GNRO-2014/00037, 2013 Annual Radioactive Effluent Release Report
| ML14121A041 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 04/30/2014 |
| From: | Nadeau J Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GNRO-2014/00037 | |
| Download: ML14121A041 (33) | |
Text
~
~Entergy Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150 James J Nadeau Manager, Regulatory Assurance Grand Gulf Nuclear Station Tel. (601) 437-2103 GNRO-2014/00037 April 30, 2014 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Grand Gulf Nuclear Station (GGNS) 2013 Annual Radioactive Effluent Release Report (ARERR)
Grand Gulf Nuclear Station (GGNS), Unit 1 Docket No. 50-416 License No. NPF-29
Dear Sir or Madam:
Attached is the GGNS Annual Radioactive Effluent Release Report (ARERR) for the period January 1, 2013 through December 31, 2013. This report is submitted in accordance with the requirements of 10CFR50.36a(a)(2) and the GGNS Technical Specification (TS) 5.6.3. The ARERR also complies with the GGNS Offsite Dose Calculation Manual (ODCM).
This letter does not contain any commitments.
If you have questions or require additional information concerning this report, please contact Richard Sumrall at (601) 437-2115.
Sincerely, JJN/ra/~j{k Attachments: 2013 Annual Radioactive Effluent Release Report cc: (See next page)
GNRO-2014/00037 Page 2 of 2 cc: NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U. S. Nuclear Regulatory Commission ATTN: Marc L. Dapas (w/2)
Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 U. S. Nuclear Regulatory Commission ATTN: Mr. Alan Wang, NRR/DORL (w/2)
Mail Stop OWFN 8 B1 Washington, DC 20555-0001 Mr. B. J. Smith Director, Division of Radiological Health Mississippi State Department of Health Division of Radiological Health 3150 Lawson Street Jackson, MS 39213 Dr. Mary Currier, M.D., M.P.H State Health Officer Mississippi Department of Health P.O. Box 1700 Jackson, MS 39215-1700
Attachment to GNRO-2014/00037 2013 Annual Radioactive Effluent Release Report
ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1,2013 - December 31,2013
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TABLE OF CONTENTS SUBJECT PAGE I. INTRODUCTION 4 II. DETAILED INFORMATION 5 A. Regulatory Limits 5
- 1. 10CFR20 Limits 5
- a. Fission and Activation Gases 5
- b. Radioiodines, Tritium and Particulates 5
- c. Liquid Effluents 5
- 2. 10CFR50, Appendix I, Limits 6
- a. Fission and Activation Gases 6
- b. Radioiodines, Tritium and Particulates 6
- c. Liquid Effluents 6
- 3. 40CFR 190 Limits 7 B. Effluent Concentrations 7
- 1. Airborne 7
- 2. Liquid 7 C. Average Energy 7 D. Measurements and Approximations of Total Activity 8
- 1. For Fission and Activation Gases 8
- 2. For Particulates and Radioiodines 9
- 3. For Continuous Releases 9
- 4. For Batch Releases: Gases 9
- 5. For Batch Releases: Liquid Effluents 10 E. Batch Releases 10
- 1. Liquid 10
- 2. Gaseous 10 F. Abnormal Releases II
- 1. Liquid II
- 2. Gaseous II env-tec/ARERR01 - 2
TABLE OF CONTENTS (CONT'D)
SUBJECT PAGE G. Estimate of Total Error II
- 1. Liquid II
- 2. Gaseous 12
- 3. Solid Radioactive Waste 12 H. Solid Radioactive Waste Shipments 12 I. Meteorological Data 12 J. Radioactive Effluent Monitoring Instrumentation Operability 12 K. Annual Sewage Disposal Summary 13 III. RADIATION DOSE
SUMMARY
13 A. Water-Related Exposure Pathway 13 B. Airborne-Related Exposure Pathway 13 IV. OFFSITE DOSE CALCULATION MANUALIRADIOACTIVE WASTE TREATMENT SYSTEM CHANGES 16 A. Offsite Dose Calculation Manual (ODCM) 16 B. Radioactive Waste Treatment Systems 16 LIST OF TABLES PAGE lA Gaseous Effluents - Summation of All Releases 17 IB Gaseous Effluents - Elevated Releases 18 lC Gaseous Effluents - Ground-Level Releases - Continuous 19 ID Radioactive Gaseous Waste Sampling and Analysis Program 20 2A Liquid Effluents - Summation of All Releases 21 2B Liquid Effluents - Continuous and Batch Modes 22 2C Radioactive Liquid Waste Sampling and Analysis Program 23 3 Solid Radioactive Waste and Irradiated Fuel Shipments 24 ATTACHMENTS PAGE Attachment I - Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results 27 env-tec/ARERR01 - 3
I. INTRODUCTION This Annual Radioactive Effluent Release Report (ARERR) for the period of January 1 through December 31, 2013, is submitted in accordance with Technical Specifications, Section 5.6.3, of Grand Gulf Nuclear Station (GGNS) License No. NPF-29* and base on data provided by GGNS.
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 lB.
The summation of all known ground-level gaseous release during the reporting period is reported in Table lC.
The radioactive gaseous sampling and analysis program implemented at GGNS is described in Table lD.
The summation of all liquid releases during the reporting period is reported in Table 2A The continuous and batch mode liquid-releases are reported in Table 2B.
The radioactive liquid waste sampling and analysis program implemented at GGNS is described in Table 2C.
Solid radioactive waste and irradiated fuel shipments during the reporting period are summarized in Table 3.
Groundwater Protection Initiative (GPI) well sample tritium results which are not included in the AREOR are incl uded as Attachment I to the ARERR.
The annual summary of meteorological data (joint frequencidistribution) 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.
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II. DETAILED INFORMATION A. Regulatory Limits
- 1. 10CFR20 Limits
- a. Fission and Activation Gases - The release rate limit at any time for noble gases to areas at or beyond the site boundary shall be such that:
D tb = average total body dose rate in the current year (mremlyr)
= XlQ Li K j Qj ~ 500 mremlyr D s = average skin dose rate in the current year (mremlyr)
= XlQ Lj (L i + 1.1 M i ) Q i ~ 3000 mremlyr where the terms are defined in the GGNS ODCM.
