ML21195A033

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Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report
ML21195A033
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 07/14/2021
From: Laura Smith
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
Download: ML21195A033 (355)
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Text

Larry D. Smith Regulatory Assurance Manager Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657 410 495 5219 Office 410 495 2067 Fax 410 610 9729 Mobile www.exeloncorp.com larry.smith2@exeloncorp.com 10 CFR 50.36(a)(2) and 72.44(d)(3)

July 14, 2021 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 NRC Docket Nos. 50-317 and 50-318 Calvert Cliffs Nuclear Power Plant Independent Spent Fuel Storage Installation, License No. SNM-2505 NRC Docket No. 72-8

Subject:

Annual Radioactive Effluent Release Report

References:

1. Calvert Cliffs Units 1 and 2 Technical Specification 5.6.3
2. Calvert Cliffs ISFSI Technical Specification 6.3
3. Calvert Cliffs Unit Nos. 1 and 2 Technical Specification 5.5.1.c.3 As required by References 1 and 2, the Annual Radioactive Effluent Release Report is attached.

Meteorological data is kept in an onsite file and is available upon request.

As required by Reference 3, a copy of Revision 3 of the Offsite Dose Calculation Manual, CY-CA-170-301, is also attached.

There are no regulatory commitments contained in this correspondence.

Should you have questions regarding this matter, please contact me at (410) 495-5219.

Respectfully, Larry D. Smith Regulatory Assurance Manager LDS/lmd

Document Control Desk July 14, 2021 Page 2

Attachment:

(1) Radioactive Effluent Release Annual Report - 2020 (2) Offsite Dose Calculation Manual for Calvert Cliffs Nuclear Power Plant, CY-CA-170-301, Revision 003 cc: NRC Project Manager, Calvert Cliffs S. Seaman, MD-DNR NRC Regional Administrator, Region I Director, NMSS NRC Resident Inspector, Calvert Cliffs C. Stewart, ANI

Document Control Desk July 14, 2021 Page 3 bcc: T. Domeyer, AGC D. P. Ferraro, AGC S. B. Rafferty-Czincila D. P. Helker F. J. Mascitelli T. P. Haaf J. A. Dullinger C. J. Jackson D. J. Hild L. D. Smith R. Thomas J. Jackson EDMS NRC 21-021

ATTACHMENT (1)

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR CALVERT CLIFFS NUCLEAR POWER PLANT UNITS 1 AND 2 AND THE INDEPENDENT SPENT FUEL STORAGE INSTALLATION Calvert Cliffs Nuclear Power Plant July 14, 2021

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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION This report covers the period January 1, 2020 to December 31, 2020 for Calvert Cliffs Nuclear Power Plant.

This report covers the period June 1, 2020 to May 31, 2021 for the Independent Spent Fuel Storage Installation.

Calvert Cliffs Nuclear Power Plant July 14, 2021

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CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020 Facility - Calvert Cliffs Nuclear Power Plant and Independent Spent Fuel Storage Installation Licensee - Calvert Cliffs Nuclear Power Plant, LLC This report covers the period January 1, 2020 to December 31, 2020 for Calvert Cliffs Nuclear Power Plant.

This report covers the period June 1, 2020 to May 31, 2021 for the Independent Spent Fuel Storage Installation.

I. PREFACE The following sections of the preface are meant to help define key concepts, provide clarity, and give context for the readers of this report.

A. Annual Reports The Nuclear Regulatory Commission (NRC) is the federal agency which has the role of protecting the health and safety of the public as it relates to nuclear energy. Nuclear Power Plants provide two reports annually to the NRC; these reports address how the stations operation impacts the environment of the local community. The NRC then reviews these reports and makes them available to the public. The names of the reports are the Annual Radioactive Effluent Release Report (ARERR) and the Annual Radiological Environmental Operating Report (AREOR).

The ARERR reports the results of a stations effluent monitoring program. An effluent is a liquid or gaseous waste containing plant-related radioactive material emitted at the boundary of the facility.

The AREOR reports the results of samples obtained in the environment surrounding the station; these samples are analyzed for radioactivity. Environmental samples include air, water, vegetation, and other sample types that are identified as potential pathways through which radioactivity can reach humans.

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CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020 Graphic 1. Examples of Gaseous and Liquid Effluent Pathways Graphic 1 demonstrates some potential exposure pathways from Calvert Cliffs Nuclear Power Plant. The ARERR and AREOR together ensure Nuclear Power Plants are operating in a manner that is within established regulatory commitments meant to adequately protect the public.

B. Understanding Radiation Generally radiation is defined as emitted energy in the form of waves or particles. If radiation has enough energy to displace electrons from an atom it is termed ionizing, otherwise it is non-ionizing. Non-Ionizing radiation includes light, heat given off from a stove, radiowaves and microwaves. Ionizing radiation occurs in atoms, particles too small for the eye to see. So, what are atoms and how does radiation come from them?

Graphic 2. Types of Radiation, from NASA Hubblesite 3

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CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020 An atom is the smallest part of an element that maintains the characteristics of that element. Atoms are made up of three parts: protons, neutrons, and electrons.

Graphic 3. Structure of an Atom The number of protons in an atom determines the element. For example, a hydrogen atom will always have one proton while an oxygen atom will always have eight protons. The protons are clustered with the neutrons forming the nucleus at the center of the atom. Orbiting around the nucleus are the relatively small electrons.

Isotopes are atoms that have the same number of protons but different numbers of neutrons. Different isotopes of an element will all have the same chemical properties and many isotopes are radioactive while other isotopes are not radioactive. A radioactive isotope can emit radiation because it contains excess energy in its nucleus. Radiactive atoms and isotopes are also referred to as radionuclides and radioisotopes.

There are two basic ways that radionuclides are produced at a nuclear power plant. The first is fission, which creates radionuclides that are called fission products. Fission occurs when a very large atom, such as uranium-235 (U-235) or plutonium-239 (Pu-239), absorbs a neutron into its nucleus making the atom unstable. The unstable atom can then split into smaller atoms. When fission occurs there is a large amount of energy released in the form of heat. A nuclear power plant uses this heat to produce steam. The steam is directed toward a turbine, forcing it to spin. The spinning of the turbine is used to produce electricity.

The second way a radionuclide is produced at a nuclear power plant is through a process called activation. The radionuclides produced in this method are termed activation products. Pure water is used to cool the reactor and also to produce steam to turn the turbines. Although this water is considered to be very pure, there are always some contaminiants within the water, either from material used in the plants construction or from the operation of the plant.

These contaminants are exposed to the fission process and may become activation products. The atoms in the water itself can also become activated and create radionuclides.

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CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020 Over time, radioactive atoms will reach a stable state and no longer be radioactive. To do this they must release their excess energy. This release of excess energy is called radioactive decay. The time it takes for a radionuclide to become stable is measured in units called half-lives. A half-life is the amount of time it takes for half of the original radioactivity to decay. Each radionuclide has a specific half-life. Some half-lives can be very long and measured in years while others may be very short and measured in seconds.

Graphic 4. Radioactive Decay Half-Life In the annual reports you will see both man made and naturally ocurring radionuclides listed, for example potassium-40 (K-40, natural) and cobalt-60 (Co-60, man-made). We are mostly concerned about man-made radionuclides because they can be produced as by-products when generating electricity at a nuclear power plant. It is important to note that there are also other ways man-made radionuclides are produced, such as detonating nuclear weapons. Weapons testing has deposited some of the same man-made radionuclides into the environment as those generated by nuclear power, and some are still present today because of long half-lives.

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CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020 C. Measuring Radiation There are four different but interrelated units for measuring radioactivity, exposure, absorbed dose, and dose equivalent. Together, they are used to report amounts of radiation and quantify its effects on humans.

  • Radioactivity refers to the amount of ionizing radiation released by a material. The units of measure for radioactivity used within the AREOR and ARERR are the Curie (Ci). Small fractions of the Ci often have a prefix, such as the microcurie (Ci), which means 1/1,000,000 of a Curie.
  • Exposure describes the amount of radiation traveling through the air. The units of measure for exposure used within the AREOR and ARERR are the roentgen (R). Traditionally direct radiation monitors placed around the site measure milliroentgen (mR), 1/1,000 of one R.
  • Absorbed dose describes the amount of radiation absorbed by an object or person. The units of measure for absorbed dose used within the AREOR and ARERR are the rad. Noble gas air doses reported by the site are measured in millirad (mrad), 1/1,000 of one rad.
  • Dose equivalent (or effective dose) combines the amount of radiation absorbed and the health effects of that type of radiation. The units used within the AREOR and ARERR are the roentgen equivalent man (rem). Regulations require doses to the whole body, specific organ, and direct radiation to be reported in millirem (mrem), 1/1,000 of one rem.

D. Sources of Radiation People are exposed to radiation every day of their lives and have been since the dawn of mankind. Some of this radiation is naturally occurring while some is man-made. There are many factors that will determine the amount of radiation individuals will be exposed to such as where they live, medical treatments, etc. The average person in the United States is exposed to approximately 620 mrem each year with 310 mrem coming from natural sources and 310 from man-made sources. The Graphic 5 shows what the typical sources of radiation are for an individual over a calendar year:

Graphic 5. Sources of Radiation Exposure in the U.S., from NCRP Report No. 160 6

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CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020 The radiation from a nuclear power plant is included in the chart as part of the Industrial and Occupational fraction,

<0.1%. The largest natural source of radiation is from radon, because radon gas travels in the air we breathe. Perhaps you know someone who had a CT scan at a hospital to check his or her bones, brain, or heart. CT scans are included in the chart as Medical Procedures, which make up the next largest fraction. Graphic 6 shows some of the common doses humans receive from radiation every year.

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CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020 Graphic 6 .Relative Doses from Radiation Sources, from EPA Radiation Doses and Sources E. Radiation Risk Current science suggests there is some risk from any exposure to radiation. However, it is very hard to tell whether cancers or deaths can be attributed to very low doses of radiation or by something else. U.S. radiation protection standards are based on the premise that any radiation exposure carries some risk.

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CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020 The following graph is an example of one study that tries to relate risk from many different factors. This graph represents risk as Days of Lost Life Expectancy. All the categories are averaged over the entire population except Male Smokers, Female Smokers, and individuals that are overweight. Those risks are only for people that fall into those categories. The category for Nuclear Power is a government estimate based on all radioactivity releases from nuclear power, including accidents and wastes.

Graphic 7. Days of Lost Life Expectancy, Adapted from the Journal of American Physicians and Surgeons Volume 8 Number 2 Summer 2003 II. REGULATORY LIMITS A. Fission and Activation Gases

1. The instantaneous release rate of noble gases in gaseous effluents shall not result in a site boundary dose rate greater than 500 mrem/year to the whole body or greater than 3000 mrem/year to the skin (Offsite Dose Calculation Manual (ODCM 3.11.2.1).
2. Gaseous Radwaste Processing System and the Ventilation Exhaust Treatment System shall be used to reduce gaseous emissions when the calculated gamma-air dose due to gaseous effluents exceeds 1.20 9

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CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020 mRad or the calculated beta-air dose due to gaseous effluents exceeds 2.4 mRad at the site boundary in a 92 day period (ODCM 3.11.2.4).

3. The air dose at the site boundary due to noble gases released in gaseous effluents shall not exceed (ODCM 3.11.2.2):

10 mRad/qtr, gamma-air 20 mRad/qtr, beta-air 20 mRad/year, gamma-air 40 mRad/year, beta-air

4. All of the above parameters are calculated according to the methodology specified in the ODCM.

B. Iodines and Particulates with Half Lives Greater than Eight Days

1. The instantaneous release rate of iodines and particulates in gaseous effluents shall not result in a site boundary dose-rate in excess of 1500 mrem/year to any organ (ODCM 3.11.2.1).
2. The Gaseous Radwaste Processing System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous effluents when calculated doses exceed 1.8 mrem to any organ in a 92 day period at or beyond the site boundary (ODCM 3.11.2.4).
3. The dose to a member of the public at or beyond the site boundary from iodine-131 and particulates with half-lives greater than eight days in gaseous effluents shall not exceed (ODCM 3.11.2.3):

15 mrem/qtr, any organ 30 mrem/year, any organ less than 0.1% of the above limits as a result of burning contaminated oil.

4. All of the above parameters are calculated according to the methodology specified in the ODCM.

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CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020 C. Liquid Effluents

1. The concentrations of radionuclides in liquid effluents from the plant shall not exceed the values specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for unrestricted areas (ODCM 3.11.1.1).
2. The liquid radwaste treatment system shall be used to reduce the concentration of radionuclides in liquid effluents from the plant when the calculated dose to unrestricted areas exceeds 0.36 mrem to the whole body, or 1.20 mrem to any organ in a 92 day period (ODCM 3.11.1.3).
3. The dose to a member of the public in unrestricted areas shall not exceed (ODCM 3.11.1.2):

3 mrem/qtr, total body 10 mrem/qtr, any organ 6 mrem/year, total body 20 mrem/year, any organ

4. All liquid dose parameters are calculated according to the methodology specified in the ODCM.

III. MAXIMUM PERMISSIBLE CONCENTRATIONS A. Fission and Activation Gases Prior to the batch release of gaseous effluents, a sample of the source is collected and analyzed by gamma spectroscopy for the principal gamma emitting radionuclides. The identified radionuclide concentrations are evaluated and an acceptable release rate is determined to ensure that the dose rate limits of ODCM 3.11.2.1 are not exceeded.

B. Iodines and Particulates with Half Lives Greater than Eight Days Compliance with the dose rate limitations for iodines and particulates is demonstrated by analysis of the charcoal and particulate samples of the station main vents. The charcoal samples are analyzed by gamma spectroscopy for quantification of radioiodine. The particulate samples are analyzed by gamma spectroscopy for quantification of particulate radioactive material. Monthly composites of the main vent particulate filters are analyzed for gross alpha. Quarterly composites are analyzed for Sr-89 and Sr-90. All of the above parameters are calculated according to the methodology specified in the ODCM. Additionally, two quarterly composites are analyzed for Fe-55; the Fe-55 analysis is not required by the ODCM, but is driven by site procedure.

C. Liquid Effluents The Maximum Permissible Concentrations (MPCs) used for radioactive materials released in liquid effluents are in accordance with ODCM 3.11.1.1 and the values from 10 CFR Part 20, Appendix B, Table II, Column 2 including applicable table notes. In all cases, the more restrictive (lower) MPC found for each radionuclide is used regardless of solubility.

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CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020 IV. TECHNICAL SPECIFICATION REPORTING REQUIREMENTS A. Calvert Cliffs Nuclear Power Plant (CCNPP), Technical Specification 5.6.3

1. 2020 Offsite Dose Due to Carbon-14 Dose due to Carbon-14 in gaseous effluents was calculated using the following conditions:
a. C-14 released to the atmosphere: 2.03E+01 Ci were released from the site.
b. Carbon-14 release values were estimated using the methodology included in the Electric Power Research Institute (EPRI) Technical Report 1021106, using the 2020 Calvert Cliffs Nuclear Power Plant assumed parameters of normalized Carbon-14 production rate of 3.822 Ci/GWt-yr, a gaseous release fraction of 0.98, a Carbon-14 carbon dioxide fraction of 0.30, a reactor power rating of 2737 MWt for Unit 1 and 2737 MWt for Unit 2, and equivalent full power operation of 341 days for Unit 1 and 366 days for Unit 2 (2020 was a leap year with 29 days in the month of February).
c. Meteorological dispersion factor (X/Q) at the nearest residence with meat cow located at 1.6 miles in the south meteorological sector is 2.07E-07 sec/m3.
d. Pathways considered to the hypothetical maximally exposed member of the public (child) were inhalation and cow meat ingestion.

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CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020

2. 2020 Dose Assessment Summary Quarter 1 Quarter 2 Quarter 3 Quarter 4 Yearly Liquid Effluent Dose 3 mrem 3 mrem 3 mrem 3 mrem 6 mrem Limit, Total Body Total Body Dose 3.07E-04 1.92E-04 3.49E-04 4.78E-04 1.33E-03

% of Limit 1.02E-02 6.40E-03 1.16E-02 1.59E-02 2.22E-02 Liquid Effluent Dose 10 mrem 10 mrem 10 mrem 10 mrem 20 mrem Limit, Any Organ Organ Dose 4.22E-04 2.18E-04 3.62E-04 5.45E-04 1.55E-03 1

% of Limit 4.22E-03 2.18E-03 3.62E-03 5.45E-03 7.75E-03 Gaseous Effluent Dose 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Limit, Gamma Air Gamma Air Dose 3.62E-05 1.92E-05 1.56E-05 1.18E-05 8.28E-05

% of Limit 3.62E-04 1.92E-04 1.56E-04 1.18E-04 4.14E-04 Gaseous Effluent Dose 20 mrad 20 mrad 20 mrad 20 mrad 40 mrad Limit, Beta Air Beta Air Dose 5.48E-05 7.46E-06 6.02E-06 4.50E-06 7.28E-05

% of Limit 2.74E-04 3.73E-05 3.01E-05 2.25E-05 1.82E-04 Gaseous Effluent Dose Limit, Any Organ 15 mrem 15 mrem 15 mrem 15 mrem 30 mrem (Iodine, Tritium, Particulates with >8 day half-life)

Organ Dose 1.83E-05 2.02E-04 4.07E-04 1.43E-04 7.70E-04 2

% of Limit 1.22E-04 1.35E-03 2.71E-03 9.53E-04 2.57E-03 Noble Gas Dose mRem NG Total Body 3.25E-05 1.82E-05 1.48E-05 1.12E-05 7.67E-05 NG Skin 5.99E-05 2.68E-05 2.17E-05 1.65E-05 1.25E-04 C-14 Total Body/Organ mRem Bone Dose 5.74E-03 6.66E-03 6.73E-03 6.73E-03 2.59E-02 Total Body Dose 1.14E-03 1.32E-03 1.33E-03 1.33E-03 5.11E-03 The controlling liquid pathway was the fish and shellfish pathway with adult as the controlling age group and the GI representing the organ with the highest calculated annual dose during the calendar year of 2020.

The controlling gaseous pathway was the teenager thyroid pathway representing the organ with the highest calculated dose during the calendar year of 2020. There is currently no milk pathway.

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CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020

3. 40 CFR 190 Total Dose Compliance Based upon the calendar year 2020 and the ODCM calculations, the maximum exposed individual received 0.113% of the allowable dose. During the calendar year 2020, there were no on-site sources of direct radiation that would have contributed to a significant or measurable off-site dose. The direct radiation contribution is measured by both on-site and off-site thermoluminescent dosimeters (TLDs).

The results of these measurements did not indicate any statistical increase in the off-site radiation doses attributable to on-site sources. Therefore, no increase in the calculated offsite dose is attributed to the direct exposure from on-site sources. A more detailed evaluation may be found in the Annual Radiological Environmental Operating Report.

EPA 40CFR190 Individual in the Unrestricted Area Whole Body Thyroid Any Other Organ Dose Limit 25 mrem 75 mrem 25 mrem Liquid 1.33E-03 1.27E-03 1.55E-03 Gas 8.47E-04 7.70E-04 7.70E-04 C-14 5.11E-03 5.11E-03 2.59E-02 Dose 7.28E-03 7.15E-03 2.82E-02

% of Limit 2.91E-02 9.53E-03 1.13E-01 Child bone dose was used for Any Other Organ due to C-14

4. Solid Waste Report Requirements During 2020, the types of radioactive solid waste shipped from Calvert Cliffs were dry compressible waste, spent resins, and cartridge filters which were shipped in either High Integrity Containers (HICs) within NRC approved casks, Sea/Land containers, or steel boxes. Appendix A of this report provides a detailed breakdown of the waste shipments for 2020 per Technical Specification 5.6.3. At CCNPP, methods of waste and materials segregation are used to reduce the volume of solid waste shipped offsite for processing, volume reduction, and burial.
5. Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP) Changes There were no revisions to the ODCM in 2020.

There were no changes to RW-AA-100, Process Control Program, in 2020.

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CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020 B. Radioactive Effluent Monitoring Instrumentation

1. The waste gas RMS, 0-RE-2191, exceeded the 30 days inoperable time period allowed in ODCM section 3.3.3.9. The monitor was declared inoperable on July 12, 2013 due to a detector failure and has remained inoperable since that time. The RMS has remained out of service due to equipment obsolescence. The station is pursuing plans to retire the system.
2. The unit 1 wide range noble gas monitor, 1-RIC-5415, exceeded the 30 days inoperable time period allowed in ODCM section 3.3.3.9. The monitor was declared inoperable on October 20th, 2020 due to failing a pump flow test.
3. The unit 1 steam generator blowdown RMS, 1-RE-4095, exceeded the 30 days inoperable time period allowed in ODCM section 3.3.3.10. The Monitor was declared inoperable on July 9th, 2019. The RMS experienced pump cavitation issues. 1-RE-4014 is credited by the ODCM as an equivalent monitor. With 1-RE-4014 in service, no compensatory actions were required.
4. The unit 2 wide range noble gas monitor, 2-RIC-5415, exceeded the 30 days inoperable time period allowed in ODCM section 3.3.3.9. The monitor was declared inoperable on July 30th, 2019. The global COVID-19 pandemic impacted equipment procurement.

C. Independent Spent Fuel Storage Installation (ISFSI), ISFSI Technical Specification 6.3 There were no casks of spent fuel transferred to the ISFSI during the reporting period. No quantity of radionuclides was released to the environment during the ISFSI operation in 2020. Additional information regarding the ISFSI radiological environmental monitoring program is included in the Annual Radiological Environmental Operation Report.

V. AVERAGE ENERGY Not Applicable.

VI. MEASUREMENTS AND APPROXIMATIONS AND TOTAL RADIOACTIVITY A. Fission and Activation Gases

1. Batch Releases Prior to each batch release of gas from a pressurized waste gas decay tank or containment, a sample is collected and analyzed by gamma spectroscopy using a germanium detector for the principal gamma emitting noble gas radionuclides. The total activity released is based on the pressure/volume relationship (gas laws). The Plant Vent Stack Radiation Monitor and the Wide Range Gas Monitor typically monitor containment releases, and the values from the radiation monitor may be used to assist in the calculation of activity discharged from containment during venting. Carbon-14 is estimated using methodology from EPRI Technical Report 1021106, as described in section IV.A.1.
2. Continuous Releases A gas sample is collected at least weekly from the main vents and analyzed by gamma spectroscopy using a germanium detector for the principal gamma emitting noble gas radionuclides. The total activity released for the week is based on the total sample activity decay corrected to the sample time multiplied by the main vent flow for the week. The Plant Vent Stack Radiation Monitor continuously 15

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020 measures routine plant vent stack releases, per design, and the values from the radiation monitor may be used to assist in the calculation of activity discharged in routine plant vent stack discharges.

During each containment purge, a gas sample is collected and analyzed by gamma spectroscopy using a germanium detector to determine the concentration of principal gamma emitting noble gas radionuclides inside containment. Total activity released during a containment purge is based on continuous radiation monitor responses, grab samples, and purge fan flow rate.

A monthly composite sample is collected from the main vents and analyzed by liquid scintillation for tritium. The total tritium release for the month is based on the sample analysis and the main vent flow.

Carbon-14 is estimated using methodology from EPRI Technical Report 1021106, as described in section IV.A.1.

B. Iodine and Particulates

1. Batch Releases The total activities of radioiodines and particulates released from pressurized waste gas decay tanks, containment purges, and containment vents are accounted for by the continuous release methodology discussed in section VI.B.2.
2. Continuous Releases During the release of gas from the main vents, samples of iodines and particulates are collected using a charcoal and particulate filter, respectively. The filters are removed weekly (or more often) and are analyzed by gamma spectroscopy using a germanium detector for significant gamma emitting radionuclides. The total activity released for the week is based on the total sample activity decay corrected to the midpoint of the sample period multiplied by the main vent flow for the week. A plate-out correction factor is applied to the results to account for the amount of iodine lost in the sample lines prior to sample collection. The weekly particulate filters are then combined to form monthly composites for gross alpha analysis. The weekly particulate filters are also combined to form quarterly composites for strontium-89 and strontium-90 analyses. Two quarterly composites per year are analyzed for Iron-55; the Iron-55 analysis is not required by the ODCM, but is driven by site procedure.

C. Liquid Effluents

1. Batch Releases Prior to the release of liquid from a waste tank, a sample is collected and analyzed by gamma spectroscopy for the principal gamma emitting radionuclides. To demonstrate compliance with the concentration requirements addressed in Section II.C.1 above, the measured radionuclide concentrations are compared with the allowable MPCs; dilution in the discharge conduit is considered, and an allowable release rate is verified.

The total activity released in each batch is determined by multiplying the volume released by the concentration of each radionuclide. The actual volume released is based on the difference in tank levels before and after the release. A proportional composite sample is also withdrawn from each release. These composite samples are used for monthly tritium and gross alpha analyses. The composite samples are also used for Iron-55, Nickel-63, Strontium-89, and Strontium-90 analyses that are performed quarterly by an offsite laboratory.

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CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020 Batch discharges of secondary (normally uncontaminated) waste streams are also monitored for radioactivity. No activity (excluding tritium) is normally detected in these secondary waste streams.

2. Continuous Releases To account for activity from continuous releases, a sample is collected and analyzed by gamma spectroscopy for the principal gamma emitting radionuclides. The measured radionuclide concentrations are compared with the allowable MPC concentrations in the discharge conduit, and an allowable release rate is verified.

When steam generator blowdown is discharged to the circulating water conduits, it is sampled and gamma isotopic analysis is performed at a minimum once per week. These results are multiplied by the actual quantity of blowdown to determine the total activity released. The weekly sample is also used to prepare monthly composites for tritium analysis.

During the monitoring for primary-to-secondary leakage low levels of tritium have been detected in the Turbine Building sumps. This water is sampled and analyzed for principal gamma emitting radionuclides weekly and composited. The composite sample is analyzed at least monthly for tritium.

The results are multiplied by the actual quantity of liquid released to determine the total activity released.

D. Estimation of Total Error Total error for all releases was estimated using, as a minimum, the random counting error associated with typical releases. In addition to this random error, the following systematic errors were also examined:

1. Liquid
a. Error in volume of liquid released prior to dilution during batch releases.
b. Error in volume of liquid released via steam generator blowdown.
c. Error in amount of dilution water used during the reporting period.
2. Gases
a. Error in main vent release flow.
b. Error in sample flow rate.
c. Error in containment purge release flow.
d. Error in gas decay tank pressure.

Where errors could be estimated they are usually considered additive.

E. Meteorological Data A summary of required meteorological data is included in the Annual Radiological Environmental Operating Report and is not included in this report.

F. Reporting and Recordkeeping for Decommissioning In accordance with 10 CFR 50.75.g, each licensee shall keep records of information important to the safe and effective decommissioning of the facility in an identified location until the license is terminated by the Commission. If records of relevant information are kept for other purposes, reference to these records and 17

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020 their locations may be used. Information the Commission considers important to decommissioning consists of records of spills or other unusual occurrences involving the spread of contamination in and around the facility, equipment, or site. These records may be limited to instances when significant contamination remains after any cleanup procedures or when there is reasonable likelihood that contaminants may have spread to inaccessible areas as in the case of possible seepage into porous materials such as concrete. These records must include any known information on identification of involved nuclides, quantities, forms, and concentrations.

To assist in the decommissioning, and to provide early and advance detection of any unmonitored releases of radioactive material from the site, groundwater is routinely sampled. These groundwater samples are analyzed for gamma and tritium activity. Sample size and/or count times are adjusted to achieve analytical sensitivities lower than the environmental LLDs for gamma emitters (listed in ODCM Table 4.12-1). The established LLD limit for groundwater tritium is 200 pCi/l. The 2020 analysis results for tritium and gamma are listed in the Annual Radiological Environmental Operating Report and are not included in this report.

VII. ERRATA I.Section IV.A.1.b. on page 11 of the 2019 Annual Radioactive Effluent Release Report incorrectly reported the full power operation days. The report should have stated: equivalent full power operation of 365 days for Unit 1 and 340 days for Unit 2. The full power operation days values were swapped between the two units. This did not impact the C-14 release calculation or the C-14 dose calculations.

18

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020 VIII. BATCH RELEASES 2020 A Liquid (1) 1ST 2ND 3RD 4TH QUARTER QUARTER QUARTER QUARTER

1. Number of batch 12 7 9 13 releases
2. Total time period for 6.02E+03 3.82E+03 4.96E+03 6.56E+03 batch releases (min)
3. Maximum time period 6.01E+02 6.04E+02 5.81E+02 6.47E+02 for a batch release (min)
4. Average time period 5.02E+02 5.45E+02 5.51E+02 5.05E+02 for batch release (min)
5. Minimum time period 1.00E+01 5.26E+02 5.20E+02 2.29E+02 for a batch release (min)
6. Average stream flow during periods of effluent into a flowing 4.59E+06 4.62E+06 4.62E+06 4.60E+06 stream (liters/min of dilution water)

(1) This table excludes batch releases from the Waste Neutralizing Tanks. While releases from these sources are sampled, documented, permitted, and accounted for in the Dose Assessment Tables, Table 2A, and 2B of this report, they are not significant contributors to radioactive effluent and are therefore not included in this table.

19

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020 B. Gaseous 1ST 2ND 3RD 4TH QUARTER QUARTER QUARTER QUARTER

1. Number of batch releases 27 21 17 14
2. Total time period for batch 1.14E+04 8.51E+03 6.97E+03 5.73E+03 releases (min)
3. Maximum time period for a 1.46E+03 7.43E+02 5.42E+02 6.88E+02 batch release (min)
4. Average time period for 4.21E+02 4.05E+02 4.10E+02 4.09E+02 batch release (min)
5. Minimum time period for a 5.40E+01 1.70E+02 2.33E+02 6.10E+01 batch release (min) 20

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2020 IX. ABNORMAL RELEASES 2020 1ST 2ND 3RD 4TH QUARTER QUARTER QUARTER QUARTER A. Liquid

1. Number of releases 2. Total activity released (Curies) B. Gaseous
1. Number of releases 2. Total activity releases (Curies) 21

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2020 ANNUAL REPORT TABLE 1A - REG GUIDE 1.21 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 1ST 2ND 3RD 4TH EST. TOTAL UNITS QUARTER QUARTER QUARTER QUARTER ERROR, %

A. FISSION AND ACTIVATION GASES

1. Total Release Ci 6.77E-01 3.99E-02 3.19E-02 2.32E-02 1.20E+01
2. Average release rate for period Ci/sec 8.58E-02 5.06E-03 4.05E-03 2.94E-03
3. Percent of ODCM limit (1)  % (1) (1) (1) (1)
4. Percent of ODCM limit (2)  % (2) (2) (2) (2)

B. IODINES

1. Total Iodine - 131 Ci <LLD <LLD <LLD <LLD 6.50E+00
2. Average release rate for period Ci/sec <LLD <LLD <LLD <LLD
3. Percent of ODCM limit  % (3) (3) (3) (3)

C. PARTICULATES

1. Particulates with half lives greater than 8 days Ci <LLD <LLD <LLD <LLD 1.20E+01
2. Average release rate for period Ci/sec <LLD <LLD <LLD <LLD
3. Percent of ODCM limit  % (3) (3) (3) (3)

D. TRITIUM

1. Total Release Ci 2.07E-01 2.28E+00 4.58E+00 1.61E+00 1.32E+01
2. Average release rate for period Ci/sec 2.62E-02 2.89E-01 5.81E-01 2.04E-01 E. GROSS ALPHA
1. Total Release Ci <LLD <LLD <LLD <LLD 2.50E+01
2. Average release rate for period Ci/sec <LLD <LLD <LLD <LLD F. Carbon-14
1. Total Release Ci 4.50E+00 5.22E+00 5.28E+00 5.28E+00 N/A
2. Average release rate for period Ci/sec 5.72E-01 6.64E-01 6.64E-01 6.64E-01 NOTES TO TABLE 1A (1) Percent of quarterly gamma-air dose limit (10 mRad) can be found in Section IV.A.2 (2) Percent of quarterly beta-air dose limit (20 mRad) can be found in Section IV.A.2 (3) Iodine, Tritium, Carbon-14, and Particulates are treated as a group. % limit can be found in Section IV.A.2 A-1

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2020 ANNUAL REPORT TABLE 1B - REG GUIDE 1.21 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE 1ST 2ND 3RD 4TH 1ST 2ND 3RD 4TH UNITS QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER

1. FISSION AND ACTIVATION GASES Argon-41 Ci <LLD <LLD <LLD <LLD 3.04E-02 2.92E-02 2.37E-02 1.80E-02 Krypton-85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Krypton-85m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Krypton-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Krypton-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xenon-131m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xenon-133 Ci 3.70E-01 <LLD <LLD <LLD 2.71E-01 1.08E-02 8.23E-03 5.15E-03 Xenon-133m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xenon-135 Ci 3.61E-03 <LLD <LLD <LLD 1.49E-03 <LLD <LLD <LLD Xenon-135m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xenon-138 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci 3.74E-01 <LLD <LLD <LLD 3.03E-01 3.99E-02 3.19E-02 2.32E-02
2. IODINES Iodine-131 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Iodine-132 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Iodine-133 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Iodine-135 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Total for Period Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

3. PARTICULATES (half life > 8 days)

Manganese-54 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Iron-55 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Iron-59 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Cobalt-58 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Cobalt-60 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Zinc-65 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Strontium-89 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Strontium-90 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Molybdenum-99 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Cesium-134 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Cesium-137 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

A-2

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2020 ANNUAL REPORT TABLE 1B - REG GUIDE 1.21 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE 1ST 2ND 3RD 4TH 1ST 2ND 3RD 4TH UNITS QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER Cerium-141 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Cerium-144 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Total for period Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

4. GROSS ALPHA RADIOACTIVITY Gross Alpha Ci <LLD <LLD <LLD <LLD N/A N/A N/A N/A
5. TRITIUM Tritium Ci 2.07E-01 2.28E+00 4.58E+00 1.61E+00 <LLD <LLD <LLD <LLD
6. Carbon-14(2)

Carbon-14 Ci 4.50E+00 5.22E+00 5.28E+00 5.28E+00 N/A N/A N/A N/A NOTES TO TABLE 1B (1) Iodines and particulates in batch releases are accounted for with the main vent continuous samplers when the release is made through the plant main vent.

(2) Carbon-14 is estimated using the methodology from EPRI Technical Report 1021106, as described in section IV.A.1.

A-3

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2020 ANNUAL REPORT TABLE 2A - REG GUIDE 1.21 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 1ST 2ND 3RD 4TH EST. TOTAL UNITS QUARTER QUARTER QUARTER QUARTER ERROR, %

A. FISSION AND ACTIVATION PRODUCTS

1. Total Release (not including tritium, gases, 2.15E-03 4.62E-04 2.45E-04 1.00E-03 alpha) Ci 1.03E+01
2. Average diluted concentration during period Ci/ml 2.04E-12 3.82E-13 2.03E-13 8.36E-13
3. Percent of ODCM limit (1)  % (1) (1) (1) (1)
4. Percent of ODCM limit (2)  % (2) (2) (2) (2)

B. TRITIUM

1. Total Release Ci 2.75E+02 1.83E+02 3.33E+02 4.53E+02 1.03E+01
2. Average diluted concentration during period Ci/ml 2.62E-07 1.52E-07 2.75E-07 3.74E-07
3. Percent of applicable limit (3)  % 8.73E-03 5.07E-03 9.17E-03 1.25E-02 C. DISSOLVED AND ENTRAINED GASES
1. Total Release Ci 7.32E-04 <LLD <LLD <LLD 1.03E+01
2. Average diluted concentration during period Ci/ml 6.98E-13 <LLD <LLD <LLD D. GROSS ALPHA RADIOACTIVITY
1. Total Release Ci <LLD <LLD <LLD <LLD N/A E. VOLUME OF WASTE RELEASED (prior to dilution)
1. Volume of waste released liters 1.10E+08 8.60E+07 8.36E+07 1.18E+08 1.30E+00 F. VOLUME OF DILUTION WATER USED liters 1.05E+12 1.21E+12 1.21E+12 1.21E+12 1.64E+01 DURING PERIOD (4)

NOTES TO TABLE 2A (1) Percent of II.C.3 Quarterly Organ Dose Limit (10 mrem) can be found in Section IV.A.2 (2) Percent of II.C.3 Quarterly Whole Body Dose Limit (3 mrem) can be found in Section IV.A.2 (3) Limit used is 3 x 10-3 Ci/ml (4) Includes dilution water used during continuous discharges.

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APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2020 ANNUAL REPORT TABLE 2B - REG GUIDE 1.21 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 1ST 2ND 3RD 4TH 1ST 2ND 3RD 4TH NUCLIDES RELEASED Units QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER Beryllium - 7 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sodium - 24 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Chromium - 51 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Manganese - 54 Ci <LLD <LLD <LLD <LLD 1.99E-05 <LLD <LLD <LLD Iron - 55 Ci (2) (2) (2) (2) 6.05E-05 <LLD <LLD 2.03E-04 Cobalt - 57 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cobalt - 58 Ci <LLD <LLD <LLD <LLD 9.35E-04 2.13E-04 4.03E-05 <LLD Iron - 59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cobalt - 60 Ci <LLD <LLD <LLD <LLD 7.99E-04 1.89E-04 1.22E-04 5.92E-04 Nickel-63 Ci <LLD <LLD <LLD <LLD 3.02E-05 <LLD <LLD 1.01E-04 Zinc - 65 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Strontium - 89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Strontium - 90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Strontium - 91 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Strontium - 92 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Niobium - 95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zirconium - 95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Niobium - 97 Ci <LLD <LLD <LLD <LLD 8.10E-06 <LLD 1.22E-05 <LLD Zirconium - 97 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Molybdenum - 99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Technetium - 99m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ruthenium - 103 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Rhodium - 105 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ruthenium - 105 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Silver - 110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Tin - 113 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Tin - 117m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Antimony - 122 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Antimony - 124 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Antimony - 125 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Tellurium - 125m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD A-5

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2020 ANNUAL REPORT TABLE 2B - REG GUIDE 1.21 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 1ST 2ND 3RD 4TH 1ST 2ND 3RD 4TH NUCLIDES RELEASED Units QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER Tellurium - 132 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Iodine - 131 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Iodine - 132 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Iodine - 133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Iodine - 135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cesium - 134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cesium - 136 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cesium - 137 Ci <LLD <LLD <LLD <LLD 2.93E-04 6.06E-05 7.07E-05 1.06E-04 Cesium - 138 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Barium - 140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Lanthanum - 140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cerium - 144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Europium - 154 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Europium - 155 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Tungsten - 187 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total For Period (F,AP) Ci <LLD <LLD <LLD <LLD 2.15E-03 4.62E-04 2.45E-04 1.00E-03 Krypton - 85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xenon - 131m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xenon - 133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xenon - 133m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xenon - 135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total For Period (NG) Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Tritium Ci 1.15E-01 1.69E-01 3.24E-01 2.72E-01 2.74E+02 1.83E+02 3.33E+02 4.52E+02 Total For Period (Tritium) Ci 1.15E-01 1.69E-01 3.24E-01 2.72E-01 2.74E+02 1.83E+02 3.33E+02 4.52E+02 NOTES TO TABLE 2B (1) Less than minimum detectable activity which meets the LLD requirements of ODCM Surveillance Requirement 4.11.1.1.1.

(2) Continuous mode effluents are not analyzed for Fe-55.

A-6

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2020 ANNUAL REPORT TABLE 3A SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

1. Type of Waste Units 12-Month Period Est. Total Error %

a) Spent resins, Filters m3 7.64E+00 25%

Ci 7.94E+01 b) Dry compressible m3 1.46E+02 25%

waste, contaminated Ci 1.20E-01 equipment, etc.

c) Irradiated components, m3 0.00E+00 N/A control rods, etc. Ci 0.00E+00 d) Other (cartridge filters, m3 8.61E+01 25%

misc. dry Ci 1.19E-02 compressible, Oil) e) Solidification agent or m3 0.00E+00 N/A absorbent Volume shipped represents waste generated prior to offsite volume reduction.

A-1

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2020 ANNUAL REPORT

5. Estimate of Major Nuclides (By Type of Waste - Only nuclides >1 % are reported)

A review of these major nuclides was performed to determine no new nuclides are present requiring an evaluation of their impact to the effluent program activity or dose. The values in these tables may not sum to 100% due to only reporting nuclides >1 % abundance.

Spent Resins, Filters Nuclide Abundance (%)

Irradiated Components Mn-54 1.12 Nuclide Abundance (%)

Fe-55 5.1 N/A Co-58 2.76 Co-60 24.51 Ni-63 14.13 Other Waste Cs-134 4.56 Nuclide Abundance%)

Cs-137 46.35 H-3 1.19 Cr-51 9.74 Mn-54 1.05 Dry Active Waste Fe-55 6.65 Nuclide Abundance (%) Co-58 8.74 Cr-51 16.09 Co-60 23.8 Mn-54 1.39 Ni-63 2.04 Fe-55 4.56 Zr-95 16.53 Co-58 19.46 Nb-95 27.79 Co-60 14.88 Cs-137 1.55 Ni-63 4.32 Zr-95 12.38 Nb-95 19.74 Cs-137 4.62

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 11 Hittman Energy Solutions Bear Creek 1560 Bear Creek Rd.

B. IRRADIATED FUEL SHIPMENTS (DISPOSITION) N/A A-1

ATTACHMENT (2)

OFFSITE DOSE CALCULATION MANUAL FOR CALVERT CLIFFS NUCLEAR POWER PLANT, CY-CA-170-301, REVISION 003 Calvert Cliffs Nuclear Power Plant July 14, 2021

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 1 of 321 Level 3 - Information OFFSITE DOSE CALCULATION MANUAL For Calvert Cliffs Nuclear Power Plant CY-CA-170-301 Revision 3 Sponsor: Manager Site Chemistry, Environmental and Radwaste Approval Authority: Plant Manager PRINT IN COLOR December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 2 of 321 Level 3 - Information EXECUTIVE

SUMMARY

OF CHANGES CHANGE IDENTIFIERS A - Administrative Changes B - Technical Changes CHANGE CHG R2 PAGE R3 PAGE DESCRIPTION TYPE

1. 1 Not Applicable A Removed the requirement for a 10 CFR 50.59/10 CFR 72.48 Applicability Determination and a 10 CFR 50.54(q)/10 CFR 72.44(f) Screening from guidance provided in LS-AA-104-1000, Exelon Resource Manual. Changes to the OCDM are controlled by reference 12 in Appendix 7.8.
2. 50 48 A Added footnote g to Table 3.12-1
3. 53 50 A Revised the following sentence Due to the geographical limitations, 9 sectors are monitored around the Calvert Cliffs Nuclear Power Plant. To Due to the geographical limitations, the number of direct radiation monitoring stations has been reduced to 9 of 16 sectors, because seven sectors are over water and therefore do not require monitoring (Developmental Reference 34).

This change was done to clarify why only 9 of 16 sectors have TLDs at site boundary.

4. Not Applicable 51 A Added the following footnote to Table 3.12-1 footnote g to provide rationale to address the logistical and historical reasons for the placement of Wa1/Wa2 sample locations:
g. The current locations, Wa1 and Wa2, represent conservative means to evaluate the relationship between quantities of radioactive material released in effluents and their presence/accumulation in the environment. These locations have been monitored since the establishment of the Preoperational Environmental Radioactivity Monitoring Program. While the sample locations do not exactly match the regulatory guidance found in NUREG-1301, the sample locations are sufficiently conservative with respect to plant releases to meet the requirements of and are compliant with 10 CFR 50 Appendix I and Appendix A, Criterion 64.
5. 57 55 A Revised note d to add the required LLD of 15 pCi/l as follows:

d LLD for drinking water samples. If no drinking water pathway exists, the LLD of GAMMA ISOTOPIC ANALYSIS (15 pCi/l) may be used.

This change was done to detail in the ODCM what the required LLD is for I-131 in surface water.

6. 173, 175 171, 173 A Changed the symbol Ki to Ri to correctly represent the formulas December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 3 of 321 Level 3 - Information CHANGE CHG R2 PAGE R3 PAGE DESCRIPTION TYPE located on pages 242-244

7. 233 231 A Added equations to Attachment 6 to show how the dose factors were calculated for the radioactive liquid effluents.
8. 233 - 235 231 - 233, A Modified the table heading from Attachment 6 Liquid Effluent Dose Factors (mrem/hr per uCi/ml) to Attachment 6 Adult -

Liquid Effluent Dose Factors (mrem/hr per uCi/ml) Saltwater Fish and Saltwater Invertebrates This was done to clarify the critical age group and ingestion pathways

9. Not Applicable 243 - 245 A Added the formulas to calculate inhalation, ground shine and ingestion dose factors for milk, vegetation and meat.
10. 265 - 274 266 - 268 A Combined the ground plane dose factor for the teenager, child and infant into one attachment, because the dose factors are the same for all age groups including the adult.
11. 311 305 A Added the following wording to Attachment 13 to clarify why direct radiation measurement devices are not located on the Chesapeake Bay.

Due to CCNPPs proximity to the Chesapeake Bay, the following sectors do not have direct radiation measurement devices as allowed by Table 3.12-1 site boundary (N, NNE, NE, ENE, E and ESE) and > 10 miles (NNW, N, NNE, NE, E and ESE).

12. Not applicable 317 - 321 A Added Attachment 25 Maximum Permissible Concentration (MPC) Values -Liquid Effluents This change was made to document in the ODCM what the MPC values are, since they were removed from 10 CFR 20, Appendix B after 1994.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 4 of 321 Level 3 - Information INTENTIONALLY BLANK December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 5 of 321 Level 3 - Information TABLE OF CONTENTS Part 1.0: PURPOSE AND APPLICABILITY/SCOPE ................................................................................. 7 Part 2.0: DEFINITIONS AND REFERENCES ........................................................................................... 9 Developmental References ..................................................................................................................... 15 Performance References......................................................................................................................... 17 Part 3.0 / 4.0: CONTROLS AND SURVEILLANCE REQUIREMENTS ................................................ 18 Monitoring Instrumentation.......................................................................................................................... 20 Radioactive Gaseous Effluent ................................................................................................................. 20 Radioactive Liquid Effluent ...................................................................................................................... 25 Radioactive Effluents .................................................................................................................................. 30 Liquid Effluents: ....................................................................................................................................... 30 Gaseous Effluents: .................................................................................................................................. 36 Total Dose ............................................................................................................................................... 43 Radiological Environmental Monitoring ....................................................................................................... 44 Program ................................................................................................................................................... 44 Land Use Census .................................................................................................................................... 56 Interlaboratory Comparison Program ...................................................................................................... 57 Part 5.0: CALCULATIONAL METHODOLOGIES ................................................................................... 58 Radioactive Liquid Effluents ........................................................................................................................ 58 Release Pathways [B527] ............................................................................................................... 58 Types of Liquid Releases ........................................................................................................................ 60 Processing Equipment............................................................................................................................. 60 Liquid Effluent Radiation Monitor Alarm and Fixed Setpoints ................................................................. 61 Limits On Radionuclide Concentrations In Liquid Effluents .................................................................... 91 Limits On Cumulative Total Body Doses And Cumulative Organ Doses For Liquid Effluents ................ 97 Limits For The Liquid Waste Processing System .................................................................................. 104 Radioactive Gaseous Effluents ................................................................................................................. 107 Release Pathways [B527] ............................................................................................................. 107 Types of Gaseous Releases ................................................................................................................. 112 Processing Equipment........................................................................................................................... 113 Gaseous Effluent Radiation Monitors And Setpoints ............................................................................ 114 Annual Total Body Dose Rate Due To Noble Gases In Gaseous Effluents .......................................... 153 Annual Skin Dose Rate Due To Noble Gases In Gaseous Effluents .................................................... 161 Annual Organ Dose Rates Due To Iodines And Particulates In Gaseous Effluents ............................. 168 Cumulative Gamma Air Doses Due To Noble Gases In Gaseous Effluents ......................................... 174 Cumulative Beta Air Doses Due To Noble Gases In Gaseous Effluents .............................................. 182 Cumulative Organ Doses Due To Iodines And Particulates In Gaseous Effluents ............................... 189 Limits For The Gaseous RadWaste Processing System ...................................................................... 196 Limits On Total Annual Dose -- Gases, Liquids, and Uranium Fuel Cycle Sources ............................. 198 Special Exceptions and Assumptions For Calculation of Doses and Dose Rates ................................ 202 Radiological Environmental Monitoring Program ...................................................................................... 204 Radiological Environmental Monitoring Program .................................................................................. 204 Land Use Census .................................................................................................................................. 209 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 6 of 321 Level 3 - Information Interlaboratory Comparison Program .................................................................................................... 211 Annual Radiological Environmental Operating Report .......................................................................... 212 Independent Spent Fuel Storage Installation Monitoring Program ....................................................... 215 Radioactive Effluent Release Report ........................................................................................................ 219 Introduction ............................................................................................................................................ 219 Responsibilities ...................................................................................................................................... 219 Report Contents .................................................................................................................................... 219 Report Submittal .................................................................................................................................... 220 Administration Of The ODCM ................................................................................................................... 221 Introduction ............................................................................................................................................ 221 Controls On The ODCM ........................................................................................................................ 221 Responsible Company Organizations ................................................................................................... 222 Initiating Conditions ............................................................................................................................... 222 Calculation Methodologies .................................................................................................................... 223 Corrective actions .................................................................................................................................. 223 Bases ........................................................................................................................................................ 223 Attachment 1 Final Grading And Drainage Plan ................................................................................ 224 Attachment 2 Sources of Liquid Radioactive Waste .......................................................................... 225 Attachment 3 Unmonitored Release Paths........................................................................................ 228 Attachment 4 Block Diagram of Liquid Radioactive Waste Systems ................................................ 229 Attachment 5 Radionuclides in Typical Radwaste Discharges ......................................................... 230 Attachment 6 Adult - Liquid Effluent Dose Factors (mrem/hr per uCi/ml) Saltwater Fish and Saltwater Invertebrates ...................................................................................................................... 231 Attachment 7 General Information Related to Gaseous Releases via the Main Vents ..................... 234 Attachment 8 General Information Related to Gaseous Releases via Pathways other than the Main Vents ................................................................................................................................... 235 Attachment 9 Block Diagram of Gaseous Radioactive Waste Systems ............................................ 236 Attachment 10 Noble Gas Dose Factors ........................................................................................... 237 Attachment 11 Empirical Derivation Of Site-Specific Dose Factors .................................................. 238 Attachment 12 Gaseous Effluent Pathway Dose Factors.................................................................. 243 Attachment 13 Environmental Monitoring Sites for REMP ................................................................ 305 Attachment 14 Radiological Environmental Monitoring Program Surveillances for Direct Radiation ............................................................................................................................................ 306 Attachment 15 Radiological Environmental Monitoring Program Surveillances for Airborne Activity ................................................................................................................................................ 307 Attachment 16 Radiological Environmental Monitoring Program Surveillances for Waterborne Activity ................................................................................................................................................ 308 Attachment 17 Radiological Environmental Monitoring Program Surveillances for Ingestible Activity ................................................................................................................................................ 309 Attachment 18 Map of Environmental Monitoring Sites for REMP (5 Km Radius) ............................ 310 Attachment 19 Map of Environmental Monitoring Sites for REMP (10 Mile Radius) ........................ 311 Attachment 20 Environmental Monitoring Sites for ISFSI ................................................................. 312 Attachment 21 Map of Environmental Monitoring Sites for ISFSI ..................................................... 313 Attachment 22 Map of Environmental Monitoring Sites for ISFSI ..................................................... 314 Attachment 23 Effluent Radiation Monitors ....................................................................................... 315 Attachment 24 Atmospheric Stability Classes ................................................................................... 316 Attachment 25 Maximum Permissible Concentration (MPC) Values - Liquid Effluents .................. 317 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 7 of 321 Level 3 - Information PART 1.0: PURPOSE AND APPLICABILITY/SCOPE PURPOSE A. The ODCM lists the radiological effluent controls established by Technical Specifications 5.5.1 and 5.5.4 at Calvert Cliffs Nuclear Power Plant (CCNPP) for the purpose of ensuring the amount of radioactive materials released to the environment are as low as reasonably achievable.

B. The ODCM defines parameters and methodologies for calculating projected doses and dose rates resulting from the release of radioactive materials in liquid and gaseous effluents.

C. The ODCM defines parameters and methodologies for calculating alarm and fixed setpoints for Technical Specification related effluent radiation monitoring systems.

D. The ODCM defines and establishes controls for the Radiological Environmental Monitoring Program.

APPLICABILITY/SCOPE A. The information presented in this manual is applicable to any division, department, section, or unit within the Calvert Cliffs Nuclear Power Plant (CCNPP) which is either wholly or partly responsible for performing any of the activities listed in the PURPOSES section of this procedure. Responsible organizations include, but are not limited to, the following:

1. CCNPP, Chemistry Operations
2. CCNPP, Electrical Maintenance
3. CCNPP, I&C Maintenance
4. CCNPP, Operations
5. CCNPP, Radiation Protection Operations B. This manual is applicable to the determination of alarm and fixed setpoints for the following radioactive gaseous effluent monitoring instrumentation:
1. 0-RE-2191
2. 1/2-RE-5415
3. 1/2-RE-5416A December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 8 of 321 Level 3 - Information C. This manual is applicable to the determination of alarm and fixed setpoints for the following radioactive liquid effluent monitoring instrumentation:

1. 0-RE-2201
2. 1/2-RE-4014
3. 1/2-RE-4095 D. This manual is applicable to the determination of the offsite doses and/or offsite dose rates due to the following:
1. Radioactive material in gaseous waste discharged from CCNPP
2. Radioactive material in liquid waste discharged from CCNPP
3. Radioactive material contained in outside storage tanks at CCNPP E. This manual is applicable to the determination of the radiological effects on the environment due to the presence of CCNPP (including the Independent Spent Fuel Storage Installation (ISFSI).

F. The ODCM is based on Technical Specifications and CCNPPs interpretation of industry standards and practices.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 9 of 321 Level 3 - Information PART 2.0: DEFINITIONS AND REFERENCES DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout these Controls.

ABNORMAL AND/OR UNANTICIPATED RADIOACTIVE RELEASE:

Any unplanned or uncontrolled release of radioactive material from the SITE BOUNDARY.

ACTION:

That part of a control which prescribes remedial measures required under designated conditions.

BATCH RELEASE:

A BATCH RELEASE is the discharge of liquid (or gaseous) waste of a discrete volume.

(NUREG-0133, page 14)

CHANNEL CALIBRATION:

A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, 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.

CHANNEL CHECK:

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.

CHANNEL FUNCTIONAL TEST:

a. An analog CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.
b. A bistable CHANNEL FUNCTIONAL TEST shall be injection of a simulated signal into the channel sensor to verify OPERABILITY including alarm and/or trip functions.

COMPOSITE SAMPLE:

A COMPOSITE SAMPLE is a combination of individual samples obtained at intervals that are very short (for example, hourly) in relation to the compositing time interval (for example, monthly) to assure obtaining a representative sample. The sample volume should be proportionate to the volume of fluid, either liquid or gas, flowing through the system.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 10 of 321 Level 3 - Information CONTINUOUS RELEASE A CONTINUOUS RELEASE is the discharge of liquid (or gaseous) wastes of a nondiscreet volume; for example, from a volume or system that has an input flow during the CONTINUOUS RELEASE.

(NUREG-0133, P. 14.)

CONTINUOUS SAMPLING FREQUENCY A CONTINUOUS SAMPLING FREQUENCY is a sampling arrangement that provides for uninterrupted sampling flow under normal operating conditions. During periods of sampling interruption, the requirement for continuous sampling is considered to be met, provided the interruption is less than one hour AND plant conditions are such that no adverse trend in effluents would be present during the period of interruption. Interruptions in continuous sampling during changing plant conditions OR interruptions in continuous sampling for greater than one hour must be evaluated to determine if an ODCM violation has occurred.

DOSE EQUIVALENT IODINE-131:

DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries per gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The TEDE (Total Effective Dose Equivalent) inhalation dose conversion factors used for this calculation shall be those listed in the Table 2.1 in the Column headed effective of Federal Guidance Report 11, ORNL, 1988, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 11 of 321 Level 3 - Information FREQUENCY NOTATION:

The frequency notation specified for the performance of Surveillance Requirements shall correspond to the intervals defined in the following Table.

Frequency Notation Table NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W At least once per 7 days M At least once per 31 days Q At least once per 92 days SA At least once per 6 months A At least once per 12 months R At least once per 18 months S/U Before each reactor startup P Completed before each release N.A. Not applicable Refueling Interval At least once per 24 months December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 12 of 321 Level 3 - Information GAMMA ISOTOPIC ANALYSIS:

A GAMMA ISOTOPIC ANALYSIS is an analytical method of measurement used for the identification and quantification of gamma-emitting radionuclides.

GASEOUS RADWASTE PROCESSING SYSTEM:

A GASEOUS RADWASTE PROCESSING SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity before release to the environment.

LIQUID RADWASTE PROCESSING SYSTEM:

A LIQUID RADWASTE PROCESSING SYSTEM is the system installed and designed to reduce radioactive liquid effluents. The minimum components necessary for reducing liquid radioactive effluents is either 13 or 14 Reactor Coolant Waste Ion Exchange; however, other equipment in the system may be used in the maintenance of ALARA for liquid radioactive effluents.

LOWER LIMIT OF DETECTION:

The LLD is 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.

MEMBERS OF THE PUBLIC:

MEMBERS OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

OFFSITE DOSE CALCULATION MANUAL:

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 and fixed setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain the radioactive effluent controls, radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Specification 5.6.2 and 5.6.3.

OPERABILITY:

A system, subsystem, train, component or device shall be operable or have OPERABILITY when it is capable of performing its specified function(s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other required auxiliary equipment that are required for the system, subcomponent or device to perform its function(s) are also capable of performing their related support function(s).

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 13 of 321 Level 3 - Information OPERATIONAL MODE:

An OPERATIONAL MODE shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified below.

Operational Modes REACTIVITY  % RATED AVERAGE COOLANT MODE CONDITION, Keff THERMAL TEMPERATURE POWER*

POWER 0.99 >5% 300 ºF OPERATION STARTUP 0.99 5% 300 ºF HOT STANDBY <0.99 0 300 ºF HOT SHUTDOWN <0.99 0 300 ºF > T avg > 200

ºF COLD SHUTDOWN <0.99 0 200 ºF REFUELING** 0.95 0 140 ºF

  • Excluding decay heat.
    • Reactor vessel head unbolted or removed and fuel in the vessel.

PROCESS CONTROL PROGRAM:

PROCESS CONTROL PROGRAM shall contain the current formula, sampling, analyses, tests, and determinations to be made to ensure that the 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 10 CFR Part 20, 10 CFR Part 71 and Federal and State and Local regulations governing the disposal of the radioactive waste.

PROJECTED DOSE:

A reasonable estimate of dose expected as a result of future radioactive releases.

PURGE OR PURGING:

PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RATED THERMAL POWER:

RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2737 MWt.

SIMULTANEOUS RELEASES:

Simultaneous liquid releases are discharges of liquid radwaste which occur at the same time.

Simultaneous gaseous releases are discharges of gaseous radwaste which occur at the same time excluding main vent discharges.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 14 of 321 Level 3 - Information SITE BOUNDARY:

The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

(The SITE BOUNDARY is depicted on Attachment 18, Environmental Monitoring Sites)

SOURCE CHECK:

A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

THERMAL POWER:

The THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TYPICAL RADWASTE RELEASES (OR TYPICAL RADWASTE EFFLUENTS):

TYPICAL RADWASTE RELEASES are defined as (1) all releases conducted during any calendar quarter while either Unit 1 or Unit 2 is in mode 1, and also includes (2) all releases conducted during any calendar quarter following mode 1 operation of either Unit 1 or Unit 2.

UNRESTRICTED AREA:

An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters of/for industrial, commercial, institutional, and/or recreational purposes.

VENTILATION EXHAUST PROCESSING SYSTEM:

A VENTILATION EXHAUST PROCESSING SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or High Efficiency Particulate Air (HEPA) filters for the purpose of removing iodines or particulates from the gaseous exhaust stream before the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING:

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 or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.

WASTE GAS HOLDUP SYSTEM:

See GASEOUS RADWASTE PROCESSING SYSTEM.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 15 of 321 Level 3 - Information REFERENCES DEVELOPMENTAL REFERENCES

1. NUREG-0133, Preparation of Radiological Effluent Technical Specification For Nuclear Power Plants, Boegli, J.S., R. R. Bellamy, W. L. Britz, and R. L. Waterfield, (October 1978)
2. Regulatory Guide 1.109, Calculation Of Annual Doses To Man From Routine Release Of Reactor Effluents For The Purpose Of Compliance With 10 CFR Part 50, Appendix I, Revision 1, (October 1977)
3. Regulatory Guide 1.111, Methods For Estimating Atmospheric Transport And Dispersion Of Gaseous Effluents In Routine Releases From Light-Water-Cooled Reactors, Revision 1, (July 1977)
4. Reference Deleted
5. Updated Final Safety Analysis Report, Chapter 11, Waste Processing And Radiation Protection
7. Reference Deleted
8. Title 10 of the Code of Federal Regulations, Part 20, Jan 1990 and May 1991
9. Title 10 of the Code of Federal Regulations, Part 50
10. Calvert Cliffs Nuclear Power Plant Semi-Annual Radiological Effluent Release Report (1986, 1987, 1988)
11. Radioactive Decay Data Tables, David C. Kocher, 1981
12. Radiological Health Handbook, Bureau of Radiological Health, Jan. 1970
13. TE-001, Main Vent Stack Flow Measurement
14. ETP-87-16, Main Vent Stack Flow Measurement
15. Verification And Validation Of The Gaseous Release Permit Portion Of The CCNPP EMS Computer Code, J. S. Bland And Associates, July 10, 1990
16. Reference Deleted December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 16 of 321 Level 3 - Information DEVELOPMENTAL REFERENCES (Continued)

17. Reference Deleted
18. NO-1-201, Calvert Cliffs Operating Manual
19. TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites
20. Plant Data Book, BGE CCNPP Units 1 and 2, Bechtel Power Corporation, Volume 1, Job 6750 21 50.59 Log No. 82-B-999-028-R00, Safety Analysis No. 2, FCR 82-1053, Supplement 1 (Component Cooling System) [B527]
22. 50.59 Log No. 90-0-074-011-R2, Activity MASE 90-7 (Plant Nitrogen System)

[B527]

23. 50.59 Log No. 90-0-029-045-R1, Activity MASE 90-6 (Plant Heating System)

[B527]

24. 50.59 Log No. 90-0-037-044-R1, Activity MASE 90-5 (Demineralized Water System) [B527]
25. 50.59 Log No. 90-B-012-043-R1, Activity MASE 90-4 (Service Water System)

[B527]

26. 50.59 Log No. 90-0-027-037-R2, Activity MASE 90-8 (Auxiliary Boiler System)

[B527]

27. Bechtel Power Corporation, Calculation Number M-90-20, Allowable Radioactive Contamination Levels in the Plant Heating System [B527]
28. Bechtel Power Corporation, Calculation Number M-90-18, Allowable Radioactive Contamination Levels in the Nitrogen System Header [B527]
29. Bechtel Power Corporation, Calculation Number M-90-04, Allowable Radioactive Contamination Levels in Auxiliary Boiler Water [B527]
30. Bechtel Power Corporation, Calculation Number M-90-21, Allowable Radioactive Contamination Levels in the Demineralized Water System [B527]
31. Bechtel Power Corporation, Calculation Number M-90-19, Allowable Radioactive Contamination Levels in the Service Water System [B527]
32. Bechtel Power Corporation, Job Number 11865, Calculation Number 7.4.3-15, Allowable Radioactive Contamination Levels in the Condensate Storage Tank

[B527]

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 17 of 321 Level 3 - Information DEVELOPMENTAL REFERENCES (CONTINUED)

33. Reference Deleted
34. NUREG-1301, OFFSITE DOSE CALCULATION MANUAL: Standard Radiological Effluent Controls for Pressurized Water Reactors, W. W. Meinke, and T. H., (Published April 1991)
36. Radiological Environmental Monitoring Program Annual Report for the Calvert Cliffs Nuclear Power Plant Units 1 and 2 January 1 - December 31, 1991, Baltimore Gas And Electric Company, March 1992
37. 50.59 Log No. 90-B-037-120-R2, Activity MASE 90-11 (Condensate Storage Tank) [B527]
38. Regulatory Guide 4.13, Performance Testing and Procedural Specifications for Thermoluminescence Dosimetry; Environmental Applications PERFORMANCE REFERENCES
1. Reference Deleted
2. OI-8A, Blowdown System
3. OI-17D, Miscellaneous Waste Processing System
4. OI-17C, Reactor Coolant Waste Processing System
5. STP-M-462-1 and STP-M-462-2, Main Vent Stack Flow Measurement
6. Technical Specifications
7. Technical Requirements Manual
8. Regulatory Guide 4.13, Performance Testing and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications
9. TE-006, Containment Purge Exhaust System HEPA Filter Test
10. CY-AA-170-000, Radioactive Effluent and Environmental Monitoring Programs
11. CY-AA-170-300, Offsite Dose Calculation Manual Administration
12. CY-AA-170-3100, Offsite Dose Calculation Manual Revisions December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 18 of 321 Level 3 - Information PART 3.0 / 4.0: CONTROLS AND SURVEILLANCE REQUIREMENTS CONTROLS 3.0.1 Compliance with the Controls contained in the succeeding controls is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Control, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a Control shall exist when the requirements of the Control and associated ACTION requirements are not met within the specified time intervals. If the Control is restored before expiration of the specified time intervals, completion of the ACTION requirements is not required.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 19 of 321 Level 3 - Information SURVEILLANCE 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Control unless otherwise stated in an individual Surveillance Requirement.

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

4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Control 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Control. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. However, this time of applicability may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement(s) associated with the Control have been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 20 of 321 Level 3 - Information MONITORING INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT CONTROLS 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm or alarm-with-automatic-termination setpoints set to ensure that the limits of Control 3.11.2.1 are not exceeded. The setpoints of these channels shall be determined and adjusted per the methodology and parameters in the ODCM.

APPLICABILITY: As shown in Table 3.3-12.

ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm setpoint less conservative than required by the above Control, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.

Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-11.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 21 of 321 Level 3 - Information TABLE 3.3-12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. WASTE GAS HOLDUP SYSTEM
a. Noble Gas Activity Monitor - Providing 1
  • 35 Alarm and Automatic Termination of Release
b. Effluent System Flow Rate Measuring 1
  • 36 Device
2. MAIN VENT SYSTEM
a. Noble Gas Activity Monitor 1
  • 37
b. Iodine Sampler 1
  • 38
c. Particulate Sampler 1
  • 38
d. Tritium Sampler 1
  • 38 At all times December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 22 of 321 Level 3 - Information TABLE 3.3-12 (Continued)

ACTION STATEMENTS ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment:

a. Using the main vent monitor as a backup and recording RMS readings every 15 minutes during the release, or
b. Provided that before initiating the release, at least two independent samples of the tank's contents are analyzed, and at least two technically qualified members of the Facility Staff independently verify the release rate calculations and two qualified operators verify the discharge valve lineup.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided either (1) grab samples are taken and analyzed for gross activity at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or (2) an equivalent monitor is provided.

ACTION 38 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided samples are continuously collected as required in Table 4.11-2 with auxiliary sampling equipment.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 23 of 321 Level 3 - Information TABLE 4.3-11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS MODES IN CHANNEL CHANNEL SOURCE CHANNEL WHICH INSTRUMENT FUNCTIONAL CHECK CHECK CALIBRATION SURVEILLANCE TEST REQUIRED

1. WASTE GAS HOLDUP SYSTEM
a. Noble Gas Activity P P R(3) SA(1)
  • Monitor - Providing Alarm and Automatic Termination of Release
b. Effluent System Flow D(4) NA R NA
  • Rate Measuring Device
2. MAIN VENT SYSTEM
a. 1/2-RE-5416A D M R(3) SA(2) *

(WRNGM)

b. 1/2-RE-5415 (Main Vent D M R(3) SA(2)
c. Iodine Sampler W NA NA NA *
d. Particulate Sampler W NA NA NA *
e. Tritium Sampler W NA NA NA *
f. Iodine, Particulate, and NA NA A NA
g. Main Vent Flow Rate(5) NA NA SA NA NA At all times other than when the line is valved out and locked.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 24 of 321 Level 3 - Information TABLE 4.3-11 (Continued)

TABLE NOTATION (1)

The CHANNEL FUNCTIONAL TEST shall also demonstrate the automatic isolation of this pathway and/or Control Room alarm annunciation occurs if the appropriate following condition(s) exists:

1. Instrument indicates measured levels above the alarm-with-automatic-termination setpoint.
2. Circuit failure.
3. Instrument indicates a downscale failure.

(2)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm setpoint.
2. Circuit failure.
3. Instrument indicates a downscale failure.

(3)

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards traceable to NIST or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system within its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration can be used.

(4)

The CHANNEL CHECK shall consist of verifying indication of flow during periods of release and shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during periods in which effluent releases are made.

(5)

Main Vent flow rates are determined through the performance of STP-M-462-1 and STP-M-462-2. There is no online instrumentation for Main Vent flow rate monitoring.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 25 of 321 Level 3 - Information RADIOACTIVE LIQUID EFFLUENT CONTROLS 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm or alarm-with-automatic-termination setpoints set to ensure that the limits of Control 3.11.1.1 are not exceeded. The setpoints of these channels shall be determined and adjusted per the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: As shown in Table 3.3-13.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Control, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.

Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-12.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 26 of 321 Level 3 - Information TABLE 3.3-13 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM INSTRUMENT CHANNELS APPLICABILITY ACTION OPERABLE

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
a. Liquid Radwaste Effluent Line 1 (2) 28
b. Steam Generator Blowdown Effluent Line 1 (2) 29
2. FLOW RATE MEASUREMENT DEVICES
a. Liquid Radwaste Effluent Line 1 (1) 30
b. Steam Generator Blowdown Effluent Line 1 (2) 30 Note: (1) At all times.

(2) At all times while process flow is present.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 27 of 321 Level 3 - Information TABLE 3.3-13 (Continued)

ACTION STATEMENTS ACTION 28 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that before initiating a release:

a. At least two independent samples are analyzed per Control 4.11.1.1.1, AND
b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and two qualified operators verify the discharge valve line up.

ACTION 29 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at the LOWER LIMIT OF DETECTION defined in Table 4.11-1:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcurie/gram DOSE EQUIVALENT I-131.
b. At least once per 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie/gram DOSE EQUIVALENT I-131.

ACTION 30 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump performance curves may be used to estimate flow.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 28 of 321 Level 3 - Information TABLE 4.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CHANNEL CHANNEL SOURCE CHANNEL INSTRUMENT FUNCTIONAL CHECK CHECK CALIBRATION TEST

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
a. Liquid Radwaste Effluent Line D P R(2) SA(1)
b. Steam Generator Blowdown Effluent D P R(2) SA(1)

Line

2. FLOW RATE MEASUREMENT DEVICES
a. Liquid Radwaste Effluent Line D(3) NA R NA
b. Steam Generator Blowdown Effluent D(3) NA R NA Line December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 29 of 321 Level 3 - Information TABLE 4.3-12 (Continued)

TABLE NOTATION (1)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and/or Control Room alarm annunciation occur if the appropriate following condition(s) exists:

1. Instrument indicates measured levels above the alarm or fixed setpoint.
2. Circuit failure.
3. Instrument indicates a downscale failure.

(2)

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards traceable to NIST or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system within its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration can be used.

(3)

CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during periods in which effluent releases are made.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 30 of 321 Level 3 - Information RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS:

Concentration CONTROLS 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.

APPLICABILITY: At all times.

ACTION:

a. With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, without delay restore the concentration to within the above limits.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1.

4.11.1.1.2 The results of the radioactivity analyses shall be used per the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 31 of 321 Level 3 - Information TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT OF LIQUID ANALYSIS TYPE OF ACTIVITY SAMPLING DETECTION RELEASE TYPE FREQUENCY ANALYSIS FREQUENCY (LLD)a (µCi/ml)

A. Batch Waste P P Principal Gamma 5x10-7 Releasesb Each Batch Each Batch Emittersc I-131 1x10-6 Mo-99, Ce-144 2x10-6 P M H-3 1x10-5 Each Batch Composited Gross Alpha 1x10-7 P Q Each Batch Composited Sr-89, Sr-90 5x10-8 B. Turbine M M Principal Gamma 5x10-7 Building Emittersc Sump I-131 1x10-6 Mo-99, Ce-144 2x10-6 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 32 of 321 Level 3 - Information TABLE 4.11-1 (Continued)

TABLE NOTATION a

The LLD is defined, for purposes of these controls, 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:

4.66 sb LLD =

E

  • V
  • 2.22 x 106
  • Y
  • exp(- t)

Where:

LLD is the a priori LOWER LIMIT OF DETECTION as defined above, as microcuries per unit mass or volume, sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, is the radioactive decay constant for the particular radionuclide, and t is the elapsed time between sample collection, or end of the sample collection period, and time of counting.

