ZS-2017-0058, Resubmittal of Radioactive Effluent Release Report, Radioactive Effluent Control Program Report, Offsite Dose Calculation Manual and Process Control Program for 2016

Resubmittal of Radioactive Effluent Release Report, Radioactive Effluent Control Program Report, Offsite Dose Calculation Manual and Process Control Program for 2016

ML17170A136
Person / Time
Site:	Dresden, Zion  File:ZionSolutions icon.png
Issue date:	06/12/2017
From:	Gerard van Noordennen ZionSolutions
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
ZS-2017-0058
Download: ML17170A136 (441)

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ZIONSOLUTIONSL_LC_ _ _ _ _ _ __

An EnergySolutions Company June 12, 2017 ZS-2017-0058 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Zion Nuclear Power Station, Units 1, 2 and ISFSI Facility Operating License Nos. DPR-39 and DPR-48 NRC Docket Nos. 50-295, 50-304 and 72-1037

Subject:

Resubmittal of Radioactive Effluent Release Report, Radioactive Effluent Control Program Report, Offsite Dose Calculation Manual and Process Control Program for 2016 Attached is a corrected copy of the Annual Radioactive Effluent Release Report (ARERR) for the period January through December 2016. During an assessment of the 2016 ARERR, several editorial and other minor errors were noted throughout the report. None of the changes affected the conclusions from data evaluation. Revision bars have been added to reflect changes in the report. There are no new regulatory commitments in this submittal. If you have any questions about this submittal please contact Mr. Christopher Keene at (224)789-4073. Respectfully, n.4 ;f G~~rt&&¥~~ Gerard van Noordennen Vice President of Regulatory Affairs Attachments:

1. Radioactive Effluent Release Report

2. Zion Station ODCM, Rev. 9

• 3. ECN 2015-07 Modification of Lake Release System

4. TR-005-2016: ODCM Rev 6 Technical Review Letter

5. TR-011-2016: ODCM Rev 7 Technical Review Letter

6. TR-012-2016: ODCM Rev 8 Technical Review Letter

7. ES&H TSD 16-007 Basis document for TR-012-2016 101 Shiloh Boulevard, Zion

• IL 60099 (224) 789-4016 *Fax: (224) 789-4008
• www.zionsolutionscompany.com

1-ZionSolutions, LLC ZS-2017-0058 Page 2 of2 cc: John Hickman, U.S. NRC Senior Project Manager Regional Administrator, U.S. NRC, Region III Service List (Cover letter only, no attachments)

Zion Nuclear Power Station, Unit 1and2 License Transfer Service List cc: Ken Robuck Russ Workman Group President Disposal and General Counsel Decommissioning EnergySolutions EnergySolutions 299 South Main Street, Suite 1700 299 South Main Street, Suite 1700 Salt Lake City, UT 84111 Salt Lake City, UT 84111 Alwyn C. Settles John Sauger Section Head, Nuclear Facility Inspection Executive VP & General Manager Bureau of Nuclear Facility Safety ZionSolutions, LLC Illinois Emergency Management Agency 101 Shiloh Boulevard 1011 North St., PO Box 250 Zion, IL 60099 Mazon, IL 60444 Gerard van Noordennen Kelly F. Grahn VP Regulatory Affairs Senior Health Physicist, Unit Supervisor ZionSolutions, LLC Bureau of Radiation Safety, Environmental 101 Shiloh Boulevard _ Management Zion, IL 60099 Illinois Emergency Management Agency 245 W Roosevelt Road, Building 8, Suite 55 Anthony Orawiec West Chicago, IL 60185 Decommissioning Plant Manager ZionSolutions, LLC Kent McKenzie 101 Shiloh Boulevard Emergency Management Coordinator Zion, IL 60099 Lake County Emergency Management Agency 1303 N. Milwaukee Avenue Dan Shrum Libertyville, IL 60048-13 08 Senior VP Regulatory Affairs . EnergySolutions John E. Matthews 299 South Main Street, Suite 1700 Morgan, Lewis & Bockius LLP Salt Lake City, UT 84111 1111 Pennsylvania A venue, NW Washington, DC 20004

ZionSolutions LLC ZS-2017-0058: Attachments ATTACHMENT I Radioactive Effluent Release Report

ZionSolutions LLC ZS-2017-0058: Attachment 1 Data Revision for AREOR 2016 Report Page 3 of 56 changed torit volume form 7,500 cfm to 5,000 cfm. Page 4 of 56 removed, there were no batch releases. Page 10 Replaced (LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (Unit 1 & Unit 2 combined) 2015 data with 2016 data. Page 14 of 56 revised table (Maximally exposed switchyard: Switchyard South (lOOmrem/year limit)) Column 3rd Qtr Row Sum, from 2.. 82E+Ol to 2.81E+Ol.

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 1of56 List of Sections Section# Description 1 Supplemental Information Effluent & Waste Disposal Summary 2.1 Unit 1 Gaseous Effluent 2.2 Unit 2 Gaseous Effluent 2 2.3 Liquid Effluent 2.4 Direct Radiation 2.5 LLD's 2.6 Error Estimation 3 Solid Waste and Irradiated Fuel Shipments Radiological Impact on Man 4.1 40CFR190 & 10CFR72 Compliance summary 4.2 Unit 1 4 4.3 Unit 2 4.4 ISFSI 4.5 Combined 40CFR190 report 5 Meteorology Data 6 Errata Data from previous years 7 Summary of Liquid and Gaseous Radwaste System Changes 8 Corrective Actions for Inoperable Rad Monitor >30 days 9 Changes to the ODCM and current copy of the ODCM

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 2of56 Section 1 - Supplemental Information

1. Regulatory Limits: The dose toa member of the public from direct radiation, liquid and gaseous effluents released from each unit to areas at or beyond site boundary shall be limited to the following:

a. Fission and Activation products:

1. Tech Spec Whole Body: 500 mrem/year

11. Tech Spec Skin: 3000 mrem/year

b. Particulates with half-lives> 8 days, tritium and Iodine:

i. Tech Spec Organ: 1500 mrem/year

11. 10 CFR 50 Organ: 7.5 mrem/quarter, 15 mrem/year

c. Liquid Effluents:

i. 10 CFR 50 Whole body: 1.5 mrem/quarter, 3 mrem/year

11. 10 CFR 50 Organ: 5 mrem/quarter, 10 mrem/year

d. Combined dose to real individual beyond controlled area:

i. 10 CFR 72 Whole body: 25 mrem/year 1i. 10 CFR 72 Thyroid: 75 mrem/year 111. 10 CFR 72 Organ: 25 mrem/year

2. Effluent Concentration Limits (ECL): Limits used in determining allowable release rates or concentrations.

a. Gaseous Effluents: 10 CFR 20 Appendix B Table 2 Column 1.

b. Liquid Effluents: 10 X 10 CFR 20 Appendix B Table 2 ~olumn 2.

3. Measurements and Approximations of Total Radioactivity.

a. Fission and Activation Products: In January of 2015 all fuel was removed from the Fuel Handling Building and transferred to the ISFSI thus in 2016 noble gases are no longer present as potential gaseous effluents. Vent stack activity was continuously monitored for particulates in gaseous effluent until 12/8/2016. On 12/8/2016, both Unit 1 and Unit 2 ventilation stacks were permanently shut down and are no longer available as gaseous effluent release points. Portable ventilation units were installed to maintain habitability inside Unit 1 and Unit 2 containments. Portable tent containments were built outside of Unit 1 and Unit 2 construction hatches for loading of decommissioning debris, and open air demolition has commenced on the fuel handling building and Auxiliary Building.

Means have been established to monitor each of the three types of release paths: Filtered ventilation, open door access points, and open air demolition. I

b. Particulate releases were continuously monitored and samples collected and analyzed weekly prior to 12/8/2016. After 12/8/2016, particulate releases are continuously monitored and analyzed daily. Particulate filters are sent to an independent lab for quarterly composite analysis. Prior to 12/8/2016 and during periods when 1RIA-PR49 and 2RIA-PR49 were Out of Service for maintenance

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 3of56 particulate activity was continuously monitored and analyzed daily in each of the areas feeding into the respective Units vent stack (i.e. Unit 1 purge system for Unit 1 vent stack and Unit 2 purge system, Aux. building, Fuel Handling Building for Unit 2 vent stack). A separate composite was sent to an independent lab for composite analysis for each area monitored. There is no longer a large volume water source containing Tritium, thus the remainder of the Tritium present is monitored and calculated in liquid effluent releases instead of estimating the release via evaporation. An alternate gaseous release path was established for the purpose of preventing the liquid effluent batch release line from freezing during the winter of the first quarter of 2016. An air compressor with a flowrate of 78 cfm @ 125psi drew air from a room in the Auxiliary Building and discharged the air thro11gh the liquid effluent discharge line. The air in the room from which it drew its suction was continuously monitored and the samples analyzed daily. All activity detected in this air sample was added to continqous alternate gaseous releases and the samples sent for quarterly composite analysis. After 12/8/2016 the release paths are defmed as Unit 1 torit, a max 17,500 c.f.m. *filtered ventilation system drawing suction from Unit 1 containment and discharging via its own built in exhaust. Unit 2 torits of which consists *of two independent 5,000 c.f.m filtered ventilations which draw suction from Unit 2 containment and discharge via their own independent exhaust hoses~ Unit 1 and Unit 2 tents each have an equipment rollup door that is open during working hours and a personnel access door, each of these 4 locatioQ.s have their O}Vll air sample continuously running to monitor any potential release ba,sed on wind speed for release rate estimation. Open air demolition of the fuei handling building has at least 4 air samples running around the area from which potential radioactivity release is monitored and dose can be estimated should there be any radioactivity identified from daily analysis or quarterly composite results. *

c. The Waste Water Treatment Facility (WWTF) liquid effluents from the turbine building drains were continuously collected, isotopic analysis performed weekly, and quarterly composites performed by a lab until 5/16/2016. On 5/16/2016 the WWTF compositor and liquid effluent lines from the turbine building were removed. The turbine building was 100% demolished by the end of2016.

d. Liquid Rad Waste Treatment System - Liquid batch releases are mixed and a representative sample taken and analyzed prior to batch release. A complete analysis of all liquid volumes was performed by an offsite laboratory to determine hard to detect nuclide activity. A conservative ratio to <:o-60 was calcufated for each hard to detect nuclide. Prior. to each batch release, these scaling factors were used to calculate the concentration of these hard to detect nuclides.

e. Occupancy factors were used in determining direct radiation dose to the maximally exposed member of the public based on habits of a real Individual in ES&H Technical Support Document 13-009 "Member of the Public Dose from All Onsite Sources." A study was completed during Q3 of 2016 in which Panasonic type 814 TLDs were placed alongside the Harshaw TLD 1OOs specified by the ODCM. The results showed the overall net dose on all of the TLDs unimpacted by neutrons from the ISFSI were almost identical for the Harshaw and Panasonic TLDs. The Harshaw TLD 100 chips which *contain natural Lithium have a gamma over-response by up to 30 mR per quarter depending on

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 4 of56 distance from the ISFSI. Ql-Q3 of2016, dose was calculated for members of the public and onsite workers using these TLDs. Note that all direct radiation doses presented in this report during QI, Q2 and Q3 reflect this over-response. Quarter 4 reflects the type of actual gamma direct radiation levels that are observed at Zion.

4. Batch Releases:

a. Liquid:

1. There were 31 liquid batch releases in 2016

2. Total time period for batch releases: 4.26E+04 min.

3. Maximum time period for a batch release: 6.67E+03 min.

4. Average time period for batch release: l.37E+03 min.

5. Minimum time period for a batch release: 5.90E+Ol min.

b. Gaseous

1. There were 28 gaseous batch releases in 2016

2. Total time period for batch releases: l.10E+05 min.

3. Maximum time period for a batch release: l.16E+04 min.

4. Average time period for batch release: 3.94E+03 min.

5. Minimum time period for a batch release: 3.00E+02 min.

5. Abnormal Releases:

a. Liquid: There were no liquid abnormal releases in 2016.

b. Gaseous: There were no gaseous abnormal releases in 2016.

6. Gaseous and Liquid Waste Treatment Systems and Process Control Program Zion Station ODCM Section 12.6.4 requires major changes to the Gaseous and Liquid Waste Treatment Systems to be reported in the Annual Radioactive Effluent Release Report. There were changes to the Liquid Waste Treatment System, these changes and their technical basis are described in Section 7.

Zion Station ODCM Section 12.7.2 requires major changes to the Process Control Program (PCP) to be submitted in the Annual Radioactive Effluent Release Report. The Waste Gas Hold-up System was permanently vented. In Zion's defueled configuration this system is no longer applicable. In Zion's defueled configuration, the charcoal iodine removal system is no longer applicable. Due to radioactive decay and no means of production, radioactive iodine is not a concern at Zion.

7. Limiting Conditions of Operation (LC Os)

Zion Station ODCM Section 12.7.2 requires explanation as to why the inoperability of liquid or gaseous mo.nitoring instrumentation was not corrected within the time specified in the ODCM to be submitted with the Annual Radioactive Effluent Release Report. There were no radiation monitors Out of Service for greater than 30 days.

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 5 of56

8. Liquid Holdup Tanks and Gas Storage Tanks Zion Station ODCM Section 12.7.2 requires a description of events leading to liquid holdup tanks or gas storage tanks exceeding technical specification limits to be included in the Annual Radioactive Effluent Release Report.

Liquid Holdup Tanks and Gas Storage Tanks have been demolished and removed as radioactive waste shipment. No tank that could be defined as having the purpose of the liquid holdup tanks exceeded the limits of Permanently Defueled Technical Specifications 5.6.3 during 2016.

9. Offsite Dose Calculation Manual (ODCM)

Changes to the ODCM and Process Control Program are required by Zion Station Quality Assurance Project Plan Section 5.6.1. and ODCM Section 12.6.3 to be submitted as part of, or concurrent with, the Annual Radioactive Effluent Release Report.

a. ODCM Revisions: There were several changes to the ODCM. The changes reflect the changes to the relocation of the liquid effluent treatment and monitoring system, and the determination that the Unit 1 and Unit 2 vent stacks are no longer required. Changes made during 2016 are listed in Attachment 9.

b. Process Control Program(PCP): There were no major changes to the PCP in 2016.

10. Switchyard Area The switchyard is an onsite area that is monitored for direct radiation dose. Access to the site is controlled by Commonwealth Edison and is not accessible to members of the general public. The dose limits for this area are regulated differently than the general offsite dose areas and comply with 10CFR20 annual dose limit of 1OOmrem/year. ES&H TSD 13-009 lists the evaluation performed to determine habits of the real individual working in the switchyard and are calculated to be occupied no more than 2088 hours/year.

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 6 of56 Section 2.1 - Unit 1 Gaseous Releases GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit 1 Vent Stack - GROUND RELEASES REPORT FOR 2016 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases

1. Total Release Ci <LLD <LLD <LLD <LLD <LLD 2 . Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD Iodine-131

1. Total Release Ci <LLD <LLD <LLD <LLD <LLD 2 . Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD Particulates Half Life >= 8 days

*1. Total Release         Ci        6.39E-06       1.82E-05      7.03E-06 9.28E-07 3.25E-05

2. Avg. Release Rate uCi/sec 8.22E-07 2.31E-06 8.84E-07 1.17E-07 1.03E-06 Tritium

1. Total Release Ci <LLD <LLD <LLD <LLD <LLD

2. Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD Gross Alpha Radioactivity

1. Total Release Ci <LLD <LLD <LLD <LLD <LLD

2. Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE REPORT FOR 2016 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation <LLD <LLD <LLD <LLD <LLD Gases Iodines <LLD <LLD <LLD <LLD <LLD

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 7of56 Section 2.1 - Unit 1 Gaseous Releases (cont.) Particulates Half Life >= 8 days C0-60 Ci 2.06E-06 7.86E-06 3.30E-06 O.OOE+OO 1.32E-05 CS-137 Ci 4.21E-06 1.03E-05 3.73E-06 O.OOE+OO 1.83E-05 NI-63 Ci 3.51E-09 O.OOE+OO O.OOE+OO O.OOE+OO 3.51E-09 Totals for Period ... Ci 6.27E-06 1.82E-05 7.03E-06 O.OOE+OO 3.15E-05 Tritium <LLD <LLD <LLD <LLD <LLD Gross Alpha Radioactivity <LLD <LLD <LLD <LLD <LLD LLD values are listed on Section 2.5 Total Error values are listed on Section 2.6

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 8 of56 Section 2.2 - Unit 2 Gaseous Releases GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit 2 Vent Stack - GROUND RELEASES REPORT FOR 2016 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases

1. Total Release Ci <LLD <LLD <LLD <LLD <LLD

2. Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD Iodine-131

1. Total Release Ci <LLD <LLD <LLD <LLD <LLD

2. Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD Particulates Half Life >= 8 days

1. Total Release Ci 4.03E-04 1.14E-05 5.48E-06 <LLD 4.20E-04 2 . Avg. Release Rate uCi/sec 5.18E-05 1.44E-06 6.90E-07 <LLD 1.33E-05 Tritium

1. Total Release Ci <LLD <LLD <LLD <LLD <LLD

2. Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD Gross Alpha Radioactivity

1. Total Release Ci <LLD <LLD <LLD <LLD <LLD

2. Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE REPORT FOR 2016 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation <LLD <LLD <LLD <LLD <LLD Gases Iodines <LLD <LLD <LLD <LLD <LLD

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 9 of56 Section 2.2- Unit 2 Gaseous Releases (cont.) Particulates Half Life >= 8 days C0-60 Ci 2.37E-04 6.26E-06 1.67E-06 <LLD 2.45E-04 CS-137 Ci 1. 66E-04 5.09E-06 3.SlE-06 <LLD 1. 75E-04 Totals for Period ... Ci 4.03E-04 1.14E-05 5.48E-06 <LLD 4.20E-04 Tritium <LLD <LLD <LLD <LLD <LLD Gross Alpha Radioactivity <LLD <LLD <LLD <LLD <LLD LLD values are listed on Section 2.5 Total Error values are listed on Section 2.6 GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE REPORT FOR 2016 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation <LLD <LLD <LLD <LLD <LLD Gases Iodines <LLD <LLD <LLD <LLD <LLD Particulates Half Life >= 8 days C0-60 Ci 7.54E-08 <LLD <LLD 1. 33E-07 2.09E-07 CS-137 Ci 1.20E-08 <LLD <LLD 7.95E-07 8.07E-07 SB-125 Ci 3.68E-08 <LLD <LLD <LLD 3.68E-08 Totals for Period ... Ci 1.24E-07 <LLD <LLD 9.28E-07 1.05E-06 Tritium <LLD <LLD <LLD <LLD <LLD Gross Alpha Radioactivity <LLD <LLD <LLD <LLD <LLD LLD values are listed on Section 2.5 Total Error .values are listed on Section 2.6

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 10of56 Section 2.3 - Liquid Effluent Releases LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (Unit 1 & Unit 2 combined) REPORT FOR 2016 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases C-14 Ci 3.64E-04 O.OOE+OO 2.61E-05 2.44E-06 3.92E-04 C0-60 Ci 8 .11E-04 O.OOE+OO l.99E-04 1. 86E-05 l.03E-03 CS-137 Ci l.82E-04 O.OOE+OO 2.26E-04 1. 40E-04 5.48E-04 FE-55 Ci l.12E-04 O.OOE+OO O.OOE+OO O.OOE+OO l.12E-04 NI-59 Ci 1. lOE-04 O.OOE+OO O.OOE+OO O.OOE+OO 1. lOE-04 NI-63 Ci 9.16E-03 O.OOE+OO 2.53E-04 2.36E-05 9.43E-03 PU-241 Ci 9.0BE-06 O.OOE+OO O.OOE+OO O.OOE+OO 9.0BE-06 SR-90 Ci 4.47E-06 O.OOE+OO 1. 56E-05 1.46E-06 2.15E-05 Totals for Period ... Ci l.07E-02 O.OOE+OO 7.19E-04 1. 86E-04 l.17E-02 Tritium H-3 Ci 6.52E-02 O.OOE+OO 9.31E-02 6.63E-03 l.65E-01 Totals for Period... Ci 6.52E-02 O.OOE+OO 9.31E-02 6.63E-03 l.65E-01 Dissolved and Entrained Gases

1. Total Release Ci <LLD <LLD <LLD <LLD <LLD Gross Alpha Radioactivity ALPHA Ci 4.86E-06 O.OOE+OO 8.27E-06 O.OOE+OO 1. 31E-05 Totals for Period ... Ci 4.86E-06 O.OOE+OO 8.27E-06 O.OOE+OO l.31E-05 Volume of liquid waste liters 7.38E+06 4.07E+05 6.55E+05 2.45E+05 8.69E+06 Permit dilution vol ltr 1. 26E+09 O.OOE+OO 1. 28E+08 2.23E+07 l.41E+09 LLD values are listed on Section 2.5 Total Error values are listed on Section 2.6

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 11 of56 Section 2.3 -Liquid Effluent Releases (cont.) LIQUID EFFLUENTS - CONTINUOUS MODE (Unit 1 & Unit 2 combined) REPORT FOR 2016 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products <LLD <LLD <LLD <LLD <LLD Tritium <LLD <LLD <LLD <LLD <LLD Dissolved and Entrained Gases <LLD <LLD <LLD <LLD <LLD Gross Alpha Radioactivity <LLD <LLD <LLD <LLD <LLD LLD values are listed on Section 2.5 Total Error values are listed on Section 2.6 LIQUID EFFLUENTS - BATCH MODE (Unit 1 & Unit 2 combined) REPORT FOR 2016 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products C-14 Ci 3.64E-04 N/A 2.61E-05 2.44E-06 3.92E-04 C0-60 Ci 8.llE-04 N/A 1. 99E-04 1.86E-05 1.03E-03 CS-137 Ci 1. 82E-04 N/A 2.26E-04 -i. 40E-04 5.48E-04 FE-55 Ci 1.12E-04 N/A <LLD <LLD 1.12E-04 NI-59 Ci 1. lOE-04 N/A <LLD <LLD 1.lOE-04 NI-63 Ci 9.16E-03 N/A 2.53E-04 2.36E-05 9.43E-03 PU-241 Ci 9.0SE-06 N/A <LLD <LLD 9.0SE-06 SR-90 Ci 4.47E-06 N/A 1.56E-05 1. 4 6E-06 2.15E-05 Totals for Period ... Ci 1.07E-02 N/A 7.19E-04 1.86E-04 1.17E-02 Tritium H-3 Ci 6.52E-02 N/A 9.31E-02 6.63E-03 1.65E-01 Totals for Period ... Ci 6.52E-02 N/A 9.31E-02 6.63E-03 1.65E-01

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 12of56 Section 2.3 - Liquid Effluent Releases (cont.) Dissolved and Entrained Gases <LLD N/A <LLD <LLD <LLD Gross Alpha Radioactivity ALPHA Ci 4.86E-06 N/A 8.27E-06 <LLD 1. 31E-05 Totals for Period ... Ci 4.86E-06 N/A 8.27E-06 <LLD 1.31E-05 LLD values are listed on Section 2.5 Total Error values are listed on Section 2.6

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 13 of56 Section 2.3 -Liquid Effluent Releases (cont.) SUPPLEMENTAL INFORMATION LIQUID EFFLUENTS - BATCH MODE REPORT FOR 2016 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Number of releases 14 0 12 5 31 Total release time minutes 3.32E+04 O.OOE+OO 8.76E+03 5.83E+02 4.26E+04 Maximum release time minutes 3.32E+03 O.OOE+OO 6.67E+03 1.59E+02 6.67E+03 Average release time minutes 2.37E+03 O.OOE+OO 7.30E+02 1.17E+02 1.37E+03 Minimum release time minutes 2.40E+02 O.OOE+OO 1.12E+02 5.90E+Ol 5.90E+Ol Permit dilution vol ltr 1.26E+09 O.OOE+OO 1.28E+08 2.23E+07 1. 41E+09 Permit dilution flow gpm 1.00E+04 O.OOE+OO 3.85E+03 1.01E+04 8.74E+03 Permit max total diluted concentration (no H-3) uCi/ml 3.23E-08 O.OOE+OO 3.59E-08 2.41E-08 3.59E-08 Period dilution vol ltr 4.96E+09 4.96E+09 5.01E+09 5.01E+09 2.00E+lO Period dilution flow gpm 1.00E+04 1.00E+04 1.00E+04 1.00E+04 1.00E+04

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 14of56 Section 2.4 - Direct Radiation Maximally exposed sector: J (25mrem/year limit) Unit Qtr 1 (mrem) Qtr2 (mrem) Qtr 3 (mrem) Qtr4 (mrem) 2016 (mrem) Unit 1 l.93E+OO l.20E+OO 6.33E-01 7.33E-01 4.50E+OO Unit2 l.93E+OO l.20E+OO 6.33E-01 7.33E-01 4.50E+OO ISFSI - gamma l.93E+OO l.20E+OO 6.33E-01 7.33E-01 4.50E+OO ISFSI - neutron 6.00E-01 3.00E-01 3.00E-01 2.00E-01 l.40E+OO Sum: 6.40E+OO 3.90E+o0 2.20E+o0 2.40E+OO 1.49E+Ol Maximally exposed switchyard: Switchyard South (lOOmrem/year limit) Switchyard Qtr 1 (mrem) Qtr2 (mrem) Qtr 3 (mrem) Qtr4 (mrem) 2016 (mrem) Gamma 2.44E+ol 2.97E+Ol 2.47E+Ol l.16E+Ol 9.04E+Ol Neutron 2.40E+o0 2.40E+OO 3.40E+OO l.20E+OO 9.40E+OO Sum 2.68E+Ol 3.21E+Ol 2.81E+Ol l.28E+Ol 9.98E+Ol

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 15 of 56 Section 2.5 - LLD's Various detectors were used on different counting platforms for the gaseous and liquid weekly effluent samples. The lower limit of detection(LLD) accompanies each counted sample and is verified to meet the following maximum LLD's: A. Liquid Lower Limit of Detection Sample frequency Type of analysis (LLD) uCi/mL Weekly/prior to each release Principal Gamma Emitters: <5.00E-07 Dissolved and Entrained <l.OOE-05 Gases Monthly composite Tritium <1.00E-05 Gross Alpha <1.00E-07 Quarterly composite Sr-90 5.00E-08 Fe-55, Ni-63 l.OOE-06 B. Gaseous Lower Limit of Detection Sample frequency Type of analysis (LLD) uCi/mL Continuous/daily/weekly Principle gamma emitters <l.OOE-11 Continuous Noble gas <l.OOE-06 Monthly Noble Gas I Principle gamma <l.OOE-04 emitters Tritium 1.00E-06 Quarterly composite Sr-90 <l.OOE-11 Fe-55 <3.00E-11 Ni-63 <l.OOE-11 Gross Alpha <l.OOE-11

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 16of56 Section 2.6 - Error Estimation Estimates of Total Error The following is a calculated estimate of the maximum potential total error associated with reported values in the Annual Radioactive Effluent Release Report. The Total error is determined by calculating the square root of the sum of the squares of the individual errors.

a. Gaseous Effluents Sampling Error .................................................................... 5%

Calibration Error ................................................................. 10% Counting Statistics Error ..................................................... 17% Sample Volume Error ......................................................... 10% Total Error ........................................................................... 23%

b. Liquid Effluents Sampling Error ............................................................................. 5%

Calibration Error .......................................................................... 10% Counting Statistics Error .............................................................. 16% Sample Volume Error ....................................................... :.......... 2% Total Error .................................................................................... 20%

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 17of56 Section 3.0 - Solid Waste and Irradiated Fuel shipments A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)

1. Types of Waste Total Total Est. Total Types of Waste Period Quantity (m3) Activity (Ci) Error%

a. Spent Resins, filter sludges,

                                               *2.91E+Ol       3.12E+OO       2016   2.50E+Ol evaporator bottoms

b. Dry compressible waste, l.37E+04 4.52E+02 2016 2.50E+Ol contaminated equipment

c. Irradiated components, control 2.05E+02 5.48E+Ol 2016 2.50E+Ol rods, etc.

d. Other (describe) O.OOE+oO O.OOE+OO 2016 2.50E+Ol

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 18 of 56 Section 3.0 - Solid Waste and Irradiated Fuel shipments (cont.)

2. Estimate of major nuclide composition (by waste type)

Waste Type a. Waste Type b. DAW Waste Typed. Major Nuclide Waste Typed. Resins, sludges contaminated Irradiated Composition Other% bottoms(%) equipment (%) components (%) Ag-108m O.OOE+oO 4.70E-04 O.OOE+OO 0.00 Ag-llOm O.OOE+oO O.OOE+oO O.OOE+OO 0.00 Am-241 1.33E-02 l.82E-02 6.18E-03 0.00 C-14 7.29E-02 8.13E-03 1.49E-04 0.00 C-14AM 4.68E-03 2.23E-03 7.50E-02 0.00 Ce-144 4.68E-03 2.23E-03 7.50E-02 0.00 Cm-242 l.71E-04 l.67E-05 4.61E-02 0.00 Cm-243 l.86E-03 5.18E-03 3.76E-05 0.00 Cm-244 O.OOE+OO O.OOE+OO 2.72E-03 0.00 Co-60 O.OOE+OO 3.27E-03 2.62E-03 0.00 Cs-134 6.80E+ol 2.53E+Ol 4.15E+Ol 0.00 Cs-137 O.OOE+oO O.OOE+OO 2.94E-05 0.00 Fe-55 5.00E+oO l.48E+o0 1.15E+OO 0.00 H-3 O.OOE+OO O.OOE+oO O.OOE+oO 0.00 I-129 O.OOE+OO O.OOE+oO O.OOE+OO 0.00 Mn-54 3.34E+OO l.03E+OO l.73E+Ol 0.00 Nb-94 l.43E-01 6.lIE-03 7.lOE-01 0.00 Ni-59 2.96E-02 1.58E-04 7.l 7E-03 0.00 Ni-63 O.OOE+oO l.04E-02 l.56E-02 0.00 Ni-63am l.27E-01 8.73E-03 O.OOE+OO 0.00 Np-237 O.OOE+OO O.OOE+oO 3.64E-02 0.00 Pu-238 2.21E-01 9.81E-01 2.81E-03 0.00 Pu-239 O.OOE+OO O.OOE+OO 4.62E-01 0.00 Pu-240 2.23E+ol 7.IOE+Ol 2.95E-01 0.00 Pu-241 O.OOE+OO O.OOE+OO 3.82E+Ol 0.00 Pu-242 O.OOE+oO O.OOE+OO O.OOE+OO 0.00 Ra-226 9.80E-03 5.17E-03 3.04E-03 0.00 Sb-125 l.97E-03 2.49E-03 8.38E-04 0.00 Sr-89 O.OOE+OO l.72E-03 8.38E-04 0.00 Sr-90 2.89E-01 6.81E-02 4.41E-02 0.00 Tc-99 5.76E-05 l.03E-05 1.1 IE-04 0.00 EU-152 O.OOE+OO 2.18E-03 l.24E-Q3 0.00 EU-154 2.20E-02 4.16E-02 4.47E-02 0.00 U-235 l.09E-02 l.33E-03 7.05E-04 0.00 U-236 l.80E-01 1.97E-02 2.22E-02 0.00 U-237 2.04E-01 l.63E-02 5.62E-02 0.00 U-238 O.OOE+oO O.OOE+OO O.OOE+OO 0.00 Zn-65 O.OOE+OO O.OOE+OO O.OOE+OO 0.00

• Ni-63AM - activated metal

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 19of56 Section 3.0 - Solid Waste and Irradiated Fuel shipments (cont.)

3. Solid Waste Disposition Number of shipments Mode of Transportation Destination 5 Truck Clive CWF 0 Rail Clive CWF 3 Truck CliveBWF 183 Rail CliveBWF B. Irradiated Fuel Shipments (disposition)

Number of shipments Mode of Transportation Destination 0 C. Changes to the Process Control Program: None

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 20of56 Section 4.1 - 40 CFR 190 & 10 CFR 72 Compliance Summary UNIT 1, 2 & ISFSI (DOCKET Numbers 50-295, 50-304 & 72-1037) EXECUTIVE

SUMMARY

A review of 2016 effluent data indicates that the activity released from the station was far below any regulatory limit. There was no noble gas releas ed in 2016. This trend can be attributed to the shutdown of both units since late September 1997. Airborne Dose to Maximally Exposed Receptor Dose to Maximally Exposed from Unit 1 Receptor from Unit 2 Gamma Air O.OOE+OO mrad O.OOE+OO mrad Beta Air O.OOE+OO mrad O.OOE+OO mrad Total Body 1.48E-02 mrem 1.48E-02 mrem Skin O.OOE+OO mrem O.OOE+OO mrem Organ 5 .1 OE-02 mrem (Infant Liver) 5.lOE-02 mrem (Infant Liver) AquatIC Dose to Maximally Exposed Re ceptor Dose to Maximally Exposed (Any) from Unit 1 Receptor (Any) from Unit 2 Total Body 4.37E-03 mrem 4.3 7E-03 mrem Organ 1.55E-02 mrem(Child Bone) 1.55E-02 mrem(Child Bone) Direct Radiation Dose to Maximally Dos e to Maximally Dose to Maximally Exposed Member of the Exp osed Member of the Exposed Member public from Unit 1 public from Unit 2 of the public from I SF SI Total Body 4.50E+OOmrem (Sec J) 4.50E+OOmrem (Sec J) 5.90E+OOmrem (Sec J) Switchyard Direct Radiation (10CFR20 limit lOOmrem/year) Switchyard Qtr 1 (mrem) Qtr 2 (mrem) Qtr 3 (mrem) Qtr 4 (mrem) 2016 (mrem) Gamma 2.44E+Ol 2.97E+Ol 2.47E+Ol l.16E+Ol 9.04E+Ol Neutron 2.40E+OO 2.40E+OO 3.40E+OO 1.20E+OO 9.40E+OO Sum 2.68E+Ol 3.21E+Ol 2.82E+Ol l.28E+Ol 9.98E+Ol

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 21of56 Section 4.2 - Unit 1 I. Unit 1 (Docket Number 50-295) A. 10 CPR 20 & 40 CPR 190 Compliance Assessment: The demonstration of compliance with 40 CPR 190 will be used to demonstrate compliance with 10 CPR 20.

1. Total Effective Dose Equivalent 4.52E+OO mrem/year

2. 40 CPR 190 Whole body limit 25 mrem/year

3. 40 CPR 190 Max exposed organ 25 mrem (75 mrem thyroid)

4. % Whole body limit 1.81E+01%

5. % Max exposed organ 1.83E+Ol % child bone Qtr 1 mrem Qtr2 mrem Qtr3 mrem Qtr4mrem 2016 mrem TBody l.94E+OO 1.20E+OO 6.35E-01 7.34E-01 4.52E+o0 Adult Thody Child Thody AdultTbody Adult Tbody Adult Thody Organ l.99E+OO 1.20E+OO 6.38E~Ol 7.35E-01 4.56E+OO Child Bone Child Bone Child Bone Child Bone Child Bone B. Maximally Exposed Receptor:

1. Airborne Yearly limit Total Dose  % of Yearly Qtr Obj 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr 10 CFR50 2016 limit App. I Gamma 5.0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 10.0 O.OOE+OO O.OOE+OO air (mrad)

Beta Air 10.0 O.OOE+OO O.OOE+oO O.OOE+OO O.OOE+OO 20.0 O.OOE+oO O.OOE+OO (mrad) Total Body 7.5 1.33E-02 l.03E-03 4.58E-04 3.95E-05 15.0 1.48E-02 9.86E-02 (mrem) Skin 7.5 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 15.0 O.OOE+OO O.OOE+oO (mrem) Organ 7.5 4.52E-02 3.92E-03 l.88E-03 l.89E-04 15.0 5.lOE-02 3.40E-01 (mrem) Critical Infant liver Infant liver Infant liver Infant liver Infant liver Infant liver Organ

2. Aquatic Yearly Total %of Qtr 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr limit Dose Yearly Obj 10CFR 50 2016 limit Aoo.I Total Body 2.5 l.60E-03 O.OOE+OO l.71E-03 l.06E-03 3.0 4.37E-03 1.46E-01 (mrem)

Organ (mrem) 2.5 l.OSE-02 O.OOE+OO 3.02E-03 l.68E-03 10.0 l.55E-02 l.55E-01 Child Child Child Teen Child Child Critical Organ bone bone bone liver bone bone

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 22of56 Section 4.2 - Unit 1 (cont.)

3. Direct (gamma) Maximally Exposed Sector: J Qtr 2nd Qtr 3rd Qtr Yearly limit Total Dose % ofYearly 1*1 Qtr 4th Qtr Obj 40CFR190 2016 limit Total 6.2 body l.93E+OO l.20E+OO 6 .33E-01 7.33E-01 25.0 4.50E+OO 1.80E+Ol 5

(mrem)

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 23of56 Section 4.3 - Unit 2 I. Unit 2 (Docket Number 50-304) A. 10 CFR 20 & 40 CFR 190 Compliance Assessment: The demonstration of compliance with 40 CFR 190 will be' used to demonstrate compliance with 1b CFR 20.

1. Total Effective Dose Equivalent 4.52E+OO mrem/year

2. 40 CFR 190 Whole body limit 25 mrem/year

3. 40 CFR 190 Max exposed organ 25 mrem (75 mrem thyroid)

4. % Whole body limit l.81E+Ol%

5. % Max exposed organ 1.83E+Ol % child bone Qtr 1 mrem Qtr 2nirem Qtr 3 mrem Qtr4mrem 2016 mrem TBody l.94E+OO l.20E+OO 6.35E-01 7.34E-01 4.52E+o0 AdultTbody Child Thody Adult Thody AdultTbody Adult Thody Organ l.99E+o0 l.20E+o0 6.38E-01 7.35E-01 4.56E+OO Child Bone Child Bone Child Bone Child Bone Child Bone B. Maximally Exposed Receptor:

Airborne Yearly Total Qtr limit  % of Yearly 1st Qtr 2ndQtr 3rd Qtr 4th Qtr Dose Obj 10CFR limit 2016 50 App. I Gamma air 5.0 O.OOE+oO O.OOE+OO O.OOE+oO O.OOE+OO 10.0 O.OOE+OO O.OOE+OO (mrad) Beta Air 10. O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 20.0 O.OOE+OO O.OOE+OO (mrad) 0 Total Body 7.5 1.33E-02 1.03E-03 4.58E-04 3.95E-05 15.0 l.48E-02 9.86E-02 (mrem) Skin (mrem) 7.5 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 15.0 O.OOE+OO O.OOE+OO Organ 7.5 4.52E-02 3.92E-03 1.88E-03 l.89E-04 15.0 5.IOE-02 3.40E-01 (mrem) Critical Infant Infant Infant Infant Infant Infant liver Organ liver liver liver liver liver Aquatic Yearly limit Qtr Total  % ofYearly 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr 10CFR Obj Dose 2016 limit 50 Aoo.I Total Body 2.5 1.60E-03 O.OOE+oO l.71E-03 1.06E-03 3.0 4.37E-03 l.46E-01 (mrem) Organ 2.5 l.08E-02 O.OOE+oO 3.02E-03 1.68E-03 10.0 1.55E-02 l.55E-01 (mrem) Critical Child Child Child Child bone Teen liver Child bone Organ bone bone bone

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 24of56 Section 4.3 - Unit 2 (cont.) Direct (gamma) Maximally Exposed Sector: J Qtr 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Yearly Total  % ofYearly Obj limit Dose 2016 limit

                                                               . 40CFR 190 Total body   6.2 l.93E+O     l.20E+O   6.33E-01  7.33E-01        25.0  4.50E+OO   l.80E+Ol (mrem)      5      0           0

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 25of56 Section 4.4 - ISFSI I. ISFSI (Docket Number 72-103 7) A. 10 CFR 72 & 40 CFR 190 Compliance Assessment:

1. Total Effective Dose Equivalent 5.90+00 mrem/year

2. 40 CFR190 I 10CFR72 Whole body limit 25 mrem/year

3. 40 CFR190 I 10CFR72 Max exposed organ 25 mrem (75 mrem thyroid)

4.  % Whole body limit 2.36E+Ol %

5.  % Max exposed organ (child bone/thyroid) 2.36E+Ol % I 7.87E+OO%

Qtr 1 mrem Qtr2mrem Qtr 3 mrem Qtr4mrem 20 16 mrem TEDE 2.53E+OO 1.23E+o0 9.33E-Ol 9.33E-01 5. 90E+OO TODE 2.53E+OO l.23E+OO 9.33E-01 9.33E-01 5. 90E+OO B. Maximally Exposed Receptor Sector: J

1. Direct (gamma + neutron)

Yearly limit Qtr 2nd Qtr 3rd Qtr 41h Qtr Tota! Dose % of Yearly 151 Qtr 40CFR190/ Obj 2016 limit 10CFR72.104 Total body 6.25 2.53E+OO 1.23E+OO 9.33E-01 9.33E-01 25.0 5.90E+OO 2.36E+ol (mrem)

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 26 of56 Section 4.5 -Combined 40 CFR 190 Report 40 CFR 190 URANIUM FUEL CYCLE DOSE REPORT LIQUID ANNUAL DOSE

SUMMARY

Year . . . . . . . . . . . . . . . . . . : 2016 From Unit . . . . . . . . . . . . .  : 1 To Unit . . . . . . . . . . . . . . .  : 2 Liquid Receptor .......  : 0 Liquid Receptor --- MAXIMUM PERIOD DOSE TO LIMIT (Any Organ) =================================== Dose Age Dose Limit Admin Admin g..0 T.Spec T.Spec g..0 Period Group Organ (mrem) Period Limit of Limit Limit of Limit Quarter 1 CHILD BONE 2.16E-02 Quarter 2.50E+OO 8.66E-01 2.50E+OO 8.66E-01 Quarter 2 ADULT BONE O.OOE+OO Quarter 2.50E+OO O.OOE+OO 2.50E+OO O.OOE+OO Quarter 3 CHILD BONE 6.04E-03 Quarter 2.50E+OO 2.42E-01 2.50E+OO 2.42E-01 Quarter 4 TEEN LIVER 3.36E-03 Quarter 2.50E+OO 1. 34E-01 2.50E+00 1.34E-01 Annual CHILD BONE 3.lOE-02 Annual 5.00E+OO 6.19E-01 5.00E+OO 6.19E-01 --- MAXIMUM PERIOD DOSE TO LIMIT (Tot Body)) =================================== Dose Age Dose Limit Admin Admin g..0 T.Spec T.Spec g..0 Period Group Organ (mrem) Period Limit of Limit Limit of Limit Quarter 1 ADULT TBODY 3.19E-03 Quarter 1.50E+00 2.13E-01 1.50E+00 2.13E-01 Quarter 2 ADULT TBODY O.OOE+OO Quarter 1.50E+OO O.OOE+OO 1.50E+OO O.OOE+OO Quarter 3 ADULT TBODY 3.42E-03 Quarter 1.50E+OO 2.28E-01 1.50E+OO 2.28E-01 Quarter 4 ADULT TBODY 2.12E-03 Quarter 1.50E+OO 1.41E-01 1.50E+OO 1.41E-01 Annual ADULT TBODY 8.73E-03 Annual 3.00E+OO 2.91E-01 3.00E+OO 2.91E-01

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 27 of56 Section 4.5-Combined 40 CFR 190 Report (cont.) 40 CFR 190 URANIUM FUEL CYCLE DOSE REPORT GAS ANNUAL DOSE

SUMMARY

Year . . . . . . . . . . . . . . . . . . : 2016 From Unit . . . . . . . . . . . . .  : 1 To Unit . . . . . . . . . . . . . . .  : 2 Coefficient Type ......  : Historical Gas Receptor . . . . . . . . . .  : 5 Composite Crit. Receptor - IP Distance (meters) .....  : 0.00 Compass Point . . . . . . . . .  : NA --- MAXIMUM PERIOD DOSE TO LIMIT (Any Organ) =================================== Dose Age Dose Limit Admin Admin g.0 T.Spec T.Spec g.0 Period Group Organ (mrem) Period Limit of Limit Limit of Limit Quarter 1 INFANT LIVER 9.03E-02 Quarter 5.63E+OO 1.61E+OO 7.50E+OO 1. 20E+00 Quarter 2 INFANT LIVER 7.84E-03 Quarter 5.63E+OO 1.39E-01 7.50E+00 1.0SE-01 Quarter 3 INFANT LIVER 3.75E-03 Quarter 5.63E+OO 6.67E-02 7.50E+OO 5.00E-02 Quarter 4 INFANT LIVER 3.78E-04 Quarter 5.63E+OO 6.72E-03 7.50E+OO 5.04E-03 Annual INFANT LIVER 1.02E-01 Annual 1.13E+Ol 9.09E-01 1.50E+Ol 6.82E-01 --- MAXIMUM PERIOD DOSE TO LIMIT (Tot Body)) =================================== Dose Age Dose Limit Adm in Admin g.0 T.Spec T.Spec g.0 Period Group Organ (mrem) Period Limit of Limit Limit of Limit Quarter 1 ADULT TBODY 2.65E-02 Quarter 5.25E+OO 5.04E-01 7.50E+OO 3.53E-01 Quarter 2 ADULT TBODY 2.0SE-03 Quarter 5.25E+OO 3.91E-02 7.50E+OO 2.74E-02 Quarter 3 ADULT TBODY 9.16E-04 Quarter 5.25E+OO 1.75E-02 7.50E+OO 1.22E-02 Quarter 4 ADULT TBODY 7.89E-05 Quarter 5.25E+OO 1. SOE-03 7.50E+OO 1.0SE-03 Annual ADULT TBODY 2.95E-02 Annual 1.05E+Ol 2.BlE-01 1.50E+Ol 1.97E-01

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 28 of56 Section 4.5 -Combined 40 CFR 190 Report (cont.) 40 CFR 190 URANIUM FUEL CYCLE DOSE REPORT COMBINED MAXIMUM ANNUAL DOSE

SUMMARY

Year . . . . . . . . . . . . . . . . . . : 2016 From Unit . . . . . . . . . . . . .  : 1 To Unit . . . . . . . . . . . . . . .  : 2 Liquid Receptor .......  : 0 Liquid Receptor Coefficient Type ......  : Historical Gas Receptor . . . . . . . . . .  : 5 Composite Crit. Receptor - IP Distance (meters) .....  : 0.00 Compass Point . . . . . . . . .  : NA --- MAXIMUM PERIOD DOSE TO LIMIT (Any Organ) =================================== Dose Age Dose Limit Percent Period Group Organ (mrem) Period Limit of Limit Quarter 1 INFANT LIVER 9.03E-02 Quarter 6.25E+OO 1. 45E+00 Quarter 2 INFANT LIVER 7.84E-03 Quarter 6.25E+OO 1. 25E-01 Quarter 3 CHILD BONE 8.61E-03 Quarter 6.25E+OO 1. 38E-01 Quarter 4 CHILD BONE 3.52E-03 Quarter 6.25E+OO 5.63E-02 Annual CHILD BONE 1.03E-01 Annual 2.50E+Ol 4.llE-01 --- MAXIMUM PERIOD DOSE TO LIMIT (Tot Body)) =================================== Dose Age Dose Limit Percent Period Group Organ (mrem) Period Limit of Limit Quarter 1 ADULT TBODY 2.96E-02 Quarter 6.25E+00 4.74E-01 Quarter 2 ADULT TBODY 2.05E-03 Quarter 6.25E+00 3.29E-02 Quarter 3 ADULT TBODY 4.34E-03 Quarter 6.25E+OO 6.95E-02 Quarter 4 ADULT TBODY 2.19E-03 Quarter 6.25E+00 3.51E-02 Annual ADULT TBODY 3.82E-02 Annual 2.50E+Ol 1. 53E-01

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 29of56 Section 5.0-Meteorology

1. Introduction The purpose of the meteorological program conducted at Zion Station site was to provide information sufficient to assess the local weather conditions and was used to determine the degree of atmospheric dispersion of airborne radioactive effluent from the station.

During the first quarter of2015, all fuel had been removed to the ISFSI location and continuous meteorological monitoring was no longer required. The previous 6 years of data from Jan. 1, 2009 to Dec. 31, 2014 was queried to generate the historic average wind rose and atmospheric dispersion parameters for future airborne effluents from Zion Station. The method of dose calculation that will be used going forward is ground level release and relevant information that is applicable to this method of effluent dose calculation has been included in this report. The meteorological tower that was used in calculation of these historical averages was 250 ft. in elevation and was instrumented at two levels. Wind speed and direction measured at 35 ft. and 250 ft. Ambient temperature was measured at 35 ft. Differential temperature, referenced to 35 ft. was measured at 250 ft. Dew point temperature was measured approximately ten feet from the tower at an elevation of 5 ft. Precipitation was measured by a rain gauge located on the roof of the meteorological shelter building. Joint frequency stability wind rose tables of wind direction, wind speed, and stability were routinely tabulated from hourly measurements during the six year period of this historical average. The six year historical average data tables are included in this report.

2. Summary Zion Station meteorological monitoring program produced 51,918 total hours valid for the instruments used in generating the historical average out of a possible 52596 total hours in the 6 year monitoring period from Jan. 1, 2009 to Dec. 31, 2014. (365.25 days X 6 years X 24 hours/day). 678 total hours of data were lost representing a 98.71 % data recovery rate.

The stability wind rose tables included in this report have been generated using the 3 5 ft. wind data with the 250-35 ft. differential temperature data.

3. Data Acquisition Information regarding Data Acquisition, Data Analysis and instruments used can be found in the meteorological monitoring sections of prior Zion Stations Annual Radioactive Environmental Monitoring Reports from 2009 to 2014.

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 30of56 Section 5.0 --'Meteorology (cont.) Table 1 - Wind Direction Classes Wind Direction Compass Direction the Wind is Coming From Class N 348.75° < WD :'.S 11.25° NNE 11.25° <WD:'.S 11.25° NE 33.75° <WD:::;. 33.75° ENE 56.25° < WD :'.S 56.25° E 78.75° <WD:'.S 78.75° ESE 101.25° <WD:'.S 101.25° SE 123.75° <WD:'.S 123.75° SSE 146.25° <WD:'.S 146.25° s 168.75° <WD:'.S 168.75° SSW 191.25° < WD :'.S 191.25° SW 213.75° <WD:'.S 213.75° WSW 236.25° ' <WD:'.S 236.25° w 258.75°  ; <WD :'.S 2~8.75° WNW 281:25° . <WD:'.S. 281.25° NW 303.75° <WD:'.S 303.75° NNW 326.25° <*WD :'.S 348.75° Table 2 - Wind Speed Classes

• Wind Speed Class Wind Speeds are* in miles per hour (mph) 1 0.0 i' <WS:'.S 0.7 2 0.7 <WS:'.S 3.5 3 3.5 :r::ws:s 7.5 4 7.5 <WS':'.S 12.5 5 12.5 <WS:'.S 18.5 6 18.5 <WS:'.S 24.5 7 24.5 <WS Table 3 - Atmospheric Stability Classes Class Differential Temperature . Differential Temperature Interval (in °C/l OOm)(l) Interval (in °F over the 250-35 ft. interval)(2)

A - Extremely Unstable 8T :'.S -1.9 8T:S-2.3 B - Moderately Unstable -1.9 < 8T :'.S -1.7 -2.3 < 8T :'.S -2.1 C - Slightly Unstable -1.7 < 8T :'.S -1.5 -2.1 < 8T :'.S -1.8 D-Neutral -1.5 < 8T :'.S -0.5 -1.8 < 8T :'.S -0.6 E - Slightly Stable -0.5 < 8T :'.S 1.5 -0.6 < 8T :'.S 1.7 F - Moderately Stable 1.5 <8T:S4.0 1.7<8T:S4.7 G - Extremely Stable 4.0 < 8T 4.7<8T (1) From ANSI/ANS 2.5 (2) ANSI/ANS 2.5 intervals scaled for instrument heights on the Zion meteorological tower.

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 31of56 Section 5.0-Meteorology (cont.)

4. The following two programs were used to calculate doses resulting from radioactive releases:

a. XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations (NUREG/CR-2919)

The program is based on the theory that material released to the atmosphere will be normally distributed (Gaussian) about the plume centerline. A straight-line trajectory is assumed between the point of release and all receptors. The program implements the assumptions outlined in Section C ofNRC Regulatory Guide 1.111. In evaluating routine releases from nuclear power plants, it primarily is designed to calculate annual relative effluent concentrations, X/Q values and annual average relative deposition, D/Q values. The historical average output from the XOQDOQ program from 2009-2014 was used to develop the input to the RETDAS program.

b. RETDAS: Radiological Effluent Tracking and Dose Assessment Software.

RETDAS is a program written for the evaluation of radiological impacts due to the release of radioactive material to the environment during normal operation of :reactors. The RETDAS code implements the radiological impact models ofNRC Regulatory Guide 1.109 Rev. 1, for atmospheric releases. The program is used to estimate the maximum individual doses at the maximally exposed location in the vicinity of the plant.

5. Detailed information regarding the meteorological maintenance and calibration information of the meteorological tower and instruments used during the historical average evaluation time period can be found in prior Zion Station Annual Radioactive Environmental Operating Reports from 2009 to 2014.

6. Stability Wind Rose Data The historical stability wind roses are given in Tables 4 through 8. For the year, winds measured at 35ft. most frequently came from the West (10.86%) and fell into the 3.6 to 7.5 mph wind speed class (34.94%). Calms (wind speeds at or below lmph were measured at 0.16% of the time and speeds greater than 24.5 mph were measured 0.09% of the time.

Stability based on the 250-35 ft. differential temperature most frequently fell into the neutral classification(39.58%)

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 32of56 Section 5. 0 - Meteorology (cont.) Table 4 Percent of time at each Wind Speed and Direction Period of Record: Jan. I, 2009 to Dec. 31, 2014 Stability Class: A - Extremely Unstable Elevation: Ground Level Release Wind Speed (mph) at I Om Level Wind

               24.5 Total:

Direction N 0 0 0.031 0.156 0.254 0.04 0.002 0.48 NNE 0 0 0.176 0.98 0.287 0.006 0 1.45 NE 0 0.002 0.391 0.559 0.075 0.004 0 1.03 ENE 0 0.002 0.368 0.22 0.019 0.002 0 0.61 E 0 0.004 0.412 0.133 0.023 0 0 0.57 ESE 0 0.002 0.379 0.141 0 0 0 0.52 SE 0 0 0.272 0.219 0.01 0 0 0.5 SSE 0 0 0.05 0.249 0.035 0 0 0.33 s 0 0 0.01 0.046 0.019 0 0 0.08 SSW 0 0.002 0.015 0.068 0.144 0.01 0 0.24 SW 0 0.002 0.041 0.319 0.331 0.015 0.006 0.71 WSW 0 0 0.133 0.516 0.366 0.021 0.004 1.04 w 0 0 0.12 0.577 0.401 0.01 0 1.11 WNW 0 0 0.089 0.492 0.187 0.002 0 0.77 NW 0 0.006 0.068 0.404 0.112 0 0 0.59 NNW 0 0 0.039 0.058 0.037 0 0 0.13 Total: 0 0.019 2.591 5.137 2.3 0.11 0.012 10.17

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 33 of56 Section 5.0 -Meteorology (cont.) Percent of time at each Wind Speed and Direction Period of Record: Jan. 1, 2009 to Dec. 31, 2014 Stability Class: B - Moderately Unstable Elevation: Ground Level Release Wind Speed (mph) at lOm Level Wind <l 1 - 3.5 3.6 - 7.5 7.6 - 12.5 12.6 - 18.5 18.6 - 24.5 >24.5 Total: Direction N 0 0 0.039 0.102 0.119 0.015 0 0.28 NNE 0 0 0.112 0.196 0.058 0.004 0.002 0.37 NE 0 0.012 0.108 0.052 0.014 0.004 0 0.19 ENE 0 0.012 0.068 0.029 0.014 0 0 0.12 E 0 0.004 0.077 0.025 0.002 0 0 0.11 ESE 0 0.008 0.066 0.045 0 0 0 0.12 SE 0 0 0.097 0.041 0 0 0 0.14 SSE 0 0 0.06 0.164 0.025 0 0 0.25 s 0 0 0.01 0.052 0.008 0.002 0 0.07 SSW 0 0 0.013 0.058 0.098 0.008 0.002 0.18 SW 0 0.002 0.033 0.149 0.158 0.013 0.002 0.36 WSW 0 0 0.062 0.193 0.089 0.012 0.002 0.36 w 0 0.002 0.068 0.211 0.129 0.004 0 0.41 WNW 0 0 0.06 0.179 0.081 0.004 0 0.32 NW 0 0.004 0.049 0.191 0.052 0 0 0.29 NNW 0 0.002 0.021 0.054 0.027 0.002 0 0.11 Total: 0 0.044 0.938 1.739 0.872 0.067 0.008 3.67

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 34of56 Section 5.0-Meteorology (cont.) Percent of time at each Wind Speed and Direction Period of Record: Jan. 1, 2009 to Dec. 31, 2014 Stability Class: C - Slightly Unstable Elevation: Ground Level Release Wind Speed (mph) at 1Om Level Wind <1 1 - 3.5 3.6 - 7.5 7.6 - 12.5 12.6 - 18.5 18.6 - 24.5 >24.5 Total: Direction N 0 0.004 0'.086 0.243 0.177 0.013 0.008 0.53 NNE 0 0.01 0.183 0.31 0.079 0.004 0 0.59 NE 0 0.023 0.15 0.102 0.031 0.01 0.006 0.32 ENE 0 0.023 0.1 0.044 0.021 0.012 0.002 0.2 E 0 0.01 0.146 0.025 0.018 0 0 0.2 ESE 0 0.019 0.115 0.037 0.014 0 0 0.18 SE 0 0.006 0.181 0.054 0.016 0 0 0.26 SSE 0 0.006 0.106 0.351 0.11 0.01 0 0.58 s 0 0.004 0.066 0.101 0.021 0 0 0.19 SSW 0 0.002 0.041 0.119 0.154 0.017 0.004 0.34 SW 0 0 0.094 0.244 0.189 0.023 0.006 0.56 WSW 0 0.004 0.11 0.252 0.139 0.01 0.002 0.52 w 0 0.008 0.133 0.277 0.165 0.008 0 0.59 WNW 0 0.008 0.127 0.308 0.079 0 0 0.52 NW 0 0.01 0.096 0.206 0.096 0 0 0.41 NNW 0 0.01 0.033 0.133 0.045 0.004 0 0.22 Total: 0 0.145 1.768 2.806 1.352 0.11 0.027 6.21

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 35of56 Section 5.0 -Meteorology (cont.) Percent of time at each Wind Speed and Direction Period of Record: Jan. 1, 2009 to Dec. 31, 2014 Stability Class: D - Neutral Elevation: Ground Level Release Wind Speed (mph) at 1Om Level Wind <1 1 - 3.5 3.6-7.5 7.6 - 12.5 12.6 - 18.5 18.6 - 24.5 >24.5 Total: Direction N 0 0.102 0.597 1.392 1.05 0.21 0.06 3.41 NNE 0 0.142 0.758 1.123 0.769 0.042 0.031 2.87 NE 0 0.161 0.528 0.57 0.405 0.046 0.025 1.74 ENE 0.001 0.137 0.348 0.346 0.347 0.092 0.008 1.28 E 0 0.121 0.392 0.303 0.353 0.094 0.013 1.28 ESE 0 0.148 0.489 0.289 0.163 0.035 0.002 1.13 SE 0 0.127 0.567 0.378 0.149 0.008 0 1.23 SSE 0 0.075 0.523 1.258 0.944 0.168 0.054 3.02 s 0 0.106 0.686 0.805 0.314 0.015 0 1.93 SSW 0 0.128 0.641 0.994 0.774 0.087 0.008 . 2.63 SW 0 0.152 0.612 1.443 1.003 0.108 0.015 3.33 WSW 0.001 0.138 0.849 1.327 0.659 0.042 0.002 3.02 w 0 0.146 1.1 1.766 0.961 0.029 0.002 4 WNW 0 0.169 1.139 1.402 0.52 0.012 0 3.24 NW 0 0.164 1 1.404 0.489 0.021 0 3.08 NNW 0 0.098 0.655 1.21 0.387 0.039 0.006 2.39 Total: 0.006 2.117 10.886 16.01 9.286 1.048 0.225 39.58

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 36of56 Section 5.0 -Meteorology (cont.) Percent of time at each Wind Speed and Direction Period of Record: Jan. 1, 2009 to Dec. 31, 2014 Stability Class: E - Slightly Stable Elevation: Ground Level Release Wind Speed (mph) at 1Om Level Wind <l 1 - 3.5 3.6-7.5 7.6 - 12.5 12.6 - 18.5 18.6 - 24.5 >24.5 Total: Direction N 0.005 0.302 0.672 0.53 0.173 0.021 0.012 1.72 NNE 0.004 0.245 0.564 0.447 0.058 0.013 0 1.33 NE 0.004 0.204 0.314 0.167 0.075 0.002 0 0.77 ENE 0.003 0.154 0.212 0.092 0.071 0.01 0 0.54 E 0.003 0.148 0.212 0.082 0.11 0.054 0.008 0.62 ESE 0.002 0.129 0.233 0.091 0.052 0.017 0 0.52 SE 0.003 0.163 0.456 0.273 0.079 0.004 0 0;98 SSE 0.004 0.192 0.452 0.84 -0.291 0.029 0.019 1.83 s 0.005 0.292 1.375 0.839 0.166 0.004 0 2.68 SSW 0.005 0.441 1.19 0.661 0.154 0.015 0 2.47 SW 0.006 0.324 0.855 0.607 0.183 0.013 0 1.99 WSW 0.004 0.277 1.008 0.503 0.069 0.002 0 1.86 w 0.005 0.353 1.349 0.649 0.117 0.006 0.002 2.48 WNW 0.005 0.38 1.136 0.599 0.05 0.002 0 2.17 NW 0.005 0.319 1.069 0.48 0.073 0 0 1.95 NNW 0.004 0.252 0.593 0.203 0.058 0 0 1.11 Total: 0.065 4.178 11.692 7.063 1.779 0.193 0.04 25.01

ZionSolutions LLC 'ZS-2017-0058: Attachment 1 Page 37of56 Section 5.0-Meteorology (cont.) Percent of time at each Wind Speed and Direction Period of Record: Jan. 1, 2009 to Dec. 31, 2014 Stability Class: F - Moderately Stable Elevation: Ground Level Release Wind Speed (mph) at 1Om Level Wind <1 1 - 3.5 3.6 - 7.5 7.6 - 12.5 12.6 - 18.5 18.6 - 24.5 >24.5 Total: Direction N 0.002 0.151 0.162 0.043 0 0 0 0.36 NNE 0.001 0.094 0.106 0.019 0 0 0 0.22 NE 0.001 0.083 0.086 0.025 0 0 0 0.2 ENE 0.001 0.076 0.064 0.024 0.014 0.002 0 0.18 E 0.001 0.079 0.077 0.027 0.01 0 0 0.19 ESE 0.001 0.077 0.111 0.045 0.016 0 0 0.25 SE 0.001 0.072 0.156 0.07 0.006 0 0 0.3 SSE 0.001 0.068 0.154 0.351 0.118 0.013 0 0.7 s 0.003 0.24 0.714 0.368 0.08 0.002 0 1.41 SSW 0.004 0.472 0.51 0.031 0.004 0 0 1.02 SW 0.005 0.454 0.334 0.023 0.002 0 0 0.82 WSW 0.005 0.495 0.368 0.015 0 0 0 0.88 w 0.005 0.416 0.637 0.015 0 0 0 1.07 WNW 0.003 0.307 0.458 0.008 0 0 0 0.78 NW 0.004 0.333 0.466 0.012 0 0 0 0.82 NNW 0.003 0.202 0.165 0.002 0.002 0 0 0.37 Total: 0.042 3.618 4.571 1.075 0.251 0.017 0 9.57

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 38of56 Section 5. 0 - Meteorology (cont.) Percent of time at each Wind Speed and Direction Period of Record: Jan. 1, 2009 to Dec. 31, 2014 Stability Class: G - Extremely Stable Elevation: Ground Level Release Wind Speed (mph) at 1Om Level Wind <1 1 - 3.5 3.6 - 7.5 7.6 - 12.5 12.6 - 18.5 18.6 - 24.5 >24.5 Total: Direction N 0.001 0.058 0.025 0 0 0 0 0.08 NNE 0.001 0.034 0.028 0 0 0 0 0.06 NE 0.001 0.03 0.01 0.008 0.002 0 0 0.05 ENE 0.001 0.029 0.018 0.008 0.012 0 0 0.07 E 0.001 0.033 0.029 0.02 0.008 0 0 0.09 ESE 0.001 0.039 0.058 0.021 0.004 0 0 0.12 SE 0.001 0.034 0.066 0.029 0.002 0 0 0.13 SSE 0.001 0.052 0.095 0.167 0.054 0 0 0.37 s 0.002 0.116 0.424 0.316 0.057 0 0 0.91 SSW 0.005 0.256 0.11 0.006 0 0 0 0.38 SW 0.005 0.258 0.189 0 0 0 0 0.45 WSW 0.006 0.481 0.316 0 0 0 0 0.8 w 0.008 0.586 0.609 0 0 0 0 1.2 WNW 0.007 0.353 0.401 0 0 0 0 0.76 NW 0.003 0.104 0.108 0 0 0 0 0.22 NNW 0.003 0.071 0.016 0 O' 0 0 0.09 Total: 0.048 2.534 2.498 0.574 0.139 0 0 5.79

ZionSolution~ LLC ZS-2017-0058: Attachment 1 Page 39of56 Section 5.0 -Meteorology (cont.) Table 5 - Percent Wind Direction by Stability Class Wind Stability Class Direction A B c D E F G Total N 0.48 0.28 0.53 3.4 1.72 0.36 0.08 6.86 NNE 1.45 0.37 0.59 2.9 1.33 0.22 0.06 6.89 NE 1.03 0.19 0.32 1.7 0.77 0.2 0.05 4.3 ENE 0.61 0.12 0.2 1.3 0.54 0.18 0.07 3 E 0.57 0.11 0.2 1.3 0.62 0.19 0.09 3.06 ESE 0.52 0.12 0.18 1.1 0.52 0.25 0.12 2.84 SE 0.5 0.14 0.26 1.2 0.98 0.3 0.13 3.54 SSE 0.33 0.25 0.58 3.0 1.83 0.7 0.37 7.08 s 0.08 0.07 0.19 1.9 2.68 1.41 0.91 7.27 SSW 0.24 0.18 0.34 2.6 2.47 1.02 0.38 7.26 SW 0.71 0.36 0.56 3.3 1.99 0.82 0.45 8.22 WSW 1.04 0.36 0.52 3.02 1.86 0.88 0.8 8.48 w 1.11 0.41 0.59 4 2.48 1.07 1.2 10.86 WNW 0.77 0.32 0.52 3.24 2.17 0.78 0.76 8.56 NW 0.59 0.29 0.41 3.08 1.95 0.82 0.22 7.36 NNW 0.13 0.11 0.22 2.39 1.11 0.37 0.09 4.42 TOTAL 10.17 3.67 6.21 39.58 25.01 9.57 5.79 100

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 40of56 Section 5.0 -Meteorology (cont.) Table 6 - Percent Wind Direction by Wind Speed Wind Speed in mph Wind <1 1 - 3.5 3.6 - 7.5 7.6- 12.6 - 18.6 - >24.5 Total: Direction 12.5 18.5 24.5 N 0.008 0.617 1.612 2.466 1.773 0.299 0.082 6.86 NNE 0.006 0.525 1.927 3.075 1.251 0.069 0.033 6.89 NE 0.006 0.515 1.587 1.483 0.602 0.066 0.031 4.3 ENE 0.006 0.433 1.178 0.763 0.498 0.118 0.01 3 E 0.005 0.399 1.345 0.615 0.524 0.148 0.021 3.06 ESE 0.004 0.422 1.451 0.669 0.249 0.052 0.002 2.84 SE 0.005 0.402 1.795 1.064 0.262 0.012 0 3.54 SSE 0.006 0.393 1.44 3.38 1.577 0.22 0.073 7.08 s 0.01 0.758 3.285 2.527 0.665 0.023 0 7.27 SSW 0.014 1.301 2.52 1.937 1.328 0.137 0.014 7.26 SW 0.016 1.192 2.158 2.785 1.866 0.172 0.029 8.22 WSW 0.016 1.395 2.846 2.806 1.322 0.087 0.01 8.48 w 0.018 1.511 4.016 3.495 1.773 0.057 0.004 10.86 WNW 0.015 1.217 3.41 2.988 0.917 0.02 0 8.56 NW 0.012 0.94 2.856 2.697 0.822 0.021 0 7.36 NNW 0.01 0.635 1.522 1.66 0.556 0.045 0.006 4.42 Total 0.161 12.655 34.944 34.404 15.979 1.545 0.312 100

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 41of56 Section 5.0 -Meteorology (cont.) Table 7 - Percent Speed by Stability Class Speed Stability Class (mph) A B c D E F G Total

   <1         0      0          0        0.006          0.065    0.042 0.048  0.161 1 - 3.5   0.227   0.177     0.524        4.22          6.601    4.625 3.303 19.677 3.6-7.5    2.591   0.938      1.768     10.886         11.692    4.571 2.498 34.944 7.6 - 12.5  5.137   1.739     2.806       16.01          7.063    1.075 0.574 34.404 12.6 -     2.3   0.872      1.352      9.286          1.779    0.251 0.139 15.979 18.5 18.6 -    0.11   0.067      0.11       1.048          0.193    0.017   0    1.545 24.5
 >24.5     0.012   0.008      0.027      0.225           0.04       0    0    0.312 Total:    10.17    3.67       6.21      39.58          25.01     9.57  5.79   100

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 42of56 Section 6 - Errata data There were a few corrections to the solid waste disposal report as reported in Zion Station 2015 ARERR. The changes were all in Section A.2.d. Irradiated components category for a few of the nuclides. The corrected data for the 2015. solid waste disposal report is as shown below. A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)

1. Types of Waste Total Total Est. Total Types of Waste Quantity Activity Period Error%

(m3) (Ci)

e. Spent Resins, filter sludges, 6.993E+Ol l.157E+02 2015 2.50E+Ol evaporator bottoms

f. Dry compressible waste, 3.l 15E+03 1.804E+02 2015 2.50E+Ol contaminated equipment

g. Irradiated components, 4.958E+02 8.316E+03 2015 2.50E+Ol control rods, etc.

h. Other (describe) O.OOE+OO O.OOE+OO 2015 2.50E+Ol

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 43of56 Section 6 - Errata data (cont.)

2. Estimate of major nuclide composition (by waste type)

Waste Type a. Waste Type b. DAW Waste Type d. Waste Major Nuclide Resins, sludges contaminated equipment Irradiated Typed. Composition bottoms(%) (%) components (%) Other% Ag-108m O.OOE+OO 2.26E-03 O.OOE+OO 0.00 Ag-1 lOm O.OOE+OO O.OOE+OO O.OOE+OO 0.00 Am-241 2.75E-03 2.30E-02 4.66E-05 0.00 C-14 1.50E-02 5.43E-02 5.64E-02 0.00 Ce-144 l.03E-03 5.86E-02 1.73E-04 0.00 Cm-242 3.91E-05 8.57E-05 l.78E-07 0.00 Cm-243 9.25E-04 7.19E-03 l.69E-05 0.00 Cm-244 O.OOE+OO 4.22E-03 8.85E-06 0.00 Co-60 4.36E+Ol 2.98E+Ol 6.49E+Ol 0.00 Cs-134 O.OOE+OO O.OOE+OO 2.61E-07 0.00 Cs-137 l.02E+Ol 5.37E+OO 3.23E-03 0.00 Fe-55 2.19E-01 3.60E+OO 9.23E+OO 0.00 H-3 5.87E-03 6.75E-02 1.43E-01 0.00 I-129 l.08E-03 5.97E-03 2.45E-05 0.00 Mn-54 O.OOE+OO 1.76E-02 l.05E-04 0.00 Nb-94 5.29E-03 2.44E-02 1.06E-03 0.00 Ni-59 3.81E+OO 7.63E-01 3.26E-01 0.00 Ni-63 4.18E+Ol 5.86E+Ol 4.lOE-04 0.00 Ni-63am O.OOE+OO 1.18E+OO 2.54E+Ol 0.00 Np-237 O.OOE+OO 6.69E-11 O.OOE+OO 0.00 Pu-238 1.50E-03 1.49E-02 2.17E-05 0.00 Pu-239 8.l lE-04 5.21E-03 8.56E-06 0.00 Pu-240 O.OOE+OO l.12E-03 6.66E-06 0.00 Pu-241 3.76E-02 9.07E-02 2.87E-04 0.00 Pu-242 4.45E-06 . l.68E-04 4.03E-07 0.00 Ra-226 O.OOE+OO 7.58E-04 1.0lE-05 0.00 Sb-125 6.59E-03 6.86E-02 1.42E-04 0.00 Sr-89 l.98E-03 1.73E-02 7.33E-06 0.00 Sr-90 2.69E-01 6.58E-02 6.50E-05 0.00 Tc-99 l.18E-02 5.34E-02 l.96E-04 0.00

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 44of56 Section 6 - Errata data (cont.) Waste Type a. Waste Type b. DAW Waste Type d. Waste Major Nuclide Resins, sludges contaminated equipment Irradiated Typed. Composition bottoms(%) (%) components (%) Other% EU-152 O.OOE+OO 6.69E-03 O.OOE+OO 0.00 EU-154 O.OOE+OO 9.29E-04 O.OOE+OO 0.00 U-235 O.OOE+OO 1.3 lE-03 O.OOE+OO 0.00 U-236 O.OOE+OO 4.34E-05 O.OOE+OO 0.00 U-237 O.OOE+OO l. lOE-05 O.OOE+OO 0.00 U-238 O.OOE+OO 4.67E-07 O.OOE+OO 0.00 Zn-65 6.39E-03 5.29E-02 9.34E-05 0.00

• Ni-63AM - activated metal

3. Solid Waste Disposition Number of shipments Mode of Transportation Destination 34 Truck CliveCWF 0 Rail CliveCWF 12 Truck CliveBWF 32 Rail CliveBWF 12 Truck wcs B. Irradiated Fuel Shipments (disposition)

Number of shi ments Mode of Trans ortation Destination 0 C. Changes to the Process Control Program: None

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 45of56 Section 7 - Changes to Zion Station Liquid Radwaste System Gaseous Effluent Treatment and Monitoring Systems

1. Changes to the Gaseous Effluent Treatment and Monitoring Systems.

a. Both Unit 1 and Unit 2 ventilation stacks and associated equipment were permanently removed from service on 12/8/2016 and all of the associated flow panels and radiation monitors to support decommissioning. Technical Support Document (TSD-16-007) was created to evaluate gaseous effluents and demonstrates that Zion Station has achieved a point in decommissioning where it is not possible to exceed dose limits from gaseous effluent. TSD-16-007 concludes that alarm capability is not required for gaseous effluent releases.

b. The gaseous effluent sampling and analysis program was changed to include all potential release points divided into 3 distinct types of releases.

1. Unit 1 and Unit 2 containments have portable filtered ventilation units for personnel habitability. Each portable filtered ventilation unit has a portable air sampler which collects a sample directly from the discharge of the exhaust of the unit. These samples are collected and analyzed daily IAW ODCM.

11. Unit 1 and Unit 2 tents have a portable air sampler continuously running at all times at each entry and egress point where the door to the entry and egress are opened to atmosphere. For the purposes of calculating release rates, the wind speed entering or exiting the tents is measured to esti~ate potential release rate.

iii. The potential release from open ::tir demolition of structures is sampled by having at a minimum of 4 portable air sampiers continuoµsly running in each of 4 general directions at all times while active demolition is in progress. Wind speed and direction are documented at each air sampler. Each air sample is collected and analyzed daily.

2. Changes to the liquid effluent treatment and monitoring system.

a. The liquid effluent treatment system'~as redesigned and relocated from the AB to the WWTF.

1. Demineralizers were moved from the Aux Building to WWTF such that the actual capability of the demineralizers and the capability of treatment of liquid effluent releases remains unchanged. *

11. Existing tanks in the AB have been abandoned and double wall frac tanks have been installed outside of WWTF in a climate controlled tent. Water pumped from the AB to these frac tanks pass through double-walled piping nested in a lined trough. One end of the outer piping provides a tell-tale drain to provide positive identification that the inner piping is not leaking. A li~ed catch-basin has been established around the a

tanks and provides discharge location from the tell-tales to provide a barrier to prevent any water from leaking onto the ground, in the event that there is a failure of the inner piping or tank overflow. '.[he liquid effluent discharge flowmeters are calibrated flowmeters. The liquid ~ffluent radiation monitor is the same monitor used in the prior system, with the same function and capabilities. The discharged water flows directly into the discharge tunnel downstream of the point the dilution pump discharge enters the tunnel.

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 46of56 Section 7 - Changes to Zion Station Liquid Radwaste System Gaseous Effluent Treatment and Monitoring Systems (cont.) iii. The methodology of calculating liquid effluent release is unchanged by this physical change to the system.

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 47of56 Section 8 - Out of Service Radiation Monitors

1. There were no radiation monitors inoperable for >30 days during 2016.

2. There was one occurrence of surveillance requirements not met on Ul filtered exhaust fan gaseous effluent sampler.

On 12/15/16 there was a loss of power to main disconnect that fed the transformer which supplied power to the Ul torit exhaust air sampler. The cause was workers had meant to turn off power to a local heating unit during work, but had opened the wrong breaker. Breakers have been more clearly labeled that Radiation Protection personnel need to be contacted prior to opening all of the breakers required for effluent air monitoring and an Issue Review(IR) was initiated. The loss of power to the air sampler occurred at 1500, during routine inspections, the shift technician identified the air sampler was not running at 1900. Supervision was notified and further investigation found the .power supply breaker in the open position. It could not be immediately determined why the breaker was opened, thus the breaker was not closed until electricians would be available on site to determine if it was safe to close the breaker. Supervision provided instruction to secure Ul torit exhaust fan to secure the release. Ul torit exhaust fan was secured at 2000. ODCM Table 12.2-3 surveillance 9.2 requires re-establishing air sampling at the discharge of exhaust fans within 4 hours, the total time elapsed from the actual loss of power to the time that Ul filtered exhaust fan was secured was 5 hours. Power to the Ul torit air sampler was restored on 12/16/17 and the air sampler re-established at 0910. The air sample filter from 12/15/16 which ran froni 0700 to 1500 was analyzed via gamma isotopic, all nuclides were< LLD. No work was being performed in Ul containment from 1500 to 2000 when Ul exhaust filtered exhaust fan was running, thus there was no potential for an increase in particulates released via this pathway. The air sample results on 12/16/17 after air sampling was re-established indicated all nuclides were <LLD. It is determined that no measurable activity would have been released during the time period the air sampler was without power.

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 48of56 Section 9 - List of Changes to the ODCM In accordance with ODCM section 12.7.3.1.c. Many changes were made to the ODCM, including an interim change for post-fuel transfer operations and a finalized change for post-fuel transfer operations. A summarized list of the changes is presented here, along with a complete copy of the current ODCM.

1. Ch.12 Rev 29 Page Section Change Summary 12-i PDTS changed to QAPP Appendix B 12-iii TOC 12.4 Removed Dose-Noble Gases, 1-131,1-133 12-3 12.1.26 Added definition for unventilated building releases 12-3 12.1.27 Removed line stating effects on noble gas and iodine.

12-4 Table 12.1-1 Removed duplicate notation on REMP program frequency limitation. 12-5 12.2.1.C Removed notation 'within the pl~t' to broaden bases to entire site. 12-6 Table 12.2-1 Removed words (Boric Acid Tanks (BAT). Added note related to surveillance 1. 12-7 Table 12.2-1 Surveillance 1, removed limitation of 14 days for inoperable monitor 12-8 Table 12.2-2 Removed words Boric Acid Tanks (BAT) 12-9 12.2.2.C Removed word.s 'within the plant' to expand bases for entire site. Removed the word 'rec:ord' as printer function is unavailable. 12-11 Table 12.2-3 2R-PR49A(Channel 1) renamed to 2R-PR49. Removed 2R-PR49E (channel 5) entirely. Removed Fuel building' monitoring section. (ORT-AR13, ORT-AIµl, ORT-AR22, ORT-AR24) 12-12 Table 12.2-3 Surveillance 8: Removed 'operations' as chemistry personnel are qualified to perform this surveillance. Changed 'station review' to

                          'review' Changed 'panel' to 'equipment'. Surveillance 10: Deleted, Surveillance 11 -3 deleted (covered by surveillance 8), Surveillance 12:

1 Deleted, Surveillance 13: Deleted 12-13 Table 12.2-4 2R-PR49A (C~annel 1) renamed to 2R-PR49. Gas Activity Monitor 2R-PR49E (channel 5) deleted. Fuel Building Monitoring ORT-AR13,21,22,24 deleted. 12-14 Table 12.2-4 Changed control room alarm annunciation occurs to 'alarms occur.' Deleted note (3;) and (4) 12-15 12.3.1.A.l Deleted 'For dissolved or entrained noble gases sentence. 12-17 Table 12.3-1 Deleted page 12-18 Table 12.3-2 Deleted (Boric Acid Tank) verbiage. Deleted sampling and analysis requirements for dissolved and entrained noble gases. 12-24 12.4.1.A 12.4.1.A.l. Deleted. 12.4.1.A.2. Removed 1-131, 1-133. 12.4.1.C removed 3000 mrem/year to the skin noble gas dose calculation.

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 49of56 Page Section Change Summary 12-25 Table 12.4-1 Moved Unit 2, FHB, AB sample requirement to combine with Unit 1 requirements. Added modular HEP A ventilation requirements (if applicable). Removed sampling and LLD limits for noble gas. 12-26 Table 12.4-1 Removed Unit 2, AB, FHB sample requirements and moved to Unit 1. Added note to explain sampling requirements for unventilated releases. Deleted note using old unventilated releases definition. 12-27 Table 12.4-1 Deleted notes: d, g, I, j 12-28 12.4.2 Deleted entire section. Dose-Noble Gas 12-29 12.4.2.C Deleted section- Bases of dose-noble Gas 12-30 12.4.3 Deleted 1-131, 1-133 12-32 12.4.4.A Deleted 1,2 mrad gamma, beta dose from noble gas. 12-37 Table 12.5-1 Changed 30 TLD stations to 31 TLD stations. Deleted ISFSI Indicator TLD locations. 12-39 Table 12.5-1 Added 5. Vegetation, sampling frequency and type of analysis 12-41 Table 12.5-2 Added Vegetation reporting activity concentration 12-42 Table 12.5-3 Added Vegetation LLD concentration. 12-45 12.5.2 A. Added a nearest garden census must be performed, C. Removed from Bases that a nearest garden census is not required. 12-49 12.7.2.1 Changed Tech Specs. to QAPP 12-51 12.7.3.1 Changed Tech Specs. to QAPP

2. Ch.12 Rev 30 Page Section Change Summary 12-6 Table 12.2-1 Removed OR-PR25, changed Turbine Building Fire Sump to WWTF 12-7 Table 12.2-1 Deleted Surveillance 2 12-8 Table 12.2-2 Removed OR-PR25 changed Turbine Building Fire Sump to WWTF 12-18 Table 12.3-2 Changed Turbine Building Fire Sump to WWTF 12-20 Table 12.3-2 Changed Turbine Building Fire Sump to WWTF

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 50of56

3. ODCMRevO Page Section Change Summary - Post Fuel Transfer Operations re-write All All Consolidation of all Chapters and appendices into a single document.

Removal of Exelon generic information that is not applicable to Zion such as river flows and boiling water reactor requirements. Removal of requirements to maintain meteorological tower. Groundwater sampling surveillances added. Added gaseous effluent considerations for future open-air demolition. Remove requirement to monitor tritium from vent stack as the tritium in water volumes is released via liquid effluents. Aerial site photographs and maps have been updated to better illustrate TLD placement locations. 14 day limitation for OOS OR-PR04 had been changed to 30 days.

4. ODCMRev 1 Page Section Change Summary 35 10.1.2.1 Clarified description of Aux Building Vent Stack Effluent Monitor 39 10.4.1 Editorial change, clarified wording 39 10.4.2 Editorial change, clarified wording 59 Table 12.2-1 Added OFI-WD005A and OFI-WD006A low flow flowmeters 61 Table 12.2-2 Added surveillance and calibration requirements forOFI-WD005A and OFI-WD006A 64 Table 12.2-3 Clarified surveillance 8 for 1&2 LP-084 panel sample pump operation requirements.

69 Table 12.3-2 Added wording to clarify WWTF compositor sampling required only during release. 71 Table 12.3-2 Clarified section f to require WWTF only d~ing system operation.

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 51of56

5. ODCMRev2 Page Section Change Summary 44 Table 11-1.1 Changed location of Air Sampler Z-03 from 0.25 miles sector R(NNW) to 0.2 miles sector B(NNE) 45 Table 11-1.2.b. Changed location ofTLD Z-03-1and2 from 0.25 miles sector R(NNW) to 0.2 miles sector B(NNE) 50 Figure 11-1 a Revised inner ring REMP map to correct sector labels. REMP sample location Z-03 moved. MET tower removed from map.

51 Figure 11-lb Re-added REMP outer ring sample locations. 57 12.2.1.A Added time frame of actions to take in inoperability of liquid effluent monitor referenced by section 1~.7.2. 58 Table 12.2-1 Added OFIT-SW54B flowmeter for high capacity dilution pump. 59 Table 12.2-1 Added verbiage to indicate the surveillance applies to the applicable (High or Low flowrate) flowmeter. 60 I Table 12.2-2 Added OFIT-SW54B i 61 12.2.2.A Moved verbiage for inoperable rad monitor reporting requirements reference by section 12. 7 .2 to this section from surveillance 8 requirement as it is more approppately located in the Action section. 63 Table 12.2-3 Removed verbiage for returning :channel to operable status time requirements from surveillance~ to relocate to section 12.2.2.A where it is more appropriately described. 97 12.7.2 Permanently Defueled Tech Spe~ change to QAPP App. B

6. ODCMRev3 Page Section Change Summary 58 Table 12.2-1 Added OFI-WD007 common discharge flowmeter 60 Table 12.2-2 Added surveillance for OFI-WD007

7. ODCMRev4 Page Section Change Summary 58 Table 12.2-1 Deleted SW54 and 54B service water flowmeters.

Added OPI-SWOlA and OPI-SWOl Pressure Gauge 59 Table 12.2-1 Added Silrveillance 2 for Service Water Pressure gauge inoperability. 60 Table 12.2-2 Deleted SW54 and SW54B flowmeters. Added OPI-SWOlA and OPI-SWOl service water pressure gauge. Modified note 4 to indicate pressure gauge verification once per day and to estimate dilution flow once per day.

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8. ODCMRev 5 Page Section Change Summary 56 Table 12.1-1 Deleted Four-Hourly notation for frequency of every 4 hours.

58 Table 12.2-1 Editorial correction OPI-SWOlA and OPI-SWOl are listed as Discharge pressure flow indicators. Note** added to clarify either pressure indication may be used to apply to minimum channels operable. Changed surveillance requirement to surveillance 3. 59 Table 12.2-1 Deleted Surveillance 2 for Service Water Pressure gauge. 60 Table 12.2-2 Editorial correction OFI-WD007 should be listed under common discharge Editorial correction OPI-SWOlA and OPI-SWOl are dilution flow pressure indicatms. Modified note 4 to indicate pressure indicators shall be checked once per day and pump curves used for flow estimation during lake release tank releases.

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 53of56 Section 9 - List of Changes to the ODCM (cont.) In accordance with ODCM section 12.7.3.1.c. Some changes were made to the ODCM to support progress of decommissioning of Zion Station, the summary of changes is listed below along with a complete copy of the current ODCM.

9. ODCM Revision 6 -This revision to the ODCM supports the changes to the liquid radwaste effluent treatment and monitoring system as described in Section 7.

Page# Section Description of change 37 10.2.1.1 Redefined definition of Lake Release Tanks 37 10.2.1.2 Removed HUTs description and replaced with Aux Building Collection tank and description. 59 Table 12.2-1 Changed effluent flowrate monitors to include only OFI-WD0005,6 and 8. Deleted OFI-WD005A and 6A. Modified Lake Release Tank #1 and #2 to read high flow pathway and low flow pathway as all flowmeters are in common header to all 3 lake release tanks. 61 Table 12.2-2 Changed effluent flowrate monitors to include only OFI-WD0005,6 and 8. Deleted OFI-WD005A and 6A. Modified Lake Release Tank #1 and #2 to read high flow pathway and low flow pathway as all flowmeters are in common header to all 3 lake release tanks. 83 Table 12.5-1 Added TLD type UD-814-Al as acceptable TLD type for Environmental Monitoring TLl)s.

10. ODCM Revision 7 -This change supports decommissioning of the Aux Building as the volume of water collection provided by the Aux Building.Collection Tank is no longer required. The Aux building sump provides all of the necdsary water storage capacity.

Page# Section Description of change* 37 10.2.1.2 Deleted Section discussing Aux Building Collection Tanlc

,~- ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 54of56 Section 9 - List of Changes to the ODCM (cont.)

11. ODCM Revision 8 - This change supports removing both Unit 1 and Unit 2 gaseous vent stacks and associated fans and requirements for alarming rad monitors. This section also provides the new methods of demonstrating compliance with gaseous effluent release sampling and analysis to ensure compliance with effluent release limits.

Page# Section Description of change 6 2.2 Ventilation exhaust treatment system changed to open air demolition sampling requirements 28 6.1 Gaseous radwaste treatment system changed to portable ventilation exhaust filtration system. 36 10.1.1 Discussion ofUl and U2 vent stack and Aux building ventilation changed to reflect air sampling configuration required for decommissioning and open air decommissioning. 36 10.1.1.1 Ventilation Exhaust Treatment System is deleted 36 10.1.2.1 Aux building vent stack effluent monitors changed to reflect open air demolition air sampling requirements 36 10.1.2.2 Containment purge effluent monitors changed to Active Decommissioning Air Sampling and description of portable exhaust filtration. 37 10.1.3.5 HV AC flowrates description changed to use max design flow capacity of portable ventilation filtration units. 39 10.4.1 Description of gaseous effluent rad monitors removed, leaving only liquid effluent rad mo.nitor in description. 39 10.4.2 Description of gaseous effluent rad monitor removed, leaving only liquid effluent rad monitor in description. 40 10.4.3 Containment Purge system effluent monitor description deleted 40 10.4.4 Fuel Building Exhaust air monitor description is deleted. 40 10.4.6 Description of calibration and testing of gaseous radiation alarlning monitor is removed from this section, leaving liquid effluent rad monitor calibration and testing unchanged. 40 10.4.7 Continuous radiation monitoring system is deleted. Added to this section requirement for continuous sampling, composite and laboratory analysis of air samples taken for active decommissioning effluent samples. 43 Table 10-2 HV AC exhaust fan capacity table is deleted. Added description to us the maximum design flowrate of portable exhaust filtration systems will be used in calculations requiring exhaust flowrate.

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 55of56 Page# Section Description of change 62 12.2.2.A Gaseous effluent rad monitor operability requirements removed. Added operability requirements for gaseous effluent air samplers during active decommissioning. 62 12.2.2.B.1 Deleted gaseous effluent radiation monitor setpoint requirements 62 12.2.2.B.2 Deleted channel calibrations for gaseous effluent radiation monitors. Added requirements to ensure gaseous effluent air sampler flow rates and counting equipment is calibrated. 62 12.2.2.C Deleted bases of gaseous effluent radiation monitors: Added bases for particulate air samplers needed for quantifying effluent release. 63 Table 12.2-3 Deleted 1(2)RIA-PR49 and 1(2)LP-084 oerability, surveillances, applicable conditions. Added Surveillances and applicable conditions for Ul, U2 containment air samplers and open air demolition air samplers and South waste loading area air samplers. 64 Table 12.2-3 Deleted surveillance for gaseous effluent rad monitor inoperability. Added surveillance requirement to ensure air samplers are operating or cease active decommissioning. 65 Table 12.2-4 Ddeted channel checks, source checks, channel calibration and functional checks of gase'~us effluent radiation monitors. 75 Table 12.4-1.B,C Deleted containment vent*.and purge, aux building, Ul vent stack, U2 vent stack samplil}g requirements. Added Ul ventilation, U2 ve1,1tilatiori and portable filtered ventilation various location requirements. 75 Table 12.4-1.D Changed unventilated rel~ase description from building to Ul, U2 tent. Modified sampli~g requirements from continuous to continuous during active *decommissioning and modified note (h) 75 Table 12.4-1.E Added this section to pro:vide sampling requirements, analysis, type of analysis and LLD's to open air decommissioning work. 76 Table 12.4-1 a. Removed 1(2) RIA-PR49, containment and AB. Added table notations requirement for continuous sampling during active decommissioning when a viable release pathway to the environment exists.

h. changed clarification of a short duration activity to include moving air sampler to a more appropriate location when necessary.

1. Changed from DELETED to add continuous air sampling at open air demolition locations are required to be maintained in 4 general directions during active open air decommissioning with potential for airborne releases.

ZionSolutions LLC ZS-2017-0058: Attachment 1 Page 56of56 Page# Section Description of change 78 12.4.4 A, B: Deleted requirements for gaseous effluent treatment system. Modified wording that dose projection every 31 days shall take place in compliance with QAPP section 5.6.2.f C: modified bases to describe ALARA practice of encapsulating loose contamination as a method of practicing ALARA during decommissioning. 94 12.7.2 Removed discussion of gaseous effluent monitoring instrumentation inoperability requirements. 181 Table F-1 Deleted reference to section C.1.3.1.2 of ODCM Appendix C. as this section was removed from the ODCM at some point prior to 2011, and the reference was overlooked in previous revisions of AppendixF.

ZionSolutions LLC ZS-2017-0058: Attachments ATTACHMENT 2 Zion Station ODCM, Rev. 9

Revision 9 I February 27, 2017 Zion Station Offsite Dose Calculation Manual Docket Numbers: 50-295, 50-304 and 72-1037 Page 1of268

Revision 9 February 27, 2017 OFFS/TE DOSE CALCULATION MANUAL TABLE OF CONTENTS PAGE Chapter 1 Introduction 3 Chapter 2 Regulations and Guidelines 4 Chapter 3 Pathways 13 Chapter4 Introduction to Methodology 16 Chapter 5 Measurement 27 Chapter 6 Implementation of Offsite Dose Assessment Program 28 Chapter 7 References 29 Chapter 8 Deleted 34 Chapter 9 Deleted 35 Chapter 10 Radioactive Effluent Treatment System and Monitoring 36 Chapter 11 Radiological Environmental Monitoring Program 44 Chapter 12 Radiological Effluent Technical Standards 54 Appendix A Compliance Methodology 98 Appendix B Models and Parameters for Airborne and Liquid Effluent Calculations 130 Appendix C Generic Data 160 Appendix D Deleted 177 Appendix E Deleted 178 Appendix F Station Specific Data 183 Appendix 0 ODCM Bases and Reference Document 256 Page 2 of 268

Revision 9 February 27, 2017 CHAPTER 1 INTRODUCTION

1.0 INTRODUCTION

The Offsite Dose Calculation Manual (ODCM) presents a discussion of the following:

• The basic concepts applied in calculating offsite doses from Zion Station effluents.
• The regulations and requirements for the ODCM and related programs.
• The methodology and parameters for the offsite dose calculations used to assess impact on the environment and compliance with regulations.

The methodology detailed in this manual is intended for the calculation of radiation doses during routine (i.e., non-accident) conditions. The calculations are normally performed using a computer program. Manual calculations may be performed in lieu of the computer program. The dose effects of airborne radioactivity releases predominately depend on meteorological conditions (wind speed, wind direction, and atmospheric stability). For airborne effluents, the dose calculations prescribed in this manual are based on historical average atmospheric conditions. This methodology is appropriate for estimating annual average dose effects and is stipulated in the Bases Section of the Radiological Effluent Technical Standards (RETS). 1.1 STRUCTURE OF THIS MANUAL Chapters 1 thru 7 provide a brief introduction and overview of Zion Stations offsite dose calculation methodology and parameters. Chapters 10 thru 12 provide specific requirements for the treatment and monitoring_ o~ radioactive effluents covered by the Radiological Environmental Monitoring Program (REMP) and the Radiological Effluent Technical Standards (RETS). Appendices A and B provide detailed information on specific aspects of the methodology. Appendix C contains tables of values of the generic parameters used in offsite dose equations. Appendix F contains tables of values for the parameters used in the offsite dose equations. Appendix 0 provides description of the bases for the methodology and parameters discussed in the ODCM. Page 3 of 268

Revision 9 February 27, 2017 CHAPTER2 REGULATIONS AND GUIDELINES

2.0 INTRODUCTION

This chapter of the ODCM serves to illustrate the regulations and requirements that define and are applicable to the ODCM. Any information provided in the ODCM concerning specific regulations are not a substitute for the regulations as found in the Code of Federal Regulations (CFR) or Quality Assurance* Project Plan (QAPP). 2.1 CODE OF FEDERAL REGULATIONS Various sections of the Code of Federal Regulations (CFR) require nuclear power stations to be designed and operated in a manner that limits the radiation exposure to members of the public. These sections specify limits on offsite radiation doses and on effluent radioactivity concentrations and they also require releases of radioactivity to be "As Low As Reasonably Achievable". These requirements are contained in 10CFR20, 10CFR50, 10CFR72 and 40CFR190. In addition, 40CFR141 imposes limits on the concentration of radioactivity in drinking water provided by the operators of public water systems. 2.1.1 10CFR20, Standards for Protection Against Radiation The 10CFR20 dose limits are summarized in Table 2-1. 2.1.2 Design Criteria (Appendix A of 10CFR50) Section 50.36 of 10CFR50 requires that an application for an operating license include proposed Technical Specifications. Final Technical Specifications are developed through negotiation between the applicant and the NRC. The Technical Specifications are then issued as a part of the operating license, and the licensee is required to operate the facility in.accordance with them. The remaining Defueled Technical Specification requirements have been relocated to the QAPP. Section 50.34 of 10CFR50 states that an application for a license must state the principal design criteria of the facility. Minimum requirements are contained in Appendix A of 10CFR50. 2.1.3 ALARA Provisions (Appendix I of 10CFR50) Sections 50.34a and 50.36a of 10CFR50 require that the nuclear plant design and the station RETS have provisions to keep levels of radioactive materials in effluents to unrestricted areas "As Low As Reasonably Achievable" (ALARA). Although 10CFR50 does not impose specific limits on releases, Appendix I of 10CFR50 does provide numerical design objectives and suggested limiting conditions for operation. According to Section I of Appendix I of 10CFR50, design objectives and limiting conditions for operation, conforming to the guidelines of Appendix I "shall be deemed a conclusive showing of compliance with the "As Low As Reasonably Achievable" requirements of 10CFR50.34a and 50.36a." An applicant must use calculations to demonstrate conformance with the design objective dose limits of Appendix I. The calculations are to be based on models and data such that the actual radiation exposure of an individual is "unlikely to be substantially underestimated" (see 10CFR50 Appendix I, Section 111.A.1). The guidelines in Appendix I call for an investigation, corrective action and a report to the NRC whenever the calculated dose due to the radioactivity released in a calendar quarter exceeds one-half of an annual design objective. The guidelines also require a surveillance program to monitor releases, monitor the environment and identify changes in land use. Page 4 of 268

Revision 9 I February 27, 2017 2.1.3 10CFR72, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste During normal operations and anticipated occurrences, 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, radon and its decay products excepted, to the general environment, *
• Direct radiation from ISFSI or MRS operations, and
• Any other radiation from uranium fuel cycle operations within the region.

2.1.4 40CFR190, Environmental Radiation Protection Standards for Nuclear Power Operations Under an agreement between the NRC and the EPA, the NRC stipulated to its licensees in Generic Letter 79-041 that "Compliance with Radiological Effluent Technical Specifications (RETS), NUREG-0472 (Rev.2) for PWR's or NUREG-0473 (Rev.2) for BWR's, implements the LWR provisions to meet 40CFR190". (See reference 103 and 49.) The regulations of 40CFR190 limit radiation doses received by members of the public as a result of operations that are part of the uranium fuel cycle. Operations must be conducted in such a manner as to provide reasonable assurance that the annual dose equivalent to any member of the public due to radiation and to planned discharges of radioactive materials does not exceed the following limits:

• 25 mrem to the total body
• 75 mrem to the thyroid
• 25 mrem to any other organ An important difference between the design objectives of 10CFR50 and the limits of 40CFR 190 is that 10CFR50 addresses only doses due to radioactive effluents. 40CFR190 limits doses due to effluents and also to radiation sources maintained on site. See Section 2.4 for further discussion of the differences between the requirements of 10CFR50 Appendix I and 40CFR 190.

2.1.5 40CFR141, National Primary Drinking Water Regulations The following radioactivity limits for community water systems were established in the July, 1976 Edition of 40CFR141:

• Combined Ra-226 and Ra-228: ~ 5 pCi/L.
• Gross alpha (particle activity including Ra-226 but excluding radon and uranium): ~ 15 pCi/L.
• The average annual concentration of beta particle and photon radioactivity from man-made radionuclides in drinking water shall not produce an annual dose equivalent to the total body or any internal organ greater than 4 mrem/yr.

The regulations specify procedures for determining the values of annual average radionuclide concentration which produce an annual dose equivalent of 4 mrem. Radiochemical analysis methods are also specified. The responsibility for monitoring radioactivity in a community water system falls on the supplier of the water. However, Zion Station has requirements related to 40CFR141 in their specific RETS. For calculation methodology, see Section A.6 of Appendix A ' Page 5 of 268

Revision 9 February 27, 2017 2.2 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS The Radiological Effluent Technical Standards (RETS) were formerly a subset of the Technical Specifications. They implement provisions of the Code of Federal Regulations aimed at limiting offsite radiation dose. The NRG published Standard Radiological Effluent Technical Specifications for PWRs (Reference 2) as guidance to assist in the development of technical specifications. These documents have undergone frequent minor revisions to reflect changes in plant design and evolving regulatory concerns. The Radiological Effluent Technical Specifications have been removed from the Technical Specifications and placed in the ODCM as the Radiological Effluent Technical Standards (RETS) (see Reference 90). The Zion Station RETS are similar, but not identical to the guidance of the Standard Radiological Effluent Technical Specifications. 2.2.1 Categories The major categories found in the RETS are the following:

• Definitions A glossary of terms (not limited to .the ODCM).
• Instrumentation This section states the Operability Requirements (OR) for instrumentation performance as well as the associated Surveillance Requirements. The conservative alarm/trip setpoints ensure regulatory compliance for both liquid and gaseous effluents. Surveillance requirements are listed to ensure ORs are met through testing, calibration, inspection and calculation. Also included are the bases for interpreting the requirements. The Operability Requirement (OR) is the ODCM equivalent of a Limiting Condition for Operation (LCO) as defined in both the NRG published Standard Radiological Effluent Technical Specifications and the stations' Technical Specifications.
• Liquid Effluents This section addresses the limits, special reports and liquid waste treatment systems required to substantiate the dose due to liquid radioactivity concentrations to unrestricted areas. Surveillance Requirements and Bases are included for liquid effluents.
• Gaseous Effluents This section addresses the limits, special reports and gaseous radwaste, open air demolition and sampling requirements necessary for adequate documentation of the instantaneous offsite radiation dose rates and. doses to a member of the public. Surveillance Requirements and Bases are included for gaseous effluents.
• Radiological Environmental Monitoring Program This section details the Radiological Environmental Monitoring Program (REMP) involving sample collection and measurements to verify that the radiation levels released are minimal. This section describes the annual land use census and participation in an interlaboratory comparison program.

