GNRO-2017/00043, Amended Annual Radioactive Effluent Release Report (ARERR) for 2015

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Amended Annual Radioactive Effluent Release Report (ARERR) for 2015
ML17186A293
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 07/05/2017
From: Ellis D
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2017/00043
Download: ML17186A293 (43)
v • d • e


Text

~Entergy Entergy Operations, Inc.

P.O. Box 756 Port Gibson, MS 39150 David Ellis Acting Regulatory Assurance Manager Grand Gulf Nuclear Station Tel. (601) 437-2489 GNRO-2017/00043 July 5,2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852

SUBJECT:

Amended Grand Gulf Nuclear Station (GGNS) Annual Radioactive Effluent Release Report (ARERR) for 2015 Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29

REFERENCES:

1. Entergy Letter to NRC, "Grand Gulf Nuclear Station 2015 Annual Radioactive Effluent Release Report (ARERR)," dated April 19, 2016 (GNRO-2016/00020) (ML16202A235)
2. Entergy Letter to NRC, "Supplement to Grand Gulf Nuclear Station 2015 Annual Radioactive Effluent Release Report (ARERR)," dated July 20, 2016 (GNRO-2016/00039) (ML16202A235)

Dear Sir or Madam:

Grand Gulf Nuclear Station (GGNS) discovered that one of the steps required for restoration of the Offgas Post Treatment Radiation Monitor was not completed in March of 2015. Grab sampling of the process stream was terminated when the Limiting Condition for Operation (LCO) was improperly exited. Consequently, the site failed to meet the sampling requirements of Offsite Dose Calculation Manual (ODCM) 6.3.10, "Radioactive Gaseous Effluent Monitoring Instrumentation," for a period of 4 days, 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />. During this period, the monitor provided continuous and accurate measurement of the process stream and the control room alarm was functional, with no alarms received. When the error was identified, the LCO Action was re-entered and grab sampling of the process stream was initiated until the monitor was returned to operable status.

There were no unmonitored gaseous effluent releases to the environment during this period. The incident is documented in the GGNS Corrective Action Program and is to be included in the Annual Radioactive Effluent Release Report (ARERR). This omission is corrected in Table 6A - Supplemental Information, included in its entirety as Attachment II to the amended 2015 ARERR (Attachment 1 to this letter).

Also, in February of 2017, GGNS identified an error that occurred during a software upgrade to the radwaste shipping database. Some documentation was inadvertently omitted. This is corrected by Table 3 - Supplemental Information, also included in its entirety as Attachment II to the revised 2015 ARERR (Attachment 1 to this letter).

GNRO-2017/00043 Page 2 of 3 This letter contains no new Regulatory Commitments.

Should you have any questions concerning the content of this letter, please contact David Ellis at 601-437-2489.

DRElsas : Amended Grand Gulf Nuclear Station (GGNS) Annual Radioactive Effluent Release Report (ARERR) for 2015

GNRO-2017/00043 Page 3 of 3 cc:

Mr. Kriss M. Kennedy U.S. Nuclear Regulatory Commission Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Mr. Siva Lingham U.S. Nuclear Regulatory Commission Mail Stop OWFN 8 B1 Rockville, MD 20852-2738 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 Dr. Mary Currier, M.D., M.P.H State Health Officer Mississippi Department of Health P.O. Box 1700 Jackson, MS 39215-1700 Email: mary.currier@msdh.ms.gov

Attachment 1 to GNRO-2017/00043 Amended Grand Gulf Nuclear Station (GGNS) Annual Radioactive Effluent Release Report (ARERR) for 2015

Ii:

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ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2015 - DECEMBER 31,2015 Prepared By: ~=Count Room Specialist Date Reviewed By:

.<<~ger :dL-Tolbert Date ChemStaff

'1- Ill-Ib Approved By: Richard Sumrall Date Chemistry Manager env*teclARERR01 TABLE OF CONTENTS SUBJECT PAGE I. INTRODUCTION 4 II. DETAILED INFORMATION 5 A. Regulatory Limits 5

1. ODCM Control 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 8 D. Measurements and Approximations of Total Activity 8
1. For Fission and Activation Gases 9
2. For Particulates and Radioiodines 10
3. For Continuous Releases 10
4. For Batch Releases: Gases 10
5. For Batch Releases: Liquid Effluents 11 E. Batch Releases 11
1. Liquid 11
2. Gaseous 11 F. Abnormal Releases 12
1. Liquid 12
2. Gaseous 12 env-teclARERR01 TABLE OF CONTENTS (CONT'D)

SUBJECT PAGE G. Estimate of Total Error 12

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

SUMMARY

14 A. Water-Related Exposure Pathway 14 B. Airborne-Related Exposure Pathway 14 IV. OFFSITE DOSE CALCULATION MANUAL/RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES 17 A. Offsite Dose Calculation Manual (ODCM) 17 B. Radioactive Waste Treatment Systems 17 LIST OF TABLES PAGE liLA 2015 Liquid Effluent Dose 14 III.B 2015 Airborne Effluent Dose 16 1A Gaseous Effluents - Summation of All Releases 18 1B Gaseous Effluents - Elevated Releases 19 1C Gaseous Effluents - Ground-Level Releases - Continuous 20 1D Radioactive Gaseous Waste Sampling and Analysis Program 21 2A Liquid Effluents - Summation of All Releases 22 28 Liquid Effluents - Continuous and Batch Modes 23 2C Radioactive Liquid Waste Sampling and Analysis Program 24 3 Solid Radioactive Waste and Irradiated Fuel Shipments 25 ATTACHMENTS PAGE Attachment I - Nuclear Energy Institute, NEI, Groundwater Protection Initiative 28 Sample Results Attachment II - Table 6A, Supplemental Information 36 env-teclARERR01 I. INTRODUCTION This Annual Radioactive Effluent Release Report (ARERR) for the period of January 1 through December 31, 2015, 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 18.

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 28.

