Text

Radioactive Effluent Release Report, January Through December 2002, List of Effective Pages - Figure 5-2
	ML030690072
Person / Time
Site:	Columbia
Issue date:	12/31/2002
From:	; Energy Northwest
To:	; Office of Nuclear Reactor Regulation
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ENERGY NORTHWEST COLUMBIA GENERATING STATION OFFSITE DOSE CALCULATION MANUAL

AMENDMENT NO. 37 JANUARY 2003 OFFSITE DOSE CALCULATION MANUAL CHAPTERS 1-5 LIST OF EFFECTIVE PAGES Page Amendment Page Amendment i 35 18 35 ii 35 19 35 35 20 36 iv 35 21 35 35 22 35 vi 35 23 35 1 35 24 35 2 35 25 35 3 35 26 35 4 35 27 35 5 35 28 35 6 35 29 35 7 35 30 35 8 35 31 35 9 35 32 35 10 35 33 35 11 35 34 35 12 35 35 35 13 35 36 35 14 35 37 35 15 35 38 35 16 35 39 35 17 35 40 35 LEP-1

AMENDMENT NO. 37 JANUARY 2003 OFFSITE DOSE CALCULATION MANUAL CHAPTERS 1-5 LIST OF EFFECTIVE PAGES Page Amendment Page Amendment 41 35 64 35 42 35 65 35 43 35 66 35 44 35 67 35 45 35 68 35 46 35 69 35 47 35 70 35 48 35 71 35 49 35 72 35 35 73 35 50 51 35 74 35 52 35 75 35 53 35 76 35 54 35 77 35 35 78 35 55 35 79 35 56 57 35 80 35 35 81 35 58 35 82 35 59 35 83 35 60 35 84 35 61 35 85 35 62 63 35 86 35 LEP-2

AMENDMENT NO. 37 JANUARY 2003 OFFSITE DOSE CALCULATION MANUAL CHAPTERS 1-5 LIST OF EFFECTIVE PAGES Page Amendment Page Amendment 87 35 88 35 89 35 90 35 LEP-3

AMENDMENT NO. 35 MARCH 2002 OFFSITE DOSE CALCUATION MANUAL TABLE OF CONTENTS Section Title

1.0 INTRODUCTION

.............................................. 1 2.0 LIQUID EFFLUENT CALCULATIONS ................................ 3 2.1 Introduction .............................................. 3 2.2 Radwaste Liquid Effluent Radiation Monitoring System ................... 3 2.3 10 CFR 20 Concentration Limits .................................. 3 2.3.1 Pre-Release Calculation ................................... 4 2.3.2 Post-Release Calculation ................................... 5 2.4 Radwaste Liquid Effluent Dilution Ratio and Alarm Setpoints Calculations ...... 5 2.4.1 Introduction ......................................... 5 2.4.2 Methodology for Determining the Total Effluent Concentration Limit (ECL) Fraction ........................... 6 2.4.3 Methodology for the Determination of Minimum Dilution Factor ....... 6 2.4.4 Methodology for the Determination of Liquid Effluent Monitor Setpoints . . 8 2.5 10 CFR 50, Appendix I, Dose Calculation ........................... 10 2.5.1 Projection of Doses .................................... 12 2.6 Methods for Calculating Doses to Man From Liquid Effluent Pathways ........ 12 2.6.1 Radiation Doses ........................................ 13 2.6.2 Plant Parameters ....................................... 16 2.7 Liquid Holdup Tanks ......................................... 17 2.7.1 Maximum Allowable Liquid Radwaste Activity in Temporary Radwaste Hold-Up Tanks ................................. 17 i

AMENDMENT NO. 35 MARCH 2002 OFFSITE DOSE CALCUATION MANUAL I TABLE OF CONTENTS Section Title 2.7.2 Maximum Allowable Liquid Radwaste in Tanks That Are Not Surrounded by Liners, Dikes, or Walls ............... ....... 19 2.8 Other Liquid Radiation Monitors ................................. 20 3.0 GASEOUS EFFLUENT DOSE CALCULATIONS .......................... 29 3.1 Introduction ............................................... 29 3.2 Gaseous Effluent Radiation Monitoring System ........................ 30 3.2.1 Reactor Building Elevated Discharge Radiation Monitor ............. 30 3.2.2 Radwaste Building Ventilation Exhaust Monitor .................. 31 3.2.3 Turbine Building Ventilation Exhaust Monitor ................... 31 3.3 Release Rate Limits .......................................... 31 3.3.1 Noble Gases .......................................... 31 3.3.2 Radioiodines and Particulates ............................... 32 3.3.2.1 Dose Parameter for Radionuclide i (P) ............... 34 3.4 Calculation of Gaseous Effluent Monitor Alarm Setpoints ................. 35 3.4.1 Introduction .......................................... 35 3.4.2 Setpoint Determination for all Gaseous Release Paths ............... 35 3.4.2.1 Setpoints Calculations Based on Whole Body Dose Limits ... 35 3.4.2.2 Setpoints Calculations Based on Skin Dose Limits ..... ... 38 3.5 10 CFR 50 Dose Calculation ................................ ... 38 3.5.1 Noble Gases ...................................... ... 39 ii

AMENDMENT NO. 35 MARCH 2002 OFFSITE DOSE CALCUATION MANUAL TABLE OF CONTENTS Section Title Page 3.5.2 Radioiodines, Tritium and Particulates ........................ 41 3.5.2.1 Dose Parameter for Radionuclide i (R). ............... 42 3.5.3 Annual Doses At Special Locations .......................... 48 4.0 COMPLIANCE WITH 40 CFR 190 - TOTAL DOSE ........................ 80 4.1 Requirement For Operability (RFO) ............................... 80 4.2 ODCM Methodology for Determining Dose and Dose Commitment from Uranium Fuel Cycle Sources ................................ 80 4.2.1 Total Dose from Liquid Effluents ............................ 80 4.2.2 Total Dose from Gaseous Effluents .......................... 80 4.2.3 Direct Radiation Contribution .............................. 81 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING ...................... 82 5.1 Radiological Environmental Monitoring Program (REMP) ................ 83 5.2 Land Use Census ............................................ 83 5.3 Laboratory Intercomparison Program .............................. 83 APPENDIX Radiological Effluent and Radiological Environmental Monitoring Controls ilU

AMENDMENT NO. 35 MARCH 2002 OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES Table Title Pane Section 2.0 2-1 Fish Bioaccumulation Factors (BF1) and Adult Ingestion Dose Conversion Factors (DF1) ......................... 21 2-2 Ingestion Dose Factors (Ai.) for Total Body and Critical Organ .................. 24 2-3 Input Parameters Used to Calculate Maximum Individual Dose from Liquid Effluents .... 27 Section 3.0 3-1 Dose Factors for Noble Gases and Daughters .............................. 49 3-2 Distances (Miles) to Typical Controlling Locations as Measured from Center of Columbia Generating Station Containment Building ....... 50 3-3 Long-Term Average Dispersion (X/Q) and Deposition (D/Q) Values for Typical Locations ................ ............. 51 3-4 Dose Rate Parameters Implementation of 10 CFR 20, Airborne Releases ............. 52 3-5a Dose Parameters for 10 CFR 50 Evaluations, Airborne Releases Age Group: Adult .................................. ............. 54 i

3-5b Dose Parameters for 10 CFR 50 Evaluations, Airborne Releases Age Group: Teen ................................... ............. 55 3-5c Dose Parameters for 10 CFR 50 Evaluations, Airborne Releases Age Group: Child ................................... ............. 56 3-5d Dose Parameters for 10 CFR 50 Evaluations, Airborne Releases Age Group: Infant .................................. ............. 57 3-6 Input Parameters for Calculating R P ....................... ............. 58 iv

AMENDMENT NO. 35 MARCH 2002 OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES Table Title Page M

3-7 Input Parameters for Calculating R 1 ................................... 59 3-8 Input Parameters for Calculating R.V 60 3-9 Input Parameters for Calculating Dose Summaries to the Maximum Individual and the Population Within 50 Miles of Columbia Generating Station from Gaseous Effluents .... ........................................... 61 3-10 Reactor Building Stack X/Q and D/Q Values .............................. 63 3-11 Turbine or Radwaste Building X/Q and D/Q Values ......................... 67 3-13 Characteristics of Gaseous Effluent Release Points .......................... 71 3-14 References for Values Listed in Tables 3-8 and 3-9 .......................... 72 3-15 Design Base Percent Noble Gas (30-minute Decay) .......................... 73 3-16 Annual Doses at Typical Locations ..................................... 74 3-17 Annual Occupied Air Dose at Typical Locations ............................ 75 Section 5.0 5-1 REMP Locations ..... ............................................ 85 V

AMENDMENT NO. 35 MARCH 2002 OFFSITE DOSE CALCULATION MANUAL LIST OF FIGURES Figure Title Page 2-1 Simplified Block Diagram of Liquid Waste System .......................... 28 3-1 Site Boundary for Radioactive Gaseous and Liquid Effluents .................... 76 3-2 Simplified Block Diagram of Gaseous Waste System ......................... 77 3-3 Simplified Block Diagram of Off-Gas Treatment System ...................... 78 3-4 Auxiliary Boiler ................................................ 79 5-1 Radiological Environmental Monitoring Sample Locations Inside of 10-Mile Radius ..... 89 5-2 Radiological Environmental Monitoring Sample Locations Outside of 10-Mile Radius .... 90 vi

AMENDMENT NO. 35 MARCH 2002

1.0 INTRODUCTION

The Offsite Dose Calculation Manual (ODCM) is required by Technical Specification Section 5.5.1. This Technical Specification section and the ODCM implement the requirements of 10 CFR 20, 10 CFR 50 and 40 CFR 190 that apply to radioactive effluents from the plant.

The ODCM contains the methodology and parameters used in the calculation of offsite radionuclide concentrations and doses resulting from liquid and gaseous radioactive effluents. In most cases, these doses must be calculated, as the amount of dose received outside the plant is too low to be measurable. The ODCM also describes the methodology used to establish gaseous and liquid effluent monitoring alarm and trip setpoints.

The ODCM also contains the Radiological Effluent and Environmental Monitoring Controls.

The Radiological Effluent Controls Program implements the requirements of Technical Specification Section 5.5.4. The Radiological Effluent Controls were previously known as the Radiological Effluent Technical Specifications (RETS). The Radiological Environmental Monitoring Controls are part of the Radiological Environmental Monitoring Program (REMP).

The REMP controls supplement the effluent controls by verifying that measurable concentrations of radioactive materials in the environment are not greater than predicted by the effluent controls. At Columbia Generating Station, the Radiological Effluent and Environmental Monitoring Controls are contained in the ODCM Appendix. They are written in the same format as the Licensee Controlled Specifications (LCS). This common format allows for ease of use by the plant staff.

The Solid Radioactive Waste or Process Control Program (PCP) is not part of the ODCM, except for Radioactive Effluent Release Report Requirements provided in the ODCM Appendix Section 6.4. FSAR Section 11.4.3 describes the requirements for the PCP. This includes the objective program requirements, process control systems, and waste characterization. Plant Procedures implement the PCP.

The ODCM reflects the requirements of both 10 CFR 20.1-20.602 (the old Part 20) and 10 CFR 20.1001-20.2402 (the new Part 20). Technical Specification 5.5.4c requires monitoring, sampling, and analysis of radioactive liquid and gaseous effluents pursuant to 10 CFR 20.1302. 10 CFR 20.1302 requires surveys of effluents in unrestricted areas for the purpose of demonstrating compliance with 10 CFR 20.1301. Section 1301 sets dose limits for members of the public. These limits are stated in terms of Total Effective Dose Equivalent (TEDE). 10 CFR 20.1-20.602 (the original Part 20 requirements) as well as 10 CFR 50, Appendix I and 40 CFR 190 regulate dose in terms of dose to a critical organ. The NRC addressed this issue in a series of Questions and Answers on this topic in 1995. The Answers state that 10 CFR 50, Appendix I is not changed concurrently with the new Part 20. Therefore, until Appendix I is changed licensees must continue to show compliance to the new Part 20 based on Appendix I, with dose calculations expressed in terms of organ and whole body doses.

The computer codes LADTAP II and GASPAR II may be used to perform these calculations.

For liquid effluents, however, the concentration limits are to be changed to reflect the new values in 10 CFR 20.1001-20.2402, Appendix B. The corresponding bases and certain alarm 1

AMENDMENT NO. 35 MARCH 2002 set points for the liquid monitors are also to be changed. The methodology used in the ODCM to determine the necessary dilutions are required to be changed from the old Maximum Permissible Concentration (MPC) to the now required Effluent Concentration Limits (ECLs).

The Columbia Generating Station ODCM has been changed to accommodate the above requirements resulting from the new 10 CFR 20.1001-20.2402.

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AMENDMENT NO. 35 MARCH 2002 2.0 LIQUID EFFLUENT CALCULATIONS Liquid effluent calculations are discussed in this section of the ODCM. Calculations of liquid effluent concentrations are made to show compliance with the limits of 10 CFR 20. The methodology for calculating dilution factors and liquid effluent monitor setpoints are also discussed. This section outlines the methods used to calculate off-site radiation dose to show compliance to 10 CFR 50, Appendix I. This section also presents the calculations used to establish the maximum allowable liquid radioactive waste activity available in temporary hold-up tanks in accordance with Technical Specification 5.5.8.b.

2.1 Introduction Liquid radwaste released from Columbia Generating Station will meet control limits at a single point of discharge to the Columbia River. Actual discharges of liquid radwaste effluents will only occur on a batch basis, and the average concentration at the point of discharge will be only a small percentage of the allowed limits. A simplified block diagram of the liquid waste management system and effluent pathways is contained in Figure 2-1.

2.2 Radwaste Liquid Effluent Radiation Monitoring System This monitoring subsystem measures the radioactivity in the liquid effluent prior to its entering the cooling tower blowdown line.

All radwaste effluent passes through a four-inch line which has an off-line sodium iodide radiation monitor. The radwaste effluent flow, (variable from 0 to 190 gpm), combines with the 36-inch cooling water blowdown line, (variable from 0 to 7500 gpm) and is discharged to the Columbia River with a total flow based on the total Effluent Concentration Limit (ECL) fraction and cooling water flushing needs.

Additional information on this monitoring system can be found in FSAR Section 11.5.2.2.2.3.

2.3 10 CFR 20 Concentration Limits The requirements pertaining to discharge of radwaste liquid effluents to the unrestricted area are specified in Requirement for Operability 6.2.1.1. In order to comply with this requirement, limits will be set to ensure that blowdown line concentrations do not exceed ten times 10 CFR 20.1001-20.2402, Appendix B, Table 2, Column 2 at any time.

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AMENDMENT NO. 35 MARCH 2002 2.3.1 Pre-Release Calculation The activity of the radionuclide mixture to be discharged and the liquid effluent discharge rate will be determined prior to discharge in accordance with Energy Northwest procedures. The effluent concentration for each nuclide is determined by the following equation:

Coc.=Cixfw Cone - iXf ft (1) where:

Cone, = Concentration of radionuclide i in the effluent at point of discharge

- yCi/ml.

Ci = Concentration of radionuclide i in the batch to be released - pCi/mi.

fw = Discharge flow rate from sample tank to the blowdown line - variable from 0 to 190 gpm.

fb = Blowdown flow rate - variable from 0 to 7500 gpm.

ft = Total discharge (ft = fb + fw) flow rate - variable from 0 to 7690 gpm.

The calculated concentration in the blowdown line must be less than ten times the concentrations listed in 10 CFR 20.1001-20.2402, Appendix B. Before releasing the batch to the environment, the following equation must hold:

m ECLf= (Conci /ECLi) 1 (2) i=1 where:

ECLf = Total ECL Fraction Conce = Concentration of radionuclide i in the effluent at the point of discharge 10Ci/mL.

ECL, = Ten times the effluent concentration of nuclide i listed in 10 CFR 20.1001-20.2402, Appendix B, Table 2, Column 2.

m = Total number of radionuclides in the batch.

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AMENDMENT NO. 35 MARCH 2002 2.3.2 Post-Release Calculation The concentration of each radionuclide in the unrestricted area, following the batch release, will be calculated as follows:

The average activity of radionuclide i during the time period of the release is divided by the Plant Discharge Flow/Tank Discharge Flow ratio yielding the concentration at the point of discharge:

Ckx fw nc - ft (3) where:

Conck = The concentration of radionuclide i in the effluent at the point of discharge during the release period k - (l.Ci/ml).

I C = The concentration of radionuclide i in the batch during the release period k

- (pCi/ml).

fw = Discharge flow rate from sample tank to the blowdown line - variable from 0 to 190 gpm.

fb = Blowdown flow rate - variable from 0 to 7500 gpm.

ft = Total discharge (ft = fb + fw) flow rate - variable from 0 to 7690 gpm.

To ensure compliance with 10 CFR 20.1001-20.2401, the following relationships must hold:

E (Concik /ECLi) __1 (4) i= 1 where the terms are as defined in Equation (2) and (3).

2.4 Radwaste Liquid Effluent Dilution Ratio and Alarm Setpoints Calculations 2.4.1 Introduction The dilution alarm ratio and setpoints of the sample liquid effluent monitor are established to ensure that the limits of ten times 10 CFR 20.1001-20.2402, Appendix B, Table 2, Column 2, are not exceeded in the effluent at the discharge point (i.e., compliance with RFO 6.2.1.1, as discussed in section 2.3.1 of this manual).

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AMENDMENT NO. 35 MARCH 2002 The alarm (HI) and the alarm/trip (HI-HI) setpoints for the liquid radwaste effluent monitor are calculated from the results of the radiochemical analysis of the pre-release effluent sample. The setpoints are set into the radwaste monitor just prior to the release of each batch of radioactive liquid.

2.4.2 Methodology for Determining the Total Effluent Concentration Limit (ECL) Fraction Radwaste liquid effluents can only be discharged to the environment through the four-inch radwaste line. The maximum radwaste discharge flow rate is 190 gpm. Prior to discharge, the tank is isolated and recirculated for at least thirty minutes, and a representative sample is taken from the tank. An isotopic analysis of the batch will be made to determine the sum of the ECL fraction (ECLf) based on ten times the 10 CFR 20.1001-20.2402 limits. From the sample analysis and ten times the effluent concentration values in 10 CFR 20.1001-20.2402, the ECLr is determined using the following equation.

ECf Ci ECL= (5) i= i ECLi where:

ECLf = Total ECL fraction in the liquid effluent waste sample.

Ci = The concentration of each measured radionuclide i observed by the radiochemical analysis of the liquid waste sample (IiCi/ml).

ECL, = Ten times the limiting concentrations of radionuclide i from 10 CFR 20.1001-20.2402, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04

/LCi/ml total activity.

m = The total number of measured radionuclides in the liquid batch to be released.

If the ECLr is less than or equal to 0.8, the liquid batch may be released at any radwaste discharge or blowdown rate. If the ECLf exceeds 0.8, then a dilution factor (Fd) must be determined. The liquid effluenft radiation monitor responds proportionally to radioactivity concentrations in the undiluted waste stream. Its setpoint must be determined for diluted releases.

2.4.3 Methodology for the Determination of Minimum Dilution Factor The measured radionuclide concentrations are used to calculate the dilution factor (Fd), which is the ratio of the total discharge flow rates (RW + CBD) to the radwaste tank effluent flow rate (RW) that is required to assure that the limiting concentrations of RFO 6.2.1.1 are met at the point of discharge.

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AMENDMENT NO. 35 MARCH 2002 The minimum dilution factor (Fd) is determined according to:

Fd =ECLf x Fs (6) where:

Fd = The minimum dilution factor required for compliance with ten times 10 CFR 20.1001-20.2402, Appendix B, Table 2, Column 2.

Fs = The safety factor; a conservative factor used to compensate for statistical fluctuations and errors in measurements. For example, a safety factor (Fs) of 1.5 corresponds to a fifty (50) percent (%) variation. The safety factor is 1.5.

The dilution which is required to ensure compliance with RFO 6.2.1.1 concentration limits will be set such that discharge rates are:

Fd < W+f fw (7) and follows that:

fW <fwb f (7a)

Fd-1 or fb > fw(Fd-1) (7b) where:

Fd = The minimum dilution factor from Equation (6).

fw = The discharge flow rate from the liquid radwaste tank to the blowdown line - variable from 0 to 190 gpm.

fb = The cooling tower blowdown flow rate - variable from 0 to 7500 gpm.

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AMENDMENT NO. 35 MARCH 2002 2.4.4 Methodology for the Determination of Liquid Effluent Monitor Setpoints Liquid effluents must meet the restrictions at the point of discharge to the river of ten times ECL or less after dilution. Therefore, the Liquid Effluent Monitor setpoint must be determined such that it will terminate a discharge at less than or equal to that point. The dilution factor must satisfy Equation (7).