Surveillance Requirements and Bases are included for environmental monitoring.

• Reports and Records This section serves as an administrative guide to maintain an appropriate record tracking system. The management of procedures, record retention, review/audit and reporting are discussed.

Page 6 of 268

Revision 9 February 27, 2017 2.3 OFFSITE DOSE CALCULATION MANUAL The NRC in Generic Letter 89-01 defines the ODCM as follows (not verbatim) (see Reference 90): The Offsite Dose Calculation Manual (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs and (2) descriptions of the Information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports. Additional requirements for the content of the ODCM are contained throughout the text of the RETS. 2.4 OVERLAPPING REQUIREMENTS In 10CFR20, 10CFR50, 10CFR72 and 40CFR190, there are overlapping requirements regarding offsite radiation dose and dose commitment to the total body. In 10CFR20.1301 the total effective dose equivalent (or TEDE) to a member of the public is limited to 100 mrem per calendar year. In addition, Appendix I to 10CFR50 establishes design objectives on annual total body dose or dose commitment of 3 mrem per reactor for liquid effluents and 5 mrem per reactor for gaseous effluents (see 10CFR50 Appendix I, Sections II.A and ll.B.2(a)). Per 10CFR72, the annual dose equivalent to a real individual beyond the controlled area boundary is limited to 25 mrem whole body from both effluents and direct radiation combined. Finally, 40CFR 190 limits annual total body dose or dose commitment to a member of the public to 25 mrem due to all uranium fuel cycle operations. While these dose limits/design objectives appear to overlap, they are different and each is addressed separately by the RETS. Calculations are made and reports are generated to demonstrate compliance to all regulations. Refer to Tables 2-1, 2-2 and 2-3 for additional information regarding instantaneous effluent limits, design objectives and regulatory compliance. 2.5 DOSE RECEIVER METHODOLOGY Table 2-2 lists the location of the dose recipient and occupancy factors, if applicable. Dose is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures with the exception of dose from contained sources. The dose calculation methodology is consistent with the methodology of Regulatory Guide 1.109 (Reference 6), NUREG 0133 (Reference 14) and NRC ISG-13 Rev. 0, Spent Fuel Project Office Interim Staff Guidance - 13 Real Individual, May 17, 2000 (Reference 108). The "maximum individual" is characterized as "maximum" with regard to food consumption, occupancy and other usage of the area in the vicinity of the plant site. Occupancy of a "maximum individual" is not used in dose assessments from contained sources. Such a "maximum individual" represents reasonable deviation from the average for the population in general. In all physiological and metabolic respects the maximum individual is assumed to have those characteristics that represent averages for their corresponding age group. When calculating dose attributed to contained sources for the "maximum individual" dose receptor location, occupancy is defined as a habit for a "real individual" at that location. 100% occupancy is not assumed when calculating dose from contained sources. Finally Table 2-3 relates the dose component (or pathway) to specific ODCM equations and the appropriate regulation. Page_ 7 of 268

Revision 9 February 27, 2017 Table 2-1 Regulatory Dose Limit Matrix REGULATION DOSE TYPE DOSE LIMIT(s) ODCM EQUATION Airborne Releases: (quarterly) (annual) 10CFR50 App. I~ Gamma Dose to Air due to Noble Gas 5 mrad 10 mrad A-1 Radionuelides (per reactor unit) Beta .Dose to Air Due to Noble Gas 10 mrad 20 mrad A-2 Radionuclides (per reactor unit) Organ Dose Due to Specified Non-Noble 7.5 mrem 15 mrem A-7 Gas Radionuclides (per reactor unit) Total Body and Skin Total Body 2.5 mrem 5 mrem A-3 Dose (if air dose is exceeded) Skin 7.5 mrem 15 mrem A-4 QAPP Organ Dose Rate Due to Specified Non- 1,500 mrem/yr A-16 Noble Gas Radionuclides (instantaneous limit, per site) Liquid Releases: (quarterly) (annual) 10CFR50 App. I" Whole (Total) Body Dose 1.5 mrem 3mrem A-17 (per reactor unit) Organ Dose (per reactor unit) 5 mrem 10 mrem A-17 QAPP The concentration of radioactivity in liquid Ten (10) times the effluents released to unrestricted areas concentration values A-21 listed in 10CFR20 Appendix B; Table 2, Column 2 *1 1 Total Doses  : 10CFR20.1301 (a)(1) Total Effective Dose Equivalent" 100 mrem/yr A-25 10CFR20.1301 (d), Total Body Dose 25 mrem/yr A-25 10CFR72.104 (a) and 40CFR190 Thyroid Dose 75 mrem/vr A-25 Other Oroan Dose 25 mrem/vr A-25 2 Other Limits  : 40CFR141 Total Body Dose Due to Drinking Water 4 mrem/yr A-17 From Public Water Systems Organ Dose Due to Drinking Water From 4 mrem/yr A-17 Public Water Svstems These doses are calculated considering all sources of radiation and radioactivity in effluents. 2 These limits are not directly applicable to nuclear power stations. They are applicable to the owners or operators of public water systems. However, the Zion Station RETS requires assessment of compliance with these limits. For additional information, see Section A.6 of Appendix A. 3 Note that 10CFRSO provides design objectives not limits. 4 Compliance with 10CFR20.1301(a)(1) is demonstrated by compliance with 40CFR190. Note that it may be necessary to address dose from on-site activity by members of the public as well. Page 8 of 268

Revision 9 February 27, 2017 TABLE 2-2 DOSE ASSESSMENT RECEIVERS Location; Occupancy if Dose Component or Pathway Different than 100% "Instantaneous" concentration limits in liquid Point where liquid effluents enter the unrestricted effluents area Annual average concentration limits for liquid Point where liquid effluents enter the unrestricted effluents area Direct dose from contained sources Dose receptor location and occupancy with respect to the habits of a real individual as described in EH&S TSD 13-009, "Member of the Public Dose from all Onsite Sources." Direct dose from airborne plume Receiver is at the unrestricted area boundary location that results in the maximum dose. Dose due to tritium and particulates with half- Receiver is at the location in the unrestricted area lives greater than 8 days for inhalation, where the combination of existing pathways and ingestion of vegetation, milk and meat, and receptor age groups indicates the highest potential ground plane exposure pathways. exposures. Ingestion dose from drinking water The drinking water pc;ithway is considered as an additive dose component in this assessment only if the public water supply serves the community immediately adjacent to the plant. Ingestion dose from eating fish The receiver eats fish from the receiving body of water (lake) Total Organ Doses Summation of ingestion/inhalation doses Total Dose Summation of above data (Note it may also be necessary to address dose from on-site activity by members of the public.) Page 9 of 268

Revision 9 February 27, 2017 TABLE 2-3 DOSE COMPONENT/REGULATION MATRIX Regulation in which dose component is utilized Dose Component or Reference equation; 10CFR50 Pathway Comments 10CFR20 10CFR72 40CFR190 App. I "Instantaneous" concentration A-21: limits in liquid effluents Ten times the limits of Table 2, Col. x(2) 2, 10CFR20, Appendix B to

                                       §§20.1001 - 20.2402 Annual average concentration             10CFR20, Appendix B to limits for liquid effluents             §§20.1001 - 20.2402(   2)                 x(3)

Direct dose from contained Section A.3.1 x x x sources Direct dose from radioactivity deposited on the ground A-7 and A-8 x x x x Inhalation dose from airborne effluents A-7 and A-9 (1) x x x x Ingestion dose from vegetables A-7, A10 and A-11 ( )1 x x x x Ingestion dose from milk A-7, A-12 and A-13 (1) x x x x Ingestion dose from meat A-7, A-14 and A-15 (1) x x x x Ingestion dose from drinking VJater A-17, A-18 and A-19 (1) x x x x Ingestion dose from eating fish A-17, A-18 and A-20 (1) x x x x Total Organ Doses A-25 x x x Total Effective Dose Equivalent A-25l"I x Ingestion/inhalation dose assessment is evaluated for adult/teen/child and infant for 10CFR50 Appendix I compliance and for 10CFR20/40CFR190 compliance. Ingestion/inhalation dose factors are taken from Reg. Guide 1.109 (Reference 6). 2 With the relocation of fuel to the ISFSI, noble gas releases can no longer occur. 3 Optional for 10CFR20 compliance. 4 Compliance with the Total Effective Dose Equivalent limits of 10CFR20 is demonstrated by compliance with 40CFR190. It may also be necessary to address dose from on-site activity by members of the public. Page 10 of 268

Revision 9 February 27, 2017 Figure 2-1 Simplified Chart of Offsite Dose Calculations 2 Frequency of Catego!:Jl Radionuclides PathwaJl Text Section Rece12tor Code and Limits Calculation 1 Airborne RETS: As required by Non-Noble Child lnhalationb A.1.5 1500 mrem/yr Station Releases: Gases: (Any Organ) Instantaneous Procedure Ground A.1.4.1 Total Body Deposition° lnhalation° A.1.4.2 3 Non-Noble 10CFR50 : Gases: Vegetationd A.1.4.3.1 Monthly and Four Age Groups 7.5 mrem/qtr, 15 mrem/yr Annually Milkd A.1.4.3.2 (All Organs) Meatd A.1.4.3.3 RETS, 10 times 10CFR20 As Required by All Water A.2.2 Not Applicable Appendix B; Table 2; Col. Station 2 Procedure ' - Water" and 3 Non-Noble 10CFR50 : A.2.1 Total Body Liquid Gases 1.5 mrem/qtr 3 mrem/yr Fish1 Monthly Releases: Non-Noble Water" and All Organs (4 3 10CFR50 : A.2.1 Gases Fish1 Age Groups) 5 mrem/qtr 10 mrem/yr Total Body and Non-Noble 40CFR141: When Required Water0 A.6 All Organs Gases 4 mrem/yr by RETS (Adult) ' Total Body 40CFR190: Uranium All releases 25 m rem/vr plus direct 40CFR190: Fuel All radiation from A.4.2 Thyroid (Adult) Annually 75 mrem/yr contained Cycle: sources Any Other Organ 40CFR190: (Adult) 25 mrem/yr Total Body 10CFR72: 25 mrem/vr All releases ISFSI and plus direct 10CFR72: Thyroid (Adult) Uranium All radiation from A.4.2 7 5 m rem/yr Annually Fuel Cycle: ISFSI plus any other radiations Any Other 10CFR72: Critical Organ 25 mrem/yr (Adult) All Licensed Total Effective Total Body and 10CFR20: All Dose A.5 All Organs Annually Operations: 100 mrem/yr Equivalent (Adult) Page 11 of 268

Revision 9 February 27, 2017 Figure 2-1 (Cont'd) Notes for Figure 2-1:

1. Definition: Monthly means at least once per 31 days or once per month. See station RETS for exact requirements.

2. Additional Calculations: In addition to the calculations shown in this figure, monthly projections of doses due to radioactive materials are required for gaseous and liquid effluents. See Sections A.1.6 and A.2.5 of Appendix A.

3. 10 CFR 50 prescribes design objectives not limits.

4. If the air dose is exceeded, doses to the total body and skin are calculated. Total body objectives are 2.5 mrem/qtr and 5.0 mrem/year; the skin dose objectives are 7.5 mrem/qtr and 15 mrem/year.

• a Evaluated at the unrestricted area boundary.

b Evaluated at the location of maximum offsite XJQ. c Ground plane and inhalation pathways are considered to be present at all offsite locations. d Evaluated at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures. If no real pathway exists then a hypothetical cow-milk producer is evaluated at 5 miles in the highest D/Q sector. e Evaluated for the nearest downstream community water supply as specified in Table A-3 of Appendix A. The flow and dilution factors specified in Table F-1 of Appendix Fare used. Evaluated for fish caught in the near-field region downstream of plant using the flow and dilution factors specified in Table F-1 of Appendix F. Page 12 of 268

Revision 9 February 27, 2017 CHAPTER3 EXPOSURE PATHWAYS

3.0 INTRODUCTION

Figure 3-1 illustrates some of the potential radiation exposure pathways to humans due to routine nuclear power station activities. These exposure pathways may be grouped into three categories:

1. Airborne Releases - Exposures resulting from radioactive materials released with gaseous effluents to the atmosphere.

2. Liquid Releases - Exposures resulting from radioactive materials released with liquid discharges to bodies of water.

3. Radiation from Contained Sources - Exposures to radiation from contained radioactive sources.

When performing radiation dose calculations, only exposure pathways that significantly contribute (~ 10%) to the total dose of interest need to be evaluated. The radiation dose from air and water exposure pathways is routinely evaluated. (See Regulatory Guide 1.109, Reference 6.) 3.1 AIRBORNE RELEASES For airborne releases of radioactivity, the NRC considers the following pathways of radiation-exposure of persons:

• External radiation from radioactivity airborne in the effluent plume.
• External radiation from radioactivity deposited by the plume on the ground.
• Ingestion of radioactivity on, or in, edible vegetation (from direct plume deposition).
• Ingestion of radioactivity that entered an animal food product (milk or meat) because the animal ingested contaminated feed, with the contamination due to direct deposition on foliage.
• Inhalation of radioactivity in the plume.

Dose for airborne releases is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures. 3.2 LIQUID RELEASES For liquid releases of radioactivity (Figure 3-1), the NRC considers the following pathways of radiation exposure of persons:

• Ingestion of aquatic food (e.g., fish or invertebrate) obtained from the body of water to which radioactive station effluents are discharged.
• Ingestion (drinking) of potable water contaminated by radioactive liquid effluents discharged from the station.

For the aquatic food pathway, only fish is considered since it is the only significant locally produced aquatic food consumed by humans. Zion Station omits the pathways involving irrigation and animal consumption of contaminated water because these pathways were determined to be insignificant. Zion Station also omits the pathway of radiation exposure from shoreline sediment because this pathway was also found to be insignificant (see Appendix 0, Section 0.3.2). Zion Station has also verified that the dose contribution to people participating in water recreational activities (swimming and boating) is negligible. (See Appendix 0, Table 0-3.) This pathway was not addressed explicitly in Regulatory Guide 1.109. Thus, Zion Station also omits dose assessments for the water recreational activities pathway. Page 13 of 268

Revision 9 February 27, 2017 Periodically, the Illinois Army Corps of Engineers dredges silt and debris from the river beds near Zion Station. As a part of the land use census, Zion Station will determine if the Corps performed dredging within one mile of the discharge point. If so, Zion Station will obtain spoils samples, through its REMP vendor, for analysis. The impact to the offsite dose will be evaluated on a case by case basis and added to the ODCM when applicable. In addition, to assure that doses due to radioactivity in liquid effluents will be ALARA, concentrations will be limited to ten times (1 Ox) the values given in 10CFR20 Appendix 8, Table 2; Column 2. 3.3 RADIATION FROM CONTAINED SOURCES Radioactivity contained within waste containers, including those present at the ISFSI, can produce radiation at offsite locations. Annual offsite radiation doses near Zion Station due to such sources have the potential to challenge annual dose limits to members of the public due to direct radiations. Additions or rearrangements of waste storage locations that may impact the offsite dose through increases to the direct radiation levels are monitored through site administrative processes and procedures. Page 14 of 268

Revision 9 February 27, 2017 Figure 3-1 Radiation Exposure Pathways to Humans Nuclear Power Plant Contained Sources Ingestion of Potable Water Liquid Effluent Releases Ingestion of Aquatic Food Inhalation Ingestion Deposition onto Vegetation Ingestion by Ingestion of Animals Milk and Meat Airborne Effluent Deposition onto Direct Radiation Soil Exposure Direct Radiation Exposure Human Page 15 of 268

Revision 9 February 27, 2017 CHAPTER4 METHODOLOGY

4.0 INTRODUCTION

This chapter provides an introduction to the methodology used at the Zion Station to calculate offsite radiation doses. Additional explanation and details of the methodology are provided in Appendices A and B. Appendix A discusses each dose limit in the RETS and provides the associated assessment equations. Appendix B describes methods used to determine values of parameters included in the equations. 4.1 IMPORTANT CONCEPTS AND PARAMETERS 4.1.1 Dose The dose calculation equations contained in the ODCM are based on two types of exposure to radiation; external and internal exposure. The first type of exposure is that resulting from radioactive sources external to the body (including radiation emanating from an effluent plume, radiation emanating from radioactivity deposited on the ground and radiation emanating from contained sources (also referred to as direct radiation)). Exposure to radiation external to the body only occurs while the source of the radioactivity is present. It should be noted that with the relocation of the fuel from the Spent Fuel Pool to the ISFSI there is no longer an exposure pathway from noble gases which affects the dose impacts at the Zion Station. Although noble gases are no longer included as an effluent from Zion Station activities, the associated information included in this chapter of the ODCM will remain at this time for historical purposes. Internal exposure occurs when the source of radioactivity is inside the body. Radiation can enter the body by breathing air containing the radioactivity, or by consumption of food or drinking water containing radioactivity. Once radioactivity enters the body and becomes internal radiation, a person will continue to receive radiation dose until the radioactivity has decayed or is eliminated by biological processes. The dose from this type of exposure is also termed dose commitment, meaning that the person will continue to receive dose even-though the plume containing the radioactivity has passed by the individual, or even-though the individual is no longer drinking water containing radioactivity. The regulations addressed by the ODCM may require assessment of either type of exposure to radiation or of both types in summation. The term dose is used instead of the term "dose equivalent," as defined by the International Commission on Radiological Units and Measurements (ICRU). When applied to the evaluation of internal deposition of radioactivity, the term "dose," as used in the ODCM, includes the prospective dose component arising from retention in the body beyond the period of environmental exposure, i.e: the dose commitment. The dose commitment is evaluated over a period of 50 years. 4.1.2 Exposure Pathways All of the exposure pathways are discussed in Chapter 3. This section presents the exposure pathways addressed by Zion Station in the ODCM and associated software. For releases of radioactivity in airborne effluents the primary pathways are the following:

• Direct radiation from an effluent plume.
• Direct radiation from radioactivity deposited on the ground by a plume.
• Inhalation of radioactivity in a plume.
• Ingestion of radioactivity that entered the food chain from a plume that deposited radioactivity on vegetation.

For releases of radioactivity in liquid effluents, the exposure pathways considered are human consumption of water and fish. Page 16 of 268

Revision 9 February 27, 2017 When determining total doses, as required by 10CFR20, 10CFR72 and 40CFR190, Zion Station considers exposure to radiation emanating from onsite radioactive waste. 4.1.3 Categories of Radioactivity Radionuclide content of effluent releases from Zion Station can be categorized according to the characteristics of the radionuclides. In evaluating doses associated with a particular pathway, only those categories of radionuclides that significantly contribute to the dose need to be included in the dose calculations (See Section 3.0). The categories of radionuclides considered by Zion Station for each of the airborne pathways are summarized in Table 4-1. Selection of the significant airborne pathways was based on the following:

• The requirements in the RETS (see discussion in Appendix A),
• Applicable regulatory guidance (References 6 and 14), and
• A study of the potential radiological implications of nuclear facilities in the upper Mississippi River basin (Reference 20).

4.1.4 Atmospheric Release Point Classifications The dose impact from airborne release of radioactivity is determined by the height of the release of the effluent plume relative to the ground and by the location of the dose recipient. The height an effluent plume maintains as it travels above the ground is related to the elevation of the release point and to the height of structures immediately adjacent as follows:

• If the elevation of the release point is sufficiently above the height of any adjacent structures, the plume will remain elevated for considerable distances.
• If the elevation of the release point is at or below the heights of adjacent structures, the plume is likely to be caught in the turbulence of the wakes created by wind passing over the buildings. The plume elevation would then drop to ground level.
• If the elevation of the release point is not significantly above the heights of adjacent structures, then the plume may be elevated or at ground level.

For the calculations of this manual, each established release point has been designated as belonging to one of three release point classifications: Stack (or Elevated) Release Points (denoted by the letter Sor subscripts) These are release points approximately twice the height of adjacent solid structures. Releases are treated as elevated releases unaffected by the presence of the adjacent structures. Ground Level Release Points (denoted by the letter G or subscript g) These are release points at ground level or lower than adjacent solid structures. Releases are considered drawn into the downwind wake of these structures and are treated as ground level releases. Vent (or Mixed Mode) Release Points (denoted by the letter V or subscript v) These are release points as high or higher than adjacent solid structures but lower than twice the structure's heights. These releases are treated as a mixture of elevated and ground level releases. The proportion of the release attributed to either elevated or ground level in a vent release is determined by the ratio of stack exit velocity to the wind speed (see Section B.1.2.4 of Appendix B). The definitions of these classifications are based on Regulatory Guide 1.111 (Reference 7). Zion Station has no Stack (Elevated) or Vent (Mixed Mode) release points, therefore; all releases at Zion Station are considered Ground Level. Page 17 of 268

Revision 9 February 27, 2017 4.1.5 Historical Average Atmospheric Conditions The dispersion characteristics of airborne effluents from a nuclear power station are dependent on weather conditions. Meteorological factors that directly affect the concentration of airborne radioactivity in a plume include the following:

• Wind Direction The concentration of radioactivity is highest in the direction toward which the wind is blowing.
• Wind Speed Greater wind speeds produce more dispersion and consequently lower concentrations of radioactivity.
• Atmospheric Turbulence The greater the atmospheric turbulence, the more a plume spreads both vertically and horizontally.

For calculations in this manual, the degree of turbulence is classified by use of seven atmospheric stability classes, designated A (extremely unstable) through G (extremely stable). The seven classes and some of their characteristics are listed in Table C-4 of Appendix C. Meteorological conditions strongly impact the values of various parameters applied in the dose calculations of this manual. These include:

• The Relative Concentration Factors x!Q and gamma-x/Q (Section 4.1.6)
• The Relative Deposition Factor D/Q (Section 4.1. 7)

The bases sections of the Standard Radiological Effluent Technical Specifications (guidance documents NUREGs 0472, 0473, 1301and1302) and the RETS specify that dose calculations be based on "historical average atmospheric conditions". Therefore, this manual provides values for the above parameters that are based on Zion Station historical average meteorological conditions. These values were obtained by averaging hourly values of the parameters over a long-term, several-year period of record. The averaging period was based on calendar years in order to avoid any bias from weather conditions associated with any one season. The period of record is identified in each of the tables providing the values (see Appendix F). 4.1.6 Relative Concentration Factors x/Q and Gamma-x/Q A person immersed in a plume of airborne radioactivity is exposed to radiation from the plume and may also inhale some of the radioactivity from the plume. The concentration of radioactivity in air near the exposed person must be calculated to adequately evaluate doses resulting from any inhalation. The relative concentration factor x!Q (referred to as "chi over Q") is used to simplify these calculations. x/Q is the concentration of radioactivity in air, at a specified location, divided by the radioactivity release rate. x!Q has the following units: Units of x/Q =(µCi/m 3

                          ) I (µCi/sec) =sec/m  3 Zion Station values of x!Q are provided in Table F-5 of Appendix F. These values are based on historical average atmospheric conditions (see Section 4.1.5). For each of the release point classifications (eg. stack, vent and ground level) and for the 16 compass-direction sectors (N, NNE, etc.), Table F-5 provides the maximum value of x!Q for locations at or beyond the unrestricted area boundary.

The value of x!Q for each sector reflects the fraction of time that the wind blew into that sector and the distribution of wind speeds and atmospheric stability classes during that time. Note that the value would be zero if the wind never blew into the sector. Page 18 of 268

Revision 9 February 27, 2017 The gamma-x/Q provides a simplified method of calculating gamma air dose and dose rates for a finite and/or elevated plume. It is used in place of the semi-infinite plume model that tends to underestimate gamma air dose for elevated plumes. Use of the gamma-X/Q also corrects for the tendency of the semi-infinite plume model to overestimate gamma air dose for mixed mode and ground level releases. The methodologies for determining x!Q and gamma-x/Q are discussed in detail in Section B.3 of Appendix B. 4.1.7 Relative Deposition Factor D/Q As a plume travels away from its release point, portions of the plume may touch the ground and deposit radioactivity on the ground and/or on vegetation. Occurrences of such deposition are important to model since any radioactivity deposited on the ground or on vegetation may directly expose people and/or may be absorbed into food products which can ultimately be ingested by people. The relative deposition factor is used to simplify the dose calculations for these pathways. The relative deposition factor D/Q is the rate of deposition .of radioactivity on the ground divided by the radioactivity release rate. Its value 'was determined for specific conditions. In this manual it has the following units: 2 Units of D/Q = [(pCi/sec)/m ] I (pCi/sec) = 1/m2 The values of D/Q are affected by the same parameters that affect the values of x/Q: release characteristics, meteorological conditions and location (see Section 4.1.6). Zion Station values of D/Q are provided in Appendix F Tables F-5 and F-6. These values are based on historical average atmospheric conditions (see Section 4.1.5). For each release point classification and for each of the 16 compass-direction sectors (N, NNE, etc.), Table F-5 provides the maximum value of D/Q for locations at or beyond the unrestricted area boundary. In Table F-6, values of D/Q are given for the locations of the nearest milk and meat producers within 5 miles of Zion Station. The methodology for determining D/Q is discussed in Section B.4 of Appendix B. 4.1.8 Dose Factors Various dose factors are used in this manual to simplify the calculation of radiation doses. These factors are listed in Table 4-2. Definitions of these factors are given in the remainder of this chapter. Methods of determining their values are addressed in Appendix B. 4.2 AIRBORNE RELEASES 4.2.1 Gamma Air Dose The term 'gamma air dose' refers to the component of dose absorbed by air resulting from the absorption of energy from photons emitted during nuclear and atomic transformations, including gamma rays, x-rays, annihilation radiation, and Bremsstrahlung radiation (see footnote on page 1.109-19 of Regulatory Guide 1.109). The noble gas dose factors of Reg. Guide 1.109, Table B-1 are based upon assumption of immersion in a semi-infinite cloud. For ground level and mixed mode releases this tends to overestimate the gamma air dose arising from a plume that is actually finite in nature. For elevated releases, the Reg. Guide 1.109 noble gas dose factors will underestimate exposure as they consider only immersion and not that portion of exposure arising from sky shine. At distances close in to the point of elevated release, the ground level concentration as predicted by xlQ will be essentially zero. In such a case, the sky shine component of the exposure becomes significant and must be considered. The gamma-x/Q provides a simplified method of calculating gamma air dose and dose rates for a finite and/or elevated plume. The methodology of Reg. Guide 1.109, Section C.2 and Appendix B provide the methodology for calculating finite cloud gamma air dose factors from which the gamma-x/Q values can be derived. Section B.5 addresses the calculation of these dose factors. Page 19 of 268

Revision 9 February 27, 2017 Three gamma-x/Q values are defined: (x/Q)5 Y, (x/Q)/ and (x/Q) 9Y for stack, vent and ground level releases, respectively. Section 8.3.5 addresses the calculation of the gamma-x/Q values. 4.2.1.1 Finite Cloud Gamma Air Dose Factor The finite cloud gamma air dose factor is determined by calculating the gamma dose rate to air (at a specific location and corresponding to a given release rate) and dividing that dose rate by the corresponding release rate: Finite Cloud Gamma Air Dose Factor= [(mrad/yr)/(µCi/sec)] The methodology for this calculation is discussed in Section 8.5 of Appendix 8. The calculation is complex because the dose rate at any given point is affected by the radioactivity concentration and distance. Calculation of the finite cloud gamma air dose factor takes into consideration release characteristics, meteorological conditions and location (see Section 4.1.6). Additionally, the value is affected by radiological parameters: the distribution of energies and intensities for gamma emissions from each specific radionuclide and the photon attenuation characteristics of air. In the ODCM, station-specific values of gamma dose factors are provided for Zion Station in Appendix F, Table F-7. These values are based on historical average atmospheric conditions (see Section 4.1.5). For the release point classification and for ~ach of the 16 compass-direction sectors, Table F-7 provides the maximum value of the gamma air dose factor for noble gas radionuclides at the unrestricted area boundary. The value includes a correction for radioactive decay during transport of the radionuclide from the release point to the dose calculation location. 4.2.1.2 Semi-Infinite Cloud Gamma Air Dose Factor The semi-infinite cloud gamma dose factor is the gamma air dose rate divided by the concentration of radioactivity in air at the dose calculation location. Values of these gamma dose factors are radionuclide specific and are provided in Appendix C, Table C-9. The semi-infinite cloud gamma dose factor is used in conjunction with gamma-x/Q to calculate noble gas gamma air dose and dose rate for elevated and finite noble gas plumes. The gamma-xfQ is defined such that for a given finite cloud the semi-infinite cloud methodology will yield the same gamma air dose as the finite cloud methodology. 4.2.2 Beta Air Dose The term 'beta air dose' refers to the component of dose absorbed by air resulting from the absorption of energy from emissions of beta particles, mono-energetic electrons and positrons during nuclear and atomic transformations (see the footnote on Page 1.109-20 of Regulatory Guide 1.109). The Beta Air Dose Factor The beta air dose factor is the beta air dose rate divided by the concentration of radioactivity in air at the dose calculation location. Values of the beta air dose factor are radionuclide specific and are provided in Appendix C Table C-9. 4.2.3 Total Body Dose and Dose Rate Total Body Dose Equation A-3 of Appendix A is used to calculate dose to the total body from noble gas radionuclides released in gaseous effluents. The total body dose equation is similar to that used to calculate gamma air dose (Equation A-1 of Appendix A). Page 20 of 268

Revision 9 February 27, 2017 Total Body Dose Rate Equation A-5 of Appendix A is used to calculate dose rate to the total body. The assumptions used for this equation are the same as those used in the calculation of total body dose (Equation A-3 of Appendix A) except that any shielding benefit (dose attenuation) provided by residential structures is not applied. Since the calculation is for the maximum instantaneous dose rate, the dose recipient may be out of doors when exposed and would not be shielded from the exposure by any structural material. The Total Body Dose Factor The total body dose factor is the total body dose rate divided by the radioactive release rate. Values for the total body dose factor are site specific and are provided in Table C-9 of Appendix C. 4.2.4 Skin Dose and Dose Rate Skin Dose Equation A-4 of Appendix A is used to calculate dose to skin from noble gas radionuclides released in gaseous effluents. The skin dose is the summation of dose to the skin from beta and gamma radiation. The equation for beta dose to skin is similar to that used to calculate beta dose to air (Equation A-2 of Appendix A) except that beta skin dose factors are used instead of beta air dose factors. The beta skin dose factor differs from the beta air dose factor by accounting for the attenuation of beta radiation by the dead layer of skin. The dead layer of skin is not susceptible to radiation damage and therefore is not of concern. The beta dose to the skin from non-noble gases is insignificant and is not calculated for the reason described in Section 4.1.3. When calculating the beta contribution to skin dose, no reduction is included in the calculations due to shielding provided by occupancy of residential structures. The equation for gamma dose to skin is similar to that used to calculate gamma dose to air except for the following:

• Equation A-4 of Appendix A includes a unit's conversion factor 1.11 rem/rad to convert from units of gamma air dose (rad) to units of tissue dose equivalent (rem).
• Equation A-4 of Appendix A includes a dimensionless factor of 0. 7 to account for the shielding due to occupancy of residential structures.

Equation A-4 of Appendix A uses gamma air dose factors not gamma total body dose factors. When calculating gamma dose to skin, no reduction is applied for the attenuation of radiation due to passage through body tissue (dead layer of skin). Skin Dose Rate Equation A-6 of Appendix A is used to calculate dose rate to skin. The assumptions are the same as those used in the calculation of skin dose (Equation A-4 of Appendix A) except that no credit is taken for shielding of gamma radiation by residential structures. The dose recipient may be outdoors when exposed and the maximum instantaneous dose rate is of concern. The Skin Dose Factor Values of the beta air dose factors and skin dose factors are nuclide specific and are provided in Table C-9 of Appendix C for 15 noble gas radionuclides. 4.2.5 Ground Radiation Equations A-7 and A-8 of Appendix A are used to calculate the total body dose due to non-noble gas radionuclides released in gaseous effluents and deposited on the ground. Page 21 of 268

Revision 9 February 27, 2017 Comment Note that if there is no release of radionuclide i during a given time period, then the deposition rate is zero, the ground plane concentration is zero and the resulting dose due to ground deposition is zero. If there is a release of radionuclide i, the ground concentration is computed as if that release had been occurring at a constant rate for the ground deposition time period. The Ground Plane Dose Conversion Factor The ground plane dose conversion factor is the dose rate to the total body per unit of radioactivity concentration on the ground. Values of the ground plane dose conversion factor that are calculated by assuming constant concentration over an infinite plane are provided for various radionuclides in Table C-10 of Appendix C. 4.2.6 Inhalation Dose Radioactivity from airborne releases of particulate and tritium can enter the body through inhalation. Equations A-7 and A-9 of Appendix A are used to calculate dose commitment to the total body or organs due to inhalation of non-noble gas radionuclides released in gaseous effluents. The Inhalation Dose Factor Values for the inhalation dose commitment factor are nuclide specific and are taken from Reg. Guide 1.109 (Reference 6) Tables E-7, 8, 9 and 10. These tables include data for four age groups (adult, teenager, child and infant) and seven body organs. Dose Rate The inhalation dose rate is the rate at which dose is accrued by an individual breathing contaminated air. Equation A-16 of Appendix A is used to calculate dose commitment rate to an organ due to inhalation of non-noble gas radionuclides. The assumptions are the same as used in the calculation of inhalation dose. The dose rate is determined for the child age group in accordance with the guidance found in NUREGs 0472, 0473, 1301and1302 (References 2, 3, 105 and 106). 4.2.7 Ingestion Airborne releases of particulate and tritium can enter the food chain through deposition on vegetation. The radioactivity can be ingested by humans who consume the vegetation or who consume products (e.g., milk or meat) of animals who have fed on the contaminated vegetation. Zion Station may consider the following ingestion pathways:

• Vegetables
• Milk
• Meat Equations A-7 and A-10 through A-15 of Appendix A are used to calculate the dose due to ingestion of food containing non-noble gas radionuclides released in gaseous effluents. Dose is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures.

Values of the ingestion dose commitment factors are taken from Reg. Guide 1.109 Tables E-11, 12, 13 and 14. These tables include data for four age groups and seven organs. The equations used for radioactivity concentration on vegetation and in milk, and meat are discussed in Appendix A. Page 22 of 268

Revision 9 February 27, 2017 4.3 LIQUID RELEASES The evaluation of dose due to releases of radioactivity in liquid effluents is required to confirm compliance with the provisions of RETS related to 10CFR50 Appendix I. The ODCM, Section 3.2 and Figure 3-1 list some of the pathways by which radioactivity in liquid effluents can impact man. The pathways used by Zion Station to calculate dose from liquid effluents are ingestion by drinking water and by eating fish from the body of water receiving station liquid discharges. Zion Station obtains the dose commitment due to radioactivity in liquid effluent releases by summing the dose commitments from the drinking water and fish pathways depending upon their presence. Equations A-17 through A-20 of Appendix A are used to calculate dose for the member of the public due to consumption of drinking water and fish. The radioactivity concentration in water is obtained by dividing the quantity of radioactivity released by the volume of water in which the release is diluted. The result can be modified by a factor to represent any additional dilution that might occur. The radioactivity concentration in fish is the product of the radioactivity concentration in water and a bioaccumulation factor. The dilution factors for fish may be different from those for water. (The fish may be caught at a location different from where drinking water is drawn.) The bioaccumulation factor accounts for the fact that the quantity of radioactivity in fish can build up with time to a higher value relative to the concentration of the radioactivity in the water they consume. The bioaccumulation factor is the equilibrium ratio of the concentration of radionuclide i in fish to its concentration in water. The same values are used for the bio-accumulation factor at Zion Station. These values are provided in Appendix C, Table C-8. 4.4 CONTAINED SOURCES OF RADIOACTIVITY In addition to the total body, skin and single 'organ dose assessments previously described, an additional assessment is required. The additional assessment addresses radiation dose due to radioactivity contained within the nuclear power station and its structures. 4.4.1 Deleted 4.4.2 Onsite Radioactive Waste and Radioactive Material Storage Facilities Low-level radioactive waste and radioactive material may be stored at Zion Station in the following types of locations:

• Concrete Rad Vaults
• Miscellaneous Shipping Containers
• Existing and temporary support structures Spent Fuel is stored at the Independent Spent Fuel Storage Installation. Administrative controls are implemented by Zion Station to ensure compliance to applicable regulations. The impact to the offsite dose from contained sources shall be documented in site Technical Support Documents. In addition, a 10CFR50.59 analysis may be required for selected radwaste storage facilities.

4.5 TOTAL DOSE REQUIREMENTS 4.5.1 Total Effective Dose Equivalent Limits; 10CFR20 and 40CFR190 10CFR20 requires compliance to dose limits expressed as "Total Effective Dose Equivalent" (TEDE). Although annual dose limits in 10CFR20 are now expressed in terms of TEDEs, 40CFR190 limits remain stated as organ dose. The NRC continues to require 10CFR50 Appendix I and 40CFR190 doses to be reported in terms of organ dose and not TEDE. Due to the fact that organ dose limits set forth in 40CFR190 are substantially lower than those of 10CFR20 (25 mrem/yr vs. 100 mrem/yr}, the NRC has stated that demonstration of compliance with the dose limits in 40CFR190 will be deemed as demonstration of compliance with the dose limits of 10CFR20 for most facilities (Reference 104).

                                                                                                . Page 23 of 268

Revision 9 February 27, 2017 In addition to compliance with 40CFR190, it may be necessary for a nuclear power plant to address dose from on-site activity by members of the public. 4.5.2 Total Dose For Uranium Fuel Cycle Zion Station is required to determine the total dose to a member of the public due to all uranium fuel cycle sources in order to assess compliance with 40CFR 190 as part of demonstrating compliance with 10CFR20. The total dose for the uranium fuel cycle is the sum of doses due to radioactivity in airborne and liquid effluents and the doses due to direct radiation from contained sources at the Zion Station. When the evaluation of total dose is required for the Zion Station, the following contributions are summed:

• Doses due to airborne and liquid effluents.
• Doses due to liquid effluents from nuclear power stations upstream
• Doses due to any onsite radioactive waste storage facilities; if applicable.

Section A.5.2 of Appendix A discusses the details of evaluations. Page 24 of 268

Revision 9 February 27, 2017 Table 4-1 Radionuclide Types Considered For Airborne Effluent Exposure Pathways External Radiation Internal Radiation Category Plume Ground Inhalation Ingestion Noble Gases X Tritium (H-3) x x Particulatea x x x a Only particulates with half-life greater than 8 days need be considered. For details, see Generic Letter 89-01 and the RETS. Page 25 of 268

Revision 9 February 27, 2017 Table 4-2 Radiation Dose Factors Name and S~mbol Units Definition Table Gamma Air Dose mrad/yr Gamma air dose rate per RG1.109 Factor per unit of radioactivity Table B-1, 3 M; µCi/m concentration for Column 4 radionuclide i. Total Body Dose mrem/yr Total body dose rate per RG1.109 Factor: per unit of radioactivity Table B-1, 3 K; µCi/m concentration for Column 5 radionuclide i. Beta Air Dose mrad/yr Beta air dose rate per RG 1.109 Factor N; per unit of radioactivity Table B-1, 3

                                     µCi/m                  concentration for                          Column 2 radionuclide i.

Beta Skin Dose mrem/yr Beta skin dose rate per RG 1.109 Factor L; per unit of radioactivity Table B-1, 3

                                     µCi/m                  concentration for                          Column 3 radionuclide i.

Ground Plane Dose mrem/hr Dose rate per unit RG 1.109 Conversion Factor per of ground radioactivity Table E-6, 2 DFG; pCi/m concentration for Column 2 radionuclide i. Inhalation Dose mrem Dose to organ j of age RG 1.109 Commitment Factor per group a per unit of Tables; DFA;ja pCi radioactivity inhaled E-7, E-8, for radionuclide i. E-9, E-10 (see Note 1) Ingestion Dose mrem Dose to organ j of age RG 1.109 Commitment Factor per group a per unit of Tables; DFliia pCi radioactivity ingested E-11, E-12, for radionuclide i. E-13, E-14 (see Note 1) Note 1: Dose assessments for 10CFR20, 10CFR72 and 40CFR190 compliance are made for an adult only. Dose assessments for 10CFR50 Appendix I are made using dose factors of Regulatory Guide 1.109 (Reference 6) for all age groups. Page 26 of 268

Revision 9 February 27, 2017 CHAPTERS MEASUREMENT

5.0 INTRODUCTION

Zion Station has two measurement programs associated with offsite dose assessment:

• Measurement of releases of radioactivity at the site.
• Measurement of levels of radiation and radioactivity in the environs surrounding the site.

5.1 EFFLUENT AND PROCESS MONITORING Radioactivity in liquid and gaseous effluents is measured in order to provide data for calculating radiation doses and radioactivity concentrations in the environment. Measurement of effluent radioactivity is required by 10CFR20.1302 and 10CFR50. The RETS provides detailed requirements for monitoring the effluents from the Zion Station. Relevant Regulatory Guides are 1.21 (Reference 4) and 4.15 (Reference 13). Chapter 10 of the ODCM includes brief descriptions of the systems. The RETS requires submission to the NRC of reports of effluent radioactivity releases and environmental measurements. 5.2 METEOROLOGICAL MONITORING A historical average of meteorological measurements is used at the Zion Station in lieu of real time monitoring. 5.3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) Zion Station has a REMP that provides representative measurements of radiation and radioactive material in the environment. The program provides verification that measurable radiological impacts from the station on the environment are within expectations derived from effluent measurements and calculations. The REMP is required by 10CFR50 (see Appendix I, Sections IV.B.2 and IV.B.3). General requirements of the program are prescribed in Zion Stations RETS and more precise details (such as specific monitoring locations) are specified in the ODCM Chapter 11. 5.3.1 lnterlaboratory Comparison Program The laboratory which performs the REMP analyses is required by the RETS to participate in an interlaboratory comparison program. The purpose is to provide an independent check on the laboratory's analytical procedures and to alert it to potential problems (e.g. accuracy). In order to assess the measurements of radioactivity in environmental media, an independent agency supplies participating laboratories with samples of environmental media containing unspecified amounts of radioactivity. The laboratories measure the radioactivity concentrations and report the results to the agency. At a later time, the agency informs the participating laboratories of the actual concentrations and associated uncertainties. Any significant discrepancies are investigated by the participating laboratories. A similar process is used to assess measurements of enviro.nmental radiation by passive thermoluminescent dosimeters. Page 27 of 268

Revision 9 February 27, 2017 CHAPTERS IMPLEMENTATION OF OFFSITE DOSE ASSESSMENT PROGRAM 6.1 NUCLEAR POWER STATION Zion Station staff is responsible for effluent monitoring. The staff determines effluent radioactivity concentration and flow rate. These data are used to determine the radioactivity release information required for the Radioactive Effluent Release Report and to perform monthly calculations and projections of offsite radiation dose. Zion Station staff is also responsible for control of effluent radioactivity. Procedures are implemented for determining, calculating and implementing monitor setpoints. Liquid radwaste treatment systems and portable ventilation exhaust filtration systems are utilized when appropriate. Zion Station staff implements the Process Control Program (PCP) for solid radwaste and measures tank radioactivity. Zion Station staff maintains instrumentation associated with these activities and demonstrates operability of the instrumentation in accordance with the surveillance requirements of the RETS. In the event that any RETS requirements are violated, Zion Station staff is responsible for taking one of the actions allowed by the RETS and issuing any required reports to the NRC. Zion Station assembles and distributes the Annual Radioactive Effluent Release Report. 6.2 REMP CONTRACTOR The radiological environmental contractor collects environmental samples and performs radiological analyses as specified in the Zion Station REMP (see ODCM Chapters 11 and 12). The contractor issues reports of results to appropriate points of contact. The contractor participates in an interlaboratory comparison program and reports results in the Annual Radiological Environmental Operating Report. The contractor performs the annual land use census and assembles the Annual Radiological Environmental Operating Report. Page 28 of 268

Revision 9 February 27, 2017 CHAPTER7 REFERENCES

1. Deleted

2. U.S. Nuclear Regulatory Commission, Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors, NUREG-0472, Rev. 3, Draft, January 1983 (frequently revised).

4. U.S. Nuclear Regulatory Commission, Measuring. Evaluating. and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants. Regulatory Guide 1.21. Revision 1, June 1974.

5. U.S. Nuclear Regulatory Commission, Onsite Meteorological Programs, Regulatory Guide 1.23, Safety Guide 23, February 17, 1972.

6. U.S. Nuclear Regulatory Commission, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50 Appendix I, Regulatory Guide 1.109, Rev. 1, October 1977.

7. U.S. Nuclear Regulatory Commission, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Regulatory Guide 1.111, Rev. 1, July 1977.

8. U.S. Nuclear Regulatory Commission, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors, Regulatory Guide 1.112, Rev. 0-R, April 1976; reissued May 1977.

9. U.S. Nuclear Regulatory Commission, Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, Regulatory Guide 1.113, Rev. 1, April 1977.

10. U.S. Nuclear Regulatory Commission, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants, Regulatory Guide 4.1, Rev. 1, April 1975.

11. U.S. Nuclear Regulatory Commission, Preparation of Environmental Reports for Nuclear Power Stations, Regulatory Guide 4.2, Rev. 2, July 1976.

12. U.S. Nuclear Regulatory Commission, Environmental Technical Specifications for Nuclear Power Plants, Regulatory Guide 4.8, Rev. 1, December 1975. (See also the related Radiological Assessment Branch Technical Position, Rev. 1, November 1979.)

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

14. U.S. Nuclear Regulatory Commission, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, edited by J. S. Boegli et al. NUREG-0133, October 1978.

15. U.S. Nuclear Regulatory Commission, XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations, J. F. Sagendorf et al.

NUREG/CR-2919, PNL-4380, September 1982.

16. U.S. Nuclear Regulatory Commission, Radiological Assessment, edited by J. E. Till and H. R.

Meyer, NUREG/CR-3332, ORNL-5968, September 1983.

17. U.S. Nuclear Regulatory Commission, Standard Review Plan, NUREG-0800, July 1981.

Page 29 of 268

Revision 9 February 27, 2017

18. U.S. Atomic Energy Commission, Meteorology and Atomic Energy 1968, edited by D. H. Slade, TID-21940, July 1968.

19. U.S. Atomic Energy Commission, Plume Rise, G. A. Briggs, TID-25075, 1969.

20. U.S. Atomic Energy Commission, The Potential Radiological Implications of Nuclear Facilities in the Upper Mississippi River Basin in the Year 2000, WASH 1209, January 1973.

21. U.S. Atomic Energy Commission, HASLProcedures Manual, Health and Safety Laboratory, HASL-300 (revised annually).

22. U.S. Department of Energy, Models and Parameters for Environmental Radiological Assessments, edited by C. W. Miller, DOE/TIC-11468, 1984.

23. U.S. Department of Energy, Atmospheric Science and Power Production, edited by D.

Randerson, DOE/TIC-27601, 1984.

24. U.S. Environmental Protection Agency, Workbook of Atmospheric Dispersion Estimates, D. B.

Turner, Office of Air Programs Publication No. AP-26, 1970. *

25. U.S. Environmental Protection Agency, 40CFR190 Environmental Radiation Protection Requirements for Normal Operations of Activities in the Uranium Fuel Cycle, Final Environmental Statement, EPA 520/4-76-016, November 1, 1976.

26. U.S. Environmental Protection Agency, Environmental Analysis of the Uranium Fuel Cycle, EPA-520/9-73-003-C, November 1973.

27. American Society of Mechanical Engineers, Recommended Guide for the Prediction of the Dispersion of Airborne Effluents, 1973.

28. Eisenbud, M., Environmental Radioactivity, 3rd Edition, (Academic Press, Orlando, FL, 1987).

29. Glasstone, S., and Jordan, W. H., Nudear Power and Its Environmental Effects (American Nuclear Society, LaGrange Park, IL, 1.980).

30. International Atomic Energy Agency, Generic Models and Parameters for Assessing the Environmental Transfer of Radionucli~es from Routine Releases, Safety Series, No. 57, 1982.

31. National Council on Radiation Protection and Measurements, Radiological Assessment:

Predicting the Transport, Bioaccumulation. and Uptake by Man of Radionuclides Released to the Environment, NCRP Report No. 76, March 15, 1984.

32. Ame~ican National Standards Institute, Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities, ANSI N13.1-1969, February 19, .1969.

33. Institute of Electrical and Electronics Engineers, Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N 13.10-1974, September 19, 1974.

34. American National Standards Institute, Testing and Procedural Specifications for Thermoluminescence Dosimetry (Environmental Applications), ANSI N545-1975, August 20, 1975.

35. American Nuclear Insurers, Effluent Monitoring, ANl/MAELU Engineering Inspection Criteria for*

Nuclear Liability Insurance, Section 5.1, Rev. 2, October 24, 1986.

36. American Nuclear Insurers, Environmental Monitoring, ANl/MAELU Engineering Inspection Criteria for Nuclear Liability Insurance, Section 5.2, Rev. 1, March 23, 1987.

Page 30 of 268

Revision 9 February 27, 2017

37. American Nuclear Insurers, Environmental Monitoring Programs, ANl/MAELU Information Bulletin 86-1, June 9, 1986.

38. Cember, H., Introduction to Health Physics, 2nd Edition (Pergamon Press, Elmsford, NY 1983).

39. Deleted

40. Deleted

41. U.S. Nuclear Regulatory Commission, Branch Technical Position, Radiological Assessment Branch, Revision 1, November 1979. (This is a branch position on Regulatory Guide 4.8.)

42. Deleted

43. U.S. Nuclear Regulatory Commission, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWR-GALE Code),

NUREG-0017, April 1976.

44. Deleted

45. Deleted

46. Deleted

47. Deleted

48. Deleted

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

50. International Commission on Radiological Protection, Report of Committee Two on Permissible Dose for Internal Radiation, Recommendations of the International Commission on Radiological Protection, ICRP Publication 2, 1959.

51. U.S. Nuclear Regulatory Commission, Age-Specific Radiation Dose Commitment Factors for a One-Year Chronic Intake, Battelle Pacific Northwest Laboratories, NUREG-0172, 1977.

52. W. C. Ng, Transfer Coefficients for Prediction of the Dose to Man via the Forage-Cow-Milk Pathway from Radionuclides Released to the Biosphere, UCRL-51939.

53. E. C. Eimutis and M. G. Konicek, Derivations of Continuous Functions for the Lateral and Vertical Atmospheric Dispersion Coefficients, Atmospheric Environment 6, 859 ( 1972).

54. D. C. Kocher, Editor, Nuclear Decay Data for Radionuclides Occurring in Routine Releases from Nuclear Fuel Cycle Facilities, ORNUNUREG/TM-102, August 1977.

55. R. L. Heath, Gamma-Ray Spectrum Catalog, Aerojet Nuclear Co., ANCR-1000-2, third or subsequent edition. *

56. S. E. Thompson, Concentration Factors of Chemical Elements in Edible Aquatic Organisms, UCRL-50564, Rev. 1, 1972.

57. U.S. Nuclear Regulatory Commission, Instruction Concerning Risks from Occupational Radiation Exposure, Regulatory Guide 8.29, July 1981.

58. Deleted

59. "Verification of Environmental Parameter Used for Commonwealth Edison Company's Offsite Dose Calculations," NUS Corporation, 1988.

Page 31 of 268

Revision 9 February27, 2017

60. Deleted

61. Deleted

62. Deleted

63. Deleted

64. "Verification of Environmental Parameter Used for Commonwealth Edison Company's Offsite Dose Calculations," NUTECH Engineering Group, 1992. -

65. Deleted

66. Deleted

67. Deleted

68. Deleted

69. Deleted

70. D. C. Kocher, Radioactivity Decay Data Tables, DOE/TIC-11026, 1981.

71. J. C. Courtney, A Handbook of Radiation Shielding Data, ANS/SD-76/14, July 1976.

72. Commonwealth Edison Company, Information Relevant to Keeping Levels of Radioactivity in Effluents to Unrestricted Areas As Low As Reasonably Achievable. Zion Station. Units 1 and 2, June 4, 1976.

73. Deleted

74. Deleted

75. Sargent & Lundy, METWRSUM, S&L Program Number 09.5.187-1.0.

76. Sargent & Lundy, Comments on CECo ODCM and List of S&L Calculations, Internal Office Memorandum, P. N. Derezotes to G. R. Davidson, November 23, 1988.

77. Sargent & Lundy, AZAP. A Computer Program to Calculate Annual Average Offsite Doses from Routine Releases of Radionuclides in Gaseous Effluents and Postaccident X/Q Values, S&L Program Number 09.8.054-1. 7.

78. National Oceanic and Atmospheric Administration, A Program for Evaluating Atmospheric Dispersion from a Nuclear Power Station, J. F. Sagendorf, NOAA Technical Memorandum ERL ARL-42, Air Resources Laboratory, Idaho Falls, Idaho, May 1974.

79. G. P. Lahti, R. S. Hubner, and J.C. Golden, Assessment of Gamma-Ray Exposures Due to Finite Plumes, Health Physics41, 319 (1981).

80. National Council of Radiation Protection and Measurements, Ionizing Radiation Exposure of the Population of the United States. NCRP Report No. 160, March 3, 2009.

81. Sargent & Lundy, Nuclear Analysis and Technology Division, Calculation No. ATD-0090, Revision 0.

82. Deleted

83. Deleted

84. Deleted Page 32 of 268

Revision 9 February 27, 2017

85. U.S. Environmental Protection Agency, Environmental Analysis of the Uranium Fuel Cycle. Part I - Fuel Supply, EPA-520/9-73-003-8, October 1973.

86. U.S. Nuclear Regulatory Commission, Final Generic Environmental Statement on the Use of Recycle Plutonium in Mixed Oxide Fuel in Light Water Cooled Reactors, NUREG-0002, August 1976.

87. U.S. Nuclear Regulatory Commission, Demographic Statistics Pertaining to Nuclear Power Reactor Sites, NUREG-0348, Draft, December 1977.

88. Nuclear News 31, Number 10, Page 69 (August 1988).

89. Deleted

90. U.S. Nuclear Regulatory Commission, Generic Letter 89-01, "Guidance For The Implementation of Programmatic Controls For RETS In The Administrative Controls Section of Technical Specifications and the Relocation of Procedural Details of Current RETS to the Offsite Dose Calculation Manual or Process Control Program", January 1989.

91. Deleted

92. Deleted

93. Deleted

94. Deleted.

95. U.S. Nuclear Regulatory Commission, Standards for Protection Against Radiation (10CFR20).

96. U.S. Nuclear Regulatory Commission, Licensing of Production and Utilization Facilities (10CFR50).

97. Federal Register, Vol. 57, No. 169, Monday, August 31, 1992, page 39358.

98. Miller, Charles W., Models and Parameters for Environmental Radiological Assessments, U.S.

Dept. of Energy, DE8102754, 1984, pages 32, 33, 48, and 49. *

99. Kocher, D. C., "Dose-Rate Conversion Factors For External Exposure To Photons and Electrons", Health Physics Vol. 45, No. 3 (September), pp. 665-686, 1983.

100. U.S. Department of Health, Education and Welfare Public Health Service, Radiological Health Handbook, January 1970. 101. Deleted 102. Deleted 103. U.S. Nuclear Regulatory Commission, Generic Letter 79-041, September 17, 1979. 104. Federal Register, Vol. 56, No. 98, Tuesday, May 21, 1991, page 23374, column 3. 105. U.S. Nuclear Regulatory Commission, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, NUREG-1301, April 1991. 106. Deleted 107. U.S. Nuclear Regulatory Commission, LADTAP II -Technical Reference and Users Guide, NUREG-4013, April 1986. 108. NRC ISG-13 Rev. 0, Spent Fuel Project Office Interim Staff Guidance - 13 Real Individual, May 17,2000 Page 33 of 268

Revision 9 February 27, 2017 CHAPTERS Deleted Page 34 of 268 .

Revision 9 February 27, 2017 CHAPTER9 Deleted Page 35 of :268

Revision 9 February 27, 2017 CHAPTER10 RADIOACTIVE EFFLUENT TREATMENT SYSTEM AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Description During decommissioning, the principal release points for potentially radioactive airborne effluents are the debris from: The auxiliary building, the Fuel Handling Building, U1 and U2 containments via equipment openings or open air demolition. Each location is classified as a ground level release. Portable air filtration units are used as needed to maintain acceptable ambient air temperatures for equipment operation and personnel habitability. They provide the bulk exhaust flow for ease of effluent control, sampling, and quantification in conjunction with other samples taken at various release points. 10.1.1.1 Deleted 10.1.2 Radiation Monitors Pertinent information is provided in the DSAR and Section 10.4. 10.1.2.1 Auxiliary Building Open Air Demolition Aux building open air demolition airborne particulates are sampled with portable samples as required during active demolition activities .. 10.1.2.2 Containment Active Decommissioning Air Sampling A 30,000 CFM maximum flow portable filtered ventilation units are used to maintain habitability while performing demolition of U1 and U2 containment and associated tents .. 10.1.3 to 10.1.3.4 Deleted Page ?6 of 268

Revision 9 February 27, 2017 10.1.3.5 HVAC Flow Rates The maximum design flow capacity for portable ventilation units will be used to estimate dose and release rates from the ventilation units. 10.2 LIQUID RELEASES 10.2.1 System Description The liquid waste system description is provided in the DSAR and Section 10.4. The liquid radwaste treatment system is designed and installed to allow for a reduction if needed, in the concentration of radioactive liquid effluents by filtration, providing for retention or holdup and/or providing for treatment by demineralizers. The overall purpose is to ensure releases to the lake do not exceed any concentration release limit and liquid effluent releases to the public are ALARA. 10.2.1.1 Lake Release Tanks There are three tanks used as Lake Release Tanks (Release/Storage Tank A and B, and Clean Water Tank). Two of which can receive unprocessed liquid waste. All three tanks are capable of sending and receiving water from the liquid effluent processing system and discharging water to Lake Michigan. ' 10.2.1.2 Deleted per Revision 7 10.2.2 Radiation Monitors 10.2.2.1 Lake Release Tank Monitors If the option is used, ORT-PR04 monitors releases from the Lake Release Tanks. On high alarm, the monitor automatically initiates closure of a valve to prevent further releases. The monitor and valve are located in an arrangement that allows closure prior to exceeding release limits. The monitor setpoints are found by solving Equation 10-5 for release setpoint P. Available information is provided in the DSAR and Section 10.4.

                                                                                                   ~age 37 of 268

Revision 9 February 27, 2017 10.2.3 Alarm and Trip Setpoints 10.2.3.1 Setpoint Calculation Alarm and trip setpoint of liquid effluent monitor at the principal release points is established to ensure that the concentration limits of the QAPP and 10 CFR 20 are not exceeded in the unrestricted area. The monitor setpoint is found by solving Equation 10-5 for a conservative mixture of radionuclides found in liquid effluents. (10-5) P Release Setpoint [µCi/ml] The alarm setpoint for radioactivity to be released in liquid effluents. Cmpc Maximum Permissible Concentration [µCi/ml] Fd Dilution Flow Rate [gpm] The flow rate of the radwaste dilution stream. Fr Discharge Flow Rate [gpm] The flow rate from the Lake Release Tank. K Factor of conservatism K = 0.5 for Lake Release Tank 10.2.3.2 Discharge Flow Rates 10.2.3.2.1 Lake Release Tank Discharge Flow Rate Prior to each batch release, a representative sample is obtained and analyzed. (1) The results of the analysis of the waste sample determine the discharge rate of each batch as follows: Frmax= (Cmpc)(FdactfC) (10-6) FrmaxMaximum Permitted Discharge Flow Rate [gpm] The maximum permitted flow rate from the Lake Release Tank. [gpm] Fdact Actual Dilution.Flow Rate [gpm] The actual flow rate of the radwaste dilution stream. 1

        <>   C Sample Radioactivity Concentration                                                       [µCi/ml]

The concentration of radioactivity in the Lake Release Tank, based on measurements of a sample drawn from the tank. Cmpc has the same definition as in Equation 10-5. 10.2.3.2 Release Limits Release limits are determined from 10 CFR 20. Page 38 of 268

Revision 9 February 27, 2017 10.2.3.3 Release Mixture The release mixture used for setpoint determination is based on a composition of 100% of a nuclide with a conservative concentration discharge limit to the lake (e.g. Sr90) 1 <> A more conservative discharge rate may be calculated based on concentration limits for NPDES constituents (e.g., boron concentration). In either case, discharge procedures verify that all discharge limits to the lake are below applicable limits. 10.2.4 Allocation of Effluents from Common Release Points Radioactive liquid effluents released from the Lake Release Tanks are comprised of contributions from both units. Under normal site conditions, it is difficult to apportion the radioactivity between the units. Consequently, allocation is based on the unit discharge canal used for dilution. 10.3 SOLIDIFICATION OF WASTE/PROCESS CONTROL PROGRAM The process control program (PCP) contains the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is ensured. 10.4 Radioactive Effluent Radiation Monitoring Systems 10.4.1 Design Bases The Radiation Monitoring System is designed to detect, indicate and alarm based on the radiation levels at selected locations in the facility. The system consists of the liquid effluent radiation monitoring system which is designed to provide early warning of increasing radiation activity due to a malfunction of plant sampling equipment, and to monitor radioactive discharges to the environment to ensure concentrations do not exceed specified limits. The radiation monitor is not relied upon to initiate an accident mitigation function for the radioactive waste handling event described in Chapter 5.0 of the DSAR. In the decommissioning configuration, the source term continues to be reduced as the buildings are prepared for decontamination and demolition. The potential radiological events of concern are limited to liquid releases to the lake. The liquid effluent radiation monitoring system provides general radiological monitoring, as well as specific information on the concentration of radioactivity in the event of liquid effluent sampling and analysis equipment malfunction. This enables personnel to evaluate and respond to an event accordingly. 10.4.2 System Description The liquid effluent radiation monitoring is controlled in accordance with Chapter 12 to ensure an "as low as reasonably achievable" Liquid effluent dose is maintained in event of sampling and analysis equipment malfunction. This is consistent with the design characteristics of the monitoring equipment, and acceptable operating considerations. . As decommissioning progresses, this monitor will no longer be needed and will be removed from service. Page 39 of 268

Revision 9 February 27, 2017 10.4.3 deleted 10.4.4 deleted 10.4.5 Waste Disposal System Liquid Effluent Monitor The liquid radiation monitor PR-04 remains an option for lake water discharges. It is a self-contained monitor and is used to measure radioactivity levels in liquid effluent being discharge to site effluent discharge point. Detector outputs are transmitted to the Radiation Monitoring alarms. High radioactivity-alarms are communicated so that actions can be implemented in accordance with approved procedures. The accuracy of these monitors will be maintained to provide a highly reliable backup to the multiple sample analyse~ prior to discharge. A single monitor is provided on each discharge line and is considered adequate since the tank sample analyses are the primary method for determination of allowable discharge volume and flow. The release of liquid waste is performed under administrative control and these channels provide contil)uous monitoring during the release. An additional option exists to complete lake water radioactive effluent discharges to alternate controls as described in Chapter 12. 10.4.6 Calibration and Testing Check source testing is performed as defined in Chapter 12. The waste disposal system liquid effluent monitors are calibrated by the use of two (2) isotopic standards of different intermediate activity levels. The standards are monitored during calibration in a configuration similar to that of the monitored sample during normal operation. This method allows for an accurate isotopic calibration without contamination of the system. The method of calibration of laboratory radiation counting instrumentation is in accordance with the vendor's manual. Complete documentation of calibration checks is maintained. 10.4.7 Effluent Monitoring and Sampling The methods used in quantifying routine effluent releases to the environment consist of continuous sampling during active decommissioning activities and/or when there is a viable release path. The samples are analyzed on site for effluent release documentation and composite samples are sent offsite for laboratory analyses. Laboratory analyses are conducted on either grab samples or composite samples for all release pathways where effluent sampling is required. All liquid and gaseous effluents sample results are recorded/saved in some form to provide a complete history of abnormal occurrences for evaluation; high radiation level alarms are sent to an on-shift individual when effluent releases are in progress. The high radiation alarm setpoint is based upon a value of activity which is sufficiently low to be in conformance with the concentration limit requirements.* Laboratory instrumentation used for radiation analysis of effluent grab samples are as described in the Chapter 12. The calibration of counting equipment will be maintained by the use of sources certified against the National Institute of Standards and Technology (NIST) certificates. Page 40 of 268

Revision 9 February 27, 2017 Effluent monitors will be calibrated at frequencies established in the Chapter 12. The multi-channel gamma analyzer will be performance checked when in use. Sources are used to verify against known energy lines and activity. Geometry factors will be checked in accordance with approved procedures. The liquid scintillation counter will be checked in accordance with approved procedures when in use. Complete documentation of all calibration checks will be maintained. Effluent discharge line waste monitors will be checked against laboratory analyzed or established known portable sources. Page 41 of 268

Revision 9 February 27, 2017 TABLE 10-1 DELETED Page 42 of 268

Revision 9 February 27, 2017 TABLE 10-2 HVAC EXHAUST FAN CAPACITIES Portable exhaust filtration units may be used and the effluent discharge flowrate used in calculations will use the maximum design flowrate listed on the unit by the manufacturer. Page 43 of 268

Revision 9 February 27, 2017 CHAPTER11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The parameters of the radiological environmental monitoring program for the environs ar,ound Zion Station are given in Table 11-1. Figures 11-1a, 11-1band11-2 show sampling and monitoring locations. Page 44 of 268

Revision 9 February 27, 2017 Table 11-1 Radiological Environmental Monitoring Program Exposure Pathway Sampling or Monitoring Sampling or Collection Frequency Type and Frequency of Analysis And/or Sample Locations

1. Airborne

a. Indicators - Near Field Particulate Sampler:

Z-01 Onsite No. 1 South side, Continuous sampler operation with Gross beta analysis following 2 0.2 mi S (0.3 km J) particulate filter collection weekly or weekly filter change and 3 Z-02 Onsite No. 2 West side, more frequently if required by dust gamma isotopic analysis 0.2 mi W (0.3 km N) loading. quarterly on composite filters by location. Z-03 Onsite No. 3 North side, 0.20 mi NNE (0.3 km B)

b. Control- Far Field Z-13 Pleasant Prairie Wisconsin 10 mi NW (15 km Q)

Page 45 of 268

Revision 9 February 27, 2017 Table 11-1 Radiological Environmental Monitoring Program - Cont. Exposure Pathway Sampling or Monitoring Sampling or Collection Frequency Type and Frequency of Analysis And/or Sample Locations 5

2. Direct Radiation a. Indicators - Inner Ring Quarterly Gamma dose on each TLD quarterly Z-101-1and2 0.2 mi N (0.3 km A)

Z-102-1and2 0.2 mi NNE (0.3 km B) Z-103-1 and 2 0.15 mi NE (0.25 km C) Z-104-1 and 2 0.13 mi ENE (0.2 km D) Z-105-1 and 2 0.1 mi E (0.15 km E) Z-106-1and2 0.1 mi ESE (0.15 km F) Z-107-1 and 2 0.1 mi SE (0.15 km G) Z-108-1and2 0.13 mi SSE (0.2 km H) Z-109-1 and2 0.2 mi SSE (0.3 km H) Z-112-1 and 2 0.7 mi WSW (1.1 km M) Z-113-1 and 2 0.6 miW (1.0 km N) Z-114-1 and 2 0.6 mi WNW (1.0 km P) Z-115-1 and 2 0.4 mi NW (0.6 km Q) Z-121-1and2 0.2 mi NNW (0.3 km R) Z-124-1and2 0.5 mi SW (0.8 km L) Z-125-1 and 2 0.4 mi SSW (0.6 km K) Z-129-1 and 2 0.2 mi NW (0.3 km P) Z-130-1 and 2 0.2 mi WNW (0.3 km N) Quarterly Gamma dose on each TLD Z-131-1and2 0.2 mi WSW (0.3 km L) quarterly

b. Other One at each airborne location given in 1.a.

Z01-1 and 2 0.2 mi S (0.3 km J) Z02-1 and 2 0.2 mi E (0.3 km N) Z03-1 and 2 0.2 mi NNE (.3 km B) One control at control airborne location Z13-1thru6 10 mi NW (15 km Q) Page 46 of 268

Revision 9 February 27, 2017 Table 11-1 Radiological Environmental Monitoring Program - Cont. Exposure Pathway Sampling or Monitoring Sampling or Collection Frequency Type and Frequency of Analysis And/or Sam pie Locations

2. Direct Radiation - d. Indicators - Outer Ring Quarterly Gamma dose on each TLD Cont. quarterly Z-209-1 and 2 5.1 mi S (8.2 km K)

Z-211-1 and 2 4.7 mi SW (7.6 km L) Z-212-1 and 2 5: 1 mi WSW (8.2 km M) Z-213-1 and2 5.1 miW (8.2 km N) Z-214-1 and 2 4.6 mi WNW (7.4 km P) Z-215-1and2 4.0 mi NW (6.4 km Q) Z-216-1 and 2 3.0 mi NNW (4.8 km R) Gamma dose on each TLD quarterly Page 47 of 268

Revision 9 February 27, 2017 Table 11-1 Radiological Environmental Monitoring Program - Cont. Exposure Pathway Sampling or Monitoring Sampling or Collection Frequency Type and Frequency of Analysis And/or Sample Locations

3. Waterborne

a. Drinking Water Indicators 3

Z-15 Lake County Water Works, Gross beta and gamma isotopic 1.4 mi NNW (2.2 km R) Weekly grab samples. analysis on monthly composite; Z-16 Waukegan Water Works, tritium analysis on quarterly 6.1 mi S (9.8 km J) composite.

b. Controls 3

Z-14 Kenosha Water Works, 10.0 mi N Gross beta and gamma isotopic (1.60 km A) Weekly grab samples. analysis on monthly composite; Z-18 Lake Forest Water Works, 12.9 mi tritium analysis on quarterly S (20.8 km J) composite.

c. Sediments 3

Z-25 Lake Michigan, Illinois Beach Semiannually Gamma isotopic analysis State Park; 2.0 mi S (3.2 km J) semiannually. Page 48 of 268

Revision 9 February 27, 2017 Table 11-1 Radiological Environmental Monitoring Program - Cont. Exposure Pathway Sampling or Monitoring Sampling or Collection Frequency Type and Frequency of Analysis And/or Sample Locations

4. Ingestion a. Fish Indicator Semiannually Z-26, Lake Michigan in vicinity of station Discharge 3

Gamma isotopic analysis on

b. Fish Control edible portions.

Z-27, Lake Michigan, 10.0 mi N (16.0 km A)

5. Vegetation a. Vegetation Indicator Annual (during growing season) 3 Z-QUAD 3, Pleasant Prairie market, 4 mi Gamma isotopic analysis on NNW (6.4 km R) edible portions.

Z-QUAD 4, Sheridan Road Zion Farmers market, 1.1 mi W (1.7 km N)

b. Vegetation Control Z-Control, Kenosha Farmers Market, 11 mi NNW (18 km R}

Page 49 of 268

Revision 9 February 27, 2017 Table 11-1 Radiological Environmental Monitoring Program - Cont.

1. Deleted - No longer applicable.

2. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in any individual air particulate sample is greater than 10 times the 1999 mean of control samples, then, a gamma isotopic analysis shall be performed on that elevated individual sample.

3. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the station.

4. Deleted - No longer applicable.

5. Limited TLD placements due to Lake Michigan and location of air samplers.

6. The closest drinking water locations (North/South) chosen for drinking water indicators; two other locations beyond 6.2 miles (North/South) chosen for control samples.

Page 50 of 268

Revision 9 February 27, 20 17 Figure 11-1 a Ai rborne and Direct Radiation Sample Locations - Inner Ring t1'1ettll l'tBIF (J"!6'.bJ::1g.1Ga l WCn~ ll!. D J Uo.IJlO!FJQ P~"'Ogr&'tt ) N>. 0 1531. St.:*S:.llllt & stf20t (1Htm ) 2'1J2J..fUlS-U.fri Co:uuy II. Ui~J!J Of.Pl DI.* 06J2.S15 RElllP.c

• TLD Monitoring Location A Air Sampling Location Page 51 of 268

Revision 9 February 27, 2017 Figure 11-1b Direct Radiation Sample Locations - Outer Ring 165 I

                                                           /

Page 52 of 268

Revision 9 February 27, 2017 Figure 11-2 Location of Waterborne and Ingestion Sampling Sites Racine Kenosha Water Works Z-14

                                                 *Z-27

---~f&ceR~----------- Zion Lake County Water Works

• Z-15 Zion*
• 2 -26 LAKE Illinois Beach Z-25 State Park MICHIGAN Waukegan Water Works North Chicago
• Sampling Locations Page 53 of 268

Revision 9 February 27, 2017 CHAPTER12 Radiological Effluent Technical Standards (RETS) SPECIAL NOTE The requirements of Quality Assurance Project Plan (QAPP) Appendix B shall take precedence over this chapter, should any differences occur. Page 54 of 268

Revision 9 February 27, 2017 12.1 DEFINITIONS 12.1.1 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 to assure representative sampling. 12.1.2 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds with the necessary range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors (where possible), alarm interlock and/or trip functions (if applicable) and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated. 12.1.3 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent INSTRUMENT CHANNELS measuring the same parameter. 12.1.4 A CHANNEL FUNCTIONAL CHECK shall be:

a. Instruments-The injection of a simulated signal(s) into the channel as close to the primary sensor(s) as practicable to verify OPERABILITY, including all channel outputs, as appropriate.

b. Logics-The application of input signals, or the operation of relays or switch contacts, in all the combinations required to produce the required decision outputs including the operation of all ACTUATION DEVICES. Where practicable, the test shall include the operation of the ACTUATED EQUIPMENT as well (i.e. pumps will be started, valves operated, etc.).

12.1.5 A COMPOSITE SAMPLE is one in which the quantity of liquid sample is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released. 12.1.6 A CONTINUOUS RELEASE is the discharge of liquid or gaseous wastes of a nondiscrete volume (e.g. from a volume or system that has an input flow during the release). 12.1.7 CONTINUOUS SAMPLING is uninterrupted sampling with the exception of sampling interruptions of short duration for routine activities (e.g. filter replacements). 12.1.8 MEMBER OF THE PUBLIC means any individual except when that individual is receiving an occupational dose. 12.1.9 OCCUPATIONAL DOSE means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation and/or radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include dose from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public. 12.1.10 OPERABLE - A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s). 12.1.11 OPERATING is defined as performing the intended function in the intended manner. Page 55 of 268

Revision 9 February 27, 2017 12.1.12 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste. 12.1.13 PURGE OR PURGING is the controlled process of discharging air from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner, that replacement air or gas is required to purify the confinement. 12.1.14 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased or otherwise controlled by the licensee. 12.1.15 SOLIDIFICATION shall be the conversion of radioactive liquid, resin and sludge wastes from liquid systems into a form that meets shipping and burial site requirements. 12.1.16 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. 12.1.17 SURVEILLANCE shall be those parts of the sections which prescribe remedial measures required under designated conditions, activities required to demonstrate instrument operability, and activities performed to ensure applicable offsite dose limits are not exceeded. 12.1.18 The SURVEILLANCE FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 12.1-1. 12.1.19 UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by the licensee. 12.1.20 UNVENTILATED BUILDING RELEASE means A building that is not negative pressure controlled with presence of radioactive that could potentially become airborne that has a pathway to be released to the environment. 12.1.21 GASEOUS EFFLUENT TREATMENT SYSTEM shall be any system designed and installed to reduce radioactive material in particulate form in effluents by passing ventilation through HEPA filters for the purpose of removing particulates from the gaseous exhaust stream prior to the release to the environment 12.1.22 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air is not provided or required during venting. Vent, used in system names, does not imply a venting process.  :* Page 56 of 268

Revision 9 February 27, 2017 TABLE 12.1-1 SURVEILLANCE FREQUENCY NOTATIONS NOTATION FREQUENCY* s (Shiftly) At least once per 12 hours D (Daily) At least once per 24 hours w (Weekly) At least once per 7 days M (Monthly) At least once per 31 days Q (Quarterly) At least once per 92 days SA (Semiannually) At least once per 184 days A (Annually) At least once per 366 days R *At least once per 18 months p (Prior) Complete prior to start of release N/A Not ApRlicable

• Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.

Page 57 of 268

Revision 9 February 27, 2017 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Plant Monitoring Instrumentation Operability Requirements 12.2.1.A The radioactive liquid plant monitoring instrumentation channels shown in Table 12.2-1 shall be OPERABLE AND. the radioactive liquid effluent monitoring instrumentation channels shall have their alarm/trip setpoints set to ensure that the limits of Section 12.3.1.A are met. Applicability: As indicated in Table 12.2-3.

1. With a radioactive liquid effluent monitoring instrument channel trip setpoint less conservative than the value necessary to prevent violating the limits of Section 12.3.1.A, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

2. With one or more radioactive liquid plant monitoring instrumentation channels inoperable, initiate the SURVEILLANCE requirement delineated in Table 12.2-1.

3. Restore the inoperable effluent monitor to OPERABLE status within 30 days, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report the reasons as detailed in Section 12.7.2 and perform a review to determine course of action to restore to OPERABLE status.

Surveillance Requirements 12.2.1.B.1 The liquid effluent monitor setpoints shall be determined in accordance with procedures as described in the ODCM. 12.2.1.B.2 Each radioactive liquid plant monitoring instrumentation channel shall be demonstrated OPERABLE by performance of a CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 12.2-2. 12.2.1.C The radioactive liquid plant monitoring instrumentation is provided to indicate abnormal radiological conditions, AND, The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the release of radioactive materials in liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of RETS. The OPERABILITY and use of this instrumentation is consistent with the requirements of Appendix A to 10CFR Part 50. Page 58 of 268

Revision 9 February 27, 2017 TABLE 12.2-1 RADIOACTIVE LIQUID PLANT MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE SURVEILLANCE# CONDITION

1. Liquid Effluent Monitors Providing Automatic Termination of Release A. Lake Release Tanks

1. OR-PR04 1* Liquid Release through this Pathway

2. Effluent Continuous Composite Sampler A. WWTF 4 During Release via this pathway

3. Effluent Flow Rate Monitor A. Lake Release Tank low flow pathway

1. OFl-WD0005 3 Liquid Release through this Pathway

2. OFl-WD0006 3 Liquid Release through this Pathway B. Lake Release Tank high flow pathway

1. OFl-WD0008 3 Liquid Release through this Pathway

4. Plant System Monitors A. Dilution Flow Pressure Indication

1. OPl-SW01A 1** 3 Liquid Release from Either LRT #1 or #2

2. OPl-SW01 1** 3 Liquid Release from Either LRT #1 or #2

• - The Surveillance 1 may be used as an equivalent alternative to the use of OR-PR04.
  • -Minimum Channels Operable for Dilution Flow Pressure Indication is one channel from OPl-SW01 OR one channel from OPl-SW01A during LRT releases.

Page 59 of 268

Revision 9 February 27, 2017 TABLE 12.2-1 RADIOACTIVE LIQUID PLANT MONITORING INSTRUMENTATION (Cont'd) SURVEILLANCE 1 If the monitor is inoperable, effluent releases from the tank may continue provided that prior to initiating the release:

1. At least two independent samples of the tank's contents are analyzed, in accordance with Section 12. 3.1. B.1, and

2. At least two technically qualified members of the facility staff independently verify the release-rate calculations and discharge flow path valving; and

3. Approval by the Plant Manager.

4. Restore the inoperable effluent monitor to OPERABLE status within 30 days, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report the reasons as detailed in Section 12.7.2 and perform a review to determine course of action to restore to OPERABLE status.

Otherwise, suspend release of radioactive effluents via this pathway. SURVEILLANCE 2 Deleted. SURVEILLANCE 3 For the applicable flowpath at least one of the listed flowmeters within the flowpath must be operable to monitor flow provided the monitored flowrate falls within the calibration range of the flowmeter. With the no flow channels OPERABLE within the flowpath, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours during actual releases. Pump curves may be used to estimate flow. SURVEILLANCE 4 If the composite sampler is inoperable, effluent releases via this pathway may continue, provided that at least once per day grab samples are taken. The samples shall be analyzed in accordance with Section 12.3.1.B.3. Page 60 of 268

Revision 9 February 27, 2017 TABLE 12.2-2 RADIOACTIVE LIQUID PLANT MONITORING INSTRUMENTATION SURVEILLANCE CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION (1) TEST (2)

1. Liquid Effluent Monitors Providing Automatic Termination Of Release A Lake Release Tanks

1. OR-PR04 p p R Q

2. Effluent Continuous Composite Sampler A WWTF N/A N/A N/A N/A

3. Effluent Flow Rate Monitor A Lake Release Tank low flow pathway

1. OFl-WD0005 D(3) N/A R N/A

2. OFl-WD0006 D(3) N/A R N/A B. Lake Release Tank high flow pathway

1. OFl-WD0008 D(3) N/A R N/A

4. Plant System Monitors A Dilution Flow Pressure Indication

1. OPl-SW01A D(4) N/A R N/A

2. OPl-SW01 D(4) N/A R N/A (1) CHANNEL CALIBRATION shall include performance of a CHANNEL FUNCTIONAL TEST.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that any automatic isolation of this pathway occurs and that control room alarm annunciation occurs if any of the following conditions exist. (if the capability is installed): a) Instrument indicates levels above the alarm setpoints. b) Circuit failure. c) Instrument indicates a downscale failure. d) Instrument controls not set in operate mode. (3) CHANNEL CHECK shall consist of verifying indications of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or BATCH RELEASES are made. (4) Dilution Flow Pressure Gauge OPl-SW01A OR OPl-SW01 may be used. The pressure gauge being used shall be verified operating at least daily during Lake Release Tank Batch discharge And pump curves used to estimate flow once per day based on the readings. Page 61 of 268

Revision 9 February 27, 2017 12.2.2 Radioactive Plant Monitoring Instrumentation Operability Requirements 12.2.2.A The radioactive plant monitoring instrumentation shown in Table 12.2-3 shall be OPERABLE while a release is in progress. Applicability: As indicated in Table 12.2-3.

1. Deleted.

2. Deleted.

3. Restore air sampler to OPERABLE status or cease active decommissioning in the affected area and isolate the release path.

Surveillance Requirements 12.2.2.B.1 Deleted. 12.2.2.B.2 Each radioactive plant monitoring instrumentation and air sampling equipment shall be calibrated as per the applicable plant Radiation Protection Instrument Calibration Procedures. The frequencies at which these calibrations are done will be as described in the applicable plant Radiation Protection Instrument Calibration Procedures. 12.2.2.C The radioactive particulate air samplers are to provide means of quantifying effluent release for reporting requirements. Page 62 of 268

Revision 9 February 27, 2017 TABLE 12.2-3 RADIOACTIVE PLANT MONITORING INSTRUMENTATION APPLICABLE INSTRUMENT SURVEILLANCE CONDITION

1. Effluent Containment release pathway A. U1

1. Unit 1 Tent sampler 8 Viable release pathway from U1 containment

2. Unit 1 filtered exhaust fan sampler 9 When exhaust fan is running B. U2

1. Unit 2 Tent sampler 8 Viable release pathway from U2 containment

2. Unit 2 filtered exhaust fan samplers 9 When exhaust fan is running

2. Open Air demolition locations A. Open air demolition air samplers(4) 11 Active Open Air Demolition that creates debris with loose surface contamination that has a potential to become airborne.

B. South waste loading area air samplers(4) 11 Active loading or offloading of debris of loose surface contamination that has a potential to become airborne. B. DELETED C. DELETED Page 63 of 268

Revision 9 February 27, 2017 TABLE 12.2-3 RADIOACTIVE PLANT MONITORING INSTRUMENTATION -(Cont'd) TABLE NOTATIONS SURVEILLANCE 6 DELETED SURVEILLANCE 7 DELETED SURVEILLANCE 8 Effluent releases via this pathway may continue provided:

1. Continuous sampling of this pathway is required during active decommissioning with a viable release pathway for airborne particulate.

2. If an air sample is not available, re-establish an operating air sampler in this pathway within 4 hours, OR cease active decommissioning at the affected location AND secure the release pathway.

SURVEILLANCE 9 Filtered ventilation exhaust fans may be operated provided:

1. Filtered exhaust fan air sampler is running.

2. If an air sampler is not available, re-establish an operating air sampler at the discharge of the exhaust fan discharge within 4 hours, OR secure the exhaust fan.

SURVEILLANCE 10 DELETED SURVEILLANCE 11 Open Air Demolition may continue provided:

1. Continuous air sampling in each of 4 general cardinal directions from debris during active open air demolition.

2. If any of the 4 air samplers is not available, re-establish air sampling in the affected general direction from the debris pile within 4 hours OR cease loading/offloading decommissioning activities.

SURVEILLANCE 12 DELETED. SURVEILLANCE 13 DELETED SURVEILLANCE 14 DELETED Page 64 of 268

Revision 9 February 27, 2017 TABLE 12.2-4 Deleted Page 65 of 268

Revision 9 February 27, 2017 12.3 LIQUID EFFLUENTS 12.3.1 Concentration Operability Requirements 12.3.1.A.1 The concentration of radioactive material released from the site to UNRESTRICTED AREAS (see Appendix F, Figure F-1) shall be limited to 10 times the concentrations specified in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402 12.3.1.A.2 During the release of radioactive liquid wastes; the combination of dilution water flow and waste water discharge flow shall be established to ensure the discharge concentra.tion limits of 12.3.1.A.1 are not exceeded. Applicability: At all times.

1. With the concentration of radioactive materials released from the site to UNRESTRICTED AREAS exceeding the limits specified in Section 12.3.1.A.1 immediately decrease the release rate of radioactive materials and/or increase the dilution flow rate to restore the concentration to within the above limits.

Surveillance Requirements 12.3.1.B.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 12.3-2. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Section 12.3.1.A.1. 12.3.1.B.2 Post-release analyses of samples composited from BATCH RELEASES shall be performed in accordance with Table 12.3-2. The results of the previous post-release analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A.1. 12.3.1.B.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 12.3-2. The results of the analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A.1. 12.3.1.B.4 Appropriate discharge and dilutions flows for each batch radioactive liquid release shall be determined with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Section 12.3.1.A.1. 12.3.1.C This Section is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to UNRESTRICTED AREAS will be less than ten (10) times the concentration levels specified in Appendix B, Table 2, Column 2 to 10CFR 20.1001-20.2402. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10CFR20.1301. Page 66 of 268

Revision 9 February 27, 2017 TABLE 12.3-1 DELETED Page 67 of 268

Revision 9 February 27, 2017 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE MINIMUM ANALYSIS LOWER LIMIT OF LIQUID RELEASE SAMPLING FREQUENCY TYPE OF DETECTION (LLD) TYPE FREQUENCY ACTIVITY ANALYSIS (µCi/ml) (a,e) A. Lake Release Prior to Each Release Prior to Each Principal Gamma 5E-7 (c) Release Emitters (e) p M Tritium 1E-5 Each Batch (c) Composite (b) Gross Alpha 1E-7 p Q Sr-90 5E-8 Each Batch (c) Composite (b) Fe-55, Ni-63 1E-6 B. WWTF (f) Continuous During W when discharging Principal Gamma 5E-7 Release (d) Emitters(e) Continuous During M Tritium 1E-5 Release(d) Composite (b) Gross Alpha 1E-7 Continuous During Q Sr-90 5E-8 Release (d) Composite (b) Fe-55, Ni-63 1E-6 C. Waste Prior to each Release Prior to each Release Principal Gamma 5E-7 Neutralizing Tank Emitters (e) p M Tritium 1E-5 Each Batch (c) Composite (b) Gross Alpha 1E-7 D. Groundwater Prior to each Release Prior to each Release Principal Gamma 5E-7 Emitters (e) p M Tritium 1E-5 Each Batch (c) Composite (b) E. Groundwater (f) Continuous During w Principal Gamma 5E-7 Release (d) Emitters(e) Continuous (d) M Tritium 1E-5 Composite (b) Page 68 of 268

Revision 9 February 27, 2017 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLiNG AND ANALYSIS SURVEILLANCE (Cont'd) TABLE NOTATIONS

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95%

probability with 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 s2 A

• E
• V
• 2.22
• Y
• exp (-A.At)

Where: LLD is the lower limit of detection as defined above in picocuries (pCi) per unit mass or volume, sb is the square root of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), A is the number of gamma rays emitted per disintegration for gamma ray radionuclide analysis (A= 1.0) for gross alpha, strontium, and tritium measurement. E is the counting efficiency (as counts per gamma), V is the sample size (in units of mass or volume), 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield when applicable (otherwise Y = 1.0) A. is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental sample). The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y, and At shall be used in the calculation. The background count rate is calculated from the background counts that are determined to be within .+/-.one FWHM (Full Width at Half Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide. Page 69 of 268

Revision 9 February 27, 2017 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE (Cont'd) TABLE NOTATIONS For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentrations of such radionuclides using observed ratios with those radionuclides which are measurable.

b. 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 which is representative of the liquids released.

1) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

2) The weekly and monthly Proportional Composite samples are not required provided that (1) the analysis required for each of these composite samples has been run on each batch discharged, and (2) a monthly record of radionuclides discharged (isotope and quantity) is maintained.

c. 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 to assure representative sampling.

d. A CONTINUOUS RELEASE is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release.

e. The principal gamma emitters for which* the LLD specification applies exclusively are the following radionuclides: Nb-94, Co-60, Cs-137 and Sb-125. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD, and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in the required dose calculations.

f. If the composite sampler is inoperable, grab samples shall be taken from the discharge stream once per day during system operation.

Page 70 of 268

Revision 9 February27, 2017 12.3.2 Dose Operability Requirements 12.3.2.A The dose or dose commitment to a MEMBER OF THE PUBLIC above background from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS (see Appendix F, Figure F-1) shall be limited:

1. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and

2. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

Applicability: At all times.

1. With the calculated dose from the release of radioactive materials in liquid effluents exceeding twice the limits specified in Section 12.3.2.A, limit the subsequent releases such that the dose or dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cycle sources is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. Demonstrate that radiation exposures to all MEMBERS OF THE PUBLIC from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40CFR Part 190 and 40CFR Part 141 Standard, otherwise obtain a variance from the Commission to permit releases which exceed the 40CFR Part 141 or 190 Standard.

The radiation exposure analysis shall use methods prescribed in the ODCM. Surveillance Requirements 12.3.2.B Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodologies and parameters of the ODCM at least once per 31 days. 12.3.2.C This Section is provided to implement the requirements of Sections II.A, Ill.A and IV.A of Appendix I, 10CFR Part 50. The limiting Condition of Operation implements the guides set forth in Section II.A 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 releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies, which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are excess of the requirements of 40CFR 141. The dose calculations in the ODCM 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 an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the dose due to the actual release rate of radioaqtive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109; Calculation of Annual Doses to Man from Routine Releases of Radioactive Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I, Revision 1, Octobe,r 1977 and Regulatory Guides 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. Page 71 of 268 L_

Revision 9 February 27, 2017 This Section applies to the release of liquid effluents from each unit at the site. For shared radwaste treatment systems, the liquid effluents from the shared systems are proportioned among the units sharing the system. 12.3.3 Liquid Radwaste Treatment System Operability Requirements 12.3.3.A The Liquid Radwaste Treatment System shall be OPERABLE* and appropriate portions of the system shall be used to reduce the radioactive materials in liquid effluents prior to discharge when the projected doses due to liquid effluent, from each unit, to UNRESTRICTED AREAS (see Appendix F, Figure F-1) would exceed 0.06 mrem to the total body or 0.20 to any organ in a 31-day period.

• The liquid Radwaste Treatment System shall be considered OPERABLE, if liquid waste can be held up and/or discharged within applicable limits.

Applicability: At all times. With the Liquid Radwaste Treatment System inoperable for more than 30 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, return the system to OPERABLE status and place the appropriate portions of the system in use. Surveillance Requirements 12.3.3.B Doses due to liquid releases from the site to UNRESTRICTED AREAS, shall be projected at least once per 31 days in accordance with the methodologies and parameters of the ODCM when the Liquid Radwaste Treatment System is not being fully utilized. 12.3.3.C The OPERABILITY of the Liquid Radwaste Treatment System ensures that the system will be available for use whenever liquid effluents require treatment prior to 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 be kept "as low as is reasonably achievable." This Section implements the requirements of 10CFR Part 50.36a, General Design Criterion of Appendix A to 10CFR Part 50 and the design objective given in Section 11.D of Appendix I to 10CFR Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a 2% fraction of the dose design objectives set forth in Section II.A of Appendix I, 10CFR Part 50, for liquid effluents. Page 72 of 268

Revision 9 February 27, 2017 12.4 GASEOUS EFFLUENTS 12.4.1 Dose Rate Operating Requirements 12.4.1.A The dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY (see Appendix F, Figure F-1), shall be limited to the following:

1. DELETED

2. For tritium and all radionuclides in particulate form with half-lives greater than 8 days the limit is less than or equal to 1500 mrem/yr to any organ.

Applicability: At all times. With a release exceeding the above limits, immediately reduce the release rate to within the above limits.

• Surveillance Requirements 12.4.1.B The dose rate due to radioactive materials in gaseous effluents shall be determined to be within the prescribed limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 12.4-1.

12.4.1.C This Section is provided to ensure that radioactive material discharged in gaseous effluents will not result in the exposure of a Member of the Public in an Unrestricted Area, either at or beyond the Site Boundary in excess of the design objectives of appendix I to 10 CFR part 50. This section is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section II.A and II design objectives of appendix I to 10 CFR part 50. These release-rate limits also restrict, at all times, the corresponding organ dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year. For purposes of calculating dose resulting from airborne releases, the stack is considered a ground-level release. The Sampling and Analysis Program requirements prescribed in Table 12.4-1 are established to provide representative and appropriate sampling of the radiologically controlled areas. The method and frequency of sampling is based on the effluent flowrate. Continuous Releases are defined for areas with forced ventilation release points. Unventilated Building Releases are defined for areas with no specific release point. Page 73 of 268

Revision 9 February 27, 2017 TABLE 12.4-1 . RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM MINIMUM TYPE OF LOWER LIMIT OF GASEOUS RELEASE SAMPLING ANALYSIS ACTIVITY DETECTION (LLD) TYPE METHOD FREQUENCY ANALYSIS I (µCi/cc) (f) A Deleted

8. Continuous Continuous during Weekly(c) Particulate 1 E-11 Releases <1l active Daily( a) Principal Gamma decommissioning (b )(h) Emitters (e)

C. Continuous Releases< 1l Unit 2 Ventilation Unit 1 Ventilation, Composite Quarterly Sr-90 Particulate 1E-11 Portable filtered Ventilation discharge at other Fe-55 Particulate 3E-11 locations( as applicable) Ni-63 Particulate 1E-11 Gross Alpha 1E-11 (1) The requirements listed in this table for Continuous Releases are applicable for release paths that are available. Page 74 of 268

Revision 9 February 27, 2017 TABLE 12.4-1 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM (Cont'd) MINIMUM TYPE OF LOWER LIMIT OF GASEOUS RELEASE SAMPLING ANALYSIS ACTIVITY DETECTION (LLD) TYPE METHOD FREQUENCY ANALYSIS (µCi/cc) (f) D. Unventilated Continuous during Daily(c) Particulate Releases( 1> active decommissioning (h) Principal Gamma 1E-11 U1 tent Emitters (e) U2 tent Composite Quarterly Sr-90 Particulate 1E-11 Fe-55 Particulate 3E-11 Ni-63 Particulate 1E-11 Gross Alpha 1E-11 1 This requirement sampling point may be used for any release point that is unventilated and will be tracked as an abnormal gaseous discharge point.TABLE 12.4-1 MINIMUM TYPE OF LOWER LIMIT OF GASEOUS RELEASE SAMPLING ANALYSIS ACTIVITY DETECTION (LLD) TYPE METHOD FREQUENCY ANALYSIS (uCi/cc) (f) E. Open Air Demolition 4 Continuous air Daily(c) Particulate 1 E-11 samples during Loading/offloading at active open air Principal Gamma South Waste Loading decommissioninQ(i) Emitters (e) Area. Composite Quarterly Sr-90 Particulate 1E-11 Fe-55 Particulate 3E-11 Ni-63 Particulate 1E-11 Gross Alpha 1 E-11 Page 75 of 268

Revision 9 February 27, 2017 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM (Cont'd) TABLE NOTATIONS

a. The daily sampling requirement is applicable when active decommissioning activities that can create airborne radioactivity are in progress in the associated building and a viable release pathway exists to the environment. *

b. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period in Section 12.4.1.

c. The particulate filter(s) shall be saved for a quarterly composite analysis for Sr-90, Ni-63, Fe-55 and gross alpha.

d. DELETED

e. For particulate emissions, the principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Nb-94, Co-60, Cs-137 and Sb-125. Other peaks which are measurable and identifiable by gamma-ray spectrometry, together with the above nuclides, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being at the LLD level for that nuclide.

f. The LLD is defined in Notation a. of Table 12.3-2.

g. DELETED

h. Sampling interruptions of short duration for routine activities, e.g. filter replacement or moving the air sampler due to accessibility or work obstruction opening/closing of the construction door, do not constitute a deviation from the requirements for continuous sampling.

i. Continuous air sampling at open air demolition location and South Waste Loading Area are required in each of the 4 general directions during active decommissioning of material with a potential of loose surface contamination to become airborne. The demolition area with airborne potential requires 4 air samplers for demolition work. The South Waste Loading Area requires 4 air samplers for loading offloading work.

Page 76 of 268

Revision 9 February 27, 2017 12.4.2 DELETED 12.4.3 Dose - Tritium and Radioactive Material in Particulate Form Operability Requirements 12.4.3.A The dose to a MEMBER OF THE PUBLIC from tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas at or beyond the SITE BOUNDARY (see Appendix F, Figure F-1) shall be limited to the following:

1. During any calendar quarter: Less than or equal to 7.5 mrem to any organ, and

2. During any calendar year: Less than or equa.1 to 15 mrem to any organ.

Applicability: At all times. With the calculated dose from the release of tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding twice the limits of Section 12.4.3.A:

1. Limit subsequent releases such that the dose or dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cycle sources to less than or equal to 25 mrem to the total body or organ (except the thyroid which is limited to less than or equal to 75 mrem) over 12 consecutive months.

2. Prepare an analysis which demonstrates that radiation exposures to all MEMBERS OF THE PUBLIC from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40CFR Part 190 Standard. Otherwise, request a variance from the Commission to permit release which exceeds the 40CFR Part 190 Standard. The radiation exposure analysis shall use the methods prescribed in the ODCM.

Surveillance Requirements 12.4.3.B Cumulative dose contribution for the current calendar quarter and current calendar year for tritium, and all radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodologies and parameters in the ODCM at least once per 31 days. 12.4.3.C This Section implements the requirements of Sections 11.C, Ill.A and IV.A of Appendix I, 10CFR Part 50. The Operability Requirements are the guides set forth in 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 releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculation methods specified in the Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The release-rate specifications for radioactive material in particulate form are dependent on the existing radionuclide pathways to man, at or beyond the SITE BOUNDARY. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) disposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man. Page 71 of 268

Revision 9 February 27, 2017 12.4.4 Gaseous Effluent Treatment System Operability Requirements 12.4.4.A The GASEOUS EFFLUENT TREATMENT SYSTEM is no longer required as the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at or beyond the SITE BOUNDARY (see Appendix F, Figure F-1) will not exceed 0.3 mrem to any organ. Applicability: deleted Action: deleted Surveillance Requirements 12.4.4.B Doses due to gaseous releases from each unit to areas at or beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodologies and parameters in the ODCM in compliance with Zion Station QAPP 5.6.2.f as the Gaseous Effluent Treatment Systems is no longer required. 12.4.4.C The OPERABILITY of the GASEOUS EFFLUENT TREATMENT SYSTEM is no longer required during decommissioning work at Zion Station as there is no longer an operational conditions that would cause airborne releases to exceed the specifications of a 2% fraction of the dose design objectives set forth in Section 11.B and 11.C of Appendix I, 10CFR50, for gaseous effluents. Engineering and administrative controls such as encapsulation will be used for consideration of "as low as is reasonably achievable" during active decommissioning. Page 78 of 268

Revision 9 February 27, 2017 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Monitoring Program Operability Requirements 12.5.1.A The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1. Applicability: At all times.

1. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 12.5-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting a program as required and the plans for preventing a recurrence.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of sampling equipment,. if a person who participates in the program goes out of business or no longer can provide sample, or contractor omission which is corrected as soon as discovered. If the equipment malfunctions, corrective actions shall be completed as soon as practical. If a person/business supplying samples goes out of business, a replacement supplier shall be found as soon as possible. All deviations from the sampling schedule shall be described in the Annual Radiological Environmental Operating Report.

2. With the level of radioactivity as a result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 12.5-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days a Special Report which 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 limits of Section 12.3.2 or 12.4.3. When more than one of the radionuclides in Table 12.5.2 are detected in the sampling medium, this report shall be submitted if:

concentration ( 1) + concentration (2) + ... ~ 1. O reporting level (1) reporting level (2) When radionuclides other than those in Table 12.5-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Section 12.3.2or12.4.3. 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.

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

Page 79 of 268

Revision 9 February 27, 2017

3. If the sample type or sampling location(s) required by Table 12.5-1 become(s) permanently unavailable, identify suitable alternative sampling media for the pathway of interest and/or specific locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program as soon as practicable. The specific locations from which samples were unavailable may then be deleted from the program.

Prepare and submit a controlled version of the ODCM within 180 days including a revised figure(s) and table reflecting the new location(s) With supporting information identifying the cause of the unavailability of samples and justifying the selection of new location(s) for obtaining samples. Surveillance Requirements 12.5.1.B.1 The Radiological Environmental Monitoring samples shall be collect~d from the locations specified in the ODCM and analyzed pursuant to Table 12.5-1 and the detection capabilities required by Table 12.5-3. 12.5.1.C The Radiological Environmental Monitoring Program required by this section 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 THE PUBLIC resulting from the station operation. This monitoring program implements Section IV.B.2 of Appendix I to 10CFR50 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 modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The ,specified monitoring program is based on baseline/historical conditions for direct radiation measurements, soil, biota, and Sediments established over years of operational experience and current site conditions/operating activities. The REMP need only be re-evaluated for major change~ to site conditions/configuration (e.g., prior to site decommissioning, if a significant release occurs, changing baseline data ... ). Program changes may be initiated at any time based on operational experience. The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLD). The LLDs required by Table 12.5-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA., "Limits for Qualitative Detection and Quantitative Determination-Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Gartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). Interpretations 12.5.1.D Table 12.5-1 requires "one sample of each community drinking water supply downstream of the plant within 10 kilometers (6.2 miles)." Drinking water supply is defined as water taken from river, lakes, or reservoirs (not well water) which is used for drinking. Since Lake Michigan has no designated downstream or upstream direction, two drinking water locations (one north/one south) within 10 kilometers shall be sampled as drinking water indicator locations, and two other locations (one north/one south) beyond 10 kilometers shall be sampled as control locations. Page 80 of 268

Revision 9 February 27, 2017 TABLE 12.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF 1 AND/ OR SAMPLE AND SAMPLE LOCATIONS' l FREQUENCY ANALYSIS

1. Airborne Samples from a total of three locations: Particulate Samgler:

Continuous sampler operation Gross beta analysis following

a. Indicator- Near Field with particulate sample collection weekly filter chan~e' 'and gamma 3

weekly (or more frequently if isotopic analysis' quarterly on Three samples from locations within 4 km required due to dust loading). composite filters by location on (2.5 mi) in different sectors. near field samples.

b. Control- Far Field One sample from location 15-25 km (10-17 mi) in minimal D/Q sector.

