ML12142A295

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2011 Annual Radioactive Effluent Release Report
ML12142A295
Person / Time
Site: Ginna Constellation icon.png
Issue date: 12/31/2011
From:
Constellation Energy Nuclear Group
To:
Office of Nuclear Reactor Regulation
References
Download: ML12142A295 (32)
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Enclosure (1 2011 Annual Radioactive Effluent Release Report Including Revision 27 of the Offsite Dose Calculation Manual R.E. Ginna Nuclear Power Plant, LLC May 14, 2012

2011 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT R. E. GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 1

TABLE OF CONTENTS 1.0 Introduction 4 2.0 Supplemental Information 4 2.1 Regulatory Limits 4 2.2 Effluent Concentration Limits 5 2.3 Release Rate Limits Based on Average Nuclide Energy 6 2.4 Measurements and Approximations of Total Radioactivity 6 2.5 Batch Releases 6 2.6 Abnormal Releases 7 3.0 Summary of Gaseous Radioactive Effluents 7 4.0 Summary of Liquid Radioactive Effluents 7 5.0 Solid Waste 8 6.0 Lower Limit of Detection 8 7.0 Radiological Impact 8 8.0 Meteorological Data 9 9.0 Land Use Census Changes 9 10.0 Changes to the Offsite Dose Calculation Manual 10 11.0 Changes to the Process Control Program 10 12.0 Major Changes to Radwaste Treatment Systems 10 13.0 Inoperable Monitors 11 14.0 Changes to Previous Annual Effluent Reports 11 15.0 Groundwater Monitoring 11 2

LIST OF TABLES Table 1A Gaseous Effluents - Summation of all Releases ...................................... 13 Table 1B Gaseous Effluents - Continuous and Batch Releases ............................ 15 Table 2A Liquid Effluents - Summation of all Releases ........................................... 17 Table 2B Liquid Effluents - Continuous and Batch Releases .................................. 19 Table 3 Solid Waste and Irradiated Fuel Shipments ............................................. 21 Table 4A Radiation Dose to Maximum Individual Receptor from Gaseous Effluents.. 23 Table 4B Radiation Dose to Maximum Individual Receptor from Liquid Effluents ...... 27 Table 5 Groundwater Monitoring W ells ............................................................... 28 Table 6 Offsite Dose due to Carbon-14 in Gaseous and Liquid Effluents ............. 30 3

1.0 INTRODUCTION

This Annual Radioactive Effluent Release Report is for the R.E. Ginna Nuclear Power Plant (Ginna) and is submitted in accordance with the require-ments of Technical Specification Section 5.6.3. The report covers the period from January 1, 2011 through December 31, 2011.

This report includes 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 R.E. 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, 4

radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 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.

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 the limits specified in accordance with Appendix B, Table II, Column 2 and notes thereto of 10CFR20, 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 Limit (ECL) 2.2.1 For gaseous effluents, effluent concentration limits 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, ten times the effluent concentration values specified in 10CFR20, Appendix B, Table II, column 2, are used to calculate release rates and permissible concentrations at the unrestricted area boundary as 5

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.

2.3 Release Rate Limits Based on Averaqe 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 2011 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 Sr-89, Sr-90, and Fe-55 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 and the total volume of effluents released.

2.5 Batch Releases 2.5.1 Liquid

1. Number of batch releases: 1.69 E+02
2. Total time period for batch releases: 2.33 E+04 min
3. Maximum time period for a batch release: 7.59 E+02 min
4. Average time period for batch releases: 1.38 E+02 min
5. Minimum time period for a batch release: 1.8 E+01 min
6. Average blowdown in liters per minute (LPM) during periods of effluent release into the discharge canal. 4.15 E+02 LPM 6

2.5.2 Gaseous

1. Number of batch releases: 5.0 E+01
2. Total time period for batch releases: 5.37 E+05 min
3. Maximum time period for a batch release: 4.46 E+04 min
4. Average time period for batch releases: 1.07 E+04 min
5. Minimum time period for a batch release: 2.60 E+01 min 2.6 Abnormal Releases There were two abnormal releases that occurred during this reporting period.

Both were unplanned gaseous releases. They are:

1. The contents of a Gas Decay Tank was unintentionally released into the Containment Building. The Containment Building ventilation to the Plant Ventilation was in-service at the time of unintentional release. The Plant Ventilation is a monitored pathway and no challenges to gaseous effluent release limits were observed. This event occurred on 4/24/2011 and permit number G-2011032 was created as a result. This event is documented in Ginna's corrective action program under CR-2011-002626.
2. A continuous air-sampler placed outside the Containment Building Equipment Hatch during the Refueling Outage yielded a positive result for radioactivity.

