View source for GNRO-2013/00040, Submittal of 2012 Annual Radioactive Effluent Release Report, Revision 1 Per 10 CFR 50.36a(a)(2)

{{Adams
| number = ML13161A313
| issue date = 06/10/2013
| title = Submittal of 2012 Annual Radioactive Effluent Release Report, Revision 1 Per 10 CFR 50.36a(a)(2)
| author name = Robinson C
| author affiliation = Entergy Operations, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000416
| license number = NPF-029
| contact person = 
| case reference number = GNRO-2013/00040
| document type = Annual Operating Report, Environmental Monitoring Report, Letter type:GNRO
| page count = 33
}}

=Text=
{{#Wiki_filter:~Entergy Entergy Operations, Inc.
P.O. Box 756 Port Gibson, Mississippi 39150 Tel: 601-437-7326 Christopher R. Robinson Licensing Manager Grand Gulf Nuclear Station GNRO-2013/00040 June 10, 2013 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

==SUBJECT:==
Grand Gulf Nuclear Station 2012 Annual Radioactive Effluent Release Report, Revision 1 per 10 CFR 50.36a(a)(2)
Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29

==REFERENCES:==
GNRO-2013/00033, Dated April 30, 2013, Grand Gulf Nuclear Station 2012 Annual Radioactive Effluent Release Report per 10 CFR 50.36a(a)(2)

==Dear Sir or Madam:==

Attached is the Grand Gulf Nuclear Station (GGNS) Annual Radioactive Effluent Release Report (ARERR), Revision 1 for the period January 1, 2012 through December 31,2012. It was identified that the Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results, pages 26 - 29 of the report were not fully complete. Revisions to the report are identified by a revision bar located on the right side of the page. This report is being submitted in accordance with the requirements of 10 CFR 50.36(a)(2) and the GGNS Technical Specifications (TS) 5.6.3. This ARERR also complies with the GGNS Offsite Dose Calculation Manual (ODCM).
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:==
Grand Gulf Nuclear Station 2012 Annual Radioactive Effluent Release Report, Revision 1 cc:           (See Next Page)

GNRO-2013/00040 Page 2 of 2 cc:         NRC Senior Resident Inspector Nuclear   ....:'I'':l1fl.'..U''l Gibson, MS 39150 U.S. Nuclear Regulatory Commission AnN: Document Control Desk Washington, DC '"v,Jv....'-v ....'v U. S. Nuclear Regulatory Commission AnN: Mr. Alan Wang, NRR/DORL (w/2)
Mail Stop OWFN 8 81 Washington, Mr. J. Smith Director, Division of Radiological Health Mississippi        Department of Health Division of Radiological Jackson, MS 39213 Dr. Mary Currier, M.D. M.P.H.
Mississippi Department of Health 1
Jackson, MS 39215-1700

Attachment To GNRO-2013/00040 Grand Gulf Nuclear Station 2012 Annual Radioactive Effluent Release Report, Revision 1

ENTE GY OPE                  10 S,      C.
GRAND GULF NUCLEAR STATION AL RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2012 - December 31, 2012 Prepared By Reviewed By
                                           /
Approved Page 1                                            Revision 1

TABLE OF CONTENTS SUBJECT            PAGE I. INTRODUCTION                                                  4 II. DETAILED INFORMATION                                          5 A. Regulatory Limits                                          5
: l. 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 "l
J. 40CFR 190 Limits                                       7 B. Effluent Concentrations                                    7
: l. Airborne                                                7
: 2. Liquid                                                  7 C. Average Energy                                             7 D. Measurements and Approximations of Total Activity          8
: l. 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
: l. Liquid                                                 10
: 2. Gaseous                                                10 F. Abnormal Releases                                         11
: l. Liquid                                                 II
: 2. Gaseous                                                11 Page 2                                                       Revision 1

TABLE OF CONTENTS (CONT'D)
SUBJECT                                               PAGE G. Estimate of Total Error                                                                      II I. Liquid                                                                                   II
: 2. Gaseous                                                                                  12
: 3. Solid Radioactive Waste                                                                  12 H. Solid Radioactive Waste Shipments                                                            12 I. Meteorological Data                                                                          12 J. Radioactive Effluent Monitoring Instrumentation Operability                                 12 K. Annual Sewage Disposal Summary                                                               12 III. RADIATION DOSE 

