Text

Annual Radioactive Effluent Release Report
	ML12121A593
Person / Time
Site:	Grand Gulf
Issue date:	04/30/2012
From:	Perino C; Entergy Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	GNRO-2012/00035
	Download: ML12121A593 (36)
	v • d • e

,.Entergy

.==:=. Entergy Operations, Inc.

P.O. Box 756 Port Gibson, Mississippi 39150 Tel: 601-437-2800 Christina L. Perino Manager, Licensing GNRO-20 12/00035 April 30, 2012 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

Subject:

Grand Gulf Nuclear Station (GGNS) 2011 Annual Radioactive Effluent Release Report (ARERR)

Grand Gulf Nuclear Station (GGNS), Unit 1 Docket No. 50-416 License No. NPF-29

Dear Sir or Madam:

Attached is the GGNS Annual Radioactive Effluent Release Report (ARERR) for the period January 1, 2011 through December 31, 2011. This report is submitted in accordance with the requirements of 10CFR50.36a(a)(2) and the GGNS Technical Specification (TS) 5.6.3. The ARERR also complies with the GGNS Offsite Dose Calculation Manual (ODCM).

This letter does not contain any commitments.

If you have questions or require additional information concerning this report, please contact Charles Nash at (601) 437-6936 or Christina Perino at (601) 437-6299.

CLP\rrj

Attachment:

2011 Annual Radioactive Effluent Release Report cc: (See Next Page)

GNRO-2012/00035 Page 2 of 2 cc:

NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission ATTN: Mr. Elmo E. Collins, Jr.

Region Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 U. S. Nuclear Regulatory Commission ATTN: Mr. Alan Wang, NRRIDORL Mail Stop OWFN/8 B1 Washington, DC 20555-0001 Mr. B. J. Smith Director, Division of Radiological Health Mississippi State Department of Health Division of Radiological Health 3150 Lawson Street Jackson, MS 39213 Dr. Mary Currier, M.D., M.P.H Mississippi Department of Health P. O. Box 1700 Jackson, MS 39215-1700

Attachment to GNRO-2012/00035 2011 Annual Radioactive Effluent Release Report

ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE EPORT January 1,2011 - December 31,2011

~y Reviewed by Approved by

TABLE OF CONTENTS SUBJECT PAGE I. INTRODUCTION 4 II. DETAILED INFORMATION 5 A. Regulatory Limits 5 I. IOCFR20 Limits 5

a. Fission and Activation Gases 5

b. Radioiodines, Tritium and Particulates 5

c. Liquid Effluents 5

2. 10CFR50, Appendix I, Limits 6

a. Fission and Activation Gases 6

b. Radioiodines, Tritium and Particulates 6

c. Liquid Effluents 6

3. 40CFR190 Limits 7 B. Effluent Concentrations 7 I. Airborne 7

2. Liquid 7 C. Average Energy 7 D. Measurements and Approximations of Total Activity 8 I. For Fission and Activation Gases 8

2. For Particulates and Radioiodines 9

3. For Continuous Releases 9

4. For Batch Releases: Gases 9

5. For Batch Releases: Liquid Effluents 10 E. Batch Releases 10 I. Liquid 10

2. Gaseous 10 F. Abnormal Releases 11 I. Liquid 11

2. Gaseous 11 env-tec/ARERR01 - 2

TABLE OF CONTENTS (CONT'D)

SUBJECT PAGE G. Estimate of Total Error 12 I. Liquid 12

2. Gaseous 12

3. Solid Radioactive Waste 12 H. Solid Radioactive Waste Shipments 13 I. Meteorological Data 13 J. Radioactive Effluent Monitoring Instrumentation Operability 13 K. Annual Sewage Disposal Summary 13 III. RADIATION DOSE

SUMMARY

14 A. Water-Related Exposure Pathway 14 B. Airborne-Related Exposure Pathway 14 IV. OFFSITE DOSE CALCULATION MANUALIRADIOACTIVE WASTE TREATMENT SYSTEM CHANGES 17 A. Offsite Dose Calculation Manual (ODCM) 17 B. Radioactive Waste Treatment Systems 17 LIST OF TABLES PAGE IA Gaseous Effluents - Summation of All Releases 18 IB Gaseous Effluents - Elevated Releases 19 1C Gaseous Effluents - Ground-Level Releases - Continuous 20 1D Radioactive Gaseous Waste Sampling and Analysis Program 21 2A Liquid Effluents - Summation of All Releases 22 2B Liquid Effluents - Continuous and Batch Modes 23 2C Radioactive Liquid Waste Sampling and Analysis Program 24 3 Solid Radioactive Waste and Irradiated Fuel Shipments 25 ATTACHMENTS PAGE Attachment I - Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results 27 env-tec/ARERR01

3

I. INTRODUCTION This Annual Radioactive Effluent Release Report (ARERR) for the period of January I through December 31, 2011, is submitted in accordance with Technical Specifications, Section 5.6.3, of Grand Gulf Nuclear Station (GGNS) License No. NPF-29. The monitoring of radioactive effluents is referenced in Offsite Dose Calculation Manual (ODCM) Appendix A, Sections 6.11 and 6.12.

Airborne discharges at GGNS are considered ground-level releases. All liquid and airborne discharges to the environment were analyzed in accordance with ODCM requirements. All effluent releases were within the concentration and total release limits specified by the ODCM. Projected offsite doses were within the dose limits specified by the ODCM.

The summation of all gaseous releases during the reporting period is reported in Table IA.

Elevated gaseous releases are not applicable at GGNS as reported in Table lB.

The summation of all ground-level gaseous release during the reporting period is reported in Table Ie.

The radioactive gaseous sampling and analysis program implemented at GGNS is described in Table ID.