The week of concern was 5/8 - 5/15/2011 and permit number G-2011041 was created as a result. This event is documented in Ginna's corrective action program under CR-2011-003654.

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 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.

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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 LLD per Table 2-1 of the ODCM were not satisfied for Auxiliary Building Ventilation on three occasions. They were:

1. The Auxiliary Building Ventilation continuous radioactive iodine monitor (R-1 OB) did not meet the required LLD on 5/10/2011. This is due to procedural requirements mandating the replacement of the Charcoal Cartridge upon receiving an alarm. The sample volume for this Charcoal Cartridge did not meet the statistical requirements necessary to achieve the appropriate LLD.
2. The Auxiliary Building Ventilation continuous radioactive particulate monitor (R-13) did not meet the required LLD on 5/12/2011. This can be attributed to the same reason noted in number 1.
3. The Auxiliary Building Ventilation continuous radioactive iodine monitor (R-1OB) did not meeting the required LLD on 5/12/2011. This can be attributed to the same reason noted in number 1.

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 from WNW through ENE are entirely over Lake Ontario.

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.

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7.1 Total Dose 40CFR190 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, 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. Dose to any real member of the public should be conservatively bounded by this calculated dose.

  • 12.4 mrem total body (12.4 mrem direct radiation plus 4.73E-02 mrem all other pathways).

9 2.41E-02 mrem maximum organ dose (Thyroid).

8.0 METEOROLOGICAL DATA The annual summary of hourly meteorological data collected during 2011 is not included with this report, but can be made available at the R. E. Ginna Nuclear Power Plant.

9.0 LAND USE CENSUS CHANGES In September 2011, a Land Use Survey was conducted 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.

The following land use changes occurred over the past year within a 5-mile radius of the power plant:

" The closest residential dwelling in the SE sector (1601 Lake Road) is no longer occupied. The new nearest residence is located in the SE sector, approximately 840 meters from the reactor.

" The Monroe County Water Authority (MCWA) continues construction of a new municipal water treatment facility on Lake Road between Salt Road and 9

Basket Road. While this facility not yet in service, its construction will be tracked and added to the REMP upon completion.

  • The construction of two small subdivisions occurred on the south side of Boston Rd. (eastern end).

" The Summer Lake Subdivision expanded into its final construction phase, adding 14 additional homes.

  • No new agricultural land use was identified.
  • No new food producing facilities were identified.
  • No new milk producing animals were identified.

10.0 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL There was one change made to the ODCM during 2011. The change went into effect on May 3, 2011. This change is summarized as follows.

1. Section 2.1: This section was deleted to be consistent with ODCM Industry Best Practices and include the conservatism to restrict gas decay tank releases to ALARA in the Waste Gas Decay Tank release procedures.
2. Section 2.5: This change clarifies the wording to better describe and allow for the rare events/evolutions that create a release pathway that is not monitored by installed plant radiological monitoring instrumentation.
3. Table 3.2-1: The purpose of this change is to adopt the requirements outlined in Action 45 of Table 3.3-13 in NUREG-1301 that would allow the release of a Waste Gas Decay Tank with R-14 (Plant Vent Noble Gas Monitor) out-of-service.
4. Section 5.4.1: Editorial correction to change the referenced procedure from CHA-QC-INTERLAB to CH-QC-INTERLAB.

A copy of the latest revision of the ODCM is attached at the end of this report.

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 10

There were no major changes to the Radwaste Treatment Systems during the reporting period.

13.0 INOPERABLE MONITORS There were four occurrences satisfying the requirement stated in Section 3.3 and Table 3.3-1, Action 1 of the ODCM for reporting inoperable radiation monitors.

