ML13121A244

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Grand Gulf, 2012 Annual Radioactive Effluent Release Report
ML13121A244
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 04/30/2013
From: Robinson C R
Entergy Operations
To:
Office of Nuclear Reactor Regulation, Document Control Desk
Shared Package
ML131210290 List:
References
GNRO-2013/00033
Download: ML13121A244 (35)
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Text

GNRO-2013/00033 April 30, 2013 U.S.Nuclear Regulatory Commission Attention:

Document Control Desk Washington, DC 20555-0001 Entergy Operations, Inc.P.o.Box 756 Port Gibson, Mississippi 39150 Tel: 601-437-7326 Christopher R.Robinson Licensing Manager Grand Gulf Nuclear Station

SUBJECT:

Grand Gulf Nuclear Station 2012 Annual Radioactive Effluent Release Report per 10 CFR 50.36a(a)(2)

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

Dear Sir or Madam:

Attached is the Grand Gulf Nuclear Station (GGNS)Annual Radioactive Effluent Release Report (ARERR)for the period January 1, 2012 through December 31,2012.This report is submitted in accordance with requirements of 10 CFR 50.36a(a)(2) and GGNS Technical Specification (TS)5.6.3.The ARERR also complies with the GGNS Offsite Dose Calculation Manual (ODCM).Revisions 38 and 39 of the GGNS Offsite Dose Calculation Manual were approved in 2012.A complete copy of the current ODCM is enclosed.There are no commitments contained in this submittal.

If you have any questions or need additional information, please contact Tommy Tankersley at 601-437-6936.CRRlcjj Attachment 1: 2012 Annual Radioactive Effluent Release Report Attachment 2: GGNS Offsite Dose Calculation Manual, Revision 39 cc: (See Next Page)

GNRO-2013/00033 Page 2 of 2 cc: NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 u.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 u.S.Nuclear Regulatory Commission ATTN: Mr.Alan Wang, NRR/DORL (w/2)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-2013/00033 2012 Annual Radioactive Effluent Release Report ENTERGY OPERATIONS, INC.GRAND GULF NUCLEAR STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1,2012-December 31,2012fA/JP L Prepared By env-tec/ARERR01

-1 TABLE OF CONTENTS , SUBJECT PAGE I.INTRODUCTION 4 II.DETAILED INFORMATION 5 A.Regulatory Limits 5 1.10CFR20 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 1.Airborne 7 2.Liquid 7 C.Average Energy 7 D.Measurements and Approximations of Total Activity 8 1.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 1.Liquid 10 2.Gaseous 10 F.Abnormal Releases 11 1.Liquid 11 2.Gaseous 11 env-tec1ARERR01

-2 TABLE OF CONTENTS (CONT'D)SUBJECT G.Estimate of Total Error 1.Liquid 2.Gaseous 3.Solid Radioactive Waste H.Solid Radioactive Waste Shipments I.Meteorological Data J.Radioactive Effluent Monitoring Instrumentation Operability K.Annual Sewage Disposal Summary III.RADIATION DOSE

SUMMARY

A.Water-Related Exposure Pathway B.Airborne-Related Exposure Pathway IV.OFFSITE DOSE CALCULATION MANUAL/RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES A.Offsite Dose Calculation Manual (ODCM)B.Radioactive Waste Treatment Systems LIST OF TABLES PAGE 11 11 12 12 12 12 12 12 13 13 13 16 16 16 PAGE lA IB lC ID 2A 2B 2C 3 Gaseous Effluents-Summation of All Releases Gaseous Effluents-Elevated Releases Gaseous Effluents-Ground-Level Releases-Continuous Radioactive Gaseous Waste Sampling and Analysis Program Liquid Effluents-Summation of All Releases Liquid Effluents-Continuous and Batch Modes Radioactive Liquid Waste Sampling and Analysis Program Solid Radioactive Waste and Irradiated Fuel Shipments ATTACHMENTS AttachmentI-Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results Attachment II-Offsite Dose Calculation Manual 17 18 19 20 21 22 23 24 PAGE 26 31 env-iec1ARERR01

-3 I.INTRODUCTION This Annual Radioactive Effluent Release Report (ARERR)for the period of January 1 through December 31,2012, 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 known gaseous releases during the reporting period is reported in Table 1A.Elevated gaseous releases are not applicable at GGNS as reported in Table 1 B.The summation of all known ground-level gaseous release during the reporting period is reported in Table 1C.The radioactive gaseous sampling and analysis program implemented at GGNS is described in Table 1D.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 which are not included in the AREOR are included as Attachment I to the ARERR.The current revision of the Offsite Dose Calsulation Manual is included as Attachment II to the ARERR.The arulual summary of meteorological data Goint 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.env-tec/ARERR01-4 II.DETAILED INFORMATION A.Regulatory Limits 1.10CFR20 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: D tb=average total body dose rate in the current year (mrem/yr),=XlQ K i Q i:s;;500 mrem/yr D s=average skin dose rate in the current year (mrem/yr),=XlQ (L i+1.1 M i)Q i:s;;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)=L'W p.Q"<1500 mrem/yr 1 1 1_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 unrestricted areas from all reactors at the site, shall be limited to2x 10-4 microcuries/ml total activity.env-tec1ARERR01