The summation of all liquid releases during the reporting period is reported in Table 2A.

The continuous and batch mode liquid releases are reported in Table 2B.

The radioactive liquid waste sampling and analysis program implemented at GGNS is described in Table 2C.

Solid radioactive waste and irradiated fuel shipments during the reporting period are summarized in Table 3.

Groundwater Protection Initiative (GPI) well sample tritium results are not included in the AREOR, but are included as Attachment I to the ARERR.

The annual summary of meteorological data Uoint frequency distribution) will be maintained on site. The option to maintain meteorological data on site is in accordance with ODCM Administrative Controls Section 5.6.3. This data shall be provided to the Nuclear Regulatory Commission (NRC) upon request.

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II. DETAILED INFORMAnON A. Regulatory Limits I. IOCFR20 Limits

a. Fission and Activation Gases - The release rate limit at any time for noble gases to areas at or beyond the site boundary shall be such that:

Dtb = average total body dose rate in the current year (mrem/yr)

= X/Q Lj K i Q i ~ 500 mrem/yr Ds = average skin dose rate in the current year (mrem/yr)

= X/Q Lj (L j + 1.1 M i ) Q i ~ 3000 mrem/yr where the terms are defined in the GGNS ODCM.

b. Radioiodines, Tritium and Particulates - The release rate limit for the sampling period for all radioiodines, tritium and radioactive materials in particulate form with half-lives greater than 8 days shall be such that:

Do = average organ dose rate in current year (mrem/yr)

= Li W Pi Q\ ~ 1500 mrem/yr where the terms are defined in the GGNS ODCM.

c. Liquid Effluents - The concentration of radioactive materials released in liquid effluents to unrestricted areas from the site shall not exceed at any time ten times the values specified in 10CFR20, Appendix B, Table 2, Column 2. The concentration of dissolved or entrained noble gases, released in liquid effluents to 4

unrestricted areas from all reactors at the site, shall be limited to 2 x 10-microcuries/ml total activity.

env-tec1ARERR01

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II. DETAILED INFORMATION (CONT'D)

2. IOCFR50, Appendix I Limits

a. Fission and Activation Gases - The dose from noble gases in gaseous effluents to areas at or beyond the site boundary shall be such that:

D y

=air dose due to gamma emissions from noble gases

= 3.17 X 8 10- Li M i XlQ' Qi ::; 5 mrad/qtr

10 mrad/yr D~ = air dose due to beta emissions from noble gases

= 3.17 X 10-8 Li Ni XlQ' Qi ::; 10 mrad/qtr

20 mrad/yr where the terms are defined in the GGNS ODCM.

b. Radioiodines, Tritium and Particulates - The dose to an individual from tritium, 1-131,1-133 and radioactive material in particulate form with half-lives greater than 8 days in gaseous effluents shall be such that:

Dp = dose to an individual from tritium, 1-131, 1-133 and radionuclides in particulate form with half-lives greater than 8 days (mrem)

= 3.17 X 10-8 Li R i W' Qi::; 7.5 mrem/qtr Any Organ

15 mrem/yr Any Organ where the terms are defined in the GGNS ODCM.

c. Liquid Effluents - The dose from radioactive materials in liquid effluents shall be such that:

m DTau =L [A iTau L Lltl C i1 F I ] ::; 1.5 mrem/qtr Total Body

\=\

5 mrem/qtr Any Organ

3 mrem/yr Total Body

10 mrem/yr Any Organ where the terms are defined in the GGNS ODCM.

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II. DETAILED INFORMAnON (CONT'D)

3. 40CFRl90 Limits Doses are calculated for Fission and Activation Gases; Radioiodines and Particulates; and Liquid Effluents according to equations contained in Sections 2.(a), (b), and (c) respectively, with the exception that the limits applied are:

S25 mrem/yr, Total Body or any Organ except Thyroid S75 mrem/yr, Thyroid SIO mrad y/qtr or S20 mrad y/yr, Fission and Activation Gases S20 mrad ~/qtr or S40 mrad ~/yr, Fission and Activation Gases Sl5 mrem/qtr or S30 mrem/yr, any Organ, Iodine and Particulates S3 mrem/qtr or S6 mrem/yr, Total Body, Liquid Effluents SIO mrem/qtr or S20 mrem/yr, any Organ, Liquid Effluents B. Effluent Concentrations

1. Airborne The Effluent Concentration Limit (ECL) of radioactive materials in gaseous effluents is limited by the dose rate restrictions given in Section II.A.l.a. In this case, the ECLs are actually determined by the dose factors in Table 2.1-1 of the GGNS ODCM.

2. Liquid The ECL of radioactive materials in liquid effluents is limited by ten times the values in IOCFR20, Appendix B, Table 2, Column 2. The ECL chosen is the most conservative value of either the soluble or insoluble ECL for each radioisotope.

C. Average Energy Not applicable for GGNS ODCM Appendix A.

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II. DETAILED INFORMATION (CONT'D)

D. Measurements and Approximations of Total Activity The following discussion details the methods used to measure and approximate the total activity for the following:

Fission and Activation Gases Particulates Radioiodines Liquid Effluents Tables ID and 2C give sampling frequencies and Lower Limit of Detection requirements for the analysis of gaseous and liquid effluent streams, respectively.

Values in the attached tables given as zero do not necessarily imply that the radionuclides were not present. A zero indicates that the radionuclide was not present at levels greater than the sensitivity requirements shown in Tables ID and 2C. For some radionuclides, lower detection levels than required may be readily achievable; when a radionuclide is measured below its stated detection limits, it is reported.

