GNRO-2017/00028, Annual Radioactive Effluent Release Report (Arerr)For 2016
| ML17117A684 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 04/27/2017 |
| From: | Nadeau J Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GNRO-2017/00028 | |
| Download: ML17117A684 (37) | |
Text
~Entergy Entergy Operations, Inc.
P.o. Box 756 Port Gibson, MS 39150 James Nadeau Manager, Regulatory Assurance Grand Gulf Nuclear Station Tel. (601) 437-2103 GNRO-2017/00028 April 27, 2017 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Grand Gulf Nuclear Station Annual Radioactive Effluent Release Report (ARERR)
Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
Dear Sir or Madam:
Attached is the Grand Gulf Nuclear Station (GGNS) Annual Radioactive Effluent Release Report (ARERR) for period the January 1,2016 through December 31,2016. This report is submitted in accordance with the requirements of 10CFR50.36(a)(2) and GGNS Technical Specification 5.6.3. The ARERR also complies with the GGNS Offsite Dose Calculation Manual (ODCM)
This letter does not contain any new commitments. If you have any questions or require additional information concerning this report, please contact Richard Sumrall at (601) 437-2115.
SinCereIY~~/f~
JJN/sas
Attachment:
Grand Gulf Nuclear Station 2016 Annual Radioactive Release Report (ARERR) cc: (see next page)
GNRO-2017/00028 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission ATTN: Mr. Siva Lingham Mail Stop OWFN 8 B1 Rockville, MD 20852-2738 U.S. Nuclear Regulatory Commission ATTN: Mr. Kriss M. Kennedy (w/2)
Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Mr. B. J. Smith (w/2)
Director, Division of Radiological Health Mississippi State Department of Health Division of Radiological Health 3150 Lawson Street Jackson, MS 39213 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
Attachment to GNRO-2017/00028 Grand Gulf Nuclear Station 2016 Radioactive Effluent Release Report (ARERR)
ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2016 - DECEMBER 31,2016 Prepared By: Jim Reese Date Sr. Chemistry Specialist Darrell Bond ChemStaff Consultant tffJ'M R~_
Approved By: T:eve5 Acting Chemistry Manager TABLE OF CONTENTS SUBJECT PAGE I. INTRODUCTION 4 II. DETAILED INFORMATION 5 A. Regulatory Limits 5
- 1. ODCM Control Limits 5
- a. Fission and Activation Gases 5
- b. Radioiodines, Tritium and Particulates 5
- c. Liquid Effluents 5
- 2. 10CFR50, Appendix I Limits 6*
- a. Fission and Activation Gases 6
- b. Radioiodines, Tritium and Particulates 6
- c. Liquid Effluents 6
- 3. 40CFR190 Limits 7 B. Effluent Concentrations 7
- 1. Airborne 7
- 2. Liquid 7 C. Average Energy 8 D. Measurements and Approximations of Total Activity 8
- 1. For Fission and Activation Gases 9
- 2. For Particulates and Radioiodines 10
- 3. For Continuous Releases 10
- 4. For Batch Releases: Gases 10
- 5. For Batch Releases: Liquid Effluents 11 E. Batch Releases 11
- 1. Liquid 11
- 2. Gaseous 11 F. Abnormal Releases 12
- 1. Liquid 12
- 2. Gaseous 12 TABLE OF CONTENTS (CONT'D)
SUBJECT PAGE G. Estimate of Total Error 12
- 1. Liquid 12
- 2. Gaseous 13
- 3. Solid Radioactive Waste 13 H. Solid Radioactive Waste Shipments 13 I. Meteorological Data 13 J. Radioactive Effluent Monitoring Instrumentation Operability 13 K. Annual Sewage Disposal Summary 13 III. RADIATION DOSE
SUMMARY
14 A. Water-Related Exposure Pathways 14 B. Airborne-Related Exposure Pathways 14 IV. OFFSITE DOSE CALCULATION MANUAL/RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES 17 A. Offsite Dose Calculation Manual (ODCM) 17 B. Radioactive Waste Treatment Systems 17 LIST OF TABLES PAGE liLA 2016 Liquid Effluent Dose 14 III.B 2016 Airborne Effluent Dose 16 1A Gaseous Effluents - Summation of All Releases 18 1B Gaseous Effluents - Elevated Releases 19 1C Gaseous Effluents - Ground-Level Releases - Continuous 20 1D Radioactive Gaseous Waste Sampling and Analysis Program 21 2A Liquid Effluents - Summation of All Releases 22 2B Liquid Effluents - Continuous and Batch Modes 23 2C Radioactive Liquid Waste Sampling and Analysis Program 24 3 Solid Radioactive Waste and Irradiated Fuel Shipments 25 ATTACHMENTS PAGE Attachment I - Nuclear Energy Institute, NEI, Groundwater Protection Initiative 28 Sample Results I. INTRODUCTION This Annual Radioactive Effluent Release Report (ARERR) for the period of January 1 through December 31, 2016 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 releas~s are not applicable at GGNS as reported in Table 18.
The summation of all known ground-level gaseous release during the reporting period is reported in Table 1C.
The radioactive gaseous sampling and analysis program implemented at GGNS is described in Table 1D.
The summation of all liquid releases during the reporting period is reported in Table 2A.
The continuous and batch mode liquid releases are reported in Table 28.
The radioactive liquid waste sampling and analysis program implemented at GGNS is described in Table 2C.
Solid radioactive waste and irradiated fuel shipments during the reporting period are summarized in Table 3.
Groundwater Protection Initiative (GPI) well sample tritium results, which are not included in the AREOR, are included as Attachment I to the ARERR.
The annual summary of meteorological data (joint frequency distribution) will be maintained on site. The option to maintain meteorological data on site is in accordance with ODCM Administrative Controls Section 5.6.3. This data shall be provided to the Nuclear Regulatory Commission (NRC) upon request.
II. DETAILED INFORMATION A. Regulatory Limits
- 1. aDCM 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
= XlQ Li K j Q i ~ 500 mrern/yr Os = average skin dose rate in the current year (mrem/yr)
= XlQ Li (L i + 1.1 Mi ) Q i ~ 3000 mrem/yr where the terms are defined in the GGNS aDCM.
- b. Radioiodines. Tritium and Particulates - The release rate limit for the sampling period for all radioiodines, tritium and radioactive materials in particulate form with half-lives greater than 8 days shall be such that:
Do = average organ dose rate in current year (mrem/yr)
= Li W Pi Q\ ~ 1500 mrem/yr where the terms are defined in the GGNS aDCM.