-5 II.DETAILED INFORMATION (CONT'D)2.10CFR50, 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=air dose due to gamma emissions from noble gases y:::;;10 mrad/Yf DJ3=air dose due to beta emissions from noble gases:::;;20 mrad/Yf 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: D p=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/Yf 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 D Tau=L[A iTau L C il F I]:::;;1.5 mrem/qtr Total Body i 1=1:::;;5 mrem/qtr Any Organ:::;;3 mrem/Yf Total Body:::;;10 mrem/yr Any Organ where the terms are defined in the GGNS ODCM.env-tec/ARERR01

-6 II.DETAILED INFORMATION (CONT'D)3.40CFR190 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:::;25 mremlyr, Total Body or any Organ except Thyroid::;75 mremlyr, Thyroid::;10 mrad y/qtr or::;20 mrad y/yr, Fission and Activation Gases::;20 mrad f3/qtr or::;40 mrad f3/yr, Fission and Activation Gases::;15 mremlqtr or::;30 mremlyr, any Organ, Iodine and Particulates

3 mremlqtr or
:;6 mremlyr, Total Body, Liquid Effluents::;10 mremlqtr or::;20 mremlyr, 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 10CFR20, 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.env-tec/ARERR01

  • 7 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 Radioiodines Particulates Liquid Effluents Tables 1D 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 1D 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 1D for sampling and analytical requirements.)

Isotopic values thus obtained are used fordoserelease rate calculations due to effluent releases as given in Section II.A.1 of this report.The radionuclides that are detected are used in this computation.

When no radionuclides are detected, a historical mixture is used.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*C i=isotopic calibration factor for isotope i Vi=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-tec/ARERR01

-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 radionuc1ides are calculated and stored.If no activity is detected in the grab sample, the calibration factor defaults to a historical mixture ofK.r-88, Xe-133, Xe-135m, Xe-135, and Xe-138.2.For Particulates and Radioiodines At a minimum, the following radioiodines and radioactive materials in particulate form to be considered are: 2n-65 Mo-99 Mn-54 Cs-134 Fe-59 Cs-137 Co-58 Ce-141 Co-60 Ce-144 Sr-89 1-131 Sr-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.

Radioiodines are collected by adsorption onto a charcoal filter.Periodically these filters are removed and analyzed by gamma spectral analysis utilizingresolution 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 1D,"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 11.41 Curies released per year in gaseous form was obtained by estimation using EPRI spreadsheet BWR Source Term Calculation (MAL-1)_rl and the information in NEAD-NS-11-0060-Rev1-EC42519 and adjusted by 236 full power production days.Carbon-14 curies are reported in Tables 1A and 1C 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 INFORMATION (CONT'D)5.For Batch Releases: Liquid Effluents At a minimum, the radionuclides listed below are considered when evaluating liquid effluents:

H-3 Mn-54 Fe-55 Co-58 Co-60 Fe-59 Zn-65 Sr-89 Sr-90 Mo-99 1-131 Cs-134 Cs-137 Ce-141 Ce-144 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 analyzedusingliquid 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 3rd Qtr 4th tr Year a.Number of releases 41 39 205 Time Period in minutes b.Total for all batches I.94 E+04 1.78E+041.25E+041.06E+04 6.03E+04 c.Max time for a batch3.95E+023.15E+02 3.20E+02 3.60E+02 3.95E+02 d.Av time for a batch 2.98E+02 2.96E+02 3.06E+02 2.73E+02 2.94 E+02 e.Min time for a batch 5.00E+Ol 1.00E+Ol 2.80E+02 1.00E+00 1.00E+00 2.Gaseous No batch releases occurred during the report period.env-tec/ARERR01*

10 II.DETAILED INFORMATION (CONT'D)F.Abnonnal Releases 1.Liquid a.Number of Releases: b.Total Activity Released: o O.OOE+OO Ci No abnonnalliquid releases were identified for this reporting period.2.Gaseous a.Number of Releases: b.Total Activity Released: o O.OOE+OO Ci No abnonnalliquid releases were identified for this reporting period.G.Estimate of Total Error 1.Liquid The maximum errors are collectively estimated to be as follows: Fission&Activation Tritium Dissolved&Entrained Gross Products Gases AI ha Sampling%2.60£+012.60£+012.60£+01 2.60£+01 Measurement

%6.80£+01 6.50£+01 6.10£+01 9.20£+01 TOTAL%7.30£+017.00£+016.60£+01 9.50£+01 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 gennanium detectors, the 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 bytakingthe 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+OI 2.30E+OI2.20E+OI2.20E+OI 2.30E+OI 6.10E+OI 6.70E+Ol 6.50E+OI l.OIE+02 6.20E+OI 6.90E+Ol 7.lOE+Ol 6.90E+OI I.03E+02 6.60E+Ol env-tec/ARERR01

-11 II.DETAILED INFORMATION (CONT'D)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+01.

Sampling errors include uncertainty associated with mixing and representative sampling.H.Solid Radioactive Waste Shipments See Table 3 for shipment infonnation.

