ML15146A170

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Annual Radioactive Effluent Release Report, January 1, 2014 - December 31, 2014
ML15146A170
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/14/2015
From: Harding T
Exelon Generation Co, Ginna
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Document Control Desk, Office of Nuclear Reactor Regulation
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ATTACHMENT 1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2014 - DECEMBER 31, 2014

Am" ExeLon Generation.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT:

JANUARY 1, 2014- DECEMBER 31, 2014 MAY 2015 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 R egulatory Lim its .................................................................................. 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 R eleases ..................................................................................... 3 2.6 A bnorm al Releases .............................................................................. 4 3.0 Summary of Gaseous Radioactive Effluents ............................................... 4 4.0 Summary of Liquid Radioactive Effluents .................................................... 4 5.0 Solid Waste .................................................................................................... 5 6.0 Lower Limit of Detection ................................................................................. 5 7.0 Radiological Impact ....................................................................................... 5 7 .1 T ota l D ose ........................................................................................... .. 5 8.0 Meteorological Data ....................................................................................... 6 9.0 Land Use Census Changes ............................................................................ 6 10.0 Changes to the Offsite Dose Calculation Manual ........................................ 7 11.0 Changes to the Process Control Program ................................................... 7 12.0 Major Changes to Radwaste Treatment Systems ......................................... 7 13.0 Inoperable Monitors ....................................................................................... 7 14.0 Changes to Previous Annual Radioactive Effluent Release Reports ...... 7 15.0 Groundwater Monitoring ................................................................................. 8 16.0 Offsite Dose Due to Carbon-14 ...................................................................... 8 16.1 G aseous Effluents ................................................................................ 9 16.2 Liquid Effluents .................................................................................... 9 R.E. Ginna Nuclear Power Plant i ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

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 2B 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 4B Radiation Dose to Maximum Receptor from Liquid Effluents .................... 24 Table 5 G roundwater Monitoring W ells ................................................................. 25 Table 6 Offsite Dose Due to Carbon-14 in Gaseous and Liquid Effluents .............. 28 R.E. Ginna Nuclear Power Plant Hi ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

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, 2014 through December 31, 2014, 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 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 radioiodines, 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 R.E. Ginna Nuclear Power Plant 1 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

that would yield < 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 < 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 1 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 01/01/2014 - 12/31/2014

2.3 Release Rate Limits Based on Averaae Nuclide Enerav 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 2014 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: 1.19E+02
2. Total time period for batch releases (Minutes): 1.90 E+04
3. Maximum time period for a batch release (Minutes): 1.44 E+03
4. Average time period for batch releases (Minutes): 1.60 E+02
5. Minimum time period for a batch release: 3.00 E+01
6. Average effluent release flowrate into the discharge canal 2.92 E+02 (Liters per Minute): 2.92_E+02
7. Average dilution flowrate of discharge canal during effluent 1.13 E+06 releases (Liters per Minute):

R.E. Ginna Nuclear Power Plant 3 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

2.5.2 Gaseous

1. Number of batch releases: 2.0 E+01
2. Total time period for batch releases (Minutes): 4.93 E+05
3. Maximum time period for a batch release (Minutes): 4.46 E+04
4. Average time period for batch releases (Minutes): 2.47 E+04
5. Minimum time period for a batch release (Minutes): 8.5 E+01 2.6 Abnormal Releases Two abnormal releases occurred in 2014.
1. Just prior to the 2014 refueling outage on 4/27/14, a leak on the Volume Control Tank (VCT) nitrogen regulator released noble gas to the Plant Vent during VCT purges. The increased noble gas activity was detected on Plant Vent Gas monitor R-14 and a grab sample was taken to quantify the release. Non-routine batch gas release permit G-2014016 was generated to calculate the dose consequence of approximately 64 mci of Xe-1 35 released.
2. During 2014 refueling outage the VCT was drained to the Waste Holdup Tank (WHT) on 4/30/14. During this evolution approximately 77 mCi of Xe-133 was released through the plant vent and documented in non-routine batch gas release permit G-2014018.