Setpoint < CM (fb + fw(8) where:

Setpoint = the radwaste effluent monitor setpoint in /lCi/ml.

CM = the maximum permissible diluted concentration, in ACi/ml, at the point of release that is in compliance with ten times 10CFR20.1001-20.2402 Appendix B, Table 2, column 2.

fb and fw are defined in equation 7b.

I The Liquid Effluent Monitor measures the undiluted effluent, therefore the term flj+ fw is used to correct for dilution.

fw The total ECL fraction of the batch to be discharged, ECLf is defined in Equation (5). Since the final concentration must be less than or equal to one ECLf:

C M ' ~3cc (8a)

Substituting into Equation (8):

Setpoint 4 1I i=

m C L fb

-ECLf fw (8b) 8

AMENDMENT NO. 35 MARCH 2002 The Liquid Effluent Monitor reads out in counts per second (cps), therefore, it is necessary to convert the setpoint from jCi/ml to cps.

S :9 0. (Ci) (E)J (fb +fwJ + BKG(9 where:

Sn = the trip setpoint in cps E = the monitor efficiency for nuclide i, in cps/tCi/ml BKG = the monitor background in cps.

At low activity levels, the monitor demonstrates a normal instrument variation. In order to prevent spurious alarms and trips resulting from this variation, the setpoint can be calculated using a 1.0 ECLs representative mixture when the ECLf of the batch is less than 1.0 ECLf.

The effluent monitor also has a high alarm setpoint that will be set to alarm if the batch contents exceed the concentration expected for the current discharge. This will warn the operator that the batch release is not proceeding as anticipated by the prerelease calculation. The discharge should be stopped and the alarm cause investigated. The Hi alarm setpoint is determined to be at the monitor response for the current batch release multiplied by 1.25 to allow for normal variation in the monitor response. When the ECLf of the batch is less than 1.0 ECLf, the high setpoint will be the greater of either the calculated setpoint, or 80% of the setpoint determined from a 1.0 ECLf mixture.

m S *_5BKG + 1.25E (Ci) (Ei) (9a) i=lI where:

Sm is the monitor Hi setpoint in cps.

1.25 is a factor to account for normal variation in the monitor reading. It results in a I

maximum of a 25 % greater than expected count rate before the alarm occurs.

Sm .5 BKG + (0.8

One-ECL) (9b)

Where one-ECL is the count rate corresponding to a 1.0 ECLf representative mixture. All other terms defined in Equation 9a. 1 Setpoints established for periods when no release is taking place are described in the implementing procedures.

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AMENDMENT NO. 35 MARCH 2002 2.5 10 CFR 50, Appendix I. Dose Calculation Surveillance Requirement 6.2.1.2.1 requires that the cumulative dose contributions be determined in accordance with the ODCM at least once per 31 days. RFO 6.2.1.2 specifies that the dose to a MEMBER OF THE PUBLIC from radioactive material in liquid effluents released to the UNRESTRICTED AREA shall be limited to:

1.5 mrem/Calendar Quarter - Total Body and

5.0 mrem/Calendar Quarter - Any Organ.

The cumulative dose for the calendar year shall be limited to:

.-3 mrem - Total Body and

10 mrem - Any Organ.

The maximum exposed individual is distinguished as "maximum" with regard to usage factors which describe food intake, occupancy, breathing rate, and other factors of the area in the region of the plant site. It is assumed to be an adult whose exposure pathways include potable water and fish consumption. The choice of an adult as the maximum exposed individual is based on the highest fish and water consumption rates shown by that age group and the fact that most of the dose from the liquid effluent comes from these two pathways.

The dose contribution will be calculated for all radionuclides identified in the liquid effluent released to the unrestricted area, using the following equation:

m Dc = (Air- AteCOFI) (10) where:

D- = The cumulative dose commitment to the total body or organ, 'r, from liquid effluents for the total time period m , in mrem.

Mt, = The length of the fth time period over which Cl and F, are averaged for all liquid releases, in hours.

m = The number of releases for the time period under consideration.

C= The average concentration of radionuclide i in undiluted liquid effluent during time period At, from any liquid release, in ttCi/ml.

10

AMENDMENT NO. 35 MARCH 2002 A1 . = The site-related ingestion dose commitment factor to the total body or any organ Tr for each identified principle gamma and beta emitter listed in Table 2-2, in mrem/hr per yCi/ml.

F= The near field average dilution factor for Cl during any liquid waste release. This is defined as the ratio of the maximum undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestricted receiving waters times 500.

While the actual discharge structure exit flow is variable from 0 to 17.1 cfs (0 to 7690 gpm), a maximum flow value of 2.0 cfs will be used for dose calculation purposes in accordance with the NUREG-0133 requirement that the product of the average blowdown flow to the receiving water body, in cfs, and the applicable factor (500), is 1000 cfs or less.

(Fe Liquid Radioactive Waste Flow fw (11)

Discharge Structure Exit Flow x 500 ft x 500 The term Air, the ingestion dose factors for the total body and critical organs, are tabulated in Table 2-2. It embodies the dose factor, fish bioaccumulation factor, pathway usage factor, and the dilution factor for the plant diffuser pipe to the Richland potable water intake. The following equation was used to calculate the ingestion dose factors:

Ai? = K, (Uw/Dw + UF BFi) DFi (12) where:

Ai = The composite dose parameter for total body or critical organ of an adult for nuclide i (in mrem/hr per gtCi/ml).

K = A conversion factor:

I 1.14E+05 = (106 pCi/PCi) x (10s ml/liter)/8760 hr/yr.

UW 730 liter/yr - which is the annual water consumption by the maximum adult (Table E-4 of Regulatory Guide 1.109, Revision 1).

BFi = Bioaccumulation factor for radionuclide i in fish - (pCi/Kg per pCi/liter)

(Table A-1 of Regulatory Guide 1.109, Revision 1 and NUREG/CR-4013).

DFi = Adult ingestion dose conversion factor for nuclide i - Total body or critical organ, "r,in (mrem/pCi) (Table E-11 of Regulatory Guide 1.109, Revision 1 and NUREG/CR-4013).

11

AMENDMENT NO. 35 MARCH 2002 DW = Dilution factor from near field area (within one-quarter mile of the release point) to the Richland potable water intake - 100.

UF Adult fish consumption, 21 kg/yr (Table E-5 of Regulatory Guide 1.109, Revision 1).

The values of BFi and DFi are listed in Table 2-1.

The U.S. Nuclear Regulatory Comnission's computer program LADTAP II can be used for dose analysis for liquid radioactive effluents from Columbia Generating Station into surface waters. The analysis estimates the radiation dose to individuals, population groups, and biota from ingestion (aquatic foods, water, and terrestrial irrigated foods) and external exposure (shoreline, swimming, and boating) pathways. Dilution assumptions, calculations, and LADTAP II input parameters are provided in Radiological Health Calculation Log 92-2.

2.5.1 Projection of Doses The projected doses due to releases of radwaste liquid effluents will be calculated for each batch, using Equation (10) or LADTAP II. If the sum of the accumulated dose to date for the month and the projected dose for the remainder of the month exceeds the RFO 6.2.1.3 limits, then the liquid radwaste treatment system shall be used. This is to ensure compliance with RFO 6.2.1.3.

Dose projections are performed by taking the ratio of the time period analyzed to the time period projected as described in plant procedures.

2.6 Methods for Calculating Doses to Man From Liquid Effluent Pathways Dose models presented in NRC Regulatory Guide 1.109, Revision 1, as incorporated in the LADTAP II computer code, will be used for offsite dose calculation. The details of the computer code, and user instruction, are included in NUREG/CR-4013, "LADTAP II Technical Reference and User Guide."

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AMENDMENT NO. 35 MARCH 2002 2.6.1 Radiation Doses Radiation doses from potable water, aquatic food, shoreline deposit, and irrigated food pathways will be calculated by using the following equations:

Potable Water R.F 1 a QiD.ipjexp(-it (13)

Aquatic Foods R.pj ajF

= 1100 pMP 1 QiBipD,*'~jexp(-Xitp)(4 (14)

Shoreline Deposits 110000 Q.T.D.Pj [exp (-.itd) (1 - exp(-X.it)]

ipMPW (15)

Irrigated foods For all radionuclides except tritium:

Rapj j= - UUvega e p - th D i [r [1 - exp(-

21E d.di exp(-it)D XEite)] + f1B1j[1 - exp(-,it,)]

ap iL YvXEi R PXi

+ U animal .. FdDaD i Q~dexp(__-it) r[1 - exp(-IEite)]

+ fiBiv [1-exp(-1jt,] + CiAQAW] (16)

PXi For tritium:

= iveg C Dap + U animal DapjFA(CvQF + CAWQAw) (17) apj ap v ap 13

AMENDMENT NO. 35 MARCH 2002 where:

B, = The equilibrium bioaccumulation factor for nuclide i in pathway p, expressed as the ratio of the concentration in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/liter), in liters/kg.

B, = The concentration factor for uptake of radionuclide i from soil by edible parts of crops, in pCi/kg (wet weight) per pCi/kg dry soil.

CrL = The concentration of radionuclide i in water consumed by animals, in pCi/liter.

C = The concentration of radionuclide i in vegetation, in pCi/kg.

Da = The dose factor specific to a given age group a, radionuclide i, pathway p, and organ j, which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi, or from exposure to a given concentration of a radionuclide in sediment, expressed as a ratio of the dose rate (in mrem/hr) and the area radionuclide concentration (in pCi/mi).

di = The deposition rate of nuclide i in pCi/mi2 per hour.

F = The flow rate of the liquid effluent, variable from 0 to 2.0 cfs, for dose calculation purposes.

f, = The fraction of the year crops are irrigated, dimensionless.

FL = The stable element transfer coefficient that relates the daily intake rate by an animal to the concentration in an edible portion of animal product, in pCi/liter (milk) per pCi/day or pCi/kg (animal product) per pCi/day.

MP = The mixing ratio (reciprocal of the dilution factor) at the point of exposure (or the point of withdrawal of drinking water or point of harvest of aquatic food), dimensionless.

P The effective "surface density" for soil, in kg (dry soil)/m2 (Table E-15, Regulatory Guide 1.109, Revision 1).

QAw = The consumption rate of contaminated water by an animal, in liters/day.

QF = The consumption rate of contaminated feed or forage by an animal, in kg/day (wet weight).

14

AMENDMENT NO. 35 MARCH 2002 Q = The release rate of nuclide i in Ci/yr.

r = The fraction of deposited activity retained on crops, dimensionless (Table E-15, Regulatory Guide 1.109, Revision 1).

Rj = The total annual dose to organ j of individuals of age group a from all of the nuclides i in pathway p, in mrem/yr.

tb = The period of time for which sediment or soil is exposed to the contaminated water, in hours (Table E-15, Regulatory Guide 1.109, 1

Revision 1).

t = The time period that crops are exposed to contamination during the growing season, in hours (Table E-15, Regulatory Guide 1.109, Revision 1).

t = A holdup time that represents the time interval between harvest and consumption of the food, in hours (Table E-15, Regulatory Guide 1.109, Revision 1).

T, = The radioactive half life of nuclide i in days.

S= The average transit time required for nuclides to reach the point of exposure. For internal dose, tý is the total time elapsed between release of the nuclides and ingestion of food or water, in hours (Table E-15, Regulatory Guide 1.109, Revision 1).

UP = A usage factor that specifies the exposure time or intake rate for an individual of age group a associated with pathway p, in hr/yr, L/yr, or kg/yr (Table E-5, Regulatory Guide 1.109, Revision 1).

W = The shoreline width factor, dimensionless (Table A-2, Regulatory Guide 1.109, Revision 1).

Y = The agricultural productivity .(yield), in kg (wet weight)/m 2 (Table E-15, Regulatory Guide 1.109, Revision 1).

XE = The effective removal rate constant for radionuclide i from crops, in hr 1 ,

where X = X. + X, Xj is tht radioactive decay constant, and X., is the removal rate constant for physical loss by weathering (Regulatory Guide 1.109, Revision 1, Table B-15).

= The radioactive decay constant of nuclide i in hr'.

15

AMENDMENT NO. 35 MARCH 2002 1100 = The factor to convert from (Ci/yr)/(ft/sec) to pCi/liter.

110,000 = The factor to convert from (Ci/yr)/(ft3/sec) to pCi/liter and to account for the proportionality constant used in the sediment radioactivity model.

These equations yield the dose rates to various organs of individuals from the exposure pathways mentioned above.

2.6.2 Plant Parameters Columbia Generation Station is a river shoreline site with a variable effluent discharge flow rate 0 to 7690 gpm. The population center nearest the site is the city of Richland, where drinking water withdrawal takes place. The applicable dilution factor is 50,000, using average river flow. The time required for released liquids to reach Richland, approximately 12 miles downstream, is estimated at 4.0 hours0 days 0 hours 0 weeks 0 months . Richland is the "realistic case" location, and doses calculated for the Richland location are typically applicable to the population as a whole.

Individual and population doses based on Richland parameters are calculated for all exposure pathways.

Only the population downstream of the site is affected by the liquid effluents released. There is no significant commercial fish harvest in the 50-mile radius region around Columbia Generating Station. Sportfish harvest is estimated at 14,000 kg/year.

For irrigated foods exposure pathways, it can be assumed that production within the 50-mile radius region around Columbia Generating Station is sufficient to satisfy consumption requirements.

Other relevant parameters relating to the irrigated foods pathways are defined as follows:

Irrigation Rate Annual Yield Growing Period Food Type (liter/m2/mo) (kg/m 2) (Days)

Vegetation 150 5.0 70 Leafy Vegetation 200 1.5 70 Feed for Milk Cows 200 1.3 30 Feed for Beef Cattle 160 2.0 130 Source terms are measured based on sampled effluent.

16

AMENDMENT NO. 35 MARCH 2002 Table 2-3 summarizes the LADTAP II input parameters. Documentation and/or calculations of these parameters are discussed in detail in PPM 16.12.1, and Radiological Health Calculation Log 92-2.

2.7 Liquid Holdup Tanks 2.7.1 Maximum Allowable Liquid Radwaste Activity in Temporary Radwaste Hold-Up Tanks The use of temporary liquid radwaste hold-up tanks is planned for Columbia Generating Station.

Technical Specification 5.5.8.b states the quantity of radioactive material contained in any outside temporary tanks shall be limited to the limits calculated in the ODCM such that a complete release of the tank contents would not result in a concentration at the nearest offsite potable water supply that would exceed ten times the limits specified in 10 CFR Part 20.1001-20.2402 Appendix B, Table 2.

Equation (18) will be used to calculate the curie limit for a temporary radwaste hold-up tank.

The total tank activity will be limited to less than or equal to ten (* 10) curies, excluding tritium and dissolved or entrained gases.

The quantity of radioactive material in the hold-up tanks shall be determined to be within the limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

AT Kd S fi (18) i EC*I e'-t where:

AT = Total allowed activity in tank (curies).

Ai = Activity of radioisotope i (curies).

ECL, = Ten times maximum permissible concentration of radionuclide i (10 CFR 20.1001-20.2402, Appendix B, Table 2, Column 2).

3i

= Decay constant (years1) radioisotope i.

t = Transit time of ground water from Columbia Generating Station to WNP-1 well (FSAR Section 2.4) = 67 years.

Fraction of radioisotope Ai fi =

17

AMENDMENT NO. 35 MARCH 2002 i = Index for all radioisotopes in tank except tritium and noble gases.

K = Dispersion constant based on hydrological parameters, (2.4E+05 Ci per FuCi/cc.)

The total allowed activity (AT) is based on limiting WNP-1 well water to less than ten times ECL, if the entire liquid content of the tank spilled to ground and then migrated via ground water to the WNP-1 well. The WNP-1 well is the location of maximum concentration since it is the nearest source of ground water and conditions are such that no spill of liquid should reach surface water. The 55-60 foot depth of the water table and the low ambient moisture of the soil requires a rather large volume of spillage for the liquid to even reach the water table. However, allowed tank activity (AT) is conservatively based on all liquid radwaste in the tank instantaneously reaching the water table.

The hydrological analysis performed for the FSAR (Section 2.4) determined that the transit time through the ground water from Columbia Generating Station to the WNP-1 well is 67 years for Strontium and 660 years for Cesium. These two radionuclides are representative of the radionuclides found in liquid radwaste. Strontium is a moderate sorber and Cesium strongly sorbs to soil particles. This calculation conservatively treats all radionuclides as moderate sorbers with a transit time of 67 years.

The concentration of each radionuclide in the well (CW.) is simply the concentration in the tank (CT.) adjusted for radioactive decay during transit (e"d) and divided by the minimum concentration reduction factor (CRF .). Limiting well concentration to 10 X ECL yields:

CWi CTie -it ECLi CRF- ECLi (From Section 2 4 of FSAR)

CRFmm =Rmn2(4 n L)3/2 (ax ay ao)1/2 (20) 2V where:

L = Migration distance = 1 mile.

V = Volume of tank.

av, a, az = Dispersion constants.

18

AMENDMENT NO. 35 MARCH 2002 Combining Equations (19) and (20) yields:

1=CTi 2V e-x't (21)

(4 n L)"2 (a , ay az)"2 EC L*

Substituting Al for CT1 V and reorganizing terms yields:

(4 Tr L)3 r2 (a, ay a)" 2 Ai (22) 2 ECLie+Xlt Making the following substitutions:

Ai = fi AT 31 2 (a:x ay a z)1 1 2 (23)

Kd (4 7t L) x 10`5 Ci/tpCi = 2.4 x l Ci per Ci 2 cc yields:

Kd = A T fi+;i ECLie -'-it or AT f ECLie .it 2.7.2 Maximum Allowable Liquid Radwaste in Tanks That Are Not Surrounded by Liners, Dikes, or Walls Although permanent outside liquid radwaste tanks which are not surrounded by liners, dikes, or walls are not planned for Columbia Generating Station, Equation (18) will be used should such tanks become necessary in the future.

19

AMENDMENT NO. 36 JUNE 2002 2.8 Other Liquid Radiation Monitors Other Liquid Radiation Monitors are provided at Columbia Generating Station to monitor the status of normally non-radioactive systems. These monitors are:

Standby Service Water (SW)

Turbine Service Water (TSW)

I Calculational methodology is not provided in the ODCM for these monitors since their setpoints do not require extensive analysis. Their setpoints are established simply as a fraction of the selected 10 CFR 20 isotope concentration. The ODCM Appendix provides these setpoints in Sections 6.1.1 and B6. 1.1. These setpoints are implemented in Plant Procedures.