Typical values of E, V, Y, and t should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 33 of 321 Level 3 - Information TABLE 4.11-1 (Continued)

TABLE NOTATION b

Before sampling Reactor Coolant Waste and Miscellaneous Waste for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

c The principal gamma emitters for which the LLD control applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, Cs-137 and Ce-141. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3.

d A COMPOSITE SAMPLE is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged in which the method of sampling employed results in a specimen that is representative of the liquids released.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 34 of 321 Level 3 - Information LIQUID EFFLUENTS:

Dose CONTROLS 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS shall be limited:

a. During any calendar quarter to less than or equal to 3.0 mrems to the total body and to less than or equal to 10 mrems to any organ, and
b. During any calendar year to less than or equal to 6 mrems to the total body and to less than or equal to 20 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission pursuant to 10 CFR 50.4 within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective ACTIONS that have been taken to reduce the releases and the proposed corrective ACTIONS to be taken to assure that subsequent releases will be in compliance with the above limits.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined per the methodology and parameters in the ODCM at least once per 31 days.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 35 of 321 Level 3 - Information LIQUID EFFLUENTS:

Liquid Radwaste Processing System CONTROLS 3.11.1.3 The LIQUID RADWASTE PROCESSING SYSTEM shall be used to reduce the radioactive materials in liquid wastes before their discharge when the calculated doses due to the liquid effluent to UNRESTRICTED AREAS exceeds 0.36 mrem to the total body or 1.20 mrem to any organ in a 92 day period.

APPLICABILITY: At all times.

ACTION:

a. With radioactive liquid waste being discharged without processing and in excess of the above limits, prepare and submit to the Commission pursuant to 10 CFR 50.4 within 30 days a Special Report that includes the following information:
1. Explanation of why liquid radwaste was being discharged without processing, identification of any inoperable equipment or subsystems, and the reason for the inoperability,
2. ACTION(s) taken to restore the inoperable equipment to OPERABLE status, and
3. Summary description of ACTION(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS 4.11.1.3 Doses over a 92-day period due to liquid releases to UNRESTRICTED AREAS shall be calculated at least once per 31 days per the methodology and parameters in the ODCM.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 36 of 321 Level 3 - Information GASEOUS EFFLUENTS:

Dose Rate CONTROLS 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see figure in UFSAR Chapter 1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and
b. For Iodine-131 and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the dose rate(s) exceeding the above limits, without delay restore the release rate to within the above limit(s).

SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits per the methodology and parameters in the ODCM.

4.11.2.1.2 The dose rate due to Iodine-131 and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents shall be determined to be within the above limits per the methodology and parameters in the ODCM by obtaining representative samples and performing analyses per the sampling and analysis program specified in Table 4.11-2.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 37 of 321 Level 3 - Information TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TYPE OF LOWER LIMIT MINIMUM GASEOUS SAMPLING ACTIVITY OF DETECTION ANALYSIS RELEASE TYPE FREQUENCY ANALYSIS (LLD)a FREQUENCY

µCi/ml A. Waste Gas P P Principal Gamma 1 x 10-4 Storagef Tank Each Tank Each Tank Emitters b Grab Sample (Gaseous Emissions Only)

B. Containment P P Principal Gamma 1 x 10-4 Purge and Each Batch Each Batch Emitters b Vent Grab Sample (Gaseous Emissions Only)

C. Main Vent M c M c Principal Gamma 1 x 10-4 Grab Sample Emittersb (Gaseous Emissions Only)

Continuousd M H-3 1 x 10-6 Continuousd W I-131 1 x 10-12 Charcoal Samplee Continuousd W Principal Gamma 1 x 10-11 Particulate Emittersb Samplee (I-131, others)

Continuousd M Gross Alpha 1 x 10-11 Composite Particulate Sample Continuousd Q Sr-89, Sr90 1 x 10-11 Composite Particulate Sample Continuousd Noble Gas Noble Gases 1 x 10-6 Monitor Gross Beta or Gamma D. Incinerated P P Principal Gamma 5 x 10-7 Oilg Each Batchh Each Batchh Emitters December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 38 of 321 Level 3 - Information TABLE 4.11-2 (Continued)

TABLE NOTATION a The LLD is defined, for purposes of these controls, 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:

4.66 sb LLD =

E

  • V
  • 2.22 x 106
  • Y
  • exp (- t)

Where:

LLD is the a priori LOWER LIMIT OF DETECTION as defined above, as microcuries per unit mass or volume, sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, is the radioactive decay constant for the particular radionuclide, and t for plant effluents is the elapsed time between sample collection or end of the sample collection period, and time of counting.

Typical values of E, V, Y, and t should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 39 of 321 Level 3 - Information TABLE 4.11-2 (Continued)

TABLE NOTATION b

The principal gamma emitters for which the LLD control applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3.

c Sampling and analysis shall also be performed following shutdown, STARTUP, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 5.

d The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made per Controls 3.11.2.1, 3.11.2.2 and 3.11.2.3.

e Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler. When sample collection time is less than seven days, the corresponding LLDs may be increased by a proportional factor.

f Collect sample and analyze daily for total Curie content per Technical Requirements Manual 15.11.2.1 when the Reactor Coolant System specific activity of Xe-133 is greater than 150 uCi/ml.

g Incinerated oil may be discharged via points other than the main vent (for example, Auxiliary Boiler). Releases shall be accounted for based on pre-release grab sample data.

h Samples for incinerated oil releases shall be collected from and representative of filtered oil in liquid form.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 40 of 321 Level 3 - Information GASEOUS EFFLUENTS:

Dose - Noble Gases CONTROLS 3.11.2.2 The air dose due to noble gases released in gaseous effluents to areas at and beyond the SITE BOUNDARY (see figure in UFSAR Chapter 1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation and,
b. During any calendar year: Less than or equal to 20 mrads for gamma radiation and less than or equal to 40 mrads for beta radiation.

APPLICABILITY: At all times.

ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission pursuant to 10 CFR 50.4 within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective ACTIONS that have been taken to reduce the releases and the proposed corrective ACTIONS to be taken to assure that subsequent releases will be in compliance with the above limits.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined per the methodology and parameters in the ODCM at least once per 31 days.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 41 of 321 Level 3 - Information GASEOUS EFFLUENTS:

Dose - Iodine-131 & Radionuclides in Particulate Form CONTROLS 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from Iodine-131 and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY (see figure in UFSAR Chapter 1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 15 mrems to any organ and,
b. During any calendar year: Less than or equal to 30 mrems to any organ.
c. Less than 0.1% of the limits of 3.11.2.3(a) and (b) as a result of burning contaminated oil.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of Iodine-131 and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission pursuant to 10 CFR 50.4 within 30 days a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective ACTIONS that have been taken to reduce the releases and the proposed corrective ACTIONS to be taken to assure that subsequent releases will be in compliance with the above limits.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and the current calendar year for Iodine-131 and radionuclides in particulate form with half lives greater than 8 days shall be determined per the methodology and parameters in the ODCM at least once per 31 days.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 42 of 321 Level 3 - Information GASEOUS EFFLUENTS:

Gaseous Radwaste Processing System CONTROLS 3.11.2.4 The GASEOUS RADWASTE PROCESSING SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste before their discharge when the gaseous effluent air doses due to gaseous effluent releases, to areas at and beyond the SITE BOUNDARY (see figure in UFSAR Chapter 1) exceeds 1.20 mrad for gamma radiation and 2.4 mrad for beta radiation in a 92 day period. The VENTILATION EXHAUST PROCESSING SYSTEM shall be used to reduce radioactive materials in gaseous waste before their discharge when the calculated doses due to gaseous effluent releases, to areas at and beyond the SITE BOUNDARY (see figure in UFSAR Chapter 1) exceeds 1.8 mrem to any organ in a 92 day period.

APPLICABILITY: At all times.

ACTION:

a. With gaseous waste being discharged without processing and in excess of the above limits, prepare and submit to the Commission pursuant to 10 CFR 50.4 within 30 days a Special Report that includes the following information:
1. Explanation of why gaseous radwaste was being discharged without processing, identification of any inoperable equipment or subsystems, and the reason for the inoperability,
2. ACTION(s) taken to restore the inoperable equipment to OPERABLE status, and
3. Summary description of ACTION(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS 4.11.2.4 Doses over a 92-day period due to gaseous releases shall be calculated at least once per 31 days per the methods and parameters in the ODCM.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 43 of 321 Level 3 - Information TOTAL DOSE CONTROLS 3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY: At all times.

ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Control 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, calculations shall be made including direct radiation contributions from the reactor units and outside storage tanks to determine whether the above limits of Control 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commission pursuant to 10 CFR 50.4 within 30 days a Special Report that defines the corrective ACTION to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance per the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff ACTION on the request is complete.

SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined per Controls 4.11.1.2, 4.11.2.2, and 4.11.2.3, and per the methods and parameters in the ODCM.

4.11.4.2 Cumulative dose contributions from direct radiation from the reactor units and outside storage tanks shall be determined per the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in Control 3.11.4.a.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 44 of 321 Level 3 - Information RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CONTROLS 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a. With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Technical Specification 5.6.2, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
b. With the level of radioactivity as the result of plant effluents in an environmental sample at a specified location exceeding the reporting levels of Table 3.12-2, prepare and submit to the Commission pursuant to 10 CFR 50.4 within 30 days after receiving the sample analysis a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective ACTIONS to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits of Controls 3.11.1.2, 3.11.2.2, and 3.11.2.3. When more than one of the radionuclides in Table 3.12-2 are detected in the sample this report shall be submitted if:

concentration (1) concentration (2)

+ + ...> 1.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 3.12-2 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 is equal to or greater than the calendar year limits of Controls 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

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

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 45 of 321 Level 3 - Information

c. With fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Technical Specification 5.6.2, identify the cause of the unavailability of samples and identify the new location(s) for obtaining the replacement samples in the next Annual Radiological Environmental Operating Report.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and figure(s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 46 of 321 Level 3 - Information TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND EXPOSURE PATHWAY SAMPLES AND SAMPLE COLLECTION FREQUENCY AND/OR SAMPLE LOCATIONSa FREQUENCY OF ANALYSIS

1. DIRECT RADIATIONb 23 routine monitoring stations At least Quarterly Gamma dose at (DR1 - DR23) either with two or least quarterly more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:

An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY (DR1 - DR09);f An outer ring of stations, one in each meteorological sector in the 6- to 8-km range from the site (DR10 - DR18);

The remaining stations (DR19 - DR23) to be placed in special interest areas such as population centers, nearby residences, schools, and in 1 area to serve as a control station.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 47 of 321 Level 3 - Information TABLE 3.12-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND EXPOSURE PATHWAY SAMPLES AND SAMPLE COLLECTION FREQUENCY AND/OR SAMPLE LOCATIONSa FREQUENCY OF ANALYSIS

2. AIRBORNE Radioiodine and Samples from 5 locations (A1-A5): Continuous Radioiodine Particulates sampler operation Canister Three samples (A1-A3) from with sample I-131 analysis close to the 3 SITE collection weekly, weekly.

BOUNDARY locations, in or more frequently different sectors of the highest if required by dust Particulate calculated annual average loading. Sampler:

ground-level D/Q. f Gross beta radioactivity One sample (A4) from the analysis vicinity of a community having following filter the highest calculated annual change;c Gamma average ground-level D/Q. isotopic analysisd of composite One sample (A5) from a control (by location) location, as for example 15-30 quarterly km distant and in the least prevalent wind direction.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 48 of 321 Level 3 - Information TABLE 3.12-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND AND/OR SAMPLE SAMPLES AND SAMPLE COLLECTION FREQUENCY LOCATIONSa FREQUENCY OF ANALYSIS

3. WATERBORNE
a. Surface One sample at intake area (Wa1) COMPOSITE GAMMA One sample at discharge area SAMPLE over ISOTOPIC (Wa2) g 1-month periode ANALYSISd Monthly.

Composite for tritium analysis quarterly

b. Sediment from One sample from downstream area Semiannually GAMMA shoreline with existing or potential ISOTOPIC recreational value. (Wb1) ANALYSISd Semiannually December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 49 of 321 Level 3 - Information TABLE 3.12-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND EXPOSURE PATHWAY SAMPLES AND SAMPLE COLLECTION FREQUENCY AND/OR SAMPLE LOCATIONSa FREQUENCY OF ANALYSIS

4. INGESTION
a. Fish and Three samples of commercially Sample in season, GAMMA Invertebrates and/or recreationally important or semiannually if ISOTOPIC species (2 fish species and 1 they are not ANALYSISd on invertebrate species) in vicinity of seasonal edible portions plant discharge area (Ia1-Ia3).

Three samples of same species in areas not influenced by plant discharge (Ia4-Ia6).

b. Food Products Samples of 3 different kinds of Monthly during Gamma isotopicd broad leaf vegetation grown near growing season and I-131 analysis the SITE BOUNDARY at 2 different locations of highest predicted annual average ground level D/Q (Ib1-Ib6). f One sample of each of the similar Monthly during Gamma isotopicd broad leaf vegetation grown 15-30 growing season and I-131 analysis km distant in the least prevalent wind direction (Ib7-Ib9).

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 50 of 321 Level 3 - Information TABLE 3.12-1 (Continued)

TABLE NOTATION a.

The code in parenthesis, for example, DR1, A1, defines generic sample locations in this control that can be used to identify the specific locations in the map(s) and table in the ODCM. Actual sample location designations can be found in Attachment 13. Specific parameters of distance and direction sector from the central point between the two containment buildings and additional description where pertinent, is provided for each sample location in Table 3.12-1, and in a table and figure(s) in the ODCM (see Attachments 13, 18 and 19). 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.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective ACTION before the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program.

Pursuant to Technical Specification 5.6.2, identify the cause of the unavailability of samples for that pathway and identify the new location(s) for obtaining samples in the next Annual Radiological Environmental Operating Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

b.

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. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. 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. Due to the geographical limitations, the number of direct radiation monitoring stations has been reduced to 9 of 16 sectors, because seven sectors are over water and therefore do not require monitoring (Developmental Reference 34).

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 51 of 321 Level 3 - Information TABLE 3.12-1 (Continued)

TABLE NOTATION c.

Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, GAMMA ISOTOPIC ANALYSIS shall be performed on the individual samples.

d.

GAMMA ISOTOPIC ANALYSIS means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

e.

A COMPOSITE SAMPLE is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program, COMPOSITE SAMPLE aliquots shall be collected at time intervals that are very short (for example, hourly) relative to the compositing period (for example, monthly) in order to assure obtaining a representative sample.

f.

Exception to these locations is in the South Sector where DR7, A1, 1b4, 1b5, and 1b6 are located approximately 0.7 km from the release point. This location is conservative with respect to the site boundary, which is located approximately 2.1 km from the release point.

g.

The current locations, Wa1 and Wa2, represent conservative means to evaluate the relationship between quantities of radioactive material released in effluents and their presence/accumulation in the environment. These locations have been monitored since the establishment of the Preoperational Environmental Radioactivity Monitoring Program. While the sample locations do not exactly match the regulatory guidance found in NUREG-1301, the sample locations are sufficiently conservative with respect to plant releases to meet the requirements of and are compliant with 10 CFR 50 Appendix I and Appendix A, Criterion 64.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 52 of 321 Level 3 - Information TABLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS AIRBORNE FISH & FOOD WATER PARTICULATE MILK ANALYSIS INVERTEBRATES PRODUCTS (pCi/l) OR GASES (pCi/l)

(pCi/kg, wet) (pCi/kg, wet)

(pCi/M3)

H-3 20,000 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 I-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 For drinking water samples. This is a 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/l may be used.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 53 of 321 Level 3 - Information TABLE 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSISa,b LOWER LIMIT OF DETECTION (LLD)c AIRBORNE FISH &

FOOD WATER PARTICULATE INVERTEBRATE MILK SEDIMENT ANALYSIS PRODUCTS (pCi/l) OR GASES S (pCi/kg, wet) (pCi/l) (pCi/kg,dry)

(pCi/kg, wet)

(pCi/M3)

Gross Beta 4 0.01 H-3 2,000 Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 I-131 1d 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 If no drinking water pathway exists, a value of 3000 pCi/l may be used.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 54 of 321 Level 3 - Information TABLE 4.12-1 (Continued)

TABLE NOTATION a

This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2.

b Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be per the recommendations of Regulatory Guide 4.13.

c The LLD is defined, for purposes of these controls, 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:

4.66 sb LLD =

E

  • V
  • 2.22
  • Y
  • exp(- t)

Where:

LLD is the A priori LOWER LIMIT OF DETECTION as defined above, as picocuries per unit mass or volume, sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, 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, is the radioactive decay constant for the particular radionuclide, and December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 55 of 321 Level 3 - Information TABLE 4.12-1 (Continued)

TABLE NOTATION t for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting.

Typical values of E, V, Y and t should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular 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 pursuant to Technical Specification 5.6.2.

d LLD for drinking water samples. If no drinking water pathway exists, the LLD of GAMMA ISOTOPIC ANALYSIS (15 pCi/l) may be used.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 56 of 321 Level 3 - Information RADIOLOGICAL ENVIRONMENTAL MONITORING:

LAND USE CENSUS CONTROLS 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles), the location in each of the 9 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden* of greater than 50 m2 (500 ft2) producing broad leaf vegetation. (For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify within a distance of 5 km (3 miles) the locations in each of the 9 meteorological sectors of all milk animals and all gardens of greater than 50 m2 producing broad leaf vegetation).

APPLICABILITY: At all times.

ACTION:

a. With a land use census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Control 4.11.2.3, identify the new location(s) in the next Annual Radiological Environmental Operating Report, pursuant to Technical Specification 5.6.2.
b. With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained per Control 3.12.1, add the new location(s) to the radiological environmental monitoring program within 30 days. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Pursuant to Technical Specification 5.6.2, identify the new location(s) in the next Annual Radiological Environmental Operating Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

SURVEILLANCE REQUIREMENTS 4.12.2 The land census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2.

  • Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3.12-1.4b shall be followed, including analysis of control samples.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 57 of 321 Level 3 - Information RADIOLOGICAL ENVIRONMENTAL MONITORING:

INTERLABORATORY COMPARISON PROGRAM CONTROLS 3.12.3 Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a. With analyses not being performed as required above, report the corrective ACTIONS taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2.

SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM. 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 pursuant to Technical Specification 5.6.2.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 58 of 321 Level 3 - Information PART 5.0: CALCULATIONAL METHODOLOGIES RADIOACTIVE LIQUID EFFLUENTS RELEASE PATHWAYS [B527]

1. Introduction a) Radioactive liquid waste generated as a result of operating the Calvert Cliffs Nuclear Power Plant (CCNPP) may be released to the Chesapeake Bay1.

b) There are three pathways by which waste water, non-radioactive and radioactive, may be discharged from the site to the bay:

(1) Outfall 001, (2) Outfall 003, (3) Outfall 004.

c) A diagram which shows the location of each outfall is included as Attachment 1.

2. Outfall 001 a) Water from the Chesapeake Bay is pumped through the condensers and is discharged to the Chesapeake Bay through the circulating water discharge conduits, known as Outfall 001.

b) The liquid radioactive waste is mixed with and diluted by the circulating water before exiting the discharge conduit.

c) The circulating water discharge conduit extends 850 feet into the Chesapeake Bay.

d) The circulating water discharge conduit may accept liquid radioactive waste from various sources. Sources which may contribute radioactive material to the circulating water discharge conduit are tabulated in Attachment 2.

3. Outfall 002 was modified in 2001 to be discharged via Outfall 001.
4. Outfalls 003 and 004 a) There are two other potential pathways for the release of radioactive liquids to the bay. These pathways are designated Outfall 003 and Outfall 004.

b) Sources which could potentially contribute radioactive material to each of these outfalls are tabulated in Attachment 8.

1 The federal controls and administrative limits associated with the release of radioactive materials from CCNPP are discussed elsewhere in this document.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 59 of 321 Level 3 - Information

5. Unmonitored release paths not shown on Attachment 3 should be evaluated and added to the ODCM as necessary.
6. Safety evaluations have been conducted for operating the following systems after they have become contaminated:

a) Component cooling water system (1) Per applicable safety evaluations (Ref. 22), continued operation of this system is allowed as long as the concentration of radionuclides in the component cooling water system is less than 3,000 MPCs.

b) Plant heating system (1) Per applicable safety evaluations (Ref. 24 and Ref. 28), continued operation of this system is allowed as long as the concentration of radionuclides in the plant heating system is less than 0.3 MPCs.

c) Auxiliary boiler system (1) Per applicable safety evaluations (Ref. 27 and Ref. 30) continued operation of this system is allowed as long as the concentration of radionuclides in the auxiliary boiler steam drum is less than 96 MPCs.

d) Demineralized water system (1) Per applicable safety evaluations (Ref. 25 and Ref. 31), continued operation of this system is allowed as long as the concentration of radionuclides in the demineralized water system is less than 0.3 MPCs.

e) Service water system (1) Per applicable safety evaluations (Ref. 26 and Ref. 32), continued operation of this system is allowed as long as the concentration of radionuclides in the service water system is less than 0.1 MPCs.

f) Condensate storage tank (1) Per applicable safety evaluations (Ref. 33), continued operation of this system is allowed as long as the concentration of radionuclides in the condensate storage tank is less than 1.0 MPCs.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 60 of 321 Level 3 - Information TYPES OF LIQUID RELEASES

1. Liquid radwaste discharges have been classified as CONTINUOUS or BATCH as shown on Attachment 2, Sources of Liquid Radioactive Waste.

PROCESSING EQUIPMENT

1. Simplified Flow Diagram a) An overview of the Liquid Waste Processing System, including major equipment and (normal) flow paths, is outlined on Attachment 4, Block Diagram of Liquid Radioactive Waste Systems.

b) There is no processing equipment for wastes discharged through Outfalls 003 and 004; however, the waste shall be analyzed for radioactivity per the analysis frequencies contained in approved Chemistry procedures.

2. Modifications a) Licensee initiated major changes to the Liquid Radioactive Waste System shall be reported to the Commission in the Radioactive Effluent Release Report for the period in which the modification to the waste system is completed. The discussion of each change shall contain:

(1) A description of the equipment, components and processes involved; AND (2) Documentation of the fact that the change, including the safety analysis, was reviewed and found acceptable by the onsite review function.

The report shall also include changes to the ODCM, per Technical Specification 5.6.3.

b) A major change or modification includes, but is not limited, to the removal or permanent bypass of any of the following:

(1) Degassifier (2) Reactor coolant waste receiver tank (3) Reactor coolant waste monitor tank (4) Letdown filter (5) Reactor coolant waste ion exchanger (6) Miscellaneous waste ion exchanger (7) Miscellaneous waste filter (8) Miscellaneous waste receiver tank (9) Miscellaneous waste monitor tank (10) Evaporator December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 61 of 321 Level 3 - Information

3. Detailed Description a) A detailed description of the Liquid Waste Processing System is beyond the scope of the ODCM.

b) For more information see the Updated Final Safety Analysis Report, Chapter 11, Waste Processing And Radiation Protection.

LIQUID EFFLUENT RADIATION MONITOR ALARM AND FIXED SETPOINTS

1. Liquid Waste Discharge Radiation Monitor (0-RE-2201) a) General description (1) Number of radiation elements: one (2) Type of radiation element: off-line sampler with scintillation detector (3) Output: analog (4) Radiation indicator: 0-RI-2201 (5) Units for radiation indicator: counts per minute (6) Supplier: General Atomics b) Functions of 0-RE-2201 (1) Continuously measure the activity contained in liquid waste discharge line (Control 3.3.3.10)

(2) Continuously indicate (via 0-RI-2201) the activity of liquids contained in liquid waste discharge line (Control 3.3.3.10)

(3) Alarm (via 0-RI-2201) before exceeding 10 CFR 20, Appendix B, Table II, Column 2 limits (per Control 3.11.1.1)

(4) Automatically terminate discharges from the Liquid Waste Processing System by closing the discharge isolation valves (MWS-2201-CV, and MWS-2202-CV) whenever the radiation indicator (0-RI-2201) exceeds the fixed setpoint.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 62 of 321 Level 3 - Information c) OPERABILITY of 0-RE-2201 (1) This monitor shall be operable (or have OPERABILITY) when it is capable of performing its specified function(s).

(2) The functions of 0-RE-2201 are listed in paragraph (b) above.

d) Monitors equivalent to 0-RE-2201 (1) There are no equivalent monitors for 0-RE-2201.

e) Radiological effluent controls for 0-RE-2201 (1) Liquid waste discharges via this pathway may continue if any one of the following two conditions are satisfied (per Control 3.3.3.10).

(a) The liquid waste discharge monitor, 0-RE-2201, is operable and the alarm-with-automatic-termination setpoint for this monitor is set to ensure the concentrations of radioactive materials released in liquid effluents to UNRESTRICTED AREAS are less than the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2, or (b) Two independent samples are analyzed per Control 4.11.1.1.1; AND at least two technically qualified members of the Facility Staff independently verify the release rate calculations; AND two qualified operators verify the discharge valve line up.

f) Surveillances for 0-RE-2201 (1) Control 4.3.3.10 requires demonstrating the OPERABILITY of 0-RE-2201 by satisfying the checks, calibrations, and tests listed below:

(a) CHANNEL CHECK within the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (b) SOURCE CHECK before each release (c) CHANNEL CALIBRATION within the past 18 months (d) CHANNEL FUNCTIONAL TEST within the past 6 six months g) Setpoints for 0-RI-2201 (1) There are three radiation alarm setpoints associated with, or otherwise related to, the liquid waste discharge monitor.

(a) 0-RI-2201 fixed high radiation alarm and automatic termination setpoint.

(b) 0-RI-2201 adjustable plant computer high radiation alarm and manual termination setpoint.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 63 of 321 Level 3 - Information (c) 0-RI-2201 low radiation alarm setpoint.

(2) In order to simplify the setpoint terminology, eliminate ambiguity, and minimize the possibility of misinterpretation, the ODCM will refer to these setpoints as follows:

(a) The 0-RI-2201 fixed high radiation alarm and automatic termination setpoint will be referred to as the fixed setpoint.

(b) The 0-RI-2201 adjustable plant computer high radiation alarm and manual termination setpoint will be referred to as the adjustable setpoint.

(c) The 0-RI-2201 low radiation alarm setpoint will be referred to as the low setpoint.

(3) Each of these alarm setpoints is described below.

h) Fixed setpoint for 0-RI-2201 (1) General information (a) This setpoint is not adjusted for each release.

(b) Whenever the fixed setpoint is exceeded, discharges from the Liquid Waste Processing System will be automatically suspended.

(c) The fixed setpoint corresponds to the maximum concentration of radionuclides allowed in liquid waste discharged from the Liquid Waste Processing System.

(d) The current value for the fixed setpoint is specified in the CCNPP Alarm Manual.

(e) The CCNPP Alarm Manual refers to this alarm and fixed setpoint as the 0-RI-2201 Liquid Waste Discharge High Alarm.

(f) The fixed setpoint is integral to the liquid release discharge monitor, as purchased from the supplier.

(g) The fixed setpoint is administratively controlled by the CCNPP Alarm Manual.

(h) The fixed setpoint shall be calculated as described below1.

1 Per Control 3.3.3.10.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 64 of 321 Level 3 - Information (2) Calculating the fixed setpoint for 0-RI-2201 (a) The fixed setpoint for 0-RI-2201 shall be calculated as follows:

FIXED SETPOINT FOR 0-RI-2201 Sfix < Ksf { ( Fd / Fu ) [ ( AiLn ) ( ei ) ] + Bkg } Eq. 1L1 Sfix = The fixed setpoint for 0-RI-2201 (cpm)

Ksf = A constant, actually a safety factor, which is the ratio of the CCNPP activity limit to the 10 CFR 20, Appendix B, Table II, Column 2 MPC limit (unitless)

The safety factor chosen shall be less than or equal to 1.00. This ensures the fixed setpoint is always less than or equal to the limits of 10 CFR 20.

A safety factor of 1.00 will yield a fixed setpoint which corresponds to 1.0 MPC.

A safety factor of 0.500 will yield a fixed setpoint which corresponds to 0.5 MPCs.

It is recommended that a safety factor of 0.5 be used for calculating the fixed setpoint, however, other values--not to exceed 1.00--may be used as directed by Management.

The use of a safety margin is per the provisions of NUREG-0133, Section 4.1.1, which states, "The alarm and trip setpoints ... should correspond to a value(s) which represents a safe margin of assurance that the instantaneous liquid release limit of 10 CFR Part 20 is not exceeded."

This safety margin will prevent minor fluctuations in the nominal circulating water flow rate (and other statistical aberrations) from adversely impacting the calculated fixed setpoint.

Fd = The dilution water flow rate (gpm) before the point of release to UNRESTRICTED AREAS The dilution water flow rate is actually the sum of the minimum circulating water flow rate, the minimum salt water flow rate, and the maximum undiluted radwaste flow rate.

The dilution water flow rate shall be calculated per equation 2L.

1 This formula has been derived from NUREG-0133, Addendum, page AA-1.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 65 of 321 Level 3 - Information DILUTION WATER FLOW RATE Fd = Fcw + Fsw + Fu Eq. 2L Fcw = The minimum circulating water system flow rate necessary to conduct liquid releases A minimum of two circulating water pumps (one circulating water pump per conduit accepting radwaste) shall be operable when discharging liquid radwaste -- via this monitor --

to Outfall 001.

Additional circulating water pumps may be required as specified in approved Chemistry Procedures.

If a release of liquid radwaste is to be conducted using less than minimum circulating water flow rate necessary to conduct liquid releases, then the release shall not be allowed until a new setpoint has been calculated and entered into 0-RI-2201 (unless the existing setpoint is conservative), or otherwise comply with the ACTION requirements of Control 3.3.3.10.

Fsw = The minimum salt water system flow rate necessary to release liquid radwaste If the minimum salt water flow rate available for liquid releases is unknown, difficult to predict, or may decrease during a liquid release, a minimum salt water flow rate of 0 gpm should be used when calculating the fixed setpoint.

If a release of liquid radwaste is to be conducted using less than the minimum salt water flow rate necessary to conduct liquid releases, the release shall not be allowed until a new setpoint has been calculated and entered into 0-RI-2201 (unless the existing setpoint is conservative), or otherwise comply with the ACTION requirements of Control 3.3.3.10.

Fu = Maximum undiluted radwaste flow rate (gpm)

Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachment 2.

Since the flow rate of undiluted liquid waste (120 gpm maximum) is insignificant relative to the circulating water flow rate (200,000 gpm per circulating water pump), the flow rate of undiluted liquid waste need not be considered when calculating the dilution water flow rate.

Since the maximum undiluted radwaste flow rate is used for calculating the fixed setpoint, a flow setpoint is not required--for the flow measuring device (0-FE-2199) in the effluent line--

to verify compliance with Control 3.3.3.10.

AiLn = Specific activity limit for the release of radionuclide, i, to UNRESTRICTED AREAS (calculated per 10 CFR 20, Appendix B, Table II, Note 1 as described below; microcuries per milliliter).

In order to calculate a meaningful and accurate fixed setpoint, the specific radionuclides, i, chosen for calculating the fixed setpoint should correspond to those radionuclides found in TYPICAL RADWASTE RELEASES from CCNPP.

Attachment 5 provides further guidance for determining the identity of those radionuclides, i, to be used to calculate a fixed setpoint.

Values for AiLn shall be calculated, as described below, for each radionuclide.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 66 of 321 Level 3 - Information SPECIFIC ACTIVITY LIMIT FOR RADIONUCLIDE i AiLn = ( fi ) ( ATLn ) Eq. 3L fi = A fraction which represents the relative activity contribution of nuclide i to the average total effluent activity (unitless).

The average total effluent activity does not include tritium or dissolved and entrained noble gases.

This value may be obtained using the guidance provided on Attachment 5.

ATLn = The sum of the total specific activities of all radionuclides found in a TYPICAL LIQUID RADWASTE RELEASE (microcuries/cm3).

This value corresponds to 1 MPC.

ATLn shall be calculated as shown below.

TOTAL SPECIFIC ACTIVITY EQUIVALENT TO 1 MPC

[ ( fi ) ( ATLn ) / AiLt ] = 1 Eq. 4L1 AiLt = The specific activity limit for radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table II, Column 2 (microcuries/cm3).

For all the radionuclides found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B, Table II, Column 2.

1 = The MPC limit (MPCs) for UNRESTRICTED AREAS.

This value is based on the MPC limit from 10 CFR 20, Appendix B, Table II, Note 1.

ei = Absolute detector efficiency for nuclide, i (cpm/microcuries per milliliter).

The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor.

Bkg = An approximation of the detector background before initiating the liquid release (cpm).

Instead of using an approximation of the detector background, a value of 0 cpm may be used as the detector background if so desired.

(3) Documenting the fixed setpoint for 0-RI-2201 (a) Whenever the fixed setpoint is calculated, the specific values chosen for each of the parameters shall be documented in the CCNPP Alarm Manual.

1 This formula has been derived from 10 CFR 20, Appendix B, Table II, Notes 1, 2, and 3.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 67 of 321 Level 3 - Information (4) Changing the fixed setpoint for 0-RI-2201 (a) If the fixed setpoint calculated per equation 1L exceeds the maximum range of the monitor, the fixed setpoint shall be adjusted to a value which falls within the normal operating range of the monitor.

(b) The fixed setpoint for 0-RI-2201 may be established at values lower than the maximum allowable setpoint, if desired.

(c) A setpoint change should be initiated whenever any of the parameters identified in equation 1L have changed.

(d) The fixed setpoint should not be changed unless one of the following occurs:

i) The relative activity1 of any radionuclide in TYPICAL LIQUID EFFLUENTS, fi, has changed by greater than 10%, and the new radionuclide mixture yields a fixed setpoint which is 10% (or more) lower than the current fixed setpoint, ii) The minimum dilution water flow rate is not available for a liquid release, iii) The values listed in 10 CFR 20, Appendix B, Table II, Column 2 have changed, iv) The radiation monitor has been recently calibrated, repaired, or otherwise altered, OR v) The monitor is not conservative in its function (see Functions of 0-RE-2201 earlier in this section).

(e) CC-AA-103-2001, Setpoint Change Control contains the administrative controls associated with changing and approving the fixed setpoint.

1 As determined in accordance with Attachment 5.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 68 of 321 Level 3 - Information i) The adjustable setpoint for 0-RI-2201 (1) General information (a) The adjustable setpoint is calculated and adjusted before each release from the Liquid Waste Processing System.

(b) The adjustable setpoint is based on the specific activities of the radionuclides present in the undiluted liquid waste (as determined by radiochemical analysis per Control 4.11.1.1.1).

(c) Whenever the adjustable setpoint is exceeded, discharges from the Liquid Waste Processing System will be manually suspended.

(d) See OI-17C, Reactor Coolant Waste Processing System, or OI-17D, Miscellaneous Waste Processing System, for a full list of operator ACTIONS taken in response to this alarm.

(e) The adjustable setpoint corresponds to the maximum concentration of radionuclides anticipated or expected in discharges from the Liquid Waste Processing System.

(f) The value for the adjustable setpoint is recorded on the liquid release permit per Chemistry procedures.

(g) This alarm is not integral to the liquid release discharge monitor, as purchased from the supplier.

(h) This alarm is generated by the plant computer, which monitors output from 0-RI-2201, and provides an alarm to plant operators when the adjustable setpoint has been exceeded.

(i) A value for the adjustable setpoint shall be calculated before each release as shown below.

(2) Calculating the adjustable setpoint for 0-RI-2201 (a) The adjustable setpoint is based on the specific activities of the radionuclides in the undiluted liquid waste (as determined by radiochemical analysis per Control 4.11.1.1.1), and shall be calculated as shown below.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 69 of 321 Level 3 - Information ADJUSTABLE SETPOINT FOR 0-RI-2201 Sadj < 1.50 [ ( Aiu ) ( ei ) + Bkg ] Eq. 5L Sadj = The adjustable setpoint for 0-RI-2201 (cpm) 1.50 = A constant, actually a safety factor, which allows for fluctuations in radiation monitor response (unitless)

This safety factor helps ensure the release is not unnecessarily terminated due to:

(1) electronic anomalies which cause spurious monitor responses (2) statistical fluctuations in disintegration rates (3) statistical fluctuations in detector efficiencies (4) errors associated with sample analysis, or (5) errors associated with monitor calibrations.1 Aiu = Specific activity of radionuclide, i, in the undiluted waste stream (microcuries per milliliter) ei = Absolute detector efficiency for nuclide, i (cpm/microcuries per milliliter)

The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor.

Bkg = An approximation of the detector background (cpm)

(3) Documenting the adjustable setpoint for 0-RI-2201 (a) Whenever the adjustable setpoint is calculated, the specific values chosen for each of the variables shall be documented per approved Chemistry procedures.

(4) Changing the adjustable setpoint for 0-RI-2201 (a) In all cases, the adjustable setpoint shall be set to a value which is less than or equal to the fixed setpoint.

(b) If the adjustable setpoint exceeds the maximum range of the monitor, the setpoint shall be adjusted to a value which falls within the normal operating range of the monitor.

(c) Chemistry procedures contain administrative controls associated with calculating and approving an adjustable setpoint.

1 The analysis errors and calibration errors refer to errors which are within established quality assurance and quality control limits.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 70 of 321 Level 3 - Information (d) Whenever 0-RI-2201 is operable, the calculated value for the adjustable setpoint shall be entered into the plant computer before each release from the Liquid Waste Processing System.

(e) Plant Operating Instructions contain administrative controls associated with entering the adjustable setpoint into the plant computer.

j) The low setpoint for 0-RI-2201 (1) This setpoint is integral to the liquid release discharge monitor, as purchased from the supplier.

(2) The current value for the low setpoint is specified in the CCNPP Alarm Manual.

(3) The low setpoint may be used to determine the OPERABILITY of this monitor (per Control 4.3.3.10, CHANNEL FUNCTIONAL TEST).

(4) The alarm generated by the low setpoint may be used to terminate a release in the event 0-RE-2201 fails (that is, downscale failure or circuit failure) per Control 4.3.3.10.

(5) The low setpoint calculations are not described in the ODCM.

(6) Changes to the low setpoint are administratively controlled by the CCNPP Alarm Manual.

2. Steam Generator Blowdown Effluent Radiation Monitors (1/2-RE-4095) a) General description of 1/2-RE-4095 (1) Number of radiation elements: one per unit (2) Type of radiation elements: off-line sampler with scintillation detectors (3) Output: analog (4) Designations for radiation indicators (a) 1-RI-4095 (b) 2-RI-4095 (5) Units for radiation indicator: counts per minute (6) Supplier: General Atomics December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 71 of 321 Level 3 - Information b) Functions of 1/2-RE-4095 (1) Continuously measure the activity contained in Steam Generator Blowdown Effluent Line (Control 3.3.3.10).

(2) Continuously indicate (via 1/2-RI-4095) the activity of liquids contained in the Steam Generator Blowdown Effluent Line (Control 3.3.3.10).

(3) Alarm (via 1/2-RI-4095) before exceeding 10 CFR 20, Appendix B, Table II, Column 2 limits (per Control 3.11.1.1).

(4) Automatically terminate Steam Generator Blowdown releases to UNRESTRICTED AREAS when the radiation indicator (1/2-RI-4095) exceeds the fixed setpoint.

c) OPERABILITY of 1/2-RE-4095 (1) This monitor shall be operable (or have OPERABILITY) when it is capable of performing its specified function(s).

(2) The functions of this monitor are listed in Section (b) above.

(3) It should be noted that if the Steam Generator Blowdown Processing System Heat Exchangers are bypassed, it is possible for blowdown flow to bypass 1/2-RE-4095. If blowdown flow is allowed to bypass 1/2-RE-4095, the minimum channels OPERABILITY requirement of Control 3.3.3.10 may not be satisfied.

d) Monitors equivalent to 1/2-RE-4095 (1) 1/2-RE-4014 is normally considered the PRIMARY MONITOR for measuring activity released via the Steam Generator Blowdown Processing System, and 1/2-RE-4095 is normally considered the BACKUP MONITOR for measuring activity released via the Steam Generator Blowdown Processing System.

(2) In the event PRIMARY MONITOR (1/2-RE-4014) is inoperable or otherwise unavailable, the BACKUP MONITOR (1/2-RE-4095) may fulfill the measuring, indicating, and alarming functions normally provided by the PRIMARY MONITOR.

(3) 1/2-RE-4014, Steam Generator Blowdown Tank Radiation Monitor is considered to be equivalent monitor to 1/2-RE-4095 as specified below.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 72 of 321 Level 3 - Information (4) 1/2-RE-4014, Steam Generator Blowdown Tank Radiation Monitor, may perform measurement, indication, alarm, and isolation functions (see Functions of 1/2-RE-4014 earlier in this section) which limit the concentration of radioactive materials released to UNRESTRICTED AREAS per Control 3.11.1.1 as long as the following conditions are satisfied:

(a) The OPERABILITY of 1/2-RE-4014 must be demonstrated per Control 4.3.3.10, Table 3.3-13(1b), and (b) The blowdown ion exchangers are isolated (or the decontamination factors for all radionuclides are verified to be greater than or equal to one for the duration of the release), and (c) The specific activities of radionuclides in the blowdown tank radiation monitor are representative of the activities of the radionuclides in the blowdown effluent line.

e) Radiological effluent controls for 1/2-RE-4095 (1) Steam Generator Blowdown releases via this pathway may continue if any one of the following two conditions are satisfied (per Control 3.3.3.10):

(a) A Steam Generator Blowdown monitor (either 1/2-RE-4095 or 1/2-RE-4014) is OPERABLE (see OPERABILITY of 1/2-RE-4095, and OPERABILITY of 1/2-RE-4014 earlier in this section) AND the setpoint for this monitor is set to ensure the concentrations of radioactive materials released in liquid effluents to UNRESTRICTED AREAS are less than the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2, or (b) A grab sample is collected AND analyzed per the provisions described below:

i) Analysis shall determine EITHER the gross gamma activity or gross beta activity of the sample ii) Sampling and analysis shall be completed at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if the specific activity of the Steam Generator Blowdown is greater than 0.01 microcuries per gram IODINE DOSE EQUIVALENT iii) Sampling and analysis shall be completed at least once per 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if the specific activity of the Steam Generator Blowdown is less than or equal to 0.01 microcuries per gram IODINE DOSE EQUIVALENT iv) The LOWER LIMITS OF DETECTION (LLDs) for the gross gamma and/or gross beta analyses are per the LLDs of Control 4.11.1.1.1 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 73 of 321 Level 3 - Information f) Surveillances for 1/2-RE-4095 (1) Control 4.3.3.10 requires demonstrating the OPERABILITY of 1/2-RE-4095 by satisfying the checks, calibrations, and tests listed below:

(a) CHANNEL CHECK within the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (b) SOURCE CHECK before each release (c) CHANNEL CALIBRATION within the past 18 months (d) CHANNEL FUNCTIONAL TEST within the past 6 six months g) Setpoints for 1/2-RI-4095 (1) There are three radiation alarm setpoints associated with the Steam Generator Blowdown Effluent Radiation Monitor.

(a) 1/2-RI-4095 fixed high radiation alarm and automatic termination setpoint (b) 1/2-RI-4095 adjustable plant computer high radiation alarm and manual termination setpoint (c) 1/2-RI-4095 low radiation alarm setpoint (2) In order to simplify the setpoint terminology, eliminate ambiguity, and minimize the possibility of misinterpretation, the ODCM will refer to these setpoints as follows:

(a) The 1/2-RI-4095 fixed high radiation alarm and automatic termination setpoint will be referred to as the fixed setpoint.

(b) The 1/2-RI-4095 adjustable plant computer high radiation alarm and manual termination setpoint will be referred to as the adjustable setpoint.

(c) The 1/2-RI-4095 low radiation alarm setpoint will be referred to as the low setpoint.

(3) Each of these alarm setpoints are described below.

h) The fixed setpoint for 1/2-RI-4095 (1) General information (a) The fixed setpoint is not adjusted for each release.

(b) Whenever the fixed setpoint is exceeded, discharges from the Steam Generator Blowdown Processing System to UNRESTRICTED AREAS will be automatically suspended.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 74 of 321 Level 3 - Information (c) The fixed setpoint corresponds to the maximum concentration of radionuclides allowed in liquid waste discharged from the Steam Generator Blowdown Processing System.

(d) The current value for the fixed setpoint is specified in the CCNPP Alarm Manual.

(e) The CCNPP Alarm Manual refers to this setpoint as the 1/2-RI-4095 Steam Generator Blowdown Recovery High Alarm.

(f) This setpoint is integral to the Steam Generator Blowdown discharge monitor, as purchased from the manufacturer.

(g) The fixed setpoint is administratively controlled by the CCNPP Alarm Manual.

(h) The fixed setpoint shall be calculated as described below1.

(2) Calculating the fixed setpoint for 1/2-RI-4095 (a) The fixed setpoint for 1/2-RI-4095 shall be calculated per equation 1L.

FIXED SETPOINT FOR 1/2-RI-4095 Sfix < Ksf { ( Fd/Fu ) [ ( AiLn ) ( ei ) ] + Bkg } Eq. 1L2 Sfix = The fixed setpoint for 1/2-RI-4095 (cpm)

Ksf = A constant, actually a safety factor, which is the ratio of the CCNPP activity limit to the 10 CFR 20, Appendix B, Table II, Column 2 MPC limit (unitless)

The safety factor chosen shall be less than or equal to 1.00. This ensures the fixed setpoint is always less than or equal to the limits of 10 CFR 20.

A safety factor of 1.00 will yield a fixed setpoint which corresponds to 1.0 MPC.

A safety factor of 0.500 will yield a fixed setpoint which corresponds to 0.5 MPCs.

It is recommended that a safety factor of 0.5 be used for calculating the fixed setpoint, however, other values--not to exceed 1.00--may be used as directed by Management.

The use of a safety margin is per the provisions of NUREG-0133, section 4.1.1, which states:

"The alarm and trip setpoints ... should correspond to a value(s) which represents a safe margin of assurance that the instantaneous liquid release limit of 10 CFR Part 20 is not exceeded."

1 Per Control 3.3.3.10.

2 Equation 1L has been derived from NUREG-0133, Addendum, page AA-1.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 75 of 321 Level 3 - Information This safety margin will prevent minor fluctuations in the nominal circulating water flow rate (and other statistical aberrations) from adversely impacting the calculated fixed setpoint.

Fd = The dilution water flow rate (gpm) before the point of release to UNRESTRICTED AREAS The dilution water flow rate is actually the sum of the minimum circulating water flow rate, the minimum salt water flow rate, and the maximum undiluted radwaste flow rate.

The dilution water flow rate shall be calculated per equation 2L.

DILUTION WATER FLOW RATE Fd = Fcw + Fsw + Fu Eq. 2L Fcw = The minimum circulating water system flow rate necessary to conduct liquid releases A minimum of two circulating water pumps (one circulating water pump per conduit accepting radwaste) shall be operable when discharging liquid radwaste -- via this monitor -- to Outfall 001.

The flow rate of each circulating water pump is 200,000 gallons per minute.

Additional circulating water pumps may be required as specified in approved Chemistry procedures.

If a release of liquid radwaste from the Steam Generator Blowdown system is to be conducted using less than minimum circulating water flow rate necessary to conduct liquid releases, the release shall not be allowed until a new setpoint has been calculated and entered into 1/2-RI-4095 (unless the existing setpoint is conservative), or otherwise comply with the ACTION requirements of Control 3.3.3.10.

Fsw = The minimum salt water system flow rate necessary to release liquid radwaste If the minimum salt water flow rate available for liquid releases is unknown, difficult to predict, or may decrease during a liquid release, a minimum salt water flow rate of 0 gpm should be used when calculating the fixed setpoint.

The maximum flow rate for one salt water pump is listed on Attachment 2.

If a release of liquid radwaste is to be conducted using less than the minimum salt water flow rate necessary to conduct liquid releases, the release shall not be allowed until a new setpoint has been calculated and entered into 1/2-RI-4095 (unless the existing setpoint is conservative),

or otherwise comply with the ACTION requirements of Control 3.3.3.10.

Fu = Maximum undiluted radwaste flow rate (gpm)

Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachment 2.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 76 of 321 Level 3 - Information Since the Steam Generator Blowdown flow rate (225 gpm maximum) is insignificant relative to the circulating water flow rate (200,000 gpm per circulating water pump), the Steam Generator Blowdown flow rate need not be considered when calculating the dilution water flow rate.

Since the maximum undiluted radwaste flow rate is used for calculating the fixed setpoint, a flow setpoint is not required--for the flow measuring device in the effluent line--to verify compliance with Control 3.3.3.10.

AiLn = Specific activity limit for the release of radionuclide, i, to UNRESTRICTED AREAS (calculated per 10 CFR 20, Appendix B, Table II, Note 1 as described below; microcuries per milliliter)

In order to calculate a meaningful and accurate fixed setpoint, the specific radionuclides, i, chosen for calculating the fixed setpoint should correspond to those radionuclides found in TYPICAL RADWASTE RELEASES from CCNPP.

Attachment 5 provides further guidance for determining which radionuclides, i, should be used to calculate a fixed setpoint.

Values for AiLn shall be calculated, as described below, for each radionuclide.

SPECIFIC ACTIVITY LIMIT FOR EACH RADIONUCLIDE i AiLn = ( fi ) ( ATLn ) Eq. 3L fi = A fraction which represents the relative activity contribution of nuclide i to the average total effluent activity (unitless)

The average total effluent activity does not include tritium or dissolved and entrained noble gases.

This value may be obtained using the guidance provided on Attachment 5.

ei = Absolute detector efficiency for nuclide, i (cpm/microcuries per milliliter)

The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 77 of 321 Level 3 - Information ATLn = The sum of the total specific activities of all radionuclides found in a TYPICAL LIQUID RADWASTE RELEASE (microcuries/cm3)

This value corresponds to 1 MPC.

ATLn shall be calculated as shown below.

TOTAL SPECIFIC ACTIVITY EQUIVALENT TO 1 MPC

[ ( fi ) ( ATLn ) / AiLt ] = 1 Eq. 4L1 AiLt = The specific activity limit for radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table II, Column 2 (microcuries/cm3)

For all the radionuclides found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B, Table II, Column 2.

1 = The MPC limit (MPCs) for UNRESTRICTED AREAS This value is based on the MPC limit from 10 CFR 20, Appendix B, Table II, Note 1.

Bkg = An approximation of the detector background (cpm)

Instead of using an approximation of the detector background, a value of 0 cpm may be used as the detector background if so desired.

(3) Documenting the fixed setpoint for 1/2-RI-4095 (a) Whenever the fixed setpoint is calculated, the specific values chosen for each of the variables shall be documented per CC-AA-103-2001.

(4) Changing the fixed setpoint for 1/2-RI-4095 (a) If the fixed setpoint calculated per equation 1L exceeds the maximum range of the monitor, the fixed setpoint shall be adjusted to a value which falls within the normal operating range of the monitor.

(b) The fixed setpoint may be established at values lower than the maximum allowable setpoint, if desired.

(c) A setpoint change should be initiated whenever any of the parameters identified in equation 1L have changed.

1 This formula has been derived from 10 CFR 20, Appendix B, Table II, Notes 1, 2, and 3.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 78 of 321 Level 3 - Information (d) The fixed setpoint should not be changed unless one of the following occurs:

i) The relative activity1 of any radionuclide in TYPICAL LIQUID EFFLUENTS has changed by greater than 10%, and the new radionuclide mixture yields a fixed setpoint which is 10% (or more) lower than the current fixed setpoint, ii) The minimum dilution water flow rate is not available for a liquid release, iii) The values listed in 10 CFR 20, Appendix B, Table II, Column 2, have changed, iv) The radiation monitor has been recently calibrated, repaired, or otherwise altered, or v) The monitor is not conservative in its function (see Functions of 1/2-RE-4095, earlier in this section).

(e) CC-AA-103-2001 contains the administrative controls associated with changing and approving the fixed setpoint.

i) The adjustable setpoint for 1/2-RI-4095 (1) General information (a) The adjustable setpoint is calculated and adjusted before each release from the Steam Generator Blowdown Processing System.

(b) The adjustable setpoint is based on the specific activities of the radionuclides present in the undiluted liquid waste (as determined by radiochemical analysis per Control 4.11.1.1.1).

(c) Whenever the adjustable setpoint is exceeded, discharges from the Steam Generator Blowdown Processing System will be manually suspended.

(d) See OI-8A, Blowdown System, for a full list of operator actions taken in response to this alarm.

(e) The adjustable setpoint corresponds to the maximum concentration of radionuclides anticipated or expected in discharges from the Steam Generator Blowdown Processing System.

(f) The value for the adjustable setpoint is recorded on the liquid release permit per Chemistry procedures.

1 As determined in accordance with Attachment 5.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 79 of 321 Level 3 - Information (g) This alarm is not integral to the Steam Generator Blowdown Effluent Monitor, as purchased from the supplier.

(h) This alarm is generated by the plant computer which monitors output from 1/2-RI-4095, and provides an alarm to plant operators when the adjustable setpoint has been exceeded.

(i) A value for the adjustable setpoint shall be calculated before each release as shown below.

(2) Calculating the adjustable setpoint for 1/2-RI-4095 (a) The adjustable setpoint is based on the specific activities of radionuclides in the undiluted liquid waste (as determined by radiochemical analysis per Control 4.11.1.1.1), and shall be calculated as shown below.

ADJUSTABLE SETPOINT FOR 1/2-RI-4095 Sadj < 2.50 [ ( Aiu ) ( ei ) + Bkg ] Eq. 5L1

Where, Sadj = The adjustable setpoint for 1/2-RI-4095 (cpm) 2.50 = A constant, actually a safety factor, which allows for fluctuation in radiation monitor response (unitless)

This safety factor helps ensure the release is not unnecessarily terminated due to (1) electronic anomalies which cause spurious monitor responses, (2) statistical fluctuations in disintegration rates, (3) statistical fluctuations in detector efficiencies, (4) errors associated with sample analysis, or (5) errors associated with monitor calibrations.2 Aiu = Specific activity of radionuclide, i, in the undiluted waste stream (microcuries per milliliter) ei = Absolute detector efficiency for nuclide, i (cpm/microcuries per milliliter)

The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor.

Bkg = An approximation of the detector background before initiating the liquid release (cpm) 1 This formula may be derived from NUREG-0133, Addendum, page AA-1.

2 The analysis errors and calibration errors refer to errors which are within established quality assurance and quality control limits.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 80 of 321 Level 3 - Information (3) Documenting the adjustable setpoint, 1/2-RI-4095 (a) Whenever the adjustable setpoint is calculated, the specific values chosen for each of the variables shall be documented per approved Chemistry procedures.

(4) Changing the adjustable setpoint for 1/2-RI-4095 (a) If the adjustable setpoint exceeds the maximum range of the monitor, the setpoint shall be adjusted to a value which falls within the normal operating range of the monitor.

(b) In all cases, the adjustable setpoint shall be set to a value which is less than or equal to the fixed setpoint.

(c) Chemistry procedures contain administrative controls associated with calculating and approving an adjustable setpoint.

(d) Whenever 1/2-RI-4095 is operable, the calculated value for the adjustable setpoint shall be entered into the plant computer before each release from the Steam Generator Blowdown Processing System.

(e) Plant Operating Instructions (for example, OI-8A) contain administrative controls associated with entering the adjustable setpoint in the plant computer.

j) The low setpoint for 1/2-RI-4095 (1) This alarm is integral to the Steam Generator Blowdown effluent monitor, as purchased from the manufacturer.

(2) The current value for the low alarm setpoint is specified in the CCNPP Alarm Manual.

(3) The low alarm setpoint may be used to determine OPERABILITY of this monitor (per Control 4.3.3.10, CHANNEL FUNCTIONAL TEST).

(4) The low alarm setpoint may be used to terminate a release in the event 1/2-RE-4095 fails (that is, downscale failure or circuit failure).

(5) Changes to the low alarm setpoint are documented in the CCNPP Alarm Manual.

(6) The ODCM does not address the calculations associated with the low alarm setpoint.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 81 of 321 Level 3 - Information

3. Steam Generator Blowdown Tank Radiation Monitors (1/2-RE-4014) a) General description of 1/2-RE-4014 (1) Number of radiation elements: one per unit (2) Type of radiation element: off-line scintillation detector (3) Output: analog (4) Designations for radiation indicators (a) 1-RI-4014 (b) 2-RI-4014 (5) Units for radiation indicator: counts per minute (6) Supplier: Westinghouse (7) A 3 gallon per minute sample is cooled, passed through the detector, and pumped back into the Steam Generator Blowdown tank.

b) Functions of 1/2-RE-4014 (1) Continuously measure the activity contained in an off-line sample of the Steam Generator Blowdown Tank (Control 3.3.3.10)

(2) Continuously indicate (via 1/2-RI-4014) the specific activity in an off-line sample of the Steam Generator Blowdown Tank (Control 3.3.3.10)

(3) Alarm (via 1/2-RI-4014) before exceeding the 10 CFR 20, Appendix B, Table II, Column 2, limits (per Control 3.11.1.1)

(4) Automatically terminate Steam Generator Blowdown releases to UNRESTRICTED AREAS when the radiation indicator (1/2-RI-4014) exceeds the fixed alarm setpoint.

c) OPERABILITY of 1/2-RE-4014 (1) This monitor shall be operable (or have OPERABILITY) when it is capable of performing its specified function(s).

(2) The functions of this monitor are listed in section (b) above.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 82 of 321 Level 3 - Information d) Monitors equivalent to 1/2-RE-4014 (1) 1/2-RE-4014 is normally considered the PRIMARY MONITOR for measuring activity released via the Steam Generator Blowdown Processing System, and 1/2-RE-4095 is normally considered the BACKUP MONITOR for measuring activity released via the Steam Generator Blowdown Processing System.

(2) In the event PRIMARY MONITOR (1/2-RE-4014) is inoperable or otherwise unavailable, the BACKUP MONITOR (1/2-RE-4095) may fulfill the measuring, indicating, and alarming functions normally provided by the PRIMARY MONITOR.

(3) 1/2-RE-4095, Steam Generator Blowdown Effluent Radiation Monitor, performs measurement, indication, alarm, and isolation functions equivalent to 1/2-RE-4014 (see Function of 1/2-RE-4014 earlier in this section), unless 1/2-RE-4095 is bypassed as described below.

(4) It should be noted that if the Steam Generator Blowdown Processing System Heat Exchangers are bypassed, it is possible for blowdown flow to bypass 1/2-RE-4095 (the Steam Generator Blowdown effluent radiation monitor). If blowdown flow is allowed to bypass 1/2-RE-4095, the minimum channels OPERABILITY requirement of Control 3.3.3.10 may not be satisfied (unless 1/2-RE-4014 is operable).

e) Radiological effluent controls for 1/2-RE-4014 (1) Steam Generator Blowdown releases via this pathway may continue if any one of the following two conditions are satisfied (per Control 3.3.3.10):

(a) A Steam Generator Blowdown monitor (either 1/2-RE-4095 or 1/2-RE-4014) is OPERABLE (see OPERABILITY of 1/2-RE-4095; and OPERABILITY of 1/2-RE-4014, earlier in this section) AND the alarm setpoint for this monitor is set to ensure the concentrations of radioactive materials released in liquid effluents to UNRESTRICTED AREAS are less than the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2, or (b) A grab sample is collected AND analyzed per the provisions described below:

i) Analysis shall determine EITHER the gross gamma activity or gross beta activity of the sample ii) Sampling and analysis shall be completed at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if the specific activity of the Steam Generator Blowdown is greater than 0.01 microcuries per gram IODINE DOSE EQUIVALENT iii) Sampling and analysis shall be completed at least once per 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if the specific activity of the Steam Generator December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 83 of 321 Level 3 - Information Blowdown is less than or equal to 0.01 microcuries per gram IODINE DOSE EQUIVALENT iv) The LOWER LIMITS OF DETECTION for the gross gamma and/or gross beta analyses are per the LLDs of Control 4.11.1.1.1.

f) Surveillances for 1/2-RE-4014 (1) Control 4.3.3.10 requires demonstrating the OPERABILITY of 1/2-RE-4014 by satisfying the checks, calibrations, and tests listed below:

(a) CHANNEL CHECK within the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (b) SOURCE CHECK before each release (c) CHANNEL CALIBRATION within the past 18 months (d) CHANNEL FUNCTIONAL TEST within the past 6 six months g) Setpoints for 1/2-RI-4014 (1) There are three radiation alarm setpoints associated with the Steam Generator Blowdown Tank Radiation Monitor:

(a) 1/2-RI-4014 fixed high radiation alarm and automatic termination setpoint (b) 1/2-RI-4014 adjustable plant computer high radiation alarm and manual termination setpoint (c) 1/2-RI-4014 low radiation alarm setpoint (2) In order to simplify the setpoint terminology, eliminate ambiguity, and minimize the possibility of misinterpretation, the ODCM will refer to these setpoints as follows:

(a) The 1/2-RI-4014 fixed high radiation alarm and automatic termination setpoint will be referred to as the fixed setpoint.

(b) The 1/2-RI-4014 adjustable plant computer high radiation alarm and manual termination setpoint will be referred to as the adjustable setpoint.

(c) The 1/2-RI-4014 low radiation alarm setpoint will be referred to as the low setpoint.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 84 of 321 Level 3 - Information (3) Each of these alarms is described below.

h) The fixed setpoint for 1/2-RI-4014 (1) General Information (a) The fixed setpoint is not adjusted for each release.

(b) Whenever the fixed setpoint is exceeded, discharges from the Steam Generator Blowdown Processing System to UNRESTRICTED AREAS will be automatically suspended.

(c) The fixed setpoint corresponds to the maximum concentration of radionuclides allowed in liquid waste discharged from the Steam Generator Blowdown Processing System.

(d) The current value for the fixed setpoint is specified in the CCNPP Alarm Manual.

(e) The CCNPP Alarm Manual refers to the fixed setpoint as the 1/2-RI-4014 Steam Generator Blowdown High Alarm.

(f) The fixed setpoint is integral to the Liquid Release Discharge Monitor, as purchased from the manufacturer.

(g) The fixed setpoint is documented in the CCNPP Alarm Manual.

(h) The fixed setpoint shall be calculated as described below1.

1 Per Control 3.3.3.10.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 85 of 321 Level 3 - Information (2) Calculating the fixed setpoint for 1/2-RI-4014 (a) The fixed setpoint for 1/2-RI-4014 shall be calculated as follows:

FIXED SETPOINT FOR 1/2-RI-4014 Sfix < Ksf { ( Fd / Fu ) [ ( AiLn ) ( ei ) ] + Bkg } Eq. 1L1

Where, Sfix = The fixed setpoint for 1/2-RI-4014 (cpm)

Ksf = A constant, actually a safety factor, which is the ratio of the CCNPP activity limit to the 10 CFR 20, Appendix B, Table II, Column 2 MPC limit (unitless)

The safety factor chosen shall be less than or equal to 1.00. This ensures the fixed setpoint is always less than or equal to the limits of 10 CFR 20.

A safety factor of 1.00 will yield a fixed setpoint which corresponds to 1.0 MPC.

A safety factor of 0.500 will yield a fixed setpoint which corresponds to 0.5 MPCs.

It is recommended that a safety factor of 0.5 be used for calculating the fixed setpoint, however, other values--not to exceed 1.00--may be used as directed by Management.

The use of a safety margin is per the provisions of NUREG-0133, SECTION 4.1.1, which states, "The alarm and trip setpoints ... should correspond to a value(s) which represents a safe margin of assurance that the instantaneous liquid release limit of 10 CFR Part 20 is not exceeded."

This safety margin will prevent minor fluctuations in the nominal circulating water flow rate (and other statistical aberrations) from adversely impacting the calculated fixed setpoint.

Fd = The dilution water flow rate (gpm) before the point of release to UNRESTRICTED AREAS The dilution water flow rate is actually the sum of the minimum circulating water flow rate, the minimum salt water flow rate, and the maximum undiluted radwaste flow rate.

The dilution water flow rate shall be calculated per equation 2L.

1 Equation 1L has been derived from NUREG-0133, Addendum, page AA-1.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 86 of 321 Level 3 - Information DILUTION WATER FLOW RATE Fd = Fcw + Fsw + Fu Eq. 2L Fcw = The minimum circulating water system flow rate necessary to conduct liquid releases A minimum of two circulating water pumps (one circulating water pump per conduit accepting radwaste) shall be operable when discharging liquid radwaste -- via this monitor -- to Outfall 001.

The flow rate of each circulating water pump is 200,000 gallons per minute.

Additional circulating water pumps may be required as specified in approved Chemistry procedures.

If a release of liquid radwaste from the Steam Generator Blowdown System is to be conducted using less than minimum circulating water flow rate necessary to conduct liquid releases, the release shall not be allowed until a new setpoint has been calculated and entered into 1/2-RI-4014 (unless the existing setpoint is conservative), or otherwise comply with the ACTION requirements of Control 3.3.3.10.

Fsw = The minimum salt water system flow rate necessary to release liquid radwaste If the minimum salt water flow rate available for liquid releases is unknown, difficult to predict, or may decrease during a liquid release, a minimum salt water flow rate of 0 gpm should be used when calculating the fixed setpoint.

The maximum flow rate for one salt water pump is listed on Attachment 2.

If a release of liquid radwaste is to be conducted using less than the minimum salt water flow rate necessary to conduct liquid releases, the release shall not be allowed until a new setpoint has been calculated and entered into 1/2-RI-4014 (unless the existing setpoint is conservative),

or otherwise comply with the ACTION requirements of Control 3.3.3.10.

Fu = Maximum undiluted radwaste flow rate (gpm)

Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachment 2.

Since the Steam Generator Blowdown flow rate (225 gpm maximum) is insignificant relative to the circulating water flow rate (200,000 gpm per circulating water pump), the Steam Generator Blowdown Flow Rate need not be considered when calculating the Dilution Water Flow Rate.

Since the maximum undiluted Radwaste Flow Rate is used for calculating the fixed setpoint, a flow setpoint is not required--for the flow measuring device in the effluent line--to verify compliance with Control 3.3.3.10.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 87 of 321 Level 3 - Information AiLn = Specific activity limit for the release of radionuclide, i, to UNRESTRICTED AREAS (calculated per 10 CFR 20, Appendix B, Table II, Note 1, as described below; microcuries per milliliter):

In order to calculate a meaningful and accurate fixed setpoint, the specific radionuclides, i, chosen for calculating the fixed setpoint should correspond to those radionuclides found in TYPICAL RADWASTE RELEASES from CCNPP.

Attachment 5 provides further guidance for determining which radionuclides, i, should be used to calculate a fixed setpoint. An acceptable alternative is to assume an isotopic mix which results in a more conservative setpoint.

Values for AiLn shall be calculated, as described below, for each radionuclide.

SPECIFIC ACTIVITY LIMIT FOR RADIONUCLIDE, i AiLn = ( fi ) ( ATLn ) Eq. 3L fi = A fraction which represents the relative activity contribution of nuclide i to the average total effluent activity (unitless)

The average total effluent activity does not include tritium or dissolved and entrained noble gases.

This value may be obtained using the guidance provided on Attachment 5.

ATLn = The sum of the total specific activities of all radionuclides found in a TYPICAL LIQUID RADWASTE RELEASE (microcuries/cm3)

This value corresponds to 1 MPC.

Calculate the value of ATLn as shown below:

TOTAL SPECIFIC ACTIVITY CORRESPONDING TO 1 MPC AT THE SITE BOUNDARY

[ ( fi ) ( ATLn ) / AiLt ] = 1 Eq. 4L1 AiLt = The specific activity limit for radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table II, Column 2 (microcuries/cm3).

For all the radionuclides found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B, Table II, Column 2.

1 This formula has been derived from 10 CFR 20, Appendix B, Table II, Notes 1, 2, and 3.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 88 of 321 Level 3 - Information 1 = The MPC limit (MPCs) for UNRESTRICTED AREAS This value is based on the MPC limit from 10 CFR 20, Appendix B, Table II, Note 1.

ei = Absolute detector efficiency for nuclide, i (cpm/microcuries per milliliter)

The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor.

Bkg = An approximation of the detector background (cpm)

Instead of using an approximation of the detector background, a value of 0 cpm may be used as the detector background if so desired.

(3) Documenting the fixed setpoint for 1/2-RI-4014 (a) Whenever the fixed setpoint is calculated, the specific values chosen for each of the variables shall be documented per CC-AA-103-2001.

(4) Changing the fixed setpoint for 1/2-RI-4014 (a) If the fixed setpoint calculated per equation 1L exceeds the maximum range of the monitor, the fixed setpoint shall be adjusted to a value which falls within the normal operating range of the monitor.

(b) The fixed setpoint may be established at values lower than the maximum allowable setpoint, if desired.

(c) A setpoint change should be initiated whenever any of the parameters identified in equation 1L (identified in this section of the ODCM) have changed.

(d) The fixed setpoint should not be changed unless one of the following occurs:

i) The relative activity1 of any radionuclide in TYPICAL LIQUID EFFLUENTS has changed by greater than 10%, and the new radionuclide mixture yields a fixed setpoint which is 10% (or more) lower than the current fixed setpoint, ii) The minimum dilution water flow rate is not available for a liquid release, iii) The values listed in 10 CFR 20, Appendix B, Table II, Column 2, have changed, 1 As determined in accordance with Attachment 5.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 89 of 321 Level 3 - Information iv) The radiation monitor has been recently calibrated, repaired, or otherwise altered, or v) The monitor is not conservative in its function (see Functions of 1/2-RE-4014, earlier in this section).

(e) CC-AA-103-2001 contains the administrative controls associated with changing and approving the fixed setpoint.

i) The adjustable setpoint for 1/2-RI-4014 (1) General information (a) The adjustable setpoint is calculated and adjusted before each release from the Steam Generator Blowdown Processing System.

(b) The adjustable setpoint is based on the specific activities of the radionuclides present in the undiluted liquid waste (as determined by radiochemical analysis per Control 4.11.1.1.1).

(c) Whenever the adjustable setpoint is exceeded, discharges from the Steam Generator Blowdown Processing System will be manually suspended.

(d) See OI-8A for a full list of operator ACTIONS taken in response to this alarm.

(e) The adjustable setpoint corresponds to the maximum concentration of radionuclides anticipated or expected in discharges from the Steam Generator Blowdown Processing System.

(f) The value for the adjustable setpoint is recorded on the liquid release permit per Chemistry procedures.

(g) This alarm is not integral to the Steam Generator Blowdown Tank Radiation Monitor, as purchased from the supplier.

(h) This alarm is generated by the plant computer which monitors output from 1/2-RI-4014, and provides an alarm to plant operators, when the 1/2-RI-4014 adjustable setpoint has been exceeded.

(i) A value for the adjustable setpoint shall be calculated before each release as shown below.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 90 of 321 Level 3 - Information (2) Calculating the adjustable setpoint for 1/2-RI-4014 (a) The adjustable setpoint is based on the specific activity of the radionuclides in the undiluted liquid waste (as determined by radiochemical analysis per Control 4.11.1.1.1), and is calculated as shown below:

ADJUSTABLE SETPOINT FOR 1/2-RI-4014 Sadj < 2.50 [ ( Aiu ) ( ei ) + Bkg ] Eq. 5L1 Sadj = The adjustable setpoint for 1/2-RI-4014 (cpm) 2.50 = A constant, actually a safety factor, which allows for fluctuation in radiation monitor response (unitless)

This safety factor helps ensure the release is not unnecessarily terminated due to:

(1) electronic anomalies which cause spurious monitor responses (2) statistical fluctuations in disintegration rates (3) statistical fluctuations in detector efficiencies (4) uncertainties associated with sample analysis, and (5) uncertainties associated with monitor calibrations.2 Aiu = Specific activity of radionuclide, i, in the undiluted waste stream (microcuries per milliliter) ei = Absolute detector efficiency for nuclide, i (cpm/microcuries per milliliter)

The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor.

Bkg = An approximation of the detector background (cpm)

(3) Documenting the adjustable setpoint for 1/2-RI-4014 (a) Whenever the adjustable setpoint is calculated, the specific values chosen for each of the variables shall be documented per approved Chemistry procedures.

(4) Changing the adjustable setpoint for 1/2-RI-4014 (a) If the adjustable setpoint exceeds the maximum range of the monitor, the setpoint shall be adjusted to a value which falls within the normal operating range of the monitor.

1 Equation 5L has been derived from NUREG-0133, Addendum, page AA-1.

2 The analysis uncertainties and calibration uncertainties refer to uncertainties which are within established quality assurance and quality control limits.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 91 of 321 Level 3 - Information (b) In all cases, the adjustable setpoint shall be set to a value which is less than or equal to the fixed setpoint.

(c) Chemistry procedures contain administrative controls associated with calculating and approving an adjustable setpoint.

(d) Whenever 1/2-RI-4014 is operable, the calculated value for the adjustable setpoint shall be entered into the plant computer before each release from the Steam Generator Blowdown Processing System.

(e) Plant Operating Instructions (for example, OI-8A) contain administrative controls associated with entering the adjustable setpoint in the plant computer.

j) The low alarm setpoint for 1/2-RI-4014 (1) This alarm is integral to the Steam Generator Blowdown tank monitor, as purchased from the manufacturer.

(2) The current value for the low alarm setpoint is specified in the CCNPP Alarm Manual.

(3) Changes to the low alarm setpoint are administratively controlled in the CCNPP Alarm Manual.

(4) The ODCM does not address the calculations associated with the low alarm setpoint.

LIMITS ON RADIONUCLIDE CONCENTRATIONS IN LIQUID EFFLUENTS

1. Introduction a) 10 CFR 20, Appendix B, specifies concentration limits associated with the release of radioactive materials to UNRESTRICTED AREAS.

b) Radiological effluent controls have been established to implement the requirements of 10 CFR 20.

c) These radiological effluent controls are described below.

2. Radiological Effluent Controls a) The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases (per Control 3.11.1.1).