3.0

SUMMARY

OF GASEOUS RADIOACTIVE EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables 1A and lB. Plant Vent and Containment Vent releases are modeled as mixed mode and the Air Ejector is modeled as a ground level release.

4.0

SUMMARY

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

R.E. Ginna Nuclear Power Plant 4 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

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 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 not satisfied on one occasion:

On May 2, 2014, the LLDs for Mo-99, 1-131, and Ce-144 were not met on Plant Vent R-10B, R-13, R-14 grab samples used in gaseous release permit G-201401 1, due to short run time on sampler which resulted in insufficient sample volume to meet the LLDs..

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.

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; 0 < 75 mrem thyroid for a calendar year.

Using the maximum exposure and uptake pathways, the maximum liquid R.E. Ginna Nuclear Power Plant 5 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

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: 11.7 mRem (Sum of 11.7 mrem direction radiation, 7.66E-03 (Total Body Liquid Dose), 2.88E-03 (Total Body Gas Dose).

  • Maximum Annual Organ Dose: 2.3E-02 mrem (Child bone C-14)
  • Maximum Annual Thyroid Dose: 1.61 E-02 mrem (Teen) 8.0 METEOROLOGICAL DATA The annual summary of hourly meteorological data collected during 2014 is not included with this report, but can be made available upon request.

9.0 LAND USE CENSUS CHANGES In September 2014, 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.

" The Monroe County Water Authority (MCWA) completed construction of a new municipal water pump station facility located at 1720 Lake Road (west of the plant) in 2013 and commenced operation in May 2014. Ginna Chemistry staff began collecting raw water samples as part of its Radiological Environmental Monitoring Program (REMP) in June 2014.

" Single family home construction was observed at various locations within the 5 mile REMP zone, at rates consistent with past years.

" No new agricultural land use was identified.

" No new food producing facilities were identified.

  • No new milk producing animals were identified.

R.E. Ginna Nuclear Power Plant 6 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

10.0 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL There were two changes to the Offsite Dose Calculation Manual (ODCM) in 2014.

1. Revision 28 of the ODCM, effective 2/4/14, included a Table of Contents as well as a List of Acronyms and editorial clarifications to references and a clarification to the symbol used for a variable in an equation.
2. Revision 29 of the ODCM, effective 6/27/14, updated Table 2-2 to reflect a revised dispersion factor for radiation monitor R-48.

11.0 CHANGES TO THE PROCESS CONTROL PROGRAM There were no changes to the Process Control Program during the reporting period.

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 RM-14A, Plant Vent Accident range gas monitor, failed calibration on 6/5/14 and was out of service until 6/18/14 at 1400, greater than 7 day reporting required in this report by ODCM Table 3.3-1.

14.0 CHANGES TO PREVIOUS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTS The 2013 Land Use Census listed Eaton milk farm as in the South East sector at 8270 meters. The Eaton milk farm is actually in the East South East sector at 8240 meters.

In the 2012 Annual Radioactive Effluent Release Report, Table 2A, B.3, Tritium percent of applicable limit in liquid effluents was wrong for each of 4 quarters-

3. Percent of applicable limit I  % I 9.30E+05 I 1.67E+06 I 2.88E+6 I 1.66E+06 This should have been reported as -
3. Percent of applicable limit I % 9.30E-05 I 1.67E-06 I 2.88E-06 I 1.66E-06 R.E. Ginna Nuclear Power Plant 7 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

15.0 GROUNDWATER MONITORING In accordance Ginna's Chemistry procedures, environmental groundwater monitoring wells are sampled on a routine frequency. During 2013, five new groundwater monitoring wells were installed. In 2014, 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

" GW1 1: 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*

  • - Asterisks denote new groundwater wells installed in 2013.

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 2014 are presented in Table 5.

All samples collected during 2014, 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 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, leads to a conservative estimate of 6.8 Curies released in gaseous effluents in 2014. Kunz further determined the chemical form of the Carbon-14 at Ginna to be approximately 10% Carbon Dioxide (CO 2 )'.

R.E. Ginna Nuclear Power Plant 8 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

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.