Two occurrences surpassed 30-days of inoperability and two occurrences were inoperable for greater than 7 days and less than 30 days. They are:

1. Radiation Monitor R-14A, Channel 3, Plant Vent Iodine Accident Range Radiation Monitor, was inoperable for greater than 30 days. The special report was sent to the NRC on 8/2/2011 outlining cause of inoperability and actions taken to restore the monitor to operable.
2. Radiation Monitor R-14A, Channel 7, Plant Vent Mid Range Noble Gas Accident Monitor became inoperable on 8/29/2011. The radiation monitor discontinued working and subsequent troubleshooting failed. The monitor was returned to operable status on 9/9/2011 following monitor replacement. The duration of inoperability was 10 days.
3. Radiation Monitor R-14A, Channel 3, Plant Vent Iodine Accident Range Radiation Monitor became inoperable on 9/30/2011. The monitor failed to meet the source check range during the monthly surveillance. R-14A, Channel 3 was was subsequently calibrated and source check verified to be within acceptable range. The monitor was returned to operable status on 10/7/2011. The duration of the inoperability was 7 days.
4. Radiation Monitors R-31 and R-32, "A" and "B" Main Steam Radiation Monitors, respectively, were inoperable for greater than 30 days. The special report was sent to the NRC on 12/6/2011 outlining cause of inoperability and plan to restore the monitors to operable.

14.0 CHANGES TO PREVIOUS ANNUAL EFFLUENT OPERATING REPORTS There was a transcriptional error identified in the 2007 Annual Radiological Effluent Release Report. Section 7.1, Total Dose, states the maximum organ dose as 4.86E-03 mrem and the total dose from all other pathways as 4.81E-03 mrem. These values are written backwards. The actual maximum organ dose is 4.81E-03 mrem and the dose from all other pathways is 4.86E-03 mrem.

15.0 GROUNDWATER MONITORING 11

In accordance with R. E. Ginna Nuclear Power Plant's Chemistry procedures, at a minimum, environmental groundwater monitoring wells are sampled quarterly.

During 2011, Ginna sampled from 10 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
  • GW1 1: Contaminated Storage Building, SE (24.0')

Groundwater samples are analyzed for tritium to a detection limit of 500 pCi/L, and for gamma emitting radionuclides to the environmental LLDs. Results of the 10 groundwater monitoring well sampled in 2011 are presented in Table 5.

There were positive tritium results (> MDA) in GW03, GW04, GW09 and GW1 1 on 2/9/2011. Condition Report CR-2011-001113 was initiated in the Ginna Corrective Action Program and an Apparent Cause Evaluation was performed.

The subsequent information was gathered regarding the positive results:

" GW03, GW09 and GW1 1 were re-sampled on 2/18/2011. The results indicated positive tritium concentrations.

" GW04 was not re-sampled due to ground surrounding well location being submerged in standing water due to inadequate ground gradient. It was determined the standing water compromised the integrity of the groundwater sample. Sampling of this well continued after the surrounding ground gradient was corrected to improve drainage in the area surrounding the groundwater well.

  • GW03 was declared out of service due to the depth to water being 3 feet higher than adjacent groundwater monitoring well, GW04. The discrepancy in water height is indicative of a degraded well material condition.
  • GW09 was declared out of service due to a significant amount of clay and silt observed in the sample. These conditions are indicative of well screen damage.
  • The apparent cause of the positive results in February was a significant snow melt that occurred the week prior to groundwater well sampling. The snow contained tritium due to tritium recapture from the Auxiliary Building Plant Ventilation.

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All other samples taken during 2011 did not indicate positive results for tritium.

Table 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES January-June 2011 Unit Quarter Quarter Est. Total A. Fission & Activation Gases 1st 2nd Error, %

1. Total release Ci 2.35E-01 1.58E+00 1.50E+01
2. Average release rate for period uCi/sec 2.98E-02 2.01E-01
3. Percent of technical specification limit  % 4.73E-06 3.19E-05 B. Iodines
1. Total iodine-131 Ci 6.03E-08 1.66E-04 1.50E+01
2. Average release rate for period uCi/sec 7.65E-09 2.10E-05
3. Percent of technical specification limit  % 1.66E-05 4.57E-02 C. Particulates
1. Particulates with half-lives > 8days Ci 1.16E-03 1.50E+01
2. Average release rate for period uCi/sec 1.47E-04
3. Percent of technical specification limit  %
4. Gross alpha radioactivity Ci D. Tritium
1. Total release Ci 1.79E+01 2.18E+01 9.20E+00
2. Average release rate for period uCi/sec 2.28E+00 2.77E+00
3. Percent of technical specification limit  % 2.67E-04 3.24E-04 Note: Isotopes for which no value is given were not identified in applicable releases.

