Text

Annual Radioactive Effluent Release Report (ARERR)
	ML22118A086
Person / Time
Site:	Grand Gulf
Issue date:	04/28/2022
From:	Hardy J; Entergy Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	GNRO2022-00018
	Download: ML22118A086 (212)
	v • d • e

entergy Entergy Operations, Inc.

P.O. Box 756 Port Gibson, Mississippi 39150 Jeffery Hardy Manager Regulatory Assurance Grand Gulf Nuclear Station Tel: 802-380-5124 GNRO2022-00018 April 28, 2022 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001

SUBJECT:

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

Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29 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, 2021 through December 31, 2021.

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

Attachments: 1. Annual Radioactive Effluent Release Report

GNRO2022-00018 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

Attachment 1 GNRO2022-00018 Annual Radioactive Effluent Release Report

) entergy Page 1 of 21 Grand Gulf Nuclear Station Year: 2021 Document Number: GNRO2022-00018 Annual Radioactive Effluent Release Report

Grand Gulf Nuclear Station Year: 2021 Page 2 of 21 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 ...................................................................................................... 19 ATTACHMENTS - Nuclear Energy Institute (NEI) Groundwater Protection Initiative Sample Results......... 20 - Revised Offsite Dose Calculation Manual .....................................................................22

Grand Gulf Nuclear Station Year: 2021 Page 3 of 21 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 346.4 effective full-power days of operation in 2021.

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 (ARERR) for the period January 1 through December 31, 2021, is submitted in accordance with Technical Specifications 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 than or equal to 20 mrad beta

Grand Gulf Nuclear Station Year: 2021 Page 4 of 21 Annual Radioactive Effluent Release Report

2. Iodine, Tritium, and Particulate Radionuclides

a. The dose rate for Iodine-131, Iodine-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 Iodine-131, Iodine-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 10 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 Year: 2021 Page 5 of 21 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 Year: 2021 Page 6 of 21 Annual Radioactive Effluent Release Report The Technical Specification 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 Year: 2021 Page 7 of 21 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 346.4 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: ET = total percent error E1 ... En = percent error due to calibration standards, laboratory analysis, instruments, sample flow, etc.

Grand Gulf Nuclear Station Year: 2021 Page 8 of 21 Annual Radioactive Effluent Release Report 2.5 Batch Releases

1. Liquid Quarter Quarter Quarter Quarter Time periods in minutes Year 1 2 3 4 Number of Releases 8 28 10 14 60 Total Release Time 2.94E+03 8.42E+03 3.03E+03 4.77E+03 1.92E+04 Maximum Release Time 5.47E+02 3.90E+02 3.25E+02 5.21E+02 5.47E+02 Average Release Time 3.67E+02 3.01E+02 3.03E+02 3.41E+02 3.19E+02 Minimum Release Time 2.83E+02 1.05E+02 2.90E+02 2.98E+02 1.05E+02 Average Dilution Water 5.29E+03 6.37E+03 6.15E+03 4.58E+03 5.71E+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 Year: 2021 Page 9 of 21 Annual Radioactive Effluent Release Report 2.7 Abnormal Releases

1. On 1/31/21 a liquid radwaste tank was partially discharged without an approved discharge permit. An approved permit was completed for Floor Drain Storage Tank A (FDST-A) but the radwaste operator inadvertently lined up to discharge FDST-B.

Approximately seven hours later, another operator discovered the error and immediately stopped the discharge. The total volume discharged was 22,790 gallons, which was approximately 80% of the tank contents. A sample was collected from the tank and analyzed, and the effluent tracking database was updated for volume, activity, and public dose for the release. This incident is documented in CR-GGN-2021-0869.

2. Liquid

a. Number of releases: 1

b. Total activity released: 1.82E-01 Ci

3. Gaseous

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

1. None 2.9 Radioactive Waste Treatment System Changes

1. None 2.10 Land Use Census Changes

1. None 2.11 Effluent Monitor Instrument Inoperability

1. None 2.12 Offsite Dose Calculation Manual Changes

1. The ODCM was revised in 2021 to Revision 43. This revision:

a. Revised Section 5.6.3 (Annual Radioactive Effluent Release Report) reporting requirements, removing supplemental reporting requirements for solid wastes to align with Regulatory Guide 1.21, Revision 1.

b. Revised Table 6.12.1-1 (Operational Radiological Environmental Monitoring Program) to correct errors introduced during Revision 42 implementation, reinserting line in table for Outfall 007 that had been inadvertently deleted.

2. A copy of the revised ODCM is submitted as Attachment 2.

Grand Gulf Nuclear Station Year: 2021 Page 10 of 21 Annual Radioactive Effluent Release Report 2.13 Process Control Program (PCP) Changes

1. None 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. None

Grand Gulf Nuclear Station Year: 2021 Page 11 of 21 Annual Radioactive Effluent Release Report 3.0 GASEOUS EFFLUENTS 3.1 Gas Effluent Reports Table 1 Gaseous Effluents - Summation of All Releases Estimated Quarter Quarter Quarter Quarter Category Unit Total %

1 2 3 4 Error FISSION and ACTIVATION GAS Total Release Ci 2.28E+01 2.31E+01 1.47E+01 1.50E+01 6.90E+01 Average Release Rate for the Period mCi/sec 2.93E+00 2.94E+00 1.85E+00 1.89E+00 IODINE Total I-131 Ci 3.88E-06 1.84E-05 7.88E-07 8.83E-05 7.10E+01 Average Release Rate for the Period mCi/sec 4.98E-07 2.33E-06 9.92E-08 1.11E-05 PARTICULATE Particulates with half-life > 8 days Ci 1.22E-06 8.23E-06 6.65E-06 8.03E-06 6.90E+01 Average Release Rate for the Period mCi/sec 1.57E-07 1.05E-06 8.36E-07 1.01E-06 TRITIUM Total Release Ci 3.79E+00 4.02E+00 5.92E+00 4.08E+00 6.60E+01 Average Release Rate for the Period mCi/sec 4.88E-01 5.12E-01 7.45E-01 5.13E-01 GROSS ALPHA Total Release Ci 4.91E-07 1.38E-07 1.10E-07 6.54E-07 1.03E+02 Average Release Rate for the Period mCi/sec 6.31E-08 1.75E-08 1.38E-08 8.23E-08 CARBON-14 Total Release Ci 4.50E+00 3.91E+00 4.57E+00 4.49E+00 Average Release Rate for the Period mCi/sec 5.78E-01 4.98E-01 5.75E-01 5.64E-01

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

Grand Gulf Nuclear Station Year: 2021 Page 12 of 21 Annual Radioactive Effluent Release Report Table 2 Gaseous Effluents - Ground Level Release - Continuous Mode Quarter Quarter Quarter Quarter Radionuclide Unit Total 1 2 3 4 FISSION and ACTIVATION GAS Kr-85 Ci 1.74E+01 ND ND ND 1.74E+01 Kr-88 Ci 1.09E-01 3.07E-01 2.94E-01 2.98E-01 1.01E+00 Xe-133 Ci 2.55E+00 1.13E+01 6.90E+00 6.98E+00 2.77E+01 Xe-135 Ci 2.44E+00 1.06E+01 6.59E+00 6.79E+00 2.64E+01 Xe-135m Ci 2.87E-01 8.11E-01 7.77E-01 7.87E-01 2.66E+00 Xe-138 Ci 6.52E-02 1.84E-01 1.76E-01 1.79E-01 6.04E-01 Total for Period Ci 2.28E+01 2.31E+01 1.47E+01 1.50E+01 7.57E+01 IODINE I-131 Ci 3.88E-06 1.84E-05 7.88E-07 8.83E-05 1.11E-04 I-133 Ci 4.98E-06 6.84E-06 3.59E-06 7.50E-05 9.04E-05 Total for Period Ci 8.85E-06 2.52E-05 4.38E-06 1.63E-04 2.02E-04 PARTICULATE Co-60 Ci ND 5.91E-06 8.94E-07 ND 6.81E-06 Cr-51 Ci ND 1.61E-06 ND ND 1.61E-06 Mn-54 Ci ND ND 2.12E-08 ND 2.12E-08 Ru-106 Ci ND ND 3.97E-06 6.78E-06 1.07E-05 Se-75 Ci 1.22E-06 7.07E-07 1.76E-06 1.25E-06 4.93E-06 Total for Period Ci 1.22E-06 8.23E-06 6.65E-06 8.03E-06 2.41E-05 TRITIUM Total for Period Ci 3.79E+00 4.02E+00 5.92E+00 4.08E+00 1.78E+01 GROSS ALPHA Total for Period Ci 4.91E-07 1.38E-07 1.10E-07 6.54E-07 1.39E-06 CARBON-14 Total for Period Ci 4.50E+00 3.91E+00 4.57E+00 4.49E+00 1.75E+01

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

Grand Gulf Nuclear Station Year: 2021 Page 13 of 21 Annual Radioactive Effluent Release Report 4.0 LIQUID EFFLUENTS 4.1 Liquid Effluent Reports Table 3 Liquid Effluents - Summation of All Releases Estimated Quarter Quarter Quarter Quarter Category Unit Total %

1 2 3 4 Error FISSION and ACTIVATION PRODUCTS Total Release Ci 1.31E-04 8.93E-04 8.69E-04 4.90E-04 7.30E+01 Average Diluted Concentration mCi/ml 2.19E-09 4.34E-09 1.21E-08 5.81E-09 TRITIUM Total Release Ci 2.05E+00 9.04E+00 3.60E+00 4.68E+00 7.00E+01 Average Diluted Concentration mCi/ml 3.42E-05 4.39E-05 5.03E-05 5.55E-05 DISSOLVED and ENTRAINED GASES Total Release Ci 1.01E-05 0.00E+00 0.00E+00 0.00E+00 6.60E+01 Average Diluted Concentration mCi/ml 1.69E-10 0.00E+00 0.00E+00 0.00E+00 GROSS ALPHA Total Release Ci 9.82E-05 0.00E+00 0.00E+00 0.00E+00 9.50E+01 VOLUMES Liquid Waste (Prior to Dilution) Liters 8.51E+05 2.89E+06 1.06E+06 1.62E+06 Dilution Water Liters 5.89E+07 2.03E+08 7.05E+07 8.27E+07

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

Grand Gulf Nuclear Station Year: 2021 Page 14 of 21 Annual Radioactive Effluent Release Report Table 4 Liquid Effluents - Batch Mode Quarter Quarter Quarter Quarter Radionuclide Unit Year 1 2 3 4 FISSION and ACTIVATION PRODUCTS Ag-110m Ci ND 1.11E-05 6.58E-05 9.11E-05 1.68E-04 Co-58 Ci ND 6.85E-05 3.15E-05 6.32E-05 1.63E-04 Co-60 Ci 5.71E-05 4.81E-04 5.71E-04 2.26E-04 1.34E-03 Cr-51 Ci ND 3.25E-05 ND ND 3.25E-05 Cs-134 Ci 1.91E-05 1.75E-05 1.09E-05 5.48E-06 5.30E-05 Cs-137 Ci 3.94E-05 4.19E-05 7.56E-05 1.25E-05 1.69E-04 Fe-59 Ci ND ND ND 1.01E-05 1.01E-05 La-140 Ci ND ND 8.56E-06 ND 8.56E-06 Mn-54 Ci 3.70E-06 1.25E-04 4.28E-05 6.46E-06 1.77E-04 Ru-106 Ci ND 5.49E-05 ND ND 5.49E-05 Sb-124 Ci ND ND 2.74E-05 ND 2.74E-05 Sb-125 Ci ND ND ND 1.77E-05 1.77E-05 Sr-92 Ci ND ND 9.17E-06 2.64E-05 3.55E-05 Tc-99m Ci ND 2.96E-07 ND ND 2.96E-07 Y-88 Ci ND ND ND 7.97E-06 7.97E-06 Zn-65 Ci 1.13E-05 5.36E-05 2.56E-05 2.28E-05 1.13E-04 Zn-69m Ci ND 7.95E-06 ND ND 7.95E-06 Total for Period Ci 1.31E-04 8.93E-04 8.69E-04 4.90E-04 2.38E-03 TRITIUM Total for Period Ci 2.05E+00 9.04E+00 3.60E+00 4.68E+00 1.94E+01 DISSOLVED and ENTRAINED GASES Xe-133 Ci 7.82E-06 ND ND ND 7.82E-06 Xe-135 Ci 2.29E-06 ND ND ND 2.29E-06 Total for Period Ci 1.01E-05 ND ND ND 1.01E-05 GROSS ALPHA Total for Period Ci 9.82E-05 ND ND ND 9.82E-05

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

Grand Gulf Nuclear Station Year: 2021 Page 15 of 21 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 Table 5 Types of Solid Waste Summary Total Quantity Total Activity Estimated Type of Waste (m3) (Ci) Total % Error Spent Resins, Filter Sludges, 2.80E+02 1.33E+02 2.50E+01 Evaporator Bottoms, etc.

Dry Compressible Waste, 4.78E+02 3.17E-01 2.50E+01 Contaminated Equipment, etc.

Irradiated Components, 0.00E+00 0.00E+00 2.50E+01 Control Rods, etc.

Other: Oil Drum Sealand, 5.66E+01 1.57E-02 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.

Cr-51 1.51 2.01E+00 Mn-54 6.83 9.11E+00 Fe-55 37.06 4.94E+01 Co-58 2.56 3.41E+00 Co-60 45.85 6.12E+01 Zn-65 2.72 3.63E+00 Dry Compressible Waste, Contaminated Equipment, etc.

Mn-54 11.18 3.54E-02 Fe-55 5.78 1.83E-02 Co-58 1.64 5.20E-03 Co-60 76.17 2.41E-01 Zn-65 1.83 5.81E-03 Cs-137 1.00 3.18E-03

Grand Gulf Nuclear Station Year: 2021 Page 16 of 21 Annual Radioactive Effluent Release Report Table 6 -Continued Major Radionuclides (> 0.1%)

Radionuclide % of Total Curies Irradiated Components, Control Rods, etc.

None None None Other: Oil Drum Sealand, Mixed Waste for Volume Reduction Cr-51 1.29 2.02E-04 Mn-54 11.30 1.78E-03 Fe-55 5.80 9.13E-04 Co-58 1.75 2.76E-04 Co-60 75.73 1.19E-02 Zn-65 1.79 2.82E-04 Cs-137 1.02 1.61E-04

Grand Gulf Nuclear Station Year: 2021 Page 17 of 21 Annual Radioactive Effluent Release Report

3. Solid Waste Disposition Table 7 Solid Waste Disposition Number of Mode of Destination Shipments Transportation EnergySolutions 5 Hittman Clive Disposal Site (Containerized Waste Facility) - Clive, UT EnergySolutions 6 Hittman Clive Disposal Site (Bulk Waste Facility) - Clive, UT EnergySolutions 36 Hittman Bear Creek Road - Oak Ridge, TN Table 8 Irradiated Fuel Shipments Disposition Number of Mode of Destination Shipments Transportation None N/A N/A

Grand Gulf Nuclear Station Year: 2021 Page 18 of 21 Annual Radioactive Effluent Release Report 6.0 RADIOLOGICAL IMPACT TO MAN 6.1 10 CFR Part 50, Appendix I Evaluation Table 9 Dose Assessment Quarter Quarter Quarter Quarter Category Annual 1 2 3 4 Liquid Effluent Dose Limit - Total Body 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem 3 mrem TOTAL BODY DOSE 1.04E-02 9.75E-03 1.21E-02 4.44E-03 3.70E-02

% of Limit 6.94E-01 6.50E-01 8.04E-01 2.96E-01 1.23E+00 Liquid Effluent Dose Limit - Any Organ 5 mrem 5 mrem 5 mrem 5 mrem 10 mrem MAXIMUM ORGAN DOSE 1.45E-02 1.39E-02 1.77E-02 6.26E-03 5.30E-02

% of Limit 2.90E-01 2.78E-01 3.54E-01 1.25E-01 5.30E-01 Gaseous Effluent Dose Limit - Gamma Air 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad GAMMA AIR DOSE 1.87E-03 6.87E-03 4.90E-03 5.10E-03 1.87E-02

% of Limit 3.74E-02 1.37E-01 9.80E-02 1.02E-01 1.87E-01 Gaseous Effluent Dose Limit - Beta Air 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad BETA AIR DOSE 8.93E-03 8.28E-03 5.30E-03 5.42E-03 2.79E-02

% of Limit 8.93E-02 8.28E-02 5.30E-02 5.42E-02 1.40E-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 1.04E+00 9.09E-01 1.06E+00 1.04E+00 4.06E+00

> 8-day Half-Life - Including C-14

% of Limit 1.39E+01 1.21E+01 1.41E+01 1.39E+01 2.70E+01 DIRECT RADIATION (mrem) 6.00E-01 0.00E+00 0.00E+00 0.00E+00 6.00E-01

Grand Gulf Nuclear Station Year: 2021 Page 19 of 21 Annual Radioactive Effluent Release Report 7.0 METEOROLOGICAL DATA

1. Data recovery for reporting period: 96%

2. Predominant wind direction: From East-Northeast 10.0% of the reporting period

3. Predominant stability class: D (30.3%)

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 Year: 2021 Page 20 of 21 Annual Radioactive Effluent Release Report Attachment 1 Page 1 of 2 Nuclear Energy Institute (NEI) Groundwater Protection Initiative Sample Results GPI Ground Water samples were collected from onsite Dewatering Wells (DW), 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, Iron-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 DW-07 indicated < MDA for all HTD radionuclides.

All results were less than Reporting Levels of GGNS ODCM Table 6.12.1-2.

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

DW-01 4 1,010 < MDA DW-02 4 663 < MDA DW-03 4 953 < MDA DW-04 4 873 < MDA DW-05 4 < 565 < MDA DW-07 4 1,990 < MDA MW-01 4 762 < MDA MW-04 4 < 568 < MDA MW-06 3 1,970 < MDA MW-100B 1 < 482 < MDA MW-101B 4 < 583 < MDA MW-102B 1 < 473 < MDA MW-103B 1 < 467 < MDA MW-104B 1 < 480 < MDA MW-105B 4 689 < MDA MW-106B 4 < 596 < MDA MW-107B 4 1,210 < MDA MW-108B 4 931 < MDA MW-109B 4 1,760 < MDA MW-110B 4 < 585 < MDA

Grand Gulf Nuclear Station Year: 2021 Page 21 of 21 Annual Radioactive Effluent Release Report Page 2 of 2 Nuclear Energy Institute (NEI) Groundwater Protection Initiative Sample Results Maximum Maximum Number of Location TRITIUM GAMMA Samples (pCi/L) (pCi/L)

MW-111B 4 937 < MDA MW-112B 4 < 568 < MDA MW-113B 4 < 584 < MDA MW-114B 4 1,180 < MDA MW-115B 3 1,820 < MDA MW-116B 4 < 590 < MDA MW-118B 4 2,600 < MDA MW-119B 1 < 497 < MDA MW-120B 1 < 493 < MDA MW-121B 1 < 487 < MDA MW-122B 4 < 567 < MDA MW-123B 4 < 564 < MDA MW-1007C 1 < 519 < MDA MW-1009C 1 < 506 < MDA MW-1012C 1 < 500 < MDA MW-1020C 1 < 505 < MDA MW-1024C 1 < 494 < MDA MW-1027C 1 < 513 < MDA MW-1042C 1 < 510 < MDA MW-1082C 1 < 510 < MDA MW-1134C 1 < 505 < MDA P-05 1 < 499 < MDA SW-102 2 < 550 < MDA SW-103A 4 < 568 < MDA

< MDA - Less than Minimum Detectable Activity

Attachment 2 GRAND GULF NUCLEAR STATION OFFSITE DOSE CALCULATION MANUAL DOCKET NO. 50-416 INTRODUCTION The Offsite Dose Calculation Manual (ODCM) describes the methodology and parameters used in the calculation of offsite doses resulting from radioactive liquid and gaseous effluents, in the calculation of liquid and gaseous effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM also contains (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification (TS) 5.5.4, and Technical Requirements Manual (TRM) 7.6.3.2, (2) descriptions of the information that is included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by TS 5.6.2 and 5.6.3, (3) a list and graphical description of the specific sample locations for the Radiological Environmental Monitoring Program, and (4) diagrams of the liquid and gaseous radwaste treatment systems.

The ODCM will be maintained at the station for use as a reference guide and training document of accepted methodologies and calculations. Changes in the calculational methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents the present methodology in all applicable areas.

Computer software to perform the described calculations will be maintained current with the ODCM.

Changes to the ODCM shall be accomplished as specified in TS 5.5.1. Records of reviews performed for changes made to the ODCM shall be retained for the duration of the Unit Operating License.

GRAND GULF, UNIT 1 Revision 43

ODCM REVISION TABLE The following ODCM Revision Table represents changes to the ODCM listed in the order of the most recent change:

Description of Change(s) Revision Month/Year Affected Number of Change Page Number(s)

Revises Table 6.3.10-1 to add table notation (h) 42 02/2020 and (i) to Step 3B Parts a-e Revises Table 6.12-1-1 to change table notation (e) on page A-53 and page A-52 Fish Pathway to notation (f) and moves pre-existing notation (e) on page A-54 to page A-53 Revises Table 6.12.1-1 to change number of samples and locations for Airborne Radioiodine and Particulates to align with Table 3.0-1 previosuly revised Revises all pages to remove previous revision bars and update all pages to current revision Corrections to Table 6.11.4-1 from LBDCR 2012-017 41 01/2019 A-39, A-41 (Correctsions implemented via LBDCR 2018-126)

Revise Tables 2.2-3, 2.2-3a, and 2.2-3b to 40 08/2018 i, vi, vii, replace X/Q and D/Q values with 2007-2016 annual viia, viii, averages. Update Reference 19. Add Reference 2.0-23,

20. 2.0-23a Add air sample location to Table 3.0-1 and to 2.0-23b, Figure 3.0-1. 3.0-2, 3.0-7, A-11 A-11a, A-23 A-23a, A-27 A-50, A-52 Revise ODCM to align usage of FUNCTIONAL versus LBDCR 1/2017 A-13, A-14, OPERABLE 15051 A-17, A-18, A-19, A-20, A-21, A-22, A-24, A-25, A-26, A-27, A-29, A-34, A-37, A-42, A-44, A-62, A-66, A-71, Corrects Revision Table and List of Effective LBDCR 2/2018 i, viii Pages Information for LBDCR 2017-00012 and LBDCR 18012 2017-00008 (Ref CR-GGN-2017-6796 CA4)

Revise Table 6.3.10-1 Section 3B to include note 39 03/2012 i, vii,

h. Note h is to acknowledge 4 Turbine Building viia, viib, roof hatches may be open in Modes 4 and 5. LDCR 2.0-35, A-2012-017 26, A-28, A-39, A-41 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 monitored viib, A-14 and measured, there is no need to suspend dilution flow activities LBDCR 12-012 GRAND GULF, UNIT 1 i Revision 43

Revise Tables 2.2-3, 2.2-3a and 2.2-3b to replace 37 02/2009 i, ii, iii, X/Q and D/Q values with 2001-2005 annual vii, viia, averages, change to Reference 19, say 2008 Land 2.0-23 Use Census utilized, and specify method of 2.0-23a calculating parameters for unavailable location. 2.0-23b Added second onsite vegetation sample location to Tables 2.2-3b and 3.0-2 and to Figure 3.0-1.

2.0-25 thru Renumbered pages 2.0-24a and 2.0-25.

2.0-30 Deleted Pages 3.0-6a, 6b, 6c, and 6d Deleted Section 2.4, Definitions of Gaseous 3.0-3a Effluents Parameters since included throughout 3.0-7 Section 2.0.

Reference:

LBDCR 2008-034 Adds Table 2.2-1.b, Pathway Dose Factors for LCO 36 11/2008 i, ii, iia, 6.11.4 and Section 2.2.1.b, (Pi), for age group v, vii Child. 2.0-8 Changes note for Section 2.2.1.b to use Child 2.0-13 Inhalation Pi values from Table 2.2-1b. 2.0-14

Reference:

LBDCR 2008-014 GRAND GULF, UNIT 1 ii Revision 43

ODCM TABLE OF CONTENTS Section Title Page INTRODUCTION TABLE OF CONTENTS LIST OF FIGURES LIST OF TABLES LIST OF REFERENCES LIST OF EFFECTIVE PAGES 1.0 LIQUID EFFLUENTS 1.1 LIQUID EFFLUENT MONITOR SETPOINTS 1.1.1 Liquid Radwaste Effluent Line Monitors 1.0-1 1.2 DOSE CALCULATIONS FOR LIQUID EFFLUENTS 1.2.1 Maximum Exposed Individual Model 1.0-7 1.2.2 Dose Projection 1.0-8 1.3 LIQUID RADWASTE TREATMENT SYSTEM 1.0-15 2.0 GASEOUS EFFLUENTS 2.1 GASEOUS EFFLUENT MONITOR SETPOINTS 2.1.1 Continuous Ventilation Monitors 2.0-1 2.1.2 Text Deleted 2.0-3 2.2 GASEOUS EFFLUENT DOSE CALCULATIONS 2.2.1 Unrestricted Area Boundary Dose Rate 2.0-7 2.2.2 Unrestricted Area Dose to Individual 2.0-9 2.2.3 Dose Projection 2.0-10b 2.3 METEOROLOGICAL MODEL 2.3.1 Atmospheric Dispersion (Annual Average) 2.0-24 2.3.2 Atmospheric Dispersion (Hourly Average) 2.0-25 2.3.3 Deposition (Hourly Average) 2.0-26 2.4 DELETED 2.0-27 2.5 GASEOUS RADWASTE TREATMENT SYSTEM 2.0-35 2.6 ANNUAL DOSE COMMITMENT 2.0-36 2.6.1 Direct Radiation Dose Measurement 2.0-36 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 3.1 SAMPLING LOCATIONS 3.0-1 APPENDIX A RADIOLOGICAL EFFLUENT CONTROLS AND RADIOLOGICAL A-0 ENVIRONMENTAL MONITORING PROGRAMS 1.0 DEFINITIONS A-2 Table 1.1 SURVEILLANCE FREQUENCY NOTATION (DELETED) A-4 Table 1.2 MODES OF OPERATION (DELETED) A-5 3.0 APPLICABILITY (DELETED) A-6 GRAND GULF, UNIT 1 iii Revision 43

ODCM TABLE OF CONTENTS Section Title Page 5.0 ADMINISTRATIVE CONTROLS A-8 5.6.2 Annual Radiological Environmental Operating Report A-9 5.6.3 Annual Radioactive Effluent Release Report A-10 6.0 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE A-12 REQUIREMENTS 6.3 INSTRUMENTATION 6.3.9 Radioactive Liquid Effluent Monitoring A-13 Instrumentation 6.3.10 Radioactive Gaseous Effluent Monitoring A-18 Instrumentation 6.11 RADIOACTIVE EFFLUENTS 6.11.1 Liquid Effluents Concentration A-29 6.11.2 Liquid Effluent Dose A-34 6.11.3 Liquid Effluent Waste Treatment A-36 6.11.4 Gaseous Effluents Dose Rate A-37 6.11.5 Gaseous Effluent Dose - Noble Gases A-42 6.11.6 Gaseous Effluent Dose - Iodine-131, Iodine-133, A-44 Tritium, and Radionuclides in Particulate Form 6.11.7 Gaseous Radwaste Treatment A-46 6.11.8 Ventilation Exhaust Treatment System A-47 6.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 6.12.1 Monitoring Program A-48 6.12.2 Land Use Census A-59 BASES 6.3 INSTRUMENTATION A-62 6.3.9 Radioactive Liquid Effluent Monitoring A-62 Instrumentation 6.3.10 Radioactive Gaseous Effluent Monitoring A-62 Instrumentation 6.11 RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS 6.11.1 Concentration A-63 6.11.2 Dose A-63 6.11.3 Liquid Waste Treatment A-66 GASEOUS EFFLUENTS 6.11.4 Dose Rate A-66 6.11.5 Dose - Noble Gases A-67 6.11.6 Dose - Iodine-131, Iodine-133, Tritium and A-69 Radionuclides in Particulate Form 6.11.7/6.11.8 Gaseous Radwaste Treatment and Ventilation Exhaust A-71 Treatment 6.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 6.12.1 Monitoring Program A-72 6.12.2 Land Use Census A-73 GRAND GULF, UNIT 1 iv Revision 43

ODCM LIST OF FIGURES Figure Title Page 1.0-1 Example Calibration Curve for Liquid Effluent Monitor 1.0-6 1.3-1 Liquid Radwaste Treatment System 1.0-16 2.3-1 Plume Depletion Effect for Ground-Level Releases 2.0-31 2.3-2 Vertical Standard Deviation of Material in a Plume 2.0-32 2.3-3 Relative Deposition for Ground-Level Releases 2.0-33 2.3-4 Deleted 2.0-34 2.5-1 Gaseous Radwaste Treatment System 2.0-35a 3.0-1 Collection Site Locations, 0-4 Mile Area Map 3.0-7 3.0-2 Collection Site Locations, General Area Map, 4-10 Mile Area Map 3.0-8 LIST OF TABLES Table Title Page 1.2-1 Bioaccumulation Factors 1.0-9 1.2-2 Ingestion Dose Conversion Factors For Adults 1.0-10 1.2-3 Site Related Ingestion Dose Commitment Factor 1.0-13 2.1-1 Dose Factors for Exposure to a Semi-infinite Cloud of Noble 2.0-6 Gases 2.2-1a Pathway Dose Factors for LCO 6.11.4 and Section 2.2.1.b 2.0-11 2.2-1b Pathway Dose Factors for LCO 6.11.4 and Section 2.2.1.b 2.0-13 2.2-2a Pathway Dose Factors for LCO 6.11.6 and Section 2.2.2.b 2.0-15 2.2-2b Pathway Dose Factors for LCO 6.11.6 and Section 2.2.2.b. 2.0-17 2.2-2c Pathway Dose Factors for LCO 6.11.6 and Section 2.2.2.b 2.0-19 2.2-2d Pathway Dose Factors for LCO 6.11.6 and Section 2.2.2.b 2.0-21 2.2-3 Controlling Receptors, Locations and Atmospheric Dispersion 2.0-23 Parameters for LCOs 6.11.5, 6.11.6 and 6.11.8 2.2-3a Site Boundary Atmospheric Dispersion Parameters for LCO 6.11.4 2.0-23a 2.2-3b Additional Receptor Locations within the Site Boundary for LCO 2.0-23b 6.11.4 2.3-1 Deleted 2.0-26 3.0-1 Air Sampler Collection Sites 3.0-2 3.0-2 Miscellaneous Collection Sites 3.0-3 3.0-3 TLD Locations 3.0-4 GRAND GULF, UNIT 1 v Revision 43

ODCM LIST OF REFERENCES

1. Boegli, T. S., R. R. Bellamy, W. L. Britz, and R. L. Waterfield, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"

NUREG-0133 (October 1978).

2. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I, U.S. NRC Regulatory Guide 1.109 (March 1976).

3. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I, U.S. NRC Regulatory Guide 1.109, Rev. 1 (October 1977).

4. "Environmental Report," Mississippi Power and Light Company, Grand Gulf Nuclear Station, Units 1 and 2.

5. "Final Safety Analysis Report," Mississippi Power and Light Company, Grand Gulf Nuclear Station.

6. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light - Water - Cooled Reactors, U.S. NRC Regulatory Guide 1.111 (March 1976).

7. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light - Water - Cooled Reactors, U.S. NRC Regulatory Guide 1.111, Rev. 1 (July 1977).

8. Age-Specific Radiation Dose Commitment Factors for a One-Year Chronic Intake, NUREG-0172, November 1977.

9. EER 93-6246 "X/Q and D/Q Atmospheric Dispersion and Deposition Factors".

10. NPE Calculation #XC-Q1111-94002, Revision 2.

11. GIN 97/01515 "Determination of Composite Dose Factor based on GGNS Historical Gaseous Releases".

12. GIN 99/00152 "Liquid Monitor Trip Setpoint for Tanks with no Gamma Emitters"

13. NUREG/CR-2919, XOQDOQ: Computer Program for the meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations.

14. NPE Calculation #XC-Q1111-01008, Revision 0

15. GIN-2002/00314 Evaluation of Updated Dispersion and Deposition Factors.

16. GIN-2002/00718 Historical ODCM Meteorological Model and Recirculation Factor Calculation Analysis.

17. GIN-2001/01196 Liquid Process and Liquid Effluent Radiation Monitor Calibration Basis.

18. GIN-2005/00562 Radiological Assessment of Storm Drain Tritium discharges at the Grand Gulf Nuclear Station.

19. GIN-2017/00046 Review of 2007-2016 Annual Average Relative Concentration and Relative Deposition.

20. GIN-2018-00104 2007-2016 Annual Average Relative Concentration and Relative Deposition Daylight hours Only.

GRAND GULF, UNIT 1 vi Revision 43

ODCM LIST OF EFFECTIVE PAGES Page No. Page No.

Cover Page 2.0-16a 2.0-16b i

2.0-16c ii 2.0-16d iii 2.0-16e iv 2.0-16f v

2.0-17 vi 2.0-18 vii 2.0-18a viia 2.0-18b viii 2.0-18c 1.0-1 2.0-18d 1.0-2 2.0-18e 1.0-3 2.0-18f 1.0-4 2.0-18g 1.0-5 2.0-18h 1.0-5a 2.0-19 1.0-6 2.0-20 1.0-7 2.0-20a 1.0-8 2.0-20b 1.0-9 2.0-20c 1.0-10 2.0-20d 1.0-11 2.0-20e 1.0-12 2.0-20f 1.0-13 2.0-20g 1.0-14 2.0-20h 1.0-15 2.0-21 1.0-16 2.0-22 2.0-22a 2.0-1 2.0-22b 2.0-2 2.0-22c 2.0-3 2.0-22d 2.0-4 2.0-22e 2.0-5 2.0-22f 2.0-6 2.0-22g 2.0-7 2.0-22h 2.0-8 2.0-23 2.0-9 2.0-23a 2.0-10 2.0-23b 2.0-10a 2.0-24 2.0-10b 2.0-25 2.0-11 2.0-26 2.0-12 2.0-27 2.0-13 2.0-28 2.0-14 2.0-29 2.0-15 2.0-16 GRAND GULF, UNIT 1 vii Revision 43

ODCM LIST OF EFFECTIVE PAGES Page No.

2.0-30 2.0-31 2.0-32 2.0-33 2.0-34 2.0-35 2.0-35a 2.0-36 2.0-37 3.0-1 3.0-2 3.0-3 3.0-3a 3.0-4 3.0-5 3.0-6 3.0-7 3.0-8 GRAND GULF, UNIT 1 viia Revision 43

ODCM LIST OF EFFECTIVE PAGES Page No.

A-0 A-42 A-1 A-43 A-2 A-44 A-3 A-45 A-4 A-46 A-5 A-47 A-6 A-48 A-7 A-49 A-8 A-50 A-9 A-51 A-10 A-52 A-11 A-53 A-11a A-54 A-12 A-55 A-12a A-56 A-13 A-57 A-13a A-58 A-13b A-59 A-14 A-60 A-14a A-61 A-15 A-62 A-16 A-63 A-17 A-64 A-18 A-65 A-19 A-66 A-20 A-67 A-21 A-68 A-22 A-69 A-23 A-70 A-24 A-71 A-25 A-72 A-26 A-73 A-27 A-28 A-29 A-30 A-31 A-32 A-33 A-34 A-35 A-36 A-37 A-38 A-39 A-40 A-41 GRAND GULF, UNIT 1 viii Revision 43

1.0 LIQUID EFFLUENTS 1.1 Liquid Effluent Monitor Setpoints 1.1.1 Liquid Radwaste Effluent Line Monitors Liquid Radwaste Effluent Line Monitors provide alarm and automatic termination of release prior to exceeding ten times the concentration limits specified in 10CFR20, Appendix B, Table 2, Column 2 at the release point to the unrestricted area. To meet this specification and for the purpose of implementation of LCO 6.3.9, the alarm/trip setpoints for liquid effluent monitors and flow measurement devices are set to assure that the following equation is satisfied:

cf C F + f (1) where:

C = ten times the effluent concentration limit (LCO 6.11.1) implementing 10CFR20 for the site, in Ci/ml.

c = The setpoint, representative of a radioactivity concentration in Ci/ml, of the radioactivity monitor measuring the radioactivity in the waste tank effluent line prior to dilution and subsequent release; the setpoint, which is inversely proportional to the volumetric flow of the effluent line and directly proportional to the volumetric flow of the dilution stream plus the waste tank effluent stream, represents a value which, if exceeded, would result in concentrations exceeding ten times the limits of 10CFR20 in the unrestricted area.

GRAND GULF, UNIT 1 1.0-1 Revision 43

f = the waste tank effluent flow setpoint as measured at the radiation monitor location, in volume per unit time, but in the same units as F, below.

F = the dilution water flow setpoint as measured prior to the release point, in volume per unit time.

At Grand Gulf Unit 1, the available dilution water flow (F) should be constant for a given release, and the waste tank flow (f) and monitor setpoint (c) are set to meet the condition of equation 1 for a given effluent concentration, C. The method by which this is accomplished is as follows:

Step 1) The isotopic concentration for a waste tank to be released is obtained from the sum of the measured concentrations as determined by the analysis required in ODCM Table 6.11.1-1:

C = C + C + C + C + C (2) i g a s t f i g s where:

C = the sum of concentrations C of each measured gamma g g g emitter observed by gamma-ray spectroscopy of the waste sample.

C = the concentration C of gross alpha emitters in a a liquid waste as measured in the monthly composite sample.

C = the measured concentrations of Sr-89 and Sr-90 in s s liquid waste as observed in the quarterly composite sample.

GRAND GULF, UNIT 1 1.0-2 Revision 43

C = the measured concentration of H-3 in liquid waste as t

determined from analysis of the monthly composite sample.

C = the concentration of Fe-55 in liquid waste as measured f

in the quarterly composite sample.

The C term will be included in the analysis of each waste g

tank batch to be released; terms for alpha, strontiums, tritium and iron are included if analysis of liquid waste has shown the presence of these isotopes.

Step 2) The measured radionuclide concentrations are used to calculate a Dilution Factor, D.F., which is the ratio of total dilution flow rate to waste tank effluent flow rate required to assure that ten times the limiting concentration of 10CFR20, Appendix B, Table 2, Column 2 are met at the point of discharge.

C i

D.F. = [ ] x S.F.

i EC i

C C C C C g a s t f

= [ + + + + ] x S.F. (3) g EC EC s EC EC EC g a s t f where:

C = C , C , C , C and C ; measured concentrations as i g a s t f defined in Step 1. Terms C , C , C and C will be a s t f included in the calculation as appropriate.

GRAND GULF, UNIT 1 1.0-3 Revision 43

EC = EC , EC , EC ,EC and EC are ten times the i g a s t f limiting concentrations of the appropriate radionuclide from 10CFR20, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4

µCi/ml total activity.

S.F. = an administrative safety factor normally applied at Grand Gulf which causes the calculated Dilution Factor to be two (2) times larger than the dilution factor required for compliance with ten times 10CFR20 limits.

Step 3) The maximum permissible waste tank effluent flow rate prior to dilution, f , is calculated based on a fixed fraction of d

the dilution flow rate, F :

d F + f F d d d f for F >>f d d d (4)

D.F. D.F.

where:

F = 0.9 x minimum expected dilution flow rate d

f = maximum permissible waste tank effluent flow rate d

D.F. = Dilution Factor from Step 2.

NOTE: Equation 4 is valid only for D.F.>1; for D.F.1, the waste tank effluent concentration meets the limits of ten times the limiting concentrations of 10CFR20 without dilution, and f may take on any desired value.

d Step 4) The dilution flow rate setpoint for minimum dilution flow rate, F, and waste tank flow rate setpoint for maximum waste tank effluent flow rate, f, are calculated as follows:

F = F = 0.9 x minimum expected dilution flow rate(5) d f = 0.9 x f = 0.9 x calculated maximum waste tank flow d

rate for the stated release conditions.(6)

GRAND GULF, UNIT 1 1.0-4 Revision 43

Thus, if instrumentation indicates the dilution flow rate falls below the assumed flow rate of 90 percent of the actual dilution flow, or if the waste tank effluent flow rate exceeds 90 percent of the calculated maximum waste tank effluent flow rate, the release is terminated (manually or automatically).

