Text

2018 Annual Radioactive Effluent Release Report, Revision 1
	ML19197A321
Person / Time
Site:	Callaway
Issue date:	07/16/2019
From:	; Ameren Missouri, Union Electric Co
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML19197A319	List: ULNRC-06523, 2018 Annual Radioactive Effluent Release Report, Revision 1;
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	ULNRC-06523
	Download: ML19197A321 (174)
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Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revision 1 Callaway Ene rgy Cen ter 201 8 Ann ual Rad ioac tive Effl uen t Release Rep ort Revision 1 Renewed Facility Operatin g License NPF-30 Docket Numbers 50-483 and 72 -1045

~'1-WAmeren I Callaway MISSOURI Ener!Jy Ce nter

Callaway Energy Center 2018 Annual Radioact ive Effluent Release Report Revision 1 Callaway Ene rgy Center 201 8 Annual Radioactive Effluent Rel ease Rep ort Revision 1 Renewed Facility Operatin g License NPF-30 Docket Numbers 50-483 and 72-1045

1. Introduc tion This Annual Radioactive Effluent Rele ase Report (ARERR) is submitted by Union Electric Co., dba Ameren Missou ri, in accordance with t he requirements of 10 CFR 50.36a and 10 CFR 72.44(d)(3), Callaway Energy Center Technical Specification 5.6.3, and HI-STORM UMAX Certificate of Compliance Section 5.1.c. This re port is for the period January 1, 2018 to December 31, 2018 .

The doses to the Member of the Public from all liquid and gaseous effluents discharged during the reporting period were small fractions of the NRC and EPA regulatory limits and the Radioactive Effluent Control lim its in the Offsite Dose Calculation Manual.

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revision 1 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 (REC) Table 16.11-1 and Table 16.:Ll-4. Gamma spectroscopy was the primary analysis technique used to determine the radionuclide composition and concentratio n 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.

2. Gaseous Effluent s The quanti ty of radioactive material released in gaseous effluents during the reporting period is summarized in Table A-1. The quarterly and annual sums of all radionuclides discharged in gaseous effluents are reported in Tables A-1A and A-1B . All gaseous effluent releases are considered to be ground level.

The quantity of 1~C released in gaseous effluents was calculated as described in EPRI Technical Report 1021106 1.

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 treatmef71t systems, Specification 3.1. 1, "Multi-Purpose Canister (MPC)",

provides assurance that there are no radioactive effluents from the ISFSl. 2

..J

Liquid Effluent s The quantity of radioactive material released in Ii.quid 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 w ere no continuous liquid discharges for the reporting per1od . Dilution by the Missouri River, in the form of the near- field dilution factor, is utilized in the QDCM dose calculation methodology .

1 Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, Technical Report 1011),06, Electric Power Research Institute, December, 2010 .

2 Certificate of Compliance No. 1040, Appendix A, Technical Specifications for the HI_STDRM UMAX Canister Storage System, Specification 5.1.

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revision 1

4. Solid Waste Storage and Shipments The volume and activity of solid waste shipped for disposal is provided in Table A-3 . Table A-3 is presented in the forhlat of rev. 1 to Regulatory Guide 1.21 because the data is not readily available in the format recommended by rev. 2 to Regulatory Guide 1.21.

5. Dose Assess1ne nts The annual evaluation of dose to the Member of the Public is calculated in accordance wlth the methodology and parameters in the ODCM and is reported in Tables A-4 and A-5 .

5. 1 Table A-4, Dose Assess ments, 1 0 CFR 50, Ap pendix 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 SO, 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 locat ion of the nearest resident with the highest value of D/Q, as described in the ODCM . The organ dose does not include the dose frohl 14 C, which is listed separately.

5.2 Table A-5, EPA 4 0 CFR 19 0 Individual in the Un r estricte d 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, t he dose reported in Table A-5 is the sum of the dose from gaseous effluents (at the Nearest Resident location and wit hin the Site Boundary), plus the dose contribution due to activities within the Site Boundary and the organ dose from inhalation of 14 C (at the Nearest Resident location and within the Site Boundary). The dose assessments in liable A-5 demonstrate compliance witl'l 10 CFR 20.1301(e) and 40 CFR 190.

6. Suppleme ntal Informatio n 6.1 Abnormal Releases or Abnormal Discharges There were no abnormal releases or abnormal discharges during the reporting period.

6.2 Non- ro utine Planned Discha rges 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.

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revision 1 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 Effluent Monitoring System Non- functionality BM-RE-52, Steam Generator srowdown Discharge Monitor, has been ngn - functional since 2010 when the surveillances were changed to on- demand . The procedures for performing discharges by this pathway were voided in 2007. The last discharge via this pathway was Q2 19863 ,

therefore the associated action statement has been met since BMRES2 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 Instrumentat ion and the associated discharge point from ODCM/FSAR-SP Table 16.11-1, Radioactive Liquid Waste Sampling and Analysis Program .

GT-RE-22, Containment Purge System Monitor, was non- functional for a period of approximate ly 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months to perform an instrument calibration. l1he containment purge valves were closed and there were no purges in progress during this time; therefore the associated action was met. GT-RE-22 was also non-function al for a period of approximate ly 3 days due to loss of flow requiring a motor replacement.

6.6 Offsite Do se Calculation Manual Changes The Offsite Dose Calculation Manual consists of two documents : APA-ZZ-01003 (Methodolog y and Parameters) and FSAR-SP Chapter 16.11 Radiological Effluent Controls (RECs) . Both were revise d in 2018. A complete copy of APA-ZZ-01003, rev. 23 and FSAR-SP Chapter 16 .11 are attached.with revision bars showing the areas of change.

The changes to APA-ZZ-01003, rev. 23 (J1:1ne 1 2018) incorporated the following changes :

Section 5.1 was revised to delete the phrase referring to HPCI 9901 because HPCI 9901 is obsolete. HPCI 1506, rev. 1, superseded portions of HPCI 9901, the remainder is superseded by HTP-ZZ-DTI-REMP-SMPL-SCHED, REMP Sample Locations and Analysis Schedule" . (CR 201705399)

Section 10, "Bibliography ", was revised to update the revision level of CDP-ZZ-00200, Appendix B, ANSI N42.18-2004 (redesignation of ANSI NB .10-1974), and HPCI 1604.

Table 1 was revised to add the Dose Commitmen t Factors for mmsn. (CR 201706108) s Callaway Plant Semiannual Rad ioactive Effluent Release Report, January- June 1986, Table 28.

Callaway En ergy Center 2018 Annual Radioactive Effluen t Release Report Revision 1 The changes to FSAR-SP Chapter 16.11 (RECs) were to revise "Operable" to "Functional" and "Specifications" to "Requirements" (LDCN 15-007 & LDCN 17-008) in accordance with NRC recommendations, and to allow the Annual Radioactive Effluent Release Report to be submitted in any format acceptable to the NRC (LDCN 17-006) in accordance with Regulatory Guide 1.21, revision 2. These changes were effective in June and August, 2018.

6. 7 Process Co ntrol Pr ogram Changes There was one revision t o APA-ZZ-01011, "Process Control Program" during the reporting period.

The changes were related to auditing requirements for vendors and did not affect significant aspects of the ODCM .

6. 8 Cor rec tio ns t o Previ ous Rep orts This report represents revision 1 to the original report (revision 0) submitted on April 30, 2019 under ULNRC -06504. Revision O omitted the data in Table A-1, Table A-lA, Table A-18, Table A-2, Table A-2A, Table A-4, and Table A-5 due to difficulties extracting the data. The omitted data is provided in this repor t.

FSAR-SP Chapter 16.11 (RE Cs), which constitutes one part of the Callaway Offsite Dose Calculation Manual, was inadvertently omitted from the original report. It is included in this r.eport.

Table A-3 to revision O of this report con tained errors due to erroneously report ing package volume vice waste volume. During the investigation, issues were also discovered with Table A-3 of the 2017 report. Th ese errors resulted from a 2017 shipm ent that was still in a "staged shipment" status in th e software when th e data for Table A-3 was generat ed for the AR ERR. The software does not consider shipments in "staged shipment" status when compiling the report.

The issues with Table A-3 are described in CR 201904190.

This report represents a full and complete 2018 Annual Radioactive Effluents Release Report and it provides a corrected Table A-3 for the 2017 report.

6.9 Othe r In formation Related to Ra dioactive Effluents Meteorological dispersion parameters, data recovery rate, and Joint Frequency Tai-lies for the monitoring period are attach ed as Appendix B.

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revision 1 Appen dix A Tables of Quanti ties Releas ed in Liquid and Gaseou s Radioa ctive Effluen ts and in Solid Radioa ctive Waste Shipm ents Tables of Doses from the Discha rge of Liquid and Gaseou s Radioa ctive Effluen ts

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revision 1 Table A-1: Gaseous Effluents- Summation of All Releases Summation Estimated Quarter Quarter ,Quarter Quarter of All Unit Total Uncertainty 1 2 3 4 Releases (%)4 Fission &

Activation Ci 5.03E-02 l .17E-01 4.67E-02 6.SSE-02 2.80E-01 20 Gases Ai'e rage Release µCi/s 6.38E-03 l.48E-02 S.93E-03 8.31E-03 8.86E-03 Rate

% oj"Limit % N/A N/A N/A N/A N/A 131 1odine Ci ND* ND* ND* ND* ND* N/A Average Release µCi/s N/A N/A N/A N/A N/A Rate

% of Limit % N/A N/A N/A N/A N/A Particulates Ci ND* ND* ND* ND* ND* N/A Average Release µCi/s N/A N/A N/A N/A N/A Rate o/i, of Limit % N/A N/A N/A N/A N/A Gross Ci 4.86E-07 2.0SE-07 1.72E-07 2 .58E-07 1 .12E-06 Alpha -

3H Ci 4.77E+OO 8.98E+OO 1.06E+Ol 5.66E+OO 3.00E+Ol 14 Average I

Release µCi/s 6 .0SE-01 l .14E+OO l .34E+OO 7.18E-01 9.SlE-01 Rate

% oj'Limit % N/A N/A N/A N/A N/A 14 ( 5 Ci 3.30E+OO 3.30E+OO 3 .30E+OO 3.30E+OO l .32E+Ol

ND means measurements were performed but no activity was detected.

4 Safety Analysis calculation 87-063-00, January 6, 1988 5 14 C activity is estimated based on EPRI report TR-1021106, Estimation of1 4 C in Nuclear Power Plant Effluents, December, 2010 .

Ca ll away Energy Center 2018 Annual Ra dioactive Efflu ent Release Report Revisi on 1 Table A-1A: Gaseous Efflu ents- Ground Level Release- Batch Mode Fission &

Quarter Quarter Quarter Quarter Total for Activat ion Units 1 2 3 4 the yea r Gases 41Ar Ci 5.03E-02 1.17E-01 4. 67E-02 6.SSE-02 2.80E-01 Iodines & Quarter Quarter Quarter Quarter Tota l for Units Halogens 1 2 3 4 the year Ci ND

ND

ND

ND* ND

Quarter Quarter Quarter Quarter Total for Particulates Units 1 2 3 4 the year Ci ND

ND

ND

ND

ND

3H Ci 3.65E-02 5 .34E-01 3 .25 E-0 1 l.80E-01 1.08E+OO Gross a Ci ND ND ND ND ND 14( Ci 2.56E-02 2.56E-02 2.56 E-02 2.56E-0 2 l .02E-01

NO means me as ure ments were performed but no activity was detected.

Callawa:y Energy Center 2018 Annual Radioactive Effluent Release Report Revision 1 Table A-lB: Gaseous Effluents- Ground Level Release- Continuous Mode Fission &

Quarter Quarter Quarter Quarter Total for Activation Units 1 2 3 4 the year Gases Ci ND

ND

ND

ND

ND

Iodines & Quarter Quarter Quarter Quarter Total for Units Halogens 1 2 3 4 the year Ci ND

ND

ND

ND

ND

Quarter Quarter Quarter Quarter Total for Particulates Units 1 2 3 4 the year Ci ND

ND

ND

ND

ND

3H Ci 4 .74E+OO 8.44E+OO l.03E+Ol 5.48E+OO 2.89E+Ol Gross a Ci 4 .86E-07 2 .0SE-07 l.72E-07 2.58E-07 l.12E-06 14( Ci 3 .27E+OO 3.27E+OO 3.27E+OO 3.27E+OO l .31E+Ol

ND means measurements were perform ed but no activity was detected.

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revision 1 I

Table A-2 : Liquid Effluents- Summati on of All Releases Summation Quarter Quarter Quarter Quarter Estimated of All Liquid Unit Total 1 2 3 4 Uncertainty (%) 6 Releases Fission and Activation Ci 2.14E-02 4.35E-03 l.83E-03 5.19E-03 3.28E-02 20 Products7 Avg Diluted µCi/

1.21E-07 3.SE-08 l.93E-08 3.54E-08 6.04E-08 Cone ml

% of Limit % N/A N/A N/A N/A N/A 3H Ci 5.2 8E+Ol 1.0lE+Ol 1.16E+02 3.35E+02 5.13E+02 14 Avg Diluted µCi/

2.98E-04 8.13E-05 1.22E-03 2.28E-03 9.45E-04 Co11c ml

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

Entrained Ci ND* ND* ND* ND* ND* 27 Gases Avg Dilu ted µCi/

N/A N/A N/A N/A N/A Cone ml I

% of Limit % N/A N/A N/A N/A N/A Gross a Ci O.OOE+OO O.OOE+OO I 1.33E-05 1.81E-05 1 3.13E-05 29 1

Avg Dilu ted µci/

O.OOE+OO O.OOE+OO 1.40E-10 l.23E-10 5,77E-11 Cone ml Vol Liquid Liters 5.91E+06 3.94E+06 3.67E+06 3.94E+06 l .74E+07 Effluent 8 Dilution Liters l .71E+08 1.20E+08 9.12E+07 1.43E+08 5.26!:+08 Volume 9 Avg river m3 /s l.70E+03 2.58E+03 3.07E+03 3.80E+03 2.79E+03 flow 10 Time period hrs 1.20E+02 8.54E+Ol 8.08E+Ol 9.76E+Ol 3.84E+02 for releases

ND means measurement s were performed but no activity was detected .

6 Safety Analysis calculation 87-063-00, January 6, 1988 7 Excludes 3 H, noble gases, and gross alpha .

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

9 Does not include Missouri River dilution .

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

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revisiom 1 Table A-2A: Liquid Effluents- Batch Mode Fission & Activation Qua r ter Quarter Quarter Quarter Total for the Units Products 1 2 3 4 year s1cr Ci l .09E- 04 O.OOE+OO O.OOE+OO 0.00E+OO 1.09E-04 ssco Ci 4.S?E-03 l .29E-03 7.29E-OS 4.llE-04 6.34E-03 6oco Ci l .88E-03 l.OOE-03 l .72E-04 2.86E-03 5.92E-03 63Ni Ci l.56E-04 4.86E-04 l.27E-03 9.71E-04 2.88E-03 1245b Ci 1.62E-03 l .95E-05 O.OOE+OO O.OOE+OO l .64E-03 125 5b Ci l .30E-02 l.54E-03 3.16E-04 9.43E-04 l.SBE-02 131Cs Ci l .12E-04 1.44E-05 O.OOE+OO S.69E-06 l.32E-04 Total Ci 2.14E-02 4.35E-03 l .83E-03 S.19E-03 3.28E-02 Di ssolved & Quarter Quarter Qua rter Quarte r Total for the Units Entrained Gases 1 2 3 4 year Total Ci ND* ND* ND

ND* ND*

3H Ci 5.28E+Ol l .OlE+Ol l.16E+02 3 .3SE+02 5.13E+02 Gross a Gi 0 0 l.33E-05 1.BlE-05 3.13E-OS

ND means measurement s were performed but no activity was detected .

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revision 1 Table A-3: Low-Level Waste Shipped for 2018 Resins, Filters, And Evaporator _Bottoms Volume Waste Class Curies Shipped fP m3 I A 1.30E+02 3.68E+OO 1.32E+OO 8 (M.~.©[+IDO I l©.ID(jl~+f)Q 11),.@,_@ ~ '!'~):0 C O.OOE+OO O.OOE+OO 0.00E+OO Unclassified O.OOE+OO O.OOE+OO O.OOE+OO All 1.30E+02 3.68E+QO 1.32E+DO Major Nuclides for the Above Table: H-3, C-14, Mn-54, Fe-55, Co-601 Ni-63 , Sr-90, Tc-99, 1-129, Cs-137, Pu-238, Pu-241 , Am-241 , Cm-242, Cm - 243 Dry Active Waste (DAW)

Volume Waste Class CuJies Shipped ft3 ml A 4.66E+0.3 i .32E+02 i .87E-01 IB1 .©J.Q©J:'1,©© I 0.'Q@I::+©,© ©,©01=-!i©:© II C O.OOE+OO O.OOE+OO O.OOE+OO I

Unclassified 0.00E+OO O.OOE+OO O.OOE+OO All 4.66E+03 1.32E+02 1.87E-01 Major Nuclides for the Above Table: Mn-54, Fe-55, Co-58, Co-60 , Ni-63 , Nb-95 , Sb-125, Cs-137 Irradiated Components Volume Waste Class Curies Shipped

'ft3 m3 A O.OOE+OO O.ODE+OO O.OOE:+00 I

HI 0.Q© lf-1'@.0 Q.©©~-¥Cil0 0.GCJE-i.©Q C 0.00E+OO O.OOE+OO O.OOE+OO Unclassified O.OOE+OO O.OOE+OO O.OOE+OO All O.OOE+OO O.OOE+OO O.OOE+OO Major Nuclides for the Above Table : N/A

Callaway Energy Center 2018 Annu al Radioactive Effluent Release Report Revision 1 Table A-3: Low-Level Waste for 2018 (continued)

Other Waste Waste .Class Volume Curles Shipped ft3 m3 A I O.OOE+QO O.OOE+O!:l O.OOE+OO 11 1B O.©O,l::4QJi) IL @.©O~.;©li) O.Jil©~+OQ C O.OOE+OO O.OOE+OO O.OOE+OO Unclassified O.OOE+OO O.OOE+OO O.OOE+OO All O.OOE+OO O.OOE+OO O.OOE+OO Major Nuclides tor the Above Table: N/A Sum Of All Low-Lev13I Waste Shipped From Site Volume Waste Class Curles Shipped ft3 ml A 4.79E+ 03 1.36E+02 1.51 E+OO I 1B Q.ff0,~+ 09 (i),,(l)©E.+©@ ©.©lllE+lllQ C O.OOE+OO O.OOE+OO O.OOE+OO Unclassified O.OOE+OO O.OOE+OO O.OOE+OO All 4.79E+03 1.36E+02 1.51 E+OO Major Nuclides tor the Above Table : H-3, C-14, Mn-54, Fe-55, Co-58 , Co-60 , Ni-63, Sr-90 ,

Nb-95 , Tc-99, Sb-125, 1-129, Cs-137 , Pu -238 , Pu -239 , Pu -241, Am -241, Cm -242, Cm -243 SO LIDIFICATION AGENT None used .

IRRADIATED FUEL SHIPMENTS (Disposition )

There we re no shipmen ts of irradiated fu el du ri ng the reportin g period.

Callaway Energy Center 20 18 Annual Rad ioactive Effluent Release Report Revision 1 Table A-4: Dose Assessm ents, 1 0 CFR 50, Append ix I Quarte r Quarter Qu arter Qua rter Yearly 1 2 3 4 t otal Li quid Effl ue nt Dose Li mit, 1.5 1.5 1.5 1.5 3 Total Body (m rem)

Total Body Dose (mrem) 3.95E-04 6.53E-05 2.61E-04 5.95E-04 1.33E-03

% Limit 0.03% 0.00% 0.02% 0.04% 0.04%

Liqu id Effluent Dose Li mit, 5 5 5 5 10 M aximum Organ (mrem)

Maximum Organ Dose (mrem) 5.40E-04 1.58E-04 3.75E-04 I

6.72E-04 1.52E-03

% Limit 0.01% 0.00% 0.01 % 0.01% 0.02%

Gase ous Efflu ent Dose 5 5 5 5 10 Li mit, Gamma Air (mrem )

Gamma Air Dose (mrad) 2.17E-05 5.04E-05 2.0l E-05 2.82E-Q5 l.20E-04

% Limit 0.00% 0.00% 0.00% 0.00% 0.00%

Gaseou s Effluent Dose 10 10 10 10 20 Limit, Beta Air (mrem)

Beta Air Dose (mrad) 7.64E-06 1 .78E-05 7.09E-06 9.95E-06 4.25 E-05

% Lim it 0.00% 0.00% 0.00% 0.00% 0.00%

Gase ous Effluent Dose Limit, Max imu m Organ 7.5 7.5 7.5 7.5 15 (mrem)

Maximum organ dose 11 (mrem) 1.19E-03 2.25E-03 2.65E-03 l .42E-03 7.51E -03

% Limit 0.02% 0.03% 0.04% 0.02 % 0.05%

14 C M aximum organ dose 4.00 E-03 4.00E-03 4.00E-03 4.00E-03 1 .6 2E-02 (mrem) 12 11 Iodine, 3 H, and particulates with great er th an an 8 day half- life.

12 Not included in above tot als

Callaway Energy Center 2018 Annual Rad ioactive Effluent Rele as e Report Revis ion 1 Table A-5: EPA 40 CFR 190 Individu al in the Unrestr icted Area Whole Body Thyroid Max Other Organ Dose Limit 25 mrem 75 mrem 25 mre m Dose 1.26E-02 l .26E-02 2.72E-02

% Limit 0.05% 0.02% 0 .11%

Callaway Energy Center 2018 Ann11al Radioacti ve Effluent Release Report Revision 1 Appen dix B Meteoro logical Dispersion Parameters and Joint Frequency Tables; Totals of Hours at Each Wind Speed & Direction for the period January 1, 2018- December 31, 2018

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revision 1 Meteorological Dispersion Parameters for the Reporting Period Nearest Resident Dispersion Parameters Direction: NNW Distance: 2897 meters X/Q, Undecayed and Undeplete d : 9.37E-07 sec/m 3 X/Q Decayed and Undepleted : 9.22E-07 sec/m 3 X/Q Decayed and Depleted: 7. 79E-07 sec/m 3 D/Q Deposition rate : 2.63E-09 m-2 Site Boundary Dispersion Paramete rs Direction : SSW Distance: 1400 meters X/Q, Undecayed and Undepleted: 1.47E-06 sec/m 3 X/Q Decayed and Un depleted: 1.46E-06 sec/m 3 X/Q Decayed and Depleted : l.30E-06 sec/m 3 D/Q Deposition rate : 5.SOE-09 m*2 Meteorological Data Recovery Rate 10 metefs elevation Hours of valid data : 8757 Total hours in period : 8760 Recovery rate : 99 .97%

60 meters elevation Hours of valid data : 8757 Total hours in period : 8760 Recovery rate : 99.97%

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revision 1 Joint Freq uency Distribution: Ho urs at Wind Speed and Direction January- December, 2018 All Stabiilitles Elevations: Winds 10m Stability 60m Wind Speed Range (m/s) I Wind Direction Sector <0.50 0.5-1 1.l-1.S 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 26 61 55 137 121 99 57 26 0

' 0 585 NNE 2 35 71 66 151 113 87 20 4 0 0 549 NE 2. 36 so 61 125 76 28 6 4 0 0 388 ENE 6 29 57 62 111 83 28 6 1 0 0 383 E 4 32 49 54 111 70 42 25 8 1 0 396 ESE 8 26 46 62 104 72 51 12 6 0 0 387 SE 5 68 96 133 236 95 58 2 2 D 0 695 SSE 6 42 75 1 64 344 171 67 27 17 0 0 913 s 2 49 49 76 260 224 166 113 56 0 0 995 SSW 2 27 58 62 184 183 81 50 27 0 0 674 SW 0 19 51 68 171 128 55 35 11 0 0 538 WSW 3 36 31 52 75 46 23 16 11 I 0 0 293 w 1 26 49 34 69 60 48 24 17 2 0 330 WNW 0 22 65 49 94 100 57 28 17 I 1 0 433 NW 4 39 69 91 146 111 60 41 1.9 0 0 580 NNW j 30 48 61 168 138 77 64 16 0 0 605 Tot 51 542 925 1150 2486 1791 1027 526 242 4 I 0 8744 Hours of Calm ........................ ... 13 Hours ef Var.l ab le Direction ,,.*. 0 Hours of Valid Data .. .......... ...... 8757 Hours of Missing Data .............. 3 Hours In Period ..............,, ......... . 8760

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revision 1 Joint Frequ ency Distribution : Hours at Wind Speed and Direction January- De cember, 2018 Class A Extremely Unstab le based on lapse rate Elevations: Winds lDm Sta bility 60m WJnd Speed Range (m/s)

Wind Dire ction Sector <0.50 0.5- 1 1.1-1 .S 1.6- 2 2.1- 3 3.1- 4 4.1- 5 5.1-6 6.1- 8 8.1-10 ?10.00 Tot al N 0 0 0 0 1 6 2 0 0 0 0 9 NNE 0 0 0 0 2 3 4 0 0 0 0 9 NE 0 0 0 0 0 0 0 0 1 0 0 1 ENE a 0 0 0 2 3 1 0 1 0 D 7 E 0 0 0 0 1 1 0 0 0 0 0 2 ESE 0 0. 0 0 0 s 2 0 0 0 0 7 SE 0 0 0 0 4 2 s 0 0 0 0 11 SSE 0 0 0 0 2 4 3 0 1 0 0 10 s 0 0 0 0 3 7 3 8 6 0 0 27 SSW 0 0 0 0 3 13 9 8 s 0 0 38 SW, 0 0 0 D 6 13 12 14 2 0 0 47 WSW 0 0 0 0 0 5 3 0 0 I 0 0 8 w 0 0 0 0 0 0 4 2 0 1 0 7 WNW 0 0 0 0 0 4 3 7 4 1 0 19 NW 0 0 0 0 0 7 4 3 3 0 0 17 NNW 0 0 Q 0 0 3 3 3 0 0 0 9 Tot 0 0 0 0 24 76 58 45 23 2 0 228 Hours of Calm ........................... 0 Hours of Va riab le Direction ..... 0 Hours of Valid Data ... ... ,.,-....... 228 Hours of M issing Data .............. 3 Hours in Period .......................... 8760

Callaway Energy Center 2018 Annual Radioactive Effl uent Release Report Revision 1 Jolnt Frequency Distribution: Hours at Wind Speed and Direction January- December, 2018 Class B Moderate ly Unstable based on la pse rate Elevations~Winds 10m Stabi llty 60m Wind Speed Range (m/s)

Wind D1rection Secto r <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 3 7 13 0 0 0 0 23 NNE 0 0 0 0 10 2 4 0 0 0 0 16 NE 0 0 0 0 2 0 0 0 0 0 0 2 ENE (l 0 0 1 7 5 0 0 0 0 0 13 E I 0 0 0 0 5 1 2 4 0 0 0 12 ESE 0 0 0 0 2 7 2 0 0 0 0 11 SE 0 0 0 1 7 7 9 0 I 0 0 0 24 I SSE 0 0 0 0 6 4 1 1 2 0 0 14 s 0 0 0 1 11 11 9 3 4 b 0 39 I SSW 0 0 1 0 13 22 I 5 7 2 0 0 so SW 0 0 0 0 14 17 11 5 0 0 0 47 WSW 0 0 0 1 2 4 1 1 0 0 0 9 w 0 0 0 0 0 8 7 0 i 0 0 16 WNW 0 0 0 0 2 8 4 0 0 0 0 14 NW 0 0 0 0 8 3 10 3 0 0 0 24 NNW 0 0 0 0 3 3 7 3 0 0 0 16 Tot 0 0 1 4 95 109 85 27 9 0 0 330 Hours of Ca lm ...... ..................... 0 Hours of Variable Direction ..... 0 I

Hours of Valid Data ___ ............ 330 Hours of Missln,g Data ............ .. 3 Hours In Period ...... .................... 8760

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revisio n 1 Joint Frequency Distribution : Hours at Wind Speed and Direction January- December, 2018 Class C Slightly Unstable based on lapse rate Elevations : Winds 10m Stability 60m Wind Speed Range (m/sj W ind Direction Sector <0.50 0.5-1 1.1- 1.5 L6-2 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 5 10 5 2 5 I 0 0 27 NNE. 0 0 D 2 14 11 12 2 1 0 0 42 NE 0 0 0 Q 10 5 3 0 2 0 0 20 ENE 0 0 1 2 9 2 1 2 0 0 0 17 E 0 0 1 2 7 6 4 1 D 1 0 22 ESE 0 D 0 1 3 11 7 2 0 0 0 24 SE 0 0 0 4 .24 14 4 0 0 0 0 46 SSE. 0 0 3 4 14 11 9 1 3 0 0 45 s 0 0 0 1 21 17 13 7 1 0 0 61 SSW 0 0 2 4 14 28 8 6 7 D 0 69 SW 0 0 0 3 30 21 8 5 1 0 0 68 WSW 0 0 1 3 9 7 0 2 0 I I 0 0 22 w 0 0 0 3 6 11 5 1 D 0 0 26 WNW 0 0 0 2 8 13 4 4 0 0 0 31 NW Q 0 0 0 12 13 2 5 1 0 0 33 NNW 0 0 0 3 9 14 9 9 2 0 D 46 Tot 0 Q 8 35 195 194 94 49 23 1 0 599 Hours of Calm ............ .......... ,.... 0 Hours o f Variab le Directien ... .. 0 i' '

Hours of Valid Data ,. ....... , ..*..... 599 Hours of M lssl ng Data .. ,.*......... 3 Hours If\ Period .......................... 8760

Callaway Energy Center 2018 AM ual Radioactive Effluent Release Report Revision 1 Jofnt Frequency Distribution: Hours at Wind Speed and Direction January- December, 2018 Class D Neutra l based on lapse rate Elevations: Winds 10m Sta bility 60m W1nd5peed Range (m/s)

W ind I

Directron Sector <0.50 0.5- 1 1.1-15 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 14 24 74 90 72 51 21 0 0 349 NNE 0 8 19 32 86 88 65 18 3 0 0 319 NE 0 5 14 23 86 63 22 6 1 0 0 220 ENE 0 6 17 16 63 so 20 4 0 0 0 176 E 0 3 10 18 58 51 32 19 8 0 0 199 I

ESE 0 1 13 27 48 33 36 10 5 0 0 173 SE 0 2 19 31 80 55 31 1 1 0 0 220 SSE 0 5 15 23 62 56 32 14 7 0 0 214 s 0 5 12 16 49 62 51 49 37 0 0 281 SSW 0 3 8 18 36 43 29 21 10 0 0 168 SW 0 2 14 26 57 39 20 ' 11 8 0 0 177 WSW 0 7 10 25 34 12 15 13 11 0 0 127 w 0 3 18 14 27 26 26 21 16 1 0 152 WNW 0 2 15 20 56 70 46 16 13 0 0 238 NW 0 2 11 2S- 84 77 42 30 15 0 0 286 NNW 0 2 4 24 78 95 58 47 14 0 0 322 Tot 0 59 213 362 978 910 597 331 170 1 0 I

3621 Hours of Calm ............... ............ 0 Hours of Variable Direction ..... 0 Hours of Va lid Data ... ...... ...... , .. 3621 Hours of Missing Data .............. 3 Hours in Period ............ .............. 8760

Callaway Energy Cehter 2018 Annual Radioactive Effluent Release Report Revision 1 Joint Frequency Distribution~ Hours at Wind Speed and Di rection January- December, 2018 Class E Slightly Stab le based on lapse rate Elevations : Winds 10m Stability 60m Wfnd Speed Range (m/s)

W i nd Direction Sector <0.5Q 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 I H 17 39 8 7 4 0 0 0 92 NNE 0 7 20 20 36 9 2 0 0 0 0 94 NE 0 4 13 20 27 7 3 0 0 0 0 74 ENE 1 4 15 33 28 23 6 0 0 0 0 110 E 0 6 23 26 37 11 4 1 0 0 0 1 08 ESE 0 5 18 22 46 16 4 0 1 0 0 112 SE 0 13 34 61 102 17 9 1 1 0 0 238 5liE 0 5 21 69 137 69 21 11 4 0 0 337 s 0 8 11 30 95 109 87 46 8 0 0 394 SSW 1 7 16 15 77 73 30 8 3 0 0 230 SW 0 8 16 24 49 26 4 0 0 0 0 127 WSW 2 9 10 16 27 17 3 0 I

0 0 0 84 w 0 8 17 11 32 12 6 0 0 0 0 86 WNW 0 4 21 16 26 5 0 i 0 0 0 73 NW 0 8 14 38 29 11 1 0 0 0 0 101 N NW 0 4 12 17 62 2.2 0 2 0 D 0 119 Tor 4 1Q6 272 435 849 435 1 87 74 17 0 0 23 79 Hou rs of Calm ........................... 0 Hours of V.rriable Direction *. .. 0 Hours of Valid Da ta .... .. ............ 2379 Hours of M tssing Data ...... ........ 3 Hours in Period ......................... . 8760

Callaway Energy Center 2018 Annual Radioactive Effl uent Release Report Revision 1 Joint Frequency Distribution : Hou rs at Wind Speed and Directio n January- December, 2018 Class F Moderately Sta ble based on lapse rate Elevations: Winds mm Sta bility 60m Wind Speed Range (m/s )

Wind I

Direction Sector <0.50 0.5- 1 1 1- 1.5 1.6-2 2.1-3 3.1* 4 4.1* 5 1 5,1* 6 6,1* 8 8.1-10 >10.00 Total I

N 0 4 17 8 14 I 0 0 0 0 0 0 43 NNE 1 4 19 9 3 0 0 0 0 0 0 36 NE 2 13 13 10 0 0 0 0 0 0 0 38 ENE 1 11 19 9 2 0 0 0 0 0 0 42 E 1 12 13 8 3 0 0 0 0 0 0 37 ESE 6 14 13 12 5 0 0 0 0 (:) 0 so Sf 2 36 39 31 14 0 0 0 0 0 0 122 SSE 2 19 27 52 101 20 1 0 0 0 0 222 s 1 14 9 18 74 17 3 0 0 0 0 136 SSW 0 8 16 13 39 4 0 0 0 0 0 80 SW 0 4 14 10 11 12 0 0 0 0 0 51 WSW 1 9 s 7 2 1 1 0 0 0 0 26 w 0 9 11 5 3 3 0 0 0 0 0 31 WNW 0 10 19 8 2 0 0 0 0 0 0 39 NW 3 17 24 19 8 0 1 0 0 0 0 72.