- b. Radioiodines, Tritium and Particulates - The release rate limit for the sampling period for all radioiodines, tritium and radioactive materials in particulate form with half-lives greater than 8 days shall be such that:
Do = average organ dose rate in current year (mremlyr)
= Lj W Pi Q\ $ 1500 mremlyr where the terms are defined in the GGNS ODCM.
- c. Liquid Effluents - The concentration of radioactive materials released in liquid effluents to unrestricted areas from the site shall not exceed at any time ten times the values specified in 10CFR20, Appendix B, Table 2, Column 2. The concentration of dissolved or entrained noble gases, released in liquid effluents to unrestricted areas from all reactors at the site, shall be limited to 2 x 10-4 microcuries/ml total activity.
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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:
DY= air dose due to gamma emissions from noble gases
= 3.17 X 10-8 Li M i XlQ' Qi ::;; 5 mrad/qtr
- 10 mrad/yr D~ = air dose due to beta emissions from noble gases
= 3.17 X 10-8 Li N i X/Q' Qi ::;; 10 mrad/qtr
- b. Radioiodines, Tritium and Particulates - The dose to an individual from tritium, 1-131,1-133 and radioactive material in particulate form with half-lives greater than 8 days in gaseous effluents shall be such that:
Dp = dose to an individual from tritium, 1-131, 1-133 and radionuclides in particulate form with half-lives greater than 8 days (mrem)
= 3.17 X 10-8 Li R i W' Qi::;; 7.5 mrem/qtr Any Organ
- c. Liquid Effluents - The dose from radioactive materials in liquid effluents shall be such that:
m DTau = L [A iTau L ~tl C il F I ] ::;; 1.5 mrem/qtr Total Body i 1=1
- 5 mrem/qtr Any Organ
- 3 mrem/yr Total Body
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II. DETAILED INFORMATION (CONT'D)
- 3. 40CFR190 Limits Doses are calculated for Fission and Activation Gases; Radioiodines and Particulates; and Liquid Effluents according to equations contained in Sections 2.(a), (b), and (c) respectively, with the exception that the limits applied are:
~25 mrem/yr, Total Body or any Organ except Thyroid
~75 mrem/yr, Thyroid
~lO 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
~l 0 mrem/qtr or ~20 mrem/yr, any Organ, Liquid Effluents B. Effluent Concentrations
- 1. Airborne The Effluent Concentration Limit (ECL) of radioactive materials in gaseous effluents is limited by the dose rate restrictions given in Section II.A.l.a. In this case, the ECLs are actually determined by the dose factors in Table 2.1-1 of the GGNS ODCM.
- 2. Liquid The ECL of radioactive materials in liquid effluents is limited by ten times the values in 10CFR20, Appendix B, Table 2, Column 2. The ECL chosen is the most conservative value of either the soluble or insoluble ECL for each radioisotope.
C. Average Energy Not applicable for GGNS ODCM Appendix A.
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II. DETAILED INFORMATION (CONT'D)
D. Measurements and Approximations of Total Activity The following discussion details the methods used to measure and approximate the total activity for the following:
Fission and Activation Gases Particulates Radioiodines Liquid Effluents Tables ID and 2C give sampling frequencies and Lower Limit of Detection requirements for the analysis of gaseous and liquid effluent streams, respectively.
Values in the attached tables given as zero do not necessarily imply that the radionuclides were not present. A zero indicates that the radionuclide was not present at levels greater than the sensitivity requirements shown in Tables 1D and 2C. For some radionuclides, lower detection levels than required may be readily achievable; when a radionuclide is measured below its stated detection limits, it is reported.
- 1. For Fission and Activation Gases At a miniumum, the following noble gases are considered in evaluating gaseous airborne discharges: .
Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-138 Periodic grab samples from Station effluent streams are analyzed by gamma spectral analysis utilizing high-resolution germanium detectors. (See Table ID 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.l of this report. The radionuclides that are detected are used in this computation. When no radionuclides are detected, a historical mixture is used. During the period between grab samples, the amount of radioactivity released is based on the effluent monitor readings. Monitors are assigned a calibration factor based upon the last isotopic analysis, using the following relationship: .
where C j = isotopic calibration factor for isotope i Vi = concentration of isotope i in the grab sample in 11 Ci/ml.
m = net monitor reading associated with the effluent stream (determined at the time of grab sampling).
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II. DETAILED INFORMATION (CONT'D)
These calibration factors, along with the hourly effluent monitor values and flow rates, are entered into the laboratory computer where the release rates for individual radionuclides are calculated and stored. If no activity is detected in the grab sample, the calibration factor defaults to a historical mixture of Kr-88, Xe-133, Xe-135m, Xe-135, and Xe-138.
- 2. For Particulates and Radioiodines At a minimum, the following radioiodines and radioactive materials in particulate form to be considered 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 Other detected radionuclides with half lives greater than 8 days.
- 3. For Continuous Releases Continuous sample collection 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. Radio-iodines are collected by adsorption onto a charcoal filter.
Periodically these filters are removed and analyzed by gamma spectral analysis utilizing high-resolution germanium detectors to identify and quantify radioactive materials collected. Particulate filters are then analyzed for gross alpha and Strontium-89/90 as required. Gross alpha is analyzed using a gas flow proportional technique. Strontium-89/90 values are obtained by chemical separation and subsequent counting analysis using gas flow proportional techniques. Tritium samples are collected on molecular sieve and concentrations are determined using distillation and liquid scintillation techniques.
During major operational occurrences, the frequency of sampling is increased to satisfy the requirements of footnote "c" of Table ID, "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) curies are reported in Tables lA and lC of this report and based on a constant release rate throughout the year.
Activity of 9.5 Curies released per year in gaseous form is used based on:
GGNS Final Safety Analysis Report Table 11.3-9 which utilizes BWR-Gale Code and says, "C-14 Released via Main Condenser Offgas System = 9.5 Ci/Yr." This is assumed to be the total released in gaseous form based on International Atomic Energy Agency Technical Reports Series No. 421, Management of Waste Containing Tritium and Carbon-14 which says, "The following systems have been considered to be release pathways for gaseous 14C from a BWR:" ... "The condenser steam jet air ejector is expected to be the most significant release point (>99% of total 14C release)."
- 4. For Batch Releases: Gases Gaseous batch releases are not normally performed at GGNS.
