D = DFI U0 COflCmeot Where:

O is the annual dose to the bone or total body for the child age group from milk ingestion, (mrem/yr);

OF! is the ingestion dose conversion factor for the maximum exposed organ. For the child age group, the bone is the maximum exposed organ. The DFlbone is 1 .21 E-5 mrem/pCi ingested and the DFItotai body is 2.42E-6 mrem/pCi ingested;117 and U3 is the ingestion rate for meat. For the child age group, Ua =41 kg/yr.118 Regulatory Guide 1.109, Table [-13 112 Regulatory Guide 1.109, Table E-5 13 Regulatory Guide 1.109, equation C-12 114 Regulatory Guide 1.109, Table [-1 115 Regulatory Guide 1.109, Table [-3 16 Regulatory Guide 1.109. Table [-15 117 Regulatory Guide 1.109. Table [-13 Page 65 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022

11) Dose to the Member of the Public from Activities within the Site Boundary The Member of the Public performing activities within the Site Boundary is described in Section 4. The ingestion dose pathways do not exist within the Site Boundary. 4C is not a gamma- emitting nuclide; therefore the ground plane pathway is negligible.

The inhalation dose, D, is calculated according to the expression119:

01= 3.1 7E4*R0 *DFA1 *Q, X/Q*1.26E-f Where:

D is the dose in mrem, to a member of the public from 14C, from the inhalation pathway, received by organ j; 3.17 E4 is the number of pCi/Ci divided by the number of sec/yr; Ra is the breathing rate for the adult age group (8000 m3/yr);12° DFA1 is the 140 inhalation pathway dose factor for organ j, appropriate to the adult age group (mrem/pCi). For 14C, the limiting organ is the bone. The DEAbone for the adult age group is 2.27E-6 mrem/pCi, and the DFAtotai body and DFAthyrOjd is 4.26E-7 mrem/pCi.12 Q is the quantity of 140 produced during the year (Ci/yr)

X/Q is the highest calculated annual average concentration for activities within the Site Boundary, as shown in Table 10.

1 .26E-1 is the fraction of the year the farmer performs activities within the Site Boundary (11 00 hrs18760 hrs), dimensionless.

118 Regulatory Guide 1.109, Table E-5 119 Regulatory Guide 1.109, equations 0-3 and C-4 120 Regulatory Guide 1.109, Table E-5 121 Regulatory Guide 1.109, Table E-7 Page 66 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022

72) Alternate Methodologies Regulatory Guide 1 .21 states that the following methods are acceptable for estimating the production of 14C:122

• Sampling and analysis of effluent streams

• Use of normalized 4C source term and scaling factors based on power generation, e.g., NCRP Report 81123

• Use of the PWR GALE code124 Callaway Plant effluents have not been sampled for 14C. NCRP Report 81, Table 3.3 states that the total 14C production rate for a PWR without reactor coolant nitrogen is 6 Ci/GWe-yr. Assuming a conversion of 0.34 GWe!GWth, the expected 14C production rate is 2 Ci!GWIh-yr or 7.2 CiJEFPY for Callaway, which is significantly lower than the quantity of 14C calculated using the EPRI methodology. The PWR GALE code does not calculate the quantity of 14C produced, but instead assigns a value of 7.3 Ci/yr for every PWR without regard for power level, reactor coolant nitrogen concentration, or waste gas system design and operation. Again, this is significantly lower than the quantity of 14C calculated using the EPRI methodology. For example, using the EPRI methodology and the neutron flux distribution for Cycle 18, the 14C production for Callaway is 13.2 Ci/EFPY.125 The 14C production calculated using the EPRI methodology is therefore conservative with respect to the methodologies mentioned in Regulatory Guide 1 .21, rev. 2.

The EPRI methodology also provides for a PWR proxy calculation. The average 14C production rate for Westinghouse PWRs is 3.4 Ci! GWIh- yr126. Callaway is rated at 3.565 GWth (3565 MWIh), therefore, the 14C production rate based on the proxy PWR is 12.1 Ci! EFPY. The 14C production calculated using the EPRI proxy methodology is therefore conservative with respect to the acceptable methodologies described in Regulatory Guide 1.21, rev. 2.

