ML18137A213

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and Independent Spent Fuel Storage Installation - Submittal of 2017 Annual Radioactive Effluent Release Report and 2017 Annual Radiological Environmental Operating Report
ML18137A213
Person / Time
Site: Ginna  Constellation icon.png
Issue date: 05/11/2018
From: Carsky W
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
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Download: ML18137A213 (36)
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Text

William Carsky Site Vice President R.E. Ginna Nuclear Power Plant 1503 Lake Rd.

Ontario, NY 14519 Exelon Generation 315-791-5200 Office www.exeloncorp.com William.carsky@exeloncorp.com May 11, 2018 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 NRG Docket No. 50-244 Independent Spent Fuel Storage Installation (ISFSI)

NRG Docket No. 72-67

Subject:

2017 Annual Radioactive Effluent Release Report and 2017 Annual Radiological Environmental Operating Report Enclosed is the Annual Radioactive Effluent Release Report (ARERR) for 2017 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. Also enclosed is the Annual Radiological Environmental Operating Report (AREOR) for 2017, submitted in

Three (3) revisions to the Offsite Dose Calculation Manual (ODCM) and one (1) revision to the Process Control Program (PCP) occurred during the 2017 reporting period. In the ARERR, the ODCM revisions are described in Section 10.0 and the PCP revisions are described in Section 11.0. A complete, legible copy of the entire ODCM annotated with all changes for the period of the report is also submitted, as required by TS 5.5.1.c.

There are no regulatory commitments contained in this submittal. Should you have any other questions regarding this submittal, please contact Kyle Garnish at 315-791-5321.

May 11, 2017 U.S. Nuclear Regulatory Commission Page 2 Attachments:

1) Annual Radioactive Effluent Release Report, January 1, 2017 - December 31, 2017
2) Annual Radiological Environmental Operating Report, January 1, 2017 -

December 31, 2017

3) Annotated copy of the latest revision (33) of the ODCM in the reporting period cc: NRC Regional Administrator, Region I NRC Project Manager, Ginna NRC Senior Resident Inspector, Ginna NYS Office of Emergency Management Division of Homeland Security and Emergency Services 1220 Washington Avenue Building 22, Suite 101 Albany, NY 12226-2251 Attn.: Ted Fisch NYS Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223 Attn.: Bridget Frymire American Nuclear Insurers 95 Glastonbury Blvd.

Glastonbury, CT 06033 Attn.: Edward Everett NYS Division of Homeland Security and Emergency Services Attn: Radiological Preparedness Department 1220 Washington Avenue Building 7A Suite 71 O Albany, NY 12242 Tim Kohlmeier, Office of Emergency Management Monroe County Office of Emergency Management 1190 Scottsville Rd., Suite 200 Rochester, NY 14624 George Bastedo, Director, Office of Disaster Preparedness Wayne County Emergency Management 7376 Rt. 31, Suite 2000 Lyons, NY 14489-9174

ATTACHMENT 1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2017- DECEMBER 31, 2017 R.E. Ginna Nuclear Power Plant, LLC L_.

ATTACHMENT 2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1, 2017 - DECEMBER 31, 2017 R.E. Ginna Nuclear Power Plant, LLC

ATTACHMENT 3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Annotated copy of ODCM Revision 33 R.E. Ginna Nuclear Power Plant, LLC L

~ Exelon Generation ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT:

JANUARY 1, 2017 - DECEMBER 31, 2017 MAY 2018 111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111111 R.E. Ginna Nuclear Power Plant 1503 Lake Road Ontario, New York 14519