I.Meteorological Data The data recovery for the reporting period was 99.8%.The predominant wind direction was from the Northeast approximately 11.30/0 of the time.The predominant stability class was class"D" approximately 29.60/0 of the time.Average wind speed during the reporting period was approximately

4.2 miles

per hour at the 33 foot elevation.

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 Liquid radwaste effluent radiation monitor was been inoperable for>14 days per Limiting Condition for Operation 1-0TS-12-0030.

This was documented in Condition Report06059.ODCM action 6.3.9 B.3 has a completion time of 14 days to restore channel to operable, which was exceeded at 12:46 on Apri, 23, 2012..Exceeding this completion timerequiresentry into Condition D with required action D.1 to immediately suspend Liquid Radwaste releases and action D.2 to immediately initiate action to explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.Restoration of this equipment was delayed by Refueling Outage 18 critical path activities.

In addition, a retest delay occuredand was documented in Condition Report GGN-2012-06007.

K.AnnualSewageDisposal Summary There were 2 sewage sludge shipments in 2012 consisting of 8 B-25 boxes that were shipped to EnergySolutions for Green is Clean.env-tec/ARERR01

-12 III.RADIATION DOSE

SUMMARY

Indicatedbelow is the annual summary of offsitedoses attributable to GGNS during 2012.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 kIn of GGNS, 40CFR190 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.2012 Liquid Effluent Dose (mrem)1 st Qtr 2ndQtr 3rd Qtr 4th Qtr TOTAL Bone1.61E-011.26E-011.55E-025.23E-03 2.68E-01 Liver 2.74E-01 3.09E-01 3.97E-02 1.23E-02 5.64E-01 Thyroid 4.81E-03 1.52E-03 1.02E-03 1.29E-03 8.03E-03 Kidney 1.18E-01 1.82E-01 2.39E-02 6.52E-03 2.98E-01 Lung 2.61E-02 1.03E-022.25E-032.12E-03 3.55E-02 GI-LLI 9.48E-02 1.69E-01 2.58E-02 1.22E-02 2.76E-01 Whole Body 1.63E-01 1.54E-01 1.95E-02 6.53E-03 3.02E-01 B.Airborne-Related Exposure Pathways The values presented in this section utilize information provided in Tables1A andIC 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 validated 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 2012 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.env-tec/ARERR01-13 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 2012 meteorological data.The critical receptor residence was determined to be located in the southwest sector at adistance 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 2012 meteorological data.The total body and skin dose rates reported are the quarterly average of the maximum instantaneous dose rates 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 2012 meteorological data.The highest dispersion factor for an unrestricted area was in the sout.q.west 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 thermoluminescent dosimeter (TLD)badges located at control locations from average doses measured by TLD badges located near the site boundary.GGNS reported measured doses in 2012 as net exposure normalized to 92 days.env-lec/ARERR01-14 III.RADIATION DOSE

SUMMARY

(CONT'D)Carbon-14 Carbon-14 (C-14)is a naturally occurring isotope of carbon.Nuclear weapons testing in the 1950s and 1960s significantly increased the amount ofC-J4 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 of95%is used based on EPRI Technical Report 1021106,"Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents".

The highest atmospheric dispersion factor for an actual garden based on the land use census was used to determine dose from C-14.Carbon-14 is dispersed as a gas (C0 2)to the garden location, where it is then incorporated into plant material.Carbon-14 dose is calculated for maximum organ dose to a MEMBER OF THE PUBLIC for the most age restrictive group (Child)and organ (bone)at the 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.2012 Airborne Effluent Dose (mrem)1st Qtr 2nd Qtr 3rd Qtr 4th Qtr TOTAL Iodine, Tritium&Particulates (excluding Carbon-14\

Child (mrem)1.08E-02 1.66E-03 5.81E-03 1.12E-02 2.95E-02 Organ Thyroid ThyroidThyroidThyroidThyroid Applicable Limit 7.5 7.5 7.5 7.5 15 Percent of Limit 1.45E-Ol 2.21E-02 7.75E-021.49E-OI1.97E-OI Iodine, Tritium&Particulates (including Carbon-14)

Child (mrem)1.45E+00 3.09E-02 2.68E+00 2.90E+00 7.06E+00 OrganBoneBoneBoneBone Bone Applicable Limit 7.5 7.5 7.5 7.5 15 Percent of Limit 1.93E+Ol 4.12E-OI 3.57E+Ol 3.87E+Ol 4.71E+Ol Total Body Dose Rate (mrem/yr)3.03E-02 3.8IE-01 5.90E-Ol 4.71E-Ol Applicable Limit500500500500 Percent of Limit6.06E-037.62E-02 1.18E-OI 9.42E-02.Skin Dose Rate(mrem/yr)7.33E-02 7.34E-Ol 8.53E-Ol 6.98E-Ol Applicable Limit 300030003000 3000 Percent of Limit 2.43E-032.45E-022.84E-02 2.33E-02 Gamma Air Dose*9.23E-03 6.34E-02 1.98E-Ol 1.52E-01 4.23E-Ol Applicable Limit 5 5 5 5 10 Percent of Limit 1.85E-Ol 1.27E+00 3.96E+00 3.05E+00 4.23E+00 Beta Air Dose*1.31E-02 6.67E-02 7.44E-02 6.20E-02 2.16E-Ol Applicable Limit 10 10 10 10 20 Percent of Limit 1.31 E-Ol 6.67E-Ol 7.44E-Ol 6.20E-Ol 1.08E+00 Direct Radiation (mrem)0.0 0.0 0.0 0.56 0.56 Verify these from REMP data*Measurement umts are mrad env-tecIARERR01*