122 Regulatory Guide 1 .21, Section 1.9 123 NCRP Report 81 124 NUREG-0017 125 HPCI 11-02 EPRI TR-1021106, Section 4.8 and Appendix D Page 67 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Appendix B: Record of Revisions127 Rev. No. 0 Date: March 1983 Rev. No. 7 Date: November, 1983 Revised to support the current RETS submittal and to incorporate NRC Staff comments.

Rev. No. 2 Date: March, 7984 Revised to incorporate NRC Staff comments Rev. No. 3 Date: June, 1985 Revised to incorporate errata identified by ULNRCOO8O3 and changes to the Environmental Monitoring Program. Incorporate results of 1984 Land Use Census.

Rev. No. 4 Date: February, 7987 Minor clarifications, incorporated 31 -day projected dose methodology. Change in the utilization of areas within the Site Boundary.

Rev. No. 5 Date: January, 1988 Minor clarifications, revised descriptions of liquid and gaseous rad monitors, revised liquid setpoint methodology to incorporate monitor background, revised dose calculations for 4OCFR19O requirements, Revised Table 6 and Figures 5.JA and 5.1B to refine descriptions of environmental TLD stations, incorporated description of environmental TLD testing required by Reg. Guide 4.13, revised Tables 1, 2, 4 and 5 to add additional nuclides, deleted redundant material from Chapter 6.

Rev. No. 6 Date: May, 1989 Revised methodology for calculating maximum permissible liquid effluent discharge rates and liquid effluent discharge rates and liquid eftluent monitor setpoints, provided methodology for calculating liquid effluent monitors response correction factors, provided an enhanced description of controls on liquid monitor background limits, provided additional liquid and gaseous dose conversion factors and bioaccumulation factors (Tables 1, 2, 4 & 5), provided description of the use of the setpoint required by Technical Specification 4.9.4.2 during Core Alterations, added discussion of gaseous and liquid monitor setpoint selection in the event that the sample contains no detectable activity, added minimum holdup requirements for Waste Gas Decay tanks, revised dispersion parameters and accompanying description per FSAR Change Notice 88-42.

APA-ZZ-07 003 Rev. No. 0 Date: August, 1989 Radiological Effluent Technical Specifications were moved from the Callaway Plant Technical Specifications to Section 9.0, Radioactive Effluent Controls, of the ODCM per NRC Generic Letter 89-01. At the same time, in order to formalize control of the entire ODCM, it was converted to APA-ZZ-01003, Off site Dose Calculation Manual.

127 Section numbers, table numbers, etc. refer to the numbering schema used in the particular revision.

Page 68 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Rev. No. 1 Date: October, 1990 Revise Action 41 of Table 9.2-A to allow continued purging for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per Amendment 20 to operating license, issued 4/10/87.

Rev. No. 2 Date: May, 1991 Section 2.4.2: Changed gross alpha analysis frequency from each batch to a monthly composite per Table 9.3-A, and the Callaway Plant NPDES permit (reissued March 15, 1991).

Rev.No. 3 Date: June,1993 Deleted HF-RE-45 and LE-RE-59 as effluent monitors. Revised table numbering for consistency with those in Section 9.0, deleted redundant material, incorporated 1992 Land Use Census results, moved LLD description to Attachment 1, moved REC Bases to Attachment 2. Deleted reporting requirements for solid radwaste, which are described in APA-ZZ-07 011, Process Control Program. Addressed compliance with 10 CFR 20.1301. Revised the dilution flow rate to allow values other than 5000 gpm, based on dilution flow monitor setpoint. Revised MPC terminology to ECV. Added Action 46 to REC 9.2 to clarify actions for inoperable mid and high range WRGM Channels. Revised references to be consistent with the revised 10 CFR 20.

Added Appendix A. Revised Action 41 of Rec 9.2 and the operability requirements of GT-RE-22/33. Incorporated the revised R1 values in Tables 3.2 and 3.3. Added Section 6.2 and Table 6.5.

Rev. No. 4 Date: September, 1994 Increased the minimum channels OPERABLE requirement of REC 9.2 for GT-RE-22 & 33 from 1 channel to 2 channels. Revised Action 41 and the Bases for REC 9.2 accordingly. Incorporated the operability requirements from Tech Spec 3.9.9 into the Action statement for clarity. (Refer to CARS 199401176).

