GNRO-2015/00028, Submittal of 2014 Annual Radioactive Effluent Release Report

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Submittal of 2014 Annual Radioactive Effluent Release Report
ML15117A524
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 04/27/2015
From: Nadeau J
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2015/00028
Download: ML15117A524 (37)
v • d • e


Text

Q

~ Entergy Entergy Operations, Inc.

P. O. Box 756 Port Gibson, MS 39150 James Nadeau Manager, Regulatory Assurance Grand Gulf Nuclear Station Tel. (601) 437-2103 GNRO-2015/00028 April 27, 2015 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Grand Gulf Nuclear Station 2014 Annual Radioactive Effluent Release Report (ARERR)

Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29

Dear Sir or Madam:

Attached is the Grand Gulf Nuclear Station (GGNS) Annual Radioactive Effluent Release Report (ARERR) for the period January 1, 2014 through December 31,2014. This report is submitted in accordance with the requirements of 10CFR50.36(a)(2) and GGNS Technical Specification 5.6.3. The ARERR also complies with the GGNS Offsite Dose Calculation Manual (ODCM).

This letter does not contain any new commitments. If you have any questions or require additional information concerning this report, please contact Richard Sumrall at (601) 437-2115.

Sincerely, JN/tmcr/~~

Attachment:

Grand Gulf Nuclear Station 2014 Annual Radioactive Effluent Release Report (ARERR) cc: (see next page)

GNRO-2015/00028 Page 2 of 2 cc:

NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission ATIN: Mr. Marc Dapas (w/2)

Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 u.S. Nuclear Regulatory Commission ATIN: Mr. A. 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 P.O. Box 1700 Jackson, MS 39205 Dr. Mary Currier, M.D., M.P.H State Health Officer Mississippi Department of Health P.O. Box 1700 Jackson, MS 39205-1700

Attachment to GNRO-2015/00028 Grand Gulf Nuclear Station 2014 Annual Radioactive Effluent Release Report (ARERR)

ENTERGY OPERATIONS Grand Gulf Nuclear Station ANNUAL RADIOACTIVE EFFLUENT REPORT JANUARY 1,2014 - DECEMBER 31,2014 Approved By

This Page Intentionally Left Blank.

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TABLE OF CONTENTS SUBJECT PAGE I. INTRODUCTION 6 II. DETAILED INFORMATION 7 A. Regulatory Limits 7

1. 10CFR20 Limits 7
a. Fission and Activation Gases 7
b. Radioiodines, Tritium and Particulates 7
c. Liquid Effluents 7
2. 10CFR50, Appendix I, Limits 8
a. Fission and Activation Gases 8
b. Radioiodines, Tritium and Particulates 8
c. Liquid Effluents 8
3. 40CFR190 Limits 9 B. Effluent Concentrations 9
1. Airborne 9
2. Liquid 9 C. Average Energy 10 D. Measurements and Approximations of Total Activity 11
1. For Fission and Activation Gases 11
2. For Particulates and Radioiodines 11
3. For Continuous Releases 11
4. For Batch Releases: Gases 11
5. For Batch Releases: Liquid Effluents 12 E. Batch Releases 12
1. Liquid 13
2. Gaseous 13 F. Abnormal Releases 14
1. Liquid 14
2. Gaseous env-tec1ARERR01 - 3

TABLE OF CONTENTS (CONT'D)

SUBJECT PAGE G. Estimate of Total Error 14

1. Liquid 14
2. Gaseous 14
3. Solid Radioactive Waste 14 H. Solid Radioactive Waste Shipments 15 I. Meteorological Data 15 J. Radioactive Effluent Monitoring Instrumentation Operability 15 K. Annual Sewage Disposal Summary 15 III. RADIATION DOSE

SUMMARY

16 A. Water-Related Exposure Pathway 16 B. Airborne-Related Exposure Pathway 16 IV. OFFSITE DOSE CALCULATION MANUAURADIOACTIVE WASTE TREATMENT SYSTEM CHANGES 19 A. Offsite Dose Calculation Manual (ODCM) 19 B. Radioactive Waste Treatment Systems 19 LIST OF TABLES PAGE III.A 2014 Liquid Effluent Dose 16 III.B 2014 Airborne Effluent Dose 18 1A Gaseous Effluents - Summation of All Releases 20 1B Gaseous Effluents - Elevated Releases 21 1C Gaseous Effluents - Ground-Level Releases - Continuous 22 10 Radioactive Gaseous Waste Sampling and Analysis Program 23 2A Liquid Effluents - Summation of All Releases 24 2B Liquid Effluents - Continuous and Batch Modes 25 2C Radioactive Liquid Waste Sampling and Analysis Program 26 3 Solid Radioactive Waste and Irradiated Fuel Shipments 27 ATTACHMENTS PAGE Attachment I - Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results 30 env-tec/ARERR01 - 4

TABLE OF CONTENTS (CONT'D)

ATTACHMENTS PAGE Attachment 11- HISTORICAL RELEASE INFORMATION 34 env-tec/ARERR01 - 5

I. INTRODUCTION This Annual Radioactive Effluent Release Report (ARERR) for the period of January 1 through December 31, 2014, 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 annual summary of meteorological data (ioint 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.

