GNRO-2013/00101, Annual Radioactive Effluent Release
| ML14008A270 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 01/08/2014 |
| From: | Seiter J Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GNRO-2013/00101 | |
| Download: ML14008A270 (33) | |
Text
Entergy Operations, Inc.
P.o. Box 756 Port Gibson, Mississippi 39150 Tel: 601-437-2344 Jeffery A. Seiter Acting Licensing Manager Grand Gulf Nuclear Station GNRO-2013/00101 January 8, 2014 U.s. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20055-0001
SUBJECT:
Grand Gulf Nuclear Station 2012 Annual Radioactive Effluent Release Report, Revision 2 per 10 CFR 50.36a(a)(2)
Grand Gulf Nuclear Station,Unit 1 Docket No. 50-416 License No. NPF-29 REFERNCES: 1. GNRO-2013/00033, Dated April 30, 2013, Grand Gulf Nuclear Station 2012 Annual Radioactive Effluent Release Report per 10 CR 50.36a(a)(2)
- 2. GNRO-2013/00040, Dated June 10, 2013, Grand Gulf Nuclear Station 2012 Annual Radioactive Effluent Release Report, Revision 1 per 10 CFR 50.36a(a)(2)
Dear Sir or Madam:
Attached is the Grand Gulf Nuclear Station (GGNS) Annual Radioactive Effluent Release Report (ARERR), Revision 2 for the period January 1 2012 through December 31,2012.
Revision 2 to the 2012 GGNS ARERR incorporates information regarding the Circulating Water Slowdown low flow monitor being out of service for greater than 30 days, a modification made to the liquid radwaste treatment system during 2012, and revision of the solid radwaste shipm~nts detailed in Table 3 of the report. Revisions to the report are identified by a revision bar located on the right side of the page. The need for the inclusion of these items was identified during the Jun~ 2013 NRC Radiation Safety Inspection.
There are no commitments contained in this submittal. If you have any questions or need additional information, please contact Richard Sumrall at 601-437-2115.
Sincerely,
/#~
JAS/cjb
Attachment:
Grand Gulf Nuclear Station 2012 Annual Radioactive Effluent Release Report, Revision 2 cc: (See Next Page)
GNRO-2013/00101 Page 2 of 2 cc: U. S. Nuclear Regulatory Commission ATTN: Mr.,Alan Wang, NRR/DORL (w/2)
Mail Stop OWFN 881 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.
Mississippi Department of Health P.O.'Box 1700 Jackson, MS 39215-1700 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
Attachment to GNRO-2013/00101 Grand Gulf Nuclear Station 2012 Annual Radioactive Effluent Release Report, Revision 2
ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1,2012 - December 31, 2012 enll-tec/ARERR01-1
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. 40CFR190 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 11
- 1. Liquid 11
- 2. Gaseous 11 env-tec/ARERR01 - 2
TABLE* OF CONTENTS (CONT'D)
SUBJECT PAGE G. Estimate of Total Error 11
- 1. Liquid 11
- 2. Gaseous 12
- 3. Solid Radioactive Waste 12 H. Solid Radioactive Waste Shipments 12 I. Meteorological Data 12 J. Radioactive Effluent Monitoring InstruJ!lentation Operability 12 K. Annual Sewage Disposal Summary 12 III. RADIATION DOSE
SUMMARY
13 A. Water-Related Exposure Pathway 13 B. Airborne-Related Exposure Pathway 13 IV. OFFSITE DOSE CALCULATION 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 26 Attachment II - Offsite Dose Calculation Manual 30 env-tec/ARERR01 - 3
I. INTRODUCTION This Annual Radioactive Effluent Release Report (ARERR) for the period of January 1 through December 31,2012, is submitted in accordance with Technical Specifications, Section 5.6.3, of Grand Gulf Nuclear Station (GGNS) License No. NPF-29. The monitoring of radioactive effluents is referenced in Offsite Dose Calculation Manual (ODCM) Appendix A, Sections 6.11 and 6.12.
Airborne discharges at GGNS are considered ground-level releases. All liquid and airborne discharges to the environment were analyzed in accordance with ODCM requirements. All effluent releases were within the concentration and total release limits specified by the ODCM., Projected offsite doses were within the dose limits specified by the ODCM.
The summation of all known gaseous releases during the reporting period is reported in Table 1A.
Elevated gaseous releases are not applicable at GGNS as reported in Table 1B.
The summation of all known ground-level gaseous release during the reporting period is reported in Table 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 2B.
The radioactive liquid waste sampling and analysis program implemented at GGNS is described in Table 2C.
Solid radioactive waste and irradiated fuel shipments during the reporting period are summarized in Table 3.
Groundwater Protection Initiative (GPI) well sample tritium results which are not included in the AREOR are included as Attachment I to the ARERR.
The current revision of the Offsite Dose Calculation Manual is included as Attachment II to the ARERR The annual summary of meteorological data Uoint frequency distribution) will be maintained on site. The option to maintain meteorological data on site is in accordance with ODCM Administrative Controls Section 5.6.3. This data shall be provided to the Nuclear Regulatory Commission (NRC) upon request.
env-tec/A RERRO 1 - 4
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 i Q i :::; 500 mremlyr D s = average skin dose rate in the current year (mremlyr)
= XlQ Li (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)
= Li 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 4
unrestricted areas from all reactors at the site, shall be limited to 2 x 10-microcuries/ml total activity.