Step 5) The radioactivity monitor setpoint may now be specified based on the values of C , F, and f which were specified i i to provide compliance with ten times the limits of 10CFR20, Appendix B, Table 2, Column 2. The monitor response is primarily to gamma radiation; therefore, when determining the setpoint, Sp the summation of the gamma emitters in the tank is used and Sp is determined as follows:

Sp(cpm) = (fd/fa x Cg x MRF)

Where:

fd = maximum permissible waste tank effluent flow rate (gpm) fa = actual or maximum expected waste tank effluent flow rate (gpm)

Cg = Summation of all detected gamma emitters (uCi/ml)

MRF = Monitor Response Factor (cpm/uCi/ml) (Figure 1.0-1)(17)

For waste tanks where the quantity of gamma emitters does not produce a significant response above background, Sp, may be determined as follows:

If Sp = 0, i.e. no gamma emitters present, then Sp = 2700 cpm Or If Sp < (Monitor Error x Background), then Sp = (Monitor Error x Background). Provided that the error times the background is not greater than 2700 cpm.

GRAND GULF, UNIT 1 1.0-5 Revision 43

Note: 2700 cpm is based on Cesium-137 monitor response and the limits specified in LCO 6.11.1. (12)

The Monitor Error will normally be set at 25% (based on the calibration error)(17).

The liquid monitor trip setpoint = Sp + Monitor Background NOTE: Setpoint adjustments are not required if the existing setpoint corresponds to a lower count rate than the calculated value. The setpoint contains a factor of conservatism, even if the calculated maximum waste tank flow rate is attainable, since the calculated rate contains the safety factor margin, waste tank effluent flow rate margin, and the dilution flow rate margin. In practice, the actual waste tank effluent flow rate normally is many times less than the calculated tank flow rate, thus providing an additional conservatism during release.

GRAND GULF, UNIT 1 1.0-5a Revision 43

Figure 1.0-1 Example Calibration Curve for Liquid Effluent Monitor Count Rate (Counts per Minute)

GRAND GULF, UNIT 1 1.0-6 Revision 43

1.2 Dose Calculations for Liquid Effluents 1.2.1 Maximum Exposed Individual Model The dose contribution to the maximum exposed individual from all radionuclides identified in liquid effluents released to unrestricted areas is calculated for the purpose of implementing LCO 6.11.2, 6.11.3, and TS 5.6.3 using the following expression:

m (1)

D = [A t C F ] (millirem) (8)

Tau iTau l il l i l=1 where:

A = Site-related ingestion dose commitment factor iTau for radionuclide i, in millirem/hr per Ci/ml.

= K U BF DF o F i i t = length of the time period over which C and F l il l are averaged for all liquid releases, in hours.

C = average concentration of radionuclide i observed il in the undiluted liquid effluent during time period tl from any liquid release in Ci/ml.

Concentrations are determined in accordance with the requirements of Table 6.11.1-1, 6.12-1-1 and 6.12.1-3. For composite samples, the last measured value from the most recent monthly and quarterly composite samples will be used in the dose calculation.

NOTE: LLD values are not used in dose calculations.

GRAND GULF, UNIT 1 1.0-7 Revision 43

F = Dilution factor for C during any liquid effluent l il release. For releases via the discharge basin, F1 is the dilution in the near field and is defined as the ratio of the average undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestricted (5) receiving waters times the applicable factor of 2

= average undiluted liquid waste flow average flow from site discharge x 2 For releases via the 007 outfall, F1 is defined as the 007 outfall runoff to the total runoff into Hamilton Lake. It is the environmental dilution derived from the lowest historical annual precipitation as recorded in the FSAR = 0.10(18) 5 K = units conversion factor 1.14 x 10 o

6 3

= 10 pCi x 10 ml 8766 hr Ci kg yr (3)

U = adult fish consumption (21 kg/yr) .

F BFi = Bioaccumulation factor for each nuclide, i, in fish, in pCi/kg per pCi/1 from ODCM Table 1.2-1.

DFi = Dose conversion factor for each nuclide, i, for adults in preselected organ, Tau, in mrem/pCi, from ODCM Table 1.2-2.

Calculated values of A for radionuclides which might be iTau observed in liquid effluents are given in ODCM Table 1.2-3.

1.2.2 Dose Projection Doses from liquid effluents to UNRESTRICTED AREAS are projected at least every 31 days as required by LCO 6.11.3.

These projections are made by averaging the doses (D )

Tau from previous operating history (normally the previous six months) which is indicative of expected future operations.

GRAND GULF, UNIT 1 1.0-8 Revision 43

TABLE 1.2-1 BIOACCUMULATION FACTORS, (BF )

i (pCi/kg per pCi/liter)*

FRESHWATER ELEMENT FISH INVERTEBRATE H 9.0E-01 9.0E-01 C 4.6E+03 9.1E+03 NA 1.0E+02 2.0E+02 P 1.0E+05 2.0E+04 CR 2.0E+02 2.0E+03 MN 4.0E+02 9.0E+04 FE 1.0E+02 3.2E+03 CO 5.0E+01 2.0E+02 NI 1.0E+02 1.0E+02 CU 5.0E+01 4.0E+02 ZN 2.0E+03 1.0E+04 BR 4.2E+02 3.3E+02 RB 2.0E+03 1.0E+03 SR 3.0E+01 1.0E+02 Y 2.5E+01 1.0E+03 ZR 3.3E+00 6.7E+00 NB 3.0E+04 1.0E+02 MO 1.0E+01 1.0E+01 TC 1.5E+01 5.0E+00 RU 1.0E+01 3.0E+02 RH 1.0E+01 3.0E+02 SB 1.0E+00 1.0E+01 TE 4.0E+02 6.1E+03 I 1.5E+01 5.0E+00 CS 2.0E+03 1.0E+03 BA 4.0E+00 2.0E+02 LA 2.5E+01 1.0E+03 CE 1.0E+00 1.0E+03 PR 2.5E+01 1.0E+03 ND 2.5E+01 1.0E+03 W 1.2E+03 1.0E+01 NP 1.0E+01 4.0E+02

Values in Table 1.2-1 are taken from Reference 3, Table A-1, except for SB which was taken from Reference 2, Table A-8.

GRAND GULF, UNIT 1 1.0-9 Revision 43

TABLE 1.2-2 INGESTION DOSE CONVERSION FACTORS FOR ADULTS, (DF )

i (mrem per pCi ingested)

Page 1 of 3 NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P 32 1.93E-04 1.20E-05 7.46E-06 NO DATA NO DATA NO DATA 2.17E-05 CR 51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN 54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 MN 56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 FE 55 2.75E-06 1.90E-06 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CO 58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 CO 60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E-04 9.01E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 NI 65 5.28E-07 6.86E-08 3.13E-08 NO DATA NO DATA NO DATA 1.74E-06 CU 64 NO DATA 8.33E-08 3.91E-08 NO DATA 2.10E-07 NO DATA 7.10E-06 ZN 65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ZN 69 1.03E-08 1.97E-08 1.37E-09 NO DATA 1.28E-08 NO DATA 2.96E-09 BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13 BR 85 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E-08 3.21E-08 NO DATA NO DATA NO DATA 8.36E-19 RB 89 NO DATA 4.01E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 SR 91 5.67E-06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 Y 91M 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1.41E-07 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 Y 92 8.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05

Values taken from Reference 3, Table E-11.

GRAND GULF, UNIT 1 1.0-10 Revision 43

TABLE 1.2-2 (Continued)

INGESTION DOSE CONVERSION FACTORS FOR ADULTS, (DF )

i (mrem per pCi ingested)

Page 2 of 3 NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 ZR 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ZR 97 1.68E-09 3.39E-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04 NB 95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 MO 99 NO DATA 4.31E-06 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E-10 6.98E-10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07 TC101 2.54E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1.87E-10 1.10E-21 RU103 1.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 RU105 1.54E-08 NO DATA 6.08E-09 NO DATA 1.99E-07 NO DATA 9.42E-06 RU106 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31E-06 NO DATA 1.78E-04 AG110M 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91E-07 NO DATA 6.04E-05 SB124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 0.0 2.18E-06 7.95E-05 SB125+D 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.0 1.38E-06 1.97E-05 SB126 1.15E-06 2.34E-08 4.15E-07 7.04E-09 0.0 7.05E-07 9.40E-05 SB127 2.58E-07 5.65E-09 9.90E-08 3.10E-09 0.0 1.53E-07 5.90E-05 TE125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 TE127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05 TE129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 NO DATA 2.37E-08 TE131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 TE131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09 TE132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 NO DATA 7.71E-05 I 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06 I 131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 I 132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 NO DATA 1.02E-07 I 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06 I 134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 NO DATA 2.51E-10 I 135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31E-06 CS134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 CS136 6.51E-06 2.57E-05 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06

Values taken from Reference 3, Table E-11, except for SB values which were taken from Reference 8, Table 4.

GRAND GULF, UNIT 1 1.0-11 Revision 43

TABLE 1.2-2 (Continued)

INGESTION DOSE CONVERSION FACTORS FOR ADULTS, (DF )

i (mrem per pCi ingested)

Page 3 of 3 NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI CS137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 CS138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E-08 7.91E-09 4.65E-13 BA139 9.70E-08 6.91E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 BA140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 BA141 4.71E-08 3.56E-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E-17 BA142 2.13E-08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.00E-26 LA140 2.50E-09 1.26E-09 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA142 1.28E-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 CE141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE143 1.65E-09 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 PR143 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 PR144 3.01E-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 ND147 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 W 187 1.03E-07 8.61E-08 3.01E-08 NO DATA NO DATA NO DATA 2.82E-05 NP239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E-05

Values taken from Reference 3, Table E-11 GRAND GULF, UNIT 1 1.0-12 Revision 43

TABLE 1.2-3 SITE RELATED INGESTION DOSE COMMITMENT FACTOR Page 1 of 2 Release Type: 1 Liquid Dose Factor: 0 AiTau ((mrem/hr)/(uCi/ml))*

AgeGroup: 0 ADULT Pathway: 2 Fresh Water Fish - Comm. (FFCM)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 0.00e+00 2.26e-01 2.26e-01 2.26e-01 2.26e-01 2.26e-01 0.00e+00 2.26e-01 C-14 3.13e+04 6.26e+03 6.26e+03 6.26e+03 6.26e+03 6.26e+03 0.00e+00 6.26e+03 NA-24 4.07e+02 4.07e+02 4.07e+02 4.07e+02 4.07e+02 4.07e+02 0.00e+00 4.07e+02 P-32 4.62e+07 2.87e+06 0.00e+00 0.00e+00 0.00e+00 5.19e+06 0.00e+00 1.79e+06 CR-51 0.00e+00 0.00e+00 7.61e-01 2.81e-01 1.69e+00 3.20e+02 0.00e+00 1.27e+00 MN-54 0.00e+00 4.38e+03 0.00e+00 1.30e+03 0.00e+00 1.34e+04 0.00e+00 8.35e+02 MN-56 0.00e+00 1.10e+02 0.00e+00 1.40e+02 0.00e+00 3.51e+03 0.00e+00 1.95e+01 FE-55 6.58e+02 4.55e+02 0.00e+00 0.00e+00 2.54e+02 2.61e+02 0.00e+00 1.06e+02 FE-59 1.04e+03 2.44e+03 0.00e+00 0.00e+00 6.82e+02 8.14e+03 0.00e+00 9.36e+02 CO-58 0.00e+00 8.92e+01 0.00e+00 0.00e+00 0.00e+00 1.81e+03 0.00e+00 2.00e+02 CO-60 0.00e+00 2.56e+02 0.00e+00 0.00e+00 0.00e+00 4.81e+03 0.00e+00 5.65e+02 NI-63 3.11e+04 2.16e+03 0.00e+00 0.00e+00 0.00e+00 4.50e+02 0.00e+00 1.04e+03 NI-65 1.26e+02 1.64e+01 0.00e+00 0.00e+00 0.00e+00 4.17e+02 0.00e+00 7.49e+00 CU-64 0.00e+00 9.97e+00 0.00e+00 2.51e+01 0.00e+00 8.50e+02 0.00e+00 4.68e+00 ZN-65 2.32e+04 7.37e+04 0.00e+00 4.93e+04 0.00e+00 4.64e+04 0.00e+00 3.33e+04 ZN-69 4.93e+01 9.43e+01 0.00e+00 6.13e+01 0.00e+00 1.42e+01 0.00e+00 6.56e+00 BR-83 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.82e+01 0.00e+00 4.04e+01 BR-84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.11e-04 0.00e+00 5.24e+01 BR-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.15e+00 RB-86 0.00e+00 1.01e+05 0.00e+00 0.00e+00 0.00e+00 1.99e+04 0.00e+00 4.71e+04 RB-88 0.00e+00 2.90e+02 0.00e+00 0.00e+00 0.00e+00 4.00e-09 0.00e+00 1.54e+02 RB-89 0.00e+00 1.92e+02 0.00e+00 0.00e+00 0.00e+00 1.12e-11 0.00e+00 1.35e+02 SR-89 2.21e+04 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.55e+03 0.00e+00 6.35e+02 SR-90 5.44e+05 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.57e+04 0.00e+00 1.34e+05 SR-91 4.07e+02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.94e+03 0.00e+00 1.64e+01 SR-92 1.54e+02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.06e+03 0.00e+00 6.68e+00 Y-90 5.76e-01 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.10e+03 0.00e+00 1.54e-02 Y-91 8.44e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.64e+03 0.00e+00 2.26e-01 Y-91M 5.44e-03 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.60e-02 0.00e+00 2.11e-04 Y-92 5.06e-02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.86e+02 0.00e+00 1.48e-03 Y-93 1.60e-01 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.09e+03 0.00e+00 4.43e-03 ZR-95 2.40e-01 7.70e-02 0.00e+00 1.21e-01 0.00e+00 2.44e+02 0.00e+00 5.21e-02 ZR-97 1.33e-02 2.68e-03 0.00e+00 4.04e-03 0.00e+00 8.30e+02 0.00e+00 1.22e-03 NB-95 4.47e+02 2.48e+02 0.00e+00 2.46e+02 0.00e+00 1.51e+06 0.00e+00 1.34e+02 MO-99 0.00e+00 1.03e+02 0.00e+00 2.34e+02 0.00e+00 2.39e+02 0.00e+00 1.96e+01 TC-99M 8.87e-03 2.51e-02 0.00e+00 3.81e-01 1.23e-02 1.48e+01 0.00e+00 3.19e-01 TC-101 9.12e-03 1.31e-02 0.00e+00 2.37e-01 6.72e-03 3.95e-14 0.00e+00 1.29e-01 RU-103 4.43e+00 0.00e+00 0.00e+00 1.69e+01 0.00e+00 5.17e+02 0.00e+00 1.91e+00 RU-105 3.69e-01 0.00e+00 0.00e+00 4.76e+00 0.00e+00 2.26e+02 0.00e+00 1.46e-01 RU-106 6.58e+01 0.00e+00 0.00e+00 1.27e+02 0.00e+00 4.26e+03 0.00e+00 8.33e+00 AG-110M 8.81e-01 8.15e-01 0.00e+00 1.60e+00 0.00e+00 3.33e+02 0.00e+00 4.84e-01

Calculated from Equation 8.

GRAND GULF, UNIT 1 1.0-13 Revision 43

TABLE 1.2-3 (Continued)

SITE RELATED INGESTION DOSE COMMITMENT FACTOR Page 2 of 2 Release Type: 1 Liquid Dose Factor: 0 AiTau ((mrem/hr)/(uCi/ml))*

AgeGroup: 0 ADULT Pathway: 2 Fresh Water Fish - Comm. (FFCM)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB SB-124 6.70e+00 1.27e-01 1.63e-02 0.00e+00 5.22e+00 1.90e+02 0.00e+00 2.66e+00 SB-125 4.29e+00 4.79e-02 4.36e-03 0.00e+00 3.30e+00 4.72e+01 0.00e+00 1.02e+00 TE-125M 2.57e+03 9.30e+02 7.72e+02 1.04e+04 0.00e+00 1.02e+04 0.00e+00 3.44e+02 TE-127 1.05e+02 3.78e+01 7.80e+01 4.29e+02 0.00e+00 8.31e+03 0.00e+00 2.28e+01 TE-127M 6.48e+03 2.32e+03 1.66e+03 2.63e+04 0.00e+00 2.17e+04 0.00e+00 7.90e+02 TE-129 3.01e+01 1.13e+01 2.31e+01 1.26e+02 0.00e+00 2.27e+01 0.00e+00 7.33e+00 TE-129M 1.10e+04 4.11e+03 3.78e+03 4.60e+04 0.00e+00 5.54e+04 0.00e+00 1.74e+03 TE-131 1.89e+01 7.88e+00 1.55e+01 8.26e+01 0.00e+00 2.67e+00 0.00e+00 5.96e+00 TE-131M 1.66e+03 8.10e+02 1.28e+03 8.21e+03 0.00e+00 8.04e+04 0.00e+00 6.75e+02 TE-132 2.41e+03 1.56e+03 1.72e+03 1.50e+04 0.00e+00 7.38e+04 0.00e+00 1.47e+03 I-130 2.71e+01 8.01e+01 6.79e+03 1.25e+02 0.00e+00 6.89e+01 0.00e+00 3.16e+01 I-131 1.49e+02 2.14e+02 7.00e+04 3.66e+02 0.00e+00 5.64e+01 0.00e+00 1.22e+02 I-132 7.29e+00 1.95e+01 6.82e+02 3.11e+01 0.00e+00 3.66e+00 0.00e+00 6.82e+00 I-133 5.10e+01 8.87e+01 1.30e+04 1.55e+02 0.00e+00 7.97e+01 0.00e+00 2.70e+01 I-134 3.81e+00 1.03e+01 1.79e+02 1.64e+01 0.00e+00 9.01e-03 0.00e+00 3.70e+00 I-135 1.59e+01 4.17e+01 2.75e+03 6.68e+01 0.00e+00 4.70e+01 0.00e+00 1.54e+01 CS-134 2.98e+05 7.09e+05 0.00e+00 2.29e+05 7.61e+04 1.24e+04 0.00e+00 5.79e+05 CS-136 3.12e+04 1.23e+05 0.00e+00 6.85e+04 9.38e+03 1.40e+04 0.00e+00 8.86e+04 CS-137 3.82e+05 5.22e+05 0.00e+00 1.77e+05 5.89e+04 1.01e+04 0.00e+00 3.42e+05 CS-138 2.64e+02 5.22e+02 0.00e+00 3.84e+02 3.79e+01 2.23e-03 0.00e+00 2.59e+02 BA-139 9.29e-01 6.62e-04 0.00e+00 6.19e-04 3.75e-04 1.65e+00 0.00e+00 2.72e-02 BA-140 1.94e+02 2.44e-01 0.00e+00 8.30e-02 1.40e-01 4.00e+02 0.00e+00 1.27e+01 BA-141 4.51e-01 3.41e-04 0.00e+00 3.17e-04 1.93e-04 2.13e-10 0.00e+00 1.52e-02 BA-142 2.04e-01 2.10e-04 0.00e+00 1.77e-04 1.19e-04 2.87e-19 0.00e+00 1.28e-02 LA-140 1.50e-01 7.54e-02 0.00e+00 0.00e+00 0.00e+00 5.54e+03 0.00e+00 1.99e-02 LA-142 7.66e-03 3.48e-03 0.00e+00 0.00e+00 0.00e+00 2.54e+01 0.00e+00 8.68e-04 CE-141 2.24e-02 1.52e-02 0.00e+00 7.04e-03 0.00e+00 5.79e+01 0.00e+00 1.72e-03 CE-143 3.95e-03 2.92e+00 0.00e+00 1.29e-03 0.00e+00 1.09e+02 0.00e+00 3.23e-04 CE-144 1.17e+00 4.88e-01 0.00e+00 2.90e-01 0.00e+00 3.95e+02 0.00e+00 6.27e-02 PR-143 5.51e-01 2.21e-01 0.00e+00 1.27e-01 0.00e+00 2.41e+03 0.00e+00 2.73e-02 PR-144 1.80e-03 7.48e-04 0.00e+00 4.22e-04 0.00e+00 2.59e-10 0.00e+00 9.16e-05 ND-147 3.76e-01 4.35e-01 0.00e+00 2.54e-01 0.00e+00 2.09e+03 0.00e+00 2.60e-02 W-187 2.96e+02 2.47e+02 0.00e+00 0.00e+00 0.00e+00 8.10e+04 0.00e+00 8.65e+01 NP-239 2.85e-02 2.80e-03 0.00e+00 8.74e-03 0.00e+00 5.75e+02 0.00e+00 1.54e-03 SB-126 2.75e+00 5.62e-02 1.69e-02 0.00e+00 1.69e+00 2.25e+02 0.00e+00 9.94e-01 SB-127 6.18e-01 1.35e-02 7.42e-03 0.00e+00 3.66e-01 1.41e+02 0.00e+00 2.37e-01

Calculated from Equation 8.

GRAND GULF, UNIT 1 1.0-14 Revision 43

1.3 Liquid Radwaste Treatment System The essential components of the liquid radwaste treatment system are indicated by an asterisk (*).

The radwaste system includes provisions for use of alternate liquid radioactive processing equipment. This system may be used in place of the precoat filters and may contain striners, carbon bed filters, cartridge filters, a reverse osmosis unit or other components which process liquid radioactive wastes. Bypassing the precoat filter (an essential component) is acceptable provided that the effluent from the alternative system provides the same level of filtration required for the precoat filters.

NOTES for Figure ODCM 1.3-1 (1) The essential components outlined on the following page are those necessary to collect, process and sample liquid radwaste prior to discharge to the environment.

(2) Only one of the following is required in order to process liquid waste.

a. Equipment drain filter

b. Floor drain filter

c. Equipment drain demineralizer

d. Floor drain demineralizer (3) The Waste Surge Tanks may be used to replace the Waste Collection Tanks.

GRAND GULF, UNIT 1 1.0-15 Revision 43

Figure 1.3-1 Liquid Radwaste Treatment System GRAND GULF, UNIT 1 1.0-16 Revision 43

2.0 GASEOUS EFFLUENTS 2.1 Gaseous Effluent Monitor Setpoints 2.1.1 Continuous Ventilation Monitors For the purpose of implementation of LCO 6.3.10, the alarm setpoint level for continuous ventilation noble gas monitors will be calculated as follows:

S = count rate (cpm) above background of vent noble gas V

monitor at the alarm setpoint level PF x R x D t TB

= the lesser of or PF x R x D s ss where:

PF = product of allocation factor (AF) and safety factor (SF), normally set at 0.1 AF = allocation factor allowing for a total of four normal effluent release points, normally set at 0.25 SF = safety factor allowing for cumulative uncertainties of measurements, normally set at 0.4 D = dose rate limit to the total body of an individual TB at the SITE BOUNDARY or at UNRESTRICTED AREAS inside the SITE BOUNDARY required to limit dose to 500 mrem in one year

= 500 mrem/yr D = dose rate limit to the skin of the body of an ss individual at the SITE BOUNDARY or at UNRESTRICTED AREAS inside the SITE BOUNDARY required to limit dose to 3000 mrem in one year

= 3000 mrem/yr GRAND GULF, UNIT 1 2.0-1 Revision 43

R = count rate (cpm) per mrem/yr to the total body t

= C [ X/Q K Q' ]

i i i

where:

C = count rate (cpm) above background of the vent monitor corresponding to grab sample radionuclide concentrations X/Q = highest historical annual average atmospheric dispersion at the SITE BOUNDARY or at UNRESTRICTED AREAS inside the SITE BOUNDARY from Table 2.2-3a or Table 2.2-3b Ki = total body dose factor due to gamma emissions from each noble gas radionuclide i (mrem/yr per µCi/m3) from ODCM Table 2.1-1 Q' = rate of release of noble gas radionuclide i (Ci/sec) i from the release point R = count rate (cpm) per mrem/yr to the skin s

= C X/Q [ (L + 1.1 M ) Q' ]

i i i i L = skin dose factor due to beta emissions from isotope i i

3 (mrem/yr per µCi/m ) from ODCM Table 2.1-1 1.1 = mrem skin dose per mrad air dose M = air dose factor due to gamma emissions from isotope i i

3 (mrad/yr per µCi/m ) from ODCM Table 2.1-1 GRAND GULF, UNIT 1 2.0-2 Revision 43

2.1.2 TEXT DELETED GRAND GULF, UNIT 1 2.0-3 Revision 43

NOTES For Section 2.1.1

1) The calculated setpoint values will determine the allowable bounds for the actual setpoint adjustments. That is, setpoint adjustments are not required to be performed if the existing setpoint level corresponds to a count rate that is less than or equal to + 25% of the calculated value.

If radionuclides are not detected in the grab sample, then the previously calculated setpoint may remain as the valid setpoint.

2) A conservative setpoint may be calculated using a composite total body dose factor. This method may be used when there are no valid isotopics available. The conservative setpoint will be calculated as follows:

S = count rate (cpm) above background of vent noble gas monitor at the v

alarm setpoint level*

= PF' x D x R "

TB t where:

PF = product of allocation factor (AF) and safety factor (SF'), normally set at 0.1 AF = allocation factor allowing for a total of four normal effluent release points, normally set at 0.25 SF' = safety factor allowing for cumulative uncertainties of measurements, normally set at 0.4.

R " = conservative count rate per mrem/yr to the total body (Xe-133 t

detection, composite dose factor)

= (3.53E-5) (60)

X/Q (X)(V)(K)

The setpoint calculation based on a skin dose is not required because the setpoint based on the total body dose is more conservative.

GRAND GULF, UNIT 1 2.0-4 Revision 43

where:

X = Xe-133 volume efficiency factor of the detector system in

µCi/cc/cpm as determined by the primary calibration*

V = maximum designed ventilation flow rate in cubic feet per minute (cfm) 3 3.53E-5 = conversion factor, ft per cc 60 = conversion factor, seconds per minute K = total body dose factor for historical mixture**,

3

= 1.51E + 03 mrem/yr per µCi/m Other variables as defined in Section 2.1.1

The instrument calibration procedures will include checks to ensure that the detector efficiency meets acceptance criteria.

- ODCM Reference 11 GRAND GULF, UNIT 1 2.0-5 Revision 43

TABLE 2.1-1 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES Nuclide Y-Body** Ki B-Skin** Li Y-Air* Mi B-Air* Ni AR-41 8.84E+03*** 2.69E+03 9.30E+03 3.28E+03 KR-83M 7.56E-02 0.00E+00 1.93E+01 2.88E+02 KR-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 KR-85M 1.17E+03 1.46E+03 1.23E+03 1.97E+03 KR-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 KR-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 KR-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 KR-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 XE-131M 9.15E+01 4.76E+02 1.56E+02 1.11E+03 XE-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 XE-133M 2.51E+02 9.94E+02 3.27E+02 1.48E+03 XE-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 XE-135M 3.12E+03 7.11E+02 3.36E+03 7.39E+02 XE-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 XE-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Values taken from Reference 3, Table B-1

mrad - m³ Ci - yr

- mrem - m³ Ci - yr 3

- - 8.84E+03 = 8.84 x 10 GRAND GULF, UNIT 1 2.0-6 Revision 43

2.2 Gaseous Effluent Dose Calculations 2.2.1 Unrestricted Area Boundary Dose Rate

a. For the purpose of implementation of LCO 6.11.4.a, the dose rate at the SITE BOUNDARY or at UNRESTRICTED AREAS within the SITE BOUNDARY due to noble gases shall be calculated as follows:

D = average total body dose rate in current year tb (mrem/yr)

= X/Q K Q' i i D = average skin dose rate in current year s

(mrem/yr)

= X/Q (L + 1.1M ) Q' i i i

b. Organ dose rate due to tritium, I-131, I-133 and all radioactive materials in particulate form, with half-lives greater than eight days will be calculated for the purpose of implementation of LCO 6.11.4.b as follows:

D = average organ dose rate in current year o

(mrem/yr)

= W P Q' i i i

where:

GRAND GULF, UNIT 1 2.0-7 Revision 43

W = highest historical annual average atmospheric dispersion at the SITE BOUNDARY or UNRESTRICTED AREAS inside the SITE BOUNDARY for the appropriate pathway from Table 2.2-3a or 2.2-3b.

Use X/Q for inhalation and all tritium pathways or Use D/Q for food and ground plane pathways P = the total dose parameter for radionuclide i, i

3 (mrem/yr per µCi/m ) for inhalation and all 2

tritium pathways and (m . mrem/yr per µCi/sec) for food and ground plane pathways, from ODCM Table 2.2-1b*

Q' = rate of release of noble gas radionuclide i i

(µCi/sec) from the release point Q' = average release rate of isotope i of tritium, i

I-131, I-133 or other radionuclide in particulate form, with half-lives greater than eight (8) days in the current year (µCi/sec)

Use child/inhalation pathway from Table 2.2-1b unless land use census identifies an infant/grass/cow/milk pathway. Then Table 2.2-1a may apply.

GRAND GULF, UNIT 1 2.0-8 Revision 43

2.2.2 Unrestricted Area Dose to Individual

a. For the purpose of implementation of LCO 6.11.5, the air dose at the SITE BOUNDARY or at UNRESTRICTED AREAS within the SITE BOUNDARY shall be determined as follows:

D = air dose due to gamma emissions from noble gas radionuclide i (mrad)

-8 ____

= 3.17 x 10 M X/Q' Q i i i where:

X/Q' = highest historical annual average atmospheric for the SITE BOUNDARY or at UNRESTRICTED AREAS within the SITE BOUNDARY from Table 2.2-3a or 2.2-3b.

M = air dose factor due to gamma emissions from i

3 noble gas radionuclide i (mrad/yr per Ci/m )

from ODCM Table 2.1-1 GRAND GULF, UNIT 1 2.0-9 Revision 43

Q = cumulative release of radionuclide i of noble i

gas, tritium, I-131, I-133, or material in particulate form over the period of interest (Ci)

-8 Note: 3.17 x 10 is the inverse of the number of seconds per year, and D = air dose due to beta emissions from noble gas radionuclide i (mrad)

-8 ___

= 3.17 x 10 N X/Q' Q i i i where:

N = air dose factor due to beta emissions from i

3 noble gas radionuclide i (mrad/yr per Ci/m )

from ODCM Table 2.1-1 X/Q' = highest historical annual average atmospheric dispersion for the SITE BOUNDARY or at UNRESTRICTED AREAS within the SITE BOUNDARY, from Table 2.2-3a or 2.2-3b.

Q = cumulative release of radionuclide i of noble i

gas, tritium, I-131, I-133, or material in particulate form over the period of interest (Ci)

GRAND GULF, UNIT 1 2.0-10 Revision 43

2.2.2 Unrestricted Area Dose to Individual

b. Dose to an individual from tritium, I-131, I-133 and radioactive materials in particulate form, with half-lives greater than eight (8) days will be calculated for the purpose of implementation of LCO 6.11.6 as follows:

D = dose to an individual from tritium, I-131, I-133 p

and radionuclides in particulate form, with half-life greater than eight days (mrem)

-8

= 3.17 x 10 R W' Q i i i

where:

W' = historical annual average X/Q and D/Q at a controlling location for an individual from Table 2.2-3*

X/Q' = for inhalation and all tritium pathways or D/Q' = for food and ground plane pathways R = the total dose factor for radionuclide i, i

3 (mrem/yr per Ci/m ) for inhalation and all 2

tritium pathways and (m . mrem/yr per Ci/sec) for food and ground plane pathways from Tables 2.2-2a - d

Dose for each controlling receptor in Table 2.2-3 is calculated and the highest dose is selected for implementation of LCO 6.11.6. The most limiting age group, child, is assumed. In accordance with ODCM Reference 1, historical annual average atmospheric dispersion conditions are used. However, real time annual average dispersion conditions are coupled with the annual release and summarized in the Annual Radioactive Effluent Release Report.

GRAND GULF, UNIT 1 2.0-10a Revision 43

2.2.2 Unrestricted Area Dose to Individual Q = cumulative release of radionuclide i of noble i

gas, tritium, I-131, I-133, or material in particulate form over the period of interest (Ci)

c. For the purpose of implementing TS 5.6.3, dose calculations will be performed using the above equations or with the substitution of average meteorological parameters (most limiting parameters will be used) which prevailed for the period of the report.

2.2.3 Dose Projection Doses from gaseous effluents to UNRESTRICTED AREAS are projected at least every 31 days as required by LCO 6.11.8. These projections are made by averaging the doses (D , D , D ) from previous operating history (normally the P

previous six months) which is indicative of future expected operations.

GRAND GULF, UNIT 1 2.0-10b Revision 43

TABLE 2.2-1a PATHWAY DOSE FACTORS FOR LCO 6.11.4 and SECTION 2.2.1.b, (P )

i Page 1 of 2 AGE GROUP (INFANT) ( N.A. ) (INFANT)

ISOTOPE INHALATION GROUND PLANE FOOD H-3 6.47E+02 0.00E+00 2.38E+03 C-14 2.65E+04 0.00E+00 2.34E+09 NA-24 1.06E+04 1.99E+07 1.56E+07 P-32 2.03E+06 0.00E+00 1.60E+11 CR-51 1.28E+04 7.85E+06 4.70E+06 MN-54 1.00E+06 1.29E+09 3.90E+07 MN-56 7.17E+04 1.52E+06 2.84E+00 FE-55 8.69E+04 0.00E+00 1.35E+08 FE-59 1.02E+06 4.56E+08 3.92E+08 CO-58 7.77E+05 6.18E+08 6.05E+07 CO-60 4.51E+06 5.17E+09 2.10E+08 NI-63 3.39E+05 0.00E+00 3.49E+10 NI-65 5.01E+04 4.93E+05 3.02E+01 CU-64 1.50E+04 9.80E+05 3.77E+06 ZN-65 6.47E+05 7.90E+08 1.90E+10 ZN-69 1.32E+04 0.00E+00 2.85E-09 BR-83 3.81E+02 1.01E+04 9.27E-01 BR-84 4.00E+02 3.38E+05 1.32E-22 BR-85 2.04E+01 0.00E+00 0.00E+00 RB-86 1.90E+05 1.47E+07 2.23E+10 RB-88 5.57E+02 5.40E+04 1.88E-44 RB-89 3.21E+02 2.11E+05 3.41E-52 SR-89 2.03E+06 3.56E+04 1.26E+10 SR-90 4.09E+07 0.00E+00 1.22E+11 SR-91 7.34E+04 3.58E+06 3.19E+05 SR-92 1.40E+05 1.23E+06 4.96E+01 Y-90 2.69E+05 7.59E+03 9.42E+05 Y-91 2.45E+06 1.70E+06 5.25E+06 Y-91M 2.79E+03 1.66E+05 2.03E-15 Y-92 1.27E+05 3.06E+05 1.02E+01 Y-93 1.67E+05 3.58E+05 1.69E+04 ZR-95 1.75E+06 3.99E+08 8.26E+05 ZR-97 1.40E+05 4.92E+06 4.44E+04 NB-95 4.79E+05 2.29E+08 2.06E+08 MO-99 1.35E+05 6.60E+06 3.10E+08 TC-99M 2.03E+03 3.01E+05 1.64E+04 TC-101 8.44E+02 3.23E+04 4.88E-57 RU-103 5.52E+05 1.80E+08 1.05E+05 RU-105 4.84E+04 1.03E+06 3.18E+00 RU-106 1.16E+07 3.59E+08 1.45E+06 AG-110M 3.67E+06 3.65E+09 1.46E+10 GRAND GULF, UNIT 1 2.0-11 Revision 43

TABLE 2.2-1a (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.4 and SECTION 2.2.1.b, (P )

i Page 2 of 2 AGE GROUP (INFANT) ( N.A. ) (INFANT)

ISOTOPE INHALATION GROUND PLANE FOOD TE-125M 4.47E+05 3.01E+06 1.51E+08 TE-127 2.44E+04 4.70E+03 1.35E+05 TE-127M 1.31E+06 1.40E+05 1.04E+09 TE-129 2.63E+04 4.41E+04 1.81E-07 TE-129M 1.68E+06 3.30E+07 1.39E+09 TE-131 8.22E+03 4.93E+07 1.41E-30 TE-131M 1.99E+05 1.35E+07 2.29E+07 TE-132 3.40E+05 7.09E+06 6.51E+07 I-130 1.60E+06 9.55E+06 8.71E+08 I-131 1.48E+07 2.98E+07 1.05E+12 I-132 1.69E+05 2.09E+06 1.36E+02 I-133 3.56E+06 4.26E+06 9.59E+09 I-134 4.45E+04 7.57E+05 7.87E-10 I-135 6.96E+05 4.21E+06 2.01E+07 CS-134 7.03E+05 3.28E+09 6.80E+10 CS-136 1.35E+05 2.44E+08 5.81E+09 CS-137 6.12E+05 1.34E+09 6.02E+10 CS-138 8.76E+02 5.86E+05 2.09E-22 BA-139 5.10E+04 1.70E+05 2.71E-05 BA-140 1.60E+06 3.35E+07 2.41E+08 BA-141 4.75E+03 6.79E+04 5.08E-44 BA-142 1.55E+03 7.23E+04 1.67E-79 LA-140 1.68E+05 3.12E+07 1.88E+05 LA-142 5.95E+04 1.30E+06 1.08E-05 CE-141 5.17E+05 2.20E+07 1.37E+07 CE-143 1.16E+05 3.75E+06 1.53E+06 CE-144 9.84E+06 6.77E+07 1.33E+08 PR-143 4.33E+05 0.00E+00 7.84E+05 PR-144 4.28E+03 3.02E+03 1.13E-48 ND-147 3.22E+05 1.44E+07 5.73E+05 W-187 3.96E+04 3.90E+06 2.48E+06 NP-239 5.95E+04 2.83E+06 9.42E+04 3

Units: Inhalation2and all tritium pathways - mrem/yr per µCi/m Others - m . mrem/yr per µCi/sec Values based on standard NUREG-0133, Section 5.2.1 assumptions unless otherwise indicated.