Page 81 of 268

Revision 9 February 27, 2017 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1 EXPOSURE NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS( > SAMPLING AND TYPE AND PATHWAY COLLECTION FREQUENCY OF AND/OR FREQUENCY ANALYSIS SAMPLE

2. Direct Thirty-one routine monitoring stations with thermoluminescent dosimeters (TLD),

Radiation(5> placed with at least one monitoring location in each meteorological sector, as follows:

a. Indicator- Inner Ring (100 Series TLD or UD-814-A1) in the general area of the SITE BOUNDARY (0.1 to 1.5 mi);

b. Other- One at each Airborne location given in part 1.a. Including 1 control TLD location located at control air sample station given in part 1.b. Quarterly Gamma dose on each TLD quarterly.

c. Indicator- Outer Ring (100 Series TLD or UD-814-A1) in the general area of the 5 mile ring. (2.0 to 10 mi);

Other TLDs may be placed at special interest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Commonwealth Edison employees have routine access. Page 82 of 268

Revision 9 February 27, 2017 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONs<1l FREQUENCY ANALYSIS

3. Waterborne 6

a. Drinking Water lndicator< l One Sample from each community Gross beta and gamma isotopic drinking water supply that could be analyses<4l on monthly composite; Weekly grab samples. tritium analysis on quarterly affected by the station discharge within 10 km (6.2 mi) of discharge (north/south). composite.

5

b. Contro1< l Gross beta and gamma isotopic One sample upstream and downstream. Weekly grab samples. analyses<4l on monthly composite; (north/south) of discharge. tritium analysis on quarterly composite.

c. Sediments 4

At least one sample within 1O km (6.2 mi) Semiannually. Gamma isotopic analysis <l of discharge semiannually. Page 83 of 268

Revision 9 February 27, 2017 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONS( 1) FREQUENCY ANALYSIS

4. Ingestion

a. Fish Indicator Representative samples of commercially 4 Semiannually Gamma isotopic analysis( l on and recreationally important species in edible portions.

discharge area. *

b. Control Representative samples of commercially Semiannually Gamma isotopic analysis on edible and recreationally important species not portions.

influenced by plant discharge.

5. Vegetation

a. Vegetation Indicator 3 Different types of broadleaf vegetation grown in the local area at publicly available vegetable markets. 2 Different types of root

• Annual (during growing season) Gamma isotopic analysis(4> on vegetables grown in the local area at edible portions.

publicly available vegetable markets.

b. Vegetation Control 3 Different types of broadleaf vegetation Annual (during growing season) Gamma isotopic analysis(4l on grown in the local area at publicly available edible portions.

vegetable markets. 2 Different types of root vegetables grown in an area >8 mi (12 km) from publicly available vegetable markets. Page 84 of 268

Revision 9 February 27, 2017 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (1) Specific parameters of distance and direction from the centerline of the midpoint of the two units and additional description where pertinent, shall be provided for each and every sample location in Table 11-1 of the ODCM Station Annexes. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,-" October 1978, and to Radiological Assessment Branch Technical, Position, Revision 1, November 1979. (2) Deleted - No longer applicable. (3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thorium daughter decay. If gross beta activity in any individual air particulate sample is greater than 10 times the 1999 mean of control samples, then, a gamma isotopic analysis shall be performed on that elevated individual sample. (4) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station. or identification of nuclides that are same type but not attributable to station effluents in the case of 'control' samples (5) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The number of locations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., If a station is adjacent to a lake (i.e. Zion}, some sectors may*be over water thereby reducing the number of dosimeters which could be placed at the indicated distances. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading. (6) Refer to Section 12.5.1.D for interpretation on the applicability of "downstream" and "upstream". If no community drinking water supply exists within 6.2 miles of the discharge, surface water sampling shall be performed. Page 85 of 268

Revision 9 February 27, 2017 TABLE 12.5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES* ANALYSIS WATER (pCi/L) AIRBORNE FISH (pCi/kg, wet) Vegetation (pCi/kg, PARTICULATE OR wet) 3 GASES (pCi/m ) H-3 20,000 \1) Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 Cs-134 30 10 1,000 Cs-137 50 20 2,000 2,000 Ba-La-140 200 (1) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I may be used.

  *This table contains reporting levels for analyses beyond the requirements of Table 12.5-1.

Page 86 of 268

Revision 9 February 27, 2017 TABLE 12.5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS 111 LOWER LIMIT OF DETECTION (LLD) 12> AIRBORNE Vegetation WATER PARTICULATE 'FISH (pCi/kg, wet) SEDIMENT ANALYSIS (pCi/L) OR GASES (pCi/kg, wet) (pCi/kg, dry) (pCi/m 3 ) Gross Beta 4 0.01 1000 H-3 2,0001" 1 Mn-54 15 130 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 Cs-134 15 0.01 100 150 Cs-137 18 0.01 100 80 180 Page 87 of 268

Revision 9 February 27, 2017 TABLE 12.5-3 (Continued) DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS (1) This table contains lower limits of detection for analyses beyond the requirements of Table 12.5-1. This table does not imply that only these nuclides are to be detected and reported; other peaks which are measurable and identifiable in the analyses required by Table 12.5-1 shall be reported in the Annual Radiological Environmental Operating Report. (2) The Lower Limit of Detection (LLD) is defined, for purposes of these specifications, as the smallest 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 include radiochemical separation, the LLD is defined as follows: LLD = (E) (V) (2.22) (Y) (exp (-A,At)) LLD - (E) (V) (2.22) (Y) (exp (-/..At)) Where: 4.66 Sb >> 3/tb LLD = the "a priori" Lower Limit of Detection (picocuries per unit mass or volume), sb = the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (counts per minute),

                              -J Total Counts
           =

tb E = the counting efficiency(counts per disintegration), V = the sample size (units of mass or volume), 2.22 = the number of disintegrations per minute per picocurie, Y = the fractional radiochemical yield, when applicable, A, =the radioactive decay constant for the particular radionuclide (sec*\ tb =counting time of the background or blank (minutes), and Page 88 of 268

Revision 9 February 27, 2017 TABLE 12.5-3 (Continued) DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS 6.t = the elapsed time between sample collection, or end of the sample collection period, and the time of counting (sec). Typical values of E, V, Y, and 6.t should be used in the calculation. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report. (3) This is the minimum required LLD; however, environmental samples analyzed off-site will be required to use 200 pCi/I. Page 89 of 268

Revision 9 February 27, 2017 12.5.2 LAND USE CENSUS Operability Requirements 12.5.2.A. A Land Use Census shall be conducted and shall identify within a distance of 10 km (6.2_mi.) the location, in each of the following meteorological sectors, A, J, K, L, M, N, P, Q, and R**, the nearest residence. For dose calculation, a garden will be assumed at the nearest will residence .. For REMP purposes, aerial photographs or equivalent method shall be used to determine the nearest garden/farm >500 sq. ft (50sq meters) in each sector within 1O mi. (15km) Applicability: At all times. Action: With a Land Use Census identifying location(s) that yields a calculated dose or dose commitment, via the same exposure pathway 20% greater than at a location from which samples are currently being obtained in accordance with Section 12.5.1, add the new location(s) within 30 days to the Radiological Environmental Monitoring Program given in Chapter 11 of the ODCM Station Annexes. The sampling location(s), excluding the control 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. Submit in the next Annual Radiological Environmental Operating Report documentation for a change in the ODCM including revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.

             ** The nearest industrial facility shall also be documented if closer than the nearest residence.

Surveillance Requirements 12.5.2.B The Land Use Census shall be conducted, between June 1 and October 1, at least once_per calendar year using that information that will provide the best results, such as by a door-to-door survey or aerial survey. The result of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report. 12.5.2.C This specification 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 this census. This census satisfies the requirements of Section IV.8.3 of Appendix I to 10 CFR Part 50. Page 90 of 268

Revision 9 February 27, 2017 12.5.3 INTERLABORATORY COMPARISON PROGRAM Operability Requirements 12.5.3.A Analyses shall be performed on radioactive materials supplied as part of an interlaboratory comparison program that correspond to samples required by Table 12.5.1. Applicability: At all times. Action:

1. 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.

Surveillance Requirements 12.5.3.B A summary of the results obtained as part of the above required interlaboratory comparison program shall be included in the Annual Radiological Environmental Operating Report. 12.5.3.C The requirement for participation in an interlaboratory comparison program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV. B.2 of Appendix I to 10 CFR Part 50. Page 91 of 268

Revision 9 February 27, 2017 12.6 PROCESS CONTROL PROGRAM (PCP) 12.6.1 PCP Program Requirements Contains the requirements and methodology for the current formulas, sampling, analyses, tests, and determinations performed to ensure the processing and packaging of solid radioactive wastes based on actual or simulated wet solid wastes is accomplished in compliance with:

• 10CFR Parts 20, 61, and 71
• State Regulations
• Burial Site Requirements
• Other Requirements Governing the Shipping and Burial of Radioactive Waste 12.6.2 Changes to the PCP Changes to the PCP include those changes that affect the process or methodology, by which wastes are solidified, packaged to meet burial site form requirements, classified, or dewatered.

12.6.2.1. Shall be documented and records of reviews performed shall be retained, and Shall contain sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s), and Shall contain a determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations, and Shall become effective after review and approval by the Decommissioning Plant Manager. Page 92 of 268

Revision 9 February 27, 2017 12.7 REPORTING REQUIREMENTS 12.7.1 Annual Radiological Environmental Operating Report* Routine Annual Radiological Environmental Operating Report covering the operation of the Unit(s) during the previous calendar year shall be submitted according to the Permanently Defueled Technical Specifications. The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including, as found appropriate, a comparison of preoperational studies with operational controls or with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The Annual Radiological Environmental Operating Report shall include the results of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in the Chapter 11 of the ODCM Station Annexes, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment 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 supplementary report. The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; legible maps covering all sampling locations keyed to a table giving distances and directions from the midpoint between the two units; reasons for not conducting the Radiological Environmental Monitoring Program as required by Section 12.5.1, and discussion for all deviations from the sampling schedule of Table 11.1-1; a Table of Missed Samples and a Table of Sample Anomalies for all deviations from the sampling schedule of Table 11.1-1; discussion of environmental sample measurements that exceed the reporting levels of Table 12.5-2 but are not the result of plant effluents; discussion of all analyses in which the LLD required by Table 12.5-3 was not achievable; results of the Land Use Census required by Section 12.5'.2; and the results of licensee participation in an interlaboratory comparison program and the corrective actions being taken if the specified program is not being performed as required by Section 12.5.3. The Annual Radiological Environmental Operating Report shall also include an annual summary of hourly meteorological data collected over the applicable 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 distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Annual Radiological Environmental Operating Report, the licensee 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.

• A single submittal may be made for a multiple unit station.

Page 93 of 268

Revision 9 February 27, 2017 The Annual Radiological Environmental Operating Report shall also include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or Station during the previous calendar year. This report shall also include an assessment of radiation 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. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM and in compliance with 10 CFR 20 and 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation." 12.7.2 Annual Radioactive Effluent Release Report** The Annual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluent from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. The Annual Radioactive Effluent Release Report shall include a list and description of unplanned releases of radioactive material in liquid effluents from the site to UNRESTRICTED AREAS and of unplanned releases of radioactive material in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY during the reporting period. The Annual Radioactive Effluent Release Report shall include any changes made during the reporting period to the Process Control Program as well as any major changes to Liquid, Gaseous or Solid Radwaste Treatment Systems, pursuant to Section 12.7.4. The Annual Radioactive Effluent Release Report shall also include the following: an explanation as to why the inoperability of liquid effluent monitoring instrumentation was not corrected within the time specified in Section 12.2.1 or 12.2.2, respectively; and description of the events leading to liquid holdup tanks exceeding the limits of the Quality Assurance Project Plan App.B. 12.7.2.1 Exceptions to Regulatory Guide 1.21 Reporting Requirements:

a. All references to "semiannual" are not applicable. The report will be submitted according to Quality Assurance Project Plan (QAPP).

b. Hourly meteorological data is recorded for all periods throughout the year, and quarterly summaries will be reported. Separate meteorological data for periods of batch releases are not required to be included.

c. Total body and significant organ doses to the maximally exposed individual from receiving-water-related exposure pathways will be provided. Associated population dose is not required to be included.

d. Organ doses to the maximally exposed individual in unrestricted areas from radioactive material in particulate form from all exposure pathways will be provided. Associated population dose is not required to be included.

e. Total body doses to the maximally exposed individual in unrestricted areas from direct radiation from the facility should be included in the report. Associated population dose is not required to be included.

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Revision 9 February 27, 2017

f. Total body doses to the population and average doses to individuals in the population from all receiving-water-related pathways are not required to be included.

g. Total body doses to the population and average doses to individuals in the population from gaseous effluents to a distance of 50 miles from the site and beyond will not be included.

• • A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

Page 95 of 268

Revision 9 February 27, 2017 12.7.3 Offsite Dose Calculation Manual CODCM) 12.7.3.1 Changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by QAPP. This documentation shall contain:

1. Sufficient Information to support the change together with the appropriate analyses or evaluations justifying the change(s); and

2. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

3. Documentation of the fact that the change has been reviewed and found acceptable by a Qualified Technical Review.

b. Shall become effective after the approval of the Decommissioning Plant Manager on the date specified by the Qualified Technical Review.

c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.,

month/year) the change was implemented. 12.7.4 Major Changes to Liquid and Gaseous Effluent Treatment Systems*** Licensee-initiated major changes to the Effluen~ Treatment Systems (liquid and gaseous):

a. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evalua.tion was reviewed by a Qualified Technical Review. The discussion of each change shall contain:

1) A summary of the evaluation that led to the determination that the change could be made in aycordance with 10 CFR 50.59;

2) Sufficient detailed information to totally support the reason for the change without benefit of additional and supplemental information;

3) A detailed description of the equ!pment, components, and processes involved and the interfaces With other plant systems.

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

5) An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF "(RE PUBLIC and to the general population that differ from those previously estimated in the License application and amendments thereto; Page 96 of 268 I

l

Revision 9 February 27, 2017 I

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

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

8) Documentation of the fact that the change was reviewed and found acceptable by a Qualified Technical Review.

b. Shall become effective upon review and acceptance by the Qualified Technical Review.

• • • Licensees may choose to submit the information called for in this standard as part of the biennial DSAR update.

Page 97 of 268

Revision 9 February 27, 2017 I APPENDIX A COMPLIANCE METHODOLOGY Page 98 of 268

Revision 9 February 27, 2017 APPENDIX A COMPLIANCE METHODOLOGY A.O INTRODUCTION This appendix reviews the offsite radiological limits applicable to Zion Station' and presents in detail the equations and procedures used to assess compliance with these limits. An introduction to the calculation approach used here is given in Chapter 4. The approach incorporates simplifications such as the following: Use of pre-calculated atmospheric transport parameters based on historical average atmospheric conditions (see Section 4.1.5). These atmospheric dispersion and deposition factors are defined in Chapter 4. The equations and parameters of this appendix are for use in calculating offsite radiation doses during routine operating conditions. They are not for use in calculating doses due to non-routine releases (e.g., accident releases). This section of the ODCM provides the methodological details for demonstrating compliance with the 10CFR20, 10CFR50 Appendix I, 10CFR72.104 and 40CFR190 radiological limits for liquid and gaseous effluents. An overview of the required compliance is given in Tables 2-1, 2-2, and 2-3. In Table 2-1, the dose components are itemized and referenced, and an indication of their regulatory application is noted. A more detailed compliance matrix is given in Table 2-3. Additionally, the locations of dose receivers for each dose component are given in Table 2-2. The following sections detail the required radiological dose calculations. A.1 AIRBORNE RELEASES A.1.1 Release Point Classifications The pattern of dispersion of airborne releases is dependent on the height of the release point relative to adjacent structures. For the equations of this appendix, each release point is classified as one of the following three height-dependent types, which are defined in Section 4.1.4:

• Stack (or Elevated) Release Point (denoted by the letter Sor subscripts)
• Ground Level Release Point (denoted by the letter G or subscript g)
• Vent (or Mixed Mode) Release Point (denoted by the letter V or subscript v)

The release point classifications of routine release points at Zion Station are stated in Table A-2. A.1.2 Dose Due to Noble Gas Radionuclides A.1.2.1 Gamma Air Dose Requirement RETS limit the gamma air dose due to noble gas effluents released from each reactor unit to areas at and beyond the unrestricted area boundary to the following:

• Less than or equal to 5 mrad per calendar quarter.
• Less than or equal to 1O mrad per calendar year.

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Revision 9 February 27, 2017 Equation The gamma air dose due to noble gases released in gaseous effluents is calculated by the following expression: Dr =(3.17E-8)LM;{(x/Q)~A;s +(x/Q)~A;v +(x/Q)~A; 9 } (A-1) i The summation is over noble gas radionuclides i. Gamma Air Dose [mrad] Dose to air due to gamma radiation from noble gas radionuclides released in gaseous effluents. 3.17E-8 Conversion Constant (seconds to years) [yr/sec] 3 M 1 Gamma Air Dose Conversion Factor [(mrad/yr)/(µCi/m )] Gamma air dose rate factor per unit of radioactivity release rate for radionuclide i. From Table 8-1 of Reg Guide 1.190. (x;o)~' (x/o)~' (x;o)~ Gamma-x/Q Factor Radioactivity concentration based on finite cloud methodology at a specific location per unit of radioactivity release rate from a stack, vent or ground level release, respectively. See Section 8.3.5 and Table F-5b of appendix F. Cumulative Radionuclide Release [µCi] Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively. Application RETS require determination of cumulative and projected gamma air dose contributions due to noble gases for the current calendar quarter and the current calendar year at least once per 31 days (see Sections 12.4 of Zion Station' RETS or Technical Specifications). Gamma air dose is calculated for the sector with the highest offsite (x/Q)Y and is compared with the RETS limits on gamma air dose. For a release attributable to a processing or effluent system shared by more than one reactor unit, the

• dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 10.

Page 100 of 268

Revision 9 February 27, 2017 A.1.2.2 Beta Air Dose Requirement RETS limit the beta air dose due to noble gases in gaseous effluents released from each reactor unit to areas at and beyond the unrestricted area boundary to the following:

• Less than or equal to 10 mrad per calendar quarter.
• Less than or equal to 20 mrad per calendar year.

Equation The beta air dose due to noble gases released in gaseous effluents is calculated by the following expression: 0 11 =(3.17E- a)L {N;l(x/Q)sAis + (x/Q}vA;v + (x/Q)9 A19 J} (A-2) i The summation is over noble gas radionuclides i. Beta Dose [mrad] Dose to air due to beta radiation from noble gas radionuclides released in gaseous effluents. 3.17E-8 Conversion Constant (seconds to years) [yr/sec] 3 Beta Air Dose Conversion Factor [(mrad/yr)/(µCi/m )] Beta air dose rate per unit of radioactivity concentration for radionuclide i. Take from Table C-9 of Appendix C. (x/Q)s Relative Concentration Factor (x/Q)v (xJQ)g Radioactivity concentration based on semi-infinite cloud methodology at a specified location per unit of radioactivity release rate for a stack, vent, or ground level release, respectively. See Section 4.1.6, Section B.3 of Appendix B, and Table F-5 of Appendix F. Cumulative Radionuclide Release [µCi] Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively. Application RETS require determination of cumulative and projected beta air dose contributions due to noble gases for the current calendar quarter and the current calendar year at least once per 31 days (see Section 12.4 of Zion Station RETS or Technical Specification). Beta air dose is calculated for the sector with the highest offsite (x/Q) and is compared with the RETS limit on beta air dose. Page 101 of 268

Revision 9 February 27, 2017 For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 1O. Page 102 of 268

Revision 9 February 27, 2017 A.1.2.3 Total Body Dose Requirement The total body dose, to any receiver is due, in part, to gamma radiation emitted from radioactivity in airborne effluents. This component is added to others to demonstrate compliance to the requirements of 40CFR 190 and 10CFR20. Equation The total body dose component due to gamma radiation from noble gases released in gaseous effluents is calculated by the following expression: Dra =(3.17E-8)LK;{(x/Q)~Ais +(x/Q)~Aiv +(x/Q)~Aig} (A-3) i The summation is over noble gas radionuclides i: Dre Total Body Dose [mrem] Dose to the total body due to gamma radiation from noble gas radionuclides released in gaseous effluents. 3.17E-8 Conversion Constant (seconds to years) [yr/sec] Gamma Total Body Dose Conversion Factor [(mrem/yr)/(uCi/m3)] Gamma total body dose factor due to gamma emissions for noble gas radionuclide i released from a stack, vent or ground level release point, respectively. Taken from Table C-9 of Appendix C. Cumulative Radionuclide Release [µCi] Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively. Application The total body dose is also calculated for the 40CFR190 and 10CFR20 compliance assessments. In some cases, the total body dose may be required in 10CFR50 Appendix I assessments (See Table 2-1). A.1.2.4 Skin Dose Requirement There is no regulatory requirement to evaluate skin dose. However, this component is evaluated for reference as there is skin dose design objective contained in 10CFR50 Appendix I. Note that in the unlikely event that if beta air dose guideline is exceeded, then the skin dose will require evaluation. Equation The part of skin dose due to noble gases released in gaseous effluents is calculated by the following expression: DsK = (3.17E-8) L {Li[ (x/Q) A1s +(x/Q)vAiv + (x/Q) 5 9 A; 9 ] i (A-4)

                                      + (1.11)M; [ (x/Q)~A;s + (x/Q)~A;v + (x/Q)~A;    9 ]}

Page 103 of 268

Revision 9 February 27, 2017 The summation is over noble gas radionuclides i. Skin Dose [mrem] Dose to the skin due to beta and gamma radiation from noble gas radionuclides released in gaseous effluents. 3 Bet~ Skin Dose Conversion Factor [(mrem/yr)/(µCi/m )] Beta skin dose rate per unit of radioactivity concentration for radionuclide i. Taken from Table C-9 of Appendix C. 1.11 Conversion Constant (rads in air to rem in tissue) [mrem/mrad] All other terms have been previously defined. Application The skin dose is calculated for reference only. A.1.3 Dose Rate Due to Noble Gas Radionuclides A.1.3.1 Total Body Dose Rate Requirement RETS limit the total body dose rate due to noble gases in gaseous effluents released from a site to areas at and beyond the site boundary to less than or equal to 500 mrem/yr at all times. (see Section 12.4 of Zion Station RETS and Technical Specifications) Equation The total body dose rate due to noble gases released in gaseous effluents is calculated by the following expression: (A-5) The summation is over noble gas radionuclides i . Ora Total Body Dose Rate [mrem/yr] Dose rate to the total body due to gamma radiation from noble gas radionuclides released in gaseous effluents. Release Rate [µCi/sec] Measured release rate of radionuclide i from a stack, vent or ground level release point, respectively. All other terms have been previously defined. Page 104 of 268

Revision 9 February 27, 2017 Application RETS require the dose rate due to noble gases in gaseous effluents be determined to be within the above limit in accordance with methodology specified in the ODCM (see Section 12.4 of Zion Stations RETS and Technical Specifications). To comply with this specification, Zion Station uses an effluent radiation monitor setpoint corresponding to an offsite total body dose rate at or below the limit (see Chapter 10). In addition, Zion Station assesses compliance by calculating offsite total body dose rate on the basis of periodic samples obtained in accordance with station procedures. A.1.3.2 Skin Dose Rate Requirement RETS limit the skin dose rate due to noble gases in gaseous effluents released from a site to areas at and beyond the site boundary to less than or equal to a dose rate of 3000 mrem/yr at all times. (See Section 12.4 of Zion Stations RETS and/or Technical Specifications) Equation The skin dose rate due to noble gases released in gaseous effluents is calculated by the following expression: DsK = L{L;[{x/Q)sQis +{x/Q)vQiv +(x/Q) Q;g] 9 i (A-6)

                               + (1.11) M; [ {x/Q)~ Qis + {x/Q)~ Qiv + {x/Q)~ Qig]}

The summation is over noble gas radionuclides i. DsK Skin Dose Rate [mrem/yr] Dose rate to skin due to beta and gamma radiation from noble gas radionuclides released in gaseous effluents. Release Rate [µCi/sec] Measured release rate of radionuclide i from a stack, vent or ground level release point, respectively. All other terms been previously defined. Application RETS require the dose rate due to noble gases in gaseous effluents to be determined to be within the above limit in accordance with methodology specified in the ODCM. (See Section 12.4 of Zion Solutions' RETS and Technical Specifications.) To comply with this specification, Zion Station uses an effluent radiation monitor setpoint corresponding to an offsite skin dose rate at or below the limit (see Chapter 10). In addition, Zion Solutions' assesses compliance by calculating offsite skin dose rate on the basis of samples obtained periodically in accordance with site procedures. Page 105 of 268

Revision 9 February27,2017 I. A.1.4 Dose Due to Non-Noble Gas Radionuclides Requirement RETS provide the following limits, based on 10CFR50 Appendix I, on the dose to a member of the public from specified non-noble gas radionuclides in gaseous effluents released from each reactor unit to areas at and beyond the unrestricted area boundary: Less than or equal to 7.5 mrem to any organ during any calendar quarter. Less than or equal to 15 mrem to any organ during any calendar year. The individual dose components are also required as part of the 40CFR190 assessments and combined as part of the 10CFR20 assessment (See Section A.4 ). The dose due to radionuclides deposited on the ground is considered to be a component of the deep dose equivalent for 10CFR20 compliance and an organ (and total body) dose component for 10CFR50 Appendix I and 40CFR190 compliance. In accordance with the definition of dose in Regulatory Guide 1.109, the term "dose" in this document when applied to individuals, is used instead of the more precise term "dose equivalent," as defined by the International Commission on Radiological Units and Measurements (ICRU). When applied to the evaluation of internal deposition of radioactivity, the term "dose" as used here, includes the prospective dose component arising from retention in the body beyond the period of environmental exposure, i.e., the dose commitment. The dose commitment is evaluated over a period of 50 years. Assessments for 10CFR50 Appendix I compliance are made for 4 age groups (adulUteenager/child/infant) using Regulatory Guide 1.109 (Reference 6) dose conversion factors. Equation The dose is calculated for releases in the time period under consideration. Specifically, the dose is calculated as follows: D~rG =(3.17E-8)_L_L(WsRaipiAis + WvRaipiAiv + W9 RaipiA;9 ] (A-7) p I The summation is over pathways p and non-noble gas radionuclides i. Dose Due to Non-Noble Gas Radionuclides [mrem] Dose due to non-noble gases (tritium and particulates) to age group a, and to organ j. 3.17E-8 Conversion Constant (seconds to years) [yr/sec] Relative Concentration Factor Radioactive concentration at a specific location per unit of radioactivity release rate or concentration for stack, vent or ground level release, respectively. W 5 , Wv. or W 9 = (x/0) 5 , (x/O)v or (x/0) 9 for immersion, inhalation and all tritium pathways. W 5 , Wv, or W 9 = (D/Q) 5 , (D/O)v or (D/Q) 9 for ground plain and all ingestion pathways. Page 106 of 268

Revision 9 February 27, 2017 Relative Concentration Factor Radioactivity concentration based on semi-infinite cloud model at a specified location per unit of radioactivity release rate for a stack, vent, or ground level release, respectively. See Section 4.1.6, Section B.3 of Appendix B, and Table F-5 of Appendix F. (D/Q)s, (D/Q)v, (D/Q)g Relative Deposition Factor Radioactivity concentration at a specified location per unit of radioactivity release concentration for a stack, vent, or ground level release, respectively. See Section 4.1.6, Section B.3 of Appendix B, and Table F-6 of Appendix F. 2 Ra1pJ Site-Specific Dose Factor [(m mrem/yr)/(µCi/sec)] 3 or [(mrem/yr)/(µCi/m )] Site-specific dose factor for age group a, nuclide i, pathway p and organ

j. Pathway included are ground plane exposure, inhalation, vegetation ingestion, milk ingestion and meat ingestion. Values of Raipi are provided in Appendix F.

Cumulative Radionuclide Release [µCi] Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively. Application RETS require cumulative and projected dose contributions for the current calendar quarter and the current calendar year for the specified non-noble gas radionuclides in airborne effluents to be determined at least once per 31 days (see Section 12.4 of Zion Stations' RETS and Technical Specifications). To comply with this specification, Zion Station obtains and analyzes samples in accordance with the radioactive gaseous waste or gaseous effluent sampling and analysis program in its RETS. In accordance with NUREG 0133 (Reference 14), dose due to non-noble gases is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure. The inhalation and ground plane exposure pathways are considered to exist at all locations. Thefood ingestion pathways at a specific location are considered based on their existence as determined by land use census. The values used for (x/Q) and (D/Q) correspond to the applicable pathway location. For a release attributable to a processing or effluent system shared by more than one reactor, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 10. The dose evaluated is also included as part of the 10CFR20 and 40CFR190 assessment (See Section A.4). A.1.4.1 Ground Deposition The site-specific dose factor for ground deposition of radioactivity is considered to be a total body dose component and is calculated by the following expression: Page 107 of 268

Revision 9 February 27, 2017 Rai{GP)i [D/Q] = K' K" (0.7)DFG; 1- e-A;lb] A; (A-8) [ 2 Rai{GP)i [D/Q] Ground Plane Deposition Dose Factor [(m mrem/yr)/(µCi/sec)] Site-specific ground plane dose factor for age group a, nuclide i and organ j. The ground plane dose is calculated using (D/Q). K' Conversion Constant (1 E6 pCi per µCi) [pCi/µCi] K" Conversion Constant (8760 hr/yr) [hr/yr] 0.7 Shielding Factor; a factor which accounts for dimensionless shielding due to occupancy of structures. 2 Ground Plane Dose Conversion Factor [(mrem/hr)/(pCi/m )] Dose rate to the total body per unit of surface radioactivity concentration due to standing on ground uniformly contaminated with radionuclide i. Taken from Table C-10 of Appendix C. Note that ground plane dose factors are only given for the total body and no age group. Doses to other organs are assumed to be equal to the total body dose. All age groups are assumed to receive the same dose. Radiological Decay Constant Radiological decay constant for radionuclide i. See Table C-7 of Appendix C. Time Period of Ground Deposition [hr] Time period during which the radioactivity on the ground is assumed to have been deposited. See Table C-1 of Appendix C. Application The ground plane exposure pathway is considered to exist at all locations. A.1.4.2 Inhalation The site-specific dose factor for inhalation is calculated by the following expression: Ra1{1nha1)1 fx/Q] = K'BRaDFAaii (A-9) 3 Rai{lnhal)i fx/Q] Inhalation Pathway Dose Factor [(mrem/yr)/(µCi/m )] Site-specific inhalation dose factor for age group a, nuclide i and organ j. The inhalation dose is calculated using (x/Q). K' Conversion Constant (1 E6 pCi per µCi) [pCi/µCi] Individual Air Inhalation Rate [m 3/yr] Page 108 of 268

Revision 9 February 27, 2017 The air intake rate for individuals in age group a. See Table C-2 of Appendix C. DFAa1J Inhalation Dose Conversion Factor [mrem/pCi] Dose commitment to an individual in age group a to organ j per unit of activity of radionuclide i inhaled. Taken from Tables E-7 through E-10 of Regulatory Guide 1.109. The value for H-3 is taken from NUREG 4013 (Reference 107). Application The inhalation exposure pathway is considered to exist at all locations. A.1.4.3 Food Ingestion Pathway Dose Factors Application Food ingestion pathway doses are calculated at locations indicated by the land use census survey. If no real pathway exists within 5 miles of the station, the cow-milk pathway is assumed to be located at 5 miles. Food pathway calculations are not made for sectors in which the offsite regions near the station are over bodies of water. A.1.4.3.1 Vegetation Ingestion Pathway Dose Factor The dose factor for consumption of vegetables is calculated by the following expression: (A-10) 2 Ra;(veg)i [D/Q] Vegetation Ingestion Pathway Dose Factor [(m mrem/yr)/(µCi/sec)] Site-specific vegetation ingestion dose factor for age group a, nuclide i and organ j. With the exception of H-3, the vegetation dose is calculated using (D/Q). K' Conversion Constant (1 E6 pCi per µCi) [pCi/µCi] r Vegetation Retention Factor dimensionless Agricultural Productivity Yield Radiological Decay Constant [1/sec] Radiological decay constant for radionuclide i. See Table C-7 of Appendix C. Weathering Decay Constant [1/sec] Removal constant for physical loss of activity by weathering. See Table C-1 of Appendix C. DFLa1J Ingestion Dose Conversion Factor [mrem/pCi] Ingestion dose conversion factor for age group a, nuclide i and organ j. Converts pCi ingested to mrem. Taken from Tables E-11 though E-14 of Page 109 of 268

Revision 9 February 27, 2017 Regulatory Guide 1.109. The value for H-3 is taken from NU REG 4013 (Reference 107). u/ Consumption Rate for Fresh Leafy Vegetation [kg/yr] Consumption rate for fresh leafy vegetation for age group a. Consumption Rate for Stored Vegetation [kg/yr] Consumption rate for stored vegetation for age group a. Local Leafy Vegetation Fraction dimensionless Fraction of the annual intake of fresh leafy vegetation which is grown locally. Local Stored Vegetation Fraction dimensionless Fraction of the annual intake of stored vegetation which is grown locally. Environmental Transport Time - Fresh Vegetation [sec] Average time between harvest of leafy vegetation and its consumption. Environmental Transport Time - Stored Vegetation [sec] Average time between harvest of stored vegetation and its consumption. The tritium dose from the vegetation pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the tritium vegetation pathway is:

                                                                                                      *(A-11) 3 Tritium Vegetation Ingestion Pathway Dose Factor          [(mrem/yr)/(µCi/m     'J Site-specific tritium vegetation ingestion dose factor for age group a and organ j. The tritium vegetation dose is calculated using x/Q.

K"' Conversion Constant (1 E3 gm per Kg) [gm/Kg] 3 H Absolute Atmospheric Humidity [gm/m ] 0.75 Water Fraction dimensionless The fraction of total vegetation that is water. 0.5 Specific Activity Ratio* dimensionless Page 110 of 268

Revision 9 February 27, 2017 A.1.4.3.2 Milk Ingestion Pathway Dose Factor The dose factor for consumption of milk is calculated by the following expressions: (A-12) 2

• Rai(Milk)j [D/Q] Milk Ingestion Pathway Dose Factor [(m mrem/yr)/(µCi/sec)]

Site-specific milk ingestion dose factor for age group a, nuclide i and organ j. With the exception of H-3, the milk dose factor is calculated using (D/Q). K' Conversion Constant (1 E6 pCi per µCi) [pCi/µCi] QF Feed Consumption [Kg/da] Amount of feed consumed by milk animal each day. See Table C-1 of AppendixC. Uam Milk Consumption Rate [I/yr] Milk consumption rate for age group a. Fm Stable Element Transfer Coefficient for Milk [da/I] Fraction of animal's daily intake of a particular chemical element which appears in each liter of milk (pCi/I in milk per pCi/da ingested by animal). See Table C-3 of Appendix C. Pasture Time Fraction dimensionless Fraction of year that animal is on pasture. Pasture Grass Fraction dimensionless Fraction of animal feed that is pasture grass while animal is on pasture. Agricultural Productivity Yield - Pasture Grass The agricultural productivity by unit area of pasture feed grass. Ys Agricultural Productivity Yield - Stored Feed The agricultural productivity by unit area of stored feed. Environmental Transport Time - Stored Feed [sec] Average time between harvest to consumption of stored feed by milk animal. Page 111of268

Revision 9 February 27, 2017 Environmental Transport Time - Pasture to Consumption [sec] Average time from pasture, to milk animal, to milk, to consumption. All other terms have been previously defined. The tritium dose from the milk pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the tritium milk pathway is: (A-13) 3 Ra(H-3XMilk)j [x/a] Tritium Milk Ingestion Pathway Dose Factor [(mrem/yr)/(µCi/m )] Site-specific tritium milk ingestion dose factor for age group a and organ

j. The tritium milk dose is calculated using x/Q.

K"' Conversion Constant (1 E3 gm per Kg) [gm/Kg] 3 H Absolute Atmospheric Humidity [gm/m ] 0.75 Water Fraction dimensionless The fraction of total vegetation that is water. 0.5 Specific Activity Ratio dimensionless All other terms have been previously defined. A.1.4.3.3 Meat The dose factor for consumption of meat is calculated by the following expression: (A-14) 2 Rai(Meat)j [D/Q] Meat Ingestion Pathway Dose Factor [(m mrem/yr)/(µCi/sec)] Site-specific meat ingestion dose factor for age group a, nuclide i and organ j. With the exception of H-3, the meat dose factor is calculated using (D/Q). Meat Consumption Rate [I/yr] Meat consumption rate for age group a. Stable Element Transfer Coefficient for Meat [da/Kg] Fraction of animal's daily intake of a particular chemical element which appears in each liter of meat (pCi/Kg in meat per pCi/da ingested by animal). See Table C-3 of Appendix C. Page 112 of 268

Revision 9 February 27, 2017 Environmental Transport Time - Stored Feed [sec] Average time between harvest to consumption of stored feed by meat animal. tf Environmental Transport Time - Pasture to Consumption [sec] Average time from pasture, to meat animal, to meat, to consumption. All other terms have been previously defined. The tritium dose from the meat pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the tritium meat pathway is: (A-15) Ra(H-3)(Meat)j [x/Q] Tritium Meat Ingestion Pathway Dose Factor [(mrem/yr)/(µCi/m 3 )] Site-specific tritium meat ingestion dose factor for age group a and organ

j. The tritium meat dose is calculated using x!Q.

K"' Conversion Constant (1 E3 gm per Kg) [gm/Kg] 3 H Absolute Atmospheric Humidity [gm/m ] 0.75 Water Fraction dimensionless The fraction of total vegetation that is water. 0.5 Specific Activity Ratio dimensionless All other terms have been previously defined. A.1.5 Dose Rate Due to Non-Noble Gas Radionuclides Requirement RETS limit the dose rate to any organ, due to radioactive materials in gaseous effluents released from a site to areas at and beyond the site boundary, to less than or equal to a dose rate of 1500 mrem/yr (see Section 12.4 of ZionSo/utions' RETS and Technical Specifications). Typically the child is considered to be the limiting receptor in calculating dose rate to organs due to inhalation of non-noble gas radionuclides in gaseous effluents. Equation The dose rate to any child organ due to inhalation is calculated by the following expression: (A-16) The summation is over non-noble gas radionuclides i. Page 113 of 268

Revision 9 February 27, 2017

• NNG D(Child)i{lnhal)j Inhalation Dose Rate [mrem/yr]

Dose rate to the child age group from radionuclide i, via the inhalation pathway to organ j due to non-noble gas radionuclides. 3 R(Chlld)l(lnhal)j Inhalation Dose Factor [(mrem/yr)/(µCi/m )] Inhalation dose factor for child age group for radionuclide i, and organ j. This dose factor is defined by Equation A-9. Radionucli,de Release Rate [µCi/sec] Measured release rate of radionuclide i from a stack, vent, or ground level release point, respectively. All other terms have been previously defined. Application RETS require the dose rate due to non-noble gas radioactive materials in airborne effluents be determined to be within the above limit in accordance with a sampling and analysis program specified in the RETS (see Section 12.4 of ZionSo/utions' RETS and Technical Specifications). To comply with this specification, Zion Solutions' obtains and analyzes samples in accordance with the sampling and analysis program in its RETS. The child organ dose rate due to inhalation is calculated in each sector at the location of the highest offsite x!Q. The result for the sector with the highest organ inhalation dose rate is compared to the limit. A.1.6 Operability and Use of Gaseous Effluent Treatment Systems Requirement 10CFRSO Appendix I and the station RETS require that the ventilation exhaust treatment system and the waste gas holdup system be used when projected offsite doses in 31 days, due to gaseous effluent releases, from each reactor unit, exceed any of the following limits:

• 0.2 mrad to air from gamma radiation.
• 0.4 mrad to air from beta radiation.
• 0.3 mrem to any organ of a member of the public.

ZionSolutions' is required to project doses due to gaseous releases from the site at least once per 31 days. Equation Offsite doses due to projected releases of radioactive materials in gaseous effluents are calculated using Equations A-1, A-2 and A-7. Projected cumulative radionuclide releases are used in place of measured cumulative releases A; 8 , A;v and A; 9 . Application For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in Chapter 10 of this manual. Page 114 of 268

Revision 9 February 27, 2017 A.2 LIQUID RELEASES A.2.1 Dose Requirement The design objectives of 10CFR50, Appendix I and RETS provide the following limits on the dose to a member of the public from radioactive materials in liquid effluents released from each reactor unit to restricted area boundaries: During any calendar quarter, less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ. During any calendar year, less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ. The organ doses due to radioactivity in liquid effluents are also used as part of the 40CFR 190 compliance and are included in the combination of doses to determine the total dose used to demonstrate 10CFR20 compliance. (See Section A.4) Dose assessments for 10CFR50 Appendix I compliance are made for four age groups (adult/teenager/child/infant) using NUREG 0133 (Reference 14) methodology and Regulatory Guide 1.109 (Reference 6) dose conversion factors. Equation The dose from radioactive materials in liquid effluents considers the contributions for consumption of fish and potable water. All of these pathways are considered in the dose assessment unless demonstrated not to be present. While the adult is normally considered the maximum individual, the methodology provides for dose to be calculated for all four age groups. The dose to each organ (and to the total body) is calculated by the following _expression: D~;q = F At LLAaipjci (A-17) p I The summation is over exposure pathways p and radionuclides i. Organ and Total Body Dose Due to Liquid Effluents [mrem] Dose to organ j (including total body) of age group a due to radioactivity in liquid effluents. F Near Field Average Dilution Factor dimensionless Dilution in the near field averaged over the period of interest. Defined as: Waste Flow F=------- (A-18) Dilution Flow x Z Waste Flow Liquid Radioactive Waste Flow [gpm] The average flow during .disposal from the discharge structure release point into the receiving water body. Dilution Flow Dilution Water Flow During Period of Interest [gpm] Page 115 of 268

Revision 9 February 27, 2017 z Discharge Structure Mixing Factor dimensionless Site-specific factor to account for the mixing effect of the discharge structure. The factor addresses the dilution which occurs in the near field between the discharge structure and the body of water containing the fish in the liquid ingestion pathway. From Table F-1, Appendix F. At Duration of Release [hrs] Average Radionuclide Concentration [µCi/ml] Average concentration of radionuclide i, in the undiluted liquid effluent during time period At. Aa1pJ Site-Specific Liquid Dose Factor [(mrem/hr)/(µCi/ml)] Site-specific dose factor for age group a, nuclide i, liquid pathway p and organ j. The pathways included are potable water and fish ingestion. Aaipi is defined for these pathways in the following sections. Values for AaiPi are provided in 'Appendix F. A 2.1.1 Potable Water Pathway The site-specific potable water pathway dose factor is calculated by the following expression: (A-19) Where: Aal(PW)J Site-Specific Dose Factor for Potable Water [(mrem/hr)/(µCi/ml)] Pathway Site-specific potable water ingestion dose factor for age group a, nuclide i and organ j. Conversion Constant ( 1.14E05) [(yr-pCi-ml)/(hr-µCi-1)] Units constant to convert years to hours, pCi to µCi and liters to ml. Potable Water Consumption Rate [I/yr] Potable water consumption rate for age group a. Taken from Table E-5 of Regulatory Guide 1.109. Potable Water Dilution Factor dimensionless Dilution factor from the near field area within one-quarter mile of the release point to the potable water intake. From Table F-1, Appendix F. DFLa1J Ingestion Dose Conversion Factor [mrem/pCi] Ingestion dose conversion factor for age group a, nuclide i and organ j. Converts pCi ingested to mrem. Taken from Tables E-11 though E-14 of Page 116 of 268 L

Revision 9 February 27, 2017 Regulatory Guide 1.109. The value for H-3 is taken from NU REG 4013 (Reference 107). A.2.1.2 Fish Ingestion Pathway The site-specific fish ingestion pathway dose factor is calculated by the following expression: (A-20) Where: Aal(Flsh)J Site-Specific Dose Factor for Potable Water [(mrem/hr)/(µCi/ml)] Pathway Site-specific fish ingestion dose factor for age group a, nuclide i and organ j. u/ Fish Consumption Rate [kg/yr] Fish consumption rate for age group a. Taken from Table E-5 of Regulatory Guide 1.109. Bioaccumulation F~ctor [(pCi/kg)/(pCi/I)] Bioaccumulation factor for nuclide i in fresh water fish. Taken from Table C-8 of Appendix C. All other terms have been previously defined. Application RETS require determination of cumulative and projected dose contributions from liquid effluents for the current calendar quarter and the current calendar year at least once per 31 days. (see Section 12.3 of ZionSolutions' RETS and/or Technical Specifications). For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM.Chapter 10. A.2.2 Liquid Effluent Concentrations Requirement Requirement One method of demonstrating compliance to the requirements of 10CFR20.1301 is to demonstrate that the annual average concentrations of radioactive material released in gaseous and liquid effluents do not exceed the values specified in 10CFR20 Appendix B, Table 2, Column 2. (See 10CFR 20.1302(b)(2).) However, as noted in Section A.5.1, this mode of 10CFR20.1301 compliance has not been elected. As a .means of assuring that annual concentration limits will not be exceeded, and as a matter of policy assuring that doses by the liquid pathway will be ALARA; RETS provides the following restriction: "The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to ten times the concentration values in Appendix B, Table 2, Column 2 to 10CFR20.1001-20,2402." This also meets the requirement of Station Technical Specifications and RETS. Page 117 of 268

Revision 9 February 27, 2017 Equation According to the footnotes to 10CFR20 Appendix B, Table 2, Column 2, if a radionuclide mix of known composition is released, the concentrations must be such that L(; ci ) 10 ECL 1 s; 1 (A-21) where the summation is over radionuclide i. Radioactivity Concentration in [µCi/ml] Liquid Effluents to the Unrestricted Area Concentration of radionuclide i in liquid released to the unrestricted area. ECL1 Effluent Concentration Limit in Liquid [µCi/ml] Effluents Released to the Unrestricted Area The allowable annual average concentration of radionuclide i in liquid effluents released to the unrestricted area. This concentration is specified in 10CFR20 Appendix B, Table 2; Column 2. Concentrations for noble gases are different and are specified in the stations' Technical Specifications/RETS. 10 Multiplier to meet the requirements of Technical Specifications. If either the identity or concentration of any radionuclide in the mixture is not known, special rules apply. These are given in the footnotes in 10CFR20 Appendix B, Table 2, Column 2. Application The RETS and Technical Specifications require a specified sampling and analysis program to assure that liquid radioactivity concentrations at the point of release are maintained within the required limits. To comply with this provision, Zion Solutions' obtains and analyzes samples in accordance with the radioactive liquid waste (or effluent) sampling and analysis program in its RETS. Radioactivity concentrations in tank effluents are determined in accordance with Equation A-22 in the next section. Comparison with the Effluent Concentration Limit is made using Equation A-21. A.2.3 Tank Discharges When radioactivity is released to the unrestricted area with liquid discharge from a tank (e.g., a radwaste discharge tank), the concentration of a radionuclide in the effluent is calculated as follows:

c. = C~ Waste Flow (A-22)

             '    ' Dilution Flow Concentration in Liquid effluent to the unrestricted area.             [µCi/ml]

Concentratio!J of radionuclide i in liquid released to the unrestricted area. Concentration in the Discharge Tank [µCi/ml] Measured concentration of radionuclide i in the discharge tank. Page 118 of 268

Revision 9 February 27, 2017 All other terms have been previously defined. A.2.4 Tank Overflow Requirement To limit the consequences of tank overflow, the quantity of radioactivity that may be stored in unprotected outdoor tanks is limited. Unprotected tanks are 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. The specific objective is to provide assurance that in the event of an uncontrolled release of a tank's contents, the resulting radioactivity concentrations beyond the unrestricted area boundary, at the nearest potable water supply and at the nearest surface water supply, will be less than the limits of 10CFR20 Appendix B, Table 2, Column 2. Application Table F-1 of Appendix F provides information on the limits for Zion Station. A.2.5 ,Operability and Use of the Liquid Radwaste Treatment System Requirement The design objectives of 10CFR50, Appendix I and RETS/Technical Specifications require that the liquid radwaste treatment system be operable and that appropriate portions be used to reduce releases of radioactivity when projected doses due to the liquid effluent from each reactor unit to restricted area boundaries exceed either of the following (see Section 12.3 of ZionSolutions' RETS or Technical Specifications);

• 0.06 mrem to the total body in a 31 day period.
• 0.2 mrem to any organ in a 31 day period.

Equation Offsite doses due to projected releases of radioactive materials in liquid effluents are calculated using Equation A-17. Projected radionuclide release concentrations are used in place of measured concentrations, Ci. A.2.6 Drinking Water ZionSolutions' has requirements for calculation of drinking water dose that are related to 40CFR141, the Environmental Protection Agency National Primary Drinking Water Regulations. These are discussed in Section A.6. A.2.7 Non-routine Liquid Release Pathways Cases in which normally non-radioactive liquid streams (such as the Service Water) are found to contain radioactive material are non-routine will be treated on a case specific basis if and when this occurs. Since Zion Station has sufficient capacity to delay a liquid release for reasonable periods of time, it is expected that planned releases will not take place under these circumstances. Therefore, the liquid release setpoint calculations need not and do not contain provisions for treating multiple simultaneous release pathways. A.3 DOSE DUE TO CONTAINED SOURCES There are multiple types of contained sources of radioactivity which contribute to Zion Solutions' offsite radiological dose assessments. When the ISFSI if fully loaded it will contain 61 Vertical Concrete Casks (VCCs) containing Spent Nuclear Fuel and 4 VCCs containing Greater Than Class C (GTCC) Waste. Page 119 of 268

Revision 9 February 27, 2017 The GTCC waste is composed primarily of reactor internals segments from both Unit 1 and Unit 2. There is a waste staging area in the Southern region of the Radiological Restricted Area for 8-120 liners containing Waste Class A, B and C. This waste is composed primarily of reactor internals segments from both Unit 1 and 2. These 8-120s are stored inside of concrete Rad Vaults then surrounded by several feet of soil above ground level. At various times throughout D&D, there will be various rail cars, lntermodals, Sealands, and various other waste containers staged onsite prior to shipment to a disposal facility. All of these various sources contribute to offsite dose from both directly emitted radiations and radiations due to skyshine from directly emitted radiations. A.3.1 Dose from Onsite Radioactive Waste Storage Low-level radioactive waste may be stored at Zion in the following types of containers and storage areas:

• Concrete vaults
• Butler buildings/warehouses
• Shipping containers while awaiting shipment
• Independent Spent Fuel Storage Installation (ISFSI) Facilities The dose rates resulting from these containers and storage areas will be monitored frequently as they are being utilized, and if necessary, a dose calculation performed to assess projected dose rates from such containers and storage areas. Dose calculations shall be documented in site specific Technical Support Documents and referenced in the ODCM.

A.4 Total Dose Limits (10CFR20, 10CFR72 and 40CFR190) The regulatory requirements of 10CFR20, 10CFR72 and 40CFR 190 each limit total dose to individual members of the public without regard to specific pathways. The only significant exposure pathways for light water reactors included in 10CFR20, 10CFR72 and 40CFR 190 not addressed by 10CFRSO Appendix I are the direct radiation pathway and exposure from on-site activity by members of the public. Sections A.1 and A.2 considered organ doses from the gaseous and liquid effluent streams for purposes of compliance with 10CFR50 Appendix I. Section A.3 addresses the direct radiation component that must be considered for 10CFR20, 10CFR72 and 40CFR190 compliance. The following sections will describe the methodology of assessing direct radiation dose and then the manner in which the various doses are combined to obtain the appropriate "total" for regulatory compliance purposes. Although annual dose limits in 10CFR20 are now expressed in terms of Total Effective Dose Equivalent (TEDE) 40CFR190limits1=1re still stated as organ 'dose. The NRC continues to require 10CFR50 Appendix I, 10CFR72 and 40CFR1~0 doses to be reported in terms of organ dose. Due to the.fact that organ dose limits set forth in 40CFR1~0 are substantially lower than those of 10CFR20 (25 mrem/yr vs 100 mrem/yr), the NRC has stated that demonstration of compliance with the dose limits in 40CFR190 will be deemed as demonstration of compliance with the dose limits of 10CFR20 for most facilities (Reference 104). In addition to compliance with 40CFR190 it may be necessary for a nuclear power plant to address dose from on-site activity by members of the public. A.4.1 External Total B~dy Dose The external total body dose is comprised of the following parts:

1) Total body dose due to noble gas radionuclides in gaseous effluents (Section A.1.2),

2) Dose due to radioactive waste and the ISFSI (Section A.3.1) and

3) Total body dose due to radioactivity deposited on the ground (Section A.1.4.1 ).

Page 120 of 268

Revision 9 February 27, 2017 The external total body dose due to radioactivity deposited on the ground is accounted for in the determination of the non-noble gas dose (See Equations A-7 and A-8) and is not considered here. Page 121 of 268

Revision 9 February 27, 2017 The total external total body dose, DEx, is given by: (A-23) Total External Total Body Dose [mrem] Total external total body dose due to irradiation by external sources at the location of interest. Noble Gas Total Body Dose [mrem] External total body dose due to gamma radiation from noble gas radionuclides released in gaseous effluents at the location of interest. See Equation A-3. Dose From On-Site Storage Facilities [mrem] External total body dose due to gamma radiation from on-site storage facilities at the location of interest. See Section A.3.1. A.4.2 Total Dose The total dose, DToi, in the unrestricted area to a member of the public due to plant operations is given by: D Tot = DEx + DLiq a]

                                                               +ON.NG aJ                                  (A-24) where:

0Tot Total Dose To Member of Public [mrem] Total off-site dose to a member of public due to plant operations. Total External Total Body Dose [mrem] Total body dose due to external exposure to noble gases and on-site radioactive waste storage. Liquid Effluent Dose [mrem] Dose due to liquid effluents to age group a and organ j. The age group and organ with the highest dose from liquid effluents is used. Non-Noble Gaseous Effluent Dose [mrem] Dose due to non-noble gaseous effluents to age group a and organ j. The age group and organ with the highest dose from non-noble gas effluents is used. Page 122 of 268

Revision 9 February 27, 2017 A.5 COMPLIANCE TO TOTAL DOSE LIMITS A.5.1 Total Effective Dose Equivalent Limit-10CFR20 Compliance Requirement ZionSolutions' RETS limits the Total Effective Dose Equivalent (TEDE) to an annual limit of 100 mrem, as required by 10CFR20.1301 (a)(1 ). Demonstration of compliance with the limits of 40CFR190 (per Section 4.5.2) will be considered to demonstrate compliance with the 100 mrem/year limit. A.5.1.1 Dose to a Member of the Public in the Unrestricted Area The NRG has stated that demonstration of compliance with the limits of 40CFR190 or with the design objectives of Appendix I to 10CFR50 will be deemed to demonstrate compliance with the limits of 10CFR20.1301 {a)(1 ). Power reactors that comply with 10CFR50 Appendix I may also have to demonstrate that they are within the 25 mrem limit of 40CFR190 (See Reference 104). Zion Station ISFSI pad operations are required to demonstrate compliance with 10CFR72.104 limits. A.5.1.2. Dose to a Member of the Public in the Restricted Area In August of 1995, a revision to 10CFR20 was implemented that changed the definition of a member of the public. NUREG/CR-5569, "Health Physics Positions Database" Question 26(a) clarifies dose to a member of the public while inside the Restricted Area. "By definition, and with the exceptions given in the definitions of "occupational dose", any dose received by any individual in a "restricted area" is an "occupational dose." No one in a restricted area is a "member of the public."" Non-trained radiation workers are administratively restricted to less than :160 total hours on site property per year. Application Evaluation of the 40CFR190 dose is used to demonstrate compliance to 10CFR20, 10CFR72 and satisfy station RETS and Technical Specifications (see Chapter 12). A.5.2 Total Dose due to the Uranium Fuel Cycle (40CFR190) Requirement RETS, 40CFR190 and 10CFR72.104 limit the annual (calendar year) dose or dose commitment to any member of the public due to releases of radioactivity arid to radiation from uranium fuel cycle sources to the following:

• Less than or equal to 25 mrem to the total body.
• Less than or equal to 25 mrem to any organ except the thyroid.
• Less than or equal to 75 mrem to the thyroid.

Total Dose Components This requirement includes the total dose from operations at the nuclear power station. This includes doses due to radioactive effluents (airborne and liquid) and dose due to direct radiation from non-effluent sources (e.g., sources contained in systems on site such as the ISFSI). The operations comprising the uranium fuel cycle are specified in 40CFR190.02(b). The following are included to the extent that they directly support the production of electrical power for public use utilizing nuclear energy:

• Milling of uranium ore.
• Chemical conversion of uranium.

Page 123 of 268

Revision 9 February 27, 2017

• Isotopic enrichment of uranium.
• Fabrication of uranium fuel.
• Generation of electricity by a light-watered-cooled nuclear power plant using uranium fuel.
• Reprocessing of spent uranium fuel.

Excluded are:

• Mining operations.
• Operations at waste disposal sites.
• Transportation of any radioactive material in support of these operations.
• The re-use of recovered non-uranium special nuclear and by-product materials from the cycle.

The different methods of Decommissioning, SAFSTOR, ENTOMB and DEGON, are not mentioned in 40CFR190. Zion was previously a light-water-cooled nuclear power plant that used uranium fuel to generate electricity, therefore, 40CFR190 is applied to the different methods of Decommissioning at Zion. When Compliance Assessment is Required Compliance with the 40CFR190 regulations is now required as part of demonstration of compliance to 10CFR20 regulations per 10CFR20.1301 (d), and 10CFR72 regulations per 10CFR72.104. Equation The dose due to the uranium fuel cycle is determined by equation A-24. A.5.3 Summary of Compliance Methodology The required compliance is given in Tables 2-1, 2-2 and 2-3. In Table 2-1, the dose components are itemized and referenced, and an indication of their regulatory application is noted. A more detailed compliance matrix is given in Table 2-3. The locations of dose receivers for each dose component are given in Table 2-2. Further, Table 2-2 states the location of the receiver and occupancy factors, if applicable. In general, the receiver spends time in locations that result in maximum direct dose exposure and inhales and ingests radioactivity from sites that yield maximum pathway doses. Thus, the dose calculated is a very conservative one compared to the "average" receiver who does not go out of his way to maximize radioactivity uptakes. Occupancy as a habit of a "real individual" is applied to doses received from contained sources. Finally, the connection between regulations, the ODCM equations and the station RETS and Technical Specifications is given in Table 12-0. ISFSI 10CFR72.104 dose limits are the same as those specified by 40CFR 190. ISFSI dose contribution is in the form of direct radiation as no liquid or gas releases are expected to occur. The report prepared in accordance with 10CFR72.212 requirements assumes a certain array of vertical concrete casks exists on the ISFSI. The dose contribution from this array of casks was analyzed to be within the 40CFR190 and 10CFR72.104 limits, and is documented in NAC International Calculation 630073-5501 ZION Site Boundary Skyshine Evaluation, Zion Technical Support Document TSD 13-008 "Evaluation of Independent Spent Fuel Storage Installation and Associated processes Dose Rates" and TSD 13-009 "Member of the Public Dose From All Onsite Sources". If the dose limits of 40CFR190 or 10CFR72.104 are exceeded, a special report to the NRC as well as an appropriate request for exemption/variance is required to be submitted to the NRC. Page 124 of 268

Revision 9 February 27, 2017 The requirement that the dose limits of 10CFR72.104 apply to any "real individual" is controlled for ISFSI activities in the ISFSI 72.212 report. Therefore, for the purposes of analyzing dose from the ISFSI, the member of the public as defined in 40CFR190 is the same as the "real individual" identified in the ES&H TSO 13-008 "Evaluation of Independent Spent Fuel Storage Installation and Associated processes Dose Rates" and TSO 13-009 "Member of the Public Dose From All Onsite Sources". A.6 DOSE DUE TO DRINKING WATER (40CFR141) The National Primary Drinking Water Regulations, 40CFR 141, contain the requirements of the Environmental Protection Agency applicable to public water systems. Included are limits on radioactivity concentration. Although these regulations are directed at the owners and operators of public water systems, Zion Station has requirements in their Technical Specifications related to 40CFR141 .. A.6.1 40CFR141 Restrictions on Manmade Radionuclides Section 141.16 states the following (not verbatim): (a) The average annual concentration of beta particle and photon radioactivity from man-made radionuclides in drinking water shall not produce an annual dose equivalent to the total body or any internal organ greater than 4 millirem/year. (b) Except for the radionuclides listed in Table A-0, the concentration of man-made radionuclides causing 4 mrem total body or organ dose equivalents shall be calculated on the basis of drinking 2 liter of water per day. (Using the 168 hour data listed in "Maximum Permissible Body Burdens and Maximum Permissible Concentration of Radionuclides in Air or Water for Occupational Exposure, "NBSHandbook 69 as amended August 1963, U.S. Department of Commerce.). If two or more radionuclides are present, the sum of their annual dose equivalents to the total body or any organ shall not exceed 4 millirem/year. Page 125 of 268

Revision 9 February 27, 2017 TABLEA-0 AVERAGE ANNUAL CONCENTRATIONS ASSUMED TO PRODUCE A TOTAL BODY OR ORGAN DOSE OF 4 MREM/YR Radionuclide Critical Orqan pCi/Liter Tritium Total Body 20,000 Strontium-90 Bone Marrow 8 A.6.2 Application The projection or calculation of dose due to the drinking water pathway is made using Equations A-17 and A-19. Projections are made using projected radionuclide releases in place of measured releases Ai. Doses calculated using Equations A-17 and A-19 may differ from doses determined by the methodology prescribed in 40CFR141.16. When required, Zion Station prepares a special report on radiological impact at the nearest community water system. This system is taken as the one listed in Table A-3 of this appendix. The report should include the following:

• The doses calculated by Equations A-17 and A-19.
• A statement identifying the dose calculation methodology (e.g., a reference to this manual).
• A statement that the doses calculated by the ODCM methodology are not necessarily the same as doses calculated by the methodology prescribed in 40CFR 141.16.
• The data used to calculate the doses. This information includes the amounts of radioactivity released and the flow rate and dilution values used (see Table F-1). This information is provided to assist the operator of the community water system in performing its own dose assessment.

Page 126 of 268

Revision 9 February 27, 2017 Table A-1 COMPLIANCE MATRIX Regulation Dose to be compared to limit 10CFR50

• Gamma air dose and beta air dose due to airborne radioactivity in effluent Appendix I plume.
• Total body and skin dose due to airborne radioactivity in effluent plume are reported only if certain gamma and beta air dose criteria are exceeded.
• Dose for all organs and all four age groups due to particulate in effluent plume. Existing pathways are considered.
• Dose for all organs and all four age groups due to radioactivity in liquid effluents.

10CFR20

• Adherence determined by compliance with dose limits of 40CFR190 .

40CFR190

• Total body dose due to direct radiation, ground and plume exposure from all sources at a station.
• Organ doses to an adult due to all pathways .

RETS/ODCM * "Instantaneous" noble gas total body and skin dose rates and tritium and particulate inhalation dose rates to a child due to radioactivity in airborne effluents.

              *   "Instantaneous" concentration limits for liquid effluents .

10CFR72.104(a)

• During normal operations and anticipated occurrences .

Page 127 of 268

Revision 9 February 27, 2017 TableA-2 Release Point Classifications Release Release Point 8 Station Point Classification Zion 1 & 2 Vent Stacks Ground Level 8 The definitions of release point classifications (stack, vent and ground level) are given in Section 4.1.4. TableA-3 Nearest Downstream Community Water Systems Characteristics of Nearest Affected Downstream Community Water Supply Location and Station Distancea Zion Lake County Intake, 1.4 miles a Appendix 0 Table 0-2 provides the basis of the location and distance data. Page 128 of 268

Revision 9 February 27, 2017 TableA-4 40CFR190, 10CFR72.104(a\ Compliance 40CFR190 Dose Annual Limit ODCM Dose and Equation Number (mrem) 10CFR72.104(a) Dose Total Body 25 Total Body Dose; A-24 evaluated for total body Thyroid 75 Thyroid Dose; A-24 evaluated for thyroid Other Organs 25 Organ Dose; A-24 evaluated for all organs except thyroid Notes:

1. The evaluation is made considering the following sources:

a. Radioactivity in contained sources within the station;

b. Radioactivity in station gaseous and liquid effluents; Page 129 of 268

Revision 9 February 27, 2017 I APPENDIX B MODELS AND PARAMETERS FOR AIRBORNE AND LIQUID EFFLUENT CALCULATIONS Page 130 of 268

Revision 9 February 27, 2017 APPENDIX B MODELS AND PARAMETERS FOR AIRBORNE EFFLUENT CALCULATIONS B.O INTRODUCTION The equations used for calculation of doses due to radioactive airborne effluents are given in Section A.1 of Appendix A The equations involve the following types of parameters:

• Meteorological Parameters These include x/Q, gamma-x/Q, D/Q and wind speed. Their values are based on historical average atmospheric conditions at a site for a selected multi-year historical period (see Section 4.1.5).
• Dose Factors These parameters are used to provide a simple way to calculate doses and dose rates due to gamma and beta radiation. These parameters are independent of meteorological conditions and therefore generic (i.e., not station-specific).
• Measured Release Parameters These are measured values of radioactivity releases and release rates.
• Radiological Decay Constants These are used to account for the radioactive decay between the release of radioactivity to the environment and the exposure of persons to it.
• Production/Exposure Parameters These are parameters characterizing agricultural production (e.g., length of growing season, transport times) and human exposure patterns (e.g., exposure period, breathing rate, food consumption rates). These parameters affect the quantities of radioactivity to which persons may be exposed.

This appendix discusses the methodology used to determine values of these parameters. Section B.1 addresses how the historical meteorology of a site is characterized by use of a function called the joint frequency distribution. Section B.1 and Sections B.3 through B.5 present equations that use the joint frequency distribution t~ obtain values for site-specific meteorological parameters. These equations involve a mathematical model of a plume known as the Gaus.sian plume model. This model is developed in Section B.2. Various generic dose factors are discussed in Sections B.6 through B.10. The other parameters are discussed in the remaining sections.

• B.1 METEOROLOGICAL DATA AND PARAMETERS Predicting where airborne effluent will travel requires information on the following:
• Wind speed
• Wind direction
• Atmospheric turbulence The greater the atmospheric turbulence, the more an effluent plume will tend to broaden and the more dilute the concentration will be. Atmospheric turbulence is affected by the general condition of the atmosphere (e.g., the vertical temperature distribution) and by local features (e.g., objects that protrude into the wind stream). A commonly used classification scheme for the degree of atmospheric turbulence associated with the general condition of the atmosphere involves seven stability classes:

A Extremely Unstable B Moderately Unstable C Slightly Unstable D Neutral Page 131 of 268

Revision 9 February 27, 2017 E Slightly Stable F Moderately Stable G Extremely Stable This classification scheme is based on Reference 5, Table 1. Each class is associated with a particular range of wind direction fluctuations and of vertical temperature gradients in the atmosphere. These are specified in Table C-4 of Appendix C. B.1.1 Data Historical atmospheric conditions at Zion Station were recorded by an instrumented meteorological tower that measured wind speed, wind direction, and temperature at various heights. Hourly average values of wind speed, wind direction, and stability class were determined. The difference in temperature between two heights was used to assign an atmospheric stability class based on the correlation between temperature gradient and stability class in Table C-4 of Appendix C. In obtaining the data, quality assurance checks and corrections were made. Also, corrections were applied to compensate for the limitations of wind sensors at low speeds. A calm was said to exist if the wind speed was less than that of the threshold of either the anemometer (wind speed meter) or the wind direction vane. For calm conditions, a wind speed equal to one-half of the higher threshold was assigned. For each stability class, the wind directions during calm conditions were assumed to be distributed in proportion to the observed wind direction distribution of the lowest non-calm wind speed class. B.1.2 Joint Frequency Distribution The data for a particular historical period are summarized by developing a joint frequency distribution (JFD). Each such distribution specifies the fraction of time during the historical period that the following jointly occur:

• Wind speed within a particular range (wind speed class).
• Downwind direction in one of the 16 sectors corresponding to the 16 principal compass directions (N, NNE, etc.).
• Atmospheric conditions corresponding to one of the seven atmospheric stability classes discussed in Section B.1. Table B-1 of this appendix displays a portion of an example JFD.

Different JFDs are associated with the different release classifications defined in Section 4.1.4. One JFD is defined for stack releases, and another JFD is defined for ground level releases. Two JFDs are associated with vent (mixed mode) releases, one for the portion of the time the release is treated as elevated and the other for the portion of the time the release is treated as ground level. B.1.2.1 Downwind Direction Versus Upwind Direction Unless otherwise noted, any reference to wind direction in this document represents downwind direction, i.e., the direction in which the wind is blowing toward. This is because the parameters developed in this document are used to calculate radioactivity concentration and radiation dose downwind of a release point. In contrast, it is conventional for meteorologists to provide JFDs based on upwind direction, the direction from which the wind is blowing. For example, the JFDs presented in the annual operating report of Zion Station are obtained from a meteorological contractor and the directions specified in the reports are upwind directions. Users of JFDs should always be careful to ascertain whether the directions specified are upwind or downwind.

• B.1.2.2 StackJFD Page 132 of 268

Revision 9 February 27, 2017 For a stack release, the JFD is defined as follows:

Ef5 (n,0,c) Joint Frequency Distribution, Stack Release The fraction of hours during a period of observation that all of the following hold:

• The average wind speed is within wind speed class n.
• The downwind direction is within the sector denoted by 0.
• The atmospheric stability class is c.

This function is defined for application to a stack release point (see Section 4.1.4). Its value is based on hourly average wind data obtained at a height representative of the release point height. The stack JFD is normalized to 1:

E f5 (n,0,c) = 1 (8-25)

The summation is over all wind speed classes n, all compass direction sectors 0, and all stability classes c. 8.1.2.3 Ground Level JFD For a ground level release, the JFD fg(n, 0,c) is defined in the same way as for a stack release except that the wind data are obtained at a height representative of a ground level release point. This height is taken as about 10 meters. The ground level JFD is normalized to 1:

E fg(n,0,c) =1 (8-26)

The summation is over all wind speed classes n, all compass direction sectors, and all stability classes c. 8.1.2.4 VentJFDs In accordance with the approach recommended in Regulatory Guide 1.111 (Reference 7), the plume from a vent release is treated as elevated part of the time and as ground level the rest of the time. Two JFDs are determined:

• fv,elev(n,0,c) characterizes the plume during the part of the time that it is considered elevated;
• fv,gnd(n,0,c) characterizes the plume during the part of the time that it is considered ground level.

Their definitions are as follows: fv,elev(n,0,c) Joint Frequency Distribution, Elevated Portion of a Vent Release The fraction of hours during a period of observation that the plume is considered elevated and that all of the following hold:

• The average wind speed is within wind speed class n.
• The downwind direction is within the sector denoted by 0.
• The atmospheric stability class is c.

Page 133 of 268

Revision 9 February 27, 2017 fv,gnd(n,0,c) Joint Frequency Distribution, Ground Level Portion of a Vent Release The fraction of hours during a period of observation that the plume is considered ground level and that all of the following hold:

• The average wind speed is within wind speed class n.
• The downwind direction is within the sector denoted by 0.
• The atmospheric stability class is c.

The value of fv,elev(n, 0,c) is based on hourly average wind data at a height representative of the vent release point. Where the measurement height differed considerably from the release height, wind speed data for the release height was obtained by extrapolation. The value of fv,gnd(n, 0,c) is based on hourly average wind data obtained at a height representative of a ground level release point. This is taken as about 10 meters. The sum of these two JFDs is normalized to 1: l:{ fv elev(n, 0,c) + fv gnd(n, 0,c) } = 1 (B-27) The summation is over all wind speed classes n, all compass direction sectors 0, and all stability classes C. The prescription of Regulatory Guide 1.111 is used in determining the fraction of time that the plume is considered elevated and the fraction of time that it is considered ground level. The fractions are obtained from the ratio of stack exit velocity W 0 to hourly average wind speed u at the height of the vent release point as follows:

            *If W 0 /u > 5, then the plume is considered elevated for the hour.
            *If W 0 /u ~ 1, then the plume is considered ground level for the hour.
            *If 1 < W 0 /u ~  5, the plume is considered to be a ground level release for a fraction Gt of the hour and an elevated release for a fraction (1 - Gt) of the hour where Gt is defined as follows:

Gt= 2.58 -1.58(W0 /u) for 1.0 < W 0 /u ~ 1.5 (B-28) Gt= 0.30 - 0.06(W0 /u) for 1.5 < W 0 /u ~ 5.0 (B-29) B.1.3 Average Wind Speed Using the joint frequency distribution, average wind speeds are obtained for Zion Station. Values are obtained for each downwind direction (N, NNE, etc.) and for various release point classifications (stack, vent, and ground level). B.1.3.1 Stack Release For a stack release, the following formula is used: u 8 (0) = l:{ f 8 (n, 0,c)un }/ l:{ f 8 (n, 0,c) } (B-30) Page 134 of 268

Revision 9 February 27, 2017 where the summations are over wind speed classes n and stability classes c. u 8 (0) Average Wind Speed, Stack Release [m/sec] The average wind speed in downwind direction 0 for a stack release. Un Wind Speed for Class n [m/sec] A wind speed representative of wind speed class n. For each wind speed class except the highest, Un is the average of the upper and lower limits of the wind speed range for the class. For the highest wind speed class, Un is the lower limit of the wind speed range for the class. The parameter fs is defined in Section 8.1.2.2. 8.1.3.2 Ground Level Release For a ground level release, the following formula is used: u (0) = l:{ fg(n, 0,c)un }/ l:{ fg(n, 9,c) } (8-31) 9 where the summations are over wind speed classes n and stability classes c. u (0) Average Wind Speed, Ground Level Release [m/sec] 9 The average wind speed in downwind direction 0 for a ground level release. The parameter fg is defined in Section 8.1.2.3. 8.1.3.3 Vent Release For a vent release, the following formula is used: Uy(0) =l: { [fv,elev(n, 0,c) + fv,gnd(n, 0,c)]un } (8-32)

                                                / l:{ fv,elev(n,0,c) + fv,gnd(n,0,c)}

where the summations are over wind speed classes n and stability classes c. uy(0) Average Wind Speed, Vent [m/sec] Release The average wind speed in downwind direction 0 for a vent release. The parameters fv,elev and fv,gnd are defined in Section 8.1.2.4. 8.2 GAUSSIAN PLUME MODELS Page 135 of 268

Revision 9 February 27, 2017 As a plume of airborne effluents moves away from an elevated release point, the plume both broadens and meanders. It has been found that the time-averaged distribution of material in an effluent plume can be well represented mathematically by a Gaussian function. B.2.1 Mathematical Representation In a widely used form of the Gaussian plume model, the distribution of radioactivity in a plume is represented mathematically by the equation below: (B-33) 3 x:(x,y,z) Radioactivity Concentration [µCi/m ] The concentration of radioactivity at point (x,y,z). The x, y, and z axis are defined as follows: x Downwind Distance [m] Distance from the stack along an axis parallel to the wind direction. y Crosswind Distance [m] Distance from the plume centerline along an axis parallel to the crosswind direction. z Vertical Distance [m] Distance from the ground (grade level at the stack) along an axis parallel to the vertical direction. Q Release Rate [µCi/sec] Release rate of radioactivity. rry, rrz Horizontal and Vertical Dispersion Coefficients [m] Standard deviations of the Gaussian distributions describing the plume cross-sections in the y and z directions, respectively. The values of rry and rrz depend on several parameters:

• Downwind distance x.

Because a plume broadens and meanders as it travels away from its release point, the values of rry and rrz increase as x increases.

• Atmospheric stability class.

The plume is broadest for extremely unstable atmospheric conditions (Class A) and narrowest for extremely stable conditions (Class G).

• Time period of averaging plume concentration.

The values of rry and rrz increase as the averaging period increases. Page 136 of 268

Revision 9 February 27, 2017 u Average Wind Speed [m/sec] The average wind speed. The average speed of travel of the plume in the x direction. he Effective Release Height [m] The effective height of effluent release above grade elevation. This may be greater than the actual release height (see Section B.3.1.1.1 ). The two exponential functions of z in the curly brackets of Equation B-9 represent the emitted and reflected components of the plume. The reflected component (represented by the exponential with (z + he) in its argument) arises from the assumption that all material in a portion of the plume that touches ground is reflected upward. This assumption is conservative if one is calculating airborne radioactivity concentration. 8.2.2 Sector-Averaged Concentration Sometimes, it is desired to determine the average concentration of radioactivity in a sector due to release at a constant rate over an extended period of time (e.g., a year). For such a case, it is reasonable to assume that the wind blows with equal likelihood toward all directions within the sector. From Equation B-9, the following equation for ground level radioactivity concentration can be derived: Xsector = [2.032 f Q/(az u x)]exp(-h2e/2a2z) (B-34) XsectorSector-Averaged Ground Level Concentration The time-averaged concentration of airborne radioactivity in a sector at ground level at a distance x from the release point. 2.032 A dimensionless constant. f Sector Fraction The fraction of time that the wind blows into the sector. Q Release rate of radioactivity. [µCi/sec] The other parameter definitions are the same as for Equation B-9. Page 137 of 268

Revision 9 February 27, 2017 B.3 RELATIVE CONCENTRATION FACTOR xJQ The relative concentration factor xtQ (called "chi over Q") provides a simplified method of calculating the radioactivity concentration at a given point in an effluent plume when the release rate is known: x =Q <xtQ) (B-35) x Concentration of Radioactivity [µCi/m3] Concentration of radioactivity at point (x,y,z) in the atmosphere. Q Release Rate [µCi/sec] Release rate of radioactivity. xtQ Relative Concentration Factor Relative concentration factor for point (x,y,z). The airborne radioactivity concentration at (x,y,z) per unit release rate. Expressions for xtQ based on Gaussian plume models can be obtained from the equations for x concentration in Section B.2 simply by dividing both sides of each equation by the release rate Q. For example, from Equation B-10, we obtain the following expression for the sector-averaged xtQ: (XsectorlQ) = [2.032 f/(crz u x)]exp(-h2e/2cr2z) (B-36) The values of xJQ used in ODCM calculations are both sector-averaged and time-averaged. The time averaging is based on the historical average atmospheric conditions of a specified multi-year time period (see Section 4.1.5) and is accomplished by use of the joint frequency distribution discussed in Section B.1.2. The formulas used to obtain the time- and sector-averaged xtQ are based on Equation B-12, but vary depending on whether the release is a stack, ground level, or vent release. The three cases are discussed below. B.3.1 Stack Release For a stack release, the relative concentration factor is designated (x/Q) 5 . Its value is obtained by the following formula: (x/Q)5 = (2.032/R) l:{ f 5 (n,0,c) x [exp (-h2e/2cr2z)]/(un crz)} (B-37) The summation is over wind speed classes n and atmospheric stability classes c. (x/Q)5 Relative Concentration Factor, Stack Release The time- and sector-averaged relative concentration factor due to a stack release for a point at ground level at distance R in downwind direction a. Page 138 of 268

Revision 9 February 27, 2017 2.032 Constant A dimensionless constant. R Downwind Distance [m] The downwind distance from the release point to the point of interest. fs(n,0,c) Joint Frequency Distribution, Stack Release This function is defined in Section 8.1.2.2. he Effective Release Heig~t [m] The effective height of an effluent release above grade elevation. For a stack release, he is obtained by correcting the actual height of the release point for plume rise, terrain effects, and downwash as described in Section 8.3.1.1, below. O"z Standard Ver1;ical Dispersion Coefficient [m] A coefficient characterizing vertical plume spread in the Gaussian model for stability class c at distance R (see Table C-5 of Appendix C). Un Wind Speed [m/sec] A wind speed representative of wind speed class n. For each wind speed class except the highest, Un is the average of the upper and lower limits of the wind speed range for the class. For the highest wind speed class, Un is the lower limit of the wind speed range for the class. This expression is recommended by the NRC in Regulatory Guide 1.111 (Reference 7) and is based on a model designated there as the "constant mean wind direction model." In this model it is assumed that the mean wind speed, the mean wind direction, and the atmospheric stability class determined at the release point also apply at all points within the region in which airborne concentration is being evaluated. 8.3.1.1 Effective Release Height For a stack release, the effective height of an effluent plume is the height of the release point corrected for plume rise and terrain effects: If (hs + hpr - ht)< 100 meters, then he= hs + hpr - ht (B-38) If (hs + hpr - ht)~ 100 meters, then; he = 100 meters (B-39) he Effective Release Height [m] The effective height of an effluent release above grade elevation. hs Actual Release Height [m] The actual height of the release above grade elevation. Page 139 of 268

Revision 9 February 27, 2017 Plume Rise [m] The rise of the plume due to its momentum and buoyancy. (See Section B.3.1.1.1.) ht Terrain Correction Parameter [m] A parameter to account for the effect of terrain elevation on the effective height of a plume. Taken as zero (see Section B.3.1.1.2). B.3.1.1.1 Plume Rise Because nuclear power stations generally have plumes that are not significantly warmer than room temperature, plume rise due to buoyancy is neglected. The formulas used to calculate plume rise due to momentum are given below. Stability Classes A, B, C, and D For these stability classes (corresponding to unstable and neutral conditions), hpr is taken as the lesser of two quantities: hpr =Minimum of [(hprh* (hpr)2] (B-40) (hprh = (1.44)(W0 /u)2/3(R/d)1/3(d) - hd (B-41) (hpr)2 = (3)(W0 /u)(d) (B-42) W0 Stack Exit Velocity [m/sec] The effluent stream velocity at the discharge point. uWind Speed [m/sec] R Downwind Distance [m] The downwind.distance from the release point to the point of interest. d Internal Stack Diameter [m] The internal diameter of the stack from which the effluent is released. Downwash Correction [m] A parameter to account for downwash at low exit velocities. The parameter hd is calculated by the following equations: hd = (3)(1.5 -W0 /u)(d) if W 0 <1.5u (B-43) (B-44) Note that (hpr)1 can increase without limit as R increases; thus, the effect of (hpr)2 is to limit calculated plume rise at large distances from the nuclear power station. Page 140 of 268

Revision 9 February 27, 2017 Stability Classes E, F, and G For these stability classes (corresponding to stable conditions}, hpr is taken as the minimum of four quantities: hpr =Minimum of [(hpr)1, (hpr)2, (hpr)3, (hpr)4] (B-45) (hpr)3 = (4)(F/S)1/4 (B-46) (hpr> 4 = (1.5)(F/u)1/3csr11s (B-47) F Momentum Flux Parameter [m4/sec2] A parameter defined as: F = W 0 2(d/2)2 (B-48) S Stability Parameter [1/sec2] A parameter defined as follows: Stability Class s E 8.70E-4 F 1.75E-3 G 2.45E-3 The quantities (hpr>1 and (hpr)2 are as defined by Equations B-17 and B-18. B.3.1.1.2 Terrain Effects Due to general flatness of the terrain in the vicinity of the Zion site, the terrain correction parameter ht was taken as zero in all calculations of meteorological dispersion and dose parameters for this Manual. B.3.2 Ground Level Release For a ground level release, the relative concentration factor is designated (x/Q) 9 . Its value is obtained by the following formula: (:x;/Q)g = (2.032/R) I:{ fg(n,0,c)/(unSz) } (B-49) The summation is over wind speed classes n and atmospheric stability classes c. (:x;/Q)g Relative Concentration Factor, Ground Level Release [sec/m3] The time- and sector-averaged relative concentration factor due to a ground level release for a point at ground level at distance R in downwind direction 0. fg(n,0,c) Joint Frequency Distribution, Ground Level Release Page 141 of 268

Revision 9 February 27, 2017 This function is defined in Section B.1.2.3. Sz Wake-Corrected Vertical Dispersion Coefficient [m] The vertical dispersion coefficient corrected for building wake effects. The correction is made as described below. The remaining parameters are defined in Section B.3.1. Wake-Corrected Vertical Dispersion Coefficient The wake-corrected vertical dispersion coefficient Sz in Equation B-25 is taken as the lesser of two quantities:

                          = Minimum of [(Sz)1, (Sz)2]                                                  (B-50)

(B-51) (Szh =(<rz)(3112 ) (B-52) Wake-Corrected Vertical Dispersion Coefficient [m] The vertical dispersion coefficient corrected for building wake effects.

        <rz Standard Vertical Dispersion Coefficient                                                    [m]

The coefficient characterizing vertical plume spread in the Gaussian model for stability class c at distance R (see Table C-5 of Appendix C). D Maximum Height of Neighboring Structure [m] The maximum height of any neighboring structure causing building wake effects (see Table F-2 of Appendix F). B.3.3 Vent Release For a vent release, the relative concentration factor is designated (x;/Q)v- Its value is obtained by the following formula: (x/Q)v = (2.032/R) l:{ fv,elev(n,0,c) (B-53) 2 2 x [exp(-h el2cr z}]l(un <rz)

                       + fv,gnd(n,0,c)/(unSz) }

The summation is over wind speed classes n and atmospheric stability classes c. (x/Q)v Relative Concentration [sec/m3] Factor, Vent Release The time and sector averaged relative concentration factor due to a vent release for a point at ground level at distance R in downwind direction 0. Page 142 of 268

Revision 9 February 27, 2017 The parameters fv,elev(n,0,c) and fv,gnd(n,0,c) are defined in Section 8.1.2.4. The parameter Sz is defined in Section 8.3.2. The remaining parameters are defined in Section 8.3.1. B.3.4 Removal Mechanisms In Regulatory Guide 1.111, the NRC allows various removal mechanisms to be considered in evaluating the radiological impact of airborne effluents. These include radioactive decay, dry deposition, wet deposition, and deposition over water. For simplicity, these removal mechanisms cited by the NRC are not accounted for in the evaluation or use of x}Q in this manual. This represents a conservative approximation as ignoring removal mechanisms increases the value of xtQ. B.3.5 Gamma-x/Q The noble gas dose factors of Reg. Guide 1.109, Table 8-1 are based upon assumption of immersion in a semi-infinite cloud. For ground level and mixed mode releases this tends to overestimate the gamma air dose arising from a plume that is actually finite in nature. For elevated releases, the Reg. Guide 1.109 noble gas dose factors will underestimate exposure as they consider only immersion and not that portion of exposure arising from sky shine. At distances close in to the point of elevated release, the ground level concentration as predicted by x}Q will be essentially zero. In such a case, the sky shine component of the exposure becomes significant and must be considered. The gamma-x/Q provides a simplified method of calculating gamma air dose and dose rates for a finite and/or elevated plume. The methodology of Reg. Guide 1.109, Section C.2 and Appendix 8 provides the methodology for calculating finite cloud gamma air dose factors from which .the gamma-x/Q values can be derived. Section 8.5 addresses the calculation of these dose factors. The gamma-x/Q is defined such that for a given finite cloud the semi-infinite cloud methodology will yield the same gamma air dose as the finite cloud methodology. Three gamma-x}Q values are defined: (x}Q) 5 r, (x/Q)} and (xJQ) 9'Y for stack, vent and ground level releases, respectively. These gamma-x/Q values are calculated as follows: For stack releases: (B-54) The summation is over all noble gas radionuclides i. (x/a)~ Gamma-y/Q for Stack Releases [sec/m3] Noble Gas Nuclide Fraction dimensionless Fraction of total noble gas release that is due to radionuclide i. Values for f 1 are listed in Table 8-0. Stack Release Gamma Air Dose Factor [(mrad/yr)/(µCi/sec)] Page 143 of 268

Revision 9 February 27, 2017 Gam'ma air dose factor for radionuclide i for stack releases as defined in Section B.5.1. Taken from Appendix F, Table 7. 3 Semi-Infinite Cloud Dose Factor [(mrad/yr)/(µCi/m )] Dose factor for immersion exposure to a semi-infinite cloud of noble gas. Taken from Reg. Guide 1.109, Table B-1, Col 4. (Note that the units in Reg. Guide 1.109 must be multiplied by 1E6 to convert pCi to µCi.) For vent releases: (B-55) The summation is over all noble gas radionuclides i. (x/o)~ Gamma-y/Q for Vent Releases [sec/m3] Vent Release Gamma Air Dose Factor [(mrad/yr)/(µCi/sec)] Gamma air dose factor for radionuclide i for stack releases as defined in Section B.5.3. Taken from Appendix F, Table 7. All other terms have been previously defined. For ground level releases: (B-56) The summation is over all noble gas radionuclides i. Gamma-y/Q for Ground Releases [sec/m3] Ground Level Release Gamma Air Dose Factor . [(mrad/yr)/(µCi/sec)] Gamma air dose factor for radionuclide i for ground level releases as defined in Section B.5.2. Taken from Appendix F, Table 7. All other terms have been previously defined. The Noble Gas Nuclide Fraction, f 1 is determined from historical release data and defined as: (B-57) The summation is over all noble gas radionuclides i. A1 Cumulative Radionuclide Release units of activity Cumulative release of noble gas radionuclide i over a period of time. Page 144 of 268

Revision 9 February 27, 2017 8.4 RELATIVE DEPOSITION FACTOR D/Q The quantity D/Q (called "Dover Q") is defined to provide the following simple way of calculating the rate of deposition of radioactivity at a given point on the ground when the release rate is known. d =Q (D/Q) (B-58) d Deposition Rate [(µCi/m2)/sec] Rate of deposition of radioactivity at a specified point on the ground. Q Release Rate of radioactivity. [µCi/sec] D/Q Relative Deposition Factor [1/m2] Relative deposition factor for a specified point on the ground. The deposition rate per unit release rate. The values of D/Q used in this manual are time-averaged. The time averaging is based on the historical average atmospheric conditions of a specified multi-year time period (see Section 4.1.5) and is accomplished by use of the joint frequency distribution described in Section 8.1.2. The formulas used to obtain D/Q vary depending on whether the release is a stack, ground level, or vent release. The three cases are discussed below. B.4.1 Stack Release For a stack release, the relative deposition factor is designated (D/Q) 5 . Its value is obtained by the following formula: (D/Q) 5 =[1/(21tR/16)] :E{f5 (n,0,c) Dr(c,R,he)} (B-59) The summation is over wind speed classes n and stability classes c. (D/Q)5 Relative Deposition Factor, Stack Release The time-averaged relative deposition factor due to a stack release for a point at distance R in the direction 0. 21t/16 Sector Width [radians] The width of a sector over which the plume direction is assumed to be uniformly distributed (as in the model of Section 8.2.2). Taken as 1/16 of a circle. R Downwind Distance [m] The downwind distance from the release point to the point of interest. f 5 (n,0,c) Joint Frequency Distribution, Stack Release This function is defined in Section 8.1.2.2. Page 145 of 268

Revision 9 February 27, 2017 Relative Deposition Rate, Stack Release The deposition rate per unit downwind distance [µCi/(sec-m)] divided by the source strength [µCi/sec] due to a stack release for stability class c, downwind distance R, and effective release height he. The value is based on Figures 7 to 9 of Regulatory Guide 1.111, which apply, respectively, to release heights of 30, 60, and 100 m. Linear interpolation is used to obtain values at intermediate release heights. If the effective release height is greater than 100 meters, then the data for 100 meters are used. he Effective Release Height [m] The effective height of the release above grade elevation. See Section B.3.1.1. B.4.2 Ground Level Release For ground level release, the relative deposition factor is designated (D/Q) 9 . Its value is obtained by the following formula: (D/Q) 9 =[1/(21tR/16)] Dr(R) ~{ f 9 (n,0,c)} (B-60) The summation is over wind speed classes n and stability classes c. (D/Q)g Relative Deposition Factor, Ground Level Release The time-averaged relative deposition factor due to a ground level release for a point at distance R in the direction 0. f g(n,0,c) Joint Frequency Distribution, Ground Level Release This function is defined in Section B.1.2.3. Dr(R) Relative Deposition Rate, Ground Level [m-1] The deposition rate per unit downwind distance [µCi/(sec-m)] divided by the source strength [µCi/sec] due to a ground level release for downwind distance R. The value is taken from Figure 6 of Regulatory Guide 1.111 and is the same for all atmospheric stability classes. The remaining parameters are defined in Section B.4.1. B.4.3 Vent Release For a vent release, the relative deposition factor is designated (D/Q)y. Its value is obtained by the following formula: (D/Q)v =[1/(21tR/16)] x [~{ fv,elev(n,0,c) Dr(c,R,he)} + Dr(R) ~{ fv,gnd(n,0,c)}] (B-61) Page 146 of 268

Revision 9 February27, 2017 The summation is over wind speed classes n and stability classes c. (D/Q)v Relative Deposition Factor, Vent Release The time-averaged relative deposition factor due to a ground level release for a point at distance R in the direction e. The parameters fv,elev(n,8,c) and fv,gnd(n,0,c) are defined in Section 8.1.2.4. The remaining parameters are defined in Sections 8.4.1 and 8.4.2. B.5 GAMMA AIR DOSE FACTORS (Sj, Vj, Gj) The gamma air dose factors provide a simple way of calculating doses and dose rates to air due to gamma radiation. For example, using a dose factor DFj, gamma air dose rate may be calculated as follows: (B-62) (B-63) The summations are over i radionuclides. D Gamma Air Dose Rate [mrad/yr] The gamma air dose rate due to all radionuclides released. 0 1 Gamma Air Dose Rate Due to Radionuclide i [mrad/yr] Q1 Release Rate of Radionuclide i [µCi/sec] DF 1 Gamma Air Dose Factor for [(mrad/yr)/ (µCi/sec)] Radionuclide i A factor used to calculate gamma air dose or dose rate due to release of radionuclide i. Gamma air dose rate at a particular location per unit release rate. Three gamma air dose factors are defined: S 11 V 11 and G 1* They are used for stack, vent, and ground level releases, respectively. These three release point classifications are defined in Section 4.1.4. The calculation of the three dose factors is discussed below. B.5.1 Stack Release For a stack release, the gamma air dose factor S 1 is obtained by a model similar to that of Equation 6 of Regulatory Guide 1.109 (Reference 6). A sector-averaged Gaussian plume is assumed and the dose factor is evaluated on the basis of historical average atmospheric conditions. The value of S 1 depends on distance R from the release point and on downwind sector e. Page 147 of 268

Revision 9 February 27, 2017 The following equation is used: (B-64) The summation is over wind speed classes n, atmospheric stability classes c, and photon group indices k. S1 Gamma Air Dose Factor, Stack Release [(mrad/yr)/ (µCi/sec)] The gamma air dose factor at ground level for a stack release for radionuclide i, downwind sector e, downwind distance R from the release point, and the average atmospheric conditions of a specified historical time period. 260 Conversion factor [(mrad-radians-m3-disintegrations)/(sec-MeV-Ci)] Reconciles units of Equation 8-36. 2n/16 Sector Width [radians] The width of a sector over which the plume direction is assumed to be uniformly distributed (as in the model of Section 8.2.2). Taken as 1/16 of a circle.

• fs(n,0,c) Joint Frequency Distribution, Stack Release This function is defined in Section 8.1.2.2.

A.1 Radiological Decay Constant [hr-1] Radiological Decay Constant for radionuclide i (see Table C-7 of Appendix C). 3600 Conversion Factor [sec/hr] The number of seconds per hour. Used to convert wind speed in meters/sec to meters/hr. Ek Photon Group Energy [MeV/photon] An energy representative of photon energy group k. The photons emitted by each radionuclide are grouped into energy groups in order to facilitate analysis. All photons with energy in energy group k are assumed to have energy Ek.

    µ8(Ek) Air Energy Absorption Coefficient The linear energy absorption coefficient for air for photon energy group k.

The fraction of energy absorbed in air per unit of distance traveled for a beam of photons of energy Ek. Distance is measured in units of linear thickness (meters). Aki Effective Photon Yield [photons/disintegration] Page 148 of 268

Revision 9 February 27, 2017 The effective number of photons emitted with energy in energy group k per decay of nuclide i. On the basis of Section B.1 of Regulatory Guide 1.109 (Reference 6), the parameter Aki is calculated as follows: (B-65) The summation in the numerator is over the index m. True Photon Yield [photons per disintegration] The actual number of photons emitted with energy Em per decay of nuclide i. Em Photon Energy [MeV/photon] 1 The energy of the m h photon within photon energy group k. l.la(Em) Air Energy Absorption Coefficient The linear energy absorption coefficient for air for photon energy Em. I( ...) I Function A dimensionless parameter obtained by numerical evaluation of integrals that arise in the plume gamma dose problem. The value of I depends on the arguments ( ... ) listed in Equation B-40. A specific definition for I is given by Equation F-13 of Regulatory Guide 1.109. The integrals involved in calculating I arise from conceptually dividing up the radioactive plume into small elements of radioactivity and adding up the doses produced at the point of interest by all of the small elements. The distribution of radioactivity in the plume is represented by a sector-averaged Gaussian plume model like that discussed in Section B.2.2. The parameters R, he, Un, and O"z are defined in Section B.3.1. B.5.2 Ground Level Release The gamma air dose factor G1 for a ground level release is defined as follows: G 1 Gamma Air Dose Factor, Ground Level Release [(mrad/yr)/(µCi/sec)] The gamma air dose factor at ground level for a ground level release for radionuclide i, downwind sector 0, downwind distance R from the release point, and the average atmospheric conditions of a specified historical time period. The value of G1 is obtained by the same equation as used for a stack release, Equation B-36 of Section B.5.1, with the following modifications:

• The joint frequency distribution for a ground level release (f9 of Section B.1.2.3) is used in place of the one for a stack release (f5 ).
• In evaluating the I function, the effective release height he is taken as zero.

Page 149 of 268

Revision 9 February 27, 2017 This corresponds to use of a finite plume model. B.5.3 Vent Release For a vent release, the gamma air dose factor is calculated as follows: Vj = [260/(21tR/16)] X ~{fv,elev(n,0,c)[exp(-A.1R/3600un)] X Ak1EkJ.la(Ek) l(he,UmC,O'z,Ek)/Un (B-66)

                  + fv,gnd(n,0,c)[exp(-A.1R/3600Un)] X Ak1EkJ.la(Ek) 1(0,UmC,O'z,Ek)/Un}

The summation is over wind speed classes n, atmospheric stability classes c, and photon group indices k. Vi Gamma Air Dose Factor, Vent Release [(mrad/yr)/(µCi/sec)] The gamma air dose factor at ground level for a vent release for radionuclide i, downwind sector 0, downwind distance R from the release point, and the average atmospheric conditions of a specified historical time period. The parameters fv,elev(n,0,c) and fv,gnd(n,0,c) are defined in Section B.1.2.4. The parameter O"z is defined in Section B.3.2. The remaining parameters are discussed in Section B.5.1. B.6 Gamma Total Body Dose Conversion Factor (K1) The gamma total body dose conversion factors (K1) are used to calculate doses and dose rates due to gamma irradiation of the whole body. The gamma total body dose conversion factors are taken from Reg. Guide 1.109, Table B-1, Column 5. The gamma total body dose conversion factors in Table B-1 of Reg. Guide 1.109 are based upon the semi-infinite cloud model. B.7 BETA AIR AND BETA SKIN DOSE CONVERSION FACTORS (Nj,Lj) The beta air (Nj) and beta skin (Lj) dose conversion factors are used to calculate doses and dose rates due to noble gas beta exposure. The beta air dose conversion factors are taken from Reg, Guide 1.109, Table B-1, Column 2. The beta skin dose conversion factors are taken from Column 5 of that same table. The values are based on a semi-infinite cloud model. B.8 GROUND PLANE DOSE CONVERSION FACTOR DFG 1 The ground plane dose conversion factor DFG1is used to calculate dose due to standing on ground contaminated with radionuclide i (see Equation A-8 of Appendix A). The units of DFG 1are (mrem/hr) per 2 (pCi/m ). Values are provided (see Table C-10 of Appendix C) for dose to the whole body. The values are taken from Regulatory Guide 1.109 and are based on a model that assumes a uniformly contaminated ground plane.

• B.9 INHALATION DOSE COMMITMENT FACTOR DFA1Ja The inhalation dose commitment factor DFA1ia is used to calculate dose and dose rate to organ j of an individual of age group a due to inhalation of radionuclide i (see Equations A-7 and A-9 of Appendix A).

Values of DFA11a for 10CFR50 compliance are taken from Regulatory Guide 1.109 (Reference 6). The units of DFA1ia are mrem per pCi inhaled. Values are provided for seven organs, with the whole body considered as an organ (see Tables E-7, E-8, E-9 and E-10 in Reg. Guide 1.109). Page 150 of 268

Revision 9 February 27, 2017 B.10 INGESTION DOSE COMMITMENT FACTOR DFL11a The ingestion dose commitment factor DFL11a is used to calculate dose to organ j of an individual of age group a due to ingestion of radionuclide i (see Equations A-7 and A10 through A20 of Appendix A). Values of DFL1ia for 10CFR50 compliance are taken from Regulatory Guide 1.109 (Reference 6). The units of DFL11a are mrem per pCi ingested. In Tables E-11, E-12, E-13 and E-14 of Reg. Guide 1.109, values are provided for seven organs, with the whole body considered as an organ. B.11 MEASURED RELEASE PARAMETERS Input parameters required for calculations of dose or dose rate due to airborne effluents include measured values of radioactivity release (A16 , A 1v, and A 19) or release rate (01s. 01v. and 019) (see Section A.1 of Appendix A). These are obtained per Zion station procedures. B.12 RADIOLOGICAL DECAY CONSTANTS Values used for these are obtained from the literature and are specified in Table C-7 of Appendix C: B.13 PRODUCTION/EXPOSURE PARAMETERS These parameters characterize various aspects of agricultural production and human exposure. Values used for generic (site-independent) parameters are specified in Appendix C. Values of site-specific parameters are given in Appendix F. Many of the values are based on Reg. Guide 1.109, while others are based on site-specific considerations. Page 151 of 268

Revision 9 February 27, 2017 SECTION 2: MODELS AND PARAMETERS FOR LIQUID EFFLUENT CALCULATIONS 8.14 INTRODUCTION Equations for radiation dose and radioactivity concentration due to liquid effluents are given in Section A.2 of Appendix A. The equations involve the following types of parameters:

• Flow and Dilution Parameters.
• Dose Factors.
• Measured Release Parameters.
• Transport/Consumption Parameters.

