Text

Annual Radioactive Effluent Release Report, Offsite Dose Calculation Manual, and Annual Radiological Environmental Operating Report
	ML14140A077
Person / Time
Site:	Ginna
Issue date:	05/13/2014
From:	Harding T; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	WPLNRC-1002870
	Download: ML14140A077 (207)
	v • d • e

WPLNRC-1002870 R.E. Ginna Nuclear Power Plant 1503 Lake Rd.

Eo G Exeln G

e nera t ionwww.exeloncorp~com Ontario, NY 14519-9364 May 13, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 R.E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 NRC Docket No. 50-244

Subject:

Annual Radioactive Effluent Release Report, Offsite Dose Calculation Manual, and Annual Radiological Environmental Operating Report R.E. Ginna Nuclear Power Plant, LLC, is pleased to submit the attached Annual Radioactive Effluent Release Report for 2013 and the latest revision of the Offsite Dose Calculation Manual (ODCM) in accordance with 10 CFR 50.36a(a)(2) and Technical Specification Sections 5.6.3 and 5.5.1c. Also attached is the Annual Radiological Environmental Operating Report for 2013 in accordance with Technical Specification Section 5.6.2.

There are no regulatory commitments contained in this submittal. Should you have any other questions regarding this submittal, please contact me at 585-771-5219.

Respectfully, 4,

Thomas L. Harding Director - Licensing R.E. Ginna Nuclear Power Plant

May 13, 2014 U.S. Nuclear Regulatory Commission Page 2 TLH/JPO Attachments:

1) Annual Radioactive Effluent Release Report, January 1, 2013 - December 31, 2013

2) Offsite Dose Calculation Manual (ODCM), Revision 28

3) Annual Radiological Environmental Operating Report, January 1, 2013 -

December 31, 2013 cc: NRC Regional Administrator, Region I NRC Project Manager, Ginna NRC Senior Resident Inspector, Ginna NYS Office of Emergency Management Division of Homeland Security Emergency Services 1220 Washington Avenue, State Office Campus Public Safety Building #22, Suite 101 Albany, NY 12226-2251 Attn.: Ted Fisch, Chief of Radiological Preparedness 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.: Stanley P. Focht INPO 700 Galleria Parkway Atlanta, GA 30339-5957 Frederick J. Rion, Emergency Preparedness Administrator 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, 2013- DECEMBER 31, 2013 R.E. Ginna Nuclear Power Plant, LLC May 13, 2014

-Exelon Generation ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT:

JANUARY 1, 2013 - DECEMBER 31, 2013 MAY 2014 1111111***********11111111111111 111111 11111111111111 1111111111111111111111111111111111 R.E. Ginna Nuclear Power Plant 1503 Lake Road Ontario, New York 14519

TABLE OF CONTENTS 1.0 Introduction ......................................................................................................... 1 2.0 Supplem ental Inform ation ................................................................................. 1 2.1 Regulatory Lim its ................................................................................... 1 2.2 Effluent Concentration Lim its ................................................................ 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 Sum mary of Gaseous Radioactive Effluents .............................................. 4 4.0 Sum mary of Liquid Radioactive Effluents ................................................... 4 5.0 Solid Waste ..................................................................................................... 5 6.0 Low er Lim it of Detection ................................................................................. 5 7.0 Radiological Im pact ........................................................................................ 5 7.1 Total Dose ............................................................................................. 5 8.0 M eteorological 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 Gaseous Effluents ................................................................................ 9 16.2 Liquid Effluents ..................................................................................... 9 R.E. Ginna Nuclear Power Plant ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

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 M onitoring W ells ................................................................. 25 Table 6 Offsite Dose due to Carbon-14 in Gaseous and Liquid Effluents .............. 28 ARERR R.E. Ginna Nuclear Power Plant iiii ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

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, 2013 through December 31, 2013, 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 01/01/2013 - 12/31/2013

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 01/01/2013 - 12/31/2013

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 2013 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 and the total volume of effluents released.

2.5 Batch Releases 2.5.1 Liquid

1. Number of batch releases: 5.70 E+01

2. Total time period for batch releases (Minutes): 7.56 E+03

3. Maximum time period for a batch release (Minutes): 3.76 E+02

4. Average time period for batch releases (Minutes): 1.33 E+02

5. Minimum time period for a batch release: 3.00 E+01

6. Average effluent release flowrate into the discharge canal 2.92E+02 (Liters per Minute):

7. Average dilution flowrate of discharge canal during effluent 1.20E+06 releases (Liters per Minute):

R.E. Ginna Nuclear Power Plant 3 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

2.5.2 Gaseous

1. Number of batch releases: 3.80 E+01

2. Total time period for batch releases (Minutes): 5.56 E+05

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

4. Average time period for batch releases (Minutes): 1.46 E+04

5. Minimum time period for a batch release (Minutes): 1.00 E+01 2.6 Abnormal Releases On April 6, 2013, Chemistry staff noted a gradual decrease in the 'A' Gas Decay Tank pressure, lowering approximately 4 psig per day over a one week period.

The decrease in pressure in the 'A' Gas Decay Tank indicated a potential release of radioactivity to the Auxiliary Building, which ultimately is routed through the Plant Vent to the atmosphere. Although a radiation monitor is installed on the plant vent with a set point designed to provide alarm if a site boundary dose limit is approached, batch releases are required by regulation to be monitored by a sample and analysis prior to release so that the radioactivity can be identified and included in offsite dose calculations. To account for the radioactivity released during this event, a conservative estimate of volume, radioactivity, and duration was calculated in accordance with section 2.5 of the site ODCM.

Ultimately, the manual calculation determined 2.73E-04 uCi/cc of Xe-1 33 (pre-dispersion concentration) was released as a result of this event. This activity was included in the annual gaseous effluent releases by manually adding it to Gas Release Permit G-2013042.

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 01/01/2013 - 12/31/2013

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:

1. On January 28, 2013, the LLD for Molybdenum-99 (Mo-99) and Iodine-1 31 (1-131) was not met during the analysis of the particulate sample collected from the R13 Radiation Monitor (i.e., Plant Vent Particulate Radiation Monitor).

Additionally, the LLD for Iodine-131 (1-131) was not met during the analysis of the iodine sample collected from the R10B Radiation Monitor (i.e., Plant Vent Iodine Radiation Monitor). The required volume requirements were not obtained due to the limited flow capacity of the temporary equipment being used while these monitors were out of service.

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:

R.E. Ginna Nuclear Power Plant 5 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

0 < 25 mrem total body or any organ and; a < 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. 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: 12.1 mRem (Sum of 12.1 mrem for direction radiation, 4.44E-04 (Total Body Liquid Dose), 5.89E-03 (Total Body Gas Dose).

" Maximum Annual Organ Dose: 2.564E-03 mrem (Teenager Liver)

Maximum Annual Thyroid Dose: 2.534E-03 mrem (Teenager) 8.0 METEOROLOGICAL DATA The annual summary of hourly meteorological data collected during 2013 is not included with this report, but can be made available upon request.

9.0 LAND USE CENSUS CHANGES In September 2013, 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). However, this facility did not initiate operations during 2013. Once operational, Ginna Chemistry staff will begin collecting raw water samples as part of its Radiological Environmental Monitoring Program (REMP).

Single family home construction was observed west of the plant along Shoreline Boulevard.

R.E. Ginna Nuclear Power Plant 6 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

The Summer Place Subdivision, located west of the plant near the intersection of Lake Road and Roder Parkway, continued to add new residential homes.

The Cool Breeze Subdivision, located west of the plant of the plant near the intersection of Lakeside Road and Boston Road, continued to add new residential 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 No changes were made to the ODCM during 2013. R.E. Ginna continued to operate under Revision 27 of the ODCM, which was implemented May 3, 2011. 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 There were no significant changes to the Radwaste Treatment Systems during the reporting period.

13.0 INOPERABLE MONITORS There were no occurrences satisfying the requirement stated in Section 3.3 and Table 3.3-1, Action 1 of the ODCM for reporting inoperable radiation monitors. No occurrences surpassed 30 days of inoperability. No monitors were inoperable for greater than 7 days and less than 30 days.

14.0 CHANGES TO PREVIOUS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTS No modifications are required to previously submitted Annual Radioactive Effluent Release Reports at this time.

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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 2013, 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)

GW1 2: West of Orchard Access Road*

GW1 3: North of Independent Spent Fuel Storage Installation (ISFSI)*

GW14: South of Canister Preparation Building*

GW1 5: 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 2013 are presented in Table 5.

All samples collected during 2013, 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 2013. Kunz further determined the chemical form of the Carbon-14 at Ginna to be approximately 10% Carbon Dioxide (C0 2 ).

R.E. Ginna Nuclear Power Plant 8 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

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 2013.

b. There was no refueling outage in 2013. Accordingly, gaseous effluents were assumed to be consistent throughout the year. However, it has little or no impact on the C-14 effluents.

c. 10% of the C-14 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/m3 .

e. Dose calculations and dose factors are from Regulatory Guide 1.109 methodology.

f. Pathways considered were inhalation, milk consumption, and vegetation ingestion.

g. The critical receptor is a child at the site boundary in the ESE direction.

See Table 6 for an estimate of Carbon-14 in gaseous effluents during 2013.

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-1 4 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-1 4 released was 1.58E-1 3 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 01/01/2013 - 12/31/2013

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 2013.

R.E. Ginna Nuclear Power Plant 10 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 2013 Effluent Type Units 1V Quarter 2"d Quarter 3'4 Quarter 41h Quarter Est. Total Error, %

A. Fission & Activation Gases

1. Total release Ci 5.73E-01 1.0OE+00 1.12E+00 4.92E-01 1.50E+01

2. Average release rate for period uCi/sec 7.27E-02 1.27E-01 1.42E-01 6.24E-02

3. Percent of technical specification limit % 1.15E-05 2.02E-05 2.25E-05 9.90E-06 B. lodines

1. Total iodine-131 Ci 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 1.50E+01

2. Average release rate for period uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

3. Percent of technical specification limit % 0.OOE+O0 0.OOE+00 0.OOE+00 O.OOE+00 C. Particulates

1. Particulates with half-lives > 8days Ci O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+O0 1.50E+01

2. Average release rate for period uCi/sec O.OOE+00 0.1OE+00 O.OOE+O0 O.OOE+0O

3. Percent of technical specification limit % O.OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+00

4. Gross alpha radioactivity Ci O.OOE+00 O.OOE+00 O.00E+O0 0.OOE+00 D. Tritium

1. Total release Ci 1.73E+01 2.78E+01 2.40E+01 2.63E+01 9.20E+00

2. Average release rate for period uCi/sec 2.19E+00 3.53E+00 3.05E+00 3.34E+00

3. Percent of technical specification limit % 2.56E-06 4.13E-06 3.57E-06 3.91E-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 01/01/2013 - 12/31/2013

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - CONTINUOUS AND BATCH RELEASES 2013 Nuclides Units Continuous Mode _____ Batch Mode Released I"~Quarter 2" Qarer 3 rd Quarter 4!h uarer 151 Quarter 2"6 uarer 3rdQuarter 4!h uarer

1. Fission Gases______________

Argon-41 Ci ______ _____4.74E-02 7.93E-02 8.03E-02 7.80E-02 Krypton-85 Ci _____ ___________

Krypton-85m Ci __________ _____ ___________

Krypton-87 Ci _____

Krypton-88 Ci _____ _____

Xenon-131m Ci Xenon-133 Ci 2.32E-01 4.05E-01 4.65E-01 1.65E-01 Xenon-133m Ci _____

Xenon-135 Ci ______7.19E-03 1.69E-02 1.61E-02 2.78E-03 Xenon-135m Ci Xenon-138 Ci ______ _____ __________ _____

Total for period Ci 2.87E-01 5.01E-01 5.61E-01 8.46E-01

2. lodines Iodine-131 Ci ______ _____ _____ _____ _____ _____

Iodine-132 Ci _____ _____ _____

Iodine-133 Ci _____ _____ ___________

Iodine-135 Ci _____ _____ _____ ______ _____ _____ ______

Total for period Ci ______ ______ ____________ ______ ______

ARERR R.E. Ginna Nuclear Power Plant 12 12 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

TABLE 1B (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - CONTINUOUS AND BATCH RELEASES 2013 Nuclides Units Continuous Mode Batch Mode Released I" Quarter 2 nd Quarter Id e Quarter I"ua Quarter 2Quarter 3 Quarter Quar

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 8.62E+00 1.37E+01 1.05E+01 1.30E+01 2.43E-02 1.93E-01 1.56E+00 2,16E-01 Note: Isotopes for which no value is given were not identified in applicable releases.

ARERR R.E. Ginna Nuclear Power Plant 13 13 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 2013 Effluent Type Units 1V' Quarter 2 nd Quarter 3 d Quarter 4 th Quarter Est. Total Error, %

A. Fission & Activation Products

1. Total Release (not including tritium, gases, Ci 3.69E-04 7.OOE-05 0.OOE+00 4.16E-06 9.90E+00 alpha)

2. Average Diluted concentration uCi/ml 9.05E-13 1.41E-13 0.0OEe00 8.59E-15

3. Percent of applicable limit % 9.05E-06 1.41E-06 0.OOE+00 8.59E-08 B. Tritium

1. Total Release Ci 2.65E+1 1.95E+01 3.OOE+01 3.29E+01 9.20E+00

2. Average Diluted Concentration uCi/ml 6.51E-08 3.93E-08 5.80E-08 6.79E-08

3. Percent of applicable limit % 6.51E-04 3.93E-04 5.80E-04 6.79E-04 C. Dissolved and Entrained Gases

1. Total Release Ci O.00E+00 O.0OE+00 0.OOE+00 0.OE+00 9.90E+00

2. Average Diluted Concentration uCi/ml 0.OOE+00 0.OOE+0O 0.OOE+00 0.OOE+00

3. Percent of applicable limit % O.OOE+00 O0.OOE+00 O.OOE+O0 0.00E400 D. Gross Alpha Radioactivity

1. Total release Ci 0.OOE+00 O.00E+00 0.OOE+00 0.OOE+00 E. Vol. of Waste Released (prior to dilution) Liters 1.07E+08 1.16E+08 1.24E+08 1.16E+08 F. Vol. of Dilution Water Used During Period Liters 4.07E+11 4.97E+11 5.16E+11 4.85E+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 2013 Nuclides Released I Units II Continuous Mode Batch Mode V Quarter 1 2" Quarter 3' Quarter 1-41" Quarter is Quarter 2"a Quarter Y3 Quarter 4" Quarter Fission & Activation Products Chromium-51 Ci Manganese-54 Ci Iron-55 Ci Iron-59 Ci Cobalt-57 Ci Cobalt-58 Ci 2.06E-04 2.82E-05 Cobalt-60 Ci Zinc-65 Ci Strontium-89 Ci Strontium-90 Ci Niobium-95 Ci Molybdenum-99 Ci Zirconium-95 Ci Silver-110m Ci Antimony-122 Ci Tellurium-123m Ci 1.62E-04 4.18E-05 Antimony-124 Ci Antimony-125 Ci Iodine-131 Ci Iodine-132 Ci Tellurium-132 Ci Iodine-135 Ci Cesium-134 Ci Cesium-136 Ci Cesium-137 Ci 4.16E-06 R.E. Ginna Nuclear Power Plant 15 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

TABLE ZB (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - CONTINUOUS AND BATCH RELEASES 2013 Nuclides Released Units Continuous Mode Batch Mode I"Quarter 2"' Quarter 3ai Quarter 4' Quarter 1" Quarter 2"° Quarter 3" Quarter 4,n Quarter Barium/Lanthanum-140 Ci Cerium-141 Ci Total (above) Ci 3.68E-04 7-00E-05 4.16E-06 Unidentified (from total Ci above)

Tritium Hydrogen-3 Ci I 5.16E-02 1.05E-01 1.22E-01 4.25E-02 2.64E+01 1.94E+01 2.98E+01 3.29E+01 Dissolved And Entrained Gases Xenon-133 Ci_

Xenon-135 Ci Note: Isotopes for which no value is given were not identified in applicable releases.

AR ER R R.E. Ginna Nuclear Power Plant 16 16 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 2013 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

1. Type of Waste JUnits 12 Month Period Est. total Error (%)

3 A - Spent Resins, Filter Sludge, Evaporator m 4.55E+01 --

Bottoms, Etc. Ci 6.11E+01 --

3 B - Dry Active Waste (DAW), Contaminated m 3.55E+02 --

Equipment, Etc. Ci 4.66E+00 --

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

ARERR R.E. Ginna Nuclear Power Plant 17 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

TABLE 3 (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 2013

2. Estimate of Major Nuclide Composition By Type of Waste Isotope Unit Type A Type B Type C Type D Co-58 % 2.2 15.1 Co-60 % 35.0 13.6 Cr-51 %

Cs-137 % 1.6 1.6 Fe-55 % 33.5 3.2 Mn-54 % 2.4 2.4 Nb-95 %

Ni-63 % 21.3 60.4 Sb-125 % 2.0 Zr-95 %

Total % 96.0 98.3 Note: Blank cells indicate nuclide composition not at significant levels.

ARERR R.E. Ginna Nuclear Power Plant 18 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

TABLE 3 (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 2013

of Shipments Mode of Type of Container Solidification Processing Destination

__fShipments Transportation Agent ProcessingDestination 1 Sole Use Truck High Integrity Containers (HICs) None Used Onsite EnergySolutions, Barnwell, SC 2 Sole Use Truck High Integrity Containers (HICs) None Used Onsite Studsvik Processing Facility, Erwin, TN Studsvik ProcessingTNFacility, Metal Containers None Used Onsite Mempis, 9 Sole Use Truck Memphis, TN 1 Sole Use Truck Metal Containers None Used Onsite EnergySolutions, BC 1 Sole Use Truck Metal Containers None Used Onsite Toxco, Inc.

2 Sole Use Truck Metal Containers None Used Onsite Duratek Services, Inc.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

of Shipments Mode of Destination Transportation None N/A N/A ARERR R.E. Ginna Nuclear Power Plant 19 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

TABLE 4A Radiation Dose to Maximum Individual Receptor from Gaseous Effluents First Quarter 2013 (Units In milliRem)

All All Adult Teen Child Infant Gamma Air Beta Air THYRD THYRD THYRD THYRD N 1.46E-06 1.13E-06 1.08E-04 1.18E-04 1.63E-04 2.39E-08 NNE 1.22E-06 9.47E-07 9.06E-05 9.92E-05 1.36E-04 2.OOE-08 NE 1.41E-06 1.09E-06 1.04E-04 1.14E-04 1.57E-04 2.31E-08 ENE 1.79E-06 1.39E-06 1.33E-04 1.45E-04 2.OOE-04 2.93E-08 E 3.25E-06 2.52E-06 2.41E-04 2.64E-04 3.63E-04 5.33E-08 ESE 4.14E-06 3.21E-06 3.07E-04 3.36E-04 4.62E-04 2.02E-04 SE 2.50E-06 1.94E-06 1.86E-04 2.04E-04 2.80E-04 4.11E-08 SSE 1.03E-06 7.99E-07 7.65E-05 8.38E-05 1.15E-04 1.69E-08 S 1.81 E-06 1.40E-06 1.34E-04 1.47E-04 2.01E-04 2.96E-08 SSW 1.81E-06 1.40E-06 1.34E-04 1.47E-04 2.01E-04 2.96E-08 SW 1.81E-06 1.40E-06 1.34E-04 1.47E-04 2.01E-04 2.96E-08 WSW 1.93E-06 1.49E-06 1.43E-04 1.56E-04 2.15E-04 3.16E-08 W 1.23E-06 9.50E-07 9,09E-05 9.96E-05 1.37E-04 2.01E-08 WNW 1.04E-07 8.03E-08 7.68E-06 8.41E-06 1.16E-05 1.70E-09 NW 3.39E-07 2.63E-07 2.52E-05 2.76E-05 3.79E-05 5.56E-09 NNW 1.06E-06 8.22E-07 7.86E-05 8.61E-05 1.18E-04 1.74E-08 MAX. 4.14E-06 3.21E-06 I 3.07E-04 I 3.36E-04 4.62E-04 I 2.02E-04 Note: Shaded regions indicate areas over Lake Ontario.

R.E. Ginna Nuclear Power Plant 20 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

TABLE 4A (Continued)

Radiation Dose to Maximum Individual Receptor from Gaseous Effluents Second Quarter 2013 (Units In milliRem)

All All Adult Teen Child Infant Gamma Air Beta Air THYRD THYRD THYRD THYRD N 2.48E-06 1.97E-06 1.74E-04 1.91E-04 2.62E-04 1.14E-04 NNE 2.08E-06 1.65E-06 1.46E-04 1.60E-04 2.19E-04 9.58E-05 NE 2.39E-06 1.90E-06 1.68E-04 1.84E-04 2.53E-04 1.10E-04 ENE 3.04E-06 2.42E-06 2.14E-04 2.34E-04 3.21E-04 1.40E-04 E 5.53E-06 4.40E-06 3.89E-04 4.26E-04 5.85E-04 2.55E-04 ESE 7.04E-06 5.60E-06 4.94E-04 5.42E-04 7.44E-04 3.25E-04 SE 4.26E-06 3.39E-06 2.99E-04 3.28E-04 4.50E-04 1.96E-04 SSE 1.75E-06 1.39E-06 1.23E-04 1.35E-04 1.85E-04 8.09E-05 S 3.07E-06 2.44E-06 2.16E-04 2.36E-04 3.24E-04 1.42E-04 SSW 3.07E-06 2.44E-06 2.16E-04 2.36E-04 3.24E-04 1.42E-04 SW 3.07E-06 2.44E-06 2.16E-04 2.36E-04 3.24E-04 1.42E-04 WSW 3.27E-06 2.60E-06 2.30E-04 2.52E-04 3.46E-04 1.51E-04 W 2.08E-06 1.66E-06 1.46E-04 1.60E-04 2.20E-04 9.61E-05 WNW 1.76E-07 1.40E-07 1.24E-05 1.35E-05 1.86E-05 8.12E-06 NW 5.77E-07 4.59E-07 4.05E-05 4.44E-05 6.1OE-05 2 66AE-05 NNW 1.80E-06 1.43E-06 1.27E-04 1.39E-04 1.90E-04 8.31E-05 MAX. 7.04E-06 i 5.60E-06 I 4.94E-04 I 5.42E-04 I 7.44E-04 3.25E-04 Note: Shaded regions indicate areas over Lake Ontario.

R.E. Ginna Nuclear Power Plant 21 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

TABLE 4A (Continued)

Radiation Dose to Maximum Individual Receptor from Gaseous Effluents Third Quarter 2013 (Units In milliRem)

All All Adult Teen Child Infant Gamma Air Beta Air THYRD THYRD THYRD THYRD N 2.56E-06 2.15E-06 2.66E-04 2.91E-04 4.00E-04 1.75E-04 NNE 2.14E-06 1.80E-06 2.23E-04 2.44E-04 3.35E-04 1.46E-04 NE 2.47E-06 2.07E-06 2.57E-04 2.81E-04 3.86E-04 1.69E-04 ENE 3.14E-06 2.64E-06 3.26E-04 3.57E-04 4.91E-04 2.14E-04 E 5.71E-06 4.79E-06 5.93E-04 6.50E-04 8.93E-04 3.90E-04 ESE 7.26E-06 6.1OE-06 7.55E-04 8.27E-04 1.14E-03 4.96E-04 SE 4.39E-06 3.69E-06 4.57E-04 5.OOE-04 6.87E-04 3.00E-04 SSE 1.81 E-06 1.52E-06 1.88E-04 2.06E-04 2.83E-04 1.23E-04 S 3.17E-06 2.66E-06 3.29E-04 3.61E-04 4.95E-04 2.16E-04 SSW 3.17E-06 2.66E-06 3.29E-04 3.61 E-04 4.95E-04 2.16E-04 SW 3.17E-06 2.66E-06 3.29E-04 3.61E-04 4.95E-04 2.16E-04 WSW 3.38E-06 2.84E-06 3.51E-04 3.85E-04 5.28E-04 2.31E-04 W 2.15E-06 1.81E-06 2.23E-04 2.45E-04 3.36E-04 1.47E-04 WNW 1.82E-07 1.53E-07 1.89E-05 2.07E-05 2.84E-05 1.24E-05 NW 5.95E-07 5.OOE-07 6.19E-05 6.78E-05 9.32E-05 4.07E-05 NNW 1.86E-06 1.56E-06 1.93E-04 2.12E-04 2.91E-04 1.27E-04 MAX. 7.26E-06 6.I*1OE-06 7.55E-04 8.27E-04 1.14E-03 4.96E-04 Note: Shaded regions indicate areas over Lake Ontario.

R.E. Ginna Nuclear Power Plant 22 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

TABLE 4A (Continued)

Radiation Dose to Maximum Individual Receptor from Gaseous Effluents Fourth Quarter 2013 (Units In milliRem)

All All Adult Teen Child Infant Gamma Air Beta Air THYRD THYRD THYRD THYRD N 2.14E-06 1.18E-06 1.65E-04 1.80E-04 2.48E-04 1.08E-04 NNE 1.79E-06 9.91E-07 1.38E-04 1.51 E-04 2.08E-04 9.07E-05 NE 2.07E-06 1.14E-06 1.59E-04 1.74E-04 2.39E-04 1.04E-04 ENE 2.63E-06 1.45E-06 2.02E-04 2.21 E-04 3.04E-04 1.33E-04 E 4.78E-06 2.64E-06 3.68E-04 4.03E-04 5.53E-04 2.42E-04 ESE 6.08E-06 3.36E-06 4.68E-04 5.13E-04 7.04E-04 3.07E-04 SE 3.68E-06 2.03E-06 2.83E-04 3.10E-04 4.26E-04 1.86E-04 SSE 1.51E-06 8.37E-07 1.17E-04 1.28E-04 1-75E-04 7.65E-05 S 2.65E-06 1.46E-06 2.04E-04 2.23E-04 3.07E-04 1.34E-04 SSW 2.65E-06 1.46E-06 2.04E-04 2.23E-04 3.07E-04 1.34E-04 SW 2.65E-06 1.46E-06 2.04E-04 2.23E-04 3.07E-04 1.34E-04 WSW 2.83E-06 1.56E-06 2.18E-04 2.38E-04 3.27E-04 1.43E-04 W 1.80E-06 9.95E-07 1.38E-04 1.52E-04 2.08E-04 9.10E-05 WNW 1.52E-07 8.40E-08 1.17E-05 1.28E-05 1.76E-05 7.68E-06 NW 4.99E-07 2.76E-07 3.84E-05 4.20E-05 5.77E-05 2.52E-05 NNW 1.56E-06 8.60E-07 1.20E-04 1.31 E-04 1.80E-04 7.87E-05 MAX. 6.08E-06 3.36E-06 4.68E-04 5.13E-04 7.04E-04 3.07E-04 Note: Shaded regions indicate areas over Lake Ontario.

R.E. Ginna Nuclear Power Plant 23 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

TABLE 4B Radiation Dose To Maximum Individual Receptor From Liquid Effluents for 2013 (Units in milliRem)

ARERR R.E. Ginna Nuclear Power Plant 24 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

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

GW01: Warehouse Access Road (Control) 03/07/2013

06/20/2013

08/13/2013

12/03/2013

GW03: Screenhouse West, South Well 10/15/2013

11/0712013

12/03/2013

GW04: Screenhouse West, North Well 02/01/2013

02/15/2013

03/07/2013

04/19/2013

05/21/2013 06/20/2013 071/25/2013 08/14/2013 09/19/2013

12/03/2013

GW05: Screenhouse East, South (15.5') 03/07/2013

06/20/2013

08/13/2013

12/03/2013

R.E. Ginna Nuclear Power Plant 25 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

TABLE 5 (Continued)

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

GW06: Screenhouse East, Middle (20.0') 03/07/2013 "

06/20/2013 08/13/2013 12/03/2013

GW07: Screenhouse East, North (24.0') 03/07/2013

06/20/2013

08/13/2013

12/03/2013 GW08: All Volatiles Treatment Building 01/30/2013

02/15/2013

03/07/2013

04/19/2013

05/21/2013 06/20/2013 07/25/2013 08/13/2013

09/19/2013

10/15/2013 11/07/2013

12/20/2013

GW1O: Technical Support Center, South 03/07/2013

06/20/2013

08/13/2013

12/03/2013

R.E. Ginna Nuclear Power Plant 26 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

TABLE 5 (Continued)

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

GW1 1: Southeast of Contaminated Service Building (CSB) 0310712013

06/20/2013

08/13/2013

12/03/2013 GW12: West of Orchard Access Road 12/03/2013 GW13: North of Independent Spent Fuel Storage Installation (ISFSI) 12/03/2013

GW14: South of Canister Preparation Building 12/0312013

GW1 5: West of Manor House 12/03/2013 GW16: Southeast of Manor House 12/03/2013 *

- Activity not detected (Tritium)

R.E. Ginna Nuclear Power Plant 27 ARERR Docket No. 50-244 01/01/2013 - 12/31/2013

TABLE 6 Offsite Dose Due to Carbon-14 in Gaseous and Liquid Effluents MAXIMUM DOSE VALUES DUE TO C-14 IN GASEOUS EFFLUENTS IN 2013 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 2013 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 01/01/2013 - 12/31/2013

ATTACHMENT 2 OFFSITE DOSE CALCULATION MANUAL (ODCM)

REVISION 28 R.E. Ginna Nuclear Power Plant, LLC May 13, 2014

ODCM CENG a joint venture of OConstellation Energy, J eF R. E. Ginna Nuclear Power Plant Offsite Dose Calculation Manual (ODCM)

Revision 28 Date: 1/23 // y Reviewed By:

RETS Manager Reviewed By: ,N, C' 6L General Supervisor-Chemistry Reviewed By/*0O002 Date: /& //V PORC Meeting Number Approved By: __________ Date: //5/ '

Plant General Manager Effective Date: February 5, 2014 R. E. Ginna Nuclear Power Plant ODCM-1 Rev. 28

ODCM TABLE OF CONTENTS Operability and Surveillance Requirements ............................................................................ 3 D efi n itio n s ..................................................................................................................................... 4 List o f A c ro n y ms ........................................................................................................................... 8 1.0RADIOACTIVE LIQUID EFFLUENTS ................................................................................ .9 1.1 Concentration (10 CFR 20) ................................................................................. 9 1.2 Dose (10 CFR 50 Appendix 1)............................................................................ 10 1.3 Total Dose (40 CFR 190) ................................................................................... 12 1.4 Liquid Effluents Release Points .......................................................................... 17 1.5 Liquid Effluents Monitor Setpoints ...................................................................... 18 1.6 Liquid Effluent Release Concentrations ............................................................ 21 1.7 Liquid Effluent Dose .......................................................................................... 22 2.0 RADIOACTIVE GASEOUS EFFLUENTS ..................................................................... 25 2.1 DELETED ............................................................................................................... 25 2.2 Dose Rate ............................................................................................................. 26 2.3 Dose (10 CFR 50, Appendix I) .......................................................................... 28 2.4 Total Dose (40 CFR 190) ................................................................................... 31 2.5 Gaseous Effluent Release Points ........................................................................... 35 2.6 Gaseous Effluent Monitor Setpoints .................................................................... 36 2.7 Gaseous Effluent Dose Rate ............................................................................. 42 2.8 Gaseous Effl uent Doses ......................................................................................... 44 3.0 RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION .............................. 49 3.1 Liquid Effluent Monitors .......................................................................................... 49 3.2 Gaseous Effluent Monitors ................................................................................. 54 3.3 Radiation Accident Monitoring Instrumentation ................................................. 60 3.4 Area Radiation Monitors .................................................................................... 64 4.0 RADW ASTE TREATM ENT .......................................................................................... 66 4.1 Liquid Radwaste Treatment System ...................................................................... 66 4.2 Gaseous Radwaste Treatment System .................................................................. 68 4.3 Solid Radwaste System ..................................................................................... 70 4.4 Configuration Changes ...................................................................................... 71 4.5 Process Control Program ................................................................................... 72 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING .................................................. 73 5.1 Monitoring Program ................................................................................................ 73 5.2 Environmental Monitor Sample Locations .......................................................... 78 5.3 Land Use Census ............................................................................................... 96 5.4 Interlaboratory Comparison Program ................................................................. 98 6.0 REPORTING REQUIREMENTS .................................................................................... 99 6.1 Annual Radiological Environmental Operating Report ........................................... 99 6.2 Annual Radioactive Effl uent Release Report ....................................................... 100 6.3 Special Reports .................................................................................................... 102

7.0 REFERENCES

................................................................................................................. 104 R. E. Ginna Nuclear Power Plant ODCM-2 Rev. 28

ODCM OPERABILITY and SURVEILLANCE REQUIREMENTS The OPERABILITY requirements in this manual follow the same LCO applicabilities as the Improved Technical Specifications with the exception of:

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

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

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

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

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

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

R. E. Ginna Nuclear Power Plant ODCM-3 Rev. 28

ODCM DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout these controls.