1. For Fission and Activation Gases The following noble gases are considered in evaluating gaseous airborne discharges:

Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-138 Periodic grab samples from Station effluent streams are analyzed by gamma spectral analysis utilizing high-resolution germanium detectors. (See Table ID for sampling and analytical requirements.) Isotopic values thus obtained are used for dose release rate calculations due to effluent releases as given in Section II.A.l of this report. Only those radionuclides that are detected are used in this computation. During the period between grab samples, the amount of radioactivity released is based on the effluent monitor readings. Monitors are assigned a calibration factor based upon the last isotopic analysis, using the following relationship:

where Ci = isotopic calibration factor for isotope i Ui = concentration of isotope i in the grab sample in /lCi/ml m = net monitor reading associated with the effluent stream (determined at the time of grab sampling) env-tec1ARERR01 - 8

II. DETAILED INFORMATION (CONT'D)

These calibration factors, along with the hourly effluent monitor values and flow rates, are entered into the laboratory computer where the release rates for individual radionuclides are calculated and stored. If no activity is detected in the grab sample, the calibration factor defaults to a historical mixture of Kr-88, Xe-133, Xe-135m, Xe-135, and Xe-138.

2. For Particulates and Radioiodines The radioiodines and radioactive materials in particulate form to be considered are:

Zn-65 Mo-99 Mn-54 Cs-134 Fe-59 Cs-137 Co-58 Ce-141 Co-60 Ce-l44 5r-89 1-131 5r-90 1-133 Other radionuclides with half lives greater than 8 days.

3. For Continuous Releases Continuous sampling is performed on the continuous release points when releasing (i.e.:

Offgas/Radwaste Building, Containment Building, Fuel Handling Area, Turbine Building, and Turbine Building Occasional Release Point). Particulate material is collected by filtration. Radio-iodines are collected by adsorption onto a charcoal filter. Periodically these filters are removed and analyzed by gamma spectral analysis utilizing high-resolution germanium detectors to identify and quantify radioactive materials collected.

Particulate filters are then analyzed for gross alpha and Strontium-89/90 as required.

Gross alpha is analyzed using a gas flow proportional technique. Strontium-89/90 values are obtained by chemical separation and subsequent counting analysis using gas flow proportional techniques. Tritium concentrations are determined using distillation and liquid scintillation techniques. During major operational occurrences, the frequency of sampling is increased to satisfy the requirements of footnote "c" of Table ID, "Radioactive Gaseous Waste Sampling and Analysis," (GGNS ODCM Appendix A, Table 6.11.4-1). Strontium analysis is performed by a qualified contract laboratory.

Carbon-14(C-14) activity of 9.5 Curies released per year in gaseous form is obtained directly from the GGNS Final Safety Analysis Report Table 11.3-9. C-14 curies are reported in Tables 1A and IC of this report and based on a constant release rate throughout the year.

4. For Batch Releases: Gases Gaseous batch releases are not normally performed at GGNS.

env-tec/ARERR01 - 9

II. DETAILED INFORMAnON (CONT'DI

5. For Batch Releases: Liquid Effluents The radionuclides listed below are considered when evaluating liquid effluents:

H-3 Sr-90 Mn-54 Mo-99 Fe-55 1-131 Co-58 Cs-134 Co-60 Cs-137 Fe-59 Ce-14l Zn-65 Ce-144 Sr-89 Representative pre-release grab samples are obtained and analyzed as required by Table 2C. Isotopic analyses are performed by gamma spectral analysis utilizing high-resolution germanium detectors. Aliquots of each pre-released sample, proportional to the waste volume released, are composited in accordance with the requirements of Table 2C.

Strontium-89/90 and Iron-55 values are obtained by individual chemical separations.

Strontium-89/90 is analyzed using gas flow proportional techniques. Iron-55 is analyzed using liquid scintillation techniques. Gross alpha is analyzed using a gas flow proportional technique. Tritium is distilled and then analyzed using liquid scintillation techniques. Dissolved gases are determined employing grab sampling techniques and analyzed by gamma spectral analysis utilizing high-resolution germanium detectors. Iron and Strontium analyses are performed by a qualified contract laboratory.

E. Batch Releases

1. Liquid 2nd Qtr 3rd Qtr 4th tr Year 28 48 30 107 Time Period (in minutes)

b. Total for all batches 3.05E+02 7.55E+03 1.44E+04 8.90E+03 3.12E+04

c. Max time for a batch 3.05E+02 3.25E+02 3.20E+02 3.15E+02 3.25E+02

d. Avg time for a batch 3.05E+02 2.70E+02 3.00E+02 2.97E+02 2.91E+02

e. Min time for a batch 3.05E+02 O.OOE+OO 2.55E+02 1.95E+02 O.OOE+OO

2. Gaseous No batch releases occurred during the report period.

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II. DETAILED INFORMAnON (CONT'D)

F. Abnormal Releases I. Liquid

a. Number of Releases: o

b. Total Activity Released: O.OOE+OOCi No abnormal liquid releases were identified for this reporting period.

