ML24113A095

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Annual Radioactive Effluent Release Report for 2023
ML24113A095
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 04/22/2024
From: Hardy J
Entergy Operations
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
GNRO2024-00015
Download: ML24113A095 (1)
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Text

) entergy GNRO2024-00015 April 22, 2024 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Entergy Operations, Inc.

P.O. Box 756 Port Gibson, Mississippi 391 50 Jeffery Hardy Manager Regulatory Assurance Grand Gulf Nuclear Station Tel: 802-380-5124 GGNS TS 5.6.2

SUBJECT:

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

Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29 In accordance with Grand Gulf Nuclear Station Unit 1 Technical Specification 5.6.2, attached is the Annual Radioactive Effluent Release Report for the time-period of January 1, 2023 through December 31, 2023.

There are no commitments contained in this submittal. If you have any questions or need additional information, please contact me at 802-380-5124.

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JH/ram

Attachment:

1. Annual Radioactive Effluent Release Report

GNRO2024-00015 Page 2 of 2 cc:

NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 State Health Officer, Mississippi Department of Health GNRO2024-00015 Annual Radioactive Effluent Release Report

) entergy Grand Gulf Nuclear Station Page 1 of 22 Year: 2023 Document Number: GNRO2024-00015 Annual Radioactive Effluent Release Report

Grand Gulf Nuclear Station I

Year: 2023 I

Page 2 of 22 Annual Radioactive Effluent Release Report TABLE OF CONTENTS

1.0 INTRODUCTION

........................................................................................................................ 3 2.0 SUPPLEMENTAL INFORMATION............................................................................................. 3 3.0 GASEOUS EFFLUENTS........................................................................................................... 11 4.0 LIQUID EFFLUENTS............................................................................................................... 13 5.0 SOLID WASTE

SUMMARY

...................................................................................................... 15 6.0 RADIOLOGICAL IMPACT TO MAN.......................................................................................... 18 7.0 METEOROLOGICAL DATA...................................................................................................... 20 ATTACHMENTS - Nuclear Energy Institute (NEI) Groundwater Protection Initiative Sample Results......... 21

Grand Gulf Nuclear Station I

Year: 2023 I

Page 3 of 22 Annual Radioactive Effluent Release Report

1.0 INTRODUCTION

Grand Gulf Nuclear Station (GGNS) is a nuclear site consisting of one General Electric BWR-6 boiling water reactor with a rated power level of 4408 MWt. The station achieved 346.9 effective full-power days of operation in 2023.

All airborne discharges at GGNS are considered ground-level releases. All liquid and airborne discharges to the environment were analyzed in accordance with Offsite Dose Calculation Manual (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.

This Annual Radioactive Effluent Release Report (AR ERR) for the period January 1 through December 31, 2023, is submitted in accordance with Technical Specifications and ODCM Section 5.6.3 of GGNS License Number NPF-29. The monitoring of radioactive effluents is referenced in ODCM Appendix A, Sections 6.11 and 6.12.

2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits The ODCM contains the limits to which GGNS must adhere. Because of the "as low as reasonably achievable" (ALARA) philosophy at GGNS, actions are taken to reduce the amount of radiation released to the environment. Liquid and gaseous release data show that the dose from GGNS is considerably below the ODCM limits. This data reveals that the radioactive effluents have an overall minimal dose contribution to the surrounding environment. The following are the limits required by the ODCM:

1.

Fission and Activation Gases

a.

Noble gas dose rate due to radioactive materials released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:

Less than or equal to 500 mrem/year to the total body Less than or equal to 3000 mrem/year to the skin

b.

Noble gas air dose due to noble gases released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:

1)

Quarterly

  • Less than or equal to 5 mrad gamma
  • Less than or equal to 10 mrad beta
2)

Yearly

  • Less than or equal to 10 mrad gamma
  • Less th_an or equal to 20 mrad beta

Grand Gulf Nuclear Station I

Year: 2023 I

Page 4 of 22 Annual Radioactive Effluent Release Report

2.

Iodine, Tritium, and Particulate Radionuclides

a.

The dose rate for lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

Less than or equal to 1500 mrem/year to any organ

b.