==SUMMARY==
13 A. Water-Related Exposure Pathway                                                              13 B. Airborne-Related Exposure Pathway                                                           13 IV. OFFSITE DOSE CALCULATION MANUAL/RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES                                                                                 16 A. Offsite Dose Calculation Manual (ODeM)                                                      16 B. Radioactive Waste Treatment Systems                                                         16 LIST OF TABLES                                             PAGE IA     Gaseous Effluents   Summation of All Releases                                                  17 IB     Gaseous Effluents   Elevated Releases                                                          18 lC     Gaseous Effluents - Ground-Level Releases     Continuous                                       19 10     Radioactive Gaseous Waste Sampling and Analysis Program                                        20 2A     Liquid Effluents - Summation of All Releases                                                   21 2B     Liquid Effluents - Continuous and Batch Modes                                                  22 2C     Radioactive Liquid Waste Sampling and Analysis Program                                         23 3     Solid Radioactive Waste and Irradiated Fuel Shipments                                          24 ATTACHMENTS                                               PAGE Attachment I - Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results                                                                                        26 30 Attachment II - Offsite Dose Calculation Manual Page 3                                                                                         Revision 1

I. INTRODUCTION This Annual Radioactive Effluent Release Report (ARERR) for the period of January I 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 IA.
Elevated gaseous releases are not applicable at GGNS as reported in Table 1B.
The summation of all known ground-level gaseous release during the reporting period is reported in Table lC.
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 which are not included in the AREOR are included as Attachment I to the ARERR.
The current revision of the Offsite Dose Calculation Manual is included as Attachment II to the ARERR The annual 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.
Page 4                                                                                           Revision 1

II. DETAILED INFORl\lATION A. Regulatory Limits
: 1. IOCFR20 Limits
: a.                                        - 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)
I Li Ki Q i    ~   500 mremlyr Os     average skin dose rate in the current year (mrem/yr) f (L i     1.1 Mi ) 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)
_      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 unrestricted areas from all reactors at the site, shall be limited to 2 x 10-4 microcuries/ml total activity.
Page 5                                                                                               Revision 1

II. DETAILED INFORL\IATION (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
3.17 X 10-8 Li Mi X/Q' Qi ::; 5 mrad/qtr
::; 10 mrad/yr D     air dose due to beta emissions from noble gases p
3.17 x 10-8 Li Ni X/Q' Qi              10 mrad/qtr
::; 20 mrad/yr where the terms are defined in the GGNS ODCM.
: b.                                                       - The dose to an individual from tritium, 1-131,1-133 and radioactive material in particulate form with half-lives                     than 8 days in gaseous effluents shall be such that:
Dp    dose to an individual from triti urn, 1-131, 1-133 and radionuclides in particulate form with half-lives greater than 8 days (mrem) 3.17 x 10-8 Li Ri W' Qi ::; 7.5 mremlqtr 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      ,1tl Cil F1 ]        ::; 1.5 mrem/qtr Total Body 1=1
::; 5 mrem/qtr Any Organ
::; 3 mrem/yr Total Body
::; 10 mrem/yr Any Organ where the terms are defined in the GGNS ODCM.
Page 6                                                                                                   Revision 1

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  mrem/yr, Total Body or any Organ except Thyroid
                       ~75  mrem/yr, Thyroid
                       ~IO  mrad y/qtr or ~20 mrad        Fission and Activation Gases
                       ~20  mrad Wqtr or ~40 mrad p/yr, Fission and Activation Gases
                       ~15  mrem/qtr or ~30 mrem/yr, any Organ, Iodine and Particulates
                       ~3  mremlqtr or  ~6 mrem/yr, Total Body, Liquid Effluents
                       ~l 0 mrem/qtr or ~20 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.I.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.
Page 7                                                                                             Revision 1

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:
Tables 10 and 2C          sampling frequencies and Lower Limit of Detection requirements for the analysis of gaseous and liquid effluent streams, respectively.
Values in the attached tables          as zero do not necessarily imply that the radionuclides were not            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:
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 for dose release rate calculations due to effluent releases as given in Section II.A.! 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 j = isotopic calibration factor for isotope i OJ = concentration of isotope i in the grab sample in /-1Ci/ml.
m   = net monitor reading associated with the effluent stream (determined at the time of grab sampling).
Page 8                                                                                              Revision 1

II. DETAILED INFORlVIATION (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. Ifno activity is detected in the grab sample, the calibration factor defaults to a historical mixture of Kr-88, Xe- 133, Xe- 135m, Xe-l     and Xe- I38.
: 2. For Particulates and Radioiodines At a minimum, the following radioiodines and radioactive materials in particulate form to be considered are:
Mo-99 Cs-134 Cs-137 Ce-141 Ce-144 1- 131 1-133
: 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 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 10, "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 11.30 Curies released per year in gaseous form was obtained by estimation using EPRI spreadsheet B\VR Source Term Calculation (MAL-1)_rl and the information in NEAD-NS-ll-0060-Revl-EC42519 and adjusted by 236 full power production days. Carbon-14 curies are reported in Tables lA and lC 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.
Page 9                                                                                           Revision 1