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 92 of 321 Level 3 - Information b) It should be noted that NUREG-0133 specifies that the concentration of radioactive materials in liquid effluents to UNRESTRICTED AREAS shall be limited to 2 E-4 microcuries per milliliter for dissolved or entrained noble gases, this control has not been incorporated into the CCNPP Technical Specifications, and as a result, the ODCM does not include calculations for same.

c) The routine surveillances which are performed to verify compliance with these radiological effluent controls are described below.

3. Surveillance Requirements a) Routine surveillances for BATCH RELEASES (1) Sample each BATCH of radioactive liquid waste before its release (per Control 4.11.1.1.1).

(2) Determine the concentrations of principle gamma emitters (including, but not limited to, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, Cs-137, Ce-141, I-131, Mo-99, and Ce-144) in the BATCH sample, before the BATCH release (per Control 4.11.1.1.1).

(3) Determine the concentration of tritium contained in a monthly COMPOSITE SAMPLE at least once per month (per Control 4.11.1.1.1).

(4) Determine the concentrations of Sr-89 and Sr-90 contained in a quarterly COMPOSITE SAMPLE at least once per quarter (per Control 4.11.1.1.1).

(5) Calculate the concentrations of radionuclides in the receiving waters at the point the liquid radioactive waste is released to UNRESTRICTED AREAS (per Control 4.11.1.1.2).

b) Routine surveillances for CONTINUOUS RELEASES (1) Sample CONTINUOUS RELEASES of radioactive liquid waste at least once per month (per Control 4.11.1.1.1).

(2) Determine the concentrations of principle gamma emitters (including, but not limited to, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, Cs-137, Ce-141, I-131, Mo-99, and Ce-144) in the undiluted, CONTINUOUS waste stream sample (per Control 4.11.1.1.1).

(3) Calculate the concentrations of radionuclides in the receiving waters at the point the liquid radioactive waste is released to UNRESTRICTED AREAS (per Control 4.11.1.1.2).

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 93 of 321 Level 3 - Information

4. Responsible Plant Organizations a) The Chemistry is responsible for performing the sampling, analysis, and calculations required by the above surveillances.

b) The conditions which initiate the required surveillances are contained in the following section.

5. Initiating Conditions a) The surveillances for BATCH RELEASES shall be performed before each BATCH RELEASE1 and may be performed more often as specified in approved Chemistry procedures.

b) The surveillances for CONTINUOUS RELEASES shall be performed at least monthly2 (until the CONTINUOUS RELEASE has been terminated) and, if activity is identified3 in the CONTINUOUS waste stream, the surveillances may be performed more often as specified in approved Chemistry procedures.

6. Calculation Methodology a) At CCNPP, there are two methods for calculating the concentrations of radionuclides in the receiving waters, at the point of release to UNRESTRICTED AREAS, resulting from the discharge of liquid waste.

(1) The rigorous method shall be used IF a computer system and the appropriate software are available.

(2) The simplified method may be used IF a computer system and the appropriate software are NOT available.

(3) These methods, as well as additional supporting information, are presented in the following sections.

b) Rigorous method (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropriate software are available.

(2) If a computer system and the appropriate software are available, ensure the concentrations of radionuclides in UNRESTRICTED AREAS are less than one MPC by verifying the following inequality is true:

1 Per Control 4.11.1.1.1.

2 Per Control 4.11.1.1.1.

3 The LOWER LIMITS OF DETECTION shall conform to Control 4.11.1.1.1, Table 4.11-1.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 94 of 321 Level 3 - Information LIMIT ON CONCENTRATIONS OF RADIONUCLIDES IN UNRESTRICTED AREAS (RIGOROUS METHOD)

( Fu / Fd ) ( Aiu / AiLt ) < 1 Eq. 6L1 Fd = The actual dilution water flow rate (gpm) before the point of release to UNRESTRICTED AREAS The actual dilution water flow rate is the sum of the circulating water flow rate, the salt water flow rate, and the undiluted radwaste flow rate.

The dilution water flow rate shall be calculated per equation 2L.

DILUTION WATER FLOW RATE Fd = Fcw + Fsw + Fu Eq. 2L Fcw = The actual circulating water system flow rate The flow rate of each circulating water pump is 200,000 gallons per minute.

Fsw = The salt water system flow rate If the actual salt water flow rate is unknown or otherwise not readily available, a salt water flow rate of 0 gpm may be used in equation 2L.

The maximum flow rate for one salt water pump is listed on Attachment 2.

Fu = Actual undiluted radwaste flow rate (gpm)

If the actual undiluted radwaste flow rate is less than 1% of the total dilution water flow rate, an undiluted radwaste flow rate of 0 gpm may be used in equation 2L.

Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachment 2.

AiLt = The specific activity limit for radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table II, Column 2 (microcuries/cm3)

Aiu = The specific activity of nuclide, i, in the undiluted liquid radwaste (microcuries per milliliter) 1 = The MPC limit (MPCs) for UNRESTRICTED AREAS This value is based on the MPC limit from 10 CFR 20, Appendix B, Table II, Note 1.

c) Simplified method (1) Whenever a computer system and appropriate software are unavailable to perform the rigorous calculations described in the previous section, ensure the 1 Equation 6L has been derived from 10 CFR 20, Appendix B, Table II, Note 1.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 95 of 321 Level 3 - Information concentrations of radionuclides in UNRESTRICTED AREAS are less than one MPC by verifying the following inequality is true.

LIMIT ON CONCENTRATIONS OF RADIONUCLIDES IN UNRESTRICTED AREAS (SIMPLIFIED METHOD)

{ Fu / [ ( Fd ) ( AI131Lt ) ( Ksf ) ] } Aiu < 1 Eq. 7L1 Fu = Actual undiluted radwaste flow rate (gpm)

If the actual undiluted radwaste flow rate is less than 1% of the total dilution water flow rate, an undiluted radwaste flow rate of 0 gpm may be used in equation 2L.

Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachment 2.

Fd = The actual dilution water flow rate (gpm) before the point of release to UNRESTRICTED AREAS The actual dilution water flow rate is the sum of the circulating water flow rate, the salt water flow rate, and the undiluted radwaste flow rate.

DILUTION WATER FLOW RATE Fd = Fcw + Fsw + Fu Eq. 2L Fcw = The actual circulating water system flow rate The flow rate of each circulating water pump is 200,000 gallons per minute.

Fsw = The actual salt water system flow rate If the actual salt water flow rate is unknown or otherwise not readily available a salt water flow rate of 0 gpm may be used in equation 2L.

The maximum flow rate for one salt water pump is listed on Attachment 2.

AI131Lt = The specific activity limit for I-131 corresponding to the limiting concentration specified in 10 CFR 20, Appendix B, Table II, Column 2 This value is 3E-7 microcuries per milliliter.

Aiu = The specific activity of nuclide, i, in the undiluted liquid radwaste (microcuries per milliliter)

Ksf = A constant, actually a safety factor, which is the ratio of the CCNPP activity limit to the activity limit of 10 CFR 20, Appendix B, Table II, Column 2, (unitless) (per Control 3.11.1.1)

The safety factor chosen shall be less than or equal to 1.00. This ensures the activity is always less than or equal to the activity limit of 10 CFR 20, Appendix B, Table II, Column 2.

1 This equation has been derived from 10 CFR 20, Appendix B, Table II, Note 1.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 96 of 321 Level 3 - Information 1 = The MPC limit (MPCs) for UNRESTRICTED AREAS This value is based on the MPC limit from 10 CFR 20, Appendix B, Table II, Note 1.

A safety factor of 1.00 will yield a activity which corresponds to the 10 CFR 20, Appendix B, Table II, Column 2, activity limit.

A safety factor of 0.500 will yield an activity which corresponds to one-half the activity limit of 10 CFR 20, Appendix B, Table II, Column 2.

It is recommended that a safety factor of 1.0 be used for calculating the activity, however, other values--not to exceed 1.00--may be used as directed by Management.

The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive liquid release permits. This administrative control is designed to minimize the possibility of violating 10 CFR 20, Appendix B, Table II, Column 2, limits whenever simplifying assumptions are used.

The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

This safety factor has been included in equation 7L to account for any potential nonconservatism associated with applying the I-131 MPC limit to all radionuclides identified in the liquid release. Such nonconservatism could conceivable be present whenever radionuclides which have an MPC value higher than the I-131 MPC limit are present in a liquid release.

d) Once the rigorous or simplified calculations have been completed, the calculation results are compared to the applicable limits and corrective ACTIONS are initiated as described below.

7. Corrective ACTIONS a) Chemistry surveillance procedures shall contain and/or reference administrative and/or Technical Specification limits for concentration of radionuclides in liquid effluents and shall specify corrective ACTIONS to be initiated when these limits are exceeded.

b) Refer to Control 3.11.1.1 for ACTIONS to be taken in the event the concentrations of radionuclides in UNRESTRICTED AREAS exceed one MPC.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 97 of 321 Level 3 - Information LIMITS ON CUMULATIVE TOTAL BODY DOSES AND CUMULATIVE ORGAN DOSES FOR LIQUID EFFLUENTS

1. Introduction a) Appendix I to 10 CFR 50 specifies total body dose limits and organ dose limits associated with the release of radioactive liquids to UNRESTRICTED AREAS.

b) Radiological effluent controls have been established to implement the requirements of 10 CFR 50, Appendix I.

c) These radiological effluent controls are described below.

2. Radiological Effluent Controls a) The total body dose to MEMBERS OF THE PUBLIC, from liquid waste discharged to UNRESTRICTED AREAS, shall be less than 3 mrems per calendar quarter and 6 mrems per calendar year (Control 3.11.1.2).

b) The organ doses to MEMBERS OF THE PUBLIC, from liquid waste discharged to UNRESTRICTED AREAS, shall be less than 10 mrems per calendar quarter and 20 mrems per calendar year (Control 3.11.1.2).

c) The routine surveillances which are performed to verify compliance with these radiological effluent controls are described below.

3. Surveillance Requirement(s) a) Cumulative total body doses to MEMBERS OF THE PUBLIC in UNRESTRICTED AREAS--for the current calendar month, the calendar quarter, the current calendar year, and the previous 92 days--shall be calculated, per equation 8L, at least once per 31 days (per Control 4.11.1.2 and 4.11.1.3).

b) Cumulative organ doses to MEMBERS OF THE PUBLIC in UNRESTRICTED AREAS--for the current calendar month, the current calendar quarter, the current calendar year, and the previous 92 days--shall be calculated, per equation 8L, at least once per 31 days (per Control 4.11.1.2 and 4.11.1.3).

4. Responsible Plant Organizations a) The Chemistry is responsible for performing the surveillances, listed above, whenever the appropriate initiating conditions, listed below, are present.

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5. Initiating Conditions a) Perform the surveillances, listed above, at least once per 31 days (per Control 4.11.1.2).

b) For BATCH RELEASES, perform the surveillances, listed above, before each BATCH RELEASE of radioactive liquid waste per approved Chemistry procedures.

c) For CONTINUOUS RELEASES, perform the surveillances, listed above, at least monthly (until the CONTINUOUS RELEASE has been terminated) and, if activity is identified1 in the CONTINUOUS waste stream, the surveillances may be performed more often as specified in approved Chemistry procedures.

d) Whenever the correct initiating conditions are present, the calculations required by the above mentioned surveillance(s) shall be completed per the methodology listed in the next section.

6. Calculation Methodology a) The cumulative total body dose and the cumulative organ doses (for the current calendar month, current calendar quarter, previous 92 days, and current calendar year) shall be calculated as follows:

CUMULATIVE TOTAL BODY OR ORGAN, o, DOSE FROM LIQUID RELEASES, r DToL = Dor Eq. 8L DToL = The sum total of the total body or organ, o, dose for all liquid releases discharged during the applicable time interval Dor = The organ or total body dose resulting from release, r Calculate the values of Dor for each liquid release as described below.

b) At CCNPP, two methods exist for calculating Dor (that is, the total body and organ doses resulting from any single release of radioactive liquid to an UNRESTRICTED AREA).

(1) The rigorous method shall be used IF a computer system and the appropriate software are available.

(2) The simplified method may be used IF a computer system and the appropriate software are NOT available.

(3) These methods, as well as additional supporting information, are presented in the following sections.

1 The LOWER LIMITS OF DETECTION shall conform to Control 4.11.1.1.1, Table 4.11-1.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 99 of 321 Level 3 - Information c) Rigorous method (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropriate software are available.

(2) If a computer system and the appropriate software are available, the dose commitments due to each release of radioactive liquid to an UNRESTRICTED AREA shall be calculated per the following equation:

DOSE TO THE TOTAL BODY OR ORGAN, o, FROM A LIQUID RELEASE (RIGOROUS EQUATION)

Do = { Vu / [ ( 60 )( Fd ) ] } { ( Aiu ) ( Cio ) } Eq. 9L1

Where, Fd = Actual dilution water flow rate (gpm) before the point of release to UNRESTRICTED AREAS The actual dilution water flow rate is the sum of the circulating water flow rate, the salt water flow rate, and the undiluted radwaste flow rate.

The dilution water flow rate shall be calculated per equation 2L.

DILUTION WATER FLOW RATE Fd = Fcw + Fsw + Fu Eq. 2L Fcw = Actual circulating water system flow rate The flow rate of each circulating water pump is 200,000 gallons per minute.

Fsw = Actual salt water system flow rate If the actual salt water flow rate is unknown or otherwise not readily available a salt water flow rate of 0 gpm may be used in equation 2L.

The maximum flow rate for one salt water pump is listed on Attachment 2.

Fu = Actual undiluted radwaste flow rate (gpm)

If the actual undiluted radwaste flow rate is less than 1% of the total dilution water flow rate, an undiluted radwaste flow rate of 0 gpm may be used in equation 2L.

Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachment 2.

Vu = Volume of undiluted radwaste (gallons) 1 Equation 9L has been derived from NUREG-0133, 4.3.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 100 of 321 Level 3 - Information Aiu = Specific activity of nuclide, i, in the undiluted liquid radwaste (microcuries per milliliter)

Cio = Liquid release dose factor for nuclide, i, and organ, o (mrem/hr per microcurie/ml)

The liquid release dose factors for principal gamma and beta emitters are listed in Attachment 6.

The liquid release dose factors for principal gamma and beta emitters were obtained per the methodology of NUREG-0133, Section 4.3.1 (for salt water sites).

60 = A constant, the number of minutes per hour (3) In the event a computer system is unavailable, a simplified equation may be used to calculate the total body and organ dose commitments due to individual liquid releases.

(4) The simplified method is presented below.

d) Simplified methods (1) Whenever a computer system is unavailable to perform the rigorous total body dose calculations described in the previous section, the total body dose commitments--due to each release of radioactive liquid to an UNRESTRICTED AREA--may be calculated per equation 10L.

(2) Whenever a computer system is unavailable to perform the rigorous organ dose calculations described in the previous section, the dose commitments--

to the maximum exposed organ, due to each release of radioactive liquid to an UNRESTRICTED AREA--may be calculated per equation 11L.

TOTAL BODY DOSE FROM A LIQUID RELEASE (SIMPLIFIED EQUATION)

Dtb = { [ ( 58.6 ) ( Vu ) ] / [ ( Ksf ) ( Fd ) ] } Aiu Eq. 10L1 Dtb = Dose commitment, to the total body, due to each release of radioactive liquid to an UNRESTRICTED AREA 58.6 = A conversion constant which includes:

1) 1.33E4 mrem/hr per microcurie/ml (the total body dose factor for Cs-134)
2) 1.000 hr/60.00 min
3) 1.000 gallons/3.785 liters Vu = Volume of undiluted radwaste (liters) 1 Equations 10L has been derived from NUREG-0133, 4.3.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 101 of 321 Level 3 - Information Ksf = A constant, actually a safety factor, which is the ratio of the CCNPP total body dose limit to the total body dose limit of Control 3.11.1.2, (unitless)

The safety factor chosen shall be less than or equal to 1.00. This ensures the total body dose is always less than or equal to the total body dose limit of Control 3.11.1.2.

A safety factor of 1.00 will yield a total body dose which corresponds to the total body dose limit of Control 3.11.1.2.

A safety factor of 0.500 will yield an total body dose which corresponds to one-half the total body dose limit of Control 3.11.1.2.

It is recommended that a safety factor of 1.0 be used for calculating the total body dose, however, other values--not to exceed 1.00--may be used as directed by Management.

The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive liquid release permits. This administrative control is designed to minimize the possibility of violating Control 3.11.1.2 when simplifying assumptions are used.

The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

This safety factor has been included in equation 10L to account for any potential nonconservatism associated with applying the Cs-134 total body dose conversion factor to all radionuclides identified in the liquid release. Such nonconservatism could conceivable be present whenever radionuclides having a dose conversion factor greater than that of Cs-134 are present in a liquid release.

Fd = Actual dilution water flow rate (gpm) before the point of release to UNRESTRICTED AREAS The actual dilution water flow rate is the sum of the circulating water flow rate, the salt water flow rate, and the undiluted radwaste flow rate.

The dilution water flow rate shall be calculated per equation 2L.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 102 of 321 Level 3 - Information DILUTION WATER FLOW RATE Fd = Fcw + Fsw + Fu Eq. 2L Fcw = Actual circulating water system flow rate The flow rate of each circulating water pump is 200,000 gallons per minute.

Fsw = Actual salt water system flow rate If the actual salt water flow rate is unknown or otherwise not readily available, a salt water flow rate of 0 gpm may be used in equation 2L.

The maximum flow rate for one salt water pump is listed on Attachment 2.

Fu = Actual undiluted radwaste flow rate (gpm)

If the actual undiluted radwaste flow rate is less than 1% of the total dilution water flow rate, an undiluted radwaste flow rate of 0 gpm may be used in equation 2L.

Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachment 2.

Aiu = Specific activity of nuclide, i, in the undiluted liquid radwaste (microcuries per milliliter)

DOSE TO THE ORGAN, o, FROM A LIQUID RELEASE (SIMPLIFIED EQUATION)

Do = { [ ( 449 ) ( Vu ) ] / [ ( Ksf ) ( Fd ) ] } Aiu Eq. 11L1 Do = The dose commitment to the maximum exposed ORGAN due to each release of radioactive liquid waste to an UNRESTRICTED AREA 449 = A conversion constant which includes:

1) 1.02E5 mrem/hr per microcurie/ml (the dose factor for I-131 to the thyroid)
2) 1.000 hr/60.00 min
3) 1.000 gallons/3.785 liters Vu = Volume of undiluted radwaste (liters)

Ksf = A constant, actually a safety factor, which is the ratio of the CCNPP organ dose limit to the organ dose limit of Control 3.11.1.2, (unitless) 1 Equations 11L has been derived from NUREG-0133, 4.3.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 103 of 321 Level 3 - Information The safety factor chosen shall be less than or equal to 1.00. This ensures the organ dose is always less than or equal to the organ dose limit of Control 3.11.1.2.

A safety factor of 1.00 will yield a organ dose which corresponds to the organ dose limit of Control 3.11.1.2.

A safety factor of 0.500 will yield an organ dose which corresponds to one-half the organ dose limit of Control 3.11.1.2.

It is recommended that a safety factor of 1.0 be used for calculating the organ dose, however, other values--not to exceed 1.00--may be used as directed by Management.

The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive liquid release permits. This administrative control is designed to minimize the possibility of violating Control 3.11.1.2 when simplifying assumptions are used.

The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

This safety factor has been included in equation 11L to account for any potential nonconservatism associated with applying the I-131 thyroid dose conversion factor to all radionuclides identified in the liquid release. Such nonconservatism could conceivable be present whenever radionuclides having a dose conversion factor greater than that of I-131 are present in a liquid release.

Fd = Dilution water flow rate (gpm) before the point of release to UNRESTRICTED AREAS The actual dilution water flow rate is the sum of the circulating water flow rate, the salt water flow rate, and the undiluted radwaste flow rate.

The dilution water flow rate shall be calculated per equation 2L.

DILUTION WATER FLOW RATE Fd = Fcw + Fsw + Fu Eq. 2L Fcw = Actual circulating water system flow rate The flow rate of each circulating water pump is 200,000 gallons per minute.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 104 of 321 Level 3 - Information Fsw = Salt water system flow rate If the actual salt water flow rate is unknown or otherwise not readily available, a salt water flow rate of 0 gpm may be used in equation 2L.

The maximum flow rate for one salt water pump is listed on Attachment 2.

Fu = Actual undiluted radwaste flow rate (gpm)

If the actual undiluted radwaste flow rate is less than 1% of the total dilution water flow rate, an undiluted radwaste flow rate of 0 gpm may be used in equation 2L.

Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachment 2.

Aiu = Specific activity of nuclide, i, in the undiluted liquid radwaste (microcuries per milliliter)

7. Corrective ACTIONS a) Chemistry surveillance procedures shall contain and/or reference administrative and/or Control limits for cumulative total body doses or cumulative organ doses resulting from liquid effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Control 3.11.1.2 for actions to be taken in the event the calculated cumulative total body dose exceeds 3 mrem per calendar quarter or 6 mrem per calendar year.

c) Refer to Control 3.11.1.2 for actions to be taken in the event the calculated cumulative organ dose--for any organ--exceeds 10 mrem per calendar quarter or 20 mrem per calendar year.

LIMITS FOR THE LIQUID WASTE PROCESSING SYSTEM

1. Introduction a) 10 CFR 50.36a requires licensees to maintain and use the equipment installed in the Liquid Waste Processing System for the purpose of controlling effluents to the environment.

b) Radiological effluent controls have been established to implement the requirements of 10 CFR 50.36a.

c) Different documents (for example, Technical Specifications or NUREG-0472) may reference this effluent control using a variety of synonyms. Examples of some of these synonyms include terms such as the PROJECTED DOSE, the 92-DAY PROJECTED DOSE, the 92-DAY CUMULATIVE DOSE, the DOSE IN A 92-DAY PERIOD, or the DOSE FOR THE PREVIOUS 92 DAYS. The ODCM methodology for calculating this dose - by whatever name - is based on a simple sum of the dose contributions for the previous 92 days. As result, all the terms listed above are considered as equivalent quantities for purposes of this effluent control at CCNPP.

For simplicity, the ODCM generally uses the phrase dose for the previous 92 days when referencing this effluent control.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 105 of 321 Level 3 - Information d) These radiological effluent controls are described below.

2. Radiological Effluent Controls a) The liquid radwaste processing system shall be used to reduce the quantity of radioactive materials in liquid waste released to the environment whenever the total body dose to MEMBERS OF THE PUBLIC, from liquid waste discharged to UNRESTRICTED AREAS, is greater than 0.36 mrem for the previous 92 days (per Control 3.11.1.3).

b) The liquid radwaste processing system shall be used to reduce the quantity of radioactive materials in liquid waste released to the environment whenever the organ doses to MEMBERS OF THE PUBLIC, from liquid waste discharged to UNRESTRICTED AREAS, is greater than 1.20 mrem for the previous 92 days (per Control 3.11.1.3).

c) The routine surveillances which are performed to verify compliance with this radiological effluent controls are described below.

3. Surveillance Requirement(s) a) The previous 92-day, cumulative, total body dose--to MEMBERS OF THE PUBLIC in UNRESTRICTED AREAS--shall be calculated, as described in the ODCM, at least once per 31 days (per Control 4.11.1.3).

b) The previous 92-day, cumulative, organ doses--to MEMBERS OF THE PUBLIC in UNRESTRICTED AREAS--shall be calculated, as described in the ODCM, at least once per 31 days (per Control 4.11.1.3).

c) The CCNPP organization(s) responsible for performing these surveillances are identified in the next section.

4. Responsible Plant Organization(s) a) The Chemistry is responsible for performing the surveillances, listed above, whenever the appropriate initiating conditions, listed below, are present.
5. Initiating Conditions a) Perform the surveillances, listed above, at least once per 31 days (per Control 4.11.1.3).

b) For BATCH RELEASES, perform the surveillances, listed above, before each BATCH RELEASE of radioactive liquid waste per approved Chemistry procedures.

c) For CONTINUOUS RELEASES, perform the surveillances, listed above, at least monthly (until the CONTINUOUS RELEASE has been terminated) and, if activity is December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 106 of 321 Level 3 - Information identified1 in the CONTINUOUS waste stream, the surveillances may be performed more often as specified in approved Chemistry procedures.

d) Whenever the correct initiating conditions are present, the calculations required by the above mentioned surveillance(s) shall be completed per the methodology contained in the following section.

6. Calculation Methodology a) The cumulative total body dose and the cumulative organ doses for the previous 92 days shall be calculated per equation 8L found in the section, Limits On Cumulative Total Body Doses And Cumulative Organ Doses For Liquid Effluents, found elsewhere in the ODCM.
7. Corrective ACTIONS a) Chemistry surveillance procedures shall contain/and or reference administrative and/or Control limits for cumulative total body doses or cumulative organ doses resulting from liquid effluents and shall specify corrective ACTIONS to be initiated when these limits are exceeded.

b) Refer to Control 3.11.1.3 for ACTIONS to be taken in the event the calculated cumulative total body dose exceeds 0.36 mrem for the previous 92 days.

c) Refer to Control 3.11.1.3 for ACTIONS to be taken in the event the calculated cumulative organ dose--for any organ--exceeds 1.2 mrem for the previous 92 days.

1 The LOWER LIMITS OF DETECTION shall conform to Control 4.11.1.1.1, Table 4.11-1.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 107 of 321 Level 3 - Information RADIOACTIVE GASEOUS EFFLUENTS RELEASE PATHWAYS [B527]

1. Introduction a) Radioactive gaseous waste generated from operation of CCNPP may be released to the atmosphere.

b) By design (that is, in the absence of primary-to-secondary leaks), there are 2 pathways by which waste gas from the site may be discharged to the atmosphere.

These pathways are listed below. General information related to each of these potential release pathways is contained on Attachment 7.

(1) Unit 1 Main Vent Stack (2) Unit 2 Main Vent Stack c) Depending on plant conditions, (for example, primary-to-secondary leaks) a potential exists for the release of radioactive materials from other pathways. Examples of these pathways are listed below. General information related to each of these potential release pathways is contained on Attachment 8.

(1) Auxiliary boiler deaerator (2) Steam generator atmospheric steam dump system (3) Plant nitrogen system (4) Turbine building ventilation exhaust (5) Emergency air lock (6) Plant compressed air (7) Main steam line penetrations (8) Containment equipment hatch (9) Auxiliary feed pumps (10) Gland steam exhaust condenser (11) RWT d) All of these pathways are described below.

2. Unit 1 Main Vent Stack December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 108 of 321 Level 3 - Information a) Dilution air and radioactive gaseous waste are discharged to the atmosphere through the Unit 1 Main Vent Stack.

b) The radioactive gaseous waste is mixed with and diluted by the outside air and building exhausts before exiting the Unit 1 Main Vent Stack.

c) The Unit 1 Main Vent Stack is secured to the Unit 1 Reactor Containment Building.

d) The top of the Unit 1 Main Vent Stack is at elevation 203.5 feet (mean sea level, MSL), and as such is 10.1 feet above the top of the Reactor Containment Building dome. As a result, the Unit 1 Main Vent Stack does not qualify as a free-standing stack greater than 80 meters tall1.

e) The Unit 1 Main Vent Stack is designed to accept gaseous radioactive waste from various sources. Sources which may contribute radioactive material to the Unit 1 Main Vent Stack are tabulated in Attachment 7.

3. Unit 2 Main Vent Stack a) Dilution air and radioactive gaseous waste are discharged to the atmosphere through the Unit 2 Main Vent Stack.

b) The Unit 2 Main Vent Stack is designed to accept radioactive gaseous waste from various sources.

c) The radioactive gaseous waste is mixed with and diluted by the outside air and building exhausts before exiting the Unit 2 Main Vent Stack.

d) The Unit 2 Main Vent Stack is secured to the Unit 2 Reactor Containment Building.

e) The top of the Unit 2 Main Vent Stack is at elevation 203.5 feet (MSL), and as such is 10.1 feet above the top of the Reactor Containment Building dome. As a result, the Unit 2 Main Vent Stack does not qualify as a free-standing stack greater than 1

80 meters tall.

f) The Unit 2 Main Vent Stack is designed to accept gaseous radioactive waste from various sources. Sources which may contribute radioactive material to the Unit 2 Main Vent Stack are tabulated in Attachment 7.

4. Auxiliary Boiler Deaerator a) Radioactive gases may be vented from the auxiliary boiler deaerator during periods of primary to secondary leakage.

b) Steam from the Moisture Separator Reheater (MSR) may be used in the deaerator.

In the event of a primary to secondary leak, the MSR steam could become contaminated. Therefore, a potential exists for the release of radioactive gases in steam discharged from the Auxiliary Boiler Deaerator.

c) The discharge of steam is accomplished via a relief vent, 0-VBV-1891, which allows excess pressure to be vented to atmosphere.

1 As defined by Regulatory Guide 1.111 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 109 of 321 Level 3 - Information d) In the event the auxiliary boiler deaerator were to become contaminated, the amount of radioactivity released and the resulting doses/dose rates at the SITE BOUNDARY can be estimated if the following parameters are known:

(1) The MSR steam activity obtained from a sample, (2) The duration of the discharge, (3) The estimated steam discharge flow rate, and (4) The measured or average annual meteorological conditions.

e) Per applicable safety evaluations1, continued operation of this system is allowed as long as the concentration of radionuclides in the auxiliary boiler steam drum is less than 96 MPCs.

5. Steam Generator Atmospheric Steam Dump System a) Radioactive gases are not normally vented from this pathway.

b) Radioactive gases may be vented from the steam generator atmospheric steam dump system during periods of primary to secondary leakage.

c) If a primary to secondary leak is present and the steam dump valves are opened, the amount of radioactivity released and the resulting doses/dose rates at the SITE BOUNDARY can be estimated if the following parameters are known (per UFSAR, 10.1.2.2):

(1) The specific activity of a main steam sample as determined by GAMMA ISOTOPIC ANALYSIS, (2) The duration of discharge, (3) The estimated steam discharge flow rate, and (4) The measured or average annual meteorological conditions.

d) The total capacity of the atmospheric steam dump valve is 5 percent of steam flow with the reactor at full power (per UFSAR, 10.1.2.2).

6. Plant Nitrogen System a) Radioactive gases are not normally vented from this pathway.

b) Nitrogen is supplied to various components which contain radioactive materials (for example, VCT).

1 See 50.59 Log No. 90-0-027-037-R1.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 110 of 321 Level 3 - Information c) In the event the plant nitrogen system were to become contaminated, the amount of radioactivity released and the resulting doses/dose rates at the SITE BOUNDARY can be estimated if the following parameters are known:

(1) The specific activity of the gas in the plant nitrogen system as determined by GAMMA ISOTOPIC ANALYSIS, (2) The pressure of the nitrogen system, (3) The volume of the nitrogen system, and (4) The measured or average annual meteorological conditions.

d) It should be noted that the amount of radioactivity released could be estimated based on knowledge of other related parameters.

e) Per applicable safety evaluations1, continued operation of this system is allowed as long as the concentration of radionuclides is less than 13,400 MPCs.

7. Turbine Building Exhaust a) Radioactive gases are not normally vented from this pathway.

b) In the event radioactive gases were to be released through the turbine building exhaust, the amount of radioactivity released and the resulting doses/dose rates at the SITE BOUNDARY can be estimated if the following parameters are known:

(1) The specific activity of the turbine building air, (2) The duration of the discharge, (3) The estimated flow rate during the discharge, and (4) The measured or average annual meteorological conditions.

8. Emergency Air Lock a) Radioactive gases are not normally vented from this pathway.

b) In the event radioactive gases were to be released through the emergency air lock, the amount of radioactivity released and the resulting doses/dose rates at the SITE BOUNDARY can be estimated if the following parameters are known:

(1) The containment air activity obtained from a sample, (2) The volume of the air lock (9.558 cubic meters),

(3) The measured or average annual meteorological conditions.

1 See 50.59 Log No. 90-0-074-011-R1.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 111 of 321 Level 3 - Information

9. Plant Compressed Air a) Radioactive gases are not normally vented from this pathway.

b) In the event the plant compressed air system were to become contaminated, the amount of radioactivity released and the resulting doses/dose rates at the SITE BOUNDARY can be estimated if the following parameters are known:

(1) The specific activity of the compressed air system, (2) The pressure of the compressed air system, (3) The volume of the compressed air system, and (4) The measured or average annual meteorological conditions.

10. Main Steam Line Penetrations a) Radioactive gases are not normally vented from this pathway.

b) This penetration is cooled by outside air.

c) Gases may be released to the atmosphere through safety vents to the roof at elevation 91.5 feet.

d) See UFSAR 9.8.2.3.

11. Steam Driven Auxiliary Feed Pumps a) Radioactive gases are not normally vented from this pathway.

b) In the event radioactive gases were to be released through the auxiliary feed pumps, the amount of radioactivity released and the resulting doses/dose rates at the SITE BOUNDARY can be estimated if the following parameters are known:

(1) The activity in the steam, (2) The volume of steam released.

12. Containment Equipment Hatch a) Radioactive gases are not normally vented from this pathway.

b) In the event radioactive gases were to be released through the Containment Equipment Hatch, the amount of radioactivity released and the resulting doses/dose rates at the SITE BOUNDARY can be estimated if the following parameters are known:

(1) The containment air activity obtained from a sample, (2) The volume of the air released, December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 112 of 321 Level 3 - Information (3) The measured or average annual meteorological conditions.

13. Gland Steam Exhaust Condenser a) Radioactive gases are not normally vented from this pathway.

b) In the event radioactive gases were to be released through the gland steam exhaust condenser, the amount of radioactivity released and the resulting doses/dose rates at the SITE BOUNDARY can be estimated if the following parameters are known:

(1) Activity in the gland steam exhaust condenser, (2) The flow rate through the gland steam exhaust condenser, (3) The duration of the leak, and (4) The measured or average annual meteorological conditions.

14. Refueling Water Storage Tanks a) Radioactive gases are not normally vented from this pathway. Air contained in the tank may be vented as the water level rises during transfers to the tank.

b) In the event radioactive gases were to be released through the Refueling Water Storage Tank venting to the environment, the amount of radioactivity released and the resulting doses/dose rates at the SITE BOUNDARY can be estimated if the following parameters are known:

(1) Tank air and water volumes and volume changes (2) The specific activity of water in the Refueling Water Storage Tank (3) The measured or annual meteorological conditions.

15. Other unmonitored release paths should be evaluated and added to the ODCM as necessary.

TYPES OF GASEOUS RELEASES

1. All gaseous radwaste releases are classified as either BATCH RELEASES or CONTINUOUS RELEASES.
2. The definition of BATCH RELEASE is included in the definitions section of the ODCM.
3. The definition of CONTINUOUS RELEASE is included in the definitions section of the ODCM.
4. Gaseous radwaste discharges have been classified as CONTINUOUS or BATCH as shown on Attachments 7 and 8.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 113 of 321 Level 3 - Information PROCESSING EQUIPMENT

1. Simplified Flow Diagram a) An overview of the gaseous waste processing system, including major equipment and (normal) flow paths, is outlined on Attachment 9.
2. Modifications a) Licensed initiated major changes to the gaseous waste processing system shall be reported to the Commission in the Radioactive Effluent Release Report for the period in which the modification to the waste system was completed (per Technical Specification 5.6.3). The discussion of each change shall contain:

(1) A description of the equipment, components and processes involved; and (2) Documentation of the fact that the change, including the safety analysis, was reviewed and found acceptable by the onsite review function.

b) A major change or modification includes, but is not limited to, the removal or permanent bypass of any of the following:

(1) Waste gas decay tank (2) Waste gas surge tank (3) Degassifier (4) HEPA filter (5) Charcoal filter

3. Detailed Description a) A detailed description of the gaseous waste processing system is beyond the scope of the ODCM.

b) For more information on the Waste Gas System, see the CCNPP System Description Number 14A, Waste Gas System.

c) For more information on the Waste Gas System, see the CCNPP Updated Final Safety Analysis Report, Chapter 11, Waste Processing And Radiation Protection.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 114 of 321 Level 3 - Information GASEOUS EFFLUENT RADIATION MONITORS AND SETPOINTS

1. Wide Range Gas Monitor (1-RE-5416A) a) General description (1) The Wide Range Gas Monitor (WRGM) contains 3 radiation elements (a) Low-range noble gas detector i) Designation of radiation element: 1-RE-5416A ii) Type of radiation element: Off-line scintillation iii) Output: digital iv) Radiation indicator: 1-RIC-5415 v) Units for radiation indicator are user programmable and are normally set to microcuries per cubic centimeter or microcuries per second vi) Supplier: General Atomics (b) Mid-range, noble gas detector i) Designation of radiation element: 1-RE-5417A ii) Type of radiation element: Solid state iii) This noble gas monitor is used to measure the release of radioactivity from unit 1 main vent in the event of an accident.

(UFSAR, 11.2.3.2.12) iv) Setpoints for the mid-range detector will not be addressed in the ODCM (c) High-range, noble gas detector i) Designation of radiation element: 1-RE-5418A ii) Type of radiation element: Solid state iii) This detector is used to measure the release of radioactivity from unit 1 main vent in the event of an accident. (UFSAR, 11.2.3.2.12) iv) Setpoints for the high-range detector will not be addressed in the ODCM December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 115 of 321 Level 3 - Information (2) The low range detector will be the only detector addressed further in the ODCM.

b) Functions of 1-RE-5416A (1) Continuously measure the release rate of noble gases emanating from the Unit 1 Main Vent Stack (Control 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2)

(2) Continuously indicate (via 1-RIC-5415) the release rate of noble gases emanating from the Unit 1 Main Vent Stack (Control 4.11.2.1.1 or Control 4.11.2.1.2, Table 4.11-2)

(3) Alarm (via 1-RIC-5415) before exceeding the site-boundary, noble-gas, total-body-dose-rate limit of 500 mr/yr (per Control 3.11.2.1.a)

(4) Alarm (via 1-RIC-5415) before exceeding the site-boundary, noble-gas, skin-dose-rate limit of 3000 mr/yr (per Control 3.11.2.1.a) c) OPERABILITY of 1-RE-5416A (1) This monitor shall be operable (or have OPERABILITY) when it is capable of performing its specified function(s).

(2) The functions of this monitor are listed in section (b) above.

d) Monitors equivalent to 1-RE-5416A (1) 1-RE-5415 [the Westinghouse Plant Vent Stack Monitor] has the capability of providing the measurement and alarm functions of 1-RE-5416A during times when 1-RE-5416A is declared inoperable.

(2) 1-RE-5415 provides redundant monitoring [for 1-RE-5416A] at the low end of the concentration ranges (UFSAR 11.2.3.2.12).

(3) In the event 1-RE-5415 is inoperable or otherwise unavailable, 1-RE-5416A may fulfill the measuring, indicating, and alarming functions normally provided by 1-RE-5415.

e) Radiological effluent controls for 1-RE-5416A (1) Control 3.3.3.9 states that releases via the plant vent stack may continue if any one of the following three conditions are satisfied:

(a) 1-RE-5415 is operable AND the alarm setpoint for 1-RI-5415 is set to ensure the annual dose rates due to noble gases at the SITE BOUNDARY are less than 500 mr/yr to the total body and are less than 3000 mr/yr to the skin (per Control 3.11.2.1.a), or December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 116 of 321 Level 3 - Information (b) An equivalent monitor is operable AND the alarm trip setpoint for the equivalent monitor is set to ensure annual dose rates due to noble gases at the SITE BOUNDARY are less than 500 mr/yr to the total body and are less than 3000 mr/yr to the skin (per Control 3.11.2.1.a),

or (c) Grab samples are obtained and analyzed for gross activity at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per Controls 3.11.2.1.a, 4.11.2.1.1, and 4.11.2.1.2 (per Control 4.3.3.9, Table 3.3-12, ACTION 37).

f) Surveillances for 1-RE-5416A (1) Control 4.3.3.9 requires demonstrating the OPERABILITY of 1-RE-5416A by satisfying the checks, calibrations, and tests listed below:

(a) CHANNEL CHECK within the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (b) SOURCE CHECK within the past 31 days (c) CHANNEL CALIBRATION within the past 18 months (d) CHANNEL FUNCTIONAL TEST within the past 6 six months g) Setpoints for 1-RIC-5415 (1) Requirements and commitments (a) The alarm and fixed setpoints shall be determined and adjusted per the methodology and parameters of the ODCM. (Control 3.3.3.9)

(b) The method for calculating fixed or adjustable setpoints shall be provided in the ODCM (per NUREG-0133, 5.1.1).

(2) There are four radiation alarm setpoints associated with, or otherwise related to, the WRGM.

(a) 1-RIC-5415 fixed high-high radiation alarm setpoint (b) 1-RIC-5415 fixed high radiation alarm setpoint (c) 1-RIC-5415 adjustable plant computer high radiation alarm setpoint (d) 1-RIC-5415 adjustable plant computer alert setpoint.

(3) In order to simplify the setpoint terminology, eliminate ambiguity, and minimize the possibility of misinterpretation, the ODCM will refer to these setpoints as follows:

(a) The 1-RIC-5415 fixed high-high radiation alarm setpoint will be referred to as the fixed high alarm setpoint (b) The 1-RIC-5415 fixed high radiation alarm setpoint will be referred to as the fixed alert setpoint December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 117 of 321 Level 3 - Information (c) The 1-RIC-5415 adjustable plant computer high radiation alarm setpoint will be referred to as the adjustable setpoint (d) The 1-RIC-5415 adjustable plant computer alert setpoint will be referred to as the alert setpoint.

(4) Each of these alarm setpoints are described below.

h) Fixed high alarm setpoint for 1-RIC-5415 (1) General information (a) The fixed high alarm setpoint is not adjusted for each release.

(b) Whenever the fixed high alarm setpoint is exceeded, an alarm will be generated.

(c) The current value for the fixed high alarm setpoint is specified in the CCNPP Alarm Manual.

(d) The CCNPP Alarm Manual1 refers to the fixed high alarm setpoint as the Unit 1 Wide Range Noble Gas Radiation Monitor high alarm setpoint.

(e) The fixed high alarm setpoint is integral to the WRGM, as purchased from the supplier.

(f) The fixed high alarm setpoint is documented in the CCNPP Alarm Manual.

(g) The fixed high alarm setpoint shall be calculated as described below.

(2) Calculating the fixed high alarm setpoint for 1-RIC-5415 (a) The fixed high alarm setpoint for 1-RIC-5415 (WRGM) shall be calculated per equation 1G.2 FIXED HIGH ALARM SETPOINT FOR 1-RIC-5415 Sfixhh < [c' / ( x/Q ) ] [ Fdx / ( Fd1 + Fd2 ) ] [ ATLn ] Eq. 1G3

Where, Sfixhh = The fixed high alarm setpoint for 1-RIC-5415 (microcuries per second) 1 The CCNPP Alarm Manual is controlled by NO-1-201.

2 The alarm and trip setpoints ... shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Control 3.3.3.9).

3 Equation 1G has been derived from NUREG-0133, 5.2.1.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 118 of 321 Level 3 - Information c' = A conversion constant (1E6 cubic centimeters per cubic meter) x/Q = The highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

Unit 1 main vent releases are considered long-term releases1, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the setpoint calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for purposes of routine, long-term concentrations (for example, routine noble gas releases)

The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3)

Fdx = The estimated Main Vent Stack (diluted gaseous radwaste) flow rate for unit, x, (cubic meters per second)

The estimated Main Vent Stack flow rates for Unit 1 and Unit 2 are defined below.

Fd1 = The estimated Main Vent Stack flow rate for Unit 1 (cubic meters per second)

Since the Main Vent Stack flow rate will vary depending on the configuration of air dampers and the input gas streams, nominal Main Vent Stack flow rate is used to calculate the fixed high alarm setpoint.

Use the nominal Unit 1 Main Vent Stack flow rate listed on Attachment 7.

The Main Vent Stack flow rate shall be determined, per approved procedures, at least once per 6 months (+ 25%). The Test and Equipment Unit shall be responsible for performing this test.

The results of the main vent flow rate test shall be evaluated to ensure the main vent flow rates used in the ODCM are an accurate reflection of the true main vent flow rates. The Radiological Effluent Technical Specifications (RETS) Program Manager is responsible for modifying the (main vent flow rates used in the) ODCM in the event the main vent flow rate for either Unit 1 or Unit 2 has increased to a value which is greater than the maximum discharge flow rates listed on Attachment 7.

Fd2 = The estimated Main Vent Stack (diluted gaseous radwaste) flow rate for Unit 2 (cubic meters per second)

Since the Main Vent Stack flow rate will vary depending on the configuration of air dampers and the input gas streams, nominal Main Vent Stack flow rate is used to calculate the fixed high alarm setpoint.

Use the nominal Unit 2 Main Vent Stack flow rate listed on Attachment 7.

The Main Vent Stack flow rate shall be determined, per approved procedures, at least once per 6 months (+ 25%). The Test and Equipment Unit shall be responsible for performing this test.

The results of the main vent flow rate test shall be evaluated to ensure the main vent flow rates used in the ODCM are an accurate reflection of the true main vent flow rates. The RETS 1 NUREG-0133, 3.3 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 119 of 321 Level 3 - Information Program Manager is responsible for modifying the (main vent flow rates used in the) ODCM in the event the main vent flow rate for either Unit 1 or Unit 2 has increased to a value which is greater than the maximum discharge flow rates listed on Attachment 7.

ATLn = The sum of the total specific activities of all radionuclides found in TYPICAL GASEOUS RADWASTE RELEASES (microcuries/cm3)

Calculate ATLn per equation 2G.

SPECIFIC ACTIVITY CORRESPONDING TO THE SITE BOUNDARY LIMIT

[ ( fi ) ( ATLn ) ] / AiLt < LMPC Eq. 2G1

Where, fi = A fraction which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitless)

This value may be obtained using the guidance provided on Attachment 5.

AiLt = The specific activity limit for radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table II, Column 1 (microcuries/cm3)

For all the radionuclides found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B, Table II, Column 1. An acceptable alternative is to assume an isotopic mix which results in a more conservative setpoint.

LMPC = The site MPC limit (MPCs) for UNRESTRICTED AREAS The value chosen for LMPC in this equation is 2. The basis for this limit is 10 CFR 50.72.

It has been shown2 that, for the radionuclides present in TYPICAL GASEOUS EFFLUENTS from CCNPP, the 2 MPC limit is more restrictive than the limits of Control 3.11.2.1(a).

It should be noted that by using 2 As the MPC limit (10 CFR 50.72), instead of using the limits of Control 3.11.2.1(a), a safety factor has been incorporated into equation 2G.

An alarm setpoint corresponding to 2 MPCs serves to initiate a determination of whether the 4-hour NRC notification (specified in 10 CFR 50.72) is required.

(3) Documenting the fixed high alarm setpoint (a) Whenever the fixed high alarm setpoint is calculated, the specific values chosen for each of the variables shall be documented per CC-AA-103-2001.

1 This equation has been derived from 10 CFR 20, Appendix B, Table II, Note 1.

2 Addendum To Setpoint Calculations For WRGM Monitors 1-RIC-5415 and 2-RIC-5415, R.L. Conatser, December 10, 1991.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 120 of 321 Level 3 - Information (4) Changing the fixed high alarm setpoint for 1-RIC-5415 (a) If the fixed high alarm setpoint calculated per equation 1G exceeds the maximum range of the monitor, the fixed high setpoint shall be adjusted to a value which falls within the normal operating range of the monitor.

(b) The fixed high alarm setpoint may be established at values lower than the maximum allowable setpoint, if desired.

(c) A setpoint change should be initiated whenever any of the parameters identified in the setpoint calculation equations (identified in this section of the ODCM) have changed.

(d) The fixed high alarm setpoint should not be changed unless one of the following occurs:

i) the relative activity1 of any radionuclide in TYPICAL GASEOUS EFFLUENTS has changed by greater than 10%,

and the new radionuclide mixture yields a fixed setpoint which is 10% (or more) lower than the current fixed setpoint, ii) the historical maximum annual average atmospheric dispersion factor has changed, iii) the MPC limit at the SITE BOUNDARY, (LMPC) has changed, iv) the Unit 1 or Unit 2 Main Vent Stack flow rate has changed by greater than or equal to 10%2, v) the values listed in 10 CFR 20, Appendix B, Table II, Column 1 have changed, vi) the radiation monitor has been recently calibrated, repaired, or otherwise altered, or vii) the monitor is not conservative in its function (see Functions of 1-RE-5416A earlier in this section).

(e) CC-AA-103-2001 contains the administrative controls associated with changing and approving fixed high alarm setpoint.

1 As determined in accordance with Attachment 5.

2 As determined by surveillance test results (e.g., STP-M-462-1 or STP-M-462-2).

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 121 of 321 Level 3 - Information i) Fixed alert setpoint for 1-RIC-5415 (1) General information (a) The fixed alert setpoint is not adjusted for each release.

(b) Whenever the fixed alert setpoint is exceeded, an alarm will be generated.

(c) The CCNPP Alarm Manual does not reference this setpoint.

(d) The fixed alert setpoint is integral to the WRGM, as purchased from the supplier.

(e) The current value for the fixed alert setpoint is specified in the CCNPP Setpoint File.

(f) The fixed alert setpoint is documented in the CCNPP Alarm Manual.

(g) The fixed alert setpoint shall be calculated as described below1.

(2) Calculating the fixed alert setpoint for 1-RIC-5415 (a) The fixed alert setpoint for 1-RIC-5415 shall be calculated as described below:

FIXED ALERT SETPOINT FOR 1-RIC-5415 Sfixh < Ksf [ Sfixhh ] Eq. 3G

Where, Sfixh = The fixed alert setpoint for 1-RIC-5415 (microcuries per second)

Sfixhh = The fixed high alarm setpoint for 1-RIC-5415 (microcuries per second)

Ksf = A constant, actually a safety factor, which is the fraction of the fixed high setpoint (unitless).

The safety factor chosen shall be less than or equal to 1.00. This ensures the fixed alert setpoint is always less than or equal to the fixed high alarm setpoint.

A safety factor of 1.00 will yield a fixed alert setpoint which corresponds to the fixed high alarm setpoint.

A safety factor of 0.100 will yield a fixed alert setpoint which corresponds to one-tenth the fixed high alarm setpoint.

1 The alarm and trip setpoints ... shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Control 3.3.3.9).

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 122 of 321 Level 3 - Information It is recommended that a safety factor of 0.1 be used for calculating the fixed alert setpoint, however, other values--not to exceed 1.00--may be used as directed by Management.

The particular value selected for the safety factor is somewhat arbitrary, however a value less than 1.00 does provide plant personnel with adequate time to respond to changing plant conditions and to initiate corrective ACTIONS so as to minimize the possibility of violating either the 10 CFR 50.72 limit or the Control 3.3.3.9 limits.

The use of the safety factor is consistent with ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

The use of a safety margin is per the provisions of NUREG-0133 which states that "... the alarm and trip setpoints ... should correspond to a value(s) which represents a safe margin of assurance that the instantaneous gaseous release limit of Control 3.11.2.1(a) will not be exceeded." (per NUREG-0133, 5.1.1).

This safety margin will prevent minor fluctuations in the nominal plant vent stack flow rates, errors in monitor efficiencies, and other statistical aberrations from adversely impacting the calculated fixed alert setpoint.

(3) Documenting the fixed alert setpoint (a) Whenever the fixed alert setpoint is calculated, the specific values chosen for each of the variables shall be documented per CC-AA-103-2001.

(4) Changing the fixed alert setpoint for 1-RIC-5415 (a) A setpoint change should be initiated whenever any of the parameters identified in equation 3G have changed.

(b) The fixed alert setpoint should be changed whenever the fixed high setpoint is changed.

(c) The fixed alert setpoint should be changed if the value of the safety factor is changed.

(d) See CC-AA-103-2001 for a description of activities associated with setpoint changes and setpoint approvals.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 123 of 321 Level 3 - Information j) Adjustable alarm setpoint for 1-RIC-5415 (1) General information (a) Whenever this monitor is satisfying the minimum channels operable requirement (per Control 3.3.3.9), the adjustable setpoint is calculated and adjusted before each release of a WGDT, each containment vent, and each containment purge discharged via the main vent.

(b) The adjustable setpoint is based on the specific activities of the radionuclides present in either the WGDT or the containment building, whichever is applicable. (The radionuclide concentrations are determined by radiochemical analysis per applicable Chemistry procedures as required by Control 4.11.2.1.2).

(c) Whenever the adjustable setpoint is exceeded, the WGDT, PURGE, or vent discharge via the main vent will be manually suspended.

(d) Refer to the Alarm Manual for a full list of operator ACTIONS taken in response to this alarm.

(e) The adjustable setpoint corresponds to the maximum concentration of radionuclides anticipated or expected when discharging a WGDT, a containment vent, or a containment purge via the main vent. For containment purges during outages, system evolutions may cause containment atmosphere activity to increase above what is normally expected for short periods of time.

(f) The value for the adjustable setpoint is recorded on the gaseous release permit per applicable Chemistry procedures.

(g) This alarm is not integral to the main vent radiation monitor, as purchased from the supplier.

(h) This alarm is generated by the plant computer which monitors output from 1/2-RIC-5415, and provides an alarm to plant operators when the 1/2-RIC-5415 adjustable setpoint has been exceeded.

(i) When this monitor is satisfying the minimum channels operable requirement (per Control 3.3.3.9), a value for the adjustable alarm setpoint shall be calculated before each release of a WGDT, each containment vent, and each containment purge as shown below.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 124 of 321 Level 3 - Information (2) Calculating the adjustable setpoint for 1/2-RIC-5415 (a) The adjustable setpoint is based on the specific activity of the radionuclides in the undiluted gaseous waste (as determined by radiochemical analysis per Control 4.11.2.1.2), and the alarm setpoint is calculated as shown below.

ADJUSTABLE SETPOINT FOR 1/2-RIC-5415 Sadj < (Ksf) [ (c' Fu Aiu ei ) + Bkg ] Eq. 29G1 Sadj = The adjustable setpoint for 1/2-RIC-5415 (microcuries per second)

Ksf = A constant, actually a safety factor, which allows for fluctuation in radiation monitor response (unitless)

This safety factor helps ensure the release is not unnecessarily terminated due to (1) electronic anomalies which cause spurious monitor responses, (2) statistical fluctuations in disintegration rates, (3) statistical fluctuations in detector efficiencies, (4) errors associated with sample analysis, (5) errors associated with monitor calibrations2, and (6) anticipated short term variations in containment activity (applicable to containment purges only).

It is recommended that a safety factor of 10 for containment purge releases be used for calculating the adjustable setpoint. However, other values for purge releases -- not to exceed 10 -- may be used as directed by Management. A safety factor of 1.5 shall be used for all other gaseous releases.

The particular value selected for the safety factor is somewhat arbitrary, however a value less than or equal to 10 does provide plant personnel with adequate time to respond to changing plant conditions and to initiate corrective ACTIONS so as to minimize the possibility of violating either the 10 CFR 50.72 limit or the Control 3.3.3.9 limits.

The use of the safety factor is consistent with ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

The use of a safety margin is per the provisions of NUREG-0133 which states that ". . . the alarm and trip setpoints . . . should correspond to a value(s) which represents a safe margin of assurance that the instantaneous gaseous release limit of Control 3.11.2.1(a) will not be exceeded."

(per NUREG-0133, 5.1.1).

1 Equation 29G has been derived from NUREG-0133, Addendum, page AA-1.

2 The analysis errors and calibration errors refer to errors which are within established quality assurance and quality control limits.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 125 of 321 Level 3 - Information This safety margin will prevent minor fluctuations in the nominal plant vent stack flow rates, errors in monitor efficiencies, and other statistical aberrations from adversely impacting the calculated adjustable setpoint. Additionally for a special case of containment purges during outages, the safety factor allows for short term variations in activity created as a result of system evolutions in containment.

Fu = Maximum undiluted radwaste flow rate (cubic meters per second)

Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachment 7.

Aiu = Specific activity of radionuclide, i, in the undiluted waste stream, either the WGDT or the containment building (microcuries per cubic centimeter) ei = Absolute detector efficiency for nuclide, i (microcuries Xe-133 equivalent per microcuries nuclide i)

The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor.

Bkg = An approximation of the detector background (microcuries per second) c' = A conversion constant (1E6 cubic centimeters per cubic meter)

(3) Documenting the adjustable setpoint for 1/2-RIC-5415 (a) Whenever the adjustable setpoint is calculated, the specific values chosen for each of the variables shall be documented per approved Chemistry procedures (for example, CP-604).

(4) Changing the adjustable setpoint for 1/2-RIC-5415 (a) In all cases, the adjustable setpoint shall be set to a value which is less than or equal to the fixed setpoint.

(b) If the adjustable setpoint exceeds the maximum range of the monitor, the setpoint shall be adjusted to a value which falls within the normal operating range of the monitor.

(c) Chemistry procedures (for example, CP-604) contain administrative controls associated with calculating and approving an adjustable setpoint.

(d) Whenever this monitor is satisfying the minimum channels operable requirement (per Control 3.3.3.9 ) the calculated value for the adjustable setpoint shall be entered into the plant computer before each release of a WGDT, a containment vent, or a containment purge via the main vent.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 126 of 321 Level 3 - Information k) Alert setpoint for 1-RIC-5415 (1) General information (a) The alert setpoint is applicable to containment purges only.

(b) Whenever this monitor is satisfying the minimum channels operable requirement (per Control 3.3.3.9 ), the alert setpoint is calculated and adjusted before each containment purge discharged via the main vent.

(c) The alert setpoint is based on the specific activities of the radionuclides present in the containment building. (The radionuclide concentrations are determined by radiochemical analysis per applicable Chemistry procedures as required by Control 4.11.2.1.2).

(d) Whenever the alert setpoint is exceeded the PURGE via the main vent may continue.

(e) The alert setpoint corresponds to a level of activity which indicates additional source term(s) may be present, and as a result, additional notifications and/or actions are required to identify the source and to accurately account for the activity discharged.

(f) The value for the alert setpoint is recorded on the gaseous release permit per applicable Chemistry procedures.

(g) This alarm is not integral to the main vent radiation monitor, as purchased from the supplier.

(h) This alarm is generated by the plant computer which monitors output from 1/2-RIC-5415, and provides an alarm to plant operators when the 1/2-RIC-5415 alert setpoint has been exceeded.

(i) When this monitor is satisfying the minimum channels operable requirement (per Control 3.3.3.9), a value for the alert setpoint shall be calculated before each containment purge via the main vent as shown below.

(2) Calculating the alert setpoint for 1/2-RIC-5415 (a) The alert setpoint is based on the specific activity of the radionuclides in the undiluted gaseous waste (as determined by radiochemical analysis per Control 4.11.2.1.2), and the setpoint is calculated as shown below.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 127 of 321 Level 3 - Information ALERT SETPOINT FOR 1/2-RIC-5415 Salert < (1.50) [ (c' Fu Aiu ei ) + Bkg ] Eq. 29G1 Salert = The alert setpoint for 1/2-RIC-5415 (microcuries per second) 1.50 = A constant, actually a safety factor, which allows for fluctuation in radiation monitor response (unitless)

This safety factor helps ensure the release is not unnecessarily terminated due to (1) electronic anomalies which cause spurious monitor responses, (2) statistical fluctuations in disintegration rates, (3) statistical fluctuations in detector efficiencies, (4) errors associated with sample analysis, and (5) errors associated with monitor calibrations2.

The use of the safety factor is consistent with ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

The use of a safety margin is per the provisions of NUREG-0133 which states that "... the alarm and trip setpoints ... should correspond to a value(s) which represents a safe margin of assurance that the instantaneous gaseous release limit of Control 3.11.2.1(a) will not be exceeded." (per NUREG-0133, 5.1.1).

This safety margin will prevent minor fluctuations in the nominal plant vent stack flow rates, errors in monitor efficiencies, and other statistical aberrations from adversely impacting the calculated alert setpoint.

Fu = Maximum undiluted radwaste flow rate (cubic meters per second)

Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachment 7.

Aiu = Apecific activity of radionuclide, i, in the containment building (microcuries per cubic centimeter) ei = Absolute detector efficiency for nuclide, i (microcuries Xe-133 equivalent per microcuries nuclide i)

The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor.

Bkg = An approximation of the detector background (microcuries per second) c' = A conversion constant (1E6 cubic centimeters per cubic meter) 1 Equation 29G has been derived from NUREG-0133, Addendum, page AA-1.

2 The analysis errors and calibration errors refer to errors which are within established quality assurance and quality control limits.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 128 of 321 Level 3 - Information (3) Documenting the alert setpoint for 1/2-RIC-5415 (a) Whenever the alert setpoint is calculated, the specific values chosen for each of the variables shall be documented per approved Chemistry procedures (for example, CP-604).

(4) Changing the alert setpoint for 1/2-RIC-5415 (a) In all cases, the alert setpoint shall be set to a value which is less than or equal to the fixed setpoint.

(b) If the alert setpoint exceeds the maximum range of the monitor, the setpoint shall be adjusted to a value which falls within the normal operating range of the monitor.

(c) Chemistry procedures (for example, CP-604) contain administrative controls associated with calculating and approving an alert setpoint.

(d) Whenever this monitor is satisfying the minimum channels operable requirement (per Control 3.3.3.9) the calculated value for the alert setpoint shall be entered into the plant computer before each containment purge via the main vent.

2. Wide Range Gas Monitor (2-RE-5416A) a) All information related to 1-RE-5416A is applicable to the Unit 2 WRGM with the following exceptions(s) b) Monitors equivalent to 2-RE-5416A (1) 2-RE-5415 [the Westinghouse Plant Vent Stack Monitor] has the capability of providing the measurement and alarm functions of 2-RE-5416A during times when 2-RE-5416A is declared inoperable (2) 2-RE-5415 provides redundant monitoring [for 2-RE-5416A] at the low end of the concentration ranges (UFSAR 11.2.3.2.12)
3. Westinghouse Plant Vent Stack Monitor (1-RE-5415) a) The Westinghouse Plant Vent Stack Monitor contains 2 radiation elements (1) 1-RE-5414 (a) Particulate detector (b) Off-line scintillation detector (c) Analog output (d) Supplies signals to radiation indicator 1/2-RI-5414 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 129 of 321 Level 3 - Information (e) Values displayed by 1/2-RI-5414 are in units of counts per minute (f) The detector manufacturer is Westinghouse (2) 1-RE-5415 (a) Noble gas detector (b) Off-line GM Tube (c) Analog output (d) Supplies signals to radiation indicator 1/2-RI-5415 (e) Values displayed by 1/2-RI-5415 are in units of counts per minute (f) The detector manufacturer is Westinghouse b) Functions of 1-RE-5414 (1) The functions of 1-RE-5414 are mentioned here only as a basis for excluding this radiation element from the setpoint controls of Control 3.3.3.9.

(2) This monitor (the particulate monitor) was retired in place.

c) Functions of 1-RE-54151 (1) Continuously measure the activity (cpm) of noble gases emanating from the Unit 1 Main Vent Stack (Control 4.11.2.1.2, Table 4.11-2)

(2) Continuously indicate (via 1-RI-5415) the activity (cpm) of noble gases emanating from the Unit 1 Main Vent Stack (Control 4.11.2.1.2, Table 4.11-2)

(3) Alarm (via 1-RI-5415) before exceeding the site-boundary, noble-gas, total-body-dose-rate limit of 500 mr/yr (per Control 3.11.2.1.a)

(4) Alarm (via 1-RIC-5415) before exceeding the site-boundary, noble-gas, skin-dose-rate limit of 3000 mr/yr (per Control 3.11.2.1.a) 1 This (radiation element) monitors noble gases. Other radiation elements monitor particulates in this waste stream.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 130 of 321 Level 3 - Information d) OPERABILITY of 1-RE-5415 (1) This monitor shall be operable (or have OPERABILITY) when it is capable of performing its specified function(s).

(2) The functions of 1-RE-5415 are listed in section (c) above.

e) Monitors equivalent to 1-RE-5415 (1) The Wide Range Gas Monitor (that is, 1-RE-5416A) has the capability of providing the measurement and alarm functions of 1-RE-5415 during times when 1-RE-5415 is declared inoperable.

(2) 1-RE-5415 provides redundant monitoring [for 1-RE-5416A] at the low end of the concentration ranges (UFSAR 11.2.3.2.12).

(3) In the event 1-RE-5415 is inoperable or otherwise unavailable, 1-RE-5416A may fulfill the measuring, indicating, and alarming functions normally provided by 1-RE-5415.

(4) The absence of a radiation element dedicated to measuring the particulate activity in the Wide Range Gas Monitor does not preclude the use of 1-RE-5416A as a backup for 1-RE-5415. This is mentioned only as a basis for excluding 1/2-RE-5414 from the setpoint controls of Control 3.3.3.9 (see Functions of 1-RE-5414 earlier in this section).

f) Radiological effluent controls for 1-RE-5415 (1) Control 3.3.3.9 states that releases via the plant vent stack may continue if any one of the following three conditions are satisfied:

(a) 1-RE-5415 is operable AND the alarm setpoint for 1-RI-5415 is set to ensure the annual dose rates due to noble gases at the SITE BOUNDARY are less than 500 mr/yr to the total body and are less than 3000 mr/yr to the skin (per Control 3.11.2.1.a), or (b) An equivalent monitor (see section (e) above) is operable AND the alarm setpoint for the equivalent monitor is set to ensure annual dose rates due to noble gases at the SITE BOUNDARY are less than 500 mr/yr to the total body and are less than 3000 mr/yr to the skin (per Control 3.11.2.1.a), or (c) Grab samples are obtained and analyzed for gross activity at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per Controls 3.11.2.1.a, 4.11.2.1.1, and 4.11.2.1.2 (per Control 4.3.3.9, Table 3.3-12, ACTION 37).

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 131 of 321 Level 3 - Information (2) Control 3.11.2.1.b (that is, dose rates due to iodines and particulates at the SITE BOUNDARY) is not applicable to noble gas detector or to the setpoints related to the noble gas detector 1-RE-5415. As a result, the 1500 my/yr organ dose limit is not included as a radiological effluent control in this section of the ODCM.

g) Surveillances for 1-RE-5415 (1) Control 4.3.3.9 requires demonstrating the OPERABILITY of 1-RE-5415 by satisfying the checks, calibrations, and tests listed below:

(a) CHANNEL CHECK within the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (b) SOURCE CHECK within the past 31 days (c) CHANNEL CALIBRATION within the past 18 months (d) CHANNEL FUNCTIONAL TEST within the past 6 six months h) Setpoints for 1-RI-5415 (1) Requirements and commitments (a) The alarm and fixed setpoints shall be determined and adjusted per the methodology and parameters of the ODCM. (Control 3.3.3.9)

(b) The method for calculating fixed or adjustable setpoints shall be provided in the ODCM. (NUREG-0133, 5.1.1)

(2) There are four alarms associated with, or otherwise related to, 1-RE-5415.

(a) 1-RI-5415 fixed high radiation alarm setpoint (b) 1-RI-5415 adjustable plant computer high radiation alarm setpoint (c) 1-RI-5415 low radiation alarm setpoint (d) 1-RI-5415 adjustable plant computer alert setpoint.

(3) In order to simplify the setpoint terminology, eliminate ambiguity, and minimize the possibility of misinterpretation, the ODCM will refer to these setpoints as follows:

(a) The 1-RI-5415 fixed high radiation alarm setpoint will be referred to as the fixed setpoint.

(b) The 1-RI-5415 adjustable plant computer high radiation alarm setpoint will be referred to as the adjustable setpoint.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 132 of 321 Level 3 - Information (c) The 1-RI-5415 low radiation alarm setpoint will be referred to as the low setpoint.

(d) The 1-RI-5415 adjustable plant computer alert setpoint will be referred to as the alert setpoint.

(4) Each of these alarm setpoints are described below.

i) The fixed setpoint for 1-RI-5415 (1) General information (a) The fixed setpoint is not adjusted for each release.

(b) Whenever the fixed setpoint is exceeded, an alarm will be generated.

(c) The current value for the fixed setpoint is specified in the CCNPP Alarm Manual.

(d) The CCNPP Alarm Manual refers to this setpoint as the 1-RI-5415 High Alarm Setpoint.

(e) The fixed setpoint is integral to the Main Vent (Westinghouse) RMS as purchased from the supplier.

(f) The fixed setpoint is documented in the CCNPP Alarm Manual.

(g) The fixed setpoint shall be calculated as described below1.

(2) Calculating the fixed setpoint for 1-RI-5415 (a) The fixed setpoint for 1-RI-5415 (plant vent stack monitor) shall be calculated per equation 4G.

THE FIXED SETPOINT FOR 1-RI-5415 Sfix < { Ksf / [ ( x/Q ) ( Fd1 + Fd2 ) ] } [ ( ei ) ( AiLn ) ] Eq. 4G2 Sfix = The fixed setpoint for 1-RI-5415 (counts per minute)

Ksf = A constant, actually a safety factor, which is the ratio of the CCNPP activity limit to the MPC limit, LMPC, used in equation 2G (unitless) 1 The alarm and trip setpoints ... shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Control 3.3.3.9).

2 Equation 4G has been derived from NUREG-0133, 5.2.1, (the 500 mr/yr equation).

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 133 of 321 Level 3 - Information The safety factor chosen shall be less than or equal to 1.00. This ensures the fixed setpoint is always less than or equal to the MPC limit, LMPC, used in equation 2G.

A safety factor of 1.00 will yield a fixed setpoint which corresponds to the MPC limit, L MPC, in equation 2G.

A safety factor of 0.500 will yield a fixed setpoint which corresponds to one-half the MPC limit, LMPC, in equation 2G.

It is recommended that a safety factor of 1.0 be used for calculating the fixed setpoint, however, other values--not to exceed 1.00--may be used as directed by Management.

The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with adequate time to respond to changing plant conditions and to initiate corrective ACTIONS so as to minimize the possibility of violating either the 10 CFR 50.72 limit or the Control 3.3.3.9 limits.

The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

The use of a safety margin is per the provisions of NUREG-0133, Section 5.1.1, which states that "... the alarm and trip setpoints ... should correspond to a value(s) which represents a safe margin of assurance that the instantaneous gaseous release limit of Control 3.11.2.1(a) will not be exceeded."

This safety margin will prevent minor fluctuations in the nominal plant vent stack flow rates, errors in detector efficiencies, and other statistical aberrations from adversely impacting the calculated fixed setpoint.

x/Q = The highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

Unit 1 and Unit 2 main vent releases are considered long-term releases1, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the setpoint calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for purposes of routine, long-term concentrations (for example, routine noble gas releases).

The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3).

1 NUREG-0133, 3.3 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 134 of 321 Level 3 - Information Fd1 = The estimated Main Vent Stack flow rate for Unit 1 (cubic meters per second)

Since the Main Vent Stack flow rate will vary depending on the configuration of air dampers and the input gas streams, nominal Main Vent Stack flow rate is used to calculate the fixed setpoint.

Use the nominal Unit 1 Main Vent Stack flow rate listed on Attachment 7.

The Main Vent Stack flow rate shall be determined, per approved procedures, at least once per 6 months (+ 25%). The Test and Equipment Unit shall be responsible for performing this test.

The results of the main vent flow rate test shall be evaluated to ensure the main vent flow rates used in the ODCM are an accurate reflection of the true main vent flow rates. The RETS Program Manager is responsible for modifying the (main vent flow rates used in the) ODCM in the event the main vent flow rate for either Unit 1 or Unit 2 has increased to a value which is greater than the maximum discharge flow rates listed on Attachment 7.

Fd2 = The estimated Main Vent Stack flow rate for unit 2 (cubic meters per second)

Since the Main Vent Stack flow rate will vary depending on the configuration of air dampers and the input gas streams, nominal Main Vent Stack flow rate is used to calculate the fixed setpoint.

Use the nominal Unit 2 Main Vent Stack flow rate listed on Attachment 7.

The Main Vent Stack flow rate shall be determined, per approved procedures, at least once per 6 months (+ 25%). The Test and Equipment Unit shall be responsible for performing this test.

The results of the main vent flow rate test shall be evaluated to ensure the main vent flow rates used in the ODCM are an accurate reflection of the true main vent flow rates. The RETS Program Manager is responsible for modifying the (main vent flow rates used in the) ODCM in the event the main vent flow rate for either Unit 1 or Unit 2 has increased to a value which is greater than the maximum discharge flow rates listed on Attachment 7.

ei = Absolute detector efficiency for nuclide, i (cpm/microcuries per milliliter)

The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor.

AiLn = The specific activities of radionuclide, i, found in TYPICAL GASEOUS RADWASTE RELEASES (calculated per 10 CFR 20, Appendix B, Table II, Note 1 as described below; microcuries per milliliter)

Calculate AiLn per equation 5G.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 135 of 321 Level 3 - Information SPECIFIC ACTIVITY LIMIT FOR NUCLIDE I IN A RADIONUCLIDE MIXTURE AiLn = ( fi ) ( ATLn ) Eq. 5G fi = A fraction which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitless)

This value may be obtained using the guidance provided on Attachment 5.

ATLn = The sum of the total specific activities of all noble gas radionuclides found in TYPICAL GASEOUS RADWASTE RELEASES (microcuries/cm3)

Calculate ATLn per equation 2G.

SPECIFIC ACTIVITY CORRESPONDING TO THE SITE BOUNDARY LIMIT

[ ( fi ) ( ATLn ) ] / AiLt < LMPC Eq. 2G1 LMPC = The MPC limit The value chosen for LMPC in this equation is 2. The basis for this limit is 10 CFR 50.72.

It has been shown2 that, for the radionuclides present in TYPICAL GASEOUS EFFLUENTS from CCNPP, the 2 MPC limit is more restrictive than the limits of Control 3.3.3.9.

