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Amend 6 to Offsite Dose Calculation Manual.
	ML17285A251
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Site:	Columbia
Issue date:	11/30/1988
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WASHINGTON PUBLIC POWER SUPPLY SYSTEM WNP-2 OFFSITE DOSE CALCULATION MANUAL 8902210 + 0 881118 05000397 PDR ADGCK P

AMENDMEHT HO. 3 February 1986 OFFSITE DOSE CALCULATION MAHUAL TABLE OF CONTENTS Section Title Page

1.0 INTRODUCTION

.

2.0 LIQUID EFFLUENT DOSE CALCULATIOH................ 2 2.1 I ntroduction.....................,... 2 2.2 Radwaste Liquid Effluent Radiation Monitoring System...... 2 2.3 10 CFR 20 Release Rate Limits 3 2.3.1 Pre-Release Calculation 3 2.3.2 Post-Release Calculation . . . . . 4 2.3.3 Continuous Release . . 5 2.4 10 CFR 50, Appendix I, Release Rate Limits . . . . . . . . . . . 6 2.4.1 Projection of Doses . . . . . . . . . . . . , . . . . . . , . . 9 2.5 2.5.1 Setpoints Calculations Introduction

.'...................

Radwaste Liquid Effluent Dilution Ratio and Alarm

. . . . . . . . . . . . . . . . . . . . . . . . .

9 9

2.5.2 Methodology for Determining the Maximum Permissible Concentra-tion (MPC) Fraction. . . . . . . . . . . . . . . . . . . . . . . 10 2.5.3 Methodology for the Determination of Liquid Effluent Monitor Setpoint .

2.6 Verification of and 10 CFR 20, Appendix B....................

Compliance with 10 CFR 50, Appendix I, 12b )

2.7 Methods for Calculating Dose to Man from Liquid Effluent Pathways . ~ 12b I 2.7.1 Radiation Doses . 13 2.7.2 Plant Parameters . . . . . 17 2.8 Compliance with Technical Specification 3.11.1.4 . .19 I 2.8.1 Maximum Allowable Liquid Radwaste Activity in Temporary Radwaste Hold-Up Tanks . .19 I 2.8. 2 Maximum Allowable Liquid Radwaste in Tanks That Are Not Surrounded by Liners, Dikes, or Walls ...22 j 2.9 Liquid Process Monitors and Alarm Setpoints Calculations . . 22 2.9.1 Standby Service Mater (SW) Monitor . . 23 2.9.2 2.9.3 Turbine Building Service Mater (TSH) Monitor Turbine Building Sumps Hater (FD) Monitor

.. . 24

. 24

AMENDMENT NO. 3 February 1986 Section Title ~Pa e 3.0 GASEOUS EFFLUENTS DOSE CALCULATION . . 33 3.1 Introduction e e e e ~ e ~ ~ ~ e ~ ~ ~ ~ ~ ~ e e ~ ~ ~ ~ ~ . 33 3.2 Gaseous Effluent Radiation Monitoring System....... ~ ~ . 34

. 34 3.2.1 Main Plant Release Point . . . . . . . . . . . . . . . . . ~ ~

3.2.2 Radwaste Building Ventilation Exhaust Monitor ~ ~ . 35 3.2.3 Turbine Building Ventilation Exhaust Monitor . . . . . . . ~ ~ . 36 3.3 10 CFR 20 Release Rate Limits ~ ~ . 36 3.3.1 Noble Gases ~ ~ . 37 3.3.2 Radioiodines and Particulates ~ ~ ~, 37 3.3.2.1 Dose Parameter for Radionuclide i (Pi) ~ ~ 40 3.4 10 CFR 50 Release Rate Limits ~ ~ . 41 3.4.1 Noble Gases (Technical Specification 3.11.2.2) ~ ~ . 42 3.4.2 Radioiodines and Particulates (Technical Specification 3.11.2.3) . ~ ~ ~ 44 3.4.2.1 Dose Parameter for Radionuclide i (R; ) ~ ~ . 47 3.4.3 Annual Dose at Special Locations . . . . . . . e ~ . 54 3.5 Compliance with Standard Technical Specifications 3.11.2.4 . 54 3.6 Calculation of Gaseous Effluent Monitor Alarm Setpoints ~ ~ . 54a 3.6.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . ~ ~ . 54a 3.6.2 Setpoint Determination for All Gaseous Release Paths . ~ ~ . 55 3.6.2.1 Setpoints Calculations Based on Whole Body Dose Limits . ~ ~ . 55 3.6.2. 2 Setpoints Calculations Based on Skin Dose Limits . ~ ~ . 58 4.0 COMPLIANCE WITH 40 CFR 190 . . 91 4.1 Technical Speci fication Requirement............ . 91 4.2 ODCM Methodology for Determining Dose and Dose Commitment from Uranium Fuel Cycle Sources. . . . . . . . . . . . . . ~ ~ . 91 4.2.1 Total Dose from Liquid Effluents . ~ ~ : 9la 4.2.2 Total Dose from Gaseous Effluents. . . . . . . . . . . . . ~ ~ . 9la 4.2.3 Direct Radiation Contribution. ~ ~ . 91a 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING . 92 5.1 Radiological Environmental Monitor ing Program (REMP) . . . . 93 5.2 Land Use Census . 94 5.3 Laboratory Intercomparison Program . . 95 5.4 Reporting Requirements . . 96 6.0 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT. .110

