Text

Annual Radioactive Effluent Release Report (ARERR)
	ML061170561
Person / Time
Site:	Grand Gulf
Issue date:	04/27/2006
From:	Bottemiller C; Entergy Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	GNRO-2006/00018
	Download: ML061170561 (216)
	v • d • e

Entergy Operations, Inc.

Waterloo Road P.O. Box 756 Port Gibson, MS 39150 Tel 601 437 6299 Charles A. Bottemiller GNRO-2006/00018 Manager Plant Licensing April 27, 2006 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTENTION : Document Control Desk

SUBJECT:

Grand Gulf Nuclear Station (GGNS) 2005 Annual Radioactive Effluent Release Report (ARERR)

Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 Ladies & Gentlemen:

Attached is the GGNS Annual Radioactive Effluent Release Report (ARERR) for the period January 1, 2005 through December 31,2005. This report is submitted in accordance with the requirements of 10CFR50.36a(a)(2) and the GGNS Technical Specification (TS) 5.6.3.

The ARERR also complies with the GGNS Offsite Dose Calculation Manual (ODCM).

This letter does not contain any commitments. If you have questions or require additional information concerning these reports, please contact Mr. Richard Scarbrough at (601) 437-6978, or this office at (601) 437-6685.

Yours trulv.

CABlMJL attachments: 2005 Annual Radioactive Effluent Release Report cc: (See Next Page)

CORRECTED COPY 21-2007 - TWO PAGES MISSING IN ORGINAL SUBMISSION

April 27, 2006 GNRO-2006/00018 Page 2 of 2 cc: NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U. S. Nuclear Regulatory Commission ATTN: Dr. Bruce S. Mallet (w/2)

Regional Administrator, Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 U. S. Nuclear Regulatory Commission ATTM: Mr. Bhalchandra Vaidya, NRR/DLPM (w/2)

ATTN: ADDRESSEE ONLY ATTN: U. S. Postal Delivery Address Only Mail Stop OWFN/ 0-7DlA Washington, DC 20555-0001 Mr. D. E. Levanway (Wise Carter)

Mr. L. J. Smith (Wise Carter)

Mr. N. S. Reynolds Mr. H. L. Thomas AEOWARERRZWO

ENTE PERATIONS, INC.

GRAND GULF NUCLEAR STATION ACTIVE EFFLUENT REL Jan~ary1,205 = December 31,205 env-tec/ARERROl - 1

TABLE OF CONTENTS SUBJECT PAGE I. INTRODUCTION 4 I1* DETAILED INFORMATION 5 A. Regulatory Limits 5 I. 10CFR20 Limits 5

a. Fission and Activation Gases 5

b. Radioiodines and Particulates 5

c. Liquid Effluents 5

2. 10CFR50, Appendix ILimits 6

a. Fission and Activation Gases 6

b. Radioiodines and Particulates 6

c. Liquid Effluents 6

3. 40CFRl90 Limits 7 B. Effluent Concentrations 7 I. Airborne 7

2. Liquid 7 C. Average Energy 7 D. Measurements and Approximations of Total Activity 8 I. For Fission and Activation Gases 8

2. For Particulates and Radioiodines 9

3. For Continuous Releases 9

4. For Batch Releases: Gases 9

5. For Batch Releases: Liquid Effluents 10 E. Batch Releases 10 I. Liquid 10

2. Gaseous 10 F. Unplanned Releases 11 I. Liquid 11

2. Gaseous 11 env-t&ARERROl -I

TABLE OF CONTENTS [CONT'D) -

PAGE G. Estimate of Total Error 11 I. Liquid 11

2. Gaseous 12

3. Solid Radioactive Waste 12 H. Solid Radioactive Waste Shipments 12 I.Meteorological Data 12

3. Radioactive Effluent Monitoring Instrumentation Operability 12 K. Annual Sewage Disposal Summary 12 111. RADIATION DOSE

SUMMARY

13 A. Water-Related Exposure Pathway 13 B. Ai rborne-Related Exposure Pathway 13 IV. OFFSITE DOSE CALCULATION MANUAL/RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES 15 A. Offsite Dose Calculation Manual (ODCM) 15 B. Radioactive Waste Treatment Systems 15 LIST OF TABLES PAGE IA Gaseous Effluents - Summation of All Releases 16 IB Gaseous Effluents - Elevated Releases 17 IC Gaseous Effluents - Ground-Level Releases - Continuous 18 ID Radioactive Gaseous Waste Sampling and Analysis Program 19 2A Liquid Effluents - Summation of All Releases 20 2B Liquid Effluents - Continuous and Batch Modes 21 2c Radioactive Liquid Waste Sampling and Analysis Program 22 3 Solid Radioactive Waste and Irradiated Fuel Shipments 23 LIST OF A'TTACHMENTS PAGE Attachment I - Offsite Dose Calculation Manual 26 em-ter/ARERROl - 3

I. INTRODUCTION This Annual Radioactive Effluent Release Report (ARERR) for the period of January 1 through December 31, 2005 is submitted in accordance with Offsite Dose Calculation Manual (ODCM), Section 5.6.3 of Grand Gulf Nuclear Station (GGNS) License No. NPF-29.

The monitoring of radioactive effluents is referenced in ODCM Appendix A, Sections 6.11 and 6.12.

Airborne discharges a t GGNS are considered ground-level releases. All liquid and airborne discharges to the environment were analyzed in accordance with ODCM requirements. All effluent releases were within the concentration and total release limits specified by the ODCM. Projected offsite doses were within the dose limits specified by the ODCM.

The summation of all gaseous releases during the reporting period is given in Table IA, while elevated releases and ground-level releases are given in Tables I B and lC, respectively. Table 1D describes the radioactive gaseous sampling and analysis program implemented a t GGNS.

The summation of all liquid releases during the reporting period is given in Table 2A, while continuous and batch mode releases are given in Table 28. Table 2C describes the radioactive liquid waste sampling and analysis program implemented a t GGNS.

Solid radioactive waste and irradiated fuel shipments during the reporting period are summarized in Table 3.

The annual summary of meteorological data (joint frequency distribution) will be maintained on site in a file that shall be provided to the Nuclear Regulatory Commission (NRC) upon request. The option to maintain meteorological data on site is in accordance with ODCM Administrative Controls Section 5.6.3.

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11. DETAILED INFORMATION A. Regulatory Limits

1. 10CFR20 Limits

a. Fission and Activation Gases - The release rate limit at any time for noble gases to areas a t or beyond the site boundary shall be such that:

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

- I

= X/Q Ci Ki Q i 5 500 mrem/yr D, = average skin dose rate in the current year (mrem/yr) where the terms are defined in the GGNS ODCM.

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

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

= ci W P,Q', 5 1500 mrem/yr where the terms are defined in the GGNS ODCM.

c. Liquid Effluents - The concentration of radioactive materials released in liquid effluents to unrestricted areas from the site shall not exceed a t any time ten times the values specified in 10CFR20, Appendix B, Table 2, Column 2. The concentration of dissolved or entrained noble gases, released in liquid effluents to unrestricted areas from all reactors at the site, shall be limited to 2 x microcuries/mI tota I activity.

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11. DETAILED INFORMATION (CONT'DI

2. 10CFR50, Appendix I Limits

a. Fission and Activation Gases - The dose from noble gases in gaseous effluents to areas a t or beyond the site boundary shall be such that:

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

= 3.17 x Ci Mi x/Q'Qi I5 mrad/qtr I I0 mrad/yr D = air dose due to beta emissions from noble gases P

= 3.17 x Ci Ni X/Q' Qi I10 mrad/qtr 2 20 mrad/yr where the terms are defined in the GGNS ODCM.

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

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

= 3.17 x Cj Ri W' Qi 5 7.5 mrem/qtr Any Organ I15 mrem/yr Any Organ where the terms are defined in the GGNS ODCM.

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

I 3 mrem/yr Total Body 2 I0 mrem/yr Any Organ where the terms are defined in the GGNS ODCM.

env-tedARERRO1 - 6

11.

3. 40CFRl90 Limits Doses are calculated for Fission and Activation Gases; Radioiodines and Particulates; and Liquid Effluents according to equations contained in Sections 2.(a), (b), and (c) respectively, with the exception that the limits applied are:

125 mrem/yr, Total Body or any Organ except Thyroid 175 mrem/yr, Thyroid 510 mrad y/qtr or 520 mrad y/yr, Fission and Activation Gases 120 mrad P/qtr or 540 mrad P/yr, Fission and Activation Gases 515 mrem/qtr or 530 mrem/yr, any Organ, Iodine and Particulates 53 mrem/qtr or 56 mrem/yr, Total Body, Liquid Effluents 510 mrem/qtr or 120 mrem/yr, any Organ, Liquid Effluents B. Effluent Concentrations

1. Airborne The Effluent Concentration Limit (ECL) of radioactive materials in gaseous effluents is limited by the dose rate restrictions given in Section 1I.A.l.a. I n this case, the ECLs are actually determined by the dose factors in Table 2.1-1 of the GGNS ODCM.

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

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

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11. DETAILED INFORMATION (CONT'D)

D. Measurements and Approximations of Total Activity The following discussion details the methods used to measure and approximate total activity for the following:

Fission and Activation Gases Particulates Radioiodines Liquid Effluents i L Tables 1D and 2C give sampling frequencies and minimum detectable sensitivity requirements for the analysis of gaseous and liquid effluent streams, respectively.

Values in the attached tables given as zero do not necessarily imply that the radionuclides were not present. A zero indicates that the radionuclide was not present a t levels greater than the sensitivity requirements shown in Tables 1D and 2C. For some radionuclides, lower detection limits than required may be readily achievable; when a radionuclide is measured below its stated detection limits, it is reported.

1. For Fission and Activation Gases The following noble gases are considered in evaluating gaseous airborne discharges:

Xe-133m Xe-138 Periodic grab samples from Station effluent streams are analyzed by a computerized pulse height analyzer system utilizing high-resolution germanium detectors. (See Table I D for sampling and analytical requirements.) Isotopic values thus obtained are used for dose release rate calculations due to effluent releases as given in Section II.A.1. of this report.

Only those radionuclides that are detected are used in this computation. During the period between grab samples, the amount of radioactivity released is based on the effluent monitor readings. Monitors are assigned a calibration factor based upon the last isotopic analysis, using the following relationship:

where Ci = isotopic calibration factor for isotope i Ui = concentration of isotope i in the grab sample in pCi/ml.

m = net monitor reading associated with the effluent stream (determined at the time of grab sampling).

env-tec/ARERROl - 8

11. DETAILED INFORMATION [CONT'DI These calibration factors, along with the hourly effluent monitor values and flow rates, are entered into the laboratory computer where the release rates for individual radionuclides are calculated and stored. If no activity is detected in the grab sample, the calibration factor defaults to a historical mixture of Kr-88, Xe-133, Xe-l35m, Xe-135, and Xe- 138.

2. For Particulates and Radioiodines The radioiodines and radioactive materials in particulate form to be considered are:

3. For Continuous Releases Continuous sampling is performed on the continuous release points (i.e.,

Offgas/Radwaste Building Vent, Containment Purge, Fuel Handling Area Vent, Turbine Building Vent). Particulate material is collected by filtration.

Radioiodines are collected by adsorption onto a charcoal filter. Periodically these filters are removed and analyzed on the pulse height analyzer to identify and quantify radioactive materials collected on the filters. Particulate filters are then analyzed for gross alpha and Strontium-89 and -90 as required. Gross alpha determinations are made using 2-pi gas flow proportional counter. Strontium-89 and -90 values are obtained by chemical separation and subsequent analysis using liquid scintillation techniques. Tritium concentrations are determined using distillation and liquid scintillation techniques. During major operational occurrences, the frequency of sampling is increased to satisfy the requirements of footnote "cll of Table lD, "Radioactive Gaseous Waste Sampling and Analysis,"

(GGNS ODCM Appendix A, Table 6.11.4-1). Currently, Strontium analysis is performed by a qualified contract laboratory.

4. For Batch Releases: Gases The processing of batch type releases (from Containment Purge) is analogous to that for continuous releases.

env-tec/ARERROl - 9

5. For Batch Releases: Liquid Effluents The radionuclides listed below are considered when evaluating liquid effluents:

Representative pre-release grab samples are obtained and analyzed as required by Table 2C. Isotopic analyses are performed using the computerized pulse height analysis system previously described. Aliquots of each pre-released sample, proportional to the waste volume released, are composited in accordance with the requirements of Table 2C.

Strontium-89, 90 and Iron-55 values are obtained by chemical separation and counting the separated strontium and iron using liquid scintillation techniques. Gross alpha determinations are made using 2-pi gas flow proportional counter. Tritium is determined using distillation and liquid scintillation techniques. Dissolved gases are determined employing grab sampling techniques and then counting on the pulse height analyzer system. Currently, Iron and Strontium analyses are performed by a qualified contract laboratory.

E. Batch Releases

1. Liquid

2. Gaseous No batch releases were made during the report period.

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11. DETAILED INFORMATION (CONT'D)

F. Unplanned Releases

1. Liquid

a. Number of Releases: None

b. Total Activity Released: O.OOE+OO Ci

2. Gaseous

a. Number of Releases: 1

b. Total Activity Released: 1.85E-04 Ci Iodine sample results taken from October 15th, 2005 to October 17th, 2005 were suspect due to oil found on the sample media. Conservative estimates of iodine released were calculated based on coolant iodine inventory and historical data. Calculation documentation reference number is CR-GGN-2005-04546, The total activity released is included in Table 1A and I C of this report. The resulting maximum organ dose was 2.97E-3 mrem which is 0.040 OO/ of the quarterly limit.

G. Estimate of Total Error

1. Liquid The maximum errors are collectively estimated to be as follows:

Dissolved & Entrained ir Samplinq O/O I 2.60E+01 I 2.60Et-01 I 2.60E+01 iIMeasuEmento/o I 6.8OE+Ol I 6.50E+01 I 6. IOEt-01 ir- TOTALVO I 7.30E+01 I 7.00E+01 I 6.60E+0 1 I 9.50Et-01 Sampling errors include uncertainty associated with mixing, representative sampling and discharge volume. Measurement errors include uncertainty associated with instrument calibration and the preparation and counting of low-activity samples. Counting errors are based on measurements of blank samples and, for germanium detectors, the least-readily-detectable radioisotope. Calibration errors are calculated by summing the errors associated with the calibration of a particular instrument with a radioactive source.

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

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11. DETAILED INFORMATION (CONT'D1

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

I Fission & Activation Sampling errors include uncertainty associated with sample flow, vent flow and monitor ca Iibration.

Measurement errors include uncertainty associated with instrument calibration and preparation and counting of low-activity samples. Measurement and total errors are calculated by the same methods used for liquid effluents.

3. Solid Radioactive Waste See Table 3 for error terms.

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

I. Meteorological Data The data recovery for the reporting period was 99.4°/~. The predominant wind direction was from the Northeast approximately 12.7% of the time. The predominant stability class was class "D" approximately 27.7% of the time. Average wind speed during the reporting period was approximately 4.3 miles per hour.

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

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

K. Annual Sewage Disposal Summary There were no sewage disposals in 2005.

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111. RADIATION DOSE

SUMMARY

Indicated below is the annual summary of offsite doses attributable to GGNS during 2005. Inspection of the values indicate that GGNS releases were within the 10CFR50, Appendix I design objectives.

Since there are no other fuel cycle facilities within 8 km of GGNS, 40CFRl90 limits have also been met during this period.

All parameters listed were calculated in accordance with the GGNS ODCM.

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

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

2005 Liauid Effluent Dose (mrem)

Kidney 1.75E-02 1.04E-02 1.30E-02 5.74E-02 9.24E-02 Lung 3.99E-04 8.95E-04 2.62E-03 1.78E-03 5.79E-03 GI-LLI 2.57E-02 3.53E-02 2.95E-02 5.94E-02 1.42E-01 Whole Body 1.22E-02 7.62E-03 1.42E-02 4.16E-02 7.21E-02 B. Airborne-Related Exposure Pathways The values presented in this section utilize information provided in Tables 1A and I C of this report and the calculational methodology of the ODCM. Dose and dose rates are computed for locations a t the site boundary or a t unrestricted areas beyond the site boundary. Because members of the public may, on occasion, be found within the site boundary, locations within the site boundary were considered when selecting locations for dose calculations.

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

The most limiting location for a member of the public is used for the dose calculations.

During routine operations the dispersion and deposition factors used for dose calculations are from historical annual average meteorological data.

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111. RADIATION DOSE

SUMMARY

ICONT'D)

Orqan Dose The maximum organ dose to a MEMBER OF THE PUBLIC (critical receptor) from radioiodines, tritium and particulates was calculated for this report using the most recent land use census and dispersion and deposition parameters from 2005 meteorological data. The critical receptor residence was determined to be located in the southwest sector a t a distance of 1432 meters (0.89 miles) from the plant. Pathways considered for use in the organ dose calculations are inhalation, ground plane, grass/cow/meat and vegetation. There is no grass/cow/miIk pathway within five miles of GGNS. It was assumed that the age group receiving the maximum dose lived at the residence and that the receptor consumed food products that were raised or produced at the residence.

Averaqe Total Body and Skin Dose Rate Individual total body and skin dose rates from exposure to a semi-infinite cloud of noble gas are computed for a location in the south sector a t a distance of 0.40 miles. This location corresponds to the highest annual average atmospheric dispersion factor for a location at an unrestricted area within the site boundary.

The total body and skin dose rates reported are the quarterly average of the maximum instantaneous dose rates determined daily during the reporting period and would represent the maximum possible dose rate received by members of the public.

Air Dose From Gamma and Beta Emissions Air doses from gaseous effluents were calculated for this report using dispersion parameters from the 2005 meteorological data. The highest dispersion factor for an unrestricted area was in the southwest sector at the site boundary, 1368 meters (0.85 miles) from the plant.

Direct Radiation Direct radiation dose is calculated by subtracting average doses measured by thermoluminescent dosimeter (TLD) badges located a t control locations from average doses measured by TLD badges located near the site boundary. GGNS reported measured doses in 2005 as net exposure normalized to 92 days.

Measurement units are mrad em-tec/ARERROl - 14

IV. OFFSITE DOSE CALCULATION MANUAL/

RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES A. Offsite Dose Calculation Manual (ODCM)

Four revisions to the ODCM was processed during the reporting period. The changes are summarized below.

Revision 29:

0 Updates and re-draws Figures 3.0-1and 3.0-2. Figures were previously illegible.

Revision 30:

0 Adds Distillate Sample Tank to Figure 1.3-1.

Revision 31:

0 Updates Introduction and removes reference to UFSAR.

Removal of duplicate pages from Operating Licensing Manual 0 Revises description of reverse osmosis equipment to allow operational flexibility.

Removes Figure 1.3-2.

Revision 32:

Changed wording in Section 1.2.1 so that the current dose calculation methodology may be used for storm drain release dose calculations.

Added Outfall 007 collection site to Table 3.0-2and Figure 3.0-1. Low levels of tritium have been detected in storm water run-off. Dose impact evaluation was performed and doses are insignificant. Sample location added to the environmental program to assure that the impact remains insignificant.

Add Storm Drain sampling frequency to Table 6.12.1-1.

Deletes Discharge Canal Flow as a required channel per Table 6.3.9-1and allows use for flow estimation per Required Action 6.3.9.C.l B. Radioactive Waste Treatment Systems No major changes were made to the liquid or gaseous radwaste treatment systems in 2005.

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TABLE 1A ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Fission and Activation Gases

1. Total Release Ci 1.983+01 1.003+01 8.973+00 1.853+02 2.243+02

2. Avg. Release Rate uCi/sec 2.553+00 1.283+00 1.133+00 2.333+01 7.103+00

3. Percent of TS Limit % 3.223-01 1.883-01 8.503-02 2.723+00 1.663+00 Iodine-131

1. Total Release Ci 8.663-04 1.393-04 7.143-04 4.083-04 2.133-03

2. Avg. Release Rate uCi/sec 1.113-04 1.773-05 8.99E-05 5.133-05 6.743-05

3. Percent of TS Limit % 2.093-01 3.373-02 1.733-01 9.863-02 2.573-01 Particulates Half Life >= 8 days

1. Total Release Ci 2.463-04 1.063-04 3.583-05 3.433-05 4.233-04

2. Avg. Release Rate uCi/sec 3.173-05 1.353-05 4.513-06 4.323-06 1.343-05

3. Percent of TS Limit % 2.103-02 1.363-02 3.353-02 6.783-03 3.743-02 Tritium

1. Total Release Ci 9.733+00 1.163+01 1.053+01 5.683+00 3.763+01

2. Avg. Release Rate uCi/sec 1.253+00 1.483+00 1.323+00 7.153-01 1.193+00

3. Percent of TS Limit % 9.273-02 1.113-01 1.003-01 5.413-02 1.793-01

_ _ _ _ _ AlDha Radioactivitv Gross ~

-A

1. Total Release Ci 6,013-07 8.163-07 6.373-07 3,013-07 2.363-06

2. AVQ. Release Rate uCi/sec 7.733-08 1.043-07 8.013-08 3.783-08 7.473-08 env-tec/ARERROl - 16

TABLE 1B ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - ELEVATED RELEASES JANUARY - DECEMBER 2005 (Not Applicable - GGNS Releases Are Considered Ground-Level) em-tec/ARERROl - 17

TABLE 1C ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - GROUND-LEVEL RELEASE-CONTINUOUS KR-85M Ci 9.553-01 0.003+00 0.003+00 2.453+01 2.553+01 KR-87 Ci 0.003+00 0.003+00 0.003+00 1.483+00 1.483+00 KR-88 Ci 8.623-01 3.933-04 1.013-01 2.883+01 2.973+01 XE-131M Ci 0.003+00 0.003+00 0.003+00 0.003+00 0.003+00 XE-133 Ci 4.603-01 9.13E-01 2.833+00 4.463+01 4.883+01 XE-133M Ci 0.003+00 0.003+00 0.003+00 0.003+00 0.003+00 XE-135 Ci 3.373+00 2.173+00 3.25E+OO 4.133+01 5.013+01 XE-135M Ci 6.75E+00 5.363-01 8.393-01 5.51E+00 1.363+01 XE-138 Ci 4.373-04 2.363-04 6.063-02 1.093+00 1.163+00 Totals for Period ... Ci 1.98E+01 1.003+01 8.983+00 1.853+02 2.243+02 Iodines 1-131 Ci 8.663-04 1.393-04 7.143-04 4.083-04 2.133-03 1-132 Ci 2.233-04 2.683-04 5.493-04 7.523-05 1.123-03 1-133 Ci 1.863-03 1,173-03 3.073-03 6.243-04 6.72E-03 1-134 Ci O.OOE+OO 0.003+00 0.003+00 9,263-05 9.263-05 1-135 Ci 1.50E-03 1.143-03 1.653-03 3.113-04 4.603-03 Totals for Period ... Ci 4.453-03 2.723-03 5.983-03 1,513-03 1.473-02 Particulates Half Life >= 8 days BA-140 Ci 0.003+00 0.003+00 0.003+00 3.383-06 3.383-06 CO-58 Ci 3.063-06 4.923-07 0.00E+00 0.003+00 3.553-06 CO-60 Ci 4.843-05 8.803-05 3.033-05 1,543-05 1.823-04 CR-51 Ci 1.823-04 9.043-06 2.673-06 0.003+00 1.943-04 CS-137 Ci 0.003+00 0.003+00 0.003+00 0.003+00 0.003+00 MN- 54 Ci 6.233-06 8.623-06 2.893-06 3.723-06 2.153-05 RU-106 Ci 4.133-06 0.003+00 O.OOE+OO O.OOE+OO 4.13E-06 SR-89 Ci 0.003+00 0.003+00 0.003+00 0.00E+00 0.003+00 ZN-65 Ci 2.823-06 0.003+00 0.003+00 1.183-05 1.463-05 Totals for Period. .. Ci 2.473-04 1.063-04 3.593-05 3.433-05 4.233-04 Tritium II H-3 Ci 9.733+00 1.163+01 1.05E+01 5.683+00 3.763+01 II Gross Alpha Radioactivity I ALPHA Ci 6.013-07 8.163-07 6.373-07 3,013-07 2.363-06 II Totals for Period ... Ci 6.016-07 8.163-07 6.373-07 3.013-07 2.363-06

TABLE 1D ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STARON UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radioactive Gaseous Waste Sampling and Analysis Program JANUARY - DECEMBER 2005 Lower Limit Sampling Minimum Analysis Type of Activity Analysis of Detection Gaseous Release Type Frequency Frequency (LLD)

( uCi/ml)a A. (1) Radwaste Building ~ 31 Days 31 Days Principal Gamma Ventilation Exhaust Grab Sample (9 Emitters (b,e)

H-3

~ (2) Fuel Handling Area Continuous 7 Days (c) 1-131 lx 10-I2 Ventilation Exhaust mf) Charcoal Sample 1-133 l x10-I0 (3) Containment Contin uous 7 Days (c) Principal Gamma lxlo-ll Ventilation Exhaust (d)(f) Particulate Sample Emitters (e) (1-131, Others)

(4) Turbine Building Cont inuous 31 Days Gross Alpha lxlO-ll Ventilation Exhaust (d)(f) Composite Particulate Sample Continuous 92 Days Sr-89, Sr-90 lxlo-ll (d)(f) Composite Particulate Samole Continuous (f) Noble Gas Monitor Noble Gases Gross IXlO+

Beta or Gamma B. (1) Offgas Post 31 Days Grab 31 Days Principal Gamma 1~10-~

Treatment Exha ust, Sample (f) Emitters (e) whenever there is flow (2) Standby Gas 31 Days Grab 31 Days Principal Gamma i~io-~

Treatment A Sample (f) Emitters(e)

Exhaust, whenever there is flow (3) Standby Gas 31 Days Grab 31 Days Principal Gamma i~io-~

Treatment B Sample (f) Emitters(e)

Exhaust, whenever there is flow NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.1L4-1.