- c. Liquid Effluents - The concentration of radioactive materials released in liquid effluents to unrestricted areas from the site shall not exceed at any time ten times the values specified in 10CFR20, Appendix B, Table 2, Column 2. The concentration of dissolved or entrained noble gases, released in liquid effluents to unrestricted areas from all reactors at the site, shall be limited to 2 x 10-4 microcuries/ml total activity.
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 10-8 Li Mj XlQ' Qi ::; 5 mrad/qtr
- 10 mrad/yr D~ = air dose due to beta emissions from noble gases
=3.17 x 10-8 Li Ni X/Q' Q i ::; 10 mrad/qtr
- b. Radioiodines. Tritium and Particulates - The dose to an individual from tritium, 1-131, 1-133and radioactive material in particulate form with half-lives greater than 8 days in gaseous effluents shall be such that:
Dp = dose to an individual from tritium, 1-131, 1-133 and radionuclides in particulate form with half-lives greater than 8 days (mrem)
= 3.17 X 10-8 Li Ri WI Qi::; 7.5 mrem/qtr Any Organ
- c. Liquid Effluents - The dose from radioactive materials in liquid effluents shall be such that:
m o., = L [A iTau L i
~tl 1=1 c, FI ] ::; 1.5 mrem/qtr Total Body
- 5 mrem/qtr Any Organ
- 3 mrem/yr Total Body
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) respectively, with the exception that the limits applied are:
~ 25 mrem/yr, Total Body or any Organ except Thyroid
~ 75 mrem/yr, Thyroid
~ 10 mrad y/qtr or ~ 20 mrad y/yr, Fission and Activation Gases
~ 20 mrad ~/qtr or ~ 40 mrad ~/yr, Fission and Activation Gases
~ 15 mrem/qtr or ~ 30 mrem/yr, any Organ, Iodine and Particulates
~ 3 mrem/qtr or ~ 6 mrem/yr, Total Body, Liquid Effluents
~ 10 mrem/qtr or ~ 20 mrem/yr, any Organ, Liquid Effluents B. Effluent Concentrations
- 1. Airborne The Effluent Concentration Limit (ECl) of radioactive materials in gaseous effluents is limited by the dose rate restrictions given in Section II.A.1.a. In this case, the ECls are actually determined by the dose factors in Table 2.1-1 of the GGNS ODCM.
Gaseous dose rates rather than Effluent Concentration Limits are used to calculate permissible release rates for gaseous releases. The maximum permissible dose rates for gaseous releases are defined in the GGNS ODCM 6.11.4.a as 500 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 10CFR20, Appendix B, Table 2, Column 2. The ECl chosen is the most conservative value of either the soluble or insoluble ECl for each radioisotope.
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 rnrern/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 II 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 Tables 10 and 2C give sampling frequencies and Lower Limit of Detection requirements for the analysis of gaseous and liquid effluent streams, respectively.
Values in the attached tables given as zero do not necessarily imply that the radionuclides were not present. A zero indicates that the radionuclide was not present at levels greater than the sensitivity requirements shown in Tables 10 and 2C. For some radionuclides, lower detection levels than required may be readily achievable; when a radionuclide is measured below its stated detection limits, it is reported.
(
II. DETAILED INFORMATION (CONT'D)
- 1. For Fission and Activation Gases The principal gamma emitters for which the LLD specification in Table 1D applies exclusively are:
Kr-87 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 1D for sampling and analytical requirements). Isotopic values thus obtained are used for dose release rate calculations due to effluent releases as given in Section II.A.1 of this report. Theradionuclides 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:
C, = isotopic calibration factor for isotope i Uj = concentration of isotope i in the grab sample in ~Ci/ml.
m = net monitor reading associated with the effluent stream (determined at the time of grab sampling).
These calibration factors, along with the hourly effluent monitor values and flow rates, are entered into the laboratory computer where the release rates for individual radionuclides are calculated and stored. If no activity is detected in the grab sample, the calibration factor defaults to a historical default mixture of Kr-88, Xe-133, Xe-135m, Xe-135, and Xe-138.
- g-
II. DETAILED INFORMATION (CONT'D)
- 2. For Particulates and Radioiodines The principal gamma emitters for which the LLD specification in Table 1D applies exclusively are:
Zn-65 Mo-99 Mn-54 Cs-134 Fe-59 Cs-137 Co-58 Ce-141 Co-60 Ce-144 Sr-89 1-131 Sr-90 1-133
- 3. For Continuous Releases Continuous sampling is performed on the continuous release points when releasing (i.e., Offgas/Radwaste Building, Containment Building, Fuel Handling Area, Turbine Building, and Turbine Building Occasional Release Point).
Particulate material is collected by filtration. Radioiodines are collected by adsorption onto a charcoal filter. Periodically these filters are removed and analyzed by gamma spectral analysis utilizing high-resolution Germanium detectors to identify and quantify radioactive materials collected. Particulate filters are then analyzed for gross alpha and Strontium-89/90 as required. Gross alpha is analyzed using a gas flow proportional 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 1D, "Radioactive Gaseous Waste Sampling and Analysis," (GGNS ODCM Appendix A, Table 6.11.4-1). Strontium analysis is performed by a qualified contract laboratory. Carbon-14 (C-14) activity of 8.88 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 177.5 full power production days. Carbon-14 curies are reported in Tables 1A and 1C of this report and based on a constant release rate throughout the quarter.
- 4. For Batch Releases: Gases Gaseous batch releases are not normally performed at GGNS.
II. DETAILED INFORMATION (CONT'D)
- 5. For Batch Releases: Liquid Effluents The principal gamma emitters for which the LLD specification in Table 2C applies exclusively are:
H-3 Sr-90 Mn-54 Mo-99 Fe-55 1-131 Co-58 Cs-134 Co-60 Cs-137 Fe-59 Ce-141 Zn-65 Ce-144 Sr-89 Representative pre-release grab samples are obtained and analyzed as required by Table 2C. Isotopic analyses are performed by gamma spectral analysis utilizing high-resolution germanium detectors. Aliquots of each pre-released sample, proportional to the waste volume released, are composited in accordance with the requirements of Table 2C. Strontium-89/90 and Iron-55 values are obtained by individual chemical separations. Strontium-89/90 is analyzed using a gas flow proportional detector. Iron-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 Period (Minutes)
Total Release Time 1.32E+04 4.55E+03 1.06E+04 4.48E+03 3.28E+04 Maximum Release Time 4.35E+02 3.65E+02 3.20E+02 3.10E+02 4.35E+02 Average Release Time 3.30E+02 3.03E+02 2.93E+02 2.99E+02 3.09E+02 Minimum Release Time 2.50E+01 2.84E+02 1.15E+02 2.75E+02 2.50E+01 Average Dilution Water 8.42E+03 4.94E+03 6.00e+03 3.03e+03 6.42e+03 Flow (GPM)
- 2. Gaseous No batch releases occurred during the report period.