env-tec1ARERR01 - 5
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
= 3.17x 10-8 LjMj XlQ'Qj*:::; 5mrad/qtr
- 10 mrad/yr D~ = air dose due to beta emissi~ns from noble gases
= 3.17 X 10-8 Li N i XlQ' 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:
D p = 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 j W' Qj:::; 7.5 mremlqtr Any Organ
- c. Liquid Effluents - The dose from radioactive materials in liquid effluents shall be such that:
m D Tau = L [A iTau L ~tl Cjl F I ] :::; 1.5 mremlqtr Total Body j 1=1
- 5 mremlqtr Any Organ
- 3 mremlyr Total Body
env-tec/ARERR01 - 6
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 ~ontained in Sections 2.(a), (b), and (c) respectively, with the exception that the limits applied are:
~25 mrem/yr, Total Body or any Organ except Thyroid
~75 mrem/yr, Thyroid
~IO mrad y/qtr or ~20 mrad y/yr, Fission and Activation Gases
~20 mrad ~/qtr or ~40 mrad ~/yr, Fission and Activation Gases
~I5 mrem/qtr or ~30 mrem/yr, any Organ, Iodine and Particulates
~3 mrem/qtr or ~6 mrem/yr, Total Body, Liquid Effluents
~IO mrem/qtr or ~20 mrem/yr, any Organ, Liquid Effluents B. Effluent Concentrations
- 1. Airborne The Effluent Concentration Limit (ECL) of radioactive materials in gaseous effluents is limited by the dose rate restrictions given in Section II.A.I.a. In this case, the ECLs are actually determined by the dose factors in Table 2.1-1 of the GGNS ODCM.
- 2. Liquid The ECL of radioactive materials in liquid effluents is limited by ten times the values in 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.
env-tec/ARERR01 - 7
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 ID and 2C. For some radionuclides, lower detection levels than required may be readily achievable; when a radionuclide is measured below its stated detection limits, it is reported.
- 1. For Fission and Activation Gases The following noble gases are considered in evaluating gaseous airborne discharges:
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 /lCi/ml.
m = net monitor reading associated with the effluent stream (determined at the time of grab sampling).
env-tec/ARERR01 - 8
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 5r-89 1-131 5r-90 1-133 Other radionuclides with half lives greater than 8 days.
- 3. For Continuous Releases Continuous sampling is performed on the continuous release points when releasing (i.e.:
OffgaslRadwaste Building, Containment Building, Fuel Handling Area, Turbine Building, and Turbine Building Occasional Release Point). Particulate material is collected by filtration. Radioiodines are collected by adsorption onto a charcoal filter. Periodically these filters are removed and analyzed by gamma spectral analysis utilizing high-resolution germanium detectors to identify and quantify radioactive materials collected.
Particulate filters are then analyzed for gross alpha and Strontium-89/90 as required.
Gross alpha is analyzed using a gas flow proportional technique. Strontium-89/90 values are obtained by chemical separation and subsequent counting analysis using gas flow proportional techniques. Tritium concentrations are determined using distillation and liquid scintillation techniques. During major operational occurrences, the frequency of sampling is increased to satisfy the requirements of footnote "c" of Table 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) activity of 11.30 Curies released per year in gaseous form was obtained by estimation using EPRI spreadsheet BWR Source Term Calculation (MAL-I )_r1 and the information in NEAD-NS-II-0060-RevI-EG42519 and adjusted by 236 full power production days. Carbon-14 curies are reported in Tables 1A and IC of this report and based on a constant release rate throughout the year.
- 4. For Batch Releases: Gases Gaseous batch releases are not normally performed at GGNS.
env-tec/A RERRO 1 - 9
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-89/90'and Iron-55 values are obtained by individual chemical separations.
Strontium-89/90 is analyzed using gas flow proportional techniques. Iron-55 is analyzed using liquid scintillation techniques. Gross alpha is analyzed using a gas flow proportional technique. Tritium is distilled and then analyzed using liquid scintillation techniques. Dissolved gases are determined employing grab sampling techniques and analyzed by gamma spectral analysis utilizing high-resolution germanium detectors. Iron and Strontium analyses are performed by a qualified contract laboratory.
E. Batch Releases
- 1. Liquid Year
- a. Number Of releases 205 Time Period (in minutes)
- b. Total for all batches 1.94E+04 1.78E+04 1.25E+04 1.06E+04 6.03E+04
- c. Max time for a batch 3.95E+02 3.15E+02 3.20E+02 3.60E+02 3.95E+02
- d. Av time for a batch 2.98E+02 2.96E+02 3.06E+02 2.73E+02 2.94E+02
- e. Min time for a batch 5.00E+OI 1.00E+OI 2.80E+02 1.00E+00 1.00E+00
- 2. Gaseous No batch releases occurred during the report period.
env-tec/ARERR01 - 10
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 &
Activation Tritium Dissolved & Entrained Gross Products Gases Al ha Sampling % 2.60E+OI 2.60E+OI 2.60E+OI 2.60E+0l Measurement % 6.80E+OI 6.50E+OI 6.10E+OI 9.20E+OI TOTAL % 7.30E+OI 7.00E+OI 6.60E+OI 9.50E+OI Sampling errors include uncertainty associated with mixing, representative sampling and discharge volume. Measurement errors include uncertainty associated with instrument calibration and the preparation and counting of low-activity samples. Counting errors are based on measurements of blank samples. For 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 (nor including sample iine loss) are collectively estimated to be as follows:
Fission & Activation Gross Products Iodine Particulate Al ha Tritium 3.20E+Ol 2.30E+Ol 2.20E+Ol 2.20E+Ol 2.30E+Ol 6.lOE+Ol 6.70E+Ol 6.50E+Ol I.OIE+02 6.20E+Ol 6.90E+Ol 7.lOE+Ol 6.90E+Ol I.03E+02 6.60E+Ol env-tec/ARERR01- 11
II. DETAILED INFORMATION (CONT'D)
Sampling errors include uncertainty associated with sample flow, vent flow and monitor calibration.