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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:

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

I

= X/Q:Ej Kj Q i s 500 mrem/yr D, = average skin dose rate in the current year (mrem/yr)

I

= X/Q :E (l, + 1.1 M Q i ~ 3000 mrem/yr j j )

where the terms are defined in the GGNS ODCM.

b. Radioiodines, Tritium and Particulates - The release rate limit for the sampling period for all radioiodines, tritium and radioactive materials in particulate form with half-lives greater than 8 days shall be such that:

Do = average organ dose rate in current year (mrem/yr)

= :E j W Pi Q~ s 1500 mrem/yr where the terms are defined in the GGNS ODCM.

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

D = air dose due to gamma emissions from noble gases y

= 3.17 x 10.8 Lj Mj X101 OJ s 5 mrad/qtr

~ 10 mrad/yr D~ = air dose due to beta emissions from noble gases

= 3.17 x 10-8 Lj Nj X10 OJ ~ 10 mrad/qtr 1

~ 20 mrad/yr where the terms are defined in the GGNS ODCM.

b. Radioiodines. Tritium and Particulates - The dose to an individual from tritium, 1-131, 1-133 and radioactive material in particulate form with half-lives greater than 8 days in gaseous effluents shall be such that:

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

= 3.17 x 10-8 Lj Rj WI OJ s 7.5 mrem/qtr Any Organ

~ 15 mrem/yr Any Organ where the terms are defined in the GGNS ODCM.

c. Liquid Effluents - The dose from radioactive materials in liquid effluents shall be such that:

m DTau = L [AiTau L ~tl Cil F1 ] s 1.5 mrem/qtr Total Body i 1=1 s 5 mrem/qtr Any Organ s 3 mrem/yr Total Body s 10 mrem/yr Any Organ where the terms are defined in the GGNS ODCM.

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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

~1 0 mrad y/qtr or ~20 mrad y/yr, Fission and Activation Gases

~20 mrad p/qtr or ~40 mrad p/yr, Fission and Activation Gases

~15 mrem/qtr or ~30 mrem/yr, any Organ, Iodine and Particulates

~3 mrem/qtr or ~6 mrem/yr, Total Body, Liquid Effluents

~1 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.1.a. In this case, the ECls are actually determined by the dose factors in Table 2.1-1 of the GGNS ODCM.

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

2. Liquid The ECl of radioactive materials in liquid effluents is limited by ten times the values in 10CFR20, Appendix B, Table 2, Column 2. The ECl chosen is the most conservative value of either the soluble or insoluble ECl for each radioisotope.

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

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

env-tec/ARERR01- 10

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 1D 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 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 1D for sampling and analytical requirements.) Isotopic values thus obtained are used for dose release rate calculations due to effluent releases as given in Section II.A.1 of this report. The radionuclides that are detected are used in this computation. When no radionuclides are detected, a historical mixture is used.

During the period between grab samples, the amount of radioactivity released is based on the effluent monitor readings. Monitors are assigned a calibration factor based upon the last isotopic analysis, using the following relationship:

where:

C, = isotopic calibration factor for isotope i Uj = concentration of isotope i in the grab sample in IlCi/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 III Other radionuclides with IleUI -

lives creater than 8 days.

3. For Continuous Releases Continuous sampling is performed on the continuous release points when releasing (i.e.: Offgas/Radwaste Building, Containment Building, Fuel Handling Area, Turbine Building, and Turbine Building Occasional Release Point).

Particulate material is collected by filtration. Radioiodines are collected by adsorption onto a charcoal filter. Periodically these filters are removed and analyzed by gamma spectral analysis utilizing high-resolution germanium detectors to identify and quantify radioactive materials collected. Particulate filters are then analyzed for gross alpha and Strontium-89/90 as required. Gross alpha is analyzed using a gas flow proportional technique. Strontium-89/90 values are obtained by chemical separation and subsequent counting analysis using gas flow proportional techniques. Tritium concentrations are determined using distillation and liquid scintillation techniques. During major operational occurrences, the frequency of sampling is increased to satisfy the requirements of footnote CII of Table 10, "Radioactive Gaseous Waste Sampling and Analysts."

II (GGNS ODCM Appendix A, Table 6.11.4-1). Strontium analysis is performed by a qualified contract laboratory. Carbon-14 (C-14) activity of 14.51 Curies released per year in gaseous form was obtained by estimation using EPRI spreadsheet BWR Source Term Calculation (MAL-1 }_r1 and the information in NEAD-NS-11-0060-Rev1-EC42519 and adjusted by 284.5 full power production days. Carbon-14 curies are reported in Tables 1A and 1C of this report and based on a constant release rate throughout the year.