II. DETAILED INFORMATION (CONT'D)
F. Abnormal Releases
- 1. Liquid
- a. Number of Releases: o
- b. Total Activity Released: O.OOE+OO Ci No abnormal liquid releases were identified for this reporting period.
- 2. Gaseous
- a. Number of Releases: o
- b. Total Activity Released: O.OOE+OO Ci No abnormal gaseous releases were identified for this reporting period.
G. Estimate of Total Error
- 1. Liquid The maximum errors are collectively estimated to be as follows:
Fission & Dissolved &
Gross 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 low-activity samples. Counting errors are based on measurements of blank samples.
For germanium detectors, the least-readily-detectable radioisotope is used to determine the counting error. Calibration errors are calculated by summing the errors associated with the calibration of a particular instrument with a radioactive source.
The total error is calculated by taking the square root of the sum of the squares of the individual errors.
II. DETAILED INFORMATION (CONT'D)
- 2. Gaseous The maximum errors (not including sample line loss) are collectively estimated to be as follows:
Fission & Activation Gross Iodine Particulate Alpha Products Tritium 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 1.01 E+02 6.20E+01 TOTAL % 6.90E+01 7.10E+01 6.90E+01 1.03E+02 6.60E+01 Sampling errors include uncertainty associated with sample flow, vent flow and monitor calibration.
Measurement and total errors are calculated by the same methods used for liquid effluents.
- 3. Solid Radioactive Waste Estimated Total Error % for all waste types is +/- 2.50E+01. Sampling errors include uncertainty associated with mixing and representative sampling.
H. Solid Radioactive Waste Shipments.
See Table 3 for shipment information.
I. Meteorological Data The data recovery for the reporting period was 99.9%. The predominant wind direction was from the east-northeast approximately 10.0 % of the time. The predominant stability class was class "0" approximately 29.0% of the time. Average wind speed during the reporting period was approximately 3.8 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-2016-2688 - On 3/22/16 the Liquid Radwaste Effluent monitor had been declared inoperable for 30 days due to plant shutdown where normal Circulating Water system blowdown flow was not available as the source for dilution water. The* monitor was restored to service upon restoration of Circulating Water system blowdown in preparation for plant startup.
CR-GGN-2016-9435 - On 12/10/16 the Standby Gas Treatment System 'B' effluent monitor had been inoperable for 30 days due to maintenance and installation of a new monitor. The new monitor was declared operable following completion of installation, testing and calibration.
K. Annual Sewage Disposal Summary There were no sewage disposals in 2016.
III. RADIATION DOSE
SUMMARY
Indicated below is the annual summary of offsite doses attributable to GGNS during 2016.
Inspection of the values indicates that GGNS releases were within the 10CFR50, Appendix I, design objectives.
Since there are no other fuel cycle facilities within 8 km of GGNS, 40CFR190 limits were also met during this period.
A. Water-Related Exposure Pathways The values calculated in this section utilize the information provided in Tables 2A and 2B of this report and the calculation methodology of the ODCM.
Liquid Effluents Total body dose and critical organ doses are computed for the maximum exposed individual. The maximum dose contribution from liquid effluents is considered to occur in the adult age group via consumption of fish.
Table III.A 2016 Liquid Effluent Dose mrem}
st 1 QTR 2nd QTR 3rd QTR 4th QTR TOTAL Bone 7.48E-02 2.38E-02 7.96E-03 1.23E-02 1.29E-01 Liver 1.29E-01 3.81 E-02 1.59E-02 2.75E-02 2.26E-01 Thyroid 1.97E-02 7.24E-04 1.24E-03 1.09E-03 2.80E-02 Kidney 5.23E-02 1.40E-02 7.78E-03 1.58E-02 9.39E-02 Lung 1.35E-02 4.98E-03 2.70E-03 2.58E-03 2.52E-02 GI-LLI 4.96E-02 5.63E-03 9.29E-03 1.68E-02 8.59E-02 Applicable Limit 5 5 5 5 10 Percent of Limit 2.57E+00 7.61 E-01 3.17E-01 5.50E-01 2.26E+00 Whole Body 8.20E-02 2.54E-02 9.28E-03 1.39E-02 1.42E-01 Applicable Limit 1.5 1.5 1.5 1.5 3 Percent of Limit 5.47E+00 1.69E+00 6.18E-01 9.30E-01 4.74E+00 B. Airborne-Related Exposure Pathways The values presented in this section utilize information provided in Tables 1A and 1C of this report and the calculation methodology of the ODCM. Dose and dose rates are computed for locations at the site boundary or at unrestricted areas within the site boundary. Because members of the public, on occasion, may be found within the site boundary, two fishing lakes, the recreational vehicle laydown area, and the GGNS Energy Services Center locations were also evaluated.
Consideration of site boundary locations as well as unrestricted areas within and beyond the site boundary provides assurance that offsite doses will not be substantially underestimated while attempting to provide an accurate dose calculation.
Doses for a Member of the Public are computed based on 2016 meteorological data and on the most recent land use census, with the most limiting location used.
During normal operations, the dispersion and deposition factors used for dose calculations are from five-year historical annual average meteorological data.
III. RADIATION DOSE
SUMMARY
(CONT'D)
Organ Dose The maximum organ dose to a MEMBER OF THE PUBLIC (critical receptor) from radioiodines, tritium, and particulates was calculated for this report using the most recent land use census and dispersion and deposition parameters from 2016 meteorological data. The critical receptor residence was determined to be located in the southwest sector at a distance of 1432 meters (0.89 miles) from the plant. Pathways considered for use in the organ dose calculations are inhalation, ground plane, grass/cow/meat, and vegetation. There is no grass/cow/milk pathway within five miles of GGNS. It was assumed that the age group receiving the maximum dose lived at the residence and that the receptor consumed food products that were raised or produced at the residence. This dose is documented in the following table as two separate entries. The first organ dose entry excludes C-14 while the second entry includes organ dose from tritium, radioiodines, particulates, and C-14.
Average Total Body and Skin Dose Rate Individual total body and skin dose rates from exposure to a semi-infinite cloud of noble gas 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 instantaneous dose rates determined daily during the reporting period and represent the maximum possible dose rate received by members of the public.
Air Dose from Gamma and Beta Emissions Air doses from gaseous effluents were calculated for this report using dispersion parameters from 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 2016 as net exposure normalized to 92 days.
III. RADIATION DOSE
SUMMARY
(CONT'D)
Carbon-14 Carbon-14 (C-14) is a naturally occurring isotope of carbon. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere.