15 IV.OFFSITE DOSE CALCULATION MANUAL/RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES A.Offsite Dose Calculation Manual (ODCM)Revisions 38 and 39 of the ODCM were issued in 2012.The revisions included Description of Change(s)Revision MonthlYear Affected Number of Change Page Number(s)Revise 6.3.9 to add condition E.Condition E is 38 03/2012 i, ia, vii, to acknowledge that as long as flow is viib, monitored and measured, there is no need to A-14 suspend dilution flow activities LBDCR 12-012 Revise Table 6.3.10-1 Section 3B to include 39 03/2012 1, VB, note h.Note h is to acknowledgeTurbine viia, viib, Building roof hatches may be open in Modes 4 2.0-35, A-and 5.LDCR 2012-017 26, A-28, A-39, A-41 A current copy of the GGNS ODCM is included in this submittal as Attachment II.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

-16 TABLEIA ENTERGY OPERATIONS, INC.GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR-----------------------

Fission and Activation Gases 1.Total Release Ci 1.35E+011.74E+021.54E+02 1.11E+02 4.53E+02 2.Avg.Release Rate uCi/sec 1.71E+00 2.22E+01 1.94E+01 1.39E+01 1.43E+01 3.Percent of TS Limit a.Gamma Air%1.85E-01 1.27E+00 3.96E+00 3.05E+00 4.23E+OO b.Beta Air%1.31E-01 6.67E-01 7.44E-01 6.20E-01 1.08E+OO Iodine-131 1.Total Release Ci 1.91E-04 5.02E-06 2.63E-05 1.96E-04 4.18E-04 2.Avg.Release Rate uCi/sec 2.43E-05 6.38E-07 3.30E-06 2.46E-05 1.32E-06 3: Percent of TS Limit%4.40E-02 1.16E-03 6.05E-034.51E-024.81E-02 Particulates Half Life>=8 days 1.Total Release Ci 3.64E-,.05 7.99E-05 5.43E-05 5.71E-05 2.28E-04 2.Avg.Release Rate uCi/sec 4.63E-06 1.02E-056.83E-067.18E-06 7.20E-06 3.Percent of TS Limit%1.42E-03 1.99E-03 2.37E-035.41E-035.37E-03 Tritium 1.Total Release Ci 7.01E+OO 1.58E+OO 5.06E+OO 7.50E+OO 2.11E+01 2.Avg.Release Rate uCi/sec 8.92E-01 2.01E-01 6.36E-01 9.43E-01 6.69E-01 3.Percent of TS Limit%9.22E-02 2.08E-02 6.65E-02 9.86E-02 1.39E-01 Carbon 14 1.Total Release Ci 2.32E+OO 5.00E-02 4.29E+OO 4.64E+OO 1.13E+01 2.Avg.Release Rate uCi/sec 2.95E-01 6.36E-035.40E-015.84E-01 3.57E-01 Edited to*match method writeup and Table 1C values Gross Alpha 1.Total Release.Ci 9.59E-08 6.59E-076.55E-087.93E-08 9.00E-07 2.Avg.Release Rate uCi/sec 1.22E-08 8.39E-08 8.25E-09 9.97E-09 2.85E-08 env-tec1ARERR01

  • 17 env-tec/ARERR01

-18 TABLE1B ENTERGY OPERATIONS, INC.GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-ELEVATED RELEASES JANUARY-DECEMBER 2012 (Not Applicable

-GGNS Releases Are Considered Ground-Level)