Rev. No. 5 Date: February, 1995 Removed the REMP station locations. Removed particulate nuclides with a halt-life of less than 8 days from Tables 3.2-3.4 and removed 14C, 32P, 63Ni, and l25mTe from Tables 2.1, 2.2, 3.2, 3.3, and 3.4. Changed the reporting frequency of the Effluent Release Report from semiannual to annual. Removed the meat, milk and vegetable pathway dispersion parameters from Tables 6.1, 6.2, and 6.3, and clarified the applicability of the dispersion parameters and dose locations in Table 6.4. Relocated REC 9.1 and 9.2 to the FSAR. Revised footnotes 3 and 7 of Table 16.11-4 to require additional sampling of the Unit Vent in the event of a reactor power transient, only if the Unit Vent noble gas activity increases by a factor of 3 or greater. Added Section 4.7.3.1.3 for determination of dose due to the on-site storage of low level radioactive waste.

Rev. No. 6 Date September, 7996 11Dm Section 2:_Added dose factors (A)for Ag, 237Np, 238Pu, 239240Pu, 241Pu, 241Am, 242Cm, and 2342Cm to Table 2.1, and Bioaccumulation Factors (Bf) for Ag, Pu, Am, and Cm to Table 2.2 due to a change in the liquid radwaste treatment process. Revised the description of the methodology for performing the 31 day dose projection in Section 2.5. Revised the maximum allowable background for HB-RE-1 8. Section 3: Eliminated Dimy and DDmTc from Table 3.4 (Meat Pathway) due to a half-life of < 8 days. Substituted the phrase more restrictive in lieu of lesser in Section 3.2. Revised the definition of Fa in equation 3.1. Added description of use of samples to verify dose rates in Section 3.3.1.2. Augmented the definition of q in Section 3.3.2.7. Edited PageG9of75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 equations 3.13 and 3.14 and added equation 3.15 to clarify dose calculations. Revised the methodology for performing the 31 day dose projection in Section 3.4. Section 4: Strengthened the discussion of the reevaluation of assumptions in Section 4.1.3. Section 6: Added new Table 6.6 to describe the selection and use of dispersion parameters during the preparation of the Effluent Release Report. Updated Tables 6.1 and 6.2 to reference the 1995 Land Use Census.

There were no changes in the receptor locations. Section 8: Replaced the reference to HDP-ZZ-04500 to a more generic reference to the plant operating procedures, due to change in organizational structure and responsibilities. Section 9: (1) Eliminated 9.0.7 and 9.0.2 due to redundancy with Technical Specifications 3.0.1 and 3.0.2; (2) Revised Table 9.3-A to incorporate sampling and analysis requirements for TRU nuclides in liquid effluents; (3) Eliminated sampling of Fuel Building Exhaust from Table 16.11-4 and the associated footnotes due to redundancy with Unit Vent sampling; revised the continuous sampling requirements for the gaseous batch release points consistent with plant design; revised the 3H analysis frequency for Purges from weekly to prior to each purge; and, (4) Revised the air sampling station location criteria on Table 9,11-A and footnote # 1, and eliminated footnote #3 in order to be less generic and more descriptive of the parameters used in determining the station locations (See CARS 199502280).Revised the location requirements for milk and vegetables.

Revised description of use of baseline samples to trigger gamma isotopic analysis in footnote #4, revised requirement for location of downstream sample station in footnote #6. Revised Surveillance Requirement 9.10.2.1 to eliminate liquid effluents from the surveillance. (5)

Revised REC 9.5 and REC 9.9 to eliminate exceptions for partially tested effluents being released in excess of the respective limit. Section 17: Added reference 11 .14.1 3.Attachment 2: Revised the Bases for REC 9.10 to support the elimination of liquid effluents from Surveillance 9.10.2.1.The remaining changes are editorial in nature and have no technical impact.(This revision implements CARS 799502055, CARS 799600167, CARS 199600961, CARS 199502280, and CARS 799600986).

Rev. No. 7 Date February, 1997 Section 9: (1) REC 9.5, Liquid Radwaste Treatment System, Action statement: Eliminated reference to COMN 7167. (2) Table 9.17-A, items 4a (milk) and 4c (vegetation): revised to required control stations in the least prevalent wind direction. (See CARS 199700166) Appendix A: revised the discussion relative to the appropriate gross alpha Effluent Concentration Value.

