ML19137A092

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Annual Radioactive Effluent Release Report, January 1, 2018 - December 31, 2018.
ML19137A092
Person / Time
Site: Ginna  Constellation icon.png
Issue date: 05/15/2019
From:
Exelon Generation Co, Ginna
To:
Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
Download: ML19137A092 (31)
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ATTACHMENT 1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2018 - DECEMBER 31, 2018 R.E. Ginna Nuclear Power Plant, LLC

Exelon Generation ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT:

JANUARY 1, 2018 - DECEMBER 31, 2018 MAY2019 111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111 R.E. Ginna Nuclear Power Plant 1503 Lake Road Ontario, New York 14519

TABLE OF CONTENTS 1.0 Introduction ........................................................................................................................ 1 2.0 Supplemental Information ................................................................................................ 1 2.1 Regulatory Limits .................................................................................................... 1 2.2 Effluent Concentration Limits ............................................ :.................................... 2 2.3 Release Rate Limits Based on Average Nuclide Energy ......................................... 3 2.4 Measurements and Approximations of Total Radioactivity .................................... 3 2.5 Batch Releases ......................................................................................................... 3 2.6 Abnormal Releases .................................................................................................. 4 3.0 Summary of Gaseous Radioactive Effluents ...................................................................4 4.0 Summary of Liquid Radioactive Effluents ...................................................................... 4 5.0 Solid Waste .........................................................................................................................4 6.0 Lower Limit of Detection ........................ ~ ............................................................. ~ ........... 4 7 .0 Radiological Impact ...........................................................................................................5 7.1 Total Dose ................................................................................................. '. .............. 5 8.0 Meteorological Data ........................................................................................................... 5 9.0 Land Use Census Changes ................................................................................................ 6 10.0 Changes to the Offsite Dose Calculation Manual ........................................................... 6 11.0 Changes to the Process Control Program ........................................................................ 7 12.0 Major Changes to Radwaste Treatment Systems ........................................................... 7 13.0 Inoperable Monitors .......................................................................................................... 7 14.0 Changes to Previous Annual Radioactive Effluent Release Reports ............................7 15.0 Groundwater Monitoring ..................................................................................................7 16.0 ISFSI ...................... ................................................................. ........ .... 8 17.0 Offsite Dose Due to Carbon-14 ..................................................................*...................... 8 17.1 Gaseous Effluents ........................................................................................... ~ ........ 9 17 .2 Liquid Effluents ................................................................. .............. 9 R.E. Ginna Nuclear Power Plant ARERR Docket No. 50-244 01/01/2018-12/31/2018

LIST OF TABLES Table lA Gaseous Effluents - Summation of all Releases .......................................................... 10 Table lB Gaseous Effluents - Continuous and Batch Releases .................................................. 11 Table 2A Liquid Effluents - Summation of all Releases ............................................................. 13 Table 2B Liquid Effluents - Continuous and Batch Releases ..................................................... 14 Table 3 Solid Waste and Irradiated Fuel Shipments ................................................................. 16 Table 4A Radiation Dose to Maximum Receptor from Gaseous Effluents ................................. 19 Table 4B Radiation Dose to Maximum Receptor from Liquid Effluents ........ :.......................... 23 Table 5 Groundwater Monitoring Wells ................................................................................ 24 Table 6 Offsite Dose Due to Carbon-14 in Gaseous and Liquid Effluents ................................ 27 Appendix A, Annual Report on the Meteorological Monitoring Program at the Ginna Nuclear Power Plant. ................................................................. ................ 28 Appendix B, R.E. Ginna Nuclear Power Plant Offsite Dose Calculation Manual, Revision 36 ................................................................. .................................... 74 R.E. Ginna Nuclear Power Plant ii ARERR Docket No. 50-244 01/01/2018-12/31/2018

1.0 INTRODUCTION

R.E. Ginna Nuclear Power Plant (Ginna) has prepared this Annual Radioactive Effluent Release Report (ARERR) in accordance with the requirements of Technical Specification Section 5.6.3.

This report, covering the period from January 1, 2018 through December 31, 2018, provides a summary of the quantities of radioactive gaseous and liquid effluents and solid waste released from the plant presented in the format outlined in Appendix B of Regulatory Guide 1.21, Revision 1, June 1974.

All gaseous and liquid effluents discharged during this reporting period complied with the limits of the Ginna Technical Specifications as defined in the Offsite Dose Calculation Manual (ODCM). The ODCM is Ginna procedure CY-GY-170-300, Offsite Dose Calculation Manual (ODCM) R.E. Ginna Nuclear Power Plant.

2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits The ODCM limits applicable to the release of radioactive material in liquid and gaseous effluents are:

2.1.1 Fission and Activation Gases The instantaneous dose rate, as calculated in the ODCM, due to noble gases released in gaseous effluents from the site shall be limited to a release rate that would yield .$

500 mrem/yr to the total body and _$ 3000 mrem/yr to the skin if allowed to continue for a full year.

The air dose, as calculated in the ODCM, due to noble gases released in gaseous effluents from the site shall be limited to the following:

(I) During any calendar quarter to.$ 5 mrad for gamma radiation and to

.$ 10 mrad for beta radiation.

(ii) During any calendar year to.$ 10 mrad for gamma radiation and to

.$ 20 mrad for beta radiation.

  • 2.1.2 Radioiodine, Tritium. and Particulates The instantaneous dose rate, as calculated in the ODCM, due to radioactive materials released in gaseous effluents from the site as radioiodine species, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than eight days shall be limited to a release rate that would yield.$ 1500 mrem/yr to any organ if allowed to continue for a full year.

R.E. Ginna Nuclear Power Plant 1 ARERR Docket No. 50-244 01/01/2018-12/31/2018

Dose to an individual from radioiodine, radioactive materials in particulate form, and radionuclides other than.noble gases with half-lives greater than eight days released with gaseous effluents is calculated in accordance with ODCM methodology. The dose to an individual shall be limited to:

(i) During any calendar quarter to~ 7.5 mrem to any organ.