This section discusses the methodology used to determine these parameters. Section B.15 addresses dose calculations and Section B.16 addresses concentration calculations for tank discharges. For dose calculations, flow and dilution parameters are discussed for the Lake Michigan Model, which is used for Zion. 8.15 DOSE 8.15.1 Drinking Water The radiation dose due to consumption of drinking water containing released radioactivity is calculated by Equations A-17, A-18 and A-19 of Appendix A: D~:q = F .At LLAaipjci (A-17) p I Waste Flow F=------- (A-18) Dilution Flow x Z (A-19) The summation is over index i (radionuclides) and p (pathways). The parameters are defined in Section A.2.1 of Appendix A. This methodology addresses the following considerations:

• The duration of the release, At.
• The concentration of the activity released, C;.
• The dilution that takes place in the environment is represented by the parameters F and Z.
• Receptor consumption rate, Uaw*
• Dilution which occurs from the near field discharge area to potable water intake as represented by ow .
• The dose commitment per unit of ingested radioactivity is DFLatJ*

8.15.2 Aquatic Foods (Fish) Near Zion station, the only aquatic food of significance for human consumption is fish. The liquid dose due to consumption of fish containing released radioactivity is calculated by Equations A-17, A-18 and A-20 of Appendix A. Page 152 of 268

Revision 9 February 27, 2017 (A-20) The parameters are defined in Section A.2.1 of Appendix A. This is similar to the methodolgy used for calculating the dose due to drinking water except for the addition of the bioaccumulation factor, BFj. This factor is the equilibrium ratio of the concentration of radionuclide i in fish (pCi/kg) to its concentration in water (pCi/L). It accounts for the fact that radioactivity ingested by fish can accumulate in their bodies to a higher concentration than in the waters in which the fish live. B.15.3 Parameters B.15.3.1 Flow and Dilution The values of dilution can differ for potable water and fish. The dilution for potable water will depends on where water is drawn, while that for fish will depends on where the fish are caught. Models used to determine these parameters are discussed below. The values used for Zion Station are summarized in Table F-1 of Appendix F. B.15.3.1.1 Lake Michigan Model Only (Zion) discharges liquid effluents into Lake Michigan. For Zion station, it is assumed that the dilution in the near-field (Z) is dictated by the initial entrainment dilution is a factor of 10. The potable water pathway dilution factor of 6 (Ow) is derived from the plume dilution (a factor of 3 over approximately 1 mile) and the current direction frequency (annual average factor of 2). B.15.3.2 Dose Factors Equations A-17 through A-20 of Appendix A determine dose due to ingested radioactivity using the same ingestion dose factor DFLija as used in the evaluation of airborne radioactivity which is ingested with foods. The units of DFLija are: (mrem) per (pCi ingested) For 10CFR50 Appendix I compliance, the data of Tables E-1, E-12, E-13 and E-14 of Reg. Guide 1.109, are used for four age groups and for seven organs, with the whole body considered as an organ. B.15.3.3 Measured Releases Calculations of dose due to liquid effluents require measured values of radioactivity concentration release (C1) for input. These release values are obtained per ZionSo/utions' procedures. B.15.3.4 Consumption Equations A-19 and A-20 of Appendix A involve consumption rates for water and fish (Uaw and U/). The values used are specified for Zion Station in Table F-1 of Appendix F. B.16 CONCENTRATION IN TANK DISCHARGES The concentration of radioactivity in a release to the unrestricted area due to a tank discharge is calculated by Equation A-22 of Appendix A: C = C~ Waste Flow (A-22) 1

                                                      ' Dilution Flow Page 153 of 268

Revision 9 February 27, 2017 The parameters are defined in Section A.2.3 of Appendix A. The radioactivity concentration released from the tank (ct1 at flow rate Fr) is diluted by mixing with the initial dilution stream (with flow rate Fd) to yield a lower concentration (C 1 ) in the combined streams. Table B-0 Noble Gas Nuclide Fractions Nuclide Zion' Ar-41 O.OOE+OO Kr-83m O.OOE+OO Kr-85 1.00E+OO Kr-85m O.OOE+OO Kr-87 O.OOE+OO Kr-88 O.OOE+OO Kr-89 O.OOE+OO Kr-90 O.OOE+OO Xe-131m O.OOE+OO Xe-133 O.OOE+OO Xe-133m O.OOE+OO Xe-135 : O.OOE+OO Xe-135m O.OOE+OO Xe-137 O.OOE+OO Xe-138 O.OOE+OO Notes: (1) From Table 10-1. Page 154 of 268

Revision 9 February 27, 2017 I Table 8-1 Portion of an Example Joint Frequency Distribution s~ry Tabla af Parc..,t by Dtrec:tton and Cl*** Cl e1111 N NPfE NE ENE E ESE SE SSE s A .289 .317 .301 .244 .249

• t90 .t98 .un .33&

B .t90 .t87 * .n8 .t58 .t215 .065 .079 .t30 .t93 c .269 .226 .262 .218

• 190 . ua
• 162 .t89 .302 D 3.298 2.327 2.338 2.684 t.992 1.334 t.365 2.172 3.012 E t.466 t. t98 .988 t.331 t .IBt t .226 t.472 2.!553 3.121 F .!504 .3t8 .t8!5 .276 .691 .&48 .103 t .293 1. 7~2 G .202 .09t .oat .osau .253 .2!50 .365 .400 .624 Tat.al 6.217 4.663 4.304 15.0t t 15. 169 3.830 4.424 6.933 9.826 Suaaary Tabla of Par-cent by Dtrectton and Spaed Speed N NNE NE ENE E ESE SE SSE s

    .45    .098       .099         .078         .030          .009           .000         .Ot4         .032      .046 1.05     .308       .154         .125         .t37           .t2t          .093         .090         .090      .127 2.05     .939       -~02         .458         .594           .143          .806          .!598       .605    t.001 3.05   1.164      '-030          .779         .Ht          \.461         1.075 t.093               t.478     \.982 4.05   t.t79       t.024          .178        .995         t.243           .B3t       1~027         t.727    2. ttO
  !5.05    .839        .&3t         .as8        .798           .724          .474          .* 852    1.254     t.636 8.05     .612        .467         .496         .1589         .417          .313           .411        .803   1. 1153 8.05      .7!55      .437         .612         .695          .3*to         .3t3           .405        .735   t.319 10.05      .253       .157        ** 183        .165           .032          .093 . .t03               .tao      .3'74 13.0S

• 053 .OBt .034 .027 .001 .03t .025 .028 .072 18.00 .016 .001 .004 .ooo .ooo .oot .001 .002 .ooo 99.00 .ooo .000 .000 .ooo .ooo .000 .ooo .ooo .000 To1:al 6.217 4.663 4.304 a.011 15. 169 3.830 4.424 1.933 1.8215 su.... ry Tabla of Parcent by Speed and C\aaa Clas* A a c D E F G Speed

               .45      .004         .0(>1        .ooo           _095

• 215'1 .2'75 .346 t.05 .018 .012 .027 .508 1.035 t.080 .780 2.05 .286 .17 t .246 3.256 !5.028 3.228 1.419 3.05 .744 .428 .St6 6.2158 7. 173 3.*272 .985 4.05 .992 . !581 .781 8. 165 6.404 , .902 .46G

            !5.05        .909         .!506        .aoa       7.302         4.:r.57           .80'1      .077 6.05        .712         .388         .6t3       6. 167        2.938             .164       .Ot3 IS.OS       .819         .!500

• 7!5!5 7.616 2..734 .oat .011 10.05 .230 .150 .t96 2.806 .867 .009 .000 13.05 .07!1 .032 .055
• 7l5!5
• Ust .001 .000 H.00 .004 .000 .0\8
• H'J .0\2 .000 .000 99.00 .000 .ooo .0(>1 .oot .ooo .000 .ooO Page 155 of 268

Revision 9 February 27, 2017 Figure 8-1 Instantaneous View of Plume

                 'I Wind This figure represents a snapshot of a projection of a plume on the horizontal plane. As it moves downwind, the plume meanders about the average wind direction and broadens (adapted from Reference 18).

Page 156 of 268

Revision 9 February 27, 2017 Page 157 of 268

Revision 9 February 27, 2017 Figure B-3 Effect of Observation Period on Plume Shape SCAL( ~ This sketch represents the approximate outlines of a smoke plume observed instataneously and averaged over periods of 10 minutes and 2 hours. The diagram on the right shows the corresponding cross plume distribution patterns. The plume width increases as the period of observation increases (from Reference 18). Page 158 of 268

Revision 9 February 27, 2017 Figure B-4 A Gaussian Plume I (x.-y.Z) This sketch illsutrates a plume characterized by Equation B-9. The plume is moving downwind in the x direction. Both the horizontal dispersion parameter sz increases as x increases. The reflected component has been omitted in this illustration (adapted from Reference 24). Page 159 of 268

Revision 9 February 27, 2017 I APPENDIX C GENERIC DATA Page 160 of 268

Revision 9 February 27, 2017 APPENDIXC GENERIC DATA C.1 INTRODUCTION This appendix contains generic offsite dose calculation parameter factors, or values. Site specific factors are provided in the station annex Appendix F. The factors described in section C.2 are found in the prescribed references and are not repeated in this appendix. C.2 10CFR50 DOSE COMMITMENT FACTORS With the exception of H-3, the dose commitment factors for 10CFR50 related calculations are exactly those provided in Regulatory Guide 1.109 (Reference 6). The following table lists the parameters and the corresponding data tables in the RG 1.109: PATHWAY ADULT TEENAGER CHILD INFANT Inhalation RG 1.109:Table E-7 RG 1.109:Table E-8 RG 1.109:Table E-9 RG 1.109:Table E-10 Ingestion RG 1.109:Table E-11 RG 1.109:Table E-12 RG 1.109:Table E-13 RG 1.109:Table E-14 These tables are contained in Regulatory Guide 1.109 (Reference 6). Each table (E-7 through E-14) provides dose factors for seven organs for each of 73 radionuclides. For radionuclides not found in these tables, dose factors will be derived from ICRP 2 (Reference 50) or NUREG-0172 (Reference 51). The values for H-3 are taken from NUREG-4013 (Reference 107). Page 161 of 268

Revision 9 February 27, 2017 Table C-1 Miscellaneous Dose Assessment Factors - Environmental Parameters Parameter Value Comment Eauation Basisa fa 0.76 A-10, A-11 A fl 1.0 A-10, A-11 A fo 1.0 A-12, A-14 A fs 1.0 A-12, A-14 A tb 262,800 hrs 30 vears A-8 c tf 48 hrs Cow Milk Pathwav A-12 A tf 480 hrs Cow Meat Pathwav A-14 A th 1440 hrs 60 davs for oroduce A-10 A th 2160 hrs 90 davs for produce A-12, A-14 A tL 24 hrs 1 day for leafv veaetables A-10 A QF 50 Kolda A-12, A-13, A-14, A-15 B r 0.2 For Particulates A-10, A-12, A-14 A Yo 0.7 Kg/m" A-12, A-14 A Ys 2.0 Ka/m" A-12, A-14 A Yv 2.0 Kg/m" A-10 A 1 Aw 0.0021 hr" A-10, A-12, A-14 A H 8 gm/m;j Absolute Atmospheric Humidity A-11, A-13, A-15 D aBasis key: A: Reference 6, Table E-15. B: Reference 6, Table E-3. C: The parameter tb is taken as the midpoint of plant operating life (based upon an assumed 60 year plant operating lifetime). D: Reference 14, Section 5.3.1.3. Page 162 of 268

Revision 9 February 27, 2017 Table C-2 Miscellaneous Dose Assessment Factors - Consumption Parameters Type Variable Infant Child Teenager Adult BRa 1400 3700 8000 8000 Air (m3/yr) Milk Uam 330 330 400 310 (L/yr) Produce Ua::J 0 520 630 520 (Kg/yr) Leafy UaL 0 26 42 64 Vegetables (Kg/yr) Meat Uat 0 41 65 110 (Kg/yr) Water Uavv 330 510 510 730 (L/yr) Fish Uar 0 6.9 16 21 (Kg/yr) From Regulatory Guide 1.109, Table E-5. Page 163 of 268

Revision 9 February 27, 2017 Table C-3 Stable Element Transfer Data Ft FM( Cow) Element Meat (d/kg) Milk (d/L) Reference H 1.2E-02 1.0E-02 6 Be 1.5E-03 3.2E-03 Footnote 1 c 3.1E-02 1.2E-02 6 F 2.9E-03 1.4E-02 Footnote 2 Na 3.0E-02 4.0E-02 6 Mg 1.5E-03 3.2E-03 Footnote 1 Al 1.5E-02 1.3E-03 Footnote 3 p 4.6E-02 2.5E-02 6 Cl 2.9E-03 1.4E-02 Footnote 2 Ar NA NA NA K 1.8E-02 7.21;::-03 16 Ca 1.6E-03 1.1E-02 16 Sc 2.4E-03 7.5E-06 Footnote 4 Ti 3.4E-02 5.0E-06 Footnote 5 v 2.8E-01 1.3E-03 Footnote 6 Cr 2.4E-03 2.2E-03 6 Mn 8.0E-04 2.5E-04 6 Fe 4.0E-02 1.2E-03 6 Co 1.3E-02 1.0E-03 6 Ni 5.3E-02 6.7E-03 6 Cu 8.0E-03 1.4E-02 6 Zn 3.0E-02 3.9E-02 6 Ga 1.5E-02 1.3E-03 Footnote 3 Ge 9.1E-04 9.9E-05 Footnote 7 As 1.7E-02 5.0E-04 Footnote 8 Se 7.7E-02 1.0E-03 Footnote 9 Br 2.9E-03 2.2E:-02 Ft Footnote 2;FM from Ref. 16 Kr NA NA NA Rb 3.1E-02 3.0E-02 6 Sr 6.0E-04 8.0E-04 6 y 4.6E-03 1.0E-05 6 Zr 3.4E-02 5.0E-06 6 Nb 2.8E-01 ~.5E-03 6 Mo 8.0E-03 7.5E-03 6 Tc 4.0E-01 2.5E-02 6 Ru 4.0E-01 1.oE-06 6 Rh 1.5E-03 1.0E-02 6 Pd 5.3E-02 6.7E-03 Footnote 10 Cd 3.0E-02 2.0E-02 Footnote 11 In 1.5E-02 1.3E-03 Footnote 3 Sn 9.1E-04 9.9~-05 Footnote 7 Sb 5.0E-03 2.0E-05 98 Ag 1.7E-02 5.0E-02 6 Te 7.7E-02 1.0E-03 6 I 2.9E-03 6.0E-03 6 Xe NA NA NA Cs 4.0E-03 1.2E:-02 6 Ba 3.2E-03 4.0E-04 6 La 2.0E-04 5.0E-06 6 Ce 1.2E-03 ~.OE-04 6 Pr 4.7E-03 5.0E-06 6 Nd 3.3E-03 5.oE-o6 6 Page 164 of 268

Revision 9 February 27, 2017 Table C-3 (Cont'd) Stable Element Transfer Data Ft FM (Cow) Element Meat (d/kg) Milk (d/L} Reference Pm 2.9E-04 2.0E-05 16 Sm 2.9E-04 2.0E-05 16 Eu 2.9E-04 2.0E-05 16 Gd 2.9E-04 2.0E-05 16 Dy 2.9E-04 2.0E-05 16 Er 2.9E-04 2.0E-05 16 Tm 2.9E-04 2.0E-05 16 Yb 2.9E-04 2.0E-05 16 Lu 2.9E-04 2.0E-05 16 Hf 3.4E-02 5.0E-06 Footnote 5 Ta 2.8E-01 1.3E-03 FM - Ref.16; Ft -Footnote 6 w 1.3E-03 5.0E-04 6 Re 1.0E-01 1.3E-03 FM- Ref.16; Ft-Footnote 12 Os 2.2E-01 6.0E-04 Footnote 13 Ir 7.3E-03 5.5E-03 Footnote 14 Pt 5.3E-02 6.7E-03 Footnote 10 Au 1.3E-02 3.2E-02 Footnote 15 Hg 3.0E-02 9.7E-06 FM - Ref.16; Ft -Footnote 11 Tl 1.5E-02 1.3E-03 FM - Ref.16; Ft -Footnote 3 Pb 9.1E-04 9.9E-05 98 Bi 1.7E-02 5.0E-04 98 Ra 5.5E-04 5.9E-04 98 Th 1.6E-06 5.0E-06 98 u 1.6E-06 1.2E-04 98 Np 2.0E-04 5.0E-06 6 Am 1.6E-06 2.0E-05 98 Notes:

1. NA =It is assumed that noble gases are not deposited on the ground.

2. Elements listed are those considered for 10CFR20 assessment and compliance.

Footnotes: There are numerous Ft and FM values that were not found in published literature. In these cases, the periodic table was used in conjunction with published values. The periodic table was used based on a general assumption that elements have similar characteristics when in the same column of the periodic table. The values of elements in the same column of the periodic table, excluding atomic numbers 58-71 and 90-103, were averaged then assigned to elements missing values located in the same column of the periodic table. This method was used for all columns where there were missing values except column 3A, where there was no data, hence, the average of column 2B and 4A were used.

1. Values obtained by averaging Reference 6 values of Ca, Sr, Ba and Ra.

2. Ft value obtained by assigning the Reference 6 value for I. FM value obtained by averaging l(Ref. 6) and Br (Ref.16).

3. Ft values obtained by averaging Zn (Ref.6) and Pb (Ref. 98); there were .novalues for elements in the same column; an average is taken between values of columns 2B and 4A on the periodic table. FM values obtained by using the value for Tl from Reference 16. *

4. Values obtained by averaging Reference 6 values of Y and La.

5. Values obtained by assigning the Reference 6 value for Zr.

6. Ft values obtained from Ref. 6 value for Nb. FM values obtained by averaging values for Nb (Ref.6) and Ta (Ref. 16).

7. Values obtained from the Reference 6 values for Pb.

8. Values obtained from the Reference 6 values for Bi.

9. Values obtained from the Reference 6 values for Te.

10. Values obtained from the Reference 6 values for Ni.

11. Ft values obtained from Ref. 6 values for Zn. FM values obtained by averaging the Reference 6 values for Zn and Hg.

12. Values obtained by averaging Reference 6 values for Mn, Tc, Nd and Reference 98 value for U.

13. Values obtained by averaging Reference 6 values from Fe and Ru.

14. Values obtained by averaging Reference 6 values from Co and Rh.

15. Values obtained by averaging Reference 6 values from Cu and Ag.

Page 165 of 268

Revision 9 February 27, 2017 Table C-4 Atmospheric Stability Classes Pasquill Temperature Change a S,tability cre with Height Description Class (degrees) (°C/100 m) Extremely A >22.5 <-1.9 Unstable Moderately B. 17.5 to 22.5 -1.9 to-1.7 Unstable Slightly c 12.5 to 17.5 -1.7 to-1.5 Unstable Neutral D 7.5 to 12.5 -1.5 to -0.5 Slightly E 3.8 to 7.5 -0.5 to 1.5 Stable Moderately F 2.1to3.8 1.5 to 4.0 Stable Extremely G Oto 2.1 >4.0 Stable 2 cr9 is the standard deviation of horizontal wind direction fluctuation over a period of 15 minutes to 1 hour. From Regulatory Guide 1.21, Table 48. Page 166 of 268

Revision 9 February 27, 2017 Table C-5 Vertical Dispersion Parameters Section 1 Vertical Dispersion Parameters O"z O"z (meters)= aRb+c with O"z limited to a maximum of 1000 meters R = downwind range (meters) a, b and c have the values listed below: Stability 100 < R < 1000 R > 1000 Class g_ Q Q g_ Q Q A * *

• 0.00024 2.094 -9.6 B * * * * *
• c 0.113 0.911 0.0 * *
• D 0.222 0.725 -1.7 1.26 0.516 -13.0 E 0.211 0.678 -1.3 6.73 0.305 -34.0 F 0.086 0.74 -0.35 18.05 0.18 -48.6 G 0.052 0.74 -0.21 10.83 0.18 -29.2 Basis: Reference 53, except for cases denoted by an asterisk. In these cases, the value of O"z is obtained by a polynomial approximation to the data from Reference 53 (see Section 2 of this table). The functions given in Reference 50 are not used because they are discontinuous at 1000 meters.

Section 2 Polynomial Approximation for crz.;. 2 3 O"z (meters)= exp [a 0 + a1P + a2P + a3P ] with O"z limited to a maximum of 1000 meters P = loge [R(meters)] ao, a1, a2 and a3 have the values listed below: Stability Class Range Coefficients A 100 ~ R ~ 1000 ao = -10.50 a1 = 6.879 a2 = -1.309 a3= 0.0957 B 100 ~ R ~ 1000 ao = -0.449 a1 = 0.218 a2 = 0.112 a3 = -0.00517 B R > 1000 ao = 319.148 a1 = -127.806 a2 = 17.093 a3 = -0.750 c R > 1000 ao = 5.300 a1 = -1.866 a2 = 0.3509 a3 = -0.01514 Page 167 of 268

Revision 9 February 27, 2017 Table C-6 Allowable Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Waste Allowable Concentration (µCi/ml) 2 Nuclide Zion Kr85m 2E-4 Kr85 5E-4 Kr87 4E-5 Kr88 9E-5 Ar41 7E-5 Xe 131m 7E-4 Xe133m 5E-4 Xe 133 6E-4 Xe 135m 2E-4 Xe 135 2E-4 2 Computed from Equation 17 of ICRP Publication 2 (Reference 50) adjusted for infinite cloud submersion 3 in water, and R = 0.01 rem/week, Pw = 1.0 gm/cm , and Pw /Pt= 1.0. Page 168 of 268

Revision 9 February 27, 2017 Table C-7 Radiological Decay Constants p,,i) in hr"1 lsotooe Lambda lsotooe Lambda lsotooe Lambda H-3 6.44E-06 As-73 3.6E-04 Tc-104 2.31E+OO Be-7 5.4E-04 As-74 1.62E-03 Ru-97 9.96E-03 C-14 1.38E-08 As-76 2.63E-02 Ru-103 7.34E-04 F-18 3.78E-01 As-77 1.79E-02 Ru-105 1.56E-01 Na-22 3.04E-05 Se-73 9.69E-02 Ru-106 7.84E-05 Na-24 4.62E-02 Se-75 2.41E-04 Rh-106 8.33E+01 Mo-27 4.39E+OO Br-77 1.21 E-02 'Pd-109 5.15E-02 Mg-28 3.31 E-02 Br-80 2.38E+OO Cd-109 6.22E-05 Al-26 1.10E-10 Br-82 1.96E-02 ln-111 1.02E-02 Al-28 1.85E+01 Br-83 2.90E-01 ln-115M 1.59E-01 P-32 2.02E-03 Br-84 1.30E+OO ln-116 7.66E-01 Cl-38 1.12E+OO Br-85 1.45E+01 Sn-113 2.51E-04 Ar-41 3.79E-01 Kr-79 1.98E-02 Sn-117M 2.12E-03 K-40 6.19E-14 Kr-81

• 3.77E-10 Sn-119M 9.85E-05 K-42 5.61E-02 Kr-83M, 3.79E-01 Sb-117 2.48E-01 K-43 3.07E-02 Kr-85M 1.55E-01 Sb-122
• 1.07E-02 Ca-47 6.37E-03 Kr-85 7.38E-06 Sb-124 4.80E-04 Sc-44 1.76E-01 Kr-87 5.44E-01
• Sb-125
• 2.86E-05 Sc-46M 1.33E+02 Kr-88 2.44E-01 Sb-126 2.33E-03 Sc-46 3.44E-04 Kr-90 7.71E+OO Ag-108M 6.23E~07 Sc-47 8.44E-03 Rb-84 8.78E-04 Aq-108 1.75E+01 Ti-44 1.67E-06 Rb-86 1.55E-03 Ao-110M 1.16E-04 V-48 1.81E-03 Rb-87 I
• 1.67E-15 Ag-111 3.87E-03 Cr-51 1.04E~03 Rb-88 2.33E+OO Te-121M 1.88E-04 Mn-52M 1.94E+OO Rb-89 2.69E+OO Te-121 1.72E-03 Mn-52 5.16E-03 Sr-85 4.45E-04* Te-123M 2.41E-04 Mn-54. 9.23E-05 Sr-87M
• 2.47E-01 Te-125M 4.98E-04 Mn-56 2.69E-01 Sr~89 5.71 E-04 Te-125 O.OOE+OO Fe-52 8.37E-02 Sr-90 2.77E-06' Te-127M 2.65E-04 Fe-55 2.93E-05 Sr-91 7.29E-02 Te-127 7.41E-02 Fe-59 6.47E-04 Sr-:92 2.56E-01 Te-129M 8.59E-04 Co-57 1.07E-04 Y-86 4.70E-02 Te-129 5.96E-01 Co-58 4.08E-04 Y-87 ' 8.63E-03 Te-131M 2.31E-02 Co-60 1.50E-05 Y-88 2.71E-04 Te-131 1.6.6E+OO Ni-63 7.90E-07 Y-90 1.08E-02 Te-132 8.86E-03 Ni-65 2.75E-01 Y-91M 8.35E-01 Te-134 9.93E-01 Cu-64 5.46E-02 Y-91 4.94E-04 1-123 5.28E-02 Cu-67 4.67E-04 Y-92 1.96E-01 1-124 6.91E-03 Cu-68 8.31E+01 Y-93 6.86E-02 1-125 4.80E-04 Zn-65 1.18E:04 Zr-95 4.51E-04 1-130 5.61E-02 Zn-69M 5.04E.,02 Zr-97 4.10E-02 1-131 3.59E-03 Zn-69 7.46E-01 Nb-94 3.90E-09 1-132 3.01E-01 Ga-66 7.37E-02 Nb-95 8.00E-03 1-133 3.33E-02 Ga-67 8.85E-03 Nb-97M 4.15E+01 1--134 7.89E-01 Ga-68 6.10E-01 Nb-97 5.76E-01 1-135 1.05E-01 Ga-72 4.91E-02 Mo-99 1.05E-02 Xe-127 7.93E-04 Ge-77 6.13E-02 Tc-99M 1.15E-01 Xe-129M 3.25E-03 As-72 2.67E-02 Tc-101 2.92E+OO Xe-131M 2.44E-03 Page 169 of 268

Revision 9 February 27, 2017 Table C-7 (Cont'd) Radiological Decay Constants p..1) in hr"1 lsotooe Lambda lsotooe Lambda Xe-133M 1.32E-02 Yb-175 6.89E-03

• Xe-133 5.51E-03 Lu-177 4.30E-03 Xe-135M 2.70E+OO Hf-181 6.81E-04 Xe-135 7.61E-02 Ta-182 2.52E-04 Xe-137 1.08E+01 Ta-183 5.78E-03 Xe-138 2.94E+OO W-187 2.91E-02 Cs-129 2.16E-02 Re-188 4.08E-02 Cs-132 4.46E-03 Os-191 1.88E-03 Cs-134 3.84E-05 lr-194 3.62E-02 Cs-136 2.19E-03 Pt-195M 7.18E-03 Cs-137 2.62E-06 Pt-197 3.79E-02 Cs-138 1.29E+OO Au-195M 8.15E+01 Cs-139 4.41E+OO Au-195 1.58E-04 Ba-131 2.45E-03 Au-198 1.07E-02 Ba-133M 1.78E-02 Au-199 9.20E-03 Ba-133 7.53E-06 Hg-197 2.91 E-02 Ba-135M 2.41E-02 Hg-203 6.20E-04 Ba-137M 1.63E+01 Tl-201 9.49E-03 Ba-137 O.OOE+OO Tl-206 9.90E+OO Ba-139 4.99E-01 Tl-208 1.36E+01 Ba-140 2.26E-03 Pb-203 .1.33E-02 Ba-141 2.27E+OO Pb-210 3.55E-06 Ba-142 3.88E+OO Pb-212 6.51E-02 La-140 1.72E-02 Pb~214 1.55E+OO La-142 4.35E-01 Bi-206 4.63E-03 I

Ce-139 2.10E-04 Bi-207 2.37E~06 Ce-141 8.88E-04 Bi-214 2.09E+OO. Ce-143 2.10E-02 Ra-226 4.94E-08 Ce-144 1.02E-04 Th-232 5.63E,.15 Pr-142 3.62E-02 U-238 1.77E-14 Pr-143 2.13E-03 Np-239 1.23E-02 Pr-144 2.40E+OO Am-241

• 1.83E-07 Nd-147 2.63E-03 Nd-149 4.01E-01 {A.i) =Radiological Decay constant Pm-145 4.47E-06 = 0.693/Ti '

Pm-148M 6.99E-04 Pm-148 5.38E-03 Ti = Radiological Half-Liie in hours Pm-149 1.31E-02 (from Reference 70). Sm-153 1.48E-02 Except for Cu-68, Tc-104, Ba-137, Ta-183, TL-206, Eu-152 5.82E-06 Bi-206 which are fro m References 100. Eu-154 8.99E-06 Eu-155 1.59E-05 Gd-153 1.20E-04 Dy-157 8.60E-02 Er-169 3.07E-03 Er-171 9.22E-02 Tm-170 2.25E-04 Yb-169 9.03E-04 Table C-8 Page 170 of 268

Revision 9 February 27, 2017 Bioaccumulation Factors (BF 1) to be Used in the Absence of Site-Specific Data BF 1 for Freshwater Fish Element (pCi/kg per pCi/L) Reference H 9.0E-01 6 Be 2.8E+01 Footnote 2 c 4.6E+03 6 F 2.2E+02 Footnote 16 Na 1.0E+02 6 Mg 2.8E+01 Footnote 2 Al 2.2E+03 Footnote 13 p 1.0E+05 6 Cl 2.2E+02 Footnote 16 Ar NA NA K 1.0E+03 Footnote 1 Ca 2.8E+01 Footnote 2 Sc 2.5E+01 Footnote 3 Ti 3.3E+OO Footnote 4 v 3.0E+04 Footnote 5 Cr 2.0E+02 6 Mn 4.0E+02 6 Fe 1.0E+02 6 Co 5.0E+01 6 Ni 1.0E+02 6 Cu 5.0E+01 6 Zn 2.0E+03 6 Ga 2.2E+03 Footnote 13 Ge 2.4E+03 Footnote 12 As 3.3E+04 Footnote 14 Se 4.0E+02 Footnote 15 Br 4.2E+02 6 Kr NA NA Rb 2.0E+03 6 Sr 3.0E+01 6 y 2.5E+01 6 Zr 3.3E+OO 6 Nb 3.0E+04 6 Mo 1.0E+01 6 Tc 1.5E+01 6 Ru 1.0E+01 6 Rh 1.0E+01 6 Pd 1.0E+02 Footnote 9 Cd 2.0E+03 Footnote 11 In 2.2E+03 Footnote 13 Sn 2.4E+03 Footnote 12 Sb 1.0E+OO 98 Ag 2.3E+OO 56 Te 4.0E+02 6 I 1.5E+01 6 Xe NA NA Cs 2.0E+03 6 Ba 4.oE+oo 6 La 2.5E+01 6 Ce 1.0E+OO 6 Pr 2.5E+01 6 Nd 2.5E+01 6 Pm 3.0E+01 98 Sm 3.0E+01 Footnote 3 Page 171 of 268

Revision 9 February 27, 2017 Table C-8 (Cont'd) Bioaccumulation Factors (BFj) to be Used in the Absence of Site-Specific Data BF 1 for Freshwater Fish Element (pCi/kg per pCi/L} Reference Eu 1.0E+02 Footnote 3 Gd 2.6E+01 Footnote 3 Dy 2.2E+03 Footnote 3 Er 3.3E+04 Footnote 3 Tm 4.0E+02 Footnote 3 Yb 2.2E+02 Footnote 3 Lu 2.5E+01 Footnote 3 Hf 3.3E+OO Footnote 4 Ta 3.0E+04 Footnote 5 w 1.2E+03 6 Re 2.1E+02 Footnote 6 Os .5.5E+01 Footnote 7 Ir 3.0E+01 Footnote 8 Pt 1.0E+02 Footnote 9 Au 2.6E+01 Footnote 10 Hg 2.0E+03 Footnote 11 Tl 2.2E+03 Footnote 13 Pb 3.0E+02 98 Bi 2.0E+01 98 Ra 5.0E+01 98 Th 3.0E+01 98 u 1.0E+01 98 Np {OE+01 6 Am 3.0E+01 98 Footnotes: NA =It is assumed that noble gases are not accumulated. In Reference 6, see Table A-1. A number of bioaccumulation factors could not be found in literature. In this case, the periodic table was used in conjunction with published element values. This method was used for periodic table columns except where there were no values for column 3A so the average of columns 28 and 4A was assigned.

1. Value is the average of Reference* 6 values in literature for H, Na, Rb and Cs.

2. Value is the average of Ref. 6 values in literature for Sr; Ba and Ref. 98 values for Ra.

3. Value is the same as the Reference 6 value used for Y.

4. Value is the same as the Reference 6 value used for Zr.

5. Value is the same as the Reference 6 value used for Nb.

6. Value is the average of Reference 6 values in literature for Mn and Tc.

7. Value is the average of Reference 6 values in literature for Fe and Ru.

8. Value is the average of Reference 6 values in literature for Co and Rh.

9. Value is the same as the Reference 6 value used for Ni.

10. Value is the average of Reference 6 values in literature for Cu and Reference 56 value for Ag.

11. Value used is the same as the Reference 6 value used for Zn.

12. Value is the average of Reference 6 value in literature for C and Reference 98 value for Pb.

13. Value is the average of columns 28 and 4A, where column 28 is the "Reference 6 value for Zn" and column 4A is the average of "Reference 6 value for C and Reference 98 value for Pb".

14. Value is the average of Ref. 6 value found in literature (or P and the Ref. 98 values for Bi and Sb.

15. Value is the same as the Reference 6 value used for Te.

16. Value is the average of Reference 6 values found in literature for Br and I.

Page 172 of 268

Revision 9 February 27, 2017 Table C-9 Dose Factors for Noble Gases Beta Air Beta Skin GammaAir Gamma Total Body Dose Factor Dose Factor Dose Factor Dose Factor Ni Li Mi Ki Nuclide (mrad/yr ger uCi/m") (mrem/yr ger uCi/m") (mrad/yr ger uCi/m") (mrem/yr ger uCi/m") Kr-83m 2.88E+02 --- 1.93E+01 7.56E..:02 Kr-85m 1.97E+03 1.46E+03 1.23E+03 1.17E+03 Kr-85 1.95E+03 1.34E+03 1.72E+01 1.61E+01 Kr-87 1.03E+04 9.73E+03 6.17E+03 5.92E+03 Kr-88 2.93E+03 2.37E+03 1.52E+04 1.47E+04 Kr-89 1.06E+04 1.01E+04 1.73E+04 1.66E+04 Kr-90 7.83E+03 7.29E+03 1.63E+04 1.56E+04 Xe-131m 1.11E+03 4,.76E+02 1.56E+02 9.15E+01 Xe-133m 1.48E+03 9.94E+02 3.27E+02 2.51E+02 Xe-133 1.05E+03 3.06E+02 3.53E+02 2.94E+02 Xe-135m 7.39E+02 7,.11E+02 3.36E+03 3.12E+03 Xe-135 2.46E+03 1.86E+03 1.92E+03 1.81E+03 Xe-137 1.27E+04 1.22E+04 1.51E+03 1.42E+03 Xe-138 4.75E+03 4.13E+03 9.21E+03 8.83E+03 Ar-41 3.28E+03 2.69E+03 . 9.30E+03 8.84E+03 Source: Table B-1 of Reference 6. Page 173 of 268

Revision 9 February 27, 2017 Table C-10 External Dose Factors for Standing on Contaminated Ground 2 DFGu {mrem/hr Rer l;!Ci/ m ) Whole Body Element Dose Factor Reference Element Dose Factor Reference H-3 O.OOE+OO 6 Be-7 5.95E-10 99 C-14 O.OOE+OO 6 F-18 1.19E-08 99 Na-22 2.42E-08 99 Na-24 2.50E-08 6 Mg-27 1.14E-08 99 Mg-28 1.48E-08 99 Al-26 2.95E-08 99 Al-28 2.00E-08 99 P-32 O.OOE+OO 6 Cl-38 1.70E-08 99 Ar-41 1.39E-08 99 K-40 2.22E-09 99 K-42 4.64E-09 99 K-43 1.19E-08 99 Ca-47 1.14E-08 99 Sc-44 2.50E-08 99 Sc-46m 1.21 E-09 99 Sc-46 2.24E-08 99 Sc-47 1.46E-09 99 Ti-44 1.95E-09 99 V-48 3.21E-08 99 Cr-51 2.20E-10 6 Mn-52m 2.79E-08 99 Mn-52 3.80E-08 99 Mn-54 5.80E-09 6 Mn-56 1.10E-08 6 Fe-52 9.12E-09 99 Fe-55 O.OOE+OO 6 Fe-59 8.00E-09 6 Co-57 1.65E-09 99 Co-58 7.00E-09 6 Co-60 1.70E-08 6 Ni-63 O.OOE+OO 6 Ni-65 3.70E-09 6 Cu-64 1.50E-09 6 Cu-67 1.52E-09 99 Cu-68 8.60E-09 1 Zn-65 4.00E-09 6 Zn-69m 5.06E-09 99 Zn-69 O.OOE+OO 6 Ga-66 2.70E-08 99 Ga-67 1.89E-09 99 Ga-68 1.24E-08 99 Ga-72 3.00E-08 99 Ge-77 1.34E-08 99 As-72 2.23E-08 99 As-73 1.16E-10 99 As-74 9.41E-09 99 As-76 6.46E-09 99 As-77 1.79E-iO 99 Se-73 1.38E-08 99 Se-75 4.98E-09 99 Br-77 3.84E-09 99 Br-80 2.01E-09 99 Br-82 3.00E-08 99 Br-83 6.40E-11 6 Br-84 1.20E-08 6 Br-85 O.OOE+OO 6 Kr-79 3.07E-09 99 Kr-81 1.59E-10 99 Kr-83m 1.42E-11 99 Kr-85m 2.24E-09 99 Kr-85 1.35E-10 99 Kr-87 1.03E-08 99 Kr-88 2.07E-08 99 Kr-90 1.56E-08 99 Rb-84 1.07E-08 99 Rb-86 6.30E-10 6 Rb-87 O.OOE+OO 99 Rb-88 3.50E-09 6 Rb-89 1.50E-08 6 Sr-85 6.16E-09 99 Sr-87m 3.92E-09 99 Sr-89 5.60E-13 6 Sr-90 1.84E-11 99 Sr-91 7.10E-09 6 Sr-92 9.00E-09 6 Y-86 4.00E-08 99 Y-87 5.53E-09 99 Y-88 2.88E-08 99 Y-90 2.20E-12 6 Y-91m 3.80E-09 6 Y-91 2.40E-11 6 Y-92 1.60E-09 6 Y-93 5.70E-10 6 Zr-95 5.00E-09 6 Zr-97 5.50E-09 6 Nb-94 1.84E-08 99 Nb-95 5.10E-09 6 Nb-97m 8.57E-09 99 Nb-97 8.48E-09 99 Mo-99 1.90E-09 6 Tc-99m 9.60E-10 6 Tc-101 2.70E-09 6 Tc-104 1.83E-08 1 Ru-97 2.99E-09 99 Ru-103 3.60E-09 6 Ru-105 4.50E-09 6 Ru/Rh-106 5.76E-09 3 6,99 Pc-109 3.80E-10 99 Cc-109 1.12E-10 99 ln-111 5.11E-09 99 ln-115m 2.01E-09 99 ln-116 O.OOE+00 2 Sn-113 1.15E-09 99 Sn-117m 1.96E-08 99 Sn-119m 7.05E-11 99 Sb-117 O.OOE+00 2 Sb-122 2.71E-09 1 Sb-124 1.16E-081 Sb-125 4.56E-09 99 Sb-126 7.13E-10 99 Ag-108m 1.92E-08 99 Ag-108 1.14E-09 99 Ag-110m 1.80E-08 6 Ag-111 6.75E-10 99 Te-121m 2.65E-09 99 Te-121 6.75E-09 99 Te-123m 1.88E-09 99 Te-125m 3.50E-11 6 Te-125 O.OOE+002 Te-127m 1.10E-12 6 Te-127 1.00E-11 6 Te-129m 7.70E-10 6 Te-129 7.10E-10 6 Te-131m 8.40E-09 6 Page 174 of 268

Revision 9 February 27, 2017 Table C-10 (cont.) External Dose Factors for Standing on Contaminated Ground 2 DFGu (mrem/hr 12er 12Ci/ m } Whole Body Element Dose Factor Reference Element Dose Factor Reference Te-131 2.20E-09 6 Te-1-132 3.40E-09 5 6 Te-134 1.05E-08 99 1-123 2.12E-09 99 1-124 1.23E-08 99 1-125 2.89E-10 99 1-130 1.40E-08 6 1-131 2.80E-09 6 1-133 3.70E-09 6 1-134 1.60E-08 6 1-135 1.20E-08 6 Xe-127 3.44E-09 99 Xe-129m 5.57E-10 99 Xe-131m 2.13E-10 99 Xe-133m 4.81E-10 99 Xe-133 5.91E-10 99 Xe-135m 5.23E-09 99 Xe-135 3.36E-09 99 Xe-137 4.26E-09 99 Xe-138 1.30E-08 99 Cs-129 3.39E-09 99 Cs-132 8.40E-09 99 Cs-134 1.20E-08 6 Cs-136 1.50E-08 6 Cs-137/Ba-137m 1.14E-084 6, 99 Cs-138 2.10E-08 6 Cs-139 5.15E-09 99 Ba-131 5.74E-09 99 Ba-133m 8.10E-10 99 Ba-133 4.85E-09 99 Ba-135m 7.26E-10 99 Ba-137m 7.17E-09 99 Ba-137 O.OOE+00 2 Ba-139 2.40E-09 6 Ba-La-140 1.71 E-086 6 Ba-141 4.30E-09 6 Ba-142 7.90E-09 6 1:.a-142 1.50E-08 6 Ce-139 2.04E-09 99 Ce-141 5.50E-10 6 7 Ce-143 2.20E-09 6 Ce-Pr-144 5.20E-10 6 Pr-142 1.84E-09 99 J?r-143 O.OOE+OO 6 Nc-147 1.00E-09 6 Nc-149 5.32E-09 99 Pm-145 3.38E-10 99 Pm-148m 2.35E-08 99 Pm-148 7.22E-09 99 f>m-149 5.32E-10 99 Sm-153 8.95E-10 99 Eu-152 1.30E-08 99 Eu-154 1.41 E-08 99 Eu-155 8.27E-10 99 Gc-153 1.46E-09 99 Dy-157 4.39E-09 99 Er-169 6.12E-14 99 Er-171 5.11E-09 99 Tm-170 3.41 E-10 99 Yb-169 4.12E-09 99 Yb-175 4.94E-10 99 Lu-177 4.60E-10 99 Hf-181 6.67E-09 99 Ta-182 1.42E-08 99 Ta-183 2.93E-09 1 W-187 3.10E-09 6 Re-188 1.89E-09 99 Os-191 9.83E-10 99 lr-194 2.31 E-09 99 Pt-195m 9.79E-10 99 Pt-197 3.57E-10 99 Au-195m 2.54E-09 99 Au-195 1.14E-09 99 J;\u-198 5.19E-09 99 Au-199 1.18E-09 99 Hg-197 9.33E-10 99 Hg-203 2.89E-09 99 Tl-201 1.24E-09 99 Tl-206 O.OOE+00 2 Tl-208 3.58E-08 99 Pb-203 3.88E-09 99 Pb-210 3.57E-11 99 Pb-212 1.91 E-09 99 Pb-214 3.18E-09 99 Bi-206 3.74E-08 99 Bi-207 1.77E-08 99 Bi-214 1.71 E-08 99 Ra-226 8.78E-11 99 Th-232 8.14E-12 99 u-238 7.98E-12 99 Np-239 9.50E-10 6 Am-241 3.48E-10 99 Valued derived by comparing the percentage and MeV of the nuclide's gammas and then comparing to Cesium-137, as a value was not available in the literature. 2 0.0 due to low yield and short half life. A value was not available in the literature. 3 Value is the sum of Ru-106 (1.50E-9) and Rh-106 (4.26E-9). The Rh-106 value is from Reference 99 and the Ru-106 value is from Reference 6. 4 Value is the sum of Cs-137 (4.20E-9) and Ba-137m (7.17E-9). The values are from references 6 and 99, respectively. 5 Value is the sum ofTe-132 (1.70E-9) and 1-132 (1.70E-9). 6 Value is the sum of Ba-140 (2.10E-9) and La-140 (1.50E-8) from reference 6. In Reference 6, see Table E-6. 7 Value is the sum of Ce-144 (3.20E-10) and Pr-144 (2.00E-10) from reference 6. Note: Dose assessments for 10CFR20 and 40CFR190 compliance are made for an adult only. Dose assessments for 10CFR50 Appendix are made using dose factors of Regulatory Guide 1.109 (Reference 6) for all age groups. Page 175 of 268

Revision 9 February 27, 2017 Table C-11 Sector Code Definitions Angle Sector Sector from North Code Direction (Degrees) A N 348. 75 < e ~ 11.25 B NNE 11.25 < e ~ 33. 75 c NE 33. 75 < e ~ 56.25 D ENE 56.25 < e ~ 78. 75 E E 78.75 < e ~ 101.25 F ESE 101.25 < e ~ 123.75 G SE 123.75 < e ~ 146.25 H SSE 146.25 < e ~ 168.75 J s 168.75 < e ~ 191.25 K SSW 191.25 < e ~ 213.75 L SW 213.75 < e ~ 236.25 M WSW 236.25 < e ~ 258. 75 N w 258.75 < e ~ 281.25 p WNW 281.25 < e ~ 303.75 Q NW 303. 75 < e ~ 326.25 R NNW 326.25 < e ~ 348.75 Page 176 of 268

Revision 9 February 27, 2017 APPENDIX D Deleted Page 177 of 268

Revision 9 February 27, 2017 APPENDIX E Deleted Page 178 of 268

Revision 9 February 27, 2017 I APPENDIX F STATION-SPECIFIC DATA FOR ZION UNITS 1AND2 Page 179 of 268

Revision 9 February 27, 2017 APPENDIX F STATION-SPECIFIC DATA FOR ZION UNITS 1AND2 F.1 INTRODUCTION This appendix contains data relevant to the Zion site. Included is a figure showing the unrestricted area boundary, restricted area boundary and values of parameters used.in offsite dose assessment. Page 180 of 268 I

Revision 9 February 27, 2017 Table F-1 Aquatic Environmental Dose Parameters General lnformationa The existence of irrigation is not mentioned in Zion Environmental Report. Recreation includes one or more of the following: boating, water skiing, swimming, and sport fishing. Water and Fish Ingestion Parameters Value 6 z 10 Limits on Radioactivity in Unprotected Outdoor Tanksc,d,e Outside Temporary Tank Activity Concentration ~10% of 10CFR20 Appendix B Table 2 Column 2 Limits a This is based on information in Zion Environmental Report Section 2.3.2.2. b The parameters are defined in Section A.2.1 of Appendix A

• c See Section A.2.4 of Appendix A d Tritium and dissolved or entrained noble gases are excluded from this limit e The sum of the fractions for each radionuclide cannot exceed unity Table F-2 Page 181 of 268

Revision 9 February 27, 2017 Station Characteristics STATION: Zion Nuclear Power Station LOCATION: Zion, Illinois Characteristics of Elevated Release Point

1) Release Height = _ _m 2) Diameter= _ _m

3) Exit Speed = _ _ms-1 4) Heat Content = _ _ Kcal s- 1 Characteristics of Vent Stack Release Point

1) Release Height = 55.32 ma 2) Diameter= 2.32 m

3) Exit Speed = 11.2 ms- 1a Characteristics of Ground Level Point

1) Release Height = 0 m

2) Building Factor (D) = 57.6 ma Meterological Data A 250 ft Tower is Located 700 m NNW of Vent Stack release point Tower Data Used in Calculations Wind Speed Differential Release Point and Direction Temperature Elevated (NA) (NA}

Vent 125 250-35 Ground 35 250-35 a Used in calculating the meteorological and dose factors in Tables F-5, F-6, and F-7. See Sections B.3 through B.6 of Appendix B. Page 182 of 268

Revision 9 February 27, 2017 Table F-3 Critical Ranges Unrestricted Restricted Area Nearest Nearest Dairy Farm Site 0 Direction Area Boundary Boundary Residentb Within 5 Milesc Sector (m) (m) (m) (m) N A 469 375 4000 None NNE 8 475 400 d None NE c 400 325 d None ENE D 400 200 d None E E 400 175 d None ESE F 400 I 175 d None SE G 400 175 d None SSE H 400 200 d None s J 433 350 d None SSW K 439 375 3700 None SW L 518 475 2000 None WSW M 671 671 2000 None w N 658 658 1100 None WNW p 893 893 2000 None NW Q 847 847 2000 None NNW R 725 250 2400: None a Used in calculating the meteorological and dose factors in Tables F-5 and F-7. See sections 8.3 through 8.6 of Appendix 8. b 1992 annual survey by Teledyne Isotopes Midwest Laboratories. The distances are rounded to the nearest conservative 100 meters. c 1992 annual milk animal census by Teledyne Isotopes Midwest Laboratories. Used in calculating the D/Q values in Table F-6. The distances are rounded to the nearest conservative 100 meters. d Lake Michigan Page 183 of 268 L __

Revision 9 February 27, 2017 Table F-4 Average Wind Speeds Downwind Direction Site Sector Average Wind Speed (m/sec)a Mixed Mode Ground Level N A 5.0 3.2 NNE B 5.3 3.3 NE c 5.8 4.1 ENE D 5.6 3.9 E E 5.7 3.9 ESE F 5.1 3.3 SE G 4.9 3.0 SSE H 5.1 3.4 s J 5.9 4.6 SSW K 5.8 4.4 SW L 5.1 4.0 WSW M 5.2 4.6 w N 5.1 4.4 WNW p 4.8 3.7 NW Q 4.7 3.1 NNW R 5.1 3.9 a Calculated in Reference 81 using formulas in Section B. t.3 of Appendix B. Based on Zion site meteorological data, January 1979 through December 1987. Page 184 of 268

Revision 9 February 27, 2017 Table F-5 XIQ and D/Q Maxima at or Beyond the Unrestricted Area Boundary Downwind Site Radius Mixed Mode Vent) Release Ground Level Release Direction Sector (meters) xJQ (sec/m 3 ) D/Q (1/m") xJQ (sec/m 3 ) D/Q (1/m") N A 469 2.032E-6 1.168E-8 9.548E-6 3.680E-8 NNE B 475 1.792E-6 9.983E-9 1.004E-5 3.256E-8 NE c 400 2.710E-6 1.997E-8 1.386E-5 5.708E-8 ENE D 400 2.180E-6 1.734E-8 1.160E-5 4.855E-8 E E 400 1.949E-6 1.889E-8 1.169E-5 5.211 E-8 ESE F 400 1.650E-9 1.319E-8 1.280E-5 4.730E-8 SE G 400 I 1.646E-6 1.237E-8 1.312E-5 4.985E-8 SSE H 400 1.001E-6 9.230E-9 7.852E-6 3.238E-8 s J 433 1.272E-6 1.524E-8 7.058E-6 3.562E-8 SSW K 439 9.650E-7 1.357E-8 5.768E-6 3.290E-8 SW L 518 4.590E-7 6.081E-9 3.125E-6 1.625E-8 WSW M 671 2.311E-7 3.509E-9 1.393E-6 8.964E-9 w N 658 2.394E-7 3.381E-9 1.445E-6 8.440E-9 WNW p 893 1.427E-7 1.869E-9 8.817E-7 4.789E-9 NW Q 847 2.110E-7 2.671E-9 1.310E-6 6.607E-9 NNW R 725 3.740E-7 4.535E-9 2.038E-6 1.148E-8 Zion Site Meteorological Data 01/79 - 12/87 NOTE: Based on the formulas in Sections B.3 and B.4 of Appendix B. x/Q is used for beta skin and inhalation pathways. See Sections A.1.2, A.1.3 and A.1.4.2 of Appendix A. D/Q is used for produce and leafy vegetable pathways. Section A.1.4 of Appendix A. The mixed mode level release data are provided for reference purposes only. Routin.e dose calculations are performed using ground level data. Radius is the approximate distance from the midpoint between gaseous effluent release points to the location of the highest x/Q Q or D/Q at or beyond the unrestricted area boundary (UAB). Page 185 of 268

Revision 9 February 27, 2017 Table F-5a x/Q and D/Q Maxima at or Beyond the Restricted Area Boundary Downwind Site Radius Mixed Mode 1Vent) Release Ground Level Release 3 3 Direction Sector (meters) y/Q (sec/m ) D/Q (1/m") x!Q (sec/m ) D/Q (1/m") N A 375 3.015E-6 1.605E-8 1.420E-5 5.165E-8 NNE B 400 2.426E-6 1.278E-8 1.363E-5 4.230E-8 NE c 325 3.917E-6 2.653E-8 2.009E-5 7.781E-8 ENE D 200 7.441E-6 4.345E-8 4.027E-5 1.330E-7 E E 175 8.400E-6 5.512E-8 5.177E-5 1.719E-7 ESE F 175 7.025E-6 3.590E-8 5.670E-5 1.559E-7 SE G 175 7.002E-6 3.298E-8 5.811 E-5 1.644E-7 SSE H 200 3.362E-6 2.113E-8 2.730E-5 8.871E-8 s J 350 1.851E-6 2:054E-8 1.031E-5 4.906E-8 SSW K 375 1.270E-6 1.676E-8 7.631E-6 4.174E-8 SW L 475 5.307E-7 6.818E-9 3.626E-6 1.858E-8 WSW M 671 2.311E-7 3.509E-9 1.393E-6 8.964E..:9 w N 658 2.394E-7 3.381 E-9 1.445E-6 8.440E-9 WNW p 893 1.427E-7 1.869E-9 8.817E-7 4.789E-9 NW Q 847 2.11E-7 2.871E-9 1.310E-6* 6.607E-9 NNW R 250 2.79E-6 1.778E-8 1.316E-5 5.779E-8 Zion Site Meteorological Data 01/79 - 12/87 NOTE: Based on the formulas in Sections B.3 and B.4 of Appendix B. The mixed mode level release data are provided for reference purposes only. Routine dose calculations are performed using ground level data. Radius is the approximate distance from the midpoint between gaseous effluent release points to the location of the highest x/Q or D/Q at or beyond the restricted area boundary (RAB). Page 186 of 268

Revision 9 February 27, 2017 Table F-5b Maximum Offsite Gamma-xJQ Ground Vent Downwind Radius Site Sector Gamma-x/Q Gamma-x/Q Direction (meters) 3 3 (sec/m ) (sec/m ) N A 469 2.51E-06 8.16E-07 NNE B 475 2.51E-06 7.26E-07 NE c 400 3.33E-06 1.05E-06 ENE D 400 2.90E-06 8.87E-07 E E 400 2.97E-06 8.62E-07 ESE F 400 3.17E-06 7.84E-07 SE G 400 3.52E-06 8.35E-07 SSE H  : 400 2.13E-06 5.70E-07 s J  : 433 1.98E-06 6.29E-07 SSW K 439 1.78E-06 5.65E-07 SW L ' 518 1.05E-06 3.39E-07 WSW M 671 5.32E-07 2.17E-07 w N  : 658 5.42E-07 2.13E-07 WNW p 893 3.58E-07 1.41 E-07 NW Q 847 5.15E-07 2.00E-07 NNW R ' 725 7.59E-07 . 3.26E-07 Page 187 of 268

Revision 9 February 27, 2017 Table F-6 x/Q and D/Q at the Nearest Resident Locations within 5 miles Mixed Mode (Vent) Site Distance Ground Level Release Release Location Description Direction Sector yJQ DIQ xtQ D/Q miles meters m*2 3 m*2 sec/m;, sec/m NEAREST RESIDENCE N A 2.49 4000 5.00E-07 7.30E-10 5.60E-08 5.80E-11 NEAREST RESIDENCE NNE B 4.97 8000 2.20E-07 2.20E-10 4.20E-08 2.50E-11 NEAREST RESIDENCE NE c 4.97 8000 2.40E-07 3.10E-10 5.20E-08 6.40E-11 NEAREST RESIDENCE ENE D 4.97 8000 2.00E-07 2.80E-10 4.80E-08 7.10E-11 NEAREST RESIDENCE E E 4.97 8000 2.40E-07 4.30E-10 6.80E-08 1.40E-10 NEAREST RESIDENCE ESE F 4.97 8000 1.80E-07 3.10E-10 5.50E-08 1.00E-10 NEAREST RESIDENCE SE G 4.97 8000 1.50E-07 2.70E-10 5.20E-08 8.80E-11 NEAREST RESIDENCE SSE H 4.97 8000 1.10E-07 1.70E-10 3.50E-08 5.30E-11 NEAREST RESIDENCE s J 4.97 . 8000 1.10E-07 2.40E-10 4.20E-08 7.70E-11 NEAREST RESIDENCE SSW K 2.30 3700 3.20E-07 1.20E-09 9.30E-08 4.70E-10 NEAREST RESIDENCE SW L 1.86 3000 3.70E-07 1.20E-09 7.80E-08 3.80E-10

NEAREST RESIDENCE WSW M 1.24 2000 4.70E-07 1.50E-09 5.00E-08 4.20E-10 NEAREST RESIDENCE w N 0.68 1100 1.50E-06 3.70E-09 3.40E-08 5.30E-10 NEAREST RESIDENCE WNW p 1.24 2000 5.20E-07 1.40E-09 4.10E-08 2.20E-10 NEAREST RESIDENCE NW Q 1.24 2000 5.60E-07 1.50E-09 4.20E-08 2.30E-10 NEAREST RESIDENCE NNW R 1.49 2400 6.30E-07 1.90E-09 6.80E-08 4.10E-10 Page 188 of 268

Revision 9 February 27, 2017 Table F-6a x/Q and D/Q at the Nearest Cow Milk Locations within 5 miles Distance Ground Level Release Mixed Mode (Vent) Release Site Location xtQ D/Q xtQ D/Q Direction Sector miles meters Description sec/m 3 m*:l sec/m 3 m*:l COW MILK N A 4.97 8000 1.90E-07 2.10E-10 4.10E-08 1.90E-11 COW MILK NNE B 4.97 8000 2.20E-07 2.20E-10 4.20E-08 2.50E-11 COW MILK NE c 4.97 8000 2.40E-07 3.10E-10 5.20E-08 6.40E-11 COW MILK ENE D 4.97 8000 2.00E-07 2.80E-10 4.80E-08 7.10E-11 COW MILK E E 4.97 . 8000 2.40E-07 4.30E-10 6.80E-08 1.40E-10 COW MILK ESE F 4.97 8000 1.80E-07 3.10E-10 5.50E-08 1.00E-10 COW MILK SE G 4.97 8000 1.50E-07 2.70E-10 5.20E-08 8.80E-11 COW MILK SSE H 4.97 8000 1.10E-07 1.70E-10 3.50E-08 5.30E-11 COW MILK s J 4.97 8000 1.10E-07 2.40E-10 4.20E-08 7.70E-11 COW MILK SSW K 4.97 8000 1.00E-07. 3.10E-10 4.90E-08 1.40E-10 COW MILK SW L 4.97 ' 8000 8.50E-08 2.20E-10 3.90E-08 8.20E-11 COW MILK WSW M 4.97 . 8000 5.80E-08 1.30E-10 2.40E-08 5.00E-11 COW MILK w N 4.97 . 8000 6.90E-08 1.20E-10 .2.50E-08 3.40E-11 COW MILK WNW p 4.97 8000 6.60E-08 1.20E-10 2.60E-08 2.70E-11 COW MILK NW Q 4.97 8000 7.10E-08 1.30E-10 2.70E-08 2.90E-11 COW MILK NNW R 4.97 8000 1.10E-07 2.20E...:10 3.40E-08 5.70E-11 Page 189 of 268

Revision 9 February 27, 2017 Table F-6b xtQ and D/Q at the Nearest Cow Milk Locations within 5 miles Mixed Mode (Vent) Distance Ground Level Release Location Release Direction Site Sector Description miles meters xfQ D/Q x.IQ D/Q sec/m 3 m*2 sec/m 3 m*2 COW MEAT N A 4.97 8000 1.90E-07 2~ 10E-10 4.10E-08 1.90E-11 COW MEAT NNE B 4.97 8000 2.20E-07 2.20E-10 4.20E-08 2.50E-11 COW MEAT NE c 4.97 8000 2.40E-07 3.10E-10 5.20E-08 6.40E-11 COW MEAT ENE D 4.97 8000 2.00E-07 2.80E-10 4.80E-08 7.10E-11 COW MEAT E E 4.97 8000 2.40E-07 4.30E-10 6.80E-08 1.40E-10 COW MEAT ESE F 4.97 8000 1.80E-07 3.10E-10 5.50E-08 1.00E-10 COW MEAT SE G 4.97 8000 1.50E-07 2.70E-10 5.20E-08 8.80E-11 COW MEAT SSE H 4.97 8000 1.10E-07 1.70E-10 3.50E-08 5.30E-11 COW MEAT s J 4.97 8000 1.10E-07 2.40E-10 4.20E-08 7.70E-11 COW MEAT SSW K 4.97 8000 1.00E-07 3.10E-10 4.90E-08 1.40E-10 COW MEAT SW L 4.97 8000 , 8.50E-08 2.20E-10 3.90E-08 8.20E-11 COW MEAT WSW M 4.47 7200 '.6.70E-08 1.60E-10 2.70E-08 6.00E-11 COW MEAT w N 3.48 5600 1.10E-07 2.20E-10 3.30E-08 6.10E-11 COW MEAT WNW p 4.97 8000 6.60E-08 1.20E-10 2.60E-08' 2.70E-11 COW MEAT NW Q 4.97 8000  : 7.10E-08 1.30E-10 2.70E-08 2.90E-11 COW MEAT NNW R 4.97 8000 ' 1.10E-07 2.20E-10 '3.40E-08 5.70E-11 Page 190 of 268

Revision 9 February 27, 2017 Table F-7 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-85 Downwtnd Unrestricted Mt>ced Mode(Vent) .Release Ground Level Release Direction Area Bound Radius V VBAR Radtus G GBAR (meters) (meters) (mrad/yr)/(uCt/sec) (meters) (mrad/yr)/(uCt/sec) N 469. 469. 1.403E-05 1. 356E-05 469. 4.313E-05 4.t7tE-05 NNE 475. 475. 1.249E-05 t.207E-05 475. 4.315E-05 4.f73E-05 NE 400. 400. 1.803E-05 1.743E-05 400. 5.723E-05 5.534E-05 ENE 400. 400. 1.526E-05 1.476E-05 400. 4.984E-05 4.819E-05 E 400. 400. 1.482E-05 1.433E-05 400. 5.110£-05 4.941£-05 ESE 400. 400. t. 349E-05 t. 304E-05 400. 5.450E-05 5.270£-05 SE 400. 400. t.436E'-05 1.388E-05 400. 6.049£-05 5.849£-05 SSE 400. 400. 9.798E.-06 9.474E-06 400. 3.657E-05 3.536E-05 s 433. 433. 1.082E-05 1.046E.-05 . 433. 3.398E-05 3.286E-05 SSW 439. 439. 9.7t5E~06 9.394E-06 439. 3.053E-05 2.952E-OS SW 518. 518. 5.829E-06 5.636E-06 518. 1.80SE-OS 1. 74.&E-OS WSW 67t. 671. 3.737E-06 3.614E-06 671. 9.147E-06 8.845E-06 w 658. 658. 3.664E-06 3.543E-06 658. 9.329E-06 9.021E-06 WNW 893. 893. 2.425E"'06 2.345E-06 893. 6. f 58.E-06 5. 955E -06 NW 847. 847. 3 . 444 E*.:05 3. 330E -06 847. 8.861E-06 8.569E-06 NNW 725. 725. *s.601E-06 5.416E-06 725. t.305E-05 1.262E-05 Z ton Stte Meteorologtca,1 Data 1/79 - 12/87 Page 191 of 268

Revision 9 February 27, 2017 Table F-8 Site Specific Potable Water Dose Factors for Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 8.31E-01 8.31E-01 8.31E-01 8.31E-01 8.31E-01 8.31E-01 Na-24 2.36E+01 2.36E+01 2.36E+01 2.36E+01 2.36E+01 2.36E+01 2.36E+01 Cr-51 O.OOE+OO O.OOE+OO 3.69E-02 2.21E-02 8.13E-03 4.90E-02 9.28E+OO Mn-54 O.OOE+OO 6.34E+01 1.21E+01 O.OOE+OO 1.89E+01 O.OOE+OO 1.94E+02 Mn-56 O.OOE+O.O 1.60E+OO 2.83E-01 O.OOE+OO 2.03E+OO O.OOE+OO 5.09E+01 Fe-55 3.81 E+01 2.64E+01 6.14E+OO O.OOE+OO O.OOE+OO 1.47E+01 1.51E+01 Fe-59 6.02E+01 1.41 E+02 5.42E+01 O.OOE+OO O.OOE+OO 3.95E+01 4.72E+02 Co-58 O.OOE+OO 1.03E+01 2.32E+01 O.OOE+OO O.OOE+OO O.OOE+OO 2.09E+02 Co-60 O.OOE+OO 2.97E+01 6.55E+01 O.OOE+OO O.OOE+OO O.OOE+OO 5.58E+02 Ni-63 1.80E+03 1.25E+02 6.05E+01 O.OOE+OO O.OOE+OO O.OOE+OO 2.61E+01 Ni-65 7.32E+OO 9.51E-01 4.34E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.41E+01 Cu-64 O.OOE+OO 1.16E+OO 5.42E-01 O.OOE+OO 2.91E+OO O.OOE+OO 9.85E+01 Zn-65 6.71 E+01 2.14E+02 9.65E+01 O.OOE+OO 1.43E+02 O.OOE+OO 1.35E+02 Zn-69 1.43E-01 2.73E-01 1.90E-02 O.OOE+OO 1.78E-01 O.OOE+OO 4.11E-02 Br-83 O.OOE+OO O.OOE+OO 5.58E~01 O.OOE+OO O.OOE+OO O.OOE+OO 8.03E-01 Br-84 O.OOE+OO

• O.OOE+OO 7.23E-01 O.OOE+OO O.OOE+OO O.OOE+OO 5.67E-06 Br-85 O.OOE+OO O.OOE+OO 2.97E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.93E+02 1.36E+02 O.OOE+OO O.OOE+OO O.OOE+OO 5.77E+01 Rb-88 O.OOE.+00 8.39E-01 4.45E-01 O.OOE+OO . O.OOE+OO O.OOE+OO 1.16E-11 Rb-89 O.OOE+OO 5.56E-01 3.91E-01 O.OOE+OO O.OOE+OO O.OOE+OO 3.23E-14 Sr-89 4.27E+03 O.OOE+OO 1.23E+02 O.OOE+OO O.OOE+OO O.OOE+OO *6.85E+02 Sr-90 1.21 E+05 O.OOE+OO . 2.43E+03 O.OOE+OO O.OOE+OO
• O.OOE+OO .3.04E+03 Sr-91 7.86E+01 O.OOE+OO 3.18E+OO O.OOE+OO  : O.OOE+OO O.OOE+OO 3.74E+02 Sr-92 2.98E+01 O.OOE+OO 1.29E+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.91E+02 Y-90 1.33E-01 O.OOE+OO
• 3.58E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.41E+03 Y-91M 1.26E-03 O.OOE+OO , 4.88E-05 O.OOE+OO O.OOE+OO O.OOE+OO 3.70E-03 Y-91 1.96E+OO O.OOE+,00 5.23E-02 O.OOE+OO
• O.OOE+OO O.OOE+OO 1.08E+03 Y-92 1.17E-02 O.OOE~OO . 3.43E-04 O.OOE+O,O . O.OOE+OO O.OOE+OO 2.05E+02 Y-93 3.72E-02 O.OOE+OO 1.03E-03 O.OOE+OO . O.OOE+OO O.OOE+OO 1.18E+03 Zr-95 4.22E-01 1.35E.i01 : 9.15E-02' O.OOE+OO 2.12E-01 .. O.OOE+OO 4.29E+02 Zr-97 2.33E-02 4.70E~03  : 2.15E-03 O.OOE+OO 7.10E-03
• O.OOE+OO 1.46E+03 Nb-95 8.63E-02 4.80E.:02 2.58E-02 O.OOE+OO 4.74E-02 *O.OOE+OO 2.91E+02 Mo-99 O.OOE+OO 5.98E+01 1.14E+01 O.OOE+OO 1.35E+02 O.OOE+OO 1.39E+02 Tc-99M 3.43E-03 9.68E-03 1.23E-01 O.OOE+OO . 1.47E-01 4.74E-03 5.73E+OO Tc-101 3.52E-03 5.08E~03 ' 4.98E-02 O.OOE+OO 9.14E-02 2.59E-03 1.53E-14 Ru-103 2.57E+OO O.OOE.+00
• 1.11E.+OO O.OOE+OO 9.79E+OO O.OOE+OO 3.00E+02 Ru-105 2.14E-01 O.OOE+OO 8.43E-02 O.OOE+OO 2.76E+OO O.OOE+OO 1.31 E+02 Ru-106 3.81E+01 O.OOE+OO  : 4.83E+oo O.OOE+OO 7.36E+01 O.OOE+OO 2.47E+03 Ag-110M 2.22E+OO 2.05E+OO ' 1.226+00 O.OOE+OO . 4.04E+OO O.OOE+OO 8.38E+02 Te-125M 3.72E+01 1.35E+01
• 4.98E+OO 1.12E+01 1.51E+02 O.OOE+OO 1.48E+02 Page 192 of 268

Revision 9 February 27, 2017 Table F-8 (continued) Site Specific Potable Water Dose Factors for Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-127M 9.39E+01 3.36E+01 1.14E+01 2.40E+01 3.81E+02 O.OOE+OO 3.15E+02 Te-127 1.53E+OO 5.48E-01 3.30E-01 1.13E+OO 6.21E+OO O.OOE+OO 1.20E+02 Te-129M 1.60E+02 5.95E+01 2.52E+01 5.48E+01 6.66E+02 O.OOE+OO 8.03E+02 Te-129 4.36E-01 1.64E-01 1.06E-01 3.34E-01 1.83E+OO O.OOE+OO 3.29E-01 Te-131M 2.40E+01 1.17E+01 9.78E+OO 1.86E+01 1.19E+02 O.OOE+OO 1.17E+03 Te-131 2.73E-01 1.14E-01 8.63E-02 2.25E-01 1.20E+OO O.OOE+OO 3.87E-02 Te-132 3.50E+01 2.26E+01 2.12E+01 2.50E+01 2.18E+02 O.OOE+OO 1.07E+03 1-130 1.05E+01 3.09E+01 1.22E+01 2.62E+03 4.83E+01 O.OOE+OO , 2.66E+01 1-131 5.77E+01 8.25E+01 4.73E+01 2.70E+04 1.41E+02 O.OOE+OO 2.18E+Ot 1-132 2.82E+OO 7.53E+OO 2.64E+OO 2.64E+02 1.20E+01 O.OOE+OO 1.41E+OO 1-133 1.97E+01 3.43E+01 1.04E+01 5.03E+03 5.98E+01 O.OOE+OO 3.08E+01 1-134 1.47E+OO '3.99E+OO 1.43E+OO 6.92E+01 6.35E+OO O.OOE+OO 3.48E-03 1-135 6.14E+OO '1.61E+01 5.94E+OO 1.06E+03 2.58E+01 O.OOE+OO . 1.82E+01 Cs-134 8.63E+02 2:05E+03 1.68E+03 O.OOE+OO 6.64E+02 2.21E+02 3.59E+01 Cs-136 9.03E+01 3.56E+02 2.57E+02 O.OOE+OO 1.98E+02 2.72E+01 . 4.05E+01 Cs-137 1.11E+03 1.51E+03 9.90E+02 O.OOE+OO 5.13E+02 1.71E+02 : 2.93E+01 Cs-138 7.66E-01 1.51 E+OO 7.49E-01 O.OOE+OO 1.11E+OO 1.10E-01 ' 6.45E-06 Ba-139 1.35E+OO 9.58E-04 3.94E-02 O.OOE+OO 8.96E-04 5.44E-04 2.39E+OO Ba-140 2.82E+02  : 3.54E-01 1.84E+0.1 O.OOE+oo

• 1.20E-01 2.03E-01 5.80E+02 Ba-141 6.53E-01 4.94E-04 2.21E-02 O.OOE+OO. 4.59E-04 2.80E-04.: 3.08E-10 Ba-142 2.95E-01 3.04E-04 1.86E-02 O.OOE+OO 2.57E-04 1.72E-04 4.16E-19 La-140 3.47E-02 1.75E-02 4.62E-03  : O.OOE+OO O.OOE+OO O.OOE+OO 1.28E+03 La-142 1.78E-03
• 8.Q7E-04 2.01E-04 O.OOE+OO O.OOE+OO O.OOE+OO: 5.89E+OO Ce-141 1.30E-01 , 8,78E-02 9.96E-03 O.OOE+OO 4.08E-02 O.OOE+OO
• 3.36E+02 Ce-143 2.29E-02 *1.69E+01 1.87E-03
• O.OOE+OO 7.45E-03 O.OOE+OO
• 6.32E+02 Ce-144 6.77E+OO :2.83E+OO 3.63E-01 O.OOE+OO 1.68E+OO O.OOE+OO, 2.29E+03 Pr-143 1.28E-01 5.12E-02 6.32E-03 O,.OOE+OO 2.95E-02 O.OOE+OO 5.59E+02 Pr-144 4.17E'-04  : 1.73E-04 2.12E-05 O.OOE+OO 9.78E-05 O.OOE+OO 6.01 E-11 Nd-147 8.72E-02 1.01 E-01 6.03E-03 O.OOE+OO 5.89E-02 O.OOE+OO 4.84E+02 W-187 1.43E+OO '1.19E+OO *4.17E-01 o*.ooE+oo O.OOE+OO O.OOE+OO 3.91E+02 Np-239 1.65E-02 1,62E:.03 8.95E-04 O.OOE+OO 5.06E-03 O.OOE+OO 3.33E+02 Notes:

1) Units are mrem/hr per µCi/ml.

Page 193 of 268

Revision 9 February 27, 2017 Table F-Sa Site Specific Potable Water Dose Factors for Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 5.85E-01 5.85E-01 5.85E-01 5.85E-01 5.85E-01 5.85E-01 Na-24 2.23E+01 2.23E+01 2.23E+01 2.23E+01 2.23E+01 2.23E+01 2.23E+01 Cr-51 O.OOE+OO O.OOE+OO 3.49E-02 1.94E-02 7.65E-03 4.98E-02 5.86E+OO Mn-54 O.OOE+OO 5.72E+01 1.13E+01 O.OOE+OO 1.71E+01 O.OOE+OO 1.17E+02 Mn-56 O.OOE+OO 1.53E+OO 2.72E-01 O.OOE+OO 1.94E+OO O.OOE+OO 1.01 E+02 Fe-55 3.66E+01 2.60E+01 6.06E+OO O.OOE+OO O.OOE+OO 1.65E+01 1.12E+01 Fe-59 5.69E+01 1.33E+02 5.13E+01 O.OOE+OO O.OOE+OO 4.19E+01 3.14E+02 Co-58 O.OOE+OO 9.42E+OO 2.17E+01 O.OOE+OO O.OOE+OO . O.OOE+OO 1.30E+02 Co-60 . O.OOE+OO 2.72E+01 6.13E+01 O.OOE+OO O.OOE+OO O.OOE+OO 3.55E+02 Ni-63 1.72E+03 1.21 E+02 5.81E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.93E+01 Ni-65 7.26E+OO 9.27E-01 4.22E-01 O.OOE+OO O.OOE+OO O.OOE+OO 5.03E+01 Cu-64 O.OOE+OO 1.11E+OO 5.24E-01 O.OOE+OO 2.82E+OO O.OOE+OO 8.64E+01 Zn-65 5.58E+01 1.94E+02 9.04E+01 O.OOE+OO .1.24E+02

• O.OOE+OO 8.21E+01 Zn-69 1.42E-01 2.71E-01 1.90E-02 O.OOE+OO 1.77E-01 . O.OOE+OO 5.00E-01 Br-83 O.OOE+OO O.OOE+OO . 5.56E-01
• O.OOE+OO
• O.OOE+oo O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 7.00E-01 O.OOE+OO O.OOE+OO
• O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 2.96E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.89E+02 1.36E+02 O.OOE+OO O.OOE+OO: O.OOE+OO 4.27E+01 Rb-88 O.OOE+OO 8.. 26E-01 4.40E-01 O.OOE+OO
• O.OOE-+cOO: O.OOE+OO 7.07E-08 Rb-89 O.OOE+OO 5.33E-01 3.77E-01 O.OOE+OO O.OOE+OO: O.OOE+OO 8.17E-10 Sr-89 4.26E+03 O.OOE+OO 1.22E+02 O.OOE+OO. O.OOE+OO, O.OOE+OO 5,08E+02 Sr-90 9.88E+04 O.OOE+OO 1.98E+03 . O.OOE+OO O.OOE+OO
• O.OOE+OO 2.26E+03 Sr-91 7.82E+-01 O.OOE+OO 3.11E+OO *O.OOE+OO O.OOE+OO O.OOE+OO 3.55E+02 Sr-92 2.96E+Q1 O.OOE+OO 1.26E+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.53E+02 y.:90 1.33E-01 O.OOE+OO 3.58E-03 *o.OOE+OO, O.OOE+OO O.OOE+OO 1.09E+03 Y-91M 1.25E-03 O.OOE+OO 4.78E-0,5 : O.OOE+OO: O.OOE+OO O.OOE+OO 5.90E-02 Y-91 1.9$E+OO O.OOE+OO 5.22E-02 :O.OOE+OO O.OOE+OO O.OOE+OO 7.98E+02 Y-92 1.17E-02 O.OOE+OO 3.39E-04 O.OOE+OO O.OOE+OO O.OOE+OO 3.22E+02 Y-93 3.71E-02 O.OOE+OO 1.02E-03 *O.OOE+OO O.OOE+oo Q.OOE+OO 1.13E+03 Zr-95 3.99E-01 1.26E-01 8.66E-02 **O.OOE+OO 1.85E-01 b:OOE+OO 2.91E+02 Zr-97 2.30E-02 4.54E-03 2.09E-03 : O.OOE+OO 6.89E-03 o;ooE+oo 1.23E+03 Nb-95 7.97E-02 4.42E-.02 2.43E-02 0.00E+OO 4.28E-02 O.OOE+OO 1

1.89E+02 Mo-99 O.OOE+OO 5.8,4E+01 1.11E+01 O.OOE+OO 1.34E+02 O.OOE+OO 1.05E+02 Tc-99M 3.22E-03 8.97E-03 1.16E-01 .o.OOE+OO

• 1.34E-01 4.98E-03 5.89E+OO Tc-101 3.49E-03 4.96E-03 4.87E-02 O.OOE+OO 8.97E-02 3.02E-03 8.48E-10 Ru-103 2.47E+OO O.OOE+OO 1.06E+OO : O.OOE+OO . 8.71E+OO O.OOE+OO 2.06E+02 Ru-105 2.11E-01 O.OOE+OO 8.20E-02 ::O.OOE+OO 2.66E+OO O.OOE+OO 1.71E+02 Ru-106 3.8'0E+01 O.OOE+OO 4.79E+OO O.OOE+OO 7.33E+01 O.OOE+OO 1.82E+03 Ag-110M 1.99E+OQ 1.88E+OO 1,14E+OO ,O.OOE+OO 3.59E+OO O.OOE+OO 5.28E+02 Te-125M 3.71E+01 1.34E+01 4.96E+OO 1.04E+01 O.OOE+OO O.OOE+OO 1.09E+02 Page 194 of 268

Revision 9 February 27, 2017 Table F-Ba (continued) Site Specific Potable Water Dose Factors for Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-127M 9.37E+01 3.32E+01 1.11 E+01 2.23E+01 3.80E+02 O.OOE+OO 2.34E+02 Te-127 1.53E+OO 5.43E-01 3.29E-01 1.06E+OO 6.20E+OO O.OOE+OO 1.18E+02 Te-129M 1.58E+02 5.86E+01 2.50E+01 5.10E+01 6.61E+02 O.OOE+OO 5.93E+02 Te-129 4.34E-01 1.62E-01 1.06E-01 3.10E-01 1.82E+OO O.OOE+OO 2.37E+OO Te-131M 2.36E+01 1.13E+01 9.46E+OO 1.71E+01 1.18E+02 O.OOE+OO 9.10E+02 Te-131 2.70E-01 1.11 E-01 8.45E-02 . 2.08E-01 1.18E+OO O.OOE+OO 2.22E-02 Te-132 3.38E+01 2.14E+01 2.02E+01 2.26E+01 2.05E+02 O.OOE+OO 6.78E+02 1-130 9.98E+OO 2.89E+01 1.15E+01 *2.35E+03 4.45E+01 O.OOE+OO 2.22E+01 1-131 5.67E+01 7.94E+01 4.26E+01 2.32E+04 1.37E+02 O.OOE+OO 1.57E+01 1-132 2.70E+OO 7.07E+OO 2.54E+OO 2.38E+02 1.11E+01 O.OOE+OO 3.08E+OO 1-133 1.95E+01 3.30E+01 1.01E+01 4.61E+03 5.79E+01 O.OOE+OO 2.50E+01 1-134 1.41E+OO 3.75E+OO 1.35E+OO 6.25E+01 5.91E+OO O.OOE+OO 4.94E-02 1-135 5.91E+OO 1.52E+01 5.64E+OO 9.79E+02 2.40E+01 O.OOE+OO 1.69E+01 Cs-134 8.11E+02 1.91 E+03 8.86E+02 O.OOE+OO 6.07E+02 2.32E+02 2.37E+01 Cs-136 8.32E+01 3.28E+02 2.20E+02 O.OOE+OO 1.78E+02 2.81 E+01 2.64E+01 Cs-137 1.09E+03 1.44E+03 5.03E+02 O.OOE+OO 4.91E+02 1.91E+02 2.05E+01 Cs-138 7.52E-01 1.44E+OO 7.22E-01 O.OOE+OO 1.07E+OO 1.24E-01 6.55E-04 Ba-139 1.35E+OO 9.48E-04 3.92E-02 O.OOE+OO: 8.93E-04 6.53E-04 1.20E+01 Ba-140 2.75E+02 3.37E-01 1.77E+01 O.OOE+OO I 1.14E-01 2.27E-01 4.24E+02 Ba-141 6.50E-01 4.85E-04 2.17E-02 O.OOE+OO 4.51 E-04 3.32E-04 1.39E-06 Ba-142 2.90E-01 2.90E-04 1.78E-02 O.OOE+OO 2.45E-04 1.93E-04 8.90E-13 La-140 3.37E-02 1.66E-02 4.41E-03 O.OOE+OO O.OOE+OO O.OOE+OO 9.52E+02 La-142 1.73E-03 7.70E-04 1.92E-04 O.OOE+OO O.OOE+OO O.OOE+OO 2.34E+01 Ce-141 1.29E-01 8.60E-02 9.88E-03 O.OOE+OO 4.05E-02 O.OOE+OO 2.46E+02 Ce-143 2.28E-02 1.66E+01 1.85E-03 O.OOE+OO 7.43E-03 O.OOE+OO 4.98E+02 Ce-144 6.74E+OO 2.79E+OO 3.62E-01 O.OOE+OO 1.67E+OO O.OOE+OO 1.70E+03 Pr-143 1.27E-01 5.07E-02 6.32E-03 O.OOE+OO 2.95E-02 O.OOE+OO 4.18E+02 Pr-144 4.17E-04 1.71 E-04 2.11 E-05 O.OOE+OO 9.79E-05 O.OOE+OO 4.59E-07 Nd-147 9.09E-02 9.88E-02 5.92E-03 O.OOE+OO 5.80E-02 O.OOE+OO 3.57E+02 W-187 1.41 E+OO 1.15E+OO 4.04E-01 O.OOE+OO O.OOE+OO O.OOE+OO 3.12E+02 Np-239 1.71 E-02 1.61E-03 8.93E-04 O.OOE+OO 5.05E-03 O.OOE+OO 2.59E+02 Notes:

1) Units are mrem/hr per µCi/ml.

Page 195 of 268 l

Revision 9 February 27, 2017 Table F-Bb Site Specific Potable Water Dose Factors for Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.12E+OO 1.12E+OO 1.12E+OO 1.12E+OO 1.12E+OO 1.12E+OO Na-24 5.62E+01 5.62E+01 5.62E+01 5.62E+01 5.62E+01 5.62E+01 5.62E+01 Cr-51 O.OOE+OO O.OOE+OO 8.62E-02 4.79E-02 1.31E-02 8.74E-02 4.57E+OO Mn-54 O.OOE+OO 1.04E+02 2.76E+01 O.OOE+OO 2.91E+01 O.OOE+OO 8.70E+01 Mn-56 O.OOE+OO 3.24E+OO 7.31E-01 O.OOE+OO 3.91E+OO O.OOE+OO 4.69E+02 Fe-55 1.11E+02 5.91E+01 1.83E+01 O.OOE+OO O.OOE+OO 3.34E+01 1.09E+01 Fe-59 1.60E+02 2.59E+02 1.29E+02 O.OOE+OO O.OOE+OO 7.50E+01 2.69E+02 Co-58 O.OOE+OO :1.74E+01 5.34E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E+02 Co-60 O.OOE+OO 5.13E+01 1.51E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.84E+02 Ni-63 5.21E+03 2.79E+02 1.77E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.88E+01 Ni-65 2,.15E+01 2.03E+OO 1.18E+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.48E+02 Cu-64 O.OOE+OO ,2.37E+OO 1.43E+OO O.OOE+OO 5.74E+OO O.OOE+OO 1.11E+02 Zn-65 1.33E+02 3.54E+02 2.20E+02 O.OOE+OO 2.23E+02 *0.00E+OO 6.21 E+01 Zn-69 4.24E-01 6.13E-01 5.67E-02 O.OOE+OO 3.72E-01 .O.OOE+OO 3.87E+01 Br-83 O.OOE+OO O.OOE+OO 1.66E+OO O.OOE+OO O.OOE+OO  :*O.OOE+OO O.OOE+OO Br-84 O.OOE+OO :o.OOE+OO *1.92E+OO O.OOE+OO. O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO '0.00E+Ob 8.84E-02 O.OOE+OO O.OOE+OO 'O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO '6.49E+02 3.99E+02 O.OOE+OO O.OOE+OO '.0.00E+OO 4.18E+01 Rb-88 O.OOE+OO *1.84E+OO 1.28E+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.03E-02 Rb-89 O.OOE+OO 11.13E+OO 1.01E+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.88E-03 Sr-89 1.28E+04 O.OOE+OO 3.65E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.95E+02 Sr-90 2.48E+05 O.OOE+OO 4.99E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.22E+03 Sr-91 2.33E+02 O.OOE+OO 8.78E+OO O.OOE+OO O.OOE+OO ,;O.OOE+OO 5.14E+02 Sr-92 8.75E+01 O.OOE+OO *3.51E+OO O.OOE+OO O.OOE+OO  :.O.OOE+OO 1.66E+03 Y-90 3.98E-01 *O.OOE-+'00 1.07E-02 O.OOE+OO O.OOE+OO ,jO.OOE+OO 1.13E+03 Y-91M 3.70E'."0;3 O.OOE+OO 1.35E-04 O.OOE+OO O.OOE+OO !O.OOE+OO 7.25E+OO Y-91 5.83E+OO 'O.OOE+OO 1.56E-01 O.OOE+OO :o.OOE+OO O.OOE+OO 7.77E+02 Y-92 3.49E;.;02 O.OOE+OO 9.98E-04

• O.OOE+OO O.OOE+OO ,O.OOE+OO 1.01 E+03 Y-93 1.10E-01 *o.OOE+OO 3.03E-03
• O.OOE+OO O.OOE+OO "O.OOE+OO 1.65E+03 Zr-95 1.12E+OO 2.47E-01 2.20E-01 O.OOE+OO 3.54E-01 *o.OOE+OO 2.58E+02 Zr-97 6.77E-02 9.79E-03 5.78E-03 O.OOE+OO 1.41E-04 *O.OOE+OO 1.48E+03 Nb-95 2.18E-O~ : 8.49E-:02 6.07E-02 O.OOE+OO 7.97E-02 *1 0.00E+OO 1.57E+02 Mo-99 O.OOE+OO :1.29E+02 3.19E+01 O.OOE+OO 2.75E+02 O.OOE+OO 1.07E+02 Tc-99M 8.94E.:-03 1.75E~02 2.91E~01 O.OOE+OO 2.55E-01 8.91E-03 9.98E+OO Tc-101 1.04E-02 ' 1.09E~02 1.38E-01 O.OOE+OO 1.85E-01 5.74E-03 3.45E-02 Ru-103 7.08E+OO O.OOE400 2.72E+OO O.OOE+OO 1.78E+01 ,O.OOE+OO 1'.83E+02 Ru-105 6.25E-01 O.OOEtOO 2.27E-01 O.OOE+OO 5.49E+OO O.OOE+OO 4.08E+02 Ru-106 1.13E+02 :O.OOE+OO 1.41E+01 O.OOE+OO 1.53E+02 O.OOE+OO 1.76E+03 Ag-110M 5.22E+.OO 3.53E+oo 2.82E+OO *o.OOE-+'00 6.57E+OO :O.OOE+OO 4.20E+02 Te-125M 1.10E+02 :2.99E+01 1:47E+01 3.10E+01 O.OOE+OO O.OOE+OO 1.07E+02 Page 196 of 268

Revision 9 February 27, 2017 Table F-Bb (continued) Site Specific Potable Water Dose Factors for Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-127M 2.80E+02 7.54E+01 3.32E+01 6.70E+01 7.98E+02 O.OOE+OO 2.27E+02 Te-127 4.56E+OO 1.23E+OO 9.79E-01 3.16E+OO 1.30E+01 O.OOE+OO 1.78E+02 Te-129M 4.72E+02 1.32E+02 7.33E+01 1.52E+02 1.39E+03 O.OOE+OO 5.76E+02 Te-129 1.30E+OO 3.62E-01 3.08E-01 9.26E-01 3.80E+OO O.OOE+OO 8.08E+01 Te-131 M 6.98E+01 2.41E+01 2.57E+01 4.96E+01 2.34E+02 O.OOE+OO 9.79E+02 Te-131 8.04E-01 2.45E-01 2.39E-01 6.15E-01 2.43E+OO O.OOE+OO 4.22E+OO Te-132 9.79E+01 4.33E+01 5.23E+01 6.31 E+01 4.02E+02 O.OOE+OO 4.36E+02 1-130 2.83E+01 5.72E+01 2.95E+01 6.30E+03 8.55E+01 O.OOE+OO 2.67E+01 1-131 1.67E+02 1.68E+02 9.53E+01 5.54E+04 2.75E+02 O.OOE+OO 1.49E+01 1-132 7.75E+OO 1.42E+01 6.55E+Od

• 6.61E+02 2.18E+01 O.OOE+OO 1.68E+01 1-133 5.74E+01 7.09E+01 2.68E+01 1.32E+04 1.18E+02 O.OOE+OO 2.86E+01 1-134 4:06E+OO 7.54E+OO 3.47E+OO 1.73E+02 1.15E+01 O.OOE+OO 5.00E+OO 1-135 1.70E+01 3.05E+01 :1.44E+01 2.70E+03 4.68E+01
• O.OOE+OO 2.33E+01 Cs-134 2.27E+03 3.72E+03 .7.85E+02 O.OOE+OO 1.15E+03 4.14E+02 2.01E+01 Cs-136 2.28E+02 6.26E+02 4.05E+02 O.OOE+OO 3.33E+02 4.97E+01 2.20E+01 Cs-137 3.17E+03 3.03E+03 4.48E+02 O.OOE+OO 9.88E+02. 3.56E+02 1.90E+01 Cs-138 2.21E+OO 3.07E+OO . 1.95E+OO *o.OOE+OO 2.16E+OO 2.33E701 1.41 E+OO Ba-139 4.01E+OO 2.14E-03 1.16E-01 . O.OOE+OO 1.87E-03 1.26E-03 .2.32E+02 Ba-140 8.05E+02 7.05E-01 4.70E+01 O.OOE+OO 2.30E-01 4.21E-01 4.08E+02 Ba-141 1.94E+OO 1.09E-03 6.31E-02 O.OOE+OO 9.39E-04 6.38E-03' 1.10E+OO Ba-142 8.47E-01 6.10E-04 4.73E-02 O.OOE+OO 4.93E-04 3.59E-04 1.10E-02 La-140 9.79E-02 3.42E-02 1.15E-02
• O.OOE+OO O.OOE+OO O.OOE+OO 9.53E+02 La-142 5.08E-03 1.62E-03. 5.07E-04 .O.OOE+OO O.OOE+OO O.OOE+OO
• 3.21E+02 Ce'-141 3.85E-01 1.92E-01 2.85E-02 , O.OOE+OO 8.41E-02 O.OOE+OO 2.39E+02 Ce-14,3 6.77E-02 3.67E+01' 5.32E-03 ** O.OOE+OO 1.54E-02
• O.OOE+OO *5.38E+02 Ce-144 2.02E+01 6.32E+OO. 1.08E+OO O.OOE+OO 3.50E+OO O.OOE+OO 1.65E+03 Pr-143 3.81E-01 1.14E-01 1.89E-02 O.OOE+OO 6.19E-02 O.OOE+OO 4.11E+02 Pr-144 1.25E-03 3.87E-04 6.29E-05 O.OOE+OO 2.04E-04 O.OOE+OO 8.32E.'..01 Nd-147 2.70E-01 2.19E-01 1.70E~02 . O.OOE+OO 1.20E-01 O.OOE+OO 3.47E+02 W-187 4.16E+OO 2.466+00 1.10E+OO O.OOE+OO
• O.OOE+OO O.OOE+OO 3.46E+02 Np-2~9 5.09E-02 3.65E-03 2.57E-03 O.OOE+OO 1.06E-02 O.OOE+OO 2.70E+02 Notes:

1) Units are mrem/hr per µCi/ml.

Page 197 of 268

Revision 9 February 27, 2017 Table F-Sc Site Specific Potable Water Dose Factors for Infant Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.10E+OO 1.10E+OO 1.10E+OO 1.10E+OO 1.10E+OO 1.10E+OO Na-24 6.33E+01 6.33E+01 6.33E+01 6.33E+01 6.33E+01 6.33E+01 6.33E+01 Cr-51 O.OOE+OO O.OOE+OO 8.84E-02 5.77E-02 1.26E-02 1.12E-01 2.58E+OO Mn-54 O.OOE+OO 1.25E+02 2.83E+01 O.OOE+OO 2.77E+01 O.OOE+OO 4.58E+01 Mn-56 O.OOE+OO 5.13E+OO 8.84E-01 O.OOE+OO 4.41E+OO O.OOE+OO 4.66E+02 Fe-55 8.72E+01 5.63E+01 1.50E+01 O.OOE+OO O.OOE+OO 2.75E+01 7.15E+OO Fe-59 1.93E+02 3.37E+02 1.33E+02 O.OOE+OO O.OOE+OO 9.97E+01 1.61 E+02 Co-58 O.OOE+OO 2.26E+01 5.63E+01 O.OOE+OO O.OOE+OO . O.OOE+OO 5.62E+01 Co-60 O.OOE+OO 6.77E+01 1.60E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.61 E+02 Ni-63 3.98E+03 2.46E+02 1.38E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.22E+01 Ni-65 2.95E+01 3.34E+OO 1.52E+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.54E+02 Cu-64 O.OOE+OO 3.82E+OO 1.77E+OO O.OOE+OO 6.46E+OO O.OOE+OO 7.84E+01 Zn-65 1.15E+02 3.96E+02 1.82E+02 O.OOE+OO 1.92E+02 O.OOE+OO 3.34E+02 Zn-69 5.85E-01 1.05E+OO 7.84E-02 O.OOE+OO 4.38E-01 O.OOE+OO 8.59E+01 Br-83 O.OOE+OO O.OOE+OO 2.28E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 2.40E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 1.22E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.07E+03 5.27E+02 O.OOE+OO

• O.OOE+OO .. O.OOE+OO 2.73E+01 Rb-88 O.OOE.+00 3.12E+OO 1.71E+OO O.OOE+OO O.OOE+OO : O.OOE+OO 3.04E+OO Rb-89 O.OOE+OO 1.79E+OO 1.24E+OO O.OOE+OO O.OOE+OO . O.OOE+OO 6.11 E-01 Sr-89 1.57E+04 O.OOE+OO 4.51E+02 O.OOE+OO O.OOE+OO < O.OOE+OO 3.24E+02 Sr-90 1.77E+o5 O.OOE+OO 3.60E+03 O.OOE+OO O.OOE+OO *. O.OOE+OO . 1.45E+03 Sr-91 3.14E+02 O.OOE+OO 1.13E+01 *O,OOE+OO O.OOE+OO "O.OOE+OO 3.71E+02 Sr-92 1.20E+02 O.OOE+OO 4.47E+OO O:OOE+OO .O.OOE+OO *. O.OOE+OO 1.30E+03 Y-90 5.45E-01 O.OOE+OO 1.46E-02 *O:OOE+OO O.OOE+OO *1 O.OOE+OO 7.52E+02 Y-91M 5.0BE-03 O.OOE+OO 1.73E-04 *o.OOE+OO O.OOE+OO O.OOE+OO 1.69E+01 Y-91 7.09E.+OO O.OOE+OO 1.89E-01 *O.OOE+OO O.OOE+OO , O.OOE+OO 5.08E+02 Y-92 4.80E-02 O.OOE+OO 1.35E-03 :o.OOE+OO O.OOE+OO O.OOE+OO 9.15E+02 Y-93 1.52E-01 O.OOE+QO 4.15E-03 O.OOE+OO 'O.OOE+OO
• O.OOE+OO 1.20E+03 Zr-95 1.29E+OO 3.15E-01 2.23E-01 O.OOE+OO 3.39E-01 . O.OOE+OO 1.57E+02 Zr-97 9.28E-02 1.59E-02 7.27E-03 'O.OOE+OO . 1.61E-02
• O.OOE+OO 1.02E+03 Nb-95 2.63E-01 1.08E-O~ 6.27E-02 O.OOE+OO 7.77E-02 O.OOE+OO 9.15E+01 Mo-99 O.OOE+OO 2.13E+02 4.16E+01 O.OOE+OO . 3.19E+02 O.OOE+OO 7.02E+01 Tc-99M 1.20E-02 2.48E-02 3.20E-01 , O.OOE+OO 2.67E-01 1.30E-02 7.21E+OO Tc-101 1.42E-02 1.79E-O~ 1.77E-01 'O.OOE+OO . 2.13E-01 9.78E-03 3.05E+OO Ru-103 9.28E+OO O.OOE+OO . 3.10E+OO . O.OOE+OO 1.93E+01 O.OOE+OO 1.13E+02 Ru-105 8.53E-01 O.OOE+OO 2.87E-01 O.OOE+OO 6.27E+OO O.OOE+OO 3.39E+02 Ru-106 1.51E+02 O.OOE+OO 1.89E+01 O.OOE+OO 1.79E+02 O.OOE+O.O 1.15E+03 Ag-110M 6.24E+OO 4.56E+OO 3.02E+OO *O.OOE+OO 6.52E+OO O.OOE+OO 2.36E+02 Te-125M 1.46E+02 4.88E+01 1.98E+01 ,4.92E+01 O.OOE+OO O.OOE+OO 6.96E+01 Page 198 of 268

Revision 9 February 27, 2017 Table F-Bc (continued) Site Specific Potable Water Dose Factors for Infant Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-127M 3.67E+02 1.22E+02 4.44E+01 1.06E+02 9.03E+02 O.OOE+OO 1.48E+02 Te-127 6.27E+OO 2.10E+OO 1.35E+OO 5.10E+OO 1.53E+01 O.OOE+OO 1.32E+02 Te-129M 6.27E+02 2.15E+02 9.66E+01 2.41E+02 1.57E+03 O.OOE+OO 3.74E+02 Te-129 1.78E+OO 6.14E-01 4.16E-01 1.49E+OO 4.43E+OO O.OOE+OO 1.42E+02 Te-131M 9.53E+01 3.84E+01 3.17E+01 7.77E+01 2.64E+02 O.OOE+OO 6.46E+02 Te-131 1.10E+OO 4.08E-01 3.10E-01 9.84E-01 2.82E+OO O.OOE+OO 4.46E+01 Te-132 1.30E+02 6.46E+01 6.03E+01 9.53E+01 4.04E+02 O.OOE+OO 2.39E+02 1-130 3.76E+01 8.28E+01 3.32E+01 9.28E+03 9.09E+01 O.OOE+OO 1.77E+01 1-131 2.25E+02 2.65E+02 1.17E+02 8.72E+04 3.10E+02 O.OOE+OO 9.47E+OO 1-132 1.04E+01 2.1~E+01 7.52E+OO 9.91E+02 2.36E+01 O.OOE+OO 1.71E+01 1-133 7.84E+01 1.14E+02 3.34E+01 2.08E+04 1.34E+02 O.OOE+OO 1.93E+01 1-134 5.45E+OO 1.12E+01 3.97E+OO 2.60E+02 1.25E+01 O.OOE+OO 1.15E+01 1-135 2.28E+01 4.54E+01 1.66E+01 4.07E+03 5.06E+01 O.OOE+OO 1.64E+01 Cs~134 2.36E+03 4.41E+03 4.45E+02 O.OOE+OO 1.13E+03 4.65E+02 1.20E+01 Cs-136 2.88E+02 8.46E+02 3.16E+02 O.OOE+OO 3.37E+02 6.90E+01 1.29E+01 cs~137 3.27E+03 3.83E+03 2.71E+02

• O.OOE+OO 1.03E+03 4.16E+02 1.20E+01 Cs-138 3.02E+OO 4.90E+OO 2.38E+OO O.OOE+OO 2.45E+OO 3.82E-01 7.84E+OO Ba-139 5.52E+OO 3.66E-03 1.60E-01 *O.OOE+OO 2.20E-03 2.22E-,03 3.50E+02 Ba-140 1.07E+03 1.07E+OO 5.52E+01 O.OOE+OO 2.55E-01 *.6.58E..:01 2.63E+02 Ba-141 2.66E+OO 1.82E-03 8.40E-02 O.OOE+OO 1.10E-03 1.11 E-03 3.25E+01 Ba-142 1.15E+OO ' 9.596-04 5.68E-02 O.OOE+OO 5.52E-04 5.81E-04 4.76E+OO La-140 1.32E-01  : 15.22E-02 1.34E-02 O.OOE+OO O.OOE+OO O.OOE+OO 6.13E+02 La.:142 6.90E-03 2.536-03 6.06E-04 O.OOE+OO O.OOE+OO
• O.OOE+OO 4.30E+02 Ce-141 4.93E-01 3.01E-01 3.54E-02 O;OOE+OO 9.28E-02 O.OOE+OO 1.55E+02 Ce-143 9.28E-02 6.16E+01 7.02E-03 O.OOE+OO 1.79E-02 O.OOE+OO 3.59E+02 Ce-144 1.87E+01
• 7.65E+OO 1.05E+OO O.OOE+OO
• 3.09E+OO O.OOE+OO 1.07E+03 Pr-143 5.10E-01  : 1.91 E-01 2.53E-02 O.OOE+OO 7.09E-02 O.OOE+OO 2.69E+02 Pr-.144 1.72E-03 6.65E-04 8.65E-05 O.OOE+OO 2.41E-04 O.OOE+OO 3.09E+01 Nd-147 3.47E-01  : 3.56E-01 2:18E-02 O.OOE+OO 1.37E-01 :o.OOE+OO 2.26E+02 W-187 5.66E+OO  : 3.94E+OO 1.36E+OO O.OOE+OO O.OOE+OO , O.OOE+OO 2.31E+02 Np-239 6.96E-02
• 6.23E-03 3.52E-03 O.OOE+OO 1.24E-02 *O.OOE+OO 1.80E+02 Notes:

1) Units are mrem/hr per µCi/ml.