Measurement and total errors are calculated by the same methods used for liquid effluents.
- 3. Solid Radioactive Waste Estimated Total Error % for all waste types is +/-2.50E+01. Sampling errors include uncertainty associated with mixing and representative sampling.
H. Solid Radioactive Waste Shipments See Table 3 for shipment information.
- 1. Meteorological Data The data recovery for the reporting period was 99.8%. The predominant wind direction was from the Northeast approximately 11.3% of the time. The predominant stability class was class "D" approximately 29.6% of the time. Average wind speed during the reporting period was approximately 4.2 miles per hour at the 33 foot elevation.
The annual meteorological data (Hourly Average Data or Joint Frequency Distribution) will be maintained on site in a file that shall be provided to the NRC upon request.
J. Radioactive Effluent Monitoring Instrumentation Operability Liquid radwaste effluent radiation monitor was inoperable for> 14 days per Limiting Condition for Operation 1-0TS-12-0030. This was documented in Condition Report GGN-2012-06059.
ODCM action 6.3.9 B.3 has a completion time of 14 days to restore channel to operable, which was exceeded at 12:46 on April 23, 2012.. Exceeding this completion time requires entry into Condition D with required action D.1 to immediately suspend Liquid Radwaste releases and action D.2 to immediately initiate action to explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner. Restoration of this equipment was delayed by Refueling Outage 18 critical path activities. In addition, a retest delay occurred and was documented in Condition Report GGN-2012-06007.
Circulating water blowdown low flow monitor was out of service from 2/22/201 to 5/29/12 for a total of 97 days due to the system being taken out of service for RF18. Per ODCM 6.3.9 Condition E, circulating discharge water flow was estimated every four hours by reviewing pump curves by Operations. The flow monitor was out greater than 30 days due to the extended power uprate outage.
K. Annual Sewage Disposal Summary There were 2 sewage sludge shipments in 2012 consisting of 8 B-25 boxes that were shipped to EnergySolutions for Green is Clean.
env-tec1ARERR01 - 12
III. RADIATION DOSE
SUMMARY
Indicated below is the annual summary of offsite doses attributable to GGNS during 2012. Inspection of the values indicates that GGNS releases were within the 10CFR50, Appendix I, design objectives.
Since there are no other fuel cycle facilities within 8 Ian 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.
2012 Liquid Effluent Dose (mrem) 4th Qtr TOTAL Bone 5.23E-03 2.68E-Ol Liver 1.23E-02 5.64E-Ol Thyroid 1.29E-03 8.03E-03 Kidney 6.52E-03 2.98E-Ol Lung 2. 12E-03 3.55E-02 GI-LLI 1.22E-02 2.76E-01 Whole Body . 6.53E-03 3.02E-Ol B. Airborne-Related Exposure Pathways The values presented in this section utilize information provided in Tables 1A and 1C of this report and the calculation methodology of the ODCM. Carbon-14 doses were calculated using Electric Power Research Institute,. EPRI, methodology and calculation software which was validated on site using Regulatory Guide 1.109. Dose and dose rates are computed for locations at the site boundary or at unrestricted areas within the site boundary. Because members of the public may, on occasion, be found within the site boundary, two fishing lakes, the recreational vehicle laydown area, and the GGNS Energy Services Center locations were also evaluated.
Consideration of site boundary locations as well as unrestricted areas within and beyond the site boundary provides assurance that offsite doses will not be substantially underestimated while attempting to provide an accurate dose calculation'.
Doses for a Member of the Public are computed based on 2012 meteorological data and on the most recent land use census, with the most limiting location used.
During normal operations, the dispersion and deposition factors used for dose calculations are from five-year historical annual average meteorological data.
env-tec/ARERR01-13
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 2012 meteorological data. The critical receptor residence was determined to be located in the southwest sector at a distance of 1432 meters (0.89 miles) from the plant. Pathways considered for use in the organ dose calculations are inhalation, ground plane, grass/cow/meat, and vegetation. There is no grass/cow/milk pathway within five miles of GGNS. It was assumed that the age group receiving the maximum dose lived at the residence and that the receptor consumed food products that were raised or produced at the residence. This dose is documented in the following table as two separate entries. The first organ dose entry excludes C-14 while the second entry includes organ dose from tritium, radioiodines, particulates, and C-14.
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 2012 meteorological data.
The total body and skin dose rates reported are the quarterly average of the maximum instantaneous dose rates determined daily during the reporting period and represent the maximum possible dose rate received by members of the public.
Air Dose from Gamma and Beta Emissions Air doses from gaseous effluents were calculated for this report using dispersion parameters from the 2012 meteorological data. The highest dispersion factor for an unrestricted area was in the southwest sector at the site boundary, 1368 meters (0.85 miles) from the plant.
Direct Radiation Direct radiation dose is calculated by subtracting average doses measured by thermoluminescent dosimeter (TLD) badges located at control locations from average doses measured by TLD badges located near the site boundary. GGNS reported measured doses in 2012 as net exposure normalized to 92 days.
env-tec/A RERRO 1 - 14
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 yeats, the analytical methods for determining C-14 have improved. Coincidentally the radioactive effluents from commercial nuclear power plants have also decreased to the point that C-14 has emerged as a principal radionuclide in gaseous effluents.
The only significant dose pathway to a member of the public from C-14 release is through consumption of vegetation. Vegetation incorporates C-14 in form of carbon dioxide (C0 2) during photosynthesis so doses are calculated based on the CO 2 fraction of the carbon released in gaseous form. A CO 2 fraction of 95% is used based on EPRI Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents". The highest atmospheric dispersion factor for an actual garden based on the land use census was used to determine dose from C-14. Carbon-14 is dispersed as a gas (C0 2) to the garden location, where it is then incorporated into plant material.
