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#REDIRECT [[GNRO-2018/00021, Annual Radioactive Effluent Release Report (ARERR)]]
| number = ML18115A440
| issue date = 04/25/2018
| title = Grand Gulf Nuclear Station Annual Radioactive Effluent Release Report (ARERR)
| author name = Neve D A
| 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-2018/00021
| document type = Environmental Monitoring Report, Letter
| page count = 37
}}
 
=Text=
{{#Wiki_filter:,. . -=~Entergy GNR0-2018/00021 April 25, 2018 U.S. NuclearRegulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Entergy Operations, Inc. P. 0. Box756 Port Gibson, MS 39150 Douglas A. Neve Manager, Regulatory Assurance Grand Gulf Nuclear Station Tel. (601) 437-2103 1 OCFR50.36(a)(2)
 
==SUBJECT:==
Grand Gulf Nuclear Station Annual Radioactive Effluent Release Report (ARE RR)
 
==Dear Sir or Madam:==
Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29 Attached is the Grand Gulf Nuclear Station Annual Radioactive Effluent Release Report for the time period of January 1, 2017 through December 31, 2017. This report is submitted in accordance with the requirements of 1 OCFR50.36(a)(2) and GGNS Unit 1 Technical Specification 5.6.3. This letter contains no new commitments.
If you have any questions or require additional information, please contact George Wynn at 601-437-1426.
Sincerely, Dougl A. Neve Regulatory Assurance Manager Grand Gulf Nuclear Station DAN/jw
 
==Attachment:==
 
Grand Gulf Nuclear Station 2017 Annual Radioactive Effluent Release Report cc: see next page GNR0-2018/00021 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission ATTN: Mr. Siva Lingam Mail Stop OWFN 8 81 Rockville, MD 20852-2738 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission ATTN: Mr. Kriss Kennedy Region Administrator, Region IV Mail Stop OWFN 8 81 Washington, DC 20555-0001 Mr. 8. J. Smith (w/2) Director, Division of Radiological Health Mississippi State Department of Health ' Division of Radiological Health 3150 Lawson Street Jackson, MS 39213 \ \)
Attachment to GNR0-2018/00021 Grand Gulf Nuclear Station 2017 Annual Radioactive Effluent Release Report I ENTERGY OPERATIONS, INC . . GRAND GULF NUCLEAR STATION ANNUAL RADIOACTIVE EFFLUENT*RELEASEREPORT JANUARY 1, 2017 -DECEMBER 31, 2017 Prepared:
-~, 4/z1/1a Jirr(R~ese Date Senior Chemistry Specialist Reviewed; o-~4 4k4tt Keith O'Neal Date Chemistry Supervisor Approved:
~-* '-llittfo Date Chemistry Manager -i -' 
-TABLE OF CONTENTS SUBJECT I. INTRODUCTION II. DETAILED INFORMATION A. Regulatory Limits 1. ODCM Control Limits a. Fission and Activation Gases b. Radioiodines, Tritium and Particulates
: c. Liquid Effluents
: 2. 1 OCFR50, Appendix I Limits a. Fission and Activation Gases \ b. Radioiodines, Tritium and Particulates
: c. Liquid Effluents
: 3. 40CFR190 Limits 6. -Effluent Concentrations
: 1. Airborne 2. 1 Liquid C. Average Energy D. Measurements and Approximations of Total Activity 1. Fission and Activation Gases 2. Particulates and Radioiodines
: 3. Continuous Releases 4. Batch Releases:
Gases 5. Batch Releases:
Liquid Effluents E. Batch Releases 1. Liquid 2. Gaseous F. Abnormal Releases 1. Liquid 2. Gaseous PAGE 4 5 5 5 5 5 5 6 6 6 6 7 7 7 7 8 8 9 10 10 10 11 11 11 12 12 12 12 TABLE OF CONTENTS (CONT'D) SUBJECT G. Estimate of Total Error 1. Liquid 2. Gaseous 3. Solid Radioactive Waste H. Solid Radioactive Waste Shipments I. Meteorological Data J. Radioactive Effluent Monitoring Instrumentation Operability K. Annual Sewage Disposal Summary Ill. RADIATION DOSE
 
==SUMMARY==
A. Water-Related Exposure Pathways B. Airborne-Related Exposure Pathways IV. OFFSITE DOSE CALCULATION MANUAL/ PAGE 12 12 13 13 13 13 13 13 14 14 14 RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES 17 A. Offsite Dose Calculation Manual (ODCM) B. Radioactive Waste Treatment Systems LIST OF TABLES Ill.A 2017 Liquid Effluent Dose 111.B 2017 Airborne Effluent Dose 1A Gaseous Effluents-Summation of All Releases 1 B Gaseous Effluents
-Elevated Releases 1 C Gaseous Effluents
-Ground-Level Releases -Continuous 1 D Radioactive Gaseous Waste Sampling and Analysis Program 2A Liquid Effluents
-Summation of All Releases 28 Liquid Effluents
-Continuous and Batch Modes -2e -Radioactive
*Liquid *waste *sampling and Analysis-Program 3 Solid Radioactive Waste and Irradiated Fuel Shipments ATTACHMENTS Attachment I -Nuclear Energy Institute (NEI) Groundwater Protection Initiative Sample Results 17 17 PAGE 14 16 18 \19 20 21 22 23 24 25 PAGE 28 
-1. **INTRODUCTION This Annual Radioactive Effluent Release Report (ARERR) for the period of January 1 through December 31, 2017 is submitted in accordance with Technical Specifications, Section 5.6.3, of Grand Gulf Nuclear Station (GGNS) License Number 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 1 C. The radioactive gaseous sampling and analysis program implemented at GGNS is described in Table 1 D. The summation of all liquid releases during the reporting pe'riod 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 Ooint frequency distribution) will be maintained on site. The option to maintain meteorological data on site is in accordanc~
with ODCM Administrative Controls Section 5.6.3. This data shall be provided to the Nuclear Regulatory Commission (NRC) upon request.
* 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)
I = XIQ Li~ Qi 500 mrem/yr Ds = average skin dose rate in the current year (mrem/yr)
I = XIQ L1 (Li + 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)
= Li W Pi Q\ :s, 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 1 OCFR20, 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.
II. DETAILED INFORMATION (CONT'D} 2. 10CFR50, Appendix I Limits a. Fission and Activation Gases -The dose from noble gases in gaseous effluents to areas at or beyond the site boundary shall be such that: D = air dose due to gamma emissions from noble gases y = 3.17 x 1 o-s Li Mi X/Q' Qi 5 mrad/qtr s 10 mrad/yr DP = air dose due to *beta emissions from noble gases = 3.17 x 1 o-s Lj Ni X/Q' Qi s 1 o mrad/qtr s 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 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-s Li Ri W' Qi s 7.5 mrem/qtr Any Organ s 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 Drau = L [AiTau L ~t1 Cn F1] s 1.5 mrem/qtr Total Body I 1=1 s 5 mrem/qtr Any Organ s 3 mrem/yr Total Body s 10 mrem/yr Any Organ where the terms are defined in the GGNS ODCM.
II. DETAILED INFORMATION
{CONT'D) 3. 40CFR 190 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) respective!y, with the exception that the limits applied are: s 25 mrem/yr, TotarBody or any Organ exceptThyroid s 75 mrem/yr, Thyroid s 10 mrad y/qtr or s 20 mrad y/yr, Fission and Activation Gases s 20 mrad p/qtr ors 40 mrad ~/yr, Fission and Activation Gases s t5 mrem/qtr ors 30 mrem/yr, any-Organ, Iodine and Particulates s 3 mrem/qtr ors 6 mrem/yr, Total Body, Liquid Effluents s 10 mrem/qtr ors 20 mrem/yr, any Organ, Liquid Effluents
: 8. 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 11.A.1.a.
In this case, the ECLs are actually determined by the dose factors in Table 2.1-1 of the GGNSODCM.
Gaseous dose rates rather than ECL 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 mrem/yr (Total Body) and 3000 mrem/yr (Skin) and in 6.11.4.b as 1500 mrem/yr (Organ). 2. Liquid The ECL of radioactive materials in liquid effluents is limited by ten times the values in 1 OCFR20, Appendix 8, Table 2, Column 2. The ECL chosen is the most conservative value of either the soluble or insoluble ECL for each radioisotope.
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 I," 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:
Fission and Activation Gases Particulates Radioiodines Liquid Effluents I Tables 1 D and 2C give sampling frequencies and Lower Limit of Detection requirements to'r 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 1 D 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.
II. *DETAILED
*INFORMATION
{CONT'D) 1. Fission and Activation Gases The principal gamma emitters for which the LLD specification in Table 1 D applies exclusively are: Kr-87 Xe-133 Xe-135 Kr-88 Xe-133m Xe-138 Periodic grab samples from Station effluent streams are analyzed by gamma spectral analysis utilizing high-resolution germanium detectors (see Table 1 D for sampling and analytical requirements).
Isotopic values thus obtained are used for dose release rate calculations due to effluent releases as given in Section 11.A.1 of this report. The radionuclides that are detected are used in this computation.
When no radionuclides are detected, a historical default 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: Ci = *isotopic calibration factor for isotope i Ui = concentration of isotope i in the grab sample in µCi/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 fa.ctor defaults to a historical default mixture of Kr~88, Xe-133, Xe-135m, Xe-135, and Xe-138.
II. DETAILED INFORMATION (CONT'D) 2. Particulates and Radioiodines The principal gamma emitters for which the LLD specification in Table 1 D applies exclusively are: '1 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..:9Q 1-133 3. 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 detector.
Strontium-89/90 values are obtained by chemical separation and subsequent counting analysis using a gas flow proportional detector.
Tritium concentrations are determined using distillation and a liquid scintillation detector.
During major operational occurrences, the frequency of sampling is increased to satisfy the requirements of footnote "c" of Table 1 D, "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 11.24 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-11-0060-Rev1-EC42519 and adjusted by 224.0 full power production days. Carbon-14 curies are reported in Tables 1A and 1 C of this report and based on a constant release rate throughout the quarter. 4. Batch Releases:
Gases Gaseous *batch releases are not normally performed at GGNS.
II. DETAILED INFORMATION
{CONT'D) 5. Batch Releases:
Liquid Effluents The principal gamma emitters for which the LLD specification in Table 20 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 20. 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 20. Strontium-89/90 and lron-55 values are obtained by individual chemical separations.
Strontium-89/90 is analyzed using a gas flow proportional detector.
lron-55 is analyzed using a low energy photon detector.
Gross alpha is analyzed using a gas flow proportional detector.
Tritium is distilled and then analyzed using a liquid scintillation detector.
* 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 Time periods in minutes 1st QTR 2ndQTR 3rd QTR 4th QTR YEAR Number of Releases 11 16 29 24 80 Total Release Time 3.25E+03 4.84E+03 8.50E+03 7.40E+03 2.40E+04 Maximum Release Time 3.08E+02 3.17E+02 3.85E+02 3.90E+02 3.90E+02 Average Release Time 2.95E+02 3.02E+02 2.93E+02 3.08E+02 3.00E+02 Minimum Release Time 2.75E+02 2.90E+02 3.00E+OO 2.60E+02 3.00E+OO Average Dilution Water 4.32E+03 5.84E+03 6.65E+03 5.75E+03 5.89E+03 Flow(GPM)
The 3rd quarter Minimum Release Time resulted from a liquid discharge that terminated shortly after starting due to high activity on the liquid effluent radiation monitor. After the monitor was flushed, the tank was resampled and discharged under a new release permit.
II. DETAILED INFORMATION (CONT'D) 2. Gaseous No batch releases occurred during the report period. F. Abnormal Releases 1. Liquid a. Number of Releases:
0 b. Total Activity Released:
O.OOE+OO Ci No abnormal liquid releases were identified for this reporting period. 2. Gaseous a. Number of Releases:
0 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
& -Gross Error values in % Activation Tritium Entrained Alpha Products Gases Sampling 2.60E+01 2.60E+01 2.60E+01 2.60E+01 Measurement 6.80E+01 6.50E+01 6.10E+01 9.20E+01 TOTAL 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 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.
II. DETAILED INFORMATION (CONT'D) 2. Gaseous The maximum errors (not including sample line loss) are collectively estimated to be as follows: Fission & Gross Error values in % Activation Iodine Particulate Tritium Products Alpha Sampling 3.20E+01 2.30E+01 2.20E+01 2.20E+01 2.30E+01 Measurement 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 'I -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+/- 25%. 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 99.6%. The predominant wind dire,ction was from the north-northeast approximately 10.4% of the time. The predominant stability class was class "D" approximately 31.8% of the time. Average wind speed during the reporting period was approximately 4.1 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 CR-GGN-2017-0051
-On 1/3/17 the Containment Building Vent effluent radiation monitor had been inoperable for 30 days due to detector failure and delays in obtaining replacement parts. Also, another issue was discovered during repairs that added additional repair time to the initial job scope. The monitor was repaired, calibrated, and restored to operable status on 1 /21 /17. K. Annual Sewage Disposal Summary There were no sewage disposals in 2017.
Ill. RADIATION DOSE
 