Terms used in these controls and not defined herein have the same definition as listed in the Technical Specifications and/or the Technical Requirements Manual. If a conflict in definition exists, the definition in the Technical Specifications takes precedence.

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

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

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instru-ment channels measuring the same parameter.

DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microCurie/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, I-133,1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calcu-lation shall be those listed in ICRP 30, Supplement to Part 1, Pages 192-212, table entitled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity" (Refer-ence 10).

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

NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months W At least once per 7 days M At least once per 31 days Q At least once per 92 days R. E. Ginna Nuclear Power Plant ODCM-4 Rev. 28

ODCM NOTATION FREQUENCY SA At least once per 184 days R At least once per 18 months S/U Prior to each reactor startup N/A Not applicable P Completed prior to each release FUNCTIONAL TEST A FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY of alarm, interlock display and/or trip func-tions. The FUNCTIONAL TEST shall include adjustments, as necessary, of the alarm, inter-lock display and/or Trip Setpoints such that the setpoints are within the required range and accuracy.

LOWER LIMIT OF DETECTION The LOWER LIMIT OF DETECTION (LLD) is the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95%

probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD is defined as a priori(before the fact) limit representing the capability of a measurement system and not as a posteriori(after the fact) limit for a particular measure-ment, the minimum detectable activity (MDA).

MEMBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for rec-reational, occupational, or other purposes not associated with the plant.

OFFSITE DOSE CALCULATION MANUAL The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liq-uid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program (REMP). The ODCM shall also contain descriptions of the Radioactive Effluent Controls and Radiological Environmental Monitoring Program and descriptions of the information that shall be included in the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report, as required by Technical Specification 5.5.1.

OPERABLE - OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s) and when all necessary attendant instrumentation, controls, electric power, cooling or seal water, lubrication or other auxiliary R. E. Ginna Nuclear Power Plant ODCM-5 Rev. 28

ODCM equipment that are required for the system, subsystem, train, component , or device to perform its function(s) are also capable of performing their related support function(s).

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

PURGE - PURGING PURGE or PURGING shall be any controlled process of discharging air or gas from a confine-ment to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RATED THERMAL POWER (RTP)

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 1520 MWt.

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

SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the chan-nel sensor is exposed to a source of increased radioactivity.

SURVEILLANCE REQUIREMENT SURVEILLANCE REQUIREMENTS shall be met during the OPERATIONAL MODES or other conditions specified for individual CONTROLS unless otherwise stated in an individual SUR-VEILLANCE REQUIREMENT. Each SURVEILLANCE REQUIREMENT shall be performed within the specified time interval with:

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

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

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

UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for resi-dential quarters or for industrial, commercial, institutional, and/or recreational purposes.

R. E. Ginna Nuclear Power Plant ODCM-6 Rev. 28

ODCM VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING VENTING shall be the controlled process of discharging air or gas from a confinement to main-tain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a venting process.

WASTE GAS HOLDUP SYSTEM A WASTE GAS HOLDUP SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System offgases and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environ-ment.

R. E. Ginna Nuclear Power Plant ODCM-7 Rev. 28

ODCM LIST OF ACRONYMS D Frequency Notation noting a surveillance frequency requirement of at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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

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

PCP Process Control Program 0 Frequency Notation noting a surveillance frequency requirement at least once per 92 days.

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

REMP Radiological Environmental Monitoring Program RTP Rated Thermal Power SA Frequency Notation noting a surveillance frequency requirement at least once 184 days.

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

S South SSE South-Southeast SSW South-Southwest S/U Frequency Notation noting a surveillance frequency requirement of being performed prior to each reactor startup.

SW Southwest W Frequency Notation noting a surveillance frequency requirement at least once per 7 days.

W West WNW West-Northwest WSW West-Southwest X/Q Dispersion parameter R. E. Ginna Nuclear Power Plant ODCM-8 Rev. 28

ODCM 1.0 RADIOACTIVE LIQUID EFFLUENTS 1.1 Concentration (10 CFR 20)

CONTROLS C.1.1 The release of radioactive liquid effluents shall be such that the concentration in the circulating water discharge does not exceed ten times the concentration values specified in Appendix B, Table 2, Column 2 to 10 CFR Part 20.1001 - 20.2402. For dissolved or entrained noble gases, the total activity due to dissolved or entrained noble gases shall not exceed 2.OE-04 pCi/ml.

APPLICABILITY: At all times.

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

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

SURVIFILLANCI= REOUIREMENTS RIF HIREMENTS S.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 1-1. The results of pre-release analyses shall be used with the calculational methods in Section 1.6 to assure that the concentration at the point of release is limited to the values in C.1.1 This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section IL.A design objectives of Appendix 1,10 CFR 50, to a MEMBER OF THE PUBLIC, and (2) the limits of Appendix B, 10 CFR 20, to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-1 35 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP)

Publication 2.

R. E. Ginna Nuclear Power Plant OD3CM-9 Rev. 28

ODCM 1.2 Dose (10 CFR 50 Appendix I)

CONTROLS C.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS shall be limited:

1. during any calendar quarter to _<1.5 mrem to the total body and to _<5 mrem to any organ, and

2. during any calendar year to !53 mrem to the total body and to

< 10 mrem to any organ.

APPLICABILITY: At all times.

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

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

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

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

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

SURVEILLANCE REQUIREMENTS S.1.2.1 Post-release analyses of samples composited from batch releases shall be performed in accordance with Table 1-1. The results of the post-release analyses shall be used with the calculational methods in Section 1.6 to assure that the dose commitments from liquids are limited to the values in C.1.2.

BASES This control is provided to implement the requirements of Sections ILA, IllA, and IV.A of Appendix 1,10 CFR 50. This control implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as reasonably achievable". Also, with Lake Ontario drinking water supplies potentially affected by plant operations, there is R. E. Ginna Nuclear Power Plant ODCM-10 Rev. 28

ODCM reasonable assurance that the operation of the plant will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational models and data, such that the actual exposure of a MEMBER OF THE PUBLIC appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I", Revision 1, October 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I",April 1977.

R. E. Ginna Nuclear Power Plant ODC M-11 Rev. 28

ODCM 1.3 Total Dose (40 CFR Part 190)

CONTROLS C.1.3 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY: At all times.

ACTION: With the calculated doses from the release of radioactive materials in liquid effluents exceeding twice the limits of C.1.2, prepare and submit to the Commission within 30 days a Special Report that defines the corrective actions to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and include scheduling for achieving conformance with the above limits. Calculations which include direct radiation contributions from the unit and from any radwaste storage shall be performed to determine total dose to a member of the public. This Special Report, as defined in 10 CFR 20.405(c) shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the releases covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190.

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

RIIRVFII I AJC:F RPFOIUIRIRMFNTR SURVEILLANCE S.1.3.1 Cumulative dose contributions from liquid and gaseous effluents for the current calendar quarter and the current calendar year shall be determined in accordance with SURVEILLANCE REQUIREMENTS S.1.2.1 at least once every 31 days, in accordance with the methodology and parameters of Section 1.7 of the ODCM.

S.1.3.2 Cumulative dose contributions from direct radiation from the unit and from radwaste storage shall be determined from environmental dosimeter data at least quarterly.

BASES This control is provided to meet the dose limitations of 40 CFR 190 that have been incorporated into 10 CFR 20 by 46FR18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. It is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the plant remains R. E. Ginna Nuclear Power Plant ODCM-12 Rev. 28

ODCM within twice the dose design objectives of Appendix I, and if direct radiation doses are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose contributions from other uranium fuel cycle sources is negligible. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance, (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR 20, as addressed in C.1.1 and C.2.2. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

R. E. Ginna Nuclear Power Plant ODCM-13 Rev. 28

ODCM Table 1-1 Radioactive Liquid Waste Sampling and Analysis Program Liquid Sampling Minimum Type of Lower Limit Release Type Frequency Analysis Activity Analysis of Detection Frequency (LLD)

(.tCilml) (a)

Batch Release (b)

P P Principal Gamma Emitters (d) 5.OE-07 Each Batch Each Batch and 1-131 1.OE-06 P M Dissolved and Entrained 1.OE-05 Batch Waste One Batch/M Gases (Gamma Emitters)

Release Tanks p M H-3 1.OE-05 Each Batch Composite (c) Gross Alpha 1.OE-07 P Q Sr-89 Sr-90 5.OE-08 Each Batch Composite (c) Fe-55 1.OE-06 Continuous Release (e)

Continuous W Principal Gamma Emitters (d) 5.OE-07 (e) Composite (c) and 1-131 1.OE-06 Continuous W Dissolved and 1.OE-05 (e) Composite (c) Entrained Gasses Retention Tank (Gamma Emitters)

Continuous M H-3 1.OE-05 (e) Composite (c) Gross Alpha 1.OE-07 Continuous Q Sr-89 Sr-90 5.OE-08 (e) Composite (c) Fe-55 1.OE-06 M or S M or S Principal Gamma Emitters (d) 5.OE-07 Grab (f Grab (f) and 1-131 1.OE-06 Service (f) (f) Dissolved and 1.OE-05 Water Entrained Gasses (CV Fan Cooler (Gamma Emitters) and SFP Hx (M (f) H-3 1.OE-05 lines) Gross Alpha 1.OE-07 (f) (f) Sr-89 Sr-90 5.OE-08 Fe-55 1.OE-06 R. E. Ginna Nuclear Power Plant ODCM-14 Rev. 28

ODCM Table 1-1 Table Notation (a) The LLD is the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

The LLD is defined as an a priori(before the fact) limit representing the capability of a measurement system and not as an a posteriori(after the fact) limit for a particular mea-surement, the minimum detectable activity (MDA).

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

LLD =(Sb)

(E)(T)(V)(2.22 E + 06) [exp (-V)]

LY Where:

LLD is the lower limit of detection as defined above as pCi per unit mass or volume Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate as counts per disintegration V is the sample size in units of mass or volume E is the counting efficiency Y is the fractional radiochemical yield when applicable 2.22E+06 is the number of disintegrations per minute per pCi x is the decay constant t is time elapsed since sample time The value of Sb used in the calculation of the LLD for a particular measurement system shall be based on the actual observed variance of the background counting rate or the counting rate of the blank samples, as appropriate, rather than on an unverified theoreti-cally predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contribution of other radionuclides normally present in the samples. Typical values of E, V, and Y should be used in the calculation.

The background count rate is calculated from the background counts that are deter-mined to be within +/- one FWHM energy band about the energy of the gamma ray peak used for the quantitative analysis for this radionuclide.

R. E. Ginna Nuclear Power Plant ODCM-15 Rev. 28

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

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

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

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

The outside Condensate Storage Tank cannot be adequately mixed by recirculating.

A sample shall be taken during mid-release and analyzed.

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

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

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

Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, Cs-137 and Ce-141. (Ce-141 shall be measured to a LLD of 5.OE-06).

This list does not mean that only these nuclides are to be detected and reported. Other nuclides which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should be reported as less than the LLD and should not be reported as being present at the LLD level. The less than values should not be used in the required dose calcula-tions.

(e) A continuous release is the discharge of liquid wastes of a non-discrete volume; e.g.,

from a volume or system that has an input flow during the continuous release. Decay corrections will be calculated based on all samples collected during the release.

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

R. E. Ginna Nuclear Power Plant ODCM-16 Rev. 28

ODCM 1.4 Liquid Effluents Release Points There are three normal release points for liquid radioactive effluents from the plant that empty into the discharge canal. These are the Radwaste Treatment Discharge, Retention Tank dis-charge and the All Volatile Treatment Discharge. Each of these is a monitored release line that can be isolated before the release reaches the discharge canal. There is also a release point for the service water lines used for cooling the heat exchangers that is a monitored release line but is not isolatable. If there is an alarm on the service water monitor, it is necessary to sample each heat exchanger separately to determine which has a leak and then isolate the affected heat exchanger. The pressure of the service water system flow would normally force water from the clean service water side into the contaminated side of the heat exchanger. Dilution of liquid effluent is provided by the discharge canal. The discharge canal flow is nominally 1.7E+05 gpm for each circulating water pump. During operating periods, two circulating water pumps are in operation. During shutdown periods, one circulating water pump is operated. If neither circulating water pump is operable, dilution is provided by operation of one to three ser-vice water pumps which provide nominally 5.3E+03 gpm each.

R. E. Ginna Nuclear Power Plant ODCM-17 Rev. 28

ODCM 1.5 Liquid Effluents Monitor Setpoints Alarm and/or trip setpoints for radiation monitors on each liquid effluent line are required. Pre-cautions, limitations and setpoints applicable to the operation of Ginna Station liquid effluent monitors are provided in plant procedure P-9. Setpoint values are calculated to assure that alarm and trip actions occur prior to exceeding ten times the effluent concentration of Appendix B, Table 2, Column 2 of 10 CFR 20.1001 - 20.2402 at the release point to the unrestricted area.

For added conservatism, liquid effluent release rates are administratively set so that only frac-tions of the applicable maximum effluent concentrations can be reached in the discharge canal.

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

sL. <C F +f-Equation (1)

Where:

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

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

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

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

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

The limiting batch release concentration (c) corresponding to the liquid waste monitor setpoint is calculated from the above expression. Since the value of (f) is very small in comparison to (F), and tritium can not be accounted for, the expression becomes:

__ xx.4 (1 - TCF) f Equation (2)

Where:

C = 10 x the allowable concentration of Cs-137 as given in Appendix B, Table 2, Column 2 of 10 CFR 20, 1 Y 105. This value is normally more restrictive than the calculated mixed isotopic release concentration. A weighted average, excluding Sb-125, from 1998 data indicated a release concentration of 1.15 x 105 pCi/ml. (See DA-RP 078). This should be reviewed as an annual basis, and the more conservative value between the two be utilized.

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

R. E. Ginna Nuclear Power Plant ODCM-18 Rev. 28

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

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

TCF Tritium Correction Factor, based on the maximum concentration of diluted RCS H-3, divided by H-3 E.C.L. The maximum UFSAR RCS tritium concentration is 3.5 iiCi/ml.

The monitor setpoint against gamma emitters must be reduced proportional to the ratio of tritium in the waste stream, to which the monitor will not respond.

The limiting release concentration (c) is then converted to a set-point count rate by the use of the monitor calibration factor determined per the individual monitor calibration procedure. The expression becomes:

c (,, C*/mI) e.StpOn' (cpm) = Cal Factor (utl/m,/epm)

Equation (3)

Example (Liquid Radwaste Monitor R-18):

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

I-3 S(IC*/'ml) <E E-O0(5Ci/ml) x 170, O000(gpm) I 1- 0 90gp L I-2 cýs6.39E -3r (u /rl)

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

6.39E - 3(i, 0 Im) = 5.33 E+05 cpm above background The setpoint values for the containment Fan Cooler monitor (R-16), Spent Fuel Pit Heat Exchanger Service Water Monitors (R-20A and R-20B), Steam Generator Blowdown Monitor R. E. Ginna Nuclear Power Plant ODCM-19 Rev. 28

ODCM (R-19), the Retention Tank Monitor (R-21, and the All volatile Treatment Waste Discharge Mon-itor (R-22) are calculated in a similar manner using equation (2), substituting appropriate val-ues of (f) and the corresponding calibration factor.

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

R. E. Ginna Nuclear Power Plant ODCM-20 Rev. 28

ODCM 1.6 Liquid Effluent Release Concentrations Liquid batch releases are controlled individually and each batch release is authorized based upon sample analysis and the existing dilution flow in the discharge canal. Plant procedures CH-RETS-LIQ-RELEASE and CH-RETS-LIQ-COMP establish the methods for sampling and analysis of each batch prior to release. A release rate limit is calculated for each batch based upon analysis, dilution flow and all procedural conditions being met before it is authorized for release. The waste effluent stream entering the discharge canal is continuously monitored and the release will be automatically terminated if the preselected monitor setpoint is exceeded. A release may continue subject to grab sample analysis and monitoring in accordance with Table 3.1-1.

The equation used to calculate activity is:

Gamma Spectroscopy u/gm Act.= peak area counts- bkgdcounts (C Time)(EFq)((Vol)(Decay)(3.7 E+04)

Equation (4)

R. E. Ginna Nuclear Power Plant ODCM-21 Rev. 28

ODCM 1.7 Liquid Effluent Dose The dose contribution received by the maximally exposed individual from the ingestion of Lake Ontario fish and drinking water is determined using the following methodology. These calcula-tions will assume a near field dilution factor of 1.0 in evaluating the fish pathway dose, and an average annual dilution factor of 200 between the plant discharge and the Ontario Water Dis-trict drinking water intake located approximately 2220 meters northeast (53 degrees) of the dis-charge canal. The average annual dilution factor of 200 was derived from the drift and dispersion study documented in reference 4.

Dose contributions from shoreline recreation, boating and swimming have been shown to be negligible in the Appendix I dose analysis, reference 5, and do not need to be routinely evalu-ated. Shoreline sediment samples downstream from the plant will be collected at least semi-annually for the Radiological Environmental Monitoring Program, as a conservatism. Presence of radioactivity above background will result in calculation of dose contribution from these path-ways. There is no known human consumption of shellfish from Lake Ontario; therefore, this pathway is not taken into consideration in dose calculations.

The dose contribution to an individual will be determined to ensure that it complies with the specification of C.1.2. Offsite receptor doses will be determined for the limiting age group and organ, unless census data show that actual offsite individuals are the limiting age group.

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

Equation (5)

Where:

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

Z is for total number of hours of releasg.

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

Cjj = the average concentration of radionuclide i in undiluted liquid effluent during time period Atj from any liquid release in p.Ci/ml.

Aj1 = the site-related ingestion dose commitment factor to the total body or any organ, T, for each identified principal gamma and beta emitter in mrem/hr per pCi/ml. See equation (6).

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

R. E. Ginna Nuclear Power Plant ODCM-22 Rev. 28

ODCM Air = ko (Uw IDI, + Up B1F.) DFr Equation (6)

Where:

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

ko= units conversion factor, 1.14E+05 = 1.OE+06 pCi/pCi x 1.OE+03 ml/kg + 8760 hr/yr Uw= a receptor person's water consumption by age group from Table E-5 of Regulatory Guide 1.109 Dw = dilution factor from the near field area of the release point to potable water intake. The site specific dilution factor is 200. This factor is 1.0 for the fish ingestion pathway.

UF = a receptor person's fish consumption by age group from Table E-5 of Regulatory Guide 1.109 BF = bioaccumulation factor for nuclide, i, in fish in pCi/kg per pCi/L, from Table A-1 of Regulatory Guide 1.109 DFi, = dose conversion factor for the ingestion of nuclide, i, for a receptor person in pre-selected organ, T, in mrem/pCi, from Tables E-11, E-12, E-13, E-14 of Regulatory Guide 1.109 The monthly dose contribution from releases for which radionuclide concentrations are deter-mined by periodic composite sample analysis may be approximated by assuming an average monthly concentration based on the previous monthly or quarterly composite analysis. How-ever, in the Annual Radioactive Effluent Release Report the calculated dose contributions from these radionuclides shall be based on the actual composite analysis.

Example:

Computing the dose to the whole body via the fish and drinking water pathways, assuming an initial Cs-137 discharge concentration of 3.OE-04 pCi/ml:

Given the following discharge factors for example, where:

Ati = 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the duration of the release Cij = 3.OE-04 pCi/ml Fj = liquid waste flow = 20 gp.m = 1.2E-04 (dilution flow)(z) 170,000 gpm z= Near field dilution = 1.0 for Ginna Dw= 200 and, taking the following values from Regulatory Guide 1.109 which concern the critical recep-tor, which is considered to be the child in this case:

UW= 510 I/year UF = 6.9 kg/year BF = 2000 pCi/kg per pCi/I R. E. Ginna Nuclear Power Plant ODCM-23 Rev. 28

ODCM DFj = 4.62E-05 mrem/pCi Then, the site-related ingestion dose commitment factor, Ai, is calculated as follows:

Ai mrem lhr k 0 (U1 v,/D 4 , + SF ) DR1

Ci/ml

= 1.14 E+05 [510+(6.9)(2000)]4.62 E-05 200 A17 = 7.27 E+ 04 mrem /hr per ACi /nl And, the whole body dose to the child is then:

D]T mrem = (A,.) (Atj) (C.) (Fj)

= (7.27 E+ 04)(1)(3.0 E- 04)(1.2 E- 04)

DT = 2.6 9- 03 mrem to the whole body from Cs- 137 The dose contribution from any other isotopes would then need to be calculated and all the iso-topic contributions summed.

R. E. Ginna Nuclear Power Plant ODCM-24 Rev. 28

ODCM 2.0 RADIOACTIVE GASEOUS EFFLUENTS 2.1 DELETED R. E. Ginna Nuclear Power Plant ODCM-25 Rev. 28

ODCM 2.2 Dose Rate CONTROLS C.2.2 The instantaneous dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY shall be limited to the following values:

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

2. The dose rate for 1-131, 1-133, tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days shall be

1500 mrem/yr to any organ.

APPLICABILITY: At all times.

Note;L For unplanned release of gaseous wastes, compliance with C.2.2 may be calculated using annual average X/Q. Compliance with C.2.2 shall be determined by considering the applicable ventilation system flow rates.

These flow rates shall be determined at the frequency required by Table 3.2-2.

ACTION: If the calculated dose rate of radioactive materials released in gaseous effluents from the site exceeds the limits of C.2.2, measures shall be initiated to restore releases to within limits. The effluent continuous monitors listed in Table 3.2-1 that have provisions for the automatic termination of gas decay tank, shutdown purge or mini-purge releases, shall be used to limit releases within the values established in C.2.2 when monitor setpoint values are exceeded.

SURVEILLANCE REQUIREMENTS S.2.2.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters of Section 2.7 of the ODCM.

S.2.2.2 The dose rate due to radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters of Section 2.7 of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 2-1.

BASES This control is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents will be within the annual dose limits of 10 CFR 20, Appendix B, Table 2, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10 CFR 20. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that R. E. Ginna Nuclear Power Plant ODCM-26 Rev. 28

ODCM for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/year to the whole body or to less than or equal to 3000 mrems/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year.

R. E. Ginna Nuclear Power Plant ODCM-27 Rev. 28

ODCM 2.3 Dose (10 CFR 50, Appendix I)

CONTROLS C.2.3.1 The dose due to noble gases released in gaseous effluents to areas at or beyond the SITE BOUNDARY shall be limited to the following:

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

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

APPLICABILITY: At all times ACTION: Whenever the calculated dose to a MEMBER OF THE PUBLIC resulting from noble gases exceeds the limits of C.2.3.1, a Special Report shall be submitted to the Commission within 30 days which includes the following information:

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

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

ACTION: During any month when the calculated dose to a MEMBER OF THE PUBLIC exceeds 1/48th the annual limits of C.2.3.1, (0.2 mrad gamma or 0.4 mrad beta), projected cumulative dose contributions from gaseous effluents shall be determined for that month and at least once every 31 days for the next 3 months.

SURVEILLANCE REQUIREMENTS S.2.3.1.1 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters of Section 2.8 of the ODCM at least once every 31 days.

This control is provided to implement the requirements of Sections li1B, Il.A, and IV.A of Appendix I, 10 CFR 50. The control implements the guides set forth in Section 1.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the release of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as reasonably achievable". The SURVEILLANCE REQUIREMENTS implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, R. E. Ginna Nuclear Power Plant ODCM-28 Rev. 28

ODCM "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I", Revision I, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors", Revision I, July 1977. The ODCM equations for determining air doses at the SITE BOUNDARY are based on historical average atmospheric conditions.

CONTROLS C.2.3.2 The dose to a MEMBER OF THE PUBLIC from 1-131, 1-133, tritium, and for all radioactive materials in particulate form with half-lives greater than eight days released with gaseous effluents from the site shall be limited to the following:

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

2. during any calendar year to 5 15 mrem to any organ.

APPLICABILITY: At all times.

ACTION: Whenever the calculated dose to a MEMBER OF THE PUBLIC resulting from radionuclides other than noble gases exceeds the limits of C.2.3.2, a Special Report shall be submitted to the Commission within 30 days which includes the following information:

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

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

ACTION: During any month when the calculated dose to a MEMBER OF THE PUBLIC exceeds 1/48th the annual limit of 2.3.2, (0.3 mrem), projected cumulative dose contributions from gaseous effluents shall be determined for that month and at least once every 31 days for the next 3 months.

SURVEILLANCE REQUIREMENTS S.2.3.2.1 Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-131, Iodine-1 33, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with methodology and parameters of Section 2.8 of the ODCM at least once every 31 days.

BASES This control is provided to implement the requirements of Sections II.C, IllA, and IV.A of Appendix 1, 10 CFR 50. The control implements the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the release of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as reasonably achievable". The SURVEILLANCE REQUIREMENTS implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a R. E. Ginna Nuclear Power Plant ODCM-29 Rev. 28

ODCM MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of the subject materials in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I", Revision I, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors", Revision I, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for Iodine-1 31, Iodine-1 33, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the areas at or beyond the SITE BOUNDARY. The pathways examined in development of the calculations were:

1. Individual inhalation of airborne radionuclides

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

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

4. Deposition of radionuclides on the ground followed by subsequent human exposure R. E. Ginna Nuclear Power Plant ODCM-30 Rev. 28

ODCM 2.4 Total Dose (40 CFR 190)

CONTROLS C.2.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY: At all times.

ACTION: With the calculated doses from the release of radioactive materials in gaseous effluents exceeding twice the limits of C.2.3.1 and C.2.3.2, prepare and submit to the Commission within 30 days a Special Report that defines the corrective actions to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and include scheduling for achieving conformance with the above limits. Calculations which include direct radiation contributions from the unit and from any radwaste storage shall be performed to determine total dose to a MEMBER OF THE PUBLIC. This Special Report, as defined in 10 CFR 20.405(c) shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the releases covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and ifthe release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190.

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

ACTION: This report shall include an analysis which demonstrates that radiation exposure to all MEMBERS OF THE PUBLIC from the plant are less than the 40 CFR 190 limits. Otherwise, the report shall request a variance from the commission to permit releases to exceed 40 CFR Part 190. Submittal of the report is considered a timely request by the NRC, and a variance is granted until staff action on the request is complete.

SURVEILLANCE REQUIREMENTS S.2.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with SURVEILLANCE REQUIREMENTS S.2.3.1, and S.2.3.2 at least once every 31 days, in accordance with the methodology and parameters of Section 2.8 of the ODCM.

S.2.4.2 Cumulative dose contributions from direct radiation from the unit and from radwaste storage shall be determined from environmental dosimeter data at least quarterly.

BASES This control is provided to meet the dose limitations of 40 CFR 190 that have been incorporated into 10 CFR 20 by 46FR18525. The specification requires the preparation and submittal of a Special Report whenever the R. E. Ginna Nuclear Power Plant ODCM-31 Rev. 28

ODCM calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. It is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the plant remains within twice the dose design objectives of Appendix I, and if direct radiation doses are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose contributions from other uranium fuel cycle sources is negligible. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance, (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR 20, as addressed in C. 1.1 and C.2.2. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

R. E. Ginna Nuclear Power Plant ODCM-32 Rev. 28

ODCM Table 2-1 Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Sampling Minimum Type of Activity Lower Limit of Release Type Frequency Analysis Analysis Detection (LLD)

Frequency (gCiicc) (a)

Containment P P Principal Gamma 1.OE-04 Purge Each Purge (bc) Emitters (e)

Grab Sample H-3 1.OE-06 Auxiliary Build- M (b) M (b) Principal Gamma 1.OE-04 ing Ventilation Grab Sample Emitters (e)

H-3 1.OE-06 Continuous (d) W (b,i) 1-131 1.OE-12 Charcoal Sam- 1-133 1.OE-10 pie Continuous (d) W (bi) Principal Gamma 1.0E-11 Particulate Emitters (e)

Sample All Release Types Continuous (d) M Gross Alpha 1.0E-11 as listed above Composite Particulate Sample Continuous (d) Q Sr-89 Sr-90 1 .OE-1 1 Composite Particulate Sample Air Ejector M (bf) M (b, f) Principal Gamma 1.QE-04 Grab Sample Emitters (e) 1-131 (h) 1.OE-12 H-3 (g) 1.OE-06 All Release Continuous (d) Noble Gas Beta or Gamma 1.0E-06 Types listed Monitor above Gas Decay Tank P P Principal Gamma 1.OE-04 Each Tank Each Tank Emitters (e)

Grab Sample R. E. Ginna Nuclear Power Plant ODCM-33 Rev. 28

ODCM Table 2-1 Table Notation (a) The lower limit of detection (LLD) is defined in Table Notation (a) of Table 1-1.

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

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

(d) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with C.2.1, C.2.2, C.2.3.1, & C.2.3.2 (e) The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:

Kr-85m, Xe-1 33, Xe-133m and Xe-1 35 for gaseous emissions 1-131, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.

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

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

(g) Air ejector tritium sample is not required if the secondary coolant activity is less than 1.OE-04 itCi/gm.

(h) Air ejector iodine samples shall be taken and analyzed weekly if the secondary coolant activity exceeds 1.OE-04 ItCi/gm.

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

R. E. Ginna Nuclear Power Plant ODCM-34 Rev. 28

ODCM 2.5 Gaseous Effluent Release Points There are three release points continuously monitored for noble gases, containment vent, plant vent and air ejector. The containment vent and plant vent are also continuously monitored for radioiodines and particulates. Since the air ejector is a steam release point, continuous radio-iodine and particulate monitoring is not required when the secondary coolant activity is less than 1.OE-04 piCi/gm. Flow rates through the vents are measured periodically. During shut-down, temporary trailers may be brought on site that also require monitoring and characteriza-tion of their releases, such as the CO 2 decon trailer.

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

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

R. E. Ginna Nuclear Power Plant ODCM-35 Rev. 28

ODCM 2.6 Gaseous Effluent Monitor Setpoints Alarm and/or trip setpoints for specified radiation monitors are required on each noble gas effluent line from the plant. Precautions, limitations and setpoints applicable to the operation of Ginna Station gaseous effluent monitors are provided in plant procedure P-9. Setpoints are conservatively established for each ventilation noble gas monitor so that dose rates in unre-stricted areas corresponding to 10 CFR Part 50 Appendix I limits will not be exceeded. Set-points shall be determined so that dose rates from releases of noble gases will comply with C.2.2.(1). Table 2-2 provides the gaseous and particulate meteorological assumption used in development of the P-9 setpoints.

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

Equation (7)

Where:

cv = setpoint in cpm QiV= release rate limit by specific nuclide (i) in [.Ci/sec from vent (v) f= discharge flow rate in cfm k = units conversion factor in cc/sec/cfm K calibration factor in ltCi/cc/cpm The general methodology for establishing plant ventilation monitor setpoints is based upon a vent concentration limit in piCi/cc derived from site specific meteorology and vent release char-acteristics.

Additional radiation monitor alarm and/or trip setpoints are calculated for radiation monitors measuring radioiodines, radioactive materials in particulate form and to radionuclides other than noble gases. Setpoints are determined to assure that dose rates from the release of these effluents shall comply with C.2.2(2)

The release rate limit for noble gases shall be calculated by the following equation for total body dose:

Q( [u/sc] 1 2i" 500 mrem/yr (X/CX, :K,2Q.

Equation (8)

Note: An occupancy factor of 1 is assumed. This may be modified following reviews of the area in question.

and by the following equation for skin doses:

R. E. Ginna Nuclear Power Plant ODCM-36 Rev. 28

ODCM

[U[ 1. OCw~

c ý5_3 3000 mreynliy T Equation (9)

Where:

Qiv= the release rate of radionuclide (i) from vent (v) which results in a dose rate of 500 mrem/yr to the whole body or 3000 mrem/yr to the skin of the critical receptor in 1iCi/

sec.