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 annual summary of meteorological data (joint 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-teclARERR01 II. DETAILED INFORMATION A. Regulatory Limits

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

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

,

= X/Q Li Ki Q i :5: 500 mrem/yr D, = average skin dose rate in the current year (mrem/yr)

I

= ~j (t, + 1.1 Mi ) Q j :5: 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 (mremlyr)

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

c. Liquid Effluents - The concentration of radioactive materials released in liquid effluents to unrestricted areas from the site shall not exceed at any time ten times the values specified in 10CFR20, Appendix 8, 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.

env-teclARERR01 II. DETAILED INFORMATION (CONT'D)

2. 1OCFR50, 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 Lj Mj X/Q' Qi s 5 mrad/qtr s 10 mrad/yr D~ = air dose due to beta emissions from noble gases

= 3.17 x 10-8 Lj Nj X/Q' Qi s 10 mrad/qtr

20 mrad/yr where the terms are defined in the GGNS ODCM.
b. Radioiodines, Tritium and Particulates - The dose to an individual from tritium, 1-131, 1-133 and radioactive material in particulate form with half-lives greater than 8 days in gaseous effluents shall be such that:

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

= 3.17 x 10-8 Lj Rj W' Qj ::;; 7.5 mrem/qtr Any Organ

15 mrem/yr Any Organ where the terms are defined in the GGNS ODCM.
c. Liquid Effluents - The dose from radioactive materials in liquid effluents shall be such that:

m DTau = L [A jTau L ~tl Cjl FI ]  ::;; 1.5 mrem/qtr Total Body j 1=1

5 mremlqtr Any Organ
3 mrem/yr Total Body
10 mrem/yr Any Organ where the terms are defined in the GGNS ODCM.

env-teciARERR01 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 p/qtr or
:;40 mrad p/yr, Fission and Activation Gases
15 mrem/qtr or
:;30 mrem/yr, any Organ, Iodine and Particulates
3 mrem/qtr or
:;6 mrem/yr, Total Body, Liquid Effluents
10 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.1.a. In this case, the ECls are actually determined by the dose factors in Table 2.1-1 of the GGNS ODCM.

Gaseous dose rates rather than Effluent Concentration Limits are used to calculate permissible release rates for gaseous releases. The maximum permissible dose rates for gaseous releases are defined in the GGNS ODCM 6.11.4.a as 500 mremlyr (Total Body) and 3000 mrem/yr (Skin) and in 6.11.4.b as 1500 mremlyr (Organ).

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.

env-teclARERR01 II. DETAILED INFORMATION (CONT'D)

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

The GGNS ODCM limits the instantaneous dose equivalent rates due to the release of noble gases to less than or equal to 500 mrem/year to the total body and less than or equal to 3000 mrem/year to the skin. The average beta and gamma energies of the radionuclide mixture in releases of fission and activation gases as described in Regulatory Guide 1.21, "Measuring, Evaluation, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," may be used to calculate doses in lieu of more sophisticated software. The GGNS radioactive effluent programs employs the methodologies presented in U.S. NRC Regulatory Guide 1.109 "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 and NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, October 1978. Therefore, average energies are not applicable to GGNS.

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 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 10 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.

env-teclARERR01 II. DETAILED INFORMATION (CONT'D)

1. For Fission and Activation Gases The principal gamma emitters for which the LLD specification in Table 1D applies exclusively are:

Kr-87 Kr-88 Xe-133 X-e-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 for dose release 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:

Cj = isotopic calibration factor for isotope i Uj = concentration of isotope i in the grab sample in ~Ci/ml.

m = net monitor reading associated with the effluent stream (determined at the time of grab sampling).

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

env-teclARERR01 II. DETAILED INFORMATION (CONT'D)

2. For Particulates and Radioiodines The principal gamma emitters for which the LLD specification in Table 1D applies exclusively are:

Zn-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

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 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 17.4 Curies released this year in gaseous form was obtained by estimation using EPRI spreadsheet BWR Source Term Calculation (MAL-1)_r1 and the information in NEAD-NS 0060-Rev1-EC42519 and adjusted by 347.1 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 quarter.

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

env-teclARERR01 II. DETAILED INFORMATION (CONT'D)

5. For Batch Releases: Liquid Effluents The principal gamma emitters for which the LLD specification in Table 2C applies exclusively are:

H-3 Sr-90 Mn-54 Mo-99 Fe-55 1-131 Co-58 Cs-134 Co-60 Cs-137 Fe-59 Ce-141 Zn-65 Ce-144 Sr-89 Representative pre-release grab samples are obtained and analyzed as required by Table 2C. Isotopic analyses are performed by gamma spectral analysis utilizing high-resolution germanium detectors. Aliquots of each pre-released sample, proportional to the waste volume released, are composited in accordance with the requirements of Table 2C. Strontium-89/90 and Iron-55 values are obtained by individual chemical separations. Strontium-89/90 is analyzed using gas flow proportional techniques. Iron-55 is analyzed using low energy photon 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 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year 38 20 19 21 98
b. Total for all batches 9.58E+03 5.52E+03 5.61E+03 6.26E+03 2.70E+04
c. Max time for a batch 3.20E+02 3.20E+02 3.07E+02 3.16E+02 3.20E+02
d. Av time for a batch 2.52E+02 2.76E+02 2.95E+02 2:98E+02 2.75E+02
e. Min time for a batch 1.35E+02 1.01E+02 2.78E+02 2.45E+02 1.01E+02
f. Avg. dil. water flow gpm 4.75E+03 5.69E+03 6.26E+03 5.49E+03 5.41E+03
2. Gaseous No batch releases occurred during the report period.

env-teciARERR01 II. DETAILED INFORMATION (CONT'D)

F. Abnormal Releases

1. Liquid
a. Number of Releases: o
b. Total Activity Released: O.OOE+OO Ci No abnormal 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 gaseous 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 &

Dissolved & Entrained Gross Activation Tritium Gases Alpha Products 2.60E+01 2.60E+01 2.60E+01 2.60E+01 6.80E+01 6.50E+01 6.10E+01 9.20E+01 7.30E+01 7.00E+01 6.60E+01 9.50E+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 germanium detectors, the least-readily-detectable radioisotope is used to determine the counting error. Calibration errors are calculated by summing the errors associated with the calibration of a particular instrument with a radioactive source.

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

env-teciARERR01

II. DETAILED INFORMATION (CONT'D)

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

Fission & Activation Gross Iodine Particulate Alpha Products Tritium 3.20E+01 2.30E+01 2.20E+01 2.20E+01 2.30E+01 6.10E+01 6.70E+01 6.50E+01 1.01E+02 6.20E+01 TOTAL % 6.90E+01 7.10E+01 6.90E+01 1.03E+02 6.60E+01 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 information.

I. Meteorological Data The data recovery for the reporting period was 99.3%. The predominant wind direction was from the North-Northeast approximately 12.0% of the time. The predominant stability class was class "0" approximately 30.4% 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 No reportable instances of inoperability occurred during the reporting period.

K. Annual Sewage Disposal Summary There were no sewage disposals in 2015.

env-teclARERR01 III. RADIATION DOSE

SUMMARY

Indicated below is the annual summary of offsite doses attributable to GGNS during 2015.

Inspection of the values indicates that GGNS releases were within the 10CFR50, Appendix I, design objectives.

Since there are no other fuel cycle facilities within 8 km 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.