Carbon-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing. In recent years, the analytical methodsfor determining C-14 have improved. Coincidentally the radioactive effluents from commercial nuclear power plants have also decreased to the point that C':'14 has emerged as a principal radionuclide in gaseous effluents.
The only significant dose pathway to a member of the public from C-14 release is through consumption of vegetation. Vegetation incorporates C-14 in form of carbon dioxide (C0 2 ) during photosynthesis so doses are calculated based on the CO 2 fraction of the carbon released in gaseous form. A CO 2 fraction of 950/0 is used based on EPRI Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents." The highest atmospheric dispersion factor for an actual garden based on the land use census was used to determine dose from C-14. Carbon-14 is dispersed as a gas (C0 2 ) to the garden location, where it is then incorporated into plant material.
Carbon-14 dose is calculated to a MEMBER OF THE PUBLIC for the most age restrictive group (Child) and organ (bone) at the garden location. This dose is then added to dose for the same organ from tritium, iodine, and particulates. This organ dose is recorded and compared to the limit in the following table.
Table III.B 2016 Airborne Effluent Dose (mrem) 1st QTR 2nd QTR 3rd QTR 4th QTR TOTAL Iodine, Tritium & Particulates (excludinq Carbon-14)
Child (mrem) 8.75E-03 4.48E-03 8.76E..03 9.97E-04 2.30E-02 Organ Thyroid Thyroid Thyroid Thyroid Thyroid Applicable Limit 7.5 7.5 7.5 7.5 15 Percent of Limit 1.17E-01 5.97E-02 1.17E-01 1.33E-02 1.53E-01 Iodine, Tritium & Particulates (including Carbon-14)
Child (mrem) 1.92E+00 3.14E+00 1.88E+00 8.51E-08 6.94E+00 Organ Bone Bone Bone Bone Bone Applicable Limit 7.5 7.5 7.5 7.5 15 Percent of Limit 2.56E+01 4.19E+01 2.51E+01 1.13E-06 4.63E+01 Total Body Dose Rate (mrem/yr) 6.19E+00 8.03E-01 1.86E+00 3.24E-02 Applicable Limit 500 500 500 500 Percent of Limit 1.24E+00 1.61E-01 3.72E-01 6.48E-03 Skin Dose Rate (mrem/yr) 1.27E+01 1.53E+00 3.13E+00 6.18E-02 Applicable Limit 3000 3000 3000 3000 Percent of Limit 4.23E-01 5.10E-02 1.04E-01 2.06E-03 Gamma Air Dose* 5.55E-02 2.56E-02 1.80E-02 3.29E-03 1.02E-01 Applicable Limit 5 5 5 5 10 Percent of Limit 1.11E+OO 5.12E-01 3.59E-01 6.59E-02 1.02E+00 Beta Air Dose* 2.96E-02 2.37E-02 1.60E-02 3.56E-03 7.29E-02 Applicable Limit 10 10 10 10 20 Percent of Limit 2.96E-01 2.37E-01 1.60E-01 3.56E-02 3.65E-01 Direct Radiation (mrem) 0.0 0.1 0.0 0.0 0.1
- Measurement units are mrad IV. OFFSITE DOSE CALCULATION MANUALI RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES A. Offsite Dose Calculation Manual (ODCM)
No revisions to the ODCM were issued during the reporting period.
B. Radioactive Waste Treatment Systems No major changes were made to the liquid or gaseous radwaste treatment systems during this reporting period.
TABLE 1A ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 2016 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases
- 1. Total Release Ci 1.21E+02 9.59E+01 6.32E+01 1.50E+01 2.95E+02
- 2. Avg. Release Rate uCi/sec 1.54E+01 1.22E+01 7.95E+00 1.88E+00 9.34E+00
- 3. Percent of TS L~it
- a. Gamma Air % N/A N/A N/A N/A N/A
- b. Beta Air % N/A N/A N/A N/A N/A Iodine-131
- 1. Total Release Ci 2.12E-04 1.10E-04 3.55E-04 3.35E-06 6.81E-04
- 2. Avg. Release Rate uCi/sec 2.70E-05 1.40E-05 4.47E-05 4.21E-07 2.15E-05
- 3. Percent of TS L~it % N/A N/A N/A N/A N/A Particulates Half Life ~ 8 days
- 3. Percent of TS L~it % N/A N/A N/A N/A N/A Tritium
- 1. Total Release Ci 8.23E+00 4.12E+00 4.91E+00 1. 46E+00 1.87E+01
- 2. Avg. Release Rate uCi/sec 1.05E+00 5.24E-01 6.18E-01 1.84E-01 5.92E-01
- 3. Percent of TS L~it % N/A N/A N/A N/A N/A Carbon 14
- 1. Total Release Ci 2.46E+00 4.02E+00 2.41E+00 O.OOE+OO 8.88E+01
- 2. Avg. Release Rate uCi/sec 3.13E-01 5.11E-01 3.03E-01 O.OOE+OO 2.81E-01 Gross Alpha
- 1. Total Release Ci 6.11E-09 3.05E-11 O.OOE+OO O.OOE+OO 6.14E-09
- 2. Avg. Release Rate uCi/sec 7.78E-10 3.88E-12 O.OOE+OO O.OOE+OO 1. 94E-10 NOTE: Limits are applicable to dose, not concentration. See Table III.B on page 16 for percentage of dose limits.