Ki = the total body dose factor due to gamma emissions for each identified noble gas radionuclide in mrem/yr per pCi/m 3 from Table 2-3.

Li = the skin dose factor due to beta emissions for each identified noble gas radionuclide in mrem/yr per p.Ci/m 3 from Table 2-3.

Mi= the air dose factor due to gamma emissions for each identified noble gas radionuclide in mrad/yr per pCi/m 3 from Table 2-3. Unit conversion constant of 1.1 mremlmrad converts air dose to skin dose.

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

Noble gas monitor setpoints are conservatively set according to procedure P-9 to correspond to fractions of the applicable 10 CFR Part 20 dose limits for unrestricted areas. Fractions are small enough to assure the timely detection of any simultaneous discharges from multiple release points before the combined downwind site boundary concentration could exceed allow-able limits. Additional conservatism is provided by basing these setpoints upon instantaneous downwind concentrations. Release rates during the remainder of a given year, combined with any infrequent releases at setpoint levels, would result in only a very small fraction of the 10 CFR Part 20 annual limits.

Historically, xenon-133 has been the principal fission product noble gas released from all vents and is appropriate for use as the reference isotope for establishing monitor setpoints. The whole body dose will be limiting, and the Xe-1 33 release rate limit is calculated by substituting the appropriate values into equation (8). After the release rate limit for Xe-1 33 is determined for each vent, the corresponding vent concentration limits are calculated based on applicable vent flow rates. During periods of high make-up water usage, argon-41 from air saturated make-up water becomes the principle radiogas of concern and may be used as the reference isotope for establishing setpoints. Calibration factors in pCi/cc per cpm are used to convert limiting vent concentrations to count rates.

Examp~le: Plant Vent Monitor, R-14 Using Xe-1 33 as the controlling isotope for the setpoint and assuming a measured activity of 2.66E-04 !iCi/cc and a ratemeter reading of 4750 cpm above background, the efficiency can be calculated, using a measured vent flow of 7.45E+04 cfm, Ki from Table 2-3 of 2.94E+02 and a (X/Q), for the site boundary of 2.7E-06, the Release Rate Limit is calculated and then the set-point determined.

R. E. Ginna Nuclear Power Plant ODCM-37 Rev. 28

ODCM Xe-133 efficiency = Activity Ac ratemeter reading

'ere-133 efficiency = 2.65 F-04 5.67 E-08 uCL/cc 4750 cpm Using Equation 8:

<500 5 6.3 F+05 uO/sec (2.94 F+02)(2.7 2-06) -

Release Rate Limit A." < 500 mrem/yr (K*) 4Wi Q),

Using Equation 7:

Setpoint c A,

()(k)(K) 6.3 E + 05 u Cis/e c

(.45 E + 04 cfm)(472 (5.67

)cc/aLe - 08 c-/cc) c5 3.2 E2+05 epni Per procedure P-9, R-14 is set at 0.4 of this value or 1.28E+05 cpm for normal operation. 40%

of the release rate limit is a conservatism based on the possibility of two release points simulta-neously at their setpoints for a total of 80% of the release rate limit.

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

R. E. Ginna Nuclear Power Plant ODCM-38 Rev. 28

ODCM Table 2-2 Meteorological Data and Locations of Receptors for Set Point Calculations Process Monitors Monitor Geographic Release X/Q DIQ Flow (Radioisotope) Location Point (seclm3) (m 2-mremlyr (cfm)

(DistancelDirection) (vent) per pCilsec)

R-10A 0.5 - 1 mile ESE Containment 2.4E-8 11,000 (Radioiodine)

R-10B 0.5 - 1 mile ESE Plant 3.OE-8 80,000 (Radioiodine)

R-11 0.5 - 1 mile ESE Containment 2.4E-8 11,000 (Cs-137)

R-12 0.5- 1 mile E Containment 1.6E-6 11,000 (Xe-133)

R-13 0.5 - 1 mile ESE Plant 3.OE-8 80,000 (Cs-1 37)

R-14 0.5 - 1 mile E Plant 2.7E-6 80,000 (Xe-i 33)

R-15 0.3 miles SSE Air Ejector 1.3E-5 600 (Xe-133)

R-47 0.3 miles SSE Air Ejector 1.3E-5 3 (Ar-41 )

Accident Monitors Monitor Geographic Release X/Q D/Q Flow (Radioisotope) Location Point (sec/m3) (m 2-mrem/yr (cfm)

(DistancelDirection) (vent) per pCilsec)

R-12A 0.5-1 mile ESE Containment >2.4E-8 11,000 (Radioiodine)

R-12A 0.5-1 mile ESE Containment 2.4E-8 11,000 (Particulate Cs-1 37)

R-12A 0.5-1 mile E Containment 1.6E-6 11,000 (Noble Gas Xe-133)

R-14A 0.5-1 mile ESE Plant 3.OE-8 80,000 (Radioiodine)

R-14A 0.5-1 mile ESE Plant 3.OE-8 80,000 (Particulate Cs-137)

R-14A 0.5-1 mile E Plant 2.7E-6 80,000 (Noble Gas Xe-133)

R. E. Ginna Nuclear Power Plant ODCM-39 Rev. 28

ODCM R-47 0.3 miles SSE Air Ejector 1.3E-5 3 (Ar-41)

R-48 0-0.5 miles NE Air Ejector 6.50E-5 600 (RCS Accident Mix)

R. E. Ginna Nuclear Power Plant ODCM-40 Rev. 28

ODCM Table 2-2 (continued...)

Further details found in procedure P-9.

1-131, 1-133, H-3 and particulates with half lifes greater than 8 days utilizes the following equa-tion:

mrern/year 2i. <1500(D1Q), P2 For Noble Gases:

5<00 mTamlear (x12)1, Ki Pi = Food and ground pathways in m2 mrem/year per VCi/sec Ki = mrem/year per l.t0i/m3 Qiv= Release rate in units of itCi/sec R. E. Ginna Nuclear Power Plant ODCM-41 Rev. 28

ODCM 2.7 Gaseous Effluent Dose Rate Gaseous effluent monitor setpoints as described in Section 2.6 of this manual are established at concentrations which permit some margin for corrective action to betaken before exceeding offsite dose rates corresponding to 10 CFR Part 20 limitations. Plant procedures CH-RETS-RMS-CV, CH-RETS-RMS-CV-ALT, CH-RETS-PURGE-CV, CH-RETS-SAMP-PV, CH-RETS-SAMP-PV-ALT, CH-RETS-PV-RELEASE, CH-RETS-AIR-H3 and CH-RETS-MINIPURGE establish the methods for sampling and analysis for continuous ventilation releases and for containment purge releases. Plant procedure CH-RETS-GDT-REL establishes the methods for sampling and analysis prior to gas decay tank releases. The instantaneous dose rate in unrestricted areas due to unplanned releases of airborne radioactive materials may be calcu-lated using annual average X/Q's. Dose rates shall be determined using the following expres-sions:

For noble gases:

= +Q) 1.1 h4) 9] <_30o00 rnr Equation (11) total gamma and beta dose to the skin D A 500 mu m/yr Equation (12) total body dose For 1-131. 1-133. tritium and all radioactive materials in particulate form with half-lives greater than 8 days:

DI=

, P1 W, Q S _ 1500 nmre ,,/yr to critical organ Equation (13)

Where:

Ki = the total body dose factor due to gamma emissions for each identified noble gas radionuclide (i) in mrem/yr per [itCi/m 3 from Table 2-2.

Li = the skin dose factor due to beta emissions for each identified noble gas radionuclide (t) in mrem/yr per pCi/m 3 from Table 2-2.

Mi= the air dose factor due to gamma emissions for each identified noble gas radionuclide (i) in mrad/yr per pCi/m 3 from Table 2-2. Unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose.

Pi = the dose parameter for radionuclide (i) other than noble gases for the inhalation pathway, in mrem/yr per pCi/m 3 . The dose factors are based on the critical individual organ and the child age group. Pi is further defined as: P, =(10 6 pCi/uCi)(BR)(DFAi) where BR is the breathing rate for a child in m 3/yr and DFAi is the dose factor for the child in mrem/pCi.

R. E. Ginna Nuclear Power Plant ODCM-42 Rev. 28

ODCM (X/Q)v = the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary in sec/m 3 .

Wv = the highest annual average dispersion parameter for estimatinT the dose to the critical receptor in sec/mrfor the inhalation pathway and in mn-for the food and ground pathways.

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

R. E. Ginna Nuclear Power Plant ODCM-43 Rev. 28

ODCM 2.8 Gaseous Effluent Doses The air dose in unrestricted areas due to noble gases released in gaseous effluents from the site shall be determined using the following expressions:

During any calendar year. for aamma air dose:

= 3.17 E-0S0 [MI (X,*9), _0, ] -5 10 m2Qd Equation (14)

Durina any calendar auarter, for gamma air dose:

= 3.17 E-O08 [Mj (X/2) P,] _55 .,. d Equation (14A)

During any calendar year for beta air dose:

D~f = 3.17 E-o08 VM /

(,',Q>, Q,, ] 5 20 mrad Equation (15)

During any calendar quarter, for beta air dose:

D~p = 3.17 E -0 [Nj (XI?)>, Q 10 ,nrad Equation (15A)

Where:

Mi= the air dose factor due to gamma emissions for each identified noble gas radionuclide in mrad/yr per ipCi/m 3 from Table 2-3 Ni = the air dose factor due to beta emissions for each identified noble gas radionuclide in mrad/yr per pCi/m 3 from Table 2-3 (X/Q), = for vent releases. The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary in sec/m3 .

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

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

QiV= the release of noble gas radionuclides, i, in gaseous effluents from vents in jLCi.

Releases shall be cumulative over the time period.

3.17E-08 =the inverse of the number of seconds in a year The dose to an individual from 1-131, 1-133, tritium and all radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released from the site to unre-stricted areas shall be determined using the following expression:

R. E. Ginna Nuclear Power Plant ODCM-44 Rev. 28

ODCM dose during any calendar year:

D,= 3.17 E -08 [Ri Wpv gi 15rn~

Equation (16) dose during any calendar quarter:

D1 = 3.17 E-02 Z [RV W, Qj, ] 5 7.5 Equation (16A)

Where:

D, = the total dose from 1-131, 1-133, tritium and all radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents in mrem.

Ri = the dose factor for each identified radionuclide (i) in m2 mrem/yr per l.Ci/sec or mrem/

yr per liCi/m 3 from Table 2-5.

W, = the annual average dispersion parameter for estimating the dose to an individual at the critical location in sec/m3 for the inhalation pathway and in m2 for the food and ground pathways.

QiV = the release of 1-131, 1-133, tritium and all radioactive materials in particulate form in gaseous effluents with half-lives greater than 8 days in piCi. Releases shall be cumulative over the desired time period as appropriate.

R. E. Ginna Nuclear Power Plant ODCM-45 Rev. 28

ODCM Table 2-3 Dose Factors to the Child For Noble Gases and Daughters*

Radio- Total Body Dose Skin Dose Gamma Air Dose Beta Air Dose nuclides Factor Ki Factor Li Factor Mi Factor Ni (mremlyr (mremlyr (mradlyr (mradfyr per i&Cilm 3) per tpCilm 3 ) per ViCi/m 3 ) per gLCi/m 3 )

Kr-83m 7.56E-02** --- 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+011 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11 E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-133m 2.51E+02 9.94E+02 3.27EE+02 1.48E+03 Xe-135m 3.12E+03 7.1IE+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 The listed dose factors are for radionuclides that may be detected in gaseous effluents. These dose factors for noble gases and daughter nuclides are taken from Table B-1 of Regulatory Guide 1.109 (reference 3). A semi-infinite cloud is assumed.

2 7.56E-02 = 7.56 10-R. E. Ginna Nuclear Power Plant ODCM-46 Rev. 28

ODCM Table 2-4 Dose Parameters for Radionuclides and Radioactive Particulate, Gaseous Effluents*

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

nuclides Pathways Ground nuclides Pathways Ground (mremlyr Pathways (mremlyr Pathways per ýtCilm 3) (m2 xmremlyr per l.Cilm 3) (m 2xmremlyr per 1 iCilsec) per .iCilsec)

H-3 6.5E+02 2.4E+03 Cd-115m 7.OE+04 4.8E+07 C-14 8.9E+03 1.3E+09 Sn-126 1.2E+06 1.1E+09 Cr-51 3.6E+02 1.1E+07 Sb-125 1.5E+04 1.1E+09 Mn-54 2.5E+04 1.1E+09 Te-127m 3.8E+04 7.4E+10 Fe-59 2.4E+04 7.OE+08 Te-129m 3.2E+04 1.3E+09 Co-58 1.1E+04 5.7E+08 Te-132 1.OE+03 7.2E+07 Co-60 3.2E+04 4.6E+09 Cs-134 7.OE+05 5.3E+10 Zn-65 6.3E+04 1.7E+10 Cs-136 1.3E+05 5.4E+09 Rb-86 1.9E+05 1.6E+10 Cs-137 6.1E+05 4.7E+10 Sr-89 4.OE+05 1.OE+10 Ba-140 5.6E+04 2.4E+08 Sr-90 4.1E+07 9.5E+10 Ce-141 2.2E+04 8.7E+07 Y-91 7.OE+04 1.9E+09 Ce-144 1.5E+05 6.5E+08 Zr-95 2.2E+04 3.5E+08 Np-239 2.5E+04 2.5E+06 Nb-95 1.3E+04 3.6E+08 1-131 1.5E+07 1.1E+12 Mo-99 2.6E+02 3.3E+08 1-133 3.6E+06 9.6E+09 Ru-103 1.6E+04 3.4E+10 Unidentified 4.1E+07 9.5E+10 Ru-106 1.6E+05 4.4E+11 ......

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

The listed dose parameters are for radionuclides that may be detected in gaseous effluents. These and additional dose parameters for isotopes not included in Table 2-4 may be calculated using the methodology described in NUREG-01 33, Section 5.2.1 (reference 2).

R. E. Ginna Nuclear Power Plant ODCM-47 Rev. 28

ODCM Table 2-5 Pathway Dose Factors Due to Radionuclides Other Than Noble Gases*

Radio- Inhalation Meat Ground Plane Cow-Milk-Child Leafy nuclides Pathway Ri Pathway Ri Pathway Ri Pathway Ri Vegetables (mremlyr (m 2 xmremlyr (m 2xmremlyr (m 2 xmremlyr Pathway Ri 3

per pCifm ) per pCilsec) per pCi/sec) per pCi/sec) (m 2 xmremlyr per i*Ci/sec)

H-3 1.12E+03 2.33E+02 0 2.38E+03 2.47E+02 Cr-51 1.70E+04 4.98E+05 5.31E+06 5.75E+06 1.63E+06 Mn-54 1.57E+06 7.60E+06 1.56E+09 3.70E+07 5.38E+07 Fe-59 1.27E+06 6.49E+08 3.09E+08 4.01E+08 1.10E+08 Co-58 1.1OE+06 9.49E+07 4.27E+08 7.01E+07 4.55E+07 Co-60 7.06E+06 3.61E+08 2.44E+10 2.25E+08 1.54E+08 Zn-65 9.94E+05 1.05E+09 8.28E+08 1.99E+10 2.24E+08 Sr-89 2.15E+06 4.89E+08 2.42E+04 1.28E+10 5.39E+09 Sr-90 1.01E+08 1.01E+10 0 1.19E+10 9.85E+10 Zr-95 2.23E+06 6.09E+08 2.73E+08 8.76E+05 1.13E+08 1-131 1.62E+07 2.60E+09 1.01E+07 4.95E+11 2.08E+10 1-133 3.84E+06 6.45E+01 1.43E+06 4.62E+09 3.88E+08 Cs-134 1.01E+06 1.42E+09 7.70E+09 6.37E+10 1.96E+09 Cs-136 1.71E+05 5.06E+07 1.64E+08 6.61E+09 1.60E+08 Cs-137 9.05E+05 1.27E+09 1.15E+10 5.75E+10 1.80E+09 Ba-140 1.74E+06 5.OOE+07 2.26E+07 2.75E+08 2.03E+08 Ce-141 5.43E+05 1.45E+07 1.48E+07 1.43E+07 8.99E+07 Additional dose factors for isotopes not included in Table 2-5 may be calculated using the methodology described in NUREG-0133, Section 5.3.1 (reference 2).

R. E. Ginna Nuclear Power Plant ODCM-48 Rev. 28

ODCM 3.0 RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION 3.1 Liquid Effluent Monitors CONTROLS C.3.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.1-1 shall be OPERABLE with their Alarm/Trip setpoints set to ensure that the limits of Control C.1.1 are not exceeded. The Alarm/Trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY: At all times.

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

corrective maintenance or calibrations require instrumentation to be declared inoperable.

ACTION: With a radioactive liquid effluent monitoring instrumentation channel Alarm/

Trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

ACTION: With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.1-1. Restore the minimum number of instrumentation channels to OPERABLE status within 30 days or explain in the next Annual Radioactive Effluent Release Report, pursuant to Section 6.2 of the ODCM, why this inoperability was not corrected in a timely manner.

SURVEILLANCE REQUIREMENTS S.3.1.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 3.1-2.

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

Trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the Alarm/Trip will occur prior to exceeding the limits of 10 CFR 20.

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

R. E. Ginna Nuclear Power Plant ODCM-49 Rev. 28

ODCM Table 3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation Gross Activity Monitors (Liquid) Minimum Action Channels OPERABLE

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

b. Liquid Radwaste (R-18) 1 2

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

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

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

f. High Conductivity Waste (R-22) 1 2 R. E. Ginna Nuclear Power Plant ODCM-50 Rev. 28

ODCM Table 3.1.1 Table Notation (a) Not required when steam generator blowdown is being recovered, i.e. not released.

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

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

Note: When counting 2 independent samples for agreement, doubling the acceptance criterion for low (< 6.OE-05 pCi/ml) activity samples from 10% to 20% results in a consequence at the release point of < 1%. The expanded acceptable criterion for low activity samples is employed to compensate for increased impact of sampling and counting error on acceptance.

1. At least two independent samples of the tank's contents, taken at least 60 minutes apart, are analyzed and agree within 10% of total activity, (20% if total activity minus noble gases < 6.OE-05 iCi/ml), and

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

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

Action 3 When Steam Generator Blowdown is being released (not recycled) and the number of channels OPERABLE is less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for isotopic concentration at a lower limit of detection (LLD) of at most 1.OE-07 pCi/gram:

1. At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when the concentration of the secondary cool-ant is > 0.01 .iCi/gram (DOSE EQUIVALENT 1-131).

2. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the concentration of the secondary coolant is _<0.01 pCi/gram (DOSE EQUIVALENT 1-131).

R. E. Ginna Nuclear Power Plant ODCM-51 Rev. 28

ODCM Table 3.1-2 Radioactive Liquid Effluent Monitoring SURVEILLANCE REQUIREMENTS Gross Activity Monitor (Liquid) Channel Source Functional Channel Check Check Test Calibration

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

b. Liquid Radwaste (R-18) D(e) M(c) 0(a) R(d)

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

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

R-20B)

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

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

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

R. E. Ginna Nuclear Power Plant ODCM-52 Rev. 28

ODCM Table 3.1-2 Table Notation (a) The FUNCTIONAL Test shall also demonstrate that automatic isolation of this pathway and control room alarm will occur if any of the following conditions exist:

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

2. Power failure. (Verified in same functional test as Alarm/Trip setpoint)

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

1. Instrument indicates measured levels above the alarm setpoint.

2. Power failure. (Verified in same functional test as Alarm setpoint)

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

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

(e) Applies only during releases via this pathway.

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

R. E. Ginna Nuclear Power Plant ODCM-53 Rev. 28

ODCM 3.2 Gaseous Effluent Monitors CONTROLS C.3.2 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.2-1 shall be OPERABLE with their Alarm/Trip setpoints set to ensure that the limits of Control C.2.2 are not exceeded. The Alarm/

Trip setpoints of these channels meeting Control C.2.2 shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY: As shown in Table 3.2-1 Note: The Radioactive Effluent Monitoring Instrumentation may be removed from service for short periods of time without the instrumentation being considered inoperable for weekly grab filter or cartridge changes or monthly/quarterly testing, with the exception of the R-1 OA, R-1 1, R-1 2 skid.

Preventative/corrective maintenance, calibrations, and moving filter replacements require instrumentation to be declared inoperable.

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

ACTION: With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.2-1. Restore the minimum number of instrumentation channels to OPERABLE status within 30 days or, if not, explain in the next Annual Radioactive Effluent Release Report, pursuant to Section 6.2 of the ODCM, why this inoperability was not corrected in a timely manner.

SIiRVI=ILLANCF RFOIUIRF*MFNTS I

SURVIFILLANCERIF UIREIVIFNITS S.3.2 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCECHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 3.2-2.

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

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

R. E. Ginna Nuclear Power Plant ODCM-54 -Rev. 28

ODCM Table 3.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation Plant Ventilation (a)(h)

a. Iodine sampler (R-10B or R-14A3)

b. Particulate Sampler (R-13 or R-14A1)

C. Noble Gas Activity (R-14 or R-14A5)

d. Containment Noble Gas Activity (R-12) or Containment Particulate Sampler (R-11)

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

a. Iodine Sampler (R-1OA or R-12A3) 1 (i) 1

b. Particulate Sampler (R-11 or R-12A1) 1 (f) 5

c. Noble Gas Activity (R-12 or R-12A5) 1 (f) 5 Air Ejector Monitor (g)(h) Minimum Action Channels OPERABLE Noble Gas Activity (R-15 or R-47) 1 4 R. E. Ginna Nuclear Power Plant ODCM-55 Rev. 28

ODCM Table 3.2-1 Table Notation (a) Required at all times.

(b) Only radiation monitor R-14 has an isolation signal. If R-14A5 is being used to monitor batch gas releases, the contents of the tank(s) may be released to the environment provided that prior to initiating the release:

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

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

(c) Required in MODES 5 and 6.

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

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

This cannot be used if Containment Ventilation Isolation is required.

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

(g) Required only when Air Ejector is operating.

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

(i) Minimum channels OPERABLE for Plant Vent Iodine, Plant Vent Particulate, and Containment Purge Iodine, refers to the sample collection system - not the radia-tion monitor.

Action I If the number of OPERABLE channels is less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may con-tinue provided iodine and particulate samples are continuously collected with alternate sampling equipment as required in Table 2-1. This should be com-pleted within one hour.

R. E. Ginna Nuclear Power Plant ODCM-56 Rev. 28

ODCM Action 2 If the number of OPERABLE channels is less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may con-tinue provided grab samples are taken and analyzed for isotopic activity at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

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

Action 4 If the number of OPERABLE Channels is less than required by the Minimum Channels OPERABLE requirement and the Secondary Activity is _<1.OE-04 [ICi/

gm, effluent releases may continue via this pathway provided grab samples are analyzed for isotopic concentration at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . If the secondary activity is > 1.OE-04 1iCi/gm, effluent releases via this pathway may continue for up to 31 days provided grab samples are taken every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and analyzed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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

R. E. Ginna Nuclear Power Plant ODCM-57 Rev. 28

ODCM Table 3.2-2 Radioactive Gaseous Effluent Monitoring SURVEILLANCE REQUIREMENTS Plant Ventilation Channel Source Functional Channel Check Check Test Calibration

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

b. Iodine Sampler (R-14A3) W(e) N.A. N.A. R(c)

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

d. Particulate Sampler (R- W(e) N.A. N.A. R(c) 14A1)

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

f. Noble Gas Activity (R-14A5) D(e) M Q(b) R(c)

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

Containment Purge Channel Source Functional Channel Check Check Test Calibration

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

b. Iodine Sampler (R-12A3) W(e) N.A. N.A. R(c)

c. Particulate Sampler (R-11) W(e) M 0(a) R(c)

d. Particulate Sampler (R- W(e) M Q(b) R(c) 12A1)

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

f. Noble Gas Activity (R-12A5) D(e) M Q(b) R(c)

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

Air Ejector Monitor Channel Source Functional Channel Check Check Test Calibration

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

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

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

R. E. Ginna Nuclear Power Plant ODCM-58 Rev. 28

ODCM Table 3.2-2 Table Notation (a) The FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm occur if any of the following conditions exist:

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

2. Power failure. (Verified in same functional test as Alarm/Trip Setpoint)

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

1. Instrument indicates measured levels above the alarm setpoint.

2. Power failure. (Verified in same functional test as Alarm Setpoint for R-1 5)

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

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

(e) Applies only during releases via this pathway.

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

R. E. Ginna Nuclear Power Plant ODCM-59 Rev. 28

ODCM 3.3 Radiation Accident Monitoring Instrumentation CONTROLS C.3.3 The radiation accident monitoring instrumentation channels shown in Table 3.3-1 shall be OPERABLE according to the following schedule:

APPLICABILITY:

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

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

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

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

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

Preventative maintenance and calibrations require instrumentation to be declared inoperable.

ACTION: With less than the minimum number of radiation accident monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-1.

SURVEILLANCE REQUIREMENTS S.3.3.1 Each radiation accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION at the frequencies shown in Table 3.3-2.

BASES Radiation accident monitoring instrumentation is provided to monitor, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the Alarm will occur prior to exceeding the limits of 10 CFR 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR 50.

R. E. Ginna Nuclear Power Plant ODCM-60 Rev. 28

ODCM Table 3.3-1 Radiation Accident Monitoring Instrumentation Instrument Minimum Action Channels Operable

a. Containment Purge Beta Particulate (R-12A1) l(a) 1 Containment Purge Alpha Particulate (R-12A2) 1(a,b) <1 Containment Purge Iodine (R-12A3) 1(a) 1 Containment Purge Low-range Gas (R- 12A5) 1(a) 1 Containment Purge Mid-range Gas (R-12A7)> <1(a) 1 Containment Purge High-range Gas (R-12A9) 1(a) 1

b. Plant Vent Beta Particulate (R-14A1) 1 1 Plant Vent Alpha Particulate (R-14A2) 1(b) 1 Plant Vent Iodine (R-14A3) 1 1 Plant Vent Low-range Gas (R-14A5) 1 1 Plant Vent Mid-range Gas (R-14A7) 1 1 Plant Vent High-range Gas (R-14A9) 1 1

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

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

e. B Main Steam Line (R-32) 1 1 R. E. Ginna Nuclear Power Plant ODCM-61 Rev. 28

ODCM Table 3.3-1 Table Notation (a) Only when the shutdown purge flanges are removed; otherwise, instrumentation kept in STANDBY mode.

(b) A bad data quality alarm on PPCS for the alpha particulate channel does not ren-der the channel inoperable.

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

Action 2 R-47 is relied upon to trend and quantify primary-to-secondary leakage. If R-47 is not OPERABLE with the air ejector in service, then perform the following actions:

1. If equipment and connections are available, then have RP/Chemistry connect temporary noble gas monitor to sample air ejector off-gas and correlate moni-tor response to leak rate from an air ejector grab sample.

2. Contact RP/Chemistry and have them perform a grab sample or trend tempo-rary noble gas monitor at the frequency specified in the table below and trend the leak rate calculated based on these results.

Existing Total Leak Rate (gpd) Frequency

<5 AT LEAST once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months L5 to < 30 AT LEAST once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months z30 to < 75 AT LEAST once every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

Ž-75 Take action perAP-SG.1 guidance Last R-47 reading or grab sample result

3. If primary-to-secondary leakage > 5 gpd is evident from grab samples or tem-porary noble gas monitor, then enter procedure AP-SG1.

4. If leak rate was increasing in an unstable manner at the time that R-47 was declared inoperable and no other reliable real-time primary-to-secondary leak-age monitor correlated to gallons per day is available, then consult higher supervision and consider initiating a plant shutdown to be in MODE 3 in six (6) hours.

R. E. Ginna Nuclear Power Plant ODCM-62 Rev. 28

ODCM Table 3.3-2 Radiation Accident Monitoring Surveillance Requirements Radiation Accident Monitoring Instrumentation Channel Channel Check Calibration

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

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

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

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

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

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

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

R. E. Ginna Nuclear Power Plant ODCM-63 Rev. 28

ODCM 3.4 Area Radiation Monitors S.3.4.1 CHANNEL CALIBRATION, CHANNEL CHECK, and a FUNCTIONAL TEST of the area radiation monitors shall be performed as specified in Table 3-4.

R. E. Ginna Nuclear Power Plant ODCM-64 Rev. 28

ODCM Table 3-4 Area Radiation Monitor Surveillance Requirements Instrument Channel Functional Channel Check Test Calibration

a. Control Room R-1 D Q R

b. Containment R-2 D Q R

c. Radiochemistry Lab R-3 D Q R

d. Charging Pump Room R-4 D Q R

e. Spent Fuel Pool R-5 D Q R

f. Nuclear Sample Room R-6 D Q R

g. Incore Detector Area R-7 D Q R

h. Drumming Station R-8 D Q R

i. Letdown Line Monitor R-9 D Q R

j. Component Cooling Water Heat Exchanger

R-17 D Q R

k. AVT A Mixed Bed R-23 N.A. Q N.A.

I. AVT B Mixed Bed R-24 N.A. Q N.A.

m. AVT C Mixed Bed R-25 N.A. 0 N.A.

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

o. HCWT and LCWT R-27 N.A. Q N.A.

p. Resin Regeneration Tank R-28 N.A. Q N.A.

q. Nuclear Sample Room Wide Range Area Monitor R-33 N.A. 0 N.A.

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

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

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

R. E. Ginna Nuclear Power Plant ODCM-65 Rev. 28

ODCM 4.0 RADWASTE TREATMENT 4.1 Liquid Radwaste Treatment System CONTROLS C.4.1 The Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent to UNRESTRICTED AREAS would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31 day period.

APPLICABILITY: At all times.

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

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

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

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

SURVEILLANCE REQUIREMENTS S.4.1.1 Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Liquid Radwaste Treatment Systems are not being fully utilized.

S.4.1.2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Controls C.1.1 and C.1.2.

The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR 50, and the design objective given in Section II.D of Appendix I to 10 CFR 50. The specified limits governing the use of the appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix A to 10 CFR 50 for liquid effluents.

R. E. Ginna Nuclear Power Plant ODCM-66 Rev. 28

ODCM Figure 4-1 Liquid Radwaste Treatment Systems Effluent Paths and Controls REACTORCOOLANT DRAIN TANX-HOT LAB DRAIN EOUIPUENT DRAIN EVAPORA70R CONDENSER DEMINERALIZER-AUXILIA.Y BUILDINGSUMP BASEMENTLEVELDRAIN INTERMEDIATE EOUWPUNTDRAIN-BU.ILOING VAROUS BuIDIN fLooR _ RETEN'TION AND ECUIPUENTDRAINS TN RETENTION TANK COMPOSITE SAMPUNT CONDENSATE R-21 CIRCULATING WATER (TO LAKCE ONTARIO)

HIGH CONDuCTMTY WASTEEFFLUENT S ONTAINMENTFANCOOLER SERVICE WATER S.*pE-T FUEL POOL HEATEx STEAMGENERATORBLOWDOV R-19

, USE OF THE DEMINERALEZER AND WASTE CONDENSATETANKSWAS DISCONTINUED IN 1990.

USE OF THE LAUNDRY WAS DISCONTINUED IN 1994.

R. E. Ginna Nuclear Power Plant ODCM-67 Rev. 28

ODCM 4.2 Gaseous Radwaste Treatment System CONTROLS C.4.2 The Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY would exceed:

1. 0.2 mrad to air from gamma radiation, or

2. 0.4 mrad to air from beta radiation, or

3. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC APPLICABILITYT At all times.

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

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

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

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

SURVEILLANCE REQUIREMENTS S.4.2.1 Doses due to gaseous releases to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Gaseous Radwaste Treatment Systems are not being fully utilized.

S.4.2.2 The installed GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be considered OPERABLE by meeting Controls C.2.2, C.2.3.1, and C.2.3.2.

The OPERABILITY of the Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". This Control implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR 50, and the design objectives given in Section II.D of Appendix Ito 10 CFR 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I to 10 CFR 50, for gaseous effluents.

R. E. Ginna Nuclear Power Plant ODCM-68 Rev. 28

GAS DECAYTANK m (30 - 45 DAY DELAY)

C)

0) t -- PLANT VENT R-14. R-13.