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TABLE 2A ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES

1. Total Release Ci 2.993-02 8.413-03 2.773-02 1,423-02 8.013-02

2. Avg. Diluted Conc. uCi/ml 6.513-07 1,363-07 1.153-07 7.563-08 1,493-07

3. Percent of Limit % 8.163-01 5.083-01 9.473-01 2.773+00 2.403+00 Tritium

1. Total Release Ci 4.253+00 7.693+00 1.813+01 1.373+01 4.373+01

2. Avg. Diluted Conc. uCi/ml 9.273-05 1.243-04 7.483-05 7.323-05 8.153-05

3. Percent of Limit % 9.273-01 1.243+00 7.483-01 7.323-01 8.153-01 Dissolved and Entrained Gases

1. Total Release Ci 3.693-04 3.293-04 9.383-04 3.963-04 2.033-03

2. Avg. Diluted Conc. uCi/ml 8.053-09 5.333-09 3.883-09 2.12E-09 3.793-09

3. Percent of Limit % 4.033-03 2.673-03 1.943-03 1.063-03 1.903-03 Gross AlDha Radioactivitv II

~~~ ~~

1. Total Release Ci O.OOE+OO 0.003+00 0.003+00 0. E E + O O 0.003+00 Volume of liquid waste liters 6.793+05 9.153+05 2.693+06 2.523+06 6.813+06 Volume of dil. water liters 4.523+07 6.093+07 2.393+08 1.853+08 5.303+08 env-tec/ARERROl - 20

TABLE 2B ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT I RADIOACTIVE EFFLUENT AND W A Q E DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - CONTINUOUS AND BATCH MODES 2.993-05 2.233-05 1.4 63-04 AS-76 Ci 0.003+00 0.003+00 0.003+00 1.633-04 1.633-04 BA-140 Ci 2.593-05 0.003+00 0.003+00 0.003+00 2.593-05 CE-141 Ci 5.423-06 O.OOE+OO 0.003+00 0.003+00 5.423-06 CO-58 Ci 4.323-04 1.333-04 2.673-04 1.873-04 1.023-03 CO-60 Ci 1.253-03 1.073-03 1.963-03 9.363-04 5.213-03 CR-51 Ci 2.573-02 1.673-03 1.403-02 4.303-03 4.573-02 CS-134 Ci 0.003+00 0.003+00 1.533-05 4.943-06 2.023-05 CS-137 Ci 0.003+00 0.003+00 4.653-05 1.773-05 6.413-05 CU- 64 Ci 3.073-04 5.933-05 1.803-04 1.243-04 6.703-04 FE-55 Ci 2.483- 04 1.863-03 5.553-03 2.623-03 1.033-02 FE-59 Ci 2.363-05 3.403-04 3.153-04 2.llE-04 8.903-04 1-131 Ci 0.003+00 0.003+00 6.293-05 2.143-05 8.433-05 LA-140 Ci 1.153-04 5.073-05 7.913-05 0.003+00 2.453-04 MN-54 Ci 7.313- 04 2.683-03 4.473-03 8.693-04 8.753-03 NB-95 Ci 0.003+00 1.813- 05 0.003+00 O.OOE+OO 1.813- 05 RB-88 Ci O.OOE+OO 0.003+00 0.003+00 1.293-03 1.2 9E-03 RU-106 ci 0.003+00 0.003+00 0.003+00 1.663-05 1.663-05 SB-125 Ci 0.003+00 0.003+00 0.003+00 1.683-05 1.683-05 SR-89 Ci 0.003+00 6.123-05 9.133-05 0.003+00 1.523-04 SR-92 Ci 1.793-05 0.003+00 0.003+00 3.913-05 5.703-05 TC-99M Ci 2.863-06 0.003+00 0.003+00 0.003+00 2.863-06 ZN-65 Ci 9.243-04 4.703-04 5.273-04 3.313-03 5.233-03 ZN-6 9M Ci 0.003+00 0.003+00 5.353-05 0.00E+00 5.353-05 Totals for Period ... Ci 2.993-02 8.413-03 2.763-02 1.41E-02 8.01E-02 Tritium 1 H-3 Ci 4.253+00 7.693+00 1.813+01 1.373+01 4.373+01 3

Dissolved and Entrained Gases 1rppKR-85M Ci O.OOE+OO 0.003+00 0.00E+00 7.013-06 7.013-06 I1 KR-88 Ci O.OOE+OO 0.003+00 0.003+00 6.093-06 6.093-06 XE-133 Ci 3.00E-04 2.323-04 6.313-04 2.513-04 1.413-03 XE-135 Ci 6.953-05 9.743-05 3.073-04 1.323-04 6.053-04 Totals for Period ... Ci 3.693-04 3.29E-04 9.383-04 3.963-04 2.033-03 Gross Alpha Radioactivity 1 ** No Nuclide Activities *

0.00E+00 0.003+00 0.003+00 0.003+00 0.003+00 I env-t@ARERROl - 21

TABLE 2C ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT I RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM JANUARY - DECEMBER 2005 Lower Limit Sampling Minimum Analysis Liquid Release Type Frequency Frequency A. Batch Waste Release Prior to Release Prior to Release Principal Gamma Tanks (c) Each Batch Each Batch Emitters (d) 5xlO-1-131 lxlo-6 Prior to Release 3 1 Days Dissolved and IXIO-~

One Batch /M Entrained Gases (Gamma Emitters)

Prior to Release 3 1 Days H-3 1~10-~

Each Batch Composite (b) Gr o s s ipha IXIO-~

Prior to Release 92 Days Sr-89, Sr-90 5x 1O-Each Batch Composite (b) Fe-55 IXlO+

B. ssw Basin (Before Blowdown) Prior to Release Prior to Release Principal Gamma Each Biowdown Each Batch Emitters (d)

NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.1-1.

env-ter/ARERROl - 22

TABLE 3 ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY - DECEMBER 2005 A. SOILD WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

1. Type of Waste 1 Unit Class A Class B Class C Est. Total Error

a. Spent resins, filter sludges, evaporator bottoms, etc.

b. Dry compressible waste, 5.68E+01 7.83E-01 0.00 E+00 0.00 E+OO OmOOE+OO O.OOE+OO I contaminated equipment, etc. 0.OO E+00 O.OOE+OO

c. Irradiated componants, control rods, etc.

d. Other: Dry compressible 0.OO E+OO O.OOE+OO 0.OO E+OO 0.OO E+OO 8.04E+04 8.46E-01 I m3 7.37 E+02 waste, contaminated equipment, Ci 2.26E+02 spent resins for volume reduction

2. Estimate of Major Nuclide Composition ( by type of waste)

a. Spent resins, filter sludges, evaporator bottoms, etc.

Isotope (greater than 0.01 %) Percent Curies C-I 4 3.37E+00 2.64E-02 CO-58 6.63E-01 5.1 9E-03 Co-60 4.80E+00 3.76E-02 Cr-51 7.86E+00 6.1 6E-02 CS-I37 1.46E+00 1.I 4E-02 Fe-55 4.92E+01 3.86E-01 H-3 1.55E+01 1.21 E-01 Mn-54 7.21 E+OO 5.65E-02 Zn-65 8.83E+00 6.92E-02 CS-I34 8.95E-01 7.01 E-03

b. Dry compressible waste, contaminated equipment, etc.

Isotope (greater than 0.01 %) Percent Curies Cr-51 1.56E+00 3.21 E-02 Mn-54 8.92E+00 1.84E-01 Fe-55 7.51 E+01 I.55E+00 Fe-59 1.79E-01 3.70E-03 Co-58 3.32 E-01 6.84 E-03 CO-60 9.84 E+OO 2.03 E-01 Ni-63 1.61 E-01 3.32E-03 Zn-65

~~

3.41 E+OO 7.03E-02 Sr-89 1.42E-01 2.93E-03 Ag-I 1Om 1.23E-01 2.54E-03 CS-I 37 1.33E-01 2.74E-03 env-tec/ARERROl - 23

TABLE 3 ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT I RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY - DECEMBER 2005 (Cont)

c. Irradiated components, control rods, etc.

Isotope (greater than 0.01 %) Percent Curies Mn-54 I.37E+00 1.IOE+03

Fe-55 3.75E+01 3.01 E+04 CO-60 5.77E+0 1 4.64E+04 Ni-63 3.29E+00 2.65E+03

d. Other: Dry compressible waste, contaminated equipment, spent resins for volume reduct ion.

Isotope (greater than 0.01 %) Percent Curies Ce-144 1.40E-02 8.44E-02 CO-58 2.26E-01 I.36E+00 CO-60 I.49E+Ol 9.01 E+01 Cr-51 2.52E+00 1.52E+OI CS-I37 I.42E-01 8.56E-01 Fe-55 5.89E+01 3.55E+02 Fe-59 6.02E-01 3.63E+00 H-3 2.03E-02 1.22E-01 Mn-54 I.78E+01 1.07E+02 Mi-63 I.22E-01 7.36E-01 Sr-90 2.37E-02 1.43E-01 Zn-65 I 4.69E+00 I 2.83E+01

3. Solid Waste Dispostion Number of Mode of Destinations Name City Shipments State Transportation 6 Duratek, LLC OakRidge TN Truck I 1 Duratek, LLC OakRidge TN Truck Envirocare of Utah, Inc. Truck I Clive UT (Conta iner ized)

Envirocare of Utah, Inc. Truck 2 CIive UT (Containerized) 3 GTS Duratek-Gallaher Road Facility Oak Ridge TN Truck 10 I Studsvik I Erwin I TN I Truck 4 Studsvik Erwin I TN I Truck 4 Studsvik Erwin TN Truck 5 Chem. Nuclear Barnwell SC Truck em-iedARERR01 - 24

TABLE 3 ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT I RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY - DECEMBER 2005 (Cont)

3. Solid Waste Dispostion (Cont)

NRC Disposal Number of Description Waste Type Description Class Vo Iume(f t 3) Containers A 96 B-25 BOX 4 DAW-U-NA B25 BOX A 199.4 210 LINER 6 BR-D-NA SRT 210 Powdex A 199.4 13 CPSIRWCU-B (Studsvik)

(Studsv ik)

A 202 RWE ES-210 4 BR-D-NA SRT (RWE liner)

A 1280 20' SEALAND 17 DAW-U-NA 20FT SL A 1280 Shielded Sealand 1 DAW-U-NA 20FT SL B

~ 132.4 EL142 Polv HIC I

1 RWCU-A DAW/Filters/lrradiated C 120.3 8-120 POIYHIC 1 Hardware C 57.4 I 3-55 steel liner I 4 Irradiated Hardware B. Irradiated Fuel Shipments (Disposition)

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION None N/A N/A C. Annual Sewage Sludge Summary NUMBER OF AVERAGE Co-60 AVERAGE Mn-54 SHIPMENTS GALLONS ACTIVITY (pCi/kg) ACTIVITY (pCi/kg)

None NIA N/A N/A env-t&ARERROI - 25

AlTACHMENT I OFFSITE DOSE CALCULATION MANUAL env-tedARERRO1 - 26

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 31 - 12/05

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)

Changed wording in Section 1.2.1 so that the 32 12/2005 i, ii, vi, current dose calculation methodology may be vii, viia, used for storm drain release dose viib, calculations.

Reference:

LDC 2005-074 1.0-7,

Added outfall 007 collection site to Table 1.0-8, 3.0-2 and Figure 3.0-1.

Reference:

LDC 3.0-3, 2005-074 3.0-7, A-14,

Adds Storm Drain sampling frequency to Table A-17, 6.12.1-1.

Reference:

LDC 2005-074 A-51

Deletes Discharge Canal Flow as a required channel per Table 6.3.9-1 and allows use for flow estimation per Required Action 6.3.9 C.1.

Reference:

LDC 2004-095

Updates Introduction and Removes reference 31 12/2005 Cover page to UFSAR. Action to implement LDC 2005-022 i, ii, v,

- Removal of duplicate pages from Operating vii, Licensing Manual 1.0-15,

Revises description of reverse osmosis 1.0-16, equipment to allow operational flexibility. 1.0-17 Removes Figure 1.3 LDC 05047

Adds Distillate Sample Tank To Figure 1.3-1 30 08/2005 i, vii, 1.0-16

Updates and re-draws Figures 3.0-1 and 3.0- 29 01/2005 i, ii, v,

2. Figures were previously illegible. vii, viia, 3.0-1, 3.0-3, 3.0-3a, 3.0-4, 3.0-7, 3.0-8

Updates Figure 1.3-2 showing liquid radwaste 28 10/2004 Cover treatment system to improve legibility and Page, i, to show addition of reverse osmosis ii, iia equipment.

Reference:

LDC2003-044. (deleted),

Adds reporting requirements for solid waste iiia which is relocated from the PCP(Process (deleted),

Control Program) deletion in LDC2001-151 to iiib Section 5.6.3 of the ODCM. This information (deleted),

was already being reported and this change iiic is considered administrative in nature. (deleted)

Reference:

LDC2001-051. iii, iv, v, vi,

Section 5.6.3.b is revised to change the use vii, viia, of PSRC to OSRC. PSRC is no longer viic, used.

Reference:

LDC2001-051. 1.0-17, A-

The signature sign-off page in the front of 11, A-11a the ODCM is being deleted. This page is no longer needed since review and approvals will be documented in the LI-113 procedure form.

Reference:

LDC2004-077.

GRAND GULF, UNIT 1 i Revision 32 - 12/05

ODCM REVISION TABLE (cont.)

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)

A Revision Table is being added to allow a 28 10/2004 convenient place for readers and the NRC to determine a chronological listing of all of the changes including pages number and a description of the changes. This will allow easy tracking of ODCM changes to ensure all changes that occur in a year are properly reported to the NRC. This is considered an enhancement over existing practice which is to only show the latest revision information.

Reference:

LDC2004-077.

The Table of Contents was reformatted to be consistent with the Operating License Manual(OLM) and Updated Final Safety Analysis Report(UFSAR).

Reference:

LDC2004-077.

Other editorial changes are being made such as page consolidations and reformatting to align the look of the ODCM with other License Basis Documents (LBD) such as the OLM and UFSAR.

Reference:

LDC2004-077.

Removes shutdown statement if offgas pre- 27 05/2004 i, ii, treatment radiation monitor is inoperable vii, from LCO 6.3.10 and adds new actions to take viib, A-to ensure appropriate monitoring. 12a, A-

Adds a new LCO Section 6.0.1 which specifies 20, A-21 actions to be taken in the event LCO associated actions are not met. This change was needed based on removal of the shutdown statement from 6.3.10 and to ensure the ODCM is consistent with LCO 6.0.1 currently contained in UFSAR Appendix 16A-0 and 16B-0 and the TRM.

Reference:

LDC2004-025.

Added methodology to calculate a liquid 26 02/2004 i, ii, monitor setpoint for waste tanks with very vi,vii, low gamma activity.

Reference:

LDC2004-011 1.0-5, 1.0-5a GRAND GULF, UNIT 1 ii Revision 32 - 12/05

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) 2.0-24a 2.3.3 Deposition (Hourly Average) 2.0-25 2.4 DEFINITIONS OF GASEOUS EFFLUENTS PARAMETERS 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 28 - 10/04

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 28 - 10/04

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 Deleted 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 31 - 12/05

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.

GRAND GULF, UNIT 1 vi Revision 32 - 12/05

ODCM LIST OF EFFECTIVE PAGES Page No. Rev No. Page No. Rev No.

Cover Page 31 2.0-16c 25 i 32 2.0-16d 25 ii 32 2.0-16e 25 iii 28 2.0-16f 25 iv 28 2.0-17 25 v 31 2.0-18 25 vi 32 2.0-18a 25 vii 32 2.0-18b 25 viia 32 2.0-18c 25 viib 32 2.0-18d 25 2.0-18e 25 1.0-1 17 2.0-18f 25 1.0-2 17 2.0-18g 25 1.0-3 17 2.0-18h 25 1.0-4 15 2.0-19 25 1.0-5 26 2.0-20 25 1.0-5a 26 2.0-20a 25 1.0-6 21 2.0-20b 25 1.0-7 32 2.0-20c 25 1.0-8 32 2.0-20d 25 1.0-9 11 2.0-20e 25 1.0-10 0 2.0-20f 25 1.0-11 11 2.0-20g 25 1.0-12 0 2.0-20h 25 1.0-13 22 2.0-21 25 1.0-14 22 2.0-22 25 1.0-15 31 2.0-22a 25 1.0-16 31 2.0-22b 25 2.0-22c 25 2.0-1 17 2.0-22d 25 2.0-2 25 2.0-22e 25 2.0-3 2 2.0-22f 25 2.0-4 23 2.0-22g 25 2.0-5 24 2.0-22h 25 2.0-6 22 2.0-23 25 2.0-7 17 2.0-23a 25 2.0-8 25 2.0-23b 25 2.0-9 25 2.0-24 25 2.0-10 25 2.0-24a 25 2.0-10a 25 2.0-25 25 2.0-10b 17 2.0-26 17 2.0-11 22 2.0-27 25 2.0-12 22 2.0-28 5 2.0-13 21 2.0-29 21 2.0-14 21 2.0-15 25 2.0-16 25 2.0-16a 25 2.0-16b 25 GRAND GULF, UNIT 1 vii Revision 32 12/05

ODCM LIST OF EFFECTIVE PAGES Page No. Rev No. Page No. Rev No.

2.0-30 25 2.0-31 15 2.0-32 25 2.0-33 15 2.0-34 25 2.0-35 17 2.0-35a 8 2.0-36 20 2.0-37 20 3.0-1 29 3.0-2 20 3.0-3 32 3.0-3a 29 3.0-4 29 3.0-5 20 3.0-6 20 3.0-6a 20 3.0-6b 13 3.0-6c 20 3.0-6d 20 3.0-7 32 3.0-8 29 GRAND GULF, UNIT 1 viia Revision 32 12/05

ODCM LIST OF EFFECTIVE PAGES Page No. Rev No. Page No. Rev No.

APPENDIX A A-45 17 A-46 17 A-0 17 A-47 17 A-1 17 A-48 17 A-2 17 A-49 17 A-3 17 A-50 20 A-4 17 A-51 32 A-5 17 A-52 21 A-6 17 A-53 20 A-7 17 A-54 20 A-8 17 A-55 17 A-9 22 A-56 17 A-10 17 A-57 17 A-11 28 A-58 17 A-11a 28 A-59 20 A-12 17 A-60 20 A-12a 27 A-61 17 A-13 18 A-62 17 A-14 32 A-63 17 A-15 17 A-64 17 A-16 17 A-65 17 A-17 32 A-66 17 A-18 17 A-67 22 A-19 23 A-68 17 A-20 27 A-69 17 A-21 27 A-70 17 A-22 17 A-71 17 A-23 17 A-72 17 A-24 18 A-73 17 A-25 21 A-74 17 A-26 18 A-27 18 A-28 21 A-29 17 A-30 17 A-31 17 A-32 17 A-33 17 A-34 25 A-35 17 A-36 17 A-37 17 A-38 17 A-39 17 A-40 17 A-41 17 A-42 17 A-43 17 A-44 17 GRAND GULF, UNIT 1 viib Revision 32 12/05

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 setooints for liquid effluent monitors and flow measurement devices are set to assure that the following equation is satisfied:

cf I c F+f (1) where:

C = ten times the effluent concent ration 1.imit (LCO 6.1 1. 1) implementing 10CFR20 for the site, in @i/ml.

c= The setpoint, representative of a radioactivity concentration in pCi/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 GOLF, UNIT i i. O-i Revision i7 - 03i95

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 isotonic

--r--

concentratiofi for 2 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-l:

CC = ccg + ca + cc + Ct + Cf (2) i S i g S where:

CC = tha Cl*r c13rn VUlll nF L cnnrontrstinnc L*ALLIILLUCI,Id C =f az,rh LUL/lI mazc,,raA IIILuduALu nzmmx yuLuLLu gg 9 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.

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

GRAND GULF, UNIT 1 1.0-2 Revision 17 - 03/95

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

determined from analysis of the monthly composite sample.

C EC 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 __ow fl 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.

'i D.F. = [Z J x S.F.

i ECi c c c c c (3 a S t f

= [C -- + +C + + x S.F. (3)

EC g g ECa ' ECs ECt where:

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

GRAND GULF, UNIT 1 1.0-3 Revision 17 - 03/95

ECi = EC EC ECs,ECt and EC are ten times the 4' a' 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 Z.OE-4 uCi/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

d fd < z for >>f Fd 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.>l; for D.F.21, the waste L-.-1.errlue~it tari~ _T?z.__L concentration meets the limits of ten times the limiting concentrations of 10CFR20 without dilution, and fd may take on any desired value.

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= = 0.9 x minimum expected dilution flow rate(5)

Fd f= 0.9Xfd = 0.9 x calculated maximum waste tank flow rate for the stated release conditions.(6)

GRAND GULF, UNIT 1 1.0-4 Revision 15 - 01/94

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 x . C F, and f which were specified 1 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, S, the summation of the gamma emitters in the tank i s used and S, is determined as follows:

S,(cpm) = (fdf, x CC, x MRF)

Where :

f, = maximum permissible waste tank effluent flow rate

( gpm )

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

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

MRF = Monitor Response Factor (cpm/uCi/ml) (Figure l . 0 - 1 ) ( 1 7 )

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

If S,= 0, i.e. no gamma emitters present, then S, = 2700 cpm Or If S, < (Monitor Error x Background), then S, = (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 26 - 02/04

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 cal bration error)( 1 7 ) .

The liquid monitor trip setpoint = S, + 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 I

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 26 - 02/04

Figure 1.0-l Example Calibration Curve for Liquid Effluent Monitor I I I I I I I I I l.OEU5 i.OE46 l.OE-07 l.OEJX l.OE+Ol l.OE+o2 l.OE+O3 l.OE+O4 GRAND GULF, UNIT 1 1.0-6 Revis on 21 - 2/97

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 µCi/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 µCi/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 32 - 12/05

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

µCi 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 32 - 12/05

TABLE 1.2-l BIOACCUMULATION FACTORS, (BFi)

(pCi/kg per pCi/liter)*

FRESHWATER ELEMENT FISH INVERTEBRATE H 9.OE-01 9.OE-01 C 4.6E+03 9.1Et03 NA l.OE+02 2.OEt02 P l.OEt05 2.OEt04 CR 2.OEt02 2.OEt03 MN 4.OEt02 9.OEt04 FE l.OEt02 3.2EtO3 co 5.OEtOl 2.OEt02 NI l.OEt02 l.OEt02 cu 5.OEtOl 4.OEt02 ZN 2.OE+03 i.OEt04 BR 4.2EtO2 3.3Et02 RB 2.OE+03 l.OEt03 SR 3.OEtOl l.OEt02 Y 2.5EtOl l.OEt03 ZR 3.3EtOO 6.7EtOO NB 3.OE+04 l.OEt02 MO l:OEtnl l:OEtQl TC 1.5EtOl 5.OEtOO RU l.OE+Ol 3.OEt02 RH l.OE+Ol 3.OEt02 SB l.OEtOO l.OEtOl TE 4.OE+02 6.1Et03 1 1.5E+Ol 5.OEtOO cs 2.OE+03 l.OEt03 BA 4.OE+OO 2.OEt02 LA 2.5Et.01 l.OEt03 CE l.OEtOO l.OEt03 PR 2.5EtOl l.OEt03 ND 2.5E+Ol l.OE+03 W 1.2E+03 l.OEtOl NP l.OE+Ol 4.OEt02

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

GRAND GULF, UNIT 1 1.0-9 Revision 11 - 06/88

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

(mrem per pCi ingested)

Page 1 of 3 NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA l.O5E-07 l.O5E-07 l.O5E-07 l.O5E-07 l.O5E-07 l.O5E-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 l.ZOE-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-0.7 MN 54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 MN 56 NO DATA l.l5E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 FE 55 2*75E-06 1.9OE-06 4.43E-07 NG DATA NO n7\'PA u-1-n 1 .""U nc;c_nr; "V i nar-nc;""

I."_JY FE 59 4.34E-06 l.OZE-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.4OE-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 Z.lOE-07 NO DATA 7.10E-06 ZN 65 4.84E-06 1.54E-05 6.96E-06 NO DATA l.O3E-05 NO DATA 9.7OE-06 ZN 69 l.O3E-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 Z.llE-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 RB 88 nnTn NO LA1 c;

.I_n?F-n8 V 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 4.943-05 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 2.7OE-05 SR 92 2.15E-06 NO DATA 9.3OE-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 l.OZE-04 Y 91M 9.09E-11 NO DATA 3.523-12 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 0 - 08/82

TABLE 1.2-2 (Continued)

INGESTION DOSE CONVERSION FACTORS FOR ADULTS, (DF$

~..._

Cmrem Iner__ nCi L- inaestedi

__ ___>_L ~~~,

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 l.O5E-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 8.2OE-07 NO DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E-10 6.98E-10 8.89E-09 NO DATA l.O6E-08 3.42E-10 4.13E-07 TClOl 2.54E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1.87E-10 l.lOE-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 1.783-04 AGllOM 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91E-07 NO DATA 6.04E-05 SB124 2.8OE-06 5.29E-08 l.llE-06 6.79E-09 0.0 2.18E-06 7.95E-05 SB125tD 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.0 1.38E-06 1.97E-05 SB126 l.l5E-06 2.343-08 4.15E-07 7.04E-09 0.0 7.05E-07 9.4OE-05 SB127 2.58E-07 5.65E-09 9.90E-08 3.10E-09 0.0 1.53E-07 5.9OE-05 TE125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 l.O9E-05 NO DATA l.O7E-05 TE127M 6.??E-06 2,42E-06 8_75F-07

