Text

2019 Annual Radioactive Effluent Release Report and 2019 Annual Radiological Environmental Operating Report
	ML20136A439
Person / Time
Site:	Ginna
Issue date:	05/15/2020
From:	Swift P; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	Download: ML20136A439 (303)
	v • d • e

Paul M. Swift Site Vice President R.E. G1nna Nuclear Pov,er Plant 1503 Lake Rd.

Ontario. NY 14519 Exelon Generation@ 315* 791-5200 Office www.exeloncorp.com paul.sw1ft .;i,exeloncorp com May 15, 2020 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington , DC 20555-0001 R.E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 NRC Docket No. 50-244 Independent Spent Fuel Storage Installation (ISFSI)

NRC Docket No. 72-67

Subject:

2019 Annual Radioactive Effluent Release Report and 2019 Annual Radiological Environmental Operating Report Enclosed is the Annual Radioactive Effluent Release Report (ARERR) for 2019 for the R.E. Ginna Nuclear Power Plant and Independent Spent Fuel Storage Installation (ISFSI) . This report is being submitted in accordance with 10 CFR 50.36a(a)(2) and Technical Specifications (TS) Sections 5.5.1 .c and 5.6.3.

No (0) revisions to the Offsite Dose Calculation Manual (ODCM) and no (0) revisions to the Process Control Program (PCP) occurred during the 2019 reporting period . In the ARE RR , ODCM revisions are described in Section 10.0 and PCP revisions are described in Section 11 .0. Submitted as Appendices to the ARERR are (A) the Annual Report on the Meteorological Monitoring Program and, (8) a complete, legible copy of the entire ODCM, as required by TS 5.5.1.c (no annotations due to no changes during the reporting period).

Also enclosed is the Annual Radiological Environmental Operating Report (AREOR) for 2019, submitted in accordance with Technical Specification Section 5.6.2.

There are no regulatory commitments contained in this submittal. Should you have any other questions regarding this submittal , please contact George Wrobel at 585-315-0552.

Respectfully,

~ ~\ij._~

Paul M. Swift ps/jf

May 15, 2018 U.S. Nuclear Regulatory Commission Page 2 Attachments:

1) Annual Radioactive Effluent Release Report, January 1, 2019 - December 31, 2019 App. A, Annual Report on the Meteorological Monitoring Program at the Ginna Nuclear Power Plant [p.31 of PDF file]

App. B, Copy of the latest revision (36) of the ODCM in the reporting period (no annotations due to no changes) [p.77 of PDF file]

2) Annual Radiological Environmental Operating Report, January 1, 2019 - December 31, 2019 [p.197 of PDF file]

cc: NRC Regional Administrator, Region I (w/o)

NRC Project Manager, Ginna (w/o)

NRC Senior Resident Inspector, Ginna (w/o)

NYS Office of Emergency Management (electronic)

Division of Homeland Security and Emergency Services 1220 Washington Avenue Building 22, Suite 101 Albany, NY 12226-2251 Attn.: Gary Machina NYS Department of Public Service (electronic) 3 Empire State Plaza,10th Floor Albany, NY 12223 Attn.: Bridget Frymire American Nuclear Insurers (electronic) 95 Glastonbury Blvd.

Glastonbury, CT 06033 Attn.: Edward Everett NYS Division of Homeland Security and Emergency Services (electronic)

Attn: Radiological Preparedness Department 1220 Washington Avenue Building 7A Suite 710 Albany, NY 12242 Tim Kohlmeier, Office of Emergency Management (electronic)

Monroe County Office of Emergency Management 1190 Scottsville Rd., Suite 200 Rochester, NY 14624 George Bastedo, Director, Office of Disaster Preparedness (electronic)

Wayne County Emergency Management 7376 Rt. 31, Suite 2000 Lyons, NY 14489-9174

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT:

JANUARY 1, 2019 - DECEMBER 31, 2019 MAY 2020 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........................................................................6 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 Offsite Dose Due To 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 i ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

LIST OF TABLES Table 1A Gaseous Effluents - Summation of all Releases ..........................................................10 Table 1B 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 Individual Receptor from Gaseous Effluents ...............19 Table 4B Radiation Dose to Maximum Individual 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 Appendix B, R.E. Ginna Nuclear Power Plant Offsite Dose Calculation Manual, Revision 36 R.E. Ginna Nuclear Power Plant ii ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

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, 2019 through December 31, 2019, provides a summary of the quantities of radioactive gaseous effluents. 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 01/01/2019 - 12/31/2019

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 CFR 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 CFR 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 01/01/2019 - 12/31/2019

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 2019 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, Sr-89, and Sr-90 by a contract laboratory. Tritium and alpha analyses 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: 6.00 E+01

2. Total time for batch releases (Minutes): 5.74 E+03

3. Maximum time for a batch release (Minutes): 2.35 E+02

4. Average time for batch releases (Minutes): 9.57 E+01

5. Minimum time for a batch release: 4.00 E+01

6. Average effluent release flowrate into the discharge 3.60 E+02 canal (Liters per Minute):

7. Average dilution flowrate of discharge canal during 1.22 E+06 effluent releases (Liters per Minute):

2.5.2 Gaseous

1. Number of batch releases: 2.00 E+01

2. Total time for batch releases (Minutes): 5.39 E+05

3. Maximum time for a batch release (Minutes): 4.46 E+04

4. Average time for batch releases (Minutes): 2.70 E+04

5. Minimum time for a batch release (Minutes): 6.00 E+01 R.E. Ginna Nuclear Power Plant 3 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

2.6 Abnormal Releases In 2019, there were two abnormal releases of gaseous effluents.

1. On 7/2/2019, a seal leak was noted on the B waste gas compressor. This leaking gas compressor resulted in a lowering of A Gas Decay Tank pressure of nine PSIG over five hours. As this release traveled through a monitored pathway, a release permit was conservatively generated to capture the release (see Issue Report 04261457 and Release Permit G-2019028).

2. On 9/16/2019, a lowering of vent header pressure of 0.25 PSIG was noted and there were no water transfers in progress or operations that would affect vent header pressure. The D Gas Decay Tank (GDT) was in service and aligned to the vent header, pressure within the tank increased from 24 PSIG to 27 PSIG. As this potential release traveled through a monitored pathway, a release permit was conservatively generated to account for any issues associated with the B waste gas compressor (see Issue Report 04279840 and Release Permit G-2019035).

3.0

SUMMARY

OF GASEOUS RADIOACTIVE EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables 1A and 1B. 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 2019.

R.E. Ginna Nuclear Power Plant 4 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

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: 1.08E-03 mRem Sum of no detectable direct radiation dose, 1.07E-03 (Total Body Liquid Dose),

and 1.35E-05 (Total Body Gas Dose).

Maximum Annual Organ Dose: 4.91E-03 mRem (Child, Thyroid)

Maximum Annual Thyroid Dose: 4.91E-03 mRem (Child) 8.0 METEOROLOGICAL DATA The annual summary report of meteorological data collected during 2019 is included with this report, as Appendix A, Annual Report on the Meteorological Monitoring Program at the Ginna Nuclear Power Plant by Murray and Trettel, Incorporated.

R.E. Ginna Nuclear Power Plant 5 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

9.0 LAND USE CENSUS CHANGES In September 2019, Ginna 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 Ginnas 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 has 25 acres of active production of AGRI-GROW tomatoes year-round at East end of Dean Parkway. (North of Route 104).

Commercial fishing information was collected from the New York State Department of Environmental Conservation (NYSDEC) which shows activity only in the Eastern basin of Lake Ontario. Commercial fishing operations have not changed in the last five-years and no commercial fishing takes place within 5-miles of Ginna.

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 no changes to the Offsite Dose Calculation Manual (ODCM) in 2019. The most recent revision of the ODCM (Revision 36) was made effective on 12/27/2018 and is included within this report as Appendix B.

11.0 CHANGES TO THE PROCESS CONTROL PROGRAM There were no changes to the Process Control Program in 2019.

R.E. Ginna Nuclear Power Plant 6 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

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 2019 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-10B. R-10B exhibited an extended run time on the filter due to R-14A being out of service which caused R-10B to not be changed. The filter on R-10B collected sample from 12/29/2018 - 1/8/2019, exceeding the weekly periodicity mandated by the ODCM. 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 Ginnas Chemistry procedures, environmental groundwater monitoring wells are sampled on a routine frequency. In 2019, Ginna staff collected and analyzed samples collected from a total of 14 groundwater monitoring wells:

GW01: Warehouse Access Road (Control)

GW03: Screenhouse West, South Well GW04: Screenhouse West, North Well GW05: Screenhouse East, South GW06: Screenhouse East, Middle GW07: Screenhouse East, North GW08: All Volatiles Treatment Building GW10: Technical Support Center, South GW11: 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 GW15: 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 2019 are presented in Table 5.

R.E. Ginna Nuclear Power Plant 7 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

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 the 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 2019. 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 01/01/2019 - 12/31/2019

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 the atmosphere in 2019.

b. There was no refueling outage in 2019. 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 2019.

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 wastewater as measured in the Kunz study was adjusted for current operating conditions and was 6.0E-07 uCi/cc.

c. 9.12E+05 liters of liquid waste (with the potential to contain C-14) were released with a total dilution flow of 1.94E+12 liters.

d. Average diluted concentration of C-14 released was 2.83E-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 infant is the critical receptor for the potable water pathway.

See Table 6 for an estimate of Carbon-14 in liquid effluents during 2019.

R.E. Ginna Nuclear Power Plant 9 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 2019 Effluent Type Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Est. Total Error, A. Fission & Activation Gases

1. Total release Ci 4.60E-01 4.71E-01 3.12E-01 4.07E-01 1.50E+01

2. Average release rate for period uCi/sec 5.84E-02 5.97E-02 3.96E-02 5.16E-02

3. Percent of technical specification limit % 9.27E-06 9.48E-06 6.29E-06 8.19E-06 B. Iodines

1. Total iodine-131 Ci 1.52E-05 1.33E-06 1.31E-07 0.00E+00 1.50E+01

2. Average release rate for period uCi/sec 1.93E-06 1.69E-07 1.66E-08 0.00E+00

3. Percent of technical specification limit % 4.20E-03 3.67E-04 3.61E-05 0.00E+00 C. Particulates

1. Particulates with half-lives > 8days Ci 0.00E+00 6.18E-08 0.00E+00 0.00E+00 1.50E+01

2. Average release rate for period uCi/sec 0.00E+00 7.84E-09 0.00E+00 0.00E+00

3. Percent of technical specification limit % 0.00E+00 7.84E-14 0.00E+00 0.00E+00

4. Gross alpha radioactivity Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 D. Tritium

1. Total release Ci 2.03E+01 2.80E+01 3.15E+01 3.66E+01 9.20E+00

2. Average release rate for period uCi/sec 2.57E+00 3.55E+00 4.00E+00 4.65E+00

3. Percent of technical specification limit % 3.01E-06 4.15E-06 4.68E-06 5.44E-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 01/01/2019 - 12/31/2019

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - CONTINUOUS AND BATCH RELEASES 2019 Nuclides Released Units Continuous Mode Batch Mode 1st 2nd 3rd 4th 1st 2nd 3rd 4th Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter

1. Fission Gases Argon-41 Ci 6.53E-03 4.83E-02 5.11E-02 5.72E-02 1.01E-01 Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-131m Ci Xenon-133 Ci 2.35E-02 1.82E-01 1.54E-01 9.88E-02 1.03E-01 Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xenon-138 Ci Total for period Ci 0.00E+00 3.00E-02 0.00E+00 0.00E+00 2.30E-01 2.05E-01 1.57E-01 2.04E-01

2. Iodines Iodine-131 Ci 7.62E-06 6.67E-07 6.54E-08 Iodine-132 Ci Iodine-133 Ci 5.28E-07 4.77E-07 Iodine-135 Ci Total for period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.15E-06 1.14E-06 6.54E-08 0.00E+00 R.E. Ginna Nuclear Power Plant 11 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

TABLE 1B (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - CONTINUOUS AND BATCH RELEASES 2019 Nuclides Released Units Continuous Mode Batch Mode 1st 2nd 3rd 4th 1st 2nd 3rd 4th Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter

3. Particulates Strontium-89 Ci Strontium-90 Ci Cesium-137 Ci Cobalt-57 Ci 3.09E-08 Cobalt-58 Ci Cobalt-60 Ci Unidentified Ci Total for period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.09E-08 0.00E+00 0.00E+00

4. Tritium Hydrogen-3 Ci 1.01E+01 1.40E+01 1.57E+01 1.83E+01 3.90E-03 8.11E-03 4.64E-02 2.40E-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 01/01/2019 - 12/31/2019

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 2019 Effluent Type Units 1st 2nd 3rd 4th Est. Total Error, Quarter Quarter Quarter Quarter %

A. Fission & Activation Products

1. Total Release (not including tritium, gases, Ci 1.04E-03 8.57E-04 4.34E-04 7.87E-05 9.90E+00 alpha)

2. Average Diluted concentration uCi/ml 2.79E-12 1.54E-12 8.43E-13 1.60E-13

3. Percent of applicable limit % 2.79E-05 1.54E-05 8.43E-06 1.60E-06 B. Tritium

1. Total Release Ci 6.12E+01 4.34E+01 1.26E+02 4.08E+02 9.20E+00

2. Average Diluted Concentration uCi/ml 1.64E-07 7.79E-08 2.44E-07 8.31E-07

3. Percent of applicable limit % 1.64E-03 7.79E-04 2.44E-03 8.31E-03 C. Dissolved and Entrained Gases

1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2. Average Diluted Concentration uCi/ml 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Percent of applicable limit % 0.00E+00 0.00E+00 0.00E+00 0.00E+00 D. Gross Alpha Radioactivity

1. Total release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E. Vol. of Waste Released (prior to dilution) Liters 1.10E+08 1.17E+08 1.22E+08 1.16E+08 F. Vol. of Dilution Water Used During Period Liters 3.72E+11 5.57E+11 5.15E+11 4.91E+11 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 01/01/2019 - 12/31/2019

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - CONTINUOUS AND BATCH RELEASES 2019 Nuclides Released Units Continuous Mode Batch Mode 1st 2nd 3rd 4th 1st 2nd 3rd 4th Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter Fission & Activation Products Chromium-51 Ci Manganese-54 Ci Iron-55 Ci Iron-59 Ci Cobalt-57 Ci Cobalt-58 Ci 4.69E-04 1.44E-04 Cobalt-60 Ci 2.41E-04 Zinc-65 Ci Strontium-89 Ci Strontium-90 Ci Niobium-95 Ci Molybdenum-99 Ci Zirconium-95 Ci Silver-110m Ci Antimony-122 Ci Tellurium-123m Ci 5.69E-04 4.73E-04 4.34E-04 7.87E-05 Antimony-124 Ci Antimony-125 Ci Iodine-131 Ci Iodine-132 Ci Tellurium-132 Ci Iodine-135 Ci Cesium-134 Ci Cesium-136 Ci Cesium-137 Ci R.E. Ginna Nuclear Power Plant 14 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

TABLE 2B (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - CONTINUOUS AND BATCH RELEASES 2019 Nuclides Released Units Continuous Mode Batch Mode 1st 2nd 3rd 4th 1st 2nd 3rd 4th Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter Barium/Lanthanum-140 Ci Cerium-141 Ci Total (above) Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.04E-03 8.58E-04 4.34E-04 7.87E-05 Unidentified (from total Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 above)

Tritium Hydrogen-3 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.12E+01 4.34E+01 1.26E+02 4.08E+01 Dissolved and Entrained Gases Xenon-133 Ci 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 01/01/2019 - 12/31/2019

TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 2019 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 1.16E+01 2.5E+01 Etc. Ci 5.70E+01 2.5E+01 B - Dry Active Waste (DAW), Contaminated m3 1.45E+02 2.5E+01 Equipment, Etc. Ci 1.07E-02 2.5E+01 C - Irradiated Components, Control Rods, Etc. m3 None N/A Ci m3 None 2.5E+01 D - Other: Sources, Filters Ci None 2.5E+01 Note: Estimated total error for solid waste shipped offsite not available.

R.E. Ginna Nuclear Power Plant 16 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

TABLE 3 (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 2019

2. Estimate of Major Nuclide Composition by Type of Waste Isotope Unit Class A Class B Type C Type D H-3 % 0.04 0.02 Be-7 % 0.30 C-14 % 0.56 0.38 Mn-54 % 4.80 3.81 Fe-55 % 6.89 7.68 Co-57 % 0.17 0.25 Co-58 % 15.55 1.01 Co-60 % 18.42 23.59 Ni-59 % 0.65 0.92 Ni-63 % 40.44 56.72 Zn-65 % 0.11 0.06 Sr-90 % 0.09 0.09 Zr-95 % 0.04 0.01 Nb-95 % 0.08 0.02 Tc-99 % 0.01 0.03 Ag-110m % 0.34 0.45 Sn-113 % 0.26 0.04 Sb-124 % 1.17 0.03 Sb-125 % 4.74 2.90 Cs-134 % 0.35 Cs-137 % 5.21 1.63 Pu-241 % 0.13 0.01 Total % 100.00 100.00 Note: Isotopes for which no value is given were not identified in applicable releases.

R.E. Ginna Nuclear Power Plant 17 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

TABLE 3 (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 2019 Mode of Type of Container Solidification

of Shipments Processing Destination Transportation Agent 2 Sole Use Truck Metal Containers None Energy Solutions, Bear Creek 1 Sole Use Truck High Integrity Container None Energy Solutions, Bear Creek 1 Sole Use Truck High Integrity Container None Energy Solutions (Treatment Facility)

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Mode of

of Shipments Destination Transportation None N/A N/A R.E. Ginna Nuclear Power Plant 18 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

TABLE 4A Radiation Dose to Maximum Individual Receptor from Gaseous Effluents First Quarter 2019 (Units In milliRem)

All All Adult Teen Child Infant Gamma Air Beta Air THYRD THYRD THYRD THYRD N

NNE

NE

ENE

E

ESE

S

WSW

W

WNW

NW

NNW

MAX. 3.96E-06 2.69E-05 6.87E-04 8.51E-04 1.41E-03 2.12E-03 Note: Shaded regions indicate areas over Lake Ontario.

R.E. Ginna Nuclear Power Plant 19 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

TABLE 4A (Continued)

Radiation Dose to Maximum Individual Receptor from Gaseous Effluents Second Quarter 2019 (Units In milliRem)

All All Adult Teen Child Infant Gamma Air Beta Air THYRD THYRD THYRD THYRD N

NNE

NE

ENE

E

ESE

S

WSW

W

WNW

NW

NNW

MAX. 4.61E-06 2.90E-06 5.26E-04 5.85E-04 8.24E-04 4.92E-04 Note: Shaded regions indicate areas over Lake Ontario.

R.E. Ginna Nuclear Power Plant 20 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

TABLE 4A (Continued)

Radiation Dose to Maximum Individual Receptor from Gaseous Effluents Third Quarter 2019 (Units In milliRem)

All All Adult Teen Child Infant Gamma Air Beta Air THYRD THYRD THYRD THYRD N

NNE

NE

ENE

E

ESE

S

WSW

W

WNW

NW

NNW

MAX. 4.37E-06 2.25E-06 5.63E-04 6.18E-04 8.50E-04 3.84E-04 Note: Shaded regions indicate areas over Lake Ontario.

R.E. Ginna Nuclear Power Plant 21 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

TABLE 4A (Continued)

Radiation Dose to Maximum Individual Receptor from Gaseous Effluents Fourth Quarter 2019 (Units In milliRem)

All All Adult Teen Child Infant Gamma Air Beta Air THYRD THYRD THYRD THYRD N

NNE

NE

ENE

E

ESE

S

WSW

W

WNW

NW

NNW

MAX. 7.50E-06 3.38E-06 6.51E-04 7.13E-04 9.79E-04 4.27E-04 Note: Shaded regions indicate areas over Lake Ontario.

R.E. Ginna Nuclear Power Plant 22 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

TABLE 4B Radiation Dose to Maximum Individual Receptor From Liquid Effluents for 2019 (Units in milliRem)

Adult Teen Child Infant First Quarter T. Body 3.13E-04 2.41E-04 2.42E-04 6.53E-05 GI-LLI 5.48E-04 4.26E-04 3.09E-04 6.53E-05 Thyroid 3.21E-04 2.48E-04 2.51E-04 6.53E-05 Second Quarter T. Body 1.58E-04 1.22E-04 1.23E-04 3.26E-05 GI-LLI 3.02E-04 2.35E-04 1.63E-04 3.26E-05 Thyroid 1.62E-04 1.25E-04 1.27E-04 3.26E-05 Third Quarter T. Body 4.43E-04 3.38E-04 3.36E-04 9.43E-05 GI-LLI 5.60E-04 4.32E-04 3.71E-04 9.44E-05 Thyroid 4.48E-04 3.43E-04 3.42E-04 9.46E-05 Fourth Quarter T. Body 1.54E-04 1.17E-04 1.16E-04 3.29E-05 GI-LLI 1.75E-04 1.34E-04 1.23E-04 3.29E-05 Thyroid 1.55E-04 1.18E-04 1.17E-04 3.29E-05 R.E. Ginna Nuclear Power Plant 23 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

Table 5 Groundwater Monitoring Wells Location Sample Date Tritium (pCi/l) Gamma1 (uCi/ml)

GW01: Warehouse Access Road (Control) 3/13/2019 < 460 < 6.95E-09 6/26/2019 < 426 < 5.92E-09 9/4/2019 < 431 < 6.97E-09 12/13/2019 < 451 < 1.12E-08 GW03: Screenhouse West, South Well2 1/27/2019 < 444 2/22/2019 < 453 3/14/2019 < 450 < 8.80E-09 4/12/2019 < 404 5/24/2019 446 5/29/2019 579 6/27/2019 < 426 < 7.06E-09 7/25/2019 < 413 8/16/2019 < 428 9/4/2019 < 439 < 1.02E-08 10/25/2019 < 488 11/19/2019 < 459 12/13/219 < 469 < 7.98E-09 GW04: Screenhouse West, North Well 3/14/2019 < 454 < 8.09E-09 6/27/2019 < 428 < 6.86E-09 9/4/2019 < 439 < 6.78E-09 12/13/2019 < 482 < 6.33E-09 GW05: Screenhouse East, South (15.5) 3/14/2019 < 452 < 6.10E-09 6/26/2019 < 427 < 8.44E-09 9/4/2019 < 457 < 9.30E-09 12/13/2019 < 484 < 8.43E-09 GW06: Screenhouse East, Middle (20.0) 3/14/2019 < 451 < 6.52E-09 6/26/2019 < 425 < 6.52E-09 9/4/2019 < 434 < 7.23E-09 12/13/2019 < 483 < 8.59E-09 GW07: Screenhouse East, North (24.0) 3/14/2019 < 454 < 7.31E-09 6/26/2019 < 423 < 6.61E-09 9/4/2019 < 448 < 7.17E-09 12/13/2019 < 486 < 7.17E-09 R.E. Ginna Nuclear Power Plant 24 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

Table 5 (Continued)

Groundwater Monitoring Wells Location Sample Date Tritium (pCi/l) Gamma (uCi/ml)

GW08: All Volatiles Treatment Building 2 1/27/2019 < 443 2/22/2019 < 449 3/14/2019 < 454 < 9.62E-09 4/12/2019 < 409 5/24/2019 542 5/29/2019 521 6/27/2019 < 424 < 8.21E-09 7/25/2019 < 430 8/16/2019 < 429 9/4/2019 < 425 < 1.14E-08 10/25/2019 < 486 11/19/2019 < 462 12/13/219 < 483 < 1.12E-08 GW10: Technical Support Center, South 3/14/2019 < 457 < 6.85E-09 6/26/2019 < 426 < 8.46E-09 9/4/2019 < 424 < 1.88E-09 12/13/2019 603 < 9.61E-09 GW11: Southeast of Contaminated Service 3/14/2019 < 449 < 9.89E-09 Building (CSB) 6/26/2019 < 427 < 6.19E-09 9/4/2019 < 448 < 8.20E-09 12/13/2019 < 479 < 8.13E-09 GW12: West of Orchard Access Road 3/13/2019 < 453 < 6.85E-09 6/26/2019 < 418 < 9.77E-09 9/4/2019 < 422 < 7.33E-09 12/13/2019 < 487 < 9.35E-09 GW13: North of Independent Spent Fuel Storage 3/14/2019 < 458 < 7.38E-09 Installation (ISFSI) 6/26/2019 < 427 < 6.21E-09 9/4/2019 < 426 < 7.98E-09 12/13/2019 < 488 < 7.92E-09 GW14: South of Canister Preparation Building 3/14/2019 < 454 < 1.05E-08 6/26/2019 < 422 < 6.30E-09 9/4/2019 < 430 < 9.36E-09 12/13/2019 < 480 < 7.50E-09 R.E. Ginna Nuclear Power Plant 25 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

Table 5 (Continued)

Groundwater Monitoring Wells Location Sample Date Tritium (pCi/l) Gamma (uCi/ml)

GW15: West of Manor House 3/13/2019 < 454 < 6.71E-09 6/26/2019 < 425 < 7.68E-09 9/4/2019 < 419 < 7.42E-09 12/13/2019 < 485 < 9.98E-09 GW16: Southeast of Manor House 3/13/2019 < 456 < 8.12E-09 6/26/2019 < 427 < 7.95E-09 9/4/2019 < 422 < 8.35E-09 12/13/2019 < 487 < 9.01E-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.

R.E. Ginna Nuclear Power Plant 26 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

TABLE 6 Offsite Dose Due to Carbon-14 in Gaseous and Liquid Effluents MAXIMUM DOSE VALUES DUE TO C-14 IN GASEOUS EFFLUENTS IN 2019 Organ Age Group mRem/yr NRC Reg. Guide 1.109, Annual Bone Dose Child 1.94E-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 2019 Organ Age mRem/yr NRC Reg. Guide 1.109, Annual Bone Dose Child 1.08E-04 NRC Reg. Guide 1.109, Annual Total Body/Organ Dose Child 2.16E-05 R.E. Ginna Nuclear Power Plant 27 ARERR Docket No. 50-244 01/01/2019 - 12/31/2019

Annual Report On the Meteorological Monitoring Program At the Ginna Nuclear Power Plant 2019 prepared for Exelon Nuclear Warrenville, IL 60555 by Murray and Trettel, Incorporated 600 First Bank Drive, Suite A Palatine, IL 60067 (84 7) 963-9000 e-mail: mt@weathercommand.com web : http://www.weathercommand .com Murray & Trettel, Inc. 600 First Bank Drive, Suite A Palatine, Illinois 60067 (847) 963-9000

Table of Contents Section Description List of Tables .. ... ...... .... .... .......... ......... ..................... .... ............................ ii 1 Introduction ............................................................................................ 1 2 Summary ................................................................................................ 2 3 Data Acquisition .... ...... ...... .... .................... ............... .......... ...... .. ... .. .... .... 3 4 Data Analysis .. ...... .................................................................................. 4 5 Results .................. .................................................................................. 7 Murl'ay & Trettel In c. 600 First Bank Drive. Suite A Palatine, Illinois 60067 (847) 963-9000

ii List of Tables Number Description Page 1 Instrument Locations ............................................................................. 3 2 Data Loggers . .. . . .. ... .. ... . ... .... .. .. ... .. .. .. .. ... .... ... ... .. .. .. . . ... ... .. .... .... .... .... ... .. 3 3 Wind Direction Classes .. ... .. .... .. .. ... .. ... .. . .... .... . . .. ... .. ... . ... ... .. .. ... .. . .. .. ... .. 5 4 Wind Speed Classes . ..... .... ... .. ... ...... .... ... ... . ... ... ..... .. . ... .. . .. ... .. .. . ... ...... .. 5 5 Atmospheric Stability Classes ................ ..... .. ... ..... .. .... ... ...... ....... ......... 6 6 0 /Q Plant Vent Release ............ .................... .. ...................................... 8 7 X/Q Plant Vent Release ........................................................................ 9 8 0/Q Containment Vent Release .......................................................... 10 9 X/Q Containment Vent Release ................. .... ................................... .. 11 10 0/Q Air Ejector Release .............................. .... .. .. ................................ 12 11 X/Q Air Ejector Release ........................... .... ....................................... 13 12 Special X/Q and 0/Q Release ......... ................ ........................... 14 13 Data Recovery Summary ... ..................... ........... ... .. ... .............. .... .. ... .. 16 14 Precipitation Totals .............................................................................. 18 15 Annual Joint Frequency Tables ........................................................... 20 Murray & Trett:el, lnc. 600 First Bank Drive, Suite A Palatine, Illinois 60067 (847) 963-9000

1

1. Introduction The purpose of the meteorological program being conducted at the Gi nna Plant site is to provide information sufficient to assess the local weather conditions and to determine the degree of atmospheric dispersion of airborne radioactive effluent from the station.

The meteorological tower is 300 ft. high and is instrumented at three levels. Wind speed and direction, and ambient temperature are measured at 33 ft. , 150 ft., and 250 ft.

Differential temperatures , referenced to 33 ft., are measured at 150 ft. and 250 ft.

Precipitation is measured at ground level.

Joint frequency stability wind rose tables of wind direction , w ind speed , and stability are routinely tabulated from hourly measurements. The annual tables are included in this report .

Descriptions of the instruments and data computers are given in Section 3 (Data Acquisition) of this report . Data reduction and processing are described in Section 4 (Data Ana lysis) . The results given in Section 5 of this report include X/Q and 0/Q data results and site meteorology.

Mw*1*ay & Trettel, Inc. 600 First Bank Driue, Suite A Palatine, Illinois 60067 (847) 963-9000

2

2. Summary The Ginna Plant meteorological monitoring program produced 96 , 197 hours0.00228 days 0.0547 hours 3.257275e-4 weeks 7.49585e-5 months of valid data out of a possible 96,360 priority parameter hours during 2019 , which represents an overall data recovery rate of 99.8% . Priority parameters are all parameters except precipitation.

The stability wind rose tables included in this report have been generated using the 33 ft .

wind data with the 150-33 ft. differential temperature data, the 150 ft. wind data with the 150-33 ft differential temperature data and the 250 ft. wind data with the 250-33 ft.

differential temperature data.

Murray & Trettel, Inc. 600 First Bank Drive, Suite A Palatine, fllin ois 60067 (847) 963-9000

3

3. Data Acquisition Wind speed and direction are measured with Climatronics F460 wind sensors. The wind speed sensors have a starting speed of 0.5 mph (0.22 mps) , a range of Oto 100 mph (0 to 44.7 mps), and a system accuracy of +/-1.0 mph at 100 mph (_0.45 mps at 44.7 mps) . The wind direction sensors have a threshold speed of 0.5 mph (0.22 mps), a range of Oto 540°, and a system accuracy of +/-5°.

Ambient and differential temperature are measured with the Climatronics 100093 system. Ambient temperature is measured within the range of -20 to 120°F (-28.9 to 48.9°C} with an accuracy of +/-0.5°F

(+/-0.3°C). Differential temperature is measured within the range of-10 to 20°F (-5.6 to 11 .1°C) with an accuracy of +/-0.18°F (+/-0.10°C) . Precipitation ls measured with a Cllmatronics tipping bucket rain gauge and is measured in increments of one one-hundredth of an inch with a system accuracy of +/-0.01 "

(+/-0.25mm}.

The meteorological data are co llected and stored by Campbell Scientific CR3000 and CR850 data loggers. The data loggers measure the analog voltages of the Instruments and record the digital equivalent within the range of Oto +5 volts. Data are obtained from the Campbell Scientific CR850 by a direct dial telephone hookup to an in-house computer system .

Table 1 Instrument Locations Measurement Sensor Type Location Elevation Wind Speed Climatronics 100075 F460 Tower 250 ft.

Wind Direction Climatronics 100076 F460 Tower 250 ft.

Differential Temperature Climatronics 100093 Tower 250 ft .

Wind Speed Climatronics 100075 F460 Tower 150 ft .

Wind Direction Climatronics 100076 F460 Tower 150 ft .

Differential Temperature Climatronics 100093 Tower 150 ft.

Wind Speed Climatronics 100075 F460 Tower 33 ft .

Wind Direction Climatronics 100076 F460 Tower 33 ft .

Ambient Temperature Climatronics 100093 Tower 33 ft .

Precipitation Climatronics 100097-1 Meteorological Ground Tipping Bucket Rain Gage shelter roof Table 2 Data Loggers Sampling Measurement Logger Type Frequency Winds, Temperatures, Campbell Scientific CR3000 (A & 8) and CRBSO 1 sec.

and Precipitation Winds, Temperatures, Johnson Yokogawa Corp. Digital Recorder 10 sec.

and Precipitation Murray & Trettel, Inc. 600 First Bank D,.iue, uile A Palatine, Illinois 60067 (847) 963-9000

4

4. Data Analysis The meteorological data are collected via modem connection to a Campbell Scientific CR850 data logger. Data are sampled once per second. The data are then stored in the meteorological data base and hourly listings of the data are generated . The data listings are examined by qualified personnel and any apparent problems are brought to the attention of the Project Manager or Environmental Meteorologist and the Instrument Maintenance staff.

Hourly values of wind speed , wind direction , ambient temperature, differential temperature , and precipitation are obtained through measurements taken at the site.

The standard deviation of wind direction {sigma) is derived . The wind direction variation is described in terms of the standard deviation of the direction about the mean direction.

The MIDAS computer derives an hourly value of wind sigma.

The data base files are edited approximately once a week . Missing values are replaced with back up data values, when available. Invalid data are deleted from the data base.

When an hourly value is missing or invalid , the numeral 999 is entered into the computer data file in the appropriate location.

A professional meteorologist reviews the data, calibration findings , equipment maintenance reports, and other information and determines which data are valid. Only the valid data are retained in the data base.

Joint frequency stability wind rose tables of hourly data measured at the site are generated. These tables indicate the prevailing wind direction , wind speed , and stability classes measured during the period of observation as well as the joint frequencies of occurrence of the wind direction, wind speed , and stability classes . The values are also used as input to the atmospheric transport and diffusion models. Wind direction, wind speed, and stability classes are given in Tables 3, 4, and 5.

M u,.ray & Tl'ettel, Inc. 600 First Bank Drive, 'uite A Pa latine, Illinois 60067 (847) 963-9000

5 Table 3 Wind Direction Classes IF 348.75° < WO -< 11.25° THEN Class is N IF 11.25° < WO -< 33.75° THEN Class is NNE IF 33.75° < WO -< 56.25° THEN Class is NE IF 56.25° < WO -< 78.75° THEN Class is ENE IF 78.75° < WO -< 101.25° THEN Class is E IF 101.25° < WO -< 123.75° THEN Class is ESE IF 123.75° < WO -< 146.25° THEN Class is SE IF 146.25° < WO -< 168.75° THEN Class is SSE IF 168.75° < WO -<< 191.25° THEN Class is s IF 191 .25° < WO - 213.75° THEN Class is SSW IF 213.75° < WO -< 236.25° THEN Class is SW IF 236.25° < WO -< 258.75° THEN Class is WSW IF 258.75° < WO -< 281.25° THEN Class is w IF 281 .25° < WO -< 303.75° THEN Class is WNW IF 303.75° < WO -< 326.25° THEN Class is NW IF 326.25° < WO - < 348.75° THEN Class is NNW Table 4 Wind Speed Classes IF ws -< 0.50 mis THEN Class is 1 IF 0.50 mis < ws -<< 1.0 mis THEN Class is 2 IF 1.1 m/s < ws - 1.5 mis THEN Class is 3 IF 1.6 m/s < ws -< 2.0 mis THEN Class is 4 IF 2.1 mis < ws -<< 3.0 mis THEN Class is 5 IF 3.1 mis < ws - 4.0 mis THEN Class is 6 IF 4.1 mis < ws -<< 5.0 mis THEN Class is 7 IF 5.1 mis < ws -< 6.0 mis THEN Class is 8 IF 6.1 mis < ws -< 8.0 mis THEN Class is 9 IF 8.1 mis < ws - 10.0 mis THEN Class is 10 IF 10.0 mis < ws THEN Class is 11 Mu rray & Trettel, Inc. 600 First Bank Drive, Suite A Palatine, Illinois 60067 (847) 963-9000

6 Table 5 Atmospheric Stability Classes Differential Temperature Differential Temperature Differential Temperature Interval Interval (in °F over the Interval (in °F over the Class (in °C/100m) (1 ) 150-33ft. range) 12) 250-33ft. range) t21 Extremely Unstable tH ~ -1.9 AT~ -1.2 ti.T < -2.3 Moderately Unstable -1.9 < 6.T ~-1 .7 -1.2 < ti. T ~ -1 .1 -2.3 < ti.T -< -2 .1 Slightly Unstable -1 .7 < ti.T ~ -1 .5 -1 .1 < ti. T ~ -1 .0 -2.1 < ti.T -< -1 .8 Neutral -1 .5 < ti.T ~-0.5 -1 .0< 6.T ~ -0.3 -1.8 < 6.T -< -0.6 Slightly Stable -0.5 < ti.T ~ 1.5 -0.3 < t.T ~ 1.0 -0.6 < t.T

-< 1.8

~ ~ 4.8 Moderately Stable 1.5 < t.T 4.0 1.0< ti.T 2.6 1.8 < t.T Extremely Stable 4.0 < AT 2.6 < AT 4.8 < AT 111 from ANSI/ANS 2.5 12 1 ANSI/ANS 2.5 intervals scaled for instrument heights on the Ginna meteorological tower Murray & Trettel, Inc. 600 First Bank Drive, Suite A Palatine, Illinois 60067 (847) 963-9000

7

5. Results 5.1 X/Q and 0/Q The ground and mixed mode values for X/Q and D/Q can be found in tables 4-9.

The following program was used to calculate X/Q and 0 /Q values:

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

The program is based on the theory that material released to the atmosphere will be normally distributed (Gaussian) about the plume centerline. A straight-line trajectory is assumed between the point of release and all receptors .

The program implements the assumptions outlined in Section C of NRC Regulatory Guide 1.111 . In evaluating routine releases from nuclear power plants, it primarily is designed to calculate annual relative effluent concentrations, X/Q values and annual average relative deposition , DlQ values .

Murray & Trett el, Inc. 600 First Bank Driue, Suite A Palatine, J/linois 60067 (847) 963-9000

Table 6 D/Q PLANT VENT 2019 Page 8 DIRECTION 804m l1609m 12416m l3218m l4022m l4827m IS632m l6436m 17240m IB04Sm D/Q N 3.llE-09 1.52E-09 9.03E-10 5.90E-10 4.17E-10 3.12E-10 2.43E-10 1.95E-10 1.60E-10 1.34E-10 NNE 1.58E-09 7.39E-10 4.32E-10 2.83E-10 2.0lE-10 1.SlE-10 1.18E-10 9.47E-11 7.79E-11 6.52E-11 NE 2.57E-09 1.21E-09 7.llE-10 4.63E-10 3.27E-10 2.44E-10 1.90E-10 l.53E-10 1.26E-10 1.0SE-10 ENE 4.12 E-09 2.13E-09 1.27E-09 8.29E-10 5.84E-10 4.36E-10 3.39E-10 2.72E-10 2.23E-10 1.87E-10 E 4.02E-09 2.17E-09 1.31E-09 8.56E-10 6.04E-10 4.SlE-10 3.53E -10 2.83E-10 2.35E-10 l.94E-10 ESE 8.32E-09 4.0lE-09 1.88E-09 1.20E-09 8.54E-10 6.32E-10 4.84E-10 4.02E-10 3.39E-10 2.95E-10 SE 7.60E-09 2.62E-09 1.34E-09 8.35E-10 S.72E-10 4.22E-10 3.68E-10 2.97E-10 2.82E-10 2.SOE-10 SSE 2.66E-09 9.25E-10 5.36E-10 3.52E-10 2.49E-10 1.84E-10 1.63E-10 1.88E-10 1.39E-10 1.20E-10 s l.58E-09 6.lSE-10 3.26E-10 2.13E-10 1.53E-10 1.30E-10 1.17E-10 1.08E-10 9.49E-11 7.87E-11 SSW 1.64E-09 6.94E-10 4.llE-10 2.64E-10 1.87E-10 1.39E-10 1.16E-10 1.lSE-10 1.04E-10 9.31E-11 SW 3.80E-09 1.48E-09 7.82E-10 5.lSE-10 3.SSE-10 2.83E-10 2.30E-10 1.85E-10 1.60E-10 1.49E-10 WSW 5.46E-09 1.99E-09 1.04E-09 6.65E-10 4.60E-10 3.43E-10 2.67E-10 2.16E-10 1.87E-10 1.61E-10 w 3.44E-09 1.43E-09 7.73E-10 5.0SE-10 3.58E-10 2.69E-10 2.llE-10 l.70E-10 1.40E-10 1.17E-10 WNW 5.30E-10 3.S3E-10 2.30E-10 l.57E-10 1.lSE-10 8.74E-11 6.90E-11 S.58E-11 4.60E-11 3.85E-11 NW 1.02E-09 6.03E-10 3.79E-10 2.56E-10 1.85E-10 1.40E-10 1.lOE-10 8.88E-11 7.32E-11 6.14E-11 NNW 3.00E-09 1.49E-09 8.87E-10 5.79E-10 4.08E-10 3.0SE-10 2.38E-10 1.91E-10 1.57E-10 1.31E-10

Table 7 X/Q PLANT VENT 2019 Page 9 DIRECTION 804m l1609m 12416m l3218m l4022m l4827m IS632m l6436m Tn4om ls04Sm X/Q N 1.2SE-07 1.18E-07 9.99E-08 8.13E-08 6.69E-08 5.61E-08 4.79E-08 4.16E-08 3.66E-08 3.25E-08 NNE 7.67E-08 7.67E-08 7.0lE-08 6.00E-08 S.11E-08 4.39E-08 3.82E-08 3.37E-08 3.00E-08 2.69E-08 NE 9.67E-08 1.03E-07 9.46E -08 8.llE-08 6.92E-08 5.97E-08 5.20E-08 4.59E-08 4.lOE-08 3.69E-08 ENE 1.49E-07 l.34E-07 l.lOE-07 8.91E-08 7.34E-08 6.18E-08 S.30E-08 4.62E-08 4.08E-08 3.65E-08 E 1.47E-07 l .29E-07 1.03E-07 8.26E-08 6.76E-08 S.67E-08 S.12E -08 4.4SE-08 4.13E-08 3.SOE-08 ESE 1.83E-07 2.0lE-07 1.0SE-07 8.69E-08 8.48E-08 7.33E-08 S.54E-08 5.38E-08 4.82E-08 4.3 1E-08 SE 1.32E-07 8.83E-08 7.74E-08 6.38E-08 5.43E-08 5.23E-08 4.63E-08 4.lSE -08 3.92E-08 3.SSE-08 SSE 9.89E-08 7.23E-08 6.61E-08 6.53E-08 5.69E-08 4.85E-08 4.35E-08 4.42E-08 3.49E-08 3.llE-08 s 4.75E-08 5.70E-08 3.98E-08 4.00E-08 3.49E-08 3.47E-08 3.lOE-08 2.78E-08 2.42E-08 2.09E-08 SSW 4.79E-08 4.49E-08 S.41E-08 5.0SE-08 4.18E-08 3.64E-08 3.30E-08 3.23E-08 3.00E-08 2.7SE-08 SW 6.94E-08 6.69E-08 5.98E-08 5.87E-08 4.67E-08 4.40E-08 4.09E-08 3.SlE-08 3.lOE-08 2.91E-08 WSW 1.04E-07 8.0BE-08 6.26E-08 6.33E-08 4.80E-08 4 .24E-08 3.54E-08 3.llE-08 2.BSE-08 2.52E-08 w 1.02E-07 l.OSE-07 7 .95E-08 6.87E -08 S.91E-08 S.13E-08 4.SlE-08 4.00E-08 3.59E-08 3.25E-08 WNW 1.95E-08 3.91E-08 4.12E-08 3.73E-08 3.28E-08 2.88E-08 2.SSE-08 2.27E-08 2.0SE-08 1.86E-08 NW 3.27E-08 5.12E-08 4.84E-08 4.lSE-08 3.53E-08 3.03E-08 2.63E-08 2.32E -08 2.06E-08 1.BSE-08 NNW 1.07E-07 9.63E-08 7.81E-08 6 .24E-08 S.OBE-08 4.24E-08 3.GlE-08 3.13E-08 2.75E-08 2.45E-08

Table 8 D/Q CONTAINMENT VENT 2019 Page 10 DIRECTION 804m I1609m 12416m l3218m l4022m l4827m IS632m l6436m Tn4om lso4Sm D/Q N l.53E-08 4.87E-09 2.44E-09 l.49E-09 l.OlE-09 7.30E-10 5.56E-10 4.39E-10 3.56E-10 2.96E-10 NNE l.04E-08 3.33E-09 l.67E-09 1.02E-09 6.89E-10 5.00E-10 3.81E-10 3.0lE-10 2.44E-10 2.03E-10 NE l.52E-08 4.82E-09 2.41E-09 1.47E-09 9.92E-10 7.20E-10 S.49E-10 4.34E-10 3.52E-10 2.92E-10 ENE l.82E-08 5.76E-09 2.88E-09 1.75E-09 1.18E-09 8.58E-10 6.53E-10 5.16E-10 4.19E-10 3.47E-10 E l.69E-08 5.36E-09 2.68E-09 l.63E-09 l.lOE-09 8.0lE-10 6.lSE-10 4.88E-10 4.00E-10 3.32E-10 ESE l.96E-08 6.28E-09 3.13E-09 l.90E-09 l.29E-09 9.34E-10 7.13E-10 5.64E-10 4.69E-10 4.07E-10 SE l.21E-08 3.80E-09 1.90E-09 l.lSE-09 7.81E-10 6.06E-10 4.86E-10 3.85E-10 3.12E-10 2.58E-10 SSE 5.lOE-09 l.61E-09 8.00E-10 4.92E-10 4.llE-10 3.04E-10 2.31E-10 l.83E-10 l.48E-10 l.22E-10 s 3.02E-09 9.54E-10 4.76E-10 2.95E-10 2.SSE-10 l.90E-10 l.44E-10 l.14E-10 9.20E-11 7.61E-11 SSW 3.39E-09 1.20E-09 5.99E-1D 3.98E-1D 2.93E-10 2.30E-10 l.75E-10 l.38E-10 1.12E-10 9.24E-11 SW 6.48E-09 2.26E-09 1.13E-09 6.83E-10 4.63E-10 3.94E-10 3.09E-10 2.44E-10 1.97E-10 l.63E-10 WSW 9.91E-09 3.16E-09 l.58E-09 9.57E-10 6.49E-10 4.72E-10 3.61E-10 2.87E-10 2.36E-10 l.98E-10 w l.07E-08 3.44E-09 l.69E-09 l.03E-09 6.99E-10 5.08E-10 3.88E-10 3.07E-10 2.SOE-10 2.08E-10 WNW 4.04E-09 l.34E-09 6.81E-10 4.17E-10 2.84E-10 2.07E-10 1.58E-10 l.26E-10 l.03E-10 8.60E-11 NW 5.SOE-09 1.81E-09 9.21E-10 5.63E-10 3.83E-10 2.79E-10 2.13E-10 l.69E-10 1.38E-10 l.lSE-10 NNW 1.20E-08 3.82E-09 1.91E-09 1.16E-09 7.87E-10 5.71E-10 4.35E-10 3.43E-10 2.79E-10 2.31E-10