TABLE OF CONTENTS 1.0 Introduction ......................................................................................................... 1 2.0 Supplemental Information .................................................................................. 1 2.1 Regulatory Limits ....................................................................................... 1 2.2 Effluent Concentration Limits ..................................................................... 2 2.3 Release Rate Limits Based on Average Nuclide Energy ........................... 3 2.4 Measurements and Approximations of Total Radioactivity ........................ 3 2.5 Batch Releases .......................................................................................... 3 2.6 Abnormal Releases ................................................................................... 4 3.0 Summary of Gaseous Radioactive Effluents ................................................... 4 4.0 Summary of Liquid Radioactive Effluents ........................................................ 4 5.0 Solid Waste ......................................................................................................... 4 6.0 Lower Limit of Detection .................................................................................... 5 7.0 Radiological Impact ............................................................................................ 5 7.1 Total Dose ................................................................................................. 5 8.0 Meteorological Data ........................................................................................... 6 9.0 Land Use Cen_sus 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 ISFSI ...................................................................................................8 17.0 Offsite Dose Due to Carbon-14 .......................................................................... 8 17.1 Gaseous Effluents ..................................................................................... 9 17.2 Liquid Effluents .............. ~ ................ ~ ........................................... 1O R.E. Ginna Nuclear Power Plant ARERR Docket No. 50-244 01/01/2017-12/31/2017

LIST OF TABLES Table 1A Gaseous Effluents - Summation of all Releases ........................................... 11 Table 1B Gaseous Effluents - Continuous and Batch Releases .................................. 12 Table 2A Liquid Effluents - Summation of all Releases ................................................ 14 Table 28 Liquid Effluents - Continuous and Batch Releases ....................................... 15 Table 3 Solid Waste and Irradiated Fuel Shipments .................................................. 17 Table 4A Radiation Dose to Maximum Receptor from Gaseous Effluents ................... 20 Table 48 Radiation Dose to Maximum .Receptor from Liquid Effluents ........................ 24 Table 5 Groundwater Monitoring Wells ...................................................................... 25 Table 6 Offsite Dose Due to Carbon-14 in Gaseous and Liquid Effluents .................. 28 Appendix A, Annual Report on the Meteorological Monitoring Program at the Ginna Nuclear Power Plant. .................. ; ..........................................................29 Appendix B, RE Ginna Nuclear Power Plant Offsite Dose Calculation Manual, Revision 33 ..................................................................................................78 .

R.E. Ginna Nuclear Power Plant ii ARERR Docket No. 50-244 01/01/2017-12/31/2017

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, 2017 through December 31, 2017, provides a summary of the quantities of radioactive gaseous and liquid effluents and solid waste released from the plant presented in the format outlined in Appendix B of Regulatory Guide 1.21, Revision 1, June 1974.

All gaseous and liquid effluents discharged during this reporting period were in compliance with the limits of the Ginna Technical Specifications as defined in the Offsite Dose Calculation Manual (ODCM).

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 radia~ion 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 radioiodines, radioactive materials in particulate form, and radionuclides other than noble R.E. Ginna Nuclear Power Plant 1 ARERR Docket No. 50-244 01/01/2017-12/31/2017

gases with half-lives greater than eight days shall be limited to a release rate that would yield .'.5 1500 mrem/yr to any organ if allowed to continue for a full year.

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 .'.5 7.5 mrem to any organ.

(ii) During any calendar year to .'.5 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 8, 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 .'.5 1.5 mrem to the total body and to .'.5 5 mrem to any organ, and (ii) During any calendar year to .'.5 3 mrem to the total body and to .'.5 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 8, 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 01/01/2017-12/31/2017

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 2017 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 analysis were performed using liquid scintillation and gas flow proportional counting respectively.

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

2.5 Batch Releases 2.5.1 Liquid

1. Number of batch releases: 1.75 E+02
2. Total time period for batch releases (Minutes): 2.68 E+04
3. Maximum time period for a batch release (Minutes): 5.40 E+02
4. Average time period for batch releases (Minutes): 1.53 E+02
5. Minimum time period for a batch release: 1.00 E+01
6. Average effluent release flowrate into the discharge canal 2.92 E+02 (Liters per Minute):
7. Average dilution flowrate of discharge canal during effluent 1.18 E+06 releases (Liters per Minute):

R.E. Ginna Nuclear Power Plant 3 ARERR Docket No. 50-244 01/01/2017-12/31/2017

2.5.2 Gaseous

1. Number of batch releases: 2.90 E+01
2. Total time period for batch releases (Minutes): 5.03 E+05
3. Maximum time period for a batch release (Minutes): 4.46 E+04
4. AveraQe time period for batch releases (Minutes): 1.73 E+04
5. Minimum time period for a batch release (Minutes): 5.80 E+01 2.6
  • Abnormal Releases One abnormal gas release occurred in 2017: A small volume of gas from a CVCS holdup tank was released as a non-routine gas release under permit G-2018056. The offsite dose consequence was small relative to total releases for the month.