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II. DETAILED INFORMATION (CONT'D)
- 5. For Batch Releases: Liquid Effluents At a minimum, the radionuclides listed below are considered when evaluating liquid effluents:
H-3 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-8,9/90 and Iron-55 values are obtained by individual chemical separations.
Strontium-89/90 is analyzed using gas flow proportional techniques. Iron-55 is analyzed using liquid scintillation techniques. Gross alpha is analyzed using a gas flow proportional technique. Tritium concentrations are determined using distillation and liquid scintillation techniques. Dissolved gases are determined employing grab sampling techniques and analyzed by gamma spectral analysis utilizing high-resolution germanium detectors. Iron and Strontium analyses are performed by a qualified contract laboratory.
E. Batch Releases
- 1. Liquid I. Number of releases Time Period (in minutes)
- 2. Total for all batches
- 3. Max time for a batch 5.75E+02
- 4. Av time for a batch 2.94E+02
- 5. Min time for a batch I.OOE+OO
- 6. Avg Stream Flow (LPM) 1.76E+04
- 2. Gaseous No batch releases occurred during the report period.
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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: 2
- b. Total Activity Released: 3.62E-Ol Ci Two abnormal gaseous releases were identified during the reporting period. Both of the releases occurred when Turbine Building Smoke Exhaust (root) hatches thought to be closed were' found open. Both instances occurred following a planned release. As a conservative measure, it was assumed that the hatches opened immediately after being checked closed and remained open until documentation showed hatches were closed.
Applying this assumption yields the following release parameters:
The planned release occurred 10/5/13 01 :00 until 10/7/13 19:43.
The first unplanned release started 10/7/13 19:43 and ended 10/9/13 18: 11.
CR 2013-6394 was written for the first release.
The second unplanned release started 10/9/13 18: 11 and ended 10/1 0/13 00:06.
CR 2013-6404 was written for second release.
Isotopic concentrations used for the planned release were also used for the unplanned releases since they were essentially a continuation of the planned release.
The activity and doses associated with these releases are included in the Airborne Effluent Dose table in section III.B and in Table lA and in Table lC of this report.
G. Estimate of Total Error
- 1. Liquid The maximum errors are collectively estimated to be as follows:
Fission &
Activation Tritium Dissolved & Entrained Gross Products Gases Al ha Sampling % 2.60E+Ol 2.60E+Ol 2.60E+OI 2.60E+OI Measurement % 6.80E+OI 6.50E+OI 6.10E+Ol 9.20E+OI TOTAL % 7.30E+Ol 7.00E+OI 6.60E+OI 9.50E+Ol env-tec/ARERR01-11
II. DETAILED INFORMATION (CONT'D)
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.
- 2. Gaseous The maximum errors (not including sample line loss) are collectively estimated to be as follows:
Fission & Activation Gross Products Iodine Particulate Al ha Tritium 3.20E+OI 2.30E+01 2.20E+OI 2.20E+Ol 2.30E+Ol 6.lOE+0l 6.70E+Ol 6.50E+Ol 1.OIE+02 6.20E+Ol 6.90E+Ol 7.lOE+Ol 6.90E+Ol 1.03E+02 6.60E+Ol 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 99.2%. The predominant wind direction was from the Northeast approximately 11.7% of the time. The predominant stability class was class "D" approximately 30.6% of the time. Average wind speed during the reporting period was approximately 3.9 miles per hour at the 33 foot elevation.
The annual meteorological data (Hourly Average Data or Joint Frequency Distribution) will be maintained on site in a file that shall be provided to the NRC upon request.
J. Radioactive Effluent Monitoring Instrumentation Operability No instances of reportable inoperability were identified for this reporting period.
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II. DETAILED INFORMATION (CONT'D)
K. Annual Sewage Disposal Summary There were no sewage disposals for this reporting period.
III. RADIATION DOSE
SUMMARY
Indicated below is the annual summary of offsite doses attributable to GGNS during 2013. 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 kIn of GGNS, 40CFR190 limits were also met during this period.
A. Water-Related Exposure Pathways The values calculated in this section utilize the information provided in Tables 2A and 2B of this report and the calculation methodology of the ODCM.
Liquid Effluents Total body dose and critical organ doses are computed for the maximum exposed individual.
The maximum dose contribution from liquid effluents is considered to occur in the adult age group via consumption of fish.
2013 L'lCUl'd Effl uent Dose mrem 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr TOTAL Bone 3.31E-02 8.96E-03 3.77E-02 4.25E-03 7.98E-02 Liver 5.89E-02 2.35E-02 6.25E-02 1.20E-02 1.49E-OI Thyroid 2.12E-03 2.21E-03 1.70E-03 1.10E-03 6.72E-03 Kidney 2.63E-02 1.32E-02 2.35E-02 7.38E-03 6.62E-02 Lung 6.90E-03 3.00E-03 7.66E-03 1.37E-03 1.80E-02 GI-LLI 2.24E-02 1.89E-02 1.04E-02 8.71E-03 5.50E-02 Applicable Limit 5 5 5 5 10 Percent of Limit 1.18E+00 4.70E-Ol 1.25E+00 2.40E-Ol 1.49E+00 Whole Body 3.49E-02 1.24E-02 4.20E-02 6.47E-03 9.71E-02 Applicable Limit 1.5 1.5 1.5 1.5 3 Percent of Limit 2.33E+00 8.27E-Ol 2.80E+00 4.31E-Ol 3.24E+00 B. Airborne-Related Exposure Pathways The values presented in this section utilize information provided in Tables 1A and 1C of this report and the calculation methodology of the ODCM. Dose and dose rates are computed for locations at the site boundary or at unrestricted areas within the site boundary. Because members of the public may, on occasion, be found within the site boundary, two fishing lakes, the recreational vehicle laydown area, and the GGNS Energy Services Center locations were also evaluated.
Consideration of site boundary locations as well as unrestricted areas within and beyond the site boundary provides assurance that offsite doses will not be substantially underestimated while attempting to provide an accurate dose calculation.
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III. RADIATION DOSE
SUMMARY
(CONT'D)
Doses for a Member of the Public (critical receptor) are computed based on 2013 meteorological data and 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.
Organ Dose The maximum organ dose to a MEMBER OF THE PUBLIC from radioiodines, tritium, and particulates was calculated for this report using the most recent land use census and dispersion and deposition parameters from 2013 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.