==SUMMARY==
Indicated below is the annual summary of offsite doses attributable to GGNS during 2017. Inspection of the values indicates that GGNS releases were within the 1 OCFR50, 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 28 of this report and the calculation methodology of the ODCM. Liquid Effluents Total body dos~ 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 Ill.A 2017 Liquid Effluent Dose Dose in mrem 1stQTR 2nd QTR 3rd QTR 4th QTR TOTAL Bone 2.61 E-02 1.25E-02 1.47E-02 4.74E-02 9.45E-02 Liver 4.29E-02 1.95E-02 2.47E-02 8.46E-02 1.61 E-01 Thyroid 4.80E-04 6.56E-04 9.55E-04 9.47E-04 3.00E-03 Kidney 1.57E-02 6.77E-03 9.28E-03 3.20E-02 6.00E-02 Lung 6.08E-03 3.60E-03 3.52E-03 9.12E-03 2.09E-02 Gl..:LU 1.0tE..:02 . *5.13E.:Q3 . *3;Q8E.:Q3 1;28E.:Q2 2.85E-U2 Applicable Limit 5 5 5 5 10 Percent bf Limit 8.58E-01 3.90E-01 4.94E-01 1.69E+OO 1.61 E+OO Whole Body 2.72E-02 1.25E-02 1.73E-02 5.89E-02 1.09E-01 Applicable Limit 1.5 1.5 1.5 1.5 3 Percent of Limit 1.82E+OO 8.35E-01 1.15E+OO 3.93E+OO 3.65E+OO B. Airborne-Related Exposure Pathways The values presented in this section utilize information provided in Tables 1A and 1 C 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, on occasion, may be found within the site boundary, ~o 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 2017 meteorological data and on the most recent land use census, with the most limiting locat~on used. During normal operations, the dispersion and deposition factors used for dose calculations are from five-year historical annual average meteorological data.
Ill. 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 2017 meteorolog*ical data. The critical receptor residence was determined to *be -iocated *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 was calculated 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 historical 5-year average meteorological data. The total body and skin dose rates reported are the quarterly average of the maximum fnstantaneous dose rates determined daily during the reporting period and represent the maximum possible dose rate received by members of the public. Air*bose*from Gamma and-Seta-Emissions Air doses from gaseous effluents were calculated for this report using dispersion parameters from historical 5-year average 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 2017 as net exposure normalized to 92 days. 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 radionucli~e in gaseous effluents.
Ill. RADIATION DOSE
 
==SUMMARY==
(CONT'D) 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 (C02) during photosynthesis so doses are calculated based on the C02 fraction of the carbon released in gaseous form. A C02 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 dosefor the same organ from tritium, iodine, and particulates.
This organ dose -is recorded and compared to the -1imit -in the following table. Table 111.B 2017 Airborne Effluent Dose rt*'.c:-* **--; J:\: ,.' '*' .* ,, ':{ 1stQTR 2ndQTR 3rdQTR 4thQTR
* TOTAL --,/ .........
:-<'-';;, ,..; ' -Iodine, Tritium & Particulates (excluding Carbon-14) -Child -(mrem) 2.976-03 --6.96E-03
--6.236-03 7.376-03 -2.356-02 Organ Thyroid Thyroid Thyroid Thyroid Thyroid Applicable Limit 7.5 7.5 7.5 7.5 15 Percent of Limit 3.97E-02 9.27E-02 8.30E-02 9.82E-02 1.57E-01 *i'', *,., _:. _,_,**,:.
":' '**->' _'* ' ::_.-,*.-'.
',., "* ', '-r.;_:, ';, ,,, __ ',, *. -**_, *!-'** , .. ,;, , '*'',.;:.:;;*, ,,* ,._,. _.-, .. *** .. :**,_ ,_ /; Iodine, Tritium & Particulates (including Carbon-14)
Child (mrem) 1.22E+OO 1.70E+OO 1.20E+OO 1.22E+OO 5.34E+OO -organ Hone Hone
* Hone
* Hone Hone Applicable Limit 7.5 7.5 7.5 7.5 15 Percent of Limit 1.63E+01 2.26E+01 1.60E+01 1.63E+01 3.56E+01 -~.c~~ '"<r*.: **** 1 ,; *~~--, :,,*.----.-,,_,., .. , .*', ** ,-*.*, ... ,*c;.*;*:*-,-:*.-,,.
*,,' ,,_., ;;;.:: ,.,,_ ." 2:~;~:o~ * ~.;;~~o**
2.38E+; 11,~f1:i,iS~J Total Body Dose Rate (mrem/yr) 4.87E-01 Applicable Limit 500 500 500 500 :;I __ _ " Percent of Limit 9.74E-02 5.82E-02 1.87E+OO 4.765-01 it < ,: : **.,.' * ,:'1::-*:,,;:
~* ,*., .: ,.-.,.,_,...._, : ,,,,, ",.:_) ., .-":'".,/
.. ** ' .. \:i ': ,{ :i; */.-C'.' .t~,\ '-' I*. *" "~'.&deg; *,, .,, ,-,_ ''.,'", ..........
<<.,-, "*'* ,, "~~:~+o~* , ;,.,.;;;;;,ii Skin Dose Rate (mrem/yr) 9.30E-01 5.55E-01 1.42E+01 Applicable Limit 3000 3000 3000 Percent of Limit 3.10E-02 1.85E-02 4.73E-01 1.22E-01 (~f~;:; '*:''.:: ,:,, .. , **.*,.,,:, ,:.,,_..'
,. ,**; :,-**.,:., .. 'i .. '* ,C'',i. ,,,_IJ ,,*,: *... :.,*:-"'' . . ... '~ -~. .;*,.,'; < ,1 1 , -;<:;, j* ,-,;,,;: h ,.,, .. ,. ,,,.,, .,.,, ',,:,;-*)-*
::;:,;:'.-'.>.
,:,('_<,,,.,'
Gamma Air Dose (mrad) 2.45E-02 1.41 E-02 4.92E-02 4.65E-02 1.34E-01 Applicable Limit 5 5 5 5 10 .Percent of -Limit 4.90E-01 . -2.82E.,01
.9.84E-01
-9.30E.,Q1 1.34E+OO :!* : ~*:\ . ',"\ 'J: I , ' ' ; : *~ ".,,.~;, c ... _ ,, * ,+, *, t * *,*.; J_i*)'.' ., ',; .. , "* ._._. ,],.,.* ,,.* -._ .. **: /, , -.,, *-* *.',.";..,, ,:, ... ;,,; **-*.,*, .:*:-.,'" ;,,,_, *., ') ',' .,*-..: Beta Air Dose (mrad) 1.91E-02 1.46E-02 3.25E-02 4.67E-02 1.13E-01 ) Applicable Limit 10 10 10 10 20 Percent of Limit 1.91E-01 1.46E-01 3.25E-01 4.67E-01 5.65E-01 '11*'1 .:*.*,'., _.,. * *~-***., ';" .:: ' ,~ ... *:*"*.,,-.:., __ -_,.-,_.,,,,/''
.. '; ,*,,, ... ,, . ' " . ~-. .. ,*'_-"",*,-:, .,., _,,_,_,-:
,"/ *<, l (~' 1. * ,_.~, ., ,:''"*'-*
-: .. ,w:.,: ,;;.* ,,*:.** .',* . . __ ,.*;.,.,;*.,:-;_.
,' ,.,.,, Direct Radiation (mrem) 1.00E-01 O.OOE+OO O.OOE+OO 5.00E-01 6.00E-01 Ill. RADIATION DOSE
 