It should be noted that by using 2 as the MPC limit (10 CFR 50.72), instead of using the limits of Control 3.11.2.1(a), a safety factor has been incorporated into equation 2G.

The use of 2 MPCs as a safety margin is consistent with the provisions of NUREG-0133, section 5.1.1, which states that, "... in all cases, conservative assumptions may be necessary in establishing these setpoints to account for system variables, ... the variability in release flow, ...

and the time lag between alarm and final isolation of radioactive effluents."

An alarm setpoint corresponding to 2 MPCs serves to initiate a determination of whether the 4-hour NRC notification (specified in 10 CFR 50.72) is required.

The use of a limiting specific activity equivalent to 2 MPCs is consistent with the provisions of 10 CFR 20.

AiLt = The specific activity limit for radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table II, Column 1 (microcuries/cm3)

For all the radionuclides found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B, Table II, Column 1. An acceptable alternative is to assume an isotopic mix which results in a more conservative setpoint.

1 Equation 2G has been derived from 10 CFR 20, Appendix B, Table II, Note 1.

2 Addendum To Setpoint Calculations For WRGM Monitors 1-RIC-5415 and 2-RIC-5415, R.L. Conatser, December 10, 1991.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 136 of 321 Level 3 - Information (3) The low setpoint for 1-RI-5415 (a) The ODCM does not address the calculations associated with the low setpoint.

(b) The low setpoint is specified in the CCNPP Alarm Manual.

(c) The low setpoint may be used to determine OPERABILITY of this monitor (per the provisions of Control 4.3.3.9, Table 4.3-11, Note 2).

(4) Adjusting the fixed setpoint for 1-RI-5415 (a) If the fixed setpoint calculated per equation 4G exceeds the maximum range of the monitor, the fixed setpoint shall be adjusted to a value which falls within the normal operating range of the monitor.

(b) The fixed setpoint may be established at values lower than the maximum allowable setpoint, if desired.

(c) A setpoint change should be initiated whenever any of the parameters identified in equation 4G have changed.

(d) The fixed setpoint should not be changed unless one of the following occurs:

i) The relative activity1 of any radionuclide in TYPICAL GASEOUS EFFLUENTS has changed by greater than 10%,

and the new radionuclide mixture yields a fixed setpoint which is 10% (or more) lower than the current fixed setpoint, ii) The historical maximum annual average atmospheric dispersion factor has changed, iii) The MPC limit at the SITE BOUNDARY, (presently 2 MPCs) has changed, iv) The estimated Unit 1 Main Vent Stack flow rate or Unit 2 Main Vent Stack flow rate has changed by greater than or equal to 10%2, v) The values listed in 10 CFR 20, Appendix B, Table II, Column 1 have changed, vi) The radiation monitor has been recently calibrated, repaired, or otherwise altered, or 1 As determined in accordance with Attachment 5.

2 As determined by surveillance test results (e.g., STP-M-462-1, STP-M-462-2).

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 137 of 321 Level 3 - Information vii) the monitor is not conservative in its function (see Section Functions of 1/2-RE-5415, earlier in this section).

(e) CC-AA-103-2001 contains the administrative controls associated with changing and approving the fixed setpoint.

j) Adjustable setpoint for 1/2-RI-5415 (1) General information (a) Whenever this monitor is satisfying the minimum channels operable requirement (per Control 3.3.3.9), the adjustable setpoint is calculated and adjusted before each release of a WGDT, each containment vent, and each containment purge discharged via the main vent.

(b) The adjustable setpoint is based on the specific activities of the radionuclides present in either the WGDT or the containment building, whichever is applicable. (The radionuclide concentrations are determined by radiochemical analysis per applicable Chemistry procedures as required by Control 4.11.2.1.2).

(c) Whenever the adjustable setpoint is exceeded, the WGDT, PURGE, or vent discharge via the main vent will be manually suspended.

(d) Refer to the Alarm Manual for a full list of operator ACTIONS taken in response to this alarm.

(e) The adjustable setpoint corresponds to the maximum concentration of radionuclides anticipated or expected when discharging a WGDT, a containment vent, or a containment purge via the main vent. For containment purges during outages, system evolutions may cause containment atmosphere activity to increase above what is normally expected for short periods of time.

(f) The value for the adjustable setpoint is recorded on the gaseous release permit per applicable Chemistry procedures.

(g) This alarm is not integral to the main vent radiation monitor, as purchased from the supplier.

(h) This alarm is generated by the plant computer which monitors output from 1/2-RI-5415, and provides an alarm to plant operators when the 1/2-RI-5415 adjustable setpoint has been exceeded.

(i) When this monitor is satisfying the minimum channels operable requirement (per Control 3.3.3.9), a value for the adjustable setpoint shall be calculated before each release of a WGDT, each containment vent, and each containment purge as shown below.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 138 of 321 Level 3 - Information (2) Calculating the adjustable setpoint for 1/2-RI-5415 (a) The adjustable alarm setpoint is based on the specific activity of the radionuclides in the undiluted gaseous waste (as determined by radiochemical analysis per Control 4.11.2.1.2), and the alarm setpoint is calculated as shown below.

ADJUSTABLE SETPOINT FOR 1/2-RI-5415 Sadj < (Ksf) [( Fu / Fdx ) [ ( Aiu ) ( ei )] + Bkg ] Eq. 27G1 Sadj = The adjustable setpoint for 1/2-RI-5415 (cpm)

Ksf = A constant, actually a safety factor, which allows for fluctuation in radiation monitor response (unitless)

This safety factor helps ensure the release is not unnecessarily terminated due to (1) electronic anomalies which cause spurious monitor responses, (2) statistical fluctuations in disintegration rates, (3) statistical fluctuations in detector efficiencies, (4) errors associated with sample analysis, (5) errors associated with monitor calibrations2, and (6) anticipated short term variations in activity (this applicable to containment purges only).

It is recommended that a safety factor of 10 for containment purge releases be used for calculating the adjustable setpoint. However, other values for purge releases -- not to exceed 10 -- may be used as directed by Management. A safety factor of 1.5 shall be used for all other gaseous releases.

The particular value selected for the safety factor is somewhat arbitrary, however a value less than or equal to 10 does provide plant personnel with adequate time to respond to changing plant conditions and to initiate corrective ACTIONS so as to minimize the possibility of violating either the 10 CFR 50.72 limit or the Control 3.3.3.9 limits.

The use of the safety factor is consistent with ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

The use of a safety margin is per the provisions of NUREG-0133 which states that "... the alarm and trip setpoints ... should correspond to a value(s) which represents a safe margin of assurance that the instantaneous gaseous release limit of Control 3.11.2.1(a) will not be exceeded." (per NUREG-0133, 5.1.1).

This safety margin will prevent minor fluctuations in the nominal plant vent stack flow rates, errors in monitor efficiencies, and other statistical aberrations from adversely impacting the calculated adjustable setpoint. Additionally for a special case of containment purges during outages, the safety factor allows for short term variations in activity created as a result of system evolutions in containment.

1 Equation 27G has been derived from NUREG-0133, Addendum, page AA-1.

2 The analysis errors and calibration errors refer to errors which are within established quality assurance and quality control limits.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 139 of 321 Level 3 - Information Fu = Maximum undiluted radwaste flow rate (cubic meters per second)

Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachment 7.

Fdx = The estimated Main Vent Stack (diluted gaseous radwaste) flow rate for unit x (cubic meters per second)

Since the Main Vent Stack flow rate will vary depending on the reactor unit, the configuration of air dampers, and the input gas streams, nominal Main Vent Stack flow rate is used to calculate the adjustable setpoint.

Use the nominal Main Vent Stack flow rate, for the appropriate unit, listed on Attachment 7.

The Main Vent Stack flow rate shall be determined, per approved procedures, at least once per 6 months (+ 25%). The Test and Equipment Unit shall be responsible for performing this test.

The results of the main vent flow rate test shall be evaluated to ensure the main vent flow rates used in the ODCM are an accurate reflection of the true main vent flow rates. The RETS Program Manager is responsible for modifying the (main vent flow rates used in the) ODCM in the event the main vent flow rate for either Unit 1 or Unit 2 has increased to a value which is greater than the maximum discharge flow rates listed on Attachment 7.

Aiu = Specific activity of radionuclide, i, in the undiluted waste stream, either the WGDT or containment building as applicable (microcuries per milliliter) ei = Absolute detector efficiency for nuclide, i (cpm/microcuries per milliliter)

The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor.

Bkg = An approximation of the detector background (cpm)

(3) Documenting the adjustable setpoint for 1/2-RI-5415 (a) Whenever the adjustable setpoint is calculated, the specific values chosen for each of the variables shall be documented per approved Chemistry procedures (for example, CP-604).

(4) Changing the adjustable setpoint for 1/2-RI-5415 (a) In all cases, the adjustable alarm setpoint shall be set to a value which is less than or equal to the fixed setpoint.

(b) If the adjustable setpoint exceeds the maximum range of the monitor, the setpoint shall be adjusted to a value which falls within the normal operating range of the monitor.

(c) Chemistry procedures (for example, CP-604) contain administrative controls associated with calculating and approving an adjustable setpoint.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 140 of 321 Level 3 - Information (d) Whenever this monitor is satisfying the minimum channels operable requirement (per Control 3.3.3.9 ) the calculated value for the adjustable setpoint shall be entered into the plant computer before each release of a WGDT, a containment vent, or a containment purge via the main vent.

k) Alert setpoint for 1/2-RI-5415 (1) General information (a) The alert setpoint is applicable to containment purges only.

(b) Whenever this monitor is satisfying the minimum channels operable requirement (per Control 3.3.3.9), the alert setpoint is calculated and adjusted before each containment purge discharged via the main vent.

(c) The alert setpoint is based on the specific activities of the radionuclides present in the containment building. (The radionuclide concentrations are determined by radiochemical analysis per applicable Chemistry procedures as required by Control 4.11.2.1.2).

(d) Whenever the alert setpoint is exceeded, the PURGE via the main vent may continue.

(e) The alert setpoint corresponds to a level of activity which indicates additional source term(s) may be present, and as a result, additional notifications and/or actions are required to identify the source and to accurately account for the activity discharged.

(f) The value for the alert setpoint is recorded on the gaseous release permit per applicable Chemistry procedures.

(g) This alarm is not integral to the main vent radiation monitor, as purchased from the supplier.

(h) This alarm is generated by the plant computer which monitors output from 1/2-RI-5415, and provides an alarm to plant operators when the 1/2-RI-5415 alert setpoint has been exceeded.

(i) When this monitor is satisfying the minimum channels operable requirement (per Control 3.3.3.9), a value for the alert setpoint shall be calculated before each containment purge as shown below.

(2) Calculating the alert setpoint for 1/2-RI-5415 (a) The alert setpoint is based on the specific activity of the radionuclides in the undiluted gaseous waste (as determined by radiochemical analysis per Control 4.11.2.1.2), and the setpoint is calculated as shown below.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 141 of 321 Level 3 - Information ALERT SETPOINT FOR 1/2-RI-5415 Salert < 1.50 [( Fu / Fdx ) [ ( Aiu ) ( ei )] + Bkg ] Eq. 27G1 Salert = the alert setpoint for 1/2-RI-5415 (cpm) 1.50 = a constant, actually a safety factor, which allows for fluctuation in radiation monitor response (unitless).

This safety factor helps ensure the release is not unnecessarily terminated due to (1) electronic anomalies which cause spurious monitor responses, (2) statistical fluctuations in disintegration rates, (3) statistical fluctuations in detector efficiencies, (4) errors associated with sample analysis, and (5) errors associated with monitor calibrations.

The use of the safety factor is consistent with ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

The use of a safety margin is per the provisions of NUREG-0133 which states that "... the alarm and trip setpoints ... should correspond to a value(s) which represents a safe margin of assurance that the instantaneous gaseous release limit of Control 3.11.2.1(a) will not be exceeded." (per NUREG-0133, 5.1.1).

This safety margin will prevent minor fluctuations in the nominal plant vent stack flow rates, errors in monitor efficiencies, and other statistical aberrations from adversely impacting the calculated alert setpoint.

Fu = maximum undiluted radwaste flow rate (cubic meters per second)

Values of maximum undiluted radwaste flow rates for various waste streams are tabulated in Attachment 7.

Fdx = the estimated Main Vent Stack (diluted gaseous radwaste) flow rate for unit x (cubic meters per second)

Since the Main Vent Stack flow rate will vary depending on the reactor unit, the configuration of air dampers, and the input gas streams, nominal Main Vent Stack flow rate is used to calculate the alert setpoint.

Use the nominal Main Vent Stack flow rate, for the appropriate unit, listed on Attachment 7.

The Main Vent Stack flow rate shall be determined, per approved procedures, at least once per 6 months (+ 25%). The Test and Equipment Unit shall be responsible for performing this test.

The results of the main vent flow rate test shall be evaluated to ensure the main vent flow rates used in the ODCM are an accurate reflection of the true main vent flow rates. The RETS Program Manager is responsible for modifying the (main vent flow rates used in the) ODCM in the event the main vent flow rate for either Unit 1 or Unit 2 has increased to a value which is greater than the maximum discharge flow rates listed on Attachment 7.

Aiu = specific activity of radionuclide, i, in the containment building (microcuries per milliliter) 1 Equation 27G has been derived from NUREG-0133, Addendum, page AA-1.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 142 of 321 Level 3 - Information ei = Absolute detector efficiency for nuclide, i (cpm/microcuries per milliliter)

The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor.

Bkg = An approximation of the detector background (cpm)

(3) Documenting the alert setpoint for 1/2-RI-5415 (a) Whenever the alert setpoint is calculated, the specific values chosen for each of the variables shall be documented per approved Chemistry procedures (for example, CP-604).

(4) Changing the alert setpoint for 1/2-RI-5415 (a) In all cases, the alert setpoint shall be set to a value which is less than or equal to the fixed setpoint.

(b) If the alert setpoint exceeds the maximum range of the monitor, the setpoint shall be adjusted to a value which falls within the normal operating range of the monitor.

(c) Chemistry procedures (for example, CP-604) contain administrative controls associated with calculating and approving an alert setpoint.

(d) Whenever this monitor is satisfying the minimum channels operable requirement ( per Control 3.3.3.9 ) the calculated value for the alert setpoint shall be entered into the plant computer before each containment purge via the main vent.

l) The low setpoint for 1/2-RI-5415 (1) This alarm is integral to the main vent monitor, as purchased from the supplier.

(2) The current value for the low alarm setpoint is specified in the CCNPP Alarm Manual.

(3) The low setpoint may be used to determine the OPERABILITY of this monitor (per Control 4.3.3.9, CHANNEL FUNCTIONAL TEST).

(4) The alarm generated by the low setpoint may be used to terminate a release in the event 1/2-RI-5415 fails (that is, downscale failure or circuit failure) per Control 4.3.3.9.

(5) The low setpoint calculations are not described in the ODCM.

(6) Changes to the low setpoint are documented in the CCNPP Alarm Manual.

4. Westinghouse Plant Vent Stack Monitor (2-RE-5415)

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 143 of 321 Level 3 - Information a) All information related to 1-RE-5415 is applicable to the Unit 2 plant vent stack monitor with the following exception(s):

b) Monitors equivalent to 2-RE-5415 (1) 2-RE-5416A [the WRNGM] has the capability of providing the measurement and alarm functions of 2-RE-5415 during times when 2-RE-5415 is declared inoperable.

(2) 2-RE-5415 provides redundant monitoring [for 2-RE-5416A] at the low end of the concentration ranges (UFSAR 11.2.3.2.12).

5. Gaseous Radwaste Processing System Radiation Monitor (0-RE-2191) a) General description (1) The GASEOUS RADWASTE PROCESSING SYSTEM Radiation Monitor (Waste Gas Decay Tank Radiation Monitor) contains 1 radiation element.

(2) It is a noble gas detector.

(3) The detector is an in-line GM tube (UFSAR, Table 11-10).

(4) The radiation element is designated 0-RE-2191.

(5) The radiation indicators designated 0-RI-2191.

(6) The units for the radiation indicator are counts per minute.

(7) The monitor was manufactured by Westinghouse.

b) Functions of 0-RE-2191 (1) Continuously measure the release rate of noble gases emanating from the waste gas decay tank discharge header (Control 4.11.2.1.2, Table 4.11-2)

(2) Continuously indicate (via 0-RI-2191) the activity (cpm) of noble gases emanating from the waste gas decay tank discharge header (Control 3.3.3.9 OPERABILITY requirement)

(3) Alarm (via 1-RI-2191) before exceeding the site-boundary, noble-gas, total-body-dose-rate limit of 500 mr/yr (per Control 3.11.2.1.a)

(4) Alarm (via 1-RI-2191) before exceeding the site-boundary, noble-gas, skin-dose-rate limit of 3000 mr/yr (per Control 3.11.2.1.a)

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 144 of 321 Level 3 - Information c) OPERABILITY of 0-RE-2191 (1) This monitor shall be operable (or have OPERABILITY) when it is capable of performing its specified function(s).

(2) For more information on the function(s) of this monitor, see Functions of 0-RE-2191, elsewhere in this section of the ODCM.

d) Monitors equivalent to 0-RE-2191 (1) There are no equivalent monitors associated with 0-RE-2191 since there are no other radiation monitors permanently installed in the waste gas discharge header, however, Control 3.3.3.9 defines the plant vent stack monitor as a BACKUP MONITOR.

(2) 0-RE-2191 is designated the PRIMARY MONITOR for measuring noble gas activity released via the GASEOUS RADWASTE PROCESSING SYSTEM.

(3) 1-RE-5415 (or 1-RE-5416A) is designated the BACKUP MONITOR if the WGDT is discharged via the Unit 1 Main Vent.

(4) 2-RE-5415 (or 2-RE-5416A) is designated the BACKUP MONITOR if the WGDT is discharged via the Unit 2 Main Vent.

(5) WGDTs may be discharged through either the Unit 1 or Unit 2 Main Vent Stack.

(6) The BACKUP MONITOR has the capability of ensuring the noble gas activity released from the GASEOUS RADWASTE PROCESSING SYSTEM--to the plant vent stack--does not exceed Control 3.11.2.1(a) at the SITE BOUNDARY (Control 3.3.3.9).

(7) In the event PRIMARY MONITOR (0-RE-2191) is inoperable or otherwise unavailable, the designated BACKUP MONITOR (either 1-RE-5415, 1-RE-5416A, 2-RE-5415, or 2-RE-5416A) may fulfill the measuring, indicating, and alarming functions normally provided by the PRIMARY MONITOR as long as plant operators record the BACKUP MONITOR readings every 15 minutes (Control 3.3.3.9, Table 3.3-12, ACTION 35a).

e) Radiological effluent controls for 0-RE-2191 (1) Control 3.3.3.9 states that releases via the GASEOUS RADWASTE PROCESSING SYSTEM may continue if ANY ONE of the following three conditions are satisfied:

(a) 0-RE-2191 is operable AND the alarm setpoint for 0-RI-2191 is set to ensure the annual dose rates due to noble gases at the SITE BOUNDARY are less than 500 mr/yr to the total body and are less than 3000 mr/yr to the skin (per Control 3.11.2.1.a), or December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 145 of 321 Level 3 - Information (b) One BACKUP MONITOR (see section (e) above) is operable; AND the BACKUP MONITOR readings are recorded every 15 minutes during the release; AND the alarm setpoint for the BACKUP MONITOR is set to ensure the annual dose rates due to noble gases at the SITE BOUNDARY are less than 500 mr/yr to the total body and are less than 3000 mr/yr to the skin (per Control 3.11.2.1.a), or (c) All three activities described below are completed before the release:

i) At least two independent samples of the waste gas decay tank's contents are analyzed, and ii) At least two technically qualified members of the Facility Staff independently verify the release rate calculations, and iii) Two qualified operators verify the discharge valve lineup.

f) Surveillances for 0-RE-2191 (1) Control 4.3.3.9 requires demonstrating the OPERABILITY of 0-RE-2191 by satisfying the checks, calibrations, and tests listed below (a) CHANNEL CHECK before each release (b) SOURCE CHECK before each release (c) CHANNEL CALIBRATION within the past 18 months (d) CHANNEL FUNCTIONAL TEST within the past 6 six months g) Setpoints for 0-RI-2191 (1) Requirements and commitments (a) The alarm and fixed setpoints shall be determined and adjusted per the methodology and parameters of the ODCM. (Control 3.3.3.9)

(b) The method for calculating fixed or adjustable setpoints shall be provided in the ODCM. (NUREG-0133, 5.1.1)

(2) There are three radiation alarm setpoints associated with, or otherwise related to, 0-RE-2191.

(a) 0-RE-2191 fixed high radiation alarm and automatic termination setpoint (b) 0-RE-2191 adjustable plant computer high radiation alarm and manual termination setpoint (c) 0-RE-2191 low radiation alarm setpoint December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 146 of 321 Level 3 - Information (3) In order to simplify the setpoint terminology, eliminate ambiguity, and minimize the possibility of misinterpretation, the ODCM will refer to these setpoints as follows:

(a) The 0-RE-2191 fixed high radiation alarm and automatic termination setpoint will be referred to as the fixed setpoint.

(b) The 0-RE-2191 adjustable plant computer high radiation alarm and manual termination setpoint will be referred to as the adjustable setpoint.

(c) The 0-RE-2191 low radiation alarm setpoint will be referred to as the low setpoint.

(4) Each of these alarm setpoints are described below.

h) Fixed setpoint for 0-RI-2191 (1) General information (a) The fixed setpoint is not adjusted for each release.

(b) The fixed setpoint is an alarm and termination setpoint.

(c) Whenever the fixed setpoint is exceeded, an alarm will be generated, and the WGDT release will be automatically suspended.

(d) The fixed setpoint corresponds to the maximum concentration of radionuclides allowed (by equation 6G) in gaseous waste discharged from the gaseous radwaste processing system.

(e) The current value for the fixed setpoint is specified in the CCNPP Alarm Manual.

(f) The CCNPP Alarm Manual refers to this setpoint as the 0-RI-2191 High Radiation Alarm Setpoint.

(g) The fixed setpoint is integral to the waste gas discharge monitor, as purchased from the supplier.

(h) The fixed setpoint is documented in the CCNPP Alarm Manual.

(i) The fixed setpoint shall be calculated as described below1.

1 The alarm and trip setpoints ... shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Control 3.3.3.9).

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 147 of 321 Level 3 - Information (2) Calculating the fixed setpoint for 0-RI-2191 (a) The fixed setpoint for 0-RI-2191 (waste gas discharge monitor) shall be calculated as described below:

FIXED SETPOINT FOR 0-RI-2191 Sfix < Ksf { { 1 / [ ( x/Q ) ( Fu ) ] } [ ( ei ) ( AiLn ) ] + Bkg } Eq. 6G1

Where, Ksf = A constant, actually a safety factor, which is the ratio of the CCNPP activity limit to the MPC Limit, LMPC, used in equation 2G (unitless)

The safety factor chosen shall be less than or equal to 1.00. This ensures the fixed setpoint is always less than or equal to the MPC limit, LMPC, used in equation 2G.

A safety factor of 1.00 is used for calculating the fixed setpoint.

By setting the safety factor to 1, the safety factor is disabled.

Although it may appear that if this safety factor is set to 1.0, no safety margin exists, in actuality, another margin of safety has been incorporated into equation 2G (see definition of LMPC).

A safety factor of 1.00 will yield a fixed setpoint which corresponds to the MPC limit, L MPC, in equation 2G.

A safety factor of 0.500 will yield a fixed setpoint which corresponds to one-half the MPC limit, LMPC, in equation 2G.

Other values of safety factors--not to exceed 1.00--may be used for calculating the fixed setpoint as directed by Management.

The particular value selected for the safety factor is somewhat arbitrary, however a value less than or equal to 1.0 does provide plant personnel with adequate time to respond to changing plant conditions and to initiate corrective ACTIONS so as to minimize the possibility of violating either the 10 CFR 50.72 limit or the Control 3.3.3.9 limits.

The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

The use of a safety margin is per the provisions of NUREG-0133 which states that "... the alarm and trip setpoints ... should correspond to a value(s) which represents a safe margin of assurance that the instantaneous gaseous release limit of Control 3.11.2.1(a) will not be exceeded." (per NUREG-0133, 5.1.1).

This safety margin will prevent minor fluctuations in the nominal WGDT discharge flow rates, errors in detector efficiencies, and other statistical aberrations from adversely impacting the calculated fixed setpoint.

1 Equation 6G has been derived from NUREG-0133, 5.2.1, (the 500 mr/yr equation).

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 148 of 321 Level 3 - Information Sfix = The fixed setpoint for 0-RI-2191 (cpm) x/Q = The highest calculated historical annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

A waste gas decay tank release via the Unit 1 or Unit 2 main vent is considered a long-term release1, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the setpoint calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6 (UFSAR, 2.3.6.3) for purposes of routine, long-term concentrations (for example, routine noble gas releases).

The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3).

Fu = The estimated maximum flow rate of undiluted gases through the waste gas discharge header (cubic meters per second)

Since WGDT pressure is the motive force for discharge of a WGDT, the waste gas flow rate will continually decrease as the release progresses (that is, as tank pressure is decreased).

Use the estimated maximum WGDT discharge flow rate, listed on Attachment 7, to calculate the fixed setpoint.

ei = Absolute detector efficiency for nuclide, i (cpm/microcuries per milliliter)

The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor.

AiLn = The specific activities of radionuclide, i, found in TYPICAL GASEOUS RADWASTE RELEASES (calculated per 10 CFR 20, Appendix B, Table II, Note 1 as described below; microcuries per milliliter)

Calculate AiLn per equation 5G.

SPECIFIC ACTIVITY LIMIT FOR NUCLIDE I IN A RADIONUCLIDE MIXTURE AiLn = ( fi ) ( ATLn ) Eq. 5G fi = A fraction which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitless)

This value may be obtained using the guidance provided on Attachment 5.

ATLn = The sum of the total specific activities of all noble gas radionuclides found in TYPICAL GASEOUS RADWASTE RELEASES (microcuries/cm3).

1 NUREG-0133, 3.3 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 149 of 321 Level 3 - Information Calculate ATLn per equation 2G.

SPECIFIC ACTIVITY OF NOBLE GASES AT THE SITE BOUNDARY

[ ( fi ) ( ATLn ) ] / AiLt < LMPC Eq. 2G1

Where, LMPC = The MPC limit The value chosen for LMPC in this equation is 2. The basis for this limit is 10 CFR 50.72.

It has been shown2 that, for the radionuclides present in TYPICAL GASEOUS EFFLUENTS from CCNPP, the 2 MPC limit is more restrictive than the limits of Control 3.3.3.9.

It should be noted that by using 2 as the MPC limit (10 CFR 50.72), instead of using the limits of Control 3.11.2.1(a), a safety factor has been incorporated into equation 2G.

The use of 2 MPCs as a safety margin is consistent with the provisions of NUREG-0133, section 5.1.1, which states that, "... in all cases, conservative assumptions may be necessary in establishing these setpoints to account for system variables, ... the variability in release flow, ...

and the time lag between alarm and final isolation of radioactive effluents." (NUREG-0133, 5.1.1)

An alarm setpoint corresponding to 2 MPCs serves to initiate a determination of whether the 4-hour NRC notification (specified in 10 CFR 50.72) is required.

AiLt = The specific activity limit for radionuclide, i, as obtained from 10 CFR 20, Appendix B, Table II, Column 1 (microcuries/cm3)

For all the radionuclides found in TYPICAL RADWASTE EFFLUENTS, use the value from 10 CFR 20, Appendix B, Table II, Column 1. An acceptable alternative is to ensure an isotopic mix which results in a more conservative setpoint.

Bkg = An approximation of the detector background before initiating the gaseous release (cpm)

Instead of using an approximation of the detector background, a value of 0 cpm may be used as the detector background if so desired.

(3) Documenting the fixed setpoint for 0-RI-2191 (a) Whenever the fixed setpoint is calculated, the specific values chosen for each of the variables shall be documented per CC-AA-103-2001.

(4) Changing the fixed setpoint for 0-RI-2191 1 Equation 2G has been derived from 10 CFR 20, Appendix B, Table II, Note 1.

2 Addendum To Setpoint Calculations For WRGM Monitors 1-RIC-5415 and 2-RIC-5415, R.L. Conatser, December 10, 1991.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 150 of 321 Level 3 - Information (a) If the fixed setpoint calculated per equation 6G exceeds the maximum range of the monitor, the fixed setpoint shall be adjusted to a value which falls within the normal operating range of the monitor.

(b) The fixed setpoint may be established at values lower than the maximum allowable setpoint, if desired.

(c) A setpoint change should be initiated whenever any of the parameters identified in equations 2G, 5G, or 6G have changed.

(d) The fixed setpoint should not be changed unless one of the following occurs:

i) The relative activity1 of any radionuclide in TYPICAL GASEOUS EFFLUENTS has changed by greater than 10%,

and the new radionuclide mixture yields a fixed setpoint which is 10% (or more) lower than the current fixed setpoint, ii) The historical maximum annual average atmospheric dispersion factor has changed, iii) The MPC limit at the SITE BOUNDARY, (presently 2 MPCs) has changed, iv) Values listed in 10 CFR 20, Appendix B, Table II, Column 1 have changed, v) The radiation monitor has been recently calibrated, repaired, or otherwise altered, or vi) The monitor is not conservative in its function (see section Functions of 0-RE-2191, earlier in this section).

(e) CC-AA-103-2001 contains the administrative controls associated with changing and approving fixed setpoint.

i) Adjustable setpoint for 0-RI-2191 (1) General information (a) Whenever this radiation monitor is operable, the adjustable setpoint is calculated and adjusted before each release of a WGDT.

(b) The adjustable setpoint is based on the specific activities of the radionuclides present in the WGDT. (The radionuclide concentrations are determined by radiochemical analysis per applicable Chemistry procedures as required by Control 4.11.2.1.2).

1 As determined in accordance with Attachment 5.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 151 of 321 Level 3 - Information (c) Whenever the adjustable setpoint is exceeded, the WGDT discharge will be manually suspended.

(d) Refer to the radwaste Alarm Manual for a full list of operator ACTIONS taken in response to this alarm.

(e) The adjustable setpoint corresponds to the maximum concentration of radionuclides anticipated or expected when discharging a WGDT.

(f) The value for the adjustable setpoint is recorded on the gaseous release permit per applicable Chemistry procedures.

(g) This alarm is not integral to the GASEOUS RADWASTE PROCESSING SYSTEM radiation monitor, as purchased from the supplier.

(h) This alarm is generated by the plant computer which monitors output from 0-RI-2191, and provides an alarm to plant operators when the 0-RI-2191 adjustable setpoint has been exceeded.

(i) When this monitor is operable, a value for the adjustable setpoint shall be calculated before each release of a WGDT as shown below.

(2) Calculating the adjustable setpoint for 0-RI-2191 (a) The adjustable setpoint is based on the specific activity of the radionuclides in the undiluted gaseous waste (as determined by radiochemical analysis per Control 4.11.2.1.2), and is calculated as shown below.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 152 of 321 Level 3 - Information ADJUSTABLE SETPOINT FOR 0-RI-2191 Sadj < 1.50 [ ( Aiu ) ( ei ) + Bkg ] Eq. 28G1 Sadj = the adjustable setpoint for 0-RI-2191 (cpm) 1.50 = a constant, actually a safety factor, which allows for fluctuation in radiation monitor response (unitless)

This safety factor helps ensure the release is not unnecessarily terminated due to (1) electronic anomalies which cause spurious monitor responses, (2) statistical fluctuations in disintegration rates, (3) statistical fluctuations in detector efficiencies, (4) errors associated with sample analysis, and (5) errors associated with monitor calibrations.

Fu = Maximum allowed undiluted radwaste flow rate (cubic meters per second)

The maximum allowed undiluted radwaste flow rate for a WGDT is tabulated in Attachment 7.

Aiu = Specific activity of radionuclide, i, in the undiluted waste stream (microcuries per milliliter) ei = Absolute detector efficiency for nuclide, i (cpm/microcuries per milliliter)

The detector efficiency for each radionuclide may be calculated from data collected during calibration of the radiation monitor.

Bkg = An approximation of the detector background (cpm)

(3) Documenting the adjustable setpoint for 0-RI-2191 (a) Whenever the adjustable setpoint is calculated, the specific values chosen for each of the variables shall be documented per approved Chemistry procedures (for example, CP-604).

(4) Changing the adjustable setpoint for 0-RI-2191 (a) In all cases, the adjustable setpoint shall be set to a value which is less than or equal to the fixed setpoint.

(b) If the adjustable setpoint exceeds the maximum range of the monitor, the setpoint shall be adjusted to a value which falls within the normal operating range of the monitor.

(c) Chemistry procedures (for example, CP-604) contain administrative controls associated with calculating and approving an adjustable setpoint.

(d) Whenever this monitor is operable, the calculated value for the adjustable setpoint shall be entered into the plant computer before each release of a WGDT via the main vent.

1 Equation 28G has been derived from NUREG-0133, Addendum, page AA-1.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 153 of 321 Level 3 - Information j) The low setpoint for 0-RI-2191 (1) This alarm is integral to the main vent monitor, as purchased from the supplier.

(2) The current value for the low setpoint is specified in the CCNPP Alarm Manual.

(3) The low setpoint may be used to determine the OPERABILITY of this monitor (per Control 4.3.3.9, CHANNEL FUNCTIONAL TEST).

(4) The alarm generated by the low setpoint may be used to terminate a release in the event 0-RI-2191 fails (that is, downscale failure or circuit failure) per Control 4.3.3.9.

(5) The low setpoint calculations are not described in the ODCM.

(6) Changes to the low setpoint are controlled by CC-AA-103-2001.

ANNUAL TOTAL BODY DOSE RATE DUE TO NOBLE GASES IN GASEOUS EFFLUENTS

1. Introduction a) 10 CFR 20.1301 specifies dose rate limits associated with the release of radioactive materials to UNRESTRICTED AREAS.

b) Radiological effluent controls have been established to implement the requirements of 10 CFR 20.1301. The 10 CFR 50 Appendix I, Design Objectives for ALARA Radioactive Effluents, upon which these calculations are based, are more restrictive than the public dose limits of 10 CFR 20.1301.

c) These radiological effluent controls are described below.

2. Radiological Effluent Controls a) The annual total body dose rate, due to noble gases in gaseous waste discharged to UNRESTRICTED AREAS, shall be less than 500 mr/yr (per Control 3.11.2.1).

b) The routine surveillances which are performed to verify compliance with this radiological effluent control is described below.

3. Surveillance Requirement a) The annual total body dose rate, due to noble gases in all gaseous effluents discharged from the site, shall be determined per equation 7G (per Control 4.11.2.1.1).

b) The results of the radioactive gaseous waste sampling and analysis program (required by Control 4.11.2.1.2, and implemented by various CCNPP Chemistry procedures) are used to calculate the annual total body dose rate due to noble gases in gaseous effluents.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 154 of 321 Level 3 - Information c) The plant group(s) responsible for performing the required surveillances are identified below.

4. Responsible Plant Organization(s) a) The Chemistry is responsible for calculating the annual total body dose rate due to noble gases in gaseous effluents.

b) The CCNPP Chemistry calculates the annual total body dose rate whenever the appropriate initiating conditions are present.

c) These initiating conditions are contained in the following section.

5. Initiating Conditions a) The annual total body dose rate due to noble gases in gaseous effluents is calculated for each release of a WGDT.

b) The annual total body dose rate due to noble gases in gaseous effluents is calculated for each vent of a containment building.

c) The annual total body dose rate due to noble gases in gaseous effluents is calculated for each PURGE of a containment building.

d) The annual total body dose rate due to noble gases in gaseous effluents is calculated at least weekly1 for CONTINUOUS discharges from plant vent stacks.

e) The annual total body dose rate due to noble gases in gaseous effluents is calculated for each discharge of combustion products resulting from the burning of contaminated oil.

f) The annual total body dose rate due to noble gases in gaseous effluents is calculated for each ABNORMAL AND/OR UNANTICIPATED RADIOACTIVE GAS RELEASE.

g) Whenever the correct initiating conditions are present, the annual total body dose rates shall be calculated as described below.

6. Calculation Methodology a) The annual total body dose rate, at the SITE BOUNDARY, due to noble gases in gaseous effluents released to UNRESTRICTED AREAS shall be calculated per equation 7G.2 1 The frequency is controlled by the implementing procedure, and is based on plant conditions. Under no conditions shall the frequency be less than once per month (Control 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2).

2 The alarm and trip setpoints ... shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Control 3.3.3.9).

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 155 of 321 Level 3 - Information ANNUAL TOTAL BODY DOSE RATE DUE TO NOBLE GASES IN ALL GAS RELEASES Dt0 = Dtr Eq. 7G Dt0 = The site-boundary annual total body dose rate due to noble gases in all gaseous effluents discharged (simultaneously) from the site (mrem/year)

Dtr = The site-boundary annual total body dose rate due to noble gases in release, r (mrem/year)

Sum for all releases, r, which are discharged simultaneously.

An example of a SIMULTANEOUS RELEASE would include the release of noble gas radionuclides from the Unit 1 plant vent stack while also discharging noble gases from the Unit 2 plant vent stack.

An example of a SIMULTANEOUS RELEASE would include the release of noble gas radionuclides from the Unit 1 plant vent stack while also discharging a waste gas decay tank.

Calculate the values of Dtr for each SIMULTANEOUS RELEASE as shown below.

b) At CCNPP, two methods exist for calculating Dtr (that is, annual total body dose rate at the SITE BOUNDARY due to noble gases contained in a gaseous radwaste release, r, discharged from the site).

(1) The rigorous method shall be used IF a computer system and the appropriate software are available.

(2) The simplified method may be used IF a computer system and the appropriate software are NOT available.

(3) These methods, as well as additional supporting information, are presented in the following sections.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 156 of 321 Level 3 - Information c) Rigorous method (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropriate software are available.

(2) If a computer system and the appropriate software are available, the annual total body dose rate due to noble gases in gaseous effluents discharged from the site to UNRESTRICTED AREAS shall be calculated per equation 8G.

ANNUAL TOTAL BODY DOSE RATE DUE TO NOBLE GASES IN GAS RELEASE, r (RIGOROUS METHOD)

Dtr = ( x/Q ) [ ( Ki ) ( Qir ) ] Eq. 8G1

Where, x/Q = The highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

All releases are considered long-term releases2, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose rate calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6 for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3)

The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3)

Ki = The total body dose factor due to gamma emissions for each identified noble gas radionuclide, i (mrem/yr per microcurie/cubic meter)

The total-body dose factors for gamma rays from noble gas radionuclides were obtained from Regulatory Guide 1.109, Appendix B, Table B-1.

The total-body dose factors for various noble gas radionuclides are tabulated in Attachment 10.

Qir = The release rate of noble gas radionuclide, i, in (simultaneous) gaseous release, r (microcuries/second).

Calculate the values of Qir for each SIMULTANEOUS RELEASE as shown below.

1 Equations 8G has been derived from NUREG-0133, 5.2.1, and Regulatory Guide 1.109 (Appendix B, Equation B-8 and Section C.2.e).

2 NUREG-0133, 3.3 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 157 of 321 Level 3 - Information INSTANTANEOUS RELEASE RATE OF NOBLE GAS NUCLIDE i IN GASEOUS RELEASE r Qir = ( Air ) ( Fr ) ( c' ) Eq. 9G

Where, Air = The specific activity of noble gas radionuclide, i, in (simultaneous) release, r (microcuries/cubic centimeter)

Fr = The discharge flow rate for (simultaneous) release, r (cubic meters per second)

If the discharge flow rate is unknown (for example, the release has not been conducted), the Maximum Discharge Flow Rate listed on Attachments 7 or 8 may be used to calculate the annual total body dose rate.

Whenever possible, the actual discharge flow rate determined from actual release conditions (for example, initial pressure, volume, and temperature of a WGDT along with final pressure and temperature) shall be used in equation 9G.

Additional guidance for calculating discharge flow rates may be contained in approved Chemistry procedures.

c' = A conversion constant (1E6 cubic centimeters per cubic meter) d) Simplified method (1) If a computer system and the appropriate software are NOT available, the annual total body dose rate due to noble gases in gaseous effluents discharged from the site to UNRESTRICTED AREAS may be calculated per equation 10G.

ANNUAL TOTAL BODY DOSE RATE DUE TO NOBLE GASES IN GAS RELEASE, r (SIMPLIFIED METHOD)

Dtr = [ ( x/Q ) ( Kavg ) / ( Ksf ) ] Qir Eq. 10G1

Where, x/Q = The highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter).

All releases are considered long-term releases2, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose rate calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6 for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3) 1 Equations 10G has been derived from NUREG-0133, 5.2.1, and historical, site-specific data.

2 NUREG-0133, 3.3 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 158 of 321 Level 3 - Information The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3)

Kavg = The empirically derived, site specific, average, total body, dose factor due to gamma emissions from TYPICAL GASEOUS EFFLUENTS (mrem/yr per microcurie/cubic meter)

A site-specific, average, gamma total body dose factor for TYPICAL GASEOUS EFFLUENTS has been calculated from historical data.

The calculation of this site-specific, average, gamma air dose factor is presented on Attachment 11.

Refer to the table on Attachment 11 for the current value for the empirically derived, site specific, average gamma total body dose factor.

Ksf = A constant, actually a safety factor, which is the ratio of the CCNPP annual total body dose rate limit to the annual total body dose rate limit of Control 3.11.2.1, (unitless)

The safety factor chosen shall be less than or equal to 1.00. This ensures the annual total body dose rate is always less than or equal to the annual total body dose rate limit of Control 3.11.2.1.

A safety factor of 1.00 will yield an annual total body dose rate which corresponds to the annual total body dose rate limit of Control 3.11.2.1.

A safety factor of 0.500 will yield an annual total body dose rate which corresponds to one-half the annual total body dose rate limit of Control 3.11.2.1.

It is recommended that a safety factor of 1.0 be used for calculating the annual total body dose rate, however, other values--not to exceed 1.00--may be used as directed by Management.

The particular value selected for the safety factor is somewhat arbitrary, however, a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive gaseous release permits. This administrative control is designed to minimize the possibility of violating Control 3.11.2.1 when simplifying assumptions are used.

The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 159 of 321 Level 3 - Information This safety factor has been included in equation 10G to account for any potential nonconservatism associated with applying the empirically derived total body gamma dose factor, Kavg, to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a total body gamma dose factor greater than Kavg are present in a gaseous release.

Qir = the release rate of noble gas radionuclide, i, in (simultaneous) gaseous release, r (microcuries/second)

Calculate the values of Qir for each SIMULTANEOUS RELEASE per equation 9G.

INSTANTANEOUS RELEASE RATE OF NOBLE GAS NUCLIDE i IN GASEOUS RELEASE r Qir = ( Air ) ( Fr ) ( c' ) Eq. 9G

Where, Air = The specific activity of noble gas radionuclide, i, in (simultaneous) release, r (microcuries/cubic centimeter)

Fr = The discharge flow rate for (simultaneous) release, r (cubic meters per second)

If the discharge flow rate is unknown (for example, the release has not been conducted), the Maximum Discharge Flow Rate listed on Attachments 7 or 8 may be used to calculate the annual total body dose rate.

Whenever possible, the actual discharge flow rate determined from actual release conditions (for example, initial pressure, volume, and temperature of a WGDT along with final pressure and temperature) shall be used in equation 9G.

Additional guidance for calculating discharge flow rates may be contained in approved Chemistry procedures.

c' = a conversion constant (1E6 cubic centimeters per cubic meter) e) Radiation monitoring system algorithms (1) The plant vent stack radiation monitoring systems display values which are proportional to the annual total body dose rates due to noble gases emanating from the plant vent stacks.

(2) The values displayed by the plant vent stack radiation monitoring systems are not used for the purpose of effluent accountability per se, but the values displayed can provide a gross approximation of annual total body dose rate (see Control 3.3.3.9).

(3) The Westinghouse Main Vent Noble Gas Monitor, 1/2-RE-5415, is an analog system and does not employ instrument algorithm to determine noble gas release rates.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 160 of 321 Level 3 - Information (a) It is possible to approximate the noble gas release rates for the Unit 1 and Unit 2 main vents based on output from 1/2-RI-5415.

(b) These calculations are described elsewhere in the ODCM. (See equation 4G in the section Calculating the Fixed Setpoint for 1/2-RI-5415.)

(4) The WRNGM, 1/2-RE-5416A, is a digital radiation monitoring system which employs an instrument algorithm to determine noble release rates (microcuries per second).

(a) It is possible to approximate the noble gas release rates for the Unit 1 and Unit 2 main vents based on output from 1/2-RIC-5415.

(b) These calculations are described elsewhere in the ODCM. (See equation 1G in the section Calculating the Fixed High-High Alarm Setpoint for 1/2-RIC-5415.)

(c) The instrument algorithms and the (data base) values accessed by the instrument algorithms are documented in the CCNPP Alarm Manual.

f) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective ACTIONS are initiated as described below.

7. Corrective actions a) Chemistry surveillance procedures shall contain/and or reference administrative and/or Control limits for annual total body dose rates for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Control 3.11.2.1 for actions to be taken in the event the calculated annual total body dose rate due to noble gases in gaseous effluents exceeds 500 mr/yr.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 161 of 321 Level 3 - Information ANNUAL SKIN DOSE RATE DUE TO NOBLE GASES IN GASEOUS EFFLUENTS

1. Introduction a) 10 CFR 20.1301 specifies dose rate limits associated with the release of radioactive materials to UNRESTRICTED AREAS.

b) Radiological effluent controls have been established to implement the requirements of 10 CFR 20.1301.

c) These radiological effluent controls are described below.

2. Radiological Effluent Controls a) The annual skin dose rate, due to noble gases in gaseous waste discharged to UNRESTRICTED AREAS, shall be less than 3000 mr/yr (per Control 3.11.2.1).

b) The routine surveillances which are performed to verify compliance with this radiological effluent controls are described below.

3. Surveillance Requirement a) The annual skin dose rate at the SITE BOUNDARY, due to noble gases in all gaseous effluents discharged from the site, shall be determined per equation 11G (per Control 4.11.2.1.1).

b) The results of the radioactive gaseous waste sampling and analysis program (required by Control 4.11.2.1.2, and implemented by various CCNPP Chemistry procedures) are used to calculate the annual skin dose rate due to noble gases in gaseous effluents.

c) The plant group(s) responsible for performing the required surveillances are identified below.

4. Responsible Plant Organization(s) a) The Chemistry is responsible for calculating the annual skin dose rate due to noble gases in gaseous effluents.

b) The CCNPP Chemistry calculates the annual skin dose rate whenever the appropriate initiating conditions are present.

c) These initiating conditions are contained in the following section.

5. Initiating Conditions a) The annual skin dose rate due to noble gases in all gaseous effluents discharged from the site is calculated for each release of a WGDT.

b) The annual skin dose rate due to noble gases in all gaseous effluents discharged from the site is calculated for each vent of a containment building.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 162 of 321 Level 3 - Information c) The annual skin dose rate due to noble gases in all gaseous effluents discharged from the site is calculated for each PURGE of a containment building.

d) The annual skin dose rate due to noble gases in all gaseous effluents discharged from the site is calculated at least weekly1 for CONTINUOUS discharges from plant vent stacks.

e) The annual skin dose rate due to noble gases in all gaseous effluents discharged from the site is calculated for each discharge of combustion products resulting from the burning of contaminated oil.

f) The annual skin dose rate due to noble gases in all gaseous effluents discharged from the site is calculated for each ABNORMAL AND/OR UNANTICIPATED RADIOACTIVE GAS RELEASE.

g) Whenever the correct initiating conditions are present, the annual skin dose rates shall be calculated as described below.

6. Calculation Methodology a) The annual skin dose rate, at the SITE BOUNDARY, due to noble gases in all gaseous effluents discharged simultaneously from the site to UNRESTRICTED AREAS shall be calculated per equation 11G.2 ANNUAL SKIN DOSE RATE DUE TO NOBLE GASES IN ALL SIMULTANEOUS GAS RELEASES, r Ds0 = Dsr Eq. 11G Ds0 = The annual skin dose rate at the SITE BOUNDARY due to noble gases in all simultaneous discharges of gaseous radwaste from the site (Unit 0)

Dsr = The annual skin dose rate at the SITE BOUNDARY due to noble gases in release, r Sum for all releases, r, which are discharged simultaneously.

An example of a SIMULTANEOUS RELEASE would include the release of noble gas radionuclides from the Unit 1 plant vent stack while also discharging noble gases from the Unit 2 plant vent stack.

An example of a SIMULTANEOUS RELEASE would include the release of noble gas radionuclides from the Unit 1 plant vent stack while also discharging a waste gas decay tank.

Calculate the values of Dsr for each SIMULTANEOUS RELEASE as shown below.

1 The frequency is controlled by the implementing procedure and is based on plant conditions. Under no conditions shall the frequency be less than once per month (Control 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2).

2 The alarm and trip setpoints ... shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Control 3.3.3.9).

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 163 of 321 Level 3 - Information b) At CCNPP, two methods exist for calculating Dsr (that is, annual total skin dose rate at the SITE BOUNDARY due to noble gases contained in a gaseous radwaste release, r, discharged from the site).

(1) The rigorous method shall be used IF a computer system and the appropriate software are available.

(2) The simplified method may be used IF a computer system and the appropriate software are NOT available.

(3) These methods, as well as additional supporting information, are presented in the following sections.

c) Rigorous Method (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropriate software are available.

(2) If a computer system and the appropriate software are available, the annual skin dose rate due to noble gases in gaseous release, r, discharged from the site to UNRESTRICTED AREAS shall be calculated per equation 12G.

ANNUAL SKIN DOSE RATE DUE TO NOBLE GASES IN GAS RELEASE, r (RIGOROUS METHOD)

Dsr = ( x/Q ) { [ Li + ( 1.1 ) ( Mi ) ] ( Qir ) } Eq. 12G1

Where, x/Q = The highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

All releases are considered long-term releases2, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose rate calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6 for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3)

The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3)

Li = The skin dose factor due to beta emissions for each identified noble gas radionuclide, i (mrem/yr per microcurie/cubic meter)

The beta skin dose factors have been obtained from Regulatory Guide 1.109, Appendix B, Table B-1.

1 Equation 12G has been derived from NUREG-0133, 5.2.1, and Regulatory Guide 1.109 (Appendix B, Equation B-9 and Section C.2.f).

2 NUREG-0133, 3.3 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 164 of 321 Level 3 - Information The beta skin dose factors for various noble gas radionuclides are tabulated in Attachment 10.

Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide, i (mrad/yr per microcurie/cubic meter)

The gamma air dose factors have been obtained from Regulatory Guide 1.109, Appendix B, Table B-1.

The gamma air dose factors for various noble gas radionuclides are tabulated in Attachment 10.

1.1 = The conversion constant, 1.1 mrem/mrad, represents the skin dose (1.1 mrem) equivalent to air dose (1.0 mrad), and is used to convert air dose to skin dose.

Qir = The release rate of noble gas radionuclide, i, in (simultaneous) release, r (microcuries/second).

This value shall be calculated per equation 9G.

INSTANTANEOUS RELEASE RATE OF NOBLE GAS NUCLIDE i IN GASEOUS RELEASE r Qir = ( Air ) ( Fr ) ( c' ) Eq. 9G Air = The specific activity of noble gas radionuclide, i, in (simultaneous) release, r (microcuries/cubic centimeter)

Fr = The discharge flow rate for (simultaneous) release, r (cubic meters per second)

If the discharge flow rate is unknown (for example, the release has not been conducted), the Maximum Discharge Flow Rate listed on Attachments 7 or 8 may be used to calculate the annual skin dose rate.

Whenever possible, the actual discharge flow rate determined from actual release conditions (for example, initial pressure, volume, and temperature of a WGDT along with final pressure and temperature) shall be used in equation 9G.

Additional guidance for calculating discharge flow rates may be contained in approved Chemistry procedures.

c' = A conversion constant (1E6 cubic centimeters per cubic meter) d) Simplified method (1) If a computer system and the appropriate software are NOT available, the annual skin dose rate due to noble gases in gaseous effluents discharged from the site to UNRESTRICTED AREAS may be calculated per equation 13G.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 165 of 321 Level 3 - Information ANNUAL SKIN DOSE RATE DUE TO NOBLE GASES IN GAS RELEASE, r (SIMPLIFIED METHOD)

Dsr = [ ( x/Q ) / ( Ksf ) ] [ Lavg + ( 1.1 ) ( Mavg ) ] Qir Eq. 13G1

Where, x/Q = The highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

All releases are considered long-term releases2, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose rate calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6) for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3)

The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3)

Ksf = A constant, actually a safety factor, which is the ratio of the CCNPP annual skin dose rate limit to the annual skin dose rate limit of Control 3.11.2.1, (unitless)

The safety factor chosen shall be less than or equal to 1.00. This ensures the annual skin dose rate is always less than or equal to the annual skin dose rate limit of Control 3.11.2.1.

A safety factor of 1.00 will yield an annual skin dose rate which corresponds to the annual skin dose rate limit of Control 3.11.2.1.

A safety factor of 0.500 will yield an annual skin dose rate which corresponds to one-half the annual skin dose rate limit of Control 3.11.2.1.

It is recommended that a safety factor of 1.0 be used for calculating the annual skin dose rate, however, other values--not to exceed 1.00--may be used as directed by Management.

The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive gaseous release permits. This administrative control is designed to minimize the possibility of violating Control 3.11.2.1 when simplifying assumptions are used.

The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

This safety factor has been included in equation 13G to account for any potential nonconservatism associated with applying the empirically derived skin beta dose factor, Lavg, to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a skin beta dose factor greater than Lavg are present in a gaseous release.

1 Equation 13G has been derived from NUREG-0133, 5.2.1, and Regulatory Guide 1.109 (Appendix B, Equation B-9 and Section C.2.f).

2 NUREG-0133, 3.3 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 166 of 321 Level 3 - Information Lavg = The empirically derived, site specific, average, skin dose factor due to beta emissions from TYPICAL GASEOUS EFFLUENTS (mrem/yr per microcurie/cubic meter)

A site-specific, average, beta skin dose factor for TYPICAL GASEOUS EFFLUENTS has been calculated from historical data.

The calculation of this site-specific, average, beta skin dose factor is presented on Attachment 11.

Refer to the table on Attachment 11 for the current value for the empirically derived, site specific, average beta skin dose factor.

Mavg = The empirically derived, site specific, average, air dose factor due to gamma emissions from TYPICAL GASEOUS EFFLUENTS (mrad/yr per microcurie/cubic meter)

A site-specific, average, gamma air dose factor for TYPICAL GASEOUS EFFLUENTS has been calculated from historical data.

The calculation of this site-specific, average, gamma air dose factor is presented on Attachment 11.

Refer to the table on Attachment 11 for the current value for the empirically derived, site specific, average gamma air dose factor.

1.1 = The conversion constant, 1.1 mrem/mrad, represents the skin dose (1.1 mrem) equivalent to air dose (1.0 mrad), and is used to convert air dose to skin dose.

Qir = The release rate of noble gas radionuclide, i, in (simultaneous) release, r (microcuries/second)

This value shall be calculated per equation 9G.

INSTANTANEOUS RELEASE RATE OF NOBLE GAS NUCLIDE i IN GASEOUS RELEASE r Qir = ( Air ) ( Fr ) ( c' ) Eq. 9G Air = The specific activity of noble gas radionuclide, i, in (simultaneous) release, r (microcuries/cubic centimeter)

Fr = The discharge flow rate for (simultaneous) release, r (cubic meters per second)

If the discharge flow rate is unknown (for example, the release has not been conducted), the Maximum Discharge Flow Rate listed on Attachments 7 or 8 may be used to calculate the annual skin dose rate.

Whenever possible, the actual discharge flow rate determined from actual release conditions (for example, initial pressure, volume, and temperature of a WGDT along with final pressure and temperature) shall be used in equation 9G.

Additional guidance for calculating discharge flow rates may be contained in approved Chemistry procedures.

c' = A conversion constant (1E6 cubic centimeters per cubic meter)

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 167 of 321 Level 3 - Information e) Radiation monitoring system algorithms (1) The plant vent stack radiation monitoring systems display values which are proportional to the annual skin dose rate due to noble gases emanating from the plant vent stacks.

(2) The values displayed by the plant vent stack radiation monitoring systems are not used for the purpose of effluent accountability per se, but the values displayed can provide a gross approximation of annual skin dose rate (see Control 3.3.3.9).

(3) The Westinghouse Main Vent Stack Noble Gas Monitor, 1/2-RE-5415, is an analog system and does not employ instrument algorithm to determine noble release rates.

(a) It is possible to approximate the noble gas release rates for the Unit 1 and Unit 2 main vents based on output from 1/2-RI-5415.

(b) These calculations are described elsewhere in the ODCM. (See equation 4G in the section Calculating the Fixed Setpoint for 1/2-RI-5415.)

(4) The WRNGM, 1/2-RE-5416A, is a digital radiation monitoring system which employs an instrument algorithm to determine noble release rates (microcuries per second).

(a) It is possible to approximate the noble gas release rates for the Unit 1 and Unit 2 main vents based on output from 1/2-RIC-5415.

(b) These calculations are described elsewhere in the ODCM. (See equation 1G in the section Calculating the Fixed High-High Alarm Setpoint for 1/2-RIC-5415.)

(5) The instrument algorithms and the (data base) values accessed by the instrument algorithms are documented in the CCNPP Alarm Manual.

f) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective ACTIONS are initiated as described below.

7. Corrective actions a) Chemistry surveillance procedures shall contain/and or reference administrative and/or Control limits for annual skin dose rate for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Control 3.11.2.1 for actions to be taken in the event the calculated annual skin dose rate exceeds 3000 mr/yr.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 168 of 321 Level 3 - Information ANNUAL ORGAN DOSE RATES DUE TO IODINES AND PARTICULATES IN GASEOUS EFFLUENTS

1. Introduction a) 10 CFR 20.1301 specifies dose rate limits associated with the release of radioactive materials to UNRESTRICTED AREAS.

b) Radiological effluent controls were originally established to implement the requirements of 10 CFR 20.1301. The 10 CFR 50 Appendix I, Design Objectives for ALARA Radioactive Effluents, upon which these calculations are based, are more restrictive than the public dose limits of 10 CFR 20.1301.

c) These radiological effluent controls are described below.

2. Radiological Effluent Controls a) The annual organ dose rates, due to iodines and particulates in gaseous waste discharged to UNRESTRICTED AREAS, shall be less than 1500 mr/yr (per Control 3.11.2.1).

b) The routine surveillances which are performed to verify compliance with this radiological effluent controls are described below.

3. Surveillance Requirements a) The Chemistry sampling and analysis procedure(s) shall describe the CCNPP radioactive gaseous waste sampling and analysis program (required by Control 4.11.2.1.2).

b) The results of the radioactive gaseous waste sampling and analysis program are used to calculate the annual organ dose rates due to iodines and particulates in gaseous effluents.

c) The plant group(s) responsible for performing the required surveillances are identified below.

4. Responsible Plant Organization(s) a) The Chemistry is responsible for calculating the annual organ dose rates due to iodines and particulates in gaseous effluents.

b) The Chemistry calculates the annual organ dose rates whenever the appropriate initiating conditions are present.

c) These initiating conditions are contained in the following section.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 169 of 321 Level 3 - Information

5. Initiating Conditions a) The annual organ dose rate--for each organ and at the SITE BOUNDARY--due to iodines and particulates in gaseous effluents is calculated at least weekly1 for CONTINUOUS discharges from plant vent stacks.

b) The annual organ dose rate--for each organ and at the SITE BOUNDARY--due to iodines and particulates in gaseous effluents is calculated for each discharge of combustion products resulting from the burning of contaminated oil.

c) The annual organ dose rate--for each organ and at the SITE BOUNDARY--due to iodines and particulates in gaseous effluents is calculated for each ABNORMAL AND/OR UNANTICIPATED RADIOACTIVE GAS RELEASE 2.

d) Whenever the correct initiating conditions are present, the annual organ dose rates shall be calculated as described below.

6. Calculation Methodology a) The annual organ dose rate, at the SITE BOUNDARY, due to iodine and particulate radionuclides in gaseous effluents released to UNRESTRICTED AREAS shall be calculated per equation 14G.3 ANNUAL ORGAN, o , DOSE RATE DUE TO IODINES AND PARTICULATES IN ALL SIMULTANEOUS GASEOUS RELEASES, r FROM THE SITE, 0 Do0 = Dor Eq. 14G Do0 = The site-boundary annual organ dose rate due to iodine and particulate radionuclides in all gaseous effluents discharged simultaneously from the site (Unit 0)

Dor = The site-boundary annual organ dose rate due to iodine and particulate radionuclides in release, r Sum for all releases, r, which are discharged simultaneously.

An example of a SIMULTANEOUS RELEASE would include the release of iodines and particulate radionuclides from the Unit 1 plant vent stack while also discharging iodines and particulate radionuclides from the Unit 2 plant vent stack.

1 The frequency is controlled by the implementing procedure and is based on plant conditions. Under no conditions shall the frequency be less than once per month (Control 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2).

2 See the definition of ABNORMAL/UNANTICIPATED GAS RELEASE in the DEFINITIONS section of the ODCM.

3 The alarm and fixed setpoints ... shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Control 3.3.3.9).

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 170 of 321 Level 3 - Information An example of a SIMULTANEOUS RELEASE would include the release of iodine and particulate radionuclides from the Unit 1 plant vent stack while also discharging a waste gas decay tank.

Calculate the values of Dor for each SIMULTANEOUS RELEASE as shown below.

b) At CCNPP, two methods exist for calculating Dor (that is, the annual organ dose rates due to iodine and particulate radionuclides in gaseous effluents released to UNRESTRICTED AREAS).

(1) The rigorous method shall be used IF a computer system and the appropriate software are available.

(2) The simplified method may be used IF a computer system and the appropriate software are NOT available.

(3) These methods, as well as additional supporting information, are presented in the following sections.

c) Rigorous Method (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropriate software are available.

(2) If a computer system and the appropriate software are available, the annual organ dose rates due to iodines and particulates in gaseous effluents released to an UNRESTRICTED AREA shall be calculated per equation 15G.

ANNUAL ORGAN, o, DOSE RATE DUE TO IODINES AND PARTICULATES IN GASEOUS RELEASE, r (RIGOROUS METHOD)

Dor = ( x/Q ) ( Pi ) ( Qir ) Eq. 15G1

Where, x/Q = The highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

All releases are considered long-term releases2, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose rate calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6 for purposes of routine, long-term concentrations (UFSAR, 2.3.6.3).

The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (UFSAR, 2.3.6.3).

1 Equation 15G has been derived from NUREG-0133, 5.2.1.

2 NUREG-0133, 3.3 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 171 of 321 Level 3 - Information Pi = The maximum organ inhalation pathway dose parameter for iodine and particulate radionuclides, i, for the most restrictive (that is, child) age group (mrem/year per microcurie/cubic meter)

The inhalation pathway dose parameters have been obtained per NUREG-0133, 5.2.1.1.

The pathway dose factor specified in NUREG-0133, 5.2.1.b, specifies calculating the exposure to the INFANT age group, where the exposure is due to a combination of three separate pathways.

1) Inhalation,
2) Ground plane, and
3) Food.

The latest NRC guidance has deleted the requirement to include the ground plane and food dose contributions when calculating maximum organ doses, therefore no pathway dose factors are calculated for the ground plane or food pathways.

The latest NRC guidance has changed the critical receptor age group from infant to child.

The child, inhalation pathway dose parameters for various radionuclides, sorted by critical organ, are tabulated in Attachment 12.

It should be noted that the dose parameters, Pi, (listed in Attachment 12) calculated per NUREG-0133, section 5.2.1.1 and the latest NRC guidance are numerically equal to the Inhalation Pathway Factors, Ri, calculated per NUREG-0133, section 5.3.1.1. As a result the ODCM does not contain two separate tables for values of Pi and Ri.

Qir = The release rate of iodine or particulate radionuclide, i, in (simultaneous) gaseous release, r (microcuries/second).

Calculate the values of Qir for each SIMULTANEOUS RELEASE per equation 9G.

INSTANTANEOUS RELEASE RATE OF IODINE OR PARTICULATE NUCLIDE i IN GASEOUS RELEASE r Qir = ( Air ) ( Fr ) ( c' ) Eq. 9G Air = The specific activity of iodine or particulate radionuclide, i, in (simultaneous) release, r (microcuries/cubic centimeter)

Fr = The discharge flow rate for (simultaneous) release, r (cubic meters per second)

If the discharge flow rate is unknown (for example, the release has not been conducted), the Maximum Discharge Flow Rate listed on Attachments 7 or 8 may be used to calculate the annual organ dose rate.

Additional guidance for calculating discharge flow rates may be contained in approved Chemistry procedures.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 172 of 321 Level 3 - Information c' = A conversion constant (1E6 cubic centimeters per cubic meter) d) Simplified method (1) If a computer system and the appropriate software are NOT available, the annual organ dose rate due to iodines and particulates in gaseous effluents discharged from the site to UNRESTRICTED AREAS may be calculated per equation 16G.

ANNUAL ORGAN, o, DOSE RATE DUE TO IODINES AND PARTICULATES IN GASEOUS RELEASE, r (SIMPLIFIED METHOD)

Dor = ( 1/ Ksf ) ( x/Q ) ( Pmax ) Qir Eq. 16G1

Where, Ksf = A constant, actually a safety factor, which is the ratio of the CCNPP organ dose rate limit to the organ dose rate limit of Control 3.11.2.1, (unitless)

The safety factor chosen shall be less than or equal to 1.00. This ensures the organ dose rate is always less than or equal to the organ dose rate limit of Control 3.11.2.1.

A safety factor of 1.00 will yield an organ dose rate which corresponds to the organ dose rate limit of Control 3.11.2.1.

A safety factor of 0.500 will yield an organ dose which corresponds to one-half the organ dose rate limit of Control 3.11.2.1.

It is recommended that a safety factor of 1.0 be used for calculating the organ dose rate, however, other values--not to exceed 1.00--may be used as directed by Management.

The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive gaseous release permits. This administrative control is designed to minimize the possibility of violating Control 3.11.2.1 when simplifying assumptions are used.

The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

This safety factor has been included in equation 16G to account for any potential nonconservatism associated with applying the dose parameter, Pmax, to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a dose parameter greater than Pmax are present in a gaseous release.

x/Q = The highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter) 1 Equation 16G has been derived from NUREG-0133, 5.2.1.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 173 of 321 Level 3 - Information All releases are considered long-term releases1, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose rate calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6 for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3).

The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3).

Pmax = The most restrictive dose parameter which would be reasonably anticipated for the inhalation pathway, child age group, thyroid organ, and I-131 radionuclide (mrem/year per microcurie/cubic meter)

The inhalation pathway dose parameters have been obtained per NUREG-0133, 5.2.1.1.

The pathway dose factor specified in NUREG-0133, 5.2.1.b, specifies calculating the exposure to the INFANT age group, where the exposure is due to a combination of three separate pathways.

1) Inhalation,
2) Ground plane, and
3) Food.

The latest NRC guidance has deleted the requirement to include the ground plane and food dose contributions when calculating maximum organ doses, therefore no pathway dose factors are calculated for the ground plane or food pathways.

The latest NRC guidance has changed the critical receptor age group from infant to child.

The child, inhalation pathway dose parameters for various radionuclides, sorted by critical organ, are tabulated in Attachment 12.

It should be noted that the dose parameters, Pi, (listed in Attachment 12) calculated per NUREG-0133, section 5.2.1.1 and the latest NRC guidance are numerically equal to the Inhalation Pathway Factors, Ri, calculated per NUREG-0133, section 5.3.1.1. As a result the ODCM does not contain two separate tables for values of Pi and Ri.

Qir = The release rate of iodine or particulate radionuclide, i, in (simultaneous) gaseous release, r (microcuries/second).

Calculate the values of Qir for each SIMULTANEOUS RELEASE per equation 9G.

1 NUREG-0133, 3.3 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 174 of 321 Level 3 - Information INSTANTANEOUS RELEASE RATE OF IODINE OR PARTICULATE NUCLIDE i IN GASEOUS RELEASE r

Qir = ( Air ) ( Fr ) ( c' ) Eq. 9G Air = The specific activity of iodine or particulate radionuclide, i, in (simultaneous) release, r (microcuries/cubic centimeter)

Fr = The discharge flow rate for (simultaneous) release, r (cubic meters per second)

If the discharge flow rate is unknown (for example, the release has not been conducted), the Maximum Discharge Flow Rate listed on Attachments 7 or 8 may be used to calculate the annual organ dose rate.

Additional guidance for calculating discharge flow rates may be contained in approved Chemistry procedures.

c' = A conversion constant (1E6 cubic centimeters per cubic meter) e) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective actions are initiated as described below.

7. Corrective actions a) Chemistry surveillance procedures shall contain/and/or reference administrative and/or Control limits for annual organ dose rates for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Control 3.11.2.1 for actions to be taken in the event the calculated annual organ dose rate to any organ exceeds 1500 mr/yr.

CUMULATIVE GAMMA AIR DOSES DUE TO NOBLE GASES IN GASEOUS EFFLUENTS

1. Introduction a) Appendix I to 10 CFR 50 specifies cumulative gamma air dose limits associated with the release of radioactive materials to UNRESTRICTED AREAS.

b) Radiological effluent controls have been established to implement the requirements of 10 CFR 50, Appendix I.

c) These radiological effluent controls are described below.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 175 of 321 Level 3 - Information

2. Radiological Effluent Controls a) The cumulative gamma air dose, due to noble gases in gaseous effluents released to UNRESTRICTED AREAS, shall be less than 10 mrads in any calendar quarter, and shall be less than 20 mrads in any calendar year (per Control 3.11.2.2) b) The routine surveillances which are performed to verify compliance with these radiological effluent controls are described below.
3. Surveillance Requirement(s) a) The cumulative gamma air doses, for the current calendar month, the calendar quarter, and the current calendar year, due to noble gases in gaseous effluents, shall be determined at least once every 31 days (Control 4.11.2.2).

b) The plant group(s) responsible for performing the required surveillance(s) are identified below.

4. Responsible Plant Organizations a) The Chemistry is responsible for calculating the cumulative gamma air doses for the current calendar quarter and the current calendar year.

b) The Chemistry calculates the cumulative gamma air doses whenever the appropriate initiating conditions are present c) These initiating conditions are contained in the following section.

5. Initiating Conditions a) The cumulative gamma air doses due to noble gases in gaseous effluents shall be determined at least once per 31 days (Control 4.11.2.2).

b) The cumulative gamma air doses due to noble gases in gaseous effluents shall be calculated for each release of a WGDT.

c) The cumulative gamma air doses due to noble gases in gaseous effluents shall be calculated for each vent of a containment building.

d) The cumulative gamma air doses due to noble gases in gaseous effluents shall be calculated for each PURGE of a containment building.

e) The cumulative gamma air doses due to noble gases in gaseous effluents shall be calculated at least weekly1 for CONTINUOUS discharges from plant vent stacks.

1 The frequency is controlled by the implementing procedure, and is based on plant conditions. Under no conditions shall the frequency be less than once per month (Control 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2).

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 176 of 321 Level 3 - Information f) The cumulative gamma air doses due to noble gases in gaseous effluents shall be calculated for each discharge of combustion products resulting from the burning of contaminated oil.

g) The cumulative gamma air doses due to noble gases in gaseous effluents shall be calculated for each ABNORMAL AND/OR UNANTICIPATED RADIOACTIVE GAS RELEASE1.

h) Whenever the correct initiating conditions are present, the cumulative gamma air doses shall be calculated as described below.

6. Calculation Methodology a) The cumulative gamma air dose at the SITE BOUNDARY (for example, for the current calendar month, current calendar quarter, current calendar year, or previous 92 days) due to noble gases in gaseous effluents shall be calculated using the following equation2:

1 The criteria used to define ABNORMAL AND UNANTICIPATED GAS RELEASES may be found in the implementing procedures.

2 The alarm and fixed setpoints ... shall be determined and adjusted in accordance with the methodology and parameters of the ODCM. (Control 3.3.3.9).

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 177 of 321 Level 3 - Information CUMULATIVE GAMMA, g, AIR DOSE FOR ALL GASEOUS RELEASES, r, DISCHARGED DURING TIME INTERVAL, t Dgt = Dgr Eq. 17G

Where, Dgt = The cumulative gamma air dose (mrad) at the SITE BOUNDARY due to noble gas radionuclides contained in all gaseous radwaste discharged from the site during the time interval, t Dgr = The cumulative gamma air dose (mrad) at the SITE BOUNDARY due to noble gas radionuclides contained in gaseous radwaste release, r, discharged from the site during the time interval of interest Calculate the values of Dgr for each gaseous release as described below.

b) At CCNPP, two methods exist for calculating Dgr (that is, the gamma air dose at the SITE BOUNDARY due to noble gas radionuclides contained in a gaseous radwaste release, r, discharged from the site during a specified time interval).

(1) The rigorous method shall be used IF a computer system and the appropriate software are available.

(2) The simplified method may be used IF a computer system and the appropriate software are NOT available.

(3) These methods, as well as additional supporting information, are presented in the following sections.

c) rigorous method (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropriate software are available.