LDCN-02-007 20

AMENDMENT NO. 35 MARCH 2002 TABLE 2-1 FISH BIOACCUMULATION FACTORS (BF)(')

AND ADULT INGESTION DOSE CONVERSION FACTORS (DFR(2)

Dose Conversion Factor (DF)

Fish Bioaccumulation Total GI Nuclide Factor (BPS) Body Bone Thyroid Liver Tract (pCi/kg per (mRem per pCi Ingested) pCi/liter)

H-3 9.OE-01 6.OE-08 __(3) 6.0E-08 6.0E-08 6.0E-08 Na-24 1.0E+02 1.77E-06 1.7E-06 1.7E-06 1.7E-06 1.7E-06 P-32 1.0E1+05 7.5E-06 1.9E-04 -_(3) 1.2E-05 2.2E-05 Cr-51 2.OE+02 2.7E-09 _(3) 1.6E-09 __(3) 6.7E-07 Mn-54 4.0E+02 8.7E-07 __(3) -_(3) 4.6E-06 1.4E-05 Mn-56 4.0E1+02 2.01E-08 __(3) -_(3) 1.2E-07 3.7E-06 Fe-55 1.0E+02 4.4E-07 2.8E-06 -_(3) 1.9E-06 1.1E-06 Fe-59 1.OE+02 3.99E-06 4.3E-06 __(3) 1.OE-05 3.4E-05 Co-58 5.0E+01 1.7E-06 __(3) __(3) 7.51E-07 1.51E-05 Co-60 5.OE+01 4.7E-06 __(3) __(3) 2.1E-06 4.01E-05 Ni-65 1.OE+02 3. 1E-08 5.3E-07 __(3) 6.9E-08 1.7E-06 Cu-64 5.0E+01 3.9E-08 __(3) __(3) 8.3E-08 7.1E-06 Zn-65 2.OE+03 7.0E-06 4.8E-06 -_(3) 1.5E-05 9.7E-06 Zn-69m 2.OE+03 3.7E-08 1.7E-07 __(3) 4.1E-07 2.51E-05 As-76 1.0E+02 4.8E-06 __(3) __(3) -(3) 4.4E-05 Br-82 4.2E+02 2.3E-06 __(3) __(3) _(3) 2.6E-06 Br-83 4.2E+02 4.01E-08 __(3) __(3) _(3) 5.8E-08 Br-84 4.2E+02 5.2E-08 __(3) __(3) _(3) 4.1E-13 Rb-89 2.OE+03 2.88E-08 __(3) __(3) 4.03-08 2.33E-21 Sr-89 3.OE+01 8.8E-06 3.1E-04 __(3) -_(3) 4.99E-05 Sr-90 3.OE+01 1.8E-04 8.7E-03 __(3) -_(3) 2.2E-04 Sr-91 3.0E+01 2.3E-07 5.7E-06 __(3) __(3) 2.7E-05 Sr-92 3.OE+01 9.3E-08 2.2E-06 __(3) __(3) 4.3E-05 Y-90 2.5E+01 2.6E-10 9.7E-09 __(3) -_(3) 1.OE-04 Y-91m 2.5E+01 3.5E-12 9.1E-11 __(3) __(3) 2.7E-10 Y-91 2.5E+01 3.8E-09 1.4E-07 __(3) __(3) 7.8E-05 21

AMENDMENT NO. 35 MARCH 2002 TABLE 2-1 (continued)

FISH BIOACCUMULATION FACTORS (BF)(')

AND ADULT INGESTION DOSE CONVERSION FACTORS (DF;'(2)

Dose Conversion Factor (DF;)

Fish Bioaccumulation Total GI Nuclide Factor (BF,) Body Bone Thyroid Liver Tract (pCi/kg per (mRem per pCi Ingested) pCi/liter)

Y-92 2.5E+01 2.5E-11 8.5E-10 __(3) __(3) 1.5E-05 Y-93 2.5E+01 7.4E-11 2.7E-09 __(3) -_(3) 8.5E-05 Zr-95 3.3E+00 6.6E-09 3.1E-08 -(3) 9.8E-09 3.1E-05 Nb-95 3.OE+04 1.9E-09 6.2E-09 -(3) 3.5E-09 2.1E-05 Zr-97 3.3E+00 1.6E-10 1.7E-09 -_(3) 3.4E-10 1.1E-04 Nb-97 3.OE+04 4.8E-12 5.2E-11 -(3) 1.3E-11 4.9E-08 Mo-99 1.OE+01 8.2E-07 5-(3) -_(3) 4.3E-06 1.OE-05 Tc-99m 1.5E+01 8.9E-09 2.5E-10 __(3) 7.OE-10 4.1E-07 Tc-101 1.5E+01 3.6E-09 2.5E-10 __(3) 3.7E-10 1.1E-21 Ru-103 1.OE+01 8.OE-08 1.9E-07 -_(3) -(3) 2.2E-05 Ru-105 1.OE+01 6.1E-09 1.5E-08 -_(3) -_(3) 9.4E-06 Rh-105 1.OE+01 5.8E-08 1.2E-07 -_(3) 8.9E-08 1.4E-05 Ru-106 1.OE+01 3.5E-07 2.8E-06 __(3) __(3) 1.SE-04 Ag-il0m 2.3E+00 8.8E-08 1.6E-07 __(3) 1.5E-07 6.OE-05 Sb-124 1.OE+00 1.1E-06 2.8E-06 6.8E-09 5.3E-08 8.OE-05 Sb-125 1.0E+00 4.3E-07 1.8E-06 1.8E-09 2.OE-08 2.OE-05 Sb-126 1.OE+00 4.2E-07 1.2E-06 7.0E-09 2.3E-08 9.4E-05 Sb-127 1.OE+00 9.9E-08 2.6E-07 3.1E-09 5.7E-09 5.9E-05 Te-127 4.OE+02 2.4E-08 1.1E-07 8.2E-08 4.OE-08 8.7E-06 Te-129m 4.OE+02 1.8E-06 1.2E-05 4.OE-06 4.3E-06 5.8E-05 Te-129 4.OE+02 7.7E-09 3.1E-08 2.4E-08 1.2E-08 2.4E-08 Te-131m 4.OE+02 7.1E-07 1.7E-06 1.3E-06 8.5E-07 8.4E-05 Te-131 4.OE+02 6.2E-09 2.OE-08 1.6E-08 8.2E-09 2.8E-09 Te-132 4.OE+02 1.5E-06 2.5E-06 1.8E-06 1.6E-06 7.7E-05 1-131 1.5E+01 3.4E-06 4.2E-06 2.OE-03 6.OE-06 1.6E-06 1-132 1.5E+01 1.9E-07 2.OE-07 1.9E-05 5.4E-07 1.OE-07 1-133 1.5E+01 7.5E-07 1.4E-06 3.6E-04 2.5E-06 2.2E-06 1-134 1.5E+01 1.0E-07 1.1E-07 5.OE-06 2.9E-07 2.5E-10 22

AMENDMENT NO. 35 MARCH 2002 TABLE 2-1 (continued)

FISH BIOACCUMULATION FACTORS (BFj)0)

AND ADULT INGESTION DOSE CONVERSION FACTORS (DF;)(2)

Dose Conversion Factor (DF;)

Fish Bioaccumulation Total GI Nuclide Factor (BF,) Body Bone Thyroid Liver Tract (pCi/kg per (mRem per pCi Ingested) pCi/liter) 1-135 1.5E+01 4.3E-07 4.4E-07 7.7E-05 1.2E-06 1.3E-06 Cs-134 2.OE+03 1.2E-04 6.2E-05 __(3) 1.5E-04 2.6E-06 Cs-136 2.OE+03 1.9E-05 6.5E-06 ._(3) 2.6E-05 2.9E-06 Cs-137 2.OE+03 7.1E-05 8.0E-05 __(3) 1.1E-04 2.1E-06 Cs-138 2.0E+03 5.4E-08 5.5E-08 __(3) 1.1E-07 4.7E-13 Ba-139 4.0E+00 2.8E-09 9.7E-08 -(3) 6.9E-11 1.7E-07 Ba-140 4.0E+00 1.3E-06 2.0E-05 -(3) 2.6E-08 4.2E-05 La-140 2.5E+01 3.3E-10 2.5E-09 __(3) 1.3E-09 9.3E-05 La-141 2.5E+01 1.6E-1 1 3.2E-10 __(3) 9.9E-11 1.2E-05 La-142 2.5E+01 1.5E-11 1.3E-10 __(3) 5.8E-11 4.3E-07 Ce-141 1.0E+00 7.2E-10 9.4E-09 -(3) 6.3E-09 2.4E-05 Ce-143 1.OE+00 1.4E-10 1.7E-09 __(3) 1.2E-06 4.6E-05 Ce-144 1.0E+00 2.6E-08 4.9E-07 -_(3) 2.0E-07 1.7E-04 Pr-143 2.5E+01 4.6E-10 9.2E-09 __(3) 3.7E-09 4.OE-05 Nd-147 2.5E+01 4.4E-10 6.2E-09 -(3) 7.3E-09 3.5E-05 Hf-179m 3.3E+00 4.8E-06 __(3) __(3) ._.(3) 4.1E-05 Hf-181 3.3E+00 4.3E-06 -(3) __(3) __(3) 4.1E-05 W-185 1.2E+03 1.4E-08 4.1E-07 __(3) 1.4E-07 1.6E-05 W-187 1.2E+03 3.0E-08 1.0E-07 __(3) 8.6E-08 2.8E-05 Np-239 1.0E+01 6.5E-1 1 1.2E-09 __(3) 1.2E-10 2.4E-05

()NRC NUREG/CR-4013.

(2)Reg. Guide 1.109.

()No data listed in Reg. Guide 1.109.

(Use total body dose conversion factor as an approximation.)

23

AMENDMENT NO. 35 MARCH 2002 TABLE 2-2 INGESTION DOSE FACTORS (A;) FOR TOTAL BODY AND CRITICAL ORGAN (in mrem/hr per uCi/ml)

Liquid Effluent Total GI Nuclide Body Bone Thyroid Liver Tract H-3 1.8E-01 ** 1.8E-01 1.8E-01 1.8E-01 Na-24 4.1E+02 4.1E+02 4.1E+02 4.1E+02 4.1E+02 P-32 1.8E+06 4.6E+07 ** 2.9E+06 5.3E+06 Cr-51 1.3E+00 ** 7.7E-01 ** 3.2E+02 Mn-54 8.3E+02 ** ** 4.4E+03 1.3E+04 Mn-56 1.9E+01 ** ** 1.6E+02 3.6E+03 Fe-55 1.1E+02 6.7E+02 ** 4.6E+02 2.6E+02 Fe-59 9.4E+02 1.OE+03 ** 2.4E+03 8.2E+03 Co-58 2.1E+02 ** ** 9.OE+01 1.8E+03 Co-60 5.7E+02 ** ** 2.5E+02 4.8E+03 Ni-65 7.5E+00 1.3E+02 ** 1.7E+01 4.1E+02 Cu-64 4.7E+00 ** ** 1.OE+01 8.6E+02 Zn-65 3.4E+04 2.3E+04 ** 7.2E+04 4.7E+04 Zn-69m 1.8E+02 8.1E+02 ** 2.OE+03 1.2E+05 As-76 1.2E+03 ** ** ** 1.1E+04 Br-82 2.3E+03 ** ** ** 2.6E+03 Br-83 4.OE+01 ** ** ** 5.8E+01 Br-84 5.2E+01 ** ** ** 4.1E-04 Rb-89 1.3E+02 ** ** 1.9E+02 1.1E-11 Sr-89 6.4E+02 2.3E+04 ** ** 3.6E+03 Sr-90 1.3E+04 6.3E+05 ** ** 1.6E+04 Sr-91 1.7E+01 4.1E+02 ** ** 2.OE+03 Sr-92 6.8E+00 1.6E+02 ** ** 3.1E+03 Y-90 1.6E-02 5.9E-01 ** ** 6.1E+03 Y-91m 2.1E-04 5.5E-03 ** ** 1.6E-02 Y-91 2.3E-01 8.5E+00 ** ** 4.7E+03 Y-92 1.5E-03 5.2E-02 ** ** 9.1E+02 Y-93 4.5E-03 1.6E-01 ** ** 5.2E+03 24

AMENDMENT NO. 35 MARCH 2002 TABLE 2-2 (continued)

INGESTION DOSE FACTORS (A;) FOR TOTAL BODY AND CRITICAL ORGAN (in mrem/hr per 14Ci/ml)

Liquid Effluent Total GI Nuclide Body Bone Thyroid Liver Tract Zr-95 5.3E-02 2.5E-01 ** 7.9E-02 2.5E+02 Nb-95 1.4E+02 4.5E+02 ** 2.5E+02 1.5E+06 Zr-97 1.3E-03 1.4E-02 ** 2.7E-03 8.8E+02 Nb-97 3.5E-01 3.7E+00 ** 9.3E-01 3.5E+03 Mo-99 2.OE+01 ** ** 1.1E+02 2.5E+02 Tc-99m 3.3E-01 9.2E-03 ** 2.6E-02 1.5E+01 TC-101 1.3E-01 9.2E-03 ** 1.4E-02 4.OE-14 Ru-103 2.OE+00 4.7E+00 ** ** 5.5E+02 Ru-105 1.5E-01 3.7E-01 ** ** 2.3E+02 Rh-105 1.4E+00 3.OE+00 ** 2.2E+00 3.5E+02 Ru-106 8.7E+00 6.9E+01 ** ** 4.5E+03 Ag-ll0m 5.6E-01 1.OE-00 ** 9.5E-01 3.8E+02 Sb-124 3.6E+00 9.OE+00 2.2E-02 1.7E-01 2.6E+02 Sb-125 1.4E+00 5.8E+00 5.8E-03 6.5E-02 6.5E+01 Sb-126 1.4E+00 3.9E+00 2.3E-02 7.4E-02 3.OE+02 Sb-127 3.2E-01 8.4E-01 1.0E-02 1.8E-02 1.9E+02 Te-127 2.3E+01 1.1E+02 7.9E+01 3.8E+01 8.3E+03 Te-129m 1.7E+03 1.2E+04 3.8E+03 4.1E+03 5.6E+04 Te-129 7.4E+00 3.OE+01 2.3E+01 1.2E+01 2.3E+01 Te-131m 6.8E+02 1.6E+03 1.3E+03 8.2E+02 8.1E+04 Te-131 5.9E+00 1.9E+01 1.5E+01 7.9E+00 2.7E+00 Te-132 1.4E+03 2.4E+03 1.7E+03 1.5E+03 7.4E-04 1-131 1.3E+02 1.5E+02 7.4E+04 2.2E+02 5.9E+01 1-132 7.OE+00 7.4E+00 7.OE+02 2.OE+01 3.7E+00 1-133 2.8E+01 5.1E+01 1.3E+04 9.2E+01 8.1E+01 1-134 3.7E+00 4.OE+00 1.8E+02 1.1E+01 9.2E-03 1-135 1.6E+01 1.6E+01 2.8E+03 4.4E+01 4.8E+01 Cs-134 5.8E+05 3.OE+05 ** 7.2E+05 1.3E+04 Cs-136 9.1E+04 3.1E+04 ** 1.3E+05 1.4E+04 Cs-137 3.4E+05 3.8E+05 ** 5.3E+05 1.OE+04 Cs-138 2.6E+02 2.6E+02 ** 5.3E+02 2.3E-03 25

AMENDMENT NO. 35 MARCH 2002 TABLE 2-2 (continued)

INGESTION DOSE FACTORS (Ai) FOR TOTAL BODY AND CRITICAL ORGAN (in mrem/hr per AiCi/ml)

Liquid Effluent Total GI Nuclide Body Bone Thyroid Liver Tract Ba-139 2.9E-02 1.0E-00 ** 7.2E-04 1.8E+00 Ba-140 1.4E+01 2.1E+02 ** 2.7E-01 4.4E+02 La-140 2.OE-02 1.5E-01 ** 7.9E-02 5.6E1+03 La-141 9.7E-04 1.9E-02 ** 6.OE-03 7.3E+02 La-142 9.1E-04 7.9E-03 ** 3.5E-03 2.6E+01 Ce-141 2.3E-03 3.OE-02 ** 2.OE-02 7.7E+01 Ce-143 4.5E-04 5.5E-03 ** 3.9E+00 1.5E+02 Ce-144 8.4E-02 1.6E+00 ** 6.5E-01 5.5E+02 Pr-143 2.8E-02 5.6E-01 ** 2.3E-01 2.4E+03 Nd-147 2.7E-02 3.8E-01 ** 4.4E-01 2.1E+03 Hf-179m 4.2E+01 ** 3.6E+02 Hf-181 3.8E1+01 ** 3.6E1+02 W-185 4.OE+01 1.2E+03 ** 4.OE+02 4.6E+04 W-187 8.6E+01 2.9E+02 ** 2.5E+02 8.1E+04 Np-239 1.6E-03 3.OE-02 ** 3.OE-03 6.OE+02

- No Ingestion Dose Factor (DF.) is listed in NUREG/CR-4013. (Total body dose factor value will be used as an approximation.)

26

AMENDMENT NO. 35 MARCH 2002 TABLE 2-3 INPUT PARAMETERS USED TO CALCULATE MAXIMUM INDIVIDUAL DOSE FROM LIQUID EFFLUENTS Drinlding Water River Dilution: 50,000 River Transit Time: 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Usage Factors: Adult = 730 1/yr Teenager = 510 1/yr Child = 510 1/yr Infant = 330 1/yr Boating and Aquatic Food River Dilution: 500 Transit Time: 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Usage Factors: (Aquatic Food) Adult = 21 kg/yr Teenager = 16 kg/yr Child = 6.9 kg/yr Infant = 0 (Boating) Adult = 100 hr/yr Teenager = 100 hr/yr Child = 85 hr/yr Infant = 0 Recreation River Dilution: 20,000 Shoreline Width Factor: 0.2 Usage Factors: Shoreline Activities: Adult = 90 hr/yr Teenager = 500 hr/yr Child = 105 hr/yr Infant = 0 Swimming: Adult = 18 hr/yr Teenager = 100 hr/yr Child = 21 hr/yr Irrigated Foodstuffs River Dilution: 50,000 River Transit Time: 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Leafy Vegetables Milk Meat Vegetables Food Delivery Time: 14 days 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 20 days 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Usage Factors:

Adult 520 kg/yr 310 1/yr 110 kg/yr 64 kg/yr Teenager 630 kg/yr 400 1/yr 65 kg/yr 42 kg/yr Child 520 kg/yr 330 1/yr 41 kg/yr 26 kg/yr Monthly Irrigation Rate: 180 l/mr 200 1/m2 160 1/m2 200 1/m2 Annual Yield: 5.0 kg/r 2 1.3 1/m2 2.0 kg/m2 1.5 kg/m2 Annual Growing Period: 70 days 20 days 130 days 70 days Annual 50-Mile Production: 3.5E+09 kg 2.8E+08 L 2.3E+07 kg 1.9E+06 kg 27

AMENDMENT NO. 35 MARCH 2002 COLUMBIA RIVER SIMPLIFIED BLOCK DIAGRAM OF LIQUID WASTE SYSTEM Figure 2-1 28

AMENDMENT NO. 35 MARCH 2002 3.0 GASEOUS EFFLUENT DOSE CALCULATIONS Gaseous effluent dose calculations are discussed in this section of the ODCM. Calculations of gaseous effluent dose rate are made to show compliance with the limits of 10 CFR 20. The methodology for calculating dose rate due to noble gases, radionuclides, and particulates are discussed. Methods used to determine the setpoints for the gaseous effluent monitors are also described. Finally, the methods used to calculate off-site radiation dose due to gaseous effluents in order to show compliance with 10 CFR 50, Appendix I are outlined.

3.1 Introduction Gaseous effluents are released on a continuous basis; in addition, batch releases also occur when containment and mechanical vacuum pump purges are performed and when the off-gas treatment system operates in the charcoal bypass mode.

Figure 3-1 delineates the Site boundary, which for dose calculation purposes, is considered circular with a radius of 1.2 miles. There are several low occupancy unrestricted locations within the site boundary. These locations, with the exception of the visitor center, are not continuously controlled by Energy Northwest. The locations are:

1. Wye burial site (burial ground 618-11) - controlled by DOE.

2. DOE railroad - approximately 3 miles of rail line pass through the site.

3. BPA Ashe Substation - occupied 2080 hour0.0241 days 0.578 hours 0.00344 weeks 7.9144e-4 months s/year. These people are not normally controlled by Energy Northwest but are involved in activities directly in support of Columbia Generating Station.

4. Energy Northwest Visitor Center - assumed occupied 8 hrs/yr by non-Energy Northwest individuals.

5. WNP occupied 2080 hrs/yr. This location is controlled by Energy Northwest.

However, activities are not in direct support of Columbia Generating Station.

6. WNP occupied 2080 hrs/yr. This location is controlled by Energy Northwest.

However, activities are not in direct support of Columbia Generating Station.

All other locations shown in Figure 3-1 support Columbia Generating Station activities and are controlled by Energy Northwest. Figure 3-2 provides a simplified block diagram of the gaseous radwaste system for the reactor, turbine and radwaste buildings. Figure 3-3 provides a simplified block diagram for the off-gas treatment system.

29

AMENDMENT NO. 35 MARCH 2002 Air doses and doses to individuals at these locations were calculated based on the NRC GALE code design base mixture, location specific estimated occupancy, and X/Qs from XOQDOQ.

(NOTE: Desert Sigmas were used in calculating X/Q and D/Q values, and are listed in Table 3-10 and 3-11). These doses are listed in Tables 3-16 and 3-17 along with the doses to the maximum exposed individual.

The most exposed member of the public beyond the site boundary is considered to be residing in Taylor Flats (4.2 miles ESE of Columbia Generating Station). This is the residential area with the highest X/Q and D/Q values.

The Auxiliary Boiler supplies heating steam to the Reactor, Radwaste, Turbine and Service buildings when Seal Steam Evaporator B is not in operation. The Auxiliary Boiler and associated heating steam system vents to the atmosphere and provides a possible unmonitored source of radioactive effluent when in operation. Samples have shown 2.0 E+06 picocuries per liter of tritium activity to be present within the Auxiliary Boiler system. Using NRC Regulatory Guide 1.109 methodology with FSAR Low Population Zone (LPZ) X/Q values and assuming one gallon per minute (1 gpm) makeup flowrate for 180 days plus a one time complete boil-off of the total water inventory, the dose contribution from tritium would be less than one tenth of a millirem per year (<0.1 mrem/yr). Figure 3-4 provides a simplified diagram for the Auxiliary Boiler.

Tritium in the form of tritiated water vapor is released to the environment through monitored/sampled effluent pathways. Under certain meteorological conditions, the tritiated water vapor may condense onto surfaces such as rooftops and exterior walls. Subsequently, this condensed, recaptured tritiated water may be carried with precipitation into the Storm Drain Pond (SDP) which serves as a collection point for rainfall on plant roofs. Influent to the SDP is continuously sampled and periodically analyzed for tritium content.