Rev. No. 8 Date May, 1997 Section 1: The Purpose and Scope was revised to describe the split of the ODCM into two sections Per FSAR Change Notice 95-058. Section 2: Sections 2.2 and 2.3 were revised to clarify the use of nuclide- specific alpha activity vice gross alpha activity for setpoint determination. Section 2.5 was revised to delete the description of the Liquid Radwaste Treatment System. Section 6: Tables 6.1, 6.2, and 6.3 were revised to reflect the results of the 1996 Annual Land Use Census. Section 7: The reporting requirements for the Annual Radiological Environmental Operating Report and the Effluent Release Report were relocated to the FSAR Per FSAR Change Notice 95-058. Section 9: RECs and the supporting Attachments 1 and 2 were relocated to the FSAR Per FSAR Change Notice 95-058. Appendix A: Appendix A was deleted. Editorial changes were made throughout the ODCM reflecting the relocation of the RECs to the FSAR.

Rev. No. 9 Date March, 1998 Page 70 of 75 INFORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Section 2.5: Revised projected liquid dose calculation to use previous 31 day cumulative doses.

Section 3.1.1: Added GLRE-202, Laundry Decon Facility Dryer Exhaust Monitor. Added action to be taken when the particulate and/or iodine grab sampler is not operable. Section 3.2: Added setpoint calculation for GL-RE-202. Section 3.2.1 and 3.3.2.2: Changes were made to correct typographical errors and have no technical impact. Section 3.4: Revised projected gas dose calculation to use previous 31 day cumulative doses. Section 3.5: Removed the word secular from secular equilibrium since the equilibrium mode could be secular or transient depending on the isotope. Table 6.2: Added Laundry Decon Facility Dryer Exhaust to title of table since these will be the dispersion factors used for this release point.

Rev. No. 10 Date December 20, 1999 Section 3.1: Added explanation that GL-RE-202 only monitors particulate. Section 3.2:

Changed Laundry Decon Facility Exhaust Monitor setpoint to less than or equal to 2000 cpm above equilibrium background with a maximum allowed background of 2000 cpm as calculated in HPCI 99-05. Tables 6.1 6.2, 6.3: Updated values as calculated in HPCI 99-02. Section 5.1:

Defined how REMP sample locations were determined. Removed reference to Plant Operating manual since it no longer exists.

Rev. No. 11 Date December 22, 1999 Changes required to go from old Technical Specifications to Improved Technical Specifications (ITS). Technical Specification 4.9.4.2 changed to FSAR 16.11.2.4.1. Technical Specification 6.8.4.Fchangedto FSAR 16.11.4. Technical Specification 6.8.1.Fchangedto Improved Technical Specification 5.4.1. Technical Specification 6.14 changed to Improved Technical Specification 5.5.1. Technical Specification 6.8.4.E changed to Improved Technical Specification 5.5.4. Technical Specification 6.9.1.6 changed to Improved Technical Specification 5.6.2.

Technical Specification 6.9.1.7 changed to Improved Technical Specification 5.6.3. Changed name of Annual Radiological Effluent Release Report to Effluent Release Report as stated in ITS.

Added liquid releases are limited to 10 times the Appendix B, Table 2, Column 2 limits Per FSAR CN 98-041 supporting implementation of ITS.

Rev. No. 12 Date December 01, 2000 Section 2.1 and 2.2.1: Updated JOCFR2O, Appendix B, Table II, Column 2 reference to the new 1 OCFR2O format. Corrected typo for f, flow setpoint should be undiluted waste flow rate.

Section 3.2.1: Corrected typo, default value for safety factor should be 0.1. Section 5.1: Updated crosscheck program used to EML since EPA program is no longer available. Section 6.2: Added vertical height of highest adjacent building used to perform concurrent year annual average atmospheric dispersion (XJQ) calculations and reference for this value. This information should be documented in the ODCM. Added responsibility for validation of meteorological data, since responsibility has changed from engineering to HPTS. Section 10.1.1: Revised to require a summary of Major Radwaste System changes to be included in the annual report. This was done to be consistent with FSAR 16.11 .5.2.Several changes were made throughout the procedure to correct typographical errors and have no technical impact.