-_____ 1,73E-06 2.75E-05 NO DATA 2.27E-05 TE127 l.lOE-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE129M l.l5E-05 4.29E-06 1.82E-06 3.95E-06 4.8OE-05 NO DATA 5.79E-05 TE129 3.14E-08 l.l8E-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 8.4OE-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../lE-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 l.O2E-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 l.O2E-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 l.O6E-07 2.88E-07 l.O3E-07 4.99E-06 4.58E-07 NO DATA 2.51E-10 I 135 4.43E-07 l.l6E-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 11 - 06/88

TABLE 1.2-2 (Continued)

INGESTION DOSE CONVERSION FACTORS FOR ADULTS, (DFi)

(mrem per pCi ingested)

Page 3 of 3 1\1TlPT TrJD I"UbYIYY cmhvz YLY T.TTTFR AdI 1 _I\ T~. unny yvy~ TFTYROID KIDNEY LUNG GI-LLI cs137 7.97E-05 l.O9E-04 7.14E-05 NO DATA 3.7OE-05 1.23E-05 2.11E-06 CS138 5.52E-08 l.O9E-07 5.4OE-08 NO DATA 8.01E-08 7.91E-09 4.65E-13 BA139 9.7OE-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 TTL?",?

LfilLfV 2.5OE-09 1.26E-09 3.33E-10 KG DATA NG DATA NO nA'Pn u-I= a 75r_nc, J.LdY "_

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 9.2OE-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 l.O3E-07 8.61E-08 3.01E-08 NO DATA NO DATA NO DATA 2.82E-05 NP239 l.l9E-09 l.l7E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.4OE-05

Values taken from Reference 3, Table E-11 GRAND GULF, UNIT 1 1.0-12 Revision 0 - 08/82

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 O.OOe+OO 2.26e-01 2.26e-01 2.26e-01 2.26e-01 2.26e-01 O.OOe+OO 2.26e-01 c-14 3.13e+04 6.26e+03 6.26e+03 6.26e+03 6.26e+03 6.26e+03 O.OOe+OO 6.26e+03 NA-24 4.07e+02 4.07e+02 4.07e+02 4.07e+02 4.07e+02 4.07e+02 O.OOe+OO 4.07e+02 P-32 4.62e+07 2.87e+06 O.OOe+OO O.OOe+OO O.OOe+OO 5.19e+06 O.OOe+OO 1.79e+06 CR-51 O.OOe+OO O.OOe+OO 7.61e-01 2.81e-01 1.69e+OO 3.20e+02 O.OOe+OO 1.27e+OO MN-54 O.OOe+OO 4.38e+03 O.OOe+OO 1.30e+03 O.OOe+OO 1.34e+04 O.OOe+OO 8.35e+02 MN-56 O.OOe+OO l.lOe+02 O.OOe+OO 1.40e+02 O.OOe+OO 3.51e+03 O.OOe+OO l.P5e+Ol FE-55 6.58e+02 4.55e+02 O.OOe+OO O.OOe+OO 2.54e+02 2.61e+02 O.OOe+OO l.O6e+02 FE-59 l.O4e+03 2.44e+03 O.OOe+OO O.OOe+OO 6.82e+02 8.14e+03 O.OOe+OO 9.36e+02 CO-58 O.OOe+OO 8.92e+Ol O.OOe+OO O.OOe+OO O.OOe+OO 1.81e+03 O.OOe+OO 2.00e+02 CO-60 O.OOe+OO 2.56e+02 O.OOe+OO O.OOe+OO O.OOe+OO 4.81e+03 O.OOe+OO 5.65e+02 NI-63 3.11e+04 2.16e+03 O.OOe+OO O.OOe+OO O.OOe+OO 4.50e+02 O.OOe+OO l.O4e+03 NI-65 1.26e+02 1.64e+Ol O.OOe+OO O.OOe+OO O.OOe+OO 4.17e+02 O.OOe+OO 7.49e+OO CU-64 O.OOe+OO P.P7e+OO O.OOe+OO 2.51e+Ol O.OOe+OO 8.50e+02 O.OOe+OO 4.68e+OO ZN-65 2.32e+04 7.37e+04 O.OOe+OO 4.93e+04 O.OOe+OO 4.64e+04 O.OOe+OO 3.33e+04 ZN-69 4.93e+Ol 9.43e+Ol O.OOe+OO 6.13e+Ol O.OOe+OO 1.42e+Ol O.OOe+OO 6.56e+OO BR-83 O.OOe+OO O.OOe+OO O.OOe+OO O.OOe+OO O.OOe+OO 5.82e+Ol O.OOe+OO 4.04e+Ol BR-84 O.OOe+OO O.OOe+OO O.OOe+OO O.OOe+OO O.OOe+OO 4.11e-04 O.OOe+OO 5.24e+Ol BR-85 O.OOe+OO O.OOe+OO O.OOe+OO O.OOe+OO O.OOe+OO O.OOe+OO O.OOe+OO 2.15e+OO RB-86 O.OOe+OO l.Ole+05 O.OOe+OO O.OOe+OO O.OOe+OO l.P9e+04 O.OOe+OO 4.71e+04 RB-88 O.OOe+OO 2.90e+02 O.OOe+OO O.OOe+OO O.OOe+OO 4.00e-09 O.OOe+OO 1.54e+02 RB-89 O.OOe+OO l.P2e+02 O.OOe+OO O.OOe+OO O.OOe+OO l.l2e-11 O.OOe+OO 1.35e+02 SR-89 2.21e+04 O.OOe+OO O.OOe+OO O.OOe+OO O.OOe+OO 3.55e+03 O.OOe+OO 6.35e+02 SR-90 5.44e+05 O.OOe+OO O.OOe+OO O.OOe+OO O.OOe+OO 1.57e+04 O.OOe+OO 1.34e+05 SR-91 4.07e+02 O.OOe+OO O.OOe+OO O.OOe+OO O.OOe+OO 1.94e+03 O.OOe+OO 1.64e+Ol SR-92 1.54e+02 O.OOe+OO O.OOe+OO O.OOe+OO O.OOe+OO 3.06e+03 O.OOe+OO 6.68e+OO y-90 5.76e-01 O.OOe+OO O.OOe+OO O.OOe+OO O.OOe+OO 6.10e+03 O.OOe+OO 1.54e-02 Y-91 8.44e+OO O.OOe+OO O.OOe+OO O.OOe+OO O.OOe+OO 4.64e+03 O.OOe+OO 2.26e-01 Y-91M 5.44e-03 O.OOe+OO O.OOe+OO O.OOe+OO O.OOe+OO 1.60e-02 O.OOe+OO 2.11e-04 Y-92 5.06e-02 O.OOe+OO O.OOe+OO O.OOe+OO O.OOe+OO 8.86e+02 O.OOe+OO 1.48e-03 Y-93 1.60e-01 O.OOe+OO O.OOe+OO O.OOe+OO O.OOe+OO 5.09e+03 O.OOe+OO 4.43e-03 ZR-95 2.40e-01 7.70e-02 O.OOe+OO 1.21e-01 O.OOe+OO 2.44e+02 O.OOe+OO 5.21e-02 ZR-97 1.33e-02 2.68e-03 O.OOe+OO 4.04e-03 O.OOe+OO 8.30e+02 O.OOe+OO 1.22e-03 NB-95 4.47e+02 2.48e+02 O.OOe+OO 2.46e+02 O.OOe+OO 1.51e+06 O.OOe+OO 1.34e+02 MO-99 O.OOe+OO l.O3e+02 O.OOe+OO 2.34e+02 O.OOe+OO 2.39e+02 O.OOe+OO 1.96e+Ol TC-PPM 8.87e-03 2.51e-02 O.OOe+OO 3.81e-01 1.23e-02 1.48e+Ol O.OOe+OO 3.19e-01 TC-101 P.l2e-03 1.31e-02 O.OOe+OO 2.37e-01 6.72e-03 3.95e-14 O.OOe+OO 1.29e-01 RU-103 4.43e+OO O.OOe+OO O.OOe+OO 1.69e+Ol O.OOe+OO 5.17e+02 O.OOe+OO l.Ple+OO RU-105 3.69e-01 O.OOe+OO O.OOe+OO 4.76e+OO O.OOe+OO 2.26e+02 O.OOe+OO 1.46e-01 RU-106 6.58e+Ol O.OOe+OO O.OOe+OO 1.27e+02 O.OOe+OO 4.26e+03 O.OOe+OO 8.33e+OO AG-11OM 8.81e-01 8.15e-01 O.OOe+OO 1.60e+OO O.OOe+OO 3.33e+02 O.OOe+OO 4.84e-01

Calculated .from Equation 8.

GRAND GULF, UNIT 1 1.0-13 Revision 22 - 03/99

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+OO 1.27e-01 1.63e-02 O.OOe+OO 5.22e+OO 1.90e+02 o.oOe+OO 2.66e+OO SB-125 4.29e+OO 4.79e-02 4.36e-03 O.OOe+OO 3.30e+OO 4.72e+Ol O.OOe+OO l.O2e+OO TE-125M 2.57e+03 9.30e+02 7.72e+02 l.O4e+04 o.OOe+OO l.O2e+04 o.oOe+OO 3.44e+O2 TE-127 l.O5e+02 3.7ae+ol 7.80e+01 4.29e+02 O.OOe+OO 8.31e+03 O.OOe+OO 2.2ae+ol TE-127M 6.48e+03 2.32e+03 1.66e+03 2.63e+04 O.OOe+OO 2.17e+04 O.OOe+OO 7.90e+02 TE-129 3.01e+Ol l.l3e+Ol 2.31e+Ol 1.26e+02 O.OOe+OO 2.27e+Ol O.OOe+OO 7.33e+OO TE-129M l.lOe+04 4.11e+03 3.78e+03 4.60e+04 O.OOe+OO 5.54e+04 O.OOe+OO 1.74e+03 TE-131 1.89e+Ol 7.88e+OO 1.55e+Ol 8.26e+Ol O.OOe+OO 2.67e+OO O.OOe+OO 5.96e+OO TE-131M 1.66e+03 8.10e+02 1.28e+03 8.21e+03 O.OOe+OO a.o4e+04 O.OOe+OO 6.75e+02 TE-132 2.41e+03 1.56e+03 1.72e+03 1.50e+04 O.OOe+OO 7.3ae+04 O.OOe+OO 1.47e+03 I-130 2.71e+Ol a.ole+Ol 6.79e+03 1.25e+02 O.OOe+OO 6.89e+ol O.OOe+OO 3.16e+Ol I-131 1.49e+02 2.14e+02 7.00e+04 3.66e+02 O.OOe+OO 5.64e+Ol O.OOe+OO 1.22e+02 I-132 7.29e+OO 1.95e+Ol 6.82e+02 3.11e+Ol O.OOe+OO 3.66e+OO O.OOe+OO 6.82e+OO I-133 5.10e+Ol a.a7e+ol 1.30e+04 1.55e+02 O.OOe+OO 7.97e+Ol O.OOe+OO 2.70e+Ol I-134 3.81e+OO l.O3e+Ol 1.79e+02 1.64e+Ol O.OOe+OO 9.01e-03 O.OOe+OO 3.70e+OO I-135 1.59e+Ol 4.17e+Ol 2.75e+03 6.68e+Ol O.OOe+OO 4.70e+Ol O.OOe+OO 1.54e+Ol cs-134 2.98e+05 7.09e+05 O.OOe+OO 2.29e+05 7.61e+04 1.24e+04 O.OOe+OO 5.79e+05 CS-136 3.12e+04 1.23e+05 O.OOe+OO 6.85e+04 9.38e+03 1.40e+04 O.OOe+OO 8.86e+04 cs-137 3.82e+05 5.22e+05 O.OOe+OO 1.77e+05 5.89e+04 l.Ole+04 O.OOe+OO 3.42e+05 cs-138 2.64e+02 5.22e+02 O.OOe+OO 3.84e+02 3.79e+Ol 2.23e-03 O.OOe+OO 2.59e+02 BA-139 9.29e-01 6.62e-04 O.OOe+OO 6.19e-04 3.75e-04 1.65e+OO O.OOe+OO 2.72e-02 BA-140 1.94e+02 2.44e-01 O.OOe+OO 8.30e-02 1.40e-01 4.00e+02 O.OOe+OO 1.27e+Ol BA-141 4.51e-01 3.41e-04 O.OOe+OO 3.17e-04 1.93e-04 2.13e-10 O.OOe+OO 1.52e-02 BA-142 2.04e-01 2.10e-04 O.OOe+OO 1.77e-04 l.l9e-04 2.87e-19 O.OOe+OO 1.2ae-02 LA-140 1.50e-01 7.54e-02 O.OOe+OO O.OOe+OO O.OOe+OO 5.54e+03 O.OOe+OO 1.99e-02 LA-142 7.66e-03 3.4ae-03 O.OOe+OO O.OOe+OO O.OOe+OO 2.54e+Ol O.OOe+OO 8.6ae-04 CE-141 2.24e-02 1.52e-02 O.OOe+OO 7.04e-03 O.OOe+OO 5.79e+Ol O.OOe+OO 1.72e-03 CE-143 3.95e-03 2.92e+OO O.OOe+OO 1.29e-03 O.OOe+OO l.O9e+02 O.OOe+OO 3.23e-04 CE-144 l.l7e+OO 4.88e-01 O.OOe+OO 2.90e-01 O.OOe+OO 3.95e+02 O.OOe+OO 6.27e-02 PR-143 5.51e-01 2.21e-01 O.OOe+OO 1.27e-01 O.OOe+OO 2.41e+03 O.OOe+OO 2.73e-02 PR-144 1.80e-03 7.4ae-04 O.OOe+OO 4.22e-04 O.OOe+OO 2.59e-10 O.OOe+OO 9.16e-05 ND-147 3.76e-01 4.35e-01 O.OOe+OO 2.54e-01 O.OOe+OO 2.09e+03 O.OOe+OO 2.60e-02 w-187 2.96e+02 2.47e+02 O.OOe+OO O.OOe+OO O.OOe+OO a.lOe+04 O.OOe+OO 8.65e+Ol NP-239 2.85e-02 2.aoe-03 O.OOe+OO 8.74e-03 O.OOe+OO 5.75e+02 O.OOe+OO 1.54e-03 SB-126 2.75e+OO 5.62e-02 1.69e-02 O.OOe+OO 1.69e+OO 2.25e+02 O.OOe+OO 9.94e-01 SB-127 6.18e-01 1.35e-02 7.42e-03 O.OOe+OO 3.66e-01 1.41e+02 O.OOe+OO 2.37e-01

Calculated from Equation 8.

GRAND GULF, UNIT 1 1.0-14 Revision 22 - OX/99

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 31 - 12/05

LIQUID RADWASTE TREATMENT SYSTEM STEAM TURBINE REACTOR CONDENSER FROM MISCELLANEOUS SURGE TANK WASTE CONDENSATE CONDENSATE STORAGE TANK DEMINERALIZER H PURITY WASTE EQUIPMENT DRAINS A. CONTAINMENT &

DRYWELL BLDG EQUIPMENT DRAINS WASTE* PRECOAT

MIXED BED

SAMPLE RADIATION MONITOR B. AUXILIARY BLDG COLLECTION FILTER DEMINERALIZER TANKS COOLING C. TURBINE BLDG TANK TOWER D. RADWASTE BLDG FILTER CAKE TO WCU DECANT SOLID WASTE ALTERNATIVE LIQUID RADIOACTIVE WASTE PROCESSING SYSTEM W PURITY WASTE DISTILLATE LOOR DRAIN SUMPS SAMPLE A. CONTAINMENT &

DRYWELL BLDG FLOOR DRAINS WASTE

PRECOAT

MIXED BED

SAMPLE TANK B. AUXILIARY BLDG FILTER DEMINERALIZER TANKS COLLECTION TANK C. TURBINE BLDG D. RADWASTE BLDG FILTER CAKE TO SOLID WASTE ISCELLANEOUS WASTE CHEMICAL DRAINS COOLING TOWER REGENERATION STATION BLOWDOWN SOLUTION NEUTRALIZER DISCHARGE RECEIVING TANK INTAKE MISCELLANEOUS CHEMICAL WASTE

MISSISSIPPI RIVER FROM PRECOAT TANK FILTER EFFLUENT D GULF, UNIT 1 1.0-16 REVISION 31, 12/05

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 PFxR xD t TB

= the lesser of or PFxR xD 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-l Revision 17 - 3/95

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

= C f [ X/Q c Ki a',]

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 I

AREAS inside the SITE BOUNDARY from Table 2.2-3a or Table 2.2-3b I Ki = total body dose factor due to gamma emissions from each noble gas radionuclide i (mrem/yr per pCi/m3) from ODCM Table 2.1-1 QIi = rate of release of noble gas radionuclide i (pCi/sec) from the release point R = count rate (cpm) per mrem/yr to the skin S

= C f X/Q [Xi (Li + 1.1 Mi) Q v i 1 L . = skin dose factor due to beta emissions from isotope i 1

3 (mrem/yr per pCi/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 1

3 (mrad/yr per pCi/m ) from ODCM Table 2.1-1 GRAND GULF, UNIT 1 2.0-2 Revision 25 - 01/03

2.1.2 TEXT DELETED GRAND GULF, UNIT 1 2.0-3 Revision 2 - 05/84

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 DTP x Rt" 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 11 = conservative count rate per mrem/yr to the total body (Xe-133 t

detection, composite dose factor)

= (3.533-5) (60)

%% (X) WI (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 23 - 03/01

where :

X = Xe-133 volume efficiency factor of the detector system in pCi/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 t 03 mrem/yr per pCi/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.

I

- ODCM Reference 11 GRAND GULF, UNIT 1 2.0-5 Revision 24 - 11/02

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*** 2.693+03 9.303+03 3.283+03 KR-83M 7.563-02 O.OOE+OO 1.93E+Ol 2.883+02 KR-85 1.61E+Ol 1.343+03 1.72E+Ol 1.953+03 KR-85M l.l7E+03 1.463+03 1.233+03 1.973+03 KR-87 5.923+03 9.733+03 6.173+03 l.O3E+04 KR-88 1.473+04 2.373+03 1.523+04 2.933+03 KR-89 1.663+04 l,OlE+04 1.733+04 l.O6E+04 KR-90 1.563+04 7.293+03 1.633+04 7.833+03 XE-131M 9.15E+Ol 4.763+02 1.563+02 l.llE+03 XE-133 2.943+02 3.063+02 3.533+02 l.O5E+03 XE-133M 2,51E+Q2 9,943+02 3.273+02 1.483+03 XE-135 1.81E+03 1.863+03 1.923+03 2.463+03 XE-135M 3.123+03 7.11E+02 3.363+03 7.393+02 XE-137 l-423+03 1.223+04 1.51E+03 1.273+04 XE-138 8.833+03 4.133+03 9.213+03 4.753+03 Values taken from Reference 3, Table B-l

mrad - m3 pCi - yr

- mrem - m3 pCi - yr

- - 8.84E+O3 = 8.84 x 10' GRAND GULF, UNIT 1 2.0-6 Revision 22 - 03/99

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 C Ki Q D = average skin dose rate in current year s

(mrem/yr)

= X/Q c (L. + l.lMi) (2.

1 1

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 0

(mredyr)

= CW P: (2:

where:

GRAND GULF, UNIT 1 2.0-7 Revision 17 - 03/95

W = highest historical annual average atmospheric dispersion at the SITE BOUNDARY or UNRESTRICTED I

AREAS inside the SITE BOUNDARY for the appropriate pathway from Table 2.2-3a or 2.2-333.

I Use for inhalation and all tritium pathways I or Use for food and ground plane pathways I

= the total dose parameter for radionuclide i f i'

3 (mrem/yr per pCi/m ) f o r inhalation and all tritium pathways and (m2 . mrem/yr per pCi/sec) for food and ground plane pathways, from ODCM QIi =

Table 2.2-la*

rate of release of noble gas radionuclide i I

(pCi/sec) f r o m the release point Q i i = average release rate of isotope i o f tritium, 1-131, 1-133 or other radionuclide in particulate form, with half-lives greater than eight (8) days in the current year (pCi/sec)

Most limiting age group, infant, is assumed via grass/cow/milk pathway for food .

GRAND GULF, UNIT 1 2.0-8 Revision 25 - 01/03

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 A R W S within the SITE BOUNDARY shall be determined as follows :

D = air dose due to gamma emissions from noble gas Y

radionuclide i (mrad)

= 3.17 x 10-8 EM. x/Q' Qi

1 I

where :

x/52' = highest historical annual average atmospheric for the SITE BOUNDARY or at UNRESTRICTED A R W S I

within the SITE BOUNDARY from Table 2.2-3a or 2.2-3b.

M. = air dose factor due to gamma emissions from 1

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

from ODCM Table 2.1-1 GRAND GULF, UNIT 1 2.0-9 Revision 25 - 01/03

Qi = cumulative release of radionuclide i of noble gas, tritium, 1-131, 1-133, or material in particulate form over the period of interest

( pCi )

Note : 3.17 x lo-* is the inverse of the number of seconds per year, and D = air dose due to beta emissions from noble gas P

radionuclide i (mrad)

= 3.17 x 10

-8 c

i N.

1 m' Qi where :

= air dose factor due to beta emissions from Ni 3

noble gas radionuclide i (mrad/yr per pCi/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.

Qi = cumulative release of radionuclide i of noble gas, tritium, 1-131, 1-133, or material in particulate form over the period of interest

( pCi 1 GRAND GULF, UNIT 1 2.0-10 Revision 25 - 01/03

2.2.2 Unrestricted Area Dose to Individual

b. Dose to an individual from tritium, 1-131, 1-133 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, 1-131, 1-133 P

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

-8

= 3.17 x 10 CRi W ' Qi 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 I pathways or D/Q' = for food and ground plane pathways 1 R. = the total dose factor for radionuclide i, 1

3 (mrem/yr per pCi/m ) for inhalation and all tritium pathways and (m2 mrem/yr per pCi/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.

G W D GULF, UNIT 1 2.0-10a Revision 25 - 01/03

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

gas, tritium, I-i3i, I-i33, or material in particulate form over the period of interest (Wi)

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 Y P' D) freF. pre~~iollr nneratinn

-=-------II hitory fnnrmallv the previous

\-----------1 P

six months) which is indicative of future expected operations.

GRAND GULF, UNIT 1 2.0-10b Revision 17 - 03/95

TABLE 2.2-la PATHWAY DOSE FACTORS FOR LCO 6.11.4 and SECTION Z.Z.l.b, (Pi)

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

ISOTOPE INHALATION GROUND PLANE FOOD H-3 6.473+02 O.OOE+OO 2.383+03 c-14 2.653+04 O.OOE+OO 2.343+09 NA-24 l.O6E+04 1.993+07 1.563+07 P-32 2.033+06 O.OOE+OO 1.60E+ll CR-51 1.283+04 7.853+06 4.703+06 MN-54 l.OOE+06 1.293+09 3.903+07 MN-56 7.173+04 1.523+06 2.843+00 FE-55 8.693+04 O.OOE+OO l-353+08 FE-59 l.O2E+06 4.563+08 3.923+08 CO-58 7.773+05 6.183+08 6.053+07 CO-60 4.513+06 5.173+09 2.10E+08 NI-63 3.393+05 O.OOE+OO 3.493+10 NI-65 5.01E+04 4.933+05 3.02E+Ol CU-64 1_50E+04 9.803+05 3.773+06 ZN-65 6.473+05 7.903+08 1.90E+lO ZN-69 1.323+04 O.OOE+OO 2.853-09 BR-83 3.813+02 l.OlE+04 9.273-01 BR-84 4.00E+02 3.383+05 l-323-22 BR-85 2.04E+Ol O.OOE+OO O.OOE+OO RB-86 1.90E+05 1.473+07 2.233+10 RB-88 5_c;7K!+n3 dIYII 5_4OE+O4 1.883-44 RB-89 3.213+02 2.11E+05 3.413-52 SR-89 2.033+06 3.563+04 1.26E+lO SR-90 4.093+07 O.OOE+OO 1.22E+ll SR-91 7.343+04 3.583+06 3.193+05 SR-92 1.40E+05 1.233+06 4.963+01 Y-90 2.693+05 7.593+03 9.423+05 Y-91 2.453+06 1.70E+06 5.253+06 Y-91M 2.793+03 1.663+05 2.033-15 Y-92 1.273+05 3.063+05 l.O2E+Ol Y-93 1.673+05 3.583+05 l-693+04 ZR-95 1.753+06 3.993+08 8.263+05 ZR-97 1.40E+05 4.923+06 4.443+04 NB-95 4.793+05 2.293+08 2.063+08

?,"A I","_99 1.353+05 c CArn#f-lLC

".""CIT"" 3 .lOE+OS TC-99M 2.033+03 3.01E+05 1.643+04 TC-101 8.443+02 3.233+04 4.883-57 RU-103 5.523+05 1.80E+08 l.O5E+05 RU-105 4.84E+04 l.O3E+06 3.18E+OO RU-106 l.l6E+07 3.593+08 1.453+06 AG-11OM 3.673+06 3.653+09 1.46E+lO GRAND GULF, UNIT 1 2.0-11 Revision 22 - 03/99

TABLE 2.2-la (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.4 and SECTION 2.2.l.b, (Pi)

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

ISOTOPE INHALATION GROUND PLANE FOOD TE-125M 4.473+05 3_01E+06 1.51E+08 TE-127 2.443+04 4.703+03 1.353+05 TE-127M 1.31E+06 1.40E+05 l.O4E+09 TE-129 2.633+04 4.413+04 1.81E-07 TE-129M 1.683+06 3.303+07 1.393+09 TE-131 8.223+03 4.933+07 1.41E-30 TE-131M 1.993+05 1.353+07 2.293+07 TE-132 3.403+05 7.093+06 6.51E+07 I-130 1_60E+06 9.553+06 8.713+08 I-131 1.483+07 2.983+07 l.O5E+12 I-132 1.693+05 2.093+06 1.363+02 I-133 3.563+06 4.263+06 9.593+09 I-134 4.453+04 7.573+05 7.873-10 I-135 6.963+05 4.213+06 2.01E+07 cs-134 7.033+05 3.283+09 6.80E+lO CS-136 1.353+05 2.443+08 5.813+09 cs-137 6.123+05 1.343+09 6.02E+lO CS-138 8.763+02 5.863+05 2.093-22 BA-139 5.10E+04 1.70E+05 2.713-05 BA-140 1.60E+06 3.353+07 2.413+08 BA-141 4.753+03 6.793+04 5.083-44 BA-142 l-553+03 7.233+04 1.673-79 LA-140 1.683+05 3.123+07 1.883+05 LA-142 5.953+04 1.30E+06 l.O8E-05 CE-141 5.173+05 2.203+07 1.373+07 CE-143 l.l6E+05 3.753+06 1.533+06 CE-144 9.843+06 6.773+07 1.333+08 PR-143 4.333+05 O.OOE+OO 7.843+05 PR-144 4.283+03 3.023+03 l-133-48 ND-147 3.223+05 l-443+07 5.733+05 W-187 3.963+04 3.903+06 2.483+06 NP-239 5.953+04 2.833+06 9.423+04 Units: Inhalation2and all tritium pathways - mrem/yr per pCi/m3 Others - m . mrem/yr per pCi/sec Values based on standard NUREG-0133, Section 5.2.1 assumptions unless otherwise indicated.

^_ I_^

GRAND GULF, UNIT 1 2.0-12 Revision 22 - U3/YY

I TABLE 2.2-lb TEXT DELETED GRAND GULF, UNIT 1 2.0-13 Revision 21 - 12/97

TABLE 2.2-lb (Continued)

TEXT DELETED GRAND GULF, UNIT 1 2.0-14 Revision 21 - 12/97

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

Page 1 of 8 Release Type: 2 Gaseous Dose Factor: 2 Ri (m"2 * (mrem/yr)/ (uCi/sec) or (mrem/yr)/ (uCi/m"3)) I AgeGroup: 3 INFANT Pathway: 0 Ground Plane Deposition (GPD)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 C-14 NA- 24 P-32 CR- 51 MN-54 MN-56 FE-55 FE-59 CO- 58 CO- 60 NI-63 NI-65 CU-64 ZN-65 ZN-69 BR- 83 BR- 84 BR- 85 RB- 86 RB-88 RB-89 SR-89 SR- 90 SR- 91 SR-92 Y-90 Y-91 Y-91M Y-92 Y-93 ZR-95 ZR-97 NB-95 MO- 99 TC-99M TC-101 RU-103 RU-105 RU-106 AG- 11OM TE-125M TE-127 TE-127M TE-129 TE-129M TE-131 TE-131M GRAND GULF, UNIT 1 2.0-15 Revision 25 - 01/03

TABLE 2.2-2a (Continued)

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

Page 2 of 8 R e l e a s e Type: 2 Gaseous D o s e Factor: 2 R i (m"2 * ( m r e m / y r ) / ( u C i / s e c ) o r (mrem/yr) / (uCi/m"3) ) I AgeGroup: 3 INFANT Pathway: 0 G r o u n d Plane D e p o s i t i o n (GPD)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 1-130 1-131 1-132 1-133 1-134 1-135 CS-134 CS-136 CS-137 CS-138 BA-139 BA-140 BA-141 BA-142 LA-140 LA-142 CE-141 CE-143 CE-144 PR-143 PR-144 ND-147 W-187 NP-239 GRAND GULF, UNIT 1 2.0-16 Revision 25 - 01/03

TABLE 2.2-2a (Continued)

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

Page 3 of 8 Release Type: 2 Gaseous Dose Factor: 2 Ri (m"2 * (mrem/yr)/ (uCi/sec) or (mrem/yr)/ (uCi/mA3))