Doses due to Carbon-14 release were calculated using Electric Power Research Institute, EPRI, methodology and calculation software which was validated on site using Regulatory Guide 1.109. The doses are documented in the following table as two separate entries. The first organ dose entry excludes C-14 while the second entry includes organ dose from tritium, radioiodines, particulates, and C-14. .
Average Total Body and Skin Dose Rate Individual total body and skin dose rates from exposure to a semi-infinite cloud of noble gas are computed for a location in the southwest sector at a distance of 1368 meters (0.85 miles) from the plant. This location corresponds to the highest annual average atmospheric dispersion factor for a location at or within the site boundary based on 2013 meteorological data.
The total body and skin dose rates reported are the quarterly average of the maximum instantaneous dose rates determined daily during the reporting period and represent the maximum possible dose rate received by members of the public.
Air Dose from Gamma and Beta Emissions Air doses from gaseous effluents were calculated for this report using dispersion parameters from the 2013 meteorological data. The highest dispersion factor for an unrestricted area was in the southwest sector at the site boundary, 1368 meters (0.85 miles) from the plant.
Direct Radiation Direct radiation dose is calculated by subtracting average doses measured by thermoluminescent dosimeter (TLD) badges located at control locations from average doses measured by TLD badges located near the site boundary. GGNS reported measured doses in 2013 as net exposure normalized to 92 days.
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III. RADIATION DOSE
SUMMARY
(CONT'D)
Carbon-14 Carbon-14 (C-14) is a naturally occurring isotope of carbon. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Carbon-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing. In recent years, the analytical methods for determining C-14 have improved. Coincidentally the radioactive effluents from commercial nuclear power plants have also decreased to the point that C-14 has emerged as a principal radionuclide in gaseous effluents.
The only significant dose pathway to a member of the public from C-14 release is through consumption of vegetation. Vegetation incorporates C-14 in the form of carbon dioxide (C0 2) during photosynthesis, therefore doses are calculated based on the CO 2 fraction of the carbon
. released in gaseous form. A CO 2 fraction of 95% is used based on EPRI Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents". The highest atmospheric dispersion factor for an actual garden based on the land use census was used to determine dose from C-14. Carbon-14 is dispersed as a gas (C0 2) to the garden location, where it is then incorporated into plant material.
Carbon-14 dose is calculated to a MEMBER OF THE PUBLIC for the most age restrictive group (Child) and organ (bone) at the garden location. This C-14 dose is then added to dose from tritium, iodine, and particulates for the same age group and organ. This organ dose is recorded and compared to the limit in the following table.
2013 Airborne Effluent Dose (mrem) 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr TOTAL Iodine, Tritium & Particulates (excluding Carbon-14)
Child (mrem) 2.29E-02 2.IIE-02 2.10E-02 3.25E-02 9.74E-02 Organ Thyroid Thyroid Thyroid Thyroid Thyroid Applicable Limit 7.5 7.5 7.5 7.5 15 Percent of Limit 3.05E-Ol 2.8IE-Ol 2.80E-Ol 4.33E-Ol 6.50E-Ol Iodine, Tritium & Particulates (including Carbon-14)
Child (mrem) 3.l6E+00 3.l9E+00 3.23E+00 . 3.23E+00 1.28E+OI Organ Bone Bone Bone Bone Bone Applicable Limit 7.5 7.5 7.5 7.5 15 Percent of Limit 4.21E+Ol 4.26E+Ol 4.30E+Ol 4.30E+Ol 8.53E+OI Total Body Dose Rate (mrem/yr) 4.96E-OI 7.29E-Ol 1.99E+00 2.tOE-Ol Applicable Limit 500 500 500 500 Percent of Limit 9.92E-02 1.46E-Ol 3.98E-Ol 4.20E-02 Skin Dose Rate (mrem/yr) 7.78E-Ol 1.07E+00 3.56E+00 3.22E-Ol Applicable Limit 3000 3000 3000 3000 Percent of Limit 2.59E-02 3.57E-02 1.19E-Ol 1.07E-02 Gamma Air Dose* 2.63E-Ol 4.22E-Ol l.08E+00 l.05E-01 1.87E+00 Applicable Limit 5 5 5 5 to Percent of Limit 5.26E+00 8.44E+00 2.l5E+Ol 2.11E+00 1.87E+Ol Beta Air Dose* 1.31E-01 1.71E-01 9.87E-Ol 5.46E-02 1.34E+00 Applicable Limit 10 to to 10 20 Percent of Limit 1.31E+00 l.7IE+00 9.87E+00 5.46E-Ol 6.72E+00 Direct Radiation (mrem) 0.0 0.0 0.3 1.3 1.6
- Measurement umts are mrad env-tec/ARERR01-15
IV. OFFSITE DOSE CALCULATION MANUAL/
RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES A. affsite Dose Calculation Manual (aDCM)
No revisions to the aDCM were issued during the reporting period.
Two aDCM revisions performed in 2012 were found not to have all the required reviews. The changes shown below received final reviews in 2013 with no changes made to the revisions.
Revisions 38 and 39 of the aDCM were issued in 2012. The revisions included:
Description of Change(s) Revision Month/Year Affected Number of Change Page Number(s)
Revise 6.3.9 to add condition E. Condition E is 38 03/2012 i, ia, vii, to acknowledge that as long as flow is viib, monitored and measured, there is no need to A-14 suspend dilution flow activities LBDCR 12- 012 Revise Table 6.3.10-1 Section 3B to include 39 03/2012 i, vii, note h. Note h is to acknowledge :S4 Turbine viia, viib, Building roof hatches may be open in Modes 4 2.0-35, A-and 5. LDCR 2012-017 26, A-28, A-39, A-41 B. Radioactive Waste Treatment Systems No major changes were made to the liquid or gaseous radwaste treatment systems during this reporting period.