==SUMMARY==
(CONT'D) The 3rd quarter Total Body Dose Rate and Skin Dose Rate increases resulted from securing the Off Gas system vault refrigeration for repairs during plant operation, which resulted in increased effluent noble gas activity.
The 4th quarter Total Body Dose Rate and Skin Dose Rate increases resulted from continued operation-with steam leaks-that caused elevated response on-the Turbine Building Vent effluent radiation monitor due to presence of N-13. The effluent dose was calculated conservatively using the default mixture when no noble gas was detected in grab samples, and the higher effluent dose rate was driven by the higher net monitor response.
IV. OFFSITE DOSE CALCULATION MANUAU RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES ) A. Offsite Dose Calculation Manual (CDCM) The ODCM was revised in January 2017 to align usage of the terms FUNCTIONAL versus OPERABLE.
B. -Radioactive
*Waste Treatment
*Systems No major changes were made to the liquid or gaseous radioactive waste treatment systems during this reporting period.
TABLE 1A ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ~PORT -FOR *2017 Units QTR -1 QTR -2 QTR -3 QTR 4 --------------------------------------
------------------------FISSION AND ACTIVATION GASES 1. Total Release Ci 6.56E+Ol 5.40E+Ol 1.05E+02 1. 73E+02 2. Avg. Release Rate uCi/sec 8.44E+OO 6.87E+OO 1.32E+Ol 2.17E+Ol 3. Percent of TS Limit a. -Gamma *Ai-r % -N/A N/A *N/A -N/A b. Beta.Air % N/A N/A N/A N/A IODINE-131 -yEAR --------3.97E+02 1.26E+Ol *N/A N/A 1. Total Release Ci 2. Avg. Release Rate uCi/sec 3.03E-06 3.90E-07 N/A 1.84E-04 1.63E-04 2.02E-04 5.52E-04 2.34E-05 2.0SE-05 2.54E-05 1.75E-05 3. Percent of TS Limit% PARTICULATES HALF LIFE 8 DAYS 1. Total Release Ci 2. Avg. Release Rate uCi/sec 3. Percent of TS Limit% TRITIUM 1. Total Release Ci 2. Avg. Release Rate. uCi/sec 3. Percent of TS Limit% CARBON-14
: 1. Total Release 2. Avg. Release Rate Ci uCi/sec GROSS ALPHA RADIOACTIVITY 5.40E-05 6.94E-06 N/A 3.81E+OO 4.90E-01 N/A 2.57E+OO 3.27E-01 N/A N/A N/A N/A 7.65E-06 9.73E-07 N/A 5.62E+00 7.lSE-01 N/A 3.57E+OO 4.59E-01 2.88E-06 1.14E-05 3.63E-07 1.44E-06 N/A N/A 5.06E+OO 5.76E+OO 6.36E-01 7.24E-Ol N/A N/A 2.52E+OO 3.17E-01 2.57E+OO 3.24E-01 7 .59E-05 2.41E-06 N/A 2.02E+Ol 6.42E-Ol N/A 1.12E+Ol 3.56E-01 1. Total Release 2. Avg. Release Rate Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO uCi/sec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NOTE: Limits are applicable to dose, not concentration.
See Table III.Bon page 16 for percentage of dose limits.
TABLE 18 ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS
-ELEVATED RELEASES JANUARY-DECEMBER 2017 (Not Applicable
-GGNS Releases Are Considered Ground-Level)
TABLE 1C ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS
-GROUND-LEVEL RELEASE-CONTINUOUS "REPORT "FOR 2017 *uni.ts QTR 1 QTR 2 QTR -3 QTR 4 -YEAR ---------------------
-----------------------
------------------------FISSION AND ACTIVATION GASES Ar-41 Kr-85m Kr-87 -Kr-88 Xe-133 Xe-135 Xe-135m Xe-138 Total for Period IODINES I-131 I-133 Total for Period Ci Ci Ci -Ci Ci Ci Ci Ci Ci Ci Ci Ci PARTICULATES HALF LIFE~ 8 DAYS Co-58 Co-60 Mn-54 Ru-106 Se-75 Zn-65 Total OTHER H-3 C-14 for Period Gross Alpha Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 7.21E+OO 7. 62E-01 1. lSE+Ol 3.54E+OO 2.30E+Ol 9.19E-Ol 6.31E-01 4. 90E+OO i 6. OSE-01 7.06E+00 O.OOE+OO O.OOE+OO 9.82E-01 O.OOE+OO 9.82E-Ol 1.15E+OO 1.-0SE+OO
-6.-51E+OO 3.36E+OO 1.21-E+Ol 2.69E+Ol 2.46E+Ol 4.04E+Ol 7. 89E+Ol 1. 71E+02 2.57E+Ol 2.36E+Ol 3.53E+Ol 7.54E+Ol 1.60E+02 3.03E+OO 2.77E+OO 4.16E+OO 8. 89E+OO 1.89E+Ol 6.88E-01 6.29E-01 9.45E-01 2.02E+OO 4.28E+OO ----------------------------------------6.56E+Ol 5.40E+Ol 1.0SE+02 1. 73E+02 3.97E+02 3.03E-06 1.84E-04 1.63E-04 2.02E-04 5.52E-04 1.96E-05 3.69E-05 4.76E-05 1.14E-04 2.lSE-04 2.27E-05 2.21E-04 2.lOE-04 3.lSE-04 7.70E-04 9.0SE-07 2.24E-06 O.OOE+OO 3. 95E-06 7 ~'lOE-06 3.64E-05 3.21E-06 2.SOE-06 5.39E-06 4. 75E-05 l.28E-05 6.76E-07 O.OOE+OO 2.0SE-0(>
1.SSE-05 O.OOE+OO 1. 33E-06 O.OOE+OO O.OOE+OO 1.33E-06 l.62E-07 1. 92E-07 3 .86E-07 4 .44E-09 7.44E-07 3.74E-06 O.OOE+OO O.OOE+OO O.OOE+OO 3.74E-06 ----------------
------------------------5.40E-05 7.65E-06 2.88E-06 1.14E-05 7.59E-05 3.81E+OO 5.62E+OO 5.06E+OO 5.76E+OO 2.02E+Ol 2.57E+OO 3.57E+OO 2.52E+OO 2.57E+OO 1.12E+Ol O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NOTE: Only radionuclides with positive results reported.
TABLE 1-0 ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radioactive Gaseous Waste Sampling and Analysis Program JANUARY-DECEMBER 2017 Gaseous Release Sampling Minimum Analysis Type of Activity Type Frequency Frequency Analysis Principal Gamma 31 Days 31 Days Emitters (b,e) Grab Sample (f) A.(1) .Radwaste-Building -H-3 Ventilation Exhaust (2) Fuel Handling Area 7 Days (c) 1-131 Ventilation Exhaust Continuous (d) (f) Charcoal Sample 1-133 (3) Containment Principal Gamma Ventilation Exhaust 7 Days (c) Continuous (d) (f) Particulate Sample Emitters (e) (4A) Turbine Building (1-131, Others) Ventilation Exhaust Continuous (d) (f) 31 Days Composite Gross Alpha (48) Turbine Building Particulate Sample Occasional Release Point (g) Continuous (d) (f) 92 Days Composite Sr-89, Sr-90 (when in service) Particulate Sample Continuous (f) Noble Gas Monitor Noble Gases Gross Beta or Gamma B. (1) Offgas Post 31 Days Grab Principal Gamma Treatment Exhaust, Sample (f) 31 Days Emitters (e) whenever there is flow (2) Standby Gas 31 Days Grab Principal Gamma Treatment A Exhaust, 31 Days whenever there is flow Sample (f) Emitters (e) -(3) Standby-Gas 31 Days Grab Principal Gamma Treatment B Exhaust, Sample (f) 31 Days Emitters (e) whenever there is flow NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.4-1. Lower Limit of Detection (LLD) (uCi/ml) (a) 1.00E-04 1;00E-06 1.00E-12 1.00E-10 1.00E-11 1.00E-11 1.00E-11 1.00E-06 1.00E-04 1.00E-04 1.00E-04 TABLE 2A ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS
-SUMMATION OFALL RELEASES -REPORT "FOR 01, *units ---------------------
-------FISSION AND ACTIVATION PRODUCTS 1. Total Release Ci 2. Avg. Diluted Cone. uCi/ml 3. Percent of Limit % TRITIUM 1. Total Release Ci 2. Avg. Diluted Cone. uCi/ml 3. Percent of Limit % DISSOLVED AND ENTRAINED GASES 1. Total Release Ci 2. Avg. Diluted Cone. uCi/ml 3. Percent of Limit % GROSS ALPHA RADIOACTIVITY
: 1. Total Release Volume of Liquid Waste Volume of Dilution Water Ci liters liters QTR 1 QTR *2 QTR -----------------------1.87E-02 1.60E-02 3.0lE-03 3.44E-07 l.47E-07 1.39E-08 N/A N/A N/A 4.25E+00 7.77E+OO 1.30E+Ol 7.82E-05 7.14E-05 5.97E-05 N/A N/A N/A 1.79E-05 3.06E-05 3.84E-05 3.29E-10 2.81E-10 l.77E-10 N/A N/A N/A QTR 4 --------3.77E-03 2.30E-08 N/A 1.llE+Ol 6.79E-05 N/A YEAR --------4.lSE-02 7.63E-08 N/A 3.61E+Ol 6.64E-05 N/A 6.87E-05 1.56E-04 4.20E-10 2.86E-10 N/A N/A O.OOE+QO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.15E+06 1.70E+06 2.98E+06 2.56E+06 8.39E+06 5.31E+07 1.07E+08 2.14E+08 l.61E+08 5.35E+08 NOTE: Limits are applicable to dose, not concentration.
See Table III.A on page 14 for percentage of dose limits.
TABLE 28 ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS
-CONTINUOUS AND BATCH MODES "REPORT -FOR 2-017 Units QTR -1 QTR -2 QTR -3 QTR 4 YEAR --------------------
----------------------------------------FISSION AND ACTIVArION GASES AG-llOM Ci 2.95E-05 O.OOE+OO 2 .44E-05 7.28E-05 1.27E-04 AS-76 Ci O.OOE+OO 6. 61E-06 O.OOE+OO O.OOE+OO 6.61E-06 C0-58 Ci O.OOE+OO 2 .17E-05 1.98E-05 1.65E-04 2 .06E-04 -C0--60 Ci :4. lOE-04 -5.30E-04 3.84E-04 1.96E-03 3.28E-03 CS-134 Ci 3.98E-05 2.45E-05 2.95E-05 l. lSE-04 2.0SE-04 CS-137 Ci 6.28E-05 3.86E-05 8.87E-05 2.17E-04 4.07E-04 FE-55 Ci 1. 77E-02 l.SOE-02 1.53E-03 7.37E-04 3.SOE-02 LA-140 Ci O.OOE+OO O.OOE+OO O.OOE+OO 1. 74E-05 1.74E-05 MN-54 Ci 1.42E-04 8.66E-05 4.48E-06 1.0lE-04 3.34E-04 NA-24 Ci . 9.28E-06 3.83E-05 O.OOE+OO O.OOE+OO
: 4. 76E-05 PT-195M Ci O.OOE+OO O.OOE+OO O.OOE+OO 2. 62E-05 2.62E-05 RB-e88 -Ci -0 ,-OOE+OO 2 .02E""0-4 7 .53E-04 -0.-00E+OO 9.SSE-04 RU-106 Ci 2.0SE-05 O.OOE+OO O.OOE+OO O.OOE+OO 2 .OSE-05 SB-124 Ci O.OOE+OO O.OOE+OO 7. 76E-05 O.OOE+OO 7. 76E-05 SB-125 Ci 1.74E-05 O.OOE+OO 3.62E-05 O.OOE+OO 5.36E-05 ZN-65 Ci 2.06E-04 7.98E-05 6.22E-05 3 .56E-04 7.0SE-04 ----------------------------------------Total for Period Ci l.87E-02 1.60E-02 3.0lE-03 3.77E-03 4.lSE-02 TRI.TIUM Total for Period Ci 4.25E+OO 7.77E+OO 1.30E+Ol 1.llE+Ol 3.61E+Ol DISSOLVED AND ENTRAINED GASES XE-133 Ci 6.53E-06 1.34E-05 3.33E-05 5. 96E-05 1.13E-04 XE-135 Ci 1.13E-05 1.72E-05 5.lOE-06 9.06E-06 4.27E-05 ----------------------------------------Total for Period Ci 1. 79E-05 3.06E-05 3.84E-05 6.87E-05 1.56E-04 GROSS ALPHA.RADIOACTIVITY Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 
\ 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 2017 Minimum Liquid Release Sampling Analysis Type of Activity Type Frequency Frequency Analysis Principal Gamma Prior to Release Prior to Release Emitters (d) \ Each Batch Each Batch 1-131 Prior to Release Dissolved and A. Batch Waste Release One Batch/Month.
31 Days Entrained Gases Tanks (c) (Gamma Emitters)
Prior to Release 31 Days H-3 Each Batch Composite (b) Gross Alpha Prior to Release 92 Days Sr-89, Sr-90 Each Batch Composite (b) Fe-55 Principal Gamma B. SSW Basin Prior to Release Prior to Release Emitters (d) (Before Slowdown)
Each Slowdown Each Batch 1-131 *NOTE: Footnotes indicated are*listed in*GGNS*Q[)CM, Appendix A Table 6.-11:1..;1. Lower Limit of Detection (LLD) (1,1Ci/ml) (a) 5.00E-07 1.00E-06 1.00E-05 1.00E-05 1.00E-07 5.00E-08 1.00E-06 5.00E-07 1.00E-06 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 2017 A. SO LIO-WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT lRRADIATED FUEL) 1. Type of Waste Unit Class A Class B Class C Estimated Total Error a. Spent resins, filter sludges, m3 1.53E+02 9.34E-01 O.OOE+OO +/-25% evaporator bottoms, etc. Ci 2.61E+02 1.06E+02 O.OOE+OO -b. -Dry -compressible-waste, 3' 7;03E+02 -Q;OQE+OO -Q;QOE+OO -m +/-25% contaminated equipment, etc. Ci 2.92E+OO 0.00E+OO O.OOE+OO c. Irradiated components, control m3. O.OOE+OO O.OOE+OO O.OOE+OO +/-25% rods, etc. Ci O.OOE+OO O.OOE+OO O.OOE+OO