3.2 Gaseous Effluent Radiation Monitoring System 3.2.1 Reactor Building Elevated Discharge Radiation Monitor The Reactor Building is continuously monitored for gaseous radioactivity prior to discharge to the environment. The effluent' is supplied from: the gland seal exhauster, mechanical vacuum pumps, treated off gas, standby gas treatment, and exhaust air from the entire reactor building's ventilation. Further information on this monitoring system can be found in FSAR Section 11.5.2.2.1.5 and the Radioactive Gaseous Effluent Monitoring Instrumentation Bases, ODCM Appendix, B6.1.2.

30

AMENDMENT NO. 35 MARCH 2002 3.2.2 Radwaste Building Ventilation Exhaust Monitor The radwaste building ventilation exhaust monitoring system monitors the radioactivity in the Radwaste Building exhaust air prior to discharge. Radioactivity can originate from: radwaste tank vents, laboratory hoods, and various cubicles housing liquid process treatment equipment and systems.

Further information on this monitoring system can be found in FSAR Section 11.5.2.2.1.7 and the Radioactive Gaseous Effluent Monitoring Instrumentation Bases, ODCM Appendix, B6.1.2.

3.2.3 Turbine Building Ventilation Exhaust Monitor This monitoring system detects fission and the activation products from the turbine building air which may be present due to leaks from the turbine and other primary components in the building. Further information on this instrumentation can be found in FSAR Section 11.5.2.2.1.6 and the ODCM Appendix, Section B6.1.2.

3.3 Release Rate Limits Limits for release of gaseous effluents from the site to areas at and beyond the site boundary are stated in RFO 6.2.2.1.

3.3.1 Noble Gases In order to comply with RFO 6.2.2.1, the following equations must hold:

Whole body:

Ki [(X/Q)m Qim +' (X/oQg Qig)] *500 mrem/yr (1)

Skin:

] [(Li + 1.1M.) ((X/Q)m 0im + (X/Q), ig)] g 3000 mrem/yr (2) 31

AMENDMENT NO. 35 MARCH 2002 3.3.2 Radioiodines and Particulates Part "b" of RFO 6.2.2.1 requires that the release rate limit for all radioiodines and radioactive materials in particulate form and radionuclides other than noble gases must meet the following relationship:

Any organ:

SPi [WM 0ir + Wg Qig] *:1500 mrem/yr (3)

The terms used in Equations (1) through (3) are defined as follows:

K* = The total body dose factor due to gamma emissions for each identified noble gas radionuclide i (mrem/yr per ItCi/m 3).

L, = The skin dose factor due to beta emissions for each identified noble gas radionuclide i (mrem/yr per JLCi/m 3).

Mi The air dose factor due to gamma emissions for each identified noble gas radionuclide in mrad/yr per tiCi/m 3 (unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose).

Pj The dose parameter for all radionuclides other than noble gases for the inhalation pathway, (mrem/yr per ICi/m3) and for food and ground plane pathways, m2(mrem/yr per tCi/sec). The dose factors are based on the critical individual organ and the most restrictive age group.

m

= The release rate of radionuclide i in gaseous effluent from mixed mode release (tCi/sec). The main plant release point is a partially elevated mixed mode release.

ig = The release rate of radionuclide i in gaseous effluent from all ground level releases (liCi/sec).

(X/Q)m= The highest calculated annual average relative concentration for any area at and beyond the site boundary due to a partially elevated mixed mode releases from the main plant vent release point (sec/in 3).

(X/Q)g The highest calculated ground level annual average relative concentration for any area at and beyond the site boundary due to Turbine and Radwaste Building releases (sec/m 3).

32

AMENDMENT NO. 35 MARCH 2002 Wg The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location due to all ground level releases.

WI = (sec/rn 3). For the inhalation pathway. The location is at and beyond the site boundary in the sector of maximum concentration.

Wg rn"2 . For ground plane pathways. The location is at and beyond the site boundary in the sector of maximum concentration.

WM The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location due to partially elevated releases:

Wm sec/m 3 . For inhalation pathway. The location is at and beyond the site boundary in the sector of maximum concentration.

WM* = m2 . For ground plane pathways. The location is at and beyond the site boundary in the sector of maximum concentration.

The factors, L, and M,, relate the radionuclide airborne concentrations to various dose rates assuming a semi-infinite cloud. These factors are listed in Table B-1 of Regulatory Guide 1.109, Revision 1, and in Table 3-1 of this manual.

The values used in the equations for the implementation of RFO 6.2.2.1 are based upon the maximum long-term annual average X/Q at and beyond the site boundary. Table 3-2 provides typical receptor locations and pathways for use in dose determinations. Table 3-3 provides these typical locations with long term X/Q and D/Q values which may be used if current annual averages are not available.

The X/Q and D/Q values listed in Tables 3-10 and.3-11 reflecting correctly acquired meteorological data, January 1, 1984 - January 1, 1990 may be utilized in GASPAR II computer runs.

33

AMENDMENT NO. 35 MARCH 2002 3.3.2.1 Dose Parameter for Radionuclide i (P.)

The dose parameters used in Equation (3) are based on:

1. Inhalation and ground plane. (Note: Food pathway is not applicable since no food is grown at or near the restricted area boundary.)

2. The annual average continuous release meteorology at the site boundary.

3. The critical organ for each radionuclide (thyroid for radioiodine).

4. The most restrictive age group.

The following equation will be used to calculate Pi (Inhalation).

P (Inhalation) = KA(BR) DFAi (mrem/yr per pCi/m 3 ) (4) where:

KA = A conversion constant, 106 pCi/jtCi.

BR = The breathing rate of the child age group, 3700 m3/yr.

DFA = The critical organ inhalation dose factor for the child age group for the ith radionuclide in mrem/pCi. The total body is considered as an organ in the selection of DFA1 .

The inhalation dose factor for DFA, for the child age group is listed in Table E-9 of Regulatory Guide 1.109, Revision 1, and Table 3-4 of this manual. Resolving the units yields:

Pi (Inhalation) = (3.7E + 09) (DFAi) (mrem/yr per pCi/m 3) (5)

I The Pi (Inhalation) values for the child age group are tabulated in Table 3-4 of this manual.

34

AMENDMENT NO. 35 MARCH 2002 3.4 Calculation of Gaseous Effluent Monitor Alarm Setpoints 3.4.1 Introduction The following procedure is used to ensure that the dose rate at or beyond the site boundary due to noble gases in the gaseous effluent do not exceed 500 mrem/yr to the whole body or 3000 mrem/yr to the skin. The initial setpoints determination was calculated using a conservative radionuclide mix obtained from the GALE code. When sufficient measurable process fission gases are in the effluent, then the actual radionuclide mix will -beused to calculate the alarm setpoint.

3.4.2 Setpoint Determination for all Gaseous Release Paths The setpoints for gaseous effluent are based on instantaneous noble gas dose rates. The three release points will be partitioned such that their sum does not exceed 100 percent of the limit.

The setpoints are set at 40 percent for the Reactor Building, 40 percent for the Turbine Building and 20 percent for the Radwaste Building. These percentages could vary at the plant discretion, should the operational conditions warrant such change. However, the combined releases due to variations in the setpoints will not result in doses which exceed the limit stated in RFO. Both skin dose and whole body setpoints will be calculated and the lower limit will be used. The mechanical vacuum pump discharge radiation monitor setpoint is also established using the methodology of this section.

3.4.2.1 Setpoints Calculations Based on Whole Body Dose Limits The fraction (it) of the total gaseous radioactivity in each gaseous effluent release path j for each noble gas radionuclide i will be determined by using the following equation:

-M.j 7it =- MrTj (dimensionless) (6) where:

M The measured individual concentration of radionuclide i in the gaseous effluent release path j (tLCi/cc).

MTj = The measured total concentration of all noble gases identified in the gaseous effluent release path j (JlCi/cc).

35

AMENDMENT NO. 35 MARCH 2002 Based on RFO 6.2.2.1, the maximum acceptable release rate of all noble gases in the gaseous effluent release path j is calculated by using the following equation:

Fj 500 QTj = (PiCi/sec)

X/Qj (Ki)(nij) i=1 U where:

Q1 = The maximum acceptable release rate ([tCi/sec) of all noble gases in the gaseous effluent release path j (ILCi/cc).

Fj = Fraction of total dose allocated to release path j.

500 = Whole body dose rate limit of 500 mrem/yr as specified in RFO 6.2.2.1.a.

X/Qj = Maximum normalized diffusion coefficient of effluent release path j at and beyond the site boundary (sec/m 3). Turbine Building and Radwaste Building values are based on average annual ground level values. Main plant vent release values are for mixed mode and may be either short term or average annual value dependent upon type of release.

K = The total whole body dose factor due to gamma emission from noble gas nuclide i (mrcmlyr per ACi/m 3) (as listed in Table B-1 of Regulatory Guide 1.109, Revision 1).

7rij = As defined in Equation (6).

m = Total number of radionuclides in the gaseous effluent.

j = Different release pathways.

The total maximum acceptable concentration (C(j) of noble gas radionuclides in the gaseous effluent release path j (tPCi/cc) will be calculated by using the following equation:

CTj = QTj (1iCilcc) (7a)

R*

36

AMENDMENT NO. 35 MARCH 2002 where:

C = The total allowed concentration of all noble gas radionuclides in the gaseous effluent release path j (pCi/cc).

Qrj = The maximum acceptable release rate (/iCi/sec) of all noble gases in the gaseous effluent release path j.

R = The effluent release rate (cc/sec) at the point of release.

To determine the maximum acceptable concentration (Cij) of noble gas radionuclide i in the gaseous effluent for each individual noble gas in the gaseous effluent (juCi/cc), the following equation will be used:

where:

C= tiCTj (pzCi/cc) (7b) nmj and Cý, are as defined in Equations (6) and (7) respectively, the gaseous effluent monitor alarm setpoint will then be calculated as follows:

m CR. = E Ci.E .(cpm) (7c) i=1 where:

CRl = Count rate above background (cpm) for gaseous release path j.

CIJ = The maximum acceptable concentration of noble gas nuclide i in the gaseous effluent release path j (puCi/cc).

S,j = Detection efficiency of the gaseous effluent monitor j for noble gas i (cpm/pCi/cc).

37

AMENDMENT NO. 35 MARCH 2002 3.4.2.2 Setpoints Calculations Based on Skin Dose Limits The method for calculating the setpoints to ensure compliance with the skin dose limits specified in RFO 6.2.2.1.a is similar to the one described for whole body dose limits (Section 3.6.2.1 of this manual), except Equation (7d) will be used instead of Equation (7) for determining maximum acceptable release rate (Qr).

F. 3000 QTJ = .(ICi/sec)

(7d)

(X/Qj) E (Li + 1.1Mi)(7r1 j) i=1 where:

QTj = The maximum acceptable release rate of all noble gases in the gaseous effluent release path j in gCi/sec.

X/Qj = The maximum annual normalized diffusion coefficient for release path j at and beyond the site boundary (sec/m 3).

Fj = Fraction Of i

total allowed dose.

L = The skin dose factor due to beta emission for each identified noble gas radionuclide i in mrem/yr per jtCi/m 3 (L, values are listed in Table 3-1).

M = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per tCi/m3 (Mi values are listed in Table 3-1).

1.1 = A conversion factor to convert dose in mrad to dose equivalent in mrem.

3000 = Skin dose rate limit of 3000 mrem/yr as specified in RFO 6.2.2.1.

3.5 10 CFR 50 Dose Calculation The U.S. Nuclear Regulatory Commission's computer program GASPAR II can be used to perform environmental dose analyses for releases of radioactive effluents from Columbia Generating Station into the atmosphere. The analyses estimates radiation dose to individuals and population groups from inhalation, ingestion (terrestrial foods), and external exposure (ground and plume) pathways. The calculated doses provide information for determining compliance with Appendix I of 10 CFR Part 50.

38

AMENDMENT NO. 35 MARCH 2002 Both the ODCM equations and the NRC GASPAR II computer program for estimating the highest dose to any organ for a particular age group provides conservatism in calculating maximum organ doses. This conservatism is recognized and is intentional.

Determination of doses due to 'short-term releases can use the annual average relative concentration (long-term) if it can be demonstrated that past short-term releases were sufficiently random in both time of day and duration (e.g., the short-term release periods were not dependent solely on atmospheric conditions or time of day) to be represented by the annual average dispersion conditions.

The requirements pertaining to 10 CFR 50 dose limits are specified in RFO 6.2.2.2 and 6.2.2.3.

3.5.1 Noble Gases (RFO 6.2.2.2)

RFO 6.2.2.2 deals with the air dose from noble gases and requires that the air dose at and beyond the site boundary due to noble gases released in gaseous effluents shall be limited to the following:

a. During any calendar quarter, for gamma radiation:

3.17 x 10-8 E Mj0-7-,Qi + (X/l),% + --Q).Qi* + (X/q)qlq] :55 mrad (8)

During any calendar quarter, for beta radiation:

3.17 x 10"8 E Ni [(-'0,Qjg + (X/q)gqg + Q--'.Q.Q + (X/q)mqm] <10 mrad (9) i

b. During any calendar year, for gamma radiation:

3.17 x 10-z X Mi [f--(X$Qji + (X/q)gqg + (X/Q)mQ.m + (X/q)mqi,] *10 mrad (10) i During any calendar year, for beta radiation:

3.17 x 10- E N1 [00--Q19 + (X/q)qqg + (X/O)mQ,, + (X/q)mq=] ,20 mrad (11) where:

Mi The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per jtCi/m3 (M, values are listed in Table 3-1).

Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide, in miad/yr per gCi/m 3 (Ni values are listed in Table 3-1).

39

AMENDMENT NO. 35 MARCH 2002 (X/Q)g = For ground level release points. The highest calculated annual average relative concentration for area at and beyond the site area boundary for long-term releases (greater than 500 hr/yr). (sec/m 3)

(X/q)g = For ground level release points. The relative concentration for areas at and beyond the site area boundary for short-term releases (equal to or less than 500 hr/yr). (sec/m 3)

(X/Q)m= For partially elevated release points. The highest calculated annual average relative concentration for areas at and beyond the site boundary for long-term releases (greater than 500 hr/yr). (sec/rn 3)

(X/q)m = For partially elevated release points. The relative concentration for areas at and beyond the site boundary for short-term releases (equal to or less than 500 hr/yr). (sec/m 3) q* = The average release of noble gas radionuclides in gaseous effluents, i, for short-term releases (equal to or less than 500 hr/yr) from the main plant release point, in gCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.

q = The average release of noble gas radionuclides in gaseous effluents, i, for short-term releases (equal to or less than 500 hr/yr) from Radwaste and Turbine Building, in pCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.

Q = The average release of noble gas radionuclides in gaseous releases, i, for long-term releases (greater than 500 hr/yr) from the main plant release point, in pCi. Release shall be cumulative over the calendar quarter or year, as appropriate.

Qg = The average release of noble gas radionuclides in gaseous effluents, i, for long-term releases (greater than 500 hr/yr) from Radwaste and Turbine Building, in uCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.

3.17 x 10.8 = The inverse of the number of seconds in a year (yr/sec).

40

AMENDMENT NO. 35 MARCH 2002 3.5.2 Radioiodines, Tritium and Particulates (RFO 6.2.2.3)

RFO 6.2.2.3 deals with radioiodines, tritium, and radioactive materials in particulate form, and requires that the dose to an individual from radioiodines, tritium and radioactive materials in particulate form with half-lives greater than eight days in gaseous effluents released to unrestricted areas shall be limited to the following:

a. During any calendar quarter:

3.17 x 10-S E R, [WmQ. + wmq* + WgQ. + wsqi] :7.5 mrem (12)

b. During any calendar year:

3.17 x 10- E R, [WmQm + wmqi. + WgQg + wqg ] ,:15 mrem (13) where:

Qun, Qig = The releases of radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases in gaseous effluents, i, for long-term releases greater than 500 hr/yr, in tCi. Releases shall be cumulative over the calendar quarter or year, as appropriate (m is for mixed mode releases, g is for ground level releases).

q., % = The releases of radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases in gaseous effluents, i, for short-term releases equal to or less than 500 hr/yr, in PCi. Releases shall be cumulative over the calendar quarter or year as appropriate (m is for mixed mode releases, g is for ground level releases).

Wm,Wg = The dispersion parameter for estimating the dose to an individual at the controlling location for long-term (greater than 500 hr) releases (m is for mixed mode releases, g is for ground level releases).

W, = (X/Q)m for the inhalation pathway and all H-3 doses in see/mi.

Wg = (D/Q)g for the food and ground plane pathways in meters2 .

41

AMENDMENT NO. 35 MARCH 2002 wmwg = The dispersion parameter for estimating the dose to an individual at the controlling location for short-term (less than 500 hr) releases (m is for mixed mode releases, g is for ground level releases).

wM = (X/q)m for the inhalation pathway and all H-3 doses in sec/m 3 .

wg (D/q)g for the food and ground plane pathways in meters2 .

3.17 x 10' = The inverse of the number of seconds in a year (yr/sec).

R The dose factor for each identified radionuclide, i, in m (mrem/yr per ptCi/sec) or mrem/yr per ICi/m3 .

3.5.2.1 Dose Parameter for Radionuclide i (Ri).

The R, values used in Equations (12) and (13) of this section are calculated separately for each of the following potential exposure pathways:

"* Inhalation

"* Ground plane contamination

"* Grass-cow/goat-milk pathway

"* Grass-cow-meat pathway

"* Vegetation pathway Monthly dose assessments for gaseous effluent will be done for all age groups.

Calculation of R! (Inhalation Pathway Factor)

R! (Inhalation) = K A (BR). (DFA)? (mrem/yr per jCi/m3) (14) where:

R. = The inhalation pathway factor (mrem/yr per ACi/m 3).

KA = A conversion constant, 106 pCi/,pCi.

AMENDMENT NO. 35 MARCH 2002 42

AMENDMENT NO. 35 MARCH 2002 (BR)a = The breathing rate of the receptor of age group (a) in meter'/yr.

(Infant = 1400, child = 3,700, teen = 8,000, adult = 8,000.

From P.32 NUREG-0133).

(DFA.), The maximum organ inhalation dose factor for receptor of age group a for the ith radionuclide (mrem/pCi). The total body is considered as an organ in the selection of (DFAj),. (DFA.)8 values are listed in Tables E-7 through E-10 of Regulatory Guide 1.109 manual, Revision 1 and NUREG/CR-4013.

Values of R1 are listed in Table 3-5.

Calculation of RG (Ground Plane Pathway Factor)

Ri (Ground Plane) = KAKB (SF)(DFG) (1- e -ý')/I* (m2 x mrem/yr per jCi/sec) (15) where:

RGi Ground plane pathway factor (in2 x mrem/yr per jCi/sec).

KA A conversion constant, (106 pCi/PCi).

KB = A conversion constant, (8760 hr/yr).

Xji = The decay constant for the ith radionuclide (sec-).

t = Exposure time, 6.31 x 108 sec (20 years).

DFG1 = The ground plane dose conversion factor for the ith radionuclide, as listed in Table E-6 of Regulatory Guide 1.109, Revision 1 and NUREG/CR-4013 (mrem/hr per pCi/in 2).

SF = Shielding Factor (dimensionless)--0.7 if building is present, as suggested in Table E-15 of Regulatory Guide 1.109, Revision 1.

The values of RG1 are listed in Table 3-5 of this manual.

43

AMENDMENT NO. 35 MARCH 2002 Calculation of Ri (Grass-Cow/Goat-Milk Pathway Factor)

R. (Grass-Cow/Goat-Milk Factor) =

K QF(Ua

+ Fm(r)(DFLi)a [ffs + (1-fpf)e e -ktf (16)

(in2 x mrem/yr per /iCi/sec) where:

K" = A conversion constant, 106 pCi/jLCi.

QF = The cow/goat consumption rate, in kg/day (wet weight).

U&P = The receptor's milk consumption rate for age a, in liters/yr.

YP = The agricultural productivity by unit area of pasture feed grass, in kg/m 2 .

Y = The agricultural productivity by unit area of stored feed, in kg/m 2 .

Fm = The stable element transfer coefficients, in days/liter.

r = Fraction of deposited activity retained on feed grass.

(DFLj) = The maximum organ ingestion dose factor for the ith radionuclide for the receptor in age group a, in mrem/pCi (Tables E-11 to E-14 of Regulatory Guide 1.109, Revision 1 and NUREG/CR-4013).

.j = The decay constant for the ith radionuclide, in sec 1 .

S= The decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10' sec' (corresponding to a 14-day half-life).

t= The transport time from pasture to animal, to milk, to receptor, in sec.

t = The transport time from pasture, to harvest, to animal, to milk, to receptor, in sec.

fp = Fraction of the year that the cow/goat is on pasture (dimensionless).