(2) If a computer system and the appropriate software are available, the gamma air dose due to noble gases in gaseous effluents released to UNRESTRICTED AREAS shall be calculated per equation 18G.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 178 of 321 Level 3 - Information GAMMA AIR DOSE DUE TO NOBLE GASES IN GAS RELEASE, r (RIGOROUS EQUATION)

Dgr = ( 3.17E-8 ) ( x/Q ) [ ( Mi ) ( Q'ir ) ] Eq. 18G1

Where, 3.17E-8 = The conversion constant, 3.17E-8, represents the inverse of the number of seconds in a year.

x/Q = The highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

All releases are considered long-term releases2, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6 for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3).

The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3).

Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide, i (mrad/yr per microcurie/cubic meter)

The gamma air dose factors have been obtained from Regulatory Guide 1.109, Appendix B, Table B-1.

The gamma air dose factors for various noble gas radionuclides are tabulated in Attachment 10.

Q'ir = The total (time averaged) activity of noble gas radionuclide, i, in gaseous release, r (microcuries).

At CCNPP, all releases are considered long term releases.

Calculate the values of Qir for each release per equation 19G.

1 Equation 18G has been derived from NUREG-0133, 5.3.1..

2 NUREG-0133, 3.3 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 179 of 321 Level 3 - Information TOTAL (TIME AVERAGED) ACTIVITY OF NOBLE GAS NUCLIDE i IN GASEOUS RELEASE r Q'ir = ( Air ) ( Fr ) ( tlr ) ( c' ) Eq. 19G Air = The specific activity of noble gas radionuclide, i, in release, r, discharged during the time interval of interest (microcuries/cubic centimeter)

Fr = The discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second)

If the discharge flow rate is unknown (for example, the gaseous radwaste has not been released), the Maximum Discharge Flow Rate listed on Attachments 7 or 8 may be used to calculate the average activity for nuclide i.

Whenever possible, the actual discharge flow rate determined from actual release conditions (for example, initial pressure, volume, and temperature of a WGDT along with final pressure and temperature) shall be used in equation 19G.

Additional guidance for calculating discharge flow rates may be contained in approved Chemistry procedures.

tlr = The duration of the gaseous radwaste release (seconds) c' = A conversion constant, 1E6 cubic centimeters per cubic meter, which represents the number of cubic centimeters per cubic meter.

(3) In the event a computer system is unavailable, a simplified equation may be used to calculate the gamma air dose due to noble gases in gaseous effluents released to UNRESTRICTED AREAS.

(4) The simplified method is presented below.

d) Simplified method (1) If a computer system and appropriate software are NOT available to perform the rigorous gamma air dose calculation described in the previous section, the gamma air dose, due to noble gas radionuclides, in any single release of waste gases discharged to UNRESTRICTED AREAS may be calculated per equation 20G.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 180 of 321 Level 3 - Information GAMMA AIR DOSE DUE TO NOBLE GASES IN GAS RELEASE, r (SIMPLIFIED EQUATION)

Dgr = [ ( 3.17E-8 ) ( x/Q ) ( Mavg ) / Ksf ] Q'ir Eq. 20G1 3.17E-8 = The conversion constant, 3.17E-8, represents the inverse of the number of seconds in a year.

x/Q = The highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

All releases are considered long-term releases2, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6) for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3).

The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3).

Mavg = The empirically derived, site specific, average gamma air dose factor for each identified noble gas radionuclide, i (mrad/yr per microcurie/cubic meter)

A site-specific, average, gamma air dose factor has been calculated from historical data.

The calculation of this site-specific, average, gamma air dose factor is presented on Attachment 11.

Ksf = A constant, actually a safety factor, which is the ratio of the CCNPP gamma air dose limit to the gamma air dose limit of Control 3.11.2.2, (unitless)

The safety factor chosen shall be less than or equal to 1.00. This ensures the gamma air dose is always less than or equal to the gamma air dose limit of Control 3.11.2.2.

A safety factor of 1.00 will yield a gamma air dose which corresponds to the gamma air dose limit of Control 3.11.2.2.

A safety factor of 0.500 will yield a gamma air dose which corresponds to one-half the gamma air dose limit of Control 3.11.2.2.

It is recommended that a safety factor of 1.0 be used for calculating the gamma air dose, however, other values--not to exceed 1.00--may be used as directed by Management.

The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive gaseous release permits. This administrative control is designed to minimize the possibility of violating Control 3.11.2.2 when simplifying assumptions are used.

1 Equation 20G has been derived from NUREG-0133, 5.3.1.

2 NUREG-0133, 3.3 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 181 of 321 Level 3 - Information The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

This safety factor has been included in equation 20G to account for any potential nonconservatism associated with applying the empirically derived gamma air dose factor, Mavg, to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a gamma air dose factor greater than Mavg are present in a gaseous release.

Q'ir = The total (time averaged) activity of noble gas radionuclide, i, in gaseous release, r (microcuries)

At CCNPP, all releases are considered long term releases.

Calculate the values of Qir for each release per equation 19G.

TOTAL (TIME AVERAGED) ACTIVITY OF NOBLE GAS NUCLIDE i IN GASEOUS RELEASE r Q'ir = ( Air ) ( Fr ) ( tlr ) ( c' ) Eq. 19G Air = The specific activity of noble gas radionuclide, i, in release, r, discharged during the time interval of interest (microcuries/cubic centimeter).

Fr = The discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second).

If the discharge flow rate is unknown (for example, the gaseous radwaste has not been released), the Maximum Discharge Flow Rate listed on Attachments 7 or 8 may be used to calculate the average activity for nuclide i.

Additional guidance for calculating discharge flow rates may be contained in approved Chemistry procedures.

tlr = The duration of the gaseous radwaste release (seconds).

c' = A conversion constant, 1E6 cubic centimeters per cubic meter, which represents the number of cubic centimeters per cubic meter.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 182 of 321 Level 3 - Information e) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective actions are initiated as described below.

7. Corrective actions a) Chemistry surveillance procedures shall contain/and or reference administrative and/or Control limits for quarterly and yearly gamma air doses for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Control 3.11.2.2 for actions to be taken in the event the calculated cumulative gamma air doses exceed 10 mrads per calendar quarter or 20 mrads per calendar year.

CUMULATIVE BETA AIR DOSES DUE TO NOBLE GASES IN GASEOUS EFFLUENTS

1. Introduction a) Appendix I to 10 CFR 50 specifies cumulative beta air dose limits associated with the release of radioactive materials to UNRESTRICTED AREAS.

b) Radiological effluent controls have been established to implement the requirements of 10 CFR 50, Appendix I.

c) These radiological effluent controls are described below.

2. Radiological Effluent Controls a) The cumulative beta air dose, due to noble gases in gaseous effluents released to UNRESTRICTED AREAS, shall be less than 20 mrads in any calendar quarter, and shall be less than 40 mrads in any calendar year (per Control 3.11.2.2) b) The routine surveillances which are performed to verify compliance with these radiological effluent controls are described below.
3. Surveillance Requirement(s) a) The cumulative beta air doses, for the current calendar quarter and the current calendar year, due to noble gases in gaseous effluents, shall be determined at least once every 31 days (Control 4.11.2.2).

b) The plant group(s) responsible for performing the required surveillance(s) are identified below.

4. Responsible Plant Organizations a) The Chemistry is responsible for calculating the cumulative beta air doses for the current calendar quarter and the current calendar year.

b) The Chemistry calculates the cumulative beta air doses whenever the appropriate initiating conditions are present December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 183 of 321 Level 3 - Information c) These initiating conditions are contained in the following section.

5. Initiating Conditions a) The cumulative beta air doses due to noble gases in gaseous effluents shall be determined at least once per 31 days (Control 4.11.2.2).

b) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for each release of a WGDT.

c) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for each vent of a containment building.

d) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for each PURGE of a containment building.

e) The cumulative beta air doses due to noble gases in gaseous effluents are calculated at least weekly1 for CONTINUOUS discharges from plant vent stacks.

f) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for each discharge of combustion products resulting from the burning of contaminated oil.

g) The cumulative beta air doses due to noble gases in gaseous effluents are calculated for each ABNORMAL AND/OR UNANTICIPATED RADIOACTIVE GAS RELEASE.

h) Whenever the correct initiating conditions are present, the cumulative beta air doses shall be calculated as described below.

6. Calculation Methodology a) The cumulative beta air doses (for example, for the current calendar month, current calendar quarter, current calendar year, or previous 92 days) due to noble gases in gaseous effluents shall be calculated per equation 21G.

1 The frequency is controlled by the implementing procedure, and is based on plant conditions. Under no conditions shall the frequency be less than once per month (Controls 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2).

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 184 of 321 Level 3 - Information CUMULATIVE BETA AIR DOSE FOR ALL GASEOUS RELEASES, r, DISCHARGED DURING TIME INTERVAL, t Dt = Dr Eq. 21G

Where, Dt = The cumulative beta air dose (mrad) at the SITE BOUNDARY due to noble gas radionuclides contained in all gaseous radwaste discharged from the site during the time interval, t Dr = The beta air dose (mrad) due to noble gas radionuclides contained in gaseous radwaste release, r, discharged from the site during the time interval of interest Calculate the values of Dr for each gaseous release as described below.

b) At CCNPP, two methods exist for calculating Dr (the beta air dose at the SITE BOUNDARY due to noble gas radionuclides contained in a gaseous radwaste release, r, discharged from the site).

(1) The rigorous method shall be used IF a computer system and the appropriate software are available.

(2) The simplified method may be used IF a computer system and the appropriate software are NOT available.

(3) These methods, as well as additional supporting information, are presented in the following sections.

c) Rigorous method (1) Solution of the following equation may prove too rigorous for routine use unless a computer system and appropriate software are available.

(2) If a computer system and the appropriate software are available, the cumulative beta air dose due to noble gases in gaseous effluents released to UNRESTRICTED AREAS shall be calculated per equation 22G.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 185 of 321 Level 3 - Information BETA AIR DOSE DUE TO NOBLE GASES IN GAS RELEASE, r (RIGOROUS EQUATION)

Dr = ( 3.17E-8 ) ( x/Q ) [ ( Ni ) ( Q'ir ) ] Eq. 22G1

Where, Dr = The beta air dose due to noble gas radionuclides contained in gaseous radwaste release, r, discharged from the site during the time interval of interest 3.17E-8 = The conversion constant, 3.17E-8, represents the inverse of the number of seconds in a year.

x/Q = the highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

All releases are considered long-term releases2, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6 for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3).

The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3).

Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide, i (mrad/yr per microcurie/cubic meter)

The beta air dose factors have been obtained from Regulatory Guide 1.109, Appendix B, Table B-1.

The beta air dose factors for various noble gas radionuclides are tabulated in Attachment 10.

Q'ir = The total (time averaged) activity of noble gas radionuclide, i, in gaseous release, r (microcuries).

At CCNPP, all releases are considered long term releases.

Calculate the values of Qir for each release per equation 19G.

1 Equation 22G has been derived from NUREG-0133, 5.3.1.

2 NUREG-0133, 3.3 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 186 of 321 Level 3 - Information TOTAL (TIME AVERAGED) ACTIVITY OF NOBLE GAS NUCLIDE i IN GASEOUS RELEASE r Q'ir = ( Air ) ( Fr ) ( tlr ) ( c' ) Eq. 19G Air = The specific activity of noble gas radionuclide, i, in release, r, discharged during the time interval of interest (microcuries/cubic centimeter).

Fr = The discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second).

If the discharge flow rate is unknown (for example, the gaseous radwaste has not been released), the Maximum Discharge Flow Rate listed on Attachments 7 or 8 may be used to calculate the average activity for nuclide i.

Additional guidance for calculating discharge flow rates may be contained in approved Chemistry procedures.

tlr = The duration of the gaseous radwaste release (seconds).

c' = A conversion constant, 1E6 cubic centimeters per cubic meter.

(3) In the event a computer system is unavailable, a simplified equation may be used to calculate the gamma air dose due to noble gases in gaseous effluents released to UNRESTRICTED AREAS.

(4) The simplified method is presented below.

d) Simplified Method (1) If a computer system and the appropriate software are NOT available to perform the rigorous beta air dose calculation described in the previous section, the beta air dose resulting from a single release of waste gases discharged to UNRESTRICTED AREAS may be calculated per equation 23G.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 187 of 321 Level 3 - Information BETA AIR DOSE DUE TO NOBLE GASES IN GAS RELEASE, r (SIMPLIFIED EQUATION)

Dr = [ ( 3.17E-8 ) ( x/Q ) ( Navg ) / Ksf ] Q'ir Eq. 23G1 3.17E-8 = The conversion constant, 3.17E-8, represents the inverse of the number of seconds in a year.

x/Q = The highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA boundary (2.2E-6 seconds per cubic meter)

All releases are considered long-term releases2, and as such, the highest historical annual average dispersion factor, (x/Q), is used in the dose calculations.

The highest annual average dispersion factor (x/Q) is 2.2E-6 for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3).

The maximum annual average on-shore concentrations occur in the southeast sector at a distance of 1300 meters for purposes of routine, long-term concentrations (for example, routine noble gas releases) (UFSAR, 2.3.6.3).

Navg = The empirically derived, site specific, average beta air dose factor for each identified noble gas radionuclide, i (mrad/yr per microcurie/cubic meter)

A site-specific, average, beta air dose factor has been calculated from historical data.

The calculation of this site-specific, average, beta air dose factor is presented on Attachment 11.

Ksf = A constant, actually a safety factor, which is the ratio of the CCNPP beta air dose limit to the beta air dose limit of Control 3.11.2.2, (unitless)

The safety factor chosen shall be less than or equal to 1.00. This ensures the beta air dose is always less than or equal to the beta air dose limit of Control 3.11.2.2.

A safety factor of 1.00 will yield an organ dose which corresponds to the beta air dose limit of Control 3.11.2.2.

A safety factor of 0.500 will yield an beta air dose which corresponds to one-half the beta air dose limit of Control 3.11.2.2.

It is recommended that a safety factor of 1.0 be used for calculating the beta air dose, however, other values--not to exceed 1.00--may be used as directed by Management.

1 Equation 23G has been derived from NUREG-0133, 5.3.1.

2 NUREG-0133, 3.3 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 188 of 321 Level 3 - Information The particular value selected for the safety factor is somewhat arbitrary, however, a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive gaseous release permits. This administrative control is designed to minimize the possibility of violating Control 3.11.2.2 when simplifying assumptions are used.

The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

This safety factor has been included in equation 23G to account for any potential nonconservatism associated with applying the empirically derived beta air dose factor, Navg, to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a beta air dose factor greater than Navg are present in a gaseous release.

Q'ir = The total (time averaged) activity of noble gas radionuclide, i, in gaseous release, r (microcuries)

At CCNPP, all releases are considered long term releases.

Calculate the values of Qir for each release per equation 19G.

TOTAL (TIME AVERAGED) ACTIVITY OF NOBLE GAS NUCLIDE i IN GASEOUS RELEASE r Q'ir = ( Air ) ( Fr ) ( tlr ) ( c' ) Eq. 19G Air = The specific activity of noble gas radionuclide, i, in release, r, discharged during the time interval of interest (microcuries/cubic centimeter)

Fr = The discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second)

If the discharge flow rate is unknown (for example, the gaseous radwaste has not been released), the Maximum Discharge Flow Rate listed on Attachments 7 or 8 may be used to calculate the average activity for nuclide i.

Additional guidance for calculating discharge flow rates may be contained in approved Chemistry procedures.

tlr = The duration of the gaseous radwaste release (seconds).

c' = A conversion constant, 1E6 cubic centimeters per cubic meter.

e) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective actions are initiated as described below.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 189 of 321 Level 3 - Information

7. Corrective actions a) Chemistry surveillance procedures shall contain/and or reference administrative and/or Control limits for quarterly and yearly beta air doses for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Control 3.11.2.2 for actions to be taken in the event the calculated cumulative beta air doses exceed 20 mrads per calendar quarter or 40 mrads per calendar year.

CUMULATIVE ORGAN DOSES DUE TO IODINES AND PARTICULATES IN GASEOUS EFFLUENTS

1. Introduction a) Appendix I to 10 CFR 50 specifies cumulative organ dose limits associated with the release of radioactive materials to UNRESTRICTED AREAS.

b) Radiological effluent controls have been established to implement the requirements of 10 CFR 50, Appendix I.

c) These radiological effluent controls are described below.

2. Radiological Effluent Controls a) The cumulative organ dose due to iodines and particulates in gaseous effluents released to UNRESTRICTED AREAS shall be less than 15 mrems per calendar quarter, and shall be less than 30 mrems per calendar year (per Control 3.11.2.3).

b) The cumulative organ dose due to iodines and particulates in gaseous, contaminated oil combustion products released to UNRESTRICTED AREAS shall be less than 0.015 mrems per quarter, and shall be less than 0.030 mrems per year (per Control 3.11.2.3).

c) The routine surveillances which are performed to verify compliance with this radiological effluent controls are described below.

3. Surveillance Requirements a) The cumulative organ doses (due to iodines and particulates in gaseous waste discharged to UNRESTRICTED AREAS), for the current calendar month, the current calendar quarter, and the current calendar year, shall be determined at least once every 31 days per the ODCM (per Control 4.11.2.3).

b) The plant group(s) responsible for performing the required surveillances are identified below.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 190 of 321 Level 3 - Information

4. Responsible Plant Organizations a) Chemistry is responsible for implementing the surveillances required by Control 4.11.2.3.

b) Chemistry calculates the cumulative organ doses whenever the appropriate initiating conditions are present c) These initiating conditions are contained in the following section.

5. Initiating Conditions a) The cumulative organ dose--for each organ--shall be determined at least once per 31 days (Control 4.11.2.2).

b) The cumulative organ dose--for each organ--due to iodines and particulates in gaseous effluents shall be calculated at least weekly1 for CONTINUOUS discharges from plant vent stacks.

c) The cumulative organ dose--for each organ--due to iodines and particulates in gaseous effluents shall be calculated for each discharge of combustion products resulting from the burning of contaminated oil.

d) The cumulative organ dose--for each organ--due to iodines and particulates in gaseous effluents shall be calculated for each ABNORMAL AND/OR UNANTICIPATED RADIOACTIVE GAS RELEASE.

e) Whenever the correct initiating conditions are present, the annual cumulative organ doses shall be calculated as described below.

6. Calculation Methodology a) The cumulative organ doses (for the calendar month, calendar quarter, previous 92 days, and calendar year) due to iodines and particulates in gaseous waste discharged to UNRESTRICTED AREAS shall be calculated per equation 24G.

1 The frequency is controlled by the implementing procedure, and is based on plant conditions. Under no conditions shall the frequency be less than once per month (Controls 4.11.2.1.1 or 4.11.2.1.2, Table 4.11-2).

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 191 of 321 Level 3 - Information CUMULATIVE DOSE TO ORGAN, o, FROM ALL GASEOUS RELEASES, r, DISCHARGED DURING TIME INTERVAL, t Dot = Dor Eq. 24G

Where, Dot = the cumulative dose (mrad) to organ, o, at the SITE BOUNDARY, due to iodine and particulate radionuclides contained in gaseous waste discharged from the site during the time interval, t Dor = the dose (mrad) to organ, o, at the SITE BOUNDARY due to iodine and particulate radionuclides in gaseous release, r, discharged from the site during the time interval of interest Calculate the values of Dor for each gaseous release as described below.

b) At CCNPP, two methods exist for calculating Dor (the organ doses due to iodines and particulates resulting from any single release of radioactive gases to an UNRESTRICTED AREA).

(1) The rigorous method shall be used IF a computer system and the appropriate software are available.

(2) The simplified method may be used IF a computer system and the appropriate software are NOT available.

(3) These methods, as well as additional supporting information, are presented in the following sections.

c) Rigorous Method (1) Application of the following equation may prove too rigorous for routine use unless a computer system and the appropriate software are available.

(2) If a computer system and the appropriate software are available, the organ doses due to iodines and particulates contained in any single release of radioactive gases to UNRESTRICTED AREAS shall be calculated per equation 25G.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 192 of 321 Level 3 - Information DOSE TO ORGAN, o, DUE TO IODINES AND PARTICULATES IN GAS RELEASE, r (RIGOROUS EQUATION)

Dor = ( 3.17E-8 ) ( Wv ) ( Ripao ) ( Q'ir ) Eq. 25G1

Where, Dor = the dose (mrem) to organ, o, at the SITE BOUNDARY due to iodine and particulate radionuclides in gaseous release, r, discharged from the site during the time interval of interest 3.17E-8 = The conversion constant, 3.17E-8, represents the inverse of the number of seconds in a year.

Wv = The dispersion parameter for estimating the dose to an individual at the controlling location for long term releases, and may assume one of two values as described below Wv is x/Q for the inhalation pathway (2.2E-6 sec/cubic meter)

Wv is D/Q for the food and ground plane pathways (meters-2)

D/Q = The dispersion parameter at the controlling location for long term releases (meters-2)

The value for D/Q has been determined to be 8.63E-10 m-2 The grass-cow-milk pathway is the controlling pathway.

The controlling sector is the south-southwest sector.

The controlling location is at a distance of 4800 meters.3 Ripao = The dose factor for each identified iodine or particulate radionuclide, i, exposure pathway, p, 2

receptor age group, a, and organ, o (m mrem/year per microcuries/second or mrem/year per microcuries/cubic meter)

Dose factors have been derived for the following pathways:

1) Inhalation - see Attachment 12
2) Ground plane - see Attachment 12
3) Grass-cow-milk - see Attachment 12
4) Grass-cow-meat - see Attachment 12
5) Vegetation - see Attachment 12 The inhalation pathway dose factors were obtained using the formula from NUREG-0133, 5.3.1.1.

The ground plane dose factors were obtained using the formula from NUREG-0133, 5.3.1.2.

1 Equation 25G has been derived from NUREG-0133, 5.3.1.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 193 of 321 Level 3 - Information The grass-cow-milk pathway dose factors were obtained using the formula from NUREG-0133, 5.3.1.3.

The grass-cow-meat pathway dose factors were obtained using the formula from NUREG-0133, 5.3.1.4.

The vegetation pathway dose factors were obtained using the formula from NUREG-0133, 5.3.1.5.

Q'ir = The total (time averaged) activity of iodine or particulate radionuclide, i, in gaseous release, r, discharged during the specified time interval (microcuries)

At CCNPP, all releases are considered long term releases.

Calculate the values of Qir for each release per equation 19G.

TOTAL (TIME AVERAGED) ACTIVITY OF IODINE OR PARTICULATE NUCLIDE i IN GASEOUS RELEASE r Q'ir = ( Air ) ( Fr ) ( tlr ) ( c' ) Eq. 19G Air = The specific activity of iodine and particulate radionuclide, i, in release, r, discharged during the time interval of interest (microcuries/cubic centimeter)

Fr = The discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second)

If the discharge flow rate is unknown (for example, the gaseous radwaste has not been released), the Maximum Discharge Flow Rate listed on Attachments 7 or 8 may be used to calculate the average activity for nuclide i.

Additional guidance for calculating discharge flow rates may be contained in approved Chemistry procedures.

tlr = The duration of the gaseous radwaste release (seconds) c' = A conversion constant, 1E6 cubic centimeters per cubic meter (3) In the event a computer system and the appropriate software are unavailable, a simplified equation may be used to calculate the organ doses due to individual gaseous releases.

(4) The simplified method is presented below.

d) Simplified Method (1) If a computer system and appropriate software are NOT available to perform the rigorous organ dose calculations described in the previous section, the organ doses due to iodines and particulates in a single release of radioactive December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 194 of 321 Level 3 - Information gases discharged to an UNRESTRICTED AREA may be calculated per equation 26G.

DOSE TO ORGAN, o, FROM IODINES AND PARTICULATES IN GAS RELEASE, r (SIMPLIFIED EQUATION)

Dmaxor = [ ( 3.17E-8 ) ( Wv ) ( RI-131 ) / Ksf ] ( Q'ir ) Eq. 26G1 Dmaxor = The maximum dose to any organ, o, due to iodines and particulates contained in any single release, r, of radioactive gases to an UNRESTRICTED AREA 3.17E-8 = The conversion constant, 3.17E-8, represents the inverse of the number of seconds in a year.

D/Q = The dispersion parameter at the controlling location for long term releases (meters-2)

The value for D/Q has been determined to be 8.63E-10 m-2.

The grass-cow-milk pathway is the controlling pathway.

The controlling sector is the south-southwest sector.

The controlling location is at a distance of 4800 meters.3 RI-131 = The infant, thyroid, dose factor for I-131 via the grass-cow-milk pathway (m2 mrem/year per microcuries/second)

This value is 1.05E12 and it is listed on Attachment 12.

Ksf = A constant, actually a safety factor, which is the ratio of the CCNPP organ dose limit to the organ dose limit of Control 3.11.2.3, (unitless)

The safety factor chosen shall be less than or equal to 1.00. This ensures the organ dose is always less than or equal to the organ dose limit of Control 3.11.2.3.

A safety factor of 1.00 will yield an organ dose which corresponds to the organ dose limit of Control 3.11.2.3.

A safety factor of 0.500 will yield an organ dose which corresponds to one-half the organ dose limit of Control 3.11.2.3.

It is recommended that a safety factor of 1.0 be used for calculating the organ dose, however, other values--not to exceed 1.00--may be used as directed by Management.

The particular value selected for the safety factor is somewhat arbitrary, however a safety factor does provide plant personnel with a degree of administrative control over the use of simplified equations for generating radioactive gaseous release permits. This administrative control is designed to minimize the possibility of violating Control 3.11.2.3 when simplifying assumptions are used.

1 Equation 26G has been derived from NUREG-0133, 5.3.1.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 195 of 321 Level 3 - Information The use of a safety factor is consistent with the ALARA philosophy that licensees should make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to UNRESTRICTED AREAS, as low as is reasonably achievable.

This safety factor has been included in equation 26G to account for any potential nonconservatism associated with applying the infant, thyroid, grass-cow-milk dose factor, RI-131, to all radionuclides identified in the gaseous release. Such nonconservatism could conceivable be present whenever radionuclides having a pathway dose factor greater than RI-131 are present in a gaseous release.

Q'ir = The total (time averaged) activity of iodine or particulate radionuclide, i, in gaseous release, r (microcuries)

At CCNPP, all releases are considered long term releases.

This value shall be calculated per equation 19G.

TOTAL (TIME AVERAGED) ACTIVITY OF IODINE OR PARTICULATE NUCLIDE i IN GASEOUS RELEASE r Q'ir = ( Air ) ( Fr ) ( tlr ) ( c' ) Eq. 19G Air = The specific activity of iodine and particulate radionuclide, i, in release, r, discharged during the time interval of interest (microcuries/cubic centimeter)

Fr = The discharge flow rate for release, r, discharged during the time interval of interest (cubic meters per second)

If the discharge flow rate is unknown (for example, the gaseous radwaste has not been released), the Maximum Discharge Flow Rate listed on Attachments 7 or 8 may be used to calculate the average activity for nuclide i.

Additional guidance for calculating discharge flow rates may be contained in approved Chemistry procedures.

tlr = The duration of the gaseous radwaste release (seconds) c' = A conversion constant, 1E6 cubic centimeters per cubic meter e) Once the calculations above have been completed, the calculation results are compared to the applicable limits and corrective actions are initiated as described below.

7. Corrective actions a) Chemistry surveillance procedures shall contain/and or reference administrative and/or Control limits for cumulative organ dose for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 196 of 321 Level 3 - Information b) Refer to Control 3.11.2.3 for actions to be taken in the event the calculated cumulative gamma air doses exceed any of the radiological effluent controls listed above.

LIMITS FOR THE GASEOUS RADWASTE PROCESSING SYSTEM

1. Introduction a) 10 CFR 50.36a requires licensees to maintain and use the equipment installed in the gaseous waste processing system for the purpose of controlling effluents to the environment.

b) Radiological effluent controls have been established to implement the requirements of 10 CFR 50.36a.

c) These radiological effluent controls are described below.

2. Radiological effluent controls a) The GASEOUS RADWASTE PROCESSING SYSTEM and the VENTILATION EXHAUST PROCESSING SYSTEM shall be used to reduce radioactive materials in gaseous waste before their discharge when the gaseous effluent air dose, to areas at and beyond the SITE BOUNDARY, exceeds 1.20 mrads gamma radiation in a 92 day period (per Control 3.11.2.4).

b) The GASEOUS RADWASTE PROCESSING SYSTEM and the VENTILATION EXHAUST PROCESSING SYSTEM shall be used to reduce radioactive materials in gaseous waste before their discharge when the gaseous effluent air dose, to areas at and beyond the SITE BOUNDARY, exceeds 2.4 mrads beta radiation in a 92 day period (per Control 3.11.2.4).

c) The VENTILATION EXHAUST PROCESSING SYSTEM shall be used to reduce the quantity of radioactive materials in gaseous waste before their discharge when the calculated doses due to gaseous effluent releases, to areas at and beyond the SITE BOUNDARY exceeds 1.80 mrem to any organ in a 92 day period (per Control 3.11.2.4).

d) The routine surveillances which are performed to verify compliance with this radiological effluent controls are described below.

3. Surveillance Requirement(s) a) The cumulative gamma air dose, for the previous 92 days, due to noble gases in gaseous effluents, shall be determined at least once every 31 days (Control 4.11.2.2).

b) The plant group(s) responsible for performing the required surveillance(s) are identified below.

4. Responsible Plant Organizations December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 197 of 321 Level 3 - Information a) Chemistry is responsible for calculating the cumulative gamma air doses for the current calendar month, the previous 92 days, the current calendar quarter, and the current calendar year.

b) The cumulative gamma air dose for the previous 92 days is calculated whenever the appropriate initiating conditions are present c) These initiating conditions are contained in the following section.

5. Initiating conditions a) For a listing of initiating conditions associated with calculating gamma air doses, see Initiating Conditions in the section of the ODCM titled, Cumulative Gamma Air Doses Due To Noble Gases In Gaseous Effluents.

b) For a listing of initiating conditions associated with calculating beta air doses, see Initiating Conditions in the section of the ODCM titled, Cumulative Beta Air Doses Due To Noble Gases In Gaseous Effluents.

c) For a listing of initiating conditions associated with calculating cumulative organ doses, see Initiating Conditions in the section of the ODCM titled, Cumulative Organ Doses Due To Iodines And Particulates In Gaseous Effluents.

6. Calculation methodology a) Calculate the previous 92-day cumulative gamma air dose as described in the section Cumulative Gamma Air Doses Due To Noble Gases In Gaseous Effluents.

b) Calculate the previous 92-day cumulative beta air dose as described in the section Cumulative Beta Air Doses Due To Noble Gases In Gaseous Effluents.

c) Calculate the previous 92-day cumulative organ dose as described in the section Cumulative Organ Doses Due To Iodines And Particulates In Gaseous Effluents.

7. Corrective actions a) Chemistry surveillance procedures shall contain/and or reference administrative and/or Control limits for 92-day cumulative gamma, beta, or organ doses for gaseous effluents and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Control 3.11.2.4 for actions to be taken in the event the calculated 92-day cumulative gamma air, beta air, or organ doses exceed any of the radiological effluent controls listed above.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 198 of 321 Level 3 - Information LIMITS ON TOTAL ANNUAL DOSE -- GASES, LIQUIDS, AND URANIUM FUEL CYCLE SOURCES

1. Introduction a) 40 CFR 190 specifies annual dose limits for radionuclides released to the environment.

b) Radiological effluent controls have been established to implement the requirements of 40 CFR 190.

c) These radiological effluent controls are described below.

2. Radiological effluent controls a) The total body dose from exposure to the combination of liquid releases, gas releases, and uranium fuel cycle sources shall be less than 25 mrem for the current calendar year (per Control 3.11.4).

b) The organ dose (for the maximum exposed organ, not including the thyroid) from exposure to the combination of liquid releases, gas releases, and uranium fuel cycle sources shall be less than 25 mrem for the current calendar year (per Control 3.11.4).

c) The thyroid dose from exposure to the combination of liquid releases, gas releases, and uranium fuel cycle sources shall be less than 75 mrem for the current calendar year (per Control 3.11.4).

d) The routine surveillances which are performed to verify compliance with these radiological effluent controls are described below.

3. Surveillance Requirements a) The cumulative gamma air doses, for current calendar month, the current calendar quarter, and the current calendar year, due to noble gases in gaseous effluents, shall be determined at least once every 31 days (Control 4.11.2.2).

b) The cumulative organ doses (due to iodines and particulates in gaseous waste discharged to UNRESTRICTED AREAS), for the current calendar month, the current calendar quarter, and the current calendar year, shall be determined at least once every 31 days per the ODCM (per Control 4.11.2.3).

c) Cumulative total body dose to MEMBERS OF THE PUBLIC in UNRESTRICTED AREAS--for the current calendar month, the calendar quarter, and the current calendar year--shall be calculated at least once per 31 days (per Control 4.11.1.2).

d) Cumulative organ doses to MEMBERS OF THE PUBLIC in UNRESTRICTED AREAS--for the current calendar month, the current calendar quarter, and the current calendar year--shall be calculated at least once per 31 days (per Control 4.11.1.2).

e) The direct radiation dose to MEMBERS OF THE PUBLIC exposed to uranium fuel cycle sources (that is, reactor units and outside storage tanks) shall be determined IF THE APPROPRIATE INITIATING CONDITIONS ARE PRESENT.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 199 of 321 Level 3 - Information

4. Responsible Plant Organization(s) a) Chemistry is responsible for implementing the effluent surveillances required by Control 4.11.4.1.

b) Chemistry is responsible for ensuring implementation of the direct radiation surveillances required by Control 4.11.4.2.

c) IT SHOULD BE NOTED THAT NO SURVEILLANCES NEED BE PERFORMED UNLESS THE APPROPRIATE INITIATING CONDITIONS ARE PRESENT.

d) These initiating conditions are contained in the following section.

5. Initiating conditions a) The total dose from liquid releases, gas releases, and uranium fuel cycle sources shall be determined whenever the calculated doses from liquid effluents exceed any of the following (per Control 4.11.4.2):

(1) Six (6) mrem per quarter to the total body (2) Twelve (12) mrem per calendar year to the total body (3) Twenty (20) mrem per quarter to any organ (4) Forty (40) mrem per calendar year to any organ b) The total dose from liquid releases, gas releases, and uranium fuel cycle sources shall be determined whenever the calculated air doses from noble gasses in gaseous effluents exceed any of the following (per Control 4.11.4.2):

(1) Twenty (20) mrad gamma per quarter (2) Forty (40) mrad gamma per calendar year (3) Forty (40) mrad beta per quarter (4) Eighty (80) mrad beta per calendar year c) The total dose from liquid releases, gas releases, and uranium fuel cycle sources shall be determined whenever the calculated organ doses from iodines and particulates in gaseous effluents exceed any of the following (per Control 4.11.4.2):

(1) Thirty (30) mrem per quarter to any organ (2) Sixty (60) mrem per calendar year to any organ d) Whenever the correct initiating conditions are present, the total doses from liquid releases, gas releases, and uranium fuel cycle sources (for the calendar year) shall be calculated as shown below.

6. Calculation methodology a) The total body dose and the organ doses from liquid releases, gas releases, and uranium fuel cycle sources (for the calendar year) shall be calculated per equation 1T and 2T respectively.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 200 of 321 Level 3 - Information TOTAL, TOTAL BODY DOSE FROM LIQUID RELEASES, GAS RELEASES, AND URANIUM FUEL CYCLE SOURCES Dtball = DToL + Dgt + Dtank Eq. 1T TOTAL ORGAN DOSES FROM LIQUID RELEASES, GAS RELEASES, AND URANIUM FUEL CYCLE SOURCES Doall = DToL + Dot + Dtank Eq. 2T Dtball = The dose (mrem) to total body resulting from the combination of all gas releases, all liquid releases, and all uranium fuel cycle sources.

Doall = The dose (mrem) to organ, o, resulting from the combination of all gas releases, all liquid releases, and all uranium fuel cycle sources.

Separate values shall be calculated for each of the organs listed below:

1. Bone
2. Liver
3. Thyroid
4. Kidney
5. Lung
6. GI tract DToL = The cumulative dose (mrem) to organ, o, for all liquid releases discharged in a given time interval Calculate this value as specified by equation 8L.

Dgt = The site-boundary cumulative gamma air dose (mrad) due to noble gas radionuclides contained in all gaseous radwaste discharged from the site during the time interval, t Calculate this value as specified by equation 17G, except substitute Ki for Mi (see Attachment 10).

Dot = The site-boundary cumulative organ dose (mrem) resulting from the release of iodine and particulate radionuclides in gaseous releases from the site Calculate this value as specified by equation 24G.

Dtank = The calendar-year cumulative dose (mrem) to the maximum exposed MEMBER OF THE PUBLIC due to direct radiation from the reactor units and outside storage tanks This value shall be based on the results of direct radiation measurements from TLDs or continuous dose rate instruments placed near the SITE BOUNDARY (for example, from radiological environmental monitoring sites DR1-DR9 described on Attachment 13 and shown on Attachment 18).

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 201 of 321 Level 3 - Information Chemistry, and the Radiation Protection are responsible for determining this value.

b) Compare the calculated values to the radiological effluent controls (listed in this section), and if any of the radiological effluent controls have been exceeded, perform the appropriate corrective actions listed below.

7. Corrective actions a) Chemistry surveillance procedures shall contain/and or reference administrative and/or Control limits for total dose for liquid releases, gaseous releases, and uranium fuel cycle sources and shall specify corrective actions to be initiated when these limits are exceeded.

b) Refer to Control 3.11.4 for actions to be taken in the event the total dose exceeds any of the radiological effluent controls listed above.

c) If any of the radiological effluent controls have been exceeded, refer to 40 CFR 302, Appendix B, and verify the quantities of radioactive materials released are less than the values specified. [B375]

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 202 of 321 Level 3 - Information SPECIAL EXCEPTIONS AND ASSUMPTIONS FOR CALCULATION OF DOSES AND DOSE RATES

1. Camp Conoy a) Location (1) Camp Conoy is located within the SITE BOUNDARY.

(2) Camp Conoy is located in the SE sector.

(3) Camp Conoy is approximately 3000 feet from the plant.

b) Occupancy (1) Camp Conoy is frequently visited by MEMBERS OF THE PUBLIC.

(2) Maximum occupancy for MEMBERS OF THE PUBLIC at Camp Conoy is restricted to approximately 3380 hours0.0391 days <br />0.939 hours <br />0.00559 weeks <br />0.00129 months <br /> per year.

c) Meteorology (1) The highest historical annual average x/Q for Camp Conoy is 2.40E-6 seconds per cubic meter.

d) Dose calculation assumptions (1) Based on sections (b) and (c) above, any actual exposure to a MEMBER OF THE PUBLIC at Camp Conoy will be less than the calculated exposure for a MEMBER OF THE PUBLIC at the SITE BOUNDARY.

(2) No special considerations are required for addressing potential exposure at Camp Conoy.

2. Visitor's Center a) Location (1) The Visitor's Center is located within the SITE BOUNDARY.

(2) The Visitor's Center is located in the WNW sector.

(3) The Visitor's Center is approximately 1000 feet from the plant.

b) Occupancy (1) The Visitor's Center is frequently visited by MEMBERS OF THE PUBLIC.

(2) Maximum occupancy for MEMBERS OF THE PUBLIC at The Visitor's Center is restricted to daylight hours.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 203 of 321 Level 3 - Information c) Meteorology (1) The highest historical annual average x/Q for the Visitor's Center is 8.68E-6 seconds per cubic meter.

(2) The wind frequency for the WNW sector, based on 1983 meteorological data, is four percent (4%).

d) Dose calculation assumptions (1) Using a conservative basis of 10% wind frequency, and individual visiting the center for 330 hour0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br />s/year during the periods of worst case meteorological conditions would be most highly exposed.

(2) The dose calculated for the controlling SITE BOUNDARY is more conservative by a factor of 7.

(3) Based on sections (b) and (c) above, any actual exposure to a MEMBER OF THE PUBLIC at The Visitor's Center will be less than the calculated exposure for a MEMBER OF THE PUBLIC at the SITE BOUNDARY.

(4) No special considerations are required for addressing potential exposure at The Visitor's Center.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 204 of 321 Level 3 - Information RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM1

1. Introduction a) 10 CFR 50, Appendix I, Section IV.B.2 requires licensees to establish an environmental surveillance and monitoring program for the purpose of evaluating the relationship between quantities of radioactive material released in effluents and resultant radiation doses to individuals.

b) Radiological environmental controls have been established to implement the requirements of 10 CFR 50, Appendix I, Section IV.B.2.

c) These radiological environmental controls are described below.

2. Controls on the Radiological Environmental Monitoring Program (REMP) a) The REMP shall consist of environmental sample locations, analysis parameters, analysis frequencies, detection limits, and ACTION levels all of which conform to the requirements of Control 3.12.1. (See Attachment 13, 14, 15, 16, and 17).

b) The REMP shall maintain a map showing sample locations near the SITE BOUNDARY per Control 3.12.1. (See Attachment 18).

c) The REMP shall maintain a map showing sample locations within a 8 km. radius of the plant per Technical Specification 5.6.2. (See Attachment 19).

3. Surveillance Requirements a) Surveillances for direct radiation (1) Direct radiation dosimetry shall be collected from locations DR1-DR23 listed on Attachment 13.

(2) In the event any of the monitoring stations, DR1-DR23, described on Attachment 13 become unavailable, establish new monitoring stations (with new dosimetry) as described below:

(a) In lieu of any location DR1-DR9 described on Attachment 13, establish a new monitoring station in the same meteorological sector in the general area of the SITE BOUNDARY.

(b) In lieu of any location DR10-DR18 described on Attachment 13, establish a new monitoring station in the same meteorological sector in the 6-8 km range from the site.

1 This portion of the environmental monitoring program is designed to monitor the environment surrounding the CCNPP. A separate environmental monitoring program designed to monitor the environment surrounding the Independent Spent Fuel Storage Installation is described elsewhere in the ODCM.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 205 of 321 Level 3 - Information (c) In lieu of any location DR19-DR23 described on Attachment 13, establish a new monitoring station in either a special interest area (for example, population center, nearby residence, school) or a control station whichever is applicable.

(3) In the event any dosimetry at an existing monitoring location DR1-DR23 becomes unavailable, place new dosimetry at the monitoring station.

(4) Analyze the dosimeters at the frequencies and for the parameters identified on Attachment 14.

(5) The sampling locations(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM after October 31 of the year in which the land use census was conducted per Control 3.12.2.b.

b) Surveillances for airborne activity (1) Radioiodine and particulate samples shall be collected from locations A1-A5 listed on Attachment 13.

(2) In the event any of the monitoring stations, A1-A5, described on Attachment 13 become unavailable, establish new monitoring station(s) (fitted with new radioiodine and particulate samplers) as described below:

(a) In lieu of any location A1-A3 described on Attachment 13, establish a new monitoring station in the general area of the SITE BOUNDARY, such that the three monitoring stations are located in the meteorological sectors with the three highest calculated annual average ground level D/Q.

(b) In lieu location A4 described on Attachment 13, establish a new monitoring station near a community having the highest calculated annual average ground level D/Q.

(c) In lieu of location A5 described on Attachment 13 establish a new control location 15 to 30 kilometers from the plant in the least prevalent wind direction.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 206 of 321 Level 3 - Information (3) In the event any radioiodine cartridge or particulate filter becomes unavailable from an existing monitoring location A1-A5 described on Attachment 13, place new radioiodine cartridge or particulate filter in the air sampler at the monitoring station.

(4) Analyze the samples at the frequencies and for the parameters identified on Attachment 15.

(5) The sampling locations(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM after October 31 of the year in which the land use census was conducted per Control 3.12.2.b.

c) Surveillances of waterborne activity (1) Water and sediment samples shall be collected from the locations Wa1, Wa2, and Wb1 listed on Attachment 13.

(2) In the event any of the samples at Wa1, Wa2, or Wb1 are unavailable, collect substitute samples as described below:

(a) In lieu of a liquid sample at Wa1, collect a substitute sample of surface water from the intake area.

(b) In lieu of a liquid sample at Wa2, collect a substitute sample of surface water from the discharge area.

(c) In lieu of sample at Wb1, collect a substitute sample of sediment from a downstream shoreline with existing or potential recreational value.

(3) Analyze the samples at the frequencies and for the parameters identified on Attachment 16.

(4) The sampling locations(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM after October 31 of the year in which the land use census was conducted per Control 3.12.2.b.

d) Surveillances for ingestible activity (1) Fish/invertebrate, milk, and food product samples shall be collected from the locations Ia1 thru Ia6 and Ib1 thru Ib9 listed on Attachment 13.

(2) In the event any of the samples at Ia1 thru Ia6 or Ib1 thru Ib9 are unavailable, collect substitute samples as described below:

(a) In lieu of samples at Ia1 thru Ia3, collect substitute three commercially and/or recreationally important species (two fish species and one invertebrate species) from the vicinity of the plant discharge area.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 207 of 321 Level 3 - Information (b) In lieu of samples at Ia4 thru Ia6, collect three commercially and/or recreationally important species (two fish species and one invertebrate species) from an area not influenced by plant discharges.

(c) In lieu of samples at Ib1 thru Ib6, collect three kinds of broad leaf vegetation grown near the SITE BOUNDARY at two different locations of highest average ground level D/Q1.

(d) In lieu of samples at Ib7 thru Ib9, collect one sample each of the similar broad leaf vegetation grown 15-30 km distant in the least prevalent wind direction.

(3) Analyze the samples at the frequencies and for the parameters identified on Attachment 17.

(4) The sampling locations(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from the Radiological Environmental Monitoring Program after October 31 of the year in which the land use census was conducted per Control 3.12.2.b.

4. Responsible Company Organizations a) Chemistry is responsible for ensuring performance of the surveillances listed above.
5. Initiating conditions a) Collect samples per the frequencies specified on Attachments 14, 15, 16, and 17.

b) Analyze samples per the frequencies specified on Attachments 15, 16, and 17.

c) Calculate the potential annual doses per the methodology outlined below if any of the following conditions are true:

(1) any of the above surveillance results reveal levels of environmental activity greater than the ACTION Levels specified on Attachments 15, 16, 17 (per Control Table 3.12-2)

(2) any radionuclides other than those in Attachments 15, 16, and 17 are detected, and the radionuclides are the result of plant effluents.

1 With fresh leafy vegetable samples unavailable from one or more of the sample locations listed on Attachment 13, perform corrective actions specified by Control 3.12.1.c.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 208 of 321 Level 3 - Information d) The REMP Manager is responsible for notifying Management, if any of the following conditions are true:

(1) Any of the above surveillance results reveal levels of environmental activity greater than the ACTION Levels specified on Attachments 15, 16 17 (per Control Table 3.12-2)

(2) Any radionuclides other than those in Attachments 15, 16, and 17 are detected, and the radionuclides are the result of plant effluents, and the potential annual doses due to the radionuclides are greater than the calendar year limits of Controls 3.11.1.2, 3.11.2.2, and 3.11.2.3.

6. Calculation Methodology a) If the correct initiating conditions, as described above, are present, calculate potential annual doses for the pathway of interest per the methodologies contained in ODCM, or b) If methodologies other than those listed in the ODCM are used to calculate potential annual doses, such methodologies shall be documented in the AREOR per Control 3.12.1.b.
7. Corrective Actions a) If a sample is unobtainable due to sampling equipment malfunction, then attempt to restore equipment to operable status before the end of the next sampling period, and document in the AREOR (per Control 4.12.1, Table 3.12-1, notation a).

b) If the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM is not being conducted per Attachments 13, 14, 15, 16, or 17 document deviations in the AREOR (per Control 3.12.1.a).

c) With fresh leafy vegetable samples unavailable from one or more of the sample locations listed on Attachment 13, establish a new monitoring location and document applicable information in the AREOR (per Control 3.12.1.c).

d) When the analysis result for any parameter exceeds the ACTION Level listed on Attachments 15, 16, or 17, submit a Special Report to the NRC (per Control 3.12.1.b).

e) When radionuclides other than those listed on Attachments 15, 16, and 17 are detected; and if those radionuclides are the result of plant effluents; and if the potential annual doses due to the radionuclides are greater than the calendar year limits of Controls 3.11.1.2, 3.11.2.2, and 3.11.2.3; submit a Special Report (per Control 3.12.1.b).

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 209 of 321 Level 3 - Information LAND USE CENSUS

1. Introduction a) 10 CFR 50, Appendix I, Section IV.B.3 requires licensees to identify changes in the use of UNRESTRICTED AREAS in order to permit modifications in monitoring programs.

b) Radiological environmental controls have been established to implement the requirements of 10 CFR 50, Appendix I, Section IV.B.3.

c) These radiological environmental controls are described below.

2. Controls on the Land Use Census a) Identify the location of the nearest milk animal, within a distance of 8 km of the plant site, in each of the 9 meteorological sectors (per Control 3.12.2).

b) Identify the location of the nearest residence, within a distance of 8 km of the plant site, in each of the 9 meteorological sectors (per Control 3.12.2).

c) Identify the location of the nearest garden, within a distance of 8 km of the plant site, in each of the 9 meteorological sectors; or if the garden census was not conducted, obtain samples of three different kinds of broad leaf vegetation from the SITE BOUNDARY in two different meteorological sectors which have the highest predicted SITE BOUNDARY D/Q (per Control 3.12.2).

3. Surveillance Requirement(s) a) Perform a land use census that will provide the best results. Example methods may include, but are not limited to, the following:

(1) Door-to-door surveys (2) Aerial views (3) Consult local agricultural authorities b) Document the results of the land use census in the Annual Radiological Environmental Operating Report per Technical Specification 5.6.2.

c) Perform an Independent Technical Review of the land use census data.

4. Responsible Company Organizations a) Chemistry is responsible for ensuring the performance of the surveillances listed above.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 210 of 321 Level 3 - Information

5. Initiating Conditions a) Conduct the land use census during the growing season, and conduct the land use census at least once per 12 months.
6. Calculation Methodology a) Calculate doses for the pathways of interest per the methodologies contained in Regulatory Guide 1.109, or b) if methodologies other than those listed in Regulatory Guide 1.109 are used to calculate doses, such methodologies should be documented in the Annual Radiological Environmental Operating Report.
7. Corrective Actions a) The results of the land use census shall be used to determine the RADIOLOGICAL ENVIRONMENTAL MONITORING Programs sample locations identified on Attachment 13.

b) If the land use census has identified a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Control 4.11.2.3, perform the following activities.

(1) Document the new location(s) in the next Annual Radiological Environmental Operating Report per Technical Specification 5.6.2, and (2) Revise the figures and tables in the ODCM to reflect the new location(s).

c) If the land use census has identified a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) which is 20% greater than the equivalent location identified on Attachment 13, perform the following activities.

(1) Add the new location(s) to the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM within 30 days, (2) Document the new location(s) in the next Annual Radiological Environmental Operating Report per Technical Specification 5.6.2, and (3) Revise the figures and tables in the ODCM to reflect the new location(s).

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 211 of 321 Level 3 - Information INTERLABORATORY COMPARISON PROGRAM

1. Introduction a) 10 CFR 50, Appendix I, Section IV.B.2 requires licensees to establish an environmental surveillance and monitoring program for the purpose of evaluating the relationship between quantities of radioactive material released in effluents and resultant radiation doses to individuals.

b) Radiological environmental controls have been established to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

c) These radiological environmental controls are described below.

2. Controls on the Interlaboratory Comparison Program a) Analyze INTERLABORATORY COMPARISON PROGRAM samples supplied by either the Commission or a Commission approved laboratory for all parameters listed on Attachments 15, 16, and/or 17, as applicable1 (per Control 3.12.3).
3. Surveillance Requirement(s) a) A summary of the results obtained as part of the Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2.

b) This section of the ODCM shall describe the Interlaboratory Comparison Program.

4. Responsible Company Organizations a) Chemistry is responsible for ensuring performance of the surveillances listed above.
5. Initiating Conditions a) Analyze INTERLABORATORY COMPARISON PROGRAM samples whenever they are supplied by either the Commission or a Commission approved laboratory.
6. Calculation Methodology a) Analysis methods and calculational methodologies used to satisfy the above surveillances shall be documented in approved procedures.
7. Corrective Actions a) If analyses are not performed as required, document actions taken to prevent reoccurrence in the Annual Radiological Environmental Operating Report (AREOR) pursuant to Technical Specification 5.6.2.

1 Since no Commission approved laboratory supplies TLDs as part of a comparison program, no TLDs are analyzed as part of the INTERLABORATORY COMPARISON PROGRAM.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 212 of 321 Level 3 - Information ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

1. Introduction a) 10 CFR 50, Appendix I, Section IV.B.2 requires licensees to provide data on measurable levels of radiation and radioactive materials in the environment.

b) Radiological environmental controls have been established to implement the requirements of 10 CFR 50, Appendix I, Section IV.B.2.

c) These radiological environmental controls are described below.

2. Controls on the Annual Radiological Environmental Operating Report (AREOR) a) The AREOR shall include a summary description of the radiological environmental monitoring program (REMP).

b) The AREOR shall include a summary description of the Independent Spent Fuel Storage Installation Monitoring Program (ISFSIMP).

c) The AREOR shall include a table similar to Attachment 13 which states the distance and direction from the central point between the two containment buildings to each of the REMP sample points.

d) The AREOR shall include a table similar to Attachment 20 which states the distance and direction from the central point of the ISFSI to each of the ISFSIMP sample points.

e) The AREOR shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period.

f) The AREOR shall include a comparison between the annual REMP results and the Radiological Environmental Operating Report preoperational studies.

g) The AREOR shall include a comparison between the annual ISFSIMP results and Radiological Environmental Operating Report pre-fuel-load studies.

h) The AREOR shall include a comparison with operational controls as appropriate.

i) The AREOR shall include a comparison with the previous environmental surveillance reports.

j) The AREOR shall include an assessment of the observed impacts of plant operation on the environment.

k) The AREOR shall include an assessment of the observed impacts of ISFSI operation on the environment.

l) The AREOR shall include the results of the land use censuses required by Control 3.12.2.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 213 of 321 Level 3 - Information m) The AREOR shall include the results of analysis of all radiological environmental samples taken during the period pursuant to the locations specified on Attachments 13 and 20.

n) The AREOR shall include the results of all environmental radiation measurements taken during the period pursuant to the locations specified on Attachments 13 and 20.

o) The AREOR shall include summarized and tabulated results--in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979--of analysis of all radiological environmental samples taken during the period pursuant to the locations specified on Attachments 13 and 20.

p) The AREOR shall include summarized and tabulated results--in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979--of all environmental radiation measurements taken during the period pursuant to the locations specified on Attachments 13 and 20.

q) The AREOR shall include an explanation for missing results, if some individual results (as described in the above paragraph) are not available for inclusion with the report.

r) The AREOR shall include any data which was missing from previous reports.

s) The AREOR shall include at least two legible maps1covering all REMP sampling locations keyed to a table giving distances and directions from the central point between the two containment buildings.

t) The AREOR shall include at least one legible map covering all ISFSIMP sampling locations keyed to a table giving distances and directions from the central point of the ISFSI.

u) The AREOR shall include results of the licensee participation in the INTERLABORATORY COMPARISON PROGRAM required by Control 3.12.3.

v) The AREOR shall include a discussion of all deviations from the sampling schedules listed on Attachments 14, 15, 16, and 17, and specify the reason(s) for the deviations, and the plan for preventing recurrence.

w) The AREOR shall include a discussion of all analyses in which the LLD listed on Attachments 15, 16, and 17 (and required by Control Table 4.12-1) was not achievable.

x) The AREOR shall include the identification of the cause of unavailability of samples (if any), and describe the locations used for replacement samples.

y) The AREOR shall include any permanent changes in the sample locations in the monitoring program.

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

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 214 of 321 Level 3 - Information z) The AREOR shall include revised figure(s) (for example, like Attachments 18 and 19) and tables (for example, like Attachment 13) for the ODCM which reflect any new REMP sample location(s).

aa) The AREOR shall include revised figure(s) (for example, like Attachments 21 and 22) and table(s) (for example, like Attachment 20) for the ODCM which reflect any new ISFSIMP sample location(s).

bb) The AREOR shall receive an independent review for technical content before submittal to the NRC.

cc) Material provided in the AREOR shall be consistent with the objectives outlined in the ODCM and 10 CFR 50, Appendix I, Section IV.3.2, IV.3.3 and IV.C.

3. Surveillance Requirement(s) a) Write the Annual Radiological Environmental Operating Report covering the previous calendar year's operation of the reactor units.
4. Responsible Company Organizations a) Chemistry is responsible for ensuring the performance of the surveillances listed above1.
5. Initiating Conditions a) Submit the Routine AREOR (covering operation of the reactor units for the previous calendar year) of each year per Technical Specification 5.6.2.
6. Calculation Methodology a) Calculational methodologies used to satisfy the above surveillances should be documented in approved procedures, or should be included in the AREOR.
7. Corrective Actions a) If analyses are not performed as required, document actions taken to prevent reoccurrence in the AREOR pursuant to Technical Specification 5.6.2.

1 A separate company may be contracted to complete the Routine AREOR.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 215 of 321 Level 3 - Information INDEPENDENT SPENT FUEL STORAGE INSTALLATION MONITORING PROGRAM

1. Introduction a) The Technical Specifications for the Independent Spent Fuel Storage Installation1 (ISFSI), licensed under 10 CFR 72, require that monitoring for the ISFSI be added to the existing environmental monitoring program for CCNPP.

b) CCNPP has committed to additional monitoring for the ISFSI.2 c) Radiological environmental controls have been established to implement the requirements and commitments described above.

d) These radiological environmental controls are described below.

2. Controls on the ISFSI Monitoring Program a) Environmental monitoring sites, as described in Attachment 20, shall be established to monitor the air, vegetation, and soil as well as direct radiation in the ISFSI environs.3 b) Analysis parameters, analysis frequencies, detection limits, and ACTION levels shall conform to the applicable requirements of Controls 3.12.1.

(See attachment 14, 15, 16, and 17) c) Map(s) shall be maintained and shall show the locations of the environmental monitoring sites with respect to plant facilities. (See attachment 21 and 22).

3. Surveillance Requirements a) Surveillances for direct radiation (1) Direct radiation dosimetry shall be collected from locations SFDR1-SFDR16, DR7, and DR30 listed in Attachment 20.

(2) In the event any dosimetry at an existing monitoring location SFDR1-SFDR16, DR7, or DR30 becomes unavailable, place new dosimetry at the monitoring station.

1 The Technical Specifications For Calvert Cliffs Independent Spent Fuel Storage Installation is Appendix A to Materials License SNM-2505.

2 See the letter titled Response to NRC's Comments to Environmental Issues Regarding BGEs License Application for Calvert Cliffs Independent Spent Fuel Storage Installation (ISFSI) from Mr. R. E. Denton (BGE) to Director, Office of Nuclear Material Safety and Safeguards (NRC), dated November 1, 1990.

3 Environmental monitoring sites and monitoring parameters specifically excluded from the ISFSIMP include airborne radioiodines, radioiodines in food products, surface water, and fish and invertebrates. Additionally, soil samples shall be collected in lieu of shoreline sediment. The sampling frequency for vegetation and soil shall be quarterly.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 216 of 321 Level 3 - Information (3) Analyze the dosimeters at the frequencies and for the parameters identified on Attachment 14.

b) Surveillances for airborne particulate activity (1) Air particulate samples shall be collected from locations A1 and SFA1-SFA4 listed on Attachment 20.

(2) In the event any particulate filter becomes unavailable from an existing monitoring location A1 or SFA1-SFA4 described on Attachment 20, place a new particulate filter in the air sampler at the monitoring station.

(3) Analyze the samples at the frequencies and for the parameters identified under Particulate Filters on Attachment 15.

c) Surveillances for deposition on vegetation (1) The vegetation samples SFb1-SFb5 shall be collected from the locations listed on Attachment 20.

(2) In the event any of the sampling sites SFb1-SFb5 described on Attachment 20 become unavailable, establish new sampling sites as described below:

(a) In lieu of sample SFb1, collect vegetation grown in the NW sector of the ISFSI.

(b) In lieu of sample SFb2, collect vegetation grown in the general vicinity of the CCNPP Visitor's Center.

(c) In lieu of sample SFb3, collect vegetation grown in the North North West sector of the ISFSI.

(d) In lieu of sample SFb4, collect vegetation grown in the South-Southeast sector of the ISFSI.

(e) In lieu of sample SFb5, collect vegetation grown in the East-Southeast sector of the ISFSI.

(3) Analyze the samples quarterly for the non-iodine parameters identified under Food Products on Attachment 17.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 217 of 321 Level 3 - Information d) Surveillances for soil activity (1) The soil samples SFS1-SFS5 shall be collected from the locations listed on Attachment 20.

(2) In the event any of the sampling sites SFS1-SFS5 described on Attachment 20 become unavailable, establish new sampling sites as described below:

(a) In lieu of sample SFS1, collect soil in the NW sector of the ISFSI.

(b) In lieu of sample SFS2, collect soil in the general vicinity of the CCNPP Visitor's Center.

(c) In lieu of sample SFS3, collect soil in the North North West sector of the ISFSI.

(d) In lieu of sample SFS4, collect soil in the South-Southeast sector of the ISFSI.

(e) In lieu of sample SFS5, collect soil in the East-Southeast sector of the ISFSI.

(3) Analyze the samples quarterly for the parameters identified under Shoreline Sediment Sample on Attachment 16.

4. Responsible Company Organizations a) Chemistry is responsible for ensuring the performance of the surveillances listed above.
5. Initiating Conditions a) Collect samples per the frequencies specified on Attachments 14, 15, 16, and 17.

Soil and vegetation samples shall be collected quarterly.

b) Analyze samples per the frequencies specified on Attachments 14, 15, 16, and 17.

Soil and vegetation samples shall be analyzed quarterly.

c) Calculate the potential annual doses per the methodology outlined elsewhere in this section if any of the following conditions are true:

(1) any of the above surveillance results reveal levels of environmental activity greater than the ACTION Levels specified on Attachments 14, 15, 16, and 17, as appropriate. (per Control Table 3.12-2), or (2) any radionuclides other than those listed on Attachments 14, 15, 16, and 17 are detected, and the radionuclides are the result of plant effluents or radionuclide deposition from the ISFSI, and the potential annual doses due to the radionuclides are greater than the limits listed in Control 3.12.1.b.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 218 of 321 Level 3 - Information d) Chemistry is responsible for notifying the Management if any of the following conditions are true:

(1) any of the above surveillance results reveal levels of environmental activity greater than the ACTION Levels specified on Attachments 14, 15, 16, and 17, as appropriate (per Control Table 3.12-2), or (2) any radionuclides other than those in Attachments 14, 15, 16, and 17 are detected, and the radionuclides are the result of plant effluents or radionuclide deposition from the ISFSI, and the potential annual doses due to the radionuclides are greater than the limits listed in Control 3.12.1.b.

6. Calculation Methodology a) If any (of the above) surveillance results reveal levels of environmental activity greater than the ACTION Levels specified on Attachments 14, 15, 16, or 17 (per Control Table 3.12-2), calculate potential annual doses for the pathway of interest, per the methodologies contained in Regulatory Guide 1.109.

b) If methodologies other than those listed in Regulatory Guide 1.109 are used to calculate potential annual doses, such methodologies shall be documented per Control 3.12.1.b.

7. Corrective Actions a) If a sample is unobtainable due to sampling equipment malfunction, then attempt to restore equipment to operable status before the end of the next sampling period, and document in the AREOR.

b) If the ISFSIMP is not being conducted per the Surveillance Requirements listed elsewhere in this section, document deviations in the AREOR.

c) When the analysis result for any parameter exceeds the ACTION Level listed on Attachments 15, 16, or 17, as appropriate, submit a Special Report to the NRC (per Control 3.12.1.b).

d) When radionuclides other than those listed on Attachments 15, 16, and 17 are detected, and when those radionuclides are the result of plant effluents or radionuclide deposition from the ISFSI, submit a Special Report if required by and (per Control 3.12.1.b).

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 219 of 321 Level 3 - Information RADIOACTIVE EFFLUENT RELEASE REPORT INTRODUCTION

1. Technical Specification 5.6.3 requires submittal of a written report to the NRC every 12 months.
2. The report is described below.

RESPONSIBILITIES

1. Chemistry is responsible for the timely and accurate completion of the report.

REPORT CONTENTS

1. The Radioactive Effluent Release Report (RERR) covering the operation of the unit shall be submitted every 12 months per 10 CFR 50.36a.
2. The RERR shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units. The material provided shall be consistent with the objectives outlined in the ODCM and in conformance to 10CFR50.36a and 10CFR50, Appendix I, section IV.B.1. Principle Gamma Emitters from Batch Waste Releases and Turbine Building Sump shall be analyzed and included in this report pursuant to Table Notation c of Control Table 4.11-1, Radioactive Liquid Waste Sampling and Analysis Program. In addition, Principal Gamma Emitters from the Waste Gas Storage Tank, Containment Purge and Vent, and the Main Vent shall be analyzed and included in this report pursuant to Table Notation b of Controls Table 4.11-2, Radioactive Gaseous Waste Sampling and Analysis Program. Additional information which may be required in the report is contained in Controls 3.3.3.9.b, 3.3.3.10.b and Technical Specification 5.6.3.
3. The RERR shall include an annual summary of hourly meteorological data collected over the previous 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.1 This same report shall 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. The assessment of radiation doses shall be performed per the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
4. The RERR shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977, and NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.

1 In lieu of submission with the Radioactive Effluent Release Report, this summary of required meteorological data may be retained on site in a file that shall be provided to the NRC upon request.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 220 of 321 Level 3 - Information

5. The RERR shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:
a. Container volume,
b. Total curie quantity (specify whether determined by measurement or estimate),
c. Principal radionuclides (specify whether determined by measurement or estimate),
d. Source of waste and processing employed (for example, dewatered spent resin, compacted dry waste, evaporator bottoms),
e. Solidification agent or absorbent (for example, cement).
6. The RERR shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
7. The RERR shall include any changes made during the reporting period to the OFFSITE DOSE CALCULATION MANUAL (ODCM) and a listing of new locations for dose calculations identified by the annual land use census pursuant to Control 3.12.2.
8. The RERR shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP)1. The report shall contain:
a. A description of the equipment, components and processes involved.
b. Documentation of the fact that the change, including the safety analysis, was reviewed and found acceptable by the POSRC.

REPORT SUBMITTAL

1. Before submittal a Independent Technical Review will be performed.
2. The RERR will be submitted every 12 months per 10 CFR 50.36a and 50.4.

1 Licensee initiated changes to the PCP shall become effective upon review by the POSRC and approval of the Plant General Manager.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 221 of 321 Level 3 - Information ADMINISTRATION OF THE ODCM INTRODUCTION

1. Procedures covering the ODCM and the implementation of the ODCM shall be implemented.
2. Administrative controls have been established to implement controls on the ODCM.
3. These administrative controls are described below.

CONTROLS ON THE ODCM

1. The format, organization, content, and administration of the ODCM are controlled by CY-AA-170-300.
2. Methodologies identified in the ODCM are implemented by various CCNNPI organizations per approved procedures. (See the RESPONSIBILITIES section of CY-AA-170-000 for a list of those Sections of CCNNPI responsible for approving and maintaining procedures, which implement the requirements of the ODCM.)
3. The Main Vent Stack flow rates shall be verified per the surveillances described in the following section, Surveillance Requirements.
4. Licensee initiated changes to the ODCM:

a) Shall be documented and records of reviews performed shall be retained. This documentation shall contain (1) Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s);

(2) A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20 (1990), 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and 10 CFR Part 50, Appendix I, and not adversely impact the accuracy or reliability of effluent dose, or setpoint calculations; b) Shall become effective upon review by the onsite review function and approval of the plant manager; and c) Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. The copy submitted to the NRC shall include markings in the margin of the affected pages, clearly indicating the area of the page that was changed and shall indicate the date (for example, month and year) the change was implemented.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 222 of 321 Level 3 - Information SURVEILLANCE REQUIREMENTS

1. Complete audits and PERIODIC REVIEWS of the ODCM per CY-AA-170-000.
2. Determine Main Vent Stack flow rates for both units as described below.

a) The Main Vent Stack flow rate shall be determined, per approved procedures, at least once per 6 months (+ 25%).

b) The Electrical and Control Section shall be responsible for performing this test.

c) The results of the main vent flow rate test shall be evaluated to ensure the main vent flow rates used in the ODCM are an accurate reflection of the true main vent flow rates.

d) IF the Main Vent Stack flow rate for either unit, as determined per approved Test and Equipment procedure(s), changes + 10% from the values referenced in Attachment 7 of the ODCM, a technical evaluation shall be initiated to determine if the ODCM should be revised.

RESPONSIBLE COMPANY ORGANIZATIONS

1. CY-AA-170-000 identifies the responsibilities of various personnel and company organizations which administer and implement the ODCM. This section of the ODCM identifies company organizations which are assigned responsibility for implementing the surveillances described above.
2. The Electrical and Control Section is responsible for ensuring the Main Vent Stack flow rate test procedure (for example, STP-M-462-1, STP-M-462-2 or equivalent) is completed per the surveillances listed above.
3. The Electrical and Control Section is responsible for forwarding Main Vent Stack flow rate test results to Chemistry.
4. The RETS Program Manager, Chemistry, is responsible for evaluating main vent flow rate test results (for example, STP-M-462-1, STP-M-462-2 or equivalent results) and for performing the technical evaluation described in the above surveillances.

INITIATING CONDITIONS

1. Main Vent Stack flow rates shall be determined at least once per 6 months (+ 25%), or more often if required by Controls.
2. Complete PERIODIC REVIEWS of the ODCM as specified in CY-AA-170-000.

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CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 223 of 321 Level 3 - Information CALCULATION METHODOLOGIES

1. Calculational methodologies used to satisfy the above surveillances should be documented in approved procedures.
2. Documents which serve as a basis for calculation methodologies used in the ODCM should be maintained in an accessible location.

(1) Supporting documents may be incorporated into the ODCM (for example, as Attachments).

(2) Supporting documents may be maintained in a procedure history file.

(3) Supporting documents may be identified in the references section of the ODCM.

CORRECTIVE ACTIONS

1. IF Main Vent Stack flow rates, as determined per appropriate Test Equipment procedure(s),

change + 10% from the values referenced in Attachment 7 of the ODCM, a technical evaluation shall be initiated to determine if the ODCM should be revised.