Table III.A 2015 Liquid Effluent Dose (mrem)

St 1 Qtr 2nd Qtr. 3rd Qtr 4th Qtr TOTAL Bone 3.12E-03 9.59E-03 O.OOE+OO 1.88E-02 3.18E-02 Liver 8.70E-03 1.63E-02 1.44E-03 3.07E-02 5.74E-02 Thyroid 8.36E-04 9.27E-04 9.09E-04 1.36E-03 4.13E-03 Kidney 5.37E-03 7.02E-03 9.24E-04 1.30E-02 2.63E-02 Lung 1.07E-03 2.42E-03 9.09E-04 3.99E-03 8.56E-03 GI-LLI 7.99E-03 4.06E-03 1.36E-03 7.30E-03 2.02E-02 Applicable Limit 5 5 5 5 10 Percent of Limit 1.74E-01 3.26E-01 2.88E-02 6.13E-01 5.74E-01 Whole Body 4.85E-03 1.05E-02 1.20E-03 1.94E-02 3.62E-02 Appl icable Limit 1.5 1.5 1.5 1.5 3 Percent of Limit 3.23E-01 7.00E-01 8.00E-02 1.29E+00 1.21E+00 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. 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 2015 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-teclARERR01 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 2015 meteorological data. The critical receptor residence was determined to be located in the southwest sector at a distance of 1432 meters (0.89 miles) from the plant. Pathways considered for use in the organ dose calculations are inhalation, ground plane, grass/cow/meat, and vegetation. There is no grass/cow/milk pathway within five miles of GGNS. It was assumed that the age group receiving the maximum dose lived at the residence and that the receptor consumed food products that were raised or produced at the residence. This dose is documented in the following table as two separate entries. The first organ dose entry excludes C-14 while the second entry includes organ dose from tritium, radioiodines, particulates, and C-14.

Average Total Body and Skin Dose Rate Individual total body and skin dose rates from exposure to a semi-infinite cloud of noble gas are computed for a location in the west-northwest sector at a distance of 1207 meters (0.75 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 2015 meteorological data.

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

Air Dose from Gamma and Beta Emissions Air doses from gaseous effluents were calculated for this report using dispersion parameters from the 2015 meteorological data. The highest dispersion factor for an unrestricted area was in the west-northwest sector at the site boundary, 1207 meters (0.75 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 2015 as net exposure normalized to 92 days.

env-teclARERR01 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 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 of 95% 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 to a MEMBER OF THE PUBLIC for the most' age restrictive group (Child) and organ (bone) at the garden location. This dose 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.

Table IlI.B 2015 Airborne Effluent Dose (mrem) 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr TOTAL Iodine, Tritium & Particulates (excludinq Carbon-14)

Child (mrem) 9.14E-03 7.50E-03 7.98E-03 8.85E-03 3.35E-02 Organ Thyroid Thyroid Thyroid Thyroid Thyroid Applicable Limit 7.5 7.5 7.5 7.5 15 Percent of Limit 1.22E-01 1.00E-01 1.06E-01 1.18E-01 2.23E-01 Iodine, Tritium & Particulates (includinq Carbon-14)

Child (mrem) 2.94E+00 3.35E+00 3.38E+00 3.38E+00 1.30E+01 Organ Bone Bone Bone Bone Bone Applicable Limit 7.5 7.5 7.5 7.5 15 Percent of Limit 3.92E+01 4.46E+01 4.50E+01 4.51E+01 8.70E+01 0~~"~11]1 Total Body Dose Rate (mrem/yr) 2.06E+00 1.92E+00 1.69E+00 1.20E+00 Applicable Limit 500 500 500 500 Percent of Limit 4.12E-01 3.84E-01 3.38E-01 2.40E-01 Skin Dose Rate (mrem/yr) 3.16E+00 2.75E+00 2.43E+00 1.72E+00 Applicable Limit 3000 3000 3000 3000 li,;:"j{i::}',::".11 Percent of Limit 1.05E-01 9.17E-02 8.10E-02 5.73E-02 1<,<,'::

Gamma Air Dose* 4.02E-02 7.66E-02 8.16E-02 1.52E-01 3.50E-01 Applicable Limit 5 5 5 5 10 Percent of Limit 8.04E-01 1.53E+00 1.63E+00 3.04E+00 3.50E+00 Beta Air Dose* 3.99E-02 3.94E-02 4.68E-02 1.46E-01 2.72E-01 Applicable Limit 10 10 10 10 20 Percent of Limit 3.99E-01 3.94E-01 4.68E-01 1.46E+00 1.36E+00 Direct Radiation (mrem) 0.0 0.0 0.0 0.4 0.4

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

env-teciARERR01 TABLE 1A ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 201 S Uni ts QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases

1. Total Release Ci 9.1SE+01 8.84E+01 1.10E+02 1.90E+02 4.79E+02
2. Avg. Release Rate uCi/sec 1.18E+01 1.12E+01 1.38E+01 2.39E+01 1.S2E+01
3. Percent of TS Limit
a. Gamma Air  % * * * * *
b. Beta Air  % * * * *
1. Total Release Ci 1. S4E-04 1. 7SE-06 2.61E-OS S.03E-06 1.87E-04
2. Avg. Release Rate uCi/sec 1. 98E-OS 2.22E-07 3.28E-06 6.32E-07 S.94E-06
3. Percent of TS Limit  % * * * *
  • Particulates Half Life >= 8 days
1. Total Release Ci O.OOE+OO O.OOE+OO 2.03E-06 S.33E-06 7.37E-06
2. Avg. Release Rate uCi/sec O.OOE+OO O.OOE+OO 2.S6E-07 6.71E-07 2.34E-07
3. Percent of TS Limit  % * * * *
1. Total Release Ci S.99E+OO 6. 96E+OO 6.94E+OO 8.17E+OO 2.81E+01
2. Avg. Release Rate uCi/sec 7.71E-01 8.8SE-01 8.73E-01 1. 03E+OO 8.90E-01
3. Percent of TS Limit  % * * * *
1. Total Release Ci 3.93E+OO 4.46E+OO 4.S0E+OO 4.S1E+OO 1. 74E+01
2. Avg. Release Rate uCi/sec S.OSE-01 S.68E-01 S.66E-01 S.68E-01 S.S2E-01 Gross Alpha
1. Total Release Ci 3.87E-08 9.82E-09 S.3SE-10 S.06E-08 9.97E-08
2. Avg. Release Rate uCi/sec 4.98E-09 1.2SE-09 6.73E-11 6.36E-09 3.16E-09
  • Applicable limits are expressed in terms of dose. See Table III.B of this report.

