ML18193A457

Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report for 2017

ML18193A457
Person / Time
Site:	Calvert Cliffs
Issue date:	07/10/2018
From:	Laura Smith Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
Download: ML18193A457 (29)

Text

i Larry D. Smith Exelon Generation ~ 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.sm1th2@exeloncorp.com 10 CFR 50.36{a){2) and 72.44(d)(3)

July 1O, 2018 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 Refere nces: 1. Calvert Cliffs Unit Nos. 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 the latest revision 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 (41 O) 495-5219.

Respectfully,

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Regulatory Assurance Manager

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Document Control Desk July 10, 2018 Page 2

Attachment:

( 1) Radioactive Effluent Release Annual Report - 2017 (2) Offsite Dose Calculation Manual for Calvert Cliffs Nuclear Power Plant, CY-CA-170-301 , Revision 000 cc: NRC Project Manager, Calvert Cliffs S. Gray, MD-DNR NRC Regional Administrator, Region I Director, NMSS NRC Resident Inspector, Calvert Cliffs J. Folkwein , ANI

Radioactive Effluent Release AnnualReport-2017

I' .

RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2017 Facility - Calvert Cliffs Nuclear Power Plant and Independent Spent Fuel Storage Installation Licensee - Calvert Cliffs Nuclear Power Plant, LLC Thi s report covers the period January 1, 2017 to December 31 , 2017 for Calvert Cliffs Nuclear Power Plant.

This report covers the period June 1, 2017 to May 3 1, 2018 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 Commi sion (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 station's 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 Effl uent Release Report (ARERR) and the Annual Radiological Environmental Operating Report (AREOR).

The ARERR reports the results of a station 's 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 sample are analyzed for radioactivity. Environmental samples include air, water, vegetation, and other sampl e types that are identified as potential pathways through which radioactivity can reac h humans.

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 Generall y 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

RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT-2017 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 The Electromagnetic Spectrum Wav*i.noth In mt1ters

<- 1 About the IIH of:

. Alomlc Builcings Gr8lns Proto zoans Bacferie Molecules Aloma of suga r nuclel An atom is the smallest part of an element that maintai ns the characteristics of that element. Atoms are made up of three parts: protons, neutrons, and electrons.

Graphic 3. Structure of an Atom Electron 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 relati vely 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 radioacti ve. A radioactive isotope can emit radi ation 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 radionucides 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 that is used to cool the reactor 2

RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2017 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 plant's 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.

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 Half-life 1000 800 The amount of time it takes for half of the origina l radioactivity to decay 600 Activity 400 200 0

1 half-life 2 half-lives 3 half-lives 4 half-lives 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.

C. Measuring Radiation There are fo ur 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 (µCi), 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 are measured milliroentgen (mR), 1/1 ,000 of one R.

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RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2017

• 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 rnillirad (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 rnillirem (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. 310 mrem comes 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:

Gra hie 5. Sources o Radiation Ex osure in the U.S. , rom NCRP Re ort No. 160 Sources of Radiation Exposure in the U.S.

Industrial a nd Terrestrial (Soil) - 3%

Occupationa l Interna l - 5% <0 .1%

Co nsum er - 2 %

Nuclear Medici ne 12%

D Natu ral Sources - 50%

-310 millirem (0.31 rem )

Man made Sources - 50 %

-3 10 millirem (0.31 rem}

Soum>, NCRP Report Nb . 1.60 {20091 Full report is ava i lable on the ~I CRP w ebsite at www. ~! CR Pon.Ii ne.o rg 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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RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT- 2017 Graphic 6 .Relative Doses from Radiation Sources, from EPA Radiation Doses and Sources RELATIVE DOSES FROM RADIATION SOURCES All dos** from the NalloM I Council on Radl atJon Prot*ctlon

• Measurements, lte port No. 160 (unless 01herwl1e d e noted)

WholeNdyCT 1 ,000 mllllrem (sin gle procedure)

Upper ~roant*tlnal *-ray axa,n wttfl fh.oroacopy 600 mllllrem (single procedure)

IUMlon I n * ~ U.S. homa 228 mllllrem

(*nnua l)

H...iCT 200 mllllrem

{slngl* procedurwJ Co*mk racllaHon ffYlf19 lff Oenve.r (h'9h etev.tlon)

• PPf'O*lmately 80 ml lll rem (annual)

M*mmot1ram 42 mllllrem

<*lngJ* pro<edu,w/

~ Coemlc rad&etlon llvlne at ...