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Table 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES July - December 2011 Unit Quarter Quarter Est. Total A. Fission & Activation Gases 3rd 4th Error, %

1. Total release Ci 2.77E-01 2.69E-01 1.50E+01
2. Average release rate for period uCi/sec 3.51E-02 3.41E-02
3. Percent of technical specification limit  % 5.57E-06 5.41E-06 B. lodines
1. Total iodine-131 Ci
2. Average release rate for period uCi/sec
3. Percent of technical specification limit  %

C. Particulates

1. Particulates with half-lives > 8days Ci
2. Average release rate for period uCi/sec
3. Percent of technical specification limit  %
4. Gross alpha radioactivity Ci D. Tritium
1. Total release Ci 2.32E-01 1.01E+01 9.20E+00
2. Average release rate for period uCi/sec 2.94E+00 1.28E+00
3. Percent of technical specification limit  % 3.44E-04 1.50E-04 Note: Isotopes for which no value is given were not identified in applicable releases.

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Table 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - CONTINUOUS AND BATCH RELEASES January - June 2011 Continuous Mode Batch Mode Nuclides released Unit Quarter Quarter IQuarter fQuarter 1st 2nd 1st 2nd

1. Fission gases argon-41 Ci 3.20E-01 9.35E-02 4.81E-02 krypton-85 Ci krypton-85m Ci 2.01E-04 krypton-87 Ci krypton-88 Ci xenon-131m Ci 3.81E-04 xenon-133 Ci 1.07E+00 1.35E-01 8.92E-02 xenon-133m Ci 1.43E-04 xenon-135 Ci 4.32E-02 6.76E-03 1.55E-02 xenon-135m Ci xenon-138 Ci others (specify) Ci Ci Total for period Ci 1.43E+00 2.35E-01 1.53E-01
2. lodines iodine-131 Ci 1.66E-04 6.03E-08 1.80E-08 iodine-132 Ci iodine-133 Ci iodine-135 Ci Total for period Ci 1.66E-04 6.03E-08 1.80E-08
3. Particulates strontium-89 Ci strontium-90 Ci cesium-137 Ci cobalt-57 Ci 1.28E-06 cobalt-58 Ci 1.07E-03 cobalt-60 Ci 9.23E-05 5.24E-09 unidentified Ci Total for period Ci 1.16E-03 O.OOE+00 5.24E-09
4. Tritium Hydrogen-3 Ci 1.79E+01 2.18E+01 1.47E-02 I 1.48E-02 15

Note: Isotopes for which no value is given were not identified in applicable releases.

Table 1 B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - CONTINUOUS AND BATCH RELEASES July - December 2011 Continuous Mode Batch Mode Nuclides released Unit Quarter Quarter Quarter Quarter 3rd 4th 3rd 4th

1. Fission gases argon-41 Ci 7.21E-02 7.55E-02 krypton-85 Ci krypton-85m Ci krypton-87 Ci krypton-88 Ci xenon-131m Ci xenon-133 Ci 2.03E-01 1.92E-01 xenon-133m Ci xenon-135 Ci 1.98E-03 1.64E-03 xenon-135m Ci xenon-138 Ci others (specify) Ci Ci unidentified Ci Total for period Ci 2.77E-01 2.69E-01
2. Iodines iodine-131 Ci iodine-133 Ci iodine-135 Ci Total for period Ci
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 2.32E+01 1.01E+01 1.17E-02 7,14E-03 16

Note: Isotopes for which no value is given were not identified in applicable releases.

Table 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES January - June 2011 Unit Quarter Quarter Est.Total A. Fission and activation products 1st 2nd Error, %

1. Total release (not including tritium, Ci 2.77E-03 9.90E+0 gases, alpha)
2. Average diluted concentration uCi/ml 9.50E-12 during period
3. Percent of applicable limit  % _9 9.50E-05 B. Tritium
1. Total release Ci 1.30E+02 1.84E+02 9.20E+00
2. Average diluted concentration uCi/ml 3.31E-07 6.31E-07 during period
3. Percent of applicable limit  % 3.31E-03 6.31E-03 C. Dissolved and entrained gases
1. Total release Ci 1.86E-03 2.OOE+01
2. Average diluted concentration uCi/mI 6.38E-12 during period
3. Percent of applicable limit  %

D. Gross alpha radioactivity

1. Total release Ci E. Vol. of waste released (prior to dilution) Liters 1.01E+08 7.50E+07 F. Vol. of dilution water used during period Liters 3.93E+11 2.92E+11 Note: Isotopes for which no value is given were not identified in applicable releases.