BASES

1. [B527], NRC Inspection Report INSR 91-30/30
2. [B375], 40 CFR 302, 11/07/1997 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 224 of 321 Level 3 - Information Attachment 1 Final Grading And Drainage Plan A reference diagram which depicts the grading for and the drainage from the Calvert Cliffs Nuclear Power Plant can be found in the following reference:

Final Grading And Drainage Plan Calvert Cliffs Nuclear Power Plant Units 1 and 2, BGE Document ID Number: 61517SH0001 BGE Document ID Number: 61514SH0002 The above referenced grading and drainage plan is intended for reference only. This drawing may not reflect the changes and modifications since March 1975.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 225 of 321 Level 3 - Information Attachment 2 Sources of Liquid Radioactive Waste Waste Stream Radiation Type of Release Max. Discharge Maximum Volume Notes Monitor Flow Rate gal/min liters/min gal liters Rx. Coolant Wst. Mon. Tk. 0-RE-2201 Batch 120 454 9000013 3.407E513 Rx. Coolant Wst. Rec. Tk. 0-RE-2201 Batch 120 454 9000013 3.407E513 Misc. Wst. Mon. Tk. 0-RE-2201 Batch 120 454 400013 1514013 Misc. Wst. Rec. Tk. 0-RE-2201 Batch 120 454 400013 1514013 Aux. Boiler Steam Drum All releases are via Auxiliary Blowdown Tank Aux. Blowdown Tk. Unmonitored Continuous 20012 757 N/A N/A Waste Neut. Tk. 11 Unmonitored Batch 10001 37901 45988 1.74E5 Waste Neut. Tk. 12 Unmonitored Batch 10001 37901 47749 1.80E5 Stm. Gen. Blowdown Tk. 1/2-RE-401414 Continuous/Batch11 2252 8522 23503 88953 Component Cooling Water4 Unmonitored Continuous variable5 variable5 440906 1.669E5 Condenser Hotwells Unmonitored Batch10 45007 170007 1.05E5 3.97E5 Salt Water System Unmonitored Continuous 15500 58670 N/A N/A Condensate Storage Tank Unmonitored Batch Variable8 Variable8 3.5E59 1.3E69 Demin. Water Storage Tank Unmonitored Batch Variable8 Variable8 3.5E59 1.3E69 Precoat Sump Unmonitored Continuous 50 94.6 103053 390043 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 226 of 321 Level 3 - Information Attachment 2 Sources of Liquid Radioactive Waste Waste Stream Radiation Type of Max. Discharge Maximum Volume Notes Monitor Release Flow Rate Gal/min liters/min gal liters Aux. Building Roof Drains19 Unmonitored Continuous Variable Variable N/A N/A Sewage Treatment Plant Unmonitored Continuous 185 700 N/A N/A Turbine Bldg. Sump No. 11 Unmonitored Continuous 470 889 1950 7381 Turbine Bldg. Sump No. 12 Unmonitored Continuous 470 889 2415 9141 Turbine Bldg. Sump No. 21 Unmonitored Continuous 470 889 2490 9425 Turbine Bldg. Sump No. 22 Unmonitored Continuous 470 889 2182 8259 Diesel Oil Interceptor Sump Unmonitored Continuous 100 378.5 5790 21920 Yard Oil Interceptor Unmonitored Continuous variable15 variable15 N/A N/A Refueling Water Tank Unmonitored Batch/Cont.17 variable15 variable15 4.2E5 1.6E6 Condensate Storage Tank Unmonitored Batch/Cont.17 variable15 variable15 3.5E516 1.3E616 Service Water System 1/2-RE-1595 Continuous variable15 variable15 31418 1.189E5 Plant Heating System18 Unmonitored Continuous variable15 variable15 N/A N/A December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 227 of 321 Level 3 - Information Attachment 2 Sources of Liquid Radioactive Waste

1. This flow rate is only an approximation. The motive force is gravity
2. This is the maximum flow rate. The actual flow rate will be considerably less.
3. This is the maximum volume of the tank for a BATCH RELEASE. If the release is a CONTINUOUS RELEASE, the volume discharged would be calculated from the discharge flow rate and duration of the release.
4. There is no direct path by which radioactive liquid from the CCW System could enter outfall 001. Liquid from the CCW System may leak into either the Salt Water System (which drains to outfall 001) or the Liquid Waste Processing System (via Aux. Bldg. Drains).
5. Radioactive liquid is not normally released from the CCW system. Flow rate to outfall 001 may occur via Salt Water System. For this pathway, the flow rate will vary (for example, depending on size of leak). See Safety Analysis No. 2, FCR 82-1053, Supplement 1.
6. System volume is 5894 cubic feet. Conversion constant is 0.13368 cubic feet per gallon.
7. The flow rate shown here is the flow rate for one condensate pump. Verify the number on condensate pumps in service, and modify this flow rate accordingly.
8. Flow rate should be calculated on a case-by-case basis.
9. Volume obtained from Plant Data Book, BGE CCNPP Units 1 and 2, Bechtel Power Corporation, Volume 1, Job 6750.
10. May be a CONTINUOUS RELEASE if contaminated sealing steam is operated during the release.
11. Although steam generator releases may be either CONTINUOUS RELEASES or BATCH RELEASES. Verify type of release to be conducted before discharge.
12. This is the maximum rated discharge for two pumps in operation.
13. The volume specified is the design basis volume from Table 11-1 of the UFSAR.
14. The Steam Generator Blowdown effluent radiation monitor, 1/2-RE-4095, may be equivalent to the 1/2-RE-4014 (see part 5, Liquid Effluent Radiation Monitor Alarm and Fixed Setpoints, para. 2)
15. Maximum discharge flow rate shall be determined on a case-by-case basis.
16. Volume obtained from Plant Data Book, BGE CCNPP Units 1 and 2, Bechtel Power Corporation, Volume 1, Job 6750.
17. Releases via this pathway would be considered a BATCH RELEASE if a catastrophic tank failure occurred. In the event of a small leak, the release may be considered a CONTINUOUS RELEASE. The release mode should be determined on a case-by-case basis.
18. The plant heating system is a closed system and is not normally released to the environment. In the event of a leak, the effluent may be released to the environment via the turbine building sumps. In some cases, depending on the location of the leak, the effluent would be collected in the auxiliary building sump and subsequently released through the liquid radioactive waste processing system. The effluent pathway should be determined on a case-by-case basis.
19. Plant drawings indicate that these drains discharge to Outfalls 003 and 004.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 228 of 321 Level 3 - Information Attachment 3 Unmonitored Release Paths

1. Sub-surface Drainage System
a. Before 2001, an unmonitored release pathway was created which allowed previously monitored, controlled and diluted liquid effluents (discharged by design into Outfall 001) to enter the groundwater through the Sub-surface Drainage System during periods of high tide.
b. This pathway was corrected in 2001.
c. Although the pathway was corrected in 2001, the groundwater at that location was discovered to contain tritium.
d. The movement of this tritum plume is being monitored by the Groundwater Protection Program.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 229 of 321 Level 3 - Information Attachment 4 Block Diagram of Liquid Radioactive Waste Systems Reactor Coolant Waste Miscellaneous Waste Unit 1 Unit 1 RC Unit 2 RC Unit 2 Unit 1 S/G Unit 2 S/G Aux. Bldg. Laundry &

CVCS Drain Tank Drain Tank CVCS Blowdown Blowdown Drains U-1& 2 Lab. Drains Letdown Letdown RC Waste Filters (2) 120 GPM Misc. Waste 1-RE-4014 2-RE-4014 Receiver Tk R R 4,000 GAL Automatic RC Waste Isolation To Gaseous Degassifiers (2) Valves Waste 1-RE-4095 2-RE-4095 Misc. Waste Processing Misc. Waste R R Filters (2) Monitor Tk System 4,000 GAL RC Waste Ion Exchangers (2) Automatic Isolation Valves Misc. Waste RC Waste Ion Receiver Tks (2) Exchanger 90,000 GAL To Solid To Solid Waste RC Waste Evap. Waste Processing Pre-Filter (2) Processing System System Boric Acid Evaporator (2) Storage 20 GPM Tanks (4)

RC Waste Ion Exchangers (2) or Radwaste Skid RC Waste Monitoring Tk

(#11) 90,000 GAL Turbine Bldg.

Sump RC Waste Chesapeake Circulating Water Bay Chesapeake Monitoring Tk (#12) 90,000 GAL Bay Automatic Isolation 0-RE-2201 R Valve December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 230 of 321 Level 3 - Information Attachment 5 Radionuclides in Typical Radwaste Discharges The term fi -- a fraction which represents the relative activity contribution of nuclide i to the average total effluent activity -- is used in several equations in the ODCM (for example, equations 2G, 5G, 3L, and 4L).

This attachment provides guidance for calculating the values of f i.

1. Select the calendar quarters which contain at least one typical liquid (or gas) release (see definition of TYPICAL RADWASTE RELEASE).
2. For each of the calendar quarters selected above, obtain a listing of the nuclides, nuclide activities, and release (end) dates.
a. This data may be obtained from the Radioactive Effluent Release Report(s) for the time periods of interest, or
b. This data may be obtained from a computer-based effluent management system (if available).
c. The values of nuclide activities and release end times may be close approximations of the true values.
3. Sum the quarterly activities (curies) for each individual radionuclide.

AiT = AiQ Eq. 1R

4. Sum the quarterly activities for all radionuclides, i.

AT = AiT Eq. 2R

5. Calculate the fraction of the total activity attributable to each radionuclide (that is, the relative activity of nuclide i).

fi = AiT / AT Eq. 3R December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 231 of 321 Level 3 - Information Attachment 6 Adult - Liquid Effluent Dose Factors (mrem/hr per uCi/ml)

Saltwater Fish and Saltwater Invertebrates The calculation of dose factors is determined by the following equation:

Ai k 0

  • UFap BFi Uap O BFi
  • DFi *RC Eq. 6-1 Where:

A i = Ingestion dose factor in mrem/hr per uCi/ml k0 = 114155 (1.0 E6 pCi/uCi x 1000 ml/1 )/ 8760 hr/yr) units conversion factor UFap = 21 (Fish (fresh or salt) consumption rate adult (kg/yr) from Reg. Guide 1.109 Table E-5 O

U ap = 5 (Other seafood consumption rate adult (kg/yr) from Reg. Guide 1.109 Table E-5 BFi = Bioaccumulation Factors (pCi/kg per pCi/liter) from Reg. Guide 1.109 Table A-1 DFi = Ingestion Dose Factors from Reg. Guide 1.109 Table E-11 RC = 1 Reconcentration Factor (Site Specific Information)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 2.820E-01 2.820E-01 2.820E-01 2.820E-01 2.820E-01 2.820E-01 BE-7 2.700E+01 1.100E+01 6.500E+01 1.300E+00 1.600E+01 3.100E+00 2.700E+02 C-14 1.450E+04 2.900E+03 2.900E+03 2.900E+03 2.900E+03 2.900E+03 2.900E+03 NA-24 4.570E-01 4.570E-01 4.570E-01 4.570E-01 4.570E-01 4.570E-01 4.570E-01 P-32 4.690E+06 2.910E+05 1.810E+05 0.000E+00 0.000E+00 0.000E+00 5.270E+05 CR-51 0.000E+00 0.000E+00 5.580E+00 3.340E+00 1.230E+00 7.400E+00 1.400E+03 MN-54 0.000E+00 7.060E+03 1.350E+03 0.000E+00 2.100E+03 0.000E+00 2.160E+04 MN-56 0.000E+00 1.780E+02 3.150E+01 0.000E+00 2.260E+02 0.000E+00 5.670E+03 FE-55 5.110E+04 3.530E+04 8.230E+03 0.000E+00 0.000E+00 1.970E+04 2.030E+04 FE-59 8.060E+04 1.900E+05 7.270E+04 0.000E+00 0.000E+00 5.300E+04 6.320E+05 CO-57 0.000E+00 1.420E+02 2.360E+02 0.000E+00 0.000E+00 0.000E+00 3.590E+03 CO-58 0.000E+00 6.030E+02 1.350E+03 0.000E+00 0.000E+00 0.000E+00 1.220E+04 CO-60 0.000E+00 1.730E+03 3.820E+03 0.000E+00 0.000E+00 0.000E+00 3.250E+04 NI-63 4.960E+04 3.440E+03 1.670E+03 0.000E+00 0.000E+00 0.000E+00 7.180E+02 NI-65 2.020E+02 2.620E+01 1.200E+01 0.000E+00 0.000E+00 0.000E+00 6.650E+02 CU-64 0.000E+00 2.140E+02 1.010E+02 0.000E+00 5.400E+02 0.000E+00 1.830E+04 ZN-65 1.610E+05 5.130E+05 2.320E+05 0.000E+00 3.430E+05 0.000E+00 3.230E+05 ZN-69 3.430E+02 6.560E+02 4.560E+01 0.000E+00 4.260E+02 0.000E+00 9.850E+01 BR-82 0.000E+00 0.000E+00 4.070E+00 0.000E+00 0.000E+00 0.000E+00 4.670E+00 BR-83 0.000E+00 0.000E+00 7.250E-02 0.000E+00 0.000E+00 0.000E+00 1.040E-01 BR-84 0.000E+00 0.000E+00 9.390E-02 0.000E+00 0.000E+00 0.000E+00 7.370E-07 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 232 of 321 Level 3 - Information Attachment 6 Adult - Liquid Effluent Dose Factors (mrem/hr per uCi/ml)

Saltwater Fish and Saltwater Invertebrates Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BR-85 0.000E+00 0.000E+00 3.860E-03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 6.240E+02 2.910E+02 0.000E+00 0.000E+00 0.000E+00 1.230E+02 RB-88 0.000E+00 1.790E+00 9.490E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 1.190E+00 8.340E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 4.990E+03 0.000E+00 1.430E+02 0.000E+00 0.000E+00 0.000E+00 8.000E+02 SR-90 1.230E+05 0.000E+00 3.010E+04 0.000E+00 0.000E+00 0.000E+00 3.550E+03 SR-91 9.180E+01 0.000E+00 3.710E+00 0.000E+00 0.000E+00 0.000E+00 4.370E+02 SR-92 3.480E+01 0.000E+00 1.510E+00 0.000E+00 0.000E+00 0.000E+00 6.900E+02 Y-90 6.060E+00 0.000E+00 1.630E-01 0.000E+00 0.000E+00 0.000E+00 6.420E+04 Y-91M 5.730E-02 0.000E+00 2.220E-03 0.000E+00 0.000E+00 0.000E+00 1.680E-01 Y-91 8.880E+01 0.000E+00 2.370E+00 0.000E+00 0.000E+00 0.000E+00 4.890E+04 Y-92 5.320E-01 0.000E+00 1.560E-02 0.000E+00 0.000E+00 0.000E+00 9.320E+03 Y-93 1.690E+00 0.000E+00 4.660E-02 0.000E+00 0.000E+00 0.000E+00 5.350E+04 ZR-95 1.590E+01 5.110E+00 3.460E+00 0.000E+00 8.020E+00 0.000E+00 1.620E+04 ZR-97 8.810E-01 1.780E-01 8.130E-02 0.000E+00 2.680E-01 0.000E+00 5.510E+04 NB-95 4.470E+02 2.490E+02 1.340E+02 0.000E+00 2.460E+02 0.000E+00 1.510E+06 NB-97 3.750E+00 9.490E-01 3.460E-01 0.000E+00 1.110E+00 0.000E+00 3.500E+03 MO-99 0.000E+00 1.280E+02 2.430E+01 0.000E+00 2.890E+02 0.000E+00 2.960E+02 TC-99M 1.300E-02 3.660E-02 4.660E-01 0.000E+00 5.560E-01 1.790E-02 2.170E+01 TC-101 1.330E-02 1.920E-02 1.880E-01 0.000E+00 3.460E-01 9.810E-03 0.000E+00 RU-103 1.070E+02 0.000E+00 4.600E+01 0.000E+00 4.070E+02 0.000E+00 1.250E+04 RU-105 8.890E+00 0.000E+00 3.510E+00 0.000E+00 1.150E+02 0.000E+00 5.440E+03 RU-106 1.590E+03 0.000E+00 2.010E+02 0.000E+00 3.060E+03 0.000E+00 1.030E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CD-109 2.100E+05 4.000E+06 1.600E+06 1.500E+05 2.200E+07 1.800E+05 2.500E+06 AG-110M 1.560E+03 1.450E+03 8.600E+02 0.000E+00 2.850E+03 0.000E+00 5.910E+05 SN-113 6.700E+03 1.200E+03 2.100E+04 6.200E+02 1.600E+03 7.300E+02 2.200E+05 SB-122 5.300E+01 5.520E+01 6.690E+02 8.780E+00 2.610E+01 1.140E+01 6.580E+03 SB-124 2.770E+02 5.230E+00 1.100E+02 6.710E-01 0.000E+00 2.150E+02 7.860E+03 SB-125 1.770E+02 1.980E+00 4.210E+01 1.800E-01 0.000E+00 1.360E+02 1.950E+03 TE-125M 2.170E+02 7.860E+01 2.910E+01 6.520E+01 8.820E+02 0.000E+00 8.660E+02 TE-127M 5.480E+02 1.960E+02 6.680E+01 1.400E+02 2.230E+03 0.000E+00 1.840E+03 TE-127 8.900E+00 3.200E+00 1.930E+00 6.600E+00 3.630E+01 0.000E+00 7.030E+02 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 233 of 321 Level 3 - Information Attachment 6 Adult - Liquid Effluent Dose Factors (mrem/hr per uCi/ml)

Saltwater Fish and Saltwater Invertebrates Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract TE-129M 9.310E+02 3.470E+02 1.470E+02 3.200E+02 3.890E+03 0.000E+00 4.690E+03 TE-129 2.540E+00 9.550E-01 6.190E-01 1.950E+00 1.070E+01 0.000E+00 1.920E+00 TE-131M 1.400E+02 6.850E+01 5.710E+01 1.080E+02 6.940E+02 0.000E+00 6.800E+03 TE-131 1.590E+00 6.660E-01 5.030E-01 1.310E+00 6.990E+00 0.000E+00 2.260E-01 TE-132 2.040E+02 1.320E+02 1.240E+02 1.460E+02 1.270E+03 0.000E+00 6.240E+03 I-130 3.960E+01 1.170E+02 4.610E+01 9.910E+03 1.820E+02 0.000E+00 1.010E+02 I-131 2.180E+02 3.120E+02 1.790E+02 1.020E+05 5.350E+02 0.000E+00 8.230E+01 I-132 1.060E+01 2.850E+01 9.960E+00 9.960E+02 4.540E+01 0.000E+00 5.350E+00 I-133 7.450E+01 1.300E+02 3.950E+01 1.900E+04 2.260E+02 0.000E+00 1.160E+02 I-134 5.560E+00 1.510E+01 5.400E+00 2.620E+02 2.400E+01 0.000E+00 1.320E-02 I-135 2.320E+01 6.080E+01 2.240E+01 4.010E+03 9.750E+01 0.000E+00 6.870E+01 CS-134 6.840E+03 1.630E+04 1.330E+04 0.000E+00 5.270E+03 1.750E+03 2.850E+02 CS-136 7.160E+02 2.830E+03 2.040E+03 0.000E+00 1.570E+03 2.160E+02 3.210E+02 CS-137 8.770E+03 1.200E+04 7.850E+03 0.000E+00 4.070E+03 1.350E+03 2.320E+02 CS-138 6.070E+00 1.200E+01 5.940E+00 0.000E+00 8.810E+00 8.700E-01 5.120E-05 BA-139 7.850E+00 5.590E-03 2.300E-01 0.000E+00 5.230E-03 3.170E-03 1.390E+01 BA-140 1.640E+03 2.060E+00 1.080E+02 0.000E+00 7.020E-01 1.180E+00 3.380E+03 BA-141 3.810E+00 2.880E-03 1.290E-01 0.000E+00 2.680E-03 1.630E-03 1.800E-09 BA-142 1.720E+00 1.770E-03 1.080E-01 0.000E+00 1.500E-03 1.000E-03 0.000E+00 LA-140 1.570E+00 7.940E-01 2.100E-01 0.000E+00 0.000E+00 0.000E+00 5.830E+04 CE-139 1.000E+02 4.800E+01 3.700E+02 6.200E-01 3.400E+01 4.800E+00 3.200E+03 LA-142 8.060E-02 3.670E-02 9.130E-03 0.000E+00 0.000E+00 0.000E+00 2.680E+02 CE-141 3.430E+00 2.320E+00 2.630E-01 0.000E+00 1.080E+00 0.000E+00 8.860E+03 CE-143 6.040E-01 4.460E+02 4.940E-02 0.000E+00 1.970E-01 0.000E+00 1.670E+04 CE-144 1.790E+02 7.470E+01 9.590E+00 0.000E+00 4.430E+01 0.000E+00 6.040E+04 PR-143 5.790E+00 2.320E+00 2.870E-01 0.000E+00 1.340E+00 0.000E+00 2.540E+04 PR-144 1.900E-02 7.870E-03 9.640E-04 0.000E+00 4.440E-03 0.000E+00 2.730E-09 ND-147 3.960E+00 4.580E+00 2.740E-01 0.000E+00 2.680E+00 0.000E+00 2.200E+04 EU-154 3.870E+02 4.760E+01 3.390E+01 0.000E+00 2.280E+02 0.000E+00 3.450E+04 EU-155 5.420E+01 7.68E+00 4.960E+00 0.000E+00 3.550E+01 0.000E+00 6.050E+03 W-187 9.160E+00 7.660E+00 2.680E+00 0.000E+00 0.000E+00 0.000E+00 2.510E+03 NP-239 3.530E-02 3.470E-03 1.910E-03 0.000E+00 1.080E-02 0.000E+00 7.110E+02 HG-203 1.400E+05 0.000E+00 1.600E+05 0.000E+00 1.600E+06 1.000E+05 3.200E+05 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 234 of 321 Level 3 - Information Attachment 7 General Information Related to Gaseous Releases via the Main Vents Waste Stream Radiation Monitor Type of release Minimum Discharge Nominal Discharge Maximum Discharge Flow Rate Flow Rate Flow Rate m3 / sec SCFM m3 / sec SCFM m3/sec SCFM Waste Gas System (WGDT) 0-RE-21911 Batch N/A N/A N/A N/A 2.36E-2 50 Cntmt. Vent (via H2 Purge) 1/2-RE-54152 Batch3 N/A N/A 2.36E-2 50 2.93E-1 620 Unit 1 Cntmt. Purge (100%) 1-RE-54154 Continuous5 N/A N/A N/A N/A 22.46 47,3876 Unit 2 Cntmt. Purge (100%) 7 5 N/A N/A N/A N/A 20.98 44,3208 2-RE-5415 Continuous Unit 1 Main Vent Release 4 Continuous 50.711 10740611 56.39 9 62.010 10 1-RE-5415 119339 131273 Unit 2 Main Vent Release 7 Continuous 38.411 8145011 9 9 10 10 2-RE-5415 42.7 90500 47.0 99550 1 Since the WGDT is released to the plant vent stack, 1/2-RE-5415 and 1/2-RE-5416A may also be used to monitor releases from a WGDT.

2 The WRGM, 1/2-RE-5416A, may also monitor these releases.

3 A containment vent is considered a batch release (even though inleakage of radioactive gases into the containment atmosphere may occur during the time the vent is in progress).

4 The WRGM, 1-RE-5416A, may also monitor these releases.

5 A purge is considered to be a CONTINUOUS RELEASE due to potential introduction of radioactive gases to the containment atmosphere during containment maintenance activities.

6 This is the purge flow rate as determined by approved test procedure (i.e., TE-006) in April 1998.

7 The WRGM, 2-RE-5416A, may also monitor these releases.

8 This is the purge flow rate as determined by approved test procedure (i.e., TE-006) in March 2001.

9 This is the mean main vent stack flow rate as determined by approved test procedure (i.e., TE-001 from 8/1990-3/1996 for Unit 1 and TE-001 from 8/1990-3/2000 for Unit 2 or STP-M-462-1 for Unit 1 and STP-M-462-2 for Unit 2 beginning in May 2002).

10 This is the maximum vent stack flow rate which is equal to 110% of the Nominal Discharge Flow rate. If flow rate is greater than this value, a technical evaluation shall be initiated per section Administration of the ODCM, Corrective Actions.

11 This value is equal to 90% of the Nominal Discharge Flow rate. If flow rate is less than this value, a technical evaluation shall be initiated per section Administration of the ODCM, Corrective Actions December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 235 of 321 Level 3 - Information Attachment 8 General Information Related to Gaseous Releases via Pathways other than the Main Vents Waste Streams Radiation Monitor Type of Release Nominal Discharge Notes Flow Rate Aux. Boiler Deaerator Unmonitored See Footnote1 See Footnote2 Stm. Gen. Atm. Stm. Dumps Unmonitored See Footnote1 See Footnote2 Plant Nitrogen System Unmonitored See Footnote1 See Footnote2 Turbine Bldg. Vent. Exh3 Unmonitored See Footnote1 See Footnote2 Emergency Air Lock Unmonitored See Footnote1 See Footnote2 Plant Compressed Air Unmonitored See Footnote1 See Footnote2 Main Steam Line Penetrations Unmonitored See Footnote1 See Footnote2 Steam Driven Auxiliary Feed Pumps Unmonitored See Footnote1 See Footnote2 Containment Equipment Hatch Unmonitored See Footnote1 See Footnote2 Refueling Water Tank Unmonitored See Footnote1 See Footnote2 Materials Processing Facility Unmonitored See Footnote1 See Footnote2 1 Since radioactive gaseous waste is not normally vented via this pathway, the determination of release type (i.e., continuous or batch) will be evaluated on a case-by-case basis.

2 Since radioactive gaseous waste is not normally vented via this pathway, the determination of discharge flow rate will be evaluated on a case-by-case basis.

3 Includes sources such as Gland Seal Exhaust.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 236 of 321 Level 3 - Information Attachment 9 Block Diagram of Gaseous Radioactive Waste Systems December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 237 of 321 Level 3 - Information Attachment 10 Noble Gas Dose Factors GAMMA BODY BETA SKIN DOSE GAMMA AIR DOSE BETA AIR DOSE DOSE NUCLIDE Li Mi Nj Ki (mrem/yr)/(µCi/m3) (mrad/yr)/(µCi/m3) (mrad/yr)/(µCi/m3)

(mrem/yr)/(µCi/m3)

Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 238 of 321 Level 3 - Information Attachment 11 Empirical Derivation Of Site-Specific Dose Factors The total body dose, the skin dose, and the air doses--resulting from gamma and beta emitting radionuclides in discharges of gaseous radwaste--are normally calculated using nuclide specific dose factors. However, these same doses may be estimated using empirically derived, site specific, dose factors as shown below.

TOTAL-BODY, GAMMA-DOSE FACTOR A site-specific, total-body, gamma-dose factor has been derived from historical data per the following equation.

Kavg = ( Ki ) ( f i ) Eq. 1F Kavg = the empirically derived, site-specific, total-body, gamma-dose factor due to all noble gases released during a specified time period Values of Kavg have been calculated using gaseous radwaste discharge data collected over several years.

The results of the calculations appear in the Table on page 5 of this attachment.

Ki = the total body dose factor due to gamma emissions for each identified noble gas radionuclide, i (mrem/yr per microcurie/cubic meter)

The total-body dose factors for gamma rays from noble gas radionuclides were obtained from Regulatory Guide 1.109, Appendix B, Table B-1.

The total-body dose factors for various noble gas radionuclides are tabulated in Attachment 10.

fi = a fraction which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitless)

This value has been calculated for all gaseous radwaste discharges for the years 1986, 1987, and 1988 per equation 3R on Attachment 5.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 239 of 321 Level 3 - Information Attachment 11 Empirical Derivation of Site-Specific Dose Factors SKIN, BETA-DOSE FACTOR A site-specific, skin, beta-dose factor has been derived from historical data per the following equation.

Lavg = ( Li ) ( f i ) Eq. 2F Lavg = The empirically derived, site-specific, skin, beta-dose factor due to all noble gases released during a specified time period Values of Lavg have been calculated using gaseous radwaste discharge data collected over several years.

The results of the calculations appear in the Table on page 5 of this attachment.

Li = The skin dose factor due to beta emissions for each identified noble gas radionuclide, i (mrem/yr per microcurie/cubic meter)

The beta skin dose factors have been obtained from Regulatory Guide 1.109, Appendix B, Table B-1.

The beta skin dose factors for various noble gas radionuclides are tabulated in Attachment 10.

fi = A fraction which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitless)

This value has been calculated for all gaseous radwaste discharges for the years 1986, 1987, and 1988 per equation 3R on Attachment 5.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 240 of 321 Level 3 - Information Attachment 11 Empirical Derivation of Site-Specific Dose Factors GAMMA-AIR-DOSE FACTOR A site-specific, gamma-air-dose factor has been derived from historical data per the following equation.

Mavg = ( M i ) ( fi ) Eq. 3F Mavg = The empirically derived, site-specific, gamma-air-dose factor due to all noble gases released during a specified time period Values of Mavg have been calculated using gaseous radwaste discharge data collected over several years.

The results of the calculations appear in the Table on page 5 of this attachment.

Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide, i (mrad/yr per microcurie/cubic meter)

The gamma air dose factors have been obtained from Regulatory Guide 1.109, Appendix B, Table B-1.

The gamma air dose factors for various noble gas radionuclides are tabulated in Attachment 10.

fi = A fraction which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitless)

This value has been calculated for all gaseous radwaste discharges for the years 1986, 1987, and 1988 per equation 3R on Attachment 5.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 241 of 321 Level 3 - Information Attachment 11 Empirical Derivation of Site-Specific Dose Factors BETA-AIR-DOSE FACTOR A site-specific, beta-air-dose factor has been derived from historical data per the following equation.

Navg = ( Ni ) ( f i ) Eq. 4F Navg = The empirically derived, site-specific, beta-air-dose factor due to all noble gases released during a specified time period Values of Navg have been calculated using gaseous radwaste discharge data collected over several years.

The results of the calculations appear in the Table on page 5 of this attachment.

Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide, i (mrad/yr per microcurie/cubic meter)

The beta air dose factors have been obtained from Regulatory Guide 1.109, Appendix B, Table B-1.

The beta air dose factors for various noble gas radionuclides are tabulated in Attachment 10.

fi = A fraction which represents the relative activity contribution of noble gas radionuclide i to the total noble gas activity for TYPICAL GASEOUS EFFLUENTS (unitless)

This value has been calculated for all gaseous radwaste discharges for the years 1986, 1987, and 1988 per equation 3R on Attachment 5.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 242 of 321 Level 3 - Information Attachment 11 Empirical Derivation of Site-Specific Dose Factors SITE-SPECIFIC, AVERAGE DOSE FACTORS Year Kavg Lavg Mavg Navg 1986 330 790 390 1100 1987 340 810 400 1100 1988 390 960 450 1200 Average 350 850 410 1100 Maximum % difference 11% 13% 10% 9%

As can be seen from the above table, the percent difference between the yearly dose factors and the 3-year average dose factors range from 9% to 13%. This variability is minor considering other areas of uncertainty inherent in the environmental dose calculation models.

It should be noted that the empirically-derived, site-specific, average dose factors listed in the above table shall only rarely be used. In those rare instances where empirically-derived, site-specific, average dose factors are used, the results shall be carefully evaluated by qualified members of the facility staff to ensure the estimated doses are only a small fraction of the Control limits. Additionally, the doses shall be recalculated using the RIGOROUS METHODS before submitting the Radioactive Effluent Release Report.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 243 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors The following formulas are used to derive the gaseous effluent dose factors for the following pathways:

Ground Plane Pathway:

(1 eit ) /

RiG k (k ")(SF) Daipj i Eq. 12-1 RiG D / Q = m2-mrem/yr per uCi/sec.

k' = 1E+06 pCi/uCi.

k" = 8760 hr/yr.

SF = shielding factor (0.7).

Daipj = dose factor for standing on contaminated ground (Reg. Guide 1.109 Table E-6).

i = decay constant for nuclide i in seconds.

t = period of buildup in soil in seconds (4.716E+08).

Vegetation Pathway:

t t RiV k Daipj U aL * ( f L )e (r) i L i h U aS * ( f g )e Yv i w

Eq. 12-2 where:

RiV = m2-mrem/yr per uCi/sec k = 1.0 E+6 pCi/uCi r = fraction of deposited particulates retained on vegetation (0.20).

r = fraction of deposited iodines retained on vegetation (1.0).

Yv = vegetation area density kg/m2 (2.0).

i = decay constant for the ith radionuclide, in sec-1.

w = decay constant for removal of activity on leaf and plant surfaces by weathering, in sec-1 (5.73E-07).

Daipj = ingestion dose factor, in mrem/pCi (Reg. Guide 1.109 Table E-11 -Table E-14).

ULa = consumption rate of fresh leafy vegetation by the receptor in age group (a), in kg/yr Adult (64.0)

Teenager (42.0)

Child (26.0) fL = fraction of the annual intake of fresh leafy vegetation grown locally (dimensionless) (1).

tL = average time between harvest of leafy vegetation and its consumption, in seconds (8.64E+04).

USa = consumption rate of stored vegetation by the receptor in age group (a), in kg/yr.

Adult (520.0)

Teenager (630.0)

Child (520.0) fg = fraction of the annual intake of stored vegetation grown locally (dimensionless) (0.76).

th = average time between harvest of stored vegetation and its consumption, in seconds (7.78E+06).

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 244 of 321 Level 3 - Information The concentrations of tritium and carbon-14 in vegetation are based on their airborne concentrations rather than their deposition. Therefore, the Ri is based on [x/Q] as follows:

RV (k' ) (k' ") UL (f ) US (f ) D 0.75 (0.5/H)

H -3 a L a g aipj Eq. 12-3 R CV-14 (k' ) (k' " ) U L (f ) US (f ) D p 0.11 0.16 a L a g aipj Eq. 12-4 where:

RHV 3 = mrem/yr per uCi/m3.

V R C 14 = mrem/yr per uCi/m3.

k' " = 1E+03, constant of unit conversion (gm/kg).

H = absolute humidity of the atmosphere, in gm/m3 (8.0).

0.75 = fraction of total feed that is water.

0.5 = ratio of the specific activity of the feed grass water to the atmospheric water.

P = fractional equilibrium ratio (4400 hrs/8760 hrs). The ratio of the total annual releae time (for C-

14) atmospheric releases) to the total annual time during photosynthesis occurs (taken to be 4400 hrs), under the condition that the value of p should never exceed unity. For continuous C-14 releases, p is taken to be unity.

0.11 = the fraction of total plant mass that is natural carbon, dimensionless.

0.16 = the concentration of natural carbon in the atmosphere, in g/m3 All other values as previously defined above.

Cow Milk / Goat Milk / Meat Pathway Q UAP fp fs (1 fp fs)eith itf k

F RMi (Fm) (r) Daipj e i

w Yp Ys Eq. 12-5 where:

RMi = m2-mrem/yr per uCi/sec.

k' = 1.0E+6 pCi/uCi.

QF = meat/cow/goat consumption rate kg/day (wet weight).

Meat (50.0)

Cow (50.0)

Goat (6.0)

UAP = receptor's milk consumption rate or meat consumption rate for age (a), in liters/yr or kg/yr.

Age Group Beef Kg/y Cow L/yr Goat L/yr Adult 110.0 310.0 310.0 Teenager 65.0 400.0 400.0 Child 41.0 330.0 330.0 Infant 0.0 330.0 330.0 i

= decay constant for the ith radionuclide, in sec-1.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 245 of 321 Level 3 - Information w

= decay constant for removal of activity on leaf and plant surfaces by weathering, in sec-1 (5.73E-07).

Fm = stable element transfer coefficients in days/liter or days/kg (Reg. Guide 1.109 Table E-1, E-2).

r = fraction of deposited particulates retained on vegetation (0.20).

r = fraction of deposited iodines retained on vegetation (1.0).

Daipj = ingestion dose factor, in mrem/pCi (Reg. Guide 1.109 Table E-11 -Table E-14).

fp = fraction of the year that the cow/goat is on pasture (dimensionless) (1).

fs = fraction of the cow/goat feed that is pasture grass while the animal is on pasture (dimensionless) (1).

Yp = agricultural productivity by unit area of pasture feed grass, in kg/m2 (0.7).

Ys = agricultural productivity by unit area of stored feed, in kg/m2 (2.0).

Th (milk) = transport time from pasture to harvest, to milk animal, to milk, to receptor, in sec (7.78E+06).

Tf (milk) = transport time from pasture to milk animal, to milk, to receptor, in sec (1.73E+05).

Th (meat) = transport time from crop field to ingestion receptor, in sec (7.78E+06).

Tf (meat) = transport time from pasture to ingestion receptor, in sec (1.73E+05).

The concentrations of tritium and carbon-14 in milk and meat are based on their airborne concentration rather than their deposition. Therefore, the Ri is based on [x/Q] as follows:

RM H3 (k ') (k '") Fm QF Uap Daipj 0.75 (0.5 / H)

Eq. 12-6 R M tC14 (k ') (k '") Fm QF Uap Daipj p

  • 0.11/ 0.16 Eq. 12-7 where:

RM H3 = mrem/yr per uCi/m3 M

R C14 = mrem/yr per uCi/m3 All other values as previously defined above.

Inhalation Pathway:

RiI = k' (BR) (Daipj) Eq. 12-8 where:

RiI = mrem/yr per uCi/m3.

k' = 1.0E+6 unit conversion pCi/uCi.

BR = breathing rate m3/yr:

Adult (8760)

Teenager (8000)

Child (8000)

Infant (3700)

Daipj = Inhalation Dose Factor (Reg. Guide 1.109 Table E-7 -Table E-10).

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 246 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS ADULT (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 3.250E+02 3.250E+02 3.250E+02 3.250E+02 3.250E+02 3.250E+02 C-14 3.330E+05 6.660E+04 6.660E+04 6.660E+04 6.660E+04 6.660E+04 6.660E+04 NA-24 1.840E-03 1.840E-03 1.840E-03 1.840E-03 1.840E-03 1.840E-03 1.840E-03 P-32 4.650E+09 2.890E+08 1.800E+08 0.000E+00 0.000E+00 0.000E+00 5.230E+08 CR-51 0.000E+00 0.000E+00 7.070E+03 4.220E+03 1.560E+03 9.380E+03 1.780E+06 MN-54 0.000E+00 9.150E+06 1.750E+06 0.000E+00 2.720E+06 0.000E+00 2.800E+07 MN-56 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-55 2.930E+08 2.020E+08 4.720E+07 0.000E+00 0.000E+00 1.130E+08 1.160E+08 FE-59 2.670E+08 6.270E+08 2.400E+08 0.000E+00 0.000E+00 1.750E+08 2.090E+09 CO-57 0.000E+00 5.640E+06 9.370E+06 0.000E+00 0.000E+00 0.000E+00 1.430E+08 CO-58 0.000E+00 1.830E+07 4.100E+07 0.000E+00 0.000E+00 0.000E+00 3.700E+08 CO-60 0.000E+00 7.520E+07 1.660E+08 0.000E+00 0.000E+00 0.000E+00 1.410E+09 NI-63 1.890E+10 1.310E+09 6.330E+08 0.000E+00 0.000E+00 0.000E+00 2.730E+08 NI-65 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CU-64 0.000E+00 2.950E-07 1.390E-07 0.000E+00 7.450E-07 0.000E+00 2.520E-05 ZN-65 3.560E+08 1.130E+09 5.120E+08 0.000E+00 7.570E+08 0.000E+00 7.130E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 4.870E+08 2.270E+08 0.000E+00 0.000E+00 0.000E+00 9.600E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 3.010E+08 0.000E+00 8.650E+06 0.000E+00 0.000E+00 0.000E+00 4.840E+07 SR-90 1.240E+10 0.000E+00 3.050E+09 0.000E+00 0.000E+00 0.000E+00 3.590E+08 SR-91 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.380E-09 SR-92 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-90 1.070E+02 0.000E+00 2.860E+00 0.000E+00 0.000E+00 0.000E+00 1.130E+06 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 1.130E+06 0.000E+00 3.030E+04 0.000E+00 0.000E+00 0.000E+00 6.240E+08 Y-92 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-93 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.080E-07 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 247 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS ADULT (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract ZR-95 1.880E+06 6.040E+05 4.090E+05 0.000E+00 9.480E+05 0.000E+00 1.910E+09 ZR-97 1.830E-05 3.690E-06 1.690E-06 0.000E+00 5.580E-06 0.000E+00 1.140E+00 NB-95 2.290E+06 1.280E+06 6.860E+05 0.000E+00 1.260E+06 0.000E+00 7.750E+09 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 MO-99 0.000E+00 1.090E+05 2.070E+04 0.000E+00 2.460E+05 0.000E+00 2.520E+05 TC-99M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 1.060E+08 0.000E+00 4.550E+07 0.000E+00 4.030E+08 0.000E+00 1.230E+10 RU-105 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-106 2.800E+09 0.000E+00 3.540E+08 0.000E+00 5.400E+09 0.000E+00 1.810E+11 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 6.690E+06 6.190E+06 3.670E+06 0.000E+00 1.220E+07 0.000E+00 2.520E+09 SB-122 5.580E+03 5.820E+03 7.050E+04 9.250E+02 2.750E+03 1.200E+03 6.930E+05 SB-124 1.980E+09 3.740E+07 7.850E+08 4.800E+06 0.000E+00 1.540E+09 5.620E+10 SB-125 1.910E+09 2.130E+07 4.540E+08 1.940E+06 0.000E+00 1.470E+09 2.100E+10 TE-125M 3.590E+08 1.300E+08 4.810E+07 1.080E+08 1.460E+09 0.000E+00 1.430E+09 TE-127M 1.120E+09 3.990E+08 1.360E+08 2.850E+08 4.530E+09 0.000E+00 3.740E+09 TE-127 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.090E-09 0.000E+00 2.100E-08 TE-129M 1.140E+09 4.270E+08 1.810E+08 3.930E+08 4.770E+09 0.000E+00 5.760E+09 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 4.510E+02 2.210E+02 1.840E+02 3.500E+02 2.240E+03 0.000E+00 2.190E+04 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 1.400E+06 9.070E+05 8.510E+05 1.000E+06 8.730E+06 0.000E+00 4.290E+07 I-130 2.350E-06 6.940E-06 2.740E-06 5.880E-04 1.080E-05 0.000E+00 5.980E-06 I-131 1.080E+07 1.540E+07 8.830E+06 5.050E+09 2.640E+07 0.000E+00 4.070E+06 I-132 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-133 4.300E-01 7.470E-01 2.280E-01 1.100E+02 1.300E+00 0.000E+00 6.720E-01 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CS-134 6.570E+08 1.560E+09 1.280E+09 0.000E+00 5.060E+08 1.680E+08 2.740E+07 CS-136 1.180E+07 4.670E+07 3.360E+07 0.000E+00 2.600E+07 3.560E+06 5.300E+06 CS-137 8.720E+08 1.190E+09 7.810E+08 0.000E+00 4.050E+08 1.350E+08 2.310E+07 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 248 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS ADULT (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BA-139 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-140 2.880E+07 3.610E+04 1.890E+06 0.000E+00 1.230E+04 2.070E+04 5.920E+07 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 3.600E-02 1.810E-02 4.790E-03 0.000E+00 0.000E+00 0.000E+00 1.330E+03 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CE-141 1.400E+04 9.480E+03 1.080E+03 0.000E+00 4.400E+03 0.000E+00 3.620E+07 CE-143 2.090E-02 1.550E+01 1.710E-03 0.000E+00 6.800E-03 0.000E+00 5.780E+02 CE-144 1.460E+06 6.090E+05 7.830E+04 0.000E+00 3.610E+05 0.000E+00 4.930E+08 PR-143 2.130E+04 8.540E+03 1.060E+03 0.000E+00 4.930E+03 0.000E+00 9.330E+07 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 7.080E+03 8.180E+03 4.900E+02 0.000E+00 4.780E+03 0.000E+00 3.930E+07 EU-154 8.030E+06 9.870E+08 7.020E+05 0.000E+00 4.720E+06 0.000E+00 7.150E+08 EU-155 1.110E+06 1.580E+05 1.020E+05 0.000E+00 7.300E+05 0.000E+00 1.240E+08 W-187 2.160E-02 1.810E-02 6.320E-03 0.000E+00 0.000E+00 0.000E+00 5.920E+00 NP-239 2.560E-01 2.510E-02 1.390E-02 0.000E+00 7.840E-02 0.000E+00 5.150E+03 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 249 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS TEEN (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 1.940E+02 1.940E+02 1.940E+02 1.940E+02 1.940E+02 1.940E+02 C-14 2.810E+05 5.620E+04 5.620E+04 5.620E+04 5.620E+04 5.620E+04 5.620E+04 NA-24 1.470E-03 1.470E-03 1.470E-03 1.470E-03 1.470E-03 1.470E-03 1.470E-03 P-32 3.930E+09 2.440E+08 1.520E+08 0.000E+00 0.000E+00 0.000E+00 3.300E+08 CR-51 0.000E+00 0.000E+00 5.650E+03 3.140E+03 1.240E+03 8.070E+03 9.500E+05 MN-54 0.000E+00 6.980E+06 1.380E+06 0.000E+00 2.080E+06 0.000E+00 1.430E+07 MN-56 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-55 2.380E+08 1.690E+08 3.930E+07 0.000E+00 0.000E+00 1.070E+08 7.300E+07 FE-59 2.130E+08 4.980E+08 1.920E+08 0.000E+00 0.000E+00 1.570E+08 1.180E+09 CO-57 0.000E+00 4.530E+06 7.590E+06 0.000E+00 0.000E+00 0.000E+00 8.450E+07 CO-58 0.000E+00 1.410E+07 3.250E+07 0.000E+00 0.000E+00 0.000E+00 1.940E+08 CO-60 0.000E+00 5.830E+07 1.310E+08 0.000E+00 0.000E+00 0.000E+00 7.600E+08 NI-63 1.520E+10 1.070E+09 5.150E+08 0.000E+00 0.000E+00 0.000E+00 1.710E+08 NI-65 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CU-64 0.000E+00 2.410E-07 1.130E-07 0.000E+00 6.100E-07 0.000E+00 1.870E-05 ZN-65 2.500E+08 8.690E+08 4.050E+08 0.000E+00 5.560E+08 0.000E+00 3.680E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 4.060E+08 1.910E+08 0.000E+00 0.000E+00 0.000E+00 6.010E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 2.540E+08 0.000E+00 7.290E+06 0.000E+00 0.000E+00 0.000E+00 3.030E+07 SR-90 8.050E+09 0.000E+00 1.990E+09 0.000E+00 0.000E+00 0.000E+00 2.260E+08 SR-91 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.100E-09 SR-92 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-90 8.980E+01 0.000E+00 2.420E+00 0.000E+00 0.000E+00 0.000E+00 7.400E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 9.560E+05 0.000E+00 2.560E+04 0.000E+00 0.000E+00 0.000E+00 3.920E+08 Y-92 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-93 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.690E-07 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 250 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS TEEN (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract ZR-95 1.510E+06 4.760E+05 3.270E+05 0.000E+00 6.990E+05 0.000E+00 1.100E+09 ZR-97 1.530E-05 3.020E-06 1.390E-06 0.000E+00 4.580E-06 0.000E+00 8.180E-01 NB-95 1.790E+06 9.940E+05 5.470E+05 0.000E+00 9.640E+05 0.000E+00 4.250E+09 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 MO-99 0.000E+00 8.980E+04 1.710E+04 0.000E+00 2.060E+05 0.000E+00 1.610E+05 TC-99M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 8.600E+07 0.000E+00 3.680E+07 0.000E+00 3.030E+08 0.000E+00 7.180E+09 RU-105 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-106 2.360E+09 0.000E+00 2.970E+08 0.000E+00 4.550E+09 0.000E+00 1.130E+11 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 5.060E+06 4.790E+06 2.910E+06 0.000E+00 9.140E+06 0.000E+00 1.350E+09 SB-122 3.300E+03 3.440E+03 4.170E+04 5.460E+02 1.620E+03 7.080E+02 4.100E+05 SB-124 1.620E+09 2.980E+07 6.310E+08 3.670E+06 0.000E+00 1.410E+09 3.260E+10 SB-125 1.560E+09 1.710E+07 3.660E+08 1.490E+06 0.000E+00 1.370E+09 1.220E+10 TE-125M 3.030E+08 1.090E+08 4.050E+07 8.470E+07 0.000E+00 0.000E+00 8.940E+08 TE-127M 9.410E+08 3.340E+08 1.120E+08 2.240E+08 3.820E+09 0.000E+00 2.350E+09 TE-127 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.750E-08 TE-129M 9.580E+08 3.560E+08 1.520E+08 3.090E+08 4.010E+09 0.000E+00 3.600E+09 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 3.760E+02 1.800E+02 1.500E+02 2.710E+02 1.880E+03 0.000E+00 1.450E+04 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 1.150E+06 7.260E+05 6.840E+05 7.660E+05 6.970E+06 0.000E+00 2.300E+07 I-130 1.890E-06 5.480E-06 2.190E-06 4.470E-04 8.440E-06 0.000E+00 4.210E-06 I-131 8.950E+06 1.250E+07 6.730E+06 3.660E+09 2.160E+07 0.000E+00 2.480E+06 I-132 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-133 3.590E-01 6.100E-01 1.860E-01 8.510E+01 1.070E+00 0.000E+00 4.610E-01 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CS-134 5.230E+08 1.230E+09 5.710E+08 0.000E+00 3.910E+08 1.490E+08 1.530E+07 CS-136 9.220E+06 3.630E+07 2.440E+07 0.000E+00 1.970E+07 3.110E+06 2.920E+06 CS-137 7.240E+08 9.630E+08 3.360E+08 0.000E+00 3.280E+08 1.270E+08 1.370E+07 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 251 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS TEEN (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BA-139 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-140 2.380E+07 2.910E+04 1.530E+06 0.000E+00 9.880E+03 1.960E+04 3.670E+07 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 2.960E-02 1.450E-02 3.870E-03 0.000E+00 0.000E+00 0.000E+00 8.350E+02 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CE-141 1.180E+04 7.860E+03 9.030E+02 0.000E+00 3.700E+03 0.000E+00 2.250E+07 CE-143 1.760E-02 1.280E+01 1.430E-03 0.000E+00 5.740E-03 0.000E+00 3.850E+02 CE-144 1.230E+06 5.080E+05 6.600E+04 0.000E+00 3.040E+05 0.000E+00 3.090E+08 PR-143 1.790E+04 7.150E+03 8.920E+02 0.000E+00 4.160E+03 0.000E+00 5.900E+07 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 6.240E+03 6.790E+03 4.060E+02 0.000E+00 3.980E+03 0.000E+00 2.450E+07 EU-154 6.090E+06 7.870E+05 5.540E+05 0.000E+00 3.520E+06 0.000E+00 4.160E+08 EU-155 1.330E+06 1.290E+05 7.970E+04 0.000E+00 5.030E+05 0.000E+00 7.380E+08 W-187 1.810E-02 1.480E-02 5.170E-03 0.000E+00 0.000E+00 0.000E+00 3.990E+00 NP-239 2.230E-01 2.110E-02 1.170E-02 0.000E+00 6.610E-02 0.000E+00 3.390E+03 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 252 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS CHILD (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 2.340E+02 2.340E+02 2.340E+02 2.340E+02 2.340E+02 2.340E+02 C-14 5.290E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 NA-24 2.340E-03 2.340E-03 2.340E-03 2.340E-03 2.340E-03 2.340E-03 2.340E-03 P-32 7.410E+09 3.470E+08 2.860E+08 0.000E+00 0.000E+00 0.000E+00 2.050E+08 CR-51 0.000E+00 0.000E+00 8.810E+03 4.890E+03 1.340E+03 8.930E+03 4.670E+05 MN-54 0.000E+00 7.990E+06 2.130E+06 0.000E+00 2.240E+06 0.000E+00 6.700E+06 MN-56 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-55 4.570E+08 2.420E+08 7.510E+07 0.000E+00 0.000E+00 1.370E+08 4.490E+07 FE-59 3.780E+08 6.120E+08 3.050E+08 0.000E+00 0.000E+00 1.770E+08 6.370E+08 CO-57 0.000E+00 5.920E+06 1.200E+07 0.000E+00 0.000E+00 0.000E+00 4.850E+07 CO-58 0.000E+00 1.650E+07 5.040E+07 0.000E+00 0.000E+00 0.000E+00 9.600E+07 CO-60 0.000E+00 6.930E+07 2.040E+08 0.000E+00 0.000E+00 0.000E+00 3.840E+08 NI-63 2.910E+10 1.560E+09 9.910E+08 0.000E+00 0.000E+00 0.000E+00 1.050E+08 NI-65 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CU-64 0.000E+00 3.240E-07 1.960E-07 0.000E+00 7.820E-07 0.000E+00 1.520E-05 ZN-65 3.750E+08 1.000E+09 6.220E+08 0.000E+00 6.300E+08 0.000E+00 1.760E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 5.760E+08 3.540E+08 0.000E+00 0.000E+00 0.000E+00 3.710E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 4.820E+08 0.000E+00 1.380E+07 0.000E+00 0.000E+00 0.000E+00 1.860E+07 SR-90 1.040E+10 0.000E+00 2.640E+09 0.000E+00 0.000E+00 0.000E+00 1.400E+08 SR-91 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.010E-09 SR-92 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-90 1.700E+02 0.000E+00 4.550E+00 0.000E+00 0.000E+00 0.000E+00 4.840E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 1.810E+06 0.000E+00 4.830E+04 0.000E+00 0.000E+00 0.000E+00 2.410E+08 Y-92 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-93 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.550E-07 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 253 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS CHILD (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract ZR-95 2.680E+06 5.890E+05 5.240E+05 0.000E+00 8.430E+05 0.000E+00 6.140E+08 ZR-97 2.840E-05 4.100E-06 2.420E-06 0.000E+00 5.890E-06 0.000E+00 6.210E-01 NB-95 3.090E+06 1.200E+06 8.610E+05 0.000E+00 1.130E+06 0.000E+00 2.230E+09 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 MO-99 0.000E+00 1.250E+05 3.090E+04 0.000E+00 2.670E+05 0.000E+00 1.030E+05 TC-99M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 1.560E+08 0.000E+00 5.980E+07 0.000E+00 3.920E+08 0.000E+00 4.020E+09 RU-105 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-106 4.440E+09 0.000E+00 5.540E+08 0.000E+00 5.990E+09 0.000E+00 6.900E+10 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 8.400E+06 5.670E+06 4.530E+06 0.000E+00 1.060E+07 0.000E+00 6.750E+08 SB-122 2.080E+03 2.170E+03 2.630E+04 3.450E+02 1.020E+03 4.460E+02 2.580E+05 SB-124 2.930E+09 3.800E+07 1.030E+09 6.460E+06 0.000E+00 1.620E+09 1.830E+10 SB-125 2.850E+09 2.190E+07 5.960E+08 2.640E+06 0.000E+00 1.590E+09 6.800E+09 TE-125M 5.690E+08 1.540E+08 7.590E+07 1.600E+08 0.000E+00 0.000E+00 5.490E+08 TE-127M 1.770E+09 4.780E+08 2.110E+08 4.240E+08 5.060E+09 0.000E+00 1.440E+09 TE-127 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.210E-09 0.000E+00 1.660E-08 TE-129M 1.810E+09 5.040E+08 2.800E+08 5.820E+08 5.300E+09 0.000E+00 2.200E+09 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 7.000E+02 2.420E+02 2.580E+02 4.980E+02 2.340E+03 0.000E+00 9.820E+03 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 2.090E+06 9.270E+05 1.120E+06 1.350E+06 8.600E+06 0.000E+00 9.330E+06 I-130 3.390E-06 6.850E-06 3.530E-06 7.540E-04 1.020E-05 0.000E+00 3.200E-06 I-131 1.660E+07 1.670E+07 9.490E+06 5.520E+09 2.740E+07 0.000E+00 1.490E+06 I-132 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-133 6.680E-01 8.260E-01 3.120E-01 1.530E+02 1.380E+00 0.000E+00 3.330E-01 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CS-134 9.220E+08 1.510E+09 3.190E+08 0.000E+00 4.690E+08 1.680E+08 8.150E+06 CS-136 1.590E+07 4.370E+07 2.830E+07 0.000E+00 2.330E+07 3.470E+06 1.540E+06 CS-137 1.330E+09 1.280E+09 1.880E+08 0.000E+00 4.160E+08 1.500E+08 7.990E+06 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 254 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS CHILD (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BA-139 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-140 4.390E+07 3.850E+04 2.560E+06 0.000E+00 1.250E+04 2.290E+04 2.220E+07 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 5.410E-02 1.890E-02 6.380E-03 0.000E+00 0.000E+00 0.000E+00 5.270E+02 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CE-141 2.220E+04 1.110E+04 1.640E+03 0.000E+00 4.840E+03 0.000E+00 1.380E+07 CE-143 3.300E-02 1.790E+01 2.590E-03 0.000E+00 7.510E-03 0.000E+00 2.620E+02 CE-144 2.320E+06 7.260E+05 1.240E+05 0.000E+00 4.020E+05 0.000E+00 1.890E+08 PR-143 3.390E+04 1.020E+04 1.680E+03 0.000E+00 5.510E+03 0.000E+00 3.660E+07 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 1.170E+04 9.480E+03 7.340E+02 0.000E+00 5.200E+03 0.000E+00 1.500E+07 EU-154 1.120E+07 1.010E+06 9.190E+05 0.000E+00 4.420E+06 0.000E+00 2.340E+08 EU-155 2.330E+06 1.680E+05 1.310E+05 0.000E+00 6.280E+05 0.000E+00 4.200E+08 W-187 3.360E-02 1.990E-02 8.920E-03 0.000E+00 0.000E+00 0.000E+00 2.790E+00 NP-239 4.200E-01 3.020E-02 2.120E-02 0.000E+00 8.730E-02 0.000E+00 2.230E+03 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 255 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MEAT DOSE FACTORS INFANT (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract THIS PATHWAY IS NOT APPLICABLE TABLE INTENTIONALLY LEFT BLANK December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 256 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors VEGETATION DOSE FACTORS ADULT (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 2.260E+03 2.260E+03 2.260E+03 2.260E+03 2.260E+03 2.260E+03 C-14 8.970E+05 1.790E+05 1.790E+05 1.790E+05 1.790E+05 1.790E+05 1.790E+05 NA-24 2.760E+05 2.760E+05 2.760E+05 2.760E+05 2.760E+05 2.760E+05 2.760E+05 P-32 1.400E+09 8.730E+07 5.420E+07 0.000E+00 0.000E+00 0.000E+00 1.580E+08 CR-51 0.000E+00 0.000E+00 4.660E+04 2.790E+04 1.030E+04 6.190E+04 1.170E+07 MN-54 0.000E+00 3.110E+08 5.940E+07 0.000E+00 9.270E+07 0.000E+00 9.540E+08 MN-56 0.000E+00 1.610E+01 2.850E+00 0.000E+00 2.040E+01 0.000E+00 5.130E+02 FE-55 2.090E+08 1.450E+08 3.370E+07 0.000E+00 0.000E+00 8.060E+07 8.290E+07 FE-59 1.270E+08 2.990E+08 1.140E+08 0.000E+00 0.000E+00 8.350E+07 9.960E+08 CO-57 0.000E+00 1.170E+07 1.950E+07 0.000E+00 0.000E+00 0.000E+00 2.970E+08 CO-58 0.000E+00 3.090E+07 6.920E+07 0.000E+00 0.000E+00 0.000E+00 6.260E+08 CO-60 0.000E+00 1.670E+08 3.690E+08 0.000E+00 0.000E+00 0.000E+00 3.140E+09 NI-63 1.040E+10 7.210E+08 3.490E+08 0.000E+00 0.000E+00 0.000E+00 1.500E+08 NI-65 6.150E+01 7.990E+00 3.650E+00 0.000E+00 0.000E+00 0.000E+00 2.030E+02 CU-64 0.000E+00 9.270E+03 4.350E+03 0.000E+00 2.340E+04 0.000E+00 7.900E+05 ZN-65 3.170E+08 1.010E+09 4.560E+08 0.000E+00 6.750E+08 0.000E+00 6.360E+08 ZN-69 8.750E-06 1.670E-05 1.160E-06 0.000E+00 1.090E-05 0.000E+00 2.510E-06 BR-82 0.000E+00 0.000E+00 1.510E+06 0.000E+00 0.000E+00 0.000E+00 1.730E+06 BR-83 0.000E+00 0.000E+00 3.210E+00 0.000E+00 0.000E+00 0.000E+00 4.630E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.190E+08 1.020E+08 0.000E+00 0.000E+00 0.000E+00 4.320E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 9.960E+09 0.000E+00 2.860E+08 0.000E+00 0.000E+00 0.000E+00 1.600E+09 SR-90 6.050E+11 0.000E+00 1.480E+11 0.000E+00 0.000E+00 0.000E+00 1.750E+10 SR-91 3.200E+05 0.000E+00 1.290E+04 0.000E+00 0.000E+00 0.000E+00 1.520E+06 SR-92 4.270E+02 0.000E+00 1.850E+01 0.000E+00 0.000E+00 0.000E+00 8.460E+03 Y-90 1.330E+04 0.000E+00 3.560E+02 0.000E+00 0.000E+00 0.000E+00 1.410E+08 Y-91M 5.830E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.710E-08 Y-91 5.130E+06 0.000E+00 1.370E+05 0.000E+00 0.000E+00 0.000E+00 2.820E+09 Y-92 9.010E-01 0.000E+00 2.630E-02 0.000E+00 0.000E+00 0.000E+00 1.580E+04 Y-93 1.740E+02 0.000E+00 4.800E+00 0.000E+00 0.000E+00 0.000E+00 5.520E+06 December 2018

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Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract ZR-95 1.190E+06 3.810E+05 2.580E+05 0.000E+00 5.970E+05 0.000E+00 1.210E+09 ZR-97 3.330E+02 6.730E+01 3.080E+01 0.000E+00 1.020E+02 0.000E+00 2.080E+07 NB-95 1.420E+05 7.910E+04 4.250E+04 0.000E+00 7.810E+04 0.000E+00 4.800E+08 NB-97 2.900E-06 7.340E-07 2.680E-07 0.000E+00 8.560E-07 0.000E+00 2.710E-03 MO-99 0.000E+00 6.250E+06 1.190E+06 0.000E+00 1.410E+07 0.000E+00 1.450E+07 TC-99M 3.060E+00 8.660E+00 1.100E+02 0.000E+00 1.320E+02 4.240E+00 5.120E+03 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 4.800E+06 0.000E+00 2.070E+06 0.000E+00 1.830E+07 0.000E+00 5.610E+08 RU-105 5.390E+01 0.000E+00 2.130E+01 0.000E+00 6.960E+02 0.000E+00 3.300E+04 RU-106 1.930E+08 0.000E+00 2.440E+07 0.000E+00 3.720E+08 0.000E+00 1.250E+10 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 1.060E+07 9.760E+06 5.800E+06 0.000E+00 1.920E+07 0.000E+00 3.980E+09 SB-122 7.500E+05 7.820E+05 9.470E+06 1.240E+05 3.690E+05 1.610E+05 9.320E+07 SB-124 1.040E+08 1.960E+06 4.110E+07 2.520E+05 0.000E+00 8.080E+07 2.950E+09 SB-125 1.360E+08 1.520E+06 3.250E+07 1.390E+05 0.000E+00 1.050E+08 1.500E+09 TE-125M 9.660E+07 3.500E+07 1.290E+07 2.900E+07 3.930E+08 0.000E+00 3.860E+08 TE-127M 3.490E+08 1.250E+08 4.260E+07 8.920E+07 1.420E+09 0.000E+00 1.170E+09 TE-127 5.760E+03 2.070E+03 1.250E+03 4.270E+03 2.350E+04 0.000E+00 4.540E+05 TE-129M 2.550E+08 9.500E+07 4.030E+07 8.750E+07 1.060E+09 0.000E+00 1.280E+09 TE-129 6.650E-04 2.500E-04 1.620E-04 5.100E-04 2.790E-03 0.000E+00 5.020E-04 TE-131M 9.120E+05 4.460E+05 3.720E+05 7.060E+05 4.520E+06 0.000E+00 4.430E+07 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 4.290E+06 2.770E+06 2.600E+06 3.060E+06 2.670E+07 0.000E+00 1.310E+08 I-130 3.960E+05 1.170E+06 4.610E+05 9.900E+07 1.820E+06 0.000E+00 1.010E+06 I-131 8.090E+07 1.160E+08 6.630E+07 3.790E+10 1.980E+08 0.000E+00 3.050E+07 I-132 5.740E+01 1.540E+02 5.380E+01 5.380E+03 2.450E+02 0.000E+00 2.890E+01 I-133 2.120E+06 3.690E+06 1.120E+06 5.420E+08 6.440E+06 0.000E+00 3.310E+06 I-134 1.060E-04 2.880E-04 1.030E-04 5.000E-03 4.590E-04 0.000E+00 2.510E-07 I-135 4.080E+04 1.070E+05 3.940E+04 7.040E+06 1.710E+05 0.000E+00 1.210E+05 CS-134 4.660E+09 1.110E+10 9.070E+09 0.000E+00 3.590E+09 1.190E+09 1.940E+08 CS-136 4.200E+07 1.660E+08 1.190E+08 0.000E+00 9.240E+07 1.270E+07 1.890E+07 CS-137 6.360E+09 8.700E+09 5.700E+09 0.000E+00 2.950E+09 9.810E+08 1.680E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 December 2018

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Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BA-139 2.950E-02 2.100E-05 8.640E-04 0.000E+00 1.960E-05 1.190E-05 5.230E-02 BA-140 1.290E+08 1.620E+05 8.430E+06 0.000E+00 5.490E+04 9.250E+04 2.650E+08 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 1.970E+03 9.920E+02 2.620E+02 0.000E+00 0.000E+00 0.000E+00 7.280E+07 LA-142 1.400E-04 6.350E-05 1.580E-05 0.000E+00 0.000E+00 0.000E+00 4.640E-01 CE-141 1.960E+05 1.330E+05 1.510E+04 0.000E+00 6.170E+04 0.000E+00 5.080E+08 CE-143 1.000E+03 7.420E+05 8.210E+01 0.000E+00 3.260E+02 0.000E+00 2.770E+07 CE-144 3.290E+07 1.380E+07 1.770E+06 0.000E+00 8.160E+06 0.000E+00 1.110E+10 PR-143 6.340E+04 2.540E+04 3.140E+03 0.000E+00 1.470E+04 0.000E+00 2.780E+08 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 3.340E+04 3.860E+04 2.310E+03 0.000E+00 2.250E+04 0.000E+00 1.850E+08 EU-154 4.850E+07 5.970E+06 4.250E+06 0.000E+00 2.860E+07 0.000E+00 4.320E+09 EU-155 6.710E+06 9.510E+05 6.140E+05 0.000E+00 4.390E+06 0.000E+00 7.490E+08 W-187 3.820E+04 3.190E+04 1.120E+04 0.000E+00 0.000E+00 0.000E+00 1.050E+07 NP-239 1.420E+03 1.400E+02 7.720E+01 0.000E+00 4.370E+02 0.000E+00 2.870E+07 December 2018

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Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 2.590E+03 2.590E+03 2.590E+03 2.590E+03 2.590E+03 2.590E+03 C-14 1.450E+06 2.910E+05 2.910E+05 2.910E+05 2.910E+05 2.910E+05 2.910E+05 NA-24 2.450E+05 2.450E+05 2.450E+05 2.450E+05 2.450E+05 2.450E+05 2.450E+05 P-32 1.610E+09 9.960E+07 6.230E+07 0.000E+00 0.000E+00 0.000E+00 1.350E+08 CR-51 0.000E+00 0.000E+00 6.200E+04 3.440E+04 1.360E+04 8.850E+04 1.040E+07 MN-54 0.000E+00 4.520E+08 8.970E+07 0.000E+00 1.350E+08 0.000E+00 9.270E+08 MN-56 0.000E+00 1.450E+01 2.580E+00 0.000E+00 1.830E+01 0.000E+00 9.540E+02 FE-55 3.250E+08 2.310E+08 5.380E+07 0.000E+00 0.000E+00 1.460E+08 9.980E+07 FE-59 1.810E+08 4.220E+08 1.630E+08 0.000E+00 0.000E+00 1.330E+08 9.980E+08 CO-57 0.000E+00 1.790E+07 3.000E+07 0.000E+00 0.000E+00 0.000E+00 3.340E+08 CO-58 0.000E+00 4.380E+07 1.010E+08 0.000E+00 0.000E+00 0.000E+00 6.040E+08 CO-60 0.000E+00 2.490E+08 5.600E+08 0.000E+00 0.000E+00 0.000E+00 3.240E+09 NI-63 1.610E+10 1.130E+09 5.450E+08 0.000E+00 0.000E+00 0.000E+00 1.810E+08 NI-65 5.730E+01 7.320E+00 3.330E+00 0.000E+00 0.000E+00 0.000E+00 3.970E+02 CU-64 0.000E+00 8.400E+03 3.950E+03 0.000E+00 2.120E+04 0.000E+00 6.510E+05 ZN-65 4.240E+08 1.470E+09 6.860E+08 0.000E+00 9.410E+08 0.000E+00 6.230E+08 ZN-69 8.190E-06 1.560E-05 1.090E-06 0.000E+00 1.020E-05 0.000E+00 2.880E-05 BR-82 0.000E+00 0.000E+00 1.330E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 3.010E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.730E+08 1.280E+08 0.000E+00 0.000E+00 0.000E+00 4.050E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 1.510E+10 0.000E+00 4.330E+08 0.000E+00 0.000E+00 0.000E+00 1.800E+09 SR-90 7.510E+11 0.000E+00 1.850E+11 0.000E+00 0.000E+00 0.000E+00 2.110E+10 SR-91 2.990E+05 0.000E+00 1.190E+04 0.000E+00 0.000E+00 0.000E+00 1.360E+06 SR-92 3.970E+02 0.000E+00 1.690E+01 0.000E+00 0.000E+00 0.000E+00 1.010E+04 Y-90 1.240E+04 0.000E+00 3.340E+02 0.000E+00 0.000E+00 0.000E+00 1.020E+08 Y-91M 5.430E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.560E-07 Y-91 7.870E+06 0.000E+00 2.110E+05 0.000E+00 0.000E+00 0.000E+00 3.230E+09 Y-92 8.470E-01 0.000E+00 2.450E-02 0.000E+00 0.000E+00 0.000E+00 2.320E+04 Y-93 1.630E+02 0.000E+00 4.470E+00 0.000E+00 0.000E+00 0.000E+00 4.980E+06 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 260 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors VEGETATION DOSE FACTORS TEEN (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract ZR-95 1.740E+06 5.490E+05 3.780E+05 0.000E+00 8.070E+05 0.000E+00 1.270E+09 ZR-97 3.090E+02 6.110E+01 2.810E+01 0.000E+00 9.260E+01 0.000E+00 1.650E+07 NB-95 1.920E+05 1.060E+05 5.860E+04 0.000E+00 1.030E+05 0.000E+00 4.550E+08 NB-97 2.690E-06 6.670E-07 2.440E-07 0.000E+00 7.800E-07 0.000E+00 1.590E-02 MO-99 0.000E+00 5.740E+06 1.090E+06 0.000E+00 1.310E+07 0.000E+00 1.030E+07 TC-99M 2.700E+00 7.540E+00 9.770E+01 0.000E+00 1.120E+02 4.190E+00 4.950E+03 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 6.870E+06 0.000E+00 2.940E+06 0.000E+00 2.420E+07 0.000E+00 5.740E+08 RU-105 5.000E+01 0.000E+00 1.940E+01 0.000E+00 6.310E+02 0.000E+00 4.040E+04 RU-106 3.090E+08 0.000E+00 3.900E+07 0.000E+00 5.970E+08 0.000E+00 1.480E+10 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 1.520E+07 1.440E+07 8.740E+06 0.000E+00 2.740E+07 0.000E+00 4.040E+09 SB-122 4.920E+05 5.130E+05 6.220E+06 8.150E+04 2.420E+05 1.060E+05 6.120E+07 SB-124 1.550E+08 2.850E+06 6.030E+07 3.510E+05 0.000E+00 1.350E+08 3.110E+09 SB-125 2.140E+08 2.340E+06 5.000E+07 2.040E+05 0.000E+00 1.880E+08 1.660E+09 TE-125M 1.480E+08 5.340E+07 1.980E+07 4.140E+07 0.000E+00 0.000E+00 4.370E+08 TE-127M 5.510E+08 1.960E+08 6.560E+07 1.310E+08 2.240E+09 0.000E+00 1.370E+09 TE-127 5.430E+03 1.920E+03 1.170E+03 3.740E+03 2.200E+04 0.000E+00 4.190E+05 TE-129M 3.670E+08 1.360E+08 5.810E+07 1.180E+08 1.540E+09 0.000E+00 1.380E+09 TE-129 6.220E-04 2.320E-04 1.510E-04 4.450E-04 2.610E-03 0.000E+00 3.400E-03 TE-131M 8.440E+05 4.050E+05 3.380E+05 6.090E+05 4.220E+06 0.000E+00 3.250E+07 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 3.900E+06 2.470E+06 2.320E+06 2.600E+06 2.370E+07 0.000E+00 7.820E+07 I-130 3.540E+05 1.020E+06 4.090E+05 8.350E+07 1.580E+06 0.000E+00 7.870E+05 I-131 7.700E+07 1.080E+08 5.790E+07 3.140E+10 1.850E+08 0.000E+00 2.130E+07 I-132 5.180E+01 1.360E+02 4.870E+01 4.570E+03 2.140E+02 0.000E+00 5.910E+01 I-133 1.970E+06 3.340E+06 1.020E+06 4.660E+08 5.860E+06 0.000E+00 2.530E+06 I-134 9.590E-05 2.540E-04 9.130E-05 4.240E-03 4.010E-04 0.000E+00 3.350E-06 I-135 3.680E+04 9.480E+04 3.520E+04 6.100E+06 1.500E+05 0.000E+00 1.050E+05 CS-134 7.090E+09 1.670E+10 7.740E+09 0.000E+00 5.300E+09 2.020E+09 2.080E+08 CS-136 4.290E+07 1.690E+08 1.130E+08 0.000E+00 9.190E+07 1.450E+07 1.360E+07 CS-137 1.010E+10 1.350E+10 4.690E+09 0.000E+00 4.590E+09 1.780E+09 1.920E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 261 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors VEGETATION DOSE FACTORS TEEN (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BA-139 2.770E-02 1.950E-05 8.080E-04 0.000E+00 1.840E-05 1.340E-05 2.470E-01 BA-140 1.380E+08 1.690E+05 8.910E+06 0.000E+00 5.750E+04 1.140E+05 2.130E+08 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 1.800E+03 8.840E+02 2.350E+02 0.000E+00 0.000E+00 0.000E+00 5.080E+07 LA-142 1.280E-04 5.690E-05 1.420E-05 0.000E+00 0.000E+00 0.000E+00 1.730E+00 CE-141 2.820E+05 1.880E+05 2.160E+04 0.000E+00 8.860E+04 0.000E+00 5.380E+08 CE-143 9.370E+02 6.820E+05 7.620E+01 0.000E+00 3.060E+02 0.000E+00 2.050E+07 CE-144 5.270E+07 2.180E+07 2.830E+06 0.000E+00 1.300E+07 0.000E+00 1.330E+10 PR-143 7.120E+04 2.840E+04 3.550E+03 0.000E+00 1.650E+04 0.000E+00 2.340E+08 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 3.630E+04 3.940E+04 2.360E+03 0.000E+00 2.320E+04 0.000E+00 1.420E+08 EU-154 7.060E+07 9.120E+06 6.430E+06 0.000E+00 4.080E+07 0.000E+00 4.820E+09 EU-155 1.540E+07 1.480E+06 9.190E+05 0.000E+00 5.800E+06 0.000E+00 8.510E+09 W-187 3.550E+04 2.900E+04 1.020E+04 0.000E+00 0.000E+00 0.000E+00 7.840E+06 NP-239 1.380E+03 1.300E+02 7.240E+01 0.000E+00 4.090E+02 0.000E+00 2.100E+07 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 262 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors VEGETATION DOSE FACTORS CHILD (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 4.010E+03 4.010E+03 4.010E+03 4.010E+03 4.010E+03 4.010E+03 C-14 3.500E+06 7.010E+05 7.010E+05 7.010E+05 7.010E+05 7.010E+05 7.010E+05 NA-24 3.830E+05 3.830E+05 3.830E+05 3.830E+05 3.830E+05 3.830E+05 3.830E+05 P-32 3.370E+09 1.580E+08 1.300E+08 0.000E+00 0.000E+00 0.000E+00 9.300E+07 CR-51 0.000E+00 0.000E+00 1.180E+05 6.540E+04 1.790E+04 1.190E+05 6.250E+06 MN-54 0.000E+00 6.610E+08 1.760E+08 0.000E+00 1.850E+08 0.000E+00 5.550E+08 MN-56 0.000E+00 1.900E+01 4.280E+00 0.000E+00 2.290E+01 0.000E+00 2.750E+03 FE-55 8.000E+08 4.240E+08 1.310E+08 0.000E+00 0.000E+00 2.400E+08 7.860E+07 FE-59 4.010E+08 6.490E+08 3.230E+08 0.000E+00 0.000E+00 1.880E+08 6.760E+08 CO-57 0.000E+00 2.990E+07 6.040E+07 0.000E+00 0.000E+00 0.000E+00 2.450E+08 CO-58 0.000E+00 6.470E+07 1.980E+08 0.000E+00 0.000E+00 0.000E+00 3.770E+08 CO-60 0.000E+00 3.780E+08 1.120E+09 0.000E+00 0.000E+00 0.000E+00 2.100E+09 NI-63 3.950E+10 2.110E+09 1.340E+09 0.000E+00 0.000E+00 0.000E+00 1.420E+08 NI-65 1.050E+02 9.890E+00 5.770E+00 0.000E+00 0.000E+00 0.000E+00 1.210E+03 CU-64 0.000E+00 1.110E+04 6.690E+03 0.000E+00 2.680E+04 0.000E+00 5.200E+05 ZN-65 8.120E+08 2.160E+09 1.350E+09 0.000E+00 1.360E+09 0.000E+00 3.800E+08 ZN-69 1.510E-05 2.180E-05 2.020E-06 0.000E+00 1.320E-05 0.000E+00 1.380E-03 BR-82 0.000E+00 0.000E+00 2.040E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 5.550E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 4.520E+08 2.780E+08 0.000E+00 0.000E+00 0.000E+00 2.910E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 3.590E+10 0.000E+00 1.030E+09 0.000E+00 0.000E+00 0.000E+00 1.390E+09 SR-90 1.240E+12 0.000E+00 3.150E+11 0.000E+00 0.000E+00 0.000E+00 1.670E+10 SR-91 5.500E+05 0.000E+00 2.080E+04 0.000E+00 0.000E+00 0.000E+00 1.210E+06 SR-92 7.280E+02 0.000E+00 2.920E+01 0.000E+00 0.000E+00 0.000E+00 1.380E+04 Y-90 2.300E+04 0.000E+00 6.170E+02 0.000E+00 0.000E+00 0.000E+00 6.560E+07 Y-91M 9.940E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.950E-05 Y-91 1.870E+07 0.000E+00 5.010E+05 0.000E+00 0.000E+00 0.000E+00 2.490E+09 Y-92 1.560E+00 0.000E+00 4.460E-02 0.000E+00 0.000E+00 0.000E+00 4.510E+04 Y-93 3.010E+02 0.000E+00 8.250E+00 0.000E+00 0.000E+00 0.000E+00 4.480E+06 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 263 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors VEGETATION DOSE FACTORS CHILD (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract ZR-95 3.900E+06 8.580E+05 7.640E+05 0.000E+00 1.230E+06 0.000E+00 8.950E+08 ZR-97 5.640E+02 8.150E+01 4.810E+01 0.000E+00 1.170E+02 0.000E+00 1.230E+07 NB-95 4.100E+05 1.590E+05 1.140E+05 0.000E+00 1.500E+05 0.000E+00 2.950E+08 NB-97 4.900E-06 8.850E-07 4.130E-07 0.000E+00 9.820E-07 0.000E+00 2.730E-01 MO-99 0.000E+00 7.830E+06 1.940E+06 0.000E+00 1.670E+07 0.000E+00 6.480E+06 TC-99M 4.650E+00 9.120E+00 1.510E+02 0.000E+00 1.330E+02 4.630E+00 5.190E+03 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 1.550E+07 0.000E+00 5.940E+06 0.000E+00 3.890E+07 0.000E+00 3.990E+08 RU-105 9.170E+01 0.000E+00 3.330E+01 0.000E+00 8.060E+02 0.000E+00 5.980E+04 RU-106 7.450E+08 0.000E+00 9.300E+07 0.000E+00 1.010E+09 0.000E+00 1.160E+10 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 3.220E+07 2.170E+07 1.740E+07 0.000E+00 4.050E+07 0.000E+00 2.580E+09 SB-122 3.050E+05 3.180E+05 3.850E+06 5.050E+04 1.500E+05 6.540E+04 3.790E+07 SB-124 3.520E+08 4.570E+06 1.230E+08 7.780E+05 0.000E+00 1.960E+08 2.200E+09 SB-125 4.990E+08 3.850E+06 1.050E+08 4.620E+05 0.000E+00 2.780E+08 1.190E+09 TE-125M 3.510E+08 9.500E+07 4.670E+07 9.840E+07 0.000E+00 0.000E+00 3.380E+08 TE-127M 1.320E+09 3.560E+08 1.570E+08 3.160E+08 3.770E+09 0.000E+00 1.070E+09 TE-127 1.000E+04 2.700E+03 2.150E+03 6.930E+03 2.850E+04 0.000E+00 3.910E+05 TE-129M 8.540E+08 2.390E+08 1.330E+08 2.750E+08 2.510E+09 0.000E+00 1.040E+09 TE-129 1.150E-03 3.220E-04 2.740E-04 8.220E-04 3.370E-03 0.000E+00 7.170E-02 TE-131M 1.540E+06 5.330E+05 5.680E+05 1.100E+06 5.160E+06 0.000E+00 2.160E+07 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 6.980E+06 3.090E+06 3.730E+06 4.500E+06 2.870E+07 0.000E+00 3.110E+07 I-130 6.210E+05 1.260E+06 6.470E+05 1.380E+08 1.880E+06 0.000E+00 5.870E+05 I-131 1.430E+08 1.440E+08 8.180E+07 4.760E+10 2.360E+08 0.000E+00 1.280E+07 I-132 9.200E+01 1.690E+02 7.770E+01 7.840E+03 2.590E+02 0.000E+00 1.990E+02 I-133 3.590E+06 4.440E+06 1.680E+06 8.250E+08 7.400E+06 0.000E+00 1.790E+06 I-134 1.700E-04 3.160E-04 1.460E-04 7.280E-03 4.840E-04 0.000E+00 2.100E-04 I-135 6.540E+04 1.180E+05 5.570E+04 1.040E+07 1.810E+05 0.000E+00 8.980E+04 CS-134 1.600E+10 2.630E+10 5.540E+09 0.000E+00 8.140E+09 2.920E+09 1.420E+08 CS-136 8.060E+07 2.220E+08 1.430E+08 0.000E+00 1.180E+08 1.760E+07 7.790E+06 CS-137 2.390E+10 2.290E+10 3.380E+09 0.000E+00 7.460E+09 2.680E+09 1.430E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 264 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors VEGETATION DOSE FACTORS CHILD (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BA-139 5.110E-02 2.730E-05 1.480E-03 0.000E+00 2.380E-05 1.610E-05 2.950E+00 BA-140 2.770E+08 2.430E+05 1.620E+07 0.000E+00 7.900E+04 1.450E+05 1.400E+08 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 3.230E+03 1.130E+03 3.810E+02 0.000E+00 0.000E+00 0.000E+00 3.150E+07 LA-142 2.320E-04 7.400E-05 2.320E-05 0.000E+00 0.000E+00 0.000E+00 1.470E+01 CE-141 6.350E+05 3.260E+05 4.840E+04 0.000E+00 1.430E+05 0.000E+00 4.070E+08 CE-143 1.730E+03 9.360E+05 1.360E+02 0.000E+00 3.930E+02 0.000E+00 1.370E+07 CE-144 1.270E+08 3.980E+07 6.780E+06 0.000E+00 2.210E+07 0.000E+00 1.040E+10 PR-143 1.480E+05 4.460E+04 7.370E+03 0.000E+00 2.410E+04 0.000E+00 1.600E+08 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 7.160E+04 5.800E+04 4.490E+03 0.000E+00 3.180E+04 0.000E+00 9.180E+07 EU-154 1.660E+08 1.500E+07 1.370E+07 0.000E+00 6.570E+07 0.000E+00 3.480E+09 EU-155 3.440E+07 2.480E+06 1.940E+06 0.000E+00 9.280E+06 0.000E+00 6.200E+09 W-187 6.470E+04 3.830E+04 1.720E+04 0.000E+00 0.000E+00 0.000E+00 5.380E+06 NP-239 2.550E+03 1.830E+02 1.290E+02 0.000E+00 5.300E+02 0.000E+00 1.360E+07 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 265 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors VEGETATION DOSE FACTORS INFANT (m2*mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract THIS PATHWAY IS NOT APPLICABLE TABLE INTENTIONALLY LEFT BLANK December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 266 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GROUND PLANE DOSE FACTORS ALL AGE GROUPS (ADULT, TEEN, CHILD, INFANT)