CL R-IOB (OR Ru-I4A) 0)

0)

U) 0 Lr --------------------------------- (D 0 --q 14 0)

CONDENSER AIR EJECTOR OFF GAS VENT 0 R-15 R-47. R.48 00 CONTAINMENT SHUTDOWN H CONTAINMENT VENT 0CD PURGER R-(OR RM-1 214 -1 r*

(D

a 0

CL CO CD

ODCM 4.3 Solid Radwaste System CONTROLS C.4.3 The solid radwaste system shall be used as applicable in accordance with the Process Control Program for the solidification and packaging of radioactive waste to ensure meeting the requirements of 10 CFR 71 prior to shipment of radioactive wastes from the site.

APPLICABILITY: At all times.

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

R. E. Ginna Nuclear Power Plant ODCM-70 Rev. 28

ODCM 4.4 Configuration Changes CONTROLS C.4.4 Major changes to the Radioactive Waste Treatment Systems, (Liquid, Solid, and Gaseous), shall be reported to the Commission by the inclusion of a suitable discussion or by reference to a suitable discussion of each change in the Annual Radioactive Effluent Release Report for the period in which the changes were made. Major changes to Radioactive Waste Treatment Systems, (Liquid, Gaseous and Solid), shall include the following:

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

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

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

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

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

APPLICABILITY: At all times.

ACTION: The discussion of each change shall contain:

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

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

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

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

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

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

R. E. Ginna Nuclear Power Plant ODCM-71 Rev. 28

ODCM 4.5 Process Control Program

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

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

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

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

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

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

R. E. Ginna Nuclear Power Plant ODCM-72 Rev. 28

ODCM 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 5.1 Monitoring Program CONTROLS C.5.1 The Radiological Environmental Monitoring Program (REMP) shall be conducted as specified in Table 5-1 at the locations given in Figures 5-1, 5-2, 5-3 and 5-4.

APPLICABILITY: At all times.

ACTION: If the radiological environmental monitoring program is not conducted as specified in Table 5-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal availability, or to malfunction of automatic sampling equipment. If the latter, efforts shall be made to complete corrective action prior to the end of the next sampling period. Sampling periods for this specification are usually of one week duration. If continuous water sampling equipment is out of service, the 120 minute aliquot sampling period does not mean that grab samples must be taken every 120 minutes, but one grab sample once each week is sufficient until the automatic sampling equipment is restored to service.

ACTION: If the level of radioactivity as a result of plant effluents in an environmental sampling medium at one or more of the locations specified exceeds the reporting levels of Table 5-4 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from receipt of the laboratory analysis a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendaryear limits of Controls C.1.2, C.2.3.1, and C.2.3.2.

When more than one of the radionuclides in Table 5-4 are detected in the sampling medium, this report shall be submitted if:

concentration (1) +concenration C-) + .

limi level (l) limit level C2)

When radionuclides other than those in Table 5-4 are detected and are the result of plant effluents, this report shall be submitted ifthe potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is greater than the calendar year limit of Controls C.1.2, C.2.3.1, and C.2.3.2 This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

R. E. Ginna Nuclear Power Plant ODCM-73 Rev. 28

ODCM ACTION: With milk or fresh leafy vegetable samples unavailable from one or more of the sampling locations indicated on Figure 5-2, a discussion shall be included in the Annual Radiological Environmental Operating Report which identifies the cause for the unavailability of samples and identifies locations for obtaining replacement samples. In selecting replacement samples, consider the implications of collecting samples outside the normal REMP ingestion pathway. In particular, recognize that perennial vegetation from relatively undisturbed areas is likely to have higher concentrations of Cs-137 than vegetation grown in soil that is regularly disturbed by cultivation and harvesting activities. If a milk or leafy vegetable sample location becomes unavailable, the location from which samples were unavailable may then be deleted provided that a comparable location is added to the radiological environmental monitoring program as described in the ODCM, unless no other sample location is available.

SURVEILLANCE REQUIREMENTS 1,- .. *Tl-r. .*

SURVEILLANCE S.5.1 The radiological environmental samples shall be collected pursuant to Table 5-1 from the specific locations given in the table and figure(s) given in the ODCM, and shall be analyzed pursuant to the requirements of Table 5-1 and the detection capabilities required by Table 5-3.

BASES The REMP required by this Control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures to MEMBERS OF THE PUBLIC resulting from plant operation.

This monitoring program implementsSection IV.B.2 of Appendix I tol0 CFR 50, and thereby supplements the RETS by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979.

R. E. Ginna Nuclear Power Plant ODCM-74 Rev. 28

ODCM Table 5-1 Radiological Environmental Monitoring Program EXPOSURE PATHWAY AND/OR SAMPLE NUMBER OF SAMPLES & SAMPLING AND COLLECTION TYPE AND FREQUENCY OF SAMPLE LOCATIONS (a) FREQUENCY ANALYSIS 1 AIRBORNE

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

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

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

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

3. WATERBORNE

a. Surface (e) 1 control (Shoremont) Composite* sample collected over a Gross beta and gamma isotopic anal-1 indicator (Condenser Water Dis- period of !531 days.(f) ysis of each composite sample. Tri-charge) tium analysis of one composite sample at least once per 92 days. (d)

b. Drinking 1 indicator (Ontario Water District Same as above (f) Same as above Intake)

C. Shoreline Sediment 1 control (Shoremont) Semi-annually Gamma isotopic analysis of each 1 indicator (Ontario Water District - sample (d)

Bear Creek)

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

R. E. Ginna Nuclear Power Plant Page 75 Rev. 28

ODCM EXPOSURE PATHWAY ANDIOR SAMPLE NUMBER OF SAMPLES & SAMPLING AND COLLECTION TYPE AND FREQUENCY OF SAMPLE LOCATIONS (a) FREQUENCY ANALYSIS

4. INGESTION

a. Milk 1 control At least once per 15 days Gamma isotopic and 1-131 analysis 1 indicator of each sample.(d,g)

(June through October) 1 control At least once per 31 days Gamma isotopic and 1-131 analysis 1 indicator of each sample.(d,g)

(November through May)

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

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

1. apples

2. cherries

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

(Nearest offsite garden within 5 miles 1. broad leaf vegetationp in the highest D/Q meteorological 2. other vegetable sector or onsite garden) leaves from 3 different plant species composited R. E. Ginna Nuclear Power Plant Page 76 Rev. 28

ODCM Table 5-1 Table Notation (a) Specific parameters of distance and direction sector from the centerline of the reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 5-1 in a table and figures in the ODCM. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, inclement weather, and malfunc-tion of automatic sampling equipment. If specimens are unavailable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be doc-umented in the next Annual Radiological Environmental Operating Report. It is recog-nized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program as described in the ODCM. Submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting informa-tion identifying the cause of the unavailability of samples for the pathway and justifying the selection of the new location(s) for obtaining samples.

(b) One or more instruments, such as a pressurized ion chamber, for measuring and record-ing dose rate continuously may be used in place of, or in addition to, integrating dosime-ters. For the purposes of this table, a dosimeter is considered to be one phosphor; two or more phosphors in one packet are considered to be two or more dosimeters. Film badges shall not be used for measuring direct radiation. The 39 stations is not an abso-lute number. The number of direct radiation monitoring stations may be reduced accord-ing to geographical limitations; e.g., some sectors may be over water so that the number of dosimeters may be reduced accordingly. The frequency of analysis or readout for dosimetry systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.

(c) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 or more hours after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

(d) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

(e) The "control sample" shall be taken at a distance beyond significant influence of the dis-charge. The "indicator sample" shall be taken in an area beyond but near the mixing zone.

(f) A composite sample is one in which the quantity (aliquot) of liquid sampled is propor-tional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) rela-tive to the compositing period (e.g., monthly) in order to assure obtaining a representa-tive sample.

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

R. E. Ginna Nuclear Power Plant ODCM-77 Rev. 28

ODCM 5.2 Environmental Monitor Sample Locations All sample locations are specified on Table 5-2, a list of direction and distance to sample points.

Indicator and control samples required by the environmental program are noted by an I or a C.

Figure 5-1 shows the onsite* sample locations for airborne particulates, radioiodine and direct radiation. Also indicated on Figure 5-1 is the onsite vegetable garden, as well as the place-ment of post accident dosimeters, locations 2 - 7 and 13 - 24. Dosimeter locations 2 - 7 are co-located with the air monitor samplers. The onsite garden is located in the SE sector near the closest resident who is the real maximally exposed individual, rather than in the ESE sector which has the highest D/Q.

Figure 5-2 gives the location of the only milk herds within 5 miles of the plant. On this map is also included the Ontario Water District intake pumping station where lake water is sampled prior to treatment.

Figure 5-3 shows the offsite control locations for direct radiation as measured by dosimeters.

Figure 5-4 shows the offsite sample locations for airborne particulates, and radioiodine. Sam-ple stations 9 and 11 are situated near population centers, Webster and Williamson, located approximately 7 miles from the Ginna Site. Dosimeter locations 8 - 12 are co-located with air monitor samplers.

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

R. E. Ginna Nuclear Power Plant ODCM-78 Rev. 28

ODCM Table 5-2 Location, Direction, and Distances to Sample Points Air Sample Locations Station Type Coordinates Coordinates Direction Distance (Latitude, N) (Longitude, W) (degrees) (meters) 2 I 43.27798 77.30450 84 360 3 I 43.27643 77.30366 108 440 4 I 43.27561 77.30600 134 320 5 I 43.27602 77.30913 186 180 6 I 43.27614 77.31198 236 300 7 I 43.27724 77.31177 259 240 8 C 43.22860 77.54403 254 19840 9 I 43.21872 77.42007 234 11150 10 C 43.16360 77.32606 186 12730 11 I 43.22327 77.18756 122 11540 12 C 43.26818 76.99870 92 25170 13 I 43.27091 77.31103 193 770 Water Sample Locations Station Type Coordinates Coordinates Direction Distance (Latitude, N) (Longitude, W) (degrees) (meters)

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

Farm A I 43.24196 77.21978 119 8240 Farm B C 43.17035 77.12589 129 19030 R. E. Ginna Nuclear Power Plant ODCM-79 Rev. 28

ODCM Produce Samples Description Type Coordinates Coordinates Direction Distance (Latitude, N) (Longitude, W) (degrees) (meters)

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

farms > 10 miles Fish Samples Sediment Samples Description Type Description Type Discharge Plume I OWD Shoreline I Lake Ontario > 10 miles C Shoremont (> 10 miles) C West of Ginna Lake Ontario Benthic S Dosimeter Sample Locations Station Type Coordinates Coordinates Direction Distance (Latitude, N) (Longitude, W) (degrees) (meters) 2 I 43.27798 77.30450 84 360 3 I 43.27643 77.30366 108 440 4 I 43.27561 77.30600 134 320 5 I 43.27602 77.30913 186 >180

>6 I 43.27614 77.31198 236 300 7 I 43.27724 77.31177 259 240 8 C 43.22860 77.54403 254 19840 9 I 43.21872 77.42007 234 11150 10 C 43.16360 77.32606 186 12730 11 I 43.22327 77.18756 122 11540 12 >C> 43.26818 76.99870 92 25170 13 I 43.27889 77.31157 303 260 14 I 43.28032 77.31886 290 860>

15 I 43.27708 77.32016 266 920 16 I 43.27310 77.31993 241 1030 17 I 43.27347 77.31162 206 510 R. E. Ginna Nuclear Power Plant ODCM-80 Rev. 28

ODCM 18 I 43.27122 77.31082 192 730 19 I 43.27346 77.30868> 178 460 20 I 43.27202 77.30650 163 650 21 I 43.27279 77.30408 144 660 22 I 43.27284 77.29960 125 920 23 I 43.27564 77.29969 107 780 24 I 43.27797 77.29993 87 730 25 C 43.23026 77.46891 248 14000 26 C 43.18249 77.43311 224 14600 27 C 43.16017 77.37563 203 14120 28 C 43.14851 77.18617 145 17450 29 C 43.23817 77.14423 108 14050 30 C 43.23687 >77.05909 103 20760 31 I 43.26868 77.39841 262 7330 32 I 43.25309 77.37582 243 6070 33 I 43.22451 77.37458 222 7950 34 I 43.22582 77.34687 208 6520 35 I 43.21207 77.33044 193 7490 36 I 43.22840 77.30405 176 5480 37 I 43.22933 77.28251 158 5770 38 I 43.23135 77.25186 138 6910 39 I 43.25321 77.23025 113 6930 40 I >43.28071 77.22961 87 6440 63 I 43.27892 77.32344 228 740 64 I 43.27320 77.31571 277 1190 Table 5-2 Notes:

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

Directions and Distance are noted from the centerline of the reator I = Indicator Sample C = Control or background sample S = Supplemental sample R. E. Ginna Nuclear Power Plant ODCM-81 Rev. 28

ODCM Figure 5-1 Location of Onsite Air Monitors and Dosimeters ODCM R. E. Ginna Nuclear Power Plant ODCM-82 Rev. 28

0-0 0

-h

-n (fu 0

C) 0l T (DCD (A

A).

0, 10 KM Milk Sample Station

ODCM Figure 5-3 Location of Offsite Dosimeters A

Z-r" c-i

-J I-LI R. E. Ginna Nuclear Power Plant ODCM-84 Rev. 28

r-0 0,

0 0-0 (fl- 0 Dic 0

0 aI 5 Miles 10 KM

ODCM Table 5-3 Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD)

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

(PCilm/3 ) wet dry gross beta 4(a) 1.OE-02 3-H 2000 (I000)(a) 54-Mn 15 130 59-Fe 30 260 58, 60-Co 15 130 65-Zn 30 260 95-Zr-Nb 15(b) 131-1 1 7.OE-02 1 60 134,137-Cs 15(10)(a), 1.OE-02 130 15 60 150 18 140-Ba-La 15(b) 15(b)

R. E. Ginna Nuclear Power Plant ODCM-86 Rev. 28

ODCM Table 5-3 Table Notation (a) LLD for drinking water (b) Total for parent and daughter The LLD shall be calculated as described in Notation (a) to Table 1-1 R. E. Ginna Nuclear Power Plant ODCM-87 Rev. 28

ODCM Table 5-4 Reporting Levels for Radioactivity Concentrations in Environmental Samples Analysis Water Airbourne Fish Milk Broad Leaf (pCill) Particulateor (pCilkg,wet) (pCi/l) Vegetables Gas (pCi/kg, wet)

(pCi/mr3)

H-3 2.0E+04 Mn-54 1000 3.OE+04 Fe-59 400 1.0E+04 Co-58 1000 3.OE+04 Co-60 300 1.OE+04 Zn-65 300 2.OE+04 Zr-Nb-95 400(a) 1-131 2 0.9 3 1.OE+02 Cs-134 30 10 1.OE+03 60 1.OE+03 Cs-137 50 20 2.OE+03 70 2.OE+03 Ba-La-140 200(a) 300 R. E. Ginna Nuclear Power Plant ODCM-88 Rev. 28

ODCM Table 5-4 Table Notation (a) Total for parent and daughter Decay correction in analysis of environmental samples is taken from the end of the sampling time not from the midpoint of the sample period.

R. E. Ginna Nuclear Power Plant ODCM-89 Rev. 28

ODCM Table 5-5 DIQ and XIQ 5 Year Average 1995 - 1999 Plant Vent Distance to section boundary in meters:

Direction 804m 1609m 2416m 3218m 4022m 4827m 5632m 6436m 7240m 8046m DIO N 1.74E-09 8.20E-10 5.54E-10 3.36E-10 2.45E-10 1.85E-10 1.41E-10 1.13E-10 I.O1E-10 3.86E-10 NNE 1.18E-09 6.28E-10 3.99E-10 2.75E-1O0 2.02E-10 1.53E-10 1.29E-10 9.54E-11 8.50E-11 2.26E-10 NE 1.74E-09 1.84E-09 6.26E-10 3.86E-10 2.83E-10 2.14E-10 1.64E-10 1.32E-10 1.09E-10 9.17E-11 ENE 2.99E-09 1.43E-09 8.56E-10 5.76E-10 4.25E-10 3.14E-10 2.39E-10 1.91E-10 1.58E-10 1.32E-10 E 5.11E-09 2.20E-09 1.23E-09 7.96E-10 5.69E-10 4.17E-10 5.09E-10 6.34E-10 4.74E-10 4.OOE-10 ESE 7.41E-09 3.19E-09 1.67E-09 1.13E-09 9.34E-10 9.18E-10 7.27E-10 5.16E-10 4.26E-10 3.54E-10 SE 4.14E-09 1.93E-09 9.91E-10 7.32E-10 7.05E-10 5.40E-1O0 4.OOE-10 3.05E-10 2.52E-10 2.09E-10 SSE 1.32E-09 6.71E-10 3.72E-10 2.68E-10 2.58E-10 1.88E-10 1.38E-10 2.76E-10 8.94E-11 7.48E-11 S 2.15E-09 1.29E-09 7.37E-10 6.54E-10 4.95E-10 3.58E-10 2.61E-10 2.02E-10 1.67E-10 1.39E-10 SSW 2.57E-09 1.48E-09 8.43E-10 5.50E-10 4.OOE-10 3.95E-10 2.87E-10 2.22E-10 1.83E-10 1.52E-10 SW 2.88E-09 1.53E-09 8.50E-10 5.66E-10 4.79E-10 4.41E-10 3.20E-10 2.49E-10 2.05E-10 1.71E-10 WSW 2.21E-09 1-18E-09 6.93E-10 4.73E-10 3.57E-10 3.04E-10 4.38E-10 3.39E-10 2.80E-10 2.33E-10 W 9.54E-10 5.40E-10 3.27E-10 2.21E-10 1.61E-10 1.20E-10 1.76E-10 2.71E-10 2.25E-10 1.87E-10 WNW 1.29E-10 9.58E-11 6.87E-11 4.91E-11 1.18E-10 2.83E-11 2.23E-11 1.82E-11 1.51E-11 1.27E-11 NW 4.80E-10 3-03E-10 2.03E-10 l.41E-10 1.05E-10 8.01E-11 6.25E-11 5.05E-11 4.20E-11 3.52E-11 NNW 1.37E-09 7.06E-10 4.40E-10 3.01E-10 2.21E-10 1.73E-10 1.29E-10 1.03E-10 8.59E-11 7.19E-11 R. E. Ginna Nuclear Power Plant Page 90 Rev. 28

ODCM Direction 804m 1609m 2416m 3218m 4022m 4827m 5632m 6436m 7240m 8045m X/Q N 8.56E-08 9.42E-08 9.19E-08 8.10E-08 6.99E-08 6.15E-08 5.38E-08 5.41E-08 6.17E-08 1.20E-07 NNE 7.17E-08 8.06E-08 8.23E-08 7.45E-08 7.21E-08 5.83E-08 5.28E-08 4.81E-08 6.98E-08 1.33E-07 NE 8.27E-08 9.48E-08 9.36E-08 8.33E-08 7.23E-08 6.94E-08 5.63E-08 5.05E-08 4.57E-08 4.18E-08 ENE 1.05E-07 1.16E-07 1.06E-07 8.89E-08 7.41E-08 6.26E-08 5.35E-08 4.66E-08 4.13E-08 3.70E-08 E 1.91E-07 1.81E-07 1.53E-07 1.16E-07 9.09E-08 7.32E-08 8.82E-08 7.67E-08 6.51E-08 5.61E-08 ESE 2.43E-07 2.13E-07 1.70E-07 1.35E-07 1.11E-07 9.27E-08 7.19E-08 5.86E-08 4.96E-08 4.27E-08 SE 1.47E-07 1.38E-07 1.15E-07 1.12E-07 9.67E-08 7.43E-08 5.79E-08 5.33E-08 5.21E-08 3.44E-08 SSE 6.06E-08 6.56E-08 5.66E-08 5.38E-08 4.55E-08 3.40E-08 2.64E-08 2.16E-08 1.83E-08 1.58E-08 S 1.06E-07 1.49E-07 1.27E-07 9.80E-08 7.10E-08 5.27E-08 4.09E-08 3.34E-08 2.83E-08 2.42E-08 SSW 1.06E-07 1.59E-07 1.54E-07 1.04E-07 7.61E-08 6.96E-08 5.35E-08 4.35E-08 3.68E-08 3.16E-08 SW 1.06E-07 1.39E-07 1.43E-07 1.18E-07 1.01E-07 9.76E-08 7.60E-08 6.22E-08 5.27E-08 4.53E-08 WSW 1.13E-07 1.40E-07 1.33E-07 1.23E-07 1.20E-07 1.302-07 1.47E-07 1.20E-07 1.02E-07 8.78E-08 W 7.19E-08 1.07E-07 9.56E-08 7,99E-08 6.66E-08 5.67E-08 9.77E-08 9.14E-08 7.77E-08 6.68E-08 WNW 6.07E-09 1.64E-08 1.96E-08 1.87E-08 1.68E-08 1.49E-08 1.33E-08 1.20E-08 1.08E-08 9.88E-09 NW 1.99E-08 3.49E-08 3.64E-08 3.24E-08 2.80E-08 2 42E-08 2.11E-08 1.86E-08 1.66E-08 1.50E-08 NNW 6.23E-08 6.98E-08 6.67E-08 5.74E-08 4.86E-08 4.15E-08 3.58E-08 3.20E-08 2.80E-08 2.53E-08 R. E. Ginna Nuclear Power Plant Page 91 Rev. 28

ODCM Table 5-6 D/Q and X/Q 5 Year Average 1995 - 1999 Containment Vent Distance to section boundary In meters:

Direction 804m 1609m 2416m 3218m 4022m 4827m 5632m 6436m 7240m 8045m D/Q N 1.88E-08 5.95E-09 2.88E-09 1.85E-09 1.31E-09 9.45E-10 6.86E-10 5.31E-10 4.42E-10 3.90E-10 NNE 1.86E-08 5.88E-09 2.85E-09 1.83E-09 1.29E-09 9.35E-10 6.79E-10 5.25E-10 4.39E-10 3.90E-10 NE 1.99E-08 6.30E-09 3.05E-09 1.96E-09 1.38E-09 1.00E-09 7.27E-10 5.62E-10 4.64E-10 3.86E-10 ENE 1,98E-08 6.28E-09 3.04E-09 1.95E-09 1.38E-09 1.08E-09 7.24E-10 5.60E-10 4.62E-10 3.84E-10 E 1.99E-08 6.30E-09 3.05E-09 1.96E-09 1.38E-09 1.00E-09 7.41E-10 5.75E-10 4.75E-10 3.95E-10 ESE 1,78E-08 5.66E-09 2.74E-09 1.77E-09 1.27E-09 9.19E-10 6.67E-10 5.16E-10 4.11E-10 3.54E-10 SE 1.01E-08 3.23E-09 1.57E-09 1.05E-09 7.51E-10 5.43E-10 3.94E-10 3.05E-10 2.52E-10 2,09E-10 SSE 3.66E-09 1.18E-09 5.75E-10 3.92E-10 2.85E-10 2.06E-10 1.50E-10 1,16E-10 9.56E-11 7.94E-11 S 6.65E-09 2.14E-09 1.07E-09 7.06E-10 4.99E-10 3.60E-10 2.62E-10 2.02E-10 1.67E-10 1.39E-10 SSW 7.05E-09 2.28E-09 1.17E-09 7.53E-10 5.35E-10 3.95E-10 2.87E-10 2.22E-10 1.83E-10 1.52E-10 SW 7.77E-09 2.50E-09 1.22E-09 7.94E-10 5.98E-10 4.43E-10 3.22E-10 2.49E-10 2.05E-10 1.71E-10 WSW 1.04E-08 3.32E-09 1.61E-09 1.04E-09 7.44E-10 5.64E-10 4.39E-10 3.39E-10 2.80E-10 2.33E-10 W 8.42E-09 2.68E-09 1.30E-09 8.33E-10 5.89E-10 4.27E-10 3.46E-10 2.72E-10 2.25E-10 1.87E-10 WNW 2.68E-09 1.18E-09 4.16E-10 2.67E-10 1.89E-10 1.36E-10 9.92E-11 7.67E-11 6.34E-11 5.27E-11 NW 5.20E-09 1.66E-09 8.05E-10 5.16E-10 3.65E-10 2.64E-10 1.92E-10 1.48E-10 1.23E-10 1.02E-10 NNW 1.13E-08 3.58E-09 1.74E-09 1.12E-09 7.88E-10 5.70E-10 4.14E-10 3.202-10 2.652-10 2.202-10 R. E. Ginna Nuclear Power Plant Page 92 Rev. 28

ODCM Direction 804m 1609m 2416m 3218m 4022m 4827m 5632m 6436m 7240m 8045m XIQ N 1.73E-06 6.24E-07 3.58E-07 2.44E-07 1.52E-07 1.42E-07 1.15E-07 9.67E-08 9.34E-08 9.86E-08 NNE 2.15E-06 7.57E-07 4.37E-07 3.01E-07 2.26E-07 1.78E-07 1.46E-07 1.24E-07 1.26E-07 1.48E-07 NE 1.94E-06 7.OOE-07 3.99E-07 2.70E-07 2.00E-07 1.55E-07 1.25E-07 1.05E-07 9.02E-08 7.88E-08 ENE 1.20E-06 4.40E-07 2.46E-07 1.64E-07 1.19E-07 9.14E-08 7.26E-08 6.03E-08 5.17E-08 4.50E-08 E 1.05E-06 3.91E-07 2.18E-07 1.44E-07 1.03E-07 7.84E-08 6.58E-08 5.39E-08 4.59E-08 3.96E-08 ESE 8.27E-07 3.15E-07 1.83E-07 1.24E-07 8.99E-08 6.76E-08 5.27E-08 4.32E-08 3.67E-08 3.16E-08 SE 5.82E-07 2.44E-07 1.56E-07 1.17E-07 8.36E-08 6.27E-08 4.88E-08 4.OOE-08 3.39E-08 2.92E-08 SSE 3.27E-07 1.42E-07 8.76E-08 6.27E-08 4.44E-08 3.31E-08 2.57E-08 2.09E-08 1.77E-08 1.52E-08 S 5.09E-07 2.29E-07 1.40E-07 8.96E-08 6.92E-08 4.71E-08 3.65E-08 2.98E-08 2.52E-08 2.16E-08 SSW 4.64E-07 2.44E-07 1.61E-07 1.03E-07 7.31E-08 5.49E-08 4.27E-08 3.49E-08 2.95E-08 2.54E-08 SW 4.99E-07 2.52E-07 1.95E-07 1.36E-07 1.OOE-07 7.59E-08 5.94E-08 4.87E-08 4.13E-08 3.56E-08 WSW 9.88E-07 3.99E-07 2.57E-07 1.99E-07 1.61E-07 1.37E-07 1.11E-07 9.16E-08 7.79E-08 6.73E-08 W 9.24E-07 3.62E-07 2.15E-07 1.49E-07 1.10E-07 8.62E-08 8.29E-08 6.83E-08 5.82E-08 5.03E-08 WNW 3.25E-07 1.26E-07 7.51E-08 5.22E-08 3.92E-08 3.08E-08 2.51E-08 2.11E-08 1.83E-08 1.60E-08 NW 5.27E-07 1.98E-07 1.14E-07 7.80E-08 5.78E-08 4.50E-08 3.62E-08 3.03E-08 2.62E-08 2.29E-08 NNW 9.39E-07 3.46E-07 1.98E-07 1.34E-07 9.89E-08 7.65E-08 6.13E-08 5.12E-08 4.41E-08 3.85E-08 R. E. Ginna Nuclear Power Plant Page 93 Rev. 28

ODCM Table 5-7 D/Q and X/Q 5 Year Average 1995 - 1999 Air Ejector Distance to section boundary in meters:

Direction 804m 1609m 2416m 3218m 4022m 4827m 5632m 6436m 7240m 8045m DIQ N 2.02E-08 6.38E-09 3.09E-09 1.98E-09 1.40E-09 1.01E-09 7.34E-10 5.68E-10 4.69E-10 3.90E-10 NNE 2.07E-08 6.55E-09 3.17E-09 2.03E-09 1.44E-09 1.04E-09 7.54E-10 5.83E-10 4.81E-10 4.00E-10 NE 2.11E-08 6.66E-09 3.22E-09 2.07E-09 1.46E-09 1.06E-09 7.67E-10 5.93E-10 4.89E-10 4.07E-10 ENE 2.05E-08 6.49E-09 3.14E-09 2.01E-09 1.42E-09 1.03E-09 7.47E-10 5.77E-10 4.77E-10 3.96E-10 E 2.04E-08 6.46E-09 3.13E-09 2.01E-09 1.42E-09 1.02E-09 7.43E-10 5.75E-10 4.75E-10 3.95E-10 ESE 1.84E-08 5.80E-09 2.81E-09 1.80E-09 1.27E-09 9.19E-10 6.67E-10 5.16E-10 4.26E-10 3.54E-10 SE 1.08E-08 3.43E-09 1.66E-09 1.06E-09 7.51E-10 5.43E-10 3.94E-10 3.05E-10 2.52E-10 2.09E-10 SSE 4.12E-09 1.30E-09 6.30E-10 4.04E-10 2.85E-10 2.06E-10 1.50E-10 1.16E-10 9.56E-11 7.94E-11 S 7.19E-09 2.27E-09 1.10E-09 7.06E-10 4.99E-10 3.60E-10 2.62E-10 2.02E-10 1.67E-10 1.39E-10 SSW 7.89E-09 2.49E-09 1.21E-09 7.74E-10 5.47E-10 3.95E-10 2.87E-10 2.22E-10 1.83E-10 1.52E-10 SW 8.85E-09 2.80E-09 1.35E-09 8.68E-10 6.13E-10 4.43E-10 3.22E-10 2.49E-10 2.05E-10 1.71E-10 WSW 1.21E-08 3.82E-09 1.85E-09 1.18E-09 8.37E-10 6.05E-10 4.39E-10 3.39E-10 2.80E-10 2.33E-10 W 9.68E-09 3.06E-09 1.48E-09 9.49E-10 6.71E-10 4.85E-10 3.52E-10 2.72E-10 2.25E-10 1.87E-10 WNW 3.28E-09 1.04E-09 5.54E-10 3.22E-10 2.51E-10 1.64E-10 1.19E-10 9.22E-11 7.62E-11 6.33E-11 NW 5.88E-09 1.86E-09 8.99E-10 5.77E-10 4.07E-10 2.94E-10 2.14E-10 1.65E-10 1.37E-10 1.13E-10 NNW 1.22E-08 3.84E-09 1.86E-09 1.19E-09 8.43E-10 6.09E-10 4.42E-10 3.42E-10 2.82E-10 2.35E-10 R. E. Ginna Nuclear Power Plant Page 94 Rev. 28

ODCM Direction 804m 1609m 241Gm 3218m 4022m 4827m 6632m 6436m 7240m 8045m XIQ N 2.34E-06 8.13E-07 4.56E-07 3.06E-07 2.24E-07 1.72E-07 137E-07 1.13E-07 9.72E-08 8.43E-08 NNE 3.01E-06 1.02E-06 5.81E-07 3.94E-07 2.91E-07 2.25E-07 1.80E-07 1.49E-07 1.28E-07 1.11E-07 NE 2.48E-06 8.70E-07 4.88E-07 3.27E-07 2.40E-07 1.84E-07 1.47E-07 1.21E-07 1.04E-07 9.01E-08 ENE 1.51E-06 5.37E-07 2.94E-07 1.92E-07 1.39E-07 1.05E-07 8.25E-08 6.79E-08 5,79E-08 5.01E-08 E 1.28E-06 4.52E-07 2-44E-07 1.58E-07 1.13E-07 8.50E-08 6.65E-08 5-46E-08 4.65E-08 4.01E-08 ESE 9.59E-07 3.28E-07 1.75E-07 1.13E-07 8.09E-08 6.08E-08 4,75E-08 3.90E-08 3.31E-08 2.85E-08 SE 7.73E-07 2.65E-07 1.42E-07 9.20E-08 6.57E-08 4.95E-08 3.87E-08 7.93E-05 2.70E-08 2.33E-08 SSE 4.47E-07 1.54E-07 8.18E-08 5.27E-08 3.75E-08 2.80E-08 2,18E-08 1.79E-08 1.52E-08 1.68E-08 S 6.59E-07 2.27E-07 1.21E-07 7.75E-08 5.49E-08 4.11E-08 3.20E-08 2.61E-08 2.21E-08 1.90E-08 SSW 6.43E-07 2.22E-07 1-19E-07 7.73E-08 5.52E-08 4.16E-08 3.25E-08 2.67E-08 2.26E-08 1.95E-08 SW 7.75E-07 2.65E-07 1.45E-07 9.61E-08 6.96E-08 5.31E-08 4.19E-08 3.46E-08 2.95E-08 2.55E-08 WSW 1.49E-06 5.11E-07 2.86E-07 1.91 E-07 1,40E-07 1.08E-07 8.58E-08 7.11E-08 6.08E-08 5.27E-08 W 1.29E-06 4.52E-07 2,51E-07 1,67E-07 1.22E-07 9.30E-08 7.37E-08 6.09E-08 5.21E-08 4.51E-08 WNW 5.27E-07 1.88E-07 1.05E-07 6.99E-08 5.10E-08 3.91E-08 3,1OE-08 2.56E-08 2.19E-08 1.90E-08 NW 7.90E-07 2.79E-07 1.54E-07 1.02E-07 7.39E-08 5.63E-08 4.45E-08 3.67E-08 3.14E-08 2.71E-08 NNW 1.28E-06 4.51E-07 2.49E-07 1.64E-07 1.19E-07 9.06E-08 7.15E-08 5.90E-08 5.04E-08 4.36E-08 R. E. Ginna Nuclear Power Plant Page 95 Rev. 28

ODCM 5.3 Land Use Census CONTROL C.5.3 A Land Use Census shall be conducted annually between June 1 and October 1, and shall identify within a distance of 5 miles the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 square feet producing broad leaf vegetation. (In lieu of a garden census, broad leaf vegetation sampling of at least three different kinds of vegetation may be performed in an onsite garden located in the meteorological sector with the highest average annual growing season deposition parameter (D/Q) OR another location with a higher D/Q than the location of the maximally exposed individual.)