GRAND GULF, UNIT 1 2.0-12 Revision 43

TABLE 2.2-1b PATHWAY DOSE FACTORS FOR LCO 6.11.4 AND SECTION 2.2.1.b, (Pi)

Page 1 of 2 AGE GROUP ( CHILD ) ( N.A. ) ( CHILD )*

ISOTOPE INHALATION GROUND PLANE GRS/ANL/MEAT H-3 1.13E+03 0.00E+00 1.83E+02 C-14 3.59E+04 0.00E+00 2.99E+08 NA-24 1.61E+04 1.98E+07 1.35E-03 P-32 2.61E+06 0.00E+00 5.78E+09 CR-51 1.70E+04 7.85E+06 3.64E+05 MN-54 1.58E+06 1.29E+09 6.25E+06 MN-56 1.23E+05 1.52E+06 1.90E-51 FE-55 1.11E+05 0.00E+00 3.57E+08 FE-59 1.27E+06 4.56E+08 4.94E+08 C0-58 1.11E+06 6.18E+08 7.49E+07 C0-60 7.07E+06 5.17E+09 2.99E+08 NI-63 8.21E+05 0.00E+00 2.27E+10 NI-65 8.40E+04 4.93E+05 3.17E-51 CU-64 3.67E+04 9.80E+05 1.09E-05 ZN-65 9.95E+05 7.90E+08 7.80E+08 ZN-69 1.02E+04 0.00E+00 0.00E+00 BR-83 4.74E+02 1.01E+04 7.43E-57 BR-84 5.48E+02 3.38E+05 0.00E+00 BR-85 2.53E+01 0.00E+00 0.00E+00 RB-86 1.98E+05 1.47E+07 4.54E+08 RB-88 5.62E+02 5.40E+04 0.00E+00 RB-89 3.45E+02 2.11E+05 0.00E+00 SR-89 2.16E+06 3.56E+04 3.76E+08 SR-90 1.01E+08 0.00E+00 8.11E+09 SR-91 1.74E+05 3.58E+06 4.13E-10 SR-92 2.42E+05 1.23E+06 2.72E-48 Y-90 2.68E+05 7.59E+03 3.81E+02 Y-91M 2.81E+03 1.66E+05 0.00E+00 Y-91 2.63E+06 1.70E+06 1.87E+08 Y-92 2.39E+05 3.06E+05 5.43E-35 Y-93 3.89E+05 3.58E+05 1.21E-07 ZR-95 2.23E+06 3.99E+08 4.76E+08 ZR-97 3.51E+05 4.92E+06 5.47E-01 NB-95 6.14E+05 2.29E+08 1.74E+09 MO-99 1.35E+05 6.60E+06 1.92E+05 TC-99M 4.81E+03 3.01E+05 5.39E-18 TC-101 5.85E+02 3.23E+04 0.00E+00 RU-103 6.62E+05 1.80E+08 3.13E+09 RU-105 9.95E+04 1.03E+06 4.59E-25 RU-106 1.43E+07 3.59E+08 5.38E+10 AG-110M 5.48E+06 3.65E+09 5.26E+08 GRAND GULF, UNIT 1 2.0-13 Revision 43

TABLE 2.2-1b (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.4 AND SECTION 2.2.1.b, (Pi)

Page 2 of 2 AGE GROUP ( CHILD ) ( N.A. ) ( CHILD )*

ISOTOPE INHALATION GROUND PLANE GRS/ANL/MEAT TE-125M 4.77E+05 3.01E+06 4.44E+08 TE-127M 1.48E+06 1.39E+05 3.95E+09 TE-127 5.62E+04 4.70E+03 1.25E-08 TE-129M 1.76E+06 3.30E+07 4.09E+09 TE-129 2.55E+04 4.41E+04 0.00E+00 TE-131M 3.08E+05 1.35E+10 7.66E+03 TE-131 2.05E+03 4.93E+07 0.00E+00 TE-132 3.77E+05 7.09E+06 7.27E+06 I-130 1.85E+06 9.55E+06 5.27E-04 I-131 1.62E+07 2.98E+07 4.29E+09 I-132 1.94E+05 2.09E+06 1.90E-57 I-133 3.85E+06 4.26E+06 1.02E+05 I-134 5.07E+04 7.57E+05 0.00E+00 I-135 7.92E+05 4.21E+06 8.10E-15 CS-134 1.01E+06 3.28E+09 1.18E+09 CS-136 1.71E+05 2.44E+08 3.45E+07 CS-137 9.07E+05 1.34E+09 1.04E+09 CS-138 8.40E+02 5.86E+05 0.00E+00 BA-139 5.77E+04 1.70E+05 0.00E+00 BA-140 1.74E+06 3.35E+07 3.42E+07 BA-141 2.92E+03 6.79E+04 0.00E+00 BA-142 1.64E+03 7.23E+04 0.00E+00 LA-140 2.26E+05 3.12E+07 4.28E+02 LA-142 7.59E+04 1.30E+06 0.00E+00 CE-141 5.44E+05 2.20E+07 1.08E+07 CE-143 1.27E+05 3.75E+06 1.96E+02 CE-144 1.20E+07 6.77E+07 1.48E+08 PR-143 4.33E+05 0.00E+00 2.82E+07 PR-144 1.57E+03 3.02E+03 0.00E+00 ND-147 3.28E+05 1.44E+07 1.17E+07 W-187 9.10E+04 3.90E+06 2.18E+00 NP-239 6.40E+04 2.83E+06 1.74E+03 Units: Inhalation and all tritium pathways - mrem/yr per µCi/m3 Others - m2 . mrem/yr per µCi/sec Values based on standard NUREG-0133, Section 5.2.1 assumptions unless otherwise inidated.

Meat consumption assumed 75 percent beef and 25 percent mutton.

GRAND GULF, UNIT 1 2.0-14 Revision 43

TABLE 2.2-2a PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 1 of 8 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 3 INFANT Pathway: 0 Ground Plane Deposition (GPD)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 C-14 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 NA-24 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.39e+07 1.20e+07 P-32 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 CR-51 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.50e+06 4.65e+06 MN-54 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.62e+09 1.38e+09 MN-56 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.07e+06 9.03e+05 FE-55 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 FE-59 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.20e+08 2.73e+08 CO-58 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.45e+08 3.80e+08 CO-60 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.53e+10 2.15e+10 NI-63 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 NI-65 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.45e+05 2.97e+05 CU-64 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.86e+05 6.05e+05 ZN-65 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.57e+08 7.46e+08 ZN-69 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BR-83 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.08e+03 4.87e+03 BR-84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.37e+05 2.03e+05 BR-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RB-86 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.03e+07 8.98e+06 RB-88 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.78e+04 3.31e+04 RB-89 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.48e+05 1.23e+05 SR-89 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.51e+04 2.16e+04 SR-90 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 SR-91 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.51e+06 2.15e+06 SR-92 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.62e+05 7.76e+05 Y-90 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.31e+03 4.50e+03 Y-91 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.21e+06 1.07e+06 Y-91M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.16e+05 1.00e+05 Y-92 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.14e+05 1.80e+05 Y-93 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.50e+05 1.83e+05 ZR-95 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.85e+08 2.45e+08 ZR-97 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.44e+06 2.96e+06 NB-95 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.61e+08 1.37e+08 MO-99 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.62e+06 3.99e+06 TC-99M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.11e+05 1.84e+05 TC-101 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.26e+04 2.03e+04 RU-103 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.26e+08 1.08e+08 RU-105 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.21e+05 6.36e+05 RU-106 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.04e+08 4.20e+08 AG-110M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.02e+09 3.45e+09 TE-125M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.13e+06 1.56e+06 TE-127 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.29e+03 2.99e+03 TE-127M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.08e+05 9.17e+04 TE-129 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.08e+04 2.61e+04 TE-129M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.31e+07 1.98e+07 TE-131 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.45e+07 2.92e+04 TE-131M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 9.46e+06 8.02e+06 GRAND GULF, UNIT 1 2.0-15 Revision 43

TABLE 2.2-2a (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 2 of 8 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 3 INFANT Pathway: 0 Ground Plane Deposition (GPD)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.97e+06 4.22e+06 I-130 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.68e+06 5.50e+06 I-131 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.09e+07 1.72e+07 I-132 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.47e+06 1.25e+06 I-133 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.98e+06 2.45e+06 I-134 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.30e+05 4.46e+05 I-135 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.95e+06 2.53e+06 CS-134 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.05e+09 6.90e+09 CS-136 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.71e+08 1.51e+08 CS-137 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.20e+10 1.03e+10 CS-138 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.10e+05 3.59e+05 BA-139 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.19e+05 1.06e+05 BA-140 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.35e+07 2.05e+07 BA-141 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.75e+04 4.17e+04 BA-142 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.06e+04 4.44e+04 LA-140 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.18e+07 1.92e+07 LA-142 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 9.12e+05 7.60e+05 CE-141 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.54e+07 1.37e+07 CE-143 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.63e+06 2.31e+06 CE-144 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.05e+07 6.96e+07 PR-143 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 PR-144 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.11e+03 1.84e+03 ND-147 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.01e+07 8.39e+06 W-187 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.73e+06 2.35e+06 NP-239 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.98e+06 1.71e+06 GRAND GULF, UNIT 1 2.0-16 Revision 43

TABLE 2.2-2a (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 3 of 8 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 3 INFANT Pathway: 1 Inhalation (INHL)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 0.00e+00 6.47e+02 6.47e+02 6.47e+02 6.47e+02 6.47e+02 0.00e+00 6.47e+02 C-14 2.65e+04 5.31e+03 5.31e+03 5.31e+03 5.31e+03 5.31e+03 0.00e+00 5.31e+03 NA-24 1.06e+04 1.06e+04 1.06e+04 1.06e+04 1.06e+04 1.06e+04 0.00e+00 1.06e+04 P-32 2.03e+06 1.12e+05 0.00e+00 0.00e+00 0.00e+00 1.61e+04 0.00e+00 7.74e+04 CR-51 0.00e+00 0.00e+00 5.75e+01 1.32e+01 1.28e+04 3.57e+02 0.00e+00 8.95e+01 MN-54 0.00e+00 2.53e+04 0.00e+00 4.98e+03 1.00e+06 7.06e+03 0.00e+00 4.98e+03 MN-56 0.00e+00 1.54e+00 0.00e+00 1.10e+00 1.25e+04 7.17e+04 0.00e+00 2.21e-01 FE-55 1.97e+04 1.18e+04 0.00e+00 0.00e+00 8.69e+04 1.10e+03 0.00e+00 3.33e+03 FE-59 1.36e+04 2.35e+04 0.00e+00 0.00e+00 1.02e+06 2.48e+04 0.00e+00 9.48e+03 CO-58 0.00e+00 1.22e+03 0.00e+00 0.00e+00 7.77e+05 1.11e+04 0.00e+00 1.82e+03 CO-60 0.00e+00 8.02e+03 0.00e+00 0.00e+00 4.51e+06 3.19e+04 0.00e+00 1.18e+04 NI-63 3.39e+05 2.04e+04 0.00e+00 0.00e+00 2.09e+05 2.42e+03 0.00e+00 1.16e+04 NI-65 2.39e+00 2.84e-01 0.00e+00 0.00e+00 8.12e+03 5.01e+04 0.00e+00 1.23e-01 CU-64 0.00e+00 1.88e+00 0.00e+00 3.98e+00 9.30e+03 1.50e+04 0.00e+00 7.74e-01 ZN-65 1.93e+04 6.26e+04 0.00e+00 3.25e+04 6.47e+05 5.14e+04 0.00e+00 3.11e+04 ZN-69 5.39e-02 9.67e-02 0.00e+00 4.02e-02 1.47e+03 1.32e+04 0.00e+00 7.18e-03 BR-83 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.81e+02 BR-84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.00e+02 BR-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.04e+01 RB-86 0.00e+00 1.90e+05 0.00e+00 0.00e+00 0.00e+00 3.04e+03 0.00e+00 8.82e+04 RB-88 0.00e+00 5.57e+02 0.00e+00 0.00e+00 0.00e+00 3.39e+02 0.00e+00 2.87e+02 RB-89 0.00e+00 3.21e+02 0.00e+00 0.00e+00 0.00e+00 6.82e+01 0.00e+00 2.06e+02 SR-89 3.98e+05 0.00e+00 0.00e+00 0.00e+00 2.03e+06 6.40e+04 0.00e+00 1.14e+04 SR-90 4.09e+07 0.00e+00 0.00e+00 0.00e+00 1.12e+07 1.31e+05 0.00e+00 2.59e+06 SR-91 9.56e+01 0.00e+00 0.00e+00 0.00e+00 5.26e+04 7.34e+04 0.00e+00 3.46e+00 SR-92 1.05e+01 0.00e+00 0.00e+00 0.00e+00 2.38e+04 1.40e+05 0.00e+00 3.91e-01 Y-90 3.29e+03 0.00e+00 0.00e+00 0.00e+00 2.69e+05 1.04e+05 0.00e+00 8.82e+01 Y-91 5.88e+05 0.00e+00 0.00e+00 0.00e+00 2.45e+06 7.03e+04 0.00e+00 1.57e+04 Y-91M 4.07e-01 0.00e+00 0.00e+00 0.00e+00 2.79e+03 2.35e+03 0.00e+00 1.39e-02 Y-92 1.64e+01 0.00e+00 0.00e+00 0.00e+00 2.45e+04 1.27e+05 0.00e+00 4.61e-01 Y-93 1.50e+02 0.00e+00 0.00e+00 0.00e+00 7.64e+04 1.67e+05 0.00e+00 4.07e+00 ZR-95 1.15e+05 2.79e+04 0.00e+00 3.11e+04 1.75e+06 2.17e+04 0.00e+00 2.03e+04 ZR-97 1.50e+02 2.56e+01 0.00e+00 2.59e+01 1.10e+05 1.40e+05 0.00e+00 1.17e+01 NB-95 1.57e+04 6.43e+03 0.00e+00 4.72e+03 4.79e+05 1.27e+04 0.00e+00 3.78e+03 MO-99 0.00e+00 1.65e+02 0.00e+00 2.65e+02 1.35e+05 4.87e+04 0.00e+00 3.23e+01 TC-99M 1.40e-03 2.88e-03 0.00e+00 3.11e-02 8.11e+02 2.03e+03 0.00e+00 3.72e-02 TC-101 6.51e-05 8.23e-05 0.00e+00 9.79e-04 5.84e+02 8.44e+02 0.00e+00 8.12e-04 RU-103 2.02e+03 0.00e+00 0.00e+00 4.24e+03 5.52e+05 1.61e+04 0.00e+00 6.79e+02 RU-105 1.22e+00 0.00e+00 0.00e+00 8.99e-01 1.57e+04 4.84e+04 0.00e+00 4.10e-01 RU-106 8.68e+04 0.00e+00 0.00e+00 1.07e+05 1.16e+07 1.64e+05 0.00e+00 1.09e+04 AG-110M 9.98e+03 7.22e+03 0.00e+00 1.09e+04 3.67e+06 3.30e+04 0.00e+00 5.00e+03 TE-125M 4.76e+03 1.99e+03 1.62e+03 0.00e+00 4.47e+05 1.29e+04 0.00e+00 6.58e+02 TE-127 2.23e+00 9.53e-01 1.85e+00 4.86e+00 1.04e+04 2.44e+04 0.00e+00 4.89e-01 TE-127M 1.67e+04 6.90e+03 4.87e+03 3.75e+04 1.31e+06 2.73e+04 0.00e+00 2.07e+03 TE-129 7.88e-02 3.47e-02 6.75e-02 1.75e-01 3.00e+03 2.63e+04 0.00e+00 1.88e-02 TE-129M 1.41e+04 6.09e+03 5.47e+03 3.18e+04 1.68e+06 6.90e+04 0.00e+00 2.23e+03 TE-131 1.74e-02 8.22e-03 1.58e-02 3.99e-02 2.06e+03 8.22e+03 0.00e+00 5.00e-03 TE-131M 1.07e+02 5.50e+01 8.93e+01 2.65e+02 1.99e+05 1.19e+05 0.00e+00 3.63e+01 GRAND GULF, UNIT 1 2.0-16a Revision 43

TABLE 2.2-2a (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 4 of 8 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 3 INFANT Pathway: 1 Inhalation (INHL)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 3.72e+02 2.37e+02 2.79e+02 1.04e+03 3.40e+05 4.41e+04 0.00e+00 1.76e+02 I-130 6.36e+03 1.39e+04 1.60e+06 1.53e+04 0.00e+00 1.99e+03 0.00e+00 5.57e+03 I-131 3.79e+04 4.44e+04 1.48e+07 5.18e+04 0.00e+00 1.06e+03 0.00e+00 1.96e+04 I-132 1.69e+03 3.54e+03 1.69e+05 3.95e+03 0.00e+00 1.90e+03 0.00e+00 1.26e+03 I-133 1.32e+04 1.92e+04 3.56e+06 2.24e+04 0.00e+00 2.16e+03 0.00e+00 5.60e+03 I-134 9.21e+02 1.88e+03 4.45e+04 2.09e+03 0.00e+00 1.29e+03 0.00e+00 6.65e+02 I-135 3.86e+03 7.60e+03 6.96e+05 8.47e+03 0.00e+00 1.83e+03 0.00e+00 2.77e+03 CS-134 3.96e+05 7.03e+05 0.00e+00 1.90e+05 7.97e+04 1.33e+03 0.00e+00 7.45e+04 CS-136 4.83e+04 1.35e+05 0.00e+00 5.64e+04 1.18e+04 1.43e+03 0.00e+00 5.29e+04 CS-137 5.49e+05 6.12e+05 0.00e+00 1.72e+05 7.13e+04 1.33e+03 0.00e+00 4.55e+04 CS-138 5.05e+02 7.81e+02 0.00e+00 4.10e+02 6.54e+01 8.76e+02 0.00e+00 3.98e+02 BA-139 1.48e+00 9.84e-04 0.00e+00 5.92e-04 5.95e+03 5.10e+04 0.00e+00 4.30e-02 BA-140 5.60e+04 5.60e+01 0.00e+00 1.34e+01 1.60e+06 3.84e+04 0.00e+00 2.90e+03 BA-141 1.57e-01 1.08e-04 0.00e+00 6.50e-05 2.97e+03 4.75e+03 0.00e+00 4.97e-03 BA-142 3.98e-02 3.30e-05 0.00e+00 1.90e-05 1.55e+03 6.93e+02 0.00e+00 1.96e-03 LA-140 5.05e+02 2.00e+02 0.00e+00 0.00e+00 1.68e+05 8.48e+04 0.00e+00 5.15e+01 LA-142 1.03e+00 3.77e-01 0.00e+00 0.00e+00 8.22e+03 5.95e+04 0.00e+00 9.04e-02 CE-141 2.77e+04 1.67e+04 0.00e+00 5.25e+03 5.17e+05 2.16e+04 0.00e+00 1.99e+03 CE-143 2.93e+02 1.93e+02 0.00e+00 5.64e+01 1.16e+05 4.97e+04 0.00e+00 2.21e+01 CE-144 3.19e+06 1.21e+06 0.00e+00 5.38e+05 9.84e+06 1.48e+05 0.00e+00 1.76e+05 PR-143 1.40e+04 5.24e+03 0.00e+00 1.97e+03 4.33e+05 3.72e+04 0.00e+00 6.99e+02 PR-144 4.79e-02 1.85e-02 0.00e+00 6.72e-03 1.61e+03 4.28e+03 0.00e+00 2.41e-03 ND-147 7.94e+03 8.13e+03 0.00e+00 3.15e+03 3.22e+05 3.12e+04 0.00e+00 5.00e+02 W-187 1.30e+01 9.02e+00 0.00e+00 0.00e+00 3.96e+04 3.56e+04 0.00e+00 3.12e+00 NP-239 3.71e+02 3.32e+01 0.00e+00 6.62e+01 5.95e+04 2.49e+04 0.00e+00 1.88e+01 GRAND GULF, UNIT 1 2.0-16b Revision 43

TABLE 2.2-2a (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 5 of 8 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 3 INFANT Pathway: 2 Vegetation (VEG)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB Not a pathway for this age group GRAND GULF, UNIT 1 2.0-16c Revision 43

TABLE 2.2-2a (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 6 of 8 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 3 INFANT Pathway: 4 Grs/Cow/Meat (CMEAT)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB Not a pathway for this agegroup GRAND GULF, UNIT 1 2.0-16d Revision 43

TABLE 2.2-2a (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 7 of 8 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 3 INFANT Pathway: 5 Grs/Cow/Milk (CMILK)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 0.00e+00 2.38e+03 2.38e+03 2.38e+03 2.38e+03 2.38e+03 0.00e+00 2.38e+03 C-14 2.34e+09 5.00e+08 5.00e+08 5.00e+08 5.00e+08 5.00e+08 0.00e+00 5.00e+08 NA-24 1.56e+07 1.56e+07 1.56e+07 1.56e+07 1.56e+07 1.56e+07 0.00e+00 1.56e+07 P-32 1.60e+11 9.42e+09 0.00e+00 0.00e+00 0.00e+00 2.17e+09 0.00e+00 6.21e+09 CR-51 0.00e+00 0.00e+00 1.05e+05 2.30e+04 2.05e+05 4.70e+06 0.00e+00 1.61e+05 MN-54 0.00e+00 3.90e+07 0.00e+00 8.64e+06 0.00e+00 1.43e+07 0.00e+00 8.84e+06 MN-56 0.00e+00 3.13e-02 0.00e+00 2.69e-02 0.00e+00 2.84e+00 0.00e+00 5.39e-03 FE-55 1.35e+08 8.73e+07 0.00e+00 0.00e+00 4.27e+07 1.11e+07 0.00e+00 2.33e+07 FE-59 2.24e+08 3.92e+08 0.00e+00 0.00e+00 1.16e+08 1.87e+08 0.00e+00 1.54e+08 CO-58 0.00e+00 2.43e+07 0.00e+00 0.00e+00 0.00e+00 6.05e+07 0.00e+00 6.05e+07 CO-60 0.00e+00 8.82e+07 0.00e+00 0.00e+00 0.00e+00 2.10e+08 0.00e+00 2.08e+08 NI-63 3.49e+10 2.16e+09 0.00e+00 0.00e+00 0.00e+00 1.07e+08 0.00e+00 1.21e+09 NI-65 3.51e+00 3.97e-01 0.00e+00 0.00e+00 0.00e+00 3.02e+01 0.00e+00 1.81e-01 CU-64 0.00e+00 1.84e+05 0.00e+00 3.11e+05 0.00e+00 3.77e+06 0.00e+00 8.51e+04 ZN-65 5.55e+09 1.90e+10 0.00e+00 9.23e+09 0.00e+00 1.61e+10 0.00e+00 8.78e+09 ZN-69 1.94e-11 3.49e-11 0.00e+00 1.45e-11 0.00e+00 2.85e-09 0.00e+00 2.60e-12 BR-83 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 9.27e-01 BR-84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.32e-22 BR-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RB-86 0.00e+00 2.23e+10 0.00e+00 0.00e+00 0.00e+00 5.69e+08 0.00e+00 1.10e+10 RB-88 0.00e+00 1.88e-44 0.00e+00 0.00e+00 0.00e+00 1.83e-44 0.00e+00 1.03e-44 RB-89 0.00e+00 3.41e-52 0.00e+00 0.00e+00 0.00e+00 1.16e-52 0.00e+00 2.35e-52 SR-89 1.26e+10 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.59e+08 0.00e+00 3.61e+08 SR-90 1.22e+11 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.52e+09 0.00e+00 3.10e+10 SR-91 2.70e+05 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.19e+05 0.00e+00 9.76e+03 SR-92 4.60e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.96e+01 0.00e+00 1.71e-01 Y-90 6.82e+02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 9.42e+05 0.00e+00 1.83e+01 Y-91 7.33e+04 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.25e+06 0.00e+00 1.95e+03 Y-91M 6.09e-19 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.03e-15 0.00e+00 2.08e-20 Y-92 5.37e-04 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.02e+01 0.00e+00 1.51e-05 Y-93 2.14e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.69e+04 0.00e+00 5.83e-02 ZR-95 6.81e+03 1.66e+03 0.00e+00 1.79e+03 0.00e+00 8.26e+05 0.00e+00 1.18e+03 ZR-97 4.05e+00 6.96e-01 0.00e+00 7.01e-01 0.00e+00 4.44e+04 0.00e+00 3.18e-01 NB-95 5.93e+05 2.44e+05 0.00e+00 1.75e+05 0.00e+00 2.06e+08 0.00e+00 1.41e+05 MO-99 0.00e+00 2.08e+08 0.00e+00 3.10e+08 0.00e+00 6.84e+07 0.00e+00 4.05e+07 TC-99M 2.74e+01 5.65e+01 0.00e+00 6.08e+02 2.95e+01 1.64e+04 0.00e+00 7.28e+02 TC-101 2.28e-59 2.87e-59 0.00e+00 3.42e-58 1.57e-59 4.88e-57 0.00e+00 2.84e-58 RU-103 8.67e+03 0.00e+00 0.00e+00 1.80e+04 0.00e+00 1.05e+05 0.00e+00 2.90e+03 RU-105 8.00e-03 0.00e+00 0.00e+00 5.88e-02 0.00e+00 3.18e+00 0.00e+00 2.69e-03 RU-106 1.90e+05 0.00e+00 0.00e+00 2.25e+05 0.00e+00 1.45e+06 0.00e+00 2.38e+04 AG-110M 3.86e+08 2.82e+08 0.00e+00 4.03e+08 0.00e+00 1.46e+10 0.00e+00 1.86e+08 TE-125M 1.51e+08 5.04e+07 5.08e+07 0.00e+00 0.00e+00 7.19e+07 0.00e+00 2.04e+07 TE-127 6.45e+03 2.16e+03 5.25e+03 1.57e+04 0.00e+00 1.35e+05 0.00e+00 1.39e+03 TE-127M 4.21e+08 1.40e+08 1.22e+08 1.04e+09 0.00e+00 1.70e+08 0.00e+00 5.10e+07 TE-129 2.27e-09 7.81e-10 1.90e-09 5.64e-09 0.00e+00 1.81e-07 0.00e+00 5.29e-10 TE-129M 5.57e+08 1.91e+08 2.14e+08 1.39e+09 0.00e+00 3.33e+08 0.00e+00 8.58e+07 TE-131 3.49e-32 1.29e-32 3.11e-32 8.91e-32 0.00e+00 1.41e-30 0.00e+00 9.79e-33 TE-131M 3.38e+06 1.36e+06 2.75e+06 9.35e+06 0.00e+00 2.29e+07 0.00e+00 1.12e+06 GRAND GULF, UNIT 1 2.0-16e Revision 43

TABLE 2.2-2a (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 8 of 8 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 3 INFANT Pathway: 5 Grs/Cow/Milk (CMILK)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 2.10e+07 1.04e+07 1.54e+07 6.51e+07 0.00e+00 3.85e+07 0.00e+00 9.71e+06 I-130 3.53e+06 7.77e+06 8.71e+08 8.53e+06 0.00e+00 1.67e+06 0.00e+00 3.12e+06 I-131 2.72e+09 3.20e+09 1.05e+12 3.74e+09 0.00e+00 1.14e+08 0.00e+00 1.41e+09 I-132 1.43e+00 2.91e+00 1.36e+02 3.25e+00 0.00e+00 2.36e+00 0.00e+00 1.04e+00 I-133 3.62e+07 5.28e+07 9.59e+09 6.20e+07 0.00e+00 8.93e+06 0.00e+00 1.55e+07 I-134 1.65e-11 3.37e-11 7.87e-10 3.77e-11 0.00e+00 3.49e-11 0.00e+00 1.20e-11 I-135 1.13e+05 2.25e+05 2.01e+07 2.50e+05 0.00e+00 8.13e+04 0.00e+00 8.19e+04 CS-134 3.65e+10 6.80e+10 0.00e+00 1.75e+10 7.18e+09 1.85e+08 0.00e+00 6.87e+09 CS-136 1.98e+09 5.81e+09 0.00e+00 2.32e+09 4.73e+08 8.82e+07 0.00e+00 2.17e+09 CS-137 5.15e+10 6.02e+10 0.00e+00 1.62e+10 6.55e+09 1.88e+08 0.00e+00 4.27e+09 CS-138 8.06e-23 1.31e-22 0.00e+00 6.53e-23 1.02e-23 2.09e-22 0.00e+00 6.35e-23 BA-139 4.29e-07 2.84e-10 0.00e+00 1.71e-10 1.72e-10 2.71e-05 0.00e+00 1.24e-08 BA-140 2.41e+08 2.41e+05 0.00e+00 5.72e+04 1.48e+05 5.92e+07 0.00e+00 1.24e+07 BA-141 4.16e-45 2.85e-48 0.00e+00 1.71e-48 1.73e-48 5.08e-44 0.00e+00 1.31e-46 BA-142 4.05e-80 3.37e-83 0.00e+00 1.94e-83 2.04e-83 1.67e-79 0.00e+00 1.99e-81 LA-140 4.06e+01 1.60e+01 0.00e+00 0.00e+00 0.00e+00 1.88e+05 0.00e+00 4.12e+00 LA-142 1.73e-10 6.35e-11 0.00e+00 0.00e+00 0.00e+00 1.08e-05 0.00e+00 1.52e-11 CE-141 4.34e+04 2.64e+04 0.00e+00 8.15e+03 0.00e+00 1.37e+07 0.00e+00 3.11e+03 CE-143 3.96e+02 2.63e+05 0.00e+00 7.65e+01 0.00e+00 1.53e+06 0.00e+00 3.00e+01 CE-144 2.33e+06 9.52e+05 0.00e+00 3.85e+05 0.00e+00 1.33e+08 0.00e+00 1.30e+05 PR-143 1.49e+03 5.56e+02 0.00e+00 2.07e+02 0.00e+00 7.84e+05 0.00e+00 7.37e+01 PR-144 6.25e-53 2.42e-53 0.00e+00 8.76e-54 0.00e+00 1.13e-48 0.00e+00 3.15e-54 ND-147 8.81e+02 9.05e+02 0.00e+00 3.49e+02 0.00e+00 5.73e+05 0.00e+00 5.54e+01 W-187 6.08e+04 4.23e+04 0.00e+00 0.00e+00 0.00e+00 2.48e+06 0.00e+00 1.46e+04 NP-239 3.64e+01 3.26e+00 0.00e+00 6.50e+00 0.00e+00 9.42e+04 0.00e+00 1.84e+00 3

Units: Inhalation2and all tritium pathways - mrem/yr per µCi/m Others - m . mrem/yr per µCi/sec Values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise indicated.

GRAND GULF, UNIT 1 2.0-16f Revision 43

TABLE 2.2-2b PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 1 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 2 CHILD Pathway: 0 Ground Plane Deposition (GPD)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 C-14 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 NA-24 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.39e+07 1.20e+07 P-32 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 CR-51 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.50e+06 4.65e+06 MN-54 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.62e+09 1.38e+09 MN-56 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.07e+06 9.03e+05 FE-55 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 FE-59 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.20e+08 2.73e+08 CO-58 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.45e+08 3.80e+08 CO-60 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.53e+10 2.15e+10 NI-63 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 NI-65 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.45e+05 2.97e+05 CU-64 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.86e+05 6.05e+05 ZN-65 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.57e+08 7.46e+08 ZN-69 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BR-83 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.08e+03 4.87e+03 BR-84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.37e+05 2.03e+05 BR-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RB-86 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.03e+07 8.98e+06 RB-88 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.78e+04 3.31e+04 RB-89 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.48e+05 1.23e+05 SR-89 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.51e+04 2.16e+04 SR-90 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 SR-91 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.51e+06 2.15e+06 SR-92 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.62e+05 7.76e+05 Y-90 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.31e+03 4.50e+03 Y-91 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.21e+06 1.07e+06 Y-91M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.16e+05 1.00e+05 Y-92 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.14e+05 1.80e+05 Y-93 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.50e+05 1.83e+05 ZR-95 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.85e+08 2.45e+08 ZR-97 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.44e+06 2.96e+06 NB-95 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.61e+08 1.37e+08 MO-99 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.62e+06 3.99e+06 TC-99M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.11e+05 1.84e+05 TC-101 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.26e+04 2.03e+04 RU-103 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.26e+08 1.08e+08 RU-105 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.21e+05 6.36e+05 RU-106 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.04e+08 4.20e+08 AG-110M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.02e+09 3.45e+09 TE-125M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.13e+06 1.56e+06 TE-127 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.29e+03 2.99e+03 TE-127M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.08e+05 9.17e+04 TE-129 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.08e+04 2.61e+04 TE-129M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.31e+07 1.98e+07 TE-131 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.45e+07 2.92e+04 TE-131M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 9.46e+06 8.02e+06 GRAND GULF, UNIT 1 2.0-17 Revision 43

TABLE 2.2-2b (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 2 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 2 CHILD Pathway: 0 Ground Plane Deposition (GPD)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.97e+06 4.22e+06 I-130 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.68e+06 5.50e+06 I-131 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.09e+07 1.72e+07 I-132 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.47e+06 1.25e+06 I-133 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.98e+06 2.45e+06 I-134 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.30e+05 4.46e+05 I-135 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.95e+06 2.53e+06 CS-134 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.05e+09 6.90e+09 CS-136 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.71e+08 1.51e+08 CS-137 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.20e+10 1.03e+10 CS-138 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.10e+05 3.59e+05 BA-139 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.19e+05 1.06e+05 BA-140 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.35e+07 2.05e+07 BA-141 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.75e+04 4.17e+04 BA-142 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.06e+04 4.44e+04 LA-140 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.18e+07 1.92e+07 LA-142 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 9.12e+05 7.60e+05 CE-141 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.54e+07 1.37e+07 CE-143 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.63e+06 2.31e+06 CE-144 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.05e+07 6.96e+07 PR-143 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 PR-144 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.11e+03 1.84e+03 ND-147 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.01e+07 8.39e+06 W-187 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.73e+06 2.35e+06 NP-239 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.98e+06 1.71e+06 GRAND GULF, UNIT 1 2.0-18 Revision 43

TABLE 2.2-2b (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 3 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 2 CHILD Pathway: 1 Inhalation (INHL)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 0.00e+00 1.13e+03 1.13e+03 1.13e+03 1.13e+03 1.13e+03 0.00e+00 1.13e+03 C-14 3.59e+04 6.73e+03 6.73e+03 6.73e+03 6.73e+03 6.73e+03 0.00e+00 6.73e+03 NA-24 1.61e+04 1.61e+04 1.61e+04 1.61e+04 1.61e+04 1.61e+04 0.00e+00 1.61e+04 P-32 2.61e+06 1.14e+05 0.00e+00 0.00e+00 0.00e+00 4.22e+04 0.00e+00 9.88e+04 CR-51 0.00e+00 0.00e+00 8.55e+01 2.43e+01 1.70e+04 1.08e+03 0.00e+00 1.54e+02 MN-54 0.00e+00 4.29e+04 0.00e+00 1.00e+04 1.58e+06 2.29e+04 0.00e+00 9.51e+03 MN-56 0.00e+00 1.66e+00 0.00e+00 1.67e+00 1.31e+04 1.23e+05 0.00e+00 3.12e-01 FE-55 4.74e+04 2.52e+04 0.00e+00 0.00e+00 1.11e+05 2.87e+03 0.00e+00 7.77e+03 FE-59 2.07e+04 3.35e+04 0.00e+00 0.00e+00 1.27e+06 7.07e+04 0.00e+00 1.67e+04 CO-58 0.00e+00 1.77e+03 0.00e+00 0.00e+00 1.11e+06 3.44e+04 0.00e+00 3.16e+03 CO-60 0.00e+00 1.31e+04 0.00e+00 0.00e+00 7.07e+06 9.62e+04 0.00e+00 2.26e+04 NI-63 8.21e+05 4.63e+04 0.00e+00 0.00e+00 2.75e+05 6.33e+03 0.00e+00 2.80e+04 NI-65 2.99e+00 2.96e-01 0.00e+00 0.00e+00 8.18e+03 8.40e+04 0.00e+00 1.64e-01 CU-64 0.00e+00 1.99e+00 0.00e+00 6.03e+00 9.58e+03 3.67e+04 0.00e+00 1.07e+00 ZN-65 4.26e+04 1.13e+05 0.00e+00 7.14e+04 9.95e+05 1.63e+04 0.00e+00 7.03e+04 ZN-69 6.70e-02 9.66e-02 0.00e+00 5.85e-02 1.42e+03 1.02e+04 0.00e+00 8.92e-03 BR-83 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.74e+02 BR-84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.48e+02 BR-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.53e+01 RB-86 0.00e+00 1.98e+05 0.00e+00 0.00e+00 0.00e+00 7.99e+03 0.00e+00 1.14e+05 RB-88 0.00e+00 5.62e+02 0.00e+00 0.00e+00 0.00e+00 1.72e+01 0.00e+00 3.66e+02 RB-89 0.00e+00 3.45e+02 0.00e+00 0.00e+00 0.00e+00 1.89e+00 0.00e+00 2.90e+02 SR-89 5.99e+05 0.00e+00 0.00e+00 0.00e+00 2.16e+06 1.67e+05 0.00e+00 1.72e+04 SR-90 1.01e+08 0.00e+00 0.00e+00 0.00e+00 1.48e+07 3.43e+05 0.00e+00 6.44e+06 SR-91 1.21e+02 0.00e+00 0.00e+00 0.00e+00 5.33e+04 1.74e+05 0.00e+00 4.59e+00 SR-92 1.31e+01 0.00e+00 0.00e+00 0.00e+00 2.40e+04 2.42e+05 0.00e+00 5.25e-01 Y-90 4.11e+03 0.00e+00 0.00e+00 0.00e+00 2.62e+05 2.68e+05 0.00e+00 1.11e+02 Y-91 9.14e+05 0.00e+00 0.00e+00 0.00e+00 2.63e+06 1.84e+05 0.00e+00 2.44e+04 Y-91M 5.07e-01 0.00e+00 0.00e+00 0.00e+00 2.81e+03 1.72e+03 0.00e+00 1.84e-02 Y-92 2.04e+01 0.00e+00 0.00e+00 0.00e+00 2.39e+04 2.39e+05 0.00e+00 5.81e-01 Y-93 1.87e+02 0.00e+00 0.00e+00 0.00e+00 7.44e+04 3.89e+05 0.00e+00 5.11e+00 ZR-95 1.90e+05 4.18e+04 0.00e+00 5.96e+04 2.23e+06 6.11e+04 0.00e+00 3.70e+04 ZR-97 1.88e+02 2.72e+01 0.00e+00 3.89e+01 1.13e+05 3.51e+05 0.00e+00 1.60e+01 NB-95 2.35e+04 9.18e+03 0.00e+00 8.62e+03 6.14e+05 3.70e+04 0.00e+00 6.55e+03 MO-99 0.00e+00 1.72e+02 0.00e+00 3.92e+02 1.35e+05 1.27e+05 0.00e+00 4.25e+01 TC-99M 1.78e-03 3.48e-03 0.00e+00 5.07e-02 9.51e+02 4.81e+03 0.00e+00 5.77e-02 TC-101 8.10e-05 8.51e-05 0.00e+00 1.45e-03 5.85e+02 1.63e+01 0.00e+00 1.08e-03 RU-103 2.79e+03 0.00e+00 0.00e+00 7.03e+03 6.62e+05 4.48e+04 0.00e+00 1.07e+03 RU-105 1.53e+00 0.00e+00 0.00e+00 1.34e+00 1.59e+04 9.95e+04 0.00e+00 5.55e-01 RU-106 1.36e+05 0.00e+00 0.00e+00 1.84e+05 1.43e+07 4.29e+05 0.00e+00 1.69e+04 AG-110M 1.69e+04 1.14e+04 0.00e+00 2.12e+04 5.48e+06 1.00e+05 0.00e+00 9.14e+03 TE-125M 6.73e+03 2.33e+03 1.92e+03 0.00e+00 4.77e+05 3.38e+04 0.00e+00 9.14e+02 TE-127 2.77e+00 9.51e-01 1.96e+00 7.07e+00 1.00e+04 5.62e+04 0.00e+00 6.11e-01 TE-127M 2.49e+04 8.55e+03 6.07e+03 6.36e+04 1.48e+06 7.14e+04 0.00e+00 3.02e+03 TE-129 9.77e-02 3.50e-02 7.14e-02 2.57e-01 2.93e+03 2.55e+04 0.00e+00 2.38e-02 TE-129M 1.92e+04 6.85e+03 6.33e+03 5.03e+04 1.76e+06 1.82e+05 0.00e+00 3.04e+03 TE-131 2.17e-02 8.44e-03 1.70e-02 5.88e-02 2.05e+03 1.33e+03 0.00e+00 6.59e-03 TE-131M 1.34e+02 5.92e+01 9.77e+01 4.00e+02 2.06e+05 3.08e+05 0.00e+00 5.07e+01 GRAND GULF, UNIT 1 2.0-18a Revision 43