The dose to a MEMBER OF THE PUBLIC from lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

1)

Quarterly

  • Less than or equal to 7.5 mrem to any organ
2)

Yearly

  • Less than or equal to 15 mrem to any organ
3.

Liquid Effluents Dose

a.

The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to unrestricted areas shall be limited to the following:

1)

Quarterly

  • Less than or equal to 1.5 mrem to the total body
  • Less than or equal to 5 mrem to any organ
2)

Yearly

  • Less than or equal to 3 mrem to the total body
  • Less than or equal to 1 O mrem to any organ
4.

Total Dose (40 CFR 190)

a.

The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to the following:

Less than or equal to 25 mrem to the total body or any organ except the thyroid Less than or equal to 75 mrem to the thyroid

Grand Gulf Nuclear Station I

Year: 2023 I

Page 5 of 22 Annual Radioactive Effluent Release Report 2.2 Maximum Permissible Concentrations

1.

Fission and Activation Gases, Iodine, and Particulates with Half Lives > 8 Days For gaseous effluents, maximum permissible concentrations are not directly used in release rate calculations since the applicable limits are expressed in terms of dose rate at the site boundary.

2.

Liquid Effluents The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to ten times the concentration specified in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the total concentration released shall be limited to 2.0E-4 microcuries/ml total activity.

2.3 Average Energy

1.

Average Energy determination is not applicable to GGNS. The 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 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 required for GGNS.

2.4 Measurements and Approximations of Total Radioactivity

1.

Gaseous Effluents

a.

Fission and Activation Gas Gas samples are collected monthly from gaseous release points and are counted on a high-purity germanium (HPGe) detector for principal gamma emitters. The radionuclides detected are used for release rate calculations. During the period between grab samples, the amount of radioactivity released is based on the effluent radiation monitor readings, which are assigned a scaling factor based on the last isotopic analysis.

The scaling factor, along with hourly effluent monitor values and flow rates, are entered into a laboratory computer where the release rates for individual radionuclides are calculated and stored. If no radionuclides are detected in the grab sample, the scaling factor defaults to the monitor response from a historical default mixture of fission gases.

Grand Gulf Nuclear Station I

Year: 2023 I

Page 6 of 22 Annual Radioactive Effluent Release Report The ODCM release points listed below are continuously monitored.

1)

Radwaste Building Vent (includes Off Gas)

2)

Containment Building Vent

3)

Fuel Handling Area Vent

4)

Turbine Building Vent

5)

Turbine Building Occasional Release Point (when releasing)

b.

Radioiodine Iodine is continuously collected on a TEDA charcoal filter via an isokinetic sampling assembly from each release point. Filters are normally exchanged once per week and then analyzed on a HPGe detector. The flow rates for each release point are averaged over the duration of the sampling period and used in conjunction with the specific radionuclide concentrations measured to calculate the total activity released during the sampling period.

c.

Particulate (Half-Life > 8 Days)

Particulates are continuously collected on a glass-fiber filter via an isokinetic sampling assembly from each release point. Filters are normally exchanged once per week and then analyzed on a HPGe detector. The flow rates for each release point are averaged over the duration of the sampling period and used in conjunction with the specific isotopic concentrations measured to calculate the total activity released during the sampling period.

d.

Tritium Tritium is collected monthly by passing a known volume of the sample stream from each release point through a molecular sieve filter. The collected sample is distilled and analyzed by liquid scintillation. The tritium released is calculated for each release point from the measured tritium concentration, the volume of the sample, the tritium collection efficiency, and the stack exhaust flow rate.

e.

Gross Alpha Particulate filters from weekly samples are retained and analyzed monthly for gross alpha radioactivity using a gas proportional detector (primary method) or a scintillation detector (backup method).

f.

Hard-to-Detect Radionuclides (Sr-89 and Sr-90)

Particulate filters from weekly samples are retained and shipped quarterly to a qualified contract lab for Strontium-89/90 analysis. This analysis involves chemical separation and subsequent measurement using a gas proportional detector.

Grand Gulf Nuclear Station I

Year: 2023 I

Page 7 of 22 Annual Radioactive Effluent Release Report

g.