AgeGroup: 3 INFANT Pathway: 1 Inhalation (INHL)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TE 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 5.31et-03 5.31e+03 5.31e+03 0.00e+00 5.31e+03 NA-24 1.06e+04 1.06e+04 1.06ef04 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 5.75ei-01 1.32ef01 1.28e+04 3.57ef02 0.00e+00 8.95e+01 MN-54 0.00e+00 2.53e+04 0.00e+00 4.98e+03 1.00eS06 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 0.00et00 0.00e+00 1.02e+06 2.48e+04 0.00e+00 9.48e+03 CO-58 O.OOe+OO 1.22e+03 0.00e+00 0.00e+00 7.77e+05 1.lle+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 0.00ef00 1.23e-01 CU-64 0.00e+00 1.88e+00 0.00et00 3.98ef00 9.30ef03 1.50ef04 0.00ei-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 0.00eS00 0.00eS00 0.00e+00 0.00e+00 3.81e+02 BR- 84 0.00eS00 O.OOe+OO O.OOe+OO 0.00eS00 0.00eS00 O.OOe+OO 0.00ef00 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 0.00eS00 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 1.12ef07 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 2.45ef06 7.03ef04 0.00et-00 1.57ef04 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 1.15et-05 2.79e+04 0.00ef00 3.11eS04 1.75e+06 2.17e+04 0.00e+00 2.03ef04 ZR-97 1.50e+02 2.56e+01 O.OOe+OO 2.59e+01 1.10e+05 1.40e+05 0.00e+00 1.17e+01 NB-95 1.57e+04 6.43e+03 0.00et00 4.72e+03 4.79e+05 1.27e+04 0.00et00 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 8.11eS02 2.03e+03 0.00e+00 3.72e-02 TC-101 6.51e-05 8.23e-05 0.00e+00 9.79e-04 5.84ef02 8.44ef02 O.OOe+OO 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 0.00ei.00 8.99e-01 1.57e+04 4.84e+04 0.00ei-00 4.10e-01 RU-106 8.68e+04 0.00e+00 0.00e+00 1.07e+05 1.16eS07 1.64e+05 0.00e+00 1.09e+04 AG- 11OM 9.98e+03 7.22e+03 0.00e+00 1.09e+04 3.67e+06 3.30e+04 0.00e+00 5.00et-03 TE-125M 4.76e+03 1.99e+03 1.62ef03 O.OOe+OO 4.47e+05 1.29e+04 0.00e+00 6.58e+02 TE-127 2.23ei-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 0.00eS.00 1.88e-02 TE-129M 1.41e+04 6.09ei-03 5.47e+03 3.18e+04 1.68e+06 6.90e+04 0.00e+00 2.23et-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 5.50ef01 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 25 - 01/03

TABLE 2.2-2a (Continued) i Page 4 of 8 Release Type: 2 Gaseous Dose Factor: 2 Ri (mA2 * (mredyr)/ (uCi/sec) or (mrem/yr)/ (uCi/mA3) ) I AqeGroup: 3 INFANT Pathway: 1 Inhalacion ( I N H L )

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 3.72e~C22.37e+02 2.79e+02 1.04e+03 3.40e+05 4.41e+04 0.00et00 1.76e+02 7-130 6.36et03 1.39e+04 1.60e+06 1.53e+04 0.00e+00 1.99e+03 0.00e+00 5.57e+03 1-131 3.79e+04 4.44e+04 1.48et07 5.18e+04 0.00e+00 l.O6e+03 0.00e+00 1.96e+04 1-1.32 1.69e+03 3.54e+03 1.69et05 3.95et03 0.00ei.00 1.90ei-03 0.00e+00 1.26e+03 1-133 1.32e+04 1.92e+04 3.56e+06 2.24et04 0.00et-00 2.16e+G3 0.00eS00 5.60e+03 1-134 9.21et02 1,88e+03 4.45e+04 2,09e+03 0.COet00 1.29ei-03 0.00e+00 6.65ef02 1-135 3.86e+03 7.60e-t03 6.96e-05 8.47e+03 0.00e+00 1.83eSO3 0.00e+00 2.77e+03 CS-134 3.96e+05 7.03e+05 O.OOe+OO 1.90e+05 7.97et04 1.33e+03 0.00e+00 7.45e+04 CS-136 &.83e+O4 1.35ef05 0.00et00 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 7.13ei.04 1.33e+03 0.00e+00 4.55e+04 CS-138 5.05e+02 7.8le+02 0.00et00 4.10e+02 6.54e+31 8.76e+02 0.00et00 3.98et02 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 5.6Cet-04 5.60et01 0.03e+00 1.34e+01 1.60e+06 3.84e+O4 0.00e+00 2.90e+03 BA-141 1.57e-01 1.08e-04 0.00ei-00 6.50e-05 2.97e+03 4.75et03 0.00e+00 4.97e-03 BA-142 3.98e-02 3.30e-05 O.OOe+OO 1.90e-05 1.55e+03 6.93e+02 0.00et00 1.96e-03 LA-140 5.05e+02 2.00e+02 0.00e+00 O.GOe+OO 1.68e+05 8.48e+04 0.00e+00 5.15e+01 LA-142 1.03e+00 3.77e-01 0.30e+00 0.00e+O0 8.22e+03 5.95et04 0.00et00 9.04e-02 CE-141 2.77e+04 1.67e+04 0.00e+00 5.25e+03 5.17e105 2.16e+04 O.OOe+OO 1.99e+03 CE-143 2.93e+02 1.93e+02 0.00e+00 5.64e+01 1.16e+C5 4.97e+04 0.00e+00 2.21et01 CE-144 3.19e+06 1.21eiG6 0.00et00 5.38e+05 9.84eSG6 1.48e+05 C.00e+00 1.76e+05 PR-143 1.40e+04 5.24er03 0.00e+00 1.97e+03 4.33e+05 3.72e+04 0.00e+00 6.99ei02 PR-144 4.79e-02 1.85e-02 0.00e+00 6.72e-03 1.61et03 4.28et03 0.00e+00 2.41e-03 ND - 147 7.94e+03 8.13e+03 0.00e+00 3.15et03 3.22et-05 3.12e+04 0.00eS00 5.00et02 w-187 1.30e+01 9.02et00 O.COe+03 0.00e+0C 3.96et04 3.56e+04 0.00e+00 3.12et00 NP-239 3.71e+02 3.32e+01 0.00e+00 6.62e+01 5.95e+04 2.49e+04 0.00et00 1.88e+01 GRAND GULF, UNIT 1 2.0-1Sb Revision 25 - 01/03

TABLE 2 . 2 - 2 a (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 A N D SECTION 2 . 2 . 2 . b , (Ri)

Page 5 of 8 Release Type: 2 Gaseous Dose Factor: 2 Ri (m"2 * (mrem/yr)/ (uCi/sec) or (mrem/yr)/ (uCi/m"3)) I 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 2.0-16~ Revision 25 - 01/03

TABLE 2 . 2 - 2 a (Continued)

PATHWAY DOSE FACTORS FOR LCO 6 . 1 1 . 6 AND SECTION 2 . 2 . 2 . b , (Ri)

P a g e 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 R e v i s i o n 25 - 01/03

TABLE 2.2-2a (Continued)

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

Page 7 of 8 Release Type: 2 Gaseous Dose Factor: 2 Ri (m"2 * (mrem/yr)/ (uCi/sec) or (mrem/yr)/ (uCi/m"3)) I 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 0.00ef00 5.00ef08 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 6.21ef09 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 3.90ef07 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 1.35eS08 8.73e+07 0.00e+00 0.00e+00 4.27e+07 l.lleS.07 0.00e+00 2.33e+07 FE-59 2.24e+08 3.92e+08 O.OOe+OO O.OOe+OO 1.16e+08 1.87e+08 O.OOe+OO 1.54e+08 CO-58 0.00e+00 2.43e+07 0.00e+00 0.00eS00 0.00e+00 6.05ef07 0.00eS00 6.05e+07 CO-60 0.00ei-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 0.00eS00 1.84e+05 0.00e+00 3.11e+05 0.00e+00 3.77e+06 0.00e+00 8.51et-04 ZN-65 5.55e+09 1.90e+10 0.00e+00 9.23e+09 0.00e+00 1.61e+10 0.00e+00 8.78ef09 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 O.OOe+OO O.OOe+OO 0.00ei.00 0.00e+00 0.00e+00 9.27e-01 BR- 84 0.00ef00 0.00eS00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.32e-22 BR- 85 O.OOe+OO 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00ef00 RB- 86 0.00e+00 2.23e+10 0.00eS00 O.OOe+OO 0.00ef00 5.69e+08 O.OOe+OO 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 0.00eS00 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 O.OOe+OO 0.00e+00 O.OOe+OO 0.00e+00 2.59e+08 O.OOe+OO 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 0.00ei.00 1.71e-01 Y-90 6.82e+02 0.00e+00 0.00e+00 0.00e+00 0.00e+00 9.42e+05 0.00eS00 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 O.OOe+OO 0.00eS00 0.00e+00 2.03e-15 0.00e+00 2.08e-20 Y-92 5.37e-04 0.00e+00 0.00e+00 0.00et-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 1.69ef04 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 2.08ef08 0.00e+00 3.10e+08 0.00e+00 6.84e+07 0.00e+00 4.05e+07 TC-99M 2.74ei-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 O.OOe+OO 2.90e+03 RU-105 8.00e-03 0.00e+00 0.00et-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 2.25et-05 0.00e+00 1.45e+06 0.00e+00 2.38e+04 AG- 11OM 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 5.08ei.07 O.OOe+OO 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 O.OOe+OO 1.35e+05 0.00e+00 1.39e+03 TE-127M 4.21e+08 1.40eS08 1.22e+08 1.04e+09 0.00e+00 1.70eS08 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 1.91eS08 2.14e+08 1.39e+09 0.00e+00 3.33e+08 0.00ef00 8.58e+07 TE-131 3.49e-32 1.29e-32 3.11e-32 8.91e-32 0.00et-00 1.41e-30 0.00e+00 9.79e-33 TE-131M 3.38e+06 1.36e+06 2.75e+06 9.35e+06 0.00et-00 2.29e+07 0.00e+00 1.12eS06 GRAND GULF, UNIT 1 2.0-16e Revision 25 - 01/03

TABLE 2.2-2a (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 A N D SECTION 2.2.2.b, (Ri)

Page 8 of 8 Release Type: 2 Gaseous Dose Factor: 2 Ri (m"2 * (mrem/yr)/ (uCi/sec) or (mrem/yr)/ (uCi/m"3)) I 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 1.54e3-07 6.51e+07 0.00e+00 3.85et07 0.00e+00 9.71e+06 1-130 3.53e+06 7.77e+06 8.71e+08 8.53e+06 O.OOe+OO 1.67et06 0.00e+00 3.12e+06 1-131 2.72e+09 3.20e+09 1.05e+12 3.74e+09 0.00e+00 1.14e+08 0.00e+00 1.41e+09 1-132 1.43e+00 2.91e+00 1.36e3.02 3.25e+00 0.00e+00 2.36et00 0.00e+00 1.04e+00 1-133 3.62e+07 5.28e+07 9.59e+09 6.20et07 0.00e+00 8.93e+06 0.00e+00 1.55e+07 1-134 1.65e-11 3.37e-11 7.87e-10 3.77e-11 0.00e+00 3.49e-11 0.00e+00 1.20e-11 1-135 1.13e+05 2.25e+05 2.01ef07 2.50e+05 0.00e+00 8.13e+04 0.00e+00 8.19ei-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-i-002.32e+09 4.73e+08 8.82e+07 0.00e+00 2.17e+09 CS-137 5.15e+10 6.02e+10 0.00et-00 1.62eS10 6.55e+09 1.88et08 0.00eS00 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 0.00et00 5.72e+04 1.48e+05 5.92et07 0.00eS00 1.24e+07 BA-141 4.16e-45 2.85e-48 0.00e3.00 1.71e-48 1.73e-48 5.08e-44 0.00e+00 1.31e-46 BA-142 4.05e-80 3.37e-83 0.00e3.00 1.94e-83 2.04e-83 1.67e-79 0.00et00 1.99e-81 LA-140 4.06e+01 1.60e+01 0.00e+00 0.00e+00 0.00ei.00 1.88e+05 0.00e+00 4.12et00 LA-142 1.73e-10 6.35e-11 0.00e+00 0.00ef00 0.00e+00 1.08e-05 0.00e+00 1.52e-11 CE-141 4.34e+04 2.64e+04 0.00ef00 8.15e+03 0.00e+00 1.37et07 0.00e+00 3.11e+03 CE-143 3.96e+02 2.63e-t-050.00e+00 7.65e+01 0.00e+00 1.53et-06 0.00e+00 3.00e+01 CE-144 2.33e+06 9.52ef05 0.00e+00 3.85e+05 0.00e+00 1.33e+08 0.00e+00 1.30et05 PR-143 1.49e+03 5.56e+02 0.00et00 2.07e+02 O.OOe+OO 7.84e+05 0.00eS00 7.37et01 PR-144 6.25e-53 2.42e-53 0.00ef00 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 5.54et01 W-187 6.08e+04 4.23e+04 0.00eS00 0.00e+00 0.00ef00 2.48ef06 0.00e+00 1.46e+04 NP-239 3.64et01 3.26e+00 0.00e+00 6.50e-t-000.00e+00 9.42e+04 0.00et00 1.84et00 3

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

GRAND GULF, UNIT 1 2.0-16f Revision 25 - 01/03

TABLE 2.2-233 PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R.1 Page 1 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m"2 * (mrem/yr)/ (uCi/sec) or (mrem/yr)/ (uCi/mA3)) I AgeGroup: 2 CHILD Pathway: 0 Ground Plane Deposition (GPD)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB H-3 C-14 NA-24 P-32 CR-51 MN-54 MN-56 FE-55 FE-59 CO-58 CO-60 NI-63 NI-65 CU-64 ZN-65 ZN-69 BR- 83 BR- 84 BR- 85 RB- 86 RB- 88 RB-89 SR-89 SR-90 SR-91 SR-92 Y-90 Y-91 Y-91M Y-92 Y-93 ZR-95 ZR-97 NB-95 MO- 99 TC-99M TC-101 RU-103 RU-105 RU-106 AG- 11OM TE-125M TE-127 TE-127M TE-129 TE-129M TE-131 TE-131M GRAND GULF, UNIT 1 2.0-17 Revision 25 - 01/03

TABLE 2.2-2b (Continued)

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

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 1-130 1-131 1-132 1-133 1-134 1-135 CS-134 CS-136 CS-137 CS-138 BA-139 BA-140 BA-141 BA-142 LA-140 LA-142 CE-141 CE-143 CE-144 PR-143 PR-144 ND-147 W-187 NP-239 GRAND GULF, UNIT 1 2.0-18 Revision 25 - 01/03

TABLE 2.2-2b (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 A N D SECTION 2.2.2.b, (Ri)

Page 3 of 10 H-3 0.00e+00 1.13e+03 C-14 3.59e+04 6.73e+03 NA-24 1.61e+04 1.61e+04 P-32 2.61e+06 1.14e+05 CR-51 0.00e+00 0.00e+00 MN-54 0.00e+00 4.29ei-04 MN-56 0.00e+00 1.66e+00 FE-55 4.74e+04 2.52e+04 FE-59 2.07e+04 3.35e+04 CO-58 0.00e+00 1.77e+03 CO-60 0.00e+00 1.31e+04 NI-63 8,21e+05 4.63e+04 NI-65 2.99e+00 2.96e-01 CU-64 0.00e+00 1.99e+00 ZN-65 4.26e+04 1.13e+05 ZN-69 6.70e-02 9.66e-02 BR- 83 0.00e+00 0.00e+00 BR- 84 0.00e+00 O.OOe+OO BR- 85 0.00e+00 0.00e+00 RB- 86 0.00e+00 1.98e+05 RB- 88 O.OOe+OO 5.62e+02 RB- 89 0.00e+00 3.45e+02 SR-89 5.99e+05 0.00e+00 SR-90 1.01e+08 0.00e+00 SR-91 1.21et02 0.00e+00 SR-92 1.31e-t.010.00e+00 Y-90 4.11e+03 0.00e+00 Y-91 9.14e+05 0.00e+00 Y-91M 5.07e-01 0.00e+00 Y-92 2.04e+01 0.00e+00 Y-93 1.87e+02 0.00e+00 ZR-95 1.90e+05 4.18e+04 ZR-97 1.88e+02 2.72e+01 NB-95 2.35e+04 9.18e+03 MO- 99 0.00e+00 1.72e+02 TC-99M 1.78e-03 3.48e-03 TC-101 8.10e-05 8.51e-05 RU-103 2.79e+03 O.OOe+OO RU-105 1.53e+00 0.00e+00 RU-106 1.36e+05 0.00e+00 AG- 11OM l169e+04 1.14e+04 TE-125M 6.73e+03 2.33e+03 TE-127 2.77e+00 9.51e-01 TE-127M 2.49e+04 8.55e+03 TE-129 9.77e-02 3.50e-02 TE-129M 1.92e+04 6.85e+03 TE-131 2.17e-02 8.44e-03 TE- 131M 1.34e+02 5.92e+01 GRAND GULF, UNIT 1 2.0-18a Revision 25 - 01/03

TABLE 2.2-233 (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 A N D SECTION 2.2.2.b, (Ri)

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 1-130 8.18e+03 1.64e+04 1.85ef06 2.45e+O4 0.00e+00 1-131 4.81e+04 4.81e+04 1.62e+07 7.88e+04 O.OOe+OO 1-132 2.12ef03 4.07ei.03 1.94e+05 6.25e+03 0.00e+00 1-133 1.66e+04 2.03e+04 3.85ei-06 3.38ef04 0.00e+00 1-134 1.17e+03 2.16e+03 5.07e+04 3.30e+03 0.00e+00 1-135 4.92e+03 8.73e+03 7.92e+05 1.34e+04 0.00e+00 CS-134 6.51e+05 1.01e+06 0.00ei-00 3.30e+05 1.21e+05 CS-136 6.51e+04 1.71e+05 0.00e+00 9.55e+04 1.45e+04 CS-137 9.07e-t.058.25e+05 0.00e+00 2.82e+05 1.04e+05 CS-138 6.33e+02 8.40e+02 0.00e+00 6.22ef02 6.81e+01 BA-139 1.84e+00 9.84e-04 0.00ef00 8.62e-04 5.77e+03 BA-140 7.40e+04 6.48e+01 0.00ef00 2.11e+01 1.74e+06 BA-141 1.96e-01 1.09e-04 0.00e+00 9.47e-05 2.92et-03 BA-142 5.00e-02 3.60e-05 0.00e+00 2,91e-05 1.64e+03 LA-140 6.44e+02 2.25e+02 0.00et-00 0.00e+00 1.83e+05 LA-142 1.29e+OO 4.11e-01 0.00e+00 0.00e+00 8.70e+03 CE-141 3.92ei-04 1.95e+04 0.00e+00 8.55e+03 5.44e+05 CE-143 3.66e+02 1.99e+02 0.00e+00 8.36e+01 1.15e+05 CE-144 6.77e+06 2.12e+06 0.00ef00 1.17e+06 1.20e+07 PR-143 1.85e+04 5.55e+03 0,00e+00 3,00e+03 4.33e+05 PR-144 5.96e-02 1.85e-02 0.00ef00 9.77e-03 1.57e+03 ND-147 1.08e+04 8.73e+03 0.00e+00 4.81e+03 3.28e+05 W-187 1.63e+01 9.66e+00 0.00e+00 0.00et-00 4.11e+04 NP-239 4.66e+02 3.35e+01 0.00e+00 9.73e+01 5.81e+04 G W D GULF, UNIT 1 2.0-18b Revision 25 - 01/03

TABLE 2.2-2b (Continued)

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

Page 5 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m"2 * (mrem/yr)/ (uCi/sec) or (mrem/yr)/ (uCi/m"3)) I AgeGroup: 2 CHILD Pathway: 2 Vegetation (VEG)

H-3 0.00e+00 4.01e-t.034.01e+03 4.01e+03 4.01e+03 4.01e+03 O.OOe+OO 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-2 4 3.75e+05 3.75e+05 3.75e+05 3.75e+05 3.75e+05 3.75e+05 0.00ef00 3.75e+05 P-32 3.36e+09 1.57e+08 0.00e+00 0.00e+00 0.00ei.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 4.22ei-00 FE-55 8.01e+08 4.25et-08 0.00e+00 0.00ei.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 0.00ei.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 3.95ef10 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 O.OOe+OO 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 6.60ef03 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 0.00eS00 0.00e+00 0.00eS00 0.00e+00 0.00e+00 O.OOe+OO 5.35e+00 BR- 84 0.00e+00 0.00e+00 0.00e+00 O.OOe+OO 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 2.91ef07 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 1.39ei-09 0.00e+00 1.03e+09 SR-90 1.24e+12 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.68ei-10 0.00e+00 3.15e+11 SR-91 5.22e+05 0.00e+00 0.00e+00 0.00e+00 0.00ei-00 1.15e+06 0.00e+00 1.97e+04 SR-92 7.24e+02 0.00e+00 0.00e+00 0.00e+00 0.00eS00 1.37ef04 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 0.00et-00 6.18e+02 Y-91 1.87e+07 0.00e+00 0.00ef00 O.OOe+OO 0.00e+00 2.49ef09 0.00e+00 4.99e+05 Y- 91M 9.23e-09 0.00e+00 0.00ef00 0.00e+00 O.OOe+OO 1.81e-05 0.00ef00 3.36e-10 Y-92 1.58e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.57e+04 O.OOe+OO 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 5.70ei-02 8.23e+01 0.00e+00 1.18e+02 0.00e+00 1.25e+07 0.00e+00 4.86e+01 NB-95 4.10ef05 1.60e+05 0.00e+00 1.50e+05 0.00e+00 2.95e+08 0.00ef00 1.14eS05 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 3.96ef08 0.00e+00 5.89e+06 RU-105 9.13ef01 0.00e+00 0.00e+00 8.02e+02 0.00e+00 5.96ef04 0.00e+00 3.31eS01 RU-106 7.45ef08 0.00e+00 0.00ef00 1.01e+09 0.00e+00 1.16eS.10 0.00e+00 9.30e+07 AG- 11OM 3.21e+07 2.17e+07 0.00ef00 4.04e+07 0.00eS00 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 2.35ei-08 2.71e+08 2.47e+09 0.00e+00 1.03eS09 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 0.00ei.00 7.71e-16 TE-131M 1.54e+06 5.33e+05 1.10ei-06 5.16e+06 0.00e+00 2.16e+07 0.00e+00 5.67e+05 GRAND GULF, UNIT 1 2.0-18~ Revision 25 - 01/03

TABLE 2.2-213 (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 O.OOe+OO 3.73e+06 1-130 6.14e+05 1.24e+06 1.37e+08 1.85e+06 0.00ei-00 5.80e+05 0.00e+00 6.39e+05 1-131 1.43e+08 1.44e+08 4.75e+10 2.36e+08 0.00e+00 1.28e+07 0.00e+00 8.17e+07 1-132 9.23e+01 1.70e+02 7.87e+03 2.60e+02 0.00e+00 2.00e+02 0.00e+00 7.80e+01 1-133 3.53ef06 4.36e+06 8.11et-08 7.27e+06 0.00e+00 1.76e+06 0.00e+00 1.65e+06 1-134 1.50e-04 2.78e-04 6.40e-03 4.26e-04 0.00e+00 1.85e-04 0.00e+00 1.28e-04 1-135 6.28e+04 1.13e+05 1.00eS-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 8.16et-09 2.93e+09 1.42ef08 0.00e+00 5.55e+09 CS-136 8.23e-t.072.26e+08 0.00ei.00 1.21e+08 1.80e+07 7.95e+06 0.00e+00 1.46e+08 CS-137 2.39e+10 2.29e+10 0.00ei-00 7.46e+09 2.69e+09 1.43et-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 0.00et-00 2.31e-05 1.56e-05 2.86e+00 0.00e+00 1.44e-03 BA-140 2.77e+08 2.43e+05 0.00ei-00 7.90e+04 1.45et-05 1.40e+08 0.00eS00 1.62e+07 BA-141 2.04e-21 1.14e-24 0.00e+00 9.90e-25 6.72e-24 1.16e-21 0.00eS00 6.65e-23 BA-142 4.06e-39 2.92e-42 0.00e+00 2.36e-42 1.72e-42 5.29e-41 0.00et-00 2.26e-40 LA-140 3.25ei-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 0.00ei00 0.00e+00 0.00ei-00 2.14e+01 0.00e+00 3.38e-05 CE-141 6.56e+05 3.27e+05 0.00ei-00 1.43e+05 0.00eS00 4.08e+08 0.00e+00 4.85ei.04 CE-143 1.72e+03 9.30e+05 0.00e+00 3.90e+02 0.00eS00 1.36e+07 0.00ei-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 2.37ei-04 0.00e+00 1.57ef08 0.00e+00 7.24e+03 PR-144 5.64e-26 1.74e-26 0.00et-00 9.22e-27 0.00e+00 3.75e-23 0.00e+00 2.84e-27 ND-147 7.14e+04 5.79e+04 0.00ei.00 3.17e+04 0.00e+00 9.16e+07 0.00e+00 4.48e+03 W-187 6.43e+04 3.81ei-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 O.OOe+OO 1.36e+07 0.00e+00 1.29e+02 GRAND GULF, UNIT 1 2.0-18d Revision 25 - 01/03

TABLE 2.2-2b (Continued)

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

Page 7 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m"2 * (mrem/yr)/ (uCi/sec) or (mrem/yr)/ (uCi/mA3))

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 2.34ei-02 2.34ei-02 2.34e+02 2.34ef02 O.OOe+OO 2.34e+02 C-14 3.83ef08 7.67e+07 7.67e+07 7.67e+07 7.67e+07 7.67e+07 0.00e+00 7.67e+07 NA-2 4 1.84e-03 1.84e-03 1.84e-03 1.84e-03 1.84e-03 1.84e-03 O.OOe+OO 1.84e-03 P-32 7.41e+09 3.47e+08 0.00eS00 0.00e+00 0.00e+00 2.05e+08 0.00eS00 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 m-54 0.00e+00 8.01e+06 0.00eS00 2.25e+06 0.00e+00 6.72e+06 0.00e+00 2.13ef06 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 4.49ef07 0.00ei.00 7.51e+07 FE-59 3.76e+08 6.08e+08 0.00e+00 O.OOe+OO 1.76e+08 6.34e+08 0.00eS00 3.03e+08 CO-58 0.00e+00 1.64e+07 O.OOe+OO 0.00e+00 0.00e+00 9.59e+07 0.00e+00 5.03ef07 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 0.00eS00 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 0.00eS00 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 O.OOe+OO 1.67e-07 ZN-65 3.75e+08 1.00e+09 0.00e+00 6.30e+O8 0.00et-00 1.76ef08 0.00e+00 6.22ef08 ZN-69 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00et-00 0.00e+00 0.00e+00 0.00e+00 BR- 83 0.00et00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 O.OOe+OO 8.89e-57 BR- 84 0.00e+00 0.00ef00 0.00e+00 0.00e+00 O.OOe+OO 0.00e+00 0.00e+00 0.00e+00 BR- 85 0.00e+00 0.00ef00 0.00e+00 0.00e+00 O.OOe+OO 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 0.00et-00 0.00e+00 0.00e+00 0.00et-00 RB- 89 0.00e+00 0.00ef00 0.00e+00 0.00ef00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 SR-89 4.81e+08 0.00e+00 0.00eS00 0.00e+00 0.00ei.00 1.86e+07 0.00e+00 1.38e+07 SR-90 1.04e+10 0.00ef00 0.00e+00 0.00e+00 0.00e+00 1.40eS08 0.00ef00 2.64ef09 SR-91 2.26e-10 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.99e-10 O.OOe+OO 8.54e-12 SR-92 1.69e-49 0.00e+00 0.00e+00 0.00ei00 O.OOe+OO 3.19e-48 0.00e+00 6.76e-51 Y-90 1.73e+02 0.00e+00 0.00e+00 0.00ei-00 0.00eS00 4.92e+05 0.00eS00 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 4.82ef04 Y-91M 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00ei00 0.00eS00 0.00e+00 0.00e+00 Y- 92 2.37e-39 0.00eS00 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 2.23et09 0.00ef00 8.61e+05 MO- 99 0.00e+00 1.14e+05 0.00e+00 2.44et.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 0.00eS00 0.00e+00 0.00e+00 0.00e+00 RU-103 1.55e+08 0.00ei-00 0.00e+00 3.90e+08 0.00e+00 4.00e+09 0.00e+00 5.95ef07 RU-105 8.48e-28 O.OOe+OO 0.00e+00 7.45e-27 0.00e+00 5.53e-25 0.00eS00 3.08e-28 RU-106 4.44e+09 0.00ef00 0.00e+00 5.99e+09 0.00e+00 6.90e+10 0.00e+00 5.54e+08 AG- 11OM 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 5.50ef08 0.00eS00 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 4.78ef08 4.24e+08 5.06e+09 0.00e+00 1.44ef09 0.00e+00 2.11eS08 TE-129 0.00e+00 0,00e+00 0.00e+00 0.00e+00 0.00e+00 0.00ef00 0.00ei-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 0.00et-00 0.00e+00 0.00ef00 0.00e+00 0.00e+00 TE-131M 6.97e+02 2.41e+02 4.96e+02 2.33ef03 0.00e+00 9.78e+03 0.00eS00 2.57e+02 GRAND GULF, UNIT 1 2.0-18e Revision 25 - 01/03

TABLE 2.2-2b (Continued)

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