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Table 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES July - December 2011 Unit Quarter Quarter Est.Total A. Fission and activation products 3rd 4th Error, %

1. Total release (not including tritium, 2.51E-03 6.91E-04 9.90E+00 gases, alpha) Ci
2. Average diluted concentration uCi/mI 4.96E-12 1.39E-12 during period
3. Percent of applicable limit  % 4.96E-05 1.39E-05 B. Tritium
1. Total release Ci 8.78E+01 1.23E+02 9.20E+00
2. Average diluted concentration uCi/mI 1.73E-07 2.47E-07 during period
3. Percent of applicable limit  % 1.73E-03 2.47E-03 C. Dissolved and entrained gases
1. Total release Ci
2. Average diluted concentration uCi/ml during period
3. Percent of applicable limit  %

D. Gross alpha radioactivity

1. Total release Ci E. Vol. of waste released (prior ro dilution) Liters 1.26E+08 1.21E+08 F. Vol. of dilution water used during period Liters 5.06E+11 4.97E+11 Note: Isotopes for which no value is given were not identified in applicable releases.

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Table 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - CONTINUOUS AND BATCH RELEASES January-June 2011 Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 1st 2nd 1st 2nd chromium-51 Ci manganese-54 Ci iron-55 Ci iron-59 Ci cobalt-58 Ci 2.76E-03 cobalt-60 Ci zinc-65 Ci strontium-89 Ci strontium-90 Ci niobium-95 Ci molybdenum-99 Ci silver-lOrm Ci antimony-122 Ci antimony-124 Ci antimony-125 Ci iodine-131 Ci iodine-132 Ci iodine-135 Ci cesium-134 Ci cesium-136 Ci cesium-137 Ci barium/lanthanum-140 Ci cerium-141 Ci Te-123m Ci 9.71E-06 Zr-95 Ci Co-57 Ci Total for period (above) Ci 0.0E+00 2.77E-03 unidentified Ci Tritium I Ci 9.97E-02 6.90E-02 1.30E+02 1.84E+02 xenon-133 Ci 1.86E-03 xenon-135 Ci Note: Isotopes for which no value is given were not identified in applicable releases.

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Table 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - CONTINUOUS AND BATCH RELEASES July- December 2011 Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 3rd 4th 3rd 4th chromium-51 Ci manganese-54 Ci iron-55 Ci iron-59 Ci cobalt-58 Ci 2.51E-03 5.57E-04 cobalt-60 Ci 1.33E-04 zinc-65 Ci strontium-89 Ci strontium-90 Ci niobium-95 Ci molybdenum-99 Ci silver-110m Ci antimony-122 Ci antimony-124 Ci antimony-125 Ci iodine-131 Ci iodine-132 Ci iodine-135 Ci cesium-134 Ci cesium-136 Ci cesium-137 Ci barium/lanthanum-140 Ci cerium-141 Ci Te-123m Ci Zr-95 Ci Co-57 Ci Total for period (above) Ci _ 2.51E-03 6.90E-04 unidentified Ci Tritium Ci 5.22E-02 4.70E-02 8.77E+01 1.23E+02 Ixenon-133 _Ci xenon-135 Ci Note: Isotopes for which no value is given were not identified in applicable releases.

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Table 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January - December 2011 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL- (Not irradiated fuel)

1. Type of Waste Unit 12 month period Est. total Error (%)

a.Spent resins, filter sludges, m3 2.69E+00 7.00E+00 evaporator bottoms, etc. Ci 7.64E+01 1.40E+01

b. Dry compressible waste, m3 5.90E+02 7.OOE+00 contaminated equip, etc. Ci 2.58E-01 1.40E+01
c. Irradiated compnents, m3 None N/A control rods, etc. Ci m_3 4.OOE+01 7.00E+00
d. Other: None Ci 3.72E-01 1.40E+01
2. Estimate of major nuclide composition (by type of waste)

Isotope Unit a. b. d.

H-3  % 12.4 C-14  % 1.8 Cr-51  % 9.1 0.6 Mn-54  % 0.7 1.7 0.1 Fe-55  % 9.0 19.1 3.6 F-59  % 0.3 Co-57  % 0.2 0.1 Co-58  % 0.7 12.7 0.7 Co-60  % 8.4 17.1 4.2 Ni-59  % 0.4 Ni-63  % 76.5 18.9 62.8 Sr-90  % 0.3 Zr-95  % 7.5 0.2 Nb-95  % 10.6 0.2 Ag-i10m  % 0.4 ______

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2. Estimate of major nuclide composition (by type of waste) continued.