2. Gaseous

a. Number of Releases: 5

b. Total Activity Released: 2.91E+00 Ci Five abnormal gaseous releases were identified during the reporting period. The releases were due to lack of negative pressure in the Turbine Building under certain operating conditions. The releases occurred August 19, August 20, August 26, and October 12, 2011, for a total release duration of 19.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />. Engineering determined the release flow rate during these periods was a maximum of 6,000 cfm. The turbine building exhaust stack sample results associated with these periods were used with annual average dispersion and deposition factors to determine the release rate and associated dose. The curies and doses are included in the Airborne Effluent Dose table in section I1LB and in Table 1A and in Table IC of this report.

env*feclARERR01- 11

II. DETAILED INFORMATION (CONT'D)

G. Estimate of Total Error I. Liquid The maximum errors are collectively estimated to be as follows:

Fission &

Activation Tritium Dissolved & Entrained Gross Products Gases AI ha Sampling % 2.60E+OI 2.60E+OI 2.60E+OI 2.60E+OI Measurement % 6.80E+OI 6.50E+OI 6.IOE+OI 9.20E+OI TOTAL % 7.30E+Ol 7.00E+OI 6.60E+01 9.50E+OI Sampling errors include uncertainty associated with mixing, representative sampling and discharge volume. Measurement errors include uncertainty associated with instrument calibration and the preparation and counting of low-activity samples. Counting errors are based on measurements of blank samples. For germanium detectors, the least-readily-detectable radioisotope is used to determine the counting error. Calibration errors are calculated by summing the errors associated with the calibration of a particular instrument with a radioactive source.

The total error is calculated by taking the square root of the sum of the squares of the individual errors.

2. Gaseous The maximum errors (not including sample line loss) are collectively estimated to be as follows:

Fission & Activation Gross Products Iodine Particulate Al ha Tritium 3.20E+Ol 2.30E+Ol 2.20E+Ol 2.20E+Ol 2.30E+Ol 6.IOE+Ol 6.70E+Ol 6.50E+Ol I.OIE+02 6.20E+Ol 6.90E+Ol 7.IOE+0l 6.90E+Ol 1.03E+02 6.60E+Ol Sampling errors include uncertainty associated with sample flow, vent flow and monitor calibration.

Measurement and total errors are calculated by the same methods used for liquid effluents.

3. Solid Radioactive Waste Estimated Total Error % for all waste types is +/-2.50E+O 1. Sampling errors include uncertainty associated with mixing and representative sampling.

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II. DETAILED INFORMAnON (CONT'D)

H. Solid Radioactive Waste Shipments See Table 3 for shipment information.

I. Meteorological Data The data recovery for the reporting period was 98.9%. The predominant wind direction was from the South approximately 9.1 % of the time. The predominant stability class was class "D" approximately 26.9% of the time. Average wind speed during the reporting period was approximately 4.5 miles per hour.

The annual meteorological data (Hourly Average Data or Joint Frequency Distribution) will be maintained on site in a file that shall be provided to the NRC upon request.

J. Radioactive Effluent Monitoring Instrumentation Operability No instances of reportable inoperability were identified for this reporting period.

K. Annual Sewage Disposal Summary There were no sewage disposals in 2011.

env-tec!ARERR01- 13

III. RADIATION DOSE

SUMMARY

Indicated below is the annual summary of offsite doses attributable to GGNS during 2011. Inspection of the values indicates that GGNS releases were within the IOCFR50, Appendix I, design objectives.

Since there are no other fuel cycle facilities within 8 km of GGNS, 40CFR 190 limits were also met during this period.

A. Water-Related Exposure Pathways The values calculated in this section utilize the information provided in Tables 2A and 2B of this report and the calculation methodology of the ODCM.

Liquid Effluents Total body dose and critical organ doses are computed for the maximum exposed individual.

The maximum dose contribution from liquid effluents is considered to occur in the adult age group via consumption of fish.

2011 L'lqUl'd Effl uent Dose mrem 1st Otr 2nd Qtr 3rd Qtr 4th Qtr TOTAL Bone O.OOe+OO 7.15e-03 1.65e-02 8.14e-03 3.18e-2 Liver 3.63e-05 1.15e-02 2.60e-02 2.1ge-02 6.lOe-2 Thyroid 3.54e-05 1.20e-03 1.70e-03 1.13e-03 4.05e-3 Kidney 3.54e-05 5.22e-03 1.04e-02 1.08e-02 2.73e-2 Lung 3.54e-05 2.66e-03 4.2Ie-03 1.96e-03 8.7Ie-3 GI-LLI 5.20e-05 5.57e-03 7.25e-03 2.44e-02 4.04e-2 Whole Body 3.74e-05 6.64e-03 1.70e-02 1.22e-02 3.66e-2 B. Airborne-Related Exposure Pathways The values presented in this section utilize information provided in Tables 1A and 1C of this report and the calculation methodology of the ODCM. Carbon-14 doses were calculated using Electric Power Research Institute, EPRI, methodology and calculation software which was val idated on site using Regulatory Guide 1.109. Dose and dose rates are computed for locations at the site boundary or at unrestricted areas within the site boundary. Because members of the public may, on occasion, be found within the site boundary, two fishing lakes, the recreational vehicle laydown area, and the GGNS Energy Services Center locations were also evaluated.

Consideration of site boundary locations as well as unrestricted areas within and beyond the site boundary provides assurance that offsite doses will not be substantially underestimated while attempting to provide an accurate dose calculation.

Doses for a Member of the Public are computed based on 2011 meteorological data and on the most recent land use census, with the most limiting location used.

During normal operations, the dispersion and deposition factors used for dose calculations are from five-year historical annual average meteorological data.

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III. RADIATION DOSE

SUMMARY

(CONT'D)

Organ Dose The maximum organ dose to a MEMBER OF THE PUBLIC (critical receptor) from radioiodines, tritium, and particulates was calculated for this report using the most recent land use census and dispersion and deposition parameters from 2011 meteorological data. The critical receptor residence was determined to be located in the southwest sector at a distance of 1432 meters (0.89 miles) from the plant. Pathways considered for use in the organ dose calculations are inhalation, ground plane, grass/cow/meat, and vegetation. There is no grass/cow/milk pathway within five miles of GGNS. It was assumed that the age group receiving the maximum dose lived at the residence and that the receptor consumed food products that were raised or produced at the residence. This dose is documented in the following table as two separate entries. The first organ dose entry excludes C-14 while the second entry includes organ dose from tritium, radioiodines, particulates, and C-14.