Page 199 of 268

Revision 9 February 27, 2017 Table F-9 Site Specific Fish Ingestion Dose Factors for Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.29E-01 1.29E-01 1.29E-01 1.29E-01 1.29E-01 1.29E-01 Na-24 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 Cr-51 O.OOE+OO O.OOE+OO 1.27E+OO 7.61E-01 2.81E-01 1.69E+OO 3.20E+02 Mn-54 O.OOE+OO 4.38E+03 8.35E+02 O.OOE+OO 1.30E+03 O.OOE+OO 1.34E+04 Mn-56 O.OOE+OO 1.10E+02 1.95E+01 O.OOE+OO 1.40E+02 O.OOE+OO 3.51E+03 Fe-55 6.58E+02 4.55E+02 1.06E+02 O.OOE+OO O.OOE+OO 2.54E+02 2.61E+02 Fe-59 1.04E+03 2.44E+03 9.36E+02 O.OOE+OO O.OOE+OO 6.82E+02 8.14E+03 Co-58 O.OOE+OO 8.92E+01 2.00E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.81E+03 Co-60 O.OOE+OO 2.56E+02 5.65E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.81E+03 Ni-63 3.11E+04 2.16E+03 1.04E+03 O.OOE+OO O.OOE+OO O.OOE+OO 4.50E+02 Ni-65 1.26E+02 1.64E+01 7.49E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.17E+02 Cu-64 O.OOE+OO 9.97E+OO 4.68E+OO O.OOE+OO 2.51E+01 O.OOE+OO 8.50E+02 Zn-65 2.32E+04 7.37E+04 3.33E+04 O.OOE+OO 4.93E+04 O.OOE+OO 4.64E+04 Zn-69 4.93E+01 9.43E+01 6.56E+OO O.OOE+OO 6.13E+01 O.OOE+OO 1.42E+01 Br-83 O.OOE+OO O.OOE+OO 4.04E+01 O.OOE+OO O.OOE+OO O.OOE+OO 5.82E+01 Br-84 O.OOE+OO O.OOE+OO 5.24E+01 O.OOE+OO O.OOE+OO O.OOE+OO 4.11E-04 Br-85 O.OOE+OO O.OOE+OO 2.15E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.01E+05 4.71E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.99E+04 Rb-88 O.OOE+OO 2.90E+02 1.54E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.00E-09 Kb-89 O.OOE:i-oo 1.92E+02 1.35E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.12E-11 Sr-89 2.21E+04 O.OOE+OO 6.35E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.55E+03 Sr-90 6.26E+05 O.OOE+OO 1.26E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.57E+04 Sr-91 4.07E+02 O.OOE+OO 1.64E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.94E+03 Sr-92 1.54E+02 O.OOE+OO 6.68E+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.06E+03 Y-90 5.76E-01 O.OOE+OO 1.54E".'02 O.OOE+OO O.OOE+OO O.OOE+OO 6.10E+03 Y-91M 5.44E-03 O.OOE+OO 2.11E-04

• O.OOE+OO O.OOE+OO O.OOE+OO 1.60E-02 Y-91 8.44E+OO O.OOE+OO 2.26E-01 O.OOE+OO O.OOE+OO O.OOE+OO 4.64E+03 Y-92 5.06E-02 O.OOE+OO 1.48E-03 O.OOE+OO O.OOE+OO O.OOE+OO 8.86E+02 Y-93 1.60E-01 O.OOE+OO 4.43E-03 O.OOE+OO O.OOE+OO O.OOE+OO 5.09E+03 Zr-95 2.40E-01 7.70E-02 5.21E-02 O.OOE+OO 1.21 E-01 O.OOE+OO 2.44E+02 Zr-97 1.33E-02 2.68E-03 1.22E-03 O.OOE+OO 4.04E-03 O.OOE+OO 8.30E+02 Nb-95 4.47E+02 2.48E+02 1.34E+02 O.OOE+OO 2.46E+02 O.OOE+OO 1.51E+06 Mo-99 O.OOE+OO 1.03E+02 1.96E+01 O.OOE+OO 2.34E+02 O.OOE+OO 2.39E+02 Tc-99M 8.87E-03 2.51E-02 3.19E-01 O.OOE+OO 3.81E-01 1.23E-02 1.48E+01 Tc-101 9.12E-03 1.31E-02 1.29E-01 O.OOE+OO 2.37E-01 6.72E-03 3.95E-14 Ru-103 4.43E+OO O.OOE+OO 1.91 E+OO O.OOE+OO 1.69E+01 O.OOE+OO 5.17E+02 Ru-105 3.69E-01 O.OOE+OO 1.46E-01 O.OOE+OO 4.76E+OO O.OOE+OO 2.26E+02 Ru-106 6.58E+01 O.OOE+OO 8.33E+OO O.OOE+OO 1.27E+02 O.OOE+OO 4.26E+03 Ag-110M 8.81E-01 8.15E-01 4.84E-01 O.OOE+OO 1.60E+OO O.OOE+OO 3.33E+02 Te-125M 2.57E+03 9.30E+02 3.44E+02 7.72E+02 1.04E+04 O.OOE+OO 1.02E+04 Page 200 of 268

Revision 9 February 27, 2017 Table F-9 (continued) Site Specific Fish Ingestion Dose Factors for Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-127M 6.48E+03 2.32E+03 7.90E+02 1.66E+03 2.63E+04 O.OOE+OO 2.17E+04 Te-127 1.05E+02 3.78E+01 2.28E+01 7.80E+01 4.29E+02 O.OOE+OO 8.31E+03 Te-129M 1.10E+04 4.11E+03 1.74E+03 3.78E+03 4.60E+04 O.OOE+OO 5.54E+04 Te-129 3.01E+01 1.13E+01 7.33E+OO 2.31 E+01 1.26E+02 O.OOE+OO 2.27E+01 Te-131M 1.66E+03 8.10E+02 6.75E+02 1.28E+03 8.21E+03 O.OOE+OO 8.04E+04 Te-131 1.89E+01 7.88E+OO 5.96E+OO 1.55E+01 8.26E+01 O.OOE+OO 2.67E+OO Te-132 2.41E+03 1.56E+03 1.47E+03 1.72E+03 1.50E+04 O.OOE+OO 7.38E+04 1-130 2.71E+01 8.01E+01 3.16E+01 6.79E+03 1.25E+02 O.OOE+OO 6.89E+01 1-131 1.49E+02 2.14E+02 1.22E+02 7.00E+04 3.66E+02 O.OOE+OO 5.64E+01 1-132 7.29E+OO 1.95E+01 6.82E+OO 6.82E+02 3.11E+01 O.OOE+OO 3.66E+OO 1-133 5.10Et01 8.87E+01 2.70E+01 1.30E+04 1.55E+02 O.OOE+OO 7.97E+01 1-134 3.81E+OO 1.03E+01 3.70E+OO .1.79E+02 1.64E+01 O.OOE+OO 9.01E-03 1-135 1.59E+01 4.17E+01 1.54E+01 2.75E+03 6.68E+01 O.OOE+OO 4.70E+01 Cs-134 2.98E+05 7.09E+05 5.79E+05 O.OOE+OO 2.29E+05 7.61E+04 1.24E+04 Cs-136 3.12E+04 1.23E+05 8.86E+04 .O.OOE+OO 6.85E+04 9.38E+03 1.40E+04 Cs-137 3.82E+05 5.22E+05 3.42E+05 O.OOE+OO 1.77E+05 5.89E+04 1.01 E+04 Cs-138 2.64E+02 5.22E+02 2.59E+02 O.OOE+OO 3.84E+02 3.79E+01 2.23E-03 Ba-139 9.29E-01 6.62E-04 *2.72E-02 O.OOE+OO 6.19E-04 3.75E-04 1.65E+OO Ba-140 1.94E+02 2.44E-01 1.27E+01 O.OOE+OO 8.30E-02 1.40E-01 4.00E+02 Ba-141 4.51E-01 3.41E-04 1.52E-02 O.OOE+oo 3.17E-04 1.93E-04 2.13E-10 Ba-142 2.04E-01 2.10E-04 1.28E-02 O.OOE+OO 1.77E-04 1.19E-04 2.87E-19 La-140 1.50E-01 7.54E-02 1.99E-02 o:ooE+oo . O.OOE+OO O.OOE+OO 5.54E+03 La-142 7.66E-03 3.48E-03 8.68E-04 O:OOE+OO O.OOE+OO O.OOE+OO 2.54E+01 Ce-141 2.24~-02 1.52E-02 1.72E-03 O.OOE+OO 7.04E-03 O.OOE+OO 5'.79E+01 Ce-143 3.95E-03 2.92E+OO 3.23E-04 O:OOE+OO 1.29E-03 O.OOE+OO 1.09E+02 Ce-144 1.17E:+-00 4.88E-01 6.27E-02 O.OOE+OO 2.90E-01 O.OOE+OO 3.95E+02 Pr-143 5.51E-01 2.21E-01 2.73E-02 O.OOE+OO 1.27E-01 O.OOE+OO 2.41E+03 Pr-144 1.80E-03 7.48E-04 9.16E-05 O:OOE+OO 4.22E-04 O.OOE+OO 2.59E-10 Nd-147 3.76E-01 4.35E-01 2.60E-02 O.OOE+OO 2.54E-01 O.OOE+OO 2.09E+03 W-187 2.96E+02 2.47E+02 8.65E+01 O.OOE+oo O.OOE+OO O.OOE+OO 8.10E+04 Np-239 2.85E-02 2.80E-03 1.54E-03 0.00E+OO 8.74E-03 O.OOE+OO 5.75E+02 Page 201 of 268

Revision 9 February 27, 2017 Table F-9a Site Specific Fish Ingestion Dose Factors for Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O:OOE+OO 9.92E-02 9.92E-02 9.92E-02 9.92E-02 9.92E-02 9.92E-02 Na-24 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 Cr-51 O.OOE+OO O.OOE+OO 1.31E+OO 7.30E-01 2.88E-01 1.88E+OO 2.21E+02 Mn-54 O.OOE+OO 4.30E+03 8.54E+02 O.OOE+OO 1.28E+03 O.OOE+OO 8.83E+03 Mn-56 O.OOE+OO 1.15E+02 2.05E+01 O.OOE+OO 1.46E+02 O.OOE+OO 7.59E+03 Fe-55 6.89E+02 4.89E+02 1.14E+02 O.OOE+OO O.OOE+OO 3.10E+02 2.12E+02 Fe-59 1.07E+03 2.50E+03 9.65E+02 O.OOE+OO O.OOE+OO 7.88E+02 5.91E+03 Co-58 O.OOE+OO 8.86E+01 2.04E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.22E+03 Co-60 O.OOE+OO 2.56E+02 5.77E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.34E+03 Ni-63 3.23E+04 2.28E+03 1.09E+03 O.OOE+OO O.OOE+OO O.OOE+OO 3.63E+02 Ni-65 1.37E+02 1.75E+01 7.95E+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.47E+02 Cu-64 O.OOE+OO 1.05E+01 4.93E+OO O.OOE+OO 2.65E+01 O.OOE+OO 8.14E+02 Zn-65 2.10E+04 7.30E+04 *3.40E+04 O.OOE+OO

• 4.67E+04 O.OOE+OO 3.09E+04 Zn-69 5.36E+01 1.02E+02 7.15E+OO O.OOE+OO "6.68E+01 O.OOE+OO 1.88E+02 Br-:83 O.OOE+OO O.OOE+OO 4.40E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 5.53E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br.:.85 O.OOE+OO O.OOE+OO 2.34E+OO . O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.09E+05 5.11 E+04 O.OOE+OO
• O.OOE+OO O.OOE+OO 1.61E+04 Rb-88 O.OOE+OO 3.11 E+02 1'.66E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.66E-05 Rb-89 O.OOE+OO 2.01E+02 1.42E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.08E-07 Sr-89 2.41E+04 O.OOE+OO 6.89E+02 O.OOE+OO O.OOE+OO *O.OOE+OO 2.87E+03 Sr-90 5.58E+05 O.OOE+OO .1.12E+04 O.OOE+OO "O.OOE-+'00 O.OOE+OO 1.27E+04 Sr-91 4.42E+02 O.OOE+OO 1.76E+01 O.OOE+OO : O.OOE+OO 'O.OOE+OO 2.00E+03 Sr-92 1.67E+02 O.OOE+OO 7.11E+OO O.OOE+OO :. O.OOE+OO . *O.OOE+OO 4.25E+03 Y-90 6.25E-01 O.OOE+OO 1.68E-02 O.OOE+OO O.OOE-+'00 O.OOE+OO 5.15E+03 Y-91M 5.88E-03 O.OOE+OO 2.25E-04 O.OOE+OO
• O.OOE+OO O.OOE+OO 2.78E-01 Y-91 9.17E+OO O.OOE+OO 4.46E-01 O.OOE+OO O.OOE+OO O.OOE+OO 3.76E+03 Y-92 5.52E-02 O.OOE+OO 1.60E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.51E+03 Y-93. 1.75E-01 O.OOE+OO 4.79E-03
• O.OOE+OO O.OOE+OO O.OOE+OO 5.34E+03 Zr:-95 2.48E-01 7.82E-02 5.38E-02 O.OOE+OO . 1.15E-01 O.OOE+OO 1.81E+02 Zr:-97 1.43E-02 2.82E-03 1.30E-03 O.OOE+OO 4.28E-03 O.OOE+OO 7.64E+02 Nb-95 4.50E+02 2.50E+02 1.'37E+02 O.OOE+OO 2.42E+02 .O.OOE+OO 1.07E+06 Mo-99 O.OOE+OO 1.10E+02 2.10E+01 O.OOE+OO '. 2.52E+02 O'.OOE+OO 1.97E+02 Tc-99M 9:08E-03 2.53E-02 3.28E-01 O.OOE+OO I 3.78E-01 1.41 E-02 1.66E+01 Tc-101 9.85E-03 1.40E-02 1.. 38E-01 O.OOE+OO : 2.53E:.01 8.54E-03 2.39E-09 Ru-103 4.65E+OO O.OOE+OO 1.99E+OO O.OOE+OO . 1.64E+01 O.OOE+OO 3.89E+02 Ru-105 3.98E-01 O.OOE+OO 1.54!=-01 O.OOE+OO : 5.02E+OO O.OOE+OO 3.21E+02 Ru-106 7.15E+01 O.OOE+OO 9.'01E+OO O.OOE+OO 1.38E+02 O.OOE+OO 3.43E+03 Ag-110M 8.60E-01 8.14E-01 4.95E-01 O.OOE+OO 1.55E+oo O. OOE+OO 2.29E+02 Te-125M 2.79E+03 1.01E+03 3.74E+02 7.81E+02 O.OOE+oo O.OOE+OO 8.24E+03 Page 202 of 268

Revision 9 February 27, 2017 Table F-9a (continued) Site Specific Fish Ingestion Dose Factors for Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-127M 7.06E+03 2.50E+03 8.39E+02 1.68E+03 2.86E+04 O.OOE+OO 1.76E+04 Te-127 1.15E+02 4.09E+01 2.48E+01 7.95E+01 4.67E+02 O.OOE+OO 8.90E+03 Te-129M 1.19E+04 4.41E+03 1.88E+03 3.84E+03 4.98E+04 O.OOE+OO 4.47E+04 Te-129 3.27E+01 1.22E+01 7.95E+OO 2.33E+01 1.37E+02 O.OOE+OO 1.79E+02 Te-131M 1.78E+03 8.54E+02 7.12E+02 1.28E+03 8.90E+03 O.OOE+OO 6.85E+04 Te-131 2.04E+01 8.39E+OO 6.36E+OO 1.57E+01 8.90E+01 O.OOE+OO 1.67E+OO Te-132 2.55E+03 1.61E+03 1.52E+03 1.70E+03 1.55E+04 O.OOE+OO 5.11E+04 1-130 2.82E+01 8.15E+01 3.26E+01 6.65E+03 1.26E+02 O.OOE+OO 6.27E+01 1-131 1.60E+02 2.24E+02 1.20E+02 6.54E+04 3.86E+02 O.OOE+OO 4.43E+01 1-132 7.63E+OO 2.00E+01 7.17E+OO 6.73E+02 '3.15E+01 O.OOE+OO 8.70E+OO 1-133 5.50E+01 9.33E+01 2.85E+01 1.30E+04 1.64E+02 O.OOE+OO 7.06E+01 1-134 3.99E+OO 1.06E+01 3.80E+OO 1.76E+02 1.67E+01 O.OOE+OO 1.40E-01 1-135 1.67E+01 4.30E+01

• 1.59E+01 2.76E+03 6.79E+01 O.OOE+OO 4.76E+01 Cs-134 3.05E+05 7.19E+05 3.33E+05 O.OOEi:-00 2.28E+05 8.72E+04 8.94E+03 Cs-136 3.13E+04 1.23E+05
• 8.28E+04 O.OOE+OO 6.71E+04 1.06E+04 9.92E+03 Cs-137 4.09E+05 5.44E+05 1.89E+05 O.OOE+OO 1.85E+05 7.19E+04 7.73E+03 Cs-138 2.83E+02 5.44E+02 2.72E+02 O.OOE.fOO 4.01E+02 4.67E+01 2.47E-01 Ba-139 1.01 E+OO 7.14E-04 2.95E-02 O.OOE-+cOO 6.73E-04 4.92E-04 9.0SE"".00 Ba-140 2.07E+02 2.54E-01 1.34E+01 o:ooE+oo 8.61E-02 1.71 E-01 3.20E+02 Ba-141 4.90E-01 3.66E-04 1.63E-02 O.OOE+OO. 3.39E.:.04 2.SOE-04 1.04E-06 Ba-142 2.18E-01 2.18E-04 1.34E-02 O.OOE+OO. 1.85E-04 1.45E-04 6.70E-13 La-140 1.59E-01 7.80E-02 2.07E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.48E+03 La-142 8.16E-:03 3.63E-03, 9.03E-04 O.OOE+OO O.OOE+OO O.OOE+OO 1.10E+02 Ce-141 2.43E-02 1.62E-02 1..86E-03 O.OOE+OO 7.62E-03 O.OOE+OO 4.63E+01 Ce-143 429E-03 3.12E+OO 3.48E-04. O.OOE+OO 1.40E.,.03. O.OOE+OO 9.38E+01 Ce-144 1.27E+OO 5.25E-01 6.82E-02 O.OOE+OO 3.14E.:.01 O.OOE+OO *3.19E+02 Pr-143 5.97E-01 2.38£;-01 . 2.97E-02 , O.OOE+OO 1.39E-01 O.OOE+OO 1.97E+03 Pr-144 1.96E-03 8.03£;-04 ' 9.94E-05
• O.OOE+OO 4.61E-04 O.OOE+OO 2.16E-06 Nd-147 4.28E-01 4.65E-01 2.79E-02. O,OOE+OO 2.73E-01 O.OOE+OO 1.68E+03 W-187 3.20E+02 2.60E+02 9'.13E+01 o:ooE+oo O.OOE+OO O.OOE+OO 7.05E+04 Np-239 3.21 E-02 3.03E-03 1.68E-03
• O.OOE+OO 9.SOE-03 O.OOE+OO 4.87E+02 Notes:

1) Units are mrem/hr per µCi/ml.

Page 203 of 268

Revision 9 1* February 27, 2017 Table F-9b Site Specific Fish Ingestion Dose Factors for Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 8.21 E-02 8.21 E-02 8.21E-02 8.21 E-02 8.21E-02 8.21 E-02 Na-24 4.56E+02 4.56E+02 4.56E+02 4.56E+02 4.56E+02 4.56E+02 4.56E+02 Cr-51 O.OOE+OO O.OOE+OO 1.40E+OO 7.77E-01 2.12E-01 1.42E+OO 7.43E+01 Mn-54 O.OOE+OO 3.37E+03 8.97E+02 O.OOE+OO 9.44E+02 O.OOE+OO 2.83E+03 Mn-56 O.OOE+OO 1.05E+02 2.37E+01 O.OOE+OO 1.27E+02 O.OOE+OO 1.52E+04 Fe-55 9.05E+02 4.80E+02 1.49E+02 O.OOE+OO O.OOE+OO 2.71E+02 8.89E+01 Fe-59 1.30E+03 2.10E+03 1.05E+03 O.OOE+OO O.OOE+OO 6.09E+02 2.19E+03 Co-58 O.OOE+OO 7.08E+01 2.17E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.13E+02 Co-60 O.OOE+OO 2.08E+02 6.14E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.15E+03 Ni-63 4.23E+04 2.27E+03 1.44E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.53E+02 Ni-65 1.75E+02 1.64E+01 9.60E+OO O.OOE+OO O.OOE+OO O.OOE+OO :2.01E+03 Cu-64 O.OOE+-00 9.64E+OO 5.82E+OO O.OOE+OO 2.33E+01 O.OOE+OO 4.52E+02 Zn-65 2.16E+04 5.74E+04 3.57E+04 O.OOE+OO 3.62E+04 O.OOE+OO 1.01 E+04 Zn-69 6.89E+01 9.96E+01 9.20E+OO . O.OOE+OO 6.04E+01 O.OOE+OO 6.28E+03 Br-83 O.OOE+OO O.OOE+OO 5.65E+01 . O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO '6.54E+01 O.OOE+OO O.OOE+OO .O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 3.01E+OO ! O.OOE+OO O.OOE+OO O.OOE+OO *O.OOE+OO Rb-86 O.OOE+OO '1.05E+05 6.48E+04

• O.OOE+OO O.OOE+OO O.OOE+OO 6.78E+03 Rb-88 O.OOE+OO 2.99E+02 2.08E+02 : O.OOE+OO O.OOE+OO O.OOE+OO 1A7E+01 Rb-89 O.OOE+OO 1.84E+02 1.64E+02 .. O.OOE+OO O.OOE+OO O.OOE+OO 1.60E+OO Sr-89 3.11E+04 O.OOE+OO 8.90E+02 .* O.OOE+OO O.OOE+OO O.OOE+OO 1.21E+03 Sr-90 6.04E+05 O.OOE+OO 1.22E+04 : O.OOE+OO O.OOE+OO O.OOE+OO 5.40E+03 Sr-91 5.66E+02 O.OOE+OO 2.14E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.25E+03 Sr-92 2.13E+02 O.OOE+OO 8.54E+'o0 O.OOE+OO O.OOE+OO O.OOE+OO 4.04E+03 Y-90 8.08E-01 O.OOE+OO 2~ 16E-02 : O.OOE+OO O.OOE+OO O.OOE+OO 2.30E+03 Y-91M 7.51E-03 O.OOE+OO. 2.73E-04 . O.OOE+OO O.OOE+OO O.OOE+OO 1.47E+01 Y-91 1.18E+01 O.OOE+OO 3.17E-01 : O.OOE+OO O.OOE+OO O.OOE+OO 1.58E+03 Y-92 7.08E-02 O.OOE+OO 2*.03E-03
• O.OOE+OO O.OOE+OO O.OOE+OO 2.05E+03 Y-93 2.24E-01 O.OOE+OO 6.16E-03. O.OOE+OO O.OOE+OO O.OOE+oo 3.34E+03 Zr-95 3.01E-01 6.62E-02 5.89E-02 O.OOE+OO 9.47E-02 O.OOE+OO 6.90E+01 Zr-97 1.81E-02 2.62E-03 1.55E-03
• O.OOE+OO 3.76E-03 O.OOE+OO 3.97E+02 Nb-95 5.31E+02 2.07E+02 1.48E+02 O.OOE+OO 1.94E+02 O.OOE+OO 3.82E+05 Mo-99 O.OOE+OO 1.05E+02 2.59E+01 O.OOE+OO 2.23E+02 O.OOE;+-00 8.65E+01 Tc- 99M 1.09E-02 2.14E-02 3.54E-01 O.OOE+OO 3.10E-01 1.08E-02 1.22E+01 Tc-101 1.26E-02 1.32E-02 1.68E-01. O.OOE+OO 2.25E-01 6.99E-03 . 4.20E-02 Ru-103 5.75E;+-OO O.OOE+OO 2.21E+OO : O.OOE+OO 1.45E+01 O.OOE+OO 1.49E+02 Ru-105 5.07E-01 O.OOE+OO 1.84E-01 * .0.00E+OO 4.46E+OO O.OOE+-00 3.31E+02 Ru-106 9.20E+01 O.OOE+OO 1.15E+01 O.OOE+OO 1.24E+02 O.OOE+OO 1.43E+03 Ag-110M 9.75~-01 6.59E-01 S:.26E-01 . O.OOE+OO 1.23E+OO. O.OOE+oo 7.83E+01 Te-125M 3.59E+-03 9.72E+02 4.78E+02 1.01 E+03 O.OOE+OO O.OOE+OO 3.46E+03 Page 204 of 268

Revision 9 February 27, 2017 Table F-9b (continued) Site Specific Fish Ingestion Dose Factors for Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-127M 9.09E+03 2.45E+03 1.08E+03 2.17E+03 2.59E+04 O.OOE+OO 7.36E+03 Te-127 1.48E+02 4.00E+01 3.18E+01 1.03E+02 4.22E+02 O.OOE+OO 5.79E+03 Te-129M 1.53E+04 4.28E+03 2.38E+03 4.94E+03 4.50E+04 O.OOE+OO 1.87E+04 Te-129 4.22E+01 1.18E+01 1.00E+01 3.01E+01 1.23E+02 O.OOE+OO 2.62E+03 Te-131M 2.27E+03 7.83E+02 8.34E+02 1.61E+03 7.58E+03 O.OOE+OO 3.18E+04 Te-131 2.61E+01 7.96E+OO 7.77E+OO 2.00E+01 7.90E+01 O.OOE+OO 1.37E+02 Te-132 3.18E+03 1.41E+03 1.70E+03 2.05E+03 1.31 E+04 O.OOE+OO 1.42E+04 1-130 3.45E+01 6.96E+01 3.59E+01 7.67E+03 1.04E+02 O.OOE+OO 3.26E+01 1-131 2.03E+02 2.04E+02 1.16E+02 6.75E+04 3.35E+02 O.OOE+OO 1.82E+01 1-132 9'.44E+OO 1.73E+01 7.98E+OO 8.05E+02 2.65E+01 O.OOE+OO 2.04E+01 1-133 6~99E+01 8.64E+01 3.27E+01 1.60E+04 1.44E+02 O.OOE+OO 3.48E+01 1-134 4.94E+OO 9.18E+OO 4.22E+OO 2.11E+02 1.40E+01 O.OOE+OO 6.09E+OO 1-135 2~06E+01  : 3.72E+01 1.7,6E+01 3.29E+03 5.70E+01 . O.OOE+OO 2.83E+01 Cs-134 3.68E+05 i 6.04E+05 1.27E+05 O.OOE+OO 1.87E+05 6.72E+04 3.26E+03 Cs-136 3.70E+04 . 1.02E+05 6.58E+04 O.OOE+OO 5.41E+04

• 8.07E+03 3.57E+03 Cs-137 5.14E+05 4.92E+05 7.27E+04 O.OOE+OO 1.60E+05 5.77E+04 3.08E+03 Cs-138 3.59E+02 . 4.99E+02 3.16E+02 O.OOE+OO 3.51E+02 3.78E+01 2.30E+02 Ba-139 :1*.30E+OO 6.95E-04 3.78E-02 O.OOE+OO 6.07E-04 4.09E.,04 7.52E+01 Ba-140 2'.61E+02: 2.29E-01 1.53E+01 O.OOE+OO 7.46E-02 1.37E-01 .1.32E+02 Ba-141 6.29E-01 . 3.52E-04 2.05E-02 O.OOE+OO 3.05E-04 2.07E-03 3.59E-01 Ba-142 :2.75E-01 : 1.98E-04 1.54E-02 . O.OOE+OO. 1.60E-04 1.16E-04 3.59E-03 La-140
• 1.99E-01 . 6.94E-02 2.34E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.94E+03 La-142 1.03E-02 3.28E-03 1.03E-03 O.OOE+OO .O.OOE+OO . O.OOE+OO 6.51E+02 Ce-141 ;3.12E-02. 1.56E-02 2.31 E-03 O.OOE+OO 6.83E-03 O.OOE+OO 1.94E+01 Ce-143 1 5.50E-03 2.98E+OO 4.32E-04 O.OOE+OO
• 1.25E-03 . O.OOE+OO 4.37E+01 Ce-144 '1.64E+OO: 5.13E-01 8.73E-02 , O.OOE+OO 2.84E-01
• O.OOE+OO 1.34E+02 Pr-143 7.73E-01 : 2.32E-01 3.83E-02 O.OOE+OO 1.26E-01 O.OOE+OO 8.34E+02 Pr-144 4.54E-03 7.85E-04 1.28E-04 O.OOE+OO 4.15E-04 O.OOE+OO 1.69E+OO Nd-147 5.49E-01
• 4.44E-01 3.44E-02 O.OOE+OO 2.44E-01 *. O.OOE+OO 7.04E+02 W-187 4.05E+02
• 2.40E+02 1.08E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.37E+04 Np-239 4.13E-02: 2.97E-03 2.08E-03 O.OOE+OO 8.57E-03 O~OOE+OO 2.19E+02 Notes:

1) Units are mrem/hr per µCi/ml.

2) The infant age group is assumed to receive no dose through the fish ingestion pathway, therefore no dose factors are supplied.

Page 205 of 268

Revision 9 February 27, 2017 Table F-10 Ground Plane Dose Factors Nuclide Bone Liver TBody Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-24 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 Cr-51 4.65E+06 4.65E+06 4.65E+06 4.65E+06 4.65E+06 4.65E+06 4.65E+06 Mn-54 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 Mn-56 9.03E+05 9.03E+05 9.03E+05 9.03E+05 9.03E+05 9.03E+05 9.03E+05 Fe-55 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Fe-59 2.73E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08 Co-58 3.80E+08 3.80E+08 3.80E+08 3.80E+08 3.80E+08 3.80E+08 3.80E+08 Co-60 2.45E+10 2.45E+10 2.45E+10 2.45E+10 2.45E+10 2.45E+10 2.45E+10 Ni-63 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ni-65 2.97E+05 2.97E+05 2:97E+05 2.97E+05 2.97E+05 2.97E+05 2.97E+05 Cu-64 6.05E+05 6.05E+05 6.05E+05 6.05E+05 6.05E+05 6.05E+05 6.05E+05 Zn-65 7.46E+08 7.46E+08 7:46E+08 7.46E+08 7.46E+08 7.46E+08 7.46E+08 Zn-69 O.OOE+OO O.OOE+OO . O,OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 4.87E+03 4.87E+03 4:87E+03 4.87E+03 4.87E+03 : 4.87E+03 4.87E+03 Br-84 2.03E+05 2.03E+05 2.03E+05 2.03E+05 2.03E+05 2.03E+05 2.03E+05 Br-85 O.OOE+OO O.OOE+OO o~ooE+oo . O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 9.01E+06 9.0~E+06 9.01E+06 :9.01E+06 9.01E+06 9.01E+06 9.01E+06 Rb-88 3.31E+04 3.31E+04 3;31E+04 3.31E+04 3.31E+04 3.31E+04 3.31E+04 Rb-89 1.23E+05 1.23E+05 1J23E+05 1.23E+05 1.23E+05 , 1.23E+05 '1.23E+05 Sr-89 2.16E+04 2.16E+04 2,16E+04 2.16E+04 2.16E+04 : 2.16E+04 2.16E+04 Sr-90 O.OOE+OO O.OOE+OO,

• o~ooE+oo O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-91 .2.14E+06 2.14E+06' 2:14E+06 * :2.14E+06. 2.14E+06 2.14Er06 2.14E+06 Sr-92 7.76E+05 7.7~E+05 : 7:76E+05 }*.76E+05 7.76E+05 7.76E+o5 7.76E+05 Y-90 4.50E+03 4.5bE+03 . 4~.50E+03 4.50E+03 4.50E+03 4.501:;+03 4.50E+03 Y-91M 1.00E+05 1.00E+05
• 1:00E+05 . 1.00E+05 ' 1.00E+05 ,1.00Ef05 1.00E+05 Y-91 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 : 1.07E+06 1.07E+06 Y-92 1.80E+05 1. 80E+.05 1:'80E+05 .1.80E+05 1.80E+05 '1.80E+05 1.80E+05 Y-93 1.83E+05 1.83E+05 1!83E+05 :1.83E+05 . 1.83E+05 '1.83E+05 1.83E+05 Zr-95 2.45E+08 2.45E+08 2:45E+08 2.45E+08 2.45E+08 2.45E+08 2.45E+08 Zr-97 2.96E+06 2.96E+06 2;96E+06 2.96E+06 2.96E+06 2.96E+06 2.96E+06 Nb-95 1.37E+08 1.37E+08 1:37E+08 '1.37E+08 1.37E+08 1.37E+08 1.37E+08 Mo-99 3.99E+06 3.99E+06 3:99E+06 3.99E+06 '3.99E+06 3.99E+06 3.99E+06 Tc-99M 1.84E+05 1.84E+05 1!84E+05 1.84E+05 *1.84E+05 1.84E+05 1.84E+05 Tc-101 2.03E+04 2.03E+04 ,2;03E+04 2.03E+04 2.03E+04 2.03E+04 2.03E+04 Ru-103 1.08E+08 1.08E+08 ' 1'.086+08
• 1.08E+08 1.08E+08 1.08E+08 t.08E+08 Ru-105 6.36E+05 6.36E+05
• 6!36E+05 . *6.36E+05 6.36E+05 6.36E'.'"05 6,36E+05 Ru-106 4.22E+08 4.22E+08 4.22E+08 ,' '4.22E+08 4.22E+08 4.22E+08 4.22E+08 Ag-110M 3.45E+09 3.4pE+09 3:45E+09
• 3.45E+09 3.45E+09 3.45E+09 3.45E+09 Page 206 of 268

Revision 9 February 27, 2017 Table F-10 (Continued) Ground Plane Dose Factors (same for all age groups) Nuclide Bone Liver TBody Thyroid Kidney Lung Gl-LLI Te-125M 1.56E+06 1.56E+06 1.56E+06 1.56E+06 1.56E+06 1.56E+06 1.56E+06 Te-127M 9.16E+04 9.16E+04 9.16E+04 9.16E+04 9.16E+04 9.16E+04 9.16E+04 Te-127 2.99E+03 2.99E+03 2.99E+03 2.99E+03

• 2.99E+03 2.99E+03 2.99E+03 Te-129M 1.98E+07 1.98E+07 1.98E+07 1.98E+07 1.98E+07 1.98E+07 1.98E+07 Te-129 2.62E+04 2.62E+04 2.62E+04 2.62E+04 2.62E+04 2.62E+04 2.62E+04 Te-131M 8.02E+06 8.02E+06 8.02E+06 8.02E+06 8.02E+06 8.02E+06 8.02E+06 Te-131 2.92E+04 2.92E+04 2.92E+04 2.92E+04 2.92E+04 2.92E+04 2.92E+04 Te-132 4.22E+06 4.22E+06 4.22E+06 4.22E+06 4.22E+06 4.22E+06 4.22E+06 1-130 5.50E+06 5.50E+06 5.50E+06 5.50E+06 5.50E+06 5.50E+06 5.50E+06 1-131 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1-132 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1-133 2.45E+06 2.45E+06 2.45E+06 2.45E+06 2.45E+06 2.45E+06 2.45E+06 1-134 4.46E+05 4.46E+05 4.46E+05 4.46E+05 4.46E+05 4.46E+05 4.46E+05 1-135 2.53E+06 2.53E+06 2.53E+06 2.53E+06 2.53E+06 2.53E+06 2.53E+06 Cs-134 6.94E+09 6.94E+09 l;).94E+09 6.94E+09 6.94E+09 6.94E+09 6.94E+09 Cs-136 1.50E+08 1.50E+08 1.50E+08 1.50E+08 1.50E+08 1.50E+08 1.50E+08 Cs-137 1.76E+10 1.76E+10 1.76E+10' 1.76E+10 1.76E+10 1.76E+10 1.76E+10 Cs-138 3.59E+05 3.59E+05 3.59E+05
• 3.59E+05 3.59E+05 3.59E+05 3.59E+05 Ba-139* 1.06E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 Ba-140 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 Ba-141 4.17E+04 4.17E+04 4.17E+04 4.17E+04 4.17E+04 4.17E+04 4.17E+04 Ba-1:42 4.44E+04 4.44E+04 4.44E+04 4.44E+04 4.44E+04 4.44E+04 4.44E+04 La-140 1.92E+07
• 1.92E+07 1.92E+07 1.92E+07 1.92E+07
• 1.92E+07 1.92E+07 La-142 7.60E+05 7.60E+05 7.60E+05 7.60E+05 7.60E+05 7.60E+05 7.60E+05 Ce-141 1.37E+.07 1.37E+07 1.37E+07 * '1.37E+07 1.37E+07 1.37E+07 1.37E+07 Ce-143 2.31E+06 2.31E+06 2.31E+06 2.31E+06 2.31E+06 2.31E+06 2.31E+06 Ce-144 6.96E+07 6.96E+07 6.96E+07 6;96E+07 6.96E+07
• 6.96E+07 6.96E+07 Pr-143 O.OOE+.00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Pr-144 1.84E+O~ 1.84E+03 1.84E+03, 1.84E+03
• 1.84E+03 1.84E+03 1.84E+03 Nd-147 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 W-187 2.35E+06 2.35E+06 2.35E+06 : :2.35E+06 . 2.35E+06 2.35E+06 2.35E+06 Np-239 1.71E'f-06 1.71E+06 1.71 E+06 , 1.71E+06 1.71 E:t-06 1.71E+06 1.71E+06 Notes:

2

1) Units are m mrem/yr per µCi/sec.

2) All age groups are assumed to receive the same dose.

Page 207 of 268

Revision 9 February 27, 2017 Table F-11 Adult Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 7.18E+02 7.18E+02 7.18E+02 7.18E+02 7.18E+02 7.18E+02 Na-24 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 Cr-51 O.OOE+OO O.OOE+OO 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 Mn-54 O.OOE+OO 3.96E+04 6.30E+03 O.OOE+OO 9.84E+03 1.40E+06 7.74E+04 Mn-56 O.OOE+OO 1.24E+OO 1.83E-01 O.OOE+OO 1.30E+OO 9.44E+03 2.02E+04 Fe-55 2.46E+04 1.70E+04 3.94E+03 O.OOE+OO O.OOE+OO 7.21E+04 6.03E+03 Fe-59 1.18E+04 2.78E+04 1.06E+04 O.OOE+OO O.OOE+OO 1.02E+06 1.88E+05 Co-58 O.OOE+OO 1.58E+03 2.07E+03 O.OOE+OO O.OOE+OO 9.28E+05 1.06E+05 Co-60 O.OOE+OO 1.15E+04 1.48E+04 O.OOE+OO O.OOE+OO 5.97E+06 2.85E+05 Ni-63 4.32E+05 3.14E+04 1.45E+04 O.OOE+OO O.OOE+OO 1.78E+05 1.34E+04 Ni-65 1.54E+OO 2.10E-01 9.12E-02 O.OOE+OO O.OOE+OO 5.60E+03 1.23E+04 Cu-64 O.OOE+OO 1.46E+OO 6.15E-01 O.OOE+OO 4.62E+OO 6.78E+03 4.90E+04 Zn-65 3.24E+04 1.03E+05 4.66E+04 O.OOE+OO 6.90E+04 8.64E+05 5.34E+04 Zn-69 3.38E-02 6.51E-02 4.52E-03 O.OOE+OO 4.22E-02 9.20E+02 1.63E+01 Br-83 O.OOE+OO O.OOE+OO 2.41E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.32E+02 Br-84 O.OOE+OO O.OOE+OO 3.13E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.64E-03 Br-85 O.OOE+OO O.OOE+OO 1.28E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.35E+05 5.90E+04 *O.OOE+OO O.OOE+OO O.OOE+OO 1.66E+04 Rb-88 O.OOE+OO 3.87E+02 1.93E+02 I O.OOE+OO O.OOE+OO O.OOE+OO 3.34E-09 Rb-89 O.OOE+OO 2.56E+02 . 1.70E+02 . O.OOE+OO O.OOE+OO O.OOE+OO 9.28E-12 Sr-89 3.04E+05 O.OOE+OO 8.72E+03 O.OOE+OO O.OOE+OO 1.40E+06 3.50E+05 Sr-90 2.87E+07 O.OOE+OO 5.77E+05  : O.OOE+OO .O.OOE+OO 9.60E+06 7.22E+05 Sr-91 6.19E+01 O.OOE+OO 2.50E+OO O.OOE+OO O.OOE+OO 3.65E+04 1.91E+05 Sr-92 6.74E+OO . O.OOE+OO 2.91E-01 I O.OOE+OO O.OOE+OO 1.65E+04 4.30E+04 Y-90 2.09E+03 : O.OOE+OO 5.61E+01 'O.OOE+OO O.OOE+OO 1.70E+05 5.06E+05 Y-91M 2.61E-01 O.OOE+OO . 1.02E-02 O.OOE+OO O.OOE+OO 1.92E+03 1.33E+OO Y-91 4.62E+05 O.OOE+OO 1.24E+04  : O.OOE+OO O.OOE+OO 1.70E+06 3.85E+05 Y-92 1.03E+01 O.OOE+OO 3.02E-01  : O.OOE+OO O.OOE+OO 1.57E+04 7.35E+04 Y-93 9.44E+01 O.OOE+OO 2.61E+OO . O.OOE+OO O.OOE+OO 4.85E+04 4.22E+05 Zr-95 1.07E+05 . 3..44E+04 2.33E+04 O.OOE+OO 5.42E+04 1.77E+06. 1.50E+05 Zr-97 9.68E+01 1.96E+01 9.04E+OO 'O.OOE+OO .2.97E+01 7.87E+04 5.23E+05 Nb-95 1.41 E+04 . 7.82E+03 . 4.21E+03 I O.OOE+OO 7.74E+03 5.05E+05 1.04E+05 Mo-99 O.OOE+OO : 1.21E+02 2.30E+01 . O.OOE+OO 2.91E+02 9.12E+04 2.48E+05 Tc-99M 1.03E-03 . 2.91E-03 3.70E-02 O.OOE+OO 4.42E-02 '7.64E+02 4.16E+03 Tc-101 4.18E-05 6.02E-05

• 5.90E-04 O.OOE+OO 1.08E-03 3.99E+02 1.09E-11 Ru-103 1.53E+03
• O.OOE+.00 6.58E+02 O.OOE+OO 5.83E+03 5.05E+05 1.10E+05 Ru-105 7.90E-01 . 0,00E+OO 3.11E-01 O.OOE+OO 1.'02E+OO 1.10E+04 4.82E+04 Ru-106 6.91E+04 , O.OOE+OO . 8.72E+03 O.OOE+OO 1.34E+05 9.36E+06 . 9.12E+05 Ag-110M 1.08E+04
• 1.00E+04 5.94E+03
• O.OOE+OO 1.97E+04 4.63E+06 3.02E+05 Page 208 of 268 L

Revision 9 February 27, 2017 Table F-11 (Continued) Adult Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl.:.LLI Te-125M 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 Te-127M 1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 Te-127 1.40E+OO 6.42E-01 3.10E-01 1.06E+OO 5.10E+OO 6.51E+03 5.74E+04 Te-129M 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+-06 3.83E+05 Te-129 4.98E-02 2.39E-02 1.24E-02 3.90E-02 1.87E-01 1.94E+03 1.57E+02 Te-131M 6.99E+01 4.36E+01 2.90E+01 5.50E+01 3.09E+02 1.46E+05 5.56E+05 Te-131 1.11 E-02 5.95E-03 3.59E-03 9.36E-03 4.37E-02 1.39E+03 1.84E+01 Te-132 2.60E+02 2.15E+02 1.62E+02 1.90E+02 1.46E+03 2.88E+05 5.10E+05 1-130 4.58E+03 1.34E+04 5.28E+03 1.14E+06 2.09E+04 O.OOE+OO 7.69E+03 1-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 O.OOE+OO 6.28E+03 1-132 1.16E+03 3.26E+03 1.16E+03 1.14E+05 5.18E+03 O.OOE+OO 4.06E+02 1-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 O.OOE+OO 8.88E+03 1-134 6.44E+02

• 1.73E+03 6.15E+02 2.98E+04 2.75E+03 O.OOE+OO 1.01E+OO 1-135 2.68E+03
• 6.98E+03 2.57E+03 4.48E+05 1.11E+04 O.OOE+OO 5.25E+03 Cs-134 3.73E+05
• 8.48E+05 7.28E+05 O.OOE+OO 2.87E+05 9.76E+04 1.04E+04 Cs-136 3.90E+04 1.46E+05 1.10E+05 O.OOE+OO 8.56E+04 1.20E+04 1.17E+04 Cs-137
• 4.78E+05 6.21E+05 4.28E+05 O.OOE+OO 2.22E+05 7.52E+04 8.40E+03 Cs-138 3.31E+02 6.21E+02 3.24E+02 O.OOE+OO 4.80E+02 4.86E+01 1.86E-03 Ba-139 9.36E-01 6.66E-04 . 2.74E-02 O.OOE+OO 6.22E-04 3.76E+03 8.96E+02 Ba-140 3.90E+04 4.90E+01 2.57E+03 O.OOE+OO 1.67E+01 1.27E+06 2.18E+05 Ba-141 1.00E-01 7.53E-05 3.36E-03 O.OOE+OO 7.00E-05 1.94E+03 1.16E-07 Ba-142 2.63E-02 2.70E-05 1.66E-03 O.OOE+OO 2:29E-05 1.19E+03 1.57E-16 La-140 3.44E+02 1.74E+02 4.58E+01 O.OOE+OO
• O.OOE+OO 1.36E+05 4.58E+05 La-142 6.83E-01
• 3.10E-Ot 7.72E-02 O.OOE+OO . O.OOE+OO 6.33E+03 2.11E+03 Ce-141 1.99E+04 1.35E+04
• 1.53E+03 O.OOE+OO 6.26E+03 3.62E+05 1.20E+05 Ce-143 1.86E+02 1.38E+n2 1.53E+01 O.OOE+OO .6.08E+01 7.98E+04 *2.26E+05 Ce-144 3.43E+06 1.43E+06 1.84E+05 O.OOE+OO 8.48E+05 7.78E+06 8.16E+05 Pr-143 9.36E+03 3.75E+03 4.64E+02 O.OOE+OO 2.16E+03 2.81E+05 2.00E+05 Pr-144 3.01E-02 . 1.25E-02 1.53E-03 O.OOE+OO 7.0SE-03 1.02E+03 2.15E-08 Nd-147. 5.27E+03 6.10E+03 3.65E+02 O.OOE+OO 3.56E+03 2.21E+05 1.73E+05 W-187 8.48E+OO 7.08E+OO 2.48E+OO O.OOE+OO 'O.OOE+OO 2~90E+04 1.55E+05 Np-239* 2.30E+02 2.03E+02 1.2.4E+01 O.OOE+OO
• 7.00E+01 376E+04 1.19E+05 Notes:

3

1) Units are mrem/yr per µCi/m .

Page 209 of 268

Revision 9 February 27, 2017 Table F-11a Teen Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 7.25E+02 7.25E+02 7.25E+02 7.25E+02 7.25E+02 7.25E+02 Na-24 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 Cr-51 O.OOE+OO O.OOE+OO 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.00E+03 Mn-54 O.OOE+OO 5.11E+04 8.40E+03 O.OOE+OO 1.27E+04 1.98E+06 6.68E+04 Mn-56 O.OOE+OO 1.70E+OO 2.52E-01 O.OOE+OO 1.79E+OO 1.52E+04 5.74E+04 Fe-55 3.34E+04 2.38E+04 5.54E+03 O.OOE+OO O.OOE+OO 1.24E+05 6.39E+03 Fe-59 1.59E+04 3.70E+04 1.43E+04 O.OOE+OO O.OOE+OO 1.53E+06 1.78E+05 Co-58 O.OOE+OO 2.07E+03 2.78E+03 O.OOE+OO O.OOE+OO 1.34E+06 9.52E+04 Co-60 O.OOE+OO 1.51E+04 1.98E+04 O.OOE+OO O.OOE+OO 8.72E+06 2.59E+05 Ni-63 5.80E+05 4.34E+04 1.98E+04 O.OOE+OO O.OOE+OO 3.07E+05 1.42E+04 Ni-65 2.18E+OO 2.93E-01 1.27E-01 O.OOE+OO O.OOE+OO 9.36E+03 3.67E+04 Cu-64 O.OOE+OO 2.03E+OO 8.48E-01 O.OOE+OO 6.41E+OO 1.11E+04 6.14E+04 Zn-65 3.86E+04 1.34E+05 6.24E+04 O.OOE+OO

• 8.64E+04 1.24E+06 4.66E+04 Zn-69 4.83E-02 9.20E-02 6.46E-03 O.OOE+OO 6.02E-02 1.58E+03 2.85E+02 Br~83 O.OOE+OO O.OOE+OO 3.44E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 4.33E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 1.83E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.90E+05 8.40E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.77E+04 Rb-88 O.OOE+OO 5.46E+02 2.72E+02 O:OOE+OO O.OOE+OO O.OOE+OO 2.92E-05 Rb-89 O.OOE+OO 3.52E+02 2.33E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.38E-07 Sr-89 4.34E+05 O.OOE+OO 1.25E+04 O.OOE+OO O.OOE+OO 2.42E+06 3.71E+05 Sr-90 3.31E+07 O.OOE+OO 6.66E+05 O.OOE+OO O.OOE+OO 1.65E+07 7.65E+05 Sr-91 8.80E+01 O.OOEtOO 3.51E+OO O.OOE+OO O.OOE+OO 6.07E+04 . 2.59E+05 Sr-92 9.52E+OO O.OOE+OO 4.06E-01 O.OOE+OO I O.OOE+OO 2.74E+04 1.19E+05 Y-90 2.98E+03 O.OOE+OO 8.00E+01 O.OOE+OO O.OOE+OO 2.93E+05 . 5.59E+05 Y-91M 3.?0E-01 O.OOE+OO 1.42E-02 O.OOE+OO O.OOE+OO 3.20E+03 3.02E+01 Y-91 6.6.1E+05 O.OOE+OO 1.77E+04 O.OOE+OO O.OOE+OO 2.94E+06
• 4.09E+05 Y-92 '1.47E+01 O.OOE+OO 4.29E-01 O.OOE+OO Q.OOE+OO 2.68E+04 1.65E+05 Y-93 1.35Et02 O.OOE+OO 3.72E+OO O.OOE+OO .O.OOE+OO 8.32E+04 5.79E+05 Zr-95 1.46E+05 4.5.8E+04 3.15E+04 O.OOE+OO 6.74E+04 2.69E+06 1.49E+05 Zr-97 1..38E+02 *2.72E+01 1.26E+01 O.OOE+OO 4.12E+01 1.30E+05 . 6.30E+05 Nb-95
• f.86E+04 1.03E+04 5.66E+03 O.OOE+OO 1.00E+04 7.51E+05 9.68E+04 Mo-99 O.OOE+OO 1.69E+02 3.22E+01 O.OOE+OO 4.11E+02 1.54E+05 2.69E+05 Tc-99M 1.38E-03 3.86E-03 4.99E-02 O.OOE+OO. 5.76E-02 1.15E+03 6.13E+03 Tc-101 5.92E-05 8.40E-05 8.24E-04 O.OOE+OO 1.52E-03 6.67E+02 8.72E-07 Ru-103 2.10E+03 O.OOE+.00 8.96E+02 O.OOE+OO
• 7.43E+03 7.83E+05 1.09E+05 Ru-105 1.12E+OO 1

O.OOE+OO 4.34E-01 O.OOE+OO 1.41 E+OO 1.82E+04 9.04E+04 Ru-106 9.. 84E+04 O.OOE+OO 1.24E+04 O.OOE+OO 1.90E+05 1.61E+07 9.60E+05 Ag-110M 1.38E+04 1.31 E+04 7.99E+03 O.OOE+OO 2.50E+04 6.75E+06 2.73E+05 Page 210 of 268

Revision 9 February 27, 2017 Table F-11a (Continued) Teen Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 4.88E+03 2.24E+03 6.67E+02 1.40E+03 O.OOE+OO 5.36E+05 7.50E+04 Te-127M 1.80E+04 8.16E+03 2.18E+03 4.38E+03 6.54E+04 1.66E+06 1.59E+05 Te-127 2.01E+OO 9.12E-01 4.42E-01 1.42E+OO 7.28E+OO 1.12E+04 8.08E+04 Te-129M 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 Te-129 7.10E-02 3.38E-02 1.76E-02 5.18E-02 2.66E-01 3.30E+03 1.62E+03 Te-131M 9.84E+01 6.01E+01 4.02E+01 7.25E+01 4.39E+02 2.38E+05 6.21E+05 Te-131 1.58E-02 8.32E-03 5.04E-03 1.24E-02 6.18E-02 2.34E+03 1.51E+01 Te-132 3.60E+02 2.90E+02 2.19E+02 2.46E+02 1.95E+03 4.49E+05 4.63E+05 1-130 6.24E+03 1.79E+04 7.17E+03 1.49E+06 2.75E+04 O.OOE+OO 9.12E+03 1-131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 O.OOE+OO 6.49E+03 1-132 1.59E+03 4.38E+03 1.58E+03 1.51E+05 6.92E+03 O.OOE+OO 1.27E+03 1-133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 O.OOE+OO 1.03E+04 1-134 8.88E+02 2.32E+03 8.40E+02 3.95E+04 3.66E+03 O.OOE+OO 2.04E+01 1-135 3.70E+03 9.44E+03 3.49E+03 6.21E+05 1.49E+04 O.OOE+OO 6.95E+03 Cs-134 5.02E+05 1.13E+06 5.49E+05 O.OOE+OO 3.75E+05 1.46E+05 9.76E+03 Cs-136 5.15E+04 1.94E+05 1.37E+05 O.OOE+OO 1.10E+05 1.78E+04 1.09E+Q4 Cs-137 6.70E+05 8.48E+05 3.11E+05 O.OOE+OO 3.04E+05 1.21 E+OS 8.48E+03 Cs-138 4.66E+02 8.56E+02 4.46E+02 O.OOE+OO 6.62E+02 7.87E+01 2.70E-01 Ba-139 1.34E+OO 9.44E-04 3.90E-02 O.OOE+OO 8.88E-04 6.46E+03 6.45E+03 Ba-140 5.47E+04

• 6.70E+01 3.52E+03 *O.OOE+OO 2.28E+01 2.03E+06 2.29E+05 Ba-141 1.42E-01 ' 1.06E-04
• 4.74E-03 O.OOE+OO 9.84E-05 3.29E+03 7.46E-04 Ba-142 3.70E-02 3.70E~05 2.27E-03. O.OOE+OO 3.14E-05 1.91 E+03 4.79E-10 La-140 4.79E+02 2.36E+02 *.6.26E+01 O.OOE+OO O.OOE+OO 2.14E+05 4.87E+05 La-142 9.60E-01 '4.25E-01 1.06E-01 O.OOE+OO O.OOE+OO 1.02E+04 1.20E+04 Ce-141 2,84E+04 1.90E+.04 2.17E+03 O.OOE+OO 8.88E+03 6.14E+05 1.26E+05 Ce-143 2'.66E+02
• 1.94E+02 2.16E+01 O.OOE+OO 8.64E+01 1.30E+05 2.55E+05 Ce-144 4.89E+06 2.02E+06 2.62E+05 O.OOE+OO 1.21 E+06 1.34E+07 8.64E+05 Pr-143 1~34E+04 5.31E+03 6.62E+02 O.OOE+OO 3.09E+03 4.83E+05 2.14E+05 Pr-144 4.30E-02 1.76E-:02 . 2.18E-03. O.OOE+OO
• 1.01E-02 1.75E+03
• 2.35E-04 Nd-147 7'.86E+03 8.56E+03 . 5.13E+02 O.OOE+OO 5.02E+03 3.72E+05 .1.82E+05 W-187 1,.'20E+01 9.76Ei100 . 3.43E+OO O.OOE+OO O.OOE+OO 4.74E+04 1.77E+05 Np-239 3.38E+02 2.88E+02 1.77E+01 O.OOE+OO 1.00E+02 6.49E+04 1.32E+05 Notes:

3

1) Units are mrem/yr per µCi/m .

Page 211 of 268

Revision 9 February 27, 2017 Table F-11b Child Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 6.40E+02 6.40E+02 6.40E+02 6.40E+02 6.40E+02 6.40E+02 Na-24 1.61E+04 1.61E+04 1.61E+04 1.61 E+04 1.61 E+04 1.61E+04 1.61 E+04 Cr-51 O.OOE+OO O.OOE+OO 1.54E+02 8.5(?E+01 2.43E+01 1.70E+04 1.08E+03 Mn-54 O.OOE+OO 4.29E+04 9.51E+03 O.OOE+OO 1.00E+04 1.58E+06 2.29E+04 Mn-56 O.OOE+OO 1.66E+OO 3.12E-01 O.OOE+OO 1.67E+OO 1.31E+04 1.23E+05 Fe-55 4.74E+04 2.52E+04 7.77E+03 O.OOE+OO O.OOE+OO 1.11E+05 2.87E+03 Fe-59 2.07E+04 3.34E+04 1.67E+04 O.OOE+OO O.OOE+OO 1.27E+06 7.07E+04 Co-58 O.OOE+OO 1.77E+03 3.16E+03 O.OOE+OO O.OOE+OO 1.11E+06 3.44E+04 Co-60 O.OOE+OO 1.31E+04 2.26E+04 O.OOE+OO O.OOE+OO 7.07E+06 9.62E+04 Ni-63 8.21E+05 4.63E+04 2.80E+04 O.OOE+OO O.OOE+OO 2.75E+05 6.33E+03 Ni-65 2.99E+OO 2.96E-01 1.64E-01 O.OOE+OO O.OOE+OO 8.18E+03 8.40E+04 Cu-64 O.OOE+OO 1.99E+OO 1.07E+OO O.OOE+OO 6.03E+OO 9.58E+03 3.67E+04 Zn-65 4.26E+04 1.13E+05 7.03E+04 O.OOE+OO 7.14E+04 9.95E+05 1.63E+04 Zn-69 6.70E-02 9.66E-02 8.92E-03 O.OOE+OO 5.85E-02 1.42E+03 1.02E+04 Br-83 O.OOE+OO O.OOE+OO 4.74E+02 O.OOE+OO O.OOE+OO O~OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 5.48E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 2.53E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.98E+05 1.14E+05 O.OOE+OO O.OOE+OO O.OOE+OO 7.99E+03 Rb-88 O.OOE+OO 5.62E+02 3.66E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.72E+01 Rb-89 O.OOE+OO 3.45E+02 2.90E+02 :.O.OOE+OO O.OOE+OO O.OOE+OO 1.89E+OO Sr-89 5.99E+05 O.OOE+OO 1.72E+04 O.OOE+OO O.OOE+OO 2.16E+06 1.67E+05 Sr-90 3.85E+07 O.OOE+OO 7.66E+05 ; O.OOE+OO O.OOE+OO 1.48E+07 3.43E+05 Sr-91 1.21E+02 O.OOE+OO 4.59E+OO . O.OOE+OO O.OOE+OO 5.33E+04 1.74E+05 Sr-92 1.31E+01 O.OOE+OO 5.25E-01 I O.OOE+OO O.OOE+OO 2.40E+04 2.42E+05 Y-90 4.11E+03 O.OOE+OO 1.11E+02 O.OOE+OO O.OOE+OO 2.62E+05 2.68E+05 Y-91M 5.07E-01 O.OOE+OO 1.84E-02 O.OOE+OO O.OOE+OO 2.81E+03 1.72E+03 Y-91 9.14E+05 O.OOE+OO 2.44E+04 O.OOE+OO I 'O.OOE+OO 2.63E+06 1.84E+05 Y-92 2.04E+01 O.OOE+OO 5.81E-01

• O.OOE+OO O.OOE+OO 2.39E+04 2.39E+05 Y-93 1.86E+02 O.OOE+OO. 5.11 E+OO . O.OOE+OO O.OOE+OO 7.44E+04 3.89E+05 Zr-95 1.90E+05 4.18E+04 3.70E+04 O.OOE+OO 5.96E+04 2.23E+06 6.11E+04 Zr-97 1.88E+02 2.72E+01 1.60E+01 O.OOE+OO 3.89E+01 1.13E+05 3.51E+05 Nb-95 2.35E+04 9:18E+03 6.55E+03 O.OOE+OO 8.62E+03 6.14E+05 3.70E+04 Mo-99 O.OOE+OO 1.72E+02 4.26E+01. O.OOE+OO *3.92E+02 'f35E+05 1.27E+05 Tc- 99M 1.78E-03 3.48E-03 5.77E-02 O.OOE+OO 5.07E-02 9.51E+02 4.81E+03 Tc-101 8.10E-05 8.51E-05 1.08E-03 O.OOE+OO 1.45E-03 5.85E+02 *1.63E+01 Ru-103 2.79E+03 O.OOE+OO 1.07E+'03 . O.OOE+OO 7.03E+03 6.62E+05 '4.48E+04 Ru-105 1.53E+OO O.OOE+OO 5.55E-01 O.OOE+OO 1.34E+OO 1.59E+04 9.95E+04 Ru-106 1.36E+05 O.OOE+OO 1.69E+04 O.OOE+OO 1
• 1.84E+05 1.43E+07 4.29E+05 Ag-110M 1.69E+04 1.14E+04 9.14E+03 : O.OOE+OO 2.12E+04 5.48E+06 1.00E+05 Page 212 of 268

Revision 9 February 27, 2017 Table F-11 b (Continued) Child Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 6.73E+03 2.33E+03 9.14E+02 1.92E+03 O.OOE+OO 4.77E+05 3.38E+04 Te-127M 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 Te-127 2.77E+OO 9.51 E-01 6.11E-01 1.96E+OO 7.07E+OO 1.00E+04 5.62E+04 Te-129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 Te-129 9.77E-02 3.50E-02 2.38E-02 7.14E-02 2.57E-01 2.93E+03 2.55E+04 Te-131M 1.34E+02 5.92E+01 5.07E+01 9.77E+01 4.00E+02 2.06E+05 3.08E+05 Te-131 2.17E-02 8.44E-03 6.59E-03 1.70E-02 5.88E-02 2.05E+03 1.33E+03 Te-132 4.81E+02 2.72E+02 2.63E+02 3.17E+02 1.77E+03 3.77E+05 1.38E+05 1-130 8.18E+03 1.64E+04 8.44E+03 1.85E+06 2.45E+04 O.OOE+OO 5.11E+03 1-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 O.OOE+OO 2.84E+03 1-132 2.12E+03 4.07E+03 1.88E+03 1.94E+05 6.25E+03 O.OOE+OO 3.20E+03 1-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 O.OOE+OO 5.48E+03 1-134 1.17E+03 2.16E+03 9.95E+02 5.07E+04 3.30E+03 O.OOE+OO 9.55E+02 1-135 4.92E+03 8.73E+03 4.14E+03 7.92E+05 1.34E+04 O.OOE+OO 4.44E+03 Cs-134 6.51E+05 1.01 E+06 2.25E+05 O.OOE+OO 3.30E+05 1.21E+05 3.85E+03 Cs-136 6.51E+04 1,71E+05 1.16E+05 O.OOE+OO 9.55E+04 1.45E+04 4.18E+03 Cs-137 9.07E+05 8.25E+05 1.28E+05 O.OOE+OO 2.82E+05 1.04E+05 3.62E+03 Cs-138 6.33E+02 8.40E+02 5.55E+02 O.OOE+OO 6.22E+02 6.81E+01 2.70E+02 Ba-139 1.84E+OO 9.84E-04 5.37E-02 O.OOE+OO 8.62E-04 5.77E+03 5.77E+04 Ba-140 7.40E+04 6.48E+01 4.33E+03 O.OOE+OO 2.11E+01 1.74E+06 1.02E+05 Ba-141 1.96E-01 1.09E-04 6.36E-03 O.OOE+OO 9.47E-05 2.92E+03 2.75E+02 Ba-142 5.00E-02  : 3.60E-05 2.79E-03 O.OOE+OO 2.91E-05 1.64E+03 2.74E+OO La-140 6.44E+02 '2.25E+02 7.55E+01 O.OOE+OO O.OOE+OO 1.83E+05 2.26E+05 La-142 1.30E+OO  : 4.11 E-01 1.29E-01 O.OOE+OO O.OOE+OO 8.70E+03

• 7.59E+04 Ce-141 3.92E+04 1.95E+04 2.90!=+03 O.OOE+OO 8.55E+03 5.44E+05 5.66E+04 Ce-143 3.66E+02 .1.99E+02 2.87E+01 O.OOE+OO 8.36E+01 1.15E+05 1.27E+05 Ce-144 6.77E+06 *2.12E+06 3.61E+05 *o.OOE+OO 1.17E+06 1.20E+07 3.89E+05 Pr-143 1.85E+04
• 5.55E+03 9.14E+02 . O.OOE+OO 3.00E+03 4.33E+05 9.73E+04 Pr-144 5.96E-02  : 1.85E-02 3.00E-03 O.OOE+OO 9.77E-03 1.57E+03 1.97E+02 Nd-147 1.08E+04 ,8.73E+03 6.81E+02 O.OOE+OO 4.81E+03 3.28E+05
• 8.21E+04 W-187 1.63E+01 :9.66E+OO 4.33E+OO O.OOE+OO O.OOE+OO 4.11E+04 9.10E+04 Np-239 4.66E+02 '3.01E+02 *2.35E+01 O.OOE+OO 9.73E+01 5.81E+04 6.40E+04 Notes:

3

1) Units are mrem/yr per µCi/m .

Page 213 of 268

Revision 9 February 27, 2017 Table F-11c Infant Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LU H-3 O.OOE+OO 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.68E+02 Na-24 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 Cr-51 O.OOE+OO O.OOE+OO 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 Mn-54 O.OOE+OO 2.53E+04 4.98E+03 O.OOE+OO 4.98E+03 1.00E+06 7.06E+03 Mn-56 O.OOE+OO 1.54E+OO 2.21E-01 O.OOE+OO 1.10E+OO 1.25E+04 7.17E+04 Fe-55 1.97E+04 1.17E+04 3.33E+03 O.OOE+OO O.OOE+OO 8.69E+04 1.09E+03 Fe-59 1.36E+04 2.35E+04 9.48E+03 O.OOE+OO O.OOE+OO 1.02E+06 2.48E+04 Co-58 O.OOE+OO 1.22E+03 1.82E+03 O.OOE+OO O.OOE+OO 7.77E+05 1.11E+04 Co-60 O.OOE+OO 8.02E+03 1.18E+04 O.OOE+OO O.OOE+OO 4.51E+06 3.19E+04 Ni-63 3.39E+05 2.04E+04 1.16E+04 O.OOE+OO O.OOE+OO 2.09E+05 2.42E+03 Ni-65 2.39E+OO 2.84E-01 1.23E-01 O.OOE+OO O.OOE+OO 8.12E+03 5.01E+04 Cu-64 O.OOE+OO 1.88E+OO 7.74E-01 O.OOE+OO 3.98E+OO 9.30E+03 1.50E+04 Zn-65 1.93E+04 6.26E+04 3.11E+04 O.OOE+OO 3.25E+04 6.47E+05 5.14E+04 Zn-69 5.39E-02

• 9.67E-02 7.18E-03 O.OOE+OO 4.02E-02 1.47E+03 1.32E+04 Br-83 O.OOE+OO O.OOE+OO 3.81E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 4.00E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 2.04E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.90E+05 8.82E+04 O.OOE+OO O.OOE+OO O.OOE+OO 3.04E+03 Rb-88 O.OOE+OO 5.57E+02 2.87E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.39E+02 Rb-89 O.OOE+OO
• 3.21E+02 2.06E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.82E+01 Sr-89 3.98E+05 : O.OOE+OO 1.14E+04 O.OOE+OO O.OOE+OO 2.03E+06 6.40E+04 Sr-90 1.55E+07 O.OOE+OO 3.12E+05 O.OOE+OO O.OOE+OO 1.12E+07 1.31 E+05 Sr-91 9.56E+01 O.OOE+OO 3.46E+OO O.OOE+OO O.OOE+OO 5.26E+04 7.34E+04 Sr-92 1.05E+01 O.OOE+OO 3.91 E-01 O.OOE+OO O.OOE+OO 2.38E+04 1.40E+05 Y-90 3.29E+03
• O.OOE+OO 8.82E+01 O.OOE+OO O.OOE+OO 2.69E+05 1.04E+05 Y-91M 4.0?E-01 O.OOE+OO 1.39E-02 O.OOE+OO O.OOE+OO 2.79E+03 2.35E+03 Y-91 5.88E+05
• O.OOE+OO 1.57E+04 O.OOE+OO O.OOE+OO 2.45E+06 7.03E+04 Y-92 1.64E+01 O.OOE+OO 4.61E-01 O.OOE+OO O.OOE+OO 2.45E;+04 1.27E+05 Y-93 1.50E+02 O.OOE+OO 4.07E+OO O.OOE+OO O.OOE+OO 7 ..64E+04 1.67E+05 Zr-95 1.15E+05 2.79E+04 2.03E+04 O.OOE+OO 3.11 E+04 1.75E+06 2.17E+04 Zr-97 1.50E+02 2.56E+01 1.17E+01 O.OOE+OO 2.59E+01 1.10E+05 1.40E+05 Nb-95 1.57E+04 6.43E+03 3.78E+03 O.OOE+OO 4.72E+03 4.79E+05 1.27E+04 Mo-99 O.OOE+OO 1.65E+02 3.23E+01 O.OOE+OO 2.65E+02 1.35E+05 4.87E+04 Tc-99M 1.40E-03 2.88E-03 3.72E-02 O.OOE+OO 3.11 E-02 8.11E+02 2.03E+03 Tc-101 6.51E-05 8.23E-05 8.12E-04 O.OOE+OO 9.79E-04 5.84E+02 8.44E+02 Ru-103 2.02E+03 O.OOE+OO 6.79E+02 O.OOE+OO 4.24E+03 5.52E+05
• 1.61E+04 Ru-105 1.22E+OO O.OOE+OO 4.10E-01 O.OOE+OO 8.99E-01 1.57E+04 4.84E+04 Ru-106 8.68E+04 O.OOE+OO 1.09E+04 O.OOE+OO 1.07E+05 1.16E+07 .1.64E+05 Ag-110M 9.98E+03 7.22E+03 5.00E+03 O.OOE+OO 1.09E+04 3.67E+06
• 3.30E+04 Page 214 of 268

Revision 9 February 27, 2017 Table F-11c (Continued) Infant Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 4.76E+03 1.99E+03 6.58E+02 1.62E+03 O.OOE+OO 4.47E+05 1.29E+04 Te-127M 1.67E+04 6.90E+03 2.07E+03 4.87E+03 3.75E+04 1.31E+06 2.73E+04 Te-127 2.23E+OO 9.53E-01 4.89E-01 1.85E+OO 4.86E+OO 1.03E+04 2.44E+04 Te-129M 1.41E+04 6.09E+03 2.23E+03 5.47E+03 3.18E+04 1.68E+06 6.90E+04 Te-129 7.88E-02 3.47E-02 1.88E-02 6.75E-02 1.75E-01 3.00E+03 2.63E+04 Te-131 M 1.07E+02 5.50E+01 3.63E+01 8.93E+01 2.65E+02 1.99E+05 1.19E+05 Te-131 1.74E-02 8.22E-03 5.00E-03 1.58E-02 3.99E-02 2.06E+03 8.22E+03 Te-132 3.72E+02 2.37E+02 1.76E+02 2.79E+02 1.03E+03 3.40E+05 4.41E+04 1:-130 6.36E+03 1.39E+04 5.57E+03 1.60E+06 1.53E+04 O.OOE+OO 1.99E+03 1-131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 O.OOE+OO 1.06E+03 1-132 1.69E+03 3.54E+03 1.26E+03 1.69E+05 3.95E+03 O.OOE+OO 1.90E+03 1-133 1.32E+04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 O.OOE+OO 2.16E+03 1-134 9.21E+02 1.88E+03 6.65.E+02 4.45E+04 2.09E+03 O.OOE+OO 1.29E+03 1-135 3.86E+03 . 7.60E+03 2.77E+03 6.96E+05 8.47E+03 O.OOE+OO 1.83E+03 Cs-134 3.96E+05 7.03E+05 7.45E+04 O.OOE+OO 1.90E+05 7.97E+04 1.33E+03 Cs-136 4.83E+04

• 1.35E+05 5.29E+04 O.OOE+OO 5.64E+04 1.18E+04 1.43E+03 Cs-137 5.49E+05 6.12E+05 4.55E+04 O.OOE+OO 1.72E+05 7.13E+04 1.33E+03 Cs-138 5.05E+02
• 7.81E+02 3.98E+02 O.OOE+OO 4.10E+02 6.54E+01 8.76E+02 Ba-139 1.48E+OO 9.84E-04 4.30E-02 O.OOE+OO 5.92E-04 5.95E+03 5.10E+04 Ba-140 5.60E+04 5.60E+01 2.90E+03 O.OOE+OO 1.34E+01 1.60E+06 3.84E+04 Ba-141 1.57E-01 1.08E-04 4:97E-03 O.OOE+OO 6.50E-05 2.97E+03 4.75E+03 Ba-142 3.98E-02
• 3.30E-05 1.96E-03 O.OOE+OO 1.90E-05 1.55E+03 6.93E+02 La-140 5.05E+02 2.00E+02 5.15E+01 O.OOE+OO O.OOE+OO 1.68E+05 8.48E+04 La-142 1.03E+OO
• 3.77E-01 9.04E-02 O.OOE+OO O.OOE+OO 8.22E+03 . 5.95E+04 Ce-141 2.77E+04 1.67E+-04 1.99E+03 O.OOE+OO 5.25E+03 5.17E+05 2.16E+04 Ce-143 2.93E'+-02 1.93E+02 2.21 ~+01 O.OOE+OO 5.64E+01 1.16E+05 4.97E+04 Ce-144 3.19E+06
• 1.21 E+O~ 1.76E+05 O.OOE+OO 5.38E+05 9.84E+06 1.48E+05 Pr-143 1.40E+04 5.24E+03 6.99E+02 O.OOE+OO 1.97E+03 4.33E+05 3.72E+04 Pr-144 4.79E-02. 1.85E-02 2.41E-03 O.OOE+OO 6.72E-03 1.61 E+03 4.28E+03 Nd-147  ?:.94E+0,3 8:13E+O$

1

                               '           5.00E+02   O.OOE+OO *3.15E+03  3.22E+05    3.12E+04 W-187        1.30E+0,1 : 9.02E+OO    3.12E+OO   O.OOE+OO  O.OOE+OO  3.96E+04    3.56E+04 Np-239       3.71E+02 : .2.98E+02    1.88E+01   O.OOE+OO  6.62E+01  5.95E+04    2.49E+04 Notes:

3

1) Units are mrem/yr per µCi/m .

Page 215 of 268

Revision 9 February 27, 2017 Table F-12 Adult Vegetation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.29E+03 1.29E+03 1.29E+03 1.29E+03 1.29E+03 1.29E+03 Na-24 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 Cr-51 O.OOE+OO O.OOE+OO 4.64E+04 2.77E+04 1.02E+04 6.15E+04 1.17E+07 Mn-54 O.OOE+OO 3.13E+08 5.97E+07 O.OOE+OO 9.31E+07 O.OOE+OO 9.58E+08 Mn-56 O.OOE+OO 1.54E+01 2.73E+OO O.OOE+OO 1.95E+01 O.OOE+OO 4.91E+02 Fe-55 2.10E+08 1.45E+08 3.38E+07 O.OOE+OO O.OOE+OO 8.08E+07 8.31E+07 Fe-59 1.26E+08 2.96E+08 1.13E+08 O.OOE+OO O.OOE+OO 8.27E+07 9.87E+08 Co-58 O.OOE+OO 3.08E+07 6.90E+07 O.OOE+OO O.OOE+OO O.OOE+OO 6.24E+08 Co-60 O.OOE+OO 1.67E+08 3.69E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.14E+09 Ni-63 1.04E+10 7.21E+08 3.49E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.50E+08 Ni-65 5.97E+01 7.75E+OO 3.54E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.97E+02 Cu-64 O.OOE+OO 9.09E+03 4.27E+03 O.OOE+OO 2.29E+04 O.OOE+OO 7.75E+05 Zn-65 3.17E+08 1.01E+09 4.56E+08 O.OOE+OO 6.75E+08 O.OOE+OO 6.36E+08 Zn-69 4.95E-06 9.48E-06 '6.59E-07 O.OOE+OO 6.16E-06 O.OOE+OO 1.42E-06 Br-83 . O.OOE+OO O.OOE+OO 3.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.32E+OO Br-84 O.OOE+OO O.OOE+OO 2.20E-11 O.OOE+OO O.OOE+OO O.OOE+OO 1.72E-16 Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO -0.00E+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.20E-t:08 1.03E+08 O.OOE+OO O.OOE+OO O.OOE+OO 4.34E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89

• O.OOE+OO O.OOE+.oo O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 9.95E+09 O.OOE+OO 2.86E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.60E+09 Sr-90 6.95E+11 O.OOE+OO 1.40E+10 O.OOE+OO .O.OOE+OO O.OOE+OO 1.75E+10 Sr-91
• 3.01E+05 O.OOE-+:00 1.22E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.43E+06 Sr-92 4.12E+02 O.OOE+.00 1.78E+01 O.OOE+OO *o.OOE+OO O.OOE+OO 8.17E+03 Y-90 ' I 1.33E+04 O.OOE+oo 3.57E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.41 E+OB Y-91M 4.~3E-09 O.OOE-t'.00 1.91E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.45E-08 Y-91
• 5.12E+06 O.OOE-+:00 1.37E+05 O.OOE+OO O.OOE+OO O.OOE+OO 2.82E+09 Y-92 . 8.95E-01 O.OOE+OO 2.62E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.57E+04 Y-93  : 1.67E+02 O.OOE+OO 4.62E+OO
• O.OOE+OO O.OOE+OO O.OOE+OO 5.31E+06 Zr-95 1.18E+06 3.77E+.05 2.55E+05 O.OOE+OO .5.92E+05 O.OOE+OO 1.20E+09 Zr-97 . 3.35E+02 6.77E+01 3.09E+01 O.OOE+OO 1.02E+02 O.OOE+OO 2.10E+07 Nb-95 . 1.43E+05 7.95E+04 4.27E+04 O.OOE+OO 7.86E+04 O.OOE+OO 4.83E+08 Mo-99 O.OOE+OO 6.1'4E+06 1.17E+06 O.OOE+OO 1.39E+07 O.OOE+OO 1.42E+07 Tc- 99M
• 3.06E+OO 8.64E+.oo 1.10E+02 O.OOE+OO '1.31E+02 4.23E+OO 5.11E+03 Tc-101 O.OOE+OO O.OOE-1;'00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 4.77E+06 O.OOE+OO 2.05E+06 O.OOE+OO 1.82E+07 O.OOE+OO 5.57E:t08 Ru-105 5.27E+01 O.OOE+OO 2.08E+01 O.OOE+OO :6.81E+02 O:OOE+OO 3.23E+04 Ru-106 1.93E+08 O.OOE~OO 2.44E+07 O.OOE+OO 3.72E+08 O.OOE+OO 1.25E+10 Ag-110M 1.05E+07 9.75E+06 5.79E+06 O.OOE+OO *1.92E+07 O.OOE+OO 3.98E+09 Page 216 of 268

Revision 9 February27, 2017 Table F-12 (Continued) Adult Vegetation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 9.67E+07 3.50E+07 1.30E+07 2.91E+07 3.93E+08 O.OOE+OO 3.86E+08 Te-127M 3.49E+08 1.25E+08 4.26E+07 8.92E+07 1.42E+09 O.OOE+OO 1.17E+09 Te-127 5.68E+03 2.04E+03 1.23E+03 4.21E+03 2.31E+04 O.OOE+OO 4.48E+05 Te-129M 2.51E+08 9.37E+07 3.97E+07 8.62E+07 1.05E+09 O.OOE+OO 1.26E+09 Te-129 7.14E-04 2.68E-04 1.74E-04 5.48E-04 3.00E-03 O.OOE+OO 5.39E-04 Te-131 M 9.09E+05 4.45E+05 3.71E+05 7.04E+05 4.50E+06 O.OOE+OO 4.41E+07 Te-131 1.26E-15 5.26E-16 3.97E-16 1.03E-15 5.51E-15 O.OOE+OO 1.78E-16 Te-132 4.28E+06 2.77E+06 2.60E+06 3.06E+06 2.67E+07 O.OOE+OO 1.31 E+08 1-130 3.89E+05 1.15E+06 4.52E+05 9.72E+07 1.79E+06 O.OOE+OO 9.87E+05 1-131 8.07E+07 1.15E+08 6.62E+07 3.78E+10 1.98E+08 O.OOE+OO 3.05E+07 1-132 5.58E+01 1.49E+02 5.22E+01 5.22E+03 2.38E+02 O.OOE+OO 2.80E+01 1-133 2.08E+06 3.62E+06 1.10E+06 5.32E+08 6.31E+06 O.OOE+OO 3.25E+06 1-134 8.55E-05 2.32E-04 8.31E-05 4.02E-03 3.69E-04 O.OOE+OO 2.02E-07 l-'135 3.87E+04 1.01E+05 3.74E+04 6.68E+06 1.62E+05 O.OOE+OO 1.14E+05 Cs-134 4.67E+09 1.11E+10 9.08E+09 O.OOE+OO 3.59E+09 1.19E+09 1.94E+08 Cs-136 4:25E+07 1.68E+08 1.21 E+08 O.OOE+OO 9.33E+07 1.28E+07 1.90E+07 Cs-137 6.36E+09 8.70E+09 5.70E+09 O.OOE+OO 2.95E+09 9.81E+08 1.68E+08 Cs-138 3.32E-11 6.56E-11 3.25E-11 O.OOE+OO 4.82E-11 4.76E-12 2.80E-16 Ba-139 2.71E-02 1.93E-05 7.92E-04 O.OOE+OO 1.80E-05 1.09E-05 4.80E-02 Ba-140 1.29E+08 1.61 E+05 8.42E+06 O.OOE+OO 5.49E+04 9.24E+04 2.65E+08 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 1.98E+03 9.97E+02 2.63E+02 O.OOE+OO O.OOE+OO O.OOE+OO 7.32E+07 La-142 1.94E-04 8.83E.:.05 2.20E-05 O.OOE+OO 'O.OOE+OO O.OOE+OO 6.45E-01 Ce-141 1.97E-i'.05 1.33E+05 1:51 E+04 O.OOE+OO 6.19E+04 O.OOE+OO 5.09E+08 Ce-143 9~94E+02 7.35E+05 8.13E+01 O.OOE+OO 3.24E+02 O.OOE+OO 2.75E+07 Ce-144 3.29E+07 1.38E+07 1.77E+06 O.OOE+OO 8.16E+06 O.OOE+OO 1.11E+10 Pr-143 ,6.27E+04 2.51E+04 :3.11E+03 O.OOE+OO 1.45E+04 O.OOE+OO 2.75E+08 Pr-144' Q.OOE+OO O.OOE-+'00 O.OOE+OO O.OOE-f,00 O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 3.37E+04 3.90E+04 2.33E+03 O.OOE+OO 2.28E+04 O.OOE+OO 1.87E+08 W-187. 3.79E+04 3.17E+04 1.11E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.04E+07 Np-239 1.42E+03 1.40E+02 7.72E+01 *o.OOE+OO 4.37E+02 O.OOE+OO 2.87E+07 Notes: 2

1) Units are m mrem/yr per µCi/sec with the exception of H-3.

2) For H-3, the units are mrem/yr per µCi/m 3 .

Page 217 of 268

I I Revision 9 February 27, 2017 I Table F-12a Teen Vegetation Dose Factors Nuclide Bone Liver TBody Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.47E+03 1.47E+03 1.47E+03 1.47E+03 1.47E+03 1.47E+03 Na-24 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 Cr-51 O.OOE+OO O.OOE+OO 6.16E+04 3.42E+04 1.35E+04 8.79E+04 1.03E+07 Mn-54 O.OOE+OO 4.54E+08 9.01E+07 O.OOE+OO 1.36E+08 O.OOE+OO 9.32E+08 Mn-56 O.OOE+OO 1.39E+01 2.47E+OO O.OOE+OO 1.76E+01 O.OOE+OO 9.13E+02 Fe-55 3.26E+08 2.31E+08 5.39E+07 O.OOE+OO O.OOE+OO 1.47E+08 1.00E+08 Fe-59 1.79E+08 4.18E+08 1.61E+08 O.OOE+OO O.OOE+OO 1.32E+08 9.89E+08 Co-58 O.OOE+OO 4.37E+07 . 1.01E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.02E+08 Co-60 O.OOE+OO 2.49E+08 5.60E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.24E+09 Ni-63 1.61E+10 1.13E+09 5.45E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.81E+08 Ni-65 5.55E+01 7.10E+OO 3.23E+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.85E+02 Cu-64 O.OOE+OO 8.24E+03 3.87E+03 O.OOE+OO 2.08E+04 O.OOE+OO 6.39E+05 Zn-65 4.24E+08 1.47E+09 6.86E+08 . O.OOE+OO 9.41E+08 O.OOE+OO

• 6:23E+08 Zn-69 4.64E-06 8.84E-06 6.19E-07 O.OOE+OO 5.78E-06 O.OOE+OO 1.63E-05 Br-83 O.OOE+OO O.OOE+OO 2.81E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 2.00E-11 O.OOE+OO
• O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.75E+08 1.29E+08 O.OOE+OO O.OOE+OO O.OOE+OO 4.06E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO . O.OOE+OO Sr.,89 1.51E+10 O.OOE+OO 4.33E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.80E+09 Sr-90 9.22E+11 O.OOE+OO 1.84E+10 O.OOE+OO O.OOE+OO O.OOE+OO 2.11E+10 Sr-91 2.81E+05 O.OOE+OO 1.12E+04
• O.OOE+OO O.OOE+OO O.OOE+OO 1.27E+06 Sr-92 3.84E+02 O.OOE+OO 1.64E+01
• O.OOE+OO O.OOE+OO O.OOE+OO 9.78E+03 Y-90
• 1.24E+04 O.OOE+OO 3.35E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E+08 Y-91M 4:59E.:09 O.OOE+OO : 1.75E-10 O.OOE+OO
• O.OOE+OO O.OOE+OO -- 2.17E-07 Y-91 7.84E+06
• O.OOE+OO 2.10E+05 O.OOE+OO O.OOE+OO O.OOE+OO 3.21E+09 Y-92 8:41 E-01 O.OOE+OO
• 2.43E-02 -0.00E+OO O.OOE+OO O.OOE+OO 2.31E+04 Y-93 1.57E+02 O.OOE+OO : 4.30E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.80E+06 Zr-95 1.72E+06 5.44E+05 3.74E+Oq O.OOE+OO 7.99E+05 O.OOE+OO 1.26E+09 Zr-97 3.10E+02 6.14E+01
• 2.83E+01.. O.OOE+OO
• 9.31E+01 O.OOE+OO 1.66E+07 Nb-95 1.93E+05 1.07E+05 5.90E+04 O.OOE+OO 1.04E+05 O.OOE+OO 4.58E+08 Mo-99 O.OOE+OO 5.63E+06, 1.07E+06 O.OOE+OO 1.29E+07 O.OOE+OO 1.01E+07 Tc-99M 2.70E+OO 7.52E+OO -9.75E+01 'O.OOE+OO 1.12E+02 4.17E+OO 4.94E+03 1

Tc-101 O.OOE+OO O.OOE+OO. O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0. 00E+OO Ru-103 6.82E+06 O.OOE+OO

• 2.91E+Oq 10.00E+OO 2.40E+07 O.OOE+OO 5.69E+08 Ru-105 4.90E+01 O.OOE+OO 1.90E+01 *0.00E+OQ 6.18E+02 O.OOE+OO 3.95E+04 Ru-106 3.09E+08 O.OOE+OO 3.90E+O~ O.OOE+OO 5.97E+08 O.OOE+OO 1.48E+10 Ag-110M 1.52E+07 1.44E+07 8.73E+06 O.OOE+OO 2.74E+07 O.OOE+OO 4.03E+09 Page 218 of 268 L __

Revision 9 February 27, 2017 Table F-12a (Continued) Teen Vegetation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 1.49E+08 5.35E+07 1.99E+07 4.15E+07 O.OOE+OO O.OOE+OO 4.38E+08 Te-127M 5.51E+08 1.96E+08 6.56E+07 1.31 E+08 2.24E+09 O.OOE+OO 1.37E+09 Te-127 5.36E+03 1.90E+03 1.15E+03 3.70E+03 2.17E+04 O.OOE+OO 4.14E+05 Te-129M 3.61E+08 1.34E+08 5.72E+07 1.17E+08 1.51 E+09 O.OOE+OO 1.36E+09 Te-129 6.68E-04 2.49E-04 1.63E-04 4.77E-04 2.80E-03 O.OOE+OO 3.65E-03 Te-131M 8.42E+05 4.04E+05 3.37E+05 6.07E+05 4.21E+06 O.OOE+OO 3.24E+07 Te-131 1.17E-15 4.82E-16 3.66E-16 9.01E-16 5.11E-15 O.OOE+OO 9.60E-17 Te-132 3.89E+06 2.46E+06 2.32E+06 2.60E+06 2.36E+07 O.OOE+OO 7.81E+07 1-130 3.47E+05 1.01 E+06 4.01E+05 8.20E+07 1.55E+06 O.OOE+OO 7.73E+05 1-131 7.68E+07 1.08E+08 5.78E+07 3.14E+10 t.85E+08 O.OOE+OO 2.13E+07 1-132 5.03E+01 1.32E+02 4.72E+01 4.43E+03 2.07E+02 O.OOE+OO 5.73E+01 1-133 1.93E+06 3.28E+06 1.00E+06 4.58E+08 , 5.75E+06 O.OOE+OO 2.48E+06 1-134 7.73E-05 2.05E-04 7.36E-05 3.41E-03 3.23E-04 O.OOE+OO 2.70E-06 1-135 3.49E+04 8.99E+04 3.33E+04 5.78E+06  : 1.42E+05 O.OOE+OO 9.97E+04 Cs-134 7.10E+09 1.67E+10 7.75E+09 O.OOE+OO 5.31E+09 2.03E+09 2.08E+08 Cs-136 4.35E+07 1.71 E+08 1.15E+08 . O.OOE+OO *9.31E+07 1.47E+07 1.38E+07 Cs-.137 1.01 E+10 1.35E+10 4.69E+09 :o.OOE+OO .4.59E+09 1.78E+09 1.92E+08 Cs-138 3.07E-11 5.89E-11 2.94E-11 O.OOE+OO 4.35E-11 5.06E-12 2.67E-14 Ba-139 2'.55E-02 1.79E-05 7.42E-04 O.OOE+OO 1.69E-05 1.23E-05 2.27E-01 Ba-140 1.38E+08 1.69E+05 8.90E+06 O.OOE+OO 5.74E+04 1.14E+05 2.13E+08 Ba-141 O.,OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 1.81E+03 8.88E+02 2.36E+02 O.OOE+OO O.OOE+OO O.OOE+OO 5.10E+07 La-142 1.78E-04 7.92E-05 1.97E-05 .O.OOE+OO O.OOE+OO O.OOE+OO 2.41E+OO Ce-141 2.83E+05 1.89E+05 2.17E+04

• O.OOE+OO 8.89E+04 O.OOE+OO 5.40E+08 Ce-143 9. 29E+02 1

6.76E+05 7.55E+01  : O.OOE+OO 3.03E+02 O.OOE+OO 2.03E+07 Ce-144 5.27E+07 2.18E+07 '2.83E+06 . O.OOE+OO 1.30E+07 O.OOE+OO 1.33E+10 Pr-143 7.01E+04 2.80E+04 3.49E+03  : O.OOE+OO 1.63E+04 *O.OOE+OO 2.31E+08 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO b.OOE+OO Nd-147 3:67E.f.04 4.00E+04 2.39E+03 O.OOE+OO *2.35E+04 O.OOE+OO 1.44E+08 W-187 3.53E+04 2.87E+04 1.01 E+04 . O,OOE+OO O.OOE+OO O.OOE+OO 7.78E+06 Np-239 1.'38E+03 1'.30E+02 7.24E+01 O.OOE+OO 4.09E+02 O.OOE+OO 2.10E+07 Notes: 2

1) Units are m mrem/yr per µCi/sec with the exception of H-3.

3

2) For H-3, the units are mrem/yr per µCi/m .

Page 219 of 268

Revision 9 February27, 2017 Table F-12b Child Vegetation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 2.29E+03 2.29E+03 2.29E+03 2.29E+03 2.29E+03 2.29E+03 Na-24 3.73E+05 3.73E+05 3.73E+05 3.73E+05 3.73E+05 3.73E+05 3.73E+05 Cr-51 O.OOE+OO O.OOE+OO 1.17E+05 6.49E+04 1.77E+04 1.18E+05 6.20E+06 Mn-54 O.OOE+OO 6.65E+08 1.77E+08 O.OOE+OO 1.86E+08 O.OOE+OO 5.58E+08 Mn-56 O.OOE+OO 1.82E+01 4.10E+OO O.OOE+OO 2.20E+01 O.OOE+OO 2.63E+03 Fe-55 8.01E+08 4.25E+08 1.32E+08 O.OOE+OO O.OOE+OO 2.40E+08 7.87E+07 Fe-59 3.97E+08 6.42E+08 3.20E+08 O.OOE+OO O.OOE+OO 1.86E+08 6.69E+08 Co-58 0.00E+OO 6.45E+07 1.97E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.76E+08 Co-60 O.OOE+OO 3.78E+08 1.12E+09 O.OOE+OO O.OOE+OO O.OOE+OO 2.10E+09 Ni-63 3.95E+10 2.11E+09 1.34E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.42E+08 Ni-65 1.02E+:02 9.59E+OO 5.60E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.18E+03 Cu-64 O.OOE+OO 1.09E+04 :6.56E+03 O.OOE+OO 2.62E+04 O.OOE+OO 5.10E+05 Zn-65 8.12E+08 2.16E+09 1.35E+09 O.OOE+OO 1.36E+09 O.OOE+OO 3.80E+08 Zn-69 a.56E.:o6 1.24E-05 1.14E-06 O.OOE+OO 7.50E-06 O.OOE+OO 7.80E-04 Br-83 O.OOE+OO O.OOE+OO 5 ..18E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 3.39E-11 O.OOE+OO *o.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 4.54E+08 2.79E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.92E+07 Rb-88 O.OOE+OO O.OOE+OO .'O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO :*O.QOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 3.59E+10 O.OOE+OO .1.03E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.39E+09 Sr-90 1.87E+12 O.OOE+OO '3.77E+10 O.OOE+OO O.OOE+OO O.OOE+OO 1.67E+10 Sr-91 5.17E+05 O.OOE+OO :1.95E+04 O.OOE+OO .O.OOE+OO O.OOE+OO 1.14E+06 Sr-92 7.04E+02 O:OOE+OO *:2.82E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.33E+04 Y-90 2.31E+04 O.OOE+OO 6.18E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.57E+07 Y-91M 8.42E-09 O.OOE+OO *I 3.06E-10 O.OOE+OO *o,OOE+OO O.OOE+OO 1.65E-05 Y-91 1.87E+07 O.OOE+OO 4.99E+05 O.OOE+OO O.OOE+OO O.OOE+OO 2.49E+09 Y-92

• 1.55E+OO O.OOE+OO 4.43E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.47E+04 Y-93 2.89E+02 O.OOE+OO 7.94E+OO O.OOE+OO :o.OOE+OO O.OOE+OO 4.31E+06 Zr-95 3.86E+06 8.50E+05 7.56E+05 O.OOE+OO : 1.22E+06 O.OOE+OO 8.86E+08 Zr-97 5.67E+02 8.19E+01 4.~3E+01 O.OOE+OO **1.18E+02 O.OOE+OO 1.24E+07 Nb-95 4.12E+05 1.61E+05 . 1.15E+05 O.OOE+OO 1.51 E+05 O.OOE+OO 2.97E+08 Mo-99 O.OOE+OO 7.69E+06 1.90E+06 O.OOE+OO 1.64E+07 O.OOE+OO 6.36E+06 Tc- 99M 4.64E+OO 9.10E+OO 1.51 E+02 O.OOE+OO 1.32E+02 4.62E+OO 5.18E+03 Tc-101 O.OOE+OO O.OOE+OO 'O.OOE+OO O.OOE+OO . O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 1.53E+07 O.OOE+OO '.5.89E+06 O.OOE+OO *.3.86E+07 O.OOE+OO 3.96E+08 Ru-105 8.97E+01 O.OOE+OO 3.25E+01 O.OOE+OO . 7.89E+02 O.OOE+OO 5.86E+04 Ru-106 7.45E+08 O.OOE+OO *:9.30E+07 O.OOE+OO 1.01E+09 O.OOE+OO 1.16E+10 Ag-110M 3.21E+07 2.17E+07 1..74E+07 O.OOE+OO 4.04E+07 O.OOE+OO 2.58E+09 Page 220 of 268

Revision 9 February 27, 2017 Table F-12b (Continued) Child Vegetation Dose Factors Nuclide Bone Liver TBody Thyroid Kidney Lung Gl-LLI Te-125M 3.51E+08 9.52E+07 4.68E+07 9.86E+07 O.OOE+OO O.OOE+OO 3.39E+08 Te-127M 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 O.OOE+OO 1.07E+09 Te-127 9.89E+03 2.67E+03 2.12E+03 6.84E+03 2.81E+04 O.OOE+OO 3.86E+05 Te-129M 8.40E+08 2.35E+08 1.30E+08 2.71E+08 2.47E+09 O.OOE+OO 1.02E+09 Te-129 1.24E-03 3.45E-04 2.94E-04 8.83E-04 3.62E-03 O.OOE+OO 7.70E-02 Te-131M 1.54E+06 5.32E+05 5.66E+05 1.09E+06 5.15E+06 O.OOE+OO 2.16E+07 Te-131 2.15E-15 6.57E-16 6.41E-16 1.65E-15 6.51E-15 O.OOE+OO 1.13E-14 Te-132 6.97E+06 3.09E+06 3.73E+06 4.49E+06 2.86E+07 O.OOE+OO 3.11E+07 1-130 6.10E+05 1.23E+06 6.35E+05 1.36E+08 1.84E+06 O.OOE+OO 5.76E+05 1-131 1.43E+08 1.44E+08 8.17E+07 4.75E+10 2.36E+08 O.OOE+OO 1.28E+07 1-132 8.93E+01 1.64E+02 7.54E+01 7.61E+03 2.51E+02 O.OOE+OO 1.93E+02 1-133 3.52E+06 4.36E+06 1.65E+06 8.09E+08 7.26E+06 O.OOE+OO 1.76E+06 1-134 1'.37E-04 2.55E-04 1.FE-04 5.86E-03 3.90E-04 O.OOE+OO 1.69E-04 1-135 6.20E+04 1.12E+05 5.28E+04 9.89E+06 1.71E+05 O.OOE+OO 8.51E+04 Cs-134 1.60E+10 2.63E+10 5.55E+09 O.OOE+OO 8.16E+09 2.93E+09 1.42E+08 Cs-136 8.18E+07 2.25E+08 1.46E+08 O.OOE+OO 1.20E+08 1.79E+07. 7.90E+06 Cs-137 2.39E+10 2.29E+10 3.38E+09 O.OOE+OO 7.46E+09 2.68E+09 1.43E+08 Cs-138 5.58E-11 7.75E-11 4.92E-11 O.OOE+OO 5.45E-11 5.87E-12 3.57E-11 Ba-139 4.69E-02 2.51 E-05 1.36E-03 O.OOE+OO :2.19E-05 1.47E-05 2.71E+OO Ba-140 2.77E+08 2.43E+05 1.62E+07 .O.OOE+OO 7.90E+04 1.45E+05 1.40E+08 1;3a-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O,OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 3.25E+03 1.13E+03 3.82E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.16E+07 La-142 3.23E-04 1.03E-04 3.22E-'05 O.OOE+OO O.OOE+OO O.OOE+OO 2.04E+01 Ce-141 6.55E+05 3.27E+05 4.85E+04 O.OOE+OO ,1.43E+05 O.OOE+OO 4.08E+08 Ce-143 1.71E+03 9.28E+05 1:34E+02 O.OOE+OO 3.89E+02 O.OOE+OO '1.36E+07 Ce-144 1.27E+08 3.98E+07 6,,78E+06 O.OOE+OO 2.21E+07 O.OOE+OO 1.04E+10 pr-143 1.46E+05 4.38E+04 7~24E+03 O.OOE+OO 2.37E+04 O.OOE+OO . 1.57E+08 Pr-144 o:ooE+oo O.OOE+OO O:OOEtOO O.OOE+OO .O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 7.27E+04 5:89E+04 4.56E+03 O.OOE+OO 3.23E+04 O.OOE+OO 9.33E+07 W-187 6.41E+04 3.80E+04 1.70E+04 O.OOE+OO O.OOE+OO O.OOE+OO 5.34E+06 Np-239 2.55E+03 1.83E+02 1:29E+02 O.OOE+OO 5.30E+02

• O.OOE+OO 1.36E+07 Notes:

2

1) Units are m mrem/yr per µCi/sec with the exception of H-3.

3

2) For H-3, the units are mrem/yr per µCi/m .

3) The infant age group is assumed to receive no due through the vegetation ingestion pathway therefore no dose factors are supplied.