Table 9 X/Q CONTAINMENT VENT 2019 Page 11 DIRECTION 804m l1609m 12416m l3218m l4022m l4827m IS632m l6436m 17240m l804Sm X/Q N 1.28E-06 4.72E-07 2.68E -07 1.80E-07 1.33E-07 1.04E-07 8.41E-08 7.03E-08 6.00E-08 S.21E-08 NNE 1.03E-06 3.96E-07 2.30E-07 l.56E-07 1.16E-07 9.lOE-08 7.42E-08 6.21E-08 5.32E-08 4.63E-08 NE 1.54E-06 5.73E-07 3.31E-07 2.25E-07 1.67E-07 1.31E-07 1.07E-07 8.93E-08 7.64E-08 6.65E-08 ENE 1.53E-06 5.59E-07 3.22E-07 2.18E-07 1.62E-07 1.27E-07 1.03E-07 8.68E-08 7.44E-08 6.48E-08 E 1.34E-06 4.93E-07 2.85E-07 1.94E-07 1.45E-07 1.14E-07 9.51E -08 8.00E-08 7.04E-08 5.99E-08 ESE 9.76E-07 4.23E-07 2.19E-07 1.53E-07 1.24E-07 9.93E-08 7.67E-08 6.78E-08 5.85E-08 5.09E-08 SE 5.38E-07 2.33E-07 l.57E-07 1.lSE-07 8.98E-08 7.7SE-08 6.43E-08 5.45E-08 4.73E-08 4.09E-08 SSE 4.85E-07 2.04E-07 1.36E-07 1.lOE-07 8.SSE-08 6.74E-08 5.54E-08 4.60E-08 3.88E-08 3.34E-08 s 2.49E-07 1.54E-07 8.64E-08 7.08E-08 5.49E-08 4.SSE-08 3.66E-08 3.02E-08 2.SSE-08 2.19E-08 SSW 2.56E-07 l.38E-07 1.16E-07 9.35E-08 7.06E-08 5.65E-08 4.69E-08 3.97E-08 3.35E-08 2.88E-08 SW 3.42E-07 2.00E-07 1.31E-07 1.0SE-07 7.70E-08 6.45E-08 5.40E-08 4.47E-08 3.80E-08 3.29E-08 WSW 4.89E-07 2.41E-07 1.43E-07 1.13E-07 8.09E-08 6.56E-08 5.29E-08 4.46E-08 3.90E-08 3.39E-08 w 1.06E-06 4.38E-07 2.54E-07 l.79E-07 l.37E-07 1.lOE-07 9.07E-08 7.70E-08 6.66E-08 5.86E-08 WNW 5.70E-07 2.38E-07 1.48E-07 1.0SE-07 8.0lE-08 6.43E-08 5.33E-08 4.54E-08 3.93E-08 3.46E-08 NW 6.59E-07 2.59E-07 1.54E-07 1.06E-07 7.99E-08 6.32E-08 S.19E-08 4.38E-08 3.76E-08 3.29E-08 NNW 9.74E-07 3.56E-07 2.03E-07 l.37E-07 l.02E-07 7.94E-08 6.46E-08 5.41E-08 4.63E-08 4.03E-08

Table 10 D/Q AIR EJECTOR 2019 Page 12 DIRECTION 804m l1609m 12416m l3218m l4022m l4827m l5632m l6436m 17240m l8045m D/Q N 1.69E-08 5.33E-09 2.66E-09 1.61E-09 1.09E-09 7.89E-10 6.00E-10 4.73E-10 3.83E-10 3.17E-10 NNE 1.18E-08 3.73E-09 1.86E-09 1.13E-09 7.62E-10 5 .52E-10 4.20E-10 3.31E-10 2.68E-1 0 2.22E-10 NE 1.70E-08 5.37E-09 2.68E-09 1.62E-09 1.lOE-09 7.96E-10 6.0SE-10 4.77E-10 3.86E-10 3.19E-10 ENE 2.02E-08 6.37E-09 3.18E-09 1.93E-09 1.30E-09 9.44E-10 7.18E-10 5.65E-10 4.58E-10 3.79E-10 E 1.91E-08 6.0lE-09 3.00E-09 1.82E-09 1.23E-09 8.90E-10 6.77E-10 S.33E-10 4.32E-10 3.57E-10 ESE 2.16E-08 6.SOE-09 3.39E-09 2.06E-09 1.39E-09 1.0lE-09 7.66E-10 6.03E-10 4.88E-10 4.04E-10 SE 1.34E-08 4.22E-09 2.llE-09 1.28E-09 8.63E-10 6.26E-10 4.76E-10 3.75E-10 3.03E-10 2.SlE-10 SSE 6.23E-09 1.96E-09 9.79E-10 5.94E-10 4.0lE-10 2.91E-10 2.21E-10 1.74E-10 1.41E-10 1.17E-10 s 3.84E-09 1.21E-09 6.04E-10 3.66E-10 2.48E-10 1.80E-10 1.37E-10 1.08E-10 8.71E-11 7.20E-11 SSW 4.65E-09 1.47E-09 7.31E-10 4.44E-10 3.00E-10 2.17E-10 1.65E-10 1.30E-10 1.0SE-10 8.72E-11 SW 8.29E-09 2.62E-09 l.30E-09 7 .91E-10 5.35E-10 3.87E-10 2.95E-10 2.32E-10 1.88E-10 1.SSE-10 WSW 1.18E-08 3.71E-09 1.85E-09 1.12E-09 7.58E-10 S.49E-10 4.18E-10 3.29E-10 2.66E-10 2.20E-10 w 1.39E-08 4.39E-09 2.19E-09 1.33E-09 8.98E-10 6.SlE -10 4.9SE-10 3.90E-10 3.16E-10 2.61E-10 WNW 6.27E-09 1.98E-09 9.86E-10 S.98E-10 4.04E-10 2.93E-10 2.23E-10 1.76E-10 1.42E- 10 1.18E-10 NW 7.40E-09 2.33E-09 l .16E-09 7.0SE-10 4.77E-10 3.45E-10 2.63E-10 2.07E-10 1.68E-10 1.39E-10 NNW 1.34E-08 4.24E-09 2.llE-09 1.28E-09 8.66E-10 6.28E-10 4.77E-10 3.76E-10 3.04E-10 2.52E-10

Table 11 X/Q AIR EJECTOR 2019 Page 13 DIRECTION 804m l1609m j2416m l3218m l4022m l4827m l5632m l6436m ]7240m ]8045m X/Q N 1.95E-06 6.70E-07 3.67E-07 2.41E-07 1.7SE-07 1.34E-07 1.0BE-07 8.94E-08 7.57E-08 6.54E-08 NNE l.65E-06 S.74E-07 3.lSE-07 2.07E-07 1.SOE-07 l .16E-07 9.30E-08 7.70E-08 6.53E-08 5.64E-08 NE 2.30E-06 8.03E-07 4.43E-07 2.92E-07 2.12E-07 1.64E-07 1.32E-07 1.09E-07 9.26E-08 8.0lE-08 ENE 2.42E-06 8.37E-07 4.62E-07 3.0SE-07 2.22E-07 1.71E-07 1.38E-07 1.lSE-07 9.72E-08 8.41E-08 E 2.28E-06 7.89E-07 4.36E-07 2.88E-07 2.09E-07 l.62E-07 l .30E-07 1.0BE-07 9.16E-08 7.92E-08 ESE l.63E-06 S.SOE-07 2.98E-07 1.9SE-07 1.40E-07 l.OBE-07 8.61E-08 7.llE-08 6.0lE-08 S.lBE-08 SE 1.19E-06 4.03E-07 2.21E -07 1.4SE-07 1.0SE-07 8.llE-08 6.52E-08 5.40E-08 4.SBE-08 3.96E-08 SSE 1.00E-06 3.39E-07 l.BSE-07 1.21E-07 8.69E-08 6.67E-08 S.34E-08 4.42E-08 3.73E-08 3.22E-08 s 6.42E-07 2.18E-07 1.19E-07 7.79E-08 S.63E-08 4.33E-08 3.47E-08 2.87E-08 2.43E-08 2.lOE-08 SSW 8.49E-07 2.84E-07 l .SSE-07 l.02E-07 7.34E-08 5.64E-08 4.53E-08 3.75E-08 3.17E-08 2.74E-08 SW 1.02E-06 3.38E-07 l.83E-07 1.19E-07 8.60E-08 6.60E-08 5.28E-08 4.36E -08 3.68E-08 3.lBE-08 WSW 1.19E-06 3.94E-07 2.13E-07 1.39E-07 1.00E-07 7.68E-08 6.lSE-08 S.OBE-08 4.30E-08 3.71E-08 w 2.39E-06 8.25E-07 4.56E-07 3.0lE-07 2.19E-07 1.69E-07 l.36E-07 l .13E-07 9.61E-08 8.31E-08 WNW l.43E-06 4.99E-07 2.78E-07 l.84E-07 1.34E-07 1.04E-07 8.40E-08 6.98E-08 5.94E-08 5.14E-08 NW 1.30E-06 4.48E-07 2.47E-07 l.63E-07 1.18E-07 9.12E-08 7.34E-08 6.08E-08 5.16E-08 4.46E-08 NNW l.SSE-06 5.31E-07 2.91E-07 1.91E-07 1.39E-07 1.07E-07 8.57E-08 7.lOE-08 6.02E-08 5.19E-08

Table 12 Page 14 Distance to Air Ejector Containment Vent Plant Vent Direction Nearset Residence (m}

X/Q (sec/m 3 )

I D/Q (m -2)

X/Q (sec/m 3 )

I D/Q (m-2)

X/Q (sec/m 3 }

I D/Q (m-2}

E 1170 l.27E-06 l.03E-08 7.70E-07 9.17E-09 1.41E-07 2.98E-09 ESE 1660 5.24E-07 6.45E-09 4.03E-07 5.96E-09 1.91E -07 3.81E-09 SE 840 l.llE-06 1.25E-08 5.08E-07 1.13E-08 1.23E-07 7.14E-09 SSE 610 1.56E-06 9.69E-09 6.06E-07 7.77E-09 8.78E-08 3.44E-09 s 1500 2.43E-07 1.37E-09 1.60E-07 l.08E-09 5.54E-08 6.86E-10 SSW 620 1.31E-06 7.06E-09 3.53E-07 5.0lE-09 5.40E-08 2.lSE-09 SW 740 1.16E-06 9.49E-09 3.79E-07 7.38E-09 7.18£-08 4.22E-09 WSW 900 9.89£-07 9.80E-09 4.27£-07 8.28E-09 8.74E-08 4.90E-09 w 1330 l.lOE-06 6.07E-09 5.47E-07 4.76E-09 l.02E-07 l.84E-09 Distance to Air Ejector Containment Vent Plant Vent Direction Nearest Milk Producing Animal (m)

X/Q (sec/m 3 }

I D/Q (m-2)

X/Q (sec/m 3 )

I D/Q (m-2)

X/Q (sec/m 3 )

I D/Q (m-2)

ESE 8240 5.0lE-08 3.87£-10 4.93£-08 3.90E-10 4.18E-08 2.87£-10 Distance to Air Ejector Containment Vent Plant Vent Direction Nearest Garden (m)

X/Q (sec/m3 )

I D/Q (m -2)

X/Q (sec/m 3 )

I D/Q (m - 2)

X/Q (sec/m 3 )

I D/Q (m -2)

E 610 3.SSE-06 2.97E-08 2.03E-06 2.62E-08 1.56E-07 4.90E-09 ESE 430 4.43E-06 5.76E-08 2.54E-06 5.22E-08 3.SOE-07 1.56E-08 SSE 660 l.37E-06 8.56E-09 5.65E-07 6.93E-09 8.91E-08 3.13E-09

15 5.2 Instrument Maintenance In January and February, at the Primary Tower, the 150' A wind direction lost a tailpiece.

All invalid data was replaced with the 150' B wind direction. The issue was fixed February 20 .

In June, a calibration of the Primary Tower and Backup Tower was performed.

In July, at the Backup Tower, the cable, crossarm and wind direction were replaced.

No other problems were encountered with the equipment, and at the end of the year, no problems were evident at the site.

MwTay & Trettel, Inc. 600 First Bank Driue, uite A Palatine, Illi11oi.~ 60067 (847) 963-9000

16 5.3 Data Recovery The record of data recovery for the year is summarized in Table 12.

Table 12 Ginna Site Data Recovery Summary 2019 Recovered Recovered lost Percent Measurement Elevation Hours Percent Hours Changed Wind Speed 33 ft. 8754 99.9 6 0.1 Wind Speed 150 ft. 8711 99.4 49 0.6 Wind Speed 250 ft. 8700 99.3 60 0.7 Wind Direction 33 ft . 8754 99.9 6 0.1 Wind Direction 150 ft . 8754 99.9 6 8.4 Wind Direction 250 ft. 8754 99.9 6 0.2 Ambient Temperature 33 ft. 8754 99.9 6 0.1 Ambient Temperature 150 ft. 8754 99.9 6 0.1 Ambient Temperature 250 ft. 8754 99.9 6 0.1 Differential Temperature 150-33 ft. 8754 99.9 6 0.3 Differential Temperature 250-33 ft. 8754 99.9 6 0.7 Precipitation 10 ft. 8754 99 .9 6 0.2 AVERAGE* 99.8

average of priority parameters (all except precipitation)

Valid Recovered lost Hours Percent Hours lower level Joint Frequency % 8754 99 .9 6 Middle Level Joint Frequency % 8711 99.4 49 Upper Level Joint Frequency% 8700 99 .3 60 Murl'ay & Trettel Inc. 600 First Bank Drive, Suite A Palatine, lliinois 60067 (847) 963-9000

17 5.4 Stability Wind Rose Data The annual stability wind roses are given at the end of this report. Wind speed classes have been altered to reflect the sensor threshold.

For the year, winds measured at 33 ft. most frequently came from the west southwest (10.61 %) and most frequently fell into the 2.1-3.0 m/s wind speed class (23%). Calms (wind speeds at or below the sensor threshold) were measured 0.00% of the time and speeds greater than 10.0 mis were measured (2 .72%) of the time . Winds measured at 150 ft. most frequently came from the west northwest (11.% ) and most frequently fell into the 6.1-8.0 m/s wind speed class (18.6%). Calms were measured 0.00% of the time and speeds greater than 10.0 mis were measured (10.67%) of the time. Winds measured at 250 ft. most frequently came from the west northwest (11 .85%) and most frequently fell into the 6.1-8.1 mis wind speed class (22.08%). Calms were measured 0.00% of the time and speeds greater than 10.0 m/s were measured (16.19%) of the tim e.

Stability based on the 150-33 ft. differential temperature most frequently fell into the neutral classification (35.24%) and stability based on the 250-33 ft. differential temperature most frequently fell into the neutral classification (43.01 %)

Murray & Trettel, Inc. 600 First Bank Drive, uite A Palatine, Illinois 60067 (847) 963-9000

18 5.5 Precipitation Table 13 Precipitation Totals (Inches) - 2019 Ginna Site Month Total January 2.18 February 1.89 March 1.32 April 2.74 May 4.41 June 4.11 July 1.48 August 3.74 September 3.37 October 5.1 3 November 1.77 December 3.96 TOTAL: 36.10*

Indicates some precipitation missing .

Murray & Trettel, Inc. 600 First Bank Dtiue, Suite A Palatine, fllinois 60067 (847) 963-9000

2019 Joint Frequency Tables Murray & Trettel, Inc. 600 First Bank Drive, Suite A Palatine, Illinois 60067 <t> (847) 963-9000

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan

Dec for years 2019

2019 All Stabilities Elevations:: Winds 33ft Stability 150ft Wind Wind Speed Range (m/s)

Direction 0.5* 1.1

1.6* 2.1* 3.1* 4.1* 5. 1* 6.1* 8.1* >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 1 18 33 38 60 32 5 5 3 0 0 195 NNE 0 12 34 36 83 45 26 24 22 8 5 295 NE 1 18 27 54 75 57 38 45 39 44 28 426 ENE 1 12 41 74 150 108 101 93 65 31 29 705 E 0 15 28 68 129 116 77 40 23 1 0 497 ESE 0 9 22 33 72 37 8 3 0 0 0 184 SE 0 8 20 28 92 63 23 10 6 0 0 250 SSE 1 8 27 33 96 79 71 51 79 19 10 474 s 0 25 49 62 139 157 127 99 115 31 8 812 SSW 0 25 77 162 293 204 97 48 14 0 0 920 SW 0 21 70 146 326 166 79 47 16 0 3 874 WSW 1 13 27 50 146 145 132 114 167 83 51 929 w 0 12 30 28 98 157 160 109 176 49 24 843 WNW 2 11 22 40 153 149 141 128 122 73 77 918 NW 1 17 26 51 77 43 37 29 39 11 3 334 NNW 0 17 17 20 24 15 3 2 0 0 0 98 Tot 8 241 550 923 2013 1573 1125 847 886 350 238 8754 Hours of Calm .. 0 Hours of Variable Direction 0 Hours of Valid Data . 8754 Hours of Hissing Data 6 Hours in Period . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan

Dec for years 2019

2019 Stability Cl ass A Extremely Unstable based on Lapse Rate Elevations:: Winds 33ft Stability 150ft Wind Wind Speed Range (m/s)

Direction 0.5* 1.1* 1.6* 2.1* 3.1* 4.1

5.1* 6.1* 8.1* >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 0 0 7 6 9 l 3 2 0 0 28 NNE 0 0 1 1 11 6 6 3 9 6 5 48 NE 0 0 0 0 4 19 20 20 20 36 28 147 ENE 0 0 0 4 28 34 45 63 48 28 29 279 E 0 0 0 0 0 3 0 7 9 1 0 20 ESE 0 0 0 0 0 2 0 0 0 0 0 2 SE 0 0 1 0 1 5 1 0 0 0 9 SSE 0 0 0 0 2 7 l 4 5 1 0 20 s 0 0 0 0 3 11 7 4 3 1 0 29 SSW 0 0 l 0 5 10 2 0 0 0 0 18 SW 0 0 0 3 4 15 11 2 0 0 0 35 WSW 0 0 0 0 0 4 3 3 3 0 0 13 w 0 0 0 0 3 6 9 6 5 2 0 31 WNW 0 0 0 1 47 65 55 50 33 14 11 276 NW 0 0 0 12 29 16 23 10 14 3 2 109 NNW 0 0 0 9 4 11 3 0 0 0 0 27 Tot 0 0 3 37 147 223 187 176 151 92 75 1091 Hours of Calm .. 0 Hours of Variable Direction 0 Hours of Valid Data . 1091 Hours of Missing Data 6 Hours in Period . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan

Dec for years 2019

2019 Stability Class B Moderately Unstable based on Lapse Rate Elevations:: Winds 33ft Stability 150ft Wind Wind Speed Range (m/s)

Direction 0.5* 1.1- 1.6* 2. l* 3.1* 4.1* 5.l* 6.1* 8.1* >10.00 Sector <0 .50 1. 0 1. 5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 0 1 5 7 10 1 0 1 0 0 25 NNE 0 0 2 3 19 6 4 9 12 1 0 56 NE 0 0 0 4 8 8 3 9 9 5 0 46 ENE 0 0 3 3 16 21 21 15 12 2 0 93 E 0 0 0 0 3 13 16 11 6 0 0 49 ESE 0 0 0 0 0 3 0 0 0 0 0 3 SE 0 0 0 1 0 3 1 2 2 0 0 9 SSE 0 0 0 1 6 9 5 3 6 1 0 31 s a a 0 2 6 4 5 2 2 4 0 25 SSW 0 0 1 2 5 5 4 1 0 0 a 18 SW a a 0 0 10 11 7 3 0 0 0 31 WSW 0 0 a 0 6 7 8 4 8 1 0 34 w 0 0 0 2 2 3 5 4 11 4 0 31 WNW 0 0 1 6 9 11 14 13 11 9 11 85 NW 0 0 0 4 3 4 4 7 10 5 0 37 NNW 0 0 2 0 0 2 0 0 0 0 0 4 Tot 0 0 10 33 100 120 98 83 90 32 11 577 Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data .. 577 Hours of Missing Data . 6 Hours in Period .. . . 8760

Joi nt Frequency Distribution Site:: Ginna Primary Period:: Months Jan Dec for years 2019

2019 Stability Cl ass C Sl ightly Unstable based on Lapse Rate Elevations:: Winds 33ft Stability 150ft Wind Wind Speed Range (m/s)

Direction 0.5

1.1* 1.6- 2.1* 3.1* 4.1* 5.1* 6. l* 8.1* >10.00 Sector <0.50 1. 0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 0 0 4 9 6 2 0 0 0 0 21 NNE 0 0 1 3 10 13 5 4 1 0 0 37 NE 0 0 2 2 13 8 6 8 4 1 0 44 ENE 0 0 2 3 11 6 6 3 2 1 0 34 E 0 0 0 2 10 6 14 2 2 0 0 36 ESE 0 0 0 1 1 3 0 0 0 0 0 5 SE 0 0 0 0 3 2 2 0 0 0 0 7 SSE 0 0 1 0 1 3 2 2 7 1 0 17 s 0 0 0 0 6 4 3 0 5 2 0 20 SSW 0 0 0 1 10 5 0 3 0 0 0 19 SW 0 0 0 0 6 5 3 2 2 0 0 18 WSW 0 0 1 2 1 4 3 4 4 3 0 22 w 0 0 0 0 3 10 8 4 7 1 0 33 WNW 0 0 0 2 4 3 4 7 7 11 14 52 NW 0 0 0 3 1 3 1 4 3 2 0 17 NNW 0 0 2 l 2 1 0 0 0 0 0 6 Tot 0 0 9 24 91 82 59 43 44 22 14 388 Hours of Calm 0 Hours of Variable Direction 0 Hours of Val id Data . 388 Hours of Missing Data 6 Hours in Period . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan

Dec for years 2019

2019 Stability Class D Neutral based on Lapse Rate Elevations:: Winds 33ft Stability 150ft Wind Wind Speed Range (m/s)

Direction 0.5* 1.1

1.6* 2.1* 3.1* 4. l

5.1* 6.1* 8.1* >10 .00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 1 9 17 15 34 6 1 2 0 0 0 85 NNE 0 4 18 20 30 15 8 5 0 0 0 100 NE 0 6 5 24 28 20 9 6 4 1 0 103 ENE 0 3 12 15 41 26 16 8 1 0 0 122 E 0 2 5 22 51 52 38 14 3 0 0 187 ESE 0 0 3 8 38 20 6 3 0 0 0 78 SE 0 2 4 7 36 40 17 7 4 0 0 117 SSE 0 1 3 13 26 40 48 35 49 14 10 239 s 0 2 12 16 35 51 58 36 56 19 8 293 SSW 0 3 4 14 49 46 21 16 8 0 0 161 SW 0 1 7 10 46 64 30 27 9 0 2 196 WSW 0 2 3 6 26 56 74 70 139 75 51 502 w 0 5 8 7 31 64 83 65 140 42 24 469 WNW 1 3 7 10 25 29 40 42 62 37 40 296 NW 1 0 13 14 21 19 9 7 11 1 1 97 NNW 0 7 9 5 16 1 0 2 0 0 0 40 Tot 3 50 130 206 533 549 458 345 486 189 136 3085 Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data . 3085 Hours of Missing Data 6 Hours in Period . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan

Dec for years 2019

2019 Stability Class E Slightly Stable based on Lapse Rate Elevations:: Winds 33ft Stability 150ft Wind Wind Speed Range (m/s)

Direction 0.5* 1.1* 1.6* 2.1* 3.1* 4.1* 5.1* 6.1* 8.1* >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 8 13 5 3 1 0 0 0 0 0 30 NNE 0 7 10 8 12 5 3 2 0 1 0 48 NE 1 5 5 10 13 1 0 2 0 1 0 38 ENE 1 3 10 23 25 13 11 4 1 0 0 91 E 0 7 11 31 37 27 6 6 3 0 0 128 ESE 0 1 12 21 26 7 2 0 0 0 0 69 SE 0 4 8 10 37 12 2 0 0 0 0 73 SSE 0 3 3 8 35 18 15 7 12 2 0 103 s 0 5 10 16 54 68 so 57 49 5 0 314 SSW 0 6 22 18 90 92 65 28 6 0 0 327 SW 0 11 23 30 138 69 28 13 5 0 1 318 WSW 0 7 15 22 64 70 44 33 13 4 0 272 w 0 4 13 15 50 71 54 30 13 0 0 250 WNW l 8 10 13 44 31 24 15 8 2 1 157 NW 0 11 11 9 8 0 0 1 1 0 0 41 NNW 0 4 2 2 1 0 0 0 0 0 0 9 Tot 3 94 178 241 637 485 304 198 111 15 2 2268 Hours of Calm 0 Hours of Variabl e Direction 0 Hours of Val i d Data. 2268 Hours of Missing Data 6 Hours in Period . . . 8760

Joi nt Frequency Distribution Site:: Ginna Primary Period:: Months Jan Dec for years 2019 - 2019 Stability Class F Moderately Stable based on Lapse Rate Elevati ons:: Winds 33ft Stability 150ft Wind Wind Speed Range (m/s)

Direction 0.5- 1.1* 1.6* 2.1- 3.1- 4.1- 5.1* 6.1- 8.1 - >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 1 2 2 1 o o 0 0 0 0 6 NNE 0 0 2 l 1 0 o 1 0 0 o 5 NE o 4 9 7 5 1 o o 2 0 o 28 ENE o 4 8 8 13 5 1 o o o o 39 E 0 4 9 4 17 6 2 o o 0 o 42 ESE D 5 6 2 3 2 0 D 0 0 0 18 SE 0 2 4 6 13 1 0 0 0 0 0 26 SSE 0 3 10 6 18 2 0 0 0 D 0 39 s 0 9 11 8 19 19 4 0 0 o 0 70 SSW 0 8 17 33 51 38 5 0 0 D 0 152 SW 0 7 26 48 72 2 0 D D 0 0 155 WSW 1 2 6 15 39 4 D 0 0 D 0 67 w 0 2 4 2 8 3 1 0 0 D 0 20 WNW 0 0 3 3 13 9 4 1 1 0 0 34 NW 0 3 2 7 12 1 D 0 0 0 0 25 NNW D 3 1 1 D D D 0 0 D 0 5 Tot 1 57 120 153 285 93 17 2 3 0 0 731 Hours of Ca 1m 0 Hours of Variable Direction D Hours of Valid Data. 731 Hours of Missing Data 6 Hours in Period . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan Dec for years 2019

2019 Stabi l ity Class G Extremely Stable based on lapse Rate Elevations:: Winds 33ft Stability 150ft Wind Wind Speed Range (m/s)

Direction 0.5* 1.1* 1. 6* 2.1* 3.1* 4.1* 5.1

6.1* 8.1* >10.00 Sector <0.50 1. 0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 1 0 0 0 0 0 0 0 0 0 1 NE 0 3 6 7 4 0 0 0 0 0 0 20 ENE 0 2 6 18 16 3 1 0 1 0 0 47 E 0 2 3 9 11 9 1 0 0 0 0 35 ESE 0 3 1 1 4 0 0 0 0 0 0 9 SE 0 0 3 4 2 0 0 0 0 0 0 9 SSE 1 1 10 5 8 0 0 0 0 0 0 25 s 0 9 16 20 16 0 0 0 0 0 0 61 SSW 0 8 32 94 83 8 0 0 0 0 0 225 SW 0 2 14 55 50 0 0 0 0 0 0 121 WSW 0 2 2 5 10 0 0 0 0 0 0 19 w 0 1 5 2 1 0 0 0 0 0 0 9 WNW 0 0 1 5 11 1 0 0 0 0 0 18 NW 0 3 0 2 3 0 0 0 0 0 0 8 NNW 0 3 1 2 1 0 0 0 0 0 0 7 Tot 1 40 100 229 220 21 2 0 1 0 0 614 Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data .. 614 Hours of Missing Data. 6 Hours in Period . . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan

Dec for years 2019 - 2019 All Stabilities Elevations:: Winds 150ft Stability 150ft Wind Wind Speed Range (m/s)

D1rection 0.5* 1.1* 1.6- 2.1* 3.1* 4.1* 5.1* 6.1* 8.1 * >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 3 16 20 32 27 8 14 25 15 11 171 NNE 0 13 15 22 37 24 24 18 23 22 9 207 NE 0 9 22 29 55 45 32 32 47 37 61 369 ENE 0 9 12 25 93 101 73 61 77 38 34 523 E 0 13 18 34 116 119 147 107 64 2 0 620 ESE l 6 18 20 58 81 52 32 11 0 0 279 SE 0 4 7 12 69 91 85 39 19 3 0 329 SSE 0 4 8 14 48 60 94 89 144 95 42 598 s 1 5 9 15 51 73 109 135 205 99 50 752 SSW 0 8 12 13 41 64 97 117 152 20 2 526 SW 0 6 10 19 47 103 210 190 131 38 4 758 WSW 0 9 10 13 56 90 142 149 207 111 112 899 w 1 8 16 20 60 65 110 115 161 140 152 848 WNW 0 4 8 21 65 81 76 91 217 158 238 9-59 NW 0 10 20 16 61 44 41 31 95 82 196 596 NNW 0 10 15 33 49 28 32 27 42 22 19 277 Tot 3 121 216 326 938 1096 1332 1247 1620 882 930 8711 Hours of Calm .. 0 Hours of Variable Direction 0 Hours of Valid Data . 8711 Hours of Missing Data 49 Hours 10 Period . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Mont hs Jan - Dec for years 2019 - 2019 Stability Cl ass A Extremely Unstable based on Lapse Rate Elevations:: Winds 150ft Stability 150ft Wind Wind Speed Range (m/s)

Direction 0.5- 1.1- 1.6* 2.1- 3.1

4 .1- 5.1- 6.1- 8.1* >10 .00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 0 0 0 4 4 0 2 5 7 4 26 NNE 0 0 0 0 4 2 2 3 6 10 7 34 NE 0 0 0 0 4 10 11 15 20 23 57 140 ENE 0 0 0 1 14 30 28 49 55 34 31 242 E 0 0 0 0 1 6 19 17 14 1 0 58 ESE 0 0 0 0 0 2 0 0 0 0 0 2 SE 0 0 0 1 0 1 4 1 1 0 0 8 SSE 0 0 0 0 0 3 7 2 4 5 3 24 s 0 0 0 0 2 4 7 9 3 2 0 27 SSW 0 0 0 0 2 3 8 0 0 0 0 13 SW 0 0 0 2 3 4 10 12 5 0 0 36 WSW 0 0 0 0 1 1 4 4 4 3 0 17 w 0 0 0 0 1 1 3 1 3 1 1 11 WNW 0 0 0 0 5 14 27 31 59 34 47 217 NW 0 0 0 0 21 22 16 16 40 22 57 194 NNW 0 0 0 0 13 4 2 1 10 4 6 40 Tot 0 0 0 4 75 111 148 163 229 146 213 1089 Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data . 1089 Hours of Missing Data 49 Hours in Period . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan

Dec for years 2019 - 2019 Stability Class B Moderately Unstable based on Lapse Rate Elevations : : Winds 150ft Stability 150ft Wind Wind Speed Range (m/s)

Direction 0.5* 1.1* 1.6* 2.1

3.1* 4.1* 5.1* 6.1* 8.1* >10. 00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 0 0 0 7 2 0 2 8 1 4 24 NNE 0 0 2 1 12 3 1 2 9 4 1 35 NE 0 0 2 4 3 8 3 4 14 9 1 48 ENE 0 0 0 3 10 13 15 7 8 2 0 58 E 0 0 0 0 1 8 22 21 15 1 0 68 ESE 0 0 0 0 1 1 1 0 0 0 0 3 SE 0 0 0 0 0 2 4 3 2 1 0 12 SSE 0 0 0 2 4 3 6 4 4 6 1 30 s 0 0 0 1 4 4 3 3 4 1 4 24 SSW 0 0 0 1 5 5 4 0 3 0 0 18 SW 0 0 0 0 0 8 9 6 6 0 0 29 WSW 0 0 0 0 2 4 4 7 10 6 1 34 w 0 0 0 2 3 1 0 2 4 3 3 18 WNW 0 0 0 2 5 6 8 3 20 13 26 83 NW 0 0 0 0 3 3 0 0 4 11 32 53 NNW 0 0 1 4 5 4 0 1 5 7 1 28 Tot 0 0 5 20 65 75 80 65 116 65 74 565 Hours of Calm 0 Hours of Variable Direction 0 Hours of Val i d Data . . 565 Hours of Missing Data . 49 Hours in Period . . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan Dec for years 2019 - 2019 Stability Cl ass C Slightly Unstable based on Lapse Rate Elevations:: Winds 150ft Stability 150ft Wind Wind Speed Range (m/s)

Direction 0.5- 1.1- 1.6- 2.1

3.1- 4.1- 5.1* 6.1* 8.1- >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 0 0 1 2 3 3 4 4 2 0 19 NNE 0 0 1 2 5 5 4 6 2 2 0 27 NE 0 0 0 1 8 6 3 6 7 2 0 33 ENE 0 0 0 3 6 6 6 1 5 0 1 28 E 0 1 0 1 6 6 13 7 3 0 0 37 ESE 0 0 0 0 0 4 1 1 0 0 0 6 SE 0 0 0 0 4 0 4 2 0 0 0 10 SSE 0 0 1 1 1 2 1 2 5 7 1 21 s 0 0 0 0 1 6 4 2 1 2 2 18 SSW 0 0 0 0 4 5 4 0 3 0 0 16 SW 0 0 0 0 4 2 3 2 4 3 0 18 WSW 0 0 0 0 1 2 4 3 4 5 3 22 w 0 0 0 1 1 1 4 3 6 4 0 20 WNW 0 0 0 0 0 3 4 6 7 9 27 56 NW 0 0 0 1 3 1 1 1 0 3 18 28 NNW 0 0 0 3 2 1 2 1 4 6 4 23 Tot 0 1 2 14 48 53 61 47 55 45 56 382 Hours of Ca 1m 0 Hours of Variable Direction 0 Hours of Valid Data . 382 Hours of Missing Data 49 Hours in Period . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan

Dec for years 2019 - 2019 Stability Cl ass D Neutral based on Lapse Rate Elevations: : Winds 150ft Stability 150ft Wind Wind Speed Range (m/s)

Direction 0.5* 1.1* 1.6* 2.1* 3.1* 4.1* 5.1* 6.1* 8.1 * >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 0 8 9 6 15 5 4 5 3 2 57 NNE 0 1 6 12 10 11 8 5 3 4 0 60 NE 0 1 11 15 22 13 11 6 6 2 1 88 ENE 0 2 4 6 27 30 7 2 6 2 0 86 E 0 l 2 10 33 35 39 27 21 0 0 168 ESE 0 1 4 6 21 20 24 14 8 0 0 98 SE 0 1 2 3 32 40 33 17 13 2 0 143 SSE 0 0 0 3 16 22 31 32 82 57 30 273 s 0 0 1 9 21 17 42 47 68 35 33 273 SSW 0 1 6 4 14 19 28 20 16 7 2 117 SW 0 1 2 4 11 26 35 49 46 17 3 194 WSW 0 1 1 2 10 21 39 52 112 77 103 418 w o 3 2 4 12 10 31 47 94 117 142 462 WNW o 1 4 5 10 19 14 27 60 58 121 319 NW 0 3 7 5 14 6 11 9 32 32 79 198 NNW o 2 6 11 15 16 18 15 16 4 8 111 Tot 0 19 66 108 274 320 376 373 588 417 524 3065 Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data . 3065 Hours of Missing Data 49 Hours in Period . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan Dec for years 2019

2019 Stability Cl ass E Slightly Stable based on Lapse Rate Elevations: : Winds 150ft Stability 150ft Wind Wind Speed Range (m/s)

Direction 0.5* 1.1* 1.6* 2.1* 3. l* 4.1* 5.1* 6.1* 8.1* >10.00 Sector <0.50 l. 0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 0 4 5 5 3 0 2 3 2 1 25 NNE 0 7 4 3 4 1 9 2 2 2 1 35 NE 0 4 4 6 10 4 2 0 0 1 1 32 ENE 0 5 2 10 21 11 14 1 2 0 0 66 E 0 2 6 15 29 34 30 24 8 0 0 148 ESE 0 0 9 9 14 23 16 13 2 0 0 86 SE 0 0 0 3 13 27 22 12 2 0 0 79 SSE 0 0 3 4 14 12 33 34 38 20 7 165 s 1 0 3 4 10 25 31 55 106 59 11 305 SSW 0 2 3 4 10 15 33 68 89 13 0 237 SW 0 2 0 5 20 21 87 79 65 18 1 298 WSW 0 3 5 4 20 22 35 55 77 20 5 246 w 0 1 5 5 17 22 36 46 50 15 6 203 WNW 0 1 2 4 26 22 19 20 61 42 15 212 NW 0 2 4 4 14 5 9 5 17 12 10 82 NNW 0 4 4 7 7 2 8 7 6 1 0 46 Tot 1 33 58 92 234 249 384 423 528 205 58 2265 Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data . 2265 Hours of Missing Data 49 Hours in Period . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan Dec for years 2019

2019 Stability Class F Moderately Stabl e based on Lapse Rate Elevations:: Winds 150ft Stability 150ft Wind Wind Speed Range (m/s)

Di rection 0.5* 1.1

1.6* 2.1

3.1* 4.1* 5.1* 6.1* 8.1* >10 .00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 1 3 3 5 0 0 0 0 0 0 12 NNE 0 0 1 0 1 1 0 0 1 0 0 4 NE 0 2 1 2 5 2 1 1 0 0 1 15 ENE 0 2 4 0 9 7 2 1 1 0 1 27 E 0 7 4 4 24 12 13 4 1 0 0 69 ESE 1 1 4 3 3 20 3 1 1 0 0 37 SE 0 2 2 3 7 12 6 4 1 0 0 37 SSE 0 2 2 0 4 4 7 12 9 0 0 40 s 0 1 1 0 6 8 9 12 21 0 0 58 SSW 0 3 0 3 2 11 12 21 32 0 0 84 SW 0 2 5 2 2 26 49 29 4 0 0 119 WSW 0 1 0 3 3 20 29 24 0 0 0 80 w 1 1 1 2 11 13 16 10 4 0 0 59 WNW 0 2 2 3 11 11 3 3 10 2 2 49 NW 0 2 4 4 6 2 3 0 1 0 0 22 NNW 0 1 2 6 5 0 2 2 1 0 0 19 Tot 2 30 36 38 104 149 155 124 87 2 4 731 Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data .. 731 Hours of Missing Data. 49 Hours in Period . . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan Dec for years 2019

2019 Stability Class G Extremely Stable based on Lapse Rate Elevations:: Winds 150ft Stability 150ft Wind Wind Speed Range (m/s)

Direction 0.5* 1.1* 1.6* 2.1- 3.1* 4.1* 5.1

6.1* 8.1* >10.00 Sector <0.50 1. 0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 2 1 2 3 0 0 0 0 0 0 8 NNE 0 5 1 4 1 1 0 0 0 0 0 12 NE 0 2 4 1 3 2 1 0 0 0 0 13 ENE 0 0 2 2 6 4 1 0 0 0 1 16 E 0 2 6 4 22 18 11 7 2 0 0 72 ESE 0 4 1 2 19 11 7 3 0 0 0 47 SE 0 1 3 2 13 9 12 0 0 0 0 40 SSE 0 2 2 4 9 14 9 3 2 0 0 45 s 0 4 4 1 7 9 13 7 2 0 0 47 SSW 0 2 3 1 4 6 8 8 9 0 0 41 SW 0 1 3 6 7 16 17 13 1 0 0 64 WSW 0 4 4 4 19 20 27 4 0 0 0 82 w 0 3 8 6 15 17 20 6 0 0 0 75 WNW 0 0 0 7 8 6 1 1 0 0 0 23 NW 0 3 5 2 0 5 1 0 1 2 0 19 NNW 0 3 2 2 2 1 0 0 0 0 0 10 Tot 0 38 49 50 138 139 128 52 17 2 1 614 Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data. 614 Hours of Missing Data 49 Hours in Period . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan - Dec for years 2019 - 2019 All Stabi lities Elevations:: Winds 250ft Stability 250ft Wind Wind Speed Range (m/s)

Direction 0.5 - 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1 - 8.1- >10.00 Sector <0.50 1.0 1. 5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N o 7 18 27 33 24 12 12 26 19 11 189 NNE 0 5 13 17 46 29 21 12 28 24 9 204 NE o 9 19 34 64 68 50 37 60 48 58 447 ENE 2 9 24 39 110 103 113 61 56 33 26 576 E 1 6 17 35 91 61 101 100 86 5 0 503 ESE 2 7 11 18 48 40 50 57 56 8 o 297 SE o 3 7 9 31 48 77 68 92 25 5 365 SSE o 3 5 7 19 38 45 64 168 153 139 641 s 1 1 2 8 38 37 50 74 156 129 94 590 SSW o 8 8 10 29 30 46 69 147 125 20 492 SW o 3 6 16 26 46 69 137 280 92 17 692 WSW 0 6 10 12 35 41 87 138 277 152 154 912 w 0 4 10 9 44 68 68 114 195 125 258 895 WNW 0 7 7 10 58 78 66 72 173 176 383 1030 NW 0 6 8 24 51 50 42 29 87 84 208 589 NNW 0 5 11 20 59 34 32 26 33 27 26 273 Tot 6 89 176 295 782 795 929 1070 1920 1225 1408 8695 Hours of Cal m .. 5 Hours of Variable Direction 0 Hours of Valid Data . 8700 Hours of Missing Data 60 Hours in Period . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan

Dec for years 2019

2019 Stability Class A Extremel y Unstable based on Lapse Rate Elevations: : Winds 250ft Stability 250ft Wind Wind Speed Range (m/s)

Direction 0.5* 1.1* 1.6* 2.1* 3.1* 4.1* 5.1* 6.1* 8.1* >10.00 Sector <0.50 1.0 1. 5 2.0 3.0 4.0 5.0 6.0 8.0 10 .0 Total N 0 0 0 0 0 0 0 0 0 0 2 2 NNE 0 0 0 0 0 0 0 0 0 2 4 6 NE 0 0 0 0 0 0 4 5 9 12 30 60 ENE 0 0 0 0 0 4 11 8 9 12 13 57 E 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 1 1 1 0 0 3 SSE 0 0 0 0 0 0 1 0 0 0 0 1 s 0 0 0 0 0 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 0 0 0 0 0 w 0 0 0 0 0 0 0 0 0 0 0 0 WNW 0 0 0 0 2 4 3 7 17 10 5 48 NW 0 0 0 0 3 12 11 8 11 7 20 72 NNW 0 0 0 0 2 2 1 0 0 1 5 11 Tot 0 0 0 0 7 22 32 29 47 44 79 260 Hours of Calm 0 Hours of Variabl e Direction 0 Hours of Valid Data . 260 Hours of Missing Data 60 Hours in Period . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan Dec for years 2019

2019 Stability Class B Moderately Unstable based on Lapse Rate Elevations:: Winds 250ft Stability 250ft Wind Wind Speed Range (m/s)

Direction 0.5* 1.1* 1.6* 2.1

3.1* 4.1* 5.1* 6.1* 8.1* >10.00 Sector <0.50 1.0 1. 5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 0 0 0 0 1 0 0 0 3 0 4 NNE 0 0 0 0 0 0 0 0 0 0 1 1 NE 0 0 0 0 0 0 4 5 2 6 17 34 ENE 0 0 0 0 0 2 4 4 10 5 3 28 E 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 1 0 0 0 0 1 s 0 0 0 0 0 0 1 1 0 0 0 2 SSW 0 0 0 0 0 0 1 0 0 0 0 1 SW 0 0 0 0 0 1 0 1 1 0 0 3 WSW 0 0 0 0 0 0 0 0 0 0 0 0 w 0 0 0 0 0 0 0 1 1 0 0 2 WNW 0 0 0 0 0 1 5 1 5 3 6 21 NW 0 0 0 0 3 2 1 1 6 1 10 24 NNW 0 0 0 0 3 5 0 0 0 1 1 10 Tot 0 0 0 0 6 12 17 14 25 19 38 131 Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data . 131 Hours of Missing Data 60 Hours in Period . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan Dec for years 2019 - 2019 Stability Cl ass C Slightly Unstable based on Lapse Rate Elevations:: Winds 250ft Stability 250ft Wind Wind Speed Range (m/s)

Direction 0.5* 1.1* 1.6* 2.1* 3.1* 4.1* 5.1

6.1* 8.1* >10.00 Sector <0.50 1. 0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 0 0 0 2 0 0 0 3 3 1 9 NNE 0 0 0 0 0 3 3 4 3 6 1 20 NE 0 0 0 0 2 7 3 6 10 8 3 39 ENE 0 0 0 1 3 4 28 8 12 8 1 65 E 0 0 0 0 a a 0 3 1 a 0 4 ESE a 0 a 0 0 a 2 0 0 a 0 2 SE 0 a 0 a 0 0 1 3 1 0 0 5 SSE a 0 0 0 0 4 4 1 5 4 2 20 s 0 0 a 0 0 2 4 1 2 1 2 12 SSW 0 0 a 0 0 1 4 2 0 0 a 7 SW 0 0 a 0 0 1 2 5 0 a 0 8 WSW 0 a a a a 1 2 1 1 1 0 6 w 0 a 0 0 a a 1 1 3 2 0 7 WNW a 0 0 a 1 3 2 4 14 9 14 47 NW a 0 a 0 2 4 1 4 8 11 21 51 NNW 0 0 a 0 3 5 0 1 5 4 0 18 Tot 0 a 0 1 13 35 57 44 68 57 45 320 Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data . 320 Hours of Missing Data 60 Hours in Period . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan Dec for years 2019

2019 Stabil ity Cl ass D Neutral based on Lapse Rate Elevations:: Winds 250ft Stability 250ft Wind Wind Speed Range (m/s)

Direction 0.5* 1.1* 1.6* 2.1

3.1* 4.1

5.1

6.1* 8.1* >10.00 Sector <0.50 1. 0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 0 7 13 15 16 10 10 22 9 6 108 NNE 0 0 8 11 22 18 12 6 21 12 2 112 NE 0 1 10 20 33 38 25 15 36 19 3 200 ENE 0 0 3 12 45 48 40 23 17 6 8 202 E 0 1 0 10 19 20 44 53 62 4 0 213 ESE 0 2 3 0 15 15 17 19 19 6 0 96 SE 0 0 0 4 19 18 39 37 35 14 4 170 SSE 0 0 1 3 5 11 18 26 64 72 76 276 s 1 0 1 5 26 19 24 27 50 20 34 207 SSW 0 1 2 4 15 13 15 26 31 4 2 113 SW 0 1 1 5 13 18 34 46 72 33 7 230 WSW 0 1 1 1 9 11 33 49 113 108 139 465 w 0 1 1 3 8 7 13 39 93 84 230 479 WNW 0 1 1 3 11 15 19 25 64 78 225 442 NW 0 1 3 9 12 8 13 8 48 42 141 285 NNW 0 1 2 7 21 10 24 20 20 17 20 142 Tot 1 11 44 110 288 285 380 429 767 528 897 3740 Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data . 3740 Hours of Missing Data 60 Hours in Period . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan - Dec for years 2019

2019 Stability Cl ass E Sl ightl y Stable based on Lapse Rate Elevations:: Winds 250ft Stability 250ft Wind Wind Speed Range (m/s)

Direction 0.5- 1.1* 1.6* 2.1* 3.1* 4.1* 5.1

6.1

8.1* >10 .00 Sector <0.50 1.0 l. 5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 2 5 7 8 3 1 1 1 2 2 32 NNE 0 4 2 1 16 5 5 1 3 3 0 40 NE 0 3 6 5 15 12 6 4 2 3 4 60 ENE 0 2 11 15 44 25 19 13 4 1 0 134 E 0 1 8 13 36 16 35 33 16 1 0 159 ESE 0 2 5 7 11 10 14 17 23 1 0 90 SE 0 0 5 1 4 17 20 13 33 6 1 100 SSE 0 1 2 2 9 13 10 26 70 54 59 246 s 0 1 0 0 5 8 9 34 79 83 57 276 SSW 0 5 4 2 6 7 17 28 76 71 13 229 SW 0 0 4 5 8 18 17 56 133 48 10 299 WSW 0 1 4 4 15 17 16 45 113 43 15 273 w 0 2 4 3 16 28 24 40 60 35 27 239 WNW 0 4 2 1 25 33 20 24 55 58 101 323 NW 0 2 5 6 14 18 10 6 13 19 10 103 NNW 0 2 4 5 13 6 6 4 8 3 0 51 Tot 0 32 71 77 245 236 229 345 689 431 299 2654 Hours of Calm 1 Hours of Variable Direction 0 Hours of Valid Data . 2655 Hours of Hissing Data 60 Hours in Period . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan

Dec for years 2019

2019 Stability Cl ass F Moderately Stable based on Lapse Rate Elevations:: Winds 250ft Stability 250ft Wind Wind Speed Range (m/s)

Direction 0.5* 1.1* 1.6* 2.1* 3.1* 4.1* 5.1* 6.1* 8.1* >10 .00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 0 4- 4 5 2 1 1 0 2 0 19 NNE 0 1 1 3 4 2 1 1 1 1 1 16 NE 0 2 2 7 11 8 7 0 1 0 1 39 ENE 0 5 6 6 8 14 10 4 4 0 1 58 E 1 3 5 8 23 14 15 5 6 0 0 80 ESE 0 2 2 4 12 8 9 10 10 1 0 58 SE 0 2 0 2 3 6 5 8 13 4 0 43 SSE 0 1 2 1 3 4 2 5 19 16 2 55 s 0 0 0 1 2 6 4- 6 13 19 1 52 SSW 0 1 0 3 5 3 6 4 25 35 3 85 SW 0 2 1 4 2 4 11 17 50 8 0 99 WSW 0 0 2 3 2 5 22 34 43 0 0 111 w 0 1 3 2 8 16 16 21 28 3 1 99 WNW 0 1 0 3 10 18 13 5 15 16 25 106 NW 0 1 0 5 8 0 4 2 0 2 1 23 NNW 0 1 2 6 14- 5 1 0 0 1 0 30 Tot 1 23 30 62 120 115 127 123 228 108 36 973 Hours of Calm 3 Hours of Variable Direction 0 Hours of Valid Data . 976 Hours of Missing Data 60 Hours in Period . . . 8760

Joint Frequency Distribution Site:: Ginna Primary Period:: Months Jan

Dec for years 2019

2019 Stability Cl ass G Extremely Stable based on Lapse Rate Elevations: : Winds 250ft Stability 250ft Wind Wind Speed Range Cm/s)

Direction 0.5* 1.1* 1.6- 2.1* 3.1* 4.1* 5.1* 6.1* 8.1* >10.00 Sector <0.50 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 Total N 0 5 2 3 3 2 0 0 0 0 0 15 NNE 0 0 2 2 4 1 0 0 0 0 0 9 NE 0 3 1 2 3 3 1 2 0 0 0 15 ENE 2 2 4 5 10 6 1 1 0 1 0 32 E 0 1 4 4 13 11 7 6 1 0 0 47 ESE 2 1 l 7 10 7 8 11 4 0 0 51 SE 0 l 2 2 5 7 11 6 9 1 0 44 SSE 0 l 0 1 2 6 9 6 10 7 0 42 s 0 0 1 2 5 2 8 5 12 6 0 41 SSW 0 1 2 1 3 6 3 9 15 15 2 57 SW 0 0 0 2 3 4 5 12 24 3 0 53 WSW 0 4 3 4 9 7 14 9 7 0 0 57 w 0 0 2 1 12 17 14 12 10 1 0 69 WNW 0 1 4 3 9 4 4 6 3 2 7 43 NW 0 2 0 4 9 6 2 0 1 2 5 31 NNW 0 1 3 2 3 1 0 1 0 0 0 11 Tot 4 23 31 45 103 90 87 86 96 38 14 617 Hours of Calm .. 1 Hours of Variable Direction 0 Hours of Valid Data . . 618 Hours of Hissing Data. 60 Hours in Period . . . . 8760

CY-GI-170-300 Revision 36 Page 1 of 120 OFFSITE DOSE CALCULATION MANUAL (ODCM)

R.E. GINNA NUCLEAR POWER PLANT No document summarizing changes is included, because there have been no ODCM changes since the last annual submittal.