TABLEIC ENTERGY OPERATIONS, INC.GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE-CONTINUOUS REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases AR-41 Ci 4.16E-02 1.08E-01 3.49E+01 1.95E+01 5.46E+01 KR-85M Ci 2.65E+00 4.76E-02 2.58E+01 1.68E+01 4.53E+01 KR-87 Ci O.OOE+OO 2.41E-01 1.01E+00 6.23E+00 7.48E+00 KR-88 Ci 8.02E-023.53E+003.79E+01 3.23E+01 7.38E+01 KR-89 Ci O.OOE+OO 1.48E+00 1.14E-01 O.OOE+OO 1.59E+OO XE-133 Ci 1.60E+00 7.89E+01 2.95E+01 1.92E+01 1.29E+02 XE-135 Ci 1.48E+00 7.56E+01 2.16E+01 1.47E+01 1.13E+02 XE-135M Ci 1.22E+00 9.34E+00 2.57E+00 1.71E+00 1.48E+01 XE-137 Ci 3.12E+00 1.33E+00 1.03E-01 O.OOE+OO 4.56E+00 XE-138 Ci 3.24E+00 3.74E+00 7.09E-01 3.88E-01 8.08E+00----------------------------------------Totals for Period...Ci 1.35E+011.74E+021.54E+02 1.11E+02 4.53E+02 Iodines I-131 Ci 1.91E-04 5.02E-06 2.63E-05 1.96E-04 4.18E-04 I-133 Ci 6.58E-04 1.16E-05 3.05E-04 4.30E-04 1.40E-03 I-135 Ci 7.75E-05 O.OOE+OO4.88E-044.77E-05 6.13E-04----------------------------------------Totals for Period...Ci 9.26E-04 1.66E-05 8.20E-04 6.73E-04 2.44E-03 Particulates Half Life>=8 days AG-110M Ci O.OOE+OO O.OOE+OO O.OOE+OO3.29E-063.29E-06 BA-140 Ci 1.41E-05 O.OOE+OO O.OOE+OO*O.OOE+OO 1.41E-05 CO-58 Ci O.OOE+OO O.OOE+OO 8.60E-06 3.90E-06 1.25E-05 CO-60 Ci 2.45E-06 1.42E-05 2.23E-06 2.37E-05 4.25E-05 CR-51 Ci 1.53E-06 O.OOE+OOO.OOE+OOO.OOE+OO 1.53E-06 CS-134 CiO.OOE+OOO.OOE+OOO.OOE+OOO.OOE+OOO.OOE+OO CS-137 Ci O.OOE+OO 2.11E-06 O.OOE+OO 1.92E-06 4.03E-06 FE-55 Ci 4.75E-07 1.44E-05 O.OOE+OO 3.68E-07 1.52E-05 MN-54 Ci 1.35E-06 7.89E-06 4.49E-06 8.63E-06 2.24E-05 RU-106 Ci O.OOE+OO O.OOE+OO 3.32E-05 8.11E-07 3.40E-05 SR-89 Ci 1.01E-05 1.21E-05 5.60E-06 1.63E-06 2.95E-05 SR-90 Ci O.OOE+OO O.OOE+OO 2.06E-07 5.04E-07 7.10E-07 ZN-65 Ci 6.40E-06 2.92E-05 O.OOE+OO 1.23E-05 4.79E-05----------------------------------------

Totals for Period...Ci 3.64E-05 7.99E-055.43E-055.71E-05 2.28E-04 Other H-3 C-14 Gross Alpha env-tec/ARERR01

-19 Ci Ci Ci 7.01E+00 2.32E+00 9.59E-08 1.58E+00 5.00E-02 6.59E-07 5.06E+00 4.29E+00 6.55E-08 7.50E+00 4.64E+00 7.93E-08 2.11E+01 1.13E+01 9.00E-07 TABLEID ENTERGY OPERATIONS, INC.GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radioactive Gaseous Waste Sampling and Analysis Program JANUARY-DECEMBER 2012 Lower Limit Sampling Minimum Analysis Type of Activity Analysis of Detection Gaseous Release Type Frequency Frequency (LLD)(uCi/ml)a A.(1)Radwaste Building 31 Days 31 Days Principal Gamma Emitters Ventilation Exhaust Grab Sample (t)02&)1X 10-4 H-3 IXlO-6 (2)Fuel Handling Area Continuous (d)(t)7 Days (c)1-131 Ix10-12 Ventilation Exhaust Charcoal Sample 1-133 Ix10-IO (3)Containment Continuous (d)(t)7 Days (c)Principal Gamma Emitters IxlO-11 Ventilation Exhaust Particulate Sample (e)(1-131, Others)(4A)Turbine Building Continuous (d)(t)31 Days Composite Gross Alpha IxlO-II Ventilation Exhaust Particulate Sample (4B)Turbine Building Occasional Continuous (d)(t)92 Days Composite Sr-89, Sr-90 IxlO-11 Release Point(g)Particulate Sample (when in service)Continuous (t)Noble Gas Monitor Noble Gases Gross Beta or1X 10-6 Gamma B.(1)Offgas Post 31 Days Grab 31 Days Principal Gamma Emitters IxlO-4 Treatment Exhaust, Sample (t)(e)whenever there is flow (2)Standby Gas 31 Days Grab 31 Days Principal Gamma1X 10-4 Treatment A Exhaust, Sample (t)Emitters(e) whenever there is flow (3)Standby Gas 31 Days Grab 31 Days Principal Gamma1X 10-4 Treatment B Exhaust, Sample (t)Emitters(e)whenever there is flow NOTE: Footnotes 10dIcated are lIsted 10 GGNS ODCM, AppendIX A, Table 6.11.4-1.env-tec/ARERR01

  • 20 TABLE2A ENTERGY OPERATIONS, INC.GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR---------------------