NNW 0 5 14 15 13 1! 0 0 0 0 0 48 Tot 20 189 27Z 234 294 58 6 0 0 0 0 1073 Hours of Calm ....... .. ............... ... 6 Hours of Variable Direction ..... 0 Hours of Valid Data ...... ,........... 1079 Hours of Missing Data .,, .... a .. .. . 3 Hours in Period ....... ..... .............. 8760

Callaway Energy Center 2018 Annual Radi oactive Efflu ent Release Report Revl sion 1 Jofnt Frequency Distribution: Hours at Wind Speed and Direction January- December, 2018 Class G Extremely Stable based on lapse rate Elevat1ons: Winds tom Stability 60m Wind Speed Range (m/s)

Wind I 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 13 19 6 1 0 0 0 0 0 0 42 NNE 1 16 13 3 0 0 0 0 0 0 0 33 NE 0 14 10 8 0 1 0 0 0 0 I 0 33 ENE 4 8 5 1 0 0 0 0 0 0 0 18 E 3 11 2 0 0 0 0 0 0 0 0 16 ESE 2 6 2 0 0 0 0 0 0 0 0 10 SE 3 17 4 5 5 0 0 0 0 0 0 34 SS E 4 13 9 16 22 7 0 0 0 0 0 71 s 1 22 17 9 7 1 I

0 0 0 0 0 57 SSW 1. 9 15 12 2 0 0 0 0 0 0 39 SW 0 5 7 5 4 0 0 0 0 0 0 21 WSW 0 11 5 0 1 0 0 0 0 0 0 17 w 1 6 3 1 1 0 0 0 0 0 0 12 WNW 0 6 10 3 0 0 0 0 0 0 0 19 NW 1 12. 20 9 5 0 0 0 0 0 0 47 NNW 3 19 18 2 3 0 0 d 0 0 0 45 Tot 27 188 159 80 51 9 0 0 0 0 0 514 Hours of Calm ......... ,..... .... ........ 7 Hours of Variable Directron ..... 0 Hours of Valfd Data .................. 521 Hours of Missing Data .............. 3 Hours in Period ......... ................. 8760

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revision 1 Joint F(equency Distribution: Hours at Wind 5peed and Direction January- December, 2018 All Stabilities Elevations: Winds 60m Stability 60m Wind Speed Range (m/s)

Wind I Direction Sector <0.50 0 ,5* 1 1.1-1.5 1.6- Z 2.1-3 3.1- 4 4.l - 5 5.1* 6 6.1- 8 8.1- 10 :>10.00 Total

~

N 0 2 9 18 50 97 121 117 96 18 0 528 NNE 0 0 7 17 76 117 141 99 62 3 0 522 I NE 0 3 12 14 68 92 95 60 31 4 0 379 ENE 1 4 7 14 74 99 110 56 36 1 0 402 E 1 7 12 18 56 108 108 72 30 8 1 421 ESE 0 3 11 17 59 92 106 92. 41 7 1 429 SE 0 7 27 46 205 187 107 51 12 1 0 643 SSE 0 6 l3 31 106 153 171 135 92 18 0 725 s 0 6 14 16 72 130 171 219 311 105 9 1053 SSW 0 0 11 18 50 97 152 174 254 45 6 807 SW 0 5 8 11 75 118 109 116 159 35 9 645 WSW 1 4 ll 18 60 54 57 so 58 21 13 347 w 0 2 7 20 37 43 46 64 68 29 15 331 WNW 0 3 9 13 43 55 86 105 104 41 20 479 NW 0 4 3 10 42 101 98 126 127 42 18 571 I

NNW 0 1 3 8 47 76 99 105 113 22 1 475 Tot 3 57 164 289 1120 1619 1777 1641 1594 400 93 8757 Hours of Cairn .... ,........... ;, .. ,...... 0 Hours of Variable Direction .. ,.. 0 I Hours af Valid Data .................. 8757 Hou rs. af Missi11g Data ............ .. 3 Hou rs in Perlod ......................... . 8760

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revision 1 Joint Frequency Distribution : Hours at Wind Speed and Direction Jan uary- Dece mber, 2018 Class A Extremely Unstable based on lapse rate Elevations: Winds 60m Stability 60m Wind Speed Range (m/s)

Wind Direction 1.1-Sector <0.50 0.5- 1 1 .6- 2 2.1- 3 3.1-4 4.1- 5 S.1-6 6,1- 8 8.1- 10 >10.00 Total 1 .5 N 0 0 0 0 0 4 s 2 0 0 0 11 NNE 0 0 0 0 0 1 3 3 0 0 0 7 NE 0 0 0 0 0 0 0 0 1 1 0 2 ENE 0 0 0 0 1 3 3 0 0 0 0 7 E 0 0 0 0 0 1 0 0 0 0 0 l ESE 0 0 0 0 0 1 5 0 0 0 0 6 SE 0 0 0 0 2 2 3 4 0 0 0 11 SSE 0 0 0 0 1 2 4 3 0 1 0 11 s 0 0 0 0 0 s 5 2 8 6 0 26 SSW 0 0 0 0 1 2 12 s 12 7 0 3'9 SW 0 0 0 0 0 4 14 3 19 7 0 47 WSW 0 0 0 0 0 0 2 4 3 0 0 .9 w 0 0 0 0 0 0 0 1 2 2 1 6 WNW 0 0 0 0 0 0 1 9 3 10 4 27 NW 0 0 0 0 0 2 1 1 6 1 3 14 I

NNW 0 0 0 0 0 0 1 1 2 0 0 I 4

Tot 0 0 0 0 s 27 59 38 56 35 8 228 Hours of Calm ............... ............ 0 Hours of Variable Dlrection ..... 0 Hours of Valid Data ... .....,......... 228 Hours of Missing Data .,,. ..,. ..... 3 Hours In Period .................. ........ 8760

Callaw ay Energy Cent er 2018 Annual Radioactive Efflu ent Release Repo rt Revision 1 Joint Frequency Distri bu tion : Hours at Wfnd Speed ,ind Direction January- December, 2018 Class B Modera tely Unstable based on lapse rate Elevatl ons: Winds 60m Sta blllty 60m W ind Speed Range (rn/s)

Win d Dir ection 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 Tota l I

N 0 0 0 0 2 3 10 6 l 0 0 22 NNE 0 0 0 0 3 8 2 2 0 0 0 15 NE 0 0 0 0 1 1 0 0 0 0 0 2 ENE 0 0 0 0 2 8 3 0 0 0 0 13 E 0 I 0 0 0 1 3 1 2 3 0 0 10 ESE D 0 0 0 1 5 4 2 1 0 0 B SE 0 0 D 0 2 10 7 3 0 © 0 22 I

SSE 0 0 0 0 4 1 5 2 1 1 0 14 s D 0 0 0 5 9 7 6 7 4 0 38 SSW D 0 0 1 5 11 20 7 6 s 0 55 SW 0 0 D D 0 12 ~o 13 9 3 0 47 WSW 0 0 D 0 1 2 D 4 2 1 0 10 w 0 0 0 D 0 D 4 5 4 D 1 14 WN W 0 D D 0 1 4 4 7 5 I 0 0 21 NW 0 0 0 0 0 4 1 8 6 3 D 22 I

NNW 0 D D 0 1 1 2 3 4 D 0 I 12 Tot G D 0 l 29 83 80 70 49 17 l 330 Hou rs of Calm ........................... 0 I

Ho u rs of Var iabl e. Di rection ..... D Hours of Valid Data ...... ,.,. ........ 330 Hours of Mlsslng Data ... ......- .. 3 Hours In Pe riod .......................... 8760

Callaway Energy Center 2018 Annual Radioactive Efflue nt Release Report Revision 1 Joint Frequency Distribution : Hours at Wind Speed and Direction Jan uary- December, 2018 Class C Slightly Unstab le based on lapse rate Elevations: Winds 60m Stability 60m Wind Speed Range (m/s)

Wind Dlrectlon Sector <0.50 0.5- 1 1.1-1.S 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 1 4 8 6 s 1 4 0 29 NNE 0 0 0 1 7 s 12 9 4 1 0 39 NE 0 0 0 0 s 9 1 4 1 1 0 21 ENE 0 0 0 0 7 5 1 1 3 0 0 17 E 0 0 0 3 2 4 s 2 1 0 1 18 ESE 0 0 0 0 3 4 10 6 1 0 0 24 SE 0 0 0 1 19 14 4 4 0 I 0 0 42 SSE 0 0 0 2 14 13 7 7 3 1 0 47 s 0 0 2 0 10 14 11 11 12 2 0 62 SSW 0 0 0 3 4 14 22 8 10 7 0 68 SW 0 0 0 0 11 19 14 I 12 10 3 1 70 WSW 0 0 0 1 5 8 3 3 1 2 0 23 w 0 0 0 2 3 2 8 8 6 2 0 31 WNW 0 0 0 1 4 4 7 6 6 4 0 32 NW 0 0 0 0 7 7 9 17 3 2 2 47 NNW 0 0 (J 0 3 5 6 3 10 2 0 29 Tot 0 0 2. 15 108 135 126 106 72. 31 4 599 Hours of Ca lm ,....,..................... 0 Hours of Variab le Direction .... . 0 Hours of Valid Data .................. 599 Hours of Missing, Data .............. 3 Hours in Period ............... .....~ .... 8760

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revision 1 Joint Frequency Distribution: Hours at Wind Speed and Direction January- December, 2018 Class D Neutral based on lapse rate Elevations: Winds 60m Stabili ty 60m W ind Speed Range (m/s)

Wind Dlrection 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 7 14 33 57 68 60 76 14 0 330 NNE 0 0 6 14 48 63 62 55 49 2 0 299 NE 0 2 11 8 43 51 54 31 18 ;I. 0 220 ENE 0 4 6 11 39 45 49 17 21 1 0 194 I

E 0 2 6 9 31 46 42 20 22 8 0 186 ESE 0 1 5 11 32 30 24 32 27 7 0 169 SE 0 2 9 13 57 56 46 20 10 0 0 I

213 SSE 0 0 4 15 35 34 49 33 27 6 0 203 s 0 3 7 11 32 36 42 37 79 47 4 298 SSW 0 0 7 10 18 25 27 32 50 1l. 3 183 I SW 0 3 4 7 35 29 29 29 29 15 8 188 I

WSW 0 0 s 9 27 25 15 10 22 15 13 141 w 0 1 4 8 17 19 11 20 33 22 13 148 WNW 0 1 6 10 24 25 33 45 74 27 15 261 NW 0 1 2 9 23 52 48 59 75 35 13 317 NNW 0 1 0 6 26 45 58 49 66 19 1 271 Tot 0 22 89 165 520 640 657 549 678 231 70 362.l I-lours of Calm ...... .............. ,,._ .. 0 I Hours of Variable Direction ..... 0 Hours of Va lid Data .................. 3621 Hours of Missing Data .............. 3 Hours in Period ............... ... ,....... 8760

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revision 1 Joint Frequency Distribution : Hours at Wind Speed and Direction January- December, 2018 I'

Class E Slightly Stable based on lapse rate Elevations: Winds 60m Stability 60m Wind Speed Range (m/s)

Wind Direction Sector <0.50 0.5-1 1. 1- 1.5 i .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 1 2 6 13 23 30 13 0 0 89 I

NNE 0 0 0 1 9 26 36 14 5 0 0 91 NE 0 0 1 4 10 23 19 11 7 0 0 7~

ENE 0 0 0 1 15 22 3-1 24 6 0 0 99 E 0 2 3 3 8 .31 32 27 4 0 0 110 ESE 0 1 0 2 14 27 37 31 12 0 1 125 SE 0 1 6 11 77 77 41 10 2 1 0 235 SSE 0 1 2 4 28 59 72 53 39 9 0 267 s 0 1 0 3 12 33 44 95 161 43 5 397 SSW 0 0 2 2 12 21 30 68 l.27 14 3 279 SW 0 1 1 1 10 29 22 40 49 3 0 156 I WSW 0 2 1

! 1 11 7 24 19 27 2 0 94 w 0 1 1 2 8 11 16 24 18 2 0 83 WNW 0 2 1 0 8 12 25 22 8 0 1 79 NW 0 0 0 0 8 23 27 26 21 0 0 105 NNW 0 0 2 1 I 10 11 24 31 14 1 0 94 To t 0 13 21 38 246 425 503 535 513 75 10 2379 Hours of Calm ......... .... " ............ 0 Hours of Variable Direction ..... 0 Hours of Valid Data .................. 23 79 Hours of Missing Data _ ........... 3 Hours ln Perl ed .................. ....... . 8760

Callaway Energy Center 2018 Annual Radioactive Effluent Rel ease Report Revision 1 Joint Frequency Distribution : Hours at WFnd Speed and D1re ~tion January- December, 201 8 Class F Modera tely Stable based on lapse rate Elev;itions: Winds 60m Stabil ity Som Wlrd Speed Range (m/s)

W i nd Direction Sector <0.50 0 .5- 1 1.1-1 .5 1.6- 2 2.1-3 3,l.- 4 4.1- 5 5.1-6 6.1~ 8 8.1- 10 >10.00 Tota l N D D 1 1 5 9 6 12 3 D D 37 NNE 0 D D D .r;; 8 15 12 2 D 0 43 NE D 1 D 2 5 5 8 6 4 0 D 31 ENE 0 D 1 1 4 8 14 7 2 D D 37 E D 2 3 1 6 18 19 13 0 D 0 62 ESE D 1 3 1 2 15 16 19 0 D 0 57 SE D 1 2 16 39 25 6 D D D D 89 SSE D 1 3 4 14 36 23 32 19 D D 132 s D 2 3 0 7 23 48 63 34 3 D 183 SSW D D 1 2 6 18 25 41 4-1 1 D 135 SW D D D 2 8 12 14 10 33 4 D 83 WSW 1 1 3 3 6 5 5 4 2 1 I

D 31 w D D 2 2 4 6 7 5 5 1 D 32 WNW D D D D 2 6 15 13 8 0 D 44, I

NW D D D 1 1 10 10 14 10 1 D 47 NNW O' 0 D 1 1 9 5 12 I 8 D D 36 Tot 1 9 22 37 116 213 236 263 171 11 D 1079 Hours of Calm ............ ............... D I

Hours of Va ri-able Direction ..... D liours of Valid Data """ "' '"""" 1079 Hours of M issing Da ta ......,.. -.... 3 Hours In Peri od ..................... ..... 8760

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revision 1 Joint Frequency Distribution: Hours at Wind Speed and Directien January- Decembe r, 2018 Class G Extremely Stable based on lapse ra te Elevations: Winds 60m Stability 60m Wind Speed Range (rn/s)

Wind Direction Sector <0.50 0 .5- 1 1.1- 1,5 1.6- 2 2.1, 3 3.l- 4 4.1-5 5.1- 6 6,1* 8 8.1- 10 >10.00 Total N 0 0 0 0 0 3 3 2 2 0 I

0 10 NNE 0 0 1 1 3 6 u 4 2 0 0 28 NE 0 0 0 o 4 3 13 8 0 o o 28 ENE 1 0 0 1 ' G 7 9 7 4 0 0 35 E 1 o 1 0 2 8 5 9 8 o 0 34 I I

ES E o 0 3 3 7 10 10 2 o 0 0 35 SE 0 3 10 5 9 3 0 0 0 0 0 30 SSE 0 4 I 4 G 10 I 8 11 5 3 o 0 51 s 0 0 2 2 G 10 14 5 10 0 0 49 SSW 0 0 1 o 4 6 16 13 8 o 0 48 SW 0 1 3 1. 11 13 6 9 10 0 0 54 WSW 0 I l 2 4 10 7 8 6 1 0 0 39 I

w 0 0 0 6 5 5 0 l 0 0 0 17 WNW 0 0 2 2 4 3 1 3 0 o 0 15 NW 0 3 1 0 3 3 2 1 6 0 0 19 I

NNW 0 0 1 0 6 4 3 6 9 o 0 29 Tot i 13 30 33 86 96 :Ll6, 80 55 o 0 521 Ho urs of Calm ............... ............ 0 Heurs of Variable Direction ,.. .. 0 Hours of Vatrd Data .................. 521 Hours of Missing Data .....", ...... 3 Hours in Peri od ............ ,............. 8760

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revis ion 1 Appen dix C Chang es to Previo us Repor ts Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From : 01/01/2 017 to 12/31/2 017

Callaway Energy Center 2018 Annual Radioactive Effluent Releas e Report Revi si on 1 Table A-3: Low Level Waste 2017 Resins, Filters, And Evaporator Bottoms Waste Volume Curies Class fP m3 - Shipped A 11.73E+02 4.90E+Cl0 3.28E+01 ffi -

1 ~ .11811 t+©'1 3.3:s:l:..:©tj ,2 .02 ~-i,©1 -

C 88.40E+OO 2.38E-01 2.10E+OO Unclassified 77.59E+OO 2.15E-01 8.66E+OO All 22.01 E+02 5.6'9E+OO 6.37E+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, Sr-90, Zr-95, Nb-94, Nb-95, Tc-99, Sn -117m, 1-129, Cs-13 4, Cs-137, Ce-144, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Am -241, Cm-242, Cm-243, Cm-244 Dry Active Waste (DAW)

Waste Volume Curies I

Class ft3 mJ Shipped I '

A 1.0SE+04 3.01 E+02 1.41 E-01 1B 0 .Cilf fi[.,ji@(j), ©,.@l=-,1,©,© ©..C!l©ff+!\10 1

I C O.OOE+OO 0.00E+OO O.OOE+OO 1

Unclassified O.OOE+OO O.OOE+OO O.OOE+OO All 1.06E+04 3.01 E+02 1.41 E-01 M ajor Nuclides for the Above Table : H-3, C-14, Cr-51, Mn-54, Fe-55, Co-5 8, 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, Ce-144, Pu-238, Pu-239, Pu-240, Pu-241, Am-241, Cm-242, Cm-243, Cm-244 Irradiated Components Waste Volume Curies Class ft3 m3 Shipped I

A 0.00E+OO O.OOE+OO O.OOE+CIQ 13, (!),,@JE-r©© ' ~

(i),,©0 ~'1-'Q© 0 .©©}ffi,i.!(j)('.)

C O.OOE+OO O.OOE+OO O.OOE+OO Unclassified O.OOE+OO O.OOE+OO O.OOE+OO All 0.0QE+OO 0.00E+OO O.OOE+OO Major Nuclides forthe Above Table : N/A

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revision 1 Table A-3: Low Level Waste 2017 (continued)

Other Waste Waste Volume - Curies Class ft3 rri3 Shipped A O.QOE+OO O.OOE+OO O.OOE+OO

~ Q,©.QE+@(i) O.O!!H:+.©© 0.©©[+0(:)

C O.OOE+OO O.OOE+OO O.OOE+OO Unclassifie d O.OOE+OO 0.00E+OO 0.00E+OO All O.OOE+OO O.OOE+OO O.OOE+OO Major Nuclides for the Above Table : N/A Sum Of Ail Low-Level Waste Shipped From Site Waste Volume Curies Class ft3 m3 Shipped A 1.08E+04 3.06E+02 33.30E+01 El 11.1 S.1::-tr!iM ,:B.:%1J£-©1 2,.,©i[+Cl ~

C 88.40E+OO 22.38E-01 2.10E+OO I Unclassifie d 77.59E+OO 22.15'E-01 8.66E+OO All 1.08E+04 33 .07E+02 6.39E+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, Zr-95, Nb-94, Nb-95 , Tc-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 SOLIDIF ICATION AGENT None used.

IRRADIATED FUEL SHIPMEN TS (Dispositi on )

There were no shipments of irradiated fuel during the reporting period .

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report Revision 1 Appen dix D Changes to the Callawa y Energy Center Of/site Dose Calculat ion Manual for the year201 8 The Callaway Offsite Dose Calculation Manual (ODCM) is collectively comprised of two documents:

APA-ZZ-01003 (Methodo logy and Parameters)

FSAR-SP Chapter 16 .11 (Radiological Effluent Controls); and The changes to the two documents are described in the text of the report. A complete text of each documen t is provided in this appendix .

~'~

'wJ'Ameren wy MISSO URI Energy Center AP A-ZZ-01003 OFF-SITE DOSE CALCULATION MANU AL MINOR Revis ion 023 Page 1 of 75 INFORMATION USE June, 2018

APA-ZZ-01003 Rev. 023 Contents

1. PURPOSE AND SCOPE ................... ...... ..... .. .................... .. ............ ...... ..... .... ... 5

2. LIQUID EFFLUENTS ............... ,.. ,... .... ... .......... ....... ......... .......... ................. ....... .. s 2.1 . Liquid Effluent Monrtors ......... ... .. ......................... ,...... .. .................... ... ..... ..... ...... s 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 .i . DOSE RATE FROM GASEOUS EFFLUENTS ............................................. 18 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 of75 INFORMATION USE June, 2018

APA-ZZ-01003 Rev . 023 4 .1. Calculation of Dose and Dose Commitment from Uranium Fuel Cycle Sources ..................................... ... ..... ... ...... .. .... ..... ..... ............. .................. 23 4.1.1. IDENTIFICATION OF THE MEMBER OF THE PUBLIC ................. ............ 23 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 ..... ....... ...... .... ................ .. .... ..... .. ... .................................. ....... .. .. ..... ... .. 27 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.i . 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 Commitme nt Values (A;t) for Adult Age Groupl 1l .......... .... ........ ...

...... 35 Table 2: Bioaccumu lation Factor (Bf;) ......... ............. ,.................... ............. .... ......................

... 38 Table 3: Dose Factor for Exposure to a Semi - Infinite Cloud of Noble Gases .. ... ...... ...........

.. ... 39 Table 4 : Ground Plane Pat hway Dose Factors (R;) .......... ...................................................

...... 40 Table 5: Child Inhalation Pathway Dose Factors (R,) .. .......... .... .. .................................... .. ........

41 Table 6: Child Grass- Covv- Mill< Pathway Dose Factors (R1)............ ,......................... ........

,..... 43 Table 7: Child Grass- Goat - Milk Pathway Dose Factors (R1).................................. ... ..............

45 Page 3 of75 INFORMATION USE June,2018

APA-ZZ-01 003 Rev. 023 Table 8: Child Meat Pathway Dose Factors (R,) ... .... ...... ............. ,... ... ... .. .. ........... ..................... 47 Table 9 : Child Vegetation Pathway Dose Fclctors (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 Elata Selection Hierarchy .... ... ..... ..................................... ..... .. .... .. ... 54 Appendix A: Methodology for Calculating Dose from 14 C in Gaseous Effluents ...... .......... ..... .... ........ ........ .......... ... .. ......... ...... ..................... ................... 55 Appendix 8: Record of Revisions ....... ... .......... .. .. ... ... ... ................. .. ... ....... ...... ........ ............ 68 Page 4 of 75 INFORMATION USE June, 2018

APA-ZZ-01003 Rev. 023 OFF-SITE DOSE CALCULATION MANUAL

1. Purpose and Scope The Otfstte Dose Calculation Manual (ODCM) describes the methodology and parameters used in the calculation of off-site doses resulting from radloactive gaseous arid liquid effluents .

In the calculation of gaseous and liquid effluent monitoring Alarmrrrip 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 TIS 5.5.4 and FSAR-SP Chapter 16.11.4, and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Effluent Release Reports required by TIS 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 wllich contains the Radiological Effluent Controls (RECs) , 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 llqu id effluent lines and the discharge line (cooling tower blowdown) . Setpoints, precautions, and limitations applicable to the operation of the Cal.laway 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) litnits in 1 o CFR Part 20 at the release point to the Unrestricted Area. The calculated alarm and trip actron setpoints for the liquid effluent line mon itors and flow measuring devices must satisfy the following equatl'on :

Eq . 1 Where :

1 Statements of Consideration, Federal Regis ter, Vol. 56 , No. 98 , Tuesda y, May 211, 1991, Subpart D, page 23374 2

10 CFR 50.36 a (b) 3 Letter, F. J . Congel to J. F. Schm idt, dated Apri l 23, 1991 Page 5 of 75 INFORMATION USE June,2018

APA-ZZ-01003 Rev. 023 C is tl1e liquid effluent concentration value (ECV) fhlplementing REC i 6.11 . i .1 for the site in

µCi/ml ;

c is the setpoint in (µCi/ml), of the radioactivity monitor measuring the radioactivity concentration In the effluent line prior to dilution and subsequent release. The setpoint, which 1s inversely related to the volumetric flow of the effluent line and directly related to the volumetric flow of the- dilution stream plus the e'ffluent steam , represents a value, which, if exceeded, would result in concentrations exceeding ten times the values of 10 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 pe~

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 unlt time. If Fis large compared to f, then F + f =F.4 If no dilution is provided then cs. 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 fo r determining the setpoint of the liquid radwaste effluent line monitor becomes:

C{F+ f) .

c~ (µC, I ml) f 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 limlt 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 setpoint 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 .

4 NUREG-0133 , pages AA-1 thru AA-3 Page 6 of 75 INFORMATION USE June,2018

APA-ZZ-01 003 Rev, 0.23 2.1 :1. Continuou s Liquid Effluent Monitors The radiation detection monitor associated with continuous liquid effluent re*leases is :5*6 Monitor I.D. Description BM-RE-52 Steam Generator Slowdown Discharge Monito r The Steam Generator Slowdown dlscharge is not consrdered 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 16.11 - 1.

2.1.2. Radioactiv e Liquid Batch Release Effluent Monitors The radiation monitor associated With the liquid effluent batch release system is:7 Monitor LD, Description HB* RE-18 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 dependenc e of the setpoint, c, on the radionuclide distribution , yields , calibration , and monitor parameters, requires that several varlables 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 i 6.11-1 , and is used to calculate an ECV sum (ECVSUM) :

EC Vs u M = ( I (C I ) I (EC\/., ) )

i=g , a,s,t, f Eq.3 Where :

C 9 is the concentrati on of each measured gamma emitting nucUde observed by gamma-ray spectrosco py of the waste sample ;

5 FSAR-SP, Section 11 .5.2.2.3.1 6 FSAR-SP, Section 11.5.2.2.3.4 7 FSAR-SP, Section 11

.5.2.2.3.2 8 NUREG-0133

, pages AA-1 thru AA-3 Page 7 of 75 INFORMATION USE June, 2018

APA-ZZ-0100 3 Rev. 023 Ca 1s the concentraton of 237 Np, 238 Pu , 2391240 Pu , 241 Pu , 241 Am , 242 Cm , & 2431244Cm , in the quarterly composite sample based on previous composite sample, analyses ;

Cs is the measured concentrations of 89 Sr and 90Sr as determined by analysis of the quarterly composite sample based on previous composite sample analyses; Ci is the measured concentration of 3 H in the waste sample; and Cr is the measured concentration of 55 Fe & 69 NI as determined by analysis of the quarterly composite sample based on previous composite sample analyses .

ECV 9 ECVs, ECVa, ECV1, and ECVt 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 2x10- 4 µCi/ml total activity.

For the case ECVSUM s1 , 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 ls requfred 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 O and 1 for a particular discharge point, provided that the sum of the allocation fractions for all discharge points must be s1.

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

Imax 5. (F + fp)

SF

N7(ECVSUM)

Eq. a Where :

fmax. is the maximum permissible liquid effluent discharge flow rate, (In gallonsJminute) ;

fp 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 ls the safety factor ; an administrative factor used to compensate for statistical fluctuatioris and errors of measur,ements. This factor also provides a margin of safety in the calculation of the maximum liquid effluent discharge flow rate (fma)

The value of SF should bes 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 8 of 75 INFORMATION USE June,2018

APA~ZZ-Oi 003 Rev. 023 In the event that fmax is less than f p, then the Value of fmax is substituted into the equation for fp, 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 ettluent monitors are Nal(TI) based systems and respond primarily to gamma radiation. Accordingly, their setpoint is based on the total concentration of garnma emitting nuclides in the effluent:

c = 0.95 {bkg+[ric g).;.SFJ]

Eq , 5 Where :

c is the monitor setpoint as previously defined , in µCi/ml ;

bkg is the monitor background prior to discharge, in µOi/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 i6.ii .i .1 L C and SF are as previously defined.

9 The monitor's background Is controlled at an appropriate lfmit to ensure adequate sensitivity.

Utilizing the methodology of ANSI Ni 3.10-i 974, the background must be maintained at a value of less than or equal to 9xi 0* 5 µCi/ml (relative to 137 Cs) in order to detect a change of 4x10*7 µCi/ml of 137Cs .9 In the event that there is no detectable gamma activity ln the effluent or if the value of

{(L C9 )+SF} is less than the background of the monitor, then the mon itor setpoint will be set at twice the current background of the monitor.

As previously stated , the monitor's 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 (NIST) traceable calibration sources:

DBCFc = (I( C 9

)) +(CMR)x(ECF )

Eq . 6 9

HPCI 9605, "Calculation of Maximum Backgr0und Value for HB-.RE-18" Page 9 of75 INFORMATION USE June, 2018

APA-ZZ-01003 Rev. 023 DBCFc is the monitor data base conversion factor Which converts count rate into concentration

(µCi/ml) ;

CMR is the calculated response of the radiation monitor to the liquid effluent; ECF *is the convers1on factor for 187 Cs, which cohverts count rate into concentration (µCi/ml) .

C is as previously defined.

9 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 8710.

2.3. Liquid Effluent Concentration Measurements Liquid batch releases are discharged as a discrete volume and each release is author1zed 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 ta.Jlk 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 limft 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 term inated 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 sgsr, sosr, ssFe, s3Ni, 231Np, 23s Pu , 239,240Pu, 241Pu, 241 Am , 242cm , & 2431244Cm, the measured concentrations frorn the previous quarterly composite analyses are used until laboratory results become available. Composite sc;1mples 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 individual's consumption of fish and potable water, as appropriate. Normally, the adult is considered to be the maximum exposed individual. 10 The Callaway Plant's liquid effluents are discharged to the Missouri River. As there are no potable water intakes within 1O miles ot the discharge point,11 ,12 this pathway does not require routine evaluatfon . 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 .

1n NUREG-0133, Section 4.3 11 Environmental Report, OLS , Table 2.1-19 12 FSAR-SA SecLion 11 .2.3.3.4 Page 10 of 75 INFORMATION USE June, 2018

APA-ZZ~Oi 003 Rev. 023 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 m

The dose contributions for the total time period _ILlt, are calculated at least once each 3i l =J days and a cumulative summation of the total body and individual organ doses is maintaine d

for each calendar quarter. Dose is calculated for all radionuclides identified in liquid effluents released to Unrestricted Areas using the following expressioh: 14 D, =~[A, t, ~t, C,1 F,J Eq. 7 Where :

D. is the cumulative dose commitment to the total body or any organ , 't, tram tl1e liquid m

effluents for the total. period IL1t1 in mrem.

l=l Mt is the length of the /h time period over which C;,1and F1are averaged for all liquid releases, in hours. Lit, corresponds to the actual duration of the release(s) .

C1,1 ls the average measured concentra tion of radionuclide, i, lh undiluted liquid effluent during the time period Lit, from any liquid release, iri (µCl/ml'}.

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

F, Is the near field average dilution factor for C11 during any liquid effluent release :

F, (F f f max)

89.77 Eq . 8 Where :

Fmax Is the maximum undiluted effluent flow rate durrng the release ;

F is the average dilution flow; and 1;i FSAR SA, Section 11 .2.3.4.3 0

14 NUREG-0133. Section 4 .3 Page 11 of 75 INFORMATION USE June, 2018

APA-ZZ-01003 Rev. 023 89.77 is site specific applicable factor for the mixing effect of the discharge structure. 15*16*17 The term C1,1 is the undiluted concentration of radioactive material in liquid waste at the common release point determined in accordance with REC 16.11.1 ., , Table 16.11-1 ,

"Radioactive Liquid Waste Sampling and Analysis Program . All dilution factors beyond the sample point(s) are included in the F1term.