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-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 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year
a. Number of releases 38 47 35 42 162 Time Period in minutes
b. Total for all batches 1.09E+04 1.52E+04 1.05E+04 1.10E+04 4.76E+04
c. Max time for a batch 4.20E+02 1.00E+03 3.27E+02 4.05E+02 1.00E+03
d. Av time for a batch 2.86E+02 3.24E+02 3.01 E+02 2.61 E+02 2.94E+02
e. Min time for a batch 4.30E+01 2.00E+00 2.62E+02 1.30E+02 2.00E+00
f. Av . dil. water flow m 5.84E+03 6.76E+03 8.35E+03 6.10E+03 6.77E+03
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:
b. Total Activity Released: 1.09E+00 Ci On March 10th, 2014 contamination was discovered on the ground outside the radiologically controlled area (RCA) but within the protected area (PA) resulting in a reportable event under 10CFR50.72. Apparent cause evaluation determined the leak was from a structurally compromised liquid radwaste system cross-tie pipe for the abandoned Unit 2. The source of the water was reactor cavity draining during Unit 1 refueling outage activities. The release is estimated to be 1.09E+00 Curies of tritium and mixed fission and activation products. The leak is contained on site so there is no dose to the public. Condition Report GGN-2014-2598 was written and an apparent cause evaluation was performed.
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 AI ha Sampling % 2.60E+01 2.60E+01 2.60E+01 2.60E+01 Measurement % 6.80E+01 6.50E+01 6.10E+01 9.20E+01 TOTAL % 7.30E+01 7.00E+01 6.60E+01 9.50E+01 Sampling errors include uncertainty associated with mixing, representative sampling and discharge volume. Measurement errors include uncertainty associated with instrument calibration and the preparation and counting of low-activity samples. Counting errors are based on measurements of blank samples.

For germanium detectors, the least-readily-detectable radioisotope is used to determine the counting error. Calibration errors are calculated by summing the errors associated with the calibration of a particular instrument with a radioactive source.

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

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II. DETAILED INFORMATION (CONT'D)

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

Fission & Activation Gross Products Iodine Particulate AI ha Tritium 3.20E+01 2.30E+01 2.20E+01 2.20E+01 2.30E+01 6.10E+01 6.70E+01 6.50E+01 1.01E+02 6.20E+01 6.90E+01 7.10E+01 6.90E+01 1.03E+02 6.60E+01 Sampling errors include uncertainty associated with sample flow, vent flow and monitor calibration.

Measurement and total errors are calculated by the same methods used for liquid effluents.

3. Solid Radioactive Waste Estimated Total Error % for all waste types is +/-2.50E+01. Sampling errors include uncertainty associated with mixing and representative sampling.

H. Solid Radioactive Waste Shipments See Table 3 for shipment information.

I. Meteorological Data The data recovery for the reporting period was 98.9%. The predominant wind direction was from the North-Northeast approximately 9.6% of the time. The predominant stability class was class "0" approximately 30.4% of the time. Average wind speed during the reporting period was approximately 4.2 miles per hour at the 33 foot elevation.

The annual meteorological data (Hourly Average Data or Joint Frequency Distribution) will be maintained on site in a file that shall be provided to the NRC upon request.

J. Radioactive Effluent Monitoring Instrumentation Operability No reportable instances of inoperability occurred during the reporting period.

K. Annual Sewage Disposal Summary There were no sewage disposals in 2014.

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III. RADIATION DOSE

SUMMARY

Indicated below is the annual summary of offsite doses attributable to GGNS during 2014.

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

Since there are no other fuel cycle facilities within 8 km of GGNS, 40CFR190 limits were also met during this period.

A. Water-Related Exposure Pathways The values calculated in this section utilize the information provided in Tables 2A and 2B of this report and the calculation methodology of the ODCM.

Liquid Effluents Total body dose and critical organ doses are computed for the maximum exposed individual. The maximum dose contribution from liquid effluents is considered to occur in the adult age group via consumption of fish.

Table III.A 2014 Liquid Effluent Dose (mrem) i Bone II 51 1 Qtr 1.93E-02 2nd Qtr 2.57E-02 3rd Otr 2.35E-02 4th Qtr 1.27E-02 TOTAL 8.30E-02 Liver 5.29E-02 4.67E-02 4.11E-02 2.59E-02 1.67E-01 Thyroid 1.39E-03 8.62E-04 5.97E-04 1.16E-03 3.82E-03 Kidney 3.38E-02 2.29E-02 1.85E-02 1.50E-02 8.83E-02 Lung 2.29E-03 5.15E-03 3.73E-03 2.33E-03 1.40E-02 GI-LLI 3.73E-02 2.39E-02 1.21E-02 1.65E-02 8.61E-02 Applicable Limit 5 5 5 5 10 Percent of Limit 1.06E+00 9.34E-01 8.22E-01 5.18E-01 1.67E+00 Whole Body 2.48E-02 2.37E-02 2.45E-02 1.46E-02 8.83E-02 Applicable Limit 1.5 1.5 1.5 1.5 3 Percent of Limit 1.65E+00 1.58E+00 1.63E+00 9.73E-01 2.94E+00 B. Airborne-Related Exposure Pathways The values presented in this section utilize information provided in Tables 1A and 1C of this report and the calculation methodology of the ODCM. Dose and dose rates are computed for locations at the site boundary or at unrestricted areas within the site boundary. Because members of the public may, on occasion, be found within the site boundary, two fishing lakes, the recreational vehicle laydown area, and the GGNS Energy Services Center locations were also evaluated.

Consideration of site boundary locations as well as unrestricted areas within and beyond the site boundary provides assurance that offsite doses will not be substantially underestimated while attempting to provide an accurate dose calculation.

Doses for a Member of the Public are computed based on 2014 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.