Page 221 of 268 I _- _

Revision 9 February27, 2017 Table F-13 Adult Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 4.35E+02 4.35E+02 4.35E+02 4.35E+02 4.35E+02 4.35E+02 Na-24 2.46E+06 2.46E+06 2.46E+06 2.46E+06 2.46E+06 2.46E+06 2.46E+06 Cr-51 O.OOE+OO O.OOE+OO 2.86E+04 1.71 E+04 6.29E+03 3.79E+04 7.18E+06 Mn-54 O.OOE+OO 8.41E+06 1.61 E+06 O.OOE+OO 2.50E+06 O.OOE+OO 2.58E+07 Mn-56 O.OOE+OO 4.13E-03 7.32E-04 O.OOE+OO 5.24E-03 O.OOE+OO 1.32E-01 Fe-55 2.51E+07 1.74E+07 4.05E+06 O.OOE+OO O.OOE+OO 9.68E+06 9.95E+06 Fe-59 2.97E+07 6.98E+07 2.67E+07 O.OOE+OO O.OOE+OO 1.95E+07 2.33E+08 Co-58 O.OOE+OO 4.72E+06 1.06E+07 O.OOE+OO O.OOE+OO O.OOE+OO 9.56E+07 Co-60 O.OOE+OO 1.64E+07 3.62E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.08E+08 Ni-63 6.73E+09 4.66E+08 2.26E+08 O.OOE+OO O.OOE+OO O.OOE+OO 9.73E+07 Ni-65 3.70E-01 4.81 E-02 2.19E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.22E+OO Cu-64 O.OOE+OO 2.36E+04 1.11E+04 O.OOE+OO 5.95E+04 O.OOE+OO 2.01E+06 Zn-65 1.37E+09 4.36E+09 1.97E+09 O.OOE+OO 2.92E+09 O.OOE+OO 2.75E+09 Zn-69 2.01 E-12 3.84E-12 2.67E-13 O.OOE+OO 2.50E-12 O.OOE+OO 5.78E-13 Br-83 O.OOE+OO O.OOE+OO 9.65E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.39E-01 Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.60E+09 1.21E+09 O.OOE+OO O.OOE+OO O.OOE+OO 5.12E+08 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO R.b-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 1.45E+09 O.OOE+OO 4.16E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.33E+08 Sr-90 5.38E+10 .O.OOE+OO 1.08E+09 O.OOE+OO : O.OOE+OO O.OOE+OO 1.35E+09 Sr-91 2 ..87E+04 O.OOE+OO 1.16E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.37E+05 Sr-92 4;84E-01 O.OOE+oo 2.09E-02 O.OOE+OO *O.OOE+OO d.OOE+OO 9.58E+OO Y-90 7.10E+01 . O.OOE+OO 1.90E+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.52E+05 Y-91M 6.42E-20 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.89E-19 Y-91 8.59E+03 . O.OOE+OO 2.30E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.73E+06 Y-94 5:57E-05 O.OOE+OO 1.63E-06 O.OOE+OO O.OOE+OO O.OOE+OO 9.75E-01 Y-93 2.22E-01 O.OOE+OO 6.12E-03 O.OOE+OO O.OOE+OO O.OOE+OO 7.03E+03 Zr-95 9.44E+02 3.03E+02 2.05E+02 O.OOE+OO. 4.75E+02 O.OOE+OO 9.59E+05 Zr-97 4'.32E~01 :8.72E-02 3.99E-02 O.OOE+OO 1.32E-01 O.OOE+OO 2.70E+04 Nb-95 8.26E+04 4.60E+04 2.47E+04 O.OOE+OO '*4.54E+04 O.OOE+OO 2.79E+08 Mo-99 O.OOE+OO 2.47E+07 4.70E+06 O.OOE+OO 5.60E+07 O.OOE+OO 5.73E+.07 Tc- 99M 3.'31E+OO 9.35E+OO 1.19E+02 *o.OOE+OO 1.42E+02 4.58E+OO 5.53E+03 Tc-101 O.*OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 1.02E+03 O.OOE+OO 4.39E+02 O.OOE+OO 3.88E+03 O.OOE+OO 1.19E+05 Ru-105 8.51E-04 O.OOE+OO 3.36E-04 O.OOE+OO 1.10E-02 O.OOE+OO 5.20E-01 Ru-106 2.04E+04 O.OOE+OO 2.58E+03 O.OOE+OO 3.94E+04 O.OOE+OO 1.32E:t-06 Ag-110M 5.82E+07 5.39E+07 3.20E+07 O.OOE+OO 1.06E+08 O.OOE+OO 2.20E+10 Page 222 of 268

Revision 9 February 27, 2017 Table F-13 (Continued) Adult Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 1.63E+07 5.91E+06 2.18E+06 4.90E+06 6.63E+07 O.OOE+OO 6.51E+07 Te-127M 4.58E+07 1.64E+07 5.58E+06 1.17E+07 1.86E+08 O.OOE+OO 1.54E+08 Te-127 6.66E+02 2.39E+02 1.44E+02 4.94E+02 2.71E+03 O.OOE+OO 5.26E+04 Te-129M 6.02E+07 2.24E+07 9.52E+06 2.07E+07 2.51E+08 O.OOE+OO 3.03E+08 Te-129 2.83E-10 1.06E-10 6.88E-11 2.17E-10 1.19E-09 O.OOE+OO 2.13E-10 Te-131 M 3.61E+05 1.76E+05 1.47E+05 2.79E+05 1.79E+06 O.OOE+OO 1.75E+07 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 2.39E+06 1.55E+06 1.45E+06 1.71 E+06 1.49E+07 O.OOE+OO 7.32E+07 1-130 4.18E+05 1.23E+06 4.86E+05 1.04E+08 1.92E+06 O.OOE+OO 1.06E+06 1-131 2.96E+08 4.23E+08 2.43E+08 1.39E+11 7.26E+08 O.OOE+OO 1.12E+08 1-132 1.65E-01; 4.40E-01 1.54E-01 1.54E+01 7.02E-01 O.OOE+OO 8.27E-02 1-133 3.88E+06 6.74E+06' 2.06E+06 9.91E+08 1.18E+07 O.OOE+OO 6.06E+06 1-134 1.89E-12 5.13E-12 1.83E-12 8.89E-11 8.16E-12 O.OOE+OO 4.47E-15 1-135 1.29E+04 3.38E+04 1.25E+04 2.23E+06 5.42E+04 O.OOE+OO 3.82E+04 Cs-134 5.65E+09 1.35E+10 1.10E+10 O.OOE+OO 4.35E+09 1.45E+09 2.35E+08 Cs-136 2.63E+08 1.04E+09 7.46E+08 O.OOE+OO 5.77E+08 7.91E+07 1.18E+08 Cs-137 7.38E+09 1.01E+10 6.61E+09 O.OOE+OO 3.43E+09 1.14E+09 1.95E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 4.43E-08

• 3.16E-11 1.30E-09 O.OOE+OO 2.95E-11 1.79E-11 7.86E-08 Ba-140. 2.69E+07 3.38E+04 1.76E+06 O.OOE+OO 1.15E+04 1.93E+04 5.54E+07 Ba-141
• O.OOE+OO O.OOE+OO . O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 4.52E+OO 2.28E+OO 6.02E-01 O.OOE+OO o:ooE+oo O.OOE+OO 1.67E+05 La-142 1.89E-11 8.59E-12
• 2.14E-12 O.OOE+OO O.OOE+OO O.OOE+OO 6.28E-08 Ce-141 4.84E+03 3.28E+03 3.72E+02 O.OOE+OO 1.52E+03 O.OOE+OO 1.25E+07 Ce-143 4.15E+01 3.07E+04 3.39E+OO O.OOE+OO
• 1:35E+01 O.OOE+OO 1.15E+06 Ce-144 . 3.58E+'05 .1.50E+05 1.92E+04 O.OOE+OO 8.87E+04 O.OOE+OO 1.21E+08 Pr-143 . 1.58E+02 6.34E+01 7.83E+OO O.OOE+OO 3.66E+01 O.OOE+OO 6.92E+05 Pr-144 O.OOE+OO O.OOE+OO
• O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 9.48E+01 1.10E+02 , 6.56E+OO O.OOE+OO 6.41E+01 O.OOE+OO 5.26E+05 W-187 6.51E+03 5.44E+03 1.90E+03 O.OOE+OO O,OOE+OO O.OOE+OO 1.78E+06 Np-239 3.67E+OO 3.61E-01 1.99E-01 O.OOE+OO 1'.12E+OO O.OOE+OO 7.40E+04 Notes:

2

1) Units are m mrem/yr per µCi/sec with the exception of H-3.

3

2) For H-3, the units are mrem/yr per µCi/m .

Page 223 of 268

Revision 9 February 27, 2017 Table F-13a Teen Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 5.66E+02 5.66E+02 5.66E+02 5.66E+02 5.66E+02 5.66E+02 Na-24 4.29E+06 4.29E+06 4.29E+06 4.29E+06 4.29E+06 4.29E+06 4.29E+06 Cr-51 O.OOE+OO O.OOE+OO 4.99E+04 2.77E+04 1.09E+04 7.12E+04 8.38E+06 Mn-54 O.OOE+OO 1.40E+07 2.78E+06 O.OOE+OO 4.18E+06 O.OOE+OO 2.87E+07 Mn-56 O.OOE+OO 7.32E-03 1.30E-03 O.OOE+OO 9.27E-03 O.OOE+OO 4.82E-01 Fe-55 4.45E+07 3.16E+07 7.36E+06 O.OOE+OO O.OOE+OO 2.00E+07 1.37E+07 Fe-59 5.18E+07 1.21E+08 4.67E+07 O.OOE+OO O.OOE+OO 3.81E+07 2.86E+08 Co-58 O.OOE+OO 7.94E+06 1.83E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.09E+08 Co-60 O.OOE+OO 2.78E+07 6.26E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.62E+08 Ni-63 1.18E+10 8.35E+08 4.01E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.33E+08 Ni-65 6.78E-01 8.66E-02 3.94E-02 O.OOE+OO O.OOE+OO O.OOE+OO :4.70E+OO Cu-64 O.OOE+OO 4.21E+04 1.98E+04 O.OOE+OO 1.06E+05 O.OOE+OO 3.26E+06 Zn-65 2.11E+09 7.31E+09 3.41E+09 O.OOE+OO 4.68E+09 O.OOE+OO 3.10E+09 Zn-69 3.70E-12 7.05E-12 4.94E-13 O.OOE+OO 4.61E-12 O.OOE+OO 1.30E-11 Br-83 O;OOE+OO O.OOE+OO 1.78E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO . O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 4.73E+09 2.22E+09 O.OOE+OO O.OOE+OO O.OOE+OO 7.01E+08 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 2.67E.+09 O.OOE+OO 7.66E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.18E+08 Sr-90 8.13E+10 O.OOE+OO 1.63E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.86E+09 Sr-91 5.27E+04 O.OOE+OO 2.10E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.39E+05 Sr-92 8.85E-01 O.OOE+OO 3.77E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.26E+01 Y-90 1.30E+02 O.OOE+OO 3.51E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.08E+06 Y-91M 1.18E-19 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.55E-18 Y-91 1.58E+04 O.OOE+OO 4.24E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.48E+06 Y-92 1.03E-04 O.OOE+OO 2.98E-06 O.OOE+OO O.OOE+OO O.OOE+OO 2.82E+OO Y-93 4.09E-01 O.OOE+OO 1.12E-02 O.OOE+OO . O.OOE+OO O.OOE+OO 1.25E+04 Zr-95 1.65E+03 5.21E+02 3.58E+02 O.OOE+OO 7.65E+02 O.OOE+OO 1.20E+06 Zr-97 7.87E-01 1.56E-01 7.17E-02 O.OOE+OO 2.36E-01 O.OOE+OO 4.22E+04 Nb-95 1.41 E+05 7.82E+Q4 4.30E+04 O.OOE+OO 7.58E+04 O.OOE+OO 3.34E+08 Mo-99 O.OOE+OO '4.46E+07 8.51E+06 O.OOE+OO 1.02E+08 O.OOE+OO 8.00E+07 Tc- 99M 5.74E+OO 1.60E+01 2.07E+02 O.OOE+OO 2.39E+02 8.89E+OO 1.05E+04 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO .O.OOE+OO O.OOE+OO Ru-103 1.81E+03 O.OOE-t;OO 7.74E+02 O.OOE+OO 6.38E+03 O.OOE+OO 1.51 E+05 Ru-105 1.55E-03 O.OOE+OO 6.03E-04 O.OOE+OO 1.96E-02 *O.OOE+OO 1.25E+OO Ru-106 3.75E+04

• O.OOE+OO 4.73E+03 *o.OOE+OO 7.24E+04 O.OOE+OO 1.80E+06 Ag-110M 9.63E+07 9.11E+07 5.54E+07 O.OOE+OO 1.74E+08 O.OOE+OO 2.56E+10 Page 224 of 268

Revision 9 February 27, 2017 Table F-13a (Continued) Teen Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 3.01E+07 1.08E+07 4.02E+06 8.40E+06 O.OOE+OO O.OOE+OO 8.87E+07 Te-127M 8.44E+07 2.99E+07 1.00E+07 2.01E+07 3.42E+08 O.OOE+OO 2.10E+08 Te-127 1.24E+03 4.38E+02 2.66E+02 8.52E+02 5.00E+03 O.OOE+OO 9.54E+04 Te-129M 1.10E+08 4.09E+07 1.74E+07 3.55E+07 4.61E+08 O.OOE+OO 4.13E+08 Te-129 5.20E-10 1.94E-10 1.27E-10 3.72E-10 2.18E-09 O.OOE+OO 2.84E-09 Te-131 M 6.57E+05 3.15E+05 2.63E+05 4.74E+05 3.28E+06 O.OOE+OO 2.53E+07 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 4.27E+06 2.71E+06 2.55E+06 2.85E+06 2.60E+07 O.OOE+OO

• 8.57E+07 1-130 7.35E+05 2.13E+06 8.49E+05 1.73E+08 3.27E+06 O.OOE+OO. 1.63E+06 1-131 5.37E+08 7.52E+08 4.04E+08 2.19E+11 1.29E+09 O.OOE+OO 1.49E+08 1-132 2.92E-01 7.64E-01 2.74E-01 2.57E+01 1.20E+OO O.OOE+OO 3.33E-01 1-133 7.08E+06 1.20E+07 3.66E+06 1.68E+09 2.11E+07 O.OOE+OO 9.09E+06 1-134 3.35E-12 8.89E-12 3.19E-12 1.48E-10 1.40E-11 O.OOE+OO 1.17E-13 1-135 2.29E+04 5.91E+04 2.19E+04 3.80E+06 9.33E+04 O.OOE+OO 6.54E+04 Cs-134 9.82E+09 2.31E+10 1.07E+10 O.OOE+OO . 7.34E+09 2.80E+09 2.87E+08 Cs-136 4.47E+08 1.76E+09 1.18E+09 O.OOE+OO 9.58E+08 1.51 E+08 1.42E+08 Cs-137 1.34E+10 1.78E+10 6.20E+09 O.OOE+OO 6.06E+09
• 2.35E+09 : 2.53E+08 Cs-138 O.OOE+OO O.OOE+OQ O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO . O.OOE+OO Ba-139 8.20E-08 5.77E-11 2.39E-09 O.OOE+OO . 5.44E-11 3.98E-11 . 7.31E-07 Ba-140 4.85E+07 5.95E+04 3.13E+06 O.OOE+OO 2.02E+.04 4.00E+04 : 7.49E+07 Ba..:141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
• O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 'O.OOE+OO La-140 8.12E+OO 3.99E+OO 1.06E+OO ,O.OOE+OO O.OOE+,00 O.OOE+OO '2.29E+05 La-142 3.41E-11 1.51E-11 3.77E-12 O.OOE+OO O.OOE+OO 'O.OOE+OO 4.61 E-07 Ce-141 8.88E+03 5.93E+03 6.81E+02 .O.OOE+OO 2.79E+03 .o.OOE+OO 1.70E+07 Ce-143 7.62E+01 *5.55E+04 6.20E+OO O.OOE+OO 2.49E+01 *O.OOE+OO , 1.67E+06 Ce-144 6,58E+05 2.72E+05 3.54E+04 .O.OOE+OO 1.63E~05 :O.OOE+OO 1.66E+08 Pr-143 2.90E+02 1.16E+02
• 1.44E+01 O.OOE+OO .'6.74E+01 ,O.OOE+OO 9.,55E+05 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO .O.OOE+OO 'O.OOE+OO :iO.OOE+OO O.OOE+OO Nd-147 1.82E+02 1.98E+02 1.19E+01  : O.OOE+OO 1.17E+02 O.OOE+OO 7.16E+05 W-187 1.19E+04 9.71E+03 3.40E+03 O.OOE+OO . O.OOE+OO *:o.OOE+OO 2.63E+06 Np-239 7.00E+OO 6.60E-01 3.67E-01 O.OOE+OO 2.07E+OO O.OOE+OO 1.06E+05 Notes:

2

1) Units are m mrem/yr per µCi/sec with the exception of H-3.

2) For H-3, the units are mrem/yr per µCi/m 3 .

Page 225 of 268

Revision 9 February 27, 2017 Table F-13b

• Child Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 8.97E+02 8.97E+02 8.97E+02 8.97E+02 8.97E+02 8.97E+02 Na-24 8.93E+06 8.93E+06 8.93E+06 8.93E+06 8.93E+06 8.93E+06 8.93E+06 Cr-51 O.OOE+OO O.OOE+OO 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5.39E+06 Mn-54 O.OOE+OO 2.10E+07 5.59E+06 O.OOE+OO 5.88E+06 O.OOE+OO 1.76E+07 Mn-56 O.OOE+OO 1.28E-02 2.88E-03 O.OOE+OO 1.54E-02 O.OOE+OO 1.85E+OO Fe-55 1.12E+08 5.93E+07 1.84E+07 O.OOE+OO O.OOE+OO 3.35E+07 1.10E+07 Fe-59 1.20E+08 1.94E+08 9.69E+07 O.OOE+OO O.OOE+OO 5.64E+07 2.02E+08 Co-58 O.OOE+OO 1.21E+07 3.71E+07 O.OOE+OO O.OOE+OO O.OOE+OO 7.08E+07 Co-60 O.OOE+OO 4.32E+07 1.27E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.39E+08 Ni-63 2.96E+10 1.59E+09 1.01E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.07E+08 Ni-65 1.66E+OO 1.56E-01 9.11 E-02 O.OOE+OO O.OOE+OO O.OOE+OO .1.91E+01 Cu-64 O.OOE+OO 7.39E+04 4.47E+04 O.OOE+OO 1.79E+05 O.OOE+OO 3.47E+06 Zn-65 4.13E+09 1.10E+10. 6.85E+09 O.OOE+OO 6.94E+09 O.OOE+OO 1.93E+09 Zn-69 9. tOE-12 1.32E-11 1.22E-12 O.OOE+OO 7.98E-12 O.OOE+OO 8.29E-10 Br-83 O.OOE+OO O.OOE+OO 4.37E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO *O.OOE+OO Rb-86 O.OOE+OO 8.78E+09 5.40E+09 O.OOE+OO O.OOE+OO O.OOE+OO 5.65E+08 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 6.62E+09 O.OOE+OO 1.89E+08 O.OOE+OO O.OOE+OO O.OOE+OO *2.56E+08 Sr-90 1.68E+11 O.OOE+OO 3.38E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.51E+09 Sr-91 1.29E+05 O.OOE+OO 4.88E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.86E+05 Sr-92 2.16E+OO O.OOE+OO 8.67E-02 O.OOE+OO. O.OOE+OO O.OOE+OO 4.09E+01 Y-90 3.23E+02 O.OOE+OO 8.64E+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.19E+05 Y-91M 2.87E-19 O.OOE+OO 1.04E-20 O.OOE+OO O.OOE+OO O.OOE+OO 5.62E-16 Y-91 3.90E+04 O.OOE+OO 1.04E+03 O.OOE+OO O.OOE+OO O.OOE+OO
• 5"20E+06 Y-92 2.53E-04 O.OOE+OO 7.23E-06 O.OOE+OO O.OOE+OO O.OOE+OO
• 7.30E+OO Y-93 t.OOE+OO O.OOE+OO 2.75E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.50E:+-04 Zr-95 3.83E+03 8,43E+02 7.50E+02 O.OOE+OO 1.21 E+03 O.OOE+OO 8.79E+05 Zr-97 1.91 E+OO 2.77E-01 ' 1.63E-01 O.OOE+OO
• 3.97E-01 O.OOE+OO 4.19E+04 Nb-95 3.18E+05 1.24E+05 8.85E+04 O.OOE+OO 1.16E+05 O.OOE+OO 2.29E+08 Mo-99 O.OOE+OO
• 8j12E+07 2.01E+07 O.OOE+OO 1.73E+08 O.OOE+OO 6.72E+07 Tc-99M 1.32E+O~ 2~58E+01 4.28E+02 O.OOE+OO 3.75E+02 1.31E+01 1.47E+04 Tc-101 O.OOE+OO O,OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 4.28E+03 o;oOEtOO 1.65E+03 O.OOE+OO 1.08E+04 O.OOE+OO 1.11E+05 Ru..:105 3.79E-03 O.OOE+OO 1.38E-03 O.OOE+OO 3.33E-02 O.OOE+OO 2.48E+OO Ru-106 9.24E+04 o:ooE+oo 1.15E+04 O.OOE+OO 1.25E+05 O.OOE+OO 1,.44E+06 Ag-110M 2.09E+08 f41E+08 1.13E+08 O.OOE+OO 2.63E+08 O.OOE+OO 1.68E+10 Page 226 of 268

Revision 9 February 27, 2017 Table F-13b (Continued) Child Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 7.38E+07 2.00E+07 9.84E+06 2.07E+07 O.OOE+OO O.OOE+OO 7.12E+07 Te-127M 2.08E+08 5.60E+07 2.47E+07 4.97E+07 5.93E+08 O.OOE+OO 1.68E+08 Te-127 3.04E+03 8.19E+02 6.51E+02 2.10E+03 8.64E+03 O.OOE+OO 1.19E+05 Te-129M 2.71E+08 7.58E+07 4.21E+07 8.75E+07 7.97E+08 O.OOE+OO 3.31E+08 Te-129 1.28E-09 3.58E-10 3.0SE-10 9.16E-10 3.75E-09 O.OOE+OO 7.99E-08 Te-131M 1.60E+06 5.53E+05 5.88E+05 1.14E+06 5.35E+06 O.OOE+OO 2.24E+07 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 1.02E+07 4.52E+06 5.46E+06 6.58E+06 4.19E+07 O.OOE+OO 4.55E+07 1-130 1.72E+06 3.47E+06 1.79E+06 3.82E+08 5.19E+06 O.OOE+OO 1.62E+06 1-131 1.30E+09 1.31E+09 7.45E+08 4.33E+11 2.15E+09 O.OOE+OO 1.17E+08 1-132 6.91E-01 127E+OO 5.84E-01 5.89E+01 1.94E+OO O.OOE+OO 1.49E+OO 1-133 1.72E+07 2.13E+07 8.05E+06 3.95E+09 3.55E+07 O.OOE+OO 8.57E+06 1-134 7.94E-12 1.47E~11 6.79E-12 3.39E-10 2.26E-11 O.OOE+OO 9.78E-12 1-135 5.43E+04 9.78E+04 4.62E+04 8.66E+06 1.50E+05 O.OOE+OO 7.45E+04 Cs-134 2.26E+10 3.72E+10 7.84E+09 O.OOE+OO 1.15E+10 4.13E+09 2*.00E+08 Cs-136 1.01 E+09 2.77E+09 1.80E+09 O.OOE+OO 1.48E+09 2.20E+08 9.75E+07 Cs-137 3.22E+10 3.09E+10 4.55E+09 O.OOE+OO 1.01E+10 3.62E+09 1.93E+08 Cs-138 . O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139

• 2.01E-07 1.08E-10 5.84E-09 O.OOE+OO 9.39E-11 6.33E-11 1.16E-05 Ba-140 . 1.17E+08 1.03E+05 6.84E+06 O.OOE+OO 3.34E+04 6.12E+04 5.94E+07 Ba-141 O'.OOE+OO O.OOE+OO ,O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 1.95E+01 6.80E4'00 '2.29E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.90E+05 La-142 8.24E-11 2.63Ec:11 8.22E-12 O.OOE+OO O.OOE+OO O.OOE+OO 5.20E-06 Ce-141 2.19E+04 1.0~E+04 1.62E+03 O.OOE+OO 4.78E+03 O.OOE+OO 1.36E+07 Ce-143 1.87E+02 1.01E+05 1.47E+01 O.OOE+OO 4.26E+01 O.OOE+OO 1.49E+06 Ce'-144 1.62E;+-06 5.09E-+:05 8.66E+.04 O.OOE+OO 2.82E+05 O.OOE+OO 1:33E+08 Pr-143 7.18E+02 2.16E+02 3.57E+01 O.OOE+OO 1.17E+02 O.OOE+OO 7,.75E+05 Pr-1'44 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 4.48E+02 3.63E+02 2.81 E+01 O.OOE+OO 1.99E+02 O.OOE+OO 5.75E+05 W-187 2.89E+04 1.71 E-+;04 7.67E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.40E+06 Np-239 1.72E+01 1.24E+oo 8.69E-01 O.OOE+OO 3.58E+OO O.OOE+OO 9.15E+04 Notes:

2

1) Units are m mrem/yr per µCi/sec with the exception of H-3.

3

2) For H-3, the units are mrem/yr per µCi/m .

Page 227 of 268

Revision 9 February 27, 2017 Table F-13c Infant Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.36E+03 1.36E+03 1.36E+03 1.36E+03 1.36E+03 1.36E+03 Na-24 1.56E+07 1.56E+07 1.56E+07 1.56E+07 1.56E+07 1.56E+07 1.56E+07 Cr-51 O.OOE+OO O.OOE+OO 1.61 E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 Mn-54 O.OOE+OO 3.90E+07 8.84E+06 O.OOE+OO 8.64E+06 O.OOE+OO 1.43E+07 Mn-56 O.OOE+OO 3.13E-02 5.39E-03 O.OOE+OO 2.69E-02 O.OOE+OO 2.84E+OO Fe-55 1.35E+08 8.73E+07 2.33E+07 O.OOE+OO O.OOE+OO 4.27E+07 1.11E+07 Fe-59 2.24E+08 3.92E+08 1.54E+08 O.OOE+OO O.OOE+OO 1.16E+08 1.87E+08 Co-58 O.OOE+OO 2.43E+07 6.05E+07 O.OOE+OO O.OOE+OO O.OOE+OO 6.04E+07 Co-60 O.OOE+OO 8.82E+07 2.08E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.10E+08 Ni-63 3.49E+10 2.16E+09 1.21 E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.07E+08 Ni-65 3.51E+OO 3.97E-01 1.81 E-01 O.OOE+OO O.OOE+OO O.OOE+OO 3.02E+01 Cu-64 O.OOE+OO 1.84E+05 8.51E+04 O.OOE+OO 3.11E+05 O.OOE+OO 3.77E+06 Zn-65 5.55E+09 1.90E+10 8.78E+09 O.OOE+OO 9.23E+09 O.OOE+OO 1.61E+10 Zn-69 1.94E-11 3.49E-11 2.60E-12 O.OOE+OO 1.45E-11 O.OOE+OO 2.85E-09 Br-83 O.OOE+OO O.OOE+OO 9.27E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO *O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.23E+10 1.10E+10 O.OOE+OO O.OOE+OO O.OOE+OO 5.70E+08 Rb-88 O:OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 1.26E+10 O.OOE+OO 3.61E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.59E+08 Sr-90 1:86E+11 O.OOE+OO 3.77E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.52E+09 Sr-91 2.70E+05 O.OOE+OO 9.76E+03 O.OOE+OO O.OOE+OO O.OOE+OO 3.19E+05 Sr-92 4.60E+OO O.OOE+OO 1.71E-01 O.OOE+OO O.OOE+OO O.OOE+OO 4.96E+01 Y-90 6.82E+02 O.OOE+OO 1.83E+01 O.OOE+OO O.OOE+OO O.OOE+OO 9.42E+05 Y-91M 6.09E-19 O.OOE+OO 2.0?E-20 O.OOE+OO O.OOE+OO O.OOE+OO 2.03E-15 Y-91 7.33E+04 O.OOE+OO 1.95E+03 O.OOE+OO O.OOE+OO O.OOE+OO 5.25E+06 Y-92 5.37E:-04 0.00E+OO 1,51E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E+01 Y-93 2,14E+OO O.OOE+OO 5.83E-02 O.OOE+OO O.OOE+OO O.OOE+OO .1.69E+04 Zr-95 6~81E+03 1*.66E+03 1.18E+03 O.OOE+OO 1.79E+03 O.OOE+OO 8.26E+05 Zr-97 4.05E+OO . 6.96E-01 3.18E-01 O.OOE+OO 7.01E-01 O.OOE+OO 4.44E+04 Nb-95 5'.94E+05 12A5E+05 '1.41E+05 O.OOE+OO 1.75E+05 O.OOE+OO *2.07E+08 Mo-99 O.OOE+OO ,2'.08E+08 4.05E+07 O.OOE+OO 3.10E+08 O.OOE+OO 6.84E+07 Tc-99M 2.74E+01 5.65E+01 7.27E+02 O.OOE+OO 6.08E+02 2.95E+01 1.64E+04 Tc-101 O.OOE+OO O.QOE+OO O.OOE+OO

• O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 8.67E+03 O.OOE+OO 2.90E+03 O.OOE+OO 1.80E+04 O.OOE+OO 1.05E+05 Ru-105 8.00E-0,3 O.OOE+OO 2.69E-03 O.OOE+OO 5.88E-02 O.OOE+OO 3.18E+OO Ru-106 1.90E+05
• O.OOE+OO 2.38E+04 O.OOE+OO 2.25E+05 O.OOE+OO . 1.44E+06 Ag-110M 3.86E+08 2.82E+08 1.86E+08 O.OOE+OO 4.03E+08 O.OOE+OO 1.46E+10 Page 228 of 268

Revision 9 February 27, 2017 Table F-13c (Continued) Infant Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 1.51E+08 5.04E+07 2.04E+07 5.08E+07 O.OOE+OO O.OOE+OO 7.19E+07 Te-127M 4.21E+08 1.40E+08 5.10E+07 1.22E+08 1.04E+09 O.OOE+OO 1.70E+08 Te-127 6.45E+03 2.16E+03 1.39E+03 5.25E+03 1.57E+04 O.OOE+OO 1.35E+05 Te-129M 5.57E+08 1.91E+08 8.58E+07 2.14E+08 1.39E+09 O.OOE+OO 3.33E+08 Te-129 2.72E-09 9.38E-10 6.35E-10 2.28E-09 6.77E-09 O.OOE+OO 2.17E-07 Te-131M 3.37E+06 1.36E+06 1.12E+06 2.75E+06 9.35E+06 O.OOE+OO 2.29E+07 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 2.10E+07 1.04E+07 9.71E+06 1.54E+07 6.51E+07 O.OOE+OO 3.85E+07 1-130 3.53E+06 7.77E+06 3.12E+06 8.71E+08 8.53E+06 O.OOE+OO 1.67E+06 1-131 2.72E+09 3.20E+09 1.41E+09 1.05E+12 3.74E+09 O.OOE+OO 1.14E+08 1-132 1.43E+OO 2.91E+OO 1.04E+OO 1.36E+02 3.25E+OO O.OOE+OO 2.36E+OO 1-133 3.63E+07 5.29E+07 1.55E+07 9.62E+09 6.22E+07 O.OOE+OO 8.95E+06 1-134 1.65E-11 3.37E-11 1.20E-11 7.87E-10 3.77E-11 O.OOE+OO 3.49E-11 1-135 1.13E+05 2.25E+05 . 8.19E+04 2.01E+07 2.50E+05 O.OOE+OO 8.13E+04 Cs-134 3.65E+10 6.80E+10 6.87E+09 O.OOE+OO 1.75E+10 7.18E+09 1.85E+08 Cs-136 1.97E+09 5.80E+09 2.16E+09 , O.OOE+OO 2.31E+09 4.72E+08 8.80E+07 Cs-137 5.15E+10 6.02E+10 '4.27E+09

• O.OOE+OO 1.62E+10 6.55E+09 1.88E+08 Cs-138
• O.OOE+OO O.OOE+OO O.OOE+OO : O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 4.29E-07 2.84E-10 1.24E-08 I O.OOE+OO 1.71E-10 1.72E-10 2.72E-05 Ba-140 2.41E+08 2.41E+05 . 1.24E+07
• O.OOE+OO 5.72E+04 1.48E+05 5.92E+07 Ba-141 . O.OOE+OO O.OOE+OO 'O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 4.06E+01 1.60E+01 4.12E+OO : O.OOE+OO O.OOE+OO O.OOE+OO 1.88E+05 La-142 1.73E-10 6.35E-11 1.52E-11
• O.OOE+OO O.OOE+OO O.OOE.+00 1.08E-05 Ce-141 4.34E+04 2.64E+04 3.11E+03 . O.OOE+OO 8.15E+03 O.OOE+OO 1.37E+07 Ce-143* 3.96E+02 2.63E+05 : 3.00E+01 O.OOE+OO 7.65E+01 O.OOE+OO 1.53E+06 Ce-144* 7.33E+06 9.52E+05 : 1.30E+05 O.OOE+OO 3.85E+05 O.OOE+OO 1.33E+08 Pr-143 1.49E+03 5.56E+02 7.37E+01 O.OOE+OO 2.07E+02 O.OOE+OO 7.84E+05 Pr-144 ** O.OOE+OO O.OOEtOO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147, 8.88E+02 9.12E+02
• 5.59E+01, O.OOE+OO 3.51E+02 O.OOE+OO 5.78E+05 W-187 : 6.08E+04 4.23E+04 1.46E+04 O.OOE+OO O.OOE+OO O.OOE+OO 2.48E+06 Np-239* 3.64E+01
• 3.26E+oo
• 1.?4E+OO O.OOE+OO 6.50E+OO O.OOE+OO 9.42E+04 Notes:

1) Units are m2 mrem/yr per µCi/sec with the exception of H-3.

3

2) For H-3, the units are mrem/yr per µCi/m .

Page 229 of 268

Revision 9 February 27, 2017 Table F-14 Adult Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 8.88E+02 8.88E+02 8.88E+02 8.88E+02 8.88E+02 8.88E+02 Na-24 2.95E+05 2.95E+05 2.95E+05 2.95E+05 2.95E+05 2.95E+05 2.95E+05 Cr-51 O.OOE+OO O.OOE+OO 3.43E+03 2.05E+03 7.55E+02 4.55E+03 8.62E+05 Mn-54 O.OOE+OO 1.01E+06 1.93E+05 O.OOE+OO 3.00E+05 O.OOE+OO 3.09E+06 Mn-56 O.OOE+OO 4.95E-04 8.79E-05 O.OOE+OO 6.29E-04 O.OOE+OO 1.58E-02 Fe-55 . 3.26E+05 2.26E+05 5.26E+04 O.OOE+OO O.OOE+OO 1.26E+05 1.29E+05 Fe-59 3.86E+05 9.07E+05 3.48E+05 O.OOE+OO O.OOE+OO 2.53E+05 3.02E+06 Co-58 O.OOE+OO 5.66E+05 1.27E+06 O.OOE+OO O.OOE+OO O.OOE+OO 1.15E+07 Co-60 O.OOE+OO 1.97E+06 4.34E+06 O.OOE+OO O.OOE+OO O.OOE+OO 3.70E+07 Ni-63 8.07E+08 5.60E+07 2.71E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.17E+07 Ni-65 4.44E-02 5.77E-03 2.63E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.46E-01 Cu-64 O.OOE+OO 2.63E+03 1.23E+03 O.OOE+OO 6.63E+03 . O.OOE+OO 2.24E+05 Zn-65 1.65E+08 5.24E+08 2.37E+08 O.OOE+OO 3.50E+08 O.OOE+OO 3.30E+08 Zn-69 2.41E-13 4.61E-13 3.21E-14 O.OOE+OO 3.00E-13 O.OOE+OO 6.93E-14 Br-83 O.OOE+OO O.OOE+OO 1.16E-02 O.OOE+OO O.OOE+OO

• O.OOE+OO 1.67E-02 Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO . O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO *O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 3.12E+08 1.45E+08 O.OOE+OO O.OOE+OO
• O.OOE+OO 6.15E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOEtOO O.OOE+OO : O.OOE+OO
• O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO ,O.OOE+OO O.OOE+OO O.OOE+OO : O.OOE+OO O.OOE+OO Sr-89 3.05E+09 . O.OOE+OO 8.74E+07 O.OOE+OO O.OOE+OO . O.OOE+OO 4.88E+08 Sr-90 1.13E+11 O.OOE+OO 2.27E+09 *o.OOE+OO O.OOE+OO O.OOE+OO . 2.84E+09 Sr-91 6.03E+04 O.OOE+OO :2.44E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.87E+05 Sr-92 1.02E+OO O.OOE+OO 4.39E-02 O.OOE+OO O.OOE+OO ; O.OOE+OO 2.01E+01 Y-90 8.52E+OO O.OOE+OO
• 2.28E-01
• O.OOE+OO O.OOE+OO : O.OOE+OO 9.03E+04 Y-91M O.OOE+OO : O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
• O.OOE+OO 2.26E-20 Y-91 1.03E+03 , O.OOE+OO . 2.76E+01 O.OOE+OO O.OOE+OO : O.OOE+OO 5.67E+05 Y-92 6.68E-06 O.OOE+OO . 1.95E-07 O.OOE+OO O.OOE+OO : O.OOE+OO 1.17E-01 Y-93 2.66E-02 O.OOE+OO 7.34E-04 O.OOE+OO O.OOE+OO i O.OOE+OO 8.43E+02 Zr-95 1.13E+02 3.63E+01 2.46E+01 O.OOE+OO 5.70E+01 I O.OOE+OO 1.15E+05 Zr-97 5.19E-02 1.05E-02 4.79E-03 O.OOE+OO 1.58E-02
• O.OOE+OO 3.24E+03 Nb-95 9.92E+03 5.52E+03 . 2.97E+03 O.OOE+OO .5.45E+03
• O.OOE+OO 3.35E+07 Mo-99 O.OOE+OO 2.97E+06 5.65E+05 O.OOE+OO
• 6.72E+06 'O.OOE+OO 6.88E+06 Tc-99M 3.97E-01 . 1.12E+OO 1.43E+01 O.OOE+OO *1.70E+01 : 5.50E-01 . 6.64E+02 Tc-101 O.OOE+OO O.OOE+OO . O.OOE+OO O.OOE+OO O.OOE+OO . O.OOE+OO .O.OOE+OO Ru-103 1.22E+02 O.OOE+OO I 5.26E+01 O.OOE+OO 4.66E+02 I O.OOE+OO 1.43E+04 Ru-105 1.02E-04 O.OOE+OO 4.03E-05 .O.OOE+OO 1.32E-03
• O.OOE+OO 6.25E-02 Ru-106 2.45E+03 O.OOE+OO '3.10E+02 *o.OOE+OO 4.73E+03 . O.OOE+OO 1.58E+05 Ag-110M 6.99E+06 6.46E+06 *'3.84E+06 O.OOE+OO 1.27E+07 . O.OOE+OO 2.64E+09 Page 230 of 268

Revision 9 February 27, 2017 Table F-14 (Continued) Adult Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 1.96E+06 7.09E+05 2.62E+05 5.88E+05 7.95E+06 O.OOE+OO 7.81E+06 Te-127M 5.49E+06 1.96E+06 6.69E+05 1.40E+06 2.23E+07 O.OOE+OO 1.84E+07 Te-127 8.00E+01 2.87E+01 1.73E+01 5.92E+01 3.26E+02 O.OOE+OO 6.31E+03 Te-129M 7.22E+06 2.69E+06 1.14E+06 2.48E+06 3.01E+07 O.OOE+OO 3.64E+07 Te-129 3.39E-11 1.27E-11 8.26E-12 2.60E-11 1.43E-10 O.OOE+OO 2.56E-11 Te-131M 4.33E+04 2.12E+04 1.76E+04 3.35E+04 2.14E+05 O.OOE+OO 2.10E+06 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 2.87E+05 1.86E+05 1.74E+05 2.05E+05 1.79E+06 O.OOE+OO 8.78E+06 1-130 5.01E+05 1.48E+06 5.84E+05 1.25E+08 2.31E+06 O.OOE+OO 1.27E+06 1-131 3.55E+08 5.08E+08 2.91E+08 1.67E+11 8.71E+08 O.OOE+OO 1.34E+08 1-132 1.98E-01 5.29E-01 1.85E-01 1.85E+01 8.42E-01 O.OOE+OO 9.93E-02 1-133 4.65E+06 8.09E+06 2.47E+06 1.19E+09 1.41E+07 O.OOE+OO 7.27E+06 1-134 2.27E-12 6.15E-12 . 2.20E-12 1.07E-10 9.79E-12 O.OOE+OO 5.36E-15 1-135 1.55E+04 4.06E+04 1.50E+04 2.68E+06 6.51E+04 O.OOE+OO 4.58E+04 Cs-134 1.70E+10 4.04E+10 3.30E+10 O.OOE+OO 1.31E+10 4.34E+09 '7.06E+08 Cs-136 7.88E+08 3.11E+09 2.24E+09 O.OOE+OO 1.73E+09 2.37E+08 3.53E+08 Cs-137 2.21E+10 3.03E+10 *1.98E+10 O.OOE+OO 1.03E+10 3.42E+09 5.86E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO . O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 5.32E-09 3.79E-12 1.56E-10 O.OOE+OO 3.54E-12 2.15E-12 9.44E-09 Ba-140

• 3.23E+06 4.05E+03 2.11E+05 O.OOE+OO ~1.38E+03 2.32E+03 6.64E+06 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO *O.OOE+OO O.OOE+OO O.OOE+OO Ba-142
• O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO :o.OOE+OO O.OOE+OO O.OOE+OO La-140 5.43E-01 2.74E-01 7.23E-02 O.OOE+OO 10.00E+OO O.OOE+OO 2.01E+04 La-142 2.27E-12 1.03E-12 2.57E-13 . O.OOE+OO  !'O.OOE+OO O.OOE+OO 7.53E-09 Ce-141 5.81E+02 3.93E+02 4.46E+01 O.OOE+OO I 1'.1.83E+02 O.OOE+OO 1.50E+06 Ce-143 4.98E+OO 3.68E+03
• 4.07E-01 . O.OOE+OO 1.62E+OO , O.OOE+OO 1.38E+05 Ce-144 4.29E+04 1.79E+04 '2.30E+03' o~ooE+oo 1.06E+04 , O.OOE+OO 1.45E+07 Pr:.143 1.90E+01 7.60E+OO <9.40E-01 O.OOE+OO ':4.39E+OO O.OOE+OO 8.31E+04 Pr-144 O.OOE+OO O.OOE+OO ::O.OOE+OO. O.OOE+OO "O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 1.14E+01 1.32E+01
• 7.87E-01 . O.OOE+OO '.7.69E+OO , O.OOE+OO 6.31E+04 W-187 7.82E+02 6.53E+02 *2.28E+02 O.OOE+OO
• 1 0.00E+OO O.OOE+OO 2.14E+05 Np-239 4.40E-01 4.33E-02 2.39E-02 : O.OOE+OO . 1.35E-01 I O.OOE+OO 8.88E+03 Notes:

2

1) Units are m mrem/yr per µCi/sec with the exception of H-3.

3

2) For H-3, the units are mrem/yr per µCi/m .

Page 231 of 268

Revision 9 February 27, 2017 Table F-14a Teen Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.16E+03 1.16E+03 1.16E+03 1.16E+03 1.16E+03 1.16E+03 Na-24 5.15E+05 5.15E+05 5.15E+05 5.15E+05 5.15E+05 5.15E+05 5.15E+05 Cr-51 O.OOE+OO O.OOE+OO 5.99E+03 3.33E+03 1.31E+03 8.55E+03 1.01E+06 Mn-54 O.OOE+OO 1.68E+06 3.34E+05 O.OOE+OO 5.02E+05 O.OOE+OO 3.45E+06 Mn-56 O.OOE+OO 8.78E-04 1.56E-04 O.OOE+OO 1.11 E-03 O.OOE+OO 5.78E-02 Fe-55 5.79E+05 4.11E+05 9.57E+04 O.OOE+OO O.OOE+OO 2.60E+05 1.78E+05 Fe-59 6.74E+05 1.57E+06 6.07E+05 O.OOE+OO O.OOE+OO 4.96E+05 3.72E+06 Co-58 O.OOE+OO 9.53E+05 2.20E+06 O.OOE+OO O.OOE+OO O.OOE+OO 1.31 E+07 Co-60 O.OOE+OO 3.34E+06 7.52E+06 O.OOE+OO O.OOE+OO O.OOE+OO 4.35E+07 Ni-63 1.42E+09 1.00E+08 4.81E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.59E+07 Ni-65 8.13E-02 1.04E-02 4.73E-03 O.OOE+OO O.OOE+OO O.OOE+OO 5.63E-01 Cu-64 O.OOE+OO 4.69E+03 2.20E+03 O.OOE+OO 1.19E+04 O.OOE+OO 3.64E+05 Zn-65 2.53E+08 8.78E+08 4.09E+08 O.OOE+OO 5.62E+08 O.OOE+OO 3.72E+08 Zn-69 4.44E-13 8.46E-13 5.92E-14 O.OOE+OO 5.53E-13 O.OOE+OO 1.56E-12 Br-83 O.OOE+OO O.OOE+OO 2.13E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 5.68E+08 2.67E+08 O.OOE+OO O.OOE+OO O.OOE+OO

• 8.41E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
• O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89* 5.61E+09 O.OOE+OO 1.61E+08 O.OOE+OO O.OOE+OO O.OOE+OO
• 6.69E+08 Sr-90 1.71E+11 O.OOE+OO 3.41E+09 O.OOE+OO O.OOE+OO O.OOE+OO : 3.90E+09 Sr-91 1.11E+05 O.OOE+OO '4.41E+03 O.OOE+OO O.OOE+OO O.OOE+OO 5.02E+05 Sr-92 1.86E+OO O.OOE+OO 7.92E-02 O.OOE+OO O.OOE+OO O.OOE+OO . 4.74E+01 Y-90 1.56E+01 O.OOE+OO 4.21E-01 *O.OOE+OO O.OOE+OO O.OOE+OO 1.29E+05 Y-91M 1.41E-20 O.OOE+OO O.OOE+OO .O.OOE+OO O.OOE+OO O.OOE+OO 6.66E-19 Y-91 1.90E+03 O.OOE+OO 5.08E+01 O.OOE+OO O.OOE+OO O.OOE+OO 7.77E+05 Y-92 1.23E.:.os O.OOE+OO
• 3.57E-07 O.OOE+OO O.OOE+OO O.OOE+OO
• 3.39E-01 Y-93 4.90E-02 O.OOE+OO 1.34E-03 O.OOE+OO O.OOE+OO O.OOE+OO . 1.50E+03 Zr-95 1.98E+02 6.25E+01 '4.30E+01 O.OOE+OO 9.18E+01 O.OOE+OO 1.44E+05 Zr-97 9.44E-02 . 1.87E-02 , 8.61E-03 O.OOE+OO 2.83E-02 O.OOE+OO. 5.06E+03 Nb-95 1.69E+04 9.38E+03 5.16E+03 O.OOE+OO 9.09E+03 O.OOE+OO 4.01E+07 Mo-99 O.OOE+OO 5.36E+06 '1.02E+06 O.OOE+OO 1.23E+07 O.OOE+OO 9.59E+06 Tc- 99M 6.89E-01 1.92E+OO 2.49E+01 O.OOE+OO 2.86E+01 1.07E+OO
• 1.26E+03 Tc-101 O.OOE+OO O:OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 2.17E+02 o:oOEtOO 9.29E+01 O.OOE+OO 7.66E+02 O.OOE+OO 1.81E+04 Ru-105 1.86E-04 O.OOE+OO 7.24E-05 O.OOE+OO 2.35E-03 O.OOE+OO 1.51 E-01 Ru-106 4.50E+03 ,O;OOE+OO ,5.67E+02 ,O.OOE+OO 8.68E+03 O.OOE+OO 2.16E+05 Ag-110M 1.16E+07 1'.09E+07 6.65E+06 O.OOE+OO 2.09E+07 O.OOE+OO 3.07E+09 Page 232 of 268

Revision 9 February 27, 2017 Table F-14a (Continued) Teen Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 3.61E+06 1.30E+06 4.82E+05 1.01 E+06 O.OOE+OO O.OOE+OO 1.06E+07 Te-127M 1.01E+07 3.59E+06 1.20E+06 2.41E+06 4.10E+07 O.OOE+OO 2.52E+07 Te-127 1.48E+02 5.25E+01 3.19E+Q1 1.02E+02 6.00E+02 O.OOE+OO 1.14E+04 Te-129M 1.32E+07 4.90E+06 2.09E+06 4.26E+06 5.53E+07 O.OOE+OO 4.96E+07 Te-129 6.24E-11 2.33E-11 1.52E-11 4.46E-11 2.62E-10 O.OOE+OO 3.41E-10 Te-131M 7.88E+04 3.78E+04 3.15E+04 5.68E+04 3.94E+05 O.OOE+OO 3.03E+06 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 5.13E+05 3.25E+05 3.06E+05 3.42E+05 3.12E+06 O.OOE+OO 1.03E+07 1-130 8.82E+05 2.55E+06 1.02E+06 2.08E+08 3.93E+06 O.OOE+OO 1.96E+06 1-131 6.45E+08 9.02E+08 4.85E+08 2.63E+11 1.55E+09 O.OOE+OO 1.78E+08 1-132 3.50E-01 9.17E-01 3.29E-01 3.09E+01 1.44E+OO O.OOE+OO 3.99E-01 1-133 8.50E+06 1.44E+07 4.40E+06 2.01E+09 2.53E+07 O.OOE+OO 1.09E+07 1-134 4.03E-12 1.07E-11 3.83E-12 1.78E-10 1.68E-11 O.OOE+OO 1.41E-13 1-135 2.75E+04 7.09E+04 2.63E+04 4.56E+06 1.12E+05 O.OOE+OO 7.85E+04 Cs-134 2.94E+10 6.93E+10 3.22E+10 O.OOE+OO 2.20E+10 8.41E+09 8.62E+08 Cs-136 1.34E+09 5.28E+09 3.54E+09 O.OOE+OO 2.87E+09 4.53E+08 4.25E+08 Cs-137 4.02E+10 5.34E+10 1.86E+10 O.OOE+OO 1.82E+10 7.06E+09 7.60E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 9.84E-09 6.92E-12 2.87E-10 O.OOE+OO 6.53E-12 4.77E-12 8.78E-08 Ba-140 5.82E+06 7.14E+03 . 3.75E+05 O.OOE+OO 2.42E+03 4.80E+03 8.98E+06 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O~OOE+OO O.OOE+OO 'O.OOE+OO O.OOE+OO O.OOE+OO *O.OOE+OO O.OOE+OO La-140 9.75E-01 4.79E-01 1.27E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.75E+04 La-142 4.09E-12 1.82E-12 4.53E-13 O.OOE+OO O.OOE+OO *o.OOE+OO 5:53E-08 Ce-141 1.07E+03 7.12E+02 8.17E+01 O.OOE+OO 3.35E+02 O.OOE+OO 2.04E+06. Ce-143 9.15E+OO .6.66E+03 7.44E-01 O.OOE+OO 2.99E+OO O. OOE+OO 2.00E+05 Ce~144 7.90E+04 3.27E+04 4.24E+03 O.OOE+OO 1.95E+04 O.OOE+OO 1.99E+07 Pr-143 3.48E+01 1.39E+01 . 1.73E+OO O.OOE+OO 8.08E+OO O.OOE+OO 1.15E+05 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 2.19E+01 2.38E+01 1.43E+OO O.OOE+OO 1.40E+01 O.OOE+OO . 8.59E+04 W-187 1.43E+03 1.17E+03 4.b8E+02 O.OOE+OO O.OOE+OO

• O. OOE+OO
• 3.15E+05 Np-239 8.40E~01 7.92E-02 ' 4.40E-02 O.OOE+OO 2.49E-01 O.OOE+OO . 1.27E+04 Notes:

2

1) Units are m mrem/yr per µCi/sec with the exception of H-3.

3

2) For H-3, the units are mrem/yr per µCi/m .

Page 233 of 268

Revision 9 February 27, 2017 Table F-14b Child Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.83E+03 1.83E+03 1.83E+03 1.83E+03 1.83E+03 1.83E+03 Na-24 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 Cr-51 O.OOE+OO O.OOE+OO 1.22E+04 6.78E+03 1.85E+03 1.24E+04 6.47E+05 Mn-54 O.OOE+OO 2.52E+06 6.70E+05 O.OOE+OO 7.06E+05 O.OOE+OO 2.11 E+06 Mn-56 O.OOE+OO 1.53E-03 3.46E-04 O.OOE+OO 1.85E-03 O.OOE+OO 2.22E-01 Fe-55 1.45E+06 7.71E+05 2.39E+05 O.OOE+OO O.OOE+OO 4.36E+05 1.43E+05 Fe-59 1.56E+06 2.53E+06 1.26E+06 O.OOE+OO O.OOE+OO 7.33E+05 2.63E+06 Co-58 O.OOE+OO 1.46E+06 4.46E+06 O.OOE+OO O.OOE+OO O.OOE+OO 8.49E+06 Co-60 O.OOE+OO 5.18E+06 1.53E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.87E+07 Ni-63 3.56E+09 1.90E+08 1.21 E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.28E+07 Ni-65 1.99E-01 1.87E-02 1.09E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.29E+OO Cu-64 O.OOE+OO 8.24E+03 4.98E+03 O.OOE+OO 1.99E+04 O.OOE+OO 3.87E+05 Zn-65 4.96E+08 1.32E+09 8.22E+08 O.OOE+OO 8.33E+08 O.OOE+OO 2.32E+08 Zn-69 1.09E-12 1.58E-12 1.46E-13 O.OOE+OO 9.57E-13 O.OOE+OO 9.95E-11 Br-83 O.OOE+OO O.OOE+OO 5.24E-02 O.OOE+OO O.OOE+OO O.OOE+OO

• O.OOE+OO Br.:84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.05E+09 6.48E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.78E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO .O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO .O.OOE+OO O.OOE+OO O.OOE+OO .O.OOE+OO O.OOE+OO Sr-89 1.39E+10 O.OOE+OO 3.97E+08 .O.OOE+OO O.OOE+OO O.OOE+OO 5.38E+08 Sr-90 3.53E+11 O.OOE+OO 7.11E+09 O.OOE+OO O.OOE+OO O.OOE+OO 3.16E+09 Sr"'.'91 2.72E+05 O.OOE+OO 1.03E+04 O.OOE+OO O.OOE+OO O.OOE+OO 6.00E+05 Sr"'.'92 4.54E+OO O.OOE+OO 1.82E-01 O.OOE+OO O.OOE+OO O.OOE+OO 8.60E+01 Y-90 3.87E+01 O.OOE+OO 1.04E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.10E+05 Y-91M 3.45E-20 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.75E-17 Y-91 4.68E+03 O.OOE+OO 1.25E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.24E+05 Y-92 3.03E-05 .O.OOE+OO
• 8.67E-07 O.OOE+OO O.OOE+OO O.OOE+OO 8.75E-01 Y-93 1.20E:-01 :O.OOE+OO 3.31 E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.80E+03 Zr-95 4.60E+02 1.01E+02 9.00E+01 O.OOE+OO 1.45E+02 O.OOE+OO 1.05E+05 Zr-97 2.30E-01 . 3.32E-02 1.96E-'02 O.OOE+OO 4.77E-02 O.OOE+OO 5.03E+0:3 Nb-95 3.82E+04 1.49E+04 1.06E+04 O.OOE+OO 1.40E+04 O.OOE+OO
• 2.75E+07 Mo-99 O.OOE+OO 9.75E+06 2.41E+06 O.OOE+OO 2.08E+07 O.OOE+OO 8.06E+06 Tc-99M 1.58E+OO 3.10E+OO 5.14E+Ot O.OOE+OO 4.50E+01 1.57E+OO 1.76E+03 Tc-101 O.OOE+OO O..OOE+OO O.OOE+oo O.OOE+OO O.OOE+OO . O.OOE+OO O.OOE+OO Ru-103 5.14E+02 O.OOE+OO 1.97E+02 O.OOE+OO 1.29E+03 O.OOE+OO 1.33E+04 Ru-105 4.55E-04 O:OOE+OO 1.65E-04 O.OOE+OO 4.00E-03 O.OOE+OO '2.97~-01 Ru-106 1.11E+04 :O.OOE+OO. 1.38E+03 O.OOE+OO . 1.50E+04 .O.OOE+OO 1.72E+05 Ag-110M 2.51E+07 '1.69E+07 1.35E+07 O.OOE+OO 3.15E+07 O.OOE+OO 2.01E+09 Page 234 of 268

Revision 9 February 27, 2017 Table F-14b (Continued) Child Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 8.86E+06 2.40E+06 1.18E+06 2.49E+06 O.OOE+OO O.OOE+OO 8.55E+06 Te-127M 2.50E+07 6.72E+06 2.96E+06 5.97E+06 7.12E+07 O.OOE+OO 2.02E+07 Te-127 3.64E+02 9.83E+01 7.82E+01 2.52E+02 1.04E+03 O.OOE+OO 1.42E+04 Te-129M 3.26E+07 9.09E+06 5.05E+06 1.05E+07 9.56E+07 O.OOE+OO 3.97E+07 Te-129 1.54E-10 4.30E-11 3.66E-11 1.10E-10 4.51E-10 O.OOE+OO 9.59E-09 Te-131M 1.92E+05 6.63E+04 7.06E+04 1.36E+05 6.42E+05 O.OOE+OO 2.69E+06 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 1.22E+06 5.42E+05 6.55E+05 7.89E+05 5.03E+06 O.OOE+OO 5.46E+06 1-130 2.06E+06 4.17E+06 2.15E+06 4.59E+08 6.23E+06 O.OOE+OO 1.95E+06 1-131 1.56E+09 1.57E+09 8.94E+08 5.20E+11 2.58E+09 O.OOE+OO 1.40E+08 1-132 8.29E-01 1.52E+OO 7.00E-01 7.07E+01 2.33E+OO O.OOE+OO 1.79E+OO 1-133 2.06E+07 2.55E+07 9.66E+06 4.74E+09 4.25E+07 O.OOE+OO 1.03E+07 1-134 9.53E-12 1.77E-11 8.14E-12 4.07E-10 2.71E-11 O.OOE+OO 1.17E-11 1:..135 6.52E+04 1.17E+05 5.55E+04 1.04E+07 1.80E+05 O.OOE+OO 8.94E+04 Cs-134 6.79E+10 1.11E+11 2.35E+10 O.OOE+OO 3.45E+10 1.24E+10 6.01E+08 Cs-136 3.03E+09 8.32E+09 5.39E+09 O.OOE+OO 4.43E+09 6.61E+08 2.92E+08 Cs-137 9.67E+10 9.26E+10 1.37E+10 O.OOE+OO 3.02E+10 1.09E+10 5.80E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 2.42E.:08 1.29E-11 7.01E-10 O.OOE+OO 1.13E-11 7.59E-12 1.40E-06 Ba-140 1.41 E+07 1.23E+04 8.21E+05 O.OOE+OO 4.01E+03 7.34E+03 7.12E+06 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 2.33E+OO 8.16E-01 2.75E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.27E+04 La-142 9.88E-12 3.15E-12 9.87E-13 O.OOE+OO O.OOE+OO O.OOE+OO 6.24E-07 Ce-141 2.62E+03 1.31E+03 1.94E+02 O.OOE+OO 5.74E+02 O.OOE+OO 1.63E+06 Ce-:143 2'.25E+.01 1.22E+04 1.76E+OO O.OOE+OO 5.11 E+OO O.OOE+OO 1.78E+05 Ce-144 1.95E+'05 6.11E~04 1.04E+04 O.OOE+OO 3.38E+04 O.OOE+OO 1.59E+07 Pr-143 8.62E+01 2.59E+01 4.28E+OO O.OOE+OO 1.40E+01 O.OOE+OO 9.30E+04 Pr-144 O.OOE+OO O.OOE+oo O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 5.37E+01 4.35E+01 3.37E+OO O.OOE+OO 2.39E+01 O.OOE+OO 6.89E+04 W-187 3.47E+03 2.05E+03 9.21E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.88E+05 Np-239 2.07E+OO 1.48E-01 1.04E-01 O.OOE+OO 4.29E-01 O.OOE+OO 1.10E+04 Notes:

1) Units are m2 mrem/yr per µCi/sec with the exception of H-3.

3

2) For H-3, the units are mrem/yr per µCi/m ..

Page 235 of 268

Revision 9 February 27, 2017 Table F-14c Infant Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 2.78E+03 2.78E+03 2.78E+03 2.78E+03 2.78E+03 2.78E+03 Na-24 1.87E+06 1.87E+06 1.87E+06 1.87E+06 1.87E+06 1.87E+06 1.87E+06 Cr-51 O.OOE+OO O.OOE+OO 1.93E+04 1.26E+04 2.76E+03 2.46E+04 5.64E+05 Mn-54 O.OOE+OO 4.68E+06 1.06E+06 O.OOE+OO 1.04E+06 O.OOE+OO 1.72E+06 Mn-56 O.OOE+OO 3.75E-03 6.47E-04 O.OOE+OO 3.22E-03 O.OOE+OO 3.41 E-01 Fe-55 1.76E+06 1.13E+06 3.03E+05 O.OOE+OO O.OOE+OO 5.55E+05 1.44E+05 Fe-59 2.92E+06 5.09E+06 2.01E+06 O.OOE+OO O.OOE+OO 1.51E+06 2.43E+06 Co-58 O.OOE.+00 2.91E+06 7.26E+06 O.OOE+OO O.OOE+OO O.OOE+OO 7.25E+06 Co-60 O.OOE+OO 1.06E+07 2.50E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.52E+07 Ni-63 4.19E+09 2.59E+08 .1.45E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.29E+07 Ni-65 4.21E-01 4.77E-02 2.17E-02 O.OOE+OO O.OOE+OO O.OOE+OO 3.63E+OO cu~64 O.OOE+OO 2.05E+04 9.48E+03 O.OOE+OO 3.46E+04 O.OOE+OO 4.20E+05 Zn-65 6.66E+08 2.28E+09 . 1.05E+09 O.OOE+OO 1.11 E+09 O.OOE+OO 1.93E+09 Zn-69 2.33E-12 4.19E-12 3.12E-13 O.OOE+OO 1.74E-12 O.OOE+OO . 3.42E-10 Br-83 O.OOE+OO O.OOE+OO 1.11 E-01 O.OOE+O.O O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO : O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO . O.OOE+OO Rb-86 O.OOE+OO 2.67E+09. 1.32E+09 O.OOE+OO O.OOE+OO O.OOE+OO . 6.84E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO *O.OOE+OO O.OOE+OO O.OOE+OO

• O.OOE+OO Rb-89 O.OOE+oo O,OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 2.64E+10 O,OOE+OO 7.58E+08 O.OOE+OO O.OOE+OO O.OOE+OO 5.43E+08 Sr-90 3 ..91E+11
• O.OOE+OO 7.92E+09 O.OOE+OO O.OOE+OO O.OOE+OO 3.19E+09 Sr-91 5.66E+05 O.OOE+OO 2.05E+04 O.OOE+OO O.OOE+OO O.OOE+OO 6.70E+05 Sr-92 9.65E+OO O.OOE+OO 3.59E-01 *O.OOE+OO O.OOE+OO O.OOE+OO 1.04E+02 Y-90 8.19E+01 O.OOE+OO 2.20E+OO . O.OOE+OO O.OOE+OO O.OOE+OO 1.13E+05 Y-91M 7.31E-20 O.OOE+OO ,O.OOE+OO .O.OOE+OO O.OOE+OO O:OOE+OO 2.44E-16 Y-91 8.79E+03 O.OOE+QO 2.34E+02 *o.OOE+OO O.OOE+OO O.OOE+OO 6.30E+05 Y-~2 6.44E-05 O.OOE+OO 1.8~E-06 O.OOE+OO O.OOE+OO O:OOE+OO 1.23E+OO Y-93 2.57E-01 O.OOE+OO 6.99E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.03E+03 zr.:.95 8.17E+02 1.99E+02 1.41E+02 O.OOE+OO 2.15E+02 O.OOE+OO 9.91E+04 Zr-97 4.87E-01 8.;35E-02 3.81 E-02 O.OOE+OO 8.42E-02 O.OOE+OO 5.33E+03 Nb-95 7.13E+04 2.94E+04 1.70E+04 O.OOE+oo 2.10E+04 O.OOE+OO 2.48E+07 Mo-99 O.OOE+OO 2.49E+07 4.86E+06 O.OOE+OO 3.72E+07 O.OOE+OO 8.21E+06 Tc-99M 3.29E+OO 6.78E+OO 8.73E+01 O.OOE+OO 7.29E+01 3.54E+OO 1.97E+03 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 1.04E+03 O.OOE+OO 3..48E+02
• O.OOE+OO 2.16E+03 O.OOE+OO 1.27E+04 Ru-105 9.60E-04 Q.QOE+OO 3.23E-04 O.OOE+OO 7.06E-03 o~ooE+oo 3.82E-01 Ru-106 2.28E+04 O.OOE+OO 2.85E+03 .O.OOE+OO 2.70E+04 O.OOE+OO 1.73E+05 Ag-110M 4.63E+07 3.38E+07
• 2.24E+07 O.OOE+OO 4.84E+07 O~OOE+OO 1.75E+09 Page 236 of 268
• Revision 9 February 27, 2017 Table F-14c (Continued)

Infant Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 1.81 E+07 6.05E+06 2.45E+06 6.09E+06 O.OOE+OO O.OOE+OO 8.62E+06 Te-127M 5.05E+07 1.68E+07 6.12E+06 1.46E+07 1.24E+08 O.OOE+OO 2.04E+07 Te-127 7.74E+02 2.59E+02 1.66E+02 6.30E+02 1.89E+03 O.OOE+OO 1.63E+04 Te-129M 6.68E+07 2.29E+07 1.03E+07 2.57E+07 1.67E+08 O.OOE+OO 3.99E+07 Te-129 3.26E-10 1.13E-10 7.62E-11 2.74E-10 8.13E-10 O.OOE+OO 2.61E-08 Te-131M 4.05E+05 1.63E+05 1.35E+05 3.30E.+05 1.12E+06 O.OOE+OO 2.74E+06 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 2.52E+06 1.25E+06 1.17E+06 1.84E+06 7.81E+06 O.OOE+OO 4.62E+06 1-130 4.24E+06 9.32E+06 3.74E+06 1.04E+09 1.02E+07 O.OOE+OO 2.00E+06 1-131 3.26E+09 3.85E+09 1.69E+09 1.26E+12 4.49E+09 O.OOE+OO 1.37E+08 1-132 '1,72E+OO 3.49E+OO 1.24E+OO 1.64E+02 3.90E+OO O.OOE+OO 2.83E+OO 1-133 4.36E+07 6.35E+07 1.86E+07 1.15E+10 7.46E+07 O.OOE+OO 1.07E+07 1-134 1.98E-11 4.0SE-11 1.44E-11 9.44E-10 4.53E-11 O.OOE+OO 4.19E-11 1-135 1.36E+05 2.70E+05 9.83E+04 2.42E+07 3.01E+05 O.OOE+OO 9.76E+04 Cs-134 1.09E+11 .2.04E+11 2.06E+10 O.OOE+OO 5.25E+10 2.15E+10 5.54E+08 Cs-136 5.91E+09 1.74E+10 6.49E+09 O.OOE+OO 6.93E+09 1.42E+09 2.64E+08 Cs-137 1.54E+11 1.81E+11 1.28E+10 O.OOE+OO 4.85E+10 1.96E+10 5.65E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 5.14E-08 3.41E-11 1.49E-09 O.OOE+OO 2.0SE-11 2.07E-11 3.26E-06 Ba-140 2.89E+07 2.89E+04 1.49E+06 ,O.OOE+OO .6.87E+03 1.78E+04 7.11E+06 Ba-141 O.OOE+.00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O~OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 4.88E+OO 1.92E+OO 4.95E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.26E+04 La-142 2.08E-11 7.62E-12 1.82E-12 O.OOE+OO O.OOE+OO O.OOE+OO 1.29E-06 Ce-141 5~20E+03 3.17E+03 3.73E+02 O.OOE+OO 9.78E+02 O.OOE+OO 1.64E+06 Ce-143 '4.75E+01 3.15E+04 3.60E+OO O.OOE+OO 9.19E+OO O.OOE+OO 1.84E+05 Ce-144 2'.79E+05 1.. 14E+05 1.56E+04 O.OOE+OO *4.62E+04 O.OOE+OO 1.60E+07 Pr-143 *1.78E+02 6.67E+01 8.84E+OO O.OOE+OO 2.48E+01 O.OOE+OO 9.41E+04 Pr-144 O'.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O:OOE+OO Nd-147 1.07E+02 1'.09E+02 6.70E+OO O.OOE+OO 4.22E+01 O.OOE+OO 6.93E+04 W-187 7.29E+03 5.07E+03 1.75E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.98E+05 Np-239 4.37E+OO 3.91 E-01 2.21E-01 O.OOE+OO 7.80E-01 O.OOE+OO 1.13E+04 Notes:

1) Units are m2 mrem/yr per µCi/sec with the exception of H-3.

3

2) For H-3, the units are mrem/yr per µCi/m .

Page 237 of 268

Revision 9 February 27, 2017 Table F-15 Adult Grass-Cow-Meat Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.85E+02 1.85E+02 1.85E+02 1.85E+02 1.85E+02 1.85E+02 Na-24

• 1.45E-03 1.45E-03 1.45E-03 1.45E-03 1.45E-03 1.45E-03 1.45E-03 Cr-51 O.OOE+OO O.OOE+OO 7.04E+03 4.21E+03 1.55E+03 9.34E+03 1.77E+06 Mn-54 O.OOE+OO 9.18E+06 1.75E+06 O.OOE+OO 2.73E+06 O.OOE+OO 2.81E+07 Mn-56 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Fe-55 2.93E+08 2.03E+08 4.72E+07 O.OOE+OO O.OOE+OO 1.13E+08 1.16E+08 Fe-59 2.65E+08 6.24E+08 2.39E+08 O.OOE+OO O.OOE+OO 1.74E+08 2.08E+09 Co-58 O.OOE+OO 1.82E+07 4.09E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.70E+08 Co-60 O.OOE+OO 7.52E+07 1.66E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.41E+09 Ni-63 1.89E+10 1.31E+09 6.33E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.73E+08 Ni-65 O.OOE+OO O.OOE+oo O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO *o.OOE+OO Cu-64 O.OOE+OO 2.52E-07 1.18E-07 O.OOE+OO 6.36E-07 O.OOE+OO 2.15E-05 Zn-65 3.56E+08 1.13E+09 5.12E+08 O.OOE+OO 7.57E+08 O.OOE+OO 7.13E+08 Zn-69 O.OOE+OO O.OOE+OO . O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE.+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO . O.OOE+OO Rb-86 O.OOE+OO 4.88E+08 2.28E+08 O.OOE+OO O.OOE+OO O.OOE+OO 9.63E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO
• O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 3.01E+08 O.OOE+OO 8.65E+06 O.OOE+OO O.OOE+OO O.OOE+OO 4.83E+07 Sr-90 1.43E+10 O.OOE+OO 2.87E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.59E+08 Sr-91 1.43E-10 O.OOE+OO 5.79E-12 O.OOE+OO O.OOE+OO
• O.OOE+OO
• 6.83E-10 Sr-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO . O.OOE+OO Y-90 1.08E+02 O.OOE+OO 2.91E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.15E+06 Y-91M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO *O.OOE+OO Y-91 1.13E+06 O.OOE+OO 3~03E+04 O.OOE+OO O.OOE+OO O.OOE+OO 6.23E+08 Y-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-93 4.39E-12 0.00E+OO 1.21E-13 O.OOE+OO O.OOE+OO O.OOE+OO 1.39E-07 Zr-95 1.87E+06 6.01E+05 4.07E+05
• O.OOE+OO 9.43E+05 O.OOE+OO . 1.91E+09 Zr-97 2.04E-05 4.,12E-06 1.88E-06 O.OOE+OO 6.22E-06 O.OOE+OO 1.28E+OO Nb-95 2.30E+06 1.28E+06 6:.89E+05 O.OOE+OO 1.27E+06 O.OOE+OO 7.78E+09 Mo-99 O.OOE+OO 9.93E+04 1.89E+04 O.OOE+OO 2.25E+05 O.OOE+OO  : 2.30E+05 Tc-99M O.OOE+OO 1.22E-20 1.56E-19 O.OOE+OO 1.85E-19 O.OOE+OO 7.23E-18 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
• O.OOE+OO Ru-103 1.05E+08 O.OOE+OO 4'.53E+07
• O.OOE+OO 4.01E+08 O.OOE+OO 1.23E+10 Ru-105 O.OOE+OO O.QOE;+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
• O.OOE+OO Ru-106 2.80E+09 O.OOE.+00 3.54E+08 O.OOE+OO 5.40E+09 O.OOE+OO '1.81E+11 Ag-110M 6.68E+06 6.18E+06 3.67E+06 O.OOE+OO 1.22E+07 O.OOE+OO 2.52E+09 Page 238 of 268

Revision 9 February 27, 2017 Table F-15 (Continued) Adult Grass-Cow-Meat Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 3.59E+08 1.30E+08 4.81E+07 1.08E+08 1.46E+09 O.OOE+OO 1.43E+09 Te-127M 1.12E+09 3.99E+08 1.36E+08 2.85E+08 4.53E+09 O.OOE+OO 3.74E+09 Te-127 2.SOE-10 8.98E-11 5.41E-11 1.85E-10 1.02E-09 O.OOE+OO 1.97E-08 Te-129M 1.13E+09 4.23E+08 1.79E+08 3.89E+08 4.73E+09 O.OOE+OO 5.71E+09 Te-129 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-131M 4.49E+02 2.20E+02 1.83E+02 3.48E+02 2.23E+03 O.OOE+OO 2.18E+04 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 1.40E+06 9.03E+05 8.48E+05 9.98E+05 8.70E+06 O.OOE+OO 4.27E+07 1-130 2.03E-06 5.98E-06 2.36E-06 5.07E-04 9.33E-06 O.OOE+OO 5.15E-06 1-131 1.07E+07 1.54E+07 8.80E+06 5.03E+09 2.63E+07 O.OOE+OO 4.05E+06 1-132 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-133 3.70E-01 6.43E-01 1:96E-01 9.45E+01 1.12E+OO O.OOE+OO 5.78E-01 1-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-135 4.66E-17 1.22E-16 4.SOE-17 8.04E-15 1.95E-16 O.OOE+OO 1.38E-16 Cs-134 6.58E+08 1.57E+09 1.28E+09 O.OOE+OO 5.07E+08 1.68E+08 2.74E+07 Cs-136 1.20E+07 4.73E+07 3.40E+07 O.OOE+OO 2.63E+07 3.61E+06 5.37E+06 Cs-137 8.72E+08 1.19E+09 7.81E+08 O.OOE+OO 4.05E+08 1.35E+08 2.31E+07 Cs-138 O.OOE+OO O.OOE+OO , O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 O.OOE+OO O:OOE+OO . O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-140 2.88E+07 3.61E+04 1.88E+06 O.OOE+OO 1.23E+04 2.07E+04 5.92E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 3.76E-02 . 1.90E-02 . 5.01E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.39E+03 La-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ce-141 1.40E+04 9.49E+03 1.08E+03 O.OOE+OO 4.41E+03 O.OOE+OO 3.63E+07 Ce-143 1.99E-02 1.47E+01 1.63E~03 O.OOE+OO 6.47E-03 O.OOE+OO 5.49E+02 Ce-144 1.46E+06. 6.09E+05 7.83E+04 O.OOE+OO 3.61E+05 O.OOE+OO 4.93E+08 Pr-143* 2.10E+04 8'.42E+03 1.04E+03 O.OOE+OO A.86E+03 O.OOE+OO 9.20E+07 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO *O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 7.21E+03 8:33E+03 4.98E+02 O.OOE+OO '4.87E+03 O.OOE+OO 4.00E+07 W-187, 2.07E-02 1.73E-02 6.04E-03 O.OOE+OO O.OOE+OO O.OOE+OO 5.66E+OO Np-239 2.57E-01 2.53E-02 : 1.40E702 O.OOE+OO 7.90E-02 O.OOE+OO 5.19E+03 Notes:

1) Units are m2 mrem/yr per µCi/sec with the exception of H-3.

3

2) For H-3, the units are mrem/yr per µCi{m .

Page 239 of 268

Revision 9 February27, 2017 Table F-15a Teen Grass-Cow-Meat Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.1 OE+02 1.10E+02 1.10E+02 1.10E+02 1.10E+02 1.10E+02 Na-24 1.16E-03 1.16E-03 1.16E-03 1.16E-03 1.16E-03 1.16E-03 1.16E-03 Cr-51 O.OOE+OO O.OOE+OO 5.63E+03 3.13E+03 1.23E+03 8.04E+03 9.46E+05 Mn-54 O.OOE+OO 7.00E+06 1.39E+06 O.OOE+OO 2.09E+06 O.OOE+OO 1.44E+07 Mn-56 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Fe-55 2.38E+08 1.69E+08 3.94E+07 O.OOE+OO O.OOE+OO 1.07E+08 7.31E+07 Fe-59 2.12E+08 4.95E+08 1.91E+08 O.OOE+OO O.OOE+OO 1.56E+08 1.17E+09 Co-58 O.OOE+OO 1.41E+07 3.24E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.94E+08 Co-60 . O.OOE+OO 5.83E+07 1.31E+08 O.OOE+OO O.OOE+OO O.OOE+OO 7.60E+08 Ni-63 1.52E+10 1.07E+09 5.15E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.71 E+08 Ni-65 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cu-64 O.OOE+OO 2.06E-07 9.68E-08 O.OOE+OO 5.21E-07 O.OOE+OO 1.60E-05 Zn-65 2.50E+08 8.69E+08 4.05E+08 O.OOE+OO 5.56E+08 O.OOE+OO. 3.68E+08 Zn-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 4.08E+08 1.91 E+08 O.OOE+OO

• O.OOE+OO O.OOE+OO '6.03E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
• O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO' O.OOE+OO Sr-89 2.54E+08 O.OOE+OO 7.28E+06 . O.OOE+OO O.OOE+OO *O.OOE+OO 3.03E+07 Sr-90 9.89E+09 O.OOE+OO 1.98E+08 ,O.OOE+OO O.OOE+OO O.OOE+OO 2.26E+08 Sr-91 1.21E-10 O.OOE+OO 4.80E-12 *O.OOE+OO O.OOE+OO O.OOE+OO 5.47E-10 Sr-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-90 9.13E+01 O,OOE+OO 2.46E+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.53E+05 Y-91M O.OOE+OO O.OOE*t-00 O,OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+oo Y-91 9.54E+05 O.OOE+OO 2.56E+04 O.OOE+OO O.OOE+OO O.OOE+OO 3.91E+08 Y-92 O.OOE+OO O,OOE+OO O.OOE+OO 'O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-93 3*_71E-12 O.OOE+OO 1.02E-13 O.OOE+OO O.OOE+OO *O.OOE+OO 1.13E-07 Zr-95 1.50E+06 4.74E+05 3.26E+05 O.OOE-+:00 6.96E+05 O.OOE+OO 1.09E+09 Zr-97 1.70F05 3.37E-06. 1.55E-06 :O.OOE+OO 5.10E-06 'O.OOE+OO 9.11E-01 Nb-95 1.80E+06 9:98E+05 5.49E+05 O.OOE+OO 9.67E+05 O.OOE+OO 4.27E+09 Mo-99 O.OOE+OO 8.21Et04 1:57E+04 O.OOE+OO .1.88E+05 O.OOE+OO 1.47E+05 Tc- 99M O.OOE+OO O.OOEtOO 1.24E-19 O.OOE+OO 1.43E-19 O.OOE+OO 6.29E-18 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO ,O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 *8.56E+07 O.OOEt-00 . 3,66E+07 O.OOE+OO 3.02E+08 O.OOE+OQ 7.15E+09 Ru-105 O.OOE+OO O,OOE:t-00 O.OOE+OO O.OOE+OO o:ooE+oo O.OOE+OO O.OOE+OO Ru-106 2.36E+09 o:ooE+oo 2.97E+08 O.OOE+OO . 4.55E+09 O.OOE+OO 1.13E+11 Ag-110M 5.06E+06 4.79E+06 2.91E+06 O.OOE+oo 9.13E+06 O.OOE+OO 1.35E+09 Page 240 of 268

Revision 9 February 27, 2017 Table F-15a (Continued) Teen Grass-Cow-Meat Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 3.03E+08 1.09E+08 4.06E+07 8.47E+07 O.OOE+OO O.OOE+OO 8.95E+08 Te-127M 9.41E+08 3.34E+08 1.12E+08 2.24E+08 3.82E+09 O.OOE+OO 2.35E+09 Te-127 2.12E-10 7.53E-11 4.57E-11 1.46E-10 8.60E-10 O.OOE+OO 1.64E-08 Te-129M 9.49E+08 3.52E+08 1.50E+08 3.06E+08 3.97E+09 O.OOE+OO 3.56E+09 Te-129 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-131M 3.75E+02 1.80E+02 1.50E+02 2.70E+02 1.87E+03 O.OOE+OO 1.44E+04 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 1.14E+06 7.24E+05 6.81E+05 7.63E+05 6.94E+06 O.OOE+OO 2.29E+07 1-130 1.63E-06 4.72E-06 1.88E-06 3.85E-04 7.27E-06 O.OOE+OO 3.63E-06 1-131 8.92E+06 1.25E+07 6.71E+06 3.64E+09 2.15E+07 O.OOE+OO 2.47E+06 1-132 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-133 3.09E-01 5.25E-01 1.60E-01 7.32E+01 9.20E-01 O.OOE+OO 3.97E-01 1-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-135 3.79E-17 9.75E-17 3.61E-17 6.27E-15 1.54E-16 O.OOE+OO 1.08E-16 Cs-134 5.23E+08 1.23E+09 5.71E+08 O.OOE+OO 3.91E+08 1.49E+08 1.53E+07 Cs-136 9.34E+06 3.68E+07 2.47E+07 O.OOE+OO 2.00E+07 3.15E+06 2.96E+06 Cs-137 .7.24E+08 9.63E+08 3.36E+08 O.OOE+OO 3.28E+08 1.27E+08 1.37E+07 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-140 2.38E+07 2.91Ef-04 1.53E+06 O.OOE+OO 9.88E+03 1.96E+04 3.67E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 3.09E-02 1.52E-02 4.04E-03 O.OOE+OO O.OOE+OO O.OOE+OO 8.73E+02 La-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ce-141 1.18E+04 7.87E+03 9.04E+02 O.OOE+OO 3.70E+03 O.OOE+OO 2.25E+07 Ce-143 1.67E-02 1.22E+01 1.36E-03 O.OOE+OO 5.46E-03 O.OOE+OO 3.66E+02 Ce-144 '1.23E+06 5.08E+05 6.60E+04 O.OOE+OO 3.04E+05 O.OOE+OO 3.09E+08 Pr-143 1.77E+04 7.05E.+03 8.79E+02 O.OOE+OO 4.10E+03 O.OOE+OO 5.81.E+07 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 6.35E+03 '6.90E+03 4.14E+02 O.OOE+OO 4.05E+03 O.OOE+OO 2.49E+07 W-187 1.73E-02 1.41E-02 4.94E-03 O.OOE+OO O.OOE+OO O.OOE+OO 3.82E+OO Np-239 2.25E-01 2.12E-02 1.18E-02 O.OOE+OO 6.66E-02 O.OOE+OO 3.41E+03 Notes:

1) Units are m2 mrem/yr per µCi/sec with the exception of H-3.

3

2) For H-3, the units are mrem/yr per µCi/m .

Page 241 of 268

Revision 9 February 27, 2017 Table F-15b Child Grass-Cow-Meat Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.34E+02 1.34E+02 1.34E+02 1.34E+02 1.34E+02 1.34E+02 Na-24 1.84E-03 1.84E-03 1.84E-03 1.84E-03 1.84E-03 1.84E-03 1.84E-03 Cr-51 O.OOE+OO O.OOE+OO 8.78E+03 4.87E+03 1.33E+03 8.90E+03 4.66E+05 Mn-54 O.OOE+OO 8.01E+06 2.13E+06 O.OOE+OO 2.25E+06 O.OOE+OO 6.72E+06 Mn-56 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Fe-55 4.57E+08 2.42E+08 7.51E+07 O.OOE+OO O.OOE+OO 1.37E+08 4.49E+07 Fe-59 3.76E+08 6.08E+08 3.03E+08 O.OOE+OO O.OOE+OO 1.76E+08 6.34E+08 Co-58 O.OOE+OO 1.64E+07 5.03E+07 O.OOE+OO O.OOE+OO O.OOE+OO 9.59E+07 Co-60 O.OOE+OO 6.93E+07 2.04E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.84E+08 Ni-63 2.91E+10 1.56E+09 9.91E+08 .O.OOE+OO O.OOE+OO O.OOE+OO 1.05E+08 Ni-65 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cu-64 O.OOE+OO 2.77E-07 1.67E-07 O.OOE+OO 6.68E-07 O.OOE+OO 1.30E-05 Zn-65 3.75E+08 1.00E+09 6.22E+08 O.OOE+OO 6.30E+08 O.OOE+OO 1.76E+08 Zn-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO . O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO. O.OOE+OO O.OOE+OO Br-85 * ,Q.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 5.78E+08 3.55E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.72E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 4.81E+08 . O.OOE+OO 1.37E+07 . O.OOE+OO O.OOE+OO O.OOE+OO 1.86E+07 Sr-90 1:57E+10 O.OOE+OO 3.15E+08

• O.OOE+OO O.OOE+OO
• O.OOE+OO 1.40E+08 Sr-91 2.26E-10 O.OOE+OO 8.54E-12 O.OOE+OO O.OOE+OO O.OOE+OO 5.00E-10 Sr-92 O.OOE+OO O.OOE+OO O.OOE+OO , O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-90 1.73E+02 O.OOE+OO 4.62E+OO . O.OOE+OO O.OOE+OO O.OOE+OO 4.92E+05 Y-91M O.OOE+OO Q.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-91 1;80E+06 Q.OOE+OO .4.82E+04 O.OOE+OO O.OOE+OO O.OOE+OO 2.40E+08 Y-92 o;ooE+oo O.OOE+OO :O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-93 6.97E-12 O.OOE+OO 1.91E-13 . O.OOE+OO O.OOE+OO O.OOE+OO 1.04E-07 Zr-95 2:67E+06 5.86E+05 .5.22E+05 O.OOE+OO 8.39E+05 O.OOE+OO 6.11E+08 Zr-97 3.16E-05 4.57E~06 2.70E-06 O.OOE+OO 6.56E-06 O.OOE+OO 6.93E-01 Nb-95 3.11E+06 1.21E+06 8.64E+05 , O.OOE+OO 1.14E+06 O.OOE+OO 2.24E+09 Mo-99 O.OOE+OO 1.14E+05 2.82E+04 , O.OOE+OO 2.44E+05 O.OOE+OO 9.44E+04 Tc- 99M O.OOE+OO 1.18E-20 , 1.96E-19 O.OOE+OO 1.72E-19 O.OOE+OO 6.72E-18 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO : O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 t.55E+08 .O.OOE+OO :5.95E+07 I O,.OOE+OO 3.90E+08 O.OOE+OO 4.00E+09 Ru-105 O.OOE+OO O.OOE+OO O.OOE+OO . O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-106 4.44E+09 O.OOE+OO 5.54E+08 i O.OOE+OO 5.99E+09 O.OOE+OO 6.90E+10 Ag-110M 8.39E+06 5.67E+06 4.53E+06 O.OOE+OO 1.06E+07 O.OOE+OO 6.74E+08 Page 242 of 268

Revision 9 February 27, 2017 Table F-15b (Continued) Child Grass-Cow-Meat Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 5.70E+08 1.54E+08 7.59E+07 1.60E+08 O.OOE+OO O.OOE+OO 5.50E+08 Te-127M 1.77E+09 4.78E+08 2.11E+08 4.24E+08 5.06E+09 O.OOE+OO 1.44E+09 Te-127 3.99E-10 1.08E-10 8.56E-11 2.76E-10 1.14E-09 O.OOE+OO 1.56E-08 Te-129M 1.79E+09 5.00E+08 2.78E+08 5.77E+08 5.25E+09 O.OOE+OO 2.18E+09 Te-129 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-131M 6.97E+02 2.41E+02 2.57E+02 4.96E+02 2.33E+03 O.OOE+OO 9.78E+03 Te-131 . O.OOE+OO O.OOE+OO O.OOE+OO . O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 2.09E+06 9.23E+05 1.12E+06 1.34E+06 8.57E+06 O.OOE+OO 9.30E+06 1-130 2.92E-06 5.89E-06 3.04E-06 6.49E-04 8.81E-06 O.OOE+OO 2.76E-06 1-131 1.65E+07 1.66E+07 9.45E+06 5.50E+09 2.73E+07 O.OOE+OO 1.48E+06 1-132 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-133 5.75E-01 7.10E-01 2.69E-01 1.32E+02 1.18E+OO O.OOE+OO 2.86E-01 1-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-135 6.86E-17 1.23E-16 5.84E-17 1.09E-14 1.89E-16 O.OOE+OO 9.40E-17 Cs-134

• 9.22E+08 1.51E+09 3.19E+08 O.OOE+OO
• 4.69E+08 1.68E+08 8.16E+06 Cs-136 1.61 E+07 4.43E+07 2.87E+07 : O.OOE+OO 2.36E+07 3.52E+06 1.56E+06 Cs-137 1.33E+09 1.28E+09 1.88E+08 O.OOE+OO . 4.16E+08 1.50E+08 7.99E+06 Cs-138 ' O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO . O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO . O.OOE+OO O.OOE+OO O.OOE+OO Ba-140 4.39E+07 3.84E+04 2.56E+06 . O.OOE+OO 1.25E+04 '2.29E+04 2.22E+07 Ba-141 O.OOE700 O.OOE+OO O.OOE+OO , O.OOE+OO
• O.OOE+OO .O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O:OOE+OO 'O.OOE+OO : O.OOE+OO O.OOE+OO O.OOE+OO La-140 '5.66E-02 1.98E-02 6.67E-03 ! O.OOE+OO O.OOE+OO O.OOE+OO 5.52E+02 La:.142 O.OOE+OO O.OOE+OO .O.OOE+OO I O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ce-141 2.22E+04 1.11 E+04 1.64E+03 . O.OOE:+-00. 4.85E+03 *o.OOE+OO 1.38E+07 Ce-143 :3,14E-02 1.70E+01 2.46E-03 : O.OOE+OO 7.14E-03 O.OOE+OO 2.49E+02 Ce-144. 2.32E+06 7.26E+05 1.24E+05 I O.OOE+OO 4.02E+05 O.OOE+OO 1.89E+08 Pr-143 3.34E+04 1.00E+04 1.66E+03 i 0.00E+OO 5.44E+03 O.OOE+OO 3.61E+07 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO i O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 ~.19E+04 9.65E+03 7.47E+02 . O.OOE+OO 5.29E+03 O.OOE+OO 1.53E+07 W-187 3.21 E-02 1.90E-02 8.52E-03
• O.OOE.+00 : O.OOE+OO O.OOE+OO 2.67E+OO Np-239 '4.23E-01 . 3.04E-02 2.14E-02 : O.OOE+OO 8.79E-02 O.OOE+OO 2.25E+03 Notes:

2

1) Units are m mrem/yr per µCi/sec with the exception of H-3.

2) For H-3, the units are mrem/yr per µCi/m 3 .

3) The infant age group is assumed to receive no dose through the meat ingestion pathway therefore no dose factors are supplied.

Page 243 of 268

Revision 9 February 27, 2017 Supplemental Table F-A Mixed Mode Joint Frequency Distribution Table Summaries 250 Foot Elevation Data Summary Table of Percent by Dtrectlon and Class E ESE SE SSE s SSW SW WSW w WNW NW NNW Total Class N NNE NE ENE

                                                            .542     .409   .247     .214      .335   .440   .648    .737     .705      .400       6.604 A   .267      .504    .349   .248     .243    .315
                                                            . I 18   . 117  .067     .050      .090   .105   .143    .138     .143      .152       I .590 B   .068      . 110   .085   .055     .079    .069
                                                            .142     .139   .07t     .065      .104   .132   .139

• t4 t .t83 .146 t .892 c . 104 .162 .12' .059 .098 .087

                                                            .741     .887   .552     .603      .978   .933  I. I 15 1.136   1 .361    t.003       13.309 D   .745      .992    .685   .498     .544    .536 1.376     1.887  1.597   1.672     2.358   2.073  2.051   2.097   2.238     t .620     26.327 E  1. 512   I .507   1.234  1. 161  1 .021    .924
                                                            .568     .923  t.196    t.133    t .354   .977   .897    .875     .858      .644      t2.483 F   .729      .603    .521    .386    .409    .410                                                                                             9.265
                                                  .247      .362     .700  t.366   t.480     t.008    .612   .421    .428     .463      .388 G   .499      .412    .352    .283    .246 3.848     5.062  5.097   !1.217    6.227   5.272  5.414   5.552   5.950    4.353       71.471 Total   3.924   4.292     3.346  2.689   2.640    2.588 summary Table of Percent by Dtrect1on and Spead N       NNE     NE     ENE       E      ESE        SE     SSE      s      SSW        SW    WSW       w    WNW       NW       NNW     Total Speed
                                                            .000     .010    .014     .002     .000   .003   .000    .001     .001      .005         .074
  .45    .003      .ooo   .005    .013    .009    .006
                                                                     .035    .026     .023     .027    .027   .027    .030    .026      .031         .459 1.05    .023      .022    .026   .043    .027    .036       .030
                                                             .262     .260   .224     .187     .189    .158   .159    .217    .213       .180      3.391 2.05    .194      .172    .200   .239     .270   .267
                                                   .515      .586     .601   .414     .362     .393    .318   .343    .433     .572      .344      7.238 3.05    .320      .372    .529    .560    .576                                                                                                    9.764
                                           .514    .473      .722     .842   .562     .590     .595    .548   .546    .716     .831      .595 4.05    .478      .599    .629    .522                                                                                                           12.256
                                           .374    .392      .753     .898   .886     .895     .937    .813   .809  t.029   t. 145       .851 5.05    .649      .720    .650    .456                                                                                                           12.467
                                           .247

• 262 .528 .807 .976 .968 . 1. 115 .993 .872 1.215 1.362 .971 6.05 .656 .713 .484 .296 20. t t6

                                           .422    .478      .72'.2 1.237  1.609    L749 2.243       1.856  1.990   1.651   1.628      1.tBO 8.05  1.106     1.257     .615    .372                                                                                                  .187      5.338
                                   .171    .182    .146      .229     .348   .365     .412      .677   .522   .630    .249     .164 10.05     .458       .407   .191                                                                                                                       .369
                           .016    .017    .020    .012      .Of7     .023   .022     .029      .048   .034   .037    .Ott     .007      .010 13.05    .037       .029 18.00     .000      .000    .000    .000    .000    .000      .000     .000   .000     .000      .ooo   .000   .ooo    .000     .000      .000         .000
                                                             .000     .000   .000     .000      .000   .000   .000    .000     .000      .000         .000 99.00     .000      .000    .000    .000    .000    .000 2:640"   2.588     3.848    5.062  5.097    5.217- 6.227     5.272  5.414   5.552   5.950      4.353      7L471 Tota1   3;924     4.292   3;345   2.689 NOTE:       Wind directions in tables are presented in "wind from* and not "wind to* direction.

(prasented in In .order to determine the final mixed mode values, 7.1. 471% of the elevated value the ground level value (presented in the 30 FT Mixed the 250 FT Mixed Mode table) and 28.529% of Mode table) are used to calculate the final values. Page 244 of 268

Revision 9 February 27, 2017 Supplemental Table F-A - Continued Mixed Mode Joint Frequency Distribution Table Summaries 250 Foot Elevation Data Summary Table of Percent by Speed and CI ass Class A B c D E F G Speed

 .45     .001     .ooo   .003      .006    .025     .016  .023 t.05     .006     .004   .005      .034    .147     .070  .193 2.05

• 119 .048 .074 .456 1.047 .618 1.031 3.05 .564 .166 .196 t .332 2.330 1.167 1.485 4.05 .940 . 22 t .275 1 .932 3.494 t .459 1.443 5.05 t .250 .267 .320 2.204 4.388 2.178 1.647 6.05 1.204 .32t .306 2.176 4.544 2.456 1.460 8.05 1.923 .401 .539 3.884 7.909 3.699 t. 760 10.05 .560 . 151 . 161 1. 188 2.279 .784 .215 13.05 .037 .OH .013 .096 .165 .039 .007 18.00 .000 .000 .ooo .coo .ooo .000 .000 99.00 .000 .coo .000 .000 .000 .000 .000 Page 245 of 268

Revision 9 February 27, 2017 Supplemental Table F-A - Continued Mixed Mode Joint Frequency Distribution Table Summaries 35 Foot Elevation Data Summary Table of Percent by Direction and Class Class N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW Total A . 325' .401 . 141 .095 .077 .100 .120 .122 .108 .127 .198 .209 .332 .278 .210 . 186 3.029 B .093 .099 .037 .028 .020 .014 .021 .048 '.041 .020 .056 .061 .080 .049 .050 .058 .775 c . 103 . 122 .047 .027 .030 .028 .028 .047 .029 .031 .065 .077 .090 .0\16 .054 .052 .885 D .708 .607 .317 .291 .266 .182 .186 .283 .281 .283 .607 .505 .664 .4~ .442 .396 6.431 E 1. 140 .850 .531 .507 .431 .288 .289 .656 .894 .818 t.403 1.177 1.133 .62\ .600 .384 11. 722 F .273 .144 .099 .098 .090 .066 . 109 .165 .!1!17 .449 .569 .436 .349 .232\ .175 . 109 3.919 G .059 .029 .027 .018 .031 .038 .039 .063 .412 .289 .247 .159 .119 .114' .081 .042 1. 768 Total 2.700 2.252 1.199 I .065 .946 . 7t7 .792 1.384 2.322 2.017 3. 144 2.623 2.766 I. 764 1.611 1.227 28.529 summary Table of Percent by Direction and Speed Speed N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW ~NW Total

 .45   .001    .002   .001    .ooo  .001  .001    .001   .003     .002     .003    .002  .002    .000    .002  *003       .oo~        .025 t.05   .007    .006   .007    .008  .005  .008    .008   .009 -   .0.19  - .020 _ .021   .012    .011    .011  .015       .Oft        .178 2.05   .082    .053   .034    .027  .033  .042    .058   .047

• 162 .250 .218 . 167 .120 .167 .218 .098 1. 715 3.05 .170 .146 .103 .076 .075 .093 .180 .148 .483* .360 .315 .312 .327 .349 .356 .205 3.699 4.05 .214 .250 .157 .090 .086 .095 .183 .255 .614 .250 .350 .379 .389 .291 .350 .230 A.182 5.05 .273 .311 .149 .084 .090 .066 .127 .245 .469 .225 .369 .382 .391 .255 ..251 . 192 ~,878 6.05 .438 .386 . 181 .091 .107 .080 . .083 .214 .278 .292 .470 .403 .450 .224 . 21 f . 173 4 .\)80 8.05 .892 .607 .268 .225 .208 . 161 .118 .323 .219 .473 1.001 .677 .762 .388 . 190 .262 6. )75 10.05 .413 .313 .208 .333 .213 . 1'8 .032 . U4 .061 .128 .317 .209 .219 .06t .019 .046 2.8~

13.05 .178 .155 .088 .117 .102 .oso .003 .025 .Ot!I .014 .075 .079 .085 .014 .000 .009 1.00~ 18.00 .032 .023 .004 .013 .025 .003 .ooo .000 .000 .001 .005 .003 .012 .003 .000 .ooo . 123 99.00 .ooo .000 .000 .ooo .ooo .000 .ooo .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 Total 2.700 2.252 1.199 t.065 .946 .717 .792 1.384 2.322 2.017 3. 144 2.623 2.766 I. 764 t.611 t.227 28.529 NOTE: Wind directions in tables are presented in *wind from* and not *wind to* direction. Page 246 of 268

Revision 9 February 27, 2017 Supplemental Table F-A - Continued Mixed Mode Joint Frequency Distribution Table Summaries 35 Foot Elevation Data Summary Table of Percent by Speed and Class Class A B c 0 E F G Speed

 .45    .ooo     .ooo    .000    .001      .003   .007   .015 t.05    .001     .000    .002    .004      .032   .048   .091 2.05    .028    .010     .010    .104      .421   .544   .658 3.05    .198     .055    .062    .486    t .333  1.014   .5St 4.05    .445    .098     .104    .786    t. 701   .81.8  .230 5.05    .424    .093    . 118    .830    1. 701   .582   .129 6.05    .429    .120    .146     .999    1. 918   .404   .063 8.05    .937     .259    .275   1.985    2.893    .403   .023 10.05    .405     .098    .103    .845    I .270   .078   .007 13.05     .147    .039    .054    .348      .401   .019   .001 f8.00    .014     .004    .012    .043      .049   .001   .000 99.00    .000     .000    .000    .000      .000   .000   .000 Page 247 of 268

Revision 9 February 27, 2017 Supplemental Table F-8 Ground Level Joint Frequency Distribution Table Summaries Summary Table of Percent by Dfrectfon and Class Class N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW Total A .573 .881 .500 .366 .343 .440 .582 .503 .397 .324 '.509 .640 .94 I .989 .950 .666 9.605 B . f75 .211 .131 .089 .087 .086 . t13 .157 .13t .058 .139 .176 .219 .t71 .215 .206 2.363 c .213 .281 .165 .1t3 .103 .120 .152 .171 .115 .089 .168 .207 .235 .182 .250 .209 2.771 D 1 .488 1.629 1.012 .801 .756 .681 .797 .971 1.036 .783 1.610 f .454 1.820 1.478 1.967 1.433 19.716 E 2.801 2.521 1.683 1 .537 1. 317 1.065 1.255 2. 107 2.835 2.531 3.911 3.300 3.293 2.756 3.239 1. 907 38.058 F f.155 .710 .463 .384 .389 .313 .509 .692 1.908 1.815 1.987 1.547 1.385 1.331 1.143 .707 16.439 G .472 .253 .176 .132 .127 .192 .258 .353 1.603 1.642 1.448 .987 1 .028 1.192 .770 .416 11.049 Total 6.877 6.486 4.130 3.421 3.122 2.898 3.667 4.954 8.025 7.241 9.772 8.3tt 8.921 8.097 8.534 5.543 100.000 Summary Table of Percent by Df rectfon and Speed Speed N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW Total

 .45    .048   .065   .058   .009    .022   .012     .018    .037   .027    .042  .027    .052    .042    .('43  .075      .054       .63f 1.05    .206   .168   .156   .t18    . 12t  . 118    .135    .134    .216   .238  .271    . 197   .233    .2G4   .350      .234     3. 158 2.05    .903   .674   .518   .467    .458   .558     .636    .534  t.254  t .834 1.675  1.396   1 .326  t .837  2.043      .990    17. 102 3.05  1 :089 L031     .861  -. 743   .683   .806   L309     1.075  2.628  1.993  1. 781 1.670   1.944   2.22U   2.304    t .333    23.474 4.05  1.054 ... 309   .883 - .554    ~456   .478    -.846   1.269  2.134  t.088  1.655  I .639  1. 715  1.534   1.873    1.234     19.724 5.05    .931 1.129    .586   .345    .338   .230     .369    .797  1.005    .755 1.450  1.328   t.404   I .079  1.079      .836    13 .66 I 6.05    .906   .841   .409   .273    .279   .231     .161    .477   .418  -.573  1.176    .894  1.007     .550   .537      .468     9.201 8.05  1. 119   .779   .354   .415    .393   .283     .158    .482   .265    .575 1.338    .845    .936    .489   .253      .338     9.022 10.05    .411   .312   .213   .366    .246   .t27     .032    .123   .063    .129  .318    .208    .219    .062   .019      .046     2.896 13.05    .177   . f54  .087   . t18   .102   .050     .003    .026   .015    .014  .075    .078    .085    .014   ."1.00    .009     1.008 18.00    .032   .023   .004   .013    .024   .003     .000    .000   .000    .001  .005    .003    .012    .003    .()\')   .000       . t2'2 99.00    .000   .ooo   .000   .000    .000   .000     .ooo    .000   .000    .000  .000    .ooo    .000    .000    .001;    .ooo       .000 Total  6.877   6.486  4.130 3.421    3. 122 2.898   3.667    4.954  8.025  7.241  9.772  8. 311  8.921   8.097   8.534    5.543    100.000 NO'l'E:   Wind directions in tables         a~e    presented in *wind from* and not *wind to* direction.