TABLE 2.2-2b (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 4 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 2 CHILD Pathway: 1 Inhalation (INHL)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 4.81e+02 2.72e+02 3.18e+02 1.77e+03 3.77e+05 1.38e+05 0.00e+00 2.63e+02 I-130 8.18e+03 1.64e+04 1.85e+06 2.45e+04 0.00e+00 5.11e+03 0.00e+00 8.44e+03 I-131 4.81e+04 4.81e+04 1.62e+07 7.88e+04 0.00e+00 2.84e+03 0.00e+00 2.73e+04 I-132 2.12e+03 4.07e+03 1.94e+05 6.25e+03 0.00e+00 3.20e+03 0.00e+00 1.88e+03 I-133 1.66e+04 2.03e+04 3.85e+06 3.38e+04 0.00e+00 5.48e+03 0.00e+00 7.70e+03 I-134 1.17e+03 2.16e+03 5.07e+04 3.30e+03 0.00e+00 9.55e+02 0.00e+00 9.95e+02 I-135 4.92e+03 8.73e+03 7.92e+05 1.34e+04 0.00e+00 4.44e+03 0.00e+00 4.14e+03 CS-134 6.51e+05 1.01e+06 0.00e+00 3.30e+05 1.21e+05 3.85e+03 0.00e+00 2.25e+05 CS-136 6.51e+04 1.71e+05 0.00e+00 9.55e+04 1.45e+04 4.18e+03 0.00e+00 1.16e+05 CS-137 9.07e+05 8.25e+05 0.00e+00 2.82e+05 1.04e+05 3.62e+03 0.00e+00 1.28e+05 CS-138 6.33e+02 8.40e+02 0.00e+00 6.22e+02 6.81e+01 2.70e+02 0.00e+00 5.55e+02 BA-139 1.84e+00 9.84e-04 0.00e+00 8.62e-04 5.77e+03 5.77e+04 0.00e+00 5.37e-02 BA-140 7.40e+04 6.48e+01 0.00e+00 2.11e+01 1.74e+06 1.02e+05 0.00e+00 4.33e+03 BA-141 1.96e-01 1.09e-04 0.00e+00 9.47e-05 2.92e+03 2.75e+02 0.00e+00 6.36e-03 BA-142 5.00e-02 3.60e-05 0.00e+00 2.91e-05 1.64e+03 2.74e+00 0.00e+00 2.79e-03 LA-140 6.44e+02 2.25e+02 0.00e+00 0.00e+00 1.83e+05 2.26e+05 0.00e+00 7.55e+01 LA-142 1.29e+00 4.11e-01 0.00e+00 0.00e+00 8.70e+03 7.59e+04 0.00e+00 1.29e-01 CE-141 3.92e+04 1.95e+04 0.00e+00 8.55e+03 5.44e+05 5.66e+04 0.00e+00 2.90e+03 CE-143 3.66e+02 1.99e+02 0.00e+00 8.36e+01 1.15e+05 1.27e+05 0.00e+00 2.88e+01 CE-144 6.77e+06 2.12e+06 0.00e+00 1.17e+06 1.20e+07 3.89e+05 0.00e+00 3.62e+05 PR-143 1.85e+04 5.55e+03 0.00e+00 3.00e+03 4.33e+05 9.73e+04 0.00e+00 9.14e+02 PR-144 5.96e-02 1.85e-02 0.00e+00 9.77e-03 1.57e+03 1.97e+02 0.00e+00 3.00e-03 ND-147 1.08e+04 8.73e+03 0.00e+00 4.81e+03 3.28e+05 8.21e+04 0.00e+00 6.81e+02 W-187 1.63e+01 9.66e+00 0.00e+00 0.00e+00 4.11e+04 9.10e+04 0.00e+00 4.33e+00 NP-239 4.66e+02 3.35e+01 0.00e+00 9.73e+01 5.81e+04 6.40e+04 0.00e+00 2.35e+01 GRAND GULF, UNIT 1 2.0-18b Revision 43

TABLE 2.2-2b (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 5 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 2 CHILD Pathway: 2 Vegetation (VEG)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 0.00e+00 4.01e+03 4.01e+03 4.01e+03 4.01e+03 4.01e+03 0.00e+00 4.01e+03 C-14 8.89e+08 1.78e+08 1.78e+08 1.78e+08 1.78e+08 1.78e+08 0.00e+00 1.78e+08 NA-24 3.75e+05 3.75e+05 3.75e+05 3.75e+05 3.75e+05 3.75e+05 0.00e+00 3.75e+05 P-32 3.36e+09 1.57e+08 0.00e+00 0.00e+00 0.00e+00 9.30e+07 0.00e+00 1.30e+08 CR-51 0.00e+00 0.00e+00 6.49e+04 1.77e+04 1.19e+05 6.20e+06 0.00e+00 1.17e+05 MN-54 0.00e+00 6.65e+08 0.00e+00 1.86e+08 0.00e+00 5.58e+08 0.00e+00 1.77e+08 MN-56 0.00e+00 1.87e+01 0.00e+00 2.26e+01 0.00e+00 2.71e+03 0.00e+00 4.22e+00 FE-55 8.01e+08 4.25e+08 0.00e+00 0.00e+00 2.40e+08 7.87e+07 0.00e+00 1.32e+08 FE-59 3.97e+08 6.42e+08 0.00e+00 0.00e+00 1.86e+08 6.69e+08 0.00e+00 3.20e+08 CO-58 0.00e+00 6.45e+07 0.00e+00 0.00e+00 0.00e+00 3.76e+08 0.00e+00 1.98e+08 CO-60 0.00e+00 3.78e+08 0.00e+00 0.00e+00 0.00e+00 2.10e+09 0.00e+00 1.12e+09 NI-63 3.95e+10 2.11e+09 0.00e+00 0.00e+00 0.00e+00 1.42e+08 0.00e+00 1.34e+09 NI-65 1.05e+02 9.89e+00 0.00e+00 0.00e+00 0.00e+00 1.21e+03 0.00e+00 5.77e+00 CU-64 0.00e+00 1.09e+04 0.00e+00 2.64e+04 0.00e+00 5.13e+05 0.00e+00 6.60e+03 ZN-65 8.12e+08 2.16e+09 0.00e+00 1.36e+09 0.00e+00 3.80e+08 0.00e+00 1.35e+09 ZN-69 9.30e-06 1.34e-05 0.00e+00 8.15e-06 0.00e+00 8.47e-04 0.00e+00 1.24e-06 BR-83 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.35e+00 BR-84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.92e-11 BR-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RB-86 0.00e+00 4.52e+08 0.00e+00 0.00e+00 0.00e+00 2.91e+07 0.00e+00 2.78e+08 RB-88 0.00e+00 4.38e-22 0.00e+00 0.00e+00 0.00e+00 2.15e-23 0.00e+00 3.04e-22 RB-89 0.00e+00 4.69e-26 0.00e+00 0.00e+00 0.00e+00 4.09e-28 0.00e+00 4.17e-26 SR-89 3.59e+10 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.39e+09 0.00e+00 1.03e+09 SR-90 1.24e+12 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.68e+10 0.00e+00 3.15e+11 SR-91 5.22e+05 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.15e+06 0.00e+00 1.97e+04 SR-92 7.24e+02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.37e+04 0.00e+00 2.90e+01 Y-90 2.31e+04 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.58e+07 0.00e+00 6.18e+02 Y-91 1.87e+07 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.49e+09 0.00e+00 4.99e+05 Y-91M 9.23e-09 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.81e-05 0.00e+00 3.36e-10 Y-92 1.58e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.57e+04 0.00e+00 4.53e-02 Y-93 2.92e+02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.35e+06 0.00e+00 8.00e+00 ZR-95 3.87e+06 8.50e+05 0.00e+00 1.22e+06 0.00e+00 8.86e+08 0.00e+00 7.56e+05 ZR-97 5.70e+02 8.23e+01 0.00e+00 1.18e+02 0.00e+00 1.25e+07 0.00e+00 4.86e+01 NB-95 4.10e+05 1.60e+05 0.00e+00 1.50e+05 0.00e+00 2.95e+08 0.00e+00 1.14e+05 MO-99 0.00e+00 7.70e+06 0.00e+00 1.65e+07 0.00e+00 6.37e+06 0.00e+00 1.91e+06 TC-99M 4.70e+00 9.22e+00 0.00e+00 1.34e+02 4.68e+00 5.25e+03 0.00e+00 1.53e+02 TC-101 1.35e-30 1.42e-30 0.00e+00 2.41e-29 7.48e-31 4.50e-30 0.00e+00 1.80e-29 RU-103 1.53e+07 0.00e+00 0.00e+00 3.86e+07 0.00e+00 3.96e+08 0.00e+00 5.89e+06 RU-105 9.13e+01 0.00e+00 0.00e+00 8.02e+02 0.00e+00 5.96e+04 0.00e+00 3.31e+01 RU-106 7.45e+08 0.00e+00 0.00e+00 1.01e+09 0.00e+00 1.16e+10 0.00e+00 9.30e+07 AG-110M 3.21e+07 2.17e+07 0.00e+00 4.04e+07 0.00e+00 2.58e+09 0.00e+00 1.74e+07 TE-125M 3.51e+08 9.52e+07 9.86e+07 0.00e+00 0.00e+00 3.39e+08 0.00e+00 4.68e+07 TE-127 9.97e+03 2.69e+03 6.90e+03 2.84e+04 0.00e+00 3.89e+05 0.00e+00 2.14e+03 TE-127M 1.32e+09 3.56e+08 3.16e+08 3.77e+09 0.00e+00 1.07e+09 0.00e+00 1.57e+08 TE-129 1.20e-03 3.36e-04 8.59e-04 3.52e-03 0.00e+00 7.49e-02 0.00e+00 2.86e-04 TE-129M 8.40e+08 2.35e+08 2.71e+08 2.47e+09 0.00e+00 1.03e+09 0.00e+00 1.30e+08 TE-131 2.59e-15 7.90e-16 1.98e-15 7.84e-15 0.00e+00 1.36e-14 0.00e+00 7.71e-16 TE-131M 1.54e+06 5.33e+05 1.10e+06 5.16e+06 0.00e+00 2.16e+07 0.00e+00 5.67e+05 GRAND GULF, UNIT 1 2.0-18c Revision 43

TABLE 2.2-2b (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 6 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 2 CHILD Pathway: 2 Vegetation (VEG)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 6.98e+06 3.09e+06 4.50e+06 2.87e+07 0.00e+00 3.11e+07 0.00e+00 3.73e+06 I-130 6.14e+05 1.24e+06 1.37e+08 1.85e+06 0.00e+00 5.80e+05 0.00e+00 6.39e+05 I-131 1.43e+08 1.44e+08 4.75e+10 2.36e+08 0.00e+00 1.28e+07 0.00e+00 8.17e+07 I-132 9.23e+01 1.70e+02 7.87e+03 2.60e+02 0.00e+00 2.00e+02 0.00e+00 7.80e+01 I-133 3.53e+06 4.36e+06 8.11e+08 7.27e+06 0.00e+00 1.76e+06 0.00e+00 1.65e+06 I-134 1.50e-04 2.78e-04 6.40e-03 4.26e-04 0.00e+00 1.85e-04 0.00e+00 1.28e-04 I-135 6.28e+04 1.13e+05 1.00e+07 1.73e+05 0.00e+00 8.61e+04 0.00e+00 5.34e+04 CS-134 1.60e+10 2.63e+10 0.00e+00 8.16e+09 2.93e+09 1.42e+08 0.00e+00 5.55e+09 CS-136 8.23e+07 2.26e+08 0.00e+00 1.21e+08 1.80e+07 7.95e+06 0.00e+00 1.46e+08 CS-137 2.39e+10 2.29e+10 0.00e+00 7.46e+09 2.69e+09 1.43e+08 0.00e+00 3.38e+09 CS-138 6.44e-11 8.95e-11 0.00e+00 6.30e-11 6.78e-12 4.12e-11 0.00e+00 5.67e-11 BA-139 4.96e-02 2.65e-05 0.00e+00 2.31e-05 1.56e-05 2.86e+00 0.00e+00 1.44e-03 BA-140 2.77e+08 2.43e+05 0.00e+00 7.90e+04 1.45e+05 1.40e+08 0.00e+00 1.62e+07 BA-141 2.04e-21 1.14e-24 0.00e+00 9.90e-25 6.72e-24 1.16e-21 0.00e+00 6.65e-23 BA-142 4.06e-39 2.92e-42 0.00e+00 2.36e-42 1.72e-42 5.29e-41 0.00e+00 2.26e-40 LA-140 3.25e+03 1.14e+03 0.00e+00 0.00e+00 0.00e+00 3.17e+07 0.00e+00 3.83e+02 LA-142 3.39e-04 1.08e-04 0.00e+00 0.00e+00 0.00e+00 2.14e+01 0.00e+00 3.38e-05 CE-141 6.56e+05 3.27e+05 0.00e+00 1.43e+05 0.00e+00 4.08e+08 0.00e+00 4.85e+04 CE-143 1.72e+03 9.30e+05 0.00e+00 3.90e+02 0.00e+00 1.36e+07 0.00e+00 1.35e+02 CE-144 1.27e+08 3.99e+07 0.00e+00 2.21e+07 0.00e+00 1.04e+10 0.00e+00 6.78e+06 PR-143 1.46e+05 4.38e+04 0.00e+00 2.37e+04 0.00e+00 1.57e+08 0.00e+00 7.24e+03 PR-144 5.64e-26 1.74e-26 0.00e+00 9.22e-27 0.00e+00 3.75e-23 0.00e+00 2.84e-27 ND-147 7.14e+04 5.79e+04 0.00e+00 3.17e+04 0.00e+00 9.16e+07 0.00e+00 4.48e+03 W-187 6.43e+04 3.81e+04 0.00e+00 0.00e+00 0.00e+00 5.35e+06 0.00e+00 1.71e+04 NP-239 2.56e+03 1.84e+02 0.00e+00 5.31e+02 0.00e+00 1.36e+07 0.00e+00 1.29e+02 GRAND GULF, UNIT 1 2.0-18d Revision 43

TABLE 2.2-2b (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 7 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 2 CHILD Pathway: 4 Grs/Cow/Meat (CMEAT)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 0.00e+00 2.34e+02 2.34e+02 2.34e+02 2.34e+02 2.34e+02 0.00e+00 2.34e+02 C-14 3.83e+08 7.67e+07 7.67e+07 7.67e+07 7.67e+07 7.67e+07 0.00e+00 7.67e+07 NA-24 1.84e-03 1.84e-03 1.84e-03 1.84e-03 1.84e-03 1.84e-03 0.00e+00 1.84e-03 P-32 7.41e+09 3.47e+08 0.00e+00 0.00e+00 0.00e+00 2.05e+08 0.00e+00 2.86e+08 CR-51 0.00e+00 0.00e+00 4.87e+03 1.33e+03 8.90e+03 4.66e+05 0.00e+00 8.78e+03 MN-54 0.00e+00 8.01e+06 0.00e+00 2.25e+06 0.00e+00 6.72e+06 0.00e+00 2.13e+06 MN-56 0.00e+00 1.56e-53 0.00e+00 1.89e-53 0.00e+00 2.26e-51 0.00e+00 3.52e-54 FE-55 4.57e+08 2.43e+08 0.00e+00 0.00e+00 1.37e+08 4.49e+07 0.00e+00 7.51e+07 FE-59 3.76e+08 6.08e+08 0.00e+00 0.00e+00 1.76e+08 6.34e+08 0.00e+00 3.03e+08 CO-58 0.00e+00 1.64e+07 0.00e+00 0.00e+00 0.00e+00 9.59e+07 0.00e+00 5.03e+07 CO-60 0.00e+00 6.93e+07 0.00e+00 0.00e+00 0.00e+00 3.84e+08 0.00e+00 2.04e+08 NI-63 2.91e+10 1.56e+09 0.00e+00 0.00e+00 0.00e+00 1.05e+08 0.00e+00 9.91e+08 NI-65 3.55e-52 3.34e-53 0.00e+00 0.00e+00 0.00e+00 4.10e-51 0.00e+00 1.95e-53 CU-64 0.00e+00 2.77e-07 0.00e+00 6.68e-07 0.00e+00 1.30e-05 0.00e+00 1.67e-07 ZN-65 3.75e+08 1.00e+09 0.00e+00 6.30e+08 0.00e+00 1.76e+08 0.00e+00 6.22e+08 ZN-69 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BR-83 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.89e-57 BR-84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BR-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RB-86 0.00e+00 5.76e+08 0.00e+00 0.00e+00 0.00e+00 3.71e+07 0.00e+00 3.55e+08 RB-88 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RB-89 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 SR-89 4.81e+08 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.86e+07 0.00e+00 1.38e+07 SR-90 1.04e+10 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.40e+08 0.00e+00 2.64e+09 SR-91 2.26e-10 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.99e-10 0.00e+00 8.54e-12 SR-92 1.69e-49 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.19e-48 0.00e+00 6.76e-51 Y-90 1.73e+02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.92e+05 0.00e+00 4.62e+00 Y-91 1.80e+06 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.40e+08 0.00e+00 4.82e+04 Y-91M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Y-92 2.37e-39 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.84e-35 0.00e+00 6.77e-41 Y-93 6.97e-12 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.04e-07 0.00e+00 1.91e-13 ZR-95 2.67e+06 5.86e+05 0.00e+00 8.39e+05 0.00e+00 6.11e+08 0.00e+00 5.22e+05 ZR-97 3.16e-05 4.57e-06 0.00e+00 6.56e-06 0.00e+00 6.93e-01 0.00e+00 2.70e-06 NB-95 3.10e+06 1.21e+06 0.00e+00 1.13e+06 0.00e+00 2.23e+09 0.00e+00 8.61e+05 MO-99 0.00e+00 1.14e+05 0.00e+00 2.44e+05 0.00e+00 9.44e+04 0.00e+00 2.82e+04 TC-99M 6.02e-21 1.18e-20 0.00e+00 1.72e-19 5.99e-21 6.72e-18 0.00e+00 1.96e-19 TC-101 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RU-103 1.55e+08 0.00e+00 0.00e+00 3.90e+08 0.00e+00 4.00e+09 0.00e+00 5.95e+07 RU-105 8.48e-28 0.00e+00 0.00e+00 7.45e-27 0.00e+00 5.53e-25 0.00e+00 3.08e-28 RU-106 4.44e+09 0.00e+00 0.00e+00 5.99e+09 0.00e+00 6.90e+10 0.00e+00 5.54e+08 AG-110M 8.39e+06 5.67e+06 0.00e+00 1.06e+07 0.00e+00 6.74e+08 0.00e+00 4.53e+06 TE-125M 5.70e+08 1.54e+08 1.60e+08 0.00e+00 0.00e+00 5.50e+08 0.00e+00 7.59e+07 TE-127 3.99e-10 1.08e-10 2.76e-10 1.14e-09 0.00e+00 1.56e-08 0.00e+00 8.56e-11 TE-127M 1.78e+09 4.78e+08 4.24e+08 5.06e+09 0.00e+00 1.44e+09 0.00e+00 2.11e+08 TE-129 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 TE-129M 1.79e+09 5.00e+08 5.77e+08 5.25e+09 0.00e+00 2.18e+09 0.00e+00 2.78e+08 TE-131 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 TE-131M 6.97e+02 2.41e+02 4.96e+02 2.33e+03 0.00e+00 9.78e+03 0.00e+00 2.57e+02 GRAND GULF, UNIT 1 2.0-18e Revision 43

TABLE 2.2-2b (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 8 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 2 CHILD Pathway: 4 Grs/Cow/Meat (CMEAT)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 2.09e+06 9.23e+05 1.35e+06 8.57e+06 0.00e+00 9.30e+06 0.00e+00 1.12e+06 I-130 2.92e-06 5.89e-06 6.49e-04 8.81e-06 0.00e+00 2.76e-06 0.00e+00 3.04e-06 I-131 1.65e+07 1.66e+07 5.50e+09 2.73e+07 0.00e+00 1.48e+06 0.00e+00 9.45e+06 I-132 1.05e-58 1.93e-58 8.93e-57 2.95e-58 0.00e+00 2.27e-58 0.00e+00 8.85e-59 I-133 5.64e-01 6.98e-01 1.30e+02 1.16e+00 0.00e+00 2.81e-01 0.00e+00 2.64e-01 I-134 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 I-135 6.86e-17 1.23e-16 1.09e-14 1.89e-16 0.00e+00 9.40e-17 0.00e+00 5.84e-17 CS-134 9.22e+08 1.51e+09 0.00e+00 4.69e+08 1.68e+08 8.16e+06 0.00e+00 3.19e+08 CS-136 1.62e+07 4.45e+07 0.00e+00 2.37e+07 3.54e+06 1.57e+06 0.00e+00 2.88e+07 CS-137 1.33e+09 1.28e+09 0.00e+00 4.16e+08 1.50e+08 7.99e+06 0.00e+00 1.88e+08 CS-138 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BA-139 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BA-140 4.39e+07 3.84e+04 0.00e+00 1.25e+04 2.29e+04 2.22e+07 0.00e+00 2.56e+06 BA-141 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BA-142 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 LA-140 5.66e-02 1.98e-02 0.00e+00 0.00e+00 0.00e+00 5.52e+02 0.00e+00 6.67e-03 LA-142 6.20e-92 1.98e-92 0.00e+00 0.00e+00 0.00e+00 3.92e-87 0.00e+00 6.19e-93 CE-141 2.22e+04 1.11e+04 0.00e+00 4.85e+03 0.00e+00 1.38e+07 0.00e+00 1.64e+03 CE-143 3.14e-02 1.70e+01 0.00e+00 7.14e-03 0.00e+00 2.49e+02 0.00e+00 2.46e-03 CE-144 2.32e+06 7.26e+05 0.00e+00 4.02e+05 0.00e+00 1.89e+08 0.00e+00 1.24e+05 PR-143 3.34e+04 1.00e+04 0.00e+00 5.44e+03 0.00e+00 3.61e+07 0.00e+00 1.66e+03 PR-144 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 ND-147 1.17e+04 9.46e+03 0.00e+00 5.19e+03 0.00e+00 1.50e+07 0.00e+00 7.32e+02 W-187 3.21e-02 1.90e-02 0.00e+00 0.00e+00 0.00e+00 2.67e+00 0.00e+00 8.52e-03 NP-239 4.23e-01 3.04e-02 0.00e+00 8.79e-02 0.00e+00 2.25e+03 0.00e+00 2.14e-02 GRAND GULF, UNIT 1 2.0-18f Revision 43

TABLE 2.2-2b (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 9 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 2 CHILD Pathway: 5 Grs/Cow/Milk (CMILK)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 0.00e+00 1.57e+03 1.57e+03 1.57e+03 1.57e+03 1.57e+03 0.00e+00 1.57e+03 C-14 1.20e+09 2.39e+08 2.39e+08 2.39e+08 2.39e+08 2.39e+08 0.00e+00 2.39e+08 NA-24 8.93e+06 8.93e+06 8.93e+06 8.93e+06 8.93e+06 8.93e+06 0.00e+00 8.93e+06 P-32 7.77e+10 3.64e+09 0.00e+00 0.00e+00 0.00e+00 2.15e+09 0.00e+00 3.00e+09 CR-51 0.00e+00 0.00e+00 5.65e+04 1.54e+04 1.03e+05 5.40e+06 0.00e+00 1.02e+05 MN-54 0.00e+00 2.10e+07 0.00e+00 5.88e+06 0.00e+00 1.76e+07 0.00e+00 5.59e+06 MN-56 0.00e+00 1.28e-02 0.00e+00 1.54e-02 0.00e+00 1.85e+00 0.00e+00 2.88e-03 FE-55 1.12e+08 5.93e+07 0.00e+00 0.00e+00 3.35e+07 1.10e+07 0.00e+00 1.84e+07 FE-59 1.20e+08 1.94e+08 0.00e+00 0.00e+00 5.64e+07 2.03e+08 0.00e+00 9.69e+07 CO-58 0.00e+00 1.21e+07 0.00e+00 0.00e+00 0.00e+00 7.08e+07 0.00e+00 3.71e+07 CO-60 0.00e+00 4.32e+07 0.00e+00 0.00e+00 0.00e+00 2.39e+08 0.00e+00 1.27e+08 NI-63 2.96e+10 1.59e+09 0.00e+00 0.00e+00 0.00e+00 1.07e+08 0.00e+00 1.01e+09 NI-65 1.66e+00 1.56e-01 0.00e+00 0.00e+00 0.00e+00 1.91e+01 0.00e+00 9.11e-02 CU-64 0.00e+00 7.39e+04 0.00e+00 1.79e+05 0.00e+00 3.47e+06 0.00e+00 4.47e+04 ZN-65 4.13e+09 1.10e+10 0.00e+00 6.94e+09 0.00e+00 1.93e+09 0.00e+00 6.85e+09 ZN-69 9.10e-12 1.32e-11 0.00e+00 7.98e-12 0.00e+00 8.29e-10 0.00e+00 1.22e-12 BR-83 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.37e-01 BR-84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.84e-23 BR-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RB-86 0.00e+00 8.77e+09 0.00e+00 0.00e+00 0.00e+00 5.64e+08 0.00e+00 5.39e+09 RB-88 0.00e+00 7.17e-45 0.00e+00 0.00e+00 0.00e+00 3.52e-46 0.00e+00 4.98e-45 RB-89 0.00e+00 1.40e-52 0.00e+00 0.00e+00 0.00e+00 1.22e-54 0.00e+00 1.24e-52 SR-89 6.62e+09 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.56e+08 0.00e+00 1.89e+08 SR-90 1.12e+11 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.51e+09 0.00e+00 2.83e+10 SR-91 1.29e+05 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.86e+05 0.00e+00 4.89e+03 SR-92 2.16e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.09e+01 0.00e+00 8.67e-02 Y-90 3.23e+02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 9.19e+05 0.00e+00 8.64e+00 Y-91 3.90e+04 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.20e+06 0.00e+00 1.04e+03 Y-91M 2.87e-19 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.62e-16 0.00e+00 1.04e-20 Y-92 2.53e-04 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.30e+00 0.00e+00 7.23e-06 Y-93 1.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.50e+04 0.00e+00 2.76e-02 ZR-95 3.83e+03 8.43e+02 0.00e+00 1.21e+03 0.00e+00 8.79e+05 0.00e+00 7.50e+02 ZR-97 1.92e+00 2.77e-01 0.00e+00 3.97e-01 0.00e+00 4.19e+04 0.00e+00 1.63e-01 NB-95 3.18e+05 1.24e+05 0.00e+00 1.16e+05 0.00e+00 2.29e+08 0.00e+00 8.84e+04 MO-99 0.00e+00 8.12e+07 0.00e+00 1.74e+08 0.00e+00 6.72e+07 0.00e+00 2.01e+07 TC-99M 1.32e+01 2.58e+01 0.00e+00 3.75e+02 1.31e+01 1.47e+04 0.00e+00 4.28e+02 TC-101 1.08e-59 1.13e-59 0.00e+00 1.92e-58 5.95e-60 3.58e-59 0.00e+00 1.43e-58 RU-103 4.28e+03 0.00e+00 0.00e+00 1.08e+04 0.00e+00 1.11e+05 0.00e+00 1.65e+03 RU-105 3.79e-03 0.00e+00 0.00e+00 3.33e-02 0.00e+00 2.48e+00 0.00e+00 1.38e-03 RU-106 9.24e+04 0.00e+00 0.00e+00 1.25e+05 0.00e+00 1.44e+06 0.00e+00 1.15e+04 AG-110M 2.09e+08 1.41e+08 0.00e+00 2.63e+08 0.00e+00 1.68e+10 0.00e+00 1.13e+08 TE-125M 7.38e+07 2.00e+07 2.07e+07 0.00e+00 0.00e+00 7.12e+07 0.00e+00 9.84e+06 TE-127 3.04e+03 8.19e+02 2.10e+03 8.64e+03 0.00e+00 1.19e+05 0.00e+00 6.51e+02 TE-127M 2.08e+08 5.60e+07 4.97e+07 5.93e+08 0.00e+00 1.68e+08 0.00e+00 2.47e+07 TE-129 1.07e-09 2.99e-10 7.63e-10 3.13e-09 0.00e+00 6.65e-08 0.00e+00 2.54e-10 TE-129M 2.71e+08 7.58e+07 8.75e+07 7.97e+08 0.00e+00 3.31e+08 0.00e+00 4.21e+07 TE-131 1.64e-32 5.01e-33 1.26e-32 4.97e-32 0.00e+00 8.64e-32 0.00e+00 4.89e-33 TE-131M 1.60e+06 5.53e+05 1.14e+06 5.35e+06 0.00e+00 2.24e+07 0.00e+00 5.88e+05 GRAND GULF, UNIT 1 2.0-18g Revision 43

TABLE 2.2-2b (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 10 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 2 CHILD Pathway: 5 Grs/Cow/Milk (CMILK)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 1.02e+07 4.52e+06 6.58e+06 4.19e+07 0.00e+00 4.55e+07 0.00e+00 5.46e+06 I-130 1.72e+06 3.47e+06 3.83e+08 5.19e+06 0.00e+00 1.62e+06 0.00e+00 1.79e+06 I-131 1.30e+09 1.31e+09 4.33e+11 2.15e+09 0.00e+00 1.17e+08 0.00e+00 7.45e+08 I-132 6.91e-01 1.27e+00 5.89e+01 1.94e+00 0.00e+00 1.49e+00 0.00e+00 5.84e-01 I-133 1.72e+07 2.12e+07 3.94e+09 3.54e+07 0.00e+00 8.55e+06 0.00e+00 8.03e+06 I-134 7.94e-12 1.48e-11 3.39e-10 2.26e-11 0.00e+00 9.78e-12 0.00e+00 6.79e-12 I-135 5.43e+04 9.78e+04 8.66e+06 1.50e+05 0.00e+00 7.45e+04 0.00e+00 4.62e+04 CS-134 2.26e+10 3.72e+10 0.00e+00 1.15e+10 4.13e+09 2.00e+08 0.00e+00 7.84e+09 CS-136 1.01e+09 2.78e+09 0.00e+00 1.48e+09 2.21e+08 9.77e+07 0.00e+00 1.80e+09 CS-137 3.22e+10 3.09e+10 0.00e+00 1.01e+10 3.62e+09 1.93e+08 0.00e+00 4.56e+09 CS-138 3.82e-23 5.31e-23 0.00e+00 3.74e-23 4.02e-24 2.45e-23 0.00e+00 3.37e-23 BA-139 2.02e-07 1.08e-10 0.00e+00 9.39e-11 6.33e-11 1.16e-05 0.00e+00 5.84e-09 BA-140 1.17e+08 1.03e+05 0.00e+00 3.34e+04 6.12e+04 5.94e+07 0.00e+00 6.84e+06 BA-141 1.96e-45 1.09e-48 0.00e+00 9.48e-49 6.43e-48 1.12e-45 0.00e+00 6.37e-47 BA-142 1.93e-80 1.39e-83 0.00e+00 1.12e-83 8.15e-84 2.51e-82 0.00e+00 1.08e-81 LA-140 1.94e+01 6.80e+00 0.00e+00 0.00e+00 0.00e+00 1.90e+05 0.00e+00 2.29e+00 LA-142 8.24e-11 2.63e-11 0.00e+00 0.00e+00 0.00e+00 5.20e-06 0.00e+00 8.22e-12 CE-141 2.19e+04 1.09e+04 0.00e+00 4.78e+03 0.00e+00 1.36e+07 0.00e+00 1.62e+03 CE-143 1.87e+02 1.01e+05 0.00e+00 4.26e+01 0.00e+00 1.49e+06 0.00e+00 1.47e+01 CE-144 1.62e+06 5.09e+05 0.00e+00 2.82e+05 0.00e+00 1.33e+08 0.00e+00 8.66e+04 PR-143 7.19e+02 2.16e+02 0.00e+00 1.17e+02 0.00e+00 7.75e+05 0.00e+00 3.56e+01 PR-144 2.95e-53 9.11e-54 0.00e+00 4.82e-54 0.00e+00 1.96e-50 0.00e+00 1.48e-54 ND-147 4.44e+02 3.60e+02 0.00e+00 1.98e+02 0.00e+00 5.70e+05 0.00e+00 2.79e+01 W-187 2.89e+04 1.71e+04 0.00e+00 0.00e+00 0.00e+00 2.40e+06 0.00e+00 7.67e+03 NP-239 1.72e+01 1.24e+00 0.00e+00 3.58e+00 0.00e+00 9.15e+04 0.00e+00 8.69e-01 3

Units: Inhalation2and all tritium pathways - mrem/yr per µCi/m Others - m . mrem/yr per µCi/sec Values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise indicated.

GRAND GULF, UNIT 1 2.0-18h Revision 43

TABLE 2.2-2c PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 1 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 1 TEEN Pathway: 0 Ground Plane Deposition (GPD)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 C-14 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 NA-24 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.39e+07 1.20e+07 P-32 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 CR-51 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.50e+06 4.65e+06 MN-54 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.62e+09 1.38e+09 MN-56 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.07e+06 9.03e+05 FE-55 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 FE-59 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.20e+08 2.73e+08 CO-58 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.45e+08 3.80e+08 CO-60 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.53e+10 2.15e+10 NI-63 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 NI-65 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.45e+05 2.97e+05 CU-64 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.86e+05 6.05e+05 ZN-65 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.57e+08 7.46e+08 ZN-69 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BR-83 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.08e+03 4.87e+03 BR-84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.37e+05 2.03e+05 BR-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RB-86 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.03e+07 8.98e+06 RB-88 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.78e+04 3.31e+04 RB-89 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.48e+05 1.23e+05 SR-89 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.51e+04 2.16e+04 SR-90 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 SR-91 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.51e+06 2.15e+06 SR-92 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.62e+05 7.76e+05 Y-90 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.31e+03 4.50e+03 Y-91 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.21e+06 1.07e+06 Y-91M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.16e+05 1.00e+05 Y-92 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.14e+05 1.80e+05 Y-93 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.50e+05 1.83e+05 ZR-95 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.85e+08 2.45e+08 ZR-97 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.44e+06 2.96e+06 NB-95 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.61e+08 1.37e+08 MO-99 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.62e+06 3.99e+06 TC-99M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.11e+05 1.84e+05 TC-101 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.26e+04 2.03e+04 RU-103 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.26e+08 1.08e+08 RU-105 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.21e+05 6.36e+05 RU-106 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.04e+08 4.20e+08 AG-110M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.02e+09 3.45e+09 TE-125M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.13e+06 1.56e+06 TE-127 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.29e+03 2.99e+03 TE-127M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.08e+05 9.17e+04 TE-129 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.08e+04 2.61e+04 TE-129M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.31e+07 1.98e+07 TE-131 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.45e+07 2.92e+04 TE-131M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 9.46e+06 8.02e+06 GRAND GULF, UNIT 1 2.0-19 Revision 43

TABLE 2.2-2c (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 2 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 1 TEEN Pathway: 0 Ground Plane Deposition (GPD)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.97e+06 4.22e+06 I-130 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.68e+06 5.50e+06 I-131 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.09e+07 1.72e+07 I-132 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.47e+06 1.25e+06 I-133 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.98e+06 2.45e+06 I-134 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.30e+05 4.46e+05 I-135 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.95e+06 2.53e+06 CS-134 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.05e+09 6.90e+09 CS-136 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.71e+08 1.51e+08 CS-137 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.20e+10 1.03e+10 CS-138 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.10e+05 3.59e+05 BA-139 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.19e+05 1.06e+05 BA-140 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.35e+07 2.05e+07 BA-141 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.75e+04 4.17e+04 BA-142 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.06e+04 4.44e+04 LA-140 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.18e+07 1.92e+07 LA-142 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 9.12e+05 7.60e+05 CE-141 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.54e+07 1.37e+07 CE-143 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.63e+06 2.31e+06 CE-144 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.05e+07 6.96e+07 PR-143 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 PR-144 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.11e+03 1.84e+03 ND-147 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.01e+07 8.39e+06 W-187 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.73e+06 2.35e+06 NP-239 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.98e+06 1.71e+06 GRAND GULF, UNIT 1 2.0-20 Revision 43

TABLE 2.2-2c (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 3 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 1 TEEN Pathway: 1 Inhalation (INHL)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 0.00e+00 1.27e+03 1.27e+03 1.27e+03 1.27e+03 1.27e+03 0.00e+00 1.27e+03 C-14 2.60e+04 4.87e+03 4.87e+03 4.87e+03 4.87e+03 4.87e+03 0.00e+00 4.87e+03 NA-24 1.38e+04 1.38e+04 1.38e+04 1.38e+04 1.38e+04 1.38e+04 0.00e+00 1.38e+04 P-32 1.89e+06 1.10e+05 0.00e+00 0.00e+00 0.00e+00 9.28e+04 0.00e+00 7.16e+04 CR-51 0.00e+00 0.00e+00 7.50e+01 3.07e+01 2.10e+04 3.00e+03 0.00e+00 1.35e+02 MN-54 0.00e+00 5.11e+04 0.00e+00 1.27e+04 1.98e+06 6.68e+04 0.00e+00 8.40e+03 MN-56 0.00e+00 1.70e+00 0.00e+00 1.79e+00 1.52e+04 5.74e+04 0.00e+00 2.52e-01 FE-55 3.34e+04 2.38e+04 0.00e+00 0.00e+00 1.24e+05 6.39e+03 0.00e+00 5.54e+03 FE-59 1.59e+04 3.70e+04 0.00e+00 0.00e+00 1.53e+06 1.78e+05 0.00e+00 1.43e+04 CO-58 0.00e+00 2.07e+03 0.00e+00 0.00e+00 1.34e+06 9.52e+04 0.00e+00 2.78e+03 CO-60 0.00e+00 1.51e+04 0.00e+00 0.00e+00 8.72e+06 2.59e+05 0.00e+00 1.98e+04 NI-63 5.80e+05 4.34e+04 0.00e+00 0.00e+00 3.07e+05 1.42e+04 0.00e+00 1.98e+04 NI-65 2.18e+00 2.93e-01 0.00e+00 0.00e+00 9.36e+03 3.67e+04 0.00e+00 1.27e-01 CU-64 0.00e+00 2.03e+00 0.00e+00 6.41e+00 1.11e+04 6.14e+04 0.00e+00 8.48e-01 ZN-65 3.86e+04 1.34e+05 0.00e+00 8.64e+04 1.24e+06 4.66e+04 0.00e+00 6.24e+04 ZN-69 4.83e-02 9.20e-02 0.00e+00 6.02e-02 1.58e+03 2.85e+02 0.00e+00 6.46e-03 BR-83 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.44e+02 BR-84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.33e+02 BR-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.83e+01 RB-86 0.00e+00 1.90e+05 0.00e+00 0.00e+00 0.00e+00 1.77e+04 0.00e+00 8.40e+04 RB-88 0.00e+00 5.46e+02 0.00e+00 0.00e+00 0.00e+00 2.92e-05 0.00e+00 2.72e+02 RB-89 0.00e+00 3.52e+02 0.00e+00 0.00e+00 0.00e+00 3.38e-07 0.00e+00 2.33e+02 SR-89 4.34e+05 0.00e+00 0.00e+00 0.00e+00 2.42e+06 3.71e+05 0.00e+00 1.25e+04 SR-90 1.08e+08 0.00e+00 0.00e+00 0.00e+00 1.65e+07 7.65e+05 0.00e+00 6.68e+06 SR-91 8.80e+01 0.00e+00 0.00e+00 0.00e+00 6.07e+04 2.59e+05 0.00e+00 3.51e+00 SR-92 9.52e+00 0.00e+00 0.00e+00 0.00e+00 2.74e+04 1.19e+05 0.00e+00 4.06e-01 Y-90 2.98e+03 0.00e+00 0.00e+00 0.00e+00 2.93e+05 5.59e+05 0.00e+00 8.00e+01 Y-91 6.61e+05 0.00e+00 0.00e+00 0.00e+00 2.94e+06 4.09e+05 0.00e+00 1.77e+04 Y-91M 3.70e-01 0.00e+00 0.00e+00 0.00e+00 3.20e+03 3.02e+01 0.00e+00 1.42e-02 Y-92 1.47e+01 0.00e+00 0.00e+00 0.00e+00 2.68e+04 1.65e+05 0.00e+00 4.29e-01 Y-93 1.35e+02 0.00e+00 0.00e+00 0.00e+00 8.32e+04 5.79e+05 0.00e+00 3.72e+00 ZR-95 1.46e+05 4.58e+04 0.00e+00 6.74e+04 2.69e+06 1.49e+05 0.00e+00 3.15e+04 ZR-97 1.38e+02 2.72e+01 0.00e+00 4.12e+01 1.30e+05 6.30e+05 0.00e+00 1.26e+01 NB-95 1.86e+04 1.03e+04 0.00e+00 1.00e+04 7.51e+05 9.68e+04 0.00e+00 5.66e+03 MO-99 0.00e+00 1.69e+02 0.00e+00 4.11e+02 1.54e+05 2.69e+05 0.00e+00 3.22e+01 TC-99M 1.38e-03 3.86e-03 0.00e+00 5.76e-02 1.15e+03 6.13e+03 0.00e+00 4.99e-02 TC-101 5.92e-05 8.40e-05 0.00e+00 1.52e-03 6.67e+02 8.72e-07 0.00e+00 8.24e-04 RU-103 2.10e+03 0.00e+00 0.00e+00 7.43e+03 7.83e+05 1.09e+05 0.00e+00 8.96e+02 RU-105 1.12e+00 0.00e+00 0.00e+00 1.41e+00 1.82e+04 9.04e+04 0.00e+00 4.34e-01 RU-106 9.84e+04 0.00e+00 0.00e+00 1.90e+05 1.61e+07 9.60e+05 0.00e+00 1.24e+04 AG-110M 1.38e+04 1.31e+04 0.00e+00 2.50e+04 6.75e+06 2.73e+05 0.00e+00 7.99e+03 TE-125M 4.88e+03 2.24e+03 1.40e+03 0.00e+00 5.36e+05 7.50e+04 0.00e+00 6.67e+02 TE-127 2.01e+00 9.12e-01 1.42e+00 7.28e+00 1.12e+04 8.08e+04 0.00e+00 4.42e-01 TE-127M 1.80e+04 8.16e+03 4.38e+03 6.54e+04 1.66e+06 1.59e+05 0.00e+00 2.18e+03 TE-129 7.10e-02 3.38e-02 5.18e-02 2.66e-01 3.30e+03 1.62e+03 0.00e+00 1.76e-02 TE-129M 1.39e+04 6.58e+03 4.58e+03 5.19e+04 1.98e+06 4.05e+05 0.00e+00 2.25e+03 TE-131 1.58e-02 8.32e-03 1.24e-02 6.18e-02 2.34e+03 1.51e+01 0.00e+00 5.04e-03 TE-131M 9.84e+01 6.01e+01 7.25e+01 4.39e+02 2.38e+05 6.21e+05 0.00e+00 4.02e+01 GRAND GULF, UNIT 1 2.0-20a Revision 43