APPLICABILITY: At all Times.

ACTION: With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Surveillance S.2.3.2.1 of the ODCM, identify the new location(s) in the next Annual Radioactive Effluent Release Report.

ACTION: With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Control C.5.1, add the new location(s) within 30 days to the REMP described in the ODCM, if permission from the owner to collect samples can be obtained and sufficient sample volume is available. The sampling location(s), excluding Control location(s), having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling location(s).

SURVEILLANCE REQUIREMENTS S.5.3 The Land Use Census shall be conducted between June 1 and October 1 of each year using a method that will best provide the necessary information such as by door-to-door survey, vehicular survey, aerial survey, or by consulting local agricultural authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Control C.6.1 of the ODCM.

BASES This specification is provided to ensure that changes in the use of areas at or beyond the SITE BOUNDARY are identified and that modifications to the REMP given in the ODC Mare made if required by the results of this census. Information from methods such as the door-to door survey, vehicular survey, aerial survey, or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of SectionlV.B.3 of Appendix I to 10 CFR 50. Restricting the census to R. E. Ginna Nuclear Power Plant ODCM-96 Rev. 28

ODCM gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored, since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) there was a vegetation yield of 2 kg/m 2 .

R. E. Ginna Nuclear Power Plant ODCM-97 Rev. 28

ODCM 5.4 Interlaboratory Comparison Program CONTROL C.5.4 Analyses shall be performed on all radioactive materials supplied as part of an Interlaboratory Comparison Program, that correspond to samples required by the REMP, and that has been approved by the Commission, if such a program exists.

APPLICABILITY: At all times.

ACTION: With analyses not performed as required above, report the corrective actions taken to prevent recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Control C.6.1 of the ODCM.

SURVEILLANCE REQUIREMENTS S.5.4.1 The Interlaboratory Comparison Program is described in and implemented by procedure CH-QC-INTERLAB. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Control C.6.1 of the ODCM.

BASES The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the Quality Assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to10 CFR 50.

R. E. Ginna Nuclear Power Plant ODCM-98 Rev. 28

ODCM 6.0 REPORTING REQUIREMENTS 6.1 Annual Radiological Environmental Operating Report An Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 15 of each year. The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with background (control) samples and previous environ-mental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The report shall also include the results of the Land Use Census as required.

This report shall include any new location(s) identified by the Land Use Census which yield a calculated dose or dose commitment greater than those forming the basis of Control C.5.1 The report shall also contain a discussion which identifies the causes of the unavailability of milk or leafy vegetable samples and identifies locations for obtaining replacement samples in accordance with Control C.5.1 The Annual Radiological Environmental Operating Report shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures of Section 5.0 of the ODCM, the summarized and tabulated results of these analyses and measurements shall be in the format of Table 6-1, derived from the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some results are not available for inclu-sion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The report shall also include the following:

a. a summary description of the radiological environmental monitoring program including a map of all sampling locations keyed to a table giving distances and directions from the reactor centerline; and

b. the results of the licensee participation in an Interlaboratory Comparison Program, and the corrective actions taken if the specified program is not being performed as required by Control C.5.4.

c. a discussion of all deviations from the sampling schedule specified in Table 5-1.

d. a discussion of any environmental sample measurements that exceed the reporting levels but are not the result of plant effluents, as required in the second ACTION of C.5.1.

e. a discussion of all analyses in which the required LLD was not achievable.

R. E. Ginna Nuclear Power Plant ODCM-99 Rev. 28

ODCM 6.2 Annual Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year of operation shall be submitted prior to May 15 each year. This report shall include a summary, on a quarterly basis, of the quantities of radioactive liquid and gaseous effluents and solid waste released as outlined in Regulatory Guide 1.21, Revision 1, with data summarized on a quarterly basis following the format of the Appendix thereof. For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories:

classes of solid wastes (as defined by 10 CFR 61), type of container (e.g. LSA, Type A, Type B, etc.) and solidification agent or absorbent (e.g., Portland cement).

The Radioactive Effluent Release Report shall include an assessment of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each of the previous four calendar quarters as outlined in Regulatory Guide 1.21, Revision 1. In addition, the site boundary maximum noble gas gamma air and beta air doses shall be evaluated. The assess-ment of radiation doses shall be performed in accordance with Controls 1.2 and 2.3. This same report shall include an annual summary of hourly meteorological data collected over the previous calendar year. Alternatively, the licensee has the option of retaining this summary on site in a file that shall be provided to the NRC upon request. The Radioactive Effluent Release Report shall include a discussion which identifies the circumstances which prevented any required detection limits for effluent sample analyses being met. This report shall also include an assessment of the radiation doses from radioactive gaseous and liquid effluents to MEM-BERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period. The assessment of radiation doses shall be performed in accordance with the method-ology and parameters in the ODCM.

The Annual Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely maximum exposed MEMBER OF THE PUBLIC from reactor operation, including doses from effluent releases and direct radiation, for the previous calendar year to demonstrate compliance with 40 CFR 190.

This report shall include a list and description of unplanned releases from the site to UNRE-STRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

This report shall include any changes made during the reporting period to the Offsite Dose Cal-culation Manual (ODCM). Licensee may make changes to this ODCM and shall submit to the Commission, with the Radioactive Effluent Release Report for the period in which any change(s) is made, a copy of the new ODCM and a summary containing:

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

b. a determination that the change will not reduce the accuracy or reliability of dose calcula-tions or setpoint determinations; and

c. documentation of the fact that the change has been reviewed and found acceptable by the Plant Operations Review Committee.

Licensee initiated changes shall become effective after review and acceptance by the Plant Operations Review Committee on a date specified by the licensee.

R. E. Ginna Nuclear Power Plant ODCM-100 Rev. 28

ODCM This report shall include any changes made during the reporting period to the Process Control Program (PCP). This report shall include a discussion of any major changes to the radioactive waste treatment systems.

The Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report will be prepared and submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555 and a copy to the Regional Administrator of the USNRC, Region I.

R. E. Ginna Nuclear Power Plant ODCM-101 Rev. 28

ODCM 6.3 Special Reports Guidance is given for each of these reports in the applicable Control. The following general guidelines are included here for calculating dose to an exposed individual or the MEMBERS OF THE PUBLIC for preparation of Special Reports:

a. The maximally exposed real MEMBER OF THE PUBLIC will generally be the same individ-ual considered in the ODCM.

b. Dose contributions to the maximally exposed individual need only be considered to be those resulting from the Ginna plant itself. All other uranium fuel cycle facilities or opera-tions are of sufficient distance to contribute a negligible portion of the individual's dose.

c. For determining the total dose to the maximally exposed individual from the major gaseous and liquid effluent pathways and from direct radiation, dose evaluation techniques used in preparing the Special Report will be those described in the ODCM, or other applicable methods where appropriate.

d. The contribution from direct radiation may be estimated by effluent dispersion modeling or calculated from the results of the environmental monitoring program for direct radiation.

R. E. Ginna Nuclear Power Plant ODCM-102 Rev. 28

ODCM Table 6-1 Environmental Radiological Monitoring Program Summary CONSTELLATION ENERGY RE. GINNA NUCLEAR POWER PLANT - Docket No. 50-244 WAYNE, NEW YORK Pathway Sampled Type And LLD Indicator Location With Highest Annual Mean Control Locations Unit Of Measurement Total Number Locations Of Analyses Mean (a) Range Name, Distance Mean (a) Range Mean (a) Range And Direction Air: Particulate Gross Beta (pCi/Cu.M.)

Gamma Scan Iodine Gamma Scan Direct Dosimetry Gamma Radiation: (mrem/quarter)

Water: Drinking Gross Beta (pCi/liter)

Gamma Scan Iodine Surface Gross Beta (pCi/liter)

Gamma Scan Iodine Shoreline Sediment Gamma Scan Milk: (pCi/liter) Iodine Gamma Scan Fish: Gamma Scan Vegetation: Gamma Scan (a) Mean and range based on detectable measurements only. Fraction of detectable measurements at specified locations in parentheses.

R. E. Ginna Nuclear Power Plant Page 103 Rev. 28

ODCM

7.0 REFERENCES

1. R. E. Ginna Nuclear Power Plant Unit No. 1, Appendix A to Operating License No.DPR-18, Technical Specifications, Rochester Gas and Electric Corporation, Docket 50-244

2. USNRC, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, NUREG-0133 (October, 1978).

3. USNRC, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Regulatory Guide 1.109, Revision 1 (October 1977).

4. "R.E. Ginna Nuclear Power Plant Tracer Dilution Study for the Town of Ontario Municipal Drinking Water Intake," HydroQual, Inc. (May 28, 2010)

5. R. E. Ginna Nuclear Power Plant, Calculations to Demonstrate Compliance with the Design Objectives of 10 CFR Part 50, Appendix I, Rochester Gas and Electric Corporation, (June, 1977).

6. USNRC, Methods for Estimating Atmospheric Transport and dispersion of Gaseous Efflu-ents in Routine Releases from Light-Water-Cooled Reactors, Regulatory Guide 1.111, Revision 1 (July, 1977).

7. R. E. Ginna Nuclear Power Plant, Incident Evaluation, Ginna Steam Generator Tube Fail-ure Incident January 25, 1982, Rochester Gas and Electric Corporation, (April12, 1982).

8. Pelletier, C. A., et. al., Sources of Radioiodine at Pressurized Water Reactors, EPRI NP-939 (November 1978).

9. NUREG-1301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for pressurized Water Reactors

10. International Commission on Radiological Protection, Publication 30 Supplement to Part I, "Limits for Intake of Radionuclides by Workers" (July 1978).

11. International Commission on Radiological Protection (ICRP) Publication 2, "Permissible Dose For Internal Radiation," 1959.

12. Nuclear Regulatory Commission Reg. Guide 1.21, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste," Revision 1, June 1974.

13. Nuclear Regulatory Commission Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implement-ing Appendix I," Revision 1, April 1977.

14. Title 10 Code of Federal Regulation Part 20 (10 CFR 20), Standards for Protection Against Radiation.

15. Title 10 Code of Federal Regulation Part 61 (10 CFR 61), Licensing Requirements for Land Disposal of Radioactive Waste.

16. Title 10 Code of Federal Regulation Part 71 (10 CFR 71), Packaging and Transportation of Radioactive Material.

17. Title 40 Code of Federal Regulation Part 141 (40 CFR 141), National Primary Drinking Water Standards.

18. Title 40 Code of Federal Regulation Part 190 (40 CFR 190), Environmental Radiation Pro-tection Standards for Nuclear Power Operations.

R. E. Ginna Nuclear Power Plant ODCM-104 Rev. 28

ODCM PDF files for Offsite Dose Calculation Manual (ODCM) are maintained in FCMS R. E. Ginna Nuclear Power Plant ODCM-105 Rev. 28

ATTACHMENT 3 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1, 2013 - DECEMBER 31, 2013 R.E. Ginna Nuclear Power Plant, LLC May 13, 2014

SExeton Generation ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT:

JANUARY 1, 2013 - DECEMBER 31, 2013 MAY 2014 R.E. Ginna Nuclear Power Plant 1503 Lake Road Ontario, New York 14519

January 1 - December 31, 2013 Docket Nos. 50-244 TABLE OF CONTENTS LIST O F FIG URES .............................................................................................................................. ii LIST O F TA BLES ............................................................................................................................... III

1. EX EC UTIV E SU M M ARY .......................................................................................................... I

2. IN TRO DUCTIO N ........................................................................................................................ 2 2.1 Station Description .................................................................................................................. 2 2.2 Program Description and Background .............................................................................. 2 2.3 Program Objectives ............................................................................................................. 2

3. PRO G RA M D ESCRIPTIO N ................................................................................................... 3 3.1 Sam ple Collection and Analysis ....................................................................................... 3 3.2 Data Interpretation ............................................................................................................. 3 3.3 Q uality A ssurance Program .............................................................................................. 3 3.4 Land Use Survey ............................................................................................................ 4 3.5 Program Exceptions .......................................................................................................... 5 3.6 Corrections to Previous Reports ........................................................................................ 6

4. RESU LTS A N D D ISCU SSION S ............................................................................................ 6 4.1 A quatic Environm ent ........................................................................................................ 6 4.1 .a Surface and Drinking W ater ........................................................................................ 6 4.1 .b Aquatic Organism s ...................................................................................................... 7

4. .c Shoreline Sedim ent ..................................................................................................... 7 4.2 A tm ospheric Environm ent ................................................................................................ 7 4.2.a Air Iodine ......................................................................................................................... 8 4.2.b A ir Particulate Filters ................................................................................................... 8 4.3 Terrestrial Environm ent ..................................................................................................... 8 4.3.a Vegetation ................................................................................................................ 9 4.3.b M ilk .................................................................................................................................. 9 4.4 Direct Radiation .............................................................................................................. 9 4.5 G roundw ater .......................................................................................................................... 11 4.6 Sum m ary and Conclusion ................................................................................................. 11

5. REFERENCES ........................................................................................................................... 12 A ppendix A REM P Sam ple Locations ....................................................................................... 16 A ppendix B R EM P Analytical Results ...................................................................................... 25 A ppendix C Q uality Assurance Program .................................................................................. 48 A ppendix D Land Use Survey ................................................................................................... 60

January I - December 31, 2013 Docket Nos. 50-244 LIST OF FIGURES Figure Title Page I Hypothetical Maximum Direct Radiation Dose Exposure per Year ..................................... 10 A-I Map of New York State and Lake Ontario Showing Location of R.E. Ginna Nuclear Power P lan t ......................................................................................................................................... 21 A -2 Onsite Sam ple Locations ...................................................................................................... 22 A-3 Offsite Sample Locations (TLDs and milk farms within 5 miles) ........................................ 23 A-4 Water Sample, Milk Farms and TLD Locations .................................................................. 24 ii

January I - December 31, 2013 Docket Nos. 50-244 LIST OF TABLES Table Title Page I Synopsis of R.E. Ginna Nuclear Power Plant Radiological Environmental Monitoring P ro gram .................................................................................................................................... 13 2 Annual Summary of Radioactivity in the Environs of the R.E. Ginna Nuclear Power Plant .... 14 A-] Locations of Environmental Sampling Stations for the R.E. Ginna Nuclear Plant ............... 18 B-I Concentration of Tritium, Gamma Emitters and Gross Beta in Surface and Drinking Water...27 B-2 Concentration of Gamma Emitters in the Flesh of Edible Fish ............................................ 29 B-3 Concentration of Gamma Emitters in Sediment ................................................................... 30 B-4 Concentration of Iodine-131 in Filtered Air (Charcoal Cartridges) ...................................... 31 B-5 Concentration of Beta Emitters in Air Particulates - Onsite Samples .................................. 33 B-6 Concentration of Beta Emitters in Air Particulates - Offsite Samples .................................. 36 B-7 Concentration of Gamma Emitters in Air Particulates ......................................................... 38 B-8 Concentration of Gamma Emitters in Vegetation Samples .................................................. 39 B-9 Concentration of Gamma Emitters (including 1-131) in Milk .............................................. 40 B-10 Typical MDA Ranges for Gamma Spectrometry .................................................................. 41 B-I I Typical LLDs for Gamma Spectrometry .............................................................................. 42 B -12 D irect R ad iation ......................................................................................................................... 43 B-1 3 Groundwater M onitoring W ells ............................................................................................ 46 C-1 Results of Participation in Cross Check Programs ................................................................ 50 C-2 Results of Quality Assurance Program ................................................................................ 53 C-3 Teledyne Brown Engineering's Typical MDAs for Gamma Spectrometry .......................... 59 D -I Land U se Survey D istances ................................................................................................... 62 iii

January I - December 31, 2013 Docket Nos. 50-244

1. EXECUTIVE

SUMMARY

The Radiological Environmental Monitoring Program (REMP) is a comprehensive surveillance program, which is implemented to assess the impact of site operations on the environment and compliance with 10 CFR 50 Appendix I and 40 CFR 190. Samples are collected from the aquatic and terrestrial pathways applicable to the site. The aquatic pathways include Lake Ontario fish, surface waters, and lakeshore sediment. The terrestrial pathways include airborne particulate and radioiodine, milk, food products, and direct radiation.

Results of the monitoring program for the 2013 operational period for R.E. Ginna Nuclear Power Plant are included in this report. This report presents a synopsis of the REMP (Table 1),

summary of the detectable activity analytical results (Table 2), sampling locations (Appendix A),

compilation of the analytical data (Appendix B), results of the Quality Assurance Program (Appendix C), and results of the Land Use Survey (Appendix D). Interpretation of the data and conclusions are presented in the body of this report.

The results of the REMP verify that the effluent releases did not impact the environment with a measurable concentration of radioactive materials and/or levels of radiation that are higher than expected. The 2013 results for all pathways sampled were consistent with the previous five-year historical results and exhibited no adverse trends. The results of the REMP continue to demonstrate that the operation of the plant did not result in a significant measurable dose to a member of the general population, or adversely impact the environment as a result of radiological effluents. The program continues to demonstrate that the dose to a member of the public, as a result of the operation of R.E. Ginna Nuclear Power Plant, remains significantly below the federally required dose limits specified in 10 CFR 20 and 40 CFR 190.

I

January 1 - December 31, 2013 Docket Nos. 50-244

2. INTRODUCTION 2.1 Station Description The R.E. Ginna Nuclear Power Plant (Ginna), owned by Constellation Energy Nuclear Group, LLC (CENG), is an operating nuclear generating facility consisting of one pressurized water reactor. Ginna achieved criticality in September 1969 and commenced commercial operation in July 1970. The location of the plant in relation to local metropolitan areas is depicted in Appendix A, Figure A-I.

2.2 Program Description and Background The Annual Radiological Environmental Operating Report is published in accordance with Section 5.0 of the Offsite Dose Calculation Manual (ODCM, Ref. I) and the Plant's Technical Specifications (Ref. 2). This report describes the REMP, and its implementation as required by the ODCM. The environmental surveillance data collected during this reporting period were compared with that generated in previous periods whenever possible to evaluate the environmental radiological impact of the R.E. Ginna Nuclear Power Plant. Results of the monitoring program for the pre-operational and previous operational periods through 2012 have been reported in a series of previously released documents.

The REMP is implemented to measure radioactivity in the aquatic and terrestrial pathways. The aquatic pathways include Lake Ontario fish, Lake Ontario water, and Deer Creek water.

Measurement results of the samples representing these pathways contained only natural background radiation or low concentrations of Cs-137 resulting from past atmospheric nuclear weapons testing. Terrestrial pathways monitored included airborne particulate and radioiodine, milk, food products, and direct radiation.

2.3 Program Objectives The objectives of the REMP for the R.E. Ginna Nuclear Power Plant are:

a. Measure and evaluate the effects of plant operation on the environment.

b. Monitor background radiation levels in the environs of the Ginna site.

c. Demonstrate compliance with the environmental conditions and requirements of applicable state and federal regulations, including the ODCM and 40 CFR 190.

d. Provide information by which the general public can evaluate environmental aspects of the operation of R.E. Ginna Nuclear Power Plant.

2

January 1 - December 31, 2013 Docket Nos. 50-244

3. PROGRAM DESCRIPTION 3.1 Sample Collection and Analysis The locations of the individual sampling stations are listed in Table A-I and shown in Figures A-2 and A-3. All samples were collected and analyzed by CENG personnel or its contractors in accordance with Ginna procedures (Ref. 3).

During 2013, 1320 samples were collected for analysis by gross beta counting and/or gamma spectroscopy. These included 76 surface water samples, 16 fish samples, 5 sediment samples, 624 air particulate samples, 306 air iodine samples, 34 vegetation samples, 40 milk samples, 55 groundwater samples, and 164 dosimeter measurements. Deviations from the REMP sampling schedule are described in section 3.5. This monitoring program satisfied the minimum number of samples required by the ODCM for all pathways.

R.E. Ginna Nuclear Power Plant's Chemistry personnel collected all REMP samples. Analysis was performed at either Ginna's onsite laboratory (groundwater samples), Environmental Dosimetry Company in Sterling Massachusetts (direct radiation samples), or Exelon Industrial Services - Ft. Smallwood Environmental Laboratory in Baltimore, Maryland (surface and drinking water, aquatic organisms, shoreline sediment, air particulate filters, air iodine, and vegetation samples). A summary of the content of the REMP and the results of the data collected for indicator and control locations are provided in Tables I and 2.

3.2 Data Interpretation Many results in environmental monitoring occur at or below the minimum detectable activity (MDA). In this report, all results below the relevant MDA are reported as being "not detected." Typical MDA values are listed in Appendix B, Table B-10.

3.3 Quality Assurance Program Appendix C provides a summary of Exelon Industrial Services - Ft. Smallwood Environmental Laboratory's quality assurance program for 2013. It consists of Table C-I, which represents a compilation of the results of the Exelon Industrial Services - Ft. Smallwood Environmental Laboratory's participation in an intercomparison program with Environmental Resource Associates (ERA) located in Arvada, Colorado and Analytics, Inc. located in Atlanta, Georgia.

Table C-2 compiles the results of the Constellation Energy Ft. Smallwood Laboratory's participation in a split sample program with Teledyne Brown Engineering located in Knoxville, Tennessee. Table C-3 identifies a list of typical MDA's achieved by Teledyne Brown for Gamma Spectroscopy.

All the Exelon Industrial Services - Ft. Smallwood Environmental Laboratory results contained in Table C-I agree with the intercomparison laboratory results within the range of +/-2 Ybetween 3

January 1 - December 31, 2013 Docket Nos. 50-244 the analytical values or are in agreement with the ranges established in the NRC Resolution Test Criteria.

All the results contained in Table C-2 agree within the range of+/-2 o of each other with their respective Ft. Smallwood Environmental Laboratory original, replicate and/or Teledyne Brown Engineering's split laboratory samples.

3.4 Land Use Survey In September 2013, 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 five-mile radius of the power plant. The Land Use Survey is conducted in accordance with Ginna procedures (Ref. 4). The position of the nearest residence and garden and animals producing milk for human consumption in each sector is provided in Appendix D, Table D-1.

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

" The nearest residence remains in the SSE sector, approximately 610 meters from the reactor.

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).

However, this facility did not initiate operations in 2013. Once operational, Ginna Chemistry staff will begin collecting raw water samples for REMP analysis.

" Single-family home construction was observed west of the plant along Shoreline Boulevard.

" The Summer Place Subdivision, located west of the plant near the intersection of Lake Road and Roder Parkway, continued to add new residential homes.

" The Cool Breeze Subdivision, located west of the plant near the intersection of Lakeside Road and Boston Road, continued to add new residential homes.

" Single family home construction was observed sporadically within 5-miles of the plant.

" No new agricultural land use was identified.

" No new food producing facilities were identified.

No new milk producing animals were identified.

4

January 1 - December 31, 2013 Docket Nos. 50-244 3.5 Program Exceptions The reportable items in the Annual Environmental Radiological Operating Report under procedure CHA-RETS-VARIATION are as follows:

I. February 11, 2013: The particulate filter contained within Environmental Monitor #8 was damaged (hole in filter). Additionally, a dark mark was noted on the Iodine filter for the same environmental monitor. The filter media was analyzed for the 02/05/2013-02/11/2013 sampling period.

2. February 12, 2013: The housing for Environmental Monitor #5 containing environmental Thernmoluminescent Dosimeter (TLD) #5, #47, and #48 was discovered laying on the ground following a windstorm that occurred on 01/31/2013. Environmental TLD #5, #47, and #48 were remounted under air monitor #5 on 02/12/2013. During the sampling period, TLDs remained on the ground between 01/31/2013-02/12/2013.

3. June 20, 2013: The circulating water discharge canal sample pump was removed from service for maintenance on 06/09/2014 at 2326 and returned to service at 1240 on 06/20/2013. The canal sample pump was offline for a total of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months , 14 minutes during the sampling period. This led to a compensatory grab sample of one liter being added to the weekly Circulation-Out composite sample in order to ensure a sufficient sample volume was collected.

4. August 27, 2013: The air sampler at Environmental Monitoring Station # 8 (Sea Breeze) had a water intrusion in the charcoal filter. Chemistry technician discovered this condition after disassembly of filter. Heavy rains were experienced prior to the sample collection date. The filter was analyzed for the sampling period of 08/20/2013-08/27/2013.

5. September 23, 2013: The normal raw water supply at Monroe County Water Authority (MCWA) in Greece, New York was taken out of service for maintenance activities. As a compensatory action, a grab sample was taken from Lake Ontario/Slater Creek to represent the 09/16/2013-09/23/2013 sampling period.

6. October 1,2013: The nonnal raw water supply at Monroe County Water Authority (MCWA) in Greece, New York was taken out of service due to degradation. The composite sample will be represented by a grab sample for this sample period. Pump was placed back in service on 10/22/2013.

7. October 15, 2013: No composite sample was taken from Ontario Water District (OWD) due to personnel moving the source tubing for the sample cup. A grab sample was obtained to be the representative sample for the sampling period of 10/07/2013-10/14/2013.

8. October 28, 2013: The TLD located at Environmental Monitoring Station #1 was missing during the exchange from the 3r quarter sampling period to the 4 1h quarter sampling 5

January I - December 31, 2013 Docket Nos. 50-244 period. TLD #1, a supplemental TLD not normally used for the REMP and stationed at the same location as TLD #21, was used for this sampling period.

3.6 Corrections to Previous Reports No modifications are required to previously submitted Annual Radiological Environmental Operating Reports at this time.

4. RESULTS AND DISCUSSIONS All environmental samples collected during the year were analyzed in accordance with Exelon analytical procedures (Ref. 5). The analytical results for this reporting period are presented in Appendix B and the detectable activity results are also summarized in Table 2. For discussion purposes, the analytical results are divided into four categories: Aquatic Environment, the Atmospheric Environment, the Terrestrial Environment, Direct Radiation, and Groundwater.

4.1 Aquatic Environment The aquatic environment surrounding the plant was monitored by analyzing samples of surface and drinking water, aquatic organisms, and shoreline sediment. These samples were obtained from various sampling locations near the plant.

4.1.a Surface and Drinking Water Monthly composite samples are collected from Lake Ontario at an upstream control location (Monroe County Water Authority - Shoremont) and a downstream indicator location (Ontario Water District Plant - OWD) and analyzed for gross beta activity (Table B-I). A grab sample of Deer Creek is collected and analyzed monthly for gross beta activity (Table B-1).

In 2013, the gross beta averages for the upstream Lake Ontario monitoring locations (controls) and downstream Lake Ontario monitoring locations (indicators) were 4.05 pCi/Liter and 2.71 pCi/Liter, respectively. Gross beta analysis of the monthly composite samples showed no statistically significant difference in activity between the control and indicator locations.

The average gross beta concentration seen in the Mill Creek samples (controls) and the Deer Creek samples was 3.96 PCi/Liter and 4.58 PCi/Liter, respectively.

Gamma isotopic analysis is performed on each monthly composite sample. These are listed in Table B-I and are separated by source of sample. During 2013, no sample results indicated detection of Gamma activity.

Tritium analysis was performed on all water samples on a monthly basis. Composites are made from the weekly samples and a portion filtered to remove interferences for analysis by beta 6

January 1 - December 31, 2013 Docket Nos. 50-244 scintillation. During 2013, no surface water or drinking water sample results indicated detectable tritium or gamma activity.

4.1.b Aquatic Organisms Indicator fish are caught in the vicinity of the Discharge Canal and analyzed for radioactivity from liquid effluent releases from the plant. The fish are filleted to represent that portion which would normally be eaten. Additional fish are caught more than 15 miles away to be used as control samples and are prepared in the same manner.

At a minimum, four different edible species of fish are analyzed during each half-year from the indicator and background locations. Fish are caught by R.E. Ginna Nuclear Power Plant environmental staff and are analyzed by gamma spectroscopy after being held for periods of less than one week to keep the LLD value for the shorter half-life isotopes realistic. Detection limits could also be affected by small mass samples, (< 2000 grams), in some species. Gamma isotopic concentrations (pCi/kilogram wet) are listed in Table B-2.

During 2013, none of the indicator samples indicated activity other than naturally occurring radionuclides. There was no significant difference in the radiological activity in the indicator and control sampling locations.

4.1.c Shoreline Sediment Samples of shoreline sediment are taken upstream (Town of Greece near Slater Creek) and downstream (Near the Ontario Water District) of R.E. Ginna Nuclear Power Plant.

Results of the gamma isotopic analysis for sediment are included in Table B-3, along with benthic sediment from Lake Ontario. During 2013, all sediment samples indicated that gamma emitters were below detection limits. There was no difference in the radiological activity observed in the indicator and control sampling locations.

4.2 Atmospheric Environment Radioactive particles in air are collected by drawing approximately one standard cubic foot per minute (SCFM) through a two inch diameter particulate filter. The volume of air sampled is measured by a dry gas meter and corrected for the pressure drop across the filter. The filters are changed weekly and allowed to decay for three days prior to counting to eliminate most of the natural radioactivity such as the short half-life decay products of radon. The decay period is used to give a more sensitive measurement of long-lived man-made radioactivity.

A ring of six sampling stations is located on the plant site from 150 to 420 meters from the reactor centerline near the point of the maximum annual average ground level concentration, one additional sampling location is located on-site at 690 meters, and two others offsite at 7

January 1 - December 31, 2013 Docket Nos. 50-244 approximately 7 miles. In addition, there are three sampling stations located approximately 7 to 16 miles from the site that serve as control stations. See Figure A-2 and Figure A-4.

4.2.a Air Iodine Radioiodine cartridges are placed at six locations. These cartridges are changed and analyzed each week. No positive analytical results were found on any sample. A list of values for these cartridges is given in Table B-4.

4.2.b Air Particulate Filters The major airborne species released from the plant are noble gases and tritium. Most of this activity is released in a gaseous form; however, some radioiodine is released as airborne particulate and some of the particulate activity is due to short lived noble gas decay products.

Tables B-5 provides a list of gross beta analysis values for the on-site sample stations. Table B-6 is a list of gross beta analysis values for the off-site sample stations.

Based on weekly comparisons, there was no statistical difference between the Control and Indicator radioactive particulate concentrations. The average for the control samples (i.e., offsite sampling locations) was 0.0230 pCi/m 3 and the averages for the indicator samples (i.e., onsite sampling locations) was 0.0230 pCi/m 3 for the period of January to December 2013. Maximum weekly concentrations for all control stations and all indicator stations were 0.039 and 0.054 pCi/m 3 , respectively.

The particulate filters from each sampling location were saved and a 13 week composite was made. A gamma isotopic analysis was performed for each sampling location and corrected for decay. No positive analytical results were found on any sample. The results of these analyses are listed in Tables B-7.