env-teclARERR01 TABLE IB ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - ELEVATED RELEASES JANUARY - DECEMBER 2015 (Not Applicable - GGNS Releases Are Considered Ground-Level) env-teclARERR01 TABLE IC ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT I EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - GROUND-LEVEL RELEASE-CONTINUOUS REPORT FOR 2015 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases AR-41 Ci 4.58E+00 1. 01E+01 1.34E+01 1. 61E+01 4.42E+01 KR-85 Ci 4.81E+01 O.OOE+OO O.OOE+OO O.OOE+OO 4.81E+01 KR-85M Ci 5.77E+00 9. 63E+00 8.47E+00 2.63E+01 5.02E+01 KR-87 Ci 6.81E-02 3.72E-01 O.OOE+OO O.OOE+OO 4.40E-01 KR-88 Ci 6. 67E+00 1.18E+01 9.76E+00 2.59E+01 5.41E+01 XE-13lM Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO XE-133 Ci 1.32E+01 3.08E+01 4.23E+01 7.75E+01 1.64E+02 XE-133M Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO XE-135 Ci 1.16E+01 2.25E+01 3.13E+01 3.84E+01 1.04E+02 XE-135M Ci 1.33E+00 2. 65E+00 3.69E+00 4.53E+00 1.22E+01 XE-138 Ci 3.01E-01 6.08E-01 8.38E-01 1. 03E+00 2.78E+00

-------- -------- -------- --------

Totals for Period ... Ci 9.15E+01 8.84E+01 1.10E+02 1.90E+02 4.80E+02 Iodines I-131 Ci 1.54E-04 1. 75E-06 2.61E-05 5.03E-06 1.87E-04 I-133 Ci 3.38E-04 1. 29E-05 1.47E-04 1.64E-05 5.15E-04

-------- -------- -------- --------

Totals for Period ... Ci 4.93E-04 1.47E-05 1.73E-04 2.14E-05 7.02E-04 Particulates Half Life >= 8 days CO-58 Ci O.OOE+OO O.OOE+OO 2.03E-06 3.70E-06 5.74E-06 CO-60 Ci O.OOE+OO O.OOE+OO O.OOE+OO 1.63E-06 1.63E-06

-------- -------- -------- --------

Totals for Period ... Ci O.OOE+OO O.OOE+OO 2.03E-06 5.33E-06 7.37E-06 Other H-3 Ci 5. 99E+00 6. 96E+00 6.94E+00 8.17E+00 2.81E+01 C-14 Ci 3. 93E+00 4.46E+00 4.50E+00 4.51E+00 1.74E+01 Gross Alpha Ci 3.87E-08 9.82E-09 5.35E-10 5.06E-08 9.97E-08 Note: Only radionuclides with positive results were reported.

env-teciARERR01 TABLE 1D ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radioactive Gaseous Waste Sampling and Analysis Program JANUARY - DECEMBER 2015 Lower Limit Sampling Minimum Analysis Type of Activity Analysis of Detection Gaseous Release Type Frequency Frequency (LLD)

( uCi/ml)a Principal Gamma A. (1) Radwaste Building 31 Days 1x10-4 31 Days Emitters (b e)

Ventilation Exhaust Grab Sample (f) 1X1O:S H-3 (2) Fuel Handling Area 7 Days (c) 1-131 1x10-12 Ventilation Exhaust Continuous (d)(f)

Charcoal Sample 1-133 1x10-10 Principal Gamma (3) Containment 7 Days (c) 1x10-11 Continuous (d)(f) Emitters (e)

Ventilation Exhaust Particulate Sample (1-131, Others)

(4A) Turbine Building Ventilation Exhaust 31 Days Composite Continuous (d)(f) Gross Alpha 1x10-11 Particulate Sample (4B) Turbine Building Occasional 92 Days Composite Release Point(g) Continuous (d)(f) Sr-89, Sr-90 1x10-11 Particulate Sample (when in service)

Noble Gases Gross Beta 1x10-6 Continuous (f) Noble Gas Monitor or Gamma B. (1) Offgas Post 31 Days Grab Principal Gamma 1x10-4 Treatment Exhaust, 31 Days Sample (f) Emitters (e) whenever there is flow (2) Standby Gas 31 Days Grab Principal Gamma 1x10-4 Treatment A Exhaust, 31 Days Sample (f) Emitters(e) whenever there is flow (3) Standby Gas 31 Days Grab Principal Gamma 1x10-4 Treatment B Exhaust, 31 Days Sample (f) Emitters(e) whenever there is flow NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.4-1.

env-teclARERR01 TABLE 2A ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 201S Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR

------- -------- -------- -------- -------- --------

Fission and Activation Products

1. Total Release Ci 2.26E-03 2.76E-03 4.72E-03 2.94E-03 1. 27E-02
2. Avg. Diluted Cone. uCi/ml 1. 31E-08 2.32E-08 3.S6E-08 2.27E-08 2.29E-08
3. Percent of Limit  % * * * *
1. Total Release Ci 7.98E+00 1.0SE+01 1.14E+01 1.S0E+01 4.49E+01
2. Avg. Diluted Cone. uCi/ml 4.63E-OS 8.83E-OS 8.60E-OS 1. 16E-04 8.11E-OS
3. Percent of Limit  % * * * *
  • Dissolved and Entrained Gases
1. Total Release Ci O.OOE+OO 1. S2E-OS 8.92E-06 2.73E-04 2.97E-04
2. Avg. Diluted Cone. uCi/ml O.OOE+OO 1. 28E-10 6.72E-11 2.10E-09 S.36E-10
3. Percent of Limit  % * * * *
  • Gross Alpha Radioactivity
1. Total Release Ci O.OOE+OO 9.16E-06 1.61E-OS O.OOE+OO 2.S3E-OS Volume of liquid waste liters 3.33E+06 1.94E+06 1.99E+06 2.17E+06 9.43E+06 Volume of dil. water liters 1. 69E+08 1.17E+08 1.31E+08 1.28E+08 S.44E+08
  • Applicable l~its are expressed in terms of dose. See table III.A of this report env-teclARERR01 TABLE 2B ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - CONTINUOUS AND BATCH MODES REPORT FOR 201S Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases AG-110M Ci 1. 19E-OS 1.71E-06 O.OOE+OO O.OOE+OO 1. 36E-OS AS-76 Ci O.OOE+OO O.OOE+OO O.OOE+OO 9.7SE-OS 9.7SE-OS CO-S8 Ci O.OOE+OO 1.44E-OS O.OOE+OO 4.23E-OS S.67E-OS CO-60 Ci 1.16E-03 2.42E-04 1. 74E-04 4.31E-04 2.01E-03 CS-134 Ci O.OOE+OO S.73E-06 O.OOE+OO O.OOE+OO S.73E-06 CS-137 Ci S.93E-06 S.06E-OS O.OOE+OO 1.11E-04 1.68E-04 FE-SS Ci 6.16E-04 1.77E-03 O.OOE+OO O.OOE+OO 2.39E-03 LA-140 Ci 8.06E-OS O.OOE+OO O.OOE+OO O.OOE+OO 8.06E-OS MN-S4 Ci 8.00E-OS 4.90E-OS 3.31E-OS 1.61E-04 3.23E-04 NA-24 Ci O.OOE+OO 4.73E-OS O.OOE+OO O.OOE+OO 4.73E-OS PT-19SM Ci 1.4SE-OS O.OOE+OO O.OOE+OO O.OOE+OO l.4SE-OS RB-88 Ci 1.14E-04 4.44E-04 4.SlE-03 1.71E-03 6.79E-03 RU-106 Ci O.OOE+OO 2.80E-OS O.OOE+OO 1.87E-04 2.1SE-04 SE-7S Ci O.OOE+OO O.OOE+OO O.OOE+OO 9.48E-06 9.48E-06 ZN-6S Ci 1.7SE-04 1.09E-04 O.OOE+OO 1.84E-04 4.69E-04