44

AMENDMENT NO. 35 MARCH 2002 f = Fraction of the cow/goat feed that is pasture grass while the cow is on pasture (dimensionless).

NOTE: For radioiodines, multiply R.Cvalue by 0.5 to account for the fraction of elemental iodine available for deposition.

The input parameters used for calculating R.are listed in Table 3-6. The individual pathway dose parameters for Ri are tabulated in Tables 3-5a through 3-5d.

For Tritium:

C In calculating R..1pertaining to tritium in milk, the airborne concentration rather than the deposition will be used:

C Rý(Grass-Cow/Goat-Milk Factor) =

KAKCFmQFUap (DFLi)a [0.75(0.5/H)] (mrem/yr per yCi/m 3 ) (17) where:

KA = A conversion constant, 106 pCi/ixCi.

Kc = A conversion constant, 10i gm/kg.

H = Absolute humidity of the atmosphere, in gm/m3 .

0.75 = The fraction of total feed that is water.

0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water.

Calculation of RM (Grass-Cow-Meat Pathway Factor)

RM4(Grass-Cow-Meat Factor) =

KA QF(U)

A F+

Frr)(D W F[r)(DFL)

FL.[fpfs Yp+

(1-f"fbe-x Y ] e- t (18)

(m2 x mrem/yr per ItCi/sec) 45

AMENDMENT NO. 35 MARCH 2002 where:

K = A conversion constant, 106pCi//.Ci.

Ff = The stable element transfer coefficients, in days/kg.

U = The receptor's meat consumption rate for age a, in kg/yr.

= The transport time from pasture to receptor, in sec.

th = The transport time from crop field to receptor, in sec.

All other parameters are as defined in Equation 16.

NOTE: For radioiodines, multiply R. value by 0.5 to account for the fraction of elemental I

iodine available for deposition.

M The input parameters used for c.lculation R. (18) are listed in Table 3-7. The individual pathway dose parameters for R i are tabulated in Tables 3-5a through 3-5d.

For Tritium:

M In calculating the R for tritium in meat, the airborne concentration is used rather than the T M deposition rate. The following equation is used to calculate the R T values for tritium:

M RT (Grass-Cow-Meat Pathway) =

KAKc [ FfQFUap (DFLi)a ] [ 0.75(0.5/H) ] (mrem/yr per ACi/m 3) (19)

M Where the terms are as defined in Equations (16) through (18), R . values for tritium pertaining to the infant age group is zero since there is no meat consumption by this age group.

46

AMENDMENT NO. 35 MARCH 2002 Calculation of R' (Vegetation Pathway Factor)

RY (Vegetation Pathway Factor)

KA~~~ (r) (DFLj)a 1[U.Lfe 1h+ Usfge ;i (0 (in 2 x mrem/yr per PiCi/sec) where:

KA = A conversion constant, 106pCi/ACi.

ULa = The consumption rate of fresh leafy vegetation by the receptor in age group a, in kg/yr.

US = The consumption rate of stored vegetation by the receptor in age a group a, in kg/yr.

fL The fraction of the annual intake of fresh leafy vegetation grown locally.

fg = The fraction of the annual intake of stored vegetation grown locally.

tL - The average time between harvest of leafy vegetation and its consumption, in seconds.

th = The average time between harvest of stored vegetation and its consumption, in seconds.

Y, = The vegetation area density, in kg/in 2 .

NOTE: For radioiodines, multiply R y value by 0.5 to account for the fraction of elemental iodine available for deposition.

All other items are as defined in Equations (16) through (18).

The input parameters for calculation R y are listed in Table 3-8. The individual pathway dose parameters for R V are tabulated in Tables 3-5a through 3-5d.

47

AMENDMENT NO. 35 MARCH 2002 For Tritium:

In calculating the R T for tritium, the concentration of tritium in vegetation is based on airborne V

concentration rather than the deposition rate. The following equation is used to calculate R T for tritium:

V R T (Vegetation Pathway Factor) =

KAKc [(U.LfL + U'f ) (DFLi)a] [0.75(0.5/H)] (mrem/yr per .Ci/m 3) (21)

Where all terms have been defined above and in Equations (16) through (18), the R v value for tritium is zero for the infant age group due to zero vegetation consumption rate by that age group. The input parameters needed for solving Equations (20) and (21) are listed in Table 3-8.

3.5.3 Annual Doses At Special Locations The Radioactive Effluent Release Report submitted within 60 days after January 1 of each year shall include an assessment of the radiation doses from radioactive gaseous effluents to MEMBERS OF THE PUBLIC, due to their activities inside the site boundary during the report period.

Annual doses within the site boundary have been determined for several locations using the NRC GASPARII computer code and source term data from Table 11.3-7 of the FSAR. These values are listed in Tables 3-16 and 3-17. Annual doses to the maximum exposed MEMBER OF THE PUBLIC within the SITE BOUNDARY shall be determined.

48

Table 3-1 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS*

D SE F CTORS F NOBLE Q SES Total Body Gamma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor Ki Md N, Radionuclide (mrem/yr per ,Ci/m3) (mrem/yr per ,Ci/m3) (mrad/yr per ,Ci/m3) (mrad/yr per ,Ci/m3)

Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

>g

The listed dose factors are for radionuclides that may be detected in gaseous effluents.

The values listed above were taken from Table B-i of NRC Regulatory Guide 1.109, Revision 1.

The values were multiplied by 106 to convert picocuries 1' to microcuries 1 .

pz

AMENDMENT NO. 35 MARCH 2002 TABLE 3-2 DISTANCES (MILES) TO TYPICAL CONTROLLING LOCATIONS AS MEASURED FROM CENTER OF COLUMBIA GENERATING STATION CONTAINMENT BUILDING*

Location Distance Sector Dose Pathways (miles)

Site Boundary 1.2 SE Air dose measurement One 4.2 ESE Ground, vegetables, and inhalation Two 6.4 SE Ground, meat, and inhalation Three 4.5 ESE Ground, vegetables, and inhalation Four 4.1 ENE Ground, vegetables, and inhalation Five 4.3 NE Ground and inhalation Six 7.2 ESE Ground, Cow milk, and inhalation

Typical locations and pathways are based on the historic Land Use Census (LUC).

50

TABLE 3-3 LONG-TERM AVERAGE DISPERSION (X/Q)

AND DEPOSITION (D/O) VALUES FOR TYPICAL LOCATIONS X/Q X/Q X/Q 2.3 Days 8.0 Days No Decay Decay Decay Location Sector Distance Point of Release No Depletion No Depletion Depleted D/O (miles) (sec/m 3) (sec/m 3) (sec/m 3) (M72)

Site Boundary SE 1.2 Reactor Bldg. 2.7E-07 2.7E-07 2.613-07 2.013-09 Turbine Bldg. 1.4E-05 1.313-05 1.213-05 1.213-08 Radwaste Bldgz. 1.4E-05 1.3E-05 1.213-05 1.213-08 One ESE 4.2 Reactor Bldg. 1.513-06 1.5E-06 1.213-06 6.013-10 Turbine Bldg. 1.11E-06 1.013-06 8.1E-07 6.OE-10 Radwaste Bldg. 1.11E-06 1.0E-d6 8.1E-07 6.OE-10 ti' f ý Two SE 6.4 Reactor Bldg. 3.713-07 3.5E-07 3.4E-07 3.213-10

ý_A Turbine Bldg. 7.213-07 6.8E-07 5. 1E-07 2.613-10 Radwaste Bldg. 7.2E-07 6.813-07 5. 1E-07 2.613-10 Three ESE 4.5 Reactor Bldg. 1.613-06 1.5E-06 1.313-06 5.1E-10 Turbine Bldg. 1.0E-06 9.8E-07 7.713-07 5.1E-10 Radwaste Bldg. 1.0E-06 9.8E-07 7.713-07 5.1E-10 Four ENE 4.1 Reactor Bldg. 9.8E-07 9.3E-07 7.7E-07 3.813-10 Turbine Bldg. 6.9E-07 6.513-07 5.213-07 3.713-10 Radwaste Bldg. 6.913-07 6.5E-07 5.213-07 3.713-10 Five NE 4.3 Reactor Bldg. 6.813-08 6.613-08 6.613-08 1.313-10 Turbine Bldg. 6.7E-07 6.313-07 5.0E-07 3.713-10 4 -d Radwaste Bldg. 6.7E-07 6.313-07 5.0E-07 3.7E-10 Six ESE 7.2 Reactor Bldg. 7.9E-07 7.11E-07 5.913-07 1.9E-10 z

Turbine Bldg. 5.213-07 4.7E-07 3.66E-07 1.913-10 z Radwaste Bldg. 5.213-07 4.713-07 3.6E-07 1.9E-10 LA

AMENDMENT NO. 35 MARCH 2002 TABLE 3-4 DOSE RATE PARAMETERS IMPLEMENTATION OF 10 CFR 20, AIRBORNE RELEASES 1

Child Dose Factor* PI DFA, DFGJ Inhalation mrem/hr mrem/lr3 pCi/rm2 u*Ci/m Nuclide X(sec-) mrem/pCi H-3 1.8E-09 1.7E-07 0.0 6.3E+02 Na-24 1.3E-05 4.4E-06 2.99E-08 1.6E+04 Cr-51 2.9E-07 4.6E-06 2.6E-10 1.7E+04 Mn-54 2.6E-08 4.3E-04 6.88E-09 1.6E+06 Mn-56 7.5E-05 3.33E-05 1.3E-08 1.2E+05 Fe-55 8.5E-09 3.0E-05 0.0 1. 1E+05 Fe-59 1.8E-07 3.4E-04 9.4E-09 1.3E+06 Co-58 1.1E-07 3.OE-04 8.2E-09 1.1E+06 Co-60 4.2E-09 1.9E-03 2.01E-08 7.0E1+06 Cu-64 1.5E-05 9.9E-06 1.77E-09 3.7E+04 Zn-65 3.3E-08 2.7E-04 4.6E-09 1.0E1+06 Zn-69m 1.4E-05 2.7E-05 3.44E-09 1.0E+05 As-76 7.3E-06 1.99E-05 1.7E-07 7.0E+04 Br-82 5.5E-06 5.7E-06 2.2E-08 2. 1E+04 Sr-89 1.5E-07 5.8E-04 6.5E-13 2.2E+06 Sr-90 7.9E-10 1.OE-02 2.6E-12** 3.7E+07 Zr-95 1.2E-07 6.0E-04 5.8E-09 2.2E+06 Nb-95 2.3E-07 1.7E-04 6.0E-09 6.3E+05 Zr-97 1.1E-05 9.5E-05 6.4E-09 3.5E+05 Nb-97 1.6E-04 7.5E-06 5.4E-09 2.8E+04 Mo-99 2.9E-06 3.7E-05 2.22E-09 1.4E+05 Tc-99m 3.22E-05 1.3E-06 1.1E-09 4.8E+03 Ru-106 2.22E-08 3.9E-03 1.8E-09 1.4E+07 Ag-110m 3.22E-08 1.51E-03 2. 1E-08 5.6E+06 Sb-124 1.3E-07 8.8E-04 1.5E-08 3.3E+06 Sb-125 7.9E-09 6.3E-04 3.5E-09 2.3E+06 Sb-126 6.5E-07 2.99E-04 1.OE-08 1.11E+06 Sb-127 2.1E-06 6.2E-05 6.66E-09 2.3E+05 Te-127 2. 1E-05 1.51E-05 1.1E-11 5.6E+04 Te-131m 6.4E-06 8.3E-05 9.99E-09 3. 1E+05 1-131 1.OE-06 4.4E-03 3.4E-09 1.6E+07 1-132 8.4E-05 5.2E-05 2.OE-08 1.9E+05 1-133 9.2E-06 1.OE-03 4.51E-09 3.7E+06 1-135 2.99E-05 2.1E-04 1.4E-08 7.8E+05 Cs-134 1.1E-08 2.7E-04 1.4E-08 1.0E+06 Cs-137 7.33E-10 2.5E-04 4.9E-09 9.3E+05 52

AMENDMENT NO. 35 MARCH 2002 TABLE 3-4 (continued)

DOSE RATE PARAMETERS IMPLEMENTATION OF 10 CFR 20, AIRBORNE RELEASES Child Dose Factor* pI 1

DFA1 DFGJ Inhalation mrem/hr mrem/yr Nuclide X(sec1 ) mrem/pCi pCi/mr2 /Ci/m 3 Cs-138 3.6E-04 2.3E-07 2.4E-08 8.5E+02 Ba-140 6.3E-07 4.7E-04 2.4E-09 1.7E+06 La-140 4.8E-06 6.1E-05 1.7E-08 2.3E+05 Ce-141 2.4E-07 1.5E-04 6.2E-10 5.6E+05 Ce-144 2.8E-08 3.2E-03 3.7E-10 1.2E+07 Nd-147 7.2E-07 8.9E-05 1.2E-09 3.3E+05 Hf-179m 3.7E-02 2.OE-05 NO DATA 7.4E+04 Hf-181 1.8E-07 6.OE-05 1.2E-08 2.2E+05 W-185 1.1E-07 1.9E-04 0.0 7.OE+05 Np-239 3.4E-06 1.7E-05 9.5E-10 6.4E+04

Maximum Organ

- No data is listed for Sr-90 in Table E-6 of Regulatory Guide 1.109, Revision 1. Y-90 values were used for dose conversion factor Sr-90.

53

AMENDMENT NO. 35 MARCH 2002 TABLE 3-5a DOSE PARAMETERS FOR 10 CFR 50 EVALUATIONS, AIRBORNE RELEASES AGE GROUP: ADULT ORGAN OF

REFERENCE:

MAXIMUM ORGAN R(I), INDIVIDUAL PATHWAY DOSE PARAMETERS FOR RADIONUCLIDES OTHER THAN NOBLE GASES Radionuclide Inhalation Ground Plane Cow Milk Goat Milk Animal Meat Vegetables (mrem/yr (M`*mrem/yr 1*mrem/yr (M&*=rem/yr (M2 *hrwyr per pCi/M') per 1pCi/sec) per pCi/sec) per UCi/sec) per pCi/sec) per pCi/sec)

H 3 7.2E+02 0 0E-01 5.8E+02 1.2E+03 2.4E+02 1.6E+03 NA 24 1.0E+04 1.2E+07 1.2E+06 2.2E+05 7.2E-04 I.IE+05 CR51 1.4E+04 4.7E+06 3 3E+06 5.9E+05 8.2E+05 2.3E+07 MN 54 1.4E+06 1.4E+09 1.4E+07 2.1E+06 1.5E+07 9.4E+08 MN 56 2 0E+04 9.0E+05 6.2E-02 1.1E-02 0.0E-01 2.0E+02 FE 55 7.2E+04 0.0E-01 1.4E+07 2.2E+06 4.6E+08 1.9E+08 FE 59 1.0E+06 2.7E+08 1.1E+08 2.0E+07 9.8E+08 1.5E+09 CO 58 9 3E+05 3.8E+08 4.7E+07 7.6E+06 1.8E+08 8.0E+08 CO60 6.0E+06 2.3E+10 1.7E+08 2.5E+07 8 0E+08 2.9E+09 CU64 4 9E+04 6 IE+05 1.0E+06 1.7E+05 1.IE-05 3.3E+05 ZN 65 8 6E+05 7.5E+08 2.7E+09 4 0E+08 7.0E+08 1.3E+09 ZN 69M 1.4E+05 1.3E+06 1.3E+07 2 4E+06 1.2E-03 1.4E+06 AS 76 1.5E+05 3.8E+06 2.1E+07 3.8E+06 2.9E+01 8.0E+06 BR 82 1.4E+04 2.1E+07 1.9E+07 3.4E+06 7.0E+02 7.7E+05 SR 89 1.4E+06 2.2E+04 6.9E+08 2.0E+ 09 1.4E+08 1.5E+10 SR 90 2.92+07 6.7E+06 3.4E+10 8.3E+10 8.9E+09 7.4E+11 ZR 95 1.821+06 2 5E+08 4.6E+05 7.6E+04 9.2E+08 1.6E+09 NB 95 5.121+05 1 4E+08 1.3E+08 2 2E+07 3.6E+09 8.4E+08 ZR 97 5.2E+05 3.0E+06 1.4E+04 2.4E+03 6.4E-01 8 8E+06 NB 97 2.4E+03 1.8E+05 1.6E-09 2 9E-10 0.0E-01 8.1E-04 MO 99 2.5E+05 4 0E+06 2.9E+07 5 2E+06 1.2E+05 9 3E+06 TC 99M 4.2E+03 1.8E+05 2.8E+03 5 0E+02 3.6E-18 2 2E+03 RU106 9.4E+06 4.2E+08 7.3E+05 1.1E+05 1.0E+11 1.2E+10 AGIlOM 4.6E+06 3.5E+09 1.2E+10 1.8E+09 1.4E+09 4.4E+09 SB124 2 5E+06 6.0E+08 3.5E+08 5.8E+07 2 7E+08 4.0E+09 SB125 1.7E+06 2.4E+09 1.3E+08 1.8E+07 1.2E+08 1.4E+09 SB126 7.7E+05 8.4E+07 2.2E+08 4.0E+07 7.6E+07 1.6E+09 SB127 3.0E+05 1.7E+07 5.2E+07 9.3E+06 1.9E+06 1.2E+08 TE127 5 7E+04 3 0E+03 2 6E+04 4.7E+03 8 4E-09 2.0E+05 TE131M 5 6E+05 8 0E+06 8.9E+06 1.6E+06 1.11+04 2.0E+07 1 131 1.2E+07 8.6E+06 3.4E+10 6.1E+10 1.2E+09 4.4E+10 1132 1.1E+05 6.2E+05 3.9E+00 6.9E+00 0.0E-01 .IE+03 1133 2 2E+06 1.2E+06 2.5E+08 4.5E+08 2.4E+01 1.1E+08 1135 4.5E+05 1 3E+06 5.5E+05 9 8E+05 1.7E-15 1.4E+06 CS134 8.5E+05 6 9E+09 7.4E+09 2.7E+10 8 6E+08 1.0E+ 10 CS136 1.5E+05 1.5E+08 5 OE+08 2.2E+09 2.3E+07 4 6E+08 CS137 6.2E+05 1.3E+10 6.0E+09 2.1E+10 7.1E+08 8 6E+09 CS138 6.2E+02 3.6E+05 L.0E-23 4 6E-23 0.0E-00 3 0E-11 BAI40 1.3E+06 2.1E+07 2.7E+07 4.8E+06 2.8E+07 7.3E+08 LA140 4.6E+05 1.9E+07 8.4E+04 1.5E+04 7.0E+02 3.3E+07 CE141 3.6E+05 1.4E+07 5.8E+06 1.0E+06 1.7E+07 9.3E+08 CE144 7.8E+06 7.0E+07 6.4E+07 9.6E+06 2.6E+08 1.1E+10 ND147 2.2E+05 8.5E+06 2 5E+05 4.6E+04 1.9E+07 5.1E+08 HF179M 1.6E+05 0.0E-01 0.0E-01 0.0E-01 0 0E-01 0 0E-01 1HF181 4.8E+05 2.1E+08 5.5E+05 9.3E+04 1.2E+10 1.8E+09 W 185 4.5E+05 1.8E+04 2.4E+07 3.9E+06 1.9E+07 8.4E+08 NP239 1.2E+05 1.7E+06 3.7E+04 6.7E+03 2.6E+03 1.6E+07 NOTE: The Y-90 ground plane dose factor was used for Sr-90.

The PARTS subroutine of GASPAR II was used to produce this table.