16.1 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 2014.
b. There was a refueling outage in 2014. 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-1 4 was in the chemical form of C0 2 , 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 2014.

16.2 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.OE-07 uCi/cc.
c. 5.24E+05 liters of liquid waste (with the potential to contain C-14) were released with a total dilution flow of 1.91 E+1 2 liters.
d. Average diluted concentration of C-14 released was 1.58E-13 uCi/cc.
e. Liquid effluent dilution factor for potable water pathway is 200.
f. Liquid effluent dilution factor for fish pathway is 1.

R.E. Ginna Nuclear Power Plant 9 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

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 2014.

R.E. Ginna Nuclear Power Plant 10 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 2014 Effluent Type Units 1 st Quarter 2 nd Quarter 3 rd Quarter 4 th Quarter Est. Total Error, %

A. Fission & Activation Gases

1. Total release Ci 6.06E-01 6.16E+00 8.64E-01 1.03E+00 2.80E+01
2. Average release rate for period uCi/sec 7.68E-02 7.82E-01 1.10E-01 1.30E-01
3. Percent of technical specification limit  % 1.22E-05 1.24E-04 1.75E-05 2.06E-05 B. lodines
1. Total iodine-131 Ci 0.OOE+00 2.32E-04 0.OOE+00 0.OOE+00 2.20E+01
2. Average release rate for period uCi/sec O.OOE+00 2.95E-05 0.OOE+00 0.OOE+00
3. Percent of technical specification limit  % 0.OOE+00 6.41E-02 0.OOE+00 0.OOE+00 C. Particulates
1. Particulates with half-lives > 8days Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 N/A
2. Average release rate for period uCi/sec 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00
3. Percent of technical specification limit  % O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
4. Gross alpha radioactivity Ci O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 D. Tritium
1. Total release Ci 3.22E+01 3.46E+01 2.62E+01 2.26E+01 1.50E+00
2. Average release rate for period uCi/sec 4.08E+00 4.38E+00 3.32E+00 2.87E+00
3. Percent of technical specification limit  % 4.78E-06 5.13E-06 3.89E-06 3.36E-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 01/01/2014 - 12/31/2014

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - CONTINUOUS AND BATCH RELEASES 2014 Batch Mode NuclidesNuclides Units Continuous Mode Batch r Mode Quarter 4"' Quarter Released 4t Quarter

-. r ~ -I ra Quarter

~. -r I -r 3m~. -r 1ST 1 " Quarter 2 na Quarter 33r° Quarter 41fl Quarter 1' Quarter 25, Quarter Vr Quarter 4' Quarter

1. Fission Gases Argon-41 Ci 3.91E-01 9.44E-02 5.97E-02 6.58E-02 6.61E-02 Krypton-85 Ci 6.42E-01 Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-131m Ci Xenon-133 Ci 1.65E+00 2.07E-01 2.71E-01 3.48E-01 4.32E-01 Xenon-133m Ci Xenon-135 Ci 1.35E-03 6.96E-02 1.89E-02 1.43E-03 Xenon-135m Ci Xenon-138 Ci Total for period Ci 2.04E+00 3.03E-01 1.04E+00 6.06E-01 5.00E-01
2. lodines Iodine-131 Ci 1.16E-04 1.18E-08 Iodine-132 Ci Iodine-133 Ci Iodine-135 Ci Total for period Ci 1.16E-04 1.18E-08 R.E. Ginna Nuclear Power Plant 12 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

TABLE 1B (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - CONTINUOUS AND BATCH RELEASES 2014 Nuclides Units Continuous Mode Batch Mode Released 1 st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1 st Quarter 2nd Quarter 3 rd Quarter 4th Quarter

3. Particulates strontium-89 Ci strontium-90 Ci cesium-137 Ci cobalt-57 Ci cobalt-58 Ci cobalt-60 Ci Unidentified Ci Total for period Ci
4. Tritium Hydrogen-3 Ci 3.22E+01 3.46E+01 2.62E+01 2.26E+01 9.07E-02 4.29E-02 1.12E-01 8.31E-02 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 01/01/2014 - 12/31/2014