Carbon-14 dose is calculated to a MEMBER OF THE PUBLIC for the most age restrictive group (Child) and organ (bone) at the garden location. This doses is then added to dose for the same organ from tritium, iodine, and particulates. This organ dose is recorded and compared to the limit in the following table.
2012 Airborne Effluent Dose (mrem) 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr TOTAL Iodine, Tritium & Particulates (excluding Carbon-14)
Child (mrem) 1.08E-02 1.66E-03 5.8lE-03 1.12E-02 2.95E-02 Organ Thyroid Thyroid Thyroid Thyroid Thyroid Applicable Limit 7.5 7.5 7.5 7.5 15 Percent of Limit 1.45E-01 2.2lE-02 7.75E-02 1.49E-01 1.97E-01 Iodine, Tritium & Particulates (including Carbon-14)
Child (mrem) 1.45E+00 3.09E-02 2.68E+00 2.90E+00 7.06E+00 Organ Bone Bone Bone Bone Bone Applicable Limit 7.5 7.5 7.5 7.5 15 Percent of Limit 1.93E+Ol 4.l2E-01 3.57E+Ol 3.87E+Ol 4.7IE+01 Total Body Dose Rate (mrem/yr) 3.03E-02 3.81E-01 5.90E-Ol 4.7lE-01 Applicable Limit 500 500 500 500 Percent of Limit 6.06E-03 7.62E-02 1.l8E-01 9.42E-02 Skin Dose Rate (mrem/yr) 7.33E-02 7.34E-01 8.53E-Ol 6.98E-01 Applicable Limit 3000 3000 3000 3000 Percent of Limit 2.43E-03 2.45E-02 2.84E-02 2.33E-02 ,
Gamma Air Dose* 9.23E-03 6.34E-02 1.98E-01 1.52E-01 4.23E-Ol Applicable Limit 5 5 5 5 10 Percent of Limit 1.85E-Ol 1.27E'+00 3.96E+00 3.05E+00 4.23E+00 Beta Air Dose* 1.3lE-02 6.67E-02 7.44E-02 6.20E-02 2.l6E-01 Applicable Limit 10 10 10 10 20 Percent of Limit 1.3lE-01 6:67E-Ol 7.44E-OI 6.20E-Ol 1.08E+00 Direct Radiation (mrem) 0.0 0.0 0.1 0.0 0.1
- Measurement umts are mrad env-tec/ARERR01-15
IV. OFFSITE DOSE CALCULATION MANUAL/
RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES A. affsite Dose Calculation Manual (aDCM)
Revisions 38 and 39 of the aDCM were issued in 2012. The revisions included Description of Change(s) Revision Month/Year Affected Number of Change Page Number(s)
Revise 6.3.9 to add condition E. Condition E is 38 03/2012 i, ia, vii, to acknowledge that as long as flow is viib, monitored and measured, there is no need to A-14 suspend dilution flow activities LBDCR 12- 012 Revise Table 6.3.10-1 Section 3B to include 39 03/2012 1, VB, note h. Note h is to acknowledge ~ 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 A current copy of the GGNS aDCM is incl uded in this submittal as Attachment II.
B. Radioactive Waste Treatment Systems In December 2012 an alternate skid-mounted filtration system was put into operation. The skid-mounted filtration system that is designed to perform the functions of the existing Equipment Drain Filter, SG17DOO1, and Floor Drain Filter, SG17D003. The filtration system shall be capable of removing suspended solids such that further processing of the waste through the radwaste demineralizers will consistently and reliably produce Condensate Storage Tank (CST) grade water.
The new system is a 150 gallons per minute Solids Removal System (SRS-150) provided by Energy Solutions, LLC, which utilizes inorganic (metallic) cross-flow filter membranes, and is designed to remove solids greater than 0.5 micron in size from liquid radwaste streams. The filter units are constructed similarly to shell and tube heat exchangers and the filter membranes are manufactured in the form of sintered metal tubes made of stainless steel and coated with titanium oxide. With cross-flow filtration, the recirculating feed stream is used to continuously shear filtered particles from the membrane surface.