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TABLEIA ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES JANUARY - DECEMBER 2013 REPORT FOR 2013 Units QTR1 QTR 2 QTR 3 QTR4 YEAR Fission and Activation Gases
- 1. Total Release Ci 1.20E+02 1.86E+02 1.54E+03 7.42E+Ol 1.92E+03
- 2. Avg. Release Rate uCi/sec 1.54E+Ol 2.37E+Ol 1.94E+02 9.34E+OO 6.09E+Ol
- 3. Percent of TS Limit
- a. Gamma Air % 5.26E+OO 8.44E+OO 2.l5E+Ol 2.llE+OO 1.87E+Ol
- b. Beta Air % 1.31E+OO 1.71E+OO 9.87E+OO 5.46E-Ol 6.72E+OO Iodine-131
- 1. Total Release Ci 3.03E-04 5.98E-05 1.73E-04 7.81E-04 1.32E-03
- 2. Avg. Release Rate uCi/sec 3.90E-05 7.61E-06 2.l8E-05 9.82E-05 4.l7E-05
- 3. Percent of TS Limit % 8.26E-02 1. 63E-02 4.72E-02 2.l3E-Ol 1. 80E-Ol Particulates Half Life >= 8 days
- 1. Total Release Ci 8.40E-05 8.83E-06 1.55E-05 5.46E-05 1.63E-04
- 2. Avg. Release Rate uCi/sec 1.08E-05 1.12E-06 1.95E-06 6.86E-06 5.l7E-06
- 1. Total Release Ci 8.26E+OO 1.02E+Ol 9.05E+OO 7.88E+OO 3.54E+Ol
- 2. Avg. Release Rate uCi/sec 1.06E+OO 1.30E+OO 1.14E+OO 9.92E-Ol 1.12E+OO
- 3. Percent of TS Limit % 2.06E-Ol 2.55E-Ol 2.26E-Ol 1.97E-Ol 4.42E-Ol Carbon 14
- 1. *Total Release Ci 2.34E+OO 2.37E+OO 2.39E+OO 2.39E+OO 9.50E+OO
- 2. Avg. Release Rate uCi/sec 3.01E-Ol 3.01E-Ol 3.01E-Ol 3.01E-Ol 3.01E-Ol Gross Alpha
- 1. Total Release Ci 4.92E-08 1.34E-07 6.99E-08 7.70E-08 3.30E-07
- 2. Avg. Release Rate uCi/sec 6.33E-09 1.71E-08 8.79E-09 9.68E-09 1.05E-08 env-tec/ARERR01 - 17
TABLEIB ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - ELEVATED RELEASES JANUARY - DECEMBER 2013 (Not Applicable - GGNS Releases Are Considered Ground-Level) env-tec1ARERR01 - 18
TABLE1C ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - GROUND-LEVEL RELEASE-CONTINUOUS JANUARY - DECEMBER 2013 REPORT FOR 2013 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases AR-41 Ci 1.17E+01 2.99E+01 1.31E+01 8.38E+OO 6.31E+01 KR-85M Ci 1.51E+01 3.06E+01 1.64E+01 6.93E+OO 6.90E+01 KR-87 Ci 1.31E+01 7.38E+OO 1.12E+01 7.20E-01 3.24E+01 KR-88 Ci 3.20E+01 5.09E+01 6.13E+01 1.01E+01 1.54E+02 KR-89 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO XE-133 Ci 2.48E+01 3.96E+01 6.83E+02 2.65E+01 7.74E+02 XE-135 Ci 2.00E+01 2.44E+01 6.49E+02 1.90E+01 7.12E+02 XE-135M Ci 2.35E+OO 2.86E+OO 8.83E+01 2.16E+OO 9.57E+01 XE-137 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO XE-138 Ci 5.32E-01 6.49E-01 1.73E+01 4.90E-01 1.89E+01 Totals for Period ... Ci 1.20E+02 1.86E+02 1.54E+03 7.42E+01 1.92E+03 Iodines 1-131 Ci 3.03E-04 5.98E-05 1. 73E-04 7.81E-04 1. 32E-03 1-133 Ci 7.13E-04 4.21E-04 3.31E-04 1.08E-03 2.54E-03 1-135 Ci 4.63E-04 3.64E-04 O.OOE+OO 1.51E-04 9.78E-04 Totals for Period ... Ci 1. 48E-03 8.44E-04 5.04E-04 2.01E-03 4.84E-03 Particulates Half Life >= 8 days AG-110M Ci 6.43E-06 O.OOE+OO O.OOE+OO 1.19E-06 7.63E-06 BA-140 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CO-58 Ci 2.62E-06 4.36E-06 O.OOE+OO 8.51E-06 1.55E-05 CO-60 Ci 3.38E-05 O.OOE+OO 2.25E-06 1.71E-05 5.32E-05 CR-51 Ci O.OOE+OO O.OOE+OO O.OOE+OO 3.45E-06 3.45E-06 CS-134 Ci 4.38E-07 O.OOE+OO O.OOE+OO O.OOE+OO 4.38E-07 CS-137 Ci 4.03E-06 O.OOE+OO 6.32E-07 O.OOE+OO 4.67E-06 FE-55 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO MN-54 Ci 1.23E-05 1.83E-06 1.12E-06 1.92E-05 3.45E-05 RU-106 Ci 2.43E-06 6.13E-07 1.12E-05 O.OOE+OO 1.42E-05 SR-89 Ci 6.86E-07 1.49E-06 O.OOE+OO O.OOE+OO 2.17E-06 SR-90 Ci 1.97E-07 5.34E-07 3.55E-07 O.OOE+OO 1.09E-06 ZN-65 Ci 2.10E-05 O.OOE+OO O.OOE+OO 5.07E-06 2.61E-05 Totals for Period ... Ci 8.40E-05 8.83E-06 1.55E-05 5.46E-05 1. 63E-04 Other H-3 Ci 8.26E+OO 1.02E+01 9.05E+OO 7.88E+OO 3.54E+01 C-14 Ci 2.34E+OO 2.37E+OO 2.39E+OO 2.39E+OO 9.50E+OO ALPHA Ci 4.92E-08 1.34E-07 6.99E-08 7.70E-08 3.30E-07 env-lec/ARERR01-19
TABLE ID ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radioactive Gaseous Waste Sampling and Analysis Program JANUARY - DECEMBER 2013 Lower Limit Sampling Minimum Analysis Type of Activity Analysis of Detection Gaseous Release Type Frequency Frequency (LLD)
( uCi/ml)a A. (1) Radwaste Building 31 Days 31 Days Principal Gamma Emitters Ventilation Exhaust Grab Sample (f) {M) Ix 10-4 H-3 IXIO- 6 (2) Fuel Handling Area Continuous (d)(f) 7 Days (c) 1-131 IxlQ-L Ventilation Exhaust Charcoal Sample 1-133 Ix 10- 10 (3) Containment Continuous (d)(f) 7 Days (c) Principal Gamma Emitters IxlQ-11 Ventilation Exhaust Particulate Sample (e) (1-131, Others)
(4A) Turbine Building Continuous (d)(f) 31 Days Composite Gross Alpha IxlQ-11 Ventilation Exhaust Particulate Sample (4B) Turbine Building Occasional Continuous (d)(f) 92 Days Composite Sr-89, Sr-90 IxlQ-11 Release Point(g) Particulate Sample (when in service)
Continuous (f) Noble Gas Monitor Noble Gases Gross Beta or IxlQ-tJ Gamma B. (l) Offgas Post 31' Days Grab 31 Days Principal Gamma Emitters IxlQ-4 Treatment Exhaust, Sample (f) (e) whenever there is flow (2) Standby Gas 31 Days Grab 31 Days Principal Gamma IxlQ-4 Treatment A Exhaust, Sample (f) Emitters(e) whenever there is flow (3) Standby Gas 31 Days Grab 31 Days Principal Gamma IxlQ-4 Treatment B Exhaust, Sample (f) Emitters(e) whenever there is flow NOTE: Footnotes mdIcated are lIsted m GGNS ODCM, AppendIx A, Table 6.11.4-1.