: d. Other: Oily waste drums m3 O.OOE+OO O.OOE+OO O.OOE+OO +/-25% Ci O.OOE+OO 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 (> 0.1 %) Percent Curies H-3 2.20E-01 8.10E-01 C-14 2.70E-01 9.87E-01 Cr-51 9.30E-01 3.41E+OO Mn-54 6.66E+OO 2.45E+01 .Fe-e55 .. 6.49E+01 2.38E+02 Fe-59 1.80E-01 ( 6.18E-01 Co-58 1.46E+OO 5.36E+OO Co-60 1.84E+01 6.75E+01 Ni-63 4.60E-01 1.70E+OO Zn-65 5.59E+OO 2.05E+01 Ag-110m
* 4:90E~01 1:80E+OO Cs-137 2.20E-01 8.07E-01 TABLE 3 -Continued 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 2017 b. Dry compressible waste, contaminated equipment, etc. Isotope(>
0.1%) Percent Curies H-3 3.60E-01 1.06E-02 Mn-54 6.84E+OO 2.00E-01 Fe-55 6.55E+01 1.91E+OO Co-58 2.00E-01 5.84E-03 Co-60 2.09E+01 6.09E-01 Zn-65 1.07E+OO 3.12E-02 Zr-95 1.39E+OO 4.0SE-02 Nb-95 2.72E+OO 7.94E-02 Sb-125 . 3.90_E-01 1.13_E-Q2 Cs-137 2.SOE-01 7.38E-03 Ce-144 1.60E~o1 4.57E-03 c. Irradiated components, control rods, etc. None d. Other: Oil drum sealand, mixed waste for volume reduction None TABLE 3 -Continued 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 2017 3. Solid *waste Disposition Number of J Destination Name City State Modeof
* Shipments Transportation 3 EnergySolutions, Clive Disposal Site Clive. UT Hittman (Bulk Waste Facility) 5 EnergySolutions, Clive Disposal Site Clive UT Hittman (Containerized Waste Facility) 24 EnergySolutions, Bear Creek Road Oak Ridge TN Hittman EnergySoluti~ns, Gallaher Road I 3 Facility Oak Ridge TN Hittman 2 EnergySolutions, Erwin Resin Erwin TN Hittman -Solutions B. Irradiated .Fuel Shipments (Disposition)
Number of Shipments Mode of Transportation Destination None N/A N/A J ATTACHMENT I Nuclear Energy Institute (NEI) Groundwater Protection Initiative Sample Results JANUARY -DECEMBER 2017 GPI Ground Water samples were collected from onsite Dewatering Wells (DW), Monitoring Wells {MW), Observation Wells (OW), and Sump Wells (SW). Samples were analyzed for Tritium and selected samples were analyzed for gamma and/or hard to detect (HTD) isotopes (Gross Alpha, lron-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 less than minimum detectable activity (<MDA). Tritium, gamma and/or 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 {pCi/L) CST FENCE 05/04/17 2040 <MDA -CST.FENCE
-08/1.0/17 6610 <MDA DW-01 02/22/17 1410 <MDA DW-01 05/10/17 2240 <MDA DW-01 08/22/17 3300 <MDA DW-01 11/15/17 886 <MDA DW-01 REANALYSIS 11/15/17 674 <MDA DW-02 01/23/17 <440 <MDA DW-02 02/21/17 <566 <MDA DW-02 DUPLICATE 02/21/17 <571 <MDA
* DW-02 03/22/17 <566 <MDA DW-02 04/12/17 <523 <MDA DW-02 05/09/17 <515 <MDA DW-02 DUPLICATE 05/09/17 <522 <MDA DW-02 06/20/17 <563 <MDA DW-02 07/26/17 712 <MDA DW-02 08/23/17 <576 <MDA DW-02 09/25/17 <534 <MDA DW-02 10/18/17 <562 <MDA -DW-02 11/15/17 <570 <-MDA DW-02 12/13/17 <556 <MDA DW-03 01/23/17 556 <MDA DW-03 02/21/17 695 <MDA DW-03 03/22/17 801 < !VIDA DW-03 04/12/17 <531 <MDA DW-03 05/09/17 795 <MDA LOCATION DATE TRITIUM {pCi/L} GAMMA {pCi/L} DW-03 06/20/17 <594 <MDA DW-03 07/26/17 <494 .. <MDA DW-03 DUPLICATE 07/26/17 661 <MDA DW-03 08/22/17 <587 <MDA DW-03 09/25/17 830 <MDA DW-03 10/18/17 <566 <MDA DW-03 DUPLICATE 10/18/17 <558 <MDA DW-03 11/14/17 <572 <MDA DW-03 12/13/17 <555 <MDA. DW-04 01123/17 <445 <MDA DW-04 DUPLICATE 01/23/17 <440 <MDA DW-04 02/23/17 <503 _<MDA DW-04 03/22/17 658 <MDA DW-04 04/13/17 719 <MDA DW-04 DUPLICATE 04/13/17 <530 <MDA DW-04 05/11/17 <523 <MDA --OW..;04 06/20/17 <593 <MDA DW-04 07/26/17 805 <MDA DW-04 08/23/17 <569 <MDA DW-04 09/26/17 <526 <MDA ) DW-04 10/19/17 <519 <MDA DW-04 11/14/17 <579 <MDA DW-04 12/14/17 <554 <MDA DW-05 01/24/17 <440 <MDA DW-05 02/21/17 <557 <MDA DW-05 03/22/17 <565 <MDA DW-05 04/12/17 <525 <MDA DW-05 05/10/17 <569 <MDA -DW-05 06/21/17 <563 <-MDA DW-05 DUPLICATE 06/21/17 <588 <MDA DW-05 07/27/1_7
<506 <MDA DW-05 08/23/17 <569 <MDA DW-05 09/25/17 <531 <MDA
* DW-05 10/18/17 <574 <MDA DW-05 11/16/17 <578 <MDA DW-05 12/13/17 <535 <MDA DW-06 11/15/17 <592 <MDA DW-07 02/22/17 2960 <MDA DW-07 DUPLICATE 02/22/17 3700 <MDA DW-07 05/10/17 5450 <MDA DW-07 DUPLICATE 05/10/17 5990 <MDA LOCATION DATE TRITIUM {pCi/L} GAMMA {pCi/L} DW-07 08/22/17 4800 <MDA DW-07 11/14/17 5060 *<MDA DW-08 01/24/17 <435 <MDA MW-01 01/23/17 <445 <MDA MW-01 02/22/17 <557 <MDA MW-01 03/22/17 <557 <MDA MW-01 04/12/17 <537 <MDA MW-01 05/10/17 <566 <MDA MW-01 06/20/17 <5.90 <MDA MW-01 07/26/17 <497 <MDA MW-01 08/22/17 <569 <MDA MW-01 09/25/17 626 <MDA MW-01 DUPLICATE 09/25/17 <522 <MDA MW-01 10/18/17 <554 <MDA MW-01 11/14/17 <599 <MDA MW.:01 t2/t3/17 789 <MDA MW-04 01/23/17 <444 <MDA MW-04 02/21/17 <562 <MDA MW-04 03/22/17 <565 <MDA MW-04 04/12/17 <535 <MDA MW-04 05/10/17 <573 <MDA MW-04 06/21/17 <588 <MDA MW-04 07/27/17 <498 <MDA MW-04 08/23/17 <578 <MDA MW-04 09/25/17 <535 <MDA MW-04 10/18/17 <550 <MDA MW-04 11/16/17 <579 <MDA -MW-04 I 12/13/17 <559 <-MDA MW-04 DUPLICATE
* 12/13/17 <551 <MDA MW-05 01/24/17 <445 <MDA MW-05 02/21/17 <560 <MDA MW-05 03/21/17 <566 <MDA MW-05 04/12/17 <527 <MDA MW-05 05/10/17 <563 <MDA MW-05 06/21/17 <588 <MDA MW-05 07/27/17 <515 <MDA MW-05 08/23/17 <586 <MDA MW-05 09/26/17 <529 <MDA MW-05 10/19/17 <550 <MDA MW-05 11/16/17 <579 <MDA MW-05 12/14/17 <560 <MDA LOCATION DATE TRITIUM (pCi/L) GAMMA {pCi/L) MW-06 02/23/17 1390 <MDA MW-06 05/11/17 1560 <MDA MW-06 08/24/17 1240 <MDA MW-06 11/15/17 683 <MDA MW-1008 08/24/17 <573 <MDA MW-1018 02/21/17 <518 <MDA MW-1018 05/10/17 <551 <MDA MW-1018 08/24/17 <576 <MDA .MW-101B 11/t5/17 <5.7-0 <MDA MW-1018 DUPLICATE 02/21/17 <511 <MDA MW-1028 08/23/17 <568 <MDA MW-1038 08/23/17 <583 <MDA "MW-1048 08/23/17 <577 <MDA MW-1058 02/21/17 648 <MDA MW-1058 RECOUNT 02/21/17 <522 <MDA MW-1058 05/10/17 <567 <MDA MW-1058 08/24/17 <581 <MDA MW-1058 11/14/17 <570 <MDA MW-1058 DUPLICATE 11/14/17 <585 <MDA MW-1068 02/21/17 <520 <MDA MW-1068 05/10/17 <562 <MDA MW-1068 08/23/17 <580 <MDA MW~1068 11/14/17 <525 <MDA MW-1078 02/22/17 1490 <MDA MW-1078 05/09/17 1210 <MDA MW-1078 08/22/17 968 <MDA MW-1078 11/14/17 849 <MDA MW-1088 02/22/17 827 <MDA MW-1088 05/11/17 1240 <MDA MW-1088 08/23/17 792 <MDA MW-1088 11/14/17 858 <MDA MW-1098 02/23/17 981 <MDA MW-1098 05/11/17 851 <MDA MW-1098 08/24/17 1080 <MDA MW-1098 11/15/17 917 <MDA LOCATION DATE TRITIUM (pCI/L) GAMMA {pCi/L) MW-1108 02/21/17 <500 <MDA MW-1108 05/10/17 <521 <MDA MW-1108 08/22/17 <579 <MDA MW-1108 11/14/17 <558 <MDA MW-1118 02/22/17 941 <MDA MW-1118 05/11/17 1430 <MDA, MW-1118 08/22/17 1980 * <MDA MW-1118 DUPLICATE 08/22/17 1830 <MDA MW-1118 11/15/17 1030 <MDA MW-1128 01/23/17 <600 <MDA MW-1128 02/22/17 <576 <MDA MW-1128 03/22/17 <566 <MDA MW-1128 04/13/17 <506 <MDA MW-1128 05/11/17 <530 <MDA MW-1128 *06/20/17
<593 <MDA MW..:1128 07/26/17 <499 <MDA MW-1128 08/23/17 <577 <MDA MW-1128 09/25/17 <531 <MDA MW-1128 10/18/17 <481 <MDA MW-1128 11/16/17 <570 <MDA MW-1128 12/13/17 761 <MDA MW-1138 01/24/17 <437 <MDA MW-1138 02/21/17 <518 <MDA MW-1138 03/21/17 <573 <MDA MW-1138 DUPLICATE 03/21/17 <562 <MDA MW-1138 04/13/17 <535 <MDA -MW-1138 .QS/1-0/17
<564 <MDA MW-1138 DUPLICATE 05/10/17 <574 <MDA MW-1138 \_ 06/21/17 <595 <MDA MW-1138 07/27/17 <501 <MDA MW-1138 08/22/17 <568 <MDA MW-1138 DUPLICATE 08/22/17 <56,9 <MDA MW-1138 09/26/17 <520 <MDA MW-1138 10/19/17 <514 <MDA MW-1138 11/14/17 <594 <MDA MW-1138 12/14/17 <566 <MDA MW-1148 02/21/17 2180 <MDA MW-1148 05/10/17 1800 <MDA MW-1148 08/22/17 1790 <MDA MW-1148 11/14/17 1360 <MDA LOCATION DATE TRITIUM {pCi/Ll GAMMA {pCi/Ll MW-1158 02/22/17 820 <MDA MW-1158 05/10/17 831 <MDA MW-1158 08/22/17 873 <MDA MW-1158 11/15/17 <569 <MDA MW-1158 DUPLICATE 11/15/17 <574 <MDA MW-1168 02/22/17 <561 <MDA MW-1168 05/10/17 <564 <MDA MW-1168 08/23/17 <564 <MDA MW-1168 11/15/17 <563 <MDA .MW-1 t6B DUPLICATE 11/t5/17 <58-0 <MDA MW-1188 02/22/17 <562 <I\IIDA MW-1188 05/10/17 <525 <MDA MW-1188 08/23/17 734 <MDA MW-1188 11/15/17 675 <MDA MW-1196 08/23/17 <569 <MDA MW-1208 08/22/17 <572 <MDA MW-1218 08/23/17 <571 <MDA MW-1228 01/24/17 <445 <MDA MW-1228 02/21/17 <570 <MDA MW-1228 03/21/17 <567 <MDA MW-1228 04/12/17 <523 <MDA MW-1228 05/10/17 <565 <MDA MW-1228 06/21/17 <597 <MDA MW-1228 07/26/17 <492 <MDA -MW-1228 -08/23/17
<566 <MDA MW-1228 09/26/17 <528 <MDA MW-1228 10/19/17 <570 <MDA MW-1228 11/16/17 <574 <MDA MW-1228 12/14/17 <556 <MDA MW-1238 01/24/17 <445 <MDA MW-1238 02/21/17 <564 <MDA \__,, MW-1238 03/22/17 <564 <MDA MW-1238 04/12/17 <528 <MDA MW-1238 05/11/17 <570 <MDA MW-1238 06/20/17 <599 <MDA (_, MW-1238 07/27/17 <498 <MDA MW-1238 08/23/17 <574 <MDA MW-1238 09/25/17 <535 <MDA LOCATION DATE TRITIUM CpCi/Ll MW-1238 10/18/17 <555 MW-1238 11/15/17 <576 MW-1238 12/13/17 <553 MW-1007C 08/23/17 <573 MW-1009C 08/24/17 <568 MW-1012C 08/24/17 <579 MW-1020C 08/23/17 <567 MW-1020C DUPLICATE 08/23/17 <564 MW-1024C 08/24/17 <581 MW-1027C 08/24/17 <575 MW-to42C 08/24/17 <585 MW-1082C 08/23/17 <573 MW-1134C 08/23/17 <590 P-05 08/24/17 <567 SW-103A 02/21/17 <507 SW-103A 05/10/17 <566 SW-103A 08/24/17 <579 SW-103A 11/15/17 <575 <MDA -Less than Minimum Detectable Activity DUPLICATE
-Duplicate sample-collected and analyzed RECOUNT -Re-performed same sample count GAMMA CpCi/Ll <MDA <MDA <MDA <MDA <MDA
<MDA <.MDA <MDA <MDA ~MDA <MDA <MDA <MDA <MDA <MDA <MDA <MDA <MDA REANALYSIS
-*Re-performed same sample analysis and counting )
,. . -=~Entergy GNR0-2018/00021 April 25, 2018 U.S. NuclearRegulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Entergy Operations, Inc. P. 0. Box756 Port Gibson, MS 39150 Douglas A. Neve Manager, Regulatory Assurance Grand Gulf Nuclear Station Tel. (601) 437-2103 1 OCFR50.36(a)(2)
 