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 1.35eS06 8.57e+06 0.00e+00 9.30e+06 O.OOe+OO 1.12e+06 1-130 2.92e-06 5.89e-06 6.49e-04 8.81e-06 0.00e+00 2.76e-06 0.00e+00 3.04e-06 1-131 1.65e+07 1.66e+07 5.50e+09 2.73e+07 0.00e+00 1.48e+06 0.00e+00 9.45e+06 1-132 1.05e-58 1.93e-58 8.93e-57 2.95e-58 O.OOe+OO 2.27e-58 0.00e+00 8.85e-59 1-133 5.64e-01 6.98e-01 1.30e+02 1.16e+00 0.00e+00 2.81e-01 0.00e+00 2.64e-01 1-134 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1-135 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 4.69ei-08 1.68e+08 8.16e+06 0.00et-00 3.19e+08 CS-136 1.62e+07 4.45e+07 0.00e+00 2.37e+07 3.54e+06 1.57e+06 0.00et-00 2.88e+07 CS-137 1.33e+09 1.28e+09 0.00e+00 4.16e+08 1.50e+08 7.99ef06 0.00eS00 1.88e+08 CS-138 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 O.OOe+OO 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 0.00ef00 1.25e+04 2.29e+04 2.22e+07 O.OOe+OO 2.56e+06 BA-141 O.OOe+OO 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 0.00eS00 O.OOe+OO 0.00e+00 0.00e+00 LA-140 5.66e-02 1.98e-02 0.00ef00 0.00e+00 0.00ef00 5.52e+02 0.00et.00 6.67e-03 LA-142 6.20e-92 1.98e-92 0.00e+00 0.00e+00 0.00eS00 3.92e-87 0.00e+00 6.19e-93 CE-141 2.22e+04 1.11e+04 0.00e+00 4.85e+03 0.00eS00 1.38e+07 0.00e+00 1.64e+03 CE-143 3.14e-02 1.70e+Ol 0.00e+00 7.14e-03 0.00ef00 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+O8 O.OOe+OO 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 O.OOe+OO 0.00ei-00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 ND-147 1.17e+04 9.46ei.03 0.00e+00 5.19e+03 0.00e+00 1.50e+07 0.00ei-00 7.32e+02 W-187 3.21e-02 1.90e-02 0.00e+00 0.00ei-00 0.00ef00 2.67et-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 0.00eS00 2.14e-02 GRAND GULF, UNIT 1 2.0-18f Revision 25 - 01/03

TABLE 2.2-2b (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R.1 Page 9 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m"2 * (mrem/yr)/ (uCi/sec) or (mrem/yr)/ (uCi/m"3)) 1 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 2.39ei-08 2.39ef08 0.00e+00 2.39ef08 NA-2 4 8.93e+06 8.93e+06 8.93e+06 8.93e+06 8.93e+06 8.93e+06 0.00ef00 8.93e+06 P-32 7.77e+10 3.64e+09 0.00e+00 0.00e+00 0.00e+00 2.15e+09 0.00ef00 3.00e+09 CR-51 0.00e+00 0.00e+00 5.65et-04 1.54e+04 1.03e+05 5.40e+06 0.00e+00 1.02ei-05 MN-54 O.OOe+OO 2.10eS07 0.00e+00 5.88e+06 0.00e+00 1.76e+07 0.00ef00 5.59e+06 MN-56 0.00e+00 1.28e-02 0.00ef00 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 0.00ei00 1.84e+07 FE-59 1.20e+08 1.94e+08 0.00e+00 O.OOe+OO 5.64e+07 2.03e+08 0.00e+00 9.69e+07 CO-58 0.00e+00 1.21e+07 0.00e+00 0.00ei.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 2.39et-08 0.00e+00 1.27e+08 NI-63 2.96ei10 1.59e+09 0.00e+00 0.00e+00 0.00e+00 1.07e+08 0.00e+00 1.01ef09 NI-65 1.66eS00 1.56e-01 0.00e+00 0.00e+00 0.00et00 1.91eS01 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 1.93ef09 0.00e+00 6.85ef09 ZN-69 9.10e-12 1.32e-11 0.00ei-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 O.OOe+OO 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 0.00eS00 0.00e+00 6.84e-23 BR- 85 0.00e+00 0.00e+00 O.OOe+OO 0.00e+00 O.OOe+OO 0.00e+00 0.00ei-00 0.00e+00 RB- 86 0.00e+00 8.77e+09 0.00e+00 0.00e+00 0.00e+00 5.64e+08 0.00et-00 5.39e+09 RB- 88 0.00e+00 7.17e-45 0.00e+00 0.00et-00 0.00e+00 3.52e-46 0.00eS00 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 0.00et00 0.00e+00 2.56e+08 0.00e+00 1.89e+08 SR-90 1.12e+11 O.OOe+OO 0.00e+00 0.00e+00 O.OOe+OO 1.51e+09 0.00e+00 2.83e+10 SR-91 1.29e+05 0.00ef00 0.00e+00 O.OOe+OO O.OOe+OO 2.86e+05 0.00ef00 4.89e+03 SR-92 2.16e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.09e+01 O.OOe+OO 8.67e-02 Y-90 3.23e+02 0.00e+00 0.00e+00 0.00e+00 0.00ef00 9.19e+05 0.00e+00 8.64e+00 Y-91 3.90e+04 0.00eS00 0.00ef00 0.00et00 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 0.00ef00 1.04e-20 Y-92 2.53e-04 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.30e+00 0.00et-00 7.23e-06 Y-93 1.00e+00 O.OOe+OO O.OOe+OO 0.00e+00 0.00e+00 1.50eS04 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 0.00ef00 3.97e-01 0.00e+00 4.19e+04 0.00ef00 1.63e-01 NB- 95 3.18ei-05 1.24e+05 0.00ef00 1.16e+05 0.00e+00 2.29ef08 0.00ei-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 2.01et-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 O.OOe+OO O.OOe+OO 3.33e-02 0.00e+00 2.48e+00 0.00eS00 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 1.15et-04 AG- 11OM 2.09e+08 1.41e+08 0.00e+00 2.63et08 0.00e+00 1.68e+10 0.00e+00 1.13e+08 TE-125M 7.38e+07 2.00ei-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 8.64ef03 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 2.47ef07 TE-129 1.07e-09 2.99e-10 7.63e-10 3.13e-09 0.00ei-00 6-65e-08 0.00e+00 2.54e-10 TE-129M 2.71e+08 7.58e+07 8.75et07 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 1.60ef06 5.53ef05 1.14e+06 5.35e+06 0.00e+00 2.24e+07 0.00et00 5.88e+05 GRAND GULF, UNIT 1 2.0-18g Revision 25 - 01/03

TABLE 2.2-2b (Continued)

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

Page 10 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m"2 * (mrem/yr)/ uci/sec) or (mrem/yr)/ (u~i/rn*3) I AgeGroup: 2 CHILD Pathway: 5 Grs/Cow/Milk (CMILK)

Nuclide Bone Liver Thyroid Kidney GI-Lli Skin TB TE-132 1.02e+07 4.52e+06 6.58e+06 4.19e+07 0.00e+00 4.55ei.07 0.00e+00 5.46e+06 1-130 1.72e+06 3.47e+06 3.83e+08 5.19e+06 0.00e+00 1.62e+06 0.00ef00 1.79e+06 1-131 1.30e+09 1.31e+09 4.33e+11 2.15e+09 0.00e+00 1.17e+08 O.OOe+OO 7.45e+08 1-132 6.91e-01 1.27eS00 5.89e+01 1.94ei-00 0.00eS00 1.49e+OO 0.00e+00 5.84e-01 1-133 1.72e+07 2.12e+07 3.94e+09 3.54e+07 0.00eS00 8.55e+06 0.00ef00 8.03e+06 1-134 7.94e-12 1.48e-11 3.39e-10 2.26e-11 0.00e+00 9.78e-12 0.00e+00 6.79e-12 1-135 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 0.00ei-00 1.15eS.10 4.13e+09 2.00e+08 0.00ef00 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 l.Ole+lO 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 1.17eS08 1.03eS05 0.00e+00 3.34e+04 6.12e+04 5.94e+07 0.00e+00 6.84ef06 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 0.00ei-00 O.OOei-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 1.87ef02 1.01ef05 0.00e+00 4.26ei-01 0.00e+00 1.49e+06 0.00ef00 1.47e+01 CE-144 1.62e+06 5.09e+05 0.00e+00 2.82e+05 O.OOe+OO 1.33e+08 O.OOe+OO 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 1.98ei-02 0.00e+00 5.70e+05 0.00ef00 2.79e+01 W-187 2.89e+04 1.71e+04 0.00e+00 0.00e+00 0.00e+00 2.40ei-06 0.00e+00 7.67e+03 NP-239 1.72e+01 1.24e+00 0.00et00 3.58e+00 0.00e+00 9.15e+04 0.00e+00 8.69e-01 Units: Inhalation2and all tritium pathways - mrem/yr per pCi/m3 Others - m . mrem/yr per pCi/sec Values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise indicated.

GRAND GULF, UNIT 1 2.0-18h Revision 25 - 01/03

TABLE 2 . 2 - 2 ~

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

Page 1 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m"2 * (mrem/yr)/ (uCi/sec) or (mrem/yr)/ (uCi/m"3)) I 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 C-14 0.00e+00 0.00e+00 0.00e+00 0.00e+00 NA-24 0.00e+00 0.00e+00 1.39e+07 1.20e+07 P-32 0.00e+00 0.00ei-00 0.00e+00 0.00eS00 CR-51 0.00e+00 0.00e+00 5.50e+06 4.65e+06 MN-54 0.00e+00 0.00e+00 1.62et09 1.38e+09 MN-56 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 FE-59 0.00e+00 0.00e+00 3.20e+08 2.73e+08 CO- 5a 0.00e+00 0.00et00 4.45e+08 3.80e+08 CO-60 0.00e+00 O.OOetO0 2.53e+10 2.15e+10 NI-63 0.00ef00 0.00e+00 0.00et00 0.00ef00 NI-65 0.00e+00 0.00e+00 3.45e+05 2.97e+05 CU-64 0.00e+00 0.00et00 6.86e+05 6.05ef05 ZN-65 0.00e+00 0.00et00 8.57e+08 7.46e+08 ZN-69 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BR- 83 0.00e+00 0.00e+00 7.08e+03 4.87ef03 BR-84 0.00e+00 0.00e+00 2.37et05 2.03e+05 BR- 85 0.00e+00 0.00e+00 0.00e+00 0.00ef00 RB- 86 0.00e+00 0.00e+00 1.03e+07 8.98e+06 RB- 88 0.00eS00 0.00eS00 3.78e+04 3.31e+04 RB- 89 0.00et00 0.00eS00 1.48e+05 1.23e+05 SR-89 0.00e+00 0.00eS00 2.51e+04 2.16ef04 SR-90 0.00e+00 0.00et00 0.00e+00 0.00e+00 SR-91 0.00e+00 0.00e+00 2.51e+06 2.15e+06 SR-92 0.00e+00 0.00eS00 8.62e+05 7.76e+05 Y-90 0.00et-00 0.00eS00 5.31e+03 4.50et03 Y-91 0.00e+00 0.00eS00 1.21e+06 1.07et06 Y-91M 0.00e+00 0.00eS00 1.16eS05 1,00e+05 Y-92 0.00eC00 0.00e+00 2.14e+05 1.80ef05 Y-93 0.00e+00 O.OOe+OO 2.50e+05 1.83ef05 ZR-95 0.00e+00 0.00e+00 2.85e+08 2.45e+08 ZR-97 0.00e+00 0.00eS00 3.44e+06 2.96e+06 NB-95 0.00e+00 0.00e+00 1.61e+08 1.37e+08 MO- 99 0.00eS00 0.00e+00 4.62et-06 3.99ef06 TC-99M 0.00eS00 0.00e+00 2.11e+05 1.84ef05 TC-101 0.00e+00 0.00e+00 2.26e+04 2.03e+04 RU-103 0.00e+00 0.00e+00 1.26e+08 1.08e+08 RU-105 0.00ei-00 0.00et00 7.21e+05 6.36ef05 RU-106 0.00e+00 0.00e+00 5.04e+08 4.20e+08 AG- 11OM 0.00e+00 0.00e+00 4.02e+09 3.45e+09 TE-125M 0.00e+00 0.00ef00 2.13e+06 1.56e+06 TE-127 0.00ef00 0.00eS00 3.29e+03 2.99e+03 TE-127M 0.00e+00 0.00e+00 1.08ef05 9.17ef04 TE-129 0.00e+00 0.00eS00 3.08ef04 2.61e+04 TE-129M 0.00e+00 0.00e+00 2.31e+07 1.98e+07 TE-131 0.00e+00 O.OOe+OO 3.45e+07 2.92e+04 TE-131M 0.00et00 0.00e+00 9.46e+06 8.02e+06 GRAND GULF, UNIT 1 2.0-19 Revision 25 - 01/03

TABLE 2.2-2c (Continued)

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

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 1-130 1-131 1-132 1-133 1-134 1-135 CS-134 CS-136 CS-137 CS-138 BA-139 BA-140 BA-141 BA-142 LA-140 LA-142 CE-141 CE-143 CE-144 PR-143 PR-144 ND-147 W-187 NP-239 GRAND GULF, UNIT 1 2

0-20 Revision 25 - 01/03

TABLE 2.2-2c (Continued)

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

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-2 4 1.38e+04 1.38e+04 1.38e+04 1.38e+04 1.38ei-04 1.38e+04 0.00e+00 1.38e+04 P-32 1.89e-t.061.10e+05 0.00e+00 0.00et-00 0.00e+00 9.28e+04 0.00e+00 7.16e+04 CR-51 0.00e+00 0.00ei-00 7.50e+01 3.07e+01 2.10e+04 3.00eS03 0.00e+00 1.35e+02 MN-54 0.00e+00 5.11e+04 0.00e+00 1.27e+04 1.98e+06 6.68ef04 0.00e+00 8.40e+03 MN-56 0.00ei-00 1.70eS00 0.00e+00 1.79e+00 1.52ef04 5.74e+04 0.00e+00 2.52e-01 FE- 55 3.34e+04 2.38et04 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 O.OOe+OO 0.00e+00 1.53e+06 1.78e+05 0.00e+00 1.43e+04 CO-58 0.00e+00 2.07e+03 O.OOe+OO 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 8.72ei-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 O.OOe+OO 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 2.03et00 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 0.00ef00 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 0.00et-00 0.00e+00 0.00e+00 0.00e+00 4.33e+02 BR-85 0.00ei-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 1.90ei-05 0.00e+00 0.00e+00 0.00e+00 1.77e+04 0.00eS00 8.40e+04 RB- 88 0.00e+00 5.46e+02 0.00ei00 0.00e+00 0.00e+00 2.92e-05 0.00e+00 2.72e+02 RB- 89 0.00eS00 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 0.00et-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 2.74et-04 1.19e+05 0.00e+00 4.06e-01 Y-90 2.98e+03 0.00ei-00 0.00e+00 0.00e+00 2.93et05 5.59e+05 O.OOe+OO 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 O.OOe+OO 0.00et-00 3.20e+03 3.02e+01 0.00e+00 1.42e-02 Y-92 1.47eS01 0.00e+00 0.00e+00 0.00e+00 2.68ef04 1.65e+05 0.00ef00 4.29e-01 Y-93 1.35e+02 0.00eS00 0.00e+00 0.00e+00 8.32ef04 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 0.00ei-00 4.12e+01 1.30e+05 6.30e+05 0.00ei-00 1.26e+01 NB-95 1.86e+04 1.03e+04 0.00e+00 1.00e+04 7.51et-05 9.68e+04 0.00e+00 5.66e+03 MO- 99 O.OOe+OO 1.69e+02 0.00e+00 4.11e+02 1.54e+05 2.69eS05 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 4.346.-01 RU-106 9.84e+04 0.00e+00 0.00e+00 1.90ei-05 1.61e+07 9.60e+05 0.00e+00 1.24e+04 AG- 11OM 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 1.40et-03 0.00e+00 5.36e+05 7.50e+04 0.00eS.00 6.67e+02 TE-127 2.01e+00 9.12e-01 1.42ef00 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 2.18ef03 TE-129 7.10e-02 3.38e-02 5.18e-02 2.66e-01 3.30e+03 1.62et03 0.00e+00 1.76e-02 TE-129M 1.39et04 6.58e+03 4.58e+03 5.19e+04 1.98e+O6 4.05e+05 0.00e+00 2.25et03 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 4.02ef01 GRAND GULF, UNIT 1 2.0-20a Revision 25 - 01/03

TABLE 2.2-2c (Continued)

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

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 3.60ei02 2.90e+02 2.46e+02 1.95ei03 4.49e+05 4.63e+05 0.00ei-00 2.19e+02 1-130 6.24e+03 1.79e+04 1.49e+06 2.75e+04 O.OOe+OO 9.12e+03 O.OOe+OO 7.17e+03 1-131 3.54ei.04 4.91ef04 1.46e+07 8.40e+04 0.00ei.00 6.49e+03 0.00e+00 2.64e+04 1-132 1.59e+03 4.38e+03 1.51e+05 6,92e+03 0.00e+00 1.27e+03 0.00e+00 1.58e+03 1-133 1.22e+04 2.05e+04 2.92e+06 3.59e+04 0.00e+00 1.03e+04 0.00e+00 6.22e+03 1-134 8.88e-t.022,32e+03 3.95e+04 3.66e+03 0.00e+00 2.04e+01 0.00eSOO 8.40e+02 1-135 3.70e+03 9.44et-03 6.21e+05 1.49e+04 0.00e+00 6.95e+03 0.00eS00 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 1.10ef05 1.78e+04 1.09eS04 0.00ef00 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 O.OOe+OO 3.90e-02 BA-140 5.47e+04 6.70e+01 0.00e+00 2,28e+01 2.03ef06 2.29e+05 0.00e+00 3.52e+03 BA-141 1.42e-01 1.06e-04 0.00e+00 9.84e-05 3.29ef03 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 0.00ef00 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 0.00ei00 1.02ei.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 1.26ef05 0.00eS00 2.17e+03 CE-143 2.66e+02 1.94ef02 0.00e+00 8.64e+01 1.30e+05 2.55ef05 0.00eS00 2.16e+01 CE-144 4.89e+06 2.02et-06 0.00e+00 1.21e+06 1.34e+07 8.64ef05 0.00e+00 2.62e+05 PR-143 1.34e+04 5.31ei-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 1.75ef03 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 9.76et00 O.OOe+OO 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 1.32ef05 0.00e+00 1.77e+Ol GRAND GULF, UNIT 1 2.0-2Ob Revision 25 - 01/03

TABLE 2.2-2c (Continued)

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

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)

H-3 0.OOefOO 2.59ei-03 2.59e+03 0.00e+00 2.59e+03 C-14 3.69e+08 7.38et-07 7.38e+07 0.00eS00 7.38e+07 NA-24 2.40e+05 2.40e+05 2.40e+05 0.00e+00 2.40e+05 P-32 lf61e+09 0.00e+00 1.35e+08 0.00e+00 6.23e+07 CR-51 O.OOe+OO 8.79e+04 1.03e+07 0.00e+00 6.16e+04 MN-54 O.OOe+OO 0.00e+00 9.32e+08 0.00e+00 9.01e+07 MN-56 O.OOe+OO 0.00e+00 9.41e+02 0.00ei-00 2.54ei-00 FE-55 3.26e+08 1.47e+08 1.00e+08 0.00e+00 5.39e+07 FE-59 1.79e-t.08 1.32e-t.089.89e+08 0.00e+00 1.61e+08 CO-58 OfOOe+OO 0.00eS00 6.02e+08 0.00e+00 1.01eS-08 CO-60 O.OOe+OO 0.00e+00 3.24e+09 O.OOe+OO 5.60e+08 NI-63 1.61e+10 0.00e+00 1.81e+08 0.00e+00 5.45e+08 NI-65 5.73e+01 0.00eS00 3.97e+02 0.00ei-00 3.33e+OO CU-64 O.OOe+OO 0.00e+00 6.43e+05 0.00e+00 3.90e+03 ZN-65 4.24e+08 0.00e+00 6.23e+08 0.00e+00 6.86ef08 ZN-69 5.04e-06 0.00eS00 1.77e-05 0.00ei-00 6.72e-07 BR- 83 0.OOefOO 0.00e+00 0.00e+00 0.00e+00 2.90ef00 BR- 84 O.OOe+OO 0.00eS00 0.00e+00 0.00e+00 2.31e-11 BR- 85 0.OOe+OO 0.00eS00 0.00e+00 0.00e+00 0.00ef00 RB- 86 0.OOe+OO 0.00eS00 4.05e+07 0.00e+00 1.29e+08 RB- 88 O.OOe+OO 0.00e+00 2.72e-29 0.00e+00 1.69e-22 RB- 89 O.OOe+OO 0.00e+00 5.46e-35 0.00eS00 2.52e-26 SR-89 1.51ef10 0.00e+00 1.80e+09 0.00eS00 4.33e+08 SR-90 7.5le+ll 0.00e+00 2.11eS10 0.00e+00 1.85et-11 SR-91 2.83e+05 0.00ef00 1.29e+06 O.OOe+OO 1.13e+04 SR-92 3.95e+02 0.00e+00 1.01e+04 0.00e+00 1.68ef01 Y-90 1.24e+04 0.00e+00 1.03eS08 O.OOe+OO 3.35ef02 Y-91 7.84e+06 0.00ef00 3.22e+09 0.00e+00 2.10e+05 Y-91M 5.04e-09 0.00ef00 2.38e-07 0.00ei.00 1.93e-10 Y-92 8.59e-01 0.00e+00 2.36e+04 0.00e+00 2.49e-02 Y-93 1.58e+02 0.00e+00 4.83e+06 0.00e+00 4.34e+00 ZR-95 1.72e+06 0.00e+00 1.26e+09 0.00e+00 3.74e+05 ZR-97 3.12e+02 0.00ef00 1.67e+07 O.OOe+OO 2.84e+01 NB-95 1.92e+05 0.00e+00 4.56e+08 0.00e+00 5.87e+04 MO- 99 O.OOe+OO 0.00e+00 1.01ei.07 0.00e+00 1.08e+06 TC-99M 2.73e+00 4.23ef00 5.00e+03 0.00e+00 9.87e+01 TC-101 7.35e-31 6.37e-31 1.79e-37 0.00ei-00 1.03e-29 RU-103 6.82e+06 0.00e+00 5.69e+08 0.00e+00 2.91e+06 RU-105 4 98e+01 0.00e+00 4.02e+04 O.OOe+OO 1.93e+01 RU-106 3.09e+08 0.00e+00 1.48eS10 0.00e+00 3.90e+07 AG- 11OM 1.52e+07 0.00e+00 4.03e+09 0.00eS00 8.73e+06 TE-125M 1,49e+08 0.00e+00 4.38e+08 0.00eS00 1.99e+07 TE-127 5.40e+03 0.00e+00 4.17e+05 0.00e+00 1.16e+03 TE-127M 5.52e+08 0.00ef00 1.37e+09 0.00eS00 6.56e+07 TE-129 6.50e-04 0.00e+00 3.56e-03 0.00eS00 1.58e-04 TE-129M 3.61e+08 0.00e+00 1.36e+09 0.00e+00 5.72e+07 TE-131 1.41e-15 0.00e+00 1.16e-16 0.00e+00 4.40e-16 TE-131M 8.44e+05 0.00e+00 3.25e+07 0.00e+00 3.38e+05 GRAND GULF, UNIT 1 2.0-2oc Revision 25 - 01/03

TABLE 2.2-2c (Continued)

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

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 1-130 3.50e+05 1.01e+06 8.25e+07 1.56e+06 0.00e+00 7.77e+05 0.00e3.00 4.04e+05 1-131 7.68e+07 1.08e+08 3.14e+10 1.85e+08 0.00e+00 2.13e+07 0.00e+00 5.78e+07 1-132 5.20e+01 1.36e+02 4.59e+03 2.14e+02 0.00e+00 5.93e+01 0.00e+00 4.88e+01 1-133 1.94e+06 3.28e+06 4.58e+08 5.76ei.06 0.00e+00 2.49e+06 0.00e+00 1.00e+06 1-134 8.44e-05 2.24e-04 3.73e-03 3.53e-04 0.00e+00 2.95e-06 0.00e+00 8.03e-05 1-135 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 O.OOe+OO 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 1.01eS10 1.35e+10 0.00e+00 4.59e+09 1.78e+09 1.92e+08 0.00e+00 4.70ef09 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 5.74ei-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 0.00el-00 0.00e+00 0.00e+00 5.11e+07 0.00eS00 2.37ef02 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 6.78ei.05 0.00e+00 3.04e+02 0.00e+00 2.04e+07 0.00eC00 7.57e+O1 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 0.00eS00 2.31e+08 0.00e+00 3.49e+03 PR-144 3.04e-26 1.24e-26 0.00et00 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 1.42ei-08 0.00e+00 2.36e+03 W-187 3.54e+04 2.88e+04 0.00ef00 0.00e+00 0.00e+00 7.80e-tO6 O.OOe+OO 1.01e+04 NP-239 1.38e+03 1.31eS02 OeOOe+OO 4.10e+02 0.00e+00 2.10e+07 0.00e+00 7.25e+01 GRAND GULF, UNIT 1 2.0-20d Revision 25 - 01/03

TABLE 2.2-2c (Continued)

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

Page 7 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (mA2 * (mrem/yr)/ (uCi/sec) or (mrem/yr)/ (uCi/mA3))

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-2 4 1.16e-03 1.16e-03 1.16e-03 1.16e-03 1.16e-03 1.16e-03 0.00et-00 1.16e-03 P-32 3.93e+09 2.43e+08 0.00e+00 0.00ei-00 0.00e+00 3.30e+08 0.00e+00 1.52e+08 CR-51 0.00e+00 0.00e+00 3.13e-t.031.23e+03 8.04e+03 9.46e+05 0.00e+00 5.63e+03 MN-54 0.00e+00 7.00e+06 O.OOe+OO 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 4.95ef08 0.00e+00 0.00e+00 1.56ef08 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 O.OOe+OO 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 1.07et-09 0.00e+00 0.00e+00 0.00et-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 0.00ef00 5.56e+08 0.00e+00 3.68ei-08 0.00ef00 4.05e+08 ZN-69 0.00e+00 0.00e+00 0.00ef00 0.00e+00 0.00e+00 0.00ei-00 0.00e+00 0.00e+00 BR- 83 0.00e+00 0.00ei-00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.73e-57 BR- 84 0.00ei.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 O.OOe+OO 0.00e+00 0.00e+00 O.OOe+OO 0.00eS00 0.00e+00 0.00e+00 RB- 86 0.00e+00 4.07e+08 0.00ef00 0.00e-i-000.00e+00 6.02e+07 0.00et-00 1.91et-08 RB- 88 0.00eS00 0.00e+00 0.00e+00 0.00eS00 0.00e+00 0.00e+00 0.00ef00 O.OOe+OO RB- 89 0.00e+00 0.00e+00 0.00e+00 0.00e+00 O.OOe+OO 0.00eS00 0.00et00 0.00e+00 SR-89 2.54e+08 O.OOe+OO 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 0.00eS00 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 O.OOei.00 0.00e+00 0.00e+00 0.00ef00 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 0.00eS00 0.00e+00 3.91e+08 0.00e+00 2.56et04 Y-91M 0.00ei-00 0.00e+00 0.00ei-00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00ef00 Y-92 1.26e-39 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.46e-35 0.00ei-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 O.OOe+OO 1.09ei-09 0.00e+00 3.26e+05 ZR-97 1.70e-05 3.37e-06 0.00ef00 5.10e-06 0.00e+00 9.11e-01 0.00e+00 1.55e-06 NB-95 1.79ef06 9.95e+05 0.00e+00 9.64e+05 0.00e+00 4.25e+09 0.00e+00 5.48ei05 MO- 99 0.00e+00 8.21e+04 0.00e+00 1.88e+05 O.OOe+OO 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 0.00ef00 5.73e-27 0.00e+00 3.67e-25 0.00e+00 1.76e-28 RU-106 2.36e+09 0.00ef00 0.00e+00 4.55e+09 0.00e+00 1.13e+11 0.00e+00 2.97e+08 AG- 11OM 5.06e+06 4.79e+06 O.OOe+OO 9.13e+06 0.00e+00 1.35e+09 0.00e+00 2.91ef06 TE-125M 3.03e+08 1.09e+08 8.48e+07 0.00eS00 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 O.OOe+OO 1.64e-08 0.00e+00 4.57e-11 TE-127M 9.42e+08 3.34ef08 2.24ef08 3.82e+09 O.OOe+OO 2.35e+09 0.00e+00 1.12e+08 TE-129 0.00e+00 0.00ef00 0.00e+00 0.00e+00 0.00eS00 0.00et00 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 0.00ei.00 0.00eS00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00ei-00 TE-131M 3.75ei-02 1.80ef02 2.70e+02 1.87e+03 0.00e+00 1.44e+04 0.00e+00 1.50e+02 G W D GULF, UNIT 1 2.0-20e Revision 25 - 01/03

TABLE 2.2-2c (Continued)

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