Page 248 of 268

Revision 9 February 27, 2017 Supplemental Table F Continued Ground Level Joint Frequency Distribution Table Summaries Summary Table of .Percent by Speed and Class Class A B c D E F G Speed

 .45    .006    .004    .005    .040      .172    .154   .249 t.05    .036    .013    .024    . 121    .797     .823  1.344 2.os    .464    . t4 t  .t94   t. 591   4.805   4.405   5.502 3.05  1.606     .433    .507   3.810    8.847   5.409   2.862 4.05  2.520     .563    .613   4.2tt    S.107   2.995    .715 5.05  t.909     .419    .509   3.384    5.795    t. 394  .251 6.05  1. 21'    .306    .368   2.527    4.023     .681   .085 8.05  t .281   .342     .381   2.766    3.745     .478   .030 10.05    .410    .099    .104    .877    t.317     .078   .010 13.05    .147    .039    .054    .348      .400    .019   .00, te.oo    .Ot4    .004    .012    .042      .049    .001   .ooo 99.00    .000    .000    .ooo    .000      .000    .000   .000 Page 249 of 268

Revision 9 February 27, 2017

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Revision 9 February 27, 2017 Meteorological Tower Shiloh Blvd.

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                                                                  ~ J Liquid Effluent Release Point OFFSITE DOSE CALCULATION MANUAL ZION STATION 200' 50'0'      200' 400' GRAPHIC SCALE 1*. 200'-0"
  -            Restricted Area Boundary      RESTRl.CTED AREA BOUNDARY

• Meteorological Tower M5593.00I 9-112 Page 251 of 268

Revision 9 February 27, 2017 I Appendix 0 ODCM BASES and REFERENCE DOCUMENT Page 252 of 268

Revision 9 February 27, 2017 Appendix 0 ODCM BASES and REFERENCE DOCUMENT This document provides supplementary information on the bases of material in Chapters 1 through 6 and Appendices A through C. 0.1 BASES OF CHAPTER 1, INTRODUCTION . 0.1.1 Offsite Radiation Doses Due to Nuclear Power Plants It is estimated that the average radiation dose received by an individual in the United States is about 625 mrem/yr and that nuclear power stations account for less than two parts in a thousand of this radiation. These figures are based on data in Table 8.3 of NCRP 160, (Reference 80). The table includes the following data: Average Individual Source Dose (mrem/yr) Ubiquitous Background 311 Medical 300 Consumer 13 Industrial, security, medical, educational and research 0.3 Occupational 0.5 Total 624.8 The radiological effects of nuclear power station operation on the environment are characterized as "usually so small that they are masked by normal fluctuations in natural background sources and by the normal uncertainties of the measurement process." The text of Chapter 1 also states that "assessing compliance with regulatory limits requires calculations because some of the limits involve quantities that cannot be directly measured ... " Limits that cannot be feasibly monitored by direct measurement include doses to internal organs and doses attributable to particular pathways (see Appendix A). 0.1.2 Historical and Concurrent Meteorology The use of historical average atmospheric conditions for assessment of radiation doses due to airborne effluents is stipulated in the Bases Section 12.4 and 12.6 of the RETS. 0.2 BASES OF CHAPTER 2, REGULATIONS AND GUIDELINES See the documents cited in the text. 0.3 BASES OF CHAPTER 3, PATHWAYS General information on offsite exposure pathways may be found in several texts and monographs (see References 16, 18, 20, 22, 25, 28, 29 and 31). Page 253 of 268

Revision 9 February 27, 2017 0.3.1 Airborne Releases (Section 3.1) Zion addresses radiation dose for the airborne pathways considered in NUREG 0133 (Reference 14). The airborne pathways found in NUREG 0133 are:

• Exposure to a cloud of noble gas.
• Exposure to standing on a contaminated ground plane.
• Inhalation of tritium and/or particulates.
• Ingestion of contaminated vegetation.
• Ingestion of contaminated cow and/or goat milk.
• Ingestion of contaminated cow meat.

The noble gas exposures are assessed at the site boundary. The ground plane, inhalation and ingestion exposures are determined at the location in the unrestricted area where the combination of pathways, age group and airborne deposition produce the highest potential dose to a member of the public. The ground plane and inhalation pathways are considered present at every location in the unrestricted area. Ingestion pathways are considered present at the locations determined by the land use census. Soil uptake is not considered by the NU REG 0133 methodology but is addressed by Regulatory Guide 1.109 (Reference 6). Ingestion exposure through the mechanism of soil uptake has been shown to be minor as compared to direct deposition onto foliage. This assumption is based upon an analysis of three nuclides: 1-131, Cs-134 and Cs-137. In a study of nuclear power station radiation exposures in the upper Mississippi River basin, these nuclides were found to contribute the major portion of the dose due to exposure to airborne radioactivity deposited on soil (see page IX-12 of Reference 20). The relative importance of uptake from soil was assessed by use of Equation C-5 of Regulatory Guide 1.109. This equation calculates radioactivity concentration in vegetation. The first term inside the curly brackets*of the equation represents the contribution from radioactivity directly deposited on plant foliage. The second term represents the contribution from radioactivity initially deposited on the ground and then taken up through the root system of the vegetation. For each of the three nuclides, the ratio of the uptake term to the direct deposition term was evaluated for two pathways; the grass-cow-milk pathway and the pathway of direct ingestion by man of produce and leafy vegetables. The parameter values used and the results are in Table 0.:1 of this document: For the six cases, the soil uptake term ranged from about 0.01 % to about 10% of the direct deposition term (see lhe column labeled "Uptake + Direct Dep" in Table 0-1 ). 0.3.2 Liquid Releases (Section 3.2) Zion addresses radiation dose for the waterborne pathways considered in NU REG 0133. The waterborne pathways found in NUREG 0133 are:

• Ingestion of contaminated potable water.
• Ingestion of fish taken from contamiRated water.
• Ingestion of invertebrates taken from contaminated water.

These dose pathways are considered unless demonstrated not be present. Exposure can also occur through recreation (shoreline activities, swimming and boating) and irrigation pathways (irrigation of directly ingested vegetation and food crops for animal consumption), but these are considered to be minor when compared to direct ingestion.

• The liquid pathways were evaluated based on surveys of surface water use and on liquid pathway dose calculations. Table 0-2 of this document summarizes principal results of the surface water use surveys.

On the basis of these surveys, it was decided to ignore the following pathways: Page 254 of 268

Revision 9 February 27, 2017 Ingestion of vegetation contaminated because of irrigation with water containing radioactivity from plant liquid discharges. Ingestion of radioactivity that entered an animal food product (milk or meat) because the animal drank water contaminated by radioactive liquid effluents from the plant or because the animal *consumed feed contaminated by irrigation with such water. Calculations were performed to estimate annual doses from the following liquid pathways:

• Consumption of drinking water.
• Consumption of fish.
• Shoreline activities (with exposure to shoreline sediments).
• Swimming and boating.

0.3.3 Radiation from Contained Sources (Section 3.3) Annual radiation doses due to contained sources of radioactivity at Zion are addressed in EH&S TSDs: 13-007, "Evaluation of Waste Classification A, B and C Storage and Staging Dose Rates"; 13-008, "Evaluation of ISFSI and Associated Processes Dose Rates" and 13-009, "Member of the Public Dose from All Onsite Sources." 0.4 BASES OF CHAPTER 4, INTRODUCTION TO METHODOLOGY Most of the material in this chapter is based on Appendix A. Additional information on bases is provided below. 0.4.1 Introduction of Time Factors The release rate of radioactive materials is the discharge of radioactive materials in liquid or gaseous effluents per unit time. The second is used as the practical reporting time unit for establishing release rates to show compliance with instantaneous limitations for noble gases. The hour is used as the practical reporting time unit is established average release rates to show conformance with the requirements of 10CFR50 for particulates released in gaseous effluents and for liquids effluents. 0.4.2 Release Point Classifications (Section 4.1.4) For additional information, see Meteorology and Atomic Energy 1968 (Reference 18), Section 3-3.5.2, and Regulatory Guide 1.111 (Reference 7), Section 8.2. 0.4.3 Airborne Releases (Section 4.2) The energies and intensities of radiations emitted from them are listed in standard compendia (e.g., see Reference 70). Gamma Radiation Mean Free Path The mean free path X of gamma radiation is calculated using the following equations: X= 1/µ (0-1)

        µ = (µ/p)p                                                  (0-2)

Page 255 of 268

Revision 9 February 27, 2017 X Mean Free Path [cm] The average distance traveled by a photon before interacting with matter.

    µ Attenuation Coefficient of Air Probability of photon absorption or scattering per unit distance traveled in air.

p Density of Air [glee] The results for photon mean free path (Section 4.2.1) are based on data in Reference 71. For a 4-MeV photon, the calculation is as follows: 2

    µIp      = 0.0308 cm /g (per Table 5.2 of Reference 71) p = 0.001293 g/cc (per Table 1.3 of Reference 71)
    µ = (0.0308 cm 2/g) (0.001293 glee)= 3.982E-5 cm- 1 1

X = (1/3.982E-5 cm- )(1 ft/30.48 cm)= 823.9 ft Range of Beta Radiation in Air The results for beta radiation range (Section 4.2.2) are based on equations in Reference 38. The range of beta radiation with a maximum energy greater than 2.5 MeV is given by the following equation (Reference 38, Page 100): R = (530) (Emax) -106 (0-3) R Range Emax Maximum Beta Energy [MeV] For Emax = 4 MeV, 2 R = (530)(4) - 106 = 2.01E3 mg/cm For an air density of 1.293 mg/cc, the range is 2 [(2.01 E3 mg/cm )/(1.293 mg/cc)] (1 ft/30.48 cm) = 51.0 ft For 0.01 ~ Emax ~ 2.5 MeV, the range of beta radiation is given by the following equation (Reference 38, Page 99): R = (412)(Emax)1.265 -(0.0954)(1n Emax) (0-4) where R and Emax have the same definitions as for Equation 0-3. For example, for Emax = 0.1 MeV, R= (412 ) (0. 1)1.2ss-10.os54)1n(o.11= 13 _5 mg/cm2 For an air density of 1.293 mg/cc, the range is 2 [(13.5 mg/cm )/(1.293 mg/cc)] (1 ft/30.48 cm)= 0.34 ft Page 256 of 268

Revision 9 February 27, 2017 0.4.4 Radionuclide Types Considered For Airborne Effluent Exposure Pathways (Table 4-1) The radionuclide types considered are the same as those recommended for concern in Regulatory Guide 1.109 except that carbon-14 is omitted. The reasons for this are discussed in the next section. 0.4.5 Reasons for Not Calculating Doses Due to Carbon-14 Carbon-14 is not considered because the RETS does not require it. Zion Station is required to consider only the following non-noble gas radionuclides: tritium and all radionuclides in particulate form with half-lives greater than 8 days. Although carbon-14 has a half-life of 5730 years, it does not fall in the last category (in particulate form with half-life greater than 8 days) because it is emitted as a gas, mainly C0 2 (see Reference 29, Page 167). Moreover, carbon-14 was not found to be a significant contributor to offsite radiation dose in a study of the potential radiological implications of nuclear facilities in the upper Mississippi River basin (see Reference 20, Page IX-8, Table IX-2). 0.5 BASES OF CHAPTER 5, MEASUREMENT See the documents cited in the text. 0.6 BASES OF CHAPTER 6, IMPLEMENTATION OF THE OFFSITE DOSE ASSESSMENT PROGRAM Chapter 6 is based on ZionSolutions' organizational structure and departmental responsibilities. 0.7 BASES OF AIRBORNE EFFLUENT CALCULATIONS (SECTION A.1 AND APPENDIX B) The methodology used to calculate doses and dose rates due to releases of radioactivity in airborne effluents is discussed below. The calculations use equations presented in Section A.1 of Appendix A. The equations involve meteorological transport and dose factors that are either obtained from the literature or calculated as described in Appendix B.

• For the most part, the methodology of this manual for airborne effluent dose calculations is identical to that of Regulatory Guides 1.109 (Reference 6) and 1.111 (Reference 7). In the discussion below, special attention will be given to the few differences.

0. 7 .1 Release Point Classifications (Section A.1.1 of Appendix A)

Regulatory Guide 1.109 uses two classifications for airborne releases (see Reference 6, Regulatory Position C.2):

• Releases from free standing stacks more than 80 meters high.
• All other releases.

This manual uses three classifications for airborne releases: stack, ground and vent level. The classifications used here are based on Regulatory Positions C.2.a and C.2. b of Regulatory Guide 1.111. Page 257 of 268

Revision 9 February 27, 2017 0.7.2 Meteorological Data (Section B.1.1 of Appendix B) The information in Section B.1.1 of Appendix B is based on Sargent & Lundy reviews and analyses of meteorological data from Zion. The procedure for treating calms is based on guidance in Regulatory Guide 1.111, Regulatory Position C.4. 0.7.3 Joint Frequency Distribution (Section B.1.2 of Appendix B) The information in Section B.1.2 of Appendix B is based on discussions with Sargent & Lundy. The procedure for determining the JFD for a vent release is based on Regulatory Position C.2.b of Regulatory Guide 1.111. An historical average JFD was calculated at Sargent & Lundy by a computer program that later evolved into the computer program METWRSUM (Reference 75). For further information on these calculations, see Reference 76. Wind speed and direction may change with height. In accordance with Regulatory Position C.2.b of Regulatory Guide 1.111, JFD calculations for elevated releases were made using wind parameters representative of conditions at the actual release height, and calculations for ground level releases were made using wind parameters corresponding to a height of approximately 10 meters. As noted in Reference 76, in some cases interpolation of wind speed data measured at different heights was used to obtain data characteristic of the height of interest. 0.7.4 Average Wind Speed (Section B.1.3 of Appendix B) The equations for obtaining average wind speed are based on the standard method of determining the average value of a quantity for which the frequency distribution is known. Average wind speeds Zionb were computed using Sargent & Lundy computer program AZAP (Reference 77). Regulatory Position C.2.a of Regulatory Guide 1.109 and C.1.c of Regulatory Guide 1.111 specify that a wind speed class be represented by the wind speed of its midpoint (i.e., average of its upper and lower limits). In the calculations this is done for each wind speed, class except the highest. The highest class contains all wind speeds greater than a specified value and so has an undefined upper limit. This class is represented by the lower limit of its wind speed range in all calculations for this manual (calculations of average wind speed, x!Q, gamma dose factors, and total body dose factors). 0.7.5 Gaussian Plume Models (Section B.2 of Appendix B) For discussion of the Gaussian plume diffusion model and its applications to dose assessment, see References 18 (Sections 2-7.2, 3-3, 4-6.2, 7-4, and 7-5), 24, 31 (Section 2.1), and 22 (Chapter 3). Equation B-9 of Appendix B is identical to Equation 3.115 on Page 99 of Reference 18. Equation B-10 of Appendix Bis derived from Equation B-9 of Appendix Bas follows: A location at ground level (z =0) is assumed. Equation B-9 of Appendix B becomes: (0-5) This expression for x(x,y,O) is integrated in the crosswind direction from

                 =

y -oo to +oo. This yields the following result (see Equation 3.143 of Reference 18): [21/2Q/(1t1/20"zU)]exp(-h2e2/2a2z) Page 258 of 268

Revision 9 February 27, 2017 The above expression is divided by the width of a sector at downwind distance x, 2nx/16. The result is: that is equal to 2 2 [2.032Q/(crz u x)]exp(-h J2cr z) The result above is multiplied by a fraction f representing the fraction of time that the wind blows into the sector of interest. This yields 2 2 [2.032 f Q/( O'z u x)]exp(-h J2cr z) that is identical to the expression in Equation B-10 of Appendix Band also to Equation 3.144 of Reference 18. 0.7.6 Relative Concentration Factor x!Q (Section 8.3 of Appendix B)

0. 7.6.1 Stack Release Equation B-13 of Appendix Bis the formula for calculating the relative concentration factor (x/Q)s due to a stack release. Equation B-13 of Appendix Bis obtained from the formula for sector-averaged concentration, Equation B-10 of Appendix B, and is of the same form as Equation 3 of Regulatory Guide 1.111. In applying Equation B-13 of Appendix B, the vertical plume spread is calculated in the way specified in the regulatory guide.

The effective release height is calculated with Equation B-14 of Appendix B. The formulas used are in accordance with those in Regulatory Guide 1.111. However, the following should be noted: Plume heights are limited to a maximum of 100 meters. This is done to allow use of the plume depletion and relative deposition data in Regulatory Guide 1.111. These data are not provided for release heights above 100 meters. The limitation to 100 meters represents a conservative approximation for cases in which the release height and the plume rise formulas would lead to higher plumes. Due to the general flatness of the terrain in the vicinity of Zion, all terrain correction parameters were taken as zero. Plume rise due to buoyancy was ignored because typical nuclear power plant plumes are not significantly warmer than room temperature. This neglect of buoyancy (which can be significant for plumes from fossil plants) is in accord with the guidelines of Regulatory Guide 1.111. The regulatory guide states that plume rise is calculated in accordance with Reference 78, which neglects rise due to buoyancy (see last sentence on Page 5 of Reference 78). Page 259 of 268

Revision 9 February 27, 2017 0.7.6.2 Ground Level Release Equation 8-25 of Appendix B is the formula for calculating the relative concentration factor (x/Q) 9 due to a ground level release. Equation 8-25 of Appendix 8 is obtained from the formula for sector-averaged concentration, Equation 8-10 of Appendix B, and is of the same form as Equation 3 of Regulatory Guide 1.111. In applying Equation 8-25 of Appendix 8, the vertical dispersion coefficient is calculated using Equations 8-26, 8-27 and 8-28 of Appendix 8, which are based on the prescription in Regulatory Position C.2.c. 0.7.6.3 Vent Release Equation 8-29 of Appendix 8 may be used for calculating the relative concentration factor (x/O)v due to a vent release. The relative concentration factor is obtained as a mixture of stack and ground level factors in accordance with the guidelines in Regulatory Position C.2.b of Regulatory Guide 1.111. 0.7.6.4 Removal Mechanisms Regulatory Position C.3 of Regulatory Guide 1.111 discusses three removal mechanisms that reduce airborne radioactivity concentration: radioactive decay, dry deposition and wet deposition. In the dose calculations involving x/Q (see Appendix A), radioactive decay is taken into account by adjusting the measured release rate of each radionuclide for radioactive decay in transit from the release point to the dose point. However, wet and dry deposition are not considered. This is a conservative approximation made to simplify the calculations. If these deposition mechanisms were considered, the X/Q values for noble gases would be different from those for particulate. 0.7.6.5 Gamma-xJQ (Section B.3.5) The noble gas dose factors used in Equations A-1, A-3, A-4, A-5 of Appendix A are taken from Regulatory Guide 1.109, Table 8-1. These values are based upon assumption of immersion in a semi-infinite cloud. For ground level and mixed mode releases this tends to overestimate the gamma air dose arising from a plume that is actually finite in nature. For elevated releases, the Regulatory Guide 1.109 noble gas dose factors will underestimate exposure as they consider only immersion and not that portion of exposure arising from sky shine. At distances close in to the point of elevated release, the ground level concentration as predicted by xtQ will be essentially zero. In such a case, the sky shine component of the exposure becomes significant and must be considered. The gamma-x/Q provides a simplified method of calculating gamma air dose and dose rates for a finite and/or elevated plume. Regulatory Guide 1.109, Section C.2 and Appendix 8 provide the methodology for calculating finite cloud gamma air dose factors from which the gamma-x/Q values can be derived. The gamma-x/Q is defined such that for a given finite cloud the semi-infinite 'cloud methodology will yield the same gamma air dose as the finite cloud methodology. Three gamma-x/Q values are defined: for stack, vent and ground level releases, respectively. The gamma-x/Q values are calculated by Equations 8-30, 8-31 and 8-32 of Appendix 8 and makes use of the finite cloud gamma air dose factors described in Section 8-5 of Appendix 8.

• These equations also utilize a noble gas nuclide fraction. These fractions can be based upon historical data or a calculated noble gas source term.
• Page 260 of 268

Revision 9 February 27, 2017 0.7.7 Relative Deposition Factor D/Q (Section 8.4 of Appendix 8) Equations 8-34, B-35, and B-36 of Appendix B are used to calculate values of the relative deposition factor 2 D/Q [1/m ]. These equations use data on deposition rate Dr [1/m] provided in Figures 6 through 9 of Regulatory Guide 1.111. Values of D/Q are obtained from Dr in accordance with the prescription in paragraph 5 of Regulatory Position C.3.b. Equation 8-37 of Appendix 8 applies to a vent release and provides a value that is a mixture of stack and ground level factors in accordance with the guidelines in Regulatory Position C.2.b of Regulatory Guide 1.111. 0.7.8 Gamma Air Dose (Section A.1.2.1 of Appendix A and Section 8.5 of Appendix 8) 0.7.8.1 Dose (Equation A-1 of Appendix A) Gamma air dose is calculated by Equation A-1 of Appendix A. This equation makes use of a term referred to as gamma-x/Q (gamma-chi-over-q) which is explained in Section 4.2.1.1. It is derived from the methodology of NUREG 0133, Section 5.3.1 .. NUREG 0133 deals only with two classes of noble gas releases; those from free-standing stacks more than 80 meters high and all other noble gas releases. Equation A-1 of Appendix A contains terms representing the appropriate release point classifications discussed in Section 4.1.4. The use of three release point classifications is based on Regulatory Guide 1.111, Regulatory Position C.2. The dose factors M1 used in Equation A-1 of Appendix A are identical to the gamma air dose factors DFB 1 specified in Table 8-1 of Regulatory Guide 1.109. 0.7.8.2 Dose Factors (Section 8.5 of Appendix 8) Calculation of gamma-x/Q involves the use of finite plume gamma air dose factors, each of which represents dose rate at a specified point per unit of radioactivity release rate. The dose factors are calculated by Equations 8-40 through 8-42 of Appendix 8. Equation 8-40 of Appendix 8 is used to calculate the finite plume gamma air dose factors for a stack release. The formula is based on Equations 6 and B-1 of Regulatory Guide 1.109. Except for notation, Equation B-40 of Appendix 8 and the regulatory prescription are identical. The finite plume gamma air dose factors for a ground level release are obtained by Equation 8-40 of Appendix B using the ground level joint frequency distribution data and assuming an effective release height of zero. The use of a finite plume model differs from NUREG 0133 in that ground level releases are based on a semi-infinite cloud model (see Equation 7 of Regulatory Position C.2.b). The approach used here is more realistic than that in the regulatory guide. Equation 8-42 of Appendix 8 is used to calculate the gamma air dose factors for a vent release. The dose factors are obtained as a mixture of stack and ground level dose factors in accordance with the guidelines in Regulatory Position C.2. b of Regulatory Guide 1.111. 0.7.8.3 Use of Unrestricted Area Boundary Values for Gamma Air Dose Factors To assess compliance with RETS limits on gamma air dose, maximum offsite values of gamma air dose should be determined. Therefore, the gamma-x/Q values should be determined for the offsite locations where they are maximum. However, the values provided in Table F-5b of Appendix F are for the unrestricted area boundary. They are judged to be very good approximations to the maximum offsite values. Page 261 of 268

Revision 9 I Febrmuy 27, 2017 This judgment is based on published values for finite cloud gamma air dose factors used to calculate gamma-x/Q (see Reference 79). Reference 79 provides values of the gamma air factor as follows: For 13 of the 15 noble gas radionuclides included in the ODCM. For each of the seven atmospheric stability classes considered in this manual (A through G). For two release heights (0 and 100 meters). As a function of distance from the release point. (Data is provided for six downwind distances over the range from 400 to 16,090 meters.) Examination of the dose factor in Reference 79 for the sector-averaged meandering plume model reveals the following: For a ground level release, the dose factor always decreases as distance from the release point increases. (The plume broadens as it moves away from the release point.) For an elevated release, the dose factor decreases as distance from the release point increases with only a few exceptions (five exceptions among the 546 dose factors that are provided). The exceptions involve only weak gamma emitters (Xe-131m, Xe-133m, and Xe-133) in combination with certain stability classes. (The exceptions are due to portions of an elevated plume moving closer to the ground as the plume moves away from the release point. This increases dose rate at ground level.) The gamma air dose factors used to calculate gamma-x/Q in Appendix Fare based on historical average atmospheric conditions (see Section 4.1.5). Therefore, each gamma air dose factor involves an average over all of the meteorological stability classes, nearly all of which have dose factors that decrease as distance from the release point increases. Furthermore, the gamma air dose factors in the ODCM for ground level releases or for mixed mode releases include a large ground level component. The ground level dose factors will always decrease as distance increases, and the mixed mode factors are likely to decrease with distance because of the effect of their ground level component. Thus, it is judged that a gamma-x/Q value calculated at the unrestricted area boundary in each sector is a very good approximation to the highest offsite value for that sector. 0.7.9 Beta Air Dose (Section A.1.2.2 of Appendix A and Section B.7 of Appendix B) Beta air dose is calculated by Equation A-2 of Appendix A This equation is explained in Section 4.2.2. It is based on Section 5.3.1 of NUREG 0133. Like Equation A-1 of Appendix A for gamma air dose, Equation A-2 of Appendix A contains a term representing each of the three release point classifications discussed in Section 4.1.4. The use of three release point classifications is based on Regulatory Guide 1.111, Regulatory Position C.2. The dose factors N1 used in Equation A-2 of Appendix A are identical to the beta air dose factors DFB 1 specified in Table B-1 of Regulatory Guide 1.109. 0.7.10 Total Body Dose (Section A.1.2.3 of Appendix A and Section B.6 of Appendix B) Total body dose is calculated by Equation A-3 of Appendix A This equation is explained in Section 4.2.3. It is based on Section 5.3.1 of NU REG 0133. Like Equation A-1 of Appendix A for gamma air dose, Equation A-3 of Appendix A contains a term representing each of the three release point classifications discussed in Section 4.1.4. The use of three release point classifications is based on Regulatory Guide 1.111, Regulatory Position C.2. The dose factors K1 used in Equation A-3 of Appendix A are identical to the beta air dose factors DFB 1 specified in Table B-1 of Regulatory Guide 1.109. Page 262 of 268

Revision 9 February 27, 2017 0.7.11 Skin Dose (Section A.1.2.4 of Appendix A and Section 8.7 of Appendix B) Skin dose is calculated by Equation A-4 of Appendix A This equation is explained in Section 4.2.4. It is based on Section 5.2.1 of NUREG 0133. Like Equation A-1 of Appendix A for gamma air dose, Equation A-4 of Appendix A contains a term representing each of the three release point classifications discussed in Section 4.1.4. The use of three release point classifications is based on Regulatory Guide 1.111, Regulatory Position C.2. The dose factors Li and Mi used in Equation A-4 of Appendix A are identical to the gamma and beta skin dose factors DFSi specified in Table B-1 of Regulatory Guide 1.109. The gamma contribution to skin dose is calculated with gamma-x/Q in the same manner as that of Equation A-1 of Appendix A to calculate gamma air dose. *This approach differs from that of the regulatory guide in that a finite cloud model is used in accounting for the portion of the dose contribution to the skin due to gamma emissions. This is more realistic than the semi-infinite cloud model used in the regulatory guide. 0.7.12 Total Body Dose Rate (Section A.1.3.1 of Appendix A) Total body dose rate is calculated by Equation A-5 of Appendix A This equation is explained in Section 4.2.3. 0.7.13 Skin Dose Rate (Section A.1.3.2 of Appendix A) Skin dose rate is calculated by Equation A-6 of Appendix A This equation is explained in Section 4.2.4. 0.7 .14 Dose Due to Non-Noble Gas Radionuclides (Section A.1.4 of Appendix A) The term dose in the title of Section A.1.4 of Appendix A includes both dose and dose commitment (see Section 4.1.1 ). This is based on its usage in the standard Technical Specifications (see Specification 3.11.2.3 of References 2 and 3). The dose due to non-noble gas radionuclides is calculated by Equation A-7 of Appendix A. It is based on Section 5.3.1 of NUREG 0133. 0.7.15 Ground Deposition Dose (Section A.1.4.1 of Appendix A and Section 8.8 of Appendix B) The dose due to deposited radionuclides is calculated by Equations A-7and A-8 of Appendix A These equations are explained in Section 4.2.5. The methodology is based upon Sections 5.3.1 and 5.3.1.2 of NU REG 0133. The ground plane dose conversion factors DFGi used in Equation A-8 of Appendix A are identical to the dose factors provided in Table E-6 of R.G. 1.109. Equation A-8 of Appendix A uses a value of 0. 7 for the shielding factor which accounts for shielding due to occupancy of structures. This value is specified in Section 1 of Appendix B, Section II; of Regulatory Guide 1.109 and Section 5.3.1.2 of NUREG 0133.

• Page 263 of 268

Revision 9 February 27, 2017 0.7.16 Inhalation Dose (Section A.1.4.2 of Appendix A and Section B.9 of Appendix B) The dose commitment due to inhalation is calculated by Equations A-7 and A-9 of Appendix A This equation is explained in Section 4.2.6. It is based on Sections 5.3.1 and 5.3.1.1 of NUREG 0133. The dose factors, DFAija. u.sed in Equation A-9 of Appendix A for 10CFR50 Appendix I compliance are identical to the inhalation dose factors provided in Tables E-7 through E-10 of Regulatory Guide 1.109.

0. 7.17 Food Pathways Doses (Section A.1.4.3 of Appendix A and Section B.10 of Appendix B)

The dose commitment due to food pathways is calculated by Equations A-7 and A-10 through A-15 of Appendix A These equations are discussed in Section 4.2.7. They are based the methodology found in Sections 5.3.1.3 through 5.3.1.5 of NU REG 0133. The dose calculations for particulate account for doses resulting from dry deposition of radioactive materials onto the ground and foliage. Wet deposition is not considered in evaluating long-term-average environmental doses at Zion for the reason put forth in Regulatory Guide 1.111 (see Page 1.111-12): 0.7.18 Inhalation Dose Rate (Section A.1.5 of Appendix A) Inhalation dose commitment rate is calculated by Equation A-16 of Appendix A This equation is explained in Section 4.2.6. 0.8 BASES OF LIQUID EFFLUENT CALCULATIONS (SECTION A.2 and Appendix B; SECTION II) This section presents bases of the methodology used to calculate doses and radioactivity concentrations due to releases of radioactivity in liquid effluents. The calculations use equations presented in Section A.2 of Appendix A The equations involve transport and dose factors that are determined as described in Appendix 8; Section II. 0.8.1 Dose (Section A.2.1 of Appendix A and Section B.15 of Appendix B) The dose due to radioactive materials in liquid effluents is calculated by Equations A-17 through A-20 of Appendix A The dose is based upon the sum of contributions from drinking water (calculated by Equations A-17, A-18 and A-19 of Appendix A) and fish (calculated by Equations A-17, A-18 and A-20 of Appendix A). The equations are explained in Section 4.3 and Section 8.15 of Appendix 8. They are based on Sections 4.3 and 4.3.1 of NU REG 0133. For Zion the flow and dilution parameters in Equations A-18 and A-19 of Appendix A are determined using the Lake Michigan model. The assumptions of this model are stated in Section 8.15.3.1.2 of Appendix 8. The assumptions used to obtain the additional dilution parameter for water consumption (Z = 10) are based on judgment, and the assumptions used to obtain the dilution flow for fish consumption (Dw = 6) are based on the cited observational data. 0.8.2 Concentration Due to Tank Discharges (Section A.2.3 of Appendix A) The concentration of radioactivity in tank discharges is calculated by Equation A-22 of Appendix A The basis of this equation is explained in Section 8.16 of Appendix 8. Page 264 of 268 L

Revision 9 February 27, 2017 0.9 BASES OF CALCULATIONS OF DOSE DUE TO CONTAINED SOURCES (SECTION A.3) Annual radiation doses due to contained sources of radioactivity at Zion are addressed in EH&S TSDs: 13-007, "Evaluation of Waste Classification A, B and C Storage and Staging Dose Rates"; 13-008, "Evaluation of ISFSI and Associated Processes Dose Rates" and 13-009, "Member of the Public Dose from All Onsite Sources." 0.10 BASES OF APPENDIX C, GENERIC DATA The bases of the data in Appendix C are presented in Appendix C. Page 265 of 268

Revision 9 February 27, 2017 Table 0-1 Comparison of Contributions of Direct Deposition and Soil Uptake Terms To Radioactivity Concentration in Vegetation For the Grass-Cow-Milk Pathway: Ai Aw AEI ~ I (hrs- 1) (hrs* 1) (hrs- 1) (hrs) 1-131 1.0 3.59E-03 2.1E-03 5.69E-03 720 Cs-134 0.2 3.83E-05 2.1E-03 2.14E-03 720 Cs-137 0.2 2.62E-06 2.1E-03 2.10E-03 720 Yv tb p Uptake+ (kg/m 2 ) ~jy (hrs) (kg/m 2 ) Direct Dep 1-131 0.7 2.0E-02 1.31E+05 240 9.40E-05 Cs-134 0.7 1.0E-02 1.31E+05 240 1.03E-02 Cs-137 0.7 1.0E-02 1.31E+05 240 4.36E-02 For Produce or Leafy Vegetables Ingested by Man: Ai Aw AEI ~

                       .l         (hrs-1)          * (hrs- 1)      (hrs-1)     (hrs) 1-131             1.0       3.59E-03            2.1E-03      5.69E-03     1440 Cs-134             0.2       3.83E-05            2.1E-03      2.14E-03     1440 Cs-137             0.2       2.62E-06            2.1E-03      2.10E-03     1440 Yv                                   tb               p       Uptake+

(kg/m 2 ) ~jy J!J.rfil (kg/m 2 ) Direct Dep 1-131 2 2.0E-02 1.31E+05 240 2.64E-04 Cs-134 2 1.0E-02 1.31E+05 240 2.42E-02 Cs-137 2 1.0E-02 1.31E+05 240 1.02E-01 Note: The parameter definitions are the same as in Regulatory Guide 1.109. Page 266 of 268

Revision 9 February 27, 2017 Table 0-2 Principal Surface Water Uses Nearest Public Potable Station Body of Water Recreation a Irrigation Receiving Water Intake Lake Yes Not Lake County Citedb Public Michigan Water District (1.4 mile north of site and 3000 ft out in Lake) Note: This table summarizes selected information from the reports referenced in the footnotes below. For more complete information, see the referenced reports. a Per Zion ER, Section 2.3.2.2. Existence of irrigation not mentioned in Zion ER. Page 267 of 268

Revision 9 February 27, 2017 Table 0-3 Predicted PWR Annual Doses for Selected Liquid Effluent Pathways Annual Whole Body Dose (mrem/yr per reactor) Pathway/Limit Zion a Eating Fish 4.5E-2 Drinking Water 1.7E-3 Shoreline Activities 1.4E-4 Swimming and Boating 1.1 E-5 10 CFR 50 Objective 3 Annual Thyroid Dose (mrem/yr per reactor) Pathway/Limit Zion a Eating Fish 3.6E-2 Drinking Water 1.7E-2 Shoreline Activities 1.4E-4 Swimming and Boating 1.1 E-5 10CFR50 Objective 10 Note: This table summarizes selected information from the reports referenced in the footnotes below. For more complete information, see the referenced reports. a Per Zion Appendix I Report (Reference 72), Table 1.1-7. Except for drinking water, these values are based on water in the discharge canal; drinking water is assumed to be from the Lake County Illinois intake (see Appendix I Report, Table 1.1-6). Page 268 of 268

ZionSolutions LLC ZS-2017-0058: Attachments ATTACHMENT 3 ECN 2015-07 Modification of Lake Release System

Attachment 41 ZS-WC-100 Design Changes - DCPs, ECNs, FCRs, and DCRs Revision 11 Information Use Exhibit A (page Al) ENGINEERING CHANGE NOTICE (Part 1) ECN No. 2015-07 ISSUANCE: [ X I FOR CONSTRUCTION [ ] FOR COl\iMENT Page: I or& Station: 2;ION [ 1 Safety Related Design Change No. 2015-07 [X] Non-Safety Related Project No.(ir.ppI.) NA Affected Unit: Common [ ] Regulatory Supp ID No. (1r.11pi.1 Changes to a previously Approved ECN [X] System: Yil/WDNC De!icription of Design Change Request: This design change provides the design and instructions to install a new liquid waste system to process and release residual low level liquid waste from the RCA through the WWTF. This design change uses existing equipment of the AB and new equipment to provide a method for making liquid waste releases to Lake Michigan. The new system consists of a storage subsystem (the existing AB sumps and HUTs), a transfer subsystem to transfer water from the HUTs to outdoor storage tanks, processing equipment which can be located in the WWTF or AB, and a release subsystem that will release processed water from the outdoor storage tanks to the Unit 2 outfall. This design change also abandons equipment of the existing liquid waste system. c:* This ECN *does not provide installation details of the transfer subsystem; installation, instructions and equipment for water transfer from the HUTs to the WWTF will be controlled by procedure. Reason for Design Change: Change and action required (Provide reason for change, specific actions required, attach supporting documents, as applicable). Decommissioning activities have progressed into the phase that will dismantle and demolish the AB. The existing equipment needs to be removed to allow decommissioning and prevent inadvertent damage. Prior to entering this phase, all stored water will be processed and released. The new liquid waste system will process and release ground water in-leakage and wash-down water used in decommissioning activities. The processing and release equipment will be located in the WWTF. The outdoor storage tanks will be located adjacent to the WWTF. INTERFACING COMMENTS by Design Group or N111De of Commenter (Printed) Signature of Commenter Date CorNC Discipline ElectJl&C Mechanical Structural D&D Operations Others ,, Prepared by: A.R. Adam~ Reviewed by: Ufi/,,,a. _Cor@ Approved bye; /-;J, ~~/~ 1{-1,;... ,~ I

                             .     .t.*"                                                                                           r2}14/2D IS Date:      I)..*-/ ~(~_ /.,.')                       Date:                                                    Date:

All affected design documents revised by (date): Verified by: Date:

Attachment 4 ZS-WC-100 Design Changes - DCPs, ECNs, FCRs, and DCRs Revision 11 Information Use Exhibit A (pageA2) DESIGN CH.ANGE DOCUMENT - AFFECTED DOCUMENT LIST {Part 2) Fe,.--,.,,, 2 l~ ..f-r Ib

                                                                                            ~?"'-"    V~"""

• Associated With:

ECN --Comment DCP Number: 2015-07

                                                                                  ~~"---""---~~-~

_x ECN - Construction FCR Other: Part 1- General Information -optionaJforFCR Date Prepared: l~t'l-/J5

, Originator:

,l A. R. Adams W.0. Number=---~------

Description:

This ECN installs a new liquid waste system and abandons the existing system .._ Part 2 - Related Design Change Documents (i.e., ECN,FCR) Ref. Ref. No. ~ Number No. ~ Number

1. ECN 392999 5.

2. FCR 394510 '6.

3. ECN 2015-09 7.

4. 8.

Attachment 4 ZS-WC-100 Design Changes - DCPs, ECNs, FCRs, and DCRs Revision 11 Infonnation Use Part 3 - Affected Design Documents DESIGN DOCUMENT (DD) (') IT,! Related DCDs Incorp. Rev.

                                                                                                ~ *t3 (Ref# from Part              or
                                                                                                  *  ** 2                         Date (Optional)

Type Number Sheet Rev. Rev Code /Page No. Date (1-Dwg 2-Calc 3-0ther)

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                                                   -~*
                                                                  ..&1.-.tr..9t.;r..1!.111 ...,_.
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1 M-1195 B R 1 1 M-49 1 A R 1 ) 1 M-59 AB c 1 1 M-511 AP R 1 1 M-900-07 A c 1 New Issue

*'C' for Construction m: 'R' for Record   **'F for FWJctional m: 'D' for Detailed

• Engineering Change Notice PA.RT 4 ECNNo.: 2015-07 Design Change No.: 2015-07 Page '~f of l~

Part4 Constructioi;i Support Information

• NOTE: The storage tanks and associated secondaiy containments shall be selected and approved by engineering prior to installation.

1. Install storage tanks with secondary containments adjacent to the WWTF along the EAST side of the WWTF, or as directed by Engineering.

2. Install Release Pump on lower level ofWWTF. Attach 3" hoses from release/storage tanks to pump inlet piping, and 2 Y2" hose to pump outlet. Route the 2 W' outlet hose to discharge manifold at ground level ofWWTF.

See Figure 1 and drawing M-900-07.

3. Install discharge piping and flow meter (2" pipe, 20" long on both sides of flow turbine) near radiation monitor on ground level ofWWTF. The Y2" hose length from the discharge manifold to the rad monitor should be minimized, and no greater than 12 feet. See Figure 1 and drawing M-900-07. Unistrut supports shall be used to anchor the discharge manifold section.

7. Attach 2" check valve to 2" branch connection on discharge pipe T-fitting. Using 2" .

pipe, hose and ball valves, route recirculation hoses to storage tanks. Recirculation hoses should be anchore<fto prevent whip. Refer to M-900-07.

8. Attach W' pipe and test valve T-fitting to Y2" branch connection on discharge pipe T-fitting. Attach W' hose to test valve T-fitting and route to radiation monitor. The outlet of the rad monitor is routed back to the release pump inlet with W' hose.

Refer to M-900-07.

9. Install solenoid valve OSOV-WDOOlO inside outfall valve house with 3" SS fittings and pipe. Valve must be installed in horizontal position. Refer to Figure 2.

  \

Prepared By: ~A~.R~.A!..=da~m~s!:---- Date: I~ -1 '-/- I:,;* Reviewed By: ,dr(/4:,-=-- Date: / z...- I 'I - 1!'

Engineering Change Notice Pfl~R-T 4 ECNNo.: 2015-07 Design Change No.: 2015-07 Page 5 of lfo Part4 Construction Support Information 1.

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     . Prepared By: ~A=.R=*;...oA~d=a~rn=s_ _ __            Date:  !;<-1'1-15
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• Reviewed By: £.;~~"?~,.-,,$.,_ ,.... Date: /'Z*-' '1; ,,. /~C

Engineering Change Notice l? P.. iz_-r 4 ECN No.: 2015-07 Design Change No.: 2015-07 Page (;.:* of /~ Part4 Construction Support Information

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                     --P. A" 1 Reviewed By:     * ~7,,,.. !-.i.*.--                       Date: /2-lfrl,L

Engineering Change Notice

                                                  .                  Pf.\-RT 4 ECN No.: 2015-07 Design Change No.: 2015-07 Page 7 of      fb Part4                                       Construction Support Information MECHANICAL PARTS LIST QTY               DESCRIPTION                     MAN PART#               McMaster#

2 Cent Pump* Dayton 12A084 Grainger 1 2 W' Globe Valve* Milwaukee 502 2~" Grainger 6 3" Ball Valves 47865K72 4 2" Ball Valves 47865K.28 1 ~"Ball Valve 47865K.23 1 W' Check Valve 2 3" x 2" Pipe T 44605K525 1 2" X W' Pipe T 44605K465 1 2 W' X 2" Pipe T 44605K645 1 3" X W' Pipe T

                         ~"Hose                                                        5405K.231 1       3" Pipe T-Y                                                   44605K362 2       2" Threaded Pipe 20" Long*

1 2" Flow Gauge & Totalizer* Halliburton Turbine Flow Meter 1 2" Check Valve 4708K58

            *Alternate parts may not be used without Engineering approval.

Diameter sizes of valves, pipe, and hoses shall be adhered to. All hoses, mm1mum pressure of> 70 psig Prepared By: A.R. Adams

     'r Reviewed By:
                         /{t/~ ~

Engineering Change Notice Pfl..Fer 4 ECN No.: 2015-07 Design Change No.: 2015-07 Page fl' of /~ Part4 Construction Support Information MECHANICAL PARTS LIST QTY DESCRIPTION MAN PART# McMaster# f 1 3" check valve 5 3" pipe nipple 44615Kl25 2 2" pipe nipple

r r

2 2 W' pipe nipple lI I 1 2 W' x 2" Reducer J 1 3" Solenoid Valve* Magnatrol PIA4K39Fl I* 2 W' Hose w/NPT ends 1548N25 I 8 3" Discharge Hose* 100 ft 1081N25 40 20 ft Hose SpillGuards RainforRent 1 3" SS 90 4464K122 3" SS Threaded Pipe Hose to Pipe Connectors 2" Hose (Recirc) 3 3" Suction Rated Hose

          *Alternate parts may not be used without Engineering approval.

Diameter sizes of valves, pipe, and hoses shall be adhered to. All hoses, m111llI1um pressure of> 70 psig Prepared By: A.~ Adams Date: /~*- 1 ""/--i,J"'

     . _Reviewe  dBy: ~uli./I /,_ ,J'/ ....___ ..          Date: /'2 -1 ';l .---1'{"....

Processing Equ!pmen1 1- _i;onnect1cm OWDlUOA Release/Stanae Tonk A OWD1117A l Second* Containment OWD111Bll

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December 14, 2015 In reply refer to CZE-15-020 To: Tony Orawiec

Subject:

Zion Station, Units 0, 1 & 2 Design Change 2015-07 Liquid Rad Waste System Code: WD, VC The Engineering Department has reviewed the subject design change in accordance with ZS-WC-100 and applicable Zion Solutions Quality Requirements. Design Input Requirements (DIR.s) as identified in NEP 12-01 have been reviewed and are included in the design change approval letter as applicable. Description of Change: This Design Change installs a new liquid rad-waste system and abandons portions of the existing system. The new system consists of the dedicated storage location inside the AB

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(HUTs) for unprocessed liquid waste, existing processing equipment, and a release ! system that uses new equipment with a new release pump and release path. With the onset of decommissioning activities in the AB, most of the existing liquid rad-waste processing system will need to be abandoned and removed. Exempt Change Design Package: The mechanical portion of the Design Change is contained in ECN 2015-07 and the electrical portion is contained in ECN 2015-09, both of which are issued "For Construction" by this letter. This Design Change supersedes the installation of previous Exempt Changes 392999. Equipment shown as "Abandoned" within this Design Change may be classified NOT REQUIRED (as defined in Zion Decommissioning procedure ZS-WC-100) under the authority of this EC. 10CFR 50.59 Evaluation I Decommissioning Impact Evaluation: A 10CFRS0.59 Evaluation was performed in accordance with ZAP 100-06 and is being transmitted along with this letter. This activity can be implemented without prior NRC approval. A Decommissioning Impact Evaluation was perfonned and it was concluded that the proposed activity is not restricted by 10CFRS0.82. 1

December 14, 2015 In reply refer to CZE-15-020 DSAR I ODCM Impact Review: DSAR Chapters 1 through 6 were reviewed for this exempt change. No changes to the DSAR are required. Additionally, a review of the ODCM was conducted. Revisions to a the ODCM are required as result of this design change as identified in Job Aid ENG-07 Exhibit A. Exhibit A is included in the DCP. Applicable Codes and Standards: This exempt change shall be installed in accordance with Zion Specification X-3646, which is the general work specification for mechanical, structural and electrical work as well as applicable site and corporate procedures. Installation requirements identified in the ECN supersede X-3646 guidance. BHic Functions: A new processing system will be installed to process liquid rad-waste during decommissioning. The current design functions of the liquid waste systems, as described in DSAR Section 4.5, are to: I. Ensure that the quantities of radioactive waste discharged from the plant during nonnal operations are as low as practicable and, i.."l any event, well within the allowable concentration limits; and

2. Limit the inadvertent release ofradioactive material from the plant so that the resulting radiation exposure to the public is as low as practicable and, in any event, well within the allowable concentration limits.

The new liquid rad-waste system will consist of outdoor tanks located adjacent to the WWTF, existing processing unit (processing tanks, filters, demins, & pump), and a new pump that will release the processed water to Lake Michigan. The materials structure of the new processing equipment will be a combination of steel, plastic and highly durable hoses to provide the ability of relocating the system as necessary to accommodate movement during decommissioning. Much of the system will be located within the WWTF. This change also maintains the Holdup Tanks (HUTs) as the dedicated storage location of the liquid waste system. These tanks are the dedicated long term storage locations of unprocessed liquid waste from the Containments, AB and FB and require manual actions by plant personnel to transfer liquid from these tanks to the outdoor storage tanks. 2

December 14, 2015 In reply refer to CZE-15-020 Industrial Satfety: This design change has no effect on the industrial safety of the plant. Installation Schedule I Outage Requirements: Installation of this exempt change will be scheduled via the site work schedule process. Technical Specification Changes: The existing Technical Specifications do not require revision as a result of this exempt change. ALARA Review: An ALARA review will not need to be performed for this exempt change. Fire Protection Review: No changes to the Fire Protection Report are required by this EC. Impact of Pending Modifications or Temporary Alterations: A review of pending design changes has been completed. No pending design changes or Temporary Alterations affect this design change. Construction Drawings: Construction is authorized to proceed-in accordance with ECNs 2015-07 and 2015-09. Identification of the Installer: This Exempt Change will be performed by the D&D department with assistance from the other groups as required. 3

December 14, 2015 In reply refer to CZE-15-020 Procurement Requirements: A Bill of Material has been included with the ECN. The design of the outdoor tanks shall either meet the design requirements specified in Table 2 of Reg Guide 1.143-2001, or an engineering analysis shall provide the basis of an acceptable alternate design to those requirements. The outdoor tank specifications are included as Attachment 1. Training Requirements: Training will be required for the Operations Department and other associated plant personnel on the operation and limitations of the new system. Testing Requirements: A functional test of the Lake Release system shall be performed to verify proper operation of the pump and flow instrument prior to any actual releases. An operational test of the Rad Monitor, associated alarms, and isolation function ofOSOV-WDOOIO shall be performed. Operating Requirements: Existing Zion procedures will require revision as identified in Job Aid ENG-07, Exhibit A. Exhibit A is included in the DCP. A new procedure for the operation of the transfer system will need to be developed and approved for use for the associated plant personnel. This procedure will provide installation and operation instructions for transferring water from the HUTs to the outdoor storage tanks. The minimum length of the 3" release hose from the discharge piping to OSOV-WDOOlO is 300 feet. With this length or greater, the maximum allowed release flow is 200 gpm. Releases from the system are limited to 20,000 gpd. The Release hose and the Transfer hose shall be contained within a secondary containment system to collect any potential leakage and pressure tested immediately (within 2 hours) prior to each use to verify no leakage. The test pressure shall be at least 61 psig. Placement of the processing equipment inside the WWTF shall include a method for the collection of any leakage. All releases from the WWTF, and transfer of water from the HUTs to the WWTF, shall be monitored (visual observation of the outside hose) to prevent inadvertent damage to the hoses from equipment, and to immediately stop the pump in the event of any leakage. Prevailing weather conditions should be considered to accomplish this. Vehicle and 4.

December 14, 2015 In reply refer to CZE-15-020 equipment traffic, and dismantlement activities shall be suspended in the immediate area of the release hoses (within 20 feet of hose) during releases. After use of the hoses:

        *e   They shall be flushed with clean (non-radioactive) water.

c The Release hose should be detached from the system and stored inside the WWTF.

         '"~ The Transfer hose shall be detached from the outdoor storage tanks and removed from the outside area.

Technical Review: The Liquid Rad Waste system is classified as REQUIRED. Therefore, this design change is subject to a Technical Review. A Technical Review (TR-025-2015) has been performed and submitted with the design package. If there are any questions regarding this design change, please contact Arthur (Bob) Adams at extension 4010.

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Arthur R. Adams Desigt:! Engineering Approved By: ~/F-f}p,.{ Don Roth D&D Engineering Supervisor cc: MAL ECN 50.59 Central File 1 1 1 Darcy Neuenfeldt originals TonyLukken 3 3 3 J. Brandis 2 2 2 I L 5

TECHNICAL REVIEW LETTER TR-025-2015 To: Tony Orawiec Decommissioning Plant Manager Zion Station

Subject:

Design Change 2015-07; New Liquid Waste System Summary: This Technical Review docµments the review of the technical basis for removal and/or abandonment of the existing liquid Rad-Waste system, and installation of the new liquid Waste system. Prepared By: Arthur R. Adams Date: 12-14-15 Required Review Disciplines:_._A~B"--i.~n.c....,'F-->o~------.::.o~~-*

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                             .£ecojJ?llliSsioning Plant Manager Distribution:

Decommissioning Plant Manager Operations Manager Engineering Supervisor RP Supervisor SRC Coordinator Master File /'

AD-11 Revision 1 Information Use ATTACHMENT B-5 50.59 Evaluation Form 50.59 Evaluation No. --=2=0=15,,_-=09=5'--------- Revision Number: _1__ Activity/Document Number: _D"""C=P_.2...0=15-07.......__ _ _ _ _ Revision Number: _o_____ I. 50.59 Evaluation/Questions: (check correct responses) Provide a separate written response providing the basis for the answer to each question below. The Resource Manual (RM) should be used to detemrine the content of each response (see Section 6.2 for additional guidance). If the Screening indicated that only a change in method of evaluation exists, only Question 8 is required to be answered. If the Screening indicated that no change in method of evaluation exists, Question 8 does need not be answered.

1. Does the proposed activity result in more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the UFSAR? (See Section 6.2.1 of the RM) _ _YES X NO The accidents previously evaluated in the DSAR are described* in Chapter 5; they are:

e>. Radioactive Waste Handling Accident. This accident postulates the failure of a High Integrity Container (HIC) containing dewatered radioactive demineralizer resin generate.d during decontamination activities to the extent that entire solid, non-combustible contents escape. The liquid waste system does not interact with the systems associated with these accidents. As such, there is no effect on the frequency of occurrence for these accidents due to the operation or failure of the liquid waste system. The inadvertent release of liquid, radioactive material from the site, with a resultant radiation exposure to the public, is not described as an accident within the DSAR; however is a design criterion. The change associated with the liquid waste system does not increase the occurrence of an inadvertent release from the site. The dedicated release path from the site to Lake Michigan ( U2 discharge pipes) and associated control methods for monitoring releases is not changed such that the concentrations of effluent are maintained well within the allowable limits of 10CFR20 and t~e notification limits of the QAPP Appendix B. The new system is controlled and operated by plant personnel, and has no automatic release features, such that all processing and transfer of liquid waste is done in batches on a periodic basis. The following design features and administrative requirements are included with the new system to maintain the existing design criteria stated in the DSAR, and to reduce the risk associated with a complete rupture of the system:*

   .c     The long term storage location for unprocessed water, the HUTs, is located inside the AB. The AB is designed as a Seismic Class I structure and would be analogous to the criteria of classification RW-lla as described in Reg Guide 1.1.43-2001. As such, the storage portion of the system is protected from destruction due to natural phenomena.
   ""' The Lake Release Tank will be isolated from the processing unit prior to and during releases. This will provide assurance that release concentrations are maintained during the release.

Page24 of61

AD-11 Revision 1 Information Use ATTACHMENT B-5 50.59 Evaluation Form 50.59 Evaluation No. --=2=0=15~-0=9=5_ _ _ _ _ _ _ _ Revision Number: _1__ Activity/Document Number:D =-=C.... P__,2"""'01=S-......0....7_ _ _ _ _ Revision Nwnber: _o__

e Many of the components of the release and processing portion of the system are located in the WWTF. The WWTF is constructed on a concrete foundation and is designed for wind loading of 100 mph. Any leakage or rupture of those portions of the system will be controlled such that it is contained within the WWTF. .

o_ The temporary storage tanks/Release tanks are located outside the WWTF. Damage and/or rupture of the tanks and associated equipment is unlikely due to their location and construction. These tanks have secondary containments capable of holding the tank contents in the event of leakage cir failure. Overflows for each temporary storage/release tank are routed to the lower level of the WWTF.

   ,.11     The maximum release concentrations of the Lake Release Tanks are administratively set at <10 times the release concentration limits of 10CFR20, Appendix B, Table 2, such that a release to Lake Michigan can never be higher than the QAPP notification limit (i.e. 10 times the 10CFR20 limits) regardless of the dilution flow rate or Lake Release Tank discharge rate:                                           '

2. Does the proposed actMty result in more than a minimal increase in the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the UFSAR? (See Section 6.2.2 of the RM)~_YES X NO As defined in the RM:

            "Malfunction of SSC important to safety means failure of SSCs to perform their intended design functions described in the UFSAR ... "

As such, there are components of the liquid waste system and aspects of design of the system that perform design functions "important to safety (as related to the 50.59 Evaluation criteria #2). The design functions described in the DSAR are to:

1. Ensure that the quantities of radioactive waste discharged from the plant during normal operations are as low as practicable and, in any event, well within the allowable concentration limits; and

2. Umit the inadvertent release of radioactive material from the plant so that the resulting radiation exposure to the public is as low as practicable and, in any event, well within the allowable concentration limits.

Specifically:

         *ii The components of the system that ensure release concentrations are "within the allowable concentration limits", perform design functions that are important to safety, as they ensure compliance with design function #1. Those components of the system are: the release flow instrumentation, the dilution flow instrumentation, the discharge radiation monitor and the high radiation isolation valve. Although not part Page 25 of61

AD-If Revision 1 Information Use ATTACHMENT B-5 50.59 Evaluation Form 50.59 Evaluation No. --"'2=0=15,__-0=9-=S_ _ _ _ _ _ _ _ Revision Number: _1__ Activity/Document Number: :;.D=C.:...P....2,,.,. 01=5'-'-0'"""7_ _ _ _ _ Revision Number: _.O..__ of the system, the dilution pump and associated dilution flow ensure compliance with design function #1.

       ;;  The SSC that limit and/or prevent inadvertent releases of radioactive material from the plant (design function #2) perform design functions that are important to safety.

Not accounting for operator error, the following SSC are considered important to safety for design function #2:

              "'   The WWTF structure as it prevents all inadvertent releases due to leakage from components inside the WWTF.
              " The release hose from the HUTs to the WWTF, and from the WWTF to the outfall (U2 discharge) as it prevents inadvertent releases due to its material, design rating and administrative controls.

o, The isolation valve SOV-WD001 O as it isolates flow to the outfall in the event of high isotopic concentrations during a release. fl The temporary Storage/Release tanks which will contain unprocessed and processed water until released. The following evaluation relates to the malfunctions associated with those SSC (identified above) that perform the DSAR described design functions. This activity installs a new liquid rad-waste system and abandons portions of the existing system under Design Change 2015-07. Due to the onset of decommissioning activities in the AB, most of the e~isting liquid rad-waste system will need to be abandoned. The original design basis of the Liquid Rad Waste system that was installed during plant operation, provided the ability to process and control liquid waste associated with failed fuel (1 % of the fuel rods releasing fission products into the coolant by diffusion out of the pellets through defects in the cladding) during power operations. The liquid waste systems also had the ability to process and control leakage and spills of highly radioactive water associated with accidents (e.g. LOCA) and maintenance activities associated with an operating power plant. During plant operation, the potential for large releases of contaminated material inside the AB was comparatively significant and could proceed, in some cases, uncontrolled. The design of the waste systems was in accordance with Reg Guide 1.143-1979.

• The design basis of the existing Liquid Rad Waste system (that was installed during plant decommissioning), provided the ability to process and control liquid waste associated with decommissioning activities; removal of residual water from abandoned system, wash-down water from decontamination of existing equipment, water used for shielding during decommissioning activities, and water that will;be drained from the SFP. The liquid waste system also had the ability to process and con~rol leakage and spills of radioactive water associated with maintenance activities. The isotopic concentration of this water was relatively low compared to the potentially large releases of contaminated material inside the AB that could occur during plant operation, which in some cases, could occur uncontrolled.

Page26 of61

AD-11 Revision 1 Infonnation Use ATTACHMENT B-5 50.59 Evaluation Form 50.59 Evaluation No. _ _,,2=0=15<---0=9=5_ _ _ _ _ _ _ _ Revision Number: _1__ Activity/Document Number: =D=C.;:;..P..-2.-01=5-....,0._.7_ _ _ _ _ Revision Number: _O....__ The design of the existing waste systems was an acceptable alternative to the design guidance of Reg Guide 1.143-1979. The major equipment of the new liquid rad-waste system will consist of: the existing HUTS and AB sumps as a collection system, tanks for temporary outside storage/release tanks, the existing filters and demins for processing the liquid to meet the applicable release limits as needed; and a new release system which will consist of the outdoor tTanks as the Release Tanks, a new pump, the existing radiation monitor with associated isolation valve, and flow monitoring instruments. The collection system is located in the AB. All of the release equipment, except for the outdoor tanks, the release hose and isolation valve, is contained within the vywTF. The processing equipment can be located in the AB or the WWTF. The components of the processing equipment are made of a combination of steel, plastic and highly durable hoses to provide the ability of relocating the system as necessary to accommodate decommissioning. Any leakage or rupture of the system inside the WWTF will be contained within the WWTF. This is due to the existing drains and structure of the WWTF. The probability of malfunctions associated with the SSC that "Ensure that the quantities of radioactive waste discharged from the plant during normal operations are as low as practicable and, in any event, well within the allowable concentration limits" (i.e. design function #1) will not increase, as this equiprrient is of the same quality and standards as the existing system equipment and are maintained and calibrated as required by the QAPP and the ODCM. Limiting an inadvertent release of liquid radioactive material from the plant, with a resultant radiation exposure to the public, is the design function that relates to the failure of SSC with resultant unintended releases such as spills and leakage. The new processing system (the portion of the liquid waste system that filters and purifies the water) is a flexible system that can be moved within the AB and WWTF. The processing system is not considered important to safety as its operation is not required to meet the design functions described in the DSAR, however a structural failure of the equipment, if located in an uncontained setting, could result in an inadvertent release to the site. The processing equipment will be located either in the AB or in the WWTF such that its failure does not result in an inadvertent release of radioactive material from the plant. The structure of the WWTF also performs this design function. The WWTF is a Seismic Class 3 structure. UFSAR Section 3.2 defines Seismic Class I, II and Ill structures and components. As described in .UFSAR Section 3.2, all Seismic Class Ill SSC meet the applicable codes. The applicable code at the time the WWTF was designed (i.e., 1977) was UBC 1976. Therefore, the design of the WWTF is acceptable for seismic loading. Reg Guide 1.143-2001 refers to ASCE 7-95 for wind loads. ASCE 7-05 (i.e., the 10 year newer edition) shows a basic wind speed for this area as being 90 mph. Per UFSAR Section Page27 of61

AD-11 Revision 1 Information Use ATTACHMENT B-5 50.59 Evaluation Form 50.59 Evaluation No. --==2=0....,15'-'-0,.,,9"""5_ _ _ _ _ _ _ _ Revision Number: _1__ Activity/Document Number: =D=C.-..P-=2=01=5-_.0.... 7_ _ _ _ _ Revision Number: _o__ 3.3.1, all structures that are not Seismic Class I were designed for 100 mph wind. Therefore, the WWTF design is acceptable for Reg Guide 1.143 wind load criteria. This Design Change does not alter the dedicated outfall from the site to Lake Michigan (U2 discharge pipes) or the associated controls and methods for monitoring releases. That is, the likelihood of occurrence of a malfunction of the components identified above as 11 "important to safety (the release flow instrumentation, the dilution flow instrumentation, and the discharge rad monitor with associated isolation valve) has not changed. The new release flow instrumentation is the same type and manufacturer as used in the previous system. The radiation monitor is the existing plant radiation monitor. The dilution flow instrumentation is not affected by this change. The Design change does alter the path from the AB to the outfall. o ----A hose will be placed on the ground and routed from the HUTs to the temporary storage Tanks located outside the WWTF. This activity will be a periodic transfer of the water collected in the HUTs. The hose will be installed just prior to the transfer, leak tested prior to the transfer, monitored by a dedicated operator during the transfer to prevent inadvertent damage to the hose, and removed after the transfer. The transfer hose will be installed within a collection trough to collect any leakage during the transfer. 111 A hose will be placed on the ground and routed from the release pump inside the WWTF to the outfall. This activity will occur for the time needed to empty the Release Tank. Releases to Lake Michigan are restricted to 20,000 gpd; so it is possible for the activity to occur several times until the storage Tanks are emptied. The hose will be installed just prior to each batch release, leak tested prior to release, monitored by a dedicated operator during the release to prevent inadvertent damage to the hose, and removed (or flushed with Clean waterer completed drained) after the release. The release hose will be installed within a collection trough to collect any leakage during the release. Release flow rates will be established that allow the entire contents of the release tank to be discharged during one 10 hour day. For both activities, administrative requirements will be established to prevent releases during potential bad weather days to preclude damage from natural forces and/or inhibit the ability to detect leakage. The hose pressure rating will be higher than the maximum discharge pressure of the release pumps to minimize the potential for rupture. The potential for leakage in this case, would be due to failure of the hose under pressure. The increased potential for failure and resultant inadvertent release from the hose under the control of an operator as described above, is small compared to the potential for a failure and resultant

                                                     .. Page 28 of61

AD-11 Revision 1 Information Use ATTACHMENT B-5 50.59 Evaluation Form 50.59 Evaluation No. ---=2=0_._,15,,__-=09=5_ _ _ _ _ _ _ _ Revision Number: _1 __ Activity/Document Number: D=CP=-=20......1=5--'-0..._7_ _ _ _ _ Revision Number: _o__ inadvertent release from a pipe buried underground. Any leakage that does occur will be collected in the hose trough, and immediately stopped and remediated. This design change does not alter the dilution flow path or flow rates. Dilution flow provides a further reduction in release concentrations to maintain releases within the limits of the ODCM (ALARA). Design Change 2015-09 installs interlocks between operation of the dilution system and the radiation monitor isolation valve such that in the event of a dilution pump trip, the liquid waste discharge isolation valve closes, preventing any further liquid waste discharge. This design change alters the location and structure pf the release tanks. The new release tanks will serve as interim storage, processing and release tanks. These tanks will be located outdoors adjacent to the WWTF. A secondary containment will be installed capable of. holding the entire contents of each tank as discussed in the Administrative Controls of the Zion QAPP. The following provides a comparison of design features for the new liquid waste system, to design criteria prE_!sented in Reg Guide 1.143:..1979. It should be noted here that the new system is designed to r.ollect and process (as necessary) ground water in-leakage and remaining wash-down water to the AB sumps during the remainder of pecommissioning. As evaluated herein, the installation and operation of:the new liquid waste system results in an insignificant change in the ability to meet the DSA.R design functions, *and therefore provides justification for an acceptable alternate method of compliance wit!i the ,existing DSAR design functions and, more specifically, for compliance w.ith the applicab'e N~C regulations. The following Sections 1 and 4 are copied in !Jold italics printfrom th,e Reg Guide. Table I is copied to show only the applicable equipment. The design features of the new system and associated justification are presented in normal (not bold) print. Items that do not specifically meet the guidance criteria of the Reg Guide are underlined and shown in [brackets].

1. SYSTEMS HANDLING RADIOACTIVE MATERIALS IN LIQUIDS 1.1 The liquid radwaste treatment system, including the steam generator blowdown system, downstream of the outermost containment is~lation valve should meet the following criteria:

1.1.1 The systems should be designed and tested to ,requirements set forth in the codes and standards listed in Table 1 supplemented by regulatory positions 1.1.2 and 4 of this guide. TABLE I (referenced) EQUIPMENT Design Material Page 29 of61

AD-11 Revision 1 Information Use ATTACHMENT B-5 50.59 Evaluation Form 50.59 Evaluation No. --=2=0=15._-0=9=5_ _ _ _ _ _ _ _ Revision Number: _1__ Activity/Document Number: ~D~C~P~2~01=5-~0_7_ _ _ _ _ Revision Number: _o.....__ Tanks ASME Sect Ill ASMESectll Piping & Valves ANSIB31.l ASMESectll Pumps Manufacturers Std Manufacturers Std The following tanks are used in the new system: HUTs-Design and Material equivalent [Storage Tanks - Does Not meet Design or Material Criteria.] The storage Tanks are located outside near the WWTF structure. These tanks will be used for interim storage of liquid waste that is transferred from the HUTs. The tanks will also be used as the release/processing tanks, as needed, to process liquid waste for compliance with applicable release limits, and then released to lake Michigan. Although the design and material of storage tanks are not designed to the criteria of the Reg Guide; (a) their catastrophic failure due to natural phenomena of Table 2 is deterred by the rugged steel construction that is an acceptable alternative to the design criteria of the Reg Guide, and (b) the operation and potential leakage of the tanks does not affect the ability to satisfy the design functions described in the DSAR since they are contained within a secondary containment to collect any leakage that occurs. Drains from the secondary contain.ment will be routed to the WWTF. The new system uses existing pipe, new pipe and hose. All of the existing piping of the Storage system (HUTs) is equivalent to the Design and Material criteria of Table 1. [New valves are not equivalent and design is based on use.] All plastic components {which are only used in the processing system) are rated at 125 psi or higher. The discharge hose {hose from the Release system to the entrance point of the U2 outfall) is pressure rated to 150 psi. The transfer hose (hose from the HUTs to the WWTF) is rated at 150 psi. The pressure rating of the plastic components, valves and hoses are greater than the maximum pressure of the pumps and .provides a margin against failure due to over-pressurization. Release Pumps - Design and Material Equivalent Process Transfer Pumps - Design and Material Equivalent The testing requirements for the new system and components are commensurate with the function of the component as well as that stated in the ODCM. All discharge piping and hoses will be pressure tested, based on maximum operational pressures, for leakage prior to initial use. 1.J.2 Materials for pressure-retaining components should conform to the requirements of the specifications for materials listed in Section II of the ASME Boiler and Pressure Vessel Code, except that malleable, wrought, or cast iron ma~rials and plastic pipe should not be used. Page 30 of61

AD-11 Revision 1 Information Use ATTACHMENT B-5 50.59 Evaluation Form 50.59 Evaluation No. --=2=0"""15"""-0...,9...,,5..___ _ _ _ _ _ _ Revision Number: _1__ Activity/Document Number: =D...,C_,,P...,2....0=15- . . . .07.._

                                                            . . . _ _ _ _ _ Revision Number: _.O...___

Materials should he compatible with the chemical, physical, and radioactive environment of specijic applications during normal conditions and f!-nticipated operational occurrences. Manufacturers' material certificates of compliance with material spedfications such as those contained in the codes referenced in Table I may be provided in lieu of certified material test reports. All equipment purchased as non-safety related. Material criteria of the components is discussed in 1.1.1 above. Design criteria for new equipment associated with the Release system was specified in the Design Change via the Bill of Material. J.J.3 Foundations and walls of structures that house the liquid radwaste system should be designed to the seismic criteria described in regulatory pos~n 5 of this guide to a height sufficient to contain the maximum liquid inventory expected to be.in the bullding. The entire storage system is located in the AB, a Seismic Class 1 structure. The release pump, the flow meter and the rad monitor of the .release system, are all located inside the WWTF, which is a Seismic Class 3 structure. The re.lease hose will exit the WWTF into the U2 outfall. The transfer hose exits the AB and will be routed to the outdoor storage tanks.This hose will only be installed to ma'ke the transfer from the HUTs to the storage tanks. The WWTF is a pre-engineered building that is attached to a reinforced concrete substructure. J.J.4 Equipment and components used to collect, process, and store liquid radioactive waste need not be designed to the seismic criteria given in regulatory position 5 of this guide. The new system is not designed to the seismic criteria. J.2 All tanks located outside reactor containment and containing radioacdve materials in liquids should be designed to prevent uncontrolled releases of radioacdve materials due to spillage in buildings or from outdoor tanks. All leakage from the outdoor tanks of the new system drains to the lower level of the WWTF via secondary containments. Damage and/or rupture of the Release Tanks and associated release equipment due to decommissioning activities or abnormal weather is unlikely due to their location adjacent to the WWTF and their construction. Overflow for each Release Tank is routed to the WWTF. The most likely source of leakage from the system would be leakage from the hoses. See the discussion above regarding failure of the transfer and release hoses. Hoses to Page31 of61

AD-11 Revision 1 Information Use ATTACHMENT B-5 50.59 Evaluation Form 50.59 Evaluation No. --=2=0=15._-0=9=5_ _ _ _ _ _ _ _ Revision Number: _1__ Activity/Document Number: =D-=C.. _P-=2..... 01=5'--'-0'""7_ _ _ _ _ Revision Number: _o.....__ and from the outdoor storage/release tanks will be isolated at the tanks to preclude leakage from the tanks through the hoses when not in use. Although the storage/release tanks do not meet the design and material criteria of Table 1, the situation described above is analogous to criterion 1.2.5 from the perspective of Risk. That is, in accordance with criterion 1.2.5, a tank constructed to the design and material criteria of Table 1 (i.e. designed to withstand destruction from natural phenomena) may be installed outdoors, provided that it has an outdoor retention pond with "provisions for sampling collected liquid and routing them to the liquid radv1aste treatment' system" in the event of overflow of the tank. Although not prescribed, it is implied that radioactive liquid from the tank would be collected in the outdoor environment. The new storage/rele~se tanks are not constructed to the design and material criteria of Table 1; however they are designed an acceptable alternative design that would protect the equipment from natural phenomena. The outdor tanks will be oontained within a retention area that provides continuous routing of any leakage to the WWTF, and prevents an uncontrolled release of radioacti,ve liquid, in the event of complete failure of the tanks. It should be noted here that the "Natural Phenomena and Internal/External Man-Induced Hazard Design Criteria" for non-safety systems, per Reg Guide 1.143-2001 Table 2 are for earthquake, wind, flood and precipitation. The following design features should be included for such tanks: J.2.1 All tanks inside and outside the plant, including the condensate storage tanks, should have provisions to monitor liquid levels. Designated high-liquid-level conditions should actuate alanns both locally and in the control room. All tanks of the system have provisions (either administrative or physical) for monitoring level. No alarms are provided for any of the tanks. The levels of the storage/Release tanks can only be increased by filling the tanks manually, while levels are monitored by plant personnel. Administrative controls limit the actual level allowed in the Release Tanks. The level in the HUTS is monitored during planned additions to the tanks, and on a periodic basis during other times. Normal, automatic additions to the HUTs from the AB sumps is due to ground water in-leakage which does not provide the capability for large additions of water such that an inadvertent overflow is unlikely. 1.2.2 All tank overflows, drains, and sample lines should be routed to the liquid radwaste treatment system. All potentially radioactive liquid in the AB is routed to the AB sumps. The AB sumps are routed to the HUTs. The storage/Release Tanks have overflow, sample and drain lines which are routed to the WWTF. Page 32 of61

AD-11 Revision 1 Information Use ATTACHMENT B-5 50.59 Evaluation Form 50.59 Evaluation No. -~2=0-=15""""-=09""-=5'--_ _ _ _ _ _ _ Revision Number: _1__ Activity/Document Number: =D-"'C=P......2=0=15-=-=-07....__ _ _ _ _ Revision Number: _o__ 1.2.3 Indoor tanks should have curbs or elevated thresholds with floor drains routed to the liquid radwaste treatment system. The HUTs are contained within a dedicated room which has provisions for containing any leakage from the tanks. 1.2.4 The design should include provisions to prevent leakage from entering unmonitored and nonradioactive systems and ductwork in the area. There are no operating systems or ductwork that leakage water can enter into in any of the buildings. The condition of all of the hoses is monitored by plant personnel during the use of the system, and would be stopped in the event of any leakage. 1.2.5 Outdoor tanks should have a dike or retention pond capable ofpreventing runoff in the event of a tank overflow and should have provisions for sampling collected liquid and routing them to the liquid radwaste treatment system. The outdoor tanks are installed within a secondary containment which drains to the WWTF.

4. ADDITIONAL DESIGN, CONSTRUCTION, AND TESTING CRITERIA In addition to the requirements inherent in the codes and standards listed in Table 1, the following criteria, as a minimum, should be implemented for components and systems considered in this guide.

4.1 Radioactive waste management structures, systems, and components should be designed to control leakage and facilitate access, operation, inspection, testing, and maintenance in order to maintain radiation exposures to operating and maintenance personnel as low as is reasonably achievable. Regulatory Guide 8.8 provides guidellnes acceptable to the NRC staff on this subject. The WWTF and the AB is designed to control leakage to the outside environment. Normal operation and maintenance of the system results in minimal dose to plant personnel due to the low levels of isotopic concentrations. 4.2 The quality assurance provisions described in regulatory position 6 of this guide should be applied. Portions of the liquid radwaste system are considered Important To Safety as described in the DSAR and the QAPP program for Zion Station. Design requirements for procurement of the new equipment is provided in the Bill of Material of the ECN. Page 33 of61

AD-11 Revision 1 Information Use ATTACHMENT*B-5 50.59 Evaluation Form 50.59 Evaluation No. 2015-095 Revision Number: _1__ Activity/Document Number: DCP 2015-07 Revision Number: _o__ 4.3 Pressure-retaining components ofprocess systems should use welded construction ro the maximum practicable extent. Process systems indude the first root valve on sample and instrument lines. Flanged joints or suitable rapid-disconnect fittings should be used only where maintenance or operational requirements dearly indicate that such constl'uction is preferable. Screwed connections in which threads provide the only seal should not be used except/or instrumentation and cast pump body drain and vent connections where welded connections are not suitable. Process lines should not be less than 314 inch (nominal). Screwed connections backed up by seal welding, mechanical joints, or socket welding may be used on lines 3 4 inches or larger but less than 2-112 inches. For lines 2-112 inches and above, pipe welds should be of the butt-joint 'type. Nonconsumable backing rings should not be used in lines carrying resins or other particulate material. All welding constituting the pressure boundary of pressure-retaining components should be performed in accordance with ASME Boiler and Pressure Vessel Code Section IX. All original piping is welded or flanged and bolted. [All new piping connections are threaded. All hose connections are either threaded and/or quick disconnects. The new piping and hose are installed and routed to minimize interference with decommissioning activities. Discharge hoses are pressure tested prior to every release. Any leakage from the system would be identified and isolated since the system is operated manually by plant personnel.) 4.4 Piping systems should be hydrostatically tested in their entire'ty except (1) at atmospheric tanks where no isolation valves exist, (2) where such temng would damage equipment, and (3) where such testing could seriously interfere with other system or component testing. In the case of (2) and (3), pneumatic testing should be performed. Pressure testing should be performed on as large a portion ofthe in-place systems as practicable. Tesdng ofpiping systems should be performed in accordance with applicable ASME or ANSI codes. The system is acceptable If pressure is held for 30 minutes with no leakage indicated. The entire system will be tested for leakage at the maximum operating pressure of the pumps for leakage. Ii' All inputs to the HUTs are routed through hoses that dump into the top man-ways of the tanks. As such, the HUTs cannot be pressurized beyond atmospheric pressure. c The processing tanks are atmospheric tanks that do not have isolation valves on the vents.

• c: The Release Tanks are atmospheric tanks that do not have isolation valves on the vents or overflow.

Page34 of61

AD-11 Revision 1 Information Use ATTACHMENT B-5 50.59 Evaluation Form 50.59 Evaluation No. --=2=0=15=---0=9-=-5_ _ _ _ _ _ _ _ Revision Number: _1__ Activity/Document Number: ... C=-P~2~01=5.._-0..... D...... 7_ _ _ _ _ Revision Number: _o___ 4.5 Testing provisions should be incorporated to enable periodic evaluation of the operability and required functional, performance ofactive components of the system. Testing and surveillance requirements for the system are specified in the ODCM.

3. Does the proposed activity result in more than a minimal increase in the consequences of an accident previously evaluated in the UFSAR? (See Section 6.2.3 of the RM) _ _YES X NO The liquid waste system does not interact with the systems associated with these accidents nor is it used to mitigate the consequences. As such, there is no effect on the consequences for these accidents due to the operation or failure of the liquid waste system.

4. Does the proposed activity result in more than a minimal increase in the consequences of a malfunction of an SSC important to safety previously evaluated in the UFSAR? (See Section 6.2.4 of the RM)

_ _YES X NO The new liquid rad waste system is a non-safety related system, and is not relied upon to mitigate accidents or transients described in the DSAR. The malfunction of the liquid waste system is not evaluated in the DSAR. As described in Reg Guide 1.143-2001 and the A 1 and A2 quantities defined in Appendix A of 10CFR71, the new system meets the classification requirements as the existing system, RW-llc, non-safety related. This is based on the total estimated curie content of liquid waste being less than ~. Malfunctions of the SSC of the new liquid rad waste system that are considered important to safety, are identified and described in 50.59 Evaluation criterion #2. The new liquid rad-waste system consists of a collection subsystem, processing equipment ( filters, demins, & pump), and a new pump that will release the processed water to Lake Michigan. The materials of the processing equipment of the system will be made of a combination of steel, plastic and highly durable hoses to provide the ability of relocating the system as necessary to accommodate decommissioning. The existing HUTs are constructed to equivalent standards described in Reg Guide 1.143. The entire collection subsystem, except for a portion of the discharge hose, will be located within the AB. Any leakage or rupture of the system inside the AB will be contained w!thin the AB. This is due to the existing drains and structure of the AB. As such, no increase in consequences can occur since no release from the AB can occur. The dedicated release path from the site to Lake Michigan (U2 discharge pipes) and associated control methods for monitoring releases is not changed. That is, this design change does not alter the function of the release flow instrumentation, the dilution flow

• instrumentation, or the discharge rad monitor, such that the concentrations of effluent are Page35 of61

AD-11 Revision 1 Information Use ATTACHMENT B~S 50.59 Evaluation Form 50.59 Evaluation No. --=2=0=15~-0=9=5_ _ _ _ _ _ _ _ Revision Number: _1 __ 01_.5-'-0....7_ _ _ _ _ Revision Number: Activity/Document Number: =D-=C..-..P'""'2..... _o.___ maintained well within the allowable limits of 10CFR20 and the notification limits of the QAPPAppendix B. The potential for the release and spread of large amounts of highly contaminated material inside the AB has been reduced to the minimum as there are no radioactive high energy sources (pressurized radioactive fluid lines) inside the AB. With the permanent shutdown of the plant and subsequent cleanup and decommissioning activities, the contamination levels inside the AB have been reduced to levels that result in dose limits comparable to the limits for an Unrestricted Area (i.e < 2mR/hr); and all stored contaminated water from abandoned equipment and decommissioning activities has been removed. As such, the potential for processing large amounts of highly contaminated liquid has been significantly reduced; and the potential for creating more contaminated water inside the AB due to decommissioning activities has been significantly reduced. The water to .be processed by the new liquid waste system will consist of mainly ground water in-leakage; .any remaining residual system water, ) and wash-down water associated with decommissioning will also be routed to the AB sumps. All water that collects in the AB is routed to the AB sumps. The majority of this water wiii be groundwater in-leakage, and any wash-down water used for decommissioning activities .. This water may become radioactive due to the r~suspension of loose contamination in the building, as the water passes over the contaminated surfaces. The AB has been decontaminated to the extent that there are only a few areas with contamination levels

    >1000 dpm/100 cm 2 (1K). As such, the areas that remain contaminated have.residual contamination that may be fixed or is not easily removed by normal wash-down efforts; so it is reasonable to use a r~suspension percentage of 10% (Ref. NUREG/CR-6755). One of these areas is the U1 HPC which has contamination levels at various points measured at 2K, 3K, 5Kand 10K.

The expected isotopic concentration of water entering the AB sumps will be the percentage of residual contamination that is suspended into the water. The following is used to establish an estimate of the expected isotopic concentrations of the water collected in the sumps. Assuming that the entire floor area of the U1 HPC is contaminated at 5K, the total gross beta contamination on the floor would be: (5000 dpm/100 cm 2 ) x 4.505 x 10*7 µCi/dpm x floor area= 2.25 x 10-3 µCi/100 cm 2 x floor area The floor area is -890 tt2 or 826,810 cm2* This results in a total contamination of 18.6 µCi. Page 36 of61

AD-11 Revision 1 Information Use ATTACHMENT B~S 50.59 Evaluation Form 50.59 Evaluation No. ---=2=0=-=15'--0=9~5_ _ _ _ _ _ _ _ Revision Number: _1_ _ Activity/Document Number: =D=CP=-=2=01=5'--0._.7_ _ _ _ _ Revision Number: _o__ Assuming that water fills the area to a depth of 1 ml (-218 gal) as it passes over the contaminated areas, the water collects 10% of the contamination. This results in a concentration of: 10% x 18.6 µCi/826,810 cm 3 = 2.25 x 10-e µCi/ml As an example of a limiting expected isotopic concentration of water collected in the sumps; a typical volume of groundwater in-leakage during the spring is -1500 gpd. Assuming that volume collects all the loose contamination in the U1 HPC results in a total collected x concentration of 3.28 1a-e µCi/ml. This concentration is less than the QAPP release limit of 10 times the value for C0-60 of Appendix B, Table 2of10CFR20 (For C0-60, this concentration is 3 x 1a..s µCi/ml).

• It should be noted here that the removal rate of residual loose contamination would be a function of the flow rate of the water passing over the surface; that is, the higher the flow rate, th~_ higher the removal rate. Also, as water continues to pass over the surface, the concentration due to re-suspension of the contamination decreases.

As shown above, the expected isotopic concentration of the collected water is less than the water that is currently being processed. As such, the consequences of malfunctions of the new system will be less than the consequences of malfunctions of the existing system.

5. Does the proposed activity create a possibility for an accident of a different type than any previously evaluated in the UFSAR? (See Section 6.2.5 of the RM) _ _YES X NO Leakage from the rad waste systems is described as one of the Fault Conditions for Nuclear Power plants, as described in ANSI 18.2. Although the standard is not applicable for decommissioning sites, leakage from radioactive sources was previously considered as a fault in the UFSAR. The design of the AB, the WWTF and the plant includes the provisions for leakage. As such, rupture of a tank or leakage from the system would not be considered an accident of a different type.

6. Does the proposed activity create a possibility for a malfunction of an SSC important to safety with a different result than any previously evaluated in UFSAR? (See Section 6.2.6 of the RM)

_ _YES~NO The malfunction of the liquid waste system is not evaluated in the DSAR. Page 37 of61

AD-11 Revision 1 Information Use ATTACHMENT B-5 50.59 Evaluation Form 50.59 Evaluation No. ---=2=0=15o._-0=9=5_ _ _ _ _ _ _ _ Revision Number: _1 __ Activity/Document Number: =-D-=C=-P-=2..-01_.S_..-0......7_ _ _ _ _ Revision Number: _,O...___ Malfunctions of SSC of the new liquid rad waste system that are considered important to safety, are described in 50.59 Evaluation criterion #2. The results of these malfunctions are an unplanned or abnormal discharge or release. Although not described iri the DSAR, a loss of dilution flow due to a pump trip during a liquid waste release, will result in isolation of the waste discharge line that discharges to the outfall. An unplanned or abnormal discharge of radioactive liquid from the plant (i.e. to the unrestricted area) would require multiple errors and/or failures by plant personnel and/or equipment. This is due mainly because all releases require manual operation by plant personnel. A likely scenario is underestimating the isotopic concentrations of the release tank.and the discharge rl;ldiation monitor failing to isolate the release. As a conservative example of this scenario, using the maximum release rate of 500 gpm +10% with the minimum dilution flow of 10,000 gpm -*10%\ and the maximum (currently measured) unprocessed Co-60 concentration of 1.333E-5 uCi/g + 10%; results in a release concentration of: * * * * (1.333E-5 uCi/g)*1.1 *(500*1.1 )/(10,000*0.9) = 8.96E-7 uCi/g This concentration is less than the limits of 10CFR20 Table 2. It should be noted here that:

• The maximum (currently measured) unprocessed Co-60 concentration of 1.333E-5 uCi/g is less than the QAPP notification limit of 3.0E-5uCi/g.

        *<!  The administrative limit for the maximum release concentrations in the Lake Release Tanks is less than the QAPP notification limit of 10 times the limits of 10CFR20.

• The maximum flow rate of the release pump is less than 500 gpm.
• The .minimum dilution flow rate is administratively controlled to be greater than 10,000 gpm.

The new system is controlled and operated by plant personnel, and has no automatic release features, such that all processing and transfer of liquid waste is done in batches on a periodic basis. The following design feat~res and administrative requirements are included with the new system to maintain the existing design criteria stated in the DSAR, and to reduce the risk of a complete rupture of the system: 6> All tanks of the storage system are located inside the AB. The AB is designed as a Seismic Class I structure and would be analogous to the criteria of classification RW-lla as described in Reg Guide 1.143-2001. As such, all tanks of the storage system are protected from destruction of the AB due to natural phenomena. o The storage/Release Tanks when used:in the release mode will be isolated from all inputs prior to and during releases. This will provide assurance that release concentrations are maintained during the release.

• Page 38of61

AD-11 Revision 1 Information Use ATTACHMENT B-5 50.59 Evaluation Form 50.59 Evaluation No. --=2=0,,_,15.._-0=9=5_ _ _ _ _ _ _ _ Revision Number: _1_ Activity/Document Number: .... D__C..._P__z__ ot__s.-o. .....7_ _ _ _ _ Revision Number: _o___

         "'  Components of the processing/release system, except for a portion of the discharge hose and the tanks, are located on or below the ground level of the WWTF. Any leakage or rupture of these components will be controlled such that it is contained within theWWTF.

• Damage and/or rupture of the storage tanks and associated equipment is unlikely due to the location and construction. Overflows for each tank are routed to the WWTF.

        &>  Plant personnel will monitor the operation of the release system and dilution system during batch releases to ensure proper operation; e.g.; proper waste discharge flow, proper dilution flow, no leakage on the discharge line.
        "   The maximum release concentrations of the Release Tanks are administratively set at
            <10 times the annual average release concentration limits of 10CFR20 Appendix B, Table 2, such that a release to Lake Mic.higan can never be higher than the QAPP notification limit ( 10 times the 10CFR20 limits) regardless of tlie dilution flow rate or

.i Release Tank discharge rate. ECN 2015-09 of this Design Change relocates radiation monitor PR-04 to the WWTF. The local alarm and isolation functions associated with the radiation monitor have been maintained. Indication of radiation level is provided locally. The original location of the isolation valve, SOV-WD0010, was inside the TB, -250 feet from the rad monitor. This location was associated with the original design of the liquid waste system and provided a period of time for the rad monitor to process an alarm, and close the valve prior to the release entering the discharge canal. The new locations and distance between the rad monitor and isolation valve will be established to provide for sufficient time to prevent the release from entering the outfall in the event of a high alarm isolatipn function. This distance will require the maximum release flow rate to be administratively controlled at less than 200 gpm.

7. Does the proposed activity result in a design basis limit for a fission product barrier as described in the UFSAR being exceeded or altered? (See Section 6.2.7 of the RM) _ _YES _LNO No fission product barriers are affected by this change. The liquid waste system is not connected to the SFP.

Page 39 of61

AD-11 Revision I

• Information Use ATTACHMENT B-5 50.59 Evaluation Forin 50.59 Evaluation No. _ _,,2=0=15:....-0=9=5_ _ _ _ _ _ _ _ Revision Number: _1__

Activity/Document Number: :::::D_,,.C~P-=2.,,.,01...,,5'--0:..:7'------- Revision Number: _o____

8. Does the proposed activity result in a departure from a method of evaluation described in the UFSAR used in establishing the design bases or in the safety analyses? (See Section 6.2.8 of the RM)

_ _YES _x__NO The design features and administrative requirements imposed on the operation of the new system (storage, processing and release systems) provide an acceptable alternate method for complying with the DSAR design functions and NRC regulations. As stated in Section D of Reg Guide 1.143-1979, its purpose was for evaluation of applications for Preliminary Design Approval, Final Design Approval, Manufacturing License and Construction permits. As stated in Section D of Reg Guide 1.143-2001, "Current Licensees may, at their option, comply with the guidance in this regulatory guide." Page 40 of61

AD-11 Revision 1 Information Use ATTACHMENT B-5 50.59 Evaluation Form 50.59 Evaluation No. _ .....2=0..-15~-~09~5'--_ _ _ _ _ _ _ Revision Number: _1 _ _ Activity/Document Number: -=D_.C=P......2...._0=15-........_07________ Revision Number: _o__ Il. Identify references used to perform the evaluation (if not provided in the response to each question). QAPP Appendix B 5.6.2.b, 5.6.3 DSAR 4.5 & 4.6 ODCM Chapters 10 & 12 m Based upon the results of this Evaluation. (Select one of the following) D If the answer to any of the questions is YES, then NRC approval is required prior to implementation. X If the answers to all of the questions are NO, then implement the Activity per plant procedures. IV. Evaluation Signoffs 50.59 Evaluator: f/rftJv~ R fkt/£.wl? * '4--.1: t--rft ,, ,, ate: _l2d_ / l-/;...Liz.,.- (Printed Name) // (Signature)

     *50.59 Reviewer:      f3t.~ L J.    !Je1r.JeClfG                   ,L~~ate: .a__j!.J!..J IS (Printed Name)                             *?(Signature)
     *so.s9 Reviewer:     -;;;;..-e,J e -;.,,-;t, (Printed Name)                       ,f;,
                                                                            ~, __R_J..1!f.! is (Signature)

-f!or VP Regulatory Affilirs' J"C Ash/ev (Printed Name) /

                                                                              ~.Dated.2JJ!Lt p~gna                .                          IS
                                                                          ,./

• QTR qualification required Page 41 of61

Decommissioning Impact Evaluation Job Aid No. ENG-06 Exhibit A Revision: .Q DECOMMISSIONING IMPACT EVAl..UATION Activity: _ 'T)c.,,./*::> ,J...t/?/ !V-O.-.I (Work Order No., Procedure No., On Site Review No., Design Change No., etc) TRACKING#:----

1. Does the proposed decommissfoning activity result in any of the following:

a. Foreclose the release of the site for possible unrestricted use;

[ ] YES

b. Result in significant environmental impacts not previously reviewed;

[ ] YES [)c1 NO "0 S' l!';Pt f!'t~J}j

                                                            . t;GG:. S'-'ePt.eHE,w"f"  I cBrn:P.tJi...

c. Result in there no longer being reasonable assurance that adequate funds will be available for decommissioning.

[ ] YES [X] NO

2. Review the answers to Step 1.a-c. 1f the answer to any of the questions is YES, Then the activity can NOT be completed, without prior notification to the NRC.

Decommissioning Impact Evaluation Job Aid No. ENG-06 "1 { Exhibit A Revision: ..Q DECOMMISSIONING IMPACT EVALUATION (Continued) Activity: _ _1)-E-,,,,.... ,P_:_-2",,_*_,,__,f;~,7_/_S_---=19_*_-,......;/_,.- - - - - - L.._<<...._. NOTE In taking actions permitted under 10CFR50.59 following submittal of the PSDAR, the licensee may perform activities inconsistent with the PSDAR, including significant schedule changes or significant cost increases, provided prior written notification is made to the NRC, as well as a copy of the notification to the State of Illinois.

3. Is this activity Inconsistent with those actions described in the Post-Shutdown Decommissioning Activities Report or cause a significant schedule change or cost increase?

[ J YES QQNO 1f the answer is YES, Then notify the NRC and the State of Illinois prior to performing the activity._

            !f the answer is NO, Then proceed without notification.

4. Implement Changes - Based on th,is evaluation, I have determined that the proposed activity is not restricted by 10CFR 50.82.

Preparer print name: fl- R liPttwr.~ Discipline: _ft Id C.. (;....- vt I~

                  /;;       ,/7           ,/   ,.4'
                                        .#-.,:-/,,...V;;!. *--- .                                     /P-).(r/~

Preparer Signature Date

5. Review - The reviewer agrees that the proposed activity is not restricted by 10 CFR 50.82.

Discipline: A.<'.'.Sl ta /~,__s----J--~--L_ 5 __ Date z '*

ZionSolutions LLC ZS-2017-0058: Attachments ATTACHMENT 4 TR-005-2016 ODCM Rev 6 Technical Review Letter

TECHNICAL REVIEW LETTER TR-005-2016 To: Tony Orawiec Decommissioning Plant Manager Zion Station

Subject:

ODCM, Rev 6

SUMMARY

OF CHANGES: Per QAPP App. B Section 5.6.1.c and ODCM Section 12. 7 .3 .1, this technical review provides sufficient information to support this ODCM revision with appropriate analysis or evaluations to justify this change. The results of this technical review demonstrates that the change( s) to the ODCM will maintain the level ofradioactive effluent controls required by 10 CFR20.1302, 40 CFR190, 10 CFR50.36a, and Appendix I to 10 CFR50 and will not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations. Signatures below by reviewers document the fact that this change has been reviewed and found acceptable. This ODCM change will become effective when issued by document control. Previous revisions to the ODCM specified Harshaw TLD series 100 chips to be used for direct radiation monitoring under the REMP program. TLD 100 chips contain elements with natural Lithium which contains 7.5% Li-6. LI-6 responds to neutrons and overestimates gamma dose when in presence of neutron skyshine or direct neutron flux. A two year study was conducted which verified that Panasonic TLD with UD-814-Al element provides a better resolution and broader range of gamma radiation detected. Additionally, the UD-814-Al chips are not adversely affected when in presence of neutrons. TLD UD-814-Al is a better choice for REMP TLDs at Zion station. ECN 2015-07 redesigned the liquid effluent system. The three HUTs are abandoned and prepared for demolition and thus may be removed from documentation. Residual water from the site is collected by the Aux Building Collection Tank (3000 gal.) and the ODCM is changed to reflect this. In addition the old Lake Release Tanks are abandoned to allow for demolition and have been replaced by three double wall 17 ,900 gallon frac tanks that can receive water from the Aux Building Collection Tank. The name on the engineering diagram labels these three Lake Release Tanks as Release/Storage Tank A and B, and Clean Water tank. All three tanks are capable of being used as Lake Release Tanks and thus collectively will be referred to as Lake Release Tanks. All three Lake Release Tanks can be filled from or send water to the demineralizers for processing. Only two of the tanks can receive unprocessed water from the Aux building. All three tanks share a common discharge header to the discharge tunnel. While Boron is still residually present, two flowmeters OFI-WD0005 and 6, are the same flowmeters previously used in the old system for the range of 5-50 gpm. these two flowmeters bypass the main flowmeter OFI-WD008 which will be used when Boron concentration permits and has a range of 50- 400 gpm, though the system will be limited to 125 gpm to allow for WD-10 to close prior to effluent reaching the discharge canal on a high alarm of OR-PR04. The lake release

TR-005-2016 Page 2of3 tanks are all double wall tanks and all suction and discharge hoses and recirculation lines are either double wall hoses, have a sleeve covering the inner hose or are located within a catch to collect leakage. On the outer hose, they are open on one end to make it possible to visibly detect a leak of the inner hose, any leakage will be caught in a contained area preventing any possible undetected release of radioactive water to the environment. Prepared By: Jared R. Smith Date: ----=6/=29::...:..1..:::...:16::..____

TR-005-2016 Page 3of3 Page# . Section Description of change

• 37 10.2.1.1 Redefined definition of Lake Release Tanks 37 10.2.1.2 Removed HUTs description and replaced with Aux Building Collection tank and description.

59 Table 12.2-1 Changed effluent flowrate monitors to include only OFI-WD0005, 6 and 8. Deleted OFI-WD005A and 6A. Modified Lake Release Tank #1 and #2 to read high flow pathway and low flow pathway as all flowmeters are in common header to all 3 lake release tanks. 61 Table 12.2-2 Changed effluent flowrate monitors to include only OFI-WD0005, 6 and 8. Deleted OFI-WD005A and 6A. Modified Lake Release Tank #land #2 to read high flow pathway and low flow p:;i.thway as all flowmeters are in common header to all 3 lake release tanks. 83 Table 12.5-1 Added TLD type UD~814-Al as acceptable TLD type for Environmental Monitoring TLDs.

ZionSolutions LLC ZS-2017-0058: Attachments ATTACHMENT 5 TR-011-2016 ODCM Rev 7 Technical Review Letter

TECHNICAL REVIEW LETTER TR-011-2016 To: Tony Orawiec Decommissioning Plant Manager Zion Station

Subject:

ODCM, Rev 7

SUMMARY

OF CHANGES: DELETE SECTION 10.2.1.2 Per QAPP App. B Section 5.6.1.c and ODCM Section 12.7.3.1, this technical review provides sufficient information to support this ODCM revision with appropriate analysis or evaluations to justify this change. The results of this technical review demonstrates that the change( s) to the ODCM will maintain the level of radioactive effluent controls required by 10 CFR20.1302, 40 CFR190, 10 CFR50.36a, and Appendix I to 10 CFR50 and will not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations. Signatures below by reviewers document the fact that this change has been reviewed and found acceptable. This ODCM change will become effective when issued by document control. Prepared By : _ ____;;Art~h=ur=o....=A'-==dam=s"---- Date: 10-10-2016

TR-011-2016 Page 2 of2 Page# Section Description of change 37 10.2.1.2 Delete Section _J

ZionSolutions LLC ZS-2017-0058: Attachments ATTACHMENT 6 TR-012-2016 ODCM Rev 8 Technical Review Letter

TECHNICAL REVIEW LETTER TR-012-2016 To: Anthony Orawiec Decommissioning Plant Manager Zion Station

Subject:

ODCM, Rev. 8

SUMMARY

OF CHANGES: Per QAPP App. B Section 5.6.1.c and ODCM Section 12.7.3.1, this technical review provides sufficient information to support this ODCM revision with appropriate analysis or evaluations to justify this change. The results of this technical review demonstrates that the change(s) to the ODCM will maintain the level ofradioactive effluent controls required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50 and will not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations. Signatures below by reviewers document the fact that this change has been reviewed and found acceptable. This ODCM change will become effective when issued by document control. Technical Review justification for changes made are discussed in ES&H TSD 16-007 and 16-009. Prepared By: Jared R. Smith Date: 12/7/2016

TR-012-2016 Page 2of4 Page#. Section .