(ii) During any calendar year to~ 15 mrem to any organ.

2.1.3 Liquid Effluents The release of radioactive liquid effluents shall be such that the concentration in the circulating water discharge does not exceed 10 times the limits specified in Appendix B, Table II, Column 2 and notes thereto of 10 CPR 20, as explained in Section 4 of the ODCM. For dissolved or entrained noble gases the total activity due to dissolved or entrained noble gases shall not exceed 2E-04 uCi/ml.

The dose or dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas is calculated according to ODCM methodology and is limited to: *

(i) During any calendar quarter to~ 1.5 mrem to the total body and to ~ 5 mrem to any organ, and (ii) During any calendar year to~ 3 mrem to the total body and to~ 10 mrem to any organ.

2.2 Effluent Concentration Limits (ECLs) 2.2.1 For gaseous effluents, effluent concentration limits (ECLs) are not directly used in release rate calculations since the applicable limits are stated in terms of dose rate at the unrestricted area boundary, in accordance with Technical Specification 5.5.4.g.

2.2.2 For liquid effluents, ECLs ten times those specified in 10 CPR 20, Appendix B, Table II, column 2, are used to calculate release rates and permissible concentrations at the unrestricted area boundary as permitted by Technical Specification 5.5.4.b. A value of 2E-04 uCi/ml is used as the ECL for dissolved and entrained noble gases in liquid effluents.

R.E. Ginna Nuclear Power Plant 2 ARERR Docket No. 50-244 01/01/2018 - 12/31/2018

2.3 Release Rate Limits Based on Average Nuclide Energy The release rate limits for fission and activation gases from the R.E. Ginna Nuclear Power Plant are not based on the average energy of the radionuclide mixture in gaseous effluents; therefore, this value is not applicable. However, the 2018 average beta/gamma energy of the radionuclide mixture in fission and activation gases released from Ginna is available for review upon request.

2.4 Measurements and Approximations of Total Radioactivity Gamma spectroscopy was the primary analysis method used to determine the radionuclide composition and concentration of gaseous and liquid effluents. Composite samples were analyzed for Fe-55, Ni-63, S.r-89, and Sr-90 by a contract laboratory. Tritium and alpha analysis were performed using liquid scintillation and gas flow proportional counting respectively.

The total radioactivity in effluent releases was determined from the measured concentration of each radionuclide present in a representative sample and the total volume of effluents released.

2.5 Batch Releases 2.5.1 Liquid

1. Number of batch releases: 1.05 E+02
2. Total time for batch releases (Minutes): 1.36 E+04
3. Maximum time for a batch release (Minutes): 5.73 E+02
4. Average time for batch releases (Minutes): 1.30 E+02
5. Minimum time for a batch release: 1.80 E+Ol
6. Average effluent release flowrate into the discharge 2.89 E+02 canal (Liters per Minute):
7. Average dilution flowrate of discharge canal during 1.24 E+06 effluent releases (Liters per Minute):

R.E. Ginna Nuclear Power Plant 3 ARERR Docket No. 50-244 01/01/2018 - 12/31/2018

2.5.2 Gaseous

1. Number of batch releases: 1.80 E+Ol
2. Total time for batch releases (Minutes): 5.01 E+05
3. Maximum time for a batch release (Minutes): 4.46 E+04
4. Average time for batch releases (Minutes): 2.79 E+04
5. Minimum time for a batch release (Minutes): 6.30 E+Ol 2.6 Abnormal Releases In 2018, there were no abnormal releases of liquid or gaseous effluents.

3.0

SUMMARY

OF GASEOUS RADIOACTIVE EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables lA and lB. Plant Vent and Containment Vent releases are modeled as mixed mode and the Air Ejector is modeled as a ground level release.

4.0

SUMMARY

OF LIQUID RADIOACTIVE EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in tables 2A and 2B.

5.0 SOLID WASTE The quantities of radioactive material released in shipments of solid waste transported from Ginna during the reporting period are summarized in Table 3. Principal nuclides were determined by gamma spectroscopy and non-gamma emitters were calculated from scaling factors determined by an independent laboratory from representative samples of that waste type.

The majority of Dry Active Waste (DAW) is processed utilizing an off-site vendor that reduces the volume and then transports the waste to a permitted landfill for disposal.

6.0 LOWER LIMIT OF DETECTION The required Lower Limit of Detection (LLD), as defined in Table 2-1 of the ODCM, was met on all effluent samples in 2018.

R.E. Ginna Nuclear Power Plant 4 ARERR Docket No. 50-244 01/01/2018-12/31/2018

7.0 RADIOLOGICAL IMPACT An assessment of doses to the hypothetical maximally exposed individual member of the public from gaseous and liquid effluents was performed for locations representing the maximum calculated dose in occupied sectors. Meteorological sectors to the north from NW through ENE are entirely over Lake Ontario, while the remaining meteorological sectors to the south (WNW through E) are over land. In all cases, doses were well below Technical Specification limits as defined in the ODCM. Doses were assessed based upon historical meteorological conditions considering the noble gas exposure, inhalation, ground plane exposure, and ingestion pathways.

The ingestion pathways considered were the fruit, vegetable, fish, drinking water, goat's milk, cow's milk and cow meat pathways.

Results of this assessment are presented in Tables 4A and 4B. Population doses are inferred from the population density, distance from the plant, and drinking water source.

7 .1 Total Dose 40 CFR 190 limits the total dose to members of the public due to radiation and radioactivity from uranium fuel cycle sources to:

  • :=:; 25 mrem total body or any organ and;
  • :=:; 75 mrem thyroid for a calendar year.