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 1-130 1.63e-06 4.72e-06 3.85e-04 7.27e-06 0.00et00 3.63e-06 0.00e+00 1.89e-06 1-131 8.92e+06 1.25ei.07 3.64e+09 2.15e+07 0.00e+00 2.47e+06 0.00e+00 6.71e+06 1-132 5.79e-59 1.52e-58 5.11e-57 2.39e-58 0.00e+00 6.60e-59 0.00e+00 5.44e-59 1-133 3.04e-01 5.15e-01 7.19e+01 9.03e-01 0.00e+00 3.90e-01 0.00ef00 1.57e-01 1-134 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1-135 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 1.37ef07 0.00e+00 3.36ef08 CS-138 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00et-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 1.96ef04 3.67e+07 0.00eS.00 1.53ef06 BA-141 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 O.OOe+OO BA-142 0.00e+00 0.00eS00 0.00e+00 0.00ei.00 0.00ei00 0.00e+00 0.00e+00 0.00e+00 LA-140 3.09e-02 1.52e-02 0.00e+00 0.00e+00 0.00ef00 8.73ef02 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 1.22ef01 0.00eS.00 5.46e-03 0.00e+00 3.66e+02 O.OOe+OO 1.36e-03 CE-144 1.23e+06 5.08ef05 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 4.10eS03 0.00e+00 5.81ef07 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 O.OOe+OO 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 25 - 01/03

TABLE 2.2-2c (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b. fR 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 O.OOe+OO 9.94e+02 9.94e+02 9.94e+02 9.94e+02 9.94et02 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-2 4 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 O.OOe+OO 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 7.12et-04 8.38e+06 0.00e+00 4.99ef04 MN-54 0.00e+00 1.40e+07 0.0Oet-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 3.16ef07 0.00e+00 O.OOe+OO 2.00ei-07 1.37e+07 0.00eS00 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 O.OOe+OO 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 3.62ei-08 0.00e+00 6.26e+07 NI-63 1.18e+lO 8.35ei-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 0.00ei.00 4.21e+04 0.00eS00 1.06e+05 O.OOe+OO 3.26e+06 0.00e+00 1.98e+04 ZN-65 2.11e+09 7.31e+09 0.00e+00 4.68ef09 0.00e+00 3.10eS09 0.00e+00 3.41e+09 ZN-69 3.70e-12 7.05e-12 0.00eS00 4.61e-12 0.00e+00 1.30e-11 0.00e+00 4.94e-13 BR- 83 0.00e+00 0.00eS.00 0.00e+00 0.00ef00 0.00e+00 0.00eS00 0.00e+00 1.78e-01 BR- 84 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00eS00 0.00eS00 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 0.00eS00 0.00e+00 0.00e+00 7.00e+08 0.00eS00 2.22e+09 RB- 88 0.00e+00 3.90e-45 0.00eS00 0.00ef00 O.OOe+OO 3.34e-52 0.00eS00 2.08e-45 RB- 89 0.00ei-00 7.96e-53 0.00eS00 0.00ef00 0.00e+00 1.22e-61 0.00e+00 5.63e-53 SR-89 2.67e+09 0.00eS00 0.00e+00 0.00e+00 0.00e+00 3.18e+08 0.00e+00 7.66e+07 SR-90 6.61eS10 0.00e+00 0.00ef00 0.00e+00 0.00e+00 1.86e+09 0.00e+00 1.63eS10 SR-91 5.27e+04 0.00eS00 0.00e+00 0.00e+00 0.00eS00 2.39e+05 O.OOe+OO 2.10ef03 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 O.OOe+OO 0.00e+00 1.08e+06 0.00e+00 3.51e+00 Y-91 1.58e+04 0.00ef00 0.00e+00 0.00e+00 0.00e+00 6.48e+06 0.00e+00 4.24ei-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 0.00ei.00 0.00eS00 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 0.00ef00 1.20e+06 0.00e+00 3.58ef02 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 0.00eS00 7.57e+04 0.00e+00 3.34e+08 0.00e+00 4.30e+04 MO- 99 0.00e+00 4.46e+07 0.00eS00 1.02e+08 O.OOe+OO 8.00e+07 0.00ef00 8.51e+06 TC- 99M 5.74e+00 1.60e+01 0.00eS00 2.39e+02 8.89e+00 1.05eS04 0.00ef00 2.08e+02 TC-101 4.39e-60 6.24e-60 0.00eS00 1.13e-58 3.80e-60 1.07e-66 0.00e+00 6.13e-59 RU-103 1.81e+03 0.00e+00 0.00eS00 6.38ef03 0.00ei-00 1.51e+05 0.00e+00 7.74e+02 RU-105 1.55e-03 0.00et00 0.00eS00 1.96e-02 0.00e+00 1.25e+00 0.00e+00 6.03e-04 RU-106 3.75e+04 0.00eS00 0.00e+00 7.23ef04 0.00e+00 1.80ef06 0.00e+00 4.73e+03 AG- 11OM 9.63ef07 9.11e+07 0.00e+00 1.74e+08 0.00eS00 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 5.00ei-03 0.00e+00 9.54e+04 0.00eS00 2.66e+02 TE-127M 8.44ef07 2.99e+07 2.01e+07 3.42e+08 0.00e+00 2.10eS08 0.00e+00 1.00eS07 TE-129 4.33e-10 1.62e-10 3.10e-10 1.82e-09 0.00e+00 2.37e-09 0.00et-00 1.05e-10 TE-129M 1.10e+08 4.09e+07 3.55e+07 4.61ef08 0.00e+00 4.13ef08 0.00ei00 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 3.28ef06 0.00e+00 2.53e+07 O.OOe+OO 2.63e+05 GRAND GULF, UNIT 1 2.0-2og Revision 25 - 01/03

TABLE 2.2-2c (Continued)

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

Page 10 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m"2 * (mrem/yr)/ (uCi/sec) or (mrem/yr)/ (uCi/mA3))

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

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 4.28et-06 2.71e+06 2.85e+06 2.60e+07 0,00e+00 8.57e+07 0.00e+00 2.55e106 1-130 7.35e+05 2.13e+06 1.73e+08 3.27et-06 0,00e+00 1.63e+06 0.00e+00 8.49et-05 1-131 5.37e+08 7.52e-t.082.19e+11 1.30e+09 0.00e+00 1.49e+08 0.00e+00 4.04e+08 1-132 2.92e-01 7.64e-01 2.58e+01 1.20eS00 0.00e+00 3.33e-01 O.OOe+OO 2.74e-01 1-133 7.06e+06 1.20e+07 1.67e+09 2.10e+07 0.00e+00 9.06e+06 0.00e+00 3.65e+06 1-134 3.36e-12 8.89e-12 1.48e-10 1.40e-11 0.00e+00 1.17e-13 0.00e+00 3.19e-12 1-135 2.29e+04 5.91e+04 3.80ef06 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-t.081.76e+09 0.00e+00 9.60e+08 1,51e+08 1.42ei.08 0.00e+00 1.18ei-09 CS-137 1.34e+10 1.78e+10 0.00ef00 6.06e+09 2.35e+09 2.53e+08 0.00e+00 6.20e+09 CS-138 1.58e-23 3.03e-23 0.00ei-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 0.00ei.00 2.02e+04 4.00e+04 7.49e+07 0.00ef00 3.13ei-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 0.00eS00 6.75e-84 5.31e-84 2.45e-92 0.00e+00 4.91e-82 LA-140 8.12e+00 3.99e+00 O.OOe+OO 0.00e+00 0.00e+00 2.29e+05 0.00eS00 1.06e+00 LA-142 3.41e-11 1.52e-11 0.00e+00 0.00e+00 O.OOe+OO 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 O.OOe+OO 1.63e+05 0.00e+00 1.66e+08 0.00e+00 3.54e+04 PR-143 2.90ef02 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-2 39 7.00e+00 6.60e-01 0.00e+00 2.07e+00 O.OOe+OO 1.06e+05 0.00eS00 3.67e-01 3

Units: Inhalation and all tritium pathways mrem/yr per pCi/m Others - m2 . mrem/yr per pCi/sec Values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise indicated.

GRAND GULF, UNIT 1 2.0-20h Revision 25 - 01/03

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

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 C-14 NA-24 P-32 CR-51 MN-54 MN-56 FE- 55 FE-59 CO-58 CO-60 NI-63 NI-65 CU-64 ZN-65 ZN-69 BR- 83 BR- 84 BR- 85 RB- 86 RB- 88 RB- 89 SR-89 SR-90 SR-91 SR-92 Y-90 Y-91 Y-91M Y-92 Y-93 ZR-95 ZR-97 NB- 95 MO- 99 TC-99M TC-101 RU-103 RU-105 RU-106 AG- 11OM TE- 125M TE-127 TE-127M TE-129 TE- 129M TE-131 TE-131M GRAND GULF, UNIT 1 2.0-21 Revision 25 - 01/03

TABLE 2.2-2d (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b' (Ri)

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 1-130 1-131 1-132 1-133 1-134 1-135 CS-134 CS-136 CS-137 CS-138 BA-139 BA-140 BA-141 BA-142 LA-140 LA-142 CE-141 CE-143 CE-144 PR-143 PR-144 ND-147 W-187 NP-239 GRAND GULF, UNIT 1 2.0-22 Revision 25 - 01/03

TABLE 2 . 2 - 2 d (Continued)

PATHWAY DOSE FACTORS FOR LCO 6 . 1 1 . 6 AND SECTION 2 . 2 . 2 . b , (Ri)

Page 3 of 1 0 H- 3 0.00ef00 1.26e+03 C-14 0.00e+00 3.41e-t.03 NA- 2 4 0.00e+00 1.02e+04 P-32 0.00e+00 5.01e+04 CR-51 0.00e+00 1.00e+02 MN-54 0.00e+00 6.30e+03 MN-56 0.00e+00 1.83e-01 FE- 5 5 0.00e+00 3.94e+03 FE-59 0.00e+00 1.06e+04 CO- 5 8 O.OOe+OO 2.07e+03 CO-60 0.00e+00 1.48e+04 NI-63 0.00e+00 1.45ef04 NI-65 0.00e+00 9.12e-02 CU-64 0.00ef00 6.15e-01 ZN-65 0.00e+00 4.66e+04 ZN-69 0.00e+00 4.52e-03 BR- 8 3 0.00e+00 2.41ei-02 BR- 8 4 0.00ei-00 3.13ei-02 BR- 8 5 0.00e+00 1.28e+01 RB- 8 6 0.00e+00 5.90e+04 RB- 8 8 0.00eS00 1.93e+02 RB- 8 9 0.00eS00 1.70et-02 SR-89 0.00e+00 8.72e+03 SR-90 O.OOe+OO 6.10e+06 SR-91 0.00e+00 2.50ef00 SR-92 0.00e+00 2.91e-01 Y-90 0.00e+00 5.61e+01 Y-91 0.00e+00 1.24e+04 Y-91M 0.00e+00 1.02e-02 Y-92 0.00e+00 3.02e-01 Y-93 0.00e+00 2.61e+00 ZR-95 0.00e+00 2.33e+04 ZR-97 0.00e+00 9.04e+00 NB-95 0.00e+00 4.21e+03 MO- 9 9 0.00et00 2.30eS01 TC- 9 9M 0.00e+00 3.70e-02 TC-101 0.00e+00 5.90e-04 RU-103 0.00e+00 6.58ef02 RU-105 0.00e+00 3.11e-01 RU-106 0.00e+00 8.72e+03 AG- 11OM 0.00ef00 5.94e+03 TE-125M 0.00e+00 4.67e+02 TE-127 0.00e+00 3.10e-01 TE-127M 0.00e+00 1.57e+03 TE-129 0.00ef00 1.24e-02 TE-129M 0.00e+00 1.58e+03 TE-131 0.00e+00 3.59e-03 TE- 1 3 1 M 0.00e+00 2.90e+01 GRAND GULF, UNIT 1 2.0-22a Revision 2 5 - 0 1 / 0 3

TABLE 2.2-2d (Continued)

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

Page 4 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m2 * (mrem/yr)/ (uCi/sec) or (mrem/yr)/ (uCi/m3))

AcreGrouo:

2 0 ADULT Pathway: 1 Inhalation (INHL)

Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB TE-132 2.60e+02 2.15e+02 1.90ef02 1.46e+03 2.88e+05 5.10e+05 0.00eS00 1.62e+02 1-130 4.58e+03 1.34e+O4 1.14e+06 2.09e+04 0.00e+00 7.69e+03 0.00e+00 5.28e+03 1-131 2.52e+04 3.58e+04 1.19e+07 6.13e+04 0.00e+00 6.28e+03 0.00e+00 2.05e+04 1-132 1.16e+03 3.26ei-03 1.14e+05 5.18e+03 0.00e+00 4.06e+02 0.00e+00 1.16e+03 1-133 8.64e+03 1.48e-t.042.15e+06 2.58et-04 0.00e+00 8.88e+03 0.00e+00 4.52e+03 1-134 6.44e+02 1.73e+03 2.98e+04 2.75e+03 0.00e+00 1.01e+00 0.00e+00 6.15e+02 1-135 2.68e+03 6.98e+03 4.48ef05 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 8.56ei.04 1.20ef04 1.17e+04 0.00e+00 1.10e+05 CS-137 4.78e+05 6.21e+05 0.00eS00 2.22e+05 7.52e+04 8.40e+03 0.00e+00 4.28e+05 CS-138 3.31e+02 6.21ef02 0.00e+00 4.80ef02 4.86e+01 1.86e-03 0.00eS00 3.24e+02 BA-139 9.36e-01 6.66e-04 0.00e+00 6.22e-04 3.76e+03 8.96ef02 0.00e+00 2.74e-02 BA-140 3.90e+04 4.90e+01 0.00e+00 1.67eS.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 1.94et-03 1.16e-07 0.00e+00 3.36e-03 BA-142 2.63e-02 2.70e-05 0.00eS00 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 4.58et05 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 1.99ei-04 1.35e+04 0.00e+00 6.26ef03 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 3.65ef02 W-187 8.48e+00 7.08eS-00 0.00eS00 0.00e+00 2.90ei.04 1.55e+05 0.00e+00 2.48ef00 NP-239 2.30e+02 2.26e+01 0,00e+00 7.00e+01 3.76e+04 1.19e+05 0.00ef00 1.24e+01 GRAND GULF, UNIT 1 2.0-22b Revision 25 - 01/03

TABLE 2.2-2d (Continued)

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

Page 5 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (mA2 * (mrem/yr)/ (uci/sec) or (mrem/yr)/ (uCi/mA3))

AgeGroup: 0 ADULT Pathway: 2 Vegetation (VEG Nuclide Bone Liver Thyroid Kidney Lung GI-Lli Skin TB

_-____---------____________________---~

H-3 O.OOe+OO 2.26e+03 2.26e+03 2.26e+03 2.26e+03 2.26e+03 0.00eS00 2.26e+03 C-14 2.28e+08 4.55e+07 4.55e+07 4.55e+07 4.55e+07 4.55et-07 0.00e+00 4.55e+07 NA-24 2.71ei-05 2.71e+05 2.71ef05 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-t.080.00e+00 9.31e+07 0.00e+00 9.58e+08 0.00e+00 5.97e+07 MN-56 0.00ei-00 1.59e+01 0.00e+00 2.01e+01 0.00e+00 5.06e-t.020.00e+00 2.81e+00 FE-55 2.10e+08 1.45e+08 0.00ef00 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 0.00eS00 1.14e+08 CO-58 0.00e+00 3.08e+07 0.00e+00 O.OOe+OO 0.00e+00 6.24e+08 0.00e+00 6.90e+07 CO-60 0.00e+00 1.67e+08 0.00e+00 O.OOe+OO 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 0.00et-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 0.00eS00 3.65e+00 CU-64 0.00e+00 9.15e+03 0.00ei-00 2.31e+04 0.00e+00 7.80e+05 0.00e+00 4.29e+03 ZN-65 3.17e+08 1.01e+09 0.00et-00 6.75ef08 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 0.00et00 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 0.00et-00 3.10e+00 BR- 84 0.00e+00 0.00e+00 0.00e+00 0.00ef00 0.00ei-00 1.99e-16 0.00eS00 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 1.02ef08 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 0.00et-00 0.00e+00 2.30e-39 0.00e+00 2.79e-26 SR-89 9.95e+09 0.00eS00 0.00e+00 0.00ef00 0.00e+00 1.60e+09 0.00e+00 2.86e+08 SR-90 6.05ef11 0.00e+00 0.00e+00 0.00e+00 O.OOe+OO 1.75e+10 0.00e+00 1.48e+11 SR-91 3.03e+05 0.00e+00 0.00ef00 0.00ef00 0.00e+00 1.45ef06 O.OOe+OO 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 1.84eS01 Y-90 1.33e+04 0.00e+00 0.00e+00 0.00e+00 0.00eS00 1.41ef08 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 0.00eS00 1.59e-08 0.00e+00 2.10e-10 Y-92 9.14e-01 0.00e+00 0.00ef00 O.OOe+OO 0.00e+00 1.60eS04 0.00e+00 2.67e-02 Y-93 1.69e+02 0.00et-00 0.00eS00 0.00eS00 0.00e+00 5.35e+06 0.00e+00 4.66e+00 ZR-95 1.18e+06 3.77e+05 0.00eS00 5.92e+05 0.00e+00 1.20e+09 0.00e+00 2.55e+05 ZR-97 3.37e+02 6.80e+01 0.00eS00 1.03e+02 0.00e+00 2.11e+07 0.00e+00 3.llefOl 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 1.39ei-07 0.00e+00 1.42e+07 0.0Oei-00 1.17e+06 TC-99M 3.10e+00 8.75e+00 0.00ei-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 2.05ef06 RU-105 5.36e+01 0.00e+00 0.00e+00 6.93e+02 O.OOe+OO 3.28e+04 0.00e+00 2.12e+01 RU-106 1.93e+08 0.00e+00 0.00e+00 3.72ef08 0.00ef00 1.25e+10 0.00e+00 2.44e+07 AG- 11OM 1.05e+07 9.75e+06 0.00eS00 1.92e+07 0.00e+00 3.98e+09 0.00ef00 5.79ef06 TE-125M 9.67e+07 3.50e+07 2.91e+07 3.93e+08 0.00eS00 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 9.37ei-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 25 - 01/03

TABLE 2.2-2d (Continued)

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

Page 6 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (mA2 * (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 1-130 3.91e+05 1.15e+06 9.78e+07 1.80e+06 0.00e+00 9.93e+05 O.OOe+OO 4.55e+05 1-131 8.07e+07 1.16e+08 3.79e+10 1.98e+08 0.00e+00 3.05ei-07 0.00e+00 6.62e+07 1-132 5.76e+01 1.54e+02 5.40e+03 2.46e+02 O.OOe+OO 2.90e+01 0.00e+00 5.40e+01 1-133 2.08e+06 3.63e+06 5.33e+08 6.33e+06 0.00e+00 3.26ei.06 O.OOe+OO 1.11e+06 1-134 9.33e-05 2.54e-04 4.39e-03 4.03e-04 0.00e+00 2.21e-07 0.00e+00 9.07e-05 1-135 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 0.00ei-00 9.08e+09 CS-136 4.27e+07 1.68e+08 0.00e+00 9.37et-07 1.28ef07 1.91e+07 0.00ei-00 1.21e+08 CS-137 6.36e+09 8.70ef09 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 0.00ei.00 8.38e-04 BA-140 1.29e+08 1,62e+05 0.00e+00 5.49e+04 9.25e+04 2.65ei-08 0.00ei-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 7.33ei-07 0.00ei.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 6.19ei.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 O.OOe+OO 1.11e+10 0.00eS00 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 0.00ef00 7.58e-27 0.00eS00 4.66e-33 0,00e+00 1.65e-27 ND-147 3.33ei-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 0.00eS00 1.11e+04 NP-239 1.43ei-03 1.40e+02 0.00ef00 4.37e+02 0.00e+00 2.88e+07 0.00e+00 7.73ei-01 GRAND GULF, UNIT 1 2.0-22d Revision 25 - 01/03

TABLE 2.2-2d (Continued)

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

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 2.41ef08 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 9.34ei-03 1.77e+06 0.00e+00 7.04e+03 m-54 0.00e+00 9.18e+06 0.00e+00 2.73e+06 0.00ei-00 2.81e+07 0.00ef00 1.75e+06 MN-56 0.00e+00 1.44e-53 0.00ei-00 1.83e-53 0.00e+00 4.60e-52 0.00e+00 2.56e-54 FE-55 2.93e+08 2.03et-08 0.00e+00 0.00e+00 1.13e+08 1.16eS08 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 0.00ei-00 1.66ei-08 NI-63 1.89ei.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 0.00eS.00 2.52e-07 0.00e+00 6.36e-07 0.00eS00 2.15e-05 0.00e+00 1.18e-07 ZN-65 3.56e+08 1.13e+09 0.00ei-00 7.57e+08 0.00e+00 7.13e+08 0.00e+00 5.12e+08 ZN-69 0.00e+00 0.00e+00 0.00ei-00 0.00ef00 0.00e+00 0.00e+00 0.00e+00 0.00eS00 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 O.OOe+OO 0.00ef00 0.00ei.00 0.00e+00 0.00e+00 0.00e+00 0.00eS00 0.00e+00 RB-86 O.OOe+OO 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 O.OOe+OO RB- 89 0.00e+00 0.00e+00 0.00e+00 0.00ei-00 0.00eS00 0.00e+00 0.00e+00 0.00e+00 SR-89 3.01e+08 0.00e+00 0.00e+00 0.00e+00 0.00eS00 4.83e+07 0.00eS00 8.65e+06 SR-90 1.24e+10 0.00e+00 0.00ef00 0.00e+00 0.00e+00 3.59ef08 0.00e+00 3.05e+09 SR-91 1.43e-10 0.00e+00 0.00e+00 0.00e+00 0.00ef00 6.83e-10 0.00et-00 5.79e-12 SR-92 1.08e-49 0.00e+00 0.00e+00 0.00eS00 0.00e+00 2.13e-48 0.00eS00 4.66e-51 Y-90 1.08e+02 0.00ef00 0.00ef00 0.00ef00 0.00e+00 1.15ef06 0.00e+00 2.91e+00 Y-91 1.13e+06 0.00e+00 O.OOe+OO 0.00e+00 0.00e+00 6.23ef08 0.00e+00 3.03e+04 Y-91M 0.00ei-00 0.00e+00 0.00e+00 0.00et-00 0.00ef00 0.00e+00 0.00e+00 0.00e+00 Y-92 1.49e-39 0.00e+00 0.00e+00 0.00e+00 O.OOe+OO 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 0.00ef00 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 1.27ef00 0.00e+00 1.88e-06 NB- 95 2.30e+06 1.28e+06 0.00et00 1.26e+06 0.00ef00 7.75e+09 0.00ef00 6.87e+05 MO- 99 0.00e+00 9.93e+04 0.00e+00 2.25e+05 0.00ef00 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 0.00ei-00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00et00 0.00e+00 0.00e+00 RU-103 1.05e+08 0.00ef00 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 0.00ei-00 2.15e-28 RU-106 2.80e+09 0.00e+00 0.00e+00 5.40ef09 0.00e+00 1.81e+11 0.00e+00 3.54ef08 AG- 11OM 6.68e+06 6.18e+06 0.00ei-00 1.22e+07 0.00ef00 2.52e+09 0.00e+00 3.67e+06 TE-125M 3.59ef08 1.30e+08 1.08e+08 1.46ef09 0.00e+00 1.43e+09 0.00e+00 4.81ef07 TE-127 2.50e-10 8.98e-11 1.85e-10 1.02e-09 0.00ef00 1.97e-08 0.00ei-00 5.41e-11 TE-127M 1.12ef09 3.99e+08 2.85e+08 4.53e+09 0.00ef00 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 0.00ef00 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 25 - 01/03

TABLE 2.2-2d (Continued)

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

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)

TE-132 1.40e+06 9.03e+05 9.98e+05 8.70e+06 0.00e+00 4.27et.07 0.00e+00 8.48e+05 1-130 2.03e-06 5.98e-06 5.07e-04 9.33e-06 0.00e+00 5.15e-06 0.00e+00 2.36e-06 1-131 1.07e+07 1.54e+07 5.03e+09 2.63e+07 0.00e+00 4.05e+06 0.00e+00 8.80e+06 1-132 7.13e-59 1.91e-58 6.68e-57 3.04e-58 0.00e+00 3.58e-59 0.00e+00 6.68e-59 1-133 3.63e-01 6.31e-01 9.28e+01 1.10e+00 0.00e+00 5.68e-01 0.00e+00 1.93e-01 1-134 0.00e+00 0.00ef00 0.00e+00 0.00ei-00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1-135 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 O.OOe+OO 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 0.00ei-00 7.81e+08 CS-138 O.OOe+OO 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 BA-139 O.OOe+OO 0.00e+00 0.00ef00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0 . 0 0 e f 0 0 BA-140 2.88e+07 3.61e+04 0.00ef00 1.23ef04 2.07e+04 5.92e+07 0.00e+00 1.88e+06 BA-141 O.OOe+OO 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

%A-142 O.OOe+OO 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 0.00ef00 0.00e+00 0.00eS00 1.39e+03 0.00e+00 5.01e-03 LA-142 4.06e-92 1.85e-92 0.00ef00 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 0.00et-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 O.OOe+OO 7.83e+04 PR-143 2.10ef04 8.42ef03 0.00e+00 4.86e+03 0,00e+00 9.20et-07 0.00e+00 1.04e+03 PR-144 O.OOe+OO 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 4.88ef02 W-187 2.07e-02 1.73e-02 O.OOe+OO 0.00eS00 0.00e+00 5.66eS00 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 25 - 01/03

TABLE 2.2-2d (Continued)

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

Page 9 of 10 Release Type: 2 Gaseous Dose Factor: 2 Ri (m"2 * (mrem/yr)/ (uCi/sec) or (mrem/yr)/ (uCi/mA3)) I AgeGroup: 0 ADULT Pathway: 5 Grs/Cow/Milk (CMILK)

Ii- 3 0.00e+00 7.63e+02 7.63e+02 7.63e+02 7.63e+02 7.63e+02 0.00eS00 7.63e+02 C-14 2.63e+08 5.27e+07 5.27e+07 5.27e+07 5.27e+07 5.27e+07 0.00eS00 5.27e+07 NA-24 2.46e+06 2.46e+06 2.46e+06 2.46e+06 2.46ei.06 2.46e+06 0.00e+00 2.46e+06 P-32 1.71e+10 1.06e+09 0.00e+00 0.00e+00 0.00ei00 1.92e+09 0.00e+00 6.60e+08 CR-51 O.OOe+OO 0.00e+00 1.71e+04 6.29e+03 3.79e+04 7.18ei-06 0.00e+00 2.86e+04 MN-54 0.00e+00 8.41e+06 O.OOe+OO 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 0.00ei-00 1.32e-01 0.00et-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-t.070.00e+00 0.00e+00 1.95e+07 2.33e+08 0.00e+00 2.68ei.07 CO-58 0.00e+00 4.72e+06 O.OOe+OO 0.00eS00 O.OOe+OO 9.56e+07 0.00e+00 1.06e+07 CO-60 0.00e+00 1.64e+07 0.00e+00 O.OOe+OO 0.00e+00 3.08e+08 0.00ef00 3.62e107 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 5.95et-04 0.00e+00 2.01e+06 0.00e+00 1.11e+04 ZN-65 1.37ei09 4.37e+09 0.00e+00 2.92e+09 0.00e+00 2.75e+09 0.00e+00 1.97ef09 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 0.00eS00 0.00ef00 0.00e+00 1.39e-01 0.00e+00 9.65e-02 BR- 84 0.00eS00 0.00e+00 0.00eS00 0.00e+00 0.00e+00 1.33e-28 0.00e+00 1.69e-23 BR- 85 0.00eS00 0.00e+00 0.00e+00 0.00ef00 0.00e+00 0.00e+00 0,00e+00 0.00e+00 RB- 86 0.00e+00 2.60e+09 0.00e+00 0.00eS.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 0.00ef00 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 0.00et-00 4.16e+07 SR-90 4.68e+10 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.35e+09 0.00eS00 1.15e+10 SR-91 2.87e+04 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.37e+05 0.00eS00 1.16ef03 SR-92 4.84e-01 0.00e+00 0.00e+00 0.00ef00 0.00e+00 9.58e+00 0.00e+00 2.09e-02 Y-90 7.10e+01 0.00e+00 0.00eS00 0.00e+00 0.00e+00 7.52et05 0.00e+00 1.90e+00 Y-91 8.59e+03 0.00e+00 0.00e+00 0.00ei.00 0.00e+00 4.73e+06 0.00e+00 2.30ef02 Y-91M 6.42e-20 0.00e+00 0.00e+00 0.00e+00 0.00ef00 1.89e-19 0.00ef00 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 0.00eS00 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 0.00et-00 9.59e+05 0.00et-00 2.05e+02 ZR-97 4.32e-01 8.72e-02 0.00e+00 1.32e-01 0.00eS00 2.70ef04 0.00e+00 3.99e-02 NB- 95 8.25ef04 4.59e+04 0.00e+00 4.54e+04 0.00e+00 2.79e+08 0.00e+00 2.47e+04 MO- 99 O.OOe+OO 2.47e+07 0.00e+00 5.60ef07 O.OOe+OO 5.73e+07 0.00e+00 4.71e+06 TC-99M 3.31e+00 9.35e+00 0.00e+00 1.42ef02 4.58e+00 5.53e+03 0.00e+00 1.19e+02 TC-101 2.40e-60 3.46e-60 0.00ei-00 6.22e-59 1.77e-60 1.04e-71 0.00et-00 3.39e-59 RU-103 1.02eC03 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 0.00ei-00 0.00e+00 1.10e-02 0.00e+00 5.20e-01 0.00e+00 3.36e-04 RU-106 2.04ef04 0.00e+00 0.00e+00 3.94e+04 0.00e+00 1.32e+06 0.00e+00 2.58ef03 AG- 11OM 5.82e+07 5.39e+07 0.00eS00 1.06e+08 0.00e+00 2.20e+10 0.00e+00 3.20ef07 TE-125M 1.63e+07 5.91e+06 4.90e+06 6.63ef07 0.00ef00 6.51e+07 0.00e+00 2.18e+06 TE-127 6.66eC02 2.39e+02 4.94ei-02 2.71e+03 0.00e+00 5.26e+04 0.00e+00 1.44e+02 TE-127M 4.58ef07 1.64e+07 le17e+07 1.86e+08 0.00eS00 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 0.00eS00 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 1.166.-33 TE-131M 3.61e+05 1.76e+05 2.80e+05 1.79e+06 0.00e+00 1.75ef07 0.00e+00 1.47e+05 GRAND GULF, UNIT 1 2.0-22g Revision 25 - 01/03