Carbon-14 Carbon-14 activity of 17.5 Curies released this year in gaseous form was obtained by estimation using EPRI spreadsheet BWR Source Term Calculation (MAL-1)_r1 and the information in NEAD-NS-11-0060-REV1-EC42519 and adjusted by 346.9 full power production days. Carbon-14 activity reported in the tables of this report are based on a constant release rate.

2.

Liquid Effluents

a.

Each tank of liquid radwaste is sampled and analyzed for principal gamma emitters prior to release. Each sample tank is recirculated for enough time prior to sampling to ensure that a representative sample is obtained.

Samples are then analyzed on a HPGe detector and liquid release permits are generated based upon the values obtained from the isotopic analysis and the most recent values for tritium, gross alpha, and hard-to-detect radionuclides (Fe-55, Ni-63, Sr-89, and Sr-90). An aliquot based on release volume is saved and added to composite containers. The concentrations of composited radionuclides and the volumes of the releases associated with these composites establish the proportional relationships that are then utilized for calculating the total activity released for these radionuclides.

b.

Tritium analysis is performed monthly on the liquid composite sample, where the sample is distilled and analyzed with a liquid scintillation detector.

c.

Gross alpha analysis is performed monthly on the liquid composite sample using a gas proportional detector.

d.

Hard-to-Detect radionuclides Fe-55, Ni-63, Sr-89, and Sr-90 analyses are performed quarterly by a qualified contract lab on the liquid composite sample. Following chemical separations, Fe-55 is analyzed with a low-energy photon detector, Ni-63 is analyzed with a liquid scintillation detector, and Sr-80/90 is analyzed using a gas proportional detector.

3.

Estimated Total Error Present Estimates of measurement and analytical error for gaseous and liquid effluents are calculated as follows:

Where: Er = total percent error E,... En = percent error due to calibration standards, laboratory analysis, instruments, sample flow. etc.

Grand Gulf Nuclear Station I

Year: 2023 I Page 8 of 22 Annual Radioactive Effluent Release Report 2.5 Batch Releases

1.

Liquid Time periods in minutes Quarter Quarter Quarter Quarter Year 1

2 3

4 Number of Releases 14 34 20 29 97 Total Release Time 4.27E+03 1.01E+04 5.99E+03 7.93E+03 2.83E+04 Maximum Release Time 4.24E+02 3.24E+02 3.20E+02 3.04E+02 4.24E+02 Average Release Time 3.05E+02 2.96E+02 3.00E+02 2.73E+02 2.91E+02 Minimum Release Time 2.80E+02 2.51E+02 2.60E+02 6.00E+00 6.00E+00 Average Dilution Water 5.28E+03 4.11E+03 4.32E+03 5.16E+03 4.63E+03 Flow (GPM)

2.

Gaseous

a.

No batch releases occurred during the report period.

2.6 Continuous Releases

1.

Liquid

a.

Number of continuous releases: None

2.

Gaseous

a.

Continuous sampling is performed on the continuous release points:

1)

Radwaste Building Vent

2)

Containment Building Vent

3)

Fuel Handling Area Vent

4)

Turbine Building Vent

5)

Turbine Building Occasional Release Point (when releasing)

Grand Gulf Nuclear Station I

Year: 2023 I Page 9 of 22 Annual Radioactive Effluent Release Report 2.7 Abnormal Releases

1.

Liquid

a.

Number of releases: None

2.

Gaseous

a.

Number of releases: None 2.8 Non-routine, Planned Discharges

1.

None 2.9 Radioactive Waste Treatment System Changes

1.

None 2.1 O Land Use Census Changes

1.

The 2022 land use census did not identify any new locations that yielded a calculated dose or dose commitment greater than those currently calculated.

No milk-producing animals were identified within a five-mile radius of the plant site.

2.11 Effluent Monitor Instrument lnoperability

1.

On 6/01/23 the Standby Gas Treatment Normal Range Radiation Monitors experienced a computer power failure and declared inoperable (LCOTR # 1-TS-23-1614). Troubleshooting took longer than expected and the radiation monitor was not restored within 30 days. With vendor assistance the issue was resolved, and the radiation monitor was returned to service on 10-25-23 (146 days). This condition is documented in CR-GGN-2023-13604 and CR-GGN-2023-14167.