II. DETAILED INFORMATION (CONT'D)
: 5. For Batch Releases: Liquid Effluents At a minimum, the radionuclides listed below are considered when evaluating liquid effluents:
5r-90 Mo-99
[-13 I Cs-I34 Cs-137 Ce-141 Ce-I44 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
: a. Number of releases Time Period (in minutes)
: b. Total for all batches
: c. Max time for a batch
: d. Av time for a batch
: e. Min time for a batch
: 2. Gaseous No batch releases occurred during the report period.
Page 10                                                                                          Revision 1

II. DETAILED INFORMATION (CONT'D)
F. Abnonnal Releases I. Liquid
: a. Number of Releases:                    o
: b. Total Activity Released:               O.OOE+OO Ci No abnonnal liquid releases were identified for this reporting period.
: 2. Gaseous
: a. Number of Releases:                    o
: b. Total Activity Released:               O.OOE+OO Ci No abnormal liquid releases were identified for this reporting period.
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              Al ha 2.60E+OI        2.60E+OI              2.60E+OI            2.60E+OI 6.80E+OI        6.50E+OI              6.lOE+OI            9.20E+Ol 7.30E+Ol        7.00E+Ol              6.60E+OI            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 gennanium detectors, the least-readily-detectable radioisotope is used to detennine 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      AI ha       Tritium 3.20E+OI          2.30E+OI        2.20E+OI      2.20E+OI     2.30E+Ol 6.lOE+OI          6.70E+OI        6.50E+Ol      l.OIE+02     6.20E+Ol 6.90E+OI          7.10E+OI        6.90E+Ol      I.03E+02     6.60E+OI Page 11                                                                                                 Revision 1

II. DETAILED INFORlVIATION (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+0 1. Sampling errors include uncertainty associated with mixing and representative sampling.
H. Solid Radioactive Waste Shipments See Table 3 for shipment information.
L   Meteorological Data The data recovery for the reporting period was 99.8%. The predominant wind direction was from the Northeast approximately 11.3% of the time. The predominant stability class was class "0" approximately 29.6% of the time.               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 inoperable for> 14 days per Limiting Condition for Operation 1-0TS-12-0030. This was documented in Condition Report GGN-2012-06059.
ODeM action 6.3.9 8.3 has a completion time of 14 days to restore channel to operable, which was exceeded at 12:46 on April         2012.. Exceeding this completion time requires entry into Condition 0 with required action 0.1 to immediately suspend Liquid Radwaste releases and action 0.2 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 occurred and was documented in Condition Report GGN-2012-06007.
K. Annual Sewage Disposal Summary There were 2 sewage sludge shipments in 2012 consisting of 8 8-25 boxes that were shipped to EnergySolutions for Green is Clean.
Page 12                                                                                          Revision 1

III. RADIATION DOSE 

==SUMMARY==

Indicated below is the annual summary of offsite doses 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 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.
2012 Li uid Effluent Dose (mrem) 5t 1 Qtr        2nd Qtr       3rd Qtr      4th Qtr      TOTAL 1.61 E-O 1     1.26E-0 1    1.55E-02                 2.68E-Ol 2.74E-Ol      3.09E-OI     3.97E-02      1.23E-02    5.64E-Ol 4.81 E-03      1.52E-03     1.02E-03     1.29E-03    8.03E-03 1.18E-OI       1.82E-Ol    2.39E-02     6.52E-03     2.98E-Ol 2.61 E-02     1.03E-02     2.25E-03     2.12E-03     3.55E-02 9.48E-02       1.69E-0 I   2.58E-02      1.22E-02    2.76E-OI 1.63E-0 1     1.54E-0 1     1.95E-02    6.53E-03     3.02E-Ol 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-I4 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.
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III. RADIATION DOSE       SU~IMARY       (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 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.
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 determined daily during the reporting period and represent the maximum possible dose rate received by members of the public.
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 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 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.
Page 14                                                                                           Revision 1