Two abnormal liquid releases occurred in 2017. During maintenance on the Retention Tank on April 26, 2017 two releases of liquid waste were made from the above ground backup retention tank, described as non-routine Batch Liquid permits L-2017100 and L-2017102.

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 28.

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 is processed utilizing an off-site processor that reduces the volume and then transports the waste to a permitted R.E. Ginna Nuclear Power Plant 4 ARERR Docket No. 50-244 01/01/2017-12/31/2017

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 2017.

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 48. Population doses are inferred from the population density, distance from the plant, and drinking water sourc~.

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

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

Using the maximum exposure and uptake pathways, the maximum liquid pathways, including C-14 dose, and the maximum direct radiation measurements at the site boundary, yield the following dose summaries to the hypothetical maximally exposed individual member of the public. The maximum total body

  • dose is determined by summing the hypothetical maximum direct radiation dose exposure and the total body dose from gaseous and liquid pathways.* Dose to any real member of the public should be conservatively bounded by these calculated doses:
  • Maximum Annual Total Body Dose: 13.1 mRem (Sum of 13.1 mrem direction radiation, 8.1 BE-03 (Total Body Liquid Dose), 2.16E-03 (Total Body Gas Dose).

R.E. Ginna Nuclear Power Plant 5 ARERR Docket No. 50-244 01/01/2017-12/31/2017

  • Maximum Annual Organ Dose: 2.32E-02 mrem (Child
  • Maximum Annual Thyroid Dose: 9.95E-03 mrem (Adult) 8.0 METEOROLOGICAL DATA The annual summary report of meteorological data collected during 2017 is included with this report, as Appendix A, Annual Report on the Meteorological Monitoring Program at the Ginna Nuclear Power Plant by Murray and Trettle, Incorporated.

9.0 . LAND USE CENSUS CHANGES In September 2017, 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 50 square meters in each of the nine sectors within a 5-mile radius of the power plant. The Land Use Survey is conducted in accordance with Ginna procedures.

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 / housing subdivision construction was observed near the plant on Ridge Road (Union Hill, Ontario), northeast corner of Lake Road and Slocum Road, and Lakeside Road.
  • New apartment complex construction observed north of Ridge Road in Ontario. *
  • Other single-family home construction was observed sporadically within S-miles of the plant.
  • A new 120-acre commercial hydroponic farm began construction on the east-end of Timothy Lane (North of Route 104).
  • A new 22-acre solar farm is located north of Route 104 (Dean Parkway, Ontario).
  • No new agricultural land use was identified.
  • No new food producing facilities were identified.
  • No new milk producing animals were identified. Eaton Farm (supplemental sample) changed names/ owner to Field Craft Farms. Their location remains unchanged.

R.E. Ginna Nuclear Power Plant 6 ARERR Docket No. 50-244 01/01/2017-12/31/2017

10.0 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL There were three changes to the Offsite Dose Calculation Manual (ODCM) in 2017.

  • Revision 31, implemented March 30, 2017, was a change to fleet procedure format with inclusion of a six year frequency for Containment Vent flow rate test.

This revision had no adverse impact on radiological controls as verified in PORC 17-0004.

  • Revision 32, implemented May 4, 2017, removed a shutdown recommendation for R-47 out of service that is controlled in Operations procedure AP-SG.1, and not required in an ODCM. This revision had no adverse impact on radiological controls as verified in PORC 17-0009.
  • Revision 33, implemented December 29, 2017, updated effluent ventilation flows to the bounding flows in ECP-16-000033. This revision had no adverse impact on radiological controls as verified in PORC 17-0004 Revision 33 of the ODCM is included with this report as Appendix B.

11.0 CHANGES TO THE PROCESS CONTROL PROGRAM There was one change to the Process Control Program on 8/23/17 as follows:

  • Former in-plant systems GE or Stock Drum Transfer Cart and Drum Storage Areas may be USED for higher dose DAW storage at Clinton, Dresden, Quad Cities, Braidwood, Byron and Nine Mile Point, and James A. Fitzpatrick Nuclear Power Plant was included in the Exelon fleet.