TABLE OF CONTENTS 1.0 Operability and Surveillance Requirements .................................................................... 4 2.0 Definitions .......................................................................................................................... 5 3.0 List of Acronyms ............................................................................................................. 10 4.0 RADIOACTIVE LIQUID EFFLUENTS ............................................................................... 12 4.1 Concentration (10 CFR 20) ....................................................................................... 12 4.2 Dose (10 CFR 50 Appendix I) ................................................................................... 14 4.3 Total Dose (40 CFR 190) .......................................................................................... 16 4.4 Liquid Effluents Release Points ................................................................................. 22 4.5 Liquid Effluents Monitor Setpoints ............................................................................. 23 4.6 Liquid Effluent Release Concentrations..................................................................... 26 4.7 Liquid Effluent Dose .................................................................................................. 27 5.0 RADIOACTIVE GASEOUS EFFLUENTS.......................................................................... 31 5.1 DELETED ................................................................................................................. 31 5.2 Dose Rate ................................................................................................................. 32 5.3 Dose (10 CFR 50, Appendix I) .................................................................................. 34 5.4 Total Dose (40 CFR 190) .......................................................................................... 38 5.5 Gaseous Effluent Release Points .............................................................................. 43 5.6 Gaseous Effluent Monitor Setpoints .......................................................................... 44 5.7 Gaseous Effluent Dose Rate ..................................................................................... 50 5.8 Gaseous Effluent Doses............................................................................................ 52 6.0 RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION.................................... 58 6.1 Liquid Effluent Monitors ............................................................................................. 58 6.2 Gaseous Effluent Monitors ........................................................................................ 64 6.3 Radiation Accident Monitoring Instrumentation ......................................................... 71 6.4 Area Radiation Monitors ............................................................................................ 75 7.0 RADWASTE TREATMENT ............................................................................................... 77 7.1 Liquid Radwaste Treatment System .......................................................................... 77 7.2 Gaseous Radwaste Treatment System ..................................................................... 80 7.3 Solid Radwaste System ............................................................................................ 83 7.4 Configuration Changes ............................................................................................. 84 7.5 Process Control Program .......................................................................................... 85

CY-GI-170-300 Revision 36 Page 2 of 120 8.0 RADIOLOGICAL ENVIRONMENTAL MONITORING ....................................................... 86 8.1 Monitoring Program................................................................................................... 86 8.2 Environmental Monitor Sample Locations ................................................................. 92 8.3 Land Use Census.................................................................................................... 110 8.4 Interlaboratory Comparison Program ...................................................................... 112 9.0 REPORTING REQUIREMENTS ...................................................................................... 113 9.1 Annual Radiological Environmental Operating Report ............................................. 113 9.2 Annual Radioactive Effluent Release Report ........................................................... 115 9.3 Special Reports ....................................................................................................... 117

10.0 REFERENCES

................................................................................................................ 119

CY-GI-170-300 Revision 36 Page 3 of 120 FIGURES Figure 7-1 Liquid Radwaste Treatment Systems Effluent Paths and Controls ...................... 79 Figure 7-2 Gaseous Radwaste Treatment Systems Effluent Paths and Controls ................. 82 Figure 8-1 Location of Onsite Air Monitors and Dosimeters ................................................. 96 Figure 8-2 Location of Farms for Milk Samples and Ontario Water District Intake ................ 97 Figure 8-3 Location of Offsite Dosimeters............................................................................ 98 Figure 8-4 Location of Offsite Air Monitors ........................................................................... 99 TABLES Table 4-1 Radioactive Liquid Waste Sampling and Analysis Program ................................ 18 Table 5-1 Radioactive Gaseous Waste Sampling and Analysis Program............................ 40 Table 5-2 Meteorological Data and Locations of Receptors for Set point Calculations ........ 48 Table 5-3 Dose Factors to the Child for Noble Gases and Daughters ................................. 55 Table 5-4 Dose Parameters for Radionuclides and Radioactive Particulate, Gaseous Effluents ............................................................................................................. 56 Table 5-5 Pathway Dose Factors Due to Radionuclides Other Than Noble Gases ............. 57 Table 6.1-1 Radioactive Liquid Effluent Monitoring Instrumentation ....................................... 60 Table 6.1-2 Radioactive Liquid Effluent Monitoring SURVEILLANCE REQUIREMENTS ....... 62 Table 6.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation .................................. 66 Table 6.2-2 Radioactive Gaseous Effluent Monitoring SURVEILLANCE REQUIREMENTS .. 69 Table 6.3-1 Radiation Accident Monitoring Instrumentation ................................................... 72 Table 6.3-2 Radiation Accident Monitoring SURVEILLANCE REQUIREMENTS ................... 74 Table 6-4 Area Radiation Monitor SURVEILLANCE REQUIREMENTS .............................. 76 Table 8-1 Radiological Environmental Monitoring Program ................................................ 88 Table 8-2 Location, Direction, and Distances to Sample Points .......................................... 93 Table 8-3 Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) ............................................................................................... 100 Table 8-4 Reporting Levels for Radioactivity Concentrations in Environmental Samples .. 102 Table 8-5 D/Q and X/Q 5 year Average 2011-2015 Plant Vent ......................................... 104 Table 8-6 D/Q and X/Q 5 year Average 2011-2015 Containment Vent ............................. 106 Table 8-7 D/Q and X/Q 5 year Average 2011-2015 Air Ejector Vent ................................. 108 Table 9-1 Radiological Environmental Monitoring Program Summary .............................. 118

CY-GI-170-300 Revision 36 Page 4 of 120 1.0 OPERABILITY and SURVEILLANCE REQUIREMENTS The OPERABILITY requirements in this manual follow the same LCO applicabilities as the Improved Technical Specifications with the exception of:

a. LCO 3.0.3 which relates to the failure to meet a Required Action and the associated plant shutdown actions;

b. LCO 3.0.4 which relates to changing MODES with inoperable equipment; and

c. LCO 3.0.6 which deals solely with ITS LCOs on support/supported system inoperabilities.

The failure to meet any Required Action for which no additional ACTIONS are provided shall result in continued efforts to meet the specified Required Action. A plant shutdown to exit the MODE of Applicability is not required unless directed by plant management.

This does not endorse the practice of failing to meet specified Required Actions.

The SURVEILLANCE REQUIREMENTS in this manual follow the same SR applicabilities as the Improved Technical Specifications with the exception of:

a. SR 3.0.4 which relates to changing MODES with incomplete surveillances.

CY-GI-170-300 Revision 36 Page 5 of 120 2.0 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout these controls. Terms used in these controls and not defined herein have the same definition as listed in the Technical Specifications and/or the Technical Requirements Manual. If a conflict in definition exists, the definition in the Technical Specifications takes precedence.

2.1 ACTION ACTION shall be that part of a Control that prescribes required actions to be taken under designated conditions, within specified completion times.

2.2 CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock display, and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

2.3 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.

2.4 DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microCurie/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 thyroid dose conversion factors used for this calculation shall be those listed in ICRP 30, Supplement to Part 1, Pages 192-212, table entitled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity" (Reference 10).

2.5 FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined as follows:

CY-GI-170-300 Revision 36 Page 6 of 120 NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 184 days R At least once per 18 months S/U Prior to each reactor startup N/A Not applicable P Completed prior to each release 6Y At least once per 6 years 2.6 FUNCTIONAL TEST A FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY of alarm, interlock display and/or trip functions. The FUNCTIONAL TEST shall include adjustments, as necessary, of the alarm, interlock display and/or Trip Setpoints such that the setpoints are within the required range and accuracy.

2.7 LOWER LIMIT OF DETECTION The LOWER LIMIT OF DETECTION (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. The LLD is defined as a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement, the minimum detectable activity (MDA).

2.8 MEMBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, 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.

2.9 OFFSITE DOSE CALCULATION MANUAL The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting

CY-GI-170-300 Revision 36 Page 7 of 120 from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program (REMP). The ODCM shall also contain descriptions of the Radioactive Effluent Controls and Radiological Environmental Monitoring Program and descriptions of the information that shall be included in the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report, as required by Technical Specification 5.5.1.

2.10 OPERABLE - OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s) and when all necessary attendant instrumentation, controls, electric power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component , or device to perform its function(s) are also capable of performing their related support function(s).

2.11 OPERATIONAL MODE - MODE An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.1-1 of Technical Specifications.

2.12 PURGE - PURGING PURGE or PURGING shall be any 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 required to purify the confinement.

2.13 RATED THERMAL POWER (RTP)

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 1775 MWt.

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

2.15 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.

CY-GI-170-300 Revision 36 Page 8 of 120 2.16 SURVEILLANCE REQUIREMENT SURVEILLANCE REQUIREMENTS shall be met during the OPERATIONAL MODES or other conditions specified for individual CONTROLS unless otherwise stated in an individual SURVEILLANCE REQUIREMENT. Each SURVEILLANCE REQUIREMENT shall be performed within the specified time interval with:

1. A maximum allowable extension not to exceed 25% of the surveillance interval, but

2. The combined time interval for any three consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval.

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

2.18 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 or for industrial, commercial, institutional, and/or recreational purposes.

2.19 VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT SYSTEM shall be 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 HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

2.20 VENTING VENTING shall be 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.

CY-GI-170-300 Revision 36 Page 9 of 120 2.21 WASTE GAS HOLDUP SYSTEM A WASTE GAS HOLDUP SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System offgases and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

CY-GI-170-300 Revision 36 Page 10 of 120 3.0 LIST OF ACRONYMS D Frequency Notation noting a surveillance frequency requirement of at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

D/Q Deposition parameter E East ENE East-Northeast ESE East-Southeast HCWT High Conductivity Waste Tank ICRP International Commission on Radiological Protection LLD Lower Limit of Detection M Frequency Notation noting a surveillance frequency requirement at least once per 31 days.

MDA Minimum Detectable Activity N North N.A. Not Applicable N/A Not Applicable NE Northeast NIST National Institute for Standards and Technology NNE North-Northeast NNW North-Northwest NW Northwest ODCM Offsite Dose Calculation Manual P Frequency Notation noting a surveillance frequency requirement of being performed prior to each release.

PCP Process Control Program Q Frequency Notation noting a surveillance frequency requirement at least once per 92 days.

R Frequency Notation noting a surveillance frequency requirement at least once per 18 months.

CY-GI-170-300 Revision 36 Page 11 of 120 REMP Radiological Environmental Monitoring Program RTP Rated Thermal Power SA Frequency Notation noting a surveillance frequency requirement at least once 184 days.

SE Southeast S Frequency Notation noting a surveillance frequency requirement of at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

S South SSE South-Southeast SSW South-Southwest S/U Frequency Notation noting a surveillance frequency requirement of being performed prior to SW Southwest W Frequency Notation noting a surveillance frequency requirement at least once per 7 days.

W West WNW West-Northwest WSW West-Southwest X/Q Dispersion parameter 6Y At least once per 6 years.

CY-GI-170-300 Revision 36 Page 12 of 120 4.0 RADIOACTIVE LIQUID EFFLUENTS 4.1 CONCENTRATION (10 CFR 20)

4.1.1 CONTROLS

1. The release of radioactive liquid effluents shall be such that the concentration in the circulating water discharge does not exceed ten times the concentration values specified in Appendix B, Table 2, Column 2 to 10 CFR Part 20.1001 -

20.2402. For dissolved or entrained noble gases, the total activity due to dissolved or entrained noble gases shall not exceed 2.0E-04 µCi/ml.

4.1.2 APPLICABILITY

At all times.

4.1.3 ACTION

If the concentration of radioactive material in the circulating water discharge exceeds ten times the concentration values of Appendix B, Table 2, Column 2 of 10 CFR 20, measures shall be initiated to restore the concentration to within these limits immediately.

4.1.4 ACTION

If the concentration when averaged over one hour exceeds ten times the applicable concentrations specified in Appendix B of 10CFR Part 20, Table 2, Column 2, at the point of entry to receiving waters, submit to the commission a special report within 30 days.

4.1.5 SURVEILLANCE REQUIREMENTS:

1. Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4-1. The results of pre-release analyses shall be used with the calculational methods in Section 4.6 to assure that the concentration at the point of release is limited to the values in Section 4.1.1 (Radioactive Liquid Effluents - Controls).

4.1.6 BASES

This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR 50, to a MEMBER OF THE PUBLIC, and (2) the limits of Appendix B, 10 CFR 20, to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air

CY-GI-170-300 Revision 36 Page 13 of 120 (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP)

Publication 2.

CY-GI-170-300 Revision 36 Page 14 of 120 4.2 DOSE (10 CFR 50 APPENDIX I)

4.2.1 CONTROLS

1. 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 1.5 mrem to the total body and to 5 mrem to any organ, and B. during any calendar year to 3 mrem to the total body and to 10 mrem to any organ.

4.2.2 APPLICABILITY

At all times.

4.2.3 ACTION

Whenever the calculated dose resulting from the release of radioactive materials in liquid effluents exceeds any of the above limits, a Special Report shall be submitted to the Commission within thirty days which includes the following information:

1. identification of the cause for exceeding the dose limit;

2. corrective actions taken and/or to be taken to reduce the releases of radioactive material in liquid effluents to assure that subsequent releases will remain within the above limits;

3. The results of the radiological analyses of the nearest public drinking water source, and an evaluation of the radiological impact due to licensee releases on finished drinking water with regard to the requirements of 40 CFR 141, Safe Drinking Water Act.

4.2.4 ACTION

During any month when the calculated dose to a MEMBER OF THE PUBLIC exceeds 1/48 the annual limit (0.06 mrem to the total body or 0.2 mrem to any organ), projected cumulative dose contributions from liquid effluents shall be determined for that month and at least once every 31 days for the next 3 months.

4.2.5 SURVEILLANCE REQUIREMENTS:

Post-release analyses of samples composited from batch releases shall be performed in accordance with Table 4-1. The results of the post-release analyses shall be used with the calculational methods in Section 1.6 to assure that the dose commitments from liquids are limited to the values in Section 4.2.1 (Dose -

Controls).

CY-GI-170-300 Revision 36 Page 15 of 120

4.2.6 BASES

This control is provided to implement the requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR 50. This control implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as reasonably achievable". Also, with Lake Ontario drinking water supplies potentially affected by plant operations, there is reasonable assurance that the operation of the plant will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational models and data, such that the actual exposure of a MEMBER OF THE PUBLIC appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I",

Revision 1, October 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I", April 1977.

CY-GI-170-300 Revision 36 Page 16 of 120 4.3 TOTAL DOSE (40 CFR PART 190)

4.3.1 CONTROLS

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

4.3.2 APPLICABILITY

At all times.

4.3.3 ACTION

With the calculated doses from the release of radioactive materials in liquid effluents exceeding twice the limits of Section 4.2.1 (Dose - Controls), prepare and submit to the Commission within 30 days a Special Report that defines the corrective actions to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and include scheduling for achieving conformance with the above limits. Calculations which include direct radiation contributions from the unit and from any radwaste storage shall be performed to determine total dose to a member of the public. This Special Report, as defined in 10 CFR 20.405(c) 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 releases 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 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

4.3.4 SURVEILLANCE REQUIREMENTS:

1. Cumulative dose contributions from liquid and gaseous effluents for the current calendar quarter and the current calendar year shall be determined in accordance with SURVEILLANCE REQUIREMENT S.1.2.1 at least once every 31 days, in accordance with the methodology and parameters of Section 1.7 of the ODCM.

2. Cumulative dose contributions from direct radiation from the unit and from radwaste storage shall be determined from environmental dosimeter data at least quarterly.

4.3.5 BASES

CY-GI-170-300 Revision 36 Page 17 of 120 This control is provided to meet the dose limitations of 40 CFR 190 that have been incorporated into 10 CFR 20 by 46FR18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. It is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the plant remains within twice the dose design objectives of Appendix I, and if direct radiation doses are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose contributions from other uranium fuel cycle sources is negligible. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance, (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR 20, as addressed in Section 4.1.1 (Radioactive Liquid Effluents - Controls) and Section 5.2.1 (Dose Rate - Controls). An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

CY-GI-170-300 Revision 36 Page 18 of 120 Table 4-1 Radioactive Liquid Waste Sampling and Analysis Program Liquid Sampling Minimum Type of Activity Lower Release Frequency Analysis Analysis Limit of Type Frequency Detection (LLD)

(µCi/ml) (a)

Batch Release (b)

P P Principal Gamma 5.0E-07 Each Batch Each Batch and I-131 Emitters (d) 1.0E-06 P M Dissolved and 1.0E-05 One Batch/M Entrained Gases Batch Waste (Gamma Emitters)

Release P M H-3 1.0E-05 Tanks Each Batch Composite (c) Gross Alpha 1.0E-07 P Q Sr-89 Sr-90 5.0E-08 Each Batch Composite (c) Fe-55 1.0E-06 Continuous Release (e)

Continuous W Principal Gamma 5.0E-07 (e) Composite (c) and I-131 Emitters (d) 1.0E-06 Continuous W Dissolved and 1.0E-05 (e) Composite (c) Entrained Gasses (Gamma Emitters)

Retention Tank Continuous M H-3 1.0E-05 (e) Composite (c) Gross Alpha 1.0E-07 Continuous Q Sr-89 Sr-90 5.0E-08 (e) Composite (c) Fe-55 1.0E-06 M or S M or S Principal Gamma 5.0E-07 Grab (f) Grab (f) and I-131 Emitters (d) 1.0E-06 Service (f) (f) Dissolved and 1.0E-05 Water Entrained Gasses (CV Fan (Gamma Emitters)

Cooler and SFP Hx (f) (f) H-3 1.0E-05 lines)

Gross Alpha 1.0E-07 (f) (f) Sr-89 Sr-90 Fe-55 5.0E-08 1.0E-06

CY-GI-170-300 Revision 36 Page 19 of 120 Table 4-1 Table Notation (a) 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. 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, the minimum detectable activity (MDA).

For a particular measurement system (which may include radiochemical separation):

Where:

LLD = the lower limit of detection as defined above as µCi per unit mass or volume Sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate as counts per disintegration V = the sample size in units of mass or volume E = the counting efficiency Y = the fractional radiochemical yield when applicable 2.22E+06 is the number of disintegrations per minute per µCi

= the decay constant t = the time elapsed since sample time The value of Sb used in the calculation of the LLD for a particular measurement system shall be based on the actual observed variance of the background counting rate or the counting rate of the blank samples, as appropriate, rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contribution of other radionuclides normally present in the samples. Typical values of E, V, and Y should be used in the calculation.

CY-GI-170-300 Revision 36 Page 20 of 120 The background count rate is calculated from the background counts that are determined to be within +/- one FWHM energy band about the energy of the gamma ray peak used for the quantitative analysis for this radionuclide.

(b) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analysis, each batch shall be isolated then thoroughly mixed according to the following:

A & B Monitor Tanks shall be mixed by recirculating for at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

The High Conductivity Waste Tank (HCWT) shall be mixed by running the pump and air blower for at least 10 minutes. HCWT isolation does not include periodic pumpdown of the AVT sample sink sump.

Steam Generator batch releases during shutdown cannot be adequately mixed by recirculating. A sample shall be taken during mid-release and analyzed.

The outside Condensate Storage Tank cannot be adequately mixed by recirculating. A sample shall be taken during mid-release and analyzed.

The sludge lance trailer shall be mixed by recirculating for at least 30 minutes.

(c) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

Decay corrections are calculated from the midpoint of the sampling period.

(d) The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:

Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, Cs-137 and Ce-141 (Ce-141 shall be measured to a LLD of 5.0E-06).

This list does not mean that only these nuclides are to be detected and reported.

Other nuclides which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should be reported as less than the LLD and should not be reported as being present at the LLD level. The less than values should not be used in the required dose calculations.

(e) A continuous release is the discharge of liquid wastes of a non-discrete volume; e.g., from a volume or system that has an input flow during the continuous release. Decay corrections will be calculated based on all samples collected during the release.

CY-GI-170-300 Revision 36 Page 21 of 120 (f) Service water samples shall be taken and analyzed once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months if alarm setpoint is reached on continuous monitor. Service water sample frequency for H-3, gross alpha, Sr-89, Sr-90, and Fe-55 will be increased to produce a composite whenever principal gamma emitters are detected. The analysis frequency will be monthly for H-3 and gross alpha, and quarterly for Sr-89, Sr-90, and Fe-55 whenever principal gamma emitters are detected.

CY-GI-170-300 Revision 36 Page 22 of 120 4.4 LIQUID EFFLUENTS RELEASE POINTS There are three normal release points for liquid radioactive effluents from the plant that empty into the discharge canal. These are the Radwaste Treatment Discharge, Retention Tank discharge and the All Volatile Treatment Discharge.

Each of these is a monitored release line that can be isolated before the release reaches the discharge canal. There is also a release point for the service water lines used for cooling the heat exchangers that is a monitored release line but is not isolatable. If there is an alarm on the service water monitor, it is necessary to sample each heat exchanger separately to determine which has a leak and then isolate the affected heat exchanger. The pressure of the service water system flow would normally force water from the clean service water side into the contaminated side of the heat exchanger. Dilution of liquid effluent is provided by the discharge canal. The discharge canal flow is nominally 1.7E+05 gpm for each circulating water pump. During operating periods, two circulating water pumps are in operation. During shutdown periods, one circulating water pump is operated. If neither circulating water pump is operable, dilution is provided by operation of one to three service water pumps which provide nominally 5.3E+03 gpm each.

CY-GI-170-300 Revision 36 Page 23 of 120 4.5 LIQUID EFFLUENTS MONITOR SETPOINTS Alarm and/or trip setpoints for radiation monitors on each liquid effluent line are required. Precautions, limitations and setpoints applicable to the operation of Ginna Station liquid effluent monitors are provided in plant procedure P-9 RADIATION MONITORING SYSTEM. Setpoint values are calculated to assure that alarm and trip actions occur prior to exceeding ten times the effluent concentration of Appendix B, Table 2, Column 2 of 10 CFR 20.1001 - 20.2402 at the release point to the unrestricted area. For added conservatism, liquid effluent release rates are administratively set so that only fractions of the applicable maximum effluent concentrations can be reached in the discharge canal.

The Calculated alarm and trip action setpoints for each radioactive liquid effluent line monitor and flow determination must satisfy the following equation:

Equation (1)

Where:

C = the effluent concentration which implements ten times 10 CFR 20 limit for unrestricted areas, in µCi/ml.

c = the setpoint of the radioactivity monitor measuring the radioactivity concentration in the discharge line prior to dilution and subsequent release, in µCi/ml.

F = the dilution water flow as determined prior to the release point, in volume per unit time.

f = the liquid waste flow as measured at the discharge point, in volume per unit time, in the same units as F.

Liquid effluent batch releases from Ginna Station are discharged through a liquid waste disposal monitor. The liquid waste stream (f) is diluted by (F) in the plant discharge canal before it enters Lake Ontario.

CY-GI-170-300 Revision 36 Page 24 of 120 The limiting batch release concentration (c) corresponding to the liquid waste monitor setpoint is calculated from the above expression. Since the value of (f) is very small in comparison to (F), and tritium cannot be accounted for, the expression becomes:

Equation (2)

Where:

C = 10 x the allowable concentration of Cs-137 as given in Appendix B, Table 2, Column 2 of 10 CFR 20, 1 x 10-5. This value is normally more restrictive than the calculated mixed isotopic release concentration. A weighted average, excluding Sb-125, from 1998 data indicated a release concentration of 1.15 x 10-5 µCi/ml. (See DA-RP-99-078). This should be reviewed as an annual basis, and the more conservative value between the two be utilized.

F = the dilution flow assuming operation of only 1 circulating water pump (170,000 gpm).

c = the limiting batch release concentration corresponding to the liquid monitor setpoint f = the maximum waste effluent discharge rate through the designated pathway.

0.4 = a conservatism based on the possibility of 2 liquid discharges occurring simultaneously, minus 0.2 (Total Instrumental Uncertainty) eg: (limit - 0.2 TIU/2)

TCF = the Tritium Correction Factor, based on the maximum concentration of diluted RCS H-3, divided by H-3 E.C.L. The maximum UFSAR RCS tritium concentration is 3.5 µCi/ml. The monitor setpoint against gamma emitters must be reduced proportional to the ratio of tritium in the waste stream, to which the monitor will not respond.

CY-GI-170-300 Revision 36 Page 25 of 120 The limiting release concentration (c) is then converted to a set-point count rate by the use of the monitor calibration factor determined per the individual monitor calibration procedure. The expression becomes:

Equation (3)

Example (Liquid Radwaste Monitor R-18):

Assuming, for example, that the maximum pump effluent discharge rate (f) is 90 gpm and the RCS tritium concentration is 3 µCi/ml, then the limiting batch release concentration (c) would be determined as follows:

The monitor R-18 alarm and trip setpoint (in cpm) is then determined utilizing the monitor calibration factor calculated in plant procedure CPI-MON-R18. Assuming a calibration factor of and a limiting batch release concentration determined above, the alarm and trip setpoint for monitor R-18 would be:

The setpoint values for the containment Fan Cooler monitor (R-16), Spent Fuel Pit Heat Exchanger Service Water Monitors (R-20A and R-20B), Steam Generator Blowdown Monitor (R-19), the Retention Tank Monitor (R-21, and the All volatile Treatment Waste Discharge Monitor (R-22) are calculated in a similar manner using equation (2),

substituting appropriate values of (f) and the corresponding calibration factor.

Effluent Monitor Warning alarm setpoints are set at one-half of the trip setpoint.

With all calculations equal this is a warning that 20% of the release limit has been reached at a single release point.

CY-GI-170-300 Revision 36 Page 26 of 120 4.6 LIQUID EFFLUENT RELEASE CONCENTRATIONS Liquid batch releases are controlled individually and each batch release is authorized based upon sample analysis and the existing dilution flow in the discharge canal. Plant procedures establish the methods for sampling and analysis of each batch prior to release. A release rate limit is calculated for each batch based upon analysis, dilution flow and all procedural conditions being met before it is authorized for release. The waste effluent stream entering the discharge canal is continuously monitored and the release will be automatically terminated if the preselected monitor setpoint is exceeded. A release may continue subject to grab sample analysis and monitoring in accordance with Table 6.1-1.

The equation used to calculate activity is:

Gamma Spectroscopy Equation (4)

CY-GI-170-300 Revision 36 Page 27 of 120 4.7 LIQUID EFFLUENT DOSE The dose contribution received by the maximally exposed individual from the ingestion of Lake Ontario fish and drinking water is determined using the following methodology. These calculations will assume a near field dilution factor of 1.0 in evaluating the fish pathway dose, and an average annual dilution factor of 200 between the plant discharge and the Ontario Water District drinking water intake located approximately 2220 meters northeast (53 degrees) of the discharge canal. The average annual dilution factor of 200 was derived from the drift and dispersion study documented in reference 10.4.

Dose contributions from shoreline recreation, boating and swimming have been shown to be negligible in the Appendix I dose analysis, reference 10.5, and do not need to be routinely evaluated. Shoreline sediment samples downstream from the plant will be collected at least semi-annually for the Radiological Environmental Monitoring Program, as a conservatism. Presence of radioactivity above background will result in calculation of dose contribution from these pathways.

There is no known human consumption of shellfish from Lake Ontario; therefore, this pathway is not taken into consideration in dose calculations.

The dose contribution to an individual will be determined to ensure that it complies with the specification of Section 4.2.1 (Dose - Controls). Offsite receptor doses will be determined for the limiting age group and organ, unless census data show that actual offsite individuals are the limiting age group.

The following expression is used to calculate ingestion pathway dose contributions for the total release period from all radionuclides identified in liquid effluents released to unrestricted areas:

Equation (5)

Where:

D = the cumulative dose commitment to the total body or any organ, t, from the liquid effluents for the summation of the total time period in mrem.

tj = the length of the jth time period over which Cij and Fj are averaged for all liquid releases in hours.

CY-GI-170-300 Revision 36 Page 28 of 120 Cij = the average concentration of radionuclide i in undiluted liquid effluent during time period tj from any liquid release in µCi/ml.

Ai = the site-related ingestion dose commitment factor to the total body or any organ,, for each identified principal gamma and beta emitter in mrem/hr per µCi/ml. See equation (6).

Fj = the discharge canal dilution factor for Cij during any liquid effluent release, defined as the ratio of the maximum undiluted liquid waste flow during release to unrestricted receiving waters. The dilution factor will depend on the number of circulation pumps operating and, during icing conditions, the percentage opening of the recirculating gate. Reference curves are presented in plant procedure CH-RETS-LIQ-RELEASE.

Equation (6)

Where:

Ai = the site-related ingestion dose commitment factor to the total body or to any organ, , for each identified principal gamma and beta emitter in mrem/hr per µCi/ml.

ko = the units conversion factor, 1.14E+05 = 1.0E+06 pCi/µCi x 1.0E+03 ml/kg 8760 hr/yr Uw = a receptor person's water consumption by age group from Table E-5 of Regulatory Guide 1.109 Dw = the dilution factor from the near field area of the release point to potable water intake. The site specific dilution factor is 200. This factor is 1.0 for the fish ingestion pathway.

UF = a receptor person's fish consumption by age group from Table E-5 of Regulatory Guide 1.109 BFi = a bioaccumulation factor for nuclide, i, in fish in pCi/kg per pCi/L, from Table A-1 of Regulatory Guide 1.109

CY-GI-170-300 Revision 36 Page 29 of 120 DFi is the dose conversion factor for the ingestion of nuclide, i, for a receptor person in pre-selected organ, t, in mrem/pCi, from Tables E-11, E-12, E-13, E-14 of Regulatory Guide 1.109 The monthly dose contribution from releases for which radionuclide concentrations are determined by periodic composite sample analysis may be approximated by assuming an average monthly concentration based on the previous monthly or quarterly composite analysis. However, in the Annual Radioactive Effluent Release Report the calculated dose contributions from these radionuclides shall be based on the actual composite analysis.

Example:

Computing the dose to the whole body via the fish and drinking water pathways, assuming an initial Cs-137 discharge concentration of 3.0E-04 µCi/ml:

Given the following discharge factors for example, where:

ti = 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the duration of the release Cij = 3.0E-04 µCi/ml Fj = liquid waste flow = 20 gpm = 1.2E-04 (dilution flow)(z) 170,000 gpm z = Near field dilution = 1.0 for Ginna Dw = 200 and, taking the following values from Regulatory Guide 1.109 which concern the critical receptor, which is considered to be the child in this case:

UW = 510 l/year UF = 6.9 kg/year BFi = 2000 pCi/kg per pCi/l DFi = 4.62E-05 mrem/pCi Then, the site-related ingestion dose commitment factor, Ai, is calculated as follows:

CY-GI-170-300 Revision 36 Page 30 of 120 And, the whole body dose to the child is then:

The dose contribution from any other isotopes would then need to be calculated and all the isotopic contributions summed.

CY-GI-170-300 Revision 36 Page 31 of 120 5.0 RADIOACTIVE GASEOUS EFFLUENTS 5.1 DELETED

CY-GI-170-300 Revision 36 Page 32 of 120 5.2 DOSE RATE 5.2.1 CONTROLS The instantaneous dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY shall be limited to the following values:

1. The dose rate for noble gases shall be 500 mrem/yr to the total body and 3000 mrem/yr to the skin, and

2. The dose rate for I-131, I-133, tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days shall be 1500 mrem/yr to any organ.

5.2.2 APPLICABILITY

At all times.

Note: For unplanned release of gaseous wastes, compliance with Section 5.2.1 (Dose Rate - Controls) may be calculated using annual average X/Q.

Compliance with Section 5.2.1 (Dose Rate - Controls) shall be determined by considering the applicable ventilation system flow rates. These flow rates shall be determined at the frequency required by Table 6.2-2.

5.2.3 ACTION

If the calculated dose rate of radioactive materials released in gaseous effluents from the site exceeds the limits of Section 5.2.1 (Dose Rate - Controls), measures shall be initiated to restore releases to within limits. The effluent continuous monitors listed in Table 6.2-1 that have provisions for the automatic termination of gas decay tank, shutdown purge or mini-purge releases, shall be used to limit releases within the values established in Section 5.2.1 (Dose Rate - Controls) when monitor setpoint values are exceeded.

5.2.4 SURVEILLANCE REQUIREMENTS:

1. The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters of Section 5.7 of the ODCM.

2. The dose rate due to radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters of Section 5.7 of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 5-1.

CY-GI-170-300 Revision 36 Page 33 of 120

5.2.5 BASES

This control is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents will be within the annual dose limits of 10 CFR 20, Appendix B, Table 2, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10 CFR 20. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/year to the whole body or to less than or equal to 3000 mrems/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year.

CY-GI-170-300 Revision 36 Page 34 of 120 5.3 DOSE (10 CFR 50, Appendix I)

5.3.1 CONTROLS

The dose due to noble gases released in gaseous effluents to areas at or beyond the SITE BOUNDARY shall be limited to the following:

1. During any calendar quarter to 5 mrad for gamma radiation and to 10 mrad for beta radiation.

2. During any calendar year to 10 mrad for gamma radiation and to 20 mrad for beta radiation.

5.3.2 APPLICABILITY

At all times

5.3.3 ACTION

Whenever the calculated dose to a MEMBER OF THE PUBLIC resulting from noble gases exceeds the limits of Section 5.3.1 (Dose - Controls), a Special Report shall be submitted to the Commission within 30 days which includes the following information:

1. Identification of the cause for exceeding the dose limit.

2. Corrective actions taken and/or to be taken to reduce releases of radioactive material in gaseous effluents to assure that subsequent releases will be within the above limits.

5.3.4 ACTION

During any month when the calculated dose to a MEMBER OF THE PUBLIC exceeds 1/48th the annual limits of Section 5.3.1 (Dose - Controls), (0.2 mrad gamma or 0.4 mrad beta), projected cumulative dose contributions from gaseous effluents shall be determined for that month and at least once every 31 days for the next 3 months.

5.3.5 SURVEILLANCE REQUIREMENTS:

Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters of Section 2.8 of the ODCM at least once every 31 days.

5.3.6 BASES

This control is provided to implement the requirements of Sections II.B, III.A, and IV.A of Appendix I, 10 CFR 50. The control implements the guides set forth in Section I.B of Appendix I. The ACTION statements provide the required operating

CY-GI-170-300 Revision 36 Page 35 of 120 flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the release of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as reasonably achievable". The SURVEILLANCE REQUIREMENTS implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I", Revision I, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors",

Revision I, July 1977. The ODCM equations for determining air doses at the SITE BOUNDARY are based on historical average atmospheric conditions.

5.3.7 CONTROLS

The dose to a MEMBER OF THE PUBLIC from I-131, I-133, tritium, and for all radioactive materials in particulate form with half-lives greater than eight days released with gaseous effluents from the site shall be limited to the following:

1. during any calendar quarter to 7.5 mrem to any organ.

2. during any calendar year to 15 mrem to any organ.

5.3.8 APPLICABILITY

At all times.

5.3.9 ACTION

Whenever the calculated dose to a MEMBER OF THE PUBLIC resulting from radionuclides other than noble gases exceeds the limits of Section 5.3.7 (Controls),

a Special Report shall be submitted to the Commission within 30 days which includes the following information:

1. Identification of the cause for exceeding the dose limit.

2. Corrective actions taken and/or to be taken to reduce releases of radioactive material in gaseous effluents to assure that subsequent releases will be within the above limits.

5.3.10 ACTION:

During any month when the calculated dose to a MEMBER OF THE PUBLIC exceeds 1/48th the annual limit of Section 5.3.7 (Controls), (0.3 mrem), projected

CY-GI-170-300 Revision 36 Page 36 of 120 cumulative dose contributions from gaseous effluents shall be determined for that month and at least once every 31 days for the next 3 months.

5.3.11 SURVEILLANCE REQUIREMENTS Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with methodology and parameters of Section 5.8 of the ODCM at least once every 31 days.

5.3.12 BASES:

This control is provided to implement the requirements of Sections II.C, III.A, and IV.A of Appendix I, 10 CFR 50. The control implements the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the release of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as reasonably achievable". The SURVEILLANCE REQUIREMENTS implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of the subject materials in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I", Revision I, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors", Revision I, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the areas at or beyond the SITE BOUNDARY.

The pathways examined in development of the calculations were:

1. Individual inhalation of airborne radionuclides

2. Deposition of radionuclides onto green leafy vegetation with subsequent consumption by man

3. Deposition of radionuclides onto grassy areas where milk animals and meat producing animals graze, followed by human consumption of that milk and meat

CY-GI-170-300 Revision 36 Page 37 of 120

4. Deposition of radionuclides on the ground followed by subsequent human exposure

CY-GI-170-300 Revision 36 Page 38 of 120 5.4 TOTAL DOSE (40 CFR 190)

5.4.1 CONTROLS

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

5.4.2 APPLICABILITY

At all times.

5.4.3 ACTION

With the calculated doses from the release of radioactive materials in gaseous effluents exceeding twice the limits of Sections 5.3.1 and 5.3.7 (Controls), prepare and submit to the Commission within 30 days a Special Report that defines the corrective actions to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and include scheduling for achieving conformance with the above limits. Calculations which include direct radiation contributions from the unit and from any radwaste storage shall be performed to determine total dose to a MEMBER OF THE PUBLIC. This Special Report, as defined in 10 CFR 20.405(c) 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 releases 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 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190.

Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

5.4.4 ACTION

This report shall include an analysis which demonstrates that radiation exposure to all MEMBERS OF THE PUBLIC from the plant are less than the 40 CFR 190 limits.

Otherwise, the report shall request a variance from the commission to permit releases to exceed 40 CFR Part 190. Submittal of the report is considered a timely request by the NRC, and a variance is granted until staff action on the request is complete.

5.4.5 SURVEILLANCE REQUIREMENTS:

1. Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Sections 5.3.5 and 5.3.11 (Surveillance Requirements) at least once every 31 days, in accordance with the methodology and parameters of Section 2.8 of the ODCM.

CY-GI-170-300 Revision 36 Page 39 of 120

2. Cumulative dose contributions from direct radiation from the unit and from radwaste storage including ISFSI, shall be determined from environmental dosimeter data at least quarterly.

5.4.6 BASES

This control is provided to meet the dose limitations of 40 CFR 190 that have been incorporated into 10 CFR 20 by 46FR18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. It is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the plant remains within twice the dose design objectives of Appendix I, and if direct radiation doses are kept small.

Cumulative direct radiation dose from environmental dosimeters shall be used to ensure that dose limits of 10CFR72.104 are met. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose contributions from other uranium fuel cycle sources is negligible. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance, (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR 20, as addressed in Section 4.1.1 (Radioactive Liquid Effluents - Controls) and Section 5.2.1 (Dose Rate - Controls). An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

CY-GI-170-300 Revision 36 Page 40 of 120 Table 5-1 Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Sampling Minimum Type of Activity Lower Limit of Release Type Frequency Analysis Analysis Detection (LLD)

Frequency (µCi/cc) (a)

Containment P P Principal Gamma 1.0E-04 Purge Each Purge (b,c) Emitters (e) 1.0E-06 Grab Sample H-3 Auxiliary M (b) M (b) Principal Gamma 1.0E-04 Building Grab Sample Emitters (e) 1.0E-06 Ventilation H-3 Continuous (d) W (b,i) I-131 1.0E-12 Charcoal I-133 1.0E-10 ple Sam-Continuous (d) W (b,i) Principal Gamma 1.0E-11 Particulate Emitters (e)

All Release Sample Types Continuous (d) M Gross Alpha 1.0E-11 as listed above Composite Particulate Sample Continuous (d) Q Sr-89 Sr-90 1.0E-11 Composite Particulate Sample Air Ejector M (b,f) Grab M (b, f) Principal Gamma 1.0E-04 Sample Emitters (e) 1.0E-12 I-131 (h) 1.0E-06 H-3 (g)

All Release Continuous (d) Noble Gas Beta or Gamma 1.0E-06 Types listed Monitor above Gas Decay Tank P P Principal Gamma 1.0E-04 Each Tank Grab Each Tank Emitters (e)

Sample

CY-GI-170-300 Revision 36 Page 41 of 120 Table 5-1 Table Notation (a) The lower limit of detection (LLD) is defined in Table Notation (a) of Table 4-1.

(b) Analyses shall also be performed when the monitor on the continuous sampler reaches its setpoint.

(c) Tritium grab samples shall be taken at least three times per week when the reactor cavity is flooded.

(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 in accordance with Sections 5.2.1, 5.3.1, and 5.3.7 (Controls).

(e) The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:

Kr-85m, Xe-133, Xe-133m and Xe-135 for gaseous emissions

I-131, 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 detected and reported.

Other nuclides which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLDs higher than required, the reasons shall be documented in the Annual Radioactive Effluent Release Report.

(f) Air ejector samples are not required during cold or refueling shutdowns.

(g) Air ejector tritium sample is not required if the secondary coolant activity is less than 1.0E-04 µCi/gm.

(h) Air ejector iodine samples shall be taken and analyzed weekly if the secondary coolant activity exceeds 1.0E-04 µCi/gm.

(i) Analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15% RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement for increased sample frequency does not apply if: (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent

CY-GI-170-300 Revision 36 Page 42 of 120 activity has not increased more than a factor of 3.

CY-GI-170-300 Revision 36 Page 43 of 120 5.5 GASEOUS EFFLUENT RELEASE POINTS There are three release points continuously monitored for noble gases, containment vent, plant vent and air ejector. The containment vent and plant vent are also continuously monitored for radioiodines and particulates. Since the air ejector is a steam release point, continuous radioiodine and particulate monitoring is not required when the secondary coolant activity is less than 1.0E-04 µCi/gm. Flow rates through the vents are measured periodically. During shutdown, temporary trailers may be brought on site that also require monitoring and characterization of their releases, such as the CO2 decon trailer.

Quarterly plant measurements of one week duration for the particulate and iodine released in the steam by the air ejector demonstrate that sampling this pathway for particulate and iodine is not necessary since these releases are less than 0.1% of the Plant Vent. The releases are correlated to blowdown activity for determining activity in steam releases. During shutdown and startup, special systems are in use that may release small amounts of radioactivity in steam releases. This is accounted for by using operational data and activity in the source of the steam.

Grab samples are obtained when practicable.

If an unmonitored release point is identified, a calculation is performed to determine the radioactivity that is released. The calculation includes a conservative estimate of source term if sample data is not available, and a conservative estimate of flow rate and duration if measurement of flow and duration are not available. If the release is continuous, it is included in the monthly report that accounts for releases from the site for calculating doses to the general public.

CY-GI-170-300 Revision 36 Page 44 of 120 5.6 GASEOUS EFFLUENT MONITOR SETPOINTS Alarm and/or trip setpoints for specified radiation monitors are required on each noble gas effluent line from the plant. Precautions, limitations and setpoints applicable to the operation of Ginna Station gaseous effluent monitors are provided in plant procedure P-9. Setpoints are conservatively established for each ventilation noble gas monitor so that dose rates in unrestricted areas corresponding to 10 CFR Part 50 Appendix I limits will not be exceeded. Setpoints shall be determined so that dose rates from releases of noble gases will comply with Section 5.2.1 (Dose Rate - Controls).(1). Table 5-2 provides the gaseous and particulate meteorological assumption used in development of the P-9 setpoints.

The calculated alarm and trip action setpoints for each radioactive gaseous effluent monitor must satisfy the following equation:

Equation (7)

Where:

cv = setpoint in cpm Qiv = release rate limit by specific nuclide (i) in µCi/sec from vent (v) f= discharge flow rate in cfm k= units conversion factor in cc/sec/cfm K= calibration factor in µCi/cc/cpm]

The general methodology for establishing plant ventilation monitor setpoints is based upon a vent concentration limit in µCi/cc derived from site specific meteorology and vent release characteristics.

Additional radiation monitor alarm and/or trip setpoints are calculated for radiation monitors measuring radioiodines, radioactive materials in particulate form and to radionuclides other than noble gases. Setpoints are determined to assure that dose rates from the release of these effluents shall comply with Section 5.2.1 (Dose Rate - Controls)(2)

CY-GI-170-300 Revision 36 Page 45 of 120 The release rate limit for noble gases shall be calculated by the following equation for total body dose:

Equation (8)

Note: An occupancy factor of 1 is assumed. This may be modified following reviews of the area in question and by the following equation for skin doses:

Equation (9)

Where:

Qiv = the release rate of radionuclide (i) from vent (v) which results in a dose rate of 500 mrem/yr to the whole body or 3000 mrem/yr to the skin of the critical receptor in µCi/ sec.

Ki = the total body dose factor due to gamma emissions for each identified noble gas radionuclide in mrem/yr per µCi/m3 from Table 5-3.

Li = the skin dose factor due to beta emissions for each identified noble gas radionuclide in mrem/yr per µCi/m3 from Table 5-3.

Mi = the air dose factor due to gamma emissions for each identified noble gas radionuclide in mrad/yr per µCi/m3 from Table 5-3. Unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose.