54

AMENDMENT NO. 35 MARCH 2002 TABLE 3-5b DOSE PARAMETERS FOR 10 CFR 50 EVALUATIONS, AIRBORNE RELEASES AGE GROUP: TEEN ORGAN OF

REFERENCE:

MAXIMUM ORGAN R(I), INDIVIDUAL PATHWAY DOSE PARAMETERS FOR RADIONUCLIDES OTHER THAN NOBLE GASES Inhalation Ground Plane Cow Milk Goat Milk Animal Meat Vegetables (mrem/yr (M'*mnrem/yr (M3*mrem/yr (M0&*xrem/yr (Mi*mrem/yr rnrem/yr Radionuclide per PCiOMW) per pCi/sec) per 1,Ci/sec) per jCi/sec) per ipCi/see) per pCi/sec)

H 3 7.3E+02 0 CE-01 7.5E+02 1.5E+03 1.5E+02 1.9E+03 NA 24 1.4E+04 1.2E+07 2.1E+06 3.9E+05 5.8E-04 1.0E+05 CR 51 2.IE+04 4.7E+06 3.9E+06 6.8E+05 4.4E+05 2.5E+07 MN 54 2.OE+06 1.4E+09 1.6E+07 2.3E+06 7.8E+06 9.6E+08 MN 56 5.7E+04 9.OE+05 2.3E-01 4.1E-02 0.OE-00 3.7E+02 FE 55 1.2E+05 0.0E-01 2.4E+07 3.8E+06 1.3E+08 3.0E+08 FE 59 1.5E+06 2.7E+08 1.3E+08 2.5E+07 5.5E+08 1.7E+09 CO 58 1.3E+06 3 8E+08 5.3E+07 8.7E+06 9.4E+07 8.3E+08 CO 60 8.7E+06 2.3E+10 2.1E+08 3.0E+07 4.3E+08 3.1E+09 CU 64 6.1E+04 6.1E+05 1.6E+06 2.7E+05 8.0E-06 2.7E+05 ZN 65 1.2E+06 7.5E+08 4.5E+09 6.7E+08 5.4E+08 2.OE+09 ZN 69M 1.7E+05 1.3E+06 2.1E+07 3 8E+06 9.1E-04 1.1E+06 AS 76 1.5E+05 3.8E+06 2.7E+07 4.9E+06 1.7E+01 5.3E+06 BR 82 1.8E+04 2.1E+07 2 8E+07 5.1E+06 4.9E+02 6.IE+05 SR 89 2 4E+06 2.2E+04 1.3E+09 3.7E+09 1.2E+08 2.4E+10 SR 90 3.3E+07 6.7E+06 5.1E+10 1.3E+11 6.2E+09 1.0E+12 ZR 95 2.7E+06 2.5E+08 5 8E+05 9.5E+04 5.3E+08 1.8E+09 NB 95 7.5E+05 1.4E+08 1.6E+08 2.7E+07 2.0E+09 9.1E+08 ZR 97 6.3E+05 3.OE+06 2.1E+04 3.8E+03 4.6E-O1 7.OE+06 NB 97 3.9E+03 1.8E+05 1.9E-08 3.3E-09 0.0E-01 4.8E-03 MO 99 2.7E+05 4.OE+06 5.1E+07 9.2E+06 9.4E+04 1.1E+07 TC 99M 6.IE+03 1.8E+05 5.3E+03 9.5E+02 3.2E-18 2.1E+03 RU106 1.6E+07 4 2E+08 9.9E+05 1.5E+05 6.2E+10 1.SE+10 AG110M 6.8E+06 3.5E+09 1.4E+10 2.1E+09 7.6E+08 4.6E+09 SB124 3.8E+06 6 0E+08 4.5E+08 7.3E+07 1.6E+08 4.6E+09 SB125 2 7E+06 2 4E+09 1.6E+08 2 3E+07 6.81+07 1.6E+09 SB126 1.2E+06 8 4E+07 2.8E+08 5.1E+07 4.5E+07 1.8E+09 SB127 3 2E+05 1.7E+07 6.9E+07 1.2E+07 1.2E+06 1.2E+08 TE127 8 1E+04 3 0E+03 4.8E+04 8.6E+03 7.OE-09 1.8E+05 TE131M 6.2E+05 8 OE+06 1.3E+07 2 3E+06 7.4E+03 1.5E+07 1131 1 5E+07 8.6E+06 5 4E+10 9.7E+10 9.OE+08 6.1E+10 1132 1.5E+05 6.2E+05 6.4E+00 1.2E+01 0.0E-00 9.3E+02 1133 2.9E+06 1.2E+06 4 2E+08 7.5E+08 1.8E+01 9.6E+07 1135 6.2E+05 1.3E+06 9.3E+05 1.7E+06 1.3E-15 1.21+06 CS134 1.1E+06 6.9E+09 1.3E+10 4.6E+10 6.8E+08 1.6E+10 CS136 1.9E+05 1.5E+08 8.4E+08 3.8E+09 1.8E+07 7.0E+08 CS137 8.5E+05 1.3E+10 1.2E+10 3.8E+10 5.7E+08 1.4E+ 10 CS138 8 6E+02 3.6E+05 1.8E-23 8.1E-23 0.02-00 2.7E-11 BA140 2.0E+06 2.1E+07 3.6E+07 6.4E+06 1.8E+07 8.8E+08 LAI40 4.9E+05 1.9E+07 1.1E+05 2.1E+04 4.4E+02 2.4E+07 CE141 6.1E+05 1.4E+07 7.9E+06 1.4E+06 1.OE+07 1.1E+09 CE144 1.3E+07 7.0E+07 8 8E+07 1.3E+07 1.6E+08 1.3E+10 ND147 3 7E+05 8.5E+06 3 5E+05 6.2E+04 1.2E+07 6.1E+08 HF179M 7.IE+04 0.0E-01 0 0E-01 0.0E-01 0.OE-01 0.0E-01 HF181 4.8E+05 2.1E+08 7.1E+05 1.2E+05 7.0E+09 2.1E+09 W 185 7.7E+05 1.8E+04 3.3E+07 5.4E+06 1.2E+07 1.0E+09 NP239 1.3E+05 1.7E+06 5.3E+04 9.6E+03 1.7E+03 1.4E+07 NOTE: The Y-90 ground plane dose factor was used for Sr-90 The PARTS subroutine of GASPAR II was used to produce this table.

55

AMENDMENT NO. 35 MARCH 2002 TABLE 3-5c DOSE PARAMETERS FOR 10 CFR 50 EVALUATIONS, AIRBORNE RELEASES AGE GROUP: CHILD ORGAN OF

REFERENCE:

MAXIMUM ORGAN R(I), INDIVIDUAL PATHWAY DOSE PARAMETERS FOR RADIONUCLIDES OTHER THAN NOBLE GASES Inhalation Ground Plane Cow Milk Goat Milk Animal Meat 0&*=L-m/y) Vegetables

&*mrem=/yr (M`*mrem/yr (M2*mrem/yr M&*mremlyr (mremlyr per juCi/sec) per pCLIM) per pCi/sec) per 1pCi/sec) per pCilsec) per PCi/sec)

Radionuclide 6.4E+02 0.0E-01 1.2E+03 2.4E+03 1.8E+02 2 9E+03 H 3 1.2E+07 4.5E+06 8.0E+05 9.2E-04 1.6E+05 NA 24 1.6E+04 4.7E+06 2.5E+06 4.4E+05 2.2E+05 1.6E+07 CR51 1.7E+04 1.4E+09 1.IE+07 1.7E+06 4.3E+06 6.9E+08 MN 54 1.6E+06 1.2E+05 9.0E+05 8.8E-01 1.6E-01 0.0E-00 1.IE+03 MN56 O.OE-01 6.1E+07 9.6E+06 2.5E+08 7.6E+08 FE 55 1.1E+05 1.3E+06 2 7E+08 9.5E+07 1.7E+07 3.0E+08 1.2E+09 FE 59 1.1E+06 3.8E+08 3.4E+07 5.6E+06 4.7E+07 5.3E+08 CO 58 2.3E+10 1.4E+08 2 0E+07 2.2E+08 2.1E+09 CO60 7.1E+06 6.1E+05 1.7E+06 2 9E+05 6.5E-06 2.2E+05 CU64 3.7E+04 7.5E+08 6.8E+09 1.OE+09 6.2E+08 3.0E+09 ZN 65 1.0E+06 1.3E+06 2 2E+07 4.0E+06 7.2E-04 9.0E+05 ZN 69M 1.0E+05 3.8E+06 2.2E+ 07 4.OE+06 1.IE+01 3.3E+06 AS 76 7.0E+04 2.1E+07 5.8E+07 1.0E+07 7.6E+02 9.5E+05 BR 82 2.1E+04 2.2E+04 3.1E+09 9.2E+09 2.3E+08 6.0E+10 SR 89 2.2E+06 6.7E+06 1.0E+11 2 6E+11 9.8E+09 2.1E+12 SR 90 3 8E+07 2.2E+06 2.5E+08 4.2E+05 7.OE+04 3.0E+08 1.3E+09 ZR 95 1.4E+08 1.1E+08 1.8E+07 1.0E+09 6.2E+08 NB 95 6.1E+05 3 5E+05 3.0E+06 2.1E+04 3.8E+03 3.5E-01 5.2E+06 ZR 97 2 8E+04 1.8E+05 4.2E-07 7.6E-08 0 0E-01 8.2E-02 NB 97 4.0E+06 8.7E+07 1.6E+07 1.2E+05 1.6E+07 MO 99 1.3E+05 1.8E+05 7.4E+03 1.3E+03 3.4E-18 2.2E+03 TC 99M 4.8E+03 4 2E+08 7.9E+05 1.2E+05 3.8E+10 1.2E+10 RU106 1.4E+07 3 5E+09 9.4E+09 1.4E+09 3.8E+08 3.0E+09 AG110M 5.5E+06 6 0E+08 3.3E+08 5.4E+07 8 8E+07 3.3E+09 SB124 3 2E+06 SB125 2 3E+06 2.4E+09 1.2E+08 1.7E+07 3.8E+07 1.2E+09 8.4E+07 2 2E+08 4 0E+07 2.7E+07 1.4E+09 SB126 1.1E+06 1.7E+07 5 5E+07 1.0E+07 7.2E+05 9.2E+07 SB127 2.3E+05 TE127 5 6E+04 3.0E+03 5 9E+04 1.IE+04 6.7E-09 1.7E+05 8.0E+06 1.1E+07 2.IE+06 5 0E+03 9 9E+06 TE131M 3.1E+05 8.6E+06 1.1E+11 1.9E+11 1.4E+09 1.2E+11 1131 1.6E+07 6.2E+05 1.5E+01 2.7E+01 O.0E-00 1.6E+03 1132 1.9E+05 1.2E+06 9.9E+08 1.8E+09 3.3E+01 1.7E+08 1133 3.8E+06 1.3E+06 2.1E+06 3.8E+06 2.3E-15 2.1E+06 1135 7.9E+05 6.9E+09 2.0E+10 7.5E+10 8.3E+08 2.6E+10 CS134 1.0E+06 1.7E+05 1.5E+08 1.3E+09 6.0E+09 2.11+07 1.1E+09 CS136 9.1E+05 1.3E+10 1.9E+10 6 8E+10 7.9E+08 2.5E+10 CS137 8 4E+02 3.6E+05 3.2E-23 1.4E-22 0.0E-00 3.6E-11 CS138 1.7E+06 2.1E+07 5 6E+07 1.OE+07 2.1E+07 1.4E+09 BAI40 2.3E+05 1.921+07 9.5E+04 1.7E+04 2.8E+02 1.6E+07 LA140 1.4E+07 6.31+06 L.1E+06 6 4E+06 9.0E+08 CE141 5 4E+05 1.2E+07 7.0E+07 7.0E+07 I.IE+07 1.0E+08 1.1E+10 CE144 ND147 3.3E+05 8 5E+06 2.8E+05 5.OE+04 7.4E+06 4.82+08 7.4E+04 0 0E-01 0.0E-01 0.0E-01 0.0E-01 0.0E-01 HF179M HF181 2.2E+05 2.1E+08 5.9E+05 9.9E+04 4.4E+09 1.821+09 6 9E+05 1.8E+04 2.7E+07 4.3E+06 7.3E+06 8.31+08 W 185 1.7E+06 4.6E+04 8.3E+03 1.1E+03 1.0E+07 NP239 6.4E+04 NOTE: The Y-90 ground plane dose factor was used for Sr-90.

The PARTS subroutine of GASPAR II was used to produce this table.

56

AMENDMENT NO. 35 MARCH 2002 TABLE 3-5d DOSE PARAMETERS FOR 10 CFR 50 EVALUATIONS, AIRBORNE RELEASES AGE GROUP: INFANT ORGAN OF

REFERENCE:

MAXIMUM ORGAN R(1), INDIVIDUAL PATHWAY DOSE PARAMETERS FOR RADIONUCLIDES OTHER THAN NOBLE GASES Inhalation Ground Plane Cow Milk Goat Milk Animal Meat (M`*mrem/yr (m1 *iremjyr PVeetables (mrem/yr (M'*mrem/yr (M0*mrem/yr M*zremlyr Radionuclide per gCiCM) per pCi/sec) per tACi/sec) per pCi/sec) per pCi/sec) per pCi/sec)

H 3 3.7E+02 0 OE-01 1.8E+03 3.7E+03 0.0E-01 0 0E-01 NA 24 1.1E+04 1.21+07 7.8E+06 1.4E+06 0.OE-01 0.0E-01 CR51 1.3E+04 4.7E+06 2 2E+06 3 8E+05 .01E-01 0.OE-01 MN 54 1.0E+06 1.4E+09 2.IE+07 3 1E+06 0.0E-01 0 0E-01 MN56 7.2E+04 9.01+05 1.3E+00 2.4E-01 0.0E-01 0.0E-01 FE 55 8.7E+04 0.01-01 7.4E+07 1.2E+07 0.0E-01 0 OE-01 FE 59 1.0E+06 2.7E+08 1.8E+08 3.4E+07 0.OE-01 0 0E-01 CO 58 7.8E+05 3.8E+08 2 9E+07 4.8E+06 0.0E-01 0.01-01 CO60 4.5E+06 2.3E+10 1.2E+08 1.7E+07 0.0E-01 0.0E-01 CU64 1.5E+04 6.1E+05 1.91+06 3.2E+05 0.OE-01 0.0E-01 ZN 65 6.5E+05 7.5E+08 1.2E+10 1.7E+09 0 0E-01 0.0E-01 ZN 69M 4.1E+04 1.3E+06 2.4E+07 4.3E+06 0OE-01 0.0E-01 AS 76 2.7E+04 3.81+06 2.2E+07 4 0E+06 O.OE-01 0.0E-01 BR 82 1.3E+04 2.1E+07 9.8E+07 1.8E+07 0 0E-01 0.OE-01 SR 89 2.0E+06 2.2E+04 6 01+09 1.8E+10 0 0E-01 0.0E-01 SR 90 1.6E+07 6 7E+06 1.2E+11 2.9E+11 O.OE-01 0.0E-01 ZR 95 1.8E+06 2.5E+08 4.0E+05 6.5E+04 0 0E-01 0OE-01 NB 95 4.8E+05 1.4E+08 9.6E+07 1.7E+07 0 0E-01 0 0E-01 ZR 97 1.4E+05 3.0E+06 2.2E+04 4.0E+03 0 0E-01 0.OE-01 NB 97 2.7E+04 1.8E+05 I.IE-06 1.9E-07 0.OE-01 0 0E-01 MO 99 1.3E+05 4.0E+06 1.6E+08 2.8E+07 0.0E-01 0.0E-01 TC 99M 2 0E+03 1.8E+05 8.2E+03 1.5E+03 0.01-01 0.0E-01 RU106 1.2E+07 4.2E+08 8.0E+05 1.2E+05 0.0E-01 0 0E-01 AG110M 3.7E+06 3.5E+09 8 2E+09 1.2E+09 0 CE-01 0 0E-01 SB124 2 6E+06 6 0E+08 3.IE+08 5.1E+07 0 OE-01 0 0E-01 SB125 1.6E+06 2.4E+09 l.IE+08 1.6E+07 0.01-01 0.0E-01 SB126 9.6E+05 8 4E+07 2.1E+08 3.7E+07 0.01-01 O.0E-01 SB127 2.2E+05 1.7E+07 5.5E+07 9.9E+06 0.0E-01 0.0E-01 TE127 2 4E+04 3.0E+03 6.8E+04 1.2E+04 0.01-01 0.0E-01 TE131M 2 0E+05 8.OE+06 1.2E+07 2.11+06 0.0E-01 0 0E-01 1131 1.5E+07 8.6E+06 2 6E+11 4.7E+11 0.0E-01 0.0E-01 1132 1.7E+05 6.2E+05 3 4E+01 6.1E+01 0.0E-01 0.OE-01 1133 3.6E+06 1.2E+06 2 4E+09 4.3E+09 0.OE-01 0.0E-01 1135 7.0E+05 1.3E+06 4.9E+06 8.9E+06 0 0E-01 0.0E-01 CS134 7.0E+05 6 9E+09 3.71+10 1.4E+11 0.OE-01 0.OE-01 CS136 1.3E+05 1.5E+08 2.8E+09 1.2E+10 0 0E-01 0.OE-01 CS137 6.1E+05 1.3E+10 3 6E+10 1.3E+11 0.02-01 0.0E-01 CS138 8 8E+02 3.6E+05 1.2E-22 5.6E-22 S02E-01 0.0E-01 BA140 1.6E+06 2.1E+07 1.2E+08 2.IE+07 0 0E-01 0.0E-01 LA140 1.7E+05 1 9E+07 9.4E+04 1.7E+04 0 0E-01 0OE-01 CE141 5.2E+05 1.4E+07 6.4E+06 1.1E+06 0.01-01 0.0E-01 CE144 9.8E+06 7.0E+07 7.1E+07 1.lE+07 0 0E-01 0 0E-01 ND147 3.2E+05 8 5E+06 2.8E+05 5.0E+04 0 OE-01 0.0E-01 HF179M 2.8E+04 0 0E-01 0.0E-01 0.02-01 0.01-01 0OE-01 HFI81 8.4E+04 2.1E+08 5.9E+05 9.91+04 0.0E-01 0OE-01 W 185 6 3E+05 1.8E+04 2.7E+07 4.4E+06 0.0E-01 0.OE-01 NP239 6.0E+04 1.71+06 4.7E+04 8.5E+03 0.0E-01 0.0E-01 NOTE. The Y-90 ground plane dose factor was used for Sr-90.

The PARTS subroutine of GASPAR 11was used to produce this table.

57

AMENDMENT NO. 35 MARCH 2002 TABLE 3-6 INPUT PARAMETERS FOR CALCULATING R Parameter Value Table*

r (dimensionless) 1.0 for radioiodine E-15 0.2 for particulates E-15 Fm (days/liter) Each stable element E-1 U., (liters/yr) --Inf mnt 330 E-5

--Child 330 E-5

--Teen 400 E-5

--Adiult 310 E-5 (DFL), (mrem/pCiI) Each radionuclide E-11 to E-14 Yp (kg//m 2) 0.7 E-15 Y, (kg/m 2) 2.0 E-15 t4 (seconds) 1.73 x 10i (2 days) E-15 t, (seconds) 7.78 x 106 (90 days) E-15 QF (kg/day) 50 for cow E-3 6 for goat E-3 fs (dimensionless) 1.0 NUREG-0133 fp (dimensionless) 0.5 for cow site specific 0.75 for goat site specific

Of Regulatory Guide 1.109, Revision 1 unless stated otherwise.

58

AMENDMENT NO. 35 MARCH 2002 TABLE 3-7 RM.

INPUT PARAMETERS FOR CALCULATING Parameter Value Table*

r (dimensionless) 1.0 for radioiodine E-15 0.2 for particulates E-15 Ff (days/kg) Each stable element E-1 Uap (kg/yr) --Infant 0 E-5

--Child 41 E-5

--Teen 65 E-5

--Adult 110 E-5 (DFL), (mrem/pCi) Each radionuclide E-11 to E-14 YP (kg/rn 2) 0.7 E-15 Y, (kg/m 2) 2.0 E-15 tf (seconds) 1.73 x 10' (20 days) E-15 tb (seconds) 7.78 x 10' (90 days) E-15 QF (kg/day) 50 E-3

Of Regulatory Guide 1.109, Revision 1.

59

AMENDMENT NO. 35 MARCH 2002 TABLE 3-8 RV INPUT PARAMETERS FOR CALCULATING 1 Parameter Value Table*

r (dimensionless) 1.0 for radioiodine E-1 0.2 for particulates E-1 (DFL.)a (mrem/pCi) -Each radionuclide -E-11 to E-14 UL 0 E-5 a (kg/yr) --Infant

--Child 26 E-5

--Teen 42 E-5

--Adult 64 E-5 US 0 E-5 a (kg/yr) --Infant

--Child 520 E-5

--Teen 630 E-5

--Adult 520 E-5 fL (dimensionless) 0.42 Ref 2**

fg (dimensionless) 0.76 E-15 tL (seconds) 8.6 x 10 (1 day) E-15 th (seconds) 5.18 x 10' (60 days) E-15 Yv (kg/m 2) 2.0 E-15

Of Regulatory Guide 1.109, Revision 1.

"**Referto Table 3-14.