Average Total Body and Skin Dose Rate Individual total body and skin dose rates from exposure to a semi-infinite cloud of noble gas are computed for a location in the southwest sector at a distance of 1368 meters (0.85 miles) from the plant. This location corresponds to the highest annual average atmospheric dispersion factor for a location at or within the site boundary based on 2011 meteorological data.

The total body and skin dose rates reported are the quarterly average of the maximum instantaneous dose rates determined daily during the reporting period and represent the maximum possible dose rate received by members of the public.

Air Dose from Gamma and Beta Emissions Air doses from gaseous effluents were calculated for this report using dispersion parameters from the 2011 meteorological data. The highest dispersion factor for an unrestricted area was in the southwest sector at the site boundary, 1368 meters (0.85 miles) from the plant.

Direct Radiation Direct radiation dose is calculated by subtracting average doses measured by thermo luminescent dosimeter (TLD) badges located at control locations from average doses measured by TLD badges located near the site boundary. GGNS reported measured doses in 2011 as net exposure normalized to 92 days.

env-tec/ARERR01* 15

III. RADIAnON DOSE

SUMMARY

(CONT'D)

Carbon-14 C-14 is a naturally occurring isotope of carbon. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing. In recent years, the analytical methods for determining C-14 have improved. Coincidentally the radioactive effluents from commercial nuclear power plants have also decreased to the point that C-14 has emerged as a principal radionuclide in gaseous effluents.

The only significant dose pathway to a member of the public from C-14 release is through consumption of vegetation. Vegetation incorporates C-14 in form of carbon dioxide (C0 2) during photosynthesis so doses are calculated based on the CO 2 fraction of the carbon released in gaseous form. A CO 2 fraction of 95% is used based on EPRI Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents". The highest atmospheric dispersion factors for an actual garden based on land use census are used to determine dose from C-14 because CO2 is dispersed as a gas to the garden location where it is then incorporated into plant material.

C-14 dose is calculated for maximum organ dose to a MEMBER OF THE PUBLIC assuming all age groups utilize that garden location. This doses is then added to dose for the same organ from tritium, iodine, and particulates. This organ dose is recorded and compared to the limit in the following table.

env-tec/ARERR01 - 16

III. RADIAnON DOSE

SUMMARY

(CONT'D) 201HI A DQ$¢lmrpm\' .'

1st Qtr 2nd Qtr 3rd Qtr 4th Qtr TOTAL Iodine, Tritium & Particulates (excluding Carbon-14)

Child (mrem) 6.94E-03 5.20E-03 4.83E-03 5.25E-03 2.22E-02 Organ Thyroid Thyroid Thvroid GILLI Thvroid Applicable Limit 7.5 7.5 7.5 7.5 15 Percent of Limit 9.26E-02 6.94E-02 6.45E"02 7.00E-02 1.48E*OI Iodine, Tritium & Particulates (including Carbon-14)

Child Bone (mrem) I.2lE+OO 1.22E+OO l.23E+OO L23E+OO 4. 89E+OO Applicable Limit 7.5 7.5 7.5 7.5 IS Percent of Limit 1.6IE+OI 1.63E+OI 1.64E+Ol 1.64E+O I 3.26E+OJ Total Body Dose Rate (mrem/yr) 1.27E-OI 3.IIE-01 3.33E-OI 6.40E-OI Applicable Limit 500 500 500 500 Percent of Limit 2.54E-02 6.22E-02 6.66E-02 1.28E-OI Skin Dose Rate (rnrem/yr) 2.4SE-Ol 7.39E-01 6.83E-01 I. 22E+00 Applicable Limit 3000 3000 3000 3000 Percent of Limit 8.17E-03 2.46E-02 2.28E-02 4.07E-02 Gamma Air Dose* 2.80E-02 6.33E-02 8.40E-02 1.34E-01 3.09E-01 Applicable Limit 5 5 5 5 to Percent of Limit 5.60E-OI 1.27E+00 1.68E+OO 2.68E+OO 3.09E+OO Beta Air Dose* 2.46E-02 8.41 E-02 8.14E-02 l.ISE-OI 3.05E-Ol Applicable Limit 10 10 10 to 20 Percent of Limit 2.46E-Ol 8AIE-OJ 8.14E-OI 1.15E+00 1.53E+OO Direct Radiation (mrem) 0.3 0.0 0.2 0.0 0.5

.-,-Measurement umts are mrad IV. OFFSITE DOSE CALCULATION MANUAL/

RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES A. affsite Dose Calculation Manual (aDCM)

No revisions to the aDCM were issued during the reporting period.

B. Radioactive Waste Treatment Systems No major changes were made to the liquid or gaseous radwaste treatment systems during this reporting period.

env-tec/ARERR01 - 17

TABLEIA ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 2011 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases

1. Total Release Ci 3.S4E+01 1.30E+02 1.18E+02 1.63E+02 4.46E+02

2. Avg. Release Rate uCi/sec 4.SSE+00 1.66E+01 1.48E+01 2.0SE+01 1.42E+01

3. Percent of TS Limit % S.60E-01 1.27E+00 1. 68E+00 2.68E+00 3.09E+00 Iodine-131

1. Total Release Ci 3.S6E-OS 1. 7SE-OS 2.43E-OS 3.00E-OS 1. 07E-04

2. Avg. Release Rate uCi/sec 4.S8E-06 2.22E-06 3.06E-06 3.78E-06 3.41E-06

3. Percent of TS Limit % 6.0SE-03 2.97E-03 4.14E-03 S.11E-03 9.13E-03 Particulates Half Life >= 8 days

1. Total Release ci 1. 33E-OS 4.SSE-06 2.84E-OS 4.30E-OS 8.92E-OS

2. Avg. Release Rate uCi/sec 1. 71E-06 S.79E-07 3.S7E-06 S.41E-06 2.83E-06

3. Percent of TS Limit % 1. 08E-02 7.14E-04 1. 83E-03 1.4SE-03 6.16E-03 Tritium

1. Total Release ci 8.9SE+00 6.90E+00 6.23E+00 6.S8E+00 2.87E+01

2. Avg. Release Rate uCi/sec 1.1SE+00 8.78E-01 7.84E-01 8.28E-01 9.09E-01

3. Percent of TS Limit % 8.S2E-02 6.S7E-02 S.94E-02 6.27E-02 1.37E-01 Carbon 14

1. Total Release Ci 2.34E+00 2.37E+00 2.39E+00 2.39E+00 9. So...**nn

2. Avg. Release Rate uCi/sec 3.01E-01 3.01E-01 3.01E-01 3.01E-01 3.01E-01 Gross Alpha

1. Total Release Ci 2.37E-08 2.08E-08 O.OOE+OO 7.70E-08 1.21E-07

2. Avg. Release Rate uCi/sec 3.04E-09 2.6SE-09 O.OOE+OO 9.68E-09 3.8SE-09 env*tec/ARERR01 - 18

TABLEIB ENTERGY OPERAnONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - ELEVATED RELEASES JANUARY - DECEMBER 2011 (Not Applicable - GGNS Releases Are Considered Ground-Level) env-tec1ARERR01 - 19

TABLEIC ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - GROUND-LEVEL RELEASE-CONTINUOUS REPORT FOR 2011 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases AR-4l ci S.lSE+OO 1. 71E+Ol 1.37E+Ol 3.44E+00 3.94E+Ol KR-8SM ci 2.l0E+00 6.l2E+00 1.S7E+Ol 1.96E+Ol 4.3SE+Ol KR-87 Ci 1.20E-Ol 6.33E-02 O.OOE+OO 2.S1E+00 2.69E+00 KR-88 Ci 1.00E-Ol 1.14E+00 8.30E+00 1.98E+Ol 2.94E+Ol KR-89 Ci O.OOE+OO 2.80E-Ol O.OOE+OO O.OOE+OO 2.80E-Ol XE-133 Ci 2.40E+00 3.l2E+Ol 1. 7SE+Ol 1.48E+Ol 6.S9E+Ol XE-13S ci 3.l4E+00 2.64E+Ol 3.02E+00 3.64E+00 3.62E+Ol XE-13SM ci 3.81E+00 7.08E+00 9.26E+00 1.90E+Ol 3.91E+Ol XE-137 ci 6.l2E+00 2.72E+Ol 2.49E+Ol 3.l9E+Ol 9.01E+Ol XE-138 Ci 1.2SE+Ol 1.39E+Ol 2.SSE+Ol 4.81E+Ol 1.00E+02 Totals for Period *** Ci 3.S4E+Ol 1.30E+02 1.18E+02 1.63E+02 4.46E+02 Iodines I-13l Ci 3.S6E-OS 1. 7SE-OS 2.43E-OS 3.00E-OS 1.07E-04 I-133 Ci 1.61E-04 7.88E-OS 1.20E-04 1.62E-04 S.22E-04 I-13S ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Totals for Period *** ci 1.97E-04 9.63E-OS 1.4SE-04 1.92E-04 6.29E-04 Particulates Half Life >= 8 days BA-140 ci O.OOE+OO 7.67E-07 7.l2E-06 3.41E-OS 4.20E-OS CO-S8 ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CO-60 Ci O.OOE+OO O.OOE+OO 8.00E-06 3.S2E-07 8.36E-06 CR-Sl Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CS-137 ci O.OOE+OO O.OOE+OO S.38E-07 O.OOE+OO S.38E-07 MN-S4 Ci O.OOE+OO O.OOE+OO 7.84E-07 O.OOE+OO 7.84E-07 RU-106 Ci O.OOE+OO O.OOE+OO 8.l2E-06 3.71E-06 1.l8E-OS SR-89 ci 1.OSE-OS 3.79E-06 3.78E-06 4.83E-06 2.29E-OS SR-90 Ci 2.79E-06 O.OOE+OO O.OOE+OO O.OOE+OO 2.79E-06 ZN-6S Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Totals for Period *** Ci 1. 33E-OS 4.SSE-06 2.84E-OS 4.30E-OS 8.92E-OS Other H-3 ci 8.9SE+00 6.90E+00 6.23E+00 6.S8E+00 2.87E+Ol C-14 Ci 2.34E+00 2.37E+00 2.39E+00 2.39E+00 9.S0E+00 Gross Alpha ci 2.37E-08 2.08E-08 O.OOE+OO 7.70E-08 1.21E-07 env-tBc/ARERR01 - 20

TABLEID ENTERGY OPERAnONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radioactive Gaseous Waste Sampling and Analysis Program JANUARY - DECEMBER 2011 Lower Limit Sampling Minimum Analysis Type of Activity Analysis of Detection Gaseous Release Type Frequency Frequency (LLD)

( uCilml)a A. (I) Radwaste Building 31 Days 31 Days Principal Gamma Emitters Ventilation Exhaust Grab Sample (f) ili&) IxlO- 4 H-3 IXIO- 6 (2) Fuel Handling Area Continuous (d)(f) 7 Days (c) 1-131 IxIO- L Ventilation Exhaust Charcoal Sample 1-133 Ix 10- 10 (3) Containment Continuous (d)(f) 7 Days (c) Principal Gamma Emitters lxlO-Ventilation Exhaust Particulate Samole (e) (1-131, Others)