Using the maximum exposure and uptake pathways, the maximum liquid pathways, including C-14 dose, and the maximum direct radiation measurements at the site boundary, yield the following dose summaries to the hypothetical maximally exposed individual member of the public. The maximum total body dose is determined by summing the hypothetical maximum direct radiation dose exposure and the total body dose from gaseous and liquid pathways. Dose to any real member of the public should be conservatively bounded by these calculated doses:

  • Maximum Annual Total Body Dose: 13.2 mRem (Sum of 13.2 mrem direct radiation, l.06E-02 (Total Body Liquid Dose), 1.98E-05 (Total Body Gas Dose).
  • Maximum Annual Organ Dose: 2.42E-02 mRem (Adult, GI)
  • Maximum Annual Thyroid Dose: l .28E-02 mRem (Adult) 8.0 METEOROLOGICAL DATA The annual summary report of meteorological data collected during 2018 is included with this report, as Appendix A, Annual Report on the Meteorological Monitoring Program at the Ginna Nuclear Power Plant by Murray and Trettle, Incorporated.

R.E. Ginna Nuclear Power Plant 5 ARERR Docket No. 50-244 01/01/2018-12/31/2018

9.0 LAND USE CENSUS CHANGES In September 2018, Ginn a staff conducted a Land Use Survey to identify the location of the nearest milk animal, the nearest residence, and the nearest garden greater than 500 square feet in each of the nine sectors within a five-mile radius of the power plant. The Land Use Survey is conducted in accordance with Ginna procedures (Reference #4). If changes are noted in the annual Land Use Survey, alterations to Ginna's REMP program would be made to ensure sampling practices cover these new areas of potential public exposure.

Over the past year, the following land use observations were made within a 5-mile radius of the power plant: *

  • The nearest residence remains in the SSE sector, approximately 610 meters from the reactor.
  • Single-family home/ senior housing subdivision/ development construction was observed near the plant on LaFrank Drive (Ontario), and South of Route 104 near Tops Plaza (Ontario).
  • Lake Front Estates and Summer Lake subdivisions continue to expand along with the southeast corner of Lake Road and Slocum Road.
  • Other single-family home construction was observed sporadically within 5-miles of the plant.
  • A new 120-acre commercial hydroponic farm continues construction on the east-end of Timothy Lane (North of Route 104). No inhabitants at this time.
  • No new agricultural land use was identified.
  • No new food producing facilities were identified as the commercial hydroponic farm is not currently growing produce.
  • No new milk producing animals were identified.

10.0 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL There were three changes to the Offsite Dose Calculation Manual (ODCM) in 2018.

  • Revision 34, implemented April 27, 2018, was made to document the relocation of Environmental Sample Station #3 within the same meteorological sector. This revision had no adverse impact on radiological controls as verified in Plant Operations Review Committee (PORC) meeting 18-0008.
  • Revision 35, implemented June 5, 2018, removed obsolete area Radiation Monitors from Table 6-4. The obsolete area radiation monitors were R23, R-24, R-25, R-27, and R-28.

This revision had no adverse impact on radiological controls as verified in PORC meeting 18-0010.

  • Revision 36, implemented December 27, 2018, updated meteorological assumptions to R.E. Ginna Nuclear Power Plant 6 ARERR Docket No. 50-244 01/01/2018 -12/31/2018

align with Revision 6 of the Ginna Emergency Action Level (EAL). This revision had no adverse impact on radiological controls as verified in PORC meeting 18-0023.

Revision 36 of the ODCM is included with this report as Appendix B.

11.0 CHANGES TO THE PROCESS CONTROL PROGRAM There was one change to the Process Control Program on 8/15/18 as follows:

This revision does not impact effluent controls or Radwaste programs at Ginna 12.0 MAJOR CHANGES TO RADWASTE TREATMENT SYSTEMS There were no changes to the Radwaste Treatment Systems during the reporting period.

13.0 INOPERABLE MONITORS There was one occurrence in 2018 satisfying the requirement stated in Section 5.4 and Table 5-1, of the ODCM for weekly sample (cartridge) collection.

The surveillance of R-14A is redundant to R-lOB. R-lOB exhibited an extended run time on the filter due to R-14A being out of service which caused R-lOB to not be changed. The filter on R-lOB collected sample from 12/29/2018 - 1/8/2019, elapsing the weekly periodicity. At no time did gaseous effluents leave the station in an unmonitored pathway. Both detectors were restored to operability on 1/8/2019.

14.0 CHANGES TO PREVIOUS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTS None.

15.0 GROUNDWATER MONITORING In accordance Ginna's Chemistry procedures, environmental groundwater monitoring wells are sampled on a routine frequency. In 2018, Ginna staff collected and analyzed samples collected from a total of 14 groundwater monitoring wells:

  • GWOl: Warehouse Access Road (Control)
  • GW03: Screenhouse West, South Well
  • GW04: Screenhouse West, North Well R.E. Ginna Nuclear Power Plant 7 ARERR Docket No. 50-244 01/01/2018-12/31/2018
  • GW05: Screenhouse East, South
  • GW06: Screenhouse East, Middle
  • GW07: Screenhouse East, North
  • GW08: All Volatiles Treatment Building
  • GW 11: Southeast of Contaminated Storage Building (CSB)
  • GW12: West of Orchard Access Road
  • GW13: North of Independent Spent Fuel Storage Installation (ISFSI)
  • GW14: South of Canister Preparation Building*
  • GW 15: West of Manor House
  • GW16: Southeast of Manor House Groundwater samples are analyzed for tritium to a detection limit of 500 pCi/L and for gamma emitting radionuclides to the environmental LLDs. The analytical results for groundwater monitoring well samples collected during 2018 are presented in Table 5. All samples collected during 2018, which were analyzed for tritium and gamma emitting nuclides, did not yield a concentration greater than the calculated MDA.

16.0 OFFSITE DOSE DUE TO ISFSI A review of direct radiation between the Ginna ISFSI facility and the nearest residents was conducted. Environmental TLD station 64 is the highest direct radiation dose offsite and is the basis for the maximum direct radiation dose reported in 7 .1 A review of TLD stations 14, 15, 16 since fuel was first stored in ISFSI in 2010 indicate no change in offsite direct radiation dose as measured by TLDs.

  • Ginna ISFSI design is such that effluent releases of noble gases are precluded.