60

AMENDMENT NO. 35 MARCH 2002 TABLE 3-9 INPUT PARAMETERS FOR CALCULATING DOSE SUMMARIES TO THE MAXIMUM INDIVIDUAL AND THE POPULATION WITHIN 50 MILES OF COLUMBIA GENERATING STATION FROM GASEOUS EFFLUENTS Input Parameter Value Reference*

Distance to Maine (miles) 3000 Ref 1 Fraction of year leafy vegetables are grown 0.42 Ref 2 Fraction of year cows are on pasture 0.5 Ref 2 Fraction of crop from garden 0.76 Ref 3 Fraction of daily intake of cows derived from pasture while on pasture 1.0 Ref 2 Annual average relative humidity (%) 53.8 Ref 4 Annual average temperature (F7) 53.0 Ref 5 Fraction of year goats are on pasture 0.75 Ref 2 Fraction of daily intake of goats derived from pasture while on pasture 1.0 Ref 2 Fraction of year beef cattle are on pasture 0.5 Ref 2 Fraction of daily intake of beef cattle derived from pasture while on pasture 1.0 Ref 2 Population within 50 miles of plant by direction and radii interval in miles 252,356 Ref 6 Annual 50-mile milk production (liters/yr) 2.8E+08 Refs 7 Annual 50-mile meat production (kg/yr) 2.3E+07 Refs 7 Annual 50-mile vegetable production (kg/yr) 3.5E+09 Refs 7 Source terms Ref 8 61

AMENDMENT NO. 35 MARCH 2002 TABLE 3-9 (continued)

InDut Parameter Value Reference*

X/Q values by sector for each distance See Tables 3-10 and Ref 10 (recirculation, no decay) (sec/m 3) 3-11 X/Q values by sector for each distance See Tables 3-10 and Ref 10 (recirculation, 2.26 days decay, undepleted) 3-11 (sec/ms)

X/Q values by sector for each distance See Tables 3-10 and Ref 10 (recirculation, 8.0 days decay, depleted) 3-11 (sec/m 3)

D/Q values by sector for each distance (1/m2) See Tables 3-10 and Ref 10 3-11

References are listed in Table 3-14.

62

TABLE 3-10*

REACTOR BUILDING STACK X/Q AND D/Q VALUES A) NO DECAY, UNDEPLETED CHI/Q (SEC/METER CUBED) FOR EACH SEGMENT SEGMENT BOUNDARIES IN MILES FROM THE SITE DIRECTION .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 FROM SITE S 3.899E-07 1.486E-07 6.171E-08 3.982E-08 3.093E-08 2.000E-08 2.118E-07 1.769E-07 1.196E-07 8.944E-08 SSW 2.557E-07 9.471E-08 3.914E-08 2.553E-08 2.000E-08 1.41 1E-08 1.702E-07 1.431E-07 9.698E-08 7.264E-08 SW 1.635E-07 6.378E-08 3.299E-08 2.517E-08 1.999E-08 3.647E-08 1.045E-07 7.704E-08 5.209E-08 3.894E-08 WSW 6.676E-08 2.927E-08 1.506E-08 1.122E-08 8.872E-09 1.668E-08 5.532E-08 4.156E-08 2.808E-08 2.098E-08 W 6.588E-08 2.996E-08 1.509E-08 1.090E-08 8.368E-09 4.928E-09 2.837E-08 2.330E-08 1.569E-08 1.170E-08 WNW 1.279E-07 5.746E-08 3.018E-08 2.258E-08 1.781E-08 1.324E-08 5.160E-08 4.103E-08 2.750E-08 2.044E-08 NW 2.423E-08 1.934E-08 1.543E-08 9.519E-b8 7.785E-08 5.228E-08 3.891E-08 2.294E-07 8.625E-08 3.624E-08 NNW 5.137E-07 1.770E-07 6.982E-08 4.507E-08 4.224E-08 2.976E-08 1.801E-07 1.479E-07 9.945E-08 7.407E-08 N 6.024E-07 2.016E-07 8.063E-08 5.264E-08 4.120E-08 2.146E-07 2.652E-07 1.430E-07 9.579E-08 7.115E-08 NNE 4.988E-07 1.690E-07 6.861E-08 4.526E-08 4.339E-08 2.904E-07 1.966E-07 1.057E-07 7.066E-08 5.243E-08 NE 3.347E-07 1.195 E-07 4.965E-08 4.175E-08 1.400E-07 3.198E-07 1.723E-07 9.247E-08 6.174E-08 4.576E-08 ENE 4.184E-07 3.067E-07 4.347E-07 9.267E-07 8.4366E-07 4.052E-07 1.641E-07 8.817E-08 5.893E-08 4.371E-08 E 4.207E-07 3.460E-07 4.968E-07 1.027E-06 8.714E-07 4.159E-07 1.669E-07 8.906E-08 5.928E-08 4.385E-08 ESE 6.224E-07 5.205E-07 7.813E-07 1.572E-06 1.364E-06 5.365E-07 2.045E-07 1.403E-07 9.350E-08 6.922E-08 SE 5.045E-07 2.156E-07 1.174E-07 3.944E-07 6.347E-07 3.083E-07 2.738E-07 1.9133E-07 1.289E-07 9.576E-08 >

SSE 4.591E-07 1.855E-07 7.985E-08 5.319E-08 4.237E-08 3.085E-08 2.635E-07 2.188E-07 1.475E-07 1.10OE-07 PO ni r) Z

z p

TABLE 3-10 (continued)

B) 2.260 DAY DECAY, UNDEPLETED CHI/Q (SEC/METER CUBED) FOR EACH SEGMENT SEGMENT BOUNDARIES IN MILES FROM THE SITE DIRECTION .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 FROM SITE S 3.887E-07 1.477E-07 6.094E-08 3.9042-08 3.0081-08 1.8982-08 1.8132-07 1.4241-07 8.918E-08 6.2012-08 SSW 2.5502-07 9.411E-08 3.8661-08 2.5042-08 1.9472-08 1.3412-08 1.493E-07 1.1901-07 7.53013-08 5.2752-08 SW 1.6302-07 6.338E-08 3.255E-08 2.463E-08 1.939E-08 3 438E-08 9.132E-08 6.300E-08 3.9691-08 2.7761-08 WSW 6.657E-08 2.909E-08 1.484E-08 1.093E-08 8.5331E-09 1.521E-08 4.618E-08 3.210E-08 1.995E-08 1.3812-08 W 6.5631-08 2.972E-08 1.4882-08 1.0692-08 8.157E-09 4.721E-09 2.3192-08 1.757E-08 1.0772-08 7.3652-09 WNW 1.275E-07 5.702E-08 2.9701-08 2.201E-08 1.717E-08 1.226E-08 4.063E-08 2.933E-08 1.7652-08 1.1942-08 NW 2.287E-07 8.5752-08 3.584E-08 2.381E-08 1.8882-08 1.470E-08 8.026E-08 6.1392-08 3.8112-08 2.6422-08 NNW 5.1252-07 1.760E-07 6.913E-08 4.4392-08 4.130E-08 2.8532-08 1.614E-07 1.2692-07 8.0772-08 5.711E-08 N 6.011E-07 2.006E-07 7.9882-08 5.1892-08 4.0401-08 2.0002-07 2.381E-07 1.202E-07 7.574E-08 5.3132-08 NNE 4.9782-07 1.6821-07 6.7952-08 4.4562-08 4.236E-08 2.7072-07 1.714E.-07 8.475E-08 5.2561-08 3.639E-08 NE 3.3392-07 1.188E-07 4.909E-08 4.0892-08 1.348E-07 2.9081-07 1.4471-07 7.008E-08 4.277E-08 2.9242-08 ENE 4.172E-07 3.040E-07 4.272E-07 8.948E-07 7.996E-07 3.720E-07 1.3902-07 6.706E-08 4.1342-08 2.8272-08 E 4.194E-07 3.430E-07 4.885E-07 9.9092-07 8.315E-07 3.861E-07 1.44521-07 7.0672-08 4.346E-08 2.9862-08 ESE 6.2072-07 5.158E-07 7.670E-07 1.5232-06 1.306E-06 5.0462-07 1.776E-07 1.1322-07 7.0122-08 4.846E-08 SE 5.0302-07 2.1422-07 1.159E-07 3.8502-07 6.171E-07 2.9462-07 2.383E-07 1.554E-07 9.668E-08 6.7011-08 SSE 4.577E-07 1.8432-07 7.887E-08 5.2142-08 4.117E-08 2.9112-08 2.219E-07 1.724E-07 1.0721-07 7.41611-08 ;0 tri cZ z

o-,

TABLE 3-10 (continued)

C) 8.000 DAY DECAY, UNDEPLETED CHI/Q (SEC/METER CUBED) FOR EACH SEGMENT SEGMENT BOUNDARIES IN MILES FROM THE SITE DIRECTION .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 FROM SITE S 3.793E-07 1.434E-07 5.872E-08 3.765E-08 2.919E-08 1.879E-08 1.925E-07 1.497E-07 9.326E-08 6.496E-08 SSW 2.479E-07 9.089E-08 3.705E-08 2.403E-08 1.880E-08 1.325E-08 1.561E-07 1.226E-07 7.691E-08 5.388E-08 SW 1.572E-07 6.070E-08 3.115E-08 2.387E-08 1.896E-08 3.473E-08 9.189E-08 6.223E-08 3.871E-08 2.694E-08 WSW 6.375E-08 2.776E-08 1.416E-08 1.057E-08 8.356E-09 1.572E-08 4.792E-08 3.295E-08 2.035E-08 1.407E-08 W 6.471E-08 2.914E-08 1.449E-08 1.047E-08 8.037E-09 4.713E-09 2.534E-08 1.922E-08 1.182E-08 8.138E-09 WNW 1.255E-07 5.587E-08 2.901E-08 2.171E-08 1.709E-08 1.261E-08 4.452E-08 3.233E-08 1.960E-08 1.335E-08 tNW NW 2.228E-07 8.309E-08 3.451E-08 2.300E-08 1.837E-08 1.471E-08 8.579E-08 6.505E-08 4.009E-08 2.769E-08 NNW 4.947E-07 1.686E-07 6.558E-08 4.219E-08 3.996E-08 2.820E-08 1.654E-07 1.272E-07 7.938E-08 5.547E-08 N 5.785E-07 1.917E-07 7.566E-08 4.927E-08 3.863E-08 2.032E-07 2.372E-07 1.154E-07 7.127E-08 4.939E-08 NNE 4.769E-07 1.602E-07 6.423E-08 4.232E-08 4.105E-08 2.728E-07 1.696E-07 8.150E-08 4.985E-08 3.425E-08 NE 3.220E-07 1.141E-07 4.688E-08 3.977E-08 1.366E-07 2.947E-07 1.433E-07 6.805E-08 4.121E-08 2.806E-08 ENE 4.056E-07 2.988E-07 3.849E-07 7.340E-07 6.588E-07 2.951E-07 1.033E-07 4.759E-08 2.806E-08 1.864E-08 E 4.072E-07 3.375E-07 4.406E-07 8.152E-07 6.738E-07 3.000E-07 1.042E-07 4.785E-08 2.822E-08 1.877E-08 ESE 5.997E-07 5.068E-07 6.926E-07 1.240E-06 1.053E-06 3.916E-07 1.247E-07 7.545E-08 4.463E-08 2.978E-08 >

SE 4.883E-07 2.075E-07 1.122E-07 3.874E-07 6.185E-07 2.852E-07 2.217E-07 1.413E-07 8.648E-08 5.940E-08 , cZ SSE 4.476E-07 1.796E-07 7.640E-08 5.064E-08 4.029E-08 2.929E-08 2.179E-07 1.669E-07 1.027E-07 7.085E-08 3

LA

TABLE 3-10 (continued)

D) REACTOR BUILDING D/Q RELATIVE DEPOSITION PER UNIT AREA (M**-2) BY DOWNWIND SECTORS SEGMENT BOUNDARIES IN MILES DIRECTION .5-I 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 FROM SITE S 4.044E-09 1.1461-09 3.7171-10 1.874E-10 1.1272-10 4.6352-11 3 8682-11 2.2832- 11 1.2192- 11 7.5482-12 SSW 2.643E-09 7.296E-10 2 3242-10 1.1652-10 7.0002- 11 2.9162-11 2 663E-11 1.5962-11 8.526E-12 5.2781-12 SW 1.429E-09 4.068E-10 1.407E-10 6.7992-11 4.0162-11 3.1922&11 2.386E-11 9.555E-12 5.1041-12 3.1602-12 WSW 4 407E-10 1.347E-10 4.908E.11 2.400E- I I 1.423E-11 1.2243-11 9.617E-12 3.865E-12 2.0642-12 1.278E-12 W 5 587E-10 1.7802-10 6 6653-11 3.2532-11 1.9292-11 7.707E-12 6.116E-12 3 6172-12 1.9322-12 1.1962-12 WNW 1,1 IOE-09 3.4591-10 1 2622-10 6.186E21 3.674E-11 2,357E- 11 1.640E-11 6.963E-12 3.7191-12 2.3022-12 NW 2.1992-09 6.289E-10 2.0512-10 1 0362-10 6.2422-11 2.6252-11 2.528E-11 1.5202-11 8.1172-12 5.0252-12 NNW 5.1611-09 1.411E-09 4.4631-10 2.2312-10 1.3822-10 5.828E-11 5.329E-11 3.1862-11 1.7022-11 1.053E-11 N 7.312E-09 1.932E-09 6 001E-10 2.9702-10 1.774E-10 1.3072-10 8 6542-11 3.4302-11 1.8322-11 1.1342-11 NNE 6 6881-09 1.751E-09 5.437E-10 2.675E-10 1.637E-10 1.566E-10 6.754E-11 2.67713-11 4.430E-11 8.8512-12 NE 4.6542-09 1.223E-09 3 8082-10 1.9312-10 2.2252-10 1.5921-10 4.683E-11 1.873E-11 1.0002-11 6.1912-12 ENE 4.8421-09 1.2772-09 6.1372-10 5 2652-10 3.0562-10 1.1892-10 3.440E- 11 1.364E-11 7.2862-12 4.511E-12 E 4 0041-09 1.1212-09 6 0442-10 5 617E-10 3.2682-10 1.248E-10 3.5902-11 1.441E-11 7.695E-12 4.7632-12 ESE 6,270E-09 1.764E-09 9.7042-10 9 0162-10 5.2072-10 2.0082-10 5.7881- 11 2.3161-11 1.23713-11 7.659E-12 SE 5.0272-09 1.477E-09 5.2182-10 5.481E-10 6 8942-10 2.6622-10 7.839E-11 3.1421-11 1.6782- 11 1.0392-11 4 4?*'T.-m 1 "i21r*-m 4.4521-10 2.2671-10 1.3661-10 5.6921-11 4.8731-11 2.8961-11 1.547F- 11 9.573E- 12 SSE 44 P- 1 32113-09 >

Based on January 1, 1984 - January 1, 1990 meteorological data.

z 0

LA

TABLE 3-11*

TURBINE OR RADWASTE BUILDING X/Q AND D/Q VALUES A) NO DECAY, UNDEPLETED CHI/Q (SEC/METER CUBED) FOR EACH SEGMENT SEGMENT BOUNDARIES IN MILES FROM THE SITE DIRECTION .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 FROM SITE S 2.782E-05 7.806E-06 2.832E-06 1.567E-06 1.037E-06 5.081E-07 2.113E-07 I. 153E-07 7.771E-08 5.794E-08 SSW 2.117E-05 6.000E-06 2.195E-06 1.220E-06 8.099E-07 3.989E-07 1.671E-07 9. 172E-08 6.199E-08 4.631E-08 SW 1.211E-05 3.404E-06 1.236E-06 6.834E-07 4.521E-07 2.214E-07 9.199E-08 5.019E-08 3.381E-08 2.520E-08 WSW 6.468E-06 1.8311E-06 6.680E-07 3.702E-07 2.451E-07 1.202E-07 5.001E-08 2.729E-08 1.837E-08 1.369E-08 W 4.034E-06 1.113E-06 3.982E-07 2.186E-07 1.439E-07 6.994E-08 2.873E-08 1.555E-08 1.043E-08 7.751E-09 WNW 7.812E-06 2.127E-06 7.518E-07 4.096E-07 2.682E-07 1.292E-07 5.239E-08 2.809E-08 1.873E-08 1.387E-08 NW 1.386E-05 3.830E-06 1.370E-06 7.517E-07 4.944E-07 2.397E-07 9.809E-08 5.290E-08 3.538E-08 2.624E-08 NNW 2.549E1-05 7.081E-06 2.548E-06 1.402E-06 9.242E-07 4.498E-07 1.849E-07 1.001E-07 6.703E-08 4.976E-08

"-J, N 2.640E-05 7.275E-06 2.599E-06 1.424E-06 9.356E-07 4.528E-07 1.845E-07 9.915E-08 6.615E--08 4.897E--08 NNE 2.061E-05 5.617E-06 1.986E-06 1.082E-06 7.085E-07 3.410E-07 1.379E-07 7.372E-08 4.906E-08 3.626E-08 NE 1.800E-05 4.929E-06 1.749E-06 9.543E-07 6.251E-07 3.009E-07 1.217E-07 6.502E-08 4.323E-08 3.193E-08 ENE 1.715E-05 4.677E-06 1.656E-06 9.030E-07 5.914E-07 2.848E-07 1.152E-07 6.164E-08 4.103E-08 3.032E-08 E 1.821E-05 4.961E-06 1.751E-06 9.521E-07 6.221E-07 2.982E-07 1.198E-07 6.368E-08 4.221E-08 3.111E-08 ESE 2.834E-05 7.730E-06 2.730E-06 1.484E-06 9.699E-07 4.651E-07 1.870E-07 9.9511E-08 6.602E-08 4.868E-08 SE 3.509E-05 9.697E-06 3.466E--06 1.899E-06 1.247E-06 6.035E-07 2.459E-07 1.322E-07 8.8231-08 6.534E1-08>

SSE 3.628E-05 1.013E-05 3.656E-06 2.015E-06 1.330E-06 6.485E-07 2.677E-07 1.453E-07 9.7553E-08 7.2553-08 Z z

3

TABLE 3-11 (continued)

B) 2.260 DAY DECAY, UNDEPLETED CHI/Q (SEC/METER CUBED) FOR EACH SEGMENT SEGMENT BOUNDARIES IN MILES FROM THE SITE DIRECTION .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 FROM SITE I S 2.763E-05 7.701E-06 2.7668-06 1.515E-06 9.933E-07 4.7458-07 1.8488-07 9.2918-08 5.7998-08 4.0228-08 SSW 2.1048-05 5.9331-06 2.152E-06 1.186E-06 7.8128-07 3.766E-07 1.492E-07 7.6158-08 4.8028-08 3.3558-08 SW 1.2038-05 3.361E-06 1.2088-06 6.623E-07 4.3431-07 2.0778-07 8.127E-08 4.1118-08 2.5818-08 1.801E-08 WSW 6.4058-06 1.7971-06 6.466E-07 3.5373-07 2.313E-07 1.0981-07 4.210E-08 2.083E-08 1.2868-08 8.865E-09 W 4.001E-06 1.095E-06 3.867E-07 2.097E-07 1.363E-07 6.4128-08 2.4248-08 1.1838-08 7.2288-09 4.9378-09 WNW 7.732E-06 2.084E-06 7.250E-07 3.891E-07 2.510E-07 1.1638-07 4.2748-08 2.03318-08 1.2228-08 8.2568-09 NW 1.376E-05 3.776E-06 1.337E-06 7.256E-07 4.724E-07 2.229E-07 8.5138-08 4.2168-08 2.6148-08 1.8108-08 NNW 2.537E-05 7.013E-06 2.506E-06 1.3698-06 8.9668-07 4.2868-07 1.6838-07 8.5908-08 5.4498-08 3.8428-08 ca N 2.626E-05 7.1991-06 2.5518-06 1.3878-06 9.044E-07 4.2891-07 1.659E-07 8.3498-08 5.2448-08 3.6688-08 NNE 2.047E-05 5.544E-06 1.941E-06 1.0471-06 6.792E-07 3.187E-07 1.2088-07 5.9608-08 3.6878-08 2.5488-08 NE 1.7848-05 4.844E-06 1.696E-06 9.137E-07 5.910E-07 2.7538-07 1.0251-07 4.95212-08 3.0138-08 2.0558-08 ENE 1.701E-05 4.603E-06 1.610E-06 8.673E-07 5.6138-07 2.621E-07 9.8038-08 4.7568-08 2.9018-08 1.9808-08 E 1.808E-05 4.891E-06 1.707E-06 9.184E-07 5.938E-07 2.769E-07 1.0371-07 5.0478-08 3.0908-08 2.1158-08 ESE 2.8138-05 7.623E-06 2.6638-06 1.434E-06 9.2788-07 4.336E-07 1.6348-07 8.0168-08 4.9418-08 3.4028-08 SE 3.4868-05 9.5748-06 3.389E-06 1.8408-06 1.1978-06 5.6548-07 2.1658-07 1.0758-07 6.6728-08 4.6158-08

SSE 3.60013-05 9.9791-06 3.5628-06 1.9428-06 1.2681-06 6.0168-07 2.3138-07 1.150E-07 7.1258-08 4.9198-08 z

Z 3

zf

TABLE 3-11 (continued)

C) 8.000 DAY DECAY, DEPLETED CHI/Q (SEC/METER CUBED) FOR EACH SEGMENT SEGMENT BOUNDARIES IN MILES FROM THE SITE DIRECTION .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 FROM SITE S 2.487E-05 6.658E-06 2.286E-06 1.213E-06 7.751E-07 3.540E-07 1.275E-07 5.998E-08 3.588E-08 2.411E-08 SSW 1.892E-05 5.121E-06 1.774E-06 9.460E-07 6.067E-07 2,788E-07 1.015E-07 4.823E-08 2.906E--08 1.964E-08 SW 1.082E-05 2.904E-06 9.977E-07 5.294E-07 3.382E-07 1.545E-07 5.566E-08 2.623E-08 1.571E-08 1.058E-08 WSW 5.777E.-06 1.559E-06 5.378E-07 2.856E-07 1. 824E-07 8.320E-08 2.980E-08 1.391E-08 8.267E-09 5.523E-09 W 3.605E-06 9.486E-07 3.209E-07 1.688E-07 1.072E-07 4.847E-08 1.714E-08 7.924E-09 4.679E-09 3.111E-09 WNW 6.978E-06 1.811E-06 6.046E-07 3.155E-07 1.992E-07 8.908E-08 3.092E-08 1.406E-08 8.205E-09 5.403E-09 NW 1.239E-05 3.267E-06 1. 106E-06 5.816E-07 3.693E.-07 1.668E-07 5.900E-08 2.734E-08 1.619E-08 1.080E-08 NNW 2.280E-05 6.047E-06 2.061E-06 1.089E-06 6.935E-07 3.153E-07 1. 129E-07 5.307E-08 3.181E-08 2.145E-08 N 2.362E-05 6.21 IE-06 2.1011E-06 1.105E-06 7.013E-07 3.169E-07 1.123E-07 5.225E-08 3.110E-08 2.086E-08 NN NNE 2.377E-07 1.843E-05 4.793E-06 1.604E-06 8.3811E-07 5.298E-07 8.323E-08 3.832E-08 2.263E-08 1.507E-08 NE 1.608E-05 4.2011E-06 1.409E-06 7.367E-07 4.655E-07 2.085E-07 7.255E-08 3.311E-08 1.939E-08 1.282E-08 ENE 1.532E-05 3.988E-06 1.335E-06 6.977E-07 4.409E-07 1.976E-07 6.893E-08 3.155E-08 1.853E-08 1.227E-08 E 1.628E-05 4.232E-06 1.413E-06 7.366E-07 4.646E-07 2.075E-07 7.206E-08 3.291E-08 1.932E-08 1.281E-08 ESE 2.534E-05 6.595E-06 2.203E-06 1. 149E-06 7.248E-07 3.241E-07 1. 128E-07 5.170E-08 3.045E-08 2.024E-08 SE 3.137E-05 8,274E-06 2.799E-06 1.471E-06 9.331E-07 4.210E-07 1.487E-07 6.892E-08 4.086E-08 2.729E-08 SSE 3.242E-05 8.636E-06 2.949E-06 1.558E-06 9.928E-07 4.510E-07 1.609E-07 7.503E-08 4.461E-08 2.984E-011 C~Z t3~

z 0

TABLE 3-11 (continued)

D) TURBINE OR RADWASTE DEPOSITION, D/Q.