env-tec/ARERR01 - 16
TABLEIA ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 2012 Units QTR 1 QTR2 QTR 3 QTR 4 YEAR Fission and Activation Gases
- 1. Total Release Ci 1.3SE+01 1.74E+02 1.S4E+02 1.11E+02 4.S3E+02
- 2. Avg. Release Rate uCi/sec 1.71E+OO 2.22E+01 1.94E+01 1.39E+01 1.43E+01
- 3. Percent of TS Limit
- a. Gamma Air % 1.SSE-01 1.27E+OO 3.96E+OO 3.0SE+OO 4.23E+OO
- b. Beta Air % . 1. 31E-01 6.67E-01 7.44E-01 6.20E-01 1.0SE+OO Iodine-131
- 1. Total Release Ci 1.91E-04 S.02E-06 2.63E-OS 1.96E-04 4.1SE-04
- 2. Avg. Release Rate uCi/sec 2.43E-OS 6.3SE-07 3.30E-06 2.46E-OS 1.32E-06
- 3. Percent of TS Limit % 4.40E-02 1.16E-03 6.0SE-03 4.S1E-02 4.S1E-02 Particulates Half Life >= S days
- 1. Total Release ci 3.64E-OS 7.99E-OS S.43E-OS S.71E-OS 2.2SE-04
- 2. Avg. Release Rate uCi/sec 4.63E-06 1.02E-OS 6.S3E-06 7.1SE-06 7.20E-06
- 3. Percent of TS Limit % 1.42E-03 1.99E-03 2.*37E-03 S.41E-Q3 S.37E-03 Tritium
- 1. Total Release Ci 7.01*E+OO 1.SSE+OO S.06E+OO 7.S0E+OO 2.11E+01
- 2. Avg. Release Rate uCi/sec S.92E-01 2.01E-01 6.36E-01 9.43E-01 6.69E-01
- 3. Percent of TS Limit % 9.22E-02 2.0SE-02 6.6SE-02 9.S6E-02 1.39E-01 Carbon 14
- 1. Total Release Ci 2.32E+OO S.OOE-02 4.29E+00 4.64E+00 1.13E+01
- 2. Avg. Release Rate uCi/sec 2.9SE-01 6.36E-03 S.40E-01 S.S4E-01 3.S7E-01 Gross Alpha
- 1. Total Release Ci 9.S9E-OS 6.S9E-07 6.SSE-OS 7.93E-OS 9.00E-07
- 2. Avg. Release Rate uCi/sec 1.22E-OS* S.39E-OS . S.2SE-09 9.97E-09 2.SSE-OS env-tec/ARERR01 - 11
TABLEIB ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - ELEVATED RELEASES JANUARY - DECEMBER 2012 (Not Applicable - GGNS Releases Are Considered Ground-Level) env-tec/ARERR01 - 18
/
TABLEIC ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - GROUND-LEVEL RELEASE-CONTINUOUS REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases AR-41 Ci 4.16E-02 1.08E-Ol 3.49E+Ol 1.95E+Ol 5.46E+Ol KR-85M Ci 2.65E+00 4.76E-02 2.58E+Ol 1.68E+Ol 4.53E+Ol KR-87 Ci O.OOE+OO 2.41E-Ol 1.01E+00 6.23E+00 7.48E+00 KR-88 Ci 8.02E-02 3.53E+00 3.79E+Ol 3.23E+Ol 7.38E+Ol KR-89 ci O.OOE+OO 1.48E+00 1.14E-Ol O.OOE+OO 1.59E+00 XE-133 Ci 1.60E+00 7.89E+Ol 2.95E+Ol 1.92E+Ol 1.29E+02 XE-135 Ci 1.48E+00 7.56E+Ol 2.16E+Ol 1.47E+Ol 1.13E+02 XE-135M Ci 1.22E+00 9.34E+00 2.57E+00 1.71E+00 1.48E+Ol XE-137 ci 3.12E+00 1.33E+00 1.03E-Ol O.OOE+OO 4.56E+00 XE-138 ci 3.24E+00 3.74E+00 7.09E-Ol 3.88E-Ol 8.08E+00 Totals for Period .** Ci 1.35E+Ol 1.74E+02 1.54E+02 1.11E+02 4.53E+02 Iodines I-131 Ci 1.91E-04 5.02E-06 2.63E-05 1.96E-04 4.18E-04 I-133 Ci 6.58E-04 1.16E-05 3.05E-04 4.30E-04 1.40E-03 I-135 Ci 7.75E-05 O.OOE+OO 4.88E-04 4.77E-05 6.13E-04 Totals for Period *** Ci 9.26E-04 1.66E-05 8.20E-04 6.73E-04 2.44E-03 Particulates Half Life >= 8 days AG-ll0M Ci O.OOE+OO O.OOE+OO O.OOE+OO 3.29E-06 3.29E-06 BA-140 Ci 1.41E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.41E-05 CO-58 ci O.OOE+OO O.OOE+OO 8.60E-06 3.90E-06 1.25E-05 CO-60 Ci 2.45E-06 1.42E-05 2.23E-06 2.37E-05 4.25E-05 CR-51 Ci 1.53E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.53E-06 CS-134 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CS-137 ci O.OOE+OO 2.11E-06 O.OOE+OO 1.92E-06 4.03E-06 FE-55 ci 4.75E-07 1.44E-05 O.OOE+OO 3.68E-07 1.52E-05 MN-54 Ci 1.35E-06 7.89E-06 4.49E-06 8.63E-06 2.24E-05 RU-l06 ci O.OOE+OO O.OOE+OO 3.32E-05 8.11E-07 3.40E-05 SR-89 Ci 1.01E-05 1.21E-05 5.60E-06 1.63E-06 2.95E-05 SR-90 Ci O.OOE+OO O.OOE+OO 2.06E-07 5.04E-07 7.10E-07 ZN-65 Ci 6.40E-06 2.92E-05 O.OOE+OO 1.23E-05 4.79E-05 Totals for Period *** ci 3.64E-05 7.99E-05 5.43E-05 5.71E-05 2.28E-04 Other H-3 Ci 7.01E+00 1.58E+00 5.06E+00 7.50E+00 2.11E+Ol C-14 Ci 2.32E+00 5.00E-02 4.29E+00 4.64E+00 1.13E+Ol Gross Alpha Ci 9.59E-08 6.59E-07 6.55E-08 7.93E-08 9.00E-07 env-tec/ARERR01 - 19