2.12 Offsite Dose Calculation Manual Changes

1.

None 2.13 Process Control Program (PCP) Changes

1.

EN-RW-105 "Process Control Program", Effective Date 12/15/2023 was revised. The revision was editorial and did not change the program.

Grand Gulf Nuclear Station I

Year: 2023 I Page 10 of 22 Annual Radioactive Effluent Release Report 2.14 NON-REMP Groundwater Monitoring Results (NEI 07-07)

1.

Ground water samples were taken in support of the Groundwater Protection Initiative. These samples are not part of the Radiological Environmental Monitoring Program. Sample results are included in Attachment 1.

2.15 Sewage Disposal Summary

1.

There were no sewage disposals during the report period.

2.16 Errata/Corrections to Previous ARERRs

1.

There were no errata issued or corrections to previous ARERRs for the 2023 reporting period.

Grand Gulf Nuclear Station I

Year: 2023 I Page 11 of 22 Annual Radioactive Effluent Release Report 3.0 GASEOUS EFFLUENTS 3.1 Gas Effluent Reports Table 1 Gaseous Effluents - Summation of All Releases Quarter Quarter Quarter Quarter Estimated Category Unit 1

2 3

4 Total%

Error FISSION and ACTIVATION GAS Total Release Ci 9.25E+00 2.07E+01 8.00E+01 2.91 E+01 6.90E+01 Average Release Rate for the Period

~LCi/sec 1.19E+00 2.64E+00 1.01E+01 3.66E+00 IODINE Total 1-131 Ci 4.25E-05 1.69E-05 2.B0E-05 1.88E-04 7.10E+01 Average Release Rate for the Period

~LCi/sec 5.46E-06 2.15E-06 3.52E-06 2.37E-05 PARTICULATE Particulates with half-life > 8 days Ci 1.76E-05 5.38E-06 7.25E-06 4.12E-05 6.90E+01 Average Release Rate for the Period

~LCi/sec 2.27E-06 6.84E-07 9.12E-07 5.18E-06 TRITIUM Total Release Ci 6.08E+00 7.17E+O0 6.81E+00 4.86E+00 6.60E+01 Average Release Rate for the Period

~LCi/sec 7.82E-01 9.13E-01 8.57E-01 6.11E-01 GROSS ALPHA Total Release Ci 2.03E-08 2.71E-08 3.56E-07 1.88E-07 1.03E+02 Average Release Rate for the Period

~1Ci/sec 2.61E-09 3.44E-09 4.48E-08 2.37E-08 CARBON-14 Total Release Ci 4.53E+00 4.51E+00 4.61E+00 3.83E+00 Average Release Rate for the Period

~LCi/sec 5.83E-01 5.74E-01 5.B0E-01 4.82E-01

% of limit is on the Radiological Impact to Man, Table 9 - Dose Assessment

Grand Gulf Nuclear Station I

Year: 2023 I Page 12 of 22 Annual Radioactive Effluent Release Report Table2 Gaseous Effluents - Ground Level Release - Continuous Mode Radionuclide Unit Quarter Quarter Quarter Quarter 1

2 3

4 FISSION and ACTIVATION GAS Ar-41 Ci 1.96E+00 7.75E+00 1.31E+01 3.11E+00 Kr-85m Ci 1.53E+00 2.86E-01 1.35E+01 6.92E+00 Kr-87 Ci 2.13E-01 ND ND 5.34E-03 Kr-88 Ci 1.67E+00 2.59E-01 2.34E+01 8.99E+00 Xe-133 Ci 2.31 E+00 5.94E+00 2.11E+01 7.43E+00 Xe-135 Ci 1.38E+00 5.68E+00 7.73E+00 2.29E+00 Xe-135m Ci 1.49E-01 6.69E-01 8.97E-01 2.61 E-01 Xe-138 Ci 3.38E-02 1.52E-01 2.04E-01 5.92E-02 Total for Period Ci 9.25E+00 2.07E+01 8.00E+01 2.91E+01 IODINE 1-131 Ci 4.25E-05 1.69E-05 2.S0E-05 1.88E-04 1-133 Ci 7.23E-05 3.87E-05 4.24E-05 3.17E-04 Total for Period Ci 1.15E-04 5.57E-05 7.04E-05 5.0SE-04 PARTICULATE Ba-140 Ci 4.23E-06 5.38E-06 3.69E-06 6.73E-06 Co-58 Ci ND ND ND 6.85E-06 Co-60 Ci 1.82E-06 ND ND 1.66E-05 Mn-54 Ci ND ND ND 4.20E-06 Ru-106 Ci 1.16E-05 ND 3.56E-06 6.32E-06 Zn-65 Ci ND ND ND 5.36E-07 Total for Period Ci 1.76E-05 5.38E-06 7.25E-06 4.12E-05 TRITIUM Total for Period Ci 6.0BE+00 7.17E+00 6.81E+00 4.86E+00 GROSS ALPHA Total for Period Ci 2.03E-08 2.71E-08 3.56E-07 1.88E-07 CARBON-14 Total for Period Ci 4.53E+00 4.51E+00 4.61E+00 3.83E+00