(X/Q)v = the highest calculated annual average dispersion parameter for estimating the dose to the critical offsite receptor from vent release point (v) in sec/m3. The (X/Q)v is calculated by the method described in Regulatory Guide 1.111.

Noble gas monitor setpoints are conservatively set according to procedure P-9, RADIATION MONITORING SYSTEM, to correspond to fractions of the applicable 10 CFR Part 20 dose limits for unrestricted areas. Fractions are small enough to

CY-GI-170-300 Revision 36 Page 46 of 120 assure the timely detection of any simultaneous discharges from multiple release points before the combined downwind site boundary concentration could exceed allowable limits. Additional conservatism is provided by basing these setpoints upon instantaneous downwind concentrations. Release rates during the remainder of a given year, combined with any infrequent releases at setpoint levels, would result in only a very small fraction of the 10 CFR Part 20 annual limits.

Historically, xenon-133 has been the principal fission product noble gas released from all vents and is appropriate for use as the reference isotope for establishing monitor setpoints. The whole-body dose will be limiting, and the Xe-133 release rate limit is calculated by substituting the appropriate values into equation (8). After the release rate limit for Xe-133 is determined for each vent, the corresponding vent concentration limits are calculated based on applicable vent flow rates. During periods of high make-up water usage, argon-41 from air saturated make-up water becomes the principle radiogas of concern and may be used as the reference isotope for establishing setpoints. Calibration factors in µCi/cc per cpm are used to convert limiting vent concentrations to count rates.

Example: Plant Vent Monitor, R-14 Using Xe-133 as the controlling isotope for the setpoint and assuming a measured activity of 2.66E-04 µCi/cc and a ratemeter reading of 4750 cpm above background, the efficiency can be calculated, using a measured vent flow of 7.45E+04 cfm, Ki from Table 5-3 of 2.94E+02 and a (X/Q)v for the site boundary of 2.7E-06, the Release Rate Limit is calculated and then the setpoint determined.

Using Equation 8:

CY-GI-170-300 Revision 36 Page 47 of 120 Using Equation 7:

Per procedure P-9, R-14 is set at 0.4 of this value or 1.28E+05 cpm for normal operation. 40% of the release rate limit is a conservatism based on the possibility of two release points simultaneously at their setpoints for a total of 80% of the release rate limit.

Effluent Monitor Warning alarm setpoints are set at one-half of the trip setpoint. With all calculations equal this is a warning that 20% of the release limit has been reached at a single release point.

CY-GI-170-300 Revision 36 Page 48 of 120 Table 5-2 Meteorological Data and Locations of Receptors for Set Point Calculations Process Monitors Monitor (Radioisotope) Geographic Release Point X/Q D/Q (m-2) Flow Location (vent) (sec/m3)

(Dist./Direction) (cfm)

R-10A (Radioiodine) 0.5 mile E Containment 1.99E-8 12,520 R-10B (Radioiodine) 0.5 mile ESE Plant 7.41E-9 81,650 R-11 (Cs-137) 0.5 mile E Containment 1.99E-8 12,520 R-12 (Xe-133) 0.5 mile NNE Containment 2.15E-6 12,520 R-13 (Cs-137) 0.5 mile ESE Plant 7.41E-9 81,650 R-14 (Xe-133) 0.5 mile ESE Plant 2.43E-7 81,650 R-15 (Xe-133) 0.5-1-mile NNE Air Ejector 3.01E-6 720 Accident Monitors Monitor (Radioisotope) Geographic Release Point X/Q D/Q (m-2) Flow Location (vent) (sec/m3)

(Dist./Direction) (cfm)

R-12A 0.5-1-mile E Containment 1.99E-8 12,520 (Radioiodine)

R-12A 0.5-1-mile E Containment 1.99E-8 12,520 (ParticulateCs-137)

R-12A 0.5-1-mile NNE Containment 2.15E-6 12,520 (Noble Gas Xe-133)

R-14A 0.5-1-mile ESE Plant 7.41E-9 81,650 (Radioiodine)

R-14A 0.5-1-mile ESE Plant 7.41E-9 81,650 (Particulate Cs-137)

R-14A 0.5-1-mile ESE Plant 2.43E-7 81,650 (Noble Gas Xe-133)

R-48 0.5-1-mile NNE Air Ejector 3.01E-6 720 (RCS Accident Mix)

CY-GI-170-300 Revision 36 Page 49 of 120 Table 5-2 (continued...)

Further details found in procedure P-9.

I-131, I-133, H-3 and particulates with half lifes greater than 8 days utilizes the following equation:

For Noble Gases:

Pi = Food and ground pathways in m2 mrem/year per µCi/sec Ki = mrem/year per µCi/m3 Qiv = Release rate in units of µCi/sec

CY-GI-170-300 Revision 36 Page 50 of 120 5.7 GASEOUS EFFLUENT DOSE RATE Gaseous effluent monitor setpoints as described in Section 5.6 of this manual are established at concentrations which permit some margin for corrective action to betaken before exceeding offsite dose rates corresponding to 10 CFR Part 20 limitations. Plant procedures establish the methods for sampling and analysis for continuous ventilation releases and for containment purge releases. Plant procedures also establish the methods for sampling and analysis prior to gas decay tank releases. The instantaneous dose rate in unrestricted areas due to unplanned releases of airborne radioactive materials may be calculated using annual average X/Q's. Dose rates shall be determined using the following expressions:

For noble gases:

Equation (11)

Total gamma and beta dose to the skin Equation (12) total body dose For I-131, I-133, tritium and all radioactive materials in particulate form with half-lives greater than 8 days:

Equation (13)

Where:

Ki = the total body dose factor due to gamma emissions for each identified noble gas radionuclide (i) in mrem/yr per µCi/m3 from Table 5-2.

Li = the skin dose factor due to beta emissions for each identified noble gas radionuclide (i) in mrem/yr per µCi/m3 from Table 5-3.

CY-GI-170-300 Revision 36 Page 51 of 120 Mi = the air dose factor due to gamma emissions for each identified noble gas radionuclide (i) in mrad/yr per µCi/m3 from Table 5-3. Unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose.

Pi = the dose parameter for radionuclide (i) other than noble gases for the inhalation pathway, in mrem/yr per µCi/m3. The dose factors are based on the critical individual organ and the child age group.

Pi is further defined as: Pi =(106pCi/uCi)(BR)(DFAi) where BR is the breathing rate for a child in m3/yr and DFAi is the dose factor for the child in mrem/pCi.

(X/Q)v = the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary in sec/m3.

Wv = the highest annual average dispersion parameter for estimating the dose to the critical receptor in sec/m3 for the inhalation pathway and in m-2 for the food and ground pathways.

Qiv = the release rate of radionuclide (i) from vent (v) in µCi/sec.

CY-GI-170-300 Revision 36 Page 52 of 120 5.8 GASEOUS EFFLUENT DOSES The air dose in unrestricted areas due to noble gases released in gaseous effluents from the site shall be determined using the following expressions:

During any calendar year, for gamma air dose:

Equation (14)

During any calendar quarter, for gamma air dose:

Equation (14A)

During any calendar year for beta air dose:

(Equation 15)

During any calendar quarter, for beta air dose:

(Equation 15A)

Where:

Mi = the air dose factor due to gamma emissions for each identified noble gas radionuclide in mrad/yr per µCi/m3 from Table 5-3 Ni = the air dose factor due to beta emissions for each identified noble gas radionuclide in mrad/yr per µCi/m3 from Table 5-3

CY-GI-170-300 Revision 36 Page 53 of 120 (X/Q)v = for vent releases. The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary in sec/m3.

D = the total gamma air dose from gaseous effluents in mrad.

D = the total beta air dose from gaseous effluents in mrad.

Qiv = the release of noble gas radionuclides, i, in gaseous effluents from vents in

µCi. Releases shall be cumulative over the time period.

3.17E-08 = the inverse of the number of seconds in a year The dose to an individual from I-131, I-133, tritium and all radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released from the site to unrestricted areas shall be determined using the following expression:

dose during any calendar year:

Equation (16) dose during any calendar quarter:

(Equation 16A)

Where:

DI = the total dose from I-131, I-133, tritium and all radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents in mrem.

Ri = the dose factor for each identified radionuclide (i) in m-2 mrem/yr per µCi/sec or mrem/ yr per µCi/m3 from Table 5-5.

Wv = the annual average dispersion parameter for estimating the dose to an individual at the critical location in sec/m3 for the inhalation pathway and in

CY-GI-170-300 Revision 36 Page 54 of 120 m-2 for the food and ground pathways.

Qiv = the release of I-131, I-133, tritium and all radioactive materials in particulate form in gaseous effluents with half-lives greater than 8 days in µCi. Releases shall be cumulative over the desired time period as appropriate.

CY-GI-170-300 Revision 36 Page 55 of 120 Table 5-3 Dose Factors to the Child For Noble Gases and Daughters*

Radio- Total Body Dose Skin Dose Factor Gamma Air Dose Beta Air Dose nuclides Factor Ki Li (mrem/yr per Factor Mi Factor Ni (mrem/yr µCi/m3) (mrad/yr (mrad/yr per µCi/m3) per µCi/m3) per µCi/m3)

Kr-83m 7.56E-02** ---- 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+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 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+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-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

The listed dose factors are for radionuclides that may be detected in gaseous effluents. These dose factors for noble gases and daughter nuclides are taken from Table B-1 of Regulatory Guide 1.109 (Reference 3). A semi-infinite cloud is assumed.

- 7.56E-02 = 7.56 x 10-2

CY-GI-170-300 Revision 36 Page 56 of 120 Table 5-4 Dose Parameters for Radionuclides and Radioactive Particulate, Gaseous Effluents*

Radio- Pi Inhalation Pi Food & Radio- Pi Inhalation Pi Food &

nuclides Pathways Ground nuclides Pathways Ground (mrem/yr per Pathways (m2 x (mrem/yr per Pathways (m2 x

µCi/m3) mrem/yr per µCi/m3) mrem/yr per

µCi/sec) µCi/sec)

H-3 6.5E+02 2.4E+03 Cd-115m 7.0E+04 4.8E+07 C-14 8.9E+03 1.3E+09 Sn-126 1.2E+06 1.1E+09 Cr-51 3.6E+02 1.1E+07 Sb-125 1.5E+04 1.1E+09 Mn-54 2.5E+04 1.1E+09 Te-127m 3.8E+04 7.4E+10 Fe-59 2.4E+04 7.0E+08 Te-129m 3.2E+04 1.3E+09 Co-58 1.1E+04 5.7E+08 Te-132 1.0E+03 7.2E+07 Co-60 3.2E+04 4.6E+09 Cs-134 7.0E+05 5.3E+10 Zn-65 6.3E+04 1.7E+10 Cs-136 1.3E+05 5.4E+09 Rb-86 1.9E+05 1.6E+10 Cs-137 6.1E+05 4.7E+10 Sr-89 4.0E+05 1.0E+10 Ba-140 5.6E+04 2.4E+08 Sr-90 4.1E+07 9.5E+10 Ce-141 2.2E+04 8.7E+07 Y-91 7.0E+04 1.9E+09 Ce-144 1.5E+05 6.5E+08 Zr-95 2.2E+04 3.5E+08 Np-239 2.5E+04 2.5E+06 Nb-95 1.3E+04 3.6E+08 I-131 1.5E+07 1.1E+12 Mo-99 2.6E+02 3.3E+08 I-133 3.6E+06 9.6E+09 Ru-103 1.6E+04 3.4E+10 Unidentified 4.1E+07 9.5E+10 Ru-106 1.6E+05 4.4E+11 ---- ---- ----

Ag-110m 3.3E+04 1.5E+10 ---- ---- ----

The listed dose parameters are for radionuclides that may be detected in gaseous effluents. These and additional dose parameters for isotopes not included in Table 5-4 may be calculated using the methodology described in NUREG-0133, Section 5.2.1 (Reference 2).

CY-GI-170-300 Revision 36 Page 57 of 120 Table 5-5 Pathway Dose Factors Due to Radionuclides Other Than Noble Gases*

Radio- Inhalation Meat Ground Plane Cow-Milk-Child Leafy nuclides Pathway Ri Pathway Ri Pathway Ri Pathway R (m2 Vegetables i

(mrem/yr per (m2 x mrem/yr (m2 x mrem/yr x mrem/yr per Pathway Ri

µCi/m3) per µCi/sec) per µCi/sec) µCi/sec) (m2 x mrem/yr per µCi/sec)

H-3 1.12E+03 2.33E+02 0 2.38E+03 2.47E+02 Cr-51 1.70E+04 4.98E+05 5.31E+06 5.75E+06 1.63E+06 Mn-54 1.57E+06 7.60E+06 1.56E+09 3.70E+07 5.38E+07 Fe-59 1.27E+06 6.49E+08 3.09E+08 4.01E+08 1.10E+08 Co-58 1.10E+06 9.49E+07 4.27E+08 7.01E+07 4.55E+07 Co-60 7.06E+06 3.61E+08 2.44E+10 2.25E+08 1.54E+08 Zn-65 9.94E+05 1.05E+09 8.28E+08 1.99E+10 2.24E+08 Sr-89 2.15E+06 4.89E+08 2.42E+04 1.28E+10 5.39E+09 Sr-90 1.01E+08 1.01E+10 0 1.19E+10 9.85E+10 Zr-95 2.23E+06 6.09E+08 2.73E+08 8.76E+05 1.13E+08 I-131 1.62E+07 2.60E+09 1.01E+07 4.95E+11 2.08E+10 I-133 3.84E+06 6.45E+01 1.43E+06 4.62E+09 3.88E+08 Cs-134 1.01E+06 1.42E+09 7.70E+09 6.37E+10 1.96E+09 Cs-136 1.71E+05 5.06E+07 1.64E+08 6.61E+09 1.60E+08 Cs-137 9.05E+05 1.27E+09 1.15E+10 5.75E+10 1.80E+09 Ba-140 1.74E+06 5.00E+07 2.26E+07 2.75E+08 2.03E+08 Ce-141 5.43E+05 1.45E+07 1.48E+07 1.43E+07 8.99E+07

Additional dose factors for isotopes not included in Table 5-5 may be calculated using the methodology described in NUREG-0133, Section 5.3.1(reference 2).

CY-GI-170-300 Revision 36 Page 58 of 120 6.0 RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION 6.1 LIQUID EFFLUENT MONITORS 6.1.1 CONTROLS The radioactive liquid effluent monitoring instrumentation channels shown in Table 6.1-1 shall be OPERABLE with their Alarm/Trip setpoints set to ensure that the limits of Section 4.1.1 (Radioactive Liquid Effluents - Controls) are not exceeded.

The Alarm/Trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

6.1.2 APPLICABILITY

At all times.

Note: The Radioactive Effluent Monitoring Instrumentation may be removed from service for short periods of time without the instrumentation being considered inoperable for monthly/quarterly testing. Preventative/ corrective maintenance or calibrations require instrumentation to be declared inoperable.

6.1.3 ACTION

With a radioactive liquid effluent monitoring instrumentation channel Alarm/ Trip setpoint less conservative than required by the above control, immediately 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.

6.1.4 ACTION

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 6.1-1.

Restore the minimum number of instrumentation channels to OPERABLE status within 30 days or explain in the next Annual Radioactive Effluent Release Report, pursuant to Section 6.2 of the ODCM, why this inoperability was not corrected in a timely manner.

6.1.5 SURVEILLANCE REQUIREMENTS 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 at the frequencies shown in Table 6.1-2.

CY-GI-170-300 Revision 36 Page 59 of 120 6.1.6 BASES The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alarm/Trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the Alarm/Trip will occur prior to exceeding the limits of 10 CFR 20.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR 50.

CY-GI-170-300 Revision 36 Page 60 of 120 Table 6.1-1 Radioactive Liquid Effluent Monitoring Instrumentation Gross Activity Monitors (Liquid) Minimum Action Channels OPERABLE

a. Containment Fan Coolers (R-16) 1 1

b. Liquid Radwaste (R-18) 1 2

c. Steam Generator Blowdown (R-19) 1(a) 3

d. Spent Fuel Pool Heat Exchanger (R-20A, R-20B) 1 1

e. Turbine Building Floor Drains (R-21) 1 1

f. High Conductivity Waste (R-22) 1 2

CY-GI-170-300 Revision 36 Page 61 of 120 Table 6.1-1 Table Notation (a) Not required when steam generator blowdown is being recovered, i.e. not released.

Action 1 If the number of OPERABLE channels is less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months grab samples are analyzed for isotopic concentration or gross radioactivity (beta or gamma) at a lower limit of detection (LLD) of at most 1.0E-07 Ci/gm.

Action 2 If the number of OPERABLE channels is less than required by the minimum Channels OPERABLE requirement, effluent releases from the tank may continue, provided that prior to initiating a release:

Note: When counting 2 independent samples for agreement, doubling the acceptance criterion for low (< 6.0E-05 Ci/ml) activity samples from 10%

to 20% results in a consequence at the release point of < 1%. The expanded acceptable criterion for low activity samples is employed to compensate for increased impact of sampling and counting error on acceptance.

1. At least two independent samples of the tank's contents, taken at least 60 minutes apart, are analyzed and agree within 10% of total activity, (20% if total activity minus noble gases < 6.0E-05 Ci/ml), and

2. At least two technically qualified members of the Facility Staff independently review and approve the analytical results, and

3. At least two technically qualified members of the Facility Staff independently verify the discharge line valving.

Action 3 When Steam Generator Blowdown is being released (not recycled) and the number of channels OPERABLE is less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for isotopic concentration at a lower limit of detection (LLD) of at most 1.0E-07 Ci/gram:

1. At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when the concentration of the secondary coolant is

> 0.01 Ci/gram (DOSE EQUIVALENT I-131).

2. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the concentration of the secondary coolant is 0.01 Ci/gram (DOSE EQUIVALENT I-131).

CY-GI-170-300 Revision 36 Page 62 of 120 Table 6.1-2 Radioactive Liquid Effluent Monitoring SURVEILLANCE REQUIREMENTS Gross Activity Monitor (Liquid) Channel Source Functional Channel Check Check Test Calibration

a. Containment Fan Coolers (R-16) D(e) M(c) Q(b) R(d)

b. Liquid Radwaste (R-18) D(e) M(c) Q(a) R(d)

c. Steam Generator Blowdown (R-19) D(e) M(c) Q(a) R(d)

d. Spent Fuel Pool Heat Exchanger (R-20A, D(e) M(c) Q(b) R(d)

R-20B)

e. Retention Tank (R-21) D(e) M(c) Q(a) R(d)

f. High Conductivity Waste (R-22) D(e) M(c) Q(a) R(d)

g. Dilution Flow Rate Determination N.A. N.A. N.A. R(f)

CY-GI-170-300 Revision 36 Page 63 of 120 Table 6.1-2 Table Notation (a) The FUNCTIONAL Test shall also demonstrate that automatic isolation of this pathway and control room alarm will occur if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm and/or trip setpoint.

2. Power failure. (Verified in same functional test as Alarm/Trip setpoint due to normally energized relay)

(b) The FUNCTIONAL Test shall also demonstrate that control room alarm occurs if any of the following conditions exist.

1. Instrument indicates measured levels above the alarm setpoint.

2. Power failure. (Verified in same functional test as Alarm setpoint due to normally energized relay)

(c) This check may require the use of an external source due to high background in the sample chamber.

(d) Source used for the CHANNEL CALIBRATION shall be traceable to the National Institute for Standards and Technology (NIST) or shall be obtained from suppliers (e.g., Analytics) that provide sources traceable to other officially designated standards agencies.

(e) Applies only during releases via this pathway.

(f) Flow rate for the discharge canal dilution, which is applied to all liquid effluent pathways, shall be determined at the frequency specified.

CY-GI-170-300 Revision 36 Page 64 of 120 6.2 GASEOUS EFFLUENT MONITORS 6.2.1 CONTROLS The radioactive gaseous effluent monitoring instrumentation channels shown in Table 6.2-1 shall be OPERABLE with their Alarm/Trip setpoints set to ensure that the limits of Control Section 5.2.1 (Dose Rate - Controls) are not exceeded. The Alarm/ Trip setpoints of these channels meeting Control Section 5.2.1 (Dose Rate -

Controls) shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

6.2.2 APPLICABILITY

As shown in Table 6.2-1 Note: The Radioactive Effluent Monitoring Instrumentation may be removed from service for short periods of time without the instrumentation being considered inoperable for weekly grab filter or cartridge changes or monthly/quarterly testing, with the exception of the R-10A, R-11, R-12 skid. Preventative/corrective maintenance, calibrations, and moving filter replacements require instrumentation to be declared inoperable.

6.2.3 ACTION

With a radioactive gaseous effluent monitoring instrumentation channel Alarm/Trip setpoint less conservative than required by the above specification, immediately declare the channel inoperable.

6.2.4 ACTION

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 6.2-1.

Restore the minimum number of instrumentation channels to OPERABLE status within 30 days or, if not, explain in the next Annual Radioactive Effluent Release Report, pursuant to Section 6.2 of the ODCM, why this inoperability was not corrected in a timely manner.

6.2.5 SURVEILLANCE REQUIREMENTS Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCECHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 6.2-2.

6.2.6 BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm/Trip setpoints

CY-GI-170-300 Revision 36 Page 65 of 120 for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the Alarm/Trip will occur prior to exceeding the limits of 10 CFR 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR 50.

CY-GI-170-300 Revision 36 Page 66 of 120 Table 6.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation Plant Ventilation (a)(h) Minimum Action Channels OPERABLE

a. Iodine sampler (R-10B or R-14AIODN) 1 (i) 1

b. Particulate Sampler (R-13 or R-14APART) 1 (i) 1

c. Noble Gas Activity (R-14 or R-14AGAS) 1 (b) 2

d. Containment Noble Gas Activity (R- 1 (d,e) 3

12) or Containment Particulate Sampler (R-11)

Containment Purge (c)(h) Minimum Action Channels OPERABLE

a. Iodine Sampler (R-10A or R-12AIODN) 1 (i) 1

b. Particulate Sampler (R-11 or R-12APART) 1 (f) 5

c. Noble Gas Activity (R-12 or R-12AGAS) 1 (f) 5 Air Ejector Monitor (g)(h) Minimum Action Channels OPERABLE Noble Gas Activity (R-15 or R-47) 1 4

CY-GI-170-300 Revision 36 Page 67 of 120 Table 6.2-1 Table Notation (a) Required at all times.

(b) Only radiation monitor R-14 has an isolation signal. If R-14AGAS is being used to monitor batch gas releases, the contents of the tank(s) may be released to the environment provided that prior to initiating the release:

1. At least two independent samples of the tank's contents are analyzed, and

2. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup.

(c) Required in MODES 5 and 6.

(d) The mini-purge system allows the release of Containment atmosphere through the plant vent. 10 CFR 100 type releases via mini-purge are limited by an isolation signal generated from Safety Injection. 10 CFR 20 releases through the mini-purge are considered to be similar to other plant ventilation releases and are monitored by R-14, R-13 and R-10B. R-14A may be used as a substitute for R-14 since automatic isolation is available from the R-11 or R-12 monitors if the activity in Containment increases. Therefore, either R-11 or R-12 is required to sample Containment during a mini-purge release. Automatic isolation of mini-purge for 10 CFR part 20 type releases is considered unnecessary due to the low flow associated with mini-purge, the continuous monitoring from R-11 or R-12 and the original measurement before the purge begins. To ensure the Containment sample monitored by R-11 or R-12 is representative of the containment atmosphere, at least one containment recirculation fan is required to be in operation during mini-purge operation.

(e) If the R-10A, R-11, R-12 skid is not OPERABLE, it is possible to substitute the R-10B,R-13, R-14 skid when the R-14A skid is OPERABLE. The setpoints for the R-10A, R-11, R-12 skid would be used. There would be no automatic containment isolation capability from the radioactive effluent monitoring instrumentation when using R-10B, R-13, R-14 skid for containment leakage measurements. This cannot be used if Containment Ventilation Isolation is required.

(f) If containment ventilation isolation instrumentation is required by LCO 3.3.5 for core alteration or movement of irradiated fuel in containment, R-12A skid cannot be used in place of the R-10A, R-11, R-12 skid.

(g) Required only when Air Ejector is operating.

(h) Gaseous effluent monitors are not considered inoperable due to changes in ventilation flow. Reduced flow in the ventilation makes the monitor setpoint more conservative.

CY-GI-170-300 Revision 36 Page 68 of 120 (i) Minimum channels OPERABLE for Plant Vent Iodine, Plant Vent Particulate, and Containment Purge Iodine, refers to the sample collection system - not the radiation monitor.

Action 1 If the number of OPERABLE channels is less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided iodine and particulate samples are continuously collected with alternate sampling equipment as required in Table 6.2-1. This should be completed within one hour.

Action 2 If the number of OPERABLE channels is less than required by the Minimum Channels OPERABLE requirement, continuous effluent releases via this pathway may continue provided grab samples are taken and analyzed for isotopic activity at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . No batch gas releases are to be made with operable channels less than required minimum channels operable.

Action 3 If the number of OPERABLE channels is less than required by the Minimum Channels OPERABLE requirement, or at least one containment recirc fan cooler is not in operation, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months terminate any mini-purge release in process.

Action 4 If the number of OPERABLE Channels is less than required by the Minimum Channels OPERABLE requirement and the Secondary Activity is 1.0E-04 µCi/

gm, effluent releases may continue via this pathway provided grab samples are analyzed for isotopic concentration at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . If the secondary activity is > 1.0E-04 µCi/gm, effluent releases via this pathway may continue for up to 31 days provided grab samples are taken every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and analyzed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Action 5 If the number of OPERABLE channels is less than required by the Minimum Channels Operable requirement, terminate the purge within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Also refer to LCO 3.3.5 if core alterations or movement of irradiated fuel in containment is in progress.

CY-GI-170-300 Revision 36 Page 69 of 120 Table 6.2-2 Radioactive Gaseous Effluent Monitoring SURVEILLANCE REQUIREMENTS Plant Ventilation Channel Source Functional Channel Check Check Test Calibration

a. Iodine Sampler (R-10B) W(e) N.A. N.A. R(c)

b. Iodine Sampler (R- W(e) N.A. N.A. R(c) 14AIODN)

c. Particulate Sampler (R-13) W(e) N.A. N.A. R(c)

d. Particulate Sampler (R- W(e) N.A. N.A. R(c) 14APART)

e. Noble Gas Activity (R-14) D(e) M Q(a) R(c)

f. Noble Gas Activity (R- D(e) M Q(b) R(c) 14AGAS)

g. Flow Rate Determination N.A. N.A. N.A. R(d)

Containment Purge Channel Source Functional Channel Check Check Test Calibration

a. Iodine Sampler (R-10A) W(e) N.A. N.A. R(c)

b. Iodine Sampler (R- W(e) N.A. N.A. R(c) 12AIODN)

c. Particulate Sampler (R-11) W(e) M Q(a) R(c)

d. Particulate Sampler (R- W(e) M Q(b) R(c) 12APART)

e. Noble Gas Activity (R-12) D(e) M Q(a) R(c)

f. Noble Gas Activity (R- D(e) M Q(b) R(c) 12AGAS)

g. Flow Rate Determination N.A. N.A. N.A. 6Y(d)

Air Ejector Monitor Channel Source Functional Channel Check Check Test Calibration

a. Noble Gas Activity (R-15) D(e) M Q(b) R(c)

b. Noble Gas Activity (R-47) D(e) M Q(b) R(c)

c. Flow Rate Determination N.A. N.A. N.A. R(f)

CY-GI-170-300 Revision 36 Page 70 of 120 Table 6.2-2 Table Notation (a) The FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm occur if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm and/or trip setpoint.

2. Power failure. (Verified in same functional test as Alarm/Trip Setpoint due to normally energized relay)

(b) The FUNCTIONAL TEST shall also demonstrate that control room alarm occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm setpoint.

2. Power failure. (Verified in same functional test as Alarm Setpoint due to normally energized relay)

(c) Source used for the Channel Calibration shall be traceable to the National Institute for Standards and Technology (NIST) or shall be obtained from suppliers (e.g., Amersham) that provide sources traceable to other officially designated standards agencies.

(d) Flow rate for main plant ventilation exhaust and containment purge exhaust are calculated by the flow capacity of ventilation exhaust fans in service and shall be determined at the frequency specified.

(e) Applies only during releases via this pathway.

(f) Flow rate of the Air Ejector vent shall be determined with the plant in operation, at the frequency specified.

CY-GI-170-300 Revision 36 Page 71 of 120 6.3 RADIATION ACCIDENT MONITORING INSTRUMENTATION

6.3.1 CONTROLS

The radiation accident monitoring instrumentation channels shown in Table 6.3-1 shall be OPERABLE according to the following schedule:

6.3.2 APPLICABILITY

1. Containment Purge (R-12A) - Modes 5 and 6 when the purge flanges are removed.

2. Plant Vent (R-14A) - All modes

3. Air Ejector (R-47 and R-48) - When air ejector is operating

4. A Main Steam Line (R-31) - Modes 1, 2, and 3

5. B Main Steam Line (R-32) - Modes 1, 2, and 3 Note: The Radiation Accident Monitoring Instrumentation may be removed from service for short periods of time without the instrumentation being considered inoperable for weekly grab filter or cartridge changes.

Preventative maintenance and calibrations require instrumentation to be declared inoperable.

6.3.4 ACTION

With less than the minimum number of radiation accident monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 6.3-1.

6.3.5 SURVEILLANCE REQUIREMENTS:

1. Each radiation accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION at the frequencies shown in Table 6.3-2.

6.3.6 BASES

Radiation accident monitoring instrumentation is provided to monitor, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the Alarm will occur prior to exceeding the limits of 10 CFR

20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR 50.

CY-GI-170-300 Revision 36 Page 72 of 120 Table 6.3-1 Radiation Accident Monitoring Instrumentation Instrument Minimum Action Channels Operable

a. Containment Purge Beta Particulate 1(a) 1 (R-12APART)

Containment Purge Iodine (R- 1(a) 1 12AIODN) Containment Purge Gas 1(a) 1 (R-12AGAS)

b. Plant Vent Beta Particulate (R- 1 1 14APART) Plant Vent Iodine (R- 1 1 14AIODN) 1 1 Plant Vent Gas (R-14AGAS)

c. Air Ejector Low-range Gas (R-47) 1 1,2 Air Ejector/Gland Seal Exhaust High-range 1 1 Gas (R-48)

d. A Main Steam Line (R-31) 1 1

e. B Main Steam Line (R-32) 1 1

CY-GI-170-300 Revision 36 Page 73 of 120 Table 6.3-1 Table Notation (a) Only when the shutdown purge flanges are removed; otherwise, instrumentation kept in STANDBY mode.

Action 1 With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirements, either restore the inoperable channel(s) to OPERABLE status within 30 days of the event, or if not restored, prepare and submit, within the following 14 days, a Special Report to the Commission outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status. If the channel(s) is inoperable greater than 7 days but less than 30 days, report the cause of the inoperability and the actions taken in the Annual Radioactive Effluent Release Report.

Action 2 R-47 is relied upon to trend and quantify primary-to-secondary leakage. If R-47 is not OPERABLE with the air ejector in service, then enter procedures CH-RETS-RMS-INOP and CH-360.

CY-GI-170-300 Revision 36 Page 74 of 120 Table 6.3-2 Radiation Accident Monitoring Surveillance Requirements Radiation Accident Monitoring Instrumentation Channel Channel Check Calibration

a. Containment Purge (R-12A) M R(a)

b. Plant Vent (R-14A) M R(a)

c. Air Ejector (R-47) M R(a)

d. Air Ejector/Gland Seal Exhaust (R-48) M R(a)

e. A Main Steam Line (R-31) M R(a)

f. B Main Steam Line (R-32) M R(a)

(a) Source used for the CHANNEL CALIBRATION shall be traceable to the National Institute for Standards and Technology (NIST) or shall be obtained from suppliers (e.g., Analytics) that provide sources traceable to other officially designated standards agencies.

CY-GI-170-300 Revision 36 Page 75 of 120 6.4 AREA RADIATION MONITORS 6.4.1 SURVEILLANCE REQUIREMENTS:

CHANNEL CALIBRATION, CHANNEL CHECK, and a FUNCTIONAL TEST of the area radiation monitors shall be performed as specified in Table 6-4.

CY-GI-170-300 Revision 36 Page 76 of 120 Table 6-4 Area Radiation Monitor Surveillance Requirements Instrument Channel Functional Channel Check Test Calibration

a. Control Room R-1 D Q R

b. Containment R-2 D Q R

c. Radiochemistry Lab R-3 D Q R

d. Charging Pump Room R-4 D Q R

e. Spent Fuel Pool R-5 D Q R

f. Nuclear Sample Room R-6 D Q R

g. Incore Detector Area R-7 D Q R

h. Drumming Station R-8 D Q R

i. Letdown Line Monitor R-9 D Q R

j. Component Cooling Water Heat Exchanger

R-17 D Q R

k. AVT D Mixed Bed R-26 N.A. Q N.A.

l. Nuclear Sample Room Wide Range Monitor R-33 N.A. Q N.A.

m. Containment Spray Pump Wide Range Area Monitor R-34 N.A. Q N.A.

n. PASS Panel Wide Range Area R-35 N.A. Q N.A.

Monitor

While not an area monitor by strict definition, it serves as an indicator of internal leakage and provides an isolation signal for the component cooling system.

CY-GI-170-300 Revision 36 Page 77 of 120 7.0 RADWASTE TREATMENT 7.1 LIQUID RADWASTE TREATMENT SYSTEM

7.1.1 CONTROLS

The Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent to UNRESTRICTED AREAS would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31 day period.

7.1.2 APPLICABILITY

At all times.

7.1.3 ACTION

With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System which could reduce the radioactive liquid waste discharged not in operation, prepare and submit to the Commission within 30 days a Special Report that includes the following information:

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

2. Action(s) taken to return the inoperable equipment to OPERABLE status, and

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

7.1.4 SURVEILLANCE REQUIREMENTS:

1. Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Liquid Radwaste Treatment Systems are not being fully utilized.

2. The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Section 4.1.1 (Radioactive Liquid Effluents -

Controls) and Section 4.2.1 (Dose - Controls).

7.1.5 BASES

The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR 50.36a,

CY-GI-170-300 Revision 36 Page 78 of 120 General Design Criterion 60 of Appendix A to 10 CFR 50, and the design objective given in Section II.D of Appendix I to 10 CFR 50. The specified limits governing the use of the appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix A to 10 CFR 50 for liquid effluents.

CY-GI-170-300 Revision 36 Page 79 of 120 Figure 7-1 Liquid Radwaste Treatment Systems Effluent Paths and Controls

CY-GI-170-300 Revision 36 Page 80 of 120 7.2 GASEOUS RADWASTE TREATMENT SYSTEM 7.2.1 CONTROLS The Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY would exceed:

1. 0.2 mrad to air from gamma radiation, or

2. 0.4 mrad to air from beta radiation, or

3. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC

7.2.2 APPLICABILITY

At all times.

7.2.3 ACTION

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

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

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

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

7.2.4 SURVEILLANCE REQUIREMENTS:

1. Doses due to gaseous releases to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Gaseous Radwaste Treatment Systems are not being fully utilized.

2. The installed GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be considered OPERABLE by meeting Sections 5.2.1, 5.3.1, and 5.3.7 (Controls).

7.2.5 BASES

The OPERABILITY of the Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". This Control implements the requirements of 10 CFR 50.36a,

CY-GI-170-300 Revision 36 Page 81 of 120 General Design Criterion 60 of Appendix A to 10 CFR 50, and the design objectives given in Section II.D of Appendix I to 10 CFR 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I to 10 CFR 50, for gaseous effluents.

CY-GI-170-300 Revision 36 Page 82 of 120 Figure 7-2 Gaseous Radwaste Treatment Systems Effluent Paths and Controls

CY-GI-170-300 Revision 36 Page 83 of 120 7.3 SOLID RADWASTE SYSTEM

7.3.1 CONTROLS

1. The solid radwaste system shall be used as applicable in accordance with the Process Control Program for the solidification and packaging of radioactive waste to ensure meeting the requirements of 10 CFR 71 prior to shipment of radioactive wastes from the site.

7.3.2 APPLICABILITY

At all times.

7.3.3 ACTION

If the packaging requirements of 10 CFR 71 are not satisfied, suspend shipments of deficiently packaged solid radioactive wastes from the site until appropriate corrective measures have been taken.

CY-GI-170-300 Revision 36 Page 84 of 120 7.4 CONFIGURATION CHANGES

7.4.1 CONTROLS

Major changes to the Radioactive Waste Treatment Systems, (Liquid, Solid, and Gaseous), shall be reported to the Commission by the inclusion of a suitable discussion or by reference to a suitable discussion of each change in the Annual Radioactive Effluent Release Report for the period in which the changes were made. Major changes to Radioactive Waste Treatment Systems, (Liquid, Gaseous and Solid), shall include the following:

1. Changes in process equipment, components and structures from those in use (e.g., deletion of evaporators and installation of demineralizers);

2. Changes in the design of Radioactive Waste Treatment Systems that could significantly alter the characteristics and/or quantities of effluents released;

3. Changes in system design which may invalidate the accident analysis (e.g., changes in tank capacity that would alter the curies released).

Note: The Radioactive Waste Treatment Systems, are those systems used to minimize the total activity released from the site.

Note: Changing the filters used, replacement resins or minor modifications (pipe or valve dimensions or manufacturers) due to maintenance activities would not be considered a major change.

7.4.2 APPLICABILITY

At all times.

7.4.2 ACTION

The discussion of each change shall contain:

1. a summary, in accordance with 10 CFR 50.59, of the evaluation that led to the determination that the change could be made;

2. sufficient detailed information to support the reason for the change;

3. a detailed description of the equipment, components and processes involved and the interfaces with other plant systems;

4. an evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents from those previously predicted;

5. an evaluation of the change which shows the expected maximum exposures to individuals in all UNRESTRICTED AREAS and to the MEMBERS OF THE PUBLIC from those previously estimated;

6. documentation of the fact that the change was reviewed and found acceptable by the Plant Operations Review Committee.

CY-GI-170-300 Revision 36 Page 85 of 120 7.5 PROCESS CONTROL PROGRAM

a. The Process Control Program (PCP) shall be a document outlining the method of processing wet or dry solid wastes and for solidification of liquid wastes. It shall include the process parameters and evaluation methods used to assure meeting the requirements or 10 CFR Part 71 prior to shipment of containers of radioactive waste from the site.

b. Licensee may make changes to the PCP and shall submit to the Commission with the Radioactive Effluent Release Report for the period in which any change(s) is made a copy of the new PCP and a summary containing:

1. sufficiently detailed information to support the rationale for the change;

2. a determination that the change will not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and

3. documentation of the fact that the change has been reviewed and found acceptable by the onsite review function.

c. Licensee initiated changes shall become effective after review and acceptance by the Plant Operation Review Committee.

CY-GI-170-300 Revision 36 Page 86 of 120 8.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 8.1 MONITORING PROGRAM

8.1.1 CONTROLS

The Radiological Environmental Monitoring Program (REMP) shall be conducted as specified in Table 8-1 at the locations given in Figures 8-1, 8-2, 8-3 and 8-4.

8.1.2 APPLICABILITY

At all times.

8.1.3 ACTION

1. If the radiological environmental monitoring program is not conducted as specified in Table 8-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal availability, or to malfunction of automatic sampling equipment. If the latter, efforts shall be made to complete corrective action prior to the end of the next sampling period. Sampling periods for this specification are usually of one week duration. If continuous water sampling equipment is out of service, the 120 minute aliquot sampling period does not mean that grab samples must be taken every 120 minutes, but one grab sample once each week is sufficient until the automatic sampling equipment is restored to service.

2. If the level of radioactivity as a result of plant effluents in an environmental sampling medium at one or more of the locations specified exceeds the reporting levels of Table 8-4 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from receipt of the laboratory 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 Sections 4.2.1, 5.3.1, and 5.3.7 (Controls).

When more than one of the radionuclides in Table 8-4 are detected in the sampling medium, this report shall be submitted if:

When radionuclides other than those in Table 8-4 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is greater than

CY-GI-170-300 Revision 36 Page 87 of 120 the calendar year limit of Sections 4.2.1, 5.3.1, and 5.3.7 (Controls). 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.

4. With milk or fresh leafy vegetable samples unavailable from one or more of the sampling locations indicated on Figure 8-2, a discussion shall be included in the Annual Radiological Environmental Operating Report which identifies the cause for the unavailability of samples and identifies locations for obtaining replacement samples. In selecting replacement samples, consider the implications of collecting samples outside the normal REMP ingestion pathway. In particular, recognize that perennial vegetation from relatively undisturbed areas is likely to have higher concentrations of Cs-137 than vegetation grown in soil that is regularly disturbed by cultivation and harvesting activities. If a milk or leafy vegetable sample location becomes unavailable, the location from which samples were unavailable may then be deleted provided that a comparable location is added to the radiological environmental monitoring program as described in the ODCM, unless no other sample location is available.

8.1.4 SURVEILLANCE REQUIREMENTS:

The radiological environmental samples shall be collected pursuant to Table 8-1 from the specific locations given in the table and figure(s) given in the ODCM, and shall be analyzed pursuant to the requirements of Table 8-1 and the detection capabilities required by Table 8-3.

8.1.5 BASES

The REMP required by this Control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures to MEMBERS OF THE PUBLIC resulting from plant operation. This monitoring program implements Section IV.B.2 of Appendix I to10 CFR 50, and thereby supplements the RETS by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.

Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979.

CY-GI-170-300 Revision 36 Page 88 of 120 Table 8-1 Radiological Environmental Monitoring Program EXPOSURE PATHWAY NUMBER OF SAMPLES & SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS (a) COLLECTION OF ANALYSIS FREQUENCY

1. AIRBORNE

a. Radioiodine 5 indicator (Samplers 2,4,7,9,11) Continuous operation of sampler with Radioiodine canister. Analyze within 1 control (Sampler 8) sample collection at least weekly (a) 7 days of collection for I-131.

b. Particulate 9 indicator Same as above Particulate sampler. Analyze for 3 control gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change.(c) Perform gamma isotopic analysis on each sample for which gross beta activity is > 10 times the mean of offsite samples. Perform gamma isotopic analysis on composite (by location) sample at least once per 92 days.(d)

2. DIRECT 30 indicator Dosimeters at least quarterly Gamma dose quarterly.

RADIATION (b) 9 control (11 placed greater than 5 miles from plant site)

3. WATERBORNE 1 control (Shoremont) Composite* sample collected over a Gross beta and gamma isotopic

a. Surface (e) period of 31 days.(f) analysis of each composite sample.

1 indicator (Condenser Water Dis-charge) Tritium analysis of one composite sample at least once per 92 days. (d) 1 indicator (Ontario Water District Same as above (f) Same as above

b. Drinking Intake) 1 control (Shoremont) Semi-annually Gamma isotopic analysis of each

c. Shoreline Sediment 1 indicator (Ontario Water District - sample (d)

Bear Creek)

Composite sample to be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

CY-GI-170-300 Revision 36 Page 89 of 120 EXPOSURE PATHWAY NUMBER OF SAMPLES & SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS (a) COLLECTION OF ANALYSIS FREQUENCY

4. INGESTION

a. Milk 2 Supplemental At least once per 15 days Gamma isotopic and I-131 analysis (June through October) of each sample.(d,g) 2 Supplemental At least once per 31 days Gamma isotopic and I-131 analysis (November through May) of each sample.(d,g)

b. Fish 4 control Twice during fishing season including Gamma isotopic analysis on edible 4 indicator (Off shore at Ginna) at least four species portions of each sample.(d,g)

c. Food Products 1 control Annual at time of harvest. Gamma isotopic analysis on edible 1 indicator (On site) Sample from two of the following: portion of each sample.(d,g)

1. apples

2. cherries

3. Other crops grown on site by contract farmer 1 control At time of harvest. One sample of: Gamma isotopic analysis on edible 1 indicator 1. broad leaf vegetation* portion of each sample.(d,g)

(Nearest offsite garden within 5 miles 2. other vegetable in the highest D/Q meteorological sector or onsite garden)

leaves from 3 different plant species composited

CY-GI-170-300 Revision 36 Page 90 of 120 Table 8-1 Table Notation (a) Specific parameters of distance and direction sector from the centerline of the reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 8-2 in a table and figures in the ODCM.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, inclement weather, and malfunction of automatic sampling equipment. If specimens are unavailable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the next Annual Radiological Environmental Operating Report. 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 as described in the ODCM. Submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples for the pathway and justifying the selection of the new location(s) for obtaining samples.

(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 dosimeter is considered to be one phosphor; two or more phosphors in one packet are considered to be two or more dosimeters. Film badges shall not be used for measuring direct radiation. The 39 stations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., some sectors may be over water so that the number of dosimeters may be reduced accordingly. The frequency of analysis or readout for dosimetry systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.

(c) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 or more hours after sampling to allow for radon and thoron daughter decay.

If gross beta activity in air particulate samples is greater than 10 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.

CY-GI-170-300 Revision 36 Page 91 of 120 (e) The "control sample" shall be taken at a distance beyond significant influence of the discharge. The "indicator sample" shall be taken in an area beyond but near the mixing zone.

(f) 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 (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

(g) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the OCDM.

CY-GI-170-300 Revision 36 Page 92 of 120 8.2 ENVIRONMENTAL MONITOR SAMPLE LOCATIONS All sample locations are specified on Table 8-2, a list of direction and distance to sample points. Indicator and control samples required by the environmental program are noted by an I or a C.

Figure 8-1 shows the onsite* sample locations for airborne particulates, radioiodine and direct radiation. Also indicated on Figure 8-1 is the onsite vegetable garden, as well as the placement of post-accident dosimeters, locations 2 -7 and 13 -24.

Dosimeter locations 2, 4,5,6, 7 are co-located with the air monitor samplers. The onsite garden is located in the SE sector near the closest resident who is the real maximally exposed individual, rather than in the ESE sector which has the highest D/Q.

Figure 8-2 gives the location of the milk herds near the plant. On this map is also included the Ontario Water District intake pumping station where lake water is sampled prior to treatment.

Figure 8-3 shows the offsite control locations for direct radiation as measured by dosimeters.

Figure 8-4 shows the offsite sample locations for airborne particulates, and radioiodine. Sample stations 9 and 11 are situated near population centers, Webster and Williamson, located approximately 7 miles from the Ginna Site.

Dosimeter locations 8 - 12 are co-located with air monitor samplers.

Onsite refers to the area surrounding the Ginna Plant bounded by Ginna property lines. Offsite refers to the area beyond the immediate Ginna property.

- Air Sampler #3 was relocated in 2018 for reliable electric power source.

TLD#3 remains in its original location for consistency of direct radiation trending.