FrOm JCRP 2007 level(lowolevatlon) appn,*lmately lO mllllrem (annual) ltacfletlon In the body 29 mllllrem (anttu* IJ TerTeStrt.l radlo.ctfvfty 21 mllllrem (annua l)

ChiNtx-,..,.-

10 mllll rem (slngle procedu,..)

Uvl"I near* nudur power station

< 1 mllllrem

( a nnual) mrem 5

RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT-2017 E. Radiation Ri sk Current science suggests there is some ri sk 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 so me ri sk.

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 ri sks 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 Days of Lost Life Expectancy Smoking* Men Heart Disease Smoking - Women Cancer Every 10 lbs overweight Stroke -

Motor Vehicle Accident -

Air Pollution

• Radon I Chemical Residue in Foods I Drowning I Hurricanes and Tornadoes lightning Nuclear Power 0 500 1000 1500 2000 2500 3000 Days of Lost Life Expectancy Hurricanes and Tornadoes Lightning Nuclear Power I 0 0.2 0 .4 0.6 0.8 1.2 1.4 1.6 1.8 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 Treatment 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 6

RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT-2017 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 Treatment 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.

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 Li ves 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 7

RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2017 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.

IV. TECHNICAL SPECIFICATION REPORTING REQUIREMENTS A. Calvert Cliffs Nuclear Power Plant (CCNPP), Technical Specification 5.6.3

1. 2017 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: 10.45 Curies of C-14 from Unit 1 and 9.82 curies from Unit 2.

b. Release was consistent throughout the year.

c. Carbon-14 release values were estimated using the methodology included in the Electric Power Research Institute (EPRI) Technical Report 1021106, using the 2017 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 364.77 days for Unit 1 and 342.67 days for Unit 2.

d. Meteorological dispersion factor (X/Q) at the nearest residence with a garden located at 1.5 miles in the southeast meteorological sector is 2.29E-07 sec/m3 .

e. Pathways considered to the hypothetical maximally exposed member of the public (child) were inhalation and leafy vegetation ingestion.

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RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2017

2. 2017 Dose Assessment Summary Quarter 1 Quarter 2 Quarter 3 Quarter 4 Yearly Liquid Effluent Dose 3mrem 3mrem 3 mrem 3mrem 6mrem Limit, Total Body Total Body Dose 3.62E-04 1.82E-04 2.85E-04 5.2 1E-04 1.35E-03

% of Limit 0.012 0.006 0.010 0.017 0.023 Liquid Effluent Dose lOmrem 10 mrem 10 mrem 10 mrem 20 mrem Limit, Any Organ Organ Dose 6.25E-04 2.03E-04 3.05E-04 5.30E-04 1.66E-03 1

% of Limit 0.006 0.002 0.003 0.005 0.008 Gaseous Effluent Dose Limit, Gamma 10 mrad 10 rnrad 10 mrad 10 mrad 20 rnrad Air Gamma Air Dose 2.19E-05 2.17E-05 2.lOE-05 1.78E-05 8.24E-05

% of Limit 0.0002 0.0002 0.0002 0.0002 0.0004 Gaseous Effluent 20 rnrad 20 mrad 20 mrad 20 mrad 40 mrad Dose Limit, Beta Air Beta Air Dose 1.37E-05 7.66E-06 7.42E-06 6.28E-06 3.51E-05

% of Limit 0.00007 0.00004 0.00004 0.00003 0.00009 Gaseous Effluent Dose Limit, Any Organ (Iodine, 15 mrem 15 rnrem 15 mrem 15 rnrem 30mrem Tritium, Particulates with >8 day half-life)

Organ Dose l.50E-04 2.72E-04 4.45E-04 l.96E-04 l.06E-03 2

% of Limit 0.001 0.002 0.003 0.001 0.004 Total Body Dose (NG) 2.06E-05 2.06E-05 2.00E-05 l .69E-05 7.81E-05 Skin Dose (due to NG) 3.20E-05 3.02E-05 2.92E-05 2.47E-05 1.16E-04 C-14 Total Body/Organ rnrem Bone Dose 3.31E-03 3.81E-03 3.85E-03 3.85E-03 1.48E-02 Total Body Dose 6.47E-04 7.46E-04 7.54E-04 7.54E-04 2.90E-03 1

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 20 17.