TABLE 2.2-2c (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 4 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 1 TEEN Pathway: 1 Inhalation (INHL)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 3.60e+02 2.90e+02 2.46e+02 1.95e+03 4.49e+05 4.63e+05 0.00e+00 2.19e+02 I-130 6.24e+03 1.79e+04 1.49e+06 2.75e+04 0.00e+00 9.12e+03 0.00e+00 7.17e+03 I-131 3.54e+04 4.91e+04 1.46e+07 8.40e+04 0.00e+00 6.49e+03 0.00e+00 2.64e+04 I-132 1.59e+03 4.38e+03 1.51e+05 6.92e+03 0.00e+00 1.27e+03 0.00e+00 1.58e+03 I-133 1.22e+04 2.05e+04 2.92e+06 3.59e+04 0.00e+00 1.03e+04 0.00e+00 6.22e+03 I-134 8.88e+02 2.32e+03 3.95e+04 3.66e+03 0.00e+00 2.04e+01 0.00e+00 8.40e+02 I-135 3.70e+03 9.44e+03 6.21e+05 1.49e+04 0.00e+00 6.95e+03 0.00e+00 3.49e+03 CS-134 5.02e+05 1.13e+06 0.00e+00 3.75e+05 1.46e+05 9.76e+03 0.00e+00 5.49e+05 CS-136 5.15e+04 1.94e+05 0.00e+00 1.10e+05 1.78e+04 1.09e+04 0.00e+00 1.37e+05 CS-137 6.70e+05 8.48e+05 0.00e+00 3.04e+05 1.21e+05 8.48e+03 0.00e+00 3.11e+05 CS-138 4.66e+02 8.56e+02 0.00e+00 6.62e+02 7.87e+01 2.70e-01 0.00e+00 4.46e+02 BA-139 1.34e+00 9.44e-04 0.00e+00 8.88e-04 6.46e+03 6.45e+03 0.00e+00 3.90e-02 BA-140 5.47e+04 6.70e+01 0.00e+00 2.28e+01 2.03e+06 2.29e+05 0.00e+00 3.52e+03 BA-141 1.42e-01 1.06e-04 0.00e+00 9.84e-05 3.29e+03 7.46e-04 0.00e+00 4.74e-03 BA-142 3.70e-02 3.70e-05 0.00e+00 3.14e-05 1.91e+03 4.79e-10 0.00e+00 2.27e-03 LA-140 4.79e+02 2.36e+02 0.00e+00 0.00e+00 2.14e+05 4.87e+05 0.00e+00 6.26e+01 LA-142 9.60e-01 4.25e-01 0.00e+00 0.00e+00 1.02e+04 1.20e+04 0.00e+00 1.06e-01 CE-141 2.84e+04 1.90e+04 0.00e+00 8.88e+03 6.14e+05 1.26e+05 0.00e+00 2.17e+03 CE-143 2.66e+02 1.94e+02 0.00e+00 8.64e+01 1.30e+05 2.55e+05 0.00e+00 2.16e+01 CE-144 4.89e+06 2.02e+06 0.00e+00 1.21e+06 1.34e+07 8.64e+05 0.00e+00 2.62e+05 PR-143 1.34e+04 5.31e+03 0.00e+00 3.09e+03 4.83e+05 2.14e+05 0.00e+00 6.62e+02 PR-144 4.30e-02 1.76e-02 0.00e+00 1.01e-02 1.75e+03 2.35e-04 0.00e+00 2.18e-03 ND-147 7.86e+03 8.56e+03 0.00e+00 5.02e+03 3.72e+05 1.82e+05 0.00e+00 5.13e+02 W-187 1.20e+01 9.76e+00 0.00e+00 0.00e+00 4.74e+04 1.77e+05 0.00e+00 3.43e+00 NP-239 3.38e+02 3.19e+01 0.00e+00 1.00e+02 6.49e+04 1.32e+05 0.00e+00 1.77e+01 GRAND GULF, UNIT 1 2.0-20b Revision 43

TABLE 2.2-2c (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 5 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 1 TEEN Pathway: 2 Vegetation (VEG)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 0.00e+00 2.59e+03 2.59e+03 2.59e+03 2.59e+03 2.59e+03 0.00e+00 2.59e+03 C-14 3.69e+08 7.38e+07 7.38e+07 7.38e+07 7.38e+07 7.38e+07 0.00e+00 7.38e+07 NA-24 2.40e+05 2.40e+05 2.40e+05 2.40e+05 2.40e+05 2.40e+05 0.00e+00 2.40e+05 P-32 1.61e+09 9.95e+07 0.00e+00 0.00e+00 0.00e+00 1.35e+08 0.00e+00 6.23e+07 CR-51 0.00e+00 0.00e+00 3.42e+04 1.35e+04 8.79e+04 1.03e+07 0.00e+00 6.16e+04 MN-54 0.00e+00 4.54e+08 0.00e+00 1.36e+08 0.00e+00 9.32e+08 0.00e+00 9.01e+07 MN-56 0.00e+00 1.43e+01 0.00e+00 1.81e+01 0.00e+00 9.41e+02 0.00e+00 2.54e+00 FE-55 3.26e+08 2.31e+08 0.00e+00 0.00e+00 1.47e+08 1.00e+08 0.00e+00 5.39e+07 FE-59 1.79e+08 4.18e+08 0.00e+00 0.00e+00 1.32e+08 9.89e+08 0.00e+00 1.61e+08 CO-58 0.00e+00 4.37e+07 0.00e+00 0.00e+00 0.00e+00 6.02e+08 0.00e+00 1.01e+08 CO-60 0.00e+00 2.49e+08 0.00e+00 0.00e+00 0.00e+00 3.24e+09 0.00e+00 5.60e+08 NI-63 1.61e+10 1.13e+09 0.00e+00 0.00e+00 0.00e+00 1.81e+08 0.00e+00 5.45e+08 NI-65 5.73e+01 7.32e+00 0.00e+00 0.00e+00 0.00e+00 3.97e+02 0.00e+00 3.33e+00 CU-64 0.00e+00 8.29e+03 0.00e+00 2.10e+04 0.00e+00 6.43e+05 0.00e+00 3.90e+03 ZN-65 4.24e+08 1.47e+09 0.00e+00 9.42e+08 0.00e+00 6.23e+08 0.00e+00 6.86e+08 ZN-69 5.04e-06 9.61e-06 0.00e+00 6.28e-06 0.00e+00 1.77e-05 0.00e+00 6.72e-07 BR-83 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.90e+00 BR-84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.31e-11 BR-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RB-86 0.00e+00 2.74e+08 0.00e+00 0.00e+00 0.00e+00 4.05e+07 0.00e+00 1.29e+08 RB-88 0.00e+00 3.17e-22 0.00e+00 0.00e+00 0.00e+00 2.72e-29 0.00e+00 1.69e-22 RB-89 0.00e+00 3.57e-26 0.00e+00 0.00e+00 0.00e+00 5.46e-35 0.00e+00 2.52e-26 SR-89 1.51e+10 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.80e+09 0.00e+00 4.33e+08 SR-90 7.51e+11 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.11e+10 0.00e+00 1.85e+11 SR-91 2.83e+05 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.29e+06 0.00e+00 1.13e+04 SR-92 3.95e+02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.01e+04 0.00e+00 1.68e+01 Y-90 1.24e+04 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.03e+08 0.00e+00 3.35e+02 Y-91 7.84e+06 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.22e+09 0.00e+00 2.10e+05 Y-91M 5.04e-09 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.38e-07 0.00e+00 1.93e-10 Y-92 8.59e-01 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.36e+04 0.00e+00 2.49e-02 Y-93 1.58e+02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.83e+06 0.00e+00 4.34e+00 ZR-95 1.72e+06 5.44e+05 0.00e+00 7.99e+05 0.00e+00 1.26e+09 0.00e+00 3.74e+05 ZR-97 3.12e+02 6.17e+01 0.00e+00 9.36e+01 0.00e+00 1.67e+07 0.00e+00 2.84e+01 NB-95 1.92e+05 1.07e+05 0.00e+00 1.03e+05 0.00e+00 4.56e+08 0.00e+00 5.87e+04 MO-99 0.00e+00 5.64e+06 0.00e+00 1.29e+07 0.00e+00 1.01e+07 0.00e+00 1.08e+06 TC-99M 2.73e+00 7.62e+00 0.00e+00 1.14e+02 4.23e+00 5.00e+03 0.00e+00 9.87e+01 TC-101 7.35e-31 1.04e-30 0.00e+00 1.89e-29 6.37e-31 1.79e-37 0.00e+00 1.03e-29 RU-103 6.82e+06 0.00e+00 0.00e+00 2.40e+07 0.00e+00 5.69e+08 0.00e+00 2.91e+06 RU-105 4.98e+01 0.00e+00 0.00e+00 6.29e+02 0.00e+00 4.02e+04 0.00e+00 1.93e+01 RU-106 3.09e+08 0.00e+00 0.00e+00 5.97e+08 0.00e+00 1.48e+10 0.00e+00 3.90e+07 AG-110M 1.52e+07 1.44e+07 0.00e+00 2.74e+07 0.00e+00 4.03e+09 0.00e+00 8.73e+06 TE-125M 1.49e+08 5.35e+07 4.15e+07 0.00e+00 0.00e+00 4.38e+08 0.00e+00 1.99e+07 TE-127 5.40e+03 1.91e+03 3.73e+03 2.19e+04 0.00e+00 4.17e+05 0.00e+00 1.16e+03 TE-127M 5.52e+08 1.96e+08 1.31e+08 2.24e+09 0.00e+00 1.37e+09 0.00e+00 6.56e+07 TE-129 6.50e-04 2.42e-04 4.64e-04 2.73e-03 0.00e+00 3.56e-03 0.00e+00 1.58e-04 TE-129M 3.61e+08 1.34e+08 1.17e+08 1.51e+09 0.00e+00 1.36e+09 0.00e+00 5.72e+07 TE-131 1.41e-15 5.80e-16 1.08e-15 6.15e-15 0.00e+00 1.16e-16 0.00e+00 4.40e-16 TE-131M 8.44e+05 4.05e+05 6.09e+05 4.22e+06 0.00e+00 3.25e+07 0.00e+00 3.38e+05 GRAND GULF, UNIT 1 2.0-20c Revision 43

TABLE 2.2-2c (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 6 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 1 TEEN Pathway: 2 Vegetation (VEG)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 3.90e+06 2.47e+06 2.60e+06 2.37e+07 0.00e+00 7.81e+07 0.00e+00 2.32e+06 I-130 3.50e+05 1.01e+06 8.25e+07 1.56e+06 0.00e+00 7.77e+05 0.00e+00 4.04e+05 I-131 7.68e+07 1.08e+08 3.14e+10 1.85e+08 0.00e+00 2.13e+07 0.00e+00 5.78e+07 I-132 5.20e+01 1.36e+02 4.59e+03 2.14e+02 0.00e+00 5.93e+01 0.00e+00 4.88e+01 I-133 1.94e+06 3.28e+06 4.58e+08 5.76e+06 0.00e+00 2.49e+06 0.00e+00 1.00e+06 I-134 8.44e-05 2.24e-04 3.73e-03 3.53e-04 0.00e+00 2.95e-06 0.00e+00 8.03e-05 I-135 3.53e+04 9.10e+04 5.85e+06 1.44e+05 0.00e+00 1.01e+05 0.00e+00 3.37e+04 CS-134 7.10e+09 1.67e+10 0.00e+00 5.31e+09 2.03e+09 2.08e+08 0.00e+00 7.76e+09 CS-136 4.37e+07 1.72e+08 0.00e+00 9.36e+07 1.48e+07 1.38e+07 0.00e+00 1.16e+08 CS-137 1.01e+10 1.35e+10 0.00e+00 4.59e+09 1.78e+09 1.92e+08 0.00e+00 4.70e+09 CS-138 3.54e-11 6.80e-11 0.00e+00 5.02e-11 5.84e-12 3.08e-14 0.00e+00 3.40e-11 BA-139 2.69e-02 1.89e-05 0.00e+00 1.79e-05 1.31e-05 2.40e-01 0.00e+00 7.84e-04 BA-140 1.38e+08 1.69e+05 0.00e+00 5.74e+04 1.14e+05 2.13e+08 0.00e+00 8.91e+06 BA-141 1.11e-21 8.26e-25 0.00e+00 7.67e-25 5.66e-25 2.36e-27 0.00e+00 3.69e-23 BA-142 2.24e-39 2.24e-42 0.00e+00 1.90e-42 1.49e-42 6.88e-51 0.00e+00 1.38e-40 LA-140 1.81e+03 8.89e+02 0.00e+00 0.00e+00 0.00e+00 5.11e+07 0.00e+00 2.37e+02 LA-142 1.87e-04 8.31e-05 0.00e+00 0.00e+00 0.00e+00 2.53e+00 0.00e+00 2.07e-05 CE-141 2.83e+05 1.89e+05 0.00e+00 8.89e+04 0.00e+00 5.40e+08 0.00e+00 2.17e+04 CE-143 9.31e+02 6.78e+05 0.00e+00 3.04e+02 0.00e+00 2.04e+07 0.00e+00 7.57e+01 CE-144 5.28e+07 2.18e+07 0.00e+00 1.30e+07 0.00e+00 1.33e+10 0.00e+00 2.83e+06 PR-143 7.02e+04 2.80e+04 0.00e+00 1.63e+04 0.00e+00 2.31e+08 0.00e+00 3.49e+03 PR-144 3.04e-26 1.24e-26 0.00e+00 7.13e-27 0.00e+00 3.35e-29 0.00e+00 1.54e-27 ND-147 3.62e+04 3.93e+04 0.00e+00 2.31e+04 0.00e+00 1.42e+08 0.00e+00 2.36e+03 W-187 3.54e+04 2.88e+04 0.00e+00 0.00e+00 0.00e+00 7.80e+06 0.00e+00 1.01e+04 NP-239 1.38e+03 1.31e+02 0.00e+00 4.10e+02 0.00e+00 2.10e+07 0.00e+00 7.25e+01 GRAND GULF, UNIT 1 2.0-20d Revision 43

TABLE 2.2-2c (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 7 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 1 TEEN Pathway: 4 Grs/Cow/Meat (CMEAT)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 0.00e+00 1.94e+02 1.94e+02 1.94e+02 1.94e+02 1.94e+02 0.00e+00 1.94e+02 C-14 2.04e+08 4.08e+07 4.08e+07 4.08e+07 4.08e+07 4.08e+07 0.00e+00 4.08e+07 NA-24 1.16e-03 1.16e-03 1.16e-03 1.16e-03 1.16e-03 1.16e-03 0.00e+00 1.16e-03 P-32 3.93e+09 2.43e+08 0.00e+00 0.00e+00 0.00e+00 3.30e+08 0.00e+00 1.52e+08 CR-51 0.00e+00 0.00e+00 3.13e+03 1.23e+03 8.04e+03 9.46e+05 0.00e+00 5.63e+03 MN-54 0.00e+00 7.00e+06 0.00e+00 2.09e+06 0.00e+00 1.44e+07 0.00e+00 1.39e+06 MN-56 0.00e+00 1.17e-53 0.00e+00 1.48e-53 0.00e+00 7.71e-52 0.00e+00 2.08e-54 FE-55 2.38e+08 1.69e+08 0.00e+00 0.00e+00 1.07e+08 7.31e+07 0.00e+00 3.94e+07 FE-59 2.12e+08 4.95e+08 0.00e+00 0.00e+00 1.56e+08 1.17e+09 0.00e+00 1.91e+08 CO-58 0.00e+00 1.41e+07 0.00e+00 0.00e+00 0.00e+00 1.94e+08 0.00e+00 3.24e+07 CO-60 0.00e+00 5.84e+07 0.00e+00 0.00e+00 0.00e+00 7.60e+08 0.00e+00 1.31e+08 NI-63 1.52e+10 1.07e+09 0.00e+00 0.00e+00 0.00e+00 1.71e+08 0.00e+00 5.15e+08 NI-65 1.90e-52 2.43e-53 0.00e+00 0.00e+00 0.00e+00 1.32e-51 0.00e+00 1.11e-53 CU-64 0.00e+00 2.06e-07 0.00e+00 5.21e-07 0.00e+00 1.60e-05 0.00e+00 9.68e-08 ZN-65 2.50e+08 8.69e+08 0.00e+00 5.56e+08 0.00e+00 3.68e+08 0.00e+00 4.05e+08 ZN-69 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BR-83 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.73e-57 BR-84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BR-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RB-86 0.00e+00 4.07e+08 0.00e+00 0.00e+00 0.00e+00 6.02e+07 0.00e+00 1.91e+08 RB-88 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RB-89 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 SR-89 2.54e+08 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.03e+07 0.00e+00 7.28e+06 SR-90 8.05e+09 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.26e+08 0.00e+00 1.99e+09 SR-91 1.21e-10 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.47e-10 0.00e+00 4.80e-12 SR-92 9.02e-50 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.30e-48 0.00e+00 3.85e-51 Y-90 9.13e+01 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.53e+05 0.00e+00 2.46e+00 Y-91 9.54e+05 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.91e+08 0.00e+00 2.56e+04 Y-91M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Y-92 1.26e-39 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.46e-35 0.00e+00 3.65e-41 Y-93 3.71e-12 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.13e-07 0.00e+00 1.02e-13 ZR-95 1.50e+06 4.74e+05 0.00e+00 6.96e+05 0.00e+00 1.09e+09 0.00e+00 3.26e+05 ZR-97 1.70e-05 3.37e-06 0.00e+00 5.10e-06 0.00e+00 9.11e-01 0.00e+00 1.55e-06 NB-95 1.79e+06 9.95e+05 0.00e+00 9.64e+05 0.00e+00 4.25e+09 0.00e+00 5.48e+05 MO-99 0.00e+00 8.21e+04 0.00e+00 1.88e+05 0.00e+00 1.47e+05 0.00e+00 1.57e+04 TC-99M 3.43e-21 9.57e-21 0.00e+00 1.43e-19 5.31e-21 6.29e-18 0.00e+00 1.24e-19 TC-101 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RU-103 8.57e+07 0.00e+00 0.00e+00 3.02e+08 0.00e+00 7.15e+09 0.00e+00 3.66e+07 RU-105 4.54e-28 0.00e+00 0.00e+00 5.73e-27 0.00e+00 3.67e-25 0.00e+00 1.76e-28 RU-106 2.36e+09 0.00e+00 0.00e+00 4.55e+09 0.00e+00 1.13e+11 0.00e+00 2.97e+08 AG-110M 5.06e+06 4.79e+06 0.00e+00 9.13e+06 0.00e+00 1.35e+09 0.00e+00 2.91e+06 TE-125M 3.03e+08 1.09e+08 8.48e+07 0.00e+00 0.00e+00 8.95e+08 0.00e+00 4.06e+07 TE-127 2.12e-10 7.52e-11 1.47e-10 8.60e-10 0.00e+00 1.64e-08 0.00e+00 4.57e-11 TE-127M 9.42e+08 3.34e+08 2.24e+08 3.82e+09 0.00e+00 2.35e+09 0.00e+00 1.12e+08 TE-129 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 TE-129M 9.49e+08 3.52e+08 3.06e+08 3.97e+09 0.00e+00 3.56e+09 0.00e+00 1.50e+08 TE-131 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 TE-131M 3.75e+02 1.80e+02 2.70e+02 1.87e+03 0.00e+00 1.44e+04 0.00e+00 1.50e+02 GRAND GULF, UNIT 1 2.0-20e Revision 43

TABLE 2.2-2c (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 8 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 1 TEEN Pathway: 4 Grs/Cow/Meat (CMEAT)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 1.14e+06 7.24e+05 7.63e+05 6.94e+06 0.00e+00 2.29e+07 0.00e+00 6.81e+05 I-130 1.63e-06 4.72e-06 3.85e-04 7.27e-06 0.00e+00 3.63e-06 0.00e+00 1.89e-06 I-131 8.92e+06 1.25e+07 3.64e+09 2.15e+07 0.00e+00 2.47e+06 0.00e+00 6.71e+06 I-132 5.79e-59 1.52e-58 5.11e-57 2.39e-58 0.00e+00 6.60e-59 0.00e+00 5.44e-59 I-133 3.04e-01 5.15e-01 7.19e+01 9.03e-01 0.00e+00 3.90e-01 0.00e+00 1.57e-01 I-134 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 I-135 3.79e-17 9.75e-17 6.27e-15 1.54e-16 0.00e+00 1.08e-16 0.00e+00 3.61e-17 CS-134 5.23e+08 1.23e+09 0.00e+00 3.91e+08 1.49e+08 1.53e+07 0.00e+00 5.71e+08 CS-136 9.39e+06 3.69e+07 0.00e+00 2.01e+07 3.17e+06 2.97e+06 0.00e+00 2.48e+07 CS-137 7.24e+08 9.63e+08 0.00e+00 3.28e+08 1.27e+08 1.37e+07 0.00e+00 3.36e+08 CS-138 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BA-139 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BA-140 2.38e+07 2.91e+04 0.00e+00 9.88e+03 1.96e+04 3.67e+07 0.00e+00 1.53e+06 BA-141 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BA-142 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 LA-140 3.09e-02 1.52e-02 0.00e+00 0.00e+00 0.00e+00 8.73e+02 0.00e+00 4.05e-03 LA-142 3.36e-92 1.49e-92 0.00e+00 0.00e+00 0.00e+00 4.54e-88 0.00e+00 3.71e-93 CE-141 1.18e+04 7.87e+03 0.00e+00 3.71e+03 0.00e+00 2.25e+07 0.00e+00 9.04e+02 CE-143 1.67e-02 1.22e+01 0.00e+00 5.46e-03 0.00e+00 3.66e+02 0.00e+00 1.36e-03 CE-144 1.23e+06 5.08e+05 0.00e+00 3.04e+05 0.00e+00 3.09e+08 0.00e+00 6.60e+04 PR-143 1.77e+04 7.05e+03 0.00e+00 4.10e+03 0.00e+00 5.81e+07 0.00e+00 8.79e+02 PR-144 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 ND-147 6.22e+03 6.77e+03 0.00e+00 3.97e+03 0.00e+00 2.44e+07 0.00e+00 4.05e+02 W-187 1.73e-02 1.41e-02 0.00e+00 0.00e+00 0.00e+00 3.82e+00 0.00e+00 4.94e-03 NP-239 2.25e-01 2.12e-02 0.00e+00 6.66e-02 0.00e+00 3.41e+03 0.00e+00 1.18e-02 GRAND GULF, UNIT 1 2.0-20f Revision 43

TABLE 2.2-2c (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 9 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 1 TEEN Pathway: 5 Grs/Cow/Milk (CMILK)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 0.00e+00 9.94e+02 9.94e+02 9.94e+02 9.94e+02 9.94e+02 0.00e+00 9.94e+02 C-14 4.86e+08 9.72e+07 9.72e+07 9.72e+07 9.72e+07 9.72e+07 0.00e+00 9.72e+07 NA-24 4.29e+06 4.29e+06 4.29e+06 4.29e+06 4.29e+06 4.29e+06 0.00e+00 4.29e+06 P-32 3.15e+10 1.95e+09 0.00e+00 0.00e+00 0.00e+00 2.65e+09 0.00e+00 1.22e+09 CR-51 0.00e+00 0.00e+00 2.77e+04 1.09e+04 7.12e+04 8.38e+06 0.00e+00 4.99e+04 MN-54 0.00e+00 1.40e+07 0.00e+00 4.18e+06 0.00e+00 2.87e+07 0.00e+00 2.78e+06 MN-56 0.00e+00 7.32e-03 0.00e+00 9.27e-03 0.00e+00 4.82e-01 0.00e+00 1.30e-03 FE-55 4.45e+07 3.16e+07 0.00e+00 0.00e+00 2.00e+07 1.37e+07 0.00e+00 7.36e+06 FE-59 5.18e+07 1.21e+08 0.00e+00 0.00e+00 3.81e+07 2.86e+08 0.00e+00 4.67e+07 CO-58 0.00e+00 7.94e+06 0.00e+00 0.00e+00 0.00e+00 1.10e+08 0.00e+00 1.83e+07 CO-60 0.00e+00 2.78e+07 0.00e+00 0.00e+00 0.00e+00 3.62e+08 0.00e+00 6.26e+07 NI-63 1.18e+10 8.35e+08 0.00e+00 0.00e+00 0.00e+00 1.33e+08 0.00e+00 4.01e+08 NI-65 6.78e-01 8.66e-02 0.00e+00 0.00e+00 0.00e+00 4.70e+00 0.00e+00 3.94e-02 CU-64 0.00e+00 4.21e+04 0.00e+00 1.06e+05 0.00e+00 3.26e+06 0.00e+00 1.98e+04 ZN-65 2.11e+09 7.31e+09 0.00e+00 4.68e+09 0.00e+00 3.10e+09 0.00e+00 3.41e+09 ZN-69 3.70e-12 7.05e-12 0.00e+00 4.61e-12 0.00e+00 1.30e-11 0.00e+00 4.94e-13 BR-83 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.78e-01 BR-84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.02e-23 BR-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RB-86 0.00e+00 4.73e+09 0.00e+00 0.00e+00 0.00e+00 7.00e+08 0.00e+00 2.22e+09 RB-88 0.00e+00 3.90e-45 0.00e+00 0.00e+00 0.00e+00 3.34e-52 0.00e+00 2.08e-45 RB-89 0.00e+00 7.96e-53 0.00e+00 0.00e+00 0.00e+00 1.22e-61 0.00e+00 5.63e-53 SR-89 2.67e+09 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.18e+08 0.00e+00 7.66e+07 SR-90 6.61e+10 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.86e+09 0.00e+00 1.63e+10 SR-91 5.27e+04 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.39e+05 0.00e+00 2.10e+03 SR-92 8.85e-01 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.26e+01 0.00e+00 3.77e-02 Y-90 1.30e+02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.08e+06 0.00e+00 3.51e+00 Y-91 1.58e+04 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.48e+06 0.00e+00 4.24e+02 Y-91M 1.18e-19 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.55e-18 0.00e+00 4.49e-21 Y-92 1.03e-04 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.82e+00 0.00e+00 2.98e-06 Y-93 4.09e-01 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.25e+04 0.00e+00 1.12e-02 ZR-95 1.65e+03 5.21e+02 0.00e+00 7.65e+02 0.00e+00 1.20e+06 0.00e+00 3.58e+02 ZR-97 7.87e-01 1.56e-01 0.00e+00 2.36e-01 0.00e+00 4.22e+04 0.00e+00 7.17e-02 NB-95 1.41e+05 7.81e+04 0.00e+00 7.57e+04 0.00e+00 3.34e+08 0.00e+00 4.30e+04 MO-99 0.00e+00 4.46e+07 0.00e+00 1.02e+08 0.00e+00 8.00e+07 0.00e+00 8.51e+06 TC-99M 5.74e+00 1.60e+01 0.00e+00 2.39e+02 8.89e+00 1.05e+04 0.00e+00 2.08e+02 TC-101 4.39e-60 6.24e-60 0.00e+00 1.13e-58 3.80e-60 1.07e-66 0.00e+00 6.13e-59 RU-103 1.81e+03 0.00e+00 0.00e+00 6.38e+03 0.00e+00 1.51e+05 0.00e+00 7.74e+02 RU-105 1.55e-03 0.00e+00 0.00e+00 1.96e-02 0.00e+00 1.25e+00 0.00e+00 6.03e-04 RU-106 3.75e+04 0.00e+00 0.00e+00 7.23e+04 0.00e+00 1.80e+06 0.00e+00 4.73e+03 AG-110M 9.63e+07 9.11e+07 0.00e+00 1.74e+08 0.00e+00 2.56e+10 0.00e+00 5.54e+07 TE-125M 3.01e+07 1.08e+07 8.40e+06 0.00e+00 0.00e+00 8.87e+07 0.00e+00 4.02e+06 TE-127 1.24e+03 4.38e+02 8.52e+02 5.00e+03 0.00e+00 9.54e+04 0.00e+00 2.66e+02 TE-127M 8.44e+07 2.99e+07 2.01e+07 3.42e+08 0.00e+00 2.10e+08 0.00e+00 1.00e+07 TE-129 4.33e-10 1.62e-10 3.10e-10 1.82e-09 0.00e+00 2.37e-09 0.00e+00 1.05e-10 TE-129M 1.10e+08 4.09e+07 3.55e+07 4.61e+08 0.00e+00 4.13e+08 0.00e+00 1.74e+07 TE-131 6.70e-33 2.76e-33 5.16e-33 2.93e-32 0.00e+00 5.50e-34 0.00e+00 2.09e-33 TE-131M 6.57e+05 3.15e+05 4.74e+05 3.28e+06 0.00e+00 2.53e+07 0.00e+00 2.63e+05 GRAND GULF, UNIT 1 2.0-20g Revision 43

TABLE 2.2-2c (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 10 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 1 TEEN Pathway: 5 Grs/Cow/Milk (CMILK)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 4.28e+06 2.71e+06 2.85e+06 2.60e+07 0.00e+00 8.57e+07 0.00e+00 2.55e+06 I-130 7.35e+05 2.13e+06 1.73e+08 3.27e+06 0.00e+00 1.63e+06 0.00e+00 8.49e+05 I-131 5.37e+08 7.52e+08 2.19e+11 1.30e+09 0.00e+00 1.49e+08 0.00e+00 4.04e+08 I-132 2.92e-01 7.64e-01 2.58e+01 1.20e+00 0.00e+00 3.33e-01 0.00e+00 2.74e-01 I-133 7.06e+06 1.20e+07 1.67e+09 2.10e+07 0.00e+00 9.06e+06 0.00e+00 3.65e+06 I-134 3.36e-12 8.89e-12 1.48e-10 1.40e-11 0.00e+00 1.17e-13 0.00e+00 3.19e-12 I-135 2.29e+04 5.91e+04 3.80e+06 9.33e+04 0.00e+00 6.55e+04 0.00e+00 2.19e+04 CS-134 9.82e+09 2.31e+10 0.00e+00 7.34e+09 2.80e+09 2.87e+08 0.00e+00 1.07e+10 CS-136 4.48e+08 1.76e+09 0.00e+00 9.60e+08 1.51e+08 1.42e+08 0.00e+00 1.18e+09 CS-137 1.34e+10 1.78e+10 0.00e+00 6.06e+09 2.35e+09 2.53e+08 0.00e+00 6.20e+09 CS-138 1.58e-23 3.03e-23 0.00e+00 2.23e-23 2.60e-24 1.37e-26 0.00e+00 1.51e-23 BA-139 8.20e-08 5.77e-11 0.00e+00 5.44e-11 3.98e-11 7.31e-07 0.00e+00 2.39e-09 BA-140 4.85e+07 5.95e+04 0.00e+00 2.02e+04 4.00e+04 7.49e+07 0.00e+00 3.13e+06 BA-141 7.95e-46 5.94e-49 0.00e+00 5.51e-49 4.07e-49 1.70e-51 0.00e+00 2.66e-47 BA-142 7.98e-81 7.98e-84 0.00e+00 6.75e-84 5.31e-84 2.45e-92 0.00e+00 4.91e-82 LA-140 8.12e+00 3.99e+00 0.00e+00 0.00e+00 0.00e+00 2.29e+05 0.00e+00 1.06e+00 LA-142 3.41e-11 1.52e-11 0.00e+00 0.00e+00 0.00e+00 4.61e-07 0.00e+00 3.77e-12 CE-141 8.88e+03 5.93e+03 0.00e+00 2.79e+03 0.00e+00 1.70e+07 0.00e+00 6.81e+02 CE-143 7.62e+01 5.55e+04 0.00e+00 2.49e+01 0.00e+00 1.67e+06 0.00e+00 6.20e+00 CE-144 6.58e+05 2.72e+05 0.00e+00 1.63e+05 0.00e+00 1.66e+08 0.00e+00 3.54e+04 PR-143 2.90e+02 1.16e+02 0.00e+00 6.74e+01 0.00e+00 9.55e+05 0.00e+00 1.44e+01 PR-144 1.19e-53 4.87e-54 0.00e+00 2.79e-54 0.00e+00 1.31e-56 0.00e+00 6.03e-55 ND-147 1.81e+02 1.97e+02 0.00e+00 1.16e+02 0.00e+00 7.11e+05 0.00e+00 1.18e+01 W-187 1.19e+04 9.71e+03 0.00e+00 0.00e+00 0.00e+00 2.63e+06 0.00e+00 3.40e+03 NP-239 7.00e+00 6.60e-01 0.00e+00 2.07e+00 0.00e+00 1.06e+05 0.00e+00 3.67e-01 3

Units: Inhalation and all tritium pathways mrem/yr per µCi/m 2

Others - m . mrem/yr per µCi/sec Values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise indicated.

GRAND GULF, UNIT 1 2.0-20h Revision 43

TABLE 2.2-2d PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 1 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 0 ADULT Pathway: 0 Ground Plane Deposition (GPD)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 C-14 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 NA-24 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.39e+07 1.20e+07 P-32 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 CR-51 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.50e+06 4.65e+06 MN-54 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.62e+09 1.38e+09 MN-56 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.07e+06 9.03e+05 FE-55 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 FE-59 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.20e+08 2.73e+08 CO-58 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.45e+08 3.80e+08 CO-60 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.53e+10 2.15e+10 NI-63 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 NI-65 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.45e+05 2.97e+05 CU-64 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.86e+05 6.05e+05 ZN-65 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.57e+08 7.46e+08 ZN-69 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BR-83 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.08e+03 4.87e+03 BR-84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.37e+05 2.03e+05 BR-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RB-86 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.03e+07 8.98e+06 RB-88 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.78e+04 3.31e+04 RB-89 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.48e+05 1.23e+05 SR-89 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.51e+04 2.16e+04 SR-90 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 SR-91 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.51e+06 2.15e+06 SR-92 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.62e+05 7.76e+05 Y-90 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.31e+03 4.50e+03 Y-91 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.21e+06 1.07e+06 Y-91M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.16e+05 1.00e+05 Y-92 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.14e+05 1.80e+05 Y-93 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.50e+05 1.83e+05 ZR-95 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.85e+08 2.45e+08 ZR-97 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.44e+06 2.96e+06 NB-95 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.61e+08 1.37e+08 MO-99 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.62e+06 3.99e+06 TC-99M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.11e+05 1.84e+05 TC-101 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.26e+04 2.03e+04 RU-103 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.26e+08 1.08e+08 RU-105 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.21e+05 6.36e+05 RU-106 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.04e+08 4.20e+08 AG-110M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.02e+09 3.45e+09 TE-125M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.13e+06 1.56e+06 TE-127 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.29e+03 2.99e+03 TE-127M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.08e+05 9.17e+04 TE-129 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.08e+04 2.61e+04 TE-129M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.31e+07 1.98e+07 TE-131 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.45e+07 2.92e+04 TE-131M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 9.46e+06 8.02e+06 GRAND GULF, UNIT 1 2.0-21 Revision 43

TABLE 2.2-2d (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 2 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 0 ADULT Pathway: 0 Ground Plane Deposition (GPD)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.97e+06 4.22e+06 I-130 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.68e+06 5.50e+06 I-131 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.09e+07 1.72e+07 I-132 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.47e+06 1.25e+06 I-133 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.98e+06 2.45e+06 I-134 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.30e+05 4.46e+05 I-135 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.95e+06 2.53e+06 CS-134 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.05e+09 6.90e+09 CS-136 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.71e+08 1.51e+08 CS-137 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.20e+10 1.03e+10 CS-138 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.10e+05 3.59e+05 BA-139 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.19e+05 1.06e+05 BA-140 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.35e+07 2.05e+07 BA-141 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.75e+04 4.17e+04 BA-142 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.06e+04 4.44e+04 LA-140 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.18e+07 1.92e+07 LA-142 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 9.12e+05 7.60e+05 CE-141 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.54e+07 1.37e+07 CE-143 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.63e+06 2.31e+06 CE-144 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.05e+07 6.96e+07 PR-143 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 PR-144 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.11e+03 1.84e+03 ND-147 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.01e+07 8.39e+06 W-187 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.73e+06 2.35e+06 NP-239 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.98e+06 1.71e+06 GRAND GULF, UNIT 1 2.0-22 Revision 43