III. RADIATION DOSE SUl\1lVIARY (CONT'D)
Carbon-l 4 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. Carbon-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 ofCarbon-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-l 4 is dispersed as a gas (C0 2) to the garden location, where it is then incorporated into plant material.
Carbon-14 dose is calculated 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 Iodine, Tritium & Particulates (excluding Carbon-14)
Child (mrem)                   1.08E-02       l.66E-03        5.81E-03     1.12E-02    2.95E-02 Organ                      Thyroid        Thvroid          Thyroid      Thyroid     Thyroid Applicable Limit                    7.5            7.5              7.5         7.5          15 Percent of Limit              l.45E-0 1      2.2IE-02         7.75E-02     l.49E-01    l.97E-OI Iodine, Tritium & Particulates (including Carbon- 14)
Child (mrem)                  l.45E+00       3.09E-02         2.68E+00    2.90E+00    7.06E+00 Organ                       Bone           Bone             Bone        Bone        Bone Applicable Limit                    7.5            7.5              7.5         7.5          15 Percent of Limit               l.93E+OI       4.12E-OI        3.57E+OI     3.87E+OI    4.7IE+OI y Dose Rate (mremfyr)      3.03E-02        3.8IE-OI         5.90E-OI    4.7IE-Ol Applicable Limit                  500             500             500          500 Percent of Limit             6.06E-03        7.62E-02         U8E-OI      9.42E-02 Skin Dose Rate (mrem/yr)           7.33E-02       7.34E-OI         8.53E-OI    6.98E-OI Applicable Limit                  3000           3000             3000        3000 Percent of Limit             2.43E-03        2.45E-02         2.84E-02    2.33E-02 Gamma Air Dose*                  9.23E-03       6.34E-02         l.98E-OI     1.52E-OI   4.23E Applicable Limit                     5              5                5           5           10 Percent of Limit              I.85E-OI       l.27E+00        3.96E+00     3.05E+00    4.23E, Beta Air Dose*                 1.3IE-02       6.67E-02         7.44E-02    6.20E-02    2.16E Applicable Limit                    10             10               10          10          20 Percent of Limit              l.3IE-01       6.67E-OI        7.44E-OI     6.20E-OI    l.08E t Radiation (mrem)                0.0            0.0             0.1          0.0         0.1
            *Measurement umts are mrad Page 15                                                                                                      Revision 1

IV. OFFSITE DOSE CALCULATION MANUAL/
RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES A. affsite Dose Calculation Manual (aDCM)
Revisions 38 and 39 of the aDCM were issued in 2012. The revisions included Description of Change(s)               Revision     Month/Year       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     i, vii, note h. Note h is to acknowledge    Turbine                                   viia, viib, Building roofhatches 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 aDCM 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.
Page 16                                                                                     Revision 1

TABLEIA ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 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+01     1.74E+02  1.54E+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+OO  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+00 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-03   4.51E-02  4.81E-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-05  6.83E-06  7.18E-06   7.20E-06
: 3. Percent of TS Limit %          1. 42E-03    1.99E-03  2.37E-03  5.41E-03   5.37E-03 Tritium
: 1. Total Release       Ci         7.01E+00     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 Gross Alpha Ci        9.59E-08     6.59E-07  6.55E-08  7.93E-08   9.00E-07 8.39E-08  8.25E-09  9.97E-09   2.85E-08 Page 17                                                                              Revision 1

TABLEIB ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT I GASEOUS EFFLUENTS ELEVATED RELEASES JANUARY - DECEMBER 2012 (Not Applicable   GGNS Releases Are Considered Ground-Level)
Page 18                                                              Revision 1