-------- -------- -------- --------

Totals for Period ... Ci 2.26E-03 2.76E-03 4.72E-03 2.94E-03 1.27E-02 Tritium H-3 Ci 7. 98E+OO 1. OSE+01 1. 14E+01 1. SOE+01 4.49E+01

-------- -------- -------- --------

Totals for Period ... Ci 7. 98E+OO 1.0SE+01 1. 14E+01 1. SOE+01 4.49E+01 Dissolved and Entrained Gases XE-133 Ci O.OOE+OO 8.43E-06 8.92E-06 1.17E-04 1.3SE-04 XE-13S Ci O.OOE+OO 6.77E-06 O.OOE+OO 1.SSE-04 1.62E-04

-------- -------- -------- --------

Totals for Period ... Ci O.OOE+OO 1.S2E-OS 8.92E-06 2.73E-04 2.97E-04 Gross Alpha Radioactivity ALPHA Ci O.OOE+OO 9.16E-06 1.61E-OS O.OOE+OO 2.S3E-OS

-------- -------- -------- --------

Totals for Period ... Ci O.OOE+OO 9.16E-06 1.61E-OS O.OOE+OO 2.S3E-OS r

env-teclARERR01 TABLE 2C 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 2015 Lower Limit Sampling Minimum Analysis Type of Activity Analysis of Detection Liquid Release Type Frequency Frequency (LLD)

( uCi/ml)(a)

Principal Gamma A. Batch Waste Release Prior to Release Prior to Release 5x10-7 Emitters (d)

Tanks (c) Each Batch Each Batch 1X1O:S 1-131 Dissolved and Entrained Prior to Release 1x10-5 31 Days Gases (Gamma One Batch 1M Emitters)

Prior to Release 31 Days H-3 1x10-5 Each Batch Composite (b) Gross Alpha 1x10-1 Prior to Release 92 Days Composite Sr-89. Sr-90 5x10-8 Each Batch (b) Fe-55 1x1O:S Principal Gamma 5x10-7 B. SSW Basin Prior to Release Prior to Release Emitters (d)

(Before Blowdown) Each Blowdown Each Batch 1x10"b 1-131 NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.1-1.

env-teclARERR01 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 2015 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

Est. Total

1. Type of Waste Unit Class A Class B Class C Error %

3

a. Spent resins, filter sludges, m 1.36E+02 5.72E+00 O.OOE+OO

+/-25%

evaporator bottoms, etc. Ci 1.33E+03 5.87E+02 O.OOE+OO 3

b. Dry compressible waste, m 7.17E+02 O.OOE+OO O.OOE+OO

+/-25%

contaminated equipment, etc. Ci 1.58E-01 O.OOE+OO O.OOE+OO 3

c. Irradiated components, control m O.OOE+OO O.OOE+OO O.OOE+OO

+/-25%

rods, etc. Ci O.OOE+OO O.OOE+OO O.OOE+OO 3

d. Other: Condensate Pre-Coat m 1.80E+01 O.OOE+OO O.OOE+OO

+/-25%

Septa Bundle Ci 3.49E-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.

Isotope (greater than 0.1%) Percent Curies Mn-54 7.47 1.43E+02 Fe-55 62.20 1.19E+03 Co-58 1.05 2.00E+01 Co-60 18.76 3.59E+02 Ni-63 0.42 7.98E+00 Zn-65 9.20 1.76E+02 Ag-110m 0.45 8.58E+00 Cs-137 0.25 4.71E+00 env-teclARERR01 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 2015

b. Dry compressible waste, contaminated equipment, etc.

Isotope (greater than 0.1%) Percent Curies H-3 0.41 6.34E-04 Mn-54 19.86 3.1OE-02 Fe-55 13.45 2.10E-02 Fe-59 0.74 *1.16E-03 Co-58 0.48 7.47E-04 Co-60 43.56 6.80E-02 Ni-63 0.50 7.85E-04 Zn-65 2.72 4.24E-03 Zr-95 5.05 7.88E-03 Nb-95 8.78 1.37E-02 Tc-99 0.47 7.29E-04 Ag-110m 1.50 2.34E-03 Sn-113 0.30 4.61E-04 Cs-137 1.25 1.95E-03 Ce-144 0.97 1.51E-03

c. Irradiated components, control rods, etc.

There were none in 2015.

d. Other: Oil Drum Sealand Isotope (greater than 0.1%) Percent Curies H-3 0.39 1.38E-04 Mn-54 19.66 6.88E-03 Fe-55 13.09 4.58E-03 Fe-59 0.81 2.83E-04 Co-58 0.50 1.75E-04 Co-GO 42.29 1.48E-02 Ni-63 0.49 1.70E-04 Zn-65 2.69 9.41E-04 Zr-95 5.71 2.00E-03 Nb-95 9.97 3.49E-03 Tc-99 0.45 1.58E-04 Ag-110m 1.48 5.19E-04 Sn-113 0.30 1.05E-04 Cs-137 1.21 4.25E-04 Ce-144 0.89 3.12E-04 env-teclARERR01 - 26 -

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 2015 (Cont.)

3. Solid Waste Disposition Number of Mode of Destination Name City State Shipments Transportation 33 EnergySolutions (Bear Creek), LLC Oak Ridge TN Hittman Energy Solutions 4 Oak Ridge TN Hittman Gallaher Road Facility EnergySolutions LLC.