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 2014 Effluent Type Units 1t Quarter 2nd Quarter 3rd Quarter 4th Quarter Est. Total Error, %

A. Fission & Activation Products

1. Total Release (not including tritium, gases, Ci 1.47E-04 3.55E-03 9.28E-04 1.41E-04 1.90E+01 alpha)
2. Average Diluted concentration uCi/ml 4.43E-13 9.07E-12 1.80E-12 2.86E-13
3. Percent of applicable limit  % 4.43E-06 9.07E-05 1.80E-5 2.86E-06 B. Tritium
1. Total Release Ci 3.23E+02 1.50E+02 3.75E+01 2.25E+01 9.20E+00
2. Average Diluted Concentration uCi/ml 9.75E-07 3.83E-07 7.26E-08 4.55E-08
3. Percent of applicable limit  % 9.75E-03 3.83E-03 7.26E-04 4.55E-04 C. Dissolved and Entrained Gases
1. Total Release Ci 3.30E-03 8.45E-03 0.OOE+00 0.OOE+00 1.90E+01
2. Average Diluted Concentration uCi/ml 9.96E-12 2.16E-11 O.OOE+00 O.OOE+00
3. Percent of applicable limit  % 9.96E-06 2.16E-05 0.OOE+00 0.OOE+00 D. Gross Alpha Radioactivity
1. Total release Ci 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 N/A E. Vol. of Waste Released (prior to dilution) Liters 1.23E+08 1.02E+08 1.27E+08 1.21E+08 F. Vol. of Dilution Water Used During Period Liters 3.32E+11 3.92E+11 5.16E+11 4.95E+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 01/01/2014 - 12/31/2014

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - CONTINUOUS AND BATCH RELEASES 2014 Nuclides Released Units Continuous Mode Batch Mode 1 1s Quarter 2no Quarter 3rd Quarter I 4"n Quarter 1st Quarter I 2n Quarter 3 r' Quarter I 4T' Quarter Fission & Activation Products Chromium-51 Ci Manganese-54 Ci Iron-55 Ci Iron-59 Ci Cobalt-57 Ci Cobalt-58 Ci 1.47E-04 3.55E-03 8.39E-04 6.95E-05 Cobalt-60 Ci 9.12E-08 Zinc-65 Ci Strontium-89 Ci Strontium-90 Ci Niobium-95 Ci Molybdenum-99 Ci Zirconium-95 Ci Silver-r10m Ci Antimony-122 Ci Tellurium-123m Ci 7.19E-05 Antimony-124 Ci Antimony-125 Ci Iodine-131 Ci Iodine-132 Ci 2.61E-07 Tellurium-132 Ci Iodine-135 Ci Cesium-134 Ci Cesium-136 Ci Cesium-137 Ci 8.93E-05 R.E. Ginna Nuclear Power Plant 15 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

TABLE 2B (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - CONTINUOUS AND BATCH RELEASES 2014 Nuclides Released Units Continuous Mode Batch Mode 1" Quarter 2no Quarter 3ra Quarter 4n Quarter 1" Quarter 2n, Quarter 3r, Quarter 4mn Quarter Barium/Lanthanum-140 Ci Cerium-141 Ci Total (above) Ci 1.47E-04 3.55E-03 9.28E-04 1.41E-04 Unidentified (from total Ci above)

Tritium Hydrogen-3 Ci 5.73E-02 0.OOE+00 2.08E-02 2.53E-02 3.23E+02 1.50E+02 3.75E+01 2.25E+01 Dissolved And Entrained Gases Xenon-133 Ci 3.30E-03 8.45E-03 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 01/01/2014 - 12/31/2014

TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 2014 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 2.75E+00 2.5E+01 Bottoms, Etc. Ci 4.93E+01 2.5E+01 B - Dry Active Waste (DAW), Contaminated m3 2.78E+02 2.5E+01 Equipment, Etc. Ci 1.75E-01 2.5E+01 3

C - Irradiated Components, Control Rods, Etc. m None N/A Ci m3 None N/A D- Other: Combined Packages Ci None N/A Note: Estimated total error for solid waste shipped offsite not available.