AMENDMENT NO. 1 May 1984 OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES Table Title Pacae Section 2.0 2-1 Fish Bioaccumulation Factors (BFi) and Adult Ingestion Dose Conversion Factors (DFi). . . . . . . . . . . . . . . . . 26 2-2 Ingestion Critical Organ........................

Dose Factors (Ai>) for Total Body and 29 2-3 From Liquid Effluents ....................

Input Parameters Used to Calculate Maximum Individual Dose 32 Section 3.0 3-1 Dose Factors for Noble Gases and Daughters . . . . . . . . . . 60 3 2 Distances (Miles) to Contro'lling Locations as Measured from Center of WNP-2 Containment Building . . . . . . . . . . . . . 61 3-3 WNP-2 Annual Average Dispersion (X/Q) and Deposition (D/Q)

Values for Special Locations . 62 3-4 Dose Rate Parameter s. Implementation of 10 CFR 20, Airborne Releases ~ ~ ~ ~ 63 3-Sa Dose Rate Parameters. Implementation of 10 CFR 50, "Airborne Releases - Age Group: Infant . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 64 3-5b Dose Rate Parameters. Implementation of 10 CFR 50, Airborne Releases - Age Group: Child ~ ~ ~ ~ ~ 65 3-5c Dose Rate Parameters. Implementation of 10 CFR 50, Airborne Releases - Age Group: Teen . ~ ~ ~ ~ ~ ~ 66 3-5d Dose Rate Parameters. Implementation of 10 CFR 50, Airborne Releases - Age Group: Adult ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 67 C

3-6 Input Parameters for Calculating R. ~ ~ ~ ~ 68 3-7 Input parameters for Calculating R-Mi ~ ~ ~ ~ 69 Input Parameters for Calculating R.V 1 70

AMENDMENT NO. 6 November -1988 Title ~Pa e Input Parameters Needed for Calculating Dose to the Maximum Individual from WNP-2 Gaseous Effluent...... 71 3-10 Reactor Building Stack X/Q and D/Q Values 73 3-11 Turbine Building X/Q and D/Q Values 77 3-12 Radwaste Building X/Q and D/Q Values . 81 3-13 Characteristics of WNP-2 Gaseous Effluent Release Points . 85 3-14 References for Values Listed in Table 3-9 86 3-15 Design Base Percent Noble Gas (30-Minute Decay) 87 3-16 Annual Doses at Special Locations Within WNP-2 Site Boundary.

Source: WNP-2 Gaseous Effluent 88 3-17 Annual Air Dose at Special Locations With'in WNP-2 Site Boundary 89 Section 5.0 5-1 Radiological Environmental Monitoring Program Plan . ~ ~ ~ ~ ~ 98 5-2 WNP-2 REMP Locations . . . . . . . . . . . . . . . . . . . . . 102 Environmental Radiological Honitoring Program Annual Summary . 108 5-4 Reporting Levels for Nonroutine Operating Reports . . . . . . 109 LIST OF FIGURES

~Fi are Ti tl e ~Pa e 2-1 Simplified Block Diagram of Liquid Waste System 32a 2-2 Simplified Block Diagram of Solid Radwaste System 32b 3-1 Site Boundary for Radioactive Gaseous and Liquid Ef fluents 90 3-2 Simplified Block Diagram of Gaseous Waste System . 90a 3-3 Simplified Block Diagram of Off-Gas Treatment System . 90b 5-1 Radiological Environmental Monitoring Sample Locations Inside of 10-Mile Radius . 106 Radiological Environmental Monitoring Sample Locations Outside of 10-Mile Radius 107 iv

1. 0 INTRODUCTION The purpose of this manual is to provide the information and methodologies to be used by the .Washington Public Power Supply System to ensure compliance with the dose requirements stated in the WNP-2 Effluents Technical Specifications.