TABLE 2.2-2d (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 3 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 0 ADULT Pathway: 1 Inhalation (INHL)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 0.00e+00 1.26e+03 1.26e+03 1.26e+03 1.26e+03 1.26e+03 0.00e+00 1.26e+03 C-14 1.82e+04 3.41e+03 3.41e+03 3.41e+03 3.41e+03 3.41e+03 0.00e+00 3.41e+03 NA-24 1.02e+04 1.02e+04 1.02e+04 1.02e+04 1.02e+04 1.02e+04 0.00e+00 1.02e+04 P-32 1.32e+06 7.71e+04 0.00e+00 0.00e+00 0.00e+00 8.64e+04 0.00e+00 5.01e+04 CR-51 0.00e+00 0.00e+00 5.95e+01 2.28e+01 1.44e+04 3.32e+03 0.00e+00 1.00e+02 MN-54 0.00e+00 3.96e+04 0.00e+00 9.84e+03 1.40e+06 7.74e+04 0.00e+00 6.30e+03 MN-56 0.00e+00 1.24e+00 0.00e+00 1.30e+00 9.44e+03 2.02e+04 0.00e+00 1.83e-01 FE-55 2.46e+04 1.70e+04 0.00e+00 0.00e+00 7.21e+04 6.03e+03 0.00e+00 3.94e+03 FE-59 1.18e+04 2.78e+04 0.00e+00 0.00e+00 1.02e+06 1.88e+05 0.00e+00 1.06e+04 CO-58 0.00e+00 1.58e+03 0.00e+00 0.00e+00 9.28e+05 1.06e+05 0.00e+00 2.07e+03 CO-60 0.00e+00 1.15e+04 0.00e+00 0.00e+00 5.97e+06 2.85e+05 0.00e+00 1.48e+04 NI-63 4.32e+05 3.14e+04 0.00e+00 0.00e+00 1.78e+05 1.34e+04 0.00e+00 1.45e+04 NI-65 1.54e+00 2.10e-01 0.00e+00 0.00e+00 5.60e+03 1.23e+04 0.00e+00 9.12e-02 CU-64 0.00e+00 1.46e+00 0.00e+00 4.62e+00 6.78e+03 4.90e+04 0.00e+00 6.15e-01 ZN-65 3.24e+04 1.03e+05 0.00e+00 6.90e+04 8.64e+05 5.34e+04 0.00e+00 4.66e+04 ZN-69 3.38e-02 6.51e-02 0.00e+00 4.22e-02 9.20e+02 1.63e+01 0.00e+00 4.52e-03 BR-83 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.32e+02 0.00e+00 2.41e+02 BR-84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.64e-03 0.00e+00 3.13e+02 BR-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.28e+01 RB-86 0.00e+00 1.35e+05 0.00e+00 0.00e+00 0.00e+00 1.66e+04 0.00e+00 5.90e+04 RB-88 0.00e+00 3.87e+02 0.00e+00 0.00e+00 0.00e+00 3.34e-09 0.00e+00 1.93e+02 RB-89 0.00e+00 2.56e+02 0.00e+00 0.00e+00 0.00e+00 9.28e-12 0.00e+00 1.70e+02 SR-89 3.04e+05 0.00e+00 0.00e+00 0.00e+00 1.40e+06 3.50e+05 0.00e+00 8.72e+03 SR-90 9.92e+07 0.00e+00 0.00e+00 0.00e+00 9.60e+06 7.22e+05 0.00e+00 6.10e+06 SR-91 6.19e+01 0.00e+00 0.00e+00 0.00e+00 3.65e+04 1.91e+05 0.00e+00 2.50e+00 SR-92 6.74e+00 0.00e+00 0.00e+00 0.00e+00 1.65e+04 4.30e+04 0.00e+00 2.91e-01 Y-90 2.09e+03 0.00e+00 0.00e+00 0.00e+00 1.70e+05 5.06e+05 0.00e+00 5.61e+01 Y-91 4.62e+05 0.00e+00 0.00e+00 0.00e+00 1.70e+06 3.85e+05 0.00e+00 1.24e+04 Y-91M 2.61e-01 0.00e+00 0.00e+00 0.00e+00 1.92e+03 1.33e+00 0.00e+00 1.02e-02 Y-92 1.03e+01 0.00e+00 0.00e+00 0.00e+00 1.57e+04 7.35e+04 0.00e+00 3.02e-01 Y-93 9.44e+01 0.00e+00 0.00e+00 0.00e+00 4.85e+04 4.22e+05 0.00e+00 2.61e+00 ZR-95 1.07e+05 3.44e+04 0.00e+00 5.42e+04 1.77e+06 1.50e+05 0.00e+00 2.33e+04 ZR-97 9.68e+01 1.96e+01 0.00e+00 2.97e+01 7.87e+04 5.23e+05 0.00e+00 9.04e+00 NB-95 1.41e+04 7.82e+03 0.00e+00 7.74e+03 5.05e+05 1.04e+05 0.00e+00 4.21e+03 MO-99 0.00e+00 1.21e+02 0.00e+00 2.91e+02 9.12e+04 2.48e+05 0.00e+00 2.30e+01 TC-99M 1.03e-03 2.91e-03 0.00e+00 4.42e-02 7.64e+02 4.16e+03 0.00e+00 3.70e-02 TC-101 4.18e-05 6.02e-05 0.00e+00 1.08e-03 3.99e+02 1.09e-11 0.00e+00 5.90e-04 RU-103 1.53e+03 0.00e+00 0.00e+00 5.83e+03 5.05e+05 1.10e+05 0.00e+00 6.58e+02 RU-105 7.90e-01 0.00e+00 0.00e+00 1.02e+00 1.10e+04 4.82e+04 0.00e+00 3.11e-01 RU-106 6.91e+04 0.00e+00 0.00e+00 1.34e+05 9.36e+06 9.12e+05 0.00e+00 8.72e+03 AG-110M 1.08e+04 1.00e+04 0.00e+00 1.97e+04 4.63e+06 3.02e+05 0.00e+00 5.94e+03 TE-125M 3.42e+03 1.58e+03 1.05e+03 1.24e+04 3.14e+05 7.06e+04 0.00e+00 4.67e+02 TE-127 1.40e+00 6.42e-01 1.06e+00 5.10e+00 6.51e+03 5.74e+04 0.00e+00 3.10e-01 TE-127M 1.26e+04 5.77e+03 3.29e+03 4.58e+04 9.60e+05 1.50e+05 0.00e+00 1.57e+03 TE-129 4.98e-02 2.39e-02 3.90e-02 1.87e-01 1.94e+03 1.57e+02 0.00e+00 1.24e-02 TE-129M 9.76e+03 4.67e+03 3.44e+03 3.66e+04 1.16e+06 3.83e+05 0.00e+00 1.58e+03 TE-131 1.11e-02 5.95e-03 9.36e-03 4.37e-02 1.39e+03 1.84e+01 0.00e+00 3.59e-03 TE-131M 6.99e+01 4.36e+01 5.50e+01 3.09e+02 1.46e+05 5.56e+05 0.00e+00 2.90e+01 GRAND GULF, UNIT 1 2.0-22a Revision 43

TABLE 2.2-2d (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 4 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 0 ADULT Pathway: 1 Inhalation (INHL)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 2.60e+02 2.15e+02 1.90e+02 1.46e+03 2.88e+05 5.10e+05 0.00e+00 1.62e+02 I-130 4.58e+03 1.34e+04 1.14e+06 2.09e+04 0.00e+00 7.69e+03 0.00e+00 5.28e+03 I-131 2.52e+04 3.58e+04 1.19e+07 6.13e+04 0.00e+00 6.28e+03 0.00e+00 2.05e+04 I-132 1.16e+03 3.26e+03 1.14e+05 5.18e+03 0.00e+00 4.06e+02 0.00e+00 1.16e+03 I-133 8.64e+03 1.48e+04 2.15e+06 2.58e+04 0.00e+00 8.88e+03 0.00e+00 4.52e+03 I-134 6.44e+02 1.73e+03 2.98e+04 2.75e+03 0.00e+00 1.01e+00 0.00e+00 6.15e+02 I-135 2.68e+03 6.98e+03 4.48e+05 1.11e+04 0.00e+00 5.25e+03 0.00e+00 2.57e+03 CS-134 3.73e+05 8.48e+05 0.00e+00 2.87e+05 9.76e+04 1.04e+04 0.00e+00 7.28e+05 CS-136 3.90e+04 1.46e+05 0.00e+00 8.56e+04 1.20e+04 1.17e+04 0.00e+00 1.10e+05 CS-137 4.78e+05 6.21e+05 0.00e+00 2.22e+05 7.52e+04 8.40e+03 0.00e+00 4.28e+05 CS-138 3.31e+02 6.21e+02 0.00e+00 4.80e+02 4.86e+01 1.86e-03 0.00e+00 3.24e+02 BA-139 9.36e-01 6.66e-04 0.00e+00 6.22e-04 3.76e+03 8.96e+02 0.00e+00 2.74e-02 BA-140 3.90e+04 4.90e+01 0.00e+00 1.67e+01 1.27e+06 2.18e+05 0.00e+00 2.57e+03 BA-141 1.00e-01 7.53e-05 0.00e+00 7.00e-05 1.94e+03 1.16e-07 0.00e+00 3.36e-03 BA-142 2.63e-02 2.70e-05 0.00e+00 2.29e-05 1.19e+03 1.57e-16 0.00e+00 1.66e-03 LA-140 3.44e+02 1.74e+02 0.00e+00 0.00e+00 1.36e+05 4.58e+05 0.00e+00 4.58e+01 LA-142 6.83e-01 3.10e-01 0.00e+00 0.00e+00 6.33e+03 2.11e+03 0.00e+00 7.72e-02 CE-141 1.99e+04 1.35e+04 0.00e+00 6.26e+03 3.62e+05 1.20e+05 0.00e+00 1.53e+03 CE-143 1.86e+02 1.38e+02 0.00e+00 6.08e+01 7.98e+04 2.26e+05 0.00e+00 1.53e+01 CE-144 3.43e+06 1.43e+06 0.00e+00 8.48e+05 7.78e+06 8.16e+05 0.00e+00 1.84e+05 PR-143 9.36e+03 3.75e+03 0.00e+00 2.16e+03 2.81e+05 2.00e+05 0.00e+00 4.64e+02 PR-144 3.01e-02 1.25e-02 0.00e+00 7.05e-03 1.02e+03 2.15e-08 0.00e+00 1.53e-03 ND-147 5.27e+03 6.10e+03 0.00e+00 3.56e+03 2.21e+05 1.73e+05 0.00e+00 3.65e+02 W-187 8.48e+00 7.08e+00 0.00e+00 0.00e+00 2.90e+04 1.55e+05 0.00e+00 2.48e+00 NP-239 2.30e+02 2.26e+01 0.00e+00 7.00e+01 3.76e+04 1.19e+05 0.00e+00 1.24e+01 GRAND GULF, UNIT 1 2.0-22b Revision 43

TABLE 2.2-2d (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 5 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 0 ADULT Pathway: 2 Vegetation (VEG)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 0.00e+00 2.26e+03 2.26e+03 2.26e+03 2.26e+03 2.26e+03 0.00e+00 2.26e+03 C-14 2.28e+08 4.55e+07 4.55e+07 4.55e+07 4.55e+07 4.55e+07 0.00e+00 4.55e+07 NA-24 2.71e+05 2.71e+05 2.71e+05 2.71e+05 2.71e+05 2.71e+05 0.00e+00 2.71e+05 P-32 1.40e+09 8.72e+07 0.00e+00 0.00e+00 0.00e+00 1.58e+08 0.00e+00 5.42e+07 CR-51 0.00e+00 0.00e+00 2.77e+04 1.02e+04 6.15e+04 1.17e+07 0.00e+00 4.64e+04 MN-54 0.00e+00 3.13e+08 0.00e+00 9.31e+07 0.00e+00 9.58e+08 0.00e+00 5.97e+07 MN-56 0.00e+00 1.59e+01 0.00e+00 2.01e+01 0.00e+00 5.06e+02 0.00e+00 2.81e+00 FE-55 2.10e+08 1.45e+08 0.00e+00 0.00e+00 8.08e+07 8.31e+07 0.00e+00 3.38e+07 FE-59 1.26e+08 2.96e+08 0.00e+00 0.00e+00 8.27e+07 9.87e+08 0.00e+00 1.14e+08 CO-58 0.00e+00 3.08e+07 0.00e+00 0.00e+00 0.00e+00 6.24e+08 0.00e+00 6.90e+07 CO-60 0.00e+00 1.67e+08 0.00e+00 0.00e+00 0.00e+00 3.14e+09 0.00e+00 3.69e+08 NI-63 1.04e+10 7.21e+08 0.00e+00 0.00e+00 0.00e+00 1.51e+08 0.00e+00 3.49e+08 NI-65 6.15e+01 7.99e+00 0.00e+00 0.00e+00 0.00e+00 2.03e+02 0.00e+00 3.65e+00 CU-64 0.00e+00 9.15e+03 0.00e+00 2.31e+04 0.00e+00 7.80e+05 0.00e+00 4.29e+03 ZN-65 3.17e+08 1.01e+09 0.00e+00 6.75e+08 0.00e+00 6.36e+08 0.00e+00 4.56e+08 ZN-69 5.38e-06 1.03e-05 0.00e+00 6.69e-06 0.00e+00 1.55e-06 0.00e+00 7.16e-07 BR-83 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.46e+00 0.00e+00 3.10e+00 BR-84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.99e-16 0.00e+00 2.54e-11 BR-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RB-86 0.00e+00 2.19e+08 0.00e+00 0.00e+00 0.00e+00 4.33e+07 0.00e+00 1.02e+08 RB-88 0.00e+00 3.43e-22 0.00e+00 0.00e+00 0.00e+00 4.74e-33 0.00e+00 1.82e-22 RB-89 0.00e+00 3.96e-26 0.00e+00 0.00e+00 0.00e+00 2.30e-39 0.00e+00 2.79e-26 SR-89 9.95e+09 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.60e+09 0.00e+00 2.86e+08 SR-90 6.05e+11 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.75e+10 0.00e+00 1.48e+11 SR-91 3.03e+05 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.45e+06 0.00e+00 1.23e+04 SR-92 4.24e+02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.41e+03 0.00e+00 1.84e+01 Y-90 1.33e+04 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.41e+08 0.00e+00 3.57e+02 Y-91 5.12e+06 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.82e+09 0.00e+00 1.37e+05 Y-91M 5.41e-09 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.59e-08 0.00e+00 2.10e-10 Y-92 9.14e-01 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.60e+04 0.00e+00 2.67e-02 Y-93 1.69e+02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.35e+06 0.00e+00 4.66e+00 ZR-95 1.18e+06 3.77e+05 0.00e+00 5.92e+05 0.00e+00 1.20e+09 0.00e+00 2.55e+05 ZR-97 3.37e+02 6.80e+01 0.00e+00 1.03e+02 0.00e+00 2.11e+07 0.00e+00 3.11e+01 NB-95 1.42e+05 7.91e+04 0.00e+00 7.82e+04 0.00e+00 4.80e+08 0.00e+00 4.25e+04 MO-99 0.00e+00 6.14e+06 0.00e+00 1.39e+07 0.00e+00 1.42e+07 0.00e+00 1.17e+06 TC-99M 3.10e+00 8.75e+00 0.00e+00 1.33e+02 4.29e+00 5.18e+03 0.00e+00 1.11e+02 TC-101 7.90e-31 1.14e-30 0.00e+00 2.05e-29 5.82e-31 3.42e-42 0.00e+00 1.12e-29 RU-103 4.77e+06 0.00e+00 0.00e+00 1.82e+07 0.00e+00 5.57e+08 0.00e+00 2.05e+06 RU-105 5.36e+01 0.00e+00 0.00e+00 6.93e+02 0.00e+00 3.28e+04 0.00e+00 2.12e+01 RU-106 1.93e+08 0.00e+00 0.00e+00 3.72e+08 0.00e+00 1.25e+10 0.00e+00 2.44e+07 AG-110M 1.05e+07 9.75e+06 0.00e+00 1.92e+07 0.00e+00 3.98e+09 0.00e+00 5.79e+06 TE-125M 9.67e+07 3.50e+07 2.91e+07 3.93e+08 0.00e+00 3.86e+08 0.00e+00 1.30e+07 TE-127 5.73e+03 2.06e+03 4.25e+03 2.33e+04 0.00e+00 4.52e+05 0.00e+00 1.24e+03 TE-127M 3.49e+08 1.25e+08 8.92e+07 1.42e+09 0.00e+00 1.17e+09 0.00e+00 4.26e+07 TE-129 6.94e-04 2.61e-04 5.33e-04 2.92e-03 0.00e+00 5.24e-04 0.00e+00 1.69e-04 TE-129M 2.51e+08 9.37e+07 8.62e+07 1.05e+09 0.00e+00 1.26e+09 0.00e+00 3.97e+07 TE-131 1.51e-15 6.32e-16 1.24e-15 6.63e-15 0.00e+00 2.14e-16 0.00e+00 4.78e-16 TE-131M 9.12e+05 4.46e+05 7.06e+05 4.52e+06 0.00e+00 4.43e+07 0.00e+00 3.72e+05 GRAND GULF, UNIT 1 2.0-22c Revision 43

TABLE 2.2-2d (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 6 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 0 ADULT Pathway: 2 Vegetation (VEG)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 4.29e+06 2.77e+06 3.06e+06 2.67e+07 0.00e+00 1.31e+08 0.00e+00 2.60e+06 I-130 3.91e+05 1.15e+06 9.78e+07 1.80e+06 0.00e+00 9.93e+05 0.00e+00 4.55e+05 I-131 8.07e+07 1.16e+08 3.79e+10 1.98e+08 0.00e+00 3.05e+07 0.00e+00 6.62e+07 I-132 5.76e+01 1.54e+02 5.40e+03 2.46e+02 0.00e+00 2.90e+01 0.00e+00 5.40e+01 I-133 2.08e+06 3.63e+06 5.33e+08 6.33e+06 0.00e+00 3.26e+06 0.00e+00 1.11e+06 I-134 9.33e-05 2.54e-04 4.39e-03 4.03e-04 0.00e+00 2.21e-07 0.00e+00 9.07e-05 I-135 3.91e+04 1.02e+05 6.75e+06 1.64e+05 0.00e+00 1.16e+05 0.00e+00 3.78e+04 CS-134 4.67e+09 1.11e+10 0.00e+00 3.60e+09 1.19e+09 1.94e+08 0.00e+00 9.08e+09 CS-136 4.27e+07 1.68e+08 0.00e+00 9.37e+07 1.28e+07 1.91e+07 0.00e+00 1.21e+08 CS-137 6.36e+09 8.70e+09 0.00e+00 2.95e+09 9.81e+08 1.68e+08 0.00e+00 5.70e+09 CS-138 3.84e-11 7.58e-11 0.00e+00 5.57e-11 5.50e-12 3.23e-16 0.00e+00 3.75e-11 BA-139 2.86e-02 2.04e-05 0.00e+00 1.91e-05 1.16e-05 5.07e-02 0.00e+00 8.38e-04 BA-140 1.29e+08 1.62e+05 0.00e+00 5.49e+04 9.25e+04 2.65e+08 0.00e+00 8.42e+06 BA-141 1.18e-21 8.95e-25 0.00e+00 8.32e-25 5.08e-25 5.58e-31 0.00e+00 4.00e-23 BA-142 2.43e-39 2.50e-42 0.00e+00 2.11e-42 1.42e-42 3.43e-57 0.00e+00 1.53e-40 LA-140 1.98e+03 9.99e+02 0.00e+00 0.00e+00 0.00e+00 7.33e+07 0.00e+00 2.64e+02 LA-142 2.04e-04 9.27e-05 0.00e+00 0.00e+00 0.00e+00 6.77e-01 0.00e+00 2.31e-05 CE-141 1.97e+05 1.33e+05 0.00e+00 6.19e+04 0.00e+00 5.09e+08 0.00e+00 1.51e+04 CE-143 9.97e+02 7.37e+05 0.00e+00 3.24e+02 0.00e+00 2.75e+07 0.00e+00 8.15e+01 CE-144 3.29e+07 1.38e+07 0.00e+00 8.16e+06 0.00e+00 1.11e+10 0.00e+00 1.77e+06 PR-143 6.27e+04 2.52e+04 0.00e+00 1.45e+04 0.00e+00 2.75e+08 0.00e+00 3.11e+03 PR-144 3.24e-26 1.34e-26 0.00e+00 7.58e-27 0.00e+00 4.66e-33 0.00e+00 1.65e-27 ND-147 3.33e+04 3.85e+04 0.00e+00 2.25e+04 0.00e+00 1.85e+08 0.00e+00 2.30e+03 W-187 3.80e+04 3.18e+04 0.00e+00 0.00e+00 0.00e+00 1.04e+07 0.00e+00 1.11e+04 NP-239 1.43e+03 1.40e+02 0.00e+00 4.37e+02 0.00e+00 2.88e+07 0.00e+00 7.73e+01 GRAND GULF, UNIT 1 2.0-22d Revision 43

TABLE 2.2-2d (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 7 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 0 ADULT Pathway: 4 Grs/Cow/Meat (CMEAT)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 0.00e+00 3.25e+02 3.25e+02 3.25e+02 3.25e+02 3.25e+02 0.00e+00 3.25e+02 C-14 2.41e+08 4.83e+07 4.83e+07 4.83e+07 4.83e+07 4.83e+07 0.00e+00 4.83e+07 NA-24 1.45e-03 1.45e-03 1.45e-03 1.45e-03 1.45e-03 1.45e-03 0.00e+00 1.45e-03 P-32 4.65e+09 2.89e+08 0.00e+00 0.00e+00 0.00e+00 5.23e+08 0.00e+00 1.80e+08 CR-51 0.00e+00 0.00e+00 4.21e+03 1.55e+03 9.34e+03 1.77e+06 0.00e+00 7.04e+03 MN-54 0.00e+00 9.18e+06 0.00e+00 2.73e+06 0.00e+00 2.81e+07 0.00e+00 1.75e+06 MN-56 0.00e+00 1.44e-53 0.00e+00 1.83e-53 0.00e+00 4.60e-52 0.00e+00 2.56e-54 FE-55 2.93e+08 2.03e+08 0.00e+00 0.00e+00 1.13e+08 1.16e+08 0.00e+00 4.73e+07 FE-59 2.65e+08 6.24e+08 0.00e+00 0.00e+00 1.74e+08 2.08e+09 0.00e+00 2.39e+08 CO-58 0.00e+00 1.83e+07 0.00e+00 0.00e+00 0.00e+00 3.70e+08 0.00e+00 4.09e+07 CO-60 0.00e+00 7.52e+07 0.00e+00 0.00e+00 0.00e+00 1.41e+09 0.00e+00 1.66e+08 NI-63 1.89e+10 1.31e+09 0.00e+00 0.00e+00 0.00e+00 2.73e+08 0.00e+00 6.33e+08 NI-65 2.27e-52 2.94e-53 0.00e+00 0.00e+00 0.00e+00 7.47e-52 0.00e+00 1.34e-53 CU-64 0.00e+00 2.52e-07 0.00e+00 6.36e-07 0.00e+00 2.15e-05 0.00e+00 1.18e-07 ZN-65 3.56e+08 1.13e+09 0.00e+00 7.57e+08 0.00e+00 7.13e+08 0.00e+00 5.12e+08 ZN-69 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BR-83 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.08e-57 0.00e+00 5.61e-57 BR-84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BR-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RB-86 0.00e+00 4.87e+08 0.00e+00 0.00e+00 0.00e+00 9.60e+07 0.00e+00 2.27e+08 RB-88 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RB-89 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 SR-89 3.01e+08 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.83e+07 0.00e+00 8.65e+06 SR-90 1.24e+10 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.59e+08 0.00e+00 3.05e+09 SR-91 1.43e-10 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.83e-10 0.00e+00 5.79e-12 SR-92 1.08e-49 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.13e-48 0.00e+00 4.66e-51 Y-90 1.08e+02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.15e+06 0.00e+00 2.91e+00 Y-91 1.13e+06 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.23e+08 0.00e+00 3.03e+04 Y-91M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Y-92 1.49e-39 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.61e-35 0.00e+00 4.36e-41 Y-93 4.39e-12 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.39e-07 0.00e+00 1.21e-13 ZR-95 1.87e+06 6.01e+05 0.00e+00 9.43e+05 0.00e+00 1.91e+09 0.00e+00 4.07e+05 ZR-97 2.04e-05 4.12e-06 0.00e+00 6.22e-06 0.00e+00 1.27e+00 0.00e+00 1.88e-06 NB-95 2.30e+06 1.28e+06 0.00e+00 1.26e+06 0.00e+00 7.75e+09 0.00e+00 6.87e+05 MO-99 0.00e+00 9.93e+04 0.00e+00 2.25e+05 0.00e+00 2.30e+05 0.00e+00 1.89e+04 TC-99M 4.32e-21 1.22e-20 0.00e+00 1.86e-19 5.98e-21 7.23e-18 0.00e+00 1.56e-19 TC-101 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RU-103 1.05e+08 0.00e+00 0.00e+00 4.01e+08 0.00e+00 1.23e+10 0.00e+00 4.53e+07 RU-105 5.43e-28 0.00e+00 0.00e+00 7.02e-27 0.00e+00 3.32e-25 0.00e+00 2.15e-28 RU-106 2.80e+09 0.00e+00 0.00e+00 5.40e+09 0.00e+00 1.81e+11 0.00e+00 3.54e+08 AG-110M 6.68e+06 6.18e+06 0.00e+00 1.22e+07 0.00e+00 2.52e+09 0.00e+00 3.67e+06 TE-125M 3.59e+08 1.30e+08 1.08e+08 1.46e+09 0.00e+00 1.43e+09 0.00e+00 4.81e+07 TE-127 2.50e-10 8.98e-11 1.85e-10 1.02e-09 0.00e+00 1.97e-08 0.00e+00 5.41e-11 TE-127M 1.12e+09 3.99e+08 2.85e+08 4.53e+09 0.00e+00 3.74e+09 0.00e+00 1.36e+08 TE-129 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 TE-129M 1.13e+09 4.23e+08 3.89e+08 4.73e+09 0.00e+00 5.71e+09 0.00e+00 1.79e+08 TE-131 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 TE-131M 4.49e+02 2.20e+02 3.48e+02 2.23e+03 0.00e+00 2.18e+04 0.00e+00 1.83e+02 GRAND GULF, UNIT 1 2.0-22e Revision 43

TABLE 2.2-2d (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 8 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 0 ADULT Pathway: 4 Grs/Cow/Meat (CMEAT)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 1.40e+06 9.03e+05 9.98e+05 8.70e+06 0.00e+00 4.27e+07 0.00e+00 8.48e+05 I-130 2.03e-06 5.98e-06 5.07e-04 9.33e-06 0.00e+00 5.15e-06 0.00e+00 2.36e-06 I-131 1.07e+07 1.54e+07 5.03e+09 2.63e+07 0.00e+00 4.05e+06 0.00e+00 8.80e+06 I-132 7.13e-59 1.91e-58 6.68e-57 3.04e-58 0.00e+00 3.58e-59 0.00e+00 6.68e-59 I-133 3.63e-01 6.31e-01 9.28e+01 1.10e+00 0.00e+00 5.68e-01 0.00e+00 1.93e-01 I-134 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 I-135 4.66e-17 1.22e-16 8.04e-15 1.96e-16 0.00e+00 1.38e-16 0.00e+00 4.50e-17 CS-134 6.58e+08 1.57e+09 0.00e+00 5.07e+08 1.68e+08 2.74e+07 0.00e+00 1.28e+09 CS-136 1.20e+07 4.75e+07 0.00e+00 2.65e+07 3.63e+06 5.40e+06 0.00e+00 3.42e+07 CS-137 8.72e+08 1.19e+09 0.00e+00 4.05e+08 1.35e+08 2.31e+07 0.00e+00 7.81e+08 CS-138 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BA-139 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BA-140 2.88e+07 3.61e+04 0.00e+00 1.23e+04 2.07e+04 5.92e+07 0.00e+00 1.88e+06 BA-141 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BA-142 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 LA-140 3.76e-02 1.90e-02 0.00e+00 0.00e+00 0.00e+00 1.39e+03 0.00e+00 5.01e-03 LA-142 4.06e-92 1.85e-92 0.00e+00 0.00e+00 0.00e+00 1.35e-88 0.00e+00 4.60e-93 CE-141 1.40e+04 9.50e+03 0.00e+00 4.41e+03 0.00e+00 3.63e+07 0.00e+00 1.08e+03 CE-143 1.99e-02 1.47e+01 0.00e+00 6.47e-03 0.00e+00 5.49e+02 0.00e+00 1.62e-03 CE-144 1.46e+06 6.09e+05 0.00e+00 3.62e+05 0.00e+00 4.93e+08 0.00e+00 7.83e+04 PR-143 2.10e+04 8.42e+03 0.00e+00 4.86e+03 0.00e+00 9.20e+07 0.00e+00 1.04e+03 PR-144 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 ND-147 7.06e+03 8.16e+03 0.00e+00 4.77e+03 0.00e+00 3.92e+07 0.00e+00 4.88e+02 W-187 2.07e-02 1.73e-02 0.00e+00 0.00e+00 0.00e+00 5.66e+00 0.00e+00 6.04e-03 NP-239 2.57e-01 2.53e-02 0.00e+00 7.90e-02 0.00e+00 5.19e+03 0.00e+00 1.40e-02 GRAND GULF, UNIT 1 2.0-22f Revision 43

TABLE 2.2-2d (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 9 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 0 ADULT Pathway: 5 Grs/Cow/Milk (CMILK)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 0.00e+00 7.63e+02 7.63e+02 7.63e+02 7.63e+02 7.63e+02 0.00e+00 7.63e+02 C-14 2.63e+08 5.27e+07 5.27e+07 5.27e+07 5.27e+07 5.27e+07 0.00e+00 5.27e+07 NA-24 2.46e+06 2.46e+06 2.46e+06 2.46e+06 2.46e+06 2.46e+06 0.00e+00 2.46e+06 P-32 1.71e+10 1.06e+09 0.00e+00 0.00e+00 0.00e+00 1.92e+09 0.00e+00 6.60e+08 CR-51 0.00e+00 0.00e+00 1.71e+04 6.29e+03 3.79e+04 7.18e+06 0.00e+00 2.86e+04 MN-54 0.00e+00 8.41e+06 0.00e+00 2.50e+06 0.00e+00 2.58e+07 0.00e+00 1.61e+06 MN-56 0.00e+00 4.13e-03 0.00e+00 5.24e-03 0.00e+00 1.32e-01 0.00e+00 7.32e-04 FE-55 2.51e+07 1.74e+07 0.00e+00 0.00e+00 9.68e+06 9.95e+06 0.00e+00 4.05e+06 FE-59 2.97e+07 6.98e+07 0.00e+00 0.00e+00 1.95e+07 2.33e+08 0.00e+00 2.68e+07 CO-58 0.00e+00 4.72e+06 0.00e+00 0.00e+00 0.00e+00 9.56e+07 0.00e+00 1.06e+07 CO-60 0.00e+00 1.64e+07 0.00e+00 0.00e+00 0.00e+00 3.08e+08 0.00e+00 3.62e+07 NI-63 6.73e+09 4.66e+08 0.00e+00 0.00e+00 0.00e+00 9.73e+07 0.00e+00 2.26e+08 NI-65 3.70e-01 4.81e-02 0.00e+00 0.00e+00 0.00e+00 1.22e+00 0.00e+00 2.20e-02 CU-64 0.00e+00 2.36e+04 0.00e+00 5.95e+04 0.00e+00 2.01e+06 0.00e+00 1.11e+04 ZN-65 1.37e+09 4.37e+09 0.00e+00 2.92e+09 0.00e+00 2.75e+09 0.00e+00 1.97e+09 ZN-69 2.01e-12 3.84e-12 0.00e+00 2.50e-12 0.00e+00 5.78e-13 0.00e+00 2.67e-13 BR-83 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.39e-01 0.00e+00 9.65e-02 BR-84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.33e-28 0.00e+00 1.69e-23 BR-85 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 RB-86 0.00e+00 2.60e+09 0.00e+00 0.00e+00 0.00e+00 5.12e+08 0.00e+00 1.21e+09 RB-88 0.00e+00 2.14e-45 0.00e+00 0.00e+00 0.00e+00 2.96e-56 0.00e+00 1.14e-45 RB-89 0.00e+00 4.50e-53 0.00e+00 0.00e+00 0.00e+00 2.61e-66 0.00e+00 3.16e-53 SR-89 1.45e+09 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.33e+08 0.00e+00 4.16e+07 SR-90 4.68e+10 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.35e+09 0.00e+00 1.15e+10 SR-91 2.87e+04 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.37e+05 0.00e+00 1.16e+03 SR-92 4.84e-01 0.00e+00 0.00e+00 0.00e+00 0.00e+00 9.58e+00 0.00e+00 2.09e-02 Y-90 7.10e+01 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.52e+05 0.00e+00 1.90e+00 Y-91 8.59e+03 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.73e+06 0.00e+00 2.30e+02 Y-91M 6.42e-20 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.89e-19 0.00e+00 2.49e-21 Y-92 5.57e-05 0.00e+00 0.00e+00 0.00e+00 0.00e+00 9.75e-01 0.00e+00 1.63e-06 Y-93 2.22e-01 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.03e+03 0.00e+00 6.12e-03 ZR-95 9.44e+02 3.03e+02 0.00e+00 4.75e+02 0.00e+00 9.59e+05 0.00e+00 2.05e+02 ZR-97 4.32e-01 8.72e-02 0.00e+00 1.32e-01 0.00e+00 2.70e+04 0.00e+00 3.99e-02 NB-95 8.25e+04 4.59e+04 0.00e+00 4.54e+04 0.00e+00 2.79e+08 0.00e+00 2.47e+04 MO-99 0.00e+00 2.47e+07 0.00e+00 5.60e+07 0.00e+00 5.73e+07 0.00e+00 4.71e+06 TC-99M 3.31e+00 9.35e+00 0.00e+00 1.42e+02 4.58e+00 5.53e+03 0.00e+00 1.19e+02 TC-101 2.40e-60 3.46e-60 0.00e+00 6.22e-59 1.77e-60 1.04e-71 0.00e+00 3.39e-59 RU-103 1.02e+03 0.00e+00 0.00e+00 3.88e+03 0.00e+00 1.19e+05 0.00e+00 4.39e+02 RU-105 8.51e-04 0.00e+00 0.00e+00 1.10e-02 0.00e+00 5.20e-01 0.00e+00 3.36e-04 RU-106 2.04e+04 0.00e+00 0.00e+00 3.94e+04 0.00e+00 1.32e+06 0.00e+00 2.58e+03 AG-110M 5.82e+07 5.39e+07 0.00e+00 1.06e+08 0.00e+00 2.20e+10 0.00e+00 3.20e+07 TE-125M 1.63e+07 5.91e+06 4.90e+06 6.63e+07 0.00e+00 6.51e+07 0.00e+00 2.18e+06 TE-127 6.66e+02 2.39e+02 4.94e+02 2.71e+03 0.00e+00 5.26e+04 0.00e+00 1.44e+02 TE-127M 4.58e+07 1.64e+07 1.17e+07 1.86e+08 0.00e+00 1.54e+08 0.00e+00 5.58e+06 TE-129 2.35e-10 8.85e-11 1.81e-10 9.89e-10 0.00e+00 1.78e-10 0.00e+00 5.74e-11 TE-129M 6.02e+07 2.25e+07 2.07e+07 2.51e+08 0.00e+00 3.03e+08 0.00e+00 9.52e+06 TE-131 3.66e-33 1.53e-33 3.01e-33 1.61e-32 0.00e+00 5.19e-34 0.00e+00 1.16e-33 TE-131M 3.61e+05 1.76e+05 2.80e+05 1.79e+06 0.00e+00 1.75e+07 0.00e+00 1.47e+05 GRAND GULF, UNIT 1 2.0-22g Revision 43

TABLE 2.2-2d (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

i Page 10 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m^2 * (mrem/yr)/(uCi/sec) or (mrem/yr)/(uCi/m^3))

AgeGroup: 0 ADULT Pathway: 5 Grs/Cow/Milk (CMILK)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 2.39e+06 1.55e+06 1.71e+06 1.49e+07 0.00e+00 7.32e+07 0.00e+00 1.45e+06 I-130 4.18e+05 1.23e+06 1.05e+08 1.92e+06 0.00e+00 1.06e+06 0.00e+00 4.86e+05 I-131 2.96e+08 4.23e+08 1.39e+11 7.26e+08 0.00e+00 1.12e+08 0.00e+00 2.43e+08 I-132 1.65e-01 4.40e-01 1.54e+01 7.02e-01 0.00e+00 8.27e-02 0.00e+00 1.54e-01 I-133 3.87e+06 6.73e+06 9.88e+08 1.17e+07 0.00e+00 6.04e+06 0.00e+00 2.05e+06 I-134 1.89e-12 5.13e-12 8.89e-11 8.15e-12 0.00e+00 4.47e-15 0.00e+00 1.83e-12 I-135 1.29e+04 3.38e+04 2.23e+06 5.42e+04 0.00e+00 3.82e+04 0.00e+00 1.25e+04 CS-134 5.65e+09 1.35e+10 0.00e+00 4.35e+09 1.45e+09 2.35e+08 0.00e+00 1.10e+10 CS-136 2.63e+08 1.04e+09 0.00e+00 5.78e+08 7.92e+07 1.18e+08 0.00e+00 7.48e+08 CS-137 7.38e+09 1.01e+10 0.00e+00 3.43e+09 1.14e+09 1.95e+08 0.00e+00 6.61e+09 CS-138 8.69e-24 1.72e-23 0.00e+00 1.26e-23 1.25e-24 7.32e-29 0.00e+00 8.50e-24 BA-139 4.43e-08 3.16e-11 0.00e+00 2.95e-11 1.79e-11 7.86e-08 0.00e+00 1.30e-09 BA-140 2.69e+07 3.38e+04 0.00e+00 1.15e+04 1.93e+04 5.54e+07 0.00e+00 1.76e+06 BA-141 4.33e-46 3.27e-49 0.00e+00 3.04e-49 1.86e-49 2.04e-55 0.00e+00 1.46e-47 BA-142 4.41e-81 4.53e-84 0.00e+00 3.83e-84 2.57e-84 0.00e+00 0.00e+00 2.77e-82 LA-140 4.52e+00 2.28e+00 0.00e+00 0.00e+00 0.00e+00 1.67e+05 0.00e+00 6.03e-01 LA-142 1.89e-11 8.60e-12 0.00e+00 0.00e+00 0.00e+00 6.28e-08 0.00e+00 2.14e-12 CE-141 4.84e+03 3.28e+03 0.00e+00 1.52e+03 0.00e+00 1.25e+07 0.00e+00 3.72e+02 CE-143 4.15e+01 3.07e+04 0.00e+00 1.35e+01 0.00e+00 1.15e+06 0.00e+00 3.39e+00 CE-144 3.58e+05 1.50e+05 0.00e+00 8.87e+04 0.00e+00 1.21e+08 0.00e+00 1.92e+04 PR-143 1.58e+02 6.34e+01 0.00e+00 3.66e+01 0.00e+00 6.92e+05 0.00e+00 7.83e+00 PR-144 6.45e-54 2.68e-54 0.00e+00 1.51e-54 0.00e+00 9.28e-61 0.00e+00 3.28e-55 ND-147 9.41e+01 1.09e+02 0.00e+00 6.36e+01 0.00e+00 5.22e+05 0.00e+00 6.51e+00 W-187 6.51e+03 5.45e+03 0.00e+00 0.00e+00 0.00e+00 1.78e+06 0.00e+00 1.90e+03 NP-239 3.67e+00 3.61e-01 0.00e+00 1.13e+00 0.00e+00 7.40e+04 0.00e+00 1.99e-01 3

Units: Inhalation2and all tritium pathways - mrem/yr per µCi/m Others - m . mrem/yr per µCi/sec Values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise indicated.

GRAND GULF, UNIT 1 2.0-22h Revision 43

TABLE 2.2-3 CONTROLLING RECEPTORS, LOCATIONS, AND ATMOSPHERIC DISPERSION PARAMETERS for LCO 6.11.5, 6.11.6, AND 6.11.8 NEAREST NEAREST DAYLIGHT RESIDENCE, GARDEN, ONLY SECTOR DIRECTION MILES** X/Q* D/Q* MILES** D/Q* X/Q***

A N 1.02 8.5E-7 3.8E-9 1.02 3.8E-9 6.60 E-7 B NNE 1.51 3.1E-7 1.5E-9 1.52 1.5E-9 2.70 E-7 C NE 0.70 7.6E-7 5.2E-9 4.14 2.4E-10 4.80 E-8 D ENE 2.60 8.9E-8 4.9E-10 4.50 1.8E-10 3.90 E-8 E E 0.83 5.3E-7 3.1E-9 0.89 2.8E-9 4.90 E-7 F ESE 2.25 8.5E-8 3.8E-10 4.49 1.1E-10 2.70 E-8 G SE 3.72 5.1E-8 2.0E-10 4.20 1.6E-10 3.90 E-8 H SSE 1.10 5.7E-7 3.2E-9 4.31 2.9E-10 5.60 E-8 J S 3.14 1.9E-7 6.5E-10 3.16 6.5E-10 1.30 E-7 K SSW 2.20 7.1E-7 1.4E-9 2.18 1.4E-9 4.10 E-7 L SW 0.89 6.0E-6 7.6E-9 0.89 7.6E-9 2.70 E-6 M WSW >5 N/A N/A >5 N/A N/A N W >5 N/A N/A >5 N/A N/A P WNW >5 N/A N/A >5 N/A N/A Q NW >5 N/A N/A >5 N/A N/A R NNW 1.44 5.4E-7 2.1E-9 >5 N/A 3.90 E-7 Table 2.2-3 locations based on 2016 Land Use Census, onsite vegetation sample locations are not considered for the Land Use Census.

Values from ODCM Reference 19.

- Distances shown are actual miles in each sector. In cases where dispersion and deposition parameters were not available for a location, they were calculated based on values at known distances.

- - Values from ODCM Reference 20.

N/A: No residence/garden within 5 miles.

GRAND GULF, UNIT 1 2.0-23 Revision 43

TABLE 2.2-3a SITE BOUNDARY ATMOSPHERIC DISPERSION PARAMETERS for LCO 6.11.4 SITE BOUNDARY DISTANCE, SECTOR DIRECTION MILES** x/Q* D/Q*

A N 0.79 1.2E-6 5.9E-9 B NNE 0.66 1.1E-6 6.0E-9 C NE 0.63 9.1E-7 6.2E-9 D ENE 0.63 8.5E-7 5.6E-9 E E 0.55 1.0E-6 6.2E-9 F ESE 0.55 8.1E-7 4.2E-9 G SE 0.51 1.2E-6 6.2E-9 H SSE 0.46 2.3E-6 1.4E-8 J S 0.61 2.4E-6 1.1E-8 K SSW 0.65 4.4E-6 1.1E-8 L SW 0.85 6.5E-6 8.2E-9 M WSW 1.07 4.3E-6 4.5E-9 N W 1.14 2.9E-6 3.8E-9 P WNW 1.34 1.4E-6 2.8E-9 Q NW 1.37 8.2E-7 3.0E-9 R NNW 1.02 9.1E-7 3.7E-9

Values from ODCM Reference 19.