2 The controlling gaseous pathway was the teen-lung pathway representing the organ with the highest calculated dose during the calendar year of 2017. There is currently no milk pathway.

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RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT- 2017

3. 40 CFR 190 Total Dose Compliance Based upon the calendar year 2017 and the ODCM calculations, the maximum exposed individual would receive 0.07 % of the allowable dose. During the calendar year 2017. 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 Any Other Whole Body Thyroid Or2an Dose Limit 25 mrem 75 mrem 25 mrem Liquid l .35E-03 l.30E-03 l.66E-03 Gas l .06E-03 l .06E-03 l.06E-03 C-14 2.90E-03 l.48E-02 Dose 5.31E-03 2.36E-03 l.75E-02

% of Limit 0.021 0.003 0.070 Child bone dose was used for Any Other Organ due to C-14

4. Solid Waste Report Requirements During 2017, 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 2017 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 Offsite Dose Calculation Manual - Two revisions were performed to the ODCM in 2017 . The March 2017 revision updated the ODCM from CH-ODCM to CY-CA-170-301 in addition to other document changes. The May 2017 revision removed a statement declaring specific controls "not applicable" in multiple tables . Both revisions are attached to this report.

Process Control Program - Two editorial changes were made to the procedure RW-AA-100, Process Control Program for Radioactive Wastes. The first change added Nine Mile Point to a list of stations in bullet 4.2.11 describing DAW storage locations . The second change added a reference to the Fitzpatrick UFSAR due to the addition of that station to the Exelon fleet.

B. Radioactive Effluent Monitoring Instrumentation During 2017, the Waste Gas RMS , O-RE-2191, exceeded the 30 days inoperable time period allowed in ODCM section 3.3.3.9. The monitor was declared inoperable on 7/12/13 , and has remained inoperable since that time.

The RMS is scheduled to be replaced in the year 2020.

C. Independent Spent Fuel Storage Installation (ISFSD, ISFSI Technical Specification 6.3 Four casks of spent fuel were transferred to the ISFSI during the reporting period. No quantity of radionuclides was released to the environment during the ISFSI operation in 2017. Additional information regarding the ISFSI radiological environmental monitoring program is included in the Annual Radiological Environmental Operation Report.

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RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2017 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

~ollected 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.I.

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 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. l.

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 11

RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT-2017 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. l 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.

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.

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RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT- 2017 Where errors could be estimated they are usuall y considered additive.

E. Meteorological Data A summary of required meteorological data is included in the Annual Radi ological En vironmental 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 lice nse is terminated by the Commission. If record of relevant information are kept for other purposes, reference to these records and their locations may be used. Information the Commission considers important to decommissioning consists of records of spills or other unu sual 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 in volved nuclides, quantities, forms, and concentrations.

To assist in the decommissioning, and to provide earl y and advance detecti on of any unmonitored releases of radioacti ve materi al fro m the site, groundwater is routinely sampled. These groundwater samples are analyzed for gamma and tritium activity. Sample size and/or count times are adju sted to achieve analytical sensiti vities lower than the environme ntal LLDs for gamma emitters (listed in ODCM Table 4 .12- 1). The established LLD limit for tritium is 200 pCi/l. The 2017 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. Correction s to the 2016 ARERR a . Appendi x B includes a correction to section III.A.3 of the 20 16 ARERR.

13

RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT- 2017 VIII. BATCH RELEASES 2017 A Liquid (1) 1ST 2ND 3RD 4TH QUARTER QUARTER QUARTER QUARTER

1. Number of batch 12 7 7 10 releases

2. Total time period for 8.08E+03 4.30E+03 3.96E+03 5.70E+03 batch releases (min)

3. Maximum time period for a batch release 1.67E+03 6.85E+02 7.05E+02 6.34E+02 (min)

4. Average time period 6.73E+02 6.15E+02 5.66E+02 5.70E+02 for batch release (min)

5. Minimum time period for a batch release 4.75E+02 5.35E+02 5.13E+02 4.22E+02 (min)

6. Average stream flow during periods of effluent into a flowing 4.56E+06 4.62E+06 4.58E+06 4 .61E+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.