I

AMENDMENT NO. 6 November 1988 2.0 LI UID EFFLUENT DOSE CALCULATION 2.1 Introduction Liquid radwaste released from HNP-2 will meet 10 CFR 20 limits at the point of discharge to the Columbia River. This design objective will be kept at all times'ctual 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. Solid radioactive wastes are disposed of by way of an approved disposal site. A simplified block diagram of the solid radwaste system is described in Figure 2-2.

The cumulative quarterly dose contributions due to radioactive liquid efflu-ents released to the unrestricted areas will be determined once every 31 days using the LADTAP II computer code. The maximum exposed individual is assumed to be an adult whose exposure pathways include potable water and fish consump-tion. 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 contributions will be calculated for all radionuclides identified in the released effluent. The calculations are based on guidelines provided by Nureg-0133 and the LADTAP II computer code.

The methods for calculating the doses are discussed in Section 2.4 of this manual.

2.2 Radwaste Li uid Effluent Radiation Monitorin S stem This monitoring subsystem measures the radioactivity in the liquid effluent prior to its entering the cooling tower blowdown line.

Af1ENDtlENT NO. 3 February 1986 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, (average of 2690 gpm) and is discharged to the Columbia River with a total flow based on ~'IPCi total, and cooling water flushing needs.

The radiation monitor has a minimum sensitivity of 10 >Ci/cc of Cs-137, and the radiation indicator has a range of seven decades. The radiation monitor is located on the 437'evel of the Radwaste Building.

2.3 10 CFR 20 Release Rate Limits The requirements pertaining to discharge of radwaste liquid effluents to the unrestricted area are specified in Technical Specification 3.11.1.1:

"The concentration of radioactive material released from the site to unrestricted areas shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than noble gases, and 2 x 10-4 pCi/m total activity concentratra-tion for all dissolved or entrained noble gases."

In order to comply with the requirements stated above, limits will be set to assure that blowdown line concentrations do not exceed 10 CFR 20, Appendix B, Table II, Column 2 at any time.

2.3.1 Pre-Release Calculation The activity of the radionuclide mixture will be determined in accordance with Supply System procedure PPt1 12.5.3, Liquid Effluent Discharge Determination.

Liquid effluent discharge is determined and calculated according to PPtl 12.11.1, Radiological Effluent tIonitoring Gaseous and Liquid. The effluent Con<,. = ~

concentration is determined by the following equation:

Cixfw

AMENDMENT NO. 3 February 1986 where:

ConC. Concentration of radionuclide i in the effluent at point of discharge - pCi/ml.

Ci Concentr ation of radionuclide i in the batch to be released - pCi/ml.

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

fb Blowdown flow rate - var iable from 0 to 7500 gpm.

ft = Total discharge flow rate - (ft = fb + fw)

The calculated concentration in the blowdown line must be less than the con-centrations listed in 10 CFR 20, Appendix B. Before releasing the batch to the environment, the following equation must hold:

g'onC'/MPC' 1 (2) i=1 where:

C'nC. The concentration of radionuclide i in the effluent at the point of discharge into the river.

MPCi Maximum permissible concentration of nuclide i as listed in 10 CFR 20, Appendix B, Table II.

m = Total number of radionuclides in the batch.

2.3.2 Post-Release Calculation The concentration of each radionuclide in the restricted area, following the batch release, will be calculated as follows:

'AMENDMENT NO. 3 February 1986 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:

Cik x fw (3)

Cik where:

ConC-k Cik

= The concentration of radionuclide i in the effluent at the point of discharge during the release period k

- (>Ci/ml).

Cik = The concentration of radionuclide i in the batch during the release per iod k - (~Ci/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 assure compliance with 10 CFR 20, the following relationships must hold:

g (ConC,-k/MPC.

i=1 1

where the terms are as defined in Equation (2).