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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 2014 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 2014 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 2014 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 2014 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 form of carbon dioxide (C0 2) during photosynthesis so doses are calculated based on the CO2 fraction of the carbon released in gaseous form. A CO2 fraction of 95% is used based on EPRI Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents." The highest atmospheric dispersion factor for an actual garden based on the land use census was used to determine dose from C-14. Carbon-14 is dispersed as a gas (C0 2 ) to the garden location, where it is then incorporated into plant material.

Carbon-14 dose is calculated to a MEMBER OF THE PUBLIC for the most age restrictive group (Child) and organ (bone) at the garden location. This dose is then added to dose for the same organ from tritium, iodine, and particulates. This organ dose is recorded and compared to the limit in the following table.

Table III.B 2014 Airborne Effluent Dose (mrem) 15t Otr 2nd Otr 3rd atr 4th Otr TOTAL Iodine, Tritium & Particulates (excludinq Carbon-14)

Child (mrem) 8.48E-03 2.57E-03 4.10E-03 6.32E-03 2.15E-02 Orqan Thyroid Thyroid Thyroid Thyroid Thyroid Applicable Limit 7.5 7.5 7.5 7.5 15 Percent of Limit 1.13E-01 3.43E-02 5.47E-02 8.43E-02 1.43E-01 Iodine, Tritium & Particulates (includmq Carbon-14)

Child (mrem) 2.36E+00 2.36E+00 2.36E+00 2.36E+00 9.44E+00 Orqan Bone Bone Bone Bone Bone Applicable Limit 7.5 7.5 7.5 7.5 15 Percent of Limit 3.15E+01 3.15E+01 3.15E+01 3.15E+01 6.29E+01 Total Body Dose Rate (mrem/yr) 1.31E+OO " 3.40E-01 6.13E-01 2.41 E-01 Applicable Limit 500 500 500 500 Percent of Limit 2.62E-01 6.80E-02 1.23E-01 4.82E-02 Skin Dose Rate (mrem/yr) 1.87E+00 5.51 E-01 8.95E-01 3.66E-01 Applicable Limit 3000 3000 3000 3000 Percent of Limit 6.23E-02 1.84E-02 2.98E-02 1.22E-02 Gamma Air Dose* 1.05E-01 9.12E-02 1.79E-01 7.43E-02 4.50E-01 Applicable Limit 5 5 5 5 10 Percent of Limit 2.11 E+OO 1.82E+00 3.58E+00 1.49E+00 4.50E+00 Beta Air Dose* 4.02E-02 5.42E-02 7.06E-02 3.36E-02 2.01 E-01 Applicable Limit 10 10 10 10 20 Percent of Limit 4.02E-01 5.42E-01 7.06E-01 3.36E-01 1.01E+OO Direct Radiation (mrem) 0.0 0.1 0.5 0.3 0.9

  • Measurement units are mrad env-tec/ARERR01 - 18

IV. OFFSITE DOSE CALCULATION MANUAU RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES A. Offsite Dose Calculation Manual (ODCM)

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

env-tec1ARERR01 - 19

TABLE 1A ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 2014 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases

1. Total Release Ci 9.18E+01 1.l6E+02 1.48E+02 8.29E+01 4.53E+02
2. Avg. Release Rate uCi/sec 1.18E+01 1.48E+01 1.86E+01 1.04E+01 1.39E+01
3. Percent of TS Limit
a. Gamma Air  % * * * * *
b. Beta Air  % * * * *
1. Total Release Ci 1.42E-04 8.01E-07 1.86E-06 7.21E-06 1.52E-04
2. Avg. Release Rate uCi/sec 1. 82E-05 1.02E-07 2.35E-07 9.07E-07 4.81E-06
3. Percent of TS Limit  % * * * *
  • Particulates Half Life >= 8 days
1. Total Release Ci 4.94E-06 9.09E-07 9.24E-07 3.52E-06 1.03E-05
2. Avg. Release Rate uCi/sec 6.35E-07 1.16E-07 1.16E-07 4.43E-07 3.26E-07
3. Percent of TS Limit  % * * * *
1. Total Release Ci 5.71E+00 2.46E+00 3.91E+00 5.93E+00 1.80E+01
2. Avg. Release Rate uCi/sec 7.34E-01 3.13E-01 4.92E-01 7.46E-01 5.71E-01
3. Percent of TS Limit  % * * * *
1. Total Release Ci 3.62E+00 3.63E+00 3.63E+00 3.63E+00 1. 45E+01
2. Avg. Release Rate uCi/sec 4.66E-01 4.62E-01 4.57E-01 4.57E-01 4.60E-01 Gross Alpha
1. Total Release Ci 4.84E-09 1.29E-07 5.30E-08 4.80E-08 2.35E-07
2. Avg. Release Rate uCi/sec 6.22E-10 1.64E-08 6.67E-09 6.04E-09 7.45E-09
  • Applicable limits are expressed in terms of dose. See Table III.B of this report.

env-tec/ARERR01 - 20

TABLE 1B ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - ELEVATED RELEASES JANUARY - DECEMBER 2014 (Not Applicable - GGNS Releases Are Considered Ground-Level) env-tec1ARERR01 - 21