1 Clive UT Hittman Containerized Waste Facility 8 Babcock Services, Inc. Oak Ridge TN Hittman NRC Disposal Number of Description Waste Type Description Class Volume(ftl\3) Containers B 120.3 8/120 HIC 6 Poly HIC - RWCU-A A 205.8 215 liner 16 Carbon Steel Liner - SRT A 90 B-25 24 Metal/DAW A 1180 20' SEALAND 24 DAW/GIC/Oil ES-210 Stainless Steel Liner A 199.4 14 (solidification) CPS/RWCU-B B. Irradiated Fuel Shipments (Disposition)

II NUMBER OF SHIPMENTS I MODE OF TRANSPORTATION I DESTI NATION I I None I

N/A I N/A I

env-teclARERR01 ATTACHMENT I Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results JANUARY - DECEMBER 2015 GPI Ground Water samples are collected from onsite dewatering wells, OW; 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 of GGNS-ODCM table 6.12.1-2.

LOCATION DATE TRITIUM (pCi/L) GAMMA (pCilL)

DW-01 02/26/15 3940 <MDA DW-01 DUP 02/26/15 3360 <MDA DW-01 06/03/15 9960 <MDA DW-01 DUP 06/03/15 8770 <MDA DW-01 08/26/15 7250 <MDA DW-01 12/10/15 3970 <MDA DW-01 RECOUNT 12/10/15 3740 DW-02 01/13/15 <422 <MDA DW-02 02/25/15 <493 <MDA DW-02 03/17/15 <302 <MDA DW-02 04/21/15 <507 <MDA DW-02 OS/20/15 <592 <MDA DW-02 06/03/15 <586 <MDA DW-02 DUP 06/03/15 <582 <MDA DW-02 07/14/15 1100 <MDA DW-02 RECOUNT 07/14/15 832 DW-02 REANALYSIS 07/14/15 892 DW-02 08/25/15 1440 <MDA DW-02 DUP 08/25/15 1290 <MDA DW-02 09/22/15 1630 <MDA DW-02 10/12/15 1100 <MDA DW-02 DUP 10/12/15 989 <MDA DW-02 11/11/15 762 <MDA DW-02 12/09/15 <531 <MDA DW-03 01/13/15 644 <MDA DW-03 02/26/15 1140 <MDA env-tec/ARERR01 LOCATION DATE TRITIUM (pCi/L) GAMMA (pCi/Ll DW-03 03/17/15 596 <MDA DW-03 04/21/15 <506 <MDA DW-03 DUP 04/21/15 656 <MDA DW-03 05/20/15 822 <MDA DW-03 06/03/15 925 <MDA DW-03 07/14/15 711 <MDA DW-03 08/26/15 546 <MDA DW-03 09/22/15 1080 <MDA DW-03 DUP 09/22/15 652 <MDA DW-03 10/12/15 658 <MDA DW-03 11/11/15 <538 <MDA DW-03 12/09/15 1050 <MDA DW-03 RECOUNT 12/09/15 1210 DW-04 01/13/15 774 <MDA DW-04 DUP 01/13/15 666 <MDA DW-04 02/25/15 1060 <MDA DW-04 03/17/15 677 <MDA DW-04 04/21/15 531 <MDA DW-04 05/20/15 673 <MDA DW-04 06/03/15 745 <MDA DW-04 07/14/15 571 <MDA DW-04 08/26/15 731 <MDA DW-04 09/23/15 716 <MDA DW-04 10/12/15 933 <MDA DW-04 11/10/15 1250 <MDA DW-04 12/09/15 707 <MDA DW-04 RECOUNT 12/09/15 868 DW-05 01/13/15 <419 <MDA DW-05 02/25/15 <491 <MDA DW-05 03/17/15 <304 <MDA DW-05 04/21/15 <509 <MDA DW-05 05/20/15 <584 <MDA DW-05 06/03/15 <587 <MDA DW-05 07/14/15 <354 <MDA DW-05 08/26/15 <525 <MDA DW-05 09/22/15 <411 <MDA DW-05 10/12/15 <394 <MDA DW-05 11/11/15 <542 <MDA DW-05 12/09/15 <538 <MDA DW-05 DUP 12/09/15 <541 <MDA env-teclARERR01 LOCATION DATE TRITIUM (pCi/Ll GAMMA (pC ilL)

DW-07 02/27/15 4270 <MDA DW-07 06/04/15 4370 <MDA DW-07 08/25/15 3610 <MDA DW-07 12/08/15 3180 <MDA MW-01 01/13/15 <426 <MDA MW-01 02/25/15 <489 <MDA MW-01 03/17/15 <485 <MDA MW-01 DUP 03/17/15 <491 <MDA MW-01 04/21/15 \ <483 <MDA MW-01 OS/20/15 <583 <MDA MW-01 DUP OS/20/15 <591 <MDA MW-01 06/03/15 <578 <MDA MW-01 07/14/15 <581 <MDA MW-01 08/25/15 523 <MDA MW-01 REANAL YSIS 08/25/15 528 MW-01 09/22/15 888 <MDA MW-01 10/12/15 741 <MDA MW-01 11/11/15 1010 <MDA MW-01 12/10/15 894 <MDA MW-01 DUP 12/10/15 982 <MDA MW-04 01/13/15 <423 <MDA MW-04 02/26/15 <520 <MDA MW-04 03/17/15 <305 <MDA MW-04 04/21/15 <498 <MDA MW-04 OS/20/15 <592 <MDA MW-04 06/03/15 <588 <MDA MW-04 07/14/15 <353 <MDA MW-04 DUP 07/14/15 <351 <MDA MW-04 08/26/15 <517 <MDA MW-04 09/22/15 <399 <MDA MW-04 10/12/15 <392 <MDA MW-04 11/10/15 <538 <MDA MW-04 DUP 11/10/15 <527 <MDA MW-04 12/09/15 <550 <MDA MW-05 01/14/15 <432 <MDA MW-05 02/27/15 <515 <MDA MW-05 03/17/15 409 <MDA MW-05 RECOUNT 03/17/15 551 MW-05 REANAL YSIS 03/17/15 513 MW-05 04/21/15 <504 <MDA MW-05 OS/20/15 <596 <MDA env-teciARERR01 LOCATION DATE TRITIUM (pCi/Ll GAMMA (pCi/Ll MW-05 06/05/15 <587 <MDA MW-05 07/14/15 <356 <MDA MW-05 08/26/15 <515 <MDA MW-05 09/23/15 <403 <MDA MW-05 10/13/15 <395 <MDA MW-05 11/13/15 <533 <MDA MW-05 12/10/15 <553 <MDA MW-06 08/26/15 1520 <MDA MW-06 RECOUNT 08/26/15 1770 MW-06 12/10/15 1090 <MDA MW-1008 08/26/15 <515 <MDA MW-1018 02/25/15 <527 <MDA MW-1018 06/09/15 <568 <MDA MW-1018 DUP 06/09/15 <571 <MDA MW-1018 08/26/15 <515 <MDA MW-1018 12/09/15 <550 <MDA MW-1028 08/26/15 <519 <MDA MW-1038 08/25/15 <525 <MDA MW-1048 08/25/15 <521 <MDA MW-1058 02/25/15 <584 <MDA MW-1058 06/09/15 625 <MDA MW-1058 08/25/15 <517 <MDA MW-1058 12/09/15 <546 <MDA MW-1058 DUP 12/09/15 <548 <MDA MW-1068 02/25/15 <521 <MDA MW-1068 06/09/15 <577 <MDA MW-1068 08/26/15 <506 <MDA MW-1068 DUP 08/26/15 <548 <MDA MW-1068 12/10/15 <539 <MDA MW-1078 02/27/15 1210 <MDA MW-1078 06/04/15 1280 <MDA MW-1078 08/25/15 1570 <MDA MW-1078 12/08/15 1880 <MDA env-teciARERR01 LOCATION DATE TRITIUM (pCi/L) GAMMA (pCi/l)