TABLE 1B ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - ELEVATED RELEASES JANUARY - DECEMBER 2016 (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 2016 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases AR-41 Ci 6.41E+00 4.50E+00 3.18E+00 O.OOE+OO 1.41E+01 KR-85 Ci 1.31E+00 O.OOE+OO O.OOE+OO O.OOE+OO 1. 31E+00 KR-85M Ci 1.68E+01 6.66E-01 4.05E+01 O.OOE+OO 1. 79E+01 KR-87 Ci 4.02E-02 O.OOE+OO 6.39E-02 O.OOE+OO 1.04E-01 KR-88 Ci 1.70E+01 1. 79E+00 1.17E+00 2.99E-01 2.02E+01 XE-131M Ci 2.57E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.57E-01 XE-133 Ci 5.74E+01 4.30E+01 2.75E+01 7.00E+00 1.35E+02 XE-133M Ci 3.15E-01 O.OOE+OO O.OOE+OO O.OOE+OO 3.15E-01 XE-135 Ci 1.87E+01 4.01E+01 2.63E+01 6.69E+00 9.18E+01 XE-135M Ci 2. 68E+00 4.73E+00 3.28E+00 7.90E-01 1.15E+01 XE-138 Ci 3.77E-01 1. 07E+00 1.34E+00 1.79E-01 2.97E+00 Totals for Period ... Ci 1.21E+02 9.59E+01 6.32E+01 1. 50E+01 2.95E+02 Iodines I-131 Ci 2.12E-04 1.10E-04 3.55E-04 3.35E-06 6.81E-04 I-133 Ci 2.25E-04 1.73E-04 1.63E-04 O.OOE+OO 5.61E-04 I-135 Ci 3.42E-05 O.OOE+OO O.OOE+OO O.OOE+OO 3.42E-05 Totals for Period ... Ci 4.71E-04 2.83E-04 5.19E-04 3.35E-06 1.28E-03 Particulates Half Life ~ 8 days AG-110M Ci 3.32E-07 5. 62E-07 O.OOE+OO O.OOE+OO 8.94E-07 CO-58 Ci 1.27E-06 1.06E-06 8.06E-06 8.96E-07 1.13E-05 CO-60 Ci 6.09E-06 3.88E-06 7.49E-06 2.31E-06 1.98E-05 Mn-54 Ci 1.34E-06 2.27E-06 5.77E-06 1.80E-07 9.56E-06 Ru-106 Ci 2.23E-06 3.78E-06 2.52E-06 O.OOE+OO 8.53E-06 Se-75 Ci O.OOE+OO O.OOE+OO O.OOE+OO 1.93E-08 1.93E-08 Totals for Period ... Ci 1. 13E-05 1.16E-05 2.38E-05 3.40E-06 5.01E-05 Other H-3 Ci 8.23E+00 4.12E+00 4.91E+00 1.46E+00 1.87E+01 C-14 Ci 2.46E+00 4.02E+00 2.41E+00 O.OOE+OO 8.88E+01 Gross Alpha Ci 6.11E-09 3.05E-11 O.OOE+OO O.OOE+OO 6.14E-09 NOTE: Only radionuclides with positive results were reported.
TABLE 10 ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radioactive Gaseous Waste Sampling and Analysis Program JANUARY - DECEMBER 2016 Lower Limit Gaseous Release Sampling Minimum Analysis Type of Activity of Detection Type Frequency Frequency Analysis (LLD)
(uCi/ml) (a)
Principal Gamma 1.0E-04 31 Days Emitters (b,e) 31 Days Grab Sample (f)
A. (1) Radwaste Building H-3 1.0E-06 Ventilation Exhaust 1-131 1.0E-12 (2) Fuel Handling Area 7 Days (c)
Ventilation Exhaust Continuous (d) (f)
Charcoal Sample 1-133 1.0E-10 (3) Containment Ventilation Exhaust Principal Gamma 7 Days (c)
Continuous (d) (f) Emitters (e) 1.0E-11 Particulate Sample (4A) Turbine Building (1-131, Others)
Ventilation Exhaust 31 Days Composite Continuous (d) (f) Gross Alpha 1.0E-11 (4B) Turbine Building Particulate Sample Occasional Release Point (g) 92 Days Composite Continuous (d) (f) Sr-89, Sr-90 1~OE-11 (when in service) Particulate Sample Noble Gases Continuous (f) Noble Gas Monitor 1.0E-06 Gross Beta or Gamma B. (1) Offgas Post 31 Days Grab Principal Gamma Treatment Exhaust, 31 Days 1.0E-04 Sample (f) Emitters (e) whenever there is flow (2) Standby Gas 31 Days Grab Principal Gamma Treatment A Exhaust, 31 Days 1.0E-04 Sample (f) Emitters (e) whenever there is flow (3) Standby Gas 31 Days Grab Principal Gamma Treatment B Exhaust, 31 Days 1.0E-04 Sample (f) Emitters (e) whenever there is flow NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.4-1.
TABLE 2A ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 2016 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products
- 1. Total Release Ci 2.72E-02 6.91E-03 1. 01E-02 6.35E-03 5.06E-02
- 2. Avg. Diluted Cone. uCi/ml 6.41E-08 7.98E-08 4.15E-08 1. 20E-07 6.26E-08
- 3. Percent of Limit % N/A N/A N/A N/A N/A Tritium
- 1. Total Release Ci 3.25E+01 7.29E+00 1.53E+01 6.83E+00 6.19E+01
- 2. Avg. Diluted Cone. uCi/ml 7.64E-05 8.42E-05 6.25E-05 1. 29E-04 7.65E-05
- 3. Percent of Limit % N/A N/A N/A N/A N/A Dissolved and Entrained Gases
- 1. Total Release Ci 6.17E-04 1.35E-05 O.OOE+OO O.OOE+OO 6.30E-04
- 2. Avg. Diluted Cone. uCi/ml 1.45E-09 1.56E-10 O.OOE+OO O.OOE+OO 7.79E-10
- 3. Percent of Limit % N/A N/A N/A N/A N/A Gross Alpha Radioactivity
- 1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Volume of liquid waste liters 4.50E+06 1.59E+06 3.71E+06 1.58E+06 1.14E+07 Volume of dil. water liters 4.21E+08 8.50E+07 2.41E+08 5.13E+07 7.98E+08 NOTE: Limits are applicable to dose, not concentration. See Table III.A on page 14 for percentage of dose limits.