TABLE IC ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - GROUND-LEVEL RELEASE-CONTINUOUS REPORT FOR 2014 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases AR-41 Ci 9.28E+00 1.11E+01 3.62E+01 1.86E+01 7.S1E+01 KR-8S Ci O.OOE+OO O.OOE+OO O.OOE+OO 1.34E+01 1.34E+01 KR-8SM Ci 2.4SE+01 6.68E+00 1.87E+01 S.S2E+00 S.S4E+01 KR-87 Ci 3.49E-01 S.3SE+00 2.11E+00 O.OOE+OO 7.82E+00 KR-88 Ci 2.S7E+01 1.49E+01 3.20E+01 1.0SE+01 8.31E+01 XE-133 Ci 1.90E+01 3.97E+01 3.40E+01 1.7SE+01 1.10E+02 XE-13S Ci 1.14E+01 3.37E+01 2.17E+01 1.S3E+01 8.21E+01 XE-13SM Ci 1.32E+00 3.97E+00 2.S6E+00 1. 78E+00 9.63E+00 XE-138 Ci 2.99E-01 9.01E-01 S.82E-01 4.04E-01 2.19E+00 Totals for Period ... Ci 9.18E+01 1.16E+02 1.48E+02 8.29E+01 4.39E+02 Iodines I-131 Ci 1.42E-04 8.01E-07 1.86E-06 7.21E-06 1.S2E-04 I-133 Ci S.02E-04 3.S1E-06 1.68E-OS S.69E-OS S.79E-04 I-13S Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Totals for Period ... Ci 6.44E-04 4.31E-06 1.87E-OS 6.41E-OS 7.31E-04 Particulates Half Life >= 8 days CO-60 Ci 4.41E-06 O.OOE+OO O.OOE+OO O.OOE+OO 4.41E-06 MN-S4 Ci 2.42E-07 O.OOE+OO O.OOE+OO O.OOE+OO 2.42E-07 RU-106 Ci O.OOE+OO O.OOE+OO 2.87E-07 3.S2E-06 3.81E-06 SR-89 Ci 1.71E-07 6.29E-07 O.OOE+OO O.OOE+OO 8.01E-07 SR-90 Ci 1.18E-07 2.79E-07 6.37E-07 O.OOE+OO 1.03E-06 Totals for Period ... Ci 4.94E-06 9.09E-07 9.24E-07 3.S2E-06 1.03E-OS Other H-3 Ci S.71E+00 2.46E+00 3.91E+00 S.93E+00 1.80E+01 C-14 Ci 3.62E+00 3.63E+00 3.63E+00 3.63E+00 1. 4SE+01 Gross Alpha Ci 4.84E-09 1.29E-07 S.30E-08 4.80E-08 2.3SE-07 env-tec1ARERR01 - 22

TABLE 10 ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radioactive Gaseous Waste Sampling and Analysis Program JANUARY - DECEMBER 2014 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 Ventilation Exhaust Grab Sample (f) Emitters (b,e) 1x10.4 H-3 1X10.6 (2) Fuel Handling Area Continuous (d)(f) 7 Days (c) 1-131 1x10* 1t:

Ventilation Exhaust Charcoal Sample 1-133 1x10*10 (3) Containment Continuous (d)(f) 7 Days (c) Principal Gamma 1x10"11 Ventilation Exhaust Particulate Sample Emitters (e) (1-131, Others)

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

Continuous (f) Noble Gas Monitor Noble Gases Gross Beta 1x10.0 or Gamma B. (1) Offgas Post 31 Days Grab 31 Days Principal Gamma 1x1O*q Treatment Exhaust, Sample (f) Emitters (e) whenever there is flow (2) Standby Gas 31 Days Grab 31 Days Principal Gamma 1x1O*q Treatment A Exhaust, Sample (f) Emitters(e) whenever there is flow (3) Standby Gas 31 Days Grab 31 Days Principal Gamma 1x10.4 Treatment B Exhaust, Sample (f) Emitters(e) whenever there is flow NOTE: Footnotes indicated are listed In GGNS ODCM, Appendix A, Table 6.11.4-1.

env-tec/ARERR01 - 23

TABLE 2A ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 2014 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products

1. Total Release Ci 1.31E-02 4.l4E-02 6.78E-03 4.l8E-03 6.55E-02
2. Avg. Diluted Cone. uCi/ml 5.34E-08 1.05E-07 2.02E-08 1.62E-08 5.31E-08
3. Percent of Limit  % * * * *
1. Total Release Ci 1.55E+Ol 1.36E+Ol 1.01E+Ol 1.28E+Ol 5.20E+Ol
2. Avg. Diluted Cone. uCi/ml 6.32E-05 3.45E-05 3.00E-05 4.96E-05 4.22E-05
3. Percent of Limit  % * * * *
  • Dissolved and Entrained Gases
1. Total Release Ci 2.47E-03 5.23E-05 9.88E-06 2.l7E-06 2.53E-03
2. Avg. Diluted Cone. uCi/ml 1.01E-08 1.33E-10 2.94E-ll 8.42E-12 2.05E-09
3. Percent of Limit  % * * * *
  • Gross Alpha Radioactivity
1. Total Release Ci 3.78E-06 3.56E-05 O.OOE+OO O.OOE+OO 3.94E-05 Volume of liquid waste liters 3.78E+06 4.49E+06 3.64E+06 3.77E+06 1.57E+07 Volume of dil. water liters 2.41E+08 3.89E+08 3.32E+08 2.54E+08 1.22E+09
  • Applicable limits are expressed in terms of dose. See table III.A of this report env-tec/ARERR01 - 24