Fission and Activation Products 1.Total Release Ci2.04E-022.94E-021.85E-021.55E-02 8.38E-02 2.Avg.Diluted Cone.uCi/ml 5.30E-08 7.38E-08 4.44E-08 5.15E-08 5.58E-08 3.Percent of Limit%9.82E-02 8.86E-023.44E-023.25E-02 6.46E-02 Tritium 1.Total Release Ci 4.66E+01 1.81E+01 1.81E+011.94E+011.02E+02 2.Avg.Diluted Cone.uCi/ml 1.21E-04 4.55E-05 4.33E-05 6.41E-05 6.80E-05 3.Percent of Limit%1.21E+00 4.55E-01 4.33E-016.41E-016.80E-01 Dissolved and Entrained Gases 1.Total Release Ci 2.81E-03 6.19E-05 1.12E-03 8.28E-04 4.82E-03 2.Avg.Diluted Cone.uCi/ml 7.32E-09 1.55E-10 2.68E-09 2.74E-09 3.21E-09 3.Percent of Limit%3.66E-03 7.77E-05 1.34E-03 1.37E-03 1.60E-03 Gross Alpha Radioactivity 1.Total Release CiO.OOE+OOO.OOE+OO O.OOE+OOO.OOE+OOO.OOE+OO Volume of liquid waste liters 6.62E+06 6.17E+06 4.28E+06 3.63E+06 2.07E+07 Volume of dil.water env-tec1ARERR01

-21 liters 3.77E+08 3.94E+08 4.13E+08 2.99E+08 1.48E+09 TABLE2B ENTERGY OPERATIONS, INC.GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS-CONTINUOUS AND BATCH MODES REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products AG-110M Ci 2.05E-04 1.74E-04 7.11E-05 1.05E-03 1.50E-03 AS-76 Ci O.OOE+OO O.OOE+OO 3.14E-05 5.23E-05 8.37E-05 Au-i99 Ci 7.52E-06 O.OOE+OO O.OOE+OO 6.63E-05 7.38E-05 CO-58 Ci 1.38E-04 1.11E-042.51E-052.51E-04 5.24E-04 CO-60 Ci 6.02E-03 3.31E-03 1.57E-03 8.46E-04 1.18E-02 CR-51 Ci 5.95E-04 3.25E-05 5.34E-05 2.73E-03 3.41E-03 CS-134 Ci O.OOE+OO 9.52E-06 O.OOE+OO O.OOE+OO 9.52E-06 CS-137 Ci 8.59E-04 3.35E-04 4.47E-05 1.89E-05 1.26E-03 CU-67 Ci O.OOE+OO O.OOE+OO O.OOE+OO 4.14E-06 4.14E-06 FE-55 Ci 3.74E-03 1.29E-02 8.88E-03 6.10E-03 3.17E-02 FE-59 Ci 1.40E-04 4.76E-05 O.OOE+OO 2.30E-04 4.18E-04 I-131 Ci 1.31E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.31E-05 LA-140 Ci 8.40E-04 O.OOE+OO 6.18E-05 3.51E-05 9.37E-04 MN-54 Ci'4.56E-03 2.08E-03 4.23E-04 8.30E-04 7.90E-03 MO-99 Ci 6.14E-05 O.OOE+OO O.OOE+OO O.OOE+OO 6.14E-05 NA-24 Ci O.OOE+OO O.OOE+OO O.OOE+OO 2.58E-05 2.58E-05 PT-195M Ci O.OOE+OO O.OOE+OO O.OOE+OO 1.94E-05 1.94E-05 RB-88 Ci, 1.97E-04 O.OOE+OO 4.40E-03 1.99E-03 6.59E-03 RU-106 ci: 2.04E-04 2.08E-04 1.16E-03 8.92E-04 2.47E-03 SB-124 Ci 6.43E-05 7.50E-05 O.OOE+OO 3.39E-05 1.73E-04 SB-125 Ci 3.00E-04 1.49E-03 8.80E-05 O.OOE+OO 1.88E-03 SE-75 Ci O.OOE+OOO.OOE+OOO.OOE+OO 3.34E-06 3.34E-06 SN-117M Ci O.OOE+OOO.OOE+OOO.OOE+OO 2.03E-05 2.03E-05 SR-92 Ci 2.53E-06 1.66E-05 O.OOE+OO 4.52E-05 6.43E-05 TC-99M Ci 7.27E-05 5.64E-06 4.80E-06 2.39E-06 8.55E-05 W-187 Ci 2.33E-05 O.OOE+OOO.OOE+OOO.OOE+OO 2.33E-05 ZN-65 Ci 2.29E-03 8.56E-03 1.68E-03 2.70E-04 1.28E-02 ZN-69M Ci 2.27E-05 6.72E-06 5.31E-06 1.30E-05 4.77E-05 ZR-97 Ci O.OOE+OO O.OOE+OO O.OOE+OO 1.54E-05 1.54E-05----------------------------------------Totals for Period...Ci 2.04E-02 2.94E-02 1.85E-02 1.55E-02 8.38E-02 Tritium H-3 Ci 4.66E+01 1.81E+01 1.81E+0J, 1.94E+01 1.02E+02----------------------------------------Totals for Period...Ci 4.66E+01 1.81E+01 1.81E+01 1.94E+01 1.02E+02 Dissolved and Entrained Gases XE-133 Ci 2.68E-03 3.33E-05 4.83E-04 3.61E-04 3.55E-03 XE-133M Ci 3.77E-05 O.OOE+OO O.OOE+OO O.OOE+OO 3.77E-05 XE-135 Ci 9.92E-05 2.87E-05 6.36E-04 4.67E-04 1.23E-03----------------------------------------Totals for Period...Ci 2.81E-03 6.19E-05 1.12E-03 8.28E-04 4.82E-03 Gross Alpha Radioactivity Alpha Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO----------------------------------------Totals for Period...Ci O.OOE+OO O.OOE+OOO.OOE+OOO.OOE+OO O.OOE+OO env-tec/ARERR01