2.3.3 Continuous Release Continuous release of liquid radwaste effluent is not planned for WNP-2.

However, should it occur, the concentrations of various radionuclides in the

AHENDHENT NO. 6 November 1988 unrestricted area would be calculated according to Equation (3) and Equa-tion (4). To show compliance with 10 CFR 20, the two equations must again hold.

2.4 10 CFR 50 A endix I Release Rate Limits Technical Specification 4.11.1.2 requires that the cumulative dose contribu-tions be determined in accordance with the ODCH at least once per 31 days.

Technical Specification 3.11.1.2 specifies that the dose to a member of the public from radioactive material in liquid effluents released to the unre-stricted 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 dose contribution will be calculated for all radionuclides identified in the liquid effluent released to the unrestricted area, using the following equation:

m D~ =g(A,. get C,. F ) (5) a=1 where:

The cumulative dose commitment to the total body or organ,~, from liquid effluents for the total time in mrem.

period g

E =.1

AMENDMENT NO. 6 November 1988 The length of the ath time period over which C.4 and Fa are averaged for all liquid releases, in hours.

The number of releases for the time period under consideration.

The average concentration of radionuclide, i, in undiluted liquid effluent during time periodhti from any liquid release, in pCi/ml.

The site-related ingestion dose commitment factor to the total body or any organ x For each identified principle gamma and beta emitter listed in Table 2-2, in mrem/hr per pCi/ml.

The near field average dilution factor for C; during any liquid waste release. 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.

Li uid Radioactive Waste Flow fw Discharge Structure Exit Flow x 500 ft x 500

ANENDNENT NO. 6 November 1988 The term A. ~

, the ingestion dose factors for the total body and critical are tabulated in Table 2-2. It embodies the dose factor, fish bioac-1J'rgans, cumulation 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:

A.. = K o(D

+

Uw UF BF 1~ )DF.1 (7) where:

The composite dose parameter for total body or criti-cal organ of an adult for nuclide i (in mrem/hr per p,Ci/ml).

K A conversion factor:

6 . 3

~

1.14E+05 = (10 pCi/pCi) x (10 ml/liter) : 8760 hr/yr.

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

Fi 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).

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

Dilution factor from near field area to the Richland potable water intake 100.

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

The values of BF.1 and DF. are 1

listed in Table 2-1.

The quarterly limits mentioned before represent one-half of the annual design objective of Section II.A of 10 CFR 50, Appendix I. If any of the limits (either that of the calendar quarter or calendar year) are exceeded, a special report pursuant to Section IV.A of 10 CFR 50, Appendix I, shall be filed with the NRC.

2.4.1 Projection of Doses The projected doses due to releases of WNP-2 radwaste liquid effluents will be calculated for each batch, using equation 5. If the sum of the accumulated dose to date for the month and the projected dose for the remainder of the month exceeds the technical specification 3.11.1.3 limits, then the liquid radwaste treatment system shall be used. This is to ensure compliance with Standard Technical Specification 3.11.1.3. This technical specification states that the liquid radwaste treatment system shall be maintained and the appropriate subsystem shall be used if the radioactive materials in liquid waste, prior to their discharge, when the dose, due to liquid effluent release to unrestricted areas when averaged over the month would exceed 0.06 mrem to total body or 0.2 mrem to any organ.

2.5 Radwaste Li uid Effluent Dilution Ratio and Alarm Set pints Calculations 2.5.1 Introduction The dilution alarm ratio and setpoints of the sample liquid effluent monitor are established to ensure that the limits of 10 CFR 20, Appendix 8, Table II, Column 2, are not exceeded in the effluent at the discharge point (i.e.,

compliance with Standard Technical Specification 3.11.1.1, as discussed in section 2.3.1 of this manual).

AMENDMENT NO. 3 February 1986 The trip/alarm setpoint for the liquid radwaste effluent monitor is calculated from the results of the radiochemical analysis of the waste solution. The setpoint will be set into the radwaste monitor just prior to the release of each batch of radioactive liquid.

2.5.2 Methodolo y for Determinin the Maximum Permissible Concentration (MPC)

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 MPC fraction (MPCf) based on 10 CFR 20 limits. From the sample analysis and the MPC values in 10 CFR 20, the MPCf is determined using the following equation.

m C.