TABLEIC ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT I GASEOUS EFFLUENTS        GROUND-LEVEL RELEASE-CONTINUOUS REPORT FOR 2012          Units     QTR 1      QTR 2      QTR 3    QTR 4     YEAR Fission and Activation Gases AR-4l                   Ci        4.l6E-02   1.08E-Ol   3.49E+Ol 1. 95E+Ol 5.46E+Ol KR-85M                 Ci        2. 65E+00  4.76E-02   2.58E+Ol 1.68E+Ol  4.53E+Ol KR-87                  Ci        O.OOE+OO   2.4lE-Ol  1.0lE+00  6.23E+00  7.48E+00 KR-88                  Ci        8.02E-02   3.53E+00  3.79E+Ol  3.23E+Ol  7.38E+Ol KR-89                  Ci        O.OOE+OO   l.48E+00  l.14E-01  O.OOE+OO  l.59E+00 XE-l33                  Ci        l.60E+00   7.89E+01  2.95E+01  l.92E+Ol  l.29E+02 XE-l35                  Ci        1. 48E+00  7.56E+01  2.l6E+01  1.47E+Ol  l.l3E+02 XE-l35M                 Ci        l.22E+00   9.34E+00  2.57E+00  1.71E+00  l.48E+01 XE-137                  Ci        3.12E+00   1.33E+00  1.03E-Ol  O.OOE+OO  4.56E+00 XE-l38                  Ci        3.24E+00   3.74E+00  7.09E-Ol  3.88E-01  8.08E+00 Totals for Period ... Ci        l.35E+01   l.74E+02  1.54E+02  1.llE+02  4.53E+02 Iodines 1-131                  Ci        1.91E-04   5.02E-06  2.63E-05  1.96E-04  4.l8E-04 1-133                  Ci        6.58E-04   1.16E-05  3.05E-04  4.30E-04  1.40E-03 1-135                  Ci        7.75E-05   O.OOE+OO  4.88E-04  4.77E-05  6.l3E-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+OO  3.29E-06  3.29E-06 BA-140                  Ci        1.4lE-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+OO  O.OOE+OO  O.OOE+OO  1.53E-06 CS-l34                  Ci        O.OOE+OO   O.OOE+OO  O.OOE+OO  O.OOE+OO  O.OOE+OO CS-l37                  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-l06                  Ci        O.OOE+OO   O.OOE+OO  3.32E-05  8.11E-07  3.40E-05 SR-89                   Ci        1.01E-05   1.2lE-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.l0E-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-05  5.43E-05  5.7lE-05  2.28E-04 Other H-3                     Ci        7.01E+00   1.58E+00  5.06E+00  7.50E+00  2.11E+Ol C-14                    Ci        2.32E+00   5.00E-02   4.29E+00 4.64E+00  1.13E+Ol Gross Alpha             Ci        9.59E-08   6.59E-07  6.55E-08  7.93E-08  9.00E-07 Page 19                                                                              Revision 1

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             Type                       of Detection Gaseous Release Type              Frequency           Frequency                                     (LLD)
( uCi/ml)a A. ( I) Radwaste Building                 31 Days              31 Days       Principal Gamma Emitters Ventilation Exhaust         Grab Sample (0                                      ~)
H-3 (2) Fuel H(l1Iulill~ Area         Continuous (d)( 0       7 Days (c)                 1-131              lxlO'I2 Ventilation Exhaust                               Charcoal Sample               1-133              IxlO'w (3) Containment                  Continuous (d)(f)        7 Days (c)      Principal Gamma Emitters      IxlO- 11 Ventilation Exhaust                              Particulate Sample      (e) (I-13I, Others)
(4A) Turbine Building            Continuous (d)(f)   31 Days Composite           Gross Alpha            IxlO- 11 Ventilation Exhaust                              Particulate Sample (4B) Turbine Building Occasional                  Continuous (d)(f)   92 Days Composite            Sr-89, Sr-90          IxlO- 11 Release Point(g)                                 Particulate Sample (when in service)
Continuous (f)     Noble Gas Monitor   Noble Gases Gross Beta or     Ix 10-6 Gamma B. (1) Offgas Post                     31 Days Grab           31 Days        Principal Gamma Emitters      Ix 10-4 Treatment Exhaust.               Sample (f)                                      (e) whenever there is flow (2) Standby Gas                   31 Days Grab            31 Days             Principal Gamma          Ix 10'4 Treatment A Exhaust,             Sample (f)                                  Emitters(e) whenever there is flow (3) Standby Gas                    31 Days Grab           31 Days            Principal Gamma Treatment B Exhaust,             Sample (f)                                  Emitters(e) whenever there is flow NOTE: Footnotes mdIcated are lIsted m GGNS ODCM, AppendIx A, Table 6.11.4-1.
Page 20                                                                                                Revision 1

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 2012        Units      QTR 1      QTR 2     QTR 3     QTR 4    YEAR Fission and Activation Products
: 1. Total Release      Ci        2.04E-02    2.94E-02  1.85E-02  1.55E-02 8.38E-02
: 2. Avg. Diluted Conc. 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-02  3.44E-02  3.25E-02 6.46E-02 Tritium
: 1. Total Release       Ci        4.66E+01    1.81E+01  1. 81E+01 1.94E+01 1.02E+02
: 2. Avg. Diluted Conc. 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-01  6.41E-01 6.80E-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 Conc. 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 Ci        O.OOE+OO    O.OOE+OO  O.OOE+OO  O.OOE+OO O.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   liters     3.77E+08   3.94E+08  4.13E+08  2.99E+08 1.48E+09 Page 21                                                                             Revision 1