Rev. No. 13 Date September 19, 2002 Section 3.2: Revised to implement the approved OL 1218, Rev. 1; License Amendment no. 152 allowing equipment hatch and emergency air lock to remain open during refueling activities (FSAR CN-01 -030 and CNO2-049). The amendment eliminated FSAR 16.11.2.4.1B and Page 71 of 75 IN FORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 subsequently deleted the core alteration setpoint value 5.0 E-3 pCi/cc for Containment Purge Monitors GT-RE-22 and GT-RE-33. The alarm setpoints for the Containment Purge Monitors will be based on the methodology described in Section 3 of the ODCM.

Rev. No. 14 Date June 17, 2003 Revised Table 2.1 (Ingestion Dose Commitment Factor for Adult Age Group) to include dose factors for Pr-i 44. (CARS 200303251).Revised Section 4.1.3.1 to adjust the Farmers residence (critical receptor) from 3830 meters in the SE sector to 2897 meters in the NNW sector. The Farmers residence (critical receptor) was changed in 2002 to a location directly across the street from the Nearest residence. For conservatism and ease in calculation, Table 6.1 and 6.2 were revised making the distances and dispersion parameters for the Farmers residence (critical receptor) and the Nearest residence the same. Revised section 7.2 to reference Table 6.6.

Revised section 10.2.2 to remove the requirement for QA department review of the ODCM for reach revision (CARS 200304509). Added a reference to 11.14.14, Calculation HPCI 03-004 (Rev. 0), Calculation of Liquid Effluent Dose Commitment factor for Pr-144 (AT) for the Adult Age Group, June, 2003.

Rev. No. 15 Date December 9, 2004 Reformatted references to FSAR-SP Chapter 16.11 in section 1,2.1.1,2.1.2, 2.2.1, 2.3, 2.4.2, 2.5, 2.6, 3.1, 3.2.1, 3.5, 5.1, 7.1, 7.2, and 9. References to 63Ni were added to section 2.2.1 for the calculation of ECVSUM, section 2.3, and described in section 2.6 since it is an exception to non- gamma emitters not listed in FSAR-SP Table 16.11-1. 63Ni was added to the ODCM based on previous 1 0 CFR 61 sample results and 2 quarter liquid composite analyses. Consolidated references listed in section 2.4.2 and 2.6 for the site related ingestion dose commitment factors (Aot Table 2.1 into HPCI 04-06, Revision 1. References to HPCIs95-004 (Ref: 11.14.13) and 03-004 (Ref: 11.14.14) were deleted and replaced with HPCI 04-06, Revision 1 which is now listed as Ref: 11.14.13. Added 63Ni and 122Sb to Table 2.1- INGESTION DOSE COMMITMENT FACTOR (AT) FOR ADULT AGE GROUP. Revised the reference for Table 2.1 to 11.14.13.

Corrected a typo in section 3.1.2 referring to the Radwaste Building Vent system designator as GT vs. GH (CAR 200406851). References 11.19 and 11.20 were deleted in section 4.1.3.1.1.

Reference 11.18 was changed to MICROSHIELD (Grove Engineering, Inc.) vs. ISOSHLD.

Reference 11.24 in section 4.1.3.1.3 was corrected to 11.18. Section 5.1 and 5.2 were revised to indicate that the Radiological Environmental Monitoring Program TLDs will be processed and provided by a vendor laboratory beginning in the first quarter of 2005. Section 5.2 was revised to delete reference 11.14.10 which refers to HPCI 88-08, Performance Testing of the Environment TLD System at Callaway Plant, August 1989. Reference 11 .14.7 was corrected with HPCI 87-10 vs. 88-10. Revised Table 6.1, Note (c) to reference FSAR Table 2.3-83 vs. Table 2.3-82.

Revised Table 6.1 and 6.2 Note (b) to reference data is from the 2002 Land Use Census.