env-tec/ARERR01 - 20
TABLE2A ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES JANUARY - DECEMBER 2013 REPORT FOR 2013 Units QTR1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products
- 1. Total Release Ci 1.72E-02 1.73E-02 1. 32E-02 3.67E-03 5.14E-02
- 2. Avg. Diluted Cone. uCi/ml 9.06E-08 6.41E-08 3.01E-08 9.80E-09 4.04E-08
- 3. Percent of Limit % 2.33E+00 8.28E-01 2.80E+00 4.32E-01 3.06E+00 Tritium
- 1. Total Release Ci 1.99E+01 2.45E+01 2.42E+01 1.68E+01 8.54E+01
- 2. Avg. Diluted Cone. uCi/ml 1.05E-04 9.05E-05 5.54E-05 4.50E-05 6.72E-05
- 3. Percent of Limit % 1.05E+00 9.05E-01 5.54E-01 4.50E-01 6.72E-01 Dissolved and Entrained Gases
- 1. Total Release Ci 2.35E-04 8.60E-04 1.97E-04 2.08E-04 1. 50E-03
- 2. Avg. Diluted Cone. uCi/ml 1.24E-09 3.18E-09 4.52E-10 5.55E-10 1.18E-09
- 3. Percent of Limit % 6.20E-04 1.59E-03 2.26E-04 2.78E-04 5.90E-04 Gross Alpha Radioactivity
- 1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO 9.71E-06 9.71E-06 Volume of liquid waste liters 3.55E+06 4.14E+06 5.29E+06 4.48E+06 1.75E+07 Volume of dil. water liters 1.87E+08 2.66E+08 4.31E+08 3.70E+08 1.25E+09 env-tec/ARERR01 - 21
TABLE2B ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - CONTINUOUS AND BATCH MODES JANUARY - DECEMBER 2013 REPORT FOR 2013 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products AG-110M Ci 2.38E-03 3.43E-03 4.29E-04 4.87E-04 6.73E-03 AS-76 Ci 5.02E-05 3.56E-05 7.32E-05 3.24E-04 4.83E-04 AU-199 Ci O.OOE+OO O.OOE+OO O.OOE+OO 3.86E-06 3.86E-06 BA-140 Ci O.OOE+OO O.OOE+OO 1.30E-05 O.OOE+OO 1.30E-05 CO-58 Ci 3.88E-04 4.12E-04 3.41E-04 1.03E-04 1.24E-03 CO-60 Ci 5.41E-04 5.90E-04 .s.60E-04 5.25E-04 2.22E-03 CR-51 Ci 2.12E-03 4.44E-05 1.02E-04 2.61E-04 2.53E-03 CS-134 Ci 5.85E-06 O.OOE+OO 5.67E-05 O.OOE+OO 6.26E-05 CS-137 Ci 1. 41E-04 2.67E-05 2.78E-04 1.57E-05 4.62E-04 FE-55 Ci 5.86E-03 3.89E-03 O.OOE+OO O.OOE+OO 9.75E-03 FE-59 Ci 7.11E-05 O.OOE+OO O.OOE+OO O.OOE+OO 7.11E-05 1-131 Ci O.OOE+OO 6.03E-06 4.49E-06 O.OOE+OO 1. 05E-05 LA-140 Ci 3.33E-05 9.90E-06 O.OOE+OO O.OOE+OO 4.32E-05 MN-54 Ci 7.76E-04 9.86E-04 5.56E-04 3.84E-04 2.70E-03 NA-24 Ci 1. 33E-04 O.OOE+OO 8.74E-05 O.OOE+OO 2.20E-04 PT-195M Ci O.OOE+OO O.OOE+OO 5.40E-05 3.84E-05 9.24E-05 RB-88 Ci 3.50E-03 6.28E-03 8.28E-03 8.67E-04 1. 89E-02 RU-106 Ci 2.02E-04 5.22E-04 9.58E-04 1.17E-04 1.80E-03 SB-124 Ci 1. 93E-04 1.78E-04 3.91E-04 6.17E-05 8.24E-04 SB-125 Ci 8.07E-05 8.57E-05 5.87E-04 2.39E-05 7.77E-04 SE-75 Ci 5.09E-06 O.OOE+OO 1.54E-05 O.OOE+OO 2.05E-05 SR-91 Ci O.OOE+OO O.OOE+OO 4.61E-06 O.OOE+OO 4.61E-06 SR-92 Ci 1.23E-04 3.02E-04 5.61E-05 7.16E-05 5.52E-04 TC-99M Ci 1.28E-05 O.OOE+OO O.OOE+OO 4.15E-06 1.69E-05 W-187 Ci 9.75E-07 3.97E-06 O.OOE+OO O.OOE+OO 4.95E-06 ZN-65 Ci 5.02E-04 4.86E-04 2.41E-04 3.74E-04 1. 60E-03 ZN-69M Ci 3.07E-06 O.OOE+OO 4.70E-05 4.32E-06 5.44E-05 ZR-95 Ci O.OOE+OO O.OOE+OO 1.53E-05 O.OOE+OO 1. 53E-05 ZR-97 Ci 8.53E-05 3.94E-05 O.OOE+OO O.OOE+OO 1.25E-04 Totals for Period ... Ci 1.72E-02 1. 73E-02 1.32E-02 3.67E-03 5.14E-02 Tritium H-3 Ci 1. 99E+01 2.45E+01 2.42E+01 1. 68E+01 8.54E+01 Totals for Period ... Ci 1.99E+01 2.45E+01 2.42E+01 1.68E+01 8.54E+01 Dissolved and Entrained Gases XE-133 ci 1.83E-04 5.41E-04 1.33E-04 1.48E-04 1.00E-03 XE-135 Ci 5.23E-05 3.19E-04 6.45E-05 5.99E-05 4.95E-04 Totals for Period ... Ci 2.35E-04 8.60E-04 1.97E-04 2.08E-04 1.50E-03 Gross Alpha Radioactivity ALPHA Ci O.OOE+OO O.OOE+OO O.OOE+OO 9.71E-06 9.71E-06 Totals for Period ... Ci O.OOE+OO O.OOE+OO O.OOE+OO 9.71E-06 9.71E-06 env-tec/ARERR01 - 22