Sn-113  % 0.4 Sb-125  % 1.7 0.9 0.1 Cs-137  % 2.0 0.2 12.8 Ce-144  % 0.2 Eu-154  % 0.2 Pu-241  % 0.2

3. Solid Waste Disposition Number of Mode of Destination shipments Transportation 4 Sole Use Truck Energy Solutions 16 Sole Use Truck Studsvik B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Mode of shipments Transportation None N/A N/A 22

Table 4A Radiation Dose to Maximum Individual Receptor from Gaseous Effluents First Quarter 2011 (Units In milliRem)

All All  :-Adult Teen Child, Infant

,Gamma Air Beta Air THYRD THYRD THYRD THYRD N 3.66E-06 2.67E-06 2.25E-04 2.47E-04 3.40E-04 1.53E-04 NNE 3.07E-06 2.23E-06 1.89E-04 2.07E-04 2.85E-04 1.28E-04 NE 3.54E-06 2.57E-06 2.18E-04 2.39E-04 3.28E-04 1.48E-04 ENE 4.50E-06 3.27E-06 2.77E-04 3.03E-04 4.17E-04 1.87E-04 E 8.18E-06 5.95E-06 5.03E-04 5.52E-04 7.59E-04 3.41E-04 ESE 1.04E-05 7.57E-06 6.40E-04 7.02E-04 9.66E-04 4.34E-04 SE 6.30E-06 4.58E-06 3.87E-04 4.25E-04 5.84E-04 2.63E-04 SSE 2.59E-06 1.89E-06 1.59E-04 1.75E-04 2.41E-04 1.08E-04 S 4.54E-06 3.30E-06 2.79E-04 3.06E-04 4.21 E-04 1.89E-04 SSW 4.54E-06 3.30E-06 2.79E-04 3.06E-04 4.21 E-04 1.89E-04 SW 4.54E-06 3.30E-06 2.79E-04 3.06E-04 4.21E-04 1.89E-04 WSW 4.84E-06 3.52E-06 2.98E-04 3.26E-04 4.49E-04 2.02E-04 W 3.08E-06 2.24E-06 1.89E-04 2.08E-04 2.86E-04 1.28E-04 WNW 2.60E-07 1.89E-07 1.60E-05 1.76E-05 2.42E-05 1.09E-05 NW 8.54E-07 6.21 E-07 5.25E-05 5.76E-05 7.92E-05 3.56E-05 NNW 2.66E-06 1.94E-06 1.64E-04 1.80E-04 2.47E-04 1.11E-04 MAX. 1.04E-05 7.57E-06 6.40E-04 7.02E-04 9.66E-04 4.34E-04 23

Table 4A Radiation Dose to Maximum Individual Receptor from Gaseous Effluents Second Quarter 2011 (Units In milliRem)

All All 'Adult Teen -Child Infant Gamma Air Beta Air THYRD THYRD THYRD THYRD N 2.04E-05 3.29E-05 3.12E-03 4.15E-03 7.53E-03 1.50E-02 NNE 1.71 E-05 2.76E-05 2.61E-03 3.48E-03 6.31E-03 1.26E-02 NE 1.97E-05 3.18E-05 3.01E-03 4.01E-03 7.28E-03 1.45E-02 ENE 2.51E-05 4.04E-05 3.82E-03 5.10E-03 9.24E-03 1.84E-02 E 4.56E-05 7.35E-05 6.96E-03 9.27E-03 1.68E-02 3.35E-02 ESE 5.80E-05 9.35E-05 8.85E-03 1.18E-02 2.14E-02 4.26E-02 SE 3.51E-05 5.66E-05 5.35E-03 7.14E-03 1.29E-02 2.58E-02 SSE 1.44E-05 2.33E-05 2.20E-03 2.94E-03 5.33E-03 1.06E-02 S 2.53E-05 4.08E-05 3.86E-03 5.14E-03 9.33E-03 1.86E-02 SSW 2.53E-05 4.08E-05 3.86E-03 5.14E-03 9.33E-03 1.86E-02 SW 2.53E-05 4.08E-05 3.86E-03 5.14E-03 9.33E-03 1.86E-02 WSW 2.70E-05 4.35E-05 4.12E-03 5.49E-03 9.95E-03 1.98E-02 W 1.72E-05 2.77E-05 2.62E-03 3.49E-03 6.33E-03 1.26E-02 WNW 1.45E-06 2.34E-06 2.21 E-04 2.95E-04 5.35E-04 1.07E-03 NW 4.76E-06 7.67E-06 7.26E-04 9.68E-04 1.75E-03 3.49E-03 NNW 1.48E-05 2.39E-05 2.27E-03 3.02E-03 5.48E-03 1.09E-02 MAX. 5.80E-05 9.35E-05 8.85E-03 1.18E-02 2.14E-02 4.26E-02 24

Table 4A Radiation Dose to Maximum Individual Receptor from Gaseous Effluents Third Quarter 2011 (Units In milliRem)

All All Adult Teen Child' Infant,-.