R.E. Ginna Nuclear Power Plant 17 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

TABLE 3 (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 2014

2. Estimate of Major Nuclide Composition By Type of Waste Isotope Unit Type A Type B Type C Type D Co-58  % 8.43 3.5 Co-60  % 7.81 10.87 Cr-51  % 6.02 Cs-137  % 6.77 Fe-55  % 5.49 14.61 Mn-54  % 2.4 4.29 Nb-95  % 7.99 Ni-63  % 55.33 49.29 Sb-125  % 1.12 Zr-95  % 5.05 Cs-134  % 2.67 Be-7  % 3.80 Total J  % 98.5 96.9 Note: Blank cells indicate nuclide composition not at significant levels.

R.E. Ginna Nuclear Power Plant 18 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

TABLE 3 (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 2014

  1. of Shipments Mode of Type of Container Solidification Processing Destination Transportation I Agent I Waste Control Specialists, Andrews, High Integrity Containers (HICs) None Used Onsite texas 1 Sole Use Truck Texas 5 Sole Use Truck Metal Containers None Used Onsite EnergySolutions, BC B. IRRADIATED FUEL SHIPMENTS (Disposition)
  1. of Shipments Mode of Destination Transportation None N/A N/A R.E. Ginna Nuclear Power Plant 19 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

TABLE 4A Radiation Dose to Maximum Individual Receptor from Gaseous Effluents First Quarter 2014 (Units In milliRem)

All All Adult Teen Child Infant Gma Air Beta Air THYRD THYRD THYRD THYRD EN E 5.78E-06 3.21E-06 4.49E-04 4.92E-04 6.75E-04 1.85E-07 ESE 7.35E-06 4.09E-06 5.71E-04 6.26E-04 8.59E-04 3.75E-04 SE 4.45E-06 2.47E-06 3.45E-04 3.79E-04 5.20E-04 1.42E-07 SSE 1.83E-06 1.02E-06 1.42E-04 1.56E-04 2.14E-04 5.85E-08 S 3.20E-06 1.78E-06 2.49E-04 2.73E-04 3.75E-04 1.02E-07 SSW 3.20E-06 1.78E-06 2.49E-04 2.73E-04 3.75E-04 1.02E-07 SW 3.20E-06 1.78E-06 2.49E-04 2.73E-04 3.75E-04 1.02E-07 WSW 3.42E-06 1.90E-06 2.66E-04 2.91E-04 3.99E-04 1.09E-07 W 2.18E-06 1.21E-06 1.69E-04 1.85E-04 2.54E-04 6.95E-08 MAx. 1.84E-07 1.02E-07 1.43E-05 1.57E-05 2.15E-05 5.87E-09 Note: Shaded regions indicate areas over Lake Ontario.

R.E. Ginna Nuclear Power Plant 20 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

TABLE 4A (Continued)

Radiation Dose to Maximum Individual Receptor from Gaseous Effluents Second Quarter 2014 (Units In milliRem)

All All Adult Teen Child Infant Gamma Air Beta Air THYRD THYRD THYRD THYRD E 5.77E-05 1.11E-04 4.87E-03 6.53E-03 1.19E-02 2.33E-02 ESE 7.34E-05 1.41E-04 6.20E-03 8.30E-03 1.52E-02 2.96E-02 SE 4.44E-05 8.53E-05 3.75E-03 5.02E-03 9.17E-03 1.79E-02 SSE 1.83E-05 3.51E-05 1.54E-03 2.07E-03 3.77E-03 7.38E-03 S 3.20E-05 6.15E-05 2.70E-03 3.62E-03 6.61E-03 1.29E-02 SSW 3.20E-05 6.15E-05 2.70E-03 3.62E-03 6.61E-03 1.29E-02 SW 3.20E-05 6.15E-05 2.70E-03 3.62E-03 6.61E-03 1.29E-02 WSW 3.41E-05 6.56E-05 2.88E-03 3.86E-03 7.05E-03 1.38E-02 W 2.17E-05 4.17E-05 1.84E-03 2.46E-03 4.49E-03 8.77E-03 MAX. 7.34E-05 1.41E-04 6.20E-03 8.30E-03 1.52E-02 2.96E-02 Note: Shaded regions indicate areas over Lake Ontario.