4.3 Terrestrial Environment Crops are grown on the plant property in a location with a highest off-site meteorological deposition parameter, and samples of the produce are collected at harvest time for analysis.

Control samples are purchased from farms greater than ten miles from the plant.

8

January I - December 31, 2013 Docket Nos. 50-244 4.3.a Vegetation There was no indication in the vegetation samples contained activity greater than naturally occurring background levels. There was no difference in the radiological activity observed in the indicator and control sampling locations. Gamma isotopic data is provided in Table B-8.

4.3.b Milk There was one indicator dairy herd located within five miles from the plant in 2013. Milk samples are collected monthly during November through May from the indicator farm and biweekly during June through October. A control fanrm sample is taken for each monthly sample and once during each biweekly period. The milk is analyzed for Iodine- 131 and also analyzed by gamma spectroscopy.

During 2013, no samples indicated 1-131 activity above detection levels. There was no difference in the radiological activity observed in the indicator and control sampling locations.

Table B-9 provides a listing of all samples collected and analytical results.

4.4 Direct Radiation Dosimeters are placed as part of the environmental monitoring program. Thirty-nine dosimeter badges are currently placed in four rings around the plant. These rings range from less than 1,000 feet to 15 miles and have been dispersed to give indications in each of the nine land based sectors around the plant should an excessive release occur from the plant. Badges are changed and read after approximately 3 months exposure. Each direct radiation sampling location is described in Table A-I and identified in Figure A-2.

Direct radiation readings at locations #7 and #13 are influenced by their close proximity to the site's Independent Spent Fuel Storage Installation (ISFSI) and will normally read slightly higher than other locations. Environmental Station 13, the closest sampling location to the ISFSI, received an average quarterly dose of 16. I mRem during 2013. All onsite indicators averaged 12.5 mRem/qtr.

For the year of 2013, the average, minimum, and maximum exposure readings was as follows:

Monitoring Group Average Min. Max (mremL/qtr) (mrem/qtr) (mrern/qtr)

Onsite Indicators 12.5 9.0 18.3 Site Boundary Indicators 12.3 10.1 15.8 Offsite Indicators 11.4 9.2 14.8 Control Locations 11.0 9.0 14.1 9

January I -Dccember 31,2013 Docket Nos. 50-244 40 CFR 190 requires that the annual dose equivalent not exceed 25 millirem to the whole body of any member of the public. The average quarterly exposure observed at the control monitoring stations was used to determine the background level (equivalent to 11.0 millirems monthly or 44.0 millirem annually), while the highest total annual dosimeter reading at an individual site boundary environmental monitoring location (56.1 millirem) was observed at Environmental Monitoring Station #64. The difference in these values determines the maximum possible direct radiation dose exposure to an offsite member of the public. Accordingly, the hypothetical maximum direct radiation dose exposure to the public for 2013 was determined to be 12.1 millirem annually.

Figure 1 presents the hypothetical maximum direct radiation dose exposure over the past ten years. As noted in the 2011 Annual Radiological Environmental Operating Report (AREOR), an apparent upward trend with the reported average annual direct radiation dose was identified. It was noted that the average annual direct dose to an offsite member of the public had increased 2

- 3 mRem since 2008 (Condition Report CR-2012-001275). Ginna staff evaluated this apparent trend and concluded the elevated dosimeter readings were likely the result of increased onsite hold times after the dosimeters had been collected. In an effort to reduce onsite hold times, the site will be changing its process for collecting and shipping dosimeters in 2014.

Figure I Hypothetical Maximum Direct Radiation Dose Exposure per Year Hypothetical Maximum Direct Radiation Dose Exposure 14 I

12 S10 4,

0 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 Year Table B-12 provides the 2013 quarterly dosimeter readings at each location.

10

January 1 - December 31,2013 Docket Nos. 50-244 4.5 Groundwater In accordance with R.E. Ginna Nuclear Power Plant's Chemistry procedures, at a minimum, environmental groundwater monitoring wells are sampled quarterly. During 2013, five new groundwater monitoring wells were installed. In 2013, Ginna staff collected and analyzed samples collected from a total of 14 groundwater monitoring wells:

" GWOI: 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

GWIO: Technical Support Center, South

" GWI 1: Contaminated Storage Building, SE (24.0')

" GW12: West of Orchard Access Road

" GW! 3: North of Independent Spent Fuel Storage Installation (ISFSI)

" GW14: South of Canister Preparation Building

" GWI5: West of Manor House

" GW16: Southeast of Manor House Groundwater samples are analyzed for tritium to a detection limit of 500 pCi/L, and for gamma emitting radionuclides to the environmental LLDs. The analytical results for groundwater monitoring well samples collected during 2013 are presented in table B-I 3.

No positive tritium results were identified in any of the groundwater monitoring wells during 2013.

4.6 Summary and Conclusion Operation of the R.E. Ginna Nuclear Power Plant produced radioactivity and ambient radiation levels significantly below the limits of the ODCM and 40 CFR 190. The analytical results from the Radiological Environmental Monitoring program indicate the operation of the R.E. Ginna Nuclear Power Plant had no measurable radiological impact on the environment or significant build-up of plant-related radionuclides in the environment. The results also indicate operation of the plant did not result in a measurable radiation dose to the general population above natural background levels.

Additionally, the 2013 results are consistent with data for the past five years and exhibited no detectable increases or adverse trends.

II

January I - December 31,2013 Docket Nos. 50-244

5. REFERENCES

1. R.E. Ginna Nuclear Power Plant, Offsite Dose Calculation Manual (ODCM),

Revision 28 (Effective Date: 02/05/2014).

2. R.E. Ginna Nuclear Power Plant, Technical Specification 5.6.2; Annual Radiological Environmental Operating Report.

3. Procedure CNG-EV-l1.01-1000, Radiological Environmental Monitoring Program (REMP).

4. Procedure CH-ENV-LAND-USE, Land Use Census; Completed September 2013.

5. Exelon Industrial Services - Ft. Smallwood Environmental Laboratory Procedures Manual, General Services Department.

12

January 1 - December 31,2013 Docket Nos. 50-244 Table 1 Synopsis of R.E. Ginna Nuclear Power Plant Radiological Environmental Monitoring Program Sample Type Sampling Number of Number Analysis Analysis Number Frequency' Locations Collected Frequency' Analyzed Aquatic Environment Surface & Drinking M/C 5 76 Gamma MC/MG 76 Water 76 Gross Beta MC/MG 76 76 Tritium M/Q 76 Bottom Sediment A 1 1 Gamma A 1 Fish2 A 3 16 Gamma A 16 Shoreline Sediment SA 2 5 Gamma SA 5 Groundwater M/Q 14 55 Tritium M/Q 55 55 Gamma M/Q 55 Atmospheric Environment Air Iodine3 W 6 306 1-131 W 306 Air Particulates 4 W 12 624 Gross Beta W 624 48 Gamma 0C 48 Direct Radiation Ambient Radiation Q 41 164 TLD Q 164 Terrestrial Environment Milk5 M/BW 2 40 Gamma M/BW 40 Vegetationb M 6 34 Gamma M 34

'W=Weekly, BW=BiWeekly (15 days), M=Monthly (31 days), Q=Quarterly (92 days), SA=Semiannual. A=Annual, C=Composite 2 Twice during fishing season including at least four species 3 The collection device contains activated charcoal 4 Beta counting is performed >= 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change. Gamma spectroscopy performed on quarterly composite of weekly samples 5 Bi-Weekly during growing season.

cAnnual at time of harvest. Samples include broad leaf vegetation 13

January I - December 31, 2013 Docket Nos. 50-244 Table 2 Annual Summary of Radioactivity in the Environs of the R.E. Ginna Nuclear Power Plant Medium or Type and Total Lower Limit of Indicator Location with Highest Annual Control Locations Pathway Sampled Number of Detection (LLD) Locations Mean Highest Annual Mean (F) / Range 1 Mean (F)/Range (Unit of Analyses (F)/Range 1 Mean Measurement) Performed Name/Distance2 &

Direction Aquatic Environment Surface & Gamma (76) 2.3 (Cs-1 37) - (51/51) -- (13/13) - (25/25)

Drinking Water Tritium (76) 500 -- (51/51) (--)

(pCi/L)

Surface & Gross Beta (76) 0.5 2.71 (51/51) MCWA, Greece - 4.58 (12/12) 4.05 (25/25)

Drinking Water, (1.15 - 6.90) 27.20 km W (3.45 - 6.90) (2.62 - 6.16)

(pCi/L)

Sediment Gamma (5) 17 (Cs-137) -- (3/3) -- (2/2) -- (2/2)

(pCi/kg)

Fish Gamma (16) 15 (Cs-1 37) -- (8/8) -- (5/5) -- (8/8)

(pCi/kg) (--) (--)

Groundwater Tritium (55) 500 -- (51/51) -- (12/12) -(4/4)

(pCi/L) Gamma (55) 18 (Cs-1 37) -- (51/51) - (12/12) -- (4/4)

Direct Radiation Ambient Radiation Dosimeters (164) 12.0 (128/128) Env. Station 13 16.1 (4/4) 11.0 (36/36)

(mR/91 days) (9.0-18.3) 1.19 km W (15.0-18.3) (9.0-14.1) 14

January I - December 31, 2013 Docket Nos. 50-244 Table 2 Annual Summary of Radioactivity in the Environs of the R.E. Ginna Nuclear Power Plant Medium or Type and Total Lower Limit of Indicator Location with Highest Annual Control Locations Pathway Sampled Number of Detection (LLD) Locations Mean Highest Annual Mean (F) / Range 1 Mean (F)/Range (Unit of Analyses (F)/Range1 Mean Measurement) Performed Name/Distance 2 &

Direction Atmospheric Environment Air Iodine 1-131 (306) 0.15 - (255/255) -- (51/51) -- (51/51)

(10.2 pCi/m 3 ) (--) (--)

(-)

Air Particulates Gross Beta (624) 0.5 2.3 (468/468) Env. Station 2 - 2.5 (52/52) 2.3 (156/156)

(10-2 pCi/m 3 ) (1.2-5.4) 0.36 km E (1.3.-5.0) (1.1 -3.9)

Air Particulates Gamma (48) -- (36/36) -- (4/4) -- (12/12)

(10,3 pCi/m3) (--)

(-) (-)

Terrestrial Environment Milk Gamma (40) 5 (Cs-137) - (20/20) -- (20/20) - (20/20)

(pCi/L) (--) (--)

(-)

Vegetation Gamma (34) 27 (Cs-1 37) - (26/26) -- (9/9) --(8/8)

(pCi/L)

' Mean and range based upon detectable measurements only. Fraction (F) of detectable measurements at specified location is indicated in parentheses 2 From the center point of the containment building.

-- No detectable activity at specified location.

15

January 1- December 31, 2013 Docket Nos. 50-244 APPENDIX A REMP Sample Locations Summary of Appendix A Content Appendix A contains information concerning the environmental samples which were collected during this operating period.

Sample locations and specific information about individual locations for Ginna are provided in Table A- 1.

Figure A-i shows the location of the R.E. Ginna Nuclear Power Plant in relation to New York State and Lake Ontario. Figures A-2, A-3, and A-4 show the locations of the power plant sampling sites in relation to the plant site at different degrees of detail.

16

January 1 - December 31, 2013 Docket Nos. 50-244 TABLE OF CONTENTS - SAMPLING LOCATIONS Table Title Page A-I Locations of Environmental Sampling Stations for the R.E Ginna Nuclear Power Plant ... 18 Figure Title Page A-1 Map of New York State and Lake Ontario Showing Location of R.E. Ginna Nuclear Power P la nt ................................................................................................................................... 21 A -2 O nsite Sam ple Locations ................................................................................................. 22 A-3 Offsite Sample Locations (TLDs and milk farms within 5 miles) .................................. 23 A-4 Water Sample, Milk Farms and TLD Locations ............................................................. 24 17

January 1 - December 31,2013 Docket Nos. 50-244 TABLE A-I Locations of Environmental Sampling Stations for the R.E. Ginna Nuclear Plant Station Description Distance Direction Meters Miles Sector Air Samplers 2 Manor House Yard 360 0.22 E 3 East Field 440 0.27 ESE 4 East of Training Center Parking Lot 320 0.20 SE 5 Creek Bridge 180 0.11 SSE 6 Onsitc-SW side of plant parking lot 300 0.19 SW 7 Onsite-utility pole along West plant fence 240 0.15 WSW 8 Seabreeze 19840 12.33 WSW 9 Webster 11150 6.93 SW 10 Walworth 12730 7.91 S II Williamson 11540 7.17 ESE 12 Sodus Point 25170 15.64 E 13 Substation 13 690 0.43 SSW Direct Radiation 2 Onsite-Manor House Yard 360 0.22 E 3 Onsite-In field approximately 200 fi SE of station #2 440 0.27 ESE 4 Onsite- East of Training Center Parking Lot 320 0.20 SE 5 Onsite-Between creek and plant entry road 180 0.11 SSE 6 Onsite-SW side of plant parking lot 300 0.19 SW 7 Onsite-utility pole along West plant fence 240 0.15 WSW 8 Topper Drive-lrondequoit, Seabreeze Substation #51 19840 12.33 WSW Phillips Road-Webster, intersection with Highway #104, 1150 6.93 SW Substation #74 10 Atlantic Avenue-Walworth, Substation #230 12730 7.91 S II W. Main Street-Williamson, Substation #207 11540 7.17 ESE 12 12 Seaman Avenue-Sodus Point-Off Lake Road by 25170 15.64 E Sewer district, Substation U209 13 Onsite - South of Meteorological Tower 260 0.16 WNW 14 NW comer of field along lake shore 860 0.53 WNW 15 Field access road, west of orchard, approximately 3000' 920 0.57 W

____ West of plant 16 SW Comer of orchard, approximately 3000' West of 1030 0.64 WSW plant, approximately 200' North of Lake Road 17 Utility pole in orchard, approximately 75" North of Lake 510 0.32 SSW Road 18 Substation 13A fence, North Side 730 0.45 SSW 19 On NW comer of house 100' East of plant access road 460 0.29 S 20 Approximately 150' West of Ontario Center Road and 650 0.40 SSE approximately 170' South of Lake Road 18

January 1 - December 31, 2013 Docket Nos. 50-244 TABLE A-I Locations of Environmental Sampling Stations for the R.E. Ginna Nuclear Plant Station Description I Distance Direction Meters Miles Sector 21 North side of Lake Road, approximately 200' East of 660 0.41 SE Ontario Center Road 22 North side of Lake Road, SE, property comer 920 0.57 SE 23 East property line, midway between Lake Road and 780 0.49 ESE Lake shore 24 Lake shore near NE comer of property 730 0.45 E 25 Substation #73, Klem Road, adjacent to 897 Klem Road 14000 8.70 WSW 26 Service Center, Plank Road, West of 250 14600 9.07 SW 27 Atlantic Avenue at Knollwood Drive utility pole, North 14120 8.77 SSW side of road 28 Substation #193, Marion, behind Stanton Ag. Service, 17450 10.84 SE North Main Street 29 Substation #208, Town Line Road (CR-I 18), 1000' 14050 8.73 ESE North of Route 104 30 District Office, Sodus, on pole, West side of bldg 20760 12.90 ESE 31 Lake Road, pole 20' North of road, 500' East of Salt 7330 4.56 W Road 32 Woodard Road at County Line Road, pole @ Northwest 6070 3.77 WSW comer.

33 County Line Road at RR tracks, pole approximately 100' 7950 4.94 SW East along tracks 34 Pole at Route 104, Lincoln Road, SW Comer. 6520 4.05 SSW 35 Transmission Right of Way, North of Clevenger Road 7490 4.65 SSW on pole.

36 Substation #205, Route 104, East of Ontario Center 5480 3.41 S Road, North side of fence.

37 Rail Road Avenue, pole at 2048 5770 3.59 SSE 38 Fisher Road at RR Tracks, pole East of road 6910 4.29 SE 39 Seeley Road. Pole South side 100' West of intersection 6930 4.31 ESE with Stony Lonesome Road 40 Lake Road at Stoney Lonesome Road, pole at SE comer 6440 4.00 E 63 Westside of warehouse access road 740 0.46 SW 64 Westside of direct road, adjacent to orchard 1190 0.74 W Fish Lake Ontario Discharge Plume 2200 1.4 ENE Russell Station 25600 15.9 W 19

January 1 - December 31, 2013 Docket Nos. 50-244 Produce (Vegetation) I Indicator and background samples of various produce are collected from gardens grown on company property and purchased from farms >I0 miles from the plant.

Station Description Distance Direction Meters Miles Sector Onsite Supplemental Garden (E) 610 0.38 E Onsite Supplemental Garden (ESE) 430 0.27 ESE

_Onsite Supplemental Garden (SSE) 660 0.41 SSE Water Shoremont/MCWA 27150 16.9 W Ontario Water District 2220 1.4 ENE Circ Water Intake 1070 0.7 N Circ Water Discharge 110 0.1 NNE Deer Creek Points Points ESE downstream downstream of Outfall of Outfall 1 1 006 006 1 Sediment Lake Ontario Discharge Plume 2200 1.4 ENE Russell Station 25600 15.9 W Bethnic 1070 0.7 N Milk Eaton Farm, Williamson (Indicator) 8240 5.1 ESE Schultz Fami, S. Sodus (Control) 19030 11.8 SE 20

January 1- December 31, 2013 Docket Nos. 50-244 Figure A-1 Map of New York State and Lake Ontario Showing Location of R.E. Ginna Nuclear Power Plant 21

January 1 - December 31, 2013 Docket Nos. 50-244 Figure A-2 Onsite Sample Locations 22

January 1 - December 31, 2013 Docket Nos. 50-244 Figure A-3 Offsite Sample Locations (TLDs and milk farms within 5 miles) 23

January 1 - December 31, 2013 Docket Nos. 50-244 Figure A-4 Water Sample, Milk Farms and TLD Locations 24

January 1 - December 31, 2013 Docket Nos. 50-244 APPENDIX B REMP Analytical Results Summary of Appendix B Content Appendix B is a presentation of the analytical results for the R.E. Ginna Nuclear Power Plant radiological environmental monitoring programs.

25

January I - December 31, 2013 Docket Nos. 50-244 TABLE OF CONTENTS - ANALYTICAL RESULTS Table Title Page B-I Concentration of Tritium, Gamma Emitters and Gross Beta in Surface and Drinking Water...27 B-2 Concentration of Gamma Emitters in the Flesh of Edible Fish ............................................ 29 B-3 Concentration of Gamma Emitters in Sediment ..................................................................... 30 B-4 Concentration of lodine-1 31 in Filtered Air (Charcoal Cartridges) ..................................... 31 B-5 Concentration of Beta Emitters in Air Particulates - Onsite Samples .................................. 33 B-6 Concentration of Beta Emitters in Air Particulates - Offsite Samples .................................. 36 B-7 Concentration of Gamma Emitters in Air Particulates ......................................................... 38 B-8 Concentration of Gamma Emitters in Vegetation Samples .................................................. 39 B-9 Concentration of Gamma Emitters (including 1-13 1) in Milk ........................... 40 B-10 Typical MDA Ranges for GammaSpectrometry .................................................................. 41 B-I I Typical LLDs for Gamma Spectrometry ............................................................................. 42 B -12 D irect R adiation ......................................................................................................................... 43 B-13 Groundw ater M onitoring W ells ............................................................................................ 46 26

January 1 - December 31, 2013 Docket Nos. 50-244 Table B-1 Concentration of Tritium, Gamma Emitters and Gross Beta in Surface and Drinking Water (Results in units of pCi/L +/- 2a)

Sample Code Sample Date Gamma Emitters Gross Beta CIRC-IN Circulating Water Inlet - N 1/15/2013 2.18+/- 0.54 2/12/2013 3.34 +/- 0.59 3/12/2013 2.59 +/- 0.57 4/11/2013 2.68 +/- 0.57 5/6/2013 2.30 +/- 0.56 6/3/2013 1.99 +/- 0.56 7/1/2013 2.04 +/- 0.54 7/29/2013 2.14 +/- 0.55 8/26/2013 1.91 +/- 0.56 9/23/2013 2.18 +/- 0.57 10/22/2013 2.99 +/- 0.60 11/18/2013 2.11 +/- 0.57 12/16/2013 1.76 +/- 0.55 CIRC-OUT Circulating Water Outlet - N 1/15/2013 2.63 +/- 0.56 2/12/2013 2.52 +/- 0.55 3/12/2013 3.05 +/- 0.60 4/9/2013 2.35 +/- 0.55 5/6/2013 1.62 +/- 0.54 6/3/2013 1.95 +/- 0.55 7/1/2013 2.08 +/- 0.54 7/29/2013 1.90 +/- 0.54 8/26/2013 1.68+/- 0.58 9/23/2013 1.80+/- 0.56 10/22/2013 1.73 +/- 0.55 11/18/2013 1.96 +/- 0.56 12/16/2013 1.49 +/- 0.54 DC Deer Creek - ESE 1/2/2013 5.00 +/- 0.73 2/19/2013 4.12 +/- 0.73 3/5/2013 3.73 +/- 0.69 4/1/2013 3.58 +/- 0.72 5/20/2013 3.65 +/- 0.81 6/17/2013 4.16 +/- 0.76 7/15/2013 4.51 +/- 0.80 8/12/2013 3.45 +/- 0.77 9/9/2013 4.88 +/- 0.92 10/9/2013 5.77 +/- 0.85 11/11/2013 6.90 +/- 0.94 12/2/2013 5.16 +/- 0.87 27

January 1 - December 31,2013 Docket Nos. 50-244 Table B-I Concentration of Tritium, Gamma Emitters and Gross Beta in Surface and Drinking Water (Results in units of pCi/L +/- 2a)

Sample Code Sample Date Gamma Emitters Gross Beta MCWA Monroe County Water/Shoremont, Greece - W' 1/14/2013 3.85 +/- 0.45 2/11/2013 4.20 +/- 0.46 3/11/2013 3.74 +/- 0.44 4/8/2013 3.79 +/- 0.44 5/6/2013 3.84 +/- 0.45 6/3/2013 4.06 +/- 0.45 7/1/2013 3.75 +/- 0.43 7/29/2013 4.42 +/- 0.47 8/26/2013 3.92 +/- 0.45 9123/2013 4.21 +/- 0.46 10/22/2013 5.42 +/- 0.56 11/18/2013 4.00 +/- 0.45 12/16/2013 4.25 +/- 0.47 ML Mill Creek - SW1 1/2/2013 3.83 +/- 0.69 2/19/2013 3.74 +/- 0.69 3/5/2013 2.62 +1- 0.64 4/1/2013 3.69 +/- 0.75 5/20/2013 3.14 +/- 0.76 6/17/2013 3.18 +/- 0.70 7/15/2013 3.89 +/- 0.79 8/12/2013 3.22 +/- 0.82 9/9/2013 4.34 +/- 0.78 10/9/2013 6.16 +/- 0.88 11/11/2013 5.42 +/- 0.88 12/2/2013 4.33 +/- 0.86 OWD Ontario Water District - NE 1/14/2013 2.85 +/- 0.57 2/11/2013 2.37 +/- 0.54 3/11/2013 2.53 +/- 0.56 418/2013 2.59 +/- 0.57 5/6/2013 2.20 +/- 0.57 6/3/2013 1.89+/- 0.55 7/1/2013 1.80 +/- 0.52 7/29/2013 2.04 +/- 0.56 8/26/2013 1.15 +/- 0.52 9/23/2013 1.77 +/- 0.56 10/22/2013 1.64 +/- 0.54 11/18/2013 1.78 +/- 0.58 12/16/2013 1.96 +/- 0.55 Control Location

No Man-Made Gamma Emitters or Tritium Detected.

28

January 1 - December 31, 2013 Docket Nos. 50-244 Table B-2 Concentration of Gamma Emitters in the Flesh of Edible Fish (Results in units of pCi/kg (wet) +/- 2a)

Sample Code Sample Date Sample Type Gamma Emitters CONTROL1 Local Sites in Control Sectors 2/22/2013 Brown Trout 5/17/2013 Rock Bass 5/24/2013 Freshwater Drum 9/30/2013 Brown Trout 9/30/2013 Chinook Salmon 9/30/2013 Lake Trout 9/30/2013 Smallmouth Bass Greece1 Control 5/3/2013 Pike NORTH North Sector 1/8/2013 Lake Trout 1/9/2013 Brown Trout 1/9/2013 Rainbow Trout 3/22/2013 Smallmouth Bass 10/31/2013 Smallmouth Bass 10/31/2013 White Bass 11/8/2013 Brown Trout

11/12/2013 Lake Trout Control Locations include Greece, NY and Irondequoit. NY.

No Man-Made Gamma Emitters Detected.

29

January 1 - December 31, 2013 Docket Nos. 50-244 Table B-3 Concentration of Gamma Emitters in Sediment (Results in units of pCi/kg (wet) +/- 2a)

Sample Code Sample Date Gamma Emitters Shoreline EAST East Sector 4/2212013 7/22/2013 GREECE1 Control 4/22/2013 7/22/2013 Benthic NORTH 4/17/2013

'Control Location

No Man-Made Gamma Emitters Detected.

30

January 1 - December 31, 2013 Docket Nos. 50-244 Table B-4 Concentration of Iodine-131 in Filtered Air (Charcoal Cartridges)

(Results in units of 10-2 pCi/ms +/- 2a)

Start Date Stop Date STATION-02 STATION-04 STATION-07 STATION- STATION-09 STATION-i 1 Manor Training West Fence 081 Webster Williamson House Yard Center Line Seabreeze Parking Lot 12/31/2012 1/7/2013 1/7/2013 1/14/2013 *

t lk 1/14/2013 1/21/2013

1/21/2013 1/28/2013

k 1/28/2013 2/412013 2/4/2013 2/11/2013 t 2/11/2013 2/18/2013 2/18/2013 2/25/2013 * *

1 3/4/2013 3/11/2013 3/11/2013 3/18/2013 3/18/2013 3/25/2013

3/25/2013 4/1/2013

4/1/2013 4/8/2013

4/8/2013 4/15/2013

4/15/2013 4/22/2013

4/22/2013 4/29/2013

t 4/29/2013 5/6/2013 5/6/2013 5/13/2013 *

5/13/2013 5/20/2013 5/20/2013 5/27/2013

5/27/2013 6/3/2013 6/3/2013 6/10/2013 6/10/2013 6/17/2013 6/17/2013 6/24/2013 6/24/2013 7/1/2013 7/1/2013 7/8/2013 7/8/2013 7/15/2013 7/15/2013 7/22/2013 *

7/22/2013 7/29/2013 7/29/2013 8/5/2013 8/5/2013 8/12/2013 8/12/2013 8/19/2013 8/19/2013 8/26/2013 8/26/2013 9/2/2013 9/2/2013 9/9/2013 9/9/2013 9/16/2013 9/16/2013 9/23/2013

9/23/2013 9/30/2013

31

January 1 - December 31, 2013 Docket Nos. 50-244 Table B-4 Concentration of Iodine-131 in Filtered Air (Charcoal Cartridges)

(Results in units of 10-2 pCi/m3 +/- 2a)

Start Date Stop Date STATION-02 STATION-04 STATION-07 STATION- STATION-09 STATION-11 Manor Training West Fence 08' Webster Williamson House Yard Center Line Seabreeze Parking Lot 9/30/2013 10/7/2013 10/7/2013 10/14/2013 *

10/14/2013 10/21/2013

10/21/2013 10/28/2013

10/28/2013 11/4/2013 *

'lb 11/4/2013 11/11/2013

11/11/2013 11/18/2013 'It" 11/18/2013 11/25/2013 11/25/2013 12/2/2013

12/2/2013 12/9/2013 *

12/9/2013 12/16/2013 t 12/16/2013 12/23/2013 12/23/2013 12/30/2013

'Control Location

1-13 1 not detected.