As there are currently no potable water intakes within 1O river miles of the discl1arge point, the drinking water pathway is not included in dose estimates to the maximally exposed individual.

Should future potable water intakes be constructed within 1 O river miles downstream of the discharge point, then this manual will be revised to include this pathway in dose estimates.18 The A,, values given in Table :1 were calculated according to: 19 Eq.9 Since there are no drinking water pathways, and CEC is a freshwater site , the terms for drinking water consumption (Uw/Dw) and invertebrate consumption (U1Bli) go to zero and the equation simplifies to :

Eq. 10 Where:

ko is a constant of units conversion , 1.14x105 = (10 6 pCi/µCi

i 03 ml/kg/ 8760 hr/yr)

UF is the adult fish consumption, 21 kg/yr 20 BF1 is the bioaccumulation factor for nuclide, i, in fresh water fish pCi/kg per pCi/L. 21 *22 DF1is the dose conversion factor for huclide, i, for adults for organ , r , in mrem/pCi .

15 NE0-54 16 UOTH 83-58 1

1 CAR 200700053- Attachments : Phase 1 final draft 1s FSAR- SP, Section i 1.2.3.3.4 19 NUREG-0133

, Section 4.3.1 20 NUREG-0133

, Section 4.3.1, pp. 16 2 1 UCRL-50564 , Table 6

22. NUREG/CR-4013, pp. 3.17 Page 12 of 75 INFORMATION USE June,2018

APA-ZZ-01 003 Rev. 023 2.4.3. Summary, Calculation of Dose Due to Liquid Effluents m

The dose contribution for the total ttme period LLlt 1 Is determined 'by calculation at least 1=1 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 radionuclid e concentrati ons are determined by periodic composite and grab sample analysis may be approximat ed by uslng the last measured value. Dose contribution s are determined for all radionuclide s 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 will be available for use when liqulds require treatment prior to their release to the environmen t.

Operability Is demonstrat ed through compliance with R~C 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 f actors of Regulatory Guide 1.109, Table 2.2 and other sources as necessary .23 *24

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

The alarm/trip (alarm & trip) setpoint for any gaseous effluent radiation monitor i~ determined based on the instantaneo us noble gas total body and skin dose rate limits of REC 16.11 .2.1, at the Site Boundary location with tile highest annual average X/Q 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/t~ip setpolnts.25 23 HPCI 0406 2' 1 HPCI 1604 Page 13 of75 INFORMATI ON USE June, 2018

APA-ZZ-01003 Rev. 023 The radiation monitor alarm/trip setpoints for eacl1 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, radloactive materials in particulate form and radlonuclides other than noble gases. The exception is GL-RE-202. The only emuent 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 capabill1ies during normal, anticipated, and unusual operating conditions , variability in release tlow 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.

3.1.1. Continuous Release Gaseous Effluent Monitors The radiation detection monitors associated with continuous gaseous effluent releases are :27*26 Monitor I.D. Description GT-RE-21 Unit Vent GH-RE-10 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 r-adioactivity. 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 bullding, auxiliary building , the access control area, the containment purge, and t he condenser air discharge.

The unit vent monitor provides alarm functions only, and does not terminate releases tram 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 f!ow path provides ventilation exhaust for all parts of the building structure and components within the building and provides a discharge path tor the waste gas decay tank release line. These 2s FSAR- SP Section 11 .5.2.1.2 26 NUREG- 0133 , section 5.1.1 21 FSAR-SP Section 11.5.2.3 .3.1 20 FSAR-SP Section 11 .5-2.3.3.2 Page 14 of75 INFORMATION USE June, 2018

APA-ZZ-01003 Rev. 023 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 rmonitor will fsolate 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 tor a monitor failure.

The continuous Unit Vent and Radwaste Building Vemt 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 ~s soon as possible.

3.1.2. Batch Release Gaseous Effluent Monitors The radiation monitors associated with batch release gaseous effluents are: 29 ,3o,3, Monitor 1.0 . Description GT-RE-22 , GT-RE-33 Containment Purge System GH-RE-10 Radwaste Building Vent 29 FSAR-SP Section 11 .5.2.3.3 .2 3

°FSAR-SP Section 11 .5.2.3.2.3 a1FSAR- SP Section 11 .5.2.3.2.2 Page 15 of75 INFORMATION USE June, 2018

APA-ZZ-01003 Rev. 023 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 16.11.2.1 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 def ault value of 2.2E-02 µCi/cc .

This corresponds to 50% of the 500 mrem/yr limit of REC 16. i i .2.1 .32 Each monitor *is allocated only 50% of the limit such that the sum total of the two monitors cannot exceed the llmit.

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'.2.1. Total Body Dose Rate Setpoint Calculations To ensure that the limits of REC 16.11.2.1 are met, tl1e alarm/trip setpoint based on the total body dose rate is calculated according to:

Stb ~ DtbRtb Ffa Eq.1.1 Where :

S1b is the alarm/trip setpoint based on the total body dose rate (µCi/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; Fs 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 Fs = 0,1.

a2 HPCI 8403 , page 9 Page 16 of 75 INFORMATION USE June,2018

APA-ZZ-01003 Rev. 023 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 16.11.2.1.

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

R1b=C -c- [(x!a) ~(K,01 )]

Ecj.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 sampllng oi 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 (µCi/cc) ;

X/Q is the highest calculated annual average relative concentration for any area at or beyond the Site Boundary in (sec/m3) (Table 1O, 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 (µCi/m 3) (Table 3); and Q, is the rate of release of noble gas radionuclide, i, in (~lCi/sec) .

01 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 setpolnt based on the skin dose rate is calculated according to :

5 , ~ DsRffa Eq . 13 Where :

Fs and Fa are as previously defined ;

Ss is the alarm/trip setpoint based on the skin dose rate ;

Ds 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 Rs is the factor used to convert dose rate to the effluent concentration as measured by the effluent monitor, in (µCi/cc) per (mrem/yr) to the skin , determined according to:

Page 17 of75 INFORMATI ON USE June,2018

APA-ZZ-0 1003 Rev. 023 Eq . 14 Where :

L, is the skin dose factor due to beta emissions for each identified noble gas radionuclide , ln

( mrem/yr) per (~LCi/m 3) ;

1.1 Is a factor of units conversion; i mrad air dose = 1. i mrem skin dose; and M, is the air dose factor due to gamma emissions for each identified noble gas radionuclide, in (mrad/yr) per (µC1/m 3) .

C, ( X/Q), and Qi are previously defined.

3.3. Calculation of Dose and Dose Rate from Gaseous Effluents 3.3.1. Dose Rate from Gaseous Effluents The following methodol ogy is applicable to the location (Site Boundary or beyond) character ized by the values of the paramete r 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 considera tion is that which minimizes the allowable release values .38 The factors K,., Li, and M, relate the radionucl ide airborne concentra tions to various dose rates assuming a semi-infin ite cloud model.

3.3. 1. 1. Dose Rate from Noble Gases The release rate limit for noble gases is determine d according to the following general relationships :34 Dtb I

J

= I:[K,Q, ((X/Q)) ~500 mrem/yr Eq . 15 D, = I[( Li + 1.1 M, )( ( x;a)ar)] .:; 3000 mrem/yr I

Eq . 16 Where ;

a3 NUREG-0133, Section 5.1 .2 3~

NUREG-01 33, Section 5 . 1.2 Page 18 of75 INFORMA TION USE June,2018

APA-ZZ-01 003 Rev. 023 01 is the release rate of noble gas radionuclides , i, in gaseous effluents, from all vent releases in (~LCi/sec) ; and 1.1 is a factor of units conversion factor ; i mrad air dose= 1.1 mrem skin dose.

Li, M1, K1, ( X/Q), Dtb ahd Ds are as previously identified.

3.3.1.2. Dose Rate from Radionuclides Other than Noble Gases The re.lease rate limit for 131 1 and 133 1, for 3 H, and for all radioactive materials in particulate form With half-lives greater than 8 days is determined according to: 35 00= IR,[Xia] a, 5 1500mrem/yr i

Eq.17 Where :

Do 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 ror the child, based on the critical organ, in (mrem/yr) per (µCi/m 3 }; and a, is the release rate of radionuclldes other than noble gases, i, in gaseous effluents, from all vent releases ih (µCt/sec).

(X/Q) is as previously defined.

The dose parameter (R1) includes the internal dosimetry of radionuclide, i, ahd the receptor's breathing rate , which are functions of the receptor's age. The child age group has been selected as the limiting age group. All radiodines are assumed to be released in elemental form .36 Ri values were calculated according to :37 R, = K' (BR) OFA7 Eq. 18 Where :

K' Is a factor of units conversion factor : ix10 6 pCi/µCi ;

BR is the breathing rate from Regulatory Guide 1.109, Table E-5 (m 3/yr) ;

35 NUREG-01'33 , Section 5 .2 .1 36 NUREG-0133, Section. 5.2.1 a7 NUREG-0133, Section 5 .2.1.'1 Page 19 of 75 INFORMATI ON USE June, 2018

APA-ZZ-0 1: 003 Rev. 023 DFAi is the maximum organ inhalation dose factor forthe 11h radionuolide, in (mrem/pCi) . The total body is considered as an organ in the selection of DFA.38 *39 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 3.3.2.1. Air Dose Due to Noble Gases The air dose at the Site Boundary due to noble gases is calculated according to the following methodology:40 During any calendar quarter, for gamma radiation :

D9 = 3.17E-08 I[ M f 1 ( X/Q) a;] ~5 mrad Eq.19 During any calendar quarter, tor beta radiation :

Db= 3.17E-OB I[N I 1 (x1a) 0;] 5,1omrad Eq . 20 During any calendar year, for gamma radiation :

D'l =3.17E-oaI [ M ;

(x;a) qJ 5,1omrad Eq . Z1 During any calendar year, tor beta radiation :

Db =3.17E-08 L[N1 ( X/0) Q J 5 20 mrad I

1 Eq.22 Where:

D9 is the air dose in mrad , from gamma radiation due to noble gases released in gaseous effluent; Db is the air dose In mrad , from beta radiation due to noble gases released in gaseous effluents; as Regulatory Gulde 1.109, Appendi x E, Table E-9 39 ZZ-48 110 NUREG-0133 , Section 5.3 .1 Page 20 of 75 INFORMATION USE June, 2018

APA-ZZ-Oi 003 Rev. 023 N1 is the air dose factor due to beta emissions for each Identified noble gas radionuclid e, i, in (mrad/yr) per (µCifm3);

01 is the releases of noble gas radionuclide s , i, in gaseous effluents, for al.I gaseous releases Jn (µCi) . Releases are cumulative over the calendar quarter or year as appropriate . Qi is calculated as the product at the ventilation flow rate and the measured activity at the effluent stream as determined by sampling; and 3.17x10* 0 is the inverse of the number of seconds per year.

X/Q & M1 are as previously defined.

3.3.2.2. Dose Due to Radionuc/ides Other than Noble Gases The dose to a Member of the Public from 131 1 and 133 1, for 3 H, and all radionuclide s in particulate form wit11 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 ahy calendar quarter:

"Ip,.1 5,7.5 mrem Eq.23 During any calendar year:

"I 1o,,1 S15 mrem Eq . 24 For each pathway, J, (i.e. , for inhalation , ground plane , meat, cow- milK , goat- milk , and vegetation) 01,1 is calculated according to the expression:

o,. =3.17E-BL,R1.1 .,[wp1J j

Eq.25 Where :

Dr,; is the dose in mrem, to a Member of the Public from radionuclide s other than noble gases ,

from pathway j, received by organ I (including total body) ;

R ,. 1,J is the dose factor for each Identified radionucl ide , i, in m 2 (mrem/yr) per (µCi/sec) or (mrem/yr) per (µCi/m 3) as appropriate, for the pathway J, and exposed organ I, appropriate to the age group of the critical Member of the Public receptor; W; is the X/Q for the inhalation and tritium pathways , in sectm 3 and is the D/Q tor the food and ground pl,;me pathways, in meters*2 .

Page 21 of75 INFORMATION USE June, 2018

APA-ZZ-0 1003 Rev . 023 D/Q is the average relative deposition of the effluent at or beyor1d the Site Boundary ,

considering depletion of the plume during transport ;

0 1is the release of radioiodines, radioactive materials in particulate form , and radionuclides other than noble gases, i, in gaseous effluents, for all gaseous releases in µCi. Releases are cumulative over the calendar quarter or year as appropriate. 0 1is calculated as the product of ventilation flow rate and the measured activity of the effluent stream as determined by sampling; and 3.17x10* 8 is the inverse of the number of seconds per year.

X/Q is as prevlously defined . Refer to Table 10, Table 11, and Table 12 for applicability ;

Although the annual average relative concentration X/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 of X/Q .41 The Total Body dose from ground plane deposition is added to the dose for each individual organ .4 2 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 coolarit 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 discharge d outside the growing season or at night such th at 14 C 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 Novembe r 1.43 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 require treatment prior to their release to the environment.

Operability is demonstrated through compliance with REC 16.11 .2.1, 16.11 .2.2, and 16.11.2.3 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 43 Hammer, Gregory, R., "Climate of Missouri"., monograph available from tl;ie National Climatic Data Center (NGOC) of the Nati onal Ocean.tc and Almospheric Administration (NOAA}, January, 2006.

Page 22 of 75 INFORMATION USE June,2018

APA-ZZ-01003 Rev. 023 compliance . This may be modified as appropriate to accmmt 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. 44*45 Particulate nuclides with a half-life of less than 8 days are not considered. 46 90 Y, 140 La, and 144 Pr are rncluded because the parent half-life rs 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 at the dose at the individual's 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 B km of the Callaway Plant.

4.1.1. Identification of the Member of the Public The Member of the Public is considered to be a real individual , Includ ing all persons not occupationally associated with the Callaway Plant, but who may use portions of the plant site

..i, ZZ-78 45 ZZ-250 46 Inspection Report 50-483/920 02 (DRSS) 47 NUREG-05 43, Section Ill , page 8 48 NUREG-05 4.3, Sectlo11 lV, page 9 Page 23 of 75 INFORMA TION USE June,2018

APA-ZZ* 01003 Rev. 023 tor recreational or other purposes not associated with the plant. 49 Accord ingly , it is necessary to characteriz e 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 assumption s which could be reevaluated if ,necessary to demonstrat e continued compliance with 40 CFR 190 through the use of more realistic assLi mptions.50 ,51 The evaluation of Total Dose from the Uranium Fuel Cycle should consider the dose to two Critical Receptors : (a) The Nearest Resideht, and (b) The Critical Receptor within the Site Boundary.

4.1.2. Total Dose to the Nearest Resident The dose to the Nearest Resident is due to plume exposure from noble gases, ground plane exposure , ahd Inhalation and ingestion pathways . It is conservativ ely 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 radioacfate 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 methodolog y discussed in Section 3, using concurrent meteorolog ical data for the location of the Nearest Resident with the highest valu e of X/Q .

The location of the Nearest Resident in each meteorolog ical sector is determined from the Annual Land Use Census conducted in accordance with the Requiremen ts of REC 16.1 1.4.2.

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 Departmen t of Conservatio n for mahageme nt of the res idual 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 fo r low intensity recreational l!.Jses (hunting ,

hiking , sightseeing , etc .) but recreationa l use is excluded in an area immediately surrounding the plant site (refer to Figure 4.1). Much of the resi dual lands within the Site Boundary are leased to area farmers by the Departmen t of Conservatio n to provide income to support manageme nt and developme nt costs . Activities conducted under these leases are pri marily comprised of farm ing (animal feed) , grazing , and forestry . Crops tor human consumptio n are specifically prohibited by the lease.52*53 ,54 9

~ NUREG-0133 , Section 3. 8 50 NUREG. Q5 43, Secti on IV, page 9 5 1 NUREG-0543 , section Ill , page 6 52 Envlro nmeAtal Report, OLS , Section 2. 1.2.3 53 Env1ronmenta l Report, OLS, Section 2.1.3.3.4 54 Management Ag ~eement for the Public Use of Lands, Exhibit A.

Page 24 of75 INFORMATION USE June, 2018

APA-ZZ-01003 Rev. 023 Based on the utilization of areas within the Site Boundary, it is reasonaore 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 1 i 00 hours0 days 0 hours 0 weeks 0 months 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) .

4.1.3.1. 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 farmer's 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 lnsignif1cant. 56 *57 55 Private communication, H.C. Lindeman & B.F.Holderness, August 6, 1986 56 HPCI i206 57 HPCI 1505 Page 25 of75 INFORMATION USE June,2018

APA-ZZ-01003 Rev. 023

~

x~~

H 1111~~~,a\\ M£T ~ ~ ~ L

~,

II I

X \ I\ j,,...tf\ I \ .x IV\~~/ .r.rra UOUNDAUY

\'

C C

rz2] CLOSED Tb ;rUDuc USE.

D !/Kl 1000

~

OW

!!1;'"1,l' l!l lU'.I iN AREA C LOS ED TO l'UBLIC' USE UNlON ELECTRJC CO, 8 CALLAWA Y l'LANT J,!C>U 1\1.h'Trm.S llltl U JOO 6110 SITE AREA CLOSED TO PUDLIC USE SCALE lN .EEBT FIGURE ~-1 REY', 6 Page 26 of 75 INFORM ATION USE June,20 18

APA-ZZ-01003 Rev. 023

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.

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 1ngestion 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 lnterlaboratory Analyses Program per Reg. Guide 4.15. 58 The laboratory participates in an lnterlaboratory 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 mon1toring 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 Guid~ 4.13 .

6. Annual Average Atmospheric Dispersion Parameters 6.1. Annual Atmospheric Dispersion Parameters The dispersion values presented in Table 1O were determined througih the analysis of five years of on-site meteorological data.59 The straight-line Gaussian dispersion model XOQD00 60 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.

6.1.1. Determination of Dispersion ,Estimates for Special Receptor Locations 58 Regulatory Guide 4.15, rev. 1, section 6.3..2 59 HPCI 1503 ea NUREG/CR2919 Page 27 of 75 INFORMATION USE June, 2018

APA-ZZ-01003 Rev. 023 XOODOQ 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 accord ing to :61 X=X 1 (d/d1 )8 Eq . 26 Where :

In (X /X 2 )

B=-- ln (d 2 /d1 )

Eq . 27 X,, X2 are the atmospheric dispersion parameters at distance d 1 and 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 Sfte Boundary are intended for a narrow scope application ; that of calculating the dose to the current farmer 62 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 farmer's time, approximately 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months per year, is spent on croplands of the Reform Conservatiori Area, including plots within the S1te Boundary, and that his time is divided among the plots proportional to the acreage of each plot. Fractiona:I acreage/time- weighted dispersion parameters were calculated for each plot as described in HPCI 1502. The weighted dispersion parameters for each plot were swmmed (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 calculati on 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 tor the wind speed , wind direction, and ambient air temperature parameters as required by

'Regulatory Guide 1.2.3 . The selection hierarchy is presented lh Table 13.

The input parameters to XOODOQ are documented in HPCI 1503.

01 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 th ose persons farming the plo ts w~hin the Site Boundary.

5a NUREG/OR-2 919 Page 28 of 75 INFORMATI ON USE June, 2018

APA-ZZ-01003 Rev. 023 A quality check of the meteorological data is performed prior to processing to ensure the val idity 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 (ARE RR) 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 ,"0ffsite Dose Calculation Manual Radioactive Effluent Controls" . T,he former ODCM REC numbers appear on each of the RE Cs 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 Cot1trols 9.1. Major Changes to Liquid and Gaseous Radwaste Treatment Systems A summary of Licensee- initiated major changes to the Radwaste Treatment Systems (liqufd and gaseous) must be reported to the Commission in the Annual Radioact1ve Effl uent Release Report (ARERR) for the peri od in which the evaluation was reviewed by the On-Site Review Committee (ORG) . On site documentation must contain :

A summary of the evaluation that led to the determ ination 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 additiona l or supplemental information;

A detailed descri ption of the equipment, components and process involved and the interfaces with other plant system s;

An evaluatron 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 H1ose previously estimated in the License application and amendments thereto; Page 29 of 75 INFORMATION USE June, 2018

APA-ZZ-01003 Rev. 023

A comparison of the predicted releases of radioactive materfals , 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 vvas 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 T/S AC 5.5. 1 Review for each revision of the ODCM must include the Radiation Protection Department.

1O. Bibliography ANSI N42.18-2004, "Specificatton & Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents". (2004)

CAR 200700053 - Missouri River Low Flow Trend for 2006", Attachments : Phase 1 Final Draft CDP~ZZ-00200 , Appendix B, Primary Plant Systems Tables", rev. 41 . April, 2018.

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

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

Schnell (UE) , dated July 12, 1996.

EPRI TR -1021106, Estimation of 14 C in Nuclear Power Plant Effluents", December, 201 O Generic Letter 89-01 , "Guidance for the Implementation of Programmatic Contr,ols for RETS in the Administrative Controls Section of Technical Specifications and the Relocation of Procedural Details of Current RETS to the Ottsite Dose Calculation Mariual or Process Control Program" , US Nuclear Regulatory Commission . (1989)

Hammer, Gregory, R., "Climate of Missouri", monograph available from the National Climatic Data Center (NGOC) 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 INFORMATION USE June, 2018

APA-ZZ-01003 Rev. 023 HPCI 8710, "Methodology for Calculating the Response of Gross Nal(TI) Monitors to Liquid Effluent Streams", rev . 1, April , 2005.

HPCI 8902, "Calculation of ODCM Dose Commitment Factors", rev. o. September , i989.

HPCI 9605 , "Calculation at Maxitnum Background Value tor HB-RE-18" , rev.a . September, 1996 HPCI 9905 , "Calculation of Setpoint for GL-RE-202 , rev.a . April , i 999.

HPCI 0406 Calculation of Liquid Effluent Dose Commitment Factors (Ait) for the Adult Age Grotip", rev . i . November, 2004.

HPCI 0509 , "Radiological Environmental Monitoring. Program (REMP) Calculation of Direct Dose from RAM Storage at Stores 11", 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.

HPCI 0601 , "Equipment Hatch Platform and Missile Shield Modification Direct Dose Calculation to the Member ot the Public", rev. O. January, 2006.

HPCI 1003, Evaluation of the 201 O Land Use Census", rev. O. December, 2010.

HPCI 1102, "Dose to the Member of the Public from the Release of 14 C in Gaseous Effluents for 201 O", rev.a. July, 2011.

HPCI 1206, "Evaluation of Direct Radiation Dose to the Member of the Public Due to Activities within the site Boundary", rev. 0. August, 2012.

HPCI 1502, "Atmospheric Dispersion Parameters for Activities Inside the Site Boundary", rev.

0. February, 2015 .

HPCI 1503, Calculation of Long- Term Meteorolog ical Dispersion Parameters", rev. i . April ,

2015 HPCI 1504, "Evaluation of the 2014 Annual Land Use Census", rev. 1. March , 2015 HPCI 1505, "Evaluation of Direct Radiation Dose to the Member of the Public from the Independent Spent Fuel Storage Facility", rev. i. July, 2015.

HPCI 1508, Evaluation of the 2015 land Use Census", rev.a. March , 2016 .

HPCI 1604, " Calculation of 126 Sb Ingestion Dose Comm itment Facto rs (Air)'1, rev . 01 . January, 2018.

HPCI 1802, ricalculation of 117msn Dose Commitment Factors (Air) and Effluents Management Software (EMS) Nuclide Data for Liquid Effluents", rev. O. May, 2018.

Page 31 of 75 INFORMATION USE June, 2018

APA-ZZ-01003 Rev, 023 IAEA Technical Reports Series no. 42i , "Management of Waste Containing Tritiwm and Carbon- 14", 2004 Internal USNRC memo, F. J. Gangel to V. L. Miller, et al, dated April 17, 11992 .

Kunz, C., "Carbon- 14 D.ischarge at Three Light- Water Reactors", Health Physics, var. 49 ,

pages 25- 35, 1985 Letter, F. J. Gangel to J. F. Schmidt, dated April 23, 1992.

Letter, F. J. Gangel to J. F. Schmidt, dated December 9, 1991 .

Letter, F. J. Gangel to J. F. Schmidt, dated June 8, 1993.

Letter, F. J. Congel to J. F. Schmldt 1 dated September 14, 1992.

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

Memo, F. J. Gangel, "Eigth Set of Questions and Answers on 10 CFR Part 20", May 26, 1994.

NCRP Report 81, "Carbon" 14 in the Environment", January 1985 Neeb, Karl- Heinz, The Radiochemistry of Nuclear Power Plants with Ught Water Reactors, Walter de Gruyter, Berlin , 1997 NE0-54, memo, D. W. Capone to S. E. Miltenberger, dated January 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 Radlological 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-1301 , "Ottsite 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 or 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 Page 32 of75 INFORMATION USE June, 2018

APA-ZZ-01003 Rev. 023 Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50 , Appendix l", Revision 1, U. S. Nuclear Regulatory Commission . (i 977)

Regulatory Guide i .1 i i , "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. (i 977)

Regulatory Guide i .2i , "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. i 3, "Performance, Testing , and procedural specifications for Thermoluminescence Dosimetry: Environmental Appfications "{Revision i ), U. S. Nuclear Regulatory Commission . (1977)

Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment" (Revision i ), U. S. Nuclear Regulatory Commission . (i 979)

Statements of Consideration , Federal Register, Vol. 56, No . 98, Tuesday, May 21 , i 991 ,

Subpart D, page 23374.

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

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

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

Title i 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 of 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 ". (i 983)

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

Westingt,ouse Calculation Note CN-TA 135, "Callaway (SCP) RSG IGOR/RETRAN Base Deck1 May i 6, 2003 ZZ-250, Rev. 0, noDCM Gaseous Pathway Dose Factors for Ohild Age Group and Ground Plane Dose Factors". ( i 992)

Page 33 of 75 INFORMATION USE June, 2018

APA-ZZ-01003 Rev. 023 ZZ-48 , "Calculation of Inhalation and Ingestion Dose Commitment Factors for the Adult and Cl1ild". (1988)

ZZ-57, "Dose Factors for Eu -154. (1989)

ZZ-78 , Rev. 2, "ODOM Gaseous Pathway Dose Factors for Adult Age Group". (1992)

Page 34 of 75 INFORMATION USE June,2018

APA-ZZ-01003 Rev. 023 Table 1: Ingestion Dose Commitm ent Values (Atr) for Adult Age Group!1 I (mrem/hr) per (µCi/ml)

Total Nuclide Bone Liver Thyroid Kidney lung Body GI-LLI 3H O.OOE+OO 2.26E-01 I 2 .26E-01 2.26E-01 2.26E-Ol 2.26E-01 2.26 E-01 7Be 1.31E*02 2.98E-02 1 .45E-02 O.OOE+OO 3 .lSE-02 O.OOE+OO 5.17E+OO 14Na 4.07E+02 4 .07E+02 4.07E+02 4.07E+02 4.07E+02 4.0?E+.02 4.07Et02 s1 cr O.OOE+OO O.OOE+OO l.27E+OO 7.61E-01 2.81E-Ol 1.69E+OO 3.20Et02 54Mn O.OOE+OO 4.38E+03 8.35Et02 0 .00E+OO l .30E+03 O.OOE+OO 1.34E+D4 s5Mn O.OOE+OO l.10Et02 1.95Et01 O.OOE+OO 1.40E+02 O.OOE+OO 3 .51E+03 ssFe 6.58E+02 4 .5SE+02 l.06E+02 O.OOE+OO O.OOE+OO 2.54Et02 2.61E+Ot s9Fe l.04E+03 2.44E+03 9.36E+02 O.OOE+OO O.OOE+OO 6.82Et02 8.14E+03 s1co 0.00E+OO 2.09E+Ol 3.48E+Ol O.OOE+OO O.OOE+OO O.OOE+ OO S.31E+02 ssco O.OOE+OO 8.92E+01 2,00E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.81E+03 6

°Co 0.00E+OO 2.56E+02 S.65E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.81E+03 63Ni 3.11E+04 2.16E+03 1.041:+03 0.00E+OO O.OOE+OO O.OOE+OO 4.SDE+D2 6sNi 1.26E+02 l.64E+Ol 7.49E+OO O.OOE+OC'l O.OOE+ OO O.OOE+OO 4.17E+02 64Cu O.OOE+OO 9 .97E+OO 4.68E+OO O.OOE+OO 2.51E+01 O.OOE+OO 8 .SOE+02 5szn 2.32E+04 7 .37E+04 3.33E+04 O.OOE+OO 4.93E+04 I O.OOE+OO 4.64Et04 69zn 4-.93E+Ol 9.43 E+ Ol 6.56E+OO O.OOE+OO 6.13E+Ol O.OOE+OO 1.42E+Dl 82 Br O.OOE+OO O.OOE+OO 2.27E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.60E+03 B3Br O.OOE+OO O.OOE+DO 4.04-E+Ol O.OOE+OO O.OOE+OO O.OOE+OO 5.82E+Ol 8~Br Ii O.OOE+OO O.OOE+OO S.24E+Ol O,OOE+OO O.OOE+OO O.OOE+OO 4.llE-04 asBr O.OOE+OO O.OOE+OO 2.151:+00 I O.OOE+OO O.OOE+OO O.OOEtOO 1.0lE-15 s6Rb O.OOE+OO l.OlE+OS 4.7lE+04 O.OOE+OO O.OOE+00 O.OOE+OO l .99E+04 as Rb D.OOE+OO 2.9DE+02 L54Et 02 O.OOE+OO O.OOE+OO O.OOE+OO 4.00E-09 B9 Rb I O.OOE+OO l.92Et02 l .35E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.12E-11 sssr 2.21E+04 O,OOE+OO 6.3SE+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.55E+03 gos r S.44E+OS O.OOE+OO l.34E+0S O.OOEt OO O.OOE+OO O.OOE+OO l.57E+04 s1.5r 4.07E+02 O.OOE+OO 1 .64-E+Ol O.OOE+OO O.OOE+OO O.OOE+OO l.94E+03 szsr 1.54E+02 O.OOE+OO 6.68E+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.06Et 03 goy S.76 E-01 O.OOE+OO 1.54E-02 O.OOE+OO O.OOE+OO O.OOE+OO 6.10E+03 I

9lmy 5.44-E-03 O.OOE+OO 2.llE O.OOE+OO 0.001:+00 O.OOE+OO 1.60E-02 91y 8.4-4-E+OO O.OOE+OO 2 .26E-01 O.OOE+OO O.OOE+OO O.OOE+OO 4.64E+03 92y 5.06E-02 O.OOE+OO 1.48E-03 O.OOE+ OO O.OOE+OO O.OOE+OO 8 .86E+D2 93y 'l_.60E=01 O.OOE+OO 4.43E-03 O,OOE+OO 0.00E+OO O,OOE+OO S.09E+03 9szr 2.40E-01 7.?0E-02 5.21E-02 O.OOE+OO l .21E-01 O.OOE+OO 2.44-E +.02 97zr 1.33E-02 2.68E-03 l.22E-03 O.OOE+.00 4.04-E-03 O.OOE+OO 8.30E+02 gs Nb 4.47E+02 2,48E+02 1 .34E+02 O.OOE+OO 2.46Et02 O.OOE+OO i.51E+06 99Mo O.OOE+OO 1.03E+02 1.96E+Ol O.OOE+OO 2 .34E+02 O.OOE+OO 2.39E+02 99mTc 8 .87E-03 2.SlE-02 3 .19E-01 O.OOE+OO 3 .81E-01 1.23E-02 1 .4-BE+Ol Page 35 of75 INFORMATION USE June,2018

APA-ZZ-01003 Rev. 023 Table 1~ Ingestion Dose Commitm ent Values {Ait) for Adult Age Group( 1 l (mrem/hr) per (µCi/ml)

Total Nuclide Bone Liver Thyroid Kidney Lung GI-LLI Body i,01Tc 9 .12 E-03 l.31E-02 1 .29E-Ol O.OOE+OO 2.37£-01 6.72E-03 3.95E-14 1D3 Ru 4.43E+OO O.OOE+OO 1.91E+OO O.OOE+OO 1 .69E+01 b.OOE+OO 5.17E+02 10,Ru 3.69E-01 O.OOE+OO 1.46E-01 O.OOE+OO 4.76E+OO O.OO E+OO 2.26£+02 106 Ru 6,58E+Ol O.OOE+OO 8.33E+OO O.OOE+OO 1.27E+02 O.OOE+OO 4.26E+03 109 Cd O.OOE+OO 5.55E+02 1.94E+Ol O.OOE+OO 5,.31[+02 O.OOE+OO 5.60E+03 uomAg 8.85E-Ol 8.lBE-01 4.86E- 01 0.00E+OO l.61E+OO O.OOE+OO 3.34E+02 1135n 5.67E+04 1 .61E+03 3.26E+03 9.19E+02 O.OOE+OO Q.OOE+OO 1.69E+OS ll7msn 2.79E+03 1.62E+02 6.99E+02 5.21E+Ol 0,00E+OO O.OOE+OO O.OOE+OO m sb 5 .48E-01 l .12E-02 l .66E-01 7.73E-03 O.OOE+OO 2.94E=Ol O.OOE+ DO 124 5b 6.70E+OO 1.27£-01 2.66E+OO 1.63£-02. O.OOE+OO S.22E+OO 1.90E+02 t 25 sb 4.29E+OO 4.79 E-02 1 .02E+OO 4.36£-03 O.OOE+OO 3.30E+OO 4.72E+Ol i i6sb 2,75E+OO 5.59£-02 9.92E-01 1.68E-02 O.OOE+OO 1.68E+OO 2.2S E+02 121mTe 6.48E+03 2.32E+03 7.90E+02 l. 66E+03 2.63E+04, O.OOE+OO 2. 17E+04 u1Te l.05E+02 3.78E+Ol 2.28E+01 7.BOE+Ol 4.29 E+02 O.OOE+OO 8.31E+03 12s"'Te 1 .10E+04 4.11E+03 1.74E+03 3.78E+03 4.. 60 E+04 O.OOE+OO 5.54E+04 129Te 3.0lE+Ol 1 .13E+Ol 7.33E+OO 2.31E+01 1.26E+02 I O.OOE+OO 2.27E+01 I 13lmTe 1.66Et 03 8.10E+02 6.75E+02 1.28E+03 8.21E+03 O.OOE+OO 8_04E+04

mTe 1.89E+Ol 7.88E+OO 5.96E+OO 1 .SSE+Ol 8.26E+Ol O.OOE+OO 2-EV£+00 n2Te 2.41E+03 i.56E+03 l .47E+03 1.72E+03 1.50E+04 O.OOE+OO 7.38E+04

.l.301 2.71E+O'l 8.01 E+01 3.16801 6.79E+03 1.25E+02 O.OOE+ OO 6.89E+Ol 1n1 1.49E+02 2.14E+02 1.22E+02. 7.00E+04 3.66E+02 O.OOE+OO 5.64E+01 1321 7.29Et 00 l .95E+Ol 6.82E+OO 6.82E+02 3.11E+ 01 O.OOE+OO 3.66 E+OO 133 1 5.14E+Ol 8.87E+01 2.70E+01 1.30E+04 l .55E+02 O.OOE+OO 7.97E+Ol 134 1 3.81E+OO l.03E+Ol 3.70E+OO 1.79 E+02 l .64Et 01 O.OOE+OO 9.0lE-03 u,, l.59E+01 4.17E+Ol 1.54E+Ol 2.75E+03 6.68E+Ol O.OOE+OO 4.70 E+Ol u Cs 2.98 E+05 7.09E+Q5 5.79E+05 O.OOE+OO 2 .29E+05 7.61E+04 1.24E+04 J36Cs 3.'12E+04 1.23E+OS 8.86E+04 O.OOE+OO 6,85E+04 9.38 E+C:l3 1 .40E+04 137 (5 3.82E+OS 5.2.2E+05 3.42E+05 O,OOE+OO 1.77E+OS 5.89E+04 1.01E+04 138 (5 2.64E+02 5.22E+02 2.59E+02 O.OO E+OO 3 .84E+02 3.79 E+Ol 2.23E-03 Bsaa 9.29 E-01 6.62E-04 2.72£-02 O.OOE+OO 6.19£-04 3 .75 E-04 1. 65E+OO 140Ba 1.94E+02 2.44E-01 1.27E+*01 O.OOE+OO 8.30£-02 1 .40E-01 4,00E+02 141Ba 4.SlE-01 3.41E-04 1.52.E-02 O.OOE+OO 3.17E-04 1,93 £-04 2.13E- 10 141 8a 2.04£-01 2.lOE-04 1. 28E-02 0.00 E+OO 1.77E- 04 l .19 E-04 2.87E-19 14ola 1.SOE-01 7.54E-02 1.99£-02 O.OOE.+00 O.OOE+OO O.OOE+OO 5.54E+03 142La I 7 .66E-03 3.48£-03 8.68E-04 O.OOE+OO O.OO E+OO O.OOE+OO 2.54E+01 141c e 2. 24E-02 1.52 E-02 1.72E-03 O.OOE+OO 7.04E-03 O.OOE+OO 5.79E+01 143 C e 3.95E-0 3 2.92E+OO 3.23 E-04 O.OOE+OO 1.29E-03 0.00E+.00 l. 09E+02.