(4A) Turbine Building Continuous (d)(f) 31 Days Composite Gross Alpha IxlO-Ventilation Exhaust Particulate Sample (4B) Turbine Building Occasional Continuous (d)(f) 92 Days Composite Sr-89, Sr-90 IxlO-Release Point(g) Particulate Sample (when in service)

Continuous (f) Noble Gas Monitor Noble Gases Gross Beta or IxlO- o Gamma B. (I) Offgas Post 31 Days Grab 31 Days Principal Gamma Emitters IxlQ-4 Treatment Exhaust, Sample (f) (e) whenever there is now (2) Standby Gas 31 Days Grab 31 Days Principal Gamma IxlQ-4 Treatment A Sample (f) Emitters(e)

Exhaust.

whenever there is now (3) Standby Gas 31 Days Grab 31 Days Principal Gamma IxlQ-4 Treatment B Sample (I) Emitters(e)

Exhaust, whenever there is now NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.4-1.

env-tecIAR£RR01 - 21

TABLE2A ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT I RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 2011 units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products

1. Total Release Ci 8.62E-06 1. 08E-02 4.15E-03 1.16E-02 2.66E-02

2. Avg. Diluted Cone. uci/ml 1.36E-09 5.69E-08 1.04E-08 3.90E-08 2.98E-08

3. Percent of Limit % 2.49E-03 4.43E-01 1.13E+00 8.12E-01 1.22E+00 Tritium

1. Total Release ci 3.91E-01 1.57E+01 2.46E+01 1.82E+01 5.89E+01

2. Avg. Diluted Cone. uCi/ml 6.17E-05 8.23E-05 6.17E-05 6.11E-05 6.59E-05

3. Percent of Limit % 6.17E-01 8.23E-01 6.17E-01 6.11E-01 6.59E-01 Dissolved and Entrained Gases

1. Total Release Ci 4.10E-05 3.92E-04 1. 74E-03 5.16E-04 2.69E-03

2. Avg. Diluted Cone. uCi/ml 6.47E-09 2.05E-09 4.36E-09 1. 73E-09 3.01E-09

3. Percent of Limit % 3.24E-03 1.03E-03 2.18E-03 8.65E-04 1.15E-03 Gross Alpha Radioactivity

1. Total Release Ci O.OOE+OO 2.19E-05 O.OOE+OO O.OOE+OO 2.19E-05 Volume of liquid waste liters 1.06E+05 2.64E+06 4.88E+06 3.04E+06 1.07E+07 Volume of dil. water liters 6.23E+06 1.88E+08 3.94E+08 2.95E+08 8.84E+08 env-tec/ARERR01 - 22

TABLE 2B ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - CONTINUOUS AND BATCH MODES REPORT FOR 2011 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products AG-110M ci O.OOE+OO O.OOE+OO O.OOE+OO 3.14E-04 3.14E-04 AS-76 ci O.OOE+OO O.OOE+OO 6.19E-OS O.OOE+OO 6.19E-OS CE-141 Ci O.OOE+OO O.OOE+OO 4.09E-06 3.46E-06 7.SSE-06 CO-58 Ci O.OOE+OO O.OOE+OO 6.44E-OS 1.02E-04 1.66E-04 CO-60 Ci 8.62E-06 S.01E-04 6.22E-04 S.69E-03 6.82E-03 CR-S1 ci O.OOE+OO O.OOE+OO 1.02E-03 6.42E-04 1.66E-03 CS-134 ci O.OOE+OO O.OOE+OO O.OOE+OO 1. 09E-OS 1.09E-OS CS-137 ci O.OOE+OO 3.02E-OS 1.39E-04 4.60E-OS 2.1SE-04 CU-64 ci O.OOE+OO 1.88E-OS O.OOE+OO O.OOE+OO 1.88E-OS FE-55 Ci O.OOE+OO 1.00E-02 O.OOE+OO O.OOE+OO 1.00E-02 FE-59 Ci O.OOE+OO O.OOE+OO 3.71E-04 2.S6E-04 6.28E-04 I-131 Ci O.OOE+OO O.OOE+OO O.OOE+OO S.90E-06 S.90E-06 MN-S4 ci O.OOE+OO 1.16E-04 3.82E-04 2.99E-03 3.48E-03 NA-24 ci O.OOE+OO 2.70E-OS 3.94E-04 8.23E-OS S.03E-04 RB-88 ci O.OOE+OO O.OOE+OO 6.9SE-04 8.96E-04 1.S9E-03 RU-106 Ci O.OOE+OO O.OOE+OO 6.42E-OS O.OOE+OO 6.42E-OS SB-124 Ci O.OOE+OO O.OOE+OO 1.13E-04 2.12E-OS 1.34E-04 SB-12S ci O.OOE+OO O.OOE+OO 1.46E-OS O.OOE+OO 1.46E-OS SN-117M ci O.OOE+OO O.OOE+OO 1.07E-OS O.OOE+OO 1.07E-OS SR-92 Ci O.OOE+OO O.OOE+OO O.OOE+OO 6.00E-OS 6.00E-OS TC-99M ci O.OOE+OO 1.30E-06 8.73E-OS S.40E-06 9.40E-OS W-187 Ci O.OOE+OO O.OOE+OO 1. 74E-OS O.OOE+OO 1.74E-OS ZN-6S Ci O.OOE+OO 1. 30E-04 8.6SE-OS S.00E-04 7.17E-04 Totals for Period *** Ci 8.62E-06 1. 08E-02 4.1SE-03 1.16E-02 2.66E-02 Tritium H-3 ci 3.91E-01 1.S7E+01 2.46E+01 1.82E+01 S.89E+01 Totals for Period *** ci 3.91E-01 1.S7E+01 2.46E+01 1.82E+01 S.89E+01 Dissolved and Entrained Gases KR-8SM ci O.OOE+OO O.OOE+OO 7.77E-06 O.OOE+OO 7.77E-06 XE-133 Ci 1.70E-OS 2.66E-04 1.1SE-03 4.S7E-04 1.89E-03 XE-13S ci 2.40E-OS 1.26E-04 S.83E-04 S.83E-OS 7.91E-04 Totals for Period *** Ci 4.10E-OS 3.92E-04 1. 74E-03 S.16E-04 2.69E-03 Gross Alpha Radioactivity ALPHA ci O.OOE+OO 2.19E-OS O.OOE+OO O.OOE+OO 2.19E-OS Totals for Period *** ci O.OOE+OO 2.19E-OS O.OOE+OO O.OOE+OO 2.19E-OS env-tec/ARERR01 - 23