TABLE 2.2-2d (Continued)

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

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 0.00ef00 1.45e+06 1-130 4.18e+05 1.23e+06 1.05e+08 1.92e+06 0.00e+00 1.06e+06 0.00e+00 4.86e+05 1-131 2.96e+08 4.23e+08 1.39e+11 7.26e+08 0.00e+00 1.12e+08 0.00e+00 2.43et-08 1-132 1.65e-01 4.40e-01 1.54e+01 7.02e-01 0.00e+00 8.27e-02 0.00ei-00 1.54e-01 1-133 3.87e+06 6.73e+06 9.88e+08 1.17e+07 0.00e+00 6.04ei-06 0.00e+00 2.05e+06 1-134 1.89e-12 5.13e-12 8.89e-11 8.15e-12 0.00e+00 4.47e-15 0.00e+00 1.83e-12 1-135 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 0.00eS00 4.35e+09 1.45e+09 2.35e+08 0.00e+00 1.10ef10 CS-136 2.63e+08 1.04e+09 0.00e+00 5.78e+08 7.92ef07 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 O.OOe+OO 1.30e-09 BA-140 2.69e+07 3.38e+04 0.00eS.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 0.00ef00 3.83e-84 2.57e-84 0.00e+00 0.00ef00 2.77e-82 LA-140 4.52e+00 2.28e+00 0.00e+00 0.00e+00 0.00e+00 1.67ef05 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 3.72ef02 CE-143 4.15e+01 3.07e+04 0.00e+00 1.35ef01 0.00e+00 1.15e+06 0.00e+00 3.39ef00 CE-144 3.58e+05 1.50e+05 0.00e+00 8.87e+04 0.00e+00 1.21e-t.080.00e+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 0.00eS00 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 0.00ef00 5.22e+05 0.00e+00 6.51ef00 W-187 6.51e+03 5.45ef03 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 pCi/m Others - m . mrem/yr per pCi/sec Values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise indicated.

GRAND GULF, UNIT 1 2.0-22h Revision 25 - 01/03

TABLE 2.2-3 CONTROLLING RECEPTORS, LOCATIONS, AND ATMOSPHERIC DISPERSION PARAMETERS*

for LCO 6.11.5, 6.11.6, AND 6.11.8 I I I I I I NEAREST RESIDENCE, SECTOR DIRECTION MILES** X/Q D/Q MILES** D/Q A N 0.94 1.5E-6 6.2E-9 1.78 2.1E-9 B NNE 0.83 1.5E-6 6.6E-9 >5 N/A C NE 0.67 2.OE-6 9.4E-9 0.67 9.4E-9 D ENE 2.57 2.7E-7 6.5E-10 2.66 6.1E-10 E E 0.88 1.2E-6 3.9E-9 0.89 3.8E-09 F ESE 2.25 2.9E-7 7.7E-10 2.25 7.7E-10 H SSE 1.11 1.2E-6 4.2E-9 4.39 3.7E-10 J S 3.16 3.OE-7 6.8E-10 3.16 6.8E-10 K ssw 2.23 6.4E-7 1.3E-9 2.23 1.3E-9 L sw 0.89 3.9E-6 6.4E-9 0.89 6.4E-9 M wsw >5 N/A N/A >5 N/A N W >5 N/A N/A >5 N/A P WNW >5 N/A N/A >5 N/A Q NW >5 N/A N/A >5 N/A R NNW 1.11 1.1E-6 4.8E-9 >5 N/A Table 2.2-3 locations based on 2001 Land Use Census, onsite gardens are not considered for the Land Use Census.

Values from ODCM Reference 15.

- Distances shown are actual miles in each sector. In cases where dispersion parameters were not available for a location they were taken from the closest distance interval to the plant.

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

GRAND GULF, UNIT 1 2.0-23 Revision 25 - 01/03

TABLE 2 . 2 - 3 a S I T E BOUNDARY ATMOSPHERIC DISPERSION PARAMETERS*

f o r LCO 6 . 1 1 . 4 SECTOR I DIRECTION 1I S I T E BOUNDARY DISTANCE, MILES** I x/o I D/O A I N 10.79 I 2.OE-6 I 8.4E-9 B NNE 0.66 2.1E-6 9.8E-9 C NE 0.63 2.3E-6 1.OE-8 D I ENE 10.63 I2.2E-6 17.33-9 E E 0.55 2.6E-6 8.5E-9 F ESE 0.55 2.5E-6 8.5E-9 G I SE 10.51 I3.4E-6 I1.3E-8 H SSE 0.46 5.OE-6 1.8E-8 J S 0.61 3.5E-6 1.2E-8 K 1 ssw 10.65 I4.1E-6 I1.OE-8 L sw 0.85 4 2E-6 6.9E-9 M wsw 1.07 2.1E-6 2.5E-9 N I W I 1.14 I 7.3E-7 I 1.OE-9 P WNW 1.34 3.5E-7 5.1E-10 Q NW 1.37 4.6E-7 1.OE-9 R I NNW / 1.02 I 1.3E-6 I 5.5E-9

V a l u e s f r o m ODCM R e f e r e n c e 1 5 .

- D i s t a n c e s s h o w n a r e a c t u a l m i l e s i n each s e c t o r GRAND GULF, UNIT 1 2.0-23a Revision 25 - 01/03

TABLE 2.2-333 ADDITIONAL RECEPTOR LOCATIONS WITHIN THE SITE BOUNDARY**

For LCO 6.11.4 SECTOR DIRECTION MILES DESCRIPTION x/Q* D/Q* Unrestricted Area Within Site Boundary B NNE 0.5 Recreational 3.3E-6 1.5E-8 No Vehicle Laydown Area R NNW I 0.5 Energy Services Center' I 3.83-6 1 1.8E-8 1 No Q NW 10.75 I Gin Lake' ~ 1.1E-6 12.93-9 I Yes P WNW 0.75 Hamilton Lake' 8.63-7 1.4E-9 Yes J S 0.40 Site Garden 7.1E-6 2.3E-8 Yes

'These locations occupy multiple sectors. In each case the SITE BOUNDARY locations used in the dose calculation was limiting.

"Values from ODCM Reference 15 I

- The X/Q and D/Q factors from ODCM Reference 14 or 15 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.

GRAND GULF, UNIT 1 2.0-23b Revision 25 - 01/03

2.3 M e t e o r o l o g i c a l Model 2.3.1 A t m o s p h e r i c D i s p e r s i o n (Annual A v e r a g e )

The XOQDOQ s o f t w a r e , NUREG/CR-2919, Computer Program f o r t h e M e t e o r o l o g i c a l E v a l u a t i o n of Routine E f f l u e n t Releases a t N u c l e a r Power S t a t i o n s , o r s i m i l a r , s h o u l d b e u s e d t o c a l c u l a t e atmospheric d i s p e r s i o n f a c t o r s f o r r o u t i n e continuous long t e r m r e l e a s e s . Software i n p u t parameters u s e t h e normal s e t t i n g s a s d e s c r i b e d i n T a b l e 2 . 1 o f NUREG/CR-2919 w i t h t h e f o l l o w i n g e x c e p t i o n s :

Calm v a l u e s a r e d i s t r i b u t e d i n a s e p a r a t e windspeed c a t e g o r y ( i . e . , lStw i n d s p e e d c a t e g o r y ) w i t h t h e same p r o p o r t i o n and d i r e c t i o n a s t h e d i r e c t i o n frequency of t h e 2nd windspeed c l a s s . (Reference 10,14,15)

No t e r r a i n recirculation factor i s applied. (Reference 5, S e c t i o n 3AI 0.224 m / s e c f o r calm ( R e f e r e n c e 7 , 15) 1 4 windspeed c a t e g o r i e s a r e u s e d ( R e f e r e n c e 1 4 , 1 5 )

7 s t a b i l i t y c l a s e s , A-G (Reference 10,14,15) 1 r e l e a s e e x i t p o i n t (Reference 10,14,15) 1 0 m e t e r f o r m e a s u r e d wind, g r o u n d l e v e l r e l e a s e

( R e f e r e n c e 7 , lo, 1 4 , 1 5 )

N o decay Normally, maximum windspeed c a t e g o r i e s a r e 0.224, 0 . 5 ,

0.75, 1 . 0 0 , 1.25, 1.50, 1 . 7 5 , 2.00, 2.50, 3.00, 4.00, 5.00, 7 . 0 0 , 13.00 ( m / s e c ) (Reference 1 4 , 1 5 )

Height of v e n t ' s r e l e a s e p o i n t = 31 m e t e r s (Reference 15)

Height of v e n t ' s b u i l d i n g = 53.3 m e t e r s (Reference 15)

Minimum c r o s s - s e c t i o n a l a r e a f o r t h e v e n t ' s b u i l d i n g =

2729 m e t e r s ' ( R e f e r e n c e 1 4 , 1 5 )

GR%ND GULF, U N I T 1 2.0-24 R e v i s i o n 25 - 0 1 / 0 3

2.3.2 Atmospheric Dispersion (Hourly Average) I 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 6 k ruC where :

r - distance (m) from release point to location of interest 6 = plume depletion factor at distance r from ODCM Figure 2.3-1 u - hourly average wind speed at ground level I (m/sec) k - open terrain recirculation factor at distance r, from ODCM Reference 16 1.2 k c = the lesser of (cr2 + b2/2n) or (3) CT where:

CT - vertical standard deviation (m) of the plume at distance r for ground level releases under the stability category indicated by AT, from ODCM Figure 2.3-2 AT = temperature differential with vertical separation ( OF/ 4Om) height of the reactor building = 53.3m G W D GULF, UNIT 1 2.0-24a Revision 25 - 01/03

2.3.3 Deposition (Hourly Average)

Relative deposition per unit area for all releases is I

calculated for a ground level release as follows:

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

(2.55 x D, x K ) / r 1 where :

D = relative deposition rate at distance r for ground 4

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 2.0-25 Revision 25 - 01/03

"TEXT DELETED" 2 . O-26

2.4 Definitions of Gaseous Effluents Parameters b = height of reactor building (m) (2.3.1) c = count rate of the station vent monitor corresponding to grab sample radionuclide concentrations (2.1.1)

C' = count rate of station vent monitor corresponding to a 1.0 pCi/ml concentration of Xe-133 (2.1.2)

D = relative deposit$on rate for ground level releases from g Figure 2.3-3 (m ) (2.3.2) average organ dose rate in current year (mrem) (2.2.1.b)

Do -

D = dose to an individual from radioiodines and radionuclides in P particulate form, with half-life greater than eight days (mrem)

(2.2.2.b)

- average skin dose rate in current year (mrem) (2.2.1.a)

Ds -

- average total body dose rate in current year (mrem)

Dtb (2.2.1.a)

D = air dose due to beta emissions from noble gas radio-nuclide i P (mrad) (2.2.2.a)

D = air dose due to gamma emissions from noble gas radio-nuclide i Y (mrad) (2.2.2.a)

-L D/Q = relative deposition per unit area (m ) (2.3.2) c T = plume depletion factor at distance r for appropriate stability class and effective height from Figures 2.3-2 and 2.3-3 (2.3.1)

F = fraction of current year elapsed at time of calculation (2.1.1) k = open terrain recirculation factor ODCM Reference 16 (2.3.2) I GRAND GULF, UNIT 1 2.0-27 Revision 25 - 01/03

2.4 Definitions of Gaseous Effluents Parameters (Continued)

K = total body dose factor for3Kr-89, the most restrictive isotope (mrem/yr per pCi/m ), from Table 2.1-l (2.1.2)

K = total body dose factor due ty gamma emissions from i isotope i (mrem/yr per pCi/m ) from Table 2.1-l (2.1.1)

D limiting dose rate to the total body based on the limit TB = of 500 mrem in one year. (2.1.1)

D = limiting dose rate to the skin based on the limit of 3000 mrem SS in one year. (2.1.1)

L = skin dose factor for Kr-89, the most restrictive isotope (mrem/yr per @i/m3) from Table 2.1-l (2.1.2)

L = skin dose factor due to beta emissions from isotope i (mrem/yr i per pCi/m'), from Table 2.1-l (2.1.1)

M = air dose factor for Kr-89, the most restrictive isotope (mrad/yr per pCi/m3) from Table 2.1-l (2.1.2)

Mi = air dose factor due to gamma emissions from isotope i (mrad/yr per @i/m3) from Table 2.1-l (2.1.1)

N = air dose factor due to beta emissions from noble gas i radionuclide i (mrad/yr per pCi/m') from Table 2.1-l (2.2.2.a)

P = dose parameter for radionuclide i, (mrem/yr per pCi/m3) for i inhalation from (m2

mrem/yr per pCi/sec) for other pathways, from Table 2.2-l (2.2.1.b).

Q = rate of release of noble gas radionuclide i (pCi/sec) (2.1.1) i I average release rate for the current year (pCi/sec) of isotope Q =

i i of tritium, I-131, I-133 or other L*uI

.___l:__.._,:A-IIuLIIuc :- ..-*+,

111 ,717,-,+r\

pa1 C_LLulaL=

form, with half-life greater than eight (8) days (2.2.1.b)

Q. = cumulative release of radionuclide i of noble gas, tritium, I-1 131, I-133, or material in particulate form over the period of interest (PCi) (2.2.2.a) (2.2.2.b)

GRAND GULF, UNIT 1 2.0-28 Revision 5 - 01/85

2.4 Definitions of Gaseous Effluents Parameters (Continued)

Q" = assigned release rate value of, for example, 1.0 pCi/sec, Xe-i 133; related to definition of C' for the vent. (Note 3)

R = do$e factor for radionuclide i, (mrem/yr per pCi/m3) or i

(m mrem/yr per yCi/sec)

R = count rate per mrem/yr to the skin. (2.1.1)

S R = count rate per mrem/yr to the total body. (2.1.1) t R" = conservative count rate per mrem/yr to the skin. (2.1.2)

S R'lt = conservative count rate per mrem/yr to the total body. (2.1.2) r = distance (m) from release point to location of interest for dispersion calculation. (2.3.1)

GRAND GULF, UNIT 1 2.0-29 Revision 21 - 12/97

2.4 Definitions of Gaseous Effluents Parameters (Continued)

S -

__ count rate of station vent noble gas monitor at alarm setpoint V

level. (2.1.1) c = vertical standard deviation of the plume with building wake correction (m). (2.3.1) c i = vertical standard deviation (m) of the plume at distance r for effective height under stability category indicated by T(m) from Figure 2.3-2. (2.3.1)

QT = temperature differential with vertical separation ("F/40m).

(2.3.1)

U - wind speed at ground level (m/sec). (2.3,l)

W -

__ controlling sector annual average atmospheric dispersion at the site boundary for the appropriate pathway ( sec/m3) . (2.2.1.b)

W' =: relative concentration for unrestricted areas (sec/m3).

(2.2.2.b)

X/Q = atmospheric dispersion (sec/m3) (2.3.1) m = highest sector annual average atmospheric dispersion at the unrestricted area boundary (sec/m3) (2.1.1) m' = relative concentration for unrestricted areas (sec/m3)

(2.2.2.a)

GRAND GULF, UNIT 1 2.0-30 Revision 25 - 01/03

Figure 2.3-l Plume Depletion Effect for Ground-Level Releases (A_11 AtmosDheric

_~~-~~~ Stability Classes) c C

Y zc 5

I I

I 3 I I 5

6, FRACTION REMAININGTN PLUME GRAND GULF, UNIT 1 2.0-31 Revision 15 - O1/94

Figure 2.3-2 V e r t i c a l Standard Deviation of M a t e r i a l i n a Plume

( L e t t e r s denote P a s q u i l l S t a b i l i t y Class)

D GULF, U N I T 1 2.0-32 Revision 25 - 01/03

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

I I I I ,,,,, I I 1 , ,I,,,

I I I I lllll 1 I I I11111 I

I I I lllll I I I I11111 II 11 lllll 1 I 1, ,,,,, i I I ,,,,, I I I I IIll I I I 1111111 I r, PLUME TRAVEL DISTANCE (KILOMETERS)

Graph taken from Reference 7, Figure 6 GRAND GULF, UNIT 1 2.0-33 Revision 15 - 01/94

Deleted GRAND GULF, UNIT 1 2.0-34 Revision 25 - 01/03

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 (lN64-HS-M611)

2. Bypass valve indication (lN64-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-l A flow diaaram

> 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 I 5%.

(3) Standby Gas Treatment System not normally operated.

GRAND GULF, UNIT 1 2.0-35 Revision 17 - 03/95

Figure 2.5-l Gaseous Radwaste Treatment System

POST

TR!3rum m ______________.__._------..---

-~~~~~.~~.~~~~-~-~~~~------~~~-_~-~~____

!&Lx. UC. PUMP (2) almoE Am

--. TO A-E CuTslaz AIR

+WlOi~~

., NaaTcu,

.a.._.-

GRAND GULF, UNIT 1 2.0-35a Revision 8 - 08/86

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 rlnqes UVUI" fnrLVL the L-j_ calendar year:

. Direct radiation dose

. Liquid effluent dose (DTau)

. Noble gas dose (D , D )

Y P

. Particulate dose (Dp)

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.l of the applicable LCO. This determination is made by the utilization of direct radiation measurements from indicator thermoluminescent dosimetefs (TLDsj I"CdLe'U

'^--c-^l IleaL

-^--

the GGNS property line in eight of the 16 meteorological sectors.

GRAND GULF, UNIT 1 2.0-36 Revision 20 - 07/96

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-19 M-25 M-17 M-21 M-28 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

--- .--__ th_e averaned

-.___~_- nllarterlv I-----__1 --------..

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 20 - 07/96

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.

Note: Sample locations preceded by S are in addition to those required by the Radiological Environmental Monitoring Program.

GRAND GULF, UNIT 1 3.0-1 Revision 29 - 01/05

ODCM TABLE 3.0-l 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 6iVA 3.0-2 NNE Of titiNS on HWY. 61, north Of the Vicksburg Airport (Sector B Radius, 18 miles)

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

GRAND GULF, UNIT 1 3.0-Z Revision 20 - 07/96

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 GRAND GULF, UNIT 1 3.0-3 Revision 32 - 12/05

ODCM TABLE 3.0-2 (Continued)

MISCELLANEOUS COLLECTION SITES Page 2 of 2 SEDIMENT SAMPLES FIGURE SEDHAM 3.0-1 Downstrear, 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)

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 I GGNS (Sector K, 10.5 miles) when available, otherwise a location 15-30 km distant 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 I point into the Mississippi River uninfluenced by plant operations GRAND GULF, UNIT 1 3.0-3a Revision 29 - 01/05

-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 I 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 I M-10 Grand Gulf Military Park 3.0-1 A 1.5 M-14 AS-3-61VAf Hwy. 61, north of 3.0-2 B 18.0 (CONTROL) Vicksburg Airport M-16 Meteorological Tower 3.0-1 A 0.9 M-17 S Side, Grand Gulf Road 3.0-1 C 0.5 M-19 Eastern SITE BOUNDARY 3.0-1 E 0.5 property line, NNE of HWSA M-2 1 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 I Port entrance GRAND GULF, UNIT 1 3.0-4 Revision 29 - 01/05

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-l R 0.8

&",.c,.,-,.,*-;~~,

+CVWCZL

~",tzctzL"l"yl_~or hl.,_,-

GRAND GULF, UNIT 1 3.0-5 Revision 20 - 01/96

"TEXT DELETED" GRAND GULF, UNIT 1 3.0-6 Revision 20 - 07/96

"TEXT DELETED" GRAND GULF, UNIT 1 3.0-6a Revision 20 - 07/96

"TEXT DELETED" GRAND GULF, UNIT 1 3.0-6b Revision 13 - 01/92

"TEXT DELETED" GRAND GULF, UNIT 1 3.0-6~ Revision 20 - 07/96

"TEXT DELETED" GRAND GULF, UNIT 1 3.0-6d Revision 20 - 07/96

FIGURE 3.0-1 Collection Site Locations 0-4 Mile Area Map LEGEND P Fish 0 Air Sampler 0 Surface Water A Ground Water El Broadleaf Vegetation 0 Sediment 0 TLD Ranney Wells Milk

- ENTERGY GRAND GULF NUCLEAR STATION 0-4 Mile Environmental Sampling Location Map 0 1 SCALE I N MILES Grand Gulf, Unit 1 3.0-7 Revision 32 12/05

FIGURE 3.0-2 Collection Site Locations, General Area Map 4-10 Mile Area Map LEGEND 0 Air Sampler 0 Surface Water A Ground Witer Broadleaf Vegetation

Sediment Ranney Wells 0 TLD Milk t-igure 3.0-1 18 MILES FROM GRAND GULF TO VICKSBURG AIRPORT Sector (B)

HERMANVILLE Located 13 Miles from Grand Gulf - Sector (F)

- ENTERGY GRAND GULF NUCLEAR STATION 4-10 Mile Environmental Sampling Location Map Grand Gulf, Unit 1 3.0-8 Revision 29 OIB5

OFFSITE DOSE CALCULATION MANUAL APPENDIX A RADIOLOGICAL EFFLUENT CONTROLS AND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMS A-G

1 .o 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 CATCIJTATTON

_--1__1--___- MA_NWL (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 17 - 03/95

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 SI'I'EBOUNDARY, 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 Technica 1 Specifica tion Set tion GRAND GULF, UNIT 1 A-3 Revision 17 - 03/95

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 17 - 03/95

TABLE 1.2 MODES Modes of operation are shown in Technical Specification Table 1.1-l GRAND GULF, UNIT 1 A-5 Revision 17 - 03/95

3.0 APPLICABILITY LIMITING CONDITION FOR OPERATION (LCO)

See Technical Specification Section 3.0 for LCO Applicability.

-i- ___- -i__- _ ----ii w?ANu bULJ2, UN11 i A-6

APPLICABILITY SURVEILLANCE REQUIREMENTS (SR)

See Technical Specification Section 3.0 for SR applicability.

GRAND GULF, UNIT 1 A-7 Revision 17 - 03/95

SECTION 5.0 ADMINISTRATIVE CONTROLS GRAND GULF, UNIT 1 A-8 Revision 17 - 03/95

5.0 ADMINISTRATIVE CONTROLS 5.6.2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

__.._I--

Koutine ..~~~~~~~~~_~

rauloloylcal ____1_______L_, "pt!LdLIIIg env~ronmen~dl ______L:__ ~^~^~c_ -^..--4-, CL.-

reP"rLs: L""e:Lllly ,..,,,+:,, VI LUC: "~C;LQL-I"II -F thie 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 1UC;IILILICU LCO 6.12.1

'ile*c:+:aJ 1:: ch=ll Ullclll be rnnn7-i-ad L\-pVLLLU. In thn oxron+

&II_ u"_*A1 that QA~P lll...c--_..._ res111ta LII-A-l AT-C I__ 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.

A-9 Revision 22 - 03/99

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,11 Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. For solid wastes, the format for Table 3 and Appendix B shall be

_T r ~__ _1 supplemented with three additionai categories: ciass of soiid wastes (as aerinea by 10 CFR Part 61), type of container (e.g., Steel Liner, High Integrity Container) and SOLIDIFICATION Agent or absorbent (e.g., cement, urea formaldehyde).

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