R.E. Ginna Nuclear Power Plant 21 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

TABLE 4A (Continued)

Radiation Dose to Maximum Individual Receptor from Gaseous Effluents Third Quarter 2014 (Units In milliRem)

All All Adult Teen Child Infant Gamma Air Beta Air THYRD THYRD THYRD THR E 4.67E-06 3.80E-06 3.66E-04 4.01E-04 5.50E-04 2.40E-04 ESE 5.94E-06 4.83E-06 4.65E-04 5.10E-04 7.OOE-04 3.06E-04 SE 3.59E-06 2.92E-06 2.81E-04 3.09E-04 4.24E-04 1.85E-04 SSE 1.48E-06 1.20E-06 1.16E-04 1.27E-04 1.74E-04 7.61E-05 S 2.59E-06 2.11E-06 2.03E-04 2.22E-04 3.05E-04 1.33E-04 SSW 2.59E-06 2.11E-06 2.03E-04 2.22E-04 3.05E-04 1.33E-04 SW 2.59E-06 2.11E-06 2.03E-04 2.22E-04 3.05E-04 1.33E-04 WSW 2.76E-06 2.25E-06 2.16E-04 2.37E-04 3.26E-04 1.42E-04 W 1.76E-06 1.43E-06 1.38E-04 1.51E-04 2.07E-04 9.04E-05 XWNW 1.49E-07 1.21E-07 1.16E-05 1.28E-05 1.75E-05 7.64E-06 MAX. 5.94E-06 4.83E-06 4.65E-04I 5.10E-04 7.00E-04 3.06E-04 Note: Shaded regions indicate areas over Lake Ontario.

R.E. Ginna Nuclear Power Plant 22 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

TABLE 4A (Continued)

Radiation Dose to Maximum Individual Receptor from Gaseous Effluents Fourth Quarter 2014 (Units In milliRem)

All All Adult Teen Child Infant Gamma Air Beta Air THYRD THYRD THYRD THYRD E 4.82E-06 4.28E-06 3.16E-04 3.46E-04 4.75E-04 2.08E-04 ESE 6.13E-06 5.44E-06 4.02E-04 4.40E-04 6.05E-04 2.64E-04 SE 3.71E-06 3.29E-06 2.43E-04 2.66E-04 3.66E-04 1.60E-04 SSE 1.53E-06 1.35E-06 1.OOE-04 1.10E-04 1.51E-04 6.58E-05 S 2.67E-06 2.37E-06 1.75E-04 1.92E-04 2.64E-04 1.15E-04 SSW 2.67E-06 2.37E-06 1.75E-04 1.92E-04 2.64E-04 1.15E-04 SW 2.67E-06 2.37E-06 1.75E-04 1.92E-04 2.64E-04 1.15E-04 WSW 2.85E-06 2.53E-06 1.87E-04 2.05E-04 2.81E-04 1.23E-04 W 1.81E-06 1.61E-06 1.19E-04 1.30E-04 1.79E-04 7.82E-05 MAX. 6.13E-06 5.44E-06 4.02E-04 4.40E-04 6.05E-04 2.64E-04 Note: Shaded regions indicate areas over Lake Ontario.

R.E. Ginna Nuclear Power Plant 23 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

TABLE 4B Radiation Dose To Maximum Individual Receptor From Liquid Effluents for 2014 (Units in milliRem)