TABLE2C ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM JANUARY - DECEMBER 2013 Lower Limit Sampling Minimum Analysis Type of Activity Analysis of Detection Liquid Release Type Frequency Frequency (LLD)
( uCi/ml)(a)
A. Batch Waste Release Prior to Release Prior to Release Each Principal Gamma Emitters Tanks (c) Each Batch Batch @ 5xlO- 7 1-131 IX 10-6 Prior to Release 31 Days Dissolved and Entrained Ix 10-5 One Batch 1M Gases (Gamma Emitters)
Prior to Release 31 Days H-3 IxlO-:>
Each Batch Composite (b) Gross Alpha IxlO- 7 Prior to Release 92 Days Composite Sr-89, Sr-90 5xlO-~
Each Batch (b) Fe-55 Ix 10-6 B. SSW Basin (Before Prior to Release Prior to Release Each Principal Gamma Emitters Blowdown) Each Blowdown Batch @ 5xlO- 7 1-131 lxlO- 6 NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.1-1.
env-tec/ARERR01 - 23
TABLE 3 ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY - DECEMBER 2013 SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)
Est. Total
- 1. Type of Waste Unit Class A Class B Class C Error %
- a. Spent resins, filter sludges, m3 1.30E+02 O.OOE+OO O.OOE+OO
+/- 25%
evaporator bottoms, etc. Ci 6.03E+Ol O.OOE+OO O.OOE+OO
- b. Dry compressible waste, m3 4. 12E+02 O.OOE+OO O.OOE+OO
+/- 25%
contaminated equipment, etc. Ci 8.38E-02 O.OOE+OO O.OOE+OO
- c. Irradiated components, m3 O.OOE+OO O.OOE+OO O.OOE+OO
+/- 25%
control rods, etc. Ci O.OOE+OO O.OOE+OO O.OOE+OO
- d. Other: Condensate Pre-Coat Septa m3 O.OOE+OO O.OOE+OO O.OOE+OO
+/- 25%
Bundle Ci O.OOE+OO O.OOE+OO O.OOE+OO env-tec/ARERR01 - 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 2013 (Cont)
- 2. Estimate of Major Nuclide Composition (by type of waste)
- a. Spent resins, filter sludges, evaporator bottoms, etc.
Isotope (2reater than 1 %) Percent Curies Co-60 17 1.03E+OI Cs-137 1.4 8.40E-OI Fe-55 42.4 2.56E+Ol Fe-59 1 5.60E-OI Mn-54 17 I.05E+Ol Zn-65 17.7 I.07E+OI
- b. Dry Compressible waste, contaminated equipment, etc.
Isotope (2reater than 1 % ) Percent Curies Co-60 42.6 3.57E-02 Cr-51 5.8 4.9E-03 Fe-55 11.8 9.9E-03 Fe-59 3.2 2.7E-03 Mn-54 27.3 2.3E-02 Zn-65 5.1 4.3E-03 Ag-IIOm I 8.5E-04 Co-58 1.5 1.3E-03
- c. Irradiated components, control rods, etc.
None
- d. Other: N/A env-tec/ARERR01 - 25
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 2013 (Cont)
- 3. Solid Waste Disposition Number of Mode of Destination Name City State Shipments Transportation 13 EnergySolutions(Duratek), LLC Oak Ridge TN Rittman 3 EnergySolutions -; Gallaher Road Facility Oak Ridge TN Rittman 1 Studsvik Erwin TN Rittman NRC Disposal Number of Description Waste Type Description Class Volume(ft"3) Containers A 205.8 215 Poly liner 22 Bead resin A 1040 20' SEALAND 14 20FT Sealand ES-210 Stainless Steel Liner A 202.2 3 (solidification) CPSIRWCU-B B. Irradiated Fuel Shipments (Disposition)
I NUMBER OF SHIPMENTS I MODE OF TRANSPORTATION I DESTINATION I II None I N/A I N/A I env-tec/ARERR01 - 26
ATTACHMENT I Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results JANUARY - DECEMBER 2013 GPI Ground Water samples are collected onsite from dewatering wells, DW; monitoring wells, MW; observation wells, OW; sump wells, SW; and one piezometer location, P. Samples were analyzed for tritium and those not reported in AREOR are reported below. Analyses are to the Lower Level of Detection (LLD) values for the GGNS Radiological Environmental Monitoring Program.