% of limit is on the Radiological Impact to Man, Table 9-Dose Assessment ND - Not Detected Total 2.59E+01 2.22E+01 2.18E-01 3.43E+01 3.68E+01 1.71E+01 1.98E+OO 4.48E-01 1.39E+02 2.75E-04 4.71E-04 7.46E-04 2.00E-05 6.85E-06 1.84E-05 4.20E-06 2.15E-05 5.36E-07 7.15E-05 2.49E+01 5.92E-07 1.75E+01

Grand Gulf Nuclear Station I

Year: 2023 J

Page 13 of 22 Annual Radioactive Effluent Release Report 4.0 LIQUID EFFLUENTS 4.1 Liquid Effluent Reports Table 3 Liquid Effluents - Summation of All Releases Quarter Quarter Quarter Quarter Category Unit 1

2 3

4 FISSION and ACTIVATION PRODUCTS Total Release Ci 8.68E-03 1.26E-02 3.84E-03 2.84E-03 Average Diluted Concentration

~LCi/ml 1.00E-07 7.85E-08 3.84E-08 1.79E-08 TRITIUM Total Release Ci 4.65E+00 2.95E+00 4.38E+00 4.97E+00 Average Diluted Concentration

~LCi/ml 5.36E-05 1.84E-05 4.38E-05 3.14E-05 DISSOLVED and ENTRAINED GASES Total Release Ci 2.05E-05 5.20E-06 4.95E-06 ND Average Diluted Concentration

~LCi/ml 2.36E-10 3.24E-11 4.95E-11 ND GROSS ALPHA Total Release Ci ND ND ND ND VOLUMES Liquid Waste (Prior to Dilution)

Liters 1.51E+06 3.57E+06 2.09E+06 2.84E+06 Dilution Water Liters 8.53E+07 1.57E+08 9.80E+07 1.55E+08

% of limit is on the Radiological Impact to Man, Table 9 - Dose Assessment ND - Not Detected Estimated Total%

Error 7.30E+01 7.00E+01 6.60E+01 9.50E+01

Grand Gulf Nuclear Station I

Year: 2023 I Page 14 of 22 Annual Radioactive Effluent Release Report Table 4 Liquid Effluents - Batch Mode Radionuclide Unit Quarter Quarter Quarter 1