==SUBJECT:==
Grand Gulf Nuclear Station Annual Radioactive Effluent Release Report (ARE RR)
 
==Dear Sir or Madam:==
Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29 Attached is the Grand Gulf Nuclear Station Annual Radioactive Effluent Release Report for the time period of January 1, 2017 through December 31, 2017. This report is submitted in accordance with the requirements of 1 OCFR50.36(a)(2) and GGNS Unit 1 Technical Specification 5.6.3. This letter contains no new commitments.
If you have any questions or require additional information, please contact George Wynn at 601-437-1426.
Sincerely, Dougl A. Neve Regulatory Assurance Manager Grand Gulf Nuclear Station DAN/jw
 
==Attachment:==
 
Grand Gulf Nuclear Station 2017 Annual Radioactive Effluent Release Report cc: see next page GNR0-2018/00021 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission ATTN: Mr. Siva Lingam Mail Stop OWFN 8 81 Rockville, MD 20852-2738 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission ATTN: Mr. Kriss Kennedy Region Administrator, Region IV Mail Stop OWFN 8 81 Washington, DC 20555-0001 Mr. 8. J. Smith (w/2) Director, Division of Radiological Health Mississippi State Department of Health ' Division of Radiological Health 3150 Lawson Street Jackson, MS 39213 \ \)
Attachment to GNR0-2018/00021 Grand Gulf Nuclear Station 2017 Annual Radioactive Effluent Release Report I ENTERGY OPERATIONS, INC . . GRAND GULF NUCLEAR STATION ANNUAL RADIOACTIVE EFFLUENT*RELEASEREPORT JANUARY 1, 2017 -DECEMBER 31, 2017 Prepared:
-~, 4/z1/1a Jirr(R~ese Date Senior Chemistry Specialist Reviewed; o-~4 4k4tt Keith O'Neal Date Chemistry Supervisor Approved:
~-* '-llittfo Date Chemistry Manager -i -' 
-TABLE OF CONTENTS SUBJECT I. INTRODUCTION II. DETAILED INFORMATION A. Regulatory Limits 1. ODCM Control Limits a. Fission and Activation Gases b. Radioiodines, Tritium and Particulates
: c. Liquid Effluents
: 2. 1 OCFR50, Appendix I Limits a. Fission and Activation Gases \ b. Radioiodines, Tritium and Particulates
: c. Liquid Effluents
: 3. 40CFR190 Limits 6. -Effluent Concentrations
: 1. Airborne 2. 1 Liquid C. Average Energy D. Measurements and Approximations of Total Activity 1. Fission and Activation Gases 2. Particulates and Radioiodines
: 3. Continuous Releases 4. Batch Releases:
Gases 5. Batch Releases:
Liquid Effluents E. Batch Releases 1. Liquid 2. Gaseous F. Abnormal Releases 1. Liquid 2. Gaseous PAGE 4 5 5 5 5 5 5 6 6 6 6 7 7 7 7 8 8 9 10 10 10 11 11 11 12 12 12 12 TABLE OF CONTENTS (CONT'D) SUBJECT G. Estimate of Total Error 1. Liquid 2. Gaseous 3. Solid Radioactive Waste H. Solid Radioactive Waste Shipments I. Meteorological Data J. Radioactive Effluent Monitoring Instrumentation Operability K. Annual Sewage Disposal Summary Ill. RADIATION DOSE
 
==SUMMARY==
A. Water-Related Exposure Pathways B. Airborne-Related Exposure Pathways IV. OFFSITE DOSE CALCULATION MANUAL/ PAGE 12 12 13 13 13 13 13 13 14 14 14 RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES 17 A. Offsite Dose Calculation Manual (ODCM) B. Radioactive Waste Treatment Systems LIST OF TABLES Ill.A 2017 Liquid Effluent Dose 111.B 2017 Airborne Effluent Dose 1A Gaseous Effluents-Summation of All Releases 1 B Gaseous Effluents
-Elevated Releases 1 C Gaseous Effluents
-Ground-Level Releases -Continuous 1 D Radioactive Gaseous Waste Sampling and Analysis Program 2A Liquid Effluents
-Summation of All Releases 28 Liquid Effluents
-Continuous and Batch Modes -2e -Radioactive
*Liquid *waste *sampling and Analysis-Program 3 Solid Radioactive Waste and Irradiated Fuel Shipments ATTACHMENTS Attachment I -Nuclear Energy Institute (NEI) Groundwater Protection Initiative Sample Results 17 17 PAGE 14 16 18 \19 20 21 22 23 24 25 PAGE 28 
-1. **INTRODUCTION This Annual Radioactive Effluent Release Report (ARERR) for the period of January 1 through December 31, 2017 is submitted in accordance with Technical Specifications, Section 5.6.3, of Grand Gulf Nuclear Station (GGNS) License Number 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 1 C. The radioactive gaseous sampling and analysis program implemented at GGNS is described in Table 1 D. The summation of all liquid releases during the reporting pe'riod 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 Ooint frequency distribution) will be maintained on site. The option to maintain meteorological data on site is in accordanc~
with ODCM Administrative Controls Section 5.6.3. This data shall be provided to the Nuclear Regulatory Commission (NRC) upon request.
* 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)
I = XIQ Li~ Qi 500 mrem/yr Ds = average skin dose rate in the current year (mrem/yr)
I = XIQ L1 (Li + 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)
= Li W Pi Q\ :s, 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 1 OCFR20, 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.
II. DETAILED INFORMATION (CONT'D} 2. 10CFR50, Appendix I Limits a. Fission and Activation Gases -The dose from noble gases in gaseous effluents to areas at or beyond the site boundary shall be such that: D = air dose due to gamma emissions from noble gases y = 3.17 x 1 o-s Li Mi X/Q' Qi 5 mrad/qtr s 10 mrad/yr DP = air dose due to *beta emissions from noble gases = 3.17 x 1 o-s Lj Ni X/Q' Qi s 1 o mrad/qtr s 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 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-s Li Ri W' Qi s 7.5 mrem/qtr Any Organ s 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 Drau = L [AiTau L ~t1 Cn F1] s 1.5 mrem/qtr Total Body I 1=1 s 5 mrem/qtr Any Organ s 3 mrem/yr Total Body s 10 mrem/yr Any Organ where the terms are defined in the GGNS ODCM.
II. DETAILED INFORMATION
{CONT'D) 3. 40CFR 190 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) respective!y, with the exception that the limits applied are: s 25 mrem/yr, TotarBody or any Organ exceptThyroid s 75 mrem/yr, Thyroid s 10 mrad y/qtr or s 20 mrad y/yr, Fission and Activation Gases s 20 mrad p/qtr ors 40 mrad ~/yr, Fission and Activation Gases s t5 mrem/qtr ors 30 mrem/yr, any-Organ, Iodine and Particulates s 3 mrem/qtr ors 6 mrem/yr, Total Body, Liquid Effluents s 10 mrem/qtr ors 20 mrem/yr, any Organ, Liquid Effluents
: 8. 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 11.A.1.a.
In this case, the ECLs are actually determined by the dose factors in Table 2.1-1 of the GGNSODCM.
Gaseous dose rates rather than ECL 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 mrem/yr (Total Body) and 3000 mrem/yr (Skin) and in 6.11.4.b as 1500 mrem/yr (Organ). 2. Liquid The ECL of radioactive materials in liquid effluents is limited by ten times the values in 1 OCFR20, Appendix 8, Table 2, Column 2. The ECL chosen is the most conservative value of either the soluble or insoluble ECL for each radioisotope.
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 I," 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:
Fission and Activation Gases Particulates Radioiodines Liquid Effluents I Tables 1 D and 2C give sampling frequencies and Lower Limit of Detection requirements to'r 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 1 D 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.
II. *DETAILED
*INFORMATION
{CONT'D) 1. Fission and Activation Gases The principal gamma emitters for which the LLD specification in Table 1 D applies exclusively are: Kr-87 Xe-133 Xe-135 Kr-88 Xe-133m Xe-138 Periodic grab samples from Station effluent streams are analyzed by gamma spectral analysis utilizing high-resolution germanium detectors (see Table 1 D for sampling and analytical requirements).
Isotopic values thus obtained are used for dose release rate calculations due to effluent releases as given in Section 11.A.1 of this report. The radionuclides that are detected are used in this computation.
When no radionuclides are detected, a historical default 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: Ci = *isotopic calibration factor for isotope i Ui = concentration of isotope i in the grab sample in &#xb5;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 fa.ctor defaults to a historical default mixture of Kr~88, Xe-133, Xe-135m, Xe-135, and Xe-138.
II. DETAILED INFORMATION (CONT'D) 2. Particulates and Radioiodines The principal gamma emitters for which the LLD specification in Table 1 D applies exclusively are: '1 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..:9Q 1-133 3. 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 detector.
Strontium-89/90 values are obtained by chemical separation and subsequent counting analysis using a gas flow proportional detector.
Tritium concentrations are determined using distillation and a liquid scintillation detector.
During major operational occurrences, the frequency of sampling is increased to satisfy the requirements of footnote "c" of Table 1 D, "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 11.24 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-11-0060-Rev1-EC42519 and adjusted by 224.0 full power production days. Carbon-14 curies are reported in Tables 1A and 1 C of this report and based on a constant release rate throughout the quarter. 4. Batch Releases:
Gases Gaseous *batch releases are not normally performed at GGNS.
II. DETAILED INFORMATION
{CONT'D) 5. Batch Releases:
Liquid Effluents The principal gamma emitters for which the LLD specification in Table 20 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 20. 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 20. Strontium-89/90 and lron-55 values are obtained by individual chemical separations.
Strontium-89/90 is analyzed using a gas flow proportional detector.
lron-55 is analyzed using a low energy photon detector.
Gross alpha is analyzed using a gas flow proportional detector.
Tritium is distilled and then analyzed using a liquid scintillation detector.
* 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 Time periods in minutes 1st QTR 2ndQTR 3rd QTR 4th QTR YEAR Number of Releases 11 16 29 24 80 Total Release Time 3.25E+03 4.84E+03 8.50E+03 7.40E+03 2.40E+04 Maximum Release Time 3.08E+02 3.17E+02 3.85E+02 3.90E+02 3.90E+02 Average Release Time 2.95E+02 3.02E+02 2.93E+02 3.08E+02 3.00E+02 Minimum Release Time 2.75E+02 2.90E+02 3.00E+OO 2.60E+02 3.00E+OO Average Dilution Water 4.32E+03 5.84E+03 6.65E+03 5.75E+03 5.89E+03 Flow(GPM)
The 3rd quarter Minimum Release Time resulted from a liquid discharge that terminated shortly after starting due to high activity on the liquid effluent radiation monitor. After the monitor was flushed, the tank was resampled and discharged under a new release permit.
II. DETAILED INFORMATION (CONT'D) 2. Gaseous No batch releases occurred during the report period. F. Abnormal Releases 1. Liquid a. Number of Releases:
0 b. Total Activity Released:
O.OOE+OO Ci No abnormal liquid releases were identified for this reporting period. 2. Gaseous a. Number of Releases:
0 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
& -Gross Error values in % Activation Tritium Entrained Alpha Products Gases Sampling 2.60E+01 2.60E+01 2.60E+01 2.60E+01 Measurement 6.80E+01 6.50E+01 6.10E+01 9.20E+01 TOTAL 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 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.
II. DETAILED INFORMATION (CONT'D) 2. Gaseous The maximum errors (not including sample line loss) are collectively estimated to be as follows: Fission & Gross Error values in % Activation Iodine Particulate Tritium Products Alpha Sampling 3.20E+01 2.30E+01 2.20E+01 2.20E+01 2.30E+01 Measurement 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 'I -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+/- 25%. 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 99.6%. The predominant wind dire,ction was from the north-northeast approximately 10.4% of the time. The predominant stability class was class "D" approximately 31.8% of the time. Average wind speed during the reporting period was approximately 4.1 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 CR-GGN-2017-0051
-On 1/3/17 the Containment Building Vent effluent radiation monitor had been inoperable for 30 days due to detector failure and delays in obtaining replacement parts. Also, another issue was discovered during repairs that added additional repair time to the initial job scope. The monitor was repaired, calibrated, and restored to operable status on 1 /21 /17. K. Annual Sewage Disposal Summary There were no sewage disposals in 2017.
Ill. RADIATION DOSE
 