14

RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT-2017 B. Gaseous 1ST 2ND 3RD 4TH QUARTER QUARTER QUARTER QUARTER

1. Number of batch releases 24 25 21 19

2. Total time period for batch l.07E+04 1.04E+04 8.89E+03 7.17E+03 releases (min)

3. Maximum time period for a 2.73E+03 7.17E+02 5.57E+02 7.85E+02 batch release (min)

4. Average time period for 4.44E+02 4.15E+02 4.23E+02 3.77E+02 batch release (min)

5. Minimum time period for a 6.00E+Ol 1.72E+02 3.41E+02 1.01E+02 batch release (min) 15

RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT-2017 IX. ABNORMAL RELEASES 2017 1ST 2ND 3RD 4TH QUARTER QUARTER QUARTER QUARTER A. Liguid I. Number of releases 2. Total activity released (Curies) B. Gaseous

1. Number of releases 2. Total activity releases (Curies) 16

APPENDIX A RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2017 TABLE lA- REG GUIDE 1.21 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 1ST 2ND 3RD 4TH EST. TOTAL UNITS QUARTER DARTER DARTER QUARTER ERROR,%

A. FISSION AND ACTIVATION GASES I. Total Release Ci l.20E-01 3.35E-02 3.24E-02 2.75E-02 +/-l.20E+OI I

2. Average release rate for period µCi/sec J.52E-02 4.25E-03 4.12E-03 3.49E-03

3. Percent of ODCM Ii mit ( I)  % (I) (l) ( 1) (])

4. Percent of ODCM limit (2)  % (2) (2) (2) (2)

B. IODINES I. Total Iodine - 131 Ci <LLD <LLD <LLD <LLD +/-6.SOE+OO I

2. Average release rate for period µCi/sec <LLD <LLD <LLD <LLD

3. Percent of ODCM limit  % (3) (3) (3) (3)

C. PARTICULATES I. Particulates with half li ves greater than 8 days Ci <LLD <LLD l .12E-07 2.09E-06 +/-l .20E+Ol I

2. Average release rate for period µCi/sec <LLD <LLD l.43E-08 2.65E-07

3. Percent of ODCM limit  % (3) (3) (3) (3)

D. TRITIUM

1. Total Relea e Ci l .69E+OO 3.07E+OO 5.0IE+OO 2.l9E+OO +/-l.32E+Ol

2. Average release rate for period Ci/sec 2.15E-O l 3.89E-OI 6.35E-0I 2.77E-OI E. GROSS ALPHA I. Total Release Ci <LLD <LLD <LLD <LLD +/-2.SOE+OI

2. Average re lease rate fo r period Ci/sec <LLD <LLD <LLD <LLD F. Carbon-14 I. Total Release Ci 4 .52E+OO 5.2IE+OO 5.27E+OO 5.27E+OO NIA

2. Average release rate for period Ci/sec 5.82-01 6.63E-Ol 6.63E-OI 6.63E-Ol NOTES TO TABLE lA (1) Percent of quarterly gam ma-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 RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT- 2017 TABLE lB - 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 3.02E-02 3.34E-02 3.24E-02 2.74E-02 Krypton-85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Krypton-85 m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Krvpton-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Krypton-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xenon-J3Im Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xenon-133 Ci <LLD <LLD <LLD <LLD 8.59E-02 2.79E-05 3.37E-05 7. l5E-05 Xenon-133m Ci <LLD <LLD <LLD <LLD 2.92E-03 <LLD <LLD <LLD Xenon-135 Ci <LLD <LLD <LLD <LLD l .20E-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 <LLD <LLD <LLD <LLD 1.20E-01 3.35E-02 3.24E-02 2.75E-02

2. IODINES Iodine-131 Ci <LLD <LLD <LLD <LLD (1) (l) (1) (l )

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

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

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

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

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

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 I .12E-07 2.09E-06 (1) (I) (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) ( I) (1) (1)

Cerium-141 Ci <LLD <LLD <LLD <LLD ( I) (1) ( 1) ( I)

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

~ Total for period Ci <LLD <LLD l.12E-07 2.09E-06 (1) (1) (1) (1)

A-2

APPENDIX A RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2017 TABLE lB- REG GUIDE 1.21 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE UNITS 1ST QUARTER I 2ND QUARTER I 3RD QUARTER I 4TH QUARTER 1ST QUARTER I QUARTER 2ND I 3RD I 4TH QUARTER QUARTER

4. GROSS ALPHA RADIOACTIVITY Gross Alpha Ci <LLD I <LLD I <LLD I <LLD <LLD I <LLD I <LLD I <LLD

5. I TRITIUM Tritium Ci l .69E+OO I 3.07E+OO I 5.0lE+OO I 2. l8E+OO 4. l3E-06 I <LLD I <LLD I <LLD

6. I Carbon-14<2>

Carbon-14 Ci 4.52E+OO I 5.21E+OO I 5.27E+OO I 5.27E+OO NIA I NIA I NIA I NIA NOTES TO TABLE lB

( 1) Iodines and particulates in batch releases are accounted for with the main vent continuous samplers when the rel ease is made through the plant main vent.