CY-GI-170-300 Revision 36 Page 93 of 120 Table 8-2 Location, Direction, and Distances to Sample Points Air Sample Locations Station Type Coordinates Coordinates Direction Distance (Latitude, N) (Longitude, W) (degrees) (meters) 2 I 43.27798 77.30450 84 360 3 I 43.27667 77.30646 120 220 4 I 43.27561 77.30600 134 320 5 I 43.27602 77.30913 186 180 6 I 43.27614 77.31198 236 300 7 I 43.27724 77.31177 259 240 8 C 43.22860 77.54403 254 19840 9 I 43.21872 77.42007 234 11150 10 C 43.16360 77.32606 186 12730 11 I 43.22327 77.18756 122 11540 12 C 43.26818 76.99870 92 25170 13 I 43.27091 77.31103 193 770 Water Sample Locations Station Type Coordinates Coordinates Direction Distance (Latitude, N) (Longitude, W) (degrees) (meters)

Shoremont C 43.27561 77.64368 270 27150 Ontario Water I 43.28963 77.28704 53 2220 District Intake Circulation Water S 43.28725 77.30928 358 1070 Intake Circulation Water I 43.27861 77.30857 13 110 Discharge Deer Creek S Points down- Points downstream N/A N/A stream from Outfall 006 from Outfall 006 Milk Sample Locations Station Type Coordinates Coordinates Direction Distance (Latitude, N) (Longitude, W) (degrees) (meters)

Farm A S 43.24196 77.21978 119 8240 Farm B S 43.17035 77.12589 129 19030

CY-GI-170-300 Revision 36 Page 94 of 120 Produce Samples Description Type Coordinates Coordinates Direction Distance (Latitude, N) (Longitude, W) (degrees) (meters)

Onsite Gardens I 43.27278 77.30413 145 660 43.27627 77.30389 111 430 43.27727 77.30140 94 610 Purchased from C -- -- -- --

farms > 10 miles Fish Samples Sediment Samples Description Type Description Type Discharge Plume I OWD Shoreline I Lake Ontario > 10 miles C Shoremont (> 10 miles) C West of Ginna Lake Ontario Benthic S Dosimeter Sample Locations Station Type Coordinates Coordinates Direction Distance (Latitude, N) (Longitude, W) (degrees) (meters) 2 I 43.27798 77.30450 84 360 3 I 43.27643 77.30366 108 440 4 I 43.27561 77.30600 134 320 5 I 43.27602 77.30913 186 180 6 I 43.27614 77.31198 236 300 7 I 43.27724 77.31177 259 240 8 C 43.22860 77.54403 254 19840 9 I 43.21872 77.42007 234 11150 10 C 43.16360 77.32606 186 12730 11 I 43.22327 77.18756 122 11540 12 C 43.26818 76.99870 92 25170 13 I 43.27889 77.31157 303 260 14 I 43.28032 77.31886 290 860 15 I 43.27708 77.32016 266 920 16 I 43.27310 77.31993 241 1030

CY-GI-170-300 Revision 36 Page 95 of 120 Dosimeter Sample Locations (Continued)

Station Type Coordinates Coordinates Direction Distance (Latitude, N) (Longitude, W) (degrees) (meters) 17 I 43.27347 77.31162 206 510 18 I 43.27122 77.31082 192 730 19 I 43.27346 77.30868 178 460 20 I 43.27202 77.30650 163 650 21 I 43.27279 77.30408 144 660 22 I 43.27284 77.29960 125 920 23 I 43.27564 77.29969 107 780 24 I 43.27797 77.29993 87 730 25 C 43.23026 77.46891 248 14000 26 C 43.18249 77.43311 224 14600 27 C 43.16017 77.37563 203 14120 28 C 43.14851 77.18617 145 17450 29 C 43.23817 77.14423 108 14050 30 C 43.23687 77.05909 103 20760 31 I 43.26868 77.39841 262 7330 32 I 43.25309 77.37582 243 6070 33 I 43.22451 77.37458 222 7950 34 I 43.22582 77.34687 208 6520 35 I 43.21207 77.33044 193 7490 36 I 43.22840 77.30405 176 5480 37 I 43.22933 77.28251 158 5770 38 I 43.23135 77.25186 138 6910 39 I 43.25321 77.23025 113 6930 40 I 43.28071 77.22961 87 6440 63 I 43.27892 77.32344 228 740 64 I 43.27320 77.31571 277 1190 Table 8-2 Notes:

Latitude and longitude coordinates are based on World Geodetic System of 1984 (WGS84) datum.

Directions and Distance are noted from the centerline of thereactor I = Indicator Sample C = Control or background sample S = Supplemental sample

CY-GI-170-300 Revision 36 Page 96 of 120 Figure 8-1 Location of Onsite Air Monitors and Dosimeters

CY-GI-170-300 Revision 36 Page 97 of 120 Figure 8-2 Location of Farms for Milk Samples and Ontario Water District Intake

CY-GI-170-300 Revision 36 Page 98 of 120 Figure 8-3 Location of Offsite Dosimeters

CY-GI-170-300 Revision 36 Page 99 of 120 Figure 8-4 Location of Offsite Air Monitors

CY-GI-170-300 Revision 36 Page 100 of 120 Table 8-3 Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD)

Analysis Water Airborne Fish Milk Food Shoreline (pCi/l) Particulate (pCi/kg) (pCi/l) Products Sediment Or Gas wet (pCi/kg) (pCi/kg)

(pCi/m3) wet dry gross beta 4(a) 1.0E-02 3-H 2000 (1000)(a) 54-Mn 15 130 59-Fe 30 260 58, 60-Co 15 130 65-Zn 30 260 95-Zr-Nb 15(b) 131-I 1 7.0E-02 1 60 134, 137-Cs 15(10)(a), 1.0E-02 130 15 60 150 18 140-Ba-La 15(b) 15(b)

CY-GI-170-300 Revision 36 Page 101 of 120 Table 8-3 Table Notation (a) LLD for drinking water (b) Total for parent and daughter The LLD shall be calculated as described in Notation (a) to Table 4-1

CY-GI-170-300 Revision 36 Page 102 of 120 Table 8-4 Reporting Levels for Radioactivity Concentrations in Environmental Samples Analysis Water Airbourne Fish Milk Broad Leaf (pCi/l) Particulate or (pCi/kg,wet) (pCi/l) Vegetables Gas (pCi/kg, wet)

(pCi/m3)

H-3 2.0E+04 Mn-54 1000 3.0E+04 Fe-59 400 1.0E+04 Co-58 1000 3.0E+04 Co-60 300 1.0E+04 Zn-65 300 2.0E+04 Zr-Nb-95 400(a)

I-131 2 0.9 3 1.0E+02 Cs-134 30 10 1.0E+03 60 1.0E+03 Cs-137 50 20 2.0E+03 70 2.0E+03 Ba-La-140 200(a) 300

CY-GI-170-300 Revision 36 Page 103 of 120 Table 8-4 Table Notation (a) Total for parent and daughter Decay correction in analysis of environmental samples is taken from the end of the sampling time not from the midpoint of the sample period.

CY-GI-170-300 Revision 36 Page 104 of 120 Table 8-5 D/Q and X/Q 5 Year Average 1995 - 1999 Plant Vent Distance to section boundary in meters:

Direction 804m 1609m 2416m 3218m 4022m 4827m 5632m 6436m 7240m 8045m D/Q N 1.74E-09 8.20E-10 5.54E-10 3.36E-10 2.45E-10 1.85E-10 1.41E-10 1.13E-10 1.01E-10 3.86E-10 NNE 1.18E-09 6.28E-10 3.99E-10 2.75E-10 2.02E-10 1.53E-10 1.29E-10 9.54E-11 8.50E-11 2.26E-10 NE 1.74E-09 1.84E-09 6.26E-10 3.86E-10 2.83E-10 2.14E-10 1.64E-10 1.32E-10 1.09E-10 9.17E-11 ENE 2.99E-09 1.43E-09 8.56E-10 5.76E-10 4.25E-10 3.14E-10 2.39E-10 1.91E-10 1.58E-10 1.32E-10 E 5.11E-09 2.20E-09 1.23E-09 7.96E-10 5.69E-10 4.17E-10 5.09E-10 6.34E-10 4.74E-10 4.00E-10 ESE 7.41E-09 3.19E-09 1.67E-09 1.13E-09 9.34E-10 9.18E-10 7.27E-10 5.16E-10 4.26E-10 3.54E-10 SE 4.14E-09 1.93E-09 9.91E-10 7.32E-10 7.05E-10 5.40E-10 4.00E-10 3.05E-10 2.52E-10 2.09E-10 SSE 1.32E-09 6.71E-10 3.72E-10 2.68E-10 2.58E-10 1.88E-10 1.38E-10 2.76E-10 8.94E-11 7.48E-11 S 2.15E-09 1.29E-09 7.37E-10 6.54E-10 4.95E-10 3.58E-10 2.61E-10 2.02E-10 1.67E-10 1.39E-10 SSW 2.57E-09 1.48E-09 8.43E-10 5.50E-10 4.00E-10 3.95E-10 2.87E-10 2.22E-10 1.83E-10 1.52E-10 SW 2.88E-09 1.53E-09 8.50E-10 5.66E-10 4.79E-10 4.41E-10 3.20E-10 2.49E-10 2.05E-10 1.71E-10 WSW 2.21E-09 1.18E-09 6.93E-10 4.73E-10 3.57E-10 3.04E-10 4.38E-10 3.39E-10 2.80E-10 2.33E-10 W 9.54E-10 5.40E-10 3.27E-10 2.21E-10 1.61E-10 1.20E-10 1.76E-10 2.71E-10 2.25E-10 1.87E-10 WNW 1.29E-10 9.58E-11 6.87E-11 4.91E-11 1.18E-10 2.83E-11 2.23E-11 1.82E-11 1.51E-11 1.27E-11 NW 4.80E-10 3.03E-10 2.03E-10 1.41E-10 1.05E-10 8.01E-11 6.25E-11 5.05E-11 4.20E-11 3.52E-11 NNW 1.37E-09 7.06E-10 4.40E-10 3.01E-10 2.21E-10 1.73E-10 1.29E-10 1.03E-10 8.59E-11 7.19E-11

CY-GI-170-300 Revision 36 Page 105 of 120 Direction 804m 1609m 2416m 3218m 4022m 4827m 5632m 6436m 7240m 8045m X/Q N 8.56E-08 9.42E-08 9.19E-08 8.10E-08 6.99E-08 6.15E-08 5.38E-08 5.41E-08 6.17E-08 1.20E-07 NNE 7.17E-08 8.06E-08 8.23E-08 7.45E-08 7.21E-08 5.83E-08 5.28E-08 4.81E-08 6.98E-08 1.33E-07 NE 8.27E-08 9.48E-08 9.36E-08 8.33E-08 7.23E-08 6.94E-08 5.63E-08 5.05E-08 4.57E-08 4.18E-08 ENE 1.05E-07 1.16E-07 1.06E-07 8.89E-08 7.41E-08 6.26E-08 5.35E-08 4.66E-08 4.13E-08 3.70E-08 E 1.91E-07 1.81E-07 1.53E-07 1.16E-07 9.09E-08 7.32E-08 8.82E-08 7.67E-08 6.51E-08 5.61E-08 ESE 2.43E-07 2.13E-07 1.70E-07 1.35E-07 1.11E-07 9.27E-08 7.19E-08 5.86E-08 4.96E-08 4.27E-08 SE 1.47E-07 1.38E-07 1.15E-07 1.12E-07 9.67E-08 7.43E-08 5.79E-08 5.33E-08 5.21E-08 3.44E-08 SSE 6.06E-08 6.56E-08 5.66E-08 5.38E-08 4.55E-08 3.40E-08 2.64E-08 2.16E-08 1.83E-08 1.58E-08 S 1.06E-07 1.49E-07 1.27E-07 9.80E-08 7.10E-08 5.27E-08 4.09E-08 3.34E-08 2.83E-08 2.42E-08 SSW 1.06E-07 1.59E-07 1.54E-07 1.04E-07 7.61E-08 6.96E-08 5.35E-08 4.35E-08 3.68E-08 3.16E-08 SW 1.06E-07 1.39E-07 1.43E-07 1.18E-07 1.01E-07 9.76E-08 7.60E-08 6.22E-08 5.27E-08 4.53E-08 WSW 1.13E-07 1.40E-07 1.33E-07 1.23E-07 1.20E-07 1.30E-07 1.47E-07 1.20E-07 1.02E-07 8.78E-08 W 7.19E-08 1.07E-07 9.56E-08 7.99E-08 6.66E-08 5.67E-08 9.77E-08 9.14E-08 7.77E-08 6.68E-08 WNW 6.07E-09 1.64E-08 1.96E-08 1.87E-08 1.68E-08 1.49E-08 1.33E-08 1.20E-08 1.08E-08 9.88E-09 NW 1.99E-08 3.49E-08 3.64E-08 3.24E-08 2.80E-08 2.42E-08 2.11E-08 1.86E-08 1.66E-08 1.50E-08 NNW 6.23E-08 6.98E-08 6.67E-08 5.74E-08 4.86E-08 4.15E-08 3.58E-08 3.20E-08 2.80E-08 2.53E-08

CY-GI-170-300 Revision 36 Page 106 of 120 Table 8-6 D/Q and X/Q 5 Year Average 1995 - 1999 Containment Vent Distance to section boundary in meters:

Direction 804m 1609m 2416m 3218m 4022m 4827m 5632m 6436m 7240m 8045m D/Q N 1.88E-08 5.95E-09 2.88E-09 1.85E-09 1.31E-09 9.45E-10 6.86E-10 5.31E-10 4.42E-10 3.90E-10 NNE 1.86E-08 5.88E-09 2.85E-09 1.83E-09 1.29E-09 9.35E-10 6.79E-10 5.25E-10 4.39E-10 3.90E-10 NE 1.99E-08 6.30E-09 3.05E-09 1.96E-09 1.38E-09 1.00E-09 7.27E-10 5.62E-10 4.64E-10 3.86E-10 ENE 1.98E-08 6.28E-09 3.04E-09 1.95E-09 1.38E-09 1.08E-09 7.24E-10 5.60E-10 4.62E-10 3.84E-10 E 1.99E-08 6.30E-09 3.05E-09 1.96E-09 1.38E-09 1.00E-09 7.41E-10 5.75E-10 4.75E-10 3.95E-10 ESE 1.78E-08 5.66E-09 2.74E-09 1.77E-09 1.27E-09 9.19E-10 6.67E-10 5.16E-10 4.11E-10 3.54E-10 SE 1.01E-08 3.23E-09 1.57E-09 1.05E-09 7.51E-10 5.43E-10 3.94E-10 3.05E-10 2.52E-10 2.09E-10 SSE 3.66E-09 1.18E-09 5.75E-10 3.92E-10 2.85E-10 2.06E-10 1.50E-10 1.16E-10 9.56E-11 7.94E-11 S 6.65E-09 2.14E-09 1.07E-09 7.06E-10 4.99E-10 3.60E-10 2.62E-10 2.02E-10 1.67E-10 1.39E-10 SSW 7.05E-09 2.28E-09 1.17E-09 7.53E-10 5.35E-10 3.95E-10 2.87E-10 2.22E-10 1.83E-10 1.52E-10 SW 7.77E-09 2.50E-09 1.22E-09 7.94E-10 5.98E-10 4.43E-10 3.22E-10 2.49E-10 2.05E-10 1.71E-10 WSW 1.04E-08 3.32E-09 1.61E-09 1.04E-09 7.44E-10 5.64E-10 4.39E-10 3.39E-10 2.80E-10 2.33E-10 W 8.42E-09 2.68E-09 1.30E-09 8.33E-10 5.89E-10 4.27E-10 3.46E-10 2.72E-10 2.25E-10 1.87E-10 WNW 2.68E-09 1.18E-09 4.16E-10 2.67E-10 1.89E-10 1.36E-10 9.92E-11 7.67E-11 6.34E-11 5.27E-11 NW 5.20E-09 1.66E-09 8.05E-10 5.16E-10 3.65E-10 2.64E-10 1.92E-10 1.48E-10 1.23E-10 1.02E-10 NNW 1.13E-08 3.58E-09 1.74E-09 1.12E-09 7.88E-10 5.70E-10 4.14E-10 3.20E-10 2.65E-10 2.20E-10

CY-GI-170-300 Revision 36 Page 107 of 120 Direction 804m 1609m 2416m 3218m 4022m 4827m 5632m 6436m 7240m 8045m X/Q N 1.73E-06 6.24E-07 3.58E-07 2.44E-07 1.52E-07 1.42E-07 1.15E-07 9.67E-08 9.34E-08 9.86E-08 NNE 2.15E-06 7.57E-07 4.37E-07 3.01E-07 2.26E-07 1.78E-07 1.46E-07 1.24E-07 1.26E-07 1.48E-07 NE 1.94E-06 7.00E-07 3.99E-07 2.70E-07 2.00E-07 1.55E-07 1.25E-07 1.05E-07 9.02E-08 7.88E-08 ENE 1.20E-06 4.40E-07 2.46E-07 1.64E-07 1.19E-07 9.14E-08 7.26E-08 6.03E-08 5.17E-08 4.50E-08 E 1.05E-06 3.91E-07 2.18E-07 1.44E-07 1.03E-07 7.84E-08 6.58E-08 5.39E-08 4.59E-08 3.96E-08 ESE 8.27E-07 3.15E-07 1.83E-07 1.24E-07 8.99E-08 6.76E-08 5.27E-08 4.32E-08 3.67E-08 3.16E-08 SE 5.82E-07 2.44E-07 1.56E-07 1.17E-07 8.36E-08 6.27E-08 4.88E-08 4.00E-08 3.39E-08 2.92E-08 SSE 3.27E-07 1.42E-07 8.76E-08 6.27E-08 4.44E-08 3.31E-08 2.57E-08 2.09E-08 1.77E-08 1.52E-08 S 5.09E-07 2.29E-07 1.40E-07 8.96E-08 6.92E-08 4.71E-08 3.65E-08 2.98E-08 2.52E-08 2.16E-08 SSW 4.64E-07 2.44E-07 1.61E-07 1.03E-07 7.31E-08 5.49E-08 4.27E-08 3.49E-08 2.95E-08 2.54E-08 SW 4.99E-07 2.52E-07 1.95E-07 1.36E-07 1.00E-07 7.59E-08 5.94E-08 4.87E-08 4.13E-08 3.56E-08 WSW 9.88E-07 3.99E-07 2.57E-07 1.99E-07 1.61E-07 1.37E-07 1.11E-07 9.16E-08 7.79E-08 6.73E-08 W 9.24E-07 3.62E-07 2.15E-07 1.49E-07 1.10E-07 8.62E-08 8.29E-08 6.83E-08 5.82E-08 5.03E-08 WNW 3.25E-07 1.26E-07 7.51E-08 5.22E-08 3.92E-08 3.08E-08 2.51E-08 2.11E-08 1.83E-08 1.60E-08 NW 5.27E-07 1.98E-07 1.14E-07 7.80E-08 5.78E-08 4.50E-08 3.62E-08 3.03E-08 2.62E-08 2.29E-08 NNW 9.39E-07 3.46E-07 1.98E-07 1.34E-07 9.89E-08 7.65E-08 6.13E-08 5.12E-08 4.41E-08 3.85E-08

CY-GI-170-300 Revision 36 Page 108 of 120 Table 8-7 D/Q and X/Q 5 Year Average 1995 - 1999 Air Ejector Distance to section boundary in meters:

Direction 804m 1609m 2416m 3218m 4022m 4827m 5632m 6436m 7240m 8045m D/Q N 2.02E-08 6.38E-09 3.09E-09 1.98E-09 1.40E-09 1.01E-09 7.34E-10 5.68E-10 4.69E-10 3.90E-10 NNE 2.07E-08 6.55E-09 3.17E-09 2.03E-09 1.44E-09 1.04E-09 7.54E-10 5.83E-10 4.81E-10 4.00E-10 NE 2.11E-08 6.66E-09 3.22E-09 2.07E-09 1.46E-09 1.06E-09 7.67E-10 5.93E-10 4.89E-10 4.07E-10 ENE 2.05E-08 6.49E-09 3.14E-09 2.01E-09 1.42E-09 1.03E-09 7.47E-10 5.77E-10 4.77E-10 3.96E-10 E 2.04E-08 6.46E-09 3.13E-09 2.01E-09 1.42E-09 1.02E-09 7.43E-10 5.75E-10 4.75E-10 3.95E-10 ESE 1.84E-08 5.80E-09 2.81E-09 1.80E-09 1.27E-09 9.19E-10 6.67E-10 5.16E-10 4.26E-10 3.54E-10 SE 1.08E-08 3.43E-09 1.66E-09 1.06E-09 7.51E-10 5.43E-10 3.94E-10 3.05E-10 2.52E-10 2.09E-10 SSE 4.12E-09 1.30E-09 6.30E-10 4.04E-10 2.85E-10 2.06E-10 1.50E-10 1.16E-10 9.56E-11 7.94E-11 S 7.19E-09 2.27E-09 1.10E-09 7.06E-10 4.99E-10 3.60E-10 2.62E-10 2.02E-10 1.67E-10 1.39E-10 SSW 7.89E-09 2.49E-09 1.21E-09 7.74E-10 5.47E-10 3.95E-10 2.87E-10 2.22E-10 1.83E-10 1.52E-10 SW 8.85E-09 2.80E-09 1.35E-09 8.68E-10 6.13E-10 4.43E-10 3.22E-10 2.49E-10 2.05E-10 1.71E-10 WSW 1.21E-08 3.82E-09 1.85E-09 1.18E-09 8.37E-10 6.05E-10 4.39E-10 3.39E-10 2.80E-10 2.33E-10 W 9.68E-09 3.06E-09 1.48E-09 9.49E-10 6.71E-10 4.85E-10 3.52E-10 2.72E-10 2.25E-10 1.87E-10 WNW 3.28E-09 1.04E-09 5.54E-10 3.22E-10 2.51E-10 1.64E-10 1.19E-10 9.22E-11 7.62E-11 6.33E-11 NW 5.88E-09 1.86E-09 8.99E-10 5.77E-10 4.07E-10 2.94E-10 2.14E-10 1.65E-10 1.37E-10 1.13E-10 NNW 1.22E-08 3.84E-09 1.86E-09 1.19E-09 8.43E-10 6.09E-10 4.42E-10 3.42E-10 2.82E-10 2.35E-10

CY-GI-170-300 Revision 36 Page 109 of 120 Direction 804m 1609m 2416m 3218m 4022m 4827m 5632m 6436m 7240m 8045m X/Q N 2.34E-06 8.13E-07 4.56E-07 3.06E-07 2.24E-07 1.72E-07 1.37E-07 1.13E-07 9.72E-08 8.43E-08 NNE 3.01E-06 1.02E-06 5.81E-07 3.94E-07 2.91E-07 2.25E-07 1.80E-07 1.49E-07 1.28E-07 1.11E-07 NE 2.48E-06 8.70E-07 4.88E-07 3.27E-07 2.40E-07 1.84E-07 1.47E-07 1.21E-07 1.04E-07 9.01E-08 ENE 1.51E-06 5.37E-07 2.94E-07 1.92E-07 1.39E-07 1.05E-07 8.25E-08 6.79E-08 5.79E-08 5.01E-08 E 1.28E-06 4.52E-07 2.44E-07 1.58E-07 1.13E-07 8.50E-08 6.65E-08 5.46E-08 4.65E-08 4.01E-08 ESE 9.59E-07 3.28E-07 1.75E-07 1.13E-07 8.09E-08 6.08E-08 4.75E-08 3.90E-08 3.31E-08 2.85E-08 SE 7.73E-07 2.65E-07 1.42E-07 9.20E-08 6.57E-08 4.95E-08 3.87E-08 7.93E-05 2.70E-08 2.33E-08 SSE 4.47E-07 1.54E-07 8.18E-08 5.27E-08 3.75E-08 2.80E-08 2.18E-08 1.79E-08 1.52E-08 1.68E-08 S 6.59E-07 2.27E-07 1.21E-07 7.75E-08 5.49E-08 4.11E-08 3.20E-08 2.61E-08 2.21E-08 1.90E-08 SSW 6.43E-07 2.22E-07 1.19E-07 7.73E-08 5.52E-08 4.16E-08 3.25E-08 2.67E-08 2.26E-08 1.95E-08 SW 7.75E-07 2.65E-07 1.45E-07 9.61E-08 6.96E-08 5.31E-08 4.19E-08 3.46E-08 2.95E-08 2.55E-08 WSW 1.49E-06 5.11E-07 2.86E-07 1.91E-07 1.40E-07 1.08E-07 8.58E-08 7.11E-08 6.08E-08 5.27E-08 W 1.29E-06 4.52E-07 2.51E-07 1.67E-07 1.22E-07 9.30E-08 7.37E-08 6.09E-08 5.21E-08 4.51E-08 WNW 5.27E-07 1.88E-07 1.05E-07 6.99E-08 5.10E-08 3.91E-08 3.10E-08 2.56E-08 2.19E-08 1.90E-08 NW 7.90E-07 2.79E-07 1.54E-07 1.02E-07 7.39E-08 5.63E-08 4.45E-08 3.67E-08 3.14E-08 2.71E-08 NNW 1.28E-06 4.51E-07 2.49E-07 1.64E-07 1.19E-07 9.06E-08 7.15E-08 5.90E-08 5.04E-08 4.36E-08

CY-GI-170-300 Revision 36 Page 110 of 120 8.3 LAND USE CENSUS 8.3.1. CONTROL A Land Use Census shall be conducted annually between June 1 and October 1, and shall identify within a distance of 5 miles the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 square feet producing broad leaf vegetation.

(In lieu of a garden census, broad leaf vegetation sampling of at least three different kinds of vegetation may be performed in an onsite garden located in the meteorological sector with the highest average annual growing season deposition parameter (D/Q) OR another location with a higher D/Q than the location of the maximally exposed individual.)

8.3.2 APPLICABILITY

At all Times.

8.3.3 ACTION

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 Section 5.3.11 (Surveillance Requirements) of the ODCM, identify the new location(s) in the next Annual Radioactive Effluent Release Report.

With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Section 8.1.1 (Radiological Environmental Monitoring -

Controls), add the new location(s) within 30 days to the REMP described in the ODCM, if permission from the owner to collect samples can be obtained and sufficient sample volume is available. The sampling location(s), excluding Control location(s), having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling location(s).

8.3.4 SURVEILLANCE REQUIREMENTS The Land Use Census shall be conducted between June 1 and October 1 of each year using a method that will best provide the necessary information such as by door-to-door survey, vehicular survey, aerial survey, or by consulting local agricultural authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Section 9.1 of the ODCM.

CY-GI-170-300 Revision 36 Page 111 of 120

8.3.5 BASES

This specification is provided to ensure that changes in the use of areas at or beyond the SITE BOUNDARY are identified and that modifications to the REMP given in the ODCM are made if required by the results of this census. Information from methods such as the door-to door survey, vehicular survey, aerial survey, or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of SectionIV.B.3 of Appendix I to 10 CFR 50.

Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored, since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) there was a vegetation yield of 2 kg/m2.

CY-GI-170-300 Revision 36 Page 112 of 120 8.4 INTERLABORATORY COMPARISON PROGRAM 8.4.1 CONTROL Analyses shall be performed on all radioactive materials supplied as part of an Interlaboratory Comparison Program, that correspond to samples required by the REMP, and that has been approved by the Commission, if such a program exists.

8.4.2 APPLICABILITY

At all times.

8.4.3 ACTION

With analyses not performed as required above, report the corrective actions taken to prevent recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Section 8.4.1 (Interlaboratory Comparison Program -

Control) of the ODCM.

8.4.4 SURVEILLANCE REQUIREMENTS The Interlaboratory Comparison Program is described in and implemented by procedure CH-QC-INTERLAB. 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 Section 8.4.1 (Interlaboratory Comparison Program - Control) of the ODCM.

8.4.5 BASES

The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the Quality Assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to10 CFR 50.

CY-GI-170-300 Revision 36 Page 113 of 120 9.0 REPORTING REQUIREMENTS 9.1 Annual Radiological Environmental Operating Report An Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 15 of each year. The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with background (control) samples and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The report shall also include the results of the Land Use Census as required.

This report shall include any new location(s) identified by the Land Use Census which yield a calculated dose or dose commitment greater than those forming the basis of Section 8.1.1 (Radiological Environmental Monitoring - Controls)

The report shall also contain a discussion which identifies the causes of the unavailability of milk or leafy vegetable samples and identifies locations for obtaining replacement samples in accordance with Section 8.1.1 (Radiological Environmental Monitoring - Controls).

The Annual Radiological Environmental Operating Report shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures of Section 5.0 of the ODCM, the summarized and tabulated results of these analyses and measurements shall be in the format of Table 9-1, derived from the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The report shall also include the following:

a. a summary description of the radiological environmental monitoring program including a map of all sampling locations keyed to a table giving distances and directions from the reactor centerline; and

b. the results of the licensee participation in an Interlaboratory Comparison Program, and the corrective actions taken if the specified program is not being performed as required by Section 8.4.1 (Interlaboratory Comparison Program - Control).

c. a discussion of all deviations from the sampling schedule specified in Table 8-1.

CY-GI-170-300 Revision 36 Page 114 of 120

d. a discussion of any environmental sample measurements that exceed the reporting levels but are not the result of plant effluents, as required in the second ACTION of Section 8.1.3.

e. a discussion of all analyses in which the required LLD was not achievable.

CY-GI-170-300 Revision 36 Page 115 of 120 9.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT The Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year of operation shall be submitted prior to May 15 each year. This report shall include a summary, on a quarterly basis, of the quantities of radioactive liquid and gaseous effluents and solid waste released as outlined in Regulatory Guide 1.21, Revision 1, with data summarized on a quarterly basis following the format of the Appendix thereof. For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories: classes of solid wastes (as defined by 10 CFR 61), type of container (e.g. LSA, Type A, Type B, etc.) and solidification agent or absorbent (e.g., Portland cement).

The Radioactive Effluent Release Report shall include an assessment of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each of the previous four calendar quarters as outlined in Regulatory Guide 1.21, Revision 1. In addition, the site boundary maximum noble gas gamma air and beta air doses shall be evaluated. The assessment of radiation doses shall be performed in accordance with Controls 1.2 and 2.3. This same report shall include an annual summary of hourly meteorological data collected over the previous calendar year. The Radioactive Effluent Release Report shall include a discussion which identifies the circumstances which prevented any required detection limits for effluent sample analyses being met. This report shall also include an assessment of the radiation doses from radioactive gaseous and liquid effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM.

The Annual Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely maximum exposed MEMBER OF THE PUBLIC from reactor operation, including doses from effluent releases and direct radiation, for the previous calendar year to demonstrate compliance with 40 CFR 190.

This report shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

This report shall include any changes made during the reporting period to the Offsite Dose Calculation Manual (ODCM). Licensee may make changes to this ODCM and shall submit to the Commission, with the Radioactive Effluent Release Report for the period in which any change(s) is made, a copy of the new ODCM and a summary containing:

CY-GI-170-300 Revision 36 Page 116 of 120

a. sufficiently detailed information to support the rationale for the change;

b. a determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and

c. documentation of the fact that the change has been reviewed and found acceptable by the Plant Operations Review Committee.

Licensee initiated changes shall become effective after review and acceptance by the Plant Operations Review Committee on a date specified by the licensee.

This report shall include any changes made during the reporting period to the Process Control Program (PCP). This report shall include a discussion of any major changes to the radioactive waste treatment systems.

The Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report will be prepared and submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555 and a copy to the Regional Administrator of the USNRC, Region I.

CY-GI-170-300 Revision 36 Page 117 of 120 9.3 SPECIAL REPORTS Guidance is given for each of these reports in the applicable Control. The following general guidelines are included here for calculating dose to an exposed individual or the MEMBERS OF THE PUBLIC for preparation of Special Reports:

a. The maximally exposed real MEMBER OF THE PUBLIC will generally be the same individual considered in the ODCM.

b. Dose contributions to the maximally exposed individual need only be considered to be those resulting from the Ginna plant itself. All other uranium fuel cycle facilities or operations are of sufficient distance to contribute a negligible portion of the individual's dose.

c. For determining the total dose to the maximally exposed individual from the major gaseous and liquid effluent pathways and from direct radiation, dose evaluation techniques used in preparing the Special Report will be those described in the ODCM, or other applicable methods where appropriate.

d. The contribution from direct radiation may be estimated by effluent dispersion modeling or calculated from the results of the environmental monitoring program for direct radiation.

CY-GI-170-300 Revision 36 Page 118 of 120 Table 9-1 Radiological Environmental Monitoring Program Summary R.E. GINNA NUCLEAR POWER PLANT Docket No. 50-244 WAYNE, NEW YORK Pathway Sampled Type And LLD Indicator Location With Highest Annual Control Unit Of Total Locations Mean Locations Measurement Number Of Mean (a)

Analyses Range Name, Distance Mean (a) Range Mean (a) Range And Direction Air: Particulate Gross Beta (pCi/Cu.M.)

Gamma Scan Iodine Gamma Scan Direct Dosimetry Gamma Radiation: (mrem/quarter)

Water: Drinking Gross Beta (pCi/liter)

Gamma Scan Iodine Surface Gross Beta (pCi/liter)

Gamma Scan Iodine Shoreline Sediment Gamma Scan Milk: (pCi/liter) Iodine Gamma Scan Fish: Gamma Scan Vegetation: Gamma Scan (a) Mean and range based on detectable measurements only. Fraction of detectable measurements at specified locations in parentheses.

CY-GI-170-300 Revision 36 Page 119 of 120

10.0 REFERENCES

10.1 R. E. Ginna Nuclear Power Plant Unit No. 1, Appendix A to Operating License No.DPR-18, Technical Specifications, Rochester Gas and Electric Corporation, Docket 50-244 10.2 USNRC, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, NUREG-0133 (October, 1978).

10.3 USNRC, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Regulatory Guide 1.109, Revision 1 (October 1977).

10.4 "R.E. Ginna Nuclear Power Plant Tracer Dilution Study for the Town of Ontario Municipal Drinking Water Intake," HydroQual, Inc. (May 28, 2010).

10.5 R. E. Ginna Nuclear Power Plant, Calculations to Demonstrate Compliance with the Design Objectives of 10 CFR Part 50, Appendix I, Rochester Gas and Electric Corporation, (June, 1977).

10.6 USNRC, Methods for Estimating Atmospheric Transport and dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Regulatory Guide 1.111, Revision 1 (July, 1977).

10.7 R. E. Ginna Nuclear Power Plant, Incident Evaluation, Ginna Steam Generator Tube Failure Incident January 25, 1982, Rochester Gas and Electric Corporation, (April12, 1982).

10.8 Pelletier, C. A., et. al., Sources of Radioiodine at Pressurized Water Reactors, EPRI NP-939 (November 1978).

10.9 NUREG-1301, Offsite Dose Calculation Manual Guidance:

Standard Radiological Effluent Controls for pressurized Water Reactors.

10.10 International Commission on Radiological Protection, Publication 30 Supplement to Part I, "Limits for Intake of Radionuclides by Workers" (July 1978).

CY-GI-170-300 Revision 36 Page 120 of 120 10.11 International Commission on Radiological Protection (ICRP) Publication 2, Permissible Dose For Internal Radiation, 1959.

10.12 Nuclear Regulatory Commission Reg. Guide 1.21, Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste, Revision 1, June 1974.

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

10.14 Title 10 Code of Federal Regulation Part 20 (10 CFR 20), Standards for Protection Against Radiation.

10.15 Title 10 Code of Federal Regulation Part 61 (10 CFR 61), Licensing Requirements for Land Disposal of Radioactive Waste.

10.16 Title 10 Code of Federal Regulation Part 71 (10 CFR 71), Packaging and Transportation of Radioactive Material.

10.17 Title 40 Code of Federal Regulation Part 141 (40 CFR 141), National Primary Drinking Water Standards.

10.18 Title 40 Code of Federal Regulation Part 190 (40 CFR 190), Environmental Radiation Protection Standards for Nuclear Power Operations.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT:

JANUARY 1, 2019 - DECEMBER 31, 2019 MAY 2020 R.E. Ginna Nuclear Power Plant 1503 Lake Road Ontario, New York 14519

January 1 - December 31, 2019 Docket Nos. 50-244 TABLE OF CONTENTS LIST OF FIGURES ........................................................................................................................ ii LIST OF TABLES......................................................................................................................... iii

1. EXECUTIVE

SUMMARY

....................................................................................................1

2. INTRODUCTION..................................................................................................................2 2.1 Station Description............................................................................................................2 2.2 Program Description and Background ..............................................................................2 2.3 Program Objectives ...........................................................................................................2

3. PROGRAM DESCRIPTION .................................................................................................3 3.1 Sample Collection and Analysis .......................................................................................3 3.2 Data Interpretation.............................................................................................................3 3.3 Quality Assurance Program ..............................................................................................3 3.4 Land Use Survey ...............................................................................................................4 3.5 Program Exceptions ..........................................................................................................5 3.6 Corrections to Previous Reports........................................................................................5

4. RESULTS AND DISCUSSIONS ..........................................................................................6 4.1 Aquatic Environment ........................................................................................................6 4.1.a Surface and Drinking Water.......................................................................................6 4.1.b Aquatic Organisms .....................................................................................................7 4.1.c Shoreline Sediment ....................................................................................................7 4.2 Atmospheric Environment ................................................................................................7 4.2.a Air Iodine ...................................................................................................................8 4.2.b Air Particulate Filters .................................................................................................8 4.3 Terrestrial Environment ....................................................................................................8 4.3.a Vegetation ..................................................................................................................9 4.3.b Milk ............................................................................................................................9 4.4 Direct Radiation ................................................................................................................9 4.5 Groundwater....................................................................................................................10 4.6 Summary and Conclusion ...............................................................................................11

5. REFERENCES.....................................................................................................................11 Appendix A REMP Sample Locations .....................................................................................15 Appendix B REMP Analytical Results.....................................................................................24 Appendix C Quality Assurance Program .................................................................................53 Appendix D Land Use Survey ..................................................................................................66 Appendix E Interpretations and Graphical Representations70 i

January 1 - December 31, 2019 Docket Nos. 50-244 LIST OF FIGURES Figure Title Page A-1 Map of New York State and Lake Ontario Showing Location of R.E. Ginna Nuclear Power Plant ........................................................................................................................20 A-2 Onsite Sample Locations ...................................................................................................21 A-3 Offsite Sample Locations (TLDs and milk farms within 5 miles).....................................22 A-4 Water Sample, Milk Farms and TLD Locations................................................................23 E-1 E-Series 1, Table B-1 (Gross Beta Values for Surface and Drinking Water)....72 E-2 E-Series 2, Table B-5 / B-6 (Beta in Air Particulates)...76 E-3 E-Series 3, Table B-12 (Direct Radiation).81 E-4 E-Series 4, Table B-13 (Tritium in Groundwater).....94 ii

January 1 - December 31, 2019 Docket Nos. 50-244 LIST OF TABLES Table Title Page 1 Synopsis of R.E. Ginna Nuclear Power Plant Radiological Environmental Monitoring Program..............................................................................................................................12 2 Annual Summary of Radioactivity in the Environs of the R.E. Ginna Nuclear Power Plant

............................................................................................................................................13 A-1 Locations of Environmental Sampling Stations for the R.E. Ginna Nuclear Plant..............17 B-1 Concentration of Tritium, Gamma Emitters and Gross Beta in Surface and Drinking Water

............................................................................................................................................26 B-2 Concentration of Gamma Emitters in the Flesh of Edible Fish ...........................................29 B-3 Concentration of Gamma Emitters in Sediment...................................................................30 B-4 Concentration of Iodine-131 in Filtered Air (Charcoal Cartridges).....................................31 B-5 Concentration of Beta Emitters in Air Particulates - Onsite Samples .................................34 B-6 Concentration of Beta Emitters in Air Particulates - Offsite Samples .................................38 B-7 Concentration of Gamma Emitters in Air Particulates.........................................................40 B-8 Concentration of Gamma Emitters in Vegetation Samples..................................................42 B-9 Concentration of Gamma Emitters (including I-131) in Milk .............................................43 B-10 Typical MDA Ranges for Gamma Spectrometry.................................................................44 B-11 Typical LLDs for Gamma Spectrometry .............................................................................45 B-12 Direct Radiation ...................................................................................................................46 B-13 Groundwater Monitoring Wells ...........................................................................................50 C-1 Results of Participation in Cross Check Programs...............................................................55 C-2 Results of Quality Assurance Program ................................................................................58 C-3 Teledyne Brown Engineerings Typical MDAs for Gamma Spectrometry .........................65 D-1 Land Use Survey Distances..................................................................................................68 iii

January 1 - December 31, 2019 Docket Nos. 50-244

1. EXECUTIVE

SUMMARY

The Radiological Environmental Monitoring Program (REMP) is a comprehensive surveillance program, which is implemented to assess the impact of site operations on the environment and compliance with 10 CFR 50 Appendix I and 40 CFR 190. Samples are collected from the aquatic and terrestrial pathways applicable to the site. The aquatic pathways include Lake Ontario fish, surface waters, groundwater, and lakeshore sediment. The terrestrial pathways include airborne particulate and radioiodine, milk, food products, and direct radiation.

Results of the monitoring program for the 2019 operational period for R.E. Ginna Nuclear Power Plant are included in this report. This report presents a synopsis of the REMP (Table 1),

summary of the detectable activity analytical results (Table 2), sampling locations (Appendix A),

compilation of the analytical data (Appendix B), results of the Quality Assurance Program (Appendix C), and results of the Land Use Survey (Appendix D). Interpretation of the data and conclusions are presented in the body of this report.

The results of the REMP verify that the effluent releases did not impact the environment with a measurable concentration of radioactive materials and/or levels of radiation that are higher than expected. The 2019 results for all pathways sampled were consistent with the previous five-year historical results and exhibited no adverse trends. The results of the REMP continue to demonstrate that the operation of the plant does not result in a measurable dose to a member of the general population, or adversely impact the environment as a result of radiological effluents.

The program continues to demonstrate that the dose to a member of the public, as a result of the operation of R.E. Ginna Nuclear Power Plant, remains significantly below the federally required dose limits specified in 10 CFR 20 and 40 CFR 190.

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January 1 - December 31, 2019 Docket Nos. 50-244

2. INTRODUCTION 2.1 Station Description R.E. Ginna Nuclear Power Plant (Ginna), owned by Exelon Generation, is an operating nuclear generating facility consisting of one pressurized water reactor. Ginna achieved criticality in September 1969 and commenced commercial operation in July 1970. The location of the plant in relation to local metropolitan areas is depicted in Appendix A, Figure A-1.

2.2 Program Description and Background The Annual Radiological Environmental Operating Report (AREOR) is published in accordance with Section 8.0 of the Offsite Dose Calculation Manual (ODCM, Ref. 1) and the Plants Technical Specifications (Ref. 2). This report describes the REMP, and its implementation as required by the ODCM. The environmental surveillance data collected during this reporting period were compared with that generated in previous periods whenever possible to evaluate the environmental radiological impact of the R.E. Ginna Nuclear Power Plant. Results of the monitoring program for the pre-operational and previous operational periods through 2018 have been reported in a series of previously released documents.

The REMP is implemented to measure radioactivity in the aquatic and terrestrial pathways. The aquatic pathways include Lake Ontario fish, surface waters, groundwater, and lakeshore sediment. Measurement results of the samples representing these pathways contained only natural background radiation or low concentrations of Cs-137 resulting from past atmospheric nuclear weapons testing. Terrestrial pathways monitored included airborne particulate and radioiodine, milk, food products, and direct radiation.

2.3 Program Objectives The objectives of the REMP for the R.E. Ginna Nuclear Power Plant are:

a. Measure and evaluate the effects of plant operation on the environment.

b. Monitor background radiation levels in the environs of the Ginna site.

c. Demonstrate compliance with the environmental conditions and requirements of applicable state and federal regulations, including the ODCM and 40 CFR 190.

d. Provide information by which the general public can evaluate environmental aspects of the operation of R.E. Ginna Nuclear Power Plant.

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January 1 - December 31, 2019 Docket Nos. 50-244

3. PROGRAM DESCRIPTION 3.1 Sample Collection and Analysis The locations of the individual sampling stations are listed in Table A-1 and shown in Figures A-2 and A-3. All samples were collected and analyzed by Exelon personnel or its contractors in accordance with Ginna procedures (Ref. 3).

During 2019, 1350 samples were collected for analysis by gross beta counting, tritium, and/or gamma spectroscopy. These included 89 surface water samples, 18 fish samples, 5 sediment samples, 623 air particulate samples, 311 air iodine samples, 28 vegetation samples, 38 milk samples, 74 groundwater samples, and 164 dosimeter measurements. Deviations from the REMP sampling schedule are described in section 3.5. This monitoring program satisfied the minimum number of samples required by the ODCM for all pathways.

Ginna Chemistry personnel collected all REMP samples. Analysis was performed at either Ginnas onsite laboratory (groundwater samples), Environmental Dosimetry Company in Sterling Massachusetts (direct radiation samples), or Exelon Industrial Services - Ft. Smallwood Environmental Laboratory in Baltimore, Maryland (surface and drinking water, aquatic organisms, shoreline sediment, air particulate filters, air iodine, and vegetation samples). A summary of the content of the REMP and the results of the data collected for indicator and control locations are provided in Tables 1 and 2.

3.2 Data Interpretation Many results in environmental monitoring occur at or below the minimum detectable activity (MDA). In this report, all results below the relevant MDA are reported as being "not detected. Typical MDA values are listed in Appendix B, Table B-10.

3.3 Quality Assurance Program Appendix C provides a summary of Exelon Industrial Services (EIS) - Ft. Smallwood Environmental Laboratorys quality assurance program for 2019. It consists of Table C-1, which represents a compilation of the results of the EIS - Ft. Smallwood Environmental Laboratorys participation in an inter-comparison program with Environmental Resource Associates (ERA) located in Arvada, Colorado and Analytics, Inc. located in Atlanta, Georgia and Eckert and Ziegler Analytics, Inc. (EZA) located in Atlanta, Georgia. Table C-2 compiles the results of the Exelon Industrial Services Ft. Smallwood Laboratorys participation in a split sample program with Teledyne Brown Engineering located in Knoxville, Tennessee. Table C-3 identifies a list of typical MDAs achieved by Teledyne Brown for Gamma Spectroscopy.

All the EIS - Ft. Smallwood Environmental Laboratory results contained in Table C-1 agree with the inter-comparison laboratory results within the range of +/-2 (standard deviation) between the analytical values or agree with the ranges established in the NRC Resolution Test Criteria.

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January 1 - December 31, 2019 Docket Nos. 50-244 All the results contained in Table C-2 agree within the range of +/-2 of each other with their respective Ft. Smallwood Environmental Laboratory original, replicate and/or Teledyne Brown Engineerings split laboratory samples.

3.4 Land Use Survey In September 2019, Ginna 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 (Ref. 4). If changes are noted in the annual Land Use Survey, alterations to Ginnas REMP program would be made to ensure sampling practices cover these new areas of potential public exposure. The position of the nearest residence and garden and animals producing milk for human consumption in each sector is provided in Appendix D, Table D-1.

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 has 25 acres of active production of AGRI-GROW tomatoes year-round at East end of Dean Parkway. (North of Route 104).

Commercial fishing information was collected from the New York State Department of Environmental Conservation (NYSDEC) which shows activity only in the Eastern basin of Lake Ontario. Commercial fishing operations have not changed in the last five-years and no commercial fishing takes place within 5-miles of Ginna.

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.

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January 1 - December 31, 2019 Docket Nos. 50-244 3.5 Program Exceptions The reportable items in the Annual Environmental Radiological Operating Report under procedure CHA-RETS-VARIATION are as follows:

On 4/18/19, during a review of REMP data at the vendor laboratory EIS, a radioiodine cartridge was counted prior to clearing the source check on the counting apparatus leading to a false-positive result. After acknowledging the error, the sample was recounted and both counts showed no I-131 activity. The peaks identified on the initial count were artifacts from the source check. Although no exception to the REMP program resulted from this laboratory practice, the issue has been included in this report.

On 7/9/19, when collecting the Webster Water Authority weekly supplemental sample, it was noted that only 4L of sample were collected in the compositor and the source of water was off. Flow was inadvertently terminated by Webster Water Authority workers.

According to the sample volume collected (4L), this represents a sample period of four days (7/2/19 - 7/6/19). The Webster Water Authority sample is a supplementary sample to the Ginna REMP program, and no compensatory sampling was performed during that week. Sample was restored to normal collection the following week and no further conditions adverse to quality existed.

On 8/13/19, when performing the weekly exchange of air filters at Environmental Sample Station (ES11, Williamson; RG&E Substation 207), it was noted the air sampler was off.

The ground fault circuit interrupter (GFCI) was unsuccessfully reset and the sampling unit was not running. For the sample period of 8/6/2019 - 8/13/2019, the sampler collected a total of 38.2 m3 (1,500 ft3) during 24.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months of runtime. This volume does not meet the Lower Limit of Detection (LLD) requirements. Sample collection returned to normal collection the following week and no further conditions adverse to quality existed.

On 11/4/19, when collecting the Webster Water Authority weekly supplemental sample, it was noted that only 1L of sample was collected in the compositor and the source of the water was off. This collection volume is less than the required minimum of 4L of sample volume. There were no issues with the collection equipment and the source of the low sample volume was determined to be the source water for the sampler being inadvertently terminated by Webster Water Authority workers. The Webster Water Authority sample is a supplementary sample to the Ginna REMP program, and no compensatory sampling was performed during that week. Sample was restored to normal collection the following week and no further conditions adverse to quality existed.