(m2*mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NA-24 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 1.210E+07 P-32 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CR-51 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06 4.680E+06 MN-54 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 1.340E+09 MN-56 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 9.050E+05 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-59 2.750E+08 2.750E+08 2.750E+08 2.750E+08 2.750E+08 2.750E+08 2.750E+08 CO-58 3.820E+08 3.820E+08 3.820E+08 3.820E+08 3.820E+08 3.820E+08 3.820E+08 CO-60 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 2.160E+10 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 CU-64 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 6.090E+05 ZN-65 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7.450E+08 7.450E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 4.890E+03 BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 8.980E+06 RB-88 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 3.290E+04 RB-89 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 1.210E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-91 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 2.190E+06 SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 Y-90 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 4.480E+03 Y-91M 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 1.010E+05 Y-91 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 1.080E+06 Y-92 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 Y-93 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 1.850E+05 ZR-95 2.480E+08 2.480E+08 2.480E+08 2.480E+08 2.480E+08 2.480E+08 2.480E+08 ZR-97 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 2.940E+06 NB-95 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+08 1.360E+08 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 267 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GROUND PLANE DOSE FACTORS ALL AGE GROUPS (ADULT, TEEN, CHILD, INFANT)

(m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract MO-99 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 4.050E+06 TC-99M 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 RU-103 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 1.090E+08 RU-105 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 RU-106 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 4.210E+08 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 3.470E+09 SB-122 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 1.070E+07 TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 TE-127M 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 9.170E+04 TE-127 3.000E+03 3.000E+03 3.000E+03 3.000E+03 3.000E+03 3.000E+03 3.000E+03 TE-129M 2.000E+07 2.000E+07 2.000E+07 2.000E+07 2.000E+07 2.000E+07 2.000E+07 TE-129 2.600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 2.600E+04 TE-131M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 TE-131 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 2.930E+04 TE-132 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 4.220E+06 I-130 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 5.530E+06 I-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 I-132 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 1.240E+06 I-133 2.470E+06 2.470E+06 2.470E+06 2.470E+06 2.470E+06 2.470E+06 2.470E+06 I-134 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 4.490E+05 I-135 2.560E+06 2.560E+06 2.560E+06 2.560E+06 2.560E+06 2.560E+06 2.560E+06 CS-134 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 6.750E+09 CS-136 1.490E+08 1.490E+08 1.490E+08 1.490E+08 1.490E+08 1.490E+08 1.490E+08 CS-137 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 1.040E+10 CS-138 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 BA-139 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 BA-140 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 BA-141 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 4.180E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 268 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GROUND PLANE DOSE FACTORS ALL AGE GROUPS (ADULT, TEEN, CHILD, INFANT)

(m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract LA-140 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 1.910E+07 LA-142 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 7.360E+05 CE-141 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 1.360E+07 CE-143 2.320E+06 2.320E+06 2.320E+06 2.320E+06 2.320E+06 2.320E+06 2.320E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 PR-143 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 PR-144 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 ND-147 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 8.400E+06 EU-154 2.700E+10 2.700E+10 2.700E+10 2.700E+10 2.700E+10 2.700E+10 2.700E+10 EU-155 9.570E+08 9.570E+08 9.570E+08 9.570E+08 9.570E+08 9.570E+08 9.570E+08 W-187 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 2.360E+06 NP-239 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 269 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS ADULT (mrem/yr per uCi/m 3)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 1.260E+03 1.260E+03 1.260E+03 1.260E+03 1.260E+03 1.260E+03 C-14 1.820E+04 3.410E+03 3.410E+03 3.410E+03 3.410E+03 3.410E+03 3.410E+03 NA-24 1.020E+04 1.020E+04 1.020E+04 1.020E+04 1.020E+04 1.020E+04 1.020E+04 P-32 1.320E+06 7.710E+04 5.010E+04 0.000E+00 0.000E+00 0.000E+00 8.640E+04 CR-51 0.000E+00 0.000E+00 1.000E+02 5.950E+01 2.280E+01 1.440E+04 3.320E+03 MN-54 0.000E+00 3.960E+04 6.300E+03 0.000E+00 9.840E+03 1.400E+06 7.740E+04 MN-56 0.000E+00 1.240E+00 1.830E-01 0.000E+00 1.300E+00 9.440E+03 2.020E+04 FE-55 2.460E+04 1.700E+04 3.940E+03 0.000E+00 0.000E+00 7.210E+04 6.030E+03 FE-59 1.180E+04 2.780E+04 1.060E+04 0.000E+00 0.000E+00 1.020E+06 1.880E+05 CO-57 0.000E+00 6.920E+02 6.710E+02 0.000E+00 0.000E+00 3.700E+05 3.140E+04 CO-58 0.000E+00 1.580E+03 2.070E+03 0.000E+00 0.000E+00 9.280E+05 1.060E+05 CO-60 0.000E+00 1.150E+04 1.480E+04 0.000E+00 0.000E+00 5.970E+06 2.850E+05 NI-63 4.320E+05 3.140E+04 1.450E+04 0.000E+00 0.000E+00 1.780E+05 1.340E+04 NI-65 1.540E+00 2.100E-01 9.120E-02 0.000E+00 0.000E+00 5.600E+03 1.230E+04 CU-64 0.000E+00 1.460E+00 6.150E-01 0.000E+00 4.620E+00 6.780E+03 4.900E+04 ZN-65 3.240E+04 1.030E+05 4.660E+04 0.000E+00 6.900E+04 8.640E+05 5.340E+04 ZN-69 3.380E-02 6.510E-02 4.520E-03 0.000E+00 4.220E-02 9.200E+02 1.630E+01 BR-82 0.000E+00 0.000E+00 1.350E+04 0.000E+00 0.000E+00 0.000E+00 1.040E+04 BR-83 0.000E+00 0.000E+00 2.410E+02 0.000E+00 0.000E+00 0.000E+00 2.320E+02 BR-84 0.000E+00 0.000E+00 3.130E+02 0.000E+00 0.000E+00 0.000E+00 1.640E-03 BR-85 0.000E+00 0.000E+00 1.280E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 1.350E+05 5.900E+04 0.000E+00 0.000E+00 0.000E+00 1.660E+04 RB-88 0.000E+00 3.870E+02 1.930E+02 0.000E+00 0.000E+00 0.000E+00 3.340E-09 RB-89 0.000E+00 2.560E+02 1.700E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 3.040E+05 0.000E+00 8.720E+03 0.000E+00 0.000E+00 1.400E+06 3.500E+05 SR-90 9.920E+07 0.000E+00 6.100E+06 0.000E+00 0.000E+00 9.600E+06 7.220E+05 SR-91 6.190E+01 0.000E+00 2.500E+00 0.000E+00 0.000E+00 3.650E+04 1.910E+05 SR-92 6.740E+00 0.000E+00 2.910E-01 0.000E+00 0.000E+00 1.650E+04 4.300E+04 Y-90 2.090E+03 0.000E+00 5.610E+01 0.000E+00 0.000E+00 1.700E+05 5.060E+05 Y-91M 2.610E-01 0.000E+00 1.020E-02 0.000E+00 0.000E+00 1.920E+03 1.330E+00 Y-91 4.620E+05 0.000E+00 1.240E+04 0.000E+00 0.000E+00 1.700E+06 3.850E+05 Y-92 1.030E+01 0.000E+00 3.020E-01 0.000E+00 0.000E+00 1.570E+04 7.350E+04 Y-93 9.440E+01 0.000E+00 2.610E+00 0.000E+00 0.000E+00 4.850E+04 4.220E+05 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 270 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS ADULT (mrem/yr per uCi/m 3)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract ZR-95 1.070E+05 3.440E+04 2.330E+04 0.000E+00 5.420E+04 1.770E+06 1.500E+05 ZR-97 9.680E+01 1.960E+01 9.040E+00 0.000E+00 2.970E+01 7.870E+04 5.230E+05 NB-95 1.410E+04 7.820E+03 4.210E+03 0.000E+00 7.740E+03 5.050E+05 1.040E+05 NB-97 2.220E-01 5.620E-02 2.050E-02 0.000E+00 6.540E-02 2.400E+03 2.420E+02 MO-99 0.000E+00 1.210E+02 2.300E+01 0.000E+00 2.910E+02 9.120E+04 2.480E+05 TC-99M 1.030E-03 2.910E-03 3.700E-02 0.000E+00 4.420E-02 7.640E+02 4.160E+03 TC-101 4.180E-05 6.020E-05 5.900E-04 0.000E+00 1.080E-03 3.990E+02 0.000E+00 RU-103 1.530E+03 0.000E+00 6.580E+02 0.000E+00 5.830E+03 5.050E+05 1.100E+05 RU-105 7.900E-01 0.000E+00 3.110E-01 0.000E+00 1.020E+00 1.100E+04 4.820E+04 RU-106 6.910E+04 0.000E+00 8.720E+03 0.000E+00 1.340E+05 9.360E+06 9.120E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 1.080E+04 1.000E+04 5.940E+03 0.000E+00 1.970E+04 4.630E+06 3.020E+05 SB-122 3.100E+03 4.110E+03 4.110E+04 1.070E+03 1.550E+03 1.670E+05 2.020E+05 SB-124 3.120E+04 5.890E+02 1.240E+04 7.550E+01 0.000E+00 2.480E+06 4.060E+05 SB-125 5.340E+04 5.950E+02 1.260E+04 5.400E+01 0.000E+00 1.740E+06 1.010E+05 TE-125M 3.420E+03 1.580E+03 4.670E+02 1.050E+03 1.240E+04 3.140E+05 7.060E+04 TE-127M 1.260E+04 5.770E+03 1.570E+03 3.290E+03 4.580E+04 9.600E+05 1.500E+05 TE-127 1.400E+00 6.420E-01 3.100E-01 1.060E+00 5.100E+00 6.510E+03 5.740E+04 TE-129M 9.760E+03 4.670E+03 1.580E+03 3.440E+03 3.660E+04 1.160E+06 3.830E+05 TE-129 4.980E-02 2.390E-02 1.240E-02 3.900E-02 1.870E-01 1.940E+03 1.570E+02 TE-131M 6.990E+01 4.360E+01 2.900E+01 5.500E+01 3.090E+02 1.460E+05 5.560E+05 TE-131 1.110E-02 5.950E-03 3.590E-03 9.360E-03 4.370E-02 1.390E+03 1.840E+01 TE-132 2.600E+02 2.150E+02 1.620E+02 1.900E+02 1.460E+03 2.880E+05 5.100E+05 I-130 4.580E+03 1.340E+04 5.280E+03 1.140E+06 2.090E+04 7.690E+03 0.000E+00 I-131 2.520E+04 3.580E+04 2.050E+04 1.190E+07 6.130E+04 0.000E+00 6.280E+03 I-132 1.160E+03 3.260E+03 1.160E+03 1.140E+05 5.180E+03 0.000E+00 4.060E+02 I-133 8.640E+03 1.480E+04 4.520E+03 2.150E+06 2.580E+04 0.000E+00 8.880E+03 I-134 6.440E+02 1.730E+03 6.150E+02 2.980E+04 2.750E+03 0.000E+00 1.010E+00 I-135 2.680E+03 6.980E+03 2.570E+03 4.480E+05 1.110E+04 0.000E+00 5.250E+03 CS-134 3.730E+05 8.480E+05 7.280E+05 0.000E+00 2.870E+05 9.760E+04 1.040E+04 CS-136 3.900E+04 1.460E+05 1.100E+05 0.000E+00 8.560E+04 1.200E+04 1.170E+04 CS-137 4.780E+05 6.210E+05 4.280E+05 0.000E+00 2.220E+05 7.520E+04 8.400E+03 CS-138 3.310E+02 6.210E+02 3.240E+02 0.000E+00 4.800E+02 4.860E+01 1.860E-03 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 271 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS ADULT (mrem/yr per uCi/m 3)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BA-139 9.360E-01 6.660E-04 2.740E-02 0.000E+00 6.220E-04 3.760E+03 8.960E+02 BA-140 3.900E+04 4.900E+01 2.570E+03 0.000E+00 1.670E+01 1.270E+06 2.180E+05 BA-141 1.000E-01 7.530E-05 3.360E-03 0.000E+00 7.000E-05 1.940E+03 1.160E-07 BA-142 2.630E-02 2.700E-05 1.660E-03 0.000E+00 2.290E-05 1.190E+03 0.000E+00 LA-140 3.440E+02 1.740E+02 4.580E+01 0.000E+00 0.000E+00 1.360E+05 4.580E+05 LA-142 6.830E-01 3.100E-01 7.720E-02 0.000E+00 0.000E+00 6.330E+03 2.110E+03 CE-141 1.990E+04 1.350E+04 1.530E+03 0.000E+00 6.260E+03 3.620E+05 1.200E+05 CE-143 1.860E+02 1.380E+02 1.530E+01 0.000E+00 6.080E+01 7.980E+04 2.260E+05 CE-144 3.430E+06 1.430E+06 1.840E+05 0.000E+00 8.480E+05 7.780E+06 8.160E+05 PR-143 9.360E+03 3.750E+03 4.640E+02 0.000E+00 2.160E+03 2.810E+05 2.000E+05 PR-144 3.010E-02 1.250E-02 1.530E-03 0.000E+00 7.050E-03 1.020E+03 2.150E-08 ND-147 5.270E+03 6.100E+03 3.650E+02 0.000E+00 3.560E+03 2.210E+05 1.730E+05 EU-154 5.920E+06 7.280E+05 5.180E+05 0.000E+00 3.490E+06 4.670E+06 2.720E+05 EU-155 8.080E+05 1.140E+05 7.370E+04 0.000E+00 5.270E+05 7.570E+05 4.760E+04 W-187 8.480E+00 7.080E+00 2.480E+00 0.000E+00 0.000E+00 2.900E+04 1.550E+05 NP-239 2.300E+02 2.260E+01 1.240E+01 0.000E+00 7.000E+01 3.760E+04 1.190E+05 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 272 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS TEEN (mrem/yr per uCi/m 3)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 1.270E+03 1.270E+03 1.270E+03 1.270E+03 1.270E+03 1.270E+03 C-14 2.600E+04 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 NA-24 1.380E+04 1.380E+04 1.380E+04 1.380E+04 1.380E+04 1.380E+04 1.380E+04 P-32 1.890E+06 1.100E+05 7.160E+04 0.000E+00 0.000E+00 0.000E+00 9.280E+04 CR-51 0.000E+00 0.000E+00 1.350E+02 7.500E+01 3.070E+01 2.100E+04 3.000E+03 MN-54 0.000E+00 5.110E+04 8.400E+03 0.000E+00 1.270E+04 1.980E+06 6.680E+04 MN-56 0.000E+00 1.700E+00 2.520E-01 0.000E+00 1.790E+00 1.520E+04 5.740E+04 FE-55 3.340E+04 2.380E+04 5.540E+03 0.000E+00 0.000E+00 1.240E+05 6.390E+03 FE-59 1.590E+04 3.700E+04 1.430E+04 0.000E+00 0.000E+00 1.530E+06 1.780E+05 CO-57 0.000E+00 6.920E+02 9.200E+02 0.000E+00 0.000E+00 5.860E+05 3.140E+04 CO-58 0.000E+00 2.070E+03 2.780E+03 0.000E+00 0.000E+00 1.340E+06 9.520E+04 CO-60 0.000E+00 1.510E+04 1.980E+04 0.000E+00 0.000E+00 8.720E+06 2.590E+05 NI-63 5.800E+05 4.340E+04 1.980E+04 0.000E+00 0.000E+00 3.070E+05 1.420E+04 NI-65 2.180E+00 2.930E-01 1.270E-01 0.000E+00 0.000E+00 9.360E+03 3.670E+04 CU-64 0.000E+00 2.030E+00 8.480E-01 0.000E+00 6.410E+00 1.110E+04 6.140E+04 ZN-65 3.860E+04 1.340E+05 6.240E+04 0.000E+00 8.640E+04 1.240E+06 4.660E+04 ZN-69 4.830E-02 9.200E-02 6.460E-03 0.000E+00 6.020E-02 1.580E+03 2.850E+02 BR-82 0.000E+00 0.000E+00 1.820E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 3.440E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 4.330E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 1.830E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 1.900E+05 8.400E+04 0.000E+00 0.000E+00 0.000E+00 1.770E+04 RB-88 0.000E+00 5.460E+02 2.720E+02 0.000E+00 0.000E+00 0.000E+00 2.920E-05 RB-89 0.000E+00 3.520E+02 2.330E+02 0.000E+00 0.000E+00 0.000E+00 3.380E-07 SR-89 4.340E+05 0.000E+00 1.250E+04 0.000E+00 0.000E+00 2.420E+06 3.710E+05 SR-90 1.080E+08 0.000E+00 6.680E+06 0.000E+00 0.000E+00 1.650E+07 7.650E+05 SR-91 8.800E+01 0.000E+00 3.510E+00 0.000E+00 0.000E+00 6.070E+04 2.590E+05 SR-92 9.520E+00 0.000E+00 4.060E-01 0.000E+00 0.000E+00 2.740E+04 1.190E+05 Y-90 2.980E+03 0.000E+00 8.000E+01 0.000E+00 0.000E+00 2.930E+05 5.590E+05 Y-91M 3.700E-01 0.000E+00 1.420E-02 0.000E+00 0.000E+00 3.200E+03 3.020E+01 Y-91 6.610E+05 0.000E+00 1.770E+04 0.000E+00 0.000E+00 2.940E+06 4.090E+05 Y-92 1.470E+01 0.000E+00 4.290E-01 0.000E+00 0.000E+00 2.680E+04 1.650E+05 Y-93 1.350E+02 0.000E+00 3.720E+00 0.000E+00 0.000E+00 8.320E+04 5.790E+05 December 2018

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Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract ZR-95 1.460E+05 4.580E+04 3.150E+04 0.000E+00 6.740E+04 2.690E+06 1.490E+05 ZR-97 1.380E+02 2.720E+01 1.260E+01 0.000E+00 4.120E+01 1.300E+05 6.300E+05 NB-95 1.860E+04 1.030E+04 5.660E+03 0.000E+00 1.000E+04 7.510E+05 9.680E+04 NB-97 3.140E-01 7.780E-02 2.840E-02 0.000E+00 9.120E-02 3.930E+03 2.170E+03 MO-99 0.000E+00 1.690E+02 3.220E+01 0.000E+00 4.110E+02 1.540E+05 2.690E+05 TC-99M 1.380E-03 3.860E-03 4.990E-02 0.000E+00 5.760E-02 1.150E+03 6.130E+03 TC-101 5.920E-05 8.400E-05 8.240E-04 0.000E+00 1.520E-03 6.670E+02 8.720E-07 RU-103 2.100E+03 0.000E+00 8.960E+02 0.000E+00 7.430E+03 7.830E+05 1.090E+05 RU-105 1.120E+00 0.000E+00 4.340E-01 0.000E+00 1.410E+00 1.820E+04 9.040E+04 RU-106 9.840E+04 0.000E+00 1.240E+04 0.000E+00 1.900E+05 1.610E+07 9.600E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 1.380E+04 1.310E+04 7.990E+03 0.000E+00 2.500E+04 6.750E+06 2.730E+05 SB-122 3.100E+03 4.110E+03 4.110E+04 1.070E+03 1.550E+03 1.670E+05 2.020E+05 SB-124 4.300E+04 7.940E+02 1.680E+04 9.760E+01 0.000E+00 3.850E+06 3.980E+05 SB-125 7.380E+04 8.080E+02 1.720E+04 7.040E+01 0.000E+00 2.740E+06 9.920E+04 TE-125M 4.880E+03 2.240E+03 6.670E+02 1.400E+03 0.000E+00 5.360E+05 7.500E+04 TE-127M 1.800E+04 8.160E+03 2.180E+03 4.380E+03 6.540E+04 1.660E+06 1.590E+05 TE-127 2.010E+00 9.120E-01 4.420E-01 1.420E+00 7.280E+00 1.120E+04 8.080E+04 TE-129M 1.390E+04 6.580E+03 2.250E+03 4.580E+03 5.190E+04 1.980E+06 4.050E+05 TE-129 7.100E-02 3.380E-02 1.760E-02 5.180E-02 2.660E-01 3.300E+03 1.620E+03 TE-131M 9.840E+01 6.010E+01 4.020E+01 7.250E+01 4.390E+02 2.380E+05 6.210E+05 TE-131 1.580E-02 8.320E-03 5.040E-03 1.240E-02 6.180E-02 2.340E+03 1.510E+01 TE-132 3.600E+02 2.900E+02 2.190E+02 2.460E+02 1.950E+03 4.490E+05 4.630E+05 I-130 6.240E+03 1.790E+04 7.170E+03 1.490E+06 2.750E+04 0.000E+00 9.120E+03 I-131 3.540E+04 4.910E+04 2.640E+04 1.460E+07 8.400E+04 0.000E+00 6.490E+03 I-132 1.590E+03 4.380E+03 1.580E+03 1.510E+05 6.920E+03 0.000E+00 1.270E+03 I-133 1.220E+04 2.050E+04 6.220E+03 2.920E+06 3.590E+04 0.000E+00 1.030E+04 I-134 8.880E+02 2.320E+03 8.400E+02 3.950E+04 3.660E+03 0.000E+00 2.040E+01 I-135 3.700E+03 9.440E+03 3.490E+03 6.210E+05 1.490E+04 0.000E+00 6.950E+03 CS-134 5.020E+05 1.130E+06 5.490E+05 0.000E+00 3.750E+05 1.460E+05 9.760E+03 CS-136 5.150E+04 1.940E+05 1.370E+05 0.000E+00 1.100E+05 1.780E+04 1.090E+04 CS-137 6.700E+05 8.480E+05 3.110E+05 0.000E+00 3.040E+05 1.210E+05 8.480E+03 CS-138 4.660E+02 8.560E+02 4.460E+02 0.000E+00 6.620E+02 7.870E+01 2.700E-01 December 2018

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Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BA-139 1.340E+00 9.440E-04 3.900E-02 0.000E+00 8.880E-04 6.460E+03 6.450E+03 BA-140 5.470E+04 6.700E+01 3.520E+03 0.000E+00 2.280E+01 2.030E+06 2.290E+05 BA-141 1.420E-01 1.060E-04 4.740E-03 0.000E+00 9.840E-05 3.290E+03 7.460E-04 BA-142 3.700E-02 3.700E-05 2.270E-03 0.000E+00 3.140E-05 1.910E+03 0.000E+00 LA-140 4.790E+02 2.360E+02 6.260E+01 0.000E+00 0.000E+00 2.140E+05 4.870E+05 LA-142 9.600E-01 4.250E-01 1.060E-01 0.000E+00 0.000E+00 1.020E+04 1.200E+04 CE-141 2.840E+04 1.900E+04 2.170E+03 0.000E+00 8.880E+03 6.140E+05 1.260E+05 CE-143 2.660E+02 1.940E+02 2.160E+01 0.000E+00 8.640E+01 1.300E+05 2.550E+05 CE-144 4.890E+06 2.020E+06 2.620E+05 0.000E+00 1.210E+06 1.340E+07 8.640E+05 PR-143 1.340E+04 5.310E+03 6.620E+02 0.000E+00 3.090E+03 4.830E+05 2.140E+05 PR-144 4.300E-02 1.760E-02 2.180E-03 0.000E+00 1.010E-02 1.750E+03 2.350E-04 ND-147 7.860E+03 8.560E+03 5.130E+02 0.000E+00 5.020E+03 3.720E+05 1.820E+05 EU-154 7.540E+06 9.840E+05 6.880E+05 0.000E+00 4.350E+06 7.300E+06 2.670E+05 EU-155 1.600E+06 1.570E+05 9.680E+04 0.000E+00 6.120E+05 1.210E+07 4.780E+05 W-187 1.200E+01 9.760E+00 3.430E+00 0.000E+00 0.000E+00 4.740E+04 1.770E+05 NP-239 3.380E+02 3.190E+01 1.770E+01 0.000E+00 1.000E+02 6.490E+04 1.320E+05 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 275 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS CHILD (mrem/yr per uCi/m 3)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 1.120E+03 1.120E+03 1.120E+03 1.120E+03 1.120E+03 1.120E+03 C-14 3.590E+04 6.730E+03 6.730E+03 6.730E+03 6.730E+03 6.730E+03 6.730E+03 NA-24 1.610E+04 1.610E+04 1.610E+04 1.610E+04 1.610E+04 1.610E+04 1.610E+04 P-32 2.600E+06 1.140E+05 9.880E+04 0.000E+00 0.000E+00 0.000E+00 4.220E+04 CR-51 0.000E+00 0.000E+00 1.540E+02 8.550E+01 2.430E+01 1.700E+04 1.080E+03 MN-54 0.000E+00 4.290E+04 9.510E+03 0.000E+00 1.000E+04 1.580E+06 2.290E+04 MN-56 0.000E+00 1.660E+00 3.120E-01 0.000E+00 1.670E+00 1.310E+04 1.230E+05 FE-55 4.740E+04 2.520E+04 7.770E+03 0.000E+00 0.000E+00 1.110E+05 2.870E+03 FE-59 2.070E+04 3.340E+04 1.670E+04 0.000E+00 0.000E+00 1.270E+06 7.070E+04 CO-57 0.000E+00 9.030E+02 1.070E+03 0.000E+00 0.000E+00 5.070E+05 1.320E+04 CO-58 0.000E+00 1.770E+03 3.160E+03 0.000E+00 0.000E+00 1.110E+06 3.440E+04 CO-60 0.000E+00 1.310E+04 2.260E+04 0.000E+00 0.000E+00 7.070E+06 9.620E+04 NI-63 8.210E+05 4.630E+04 2.800E+04 0.000E+00 0.000E+00 2.750E+05 6.330E+03 NI-65 2.990E+00 2.960E-01 1.640E-01 0.000E+00 0.000E+00 8.180E+03 8.400E+04 CU-64 0.000E+00 1.990E+00 1.070E+00 0.000E+00 6.030E+00 9.580E+03 3.670E+04 ZN-65 4.260E+04 1.130E+05 7.030E+04 0.000E+00 7.140E+04 9.950E+05 1.630E+04 ZN-69 6.700E-02 9.660E-02 8.920E-03 0.000E+00 5.850E-02 1.420E+03 9.510E+03 BR-82 0.000E+00 0.000E+00 2.090E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 4.740E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 5.480E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 2.530E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 1.980E+05 1.140E+05 0.000E+00 0.000E+00 0.000E+00 7.990E+03 RB-88 0.000E+00 5.620E+02 3.660E+02 0.000E+00 0.000E+00 0.000E+00 1.720E+01 RB-89 0.000E+00 3.450E+02 2.900E+02 0.000E+00 0.000E+00 0.000E+00 1.890E+00 SR-89 5.990E+05 0.000E+00 1.720E+04 0.000E+00 0.000E+00 2.160E+06 1.670E+05 SR-90 1.010E+08 0.000E+00 6.440E+06 0.000E+00 0.000E+00 1.480E+07 3.430E+05 SR-91 1.210E+02 0.000E+00 4.590E+00 0.000E+00 0.000E+00 5.330E+04 1.740E+05 SR-92 1.310E+01 0.000E+00 5.250E-01 0.000E+00 0.000E+00 2.400E+04 2.420E+05 Y-90 4.110E+03 0.000E+00 1.110E+02 0.000E+00 0.000E+00 2.620E+05 2.680E+05 Y-91M 5.070E-01 0.000E+00 1.840E-02 0.000E+00 0.000E+00 2.810E+03 1.720E+03 Y-91 9.140E+05 0.000E+00 2.440E+04 0.000E+00 0.000E+00 2.630E+06 1.840E+05 Y-92 2.040E+01 0.000E+00 5.810E-01 0.000E+00 0.000E+00 2.390E+04 2.390E+05 Y-93 1.860E+02 0.000E+00 5.110E+00 0.000E+00 0.000E+00 7.440E+04 3.890E+05 ZR-95 1.900E+05 4.180E+04 3.700E+04 0.000E+00 5.960E+04 2.230E+06 6.110E+04 December 2018

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Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract ZR-97 1.880E+02 2.720E+01 1.600E+01 0.000E+00 3.890E+01 1.130E+05 3.510E+05 NB-95 2.350E+04 9.180E+03 6.550E+03 0.000E+00 8.620E+03 6.140E+05 3.700E+04 NB-97 4.290E-01 7.700E-02 3.600E-02 0.000E+00 8.550E-02 3.420E+03 2.780E+04 MO-99 0.000E+00 1.720E+02 4.260E+01 0.000E+00 3.920E+02 1.350E+05 1.270E+05 TC-99M 1.780E-03 3.480E-03 5.770E-02 0.000E+00 5.070E-02 9.510E+02 4.810E+03 TC-101 8.100E-05 8.510E-05 1.080E-03 0.000E+00 1.450E-03 5.850E+02 1.630E+01 RU-103 2.790E+03 0.000E+00 1.070E+03 0.000E+00 7.030E+03 6.620E+05 4.480E+04 RU-105 1.530E+00 0.000E+00 5.550E-01 0.000E+00 1.340E+00 1.590E+04 9.950E+04 RU-106 1.360E+05 0.000E+00 1.690E+04 0.000E+00 1.840E+05 1.430E+07 4.290E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 1.690E+04 1.140E+04 9.140E+03 0.000E+00 2.120E+04 5.480E+06 1.000E+05 SB-122 1.440E+03 1.980E+03 1.900E+04 4.960E+02 7.180E+02 7.730E+04 9.360E+04 SB-124 5.740E+04 7.400E+02 2.000E+04 1.260E+02 0.000E+00 3.240E+06 1.640E+05 SB-125 9.840E+04 7.590E+02 2.070E+04 9.100E+01 0.000E+00 2.320E+06 4.030E+04 TE-125M 6.730E+03 2.330E+03 9.140E+02 1.920E+03 0.000E+00 4.770E+05 3.380E+04 TE-127M 2.490E+04 8.550E+03 3.020E+03 6.070E+03 6.360E+04 1.480E+06 7.140E+04 TE-127 2.770E+00 9.510E-01 6.110E-01 1.960E+00 7.070E+00 1.000E+04 5.620E+04 TE-129M 1.920E+04 6.850E+03 3.040E+03 6.330E+03 5.030E+04 1.760E+06 1.820E+05 TE-129 9.770E-02 3.500E-02 2.380E-02 7.140E-02 2.570E-01 2.930E+03 2.550E+04 TE-131M 1.340E+02 5.920E+01 5.070E+01 9.770E+01 4.000E+02 2.060E+05 3.080E+05 TE-131 2.170E-02 8.440E-03 6.590E-03 1.700E-02 5.880E-02 2.050E+03 1.330E+03 TE-132 4.810E+02 2.720E+02 2.630E+02 3.170E+02 1.840E+03 3.770E+05 1.380E+05 I-130 8.180E+03 1.640E+04 8.440E+03 1.850E+06 2.450E+04 0.000E+00 5.110E+03 I-131 4.810E+04 4.810E+04 2.730E+04 1.620E+07 7.880E+04 0.000E+00 2.840E+03 I-132 2.120E+03 4.070E+03 1.880E+03 1.940E+05 6.250E+03 0.000E+00 3.200E+03 I-133 1.660E+04 2.030E+04 7.700E+03 3.850E+06 3.380E+04 0.000E+00 5.480E+03 I-134 1.170E+03 2.160E+03 9.950E+02 5.070E+04 3.300E+03 0.000E+00 9.550E+02 I-135 4.920E+03 8.730E+03 4.140E+03 7.920E+05 1.340E+04 0.000E+00 4.440E+03 CS-134 6.510E+05 1.010E+06 2.250E+05 0.000E+00 3.300E+05 1.210E+05 3.850E+03 CS-136 6.510E+04 1.710E+05 1.160E+05 0.000E+00 9.550E+04 1.450E+04 4.180E+03 CS-137 9.070E+05 8.250E+05 1.280E+05 0.000E+00 2.820E+05 1.040E+05 3.620E+03 CS-138 6.330E+02 8.400E+02 5.550E+02 0.000E+00 6.220E+02 6.810E+01 2.700E+02 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 277 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS CHILD (mrem/yr per uCi/m 3)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BA-139 1.840E+00 9.840E-04 5.370E-02 0.000E+00 8.620E-04 5.770E+03 5.770E+04 BA-140 7.400E+04 6.480E+01 4.330E+03 0.000E+00 2.110E+01 1.740E+06 1.020E+05 BA-141 1.960E-01 1.090E-04 6.360E-03 0.000E+00 9.470E-05 2.920E+03 2.750E+02 BA-142 5.000E-02 3.600E-05 2.790E-03 0.000E+00 2.910E-05 1.640E+03 2.740E+00 LA-140 6.440E+02 2.250E+02 7.550E+01 0.000E+00 0.000E+00 1.830E+05 2.260E+05 LA-142 1.300E+00 4.110E-01 1.290E-01 0.000E+00 0.000E+00 8.700E+03 7.590E+04 CE-141 3.920E+04 1.950E+04 2.900E+03 0.000E+00 8.550E+03 5.440E+05 5.660E+04 CE-143 3.660E+02 1.990E+02 2.870E+01 0.000E+00 8.360E+01 1.150E+05 1.270E+05 CE-144 6.770E+06 2.120E+06 3.610E+05 0.000E+00 1.170E+06 1.200E+07 3.890E+05 PR-143 1.850E+04 5.550E+03 9.140E+02 0.000E+00 3.000E+03 4.330E+05 9.730E+04 PR-144 5.960E-02 1.850E-02 3.000E-03 0.000E+00 9.770E-03 1.570E+03 1.970E+02 ND-147 1.080E+04 8.730E+03 6.810E+02 0.000E+00 4.810E+03 3.280E+05 8.210E+04 EU-154 1.010E+07 9.210E+05 8.400E+05 0.000E+00 4.030E+06 6.140E+06 1.100E+05 EU-155 2.070E+06 1.500E+05 1.180E+05 0.000E+00 5.590E+05 1.030E+06 1.990E+05 W-187 1.630E+01 9.660E+00 4.330E+00 0.000E+00 0.000E+00 4.110E+04 9.100E+04 NP-239 4.700E+02 3.340E+01 2.350E+01 0.000E+00 9.730E+01 5.810E+04 6.400E+04 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 278 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS INFANT (mrem/yr per uCi/m 3)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 6.470E+02 6.470E+02 6.470E+02 6.470E+02 6.470E+02 6.470E+02 C-14 2.650E+04 5.310E+03 5.310E+03 5.310E+03 5.310E+03 5.310E+03 5.310E+03 NA-24 1.060E+04 1.060E+04 1.060E+04 1.060E+04 1.060E+04 1.060E+04 1.060E+04 P-32 2.030E+06 1.120E+05 7.740E+04 0.000E+00 0.000E+00 0.000E+00 1.610E+04 CR-51 0.000E+00 0.000E+00 8.950E+01 5.750E+01 1.320E+01 1.280E+04 3.570E+02 MN-54 0.000E+00 2.530E+04 4.980E+03 0.000E+00 4.980E+03 1.000E+06 7.060E+03 MN-56 0.000E+00 1.540E+00 2.210E-01 0.000E+00 1.100E+00 1.250E+04 7.170E+04 FE-55 1.970E+04 1.170E+04 3.330E+03 0.000E+00 0.000E+00 8.690E+04 1.090E+03 FE-59 1.360E+04 2.350E+04 9.480E+03 0.000E+00 0.000E+00 1.020E+06 2.480E+04 CO-57 0.000E+00 6.510E+02 6.410E+02 0.000E+00 0.000E+00 3.790E+05 4.860E+03 CO-58 0.000E+00 1.220E+03 1.820E+03 0.000E+00 0.000E+00 7.770E+05 1.110E+04 CO-60 0.000E+00 8.020E+03 1.180E+04 0.000E+00 0.000E+00 4.510E+06 3.190E+04 NI-63 3.390E+05 2.040E+04 1.160E+04 0.000E+00 0.000E+00 2.090E+05 2.420E+03 NI-65 2.390E+00 2.840E-01 1.230E-01 0.000E+00 0.000E+00 8.120E+03 5.010E+04 CU-64 0.000E+00 1.880E+00 7.740E-01 0.000E+00 3.980E+00 9.300E+03 1.500E+04 ZN-65 1.930E+04 6.260E+04 3.110E+04 0.000E+00 3.250E+04 6.470E+05 5.140E+04 ZN-69 5.390E-02 9.670E-02 7.180E-03 0.000E+00 4.020E-02 1.470E+03 1.320E+04 BR-82 0.000E+00 0.000E+00 1.330E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 3.810E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 4.000E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 2.040E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 1.900E+05 8.820E+04 0.000E+00 0.000E+00 0.000E+00 3.040E+03 RB-88 0.000E+00 5.570E+02 2.870E+02 0.000E+00 0.000E+00 0.000E+00 3.390E+02 RB-89 0.000E+00 3.210E+02 2.060E+02 0.000E+00 0.000E+00 0.000E+00 6.820E+01 SR-89 3.980E+05 0.000E+00 1.140E+04 0.000E+00 0.000E+00 2.030E+06 6.400E+04 SR-90 4.090E+07 0.000E+00 2.590E+06 0.000E+00 0.000E+00 1.120E+07 1.310E+05 SR-91 9.560E+01 0.000E+00 3.460E+00 0.000E+00 0.000E+00 5.260E+04 7.340E+04 SR-92 1.050E+01 0.000E+00 3.910E-01 0.000E+00 0.000E+00 2.380E+04 1.400E+05 Y-90 3.290E+03 0.000E+00 8.820E+01 0.000E+00 0.000E+00 2.690E+05 1.040E+05 Y-91M 4.070E-01 0.000E+00 1.390E-02 0.000E+00 0.000E+00 2.790E+03 2.350E+03 Y-91 5.880E+05 0.000E+00 1.570E+04 0.000E+00 0.000E+00 2.450E+06 7.030E+04 Y-92 1.640E+01 0.000E+00 4.610E-01 0.000E+00 0.000E+00 2.450E+04 1.270E+05 Y-93 1.500E+02 0.000E+00 4.070E+00 0.000E+00 0.000E+00 7.640E+04 1.670E+05 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 279 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS INFANT (mrem/yr per uCi/m3)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract ZR-95 1.150E+05 2.790E+04 2.030E+04 0.000E+00 3.110E+04 1.750E+06 2.170E+04 ZR-97 1.500E+02 2.560E+01 1.170E+01 0.000E+00 2.590E+01 1.100E+05 1.400E+05 NB-95 1.570E+04 6.430E+03 3.780E+03 0.000E+00 4.720E+03 4.790E+05 1.270E+04 NB-97 3.420E-01 7.290E-02 2.630E-02 0.000E+00 5.700E-02 3.320E+03 2.690E+04 MO-99 0.000E+00 1.650E+02 3.230E+01 0.000E+00 2.650E+02 1.350E+05 4.870E+04 TC-99M 1.400E-03 2.880E-03 3.720E-02 0.000E+00 3.110E-02 8.110E+02 2.030E+03 TC-101 6.510E-05 8.230E-05 8.120E-04 0.000E+00 9.790E-04 5.840E+02 8.440E+02 RU-103 2.020E+03 0.000E+00 6.790E+02 0.000E+00 4.240E+03 5.520E+05 1.610E+04 RU-105 1.220E+00 0.000E+00 4.100E-01 0.000E+00 8.990E-01 1.570E+04 4.840E+04 RU-106 8.680E+04 0.000E+00 1.090E+04 0.000E+00 1.070E+05 1.160E+07 1.640E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 9.980E+03 7.220E+03 5.000E+03 0.000E+00 1.090E+04 3.670E+06 3.300E+04 SB-122 5.430E+02 7.200E+02 7.200E+03 1.880E+02 2.720E+02 2.930E+04 3.540E+04 SB-124 3.790E+04 5.560E+02 1.200E+04 1.010E+02 0.000E+00 2.650E+06 5.910E+04 SB-125 5.170E+04 4.770E+02 1.090E+04 6.230E+01 0.000E+00 1.640E+06 1.470E+04 TE-125M 4.760E+03 1.990E+03 6.580E+02 1.620E+03 0.000E+00 4.470E+05 1.290E+04 TE-127M 1.670E+04 6.900E+03 2.070E+03 4.870E+03 3.750E+04 1.310E+06 2.730E+04 TE-127 2.230E+00 9.530E-01 4.890E-01 1.850E+00 4.860E+00 1.030E+04 2.440E+04 TE-129M 1.410E+04 6.090E+03 2.230E+03 5.470E+03 3.180E+04 1.680E+06 6.900E+04 TE-129 7.880E-02 3.470E-02 1.880E-02 6.750E-02 1.750E-01 3.000E+03 2.630E+04 TE-131M 1.070E+02 5.500E+01 3.630E+01 8.930E+01 2.650E+02 1.990E+05 1.190E+05 TE-131 1.740E-02 8.220E-03 5.000E-03 1.580E-02 3.990E-02 2.060E+03 8.220E+03 TE-132 3.720E+02 2.370E+02 1.760E+02 2.790E+02 1.030E+03 3.400E+05 4.410E+04 I-130 6.360E+03 1.390E+04 5.570E+03 1.600E+06 1.530E+04 0.000E+00 1.990E+03 I-131 3.790E+04 4.440E+04 1.960E+04 1.480E+07 5.180E+04 0.000E+00 1.060E+03 I-132 1.690E+03 3.540E+03 1.260E+03 1.690E+05 3.950E+03 0.000E+00 1.900E+03 I-133 1.320E+04 1.920E+04 5.600E+03 3.560E+06 2.240E+04 0.000E+00 2.160E+03 I-134 9.210E+02 1.880E+03 6.650E+02 4.450E+04 2.090E+03 0.000E+00 1.290E+03 I-135 3.860E+03 7.600E+03 2.770E+03 6.960E+05 8.470E+03 0.000E+00 1.830E+03 CS-134 3.960E+05 7.030E+05 7.450E+04 0.000E+00 1.900E+05 7.970E+04 1.330E+03 CS-136 4.830E+04 1.350E+05 5.290E+04 0.000E+00 5.640E+04 1.180E+04 1.430E+03 CS-137 5.490E+05 6.120E+05 4.550E+04 0.000E+00 1.720E+05 7.130E+04 1.330E+03 CS-138 5.050E+02 7.810E+02 3.980E+02 0.000E+00 4.100E+02 6.540E+01 8.760E+02 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 280 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors INHALATION DOSE FACTORS INFANT (mrem/yr per uCi/m 3)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BA-139 1.480E+00 9.840E-04 4.300E-02 0.000E+00 5.920E-04 5.950E+03 5.100E+04 BA-140 5.600E+04 5.600E+01 2.900E+03 0.000E+00 1.340E+01 1.600E+06 3.840E+04 BA-141 1.570E-01 1.080E-04 4.970E-03 0.000E+00 6.500E-05 2.970E+03 4.750E+03 BA-142 3.980E-02 3.300E-05 1.960E-03 0.000E+00 1.900E-05 1.550E+03 6.930E+02 LA-140 5.050E+02 2.000E+02 5.150E+01 0.000E+00 0.000E+00 1.680E+05 8.480E+04 LA-142 1.030E+00 3.770E-01 9.040E-02 0.000E+00 0.000E+00 8.220E+03 5.950E+04 CE-141 2.770E+04 1.670E+04 1.990E+03 0.000E+00 5.250E+03 5.170E+05 2.160E+04 CE-143 2.930E+02 1.930E+02 2.210E+01 0.000E+00 5.640E+01 1.160E+05 4.970E+04 CE-144 3.190E+06 1.210E+06 1.760E+05 0.000E+00 5.380E+05 9.840E+06 1.480E+05 PR-143 1.400E+04 5.240E+03 6.990E+02 0.000E+00 1.970E+03 4.330E+05 3.720E+04 PR-144 4.790E-02 1.850E-02 2.410E-03 0.000E+00 6.720E-03 1.610E+03 4.280E+03 ND-147 7.940E+03 8.130E+03 5.000E+02 0.000E+00 3.150E+03 3.220E+05 3.120E+04 EU-154 4.140E+06 4.840E+05 3.430E+05 0.000E+00 1.540E+06 4.270E+06 3.980E+04 EU-155 8.360E+05 8.010E+04 4.840E+04 0.000E+00 2.210E+05 7.280E+05 7.270E+04 W-187 1.300E+01 9.020E+00 3.120E+00 0.000E+00 0.000E+00 3.960E+04 3.560E+04 NP-239 3.710E+02 3.320E+01 1.880E+01 0.000E+00 6.620E+01 5.950E+04 2.490E+04 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 281 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS ADULT (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 7.630E+02 7.630E+02 7.630E+02 7.630E+02 7.630E+02 7.630E+02 C-14 3.630E+05 7.260E+04 7.260E+04 7.260E+04 7.260E+04 7.260E+04 7.260E+04 NA-24 2.540E+06 2.540E+06 2.540E+06 2.540E+06 2.540E+06 2.540E+06 2.540E+06 P-32 1.710E+10 1.060E+09 6.600E+08 0.000E+00 0.000E+00 0.000E+00 1.920E+09 CR-51 0.000E+00 0.000E+00 2.860E+04 1.710E+04 6.300E+03 3.800E+04 7.200E+06 MN-54 0.000E+00 8.400E+06 1.600E+06 0.000E+00 2.500E+06 0.000E+00 2.570E+07 MN-56 0.000E+00 4.230E-03 7.510E-04 0.000E+00 5.380E-03 0.000E+00 1.350E-01 FE-55 2.510E+07 1.730E+07 4.040E+06 0.000E+00 0.000E+00 9.670E+06 9.950E+06 FE-59 2.980E+07 7.000E+07 2.680E+07 0.000E+00 0.000E+00 1.950E+07 2.330E+08 CO-57 0.000E+00 1.280E+06 2.130E+06 0.000E+00 0.000E+00 0.000E+00 3.250E+07 CO-58 0.000E+00 4.720E+06 1.060E+07 0.000E+00 0.000E+00 0.000E+00 9.570E+07 CO-60 0.000E+00 1.640E+07 3.620E+07 0.000E+00 0.000E+00 0.000E+00 3.080E+08 NI-63 6.730E+09 4.660E+08 2.260E+08 0.000E+00 0.000E+00 0.000E+00 9.730E+07 NI-65 3.700E-01 4.810E-02 2.190E-02 0.000E+00 0.000E+00 0.000E+00 1.220E+00 CU-64 0.000E+00 2.410E+04 1.130E+04 0.000E+00 6.080E+04 0.000E+00 2.050E+06 ZN-65 1.370E+09 4.360E+09 1.970E+09 0.000E+00 2.920E+09 0.000E+00 2.750E+09 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.590E+09 1.210E+09 0.000E+00 0.000E+00 0.000E+00 5.110E+08 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 1.450E+09 0.000E+00 4.160E+07 0.000E+00 0.000E+00 0.000E+00 2.330E+08 SR-90 4.680E+10 0.000E+00 1.150E+10 0.000E+00 0.000E+00 0.000E+00 1.350E+09 SR-91 3.130E+04 0.000E+00 1.270E+03 0.000E+00 0.000E+00 0.000E+00 1.490E+05 SR-92 4.890E-01 0.000E+00 2.110E-02 0.000E+00 0.000E+00 0.000E+00 9.680E+00 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 282 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS ADULT (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract Y-90 7.070E+01 0.000E+00 1.900E+00 0.000E+00 0.000E+00 0.000E+00 7.500E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 8.600E+03 0.000E+00 2.300E+02 0.000E+00 0.000E+00 0.000E+00 4.730E+06 Y-92 5.420E-05 0.000E+00 1.580E-06 0.000E+00 0.000E+00 0.000E+00 9.490E-01 Y-93 2.330E-01 0.000E+00 6.430E-03 0.000E+00 0.000E+00 0.000E+00 7.390E+03 ZR-95 9.460E+02 3.030E+02 2.050E+02 0.000E+00 4.760E+02 0.000E+00 9.620E+05 ZR-97 4.260E-01 8.590E-02 3.930E-02 0.000E+00 1.300E-01 0.000E+00 2.660E+04 NB-95 8.250E+04 4.590E+04 2.470E+04 0.000E+00 4.540E+04 0.000E+00 2.790E+08 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.470E-09 MO-99 0.000E+00 2.520E+07 4.800E+06 0.000E+00 5.720E+07 0.000E+00 5.850E+07 TC-99M 3.250E+00 9.190E+00 1.170E+02 0.000E+00 1.400E+02 4.500E+00 5.440E+03 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 1.020E+03 0.000E+00 4.390E+02 0.000E+00 3.890E+03 0.000E+00 1.190E+05 RU-105 8.570E-04 0.000E+00 3.380E-04 0.000E+00 1.110E-02 0.000E+00 5.240E-01 RU-106 2.040E+04 0.000E+00 2.580E+03 0.000E+00 3.940E+04 0.000E+00 1.320E+06 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 5.830E+07 5.390E+07 3.200E+07 0.000E+00 1.060E+08 0.000E+00 2.200E+10 SB-122 6.010E+05 6.270E+05 7.590E+06 9.960E+04 2.960E+05 1.290E+05 7.470E+07 SB-124 8.580E+08 1.620E+07 3.400E+08 2.080E+06 0.000E+00 6.680E+08 2.440E+10 SB-125 6.810E+08 7.610E+06 1.620E+08 6.930E+05 0.000E+00 5.250E+08 7.500E+09 TE-125M 1.630E+07 5.900E+06 2.180E+06 4.900E+06 6.630E+07 0.000E+00 6.500E+07 TE-127M 4.580E+07 1.640E+07 5.580E+06 1.170E+07 1.860E+08 0.000E+00 1.540E+08 TE-127 6.720E+02 2.410E+02 1.450E+02 4.980E+02 2.740E+03 0.000E+00 5.300E+04 TE-129M 6.040E+07 2.250E+07 9.570E+06 2.080E+07 2.520E+08 0.000E+00 3.040E+08 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 3.610E+05 1.770E+05 1.470E+05 2.800E+05 1.790E+06 0.000E+00 1.750E+07 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 2.390E+06 1.550E+06 1.450E+06 1.710E+06 1.490E+07 0.000E+00 7.320E+07 I-130 4.260E+05 1.260E+06 4.960E+05 1.070E+08 1.960E+06 0.000E+00 1.080E+06 I-131 2.960E+08 4.240E+08 2.430E+08 1.390E+11 7.270E+08 0.000E+00 1.120E+08 I-132 1.640E-01 4.370E-01 1.530E-01 1.530E+01 6.970E-01 0.000E+00 8.220E-02 I-133 3.970E+06 6.900E+06 2.100E+06 1.010E+09 1.200E+07 0.000E+00 6.200E+06 December 2018