17.0 OFFSITE DOSE DUE TO CARBON-14 A study of Carbon-14 in effluent releases from Ginna was conducted in 1982 by Charles Kunz of New York State Department of Health, Center for Laboratories and Research. Results of this study are used as the basis for current Carbon-14 production and releases at Ginna. Using the Carbon-14 releases measured in the Kunz study at 4.3 Curies, adjusted for power uprate from 490 MWe to 580 MWe, and adjusted for increased capacity factor and 18-month fuel cycles, leads to a conservative estimate of 6.8 Curies released in gaseous effluents in 2018. Kunz further determined the chemical form of the Carbon-14 at Ginna to be approximately 10% Carbon Dioxide (CO2).

As a cross-check, the EPRI Carbon-14 Source Term Calculator was used to estimate Carbon-14 releases from Ginna, using Ginna specific reactor core data and reactor coolant chemistry to estimate the products of the activation reactions. The resulting estimate of 6.9 Curies per Equivalent Full Power Year (EFPY) agrees with the Kunz data, adjusted for current operating cycles.

R.E. Ginna Nuclear Power Plant 8 ARERR Docket No. 50-244 01/01/2018 - 12/31/2018

17.1 Gaseous Effluents Dose due to Carbon-14 in gaseous effluents was calculated using the following conditions:

a. 6.8 Curies of C-14 were released to atmosphere in 2018.
b. There was a refueling outage in 2018. However, according to the Kunz study it has little or no impact on the C-14 effluents and was not considered in this report.
c. 10% of the C-14 was in the chemical form of carbon dioxide (CO2), which is the only dose contributor. The bulk of C-14 is released in the chemical form of methane (CH4) .

. Methane would exhibit high upward velocity due to its low density relative to air.

Additionally, CH4 does not have an uptake pathway for humans.

d. Meteorological dispersion factor, (X/Q), at the site boundary to the hypothetical maximally exposed member of the public is 2.43E-07 sec/m3.
e. Dose calculations and dose factors are from Regulatory Guide 1.109 methodology.
f. Pathways considered were inhalation, milk consumption, and vegetation ingestion.
g. The critical receptor is a child at the site boundary in the ESE direction.

See Table 6 for an estimate of Carbon-14 in gaseous effluents during 2018.

17.2 Liquid Effluents Dose due to Carbon-14 in liquid effluents was calculated using the following conditions:

a. The liquid waste processing system.at Ginna has not been evaluated for efficiency of removal of Carbon-14. Therefore, no removal term was used in estimation of offsite dose.
b. Average concentration of C-14 in waste water as measured in the Kunz study was adjusted for current operating conditions and was 6.0E-07 uCi/cc.
c. l.72E+06 liters ofliquid waste (with the potential to contain C-14) were released with a total dilution flow of l.87E+ 12 liters.
d. Average diluted concentration of C-14 released was 5 .52E-13 uCi/cc.
e. Liquid effluent dilution factor for potable water pathway is 200.
f. Liquid effluent dilution factor for fish pathway is 1.
g. Dose calculations and dose factors are from Regulatory Guide 1.109 methodology.
h. The critical receptor is a child for the fish consumption pathway and the child is the critical receptor for the potable water pathway.

See Table 6 for an estimate of Carbon-14 in liquid effluents during 2018.

R.E. Ginna Nuclear Power Plant 9 ARERR Docket No. 50-244 01/01/2018 - 12/31/2018

TABLElA EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 2018 Effluent Type Units 1st Quarter 2°d Quarter Est. Total Error, 3rd Quarter 4th Quarter  %

A. Fission & Activation Gases

1. Total release Ci 2.08E-01 2.44E-01 4.12E-01 4.53E-01 2.80E+Ol
2. Average release rate for period uCi/sec 2.64E-02 3.09E-02 5.22E-02 5.75E-02
3. Percent of technical specification limit  % 4.19E-06 4.90E-06 8.29E-06 9.13E-06 B. Iodines
1. Total iodine-131 Ci 4.SlE-07 O.OOE+OO O.OOE+OO 7.08E-08 2.20E+Ol
2. Average release rate for period uCi/sec 5.72E-08 O.OOE+OO O.OOE+OO 8.99E-09
3. Percent of technical specification limit  % 1.24E-04 O.OOE+OO O.OOE+OO 1.95E-05 C. Particulates
1. Particulates with half-lives> 8days Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NIA
2. Average release rate for period uCi/sec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
3. Percent of technical specification limit  % O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
4. Gross alpha radioactivity Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Tritium
1. Total release Ci 4.64E+Ol 2.55E+Ol 3.48E+Ol 2.79E+Ol 1.50E+Ol
2. Average release rate for period uCi/sec 5.88E+OO 3.23E+OO 4.41E+OO 3.54E+OO
3. Percent of technical specification limit  % 6.88E-06 3.78E-06 5.16E-06 4.14E-06 Notes: Isotopes for which no value is given were not identified in applicable releases.

R.E. Ginna Nuclear Power Plant 10 ARERR Docket No. 50-244 01/01/2018 -12/31/2018

TABLElB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - CONTINUOUS AND BATCH RELEASES 2018 Nuclides Released Units Continuous Mode Batch Mode 3rd 4th pt Quarter znd Quarter 1*1 Quarter znd Quarter 3rd Quarter 4th Quarter Quarter Quarter

1. Fission Gases Argon-41 Ci 6.70E-03 9.58E-02 l.13E-01 l.30E-01 5.78E-02 Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-131m Ci Xenon-133 Ci 4.0SE-02 6.90E-03 8.73E-03 7.59E-02 l.18E-01 Xenon-133m Ci Xenon-135 Ci 1.43E-03 l.SOE-03 l.82E-03 Xenon-135m Ci Xenon-138 Ci Total for period Ci
2. Iodines Iodine-131 Ci 2.25E-07 3.54E-08 Iodine-132 Ci Iodine-133 Ci 6.23E-08 Iodine-135 Ci Total for period Ci 4.86E-02 1.04E-01 1.22E-01 2.06E-01 1.78E-01 R.E. Ginna Nuclear Power Plant 11 ARERR Docket No. 50-244 01/01/2018-12/31/2018

TABLE lB (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - CONTINUOUS AND BATCH RELEASES 2018 Nuclides Released Units Continuous Mode Batch Mode 2nd 3rd 4th 1st Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Quarter Quarter Quarter

3. Particulates strontium-89 Ci strontium-90 Ci cesium-137 Ci cobalt-57 Ci cobalt-58 Ci cobalt-60 Ci Unidentified Ci Total for period Ci
4. Tritium Hydrogen-3 Ci l.20E+Ol l.26E+Ol l.72E+Ol l.39E+Ol l.12E+Ol l.04E-01 l.86E-01 3.48E-02 Note: Isotopes for which no value is given were not identified in applicable releases.