MW-1088 02/26/15 2730 <MDA MW-1088 06/04/15 1830 <MDA MW-1088 08/25/15 978 <MDA MW-1088 12/09/15 1720 <MDA MW-1088 RECOUNT 12/09/15 1560 MW-1098 .02/27/15 704 <MDA MW-1098 06/04/15 856 <MDA MW-1098 08/26/15 <519 <MDA MW-1098 12/09/15 <546 <MDA MW-1108 02/24/15 <527 <MDA MW-1108 06/09/15 <580 <MDA MW-1108 08/25/15 <523 <MDA MW-1108 12/08/15 <550 <MDA MW-1118 02/26/15 2110 <MDA MW-1118 06/04/15 1460 <MDA MW-1118 08/26/15 1450 <MDA MW-1118 12/10/15 1150 <MDA MW-1128 01/14/15 <421 <MDA MW-1128 02/26/15 <524 <MDA MW-1128 03/17/15 <298 <MDA MW-1128 04/21/15 <508 <MDA MW-1128 OS/20/15 <600 <MDA MW-1128 06/03/15 <587 <MDA MW-1128 07/14/15 <355 <MDA MW-1128 08/26/15 <507 <MDA MW-1128 09/23/15 <395 <MDA MW-1128 10/12/15 <396 <MDA MW-1128 11/13/15 <530 <MDA MW-1128 12/10/15 <530 <MDA MW-1138 01/15/15 <420 <MDA MW-1138 02/26/15 <492 <MDA MW-1138 DUP 02/26/15 <490 <MDA MW-1138 03/17/15 <303 <MDA MW-1138 04/20/15 <502 <MDA MW-1138 DUP 04/20/15 <496 <MDA MW-1138 05/19/15 <585 <MDA MW-1138 05/19/15 <585 <MDA MW-1138 06/09/15 <571 <MDA MW-1138 07/13/15 <572 <MDA env-teciARERR01 LOCATION DATE TRITIUM (pCi/Ll GAMMA (pCilLl MW-1138 08/26/15 <519 <MDA MW-1138 09/23/15 <404 <MDA MW-1138 10/13/15 <391 <MDA MW-1138 11/09/15 <543 <MDA MW-1138 12/08/15 <548 <MDA MW-1148 02/26/15 2680 <MDA MW-1148 06/08/15 2940 <MDA MW-1148 08/26/15 3220 <MDA MW-1148 12/09/15 2370 <MDA MW-1158 02/26/15 586 <MDA MW-1158 06/04/15 2990 <MDA MW-1158 RECOUNT 06/04/15 3720 MW-1158 REANALYSIS 06/04/15 2900 MW-1158 08/26/15 1710 <MDA MW-1'158 12/10/15 1980 <MDA MW-1168 02/26/15 <524 <MDA MW-1168 06/04/15 <571 <MDA MW-1168 08/26/15 <529 <MDA MW-1168DUP 08/26/15 <511 <MDA MW-1168 12/10/15 <554 <MDA MW-1188 02/26/15 854 <MDA MW-1188 06/04/15 <565 <MDA MW-1188 08/26/15 991 <MDA MW-1188 REANALYSIS 08/26/15 896 MW-1188 12/10/15 <548 <MDA MW-1198 02/25/15 <522 <MDA MW-1198 06/09/15 <576 <MDA MW-1198 08/26/15 <524 <MDA MW-1208 02/25/15 <533 <MDA MW-1208 08/26/15 <516 <MDA MW-121 02/24/15 <505 <MDA MW-1218 06/09/15 <566 <MDA MW-1218 08/25/15 <517 <MDA MW-1228 11/24/15 <524 <MDA MW-1228 12/09/15 675 <MDA env-tec/ARERR01 LOCATION DATE TRITIUM (pCi/L) GAMMA (pCi/L)

MW-1228 RECOUNT 12/09/15 663 MW-1228 REANALYSIS 12/09/15 583 MW-1238 11/24/15 <524 <MDA MW-1238 12/09/15 <548 <MDA MW-1007C 09/01/15 <513 <MDA MW-1009C 09/01/15 <513 <MDA MW-1012C 09/01/15 <517 <MDA MW-10168 01/12/15 <436 <MDA MW-10168 02/26/15 <486 <MDA MW-10168DUP 02/26/15 <500 <MDA MW-10168 03/16/15 <301 <MDA MW-10168DUP 03/16/15 <298 <MDA MW-10168 04/20/15 <507 <MDA MW-10168 05/19/15 <596 <MDA MW-10168 06/10/15 <570 <MDA MW-10168DUP 06/10/15 <570 <MDA MW-10168 07/13/15 <353 <MDA MW-10168DUP 07/13/15 <361 <MDA MW-1020C 09/02/15 <508 <MDA MW-10238 01/14/15 <426 <MDA MW-10238 02/26/15 <477 <MDA MW-10238 03/16/15 <301 <MDA MW-10238 04/20/15 <506 <MDA MW-10238 05/19/15 <599 <MDA MW-10238 06/10/15 <575 <MDA MW-10238 07/15/15 <350 <MDA MW-1024C 09/01/15 <512 <MDA MW-1024C DUP 09/01/15 <506 <MDA MW-1027A 02/27/15 <567 <MDA MW-1027A 06/09/15 <585 <MDA MW-10278 01/12/15 <426 <MDA MW-10278 02/27/15 <529 <MDA MW-10278 03/18/15 <291 <MDA MW-10278 04/22/15 <501 <MDA env-teciARERR01 LOCATION DATE TRITIUM (pCi/Ll GAMMA (pCi/Ll MW-10278 OS/21/15 <590 <MDA MW-10278 06/10/15 <565 <MDA MW-1027C 09/02/15 <514 <MDA MW-1042C 08/26/15 <523 <MDA MW-1082C 08/26/15 <522 <MDA MW-1134C 09/02/15 <510 <MDA OW-1108 01/15/15 <419 <MDA OW-1108 DUP 01/15/15 <420 <MDA OW-1108 02/27/15 <522 <MDA OW-1108 03/17/15 <294 <MDA OW-1108 04/22/15 <505 <MDA OW-1108 05/19/15 <588 <MDA OW-1108 06/10/15 <576 <MDA OW-1108 07/15/15 <348 <MDA SW-103A 02/27/15 <536 <MDA SW-103A 06/10/15 <579 <MDA SW-1038 08/25/15 <517 <MDA SW-1038DUP 08/25/15 <515 <MDA SW-1038 12/09/15 <530 <MDA