TABLE 2B ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - CONTINUOUS AND BATCH MODES REPORT FOR 2016 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases AG-110M Ci 2.21E-03 1.02E-04 4.47E-05 6.99E-05 2.43E-03 AS-76 Ci O.OOE+OO 8.50E-05 1.13E-04 O.OOE+OO 1.98E-04 AU-199 Ci 3.97E-05 O.OOE+OO O.OOE+OO O.OOE+OO 3.97E-05 CE-141 Ci 1.37E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.37E-05 CO-58 Ci 7.61E-04 2.57E-05 1.26E-04 2.24E-05 9.35E-04 CO-60 Ci 4.30E-03 4.25E-04 1.07E-03 6.43E-04 6.44E-03 CR-51 Ci 4.45E-03 1.04E-04 O.OOE+OO O.OOE+OO 4.55E-03 CS-134 Ci 1.11E-04 2.79E-05 8.47E-06 O.OOE+OO 1.47E-04 CS-137 Ci 5.74E-04 1.04E-04 2.23E-05 1.46E-05 7.15E-04 FE-55 Ci 9.20E-03 5.71E-03 8.24E-03 4.89E-03 2.80E-02 1-131 Ci 9.84E-04 O.OOE+OO O.OOE+OO O.OOE+OO 9.84E-04 LA-140 Ci 5.78E-05 O.OOE+OO O.OOE+OO O.OOE+OO 5.78E-05 MN-54 Ci 2.06E-03 8.72E-05 2.41E-04 4.03E-05 2.43E-03 NA-24 Ci 8.20E-06 1. 62E-05 O.OOE+OO O.OOE+OO 2.44E-05 NB-95 Ci 3.76E-05 O.OOE+OO O.OOE+OO O.OOE+OO 3.76E-05 PT-195M Ci 3.19E-05 2.37E-05 1.87E-05 4.34E-05 1.18E-04 RU-106 Ci 2.11E-04 O.OOE+OO O.OOE+OO O.OOE+OO 2.11E-04 SB-124 Ci 1.37E-04 7.86E-06 O.OOE+OO 6.75E-06 1.51E-04 SB-125 Ci 1. 23E-04 5.91E-05 O.OOE+OO 2.52E-04 4.34E-04 SE-75 Ci O.OOE+OO 5.61E-06 O.OOE+OO O.OOE+OO 5.61E-06 SR-92 Ci 1.08E-04 O.OOE+OO 5.51E-06 1.08E-06 1.15E-04 Y-88 Ci O.OOE+OO 1.69E-05 O.OOE+OO O.OOE+OO 1.69E-05 ZN-65 Ci 1. 32E-03 1.08E-04 2.43E-04 3.69E-04 2.04E-03 ZR-95 Ci 1.20E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.20E-05 ZR-97 Ci 3.60E-05 O.OOE+OO O.OOE+OO O.OOE+OO 3.60 -05 Totals for Period ... Ci 2'. 72E-02 6.91E-03 1.01E-02 6.35E-03 5.06E-02 Tritium H-3 Ci 3.25E+01 7.29E+00 1.53E+01 6.83E+00 6.19E+01 Totals for Period ... Ci 3.25E+01 7.29E+00 1.53E+01 6.83E+00 6.19E+01 Dissolved and Entrained Gases XE-133 Ci 6.17E-04 3.87E-06 O.OOE+OO O.OOE+OO 6.21E-04 XE-135 Ci O.OOE+OO 9.65E-06 O.OOE+OO O.OOE+OO 9.65E-06 Totals for Period ... Ci 6.17E-04 1.35E-05 O.OOE+OO O.OOe+OO 6.30E-04 Gross Alpha Radioactivity ALPHA Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Totals for Period ... Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 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 2016 Lower Limit Minimum Liquid Release Sampling Type of Activity of Detection Analysis Type Frequency Analysis (LLD)
Frequency (IJCi/ml) (a)
Principal Gamma Prior to Release Prior to Release 5.0E-07 Emitters (d)
Each Batch Each Batch 1-131 1.0E-06 Dissolved and Prior to Release 31 Days Entrained Gases 1.0E-05 A. Batch Waste Release One Batch/Month (Gamma Emitters)
Tanks (c)
Prior to Release 31 Days H-3 1.0E-05 Each Batch Composite (b) Gross Alpha 1.0E-07 Prior to Release 92 Days Sr-89, Sr-90 5.0E-08 Each Batch Composite (b) Fe-55 1.0E-06 Principal Gamma B. SSW Basin Prior to Release Prior to Release 5.0E-07 Emitters (d)
(Before Blowdown) Each Blowdown Each Batch 1-131 1.0E-06 NOTE: Footnotes indicated are listed in GGNS aDeM, Appendix A Table 6.11.1-1.
- . 24-
TABLE 3 ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY - DECEMBER 2016 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)
Estimated
- 1. Type of Waste Unit Class A Class ~ Class C Total Error
- a. Spent resins, filter sludges, m3 1.22E+02 2.86E+00 O.OOE+OO
+/-25%
evaporator bottoms, etc. Ci 2.22E+02 4.79E+02 O.OOE+OO 3
- b. Dry compressible waste, m 1.33E+03 O.OOE+OO O.OOE+OO
+/-25%
contaminated equipment, etc. Ci 2.02E-00 O.OOE+OO O.OOE+OO 3
- c. Irradiated components, control m O.OOE+OO O.OOE+OO O.OOE+OO
+/-25%
rods, etc. Ci O.OOE+OO .O.OOE+OO O.OOE+OO 3
m 3.14E+01 O.OOE+OO O.OOE+OO
- d. Other: Oily waste drums +/-25%
Ci 1.09E-02 O.OOE+OO O.OOE+OO
- 2. Estimate of Major Nuclide Composition (by type of waste)
- a. Spent resins, filter sludges, evaporator bottoms, etc.
Isotope (greater than 0.1%) Percent Curies Cr-51 2.03 1.42E+01 Mn-54 6.90 4.83E+01 Fe-55 67.45 4.72E+02 Fe-59 0.58 4.08E+00 Co-58 2.39 1.67E+01 Co-60 15.01 1.05E+02 Ni-63 0.31 2.19E+00 Zn-65 4.37 3.05E+01 Nb-95 0.12 8.36E-01 Ag-110m 0.31 2.13E+00 Cs-137 0.13 8.89E-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 2016
- b. Dry compressible waste, contaminated equipment, etc.
Isotope (greater than 0.1%) Percent Curies H-3 2.34 4.74E-02 Mn-54 7.64 1.55E-01 Fe-55 43.19 8.76E-01 Fe-59 0.11 2.16E-03 Co-60 39.36 7.98E-01 Ni-63 0.67 1.35E-02 Zn-65 2.72 5.52E-02 Zr-95 0.70 1.42E-02 Nb-95 1.25 2.53E-02 Tc-99 0.30 6.00E-03 Ag-110m 0.20 2.96E-03 Cs-137 0.70 1.41E-02 Ce-144 0.62 1.26E-02
- c. Irradiated components, control rods, etc.
None
- d. Other: Oil Drum Sealand Isotope (greater than 0.1%) Percent Curies H-3 2.72 2.98E-04 Mn-54 5.30 5.80E-04 Fe-55 47.34 5.19E-03 Co-60 40.08 4.39E-03 Ni-63 0.73 7.96E-05 Zn-65 2.29 2.50E-04 Tc-99 0.29 3.12E-05 Cs-137 0.64 7.04E-05 Ce-144 0.50 5.48E-05 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 2016
- 3. Solid Waste Disposition Number of Mode of Destination Name City State Shipments Transportation 30 EnergySolutions (Bear Creek), LLC Oak Ridge TN Hittman Energy Solutions 5 Oak Ridge TN Hittman Gallaher Road Facility 1 Erwin Resin Solution, LLC Erwin TN Hittman EnergySolutions LLC 1 Clive UT Hittman Containerized Waste Facility EnergySolutions, LLC 4 Clive UT Hittman Bulk Waste Facility 1 ALARON Corporation Wampum PA Hittman 1 Unitech/Babcock Services, Inc. Oak Ridge TN Hittman NRC Disposal Number of Description Waste Type Description Class Volume (ft3) Containers B 120.3 8/120 HIC 1 Poly HIC - RWCU-A A 205.8 215 liner 15 Poly Liner - SRT A 90.0 B-25 20 Metal/DAW A 1180.0 20' SEALAND 46 DAW/GIC/Oil A 680.0 20' Intermodal 1 GIC Stainless Steel Liner-A 199.4 ES-210 (solidification) 9 CPS/RWCU-B A 75.7 Small PAC Tec Bag 2 High Rad DAW B. Irradiated Fuel Shipments (Disposition)
II Num ber of Shipments I Mode of Transportation I Destination I I None N/A I N/A I ATTACHMENT I Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results JANUARY - DECEMBER 2016 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, Iron-55, Nickel-63, Strontium-89 and Strontium-90). Analyses are to the Lower Level of Detection (LLD) values for the GGNS Radiological Environmental Monitoring Program.