TABLE1D ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radioactive Gaseous Waste Sampling and Analysis Program
, JANUARY - DECEMBER 2012 Lower Limit Sampling Minimum 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) ili&) lxlO- 4 H-3 IX 10-6 (2) Fuel Handling Area Continuous (d)(f) 7 Days (c) 1-131 IxlO- l l Ventilation Exhaust Charcoal Sample 1-133 lxlO- IO (3) Containment Continuous (d)(f) 7 Days (c) Principal Gamma Emitters lxlO- 11 Ventilation Exhaust Particulate Sample (e) (1-131, Others)
(4A) Turbine Building Continuous (d)(f) 31 Days Composite Gross Alpha lxlO- 11 Ventilation Exhaust Particulate Sample (4B) Turbine Building Occasional Continuous (d)(f) 92 Days Composite Sr-89, Sr-90 lxlO- 11 Release Point(g) Particulate Sample (when in service)
Continuous (f) Noble Gas Monitor Noble Gases Gross Beta or Ix 10-6 Gamma B. (l) Offgas Post 31 Days Grab 31 Days Principal Gamma Emitters IxlO- 4 Treatment Exhaust, Sample (f) (e) whenever there is flow (2) Standby Gas 31 Days Grab 31 Days Principal Gamma lxlO- 4 Treatment A Exhaust, Sample (f) Emitters(e) whenever there is flow (3) Standby Gas 31 Days Grab 31 Days Principal Gamma Ix 10-4 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 REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products
- 1. Total Release ci 2.04E-02 2.94E-02 1.8SE-02 1.SSE-02 8.38E-02
- 2. Avg. Diluted Cone. uci/ml S.30E-08 7.38E-08 4.44E-08 S.lSE-08 S.S8E-08
- 3. Percent of Limit % 9.82E-02 8.86E-02 3.44E-02 3.2SE-02 6.46E-02 Tritium
- 1. Total Release Ci 4.66E+01 1.81E+01 1.81E+01 1.94E+01 1.02E+02
- 2. Avg. Diluted Cone. uCi/ml 1.21E-04 4.SSE-OS 4.33E-OS 6.41E-OS 6.80E-OS
- 3. Percent of Limit % 1.21E+00 4.SSE-01 4.33E-01 6.41E-01 6.80E-01 Dissolved and Entrained Gases
- 1. Total Release Ci 2.81E-03 6.19E-OS 1.12E-03 8.28E-04 4.82E-03
- 2. Avg. Diluted Cone. uCi/ml 7.32E-09 1.SSE-10 2.68E-09 2.74E-09 3.21E-09
- 3. Percent of Limit % 3.66E-03 7.77E-OS 1.34E-03 1.37E-03 1.60E-03 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 6.62E+06 6.17E+06 4.28E+06 3.63E+06 2.07E+07 Volume of dil. water liters 3.77E+08 3.94E+08 4.13E+08 2.99E+08 1.48E+09 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 REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products AG-ll0M ci 2.0SE-04 1.74E-04 7.11E-OS 1.0SE-03 1.S0E-03 AS-76 Ci O.OOE+OO O.OOE+OO 3.14E-OS S.23E-OS 8.37E-OS AU-199 Ci 7.S2E-06 O.OOE+OO O.OOE+OO 6.63E-OS 7.38E-OS CO-58 ci 1.38E-04 1.11E-04 2.S1E-OS 2.S1E-04 S.24E-04 CO-60 Ci 6.02E-03 3.31E-03 1.S7E-03 8.46E-04 1.18E-02 CR-Sl Ci S.9SE-04 3.2SE-OS S.34E-OS 2.73E-03 3.41E-03 CS-134 ci O.OOE+OO 9.S2E-06 O.OOE+OO O.OOE+OO 9.S2E-06 CS-137 Ci 8.S9E-04 3.3SE-04 4.47E-OS 1.89E-OS 1.26E-03 CU-67 Ci O.OOE+OO O.OOE+OO O.OOE+OO 4.14E-06 4.14E-06 FE-:-SS Ci 3.74E-03 1.29E-02 8.88E-03 6.10E-03 3.17E":02 FE-59 Ci 1.40E-04 4.76E-OS O.OOE+OO 2.30E-04 4.18E-04 1-131 Ci 1.31E-OS O.OOE+OO O.OOE+OO O.OOE+OO 1.31E-OS LA-140 ci 8.40E-04 O.OOE+OO 6.18E-OS 3.S1E-.OS 9.37E-04 MN-S4 Ci 4.S6E-03 2.08E-03 4.23E-04 8.30E-04 7.90E-03 MO-99 ci 6.14E-OS O.OOE+OO O.OOE+OO O.OOE+OO 6.14E-OS NA-24 Ci O.OOE+OO O.OOE+OO O.OOE+OO 2.S8E-OS 2.S8E-OS PT-19SM ci O.OOE+OO O.OOE+OO O.OOE+OO 1.94E-OS 1.94E-OS RB-88 ci 1.97E-04 O.OOE+OO 4.40E-03 1.99E-03 6.S9E-03 RU-l06 Ci 2.04E-04 2.08E-04 1.16E-03 8.92E-04 2.47E-03 SB-124 Ci 6.43E-OS 7.S0E-OS O.OOE+OO 3.39E-OS 1.73E':"04 SB-12S Ci 3.00E-04 1.49E-03 8.80E-OS O.OOE+OO 1.88E-03 SE-7S ci O.OOE+OO O.OOE+OO O.OOE+OO 3.34E-06 3.34E-06 SN-117M Ci O.OOE+OO O.OOE+OO O.OOE+OO 2.03E-OS 2.03E-OS SR-92 Ci 2.S3E-06 1.66E-OS O.OOE+OO 4.S2E-OS 6.43E-OS TC-99M Ci 7.27E-OS S.64E-06 4.80E-06 2.39E-06 