Page 36 of 75 INFORMATION USE June,2018

APA-ZZ-01003 Rev. 023 Table 1: Ingestion Dose Commitment Values (A;t) for Adult Age Group<1l (mrem/hr) per (µCi/ml)

Total Nuclide Bone Liver Thyroid Kidney Lung GI-LU Body 144Ce 1.17E+OO 4.88E-01 6.27E-02 O.OOE+OO 2.90E-01 O.OOE+OO 3.95E+02 14apr 5.SlE-01 2.21E- 01 2.73E-02 O.OOE+OO l.27E-01 O.OOE+OO 2.41E+03 144Pr l .80E-03 7.48E-04 9.16E-05 0.00E+OO 4.22E-04 O.OOE+OO 2.59E-10 141 Nd 3.76E-01 4.35E-01 2 .60E-02 O,OOE+OO 2.54E-01 O.OOE+OO 2.09E+03 m ru 3.68E+Ol 4.52E+OO 3.22E+OO 0,00E+OQ 2.17E+01 O.OOE+OO 3.28E+03 1s1H f 4.00E-02 1.94E-01 l.80E-02 O.OOE+OO 4.18E-02 O.OOE+OO 2.21E+02 l B?W 2 .96E+02 2.47E+.02 8.65E+Ol O.OOE+OO O.OOE+OO O.OOE+OO 8.10E+04 m Np 3.28E+04 2.85E+03 1.33E+03 O.OOE+OO 9.86E+03 O.OOE+OO 1.90E+03 239Np 2.BSE-02 2.BOE-03 1.54E-03 O.OOE+OO 8.74E-03 O.OOE+OO 5,75E+02 23S pU 5.70E+03 8.03E+02 1.43E+02 0.00E+OO 6.13E+02 O.OOE+OO 6.12E+02 239Pu

6.59E+03 8.88E+02 l.60E+02 O.OOE+OO 6.80E+02 O.OOE+OO 5.68E+02 241 Pu 1 .38E+02 7 .07E+OO 2.78E+OO l'l.OOE+OO l.28E+Ol O.OOE+OO 1.1 7E+01

.i*1Am 4.90E+04 .1.72£+04 3.24E+03 O.OOE+OO ' 2.44[+04 O.OOE+OO 4.44E+03 2*2cm l .23E+03 1.26E+03 8.20E+Ol O.OOE+OO 3.72[+02 O.OOE+OO 4.74E+03 z43Cm** 3.82E+04 1.44E+04 2 .24E+03 O.OOE+OO l.OSE+04 O.OOE+OO 4,67 E+03

Includes 240 Pu contribution

"' Includes 244 Cm contribution (1) UOTH 83-58, Calculation 88 -002-00-F, ZZ-48, ZZ-57 1 ZZ-78, HPCI 8902 1 HPCI 0406, HPCI 1604, HPCI 1802.

Page 37 of7S INFORMATION USE June, 2fJ18

APA-ZZ-01003 Rev. 023 Table 2: Bioaccumulation Factor (Bfj) (;i)

(pCi/kg) per (pCi/liter) 11 Element Bf1 Fish (Freshwater) I Element Bf1Fish (Freshwater)

H -

9.0 E - 01 Rh 1.0 E t 01 Be 2.0 E+ 00 Ag 2.3 EtOO Na 1 .0 E +02 Cd 2.0 E + 02 Cr 2.0 E + 02 Sn 3.0E+03 Mn 4 .0 E + 02 Sb 1.0 E + 00 Fe 1.0 E + 02 Te 4.0 E + 02 Co S.O E+ Ol I 1.5 E + 01 Ni 1.0 E + 02 Cs 2.0 E + 03 Cu 5.0 E + 01 Ba 4.0 E + 00 I Zn 2.0 E + 03 La 2.5 E + 01 Br 4 .2E+02 Ce 1.0 E + 00 Rb 2.0 E + 03 Pr 2.5 E + 01 Sr 3 .0 E + 01 Nd 2.5 E + 01 y 2.5 E + 01 ~u 2.5 E + 01 Zr 3.3E+OO Hf 3 .3 E + 00 Nb 3.0 E + 04 w 1.2 E + 03 Mo 1.0E+Ol Np 1.0 E + 01 Tc 1.5 E + 01 Pu 3.SE+OO Ru 1.0 E + 01 Am 2.5 E + 01 Cm 2.SE+Ol (a) Values from Regulatory Guide 1.109, Rev. 1, Table A-1 and HPCI 0406 .

Page 38 of 75 INFORMATI ON USE June, 20 18

APA-ZZ-01003 Rev. 023 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 Ki Li Mi Ni (mrem/yr) per (µCi/m 3 ) (mrem/yr) per (µCi/m 3 ) (mrad/yr) per (µCi/m 3

) (mrad/yr) per (µCi/m 3 )

a311,Kr 7.56 E-02 -~ 1 .93 E+Ol 2.88 E+02 asmKr 1.171:+03 1.46E+03 1.23 E+03 1.97 E+03 ssKr 1.61 E+Ol 1.34 E+03 l .72 E+Ol 1 .95 E+03 a1Kr 5.92 E+03 9 .73 E+03 6.17 E+03 1.03 E+04 118 Kr 1.47 E+04 2.37 E+03 1 .52 E+04 2.93 E+03 I S9Kr 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 131m Xe 9.15 E+Ol 4.76 Et02 1.56 E+02 1.11 E+oa 133m Xe 2.51 E+02 9 .94. E+02 3 .27 802 1.48 E+03 133 Xe 2.94 E+02 3.06 E+02 3.53 E+02 l 1,05 E+03 BSrn Xe 3.12 E+m 7 .11 E+02 3.36 E+03 7.39 E+02 Bsxe 1.81 E+03 1.86 E+03 1.92 E+03 2.46 E+03 137Xe 1.42 E+03 1.22 E+04 1.51 E+03 1 .27 E+04 m xe 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 INFORMA TION USE June,2018

APA-ZZ-Oi 003 Rev. 023 Table 4: Ground Plane Pathway Dose Factors (R1)

(m 2 mrem/yr) per (µCi/sec)

Nuclide Total Body Skin Nuclide Total Body Skin 3H O.OOE+OO O.OOE+OO 1135n 1.43Et07 4 .09E+ 07 7

Be 2 .24E+07 3 .21E+07 124 Sb 8.74E+08 1.23E+09 Sl(r 4 .66E+06 5 .51E+06 125 5b 3.57E+09 5.19E+D9 54Mn 1.39E+09 1 .63E+09 U7mre 9.17E+04 1.08E+05

ssFe 0.00E+OO O.OOE+OO 119mTe 1.98E+07 2 .31E+07 59Fe 2.73E+08 3.21E+08 1301 5 .51E+06 6.69E+06 57co 2 .98E+08 4.37E+08 :1311 1.72E+07 2.09E+07 ssco I 3.79E+.08 4.44E+08 Bl l 1.25E+06 1.47E+06 6oco 2.15E+10 2.53E+10 133 1 2.45E+06 2.98E+06 G, Ni O.OOE+OO 0.00E+OO 134, 4 .47E+05 5.31E+OS 65 Zn 7.47E+08 8.59E-+'08 ml 2.53E+06 2.95E+06 s6 Rb 8.99E+06 1.03E+07 t34Cs 6.SSE,1-09 8.00E+09 1 agsr 2.16E+04 2.51E+04 136Cs 1.51E+08 1.71E+08 9osr O.OOE+OO 0 .00E+ OO incs 1.03E+10 1 .20E+10 9oy S.36E+06 6.32E+06 I

140Ba 2.0SE+07

' 2.35E+07 9l y 1.07E+06 1.21E+06 140La 1.47E+08 1.66E+08 9szr 2.45E+08 2.84E+08 14.ice 1.37&:+07 1.54E+07 gsNb 2 .50E+08 2.94E+08 I t44ce 6.96E+07 8.04E+07 103Ru 1.08E+08 1.26E+08 rnJ pr 0.00E+OO O.OOE+OO 106Ru 4.22E+08 5.07E+08 14'1 pr 4 .35E+07 5,00E+ 07

~

llOmAg 3.44E+09 4.01E+09 1_47 Nd 8.39E+06 1,01E+07 109Cd 3.76E+07 1.54E+08 154 Eu 2.21E+10 3.15E+10 191 Hf 1.97E+08 2.82E+08 Page 40 of75 INFORMATION USE June,2018

APA-ZZ-01003 Rev. 023 Table 5: Child Inhalation Pathway Dose Factors (Ri)

(mrem/yr) per (µCi/m 3)

Nuclide Bone Liver Total Body Thyroid Kidney Lung I GI-LU 3H O.OOE+OO 1.12E+03 1.12Et03 1.12E+03 1.12E+03 1.l2E+03 1.12E+03 7

Be 8.47E+02 1.44E+03 9.25E+02 O.OOE+OO O.OOE+OO 6.47E+04 2.SSE+03 1 1

s1cr O.OOE+OO O.OOE+OO 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 S4Mn 0.00E+OO 4.29E+04 9.51E+03 O.OOE+OO 1.00E+04 1.58E+06 2.29E+04 s,Fe 4.74E+04 2.52E+04 7.nE+03 O.OOE+OO O.OOE+OO 1.11E+OS 2.87E+03 S9Fe 2.07E+04 3.34E+04 1.67E+04 O.OOE+OO O.OOE+OO l .27E+06 7.07E+04 57(0 0.00E+OO 9.03E+02 l .07E+03 O.OOE+OO O.OOE+OO 5.07E+05 1.32E+04 saco O.OOE+OO ;I..77E+03 3.16E+03 O.OOE+OO 0.00E+OO 1.11Fr06 3.44E+04 60(0 O.OOE+OO l .31E+04 2.26E+04 O.OOE+OO O.OOE+OO 7.07E+06 9.62E+04 1 6aNi 8.21E+OS 4.63E+04 2.80E+04 O.OOt+OO O.OOE+OO 2.7SE+05 6.33E+03 6szn 4.25E+04 1.13E+05 7.03E+04 O.OOE+OO 7.14E+04 9.95E+05 1.63E+04 66R'b O,OOE+OO 1.98E+OS 1.14E+OS 0.00E+OO O.OOE+OO 0.00E+OO 7.99E+03 e9sr 5,99E+OS O.OOE+OO 1.72E+04 0.00E+OO O.OOE+OO 2.16E+06 1.67E+OS I sosr 1.01E+08 O.OOE+OO 6.44E+06 0.00E+OO 0.00E+OO 1,48E+07 3.43E+05 9Cly 4.11E+03 O.OOE+OO 1.11E+02 O.OOE+OO O.OOE+OO 2.62E+OS 2.68E+OS 91y 9.14E+OS O.OOE+OO 2.44E+04 O.OOE+OO O.OOE+QO 2 .63E+06 1.84E+05 95zr 1.90E+05 4.18E+04 3.70E+04 0.00800 1 5.96E+04 2.23E+06 6.11E+04 gs Nb 2.3SE+.04 9.18E+03 6.55E+03 0.00E+OO 8.62E+03 6.14E+OS 3.70E+04 I

103Ru 2.79E+03 0.00.E+OO 1.07E+03 0.00E+OO 7.03E+03 6,62E+OS 4.48E+04 106Ru 1.36Et05 O.OOE+OO 1.69Et04 0.00E+OO 1.84E+05 l.43E+07 4.29E+OS 11orn Ag 1.69Et 04 1.14E+04 9.14E+03 0.00E+OO 2. 12E+04 S.48E+06 1.00E+OS 109Cd 0.00E+OO 5.48E+OS I 2.59E+04 O.OOE+OO 4.96E+OS 1.0SE+06 2.78E+04 in sn 1.13E+OS 3.12E+03 8.62E+03 2.33E+03 0.00E+OO 1.46E+06 2.26Et05 124 5b 5.74E+04 7.40E+02 2.0DE+04 1.26E+02 O.OOE+OO 3.24E+06 1.64E+OS 125 5b 9.84E+04 7.59E+02 2.07E+04 9.10E+01 O.OOE+OO 2.32E+06 4,03E+04 I

U7rn Te 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 129rt1Te 1.92E+04 6.8SE+03 3.04E-r03 6.33E+03 5,03E+04 1.76E+06 1.82E+OS Page 41 of 75 INFORMATI ON USE June, 2018

APA-ZZ-01003 Rev. 023 Table 5: Child Inhalation Pathway Dose factors (Ri)

(mrem/yr) per (µCi/m 3 )

Nuclide Bone Liver lotal Body Thyroid Kidney Lung GI-LU 1301 8.18E+03 1.64E+04 8.44E+03 l.85E+06 2.45E+04 O.OOE+OO 5 .11E+03 1:ll l 4.811:+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 O.OOE+OO 1 2.84E+03 1321 2.12E+03 4.07E+03 1.88E+03 1.94E+OS 6.25E+03 O,OOE+OO 3.20E+03 1331 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 O.OOE+OO 5.48E+03 1341 1.171:+03 2.16E+03 9.9SE+02 S.07E+04 3.30E+03 O.OOE+OO 9.SSE+02 1351 4.92E+03 8.73E+03 4.14E+03 7.92E+OS 1.34E+04 O.OOE+OO 4.44E+03 l34(s 6.51E+05 l.01E+06 2.25E+OS O.OOE+OO 3.30E+OS 1.21E+05 3.8SE+03 136(5 6.51E+04 1.71E+OS l.16E+OS 1 O.OOE+OO 9.SSE+04 l.45E+04 4.18E+03 131Cs 9.07Et05 8.25E+OS l.28E+OS 0.00E+OO 2.82E+OS 1.04E+05 3.62E+03 14oBa 7.40E+04 6.48E+01 4.33E+03 O.OOE+OO 2.11E+01 l.74E+06 1.02E+OS HoLa 6.44E+02 2.25E+02 7.SSE+Ol i O.OOE+OO 0.BOE+OO l.83E+OS 2.26E+OS 141 Ce 3.92E+04 1.95E+04 2.90E+03 O.OO!i:+00 8.55E+03 S.44E+OS 5.66E+04

~44 Ce 6.77E+06 2.12E+06 3.61E+OS O.OOE+OO 1.17E+06 1.20Et07 3.89E+OS I 143pr l.85E+04 1 5.SSE+03 9.14E+02 O.OOE+OO 3.00E+03 4.331!+0.S 9.73E+04 144 pr 5.96E-02 1.85E-02 3.00E-03 0.00E+OO 9.77E-03 1.57E+03 l.97E+02 141Nd 1.08E+04 8.73E+03 6.81E+02 O.OOE+OO I 4.81E+D3 3 .28E+05 8.21E+04 is>> Eu l.01E+D7 9.21E+OS 8.40E+05 0.00E+OO 4.03E+06 6.14E+06 1.lOE+OS 1s1Hf 2.78Et04 1.0lE+OS 1.25E+04 0.00E+OO 2.05E+04 l.06E+06 6.62E+04 Page 42 of 75 INFORMATION use June, 2018

APA-ZZ-01003 Rev. 023 TabJe 6: Child Grass- Cow - Milk Pathway Dose Factors (R1)

(m 2 mrem/yr) per (µCi/sec)

Nuclide Bone Liver Total Body Thyroid Kidney Lung GI-LU 3H O.OOE+OO 1.57E+03 l.57E+03 1.57E+03 l.57E+03 1.57E+03 1.57E+03 7

Be 7.SOE+03 1.28E+04 8.20E+03 O.OOE+OO 1.25E+04 O.OOE+OO 7.12E+OS s1cr O.OOE+OO O.OOE+OO 1.02E+OS 5.66E+04 1,SSE+04 1.03E+OS 5.40E+06 .

54 Mn O.OOE+OO 2.10E+07 5.59E+06 O.OOEtOO 5.89E+06 O.OOE+OO 1.76E+07 ssFe 1.12E+08 5.94E+07 1.84E+07 0.001;+00 0.00E+OO 3.36E+07 1.10E+07 s9Fe 1.20E+08 l.95E+08 9.70E+07 0.00E+OO 0.00E+OO 5 .64E+07 2.03E+08 57 Co O.OOE+OO 3.84E+06 7.78E+06 O.OOE+OO O.OOE+OO O,OOE+OO 3.1SE+07 saco O.OOE+O.O 1.21E+07 3.72E+07 0.00E+OO O.OOE+OO O.OOE+OO 7.08E+07 60( 0 O.OOE+OO 4.32E+07 1.27E+08 0 ..00E+OO O.OOE+OO O.OOE+OO 2.39E+08 63 Ni 2.97E+l0 1.59E+09 1.01E+09 0.00E+OO O.OOE+OO O.OOE+OO 1.07E+08 65zn 4.14E+09 1.lOE+lO 6.86E+09 O.OOE+OO 6.95E+09 O.OOE+OO 1.94E+09 a6Hb 0.00E+OO 8.78E+09 5.40E+09 O.OOE+OO O.OOE+OO O.OOE+OO 5.65E+08 agsr 6.63E+09 O.OOE+OO 1.89E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.57E+08 I

9osr 1.12E+11 O.OOE+OO 2.84E+10 O.OOE+OO O.OOE+OO O.OOE+OO 1.51E+09 9oy 3.38E+03 O.OOE+OO 9.0SE+Ol O.OOE+OO O.OOE+OO O.OOE+OO 9,62E+06 9ly 3.91Et04 0.00E+OO 1.04E+03 O.OOE+OO 0.00E+OO O.OOE+OO 5.20E+06 sszr 3.84Et03 8.43E+02 7.51E+02 0.00E+OO 1.21E+03 I

O.OOE+OO 8.80E+05 gsNb 3.72E+05 1.4SE+OS 1.03Et05 O.OOE+OO 1.36E+OS O.OOE+OO 2.68E+08 103Ru 4.29E+03 O.OOE+OO 1.65E+03 O.OOE+OO ;L08E+04 O.OOE+OO 1.11E+.OS ioGRu 9.2SE+04 O.OOE+OO 1.15E+04 0.00E+OO 1.2SE+05 O.OOE+OO l.44E+06 llOm Ag 2.09E+08 1.41E+08 1.13E+08 O.OOE+OO 2.63E+08 O.OOE+OO 1.68E+10 109Cd 0.00E+OO 3.86E+06 1.79E+OS O.OOE+OO 3.45£+06 O.OOE+OO l.25Et07 1135n 6.11E+08 1.26E+07 3.48E+07 9.29E+08 O.OOE+OO O.OOE+OO 4.32E+08 124Sb 1.09E+08 1.41E+06 3.81E+07 2.40E+OS O.OOE+OO 6.03E+07 6.80E+08 1255b 8.71E+07 6.72 E+OS 1 .83E+07 8.07E+04 0.00E+OO 4.86E+07 2.08E+08 1271T' Te 2.08E+08 5.61E+07 2.47E+07 4.98E+07 5.94E+08 I O.OOE+OO 1.69E+08 1ismTe 2.72E+08 7.59E+07 4.22 Et 07 8.76E+07 7.98E+08 O.OOE+OO 3.31E+08 Page 43 of 75 INFORMATION USE June,2018

APA-ZZ-0 1003 Rev. 023 Table 6: Child Grass- Cow - Milk Pathway Dose Factors (Ri)

(m 2 mrem/yr) per (µCi/sec)

Nuclide Bone Liver Total Body Thyroid Kidney Lung Gl ~LLI 1301 1.73E+06 , 3.50E+06 l .80E+06 3.85E+08 5. 23E+06 O.OOE+OO 1.64E+06 131 1 1.30E+09 l.31E+09 7.46E+08 4.34E+11 2.15E+09 0.00E+OO l.17E+08 1321 6.92E-01 l .27E+OO 5.85E-01 5.90E+01 1.95E+OO O.OOE+OO 1.SOE+OO 1331 1.72E+07 2.13E+07 8.0SE+06 3.95E+09 3.54E+07 O.OOE+OO 8.57E+06 134 1 0.00E+OO O.OOE+OO 0.00E+OO 0.00E+OO O.OOE+ OO 0.00E+OO O.OOE+OO 135 1 5.41E+04 9.74E+04 4.61E+04 8.63E+06 1.49E+05 O.OOE+OO 7.42E+04 m es 2.27E+10 3.72E+10 7.84E+09 O.OOE+OO 1.15E+10 4.14E+09 2.00E+08 136(5 1.01E+09 2.78E+09 1.80E+09 O.OOE+OO 1.48E+09 2.21E+08 9.78E+07 l37Cs 3.23E+10 3.09E+l0 4.56E+09 O.OOE+OO 1.01E+10 3.62E+09 1.93E+08 140 8 a 1.17E+08 1.03E+OS 6.84E+06 O.OOE+OO 3.34E+04 6.12E+04 5.94E+07 140 La 1.78E+02 6.23E+01 2.10E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.74E+06 1Al(e 2.19E+04 1.09 E+04 1.62E+03 0.00E+OO 4.79E+03 O.OOE +OO 1.36E+07 144ce 1.62E+06 5.09E+05 8.67 E+04 O.OOE+OO 2.82E+OS O,OOE+OO 1.33E+08 l43 pr 7 .19E+02 2.16E+02 3.57E+01 O.OOE+OO 1.17E+02 O.OOE+OO 7.76E+OS

' 144 pr 5.04E+OO l .56E+OO 2.53E-01 O.OOE+OO 8.24E-01 0.00E+OO 3.35E+03 141Nd 4.45E.:t02 3.61E+02 2.79E+Ol O.OOE+OO 1.98E+02 O.OOE+OO 5.71E+OS 1s4Eu 9.43E+04 8.48E+03 7.75E+03 0.00£.hOO 3.73E+04 O.OOE+OO 1.97E+06

!Bl Hf 6.44E+02 2.35E+03 2.91E+02 O.OOE+OO 4.76E+02 O.OOE+OO 8.66E+OS Page 44 of 75 INFORMA TION USE June, 2018

APA-ZZ-01003 Rev. 023 Table 7: Child Grass- Goat - Milk Pathway Dose Factors (Ri)

(m 2mrem/yr) per (µCi/sec)

Nllclide. Bone Liver Total Body Thyroid Kidney Lung GI-LLI 3H O.OOE+OO 3.20E+03 3 .20E+03 3.20E+03 1

3.20E+03 3.20E+03 3.20E+03 7Be 9.00E+02 l.53E+03 9.84E+02 O.OOE+OO 1.50E+03 O.OOE+OO 8.SSE+04 sicr 0.00E+OO O.OOE-t'OO l .22E+04 6.79E+03 l.85E+03 l .24E+04 6.48E+OS s4Mn O.OOE+OO 2.52E+06 6.71E+OS O.OOE+OO 7.06E+OS O.OOE+OO 2.11E+06 I ssFe 1.45E+06 , 7.72E+OS 2 .39E+OS O,OOE+OO O.OOE+OO 4.36Et05 1.43E+OS s9Fe l.S6E+06 2.53E+06 1 .26E+06 O.OOE+OO O.OOE+OO . 7.34E+05 I

2.64E+06 57(0 O.OOE+OO 4.61E+OS 9.33E+OS 0.00E+OO O.OOE+OO O.OOE+OO 3.78E+06 seco O.OOE+OO 1.46E+06 4.46E+06 O,OOE+OO O.OOE+OO O.OOE+OO 8.50£+06 Goco 0.00E+OO 5.19E+06 1.53E+07 O.OOE+OO O.OOE+OO O.OOE+OO '2.87E+07 63Ni 3.56E+09 l.91E+08 1.2lE+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.28E+07 65zn 4.97E+08 1.32E+09 ~.23E+08 0.00E+OO 8.34E+08 O.OOE+OO 2.32E+08 eGRb O.OOEtOO l .OSE+09 6.48E+08 0.00E+OO 0.00E+OO O.OOE+OO 6.78E+07 e9Sr 1.39E+10 O.OOE+OO 3.97E+08 O.OOE+OO O.OOE+OO O.OOE+OO 5.39E+08 90Sr 2.35E+11 O.OOE+OO 5.95E+10 O.OOE+OO 0.00E+OO O.OOE+OO 3.16E+09 9Dy 4.06E+02 O.OOE+OO l.09E+01 O.OOE+OO 0.00E+OO O.OOE+OO l .15E+06 91y 4.69E+03 O.OOE+OO 1.25E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.25E+05 95zr 4.60E+02 1.01E+02 9.0lE+Ol O.OOE+OO 1.45E+02 0.00E+OO 1.06E+OS 9SNb 4.46E+04 1.74E+04 1.24E+04 O.OOE+OO 1.63E+04 O,OOE+OO 3.21E+07 103Ru 5.14E+02 O.OOE+QO 1.98E+02 0.00E+OO 1.29E+03 O.OOE+OO 1.33E+04 106Ru 1.11E+04 0.00E+OO 1.38E+03 O,OOE+OO 1.50E+04 O.OOE+OO 1.73Et05 nom Ag 2.S1E+07 1.69E+07 1.35E+07 O.OOE+OO 3.15E+07 O.OOE+OO 2.01~+09 109Cd O.OOE+OO 4.64E+OS 2.15E+04 0.00E+OO 4.14E+OS O.OOE+OO 1.50£+06 113Sn 7.33~+07 l.51E+06 4.18Et06 1.11E+08 O.OOE+OO O.OOE+OO 5.18E+07 124 5b 1.30£+07 1 .69E+OS 4.57£+06 2.88E+04 O.OOE+OO 7.24E+06 8.16E+07 12S5b 1.05E+07 8.06E+-04 2.19E+06 9.68E+03 O.OOE+OO 5.83'E+06 2.SO'E+07 127rn Te 2.50E+07 6.73E+06 2.97E+06 5.98E+06 7.13E+07 O.OOE+OO 2.02E+07 129m Te 3.26E+07 9.10£+06 5.06E+06 l.OSE+07 9.57E+07 O.DOE+OO 3.98E+07 Page 45 of 75 INFORMATION USE June, 2018

APA-ZZ-01003 Rev. 023 Table 7: Child Grass- Goat - Milk Pathway Dose Factors (R1)

(m 2 mrem/yr) per (µCi/sec)

Nuclide Bone liver Total Body Thyroid Kidney Lung GI- LLI

]301 2.08Et06 4.20Et06 2.16Et06 4.62E+08 6,27Et06 O.OOE+OO 1.96E+06 1311 1.57E+09 1.57f+09 8,9SE+08 5.21E+ll 2.58E+09 0.00E+OO 1.40E+08 1321 8,30E-Ol 1.53E+OO 7.02E-01 7.08E+01 2.34£+00 O.OOE+OO l .80E+OO m1 2.06E+07 2.55E+07 9.66E+06 4.74E+09 4.25E+07 O.OOE+OO l.03E+07 1341 O.OOE+OO O.OOE+OO 0.00E+OO 0.0QE+OO 0.00E+OO O,OOE+OO O.OOE+OO 135 1 6.49E+04 l.17E+OS 5.53E+04 1.04E+07 l.79E+OS O.OOE+OO 8.90E+04 m es 6.80E+10 1.12E+ll 2.35E+10 0,00E+OO 3.46E+10 1 .24E+10 6.01E+08 136(5 3.04Et09 8.35E+09 5.40E+09 0.00E+OO 4.45E+09 6.63Et08 2.93E+08 B7(s 9.68E+l0 9.27E+10 1.37E+10 O.OOE+OO 3.02E+10 l.09E+10 5.80E+08 140Ba 1.41Et07 l.23E+04 8.21E+OS O.OOE+OO 4.01Et03 7.35E+03 7 .13 E+06 140La 2.14Et 01 7.47E+OO 2,52E+OO 0.00E+OO O.OOE+OO O.OOE+OO 2.08E+OS 141Ce 2.63E+03 1.31E+03 1.951:+02 O.OOE+OO 5.75E+02 I O.OOE+OO 1.63E+06 l.44Ce 1.95E+05 6.11E+04 1.04Et04 0.00E+OO 3.38E+04 O.OOE+OO l.59E+07 143pr 8.63E+01 2.59E+01 4.28E+OO O.OOE+OO 1.40E+Ol O.OOE+OO 9.31E+04 144Pr 6.0SE-01 1.87E-01 3.04E-02 O.OOE+OO 9.89E-02 O..OQE+OO 4.03E+02 147Nd 5.34E+01 4.33Et01 3.35E+OO O.OOE+OO 2.37E+ 01 O.OOE+OO 6.85E+04 1s4Eu 1.13E+04 1.02E+03 9.29E+02 0.00E+OO 4.47E+03 O.OOE+OO 2.37E+OS lBl Hf 7.73E+01 2.81E+.02 3.49E+Ol O.OOE+OO 5.72E+Ol O.OOE+OO l.04E+05 Page 46 of75 INFORMATION USE June, 2018

APA-ZZ-01003 Rev . 023 Table 8*: Child Meat Pathway Dose Factors (Ri)

(m 2 mrem/yr) per (µCi/sec)

Nuclide Bone Liver Total Body Thyroid Kidney Lung GI-LLI JH O.OOEtOO 2.34Et02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 7