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Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 1.390E+04 3.630E+04 1.340E+04 2.400E+06 5.830E+04 0.000E+00 4.100E+04 CS-134 5.650E+09 1.340E+10 1.100E+10 0.000E+00 4.350E+09 1.440E+09 2.350E+08 CS-136 2.610E+08 1.030E+09 7.420E+08 0.000E+00 5.740E+08 7.870E+07 1.170E+08 CS-137 7.380E+09 1.010E+10 6.610E+09 0.000E+00 3.430E+09 1.140E+09 1.950E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 4.700E-08 0.000E+00 1.380E-09 0.000E+00 0.000E+00 0.000E+00 8.340E-08 BA-140 2.690E+07 3.380E+04 1.760E+06 0.000E+00 1.150E+04 1.930E+04 5.540E+07 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 4.490E+00 2.260E+00 5.970E-01 0.000E+00 0.000E+00 0.000E+00 1.660E+05 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.030E-08 CE-141 4.840E+03 3.270E+03 3.710E+02 0.000E+00 1.520E+03 0.000E+00 1.250E+07 CE-143 4.190E+01 3.090E+04 3.420E+00 0.000E+00 1.360E+01 0.000E+00 1.160E+06 CE-144 3.580E+05 1.500E+05 1.920E+04 0.000E+00 8.870E+04 0.000E+00 1.210E+08 PR-143 1.590E+02 6.370E+01 7.880E+00 0.000E+00 3.680E+01 0.000E+00 6.960E+05 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 9.420E+01 1.090E+02 6.520E+00 0.000E+00 6.370E+01 0.000E+00 5.230E+05 EU-154 2.370E+04 2.910E+03 2.070E+03 0.000E+00 1.390E+04 0.000E+00 2.110E+06 EU-155 3.300E+03 4.680E+02 3.020E+02 0.000E+00 2.160E+03 0.000E+00 3.680E+05 W-187 6.560E+03 5.480E+03 1.920E+03 0.000E+00 0.000E+00 0.000E+00 1.800E+06 NP-239 3.660E+00 3.600E-01 1.980E-01 0.000E+00 1.120E+00 0.000E+00 7.390E+04 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 284 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS TEEN (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 9.940E+02 9.940E+02 9.940E+02 9.940E+02 9.940E+02 9.940E+02 C-14 6.700E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 NA-24 4.440E+06 4.440E+06 4.440E+06 4.440E+06 4.440E+06 4.440E+06 4.440E+06 P-32 3.150E+10 1.950E+09 1.220E+09 0.000E+00 0.000E+00 0.000E+00 2.650E+09 CR-51 0.000E+00 0.000E+00 5.000E+04 2.780E+04 1.100E+04 7.130E+04 8.400E+06 MN-54 0.000E+00 1.400E+07 2.780E+06 0.000E+00 4.170E+06 0.000E+00 2.870E+07 MN-56 0.000E+00 7.510E-03 1.330E-03 0.000E+00 9.500E-03 0.000E+00 4.940E-01 FE-55 4.450E+07 3.160E+07 7.360E+06 0.000E+00 0.000E+00 2.000E+07 1.370E+07 FE-59 5.200E+07 1.210E+08 4.680E+07 0.000E+00 0.000E+00 3.820E+07 2.870E+08 CO-57 0.000E+00 2.250E+06 3.760E+06 0.000E+00 0.000E+00 0.000E+00 4.190E+07 CO-58 0.000E+00 7.950E+06 1.830E+07 0.000E+00 0.000E+00 0.000E+00 1.100E+08 CO-60 0.000E+00 2.780E+07 6.260E+07 0.000E+00 0.000E+00 0.000E+00 3.620E+08 NI-63 1.180E+10 8.350E+08 4.010E+08 0.000E+00 0.000E+00 0.000E+00 1.330E+08 NI-65 6.780E-01 8.660E-02 3.940E-02 0.000E+00 0.000E+00 0.000E+00 4.700E+00 CU-64 0.000E+00 4.290E+04 2.020E+04 0.000E+00 1.090E+05 0.000E+00 3.330E+06 ZN-65 2.110E+09 7.310E+09 3.410E+09 0.000E+00 4.680E+09 0.000E+00 3.100E+09 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 4.730E+09 2.220E+09 0.000E+00 0.000E+00 0.000E+00 7.000E+08 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 2.670E+09 0.000E+00 7.660E+07 0.000E+00 0.000E+00 0.000E+00 3.180E+08 SR-90 6.610E+10 0.000E+00 1.630E+10 0.000E+00 0.000E+00 0.000E+00 1.860E+09 SR-91 5.750E+04 0.000E+00 2.290E+03 0.000E+00 0.000E+00 0.000E+00 2.610E+05 SR-92 8.950E-01 0.000E+00 3.810E-02 0.000E+00 0.000E+00 0.000E+00 2.280E+01 Y-90 1.300E+02 0.000E+00 3.500E+00 0.000E+00 0.000E+00 0.000E+00 1.070E+06 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 1.580E+04 0.000E+00 4.240E+02 0.000E+00 0.000E+00 0.000E+00 6.480E+06 Y-92 1.000E-04 0.000E+00 2.900E-06 0.000E+00 0.000E+00 0.000E+00 2.750E+00 Y-93 4.300E-01 0.000E+00 1.180E-02 0.000E+00 0.000E+00 0.000E+00 1.310E+04 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 285 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS TEEN (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract ZR-95 1.650E+03 5.220E+02 3.590E+02 0.000E+00 7.670E+02 0.000E+00 1.200E+06 ZR-97 7.750E-01 1.530E-01 7.060E-02 0.000E+00 2.320E-01 0.000E+00 4.150E+04 NB-95 1.410E+05 7.800E+04 4.300E+04 0.000E+00 7.570E+04 0.000E+00 3.340E+08 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.340E-08 MO-99 0.000E+00 4.560E+07 8.690E+06 0.000E+00 1.040E+08 0.000E+00 8.160E+07 TC-99M 5.640E+00 1.570E+01 2.040E+02 0.000E+00 2.340E+02 8.730E+00 1.030E+04 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 1.810E+03 0.000E+00 7.750E+02 0.000E+00 6.400E+03 0.000E+00 1.520E+05 RU-105 1.570E-03 0.000E+00 6.080E-04 0.000E+00 1.970E-02 0.000E+00 1.260E+00 RU-106 3.750E+04 0.000E+00 4.730E+03 0.000E+00 7.230E+04 0.000E+00 1.800E+06 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 9.630E+07 9.110E+07 5.540E+07 0.000E+00 1.740E+08 0.000E+00 2.560E+10 SB-122 7.760E+05 8.090E+05 9.800E+06 1.290E+05 3.820E+05 1.660E+05 9.640E+07 SB-124 1.530E+09 2.820E+07 5.970E+08 3.470E+06 0.000E+00 1.340E+09 3.080E+10 SB-125 1.220E+09 1.330E+07 2.850E+08 1.160E+06 0.000E+00 1.070E+09 9.480E+09 TE-125M 3.000E+07 1.080E+07 4.020E+06 8.390E+06 0.000E+00 0.000E+00 8.860E+07 TE-127M 8.440E+07 2.990E+07 1.000E+07 2.010E+07 3.420E+08 0.000E+00 2.100E+08 TE-127 1.240E+03 4.410E+02 2.680E+02 8.590E+02 5.040E+03 0.000E+00 9.610E+04 TE-129M 1.110E+08 4.100E+07 1.750E+07 3.570E+07 4.620E+08 0.000E+00 4.150E+08 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.670E-09 0.000E+00 2.180E-09 TE-131M 6.570E+05 3.150E+05 2.630E+05 4.740E+05 3.290E+06 0.000E+00 2.530E+07 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 4.280E+06 2.710E+06 2.550E+06 2.860E+06 2.600E+07 0.000E+00 8.580E+07 I-130 7.490E+05 2.170E+06 8.660E+05 1.770E+08 3.340E+06 0.000E+00 1.670E+06 I-131 5.380E+08 7.530E+08 4.040E+08 2.200E+11 1.300E+09 0.000E+00 1.490E+08 I-132 2.900E-01 7.590E-01 2.720E-01 2.560E+01 1.200E+00 0.000E+00 3.310E-01 I-133 7.240E+06 1.230E+07 3.750E+06 1.720E+09 2.150E+07 0.000E+00 9.300E+06 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 2.470E+04 6.350E+04 2.350E+04 4.080E+06 1.000E+05 0.000E+00 7.030E+04 CS-134 9.810E+09 2.310E+10 1.070E+10 0.000E+00 7.340E+09 2.800E+09 2.870E+08 CS-136 4.450E+08 1.750E+09 1.180E+09 0.000E+00 9.530E+08 1.500E+08 1.410E+08 CS-137 1.340E+10 1.780E+10 6.200E+09 0.000E+00 6.060E+09 2.350E+09 2.530E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 286 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS TEEN (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BA-139 8.690E-08 0.000E+00 2.530E-09 0.000E+00 0.000E+00 0.000E+00 7.750E-07 BA-140 4.850E+07 5.950E+04 3.130E+06 0.000E+00 2.020E+04 4.000E+04 7.490E+07 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 8.060E+00 3.960E+00 1.050E+00 0.000E+00 0.000E+00 0.000E+00 2.270E+05 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.230E-07 CE-141 8.870E+03 5.920E+03 6.810E+02 0.000E+00 2.790E+03 0.000E+00 1.690E+07 CE-143 7.690E+01 5.600E+04 6.250E+00 0.000E+00 2.510E+01 0.000E+00 1.680E+06 CE-144 6.580E+05 2.720E+05 3.540E+04 0.000E+00 1.630E+05 0.000E+00 1.660E+08 PR-143 2.920E+02 1.170E+02 1.450E+01 0.000E+00 6.770E+01 0.000E+00 9.610E+05 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 1.810E+02 1.970E+02 1.180E+01 0.000E+00 1.160E+02 0.000E+00 7.110E+05 EU-154 3.920E+04 5.060E+03 3.570E+03 0.000E+00 2.260E+04 0.000E+00 2.670E+06 EU-155 8.600E+03 8.310E+02 5.140E+02 0.000E+00 3.250E+03 0.000E+00 4.760E+06 W-187 1.200E+04 9.780E+03 3.430E+03 0.000E+00 0.000E+00 0.000E+00 2.650E+06 NP-239 6.990E+00 6.590E-01 3.660E-01 0.000E+00 2.070E+00 0.000E+00 1.060E+05 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 287 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS CHILD (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 1.570E+03 1.570E+03 1.570E+03 1.570E+03 1.570E+03 1.570E+03 C-14 1.650E+06 3.290E+05 3.290E+05 3.290E+05 3.290E+05 3.290E+05 3.290E+05 NA-24 9.230E+06 9.230E+06 9.230E+06 9.230E+06 9.230E+06 9.230E+06 9.230E+06 P-32 7.770E+10 3.640E+09 3.000E+09 0.000E+00 0.000E+00 0.000E+00 2.150E+09 CR-51 0.000E+00 0.000E+00 1.020E+05 5.660E+04 1.550E+04 1.030E+05 5.410E+06 MN-54 0.000E+00 2.090E+07 5.580E+06 0.000E+00 5.870E+06 0.000E+00 1.760E+07 MN-56 0.000E+00 1.310E-02 2.950E-03 0.000E+00 1.580E-02 0.000E+00 1.900E+00 FE-55 1.120E+08 5.930E+07 1.840E+07 0.000E+00 0.000E+00 3.350E+07 1.100E+07 FE-59 1.200E+08 1.950E+08 9.710E+07 0.000E+00 0.000E+00 5.650E+07 2.030E+08 CO-57 0.000E+00 3.840E+06 7.770E+06 0.000E+00 0.000E+00 0.000E+00 3.140E+07 CO-58 0.000E+00 1.210E+07 3.720E+07 0.000E+00 0.000E+00 0.000E+00 7.080E+07 CO-60 0.000E+00 4.320E+07 1.270E+08 0.000E+00 0.000E+00 0.000E+00 2.390E+08 NI-63 2.960E+10 1.590E+09 1.010E+09 0.000E+00 0.000E+00 0.000E+00 1.070E+08 NI-65 1.660E+00 1.560E-01 9.110E-02 0.000E+00 0.000E+00 0.000E+00 1.910E+01 CU-64 0.000E+00 7.550E+04 4.560E+04 0.000E+00 1.820E+05 0.000E+00 3.540E+06 ZN-65 4.130E+09 1.100E+10 6.850E+09 0.000E+00 6.940E+09 0.000E+00 1.930E+09 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.140E-09 BR-82 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 8.770E+09 5.390E+09 0.000E+00 0.000E+00 0.000E+00 5.640E+08 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 6.620E+09 0.000E+00 1.890E+08 0.000E+00 0.000E+00 0.000E+00 2.560E+08 SR-90 1.120E+11 0.000E+00 2.830E+10 0.000E+00 0.000E+00 0.000E+00 1.510E+09 SR-91 1.410E+05 0.000E+00 5.330E+03 0.000E+00 0.000E+00 0.000E+00 3.120E+05 SR-92 2.190E+00 0.000E+00 8.760E-02 0.000E+00 0.000E+00 0.000E+00 4.140E+01 Y-90 3.220E+02 0.000E+00 8.610E+00 0.000E+00 0.000E+00 0.000E+00 9.150E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 3.910E+04 0.000E+00 1.040E+03 0.000E+00 0.000E+00 0.000E+00 5.210E+06 Y-92 2.460E-04 0.000E+00 7.030E-06 0.000E+00 0.000E+00 0.000E+00 7.100E+00 Y-93 1.060E+00 0.000E+00 2.900E-02 0.000E+00 0.000E+00 0.000E+00 1.570E+04 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 288 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS CHILD (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract ZR-95 3.840E+03 8.450E+02 7.520E+02 0.000E+00 1.210E+03 0.000E+00 8.810E+05 ZR-97 1.890E+00 2.720E-01 1.610E-01 0.000E+00 3.910E-01 0.000E+00 4.130E+04 NB-95 3.180E+05 1.240E+05 8.840E+04 0.000E+00 1.160E+05 0.000E+00 2.290E+08 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.450E-06 MO-99 0.000E+00 8.290E+07 2.050E+07 0.000E+00 1.770E+08 0.000E+00 6.860E+07 TC-99M 1.290E+01 2.540E+01 4.200E+02 0.000E+00 3.680E+02 1.290E+01 1.440E+04 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 4.290E+03 0.000E+00 1.650E+03 0.000E+00 1.080E+04 0.000E+00 1.110E+05 RU-105 3.820E-03 0.000E+00 1.390E-03 0.000E+00 3.360E-02 0.000E+00 2.490E+00 RU-106 9.240E+04 0.000E+00 1.150E+04 0.000E+00 1.250E+05 0.000E+00 1.440E+06 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 2.090E+08 1.410E+08 1.130E+08 0.000E+00 2.630E+08 0.000E+00 1.680E+10 SB-122 4.140E+06 4.320E+06 5.230E+07 6.870E+05 2.040E+06 8.890E+05 5.150E+08 SB-124 3.620E+09 4.700E+07 1.270E+09 7.990E+06 0.000E+00 2.010E+09 2.260E+10 SB-125 2.900E+09 2.240E+07 6.080E+08 2.690E+06 0.000E+00 1.620E+09 6.930E+09 TE-125M 7.380E+07 2.000E+07 9.840E+06 2.070E+07 0.000E+00 0.000E+00 7.120E+07 TE-127M 2.080E+08 5.600E+07 2.470E+07 4.970E+07 5.930E+08 0.000E+00 1.680E+08 TE-127 3.060E+03 8.250E+02 6.560E+02 2.120E+03 8.710E+03 0.000E+00 1.200E+05 TE-129M 2.720E+08 7.610E+07 4.230E+07 8.780E+07 8.000E+08 0.000E+00 3.320E+08 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.870E-09 0.000E+00 6.120E-08 TE-131M 1.600E+06 5.530E+05 5.890E+05 1.140E+06 5.350E+06 0.000E+00 2.240E+07 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 1.020E+07 4.520E+06 5.460E+06 6.580E+06 4.200E+07 0.000E+00 4.550E+07 I-130 1.750E+06 3.540E+06 1.820E+06 3.900E+08 5.290E+06 0.000E+00 1.660E+06 I-131 1.300E+09 1.310E+09 7.460E+08 4.340E+11 2.150E+09 0.000E+00 1.170E+08 I-132 6.860E-01 1.260E+00 5.800E-01 5.850E+01 1.930E+00 0.000E+00 1.480E+00 I-133 1.760E+07 2.180E+07 8.230E+06 4.040E+09 3.630E+07 0.000E+00 8.770E+06 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 5.840E+04 1.050E+05 4.970E+04 9.300E+06 1.610E+05 0.000E+00 8.000E+04 CS-134 2.260E+10 3.710E+10 7.830E+09 0.000E+00 1.150E+10 4.130E+09 2.000E+08 CS-136 1.000E+09 2.760E+09 1.790E+09 0.000E+00 1.470E+09 2.190E+08 9.700E+07 CS-137 3.220E+10 3.090E+10 4.550E+09 0.000E+00 1.010E+10 3.620E+09 1.930E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 289 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS CHILD (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BA-139 2.140E-07 0.000E+00 6.190E-09 0.000E+00 0.000E+00 0.000E+00 1.230E-05 BA-140 1.170E+08 1.030E+05 6.840E+06 0.000E+00 3.340E+04 6.120E+04 5.940E+07 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 1.930E+01 6.740E+00 2.270E+00 0.000E+00 0.000E+00 0.000E+00 1.880E+05 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.510E-06 CE-141 2.190E+04 1.090E+04 1.620E+03 0.000E+00 4.780E+03 0.000E+00 1.360E+07 CE-143 1.890E+02 1.020E+05 1.480E+01 0.000E+00 4.290E+01 0.000E+00 1.500E+06 CE-144 1.620E+06 5.090E+05 8.660E+04 0.000E+00 2.820E+05 0.000E+00 1.330E+08 PR-143 7.230E+02 2.170E+02 3.590E+01 0.000E+00 1.170E+02 0.000E+00 7.800E+05 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 4.450E+02 3.600E+02 2.790E+01 0.000E+00 1.980E+02 0.000E+00 5.710E+05 EU-154 9.420E+04 8.470E+03 7.740E+03 0.000E+00 3.720E+04 0.000E+00 1.970E+06 EU-155 1.970E+04 1.420E+03 1.110E+03 0.000E+00 5.300E+03 0.000E+00 3.540E+06 W-187 2.910E+04 1.720E+04 7.730E+03 0.000E+00 0.000E+00 0.000E+00 2.420E+06 NP-239 1.720E+01 1.230E+00 8.680E-01 0.000E+00 3.570E+00 0.000E+00 9.140E+04 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 290 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS INFANT (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 2.380E+03 2.380E+03 2.380E+03 2.380E+03 2.380E+03 2.380E+03 C-14 3.230E+06 6.890E+05 6.890E+05 6.890E+05 6.890E+05 6.890E+05 6.890E+05 NA-24 1.610E+07 1.610E+07 1.610E+07 1.610E+07 1.610E+07 1.610E+07 1.610E+07 P-32 1.600E+11 9.420E+09 6.210E+09 0.000E+00 0.000E+00 0.000E+00 2.170E+09 CR-51 0.000E+00 0.000E+00 1.610E+05 1.050E+05 2.300E+04 2.050E+05 4.710E+06 MN-54 0.000E+00 3.890E+07 8.830E+06 0.000E+00 8.630E+06 0.000E+00 1.430E+07 MN-56 0.000E+00 3.210E-02 5.530E-03 0.000E+00 2.760E-02 0.000E+00 2.910E+00 FE-55 1.350E+08 8.720E+07 2.330E+07 0.000E+00 0.000E+00 4.270E+07 1.110E+07 FE-59 2.250E+08 3.930E+08 1.550E+08 0.000E+00 0.000E+00 1.160E+08 1.880E+08 CO-57 0.000E+00 8.950E+06 1.460E+07 0.000E+00 0.000E+00 0.000E+00 3.050E+07 CO-58 0.000E+00 2.430E+07 6.060E+07 0.000E+00 0.000E+00 0.000E+00 6.050E+07 CO-60 0.000E+00 8.810E+07 2.080E+08 0.000E+00 0.000E+00 0.000E+00 2.100E+08 NI-63 3.490E+10 2.160E+09 1.210E+09 0.000E+00 0.000E+00 0.000E+00 1.070E+08 NI-65 3.510E+00 3.970E-01 1.810E-01 0.000E+00 0.000E+00 0.000E+00 3.020E+01 CU-64 0.000E+00 1.880E+05 8.690E+04 0.000E+00 3.170E+05 0.000E+00 3.850E+06 ZN-65 5.550E+09 1.900E+10 8.780E+09 0.000E+00 9.230E+09 0.000E+00 1.610E+10 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.360E-09 BR-82 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.220E+10 1.100E+10 0.000E+00 0.000E+00 0.000E+00 5.690E+08 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 1.260E+10 0.000E+00 3.610E+08 0.000E+00 0.000E+00 0.000E+00 2.590E+08 SR-90 1.220E+11 0.000E+00 3.100E+10 0.000E+00 0.000E+00 0.000E+00 1.520E+09 SR-91 2.940E+05 0.000E+00 1.060E+04 0.000E+00 0.000E+00 0.000E+00 3.480E+05 SR-92 4.650E+00 0.000E+00 1.730E-01 0.000E+00 0.000E+00 0.000E+00 5.010E+01 Y-90 6.800E+02 0.000E+00 1.820E+01 0.000E+00 0.000E+00 0.000E+00 9.390E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 7.330E+04 0.000E+00 1.950E+03 0.000E+00 0.000E+00 0.000E+00 5.260E+06 Y-92 5.220E-04 0.000E+00 1.470E-05 0.000E+00 0.000E+00 0.000E+00 9.970E+00 Y-93 2.250E+00 0.000E+00 6.130E-02 0.000E+00 0.000E+00 0.000E+00 1.780E+04 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 291 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS INFANT (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract ZR-95 6.830E+03 1.660E+03 1.180E+03 0.000E+00 1.790E+03 0.000E+00 8.280E+05 ZR-97 3.990E+00 6.850E-01 3.130E-01 0.000E+00 6.910E-01 0.000E+00 4.370E+04 NB-95 5.930E+05 2.440E+05 1.410E+05 0.000E+00 1.750E+05 0.000E+00 2.060E+08 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.700E-06 MO-99 0.000E+00 2.120E+08 4.130E+07 0.000E+00 3.170E+08 0.000E+00 6.980E+07 TC-99M 2.690E+01 5.550E+01 7.150E+02 0.000E+00 5.970E+02 2.900E+01 1.610E+04 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 8.690E+03 0.000E+00 2.910E+03 0.000E+00 1.810E+04 0.000E+00 1.060E+05 RU-105 8.060E-03 0.000E+00 2.710E-03 0.000E+00 5.920E-02 0.000E+00 3.210E+00 RU-106 1.900E+05 0.000E+00 2.380E+04 0.000E+00 2.250E+05 0.000E+00 1.440E+06 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 3.860E+08 2.820E+08 1.860E+08 0.000E+00 4.030E+08 0.000E+00 1.460E+10 SB-122 6.400E+05 6.670E+05 8.080E+06 1.060E+05 3.150E+05 1.370E+05 7.950E+07 SB-124 6.980E+09 1.030E+08 2.160E+09 1.850E+07 0.000E+00 4.370E+09 2.150E+10 SB-125 4.980E+09 4.820E+07 1.020E+09 6.240E+06 0.000E+00 3.130E+09 6.640E+09 TE-125M 1.510E+08 5.040E+07 2.040E+07 5.070E+07 0.000E+00 0.000E+00 7.180E+07 TE-127M 4.210E+08 1.400E+08 5.100E+07 1.220E+08 1.040E+09 0.000E+00 1.700E+08 TE-127 6.500E+03 2.180E+03 1.400E+03 5.290E+03 1.590E+04 0.000E+00 1.360E+05 TE-129M 5.590E+08 1.920E+08 8.620E+07 2.150E+08 1.400E+09 0.000E+00 3.340E+08 TE-129 2.080E-09 0.000E+00 0.000E+00 1.750E-09 5.180E-09 0.000E+00 1.660E-07 TE-131M 3.380E+06 1.360E+06 1.120E+06 2.760E+06 9.350E+06 0.000E+00 2.290E+07 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 2.100E+07 1.040E+07 9.720E+06 1.540E+07 6.510E+07 0.000E+00 3.850E+07 I-130 3.600E+06 7.920E+06 3.180E+06 8.880E+08 8.700E+06 0.000E+00 1.700E+06 I-131 2.720E+09 3.210E+09 1.410E+09 1.050E+12 3.750E+09 0.000E+00 1.150E+08 I-132 1.420E+00 2.890E+00 1.030E+00 1.350E+02 3.220E+00 0.000E+00 2.340E+00 I-133 3.720E+07 5.410E+07 1.580E+07 9.840E+09 6.360E+07 0.000E+00 9.160E+06 I-134 0.000E+00 0.000E+00 0.000E+00 1.010E-09 0.000E+00 0.000E+00 0.000E+00 I-135 1.210E+05 2.410E+05 8.800E+04 2.160E+07 2.690E+05 0.000E+00 8.740E+04 CS-134 3.650E+10 6.800E+10 6.870E+09 0.000E+00 1.750E+10 7.180E+09 1.850E+08 CS-136 1.960E+09 5.770E+09 2.150E+09 0.000E+00 2.300E+09 4.700E+08 8.760E+07 CS-137 5.150E+10 6.020E+10 4.270E+09 0.000E+00 1.620E+10 6.550E+09 1.880E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 292 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-COW-MILK DOSE FACTORS INFANT (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BA-139 4.550E-07 0.000E+00 1.320E-08 0.000E+00 0.000E+00 0.000E+00 2.880E-05 BA-140 2.410E+08 2.410E+05 1.240E+07 0.000E+00 5.730E+04 1.480E+05 5.920E+07 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 4.030E+01 1.590E+01 4.090E+00 0.000E+00 0.000E+00 0.000E+00 1.870E+05 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.210E-06 CE-141 4.330E+04 2.640E+04 3.110E+03 0.000E+00 8.150E+03 0.000E+00 1.370E+07 CE-143 4.000E+02 2.650E+05 3.020E+01 0.000E+00 7.720E+01 0.000E+00 1.550E+06 CE-144 2.330E+06 9.520E+05 1.300E+05 0.000E+00 3.850E+05 0.000E+00 1.330E+08 PR-143 1.490E+03 5.590E+02 7.410E+01 0.000E+00 2.080E+02 0.000E+00 7.890E+05 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 8.820E+02 9.060E+02 5.550E+01 0.000E+00 3.490E+02 0.000E+00 5.740E+05 EU-154 1.080E+05 1.500E+04 9.010E+03 0.000E+00 4.070E+04 0.000E+00 1.880E+06 EU-155 2.210E+04 2.550E+03 1.320E+03 0.000E+00 5.710E+03 0.000E+00 3.410E+06 W-187 6.120E+04 4.260E+04 1.470E+04 0.000E+00 0.000E+00 0.000E+00 2.500E+06 NP-239 3.640E+01 3.250E+00 1.840E+00 0.000E+00 6.490E+00 0.000E+00 9.400E+04 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 293 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS ADULT (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 1.560E+03 1.560E+03 1.560E+03 1.560E+03 1.560E+03 1.560E+03 C-14 3.630E+05 7.260E+04 7.260E+04 7.260E+04 7.260E+04 7.260E+04 7.260E+04 NA-24 3.050E+05 3.050E+05 3.050E+05 3.050E+05 3.050E+05 3.050E+05 3.050E+05 P-32 2.050E+10 1.270E+09 7.930E+08 0.000E+00 0.000E+00 0.000E+00 2.310E+09 CR-51 0.000E+00 0.000E+00 3.430E+03 2.050E+03 7.560E+02 4.560E+03 8.640E+05 MN-54 0.000E+00 1.010E+06 1.920E+05 0.000E+00 3.000E+05 0.000E+00 3.090E+06 MN-56 0.000E+00 5.080E-04 9.010E-05 0.000E+00 6.450E-04 0.000E+00 1.620E-02 FE-55 3.260E+05 2.250E+05 5.260E+04 0.000E+00 0.000E+00 1.260E+05 1.290E+05 FE-59 3.870E+05 9.090E+05 3.490E+05 0.000E+00 0.000E+00 2.540E+05 3.030E+06 CO-57 0.000E+00 1.540E+05 2.550E+05 0.000E+00 0.000E+00 0.000E+00 3.900E+06 CO-58 0.000E+00 5.660E+05 1.270E+06 0.000E+00 0.000E+00 0.000E+00 1.150E+07 CO-60 0.000E+00 1.970E+06 4.340E+06 0.000E+00 0.000E+00 0.000E+00 3.700E+07 NI-63 8.070E+08 5.600E+07 2.710E+07 0.000E+00 0.000E+00 0.000E+00 1.170E+07 NI-65 4.440E-02 5.770E-03 2.630E-03 0.000E+00 0.000E+00 0.000E+00 1.460E-01 CU-64 0.000E+00 2.690E+03 1.260E+03 0.000E+00 6.770E+03 0.000E+00 2.290E+05 ZN-65 1.650E+08 5.240E+08 2.370E+08 0.000E+00 3.500E+08 0.000E+00 3.300E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 3.900E+06 0.000E+00 0.000E+00 0.000E+00 4.470E+06 BR-83 0.000E+00 0.000E+00 1.240E-02 0.000E+00 0.000E+00 0.000E+00 1.790E-02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 3.110E+08 1.450E+08 0.000E+00 0.000E+00 0.000E+00 6.140E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 3.050E+09 0.000E+00 8.740E+07 0.000E+00 0.000E+00 0.000E+00 4.890E+08 SR-90 9.830E+10 0.000E+00 2.410E+10 0.000E+00 0.000E+00 0.000E+00 2.840E+09 SR-91 6.580E+04 0.000E+00 2.660E+03 0.000E+00 0.000E+00 0.000E+00 3.130E+05 SR-92 1.030E+00 0.000E+00 4.440E-02 0.000E+00 0.000E+00 0.000E+00 2.030E+01 Y-90 8.480E+00 0.000E+00 2.280E-01 0.000E+00 0.000E+00 0.000E+00 8.990E+04 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 1.030E+03 0.000E+00 2.760E+01 0.000E+00 0.000E+00 0.000E+00 5.680E+05 Y-92 6.510E-06 0.000E+00 1.900E-07 0.000E+00 0.000E+00 0.000E+00 1.140E-01 Y-93 2.800E-02 0.000E+00 7.720E-04 0.000E+00 0.000E+00 0.000E+00 8.870E+02 ZR-95 1.140E+02 3.640E+01 2.470E+01 0.000E+00 5.710E+01 0.000E+00 1.150E+05 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 294 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS ADULT (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract ZR-97 5.110E-02 1.030E-02 4.710E-03 0.000E+00 1.560E-02 0.000E+00 3.190E+03 NB-95 9.900E+03 5.510E+03 2.960E+03 0.000E+00 5.440E+03 0.000E+00 3.340E+07 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 MO-99 0.000E+00 3.030E+06 5.760E+05 0.000E+00 6.860E+06 0.000E+00 7.020E+06 TC-99M 3.900E-01 1.100E+00 1.400E+01 0.000E+00 1.670E+01 5.400E-01 6.520E+02 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 1.220E+02 0.000E+00 5.270E+01 0.000E+00 4.670E+02 0.000E+00 1.430E+04 RU-105 1.030E-04 0.000E+00 4.060E-05 0.000E+00 1.330E-03 0.000E+00 6.290E-02 RU-106 2.450E+03 0.000E+00 3.100E+02 0.000E+00 4.730E+03 0.000E+00 1.580E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 6.990E+06 6.470E+06 3.840E+06 0.000E+00 1.270E+07 0.000E+00 2.640E+09 SB-122 7.210E+04 7.520E+04 9.110E+05 1.200E+04 3.550E+04 1.550E+04 8.960E+06 SB-124 3.090E+06 5.840E+04 1.220E+06 7.490E+03 0.000E+00 2.410E+06 8.770E+07 SB-125 2.450E+06 2.740E+04 5.840E+05 2.490E+03 0.000E+00 1.890E+06 2.700E+07 TE-125M 1.950E+06 7.080E+05 2.620E+05 5.880E+05 7.950E+06 0.000E+00 7.810E+06 TE-127M 5.490E+06 1.960E+06 6.690E+05 1.400E+06 2.230E+07 0.000E+00 1.840E+07 TE-127 8.060E+01 2.890E+01 1.740E+01 5.970E+01 3.280E+02 0.000E+00 6.360E+03 TE-129M 7.250E+06 2.710E+06 1.150E+06 2.490E+06 3.030E+07 0.000E+00 3.650E+07 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 4.330E+04 2.120E+04 1.770E+04 3.360E+04 2.150E+05 0.000E+00 2.100E+06 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 2.870E+05 1.860E+05 1.740E+05 2.050E+05 1.790E+06 0.000E+00 8.790E+06 I-130 5.110E+05 1.510E+06 5.950E+05 1.280E+08 2.350E+06 0.000E+00 1.300E+06 I-131 3.560E+08 5.090E+08 2.920E+08 1.670E+11 8.720E+08 0.000E+00 1.340E+08 I-132 1.960E-01 5.250E-01 1.840E-01 1.840E+01 8.360E-01 0.000E+00 9.860E-02 I-133 4.760E+06 8.280E+06 2.520E+06 1.220E+09 1.440E+07 0.000E+00 7.440E+06 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 1.670E+04 4.360E+04 1.610E+04 2.880E+06 6.990E+04 0.000E+00 4.920E+04 CS-134 1.700E+10 4.030E+10 3.300E+10 0.000E+00 1.310E+10 4.330E+09 7.060E+08 CS-136 7.840E+08 3.090E+09 2.230E+09 0.000E+00 1.720E+09 2.360E+08 3.520E+08 CS-137 2.210E+10 3.030E+10 1.980E+10 0.000E+00 1.030E+10 3.420E+09 5.860E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 295 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS ADULT (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BA-139 5.640E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.000E-08 BA-140 3.230E+06 4.050E+03 2.110E+05 0.000E+00 1.380E+03 2.320E+03 6.650E+06 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 5.380E-01 2.710E-01 1.990E+04 0.000E+00 0.000E+00 0.000E+00 1.990E+04 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.640E-09 CE-141 5.810E+02 3.930E+02 4.450E+01 0.000E+00 1.820E+02 0.000E+00 1.500E+06 CE-143 5.020E+00 3.710E+03 4.110E-01 0.000E+00 1.630E+00 0.000E+00 1.390E+05 CE-144 4.290E+04 1.790E+04 2.300E+03 0.000E+00 1.060E+04 0.000E+00 1.450E+07 PR-143 1.910E+01 7.650E+00 9.450E-01 0.000E+00 4.410E+00 0.000E+00 8.350E+04 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 1.130E+01 1.310E+01 7.820E-01 0.000E+00 7.640E+00 0.000E+00 6.270E+04 EU-154 2.840E+03 3.490E+02 2.480E+02 0.000E+00 1.670E+03 0.000E+00 2.530E+05 EU-155 3.950E+02 5.610E+01 3.620E+01 0.000E+00 2.590E+02 0.000E+00 4.410E+04 W-187 7.870E+02 6.580E+02 2.300E+02 0.000E+00 0.000E+00 0.000E+00 2.160E+05 NP-239 4.390E-01 4.320E-02 2.380E-02 0.000E+00 1.350E-01 0.000E+00 8.860E+03 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 296 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS TEEN (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 2.030E+03 2.030E+03 2.030E+03 2.030E+03 2.030E+03 2.030E+03 C-14 6.700E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 1.340E+05 NA-24 5.330E+05 5.330E+05 5.330E+05 5.330E+05 5.330E+05 5.330E+05 5.330E+05 P-32 3.780E+10 2.340E+09 1.470E+09 0.000E+00 0.000E+00 0.000E+00 3.180E+09 CR-51 0.000E+00 0.000E+00 6.000E+03 3.330E+03 1.310E+03 8.560E+03 1.010E+06 MN-54 0.000E+00 1.680E+06 3.330E+05 0.000E+00 5.010E+05 0.000E+00 3.440E+06 MN-56 0.000E+00 9.010E-04 1.600E-04 0.000E+00 1.140E-03 0.000E+00 5.930E-02 FE-55 5.790E+05 4.100E+05 9.570E+04 0.000E+00 0.000E+00 2.600E+05 1.780E+05 FE-59 6.750E+05 1.580E+06 6.090E+05 0.000E+00 0.000E+00 4.970E+05 3.730E+06 CO-57 0.000E+00 2.690E+05 4.520E+05 0.000E+00 0.000E+00 0.000E+00 5.030E+06 CO-58 0.000E+00 9.540E+05 2.200E+06 0.000E+00 0.000E+00 0.000E+00 1.310E+07 CO-60 0.000E+00 3.340E+06 7.510E+06 0.000E+00 0.000E+00 0.000E+00 4.350E+07 NI-63 1.420E+09 1.000E+08 4.810E+07 0.000E+00 0.000E+00 0.000E+00 1.590E+07 NI-65 8.130E-02 1.040E-02 4.730E-03 0.000E+00 0.000E+00 0.000E+00 5.640E-01 CU-64 0.000E+00 4.790E+03 2.250E+03 0.000E+00 1.210E+04 0.000E+00 3.710E+05 ZN-65 2.530E+08 8.780E+08 4.090E+08 0.000E+00 5.620E+08 0.000E+00 3.720E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 6.670E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 2.290E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 5.670E+08 2.670E+08 0.000E+00 0.000E+00 0.000E+00 8.400E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 5.620E+09 0.000E+00 1.160E+08 0.000E+00 0.000E+00 0.000E+00 6.690E+08 SR-90 1.390E+11 0.000E+00 3.430E+11 0.000E+00 0.000E+00 0.000E+00 3.900E+09 SR-91 1.210E+05 0.000E+00 4.810E+03 0.000E+00 0.000E+00 0.000E+00 5.480E+05 SR-92 1.880E+00 0.000E+00 8.010E-02 0.000E+00 0.000E+00 0.000E+00 4.790E+01 Y-90 1.560E+01 0.000E+00 4.200E-01 0.000E+00 0.000E+00 0.000E+00 1.290E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 1.900E+03 0.000E+00 5.090E+01 0.000E+00 0.000E+00 0.000E+00 7.780E+05 Y-92 1.200E-05 0.000E+00 3.480E-07 0.000E+00 0.000E+00 0.000E+00 3.300E-01 Y-93 5.160E-02 0.000E+00 1.410E-03 0.000E+00 0.000E+00 0.000E+00 1.580E+03 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 297 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS TEEN (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract ZR-95 1.990E+02 6.260E+01 4.310E+01 0.000E+00 9.200E+01 0.000E+00 1.450E+05 ZR-97 9.300E-02 1.840E-02 8.480E-03 0.000E+00 2.790E-02 0.000E+00 4.980E+03 NB-95 1.690E+04 9.370E+03 5.160E+03 0.000E+00 9.080E+03 0.000E+00 4.010E+07 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.610E-09 MO-99 0.000E+00 5.470E+06 1.040E+06 0.000E+00 1.250E+07 0.000E+00 9.800E+06 TC-99M 6.770E-01 1.890E+00 2.450E+01 0.000E+00 2.810E+01 1.050E+00 1.240E+03 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 2.180E+02 0.000E+00 9.310E+01 0.000E+00 7.670E+02 0.000E+00 1.820E+04 RU-105 1.880E-04 0.000E+00 7.290E-05 0.000E+00 2.370E-03 0.000E+00 1.520E-01 RU-106 4.500E+03 0.000E+00 5.670E+02 0.000E+00 8.680E+03 0.000E+00 2.160E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 1.160E+07 1.090E+07 6.650E+06 0.000E+00 2.090E+07 0.000E+00 3.070E+09 SB-122 9.310E+04 9.710E+04 1.180E+06 1.540E+04 4.580E+04 2.000E+04 1.160E+07 SB-124 5.510E+06 1.020E+05 2.150E+06 1.250E+04 0.000E+00 4.810E+06 1.110E+08 SB-125 4.380E+06 4.790E+04 1.030E+06 4.190E+03 0.000E+00 3.850E+06 3.410E+07 TE-125M 3.600E+06 1.300E+06 4.820E+05 1.010E+06 0.000E+00 0.000E+00 1.060E+07 TE-127M 1.010E+07 3.590E+06 1.200E+06 2.410E+06 4.100E+07 0.000E+00 2.520E+07 TE-127 1.490E+02 5.290E+01 3.210E+01 1.030E+02 6.050E+02 0.000E+00 1.150E+04 TE-129M 1.330E+07 4.920E+06 2.100E+06 4.280E+06 5.550E+07 0.000E+00 4.980E+07 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 7.890E+04 3.780E+04 3.150E+04 5.690E+04 3.940E+05 0.000E+00 3.030E+06 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 5.130E+05 3.250E+05 3.060E+05 3.430E+05 3.120E+06 0.000E+00 1.030E+07 I-130 8.990E+05 2.600E+06 1.040E+06 2.120E+08 4.010E+06 0.000E+00 2.000E+06 I-131 6.450E+08 9.030E+08 4.850E+08 2.640E+11 1.560E+09 0.000E+00 1.790E+08 I-132 3.480E-01 9.110E-01 3.270E-01 3.070E+01 1.430E+00 0.000E+00 3.970E-01 I-133 8.690E+06 1.470E+07 4.500E+06 2.060E+09 2.590E+07 0.000E+00 1.120E+07 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 2.960E+04 7.620E+04 2.820E+04 4.900E+06 1.200E+05 0.000E+00 8.440E+04 CS-134 2.940E+10 6.930E+10 3.210E+10 0.000E+00 2.200E+10 8.410E+09 8.620E+08 CS-136 1.330E+09 5.250E+09 3.530E+09 0.000E+00 2.860E+09 4.510E+08 4.230E+08 CS-137 4.020E+10 5.340E+10 1.860E+10 0.000E+00 1.820E+10 7.060E+09 7.600E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 298 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS TEEN (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BA-139 1.040E-08 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.310E-08 BA-140 5.830E+06 7.140E+03 3.750E+05 0.000E+00 2.420E+03 4.800E+03 8.980E+06 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 9.760E-01 4.750E-01 1.260E-01 0.000E+00 0.000E+00 0.000E+00 2.730E+04 LA-142 1.980E-12 8.780E-13 2.190E-13 0.000E+00 0.000E+00 0.000E+00 2.670E-08 CE-141 1.060E+03 7.110E+02 8.170E+01 0.000E+00 3.350E+02 0.000E+00 2.030E+06 CE-143 9.230E+00 6.720E+03 7.500E-01 0.000E+00 3.010E+00 0.000E+00 2.020E+05 CE-144 7.900E+04 3.270E+04 4.240E+03 0.000E+00 1.950E+04 0.000E+00 1.990E+07 PR-143 3.500E+01 1.400E+01 1.740E+00 0.000E+00 8.130E+00 0.000E+00 1.150E+05 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 2.180E+01 2.370E+01 1.420E+00 0.000E+00 1.390E+01 0.000E+00 8.530E+04 EU-154 4.700E+03 6.070E+02 4.280E+02 0.000E+00 2.720E+03 0.000E+00 3.210E+05 EU-155 1.030E+03 9.970E+01 6.170E+01 0.000E+00 3.900E+02 0.000E+00 5.710E+05 W-187 1.440E+03 1.170E+03 4.110E+02 0.000E+00 0.000E+00 0.000E+00 3.180E+05 NP-239 8.390E-01 7.910E-02 4.390E-02 0.000E+00 2.480E-01 0.000E+00 1.270E+04 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 299 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS CHILD (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 3.200E+03 3.200E+03 3.200E+03 3.200E+03 3.200E+03 3.200E+03 C-14 1.650E+06 3.290E+05 3.290E+05 3.290E+05 3.290E+05 3.290E+05 3.290E+05 NA-24 1.110E+06 1.110E+06 1.110E+06 1.110E+06 1.110E+06 1.110E+06 1.110E+06 P-32 9.330E+10 4.370E+09 3.600E+09 0.000E+00 0.000E+00 0.000E+00 2.580E+09 CR-51 0.000E+00 0.000E+00 1.220E+04 6.790E+03 1.860E+03 1.240E+04 6.490E+05 MN-54 0.000E+00 2.510E+06 6.690E+05 0.000E+00 7.050E+05 0.000E+00 2.110E+06 MN-56 0.000E+00 1.570E-03 3.550E-04 0.000E+00 1.900E-03 0.000E+00 2.280E-01 FE-55 1.450E+06 7.700E+05 2.390E+05 0.000E+00 0.000E+00 4.360E+05 1.430E+05 FE-59 1.570E+06 2.530E+06 1.260E+06 0.000E+00 0.000E+00 7.350E+05 2.640E+06 CO-57 0.000E+00 4.600E+05 9.320E+05 0.000E+00 0.000E+00 0.000E+00 3.770E+06 CO-58 0.000E+00 1.460E+06 4.460E+06 0.000E+00 0.000E+00 0.000E+00 8.500E+06 CO-60 0.000E+00 5.180E+06 1.530E+07 0.000E+00 0.000E+00 0.000E+00 2.870E+07 NI-63 3.560E+09 1.900E+08 1.210E+08 0.000E+00 0.000E+00 0.000E+00 1.280E+07 NI-65 1.990E-01 1.870E-02 1.090E-02 0.000E+00 0.000E+00 0.000E+00 2.290E+00 CU-64 0.000E+00 8.410E+03 5.080E+03 0.000E+00 2.030E+04 0.000E+00 3.950E+05 ZN-65 4.960E+08 1.320E+09 8.220E+08 0.000E+00 8.330E+08 0.000E+00 2.320E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 1.390E+07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 5.620E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 1.050E+09 6.470E+08 0.000E+00 0.000E+00 0.000E+00 6.770E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 1.390E+10 0.000E+00 3.970E+08 0.000E+00 0.000E+00 0.000E+00 5.380E+08 SR-90 2.350E+11 0.000E+00 5.950E+10 0.000E+00 0.000E+00 0.000E+00 3.190E+09 SR-91 2.970E+05 0.000E+00 1.120E+04 0.000E+00 0.000E+00 0.000E+00 6.550E+05 SR-92 4.590E+10 0.000E+00 1.840E-01 0.000E+00 0.000E+00 0.000E+00 8.690E+01 Y-90 3.860E+01 0.000E+00 1.030E+00 0.000E+00 0.000E+00 0.000E+00 1.100E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 4.690E+03 0.000E+00 1.250E+02 0.000E+00 0.000E+00 0.000E+00 6.250E+05 Y-92 2.950E-05 0.000E+00 8.440E-07 0.000E+00 0.000E+00 0.000E+00 8.520E-01 Y-93 1.270E-01 0.000E+00 3.480E-03 0.000E+00 0.000E+00 0.000E+00 1.890E+03 ZR-95 4.610E+02 1.010E+02 9.030E+01 0.000E+00 1.450E+02 0.000E+00 1.060E+05 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 300 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS CHILD (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract ZR-97 2.260E-01 3.270E-02 1.930E-02 0.000E+00 4.690E-02 0.000E+00 4.950E+03 NB-95 3.810E+04 1.480E+04 1.060E+04 0.000E+00 1.390E+04 0.000E+00 2.750E+07 NB-97 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.740E-07 MO-99 0.000E+00 9.950E+06 2.460E+06 0.000E+00 2.120E+07 0.000E+00 8.230E+06 TC-99M 1.550E+00 3.040E+00 5.040E+01 0.000E+00 4.420E+01 1.550E+00 1.730E+03 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 5.150E+02 0.000E+00 1.980E+02 0.000E+00 1.300E+03 0.000E+00 1.330E+04 RU-105 4.590E-04 0.000E+00 1.660E-04 0.000E+00 4.030E-03 0.000E+00 2.990E-01 RU-106 1.110E+04 0.000E+00 1.380E+03 0.000E+00 1.500E+04 0.000E+00 1.720E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 2.510E+07 1.690E+07 1.350E+07 0.000E+00 3.150E+07 0.000E+00 2.010E+09 SB-122 7.680E+04 8.010E+04 9.700E+05 1.270E+04 3.780E+04 1.650E+04 9.540E+06 SB-124 1.300E+07 1.690E+05 4.570E+06 2.880E+04 0.000E+00 7.240E+06 8.150E+07 SB-125 1.040E+07 8.050E+04 2.190E+06 9.670E+03 0.000E+00 5.820E+06 2.490E+07 TE-125M 8.850E+06 2.400E+06 1.180E+06 2.480E+06 0.000E+00 0.000E+00 8.540E+06 TE-127M 2.500E+07 6.720E+06 2.960E+06 5.970E+06 7.120E+07 0.000E+00 2.020E+07 TE-127 3.670E+02 9.910E+01 7.880E+01 2.540E+02 1.050E+03 0.000E+00 1.440E+04 TE-129M 3.270E+07 9.130E+06 5.080E+06 1.050E+07 9.600E+07 0.000E+00 3.990E+07 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.340E-09 TE-131M 1.920E+05 6.640E+04 7.070E+04 1.370E+05 6.430E+05 0.000E+00 2.690E+06 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 1.230E+06 5.420E+05 6.550E+05 7.900E+05 5.040E+06 0.000E+00 5.460E+06 I-130 2.100E+06 4.250E+06 2.190E+06 4.680E+08 6.350E+06 0.000E+00 1.990E+06 I-131 1.570E+09 1.570E+09 8.950E+08 5.210E+11 2.580E+09 0.000E+00 1.400E+08 I-132 8.230E-01 1.510E+00 6.960E-01 7.020E+01 2.320E+00 0.000E+00 1.780E+00 I-133 2.110E+07 2.610E+07 9.880E+06 4.850E+09 4.350E+07 0.000E+00 1.050E+07 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 7.000E+04 1.260E+05 5.960E+04 1.120E+07 1.930E+05 0.000E+00 9.600E+04 CS-134 6.790E+10 1.110E+11 2.350E+10 0.000E+00 3.450E+10 1.240E+10 6.010E+08 CS-136 3.010E+09 8.280E+09 5.360E+09 0.000E+00 4.410E+09 6.580E+08 2.910E+08 CS-137 9.670E+10 9.260E+10 1.370E+10 0.000E+00 3.020E+10 1.090E+10 5.800E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 301 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS CHILD (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BA-139 2.560E-08 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.480E-06 BA-140 1.410E+07 1.230E+04 8.210E+05 0.000E+00 4.010E+03 7.340E+03 7.120E+06 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 2.310E+00 8.090E-01 2.730E-01 0.000E+00 0.000E+00 0.000E+00 2.260E+04 LA-142 4.770E-12 1.520E-12 4.770E-13 0.000E+00 0.000E+00 0.000E+00 3.020E-07 CE-141 2.620E+03 1.310E+03 1.940E+02 0.000E+00 5.730E+02 0.000E+00 1.630E+06 CE-143 2.270E+01 1.230E+04 1.780E+00 0.000E+00 5.150E+00 0.000E+00 1.800E+05 CE-144 1.950E+05 6.100E+04 1.040E+04 0.000E+00 3.380E+04 0.000E+00 1.590E+07 PR-143 8.670E+01 2.600E+01 4.300E+00 0.000E+00 1.410E+01 0.000E+00 9.350E+04 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 5.340E+01 4.320E+01 3.350E+00 0.000E+00 2.370E+01 0.000E+00 6.850E+04 EU-154 1.130E+04 1.020E+03 9.290E+02 0.000E+00 4.470E+03 0.000E+00 2.360E+05 EU-155 2.360E+03 1.700E+02 1.330E+02 0.000E+00 6.630E+02 0.000E+00 4.250E+05 W-187 3.490E+03 2.070E+03 9.270E+02 0.000E+00 0.000E+00 0.000E+00 2.900E+05 NP-239 2.060E+00 1.480E-01 1.040E-01 0.000E+00 4.280E-01 0.000E+00 1.100E+04 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 302 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS INFANT (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract H-3 0.000E+00 4.860E+03 4.860E+03 4.860E+03 4.860E+03 4.860E+03 4.860E+03 C-14 3.230E+06 6.890E+05 6.890E+05 6.890E+05 6.890E+05 6.890E+05 6.890E+05 NA-24 1.930E+06 1.930E+06 1.930E+06 1.930E+06 1.930E+06 1.930E+06 1.930E+06 P-32 1.920E+11 1.130E+10 7.450E+09 0.000E+00 0.000E+00 0.000E+00 2.600E+09 CR-51 0.000E+00 0.000E+00 1.940E+04 1.260E+04 2.760E+03 2.460E+04 5.650E+05 MN-54 0.000E+00 4.670E+06 1.060E+06 0.000E+00 1.040E+06 0.000E+00 1.720E+06 MN-56 0.000E+00 3.850E-03 6.630E-04 0.000E+00 3.310E-03 0.000E+00 3.490E-01 FE-55 1.760E+06 1.130E+06 3.030E+05 0.000E+00 0.000E+00 5.540E+05 1.440E+05 FE-59 2.920E+06 5.110E+06 2.010E+06 0.000E+00 0.000E+00 1.510E+06 2.440E+06 CO-57 0.000E+00 1.070E+06 1.750E+06 0.000E+00 0.000E+00 0.000E+00 3.660E+06 CO-58 0.000E+00 2.910E+06 7.270E+06 0.000E+00 0.000E+00 0.000E+00 7.260E+06 CO-60 0.000E+00 1.060E+07 2.500E+07 0.000E+00 0.000E+00 0.000E+00 2.520E+07 NI-63 4.190E+09 2.590E+08 1.450E+08 0.000E+00 0.000E+00 0.000E+00 1.290E+07 NI-65 4.210E-01 4.770E-02 2.170E-02 0.000E+00 0.000E+00 0.000E+00 3.630E+00 CU-64 0.000E+00 2.090E+04 9.680E+03 0.000E+00 3.540E+04 0.000E+00 4.290E+05 ZN-65 6.660E+08 2.280E+09 1.050E+09 0.000E+00 1.110E+09 0.000E+00 1.930E+09 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-82 0.000E+00 0.000E+00 2.330E+07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 1.190E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.670E+09 1.320E+09 0.000E+00 0.000E+00 0.000E+00 6.830E+07 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 2.640E+10 0.000E+00 7.580E+08 0.000E+00 0.000E+00 0.000E+00 5.430E+08 SR-90 2.550E+11 0.000E+00 6.500E+10 0.000E+00 0.000E+00 0.000E+00 3.190E+09 SR-91 6.180E+05 0.000E+00 2.240E+04 0.000E+00 0.000E+00 0.000E+00 7.310E+05 SR-92 9.760E+00 0.000E+00 3.620E-01 0.000E+00 0.000E+00 0.000E+00 1.050E+02 Y-90 8.160E+01 0.000E+00 2.190E+00 0.000E+00 0.000E+00 0.000E+00 1.130E+05 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 8.800E+03 0.000E+00 2.340E+02 0.000E+00 0.000E+00 0.000E+00 6.310E+05 Y-92 6.270E-05 0.000E+00 1.760E-06 0.000E+00 0.000E+00 0.000E+00 1.200E+10 Y-93 2.700E-01 0.000E+00 7.350E-03 0.000E+00 0.000E+00 0.000E+00 2.130E+03 ZR-95 8.190E+02 2.000E+02 1.420E+02 0.000E+00 2.150E+02 0.000E+00 9.940E+00 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 303 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS INFANT (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract ZR-97 4.790E-01 8.220E-02 3.760E-02 0.000E+00 8.290E-02 0.000E+00 5.240E+03 NB-95 7.120E+04 2.930E+04 1.690E+04 0.000E+00 2.100E+04 0.000E+00 2.470E+07 NB-97 6.590E-12 1.410E-12 5.070E-13 0.000E+00 1.100E-12 0.000E+00 4.440E-07 MO-99 0.000E+00 2.540E+07 4.960E+06 0.000E+00 3.800E+07 0.000E+00 8.830E+06 TC-99M 3.230E+00 6.660E+00 8.570E+01 0.000E+00 7.160E+01 3.480E+00 1.930E+03 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 1.040E+03 0.000E+00 3.490E+02 0.000E+00 2.170E+03 0.000E+00 1.270E+04 RU-105 9.670E-04 0.000E+00 3.260E-04 0.000E+00 7.110E-03 0.000E+00 3.850E-01 RU-106 2.280E+04 0.000E+00 2.850E+03 0.000E+00 2.700E+04 0.000E+00 1.730E+05 RH-103M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RH-106 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 AG-110M 4.630E+07 3.380E+07 2.240E+07 0.000E+00 4.840E+07 0.000E+00 1.750E+09 SB-122 7.680E+04 8.010E+04 9.700E+05 1.270E+04 3.780E+04 1.650E+04 9.540E+06 SB-124 2.510E+07 3.700E+05 7.790E+06 6.670E+04 0.000E+00 1.570E+07 7.750E+07 SB-125 1.790E+07 1.740E+05 3.690E+06 2.250E+04 0.000E+00 1.130E+07 2.390E+07 TE-125M 1.810E+07 6.050E+06 2.450E+06 6.090E+06 0.000E+00 0.000E+00 8.620E+06 TE-127M 5.050E+07 1.680E+07 6.120E+06 1.460E+07 1.240E+08 0.000E+00 2.040E+07 TE-127 7.800E+02 2.610E+02 1.680E+02 6.350E+02 1.900E+03 0.000E+00 1.640E+04 TE-129M 6.710E+07 2.300E+07 1.030E+07 2.580E+07 1.680E+08 0.000E+00 4.010E+07 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.000E-08 TE-131M 4.050E+05 1.630E+05 1.350E+05 3.310E+00 1.120E+06 0.000E+00 2.750E+06 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 2.520E+06 1.250E+06 1.170E+06 1.840E+06 7.820E+06 0.000E+00 4.620E+06 I-130 4.320E+06 9.510E+06 3.820E+06 1.070E+09 1.040E+07 0.000E+00 2.040E+06 I-131 3.270E+09 3.850E+09 1.690E+09 1.270E+12 4.500E+09 0.000E+00 1.370E+08 I-132 1.710E+00 3.470E+00 1.230E+00 1.630E+02 3.870E+00 0.000E+00 2.810E+00 I-133 4.460E+07 6.490E+07 1.900E+07 1.180E+10 7.630E+07 0.000E+00 1.100E+07 I-134 0.000E+00 0.000E+00 0.000E+00 1.210E-09 0.000E+00 0.000E+00 0.000E+00 I-135 1.460E+05 2.900E+05 1.060E+05 2.600E+07 3.230E+05 0.000E+00 1.050E+05 CS-134 1.090E+11 2.040E+11 2.060E+10 0.000E+00 5.250E+10 2.150E+10 5.540E+08 CS-136 5.880E+09 1.730E+10 6.460E+09 0.000E+00 6.900E+09 1.410E+09 2.630E+08 CS-137 1.540E+11 1.810E+11 1.280E+10 0.000E+00 4.850E+10 1.960E+10 5.650E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 304 of 321 Level 3 - Information Attachment 12 Gaseous Effluent Pathway Dose Factors GRASS-GOAT-MILK DOSE FACTORS INFANT (m2 *mrem/yr per uCi/sec)

Nuclide Bone Liver Tbody Thyroid Kidney Lung GItract BA-139 5.450E-08 0.000E+00 1.580E-09 0.000E+00 0.000E+00 0.000E+00 3.450E-06 BA-140 2.890E+07 2.890E+04 1.490E+06 0.000E+00 6.870E+03 1.780E+04 7.110E+06 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 4.840E+00 1.910E+00 4.900E-01 0.000E+00 0.000E+00 0.000E+00 2.240E+04 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CE-141 5.200E+03 3.170E+03 3.730E+02 0.000E+00 9.780E+02 0.000E+00 1.640E+06 CE-143 4.800E+01 3.180E+04 3.630E+00 0.000E+00 9.270E+00 0.000E+00 1.860E+05 CE-144 2.790E+05 1.140E+05 1.560E+04 0.000E+00 4.620E+04 0.000E+00 1.600E+07 PR-143 1.790E+02 6.710E+01 8.890E+00 0.000E+00 2.490E+01 0.000E+00 9.470E+04 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 1.060E+02 1.090E+02 6.660E+00 0.000E+00 4.190E+01 0.000E+00 6.890E+04 EU-154 1.300E+04 1.800E+03 1.080E+03 0.000E+00 4.890E+03 0.000E+00 2.250E+05 EU-155 2.650E+03 3.060E+02 1.580E+02 0.000E+00 6.850E+02 0.000E+00 4.100E+05 W-187 7.350E+03 5.110E+03 1.770E+03 0.000E+00 0.000E+00 0.000E+00 3.000E+05 NP-239 4.360E+00 3.900E-01 2.210E-01 0.000E+00 7.780E-01 0.000E+00 1.130E+04 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 305 of 321 Level 3 - Information Attachment 13 Environmental Monitoring Sites for REMP SAMPLE SITE SECTOR DISTANCE1 DESCRIPTION km mi DR1 NW 0.6 0.4 Onsite, Along Cliffs DR2 WNW 2.7 1.7 Rt. 765, Auto Dump DR3 W 2.3 1.4 Rt. 765, Giovanni's Tavern (Knotty Pine)

DR4 WSW 2.0 1.2 Rt. 765, Across from White Sand Drive Ib10, Ib11, Ib12, SFA1 SW 0.7 0.4 Meteorological Station DR5 SW 2.4 1.5 Rt. 765 at Johns Creek SFA3 SSW 0.6 0.4 NNW of ISFSI SFA4 SSW 0.8 0.5 SSE of ISFSI DR6, A4 SSW 2.9 1.8 Rt. 765 at Lusby, Franks Garage DR7, A1, Ib4, Ib5, Ib6 S 0.7 0.5 Onsite, before entrance to Camp Conoy DR8, A2 SSE 2.5 1.5 Camp Conoy Road at Emergency Siren DR9, A3 SE 2.6 1.6 Bay Breeze Road DR10 NW 6.4 4.0 Calvert Beach Rd & Decatur St DR11 WNW 6.6 4.1 Dirt Road off Mackall Rd & Parran Rd DR12 W 6.7 4.2 Bowen Rd & Mackall Rd DR13 WSW 6.1 3.8 Mackall Rd near Wallville DR14 SW 6.4 4.0 Rodney Point DR15 SSW 6.2 3.9 Mill Bridge Rd & Turner Rd DR16 S 6.5 4.1 Across from Appeal School DR17 SSE 5.9 3.7 Cove Point Rd & Little Cove Point Rd DR18 SE 7.1 4.5 Cove Point DR19 NW 4.4 2.8 Long Beach DR20 NNW 0.4 0.3 Onsite, near shore DR21, A5, Ib7, Ib8, Ib9 WNW 19.3 12.1 Emergency Operations Facility DR22 S 12.5 7.8 Solomons Island DR23 ENE 12.4 7.7 Taylors Island, Andersons Property Wa1 NNE 0.2 0.1 Intake Area Wa2, Ia1, Ia2 N 0.3 0.2 Discharge Area Wb1 ESE 0.6 0.4 Shoreline at Barge Road Ia4, Ia5 (Area not influenced by Plant Patuxent River Discharge)

Ia3 E 0.9 0.6 Camp Conoy Ia6 NNW 10.7 6.7 Kenwood Beach Due to CCNPPs proximity to the Chesapeake Bay, the following sectors do not have direct radiation measurement devices as allowed by Table 3.12-1 site boundary (N, NNE, NE, ENE, E and ESE) and > 10 miles (NNW, N, NNE, NE, E and ESE).

1 Distance and direction from the central point of the two containment buildings.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 306 of 321 Level 3 - Information Attachment 14 Radiological Environmental Monitoring Program Surveillances for Direct Radiation PARAMETER UNITS FREQUENCY LLD ACTION LEVEL GAMMA DOSE(1) mR at least quarterly (2) N/A (1) Each sample point shall be monitored using two or more dosimeters OR one instrument for measuring and recording dose rate continuously.

(2) LLD for TLDs used for environmental measurements shall be per the recommendations of Regulatory Guide 4.13.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 307 of 321 Level 3 - Information Attachment 15 Radiological Environmental Monitoring Program Surveillances for Airborne Activity RADIOIODINE CANNISTER (5)

PARAMETER UNITS FREQUENCY LLD ACTION LEVEL I-131 pCi/m3 at least weekly 0.07 0.9 PARTICULATE FILTER (1)

(5)

PARAMETER UNITS FREQUENCY LLD ACTION LEVEL Gross Beta Activity pCi/m3 at least weekly (2) 0.01 N/A (3)

Cs-134 pCi/m3 at least quarterly (4) 0.05 10.0 Cs-137 pCi/m3 at least quarterly (4) 0.06 20.0 (1) All samples consist of continuous sampler operation with sample collection weekly, or more frequently if required by dust loading.

(2) Analyze for gross beta activity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay.

(3) Although there is not an ACTION Level for gross beta activity, if this parameter is greater than ten times the yearly mean of the control sample, perform GAMMA ISOTOPIC ANALYSIS on the individual sample.

(4) Perform a GAMMA ISOTOPIC ANALYSIS of a quarterly COMPOSITE SAMPLE. A separate COMPOSITE SAMPLE shall be prepared for each sample location, A1 thru A5. Each COMPOSITE SAMPLE shall be a prepared from individual particulate filter samples collected during the applicable calendar quarter and from a single location.

(5) If an ACTION Level is exceeded, check the initiating conditions listed in Radiological Environmental Monitoring Program section 5.c and Radiological Environmental Monitoring Program section 5.d, and perform the corrective actions specified in Radiological Environmental Monitoring Program section 7.d and/or Radiological Environmental Monitoring Program section 7.e.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 308 of 321 Level 3 - Information Attachment 16 Radiological Environmental Monitoring Program Surveillances for Waterborne Activity SURFACE WATER SAMPLE (1)

PARAMETER UNITS FREQUENCY LLD ACTION LEVEL (2)

H-3 pCi/l at least quarterly 2000(3) 20,000(4)

Mn-54 pCi/l at least monthly 15 1000 Fe-59 pCi/l at least monthly 30 400 Co-58 pCi/l at least monthly 15 1000 Co-60 pCi/l at least monthly 15 300 Zn-65 pCi/l at least monthly 30 300 Zr-95 / Nb-95 pCi/l at least monthly 15 400 I-131 pCi/l at least monthly 1(5) 2 Cs-134 pCi/l at least monthly 15 30 Cs-137 pCi/l at least monthly 18 50 Ba-140 / La-140 pCi/l at least monthly 15 200 SHORELINE SEDIMENT SAMPLE PARAMETER UNITS FREQUENCY LLD ACTION LEVEL (2)

Cs-134 pCi/kg, dry at least 150 N/A semiannually Cs-137 pCi/kg, dry at least 180 N/A semiannually (1) The water sample shall be a composite of individual samples collected over a 1 month period.

(2) If an ACTION Level is exceeded, check the initiating conditions listed in sections REMP SECTION 5.c and REMP SECTION 5.d, and perform the corrective actions specified in section REMP SECTION 7.d and/or REMP SECTION 7.e.

(3) If a drinking water pathway does not exist, a value of 3000 pCi/l may be used.

(4) If a drinking water pathway does not exist, a value of 30,000 pCi/l may be used.

(5) LLD for drinking water samples. If no drinking water pathway exists, the LLD of the gamma isotopic analysis may be used.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 309 of 321 Level 3 - Information Attachment 17 Radiological Environmental Monitoring Program Surveillances for Ingestible Activity FISH AND INVERTEBRATES (1)

PARAMETER UNITS FREQUENCY LLD ACTION LEVEL (5)

(2)

Mn-54 pCi/kg, wet 130 30,000 (2)

Fe-59 pCi/kg, wet 260 10,000 (2)

Co-58 pCi/kg, wet 130 30,000 (2)

Co-60 pCi/kg, wet 130 10,000 (2)

Zn-65 pCi/kg, wet 260 20,000 (2)

Cs-134 pCi/kg, wet 130 1000 (2)

Cs-137 pCi/kg, wet 150 2000 MILK PARAMETER UNITS FREQUENCY LLD ACTION LEVEL (5)

I-131 pCi/l, wet at least monthly (4) 1 3 Cs-134 pCi/l, wet at least monthly (4) 15 60 Cs-137 pCi/l, wet at least monthly (4) 18 70 Ba-140 / La-140 pCi/l, wet at least monthly (4) 15 300 FOOD PRODUCTS PARAMETER UNITS FREQUENCY LLD ACTION LEVEL (5)

I-131 pCi/kg, wet at least monthly(3) 60 100 Cs-134 pCi/kg, wet at least monthly(3) 60 1000 Cs-137 pCi/kg, wet at least monthly(3) 80 2000 (1) Edible portions of the fish and invertebrates shall be used for analysis.

(2) The fish and invertebrates shall be sampled at least once per year in season, or semiannually if they are not seasonal.

(3) The food products shall be sampled during the growing season.

(4) The milk samples need be collected and analyzed only if the milk is commercially available in quantities greater than 310 liters per year (see NUREG-0133, 5.3.1.1).

(5) If an ACTION Level is exceeded, check the initiating conditions listed in Radiological Environmental Monitoring Program section 5.c and Radiological Environmental Monitoring Program section 5.d, and perform the corrective actions specified in Radiological Environmental Monitoring Program section 7.d and/or Radiological Environmental Monitoring Program section 7.e.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 310 of 321 Level 3 - Information Attachment 18 Map of Environmental Monitoring Sites for REMP (5 Km Radius)

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 311 of 321 Level 3 - Information Attachment 19 Map of Environmental Monitoring Sites for REMP (10 Mile Radius)

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 312 of 321 Level 3 - Information Attachment 20 Environmental Monitoring Sites for ISFSI DISTANCE1 DIRECTION1 STATION DESCRIPTION (Kilometers) (Sector)

AIR SAMPLERS A12 On Site Before Entrance to Camp Conoy 0.3 ESE SFA1 Meteorological Station 0.3 NW SFA2 CCNPP Visitor's Center 0.8 N SFA3 North Northwest of ISFSI 0.1 NNW SFA4 SSE of ISFSI 0.1 SSE TLD LOCATIONS SFDR1 Southwest of ISFSI 0.2 SW SFDR2 North of ISFSI 0.2 N SFDR3 North of ISFSI 0.1 N SFDR4 Northeast of ISFSI <0.1 NE SFDR5 East of ISFSI <0.1 E SFDR6 East Southeast of ISFSI 0.1 ESE SFDR7 CCNPP Visitor's Center 0.8 N SFDR8 North Northwest of ISFSI 0.1 NNW SFDR9 SSE of ISFSI 0.1 SSE SFDR10 Northwest of ISFSI 0.1 NW SFDR11 West Northwest of ISFSI 0.1 WNW SFDR12 WSW of ISFSI <0.1 WSW SFDR13 South of ISFSI <0.1 S SFDR14 Southeast of ISFSI 0.1 SE SFDR15 East Northeast of ISFSI <0.1 ENE SFDR16 Southwest of ISFSI <0.1 SW DR72 On Site Before Entrance to Camp Conoy 0.3 ESE DR30 Meteorological Station 0.3 NW SFDR17 NNE OF ISFSI 0.1 NNE SFDR18 West OF ISFSI 0.04 W VEGETATION SFb1 Meteorological Station 0.3 NW SFb2 CCNPP Visitor's Center 0.8 N SFb3 North Northwest of ISFSI 0.1 NNW SFb4 SSEof ISFSI 0.1 SSE SFb5 On Site Before Entrance to Camp Conoy 0.3 ESE SOIL SFS1 Meteorological Station 0.3 NW SFS2 CCNPP Visitor's Center 0.8 N SFS3 North Northwest of ISFSI 0.1 NNW SFS4 SSE of ISFSI 0.1 SSE SFS5 On Site Before Entrance to Camp Conoy 0.3 ESE 1 Distance and direction from the Central Point of the ISFSI.

2 Common to both the REMP and the ISFSIMP.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 313 of 321 Level 3 - Information Attachment 21 Map of Environmental Monitoring Sites for ISFSI December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 314 of 321 Level 3 - Information Attachment 22 Map of Environmental Monitoring Sites for ISFSI (ENLARGED)

A = Air Sampler (Plant)

DR = Direct Radiation (Plant)

SFDR = Direct Radiation (Spent Fuel)

SFA = Air Sampler (Spent Fuel)

SFS = Soil (Spent Fuel)

SFb = Vegetation (Spent Fuel)

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 315 of 321 Level 3 - Information Attachment 23 Effluent Radiation Monitors Description Radiation Radiation Element Indicator Liquid Waste Discharge Radiation Monitor 0-RE-2201 0-RI-2201 Steam Generator Blowdown Effluent Radiation Monitor 1-RE-4095 1-RI-4095 Steam Generator Blowdown Effluent Radiation Monitor 2-RE-4095 2-RI-4095 Steam Generator Blowdown Tank Radiation Monitor 1-RE-4014 1-RI-4014 Steam Generator Blowdown Tank Radiation Monitor 2-RE-4014 2-RI-4014 Wide Range Gas Monitor, Low Range 1-RE-5416A 1-RIC-5415 Wide Range Gas Monitor, Low Range 2-RE-5416A 2-RIC-5415 Westinghouse Plant Vent Stack Monitor 1-RE-5415 1-RI-5415 Westinghouse Plant Vent Stack Monitor 2-RE-5415 2-RI-5415 Gaseous Radwaste Processing System Radiation Monitor 0-RE-2191 0-RE-2191 Accident Monitors Not Addressed By The ODCM Wide Range Gas Monitor, Mid Range 1-RE-5417A Wide Range Gas Monitor, High Range 1-RE-5418A Wide Range Gas Monitor, Mid Range 2-RE-5417A Wide Range Gas Monitor, High Range 2-RE-5418A December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 316 of 321 Level 3 - Information Attachment 24 Atmospheric Stability Classes Stability Class Letter Stability Class Desc. T Interval (°C/100m) T Interval (°C/50m)

A Extremely Unstable T -1.9 T -0.95 B Moderately Unstable -1.9 < T -1.7 -0.95 < T -0.85 C Slightly Unstable -1.7 < T -1.5 -0.85 < T -0.75 D Neutral -1.5 < T -0.5 -0.75 < T -0.25 E Slightly Stable -0.5 < T 1.5 -0.25 < T 0.75 F Moderately Stable 1.5 < T 4.00 0.75 < T 2.00 G Extremely Stable T > 4.00 T > 2.00 This information was provided by Murray and Trettel/WeatherCommand on 7/27/2016. The values are derived from Regulatory Guide 1.23, Meteorological Monitoring Programs for Nuclear Power Plants.

December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 317 of 321 Level 3 - Information Attachment 25 Maximum Permissible Concentration (MPC) Values - Liquid Effluents The following radionuclide concentrations were obtained from 10 CFR 20 Appendix B, Table II, Column 2 as revised January 1, 1988 and referred to as the "old" 10 CFR 20.

Insoluble Soluble Conc. Insoluble Conc. Soluble Conc.

Element Isotope Element Isotope Conc.

(uCi/ml) (uCi/ml) (uCi/ml)

(uCi/ml)

Actinium (89) Ac-227 2E-6 3E-4 Bromine (35) Br-82 3E-4 4E-5 Ac-228 9E-5 9E-5 Br-83 3E-6 3E-6 Americium (95) Am-241 4E-6 3E-5 Cadmium (48) Cd-109 2E-4 2E-4 Am-242m 4E-6 9E-5 Cd-115m 3E-5 3E-5 Am-242 1E-4 1E-4 Cd-115 3E-5 4E-5 Am-243 4E-6 3E-5 Calcium (20) Ca-45 9E-6 2E-4 Am-244 5E-3 5E-3 Ca-47 5E-5 3E-5 Antimony (51) Sb-122 3E-5 3E-5 Californium (98) Cf-249 4E-6 2E-5 Sb-124 2E-5 2E-5 Cf-250 1E-5 3E-5 Sb-125 1E-4 1E-4 Cf-251 4E-6 3E-5 Sb-126 3E-6 3E-6 Cf-252 7E-6 7E-6 Arsenic (33) As-73 5E-4 5E-4 Cf-253 1E-4 1E-4 As-74 5E-5 5E-5 Cf-254 1E-7 1E-7 As-76 2E-5 2E-5 Carbon (6) C-14 8E-4 -------

As-77 8E-5 8E-5 Cerium (58) Ce-141 9E-5 9E-5 Astatine (85) At-211 2E-6 7E-5 Ce-143 4E-5 4E-5 Barium (56) Ba-131 2E-4 2E-4 Ce-144 1E-5 1E-5 Ba-140 3E-5 2E-5 Cesium (55) Cs-131 2E-3 9E-4 Berkelium (97) Bk-249 6E-4 6E-4 Cs-134m 6E-3 1E-3 Bk-250 2E-4 2E-4 Cs-134 9E-6 4E-5 Beryllium (4) Be-7 2E-3 2E-3 Cs-135 1E-4 2E-4 Bismuth (83) Bi-206 4E-5 4E-5 Cs-136 9E-5 6E-5 Bi-207 6E-5 6E-5 Cs-137 2E-5 4E-5 Bi-210 4E-5 4E-5 Chlorine (17) Cl-36 8E-5 6E-5 Bi-212 4E-4 4E-4 Cl-38 4E-4 4E-4 May2017

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 318 of 321 Level 3 - Information Attachment 25 Maximum Permissible Concentration (MPC) Values - Liquid Effluents Insoluble Soluble Conc. Insoluble Conc. Soluble Conc.

Element Isotope Element Isotope Conc.

(uCi/ml) (uCi/ml) (uCi/ml)

(uCi/ml)

Chromium (24) Cr-51 2E-3 2E-3 Gadolinium (64) Gd-153 2E-4 2E-4 Cobalt (27) Co-57 5E-4 4E-4 Gd-159 8E-5 8E-5 Co-58m 3E-3 2E-3 Gallium (31) Ga-72 4E-5 4E-5 Co-58 1E-4 9E-5 Holmium (67) Ho-166 3E-5 3E-5 Co-60 5E-5 3E-5 Hydrogen (3) H-3 3E-3 3E-3 Copper (29) Cu-64 3E-4 2E-4 Indium (49) In-113m 1E-3 1E-3 Curium (96) Cm-242 2E-5 2E-5 In-114m 2E-5 2E-5 Cm-243 5E-6 2E-5 In-115m 4E-4 4E-4 Cm-244 7E-6 3E-5 In-115 9E-5 9E-5 Cm-245 4E-6 3E-5 Iodine (53) I-125 2E-7 2E-4 Cm-246 4E-6 3E-5 I-126 3E-7 9E-5 Cm-247 4E-6 2E-5 I-129 6E-8 2E-4 Cm-248 4E-7 1E-6 I-130 3E-6 3E-6 Cm-249 2E-3 2E-3 I-131 3E-7 6E-5 Einsteinium (99) Es-253 2E-5 2E-5 I-132 8E-6 2E-4 Es-254m 2E-5 2E-5 I-133 1E-6 4E-5 Es-254 1E-5 1E-5 I-134 2E-5 6E-4 Es-255 3E-5 3E-5 I-135 4E-6 7E-5 Erbium (68) Er-169 9E-5 9E-5 Iridium (77) Ir-190 2E-4 2E-4 Er-171 1E-4 1E-4 Ir-192 4E-5 4E-5 Europium (63) Eu-152 (9.2 hrs) 6E-5 6E-5 Ir-194 3E-5 3E-5 Eu-152 (13 yrs) 8E-5 8E-5 Iron (26) Fe-55 8E-4 2E-3 Eu-154 2E-5 2E-5 Fe-59 6E-5 5E-5 Eu-155 2E-4 2E-4 Lanthanum (57) La-140 2E-5 2E-5 Fermium (100) Fm-254 1E-4 1E-4 Lead (82) Pb-203 4E-4 4E-4 Fm-255 3E-5 3E-5 Pb-210 1E-7 2E-4 Fm-256 9E-7 9E-7 Pb-212 2E-5 2E-5 Fluorine (9) F-18 8E-4 5E-4 Lutetium (71) Lu-177 1E-4 1E-4 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 319 of 321 Level 3 - Information Attachment 25 Maximum Permissible Concentration (MPC) Values - Liquid Effluents Insoluble Soluble Conc. Insoluble Conc. Soluble Conc.

Element Isotope Element Isotope Conc.

(uCi/ml) (uCi/ml) (uCi/ml)

(uCi/ml)

Germanium (32) Ge-71 2E-3 2E-3 Palladium (46) Pd-103 3E-4 3E-4 Gold (79) Au-196 2E-4 1E-4 Pd-109 9E-5 7E-5 Au-198 5E-5 5E-5 Phosphorus (15) P-32 2E-5 2E-5 Au-199 2E-4 2E-4 Platinum (78) Pt-191 1E-4 1E-4 Hafnium (72) Hf-181 7E-5 7E-5 Pt-193m 1E-3 1E-3 Manganese (25) Mn-52 3E-5 3E-5 Pt-193 9E-4 2E-3 Mn-54 1E-4 1E-4 Pt-197m 1E-3 9E-4 Mn-56 1E-4 1E-4 Pt-197 1E-4 1E-4 Mercury (80) Hg-197m 2E-4 2E-4 Plutonium (94) Pu-238 5E-6 3E-5 Hg-197 3E-4 5E-4 Pu-239 5E-6 3E-5 Hg-203 2E-5 1E-4 Pu-240 5E-6 3E-5 Molybdenum (42) Mo-99 2E-4 4E-5 Pu-241 2E-4 1E-3 Neodymium (60) Nd-144 7E-5 8E-5 Pu-242 5E-6 3E-5 Nd-147 6E-5 6E-5 Pu-243 3E-4 3E-4 Nd-149 3E-4 3E-4 Polonium (84) Po-210 7E-7 3E-5 Neptunium (93) Np-237 3E-6 3E-5 Potassium (19) K-42 3E-4 2E-5 Np-239 1E-4 1E-4 Praseodymium(59) Pr-142 3E-5 3E-5 Nickel (28) Ni-59 2E-4 2E-3 Pr-143 5E-5 5E-5 Ni-63 3E-5 7E-4 Promethium (61) Pm-147 2E-4 2E-4 Ni-65 1E-4 1E-4 Pm-149 4E-5 4E-5 Niobium (41) Nb-93m 4E-4 4E-4 Protactinium(91) Pa-230 2E-4 2E-4 Nb-95 1E-4 1E-4 Pa-231 9E-7 2E-5 Nb-97 9E-4 9E-4 Pa-233 1E-4 1E-4 Osmium (76) Os-185 7E-5 7E-5 Radium (88) Ra-223 7E-7 4E-6 Os-191m 3E-3 2E-3 Ra-224 2E-6 5E-6 Os-191 2E-4 2E-4 Ra-226 3E-8 3E-5 Os-193 6E-5 5E-5 Ra-228 3E-8 3E-5 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 320 of 321 Level 3 - Information Attachment 25 Maximum Permissible Concentration (MPC) Values - Liquid Effluents Element Isotope Soluble Insoluble Element Isotope Soluble Insoluble Conc. Conc. Conc. Conc.

(uCi/ml) (uCi/ml) (uCi/ml) (uCi/ml)

Rhenium (75) Re-183 6E-4 3E-4 Strontium (38) Sr-85m 7E-3 7E-3 Re-186 9E-5 5E-5 Sr-85 1E-4 2E-4 Re-187 3E-3 2E-3 Sr-89 3E-6 3E-5 Re-188 6E-5 3E-5 Sr-90 3E-7 4E-5 Rhodium (45) Rh-103m 1E-2 1E-2 Sr-91 7E-5 5E-5 Rh-105 1E-4 1E-4 Sr-92 7E-5 6E-5 Rubidium (37) Rb-86 7E-5 2E-5 Sulfur (16) S-35 6E-5 3E-4 Rb-87 1E-4 2E-4 Tantalum (73) Ta-182 4E-5 4E-5 Ruthenium (44) Ru-97 4E-4 3E-4 Ru-103 8E-5 8E-5 Technetium (43) Tc-96m 1E-2 1E-2 Ru-103m 3E-6 3E-6 Tc-96 1E-4 5E-5 Ru-105 1E-4 1E-4 Tc-97m 4E-4 2E-4 Ru-106 1E-5 1E-5 Tc-97 2E-3 8E-4 Samarium (62) Sm-147 6E-5 7E-5 Tc-99m 6E-3 3E-3 Sm-151 4E-4 4E-4 Tc-99 3E-4 2E-4 Sm-153 8E-5 8E-5 Tellurium (52) Te-125m 2E-4 1E-4 Scandium (21) Sc-46 4E-5 4E-5 Te-127m 6E-5 5E-5 Sc-47 9E-5 9E-5 Te-127 3E-4 2E-4 Sc-48 3E-5 3E-5 Te-129m 3E-5 2E-5 Selenium (34) Se-75 3E-4 3E-4 Te-129 8E-4 8E-4 Silicon (14) Si-31 9E-4 2E-4 Te-131m 6E-5 4E-5 Silver (47) Ag-105 1E-4 1E-4 Te-132 3E-5 2E-5 Ag-110m 3E-5 3E-5 Terbium (65) Tb-160 4E-5 4E-5 Ag-111 4E-5 4E-5 Thallium (81) Tl-200 4E-4 2E-4 Sodium (11) Na-22 4E-5 3E-5 Tl-201 3E-4 2E-4 Na-24 2E-4 3E-5 Tl-202 1E-4 7E-5 Tl-204 1E-4 6E-5 December 2018

CY-CA-170-301 Revision 3 OFFSITE DOSE CALCULATION MANUAL Page 321 of 321 Level 3 - Information Attachment 25 Maximum Permissible Concentration (MPC) Values - Liquid Effluents Element Isotope Soluble Insoluble Element Isotope Soluble Insoluble Conc. Conc. Conc. Conc.

(uCi/ml) (uCi/ml) (uCi/ml) (uCi/ml)

Thorium (90) Th-227 2E-5 2E-5 Vanadium (23) V-48 3E-5 3E-5 Th-228 7E-6 1E-5 Ytterbium (70) Yb-175 1E-4 1E-4 Th-230 2E-6 3E-5 Yttrium Y-90 2E-5 2E-5 Th-231 2E-4 2E-4 Y-91m 3E-3 3E-3 Th-232 2E-6 4E-5 Y-91 3E-5 3E-5 Th-natural 2E-6 2E-5 Y-92 6E-5 6E-5 Th-234 2E-5 2E-5 Y-93 3E-5 3E-5 Thulium (69) Tm-170 5E-5 5E-5 Zinc (30) Zn-65 1E-4 2E-4 Tm-171 5E-4 5E-4 Zn-69m 7E-5 6E-5 Tin (50) Sn-113 9E-5 8E-5 Zn-69 2E-3 2E-3 Sn-124 2E-5 2E-5 Zirconium (40) Zr-93 8E-4 8E-4 Tungsten (74) W-181 4E-4 3E-4 Zr-95 6E-5 6E-5 W-185 1E-4 1E-4 Zr-97 2E-5 2E-5 W-187 7E-5 6E-5 Uranium (92) U-230 5E-6 5E-6 U-232 3E-5 3E-5 U-233 3E-5 3E-5 U-234 3E-5 3E-5 U-235 3E-5 3E-5 U-236 3E-5 3E-5 U-238 4E-5 4E-5 U-240 3E-5 3E-5 U-natural 3E-5 3E-5 Any single radio-nuclide not listed above with decay mode other than alpha emission or spontaneous fission and with radio - active half-life 3E-6 3E-6 greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Any single radio- nuclide not listed above, which decays by alpha emission or spontaneous fission. 3E-8 3E-8

1. If the identity of any radionuclide is not known, the limiting values for purposes of this table shall be: 3E-8 uCi/ml.
2. If the identity and concentration of each radionuclide are known, the limiting values should be derived as follows: Determine, for each radionuclide in the mixture, the ratio between the quantity present in the mixture and the limit otherwise established in Appendix B for the specific radionuclide not in a mixture. The sum of such ratios for all the radionuclides in the mixture may not exceed 1 (i.e. unity).

December 2018

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