- Distances shown are actual miles in each sector.

GRAND GULF, UNIT 1 2.0-23a Revision 43

TABLE 2.2-3b ADDITIONAL RECEPTOR LOCATIONS WITHIN THE SITE BOUNDARY**

For LCO 6.11.4 Unrestricted Daylight SECTOR DIRECTION MILES DESCRIPTION x/Q* D/Q* Area Within Site Only Boundary x/Q***

B NNE 0.5 Recreational 1.7E-6 9.5E-9 Yes NA Vehicle Laydown Area R NNW 0.5 Energy 2.7E-6 1.2E-8 Yes NA Services Center1 Q NW 0.75 Gin Lake1 2.0E-6 8.3E-9 Yes NA P WNW 0.75 Hamilton 3.3E-6 7.5E-9 Yes NA Lake1 J S 0.40 Onsite 4.6E-6 2.2E-8 Yes 3.4E-6 vegetation sample locations H SSE 0.46 Onsite 2.3E-6 1.4E-8 Yes 2.2E-6 vegetation sample location 1These locations occupy multiple sectors. In each case the SITE BOUNDARY locations used in the dose calculation was limiting.

Values from ODCM Reference 19

- The X/Q and D/Q factors from ODCM References 14 and 19 may be used to evaluate dose to members of the public that are located inside the site boundary.

If appropriate, occupancy factors should be applied to the dose calculation.

- - Values from ODCM Reference 20.

GRAND GULF, UNIT 1 2.0-23b Revision 43

2.3 Meteorological Model 2.3.1 Atmospheric Dispersion (Annual Average)

The XOQDOQ software, NUREG/CR-2919, Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations, or similar, should be used to calculate atmospheric dispersion factors for routine continuous long term releases. Software input parameters use the normal settings as described in Table 2.1 of NUREG/CR-2919 with the following exceptions:

Calm values are distributed in a separate windspeed category (i.e., 1st windspeed category) with the same proportion and direction as the direction frequency of the 2nd windspeed class. (Reference 10,14,15)

No terrain recirculation factor is applied. (Reference 5, Section 3A) 0.224 m/sec for calm (Reference 7, 15) 14 windspeed categories are used (Reference 14,15) 7 stability clases, A-G (Reference 10,14,15) 1 release exit point (Reference 10,14,15) 10 meter for measured wind, ground level release (Reference 7, 10, 14, 15)

No decay Normally, maximum windspeed categories are 0.224, 0.5, 0.75, 1.00, 1.25, 1.50, 1.75, 2.00, 2.50, 3.00, 4.00, 5.00, 7.00, 13.00 (m/sec) (Reference 14, 15)

Height of vents release point = 31 meters (Reference 15)

Height of vents building = 53.3 meters (Reference 15)

Minimum cross-sectional area for the vents building =

2729 meters2 (Reference 14, 15)

GRAND GULF, UNIT 1 2.0-24 Revision 43

2.3.2 Atmospheric Dispersion (Hourly Average)

The atmospheric dispersion for gaseous releases may be calculated using a ground level, wake-split form of the straight line flow model.

X/Q = atmospheric dispersion (sec/m³)

2.03 k ru where:

r = distance (m) from release point to location of interest

= plume depletion factor at distance r from ODCM Figure 2.3-1 u = hourly average wind speed at ground level (m/sec) k = open terrain recirculation factor at distance r,

from ODCM Reference 16 1/2 1/2

= the lesser of (² + b²/2) or (3) where:

= vertical standard deviation (m) of the plume at distance r for ground level releases under the stability category indicated by T, from ODCM Figure 2.3-2 T = temperature differential with vertical separation (F/40m) b = height of the reactor building = 53.3m GRAND GULF, UNIT 1 2.0-25 Revision 43

2.3.3 Deposition (Hourly Average)

Relative deposition per unit area for all releases is calculated for a ground level release as follows:

-2 D/Q = relative deposition per unit area (m )

= (2.55 x Dg x K)/r where:

D = relative deposition rate at distance r for ground g

level releases from ODCM Figure 2.3-3 k = open Terrain Recirc Factor (ODCM Reference 16) r = distance from release point (meters)

Additional information on the X/Q and D/Q calculations can be found in ODCM References 9 and 10.

GRAND GULF, UNIT 1 2.0-26 Revision 43

"TEXT DELETED" GRAND GULF, UNIT 1 2.0-27 Revision 43

"TEXT DELETED" GRAND GULF, UNIT 1 2.0-28 Revision 43

"TEXT DELETED" GRAND GULF, UNIT 1 2.0-29 Revision 43

"TEXT DELETED" GRAND GULF, UNIT 1 2.0-30 Revision 43

Revision 43 1.0

-... I'-- ....

Figure 2.3-1

,0.9:

~

r-,-.......

w ~

E 0.8 ~~

, ~

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CL

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z 0.7 2.0-31 CJ

-<z-z Plume Depletion Effect for Ground-Level Releases 0.6

E

~

w ~ "'-

a:: 0.5 z '--

0 6< ~--- .

~

0.4 a:

(All Atmospheric Stability Classes) u.

0.3 0.2 GRAND GULF, UNIT 1 0.1 0.1' 1,0- 10.0 100.0 200.0 PLUM.E TRAVEL DISTANCE {KJLOMETERS)*

Figure 2.3-2 Vertical Standard Deviation of Material in a Plume (Letters denote Pasquill Stability Class)

I I I I I

I I I I I V j I /

,I' Av I

V V

/

I

,, /

I I

/ ,, C, D,, ./

~

a:

/ V /'

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- ~

I

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,_,'fl'

/ / ;' L/

,/ / V

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V 1~ 10 100 PLUME TRAVEL DISTANCE (KILOMETERS) r.,PLDME'UU.YU. O I S ' l " A N C £ ~

> ~u, ,..a s ~l.2Z! B - .... *_

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> ..:a.n:..a s-i a C . :~ *~ , I

> -J- aail ~ ,<<36__ :D

.... ~ . . .**,S:1.8111 E

> 1.-..*s:z.a,

>1.U G . l.

GRAND GULF, UNIT 1 2.0-32 Revision 43

Figure 2.3-3 Relative Deposition for Ground-Level Releases (All Atmospheric Stability Classes) r-,.....

~

~~

~

""~

~

,.0 ,o.o 100.0 200.0 r, PLUME TRAVEL DISTANCE (KILOMETERS)

Graph takett from Reference 7. F"11!11tt 6 GRAND GULF, UNIT 1 2.0-33 Revision 43

Deleted GRAND GULF, UNIT 1 2.0-34 Revision 43

2.5 Gaseous Radwaste Treatment System The instruments required to be checked by LCO 6.11.7 to ensure that the GASEOUS RADWASTE TREATMENT (Offgas) SYSTEM is functioning are:

1. Adsorber train bypass switch (1N64-HS-M611)

2. Bypass valve indication (1N64-F045)

When the adsorber train bypass switch is in the TREAT position and the bypass valve indicates closed, the GASEOUS RADWASTE TREATMENT (Offgas) SYSTEM is functioning.

NOTES for ODCM Figure 2.5-1 A flow diagram for the Gaseous Radwaste Treatment System is provided on the following page. Notes for the diagram are listed below.

(1) The charcoal beds are bypassed during startup until an adequate dewpoint is obtained in the process stream.

(2) This pathway may be utilized for power levels 5%.

(3) Standby Gas Treatment System not normally operated.

(4) In modes 1, 2 and 3, the south-east most smoke hatch of the turbine building may be used as an occasional release point provided that the proper monitoring equipment is used. During Modes 4 & 5 up to four roof hatches may be used and release rates estimated based on calculated flow rates and measured activity.

GRAND GULF, UNIT 1 2.0-35 Revision 43

Figure 2.5-1 Gaseous Radwaste Treatment System GRAND GULF, UNIT 1 2.0-35a Revision 43

2.6 Annual Dose Commitment If required, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC will be calculated by summing the following doses for the calendar year:

Direct radiation dose

Liquid effluent dose (D )

Tau

Noble gas dose (D , D )

Particulate dose (D )

p These calculations are required only if the liquid or gaseous effluents exceed twice the limits of LCOs 6.11.2, 6.11.5 and 6.11.6.

2.6.1 Direct Radiation Dose Measurement LCOs 6.11.2, 6.11.5 and 6.11.6 require the determination of cumulative dose contributions to a MEMBER OF THE PUBLIC from direct radiation from the reactor units and from radwaste storage tanks. This requirement is applicable only under conditions set forth in Action B.1 of the applicable LCO.

This determination is made by the utilization of direct radiation measurements from indicator thermoluminescent dosimeters (TLDs) located near the GGNS property line.

GRAND GULF, UNIT 1 2.0-36 Revision 43

Measurements from these TLDs represent the direct radiation generated by the facility plus normal background radiation.

The locations are identified in ODCM Table 3.0-3 by the following TLD numbers:

M-16 M-22 M-23 M-97 M-100 M-19 M-25 M-95 M-98 M-21 M-28 M-96 M-99 Control TLDs are also utilized to differentiate between background radiation and direct radiation from the facility.

The following two TLDs are designated as controls based on the criterion that they are located ten miles or greater from the facility. Exact locations are identified in ODCM Table 3.0-3.

M-14 M-33 The difference between the averaged quarterly radiation measurements of the indicator TLDs and the control TLDs represents the direct radiation dose to a MEMBER OF THE PUBLIC from the operating facility.

GRAND GULF, UNIT 1 2.0-37 Revision 43

3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 3.1 Sampling Locations Sampling locations to fulfill the requirements of LCO 6.12.1, as described in ODCM Table 6.12.1-1, are identified in ODCM Tables 3.0-1 through 3.0-3 and shown on maps in ODCM Figures 3.0-1 and 3.0-2.

GRAND GULF, UNIT 1 3.0-1 Revision 43

ODCM TABLE 3.0-1 AIR SAMPLER COLLECTION SITES AIR SAMPLERS NUMBER FIGURE LOCATION AS-1 PG 3.0-2 Southeast of GGNS at the Port Gibson City Barn (Sector G Radius, 5.5 miles)

AS-3 61VA 3.0-2 NNE of GGNS on Hwy. 61, north of the Vicksburg Airport (Sector B Radius, 18 miles)

AS-7 UH 3.0-1 SSE of GGNS at the IBEW Union Hall (Sector H Radius, 0.5 miles)

AS-20 GR 3.0-1 SSE of GGNS at the Former Glodjo residence (Sector L, Radius 0.9 miles)

GRAND GULF, UNIT 1 3.0-2 Revision 43

ODCM TABLE 3.0-2 MISCELLANEOUS COLLECTION SITES Page 1 of 2 MILK SAMPLES (CONTROL LOCATION) FIGURE ALCONT 3.0-2 Located SSW of GGNS at Alcorn State University (Sector K Radius 10.5 miles)

GROUND WATER PGWELL 3.0-2 PORT GIBSON WELLS - Taken from distribution system or one of the five wells (Sector G Radius 5.0 miles)

Construction Water Well 3.0-1 GGNS CONSTRUCTION WATER WELL -

Taken from distribution system or the well (Sector Q Radius 0.4 miles)

SURFACE WATER Upstream 3.0-1 At least 4500 ft upstream of the GGNS discharge point into the Mississippi River to allow adequate mixing of the Mississippi and Big Black Rivers (Sector R, 1.8 miles)

Downstream 3.0-1 At least 5000 ft downstream of the GGNS discharge point into the Mississippi River near Radial Well No. 1 (Sector N, 1.6 miles)

MS River Downstream 3.0-1 Downstream of the GGNS discharge point (during a liquid radwaste discharge) in the Mississippi River near Radial Well No. 5 (Sector P, 1.3 miles)

Storm Drain Outfall 007 3.0-1 Outfall 007 (Sector N, 0.2 miles)

GRAND GULF, UNIT 1 3.0-3 Revision 43

ODCM TABLE 3.0-2 (Continued)

MISCELLANEOUS COLLECTION SITES Page 2 of 2 SEDIMENT SAMPLES FIGURE SEDHAM 3.0-1 Downstream of the GGNS discharge point in the Mississippi River near Hamilton Lake outlet (Sector N, 1.6 miles)

SEDCONT 3.0-1 Upstream of the GGNS discharge point in the Mississippi River (Minimum of 100 yds)

VEGETATION Broadleaf Vegetation 3.0-1 S of GGNS near former Training Center on Bald Hill Road (Sector J, 0.4 miles)

OR SSE of GGNS near former Training Center on Bald Hill Road (Sector H, 0.46 miles)

NOTE: The above location is located inside the SITE BOUNDARY. The sampling site exceeds the requirements of LCO 6.12.1.

3.0-2 Alcorn State University SSW of GGNS (Sector K, 10.5 miles) any alternate location 15-30 km distant may be used.

FISH SAMPLES Fish and Invertebrates 3.0-1 Downstream of the GGNS discharge point into the Mississippi River 3.0-1 Upstream of the GGNS discharge point into the Mississippi River uninfluenced by plant operations GRAND GULF, UNIT 1 3.0-3a Revision 43

ODCM TABLE 3.0-3 TLD LOCATIONS Page 1 of 2 TLD NO. LOCATION FIGURE SECTOR MILE M-01 Across the road from Lake 3.0-1 E 3.5 Claiborne entry gate M-07 AS-1 PG, Port Gibson City Barn 3.0-2 G 5.5 M-09 Warner Tully Y-Camp 3.0-1 D 3.5 M-10 Grand Gulf Military Park 3.0-1 A 1.5 M-14 AS-3-61VA, Hwy. 61, north of 3.0-2 B 18.0 (CONTROL) Vicksburg Airport M-16 Meteorological Tower 3.0-1 A 0.9 M-19 Eastern SITE BOUNDARY 3.0-1 E 0.5 property line, NNE of HWSA M-21 Near former Training Center 3.0-1 J 0.4 Building, on Bald Hill Road M-22 Former RR entrance crossing on 3.0-1 G 0.5 Bald Hill Road M-23 Gin Lake Road 50 yards north of 3.0-1 Q 0.5 Heavy Haul Road on power pole M-25 Radial Well Number 1 3.0-1 N 1.6 M-28 Former Glodjo residence 3.0-1 L 0.9 M-33 Newellton, Louisiana, Water 3.0-2 P 12.5 Tower M-36 Curve on HW 608, point nearest 3.0-2 P 5.0 GGNS at power pole M-38 Lake Bruin State Park, entrance road 3.0-2 M 9.5 M-39 St. Joseph, Louisiana, Aux. 3.0-2 M 13.0 Water Tank M-40 Headley Drive, near River 3.0-1 M 2.3 Port entrance GRAND GULF, UNIT 1 3.0-4 Revision 43

ODCM TABLE 3.0-3 (Continued)

TLD LOCATIONS Page 2 of 2 TLD NO. LOCATION FIGURE SECTOR MILE M-48 0.4 miles South on Mont Gomer 3.0-2 K 4.8 Road on west side M-49 Fork in Bessie Weathers Road/ 3.0-2 H 4.5 Shaifer Road M-50 Panola Hunting Club entrance 3.0-2 B 5.3 M-55 Near Ingelside Karnac Ferry Road/ 3.0-2 D 5.0 Ashland Road Intersection M-57 Hwy. 61, behind the Welcome 3.0-2 F 4.5 to Port Gibson sign at Glensdale Subdivision M-94 Sector R near 3.0-1 R 0.8 Meterological tower M-95 Spoils Area, fence of old storage 3.0-1 F 0.5 area, near entrance gate M-96 North Gate fence 3.0-1 B 0.7 M-97 Grand Gulf Road entrance gate 3.0-1 D 0.8 to spoils area M-98 Bald Hill Road, across from 3.0-1 H 0.5 Union Hall, in curve M-99 North Fence of old Ball Field 3.0-1 K 0.4 Near utility pole M-100 Grand Gulf Road, across from 3.0-1 C 0.6 L. Frazier GRAND GULF, UNIT 1 3.0-5 Revision 43

"TEXT DELETED" GRAND GULF, UNIT 1 3.0-6 Revision 43

FIGURE 3.0-1 Collection Site Locations 0- 4 Mile Area Map LEGEND

.p Fish D Air Sampler 0 Surface Water Ground Water 8 Broadleaf Vegetation Sediment 0 TLD Ranney Wells Milk ENTERGY GRANO GULF NUCLEAR S1Al\ON 0-4 Mile Environmental Sampling Location Map

- -c~-

SCALf IN MI LES Granrl Gull , un;, J 0--7 Revis,on JS 09{)7

Figure 3.0-2 Collection Site Locations, General Area Map, 4-10 Mile Area Map R A B (NNE)

FIGURE 3.0-2 (NNW)

Collection Site Locations, General Area Map C 4-10 Mile Area Map LEGEND O ,.;,sampler 0 Surface Water A

D [:]

Ground Water Broadleaf Vegetation

Seolment 0 TLD

f

. Ranney Wells Milk See N Figure E 3.0-1 (E) 18 MILES FROM GRAND GULF 10 F

VICKSBURG AIRPORT Secto, (B)

(ESE)

G (SE)

ENTERGY GRAND GULF NUCLEAR STATION L 4-10 Mile Environmental

~

{SSW)

H (SSE) w Sampling Location Map Grand Gulf, Unit 1 3.0-S Revision 35 09-07 (SJ GRAND GULF, UNIT 1 3.0-8 Revision 43

OFFSITE DOSE CALCULATION MANUAL APPENDIX A RADIOLOGICAL EFFLUENT CONTROLS AND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMS GRAND GULF, UNIT 1 A-0 Revision 43

"TEXT DELETED" GRAND GULF, UNIT 1 A-1 Revision 43

1.0 DEFINITIONS GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM 1.1 The GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM is the system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

MEMBER(S) OF THE PUBLIC 1.2 MEMBER(S) OF THE PUBLIC shall include individuals in a controlled or unrestricted area. However, an individual is not a member of the public during any period in which the individual receives an occupational dose.

OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.3 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification 5.5.4 and Technical Requirement 7.6.3.2 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Technical Specifications 5.6.2 and 5.6.3.

PROCESS CONTROL PROGRAM (PCP) 1.4 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

GRAND GULF, UNIT 1 A-2 Revision 43

SITE BOUNDARY 1.5 The SITE BOUNDARY shall be that line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee.

UNRESTRICTED AREA 1.6 An UNRESTRICTED AREA shall be any area, at or beyond the SITE BOUNDARY, access to which is not controlled by the licensee for the purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial commercial, institutional, and/or recreational purposes. The UNRESTRICTED AREA and SITE BOUNDARY are synonymous with the exception of areas over bodies of water.

VENTILATION EXHAUST TREATMENT SYSTEM 1.7 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

Additional Definitions are listed in Technical Specification Section 1.1.

GRAND GULF, UNIT 1 A-3 Revision 43

TABLE 1.1 SURVEILLANCE FREQUENCY NOTATION Surveillance Frequencies are specified in individual LCOs. For more information see Technical Specification Section 1.4.

GRAND GULF, UNIT 1 A-4 Revision 43

TABLE 1.2 MODES Modes of operation are shown in Technical Specification Table 1.1-1 GRAND GULF, UNIT 1 A-5 Revision 43

3.0 APPLICABILITY LIMITING CONDITION FOR OPERATION (LCO)

See Technical Specification Section 3.0 for LCO Applicability.

GRAND GULF, UNIT 1 A-6 Revision 43

APPLICABILITY SURVEILLANCE REQUIREMENTS (SR)

See Technical Specification Section 3.0 for SR applicability.

GRAND GULF, UNIT 1 A-7 Revision 43

SECTION 5.0 ADMINISTRATIVE CONTROLS GRAND GULF, UNIT 1 A-8 Revision 43

5.0 ADMINISTRATIVE CONTROLS 5.6.2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

The annual radiological environmental operating reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by LCO 6.12.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include summarized and tabulated results in the format of the Table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979 of all radiological environmental samples taken during the report period. Deviations from the sampling program identified in LCO 6.12.1 shall be reported. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following:

1) a summary description of the radiological environmental monitoring program;

2) a map of all sampling locations keyed to a table giving distances and directions from one reactor;

3) and the results of licensee (or offsite laboratory's) participation in the Interlaboratory Comparison Program, required by LCO 6.12.1.

GRAND GULF, UNIT 1 A-9 Revision 43

5.0 ADMINISTRATIVE CONTROLS 5.6.3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT A Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted before May 1 of each year.

a. The Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The Radioactive Effluent Release Report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.* This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the reporting period. All assumptions used in making these assessments, i.e.,

specific activity, exposure time, and location, shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement or historical annual average meteorological conditions, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

The Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev 1, October 1977 and NUREG - 0133.

The Radioactive Effluent Release Report shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Radioactive Effluent Release Report shall include any changes made during the reporting period to the OFFSITE DOSE CALCULATION MANUAL (ODCM), pursuant to Technical Specification 5.5.1, as well as any major change to Liquid, Gaseous, or Solid Radwaste Treatment Systems. It shall also include a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to LCO 6.12.2.

In lieu of submission with the Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meterological data onsite in a file that shall be provided to the NRC on request.

GRAND GULF, UNIT 1 A-10 Revision 43

5.0 ADMINISTRATIVE CONTROLS CONTROLS 5.6.3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)

The Radioactive Effluent Release Report shall also include the following:

an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in LCOs 6.3.9 or 6.3.10, and description of the events leading to liquid holdup tanks exceeding the limits of Technical Specification 5.5.8.b.

b. Major changes to the Radioactive Waste Treatment System (liquid, gaseous and solid**) shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the OSRC.

(1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; (2) Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; (3) A detailed description of the equipment, components and processed involved and the interfaces with other plant systems; (4) An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto; (5) An evaluation of the change which shows the expected maximum exposures to MEMBERS OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto; (6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period before when the changes are to be made; (7) An estimate of the exposure to plant operating personnel as a result of the change; and (8) Documentation of the fact that the change was reviewed and found acceptable by the OSRC.

- The information called for in this Specification may be submitted as part of the next UFSAR update.

GRAND GULF, UNIT 1 A-11 Revision 43

5.0 ADMINISTRATIVE CONTROLS 5.6.3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)

c. The Radioactive Effluent Release Report shall also include a summary of the quantities of radioactive solid waste released from the unit as outlined in Regulatory Guide 1.21, Measuring, Evaluating, and Report Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, Revision 1, June 1974, with data summarized following the format of Appendix B and Table 3.

The following information for each type of solid waste shipped off-site will be included in the report:

(1) The total quantity in cubic meters and the total radioactivity in curies for the categories or types of waste.

(a) Spent resins, filter sludges, evaporator bottoms (b) Dry compressible waste, contaminated equipment, etc.

(c) Irradiated components, control rods, etc.

(d) Other (furnish description)

(2) An estimate of the major nuclide composition in the categories of waste in 5.6.3.c(1),

(3) The disposition of solid waste shipments, identifying the number of shipments, the mode of transport, and the destination.

(4) The disposition of irradiated fuel shipments, identifying the number of shipments, the mode of transport, and the destination.

Estimates of the total error associated with certain total values should be provided in each report. These error values should be the best effort of and overall estimate of the errors associated with the totals in the report.

GRAND GULF, UNIT 1 A-11a Revision 43

SECTION 6.0 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS GRAND GULF, UNIT 1 A-12 Revision 43

6.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 6.0.1 When a Technical Specification (if LCO 3.0.3 is not applicable) or an Offsite Dose Calculation Manual LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the following actions shall be taken:

1. Develop and implement compensatory actions as needed.

2. Verify that a required safety function is not compromised by the inoperabilities.

3. Develop a plan for exiting LCO 6.0.1.

4. Obtain Duty Manager approval of the compensatory actions and a plan for exiting LCO 6.0.1 within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 6.0.1 is not required.

LCO 6.0.1 is always applicable to Offsite Dose Calculation Manual LCOs and only applicable to Technical Specification LCOs if LCO 3.0.3 is not applicable.

LCO 6.0.1 is not to be voluntarily entered and actions to exit LCO 6.0.1 must be pursued without delay and in a controlled manner.

GRAND GULF, UNIT 1 A-12a Revision 43

6.3 INSTRUMENTATION 6.3.9 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LCO 6.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 6.3.9-1 shall be FUNCTIONAL with required alarm/trip setpoints set to ensure that the limits of LCO 6.11.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: At all times.

ACTIONS

NOTES--------------------------------------

1. Separate Condition entry is allowed for each Channel.

2. The provisions of LCO 3.0.3 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Suspend release of Immediately channels nonfunctional. radioactive effluent via affected pathway.

OR

NOTES-----------

Once required Action A.2 is entered the Completion Time for Condition B or C can not be restarted by reentering Required Action A.1.

A.2 Enter the Condition Immediately referenced in Table 6.3.9-1 for the channel.

(continued)

GRAND GULF, UNIT 1 A-13 Revision 43

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. As required by Required B.1 At least two independent Prior to each Action A.2 and referenced samples are analyzed in release.

in Table 6.3.9-1. accordance with LCO 6.11.1.

AND B.2 At least two technically Prior to each qualified members of the release.

Facility Staff independently verify the release rate calculations and discharge path valve line-up.

AND B.3 Restore channel to 14 days FUNCTIONAL.

C. As required by Required C.1 Estimate the flow rate for Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Action A.2 and referenced the affected pathway during in Table 6.3.9-1. actual releases. Pump curves or discharge canal flow monitor may be used to estimate flow.

AND 30 days C.2 Restore channel to FUNCTIONAL.

D. Required Action and D.1 Suspend release of Immediately associated Completion Time radioactive effluent via of Condition B not met. affected pathway.

AND Immediately D.2 Initiate action to explain why this nonfunctionality was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report.

GRAND GULF, UNIT 1 A-13a Revision 43

ACTIONS (continued)

E. Required Action and E.1 Initiate action to explain Immediately associated Completion Time why this nonfunctionality was of Condition C not met. not corrected in a timely manner in the next Annual Radioactive Effluent Release Report.

GRAND GULF, UNIT 1 A-13b Revision 43

SURVEILLANCE REQUIREMENTS

NOTES--------------------------------------

Refer to Table 6.3.9-1 to determine which SRs apply to each channel.

SURVEILLANCE FREQUENCY SR 6.3.9.1 -----------------------NOTE-----------------------

For flow rate measurement devices a CHANNEL CHECK 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months shall consist of verifying indication of flow during periods of release. A CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days which batch releases are made.

Perform CHANNEL CHECK.

SR 6.3.9.2 Perform a source check, a qualitative assessment Prior to each of channel response when the channel sensor is release.

exposed to a radioactive source.

SR 6.3.9.3 -----------------------NOTE-----------------------

The CHANNEL FUNCTIONAL TEST shall also demonstrate 92 days that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure.

4. Instrument controls not set in operate mode.

Perform CHANNEL FUNCTIONAL TEST.

(continued)

GRAND GULF, UNIT 1 A-14 Revision 43

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 6.3.9.4 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 6.3.9.5 -----------------------NOTE-----------------------

The initial CHANNEL CALIBRATION shall be performed 12 months using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

Perform a CHANNEL CALIBRATION.

SR 6.3.9.6 Perform a CHANNEL CALIBRATION 18 months GRAND GULF, UNIT 1 A-14a Revision 43

TABLE 6.3.9-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONDITIONS REFERENCED MINIMUM FROM CHANNELS REQUIRED SURVEILLANCE INSTRUMENT FUNCTIONAL ACTION A.2 REQUIREMENTS

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line 1 B SR 6.3.9.1 SR 6.3.9.2 SR 6.3.9.3 SR 6.3.9.5

2. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line 1 C SR 6.3.9.1 SR 6.3.9.4 SR 6.3.9.6

b. Circulating Water Blowdown 1 C SR 6.3.9.1 SR 6.3.9.4 SR 6.3.9.6 GRAND GULF, UNIT 1 A-15 Revision 43

6.3 INSTRUMENTATION 6.3.10 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LCO 6.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 6.3.10-1 shall be FUNCTIONAL with their alarm/trip setpoints set to ensure that the limits of LCO 6.11.4 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: As shown in Table 6.3.10-1 ACTIONS

NOTES--------------------------------------

1. Separate Condition entry is allowed for each Channel.

2. The provisions of Specification 3.0.3 and LCO 3.0.4 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Suspend release of Immediately channels nonfunctional. radioactive effluent via affected pathway.

OR

NOTES------------

Once required Action A.2 is entered the Completion Time for Condition Referenced on Table 6.3.10-1 can not be restarted by reentering Required Action A.1.

A.2 Enter the Condition Immediately referenced in Table 6.3.10-1 for the channel.

(continued)

GRAND GULF, UNIT 1 A-16 Revision 43

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. As required by Required B.1 Take grab samples during Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Action A.2 and referenced release.

in Table 6.3.10-1.

AND B.2 Analyze the above required Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of samples for gross taking the sample activity.

AND 30 days B.3 Restore channel to FUNCTIONAL.

C. As required by Required C.1 Establish an alternate Immediately Action A.2 and referenced means to collect samples in Table 6.3.10-1. required by Table 6.11.4-1.

AND C.2 Enter Condition D for the Immediately alternate sample established in C.1.

AND C.3 Restore channel to FUNCTIONAL. 30 days D. As required by Required D.1 Estimate flow rate. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Action A.2 and referenced in Table 6.3.10-1 or AND Required Action C.2.

D.2 Restore channel to 30 days FUNCTIONAL.

(continued)

GRAND GULF, UNIT 1 A-17 Revision 43

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 Place the nonfunctional 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action A.2 and referenced channel in downscale trip.

in Table 6.3.10-1.

OR

NOTE------------

With both required monitors nonfunctional take Required Actions E.2.

E.2.1 Take grab samples during Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months release.

AND E.2.2 Analyze the above Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of required samples for taking the sample gross activity.

AND E.2.3 Restore channel to 30 days FUNCTIONAL.

GRAND GULF, UNIT 1 A-18 Revision 43

ACTIONS (continued)

F. As required by Required F.1 Verify the offgas system is Immediately Action A.2 and referenced not bypassed, except for in Table 6.3.10-1. filtration system bypass during plant startups.

AND F.2 Verify by administrative Immediately means that the charcoal vault radiation monitor and the main steam line radiation monitors are FUNCTIONAL.

AND F.3.1 Take grab samples and Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and analyze. once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

OR F.3.2 Verify an installed Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months portable radiation monitor on the offgas pre-treatment line is capable of detecting a 50% change in radiation level and record the value.

AND F.4 Restore channel to 30 days FUNCTIONAL.

(continued)

GRAND GULF, UNIT 1 A-19 Revision 43

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. As required by Required G.1 Take grab samples during Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Action A.2 and referenced release.

in Table 6.3.10-1.

AND G.2 Analyze the above required Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of samples for gross taking the sample activity.

AND 30 days G.3 Restore channel to FUNCTIONAL.

H. Required Actions and H.1 Suspend release of Immediately associated Completion radioactive effluent via Times of Condition B,C,D,E this pathway.

or G not met.

AND H.2 Initiate action to explain Immediately why this nonfunctionality was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report.

I. Required Action and I.1 Enter LCO 6.0.1 Immediately associated Completion Time of Condition F not met.

GRAND GULF, UNIT 1 A-20 Revision 43

SURVEILLANCE REQUIREMENTS

NOTES-----------------------------------------

1. Refer to Table 6.3.10-1 to determine which SRs apply to each channel.

2. When a monitor is placed in an nonfunctional status solely for performance of required Surveillances, entry into associated Conditions and Required Actions in accordance with LCO 6.3.10 may be delayed for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

SURVEILLANCE FREQUENCY SR 6.3.10.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 6.3.10.2 Perform CHANNEL CHECK. 7 days SR 6.3.10.3 -----------------------NOTE-----------------------

1. Not required to be performed in MODES 1 and 2 for the offgas pre-treatment monitor if inaccessible due to a high radiation area.

2. Not required to be performed for the offgas pretreatment monitor when entering MODES 3 and 4 from MODES 1 or 2 until 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after entering MODE 3 or 4 if monitor was inaccessible due to a high radiation area.

Perform SOURCE CHECK , a qualitative assessment of channel response when the channel sensor is 31 days exposed to a radioactive source.

SR 6.3.10.4 -----------------------NOTE-----------------------

The CHANNEL FUNCTIONAL TEST shall also demonstrate the automatic isolation capability of the instrumentation for this pathway and the control room alarm annunciation capability, if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure.

4. Instrument controls not set in operate mode.

92 days Perform CHANNEL FUNCTIONAL TEST.

(continued)

GRAND GULF, UNIT 1 A-21 Revision 43

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 6.3.10.5 -----------------------NOTE-----------------------

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occur if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure.

4. For SGTS A radioactivity monitoring, Instrument Controls not set in operate mode.

For SGTS B radioactivity monitoring, in 92 days deferred. For all other equipment, Instrument Controls not set in operate mode.

Perform CHANNEL FUNCTIONAL TEST.

SR 6.3.10.6 -----------------------NOTE-----------------------

Compare the measured flow rate to the expected design flow rate for existing plant conditions.

Perform CHANNEL FUNCTIONAL TEST.

92 days GRAND GULF, UNIT 1 A-22 Revision 43

SR 6.3.10.7 -----------------------NOTE-----------------------

1. The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

2. The offgas pre-treatment and offgas post-treatment sensors will be calibrated for mr/hr or cpm from the calibration standard. The conversion to release rate will be performed during subsequent unit operation, but within one week.

12 months Perform a CHANNEL CALIBRATION.

GRAND GULF, UNIT 1 A-22 Revision 43

SR 6.3.10.8 -----------------------NOTE-----------------------

1. The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

Perform a CHANNEL CALIBRATION 18 months GRAND GULF, UNIT 1 A-23 Revision 43

TABLE 6.3.10-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONDITIONS REFERENCED FROM MINIMUM CHANNELS REQUIRED SURVEILLANCE INSTRUMENT OPERABLE APPLICABILITY ACTION A.2 REQUIREMENTS

1. RADWASTE BUILDING VENTILATION MONITORING SYSTEM

a. Noble Gas Activity Monitor Providing Alarm 1 (a) B SR 6.3.10.1 SR 6.3.10.3 SR 6.3.10.5 SR 6.3.10.7

b. Iodine Sampler 1 (a) C SR 6.3.10.2

c. Particulate Sampler 1 (a) C SR 6.3.10.2

d. Effluent System Flow Rate Measuring Device 1 (a) D SR 6.3.10.1 SR 6.3.10.8

e. Sampler Flow Rate Measuring Device 1 (a) D SR 6.3.10.1 SR 6.3.10.8

2. CONTAINMENT VENTILATION MONITORING SYSTEM

a. Noble Gas Activity Monitor Providing Alarm 1 (a) B SR 6.3.10.1 SR 6.3.10.3 SR 6.3.10.5 SR 6.3.10.7 GRAND GULF, UNIT 1 A-24 Revision 43

TABLE 6.3.10-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONDITIONS REFERENCED FROM MINIMUM CHANNELS REQUIRED SURVEILLANCE INSTRUMENT FUNCTIONAL APPLICABILITY ACTION A.2 REQUIREMENTS

b. Iodine Sampler 1 (a) C SR 6.3.10.2

c. Particulate Sampler 1 (a) C SR 6.3.10.2

d. Effluent System Flow Rate

1. High Volume Flow Device 1 (d) D SR 6.3.10.1 SR 6.3.10.8

2. Low Volume Flow Device 1 (e) D SR 6.3.10.1 SR 6.3.10.6 SR 6.3.10.8

e. Sampler Flow Rate 1 (a) D SR 6.3.10.1 Measuring Device SR 6.3.10.8 3A. TURBINE BLDG. VENTILATION MONITORING SYSTEM

a. Noble Gas Activity 1 (a) B SR 6.3.10.1 Providing Alarm SR 6.3.10.3 SR 6.3.10.5 SR 6.3.10.7

b. Iodine Sampler 1 (a) C SR 6.3.10.2

c. Particulate Sampler 1 (a) C SR 6.3.10.2

d. Effluent System Flow Rate 1 (a) D SR 6.3.10.1 Measuring Device SR 6.3.10.8

e. Sampler Flow Rate 1 (a) D SR 6.3.10.1 Measuring Device SR 6.3.10.8 GRAND GULF, UNIT 1 A-25 Revision 43

TABLE 6.3.10-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONDITIONS REFERENCED FROM MINIMUM CHANNELS REQUIRED SURVEILLANCE INSTRUMENT FUNCTIONAL APPLICABILITY ACTION A.2 REQUIREMENTS 3B. TURBINE BUILDING OCCASIONAL RELEASE POINT MONITORING SYSTEM

a. Noble Gas Activity 1 (f)(h)(i) Immediately SR 6.3.10.1(g)

Providing Alarm isolate SR 6.3.10.3(g)

SR 6.3.10.5(g)

SR 6.3.10.7(g)

b. Iodine Sampler 1 (f) (h)(i) Immediately SR 6.3.10.2(g) isolate

c. Particulate Sampler 1 (f) (h)(i) Immediately SR 6.3.10.2(g) isolate

d. Effluent System Flow Rate 1 (f) (h)(i) Immediately SR 6.3.10.1(g)

Measuring Device isolate SR 6.3.10.6(g)

SR 6.3.10.8(g)

e. Sampler Flow Rate 1 (f) (h)(i) Immediately SR 6.3.10.1(g)

Measuring Device isolate SR 6.3.10.8(g)

4. FUEL HANDLING AREA VENTILATION MONITORING SYSTEM

a. Noble Gas Activity 1 (a) B SR 6.3.10.1 Providing Alarm SR 6.3.10.3 SR 6.3.10.5 SR 6.3.10.7

b. Iodine Sampler 1 (a) C SR 6.3.10.2

c. Particulate Sampler 1 (a) C SR 6.3.10.2

d. Effluent Flow Rate 1 (a) D SR 6.3.10.1 Measuring Device SR 6.3.10.8

e. Sampler Flow Rate 1 (a) D SR 6.3.10.1 Measuring Device SR 6.3.10.8 GRAND GULF, UNIT 1 A-26 Revision 43

TABLE 6.3.10-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONDITIONS REFERENCED FROM MINIMUM CHANNELS REQUIRED SURVEILLANCE INSTRUMENT FUNCTIONAL APPLICABILITY ACTION A.2 REQUIREMENTS

5. OFFGAS PRE-TREATMENT MONITOR

a. Noble Gas Activity Monitor 1 (c) F SR 6.3.10.1 Providing Alarm SR 6.3.10.3 SR 6.3.10.5 SR 6.3.10.7

6. OFFGAS POST-TREATMENT MONITOR

a. Noble Gas Activity Monitor Providing 2 (b) E SR 6.3.10.1 Alarm and Automatic Termination of SR 6.3.10.3 Release SR 6.3.10.4 SR 6.3.10.7

7. STANDBY GAS TREATMENT EXHAUST MONITORING SYSTEM (A)

a. Noble Gas Activity Monitor 1/system (a) G SR 6.3.10.1 Providing Alarm SR 6.3.10.3 SR 6.3.10.5 SR 6.3.10.7

8. STANDBY GAS TREATMENT EXHAUST MONITORING SYSTEM (B)

a. Noble Gas Activity Monitor 1/system (a) G SR 6.3.10.1 Providing Alarm SR 6.3.10.3 SR 6.3.10.5 SR 6.3.10.8 GRAND GULF, UNIT 1 A-27 Revision 43

TABLE 6.3.10-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION (a) At all times.

(b) During main condenser offgas treatment system operation.

(c) When any steam jet air ejector (SJAE) is in operation.

(d) During containment high volume purge.

(e) During containment low volume purge.

(f) In modes 1, 2 and 3, when in service.

(g) Prior to each use and at the specified frequency.

(h) When in modes 4, & 5, UP TO 4 Turbine roof hatches may be open as long as the radionuclide concentrations are 30% of the ODCM dose limits in 6.11.4 and 6.11.6.

(i) When in modes 4 and 5, this monitoring instrumentation is not required.