==SUMMARY==
Indicated below is the annual summary of offsite doses attributable to GGNS during 2017. Inspection of the values indicates that GGNS releases were within the 1 OCFR50, 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 28 of this report and the calculation methodology of the ODCM. Liquid Effluents Total body dos~ 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 Ill.A 2017 Liquid Effluent Dose Dose in mrem 1stQTR 2nd QTR 3rd QTR 4th QTR TOTAL Bone 2.61 E-02 1.25E-02 1.47E-02 4.74E-02 9.45E-02 Liver 4.29E-02 1.95E-02 2.47E-02 8.46E-02 1.61 E-01 Thyroid 4.80E-04 6.56E-04 9.55E-04 9.47E-04 3.00E-03 Kidney 1.57E-02 6.77E-03 9.28E-03 3.20E-02 6.00E-02 Lung 6.08E-03 3.60E-03 3.52E-03 9.12E-03 2.09E-02 Gl..:LU 1.0tE..:02 . *5.13E.:Q3 . *3;Q8E.:Q3 1;28E.:Q2 2.85E-U2 Applicable Limit 5 5 5 5 10 Percent bf Limit 8.58E-01 3.90E-01 4.94E-01 1.69E+OO 1.61 E+OO Whole Body 2.72E-02 1.25E-02 1.73E-02 5.89E-02 1.09E-01 Applicable Limit 1.5 1.5 1.5 1.5 3 Percent of Limit 1.82E+OO 8.35E-01 1.15E+OO 3.93E+OO 3.65E+OO B. Airborne-Related Exposure Pathways The values presented in this section utilize information provided in Tables 1A and 1 C 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, on occasion, may be found within the site boundary, ~o 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 2017 meteorological data and on the most recent land use census, with the most limiting locat~on used. During normal operations, the dispersion and deposition factors used for dose calculations are from five-year historical annual average meteorological data.
Ill. 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 2017 meteorolog*ical data. The critical receptor residence was determined to *be -iocated *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 was calculated 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 historical 5-year average meteorological data. The total body and skin dose rates reported are the quarterly average of the maximum fnstantaneous dose rates determined daily during the reporting period and represent the maximum possible dose rate received by members of the public. Air*bose*from Gamma and-Seta-Emissions Air doses from gaseous effluents were calculated for this report using dispersion parameters from historical 5-year average 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 2017 as net exposure normalized to 92 days. 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 radionucli~e in gaseous effluents.
Ill. RADIATION DOSE
 
==SUMMARY==
(CONT'D) 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 (C02) during photosynthesis so doses are calculated based on the C02 fraction of the carbon released in gaseous form. A C02 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 dosefor the same organ from tritium, iodine, and particulates.
This organ dose -is recorded and compared to the -1imit -in the following table. Table 111.B 2017 Airborne Effluent Dose rt*'.c:-* **--; J:\: ,.' '*' .* ,, ':{ 1stQTR 2ndQTR 3rdQTR 4thQTR
* TOTAL --,/ .........
:-<'-';;, ,..; ' -Iodine, Tritium & Particulates (excluding Carbon-14) -Child -(mrem) 2.976-03 --6.96E-03
--6.236-03 7.376-03 -2.356-02 Organ Thyroid Thyroid Thyroid Thyroid Thyroid Applicable Limit 7.5 7.5 7.5 7.5 15 Percent of Limit 3.97E-02 9.27E-02 8.30E-02 9.82E-02 1.57E-01 *i'', *,., _:. _,_,**,:.
":' '**->' _'* ' ::_.-,*.-'.
',., "* ', '-r.;_:, ';, ,,, __ ',, *. -**_, *!-'** , .. ,;, , '*'',.;:.:;;*, ,,* ,._,. _.-, .. *** .. :**,_ ,_ /; Iodine, Tritium & Particulates (including Carbon-14)
Child (mrem) 1.22E+OO 1.70E+OO 1.20E+OO 1.22E+OO 5.34E+OO -organ Hone Hone
* Hone
* Hone Hone Applicable Limit 7.5 7.5 7.5 7.5 15 Percent of Limit 1.63E+01 2.26E+01 1.60E+01 1.63E+01 3.56E+01 -~.c~~ '"<r*.: **** 1 ,; *~~--, :,,*.----.-,,_,., .. , .*', ** ,-*.*, ... ,*c;.*;*:*-,-:*.-,,.
*,,' ,,_., ;;;.:: ,.,,_ ." 2:~;~:o~ * ~.;;~~o**
2.38E+; 11,~f1:i,iS~J Total Body Dose Rate (mrem/yr) 4.87E-01 Applicable Limit 500 500 500 500 :;I __ _ " Percent of Limit 9.74E-02 5.82E-02 1.87E+OO 4.765-01 it < ,: : **.,.' * ,:'1::-*:,,;:
~* ,*., .: ,.-.,.,_,...._, : ,,,,, ",.:_) ., .-":'".,/
.. ** ' .. \:i ': ,{ :i; */.-C'.' .t~,\ '-' I*. *" "~'.&deg; *,, .,, ,-,_ ''.,'", ..........
<<.,-, "*'* ,, "~~:~+o~* , ;,.,.;;;;;,ii Skin Dose Rate (mrem/yr) 9.30E-01 5.55E-01 1.42E+01 Applicable Limit 3000 3000 3000 Percent of Limit 3.10E-02 1.85E-02 4.73E-01 1.22E-01 (~f~;:; '*:''.:: ,:,, .. , **.*,.,,:, ,:.,,_..'
,. ,**; :,-**.,:., .. 'i .. '* ,C'',i. ,,,_IJ ,,*,: *... :.,*:-"'' . . ... '~ -~. .;*,.,'; < ,1 1 , -;<:;, j* ,-,;,,;: h ,.,, .. ,. ,,,.,, .,.,, ',,:,;-*)-*
::;:,;:'.-'.>.
,:,('_<,,,.,'
Gamma Air Dose (mrad) 2.45E-02 1.41 E-02 4.92E-02 4.65E-02 1.34E-01 Applicable Limit 5 5 5 5 10 .Percent of -Limit 4.90E-01 . -2.82E.,01
.9.84E-01
-9.30E.,Q1 1.34E+OO :!* : ~*:\ . ',"\ 'J: I , ' ' ; : *~ ".,,.~;, c ... _ ,, * ,+, *, t * *,*.; J_i*)'.' ., ',; .. , "* ._._. ,],.,.* ,,.* -._ .. **: /, , -.,, *-* *.',.";..,, ,:, ... ;,,; **-*.,*, .:*:-.,'" ;,,,_, *., ') ',' .,*-..: Beta Air Dose (mrad) 1.91E-02 1.46E-02 3.25E-02 4.67E-02 1.13E-01 ) Applicable Limit 10 10 10 10 20 Percent of Limit 1.91E-01 1.46E-01 3.25E-01 4.67E-01 5.65E-01 '11*'1 .:*.*,'., _.,. * *~-***., ';" .:: ' ,~ ... *:*"*.,,-.:., __ -_,.-,_.,,,,/''
.. '; ,*,,, ... ,, . ' " . ~-. .. ,*'_-"",*,-:, .,., _,,_,_,-:
,"/ *<, l (~' 1. * ,_.~, ., ,:''"*'-*
-: .. ,w:.,: ,;;.* ,,*:.** .',* . . __ ,.*;.,.,;*.,:-;_.
,' ,.,.,, Direct Radiation (mrem) 1.00E-01 O.OOE+OO O.OOE+OO 5.00E-01 6.00E-01 Ill. RADIATION DOSE
 