TABLE2C ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM JANUARY - DECEMBER 2011 Lower Limit Sampling Minimum Analysis Type of Activity Analysis of Detection Liquid Release Type Frequency Frequency (LLD)

( uCilml)(a)

A. Batch Waste Release Prior to Release Prior to Release Each Principal Gamma Emitters Tanks (c) Each Batch Batch @ 5xlO- 7 1-131 IXIO- 6 Prior to Release 31 Days Dissolved and Entrained IxlO-)

One Batch 1M Gases (Gamma Emitters)

Prior to Release 31 Days H-3 IxlO' Each Batch Composite (b) Gross Alpha Ix 10-7 Prior to Release 92 Days Composite Sr-89. Sr-90 5xlO- x Each Batch (b) Fe-55 Ix 10-6 B. SSW Basin (Before Prior to Release Prior to Release Each Principal Gamma Emitters Blowdown) Each Blowdown Batch @ 5xlO- 7 1-131 Ix 10-6 NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.1-1.

env-tec/ARERR01 - 24

TABLE 3 ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY - DECEMBER 2011 A SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

Est. Total I. Type of Waste Unit Class A Class B Class C Error %

a. Spent resins, filter sludges, m3 7.65E+OI 5.52E+00 O.OOE+OO

+/- 25%

evaporator bottoms, etc. Ci 2.54E+02 1.86E+03 O.OOE+OO

b. Dry compressible waste, m3 4.26E+02 O.OOE+OO O.OOE+OO

+/- 25%

contaminated equipment, etc. Ci 1.22E+00 O.OOE+OO O.OOE+OO

c. Irradiated components, m3 O.OOE+OO O.OOE+OO O.OOE+OO

+/- 25%

control rods, etc. Ci O.OOE+OO O.OOE+OO O.OOE+OO

d. Other: Condensate Pre-Coat Septa m3 5.64E+00 O.OOE+OO O.OOE+OO

+/- 25%

Bundle Ci 1.13E+OI O.OOE+OO O.OOE+OO

2. Estimate of Major Nuclide Composition ( by type of waste)

a. Spent resins, filter sludges, evaporator bottoms, etc.

None

b. Dry compressible waste, contaminated equipment, etc.

None

c. Irradiated components, control rods, etc.

None

d. Other: Condensate Pre-Coat Septa Bundle Isotope (greater than 0.1 %) Percent Curies Ni-63 0.390 8.27E+OO Co-60 9.497 2.02E+02 Cr-51 0.660 1.40E+OI Cs-137 0.132 2.80E+OO Fe-55 75.113 1.59E+03 Fe-59 0.843 1.79E+OI Mn-54 10.085 2.14E+02 Co-58 0.396 8.40E+00 Zn-65 2.832 6.0IE+OI env-tec/ARERR01 - 25

TABLE 3 ENTERGY OPERAnONS, INC.

GRAND GULF NUCLEAR STAnON UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY - DECEMBER 2011 (Cont)

3. Solid Waste Disposition Number of Mode of Destination Name City State Shipments Transportation 10 EnergySolutions(Duratek), LLC Oak Ridge TN Hittman EnergySolutions - Bulk Waste Disposal Hittman I Clive UT Facility 14 Studsvik Erwin TN Hittman r NRC Class B

A Disposal Volume(ftI\3) 120.3 202 Description 8/120 HIC ES-210 Number of Containers 2

Waste Type Description Poly HIC - RWCU-A 3 Carbon Steel Liner - SRT A 1180 20' SEALAND 16 20FT Sealand ES-210 Stainless Steel Liner A 199.4 12 (solidification) CPSIRWCU-B B. Irradiated Fuel Shipments (Disposition)

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION None N/A N/A env-tec/ARERR01 - 26

ATTACHMENT I GPI Sample Results JANUARY - DECEMBER 2011 GPI Ground Water samples are collected from onsite dewatering wells, DW; monitoring wells, MW; observation wells, OW; and sump wells, SW. Samples were analyzed for tritium and selected samples were analyzed for gamma and/or hard to detect (HTD) isotopes (Gross Alpha, Iron-55, Nickel-63, Strontium-89 and Strontium-90. Analyses are to the Lower Level of Detection (LLD) values for the GGNS Radiological Environmental Monitoring Program.

No dose to the public is attributed to ground water since wells with results above MDA are bounded by wells which are <MDA. Tritium, gamma and HTD results are shown in the table below.

MW -I 05B indicated one positive result near the detection level of 15 pCiIL for Manganese-54 (Mn-54) and Cobalt-60 (Co-60). All previous and subsequent samples for MW-I 05B measured <MDA for gamma emitting and hard to detect isotopes. All results were less than Reporting Levels of GGNS-ODCM table 6.12.1-2.