TABLE 2B ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - CONTINUOUS AND BATCH MODES REPORT FOR 2014 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products AG-llOM Ci 3.02E-04 9.86E-OS 2.46E-OS 2.61E-04 6.86E-04 AS-76 Ci O.OOE+OO S.22E-OS O.OOE+OO O.OOE+OO S.22E-OS CO-S8 Ci 2.40E-04 S.37E-OS 1.21E-OS 7.l0E-OS 3.77E-04 CO-60 Ci 1. OSE-03 1.21E-03 8.1SE-04 1.39E-03 4.46E-03 CR-Sl Ci 2.71E-04 2.69E-OS O.OOE+OO O.OOE+OO 2.98E-04 CS-134 Ci O.OOE+OO O.OOE+OO 7.84E-06 O.OOE+OO 7.84E-06 CS-136 Ci 1.OSE-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.OSE-06 CS-137 Ci 9.06E-06 1.OSE-04 1. 84E-04 6.24E-OS 3.61E-04 CS-138 Ci O.OOE+OO 2.63E-OS O.OOE+OO O.OOE+OO 2.63E-OS FE-SS Ci 8.46E-03 3.S8E-02 2.22E-03 O.OOE+OO 4.6SE-02 FE-S9 Ci 7.29E-06 2.49E-OS O.OOE+OO O.OOE+OO 3.22E-OS 1-131 Ci 3.69E-06 O.OOE+OO O.OOE+OO O.OOE+OO 3.69E-06 LA-140 Ci O.OOE+OO O.OOE+OO O.OOE+OO 2.71E-04 2.71E-04 MN-S4 Ci 6.S2E-04 7.27E-04 3.SSE-04 S.89E-04 2.32E-03 NA-24 Ci O.OOE+OO O.OOE+OO 1.S9E-OS 1.84E-OS 3.44E-OS PT-19SM Ci O.OOE+OO O.OOE+OO O.OOE+OO 2.l8E-OS 2.l8E-OS RB-88 Ci 2.98E-04 2.06E-03 2.l6E-03 4.00E-04 4.92E-03 RU-106 Ci 1.88E-OS 3.70E-OS 2.99E-04 1.30E-04 4.84E-04 SR-90 Ci S.20E-06 O.OOE+OO O.OOE+OO O.OOE+OO S.20E-06 SR-92 Ci 2.91E-OS O.OOE+OO 6.2SE-06 2.6SE-OS 6.l9E-OS TE-12SM Ci O.OOE+OO O.OOE+OO O.OOE+OO 4.73E-04 4.73E-04 ZN-6S Ci 1.73E-03 1.20E-03 6.81E-04 4.62E-04 4.07E-03 Totals for Period ... Ci 1.31E-02 4.l4E-02 6.78E-03 4.l8E-03 6.SSE-02 Tritium H-3 Ci 1.SSE+Ol 1. 36E+Ol 1.01E+Ol 1. 28E+Ol S.20E+Ol Totals for Period ... Ci 1.SSE+Ol 1.36E+Ol 1.01E+Ol 1.28E+Ol S.20E+Ol Dissolved and Entrained Gases KR-8SM Ci 6.l6E-06 O.OOE+OO O.OOE+OO O.OOE+OO 6.l6E-06 XE-133 Ci 2.31E-03 1. 42E-OS O.OOE+OO O.OOE+OO 2.33E-03 XE-133M Ci 1.3SE-OS O.OOE+OO O.OOE+OO O.OOE+OO 1.3SE-OS XE-13S Ci 1.32E-04 3.81E-OS 9.88E-06 2.l7E-06 1.82E-04 Totals for Period ... Ci 2.47E-03 S.23E-OS 9.88E-06 2.l7E-06 2.S3E-03 Gross Alpha Radioactivity ALPHA Ci 3.78E-06 3.S6E-OS O.OOE+OO O.OOE+OO 3.94E-OS Totals for Period ... Ci 3.78E-06 3.S6E-OS O.OOE+OO O.OOE+OO 3.94E-OS env-tec/ARERR01 - 25

TABLE 2C ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM JANUARY - DECEMBER 2014 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 Principal Gamma Tanks (c) Each Batch Each Batch Emitters (d) 5x10-7 1-131 1X10-6 Prior to Release 31 Days Dissolved and Entrained 1x10-o One Batch 1M Gases (Gamma Emitters)

Prior to Release 31 Days H-3 1x10-o Each Batch Composite (b) Gross Alpha 1x10-7 Prior to Release 92 Days Composite Sr-89. Sr-90 5x10-lj Each Batch (b) Fe-55 1x10-6 B. SSW Basin (Before Prior to Release Prior to Release Principal Gamma Blowdown) Each Blowdown Each Batch Emitters (dl 5x10-7 1-131 1x10-6 NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.1-1.

env-tec/ARERR01 - 26

TABLE 3 ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY - DECEMBER 2014 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

Est.