==SUMMARY==
(CONT'D) The 3rd quarter Total Body Dose Rate and Skin Dose Rate increases resulted from securing the Off Gas system vault refrigeration for repairs during plant operation, which resulted in increased effluent noble gas activity.
The 4th quarter Total Body Dose Rate and Skin Dose Rate increases resulted from continued operation-with steam leaks-that caused elevated response on-the Turbine Building Vent effluent radiation monitor due to presence of N-13. The effluent dose was calculated conservatively using the default mixture when no noble gas was detected in grab samples, and the higher effluent dose rate was driven by the higher net monitor response.
IV. OFFSITE DOSE CALCULATION MANUAU RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES ) A. Offsite Dose Calculation Manual (CDCM) The ODCM was revised in January 2017 to align usage of the terms FUNCTIONAL versus OPERABLE.
B. -Radioactive
*Waste Treatment
*Systems No major changes were made to the liquid or gaseous radioactive waste treatment systems during this reporting period.
TABLE 1A ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ~PORT -FOR *2017 Units QTR -1 QTR -2 QTR -3 QTR 4 --------------------------------------
------------------------FISSION AND ACTIVATION GASES 1. Total Release Ci 6.56E+Ol 5.40E+Ol 1.05E+02 1. 73E+02 2. Avg. Release Rate uCi/sec 8.44E+OO 6.87E+OO 1.32E+Ol 2.17E+Ol 3. Percent of TS Limit a. -Gamma *Ai-r % -N/A N/A *N/A -N/A b. Beta.Air % N/A N/A N/A N/A IODINE-131 -yEAR --------3.97E+02 1.26E+Ol *N/A N/A 1. Total Release Ci 2. Avg. Release Rate uCi/sec 3.03E-06 3.90E-07 N/A 1.84E-04 1.63E-04 2.02E-04 5.52E-04 2.34E-05 2.0SE-05 2.54E-05 1.75E-05 3. Percent of TS Limit% PARTICULATES HALF LIFE 8 DAYS 1. Total Release Ci 2. Avg. Release Rate uCi/sec 3. Percent of TS Limit% TRITIUM 1. Total Release Ci 2. Avg. Release Rate. uCi/sec 3. Percent of TS Limit% CARBON-14
: 1. Total Release 2. Avg. Release Rate Ci uCi/sec GROSS ALPHA RADIOACTIVITY 5.40E-05 6.94E-06 N/A 3.81E+OO 4.90E-01 N/A 2.57E+OO 3.27E-01 N/A N/A N/A N/A 7.65E-06 9.73E-07 N/A 5.62E+00 7.lSE-01 N/A 3.57E+OO 4.59E-01 2.88E-06 1.14E-05 3.63E-07 1.44E-06 N/A N/A 5.06E+OO 5.76E+OO 6.36E-01 7.24E-Ol N/A N/A 2.52E+OO 3.17E-01 2.57E+OO 3.24E-01 7 .59E-05 2.41E-06 N/A 2.02E+Ol 6.42E-Ol N/A 1.12E+Ol 3.56E-01 1. Total Release 2. Avg. Release Rate Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO uCi/sec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NOTE: Limits are applicable to dose, not concentration.
See Table III.Bon page 16 for percentage of dose limits.
TABLE 18 ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS
-ELEVATED RELEASES JANUARY-DECEMBER 2017 (Not Applicable
-GGNS Releases Are Considered Ground-Level)
TABLE 1C ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS
-GROUND-LEVEL RELEASE-CONTINUOUS "REPORT "FOR 2017 *uni.ts QTR 1 QTR 2 QTR -3 QTR 4 -YEAR ---------------------
-----------------------
------------------------FISSION AND ACTIVATION GASES Ar-41 Kr-85m Kr-87 -Kr-88 Xe-133 Xe-135 Xe-135m Xe-138 Total for Period IODINES I-131 I-133 Total for Period Ci Ci Ci -Ci Ci Ci Ci Ci Ci Ci Ci Ci PARTICULATES HALF LIFE~ 8 DAYS Co-58 Co-60 Mn-54 Ru-106 Se-75 Zn-65 Total OTHER H-3 C-14 for Period Gross Alpha Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 7.21E+OO 7. 62E-01 1. lSE+Ol 3.54E+OO 2.30E+Ol 9.19E-Ol 6.31E-01 4. 90E+OO i 6. OSE-01 7.06E+00 O.OOE+OO O.OOE+OO 9.82E-01 O.OOE+OO 9.82E-Ol 1.15E+OO 1.-0SE+OO
-6.-51E+OO 3.36E+OO 1.21-E+Ol 2.69E+Ol 2.46E+Ol 4.04E+Ol 7. 89E+Ol 1. 71E+02 2.57E+Ol 2.36E+Ol 3.53E+Ol 7.54E+Ol 1.60E+02 3.03E+OO 2.77E+OO 4.16E+OO 8. 89E+OO 1.89E+Ol 6.88E-01 6.29E-01 9.45E-01 2.02E+OO 4.28E+OO ----------------------------------------6.56E+Ol 5.40E+Ol 1.0SE+02 1. 73E+02 3.97E+02 3.03E-06 1.84E-04 1.63E-04 2.02E-04 5.52E-04 1.96E-05 3.69E-05 4.76E-05 1.14E-04 2.lSE-04 2.27E-05 2.21E-04 2.lOE-04 3.lSE-04 7.70E-04 9.0SE-07 2.24E-06 O.OOE+OO 3. 95E-06 7 ~'lOE-06 3.64E-05 3.21E-06 2.SOE-06 5.39E-06 4. 75E-05 l.28E-05 6.76E-07 O.OOE+OO 2.0SE-0(>
1.SSE-05 O.OOE+OO 1. 33E-06 O.OOE+OO O.OOE+OO 1.33E-06 l.62E-07 1. 92E-07 3 .86E-07 4 .44E-09 7.44E-07 3.74E-06 O.OOE+OO O.OOE+OO O.OOE+OO 3.74E-06 ----------------
------------------------5.40E-05 7.65E-06 2.88E-06 1.14E-05 7.59E-05 3.81E+OO 5.62E+OO 5.06E+OO 5.76E+OO 2.02E+Ol 2.57E+OO 3.57E+OO 2.52E+OO 2.57E+OO 1.12E+Ol O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NOTE: Only radionuclides with positive results reported.
TABLE 1-0 ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radioactive Gaseous Waste Sampling and Analysis Program JANUARY-DECEMBER 2017 Gaseous Release Sampling Minimum Analysis Type of Activity Type Frequency Frequency Analysis Principal Gamma 31 Days 31 Days Emitters (b,e) Grab Sample (f) A.(1) .Radwaste-Building -H-3 Ventilation Exhaust (2) Fuel Handling Area 7 Days (c) 1-131 Ventilation Exhaust Continuous (d) (f) Charcoal Sample 1-133 (3) Containment Principal Gamma Ventilation Exhaust 7 Days (c) Continuous (d) (f) Particulate Sample Emitters (e) (4A) Turbine Building (1-131, Others) Ventilation Exhaust Continuous (d) (f) 31 Days Composite Gross Alpha (48) Turbine Building Particulate Sample Occasional Release Point (g) Continuous (d) (f) 92 Days Composite Sr-89, Sr-90 (when in service) Particulate Sample Continuous (f) Noble Gas Monitor Noble Gases Gross Beta or Gamma B. (1) Offgas Post 31 Days Grab Principal Gamma Treatment Exhaust, Sample (f) 31 Days Emitters (e) whenever there is flow (2) Standby Gas 31 Days Grab Principal Gamma Treatment A Exhaust, 31 Days whenever there is flow Sample (f) Emitters (e) -(3) Standby-Gas 31 Days Grab Principal Gamma Treatment B Exhaust, Sample (f) 31 Days Emitters (e) whenever there is flow NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.4-1. Lower Limit of Detection (LLD) (uCi/ml) (a) 1.00E-04 1;00E-06 1.00E-12 1.00E-10 1.00E-11 1.00E-11 1.00E-11 1.00E-06 1.00E-04 1.00E-04 1.00E-04 TABLE 2A ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS
-SUMMATION OFALL RELEASES -REPORT "FOR 01, *units ---------------------
-------FISSION AND ACTIVATION PRODUCTS 1. Total Release Ci 2. Avg. Diluted Cone. uCi/ml 3. Percent of Limit % TRITIUM 1. Total Release Ci 2. Avg. Diluted Cone. uCi/ml 3. Percent of Limit % DISSOLVED AND ENTRAINED GASES 1. Total Release Ci 2. Avg. Diluted Cone. uCi/ml 3. Percent of Limit % GROSS ALPHA RADIOACTIVITY
: 1. Total Release Volume of Liquid Waste Volume of Dilution Water Ci liters liters QTR 1 QTR *2 QTR -----------------------1.87E-02 1.60E-02 3.0lE-03 3.44E-07 l.47E-07 1.39E-08 N/A N/A N/A 4.25E+00 7.77E+OO 1.30E+Ol 7.82E-05 7.14E-05 5.97E-05 N/A N/A N/A 1.79E-05 3.06E-05 3.84E-05 3.29E-10 2.81E-10 l.77E-10 N/A N/A N/A QTR 4 --------3.77E-03 2.30E-08 N/A 1.llE+Ol 6.79E-05 N/A YEAR --------4.lSE-02 7.63E-08 N/A 3.61E+Ol 6.64E-05 N/A 6.87E-05 1.56E-04 4.20E-10 2.86E-10 N/A N/A O.OOE+QO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.15E+06 1.70E+06 2.98E+06 2.56E+06 8.39E+06 5.31E+07 1.07E+08 2.14E+08 l.61E+08 5.35E+08 NOTE: Limits are applicable to dose, not concentration.
See Table III.A on page 14 for percentage of dose limits.
TABLE 28 ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS
-CONTINUOUS AND BATCH MODES "REPORT -FOR 2-017 Units QTR -1 QTR -2 QTR -3 QTR 4 YEAR --------------------
----------------------------------------FISSION AND ACTIVArION GASES AG-llOM Ci 2.95E-05 O.OOE+OO 2 .44E-05 7.28E-05 1.27E-04 AS-76 Ci O.OOE+OO 6. 61E-06 O.OOE+OO O.OOE+OO 6.61E-06 C0-58 Ci O.OOE+OO 2 .17E-05 1.98E-05 1.65E-04 2 .06E-04 -C0--60 Ci :4. lOE-04 -5.30E-04 3.84E-04 1.96E-03 3.28E-03 CS-134 Ci 3.98E-05 2.45E-05 2.95E-05 l. lSE-04 2.0SE-04 CS-137 Ci 6.28E-05 3.86E-05 8.87E-05 2.17E-04 4.07E-04 FE-55 Ci 1. 77E-02 l.SOE-02 1.53E-03 7.37E-04 3.SOE-02 LA-140 Ci O.OOE+OO O.OOE+OO O.OOE+OO 1. 74E-05 1.74E-05 MN-54 Ci 1.42E-04 8.66E-05 4.48E-06 1.0lE-04 3.34E-04 NA-24 Ci . 9.28E-06 3.83E-05 O.OOE+OO O.OOE+OO
: 4. 76E-05 PT-195M Ci O.OOE+OO O.OOE+OO O.OOE+OO 2. 62E-05 2.62E-05 RB-e88 -Ci -0 ,-OOE+OO 2 .02E""0-4 7 .53E-04 -0.-00E+OO 9.SSE-04 RU-106 Ci 2.0SE-05 O.OOE+OO O.OOE+OO O.OOE+OO 2 .OSE-05 SB-124 Ci O.OOE+OO O.OOE+OO 7. 76E-05 O.OOE+OO 7. 76E-05 SB-125 Ci 1.74E-05 O.OOE+OO 3.62E-05 O.OOE+OO 5.36E-05 ZN-65 Ci 2.06E-04 7.98E-05 6.22E-05 3 .56E-04 7.0SE-04 ----------------------------------------Total for Period Ci l.87E-02 1.60E-02 3.0lE-03 3.77E-03 4.lSE-02 TRI.TIUM Total for Period Ci 4.25E+OO 7.77E+OO 1.30E+Ol 1.llE+Ol 3.61E+Ol DISSOLVED AND ENTRAINED GASES XE-133 Ci 6.53E-06 1.34E-05 3.33E-05 5. 96E-05 1.13E-04 XE-135 Ci 1.13E-05 1.72E-05 5.lOE-06 9.06E-06 4.27E-05 ----------------------------------------Total for Period Ci 1. 79E-05 3.06E-05 3.84E-05 6.87E-05 1.56E-04 GROSS ALPHA.RADIOACTIVITY Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 
\ 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 2017 Minimum Liquid Release Sampling Analysis Type of Activity Type Frequency Frequency Analysis Principal Gamma Prior to Release Prior to Release Emitters (d) \ Each Batch Each Batch 1-131 Prior to Release Dissolved and A. Batch Waste Release One Batch/Month.
31 Days Entrained Gases Tanks (c) (Gamma Emitters)
Prior to Release 31 Days H-3 Each Batch Composite (b) Gross Alpha Prior to Release 92 Days Sr-89, Sr-90 Each Batch Composite (b) Fe-55 Principal Gamma B. SSW Basin Prior to Release Prior to Release Emitters (d) (Before Slowdown)