Description:

of ch.ange . 6 2.2 Ventilation exhaust treatment system changed to open aif demolition sampling requirements 28 6.1 Gaseous radwaste treatment system changed to portable ventilation exhaust filtration system. 36 10.1.1 Discussion ofUl and U2 vent stack and Aux building ventilation changed to reflect air sampling configuration required for decommissioning and open air decommissioning. 36 10.1.1.1 Ventilation,Exhaust Treatment System is deleted 36 10.1.2.1 Aux building vent stack effluent monitors changed to reflect open air demolition air sampling requirements 36 10.1.2.2 Containmel)t purge effluent monitors changed to Active Decommissioning Air Sa:mplirig and description of portable exhaust filtration. 37 10.1.3.5 HVAC floW!ates description changed to use max design flow capacity of portable ventilation filtration units. 39 10.4.1 Description of gaseous effluent rad monitors removed, leaving only liquid effluent rad monitor in d~scription. 39 10.4.2 Descriptio~ of gaseou~ effluent rad monitor removed, leaving only liquid 'effluent rad monitor in description. 40 10.4.3 Containment Purge system effluent monitor description deleted 40 10.4.4 Fuel Builqipg Exhaust air monitor description is deleted. 40 10.4.6 Descriptiori ofcalibr~t,i()h and testing of gaseous radiation alarming monitor is rem0ved from this section, leaving liquid effluent raq monitor ,caiibratio~ and testing unchanged. 40 10.4.7 Continuou~* radiation mo.nitoririg system is deleted. Added to this section req\lirement for contim~ous sampling, composite and laboratory analysis of ~if samples taken for active decommissioning effluel)t sampl~s.

                                  .       '       'I   I        '

43 Table 10-2 HVAC exhaust fan qapacity table is deleted. Added description to us the m~ximum design flowra,te of portable exhaust filtration systems willI* be used in calculations requiring exhaust flowrate. 62 12.2.2.A Gaseous e$uent rad monitor operability requirements removed. Added operabiJity teq~irements for gaseous effluent air samplers during acti~e I decommissioning.

                                       '1      . I  I 62          12.2.2.B.l   Deleted gaseous effluent radiation monitor setpoint requirements
                                                 '  I ,,

I 62 12.2.2.B.2 Deleted channel caJiprations for gaseous effluent radiation monitors. Added teqhirements

                                                 ' '  I to ensure gaseous effluent air sampler flow rates wjd counting equipment is calibrated.

TR-012-2016 Page 3of4 Page# Section Description ofchange -- 62 12.2.2.C Deleted bases of gaseous effluent radiation monitors. Added bases for particulate air samplers needed for quantifying effluent release. 63 Table 12.2-3 Deleted 1(2)RIA-PR49 and 1(2)LP-084 oerability, surveillances, applicable conditions. Added Surveillances and applicable conditions for Ul, U2 containment air samplers and open air demolition air samplers and South waste loading area air samplers. 64 Table 12.2-3 Deleted surveillance for gaseous effluent rad monitor inoperability. Added surveillance requirement to ensure air samplers are operating or cease active decommissioning. 65 Table 12.2-4 Deleted channel checks, source checks, channel calibration and functional checks of gaseous effluent radiation monitors. 75 Table 12.4-1.B,C Deleted containment vent and purge, aux building, Ul vent stack, U2 vent stack sampling requirements. Added Ul ventilation, U2 ventilation and portable filtered ventilation various location requirements. 75 Table 12.4-1.D Changed unventilated. release description from building to Ul, U2 tent. Modified sampling requirements from continuous to continuous during active decommissioning and modified note (h) 75 Table 12.4-1.E Added this section to provide sampling requirements, analysis, type of analysis and LLD's to open air decommissioning work. 76 Table 12.4-1 a. Removed 1(2) RIA-PR49, containment and AB. Added table notations requirement for continuous sampling during active decommissioning when a vialbe release pathway to the en:vironment exists.

h. changed clarification of a short duration activity to include moving a.fr sampler to a more appropriate location when necessary.

1. Changed from DELETED to add continuous air sampling at open air demolition locations are required to be maintained in 4 general directions during active open air decommissioning with potential for airborne releases.

78 12.4.4 A,B: Deleted requirements for gaseous effluent treatment system. Modified wording that dose projection every 31 days shall take place in compliance with QAPP section 5.6.2.f C: modified bases to describe ALARA practice of encapsulating loose contamination as a method of practicing ALARA during decommissioning. I

TR-012-2016 Page 4of4 Page# Section Description of change 94 12.7.2 Removed discussion of gaseous effluent monitoring instrumentation inoperability requirements. 181 Table F-1 Deleted reference to section C.1.3.1.2 ofODCM Appendix C. as this section was removed from the ODCM at some point prior to 2011, and the reference was overlooked in previous revisions of Appendix F.

ZionSolutions LLC ZS-2017-0058: Attachments ATTACHMENT 7 ES&H TSD 16-007 Basis Document for TR-012-2016

ZionSolutions, LLC. Technical Support Document TSD 16-007 Justification for Removing 1/2 RIA-PR49, gaseous effluent sampling Originator: Jared R. Smith 1113/2016 Name Reviewer:~~,.., h""'""'IR.~: Name Page 1 of Stf S'S'

TSD-16-0071 Rev.a Summary of Changes in this Revision:

• Rev. 0 -Initial issuance.

Page 2 of SS

TSD-16-0071 Rev. 0

1.0 INTRODUCTION

This Technical Support Document (TSD) provides the bases for removing the requirement of 1RIA-PR49 and 2RIA-PR49 Vent Stack Radiation Monitors. Zion Station is at a point in decommissioning where the. activity concentration of radioactivity that could be released has such low potential impact to dose to the public that an alarming feature in gaseous effluent monitoring is no longer required. This TSD was created as upcoming stages of decommissioning require the removal of equipment in the Aux Building to proceed with decommissioning. The information presented will demonstrate that the dose resulting from decommissioning activities will be well below regulatory limits This document will discuss means for sampling and analysis of airborne samples and guidance for generating administrative job aids for monitoring gaseous effluent releases. 2.0 ZION STATION PROGRAM GUIDANCE 2.1 Zion Station DSAR (ref 10.1): The applicable portions of the DSAR to be consider are found in section 3 .1 Design Basis-Conformance with NRC General Design Criteria(GDC). 2.1.1 Criterion 17 - Monitoring Radioactivity Releases Meansshall be provided for monitoring the containment atmosphere, the facility effluent discharge paths, and the facility environs for radioaetivity that could be released from normal operations, from anticipated transients, and from accident conditions. 2.1.2 Criterion 70 - Control of Releases of Radioactivity to the Environment: The facility design shall include those means necessary to maintain control over the plant radioactive effluents, whether gaseous, liquid, or solid. Appropriate holdup capacity shall be provided for retention of gaseous, liquid, or solid effluents, particularly where unfavorable environmental conditions can be expected to require operational limitations upon the release of radioactive effluents to the environment. In all cases, the design for radioactivity control shall be justified: (a) on the basis of 10 CFR 20 requirements for normal operations and for any transient situation that might reasonably be anticipated to occur; and (b) on the basis of 10 CFR 100 dosage level guidelines for potential reactor accidents of exceeding low probability of occurrence except that reduction of the recommended dosage levels may be required where high population densities or very large cities can be affected by the radioactive effluents. 2.1.3 DSAR section 4.6 Radiation Monitoring Systems. Section 4.6.1: Design Bases: The original purpose of the radiation monitoring system was to annunciate and record radiation levels at selected locations of the plant. As the plant is in later stages of decommissioning and the source term significantly reduced, there is no longer a credible accident that could cause a significant increase in radiation levels or effluents released in gaseous activity to the point of reaching any regulatory limits. Page 3 of55

TSD-16-0071 Rev. 0 Portable radiation monitoring equipment will be used to maintain ALARA for radiation workers and members of the public. The liquid effluent radiation monitoring system will be maintained and used as required per the QAPP and ODCM. 2.2 Zion Station QAPP section 5.6.2(ref. 10.2): The QAPP is a license compliance document that demonstrates our operations are in conformance to 10CFR 50.36a (ref 10.12), 10CFR20.l30l(ref 10.6), 10CFR20 App. B Table 2 Column l(ref 10.5), 10CFR50.App. I(ref 10.7) dose limits. It is important to note the terminology in the QAPP that states "Gaseous Monitoring Instrumentation." That for an operating Reactor, the word 'monitoring' refers to continuous radiation monitoring with alarm set-points where in the case of late stages of decommissioning, 'monitoring' will be used to define the equipment and procedures used in collecting and analyzing airborne samples. ANSI N13.1 - 1999(ref10.4) and this TSD will be used to demonstrate the differing levels of potential impact categories and how to define what type of monitoring is required based on operational/decommissioning status of the plant. 2.3 10CFR50.36a Technical Specifications on effluents from nuclear power reactors(ref 10.12): This regulation requires plants to maintain radioactive releases as low as reasonably achievable and comply with provisions of 10CFR20.1301. This section ofregulation guides the annual effluent release report. All releases will continue to be included in the annual effluent release report. 2.4 10CFR20.1301ref 10.6): Section 1: The applicable portions of guidance for the purposes of this TSD is that the TEDE to individual members of the public do not exceed lOOmrem in a year. However, this guidance further states that a licensee subject to provisions of EPA' s generally applicable environmental radiation standards in 40CFR190. 2.5 40CFR190(ref 10.11): Rule summary: Annual dose equivalent to any member of the public from all sources to 25mrem per year TEDE, 75mrem per year thyroid, and 25 mrem per year for any other organ, and 0.5 mCi combined of Pu-239 and other alpha-emitting transuranic radionuclides with half-lives> 1 year. 2.6 10CFR50 App. I(ref 10.7): Regulatory Staff position guidance: Design objectives state that Section II.C. Gaseous effluents released to the air will be demonstrated to be ALARA if it can be shown that all annual total quantity of all radioactive material in particulate form above background will not result in annual dose or dose commitment from all pathways to be in excess of 5 mrem Total Body and 15 mrem to any organ. Page 4 of55

TSD-16-0071 Rev. 0 2.7 Zion Station ODCM (ref 10.3) 2.7.1 Section 12.4.1.A: For tritium and particulates with tl/2 > 8 days the limit is less than or equal to 1500 mrem/yr to any organ. RETS limit 2.7.2 Section 12.4.3.A: The dose to a MEMBER OF THE PUBLIC from tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas at or beyond the SITE BOUNDARY (see ODCM Appendix F, Figure F-1) shall be limited to the following: During any calendar year: Less than or equal to 15 mrem to any organ. 2.7.3 12.4.4.A The GASEOUS EFFLUENT TREATMENT SYSTEM shall be OPERABLE* and appropriate portions of these systems shall be used to reduce radioactive materials in gaseous effluents when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at or beyond the SITE BOUNDARY (see ODCM Appendix F, Figure F-1) would exceed 0.3 mrem to any organ. ANSI N13.1 - 1999(ref10.4): Specific Section regarding potential impact categories (PIC)s are cited here and form the bases for removal of 1&2 RIA-PR49:

       "A graded approach is recommended in the design of systems that fulfill the requirements for sampling radionuclides in stacks and ducts of the nuclear industry. If the source is Potential Impact Category (PIC) 3 of table 2, only periodic confirmatory sampling is required. Such sampling shall be carried out using either installed or portable equipment meeting or exceeding the requirements of this standard. Often extended sampling periods (on the order of several days) may be needed to adequately characterize a PIC 3 source. If the source is either a PIC 1 or a PIC 2 of table 2, continuous sampling is required; and, if the source is PIC 1, continuous monitoring is also required. The focus of this clause is on continuous sampling and monitoring requirements." Quoted from Section 6 of ANSI N13 .l-1999(ref10.4) pp. 32.

Page 5 of SS

TSD-16-0071 Rev. 0 Table 2 - Graded approach to sampling and momtonng Potential impact Monitoring and sample analysis procedures Potential fraction category of allowable limit 1 Continuous sampling for a record of emissions and > 0.5 in-line, realtime monitoring with alarm capability; consideration of separate accident monitoring system 2 Continuous sampling for record of emissions, with >0.01 and retrospective , off-line periodic analysis s0.5 3 Periodic confirmatory sampling and off-line >0.0001 and s0.01 analysis 4 Annual administrative review of facil ity uses to _0 .0001 confirm absence of rad ioactive materials in forms and quantities not conforming to prescribed specifications and limits Table quoted from ANSI-N13.1 - 1999(ref 10.4) pp. 15 3.0 PARAMETERS USED FOR ANALYSIS 3.1 Flow Rates: The current DSEP scenarios use a value of 186,000 cfm release rate based on ventilation fan configuration. The purpose of this TSD is to demonstration removal of this system and thus new CFM release rates need to be considered. There are two pathways of releases considered. 3.1.1 Portable exhaust fan : A 30,000 CFM maximum flow filtered ventilation unit to maintain habitability while performing demolition of Ul and its associated tent. Additionally a combined 10,000 CFM maximum flow filtered ventilation to maintain habitability for the U2 containment and its associated tent. 3.1.2 Wind blowing through an open doorway: To determine the flowrate of wind blowing through and opening, two factors need to be considered. These are the area of the opening and the speed of the wind. 3.1.2.a Two wind speeds will be considered: lm/s wind speed from ANL/EAD/TM-53(ref 10.16) and the average historic wind speed from the wind rose. The wind rose is broken down into wind speed categories. It has been recommended to use the maximum wind speed of the average wind speed band. The 3.6-7.5 mph category and the 7.6-12.5 mph category represent 35% and 34% Page 6 of SS

TSD-16-0071 Rev. 0 of the average annual wind speed respectively. Thus 12.5 mph will be used. NRC staff guides when using mean wind speed for release rates, use the upper end of the wind speed of the class in which the mean wind speed falls within.(See attachment 1) 3.1.2.b Areaofopenings: The area of the various openings is listed in the chart below for comparison. The primary consideration will be the roll up door of the construction tents outside ofUl and U2 demolition access. In reality there would need to be a wind tunnel effect in order for the wind to blow through at the rate calculated with an opening of the same size, but this theoretical situation will be considered. Standard door: 3' x 8' = 24 ft2 AB 592' rollup doors: 12' x 12' = 144 ft2 FHB truck bay doors: 18' x 20' = 360 ft2 Tent roll up door(proposed): 13 ' x 18' = 234 ft2 Table 1 CFM values Wind speed 1 mis (197 12.5 mph (1100 ft/min) ft/min) Location Door CFM CFM size Standard personnel 24 ft2 4728 26400 door AB 592 ' rollup 144 ft2 28368 158400 FHB truck bay 360 ft2 70920 396000 Tent rollup 234 ft2 46098 CFM 257400 CFM 3.1.3 A third value of 1 cfm will be presented for a calculation factor. This value will be provided for input to aid in calculating any dose rate during any time period. 3.2 Dose: This is the dose assigned to the maximally exposed age group. With the ratios of our target nuclides, the maximally exposed age group for Total body is Adult, maximally exposed organ, Teen Bone. The dose is the mrem value of the sum of the dose over 50 years, all assigned the first year. 3.3 BR: Breathing rate. RG 1.109 (ref 10.13) listed values of breathing rates for various age groups: Page 7 of SS

TSD-16-0071 Rev. 0 Table 2 Breathing Rates Age group Breathing rate Adult 8000 m3 I year Teen 8000 m3 I year Child 3700 m3 I year infant 1400 m3 I year 3.4 Ko: Conversion factor: Converts pCi to Ci and seconds to years= 3.17 E+4 pCi-year/Ci-sec 3.5 Q: Release Rate. Quantity released in Ci/year or uCi/sec 3.6 x: relative concentration factor (pCi/m3) this value is taken at 400m

3. 7 xIQ: Chi over Q atmospheric dispersion coefficient taken at 400m for Pasquill F ground level release= 6.59 E-4 sec/m3. Value taken from TSD-12-00l(ref 10.15)

Table 3 x/Q values Distance y}Q (meters) (sec/m3) 100 8.650E-03 150 3.248E-03 200 2.487E-03 300 1.163E-03 400 6.593E-04 3.8 DF Aeff: Effective Inhalation Dose Factor (rnrern/pCi). DFAeff is a weighted value of inhalation dose factors (DFAs) from NUREG 0172(ref10.8). The DFA is the dose received over 50 years per pCi of isotope inhaled the first year, with the dose assigned to the first year of inhalation. To Estimate dose from hard to detect (HTDs) and alpha emitting nuclides, the scaling factors or ratios to Co-60(rCo60) of the HTDs and transuranics were multiplied by the DFAs of each nuclide and summed. This was done for Total body (Tbody) and each organ for each age group (See attachment 4). The results of this calculation is the Effective Dose Conversion Factor (DF Aeff)(See attachment 3). The DFAefffor Tbody of each age group was compared, similarly, the highest value of each organ of each age group was compared. The highest values from this comparison are listed below and will be used in calculations. Page 8 of SS

TSD-16-0071 Rev. 0 T able 4 DFAeff values( Attachment 3) Age group-organ DFAeff Adult Tbody 1.12 E-3 mrem/pCi-year Teen Bone 1.81 E-2 mrem/pCi-year 3.9 r(isotope i): Ratio of nuclide i to Co-60(e.g. rNi-63 , rAm-241. Values were obtained by comparing smear results from various areas of the plant for part 61 data (See attachments 5&6). Each set of smears was forward decay corrected to a future date of 1/1/2018. The future decay correction was used instead of present because as time progresses, Co-60 decays faster than the remaining primary dose contributing isotopes. Additionally as time progresses, there is ingrowth of Am-241 from the decay of Pu-241 , this factor is also considered in the ratio. Overall, the more that time passes from the decay correction of the analysis results, the less conservative the ratios become, thus a future date was selected. After forward decay correction, each set of part 61 data was reviewed for each nuclide. The value at the location with highest ratio of the specific nuclide was selected to be include in the composite scaling factors. Table 5 shows the composite scaling factors (ratios) to Co-60 that are used in calculations. Table 5 rCo60 - Composite scaling factors to Co-60 as of 11112018 (See attachment 5) Radionuclide r(isotope i) Radionuclide r(isotope i) C-14 2.62E-02 Sb-125 1.88E-03 Fe-55 7.64E+Ol Cs-137 8.04E+OO Ni-59 2.05E-01 Am-241(1) 5.24E-03 Ni-63 l.46E+Ol Cm-242 2.00E-06 Sr-90 3.36E-03 Cm-243/244 1.97E-03 Tc-99 7.1 lE-04 Pu-238 l .36E-03 Co-60 1.00E+OO Pu-239/240 2.3 lE-04 Nb-94 3.35E-02 Pu-241 5.34E-02 (1) Am-241 includes ingrowth. 3.10 Dose limits: Various dose limits are considered in order to reverse calculate the uCi/mL activity concentration that would give each specific dose limit for the three flow rates considered. Below is a list of the Dose limits and where the values came from. Page 9of55

TSD-16-0071 Rev. 0 Table 6 Dose limits considered Dose description Taken from 1 mrem Tbody Convenience for calculations 1 mrem Organ Convenience for calculations 5 mrem Tbody 10CFR50 App. I I ODCM 15 mrem organ 10CFR50 App. I I ODCM 1500 mrem organ QAPP/ODCM (RETS) 1.2 mrem Tbody QAPP 2% of annual limit in 31 days x 12 3.6 mrem organ QAPP 2% annual limit in 31 days x 12 3.11 EC: Effluent Concentration Limit taken from 10CFR20 App. B Table 2 Column 1 (ref 10.5). The activity in uCi/mL of air that if breathed in by a member of the public for 8760 hours per year (with adjustments for occupancy and age) would result in a committed dose or dose equivalent of 50 mrem per year. 3.12 ECeff: Effective Effluent Concentration Limit. This is a weighted value of the EC factors using the scaling ratios to Co-60. ECeff is the sum of the r(isotope i) divided by the EC of isotope i.(See Attachment 2) 3.13 ECf: Effluent Concentration fraction: This value must be ~ 1 per 10CFR20.1302 (ref 10.14). This value represents the sum of the concentration of nuclide i in uCi/mL divided by the EC of nuclide i. The manner this document will make this calculation is the concentration of Co-60 divided by the ECeff. 4.0 EQUATIONS AND CALCULATIONS 4.1 Equations Eq.l DFAeff = :LDFAij

• rCo60i (Attachments 3&4)

Eq .1 Expanded: DFAeff(organj)= DFACo-60

• rCo-60 + DFAC-14* rC-14 + DFAFe-55* rFe-55 +

DFANi-59* rNi-59 + DFANi-63* rNi-63 + DFASr-90* rSr-90 + DFATc-99* rTc-99

       + DFANb-94* rNb-94 + DFASb-125* rSb-125 + DFACs-137* rCs-137 + DFAAm-241

• rAm-241 + DFACm-242* rCm-242 + DFACm-243/4* rCm-243/4 + DFAPu-238* rPu-238 + DFAPu-239* rPu-239 + DFAPu-241
• rPu-241 Page 10 of55

TSD-16-007 1 Rev. 0 Eq.2 x = ko

• Q
• x/Q Eq.3 Dose = BR* X
• DFAeff Eq4.

[Isotope activity concentration] = Q I release rate

• unit conversion Eq.5 ECeff(x) = I rCo60i I EC (Attachment 2)

Eq. 5 Expanded: ECeff(x) = rCo-60 I ECCo-60 +rC-14/ ECC-14 +rFe-55/ ECFe-55 +rNi-59/ ECNi-59

        +rNi-63/ ECNi-63 +rSr-90/ ECSr-90 +rTc-99/ ECTc-99 +rNb-94/ ECNb-94 +rSb-125/

ECSb-125 +rCs-137/ ECCs-137 +rAm-241 / ECAm-24 1 +rCm-242/ ECCm-242

        +rCm-243/4/ ECCm-243/4 +rPu-238/ ECPu-238 +rPu-239/ ECPu-239 +rPu-241/

ECPu-241 Eq. 6 ECf = I[uCi/ml of isotope I] I (EC of isotope i at release point) S 1 Eq. 6 Re-written using ECeff: ECf = [Co-60 uCi/ml] I (ECeff) S 1

4.2 Calculations

The premise is to solve the equations for the minimum effluent concentration in uCi/mL that can be released via modular filtered ventilation or that could escape through the openings that would cause there to be dose rates of the various limits. 4.2.1 Solve for Q using equations Eq.l, Eg.2, and Eq.3 Dose = BR* X

• DFAeff Dose I (BR* DFAeff) = x x= ko
• Q
• x/Q Dose I (BR* DFAeff) = ko
• Q
• x/Q Q = Dose/ (BR* DFAeff
• ko
• x/Q)

Page 11of55

TSD-16-0071 Rev. 0 Q(Ci/yr) = Dose (mrem) I { BR(m 3/yr)

• DFAeff(mrem/yr-pCi)
• ko(pCi-yr/Ci-sec)
• x/Q(sec/ m 3) }

Q(uCi/sec) = Q(Ci/yr)

• 3.17E-2 (uCi-yr/Ci-sec) 4.2.2 Substitute Parameters for organ and Tbody dose:

4.2.2.a Adult Tbody Q(uCi/sec) = (3.17E-2(uCi-yr/Ci-sec)

• Dose(mrem) /{ 8000m 3/yr *1.12E-3(mrem/yr-pCi)
• 3. l 7E+4(pCi-yr/Ci-sec)
• 6.59E-4(sec/ m 3)}

I Q(uCi/sec)Adult Tbody =Dose (mrem in 1 year)* 1.70 E-4 (uCi/mrem-sec) 4.2.2.b Teen Bone Q(uCi/sec) = (3.17E-2(uCi-yr/Ci-sec)

• Dose(mrem) /{8000m 3/yr *1.81E-2(mrem/yr-pCi)
• 3.17E+4(pCi-yr/Ci-sec)
• 6.59E-4(sec/m 3)}

I Q(uCi/sec)Teen Bone = Dose (mrem in 1 year)* 1.05 E-5 (uCi/mrem-sec) 4.2.3 Substitute Co-60 concentration using equation Eg.4 and results of 4.2.2.a. and 4.2.2.b. [Co-60] (uCi/mL) = Q(uCi/sec) I (release flowrate(cfm)

• 472 (cc-min/cf-sec))

4.2.3.a Adult Tbody [Co-60](uCi/mL) =(Dose (mrem/yr)* 1.70 E-4 (uCi/mrem-sec)) I (release rate(cfm)

• 4 72( cc-min/cf-sec)

I [Co-60](uCi/mL) =(Dose (mrem/yr)* 3.60E-7 (uCi-cfm/cc-mrem)) I release rate(cfm) 4.2.3.b Teen Bone [Co-60](uCi/mL) =(Dose (mrem/yr)* 1.05 E-5 (uCi/mrem-sec)) I (release rate(cfm)

• 4 72(cc-min/cf-sec) l[Co-60](uCi/mL) =(Dose (mrem/yr)* 2.22E-8 (uCi-cfm/cc-mrem)) I release rate(cfm)

Page 12 of SS

TSD-16-0071 Rev. 0 4.2.4 Find maximum [Co-60](uCi/mL) to maintain ECf < 1 using equation Eg.2, Eq.4 and Eq.6 ECf = [Co-60 (uCi/mL)] I (ECeff) [Co-60(uCi/mL)] = QEceff/ Release rate(cfm) *conversion factor XECeff = ko

• QEceff
• x/Q 3

QEceff = XEceff I x/Q(sec/m )

• conversion factor

[Co-60(uCi/mL)] = XEceff (uCi/mL) I ( x/Q(sec/m3) *release flowrate (cfm))

• conversion factor

[Co-60(uCi/mL)] = l.66E-12 (uCi/mL) I (6.59E-4 (sec/m 3) *release flowrate (cfm)

• 4.72E-4 (m3/cfm-sec))

     ![Co-60 uCi/ml] max for ECf :S 1 = release rate(cfm)

• 5.34E-6 (uCi/mL-cfm)I 5.0 CALCULATION RESULTS Tables 7, 8, and 9 - Substitution of Parameters from Table 1 and Table 6 into Calculation results of 4.2.2.a,b, 4.2.3.a,b and 4.2.4 to find maximum allowable Co-60 concentration at release point to remain under given limits. Periods of time other than 1 year may be calculated as well as different flowrates or desired mrem values by following the notes after the tables.

T abl e 7 - Ad uIt Tb 0 dIV Adult Thody dose vs. Co-60 concentration continuous discharge Dose Limit Q release I release [Co-60] (mrem/year) rate(uCi/sec) flowrate (uCi/mL) (cfm) 1 1.70E-4 1 3.59E-07 30,000 l.20E-11 257,400 l.40E-12 5 8.48E-4 1 1.80E-06 30,000 5.99E-11 257,400 6.98E-12 1.2 2.03E-4 1 4.31E-07 30,000 l.44E-11 257,400 l.67E-12 Page 13 of55

l TSD-16-0071 Rev. 0 Table 8 - Teen Bone Teen Bone dose vs. Co-60 concentration continuous discharge Dose Limit Q release I release [Co-60] (mrem/year) rate(uCi/sec) flowrate (uCi/mL) (cfin) 1 l .05E-5 1 2.22E-08 30,000 7.40E-13 257,400 8.62E-14 15 1.57E-4 1 3.33E-07 30,000 l. llE-11 25 7,400 1.29E-12 3.6 3.77E-5 1 7.99E-08 30,000 2.66E-12 257,400 3.IOE-13 1500 1.57E-2 1 3.33E-05 30,000 l.llE-09 257,400 l.29E-10 Table 9 - ECf < 1 at 400m Co-60 concentration at release point that will give ECf of 1 at 400m Multiplication Release flowrate Max [Co-60] factor (cfm) (uCi/mL) 5.34E-6 1 5.34E-6 (uC/mL-cfm) 30,000 l.78E-10 257,400 2.07E-11 Notes on Tables 7,8 and 9: If it is desired to find a uCi/mL value other than those listed: For a change in cfm: Take the uCi/mL value at 1 cfm and divide this value by the new cfm. Notes on Tables 7,8: I-To determine uCi/mL for a different annual dose, multiply the value listed for 1 mrem by the desired annual dose in mrem. 2-To find a period oftime other than 1 year to reach the annual dose, find the periodicity of the new time frame in 1 year, then multiply the uCi/mL value by that time period. e.g. A proposed situation is that somehow the door to the containment access tent is inadvertently left open over a weekend. What is the max uCi/mL Co-60 concentration of the air blowing out that would not exceed 10% of the 3.6 mrem unfiltered ventilation limit for teen bone dose. Flowrate: 257,400 cfm Periodicity: 365 days/ 3 days= 122 Page 14 of SS

TSD-16-007 1 Rev. 0 Dose: 0.36 mrem uCi/mL Co-60 = 8.62E-14 x 122 x 0.36 mrem = 3.78E-12 uCi/mL Co-60 for 3 days would reach 0.36 mrem. 6.0 COMPARISON of ANALYSIS RESULTS to EMPIRICAL DATA: To analyze the results the effluent release database was queried to find all positive Co-60 activities that have had results greater than LLD and have been reported in the annual radioactive effluent release reports from Oct. 2012 to Oct. 2016. Each year, there were 52 weekly releases from each unit for a total of 416 weekly release reports. The following represents the 4.3% of the effluent samples with >LLD Co-60 values. Table 10 - Continuous release Co-60 >LLD 2012-2016 Effluent Database Query Release ID# Unit Co-60 (uCi/rnL) 2015024 2 1.35E-14 2015070 2 1.12E-13 2015092 2 1.35E-13 2015101 2 1.18E-13 2015083 2 1.3E-13 2016009 1 1.35E-13 2016033 2 9.52E-13 2016036 2 1.38E-12 2016037 2 6.79E-12 2016040 2 6.SlE-13 2016045 1 5.35E-14 2016061 1 1.69E-13 2016062 1 2.lE-13 2016064 2 9.35E-14 2016063 2 7.97E-14 2016069 2 8.5E-14 2016070 1 1.52E-13 2016083 1 3.36E-13 Average ignoring samples <LLD(sum/18) 6.44E-13 Average including samples <LLD (1.35E-14

• 398 +

sum)/416 4.08E-14 6.1 Reviewing the above table, the worst case concentration of Co-60 on the outlet of filtered ventilation was 6. 79E-12 uCi/rnL. This was during a period of time that demolition work was being performed on the chemical drain tank (one of the higher internally contaminated tanks). The RWST, and HUTs have been removed, thus it is not Page 15 of SS

TSD-16-0071 Rev. 0 foreseeable that there would ever be a concentration of Co-60 airborne on the outlet of filtered exhaust to be greater than this value. The highest 3 concentrations of Co-60 are compared to the annual dose limits at 30,000 cfm, if this concentration is to be released for 24 hours a day for a full year. T a bl e 11 - PIC comoansons Maximum possible Fraction of actual releases to annual limits at 30,000 cfm Co-60 (uCi/mL) Adult Tbody Fraction of Teen Bone Fraction of annual limit Tbody limit annual limit Bone limit 6.79E-12 5.99E-ll 0.11 1.1 lE-11 0.612 1.38E-12 0.023 0.12 9.52E-13 0.016 0.086 6.44 E-13( avg. 0.011 0.058 ignoring

            <LLD) 4.08E-14                               0.00068                       0.0037 (absolute average) 6.2 In one instance over the previous 4 years, there was 1 air sample representing 1 week of work where the activity of Co-60 would, if discharged at the value of 6.79E-12 uCi/ml for the entire year, have given an organ dose representing 0.612 of the annual limit. The average value of Co-60 ignoring those values of <LLD would have been at 0.058 of the annual limit for organ dose. Taking it another step and assuming the remaining 398 samples <LLD were at the exact value of 1.35E-14 uCi/mL, the new average would be at maximum level of 0.0037 of the annual limit.

The method that was used to reverse calculate the max concentration of Co-60 from a dose limit at a distance from the site already has heavily conservative factors built in. The first assumption of conservatism was starting with the part 61 data. The worst case ratio to Co-60 from all areas was used instead of an average or weighted value. For example in Attachment 5 and 6, the Spent Fuel Pool I Transfer canal lists Sr-90 ratio to Co-60 as 0, and the Am-241 ratio as 5.24E-3. This ratio to Am-241 was used for all areas of the site in this estimation. Unit 1 sump Sr-90 to Co-60 ratio is 3.36E-3 where Am-241 in this area is 7.95E-4. Obviously if one room is being demolished, only that part 61 would apply, or if both are being demolished at the same time, the actual ratio of these nuclides would be somewhere between the average of both of the values. Averages were not used in creating the ratios, only the absolute maximum. Which creates a strong factor of conservatism as this overestimation is carried forward throughout the effective dose conversion factors and the effective EC fraction calculation. Page 16 of SS

TSD-16-0071 Rev. 0 As decommissioning progresses, the source term will be ever diminishing. The removal of the chemical drain tank for example was responsible for the highest 3 levels of Co-60 of the four year period. Even so, the activity would have had to remain at this level for the entire year to keep Zion Station in PIC category 1.

7.0 CONCLUSION

Based on the results of this TSD, radioactive effluent releases during normal, routine decommissioning activities results in only a small fraction of regulatory limits. These results, in combination with the current bounding accident described in the DSAR, provide the basis for using the effluent sampling requirements described in the PIC 2 category of ANSI Standard ANSI/HPS N13.l-1999. The original design function of the AB Ventilation system was to maintain the AB and FHB at a negative pressure with respect to the atmosphere. This prevented uncontrolled and unmonitored releases ofradioactivity from the buildings. The exhaust of the ventilation system was monitored by radiation monitors 1(2)RIA-PR49 via the isokinetic flow panels 1(2)LP-084; this provided for monitoring of effluents as required by 10CFR20.1304 and alarm capability in the event of an accidental release of radioactivity. The 1(2)LP-084 flow panels provision of isokinetic flow and sampling to radiation monitors 1(2)RIA-PR49 is described in ANSI Standard ANSl/HPS N13.l-1969. The radiation monitors provided for monitoring of gaseous-particulate effluent releases from the site, and alarm capability in the event of increased radiation levels. With the progress of decommissioning, the contamination levels and associated source term have been reduced to the extent that the potential for an unmitigated accidental release of radioactivity that exceeds the 10CFRl00 limits no longer exists. Monitoring of effluents to comply with 10CFR20 will be performed by periodic sampling as described in ANSI Standard ANSI/RPS N 13 .1-1999. The discussion and requirements of the flow panels and radiation monitors as described in the ODCM, Sections 10.1, 10.4, 12.2, Table 12.2-3, Table 12.2-4, and 12.4-1 are no longer required. ANSI Standard ANSI/RPS N 13 .1-1999 provides a graded approach for monitoring radioactive releases from the site. The criteria for the graded approach, defined in each Potential Impact Category (PIC), are based on the amount of radioactivity onsite (i.e. the site source term) compared to the potential release fraction of the allowable limit. Each PIC has sampling methods prescribed in the standard that are based on the amount of radioactivity that could be released (uncontrolled) and what fraction of the allowable limit results from the release. PIC 1, defined by a potential fraction of the allowable limit to be greater than 0.5, uses "Continuous sampling for a record of emissions and in-line, real-time monitoring with alarm capability"; the current configuration of effluent Page 17 of SS

TSD-16-0071 Rev. 0 sampling. PIC 2, defined by a potential fraction of the allowable limit to be greater than 0.01 and less than 0.5 , uses "Continuous sampling for a record of emissions and off-line periodic analysis"; the proposed configuration for effluent sampling. Currently, the bounding accident described in the DSAR is the Radioactive Waste Handling accident; failure of a HIC. This accident results in a projected organ dose of ~0.9 Rem, which is less than the 10CFRl00 limit of 25 Rem and less than 0.5 of the allowable limit. Not having real-time monitoring and alarm capability is justifiable at this point in decommissioning based on the circumstances of this accident; (1) the occurrence of this situation would be immediately recognized and dealt with the personnel moving the HIC or in the case of a natural disaster, and (2) the calculated dose is significantly less than the allowable limit which has been accepted by the staff. In both cases, real-time monitoring with alarm capability does not affect the results of the accidents. The need for continuous sampling for record of emissions still applies with retrospective periodic off-line analysis will meet the needs of the site based on the above considerations. Air samples are to be placed at points where there is a potential release path during active work which could generate airborne radioactivity, the samples analyzed per requirements in the ODCM Ch.12 with the lower limits of detection and composite analysis as described in the ODCM Ch.12. 8.0 AIR SAMPLING AND REPORTING IS REQUIRED PER REGULATORY REQUIREMENTS 8.1 One of the following methods of representative air sampling shall be followed to maintain compliance with effluent monitoring. 8.1.1 Continue operating 1&2RIA-PR49 and associated 1&2LP-084 panels until ventilation is secured. 8.1.2 After normal ventilation flowpath is secured and a portable 30,000 cfm filtered ventilation unit is installed, place an alarming AMS-4 monitor with the filter head directly in the discharge flowpath. The alarm is not for the purpose of protection of public dose, but is an additional feature of this air sampler that may be used if desired for additional indication and set at a level determined for administrative purposes. 8.1.3 Instead of an alarming AMS-4 unit, an air sampler of the same variety used to provide air samples during job coverage work may be used with the sample collection head directly in the effluent flowpath of the discharge from the filtered exhaust unit. The air sample filter from the non-alarming air sampler must be pulled and analyzed daily while work is Page 18 of SS

TSD-16-0071 Rev. 0 in progress. If work is not in progress, there is no normal release situation that would create an increase in airborne levels at decommissioning sites. 8.1.4 As is the case now, all gaseous effluent flow paths must have an air sampler continuously running on the downstream side of the gaseous release point at a location that would result in a representative or conservative sample. If negative ventilation can be maintained via the normal ventilation system, these air samples may be analyzed weekly. If negative ventilation cannot be maintained, these air samples must be collected and analyzed daily while work is in progress. 9.0 DOSE ESTIMATION AND RECORD KEEPING 9.1 The air sample filters and results from the collection and analysis of all of the methods of section V.D.1 above are required to be analyzed per ODCM guidance. The LLD of the analysis is unchanged, the requirement to perform a composite sample analysis once per quarter on collected samples is unchanged. All effluent flow paths must have a dose estimation performed. 9.2 Methods of estimating and reporting dose to the public from gaseous effluents: 9.2.1 Outlet of filtered ventilation. 9.2.1.a Use the maximum possible design flow of the filtered ventilation unit for effluent release rate. (30,000cfrn) 9.2.1.b Use the activity concentration on the filter head for release activity concentration. 9.2.2 Other effluent flow paths. 9.2.2.a Use the actual wind speed from NOAA for the Zion area for wind speed. If this is unavailable use the upper band of the historic average wind speed 12.5 mph. multiplied by area of the doorway over an estimated 4 hours per day of the doors being open. Using this method requires using the correct xJQ at this wind speed thus a x/Q value will need to be calculated and documented with the release package when using wind speed as the driving force for release rate. 9.2.2.b Use the activity concentration from the analysis of the air sample results at each gaseous effluent flowpath. Page 19 of SS

TSD-16-0071 Rev. 0 9.2.2.c Other methods may be used for that can provide means of calculating release rate, such as barometric pressure difference or direct measurement with an anemometer. Any method can be used as long as a reasonable estimation of effluent release flowrate and representative sampling can be achieved.

10.0 REFERENCES

10.1 Zion Station Defueled Safety Analysis Report"DSAR" 10.2 Zion Station Quality Assurance Project Plan "QAPP" 10.3 Zion Station Offsite Dose Calculation Manual "ODCM" 10.4 ANSI NB.1-1999 "Sampling and Monitoring Releases of Airborne Radioactive Substances From the Stacks and Ducts of Nuclear Facilities." 10.5 10CFR20 App. B Table 2 Col. 1 "Effluent concentrations" 10.6 10CFR20.1301 "Dose Limits for Individual Members of the Public."

10. 7 10CFR50 App. I "Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion "As Low As is Reasonably Achievable" for Radioactive Material in Light Water cooled Nuclear Power Reactor Effluents."

10.8 NUREG 0172 "Age Specific Dose Factors 1 year intake" 10.9 LADTAP II computer code spreadsheet based on NUREG 0172 10.10 Regulatory Guide(RG) 1.111 "Gas Release Estimating Transport & Dispersion." 10.11 40CFR190 "Environmental Radiation Protection Standards for Nuclear Power Operations." 10.12 10CFR50.36a "Technical Specifications on Effluents from Nuclear Power Reactors." 10.13 Regulatory Guide 1.109 "Calculation of Annual Doses to Man from routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50 Appendix I." 10.14 10CFR20.1302 "Compliance with Dose Limits for Individual Members of the Public." 10.15 Zion Station ES&H TSD 12-001 10.16 ANL/EAD/TM-53, "Supplemental Analysis ofAccident Sequences and Source Terms for Waste Treatment and Storage Operations and Related Facilities for the US. Department of Energy Waste Manage ment Programmatic Environmental Impact Statement" Page 20 of55

TSD-16-0071 Rev. 0 Attachment 1 Percent Wind Direction by Wind Speed 6-year historic average from MET data Jan. 1, 2009 - Dec. 31, 2014 w*ID d s1peed ID

• mp h Wind <1 1 - 3.5 3.6 - 7.5 7.6 - 12.6 - 18.6 - >24.5 Total:

Directio 12.5 18.5 24.5 n N 0.008 0.617 1.612 2.466 1.773 0.299 0.082 6.86 NNE 0.006 0.525 1.927 3.075 1.251 0.069 0.033 6.89 NE 0.006 0.515 1.587 1.483 0.602 0.066 0.031 4.3 ENE 0.006 0.433 1.178 0.763 0.498 0.118 0.01 3 E 0.005 0.399 1.345 0.615 0.524 0.148 0.021 3.06 ESE 0.004 0.422 1.451 0.669 0.249 0.052 0.002 2.84 SE 0.005 0.402 1.795 1.064 0.262 0.012 0 3.54 SSE 0.006 0.393 1.44 3.38 1.577 0.22 0.073 7.08 s 0.01 0.758 3.285 2.527 0.665 0.023 0 7.27 SSW 0.014 1.301 2.52 1.937 1.328 0.137 0.014 7.26 SW 0.016 1.192 2.158 2.785 1.866 0.172 0.029 8.22 WSW 0.016 1.395 2.846 2.806 1.322 0.087 0.01 8.48 w 0.018 1.511 4.016 3.495 1.773 0.057 0.004 10.86 WNW 0.015 1.2 17 3.41 2.988 0.917 0.02 0 8.56 NW 0.012 0.94 2.856 2.697 0.822 0.021 0 7.36 NNW 0.01 0.635 1.522 1.66 0.556 0.045 0.006 4.42 Total 0.161 12.655 34.944 34.404 15.979 1.545 0.312 100 Page 21 of SS

TSD-16-007 1 Rev. 0 Attachment 2 - EC's and ECeff. ECeff Ratio to Co- rCo60 I Radionuclide 60 EC(uCi/mL) EC C-14 2.62E-02 3.00E-09 8.73E+06 Fe-55 7.64E+Ol 3.00E-09 2.55E+10 Ni-59 2.05E-01 5.00E-09 4.10E+07 Ni-63 1.46E+Ol 2.00E-09 7.31E+09 Sr-90 3.36E-03 6.00E-12 5.60E+08 Tc-99 7.llE-04 9.00E-10 7.90E+05 Co-60 1.00E+OO 5.00E-11 2.00E+lO Nb-94 3.35E-02 2.00E-11 1.68E+09 Sb-125 1.88E-03 7.00E-10 2.68E+06 Cs-137 8.04E+OO 2.00E-10 4.02E+l0 Am-241(1) 5.24E-03 2.00E-14 2.62E+ll Cm-242 2.00E-06 4.00E-13 5.00E+06 Cm-243/244 1.97E-03 2.00E-14 9.87E+l0 Pu-238 1.36E-03 2.00E-14 6.79E+10 Pu-239/240 2.31E-04 2.00E-14 1.15E+l0 Pu-241 5.34E-02 8.00E-13 6.67E+10 Sum: 1/ECeff = 6.02E+ll ECeff (x) = 1.GGE-12 uCi/ml I To find ECeff at point of release: ECeff = ECeff (X) / (cfm x 4.72E-4 x x/Q) Page 22 of SS

TSD-16-0071 Rev. 0 Attachment 3- DFAeff. Adult Weighted inhalation DFA's by rCo60 Radionuclide Ratio to INHALATION DOSE FACTORS X ratio to Co-60 Co-60 Bone Liver TBody Thyroid Kidney Lung GI-LLI C-14 2.62E-02 5.95E-08 l .12E-08 l .12E-08 1.12E-08 1.12E-08 1.12E-08 l .12E-08 FE-55 7.64E+Ol 2.35E-04 l.62E-04 3.77E-05 O.OOE+OO O.OOE+OO 6.88E-04 5.76E-05 C0-60 l.OOE+OO O.OOE+OO l.44E-06 1.85E-06 O.OOE+OO O.OOE+OO 7.46E-04 3.56E-05 NI-59 2.05E-01 8.33E-07 3.00E-07 l .39E-07 O.OOE+OO O.OOE+OO 1.68E-06 1.25E-07 NI-63 l.46E+Ol 7.90E-04 5.75E-05 2.65E-05 O.OOE+OO O.OOE+OO 3.26E-04 2.44E-05 SR-90 3.36E-03 l.21E-05 O.OOE+OO 2.42E-07 O.OOE+OO O.OOE+OO 4.03E-06 3.03E-07 Nb-94 3.35E-02 TC-99 7.1 l E-04 2.22E-11 3.30E-11 8.88E-12 O.OOE+OO 4.16E-10 7.18E-08 5.36E-09 SB-1 25 l.88E-03 1.25E-08 l.40E-10 2.97E-09 l.27E-11 O.OOE+OO 4.IOE-07 2.37E-08 CS-137 8.04E+OO 4.81E-04 6.24E-04 4.30E-04 O.OOE+OO 2.24E-04 7.56E-05 8.45E-06 PU-238 1.36E-03 l.94E-03 l .32E-03 9.37E-05 O.OOE+OO 4.02E-04 2.47E-04 6.14E-08 PU-239/240 2.3 lE-04 3.83E-04 2.47E-04 1.79E-05 O.OOE+OO 7.62E-05 3.97E-05 9.53E-09 PU-241 5.34E-02 1.83E-03 4.64E-04 6.88E-05 O.OOE+OO 3.16E-04 8. l lE-06 4.62E-08 AM-241 5.24E-03 8.80E-03 5.92E-03 3.52E-04 O.OOE+OO 2.64E-03 3.17E-04 2.41 E-07 CM-242 2.00E-06 4.44E-08 3.54E-08 1.97E-09 O.OOE+OO 8.96E-09 7.84E-08 9.82E-11 CM-243/244 1.97E-03 2.17E-03 1.50E-03 9.lOE-05 O.OOE+OO 4.25E-04 1.25E-04 9.56E-08 sum 1.66E-02 l.03E-02 1.12E-03 1.12E-08 4.08E-03 2.58E-03 l.27E-04 BR x DFA= l.33E+02 8.96E+OO mrem-m3/pCi-year BR x DFAeff is the test to determine which age group will give the largest DFAeff after the age group breathing rate is applied. Page 23 of 55

TSD-16-0071 Rev. 0 Attachment 3

                                                      - DFAeff. - continued Teen Weighted inhalation DFA's by rCo60 Radionuclide    Ratio to                   INHALATION DOSE FACTORS X ratio to Co-60 Co-60      Bone       Liver      TBody       Thyroid      Kidney    Lung         GI-LLI C-14           2.62E-02     8.52E-08   1.60E-08 1.60E-08 1.60E-08 1.60E-08 1.60E-08               l .60E-08 FE-55         7.64E+Ol      3.19E-04   2.28E-04 5.30E-05 O.OOE+OO O.OOE+OO 1.18E-03               6.llE-05 C0-60         1.00E+OO      O.OOE+OO   1.89E-06 2.48E-06 O.OOE+OO O.OOE+OO l.09E-03               3.24E-05 NI-59          2.05E-01     l .12E-06  4.15E-07 1.90E-07 O.OOE+OO O.OOE+OO 2.89E-06               1.33E-07 NI-63         1.46E+Ol      1.06E-03   7.94E-05 3.61E-05 O.OOE+OO O.OOE+OO 5.62E-04               2.59E-05 SR-90          3.36E-03     1.39E-05   O.OOE+OO 2.80E-07 O.OOE+OO O.OOE+OO 6.93E-06               3.21E-07 Nb-94         3.35E-02 TC-99          7.1 lE-04    3.18E-11   4.68E-11   l.27E-11    O.OOE+OO 5.93E-10      l .24E-07    5.68E-09 SB-125         1.88E-03     l.73E-08   l.90E-10   4.04E-09    l.65E-11 O.OOE+OO      6.42E-07     2.33E-08 CS-137        8.04E+OO      6.74E-04   8.53E-04   3.13E-04    O.OOE+OO 3.06E-04      l.21E-04     8.53E-06 PU-238         1.36E-03     2.04E-03   1.40E-03   9.81E-05    O.OOE+OO 4.21E-04      4.24E-04     6.51E-08 PU-239        2.3 lE-04     3.99E-04   2.59E-04   l.86E-05    O.OOE+OO 7.94E-05      6.76E-05     l.OlE-08 PU-241        5.34E-02      2.00E-03   5.lOE-04   7.47E-05    O.OOE+OO 3.45E-04      1.39E-05     4.89E-08 AM-241        5.24E-03      9.27E-03   6.29E-03   3.72E-04    O.OOE+OO 2.79E-03      5.50E-04     2.56E-07 CM-242        2.00E-06      6.34E-08   5.02E-08   2.82E-09    O.OOE+OO l.28E-08      1.35E-07     1.04E-10 CM-243         l .97E-03    2.35E-03   1.64E-03   9.87E-05    O.OOE+OO 4.62E-04      2.15E-04     l.OlE-07 sum                         1.81E-02   l.13E-02   1.07E-03    1.60E-08 4.40E-03      4.24E-03     1.29E-04 BRXDFA                      1.45E+02              8.54E+OO    mrem-m3/pCi-year BR x DFAeff is the test to determine which age group will give the largest DFAeff after the age group breathing rate is applied.

Page 24 of SS

TSD-16-007 1 Rev. 0 Attachment 3- DFAeff. - continued Child Weighted inhalation DFA's by rCo60 Radionuclide Ratio to INHALATION DOSE FACTORS X ratio to Co-60 Co-60 Bone Liver TBody Thyroid Kidney Lung GI-LLI C-14 2.62E-02 2.54E-07 4.77E-08 4.77E-08 4.77E-08 4.77E-08 4.77E-08 4.77E-08 FE-55 7.64E+Ol 9.78E-04 5.20E-04 1.60E-04 O.OOE+OO O.OOE+OO 2.29E-03 5.92E-05 C0-60 1.00E+OO O.OOE+OO 3.55E-06 6.12E-06 O.OOE+OO O.OOE+OO 1.91E-03 2.60E-05 NI-59 2.05E-01 3.41E-06 9.58E-07 5.81E-07 O.OOE+OO O.OOE+OO 5.60E-06 l.29E-07 NI-63 1.46E+Ol 3.25E-03 1.83E-04 1.1 lE-04 O.OOE+OO O.OOE+OO l.09E-03 2.50E-05 SR-90 3.36E-03 3.50E-05 O.OOE+OO 6.96E-07 O.OOE+OO O.OOE+OO 1.34E-05 3.12E-07 Nb-94 3.35E-02 TC-99 7.1 lE-04 9.52E-11 1.06E-10 3.80E-11 O.OOE+OO l .24E-09 2.39E-07 5.51E-09 SB-125 1.88E-03 5.00E-08 3.85E-10 l .05E-08 4.62E-11 O.OOE+OO l .18E-06 2.05E-08 CS-137 8.04E+OO 1.97E-03 l.79E-03 2.79E-04 O.OOE+OO 6.14E-04 2.26E-04 7.87E-06 PU-238 1.36E-03 3.46E-03 2.17E-03 1.64E-04 O.OOE+OO 6.07E-04 8.26E-04 6.32E-08 PU-239 2.3 lE-04 6.44E-04 3.88E-04 2.95E-05 O.OOE+OO 1.1 OE-04 l.32E-04 9.79E-09 PU-241 5.34E-02 4.24E-03 9.34E-04 1.56E-04 O.OOE+OO 5.87E-04 2.70E-05 4.75E-08 AM-241 5.24E-03 l.56E-02 9.64E-03 6.50E-04 O.OOE+OO 4.00E-03 l .06E-03 2.48E-07 CM-242 2.00E-06 l.90E-07 1.14E-07 8.40E-09 O.OOE+OO 2.68E-08 2.62E-07 1.0lE-10 CM-243 1.97E-03 4.58E-03 2.80E-03 l .96E-04 O.OOE+OO 7.39E-04 4.15E-04 9.83E-08 sum 3.47E-02 l.84E-02 1.75E-03 4.77E-08 6.65E-03 7.99E-03 l .19E-04 BRXDFA l.28E+02 6.49E+OO mrem-m3/pCi-year BR x DFAeff is the test to determine which age group will give t e largest DFAeff after the age group breathing rate is applied. Page 25 of 55

TSD-16-0071 Rev. 0 Attachment 3- DFAeff. - continued Infant Weighted inhalation DFA's by rCo60 Radionuclide Ratio to INHALATION DOSE FACTORS X ratio to Co-60 Co-60 Bone Liver TBody Thyroid Kidney Lung GI-LLI C-14 2.62E-02 4.95E-07 9.93E-08 9.93E-08 9.93E-08 9.93E-08 9.93E-08 9.93E-08 FE-55 7.64E+Ol 1.08E-03 6.41E-04 1.82E-04 O.OOE+OO 0.00E+OO 4.75E-03 5.98E-05 C0-60 l.OOE+OO O.OOE+OO 5.73E-06 8.41E-06 O.OOE+OO O.OOE+OO 3.22E-03 2.28E-05 NI-59 2.05E-01 3.71E-06 1.12E-06 6.36E-07 0.00E+OO O.OOE+OO 1.12E-05 1.30E-07 NI-63 1.46E+Ol 3.54E-03 2.14E-04 1.21E-04 O.OOE+OO O.OOE+OO 2.18E-03 2.53E-05 SR-90 3.36E-03 3.73E-05 0.00E+OO 7.SOE-07 O.OOE+OO 0.00E+OO 2.70E-05 3.lSE-07 Nb-94 3.35E-02 TC-99 7.1 lE-04 1.49E-10 1.90E-10 6.29E-11 O.OOE+OO 1.77E-09 4.81E-07 5.56E-09 SB-125 1.88E-03 6.93E-08 6.41E-10 1.46E-08 8.36E-11 O.OOE+OO 2.20E-06 1.97E-08 CS-137 8.04E+OO 3.lSE-03 3.52E-03 2.61E-04 0.00E+OO 9.89E-04 4.09E-04 7.67E-06 PU-238 1.36E-03 3.65E-03 2.28E-03 1.73E-04 O.OOE+OO 6.30E-04 1.23E-03 6.37E-08 PU-239 2.31E-04 6.76E-04 4.06E-04 3.09E-05 O.OOE+OO 1.14E-04 1.95E-04 9.88E-09 PU-241 5.34E-02 4.SOE-03 9.87E-04 l.66E-04 O.OOE+OO 6.14E-04 4.07E-05 4 .79E-08 AM-241 5.24E-03 1.65E-02 1.02E-02 6.86E-04 O.OOE+OO 4.16E-03 2.13E-03 2.SOE-07 CM-242 2.00E-06 2.56E-07 1.73E-07 l.14E-08 O.OOE+OO 3.38E-08 5.94E-07 1.02E-10 CM-243 l.97E-03 4.88E-03 3.00E-03 2.09E-04 0.00E+OO 7.72E-04 8.37E-04 9.91E-08 sum 3.BOE-02 2.13E-02 1.84E-03 9.94E-08 7.28E-03 1.SOE-02 1.17E-04 BRXDFA 5.32E+Ol 2.58E+OO mrem-m3/pCi-year BR x DFAeff is the test to determine which age group will give the largest DFAeff after the age group breathing rate is applied. Page 26 of SS _j

TSD-16-0071 Rev. 0 Attachment 4 Inhalation Dose Factor DFA's by age group from NUREG 0172/LADTAP II computer code inputs ADULT INHALATION DOSE FACTORS Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 FE-55 3.07E-06 2.12E-06 4.93E-07 O.OOE+OO O.OOE+OO 9.0lE-06 7.54E-07 C0-60 O.OOE+OO 1.44E-06 1.85E-06 O.OOE+OO O.OOE+OO 7.46E-04 3.56E-05 NI-59 4.06E-06 1.46E-06 6.77E-07 O.OOE+OO O.OOE+OO 8.20E-06 6.l lE-07 NI-63 5.40E-05 3.93E-06 1.81E-06 O.OOE+OO O.OOE+OO 2.23E-05 1.67E-06 SR-90 3.59E-03 O.OOE+OO 7.21E-05 O.OOE+OO O.OOE+OO l.20E-03 9.02E-05 Nb-94 TC-99 3.13E-08 4.64E-08 l.25E-08 O.OOE+OO 5.85E-07 1.0lE-04 7.54E-06 SB-125 6.67E-06 7.44E-08 l.58E-06 6.75E-09 O.OOE+OO 2.18E-04 1.26E-05 CS-137 5.98E-05 7.76E-05 5.35E-05 O.OOE+OO 2.78E-05 9.40E-06 1.05E-06 PU-238 1.43E+OO 9.71E-01 6.90E-02 O.OOE+OO 2.96E-01 1.82E-01 4.52E-05 PU-239/240 1.66E+OO 1.07E+OO 7.75E-02 O.OOE+OO 3.30E-01 1.72E-01 4.13E-05 PU-241 3.42E-02 8.69E-03 1.29E-03 O.OOE+OO 5.93E-03 1.52E-04 8.65E-07 AM-241 1.68E+OO l.13E+OO 6.71E-02 O.OOE+OO 5.04E-01 6.06E-02 4.60E-05 CM-242 2.22E-02 l.77E-02 9.84E-04 O.OOE+OO 4.48E-03 3.92E-02 4.91E-05 CM-243/244 1.lOE+OO 7.61E-01 4.61E-02 O.OOE+OO 2.15E-01 6.31E-02 4.84E-05 Units: mrem/pCi inhaled. Dose is the sum of mrem for 50 year time period, assigned the first year after inhalation. Page 27 of SS

TSD-16-0071 Rev. 0 Attachment 4 - continued Inhalation Dose Factor DFA's by age group from NUREG 0172/LADTAP II computer code inputs TEEN INHALATION DOSE FACTORS Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 FE-55 4.18E-06 2.98E-06 6.93E-07 O.OOE+OO O.OOE+OO 1.55E-05 7.99E-07 C0-60 O.OOE+OO l .89E-06 2.48E-06 O.OOE+OO O.OOE+OO 1.09E-03 3.24E-05 NI-59 5.44E-06 2.02E-06 9.24E-07 O.OOE+OO O.OOE+OO 1.41E-05 6.48E-07 NI-63 7.25E-05 5.43E-06 2.47E-06 O.OOE+OO O.OOE+OO 3.84E-05 1.77E-06 SR-90 4.14E-03 O.OOE+OO 8.33E-05 O.OOE+OO O.OOE+OO 2.06E-03 9.56E-05 Nb-94 TC-99 4.48E-08 6.58E-08 1.79E-08 O.OOE+OO 8.35E-07 1.74E-04 7.99E-06 SB-125 9.23E-06 1.0lE-07 2.15E-06 8.80E-09 O.OOE+OO 3.42E-04 1.24E-05 CS-137 8.38E-05 1.06E-04 3.89E-05 O.OOE+OO 3.80E-05 1.51E-05 l .06E-06 PU-238 1.50E+OO 1.03E+OO 7.22E-02 O.OOE+OO 3.IOE-01 3.12E-01 4.79E-05 PU-239 1.73E+OO 1.12E+OO 8.05E-02 O.OOE+OO 3.44E-01 2.93E-01 4.37E-05 PU-241 3.74E-02 9.56E-03 1.40E-03 O.OOE+OO 6.47E-03 2.60E-04 9.17E-07 AM-241 l .77E+OO 1.20E+OO 7.lOE-02 O.OOE+OO 5.32E-01 l .05E-01 4.88E-05 CM-242 3.l 7E-02 2.51E-02 1.41E-03 O.OOE+OO 6.40E-03 6.76E-02 5.21E-05 CM-243 l.19E+OO 8.30E-01 5.00E-02 O.OOE+OO 2.34E-01 1.09E-01 5.13E-05 Units: mrem/pCi inhaled. Dose is the sum of mrem for 50 year time period, assigned the first year after inhalation. Page 28 of SS

TSD-16-0071 Rev. 0 Attachment 4 - continued Inhalation Dose Factor DFA's by age group from NUREG 0172/LADT AP II computer code inputs CHILD INHALATION DOSE FACTOR Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI C-14 9.70E-06 l .82E-06 l .82E-06 l.82E-06 1.82E-06 1.82E-06 1.82E-06 FE-55 1.28E-05 6.80E-06 2.lOE-06 O.OOE+OO O.OOE+OO 3.00E-05 7.75E-07 C0-60 O.OOE+OO 3.55E-06 6.12E-06 O.OOE+OO O.OOE+OO l.91E-03 2.60E-05 NI-59 1.66E-05 4.67E-06 2.83E-06 O.OOE+OO O.OOE+OO 2.73E-05 6.29E-07 NI-63 2.22E-04 l.25E-05 7.56E-06 O.OOE+OO O.OOE+OO 7.43E-05 l.71E-06 SR-90 l.04E-02 O.OOE+OO 2.07E-04 O.OOE+OO O.OOE+OO 3.99E-03 9.28E-05 Nb-94 TC-99 1.34E-07 1.49E-07 5.35E-08 O.OOE+OO l.75E-06 3.37E-04 7.75E-06 SB-125 2.66E-05 2.0SE-07 5.59E-06 2.46E-08 O.OOE+OO 6.27E-04 l.09E-05 CS-137 2.45E-04 2.23E-04 3.47E-05 O.OOE+OO 7.63E-05 2.81E-05 9.78E-07 PU-238 2.55E+OO l.60E+OO 1.21E-01 O.OOE+OO 4.47E-Ol 6.08E-01 4.65E-05 PU-239 2.79E+OO l.68E+OO 1.28E-01 O.OOE+OO 4.78E-01 5.72E-01 4.24E-05 PU-241 7.94E-02 1.75E-02 2.93E-03 O.OOE+OO l.lOE-02 5.06E-04 8.90E-07 AM-241 2.97E+OO 1.84E+OO l.24E-01 O.OOE+OO 7.63E-01 2.02E-01 4.73E-05 CM-242 9.48E-02 5.68E-02 4.20E-03 O.OOE+OO 1.34E-02 1.3 lE-01 5.06E-05 CM-243 2.32E+OO 1.42E+OO 9.95E-02 O.OOE+OO 3.74E-01 2.lOE-01 4.98E-05 Units: mrem/pCi inhaled. Dose is the sum of mrem for 50 year time period, assigned the first year after inhalation. Page 29 of SS

TSD-16-0071 Rev.O Attachment 4 - continued Inhalation Dose Factor DFA's by age group from NUREG 0172/LADTAP II computer code inputs INFANT INHALATION DOSE FACTORS Nuclide Bone Liver TBody Thyroid Kidney Lung GI-LLI C-14 l .89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 FE-55 l.41E-05 8.39E-06 2.38E-06 O.OOE+OO O.OOE+OO 6.21E-05 7.82E-07 C0-60 O.OOE+OO 5.73E-06 8.4 lE-06 O.OOE+OO O.OOE+OO 3.22E-03 2.28E-05 NI-59 l.81E-05 5.44E-06 3.lOE-06 O.OOE+OO O.OOE+OO 5.48E-05 6.34E-07 NI-63 2.42E-04 1.46E-05 8.29E-06 O.OOE+OO O.OOE+OO 1.49E-04 l.73E-06 SR-90 1.llE-02 O.OOE+OO 2.23E-04 O.OOE+OO O.OOE+OO 8.03E-03 9.36E-05 Nb-94 TC-99 2.09E-07 2.68E-07 8.85E-08 O.OOE+OO 2.49E-06 6.77E-04 7.82E-06 SB-125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 O.OOE+OO l .17E-03 l .05E-05 CS-137 3.92E-04 4.37E-04 3.25E-05 O.OOE+OO l.23E-04 5.09E-05 9.53E-07 PU-238 2.69E+OO l.68E+OO 1.27E-01 O.OOE+OO 4.64E-01 9.03E-01 4.69E-05 PU-239 2.93E+OO l.76E+OO l.34E-01 O.OOE+OO 4.95E-01 8.47E-01 4.28E-05 PU-241 8.43E-02 l.85E-02 3.llE-03 O.OOE+OO l.15E-02 7.62E-04 8.97E-07 AM-241 3.15E+OO l.95E+OO l.3 lE-01 O.OOE+OO 7.94E-01 4.06E-01 4.78E-05 CM-242 1.28E-01 8.65E-02 5.70E-03 O.OOE+OO l.69E-02 2.97E-01 5.1 OE-05 CM-243 2.47E+OO l.52E+OO l .06E-01 O.OOE+OO 3.91E-01 4.24E-01 5.02E-05 Units: mrem/pCi inhaled. Dose is the sum of mrem for 50 year time period, assigned the first year after inhalation. Page 30 of SS

TSD-16-0071 Rev.0 Attachment S M ax ra f10 of sea Ied 1.so t opes t o Co-60 base d on part61 daat U-2 Steam Generator SFP Transfer Canal 4/17/201 10/16/2015 111/2018 5 1/1/2018 Radionuclid Half-Life Activity Activity ratio to Activity Activity ratio to e (yrs) Cone. Cone. Co-60 Cone. Cone. Co-60 C-14 5.72E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.l lE-04 2.l lE-04 2.62E-02 Fe-55 2.75 8.49E-03 4.86E-03 9.41E-03 O.OOE+OO O.OOE+OO O.OOE+OO Ni-59 7.60E+04 l .06E-01 l.06E-01 2.0SE-01 O.OOE+OO O.OOE+OO O.OOE+OO Ni-63 101 7.67E+OO 7.55E+OO 1.46E+Ol 3.38E-02 3.32E-02 4.12E+OO Sr-90 28 .8 4.12E-04 3.91E-04 7.56E-04 O.OOE+OO O.OOE+OO O.OOE+OO Tc-99 2.13E+05 3.67E-04 3.67E-04 7.llE-04 O.OOE+OO O.OOE+OO O.OOE+OO Co-60 5.271 6.91E-01 5.16E-01 l.OOE+OO 1.15E-02 8.05E-03 l.OOE+OO Nb-94 2.00E+04 O.OOE+OO O.OOE+OO O.OOE+OO 2.70E-04 2.70E-04 3.3SE-02 Sb-125 2.758 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-137 30.07 O.OOE+OO O.OOE+OO O.OOE+OO 5.79E-03 5.44E-03 6.76E-01 Arn-241(1) 432.7 1.09E-03 1. lOE-03 2.13E-03 4.14E-05 4.22E-05 S.24E-03 Cm-242 0.446 O.OOE+OO O.OOE+OO O.OOE+OO l.09E-06 l.61E-08 2.00E-06 Cm-243/244 7.37E+03 2.51E-04 2.51E-04 4.86E-04 l.59E-05 1.59E-05 1.97E-03 Pu-238 87.7 8.58E-05 8.43E-05 1.63E-04 4.05E-06 3.96E-06 4.92E-04 Pu-239/240 2.41E+04 4.03E-05 4.03E-05 7.80E-05 O.OOE+OO O.OOE+OO O.OOE+OO Pu-241 14.29 4.77E-03 4.28E-03 8.30E-03 2.84E-04 2.49E-04 3.09E-02 Arn-241 ingrowth 1.60E-05 9.53E-07 Arn-241 decayed l .09E-03 4.12E-05 Ad(t) = Ap(O) *(Ad I (Ad - Ap) * (exp(-Apt) - exp(-Adt) + Ad(o)exp(-Adt) Ad= AAm-241 = l .60E-03 I year Ap = APu-241 = 4.85E-02 I year Page 31 of SS

TSD-16-0071 Rev. 0 Attachment 5 Continued U-2 Containment 568' Sump U-1 Containment 568' Sump U-1 S/G Tube Sheet 4/17/2015 1/1/2018 4117/2015 111/2018 4/17/2015 1/1/2018 Activity Activity ratio to Activity Activity ratio to Activity Activity ratio to Radionuclide Cone. Cone. Co-61 Cone. Cone. Co-60 Cone. Cone. Co-60 C-14 2.03E-04 2.03E-04 2.lOE-03 2.30E-04 2.30E-04 l.62E-02 1.44E-04 l.44E-04 l.79E-04 Fe-55 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 8.61E-03 4.35E-03 5.40E-03 Ni-59 l.14E-03 1.14E-03 l .18E-02 O.OOE+OO O.OOE+OO O.OOE+OO 9.21E-04 9.21E-04 1.14E-03 Ni-63 7.85E-02 7.71E-02 7.98E-01 1.22E-02 l.20E-02 8.43E-01 4.38E-02 4.30E-02 5.34E-02 Sr-90 1.73E-04 l.62E-04 l .68E-03 5.lOE-05 4.78E-05 3.36E-03 O.OOE+OO O.OOE+OO O.OOE+OO Tc-99 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-60 l.38E-01 9.66E-02 l.OOE+OO 2.03E-02 1.42E-02 1.00E+OO l.15E+OO 8.05E-01 1.00E+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-125 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-137 9.57E-03 8.99E-03 9.31E-02 7.66E-02 7.20E-02 5.06E+OO l.32E-03 l.24E-03 1.54E-03 Am-241(1) 4.85E-05 4.96E-05 5.13E-04 1.08E-05 l.13E-05 7.95E-04 3.34E-04 3.35E-04 4.17E-04 Cm-242 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.40E-06 2.07E-08 2.57E-08 Cm-243/244 9.63E-06 9.63E-06 9.97E-05 l .79E-06 l.79E-06 1.26E-04 7.50E-05 7.50E-05 9.3 lE-05 Pu-238 3.19E-05 3.12E-05 3.23E-04 3.90E-06 3.82E-06 2.69E-04 l.16E-04 l.14E-04 1.41E-04 Pu-239/240 2.07E-05 2.07E-05 2.14E-04 3.28E-06 3.28E-06 2.31E-04 9.42E-05 9.42E-05 1.17E-04 Pu-241 3.82E-04 3.35E-04 3.47E-03 l.64E-04 l.44E-04 l.OlE-02 8.25E-04 7.23E-04 8.99E-04 Am-241 ingrowth l .28E-06 5.50E-07 2.77E-06 Am-241 decayed 4.83E-05 l .08E-05 3.33E-04 Page 32 of SS

TSD-16-007 1 Rev. 0 Attachment 5 Continued SFP Bathtub ring U-1 Containment Cavity U-2 Reactor Vessel 4/17/2015 1/1 /2018 4/17/2015 1/1/2018 4/17/2015 1/1 /2018 Activity Activity ratio to Activity Activity ratio to Activity Activity ratio to Radionuclide Cone. Cone. Co-60 Cone. Cone. Co-60 Cone. Cone. Co-60 C-14 8.27E-05 8.27E-05 4.03E-03 2.29E-04 2.29E-04 3.72E-03 O.OOE+OO O.OOE+OO O.OOE+OO Fe-55 O.OOE+OO O.OOE+OO O.OOE+OO 2.24E-02 l.13E-02 l.84E-01 8.71E-03 4.40E-03 4.19E-03 Ni-59 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.63E-02 l.63E-02 1.55E-02 Ni-63 3.76E-02 3.69E-02 1.80E+OO 3.36E-02 3.30E-02 5.37E-01 1.42E+OO l.39E+OO l.33E+OO Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.65E-04 1.55E-04 l.47E-04 Tc-99 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.67E-04 5.67E-04 5.40E-04 Co-60 2.93E-02 2.05E-02 1.00E+OO 8.78E-02 6.15E-02 l.OOE+OO l.50E+OO 1.05E+OO 1.00E+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.60E-03 5.60E-03 5.33E-03 Sb-125 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.90E-03 l.97E-03 1.88E-03 Cs-137 2.92E-03 2.74E-03 l.34E-01 6.85E-04 6.43E-04 l.05E-02 O.OOE+OO O.OOE+OO O.OOE+OO Am-241(1) 2.37E-05 2.43E-05 1.18E-03 4.81E-05 4.91E-05 7.99E-04 l .3 lE-03 l.3 lE-03 l .25E-03 Cm-242 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.09E-06 4.56E-08 4.3 5E-08 Cm-243/244 9.60E-06 9.60E-06 4.68E-04 l.09E-05 l.09E-05 1.77E-04 3.05E-04 3.05E-04 2.90E-04 Pu-238 5.58E-06 5.46E-06 2.66E-04 2.19E-05 2.14E-05 3.49E-04 3.92E-04 3.84E-04 3.65E-04 Pu-239/240 2.39E-06 2.39E-06 l .17E-04 l.12E-O ~ 1.12E-05 l .82E-04 2.04E-04 2.04E-04 l.94E-04 Pu-241 l.99E-04 l.74E-04 8.51E-03 3.68E-04 3.23E-04 5.25E-03 l.71E-03 l.50E-03 l.43 E-03 Am-241 ingrowth 6.68E-07 l .24E-06 5.74E-06 Am-241 decayed 2.36E-05 4.79E-05 l.30E-03 Page 33 of55

TSD-16-0071 Rev. 0 Attachment 5 Continued Auxilliary Building 4/17/2015 111/2018 Max ratio to Activity ratio to Co-60 on Radionuclide Activity Cone. Cone. Co-61 Radionuclide 1/1/2018 C-14 O.OOE+OO O.OOE+OO O.OOE+OO C-14 2.62E-02 Fe-55 3.73E-01 l.88E-01 7.64E+Ol Fe-55 7.64E+Ol Ni-59 O.OOE+OO O.OOE+OO O.OOE+OO Ni-59 2.0SE-01 Ni-63 5.88E-03 5.77E-03 2.34E+OO Ni-63 1.46E+Ol Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO Sr-90 3.36E-03 Tc-99 O.OOE+OO O.OOE+OO O.OOE+OO Tc-99 7.llE-04 Co-60 3.52E-03 2.46E-03 l.OOE+OO Co-60 1.00E+OO Nb-94 O.OOE+OO O.OOE+OO O.OOE+OO Nb-94 3.35E-02 Sb-125 O.OOE+OO O.OOE+OO O.OOE+OO Sb-125 1.88E-03 Cs-137 2.1lE-02 l.98E-02 8.04E+OO Cs-137 8.04E+OO Am-241(1) 3.30E-06 3.79E-06 l.54E-03 Am-241(1) 5.24E-03 Cm-242 O.OOE+OO O.OOE+OO O.OOE+OO Cm-242 2.00E-06 Cm-243/244 9.84E-07 9.84E-07 3.99E-04 Cm-243/244 1.97E-03 Pu-238 3.42E-06 3.35E-06 1.36E-03 Pu-238 1.36E-03 Pu-239/240 O.OOE+OO O.OOE+OO O.OOE+OO Pu-239/240 2.31E-04 Pu-241 l .50E-04 l.32E-04 5.34E-02 Pu-241 5.34E-02 Am-241 ingrowth 5.03E-07 (1) Am-241 includes ingrowth Am-241 decayed 3.29E-06 Page 34 of55

TSD-16-007 Rev.O Attachment 6- Part 61 smear data fi;i TtLEDYNE BROWN ENGi EERINS, INC.

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SOU#: Thill is tO cc.rtify 1hat Teledyne Brown Eogi.ocering - Environmental Servite3 loca:ted at 250 Qlllllity Lane, Knoxville, Tennessee, 37931, has 8Dl:llyzed, tested and documented SllIIlples, as received by the laboratoty, as specified in the applicable purchase order. This also certifies that requirements of applicable codes, standards and specifications have been fully met and that ony quality assurance documentation which verified confurmanoe to the purchase order is on file and may be c:x.amined upon request. I hereby certify that the above statt:marts are true 8Jld correct o.....r ~** 1ahk ClilmtID Labclnlo:y ID Stallon lD If llcable SPP TMNSFBR CANAL .I.62439-1 4584 Ul561SUMP 439- 45119 Ul ~ 1.62439-3 4Slll Ul SG 11JBB SHBBT L62439-4 4'90 SPPBTJUNG 1.6:2439-S 4S8S UI CTMT CAVITY 1.62439-6 I IJ2 RX VBSsBL .62439-7 4SB7 AUXBl.DO l.6243~ 459'.2 l'llgc 1 or 1s Part 61 Data Page 35 of SS

TSD-1 6-0071 Rev. 0 TELEDYNE BROW ENGJNEERING, I C.

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Report of Analysis .-.a..- TEl.EDYICE 04/17/lS l4:34 BROWN ENGINEERING, INC.

                                                                                                                                                                                                                  ,.,......... lMi>""v'n C..,.*

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                                                      -:U7B-OS l.6S}:,.()4 J.47ll-04 2.64B-04

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                                                                                       '50lt-04 uCifroCal uCiftQQI 100 UlO        "'~    03/10/15 00:00 03/1OfU00:00 l})/31/1 5 0313UU 3600 3600 Sa; Soc            u No No I

1U.' I0.3 0 2007 6.14.8-0S l.2iPA4 2.UE-04 uCi/TotQI 100  % 03/1 Of!S 00:00 03/3111l 3600 S<< u No RU*Hltl 2007 4.04.&-04 2. ISE-02 5:.filE-03 1Cil'fOlal 100  % 03/10,'15 00;1)() 0313Ul5 .3600 Sec u No ACJ..JOSM 2007 S.33&-0S l.l0!W4 lJllE-04 uCiffotal 100  % OJllO/l.S 00:00 031'31115 J(,00 Sec u No AG*llOM 2007 l.31E-04 .L_!..24F:-04 l.88.E-4M ll\;lffotsi 100  % 0311Q,'JS00;00 03/3lll5J 3600 ~ u No Rae ValUC11 u Campound/Ali8'}'Z notddod.id (-< MDC)..- lccl tltu 3 Jllpna ~ - PC i!Cl(id<<oflli""' 111 pwtllllfpoelnmi ..:.

        +

u* FfQll! r Mtitity~ ~MDC md 3 sigma; pnt~ ottl1)

                      ~Alilllttc !!DI ~ Poak Ill'! illcntifiod, 11111. farced 1C!tvitJ COl\CIOlll!"llJQn C(cral.~Y.PC arul J ~a Y* n PM identi:fie--l Acd;-ijy OClla:llln!licm '"""""" cmtomcr n:pxting vlhic                                                                                                                                                                           ~*~

sroe MDC ~ccada cmtncncr1eclmicol rpeclficltion lrO n':h~ mly Ill) 01<! JU:!!f.JCC .t imd in Ille -ditiCll !b.."7 C/l L ~ IAor reoowry .... ~bylbchbn!ay.  ! t:J i*t: H - Hlgh n:ccJl'tty I Boldtd tut mtllcatet reportablcnl..,_ MOC - Minlmmn IJalodal)lc o...:arttalion ""*_, i';:l .... 1'11g1: 11 otlll ~ 9" 0 0 0 -..J

    ~-             *' .,

Report of Analysis ....,.... TtU:DYNE 04IJ7/lS 14:34 BROWN '61 EERING, I C. llT~Ttcittoloalo< ~ L62439 ZicnSohmon Steve Ritt BN010-3l'61ZION*10 SmapleID: SJ!1' BT RING CollectSt= 03flOllO IS 00:00 Malth: SwlJW!" (SW) SUltioc.: 4:535 Coll<l:t SlXlp: Volmrn::

Description:

Recd're Da:: 03/18/'lOIS  % Mol.!tmc: LIMS Number: Ui2439-1 Adtrity U11ccrtal1fy Ali9u t Aliqu.ot Ref~nnce Co1111t l

                                                                                                                               .Ihm                                                Count         Coaat Rl.dloll11cllde                      SOP#             Cone          1 Slgnn             MDC                 Uni a            #     Volwne    Ua!U             Dm               om           rune      Uali.,           FJ-cVlllu..
  '>'N-lU                                ioo7         9.2'11HJ6          l.ll.E-04      U4&-04              UCVI'otal                    100         %    0311 OllHO:OO          03131115,       3600        Sec       u                   No           ... .,

2007 uCifl'~  ; 3600 u

  'm-124

[ ~12S 2007

                                                     -S.421',-06         8S1E*OS 234FA4 UJ:&-04                                         100 100       ",,,  OJ/I Oils 00:00        0313 lflS 3600     sec Sec u

No !

                                                     -1.JlB-04
                                                                                                                                                     "                          03131/1.5j 3.'T4T.-04          u(,'lfr.rtaj                                  03/lOflS l)():<l(I                                                               No rE-125M                               2007        -7.05R-0)           l.8()£..()2    l..3SUll            uCifn>lal       '            100              03/HlllS 00:00        03131/U          3600        Sec       u                   No 20()7                                                                                                            Olf I Of! S 00:00     0313Vl           J600   I See       u                  No I 1-131 JCS~

1:;.c;...137 2007 l.29E-<M

                                                     -Ll7E-O~

ol.741!-<M JAlll',..{14

                                                                                        ?A!E-M 1391:-N uCifr o!al uCi/IOW oCVTolal I            100 JOO
                                                                                                                                         ]()0
                                                                                                                                                     %    03/l(){ISOO:OO      I 03/3lll.S        3600        Sec       u                   No Yes
                                                                                                                                                                                                                                                ~

I 2007 j l.9U-OJ 2..Sm-04 1.9ZE.().4 I  % 0311 IYI' 00:00 03/3111' 3500 Sc:c + liM-1-10 I 2007 -9.j6R.().t 1.05.&-0J t.64l'..o3 uC"VTo:al 100  % Olll 0115 00:00 03131/U 3600 Sec u No LA* HO 2007 3.21\E-06 l.06Jl.04 J.79Ul4 oCllThUtl too  % UJ/ l ()'JS 00:00 0313l/1S ]600 Soc ti No CFA4! 2007 4.42E-05 I.llE--01 2.UL-04 uOfl'ottl 100  % 03flOflS 00:00 03/31/JS 3600 Soc u No CE-144 2007 1.71£-06 l. 7(,E.-04 6.33.£ -H uCl/Ta11ll 100  % Olll OllS 00:00 OJf.JlM 3600 Soc u No

  ~1-154                                 2007        -4.99MS            1.73£.-04      2..7JU4              UU/ 1018.I                   100        %     03/lQ(I S 00:00       0313Ul5          1600        Sa:      t.l                 No
  \\A.*226                               2007       ..g_ 71'&-0-1        IA6Fr 03      1AZU3               oClfl'olal                   100        %      03/l(ll!S 00:00       OJ/3 1/U         3600        Sec      u                    ~o I>>-232                                 2007         4.31£-04          6.12&-0~        l ..O:Jl:.ill3     uCJ/Io.tal                   100        ')i    0311 WU 00:00         OJ!!UU           3600        Sec      u UI No           ~**
                                                                                                                                                                                                                                                       ~ **

NP-237 2007 6..&IPA>S U3E-04 ~ uCllfolal 100  % 03/10fl3 00:00 ()3/31/15 3600 Soc No AM-241 (AS) 2001 l.37£.05 3.41B-06 l.OliB-06 uCi/f'otal I 2.41$  % 04/H~'JS 60000 sec +

 .;;:M-242 (AS)                          2()0}   I   7.59&-07           6JBE.Q7        5.01&-07            uCifro1lll                  .0241      !Dt!ll                        WIWIS          60000         sac      u I ~10/U r~*i-2431244 tAS)                         2001        9.6-0&-06          2..03E--06      7..61&()7          oe.vrimi
                                                                                                                                       .0241      a><ft[                                       60000         sec      +

lfU*:Z:fll (AS) 2001 S.58f..-06 2 .19Fr06 3.461!--06 uCilrot.al 2.47$  % 04fl0ll s 60002 ~ + u<::vrotal i'U*23W2'40 (A.<;) 200 1 :1.3,J:-06 1.40&-06 J.64E-06 2.475

                                                                                                                                                   "'                           IMllOll.S 04~l/1 .s

(,()002

                                                                                                                                                                                                                      +
                                                                                                                                                                                                                       ~                      I 1

l'U-241 9.1s..,,..,5 J.l;IB--0<! _j_~ 2001 M

.~IJ-l4l {AJ)')                       l 2001     I I.99'&-04
                                                    -2.TTFAJ7           2.7l!F,.-07    1.lOE-416 uCi/To'.:8J ilCVfll1!.I 2.475 2.47$       "
                                                                                                                                                   %                            04 OM 3-0 60002
                                                                                                                                                                                                        -             u                 J     j
   ~,_     v .ive.

u

   ~

u* ffld>

               ---   C~Afl.11.YllOllO( dcblollxl (<MDq orJ,... thsnJ '""'"

Ac!MtyaJIJCClltnill0t1 "'":a:dsMDC IJld 3 slvm; iu* idcntificd(,pcmt.aml;y) C'.ampomxVAnafyle Olli dcl.tdleli l'l!1k ort idtr:Jti!it:d, but~ ll<'liYfly

                     }.di.tty °""""""1IOG CU:C:do Cllltamn- JCIKltliot; ,..)ue
                                                                                                    """°""""'lt)rl ttettxis MDC w '.l dgm1 No - <'Oll:!lC>IUlcnli fkdiD-lp<dnn Yer eJ'l:likidmtlflcdinpmaaspc:.:trum
                                                                                                                                                                       *"'Unless othenviao llt1led, the aoaljtlcol ruuJts r<:pmod
   ~            -    MDC ,.._11' -            lcc!mleal .tpeelfatioD                                                                                                   1R>n:ldmualy1D dx ~             """""'1'* Ill COdll!illatl I.hey L            ~

Lmrmc"""J' ~~ trytt>e lol>cn:ay. H - fl) flll toCO""Y M1JC *M'llllmlllIJ Dctcctlhlc Co~ Bnldod tut indlcltts rep<ll'labfo nta11. Pqc 12oCIB

                                                                                                                                                                                                                                                      ~!
                                                                                                                                                 -- - - -                                                                                     *--.-...m.

Report of Analysis ~TE1S1\'NE 04/l7n s i d.:34 BROWN ENGltfilRlNG. INC.

                                                                                                                                                                                                                   .. ..,.,.,,..~~     .. rm....,

L62439 ZionSo.lution

   ~e mu                                                                                                        HN010-3P61ZlON-lO Sample IP: Ul Cl'MT CA \"l'fY                                                                    Col!CCt Slmt: CB/IOl20l .5 CHJiOO                                 Meltilc Sw:\pcol                                                (SW)

SIRtiao: 4S9l Collect Stnp: Volumt:: Descrip1ioo: Rcccive Dl!te: 03n snois %Moimnre; UMSNumber: L624J9-6 I RtidiOIJKlld* so #I Ar.tMty j Un<<ttsillt)' Coac . l igms MDC nits R*111: ' fl Aflqlotl Volo111e Aliquot am Rd'uc~ Dalt I Coant Dt: COVJ1t Time Cmi Um:ib I ll'JagVlllac.s

                                                                                                                                                                                                                                                               .c.

C-1'1 2002 I l.29!-04 6.71P..()5 9.~9~ ucirr01a1 I I S.2S  % OC/1 4115 30 M + I {)](J ()(15 00;00 CE-144 (RAD) fffi.55 2004 2006 4.52&-0S 2,UUll

                                                                     .5.0f!.OS J.71ll-03 l:OSE-<M l.42B-03 uCi/Tctal 11CilrOU11 4.75 2.375         "'~    0311Clll5 00:00 04/17/IS 04flSflS 7200 900 Sec I U Sec         .j.

1 No Yu 11*3 2010 3.37B-OS l.'nB-04 l.~ uCTITciJll .2.l  % 001-'?JS 5 M u ......... 1*129 1.012 l.?36-06 3.S9U.VS 6.01£-05 uCi/l'nW 10.S  % Oltt Oil S 00:00 04/16/JS ~ Sec. u No 03/Wl5 00:00 CMflll l.S llOO Sec u No 1 lNl-59 NI-63 2013 2CIJ I 3.8Jl'AlS J.JR.-02 7 _57E-{)j' 4.9SIJ.-O~ 6.7&F.--04 11.llll.-04

                                                                                       !.Olm~

uCVl'O!l\l uCl/Total oCil'IolD.l 4.7' 4.75

                                                                                                                                               %                                 <J.CIWIS            .5            M u
                                                                                                                                                                                                                             .1.                        -

SR-li9 201! 6.73~ 1.041:-04 4.75

                                                                                                                                               '~     V..H' l IVl.5 00:00        04.'14/ l           IS            M I

'SR.- 90 2018 1.21&-05 l.JIB-05 .4,13.lf,.0;5 UCiffotal 4.15  % 03/10/15 00:00 001411.5 15 M u I £C.99 2021 1 7.38E-05 l .7Se-04 l,33:£..G.f uCifJ'oW .475 I

                                                                                                                                               %                                 04/llllS'          30             M         u              -      1---

BB-7 2.007 -1.07&-04 l.37.B-03 l.31.E-ro uurrll!BI 100  % OJIUVlS 00:00 03131/U 3600 Sec u No K-iO 2007 *l.96B-04 5.16B-04 8.94f...CM acuroml 100  % 03/lQIJS 00:00 .113/31/lS 31i(]0 S<C u No

lR.-SI ' JANI l..:n&-03 1.-41>1>11.J 1.42"'-<<l UUl lOllil 100  % 03/lOllS 00:00 OJ/31115 3C-00 ~ u Nn MN*54 2007 *8.21FA5 2.28PM 3.70&-04 aC"1'o!Jil 100  % If.If l n11.5 00;00 0313lll5 3600  ::;c:c; u No CO.S7 2007 6.07E-CS 6.70B-OS 1-1~ uClf'I'otlll 100  % 03f11¥1S 00:00 03131/lS 3600 Sec u No C0-53 wen *SASS.OS U5E41 4.lflr-04 l!Ci/Total I 100  % 03/10/lS 00:00 03/31/lj 3000 Sl!c u No l'B-59 20()"7 UIE-0.5 3ALB-04 S.7l"E-<M nCirrotFJ 100  % 03i IO/lS 00:00 03f.3l/IS 3600 Sec u 'No I 1~

20CY7 2007 ' s.78}',..Ql 8.JIB-04 7.77E--04 6.0lB-04 USE.-04

                                                                                      '-9J:E4M 1lCl!total oCi'Total 100 100 100 03110/15 00:00 03ll<W1S 00:0()

03110/15 OO:OD 03J3Ul.5 OJJ3t/1S OJJ3tl1S 3600 3600 Sec Sec

                                                                                                                                                                                                                 ~
                                                                                                                                                                                                                            ~*

u u Ya,, No lt-.'B-94 NB-9.S 2007 2007 l.64E-04 1..23&-0ot 2.46e.Gi 436&-01

                                                                                      '.J)6]!..(M

J.92&.o4 nc..'ifrollll auriofll 100 "

                                                                                                                                               %     03/10/15 OO:OD              03/ll/JS 3000 3fi00           Sec        lJ No No llR-9:5
                                    ' 7.001         .2.JQB-04       4.24&-04          6.90]!'..M    iiCiffiillll                  100          %     OJ/I 0115 00:00            0313In.S         3000            Sec        u                  N'o iRU'-I0.3                              2007           *9.82U.-05     1.!ZE-IM          l.03Jl'..64   11Uf loW                      JOO          %     <DllO/U 00:00               03J31/H         3600            Soc        u                 No rR.U-10/i                              2Q<J7           l.6GB-02      330£.-02          9.GlE-113*    uCilTolal                     100         %      OJ/l()'l5 00:00            0313 1113        ' DIN           Sec        u                 No

• AO* I OS~f 2007 -6.90....05 I~ r l.S4&-04 nCifl'oW lOO '  % 03f1Q/1S 00:00 03/3111S 3600 Sec u No 3.7(Jl,.0.5 uCi/Tbtal u

 ~0-1/0M                              2007                          l.00.i;..()4      2..90.lt-04                                 100
                                                                                                                                              "      0311 Oils oo~

03/llllS l600 Sec No r1~Vllluco ti = CampooirltVf\mllyte n<i. dclccu:d (<:MDC) Qt , l iJ;rDl1 1'16 Ml ktmlllltd 1. ~

             -=    Acti-rity eaccmln.tlan """""'11 MDC O!ld 3 sip>a; pea- ~111Wna <mfy)                                                                             'I:<:! - l'cal idmtt6eil jg~~

1.I' fflp,b ~ Campoom'~ ~cletDcld l'talt llCJI idcrilified, bu! !urocd ~jty m=:ninll<xl cru:coill MOC and l Rmia

                   /lal/vltywhCC()traOon 1:11"""1b c;uslum...-~V1111oe                                                                                               *-u             ~DColfld. lllo ~ ....W::. n:iioct.d Spa;             MDC c:u:ccdl W!tomtrtocb.1ical speoltlcollQn                                                                                                      lltl!l'lkcd lJ' II) ,fl<e Jartlj>&:il 1""1.cd in ClC ""11fltflon fbey L

II Bolded Int I.aw rtJCIWt6)' Ilil!h n:am:ry dfClltu Nojltu'hlbl~ ....tu *

                                                                                               -                                                                     ire .rocioivd l!y l!to lllxml!Dry.

MDC* Minimum Dcticr:Ul>:e ~ioll Page 13 of lli

Report of Analysis TElEDYNE 04/17/JS 14:34 BROWN ENGINEERING, INC.

                                                                                                                                                                                                                  ~l*'"""'8 r.o .....w;ta~

L62439 ZiooSofotion Steve.Hitt ENOJ.().JPfilZION* lO S11mple ID: IJJ CTMT CA VHY Collea Stmt: CIJ/IOl'1.0I5 00:00 Matrix: Swiprs (SW) S!atioo: ~591 Collect Stop: Vur--

        ~criptiou:                                                                                           Rccllh-c:Dllll:~   OOllR/2015                                %Mo~:

LIMS Nombe!: 1.62439-6 Radionutlldt I SOP# I Ad Mey IU11ummty CollC 1 Sipw )fl>C I Uaiit R_uq i Aliquot Velllllle AJ"quat UD.111 Reftneee J)Ib CollJlt Dllh

                                                                                                                                                                                                       <Aunt lune I Count U..ib            ~&V1Iu.*

I I

~11-113 2007 1.6S~ 2..71J!..O' uCI/TcrtBI 100  % 03flOll s 00:00 OJ/JUI 3(,()0 Son u No 1.72E-O' SB-12*

1SB*l2.5 2007 2001 I I

                                                  -1.99B-05 J.42&-<M           '  l. 15.8-04 3A2ll-04 1.81:&-04 5.50'...&.4 11Ci1Total l!Cift'obll 100 100
                                                                                                                                                    %       03/l Ofl S 00.:00 03/1Clfl5 00:00 0313 111 0)/31/l 3600 3600 Sa:

Sa: u u No Ne IIE-12SM 2007 I 9.JIE.Q3 2.4SE-02 U8Jt..Ol uCifl'C!llll I 100  % 03/Hlfl.S 00.-00 0313111 3(.00 Sec u Nn {-131 CS-13<1. jCS-137 p_:u ::001 I

                                                 -4.411!-04
                                                  -9.08Pr05 6.3S'f!,.{14 7.ISB-04 2..l9n.M 2 .43£.-04 l.~

l.90S-04 J .06E-04 aCitl'otal 11Ciffo1el Ul.:VIC)tll) 100 100 100 03/lOllS 00:00 03110/IS 00:00 03/l MS 00:00 0313 l/J 0313 111 03131115 3600 3600

                                                                                                                                                                                                       )c.-00 So:c Sec Sec u

u

                                                                                                                                                                                                                               +
                                                                                                                                                                                                                                            ! No No Yes
!lA-1-40                             2007          2.900--04             UBB-03           2.U-£.03       ucL'rat&l                     100          %       03110/U 00:00            OJ!JU15           3600      Sec           u                No     I IL.A-MO                               2001 1 -7..17E-OS                   l.7Sli--04       2.6,T.&        uCl!Tobol                     100          %       03fl0/IS 00:00           O.lr'llfl.S       36-00     SC<>         u                 No              ...;

CJl.-1'1 l 2007 I -6.07E-0.'! J.li:IB-04 3,0jlt-114 uCilfatal I 100  % 03/IWlS 00:00 0313(fU 3600 Sec u 'Nn

                                                                                                                                                                                                                                                            ~

CS-14' lnJ.lS.4 2007 ' 2007 7.S~ 2.1111>-<M S.29.E-04 237B-04 l.90"£.44 4.9'E-& nCVrotal uCi/T'DtRI t-- 100 100 03/lM.S: 00:00 03/lOfl 5 00:00 03131/ll OJ13111S,

                                                                                                                                                                                                       *OD 3600 See s....

u u No

                                                                                                                                                                                                                                             *No--          . ~ *. *
                                                                                                                                                                                                                                                            ~

RA-226 2007 ' -9.681'.--0S 2.06B-03 3.,lJt-03 o<WTO!al IOO Olll !lfl S 00:00 OJ/3111..SI 3600 S<ie u u No f,, 1Jli-232 2007 -1.02£.-03 9.llm-04 U IL-00 U\,;Vl"otal I 100  % 03/JQ/IS 00:00 OJJ3l/l.5 3600 Sec No IN'P-237 2001 I l.118-04 ~ J ,66R-(M llCifro!al 100  % 03/lOllS 00:00 OJ/3 UlSI 3600 Sa: lJ No If~ 2001 I 4.lllfi,..()5 r.<<&-07 11Cifl'otnl :Z.373 04110/l '} 60000 + I 5!' AM-241 (AS) C.\1*242 (AS) CM-243f.l44 (AS)

WO!

2001 I 1.119~ 7.65£.-07 S.28&-06 S.62B-07

2. lfiE.-06 356Jt..01 7.S6B-07 ueirrota1.

nCiffobtl

                                                                                                                                     .0238
                                                                                                                                     .0218 IDtll total 0.,10/tsl 0-ll!Oll' 60001)
                                                                                                                                                                                                     !iOOOO sec sec u
                                                                                                                                                                                                                              +

t'U-l3& (AS) 2001 I .1.JJJ!.-05 .urn-or. 2.116-06 uCi/Totnl 2.315  % 04/10/15 60001 ..., + PlJ-2391240 (AS) l'U-l41 PU-W(AS) 2001 t 2001 I J.11£.-05 3.'3£.-04 2001 I -2.04B-07 l .3SE-06 1.096-04 2..36B--07 2..22.B-06 l.39B-04

                                                                                          .9.30~

uClfl'otAI u.Ci/I'otlll aCilibW 2..375 2.375 2.37~ 04/10/JS 60001 04/l.5/151 CWlOlll1 30 60001

                                                                                                                                                                                                                 "°° M
                                                                                                                                                                                                                             +
                                                                                                                                                                                                                              +

ti I J:

                                                                                                                                                                                                                                                           ~! I

-~

Flag Vibes

 ..u --      ~

Compaand/~ocC d~ (< MDC) ot .... lbei:i 3 At.troty ~~~MDC 111d l silll'I: pcM: irlartificd(pmma CJll!y)

                                                                                  *!Jlmll                                                                                No - l'Clt oot ldailifi<:d .. pm!Dll lp:c:lrum v.. - h1ik ldctitifiQI ill                                                        ~:

11' ~l\rlal)'len<< . S - . l'elllc not idmtifl!>d. b!a-w:c!Tlty wcku1ai=lsMDCr.ncl 3 ** ipccllllln f'.

                                                                                                                                                                         .... u..1- ~""' ""ll>d, the maly!lc:ol ...mts tq>Orlod                                          ....,
                                                                                                                                                                                                                                                           ~

ffli;b A<:tmty 1XY.cmlrllliDa e<...Cdt - ~.,. ~... s- Mlx: ct""""11 ~ Jcc!!fllcal spccifi1'Cion ""'t'ClllC!ld ..,1y IO Ole samploa lmio.i lo 11111 oom1i6oo ll"'J L :i:.owni..mry in l'l!ODMd by Ille~- (/) H = Hilb l'C"""'Y MDC-M-.nbnum D.u.c:tabfo ~

                                                                                                                                                                                                                                                             *,          u I Balded Int Sndlcata rq1011able valac.                                                                                                                                                                                                                                   ......

flj 0\ l'qi; 14of18 i_g*; r (!) 0 0 0 I

                                                                                                                                                                                                                                                                         -....)

Report of Atlalysi TB.EDYNJ: BROWN ENGINEEJllNG, INC. 04/17/t:i 14:3' A1""""'~~ I.62439 7..ionSolution Stxlw Hitt EN010-3P61ZJO *JO SM!!ple ID: U2 :RX Vl!SSJ:J, Collcet Stmt: 03/1 Q/2iJ l S 00:00 M!triJt: s~ (SW) SWlo:i: 4537 CoJleel Stop: Valumc: OC1crip!ion: R.ecch-e DU:: Q3f!A/20JS %Moimlrc: 1-'S Nurobcr: 1.62439-7 I Radion11tlldc SOl'il ActMty jUll.cert.1111.7 Coot 2 Sigma I MDC Unlta I Boni Allq Volume ot Allq I>! Uaitit Ref~-- Oat. Q)llJ){ Jn.fl: Co~ Time t Co1111t (J FlqV.i I

  ;;;-14                                2002         6.S JB-OS        5.585-05         S.73~5         oC:Vrobll                     s.32           %                               04/14/U           30          ),.f       u                     I 1
  .:B-144 (RAD)                         ?(.1(1<1     6.9.SE--05        LY7E-~         2,llOF~        oCVfollll                      4.lill        %       03/lOll s 00:00          04/1 7/1         4390        Sec        u                No
                                                                                                                                                                                                                            ...                     I 1~                                     2006          ll.7JM3 WlO I -6.6'7FA>S 1  U CE-03          S.l fffi.03 1..741'....fM uCi/J'otal uCill"lbl 2.l4 2.128 03/Hlf!S 00:00           04/I Sl l IW14/1' 900 s

Sec M u Yes R*3

                                                 -                     l.YlrAK                                                                                                                              I 1*-129
 !'1;1*59 2012 2013
                                                    -6.99S-06 I 1.(>)Jt.-02 1.42Jt+<<l 3.76Jl.05 U3Il.03 4.43B-03
                                                                                      .5.97:&-115 1.90"--0l 8.ZOB-0$

uCifrotal u<.:Vl'oW

                                                                                                                        -j 10.64 4..611 4.68 03110/IS 00:00 11311 IV15 00:00 04/l(i{l 04ll.:J/ l5 04/14/J w.i 600 5

Sec Sec M u No Yen 1 Nl-6J 20!3 oCi/Trn.J

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                                                                ,.,~1o>hn1lctltotlrttp1JY 1508 QRJ.ity L-.c Knoxville, 1107931-3133 865-69:).6819 Steve Hirt ZlooScilulioo 101 Shiloh 'bt>Ule,*ard Report of AnalYJWCtirtificAte of Confonuan*ce 10/16/2015 LIW.S#:   L6S197 Project ID#;  ~OJ0-3P61ZION*IO Recillnd:  10,'0612015 Dellvccy Date:  10/   /201~

P.O.#: (;17132 Role fl: SDGi; This is to certiCy that Telcdyno Brown Engineering - Environmcninl Services 1o~atcd at 2508 Quality Lane, Knoxville, Ten.ne~ 3793 l, has analyr.cd. tebied and documented samples, as receh*ed by 1he lahoratcny, es specified in the applicable purchase order. This also certi:fi that requ:irementll of applicable codes, standards and specifications have been folly met and that any quality assurance documentation whieh verified confonntmCC to 'the pmcllase ordc2 is on file end may be examined upon request. I hereby certify that the above statements are true and COireCt

       ~ii!;JiL Operations Manager CliaatID                                 ID                   Stalion. ID ii'  licahlc 13296                                                                   UZ!IO MAtriz                             AmlyJis                                      Method kdireDcci SW                                 GAMMA                                    -~.,...1------                   ----.. . i. .

This report shall .nol be rt:produced or distributed except in its entirety. l'AA>11 I of3 Page 53 of SS I ___ _

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