Be 7.38E+03 1.26E+04 8.07E+03 O.OOE+OO 1.23E+04 0.00E+OO 7.00E+OS s1cr O.OOE+OO O.OOE+OO 8.80E+03 4.88E+03 1.33E+03 8.92Et03 4.67E+OS sa Mn O,OOE+OO 8.02E+06 2.14E+06 0.00E+OO 2.25E+06 O.OOE+OO 6.73Et06 ssFe 4.58Et08 2.43E+08 7.52E+07 O.OOE+OO O.OOE+OO 1.37E+08 4.50£+07 S9Fe 3.77E+08 6.10E+08 3.04Et08 O.OOE+OO 0.00E+OO 1.77E+08 6.35E+08 57cc 0.00E+OO 5.92E+06 1 .20E+07 0.00E+OO O.OOE+OO O.OOE+OO 4.85Et07 ssco O.OOE+OO 1.64E+07 5.03E+07 O.OOE+OO O.OOE+OO O,OOE+OO 9.59E+07 60(0 O.OOE+OO 6.94E+07 2.0SE+08 O.OOE+OO 0.00E+OO O.OOE+OO 3.84E+08 63NI 1 2.92E+10 1.56Et09 9.92E+08 O.OOE+OO 0.0DE+OO O.OOE+OO 1.05E+08 sszn 3,76E+08 1.00E+09 6.23E+08 0.00E+OO 6.31E+08 O.OOE-f00 1.76Et08 B6Rb O.OOE+OO 5.77E+08 3.55E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3 .71E+07 a9Sr 4.82E+08 O.OOE+OO 1.38E+07 O.OOE+OO O,OOE+OO O.OOE+OO 1.87E+07 9osr l .04E+10 O.OOE+OO 2.64E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.40E+08 90 y 1.93E+05 O.OOE+OO 5 .16E+03 O.OOE+OO O.OOE+OO O.OOE+OO S.49E+08 9ly 1.80E+06 O.OOE+OO 4.82E+04 O.OOE+OO 0.00E+OO O.OOE+OO 2.401:+08 95zr 2.67E+06 5.86E+OS 5.22E+05 Q.OOE+OO 8.39E+05 O.OOE+OO 6.11E+08 9sNb 4.26Et06 1.66E+06 1.18E+06 O.OOE+OO 1.56E+06 O.OOE+OO 3.07E+09 103Ru 1.SSE+08 0.00E+OO 5.96E+07 O.OOE+OO 3.90E+08 O.OOE+OO 4.01E+09 iosRu 4.44E+09 O.OOE+OO 5.54E+08 0.00E+OO 6.00E+09 O.OOE+OO 6.91E+10 llOm Ag 8.40E+06 5.67E+06 4.53E+06 O.OOE+OO 1.06E+07 O.OOE+OO 6.75E+08 109Cd 0.00E+OO l .91E+06 8.84E+04 O.OOE+OO 1.70Et 06 0.00E+OO 6.18E+06 3

u Sn 2.18E+09 4.48E+07 1.24E+08 ' 3.31E+09 , O.OOE+OO 0 .00E+OO 1.54~+09 124 5b 2.93E+07 3.80E+05 1.03E+07 6.46E+04 O.OOE+OO 1.62E+07 1.83E+08 1

125 Sb 2.85E+07 2.20E+05 5.97£+06 2.64E+04 O.OOE+OO l.59E+07 6,81E+07 u1"'Te. 1.78E+09 4.78E+08 2.11E+08 4.25E+08 5.07E+09 O.OOE+OO 1.44E+09 129m Te 1.79E+09 5.00E+08 2.78E+08 5.78£+08 5.26E+09 O.OOE+OO 2.19E+09 Page 47 of75 INFORMATION USE June, 2018

APA-ZZ-01003 Rev. 023 Table 8: Child Meat Pathway Dose Factors (Ri)

(m 2 mrem/yr) per (µCi/sec)

Nuclide Bone liver Total Body Thyroid Kidney Lung GI-LU no 1 3.06E-06 6.18E-06 I

3.18 E-06 6.80E-04 9,23E-06 O.OOE+OO 2.89E-06 13lj 1.66E+07 1.67E+07 9.47E+06 S.51E+09 2.74E+07 O.OOE+OO 1.48E+06 1321 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO ml S.70E-01 7.0SE-01 2.67E-01 1.31E-+02 l.17E+OO O.OOE+OO 2.84E-01 1341 O,OOE+OO O.OOE+OQ 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 135 1 O.OOE+OO 0.00E+OO , O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO 13A(S 9.23E+08 l.51E+09 3.20E+08 O.OOE+OO 4.69E+08 1.68E+08 8,17E+06 136(5 1. 62E+07 4.46E+07 2.89Et 07 O.OOE+OO 2.38E+07 3.54E+06 1.57E+06 137 Cs 1,33E+09 1.28E+09 l.89E+08 O.OOE+OO 4.16E+08 1.50E+08 8.00E+06 140Ba 4.39E+07 3.85E+04 2.56E+06 0.00E+OO 1.25E+04 2.29E+04 2.22E+07 140La 3.33E+02 1.17E+02 3.93Et01 O.OOE+OO O.OOE+OO O.OOE+OO 3.25E+06 141ce 2.22E+04 1.11E+04 1.65E+03 O.OOE+OO 4.86E+03 0.00E+OO 1.38E+07 144Ce 2.32E+06 7 .27Et 05 1.24E+05 O.OOE+OO 4.02E+OS O.OOE+OO l.89E+08 m pr 3.34E+04 1.00E+04 1.66E+03 O.OOE+OO 5.43Et03 0.00E+OO 3.61E+07 144pf 5 .63E+02 1.74E+02 2.83E+01 O.OOE+OfJ 9.21E+01 0.001:+00 3.75Et05

!47Nd l .17E+04 9 .48E+03 7.34E+02 O.OOE+ OO S.20E+03 O.OOE+OO 1.SOE+07 1sqEu 1.12E+07 1.0lE:+-06 9.20E+OS O.OOE+OO 4.43E+06 O.OOE+OO 2.34E+08 1a1Hf 4.77E+06 1.74E+07 2.15Et06 O.OOE+OO 3.53E+06 0.00E+OO 6.41E+09 Page 48 of 75 INFORMATION USE June,2018

APA-ZZ -01003 Rev. 023 Table 9: Child Vegetat ion Pathway Dose Factors (R1) 2 (m mrem/yr) per (µCi/sec)

Nuclide Bone Liver Total Body Thyroid Kidney Lung GI-LU "H D.OOE+OO 4.01E+D3 4.01E+03 4.01E+03 4.01E+03 4.01E+03 4.01E+D3 7

Be 3.38E+OS 5.76E+DS 3.7DE+OS 0.00E+OD 5.6SE+OS O.ODE+OO 3.2lE+07 s1cr O.OOE+OO O.OOE+OO 1.17E+DS 6.50E+04 I 1.78E+04 l .19E+OS 6.21E+06 s4Mn O.OOE+OO 6.65E+08 1.77E+08 O.OOE+OO 1.86E+08 O.OOE+OO 5.58E+08 ssFe 8.01E+08 4.25E+08 1.32E+08 O.OOE+OO O.OOE+OO 2.40.E+08 7.87E+07 ss Fe 3.98E+08 6.43E+08 3.20E+08 0.006+00 O,OOE+OO 1.87E+08 6.70E+08 s1co O,OOE+OO 2.99E+07 6.04E+07 O.ODE+DO ' O.OOE+OO 0.00E+OO }.45Et08 I

58(0 O.OOE+OO 6.44E+07 1.97E+08 O.ODE+OO O.OOE+OO O.OOE+OO 3.76E-l'08 60(0 O.OOE+OO 3.78E+08 l .12E+09 O.OOE+OO 0.00E+OO O.OOE+OO 2.10E+09 63 Ni 3.95E+10 ' 2.11E+09 1.34E;t-09 O.OOE+OO 0.DOE+OO 0.00E+OO 1.42E+08 6szn 8.13E+08 2.17E+09 1.35E+09 0.00E+OO 1.36E+09 O.OOE+OO 3 .80E+08 a6Rb O.OOE+DO 4.52E+08 2.78E+08 0.00E+OO O.OOE+OO O.ODE+OO 2.91E+D7 egsr 3.60E+10 0.0DE+OO 1.03E+D9 O.OOE+OO O.OOE+OO O.OOE+OO l .39E+09 I sosr 1.24E+l2 O.OOE+OO 3.15E+11 O.OOE+OO 0.00E-1'00 O.OOE+OO 1.67E+l0 soy 3.01E+06 O.OOE+OO 8.04E+04 O.OOE+OO O.OOE+OO 0.00E+QO 8.56E+09 91y 1.86E+07 0.00E+DO 4.99E+05 O.OOE+OO O.OOE+OD 0.00E+DO 2.48E-ti09 95zr 3.86E+06 8.48E+OS 7.SSE+OS O.OOE+OO 1.21E+06 O.OOE+OO 8.85E+08 9sNb 7.48E+OS 2 .91E+05 2.08E+05 O,OOE+OO 2.74E+DS O.OOE+OO 5.39£+08 103Ru 1.53E+07 O.OOE+OO 5.90Et06 O.OOE+OO 3.86E+07 O.OOE+OO 3.97E+08 106 Ru 7.45E+08 O.OOE+OO 9 .30E+07 O.OOE+DO 1.01E+09 0.00E+OO 1.16E+l0 110m Ag 3.21E+07 2.17E+07 1.73E+07 0.00E+OO 4.04E+07 O.OOE+OO 2.58E+09 1ogCd O.OOE+OO 2.45E+08 1.14E+07 O.OOE+OO 2.18E+08 0.00E+OO 7.94E+08 113 5n l .58E+09 3 .25E+07 9.00E+07 2.40E+09 O,OOE+OO O.OOE+OO 1.12E+09 124 5b 3.52E+08 4.57E+06 1.23E+08 7.77E+OS 0.0DE+OO 1.95E+08 2.20E*f09 l2'S5b 4.99E+08 3.85E+06 1.05E+08 4.63E+D5 O.OOE+OO 2.78E+08 l.1.9E+09 tnm Te 1.32E+09 3.56E+08 1.57Et08 3.16E+08 3.77E+09 O.OOE+OO l.07E+09 129m Te 8.41E+08 2.35E+08 1.31E+08 2.71E+08 2.47E+09 O.OOE+OO 1.03E+09 Page 49 of 75 INFORMATION USE June, 2018

APA-ZZ-01003 Rev. 023 Table 9: Child Vegetatio n Pathway Dose Factors (Rr)

(m 2 mrem/yr) per (µCi/sec)

Nuclide Bone Liver Total Body Thyroid Kidney Lung Gl-1:LI 130[ 6.16E+OS 1.24E+06 6.41E+05 l.37E+08 1.86E+06 O.OOE+OO 5.82E+OS 1311 1.43E+08 1.44E+08 8.17E+07 4.76E+10 2.36E+08 O.OOE+OO 1.28E+07 1321 9.23E+01 1.70E+02 7.80E+01 7.87E+03 2.60E+02 O.OOE+OO 2.00E+02

.1331 3.53E+06 4.37E+06 1.65E+06 8.12E+08 7.28E+06 O.OOE+OO 1.76E+06 134 1 1.56E-04 2.89E-04 1.33E-04 6.65E-03 4.42E-04 O.OOE+OO 1.92E-04 us, 6.26E+04 1.13Et05 5.33E+04 9.98E+06 1

1.73E+05 O.OOE+OO 8.59E+04 134 Cs 1.60E+10 2.63E+10 5.SSE+.09 1 0.00E+OO 8.15E+09 2'.93E+09 1.42E+08 mes 8.24E+07 2.27E+08 1.47E+08 O.OOE+OO 1.21E+08 1.80E+07 7.96E+06 137 Cs 2.39E+10 2.29E+10 3.38E+09 O.OOE+OO 7.46E+09 2. 68E+09 1.43E+08 140Ba 2.77E+08 2.43E+OS 1.62E+07 0.00&:+00 7.90E+04 1.45E+OS 1.40E+08 14Dla 3,36E+04 1.18E+04 3.96E+03 O.OOE+OO O.OOE+OO O.OOE+OO 3.28E+08 1uce 6.56E+05 3.27E+05 4.86E+04 O.OOE+OO l.43E+05 0.001:+00 4.08E+08 144Ce 1.27E+08 3.98E+07 6.78E+06 0.00E+OO 2.21E+07 O.OOE+OO 1.04E+l:0 143pr 1.46E+OS 4.37E+04 7.23E+03 0.00E+OO 2.37E+04 O.OOE+OO 1.57E+08 144pr 7,88E+03 2.44E+03 3.97E+02 0.00E+OO l.29E+03 O.OOE+OO 5.25E+06 141Nd 7 .15E+04 5.. 79E+.04 4.48E+03 O.OOE+OO 3.18E+04 O.OOE+OO 9.17E+07 1s4Eu 1.66E+08 1.SOE+07 L 37E+07 0.00E+OO 6.S7E+07 0.00E+OO 3.48E+09 1s1Hf 4.90E+05 1.79E+06 2.21E+OS O.OOE+OO 3.63E+OS O.OOE.t-00 6.59E+08 Page 50 of 75 INFORMA TION USE June, 2018

APA-ZZ-01003 Rev. 023 Table 10: Highest Annual Average Atmosp heric Dispersion Paramet ers X/Q X/Q Undecayed/ X/Q Decayed/

Locationlbl Meteorological Distance D!:!cayed/

undepleted Depleted D/Q Sector (meters) Undepleted (sec/m 3 ) (m-2)

(sec/m 3 )

{sec/m 3 )

Site Boundary 64 SSW 1400 1.8E-6 l .7E-6 1.6E-6 4.SE-9 Nearest Residence 65 *66 NNW 2900 1.lE-6 1.QE-6 9.0E-7 3.0E-9 Farming Areas within the N/A 1 .6E-6 N/A 1.6E-6 1.4E-6 5.SE-9 Site Boundary 67*68 6q Dispers'fon parameters fro1n HPCI 1503 Gs Dispers'ion paramet ers from HPC) 1504 66 Al l fngestion dose pathways are assumed to exist at the locatfon of the nearest resldent 67 Di_spersion parameters from HPCI 1 502 68 These values we re derived for a narrow scope application . Extreme ca ution should be exerc1sed when determinin g their suitability for use in other applicati ons Page 51 of 75 INFORMATION USE June,2018

APA-ZZ ~01003 Rev. 023 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 Beta Air & Gamma Air N/A 16.11.2.2 (2.26 day half-life)

Noble Gas, X/Q, decayed/undep!eted Total Body & Skin (2 .26 day half-life) N/A 16.11.2.1 Site Boundary X/Q, decayed/depleted 16.11.2.1 Inhalation Child Nearest Resident (8 day half-life) 16.11. 2.3 Site Boundary Ground Plane Deposition D/Q N/A 16.11.2.3 Nearest Resident lrngestion pathways D/Q,i; Child 16.11.2.3 Nearest Resident

For 3 H, X/Q decayed/depleted ls used instead of D/Q.69 69 Regulatory Gulde 1.109, Appendlx C, Section 3.a Page 52 of 75 INFORMATION USE June,201 8

APA-ZZ-01003 Rev. 023 Table 12: Application of Atmospheric Di spersion Parameters Annual Radioactive Effluent Release Report Dose Pathwa y Controlling Dispersion Parame ter Dispersion Values70 Controlling Location Age Group Noble Gas, X/Q, decaye d/undep leted Site Boundary Beta Air & Gamma Air Dose N/A Conturr ent (2 .26 day halHfe) Nearest Resident Noble Gas, X/Q, decayed/undepleted Site Boundary Concurrent Total Body & Skin Dose N/A Nearest Resident (2.26 day half-life)

Historical Inside Site Boundary I

Site Boundary Ground Plane Deposition Dose Concurrent D/Q N/A Nearest Resident I

Historical Inside Site Boundary Site Boundary I Child Concurrent X/Q, decayed/depleted Nearest Resident Inhalation Dose (8 day half-life) Concurrent Nearest Residence Adult Historical Inside Site Boundary D/Q Ingestion Dose Pathways (For H3, X/Q, decayed /deplete d Site Boundary Child Concurrent Is used instead of D/Q.)71 Nearest Resident 14 C Child Concurrent Nearest Resident All Dose Pathways 72 X/Q, undeca yed/und epleted Adult Historical Inside Site Boundary 70 Historical',

i.e., 5 year average , dispersion parameters for activities inside the Site 71 Boundary are provided in Table 1O.

Regulatory Gulde 1.109, Appendix C, Section 3.a 12 See Appendix A Page 53 of 75 INFORMATION USE June,20 18

APA-ZZ-01003 Rev. 023 Table 13: Meteorological Data Selection Hierarchy First Second Third Parameter Primary Alternate Alternate Alternate Wind Speed lOmA 10m B 60tn A 60m B Wind Direction lOmA 10m B 60mA 60m B Air Temperatu re lOmA 10m B Wind Variability lOmA 10m B 60m A 60m B Temp Difference 60-lOm A 60-lOm B Dew point/Rela tive Humidity lOmA 60m B Precipitat ion lm (a) 'A' indicates Alpha train meteorolo gical instrumen tation .

(b) 'B' indicates Bravo train meteorolo gical instrumen tation.

Page 54 of 75 INFORMATION USc June, 2018

APA-ZZ-0 1003 Rev . 023 Appendix A: Methodology for Calculating. Dose from 14 C in Gaseous Effluents 1} Introduction The purpose of this Appendix is to provide methodol ogy and paramete rs for calculating (1) the quantity of 14 C released in gaseous effluents , (2) the dose to the Member of the Public at the nearest recepto r location due to 14 C released in gaseous effluer,its , and (3) the dose frotn 14C released in gaseous effluents to the Member of the Publrc due to activities within the Site Boundary.

The quantity of 14 C discharge d can be estimated73 by sample measurem ents , or by use of a normalized 14C source term and scaling factors based on power generatio n,74 or by use of the GALE code, 75 or by use of the EPRI site specific or proxy methodol ogles.76

Any of these methodologies is acceptable for estimating the 14G discharged in gaseous effluents.

2} Assumptions

a. The total quantity of 14 C produced during the year is assumed to be released during the year in which it was produced .

b. The quantity of 14 C produced is determ1ned using the methodol ogy in EPRI TR-10211 06.

c. For conservatism , it is assumed that all 14C produced is released tn gaseous effluents .

d. The dose contribution of 14 C from liquh;:J effluents is much less than that contributed by gaseous effluents, therefore evaluation of 14C in liquid effluents is hot required .77

e. The dose to the Member of the Public is determine d in accordan ce with the methodol ogy and paramete rs in Regulator y Gu ide 1.109.

f. 14 C has a long half- life with respect to the plume transit time. 14C Is discharge d as CH4 or CO2 gas ar.id does not deplete or undergo chem ical change before it reaches rt.he receptor location . Therefore the appropria te dispersion paramete r is X/Q (undecayed and undepleted) .

12 Regulatory Guide 1.21 , rev. 2, Section 1.9 7~ NCRP Report 81 7.s NUREG-0017 76 EP RI TR-102110 6, Secti on 4 n Regulatory Guide 1.21 , rev. 2, Section 1,9 Page 55 of 75 INFORMA TION USE June,2018

APA-ZZ-01 003 Rev. 023

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.

i. The appropriate dispersion parameters for actiVlt1es within the Site Boundary is provided in Table 10.

J. 14C 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.

I. Only 14C02 discharged during periods of photosynth esis is considered for the ingestion pathways.

m. All of the 14C 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 1

Iodine and radioactive material in particulate form above background to be released from each light-water-cooled nuclear pow.er reactor in effluents to the atmosphere will not result in ah estimated annual dose or dose commitmen t 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 Rad iological* Effluent Control (REC) 16.11.2.3 limits the annual dose to the Member of the Public from ,:n I, 133 I, 3

H, and particulates with half-lives greater than 8 days released in gaseous effluents to 15 mrem to any organ. 79 14 C is released as a gas in the form of CH4 or CO2 and is not a r.adioiodtne, tritium , or particulate, therefore the design objectives in 1 O CFR 50 ,

Appendix I and the limits of REC 16.11 ,2.3 do not apply to 14 C.

10 CFR 20 .1301 (a)(1) limits the annual TEDE dose to the Member of the Public to 100 mrem.

79 10 CFR 50, Apperidix: I, section II , paragraph C w NUREG-1301 , REC 3.11.2.3 Page 56 of 75 INFORMATION USE June,2018

APA-ZZ-01003 Rev. *023 40 CFR i 90.1 O(a) limits the total annual dose from 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 at 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 of radioactive materials and direct radiation from Independent Spent Fuel Storage Installation (ISFSI) operations. There are no radioactive effluents from the ISFSI. The H1I-STORM UMAX Canister Storage System does not create any radioactive materials or have any rad ioactive waste treatment systems . COG Specif,ication 3.1.1, "Multi-Purpose Canister (MPG)", provides assurance that there are no radioactive effluents from the ISFSl. 80 14 C is a weak beta emitter and does not contribute to direct radiation dose.

4) Estimation of 14 C in Gaseous Effluents 14 c exists in all PWR systems, and any location or system t hat contains tritium most likely also will contain 14 C ih 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-1021106.81 As a general rule , 14 C in the primary coolant is essentially all organic with a significant fraction 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 du ring refueling outages, a slow transformation from an organic to an inorganic chemical form can occur.

Dissolved nltrogen gas and ammonia in the RCS could contribute to the 14 C 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 dHutlon.

Callaway maintains a hydrogen gas overpressl:Jre 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 ls produced in light water moderated nuclear power reactors by 14 N(n,p) 14 C 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 0

°Certfficate of Compliance Nia. 1040. Appendix A, Specification 5.1.

H1 EPRl TR -1 021106 , Section 4.1 82 CDP-ZZ-00200 , Appendix B, Table 1 .1," Reactor Coolant System-MO DES 1 , 2, 3, and 4". page@

of 23 Page 57 of75 INFORMATION USE' June, 2018

APA-ZZ-0 1003 Rev. 023 effluents.83 Kunz estimated the fraction of 14 C in liquid and solid wastes at <5% of that in gaseous discharge s84

Regulatory Guide 1.21 states that the dose contribution from 14C in liquid discharges is insignifica nt and evaluation of 14 C released in liquid effluents is not required .85 The release and removal pathways from the primary coolant imclude VCT venting , boron dilution , Inventory buildup on the letdown deminera lizers and filters, and reactor coolant leakage. Letdown system removal is approxim ately 1 Ci/yr. 86 The 14C production balance is shown in Figure 1.

14

( ____ _ _ _ _ __ s_o_u_rc_e_T_e_r_m_-~ _C_P_r_o_du_c_ti_on_ _ _ _ _ _ _ _ _~ )

System Inventory RCS Gaseous Release l

SoHd Re/ease Waste Gase System Fuel Pool Waste Gas System Llqu/d *Release Conlainmenl'Vent PrTmaiy System IX resins &

RWST Containment Purge Discharge Monitor Tanks Jitters Radwaste Syste*ms Aux. Bldg. Veritilation Fuel pool IX resins & filters IX resins Radwasle IX resins FIiters fu el Bldg. VenOlation Charcoal ISFSI CanTs{ers Figure 1: 14 C Production Balance

5) Chemical Form of 14 C in Gaseous Effluents Since the PWR operates w ith a reducing chemical environm ent, most, if not all, of the 14 C species initially produced are in the reduced , 1. e., organic, form and contain only a single carbon atom. Possible species include methane {1 4 CH4), methanol (1 4CH30H) ,

formaldeh yde (H214C=0 or the gem"diol H214C(OH) 2 ) and formic acid (H 14 COOH). In theory, the only ion ic species produced will be formic aoid (H 14C02H)

and some or all of the formic acid will be r-emoved by the letdown deminera lizers. Formalde hyde is soluble in water and may partially be chemisor bed 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 ls 14 CH 4 which partitions between the liquid and gas phases in the VCT and pressuriz er.87 The airborne 14C released from PWRs is predomin antly hydmcarb ons (75-95%) , mainly methane (CH4) , with only a small fraction 83 IAEA Report 421 , Section 3.1.3 84 Kunz, l985 85 Regulatory GUic\e 1.21, rev. 2, section 1.09 88 EPR/ TR-1021106 , Section 4.1 87 EPRI TR-1021106 , Section 4.1 Page 58 of7S INFORMA TION USE June,2018

APA-ZZ-Oi 003 Rev. 023 1n the form of C02.88 *89 Regulatory Guide i .21 states that 14C releases in PWRs occur primarily as a mix of organic carbon and CO2 in gaseous waste from the waste gas system. 90 NUREG-0 01791 concludes that 16.4% of the 14 C produced in a PWR will be released via the waste gas processing system , and the remainde r, 83.6%, from the Reactor Building and the Auxiliary Building .

Due to the presence of high temperatu re hydrogen recombiners in the Callaway waste gas system , 100% of the 14C 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 CO2.

The 14C released from the unit vent is assumed to be in the reduced (organic) form as CH4, therefore i 6.4% of the 14C produced is released through the Waste Gas DeGay tanks (WGDT) as 002, and' 83.6% is released via the Unit Vent as CH4.

14

( _ _ _ __ _ C_i_n_G_a_s_e_o~u_s_D_is_c_h_a_rg_e_s_ _ _~)

16.4% 83.6%

Waste Gas System, PJant Vents Waste Gas Decay Tanks Containment Vent Containment Purge CO2 Aux . Bldg . Ventilation Fuel Bldg . Ventilation CH; 14 Figure 2: C Gaseous Discharge Balance

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

The 170(n ,a) 14C 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 = Nr * {( O'J * <p1) + (O'e * <pe) + (crr * <pr)}

Where :

Na is the rate of production, atoms/se c 1rn IAEA Report 421 , Section 3.1.3 ss Neeb, sectic:in 4.2.4 90 Regulatory Guide 1.21 , rev. 2, section 1.09 9t NUREG-00 17 , Section 2.2.25.2 Page 59 of75 INFORMATION USE June,2018

APA-ZZ~01003 Rev. 023 NT is the number of 17 0 or 14 N target atoms per kg of coolant a, i*s the effective neutron cross section for thermal neutron absorption, cm 2

<p, is the thermal neutron flux , n/cm 2-sec O'e is the effective neutron cross section for epithermal energy newtron absorption ,

2 cm

<pe is the epithermal neutron flux , n/cm 2-sec a, is the effective neutron cross section for fast neutron absorption , cm 2

<p, is the fast neutron flux , n/cm 2-sec ENOF/ 8 - Vlj 0-17 Principal cross sections en C

tu ,uo e

C 0

U 'IQ I ru rn rn rn e ,o .,-- lalal u al:Jsurp uon elastic 10-3 1

10 11-*10 10

1J

9 ,d-e 10 7 10 -6 1J 5 10 Energy (MeV)

Figure 3: ENDF/8 VII Cross Sections for 17 0

Table 14: Effective Cross Section for the 17 0(n,a) 14C Reaction in the PWR as a Function of Neutron Energy 92 Neutron Group Group Energy Effective. Cross Section Thermal ::;Q.625 eV O. i2i barns Epithermal (E) >0.625 eV - <1 MeV 0.0291 barns Ii Fast (F) 2:1 MeV 0.1 124 barns I The source term of each species A1, is given by:

A0 (dps) =N0

A.

0 92 EPRI TR* 1021 106, Section 4.3.2.2 Page 60 of 75 INFORMA TION USE June,2018

APA-ZZ-01003 Rev. 023 N *A0 A0 {µCi) = 3.7£4 Where Aais the activity of species a, Na is the number of atoms of species a, 'A a is the decay constant of species a, in seconds. The 14C production rate from the 170(n,a) 14 C reaction is calculated for the three group flux distribution according to :93 14 . {1E-24 *A- N * ((a/Pt)+ (ae<pe) + (a-/p )}

C product,on rate= ----- ----- ---=- -=-- 1 3.7£4 Where:

14 14 C Production rate is C rate of production , µCi/sec- kg N is the number of target atoms per unit mass of coolant (1.27E22 atoms 17 0 / kg H20) ;

c1tis the effective neutron cross section for thermal neutron absorption, in barns; q,, is the thermal neutron flux , n/cm 2-sec; Cle is the effective neutron cross section for epithermal energy neutron absorption , in barns ;

'Pe is the epitt,ermal neutron flux , n/cm 2-sec; u, is the effective neutron cross section for fast neutron absorption, in barns ;

<pr is t11e fast neutron flux, n/cm 2-sec ;

1.0E-24 is a units conversion factor, 1.0E-24 cm 2/barn ;

_A Is the 14C decay constant, 3.833E-i 2/sec; and 3.7E4 is a units conversion factor, 3.7E4 d/(sec- µCi) .

The activity of r4c produced is thus the product of the production rate , the coolant mass in the active core region , and time :

Ac= Production rate *coolant mass *time Where :

Acls the activity of 14C produced , in µCi; 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 i 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 193 fuel 93 EPRITR-1021106, Section 4.3.2.1 Page 61 of 7S INFORMA TION USE June,2018

APA-ZZ-01003 Rev. 023 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 14C production from the 14 N(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 14 C

l'he child age group is the critical age group for an airborne release of 14C due to higher inhalation dose factors and higher ingestion dose factors .95 The inhalation dose for the child age group, D, fs calculated according to the expression 96 :

0 1= 3.17E4

R0

DFA1 *Q1

X/Q Where:

Dis the dose in mrem, to a member of the public frnm 14 C, from the inhaJation 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 DFA1 is the 14C inhalation pathway dose factor for organ j, appropriate to the child age group (mrem/pCi) . For 14 C, the limiting organ is the bone. The DFAbone for the chHd age group is 9.?OE-6 mrem/pCi, and the DFA1ata1 body for the child age group is 1.82E-6;98 Q1 is the quantity of 14 C produced during the year (Ci/yr); and X/Q is the highest calculated annual average concentration at the nearest rnceptor location (sec/m3 ) .

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

D bane =1138

Q;

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

D to ral body = 213

O;

X/Q 94 W estinghouse Calculation Note CN-TA-02-135, Callaway (SCP ) RSG IGOR/RETRAN Base Deck",

May 16, 2003 95 Regulatory Gulde 1.109, Table E-9 , and Table E-13 as Regulatory Guide 1.109, equations C-3 and C-4.

97 Regulatory Guide 1.109, Table E-5

'3B Regulatory Gulde 1 109, Table E-9.

Page *G2 of 75 INFORMA TION USE June,2018

APA-ZZ-01003 Rev. 023

8) Dose from 14 C in Fresh Leafy Vegetation The concentration of 14C in leafy vegetatiQn is calculated by assuming that the 14 C ratio to the natural carbon in the vegetation Is the same as the ratio of 14C to natural carbon in tile atmosphere surrounding the vegetation .99 Only 14C released in the oxide form (CO or CO2) is incorporated into the plant material. 100 All 14C released from the waste gas decay tanks is assumed to be in the organic form , as CO2. The inorganic form, e.g., CH4, is not incorporated into plant material, therefore, only the orgahic form , e.g. , CO2 contributes to the ingestion dose pathway . 14C02 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. 14C02 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- Novembe r 1.101 Tl1e concentration of 14C in leafy vegetation is given by :102 3 .17E7

Q;* X/Q

0.11 Cone = - - - - ' - - - - -

v 0.16 Where :

Concv is the concentration of MC in leafy vegetation grown at the nearest receptor location (r,Ci/kg) ;

3.17E7 is equal to (1E12pCI/C)(1 E3g/kg)/(3 , 15E7 sec/yr) ;

01 is the quantity of 14C released as CO2 during periods of photosynthesis (Ci/yr) ;

X/Q is the highest calculated annual average concentration at the nearest receptor location (sec/m3 );

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

Substitution of constants yields:

Concv = 2 .2E7 *O;

X/Q The leafy vegetation ingestion dose for the Child age group at the nearest receptor location is given by:11l3 99 Regulatory Guide 1.109, Appendix C 1oa 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 Page 63 of75 INFORMATION:USE June,2018

APA-ZZ-01003 Rev . 023 Where:

Dis 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 fo r the maximum exposed organ . For the child age group, the bone is the maximum exposed organ. The DFlbone is i .2 1E-5 mrem/pCI ingested and the DFl1ota1 body is 2.42E-6 mrem/pCi ingested ;194 f, is the fraction 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 a9e group, Ua = 26 kg/yr.106

9) Dose from 14 C in Milk The concentration of 14 C in milk is determined as 1°7 :

Concm11k is the concentration of 14C in milk, in pCi/L; Fm is the average fraction of the anirnal 1s daily intake of 14C which appears in each liter of milk, in days/L. For cow milk, Fmis 1.2E-2 days/ L.108 For goat milk, Fmis 0.1 O 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 consume d by the animal' per day, in kg/day. For cows, Q F is equal to 50 kg/day and for goats OF is equal to 6 kg/day;110 t, is the average transpo1i time of the 14C from the feed into the milk and to the receptor (a value of 2 days is assumed) : and J\ is the radlological1decay constant for 14C, 3.32E-7 days*1 .