R.E. Ginna Nuclear Power Plant 12 ARERR Docket No. 50-244 01/01/2018 -12/31/2018

TABLE2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 2018 Effluent Type Units 1*1 Quarter 2°d Quarter Est. Total Error, 3rd Quarter 4th Quarter  %

A. Fission & Activation Products

1. Total Release (not including tritium, gases, Ci O.OOE+OO O.OOE+OO 2.08E-05 l.39E-02 2.80E+Ol alpha)
2. Average Diluted concentration uCi/ml O.OOE+OO O.OOE+OO 4.03E-14 2.92E-11
3. Percent of aoolicable limit  % O.OOE+OO O.OOE+OO 4.03E-07 2.92E-04 B. Tritium
1. Total Release Ci l.31E+02 6.81E+Ol l.69E+02 l.14E+02 9.20E+OO
2. Average Diluted Concentration uCi/ml 3.41E-07 l.38E-07 3.28E-07 2.40E-07
3. Percent of applicable limit  % 3.41E-03 l.38E-03 3.28E-03 2.40E-03 C. Dissolved and Entrained Gases
1. Total Release Ci 5.13E-05 O.OOE+OO O.OOE+OO l.68E-03 2.80E+Ol
2. Average Diluted Concentration uCi/ml l.34E-13 O.OOE+OO O.OOE+OO 3.53E-12
3. Percent of aoolicable limit  % 6.70E-08 O.OOE+OO O.OOE+OO 1.77E-06 D. Gross Alpha Radioactivity
1. Total release Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO E. Vol. of Waste Released (prior to dilution) Liters l.12E+08 l.17E+08 l.95E+08 l.08E+08 F. Vol. of Dilution Water Used During Period Liters 3.83E+ll 4.93E+l 1 5.16E+l 1 4.76E+l 1 Note: Isotopes for which no value is given were not identified in applicable releases.

R.E. Ginna Nuclear Power Plant 13 ARERR Docket No. 50-244 01/01/2018 -12/31/2018

TABLE2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - CONTINUOUS AND BATCH RELEASES 2018 Nuclides Released Units Continuous Mode Batch Mode 3rd 4th 1st Quarter 2nd Quarter pt Quarter 2nd Quarter 3rd Quarter 4th Quarter Quarter Quarter Fission & Activation Products Chromium-51 Ci Manganese-54 Ci Iron-55 Ci Iron-59 Ci Cobalt-57 Ci Cobalt-58 Ci l.29E-02 Cobalt-60 Ci . 6.37E-04 Zinc-65 Ci Strontium-89 Ci Strontium-90 Ci Niobium-95 Ci Molybdenum-99 Ci Zirconium-95 Ci Silver- l lOm Ci Antimony-122 Ci Tellurium-123m Ci 2.08E-05 l.39E-04 Antimony-124 Ci Antimony-125 Ci Iodine-131 Ci Iodine-132 Ci Tellurium-132 Ci l.09E-04 Iodine-135 Ci Cesium-134 Ci Cesium-136 Ci Cesium-137 Ci R.E. Ginna Nuclear Power Plant 14 ARERR Docket No. 50-244 01/01/2018 - 12/31/2018

TABLE 2B (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - CONTINUOUS AND BATCH RELEASES 2018 Nuclides Released Units Continuous Mode Batch Mode 2nd 3rd 4th 1st Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Quarter Quarter Quarter Barium/Lanthanum-140 Ci Cerium-141 Ci Total (above) Ci 2.08E-05 l.38E-02 Unidentified (from total Ci above)

Tritium Hvdrogen-3 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.31E+02 6.81E+Ol l.69E+02 l.14E+02 Dissolved and Entrained Gases Xenon-133 Ci 5.13E-05 l.68E-03 Xenon-135 Ci Note: Isotopes for which no value is given were not identified in applicable releases.

R.E. Ginna Nuclear Power Plant 15 ARERR Docket No. 50-244 01/01/2018-12/31/2018

TABLE3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 2018 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, Filter Sludge, Evaporator Bottoms, m3 3.40E+OO 2.5E+Ol Etc. 2.5E+Ol Ci l.83E+Ol B - Dry Active Waste (DAW), Contaminated m3 2.79E+02 2.5E+Ol Equipment, Etc. Ci l.38E-01 2.5E+Ol C - Irradiated Components, Control Rods, Etc. m3 None NIA Ci m3 3.42E+Ol 2.5E+Ol D - Other: Sources, Filters Ci l.27E-02 2.5E+Ol Note: Estimated total error for solid waste shipped offsite not available.

R.E. Ginna Nuclear Power Plant 16 ARERR Docket No. 50-244 01/01/2018 - 12/31/2018

TABLE 3 (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 2018

2. Estimate of Ma.ior Nuclide Composition by Type of Waste Isotope Unit Class A Class B TypeC TypeD H-3  % 0.03 C-14  % 0.09 Cr-51  % 0.10 Mn-54  % 3.83 Fe-55  % 3.52 Co-58  % 10.37 Co-60  % 26.04 Ni-63  % 49.76 Sr-90  % 0.03 Zr-95  % 0.19 Nb-95  % 0.34 Ag-1 lOm  % 0.44 Sn-113  % 0.01 Sb-124  % 0.07 Sb-125  % 3.38 Cs-137  % 0.24 Pu-241  % 0.01 Total  % 98.45 Note: Blank cells indicate nuclide composition not at significant levels.