2 3

FISSION and ACTIVATION PRODUCTS Ag-110m Ci 2.13E-04 4.10E-05 4.88E-05 Ce-141 Ci 5.51 E-05 ND 1.36E-05 Ce-143 Ci ND 1.91 E-06 6.39E-06 Co-58 Ci 1.09E-03 6.04E-04 1.02E-04 Co-60 Ci 2.62E-03 5.42E-03 1.04E-03 Cr-51 Ci 4.08E-04 ND ND Cs-134 Ci 1.17E-05 3.50E-05 3.73E-05 Cs-137 Ci 8.02E-05 2.58E-04 3.45E-04 Fe-55 Ci 9.96E-05 2.16E-03 ND Fe-59 Ci 1.15E-04 ND ND La-140 Ci 3.55E-04 2.36E-05 8.34E-05 Mn-54 Ci 1.79E-03 2.02E-03 4.67E-04 Na-24 Ci ND ND 9.53E-05 Pt-195m Ci ND 2.06E-05 5.67E-05 Ru-106 Ci 4.94E-04 6.09E-05 2.28E-05 Sb-124 Ci ND ND 2.69E-05 Sb-125 Ci 8.81 E-06 ND ND Sr-89 Ci 1.50E-05 3.24E-04 ND Sr-92 Ci 1.52E-05 ND 1.57E-06 Y-88 Ci 9.69E-06 1.11E-05 2.49E-04 Zn-65 Ci 1.30E-03 1.63E-03 1.24E-03 Total for Period Ci 8.68E-03 1.26E-02 3.84E-03 TRITIUM Total for Period Ci 4.65E+00 2.95E+O0 4.38E+00 DISSOLVED and ENTRAINED GASES Xe-133 Ci 1.64E-05 ND ND Xe-135 Ci 4.0BE-06 5.20E-06 4.95E-06 Total for Period Ci 2.05E-05 5.20E-06 4.95E-06 GROSS ALPHA Total for Period Ci ND ND ND

% of limit is on the Radiological Impact to Man, Table 9 - Dose Assessment ND - Not Detected Quarter 4

3.41 E-05 2.84E-06 ND 1.0?E-04 1.54E-03 6.54E-05 1.27E-05 1.55E-04 ND 1.79E-05 1.23E-05 3.04E-04 1.92E-05 ND 2.12E-05 4.87E-06 ND ND 8.21 E-06 3.22E-05 5.05E-04 2.84E-03 4.97E+00 ND ND ND ND Year 3.37E-04 7.16E-05 8.30E-06 1.90E-03 1.06E-02 4.74E-04 9.69E-05 8.38E-04 2.26E-03 1.32E-04 4.75E-04 4.57E-03 1.14E-04 7.73E-05 5.99E-04 3.18E-05 8.81E-06 3.39E-04 2.50E-05 3.02E-04 4.68E-03 2.S0E-02 1.70E+01 1.64E-05 1.42E-05 3.0SE-05 ND

Grand Gulf Nuclear Station I

Year: 2023 I Page 15 of 22 Annual Radioactive Effluent Release Report 5.0 SOLID WASTE

SUMMARY

5.1 Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel)

1.

Types of Waste Tables Types of Solid Waste Summary Type of Waste Total Quantity Total Activity Estimated

{ml)

(Ci)

Total % Error Spent Resins, Filter Sludges, 1.87E+02 7.42E+01 2.50E+01 Evaporator Bottoms, etc.

Dry Compressible Waste, 4.09E+02 5.31 E-01 2.50E+01 Contaminated Equipment, etc.

Irradiated Components, 9.03E-01 4.26E+04 2.50E+01 Control Rods, etc.

Other: Oil Drum Sealand, 0.00E+00 0.00E+00 2.50E+01 Mixed Waste

2.

Estimate of Major Radionuclide Composition (by Waste Type)

Table 6 Major Radionuclides (> 0.1 %)

Radionuclide

% of Total Curies Spent Resins, Filter Sludges, Evaporator Bottoms, etc.

H-3 0.41 3.01E-01 C-14 0.10 7.75E-02 Cr-51 2.00 1.48E+00 Mn-54 6.87 5.10E+00 Fe-55 28.43 2.11E+01 Fe-59 0.36 2.64E-01 Co-58 3.30 2.45E+00 Co-60 52.18 3.87E+01 Ni-63 0.84 6.20E-01 Zn-65 3.99 2.96E+00 Sr-89 0.33 2.43E-01 Cs-134 0.17 1.28E-01 Cs-137 0.82 6.10E-01 Ce-144 0.13 9.53E-02

Grand Gulf Nuclear Station I

Year: 2023 I Page 16 of 22 Annual Radioactive Effluent Release Report Table 6 Major Radionuclides (> 0.1 %)

Radionuclide

% of Total Curies Dry Compressible Waste, Contaminated Equipment, etc.

Cr-51 3.06 1.62E-02 Mn-54 13.08 6.94E-02 Fe-55 5.55 2.95E-02 Fe-59 1.19 6.29E-03 Co-58 4.14 2.20E-02 Co-60 68.45 3.63E-01 Zn-65 3.55 1.88E-02 Cs-137 0.25 1.33E-03 Ce-144 0.62 3.31 E-03 Irradiated Components, Control Rods, etc.