The dose from 14 C in milk is determine d as :

D =OF/ -U0

Concmilh Where:

1o4 Regulatory Guide 1.109, Table E-1 3 10s Regulatory Guide 1.109, Table E-15 105 Regulatory Guide 1.109, Table E-5 107 Regulatory Gu lde 1.109, equation C-1O Joa Regulatory Gu!de 1.109, Table E-1 109 Regulatory Gulde 1.109, Table E-2 11a Regulatory Gulde 1.109, Table E-3 Page 64 of75 INFORMA TION USE June, 2018

APA-ZZ-01003 Rev. 023 Dis the annual dose to the bone or total body for the child age grout:> from 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 DFlbone is 1.21 E-5 mrem/pCi ingested and the DFl1ota1 body is 2.42E-6 mrem/pCl ingested; 11 1 and Ua is the ingestion rate for milk. For the child age group, Ua : 330 L/yr (for both cow and goat milk) .112

10) Dose from 14 C in Meat The concentration of 14 C in meat is determine d as 113 :

Conemeat = 3.1E-2

Conc *SD

e-/20 g33 2 E- 7 /

v Where:

Concmeat is the concentration of 14C In meat, in pCl/kg ;

3.1 E-02 is the stable ,element transfer factor, ih days/kg, for beef114 Concv is the concentration of 14 C in leafy vegetation grown at the receptor location (pCi/kg) , as described above ;

50 kg/day is the amount of feed consumed by the beef animal per day; 115 20 days is the average time from slaughter to consumption 116 : and 3.32E-7 days-1 is the radiolog ical decay constant for 14 G.

The dose from 14 C in meat is determined as :

D = OF/

U0

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

DFI ts the ingestion dose converslon factor for the maximum exposed organ . For the child age g*roup , the bone is the maximum exposed organ . The DFlbone is 1.21 E-5 mrem/pCi ingested and the DFl101a1body is 2.42E-6 rnrem /pCi ingested ;117 and Ua is the ingestion rate for meat. For the child age group, Ua ==41 kg/yr. 116 11

' Regulatory Guide i .109, Table E-1 3 1 12 Regulatory Guide i. 109, Table E-5 11 1

'Regulatory Guide 1.109, equation C-i 2 11

~ Re.9ulatory Goide 1.109 Table E-1 115 Regulatory Guide 1.1 09 , Table E-3 116 Regulatory Guide 1.109, Table E-15 117 Regulatory Guide U09, Table E-13 11 0 Regulatory Guide i .109, Table E-5 l?age 65 of 75 INFORMA TION USE June, 2018

APA-ZZ-01003 Rev. 023

11) Dose to the Member of the Public from Activities within the Site Boundary The Member ot the Public performing activities with in the Site Boundary is described in Section 4. The Ingestion dose pathways do not exist within the Site Boundary. 14C is not a gamma- emitting nuclide ; therefore the ground plane pathway Is negligible.

The inhalation dose, D, is calculated according to the expression 119 :

Di = 3.17E4

Ra

DFA1

Q;

X/Q *1.26E-1 Where:

Dis the dose in mrem , to a member of the public from 14 C, 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) ;120 DFAi is the 14 C inhalation pathway dose factor for organ j, appropriate to the adult age group (mrem/pCi) . For 14C, the limiting organ is the bone . The DFAbone for the adult age group is 2.27E-6 mrem/pCi, and the DFAtota1 body and DFA111yro1d is 4.26E-7 mrem/pCi . 121 Q; is the quantity of 1dC 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 tile year the farmer performs activities within the Site Boundary (1100 hrs/8760 hrs), dimensionless.

119 Regulatory Gulde t 109, equati ons C-3 and C-4 120 Regulatory Guide 1.109, Table E* 5 121 Regulatory Guide i . 109, Table E-7 Page 66 of 75 INFORMATI ON USE June, 2018

APA-ZZ-01003 Rev. 023 12} Alternate Methodologies Regulatory Gt1ide 1.21 states that the following methods are acceptable tor estimating the production of 14 C:122

Sampl ing and analysis of effluent streams

Use of normalized 14 C source term and scaling factors based on power generation, e.g ., NCRP Report 81 123

Use of the PWR GALE code 124 Callaway Plant effluents have not been sampled for 14C. NCRP Report 81 , Table 3.3 states that the total 14 C 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/GW1h-yr or 7.2 Ci/EFPY 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 sign ificantly lower than the quantity of 14 C 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 14 C 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 fo r a PWR proxy calculation . The average 14 C production rate for Westinghouse PWRs is 3.4 Cl/ GW,h- yr 126 . Callaway is rated at 3.565 GW1h (3565 MW1h), therefore, the 14C production rate based on the proxy PWR is 12.1 Ci/ E'FPY. 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 Regul&tory Gu ide 1.21, Section 1.9 123 NCRP Report 81 12

'l NUREG-0017 125 HPC) 1 102 iw EPRI TR-1021106, Section 4.8 and Appendix D Page 67 of75 INFORMATI ON USE June,2018

APA-ZZ-01003 Rev. 023 Appendix B: Record of Revisions 1 v Rev. No. 0 Date: March 1983 Rev. No. 1 Date: November, 1983 Revised to support the current RETS submittal and to incorporate NRG Staff comments .

Rev. No. 2 Date: March, 1984 Revised to incor,porate NRG Staff comments Rev. No. 3 Date: Juhe, 1985 Revised to incor.porate errata identified by ULNRC00803 and changes to the Environmental Monitoring Program. Incorporate results of 1984 Land Use Census.

Rev. No. 4 Date: February, 1987 Minor clarifications, incorporated 31 -day projected dose methodology. Change in the Utlli;zation of areas within the Site Boundary.

Rev. No. 5 Date: January, 1988 Minor clarifications, revised descriptions nf liquid and gaseous rad monitors , revised liqurd

,setpoint methodology to incorporate monitor background, revised dose calct:.1lations for 40CFR190 requirements , Revised Table 6 and Figures 5.1A and 5.1 B to refine descriptions ot environmental TLD stations, incorporated description of environmental TLD testing required by Reg . Guide 4.13, revised Tables 1, 2, 4 and 5 to add addftronal rn;clides. deleted redundant material from Chapter 6.

Rev. No. 6 Date: May, 1989 Revised methodology for calculatrng maximum permissible liquid effluent discharge rates and liquid effluent discharge rates a~d liquid effluent monitor setpotnts , provided methodology tor calculating liquid effluent monitors response correction factors, provided an enhanced desoriptfon of controls on liquid monitor background limits , provided additional liquid and gaseous dose conversion factors and bioaccumulation factors (Tables i , 2, 4 & 5) ,, provided descr1ption 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-22-01003 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 NRG Generic Letter 89-01. At the same tlme, in order to formalize control of the entire ODCM , it was converted ro APA~ZZ-01003, Offsite Dose Calculation Manual.

127

.Section numbers , table numbers, etc. referto the numbering schema used n the particular revision .

Page 68 of75 INFORMATION USE June,2018

APA-ZZ-01003 Rev. 023 Section 2.5: Revised projected liquid dose calculation to use previous 31 day cumulative. doses .

Section 3,1.1 : Added GL-RE-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 . i and 3.3.2.2: Changes were made to eorrect typographical errors and have no technical impact. Section 3.4: Revised projected gas dose calculatron to use previous 31 day cumulative doses . Section 3.5: Removed the word secular from secular equilibrium" since the equilibfium mode could be secular or transient depending on the isotope. Table 6.2 : Added Launclry Decon Facility Dryer Exhaust to title of table s1nce 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 w1th a maximum allowed background of 2000 cpm as calculated in HPCI 9905 . Tables 6.1, 6.2, 6.3: Updated values as calculated in HPCI 9982 . Section 5.1:

Defined how REMP sample locations were determined . Removed reference to Plant Operatrng 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.F changed to FSAR 16.11 .4. Techntcal Specification 6.8. i .F changed to Improved Technical Speciffcation 5.4 .1. Technical Specification 6. i 4 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. L6 changed to Improved Technical Specification 5.6.2.

Technical Specification 6.9 .i .7 changed to Improved Technical Specification 5.6.3. Changed name of Annual Radiological Effluent Release Report to EHII.Jent Release Report as stated in ITS.

Added liquid releases are lim ited 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 10CFR20, Appendi x B, Table II , Column 2 reference to the new 10CFR20 format. Corrected typo for "f" , flow setpoint should be undiluted waste flow rate.

Section 3 .2.1: Cmrected typo, default value for safety factor shou ld 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 (X/Q) 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 H PTS . 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 impac t.

Rev . No. 13 Date September 19, 2002 Section 3.2: Revised to implement the approved OL i 2i 8, Rev. 1; License Amendment no. 1*52 allowing equipment hatch and emergency air lock to remain open during refueling activities (FSAR CN-01 -030 and CN 049) . The amendment eliminated FSAR 16.11 .2.4.18 and Page 71 of 75 INFORM~TION USE*

June,2018

APA-ZZ-01 003 Rev., 023 subsequently deleted the core alteration setpoint value 5.0 E-3 µCi/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-144. (CARS 200303251 ).Revised Section 4.1.3.1, to adjust the Farmer's residence (critical receptor) from 3830 meters rn the SE sector to 2897 meters in the NNW sector. The Farmer's residence (critical rnGeptor) 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 di~persion parameters for the Farmer's residence (critical receptor) and the Nearest residence the same. Revised section 7.2 to reference Taj)le 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 0304 (Rev.

0), "Calculation of Liquid Effluent Dose Commitment factor for Pr-144 (A11) ,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 63 Ni 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 -i. 63 Ni was added to the ODCM based on previous 10 CFR 61 sample results and 2nd quarter liquid composite analyses . Consolidated references listed in section 2.4.2 and 2.6 for the site related ingestion dose commitment factors (Air of Table 2.1 into HPCI 0406, Revision 1. References to HPCI 9504 (Ref: 11 .14.13) and HPCI 0304 (Ref: 11 .14.14) were deleted and replaced with HPCI 0406 , Revision 1 which Is now listed as Ref: 11 .14.13. Added 63 Ni and 122 Sb to Table 2.1- INGESTION DOSE COMMITMENT FACTOR (A17) 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 t he Radiological Erwironmenial Monitoring Program TLDs will be processed and provided by a vendor laboratory beginnihg in the first quarter of 2085. Seciion 5.2 was revised to delete reference 11 .14.10 which refers to HPCI 8808, "Performance Testing of the Environment TLD System at Callaway Plant", August 1989. Reference 11.14.7 was corrected with HPCI 8710 vice HPCI 8810. 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 (L1) units in Table 3.1 (Dose Factor for exposure to a Semi -I nfinite Cloud of Noble Gases) to mrem/yr per uCi/r:n 3 . 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 R1,1 .1values. This paragraph was taken directly from section 5.3.1 of NU REG 0133, U.S. Nuclear Regulatory Commission , "Preparation of Radiological Effluent Technical Specification tor Nuclear, Power Plants", USN RC NUREG-0133 , Wash ington ,

D.C . 20555, October, 1978. This paragraph does not apply since the use of pathways is already considered as described 1n sections 4.1 .2 and 4. i _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 of75 INFORMATI ON USE June,2018

APA-ZZ-Oi 003 Rev. 023 Census. Revised Notes (a) *am:t (c) from Table 6.2 to reference FSAR-SA Table 2.3-84 and 2.3-81 respectively. Added a 0.95 conservatism factorto section 2.2.3 Calculation of Liquid Effluent Monitor Setpolnt. Th is will conservatively reduce the liquid monitor setpoint to further ensure the section 4.4.1 of NUREG 0133 , U.S. Nuclear Regulatory Commission , "Preparation ot Radiological Effluent Technical Specfflcation for Nuclear Power Plants, USNRC NUREG-0133 , Washington ,

O.C. 20555, October, 1978 which states the alarm and trip setpornts for each instrument channel listed in Table 3.3-11 should be provided and should correspond to a value(s) which represents a safe margin of assutance that the instantaneous liquid release limit of 10 CFR Part 20 is not exceeded . A determination was made IAW T/S 5.5.1 that the associated changes with Revision 15 maintain the levels of radioactive effluent control required by 10 GFR 20 .1302, 40 CFR i 90 ,

10 CFR 50.36a, and 10 CFR 50 Append ix 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 lnterlaboratory Comparison (crosscheck) requirements for the Radiological Environmen tal Monitoring Program (REMP) contract lab. Reference 11.14.14 to Reg . Guide 4.15, Quality Assurance fat Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment, was added to provide supporting documentation for contract lab lnterlaboratory Comparison requirements . Additional i nformation on REMP contract lab participation in lhterlaboratory Comparisons was also added in section 5.1 ,

(CAR 200500891) Revised reference 1i .14.7 by adding normalization and standardization factors for radionuclides listed ih Table 2.1 of the OOCM 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 Stearn 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 io fnclude 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 calcu lation to the Member of the Publfc from Modificatio n 03 -1008. Revised section 4.1.3.1.3 to include and describe direct dose calculations from the Radwaste Yard RAM storage and Stores 11 . 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 determ ination was made IAW T/8 5.5.1 that the associated changes with Revision 16 maintain the levels of radioactive effluent contrnl required by 10 CFR 20.1302, 40 CFR 190, 1o CFR 50.36a, and 10 CFR 50 Appendix I, and not adversely impact the accuracy or re liability 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 16.1,1.4.2c. 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.

Rev. No. 18 Date October 11 , 2007 Page 73 of 75 INFORMATION USE June, 2018

APA-ZZ-Oi 003 Rev. 023 Revi sed Table 6.5 was revfsed 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, 2012 Converted to Word 2010, including appropriate formattfng 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 14 G 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 1206. Section 5.2- changed to allow use of dosimeters other than TLDs. Section 6.1- Deleted discussion of short- term X/Q 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 201104163, 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 Farmer's residence were removed . As a first approximation , the dispersron parameters for the Nearest Residence will be used for the Fatmer's residence . Appendix A-Appendix A was added to describe the calculation of the production of 14 C ahd the calculation of dose from 14C in gaseous effluents. (CAR 201 i 04163) 63 Ni was added to the gaseous effluent inhalation pathway and ingestion pathways dose factor tables . Values for 63 Ni are from APA-ZZ-01003 , rev. 4. (CAR 201104197) . Adult Ingestion dose factors removed . Ingestion dose pathway removed from Table i 3 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 HPCi1503 . Added HPCl1502 , 'HPCli 503 ,

HPCl1504, & HPCl1505 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 parameter s.

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 CR 's 201604927, 201602733 , 201603668 , and 201602733 The methodology used to calculate the A1, values was added to section 2.4.2. Default setpoint values for GTRE21 Band GHRE.1 OB were added to section 3.2. Deleted the specific years of the Page 74 of75 INFORMA TION USE June,2018

APA-ZZ-01003 Rev. 023 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 HPCl 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 composi te and not an actual person .

Section 6.2 was revised to clarify thequal1ty check of the meteorological data prior t o processing .

Section i 0, "Bibliography" was revlsed to add new references and to update the revision level of CDP-ZZ-00200 . 126 Sb was added to Table 1. Table 12 was revised to change the "Farmer's Residence" to the "Nearest Resident" because the farmihg 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 3 H dispersion parameters was moved into the table. 14C was added to Table

12. Appendix A was reformatted for better readability. Append ix A, Section 2, Assumptions " was revised to clarify the assumptions , principally dispersion parameter use and the dose pathways and locati0ns. 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 irom Activities Within the Site Boundary, was revised to eliminate the value of the X/Q for acHvities within the Site Boundary and to instead refer to Table 10 as the source for the X/Q. The three condensed form equations were likewise eliminated. This eliminated an error trap in that the X/Q could be revised and it may not be recogr:iized that the specific value was stated in the text of Appendix A, Section 11 .

Appendix A, Section 12 was edited for readability.

Rev. No. 23 Date June, 2018

Section 5.1 was revised to delete the phrase referring to HPOI 9901 because HPCI 9901 is obsolete. HPCI 1506, rev. 1, superseded portions of of HPCI 9901 , the remainder is superseded by HTP-ZZ-DTI -REMP-SMPL-SCHED , F.lEMP Sample Locations and Analysis Schedule. (CR 201705399)

Section i 0, "Bibliography", was revised lo update the revisi0n level of CDP-ZZ-00200, Appendix B, ANSI N42.18-2004 (redesignation of ANSI N13.10-1974)t and HPCl 1604.

Table 1 was revised to add the Dose Comm itment Factors f or 1 17 fT1Sn. (CR 201 706108)

Format changes are not marked with revision bars.

Page 75 of75 INFORMATION USE June, 2018

CALLAWA Y-SP 16.11 OFFSITE DOSE CALCULATION MANUAL (ODCM 9.0) RADIOACT,IVE EFFLUENT CONTROLS 16.11 .1 LIQUID EFFLUENT 16.1 1.1.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION (ODCM 9.3 .1)

The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 16.11 -1) shall be limited to 10 times the concentration values in Appendix 8, Table 2, Column 2 to 10 CFR 20'.1001-20.2402, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 1o-4 microCurie/ml total activity.

APPLICAB ILfIY: At all times.

ACTION :

With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits , immediately restore the concentration to within the above limits.

16.11.1 .1.1 SURVEILLANCE REQUIREMENTS (ODCM 9.3.2) 16.11 .1. 1.1.a Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Tabl e 16.*11- 'l.

16.11 .1.1.1.b The results of the radioactivity analysis shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Section 16 11 1 1.

16.11.1.1 .2 BASES This section is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than 10 times the concentration in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within : (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC, and 16.11-1 Rev . OL-23 6/18

CALLAWA Y-SP (2) the limits of 10 CFR Part 20.1301 to the population . The concentration limit for dissolved or entrained noble gases Is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

The required detection capabilities for rad ioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLD's) .

16.11 -2 Rev. OL-23 6/18

CALLAWAY - SP 16.11 .1.2 DOSE FROM LIQUID EFFLUENTS LIMITING CONDITION FOR OPERATION (ODCM 9.4.1)

The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released , from each unit, to UNRESTRICTED AREAS (see Figure 16.11-1 ) shall be limited :

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ , and

b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 1O mrems to any organ.

APPLICABILITY: At all times.

ACTION :

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and. defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits . This Special Report shall also include: .(1) the results of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requl rements o,f 40 CFR Part 141 ,

Clean Drinking Water Act.*

16.11 .1.2.1 SURVEILLPJNCE REQUIREMENTS (ODCM 9.4.2)

Cumulative dose contrlbtttions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the OOCM at least once per 31 days.

16.11 .1.2.2 BASES This section is provided to implement the requirements of Sections II .A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required

The requirements of ACTION a.( 1) and (2) are applicable only if drinking water supply is taken from the receivlhg water body within 3 miles of the plant discharge, lr.i the case of river-sited plants this is 3 miles downstream only.

16.11-3 Rev. OL-23 6/18

CALLAWAY - SP operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonal:Dly achievable".

Also , for fresh water sites with d~inking water supplies that can be potentially affected by plant operations , there is reasonable assurance that the operation of the facil'ity will not result in radionuclide concentrations in the finished drinkihg water that are in excess of the requirements of 40 CFR Part 141 . The dose calculation methodology and pa.rameters in the ODCM implement the requirements in Section Ill.A of Appendix I which specify that conformance with the guides of Appendix I be -shown by calculational procedures based on models and data , such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated . The equations specified in the ODCM for calculating the doses due to the actual' release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.1 09, "Calculations of Annual Doses to Man from R.outine Releases of Reactor Effluents with 10 CFR Part 50 , Appendix I; Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic and Dispersion of Effluents from accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, April 1977.

The reporting requirements of Action(a) implement the requirements of 10CFR20.2203.

16.11-4 Rev. OL-23 6/18

CALLAWAY- SP 16.11.1 .3 RADIOACTIV E LIQUID EFFLUENT MONITORIN G INSTRUMEN TATION LIMITING CONDITION FOR OPERATION (ODCM 9 .1.1)

The radioactive liquid effluent monitoring instrumentation channels shown ih Table 16.11-2 shall be FUNCTIONA L with their Alarm/Trip Setpoints set to ensure that the limits of Section 16. 11 .1.1 are not exceeded . The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM .

APPLICABIL ITY: At all times .

ACTION :

a. With a radioactive liquid effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above, immediately suspend the release of radioactive liquid effluents monitored by the affected channel , or declare the channel non-functional.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels FUNCTIONA L, take the ACTION shown in Table 16.11 -

2. Restore the non-functional instrumentation to FUNCTIONA L status within 30 days and , if unsuccessful , explain in the next Radioactive Effluent Release Report, pursuant to Techn ical Specification 5.6.3, why this non-functionality was not corrected within the time specified .

16.11 .1.3.1 SURVEILLAN CE REQUIREME NTS (ODCM 9.1.2)

Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated FUNCTIONA L by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL OPERATION AL TEST at the frequencies shown in Tab le 16_11 -3 .

16.11 .1.3.2 BASES The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the rel.eases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The FUNCTIONA LITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 , and 64 of Appendi x A to 10 CFR Part 50.

16.11 -5 Rev. OL-23 6/18

CALLAWAY - SP 16.11.1.4 LIQUID RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION (ODCM 9.5.1)

The Liquid Radwaste Treatment System shall be FUNCTIONAL and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Figu re 16 11-1) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31 day period .

APPLICABILITY: At all times.

ACTION:

With radioactive liquid waste being discharged in excess of the above limits and the Liquid Radwaste Treatment Systems are not being fully utilized, prepare and submit to the Commission within 30 days a Special Report that includes the following information :

1) Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems , and the reason for the inoperability.

2) Action(s) taken to restore the inoperable equipment to OPERABLE status ,

and

3) Summary descrip1ion of action(s) taken to prevent a recurrence .

16.11 .1.4.1 SURVEILLANCE REQU IREMENTS (ODCM 9.5.2) 16.11 .1.4.1.a Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM .

16.11 .1.4.1.b The installed Liquid Radwaste Treatment System shall be considered FUNCTIONAL by meeting Sections 16 11.1 1 and 16.11 .1 2.

16.11.1.4.2 BASES The FUNCTIONALITY of the Liquid Radwaste Treatment System ensures that this system wil11be available for use whenever liquid effluents require treatment prior to 16.11-6 Rev. OL-23 6/18

GALLAWAY - SP release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will pe kept as low as is reasonably achievable". This section implements the requirements of 10 CFR Part 50.36a , General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section 11.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

16.11-7 Rev. OL-23 6/18

CALLAWAY - SP 16.11 .1.5 LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION The quantity of radioactive material contained in each of the following unprotected outdoor tanks shall be limited to less than or equal to 150 Curies, excluding tritium and dissolved or entrained noble gases :

a. Reactor Makeup Water Storage Tank,

b. Refueling Water Storage Tank ,

c. Condensate Storage Tank, and

d. Outside temporary tanks , exclud ing demineralize r vessels and the liner being used to solidify radioactive waste.

APPLICABIL ITY: At all times .

ACTION :

With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and describe the events leading to this condition in the next Radioactive Effluent Release Report. pursuant to Technical Specification 5.6.3 .

e.

16.11 .1.5.1 SURVEILLAN CE REQUIREME NTS (4.11 .1 .4)

The quantity of radioactive material contained in each of the above listed tanks shall be determ ined to be within the above limit by analyzing a representative sample of the tank's contehts at least once per 7 days when radioactive materials are being added and within 7 days following any addition of radioactive material to the tank. The provisions of Sections 16.0.2 2 and 16.0.2.3 are applicable, however the allowed surveillance interval extension beyond 25% shall not be exceeded . These tanks are also covered by Administrativ e Controls Section 5.5.12 of the plant Techn ical Specifications.

16 .11 .1.5.2 BASES The tanks* l1isted above include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System .

16.11-8 Rev . OL-23 6/18

CALLAWAY - SP Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents , the resulting concentrations would be less than the limits of 10 GFR Part 20.1-20.602 ,

Appendix B, Table II, Column 2, (redesignated at 56FR23391 , May 21 , 1991) at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

16.11 -9 Rev. OL-23 6/18

CALLAWAY - SP 16.11 .2 GASEOUS EFFLUENTS 16.11 .2.1 GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION OF OPERATION (ODCM 9.6.1)

The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 16 11-2) shall be limited to the following :

a. For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skill, and

b. For lodine-131 and 133, for tritium , and for all radionuclides in particulate form with half~lives greater than 8 days : Less than or equal to 1500 mrems/yr to any organ.

APPLICABILITY: At all times.

ACTION :

With the dose rate(s) exceeding the above limits, immediately restore the release rate to within the above limit(s) .

16.11 .2.1.1 SURVEILLANCE REQUIREMENTS (ODCM 9.6.2) 16.11 .2.1.1.a The dose rate *due to noble gases in gaseous effluents shall be determined to b.e within the above limits in accordance with the methodology and parameters in the ODCM .

16.1 1.2.1.1.b The dose rate due to lodine-131 and 133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 16 11-4.

16.11.2.1.2 BASES This section is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effiuer.its from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The dose rate limits are the 16.11-10 Rev. OL-23 6/18

CALLAWAY - SP doses associated with the concentrat ions of 10 CFR Part 20 .1-20.601 , Appendix B, Table II , Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTR ICTED AREA, either within or outside the SITE BOUNDAR Y, to annual average concentrations exceeding the dose limits specified in 10 CFR Part 20 10 CFR 20.1301 . For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensa te for any increase in the atmospher ic diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC , with the appropriate occupancy factors , shall be given in the ODCM. The specified release rate limits restrict, at all times , the corresponding gamma and beta dose rates above backgroun d to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDAR Y to less than or equal to 500 mrem/yea r to the whole body or to less than or equal to 3000 mrems/yea r to the skin. These release rate limits also restrict, at all times ,

the correspond ing thyroid dose rate above backgroun d to a child via the inhalation pathway to less than or equal to 1500 mrems/yea r.

The required detection capabilities for rad ioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLD's).

The requireme nt for add itional sampling of the Unit Vent following a reactor power transient is provided to ensure that the licensee is aware of and properly accounts for any increases in the release of gaseous ,effluents due to spiklng which may occur as a result of the power transient. Monitoring the Unit Vent for increased noble gas activity is appropriate because it is the release point for any increased activity which may result from the power transient.

Since the escape rate coefficients for the noble gas nuclides is equal to or greater than the escape rate coefficient for iodine and the particulate nuclides***'* , it is reasonable to assume that the RCS spiking behavior of the noble gas nu el ides is similar to that of the particulate and iodine nuclides . Cons idering the effects of iodine and particulate partitioning , plateout on plant and ventilation s.ystem surfaces , and the 99% efficiency .o f the Unit Vent HEPA filters and charcoal absorbers , it is reasonable to assume that the relative concentrations of the noble gas nuclides will be much greater than those of the iodine and particulate nuclides. Therefo re, an ihcrease in the iodine and particulate RCS activity is not an appropriate indicator of an increase in the Unit Vent activity, and it is appropriate to monitor the Unit Vent effluent activity as opposed to the RCS activity as an indicator of the need to perform post-trans ient sampling . In addition , it is appropriate to monitor the noble gas activity due to its relatively greater concentration in the Unit Vent.

+.-

Cohen , Paul , Water Coolant Technology of Power Reactors , Table 5. 19 , page 198. American Nuclear Society, 1980.

H NUREG-0772 , Technical Bases for Estimating Fi ssion Product Behavior During LWR Accidents",

Silberberg , M., editor, USNRC ; Figure 4.3, page 4.'22. June , 1981 .

16.11-11 Rev. OL-23 6/18

CALLAWAY - SP 16.11.2.2 DOSE- NOBLE GASES LIMITING CONDITIO N OF OPERATIO N (ODCM 9.7.1)

The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDAR Y (see Ffgure 16.11-2) shall be limited to the following :

During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 1O r:nrads for beta radiation, and During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation .

APPLICAB ILITY: At all times.

ACTION :

With the calculated air dose from radioactive noble gases in gaseous effluents exceed1ng any of the above limits, prepare and submit to the Commissio n within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequen t releases will be in complianc e with the above limits .

16.11.2.2.1 SURVEILL ANCE REQLJrREMENTS (ODCM 9.7.2)

Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodolo gy and parameters in the ODCM at least once per 31 days.

16.11 .2.2.2 BASES This section is provided to implement the requirements of Sections 11.B, Ill.A, and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implement s the guides set forth in Section 11.B of Appendix I. The ACTION statement provides the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material ih gaseous effluents to UNRESTR ICTED AREAS will be kept "as low as is reasonably achievable" .

The Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropr.iate pathways is unliikely to be substantially underestim ated .

The dose calculation methodolo gy and parameters established in the ODCM for 16.11-12 Rev . OL-23 6/18

CALLAWAY - SP calculating the doses due to the actual .release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases on Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111 , "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light~Water Cooled Reactors", Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions .

The reporting requirements of Action(a) implement the requirements of 10CFR20.2203.

16.11-13 Rev. OL-23 6/18

CALLAWAY - SP 16.11 .2.3 DOSE-IODIN E-131 AND 133, TRITIUM , AND RADIOACTIVE MATERIAL IN PARTICULATE FORM LIMITING CONDITION OF OPERATION (ODCM 9.8.1)

The dose to a MEMBER OF THE PUBLIC from lodine-131 and 133, tritium , and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released , from each unit, to areas at and beyond the SITE BOUNIDARY (see Figure 16.11 -2) shall be limited to the following :

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ , and

b. During any calendar year: Less than or equal to 15 mrems to any organ.

APPLICABILITY: At all titnes .

.ACTl*ON :

a. With the calculated dose from the release of lodine-131 and 133, tritium , and radionuclides in particulate form with half-lives greater than 8 days , in gaseous effluents exceeding any of the above limits , prepare and submit to the Commission within 30 days a Special Report that identifies the cause(s) for exceeding the limits and defines the corrective actions that have been tc1ken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits .

b. The provisions of Sections 16.0.1..3 and 16.0 1.4 are not applicable.

16.11 .2.3.1 SURVEILLANCE REQUIREMENTS (ODCM 9.8.2)

Cumulative dose contributions for the current calendar quarter and current calend'ar year for lodine-131 and 133, tritium , and radionucl ides in particulate form with half-lives greater than 8 days shall be determined in accordance with. the methodology and parameters in the ODCM at least once per 31 days_

16.11 .2.3.2 BASES This section is provided to implement the requirements of Sections 11.C , Ill.A, and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth i n Section 11.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the release of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as reasonably achievable". The ODCM calculational methods specified in the Survelllance Requirements implement the requirements in Section Ill.A of Append ix I that conformance with the guides of Appendix 16.11-14 Rev. OL-23 6/18

CALLAWAY - SP I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODOM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases o.f Reactor Effluents for the Purpose of Evaluating Complianoe with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111 , "Methods for Estimatin9 Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors" , Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions . The release rate controls for lodine-131 ,

and 133, tritium , and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man , in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were : (1) individual inhalation of airborne radionuclides , (2) deposition of radionuclides onto green le*afy vegetation with subsequent consumption by man , (3) deposition of radionuclfdes onto grassy areas where milk animals and meat-producing animals graze with consumption of the milk and meat by man , and (4) deposition on the ground with subsequent exposure of man .

The reporting requirements of Action(a) implement the requirements of 10CFR20.2203.

16.11-15 Rev. OL-23 6/18

CALLAWAY - SP 16.11 .2.4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION (OOCM 9.2. 1)

The radioactive gaseous effluent monitoring instrumentation channels shown in Ta ble

16. 11-5 shall be FUNCTIONAL with their Alarm/Trip Setpoints set to ensure that the limits of Section 16.11.2.1 are not exceeded . The Alarm/Trip Setpoints of these channels meeting Section 1.6.11 .2.1 shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY: As shown in Ta ble 16.i 1-5 .

ACTION :

a. With a radioactive gaseous effluent monitorihg instrumentation channel Alarm/Trip Setpoint less conservative than required by the above, immediately declare the channel non-functional.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels FUNCTIONAL, take the ACTION shown in Tab le 16.11 -

5. Restore the non-functional, instrumentation to FUNCTIONAL status within the time specified in the ACTION , or explain in the next Radioactive Effluent Release Report, pur:suant to Technical Specification 5.6.3, why this non-functionality was not corrected withir.i the time specified .

16.i1.2.4.1 SURVEILLANCE REQUIREMENTS (ODCM 9.2.2)

Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL OPERATIONAL TEST at the frequencies shown in Table 16.11-6.

16.11.2.4.2 BASES The radioactive gaseous effluent monitor,ing instrumentation is provided to monitor and control, as applicable , the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60 , 63 , and 64 of Appendix A to 10 CFR Part 50. The sensitivity of a,ny noble gas activity monitor used to show compliance with the gaseous effluent release requirements of Section 16 .11.2.1 shall be such that concentrations as low as 1 x 1o-6 µCi/cc are measurable .

16.11-16 Rev. OL-23 6/18

CALLAWAY - SP The monitors GT-RE-22 and GT-RE-33 are only required for automatic containment purge isolation in MODES 1 through 4. For plant conditions during CORE ALTERATIONS and during movement of irradiated fuel within containment, the function of the monitors is to alarm only and the trip signals for automatic actuation of CPIS may be bypassed . Based on the guidance provided in Regulc1,tory Guide 1.97 concerning monitoring .requirements for containment or purge effluent, the monitors GT-RE-22 and GT-RE-33 do not need to meet the single failure criterion for an Alarm function only during CORE ALTERATIONS or during movement of, irradiated fuel in containment. One instrumentation channel at a minimum is required for the alarm only function during refueling activities.