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-OS 1.05E-03  1.50E-03 AS-76                   Ci        O.OOE+OO    O.OOE+OO  3.14E-OS S.23E-OS  8.37E-OS AU-199                  Ci        7.S2E-06    O.OOE+OO  O.OOE+OO 6.63E-05  7.38E-05 CO-58                   Ci        1.38E-04    1.1IE-04  2.S1E-OS 2.S1E-04  S.24E-04 CO-60                   Ci        6.02E-03    3.31E-03  1.S7E-03 8.46E-04  1.18E-02 CR-51                   Ci        S.9SE-04    3.2SE-OS  S.34E-OS 2.73E-03  3.41E-03 CS-134                  Ci        O.OOE+OO    9.S2E-06  O.OOE+OO O.OOE+OO  9.S2E-06 CS-137                  Ci        8.59E-04    3.35E-04  4.47E-OS 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-OS  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.S1E-OS  9.37E-04
:MN-S4                  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-OS  2.58E-05 PT-19SM                 Ci        O.OOE+OO   O.OOE+OO   O.OOE+OO 1. 94E-OS 1.94E-OS 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-OS   O.OOE+OO 3.39E-05  1.73E-04 SB-12S                  Ci        3.00E-04   1.49E-03   8.80E-OS O.OOE+OO  1.88E-03 SE-75                   Ci        O.OOE+OO   O.OOE+OO   O.OOE+OO 3.34E-06  3.34E-06 SN-117M                 Ci        O.OOE+OO   O.OOE+OO   O.OOE+OO 2.03E-OS  2.03E-05 SR-92                   Ci        2.S3E-06   1.66E-OS   O.OOE+OO 4.S2E-05  6.43E-05 TC~99M                  Ci        7.27E-OS   S.64E-06   4.80E-06 2.39E-06  8.55E-OS W-187                   Ci        2.33E-05   O.OOE+OO   O.OOE+OO O.OOE+OO  2.33E-05 ZN-6S                   Ci        2.29E-03   8.56E-03   1.68E-03 2.70E-04  1.28E-02 ZN-69M                  Ci        2.27E-OS   6.72E-06   5.31E-06 1. 30E-OS 4.77E-05 ZR-97                   Ci        O.OOE+OO   O.OOE+OO   O.OOE+OO 1.54E-OS  1.S4E-OS Totals for Period ... Ci        2.04E-02   2.94E-02   1.85E-02 1.S5E-02  8.38E-02 Tritium H-3                     Ci        4.66E+Ol   1.81E+Ol 1.81E+Ol 1.94E+Ol 1.02E+02 Totals for Period ... Ci        4.66E+Ol 1.81E+Ol 1.81E+Ol 1.94E+Ol 1.02E+02 Dissolved and Entrained Gases XE-133                  Ci        2.68E-03   3.33E-OS   4.83E-04 3.61E-04 3.SSE-03 XE-133M                 Ci        3.77E-OS   O.OOE+OO   O.OOE+OO O.OOE+OO 3.77E-OS XE-13S                  Ci        9.92E-OS   2.87E-OS   6.36E-04 4.67E-04 1.23E-03 Totals for Period ... Ci        2.81E-03   6.19E-OS 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+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 22                                                                             Revision 1

TABLE2C ENTERGY OPERATrONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANAL YSIS PROGRAM JANUARY DECEMBER2012 Lower Limit Minimum Analysis                               of Detection 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                    {Q)
I~131 Prior to Release         31 Days         Dissolved and Entrained One Batch 1M                           Gases (Gamma Emitters)
Prior to Release          31 Days                    H-3 Each Batch          Composite (b)            Gross Alpha Prior to Release   92 Days Composite            Sr-89. Sr-90 Each Batch                (b)                   Fe~55 B. SSW Basin (Before          Prior to Release   Prior to Release Each Principal Gamma Emitters Blowdown)                     Each Blowdown               Batch                    @
1-131 NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.1-1.
Page 23                                                                                         Revision 1

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
: a. Spent resins, filter sludges,              m3      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,                    m3      3.94E+03      O.OOE+OO O.OOE+OO 25%
contaminated equipment, etc.                  Ci      3.46E+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                   4.19E+Ol     O.OOE+OO  O.OOE+OO
                                                                                       +/- 25%
Bundle                                        Ci      7.93E-02     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 Isoto e ((Treater than O. I %
Ni-63                                                            +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 Page 24                                                                                      Revision 1