32

January I - December 31, 2013 Docket Nos. 50-244 Table B-5 Concentration of Beta Emitters in Air Particulates - Onsite Samples (Results in units of 10-2 pCi/m 3 +/- 2ar Uncertainty)

Start Date Stop Date STATION-02 STATION-03 STATION-04 STATION-05 STATION-06 STATION-07 STATION-1 3 Manor House East Field Training Creek Bridge Main Parking West Fence Substation 13 Yard Center Parking Lot Line Lot 12/31/2012 1/7/2013 5.0 +/- 0.3 4.8 +/- 0.2 4.6 +/- 0.2 5.1 +/- 0.2 5.0 +/-0.2 5.1 +/-0.2 5.4 +/- 0.2 1/7/2013 1/14/2013 4.7 +/- 0.3 3.7 +/- 0.2 3.3 +/- 0.2 3.9 +/- 0.2 4.1 +/-0.2 3.9 +/- 0.2 4.4 +/- 0.2 1/14/2013 1/21/2013 2.5 +/- 0.3 2.2 +/- 0.1 2.3 +/- 0.1 2.3 +/- 0.1 2.2 +/- 0.1 2.1 +/-0.1 2.3 +/- 0.1 1/21/2013 1/28/2013 1.8 +/- 0.2 1.6+/-0.1 1.9 +/-0.1 1.8 +/-0.1 1.9 +/- 0.1 1.8+/-0.1 2.0 +/- 0.1 1/28/2013 2/4/2013 3.2 +/- 0.3 2.7 +1-0.1 2.9 +/- 0.2 3.0 +/- 0.1 2.8 +/- 0.1 3.0 +/- 0.1 3.1 +/-0.1 2/4/2013 2/11/2013 3.5 +/- 0.3 3.1 +/-0.2 2.9 +/- 0.2 3.3 +/-0.2 2.9 +/-0.2 3.1 +/-0.2 3.1 +/-0.2 2/11/2013 2/18/2013 2.4 +/- 0.3 2.2 +/- 0.1 2.1 +/-0.1 2.3 +/- 0.1 2.3 +/- 0.1 2.4 +1- 0.1 2.4 +1-0.1 2/18/2013 2/25/2013 1.8 +/-0.3 1.4 +/-0.1 1.6 +/-0.1 1.5 +/-0.1 1.4 +/-0.1 1.4 +/- 0.1 1.5 +/-0.1 2/25/2013 3/4/2013 2.1 +/-0.2 1.6 +/-0.1 1.7 +/- 0.1 1.8 +/-0.1 1.7 +/- 0.1 1.7 +/- 0.1 1.8 +/- 0.1 3/4/2013 3/11/2013 1.8 +/-0.2 1.3 +1-0.1 1.4 +/-0.1 1.4 +/-0.1 1.5 +/-0.1 1.5 +/- 0.1 1.6 +/-0.1 3/11/2013 3/18/2013 2.7 +/- 0.2 2.3 +/- 0.1 2.5 +/- 0.1 2.6 +/- 0.1 2.4 +/- 0.1 2.6 +/- 0.1 2.5 +/- 0.1 3/18/2013 3/25/2013 1.9 +/- 0.2 1.6 +/-0.1 1.7 +/-0.1 1.7 +/-0.1 1.5 +/-0.1 1.6 +/-0.1 1.7 +/-0.1 3/25/2013 4/1/2013 1.3 +/-0.2 1.2 +/-0.1 1.2 +/-0.1 1.3 +/-0.1 1.3 +/-0.1 1.4 +/- 0.1 1.3 +/- 0.1 4/1/2013 4/8/2013 2.4 +/- 0.2 2.2 +/- 0.1 2.3 +/- 0.1 2.3 +/- 0.1 2.3 +/- 0.1 2.4 +1-0.1 2.2 +1-0.1 4/8/2013 4/15/2013 1.8 +/-0.2 1.3 +/-0.1 1.3 +/- 0.1 1.3 +/-0.1 1.3 +/-0.1 1.4 +/-0.1 1.4 +/-0,1 4/15/2013 4/22/2013 1.8 +/- 0.3 2.0+/-0.1 2.0 +/- 0.1 2.2 +1-0.1 2.3 +/- 0.1 2.2 +/- 0.1 2.0 +/- 0.1 4/22/2013 4/29/2013 2.9 +/- 0.2 2.8 +/- 0.1 2.8 +/- 0.2 2.9 +1- 0.1 2.8 +/- 0.2 2.8 +/- 0.1 2.9 +/- 0.1 4/29/2013 5/6/2013 2.7 +/- 0.3 1.9 +/-0.1 2.1 +/-0.1 1.9 +/-0.1 1.9 +/-0.1 2.0 +/- 0.1 1.8 +/-0.1 5/6/2013 5/13/2013 1.8 +/-0.3 1.2 +/-0.1 1.2 +/- 0.1 1.4 +/-0.1 1.4 +/- 0.1 1.2 +/-01 1.3 +/-0.1 5/13/2013 5/20/2013 3.1 +/-0.4 1.9 +/-0.1 2.1 +1-0.1 2.0 +/- 0.1 2.1 +/-0.1 2.1 +/-0.1 2.0 +/- 0.1 5/20/2013 5/27/2013 1.9 +/-0.2 1.7 +/-0.1 1.8 +/-0.1 1.8 +/-0.1 1.7 +/- 0.1 1.8 +/-0.1 1.7 +/-0,1 5/27/2013 6/3/2013 2.5 +/- 0.2 2.0 +/- 0.1 3.4 +/- 0.2 2.2 +/-0.1 2.1 +/-0.1 2.1 +/-0.1 2.1 +/-0.2 33

January 1 - December 31, 2013 Docket Nos. 50-244 Table B-5 Concentration of Beta Emitters in Air Particulates - Onsite Samples (Results in units of 10-2 pCi/m3 +/- 2a Uncertainty)

Start Date Stop Date STATION-02 STATION-03 STATION-04 STATION-05 STATION-06 STATION-07 STATION-1 3 Manor House East Field Training Creek Bridge Main Parking West Fence Substation 13 Yard Center Parking Lot Line Lot 6/3/2013 6/10/2013 1.6 +/-0.2 1.8 +/-0.2 1.5 +/- 0.1 1.5 +/-0.1 1.6 +/- 0.1 1.6 +/-0.1 1.4 +/-0.1 6/10/2013 6/17/2013 1.6+/-0.2 1.5 +/-0.1 1.6 +/- O.1 1.6 +/-0.1 1.5 +/- 0.1 1.7 +/-0.1 1.5 +/- 0.1 6/17/2013 6/24/2013 2.9 +/- 0.2 2.4 +/- 0.1 2.8 +/- 0.1 2.6 +/- 0.1 2.6 +/- 0.1 2.7 +/- 0.1 2.6 +/- O.1 6/24/2013 7/1/2013 1.9 +/-0.3 1.5 +/-0.1 1.8 +/- 0.2 1.6 +/-0.1 1.5 +/-0.1 1.7 +/-0.1 1.6 +/-0.1 7/1/2013 7/8/2013 2.2 +/-0.3 1.9 +/-0.1 2.2 +/- 0.1 2.2 +/-0.2 2.2 +/- 0.1 2.1 +/-0.1 2.2 +/- 0.1 7/8/2013 7/15/2013 2.2 +/- 0.2 1.9 +/-0.1 2.2 +/- 0.1 2.3 +/- 0.1 2.1 +/-0.1 2.1 +/-0.1 1.9 +/-0.1 7/15/2013 7/22/2013 4.5+/-0.3 2.9 +/- 0.2 2.7 +/- 0.2 2.6 +/- 0.1 2.5 +/- 0.1 2.4 +/- 0.1 2.2 +/- 0.1 7/22/2013 7/29/2013 1.5+!-0.1 1.2 +/- 0.1 1.5 +/-0.1 1.6 +/-0.1 1.5 +/- 0.1 1.4 +/-0.1 1.4 +/-O.1 7/29/2013 8/5/2013 1.7 +/-0.1 1.4 +/-0.1 1.8 +/-0.1 1.7 +/-0.1 1.7 +/-0.1 1.6 +/-0.1 1.7 +/-0.1 8/5/2013 8/12/2013 1.8+/-0.1 1.6 +/- 0.1 1.9 +/-0.1 1.8 +/-0.1 1.8 +/-01 1.9 +/-0.1 1.9 +/-0.1 8/12/2013 8/19/2013 2.0 +/- 0.1 1.9 +/- 0.1 2.1 +/-0.1 2.0 +/- 0.1 2.2 +/- 0.1 2.0 +/-0.1 2.2 +/-0.1 8/19/2013 8/26/2013 3.6+/-0.2 3.6 +/- 0.2 3.8 +/- 0.2 3.6 +/- 0.2 2.4 +/- 0.1 3.8 +/- 0.2 3.7 +/- 0.2 8/26/2013 912/2013 3.5 +/- 0.2 3.0 +/- 0.1 3.7 +/- 0.2 3.4 +/-0.2 3.4 +/- 0.2 3.6 +/- 0.2 3.1 +/-0.1 9/2/2013 9/9/2013 2.0 +1-0.1 1.9 +/-0.1 2.1 +/-0.1 1.8 +/- 0.1 1.9 +/-0.1 1.9 +/- O.1 2.2 +/- 0.1 9/9/2013 9/16/2013 3.1 +/-0.2 2.8 +/- 0.2 3.5 +/-0.2 3.0 +/- 0.2 3.0 +/-0.2 3.1 +/-0.2 2.7 +/- 0.1 9/16/2013 9/23/2013 2.1 +/-0.1 2.0 +/- 0.1 2.1 +/-0.1 2.2 +/- 0.1 1.8 +/-0.1 2.2 +/- 0.1 2.2 +/- 0.1 9/23/2013 9/30/2013 2.0 +/- 0.1 1.8 +/-0.1 2.0 +/- 0.1 1.9 +/-0.1 1.9 +/-0.1 1.9 +/-0.1 2.0 +/- 0.1 9/30/2013 10/7/2013 3.3 +/-0.2 3.0 +/- 0.1 3.2 +/- 0.2 3.1 +/-0.2 3.3 +/- 0.2 3.3 +/- 0.2 3.1 +/-0.2 10/7/2013 10/14/2013 2.5 +/- 0.2 2.5 +/- 0.1 2.7 +/-0.2 2.3 +/- 0.1 2.8 +/- 0.2 2.6 +/- 0.2 2.3 +/- 0.1 10/14/2013 10/21/2013 2.6 +/- 0.1 2.5 +/- 0.1 2.9 +/- 0.1 2.6 +/- 0.1 2.7 +1-0.1 2.7 +/- 0.1 2.7 +/- 0.1 10/21/2013 10/28/2013 1.4 +/-0.1 1.3 +/-0.1 1.4 +/-0.1 1.4 +/-0.1 1.4 +/-0.1 1.2 +/-0.1 1.3 +/- 0.1 34

January 1 - December 31, 2013 Docket Nos. 50-244 Table B-5 Concentration of Beta Emitters in Air Particulates - Onsite Samples (Results in units of 10-2 pCi/m3 +/- 2a Uncertainty)

Start Date Stop Date STATION-02 STATION-03 STATION-04 STATION-05 STATION-06 STATION-07 STATION-13 Manor House East Field Training Creek Bridge Main Parking West Fence Substation 13 Yard Center Parking Lot Line Lot 10/28/2013 11/4/2013 2.8+/-0.2 2.7+/-0.1 3.0+/-0.2 2.8+/-0.1 2.9+/-0.1 3.0+/-0.1 2.7+/-0.1 11/4/2013 11/11/2013 1.8+/-0.1 1.8+/-0.1 2.1 +/-0.1 1.8+/-0.1 1.9+/-0.1 1.8+/-0.1 2.0+/-0.1 11/11/2013 11/18/2013 2.2+/-0.1 2.1 +/-0.1 2.5+/-0.1 2.1 +/-0.1 2.5+/-0.2 2.1 +/-0.1 2.1 +/-0.1 11/18/2013 11/25/2013 1.4+/-0.1 1.4+1-0.1 1.5+/-0.1 1.4+/-0.1 1.5+/-0.1 1.4+/-0.1 1.7+/-0.1 11/25/2013 12/2/2013 2.7+/-0.1 2.7+/-0.1 2.8+/-0.2 2.6+/-0.1 2.6+/-0.1 2.6+/-0.1 2.8+/-0.1 12/2/2013 12/9/2013 3.6 +/-0.2 3.6 +/-0.2 3.7 +/-0.2 3.4 +/-0.2 3.7+/-0.1 3.7 +/-0.2 3.6 +/-0.2 12/9/2013 12/16/2013 3.0+/-0.2 3.1 +/-0.1 3.2+/-0.2 2.9+/-0.1 2.9+/-0.1 2.9+/-0.1 3.0+/-0.1 12/16/2013 12/23/2013 2.4 +/-0.1 2.2 +/-0.1 2.3+/-0.1 2.3 +/-0.1 2.6 +/-0.2 2.6 +/-0.1 2.4 +/-0.1 12/23/2013 12/3012013 3.5 +/-0.2 3.4 +/-0.2 3.1 +/-0.2 3.4 +/-0.2 3.5 +/-0.2 3.6 +/-0.2 3.5 +/-0.2 35

January I - December 31, 2013 Docket Nos. 50-244 Table B-6 Concentration of Beta Emitters in Air Particulates - Offsite Samples (Results in units of 10-2 pCi/m3 +/- 2y Uncertainty)

Start Date Stop Date STATION- STATION- STATION- STATION- STATION-081 09 10' 11 121 Seabreeze Webster Walworth Williamson Sodus Point 12/2/2013 12/9/2013 3.6 +/- 0.2 3.6 +/- 0.2 3.7 +/- 0.2 3.4 +/- 0.2 3.7 +/-0.1 12/9/2013 12/16/2013 3.0 +/-0.2 3.1 +/-0.1 3.2 +/- 0.2 2.9 +/- 0.1 2.9 +/-0.1 12/16/2013 12/23/2013 2.4 +/- 0.1 2.2 ÷/- 0.1 2.3 +/- 0.1 2.3 +/- 0.1 2.6 +1- 0.2 12/23/2013 12/30/2013 3.5 +/- 0.2 3.4 4/- 0.2 3.1 +/-0.2 3.4 +/-0.2 3.5 +/- 0.2 1/28/2013 2/4/2013 3.2 +/- 0.2 2.8 +/- 0.2 3.0 +/-0.2 3.1 +/-0.2 2.9 +/- 0.1 2/4/2013 2/11/2013 2.6+/-0.2 3.0 +/- 0.2 2.7 +/- 0.2 3.2 +/-0.3 2.9 +/- 0.2 2/11/2013 2/18/2013 2.3 +/- 0.1 2.1 +/-0.1 2.4 +/- 0.1 2.5 +/- 0.2 2.3 +/- 0.1 2/18/2013 2/25/2013 1.5 +/-0.1 1.5 +/-0.1 1.5+/-0.1 1.6 +/- 0.2 1.6 +/- 0.1 2/25/2013 3/4/2013 1.7 +/-0.1 1.6 +/-0.1 1.6 +/-0.1 1.8 +/- 0.2 1.7 +/- 0.1 3/4/2013 3/11/2013 1.5 +/-0.1 1.4 +/-0.1 1.4 +/- 0.1 1.5 +/- 0.2 1.4 +/- 0.1 3/11/2013 3/18/2013 2.3 +/- 0.1 2.5 +/- 0.1 2.4 +/- 0.1 2.9 +/- 0.2 2.3 +/- 0.1 3/18/2013 3/25/2013 1.7 +1-0.1 1.7 +/-0.1 1.7 +/-0.1 1.9 +/- 0.2 1.7 +/-0.1 3/25/2013 4/11/2013 1.3 +/-0.1 1.2 +/- 0.1 1.1 +/-0.1 1.5 +/-0.2 1.3 +/-0.1 4/1/2013 4/812013 2.4 +/- 0.1 2.4 +/-0.1 2.2 +/-0.1 2.4 +/- 0.2 2.1 +/-0.1 4/8/2013 4/15/2013 1.4 +/-0.1 1.4 +/-0.1 1.3 +/-0.1 1.5 +/-0.2 1.3 +/-0.1 4/15/2013 4/22/2013 2.3 +1-0.1 2.1 +/-0.1 2.1 +/-0.1 2.3 +/- 0.2 2.0 +/- 0.1 4/22/2013 4/29/2013 3.0 +/-0.2 3.0 +/- 0.2 2.8 +/- 0.2 2.9 +/- 0.2 2.6 +/- 0.1 4/29/2013 5/6/2013 1.9 +/-0.1 1.8 +/- 0.1 1.9 +/-0.1 1.9+/-0.1 1.9 +/-0.1 5/6/2013 5/13/2013 1.5 +/-01 1.6 +/-0.2 1.3 +/-0.1 1.3 +/-0.1 1.2 +/-0.1 5/13/2013 5/20/2013 2.2 +/- 0.1 2.2 +/- 0.2 2.1 +/-0.1 2.0 +/- 0.1 1.7 +/-0.1 5/20/2013 5/27/2013 1.9 +/-0.1 1.9 +/- 0.2 1.7 +/- 0.1 1.9 +/- O.1 1.6 +/-0.1 5/27/2013 6/3/2013 2.3 +/- 0.2 2.7 +/- 0.3 2.3 +/- 0.2 2.2 +/-0.2 2.1 +/-0.1 6/3/2013 6/10/2013 1.5 +/-0.1 1.7 +/-0.2 1.4 +/-0.1 1.6 +/- O.1 1.4 +/- 0.1 6/10/2013 6/17/2013 1.7 +/-0.1 1.8 +/- 0.2 1.6 +/-0.1 1.6 +/- O.1 1.6 +/- 0.1 6/17/2013 6/24/2013 3.0 +/-0.2 2.9+/-0.2 2.7 +/- 0.1 2.9 +/- 0.2 2.6 +/- 0.1 6/24/2013 7/1/2013 1.7 +/-0.2 1.7 +/- 0.2 1.5 +/-0.1 1.6 +/-0.2 1.4 +/-0.1 7/1/2013 7/8/2013 2.3 +/- 0.2 2.4 +/-0.3 1.9 +/-0.1 2.3 +/- 0.2 2.1 +1-0.1 7/8/2013 7/15/2013 2.4 +/- 0.2 2.4 +/- 0.2 2.0 +/- 0.1 2.2 +/- 0.1 2.1 +/-0.1 7/15/2013 7/22/2013 2.4 +/- 0.2 2.8 +/- 0.2 2.3 +/- 0.1 3.7 +/- 0.3 3.4 +/- 0.3 7/22/2013 7/29/2013 1.6 +/-0.1 1.7 +/-0.2 1.3 +/-0.1 1.5 +/-0.1 1.4 +/-0.1 7/29/2013 8/5/2013 1.9 +/-01 1.9 +/-0.2 1.7 +/-0.1 1.9 +/- 0.1 1.8 +/-0.1 8/5/2013 8/12/2013 2.0 +/- 0.1 1.9 +/-0.2 1.8 +/-0.1 2.0 +/- 0.1 1.8 +1-0.1 8/12/2013 8/19/2013 2.3 +/- 0.1 2.3 +/- 0.2 2.1 +/-0.1 2.3 +/- 0.2 2.3 +/- 0.1 8/19/2013 8/26/2013 3.9 +/- 0.2 4.1 +/-0.3 3.6 +1-0.2 4.0 +/- 0.2 3.5 +/- 0.2 8126/2013 9/2/2013 3.4 +/- 0.2 3.5 +/- 0.2 3.1 +1-0.1 3.3 +/- 0.2 3.3 +/- 0.1 36

January I - December 31, 2013 Docket Nos. 50-244 Table B-6 Concentration of Beta Emitters in Air Particulates - Offsite Samples (Results in units of 10-2 pCi/m3 +/- 2c Uncertainty)

Start Date Stop Date STATION- STATION- STATION- STATION- STATION-08' 09 101 11 12' Seabreeze Webster Walworth Williamson Sodus Point 9/2/2013 9/9/2013 2.4 +/- 0.2 2.7 +/- 0.3 2.1 +/-0.1 2.3 +/-0.2 2.0 +/- 0.1 9/9/2013 9/16/2013 2.9 +/- 0.2 3.0 +/- 0.3 2.7 +/- 0.1 3.0 +/- 0.2 2.9 +/- 0.2 9/16/2013 9/23/2013 2.7+/-0.2 2.6 +/-0.2 2.0 +/- 0.1 2.6 +/-0.2 2.4 +/- 0.1 9/23/2013 9/30/2013 2.4 +1-0.1 2.2 +1-0.2 2.0 +1-0.1 2.1 +/-0.1 1.9 +/- 0.1 9/30/2013 10/7/2013 3.2 +/- 0.2 3.7 +/- 0.3 3.1 +/-0.1 3.5 +/-0.2 3.4 +/- 0.2 10/7/2013 10/14/2013 2.6+/-0.2 2.6+/-0.2 2.2 +/- 0.1 2.6 +/-0.2 2.6 +/- 0.1 10/14/2013 10/21/2013 3.0 +/- 0.2 3.1 +/-0.3 2.7 +/- 0.1 3.1 +/-0.2 2.9 +/- 0.1 10/21/2013 10/28/2013 1.5 +/-0.1 1.5 +/- 0.2 1.2 +/-0.1 1.4 +/-0.1 1.3 +/-0.1 10/28/2013 11/4/2013 2.8 +/-0.2 2.8 +/- 0.2 2.6 +/- 0.1 3.0 +/- 0.2 2.8 +/- 0.1 11/4/2013 11/11/2013 2.0 +/- 0.1 1.9 +/-0.2 1.8 +/- 0.1 2.1 +/-0.1 1.9 +/-0.1 11/11/2013 11/18/2013 2.3 +/- 0.1 2.4 +/-0.2 2.1 +/-0.1 2.4 +/- 0.1 2.1 +/-0.1 11/18/2013 11/25/2013 1.6 +/- 0.1 1.7 +/-0.2 1.4 +/-0.1 1.7 +/-0.1 1.7 +/-0.1 11/25/2013 12/2/2013 3.0 +/- 0.2 3.1 +/-0.2 2.6 +/- 0.1 3.2 +/- 0.2 3.0 +/- 0.1 12/2/2013 12/9/2013 3.8 +/- 0.2 3.7+/-0.3 3.3 +/- 0.1 3.7 +/- 0.2 3.5 +/- 0.2 12/9/2013 12/16/2013 2.9+/-0.2 3.0 +/- 0.2 2.6 +/- 0.1 3.1 +/-0.2 3.1 +/-0.1 12/16/2013 12/23/2013 2.6 +/- 0.2 2.4 +/-0.2 2.3 +/- 0.1 2.9 +/- 0.2 2.6 +1-0.1 12/23/2013 12130/2013 3.3+/-0.2 3.5+/-0.3 3.2 +/- 0.1 3.9 +/-0.2 3.5 +/-0.2

'Control Location 37

January 1 - December 31, 2013 Docket Nos. 50-244 Table B-7 Concentration of Gamma Emitters in Air Particulates (Results in units of 10-1 pCi/mr3 +/- 2c)

Location Description 4/1/2013 7/1/2013 9/30/2013 12/30/2013 Manor House STATION-02 Manor House Yard STATION-03 East Field

'k STATION-04 Training Center Parking Lot STATION-05 Creek Bridge STATION-06 Main Parking Lot STATION-07 West Fence Line STATION-08 1 Seabreeze STATION-09 Webster STATION-10' Walworth t t STATION-1 1 Williamson

'It 'It STATION-1 21 Sodus Point STATION-1 3 Substation 13 Control Location

No Man-Made Gamma Emitters Detected.

38

January 1 - December 31, 2013 Docket Nos. 50-244 Table B-8 Concentration of Gamma Emitters in Vegetation Samples (Results in units of pCi/kg (wet) +/- 2a)

Sample Code Sample Date Sample Type Gamma Emitters CONTROL1 Local Sites in Control Sectors 8/1/2013 Cucumbers 811/2013 Onion (root) 8/1/2013 Squash 8/1/2013 Tomato 8/1/2013 Tuber (potato) 10/17/2013 Apples 10/17/2013 Cabbage EAST East Sector 7(1/2013 Greens 7/22/2013 Onion (root) 7(22/2013 Tuber (potato) 7/30/2013 Squash 8/20/2013 Tomato 9/9/2013 Tomato 9/20/2013 Apples 9/26/2013 Cucumbers 10/15/2013 Cabbage ESE East South East Sector 7/15/2013 Squash 7/19/2013 Onion (root) 7/19/2013 Tuber (potato) 7/22/2013 Cucumbers 7/22/2013 Greens 7/30/2013 Blackberries 9/9/2013 Tomato 10/15/2013 Cabbage HAMLIN 1 Control 8/1/2013 Greens SSE ak South South East Garden 7/1/2013 Greens 7/15/2013 Onion (root) 7/19/2013 Squash 7/19/2013 Tuber (potato) 8/5/2013 Cucumbers *z 9/9/2013 Cabbage 9/9/2013 Tomato 9/11/2013 Apples SW South West Sector 7/3/2013 Raspberries

'Control Location

No Man-Made Gamma Emitters Detected.

39

January I - December 31,2013 Docket Nos. 50-244 Table B-9 Concentration of Gamma Emitters (including 1-131) in Milk (Results in units of pCi/Liter +/- 2ca Sample Code Sample Date Gamma Emitters EATON ESE Indicator 1/22/2013 2/19/2013 3/19/2013 4/16/2013 5/13/2013 5/28/2013 6/10/2013 6/25/2013 7/8/2013 7/16/2013 7/22/2013 815/2013 8/19/2013 9/3/2013 9/16/2013 9/30/2013 10/14/2013 10/28/2013 11/25/2013 12/17/2013 SCHULTZ South Sodus Control 1/22/2013 2/19/2013 3/19/2013 4/16/2013 5/13/2013 5/28/2013 6/10/2013 6/25/2013 718/2013 7/16/2013 7/22/2013 8/5/2013 8/19/2013 9/3/2013 9/16/2013 9/30/2013 10/1412013 10/28/2013 11/25/2013 12/17/2013

No Man-Made Gamma Emitters Detected.

40

January I - December 31, 2013 Docket Nos. 50-244 Table B-10 Typical MDA Ranges for Gamma Spectrometry Surface Selected Air Water, Ground- Oysters Shoreline Vegetation Nuclides Particulates Drinking Fish water Milk (pCikg) Sediment Soil (pCi/kg) (pCiIL)

(10.2 pCi/m3 ) Water (pCi/L)

Na-22 0-0 2.4-5.6 15.1 -20.5 3.8-4.6 4.5-6.5 11.6-16 30.7-51 36.8-62.7 11.5-34.1 K-40 0-0 26.7 - 56.4 99.2 - 162.5 37.1 - 55.5 36.3 - 53.7 94.1 - 125.4 229.6 - 461.4 298 - 492.8 80.3 - 307.1 Cr-51 0-0 21.3-37.4 57.8-164.8 28.4- 34.9 27.7- 38.4 60.4-87.9 225.1 - 285.2 261.3 - 490.7 60.6-251.2 Mn-54 0-0 2.4-4.7 11.5-15.3 3.4-4.3 3.5-5 8.9-12.2 29.1 -38 31.6-56.2 8.6-28.2 Co-58 0-0 2.5-4.7 11-17.2 3.6-4.1 3.4-5 8.9-12.3 29.6-37.8 33.2-57.1 8.6-28.7 Fe-59 0-0 4.8-10.8 24.4-49.2 7.4-9 8.3-11.8 20.3-30 60.7-93.7 71.8-126.1 19.3-66.9 Co-60 0-0 2.4-5.2 13.5-18.5 3.7-4.6 4-5.9 10.4-13.8 28.6-40.5 34.9-60 10.2-31.3 Zn-65 0-0 4.9- 10.6 28.6-41.8 7.5- 11.4 8.6- 12.2 23.4-29.8 70.7- 109.1 84.7-151 22.3-68.3 Nb-95 0-0 2.8-5 10.4- 22.1 4.1 -4.7 3.5-5 9.8- 14.2 34.9-44.7 39.9- 75.3 8- 32.2 Zr-95 0 -0 4.4-8.2 19.1 - 30.4 6.1 - 7.1 6- 8.3 16.3 - 20.9 47.7 - 72 58.9- 102.3 14.2 - 50 Ru-106 0-0 22.6- 39.2 96.1 - 122.9 29.6- 36.1 30.5-40.6 82.5- 102.4 235.6 - 304.7 270.8 - 446.6 81.4-233.2 Ag-110m 0-0 2.4-4.4 10.9-14.5 2.7-4 3.3-4.4 8.9-11.8 22.2-34.6 35.2-57.1 8.3-26.6 1-1311 0-1.7 .4-6.5 14.3-254.5 2.6-10.4 .5-.6 9.3-19.5 41.9-71.6 40.4-184.2 9.1 -96.3 Cs-134 0-0 2.4-4.3 10.1 -13.1 3.3-4.1 3.2-4.4 8.7-10.5 26.9-38 32.6-56.9 8.1 -26.3 Cs-137 0-0 2.3-4.6 8.4-15.1 3.1 -4.5 3.2-4.7 7.5-12.1 25.6-37.5 31 -49.4 8.8-28.5 Ba-140 0- .1 4.5-9.8 15.1 - 107.5 5.2-10.4 4.5-8 11.3-26.3 53.1 -75.4 65.8-163.9 .2-72.6 La-140 0-.1 4.5-9.8 15.1 -107.5 5.2-10.4 4.5-8 11.3-26.3 53.1 -75.4 65.8-163.9 .2-72.6 Ce-144 0-0 15.4-23.2 44.3-58.4 16.1 -23 18.7-23.7 43.1 -48.6 111.6 - 142.4 128.2 - 221.1 38.2-118.6

' This MDA range for 1-131 on a charcoal cartridge is typically 4.16 x 10--" to 3.40 x 10- pCi.'m' 41

January 1 - December 31, 2013 Docket Nos. 50-244 Table B-1I1 Typical LLDs for Gamma Spectrometry Selected Air Surface Water, Fish pCi/kg Groundwater Oysters pCi/kg Soil pCi/kg Precipitation Vegetation Particulates (dry) pCi/kg (dry)

Nuclides 10,3 pCi/m3 pCi/L (wet) pCi/L (wet) pCi/L Na-22 2.9 2.9 22 2.9 22 2.9 24 35 Cr-51 12 17 88 17 88 17 110 162 Mn-54 2.1 2.4 17 2.4 17 2.4 18 27 Co-58 2 2.4 16 2.4 16 2.4 17 25 Fe-59 4.6 5.2 37 5.2 37 5.2 38 60 Co-60 2.7 2.8 22 2.8 22 2.8 21 33 Zn-65 2.8 5.6 23 5.6 23 5.6 54 66 Nb-95 1.9 2.2 15 2.2 15 2.2 18 25 Zr-95 3.3 3.8 27 3.8 27 3.8 29 44 Ru-106 17 20 135 20 135 20 146 223 Ag-110rn 1.8 2.1 14 2.1 14 2.1 16 25 Te-1 29m 20 26 149 26 149 26 180 265 1-131* 1.5 2 11 2 11 2 14 20 Cs-1 34 1.9 2.2 15 2.2 15 2.2 20 24 Cs-1 37 1.8 2.3 15 2.3 15 2.3 17 27 Ba-140 6.1 7.3 48 7.3 48 7.3 54 80 La-140 3.4 4.1 26 4.1 26 4.1 25 41 Ce-144 5.5 12 43 12 43 12 75 101

The LLD for 1-131 measured on a charcoal cartridge is 2.0 x 10"' pCi/m "

42

January I - December 31, 2013 Docket Nos. 50-244 Table B-12 Direct Radiation (Results in Units of mR/90 days +/- 2a)

Station Location First Second Third Fourth Quarter Quarter Quarter Quarter 2 Onsite-Manor House Yard 12.7 _ 0.4 12.2 1 0.7 11.5 +/- 0.6 14.8 +/- 0.8 Onsite-In field approximately 200 ft SE of 3 12.3 +/- 0.7 12.2 +/- 0.5 12.7 +/- 0.7 15.7 +/- 1.2 station #2 4 Onsite-Training Center yard driveway circle 11.3 +/- 0.5 11.9 +/- 0.6 11.2 +/- 0.6 14.0 +/- 0.8 5 Onsite-Between creek and plant entry road 12.7 _ 0.5 12.5 +/- 0.9 12.3 +/- 0.5 14.8 +/- 0.8 6 Onsite-SW side of plant parking lot 9.6 + 0.6 9.5 +/- 0.8 9.0 +/- 0.4 11.8 +/- 1.3 7 Onsite-utility pole along West plant fence 12.5 +/- 0.8 11.0 +/- 0.6 10.6 +/- 0.7 13.5 +/- 1.0 Topper Drive-Irondequoit, Seabreeze 81 10.9 +/- 0.5 11.3 +/- 0.7 10.4 +/- 0.7 13.6 +/- 1.1 Substation #51 Phillips Road-Webster, intersection with 9 10.9 +/- 0.6 10.9 +/- 0.5 10.7 +/- 0.5 12.5 +/- 1.1 Highway #104, Substation #74 101 Atlantic Avenue-Walworth, Substation #230 10.3 +/- 0.8 10.0 +/- 0.7 9.7 +/- 0.4 12.2 +/- 0.6 11 W. Main Street-Williamson, Substation #207 9.8 + 0.5 10.4 +/- 0.8 10.1 +/- 0.7 12.5 +/- 1.0 12 Seaman Avenue-Sodus Point-Off Lake Road 121 11.4 +/- 0.8 11.7 +/- 0.5 11.3 +/- 0.6 14.1 + 1.1 by Sewer district, Substation #209 13 Onsite- South of Meteorological Tower 15.9 + 0.9 15.0 +/- 0.6 15.3 +/- 1.0 18.3 +/- 0.8 14 NW corner of field along lake shore 11.5 +/- 0.5 12.0 +/- 0.8 10.9 +/- 0.5 14.2 + 1.0 Field access road, west of orchard, 15 12.0 + 0.5 13.4 +/- 0.8 12.7 +/- 0.6 14.2 + 0.7 approximately 3000' West of plant 43

January I - December 31, 2013 Docket Nos. 50-244 TABLE B-12 (Continued)

Direct Radiation (Results in Units of mR/90 days +/- 2c)

First Second Third Fourth Station Location Quarter Quarter Quarter Quarter SW Corner of orchard, approximately 3000' 16 West of plant, approximately 200' North of 11.8 + 0.6 12.7 +/- 0.9 12.3 +/- 0.5 14.6 +/- 0.9 Lake Road 17 Utility pole in orchard, approximately 75" North 11.6 0.8 12.2 +/- 0.9 11.8 +/- 0.7 13.8 1.1 of Lake Road 18 Approximately 30' North of NE corner of 9.8 0.8 9.8 +/- 0.5 9.3 +/- 0.6 13.0 0.9 Substation 13A fence 19 On NW corner of house 100' East of plant 10.4 + 0.5 11.1 +/- 1.0 10.1 +/- 0.8 11.5 + 0.7 access road Approximately 150' West of Ontario Center 20 Road and approximately 170' South of Lake 11.4 + 0.6 11.4 +/- 0.8 11.4 +/- 0.6 14.3 + 0.9 Road North side of Lake Road, approximately 200' 21 East of Ontario Center Road 11.2 +/- 0.6 11.5 +/- 0.5 11.8 +/- 0.6 13.5 + 0.7 22 North side of Lake Road, SE, property owner 10.7 +/- 0.5 10.1 +/- 0.5 10.5 +/- 0.5 12.4 +/- 0.9 East property line, midway between Lake 0.5 +/- 1.1 23 Road and Lake shore 11.3 + 12.2 +/- 0.6 12.2 t 0.9 14.4 24 Lake shore near NE corner of property 12.4 + 0.5 12.1 +/- 0.7 12.0 t 0.6 14.1 +/- 0.8 25 Substation #73, Klein Road, adjacent to 897 1

Klem Road 9.9 + 0.5 10.6 + 0.7 9.3 t 0.6 12.9 +/- 0.9 26 Service Center, Plank Road, West of 250 10.3 +/- 0.4 11.0 10.7 +/- 0.5 12.3 +/- 0.7 Atlantic Avenue at Knollwood Drive utility pole, 271 North side of road 10.9 + 0.4 11.1 - 0.6 10.4 +/- 0.6 12.9 + 0.9 Substation #193, Marion, behind Stanton Ag.