Changed and/or corrected the Skin dose factor (Li) units in Table 3.1 (Dose Factor for exposure to a Semi-Infinite Cloud of Noble Gases) to mrem/yr per uCi/m3. Revised section 3.3.1.2: Added units for the term BR in m3/yr. Removed paragraph in section 3.3.2.2 that describes actions for implementing the use of appropriate values. This paragraph was taken directly from section 5.3.1 of NUREG 0133, U.S. Nuclear Regulatory Commission, Preparation of Radiological Effluent Technical Specification for Nuclear Power Plants, USNRC NUREG-Ol 33, Washington, D.C. 20555, October, 1978. This paragraph does not apply since the use of pathways is already considered as described in sections 4.1.2 and 4.1.3.1. Revised note (C) of Table 6.1 to reference FSAR-SA Table 2.3-83. Revised note (a) from Table 6.1 to reference FSAR-SA Table 2.3-82. In addition, revised Note (b) from Table 6.1 to reference data taken from the 2002 Land Use Page 72 of 75 IN FORMATION USE March, 2017

APA-ZZ-01 003 Rev. 022 Census. Revised Notes (a) and (c) from Table 6.2 to reference FSAR-SA Table 2.3-84 and 2.3-81 respectively. Added a 0.95 conservatism factor to section 2.2.3 Calculation of Liquid Effluent Monitor Setpoint. This will conservatively reduce the liquid monitor setpoint to further ensure the section 4.4.1 of NUREG 0133, U.S. Nuclear Regulatory Commission, Preparation of Radiological Effluent Technical Specification for Nuclear Power Plants, USNRC NUREG-0133, Washington, D.C. 20555, October, 1978 which states the alarm and trip setpoints for each instrument channel listed in Table 3.3-1 1 should be provided and should correspond to a value(s) which represents a safe margin of assurance that the instantaneous liquid release limit of 10 CFR Part 20 is not exceeded. A determination was made lAW T/S 5.5.1 that the associated changes with Revision 15 maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50 Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

Rev. No. 16 Date December 1, 2005 Section 5.1 was revised to remove an invalid requirement that a third-party laboratory performing analysis specifically state the Interlaboratory Comparison (crosscheck) requirements for the Radiological Environmental Monitoring Program (REMP) contract lab. Reference 11.14.14 to Reg. Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Normal Operations)- Effluent Streams and the Environment, was added to provide supporting documentation for contract lab lnterlaboratory Comparison requirements. Additional information on REMP contract lab participation in Interlaboratory Comparisons was also added in section 5.1.

(CAR 200500891) Revised reference 11.14.7 by adding normalization and standardization factors for radionuclides listed in Table 2.1 of the ODCM that were not included in the original calculation.

Added section 4.1 .3.1 .4 to describe direct dose to a Member of the Public from the Old Steam Generator Storage Facility (OSGSF). Reworded step 4.1.2 to describe the sources of direct radiation from outside storage tanks to storage of radioactive material. Revised section 4.1.3.1.2 to include and describe direct dose calculations in support of Modification 03-1008, Equipment Hatch Platform and Missile Shield Modification. Reference 11.14.10 was added to reference direct dose calculation to the Member of the Public from Modification 03-1008. Revised section 4.1.3.1.3 to include and describe direct dose calculations from the Radwaste Yard RAM storage and Stores II. Reference 11.19 and 11.20 were added to reference direct dose calculations to the Member of the Public from RAM storage at Stores II and the Radwaste Yard. A determination was made lAW T/S 5.5.1 that the associated changes with Revision 16 maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50 Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

Rev. No. 17 Date March 14, 2007 Section 2.4.1 was revised Per CAR 200701309 to state that no potable water intakes exist within 10 miles of the plant discharge point. This is due to the fact that the Annual Land Use Census ensures no newly developed potable water intakes within 10 miles of the plant discharge Per FSAR-SP Chapter 16.11 .4.2c. Section 2.4.2 was revised to add reference 11.6.18 to CAR 200700053 which provides documentation of an evaluation of the site specific mixing factor for liquid effluents. Modification 06-0061 reconfigured the plant discharge terminus at the Missouri River. The modification was completed in January 2007.

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APA-ZZ-01 003 Rev. 022 Revised Table 6.5 was revised to reflect upgrade/replacement of the primary meteorological tower instrumentation as per Modification Package 04-1020. Section 2.4.2 was revised to remove the discussion of the nearest municipal potable water intake downstream from the liquid effluent discharge point as being located near the city of St. Louis, Missouri, approximately 78 miles downstream. Since the Land Use Census annually verifies no potable water intakes within 10 miles this discussion was deemed inappropriate in describing methodology for calculating dose to the public from liquid effluents. In addition, the distance referenced as not having potable water intakes downstream of the plant discharge was changed for consistency with section 2.4.1 and the Land Use Census.