TABLE 3 ENTERGY OPERATIONS, lNC.
GRAND GULF NUCLEAR STATlON UNlT 1 SOLID RADlOACTIVE WASTE AND lRRADlATED FUEL SHIPMENTS JANUARY - DECEMBER 2012 (Cont)
: 3. Solid Waste Disposition Number of                                                                                Mode of Destination Name               I    C:ity     State Shi ments                                                                            Trans ortation 68                EnergySolutions(Duratek), LLC          Oak Ridge     TN            Hittman
                                                                                    --+-------il 19            EnergySolutions Gallaher Road Facili       Oak Ridge                   Hittman 10                           Studsvik                      Erwin                     Hittman Description                                   te Type Description 8/120 HIC                 1              Poly HIC RWCU-A ES-21O                  18             Carbon Steel Liner - SRT 20' SEALAND                135                   20FT Sealand Water Tanker               2                     Water tanker ES-210                                   Stainless Steel Liner A              199.4                                     9 (solidification)                                CPS/RWCU-B ES-210 A             199.4                                      3             Empty - Stainless Steel Liner (solidification)
B. Irradiated Fuel Shipments (Disposition)
Page 25                                                                                              Revision 1

ATTACHlVlENT I Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results JANUARY - DECElVlBER 2012 GPI Ground \Yater samples are collected from onsite dewatering wells, DW; monitoring wells, lVIW; observation wells, OW; and sump wells, S\Y. 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 lVlonitoring Program.
No dose to the public is attributed to ground water since wells with results above lVlDA 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 of GGNS-ODCM table 6.12.1-2.
LOCATION                         DATE         TRITIUM (pCilL)                GAMMAlHTD (pCi/L)
OW-OJ                       2/9120] 2             17800                           <MOA OW-Ol                      6113/2012              12800                           <MOA OW-OI                      9112/2012              16800                           <MOA OW-OJ                      1117/2012              12600                           <MOA OW-07                      9112/2012              6550                            <MOA OW-07                      111612012              8350                            <MOA MW-OI                       2/9/2012              <239                            <MOA MW-OI                      6113/2012              <351                            <MOA MW-Ol                      9/1112012               380                            <MOA MW-Ol           OUP        911112012               359                            <MDA MW-OI                      1117/2012              <262                            <MDA MW-08                       2/812012              <326                            <MOA MW-08                      6113/2012              <347                            <MDA MW-08           OUP        6/13/2012              <350                           <MDA MW-09                       2/9/2012              <234                            <MOA MW-09                      6/13/2012              <342                           <MOA MW-lO                      6/13/2012              <337                           <MOA MW-13                      6/20/2012              <284                           <MDA MW-15                      6/2012012              <342                           <MDA MW-18                      6/20/2012              <275                           <MDA MW-21                       6/20/2012              <277                           <MOA MW-23                       2/9/2012              <233                           <MOA MW-23                       6/12/2012              <346                           <MOA Page 26                                                                                              Revision 1

ATTACHMENT I Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results JANUARY     DECEMBER 2012 (Cont)
LOCATION                    DATE        TRITIUM (pCi/L)           GAMMAlHTD (pCi/L)
MW-IOOB                  2/912012          <234                         <MDA MW-IOOB                 6/12/2012          <341                         <MDA MW-IOOB                 9112/2012          <204                         <MDA MW-IOOB                 1118/2012          <263                         <MDA MW-102B                  2/9/2012          <238                         <MDA MW-I02B                 6112/2012          <347                         <MDA MW-I02B                 9/12/2012            347                        <MDA MW-I02B                 1117/2012           268                         <MDA MW-103A                 9112/2012          <218                         <MDA MW-103B                  2/8/2012          <235                         <MDA MW-103B                 6/13/2012          <339                         <MDA MW-103B                 9/12/2012          <215                         <MDA MW-103B                 111712012          <271                         <MDA MW-I04B                  2/9/2012          <235                         <MDA MW-104B                 6113/2012          <347                         <MOA MW-I04B                 9113/2012          <219                         <MDA MW-104B                 1117/2012          <268                         <MDA MW-105B                  2/9/2012            740                        <MDA MW-105B       OUP        2/9/2012           904                          N/A MW-105B                 6112/2012           560                         <MDA MW-105B                 9/12/2012            773                        <MDA MW-105B                 111812012            823                        <MDA MW-105B       OUP       1118/2012           665                          N/A MW-I06B                  2/9/2012          <235                         <MDA MW-I06B                 6/12/2012          <355                         <MDA M\V-I06B                9112/2012          <213                         <MDA MW-I06B                 1117/2012          <269                         <MDA MW-I07B                  2/8/2012          3430                         <MDA MW-I07B                 6112/2012           2430                        <MDA MW-I07B                 9/12/2012          2440                         <MDA MW-107B                 111612012           2070                        <MDA MW-108B                  2/8/2012           612                         <MDA MW-108B                 6113/2012           604                         <MDA MW-I08B                 9112/2012           983                         <MDA MW-108B                 1116/2012           994                         <MDA MW-108B       OUP       1116/2012            868                         N/A MW-109B                  2/8/2012           699                         <MDA MW-I09B                 6/13/2012          <344                         <MDA MW-I09B                 9/12/2012           816                         <MDA MW-I09B                 111612012           591                         <MDA Page 27                                                                                 Revision 1