Each Slowdown Each Batch 1-131 *NOTE: Footnotes indicated are*listed in*GGNS*Q[)CM, Appendix A Table 6.-11:1..;1. Lower Limit of Detection (LLD) (1,1Ci/ml) (a) 5.00E-07 1.00E-06 1.00E-05 1.00E-05 1.00E-07 5.00E-08 1.00E-06 5.00E-07 1.00E-06 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 2017 A. SO LIO-WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT lRRADIATED FUEL) 1. Type of Waste Unit Class A Class B Class C Estimated Total Error a. Spent resins, filter sludges, m3 1.53E+02 9.34E-01 O.OOE+OO +/-25% evaporator bottoms, etc. Ci 2.61E+02 1.06E+02 O.OOE+OO -b. -Dry -compressible-waste, 3' 7;03E+02 -Q;OQE+OO -Q;QOE+OO -m +/-25% contaminated equipment, etc. Ci 2.92E+OO 0.00E+OO O.OOE+OO c. Irradiated components, control m3. O.OOE+OO O.OOE+OO O.OOE+OO +/-25% rods, etc. Ci O.OOE+OO O.OOE+OO O.OOE+OO
: d. Other: Oily waste drums m3 O.OOE+OO O.OOE+OO O.OOE+OO +/-25% Ci O.OOE+OO 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 (> 0.1 %) Percent Curies H-3 2.20E-01 8.10E-01 C-14 2.70E-01 9.87E-01 Cr-51 9.30E-01 3.41E+OO Mn-54 6.66E+OO 2.45E+01 .Fe-e55 .. 6.49E+01 2.38E+02 Fe-59 1.80E-01 ( 6.18E-01 Co-58 1.46E+OO 5.36E+OO Co-60 1.84E+01 6.75E+01 Ni-63 4.60E-01 1.70E+OO Zn-65 5.59E+OO 2.05E+01 Ag-110m
* 4:90E~01 1:80E+OO Cs-137 2.20E-01 8.07E-01 TABLE 3 -Continued 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 2017 b. Dry compressible waste, contaminated equipment, etc. Isotope(>
0.1%) Percent Curies H-3 3.60E-01 1.06E-02 Mn-54 6.84E+OO 2.00E-01 Fe-55 6.55E+01 1.91E+OO Co-58 2.00E-01 5.84E-03 Co-60 2.09E+01 6.09E-01 Zn-65 1.07E+OO 3.12E-02 Zr-95 1.39E+OO 4.0SE-02 Nb-95 2.72E+OO 7.94E-02 Sb-125 . 3.90_E-01 1.13_E-Q2 Cs-137 2.SOE-01 7.38E-03 Ce-144 1.60E~o1 4.57E-03 c. Irradiated components, control rods, etc. None d. Other: Oil drum sealand, mixed waste for volume reduction None TABLE 3 -Continued 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 2017 3. Solid *waste Disposition Number of J Destination Name City State Modeof
* Shipments Transportation 3 EnergySolutions, Clive Disposal Site Clive. UT Hittman (Bulk Waste Facility) 5 EnergySolutions, Clive Disposal Site Clive UT Hittman (Containerized Waste Facility) 24 EnergySolutions, Bear Creek Road Oak Ridge TN Hittman EnergySoluti~ns, Gallaher Road I 3 Facility Oak Ridge TN Hittman 2 EnergySolutions, Erwin Resin Erwin TN Hittman -Solutions B. Irradiated .Fuel Shipments (Disposition)
Number of Shipments Mode of Transportation Destination None N/A N/A J ATTACHMENT I Nuclear Energy Institute (NEI) Groundwater Protection Initiative Sample Results JANUARY -DECEMBER 2017 GPI Ground Water samples were collected from onsite Dewatering Wells (DW), Monitoring Wells {MW), Observation Wells (OW), and Sump Wells (SW). Samples were analyzed for Tritium and selected samples were analyzed for gamma and/or hard to detect (HTD) isotopes (Gross Alpha, lron-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 less than minimum detectable activity (<MDA). Tritium, gamma and/or 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 {pCi/L) CST FENCE 05/04/17 2040 <MDA -CST.FENCE
-08/1.0/17 6610 <MDA DW-01 02/22/17 1410 <MDA DW-01 05/10/17 2240 <MDA DW-01 08/22/17 3300 <MDA DW-01 11/15/17 886 <MDA DW-01 REANALYSIS 11/15/17 674 <MDA DW-02 01/23/17 <440 <MDA DW-02 02/21/17 <566 <MDA DW-02 DUPLICATE 02/21/17 <571 <MDA
* DW-02 03/22/17 <566 <MDA DW-02 04/12/17 <523 <MDA DW-02 05/09/17 <515 <MDA DW-02 DUPLICATE 05/09/17 <522 <MDA DW-02 06/20/17 <563 <MDA DW-02 07/26/17 712 <MDA DW-02 08/23/17 <576 <MDA DW-02 09/25/17 <534 <MDA DW-02 10/18/17 <562 <MDA -DW-02 11/15/17 <570 <-MDA DW-02 12/13/17 <556 <MDA DW-03 01/23/17 556 <MDA DW-03 02/21/17 695 <MDA DW-03 03/22/17 801 < !VIDA DW-03 04/12/17 <531 <MDA DW-03 05/09/17 795 <MDA LOCATION DATE TRITIUM {pCi/L} GAMMA {pCi/L} DW-03 06/20/17 <594 <MDA DW-03 07/26/17 <494 .. <MDA DW-03 DUPLICATE 07/26/17 661 <MDA DW-03 08/22/17 <587 <MDA DW-03 09/25/17 830 <MDA DW-03 10/18/17 <566 <MDA DW-03 DUPLICATE 10/18/17 <558 <MDA DW-03 11/14/17 <572 <MDA DW-03 12/13/17 <555 <MDA. DW-04 01123/17 <445 <MDA DW-04 DUPLICATE 01/23/17 <440 <MDA DW-04 02/23/17 <503 _<MDA DW-04 03/22/17 658 <MDA DW-04 04/13/17 719 <MDA DW-04 DUPLICATE 04/13/17 <530 <MDA DW-04 05/11/17 <523 <MDA --OW..;04 06/20/17 <593 <MDA DW-04 07/26/17 805 <MDA DW-04 08/23/17 <569 <MDA DW-04 09/26/17 <526 <MDA ) DW-04 10/19/17 <519 <MDA DW-04 11/14/17 <579 <MDA DW-04 12/14/17 <554 <MDA DW-05 01/24/17 <440 <MDA DW-05 02/21/17 <557 <MDA DW-05 03/22/17 <565 <MDA DW-05 04/12/17 <525 <MDA DW-05 05/10/17 <569 <MDA -DW-05 06/21/17 <563 <-MDA DW-05 DUPLICATE 06/21/17 <588 <MDA DW-05 07/27/1_7
<506 <MDA DW-05 08/23/17 <569 <MDA DW-05 09/25/17 <531 <MDA
* DW-05 10/18/17 <574 <MDA DW-05 11/16/17 <578 <MDA DW-05 12/13/17 <535 <MDA DW-06 11/15/17 <592 <MDA DW-07 02/22/17 2960 <MDA DW-07 DUPLICATE 02/22/17 3700 <MDA DW-07 05/10/17 5450 <MDA DW-07 DUPLICATE 05/10/17 5990 <MDA LOCATION DATE TRITIUM {pCi/L} GAMMA {pCi/L} DW-07 08/22/17 4800 <MDA DW-07 11/14/17 5060 *<MDA DW-08 01/24/17 <435 <MDA MW-01 01/23/17 <445 <MDA MW-01 02/22/17 <557 <MDA MW-01 03/22/17 <557 <MDA MW-01 04/12/17 <537 <MDA MW-01 05/10/17 <566 <MDA MW-01 06/20/17 <5.90 <MDA MW-01 07/26/17 <497 <MDA MW-01 08/22/17 <569 <MDA MW-01 09/25/17 626 <MDA MW-01 DUPLICATE 09/25/17 <522 <MDA MW-01 10/18/17 <554 <MDA MW-01 11/14/17 <599 <MDA MW.:01 t2/t3/17 789 <MDA MW-04 01/23/17 <444 <MDA MW-04 02/21/17 <562 <MDA MW-04 03/22/17 <565 <MDA MW-04 04/12/17 <535 <MDA MW-04 05/10/17 <573 <MDA MW-04 06/21/17 <588 <MDA MW-04 07/27/17 <498 <MDA MW-04 08/23/17 <578 <MDA MW-04 09/25/17 <535 <MDA MW-04 10/18/17 <550 <MDA MW-04 11/16/17 <579 <MDA -MW-04 I 12/13/17 <559 <-MDA MW-04 DUPLICATE
* 12/13/17 <551 <MDA MW-05 01/24/17 <445 <MDA MW-05 02/21/17 <560 <MDA MW-05 03/21/17 <566 <MDA MW-05 04/12/17 <527 <MDA MW-05 05/10/17 <563 <MDA MW-05 06/21/17 <588 <MDA MW-05 07/27/17 <515 <MDA MW-05 08/23/17 <586 <MDA MW-05 09/26/17 <529 <MDA MW-05 10/19/17 <550 <MDA MW-05 11/16/17 <579 <MDA MW-05 12/14/17 <560 <MDA LOCATION DATE TRITIUM (pCi/L) GAMMA {pCi/L) MW-06 02/23/17 1390 <MDA MW-06 05/11/17 1560 <MDA MW-06 08/24/17 1240 <MDA MW-06 11/15/17 683 <MDA MW-1008 08/24/17 <573 <MDA MW-1018 02/21/17 <518 <MDA MW-1018 05/10/17 <551 <MDA MW-1018 08/24/17 <576 <MDA .MW-101B 11/t5/17 <5.7-0 <MDA MW-1018 DUPLICATE 02/21/17 <511 <MDA MW-1028 08/23/17 <568 <MDA MW-1038 08/23/17 <583 <MDA "MW-1048 08/23/17 <577 <MDA MW-1058 02/21/17 648 <MDA MW-1058 RECOUNT 02/21/17 <522 <MDA MW-1058 05/10/17 <567 <MDA MW-1058 08/24/17 <581 <MDA MW-1058 11/14/17 <570 <MDA MW-1058 DUPLICATE 11/14/17 <585 <MDA MW-1068 02/21/17 <520 <MDA MW-1068 05/10/17 <562 <MDA MW-1068 08/23/17 <580 <MDA MW~1068 11/14/17 <525 <MDA MW-1078 02/22/17 1490 <MDA MW-1078 05/09/17 1210 <MDA MW-1078 08/22/17 968 <MDA MW-1078 11/14/17 849 <MDA MW-1088 02/22/17 827 <MDA MW-1088 05/11/17 1240 <MDA MW-1088 08/23/17 792 <MDA MW-1088 11/14/17 858 <MDA MW-1098 02/23/17 981 <MDA MW-1098 05/11/17 851 <MDA MW-1098 08/24/17 1080 <MDA MW-1098 11/15/17 917 <MDA LOCATION DATE TRITIUM (pCI/L) GAMMA {pCi/L) MW-1108 02/21/17 <500 <MDA MW-1108 05/10/17 <521 <MDA MW-1108 08/22/17 <579 <MDA MW-1108 11/14/17 <558 <MDA MW-1118 02/22/17 941 <MDA MW-1118 05/11/17 1430 <MDA, MW-1118 08/22/17 1980 * <MDA MW-1118 DUPLICATE 08/22/17 1830 <MDA MW-1118 11/15/17 1030 <MDA MW-1128 01/23/17 <600 <MDA MW-1128 02/22/17 <576 <MDA MW-1128 03/22/17 <566 <MDA MW-1128 04/13/17 <506 <MDA MW-1128 05/11/17 <530 <MDA MW-1128 *06/20/17
<593 <MDA MW..:1128 07/26/17 <499 <MDA MW-1128 08/23/17 <577 <MDA MW-1128 09/25/17 <531 <MDA MW-1128 10/18/17 <481 <MDA MW-1128 11/16/17 <570 <MDA MW-1128 12/13/17 761 <MDA MW-1138 01/24/17 <437 <MDA MW-1138 02/21/17 <518 <MDA MW-1138 03/21/17 <573 <MDA MW-1138 DUPLICATE 03/21/17 <562 <MDA MW-1138 04/13/17 <535 <MDA -MW-1138 .QS/1-0/17
<564 <MDA MW-1138 DUPLICATE 05/10/17 <574 <MDA MW-1138 \_ 06/21/17 <595 <MDA MW-1138 07/27/17 <501 <MDA MW-1138 08/22/17 <568 <MDA MW-1138 DUPLICATE 08/22/17 <56,9 <MDA MW-1138 09/26/17 <520 <MDA MW-1138 10/19/17 <514 <MDA MW-1138 11/14/17 <594 <MDA MW-1138 12/14/17 <566 <MDA MW-1148 02/21/17 2180 <MDA MW-1148 05/10/17 1800 <MDA MW-1148 08/22/17 1790 <MDA MW-1148 11/14/17 1360 <MDA LOCATION DATE TRITIUM {pCi/Ll GAMMA {pCi/Ll MW-1158 02/22/17 820 <MDA MW-1158 05/10/17 831 <MDA MW-1158 08/22/17 873 <MDA MW-1158 11/15/17 <569 <MDA MW-1158 DUPLICATE 11/15/17 <574 <MDA MW-1168 02/22/17 <561 <MDA MW-1168 05/10/17 <564 <MDA MW-1168 08/23/17 <564 <MDA MW-1168 11/15/17 <563 <MDA .MW-1 t6B DUPLICATE 11/t5/17 <58-0 <MDA MW-1188 02/22/17 <562 <I\IIDA MW-1188 05/10/17 <525 <MDA MW-1188 08/23/17 734 <MDA MW-1188 11/15/17 675 <MDA MW-1196 08/23/17 <569 <MDA MW-1208 08/22/17 <572 <MDA MW-1218 08/23/17 <571 <MDA MW-1228 01/24/17 <445 <MDA MW-1228 02/21/17 <570 <MDA MW-1228 03/21/17 <567 <MDA MW-1228 04/12/17 <523 <MDA MW-1228 05/10/17 <565 <MDA MW-1228 06/21/17 <597 <MDA MW-1228 07/26/17 <492 <MDA -MW-1228 -08/23/17
<566 <MDA MW-1228 09/26/17 <528 <MDA MW-1228 10/19/17 <570 <MDA MW-1228 11/16/17 <574 <MDA MW-1228 12/14/17 <556 <MDA MW-1238 01/24/17 <445 <MDA MW-1238 02/21/17 <564 <MDA \__,, MW-1238 03/22/17 <564 <MDA MW-1238 04/12/17 <528 <MDA MW-1238 05/11/17 <570 <MDA MW-1238 06/20/17 <599 <MDA (_, MW-1238 07/27/17 <498 <MDA MW-1238 08/23/17 <574 <MDA MW-1238 09/25/17 <535 <MDA LOCATION DATE TRITIUM CpCi/Ll MW-1238 10/18/17 <555 MW-1238 11/15/17 <576 MW-1238 12/13/17 <553 MW-1007C 08/23/17 <573 MW-1009C 08/24/17 <568 MW-1012C 08/24/17 <579 MW-1020C 08/23/17 <567 MW-1020C DUPLICATE 08/23/17 <564 MW-1024C 08/24/17 <581 MW-1027C 08/24/17 <575 MW-to42C 08/24/17 <585 MW-1082C 08/23/17 <573 MW-1134C 08/23/17 <590 P-05 08/24/17 <567 SW-103A 02/21/17 <507 SW-103A 05/10/17 <566 SW-103A 08/24/17 <579 SW-103A 11/15/17 <575 <MDA -Less than Minimum Detectable Activity DUPLICATE
-Duplicate sample-collected and analyzed RECOUNT -Re-performed same sample count GAMMA CpCi/Ll <MDA <MDA <MDA <MDA <MDA
<MDA <.MDA <MDA <MDA ~MDA <MDA <MDA <MDA <MDA <MDA <MDA <MDA <MDA REANALYSIS
-*Re-performed same sample analysis and counting ) }}

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