Total

1. Type of Waste Unit Class A Class B Class C Error 3
a. Spent resins, filter sludges, m 9.91 E+01 5.72E+00 O.OOE+OO +/-

evaporator bottoms, etc. Ci 2.02E+02 6.91 E+02 O.OOE+OO 25%

3

b. Dry compressible waste, m 1.33E+03 O.OOE+OO O.OOE+OO +/-

contaminated equipment, etc. Ci 5.32E-01 O.OOE+OO O.OOE+OO 25%

3

c. Irradiated components, m O.OOE+OO O.OOE+OO O.OOE+OO +/-

control rods, etc. Ci O.OOE+OO O.OOE+OO O.OOE+OO 25%

3

d. Other: Condensate Pre-Coat Septa m 7.22E+00 O.OOE+OO O.OOE+OO +/-

Bundle Ci 3.93E+00 O.OOE+OO O.OOE+OO 25%

2. Estimate of Major Nuclide Composition ( by type of waste)
a. Spent resins, filter sludges, evaporator bottoms, etc.

Isotope (greater than 0.1 %) Percent Curies Mn-54 7.509 6.71 E+01 Fe-55 61.352 5.48E+02 Co-58 1.053 9.40E+00 Co-60 18.984 1.70E+02 Cs-137 0.249 2.23E+00 Ag-110m 0.414 3.70E+00 Ni-63 0.427 3.82E+00 Zn-65 9.710 8.67E+01 env-tec/ARERR01-27

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 2014

b. Dry compressible waste, contaminated equipment, etc.

Isotope (greater than 0.1 0/0) Percent Curies Cr-51 4.081 2.17E-02 Mn-54 25.581 1.36E-01 Fe-55 12.519 6.65E-02 Fe-59 2.513 1.34E-02 Co-58 1.233 6.55E-03 Co-60 43.281 2.30E-01 Ni-63 0.403 2.14E-03 Zn-65 4.595 2.44E-02 Zr-95 1.160 6.16E-03 Nb-95 1.803 9.58E-03 Aq-110m 1.148 6.10E-03 Cs-137 1.008 5.36E-03 Ce-144 0.300 1.59E-03 Pu-241 0.248 1.32E-03

c. Irradiated components, control rods, etc.

There were none in 2014.

d. Other: Condensate Oil Drum Sealand Isotope (qreater than 0.1 0/0) Percent Curies Cr-51 1.690 6.65E-05 Mn-54 27.497 1.08E-03 Fe-55 12.898 5.07E-04 Fe-59 1.575 6.19E-05 Co-58 1.007 3.96E-05 Co-60 47.429 1.86E-03 Ni-63 0.403 1.58E-05 Zn-65 4.991 1.96E-04 Ag-110m 0.993 3.90E-05 Cs-137 1.006 3.96E-05 Pu-241 0.360 1.42E-05 env-tec/ARERR01 - 28

TABLE 3 ENTERGY OPEHATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY - DECEMBER 2014 (Cont)

3. Solid Waste Disposition I

Number of Mode of Destination Name City State Shipments Transportation 28 EnergySolutions(Duratek), LLC Oak Ridge TN Hittman EnergySolutions - Gallaher Road Hittman 13 Oak Ridge TN Facility 1 Studsvik Erwin TN Hittman NRC Disposal Number of Description Waste Type Description Class Volume(ft/\3) Containers B 120.3 8/120 HIC 2 Poly HIC-RWCU-A A 205.8 215 Linear 10 Carbon Steel Liner - SRT A 90 B-25 2 Metal/DAW A 680 Intermodal 5 Bulk Soil A 1180 20' SEALAND 44 DAW/GIC ES-210 Stainless Steel Liner A 199.4 9 (Solidification) CPS/RWCU-B B. Irradiated Fuel Shipments (Disposition)

II NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION I I None I

N/A I

N/A I

env-tec1ARERR01 - 29

ATTACHMENT I Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results JANUARY - DECEMBER 2014 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-01 2/9/2014 2957 <MDA DW-01 6/13/2014 5536 <MDA DW-01 9/12/2014 6688 <MDA DW-01 11/7/2014 3490 <MDA DW-07 9/12/2014 4611 <MDA DW-07 11/6/2014 5779 <MDA MW-01 2/9/2014 <530 <MDA MW-01 6/13/2014 <417 <MDA MW-01 9/11/2014 <497 <MDA MW-01 DUP 9/11/2014 <416 <MDA MW-01 11/7/2014 <504 <MDA MW-08 2/8/2014 <326 <MDA MW-08 6/13/2014 <347 <MDA MW-08 DUP 6/13/2014 <350 <MDA MW-09 2/9/2014 <234 <MDA MW-09 6/13/2014 <342 <MDA MW-10 6/13/2014 <337 <MDA MW-13 6/20/2014 <284 <MDA MW-15 6/20/2014 <342 <MDA MW-18 6/20/2014 <275 <MDA MW-21 6/20/2014 <277 <MDA MW-22 6/20/2014 446 <MDA MW-23 2/9/2014 <233 <MDA MW-23 6/12/2014 <346 <MDA env-teclARERR01 - 30

ATTACHMENT I Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results JANUARY - DECEMBER 2014 (Cont)