Mn-54 1.56 6.64E+02 Fe-55 41.61 1.77E+04 Co-60 49.40 2.10E+04 Ni-63 7.24 3.08E+03 Other: Oil Drum Sealand, Mixed Waste for Volume Reduction None N/A N/A N/A - Not Applicable

Grand Gulf Nuclear Station I

Year: 2023 I Page 17 of 22 Annual Radioactive Effluent Release Report

3.

Solid Waste Disposition Table 7 Solid Waste Disposition Number of Mode of Destination Shipments Transportation 5

Hittman Energy Solutions Clive Disposal Site (Containerized Waste Facility) - Clive, UT 2

Hittman Energy Solutions Clive Disposal Site (Bulk Waste Facility) - Clive, UT 30 Hittman EnergySolutions Bear Creek Road - Oak Ridge, TN 7

Hittman Waste Control Specialists - Andrews, TX Table 8 Irradiated Fuel Shipments Disposition Number of Mode of Destination Shipments Transportation None N/A N/A N/A - Not Applicable

Grand Gulf Nuclear Station I

Year: 2023 I Page 18 of 22 Annual Radioactive Effluent Release Report 6.0 RADIOLOGICAL IMPACT TO MAN 6.1 10 CFR Part 50, Appendix I Evaluation Table 9 Dose Assessment Category Quarter Quarter Quarter Quarter Annual 1

2 3

4 Liquid Effluent Dose Limit - Total Body 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem 3mrem TOTAL BODY DOSE 3.36E-02 8.89E-02 9.03E-02 3.31 E-02 2.39E-01

% of Limit 2.24E+00 5.93E+00 6.02E+00 2.21E+00 7.97E+00 Liquid Effluent Dose Limit - Any Organ 5 mrem 5mrem 5 mrem 5 mrem 10 mrem MAXIMUM ORGAN DOSE 6.40E-02 1.54E-01 1.49E-01 5.42E-02 4.1 0E-01

% of Limit 1.28E+00 3.07E+00 2.98E+00 1.08E+00 4.10E+O0 Gaseous Effluent Dose Limit - Gamma Air 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad GAMMA AIR DOSE 1.52E-02 2.78E-02 1.55E-01 5.44E-02 2.53E-01

% of Limit 3.04E-01 5.55E-01 3.09E+00 1.09E+0O 2.53E+OO Gaseous Effluent Dose Limit - Beta Air 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad BETA AIR DOSE 6.74E-03 1.43E-02 5.39E-02 1.91 E-02 9.41 E-02

% of Limit 6.74E-02 1.43E-01 5.39E-01 1.91E-01 4.71E-01 Gaseous Effluent Organ Dose Limit Iodine, Tritium, Particulates with 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem

> 8-day Half-Life GASEOUS EFFLUENT ORGAN DOSE Iodine, Tritium, Particulates with 1.13E-02 1.21 E-02 1.20E-02 1.49E-02 5.03E-02

> 8-day Half-Life

% of Limit 1.51 E-01 1.62E-01 1.59E-01 1.98E-01 3.35E-01 DIRECT RADIATION (mrem) 0.0OE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+O0 Gas doses were recalculated using 2023 X/Q and D/Q meteorological data

Grand Gulf Nuclear Station I

Year: 2023 I Page 19 of 22 Annual Radioactive Effluent Release Report 6.2 Dose to a Member of the Public inside the Site Boundary Table 10 Dose to a Member of the Public Inside the Site Boundary Approx.

Dose (mrem)

Occupancy Location Sector Hours Distance (Miles)

Total Body Organ Energy Service NNW 2000 0.5 7.56E-03 1.06E-02 Center Credit Union NW 2000 0.18 4.35E-02 6.11E-02 Doses calculated using GASPARI!, NRCDose3, Version 1.1.3. Adult working 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> per year. 2023 Daytime X/Q and D/Q was used. Plume, Ground Plane and Inhalation doses were considered C-14 is included.