~~~~ L-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 17 - 03/95

5.0 ADMINISTRATIVE 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 Radioactive Effluent Release Report shall also include:

c. 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 on a quarterly basis following the format of Appendix B and Table 3. The following information for each type of solid waste shipped offsite for the report will be included in the report:

(1) Container Volume, (2) Total curie quantity (specify whether determined by measurement or estimate),

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

GRAND GULF, UNIT 1 A-11 Revision 28 - 10/04

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

(3) Principal radionuclide (specify whether determined by measurement or estimate),

(4) Type of waste (e.g., spent resin, compact dry waste),

(5) Class of solid waste (as defined by 10CFR Part 61),

(6) Type of Container (e.g. Steel Liner, High Integrity Container),

(7) Solidification agent or absorbent (e.g. cement, urea formaldehyde).

GRAND GULF, UNIT 1 A-11a Revision 28 - 10/04

SECTION 6.0 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS GRAND GULF, UNIT 1 A-12 Revision 17 - 03/95

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 27 - 05/04

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 OPERABLE 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 inoperable. radiactive 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 18 - 02/96

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 operable.

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 operable.

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

met.

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

GRAND GULF, UNIT 1 A-14 Revision 32 - 12/05

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-15 Revision 17 - 03/95

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-16 Revision 17 - 03/95

TABLE 6.3.9-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONDITIONS REFERENCED MINIMUM FROM CHANNELS REQUIRED SURVEILLANCE INSTRUMENT OPERABLE 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-17 Revision 32 - 12/05

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 OPERABLE 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 inoperable. radiactive 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-18 Revision 17 - 03/95

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 operable.

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 operable. 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 operable.

(continued)

GRAND GULF, UNIT 1 A-19 Revision 23 - 03/01

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 Place the inoperable 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 inoperable 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 operable.

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 operable.

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 operable.

(continued)

GRAND GULF, UNIT 1 A-20 Revision 27 - 05/04

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 operable.

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 inoperability 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-21 Revision 27 - 05/04

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 inoperable 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-22 Revision 17 - 03/95

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. Instrument controls not set in operate mode.

92 days 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 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.

Perform a CHANNEL CALIBRATION. 12 months SR 6.3.10.8 Perform a CHANNEL CALIBRATION 18 months GRAND GULF, UNIT 1 A-23 Revision 17 - 03/95

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 6.3.10.6 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 18 - 02/96

TABLE 6.3.10-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONDITIONS REFERENCED FROM MINIMUM CHANNELS REQUIRED SURVEILLANCE INSTRUMENT OPERABLE 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 6.3.10.6 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

3. 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 6.3.10.6 SR 6.3.10.8

e. Sampler Flow Rate 1 (a) D SR 6.3.10.1 Measuring Device SR 6.3.10.8 GRAND GULF, UNIT 1 A-25 Revision 21 - 12/97

TABLE 6.3.10-1 (Continued)

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

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 6.3.10.6 SR 6.3.10.8

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

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 GRAND GULF, UNIT 1 A-26 Revision 18 - 02/96

TABLE 6.3.10-1 (Continued)

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

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&B)

a. Noble Gas Activity Monitor 1/system (a) G SR 6.3.10.1 Provding Alarm SR 6.3.10.3 SR 6.3.10.5 SR 6.3.10.7 GRAND GULF, UNIT 1 A-27 Revision 18 - 02/96

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.

GRAND GULF, UNIT 1 A-28 Revision 21 - 12/97

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 inoperable.

GRAND GULF, UNIT 1 A-29 Revision 17 - 03/95

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 17 - 03/95

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 17 - 03/95

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 17 - 03/95

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 17 - 03/95

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 inoperable.

(continued)

GRAND GULF, UNIT 1 A-34 Revision 25 - 01/03

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 17 - 03/95

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 17 - 03/95

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 inoperable.

GRAND GULF, UNIT 1 A-37 Revision 17 - 03/95

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 17 - 03/95

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)

(4) Turbine Continuous(d) 31 days Gross Alpha 1x10-11 Building (f) Composite Ventilation Particulate Exhaust Sample Continuous(d) 92 days Sr-89, Sr-90 1x10-11 (f) Composite Particulate 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 17 - 03/95

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 17 - 03/95

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 inoperable 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 .

GRAND GULF, UNIT 1 A-41 Revision 17 - 03/95

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 inoperable.

(continued)

GRAND GULF, UNIT 1 A-42 Revision 17 - 03/95

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 17 - 03/95

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. inoperable.

(continued)

GRAND GULF, UNIT 1 A-44 Revision 17 - 03/95

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 17 - 03/95

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 17 - 03/95

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 17 - 03/95

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 effluent in an Report 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 17 - 03/95

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 17 - 03/95

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 3 locations: Continuous sampler Radioiodine Cannister:

Particulates operation with sample I-131; 7 days 1 sample 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.

GRAND GULF, UNIT 1 A-50 Revision 20 - 07/96

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 32 - 12/05

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 in vicinity of GGNS 366 days Gamma isotopic(c) discharge point on edible portion; 366 days 1 sample uninfluenced by GGNS 366 days Gamma isotopic(c) discharge on edible portion; 366 days GRAND GULF, UNIT 1 A-52 Revision 21 - 12/97

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.

GRAND GULF, UNIT 1 A-53 Revision 20 - 07/96

TABLE 6.12.1-1 (Continued)

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATION (Continued) 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.

GRAND GULF, UNIT 1 A-54 Revision 20 - 07/96

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-55 Revision 17 - 03/95

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 H-3 2 x 103(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-56 Revision 17 - 03/95

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 LLD = b 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-57 Revision 17 - 03/95

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-58 Revision 17 - 03/95

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-59 Revision 20 - 07/96

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-60 Revision 20 - 07/96

BASES FOR SECTION 6.0 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS GRAND GULF, UNIT 1 A-61 Revision 17 - 03/95

6.3 INSTRUMENTATION 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 OPERABILITY 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 OPERABILITY 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-62 Revision 17 - 03/95

6.11 RADIOACTIVE EFFLUENTS 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 1I.A and 1I.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 1I.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, 1II.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 1II.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-63 Revision 17 - 03/95

RADIOACTIVE EFFLUENTS 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-64 Revision 17 - 03/95

RADIOACTIVE EFFLUENTS 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-65 Revision 17 - 03/95

RADIOACTIVE EFFLUENTS 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 1I.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 1I.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 inoperable equipment or subsystems which resulted in liquid radwaste being discharged without treatment, (3) the reason for the inoperability (4) action(s) taken to restore the inoperable equipment to an OPERABLE 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 1I.A and 1I.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-66 Revision 17 - 03/95

RADIOACTIVE EFFLUENTS 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, 1II.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section 1I.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 1II.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-67 Revision 22 - 03/99

RADIOACTIVE EFFLUENTS 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-68 Revision 17 - 03/95

RADIOACTIVE EFFLUENTS 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, 1II.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section 1I.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 1II.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 inhalation 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) (41, 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-69 Revision 17 - 03/95

RADIOACTIVE EFFLUENTS 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-70 Revision 17 - 03/95

RADIOACTIVE EFFLUENTS 6.11.7 and 6.11.8 GASEOUS RADWASTE TREATMENT AND VENTILATION EXHAUST TREATMENT The OPERABILITY 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 1I.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 1I.B and 1I.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 inoperable equipment or subsystems which resulted in gaseous radwaste being discharged without treatment, (3) the reason for the inoperability, (4) action(s) taken to restore the inoperable equipment to an OPERABLE 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 (lN64-HS-M611),

(2) Bypass Valve Indication (lN64-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-71 Revision 17 - 03/95

6.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 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-72 Revision 17 - 03/95

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) + . ..21.0. 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-73 Revision 17 - 03/95

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-74 Revision 17 - 03/95

GNRO-2006/00018, Annual Radioactive Effluent Release Report (ARERR)

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GNRO-2006/00018, Annual Radioactive Effluent Release Report (ARERR)

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