R.E. Ginna Nuclear Power Plant 17 ARERR Docket No. 50-244 01/01/2018 -12/31/2018

TABLE 3 (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 2018 Mode of Type of Container Solidification

  1. of Shipments Processing Destination Transportation A2ent 6 Sole Use Truck Metal Containers None Energy Solutions, BC 1 Sole Use Truck Metal Containers None Energy Solutions, Gallaher Rd 1 Sole Use Truck High Integrity Container None Energy Solutions (Treatment Facility)

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Mode of

  1. of Shipments Destination Transportation None NIA NIA R.E. Ginna Nuclear Power Plant 18 ARERR Docket No. 50-244 01/01/2018 -12/31/2018

TABLE4A Radiation Dose to Maximum Individual Receptor from Gaseous Effluents First Quarter 2018 (Units In milliRem)

All All Adult Teen Child Infant Gamma Air Beta Air THYRD THYRD THYRD THYRD J--, )

N! 2.43E-06' 8.84E-07 2.93E-04 *; 3.23E-04 4.46E-04 l.93E-07

Ni,rn *2.04E-06 7.40E-07 2.46E-04 2.70E-04 . 3.73E-04 l.61E-07 1NE'. 2.35E-06 8.53E~07
  • 2.83E-04 . 3.12E-04 4.30E-04 l.86E-07
r*-*-~---*,

1ENE' . 2.99E-06 l.OSE-06 3.60E-04 ' 3.96E-04 5.47E-04 2.36E-07 E 5.43E-06 l.97E-06 6.55E-04 7.20E-04 9.95E-04 4.30E-07 ESE 6.91E-06 2.SlE-06 8.34E-04 9.16E-04 l.27E-03 5.97E-04 SE 4.18E-06 l.52E-06 5.04E-04 5.54E-04 7.66E-04 3.31E-07 SSE l.72E-06 6.25E-07 2.0SE-04 2.28E-04 3.lSE-04 1.36E-07 s 3.0lE-06 l.09E-06 3.63E-04 3.99E-04 5.52E-04 2.38E-07 SSW 3.0lE-06 l.09E-06 3.63E-04 3.99E-04 5.52E-04 2.38E-07 SW 3.0lE-06 l.09E-06 3.63E-04 3.99E-04 5.52E-04 2.38E-07 WSW 3.21E-06 l.17E-06 3.88E-04 4.26E-04 5.89E-04 2.54E-07 w 2.0SE-06 7.43E-07 2.47E-04 2.71E-04 3.75E-04 l.62E-07 WNW l .73E-07 6.28E-08 2.08E-05 2.29E-05 3.17E~os l.37E-08 NW: 5.67E-07 2.06E-07 6.84E-05 7.SlE-05 l.04E-04 4.49E-08 JNN\Vi l.77E-06 6.43E-07 2.13E-04 2.35E-04 3.24E-04 l.40E-07 I MAX. 1. 6.91E-06 I 2.SlE-06 I 8.34E-04 I 9.16E-o4 I l.27E-03 I 5.97E-04 I Note: Shaded regions indicate areas over Lake Ontario.

R.E. Ginna Nuclear Power Plant 19 ARERR Docket No. 50-244 01/01/2018 -12/31/2018

TABLE 4A (Continued)

Radiation Dose to Maximum Individual Receptor from Gaseous Effluents Second Quarter 2018 (Units In milliRem)

All All Adult Teen Child Infant Gamma Air Beta Air THYRD THYRD THYRD THYRD N. 2.86E~06 l.03E-06 l.59E-04 l.74E-04 2.40E-04 t:OSE-04 t .

NNE 2.40E-06  : 8.64E-07 l.33E 04 0 . , l.46E-04 2.0lE-04 8.77E:os**

NE 2.76E-06 '

9.96E-07 l.54E-04 . -l.69E-04 2.31E-04 l.OlE-04 ENE. 3.51E-06 l.27E-06 l.95E:Q4 . 2.14E-04 2.94E-04. l.28E-04 E 6.39E-06 2.30E-06 3.56E-04 3.90E-04 5.35E-04 2.34E-04 ESE 8.13E-06 2.93E-06 4.53E-04 4.96E-04 6.8IE-04 2.97E-04 SE 4.92E-06 l.77E-06 2.74E-04 3.00E-04 4.12E-04 l.80E-04 SSE 2.02E-06 7.30E-07 l.13E-04 l.23E-04 l.69E-04 7.40E-05 s 3.54E-06 l.28E-06 l.97E-04 2.16E-04 2.97E-04 l.30E-04 SSW 3.54E-06 l.28E-06 l.97E-04 2.16E-04 2.97E-04 l.30E-04 SW 3.54E-06 l.28E-06 l.97E-04 2.16E-04 2.97E-04 l.30E-04 WSW 3.78E-06 l.36E-06 2.lOE-04 2.30E-04 3.17E-04 l.38E-04 w 2.41E-06 8.67E-07 l._34E-04 l.47E-04 2.0IE-04 8.SOE-05 WNW 2.03E-07 7.33E-08 l.13E-05 l.24E-05 l.70E-05 7.43E-06 NW 6.67E-07 2.40E-07 3.71E-05 4.06E-05

  • 5.58E-05
  • 2:44E~05 NNW 2.08E-06 7.SOE-07 l.16E-04 l.27E-04 l.74E-04 7.61E-05 I MAX. 8.13E-06 2.93E-06 I 4.53E-04 I 4.96E-04 I 6.8 IE-04 I 2.97E-04 I Note: Shaded regions indicate areas over Lake Ontario.

R.E. Ginna Nuclear Power Plant 20 ARERR Docket No. 50-244 01/01/2018 -12/31/2018

TABLE 4A (Continued)

Radiation Dose to Maximum Individual Receptor from Gaseous Effluents Third Quarter 2018 (Units In milliRem)

All All Adult Teen Child Infant Gamma Air Beta Air THYRD THYRD THYRD THYRD N * . 3.35E-06 1.37E-06 i17E-04  ; 2.38E-04 3.27:E-04 .. J.43Ec04 NNE 2.8IE-06 ' .*l.lSE-06 i.82E-04.