In the event that the containment mini-puge supply and exhaust valves have been closed to satisfy Action 41 of Tab le 16.11- 5 due to non-functionality of GTRE0022 and/or GTRE0033 , an allowance is provided in Action 41 to open the containment tnini-purge supply and exhaust valves under administrative controls for the purpose of equalizing containment pressure. The administrative controls consist of designating a control room operator to rapidly close the valves when a need for system isolation is indicated .

16.11-17 Rev. OL-23 6/18

CALLAWAY - SP 16.11 .2.5 GASEOUS RADWASTE TREATMENT SYSTEM LIMITING CONDITION OF OPERATION (ODCM 9.9.1)

The VENTILATION EXHAUST TREATMEN,T SYSTEM and the WASTE GAS HOLDUP SYSTEM shaU be FUNCTIONAL and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases , from each unit, to areas at and beyond the SITE BOUNDARY (see Figure *16.11-2) would exceed :

a. 0.2 mrad to air from gamma radiation , or

b. 0.4 mrad to air from beta radiation , or

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC .

APPLICABILITY: At all times ACTION ;

With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days a Special Report that inclwdes the following information :

1) Identification of any non-functional equipment or subsystems , and the reason for the non-functionality,

2) Actiom(s) taken to restore the non-functional equipment to FUNCTIONAL status , and

3) Summary description of action(s) taken to prevent a recurrence .

16.11 .2.5.1 SURVEILLANCE REQUIREMENTS (ODCM 9.9.2) 16.11.2.5.1.a Doses due to gaseous releases to areas at and beyond the SITE BOUNDARY shall be projected aUeast once per 31 days in accordance with the methodology and parameters in the ODCM.

16.11 .2.5.1.b 16.11-18 Rev. OL-23 6/18

Ct,.;LLAWAY - SP The installed VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEMS shal.l be considered FUNCTIONAL by meeting Sections 16.11 2.1 and 161 1 22 or 16.11 .2.3.

16.11 .2.5.2 BASES The FUNCTIONALITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate ,portions of these systems be used , when specified ,

provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept as low as is reasonably achievable ." This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 , and the design objectives given in Section 11.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections 11.B and 11.C of Appendix I, 10 CPR Part 50 , for gaseous effluents.

16.11-19 Rev. OL-23 6/18

CALLAWAY - SP 16.11 .2 .6 EXPLOSIV E GAS MIXTURE LIMITING CONDITION FOR OPERATIO N The concentration of oxygen in the WAS1E GAS HOLDUP SYSTEM shall be limited to less than or equal to 3% by volume whenever the hydrogen concentrat ion exceeds 4%

by volume .

APPLICAB ILITY: At all times .

ACTION :

a. With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 3% by volume but less than or equal to 4% by volume , reduce the oxygen concentration to the above Hmit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b. With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 4% by volume and the hydrogen concentration greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration on oxygen to less than or equal to 4% by volume, then take ACTION a. above .

16. 11.2.6.1 SURVEILL ANCE REQUIRE MENTS The concentrations of hydrogen and oxygen in the WASTE GAS HOLDUP SYSTEM shall be determined to be within the above limits by continuously monitoring the waste gases in the WASTE GAS HOLDUP SYSTEM with the hydrogen and oxygen monitors required FUNCTION AL by Section 16.11 .2.7. Th is system is covered by Technical Specification 5.5.12 which governs surveillance test frequencies and missed surveillances .

16.11 .2.6.2 BASES This Requirement js provided to ensure that the concentration of potentially explosive gas mixtures contained in the WASTE GAS HOLDUP SYSTEM is maintained below the flammability limits of hydrogen and oxygen . Automatic ,control features are included in the system to prevent the hydrogen and oxygen concentrat ions from reaching these flammability limits. These automatic control feature-s include isolation of the source of hydrogen and/or oxygen. Maintaining the concentration of hydrogen and oxygen pelow their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

16.11 -20 Rev. OL-23 6/18

CALLAW AY-SP 16.11 .2.7 WASTE GAS HOLDUP SYSTEM RECOMB INER EXPLOSIVE GAS MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION At least one hydrogen and both the inlet and outlet oxygen explosive gas monitoring instrument channels for each WASTE GAS HOLDUP SYSTEM recombiner shall be FUNCTIO NAL with their Alarmffr ip Setpoints (with the exception of the "FEED H2 4%/

FEED 02 3%" and "FEED H2 4%/FEED 02 4%" alarms) set to ensure that the limits of Section 16.11 .2.6 are not exceeded .

APPLICA BILITY: During WASTE GAS HOLDUP SYSTEM operation.

ACTION :

a. With an outlet oxygen monitor channel non-functional , operation of the system may continue provided grab samples are taken and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b. With both oxygen or both hydrogen charmels or both the inl.e t oxygen and imlet hydrogen monitor channels for one recombiner non-functional, suspend oxygen supply to the recombiner. Addition of waste .gas to the system may continue provided grab samples are taken and analyzed at least: 1) once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during mechanical or chemical degassing in preparation for plant shutdown , and

2) once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during other operations.

c. With the inlet oxygen analyzer non-functional , operation of the system may continue provided the inlet hydrogen is maintained less than 4%. If inlet hydrogen is greater than 4% , suspend oxygen to the recombiner. Addition of waste gas to the system may continue provided grab samples are taken and analyzed at least:

1) once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during mechanical or chemical degassing operations in preparation for plant shutdown , and 2) once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during other operations.

16.11.2.7.1 SURVEI LLANCE REQUIREMENTS This system is covered by Techn ical Specification 5.5.12 which governs surveillance test frequencies and missed sL:Jrveillances.

Each waste gas holdup system recombiner explosive gas monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of:

a. A CHANNE L CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

b. Not used 16.11-21 Rev. OL-23 6/18

CALLAWAY - SP

c. A CHANNEL CALIBRATION at least once per 92 days with the use of standard gas samples containing a nominal:

1) One volume percelilt hydrogen, balance nitrogen and four volume percent hydrogen , balance nitrogen for the hydrogen monitor, and

2) One volume percent oxygen , balance nitrogen , and four volume percent oxygen, balance nitrogen for the inlet oxygen monitor, and

3) 10 ppm by volume oxygen, balance nitrogen and 80 ppm by volume oxygen , balance nitrogen for the outlet oxygen monitor.

16.11.2.7.2 BASES Mechanical 'degassing operation' is defined as the transfer of gas from the Volume Control Tank (VCT) to the Waste Gas Holdup System when establishing a nitrogen blanket on the VCT in preparation for a plant shutdown. Chemical degassing operation' is the process of adding hydrogen peroxide to the RCS after the VCT hydrogen blanket has been replaced with nitrogen per the mechanical degassification process and the RCS has been reduced to less than 180°F. Both mechanical and chemical degassification may lead to an explosive gas mixture in the Waste Gas Holdup System ,

thus requir.ing the more restrictive 4-hour sampling . Other operations require 24-hour sampling .

The "FEED H2 4%/FEED 02 3%" AND "FEED H2 4%/FEED 02 4%" alarms are not required to be FUNCTIONAL. These alarms result from the combination of inlet hydrogen and inlet oxygen analyzer outputs while the FSAR only addresses FUNCTIONALITY of each separate analyier. Only the individual alarms and control functions associated with each analyzer are to be used to determine its functionality.

These alarms and control functions are sufficient to ensure that the limits of Section 16.11 .2.6 are not exceeded.

The CHANNEL CALIBRATION includes triggering the following alarms at the analyzer and verifying that the required control board annunciators and control functions actuate:

1) Feed Gas High H2

2) HARC-1104 OAIC-1112 Hi Hl H2/0 2 0 2 Shutdown

3) H2 Reactor High Oxygen 0 2 Limit

4) Product Gas High H2

5) Product Gas High Oxygen 16.11-22 Rev . OL-23 6/18

CALLAW AY-SP 6} Product Gas Hi Hi 0 2 Shutdown This surveillance verifies the FUNCTIONALITY of the analyzers' output relays , all interposing relays , and the annunciators . Setpoint verification Gonsists of verifying that the correct setpoint values are entered in the analyzers' database .

16.11-23 Rev. OL-23 6/18

CALLAWAY - SP 16.11 .2.8 GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 2.5 x 10 5 Curies of noble gases (considered as Xe-133 equivalent) .

APPLICABILITY; At all times.

ACTION :

With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , reduce the tank contents to within the limit, and describe the events leading to this condition in the next Radioactive Effluent Release Report, pursuant to Technical Specification 5.6.3 .

16.11.2.8.1 SURVEILLAN CE REQUIREMENTS The provisions of Section s 16.0.2.2 and 16.0.2.3 are applicable, however the allowed survetllance interval extension beyond 25% shall not be exceeded . This system is also covered by Administrative Controls Section 5.5.12 of the plant Technica'I Specifications .

The quantity of radioactive material contained in each gas storage tank sha*11 be determined to be within the above limit at least once per 18 months.

16.11 .2. 8.2 BASES The tanks included in this Requirement are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Requirement.

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents , the resulting whole body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 rem . This is consistent with Standard Review Plan 11 .3, Branch Technical Position ETSB 11-5, "Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure ," in NUREG-0800, July 1981 . The determination of Xe-133 equivalent uses the effective dose conversion factors for air submersion listed in Table 111.1 of EPA Federal Guidance Report No. 12, EPA-402-R-93-081 , '1External Exposure to Radionuclides in Air. Water, and Soil ," 1993.

16.11-24 Rev. OL-23 6/18

CALLAWAY - SP 16.11 .3 TOTAL DOSE 16.11 .3.1 TOTAL DOSE LIMITING CONDITION FOR OPERATION (ODCM 9.10 .1)

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 rnrems to the whole body or any organ , except the thyroid , which shall be limited to less than or equal to 75 mrem.

APPLICABILITY: At all times.

ACTION:

With the calculated doses from the release of radioactive materials in gaseous effluents exceeding twice the limits of Section 16.11 .2.2a, 16 11 .22b, 16.11 .2.3a, or 16 11 .2.3b, calculations should be made including direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of Section 16.11.3.1 have been exceeded . If such is the case, prepare and submit to the Commission within 30 days a Special Report that defines the corrective action to be taken to reduce subsequent release to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.2203, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation , for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved , and the cause of the exposure levels or concentrations . If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

16.11 .3.1.1 SURVEILLANCE REQUIREMENTS (ODCM 9.10.2) 16.11.3.1.1 .a Cumulative dose contributions from gaseous effluents shall be determined in accordance with Sections 16.11 .2 2.1, and 16. 1 2 3, 1, and in accordance with the methodology and parameters in the ODCM .

16.11 .3.1 .1.b 16.11-25 Rev. OL-23 6/18

CALLAW AY - SP Cumulative dose contributions from direct radiation from the units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM . This requirements is applicable only under condihons set forth in ACTION

a. of Section 16.11 3 1.

16.11.3.1 .2 BASES This Requirement ,is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301. The control requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and the radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ except the thyroid , which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and from outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits.

For the purposes of the Special Report, it may be assumed th,a t the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible , with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered . If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected) , in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR 20.2203, i*s considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed . The variance only relates to 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20 , as addressed in Sections 16 .11.1. 1 and 16.11.2 1.

An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

There are three defined effluent release categories : 1.) Releases directly to the hydrosphere; 2.) noble gas releases to the atmosphere; 3.) radioiodine and particulate releases to the atmosphere. For each effluent release category, it is assumed in the dose calculations that an individual with the highest dose potential is the receptor. In general , the adult is considered to be the critical age group for liquid effluents , and the child age group is the most limiting for radioiodine and particulates [n gaseous effluents ,

Thus, it is highly unlikely or impossible for the same individual to simultaneously receive the highest dose via all three effluent categories. For most reactor sites , it is also unlikely that all different potential dose pathways would contribute to the dose to a single real individual. Since it is difficult or impossible to continually determine actual food use patterns and critical age group, for calculationc~I purposes , assumptions are made which tend to maximize doses. Any refinement in the assumptions would have the effect of 16.11-26 Rev. OL-23 6/18

CALLAWAY - SP reducing the estimated dose. For radior.it1clides released to the hydrosphe re , the degree of overestimation in most situations is such that no individual will receive a significant dose. These conseNati ve assumptions generally result in an overestimation of dose by one or two orders of magnitude . Since these assumptions are reflected in the Radiological Effluent Controls limiting radionuclide releases to design objective individual doses, no offsite individual is likely to actually receive a significant dose. Since the doses from liquid releases are very conservati vely evaluated , there is reasonable assurance that no real individual will receive a significant dose from radioactive liquid release pathway. Therefore, only doses to individuals via airborne pathways and dose resulting from direct radiation need to be considered in determinin g potentiail com.Pliance to 40 CFR 190*.

The reporting requirements of Action(a) implement the requirements of 1 OCFR20.2203.

. NUREG-0543 , "Methods for Demonstrating LWR compliance w1th the EPA Uranium Fuel Cycle Standard (40 CFR 190)", Congel , F. J., Office of Nuclear Reactor Regulation , USNRC. January, 1980.

pp. 5-8 .

16.11-27 Rev. OL-23 6/18

CALLAW AY - SP 16.11.4 RADIOLOGICAL ENVIRONMENTAL MONITORING 16.11.4.1 MONITORING PROGRAM LIMITING CONDITION OF OPERATION (ODCM 9.11 .1)

The Radiological Environmental Monitoring Program shall be conducted as specified In Tab le 16.11-7.

APPLICABILITY: At all tirrnes.

ACTION :

a. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 16.11-7, prepare and submit to the Commission , in the Annual Radiological Environmental Operating Report required by Technical Specification 5.6.2, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Tabl e 16.11-8 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendar year limlts of Sections 16.11 .1.2 , 16.11 .2.2, or 16 11 .2.3. When more than one of the radionuclides in Tab le 16.11-8 are detected in the sampling medium , this report shall be submitted if:

conc~ntration (1) + concent~ation (2) + ... ~ .

reporting level (1) 10 reporting (2)

When radionudides other than those in Table 16.11 -8 are detected and are the result of plant effluents , this report shall be submitted if the potential ' annual1dose*

to A MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Secti ons 16.11.1.2 , 16 .11.2.2 or 16.11 .2 3. This report is not required if the measured level of radioactivity was not the result of plant effluents ; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report, required by Technical Specification 5.6.2.

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Ta ble 16.11-7, identify specific locations for

The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report .

16.11-28 Rev. OL-23 6/18

CALLAWAY -SP obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program *. The specific locations from which samples were unavailable may then be deleted from the monitoring program. In the next Annual Radiological Environmental Operating Report include the revised figure(s) and tables reflecting the new sample location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of new location(s) for obtaining samples .

d. When LLDs specified in Table '16 11-9 are unachievable due to uncontrollable circumstances such as background fluctuations , unavailable small sample sizes, the presence of interfering nuclides , etc. , the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

16.11.4.1.1 SURVEILLANCE REQUIREMENTS (ODCM 9.11.2)

The radiol.ogical environmental monitoring samples shall be collected pursuant to Tab le 16.11-7 and shall be analyzed pursuant to the requirements of Table 16.11 -7 and the detection capabilities required by Table 16.11 -9.

16.11.4.1.2 BASES The Radiological Environmental Monitoring Program provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THI= PUBLIC resulting from the station operation . This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than .expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways . Guidance for the initial monitoring program was provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring , Revision 1, Novemb er 1979.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLD's) . The LLD's required by Table 16 11-9 are considered optimum for routine environmental measurements in industrial laboratories.

Excluding short term or temporary unavailability.

16.11-29 Rev. OL-23 6/18

CALLAWAY - SP 16.11.4.2 LAINO USE CENSUS LIMITING CONDITIO N OF OPERATIO N (ODCM 9.12.1)

A Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal ,

the nearest residence and the nearest garden* of greater than 50 m 2 (500 ft2 ) producing broad leaf vegetation. The Land Use Census shall identify water intakes constructed within 10 river miles downstream of the plant discharge point.

APPLICABILITY: At all times .

ACTION :

a. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitme nt greater than the values currently being calculated by Section 16.11 .2.3.1, identify the new location(s) in the next Radioactive Effluent Release Report, pursuant to Technical Specification 5.6.3.

b. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitme nt (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Section 16.11 .4.1, add the new location(s) within 30 days to the Radio.logical Environmental Monitoring Program except for vegetation samples which shall be added to the program before the next growing season. The sampling location(s),

excluding the control station location , having the lowest calculated dose or dose commitment(s) , via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted . In the next Annual Radiological Environmental Operating. Report include the revised figure(s) and tables reflecting the new sample location(s) with information supporting the change in sample location .

C. With a Land Use Census identifying a water intake within 10 river miles downstream of the plant discharge point, implement the appropriate waterborne or ingestion sampling required by Table 16 11-7.

Broad leaf vegetation sampling of at least th tee different kinds of vegetation may be performed at the SITE BOUNDARY ih each to two different direction sectors with the highest predicted D/Q 1s in lieu of the _garden census. Requirements for broad leaf vegetation sampling in Table 16.11-7, Part 4.c shall be followed , including analysis of control samples.

16.11 -30 Rev. Ol-23 6/18

CALLAWAY - SP 16.11.4.2.1 SURVEILLANCE REQUIREMENTS (ODCM 9.12.2)

The Land Use Census shall be conducted during the growing season at least once per 12 months using that information which will provide the best results , such as , but not limited to , door-to-door survey, aerial survey, or by consulting focal agriculture authorities and/or residents . The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2.

16.11.4.2.2 BASES This Requirement is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of th is census. Information that Will provide the best results , such as door-to-door survey, aerial survey, or consulting with local agricultural authorities , shall be used . This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50 .

Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child . To determine this minimum garden size , the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i. e. , similar to lettuce a.nd cabbage) , and (2) a vegetation yield of 2 kg/m 2.

16.11-31 Rev. OL-23 6/18

CALLAWAY - SP 16.11.4.3 INTERLAB ORATORY COMPARISON PROGRAM LIMITING CONDITION OF OPERATION (ODCM 9.13.1)

Analyses shall be performed on radioactive materials supplied as part of an lnterlaboratory Comparison Program that has been approved by the USNRC.

APPLICABILITY: At all times.

ACTION :

With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6 .2.

16.11.4.3.1 SURV~ILL ANCE REQUIREMENTS (ODCM 9.13.2)

The lnterlaboratory Comparison Program shall be described in the plant procedures. A summary of the results obtained as part of the above required lnterlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Technical Sp.ecification 5.6.2.

16.11.4.3.2 BASES The requirement for participation in an approved lnterlaboratory Comparisofil Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the rest.lits are valid for the purpose of Section IV.B.2 of Appendix I to 10 CFR Part 50 .

16.11-32 Rev. OL-23 6/18

CALLAWAY - SP 16.11.5 ADMINIST RATIVE CONTROL S 16.11 .5.1 ANNUAL RADIOLO GICAL ENVIRON MENTAL OPERATIN G REPORT (ODCM 7.1)

Routine Annual Radiological Environme ntal Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

The Annual Radiological Environme ntal Operating Report shall include summaries ,

interpretations, and an analysis of trends of the results of the radiological environme ntal surveillance activities for the report period , including a comparison with preoperational studies, with operational controls and with previous environmental surveillance reports ,

and an assessme nt of the observed impacts of the plant operation on the environme nt.

The reports shall include the results of Land Use Census required by Section 16 11.4.2.

It shall also include a listing of new locations for environmental monitoring identified by the Land Use Census pursuant to Section 16 11.4.2.

The Annual Radiological Environmental Operating Report shall include the results of analysis of all radiological envirof'ilrnental samples and of all environme ntal radiation measurem ents taken during the period pursuant to Section 16.11 .4. 1, as well as summarize d tabulated results of these analyses and measurem ents in the format of the table in the Radiological Assessme nt Branch Technical Position , Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results . The missing data shall be submitted as soon as possible in a supplemen tary report. The reports shall also include the following : a summary description of the radiological environmental monitoring program ; at least two legible maps* covering all sampling locations keyed to a table giving distances and directions from the midpoint between the two reactors ; t he results of licensee participation in the lnterlabora tory Compariso n Program and the corrective action being taken lf the specified program is not being performed as required by Seeton 16.11 4 3; reasons for not conducting the Radiological Environmental Monitoring Program as required by Section i 6 11 A 1 and discussion of all deviations from the sampling schedule of Tab le 16.11 -7, discussion of environme ntal sample measurem ents that exceed the reporting levels of Table 16.11 -8, but are not the result of the plant effluents, pursuant to Section 16 11.4.1; and discussion of all analyses in wh ich the LLD required by Table 16.11-9 was not achievable .

16.11.5.1 .1 BASES The reporting requireme nt for the Annual Radiolog ical Environmental Operating Report is provided to ensure compliance with Technical Specification 5.6.2. This requireme nt was relocated from the Offsite Dose Calculation Manual to FSAR Chapter 16.

One map shall cover stations near the SITE BOUNDARY ; a- second shall include the more distant stations .

16.11-33 Rev. OL-23 6/18

CALLAWAY - SP 16.11 .5.2 RADIOAC TIVE EFFLUEN T RELEASE REPORT (ODCM 7.2)

Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

The Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents released from the unit as outlined in Regulatory Guide 1.21 , "Measuring , Evaluating , and Reporting Radioactivity in Solid Wastes and Releases Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, "Revision 1, June 1974, with data summarized on a quarterly basis in a format acceptable to the NRC.

The Radioactive Effluent Release Report shall include an annual summary of hourly meteorological data collected over the previous calender year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction , atmospheric stability, and precipitation (if measured) , or in the form of joint frequency distribution of wind speed , wind direction , and atmospher ic stability* .

This report shall also include an assessme nt of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit during the previous calendar year.

This report shall also include an assessme nt of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDAR Y (Figures 16.11 -1 and 16 11 -2 ) during the report period using historical average atmospher ic conditions . All assumptions used in making these assessments, Le., specific activity, exposure time and location , shall be included in these reports . The meteorological cond itions concurren t with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurem ent, shall be used for determining the gaseous pathway doses. Assessme nt of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM) .

The Radioactive Effluent Release Report shall include an assessme nt of rad[ation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation , for the previous calendar year to show confo rmance with 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation ."

Doses to the MEMBER OF THE PUBLIC shall be calculated using the methodology and parameters of the ODCM .

In lieu oi submission with the Annual Rad ioactive Effluent Release Report, Union Electric has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

16.11-34 Rev. OL-23 6/18

CALLAWAY - SP As required by 10 CFR 72.44(d)(3), an annual report shall be submitted to the Commission in accordance with 10 CFR 72.4, specifying the quantity of each of the principal rndionuclides released to the environment in liquld and in gaseous effluents during the previous 12 months of operation. The report must be submitted within 60 days after the end of the 12-month monitoring period .

The Radioactive Effluent Release Report shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period .

The Rad ioactive Effluent Release Report shall include a summary description of any major changes made during the year to any Uquid or Gc1seous Treatment Systems, pursuant to Offsite Dose Calculation Manual. It shall also include a listing of new locations for dose calculations identified by the Land Use Census pursuant to Sectron 16.11.4.2.

Reporting requ irements for changes to Solid Waste Treatment Systems are addressed in APA-ZZ-01011 , PROCESS CONTROL PROGRAM (PCP) .

The Radioactive Effluent Release Report shall also include the following information : An explanation as to why the liquid or gaseous effluent monitoring instrumentation was not restored to service within the time specified , and a description of the events leading the liquid holdup tanks or gas storage tanks exceeding the limits of Section 16. 11 .*1.5 or 16.11 2 8.

The Radioactive Effluent Release Report shall include as part of or submitted concurrent with , a complete and legible copy of all revisions of the ODCM that occurred during the year pursuant to Technical Specification 5.5.1 .

Solid Waste reporting is addressed in APA-ZZ~010 11, PROCESS CONTROL PROGRAM (PCP) .

16.11 .5.2.1 BASES The reporting requi rement for the Radioactive Effluent Release Report is provided to ensure compliance with Technical Specification 5.6.3. Th is requirement was relocated from the Offsite Dose Calculation Manual implementing procedure to FSAR Chapter 16.

In addition to the above reporting requirement, an annual report shall also be submitted in compliance with the HI-STORM UMAX Certificate of Compliance (CoC) , Appendix A, Section 5. 1 16.11-35 Rev. OL-23 6/18

CALLAWAY - SP TABLE rn .11 - 1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM

1. Discharge Monitor TarJks (Batch Release) (2)

S,AMPLING FREQUENCY(?) TYPE OF LLD (1)

MINIMUM ANALYSIS ACTIVITY (µCi/ml)

FREQUENCY ANALYSIS 1-'rtor to t:acn t1atc11 , 1-'rlor to t:acn t!atcn 1r>rmc1pa1 Gatnma t:m1tters \-'/ oi=.-/

1-131 lE-6 Dissolved and Entrained 1E- 5 Gases (Gamma Emitters)

H-3 1E-5 Monthly Composite (4) Gross Alpha 1E-7 Quarterly Composite (4) ~r-89, Sr-90 SE-8 Fe-55 1E-6

' Nl-63 5E-8 Np-237 5&9 Pu-238 5E-9 Pu-239/240 5E-9 Pu-241 5E-7

~m-241 5E-9 Cm-242 5E-9

- ;'.:m-243/244 SE-9

2. Steam Generator Slowdown (Continuous Re lease) (5)

SAMPLING FREQUENCY(7) TYPE OF LLD (1 )

MINIMUM ANALYSIS ACTIVITY (µCi/ml)

FREQUENCY ANALYSIS ua11y urao ::;ample (ll) wa11y ..,nnc1pal bamma 1::m1tters (JJ pi=.-(

1-131 1E-6 Dissolved and Entrained 1E-5 Gases (Gamma Emitters)

H-3 1E-5 MontlilyComposite (4) Gross Alpha 1'E-7 Quarterly Composite (4 ) Sr-89, Sr-90 5E-8 Fe-55 1E-6 TABLE NOTATIONS (1 ) The LLD Is defined , for purposes of these Requirements , as the smallest concenlratfon of radioactrve material in a sample that Will yield a net count, above system background , that will be detecled with 95% probability with onfy 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD = 4 .66 Sb Ex V l< 2.22E6 x Y x exp (-Mt)

Where{

LLD the "a priori" lower limit of detection (microCUries per unit mass or volume) ,

Sb the standard deviation of the background couf)ling rate or of the counting ra!e of a blank sample as appropriate (counts per minute) ,

E = the counting efficiency (counts per disintegration),

V ~

the sample size (units of mass or volume),

2.22E6= the number of disintegra\lons per minute per micro Curie, Y the fraclional radiochemical yield . when applicable ,

the radioactive decay constant for the particular radionuclide (sec-1 ), and Rev. OL-23 6/18

CALLAWAY - SP TABLE 16. 11-1 (Sheet 2)

Lil = the elapsed time between the midpoint of the sample collection period, and the time of counting (sec) . For batch releases , ll.t=O.

Typical values of E, V, Y, and M should be used in the calculation.

It should be recognized that the LLD is defined as a "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori (aijer the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLD's will be achieved under routine conditions.

(2) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses , each batch shall be isolated, and then thoroughly mixed by a method described fn the ODCM to assure representative samplfng .

(3) The principal gamma emitters for Which the LLD control applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 , and Ce0 144 .. This list does not mean that only these nucltdes are to be considered. Other gamma peaks that are identifiable, together with tmose of the above nuclldes , shall also be analyzed and reported fn the Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 , In the format outlined in Regulatory GLJlde 1.21 , Appendix B, Revision 1, June 1974.

(4) A. composite sample is one In which the quantity of liquid sampled is proportional to the quantity of liquid Waste discharged and in which the method of sampling employed,results in a specimen that is representative of the liquids released . Prior to analysis, all samples taken for the compos'lte st'lall be thoroughly mixed in order for the composite samples to be representative of the effluent release .

(5) A continuous release is the discharge of liquid wastes of a nondlscrete volume, e.9 ., from a volume of a system that has an input flow during the contlnuous release.

(6) Samples shall be taken al the initiation of effluent flow and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter while the release is occur~ing .

To be representative of the liquid effluent, the sample volume shall be proportioned to the effluent stream discharge volume.

The ratio of sample volume to effluent dischar!!le volume shall be maintained constant for all samples taken for lhe composite sample.

(7) Samples shall be representative of the effluent release.

Rev. OL-23 6/18

CALLAWAY - SP TABLE 16.11-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUM ENT FUNCTIONAL ACTION

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Discharge Monitor 1 31 (HB-Rc-18)

b. Steam Generator Slowdown 1 32 Discharge Monitor (BM-RE-52)

2. Flow Rate Measurement Devices

a. Liquid Radwaste Slowdown 1 34 Discharge Line (HB-FE-2017)

b. Steam Generator Blowdown 1 34 Discharge Line (BM-FE-0054)

C. Cooling Tower Slowdown and 1 34 Bypass Flow Totalizer (FYDB 1017A)

3. Discharge Monitoring Tanks (DMT1s) Level

a. DMT A (HB-Ll-2004) *1 33

b. DMT B (HB-Ll-2005) 1 33 ACTION STATEMENTS ACTION 31 - With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided that prior to initiating a release :

a. At least two independent samples are analyzed in accordance with Section 16 11 1 , 1 , and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving .

Otherwise , suspend release of radioactive effluents via this pathway.

Rev. OL-23 6/18

CALLAWA Y-SP TABLE 16.11-2 (Sheet 2)

ACTION STATEMENTS ACTION 32 - With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided grab samples are analyzed for principal gamma emitters and 1-131 at a lower limit of detection as specified in Table 16.11- 1:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 micro-Curie/gram DOSE EQUIVALENT 1-131 , or

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coo lant is less than or equal to 0.01 micro-Curie/gram DOSE EQUIVALENT 1-131 .

ACTION 33 -With the number of channels FUNCTIONAL less than required by the Minimum Channe'ls FUNCTIONAL requirement, effluent releases via this pathway may continue provided the volume discharged is determined by alternate means.

ACTION 34 -With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves generated i,n place may be used to estimate flow.

Rev. OL-23 6/18

CALLAWAY - SP TABLE 16.11-3 RADIOACTIVE LIQUID EFFLUENT MONITOR ING INSTRUMENTATION SURVEILL ANCE REQUIRE MENTS CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL INSTRUM ENT CHECK CHECK CALIBRATION TEST

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste D p R(2) 0(1)

Discharge Monitor (HB-RE-18) b .. Steam Generator D M R(2) Q(1')

Blowdown Discharge Monitor (BM-RE-52)

2. Flow Rate Measurement Devices

a. Liquid Radwaste 0(3) N.A. R N.A.

Slowdown Discharge Line (HB-FE-2017)

b. Steam Generator 0(3) N.A. R N.A.

Slowdown Discharge Line (BM-FE-0054)

C. Cooling Tower 0(.3) N.A. R N.A.

Slowdown and Bypass Flow Totalizer (FYDB1017A)

3. Discharge Monitoring Tanks (DMT's) Level

a. DMT A(HB-Ll-2004) Prior to N.A. R N.A.

release (4)

b. DMT B(HB-Ll-2005) Prior to N.A. R N.A.

release (4)

Rev. OL-14 12/04

CALLAW AY - SP TABLE 16.11'-3 (Sheet 2)

TABLE NOTATIONS

1. The CHANNEL OPERATIONAL TEST shall a,lso demonstrate that automatic isolation of this pathway and control room a'larm annunciation occur as appropriate if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm/Trip Setpoint (isolation and alarm) , or

b. Circuit failure (alarm only), or

c. Instrument indicates a downscale failure (alarm only) , or

d. Instrument controls not set in operate mode (alarm only).

2. The initial CHANNEL CALIBRATION shall be performed using one or more of the reference (gas or liquid and solid) standards obtained from the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended riange of energy, measurement range , and establish monitor response to a solid calipration source.

For subsequent CHANNEL CALlBRATION , NIST traceable standard (gas , liquid

, or solid) may be used ; or a gas, liquid, or solid source that has been calibrated by relating it to equipment that was previously (within 30 days) calibrated by the same geometry and type of source standard traceable to NIST.

3. CHANNEL CHECK shall consist of verifying indication of flow during periods of release . CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous , periodic , or batch ,releases are made.

4. CHANNEL CHECK shall consist of verifying indication of tank level during periods of release . CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous , periodic, or batch releases are made from the DMT.