Gamma Air Beta Air THYRD THYRD THYRD THYRD N 2.02E-06 1,23E-06 2.90E-04 3.18E-04 4.36E-04 1.91 E-04 NNE 1.70E-06 1.03E-06 2.43E-04 2.66E-04 3.66E-04 1.60E-04 NE 1.96E-06 1.19E-06 2.81E-04 3.07E-04 4.22E-04 1.84E-04 ENE 2.48E-06 1.51 E-06 3.56E-04 3.90E-04 5.36E-04 2.34E-04 E 4.52E-06 2.75E-06 6.48E-04 7.1OE-04 9.75E-04 4.26E-04 ESE 5.75E-06 3.50E-06 8.25E-04 9.03E-04 1.24E-03 5.42E-04 SE 3.48E-06 2.12E-06 4.99E-04 5.46E-04 7.50E-04 3.28E-04 SSE 1.43E-06 8.72E-07 2.05E-04 2.25E-04 3.09E-04 1.35E-04 S 2.51 E-06 1.53E-06 3.60E-04 3.94E-04 5.41 E-04 2.36E-04 SSW 2.51 E-06 1.53E-06 3.60E-04 3.94E-04 5.41E-04 2.36E-04 SW 2.51 E-06 1.53E-06 3.60E-04 3.94E-04 5.41 E-04 2.36E-04 WSW 2.67E-06 1.63E-06 3.84E-04 4.20E-04 5.77E-04 2.52E-04 W 1.70E-06 1.04E-06 2.44E-04 2.67E-04 3.67E-04 1.60E-04 WNW 1.44E-07 8.75E-08 2.06E-05 2.26E-05 3.1OE-05 1.36E-05 NW 4.72E-07 2.87E-07 6.77E-05 7.40E-05 1.02E-04 4.44E-05 NNW 1.47E-06 8.96E-07 2.11E-04 2.31E-04 3.17E-04 1.39E-04 MAX. 5.75E-06 3.50E-06 8.25E-04 9.03E-04 1.24E-03 5.42E-04 25

Table 4A Radiation Dose to Maximum Individual Receptor from Gaseous Effluents Fourth Quarter 2011 (Units In milliRem)

All All Adult Teen Child 'Infant, Gamma Air Beta Air THYRD THYRD THYRD THYRD N 2.1OE-06 1.23E-06 1.27E-04 1.39E-04 1.91E-04 8.34E-05 NNE 1.76E-06 1.03E-06 1.06E-04 1.17E-04 1.60E-04 6.99E-05 NE 2.03E-06 1.19E-06 1.23E-04 1.34E-04 1.84E-04 8.06E-05 ENE 2.57E-06 1.51 E-06 1.56E-04 1.71 E-04 2.34E-04 1.02E-04 E 4.68E-06 2.74E-06 2.84E-04 3.1OE-04 4.26E-04 1.86E-04 ESE 5.96E-06 3.49E-06 3.61 E-04 3.95E-04 5.42E-04 2.37E-04 SE 3.61E-06 2.11E-06 2.18E-04 2.39E-04 3.28E-04 1.43E-04 SSE 1.48E-06 8.69E-07 8.99E-05 9.84E-05 1.35E-04 5.90E-05 S 2.60E-06 1.52E-06 1.57E-04 1.72E-04 2.36E-04 1.03E-04 SSW 2.60E-06 1.52E-06 1.57E-04 1.72E-04 2.36E-04 1.03E-04 SW 2.60E-06 1.52E-06 1.57E-04 1.72E-04 2.36E-04 1.03E-04 WSW 2.77E-06 1.62E-06 1.68E-04 1.84E-04 2.52E-04 1.10E-04 W 1.76E-06 1.03E-06 1.07E-04 1.17E-04 1.60E-04 7.02E-05 WNW 1.49E-07 8.73E-08 9.03E-06 9.88E-06 1.36E-05 5.93E-06 NW 4.89E-07 2.86E-07 2.96E-05 3.24E-05 4.44E-05 1.94E-05 NNW 1.53E-06 8.93E-07 9.24E-05 1.01E-04 1.39E-04 6.07E-05 MAX. 5.96E-06 I 3.49E-06 3.61 E-04 3.95E-04 5.42E-04 2.37E-04 26