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

A-3

APPENDIX A RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2017 TABLE 2A - REG GUIDE 1.21 LIOUID EFFLUENTS - SUMMATION OF ALL RELEASES 1ST 2ND 3RD 4TH EST. TOTAL UNITS QUA RTER QUARTER QUARTER QUARTER ERROR,%

A. FISSION AND ACTIVATION PRODUCTS

1. Total Release (not including tritium , gases, alpha) Ci 2.12E-03 6.37E-04 4.0SE-04 6.54E-04 +/-l.03E+Ol

2. Average di luted concentration during period µCi/ml 2.02E-12 5.26E-13 3.35E-13 5.41E-13

3. Percent ofODCM limit (I)  % (I) (1) (1) (l)

4. Percent of ODCM limit (2)  % (2) (2) (2) (2)

B. TRITIUM I. Total Release Ci 3.33E+02 1.71E+02 2.75E+02 5.00E+02 +/-l.03E+OI

2. Average di luted concentration during period µ_Ci/ml 3. l 7E-07 I .41E-07 2.27E-07 4.13E-07

3. Percent of applicable limit (3)  % l.06E-02 4.70E-03 7.57E-03 l.38E-02 C. DISSOLVED AND ENTRAINED GASES I. Total Release Ci 5.03E-04 3.28E-05 4.lSE-05 2.0SE-04 +/-l.03E+Ol

2. Average di luted concentration during period µ_Ci/ml 4.79E-1 3 2.71E-14 3.43E- 14 l.69E-1 3 D. GROSS ALPHA RADIOACTIVITY I 1. Total Release Ci <LLD <LLD <LLD <LLD NIA E VOLUME OF WASTE RELEASED ( pnor to 1 ut1on I. Volume of waste released liters I. l IE+08 9.37E+07 9.53E+07 l . 13E+08 +/-l .30E+OO F. VOLUME OF DILUTION WATER USED l.05E+I2 1.2 IE+ 12 I.2IE+12 l.21E+l2 +/-l.64E+Ol DURING PERIOD (4) liters NOTES TO TABLE 2A (1) Percent ofll.C.3 Quarterly Organ Dose Limit (10 rnrem) can be found in Section IV.A.2 (2) Percent of II.C.3 Quarterly Whole Body Dose Limit (3 rnrem) can be found in Section IV.A.2 (3) Limit used is 3 x 10-3 µCi/ml (4) Includes di lution water used during continuous discharges.

A-4

APPENDIX A RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2017 TABLE 2B - REG GUIDE 1.21 LIOUID EFFLUENTS CONTINUOUS MODE BATCH MODE 1ST 2ND 3RD 4TH 1ST 2ND 3RD 4TH NUCLIDES RELEASED Units QUARTER QUARTER QUARTER QUARTER QUA RTER 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 <LLD <LLD <LLD <LLD Iron - 55 Ci (2) (2) (2) (2) <LLD <LLD <LLD <LLD Cobalt - 57 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cobalt - 58 Ci <LLD <LLD <LLD <LLD l .08E-03 3.55E-04 l.92E-04 6.60E-05 Iron - 59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cobalt - 60 Ci <LLD <LLD <LLD <LLD 6.24E-04 l . 17E-04 l.43E-04 I .41E-04 Nickel-63 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 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 Stro ntium - 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 l.58E-05 <LLD <LLD 5.37E-06 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 - I 05 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ruthe nium - 105 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Si lver - 11 Om Ci <LLD <LLD <LLD <LLD 7.72E-05 <LLD <LLD <LLD T in - 11 3 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Tin - ll7m 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 l.12E-04 Tellurium - 125m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Tellurium - 132 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Iodine - 13 1 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Iodine - 132 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD A-5