No dose to the public is attributed to ground water since wells with results above MDA are bounded by wells which are 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)
DW-01 02/17/16 3020 <MDA DW-01 OS/26/16 4820 <MDA DW-01 09/08/16 3680 <MDA DW-01 12/07/16 2750 <MDA DW-02 01/21/16 <563 <MDA DW-02 02/18/16 <545 <MDA DW-02 DUPLICATE 02/18/16 <556 <MDA DW-02 03/14/16 <498 <MDA DW-02 04/18/16 <465 <MDA DW-02 OS/24/16 572 <MDA DW-02 06/15/16 1520 <MDA DW-02 07/19/16 1630 <MDA DW-02 08/09/16 817 <MDA DW-02 09/07/16 1800 <MDA DW-02 DUPLICATE 09/07/16 1790 <MDA DW-02 10/18/16 730 <MDA DW-02 11/09/16 608 <MDA DW-02 12/07/16 549 <MDA DW-03 01/21/16 870 <MDA DW-03 02/18/16 612 <MDA DW-03 03/14/16 960 <MDA DW-03 DUPLICATE 03/14/16 631 <MDA DW-03 04/18/16 597 <MDA DW-03 OS/24/16 <521 <MDA DW-03 06/15/16 920 <MDA DW-03 07/19/16, 1020 <MDA DW-03 DUPLICATE 07/19/16 580 <MDA LOCATION DATE TRITIUM (pCi/L) GAMMA (pCi/L)
DW-03 08/09/16 <484 <MDA DW-03 DUPLICATE 08/09/16 565 <MDA DW-03 09/07/16 <585 <MDA DW-03 10/18/16 <529 <MDA DW-03 DUPLICATE 10/18/16 748 <MDA DW-03 11/09/16 <572 <MDA DW-03 DUPLICATE 11/09/16 <552 <MDA DW-03 12/07/16 <498 <MDA DW-04 01/20/16 621 <MDA DW-04 DUPLICATE 01/20/16 702 <MDA DW-04 02/18/16 <543 <MDA DW-04 03/14/16 <425 <MDA DW-04 04/19/16 544 <MDA DW-04 OS/24/16 <501 <MDA DW-04 06/15/16 697 <MDA DW-04 07/19/16 1280 <MDA DW-04 08/09/16 <489 <MDA DW-04 09/07/16 745 <MDA DW-04 10/18/16 722 <MDA DW-04 11/11/16 615 <MDA DW-04 12/07/16 555 <MDA DW-05 01/20/16 <563 <MDA DW-05 02/18/16 <548 <MDA DW-05 03/15/16 <493 <MDA DW-05 04/19/16 <462 <MDA DW-05 OS/25/16 <510 <MDA DW-05 06/15/16 <482 <MDA DW-05 07/19/16 <509 <MDA DW-05 08/09/16 <485 <MDA DW-05 09/07/16 <589 <MDA DW-05 10/18/16 <524 <MDA DW-05 11/10/16 <566 <MDA DW-05 12/08/16 <502 <MDA DW-07 02/16/16 4230 <MDA DW-07 OS/26/16 3270 <MDA DW-07 09/06/16 3530 <MDA DW-07 DUPLICATE 09/06/16 3320 <MDA DW-07 12/06/16 3220 <MDA DW-07 DUPLICATE 12/06/16 3050 <MDA LOCATION DATE TRITIUM (pCi/L) GAMMA (pCi/L)
MW-01 01/21/16 <561 <MDA MW-01 02/18/16 <552 <MDA MW-01 03/14/16 <497 <MDA MW-01 04/18/16 <447 <MDA MW-01 OS/24/16 <514 <MDA MW-01 06/15/16 777 <MDA MW-01 07/19/16 941 <MDA MW-01 08/09/16 648 <MDA MW-01 09/07/16 1080 <MDA MW-01 10/18/16 644 <MDA MW-01 11/09/16 791 <MDA MW-01 12/07/16 <501 <MDA MW-04 01/20/16 <560 <MDA MW-04 02/18/16 <548 <MDA MW-04 03/15/16 <493 <MDA MW-04 04/19/16 <463 <MDA MW-04 OS/25/16 <510 <MDA MW-04 06/15/16 <484 <MDA MW-04 07/19/16 <520 <MDA MW-04 08/09/16 <494 <MDA MW-04 09/07/16 <585 <MDA MW-04 10/19/16 <528 <MDA MW-04 11/11/16 <570 <MDA MW-04 12/08/16 <501 <MDA MW-05 01/20/16 <500 <MDA MW-05 02/17/16 765 <MDA MW-05 RECOUNT 02/17/16 1370 MW-05 REANAL YSIS 02/17/16 999 MW-05 03/15/16 691 <MDA MW-05 04/19/16 <457 <MDA MW-05 OS/25/16 <522 <MDA MW-05 06/16/16 721 <MDA MW-05 07/20/16 569 <MDA MW-05 08/10/16 <483 <MDA MW-05 09/07/16 <561 <MDA MW-05 10/19/16 <530 <MDA MW-05 11/11/16 <585 <MDA MW-05 12/08/16 <500 <MDA MW-06 02/17/16 1180 <MDA MW-06 OS/26/16 1770 <MDA MW-06 09/08/16 1890 <MDA LOCATION DATE TRITIUM (pCi/L) GAMMA (pCi/L)
MW-06 12/09/16 1330 <MDA MW-1008 09/07/16 <577 <MDA MW-1018 02/17/16 <584 <MDA MW-1018 05/25/16 <509 <MDA MW-1018 09/07/16 <567 <MDA MW-1018 12/07/16 <497 <MDA MW-1028 09/07/16 <571 <MDA MW-1038 09/08/16 <572 <MDA MW-1048 09/08/16 <574 <MDA MW-1058 02/17/16 <576 <MDA MW-1058 05/25/16 <529 <MDA MW-1058 09/07/16 <540 <MDA MW-1058 12/07/16 <501 <MDA MW-1068 02/17/16 <576 <MDA MW-1068 05/25/16 <516 <MDA MW-1068 09/07/16 <563 <MDA MW-1068 12/06/16 <504 <MDA MW-1078 02/16/16 1920 <MDA MW-1078 05/25/16 1210 <MDA MW-1078 09/06/16 1670 <MDA MW-1078 12/06/16 1560 <MDA MW-1088 02/17/16 1500 <MDA MW-1088 05/26/16 1220 <MDA MW-1088 09/07/16 1360 <MDA MW-1088 12/08/16 971 <MDA MW-1098 02/17/16 712 <MDA MW-1098 RECOUNT 02/17/16 970 MW-1098 REANALYSIS 02/17/16 1220 MW-1098 05/26/16 <514 <MDA MW-1098 09/07/16 818 <MDA MW-1098 12/08/16 1080 <MDA MW-1108 02/16/16 <583 <MDA MW-1108 05/24/16 <512 <MDA LOCATION DATE TRITIUM (pCi/L) GAMMA {pCilL}