Table 4B Radiation Dose To Maximum Individual Receptor From Liquid Effluents for 2011 (Units In milliRem)

Adult Teen Child Infant First Quarter T. Body 5.88E-04 4.47E-04 4.43E-04 1.27E-04 GI-LLI 5.88E-04 4.47E-04 4.43E-04 1.27E-04 Thyroid 5.88E-04 4.47E-04 4.43E-04 1.27E-04 Second Quarter T. Body 1.05E-02 8.02E-03 7.96E-03 2.25E-03 GI-LLI 1.11E-02 8.36E-03 8.02E-03 2.25E-03 Thyroid 1.05E-02 7.96E-03 7.89E-03 2.25E-03 Third Quarter T. Body 3.20E-04 2.44E-04 2.43E-04 6.74E-05 GI-LLI 3.73E-04 2.78E-04 2.49E-04 6.74E-05 Thyroid 3.13E-04 2.38E-04 2.36E-04 6.73E-05 Fourth Quarter T. Body 4.45E-04 3.39E-04 3.36E-04 9.52E-05 GI-LLI 4.64E-04 3.51 E-04 3.38E-04 9.52E-05 Thyroid 4.42E-04 3.36E-04 3.33E-04 9.52E-05 27

TABLE 5 Groundwater Monitoring Wells Location Sample Date Tritium (uCilml)

GWO1: Warehouse Access Road (Control) 02/09/11

  • 03/03/11
  • 06/22/11
  • 08/30/11
  • 12/08/11
  • GW03: Screenhouse West, South Well 02/09/11 3.53E-07 02/18/11 1.82E-06 GW04: Screenhouse West, North Well 01/21/11
  • 02/09/11 3.49E-07 06/29/11
  • 07/21/11
  • 08/30/11
  • 09/29/11
  • 10/27/11
  • 11/29/11
  • 12/14/11
  • GW05: Screenhouse East, South (15._"______ 02/09/11
  • 06/22/11
  • 08/30/11
  • 12/08/11
  • GW06: Screenhouse East, Middle (20.0') 02/09/11
  • 06/22/11
  • 07/21/11
  • 08/30/11
  • 12/08/11
  • GW07: Screenhouse East, North (24.0') 02/09/11
  • 03/03/11
  • 03/18/11
  • 04/01/11
  • 05/06/11
  • 06/22/11
  • 08/30/11
  • 12/08/11
  • GW08: All Volatiles Treatment Building 01/21/11
  • 02/09/11
  • 06/29/11
  • 09/29/11
  • 10/27/11
  • 11/29/11
  • 12/08/11
  • 03/03/11 28

GWl 0: Technical Support Center, South GWI 1: Contaminated Service Building, SE (24.0')

t Groundwater Monitoring Wells (continued)

/

06/22/11 o__08/30/11 12/08/11*

02/09/11 4.36E-07 02/18/11 9.66 E-07 03/03/11*

06/22/11*

_ 0_8/30/1__

_1_ _

12/08/11 *

Table 6 2011 Offsite Dose Due to Carbon-14 in Gaseous and Liquid Effluents R E Ginna Nuclear Power Plant 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 2011. Kunz further determined the chemical form of the Carbon-14 at Ginna to be approximately 10% C02.

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 EFPY agrees with the Kunz data.

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

a. 6.8 Curies of C-14 released to atmosphere in 2011
b. Release was consistent throughout the year. There was an outage in 2011, however it has little or no impact on the C-14 effluents.
c. 10% of the C-14 was in the chemical form of C02, which is the only dose contributor. The bulk of C-14 in the chemical form of methane (CH4) would exhibit high upward velocity due to its low density relative to air. In addition 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 and vegetation ingestion.
g. Critical receptor is child at the site boundary in the ESE direction.

MAXIMUM DOSE VALUES DUE TO C-14 IN GASEOUS EFFLUENTS IN 2010 Organ Age mRemlyr RG-1.109 Bone Child 1.94E-02 RG-1.109 T.Body/Other Child 3.86E-03 30

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-7 uCi/cc.
c. 2.69E6 liters of liquid waste were released in 2011 with total dilution flow of 1.69E12 liters.
d. Average diluted concentration of C-14 released was 9.55E-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. Critical receptor is teen for both potable water and fish pathways.

MAXIMUM DOSE VALUES DUE TO C-14 IN LIQUID EFFLUENTS IN 2010 Organ Age mRemlyr RG-1.109 Bone Teen 2.57E-04 RG-1.109 T.Body/Other Teen 5.12E-05 31

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