ATTACHlVlENT I Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results JANUARY - DECEl\tlBER 2012 (Cont)
LOCATION                    DATE        TRITIUM (pCi/L)           GAMM.A/HTD (pCi/L)
MW~110B                   2/9/2012           <229                         N/A MW~110B                 6/13/2012           <341                        <MDA MW-IIOB                  9/11/2012           <218                        <MDA MW~IIOB                 11/8/2012           <278                        <MDA M\V~I11B                1/17/2012          10100                        <MDA MW-I11B                  6/13/2012          18400                        <MDA MW-II1B                  9/11/2012           11000                       <MDA MW-II1B                 1117/2012           8920                        <MDA MW-112B                  2/9/2012           <229                        <MDA MW-112B                 6/13/2012           <347                        <MDA MW-112B                 9/1112012           <220                        <MDA MW-112B                 1117/2012           <268                        <MDA MW-113B                  2/9/2012            356                        <MDA MW-I13B                 6/13/2012           <350                        <MDA MW-113B       DUP       6/13/2012           <348                        <MDA MW-113B                 9/12/2012           <211                        <MDA MW-113B                  1117/2012           352                        <MDA MW-114B                  2/9/2012           2340                        <MDA MW-114B                 6/13/2012           3260                        <MDA MW-114B                 9/12/2012           2460                        <MDA MW-1I4B       DUP       9/12/2012           2950                        <MDA MW-114B                  1117/2012          2970                        <MDA MW-115B                  2/9/2012           5630                        <MDA MW-115B       DUP        2/9/2012           4510                        <MDA MW~115B                 6/13/2012            1680                       <MDA MW-1I5B                 9/12/2012           5230                        <MDA MW-115B                  1117/2012          2510                        <MDA MW-118B                  1/17/2012           491                        <MDA MW-118B                 6/13/2012            1700                       <MDA MW-118B                 9/11/2012            1050                       <MDA MW-118B                  11/6/2012           1060                       <MDA MW-I007B                 6/19/2012           <282                        <MDA MW-I007C                 6/14/2012           <286                        <MDA MW-I009B                 6/19/2012           <283                        <MDA MW-I012C                 6/14/2012           <281                        <MDA MW-IOI2C       DUP       6/14/2012            <285                       <MDA MW-1019B                  6/20/2012          <336                        <MDA Page 28                                                                                 Revision 1

ATTACHMENT I Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results JANUARY - DECEMBER 2012 (Cont)
LOCATION                   DATE         TRITIUM (pCiIL)             GAMMAlHTD (pCi/L)
MW-I020C                 6114/2012             <289                      <MDA MW-I022B                 6119/2012             <334                      <MDA MW-I024C                 6112/2012             <341                      <MDA MW-I026B                 6/14/2012             <289                      <MDA MW-I026B                 6/19/2012             <288                      <MDA MW-I027B                 6/20/2012              372                      <MDA M\V-I027C                611412012             <286                      <MDA MW-I027C       DUP       6/14/2012             <289                      <MDA MW-I042C                 611212012             <341                      <MDA MW-1045B                 6/14/2012             <337                      <MDA MW-1045B       DUP       611412012             <340                      <MDA MW-I082C                 6/12/2012             <341                      <MDA MW-1134C                 611212012             <342                      <MDA OW-05                 6119/2012             <288                      <MDA OW-209B                  2/9/2012             5980                      <MDA OW-209B                 6112/2012             2650                      <MDA OW-209B                 911112012             2430                      <MDA OW-209B                 1118/2012             2210                      <MDA OW-1008                 6119/2012             <287                      <MDA OW-1I08                 6/19/2012             <332                      <MDA SW-I03A                 6/14/2012             <338                      <MDA SW-103A                 911212012             <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)
(N/A = not analyzed Page 29                                                                                 Revision 1

ATTACHMENT II Offsite Dose Calculation ~Ianual The Grand Gulf Nuclear Station Offsite Dose Calculation Manual was previously submitted on April 30,2013 Page 30                                                                                               Revision 1}}