3.6 Corrections to Previous Reports There are no corrections necessary to any previously submitted Annual Radiological Environmental Operating Report (AREOR).

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January 1 - December 31, 2019 Docket Nos. 50-244

4. RESULTS AND DISCUSSIONS All environmental samples collected during the year were analyzed in accordance with Exelon analytical procedures (Ref. 5). The analytical results for this reporting period are presented in Appendix B and the detectable activity results are also summarized in Table 2. For discussion purposes, the analytical results are divided into five categories: Aquatic Environment, the Atmospheric Environment, the Terrestrial Environment, Direct Radiation, and Groundwater.

4.1 Aquatic Environment The aquatic environment surrounding the plant was monitored by analyzing samples of surface and drinking water, Lake Ontario fish, and shoreline sediment. These samples were obtained from various sampling locations near the plant.

4.1.a Surface and Drinking Water Monthly composite samples are collected from Lake Ontario at an upstream control location (Monroe County Water Authority - Shoremont) and a downstream indicator location (Ontario Water District Plant - OWD) and analyzed for gross beta activity (Table B-1). A supplemental sample is also collected at the upstream location of the Webster Water Authority. A grab sample of Deer Creek is collected and analyzed monthly for gross beta activity (Table B-1). Lake Ontario is a primary indicator for sampling due to the close proximity to the station as well as the Lake providing recreational activities which could be a means of public exposure. Additionally, liquid releases from the station enter Lake Ontario waters, which leads to sampling of this environment, in all its forms, to be a priority.

In 2019, the gross beta averages for the upstream Lake Ontario monitoring locations (controls) and downstream Lake Ontario monitoring locations (indicators) were 2.09 pCi/Liter and 2.10 pCi/Liter, respectively. Gross beta analysis of the monthly composite samples showed no statistically significant difference in activity between the control and indicator locations that would indicate plant related activity higher than background.

The average gross beta concentration seen in the Mill Creek samples (control) and the Deer Creek (indicator) samples were 3.81 pCi/Liter and 3.73 pCi/Liter, respectively. Results from Deer Creek (indicator) and Mill Creek (control) are higher than other surface water samples within the REMP program due to naturally occurring radiological daughter products from radon within the soil being introduced into the samples. These naturally occurring radiological daughter products would exist in this environ at these same levels even if Ginna had never been built. Gross beta analysis of the samples showed no statistically significant difference in activity between the control and indicator locations that would indicate plant related activity higher than background.

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January 1 - December 31, 2019 Docket Nos. 50-244 Gamma isotopic analysis is performed on each monthly composite sample. These are listed in Table B-1 and are separated by source of sample. During 2019, no sample results indicated detection of gamma activity above MDA.

Tritium analysis was performed on all water samples on a monthly basis. Composites are made from the monthly samples and a portion filtered to remove interferences for analysis by beta scintillation. During 2019, no surface water or drinking water sample results indicated detectable tritium activity.

4.1.b Aquatic Organisms Indicator fish are caught in the vicinity of the Discharge Canal and analyzed for radioactivity from liquid effluent releases from the plant. The fish are filleted to represent that portion which would normally be eaten and represents the likely pathway for human exposure. Additional fish are caught more than 15 miles away to be used as control samples and are prepared in the same manner.

At a minimum, four different edible species of fish are analyzed during each half-year from the indicator and background locations. Fish are caught by R.E. Ginna Nuclear Power Plant Chemistry personnel and are analyzed by gamma spectroscopy after being held for periods typically less than two weeks to keep the LLD value for the shorter half-life isotopes realistic.

Detection limits could also be affected by small mass samples, (< 2000 grams), in some species.

gamma isotopic concentrations (pCi/kilogram wet) are listed in Table B-2.

During 2019, none of the indicator samples indicated activity other than naturally occurring radionuclides.

4.1.c Shoreline Sediment Samples of shoreline sediment are taken upstream (Town of Greece near Slater Creek) and downstream (Near the Ontario Water District) of R.E. Ginna Nuclear Power Plant. The control sample is typical of the lake bottom, rich in mollusk shells and rocky particulate. These samples are analyzed for radionuclides that a member of the public would be expected to encounter during swimming and wading activities. Similarly, indicator samples are collected at the Bear Creek boat dock as this is another recreational area accessible to the public.

Results of the gamma isotopic analysis for sediment are included in Table B-3. During 2019, all sediment samples indicated that gamma emitters were below detection limits.

4.2 Atmospheric Environment Radioactive particles in air are collected by drawing approximately one standard cubic foot per minute (SCFM) through a two-inch diameter particulate filter. The volume of air sampled is measured by a dry gas meter and corrected for the pressure drop across the filter. The filters are changed weekly and allowed to decay for three days prior to counting to eliminate 7

January 1 - December 31, 2019 Docket Nos. 50-244 most of the natural radioactivity such as the short half-life decay products of radon. The decay period is used to give a more sensitive measurement of long-lived man-made radioactivity.

A ring of six sampling stations is located on the plant site from 180 to 440 meters from the reactor centerline near the point of the maximum annual average ground level concentration, one additional sampling location is located on-site at 770 meters, and two others offsite at approximately seven miles. In addition, there are three sampling stations located approximately seven to 16 miles from the site that serve as control stations. The arrangement of air sampling stations in concentric rings around the station would ensure the environment would be appropriately monitored if a radiological release were to occur. See Figure A-2 and Figure A-4.

4.2.a Air Iodine Radioiodine cartridges are placed at six locations. These cartridges are changed and analyzed each week. No positive analytical results were found on any sample. A list of values for these cartridges is given in Table B-4.

4.2.b Air Particulate Filters The major airborne species released as gaseous effluents are noble gases and tritium. Most of this activity is released in a gaseous form; however, some radioiodine is released as airborne particulate and some of the particulate activity is due to short lived noble gas decay products.

Tables B-5 provides a list of gross beta analysis values for the on-site sample stations. Table B-6 is a list of gross beta analysis values for the off-site sample stations.

Based on the weekly comparisons, there was no statistical difference between the control and indicator radioactive particulate concentrations. The average for the control samples (i.e., offsite sampling locations) was 0.021 pCi/m3 and the averages for the indicator samples (i.e., onsite sampling locations) was 0.021 pCi/m3 for the period of January to December 2019. Maximum weekly concentrations for all control stations and all indicator stations were 0.038 pCi/m3 and 0.039 pCi/m3, respectively.

The particulate filters from each sampling location were saved and a 13-week composite was made. A gamma isotopic analysis was performed for each sampling location and corrected for decay. No positive analytical results were found on any sample. The results of these analyses are listed in Tables B-7.

4.3 Terrestrial Environment Crops are grown on the plant property in a location with a highest off-site meteorological deposition parameter, and samples of the produce are collected at harvest time for analysis.

Control samples are purchased from farms greater than 10 miles from the plant.

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January 1 - December 31, 2019 Docket Nos. 50-244 4.3.a Vegetation There was no indication in the vegetation samples of activity greater than naturally occurring background levels. Both onsite (indicator) and offsite (control) vegetation samples are rinsed prior to sampling as this is the expected behavior to be exhibited by a member of the public prior to consuming any produce. Analyses revealed that there was no difference in the radiological activity observed in the indicator and control sampling locations. Gamma isotopic data is provided in Table B-8.

4.3.b Milk Although there are no indicator dairy herds located within five miles from the plant, Ginna has elected to continue sampling the milk pathway as a supplemental sample to satisfy this potential exposure pathway to a member of the public. This pathway is specific to gaseous radiological releases from Ginna station that could deposit onto the grazing pastures of dairy farms. When these grazing cows are milked, any potential radiological exposure received by the cow could enter the human pathway.

In 2019, milk samples were collected monthly during November through May from the indicator farm and biweekly during June through October. Samples are collected twice as frequently in the summer as the likelihood of cows grazing and not consuming stored feed is higher during this time. A control farm sample is taken for each monthly sample and once during each biweekly period. The milk is analyzed for Iodine-131 and also analyzed by gamma spectroscopy.

During 2019, no samples indicated I-131 activity above detection levels. There was no difference in the radiological activity observed in the indicator and control sampling locations. Table B-9 provides a listing of all samples collected and analytical results.

4.4 Direct Radiation Thermoluminescent Dosimeter (TLDs / Dosimeters) are placed as part of the environmental monitoring program. 41 dosimeter badges are currently placed in four rings around the plant.

These rings range from less than 1,000 feet to 15 miles and have been dispersed to give indications in each of the nine land-based sectors around the plant should an excessive release occur from the plant. Badges are changed and read after approximately three months exposure.

Each direct radiation sampling location is described in Table A-1 and identified in Figure A-2.

In 2019, Ginna adopted Exelon procedure CY-AA-170-1001, Environmental Dosimetry Performance Specifications, Testing, and Data Analysis, which included new methodology for determining dose attributable to facility operations. As part of this methodology, the direct radiation dose to the general public is now determined in accordance with the Environmental Protection Agency (EPA) guidance 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operations. This methodology incorporates the concepts established in ANSI/HPS N13.37, Environmental Dosimetry as established in NRC Regulatory Guide 4.13, Environmental Dosimetry - Performance, Specifications, Testing, and Data Analysis.

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January 1 - December 31, 2019 Docket Nos. 50-244 In accordance with the measures set forth in this new methodology for reporting ambient gamma radiation, Ginna evaluated the last 5 years of TLD data to establish a background dose and baseline dose for each TLD location in the REMP. Detectable Facility Dose is now classified as any normalized net dose above the baseline (i.e. background) and is reported both quarterly and annually for each location. Therefore, the mean dose for both Indicator and Control locations will no longer be reported.

This new methodology of reporting Quarterly and Annual Normalized Net Dose for each location is reported in Table B-12, Direct Radiation. No locations showed a net positive normalized dose in 2019, meaning that Ginna had no statistically significant dose contributions for operations in 2019.

4.5 Groundwater Groundwater monitoring wells have been established in close proximity to the station and are routinely sampled by Ginna personnel. In 2019, Ginna staff collected and analyzed samples collected from a total of 14 groundwater monitoring wells:

GW01: Warehouse Access Road (Control)

GW03: Screenhouse West, South Well

GW04: Screenhouse West, North Well

GW05: Screenhouse East, South (15.5)

GW06: Screenhouse East, Middle (20.0)

GW07: Screenhouse East, North (24.0)

GW08: All Volatiles Treatment Building

GW10: Technical Support Center, South

GW11: Contaminated Storage Building, SE (24.0)

GW12: West of Orchard Access Road

GW13: North of Independent Spent Fuel Storage Installation (ISFSI)

GW14: South of Canister Preparation Building

GW15: West of Manor House

GW16: Southeast of Manor House Tritium is sampled for at nuclear facilities due to the migration capabilities of tritium.

Essentially, tritium, when in an aqueous form, flows like water and can be found in surface water, groundwater, and atmospheric environs due to evaporative processes found in nature.

Nuclear stations place a sensitivity on detecting tritium in the environment as it is an efficient marker to show if radioactivity has been introduced off-site. 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 2019 are presented in table B-13.

In 2019, supplemental low-level tritium analysis was performed on select groundwater samples.

This low-level study (which analyzed samples to a detection limit of 200 pCi/L), some positive detections were made ranging from 446 - 603 pCi/L. These positive results are within agreement with our gaseous tritium recapture experiences detailed in E-Series 4 at the end of this report.

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January 1 - December 31, 2019 Docket Nos. 50-244 4.6 Summary and Conclusion Operation of the R.E. Ginna Nuclear Power Plant produced radioactivity and ambient radiation levels significantly below the limits of the ODCM and 40 CFR 190. The analytical results from the Radiological Environmental Monitoring Program indicate the operation of the R.E. Ginna Nuclear Power Plant had no measurable radiological impact on the environment or measurable build-up of plant-related radionuclides in the environment. The results also indicate operation of the plant did not result in a measurable radiation dose to the general population above natural background levels.

Additionally, the 2019 results are consistent with data for the past seven years and exhibited no detectable increases or adverse trends. Further explanation on REMP data can be found in Appendix E.

5. REFERENCES

1. Procedure CY-GI-170-300, Offsite Dose Calculation Manual (ODCM) R.E. Ginna Nuclear Power Plant, Revision 36 (Effective Date: 12/27/2018)

2. R.E. Ginna Nuclear Power Plant, Technical Specification 5.6.2; Annual Radiological Environmental Operating Report.

3. Procedure CY-AA-170-100, Radiological Environmental Monitoring Program.

4. Procedure CH-ENV-LAND-USE, Land Use Census; Completed September 2019.

5. Exelon Industrial Services - Ft. Smallwood Environmental Laboratory Procedures Manual, General Services Department.

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January 1 - December 31, 2019 Docket Nos. 50-244 Table 1 Synopsis of R.E. Ginna Nuclear Power Plant Radiological Environmental Monitoring Program Sample Type Sampling Number of Number Collected Analysis Analysis Number Analyzed Frequency1 Locations Frequency1 Aquatic Environment Surface & Drinking M/C 7 89 Gamma MC/M 89 Water 89 Gross Beta MC/M 89 89 Tritium M/Q 89 Fish2 A 4 18 Gamma A 18 Shoreline Sediment SA 2 5 Gamma SA 5 Groundwater M/Q 14 74 Tritium M/Q 74 74 Gamma M/Q 74 Atmospheric Environment Air Iodine3 W 6 311 I-131 W 311 Air Particulates4 W 12 623 Gross Beta W 623 48 Gamma QC 48 Direct Radiation Ambient Radiation Q 41 164 TLD Q 164 Terrestrial Environment Milk5 M/BW 2 38 Gamma M/BW 38 Vegetation6 M 4 28 Gamma M 28 1 W=Weekly, BW=BiWeekly (15 days), M=Monthly (31 days), Q=Quarterly (92 days), SA=Semiannual, A=Annual, C=Composite 2 Twice during fishing season including at least four species.

3 The collection device contains activated charcoal.

4 Beta counting is performed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change. Gamma spectroscopy performed on quarterly composite of weekly samples.

5 Bi-Weekly during growing season.

6 Annual at time of harvest. Samples include broad leaf vegetation.

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January 1 - December 31, 2019 Docket Nos. 50-244 Table 2 Annual Summary of Radioactivity in the Environs of the R.E. Ginna Nuclear Power Plant Medium or Pathway Type and Total Lower Limit of Indicator Locations Location with Highest Annual Control Locations Sampled (Unit of Number of Analyses Detection (LLD) Mean (F)/Range1 Highest Annual Mean (F) / Range1 Mean (F)/Range Measurement) Performed Mean Name/Distance &

Direction2 Aquatic Environment Surface & Drinking Gamma (84) 2.3 (Cs-137) -- (48/48) -- -- (12/12) -- (24/24)

Water Tritium (84) 2000 -- (48/48) -- -- (12/12) -- (24/24)

(pCi/L)

Surface & Drinking Gross Beta (89) 0.5 2.48 (51/51) Mill Creek - 3.81 (12/12) 2.92 (25/25)

Water, (1.38 - 6.71) SW (1.93 - 7.10) (1.42 - 7.10)

(pCi/L)

Sediment Gamma (5) 17 (Cs-137) -- (3/3) -- -- (3/3) -- (2/2)

(pCi/kg) --(3/3) --(3/3) --(2/2)

Fish Gamma (18) 15 (Cs-137) -- (8/8) -- -- (8/8) -- (10/10)

(pCi/kg) --(8/8) -- (8/8) -- (10/10)

Groundwater3 Tritium (74) 500 538 (5/70) GW10 602 (1/4) -- (4/4)

(pCi/L) Gamma (56) 2.3 (Cs-137) -- (56/56) (0.067 km E) (602) -- (4/4)

Direct Radiation Ambient Radiation Dosimeters (164) -- 12.2 (128/128) Env. Station 13 19.5 (4/4) 11.0 (36/36)

(mR/91 days) (9.3-21.0) 0.77 km SSW (17.6-21.0) (9.3-13.1) 13

January 1 - December 31, 2019 Docket Nos. 50-244 Table 2 Annual Summary of Radioactivity in the Environs of the R.E. Ginna Nuclear Power Plant Medium or Pathway Type and Total Lower Limit of Indicator Locations Location with Highest Annual Control Locations Sampled (Unit of Number of Analyses Detection (LLD) Mean (F)/Range1 Highest Annual Mean (F) / Range1 Mean (F)/Range Measurement) Performed Mean Name/Distance &

Direction2 Atmospheric Environment Air Iodine I-131 (311) 0.002 -- (259/259) -- -- (52/52) -- (52/52)

(10-2 pCi/m3) -- (259/259) -- (52/52) -- (52/52)

Air Particulates Gross Beta (623) 0.5 2.1 (467/467) Env. Station 3 - 2.2 (52/52) 2.1 (156/156)

(10-2 pCi/m3) (1.0 - 3.9) 0.44 km ESE (1.2 - 3.8) (1.1 - 3.8)

Air Particulates Gamma (48) 1.8 (Cs-137) -- (36/36) -- -- (4/4) -- (12/12)

(10-3 pCi/m3) -- (36/36) -- (4/4) -- (12/12)

Terrestrial Environment Milk Gamma (38) 0.01 (I-131) -- (19/19) -- -- (19/19) -- (19/19)

(pCi/L) -- (19/19) -- (19/19) -- (19/19)

Vegetation Gamma (28) 27 (Cs-137) -- (20/20) -- -- (8/8) --(8/8)

(pCi/L) -- (20/20) -- (8/8) --(8/8) 1 Mean and range based upon detectable measurements only. Fraction (F) of detectable measurements at specified location is indicated in parentheses 2 From the center point of the containment building.

3 Most of the groundwater sample results for calculations were less-than detectable numerical values.

-- No detectable activity at specified location.

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January 1 - December 31, 2019 Docket Nos. 50-244 APPENDIX A REMP Sample Locations Summary of Appendix A Content Appendix A contains information concerning the environmental samples which were collected during this operating period.

Sample locations and specific information about individual locations for Ginna are provided in Table A-1.

Figure A-1 shows the location of the R.E. Ginna Nuclear Power Plant in relation to New York State and Lake Ontario. Figures A-2, A-3, and A-4 show the locations of the power plant sampling sites in relation to the plant site at different degrees of detail.

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January 1 - December 31, 2019 Docket Nos. 50-244 TABLE OF CONTENTS - SAMPLING LOCATIONS Table Title Page A-1 Locations of Environmental Sampling Stations for the R.E Ginna Nuclear Power Plant ...17 Figure Title Page A-1 Map of New York State and Lake Ontario Showing Location of R.E. Ginna Nuclear Power Plant ...................................................................................................................................20 A-2 Onsite Sample Locations......................................................................................................21 A-3 Offsite Sample Locations (TLDs and milk farms within 5 miles) .......................................22 A-4 Water Sample, Milk Farms and TLD Locations ..................................................................23 16

January 1 - December 31, 2019 Docket Nos. 50-244 TABLE A-1 Locations of Environmental Sampling Stations for the R.E. Ginna Nuclear Plant Station Description Distance Direction Meters Miles Sector Air Samplers 2 Manor House Yard 360 0.22 E 3 North of Training Center Parking Lot 220 0.14 ESE 4 East of Training Center Parking Lot 320 0.20 SE 5 Creek Bridge 180 0.11 SSE 6 Onsite-SW side of plant parking lot 300 0.19 SW 7 Onsite-utility pole along West plant fence 240 0.15 WSW 8 Seabreeze 19840 12.33 WSW 9 Webster 11150 6.93 SW 10 Walworth 12730 7.91 S 11 Williamson 11540 7.17 ESE 12 Sodus Point 25170 15.64 E 13 Substation 13 770 0.48 SSW Direct Radiation 2 Onsite-Manor House Yard 360 0.22 E 3 Onsite-In field approximately 200 ft SE of station #2 440 0.27 ESE 4 Onsite- East of Training Center Parking Lot 320 0.19 SE 5 Onsite-Between creek and plant entry road 180 0.11 SSE 6 Onsite-SW side of plant parking lot 300 0.19 SW 7 Onsite-utility pole along West plant fence 240 0.15 WSW 8 Topper Drive-Irondequoit, Seabreeze Substation #51 19840 12.33 WSW Phillips Road-Webster, intersection with Highway #104, 9 11150 6.93 SW Substation #74 10 Atlantic Avenue-Walworth, Substation #230 12730 7.91 S 11 W. Main Street-Williamson, Substation #207 11540 7.17 ESE 12 Seaman Avenue-Sodus Point-Off Lake Road by 12 25170 15.64 E Sewer district, Substation #209 13 Onsite - South of Meteorological Tower 260 0.16 WNW 14 NW corner of field along lake shore 860 0.53 WNW Field access road, west of orchard, approximately 3000' 15 920 0.57 W West of plant SW Corner of orchard, approximately 3000' West of 16 1030 0.64 WSW plant, approximately 200' North of Lake Road Utility pole in orchard, approximately 75" North of Lake 17 510 0.32 SSW Road 18 Substation 13A fence, North Side 730 0.45 SSW 19 On NW corner of house 100' East of plant access road 460 0.29 S Approximately 150' West of Ontario Center Road and 20 650 0.40 SSE approximately 170' South of Lake Road 17

January 1 - December 31, 2019 Docket Nos. 50-244 Station Description Distance Direction Meters Miles Sector North side of Lake Road, approximately 200' East of 21 660 0.41 SE Ontario Center Road 22 North side of Lake Road, SE, property corner 920 0.57 SE East property line, midway between Lake Road and 23 780 0.49 ESE Lake shore 24 Lake shore near NE corner of property 730 0.45 E 25 Substation #73, Klem Road, adjacent to 897 Klem Road 14000 8.70 WSW 26 Service Center, Plank Road, West of 250 14600 9.07 SW Atlantic Avenue at Knollwood Drive utility pole, North 27 14120 8.77 SSW side of road Substation #193, Marion, behind Stanton Ag. Service, 28 17450 10.84 SE North Main Street Substation #208, Town Line Road (CR-118), 1000 '

29 14050 8.73 ESE North of Route 104 30 District Office, Sodus, on pole, West side of bldg. 20760 12.90 ESE Lake Road, pole 20' North of road, 500' East of Salt 31 7330 4.56 W Road Woodard Road at County Line Road, pole @ Northwest 32 6070 3.77 WSW corner.

County Line Road at RR tracks, pole approximately 100' 33 7950 4.94 SW East along tracks 34 Pole at Route 104, Lincoln Road, SW Corner. 6520 4.05 SSW Transmission Right of Way, North of Clevenger Road 35 7490 4.65 SSW on pole.

Substation #205, Route 104, East of Ontario Center 36 5480 3.41 S Road, North side of fence.

37 Railroad Avenue, pole at 2048 5770 3.59 SSE 38 Fisher Road at RR Tracks, pole East of road 6910 4.29 SE Seeley Road, Pole South side 100' West of intersection 39 6930 4.31 ESE with Stony Lonesome Road 40 Lake Road at Stoney Lonesome Road, pole at SE corner 6440 4.00 E 63 Westside of warehouse access road 740 0.46 SW 64 Westside of direct road, adjacent to orchard 1190 0.74 W Fish Lake Ontario Discharge Plume 2200 1.37 ENE Russell Station 25600 15.9 W 18

January 1 - December 31, 2019 Docket Nos. 50-244 Produce (Vegetation)

Indicator and background samples of various produce are collected from gardens grown on company property and purchased from farms >10 miles from the plant.

Station Description Distance Direction Meters Miles Sector Onsite Supplemental Garden (E) 610 0.38 E Onsite Supplemental Garden (ESE) 430 0.27 ESE Onsite Supplemental Garden (SSE) 660 0.41 SSE Water Shoremont/MCWA 27150 16.87 W Ontario Water District 2220 1.38 ENE Circ Water Intake 1070 0.66 N Circ Water Discharge 110 0.07 NNE Deer Creek Points Points ESE downstream downstream of Outfall of Outfall 006 006 Sediment Lake Ontario Discharge Plume 2200 1.37 ENE Russell Station 25600 15.91 W Benthic 1070 0.66 N Milk Field Craft Farm, Williamson (Indicator) 8240 5.12 ESE Schultz Farm, S. Sodus (Control) 19030 11.82 SE 19

January 1 - December 31, 2019 Docket Nos. 50-244 Figure A-1 Map of New York State and Lake Ontario Showing Location of R.E. Ginna Nuclear Power Plant 20

January 1 - December 31, 2019 Docket Nos. 50-244 Figure A-2 Onsite Sample Locations 21

January 1 - December 31, 2019 Docket Nos. 50-244 Figure A-3 Offsite Sample Locations (TLDs and Milk Farms within 5 Miles) 22

January 1 - December 31, 2019 Docket Nos. 50-244 Figure A-4 Water Sample, Milk Farms and TLD Locations 23

January 1 - December 31, 2019 Docket Nos. 50-244 APPENDIX B REMP Analytical Results Summary of Appendix B Content Appendix B is a presentation of the analytical results for the R.E. Ginna Nuclear Power Plant radiological environmental monitoring programs.

24

January 1 - December 31, 2019 Docket Nos. 50-244 TABLE OF CONTENTS - ANALYTICAL RESULTS Table Title Page B-1 Concentration of Tritium, Gamma Emitters and Gross Beta in Surface and Drinking Water

............................................................................................................................................26 B-2 Concentration of Gamma Emitters in the Flesh of Edible Fish ...........................................29 B-3 Concentration of Gamma Emitters in Sediment...................................................................30 B-4 Concentration of Iodine-131 in Filtered Air (Charcoal Cartridges).....................................31 B-5 Concentration of Beta Emitters in Air Particulates - Onsite Samples .................................34 B-6 Concentration of Beta Emitters in Air Particulates - Offsite Samples .................................38 B-7 Concentration of Gamma Emitters in Air Particulates.........................................................40 B-8 Concentration of Gamma Emitters in Vegetation Samples..................................................42 B-9 Concentration of Gamma Emitters (including I-131) in Milk .............................................43 B-10 Typical MDA Ranges for Gamma Spectrometry.................................................................44 B-11 Typical LLDs for Gamma Spectrometry .............................................................................45 B-12 Direct Radiation ...................................................................................................................46 B-13 Groundwater Monitoring Wells ...........................................................................................50 25

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-1 Concentration of Tritium, Gamma Emitters and Gross Beta in Surface and Drinking Water (Results in units of pCi/L +/- 2)

Sample Code Sample Date Cs-137 Tritium Gamma Emitters2 Gross Beta CIRC-IN Circulating Water Inlet - N 1/7/2019 < 2.3 < 961

2.14 +/- 0.67 2/4/2019 < 2.3 < 999

2.29 +/- 0.67 3/4/2019 < 2.3 < 984

3.60 +/- 0.74 4/1/2019 < 2.3 < 993

2.77 +/- 0.71 4/29/2019 2.21 +/- 0.67 5/28/2019 < 2.3 < 989

1.61 +/- 0.65 6/24/2019 < 2.3 < 952

2.08 +/- 0.65 7/22/2019 < 2.3 < 951

2.22 +/- 0.65 8/19/2019 < 2.3 < 959

2.45 +/- 0.65 9/16/2019 < 2.3 < 965

3.40 +/- 0.70 10/14/2019 < 2.3 < 959

1.88 +/- 0.61 11/11/2019 < 2.3 < 966

1.45 +/- 0.65 12/9/2019 < 2.3 < 971

1.78 +/- 0.64 CIRC-OUT Circulating Water Outlet - N 1/7/2019 < 2.3 < 965

1.38 +/- 0.62 2/4/2019 < 2.3 < 985

2.48 +/- 0.68 3/4/2019 < 2.3 < 981

1.95 +/- 0.63 4/1/2019 < 2.3 < 993

1.68 +/- 0.64 4/29/2019 2.01 +/- 0.66 5/28/2019 < 2.3 < 989

1.66 +/- 0.65 6/24/2019 < 2.3 < 946

1.98 +/- 0.65 7/22/2019 < 2.3 < 957

1.73 +/- 0.62 8/19/2019 < 2.3 < 962

2.01 +/- 0.61 9/16/2019 < 2.3 < 969

1.53 +/- 0.57 10/14/2019 < 2.3 < 956

2.27 +/- 0.54 11/11/2019 < 2.3 < 963

1.81 +/- 0.67 12/9/2019 < 2.3 < 971

2.13 +/- 0.66 DC Deer Creek - ESE 1/3/2019 < 2.3 < 979

3.74 +/- 0.80 2/19/2019 < 2.3 < 990

3.18 +/- 0.76 3/13/2019 < 2.3 < 993

2.51 +/- 0.68 4/22/2019 < 2.3 < 999

2.43 +/- 1.21 5/14/2019 < 2.3 < 1000

2.70 +/- 1.27 6/10/2019 < 2.3 < 961

4.19 +/- 1.33 7/10/2019 < 2.3 < 963

2.70 +/- 1.13 8/5/2019 < 2.3 < 963

6.71 +/- 1.683 9/3/2019 < 2.3 < 973

5.10 +/- 1.55 10/2/2019 < 2.3 < 970

2.99 +/- 1.41 11/4/2019 < 2.3 < 947

5.00 +/- 1.71 12/4/2019 < 2.3 < 978

3.48 +/- 1.55 26

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-1 Concentration of Tritium, Gamma Emitters and Gross Beta in Surface and Drinking Water (Results in units of pCi/L +/- 2)

Sample Code Sample Date Cs-137 Tritium Gamma Emitters2 Gross Beta MCWA Monroe County Water/Shoremont, Greece - W1 1/7/2019 < 2.3 < 967

2.25 +/- 0.68 2/4/2019 < 2.3 < 971

2.86 +/- 0.71 3/4/2019 < 2.3 < 968

2.36 +/- 0.66 4/1/2019 < 2.3 < 991

3.12 +/- 0.73 4/29/2019 < 2.3 < 995

2.10 +/- 0.67 5/28/2019 1.42 +/- 0.64 6/24/2019 < 2.3 < 949

2.25 +/- 0.67 7/22/2019 < 2.3 < 958

2.13 +/- 0.64 8/19/2019 < 2.3 < 955

1.56 +/- 0.58 9/16/2019 < 2.3 < 969

1.56 +/- 0.57 10/14/2019 < 2.3 < 969

2.17 +/- 0.64 11/11/2019 < 2.3 < 970

1.59 +/- 0.66 12/9/2019 < 2.3 < 970

1.84 +/- 0.64 ML Mill Creek - SW1 1/3/2019 < 2.3 < 978

3.78 +/- 0.80 2/19/2019 < 2.3 < 987

2.66 +/- 0.72 3/13/2019 < 2.3 < 998

2.64 +/- 0.70 4/22/2019 < 2.3 < 998

2.60 +/- 0.94 5/13/2019 < 2.3 < 998

1.93 +/- 1.21 6/10/2019 < 2.3 < 957

3.71 +/- 1.29 7/10/2019 < 2.3 < 962

2.34 +/- 1.39 8/5/2019 < 2.3 < 960

7.10 +/- 1.703 9/3/2019 < 2.3 < 971

4.04 +/- 1.44 10/2/2019 < 2.3 < 978

5.19 +/- 1.57 11/4/2019 < 2.3 < 931

5.76 +/- 1.76 12/2/2019 < 2.3 < 981

3.99 +/- 1.57 W

Webster (Supplemental) 1/7/2019 < 2.3 < 964

1.58 +/- 0.63 2/4/2019 < 2.3 < 965

1.29 +/- 0.60 3/4/2019 < 2.3 < 973

2.06 +/- 0.64 4/1/2019 < 2.3 < 989

1.92 +/- 0.65 4/29/2019 < 2.3 < 981

1.75 +/- 0.64 5/28/2019 1.72 +/- 0.66 6/24/2019 < 2.3 < 950

1.88 +/- 0.64 7/22/2019 < 2.3 < 958

2.02 +/- 0.64 8/19/2019 < 2.3 < 953

2.03 +/- 0.62 9/16/2019 < 2.3 < 971

2.78 +/- 0.66 10/14/2019 < 2.3 < 958

2.11 +/- 0.63 11/11/2019 < 2.3 < 966

1.32 +/- 0.54 12/9/2019 < 2.3 < 966

1.99 +/- 0.65 27

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-1 Concentration of Tritium, Gamma Emitters and Gross Beta in Surface and Drinking Water (Results in units of pCi/L +/- 2)

Sample Code Sample Date Cs-137 Tritium Gamma Emitters2 Gross Beta OWD Ontario Water District - NE 1/7/2019 < 2.3 < 964

2.03 +/- 0.67 2/4/2019 < 2.3 < 984

3.45 +/- 0.74 3/4/2019 < 2.3 < 979

2.44 +/- 0.67 4/1/2019 < 2.3 < 995

1.92 +/- 0.65 4/29/2019 < 2.3 < 986

1.55 +/- 0.63 5/28/2019 1.84 +/- 0.67 6/24/2019 < 2.3 < 953

2.16 +/- 0.66 7/22/2019 < 2.3 < 951

1.73 +/- 0.62 8/19/2019 < 2.3 < 954

2.12 +/- 0.62 9/16/2019 < 2.3 < 972

2.24 +/- 0.62 10/14/2019 < 2.3 < 957

2.00 +/- 0.63 11/11/2019 < 2.3 < 966

1.76 +/- 0.67 12/9/2019 < 2.3 < 966

2.20 +/- 0.67 1 Control Location 2 All Non-Natural Gamma Emitters < MDA.

3 The cause of the elevated Gross Beta analysis for Deer Creek and Mill Creek in August 2019 is due to seasonal stagnation of the creek allowing for accumulation of natural beta emitters in the low water level.

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January 1 - December 31, 2019 Docket Nos. 50-244 Table B-2 Concentration of Gamma Emitters in the Flesh of Edible Fish (Results in units of pCi/kg (wet) +/- 2)

Sample Code Sample Date Sample Type Gamma Emitters (Cs-137)

CONTROL1 6/21/2019 Rainbow Trout

Local Sites 6/21/2019 Chinook Salmon

GREECE1 6/14/2019 Freshwater Drum

Control 6/26/2019 Largemouth Bass

6/28/2019 Brown Trout

6/28/2019 Lake Trout

HAMLIN1 9/30/2019 Chinook Salmon

Control 9/30/2019 Bowfin

9/30/2019 Largemouth Bass

9/30/2019 Carp

NORTH 1/4/2019 Lake Trout

North Sector 1/16/2019 Brown Trout

1/17/2019 Rainbow Trout

6/14/2019 Smallmouth Bass

11/8/2019 Lake Trout

11/13/2019 White Sucker Fish

11/22/2019 Brown Trout

12/6/2019 Carp

1 Control Locations include Greece, NY and Irondequoit, NY.

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January 1 - December 31, 2019 Docket Nos. 50-244 Table B-3 Concentration of Gamma Emitters in Sediment (Results in units of pCi/kg (wet) +/- 2)

Sample Code Sample Date Gamma Emitters (Cs-137)

EAST - Shoreline 5/6/2019

East Sector 8/26/2019

10/7/2019

Greece1 - Shoreline 5/6/2019

Control 8/6/2019

1 Control Location 30

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-4 Concentration of Iodine-131 in Filtered Air (Charcoal Cartridges)

(Results in units of 10-2 pCi/m3 +/- 2)

Start Date Stop Date STATION-02 STATION-04 STATION-07 STATION- STATION-09 STATION-11 Manor House Training West Fence 081 Webster Williamson Yard Center Line Seabreeze Parking Lot 1/2/2019 1/8/2019 < 0.002 < 0.002 < 0.002 < 0.002 < 0.002 < 0.002 1/8/2019 1/15/2019 < 0.002 < 0.002 < 0.002 < 0.002 < 0.002 < 0.002 1/15/2019 1/22/2019 < 0.002 < 0.002 < 0.002 1/15/2019 1/23/2019 < 0.002 < 0.002 < 0.002 1/22/2019 1/28/2019 < 0.002 < 0.002 < 0.002 1/23/2019 1/29/2019 < 0.002 < 0.002 < 0.002 1/28/2019 2/4/2019 < 0.002 < 0.002 < 0.002 1/29/2019 2/5/2019 < 0.002 < 0.002 < 0.002 2/4/2019 2/11/2019 < 0.002 < 0.002 < 0.002 2/5/2019 2/13/2019 < 0.002 < 0.002 < 0.002 2/11/2019 2/19/2019 < 0.002 < 0.002 < 0.002 2/13/2019 2/20/2019 < 0.002 < 0.002 < 0.002 2/19/2019 2/25/2019 < 0.002 < 0.002 < 0.002 2/20/2019 2/26/2019 < 0.002 < 0.002 < 0.002 2/25/2019 3/4/2019 < 0.002 < 0.002 < 0.002 2/26/2019 3/5/2019 < 0.002 < 0.002 < 0.002 3/4/2019 3/11/2019 < 0.002 < 0.002 < 0.002 3/5/2019 3/12/2019 < 0.002 < 0.002 3/5/2019 3/13/2019 < 0.002 3/11/2019 3/18/2019 < 0.002 < 0.002 < 0.002 3/13/2019 3/19/2019 < 0.002 3/12/2019 3/19/2019 < 0.002 < 0.002 3/18/2019 3/25/2019 < 0.002 < 0.002 < 0.002 3/19/2019 3/27/2019 < 0.002 < 0.002 < 0.002 3/25/2019 4/1/2019 < 0.002 < 0.002 < 0.002 3/27/2019 4/2/2019 < 0.002 < 0.002 < 0.002 4/1/2019 4/9/2019 < 0.002 < 0.002 < 0.002 4/2/2019 4/9/2019 < 0.002 < 0.002 < 0.002 4/9/2019 4/15/2019 < 0.002 < 0.002 < 0.002 4/9/2019 4/16/2019 < 0.002 < 0.002 < 0.002 4/15/2019 4/22/2019 < 0.002 < 0.002 < 0.002 4/16/2019 4/23/2019 < 0.002 < 0.002 < 0.002 4/22/2019 4/29/2019 < 0.002 < 0.002 < 0.002 4/23/2019 4/30/2019 < 0.002 < 0.002 < 0.002 4/29/2019 5/6/2019 < 0.002 < 0.002 < 0.002 4/30/2019 5/7/2019 < 0.002 < 0.002 < 0.002 5/6/2019 5/13/2019 < 0.002 < 0.002 < 0.002 5/7/2019 5/14/2019 < 0.002 < 0.002 < 0.002 5/13/2019 5/20/2019 < 0.002 < 0.002 < 0.002 5/14/2019 5/21/2019 < 0.002 < 0.002 < 0.002 5/20/2019 5/28/2019 < 0.002 < 0.002 < 0.002 5/21/2019 5/29/2019 < 0.002 < 0.002 < 0.002 31

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-4 Concentration of Iodine-131 in Filtered Air (Charcoal Cartridges)

(Results in units of 10-2 pCi/m3 +/- 2)

Start Date Stop Date STATION-02 STATION-04 STATION-07 STATION- STATION-09 STATION-11 Manor House Training West Fence 081 Webster Williamson Yard Center Line Seabreeze Parking Lot 5/28/2019 6/3/2019 < 0.002 < 0.002 < 0.002 5/29/2019 6/4/2019 < 0.002 < 0.002 < 0.002 6/3/2019 6/10/2019 < 0.002 < 0.002 < 0.002 6/4/2019 6/11/2019 < 0.002 < 0.002 < 0.002 6/10/2019 6/18/2019 < 0.002 < 0.002 < 0.002 6/11/2019 6/18/2019 < 0.002 < 0.002 < 0.002 6/18/2019 6/24/2019 < 0.002 < 0.002 < 0.002 < 0.002 < 0.002 < 0.002 6/24/2019 7/2/2019 < 0.002 < 0.002 < 0.002 6/25/2019 7/3/2019 < 0.002 < 0.002 < 0.002 7/2/2019 7/9/2019 < 0.002 < 0.002 < 0.002 7/3/2019 7/10/2019 < 0.002 < 0.002 < 0.002 7/9/2019 7/16/2019 < 0.002 < 0.002 < 0.002 7/10/2019 7/16/2019 < 0.002 < 0.002 < 0.002 7/16/2019 7/22/2019 < 0.002 < 0.002 < 0.002 7/16/2019 7/24/2019 < 0.002 < 0.002 < 0.002 7/22/2019 7/29/2019 < 0.002 < 0.002 < 0.002 7/24/2019 7/30/2019 < 0.002 < 0.002 < 0.002 7/29/2019 8/5/2019 < 0.002 < 0.002 < 0.002 7/30/2019 8/6/2019 < 0.002 < 0.002 < 0.002 8/5/2019 8/13/2019 < 0.002 < 0.002 < 0.002 8/6/2019 8/13/2019 < 0.002 < 0.002 2 8/13/2019 8/19/2019 < 0.002 < 0.002 < 0.002 8/14/2019 8/21/2019 < 0.002 8/13/2019 8/21/2019 < 0.002 < 0.002 8/19/2019 8/26/2019 < 0.002 < 0.002 < 0.002 8/21/2019 8/27/2019 < 0.002 < 0.002 < 0.002 8/26/2019 9/3/2019 < 0.002 < 0.002 < 0.002 8/27/2019 9/4/2019 < 0.002 < 0.002 < 0.002 9/3/2019 9/11/2019 < 0.002 < 0.002 < 0.002 9/4/2019 9/12/2019 < 0.002 < 0.002 < 0.002 9/11/2019 9/16/2019 < 0.002 < 0.002 < 0.002 9/12/2019 9/17/2019 < 0.002 < 0.002 < 0.002 9/16/2019 9/23/2019 < 0.002 < 0.002 < 0.002 9/17/2019 9/24/2019 < 0.002 < 0.002 < 0.002 9/23/2019 10/1/2019 < 0.002 < 0.002 < 0.002 9/24/2019 10/1/2019 < 0.002 < 0.002 < 0.002 10/1/2019 10/7/2019 < 0.002 < 0.002 < 0.002 10/1/2019 10/8/2019 < 0.002 < 0.002 < 0.002 10/7/2019 10/14/2019 < 0.002 < 0.002 < 0.002 10/8/2019 10/15/2019 < 0.002 < 0.002 < 0.002 10/14/2019 10/22/2019 < 0.002 < 0.002 < 0.002 10/15/2019 10/22/2019 < 0.002 < 0.002 < 0.002 10/22/2019 10/28/2019 < 0.002 < 0.002 < 0.002 10/22/2019 10/29/2019 < 0.002 < 0.002 < 0.002 32

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-4 Concentration of Iodine-131 in Filtered Air (Charcoal Cartridges)

(Results in units of 10-2 pCi/m3 +/- 2)

Start Date Stop Date STATION-02 STATION-04 STATION-07 STATION- STATION-09 STATION-11 Manor House Training West Fence 081 Webster Williamson Yard Center Line Seabreeze Parking Lot 10/28/2019 11/4/2019 < 0.002 < 0.002 < 0.002 10/29/2019 11/5/2019 < 0.002 < 0.002 < 0.002 11/4/2019 11/11/2019 < 0.002 < 0.002 < 0.002 11/5/2019 11/12/2019 < 0.002 < 0.002 < 0.002 11/11/2019 11/18/2019 < 0.002 < 0.002 < 0.002 11/12/2019 11/19/2019 < 0.002 < 0.002 < 0.002 11/18/2019 11/25/2019 < 0.002 < 0.002 < 0.002 11/19/2019 11/26/2019 < 0.002 < 0.002 < 0.002 11/25/2019 12/2/2019 < 0.002 < 0.002 < 0.002 11/26/2019 12/3/2019 < 0.002 < 0.002 < 0.002 12/2/2019 12/9/2019 < 0.002 < 0.002 < 0.002 12/3/2019 12/10/2019 < 0.002 < 0.002 < 0.002 12/9/2019 12/18/2019 < 0.002 < 0.002 < 0.002 12/10/2019 12/18/2019 < 0.002 < 0.002 < 0.002 12/18/2019 12/26/2019 < 0.002 < 0.002 < 0.002 < 0.002 < 0.002 < 0.002 12/26/2019 1/2/2020 < 0.002 < 0.002 < 0.002 < 0.002 < 0.002 < 0.002 1Control Location 2Sampler Malfunction / Low Flow 33

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-5 Concentration of Beta Emitters in Air Particulates - Onsite Samples (Results in units of 10-2 pCi/m3 +/- 2 Uncertainty)

Start Date Stop Date STATION-02 STATION-03 STATION-04 STATION-05 STATION-06 STATION-07 STATION-13 Manor House East Field Training Center Creek Bridge Main Parking West Fence Substation 13 Yard Parking Lot Lot Line 1/2/2019 1/8/2019 3.0 +/- 0.2 3.1 +/- 0.2 3.0 +/- 0.1 2.9 +/- 0.2 3.1 +/- 0.2 3.0 +/- 0.2 2.7 +/- 0.1 1/8/2019 1/15/2019 1.7 +/- 0.1 2.1 +/- 0.1 1.7 +/- 0.1 1.7 +/- 0.1 1.8 +/- 0.2 1.9 +/- 0.1 1.6 +/- 0.1 1/15/2019 1/22/2019 1.7 +/- 0.1 2.1 +/- 0.1 1.8 +/- 0.1 1.8 +/- 0.1 1.9 +/- 0.2 1.8 +/- 0.1 1/15/2019 1/23/2019 1.7 +/- 0.1 1/22/2019 1/28/2019 2.2 +/- 0.1 2.5 +/- 0.1 2.3 +/- 0.1 2.4 +/- 0.1 2.5 +/- 0.2 2.5 +/- 0.2 1/23/2019 1/29/2019 2.2 +/- 0.1 1/28/2019 2/4/2019 2.7 +/- 0.1 3.1 +/- 0.1 2.6 +/- 0.1 2.8 +/- 0.1 2.9 +/- 0.2 3.2 +/- 0.2 1/29/2019 2/5/2019 2.9 +/- 0.1 2/4/2019 2/11/2019 1.8 +/- 0.1 2.1 +/- 0.1 1.8 +/- 0.1 1.9 +/- 0.1 1.9 +/- 0.2 1.9 +/- 0.1 2/5/2019 2/13/2019 1.5 +/- 0.1 2/11/2019 2/19/2019 2.3 +/- 0.1 2.5 +/- 0.1 2.4 +/- 0.1 2.3 +/- 0.1 2.5 +/- 0.2 2.4 +/- 0.1 2/13/2019 2/20/2019 2.5 +/- 0.1 2/19/2019 2/25/2019 2.6 +/- 0.1 2.8 +/- 0.2 2.5 +/- 0.1 2.7 +/- 0.2 2.6 +/- 0.2 2.7 +/- 0.2 2/20/2019 2/26/2019 2.6 +/- 0.1 2/25/2019 3/4/2019 2.6 +/- 0.1 2.8 +/- 0.1 2.6 +/- 0.1 2.4 +/- 0.1 2.6 +/- 0.2 2.9 +/- 0.1 2/26/2019 3/5/2019 2.5 +/- 0.1 3/4/2019 3/11/2019 2.6 +/- 0.1 2.5 +/- 0.1 2.4 +/- 0.1 2.5 +/- 0.1 2.6 +/- 0.2 2.5 +/- 0.1 3/5/2019 3/12/2019 2.6 +/- 0.1 3/11/2019 3/18/2019 3.6 +/- 0.2 3.8 +/- 0.2 3.5 +/- 0.1 3.7 +/- 0.2 3.8 +/- 0.2 3.8 +/- 0.2 3/12/2019 3/19/2019 3.1 +/- 0.1 3/18/2019 3/25/2019 2.1 +/- 0.1 2.3 +/- 0.1 2.1 +/- 0.1 2.2 +/- 0.1 2.2 +/- 0.2 2.4 +/- 0.1 3/19/2019 3/26/2019 1.9 +/- 0.1 34

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-5 Concentration of Beta Emitters in Air Particulates - Onsite Samples (Results in units of 10-2 pCi/m3 +/- 2 Uncertainty)