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

13.0 INOPERABLE MONITORS There were one occurrence in 2017 satisfying the requirement stated in Section 6.3 and Table 6.3-1, Action 1 of the ODCM for reporting inoperable radiation monitors.

R-48 was declared out of service @ 1757 on 1/6/17 due to an unexplained spike. R-48 was repaired and returned to service@ 1422 on 1/20/17. Cause was water in detector.

Detector was replaced with a moisture sealed detector.

R.E. Ginna Nuclear Power Plant 7 ARERR Docket No. 50-244 01/01/2017-12/31/2017

14.0 CHANGES TO PREVIOUS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTS None 15.0 GROUNDWATER MONITORING In accordance Ginna's Chemistry procedures, environmental groundwater monitoring wells are sampled on a routine frequency. In 2017, 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
  • 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
  • GW 16: 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 2017 are presented in Table 5.

All samples collected during 2017, which were analyzed for tritium and gamma emitting nuclides, did not yield a concentration greater than the calculated MDA.

16.0 OFFSITE DOSE DUE TO ISFSI A review of direct radiation between the Ginna ISFSI facility and the nearest residents was conducted. Environmental TLD station 64 is the highest direct radiation dose offsite and is the basis for the maximum direct radiation dose reported in 7.1 A review of TLD stations 14, 15, 16 since fuel was first stored in ISFSI in 2010 indicate no change in offsite direct radiation dose as measured by TLDs.

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

R.E. Ginna Nuclear Power Plant 8 ARERR Docket No. 50-244 01/01/2017-12/31/2017

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 2017. 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.

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

a. 6.8 Curies of C-14 were released to atmosphere in 2017.
b. There was a refueling outage in 2017. 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/m 3 .
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 2017.

R.E. Ginna Nuclear Power Plant 9 ARERR Docket No. 50-244 01/01/2017-12/31/2017

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

a. The liquid waste processing system at Ginna has not been evaluated for efficiency of removal of Carbon-14. Therefore no removal term was used in estimation of offsite dose. * *
b. Average concentration of C-14 in waste water as measured in the Kunz study was adjusted for current operating conditions and was 6.0E-07 uCi/cc.
c. 1.92E+06 liters of liquid waste (with the potential to*contain C-14) were released with a total dilution flow of 1.88E+ 12 liters.
d. Average diluted concentration of C-14 released was 6.13E-13 uCi/cc.
e. Liquid effluent dilution factor for potable water pathway is 200.
f. Liquid effluent dilution factor for fish pathway is 1.
g. Dose calculations and dose factors are from Regulatory Guide 1.109 methodology.
h. The critical receptor is a child for the fish consumption pathway and the child is the critical receptor for the potable water pathway.

See Table 6 for an estimate of Carbon-14 in liquid effluents during 2017.

R.E. Ginna Nuclear Power Plant 10 ARERR Docket No. 50-244 01/01/2017-12/31/2017

TABLE lA EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 2017 Effluent Type Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Est. Total Error,%

A. Fission & Activation Gases

1. Total release Ci 1.43E-01 2.85E+OO 3.29E-01 2.07E-01 2.80E+01
2. Average release rate for period uCi/sec 1.82E-02 3.61E-01 4.17E-02 2.63E-02
3. Percent of technical specification limit  % 2.89E-06 5.73E-05 6.62E-06 4.17E-06 B. Iodines
1. Total iodine-131 Ci 5.42E-07 2.43E-05 9.09E-09 6.91E-07 2.20E+01
2. Average release rate for period uCi/sec 6.88E-08 3.08E-06 1.26E-09 8.76E-08
3. Percent of technical specification limit  % 1.SOE-04 6.70E-03 2.74E-06 1.90E-04 C. Particulates
1. Particulates with half-lives> 8days Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO N/A
2. Average release rate for period uCi/sec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
3. Percent of technical specification limit  % O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
4. Gross alpha radioactivity Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Tritium
1. Total release Ci 2.03E+01 1.47E+01 2.52E+01 1.99E+01 1.SOE+Ol
2. Average release rate for period uCi/sec 2.58E+OO 1.87E+OO 3.20E+OO 2.53E+OO
3. Percent of technical specification limit  % 3.02E-06 2.19E-06 3.74E-06 2.96E-06 Notes: Isotopes for which no value is given were not identified in applicable releases.