  • 2.00E-04 2.74-E-04' 1.20E~04

.NE 3.24E-06 L33E-06 2.lOE~04. * {2.30E-04 .3.i6E~04 l:38E-04 ENE . "

4.llE-06 ' . t68E-06_ ,. 2.67E-04 * , 2.92E~04 4.02E-04 1.75E-04 E 7.48E-06 3.07E-06 4.86E-04 5.32E-04 7.3IE-04 3.19E-04 ESE 9.52E-06 3.90E-06 6.18E-04 6.77E-04 9.30E-04 4.06E-04 SE 5.76E-06 2.36E-06 3.74E-04 4.09E-04 5.62E-04 2.46E-04 SSE 2.37E-06 9.71E-07 1.54E-04 l.68E-04 2.3IE-04 1.0lE-04 s 4.15E-06 l.70E-06 2.69E-04 2.95E-04 4.0SE-04 1.77E-04 SSW 4.15E-06 l.70E-06 2.69E-04 2.95E-04 4.0SE-04 1.77E-04 SW 4.lSE-06 1.70E-06 2.69E-04 2.95E-04 4.0SE-04 l.77E-04 WSW 4.43E-06 1.8IE-06 2.87E-04 3.lSE-04 4.32E-04 1.89E-04 w 2.82E-06 l.lSE-06 l.83E-04 2.00E-04 2.75E-04 1.20E-04 WNW 2.38E-07 9.75E-08 1.54E-05 1.69E-05 2.32E-05 1.0lE-05

,NW ' 7;81E-07" 3.20E~07 ., 5.07E-05 5.SSE-05. 7.62E-05 .3.33E-os NNW . '

2.44E~o6* 9.98Eso?: , . l.58E-.04 *  ; 1:.73:E-04 2 ..38E-04'.* i'.04E~04 I MAX. 9.52E-06 I 3.90E-06 I 6.18E-04 I 6.77E-04 I 9.30E-04 I 4.06E-04 I Note: Shaded regions indicate areas over Lake Ontario.

R.E. Ginna Nuclear Power Plant 21 ARERR Docket No. 50-244 01/01/2018 -12/31/2018

TABLE 4A (Continued)

Radiation Dose to Maximum Individual Receptor from Gaseous Effluents Fourth Quarter 2018 (Units In milliRem)

All All Adult Teen Child Infant Gamma Air Beta Air THYRD THYRD THYRD THYRD N l.88E-06 l l.29E-06 2.04E-04 2.24E-04. 3.08E-01 l.37E-04 NNE 1.58E-06 . l.08E~06 l.71E-04  ; l.88E-04 2.58E-Oi' l.15E-04 NE . l.82E-06 l.25E-06 l.97E-04 2.16E-04 2.97E-01 1.32E-04

.ENE 2.31E-06 1.59E-06 2.51E-04 * ; 2.75E-04 . 3.78E-01 l.68E-04 E 4.20E-06 2.88E-06 4.56E-04 5.00E-04 6.88E-01 . 3.06E-04 ESE 5.34E-06 3.67E-06 5.80E-04 6.36E-04 8.75E-01 3.89E-04 SE 3.23E-06 2.22E-06 3.51E-04 3.85E-04 5.29E-01 2.35E-04 SSE l.33E-06 9.14E-07 l.44E-04 l .58E-04 2.18E-01 9.68E-05 s 2.33E-06 1.60E-06 2.53E-04 2.77E-04 3.81E-01 l.70E-04 SSW 2.33E-06 l.60E-06 2.53E-04 2.77E-04 3.81E-01 l.70E-04 SW 2.33E-06 l.60E-06 2.53E-04 2.77E-04 3.81E-01 l.70E-04 WSW 2.48E-06 l.71E-06 2.70E-04 2.96E-04 4.07E-01 l.8 lE-04 w 1.58E-06 l.09E-06 1.72E-04 l.88E-04 2.59E-01 l.15E-04 WNW 1.34E-07 9.18E-08 1.45E-05 1.59E-05 2.19E-02 9.72E-06

.NW 4.38£-07 ' 3.0lE-07 4.76E-05  : 5.22E-05 7.I7E-02 3.19E-05

  • NNW 1.37E-06 9.40E-07 l.49E-04 , l.63E-04 ' 2.24£-01. 9.96E-05 I MAX. 5.34E-06 I 3.67E-06 I 5.80E-o4 I 6.36E-04 I 8.75E-01 I 3.89E-04 I Note: Shaded regions indicate areas over Lake Ontario.

R.E. Ginna Nuclear Power Plant 22 ARERR Docket No. 50-244 01/01/2018-12/31/2018

TABLE4B Radiation Dose to Maximum Individual Receptor From Liquid Effluents for 2018 (Units in milliRem)

Adult Teen Child Infant First Quarter T.Body 6.18E-04 4.70E-04 4.65E-04 l.33E-04 GI-LLI 6.18E-04 4.70E-04 4.65E-04 l.33E-04 Thyroid 6.18E-04 4.70E-04 4.65E-04 l.33E-04 Second Quarter T.Body 2.58E-04 1.96E-04 l.94E-04 5.56E-05 GI-LLI 2.58E-04 l.96E-04 l.94E-04 5.56E-05 Thyroid 2.58E-04 1.96E-04 1.94E-04 5.56E-05 Third Quarter T.Body 5.91E-04 4.49E-04 4.45E-04 l.27E-04 GI-LLI 5.97E-04 4.54E-04 4.47E-04 l.27E-04 Thyroid 5.92E-04 4.49E-04 4.45E-04 l.27E-04 Fourth Quarter T.Body 9.1 lE-03 7.07E-03 7.08E-03 l.84E-03 GI-LLI 2.03E-02 1.49E-02 9.20E-03 1.84E-03 Thyroid 8.88E-03 6.83E-03 6.86E-03 l.84E-03 R.E. Ginna Nuclear Power Plant 23 ARERR Docket No. 50-244 01/01/2018 - 12/31/2018