APPENDIX A RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT- 2017 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 Iodine - 133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Iod ine - 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 3.18E-04 l .64E-04 7.04E-05 3.29E-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 (l,P) Ci <LLD <LLD <LLD <LLD 2.12E-03 6.36E-04 4.05E-04 6.54E-04 Krypton - 85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xenon - 13lm Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xenon - 133 Ci <LLD <LLD <LLD <LLD 5.03E-04 3.28E-05 4.15E-05 2.05E-04 Xenon - 133m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LE.D Xenon - 135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total For Period (NG) Ci <LLD <LLD <LLD <LLD 5.03E-04 3.28E-05 4.15E-05 2.05E-04 Triti um Ci 1.12E-Ol I .69E-Ol 2.37E-Ol l.86E-Ol 3.33E+02 l.7 IE+02 2.75E+02 5.00E+02 Total For Period (Triti um) Ci l.12E-01 l.69E-Ol 2.37E-Ol l.86E-0I 3.33E+02 l.71E+02 2.75E+02 5.00E+02 NOTES TO TABLE 2B (I) 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 RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT- 2017 TABLE3A 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 1.17E+Ol 25 %

Ci l.75E+02 b) Dry compressible m3 3.37E+02 25 %

waste, contaminated Ci 6.27E-01 equipment, etc .

c) Irradiated components, m3 NIA NIA control rods, etc. Ci d) Other (cartridge filters, m3 NIA 25 %

rrusc. dry Ci compressible, Oil) e) Solidification agent or m3 NIA NIA absorbent Volume shipped represents waste generated prior to offsite volume reduction .

2. Estimate of Major Nuclides (B y T ype of W aste - O nlLy nuc l'1des > 1 % are reported)

Spent Resins, Filters Nuclide Abundance (%)

Mn-54 1.36 Fe-55 4.60 Co-58 16.46 Co-60 13 .64 Ni-63 21.38 Cs-134 3.25 Cs-137 36.53 A-7

APPENDIX A RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT-2017

2. Estimate of Major Nuclides (B,y T ype ofW aste - 01nly nuc I"1des > 1 % are reported)( cont.)

Dry Active Waste Nuclide Abundance (%)

Cr-51 4.74 Fe-55 11.92 Co-58 22.49 Co-60 8.36 Ni-63 26.19 Zr-95 4.45 Nb-95 7.35 Sb-125 1.08 Cs-137 11 .83 Irradiated Components Nuclide I Abundance(%)

NIA Other Waste Nuclide Abundance(%)

NIA NIA A-8

APPENDIX A RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2017

3. S0 l"dW I aste 1spos1tion Number of Shioments Mode of Transoortation Destination 8 Motor Surface Transit Energy Solutions (Hittman) Oak Ridge, TN 2 Motor Surface Transit Energy Solutions (Hittman) Clive, UT 2 Motor Surface Transit Waste Control Specialists LLC (Hittman) Andrews, TX 1 Motor Surface Transit Energy Solutions (Interstate Ventures) Oak Ridge, TN 1 Motor Surface Transit Energy Solutions (Landstar lnway) Oak Ridge, TN 1 Motor Surface Transit Energy Solutions (Tri-State Motor Transit Co.) Oak Ridge, TN B. IRRADIATED FUEL SHIPMENTS (DISPOSITION) NIA A-9 L

APPENDIX B RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT- 2017 ERRATA/CORRECTIONS TO 2016 ARERR Secti on III.A.3. 40 CFR 190 Total Dose Compliance of the 201 6 ARERR excluded the C-14 dose values fro m the summations listed in the 'Dose' and '% of Limit' rows of the table.

EPA 40CFR190 Individual in the Unrestricted Area Whole Body Thyroid Any Other Organ Dose Limit 25 mrem 75 mrem 25 mrem Liquid 2.89E-03 l.80E-03 5.46E-03 Gas 3.18E-04 4.33E-03 3.35E-04 C-14 8.20E-03 4.13E-02 Dose 1.14E-02 6.13E-03 4.71 E-02

% of Limit 4.56E-02 8.17E-03 1.88E-01 Child bone dose was used fo r Any Other Organ due to C-14 The paragraph preceding the table should reflect this change:

Based upon the calendar year 2016 and the ODCM calcul ations, the maximum exposed individual would receive 0.188%

of the allowable dose.

B-1