R.E. Ginna Nuclear Power Plant 11 ARERR Docket No. 50-244 01/01/2017-12/31/2017

TABLE1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - CONTINUOUS AND BATCH RELEASES 2017 Nuclides Units Continuous Mode Batch Mode Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter

1. Fission Gases Argon-41 Ci 3.12E-01 3.92E-02 4.41E-02 8.36E-02 8.19E-02 Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-131m Ci Xenon-133 Ci 8.76E-01 3.24E-02 1.33E-01 8.08E-02 2.17E-02 Xenon-133m Ci Xenon-135 Ci 5.75E-02 8.72E-04 Xenon-135m Ci Xenon-138 Ci Total for period Ci 1.25E+OO 7.16E-02 1.78E-01 1.64E-01 1.04E-01
  • 2 .. Iodines 4.39E-06 2.71E-07 7.77E-06 4.95E-09 3.45E-07 lodine-131 Ci lodine-132 Ci lodine-133 Ci 5.33E-08 1.42E-06 7.44E-06 2.59E-09 1.72E-06 lodine-135 Ci 8.SOE-07 Total for period Ci 4.44E-06 1.92E-08 1.61E-05 7.54E-09 2.07E-06 R.E. Ginna Nuclear Power Plant 12 ARERR Docket No. 50-244 01/01/2017-12/31/2017

TABLE 18 (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - CONTINUOUS AND BATCH RELEASES 2017 Nuclides Units Continuous Mode Batch Mode Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter

3. Particulates stro nti u m-89 Ci strontium-90 Ci cesium-137 Ci cobalt-57 Ci cobalt-58 Ci cobalt-60 Ci Unidentified Ci Total for period Ci
4. Tritium Hydrogen-3 Ci 1.01E+01 7.31E+OO 1.2SE+01 9.78E+OO 1.81E-02 3.SOE-02 1.04E-01 1.81E-01 Note: Isotopes for which no value is given were not identified in applicable releases.

'i R.E. Ginna Nuclear Power Plant 13 ARERR Docket No. 50-244 01/01/2017-12/31/2017

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 2017 Effluent Type Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Est. Total Error, %

A. Fission & Activation Products

1. Total Release (not including tritium, gases, Ci O.OOE+OO 5.87E-03 7.74E-05 O.OOE+OO 2.80E+01 alpha)
2. Average Diluted concentration uCi/ml O.OOE+OO 1.39E-11 1.SlE-13 O.OOE+OO
3. Percent of applicable limit  % O.OOE+OO 1.39E-04 1.SlE-06 O.OOE+OO B. Tritium
1. Total Release Ci 3.22E+02 1.53E+02 1.63E+01 5.09E+01 9.20E+OO
2. Average Diluted Concentration uCi/ml 7.17E-07 3.62E-07 3.17E-08 1.03E-07
3. Percent of applicable limit  % 7.17E-03 3.62E-03 3.17E-04 1.03E-03 C. Dissolved and Entrained Gases
1. Total Release Ci 2.22E-03 2.29E-04 O.OOE+OO O.OOE+OO 2.80E+01
2. Average Diluted Concentration uCi/ml 4.89E-12 5.43E-13 O.OOE+OO O.OOE+OO
3. Percent of applicable limit  % 2.45E-06 2.72E-07 O.OOE+OO O.OOE+OO D. Gross Alpha Radioactivity
1. Total release Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO E. Vol. of Waste Released (prior to dilution) Liters 1.33E+08 1.20E+08 1.32E+08 1.24E+08 F. Vol. of Dilution Water Used During Period Liters 4.53E+11 4.22E+11 5.13E+11 4.92E+11 Note: Isotopes for which no value is given were not identified in applicable releases.