28' 9.8 + 0.4 10.8 +/- 0.6 9.8 +/- 0.8 12.5 +/- 0.7 Service, North Main Street 44

January 1 - December 31, 2013 Docket Nos. 50-244 TABLE B-12 (Continued)

Direct Radiation (Results in Units of mR/90 days +/- 2a)

.*tnif,, I ,.-mo*. First Second Third Fourth Quarter Quarter Quarter Quarter 29 ' Substation #208, Town Line Road (CR-118),

1000' North of Route 104 10.1 + 0.5 10.5 +/- 0.7 10.1 +/- 0.5 12.7 + 1.0 30 1 District Office, Sodus, on pole, West side of 9.6 +/- 0.6 9.7 +/- 0.5 9.0 +/- 0.5 11.7 +/- 1.1 bldg Lake Road, pole 20' North of road, 500' East of Salt Road 11.7 +/- 0.6 12.0 +/- 0.8 12.2 1 0.7 14.5 + 0.8 32 Woodard Road at County Line Road, pole @

9.9 + 0.6 10.2 +/- 0.5 10.1 +/- 0.5 13.1 +/- 0.8 BW corner 33 County Line Road at RR tracks, pole 10.6 _ 0.6 9.5 +/- 0.8 10.6 +/- 0.5 12.7 + 0.9 approximately 100' East along tracks Lincoln Road, pole midway between Ridge 12.3 +/- 0.6 12.4 +/- 0.9 12.4 +/- 0.6 14.8 + 0.8 Road and Route 104 Transmission Right of Way, North of 11.0 + 0.5 12.4 +/- 0.8 12.0 +/- 0.6 13.8 _ 0.8 Clevenger Road on pole 36 Substation #205, Route 104, East of Ontario 9.9 +/- 0.6 11.1 +/- 0.6 10.0 +/- 0.5 12.6 +/- 1.0 Center Road, North side of fence 37 Rail Road Avenue, pole at 2048 9.5 +/- 0.6 9.8 +/- 0.7 9.2 +/- 0.7 12.4 +/- 0.7 38 Fisher Road at RR Tracks, pole East of road 12.1 _ 0.7 11.9 +/- 0.8 11.4 +/- 0.5 14.1 +/- 0.9 39 Seeley Road, Pole South side 100' West of intersection with Stony Lonesome Road 11.1 +/- 0.7 11.9 +/- 0.6 11.2 +/- 0.6 14.1 + 0.8 Lake Road at Stoney Lonesome Road, pole at 10.1 _ 0.5 10.1 +/- 0.7 10.1 +/- 0.5 12.1 +/- 0.9 SE corner 63 Westside of warehouse access road 11.9 +/- 0.6 11.3 +/- 1.0 11.8 +/- 0.8 13.6 +/- 1.1 64 Westside of direct road, adjacent to orchard 13.8 +/- 0.5 13.1 +/- 0.6 13.3 +/- 0.8 15.8 +/- 0.8 1 - Control Location 45

January I - December 31, 2013 Docket Nos. 50-244 TABLE B-13 Groundwater Monitoring Wells Location Sample Date Tritium (uCi/ml) Gamma (uCi/mi)

GW01: Warehouse Access Road (Control) 03/07/2013 *

06/20/2013 *

08/13/2013

12/03/2013 *

GW03: Screenhouse West, South Well 10/15/2013 *

11/07/2013

12/03/2013

GW04: Screenhouse West, North Well 02/01/2013

02/15/2013 *

03/07/2013 *

04/19/2013 *

05/21/2013

06/20/2013

07/25/2013 *

08/14/2013 *

09/19/2013 *

12/03/2013 *

GW05: Screenhouse East, South (15.5') 03/07/2013

06/20/2013 *

08/13/2013 *

12/03/2013 *

GW06: Screenhouse East, Middle (20.0') 03/07/2013 *

06/20/2013 *

08/13/2013 *

12/03/2013 *

GWO7: Screenhouse East, North (24.0') 03/07/2013 *

06/20/2013 *

08/13/2013 *

12/03/2013 *

46

January I - December 31, 2013 Docket Nos. 50-244 TABLE B-13 (Continued)

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

GW08: All Volatiles Treatment Building 01/30/2013 *

02/15/2013

03/07/2013 *

04/19/2013

05/21/2013 *

06/20/2013 *

07/25/2013 *

08/13/2013 *

09/19/2013 *

10/15/2013 *

11/07/2013 *

12/20/2013 *

GW1 0: Technical Support Center, South 03/07/2013

06/20/2013

08/13/2013

12/03/2013 *

GW1 1: Southeast of Contaminated Service Building (CSB) 03/07/2013

06/20/2013 *

08/13/2013 *

12/03/2013 *

GW12: West of Orchard Access Road 12/03/2013 GW13: North of Independent Spent Fuel Storage Installation (ISFSI) 12/03/2013 GW14: South of Canister Preparation Building 12/03/2013 GW15: West of Manor House 12/03/2013 GW16: Southeast of Manor House 12/03/2013

No Man-Made Gamma Activity or Tritium Detected 47

January 1 - December 31,2013 Docket Nos. 50-244 APPENDIX C Quality Assurance Program Summary of Appendix C Content:

Appendix C is a summary of Exelon Industrial Services - Ft. Smallwood Environmental Laboratory quality assurance program. It consists of Table C-I which is a compilation of the results of the Constellation Energy Laboratory's participation in an intercomparison program with Environmental Resource Associates (ERA) located in Arvada, Colorado and Analytics, Inc. located in Atlanta, Georgia.

It also includes Table C-2 which is a compilation of the results of the Ft. Smallwood Environmental Laboratory's participation in a split sample program with Teledyne Brown Engineering located in Knoxville, Tennessee and Table C-3 which is a list of typical MDA's achieved by Teledyne Brown for Gamma Spectroscopy.

Of the 74 Ft. Smallwood Environmental Laboratory results contained in Table C-1, 67 agree with the intercomparison laboratory results within the range of +2 a of each other (90.54%). The seven exceptions are as follows:

1. 03/14/13 sample of milk for Cs-137.

2. 04/18/13 sample of water for Gross Beta

3. 06/13/13 air filter sample for Cs- 134

4. 12/05/13 air filter sample for Zn-65

5. 12/05/13 air filter sample for Cs- 134

6. 12/05/13 sample of milk for Cs-137

7. 12/05/13 sample of water for Gross Beta The above-mentioned intercomparisons do not satisfy the +/-2 a crosscheck, but all are within full agreement when they were further evaluated using the NRC Resolution Test Criteria.' The uncertainties for the Ft. Smallwood Environmental Laboratory results2 and Analytics' results are +2a while the ERA laboratory's uncertainty is based on USEPA guidelines.

All results contained in Table C-2 agree within the range of +/-2 a of each other with their respective Ft.

Smallwood Environmental Laboratory original, replicate, and/or Teledyne Brown Engineering's split laboratory samples. Other samples whose nature generally precludes sample splitting are marked "**"

in the Split Analysis column.

48

January I - December 31,2013 Docket Nos. 50-244 TABLE OF CONTENTS - ANALYTICAL RESULTS Table Title Page C-1 Results of Participation in Cross Check Program ....................................................................... 50 C-2 Results of Quality Assurance Program ....................................................................................... 53 C-3 Teledyne Brown Engineering's Typical MDAs for Gamma Spectrometry ............................... 59 49

January I - December 31, 2013 Docket Nos. 50-244 TABLE C-I Results of Participation in Cross Check Program Reported Cross Check Lab Sample Date Sample Type and Isotope Observed Laboratory's Ross Units ResultsResults 03/14/13 Milk - pCi Mn-54 213+/-15 208 +1-3.5 Fe-59 288 +/- 25 252 +/- 4.2 Cr-51 433 +/- 96 472 +/- 7.9 Ce-141 198+/-22 187 +/- 3.1 Cs-1 37 286+/-16 26.6 +/-4.4 Cs-1 34 208 +/- 7.0 214 +/- 3.6 1-131 85 +/- 42 100 +/-1.7 Zn-65 342 +/- 29 301 +1-29.0 Co-58 216+/-17 208 +/- 3.5 Co-60 399 +/- 14 400 +/- 6.7 03/14/13 Water - pCi/L Gross Beta 312 +/-4.0 300 +/-5.0 04/08/13 Water - pCi/L Cs-1 34 39.0 +/- 3.0 42.8 Zn-65 203 +/- 13 189 Co-60 66.0 +/-4.0 65.9 Cs-1 37 42.0 +/- 4.0 41.7 04/18/13 Water - pCi/L Gross Beta 15.5 +/- 1.0 21.6 06/13/13 Water - pCi/L Mn-54 215 +/- 14 210 +/- 3.5 Fe-59 160 +/- 15 146 +/- 2.4 Co-58 113+/-11 115 +/-1.9 Co-60 216 +/- 10 214 +/- 3.6 Zn-65 283 +/- 25 265 +/- 4.4 1-131 102 +/- 11 95.4 +1-1.6 Cs-1 34 143 +/-8 153 +/- 2.6 Cs-1 37 187 +/- 13 184 +/- 3.1 Ce-141 108 +/- 12 110 +/- 1.8 Cr-51 317+/-67 306 +/- 5.1 06/13/13 Air Filter - pCi/L1 Mn-54 91.0 +/-7.0 90.4 +/- 1.5 Fe-59 67.0 +/- 8.0 62.9 +1-1.1 Co-58 48.0 +/- 5.0 49.4 +/-0.8 Co-60 91.0 +/-6.0 92.2 +/-1.5 Zn-65 122 +/- 13.0 114.0 +/- 1.9 Cs-1 34 55.0 +/- 4.0 65.8 +/- 1.1 Cs-1 37 78.0 +/-6.0 79.4 +/- 1.3 Ce-1 41 48.0 +/-4.0 47.5 +/- 0.8 Cr-51 134 +/-25 132 +/- 2.2 Mn-54 91.0 +/-7.0 90.4 +/-1.5 50

January 1 - December 31, 2013 Docket Nos. 50-244 TABLE C-I - Continued Results of Participation in Cross Check Program Reported Cross Check Lab SampleD Sample Type and Isotope Observed Laboratory's Ross Sam eUnits ResulResults 07/08/13 Water - pCi/L Gross Beta 307 +/- 3.71 294 +/- 4.9 07/08/13 Water - pCi/L Cs-1 34 66.0 +/- 3 72.4 +/- 3 1-131 21.0 +/- 8 24.3 +/- 2 Co-60 82.4 +/- 5 82.3 +/- 4 Zn-65 286 +/- 16 286 +/- 19 Cs-1 37 152 +/- 7 155 +/- 8 07/08/13 Water - pCi/L Ba-1 33 68.3 +/- 5 74.5+/-4 09/12/13 Air Filter - pCi/L Gross Beta 34.0 +/- 1 41.8 +/- 6 09/12/13 Water - pCi/L Gross Beta 71.6 +/-2 67.2 +/- 1.12 10/07/13 Water - pCi Zn-651 394 +/- 24 333 +/- 13 Cs-1 34 86.8 +/- 7 86.7 +/- 4 Co-60 Il1 +/-8 102 +/- 5 10/07/13 Water - pCi 1-131 22.4 +/-4 23.6 +/- 1 12/05/13 Air Filter - pCi/L Cs-i 37 225 +/- 11.0 206 +/- 7.4 Fe-59 109 +/- 12.0 94.7 +/- 1.6 Co-58 93.0 +/- 9.0 96.3 +/- 1.6 Co-60 125 +/- 6.0 126 +/- 2.1 Zn-65 744.0 +/- 29.0 637.0 +/- 10.6 Cs-i 34 100.0 +/- 4.0 122.0 +/- 2.0 Cs-i 37 112.0 +/- 7.0 108.0 +/- 1.8 Mn-54 153.0 +/- 9.0 144.0 +/- 2.4 Cr-51 233.0 +/- 75.0 255.0 +/- 4.3 12/05/13 Air Iodine Ce-141 99.0 +/- 10.0 94.3 +/- 1.6 12/05/13 Bay Water 1-131 80.0 +/- 6.0 80.2 +/- 1.3 51

January 1 - December 31,2013 Docket Nos. 50-244 TABLE C-I - Continued Results of Participation in Cross Check Program Sample Type and Reported Cross Check Lab Sample Date SmlDaeUnits Same TIsotope Observed Laboratory's Results Results Results 12/05/13 Milk - pCi/L H-3 23.0 +/- 0.0 25.0 Fe-59 122+/-14 110+/-1.8 Co-58 114+/-11 112 +/- 1.9 Co-60 152+/-8 147+/-2.5 Zn-65 809 +/- 37 741 +/- 12.4 1-131 87+/- 15 96.1 +/- 1.6 Mn-54 175 +/- 13 168 +/- 2.8 Cs-137 130+/-11 216+1-2.1 Ce-141 105+/-15 110+/-1.8 Cr-51 285 +/- 91 297 +/- 5.0 12/05/13 Water - pCi/L Cs-1 34 126 +/- 6 142 +/- 2.4 Gross Beta 324 +/- 3.82 279 +/- 4.67

'See discussion at the beginning of the Appendix 52

January 1 - December 31, 2013 Docket Nos. 50-244 TABLE C-2 Results of Quality Assurance Program Sample Type ( Sample Type of Original Replicate Split and Location (2) Date Analysis Analysis Analysis Analysis Air Filter - Al 01/07/13 Gross Beta 4.8 +/-0.2 4.6 +/-0.2 Air Filter - A2 01/07/13 Gross Beta 4.5 +/- 0.2 4.3 +/- 0.2 Air Filter - A3 01/07/13 Gross Beta 4.7 +/- 0.2 4.7 +/- 0.2 **

Air Filter - A4 01/07/13 Gross Beta 4.7 +/- 0.2 4.8 +/- 0.2 Air Filter - A5 01/07/13 Gross Beta 4.6 +/- 0.2 4.5 +/- 0.2 Air Filter - SFA1 01/07/13 Gross Beta 4.9 +/- 0.2 4.9 +/- 0.2 **

Air Filter - SFA2 01/07/13 Gross Beta 4.7 +/- 0.2 4.8 +1- 0.2 Air Filter - SFA3 01/07/13 Gross Beta 4.4 +/- 0.2 4.5 +/- 0.2 Air Filter - SFA4 01/07/13 Gross Beta 4.9 +/- 0.2 4.9 +/- 0.2 **

Air Iodine - Al 01/28/13 1-131 <MDA <MDA Air Iodine - A2 01/28/13 1-131 <MDA <MDA Air Filter - Al 02/04/13 Gross Beta 3.6 +/- 0.1 3.5 +/- 0.1 Air Filter - A2 02/04/13 Gross Beta 3.5 +/- 0.1 3.6 +/- 0.1 **

Air Filter - A3 02/04/13 Gross Beta 3.6 +/- 0.1 3.3 +/- 0.1 Air Filter - A4 02/04/13 Gross Beta 3.7 +/- 0.1 3.7 +/- 0.1 Air Filter - A5 02/04/13 Gross Beta 3.8 +/- 0.1 3.8 +/- 0.1 Air Filter - SFA1 02/04/13 Gross Beta 3.7 +/- 0.1 3.8 +/- 0.2 **

Air Filter - SFA2 02/04/13 Gross Beta 3.8 +/- 0.1 3.8 +/- 0.2 Air Filter - SFA3 02/04/13 Gross Beta 3.5 +/- 0.1 3.5 +/- 0.1 Air Filter - SFA4 02/04/13 Gross Beta 3.5 +/- 0.1 3.6 +/- 0.1 **

Air Filter - Al 02/12/13 Gamma <MDA <MDA <MDA Air Filter - A2 02/12/13 Gamma <MDA <MDA <MDA Air Filter - A3 02/12/13 Gamma <MDA <MDA <MDA Air Filter - A4 02/12/13 Gamma <MDA <MDA <MDA Air Filter - A5 02/12/13 Gamma <MDA <MDA <MDA Air Filter - SFA1 02/12/13 Gamma <MDA <MDA <MDA Air Filter - SFA2 02/12/13 Gamma <MDA <MDA <MDA Air Filter - SFA3 02/12/13 Gamma <MDA <MDA <MDA Air Filter - SFA4 02/12/13 Gamma <MDA <MDA <MDA Air Iodine - A3 02/18/13 1-131 <MDA <MDA Air Iodine - A4 02/18/13 1-131 <MDA <MDA **

53

January I - December 31, 2013 Docket Nos. 50-244 TABLE C Continued Results of Quality Assurance Program Sample Type Sample I Type of Original Replicate Split and Location (2) Date Analysis Analysis Analysis Analysis Air Filter - Al 03/04/13 Gross Beta 0.9 +/- 0.1 1.0 +/- 0.1 Air Filter - A2 03/04/13 Gross Beta 0.8 +/- 0.1 1.0 +/- 0.1 Air Filter - A3 03/04/13 Gross Beta 1.1 +/- 0.1 1.1 +/- 0.1 **

Air Filter - A4 03/04/13 Gross Beta 1.1 +/- 0.1 1.1 +/- 0.1 Air Filter - A5 03/04/13 Gross Beta 1.0 +/- 0.1 1.0 +/- 0.1 Air Filter - SFA1 03/04/13 Gross Beta 1.0 +/- 0.1 1.1 +/- 0.1 **

Air Filter - SFA2 03/04/13 Gross Beta 1.0 +/- 0.1 1.0 +/- 0.1 **

Air Filter - SFA3 03/04/13 Gross Beta 1.0 +/- 0.1 1.0 +/- 0.1 **

Air Filter - SFA4 03/04/13 Gross Beta 1.0 +/- 0.1 1.1 +/- 0.1 Air Iodine - Al 03/04/13 1-131 <MDA <MDA **

Air Iodine - A2 03/04/13 1-131 <MDA <MDA **

Oysters - IA3 03/22/13 Gamma <MDA <MDA <MDA Oysters - IA6 03/22/13 Gamma <MDA <MDA <MDA Misc ground coverage - SFB1 03/27/13 Gamma <MDA <MDA Misc ground coverage - SFB2 03/27/13 Gamma <MDA <MDA <MDA Soil - SFS1 03/27/13 Gamma <MDA <MDA <MDA Soil - SFS2 03/27/13 Gamma <MDA <MDA <MDA Bay Water - WA1 04/02/13 Gamma <MDA <MDA <MDA Bay Water - WA2 04/02/13 Gamma <MDA <MDA <MDA Shoreline sediment - WB1 04/05/13 Gamma <MDA <MDA <MDA Air Filter - Al 05/13/13 Gross Beta 1.3 +/-0.1 1.4 +/-0.1 **

Air Filter - A2 05/13/13 Gross Beta 1.2 +/- 0.1 1.4 +/- 0.1 Air Filter - A3 05/13/13 Gross Beta 1.4 +/- 0.1 1.3 +/- 0.1 **

Air Filter - A4 05/13/13 Gross Beta 1.5 +/-0.1 1.6 +/-0.1 Air Filter - A5 05/13/13 Gross Beta 1.4 +/- 0.1 1.5 +/- 0.1 **

Air Filter - SFA1 05/13/13 Gross Beta 1.6 +/- 0.1 1.5 +/- 0.1 Air Filter - SFA2 05/13/13 Gross Beta 1.5 +/- 0.1 1.5 +/- 0.1 Air Filter - SFA3 05/13/13 Gross Beta 1.3 +/- 0.1 1.3 +/- 0.1 Air Filter - SFA4 05/13/13 Gross Beta 1.5 +/- 0.1 1.4 +/- 0.1 54

January 1 - December 3l, 2013 Docket Nos. 50-244 TABLE C Continued Results of Quality Assurance Program Sample Type] Sample Type of Original Replicate Split and Location (2) Date Analysis Analysis Analysis Analysis Air Iodine - Al 05/27/13 1-131 <MDA <MDA Air Iodine - A2 05/27/13 1-131 <MDA <MDA **

Air Iodine - A3 05/27/13 1-131 <MDA <MDA Air Iodine - A4 05/27/13 1-131 <MDA <MDA Air Iodine - A5 05/27/13 1-131 <MDA <MDA Brussels sprouts -

111 06/17/13 Gamma <MDA <MDA <MDA Brussels sprouts -

1B4 06/17/13 Gamma <MDA <MDA <MDA Brussels sprouts -

1B7 06/17/13 Gamma <MDA <MDA <MDA Cabbage - 1B2 06/17/13 Gamma <MDA <MDA <MDA Cabbage - 1B5 06/17/13 Gamma <MDA <MDA <MDA Cabbage - 1B8 06/17/13 Cs-1 37 28.6 +/-9.8 16.6 +/- 8.3 **

Collards - 1B3 06/17/13 Gamma <MDA <MDA <MDA Collards - 1B6 06/17/13 Gamma <MDA <MDA <MDA Collards - 1B9 06/17/13 Gamma <MDA <MDA <MDA Bottom sediment

- WBS2 06/19/13 Cs-137 104.0 +/- 31.4 118.2 +/- 37.9 158.0 +/- 58.2 Bottom sediment

- WBS2 06/19/13 Gamma <MDA <MDA <MDA Bottom sediment

-WBS4 06/19/13 Cs-137 102.9 +/- 32.0 74.2 +/- 27.5 156.0 +/- 48.1 Bottom sediment

- WBS4 06/19/13 Gamma <MDA <MDA <MDA Oysters - IA3 06/19/13 Gamma <MDA <MDA <MDA Oysters - IA6 06/19/13 Gamma <MDA <MDA <MDA Air Iodine - Al 06/24/13 1-131 <MDA <MDA **

Air Iodine - A2 06/24/13 1-131 <MDA <MDA Air Iodine - A3 06/24/13 1-131 <MDA <MDA Air Iodine - A4 06/24/13 1-131 <MDA <MDA **

Oysters - IA3 08/15/13 Gamma <MDA <MDA 55

January I - December 3 1, 2013 Docket Nos. 50-244 TABLE C Continued Results of Quality Assurance Program Sample Type Sample Type of Original Replicate Split and Location (2) Date Analysis Analysis Analysis Analysis Air Filter - Al 08/19/13 Gross Beta 1.3 +1-0.1 1.5 +/- 0.2 Air Filter - A2 08/19/13 Gross Beta 1.3+/-0.1 1.3 +/- 0.1 **

Air Filter - A3 08/19/13 Gross Beta 1.4 +/- 0.1 1.4 +/- 0.1 Air Filter - A4 08119/13 Gross Beta 1.7 +/- 0.2 1.7 +/- 0.2 Air Filter - A5 08/19/13 Gross Beta 1.5 +/- 0.2 1.7 +/- 0.2 Air Filter - SFA1 08/19/13 Gross Beta 1.5 +/- 0.2 1.5 +/- 0.2 Air Filter - SFA2 08/19/13 Gross Beta 1.2 +/- 0.1 1.2 +/- 0.1 Air Filter - SFA3 08/19/13 Gross Beta 1.4 +/- 0.1 1.4 +/- 0.1 Air Filter - SFA4 08/19/13 Gross Beta 1.6+/-0.2 1.5+/-0.1 Air Iodine - Al 08/19/13 1-131 <MDA <MDA Air Iodine - A2 08/19/13 1-131 <MDA <MDA Air Iodine - A3 08/19/13 1-131 <MDA <MDA **

Air Iodine - A4 08/19/13 1-131 <MDA <MDA **

Air Iodine - A5 08/19/13 1-131 <MDA <MDA Air Filter - Al 08/26/13 Gross Beta 1.9 +/- 0.1 1.8 +/- 0.1 **

Air Filter - A2 08/26/13 Gross Beta 1.9 +/-0.1 1.8+/-01 **

Air Filter - A3 08/26/13 Gross Beta 1.6 +/- 0.1 1.7 +/- 0.1 Air Filter - A4 08/26/13 Gross Beta 2.0 +/- 0.1 1.9 +/- 0.1 Air Filter - A5 08/26/13 Gross Beta 2.0 +/- 0.1 2.0 +/- 0.1 Air Filter - SFA1 08/26/13 Gross Beta 1.9 +/- 0.1 2.0 +/- 0.1 **

Air Filter - SFA2 08/26/13 Gross Beta 2.0 +/- 0.1 1.9 +/- 0.1 **

Air Filter - SFA3 08/26/13 Gross Beta 1.9 +/- 0.1 1.9 +/- 0.1 Air Filter - SFA4 08/26/13 Gross Beta 1.8 +/- 0.1 1.8 +/- 0.1 **

Air Iodine - Al 08/26/13 1-131 <MDA <MDA **

Air Iodine - A2 08/26/13 1-131 <MDA <MDA **

Air Iodine - A3 08/26/13 1-131 <MDA <MDA Air Filter - Al 09/02/13 Gross Beta 2.8 +/- 0.1 2.8 +/- 0.1 Air Filter - A2 09/02/13 Gross Beta 2.6 +/- 0.1 2.7 +/- 0.1 **

Air Filter - A3 09/02/13 Gross Beta 2.7 +/- 0.1 2.6 +/- 0.1 Air Filter - A4 09/02/13 Gross Beta 3.2 +/- 0.1 3.1 +/- 0.1 Air Filter - A5 09/02/13 Gross Beta 3.2 +/- 0.1 3.2 +/- 0.1 **

56

January 1 - December 31, 2013 Docket Nos. 50-244 TABLE C Continued Results of Quality Assurance Program Sample Type Sample Type ofT Original Replicate Split and Location (2) Date Analysis Analysis Analysis Analysis Air Filter - SFA1 09/02/13 Gross Beta 3.2 +/- 0.1 3.0 +/- 0.1 Air Filter - SFA2 09/02/13 Gross Beta 3.1 +/- 0.1 2.9 +/- 0.1 **

Air Filter - SFA3 09/02/13 Gross Beta 3.2 +/- 0.1 2.9 +/- 0.1 Air Filter - SFA4 09/02/13 Gross Beta 2.8 +/- 0.1 2.7 +/- 0.1 Air Iodine - Al 09/09/13 1-131 <MDA <MDA **

Air Iodine - A2 09/09/13 1-131 <MDA <MDA **

Air Iodine - A3 09/09/13 1-131 <MDA <MDA **

Air Iodine - A4 09/09/13 1-131 <MDA <MDA Air Iodine - A5 09/09/13 1-131 <MDA <MDA Air Filter - Al 09/16/13 Gamma <MDA <MDA <MDA Air Filter - A2 09/16/13 Gamma <MDA <MDA <MDA Air Filter - A3 09/16/13 Gamma <MDA <MDA <MDA Air Filter - A4 09/16/13 Gamma <MDA <MDA <MDA Air Filter - A5 09/16/13 Gamma <MDA <MDA <MDA Air Filter - SFA1 09/16/13 Gamma <MDA <MDA <MDA Air Filter - SFA2 09/16/13 Gamma <MDA <MDA <MDA Air Filter - SFA3 09/16/13 Gamma <MDA <MDA <MDA Air Filter - SFA4 09/16/13 Gamma <MDA <MDA <MDA Air Iodine - Al 09/16/13 1-131 <MDA <MDA **

Air Iodine - A2 09/16/13 1-131 <MDA <MDA **

Air Iodine - A3 09/16/13 1-131 <MDA <MDA Air Iodine - A4 09/16/13 1-131 <MDA <MDA Air Iodine - A5 09/16/13 1-131 <MDA <MDA Misc ground coverage - SFB1 09/23/13 Gamma <MDA <MDA <MDA Soil - SFSl 09/23/13 Gamma <MDA <MDA <MDA Oysters - IA3 10/16/13 Gamma <MDA <MDA <MDA Oysters - IA6 10/16/13 Gamma <MDA <MDA <MDA 57

January I - December 31, 2013 Docket Nos. 50-244 TABLE C Continued Results of Quality Assurance Program Sample Type Sample Type of Original Replicate Split and Location (2) Date Analysis Analysis Analysis Analysis Air Filter - Al 10/21/13 Gross Beta 2.3 +1-0.1 2.3 +/- 0.1 Air Filter - A2 10/21/13 Gross Beta 4.0 +/- 0.2 4.0 +/- 0.2 **

Air Filter - A3 10/21/13 Gross Beta 2.3 +/- 0.1 2.3 +/- 0.1 Air Filter - A4 10/21/13 Gross Beta 2.1 +/-0.1 2.1 +/-0.1 Air Filter - A5 10/21/13 Gross Beta 2.1 +/- 0.1 2.2 +/- 0.1 **

Air Filter - SFA1 10/21/13 Gross Beta 2.2 +/- 0.1 2.2 +/- 0.1 Air Filter - SFA2 10/21/13 Gross Beta 2.4 +/- 0.1 2.3 +1-0.1 **

Air Filter - SFA3 10/21/13 Gross Beta 1.0 +/-0.1 0.9 +/-0.1 **

Bay Water - WA1 11/01/13 Gamma <MDA <MDA <MDA Bay Water - WA2 11/01/13 Gamma <MDA <MDA <MDA Air Iodine - Al 12/09/13 1-131 <MDA <MDA Air Iodine - A2 12/09/13 1-131 <MDA <MDA **

Air Iodine - A3 12/09/13 1-131 <MDA <MDA Air Iodine - A4 12/09/13 1-131 <MDA <MDA Air Iodine - A5 12/09/13 1-131 <MDA <MDA Air Iodine - Al 12/16/13 1-131 <MDA <MDA Air Iodine - A2 12/16/13 1-131 <MDA <MDA **

Air Iodine - A3 12/16/13 1-131 <MDA <MDA Air Iodine - A4 12/16/13 1-131 <MDA <MDA **

Air Iodine - A5 12/16/13 1-131 <MDA <MDA Air Iodine - Al 12/30/13 1-131 <MDA <MDA Air Iodine - A2 12/30/13 1-131 <MDA <MDA Air Iodine - A3 12/30/13 1-131 <MDA <MDA **

Air Iodine - A4 12/30/13 1-131 <MDA <MDA Air Iodine - A5 12/30/13 1-131 <MDA <MDA **

See discussion at the beginning of the Appendix Results reported for Air samples 1-131 and Beta are in 10-2 pCi/m3. All Vegetation and Soil, Oysters and Fish are in pCi/Kg. All water and milk are in pCi/L, TLD are in mR/90 Day

- The nature of these samples precluded splitting them with an independent laboratory.

All Non natural Gamma Emitters are <MDA 58

January 1 - December 31, 2013 Docket Nos. 50-244 Table C-3 Teledyne Brown Engineering's Typical MDAs for Gamma Spectrometry d Bay Selecte d Water Fish Shellfish Sediment Vegetation Parti culates 3

Nuclide s pCilt pCilkg pCi/kg pCi/kg pCi/kg 10-3 pCilm H-3 175 -- -- -- --

Na-22 1 8 3 12 6 5 Cr-51 12 105 4 104 50 63 Mn-54 1 9 3 12 5 4 Co-58 1 9 4 9 4 5 Fe-59 3 28 9 24 10 12 Co-60 1 9 4 12 5 6 Zn-65 2 20 8 25 10 9 Nb-95 1 12 7 14 6 9 Zr-95 2 18 8 20 9 9 Ru-1 06 9 75 30 90 41 40 Ag-1 10n 1 10 10 10 5 4 Te-1 29n 16 131 60 162 79 95 1-131 4 65 30 35 22 74 Cs-1 34 1 8 4 10 5 4 Cs-1 37 1 9 4 10 5 4 BaLa-14' 0 3 32 15 25 14 36 Ce-144 7 40 16 54 26 18 59

January 1 - December 31, 2013 Docket Nos. 50-244 APPENDIX D Land Use Survey Summary of Appendix D Content:

Appendix D contains the results of a Land Use Survey conducted around R.E. Ginna Nuclear Power Plant during this operating period. A discussion of the results is included in Section 3.4 of this report.

60

January 1 - December 31, 2013 Docket Nos. 50-244 TABLE OF CONTENTS - LAND USE SURVEY Table Title Page D-1 Land Use Survey Distances ........................................................................................................ 62 61

January I - December 31, 2013 Docket Nos. 50-244 TABLE D-1 Land Use Survey Distances Sector Distance to Distance to Nearest Garden Distance to Milk (Direction Nearest (Latitude N, Longitude W) Producing Animals in Degrees) Residence (Latitude N, Longitude W)

E 610 m E 1170 m Onsite Supplemental Garden N/A (94) (43.27727, 77.30140)

ESE 430 m (111) 1660 m Onsite Garden N/A (43.27627, 77.30389)

ESE 840m N/A 8240 m 119) (43.24196, 77.21978)

SSE 660 m 610 m Onsite Supplemental Garden N/A (145) (43.27278, 77.30413)

S 1500 m N/A N/A SSW 620 m N/A N/A SW 740 m N/A N/A WSW 1470 m N/A N/A W 2420 in N/A N/A The nearest milk producing animals within a 5-mile radius of the power plant are located in the ESE sector at Eaton Farm located at 6747 Salmon Creek Road, Williamson, NY (8,240 meters).

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ML14140A077

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ML14140A077

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