GRAND GULF, UNIT 1 A-28 Revision 43

6.11 RADIOACTIVE EFFLUENTS 6.11.1 LIQUID EFFLUENTS CONCENTRATION LCO 6.11.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to ten times the effluent concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 microcuries/ml total activity.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The concentration of A.1 Restore the concentration Immediately radioactive material to within the above limits.

released in liquid effluents to UNRESTRICTED AND AREAS exceeds the above limits. A.2 Declare the liquid effluent waste treatment system nonfunctional.

GRAND GULF, UNIT 1 A-29 Revision 43

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.11.1.1 The radioactivity content of each batch of Per (ODCM) radioactive liquid waste shall be determined Table 6.11.1-1.

before release by sampling and analysis in accord-ance with (ODCM)Table 6.11.1-1.

SR 6.11.1.2 Post-release analyses of samples composited from Per (ODCM) batch releases shall be performed in accordance Table 6.11.1-1.

with (ODCM)Table 6.11.1-1.

GRAND GULF, UNIT 1 A-30 Revision 43

TABLE 6.11.1-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Type of Lower Limit Liquid Release Sampling Analysis Activity of Detection Type Frequency Frequency Analysis (LLD)

(µCi/ml)(a)

A. Batch Waste Prior to Prior to Principal Gamma 5x10-7 Release Release Release Emitters(d)

Tanks(c) Each Batch Each Batch I-131 1x10-6 Prior to 31 days Dissolved and 1x10-5 Release Entrained Gases One Batch/M (Gamma emitters)

Prior to 31 days H-3 1x10-5 Release Composite(b)

Each Batch Gross Alpha 1x10-7 Prior to 92 days Sr-89, Sr-90 5x10-8 Release Composite(b)

Each Batch Fe-55 1x10-6 B. SSW Basin Prior to Prior to Principal Gamma 5x10-7 (before Release Release Emitters(d) blowdown) Each Each Batch Blowdown I-131 1x10-6 GRAND GULF, UNIT 1 A-31 Revision 43

TABLE 6.11.1-1 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95%

probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 sb LLD =

E V 2.22 x 106 Y exp(-t) where LLD is the "a priori" lower limit of detection as defined above (as µCi per unit mass or volume). (Current literature defines the LLD as the detection capability for the instrumentation only, and the MDC, minimum detectable concentration, as the detection capability for a given instrument, procedure, and type of sample.)

sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

E is the counting efficiency (as counts per disintegration)

V is the sample size (in units of mass or volume) 2.22 x 106 is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable) is the radioactive decay constant for the particular radionuclide t is the elapsed time between sample collection (or end of the sample collection period) and time of counting The value of sb used in the calculation of the LLD for a particular measurement system should be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicated variance.

Typical values of E, V, Y and t should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.

GRAND GULF, UNIT 1 A-32 Revision 43

TABLE 6.11.1-1 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (Continued)

b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

c. A batch release is the discharge of liquid wastes of a discrete volume. Before sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

d. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

GRAND GULF, UNIT 1 A-33 Revision 43

6.11 RADIOACTIVE EFFLUENTS 6.11.2 LIQUID EFFLUENT DOSE LCO 6.11.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS shall be:

a. 1.5 mrem to the total body and 5 mrem to any organ, during any calendar quarter, and

b. 3 mrem to the total body and 10 mrem to any organ, during any calendar year.

APPLICABILITY: At all times.

ACTIONS

NOTES---------------------------------------

1. The provisions of Specification 3.0.3 are not applicable.

2. Separate Condition entry is allowed for each of the above limits.

CONDITION REQUIRED ACTION COMPLETION TIME A. The calculated dose from A.1 Initiate action to prepare Immediately the release of radioactive and submit a Special Report materials in liquid within 30 days.

effluents greater than any of the above limits. AND A.2 Declare the liquid effluent waste treatment system nonfunctional.

(continued)

GRAND GULF, UNIT 1 A-34 Revision 43

B. The calculated doses from B.1 Initiate action to Immediately the release of radioactive calculate the direct materials in liquid radiation contributions effluents greater than from the reactor unit and twice any of the above from outside storage tanks limits. to determine whether the total annual dose or dose commitment to any MEMBER OF THE PUBLIC greater than:

a) 25 mrem to the total body or any organ, except the thyroid.

OR b) 75 mrem to the thyroid.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.11.2.1 Cumulative dose contributions from liquid 31 days effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters of the ODCM.

GRAND GULF, UNIT 1 A-35 Revision 43

6.11 RADIOACTIVE EFFLUENTS 6.11.3 LIQUID EFFLUENT WASTE TREATMENT LCO 6.11.3 The liquid radwaste system shall be used to reduce the radioactive materials in liquid wastes before their discharge when the projected doses due to the liquid effluent to UNRESTRICTED AREAS would be 0.06 mrem to the total body or 0.2 mrem to any organ, in a 31-day period.

APPLICABILITY: At all times.

ACTIONS

NOTES---------------------------------------

The provisions of specification 3.0.3 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Radioactive liquid waste A.1 Initiate action to prepare Immediately being discharged without and submit, a Special treatment and in excess of Report within 30 days.

the above limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.11.3.1 Doses due to liquid releases to UNRESTRICTED AREAS 31 days shall be projected in accordance with methodology and parameters in the ODCM.

AND

NOTE-----------------------

Not required to be met when the projected dose less than or equal to the above limit.

Verify the liquid effluent waste treatment system is being used to reduce radioactive materials before discharge.

GRAND GULF, UNIT 1 A-36 Revision 43

6.11 RADIOACTIVE EFFLUENTS 6.11.4 GASEOUS EFFLUENTS - DOSE RATE LCO 6.11.4 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be:

a. For noble gases: 500 mrem/yr to the total body and 3000 mrem/yr to the skin, and

b. For all iodine-131, iodine-133, tritium and all radionuclides in particulate form with half lives greater than 8 days: 1500 mrem/yr to any organ.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Dose rate exceeding the A.1 Decrease the release rate Immediately above limits. to within the above limit(s).

AND A.2 Declare the ventilation exhaust treatment system nonfunctional.

GRAND GULF, UNIT 1 A-37 Revision 43

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.11.4.1 The dose rate due to noble gases in gaseous Per (ODCM) effluents shall be determined to be within the Table 6.11.4-1.

above limits by obtaining representative samples and performing analyses in accordance with (ODCM)Table 6.11.4-1.

SR 6.11.4.2 The dose rate due to iodine-131, iodine-133, Per (ODCM) tritium and to radionuclides in particulate form Table 6.11.4-1.

with half lives greater than 8 days in gaseous effluents shall be determined to be within the above limits by obtaining representative samples and performing analyses in accordance with (ODCM)Table 6.11.4-1.

GRAND GULF, UNIT 1 A-38 Revision 43

TABLE 6.11.4-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Release Sampling Minimum Type of Lower Limit Type Frequency Analysis Activity of Detection Frequency Analysis (LLD)

(µCi/ml) (a)

A. (1) Radwaste 31 days 31 days Principal Gamma 1x10-4 Building Grab Sample(f) Emitters(b,e)

Ventilation Exhaust H-3 1x10-6 (2) Fuel Handling Continuous(d) 7 days(c) I-131 1x10-12 Area Ventila- (f) Charcoal tion Exhaust Sample I-133 1x10-10 (3) Containment Continuous(d) 7 days(c) Principal Gamma 1x10-11 Ventilation (f) Particulate Emitters(e)

Exhaust Sample (I-131, Others)

(4A) Turbine Continuous(d) 31 days Gross Alpha 1x10-11 Building (f) Composite Ventilation Particulate Exhaust Sample (4B) Turbine Building Continuous(d) 92 days Sr-89, Sr-90 1x10-11 Occasional (f) Composite Release Point Particulate (when in service) Sample Continuous(f) Noble Gas Noble Gases 1x10-6 Monitor Gross Beta or Gamma B. (1) Offgas Post 31 days 31 days Principal Gamma 1x10-4 Treatment Grab Sample(f) Emitters(e)

Exhaust, whenever there is flow (2) Standby Gas Treatment A Exhaust, whenever there is flow (3) Standby Gas Treatment B Exhaust, whenever there is flow See "Table Notation" which follows.

GRAND GULF, UNIT 1 A-39 Revision 43

TABLE 6.11.4-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95%

probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 sb LLD =

E V 2.22 x 106 Y exp (-t) where LLD is the "a priori" lower limit of detection as defined above (as µCi per unit mass or volume). (Current literature defines the LLD as the detection capability for the instrumentation only, and the MDC, minimum detectable concentration, as the detection capability for a given instrument, procedure, and type of sample.)

sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

E is the counting efficiency (as counts per disintegration)

V is the sample size (in units of mass or volume) 2.22 x 106 is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable) is the radioactive decay constant for the particular radionuclide t is the elapsed time between sample collection (or end of the sample collection period) and time of counting The value of sb used in the calculation of the LLD for a particular measurement system should be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicated variance.

Typical values of E, V, Y and t should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.

GRAND GULF, UNIT 1 A-40 Revision 43

TABLE 6.11.4-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (Continued)

b. Analyses shall also be performed following startup from cold shutdown, or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period. This requirement does not apply if:

(1) routine analysis required by the Surveillance Requirements of LCO 3.4.8 shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

c. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing or after removal from sampler. Sampling and analyses shall be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLD's may be increased by a factor of 10. This requirement does not apply if:

(1) routine analysis required by the Surveillance Requirements of LCO 3.4.8 shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

d. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with LCOs 6.11.4 and 6.11.6.

e. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

f. When a monitor is placed in an nonfunctional status solely for performance of required Surveillances, entry into associated Conditions and Required Actions in accordance with LCO 6.3.10 may be delayed for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

g. When in modes 4 and 5, continuous noble gas monitor alarm is not required.

GRAND GULF, UNIT 1 A-41 Revision 43

6.11 RADIOACTIVE EFFLUENTS 6.11.5 GASEOUS EFFLUENT DOSE - NOBLE GASES LCO 6.11.5 The air dose due to noble gases released in gaseous effluents, from the site to areas at and beyond the SITE BOUNDARY shall be:

a. 5 mrad for gamma radiation and 10 mrad for beta radiation, during any calendar quarter and

b. 10 mrad for gamma radiation and 20 mrad for beta radiation during any calendar year.

APPLICABILITY: At all times.

ACTIONS

NOTES---------------------------------------

1. The provisions of Specification 3.0.3 are not applicable.

2. Separate Condition entry is allowed for each of the above limits.

CONDITION REQUIRED ACTION COMPLETION TIME A. The calculated air dose A.1 Initiate action to prepare Immediately from the radioactive noble and submit, a Special gases in gaseous effluents Report within 30 days.

greater than any of the above limits. AND A.2 Declare the ventilation exhaust treatment system nonfunctional.

(continued)

GRAND GULF, UNIT 1 A-42 Revision 43

B. The calculated doses from B.1 Initiate action to Immediately the release of radioactive calculate the direct materials in gaseous radiation contributions effluents greater than from the reactor unit and twice any of the above from outside storage tanks limits. to determine whether the total annual dose or dose commitment to any MEMBER OF THE PUBLIC greater than:

a) 25 mrem to the total body or any organ, except the thyroid.

OR b) 75 mrem to the thyroid.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.11.5.1 Cumulative dose contributions for noble gases for 31 days the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the ODCM.

GRAND GULF, UNIT 1 A-43 Revision 43

6.11 RADIOACTIVE EFFLUENTS 6.11.6 GASEOUS EFFLUENT DOSE - IODINE-131, IODINE-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM LCO 6.11.6 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from the site to areas at and beyond the SITE BOUNDARY shall be:

a. 7.5 mrem to any organ during any calendar quarter, and

b. 15 mrem to any organ during any calendar year.

APPLICABILITY: At all times.

ACTIONS

NOTES---------------------------------------

1. The provisions of Specification 3.0.3 are not applicable.

2. Separate Condition entry is allowed for each of the above limits.

CONDITION REQUIRED ACTION COMPLETION TIME A. The calculated dose from A.1 Initiate action to prepare Immediately the release of iodine-131, and submit, a Special iodine-133, tritium and Report within 30 days.

radionuclides in particulate form, with AND half-lives greater than 8 days, in gaseous effluents A.2 Declare the ventilation greater than any of the exhaust treatment system above limits. nonfunctional.

(continued)

GRAND GULF, UNIT 1 A-44 Revision 43

B. The calculated doses from B.1 Initiate action to Immediately the release of radioactive calculate the direct materials in gaseous radiation contributions effluents greater than from the reactor unit and twice any of the above from outside storage tanks limits. to determine whether the total annual dose or dose commitment to any MEMBER OF THE PUBLIC greater than:

a) 25 mrem to the total body or any organ, except the thyroid.

OR b) 75 mrem to the thyroid.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.11.6.1 Cumulative dose contributions from iodine-131, 31 days iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the ODCM.

GRAND GULF, UNIT 1 A-45 Revision 43

6.11 RADIOACTIVE EFFLUENTS 6.11.7 GASEOUS RADWASTE TREATMENT LCO 6.11.7 The GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM shall be in operation.

APPLICABILITY: When the steam jet air ejector (SJAE) is in operation.

ACTIONS

NOTES----------------------------------------

The provisions of Specification 3.0.3 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Gaseous radwaste from the A.1 Restore treatment to this 7 days SJAE being discharged discharge.

without treatment.

B. Required Action A.1 and B.1 Initiate action to prepare Immediately Associated Completion Time and submit a Special Report not met. to the Commission within 30 days.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.11.7.1 Ensure that the GASEOUS RADWASTE TREATMENT 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (OFFGAS) SYSTEM is operating.

GRAND GULF, UNIT 1 A-46 Revision 43

6.11 RADIOACTIVE EFFLUENTS 6.11.8 VENTILATION EXHAUST TREATMENT SYSTEM LCO 6.11.8 The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste before their discharge when the projected dose due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY in a 31 day period would exceed 0.3 mrem to any organ.

APPLICABILITY: At all times.

ACTIONS

NOTES---------------------------------------

The provisions of Specification 3.0.3 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Gaseous waste being A.1 Initiate action to prepare Immediately discharged without and submit a Special Report treatment and greater than to the Commission within the above limit. 30 days.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.11.8.1 Doses due to gaseous releases to areas at and 31 days beyond the SITE BOUNDARY shall be projected in accordance with the methodology and parameters in the ODCM.

AND

NOTE------------------

1. Not required to be met when the ventilation exhaust treatment system is undergoing routine maintenance.

2. Not required to be met when the projected dose less than or equal to the above limit.

Verify the ventilation exhaust treatment system is operating.

GRAND GULF, UNIT 1 A-47 Revision 43

6.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 6.12.1 MONITORING PROGRAM LCO 6.12.1 The radiological environmental monitoring program shall be conducted as specified in ODCM Table 6.12.1-1. The results of this program shall be validated by use of an Interlaboratory Comparison Program corresponding to samples required by Table 6.12.1-1.

APPLICABILITY: At all times.

ACTIONS

NOTES---------------------------------------

The provisions LCO 3.0.3 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. The radiological A.1 Initiate action to include Immediately environmental monitoring in the next Annual program not being Radiological Environmental conducted as specified in Operating Report, a ODCM Table 6.12.1-1. description of the reasons for not conducting the OR program as required and the plans for preventing a The required recurrence.

Interlaboratory Comparison Program not performed.

B. The level of radioactivity B.1 Initiate action to prepare Immediately as the result of plant and submit a Special Report effluent in an within 30 days.

environmental sampling medium at a specified location exceeding the reporting levels of ODCM Table 6.12.1-2 when averaged over any calendar quarter.

(continued)

GRAND GULF, UNIT 1 A-48 Revision 43

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Milk or broad leaf C.1 Initiate action to identify Immediately vegetation sampling is this changed location(s) in relocated from one or more the next Annual Radioactive of the sample locations Effluent Release Report.

required by ODCM Table 6.12.1-1. AND C.2 Add this location(s) to the 30 days radiological environmental monitoring program.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.12.1.1 Radiological environmental monitoring samples Per ODCM shall be collected pursuant to ODCM Table 6.12.1-1 Table 6.12.1-1.

from the locations given in the table and figures in the ODCM and shall be analyzed pursuant to the requirements of ODCM Tables 6.12.1-1 and 6.12.1-3.

SR 6.12.1.2 Conduct an Interlaboratory Comparison Program and 366 days include a summary of the results in the Annual Radiological Environmental Operating Report.

GRAND GULF, UNIT 1 A-49 Revision 43

TABLE 6.12.1-1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples(a) Sampling and Type and Frequency and/or Sample and Locations Collection Frequency(a) of Analysis AIRBORNE Radioiodine and Samples from 4 locations: Continuous sampler Radioiodine Cannister:

Particulates operation with sample I-131; 7 days 2 samples close to the SITE collection per 7 days or as BOUNDARY having the highest required by dust calculated annual average loading, whichever is groundlevel D/Q. more frequent 1 sample from the vicinity of a Particulate Sampler:

community having the highest Gross beta radio-calculated annual average activity following groundlevel D/Q. filter change(b),

composite (by location) 1 sample from a control location for gamma isotopic(c);

15-30 km (10-20 miles) distance(d) 92 days DIRECT RADIATION(e) 16 stations with two or more 92 days Gamma dose; 92 days dosimeters or one instrument for measuring and recording dose rate continuously. The stations will be placed in accessible sectors alternating between inner and outer ring locations*:

1) an inner ring of stations in the general areas of the SITE BOUNDARY

2) an outer ring approximately 3 to 5 miles from the site.

8 additional stations should be placed in special interest areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations.

5 additional stations will be placed in locations in the general area of the site boundary to supplement the inner ring monitoring locations.

GRAND GULF, UNIT 1 A-50 Revision 43

TABLE 6.12.1-1 (Continued)

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples(a) Sampling and Type and Frequency and/or Sample and Locations Collection Frequency(a) of Analysis WATERBORNE Surface 1 sample upstream 92 days Gamma isotopic(c) and 1 sample downstream tritium analyses; 92 days One sample downstream 366 days Gamma Isotopic (c) and during a liquid Radwaste tritium analyses; 366 days Discharge 1 sample from Outfall 007 31 days Tritium; 31 days Ground Samples from 2 sources 366 days Gamma isotopic(c) and tritium; 366 days Sediment from 1 sample from downstream area 366 days Gamma isotopic(c);

Shoreline 1 sample from upstream area 366 days INGESTION Milk 1 sample from milking animals 92 days when required Gamma isotopic(c) and within 8 km if milk is I-131; 92 days available commercially.

1 control sample (only if indicator exists) > 8 km if milk is available.

GRAND GULF, UNIT 1 A-51 Revision 43

TABLE 6.12.1-1 (Continued)

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples(a) Sampling and Type and Frequency and/or Sample and Locations Collection Frequency(a) of Analysis Food Products 1 sample of broad leaf 92 days when available Gamma isotopic(c) vegetation grown in one of and I-131; 92 days two different offsite locations with highest anticipated annual average ground level D/Q if milk sampling is not performed 1 sample of similar 92 days when available Gamma isotopic(c) vegetation grown 15-30 km and I-131; 92 days distant if milk sampling is not performed Fish 1 sample (f) in vicinity of GGNS 366 days Gamma isotopic(c) discharge point on edible portion; 366 days 1 sample (f) uninfluenced by GGNS 366 days Gamma isotopic(c) discharge on edible portion; 366 days GRAND GULF, UNIT 1 A-52 Revision 43

TABLE 6.12.1-1 (Continued)

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATION

As described in the ODCM. If a location is not accessible, instruments may be placed in an adjacent inner or outer location.

a Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 6.12.1-1 in the table(s) and figure(s) in the ODCM. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment, malfunction, every effort shall be made to complete corrective action before the end of the next sampling period. All above deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report.

It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. Identify the cause of the unavailability of samples for that pathway and identify the new location(s) for obtaining replacement samples in the next Annual Radioactive Effluent Release Report and also include in the report a revised figure(s) and table(s) for the ODCM reflecting the new location(s).

b Particulate sample filters should be analyzed for gross beta 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air or water is greater than ten times the yearly mean of control samples for any medium, gamma isotopic analysis should be performed on the individual samples.

c Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

d The purpose of this sample is to obtain background information.

e One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter may be considered to be one phosphor and two or more phosphors in a packet may be considered as two or more dosimeters. Film badges should not be used for measuring direct radiation.

f Commercially important species preferred (catfish, buffalo); however, if unavailable, other species may be substituted.

GRAND GULF, UNIT 1 A-53 Revision 43

TABLE 6.12.1-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levelsb Water Airborne Particulate Fish Milk Food Products Analysis (pCi/l) or Gases (pCi/m3) (pCi/Kg, wet) (pCi/l) (pCi/Kg, wet) 4a H-3 2 x 10 NA NA NA NA 3 4 Mn-54 1 x 10 NA 3 x 10 NA NA 2 4 Fe-59 4 x 10 NA 1 X 10 NA NA 3 4 Co-58 1 x 10 NA 3 x 10 NA NA 2 4 Co-60 3 x 10 NA 1 x 10 NA NA 2 4 Zn-65 3 x 10 NA 2 x 10 NA NA 2

Zr-Nb-95 4 x 10 NA NA NA NA 2

I-131 2 0.9 NA 3 1 x 10 3 3 Cs-134 30 10 1 x 10 60 1 x 10 3 3 Cs-137 50 20 2 x 10 70 2 x 10 2 2 Ba-La-140 2 x 10 NA NA 3 x 10 NA a For drinking water samples. This is a 40 CFR Part 141 value. If no drinking water pathway exists, a value of 3 x 104 pCi/l may be used.

b See BASES 6.12.1 for reporting requirements when multiple or unlisted radionuclides are detected.

GRAND GULF, UNIT 1 A-54 Revision 43

TABLE 6.12.1-3 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)(a,b)

Airborne Particulate Broad Leaf Water or Gas Fish Milk Vegetation Sediment Analysis (pCi/l) (pCi/m3) (pCi/kg, wet) (pCi/l) (pCi/kg, wet) (pCi/kg, dry)

-2 Gross beta 4 1 x 10 NA NA NA NA 3

H-3 2 x 10 (d) NA NA NA NA NA Mn-54 15 NA 1.3 x 102 NA NA NA Fe-59 30 NA 2.6 x 102 NA NA NA Co-58,60 15 NA 1.3 x 102 NA NA NA Zn-65 30 NA 2.6 x 102 NA NA NA Zr-95 30 NA NA NA NA NA Nb-95 15 NA NA NA NA NA I-131 1(c) 7 x 10-2 NA 1 60 NA Cs-134 15 5 x 10-2 1.3 x 102 15 60 1.5 x 102 Cs-137 18 6 x 10-2 1.5 x 102 18 80 1.8 x 102 Ba-140 60 NA NA 60 NA NA La-140 15 NA NA 15 NA NA GRAND GULF, UNIT 1 A-55 Revision 43

TABLE 6.12.1-3 (Continued)

MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)

TABLE NOTATION

a. Acceptable detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

b. Table 6.12.1-3 indicates acceptable detection capabilities for radioactive materials in environmental samples. These detection capabilities are tabulated in terms of the lower limits of detection (LLDs). The LLD is defined, for purposes of this guide, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 s b

LLD =

E V 2.22 Y exp (-t) where LLD is the "a priori" lower limit of detection as defined above (as pCi per unit mass or volume). (Current literature defines the LLD as the detection capability for the instrumentation only, and the MDC, minimum detectable concentration, as the detection capability for a given instrument, procedure, and type of sample.)

s is the standard deviation of the background counting rate or of the b

counting rate of a blank sample as appropriate (as counts per minute)

E is the counting efficiency (as counts per disintegration)

V is the sample size (in units of mass or volume) 2.22 is the number of disintegrations per minute per picocurie Y is the fractional radiochemical yield (when applicable) is the radioactive decay constant for the particular radionuclide t is the elapsed time between sample collection (or end of the sample collection period) and time of counting The value of sb used in the calculation of the LLD for a particular measurement system should be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicated variance.

GRAND GULF, UNIT 1 A-56 Revision 43

TABLE 6.12.1-3 (Continued)

MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)

TABLE NOTATION (Continued)

Typical values of E, V, Y and t should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement. Occasionally background fluctuations, unavoidable small sample size, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors should be identified and described in the Annual Radiological Environmental Operating Report.

c. LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic may be used.

d. If no drinking water pathway exists, a value of 3 x 103 pCi/1 may be used.

GRAND GULF, UNIT 1 A-57 Revision 43

6.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 6.12.2 LAND USE CENSUS LCO 6.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden of greater than 50 m2 (500 ft2) producing broad leaf vegetation. Broad leaf vegetation sampling may be performed at the SITE BOUNDARY in one of two different offsite locations with the highest predicted D/Qs in lieu of the garden census.

APPLICABILITY: At all times.

ACTIONS

NOTES----------------------------------------

The provisions of LCO 3.0.3 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. A land use census A.1 Initiate action to identify Immediately identifies a location(s) the new location(s) in the which yields a calculated next Annual Radioactive dose or dose commitment Effluent Release Report.

greater than the values currently being calculated in LCO 6.11.6.

B. A land use census B.1 Initiate action to identify Immediately identifies a location(s) these higher dose which yields a calculated location(s) in the next dose or dose commitment Annual Radioactive Effluent (via the same exposure Release Report.

pathway) 20 percent greater than at a location AND from which samples are currently being obtained B.2 Add these location(s) to 30 days in accordance with LCO the radiological 6.12.1. environmental monitoring program.

GRAND GULF, UNIT 1 A-58 Revision 43

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.12.2.1 Conduct a land use census during the growing Once per 2 years season. The land use census shall verify the appropriateness of the sample location used to fulfill the requirements of LCO 6.12.1 GRAND GULF, UNIT 1 A-59 Revision 43

BASES FOR SECTION 6.0 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS GRAND GULF, UNIT 1 A-60 Revision 43

6.3 INSTRUMENTATION BASES 6.3.9 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The LCO for radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm/trip will occur before exceeding ten times the effluent concentration limits of 10 CFR Part 20. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General design Criteria 60, 63 and 64 of Appendix A to 10 CFR 50.

6.3.10 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The LCO for radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, gaseous effluents during actual or potential releases. Those instruments that monitor the activity of gaseous effluents being released to the environment shall have their alarm/trip setpoints calculated in accordance with the methods in the ODCM to ensure that the alarm/trip will occur before exceeding the limits of 10 CFR Part 20. Other instruments that monitor offgas processing, (i.e., Offgas Pre-Treatment Monitor and Offgas Post-Treatment Monitor) are calibrated according to plant procedures. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

GRAND GULF, UNIT 1 A-61 Revision 43

6.11 RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS 6.11.1 CONCENTRATION This LCO is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than ten times the effluent concentration values specified in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402. It provides operational flexibility for releasing liquid effluents in concentrations to follow the Section II.A and II.C design objectives of Appendix I to 10 CFR Part 50. This limitation provides reasonable assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR 50, to a MEMBER OF THE PUBLIC, and (2) restrictions authorized by 10 CFR 20.1301(e). The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radionuclide and its effluent concentration in air (submersion) was converted to an equivalent concentration in water. This LCO does not affect the requirement to comply with the annual limitations of 10 CFR 20.1301(a).

The results of pre-release analyses and post release analyses (of composited samples) shall be used with the calculational methods and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits, can be found in:

(1) HASL Procedures Manual, HASL-300.

(2) Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968).

(3) Hartwell, J. K., "Detection Limits for Radioisotopic Counting Techniques,"

Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).

6.11.2 DOSE This LCO is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I which assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

GRAND GULF, UNIT 1 A-62 Revision 43

RADIOACTIVE EFFLUENTS BASES 6.11.2 DOSE (Continued)

The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in 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 Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluent from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

This LCO, in conjunction with LCOs 6.11.5 and 6.11.6 is also provided to meet the dose limitation of 40 CFR 190 that has been incorporated into 10 CFR 20.1301(d).

Even if a site contained up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the individual reactors remain within twice the dose design objectives of 10 CFR 50 Appendix I, and the direct radiation doses from the units (including outside storage tanks, etc.) are kept small.

Special Report:

LCO 6.11.2 requires preparation and submittal of a report in accordance with 10 CFR 50.4 and as defined in 10 CFR 20.2203(a)(4), if the dose design objectives of 10 CFR 50 Appendix I are exceeded.

If either the quarterly or the annual limit is exceeded, the report will:

(1) identify the cause(s) for exceeding the limit(s),

(2) define the corrective actions that have been taken to reduce the releases, and (3) define the corrective actions to be taken to ensure that future releases will be in compliance with the limits.

If a drinking water supply is taken from the receiving water body within three miles downstream of the plant discharge, the report shall also include:

(1) results of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141.

If the doses exceed the limits of 40 CFR 190, 25 mrems to the whole body or any organ, except the thyroid, which is limited to 75 mrems, the report shall:

(1) define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits, (2) include the schedule for achieving conformance with the above limits, (3) include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report, (4) describe the levels of radiation and concentrations of radioactive material involved, (5) describe the cause of the exposure level or concentrations involved, GRAND GULF, UNIT 1 A-63 Revision 43

RADIOACTIVE EFFLUENTS BASES 6.11.2 DOSE (Continued)

(6) describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR 190 limits.

For the purposes of the report it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that the dose distribution from other nuclear fuel cycle facilities at the same site or within a radius of 8 kilometers must be considered.

The Special Report with a request for a variance (provided the release conditions resulting in a violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203(a)(4), is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to other requirements for dose limitations of 10 CFR 20, as addressed in LCOs 6.11.1 and 6.11.4. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

Demonstration of compliance with the limits of 40 CFR 190 or with the design objectives of Appendix I to 10 CFR 50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR 20.1301.

GRAND GULF, UNIT 1 A-64 Revision 43

RADIOACTIVE EFFLUENTS BASES 6.11.3 LIQUID WASTE TREATMENT The LCO that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This LCO implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limit governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

Special Report:

LCO 6.11.3 requires preparation and submittal of a report in accordance with 10 CFR 50.4 if radioactive liquid waste is being discharged without treatment and in excess of the limits. The report shall include:

(1) an explanation why liquid radwaste was being discharged without treatment, (2) identification of any nonfunctional equipment or subsystems which resulted in liquid radwaste being discharged without treatment, (3) the reason for the nonfunctionality (4) action(s) taken to restore the nonfunctional equipment to an FUNCTIONAL status, (5) summary descriptions of actions taken to prevent a recurrence.

GASEOUS EFFLUENTS 6.11.4 DOSE RATE This LCO provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either at or beyond the SITE BOUNDARY in excess of the design objectives of Appendix I to 10 CFR Part 50. This specification is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section II.A and II.C design objectives of Appendix I to 10 CFR Part

50. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for the reduced atmosphere dispersion of gaseous effluents relative to that for the SITE BOUNDARY. The calculational methods and parameters in the ODCM are used to assure that the dose rates are maintained within the limits. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin. These releases rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year. This specification does not affect the requirement to comply with the annual limitations of 10 CFR 20.1301(a).

The dose rate due to radioactive gaseous effluents shall be determined in accordance with the methodology and parameters of the ODCM.

GRAND GULF, UNIT 1 A-65 Revision 43

RADIOACTIVE EFFLUENTS BASES 6.11.4 DOSE RATE (Continued)

The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits, can be found in:

(1) HASL Procedures Manual, HASL-300 (revised annually).

(2) Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968).

(3) Hartwell, J. K., "Detection Limits for Radioisotopic Counting Techniques,"

Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).

6.11.5 DOSE - NOBLE GASES This LCO is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."

The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in 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 Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

This LCO, in conjunction with LCOs 6.11.2 and 6.11.6 is also provided to meet the dose limitation of 40 CFR 190 that has been incorporated into 10 CFR 1301(d). Even if a site contained up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the individual reactors remain within twice the dose design objectives of 10 CFR 50 Appendix I, and if the direct radiation doses from the units (including outside storage tanks, etc.) are kept small.

GRAND GULF, UNIT 1 A-66 Revision 43

RADIOACTIVE EFFLUENTS BASES 6.11.5 DOSE - NOBLE GASES (Continued)

Special Report:

LCO 6.11.5 requires preparation and submittal of a report in accordance with 10 CFR 50.4 and as defined in 10 CFR 20.2203(a)(4), if the dose design objectives of 10 CFR 50 Appendix I are exceeded.

If either the quarterly or the annual limit is exceeded, the report will:

(1) identify the cause(s) for exceeding the limit(s),

(2) define the corrective actions that have been taken to reduce the releases, and (3) define the corrective actions to be taken to ensure that future releases will be in compliance with the limits.

If the doses exceed the limits of 40 CFR 190, 25 mrems to the whole body or any organ, except the thyroid, which is limited to 75 mrems, the report shall:

(1) define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits, (2) include the schedule for achieving conformance with the above limits, (3) include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report, (4) describe the levels of radiation and concentrations of radioactive material involved, (5) describe the cause of the exposure level or concentrations involved, (6) describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR 190 limits.

For the purposes of the report it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that the dose distribution from other nuclear fuel cycle facilities at the same site or within a radius of 8 kilometers must be considered.

The Special Report with a request for a variance (provided the release conditions resulting in a violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203(a)(4), is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed.

The variance only relates to the limits of 40 CFR 190, and does not apply in any way to other requirements for dose limitations of 10 CFR 20, as addressed in LCOs 6.11.1 and 6.11.4. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

Demonstration of compliance with the limits of 40 CFR 190 or with the design objectives of Appendix I to 10 CFR 50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR 20.1301.

GRAND GULF, UNIT 1 A-67 Revision 43

RADIOACTIVE EFFLUENTS BASES 6.11.6 DOSE - IODINE-131, IODINE-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM This LCO is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A. of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in 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 Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for iodine-131, iodine-133, tritium and radionuclides in particulate form are dependent on the existing radionuclide pathway to man in the areas at and beyond the SITE BOUNDARY. The pathways which were examined in the development of these calculations were: (1) individual inha-lation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat-producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.

This LCO, in conjunction with LCOs 6.11.2 and 6.11.5 is also provided to meet the dose limitation of 40 CFR 190 that has been incorporated into 10 CFR 1301(d). Even if a site contained up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the individual reactors remain within twice the dose design objectives of 10 CFR 50 Appendix I, and if the direct radiation doses from the units (including outside storage tanks, etc.) are kept small.

Special Report:

LCO 6.11.6 requires preparation and submittal of a report in accordance with 10 CFR 50.4 and as defined in 10 CFR 20.2203(a)(4), if the dose design objectives of 10 CFR 50 Appendix I are exceeded.

If either the quarterly or the annual limit is exceeded, the report will:

(1) identify the cause(s) for exceeding the limit(s),

(2) define the corrective actions that have been taken to reduce the releases, and (3) define the corrective actions to be taken to ensure that future releases will be in compliance with the limits.

GRAND GULF, UNIT 1 A-68 Revision 43

RADIOACTIVE EFFLUENTS BASES 6.11.6 DOSE - IODINE-131, IODINE-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM (Continued)

If the doses exceed the limits of 40 CFR 190, 25 mrems to the whole body or any organ, except the thyroid, which is limited to 75 mrems, the report shall:

(1) define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits, (2) include the schedule for achieving conformance with the above limits, (3) include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report, (4) describe the levels of radiation and concentrations of radioactive material involved, (5) describe the cause of the exposure level or concentrations involved, (6) describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR 190 limits.

For the purposes of the report it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that the dose distribution from other nuclear fuel cycle facilities at the same site or within a radius of 8 kilometers must be considered.

The Special Report with a request for a variance (provided the release conditions resulting in a violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203(a)(4), is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed.

The variance only relates to the limits of 40 CFR 190, and does not apply in any way to other requirements for dose limitations of 10 CFR 20, as addressed in LCOs 6.11.1 and 6.11.4. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

Demonstration of compliance with the limits of 40 CFR 190 or with the design objectives of Appendix I to 10 CFR 50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR 20.1301.

GRAND GULF, UNIT 1 A-69 Revision 43

RADIOACTIVE EFFLUENTS BASES 6.11.7 and 6.11.8 GASEOUS RADWASTE TREATMENT AND VENTILATION EXHAUST TREATMENT The FUNCTIONALITY of the GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment before release to the environment.

The requirement that the appropriate portions of the system be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the system were specified as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR 50, for gaseous effluents.

Special Report:

LCOs 6.11.7 and 6.11.8 require preparation and submittal of a report in accordance with 10 CFR 50.4 including:

(1) an explanation of why gaseous radwaste was being discharged without treatment, (2) identification of the nonfunctional equipment or subsystems which resulted in gaseous radwaste being discharged without treatment, (3) the reason for the nonfunctionality, (4) action(s) taken to restore the nonfunctional equipment to an FUNCTIONAL status, (5) summary descriptions of action(s) taken to prevent a recurrence.

LCO 6.11.8 is not applicable to the Turbine Building ventilation exhaust unless filtration media is installed.

Instruments checked to ensure the GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM is functioning are:

(1) Adsorber Train Bypass Switch (1N64-HS-M611),

(2) Bypass Valve Indication (1N64-F045).

When the Adsorber Train Bypass Switch is in the TREAT position and the bypass valve indicates CLOSED, the GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM is functioning.

GRAND GULF, UNIT 1 A-70 Revision 43

6.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 6.12.1 MONITORING PROGRAM The radiological monitoring program required by this LCO provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The detection capabilities required by Table 6.12.1-3 are state-of-the-art for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

For a more complete discussion of the LLD, and other detection limits, see the following:

(1) HASL Procedure Manual, HASL-300 (revised annually).

(2) Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal.Chem. 40, 586-93 (1968).

(3) Hartwell, J. K., "Detection Limits for Radioisotopic Counting Techniques,"

Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).

If milk or broadleaf vegetation sampling locations are relocated, the cause shall be reported in the next Annual Radioactive Effluent Release Report. Also, include in this report, revised ODCM figure(s) and table(s) reflecting the new locations. The specific locations from which samples were unavailable may then be deleted from the radiological environmental monitoring program and the table(s) in the ODCM, provided the locations from which the replacement samples were obtained are added to the table(s) as replacement locations.

The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measures of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

GRAND GULF, UNIT 1 A-71 Revision 43

6.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 6.12.1 MONITORING PROGRAM (Continued)

Special Report:

LCO 6.12.1 requires preparation and submittal of a report in accordance with 10 CFR 50.4 when:

(1) the level of radioactivity as a result of plant effluents in an environmental sampling medium at a specified location exceeds the reporting level(s) in ODCM Table 6.12.1-2 when averaged over a calendar quarter, or (2) more than one of the radio nuclides in ODCM Table 6.12.1-2 are detected in the sampling medium and concentration (1) + concentration (2) + ...1.0, or reporting level (1) reporting level (2)

(3) radio nuclides other than those in ODCM Table 6.12.1-2 are detected, and the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of LCOs 6.11.2, 6.11.5 and 6.11.6.

The report shall:

(1) identify the cause(s) for exceeding the limit(s), and (2) define the corrective actions to be taken to reduce radioactive effluents so the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of LCOs 6.11.2, 6.11.5 and 6.11.6.

The Special Report is not required if the measured level of radioactivity is not the result of plant effluents; however in such an event, the condition shall be reported and identified in the Annual Radiological Environmental Operating Report.

6.12.2 LAND USE CENSUS This LCO is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of the census.

The best information from door-to-door survey, visual or aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m2.

Specifications for broad leaf vegetation sampling in the Table 6.12.1-1 shall be followed, including analysis of control samples.

GRAND GULF, UNIT 1 A-72 Revision 43

6.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 6.12.2 LAND USE CENSUS (Continued)

The land use census should utilize information which provides the best results, such as a door-to-door-survey, an aerial survey or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2.

When the Land Use Census requires addition of sampling location(s) to the Environmental Monitoring Program, the sampling locations(s) having the lowest calculated dose or dose commitments(s), via the same exposure pathway, may be deleted from the monitoring program. This deletion may take place after October 31 of the year in which this land use census was conducted.

The new sampling location(s) shall be identified in the next Annual Radioactive Effluent Release Report including a revised figure(s) and table(s) for the ODCM.

GRAND GULF, UNIT 1 A-73 Revision 43

ML22118A086

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ML22118A086

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SUMMARY

1.0 INTRODUCTION

SUMMARY

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Reference:

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