R.E. Ginna Nuclear Power Plant 14 ARERR Docket No. 50-244 01/01/2017-12/31/2017

TABLE 28 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - CONTINUOUS AND BATCH RELEASES 2017 Nuclides Released Units Continuous Mode Batch Mode 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission & Activation Products Chromium-51 Ci Manganese-54 Ci lron-55 Ci lron-59 Ci Cobalt-57 Ci Cobalt-58 Ci 5.08E-03 7.44E-05 Cobalt-60 Ci Zinc-65 Ci Stro nti u m-89 Ci Strontium-90 Ci Niobium-95 Ci Molybdenum-99 Ci Zirconium-95 Ci Silver-110m Ci Antimony-122 Ci Tellurium-123m Ci 7.88E-04 Antimony-124 Ci Antimony-125 Ci lodine-131 Ci lodiile-132 Ci Tellurium-132 Ci 6.00E-06

!odine-135 Ci Cesium-134 Ci Cesium-136 Ci Cesium-137 Ci 2.lSE-07 R.E. Ginna Nuclear Power Plant 15 ARERR Docket No. 50-244 01/01/2017 - 12/31/2017

TABLE 28 (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLl:,IENTS - CONTINUOUS AND BATCH RELEASES 2017 Nuclides Released Units Continuous Mode Batch Mode 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Barium/Lanthanum-140 Ci Cerium-141 Ci Total (above) Ci 5.87E-03 7.44E-05 Unidentified (from total Ci above)

Tritium Hydrogen-3 Ci 2.22E-02 1.37E-02 O.OOE+OO 6.62E-02 3.22E+02 1.53E+02 1.63E+Ol 5.08E+Ol Dissolved And Entrained Gases Xenon-133 Ci 2.22E-03 2.29E-04 Xenon-135 Ci Note: Isotopes for which no value is given were not identified in applicable releases.

R.E. Ginna Nuclear Power Plant 16 ARERR Docket No. 50-244 01/01/2017 -12/31/2017

TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 2017 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 m3 7.87E+OO 2.SE+Ol Bottoms, Etc. Ci 8.SOE+Ol 2.SE+Ol B - Dry Active Waste (DAW), Contaminated m3 2.70E+02 2.SE+Ol Equipment, Etc. Ci 1.64E-01 2.SE+Ol m3 C - Irradiated Components, Control Rods, Etc. None N/A Ci m3 2.83E+OO 2.SE+Ol D - Other: Sources, Filters Ci 5.74E+OO 2.SE+Ol Note: Estimated total e*rror for solid waste shipped offsite not available.

R.E. Ginna Nuclear Power Plant 17 ARERR Docket No. 50-244 01/0l/2017-12/31/2017

TABLE 3 {Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 2017

2. Estimate of Major Nuclide Composition By Type of Waste Isotope Unit Class A Class B TypeC Type D Co-58  % 2.53 Co-60  % 26.45 Cr-51  % 0.3 Cs-137  % 3.51 Fe-55  % 22.70 Mn-54  % 5.12 Nb-95  % 0.97 Ni-63  % 30.96 Sb-125  % 1.16 Zr-95  % 0.46 Cs-134  % 0.29 Zn-65  % 0.18 H-3  % 2.21 C-14  % 1.87 Total  % 98.7 Note: Blank cells indicate nuclide composition not at significant levels.

R.E. Ginna Nuclear Power Plant 18 ARERR Docket No. 50-244 01/01/2017- 12/31/2017

TABLE 3 (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 2017 Mode of Type of Container Solidification

  1. of Shipments Processing Destination Transportation Agent 4 Sole Use Truck Metal Containers None Energy Solutions, BC Energy Solutions, 1 Sole Use Truck Metal Containers None (Bulk Waste Facility)

Energy Solutions, 2 Sole Use Truck High Integrity Containers (HICs) None (Bulk Waste Facility) 2 Sole Use Truck High Integrity Containers (HICs) None ALARON Corporation B. IRRADIATED FUEL SHIPMENTS (Disposition)

Mode of

  1. of Shipments Destination Transportation None N/A N/A R.E. Ginna Nuclear Power Plant 19 ARERR Docket No. 50-244 01/01/2017-12/31/2017
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