<MDA - Less than Minimum Detectable Activity DUP - Duplicate sample collected and analyzed RECOUNT - Re-performed same sample count REANALYSIS - Re-performed same sample analysis and counting env-teciARERR01 ATTACHMENT II TABLE 6A ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JANUARY - DECEMBER 2015

5. Effluent Monitor Instrument Operability During the closure review of a completed work order, the site discovered one of the steps required for restoration of the Offgas Post Treatment Radiation Monitor (1017-J013) to operable status was not completed. Specifically, the failure to reconnect a terminal lead previously removed during testing had disabled the monitor's automatic isolation function of the treatment stream during alarm conditions.

The grab sampling of the process stream was terminated when the LCO for the monitor work was improperly exited. Consequently, the site failed to meet the sampling requirements of ODCM 6.3.10 (Radioactive Gaseous Effluent Monitoring Instrumentation) for a period of 4 days, 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />. During this period, the monitor provided continuous and accurate measurement of the process stream and the control room alarm was functional, with no alarms received. When the error was identified, the LCO was re-entered and grab sampling of the process stream was initiated until the disconnected lead was re-connected and the monitor returned to operable status.

There were no unmonitored gaseous effluent releases to the environment during this period. The Offgas treatment system discharges to the Radwaste Building ventilation system, with monitoring provided by the Radwaste Building Vent Radiation Monitor prior to release to the environment.

The incident is documented in Condition Report CR-GGN-2015-1631, and is required by ODCM 6.3.10 step H.2 to be included in the Annual Radioactive Effluent Release Report.

The site failed to include this incident in the initial 2015 ARERR filing. This omission is corrected by the addition of Table 6A - Supplemental Information, which is included in its entirety as Attachment II to the revised 2015 ARERR.

TABLE 3 - Solid Radioactive Waste and Irradiated Fuel Shipments CR-GGN-2017-1409 identified a number of shipments that were deleted in a database by a vendor performing a software upgrade. The database was corrected by manually inputting data using shipping, documentation stored in plant records. The correction affected previously reported Table 3 entries, and the corrected table is included in its entirety in Attachment II of this amended filing.

env-teciARERR01 ATTACHMENT II TABLE 6A - Continued ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JANUARY - DECEMBER 2015 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 2015 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

Est. Total

1. Type of Waste Unit Class A Class B Class C Error %
a. Spent resins, filter sludges, m 3

1.68E+02 5.72E+00 O.OOE+OO evaporator bottoms, etc. +/-25%

Ci 1.33E+03 5.87E+02 O.OOE+OO 3

b. Dry compressible waste, m 5.92E+02 O.OOE+OO O.OOE+OO

+/-25%

contaminated equipment, etc. Ci 1.49E-01 O.OOE+OO O.OOE+OO 3

c. Irradiated components, control m O.OOE+OO O.OOE+OO O.OOE+OO

+/-25%

rods, etc. Ci O.OOE+OO O.OOE+OO O.OOE+OO 3

d. Other: Condensate Pre-Coat m 5.06E+01 O.OOE+OO O.OOE+OO

+/-25%

Septa Bundle Ci 5.07E-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.

Isotope (greater than 0.1 %) Percent Curies Mn-54 7.48 1.43E+02 Fe-55 62.15 1.19E+03 Co-58 1.05 2.00E+01 Co-60 18.76 3.59E+02 Ni-63 0.43 8.25E+00 Zn-65 9.20 1.76E+02 Ag-110m 0.45 8.60E+00 Cs-137 0.25 4.77E+00 env-teciARERR01

b. Dry compressible waste, contaminated equipment, etc.

Isotope (greater than 0.1%) Percent Curies H-3 0.42 6.34E-04 Mn-54 19.37" 2.90E-02 Fe-55 14.02 2.10E-02 Fe-59 0.77 1.16E-03 Co-58 0.50 7.47E-04 Co-60 42.35 6.34E-02 Ni-63 0.52 7. 85E-04 Zn-65 2.83 4.24E-03 Zr-95 5.26 7.88E-03 Nb-95 9.16 1.37E-02 Tc-99 0.49 7.29E-04 Ag-110m 1.56 2.34E-03 Sn-113 0.31 4.61E-04 Cs-137 1.31 1.95E-03 Ce-144 0.94 1.41E-03

c. Irradiated components, control rods, etc.

There were none in 2015.

d. Other: Oil Drum Sealand Isotope (greater than 0.1%) Percent Curies Mn-54 24.19 4.81E-01 Fe-55 0.34 6.76E-03 Co-60 51.77 1.03E+00 Zr-95 7.27 1.45E-01 Nb-95 13.11 2.61E-01 Tc-99 0.45 1.58E-04 Ag-110m 1.96 3.91E-02 Ce-144 1.18 2.35E-02 env-teciARERR01
3. Solid Waste Disposition Number of Mode of Destination Name City State Shipments Transportation 33 EnergySolutions (Bear Creek), LLC Oak Ridge TN Hittman Energy Solutions 4 Oak Ridge TN Hittman Gallaher Road Facilitv EnergySolutions LLC.

1 Clive UT Hittman Containerized Waste Facility 3 Babcock Services, Inc. Oak Ridge TN Hittman NRC Disposal Number of Description Waste Type Description Class Volume(ftJ\3) Containers B 120.3 8/120 HIC 2 Poly HIC - RWCU-A A 120.3 8/120 HIC 4 Poly HIC - RWCU-A A 205.8 215 liner 16 Poly Liner - SRT A 90 B-25 24 Metal/DAW A 1180 20' SEALAND 25 DAW/~IC/Oil ES-210 Stainless Steel Liner A 199.4 14 (solidification) CPS/RWCU-B B. Irradiated Fuel Shipments (Disposition)

II NUMBER OF SHIPMENTS I MODE OF TRANSPORTATION I DESTINATION I I None I N/A I N/A I

env-teclARERR01

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