-22 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 2012 Lower Limit Sampling Minimum Analysis Type of Activity Analysis of Detection Liquid Release Type Frequency Frequency (LLD)(uCi/ml)(a)

A.Batch Waste Release Prior to Release Prior to Release Each Principal Gamma Emitters Tanks (c)Each Batch Batch (g)5xlO,7 1-131IX 10'6 Prior to Release 31 Days Dissolved and Entrained IxIO')One Batch 1M Gases (Gamma Emitters)Prior to Release 31 Days H-3 I X 10.5 Each Batch Composite (b)Gross Alpha I X 10'7 Prior to Release 92 Days Composite Sr-89, Sr-90 5xlO'lS Each Batch (b)Fe-55 IxlO,6 B.SSW Basin (Before Prior to Release Prior to Release Each Principal Gamma Emitters Blowdown)Each Blowdown Batch@5xlO,7 1-131 I X 10'6 NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table11.1-1.env*tec1ARERR01

-23 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 2012 A.SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)1.Type of Waste Unit Class A Class B Class C Est.Total Error%a.Spent resins, filter sludges, m 3 1.40E+02 2.86E+00 O.OOE+OO+/-25%evaporator bottoms, etc.Ci 5.05E+02 1.06E+03 O.OOE+OO b.Dry compressible waste, m 3 3.94E+03 O.OOE+OO O.OOE+OO+/-25%contaminated equipment, etc.Ci 3.46E+00O.OOE+OOO.OOE+OO c.Irradiated components, m 3 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 m 3 4.19E+OlO.OOE+OOO.OOE+OO

+/-25%Bundle Ci 7.93E-02O.OOE+OOO.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 0.414 6.50E+00 Co-60 9.097 1.43E+02 Cr-51 0.545 8.55E+00 Cs-137 0.232 3.64E+00 Fe-55 75.449 1.18E+03 Fe-59 0.691 1.08E+Ol Mn-54 9.488 1.49E+02 Co-58 0.352 5.52E+00 Zn-65 3.617 5.68E+Ol env-tec/ARERR01

-24 TABLE 3 ENTERGY OPERATIONS,GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY-DECEMBER 2012 (Cont)3.Solid Waste Disposition Number of Destination Name City State Mode of Shipments Transportation 68 EnergySolutions(Duratek), LLC OakRidge TN Hittman 19 EnergySolutions

-Gallaher Road Facility OakRidge TN Hittman 10 Studsvik Erwin TN Hittman NRC Disposal Description Number of Waste Type Description Class Volume(ft"3)

Containers B 120.3 81120 HIC 1 Poly HIC-RWCU-A A 202.2 ES-210 18 Carbon Steel Liner-SRT A 1290 20'SEALAND 135 20FT Sealand A 800 Water Tanker 2 Water tanker A 199.4 ES-210 9 Stainless Steel Liner See below (solidification)

CPS/RWCU-B 199.4 ES-210 A Verify same (solidification) 3 Empty-Stainless Steel Liner number?B.Irradiated Fuel Shipments (Disposition)

I NUMBER OF SHIPMENTS I MODE OF TRANSPORTATION I None i N/A env-tec/ARERR01

-25 I DESTINATION I I N/A I ATTACHMENT I GPI Sample Results JANUARY-DECEMBER 2012 Verify numbers against raw data, resolve highlighted

??Are double values dup samples?[need'DUP'annotation, or just second count.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.All results were less than Reporting Levels ofGGNS-ODCM table 6.12.1-2.LOCATION DATE TRITIUM (pCi/Ll GAMMAlHTD (pCi/Ll DW-Ol 2/9/2012 17800<MDA DW-Ol 6/13/2012 12800<MDA DW-Ol 9/12/2012 16800<MDA DW-Ol 11/7/2012 12600<MDA DW-07 9/12/2012 6550<MDA DW-07 11/6/2012 8350<MDA MW-Ol 2/9/2012<239<MDA MW-Ol 6/13/2012<351<MDA MW-Ol 9/11/2012 380/359(DUP)