LOCATION DATE TRITIUM (pCi/L) GAMMAlHTD (pCi/L)

MW-1008 2/9/2014 <234 <MDA MW-1008 6/12/2014 <341 <MDA MW-1008 9/12/2014 <204 <MDA MW-1008 11/8/2014 <263 <MDA MW-1018 2/9/2014 <522 <MDA MW-1028 9/12/2014 <578 <MDA MW-103A 9/12/2014 <218 <MDA MW-1038 2/8/2014 <471 <MDA MW-1038 6/13/2014 <339 <MDA MW-1038 9/12/2014 <215 <MDA MW-1038 11/7/2014 <271 <MDA MW-1048 2/9/2014 <469 <MDA MW-1058 2/9/2014 1873 <MDA MW-1068 2/9/2014 <507 <MDA MW-1068 6/12/2014 <500 <MDA MW-1068 9/12/2014 <472 <MDA MW-1068 11/7/2014 <468 <MDA MW-1078 2/8/2014 1321 <MDA MW-1078 6/12/2014 1465 <MDA MW-1078 9/12/2014 1625 <MDA MW-1078 11/6/2014 1028 <MDA MW-1088 2/8/2014 1347 <MDA MW-1088 6/13/2014 1337 <MDA MW-1088 9/12/2014 1873 <MDA MW-1088 11/6/2014 2327 <MDA MW-1098 2/8/2014 <578 <MDA MW-1098 6/13/2014 <434 <MDA MW-1098 9/12/2014 1168 <MDA MW-1098 11/6/2014 801 <MDA env-tec/ARERR01 - 31

ATTACHMENT I Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results JANUARY - DECEMBER 2014 (Cont)

LOCATION DATE TRITIUM (pCi/L) GAMMAlHTD (pCi/L)

MW-1108 2/9/2014 <546 N/A MW-1108 6/13/2014 <441 <MDA MW-1108 9/11/2014 <515 <MDA MW-1108 11/8/2014 <472 <MDA MW-1118 1/17/2014 1519 <MDA MW-1118 6/13/2014 2710 <MDA MW-1118 9/11/2014 2627 <MDA MW-1118 11/7/2014 3646 <MDA MW-1128 2/9/2014 <515 <MDA MW-1128 6/13/2014 <417 <MDA MW-1128 9/11/2014 <510 <MDA MW-1128 11/7/2014 <525 <MDA MW-1138 2/9/2014 <474 <MDA MW-1138 6/13/2012 <450 <MDA MW-1138 DUP 6/13/2014 <504 <MDA MW-1138 9/12/2014 <357 <MDA MW-1138 11/7/2014 <352 <MDA MW-1148 2/9/2014 1746 <MDA MW-1148 6/13/2014 1983 <MDA MW-1148 9/12/2014 2744 <MDA MW-1158 2/9/2014 5630 <MDA MW-1158 DUP 2/9/2014 4510 <MDA MW-1158 6/13/2014 1680 <MDA MW-1158 9/12/2014 5230 <MDA MW-1158 11/7/2014 2510 <MDA MW-1168 1/17/2014 508 <MDA MW-1168 6/13/2014 442 <MDA MW-1168 9/11/2014 508 <MDA MW-1168 11/6/2014 472 <MDA MW-1007C 6/14/2014 <472 <MDA MW-1009C 6/19/2014 <283 <MDA MW-1012C 6/14/2014 <473 <MDA MW-10198 6/20/2014 <336 <MDA env-tec1ARERR01 - 32

ATTACHMENT I Nuclear Energy Institute, NEI, Groundwater Protection Initiative Sample Results JANUARY - DECEMBER 2014 (Cont)

LOCATION DATE TRITIUM (pCilL} GAMMAlHTD (pCi/L)

MW-1020C 6/14/2014 <473 <MDA MW-1022B 6/19/2014 <512 <MDA MW-1024C 6/12/2014 <470 <MDA MW-1027B 6/20/2014 <540 <MDA MW-1027C 6/14/2014 <468 <MDA MW-1042C 6/12/2014 <476 <MDA MW-1082C 6/12/2014 <474 <MDA MW-1134C 6/12/2014 <462 <MDA OW-209B 2/9/2014 <563 <MDA OW-209B 6/12/2014 <492 <MDA OW-209B 9/11/2014 <579 <MDA OW-1108 2/09/2014 <523 <MDA SW-103A 2/09/2014 <520 <MDA SW-103A 6/14/2014 <503 <MDA SW-103A 9/11/2014 <519 <MDA

<<MDA = less than minimum detectable activity)

(DUP =separate sample collected and analyzed)

(NI A =not analyzed env-tec/ARERR01 - 33

ATTACHMENT II HISTORICAL RELEASE INFORMATION In third Quarter 2013, GGNS released approximately 1,540 Ci of gaseous effluent. This amount was higher than normal due to refrigeration equipment issues affecting charcoal adsorption efficiency. The Radwaste Building Vent contributed approximately 90% of the release during that quarter. The Dose Assessment performed for this period calculated 2.1 E-2 mrem for the most age restrictive group (child), with the bone being the most restricted organ. This dose was within the limit of 7.5 mrem for the quarter.

env-tec/ARERR01 - 34

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