6.3 40 CFR Part 190 Calculation Table 11, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits Whole Body Thyroid Max Other Organ Gaseous1 2.93E-01 5.03E-02 5.03E-02 Carbon-14 1.11E+00 1.11E+00 5.54E+00 Liquid 2.39E-01 1.81E-03 4.10E-01 Direct Shine*

0 0

0 Total Site Dose 1.64E+00 1.16E+00 6.00E+00 Total w/Other Nearby Facility2 N/A N/A N/A Limit 25 mrem 75 mrem 25 mrem

% of Limit 6.56E+00 1.55E+00 2.40E+01

  • Based on data from the Radiological Environmental Monitoring Program, direct radiation at the site boundary is indistinguishable from background at the plant perimeter.

1 Gaseous dose values in the 40 CFR Part 190 calculation includes organ dose from Noble Gas, Iodine, Tritium, and particulates 2 Other fuel cycle sources within 5 miles of the site are considered in this analysis.

Grand Gulf Nuclear Station I

Year: 2023 I Page 20 of 22 Annual Radioactive Effluent Release Report 7.0 METEOROLOGICAL DATA

1.

Data recovery for reporting period: 99%

2.

Predominant wind direction: From North-Northeast 14.3% of the reporting period

3.

Predominant stability class: D (43.0%)

4.

Average wind speed: 4.1 miles per hour at the 33-foot level

5.

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

Grand Gulf Nuclear Station I

Year: 2023 I Page 21 of 22 Annual Radioactive Effluent Release Report Nuclear Energy Institute (NEI) Groundwater Protection Initiative Sample Results GPI Ground Water samples were collected from onsite Dewatering Wells (OW), Monitoring Wells (MW),

and Sentinel Wells (SW). Samples were analyzed for Tritium and gamma and selected samples were analyzed for hard-to-detect (HTD) radionuclides (Americium-241, Curium-242, Curium-243/244, lron-55, Nickel-63, Plutonium-238, 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 Minimum Detectable Activity (MDA) are bounded by wells which are less than MDA. Tritium and gamma results are shown in the table below. HTD analyses performed on MW-1148 indicated< MDA for all HTD radionuclides.

Number of Maximum Maximum Location Samples TRITIUM GAMMA (pCi/L)

(pCi/L)

DW-01 5

3,620

<MDA DW-02 5

1,510

<MDA DW-03 4

947

< MDA DW-04 4

1,360

<MDA DW-05 4

<648

<MDA DW-07 5

1,490

<MDA MW-01 4

613

<MDA MW-04 6

<589

<MDA MW-06 5

2,280

<MDA MW-1008 1

< 500

<MDA MW-1018 4

< 649

<MDA MW-1028 1

<494

<MDA MW-1038 1

< 587

<MDA MW-1048 1

< 581

<MDA MW-1058 4

716

< MDA MW-1068 4

< 614

<MDA MW-1078 4

<611

<MDA MW-1088 5

1,060

<MDA MW-1098 4

1,670

<MDA

Grand Gulf Nuclear Station I

Year: 2023 I Page 22 of 22 Annual Radioactive Effluent Release Report Nuclear Energy Institute (NEI) Groundwater Protection Initiative Sample Results Number of Maximum Maximum Location Samples TRITIUM GAMMA (pCi/L)

(pCi/L)

MW-110B 4

< 644

<MDA MW-111B 4

3,770

<MDA MW-112B 4

< 590

<MDA MW-113B 8

< 662

<MDA MW-114B 4

3,160

<MDA MW-115B 4

5,990

< MDA MW-116B 4

< 591

<MDA MW-118B 4

770

<MDA MW-119B 2

< 500

<MDA MW-120B 1

< 503

<MDA MW-1218 1

< 578

<MDA MW-122B 4

< 596

< MDA MW-123B 5

<651

<MDA MW-1007C 1

< 577

<MDA MW-1009C 1

< 587

<MDA MW-1012C 1

< 587

<MDA MW-1020C 2

< 583

<MDA MW-1024C 1

< 579

< MDA MW-1027C 1

< 573

<MDA MW-1042C 1

< 587

<MDA MW-1134C 1

< 584

<MDA MW-1082C 1

< 575

<MDA P-05 1

< 582

<MDA SW-103A 4

< 595

<MDA

< MDA - Less than Minimum Detectable Activity

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