Rev. OL-14 12/04

CALLAWAY - SP TABLE '16.11-4 RADIOACTIVE GASEOUS EFFLUENTS SAMPLJNG AND ANALYSIS PROGRAM 1 . Waste Gas Decay Tank SAMPLING FREQUENCY (9) MINIMUM ANALYSIS TYPE OF ACTIVITY ANALYSIS LLD (i)

FREQUENCY (1.11;:i/ml) t-'rlor to each release- grab f-'nor to eaeh tank f-'nnc1pa1 Gamma t::mmers- 1 t::-4 sample particulate, iodine, noble gas (2)

Contrnuous See footnote 8

2. Contair:iment Pur.9e or Vent SAMPLING FREQUENCY (9) MINIMUM ANALYSIS TYPE OF ACTIVITY ANALYSIS LLIJ (1)

FREQUENCY (µCl/ml)

Prior to each release" _grab Pnon o each release f-'rmc1pa1 Gamm.a 1::mmers- 1't::-4 sample particulate , iodine, noble gas (2) 1' H-3(oxide) 1E-6 Continuous See footnote 8

3. Unit Vent (3)

SAMPLING FREQUENCY (9) MINIMUM ANALYSIS TYPE OF ACTIVITY ANALYSIS LLD (1)

FREQUENCY (µCi/ml)

MonthlY- grab sample \Jl\'1/ Monthly (3)(4) f-'nnclpa l Gamma t:.mitlers- 11::-4 noble gas (2)

H-3(oxide) 1E-6 Continuous (6) Weel1ly (7) 1-131 1E-12 1-133 1E-1 0 Principal Gamma Emitters- 1E-11 particulate nucli~es only (2)

MonthlyCompos ile Gross Alpha 1E-11 Quarterly Composlte Sr-89, Sr-90 , Ni-63 , Fe-55 1E-11

- 4 . Ra.dwaste Building Vent SAMPLING FREQUENCY (9) MINIMUM ANALYSIS TYPE OF ACTIVITY ANALYSIS LLD (1 )

FREQUENC Y (~1Ci/ml)

Mor:itniy- grab samp1e 1V1onm1y Principal Gamma Em1rters- 11::-4 noble gas (2)

Continuous (6) Weekly (7) 1-131 1 E-12 f-"133 1E-10 Principal Gamma Emitters- ~ E- 11 particulate nucfides only (2)

Monthly Composite Gross Alpha 1E- 11 Quarterly Composite Sr-89, Sr-90, Ni-63, Fe-55 1'E-11

5. Laundry Decontamination Facility Dryer Exhausl SAMPLING FREQUENCY (9) MINIMUM ANALYSIS TY PE OF ACTIVITY ANALYSIS LLD (1 )

- FREQUENCY (µC i/ml) lAmtmuous (b) wee111y111 ,..,nncrpal bamma t::m1tters- 1t::.-1' particulate nuclides only (2) I Monthly. (1 0) Composite Gross Alpha 1E 11 Quarterly (10) Cornposite Sr-89, Sr-90, Ni-63, Fe-55 lE-11 Rev. OL-23 6/18

CALLAWA Y-SP TABLE 16.1 1-4 (Sheet 2) 6 . Containment ILRT Depressurization (Post-test Ven!)

SAMPLING FREQUENCY (9) MINIMUM ANALYSIS TYPE OF ACTIVITY ANALYSIS LLD (1)

FREQUENCY (µCi/ml) 1-'rlor to each release- gr<1b Pnor to each release Pnnc1pa1 Gamma t:m1tters- 11::-4 sample particulate, iodine, noble gas (2)

H-3(oxide) 1E-6 TABLE NOTATIONS (1) The LLD is defined , for purposes of these Requirements, as the srnailest concentration of radioactive material in a sample that will yield a net count, above system background , that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may incltJde radiochemical separation:

LLD = 4.66 S b E x V x 2 .22E6 x Y x exp(-A.£'.t )

Where:

LLD = the "a priori" lower limit of detection (m1croCurles per unit mass or volume) ,

Sb = the standard deviation of the background counting rate or of the counting rate of a blank sarnple as appropriate (counts per minute) ,

E the counling efficiency (counts per disintegration),

V the sample s]ze (units of mass or volume) ,

2.22E6= the number of disintegrations per minute per microCurie, Y =- the fractiona l radiochemical yield , when applicable ,

,.. = the radioactive decay constant for the particular radionuciide (se*c* 1), and 6t the elapsed time between the midpoint of the sample collection period , and the time of counting (sec) .

Typical values of E, V, Y, and -6l should be used in tt,e calculation.

It shoutd be recognized that the LLD ls defined as a "a priori" (before the fact) limit representing the capability of a

measurement system and not as an "a posteriori" (after the fact) limit for a particular measurernent. Analyses shall be performed In such a manner that tile stated LLD's will be achieved under routine conditibns.

(2) The principal gamma emitters for Which the LLD Requirement applfes in*clude U,e following radlonuclldes : Kr.87, Kr-88 . Xe-133, Xe-133m, Xe-135, a.nd Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58 , Co-60, Zn-65, 1-13 1, Cs-B4.

Cs-137 , Ce-141 , and Ce-144 in iodine and particulate releases . This list does not mean that only these nllclfdes are to be considered.

Any nuclide which Is tdenlified in the sample ano which is also listed in the ODCM gaseous effluents dose factor tables.

shall be analyzed and reported in the Radioactive Effluent Release Report.

(3) If !he Unit Vent noble gas monitor (GT-RE-21 B) shows tt,at 1he effluent actlvilY has increased (relative to the pre-lransient activity) by more than a factor of 3 following a reactor shutdown , startup , or a tt,erma l power change whfch exceeds 15% of the rated thermal power Within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period, samples shall be obtained and analyzed for noble gas, partfculates and iodines.

This sampling shall continue to be performed at least once per 24 tiours for a period of 7 days or until the Unit Vent Aoble gas monitor no longer indicates a factor of 3 increase in Unit Vent noble gas activity, whichever comes first.

(4) Tritlum grab samples shall be taken and analyzed al least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal Is flooded (5) Deleted .

(6) 'The ratio of the sample flow rate to the sampled stream flow rate shall be known for the lime period covered by each dose or dose rate calculation made in accordance witt, Sections 1 1 f 2 t 16 11 2 2, and 1G 11 2 3 (7) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or removal from the sampler. When sampling ts performed In accordance with footnote 3 (above) , lhen the LLD may be increased by a factor of 10.

(8) Continuous sampling of this batch release pa.thWay is included in the continuous sampling performed for the correspond1ng continuous release pathway.

(9) Samples shall be representative of the effluent release .

( 10) Required only If Mn-54, Fe-59', Co-58, Co-60, Zn-65, Cs-134, Cs-137 , Ce-141 , or Ce-144 are detected in principle gamma emitter analyses.

Rev. OL-23 6/18

CALLAWAY - SP TABLE 16.11-5 RADIOAC TIVE GASEOUS EFFLUEN T MONITOR ING INSTRUM ENTATION MINIMUM CHANNEL S INSTRUM ENT FUNCTION AL APPLICAB ILITY ACTION 1, Unit Vent System

a. Noble Gas Activity 1 At all times 40,46 Monitor - Providing Alarm (GT-RE-21)

b. Iodine Sampler 1 At all times 43 C. Particulate Sampler 1 At all times 43

d. Unit Vent Flow Rate 1 At all-times 45

e. Particulate and 1 At all times 43 Radioiodine Sampler Flow Rate Monitor

2. Containment Purge System

a. Noble Gas Activity Monitor Providing Alarm and 2 MODES 1,2,3, and 41 Automatic 4.

Termination of Release (GT-RE-22 ,

GT-RE-33)

- Providing Alarm 1 During CORE 42 function only ALTERATIONS or movement of irradiated fuel with in the containment

b. Iodine Sampler 1 MODES 1,2,3,4 and 43 during CORE ALTERATIONS or movement of irradiated fuel within the containment

c. Particulate Sampler 1 MODES 1,2 ,3,4 and 43 during CORE ALTERATIONS or movement of irradiated fuel wfthin the containme nt

d. Containme nt Purge N/A N/A N/A Ventilation Flow Rate Rev. OL-23a 8/18

CALLAWAY - SP TABLE 16.11-5 (Sheet2)

e. Particulate and 1 MODES 1,2,3,4 and 43 Radioiodine Sampler during CORE Flow Rate Monitor ALTERATIONS or movement of irradiated fuel within the containment

3. Radwaste Building Vent System

a. Noble Gas Activity 1 At all times 38,40 Monitor-Providing Alarm and Automatic Termination of Release (GH-RE-10)

b. Iodine Sampler 1 At all times 43 C. Particulate Sampler 1 At all times 43

d. Radwaste Building Vent NIA NIA N/A Flow Rate

e. Particulate and 1 At all times 43 Radiotodine Sampler Flow Rate Monitor

4. Laundry Decontamination Faciliy Dryer Exhaust

a. Particulate Monitor 1 When the dryers 47 are operating b, Particulate Monitor Flow 1 When the dryers 47 Rate Meter are operating C. Dryer Exhaust NA NA NA Ventilation Flow Rate ACTION STATEMENTS ACTION 38 - With the number of low range channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement. the contents of the tank(s) may be released to the environment for up to 14 days provided that prior to initiating the release:

a. At least two independent samples of the tank's contents are analyzed ,

and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup.

Rev. OL-23a 8/18

CALLAW AY - SP iABLE 16.11-5 (Sheet 3)

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 39 - Deleted.

ACTION 40 - With the number of low range channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 41 - With the number of channels FUNCTIONAL one less than required by the Minimum Channels FUNCTIONAL requirement, restore the affected channel to FUNCTIONAL status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . If the non-functional channel is not restored within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or with no channels FUNCTIONAL, immediately suspend the release of radioactive efflttents via this pathway.

Containment mini-purg.e supply and exhaust valves that have been closed to satisfy this Action may be opened under administrative controls provided either:

a. one channel is FUNCTIONAL, or b, the requirer.nents for Table 16.11-5 Function 1.a are met and the requirements for minimum channels FUNCTIONAL for the Unit Vent Noble Gas Monitor (GT-RE-21) specified in Tab le 16 3-7 Function 3 are met.

The administrative controls consist of designating a control room operator to rapidly close the valves when a need for system isolation is indicated .

ACTION 42 - With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, and if the containment equipment hatch is open , then immediately suspend CORE ALTERATIONS and movement of irradiated fuel assemblies within containment. If the containment equipment hatch is not open , then suspend the release of radioactive effluents via this pathway or immediately suspend CORE ALTERATIONS and movement of irradiated fuel assemblies within containment.

ACTION 43 - With the number of channels FUNCTIO NAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 16 11 -4 Rev. OL-23a 8/18

CALLAW AY-SP TABLE 16.11-5 (Sheet4 )

ACTION 44 - Deleted.

ACTION 45 - Flow rate for this system shall be based on fan status and operating curves or actual measurements.

ACTION 46 - For midrange and high range channels only - with the number of FUNCTIONAh.. channels less than required by the Minimum Channels FUNCTIONAL requirement, take the action specified in Section 16.3.3.4 ,

ACTION C.

ACTION 47 - With the number of channels FUNCTIONAL less than requ ired by the Minumum Channels FUNCTIONAL requirement, immediately suspend the release of radioactivite effluents via th is pathway.

Rev. OL-23a 8/18

CALLAW AY-SP TABLE 16.11-6 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUME NTATION SURVEILL ANCE REQUIREMENTS MODES FOR WHICH CHANNEil_ SOURCE CHANNEL CHANNEL OPERATIONAL INSTRUME NT SURVEILLANCE CHECI< CHECK CAUBRAT ION TEST

, . Unit Vent System IS REQUIRED

a. Noble Gas Activity Monitor - D M R(3) Q(2) Al all times Providing Alarm (GT-RE-21)

b. Iodine Sampler w N.A. N.A. N.A. At all tfmes C. Particulate Sampler w N.A. N.A. N.A. At all times

d. Unit Vent:- Flow Rate N.A. N.A. R(4) Q At all times

e. Particulate and Radioiodine D N.A. R Q Al all times Sampler Flow Rate Monitor 2.. Containment Purge System

a. Noble Gas Activity Monitor - NA p N.A. N.A. MODES 1,2,3,4 and during Providing Alarm and Automatic Terml natron of Release (GT-RE- CORE ALTERATIONS or 22 , GT-RE-33) movement of irradiated fuel within the containmen t

b. Iodine Sampler w NA N.A. N.A. MODES 1,2 ,3.4 and during CORE ALTERATIONS or movement af l rradiated fuel within lhe containment C. Partfculate Sampler w NA NA N.A. MODES 1,2,3,4 and during CORE ALTERATIONS or movement of irradiated fuel within the containment d, Containment Purge Ventilation N.A. N.A. R(4l N.A. MODES 1,2,3,4 and during Flow Rate CORE ALTERATIONS or movement of irradTated fuel within the containment Rev. OL-13 5/03

CALLAWAY - SP TABLE 16. 11-6 (Sheet 2)

MODES FOR WHICH CHANNEL SOURCE CHANNEL CHANNEL OPERATION AL INSTRUMEN T SURVEILLAN CE CHECK CHECK CALIBRATION TE~,J IS REQUIRED

e. Particulate and Radioiodine D N.A. R N.A. MODES 1,2,3.4 and during Sampler Flow Rate Monitor CORE ALTERATIONS or movement of irradiated fuel within the conta1nment

3. Radwaste Building Vent System

a. Noble Gas Activity Monitor - D,P M,P R(3) Q(i) Atalf times Providing Ala{TTl and Automatic Termination of Release (GH-RE-10)

b. Iodine Sampler w N.A. N.A. N.A. At all times

c. Particulate Sampler w N.A. N.A. N.A. At all times d, Radwaste Building Vent Flow N,A. N.A. R(4) N.A. At all times Rate

e. Particulate and Rad ioiodine D N.A. R NA At all times Sampler Flow Rate Monitor

4. Laundry Decontamination Facility Dryer Exhaust

a. Particulate Monitor NA D A Q(S) When the dryers are operating

b. Particulate Monitor Flow Rafe D NA A Meter NA When the dryers are operating

c. Dryer Exhaust Ventilation Flow NA NA R(4) NA vvtien the dryers are 0perating Rate Rev. OL-13 5/03

CALLAW AY - SP TABLE 16.11-6 (Sheet 3) 1.. The CHANNEL OPERATIONAL TEST shall also demonstrate that 3. The Initial CHANNEL CALIBRAT ION shall be performed using one or more of automatic isolation of this pathway and control room alarm the reference (gas or liquid and solid) standards certified by the National Institute of Standards & Technology annunciation occur as approprlate if any of the following conditions (Nlsn or using standards that have been obtained from suppliers that participate in measurem exists: ent assurance activities with NIST. These standards shall permit calibrating the system over lts intended range of energy, measure*ment range , and establish monitor response to

a. Instrument indicates measured levels above the Alarmfrrip a solid calibration source. For subsequent CHANNEL CALIBRATION, NIST traceable standard Setpoint (isolation and alarm) , or (gas, liquid, or solid) may be used ; or a gas, liquid, or solid source that has been calibrated by relating II to equipment that was previously (within 30 days) calibrated by the same geometry

b. Circuit failure (alarm only) , or and type of source standard traceable to NIST.

c. Instrument indicates a downscale failure (alarm only) , or 4. tfflow rate is determined by exhaust fan status and fan performance curves , the following su.rvelllance operations shall be performed at least once per 18 months:

d. Instrument controls not set in operate mode (alarm ooly).

a. The specific vent fiows by direct measurement, or

2. The CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following b. The differential pressure across lhe exhaust fan and vent flow established by conditions exists: the fan's "flow-t.P" curve , or

a. Instrument indicates .measured levels above the Alarm Setpoinl, or c. The fan motor horsepower measured and vent flow established by the fan's "flow-horse power" curve.

b, Circuit failure, or 5 . The CHANNEL OPERATIONAL TEST shall also demonstrate that automatic

c. Instrument Indicates a downscale failure . or isolation of1hls pathway and the shutdown of the dryers occur as appropriate if any of the following conditlons eliists :

d. Instrument controls not set In operate mode.

a. Instrument indicates measured levels above the Alarrnfrr(p Setpoint. or

b. Monitor failure.

Rev. OL-13 5/03

CALLAWAY - SP TABLE 16.11-7 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTA'IWE EXPOSUR E PATHWAY SAMPLES ANO SAMPLE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE LOCATIONS (1) COLLECTION FREQUENCY OF ANALYSIS

1. Direct Radlation (2l Forty routine monitoring stations Quarterly Gamma dose for each sample. Neutron either with two or more dosimeters or dose for the four samples monitor1ng with one instrument for measuring and ISFSI direct radiation.

recording dose rate continuously, placed as follows :

An inner ring of sixteen stations. one in each meteorological sector in the general area of the Sl'T'E BOUNDARY; Four otthe stations shall be placed lo monitor for gamma and neutron dose from the ISFSI; All outer ring of stations, one in each meteorolo.gical sector in the 6-to 8-km (3 to 5 mile) range from ttte site; and Eight stations to be placed in special Interest areas such as population centers. nearby residences . schools, and in one or two areas to serve as control stations.

2. Airborne Radioiodine and Particulates Samples from five locations ;

Three samples from close to the SITE Continuous sampler operation with Radloiodfne Canister: 1-131 analysis BOUNDARY locations , rn different sample collection weekly, or mere for each sample .

sectors. with high calculated annual frequently if requfred by dust loading .

average ground level D/Qs.

Gamma isotopic analysis(S) for each sample.

One sample from the vicinity of a community located near the plant with a high calc:ulated annual average ground level D/Q.

One sample from a location in the vicinity of Fulton. MO.

Rev. OL-22 11/16

CALLAWAY - SP TABLE 16.11-7 (Sheet 2)

NUMBER *OF REPRESENTATIVE EXPOSUR E PATHWAY SAMPLES AND SAMPL[=

SAMPLING AND TYPE AND FREQUEN CY AND/OR SAMPLE LOCATIONS (l I COLLECTION FREQUEN CY OF ANALYSIS

3. Waterborne

a. Surface (6) (river) One sample upstream Composite sample over 1-monlh Gamma lsotopic(5) and tritium One sample downstream period (7) . analysls for each sample.

b, Surface (onsite po11ds) Waler sample from on site ponds Semiannually Gamma isotopic(5) and tritium forming a ri n_g around the plant, analyses for each sample. If suitable for monitoring for plant storm contaminated with gamma emitting water runoff and washout from plant nuclldes of plant origfn, analyze for gaseous effiuents, placed as follows:

HTD nuclides(11).

Each seltlrng pond receiving plant storm water runoff.

One of t~e in-service sludge lagoons.

Two additional on site ponds most lll~ely to be affected by washou t of radioactiv1ty released ln gaseous effluents.

c, Groundwater (non-drinking water) Groundwater samples from non* Quarterly Gamma isotopic(6l and trillum drinking water shallow and deep! 12l analyses for each sample. If monitoring wells located as follows :

contaminated with gamma emitting nu elides of plant origin , analyze for Samples from one deep well located upgradient of the plant power block HTD nuclldesl11 ).

and one deep well located downgradient of the sludge lagoons.

Samples from seven shallow wells or groundwater sumps in locations suitable (o monitor for subsurface leakage from power block structures and com,µon~nts .

Rev. OL-22 11/16

CALLAW AY - SP TABLE 16.11-7 (Sheet 3)

NUMBER OF REPRESENTATIVE EXPOSUR E PATHWAY SAMPLES AND SAMPLE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE LOCATIONS (H COLLECTION FREQUEN CY OF ANALYSIS

c. Groundwater (non-drinking waler) Samples from three shallow wells In (continued) locations suitable to monitor for migrations of contaminated groundwater from the power bloc}<

area to areas outside the Owner Controlled Area fence (one Well upgradient of the plant power block and two wells fn areas likely to be affected.)

Samples tram one shallow well located immectiately downgradlent of the sludge ponds.

Samples from fi.ve shallow wells located along the discharge pipeline corridor in the a*11uvial plain ,

Samples from three shallow wells near the property boundary loca ted to monitor for migration of contaminated groundwater from the discharge pfpellne to the nearest potable water well.

Samples from one deep well near the property boundary located to monitor for n,igration of contaminated groundwat er from the discharge pipeline to the nearest potable water well.

Rev. OL-22 11 /16

CALLAW AY - SP TABLE 16.11-7 (Sheet 4)

NUMBER OF REPRESENTATIVE EXPOSUR E PATHWAY SAMPLES AND SAMPLE SAMPLING AND TYPE AND FREQUENCY ANt:l/OR SAMPLE LOCATIONS ( ll COLLECTION FREQUENCY OF ANALYSIS

d. Drinking (rfver waler) One sarnple of each of one to three o"f Composite sample over 2-week 1-1 31 analysis on each composite the nearest water supplies within 1O period(7J when 1-131 analysis is when the dose calculated for the miles downstream that could be performed, menthly composite consumption of the water is greater affected by its discharge .

otherwise. than 1 mrem per year< 9 ). Composite for gross beta and gamma isotopic analyses(5l monthly. Composite for tritium analysis quarterly.

One sample from a control location.

As there are no drinking water intakes with in 1 O mlles downstream of the discharge point, the drinking water pathway Is currently not 1ncfuded as part of the Callaway Radiological Environmental Monitoring Program. Should the annual Land Use Census Plant identify water intakes within 10 river miles downstream of the discharge point , the be revised to include this pathway. program will

e. Drinkfng (potable well water) Samples of potable well water Quarterly appropri,Jte for monitoring for Gamma rsotopicC 51and trltrurn radioactivity in drinking water supplies analyses for each sample. It in areas most likely to be affected by a contamihated with nuclides of plan!

spill or leak. orig1n, analyze for HTD nuclides f1 1).

Two samples of potable well water from lhe communlty of Portland , MO.

One sample of Callaway Plant potable water.

One sample of potable well waler from each resident bordering plant property along Mud Creek and Logan Creek.

f, Sediment from rlver shoreline One sample from downstream area Semiannually with existing ar potential recreational Gamma isotopic analysis<51for each value sample One sample from upstream control location.

Rev. OL-22.

11/16

CALLAW AY - SP TABLE 16.11-7 (Sheet 5)

NUMBER OF REPRESENTATIVE EXPOSUR E PATHWAY SAMPLES AND SAMPLE SAMPLING AND TYPE AND FREQUENCY ANO./OR SAMPLE LOCATIONS (1J COLLECTION FREQUEN CY OF ANALYSIS

g. Shoreline sediment from sludge Shoreline sedlment from each on slte Annually ponds sludge pond most likely lo be affected. Gamma lsotopJc(5l analysis for each sample.

One sample from each in-service sludge pond .

One sample from each wetlands pond.

4. lngestton ca. Milk Samples from milking animals in three Semlmonthly when animals are on different meteorological seclors within Gamma isotop(c! 5) and 1-1 31 analyses pasture, monthly at other times 5 km (3 rnlle) distance having the for each sample highest dose poteratial. If there are none , then one sample from milking animals in each of three different meteorological sectors between 5 to 8 km (3 to 5 mile) distance where doses are calculated to be greater than 1 mrem per yr.! 9)

One sample from milking animals at a contro l location , 15 lo 30 km (1 O to 20 mile) distance and in the le;ist prevalent wlnd directlon .

Due to !he lack of milking animals which satisfy these requirements , the milk pathway is currently not included as part of the Callaway Plant Radiological Environmental Pro_gram. Should the Annual Land Use Census identify the existence of milking Monitoring animals 1n locatfons which satisfy .these requirements , then *the program writ be revised pathway, lo include this

b. Fish One sample o'feach commercially and Sample in season, or semiannually if recreatfona lly important species in Gamma isotopic analysis<5 l on edible they are not seasonal vlcinlly of plant discharge area . portions for each sample One sample of same species in areas not influenced by plant discharge.

Rev. OL-22.

11/16

CALLAWAY - SP TABLE 16.11-7 (Sheet 6)

NUMBER OF REPRESE NTATIVE EXPOSU RE PATHWAY SAMPLES AND SAMPLE SAMPLIN G AND TYPE AND FREQUEN CY AND/OR SAMPLE LOCATIO NS (1) COLLECT ION FREQUE NCY OF ANALYSI S

c. Food Products One samp le of each principal class of At time of harvest(1D) Gamma isotopic analysis( 5) on edible food products from any area that 1s irrigated by water in which liquid plant portion for each sample wastes have been discharge d .

As there c1re no areas krfgated by waler fn which liquid plant wastes have been discl~arged within -50 mlles downstrea m of the discharge included as part of the Callaway Plant Radiologi cal Environm ental Monitoring point this sample type is not currently Program. Should the annual Land Use Census ldentify Irrigation water downstrea m of the discharge point, the program will be revised lo include intakes within 10 river miles this sample type.

Samples of three different kinds of Monthly when available broad leaf vegetation if available Gamma isotopic (S) and 1-131 grown nearest each of two different analyses o~site locations of highest predicted annual average ground level D/Q if milk sampllng is not performed One sample of each o'f the similar Monthly when available broad leaf vegetation grown 15 to 30 Gamma isotopic (S) and 1-131 km (1 O to ;w mile) distant in the least analyses prevalent wihd direction if milk sampling is not performed

5. Soil Surface soil samples suitable for Annually monitoring for ground deposition if Gamma isotopfc(5l analysis for each radioactiv ity in gaseous effluents as sample.

follows :

Four ecology plots located in four quadrants surroundi ng the planl One control location from an area not likely to be iriOuenced by plant gaseous eff]uenls.

Rev. OL-22 11 /16

CALLAW AY - SP TABLE 16. 11 -7 (Sheet 7)

NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE LOCATIONS (11 COLLECTION FREQUENCY OF ANALYSIS

6. Farm crops( 13l Farm crops from areas most likely to At lime ofharvestl1D) Gamma isotopic(5l and tritium be affected by a break or leak in the discharge pipeline , located as follows : analyses for each sample Three samples of each type of farm crop along the discharge plpeline corridor between manhole 8 and Katy Trail.

Three samples of each type of farm crop along lhe discharge pipellne corridor between manhole 5 and manhole 38.

Three samples of each type of farm crop along O,e discharge pipeline easement between Hwy 94 and the barge loading dock access road.

One sample of each type of crop sampled above, from a control location unlikely lo be influenced by plant operations.

TABLE NOTATIONS 1, Specific parameters of distance and direction sector from the centerline of one unit.

and additional description where pertinent. shall be provided for each and every in Table *16 .11-7 in a table and flgUr'e(s) in the appropriate plant procedures. Deviations sample lo ca lion are permitted from the required sampling schedule if specimens are unobtaina.b hazardous conditions, seasonal Unavailability, malfunction of automatic sampling le due to equipment, and other legitimate reasons. If specimens are unobtainable due to equipment malfunction , every effort shall be made to complete corrective action samplfng prior to the end of Uie next sampling period. All deviations from the sampling schedule documented in the Annual Radiological Environmental Operatrng Report pursuant shall be to Technical Specification 5.6.2.

It is recognized that, at titnes, it may nDt be possible or practicable to conGnue to obtain samples of the media of choice al the most desired location or time . In these suitable specific alte~native media and locations may be chosen for the particu.lar instances pathway in question and appropriate substitutions made within 30 days in the Radiologica Environmental MonitorTng Program. Submit in !Me next Annual Radiological Environme l ntal Operatlng Report documentation for a change including the revised ligure(s) reflecting the new location(s) Wllh supporting information identifying the cause of and table the unavailability of samples for tha1 pathway and justifying the selection of the new obtaining samples. location(s) f or Rev. OL-22 11/16

CALLA WAY - SP TABLE 16.11-7 (SheetB)

The selection of sample locations should consider accessibility of sample sile, availability of power, wind direction frequency. sector population presence of potentially adverse environmental conditio ns (such as unusually , equipmen t securit,y, and the dusty condltrons , etc.).

2. One or (Jlore instruments . such as a pressurized ion chamber, for measuring and record ing dose rate continuously may be used in place of, or in addition For the purposes oflhls table, a thermolum inescent dosimeter (TLD) to , integrating dosimeters.

and/or an optlcally stimulated luminesce nt dosl meter (OSLO) , are considere phosphors in a packet are considered as two or more dosimeter s. Film d to be one phosphor ; two or more badges shall not be used as dosimeter s for measuring direct radiation monitoring statrons may be reduced according to geograph ical limitations . The number of direct radtation

e.g .. al an ocean site , some sectors will be over waler so that the number accordingly. The freq uency of analysis or readout for TLD systems will of dosimeter s may be reduced depend upon the character1stics of the specific system used and should information with minimal fading . be selected to obtain optimum dose

3. Deleted.

4. Deleted .

5. Gamma Isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

6 . The "upstream sample" shall be talsen at a distance beyond significan t influence of the discharge . The downstream" sample shall be taken in an area the mixin.9 zone. near the downstrea m edge of

7. In this program, composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g.,

obtaining a representative sample. monthly) In order to assure

8. Groundwa ter samples shall be taken when this source is tapped for drinking or irrigation purposes l n areas where the hydraulic gradient or recharge contamination. properties are suitable for

9. The dose shall be calculated for the maximum organ and age group.

using the methodology and parameters in the ODCM.

10. lf harvest occurs more than once a year, sampling shall be performed durin.9 each discrete harvest. If harvest occurs continuously, sampling shall paid to including samples of tuberous and root food products. be mot1lhly. Atter,tion shall be 11 , *In this program , HTD nuclides are defined as 69 Sr, 90 sr, 55 Fe, 63 Ni, 237Np , 238 Pu , 241 Am , 242 cm , and 243124 4cm .

12. In this program, a shallow well is defined as a well which extracts groundwa ter from the vadose zone. A deep well is defined as a well wtiich extracts zone. groundwa terfrom the saturated

13. Edible, and r,on-edib le farm crops from areas that could be affected by a break or leal< in the discharge pl peline (including the retired discharge pipeiine.)

Rev. OL-22 11/16

CALLAWAY - SP TABLE 16.11-8 REPORTING LEVELS FOR RADIOACTIVITY CONCEN TRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS FISH WATER AIRBORNE PARTICULATE (pGl/kg, MILK FOOD PRODUCTS ANALYSIS (pCillt OR GASES (pCi/m3) wet)b (pCi/lJa pCi/k:g, wet)b H-3 20.000*

Mn-54 1 ,000 30 ,000 Fe-59 400 10,000 Co-58 1,000 30,000 Cos60 300 10,000 zn:65 300 20,000 Zr-Nb-95~ 400 1-131 2 0,9 3 100 Cs-134 30 10 1.000 60 1,000 Cs-137 50 20 2.000 70 2,000 Ba La-14o**

0 200 300 (a) Multiply the values In 1h1s table by 1E-9 to convert to units of µCi/ml.

(b) Multiply the values in this table by 1 E-9 to convert to units of ftCllg.

For drinking water samples . This is 40 CFR Pact 141 value. For surface waler samples; a value of 30,000 pCl/1 may be used.

Total activity, parent plus daughter activity_

Rev. OL-14 12/04

CALLAW AY - SP TABLE 16.11-9 DETECTION CAPABILITITES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMrT OF DETECTION (LLD) (1), (2) , (3)

FOOD AIRBORNE FISH PRODUCTS SURFACE SEDIMENT DRINKING PARTICULATE (pCi/kg , MILK (pGilkg , (pCilkg, ANALYSIS WATER (pCi/l)a WATER (pCi/l)a OR GASES (pCl/m3) wet)b (pGf/J)a wet)b dry)b Gross Beta 4 4 0.01 H-3 3000 2000 Mn-54 15 *15 130 Fe-59 30 30 260 Co-58.60 15 15 130 Zn-65 30 30 260 Zr-Nb-gs* 15 15 1-131 .. 1 0.07 60 Cs-*134 15 15 0.05 130 15 60 150 Cs-137 18 16 0.06 150 18 60 160 Ba-La-140' 15 15 ,s (a) Multiply the values In this !able by 1E-9 to convert to units ofµCl/ml.

(b) Multiply the values in thts table by 1E--9 to convert to units of µCilg.

Total activity, parent plus dau.ghter activity.

For surface water samples, ttw LLD of gamma isotopic analysis may be used .

Rev. OL-23 6/18

CALLA WAY - SP TABLE 16,11-9 (Sheet2)

TABLE NOTATIONS

1. Thfs list does not mean that only these nuclldes are to be considered.

Other peaks that are fdentifiable , together wtth those of the lfsted nuclides, in the Annual Rad iological Environmental Operating Report. shall atso be analyzed and reported

2. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the 4.13 , Revision 1, July 1977. recommendations of Regulatory Guide

3. The LLD is defined , for purposes of lhese Requirements, as the smallest concentration of radioactive material in a sample that will yield a net count, will be detected with 95% probabiltty wifh only 5% probability of falsely above system background , that concluding that a blank observation represents a real" sfgnal.

Fora particular measurement system , Which may include radiochemical separation :

LLD = = - - - - -4 ,--,_66_S-: -b:---,,-- .-

E x V x 2,22E6 x Y x exp(-A.6.t)

Where:

LLD = the "a priori" lower limit of detection (rnlcroCuries per unit mass or volume) .

Sb = the standard deviation of the background counting rate or of the countlng rate of a blank sample as appropriate (counts per minute) ,

E = the counting efficiency (counts per disintegration) ,

V = the sample size (units of mass or volume) ,

2.22E6 = the number of disintegrations per minute per microCurie .

Y = the fractional radiochemical yield, when applicable ,

7c = the radioactive decay constant for the particular ra dionuclide {sec-1 ), and t,.t = the elapsed time between the end of the sample collection period , and the time of counting (sec),

Typical values of E, V, Y, and ~ t should be used in the calculation .

It should be recognized that the LLD ls defined as a "a priori" (before the fac.t) limit representing the capability ofa measurement system and not limit for a particular measurement. Analyses shall be performed in sucli as an "a posteriori" (after the fact) a manner that the stated LLD's will be achieved under routine conditions Rev. OL-23 6/18

ULNRC-06523, 2018 Annual Radioactive Effluent Release Report, Revision 1

Text

SUMMARY

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