<MDA MW-Ol 11/7/2012<262<MDA MW-08 2/8/2012<326<MDA MW-08 6/13/2012<347/350<MDA MW-09 2/9/2012<234<MDA MW-09 6/13/2012<342<MDA MW-I0 6/13/2012<337<MDA MW-13 6/20/2012<284<MDA MW-15 6/20/2012<342<MDA MW-18 6/20/2012<275<MDA env-tec/ARERR01-26 ATTACHMENT I GPI Sample Results JANUARY-DECEMBER 2012 (Cant)LOCATION DATE TRITIUM (pCi/L)GAMMAlHTD (pCi/L)MW-21 6/20/2012<277<MDA MW-23 2/9/2012<233<MDA MW-23 6/12/2012<346<MDA MW-100B 2/9/2012<234<MDA MW-100B 6/12/2012<341<MDA MW-100B 9/12/2012<204<MDA MW-100B*11/8/2012<263<MDA MW-102B 2/9/2012<238<MDA MW-102B 6/12/2012<347<MDA MW-102B 9/12/2012 347<MDA MW-102B 11/7/2012 268<MDA MW-103B 2/8/2012<235<MDA MW-103B 6/13/2012<339<MDA MW-103B 9/12/2012<215<MDA MW-103B 11/7/2012<271<MDA MW-104B 2/9/2012<235<MDA MW-104B 6/13/2012<347<MDA MW-104B 9/13/2012<219<MDA MW-104B 11/7/2012<268<MDA MW-105B 2/9/2012 740/904<MDA MW-105B 6/12/2012 560<MDA MW-105B 9/12/2012 773<MDA MW-105B 11/8/2012 823/665<MDA MW-106B 2/9/2012<235<MDA MW-106B 6/12/2012<355<MDA MW-106B 9/12/2012<213<MDA MW-106B 11/7/2012<269<MDA MW-107B 2/8/2012 3430<MDA MW-107B 6/12/2012 2430<MDA MW-107B 9/12/2012 2440<MDA env-tecIARERR01-27 MW-I07B 11/6/2012 2070<MDA ATTACHMENT I GPI Sample Results JANUARY-DECEMBER 2012 (Cant)LOCATION DATE TRITIUM (pCi/L)GAMMAlHTD (pCi/L)MW-I08B 2/8/2012 612<MDA MW-I08B 6/13/2012 604<MDA MW-I08B 9/12/2012 983<MDA MW-I08B 11/6/2012 994/868<MDA MW-I09B 2/8/2012 699<MDA MW-I09B 6/13/2012<344<MDA MW;i09Ij,MW-I09B 11/6/2012 591<MDA MW-I09R 9/12/2012 816<MDA MW-I10B 2/9/2012<231 MW-I10B 6/13/2012<341<MDA MW-I10B 9/11/2012<218<MDA MW-I10B 11/8/2012<354<MDA MW-I11B Jan-:-l2, 10100 MW-IIIB 6/13/2012 18400<MDA MW-I11B 9/11/2012 11000<MDA MW-II1B 11/7/2012 8920<MDA MW-112B 2/9/2012<229<MDA MW-112B 6/13/2012<347<MDA MW-112B 9/11/2012<220<MDA MW-112B 11/7/2012<268<MDA MW-113B 2/9/2012 356<MDA MW-113B 6/13/2012<350/348<MDA 9/12/2012<211<MDA MW-113B 11/7/2012 352<MDA MW-114B 2/9/2012 2340<MDA MW-114B 6/13/2012 3260<MDA MW-114B 9/12/2012 2460/2950<MDA MW-114B 11/7/2012 2970<MDA env-tec/ARERR01

-28 ATTACHMENT I GPI Sample Results JANUARY-DECEMBER 2012 (Cant)LOCATION DATE TRITIUM (pCi/L)GAMMAlHTD (pCi/L)MW-115B 2/9/2012 5630/4510<MDA MW-115B 6/13/2012 1680<MDA MW-115B 9/12/2012 5230<MDA MW-115B 11/7/2012 2510<MDA MW-118B 491 MW-118B 6/13/2012 1700<MDA MW-118B 9/11/2012 1050<MDA MW-118B 11/6/2012 1060<MDA MW-1007B 6/19/2012<282<MDA MW-1007C 6/14/2012<286<MDA MW-1009B 6/19/2012<283<MDA MW-1012C 6/14/2012<281/<285<MDA MW-1019B 6/20/2012<336<MDA MW-1022B 6/19/2012<334<MDA MW-1024C 6/12/2012<341<MDA MW-1026B 6/14/2012<289<MDA MW-1026B 6/19/2012<288<MDA MW-1027B 6/20/2012 372<MDA MW-1027C 6/14/2012<286/<289<MDA MW-1042C 6/12/2012<341<MDA MW-1045B 6/14/2012<337/<340<MDA MW-1082C 6/12/2012<341<MDA env-tec/ARERR01

-29 MW-1134C 6/12/2012<342<MDA ATTACHMENT I GPI Sample Results JANUARY-DECEMBER 2012 (Cant)OW-05 6/19/2012<288<MDA OW-209B 2/9/2012 5980<MDA OW-209B 6/12/2012 2650<MDA OW-209B 9/1112012 2430<MDA OW-209B 1118/2012 2210<MDA OW-1008 6/19/2012<287<MDA OW-1108 6/19/2012<332<MDA P-05 6/13/2012<330<MDA SW-103A 6/14/2012<338<MDA SW-103A 9/12/2012<218<MDA SW-103A 1118/2012'

<273<MDA SW-103B 2/9/2012<366<MDA<<MDA=less than minimum detectable activity)(DUP=separate sample collected and analyzed)env-teclARERR01

-30 env*tec/ARERR01

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