8.SSE-OS W-187 ci 2.33E-OS O.OOE+OO O.OOE+OO O.OOE+OO 2.33E-OS ZN-6S ci 2.29E-03 8.S6E-03 1.68E-03 2.70E-04 1.28E-02 ZN-69M Ci 2.27E-OS 6.72E-06 S.31E-06 1.30E-OS 4.77E-OS ZR-97 Ci O.OOE+OO O.OOE+OO O.OOE+OO 1.S4E-OS 1.S4E-OS Totals for Period *** Ci 2.04E-02 2.94E-02 1.8SE-02 1.SSE-02 8.38E-02 Tritium H-3 Ci 4.66E+Ol 1.81E+Ol 1.81E+Ol 1.94E+Ol 1.02E+02 Totals for Period *** ci 4.66E+Ol 1.81E+Ol 1.81E+Ol 1.94E+Ol 1.02E+02 Dissolved and Entrained Gases XE-133 ci 2.68E-03 3.33E-OS 4.83E-04 3.61E-04 3.SSE-03 XE-133M ci 3.77E-OS O.OOE+OO O.OOE+OO O.OOE+OO 3.77E-OS XE-13S Ci 9.92E-OS 2.87E-OS 6.36E-04 4.67E-04 1.23E-03 Totals for Period *** Ci 2.81E-03 6.19E-OS 1.12E-03 8.28E-04 4.82E-03 Gross Alpha Radioactivity Alpha Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Totals for Period *** Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 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 2012 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 IXlO- 6 Prior to Release 31 Days Dissolved and Entrained IxlO- J One Batch 1M Gases (Gamma Emitters)
Prior to Release 31 Days H-3 IxlO- J Each Batch Composite (b) Gross Alpha IxlO- 7 Prior to Release 92 Days Composite Sr-89, Sr-90 5xlO- 1I Each Batch (b) Fe-55 I X 10-6 B. SSW Basin (Before Prior to Release Prior to Release Each Principal Gamma Emitters Blowdown)
\
Each Blowdown Batch @ 5xlO- 7 1-131 Ix 10-6 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 2012 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)
Est. Total
- 1. Type of Waste Unit Class A Class B Class C Error %
- a. Spent resins, filter sludges, m3 1.40E+02 2.86E+00 O.OOE+OO
+/- 25%
evaporator bottoms, etc. Ci 5.05E+02 1.06E+03 O.OOE+OO
- b. Dry compressible waste, m3 4.38E+03 O.OOE+OO O.OOE+OO
+/- 25%
contaminated equipment, etc. Ci 3.49E+00 O.OOE+OO O.OOE+OO
- c. Irra~iated 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 4. 19E+Ol O.OOE+OO O.OOE+OO
+/- 25%
Bundle Ci 7.93E-02 O.OOE+OO O.OOE+OO
- 2. Estimate of Major Nuclide Composition (by type of waste)
- a. Spent resins, filter sludges, evaporator bottoms, etc.
None
- b. Dry compressible waste, contaminated equipment, etc.
None
- c. Irradiated components, control rods, etc.
None
- d. Other: water tankers Isotope (greater than 0.1 %) Percent Curies Ni-63 0.414 6.50E+00 Co-60 9.097 1.43E+02 Cr-51 0.545 8.55E+00 Cs-137 0.232 3.64E+00 Fe-55 75.449 1.18E+03 Fe-59 0.691 1.08E+Ol Mn-54 9.488 1.49E+02 Co-58 0.352 5.52E+00 Zn-65 3.617 5.68E+Ol 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 2012 (Cont)
- 3. Solid Waste Disposition Number of Mode of Destination Name City State Shipments Transportation 72 EnergySolutions(Duratek), LLC Oak Ridge TN Rittman 9 EnergySolutions - qallaher Road Facility OakRidge TN Rittman 10 Studsvik Erwin TN Rittman NRC Disposal Number of Description Waste Type Description Class Volume(ft"3) Containers B 120.3 8/120 HIC 1 Poly RIC - RWCU-A A 202.2 ES-210 18 Carbon Steel Liner - SRT A 1290 20' SEALAND 139 20FT Sealand A 700 20' Inter~odal 2 20FT Intermodal A 90 B-25 box 4 B-25 box A 800 Water Tanker 2 Water tanker ES-210 Stainless Steel Liner A 199.4 9 (solidification) CPSIRWCU-B ES-210 A 199.4 3 Empty - Stainless Steel Liner (solidification)
B. Irradiated Fuel Shipments (Disposition)
I NUMBER OF SHIPMENTS I MODE OF TRANSPORTATION I DESTINAnON I I None I N/A I N/A I env-tec/ARERR01 - 25
ATTACHMENT I Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results JANUARY -DECEMBER 2012 GPI Ground Water samples are 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 <MDA. Tritium, gamma and HTD results are shown in the table below.
All results were less than Reporting Levels of GGNS-ODCM table 6.12.1-2.