Start Date Stop Date STATION-02 STATION-03 STATION-04 STATION-05 STATION-06 STATION-07 STATION-13 Manor House East Field Training Center Creek Bridge Main Parking West Fence Substation 13 Yard Parking Lot Lot Line 3/25/2019 4/1/2019 1.8 +/- 0.1 1.8 +/- 0.1 1.7 +/- 0.1 1.6 +/- 0.1 1.8 +/- 0.2 1.8 +/- 0.1 3/26/2019 4/2/2019 1.7 +/- 0.1 4/1/2019 4/9/2019 1.9 +/- 0.1 2.1 +/- 0.1 1.9 +/- 0.1 1.9 +/- 0.1 1.9 +/- 0.2 2.0 +/- 0.1 4/2/2019 4/9/2019 1.9 +/- 0.1 4/9/2019 4/15/2019 1.3 +/- 0.1 1.2 +/- 0.1 1.3 +/- 0.1 1.2 +/- 0.1 1.3 +/- 0.2 1.3 +/- 0.1 4/9/2019 4/16/2019 1.2 +/- 0.1 4/15/2019 4/22/2019 1.2 +/- 0.1 2.0 +/- 0.2 1.4 +/- 0.1 1.4 +/- 0.1 1.5 +/- 0.2 1.3 +/- 0.1 4/16/2019 4/23/2019 1.2 +/- 0.1 4/22/2019 4/29/2019 1.3 +/- 0.1 1.2 +/- 0.1 1.2 +/- 0.1 1.3 +/- 0.1 1.4 +/- 0.2 1.5 +/- 0.1 4/23/2019 4/30/2019 1.3 +/- 0.1 4/29/2019 5/6/2019 1.5 +/- 0.1 1.6 +/- 0.1 1.6 +/- 0.1 1.6 +/- 0.1 1.5 +/- 0.2 1.6 +/- 0.1 4/30/2019 5/7/2019 1.5 +/- 0.1 5/6/2019 5/13/2019 1.4 +/- 0.1 1.5 +/- 0.1 1.4 +/- 0.1 1.5 +/- 0.1 1.8 +/- 0.2 1.5 +/- 0.1 5/7/2019 5/14/2019 1.0 +/- 0.1 5/13/2019 5/20/2019 1.6 +/- 0.1 1.7 +/- 0.1 1.4 +/- 0.1 1.7 +/- 0.1 1.7 +/- 0.2 1.7 +/- 0.1 5/14/2019 5/21/2019 1.5 +/- 0.1 5/20/2019 5/28/2019 1.3 +/- 0.1 1.4 +/- 0.1 1.4 +/- 0.1 1.4 +/- 0.1 1.4 +/- 0.1 1.4 +/- 0.1 5/21/2019 5/29/2019 1.6 +/- 0.1 5/28/2019 6/3/2019 1.4 +/- 0.1 1.5 +/- 0.1 1.5 +/- 0.1 1.7 +/- 0.1 1.6 +/- 0.2 1.5 +/- 0.1 5/29/2019 6/4/2019 1.6 +/- 0.1 6/3/2019 6/10/2019 1.7 +/- 0.1 1.7 +/- 0.1 1.7 +/- 0.1 1.8 +/- 0.1 1.6 +/- 0.2 1.7 +/- 0.1 6/4/2019 6/11/2019 1.8 +/- 0.1 6/10/2019 6/18/2019 1.3 +/- 0.1 1.4 +/- 0.1 1.4 +/- 0.1 1.3 +/- 0.1 1.4 +/- 0.1 1.4 +/- 0.1 6/11/2019 6/18/2019 1.7 +/- 0.1 6/18/2019 6/24/2019 1.6 +/- 0.1 1.5 +/- 0.1 1.4 +/- 0.1 1.7 +/- 0.1 1.2 +/- 0.1 1.4 +/- 0.1 6/18/2019 6/25/2019 1.8 +/- 0.1 35

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-5 Concentration of Beta Emitters in Air Particulates - Onsite Samples (Results in units of 10-2 pCi/m3 +/- 2 Uncertainty)

Start Date Stop Date STATION-02 STATION-03 STATION-04 STATION-05 STATION-06 STATION-07 STATION-13 Manor House East Field Training Center Creek Bridge Main Parking West Fence Substation 13 Yard Parking Lot Lot Line 6/24/2019 7/2/2019 1.9 +/- 0.1 2.2 +/- 0.1 2.0 +/- 0.1 2.0 +/- 0.1 1.6 +/- 0.1 2.1 +/- 0.1 6/25/2019 7/3/2019 2.1 +/- 0.1 7/2/2019 7/9/2019 2.1 +/- 0.1 2.3 +/- 0.1 2.0 +/- 0.1 2.2 +/- 0.2 1.7 +/- 0.1 2.3 +/- 0.2 7/3/2019 7/10/2019 2.1 +/- 0.1 7/9/2019 7/16/2019 1.5 +/- 0.1 1.6 +/- 0.1 1.5 +/- 0.1 1.6 +/- 0.1 1.3 +/- 0.1 1.8 +/- 0.2 7/10/2019 7/16/2019 1.7 +/- 0.2 7/16/2019 7/22/2019 1.9 +/- 0.1 1.9 +/- 0.2 1.8 +/- 0.1 1.8 +/- 0.2 1.4 +/- 0.1 1.9 +/- 0.2 7/16/2019 7/23/2019 2.1 +/- 0.1 7/22/2019 7/29/2019 2.6 +/- 0.2 2.5 +/- 0.2 2.5 +/- 0.1 2.6 +/- 0.2 2.1 +/- 0.1 2.9 +/- 0.2 7/23/2019 7/30/2019 2.9 +/- 0.2 7/29/2019 8/5/2019 1.9 +/- 0.1 2.2 +/- 0.2 2.0 +/- 0.1 2.1 +/- 0.2 1.6 +/- 0.1 2.2 +/- 0.2 7/30/2019 8/6/2019 2.0 +/- 0.1 8/5/2019 8/13/2019 2.3 +/- 0.1 2.1 +/- 0.2 2.2 +/- 0.1 2.3 +/- 0.1 1.8 +/- 0.1 2.4 +/- 0.2 8/6/2019 8/13/2019 2.3 +/- 0.2 8/13/2019 8/19/2019 2.7 +/- 0.2 2.7 +/- 0.2 2.4 +/- 0.1 2.6 +/- 0.2 2.0 +/- 0.1 2.7 +/- 0.2 8/13/2019 8/20/2019 2.6 +/- 0.2 8/19/2019 8/26/2019 1.7 +/- 0.1 1.6 +/- 0.2 1.6 +/- 0.1 1.8 +/- 0.1 1.4 +/- 0.1 1.9 +/- 0.2 8/20/2019 8/27/2019 1.7 +/- 0.1 8/26/2019 9/3/2019 1.8 +/- 0.1 1.9 +/- 0.2 1.9 +/- 0.1 1.8 +/- 0.1 1.5 +/- 0.1 2.0 +/- 0.1 8/27/2019 9/4/2019 2.3 +/- 0.1 9/3/2019 9/11/2019 2.0 +/- 0.1 2.1 +/- 0.2 2.0 +/- 0.1 2.2 +/- 0.1 1.8 +/- 0.1 2.2 +/- 0.2 9/4/2019 9/12/2019 2.0 +/- 0.1 9/11/2019 9/16/2019 1.9 +/- 0.2 2.1 +/- 0.3 1.8 +/- 0.2 2.0 +/- 0.2 1.6 +/- 0.1 2.0 +/- 0.2 9/12/2019 9/17/2019 1.9 +/- 0.2 9/16/2019 9/23/2019 3.6 +/- 0.2 3.6 +/- 0.2 3.5 +/- 0.2 3.5 +/- 0.2 3.0 +/- 0.1 3.8 +/- 0.2 9/17/2019 9/24/2019 3.8 +/- 0.2 36

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-5 Concentration of Beta Emitters in Air Particulates - Onsite Samples (Results in units of 10-2 pCi/m3 +/- 2 Uncertainty)

Start Date Stop Date STATION-02 STATION-03 STATION-04 STATION-05 STATION-06 STATION-07 STATION-13 Manor House East Field Training Center Creek Bridge Main Parking West Fence Substation 13 Yard Parking Lot Lot Line 9/24/2019 10/1/2019 2.8 +/- 0.2 9/23/2019 10/1/2019 2.6 +/- 0.1 2.6 +/- 0.2 2.5 +/- 0.1 2.7 +/- 0.2 2.2 +/- 0.1 2.7 +/- 0.2 10/1/2019 10/7/2019 1.8 +/- 0.1 1.6 +/- 0.2 1.7 +/- 0.1 1.8 +/- 0.2 1.5 +/- 0.1 1.9 +/- 0.2 10/1/2019 10/8/2019 1.9 +/- 0.1 10/7/2019 10/14/2019 2.7 +/- 0.2 2.9 +/- 0.2 2.5 +/- 0.1 2.6 +/- 0.2 2.3 +/- 0.1 2.9 +/- 0.2 10/8/2019 10/15/2019 2.6 +/- 0.2 10/14/2019 10/22/2019 1.9 +/- 0.1 2.0 +/- 0.2 1.8 +/- 0.1 2.1 +/- 0.1 1.7 +/- 0.1 2.1 +/- 0.1 10/15/2019 10/22/2019 2.1 +/- 0.1 10/22/2019 10/28/2019 1.5 +/- 0.1 1.8 +/- 0.2 1.6 +/- 0.1 1.6 +/- 0.1 1.4 +/- 0.1 1.7 +/- 0.2 10/22/2019 10/29/2019 1.7 +/- 0.1 10/28/2019 11/4/2019 2.0 +/- 0.1 2.0 +/- 0.2 1.8 +/- 0.1 2.0 +/- 0.2 1.7 +/- 0.1 2.1 +/- 0.2 10/29/2019 11/5/2019 2.3 +/- 0.2 11/4/2019 11/11/2019 2.1 +/- 0.1 2.1 +/- 0.2 1.9 +/- 0.1 2.0 +/- 0.1 1.6 +/- 0.1 2.2 +/- 0.2 11/5/2019 11/12/2019 2.0 +/- 0.1 11/11/2019 11/18/2019 1.6 +/- 0.1 1.8 +/- 0.2 1.5 +/- 0.1 1.7 +/- 0.1 1.4 +/- 0.1 1.7 +/- 0.1 11/12/2019 11/19/2019 1.8 +/- 0.1 11/18/2019 11/25/2019 2.4 +/- 0.1 2.4 +/- 0.2 2.0 +/- 0.1 2.1 +/- 0.2 2.0 +/- 0.1 2.3 +/- 0.2 11/19/2019 11/26/2019 2.8 +/- 0.2 11/25/2019 12/2/2019 2.0 +/- 0.1 2.1 +/- 0.2 2.0 +/- 0.1 2.1 +/- 0.1 1.8 +/- 0.1 2.1 +/- 0.1 11/26/2019 12/3/2019 2.0 +/- 0.1 12/2/2019 12/9/2019 2.1 +/- 0.1 2.1 +/- 0.2 1.8 +/- 0.1 2.0 +/- 0.1 1.8 +/- 0.1 2.2 +/- 0.2 12/3/2019 12/10/2019 2.3 +/- 0.1 12/9/2019 12/18/2019 1.8 +/- 0.1 1.9 +/- 0.2 1.5 +/- 0.1 1.9 +/- 0.1 1.7 +/- 0.1 1.8 +/- 0.1 12/10/2019 12/18/2019 1.9 +/- 0.1 12/18/2019 12/26/2019 3.7 +/- 0.2 3.8 +/- 0.2 3.3 +/- 0.1 3.6 +/- 0.2 3.1 +/- 0.1 3.7 +/- 0.2 3.9 +/- 0.2 12/26/2019 1/2/2020 3.3 +/- 0.2 3.6 +/- 0.2 3.2 +/- 0.2 3.4 +/- 0.2 3.1 +/- 0.1 3.3 +/- 0.2 3.8 +/- 0.2 37

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-6 Concentration of Beta Emitters in Air Particulates - Offsite Samples (Results in units of 10-2 pCi/m3 +/- 2 Uncertainty)

Start Date Stop Date STATION- STATION- STATION- STATION- STATION-081 09 101 11 121 Seabreeze Webster Walworth Williamson Sodus Point 1/2/2019 1/8/2019 3.2 +/- 0.2 2.8 +/- 0.2 2.9 +/- 0.2 2.8 +/- 0.2 2.8 +/- 0.1 1/8/2019 1/15/2019 2.0 +/- 0.1 1.7 +/- 0.1 1.9 +/- 0.1 1.8 +/- 0.1 1.8 +/- 0.1 1/15/2019 1/22/2019 1/15/2019 1/23/2019 1.9 +/- 0.1 1.9 +/- 0.1 1.9 +/- 0.1 1.8 +/- 0.1 1.9 +/- 0.1 1/22/2019 1/29/2019 2.6 +/- 0.1 1/23/2019 1/29/2019 2.8 +/- 0.2 2.4 +/- 0.1 2.8 +/- 0.2 2.7 +/- 0.2 1/29/2019 2/5/2019 3.1 +/- 0.2 2.6 +/- 0.1 3.0 +/- 0.2 2.9 +/- 0.2 3.1 +/- 0.1 2/5/2019 2/13/2019 1.7 +/- 0.1 1.5 +/- 0.1 1.6 +/- 0.1 1.4 +/- 0.1 1.5 +/- 0.1 2/13/2019 2/20/2019 2.9 +/- 0.2 2.6 +/- 0.1 2.5 +/- 0.1 2.4 +/- 0.1 2.6 +/- 0.1 2/20/2019 2/26/2019 2.9 +/- 0.2 2.8 +/- 0.2 3.0 +/- 0.2 2.7 +/- 0.2 2.8 +/- 0.1 2/26/2019 3/5/2019 2.7 +/- 0.2 2.6 +/- 0.1 2.5 +/- 0.1 2.4 +/- 0.1 2.7 +/- 0.1 3/5/2019 3/12/2019 3.0 +/- 0.2 2.9 +/- 0.1 3.1 +/- 0.2 3/5/2019 3/13/2019 3.1 +/- 0.1 3.1 +/- 0.1 3/13/2019 3/19/2019 2.8 +/- 0.2 2.8 +/- 0.1 3/12/2019 3/19/2019 3.3 +/- 0.2 3.0 +/- 0.1 3.2 +/- 0.2 3/19/2019 3/26/2019 1.9 +/- 0.1 3/19/2019 3/27/2019 2.1 +/- 0.1 1.9 +/- 0.1 1.9 +/- 0.1 1.9 +/- 0.1 3/26/2019 4/2/2019 1.8 +/- 0.1 3/27/2019 4/2/2019 2.1 +/- 0.2 1.8 +/- 0.1 2.1 +/- 0.1 1.9 +/- 0.1 4/2/2019 4/9/2019 2.2 +/- 0.1 2.1 +/- 0.1 2.2 +/- 0.1 2.0 +/- 0.1 2.1 +/- 0.1 4/9/2019 4/16/2019 1.3 +/- 0.1 1.4 +/- 0.1 1.4 +/- 0.1 1.3 +/- 0.1 1.3 +/- 0.1 4/16/2019 4/23/2019 1.4 +/- 0.1 1.4 +/- 0.1 1.4 +/- 0.1 1.3 +/- 0.1 1.1 +/- 0.1 4/23/2019 4/30/2019 1.6 +/- 0.1 1.4 +/- 0.1 1.6 +/- 0.1 2.0 +/- 0.2 1.4 +/- 0.1 4/30/2019 5/7/2019 1.8 +/- 0.1 1.7 +/- 0.1 1.8 +/- 0.1 1.9 +/- 0.2 1.5 +/- 0.1 5/7/2019 5/14/2019 1.2 +/- 0.1 1.1 +/- 0.1 1.2 +/- 0.1 1.5 +/- 0.2 1.1 +/- 0.1 5/14/2019 5/21/2019 1.8 +/- 0.1 1.7 +/- 0.1 1.8 +/- 0.1 2.0 +/- 0.2 1.6 +/- 0.1 5/21/2019 5/29/2019 1.4 +/- 0.1 1.5 +/- 0.1 1.5 +/- 0.1 1.6 +/- 0.2 1.3 +/- 0.1 5/29/2019 6/4/2019 1.6 +/- 0.1 1.5 +/- 0.1 1.7 +/- 0.1 1.8 +/- 0.2 1.5 +/- 0.1 6/4/2019 6/11/2019 1.9 +/- 0.1 1.7 +/- 0.1 1.9 +/- 0.1 2.0 +/- 0.2 1.7 +/- 0.1 6/11/2019 6/18/2019 1.6 +/- 0.1 1.5 +/- 0.1 1.6 +/- 0.1 1.7 +/- 0.2 1.5 +/- 0.1 6/18/2019 6/25/2019 1.6 +/- 0.1 1.8 +/- 0.1 1.7 +/- 0.1 2.0 +/- 0.2 1.7 +/- 0.1 6/25/2019 7/3/2019 2.2 +/- 0.1 2.1 +/- 0.1 2.0 +/- 0.1 2.0 +/- 0.2 2.2 +/- 0.1 7/3/2019 7/10/2019 2.1 +/- 0.1 2.1 +/- 0.2 2.1 +/- 0.1 2.1 +/- 0.2 2.2 +/- 0.1 7/10/2019 7/16/2019 1.7 +/- 0.1 1.7 +/- 0.2 1.7 +/- 0.1 1.6 +/- 0.3 1.7 +/- 0.1 7/16/2019 7/23/2019 1.9 +/- 0.1 7/16/2019 7/24/2019 1.9 +/- 0.1 1.8 +/- 0.1 1.8 +/- 0.1 1.9 +/- 0.2 7/23/2019 7/30/2019 2.9 +/- 0.2 7/24/2019 7/30/2019 3.0 +/- 0.2 3.2 +/- 0.2 2.8 +/- 0.2 3.1 +/- 0.3 38

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-6 Concentration of Beta Emitters in Air Particulates - Offsite Samples (Results in units of 10-2 pCi/m3 +/- 2 Uncertainty)

Start Date Stop Date STATION- STATION- STATION- STATION- STATION-081 09 101 11 121 Seabreeze Webster Walworth Williamson Sodus Point 7/30/2019 8/6/2019 2.0 +/- 0.1 2.0 +/- 0.2 1.9 +/- 0.1 2.0 +/- 0.2 1.9 +/- 0.1 8/6/2019 8/13/2019 2.4 +/- 0.1 2.3 +/- 0.2 2.2 +/- 0.1 2 2.3 +/- 0.1 8/13/2019 8/20/2019 2.4 +/- 0.1 8/14/2019 8/21/2019 2.6 +/- 0.2 8/13/2019 8/21/2019 2.6 +/- 0.1 2.7 +/- 0.2 2.4 +/- 0.1 8/20/2019 8/27/2019 1.6 +/- 0.1 8/21/2019 8/27/2019 1.4 +/- 0.1 1.4 +/- 0.2 1.4 +/- 0.1 1.4 +/- 0.2 8/27/2019 9/4/2019 2.2 +/- 0.1 2.3 +/- 0.1 2.0 +/- 0.1 2.2 +/- 0.1 2.0 +/- 0.1 9/4/2019 9/12/2019 2.1 +/- 0.1 2.0 +/- 0.1 1.9 +/- 0.1 2.0 +/- 0.1 2.0 +/- 0.1 9/12/2019 9/17/2019 2.0 +/- 0.2 1.9 +/- 0.2 1.6 +/- 0.1 1.7 +/- 0.2 1.7 +/- 0.2 9/17/2019 9/24/2019 3.6 +/- 0.2 3.4 +/- 0.2 3.5 +/- 0.2 3.6 +/- 0.2 3.5 +/- 0.2 9/24/2019 10/1/2019 2.9 +/- 0.1 2.8 +/- 0.2 2.8 +/- 0.1 2.9 +/- 0.2 2.7 +/- 0.1 10/1/2019 10/8/2019 2.0 +/- 0.1 1.8 +/- 0.1 1.9 +/- 0.1 2.0 +/- 0.1 1.8 +/- 0.1 10/8/2019 10/15/2019 2.5 +/- 0.1 2.5 +/- 0.2 2.4 +/- 0.1 2.6 +/- 0.2 2.6 +/- 0.1 10/15/2019 10/22/2019 2.0 +/- 0.1 2.1 +/- 0.1 2.0 +/- 0.1 2.2 +/- 0.2 2.0 +/- 0.1 10/22/2019 10/29/2019 1.7 +/- 0.1 1.6 +/- 0.1 1.7 +/- 0.1 1.8 +/- 0.1 1.8 +/- 0.1 10/29/2019 11/5/2019 2.0 +/- 0.1 2.2 +/- 0.2 1.9 +/- 0.1 2.1 +/- 0.2 2.0 +/- 0.1 11/5/2019 11/12/2019 1.9 +/- 0.1 1.7 +/- 0.1 2.0 +/- 0.1 1.9 +/- 0.1 1.8 +/- 0.1 11/12/2019 11/19/2019 1.5 +/- 0.1 1.6 +/- 0.1 1.6 +/- 0.1 1.7 +/- 0.1 1.6 +/- 0.1 11/19/2019 11/26/2019 2.6 +/- 0.1 2.5 +/- 0.2 2.5 +/- 0.1 2.4 +/- 0.2 2.7 +/- 0.1 11/26/2019 12/3/2019 1.8 +/- 0.1 1.7 +/- 0.1 1.8 +/- 0.1 1.8 +/- 0.1 1.8 +/- 0.1 12/3/2019 12/10/2019 2.1 +/- 0.1 1.7 +/- 0.1 2.0 +/- 0.1 2.0 +/- 0.1 2.1 +/- 0.1 12/10/2019 12/18/2019 1.9 +/- 0.1 1.7 +/- 0.1 1.8 +/- 0.1 1.7 +/- 0.1 1.9 +/- 0.1 12/18/2019 12/26/2019 3.7 +/- 0.1 3.6 +/- 0.2 3.6 +/- 0.1 3.7 +/- 0.2 3.8 +/- 0.2 12/26/2019 1/2/2020 3.5 +/- 0.2 3.2 +/- 0.2 3.3 +/- 0.1 3.2 +/- 0.2 3.0 +/- 0.2 1Control Location 2Sampler Malfunction / Low Flow. See Section 3.5 for additional information.

39

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-7 Concentration of Gamma Emitters in Air Particulates (Results in units of 10-3 pCi/m3 +/- 2)

Location Description Sample Date Gamma Emitters (Cs-137) (I-131)

STATION-02 Manor House Yard 1/2/2019 < 1.8 < 0.002 4/1/2019 < 1.8 < 0.002 7/2/2019 < 1.8 < 0.002 10/1/2019 < 1.8 < 0.002 North of Training STATION-03 Center Parking Lot 1/2/2019 < 1.8 < 0.002 4/1/2019 < 1.8 < 0.002 7/2/2019 < 1.8 < 0.002 10/1/2019 < 1.8 < 0.002 Training Center STATION-04 Parking Lot 1/2/2019 < 1.8 < 0.002 4/1/2019 < 1.8 < 0.002 7/2/2019 < 1.8 < 0.002 10/1/2019 < 1.8 < 0.002 STATION-05 Creek Bridge 1/2/2019 < 1.8 < 0.002 4/1/2019 < 1.8 < 0.002 7/2/2019 < 1.8 < 0.002 10/1/2019 < 1.8 < 0.002 STATION-06 Main Parking Lot 1/2/2019 < 1.8 < 0.002 4/1/2019 < 1.8 < 0.002 7/2/2019 < 1.8 < 0.002 10/1/2019 < 1.8 < 0.002 STATION-07 West Fence Line 1/2/2019 < 1.8 < 0.002 4/1/2019 < 1.8 < 0.002 7/2/2019 < 1.8 < 0.002 10/1/2019 < 1.8 < 0.002 STATION-081 Seabreeze 1/2/2019 < 1.8 < 0.002 4/2/2019 < 1.8 < 0.002 7/3/2019 < 1.8 < 0.002 10/1/2019 < 1.8 < 0.002 STATION-09 Webster 1/2/2019 < 1.8 < 0.002 4/2/2019 < 1.8 < 0.002 7/3/2019 < 1.8 < 0.002 10/1/2019 < 1.8 < 0.002 STATION-101 Walworth 1/2/2019 < 1.8 < 0.002 4/2/2019 < 1.8 < 0.002 7/3/2019 < 1.8 < 0.002 10/1/2019 < 1.8 < 0.002 40

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-7 (Continued)

Concentration of Gamma Emitters in Air Particulates (Results in units of 10-3 pCi/m3 +/- 2)

Location Description Sample Date Gamma Emitters (Cs-137) (I-131)

STATION-11 Williamson 1/2/2019 < 1.8 < 0.002 4/2/2019 < 1.8 < 0.002 7/3/2019 < 1.8 < 0.002 10/1/2019 < 1.8 < 0.002 STATION-121 Sodus Point 1/2/2019 < 1.8 < 0.002 4/2/2019 < 1.8 < 0.002 7/3/2019 < 1.8 < 0.002 10/1/2019 < 1.8 < 0.002 STATION-13 Substation 13 1/2/2019 < 1.8 < 0.002 4/2/2019 < 1.8 < 0.002 7/3/2019 < 1.8 < 0.002 10/1/2019 < 1.8 < 0.002 1

Control Location 41

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-8 Concentration of Gamma Emitters in Vegetation Samples (Results in units of pCi/kg (wet) +/- 2)

Sample Code Sample Date Sample Type Gamma Emitters (Cs-137) (I-131)

CONTROL1 Local Sites in Control Sectors 7/11/2019 Zucchini < 27 < 20 7/13/2019 Greens < 27 < 20 9/19/2019 Apples < 27 < 20 9/19/2019 Grapes < 27 < 20 9/19/2019 Onion (root) < 27 < 20 9/19/2019 Pears < 27 < 20 9/19/2019 Tomato < 27 < 20 9/19/2019 Tuber (potato) < 27 < 20 EAST East Sector 7/11/2019 Greens < 27 < 20 7/16/2019 Zucchini < 27 < 20 8/5/2019 Tuber (potato) < 27 < 20 8/27/2019 Onion (root) < 27 < 20 8/27/2019 Tomato < 27 < 20 9/19/2019 Pears < 27 < 20 ESE East South East Sector 7/11/2019 Greens < 27 < 20 7/22/2019 Raspberries < 27 < 20 7/24/2019 Tomato < 27 < 20 8/5/2019 Tuber (potato) < 27 < 20 8/5/2019 Zucchini < 27 < 20 9/3/2019 Onion (root) < 27 < 20 9/19/2019 Grapes < 27 < 20 SSE South South East Garden 7/10/2019 Greens < 27 < 20 7/16/2019 Zucchini < 27 < 20 8/5/2019 Onion (root) < 27 < 20 8/27/2019 Tomato < 27 < 20 8/27/2019 Tuber (potato) < 27 < 20 1 Control Location 42

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-9 Concentration of Gamma Emitters (including I-131) in Milk (Results in units of pCi/Liter +/- 2)

Sample Code Sample Date Gamma Emitters Cs-137 (I-131)

FARM_A (FIELD CRAFT)

ESE Supplemental 1/14/2019 < 0.4 < 0.01 2/11/2019 < 0.4 < 0.01 3/11/2019 < 0.4 < 0.01 4/8/2019 < 0.4 < 0.01 5/6/2019 < 0.4 < 0.01 5/20/2019 < 0.4 < 0.01 6/3/2019 < 0.4 < 0.01 6/17/2019 < 0.4 < 0.01 7/1/2019 < 0.4 < 0.01 7/15/2019 < 0.4 < 0.01 7/29/2019 < 0.4 < 0.01 8/12/2019 < 0.4 < 0.01 8/26/2019 < 0.4 < 0.01 9/9/2019 < 0.4 < 0.01 9/23/2019 < 0.4 < 0.01 10/7/2019 < 0.4 < 0.01 10/21/2019 < 0.4 < 0.01 11/18/2019 < 0.4 < 0.01 12/16/2019 < 0.4 < 0.01 FARM_B (SCHULTZ1)

South Sodus Control 1/14/2019 < 0.4 < 0.01 2/11/2019 < 0.4 < 0.01 3/11/2019 < 0.4 < 0.01 4/8/2019 < 0.4 < 0.01 5/6/2019 < 0.4 < 0.01 5/20/2019 < 0.4 < 0.01 6/3/2019 < 0.4 < 0.01 6/17/2019 < 0.4 < 0.01 7/1/2019 < 0.4 < 0.01 7/15/2019 < 0.4 < 0.01 7/29/2019 < 0.4 < 0.01 8/12/2019 < 0.4 < 0.01 8/26/2019 < 0.4 < 0.01 9/9/2019 < 0.4 < 0.01 9/23/2019 < 0.4 < 0.01 10/7/2019 < 0.4 < 0.01 10/21/2019 < 0.4 < 0.01 11/18/2019 < 0.4 < 0.01 12/16/2019 < 0.4 < 0.01 1 Control Location 43

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-10 Typical MDA Ranges for Gamma Spectrometry Surface Shoreline Air Water, Ground- Vegetation Selected Fish (pCi/kg) Milk Oysters Sediment Soil (pCi/kg)

Particulates Drinking water (pCi/kg)

Nuclides Wet (pCi/L) (pCi/kg) (pCi/kg) Dry (10-2 pCi/m3) Water (pCi/L) Wet Dry (pCi/L)

Na-22 0.03 - 0.47 3.1 - 5.1 9.6 - 25.7 3.6 - 5.2 5 - 7.3 5.9 - 23.6 27.1 - 74.8 33.9 - 90.3 11.1 - 32.3 K-40 0.16 - 8.09 32.2 - 58.8 69.2 - 212 41.4 - 63 40.4 - 61.7 70.8 - 204 300 - 749 308 - 744 91.8 - 270 Cr-51 1.31 - 11.0 27.6 - 43.3 74 - 267 29.4 - 39.8 36.9 - 52.5 25.8 - 285 477 - 1303 507 - 1486 29.2 - 327 Mn-54 0.03 - 0.52 3 - 4.6 6.9 - 36.2 3.2 - 4.8 3.9 - 5.6 9.4 - 21.7 27.0 - 69.9 32.7 - 82.6 8.9 - 28.2 Co-58 0.05 - 0.73 3.1 - 4.7 8.6 - 38.6 3.2 - 4.8 4.1 - 5.7 7.4 - 30 38.6 - 96.8 38.1 - 109 8.2 - 30.5 Fe-59 0.21 - 2.35 6.8 - 10.4 26.8 - 97.6 7.1 - 10.8 10.1 - 14.3 14.3 - 87.1 96.7 - 271 100 - 283 18.5 - 73.9 Co-60 0.03 - 0.48 3.1 - 4.7 10.2 - 33.3 3.3 - 4.9 4.5 - 6.5 10 - 21.9 26.2 - 72 31.1 - 82.5 10.1 - 29.8 Zn-65 0.08 - 1.33 6.5 - 10.3 22.5 - 82.3 7.2 - 12 10.1 - 15.2 23.1 - 54 81 - 196 86.9 - 240 22.2 - 68.2 Nb-95 0.14 - 1.07 3.4 - 5.3 9 - 33.5 3.6 - 5.2 4.5 - 6.2 5.3 - 31.1 64.7 - 155 62.1 - 183 6.9 - 38.9 Zr-95 0.10 - 1.01 5.3 - 8.2 15.1 - 42.8 5.8 - 8 7.1 - 9.6 10.2 - 38.9 66.7 - 166 77.4 - 192 14.2 - 53.7 Ru-106 0.30 - 396 25.8 - 40.9 65.3 - 170 28.6 - 40.8 33.6 - 47.6 42.7 - 159 226 - 560 292 - 699 77.4 - 236 Ag-110m 0.03 - 0.43 2.9 - 4.5 7.8 - 20.2 3.2 - 4.5 3.7 - 5.2 5.1 - 18.3 26.7 - 65.1 35.2 - 90 8.3 - 26.4 I-1311 1.85 - 137 1.7 - 10.5 0 - 466 5.1 - 8.8 0.4 - 11.1 0 - 1046 294 - 4372 0 - 3833 0 - 583 Cs-134 0.03 - 0.40 2.9 - 4.4 7.7 - 30.1 3.2 - 4.6 3.6 - 5.3 8.5 - 21.4 41.6 - 66.6 44.5 - 84.4 10.2 - 27.5 Cs-137 0.03 - 0.43 3.2 - 4.9 7.7 - 36.6 3.5 - 5 4 - 5.7 9.7 - 21.4 42 - 59.7 40.6 - 87.2 11.2 - 29.3 Ba-140 1.01 - 17.2 5.1 - 14.2 0 - 145 5.8 - 9.7 7.8 - 28 0 - 199 274 - 1006 44.9 - 1198 0 - 175 La-140 1.01 - 17.2 6.1 - 10.6 0 - 142.5 5.8 - 9.7 6.3 - 10.9 0 - 199 274 - 1006 45.0 - 1198 0 - 174 Ce-144 0.12 - 2.05 16.2 - 30.9 39.4 - 110 19.8 - 26.6 22.7 - 37.2 27.3 - 112 128 - 314 187 - 435 42 - 127 1 This MDA range for I-131 on a charcoal cartridge is typically 3.94 x 10-3 to 6.10 x 10-2 pCi/m3 44

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-11 Typical LLDs for Gamma Spectrometry Air Surface Water, Selected Fish pCi/kg Groundwater Oysters pCi/kg Precipitation Soil pCi/kg Vegetation Particulates Drinking Water Nuclides (wet) pCi/L (wet) pCi/L (dry) pCi/kg (wet) 10-3 pCi/m3 pCi/L Na-22 2.9 2.9 22 2.9 6 22 24 35 Cr-51 12 17 88 17 30 88 110 162 Mn-54 2.1 2.4 17 2.4 5 17 18 27 Co-58 2 2.4 16 2.4 5 16 17 25 Fe-59 4.6 5.2 37 5.2 11 37 38 60 Co-60 2.7 2.8 22 2.8 6 22 21 33 Zn-65 2.8 5.6 23 5.6 12 23 54 66 Nb-95 1.9 2.2 15 2.2 4 15 18 25 Zr-95 3.3 3.8 27 3.8 8 27 29 44 Ru-106 17 20 135 20 39 135 146 223 Ag-110m 1.8 2.1 14 2.1 4 14 16 25 Te-129m 20 26 149 26 50 149 180 265 I-131 1.5* 2** 11 2 4** 11 14 20 Cs-134 1.9 2.2 15 2.2 4 15 20 24 Cs-137 1.8 2.3 15 2.3 5 15 17 27 Ba-140 6.1 7.3 48 7.3 5 48 54 80 La-140 3.4 4.1 26 4.1 5 26 25 41 Ce-144 5.5 12 43 12 20 43 75 101 3

The LLD for I-131 measured on a charcoal cartridge is 2.0 x10-3 pCi/m

- The LLD for Low Level I-131 measured in drinking water and milk is 0.3 pCi/L 45

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-12 Direct Radiation 2019 Quarterly Dose (mrem/ 91 days) 2019 Location Quarterly Quarterly QTRLY mrem / 91 Days Quarterly Standard Facility CVQ Value Baseline, Deviation, Dose, FQ

+3 SDs TLD 1st QTR 2nd QTR 3rd QTR 4th QTR AVG MAX BQ (mrem) SQ (mrem) (mrem) 2 12.4 +/- 0.4 13.0 +/- 0.6 11.8 +/- 0.7 13.6 +/- 0.5 12.7 13.6 12.7 0.94 0.07 15.54 ND 3 12.4 +/- 0.5 13.5 +/- 0.7 12.5 +/- 0.6 14.0 +/- 0.7 13.1 14.0 13.0 1.07 0.08 16.20 ND 4 11.1 +/- 0.6 12.3 +/- 0.8 11.1 +/- 0.4 13.1 +/- 0.7 11.9 13.1 11.8 0.98 0.08 14.80 ND 5 12.3 +/- 0.4 13.2 +/- 1.0 12.7 +/- 0.6 13.6 +/- 0.9 12.9 13.6 12.8 0.95 0.07 15.64 ND 6 9.7 +/- 0.4 10.1 +/- 0.8 9.8 +/- 0.4 10.3 +/- 0.4 10.0 10.3 9.9 1.09 0.11 13.22 ND 7 11.6 +/- 0.4 11.8 +/- 0.8 11.6 +/- 0.4 12.4 +/- 0.5 11.8 12.4 11.8 1.35 0.11 15.89 ND 81 11.4 +/- 0.6 11.4 +/- 0.6 11.3 +/- 0.5 12.6 +/- 0.7 11.7 12.6 11.4 0.98 0.09 14.34 ND 9 10.4 +/- 0.6 11.2 +/- 0.6 11.0 +/- 0.7 12.0 +/- 0.8 11.1 12.0 11.1 0.84 0.08 13.59 ND 101 10.3 +/- 0.3 10.8 +/- 0.7 10.0 +/- 0.4 11.9 +/- 0.6 10.7 11.9 10.4 0.85 0.08 12.95 ND 11 10.5 +/- 0.8 10.6 +/- 0.7 10.6 +/- 0.5 11.6 +/- 0.5 10.8 11.6 10.7 0.89 0.08 13.38 ND 121 11.6 +/- 0.6 12.4 +/- 0.6 11.8 +/- 0.4 13.1 +/- 0.7 12.2 13.1 12.0 0.91 0.08 14.69 ND 13 19.0 +/- 0.9 20.3 +/- 1.1 17.6 +/- 0.6 21.0 +/- 1.0 19.5 21.0 17.4 2.28 0.13 24.26 ND 14 11.4 +/- 0.4 12.5 +/- 0.6 11.7 +/- 0.4 13.3 +/- 0.6 12.2 13.3 12.3 1.11 0.09 15.60 ND 15 12.1 +/- 0.4 13.4 +/- 0.7 12.7 +/- 0.6 15.0 +/- 0.6 13.3 15.0 13.3 1.00 0.07 16.28 ND 16 12.6 +/- 0.6 13.2 +/- 0.6 12.9 +/- 0.7 13.8 +/- 0.6 13.1 13.8 12.9 0.91 0.07 15.65 ND 17 11.8 +/- 0.4 12.9 +/- 0.6 11.8 +/- 0.6 13.4 +/- 0.6 12.5 13.4 12.3 1.06 0.09 15.53 ND 18 10.4 +/- 0.6 10.1 +/- 0.5 9.7 +/- 0.6 11.6 +/- 0.7 10.5 11.6 10.5 1.01 0.10 13.48 ND 19 10.6 +/- 0.5 10.1 +/- 0.7 9.7 +/- 0.7 10.7 +/- 0.5 10.3 10.7 10.4 0.84 0.08 12.94 ND 20 12.3 +/- 0.5 11.9 +/- 0.6 11.6 +/- 0.5 13.8 +/- 1.0 12.4 13.8 12.3 1.04 0.08 15.45 ND 21 11.5 +/- 0.7 12.5 +/- 0.9 11.8 +/- 0.7 13.3 +/- 0.5 12.3 13.3 12.2 0.95 0.08 15.05 ND 22 11.8 +/- 0.4 10.8 +/- 0.7 10.7 +/- 0.4 12.4 +/- 0.5 11.4 12.4 11.1 0.89 0.08 13.75 ND 23 11.9 +/- 0.6 13.0 +/- 0.9 12.5 +/- 0.4 14.4 +/- 0.9 13.0 14.4 12.7 1.06 0.08 15.86 ND 24 12.0 +/- 0.5 12.8 +/- 0.6 12.1 +/- 0.7 14.0 +/- 0.9 12.7 14.0 12.6 0.99 0.08 15.61 ND 251 10.8 +/- 0.5 11.0 +/- 0.6 10.1 +/- 0.4 12.0 +/- 0.6 11.0 12.0 10.9 0.97 0.09 13.77 ND 261 9.4 +/- 0.4 9.8 +/- 0.6 9.3 +/- 0.4 11.6 +/- 0.6 10.0 11.6 10.6 1.03 0.10 13.69 ND 46

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-12 Direct Radiation 2019 Quarterly Dose (mrem/ 91 days) 2019 Location Quarterly Quarterly QTRLY mrem / 91 Days Quarterly Standard Facility CVQ Value Baseline, Deviation, Dose, FQ

+3 SDs TLD 1st QTR 2nd QTR 3rd QTR 4th QTR AVG MAX BQ (mrem) SQ (mrem) (mrem) 1 27 10.3 +/- 0.5 11.1 +/- 0.5 11.1 +/- 0.4 11.3 +/- 0.6 11.0 11.3 11.1 0.97 0.09 14.02 ND 281 10.6 +/- 0.3 11.3 +/- 0.6 10.4 +/- 0.4 12.2 +/- 0.6 11.1 12.2 10.9 1.00 0.09 13.87 ND 291 10.7 +/- 0.5 11.3 +/- 0.6 10.4 +/- 0.4 12.2 +/- 0.8 11.1 12.2 10.8 0.97 0.09 13.71 ND 301 9.7 +/- 0.5 9.9 +/- 0.6 9.3 +/- 0.3 10.7 +/- 0.5 9.9 10.7 9.8 0.92 0.09 12.57 ND 31 12.3 +/- 0.6 12.5 +/- 0.8 12.6 +/- 0.5 13.6 +/- 0.8 12.8 13.6 12.7 1.07 0.08 15.94 ND 32 10.6 +/- 0.4 11.4 +/- 0.9 10.3 +/- 0.5 11.9 +/- 0.7 11.1 11.9 11.0 0.94 0.09 13.78 ND 33 10.1 +/- 0.4 10.4 +/- 0.6 9.9 +/- 0.6 11.5 +/- 0.7 10.5 11.5 10.5 1.01 0.10 13.53 ND 34 12.9 +/- 0.8 13.5 +/- 0.7 12.1 +/- 0.6 14.1 +/- 0.9 13.1 14.1 13.1 0.96 0.07 16.02 ND 35 11.9 +/- 0.7 12.6 +/- 0.6 12.6 +/- 0.5 13.2 +/- 0.5 12.6 13.2 12.7 1.16 0.09 16.13 ND 36 10.3 +/- 0.7 10.9 +/- 0.7 10.2 +/- 0.5 12.4 +/- 0.6 10.9 12.4 11.0 0.94 0.09 13.78 ND 37 9.8 +/- 0.6 10.6 +/- 0.8 10.1 +/- 0.4 11.4 +/- 0.5 10.5 11.4 10.3 1.01 0.10 13.35 ND 38 12.4 +/- 0.5 12.6 +/- 0.8 12.2 +/- 0.4 13.4 +/- 0.9 12.7 13.4 12.4 1.00 0.08 15.42 ND 39 11.4 +/- 0.4 12.6 +/- 1.1 11.7 +/- 0.7 13.2 +/- 0.8 12.2 13.2 12.2 1.10 0.09 15.50 ND 40 10.4 +/- 1.1 11.4 +/- 0.6 10.5 +/- 0.8 11.6 +/- 0.6 11.0 11.6 10.7 0.84 0.08 13.21 ND 63 12.3 +/- 0.6 13.1 +/- 1.0 12.1 +/- 0.5 14.1 +/- 0.6 12.9 14.1 12.6 1.02 0.08 15.67 ND 64 13.4 +/- 0.5 14.3 +/- 0.8 13.0 +/- 0.8 14.7 +/- 0.8 13.9 14.7 13.8 1.11 0.08 17.19 ND 1 - Control Location 47

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-12 Direct Radiation 2019 Annual Dose (mrem/ year)

YRLY 2019 Annual Baseline, Annual Standard Deviation, Values Annual Facility TLD (mrem) BA (mrem) SA (mrem) CVA +3 SDs Dose, FA 2 50.7 50.9 1.03 0.02 53.95 ND 3 52.4 52.0 1.28 0.02 55.85 ND 4 47.5 47.4 0.85 0.02 49.93 ND 5 51.8 51.2 1.22 0.02 54.89 ND 6 39.9 39.8 0.87 0.02 42.41 ND 7 47.2 47.4 3.70 0.08 58.49 ND 81 46.7 45.6 0.81 0.02 48.00 ND 9 44.6 44.3 0.63 0.01 46.16 ND 101 43.0 41.5 0.95 0.02 44.40 ND 11 43.2 42.9 0.89 0.02 45.54 ND 121 48.8 47.9 0.85 0.02 50.45 ND 13 77.9 69.7 7.68 0.11 92.76 ND 14 49.0 49.0 1.32 0.03 52.99 ND 15 53.3 53.2 0.85 0.02 55.72 ND 16 52.5 51.7 1.17 0.02 55.18 ND 17 49.9 49.4 0.95 0.02 52.21 ND 18 41.8 41.8 0.43 0.01 43.11 ND 19 41.1 41.6 0.97 0.02 44.55 ND 20 49.4 49.4 0.90 0.02 52.05 ND 21 49.0 48.7 1.29 0.03 52.59 ND 22 45.7 44.3 1.13 0.03 47.69 ND 23 51.8 50.7 1.02 0.02 53.77 ND 24 50.9 50.6 1.25 0.02 54.30 ND 251 43.9 43.4 0.89 0.02 46.08 ND 261 40.2 42.4 2.37 0.06 49.46 ND 48

January 1 - December 31, 2019 Docket Nos. 50-244 Table B-12 Direct Radiation 2019 Annual Dose (mrem/ year)

YRLY 2019 Annual Baseline, Annual Standard Deviation, Values Annual Facility TLD (mrem) BA (mrem) SA (mrem) CVA +3 SDs Dose, FA 271 43.9 44.5 1.58 0.04 49.21 ND 281 44.6 43.5 0.93 0.02 46.31 ND 291 44.6 43.1 1.17 0.03 46.64 ND 301 39.5 39.2 0.78 0.02 41.56 ND 31 51.0 50.9 1.71 0.03 56.03 ND 32 44.2 43.8 1.02 0.02 46.91 ND 33 42.0 42.0 1.26 0.03 45.76 ND 34 52.5 52.6 1.35 0.03 56.63 ND 35 50.3 50.6 1.93 0.04 56.41 ND 36 43.7 43.9 1.09 0.02 47.15 ND 37 41.9 41.3 0.79 0.02 43.63 ND 38 50.7 49.6 1.03 0.02 52.74 ND 39 48.9 48.8 0.80 0.02 51.20 ND 40 43.8 42.8 0.79 0.02 45.16 ND 63 51.5 50.4 1.49 0.03 54.86 ND 64 55.5 55.4 1.33 0.02 59.37 ND 1 - Control Location 49

January 1 - December 31, 2019 Docket Nos. 50-244 TABLE B-13 Groundwater Monitoring Wells Location Sample Date Tritium (pCi/l) Gamma1 (uCi/ml)

GW01: Warehouse Access Road (Control) 3/13/2019 < 460 < 6.95E-09 6/26/2019 < 426 < 5.92E-09 9/4/2019 < 431 < 6.97E-09 12/13/2019 < 451 < 1.12E-08 GW03: Screenhouse West, South Well2 1/27/2019 < 444 2/22/2019 < 453 3/14/2019 < 450 < 8.80E-09 4/12/2019 < 404 5/24/2019 446 5/29/2019 579 6/27/2019 < 426 < 7.06E-09 7/25/2019 < 413 8/16/2019 < 428 9/4/2019 < 439 < 1.02E-08 10/25/2019 < 488 11/19/2019 < 459 12/13/219 < 469 < 7.98E-09 GW04: Screenhouse West, North Well 3/14/2019 < 454 < 8.09E-09 6/27/2019 < 428 < 6.86E-09 9/4/2019 < 439 < 6.78E-09 12/13/2019 < 482 < 6.33E-09 GW05: Screenhouse East, South (15.5) 3/14/2019 < 452 < 6.10E-09 6/26/2019 < 427 < 8.44E-09 9/4/2019 < 457 < 9.30E-09 12/13/2019 < 484 < 8.43E-09 GW06: Screenhouse East, Middle (20.0) 3/14/2019 < 451 < 6.52E-09 6/26/2019 < 425 < 6.52E-09 9/4/2019 < 434 < 7.23E-09 12/13/2019 < 483 < 8.59E-09 GW07: Screenhouse East, North (24.0) 3/14/2019 < 454 < 7.31E-09 6/26/2019 < 423 < 6.61E-09 9/4/2019 < 448 < 7.17E-09 12/13/2019 < 486 < 7.17E-09 50

January 1 - December 31, 2019 Docket Nos. 50-244 TABLE B-13 (Continued)

Groundwater Monitoring Wells Location Sample Date Tritium (pCi/l) Gamma (uCi/ml)

GW08: All Volatiles Treatment Building2 1/27/2019 < 443 2/22/2019 < 449 3/14/2019 < 454 < 9.62E-09 4/12/2019 < 409 5/24/2019 542 5/29/2019 521 6/27/2019 < 424 < 8.21E-09 7/25/2019 < 430 8/16/2019 < 429 9/4/2019 < 425 < 1.14E-08 10/25/2019 < 486 11/19/2019 < 462 12/13/219 < 483 < 1.12E-08 GW10: Technical Support Center, South 3/14/2019 < 457 < 6.85E-09 6/26/2019 < 426 < 8.46E-09 9/4/2019 < 424 < 1.88E-09 12/13/2019 603 < 9.61E-09 GW11: Southeast of Contaminated Service 3/14/2019 < 449 < 9.89E-09 Building (CSB) 6/26/2019 < 427 < 6.19E-09 9/4/2019 < 448 < 8.20E-09 12/13/2019 < 479 < 8.13E-09 GW12: West of Orchard Access Road 3/13/2019 < 453 < 6.85E-09 6/26/2019 < 418 < 9.77E-09 9/4/2019 < 422 < 7.33E-09 12/13/2019 < 487 < 9.35E-09 GW13: North of Independent Spent Fuel 3/14/2019 < 458 < 7.38E-09 Storage Installation (ISFSI) 6/26/2019 < 427 < 6.21E-09 9/4/2019 < 426 < 7.98E-09 12/13/2019 < 488 < 7.92E-09 GW14: South of Canister Preparation Building 3/14/2019 < 454 < 1.05E-08 6/26/2019 < 422 < 6.30E-09 9/4/2019 < 430 < 9.36E-09 12/13/2019 < 480 < 7.50E-09 51

January 1 - December 31, 2019 Docket Nos. 50-244 TABLE B-13 (Continued)

Groundwater Monitoring Wells Location Sample Date Tritium (pCi/l) Gamma (uCi/ml)

GW15: West of Manor House 3/13/2019 < 454 < 6.71E-09 6/26/2019 < 425 < 7.68E-09 9/4/2019 < 419 < 7.42E-09 12/13/2019 < 485 < 9.98E-09 GW16: Southeast of Manor House 3/13/2019 < 456 < 8.12E-09 6/26/2019 < 427 < 7.95E-09 9/4/2019 < 422 < 8.35E-09 12/13/2019 < 487 < 9.01E-09 1Gamma 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.