Rev. No. 19 Date August, 2072 Converted to Word 2010, including appropriate formatting changes and cross-referencing for the conversion. Deleted all references to the obsolete Commitment Tracking System (COMN) and all hidden text for the obsolete hidden text referencing system. Added level of use. (CAR 201104163, Action 1) Section 3.4- Added dose reduction controls for discharge of 14C from the waste gas system and defined the growing season. Section 3.5- Deleted statement that non- gamma emitting nuclides not listed in the FSAR-SP Table 16.11.4 are not considered in dose calculations. Eliminated Sections 4.1.3.1.1, 4.1.3.1.2, 4.1.3.1.3, and 4.1 .3.1.4- direct radiation dose is negligible; refer to HPCI 1 2-06. Section 5.2- changed to allow use of dosimeters other than TLDs. Section 6.1- Deleted discussion of short- term XJQ processing and the slope factor and deleted the associated table of S factors. Section 6.2- Deleted designation of responsibilities for met data review. (CAR 201104163, Action 1) Section 10.2- changed to align with T/S 5.5.1. CAR 2011041 63, Action 2) Corrected the department title to align with organizational structure. (CAR 201104163, Action 1). Table 10 and Table 11- The dispersion parameters for the Farmers residence were removed. As a first approximation, the dispersion parameters for the Nearest Residence will be used for the Farmers residence. Appendix A-Appendix A was added to describe the calculation of the production of 14C and the calculation of dose from 14C in gaseous effluents. (CAR 201104163) 63Ni was added to the gaseous effluent inhalation pathway and ingestion pathways dose factor tables. Values for 63Ni are from APA-ZZ 01003, rev. 4. (CAR 201104197). Adult ingestion dose factors removed. Ingestion dose pathway removed from Table 13 for activities inside the Site Boundary.

Rev. No. 20 Date April, 2015 Revised Table 10 to implement the recalculated dispersion parameters using 2009- 2013 meteorology. Deleted Table 11 as described in HPCIJ5O3. Added HPCI15O2, HPCI15O3, HPCI15O4, & HPCI15O5 as references. Deleted reference to ZZ-67. Added ISFSI to Appendix A, Figure 1. Revised Section 6 to describe the recalculation of the long- term dispersion parameters.

Deleted Section 8; following sections were renumbered accordingly.

Rev. No. 21 Date May, 2015 Revised Table 10 to correct the dispersion parameters for the Site Boundary and Nearest Resident locations and edited to two significant digits for consistency with the remainder of Table

10. (CAR 201502908)

Rev. No. 22 Date March, 2017 The following changes implement CRs 201604927, 201602733, 201603668, and 201602733:

• The methodology used to calculate the A values was added to section 2.4.2.

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APA-ZZ-01 003 Rev. 022

• Default setpoint values for GTRE21B and GHRE1OB were added to section 3.2.

• Deleted the specific years of the meteorological data in section 6.1 and instead stated the dispersion parameters represent five years of on- site data to eliminate a potential error trap. The HPCI referenced in section 6.1 provides the necessary level of detail, including the years represented by the data.

• A footnote was added to section 6.1.2 to clarify that the farmer is a composite and not an actual person.

• Section 6.2 was revised to clarify the quality check of the meteorological data prior to processing.

• Section 10, Bibliography was revised to add new references and to update the revision level of CDP-ZZ-00200.

• 1265b was added to Table 1.

• Table 12 was revised to change the Farmers Residence to the Nearest Resident because the farming plots are now leased to multiple farmers and it is not feasible to calculate dose to multiple farmers residences. The footnote in Table 12 regarding 3H dispersion parameters was moved into the table. was added to Table 12.

• Appendix A was reformatted for better readability.

• Appendix A, Section 2, Assumptions was revised to clarify the assumptions, principally dispersion parameter use and the dose pathways and locations.

• Appendix A, Section 3, Applicable Dose Limits, was revised to add 10 CFR 72.104.

• Appendix A, Section 11, Dose to the Member of the Public from Activities Within the Site Boundary, was revised to eliminate the value of the )QQ for activities within the Site Boundary and to instead refer to Table 10 as the source for the XJQ. The three condensed form equations were likewise eliminated. This eliminated an error trap in that the XIQ could be revised and it may not be recognized that the specific value was stated in the text of Appendix A, Section 11.

• Appendix A, Section 12 was edited for readability.

• Formatting changes are not marked with revision bars.

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