LOCATION DATE TRITIUM (pCi/L) GAMMAlHTD (pCi/L)
DW-Ol 2/912012 17800 <MDA DW-Ol 6/1312012 12800 <MDA DW-Ol 9/1212012 16800 <MDA DW-Ol 1117/2012 12600 <MDA DW-07 9/1212012 6550 <MDA DW-07 111612012 8350 <MDA MW-Ol 2/9/2012 <239 <MDA MW-Ol 6/1312012 <351 <MDA MW-Ol 9/1112012 380 <MDA MW-Ol DUP 9/1112012 359 <MDA MW-Ol 111712012 <262 <MDA MW-08 2/812012 <326 <MDA MW-08 6/1312012 <347 <MDA MW-08 DUP 6/1312012 <350 <MDA MW-09 2/912012 <234 <MDA MW-09 6/13/2012 <342 <MDA MW-I0 6/1312012 <337 <MDA MW-13 612012012 <284 <MDA MW-15 612012012 <342 <MDA MW-18 612012012 <275 <MDA MW-21 612012012 <277 <MDA MW-23 2/912012 <233 <MDA MW-23 6/1212012 <346 <MDA env-tec/ARERR01 - 26
ATTACHMENT I Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results JANUARY - DECEMBER 2012 (Cont)
LOCATION DATE TRITIUM (pCiIL) GAMMAlHTD (pCiIL)
MW-100B 2/912012 <234 <MDA MW-100B 6/1212012 <341 <MDA MW-100B 9/1212012 <204 <MDA MW-100B 11/812012 <263 <MDA MW-102B 2/912012 <238 <MDA MW-102B 6/1212012 <347 <MDA MW-102B 9/1212012 347 <MDA MW-102B 11/7/2012 268 <MDA MW-103A 9/1212012 <218 <MDA MW-103B 2/8/2012 <235 <MDA MW-103B 6/1312012 <339 <MDA MW.:103B 9/1212012 <215 <MDA MW-103B 11/712012 <271 <MDA MW-104B 2/9/2012 <235 <MDA MW-104B 6/1312012 <347 <MDA MW-104B 9/13/2012 <219 <MDA MW-104B 11/712012 <268 <MDA MW-105B 2/912012 740 <MDA MW-105B DUP 2/9/2012 904 N/A MW-105B 6/1212012 560 <MDA MW-105B 9/12/2012 773 <MDA MW~105B 11/812012 823 <MDA MW-105B DUP 11/812012 665 N/A MW-106B 2/912012 <235 <MDA MW-106B 6/1212012 <355 <MDA MW-106B 9/1212012 <213 <MDA MW-106B 11/7/2012 <269 <MDA MW-107B 2/812012 3430 <MDA MW-107B 6/1212012 2430 <MDA MW-107B 9/1212012 2440 <MDA MW-107B 11/612012 2070 <MDA MW-108B 2/812012 612 <MDA MW-108B 6/1312012 604 <MDA MW-108B 9/1212012 983 <MDA MW-108B 11/612012 994 <MDA MW-108B DUP 11/6/2012 868 N/A MW-109B 2/812012 699 <MDA MW-109B 6/1312012 <344 <MDA MW-109B 9/1212012 816 <MDA MW-109B 11/612012 591 <MDA env-tec/ARERR01-27
ATTACHMENT I Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results JANUARY - DECEMBER 2012 (Cont)
LOCATION DATE TRITIUM (pCiIL) GAMMAlHTD (pCiIL)
MW-110B 2/9/2012 <229 N/A MW-110B 6/1312012 <341 <MDA MW-110B 9/1l/2012 <218 <MDA MW-110B 1l/812012 <278 <MDA MW-111B l/1712012 10100 <MDA MW-111B 6/1312012 18400 <MDA MW-111B 9/1l/2012 11000 <MDA MW-1l1B 11/712012 8920 <MDA MW-112B 2/912012 <229 <MDA MW-112B 6/1312012 <347 <MDA MW-112B 9/1l/2012 <220 <MDA MW-112B 11/712012 <268 <MDA MW-113B 2/912012 356 <MDA MW-l13B 6/1312012 <350 <MDA MW-113B DUP 6/1312012 <348 <MDA MW-113B 9/1212012 <211 <MDA MW-i13B 11/712012 352 <MDA MW-114B 2/912012 2340 <MDA MW-114B 6/1312012 3260 <MDA MW-114B 9/1212012 2460 <MDA MW-114B DUP 9/1212012 2950 <MDA MW-114B 11/712012 2970 <MDA MW-115B 2/912012 5630 <MDA MW-115B DUP 2/912012 4510 <MDA MW-1l5B 6/1312012 1680 <MDA MW-115B 9/1212012 5230 <MDA MW-115B 11/712012 2510 <MDA MW-1l8B 1/1712012 491 <MDA MW-118B 6/1312012 1700 <MDA MW-118B 9/1l/2012 1050 <MDA MW-118B 1l/612012 1060 <MDA MW-1007B 6/1912012 <282 <MDA MW-I007C 6/1412012 <286 <MDA MW-1009B 6/1912012 <283 <MDA MW-1012C 6/1412012 <281 <MDA MW-I012C DUP 6/1412012 <285 <MDA MW-I019B 612012012 <336 <MDA env*tec1ARERR01 *28
ATTACHMENT I Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results JANUARY - DECEMBER 2012 (Cont)
LOCATION DATE TRITIUM (pCiIL) GAMMAlHTD (pCiIL)
MW-1020C 6/1412012 <289 <MDA MW-I022B 6/1912012 <334 <MDA MW-1024C 6/1212012 <341 <MDA.
MW-1026B 6/1412012 <289 <MDA MW-1026B 6/1912012 <288 <MDA MW-1027B 612012012 372 <MDA MW-1027C 6/1412012 <286 <MDA MW-1027C DUP 6/1412012 <289 <MDA MW-1042C 6/1212012 <341 <MDA MW-I045B 6/14/2012 <337 <MDA MW-I045B DUP 6/1412012 <340 <MDA MW-1082C 6/1212012 <341 <MDA MW-1134C 6/1212012 <342 <MDA OW-05 6/1912012 <288 <MDA OW-209B 2/912012 5980 <MDA OW-209B 6/1212012 2650 <MDA OW-209B 9/1112012 2430 <MDA OW-209B 11/812012 2210 <MDA OW-I008 6/1912012 <287 <MDA OW-1I08 6/1912012 <332 <MDA SW-103A 6/1412012 <338 <MDA SW-I03A 9/1212012 <218 <MDA SW-103A 11/812012 <273 <MDA SW-103B 2/912012 <366 <MDA
<<MDA =less than minimum detectable activity)
(DUP =separate sample collected and analyzed)
(N/A =not analyzed env-tec/ARERR01 - 29
ATTACHMENT II Offsite Dose Calculation Manual The Grand Gulf Nuclear Station Offsite Dose Calculation Manual was previously submitted on April 30, 2013 env-tec/ARERR01 - 30