RELATIVE DEPOSITION PER UNIT AREA (M**-2) BY DOWNWIND SECTORS SEGMENT BOUNDARIES IN MILES DIRECTION .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 FROM SITE S 2.664E-08 5.457E-09 1.425E-09 6.398E-10 3.620E-10 1.392E-10 4.027E-1 I 1.596E-11 8.523E-12 5.275E-12 SSW 1.853E-08 3.796E-09 9.909E-10 4.450E-10 2.518E-10 9.682E-11 2.801E-11 1.110E-11 5.928E-12 3.669E-12 SW 1.160E-08 2.375E-09 6.201E-10 2.785E-10 1.575E-10 6.058E-11 1.753E-11 6.947E-12 3.710E-12 2.296E-12 WSW 4.652E-09 9.529E-10 2.488E-10 1.117E-10 6.321E-1 I 2.4311E-11 7.032E-12 2.787E-12 1.488E-12 9.212E-13 W 4.254E-09 8.714E-10 2.275E-10 1.022E-10 5.780E-1 I 2.223E-11 6.430E-12 2.549E-12 1.361E-12 8.424E-13 WNW 8.379E-09 1.716E-09 4.481E-10 2.012E-10 1.138E-10 4.378E-1 1 1.266E-11 5.020E-12 2.681E-12 1.659E-12 NW 1.761E-08 3.608E-09 9.419E-I0 4.230E-10 2.393E-10 9.203E-11 2.662E-11 1.055E-11 5.635E-12 3.488E-12 NNW 3.707E-08 7.593E-09 1.982E-09 8.903E-10 5.036E-I0 1.937E-10 5.603E-11 2.22iE-11 1.186E-11 7.340E-12 N 4.270E-08 8.746E-09 2.283E-09 1.025E-09 5.801E-10 2.231E-10 6.454E-1 1 2.558E-11 1.366E-11 8.455E-12 NNE 3.448E-08 7.062E-09 1.844E-09 8.280E-10 4.684E-10 1.801E-10 5.2111E-11 2.065E-1 1 1.103E-11 6.827E-12 NE 2.465E-08 5.050E-09 1.318E-09 5.921E-10 3.349E-10 1.288E-10 3.726E-11 1.477E-11 7.887E-12 4.881E-12 ENE 2.235E-08 4.579E-09 1.195E-09 5.368E-10 3.037E-10 1.168E-10 3.379E-1 1 1.339E-11 7.151E-12 4.426E-12 E 2.363E-08 4.841E-09 1.264E-09 5.676E-10 3.2111E-10 1.235E-10 3.572E-11 1.416E-11 7.560E-12 4.679E-12 ESE 3.810E-08 7.804E-09 2.037E-09 9.150E-10 5.176E-10 1.991E-10 5.759E-1 1 2.282E-11 1.219E-11 7.544E-12 SE 4.168E-08 8.537E-09 2.229E-09 1.001E-09 5.663E-10 2.178E-10 6.300E-11 2.497E-1 I 1.333E-11 8.25313-12 SSE 3.672E-08 7.521E-09 1.963E-09 8.818E-10 4.988E-10 1.918E-10 5.550E-1 1 2.200E-11 1.175E-11 7.270E-12 ý0~T

Based on January 1, 1984 - January 1, 1990 meteorological data. z o

z 0h

AMENDMENT NO. 35 MARCH 2002 TABLE 3-13 CHARACTERISTICS OF GASEOUS EFFLUENT RELEASE POINTS Reactor Radwaste Turbine Building Building Building Height of release point above ground level (m) 70.3 20.4 36.3 Annual average rate of air flow from release point (m3/sec) 37.8 39.2 169.9 Annual average heat flow from release point (cal/sec) 1.06 x 106 2.9 x 106 9.1 x 10U Type and size of release Duct 3 Louver houses, 4 Exhaust point (m) 1.14 x 3.05 Each fans, Each 1.37 x 2.44 x 0.75 1.45 x 2.01 Effective vent area (m2) 3.48 11.58** 8.74***

Vent velocity (m/sec)* 10.9 3.4 19.5 Effective diameter (m) 2.1 3.8 3.3 (nrr 2 = area)

Building height (m) 70.1 42.4

Reactor Building exhaust in vertical direction. Radwaste and Turbine Building exhaust in horizontal plane.

"**Equivalent to two vents (as per FSAR Section 9.4.3.2, 2 of 3 will normally be in operation).

- - Equivalent to three vents (as per FSAR Section 9.4.6.2.2, 3 of 4 will normally be in operation).

"****Heightof the Radwaste and Control Building.

71

AMENDMENT NO. 35 MARCH 2002 TABLE 3-14 REFERENCES FOR VALUES LISTED IN TABLES 3-8 and 3-9 Reference 1 U.S. Map Reference 2 Health Physics Calculation Log 93-2 Reference 3 Regulatory Guide 1.109, Revision 1, Table E-15 Reference 4 Columbia Generating Station FSAR, Table 2.3-1 Reference 5 Columbia Generating Station-FSAR, Page 2.3-2 Reference 6 Columbia Generating Station Emergency Preparedness Plan Table 12.1, Permanent Population Distribution, Rev 5, Feb. 88 Reference 7 1986 50-Mile Land Use Census, Energy Northwest REMP Reference 8 Effluent Analysis for Applicable Time Period Reference 9 Health Physics Calculation Log No. 93-2 Reference 10 NUREG/CR-2919, XOQDOQ: Computer Program For The Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations, September 1982.

72

AMENDMENT NO. 35 MARCH 2002 TABLE 3-15 DESIGN BASE PERCENT NOBLE GAS (30-MINUTE DECAY)*

Isotope Percent of Total Activity Kr-83M 2.9 Kr-85M 5.6 Kr-85 0 Kr-87 15 Kr-88 18 Kr-89 0.2 Xe-131M 0.02 Xe-133M 0.3 Xe-133 8.2 Xe-135M 6.9 Xe-135 22 Xe-137 0.7 Xe-138 21

From FSAR Table 11.3-1 73

AMENDMENT NO. 35 MARCH 2002 TABLE 3-16 ANNUAL DOSES AT TYPICAL LOCATIONS Source: Gaseous Effluent Whole Distance Occupancy Body Dose Thyroid Dose Location (Miles) (hrs/yr) (mrem/yr) (mrem/yr)

BPA Ashe Substation 0.5N 2080 1.1E+00 1.7E+00 DOE Train 0.5 SE* 78 6.7E-02 1.0E-01 Wye Burial Site 0.5 WNW 8 4. 1E-03 6.5E-03 WNP-1 1.2 ESE 2080 3.8E-02 1.3E-01 WNP-4 1.0 ENE 2080 7.01E-02 1.1E-01 Visitor Center 0.08 ESE 8 8.66E-02 1.3E-01 Taylor Flats** 4.2 ESE 8760 3. 1E-02 5.2E+00 Site Boundary*** 1.2 SE 8760 1.1E+00 1.7E+00

The sector with the highest X/Q values (within 0-0.5 mile radius) was used.

- Closest residential area representative of maximum individual dose from plume, ground, ingestion, and inhalation exposure pathways. Included for comparison.

Assumed continuously occupied. Actual occupancy is very low. Doses from Inhalation and Ground Exposure pathways. No food crops.

74

AMENDMENT NO. 35 MARCH 2002 TABLE 3-17 ANNUAL OCCUPIED AIR DOSE AT TYPICAL LOCATIONS Annual Beta Air dose Annual Location (mrad) Gamma Air Dose BPA Ashe Substation 8.9E-01 1.5E+00 DOE Train 5.3E-02 9.2E-02 Wye Burial Site 3.2E-03 5.7E-03 WNP-1 3.3E-02 2.8E-02 WNP-4 5.3E-02 8.5E-02 Visitor Center 7.OE-02 1.2E-01 Taylor Flats* 2.3E-02 1.4E-02 Site Boundary 8.7E-01 1.5E+00

Closest residential area.

75

AMENDMENT NO. 35 MARCH 2002 aulom.

SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS Figure 3-1 76

AMENDMENT NO. 35 MARCH 2002 Noble Gas Eilevated Reactor Bldg Monitor Activity Discharge Refueling Pump Rooms Iodine and Main Steam Tunnels Particulate Offgas Treatment System Sampler Standby Gas Mechanical Vacuum Pumps Radwaste 1gd To Hot Machine Shop Atmosphere Chemistry Labs Demineralizer Room Radwaste Proc. Area Control Room SIMPLIFIED BLOCK DIAGRAM OF GASEOUS WASTE SYSTEM Figure 3-2 77

AMENDMENT NO. 35 MARCH 2002 SIMPLIFIED BLOCK DIAGRAM OF OFF-GAS TREATMENT SYSTEM Figure 3-3 78

AMENDMENT NO. 35 MARCH 2002 WATER COLUMN I TO AWL. SOLER OLOWDOWH TAN' AUXILIARY BOILER Figure 3-4 79

AMENDMENT NO. 35 MARCH 2002 4.0 COMPLIANCE WITH 40 CFR 190 - TOTAL DOSE 4.1 Requirement for Operability (RFO)

RFO 6.2.3.1 states, "The annual dose or dose commitment to any MEMBER OF THE PUBLIC in the UNRESTRICTED AREA, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid and to less than or equal to 75 mrems to the thyroid."

4.2 ODCM Methodology for Determining Dose and Dose Commitment from Uranium Fuel Cycle Sources The annual dose or dose commitment to a MEMBER OF THE PUBLIC for the uranium fuel cycle sources is determined as:

a) Dose to the total body due to the release of radioactive materials in liquid effluents.

b) Dose to any organ due to the release of radioactive materials in liquid effluents.

c) Air doses due to noble gases released in gaseous effluents.

d) Dose to any organ due to the release of radioiodines, tritium and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents.

e) Dose due to direct radiation from the plant.

The annual dose or dose commitment to a MEMBER OF THE PUBLIC from the uranium fuel cycle sources is determined whenever the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceed twice the limits in RFO 6.2.1.2.a, 6.2.1.2.b, 6.2.2.2.a, 6.2.2.2.b, 6.2.2.3.a, or 6.2.2.3.b. Direct radiation measurements may also be made to determine if the limits of RFO 6.2.3.1 have been exceeded.

4.2.1 Total Dose from Liquid Effluents The annual dose to a MEMBER OF THE PUBLIC from liquid effluents will be determined using NRC LADTAP II computer code or the methodology presented by Equation (10) in Section 2.5. It is assumed that dose contribution pathways to a MEMBER OF THE PUBLIC do not exist for areas within the site boundary.

4.2.2 Total Dose from Gaseous Effluents The annual dose to a MEMBER OF THE PUBLIC from gaseous effluents will be determined using NRC GASPAR II computer code or the methodology presented by Equations (10), (11) and (13) in Section 3.5. Appropriate atmospheric dispersion parameters will be used.

80

AMENDMENT NO. 35 MARCH 2002 4.2.3 Direct Radiation Contribution The dose to a MEMBER OF THE PUBLIC due to direct radiation from the reactor plant and the Independent Spent Fuel Storage Installation (ISFSI) will be determined using thermoluminescent dosimeters (TLDs) or may be calculated. TLDs are placed at sample locations and analyzed as per Table 6.3.1-1.

81

AMENDMENT NO. 35 MARCH 2002 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING Radiological environmental monitoring is intended to supplement radiological effluent monitoring by verifying that measurable concentrations of radioactive materials and levels of radiation in the environment are not greater than expected based on effluent measurement and dose modeling of environmental exposure pathways. The Radiological Environmental Monitoring Program (REMP) for Columbia Generating Station provides for measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides for which the highest potential dose commitment to a MEMBER OF THE PUBLIC would result due to plant operations. The REMP implements Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR 50. It also provides the information required by Technical Specification Section 5.6.2.

The REMP is designed to conform to regulatory guidance provided by Regulatory Guide 4.1, 4.8, 4.15 and the Radiological Assessment Branch Technical Position (BTP), taking into consideration certain site specific characteristics. The unique nature of the site on Federally owned and administered land (Hanford Site) dedicated to energy facilities, research, waste management and as a natural reserve, forms the basis for many of the site specific parameters.

Among the many site specific parameters considered is demographic data such as:

"* No significant clusters of population including schools, hospitals, business facilities or primary public transportation routes are located within 8 km (5 mile) radius of the plant.

"* No private residences are located on the Hanford Site.

"* The closest resident is east of the Columbia River at a distance of approximately 4 miles.

82

AMENDMENT NO. 35 MARCH 2002 5.1 Radiological Environmental Monitoring Program (REMP)

Environmental samples for the REMP are collected in accordance with ODCM RFO 6.3.1 and Table 6.3.1-1. This table provides a detailed outline of the environmental sampling plan items by sample type, sampling and collection frequency, and type and frequency of analysis.

Deviations from the sampling frequency detailed in Table 6.3.1-1 may occur due to circumstances such as hazardous conditions, malfunction of automatic sampling equipment, seasonal unavailability, or other legitimate reasons. When sample media is unobtainable due to equipment malfunction, special actions per program instruction shall be taken to ensure that corrective action is implemented prior to the end of the next sampling period. In some cases, alternate sample collection may be substituted for the missing specimen.

Sampling stations are described in Table 5-1. Each station is identified by an assigned number or alphanumeric designation, meteorological sector (16 different, 22-1/2" compass sections) in which the station is located, and radial distance from containment as estimated from map positions. Also included in Table 5-1 is information identifying the type(s) of samples collected at each station. Figures 5-1 and 5-2 depict the geographical locations of each of the sample stations listed in Table 5-1.

5.2 Land Use Census A Land Use Census shall be conducted in accordance with the requirements of ODCM RFO 6.3.2. It shall identify within a distance of 8 km (5 miles) in each of the 16 meteorological sectors, the location of the nearest milk animal, the nearest residence and the nearest garden of greater than 50m 2 (500 ft) producing broad leaf vegetation. Field activities pertaining to the Land Use Census will be initiated during the growing season and completed no later than September 30 each year. The information obtained during the field survey is used along with other demographic data to assess population changes in the unrestricted area that might require modifications in the sampling plan to ensure adequate evaluation of dose or dose commitment.

5.3 Laboratory Intercomparison Program A Laboratory Intercomparison program shall be conducted in accordance with the requirements of ODCM RFO 6.3.3. Analysis of REMP samples is contracted to a provider of radiological analytical services. By contract, this analytical service vendor is required to conduct all activities in accordance with Regulatory Guides 4.1, 4.8, and 4.15 and to include in each quarterly report, actions pertinent to their participation in the Interlaboratory Comparison Program. A precontract award survey and periodic audit at the contractor's facility ensure that the contractor is participating in the Crosscheck Program, as reported.

83

AMENDMENT NO. 35 MARCH 2002 Besides the vendor's required participation in the Interlaboratory Comparison Program, the Department of Health (DOH) of the State of Washington oversees an analytical program for the Energy Facility Site Evaluation Council (EFSEC) to provide an independent test of Columbia Generating Station REMP sample analyses. The Columbia Generating Station/DOH split samples are analyzed by Washington State's Office of Public Health Laboratories and Epidemiology, Environmental Radiation Laboratory (ERL). The results of the ERL analysis and Interlaboratory Comparison Program data are included in an annual report, "Environmental Radiation Program, Environmental Health Surveillance, State of Washington" and are available for comparison with the Columbia Generating Station data.

Energy Northwest participates in the International Intercomparison of Environmental Dosimeter Program. Results of this intercomparison program are reported in the REMP Annual Report, when available.

84

TABLE 5-1 REMP LOCATIONS Station Sector Radial Miles" TLD AP/AI SW DW GW SE MI Fl GP 1 S 1.3 0 2 NNE 1.8 0 4 SSE 9.3 0 0 5 ESE 7.7 0 6 S 7.7 0 7 WNW 2.7 0 8 ESE 4.5 0 0 9A* WSW 30.0 0 0 9B WSW 33.0 0 0 9C WSW 35.0 0 10 E 3.1 0 13 SW 1.4 0 14 WSW 1.4 0 15 W 1.4 0 16 WNW 1.4 0 17 NNW 1.2 0 z

p LbJ LA

TABLE 5-1 (continued)

REMP LOCATIONS Station Sector Radial Miles" TLD AP/AI SW DW GW SE MI FI GP 18 N 1.1 0 19 NE 1.8 0 20 ENE 1.9 0 22 E 2.1 0 24 SE 1.9 0 25 SSE 1.6 0 26* E 3.2 0 0 27 E 3.2 0 29 SSE 11.0 0 30 E 3.3 0 31 ESE 1.1 0 34 ESE 3.5 0 36 ESE 7.2 0 37 SSE 17.0 0 38* E 26.5 0 >.

4I1>

z z

I,-'

TABLE 5-1 (continued)

REMP LOCATIONS Station Sector Radial Miles" TLD AP/AI sw DW GW SE MI Fl GP 40 SE 6.4 0 0 41 SE 5.8 0 42 ESE 5.6 0 43 E 5.8 0 44 ENE 5.8 0 45 ENE 4.3 0 46 NE 5.0 0 48 NE 4.5 0 49 NW 1.2 0 50 SSW 1.2 0 51 ESE 2.1 0 52 N 0.1 0 53 N 7.5 0 54 NNE 6.5 0 55 SSE 6.2 0 56 SSW 7.0 0 57 N 0.8 0 64 ESE 9.9 0 0 0

Ul

TABLE 5-1 (continued)

REMP LOCATIONS Station Sector Radial Miles" TLD AP/AI SW DW GW SE MI FI GP

Control location.

O - Radiological Environmental RFO sample collected at station.

a - Estimated from center of Plant Containment from map positions.

TLD = Thermoluminescent dosimeter AP/AI = Air Particulate and Iodine SW = Surface Water (River Water)

DW = Drinking Water 00 GW = Ground Water SE = Shoreline Sediment MI = Milk FI = Fish GP = Garden Produce C)

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ML030690072

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