MW-1108 09/07/16 <578 <MDA MW-1108 12/06/16 <502 <MDA MW-1118 02/17/16 1690 <MDA MW-1118 OS/25/16 3200 <MDA MW-1118 DUPLICATE OS/25/16 3180 <MDA MW-1118 09/08/16 <579 <MDA MW-1118 12/07/16 962 <MDA MW-1128 01/21/16 <563 <MDA MW-1128 02/18/16 <550 <MDA MW-1128 DUPLICATE 02/18/16 <547 <MDA MW-1128 03/14/16 <497 <MDA MW-1128 04/18/16 <446 <MDA MW-1128 OS/25/16 <504 <MDA MW-1128 06/15/16 <487 <MDA MW-1128 07/19/16 <425 <MDA MW-1128 08/09/16 <487 <MDA MW-1128 09/07/16 <545 <MDA MW-1128 10/18/16 <532 <MDA MW-1128 11/09/16 <571 <MDA MW-1128 12/07/16 <509 <MDA MW-1138 01/21/16 <569 <MDA MW-1138 02/17/16 <573 <MDA MW-1138 DUPLICATE 02/17/16 <579 <MDA MW-1138 03/15/16 <495 <MDA MW-1138 04/18/16 <459 <MDA MW-1138 DUPLICATE 04/18/16 <451 <MDA MW-1138 OS/24/16 <514 <MDA MW-1138 DUPLICATE OS/24/16 <515 <MDA MW-1138 06/20/16 <500 <MDA MW-1138 07/20/16 <511 <MDA MW-1138 08/10/16 <480 <MDA MW-1138 09/08/16 <577 <MDA MW-1138 DUPLICATE 09/08/16 <581 <MDA MW-1138 10/19/16 <530 <MDA MW-1138 11/11/16 <566 <MDA MW-1138 12/06/16 <499 <MDA MW-1138 DUPLICATE 12/06/16 <490 <MDA MW-1148 02/17/16 2960 <MDA MW-1148 OS/24/16 2160 <MDA MW-1148 09/08/16 1850 <MDA LOCATION DATE TRITIUM (pCi/L) GAMMA (pCi/L)
MW-114B 12/06/16 2530 <MDA MW-115B 02/17/16 685 <MDA MW-115B OS/24/16 2040 <MDA MW-115B 09/08/16 675 <MDA MW-115B 12/07/16 <508 <MDA MW-116B 02/17/16 <578 <MDA MW-116B OS/24/16 <517 <MDA MW-116B 09/08/16 <580 <MDA MW-116B 12/06/16 <509 <MDA MW-116B DUPLICATE 12/06/16 <490 <MDA MW-118B 02/17/16 <580 <MDA MW-118B OS/25/16 772 <MDA MW-118B DUPLICATE OS/25/16 584 <MDA MW-118B 09/08/16 711 <MDA MW-118B 12/06/16 <498 <MDA MW-119B 09/07/16 <588 <MDA MW-119B DUPLICATE 09/07/16 <578 <MDA MW-120B 09/08/16 <565 <MDA MW-121B 09/08/16 <577 <MDA MW-122B 01/20/16 <558 <MDA MW-122B 02/18/16 <555 <MDA MW-122B 03/15/16 <495 <MDA MW-122B 04/19/16 <463 <MDA MW-122B OS/25/16 <507 <MDA MW-122B 06/16/16 <505 <MDA MW-122B 07/20/16 <509 <MDA MW-122B 08/10/16 <482 <MDA MW-122B 09/07/16 <582 <MDA MW-122B 10/19/16 <530 <MDA MW-122B 11/11/16 <579 <MDA MW-122B 12/08/16 <502 <MDA MW-123B 01/21/16 <563 <MDA MW-123B 02/18/16 <540 <MDA MW-123B 03/15/16 <486 <MDA MW-123B 04/19/16 <449 <MDA MW-123B OS/25/16 <522 <MDA LOCATION DATE TRITIUM (pCi/L) GAMMA (pCi/L)
MW-1238 06/16/16 <510 <MDA MW-1238 DUPLICATE 06/16/16 <499 <MDA MW-1238 07/20/16 <425 <MDA MW-1238 08/09/16 <482 <MDA MW-1238 09/07/16 <582 <MDA MW-1238 10/19/16 <525 <MDA MW-1238 11/10/16 <570 <MDA MW-1238 12/07/16 <498 <MDA MW-1007C 09/07/16 <570 <MDA MW-1009C 09/07/16 <568 <MDA MW-1012C 09/08/16 <576 <MDA MW-1020C 09/07/16 <565 <MDA MW-1020C DUPLICATE 09/07/16 <568 <MDA MW-1024C 09/07/16 <573 <MDA MW-1027C 09/08/16 <582 <MDA MW-1042C 09/08/16 <579 <MDA MW-1082C 09/08/16 <568 <MDA MW-1134C 09/09/16 <564 <MDA SW-102 OS/24/16 <520 <MDA SW-103A 02/18/16 <569 <MDA SW-103A OS/24/16 <519 <MDA SW-103A 09/08/16 <567 <MDA SW-103A 12/06/16 <502 <MDA
<MDA - Less than Minimum Detectable Activity DUPLICATE - Duplicate sample collected and analyzed RECOUNT - Re-performed same sample count REANALYSIS - Re-performed same sample analysis and counting