52

January 1 - December 31, 2019 Docket Nos. 50-244 APPENDIX C Quality Assurance Program Summary of Appendix C Content:

Appendix C is a summary of Exelon Industrial Services (EIS) laboratorys quality assurance program. It consists of Table C-1 which is a compilation of the results of the EIS laboratorys participation in an interlaboratory comparison program with Environmental Resource Associates (ERA) located in Arvada, Colorado and Eckert and Ziegler Analytics, Inc. (EZA) located in Atlanta, Georgia. It also includes Table C-2, which is a compilation of the results of the EIS laboratorys participation in a split sample program with Teledyne Brown Engineering located in Knoxville, Tennessee. Finally, Table C-3, is a list of the power plant's ODCM required LLDs, all of which are achieved by both EIS laboratory and Teledyne Brown Engineering for the analyses reported.

All the EIS laboratorys results contained in Table C-1, inter-comparison results, are in full agreement when they were evaluated using the NRC Resolution Test Criteria[1]. The EIS laboratorys results are provided with their analytical uncertainties of 2 sigma. When evaluating with the NRC Resolution Test a one sigma uncertainty is used to determine Pass or Fail and noted accordingly.

The EIS laboratory results contained in Table C-2 are inter-comparison results for routine samples analyzed for replicate and split analyses and evaluated for beta and non-natural gamma emitters. The EIS laboratorys results are provided with their analytical uncertainties of 2 sigma. When evaluating with the NRC Resolution Test a one sigma uncertainty is used to determine Pass or Fail and noted accordingly. In the event there are no non-natural isotopes detected, the samples are reported <MDA and designated as Pass.

All the results contained in Table C-2 agree with their respective EIS laboratory original, replicate and/or Teledyne Brown Engineerings split laboratory samples, except for the comparisons of Beta emitters in a particulate sample with poor resolution at A2 collected on 06/10/19 and one sample involving Cs-137 results for a bottom sediment sample at WBS2 collected on 6/25/19.

The original and replicate analysis of the air particulate sample from A2 collected on 06/10/19 failed the NRC Resolution test criteria due to low volume collected resulting from a power outage to the air sampler. Poor resolution of these results is attributed to the low volume collected resulting in insufficient counting statistics. A nonconformance was issued on this event and recorded in the corrective action program.

In the bottom sediment sample, WBS2 collected on 6/25/19, the original and replicate analysis do pass NRC Resolution test criteria however the result does not agree within the required resolution for the split lab result. These minor discrepancies, which have been observed in previous reporting periods, are most probably due to counting statistics and/or the non-homogeneous nature of this type of sample.

All air particulate samples contain beta emitters and are reported with a 2-sigma uncertainty. The original and replicate analyses are evaluated for agreement using the NRC Resolution Test Criteria1.These samples must be composited for further analysis and this precludes them from being split for analysis of beta emitters. Filters and other samples whose nature generally preclude sample splitting are marked ** in the Split Analysis column.

[1] NRC Inspection Manual, Inspection Procedure 84750, March 15, 1994 53

January 1 - December 31, 2019 Docket Nos. 50-244 TABLE OF CONTENTS - ANALYTICAL RESULTS Table Title Page C-1 Results of Participation in Cross Check Program............................................................................ 55 C-2 Results of Quality Assurance Program ............................................................................................ 58 C-3 Teledyne Brown Engineerings Typical MDAs for Gamma Spectrometry .................................... 65 54

January 1 - December 31, 2019 Docket Nos. 50-244 TABLE C-1 Results of Participation in Cross Check Program Reported Sample Type and Cross Check Lab Sample Date Isotope Observed Laboratory's Units Results Results 3/14/2019 Air Iodine - pCi I-131 73.0 +/- 11.0 75.6 3/14/2019 Milk - pCi/L Fe-59 149 +/- 25.0 159 Mn-54 141 +/- 16.0 143 Co-60 262 +/- 16.0 299 Co-58 128 +/- 17.0 143 Cr-51 227 +/- 101.0 293 Ce-141 101 +/- 20.0 117 Cs-137 184 +/- 18.0 196 Cs-134 138 +/- 10.0 160 I-131 92.0 +/- 36.0 89.5 Zn-65 177 +/- 32.0 220 3/14/2019 Water - pCi/L Gross Beta 26.4 +/- 4.84 28.8 4/8/2019 Water - pCi/L I-131 25.3 +/- 8.0 28.4 Ba-133 23.0 +/- 2.7 24.1 Cs-137 34.4 +/- 3.4 33.1 Cs-134 10.8 +/- 1.7 12.1 Zn-65 88.0 +/- 9.3 89.2 Co-60 11.3 +/- 1.8 11.5 4/8/2019 Water - pCi/L Gross Beta 28.8 +/- 2.09 29.9 6/6/2019 Air Iodine - pCi Cs-134 80.9 +/- 4.4 93 Zn-65 185 +/- 18.0 164 Co-60 139 +/- 7.0 131 Co-58 77.7 +/- 7.4 74.1 Fe-59 121 +/- 13.0 93.5 Mn-54 142 +/- 8.9 126 Cs-137 119 +/- 7.7 111 Cr-51 222 +/- 50.6 223 Ce-141 97.7 +/- 7.7 88.3 6/6/2019 Water Mn-54 214 +/- 17.6 207 Fe-59 154 +/- 22.5 154 Co-58 115 +/- 15.6 122 Co-60 216 +/- 12.8 216 Zn-65 257 +/- 31.6 270 I-131 115 +/- 77.0 89.1 Cs-134 139 +/- 8.8 153 Cs-137 186 +/- 15.7 184 Ce-141 142 +/- 22.7 145 Cr-51 327 +/- 117 368 6/6/2019 Water - pCi/L Gross Beta 199 +/- 4.2 199 9/12/2019 Air Filter - pCi/m3 Gross Beta 271 +/- 3.42 221 55

January 1 - December 31, 2019 Docket Nos. 50-244 TABLE C Continued Results of Participation in Cross Check Program Reported Sample Type and Cross Check Lab Sample Date Isotope Observed Laboratory's Units Results Results 9/16/2019 Air Iodine - pCi Am-241 28.4 +/- 9.9 32 Cs-137 440 +/- 20.0 437 Cs-134 60.7 +/- 5.2 59 Zn-65 381 +/- 31.0 364 Co-60 57.5 +/- 6.1 58.4 10/4/2019 Water - pCi/L Cs-137 80.3 +/- 7.2 78.7 Ba-133 37.2 +/- 5.4 43.8 Cs-134 52.2 +/- 4.2 55.9 Zn-65 39.3 +/- 10.0 34 I-131 25.4 +/- 8.3 23.9 Co-60 54.8 +/- 5.1 53.4 Air Filter -

12/5/2019 Mn-54 170 +/- 13.0 155 pCi (Det 2)

Fe-59 124 +/- 14.3 104 Co-58 117 +/- 11.7 107 Co-60 139 +/- 9.1 138 Zn-65 194 +/- 24.8 190 Cs-134 123 +/- 7.4 135 Cs-137 128 +/- 11.6 121 Ce-141 98.5 +/- 6.4 99.1 Cr-51 246 +/- 46.6 288 Air Filter -

12/5/2019 Mn-54 173 +/- 11.3 155 pCi (Det 3)

Fe-59 122 +/- 10.8 104 Co-58 111 +/- 8.9 107 Co-60 148 +/- 7.9 138 Zn-65 203 +/- 20.9 190 Cs-134 128 +/- 5.7 135 Cs-137 128 +/- 8.9 121 Ce-141 95.7 +/- 7.0 99.1 Cr-51 257 +/- 40.6 288 Air Filter -

12/5/2019 Mn-54 167 +/- 9.1 155 pCi (Det 4)

Fe-59 132 +/- 10.3 104 Co-58 102 +/- 7.3 107 Co-60 146 +/- 7.2 138 Zn-65 195 +/- 17.3 190 Cs-134 122 +/- 4.9 135 Cs-137 122 +/- 7.6 121 Ce-141 102 +/- 6.1 99.1 Cr-51 299 +/- 29.9 288 56

January 1 - December 31, 2019 Docket Nos. 50-244 TABLE C Continued Results of Participation in Cross Check Program Reported Sample Type and Cross Check Lab Sample Date Isotope Observed Laboratory's Units Results Results Air Iodine - pCi 12/5/2019 I-131 79.2 +/- 5.7 88.2 (Det 4)

(Det 2) I-131 79.0 +/- 6.3 88.2 (Det 3) I-131 79.1 +/- 6.0 88.2 12/5/2019 Milk pCi/L I-131 100 +/- 16.9 94.5 (DET 2)

Ce-141 82.4 +/- 15.9 83 Cr-51 271 +/- 76.7 241 Cs-134 112 +/- 11.9 113 Cs-137 123 +/- 17.9 102 Co-58 84.9 +/- 14.6 89.9 Mn-54 128 +/- 17.4 130 Fe-59 95.5 +/- 20.2 87.1 Zn-65 148 +/- 34.3 159 Co-60 119 +/- 13.3 115 12/5/2019 Milk pCi/L I-131 99.3 +/- 15.0 94.5 (DET 3)

Ce-141 80.7 +/- 12.5 83 Cr-51 228 +/- 63.0 241 Cs-134 103 +/- 9.6 113 Cs-137 109 +/- 12.2 102 Co-58 102 +/- 12.2 89.9 Mn-54 141 +/- 15.2 130 Fe-59 102 +/- 15.7 87.1 Zn-65 166 +/- 28.4 159 Co-60 111 +/- 10.8 115 12/5/2019 Milk pCi/L I-131 104 +/- 13.5 94.5 (DET 4)

Ce-141 78.3 +/- 12.7 83 Cr-51 235 +/- 68.0 241 Cs-134 114 +/- 8.3 113 Cs-137 105 +/- 13.2 102 Co-58 92.0 +/- 11.4 89.9 Mn-54 143 +/- 13.8 130 Fe-59 104 +/- 14.9 87.1 Zn-65 164 +/- 27.2 159 Co-60 123 +/- 10.2 115 12/5/2019 Water - pCi/L Gross Beta 260 +/- 4.76 269 1 See discussion at the beginning of the Appendix 57

January 1 - December 31, 2019 Docket Nos. 50-244 TABLE C-2 Results of Quality Assurance Program Sample Type and Type of Result2 Original Replicate Split Sample Date Location Analysis Units Analysis Analysis Analysis Air Iodine - A1 1/7/2019 I-131 pCi/m3 <MDA <MDA **

Air Iodine - A2 1/7/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A3 1/7/2019 I-131 pCi/m3 <MDA <MDA **

Air Iodine - A4 1/7/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A5 1/7/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - SFA1 1/7/2019 I-131 pCi/m 3

<MDA <MDA **

Air Filter - A1 2/11/2019 Gross Beta pCi/m 3 2.3 +/- 0.1 2.3 +/- 0.1 **

Air Filter - A2 2/11/2019 Gross Beta pCi/m3 2.4 +/- 0.1 2.3 +/- 0.1 **

Air Filter - A3 2/11/2019 Gross Beta pCi/m 3 2.1 +/- 0.1 2.1 +/- 0.1 **

Air Filter - A4 2/11/2019 Gross Beta pCi/m 3 2.1 +/- 0.1 2.2 +/- 0.1 **

Air Filter - A5 2/11/2019 Gross Beta pCi/m 3 2.4 +/- 0.1 2.3 +/- 0.1 **

Air Filter - SFA1 2/11/2019 Gross Beta pCi/m 3 2.2 +/- 0.1 2.2 +/- 0.1 **

Air Filter - SFA2 2/11/2019 Gross Beta pCi/m3 2.3 +/- 0.1 2.2 +/- 0.1 **

Air Filter - SFA3 2/11/2019 Gross Beta pCi/m 3 2.5 +/- 0.1 2.2 +/- 0.1 **

Air Filter - SFA4 2/11/2019 Gross Beta pCi/m 3 2.2 +/- 0.1 2.4 +/- 0.1 **

Air Iodine - A1 2/11/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A2 2/11/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A3 2/11/2019 I-131 pCi/m3 <MDA <MDA **

Air Iodine - A4 2/11/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A5 2/11/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - SFA1 2/11/2019 I-131 pCi/m 3

<MDA <MDA **

Air Filter - A1 3/4/2019 Gross Beta pCi/m 3 1.7 +/- 0.1 1.7 +/- 0.1 **

Air Filter - A2 3/4/2019 Gross Beta pCi/m3 1.8 +/- 0.1 2.0 +/- 0.1 **

Air Filter - A3 3/4/2019 Gross Beta pCi/m 3 1.6 +/- 0.1 1.7 +/- 0.1 **

Air Filter - A4 3/4/2019 Gross Beta pCi/m 3 1.6 +/- 0.1 1.8 +/- 0.1 **

Air Filter - A5 3/4/2019 Gross Beta pCi/m 3 1.8 +/- 0.1 1.9 +/- 0.1 **

Air Filter - SFA1 3/4/2019 Gross Beta pCi/m 3 1.7 +/- 0.1 1.6 +/- 0.1 **

Air Filter - SFA2 3/4/2019 Gross Beta pCi/m3 1.5 +/- 0.1 1.6 +/- 0.1 **

Air Filter - SFA3 3/4/2019 Gross Beta pCi/m 3 1.7 +/- 0.1 1.7 +/- 0.1 **

Air Filter - SFA4 3/4/2019 Gross Beta pCi/m 3 1.7 +/- 0.1 1.6 +/- 0.1 **

58

January 1 - December 31, 2019 Docket Nos. 50-244 TABLE C Continued Results of Quality Assurance Program Sample Type and Type of Original Replicate Split Sample Date Result2 Units Location Analysis Analysis Analysis Analysis Air Iodine - A1 3/4/2019 I-131 pCi/m3 <MDA <MDA **

Air Iodine - A2 3/4/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A3 3/4/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A4 3/4/2019 I-131 pCi/m3 <MDA <MDA **

Air Iodine - A5 3/4/2019 I-131 pCi/m3 <MDA <MDA **

Air Iodine - SFA1 3/4/2019 I-131 pCi/m 3

<MDA <MDA **

Air Filter - A1 4/8/2019 Gross Beta pCi/m 3 2.1 +/- 0.1 2.1 +/- 0.1 **

Air Filter - A2 4/8/2019 Gross Beta pCi/m 3 1.9 +/- 0.1 1.9 +/- 0.1 **

Air Filter - A3 4/8/2019 Gross Beta pCi/m3 2.0 +/- 0.1 2.0 +/- 0.1 **

Air Filter - A4 4/8/2019 Gross Beta pCi/m3 1.8 +/- 0.1 1.8 +/- 0.1 **

Air Filter - A5 4/8/2019 Gross Beta pCi/m 3 2.0 +/- 0.1 2.0 +/- 0.1 **

Air Filter - SFA1 4/8/2019 Gross Beta pCi/m 3 1.7 +/- 0.1 1.9 +/- 0.1 **

Air Filter - SFA2 4/8/2019 Gross Beta pCi/m 3 1.6 +/- 0.1 1.6 +/- 0.1 **

Air Filter - SFA3 4/8/2019 Gross Beta pCi/m3 1.9 +/- 0.1 1.8 +/- 0.1 **

Air Filter - SFA4 4/8/2019 Gross Beta pCi/m3 1.9 +/- 0.1 1.9 +/- 0.1 **

Air Iodine - A1 4/15/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A2 4/15/2019 I-131 pCi/m 3

<MDA <MDA **

Shoreline Sediment-4/29/2019 Gamma pCi/kg <MDA <MDA <MDA WB1 Air Filter - A1 5/7/2019 Gross Beta pCi/m3 1.2 +/- 0.1 1.1 +/- 0.1 **

Air Filter - A2 5/7/2019 Gross Beta pCi/m3 1.2 +/- 0.1 1.2 +/- 0.1 **

Air Filter - A3 5/7/2019 Gross Beta pCi/m 3 1.3 +/- 0.1 1.2 +/- 0.1 **

Air Filter - A4 5/7/2019 Gross Beta pCi/m 3 1.2 +/- 0.1 1.3 +/- 0.1 **

Air Filter - A5 5/7/2019 Gross Beta pCi/m 3 1.3 +/- 0.1 1.2 +/- 0.1 **

Air Filter - SFA1 5/7/2019 Gross Beta pCi/m 3 1.2 +/- 0.1 1.3 +/- 0.1 **

Air Filter - SFA2 5/7/2019 Gross Beta pCi/m3 1.1 +/- 0.1 1.1 +/- 0.1 **

Air Filter - SFA3 5/7/2019 Gross Beta pCi/m 3 1.2 +/- 0.1 1.1 +/- 0.1 **

Air Filter - SFA4 5/7/2019 Gross Beta pCi/m 3 1.0 +/- 0.1 1.0 +/- 0.1 **

Air Iodine - A1 6/3/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A2 6/3/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A3 6/3/2019 I-131 pCi/m3 <MDA <MDA **

Air Iodine - A4 6/3/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A5 6/3/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - SFA1 6/3/2019 I-131 pCi/m 3

<MDA <MDA **

59

January 1 - December 31, 2019 Docket Nos. 50-244 TABLE C Continued Results of Quality Assurance Program Sample Type and Type of Original Replicate Split Sample Date Result2 Units Location Analysis Analysis Analysis Analysis Air Filter - A1 6/10/2019 Gross Beta pCi/m3 1.8 +/- 0.1 1.7 +/- 0.1 **

Air Filter - A2 6/10/2019 Gross Beta pCi/m 3 1.6 +/- 0.4 0.9 +/- 0.3 **

Air Filter - A3 6/10/2019 Gross Beta pCi/m 3 1.7 +/- 0.1 1.7 +/- 0.1 **

Air Filter - A4 6/10/2019 Gross Beta pCi/m3 1.7 +/- 0.1 1.8 +/- 0.1 **

Air Filter - A5 6/10/2019 Gross Beta pCi/m3 1.8 +/- 0.1 1.7 +/- 0.1 **

Air Filter - SFA1 6/10/2019 Gross Beta pCi/m 3 1.8 +/- 0.1 1.8 +/- 0.1 **

Air Filter - SFA2 6/10/2019 Gross Beta pCi/m 3 1.6 +/- 0.1 1.6 +/- 0.1 **

Air Filter - SFA3 6/10/2019 Gross Beta pCi/m 3 1.7 +/- 0.1 1.7 +/- 0.1 **

Air Filter - SFA4 6/10/2019 Gross Beta pCi/m3 1.6 +/- 0.1 1.5 +/- 0.1 **

Soil - SFS2 6/12/2019 GAMMA pCi/kg <MDA <MDA <MDA Soil - SFS5 6/12/2019 Cs-137 pCi/kg 96.3 +/- 25.1 75.2 +/- 21.3 <MDA Oysters - IA3 6/25/2019 GAMMA pCi/kg <MDA <MDA <MDA Oysters - IA6 6/25/2019 GAMMA pCi/kg <MDA <MDA <MDA Bottom sed.-WBS21 6/25/2019 Cs-137 pCi/kg 91.4 +/- 79.2 149 +/- 72.3 341 +/- 189 Bottom sed.- WBS4 6/25/2019 Cs-137 pCi/kg 113 +/- 73.8 <MDA <MDA Air Filter - A1 7/1/2019 GAMMA pCi/m 3

<MDA <MDA <MDA Air Filter - A2 7/1/2019 GAMMA pCi/m 3

<MDA <MDA <MDA Air Filter - A3 7/1/2019 GAMMA pCi/m 3

<MDA <MDA <MDA Air Filter - A4 7/1/2019 GAMMA pCi/m3 <MDA <MDA <MDA Air Filter - A5 7/1/2019 GAMMA pCi/m3 <MDA <MDA <MDA Air Filter - SFA1 7/1/2019 GAMMA pCi/m 3

<MDA <MDA <MDA Air Filter - SFA2 7/1/2019 GAMMA pCi/m 3

<MDA <MDA <MDA Air Filter - SFA3 7/1/2019 GAMMA pCi/m 3

<MDA <MDA <MDA Air Filter - SFA4 7/1/2019 GAMMA pCi/m3 <MDA <MDA <MDA Gamma field- DR5 7/1/2019 TLD mR/Qtr 12.1 +/- 0.7 10.8 +/- 1.3 **

Gamma field- DR6 7/1/2019 TLD mR/Qtr 10.3 +/- 0.7 10.0 +/- 0.9 **

Gamma field- DR7 7/1/2019 TLD mR/Qtr 10.2 +/- 0.6 10.0 +/- 1.1 **

Gamma field- DR8 7/1/2019 TLD mR/Qtr 13.3 +/- 1.2 12.8 +/- 1.2 **

Gamma field- DR9 7/1/2019 TLD mR/Qtr 10.3 +/- 0.9 10.4 +/- 0.7 **

Gamma field- DR10 7/1/2019 TLD mR/Qtr 10.6 +/- 1.1 10.7 +/- 1.7 **

Gamma field- DR11 7/1/2019 TLD mR/Qtr 10.6 +/- 0.4 10.4 +/- 0.6 **

60

January 1 - December 31, 2019 Docket Nos. 50-244 TABLE C Continued Results of Quality Assurance Program Sample Type and Type of Original Replicate Split Sample Date Result Units Location Analysis Analysis Analysis Analysis Gamma field-7/1/2019 TLD mR/Qtr 40.9 +/- 2.8 46.4 +/- 5.1 **

SFDR14 Gamma field -

7/1/2019 TLD mR/Qtr 20.1 +/- 2.8 24.0 +/- 6.8 **

SFDR15 Gamma field -

7/1/2019 TLD mR/Qtr 14.6 +/- 1.1 13.5 +/- 1.1 **

DR23 Air Iodine - A1 7/15/2019 I-131 pCi/m3 <MDA <MDA **

Air Iodine - A2 7/15/2019 I-131 pCi/m3 <MDA <MDA **

Air Iodine - A3 7/15/2019 I-131 pCi/m 3

<MDA <MDA **

Chard - IB5 7/22/2019 Cs-137 pCi/kg 18.6 +/- 13.9 <MDA 18.2 +/- 5.6 Cabbage - IB4 7/22/2019 GAMMA pCi/kg <MDA <MDA <MDA Collards - IB10 7/22/2019 GAMMA pCi/kg <MDA <MDA <MDA Cabbage - IB12 7/22/2019 GAMMA pCi/kg <MDA <MDA <MDA Air Filter - A1 8/5/2019 Gross Beta pCi/m 3 2.7 +/- 0.2 2.4 +/- 0.2 **

Air Filter - A2 8/5/2019 Gross Beta pCi/m 3 2.8 +/- 0.2 2.6 +/- 0.2 **

Air Filter - A3 8/5/2019 Gross Beta pCi/m 3 2.6 +/- 0.2 2.6 +/- 0.2 **

Air Filter - A4 8/5/2019 Gross Beta pCi/m 3 2.5 +/- 0.2 2.5 +/- 0.2 **

Air Filter - A5 8/5/2019 Gross Beta pCi/m3 2.4 +/- 0.2 2.4 +/- 0.2 **

Air Filter - SFA1 8/5/2019 Gross Beta pCi/m 3 2.7 +/- 0.2 2.6 +/- 0.2 **

Air Filter - SFA2 8/5/2019 Gross Beta pCi/m 3 2.5 +/- 0.2 2.4 +/- 0.2 **

Air Filter - SFA3 8/5/2019 Gross Beta pCi/m 3 2.6 +/- 0.2 2.5 +/- 0.2 **

Air Filter - SFA4 8/5/2019 Gross Beta pCi/m 3 2.4 +/- 0.2 2.5 +/- 0.2 **

Air Iodine - A1 8/12/2019 I-131 pCi/m3 <MDA <MDA **

Air Iodine - A2 8/12/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A3 8/12/2019 I-131 pCi/m 3

<MDA <MDA **

Span. Mack.- IA5 8/12/2019 Gamma pCi/kg <MDA <MDA <MDA Spot - IA1 8/12/2019 Gamma pCi/kg <MDA <MDA <MDA Span. Mack.- IA2 8/12/2019 Gamma pCi/kg <MDA <MDA <MDA Air Iodine - A1 9/9/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A2 9/9/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A3 9/9/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A4 9/9/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A5 9/9/2019 I-131 pCi/m3 <MDA <MDA **

Air Iodine - SFA1 9/9/2019 I-131 pCi/m 3

<MDA <MDA **

61

January 1 - December 31, 2019 Docket Nos. 50-244 TABLE C Continued Results of Quality Assurance Program Sample Type and Type of Original Replicate Split Sample Date Result Units Location Analysis Analysis Analysis Analysis Water - WA2 9/27/2019 Gamma pCi/L <MDA <MDA <MDA Water - WA1 9/27/2019 Gamma pCi/L <MDA <MDA <MDA Air Filter - A1 10/1/2019 GAMMA pCi/m3 <MDA <MDA <MDA Air Filter - A2 10/1/2019 GAMMA pCi/m3 <MDA <MDA <MDA Air Filter - A3 10/1/2019 GAMMA pCi/m 3

<MDA <MDA <MDA Air Filter - A4 10/1/2019 GAMMA pCi/m 3

<MDA <MDA <MDA Air Filter - A5 10/1/2019 GAMMA pCi/m 3

<MDA <MDA <MDA Air Filter - SFA1 10/1/2019 GAMMA pCi/m3 <MDA <MDA <MDA Air Filter - SFA2 10/1/2019 GAMMA pCi/m3 <MDA <MDA <MDA Air Filter - SFA3 10/1/2019 GAMMA pCi/m 3

<MDA <MDA <MDA Air Filter - SFA4 10/1/2019 GAMMA pCi/m 3

<MDA <MDA <MDA Air Filter - A1 10/7/2019 Gross Beta pCi/m 3 2.0 +/- 0.1 2.1 +/- 0.2 **

Air Filter - A2 10/7/2019 Gross Beta pCi/m3 1.9 +/- 0.1 1.8 +/- 0.1 **

Air Filter - A3 10/7/2019 Gross Beta pCi/m3 2.1 +/- 0.1 2.1 +/- 0.2 **

Air Filter - A4 10/7/2019 Gross Beta pCi/m 3 2.1 +/- 0.1 2.0 +/- 0.1 **

Air Filter - A5 10/7/2019 Gross Beta pCi/m 3 2.1 +/- 0.1 2.1 +/- 0.2 **

Air Filter - SFA1 10/7/2019 Gross Beta pCi/m 3 2.2 +/- 0.2 1.9 +/- 0.1 **

Air Filter - SFA2 10/7/2019 Gross Beta pCi/m3 1.9 +/- 0.1 1.9 +/- 0.1 **

Air Filter - SFA3 10/7/2019 Gross Beta pCi/m3 2.0 +/- 0.1 2.0 +/- 0.2 **

Air Filter - SFA4 10/7/2019 Gross Beta pCi/m 3 2.0 +/- 0.1 1.8 +/- 0.1 **

Air Iodine - A1 10/7/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A2 10/7/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A3 10/7/2019 I-131 pCi/m3 <MDA <MDA **

Air Iodine - A4 10/7/2019 I-131 pCi/m3 <MDA <MDA **

Air Iodine - A5 10/7/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - SFA1 10/7/2019 I-131 pCi/m 3

<MDA <MDA **

Oysters - IA3 10/23/2019 GAMMA pCi/kg <MDA <MDA <MDA Oysters - IA6 10/23/2019 GAMMA pCi/kg <MDA <MDA <MDA 62

January 1 - December 31, 2019 Docket Nos. 50-244 TABLE C Continued Results of Quality Assurance Program Sample Type and Type of Original Replicate Split Sample Date Result Units Location Analysis Analysis Analysis Analysis Air Filter - A1 11/4/2019 Gross Beta pCi/m3 1.6 +/- 0.1 1.6 +/- 0.1 **

Air Filter - A2 11/4/2019 Gross Beta pCi/m 3 1.4 +/- 0.1 1.4 +/- 0.1 **

Air Filter - A3 11/4/2019 Gross Beta pCi/m3 1.4 +/- 0.1 1.3 +/- 0.1 **

Air Filter - A4 11/4/2019 Gross Beta pCi/m 3 1.4 +/- 0.1 1.4 +/- 0.1 **

Air Filter - A5 11/4/2019 Gross Beta pCi/m 3 1.5 +/- 0.1 1.7 +/- 0.1 **

Air Filter - SFA1 11/4/2019 Gross Beta pCi/m 3 1.5 +/- 0.1 1.5 +/- 0.1 **

Air Filter - SFA2 11/4/2019 Gross Beta pCi/m 3 1.5 +/- 0.1 1.4 +/- 0.1 **

Air Filter - SFA3 11/4/2019 Gross Beta pCi/m3 1.4 +/- 0.1 1.4 +/- 0.1 **

Air Filter - SFA4 11/4/2019 Gross Beta pCi/m 3 1.6 +/- 0.1 1.3 +/- 0.1 **

Air Iodine - A1 11/4/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A2 11/4/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A3 11/4/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A4 11/4/2019 I-131 pCi/m3 <MDA <MDA **

Air Iodine - A5 11/4/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - SFA1 11/4/2019 I-131 pCi/m 3

<MDA <MDA **

Vegetation- SFB2 11/18/2019 Gamma pCi/kg <MDA <MDA <MDA Vegetation - SFB5 11/18/2019 Cs-137 pCi/kg <MDA <MDA 19.5 +/- 8.9 Water - WA1 12/2/2019 Gamma pCi/L <MDA <MDA <MDA Water - WA2 12/2/2019 Gamma pCi/L <MDA <MDA <MDA Air Iodine - A1 12/9/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A2 12/9/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A3 12/9/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - A4 12/9/2019 I-131 pCi/m3 <MDA <MDA **

Air Iodine - A5 12/9/2019 I-131 pCi/m 3

<MDA <MDA **

Air Iodine - SFA1 12/9/2019 I-131 pCi/m 3

<MDA <MDA **

63

January 1 - December 31, 2019 Docket Nos. 50-244 TABLE C Continued Results of Quality Assurance Program Sample Type and Type of Original Replicate Split Sample Date Result Units Location Analysis Analysis Analysis Analysis Gamma field -

1/21/2020 TLD mR/Qtr 15.3 +/- 1.6 15.1 +/- 1.0 **

DR05 Gamma field -

1/21/2020 TLD mR/Qtr 13.6 +/- 0.8 13.2 +/- 0.5 **

DR06 Gamma field -

1/21/2020 TLD mR/Qtr 13.6 +/- 1.0 13.9 +/- 1.2 **

DR07 Gamma field -

1/21/2020 TLD mR/Qtr 18.2 +/- 1.0 18.2 +/- 1.8 **

DR08 Gamma field -

1/21/2020 TLD mR/Qtr 13.6 +/- 1.4 13.5 +/- 1.1 **

DR09 Gamma field -

1/21/2020 TLD mR/Qtr 13.7 +/- 0.7 14.6 +/- 3.7 **

DR10 Gamma field -

1/21/2020 TLD mR/Qtr 14.3 +/- 1.0 14.1 +/- 0.9 **

DR11 Gamma field -

1/21/2020 TLD mR/Qtr 76.1 +/- 40.2 83.0 +/- 55.5 **

SFDR14 Gamma field -

1/21/2020 TLD mR/Qtr 31.7 +/- 6.0 33.9 +/- 5.8 **

SFDR15 Gamma field -

1/21/2020 TLD mR/Qtr 21.9 +/- 2.1 20.3 +/- 1.0 **

DR23 1 See discussion at the beginning of the Appendix.

- The nature of these samples precluded splitting them with an independent laboratory.

64

January 1 - December 31, 2019 Docket Nos. 50-244 Table C-3 Teledyne Brown Engineerings Typical MDAs for Gamma Spectrometry Selected Bay Water Fish Shellfish Sediment Vegetation Particulates Nuclides pCi/l pCi/kg pCi/kg pCi/kg pCi/kg 10-3 pCi/m3 H-3 175 -- -- -- -- --

Na-22 1 8 3 12 6 5 Cr-51 12 105 4 104 50 63 Mn-54 1 9 3 12 5 4 Co-58 1 9 4 9 4 5 Fe-59 3 28 9 24 10 12 Co-60 1 9 4 12 5 6 Zn-65 2 20 8 25 10 9 Nb-95 1 12 7 14 6 9 Zr-95 2 18 8 20 9 9 Ru-106 9 75 30 90 41 40 Ag-110m 1 10 10 10 5 4 Te-129m 16 131 60 162 79 95 I-131 4 65 30 35 22 74 Cs-134 1 8 4 10 5 4 Cs-137 1 9 4 10 5 4 BaLa-140 3 32 15 25 14 36 Ce-144 7 40 16 54 26 18 65

January 1 - December 31, 2019 Docket Nos. 50-244 APPENDIX D Land Use Survey Summary of Appendix D Content:

Appendix D contains the results of a Land Use Survey conducted around R.E. Ginna Nuclear Power Plant during this operating period. A discussion of the results is included in Section 3.4 of this report.

66

January 1 - December 31, 2019 Docket Nos. 50-244 TABLE OF CONTENTS - LAND USE SURVEY Table Title Page D-1 Land Use Survey Distances..................................................................................................68 67

January 1 - December 31, 2019 Docket Nos. 50-244 TABLE D-1 Land Use Survey Distances Sector Distance to Distance to Nearest Garden Distance to Milk Producing (Direction in Nearest (Latitude N, Longitude W) Animals Degrees) Residence (Latitude N, Longitude W) 610 m E

1170 m Onsite Supplemental Garden N/A (94)

(43.27727, 77.30140) 430 m ESE 1660 m Onsite Garden N/A (111)

(43.27627, 77.30389)

ESE 8240 m 840 m N/A (119) (43.24196, 77.21978) 660 m SSE 610 m Onsite Supplemental Garden N/A (145)

(43.27278, 77.30413)

S 1500 m N/A N/A SSW 620 m N/A N/A SW 740 m N/A N/A WSW 900 m N/A N/A W 1330 m N/A N/A 68

January 1 - December 31, 2019 Docket Nos. 50-244 Discussion A Land Use Survey was conducted to identify, within five miles, 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 over land. The position of the nearest residence and garden and animals producing milk for human consumption in each sector out to five miles is given in the above Table D-1.

Changes from Previous Years:

- 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 has 25-acres of active production of AGRI-GROW tomatoes year-round at East end of Dean Parkway (North of Route 104)

- Commercial fishing information was collected from the New York State Department of Environmental Conservation (NYSDEC) which shows activity only in the Eastern basin of Lake Ontario. Commercial fishing operations have not changed in the last five-years and no commercial fishing takes place within 5-miles of Ginna.

- 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.

Milk Animal Locations

- Schultz Farm - 450 Boston Road, Ontario NY

- Field Craft Farm (supplemental sample) - 6747 Salmon Creek Road, Williamson NY

- No new milk producing animals were identified in the 2019 survey.

69

January 1 - December 31, 2019 Docket Nos. 50-244 APPENDIX E Interpretations and Graphical Representations Summary of Appendix E Content:

To better illustrate that the continued operation of the R.E. Ginna Nuclear Power Plant (Ginna) has no statistically significant impact on the surrounding environment, Appendix E contains the results of the last eight years of Radiological Environment Monitoring Program (REMP) data.

Where applicable (when analytical results produced a measured numerical value), trends have been produced to show values that have been observed in the various environs surrounding Ginna. A discussion of these results will accompany each series of trends to enhance understanding of the REMP program.

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INTERPRETATIONS AND GRAPHICAL REPRESENTATIONS Table Title Page E-1 E-Series 1, Table B-1 (Gross Beta Values for Surface and Drinking Water)....................72 E-2 E-Series 2, Table B-5 / Table B-6 (Beta in Air Particulates).76 E-3 E-Series 3, Table B-12 (Direct Radiation).81 E-4 E-Series 4, Table B-13 (Tritium in Groundwater).94 71

January 1 - December 31, 2019 Docket Nos. 50-244 E-Series 1 Table B-1 (Gross Beta Values for Surface and Drinking Water)

Ginnas Offsite Dose Calculation Manual (ODCM) is written in accordance with specifications contained within 10 CFR 20 and the Branch Technical Position document published by the NRC in 1979. This document specifies Gross Beta in Surface Water samples to be detected to a Lower Limit of Detection (LLD) of 4 pCi/l. Since that time, detection capabilities have improved which allow values to be measured lower than the required 4 pCi/l.

The trends below include the Gross Beta averages (from 2012-2019) for Ginnas surface water samples (Circ - In, Circ - Out, MCWA, Deer Creek, Mill Creek, OWD, and Webster). An elevated Gross Beta result inconsistent with the trend would indicate radionuclides in the sample which would require further analysis. From 2012 through 2019, no such results have been measured within Ginnas REMP program.

Results from Deer Creek (indicator) and Mill Creek (control) are higher than other surface water samples within the REMP program due to naturally occurring radiological daughter products within the soil being introduced into the samples. It is worth noting that these naturally occurring radiological daughter products would exist in this environ at these same levels even if Ginna had never been built. These samples are obtained to evaluate the potential for public exposure due to the surface water (Mill Creek, Circ-In, Circ-Out, and Deer Creek) and drinking water pathway (Monroe County Water Authority, Webster Water Authority, and Ontario Water District). These locations are chosen as a member of the public is most likely to encounter water which has left Ginna property via these sample streams.

Trend B-1 Control and Indicator Averages (2012-2019) shows the relationship between the control samples (Mill Creek, MCWA, and Webster Water Authority) and the indicator samples (Circ-In, Circ-Out, Deer Creek, and OWD). This trend illustrates that there is no statistically significant difference between control and indicator samples for Gross Beta in Surface water from 2012-2019.

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January 1 - December 31, 2019 Docket Nos. 50-244 E-Series 2 Table B-5 / Table B-6 (Beta in Air Particulates)

Ginnas Offsite Dose Calculation Manual (ODCM) is written in accordance with specifications contained within 10 CFR 20 and the Branch Technical Position document published by the NRC in 1979. This document specifies Gross Beta in Air Particulate samples to be detected to a Lower Limit of Detection (LLD) of 1.0 X 10-2 pCi/m3. Accordingly, analyses performed as part of the REMP at Ginna satisfy this requirement.

The trends below include the Gross Beta averages (from 2012-2019) for Ginnas air particulate samples (Station-02 through Station-13). An elevated Gross Beta result inconsistent with the trend would indicate radionuclides in the sample which would require further analysis. From 2012 through 2019, no such results have been measured within Ginnas REMP program.

Sampling locations (Station-02 through Station-13) are noted below, and their classification as either a control or an indicator. These locations were selected to show areas where breathable air, which has the potential to be in communication with air released from Ginna, could lead to public exposure. Some locations (such as Station-08, Seabreeze and Station-12, Sodus Point) are sampled due to recreational activities in the area and their associated sensitivity.

Station Manor House Yard, Ginna Property (Indicator)

Station North of Training Center Parking Lot, Ginna Property (Indicator)

Station East of Training Center Parking Lot, Ginna Property (Indicator)

Station Bridge Near Deer Creek, Ginna Property (Indicator)

Station Southwest of Plant Parking Lot, Ginna Property (Indicator)

Station Utility Pole West of Parking Lot, Ginna Property (Indicator)

Station Seabreeze (Control)

Station Webster (Indicator)

Station Walworth (Control)

Station Williamson (Indicator)

Station Sodus Point (Control)

Station Substation 13 (Indicator)

Trend B-5 / B-6 Control and Indicator Averages (2012 - 2019) shows the relationship between the control samples (Station-08, Station-10, and Station-12) and the indicator samples (Station-02, Station-03, Station-04, Station-05, Station-06, Station-07, Station-09, and Station-11). This trend illustrates that there is no statistically significant difference between control and indicator samples for Gross Beta in Air Particulates from 2012-2019.

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January 1 - December 31, 2019 Docket Nos. 50-244 E-Series 3 Table B-12 (Direct Radiation)

In 2019, Ginna adopted Exelon procedure CY-AA-170-1001, Environmental Dosimetry Performance Specifications, Testing, and Data Analysis, which included new methodology for determining dose attributable to facility operations. As part of this methodology, the direct radiation dose to the general public is now determined in accordance with the Environmental Protection Agency (EPA) guidance 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operations. This methodology incorporates the concepts established in ANSI/HPS N13.37, Environmental Dosimetry as established in NRC Regulatory Guide 4.13, Environmental Dosimetry - Performance, Specifications, Testing, and Data Analysis.

The values below have been maintained and include the average quarterly exposure (in millirem) for Ginnas direct radiation monitoring locations. This quarterly average is averaged for the year to facilitate trending.

Direct radiation is the measurement that a member of the public would experience due to being near a source of radioactivity, such as a nuclear power plant in addition to natural sources. These natural sources are present throughout the environment (examples include being near bedrock rich in granite, being in the presence of the sun, radon gas emerging from layers of earth, etc.)

and the direct radiation measurement Ginna collects is to determine if there is any statistically significant additional exposure from the operations of the nuclear facility.

Trend B-12 Control and Indicator Averages (2012-2019) shows the relationship between the control samples (TL-08, TL-10, TL-12, TL TL-30) and the indicator samples (TL TL 07, TL-11, TL TL-24, TL TL-40, TL-63, and TL-64). This trend illustrates that there is no statistically significant difference between control and indicator samples for direct radiation exposure in millirem from 2012-2019.

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January 1 - December 31, 2019 Docket Nos. 50-244 E-Series 4 Table B-13 (Tritium in Groundwater)

Ginnas Offsite Dose Calculation Manual (ODCM) is written in accordance with specifications contained within 10 CFR 20 and the Branch Technical Position document published by the NRC in 1979. This document specifies Tritium and Gamma in Groundwater samples to be detected to a Lower Limit of Detection (LLD) of 2,000 pCi/l. Since that time, detection capabilities have improved which allow values to be measured lower than the required 2,000 pCi/l and Ginna measures tritium concentration down to an LLD of 500 pCi/l and certain vendor laboratories down to an LLD of 200 pCi/l.

The trends below include the tritium averages (from 2012-2019) for Ginnas groundwater samples (GW01, GW03 - GW08, GW GW16). A tritium value of greater than 20,000 pCi/l (20,000 pCi/l value from Environmental Protection Agency EPA standards) would indicate radionuclides in the sample which would require further analysis and offsite reporting. From 2012 through 2019, no such results have been received from Ginnas REMP program.

Tritium (H-3) is a radioactive form of Hydrogen and, when detected in the environment at high-levels (greater than 2,000 pCi/l, can be an indication that plant effluents may have been introduced into the environment. Tritium is sampled for at nuclear facilities due to its exposure capabilities for members of the public. Essentially, Tritium, when in an aqueous form, flows like water and can be found in surface water, groundwater, and atmospheric environs due to evaporative processes found in nature. Nuclear stations place a sensitivity on detecting Tritium in the environment as it is an efficient marker to show if radioactivity has been introduced off-site.

All results shown below are less-than values (< LLD) excluding the sample result for groundwater monitoring well GW04 from 1/30/2013 (2,520 pCi/l). This value was the result of atmospheric recapture of gaseous tritium which accumulated in snow located around the facility.

As this snow melted during this sampling period, this recaptured tritium was introduced into the groundwater and captured via our groundwater sampling program. This value of 2,520 pCi/l is roughly 8-times lower than the reportable limit of 20,000 pCi/l. This recapture phenomenon was also experienced for the GW10 sample collected on 12/13/2019 (result of 603 pCi/L).

Additionally, groundwater monitoring well GW14 on 3/11/2014 was counted to an LLD of 2,000 pCi/l rather than the LLD of 500 pCi/l. Actual result was a less than value of < 1,950 pCi/l.

Subsequent samples were collected to ensure there was no detectable tritium in the environment and these samples returned values of less than 500 pCi/l.

Ginna groundwater monitoring well GW01 (West of the station) is the control location for sampling and due to the sampling frequencies of this program, it is difficult to graphically compare the control samples against the indicator samples. Since 2012, the average tritium concentration in control samples was < 451 pCi/l whereas the average tritium concentration in indicator samples (Groundwater Monitoring Well GW GW08, GW10-GW16) was < 454 pCi/l. This result demonstrates that there is no statistically significant difference between control and indicator samples for Ginnas groundwater samples for the REMP.

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ML20136A439

Text

Subject:

1.0 INTRODUCTION

SUMMARY

SUMMARY

10.0 REFERENCES

4.1.1 CONTROLS

4.1.2 APPLICABILITY

4.1.3 ACTION

4.1.4 ACTION

4.1.6 BASES

4.2.1 CONTROLS

4.2.2 APPLICABILITY

4.2.3 ACTION

4.2.4 ACTION

4.2.6 BASES

4.3.1 CONTROLS

4.3.2 APPLICABILITY

4.3.3 ACTION

4.3.5 BASES

5.2.2 APPLICABILITY

5.2.3 ACTION

5.2.5 BASES

5.3.1 CONTROLS

5.3.2 APPLICABILITY

5.3.3 ACTION

5.3.4 ACTION

5.3.6 BASES

5.3.7 CONTROLS

5.3.8 APPLICABILITY

5.3.9 ACTION

5.4.1 CONTROLS

5.4.2 APPLICABILITY

5.4.3 ACTION

5.4.4 ACTION

5.4.6 BASES

6.1.2 APPLICABILITY

6.1.3 ACTION

6.1.4 ACTION

6.2.2 APPLICABILITY

6.2.3 ACTION

6.2.4 ACTION

6.3.1 CONTROLS

6.3.2 APPLICABILITY

6.3.4 ACTION

6.3.6 BASES

7.1.1 CONTROLS

7.1.2 APPLICABILITY

7.1.3 ACTION

7.1.5 BASES

7.2.2 APPLICABILITY

7.2.3 ACTION

7.2.5 BASES

7.3.1 CONTROLS

7.3.2 APPLICABILITY

7.3.3 ACTION

7.4.1 CONTROLS

7.4.2 APPLICABILITY

7.4.2 ACTION

8.1.1 CONTROLS

8.1.2 APPLICABILITY

8.1.3 ACTION

8.1.5 BASES

8.3.2 APPLICABILITY

8.3.3 ACTION

8.3.5 BASES

8.4.2 APPLICABILITY

8.4.3 ACTION

8.4.5 BASES

10.0 REFERENCES

SUMMARY

SUMMARY

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