No dose to the public is attributed to ground water since wells with results above MDA are bounded by wells which are <MDA. 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 (pCiIL) GAMMA (pCiIL)
DW-Ol 13-Feb-13 10070 <MDA DW-Ol 8-May-13 7523 <MDA DW-Ol 14-Aug-13 7236 <MDA DW-Ol 4-Dec-13 2411 <MDA DW-Ol DUP 4-Dec-13 2584 <MDA DW-07 14-Feb-13 9035 <MDA DW-07 8-May-13 9106 <MDA DW-07 14-Aug-13 7937 <MDA DW-07 5-Dec-13 5461 <MDA DW-08 13-Aug-13 <531.6 <MDA MW-Ol 13-Feb-13 <534.9 <MDA MW-Ol 8-May-13 <571.8 <MDA MW-Ol 13-Aug-13 <540 <MDA MW-Ol 4-Dec-13 <514.1 <MDA MW-Ol DUP 4-Dec-13 <509.4 <MDA MW-I007C 14-Noy-13 <515.7 <MDA MW-I009C 6-Dec-13 <511.1 <MDA MW-I00B 4-Dec-13 <420.9 <MDA MW-I012C 15-Noy-13 <518 <MDA MW-IOIB 6-Dec-13 <508 <MDA MW-I020C 13-Noy-13 <515.7 <MDA env-tec/ARERR01-27
ATTACHMENT I Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results JANUARY - DECEMBER 2013 (Cont)
LOCATION DATE TRITIUM (pCiIL) GAMMA (pCiIL)
MW-I024C 6-Dec-13 <426 <MDA MW-I027C 6-Dec-13 <438.4 <MDA MW-I02B 4-Dec-13 <479.8 <MDA MW-I03B 13-Feb-13 <520.2 <MDA MW-I03B 4-Dec-13 <509.5 <MDA MW-I042C 14-Nov-13 <516.6 <MDA MW-I042C DUP 14-Nov-13 <512.4 <MDA MW-I04B 13-Feb-13 <522.2 <MDA MW-I04B 5-Dec-13 <499.9 <MDA MW-I05B 12-Feb-13 1107 <MDA MW-I05B 7-May-13 <569.3 <MDA MW-I05B DUP 7-May-13 <570.3 <MDA MW-I05B 13-Aug-13 495.2 <MDA MW-I05B 4-Dec-13 765.7 <MDA MW-I05B DUP 4-Dec-13 652.4 <MDA MW-I06B 14-Feb-13 <525.5 <MDA MW-I06B 8-May-13 <560.4 <MDA MW-I06B 14-Aug-13 <552.1 <MDA MW-I06B 4-Dec-13 <497.3 <MDA MW-I07B 12-Feb-13 2822 <MDA MW-I07B DUP 12-Feb-13 2604 <MDA MW-I07B 7-May-13 1590 <MDA MW-I07B 14-Aug-13 1780 <MDA MW-I07B 5-Dec-13 1334 <MDA MW-I082C 6-Dec-13 <495.1 <MDA MW-I08B 13-Feb-13 1235 <MDA MW-I08B 7-May-13 845.3 <MDA MW-I08B 13-Aug-13 1083 <MDA MW-I08B 5-Dec-13 1560 <MDA MW-I09B 13-Feb-13 976.9 <MDA MW-I09B 7-May-13 542.5 <MDA MW-I09B 13-Aug-13 705 <MDA MW-I09B 5-Dec-13 1094 <MDA env-tec/ARERR01 - 28
ATTACHMENT I Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results JANUARY - DECEMBER 2013 (Cant)
LOCATION DATE TRITIUM (pCi/L) GAMMA (pCi/L)
MW-II0B 12-Feb-13 <521.3 N/A MW-llOB 13-Feb-13 N/A <MDA MW-llOB 8-May-13 <577.6 <MDA MW-llOB 14-Aug-13 <546.4 <MDA MW-llOB 5-Dec-13 <509.5 <MDA MW-lllB 13-Feb-13 10120 <MDA MW-lllB 8-May-13 2497 <MDA MW-lllB DUP 8-May-13 2270 <MDA MW-llIB 14-Aug-13 1480 <MDA MW-lllB DUP 14-Aug-13 1245 <MDA MW-lllB 4-Dec-13 1137 <MDA MW-1l2B 13-Feb-13 <500.6 <MDA MW-l12B 7-May-13 <371.1 <MDA MW-112B 13-Aug-13 <534.1 <MDA MW-112B 4-Dec-13 <508.9 <MDA MW-1134C 5-Dec-13 <494.5 <MDA MW-l13B 13-Feb-13 <526.5 <MDA MW-l13B 4-Dec-13 <422.6 <MDA MW-114B 13-Feb-13 2684 <MDA MW-114B DUP 13-Feb-13 2391 <MDA MW-l14B 8-May-13 1238 <MDA MW-1l4B 14-Aug-13 3984 <MDA MW-114B 5-Dec-13 2983 <MDA MW-115B 13-Feb-13 3087 <MDA MW-115B 7-May-13 2254 <MDA MW-115B 14-Aug-13 978.4 <MDA MW-115B 4-Dec-13 582.9 <MDA MW-116B 13-Feb-13 <536.9 <MDA MW-1l6B 7-May-13 <512.8 <MDA MW-1l6B 14-Aug-13 <530.6 <MDA MW-1l6B 4-Dec-13 <504.9 <MDA MW-118B 13-Feb-13 1159 <MDA MW-1l8B 8-May-13 1831 <MDA MW-118B 14-Aug-13 1156 <MDA MW-118B 4-Dec-13 718.7 <MDA MW-1l9B 19-Dec-13 <500.2 <MDA env-tec/ARERR01 - 29
ATTACHMENT I Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results JANUARY - DECEMBER 2013 (Cant)
LOCATION DATE TRITIUM (pCi/L) GAMMA (pCi/L)
MW-120B 8-May-13 <559.9 <MDA MW-120B 14-Aug-13 <553.7 <MDA MW-120B DUP 14-Aug-13 <555.3 <MDA MW-120B 4-Dec-13 <424.4 <MDA MW-121B 19-Dec-13 <503.6 <MDA OW-209B 12-Feb-13 2538 <MDA OW-209B 7-May-13 1144 <MDA OW-209B 14-Aug-13 <516.7 <MDA OW-209B 4-Dec-13 638.9 <MDA P-05 14-Nov-13 <516.1 <MDA SW-I03A 8-May-13 <575.5 <MDA SW-I03A 14-Aug-13 <555.8 <MD~
SW-I03B 13-Feb-13 <525.1 <MDA SW-I03B 5-Dec-13 <504.7 <MDA
<<MDA =less than minimum detectable activity)
(DUP = separate sample collected and analyzed)
(N/A = not analyzed env-tec/ARERR01 - 30