Adult Teen Child Infant First Quarter T. Body 2.92E-03 2.21 E-03 2.20E-03 6.29E-04 GI-LLI 2.93E-03 2.23E-03 2.20E-03 6.29E-04 Thyroid 2.92E-03 2.22E-03 2.20E-03 6.27E-04 Second Quarter T. Body 5.26E-03 4.04E-03 4.01 E-03 1.10E-03 GI-LLI 6.49E-03 4.81 E-03 4.16E-03 1.10E-03 Thyroid 5.11 E-03 3.88E-03 3.85E-03 1.01 E-03 Third Quarter T. Body 2.51 E-03 1.41 E-03 6.06E-04 2.82E-05 GI-LLI 2.21E-04 1.66E-04 1.22E-04 2.82E-05 Thyroid 1.31 E-04 9.94E-05 9.86E-05 2.82E-05 Fourth Quarter T. Body 8.49E-05 6.39E-05 6.33E-05 1.81 E-05 GI-LLI 8.55E-05 6.48E-05 6.35E-05 1.81 E-05 Thyroid 8.39E-05 6.37E-05 6.31 E-05 1.81 E-05 R.E. Ginna Nuclear Power Plant 24 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

TABLE 5 Groundwater Monitoring Wells Location Sample Date Tritium (uCi/ml)

GW01: Warehouse Access Road (Control) 03/11/2014

  • 06/27/2014
  • 09/21/2014
  • 12/10/2014
  • GW03: Screenhouse West, South Well 01/24/2014
  • 02/25/2014
  • 03/11/2014
  • 04/18/2014
  • 05/14/2014
  • 06/27/2014
  • 07/24/2014
  • 08/23/2014
  • 09/21/2014
  • 10/31/2014
  • 11/14/2014
  • 12/10/2014
  • GW04: Screenhouse West, North Well 03/11/2014
  • 06/27/2014
  • 09/21/2014
  • 12/10/2014
  • GW05: Screenhouse East, South (15.5') 03/11/2014
  • 06/27/2014
  • 09/21/2014
  • 12/10/2014
  • R.E. Ginna Nuclear Power Plant 25 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

TABLE 5 (Continued)

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

GW06: Screenhouse East, Middle (20.0') 03/11/2014

  • 06/27/2014
  • 09/21/2014
  • 12/10/2014
  • GW07: Screenhouse East, North (24.0') 03/11/2014
  • 06/27/2014
  • 09/21/2014
  • 12/10/2014
  • GWO8: All Volatile Treatment Building 01/24/2014
  • 02/25/2014
  • 03/11/2014
  • 04/18/2014
  • 05/14/2014
  • 06/27/2014
  • 07/24/2014
  • 08/23/2014
  • 09/21/2014
  • 10/31/2014
  • 11/14/2014
  • 12/10/2014
  • 06/27/2014
  • 09/21/2014
  • 12/10/2014
  • R.E. Ginna Nuclear Power Plant 26 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

TABLE 5 (Continued)

Groundwater Monitoring Wells Location Sample Date Tritium (uCi/mil)

GW1 1: Southeast of Contaminated Service Building (CSB) 02/28/2014

  • 03/11/2014
  • 06/27/2014
  • 09/21/2014
  • 12/10/2014
  • GW 12: West of Orchard Access Road 03/11/2014
  • 06/27/2014
  • 09/21/2014
  • 12/10/2014
  • GW13: North of Independent Spent Fuel Storage Installation (ISFSI) 03/11/2014
  • 06/27/2014
  • 09/21/2014
  • 12/10/2014
  • GW14: South of Canister Preparation Building 03/11/2014
  • 06/27/2014
  • 09/21/2014
  • 12/10/2014
  • GW1 5: West of Manor House 03/11/2014
  • 06/27/2014
  • 09/21/2014
  • 12/10/2014
  • GW16: Southeast of Manor House 03/11/2014
  • 06/27/2014
  • 09/21/2014 Dry- no sample 12/10/2014 Dry - no sample

I ________ I________

R.E. Ginna Nuclear Power Plant 27 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

TABLE 6 Offsite Dose Due to Carbon-14 in Gaseous and Liquid Effluents MAXIMUM DOSE VALUES DUE TO C-14 IN GASEOUS EFFLUENTS IN 2014 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 2014 Organ Age mRem/yr NRC Reg. Guide 1.109, Annual Bone Dose Child 5.84E-05 NRC Reg. Guide 1.109, Annual Total Body/Organ Dose Child 1.17E-05 R.E. Ginna Nuclear Power Plant 28 ARERR Docket No. 50-244 01/01/2014 - 12/31/2014

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