Table 5 Groundwater Monitoring Wells Sample Location Date Tritium (nCi/1) Ga~ma 1 (uCi/ml)

GWOl: Warehouse Access Road (Control) 3/23/2018 <426 < 8.93E-09 6/14/2018 < 415 < 9.02E-09 9/7/2018 <447 < 8.92E-09 12/21/2018 < 399 < l.30E-08 GW03: Screenhouse West, South W e!I2 1/12/2018 <454 2/16/2018 <455 3/23/2018 <438 < 9.12E-09 4/25/2018 <437 5/25/2018 < 416 6/15/2018 <413 < 8.75E-09 7/29/2018 < 421 8/21/2018 < 414 9/7/2018 <449 < 7.80E-09 10/18/2018 <438 11/28/2018 < 396 12/23/2018 <403 < 7.53E-09 GW04: Screenhouse West, North Well 3/23/2018 <445 < 8.35E-09 6/15/2018 < 416 < 7.65E-09 9/7/2018 <447 < 7.08E-09 12/23/2018 <401 < 6.87E-09 GW05: Screenhouse East, South (15.5') 3/23/2018 <445 < 9.0lE-09 6/17/2018 < 414 < 8.75E-09 9/7/2018 <453 < l.06E-08 12/23/2018 <403 < 7.22E-09 GW06: Screenhouse East, Middle (20.0') 3/23/2018 < 441 < 7.73E-09 6/15/2018 <413 < 9.86E-09 9/7/2018 <444 < 9.69E-09 12/23/2018 <402 < 7.74E-09 GW07: Screenhouse East, North (24.0') 3/23/2018 <440 < 6.78E-09 6/15/2018 < 416 < 8.60E-09 9/7/2018 <447 < 6.53E-09 12/23/2018 <402 < 6.14E-09 R.E. Ginna Nuclear Power Plant 24 ARERR Docket No. 50-244 01/01/2018 - 12/31/2018

Table 5 (Continued)

Groundwater Monitoring Wells Location Sample Date Tritium (pCi/1) Gamma (uCi/ml) 2 <457 GW08: All Volatiles Treatment Building 1/12/2018 2/16/2018 <461 3/23/2018 <444 < 7.81E-09 4/25/2018 < 431 5/25/2018 <418 6/19/2018 < 416 < 5.88E-09 7/29/2018 < 417 8/21/2018 < 415 9/7/2018 <445 < 7.48E-09 10/18/2018 <436 11/28/2018 < 401 12/23/2018 < 399 < 6.28E-09 GWlO: Technical Suooort Center, South 3/23/2018 <427 < 1.46E-08 6/15/2018 <413 < l.03E-08 9/7/2018 <446 < 8.61E-09 12/23/2018 <400 < 7.46E-09 GWI I: Southeast of Contaminated Service Building (CSB) 3/23/2018 <447 < 7.25E-09 6/15/2018 <412 < 6.95E-09 9/7/2018 <444 < 7.29E-08 12/23/2018 < 398 < 7.82E-09 GW12: West of Orchard Access Road 3/23/2018 <439 < 7.25E-09 6/14/2018 <415 < 8.21E-08 9/7/2018* EMPTY EMPTY 12/21/2018 < 396 < 9.41E-09 GW 13: North of Independent Spent, Fuel Storage Installation (ISFSI) 3/23/2018 <443 < 9.31E-09 6/14/2018 < 415 < 7.82E-09 9/7/2018 <446 < 1.07E-08 12/21/2018 < 397 < l.26E-08 GW14: South of Canister Preparation Building 3/23/2018 < 441 < 8.55E-09 6/14/2018 <420 < 9.1 lE-09 9/7/2018 <447 < 8.27E-09 12/21/2018 < 396 < 9.60E-09 R.E. Ginna Nuclear Power Plant 25 ARERR Docket No. 50-244 01/01/2018 - 12/31/2018

Table 5 (Continued)

Groundwater Monitoring Wells Location Sam leDate Tritium ( Ci/I) Gamma (uCi/ml)

GW15: West of Manor House 3/23/2018 <438 < 9.8 6E-09 6/14/2018 < 414 < 9.5 OE-09 9/7/2018 <447 < 8.7 2E-09 12/21/2018 < 399 < 9.9 4E-09 GW16: Southeast of Manor House 3/23/2018 <445 < 8.0 9E-09 6/14/2018 < 417 < 8.9 5E-09 9/7/2018 <444 < 1.24E-08 12/21/2018 < 397 < 7.1 OE-09 1 Gamma analysis is performed on a quarterly basis for groundwater monitoring well results.

2 Groundwater monitoring wells GW03 and GW08 are sampled monthly due to their location being important for early detection of any tritium within the environment.

  • Groundwater Monitoring Well GW12 did not return a sample on 9/7/2018 as there was no groundwater in the monitoring well.

R.E. Ginna Nuclear Power Plant 26 ARERR Docket No. 50-244 01/01/2018 - 12/31/2018

TABLE6 Offsite Dose Due to Carbon-14 in Gaseous and Liquid Effluents MAXIMUM DOSE VALUES DUE TO C-14 IN GASEOUS EFFLUENTS IN 2018 Orean AeeGroup mRem/yr NRC Reg. Guide 1.109, Annual Bone Dose Child l.94E-02 NRC Reg. Guide 1.109, Annual Total Body/Organ Dose Child 3.86E-03 MAXIMUM DOSE VALUES DUE TO C-14 IN LIQUID EFFLUENTS IN 2018 Orean A~e mRem/vr NRC Reg. Guide 1.109, Annual Bone Dose Child 2.08E-04 NRC Reg. Guide 1.109, Annual Total Body/Organ Dose Child 4.16E-05 R.E. Ginna Nuclear Power Plant 27 ARERR Docket No. 50-244 01/01/2018 -12/31/2018

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