1 MPC (8) i=1 i where:

4 h1PC f Total fraction of the Maximum Permissible Concentra-tions (MPCs) in the liquid effluent waste sample.

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

10

AMENDMENT NO. 3 February 1986 MPC. The 1 imi ting concentrations of the appropri ate radionuclide (i) from 10 CFR 20, Appendix B, Table II, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 pCi/ml total activity.

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

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

2.5.3 Methodolo y for the Determination of Li uid Effluent Monitor Set oint The measured radionuclide concentrations are used to calculate the dilution factor (Fd), which is the ratio of the total discharge flow rates (fw + fb) to the radwaste tank effluent flow rate (fw) that is required to assure that the limiting concentrations of Technical Specification 3. ll.l.l are met at the point of discharge.

The dilution factor (Fd) is determined accor ding to:

x Fs (9)

Where:

The dilution factor required for compliance with 10 CFR 20, Appendix B, Table II, Column 2.

AMENDMENT NO. 3 February 1986 C. The concentration of each radionuclide (i ) observed by radiochemical analysis of the liquid waste sample (yCi/ml).

MPCi The 1 imi ting concentration of the appropriate radionuclide (i) from 10 CFR 20, Appendix B, Table II, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 pCi/ml total activity.

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 ('X) variation.

The total number of measured radionuclides (i) in the liquid batch to be released.

The dilution which is required to ensure compliance with Technical Specification 3.11.1.1 concentration limits will be set such that discharge rates are:

< fw + fb (10)

Fd fw and follows that:

fw- fb (loa) or fb ~ fw(Fd-1) (1 ob)

Where:

Fd The dilution factor from equation 9.

12

NENDMENT NO. 3 February 1986 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.

The liquid effluent radiation monitor response is based on the results of the radiochemical analysis of the waste solution. Therefore the calculation for the radiation monitor's alarm/trip setpoint is; SP = C + BKg + K [C + Bkg]l/2 Mhere:

SP Radiation monitor setpoint (count rate) i=1 (C; x Efi) represents the count rate from the radionuclides in the liquid radwaste.

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

Same as for equation 9.

The radwaste effluent monitor's response to radionuclide (i) (count rate per pCi/ml).

12a

AHENDHENT NO. 5 April 1988 BKg Background count rate of the radwaste effluent monitor.

A constant to compensate for normal expected statistical variations in the liquid effluent radiation monitor count rate to reduce the chance of false alarms/trips; K=3.

2.6 Verification of Com liance with 10 CFR 50 A endix I and 10 CFR 20 A endix 8 Verification of compliance with 10 CFR 50, Appendix I, and 10 CFR 20, Appen-dix B, limits will be achieved by following NNP-2 Plant Procedures for liquid discharge and the periodic application of the LADTAP II computer code.

2.7 Methods for Calculatin Doses to Han From Li uid Effluent Pathwa s 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."

12b

2.7.1 Radiation Doses Radiation doses from potable water, aquatic food, shoreline deposit, and irrigated food pathways will be calculated by using the following equations:

a. Potable Water U

R . = 1100 ~<Z Q,.D, Mp exp(-X,.t ) (13)

b. Aquatic Foods U Mp R . = 1100 ~RZ0,.D,. D, exp(-1,.t )

c. Shoreline Deposits U M W R . = 110,000 ~p gl Q.T.D . .[exp(-> .t ) (1 - exp(-X,.tt)j (10)

d. Irrigated foods For all radionuclides except tritium:

r[1 - exp(-XE,.t )j fI iv[ - exp(-X,.t+)j Ra

= U Z diexP( ~ith ai j v Ei pp.

1 r[l - exp(->E,.t )j v Ei fIB - exp(-~'tb j I lv [1 i b P). iAw~Aw 1

l3

For tritium:

= Uv gC P + " m P F (C q + C ) (l7)

Awq Aw U

apj ap v apj ap apj A v F where:

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

B.

1V 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.

C.

iAw The concentration of radionucl ide i in water consumed by animals, in pCi/liter.

1V The concentration of radionuclide i in vegetation, in pCi/kg.

alpj 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 areal radionuclide concentration (in pCi/m ).

14

AMENDMENT NO. 6 November 1988 d ~ The deposition rate of nuclide i, in pCi/m per hour.

The flow rate of the liquid effluent, in ft /sec.

The fraction of the year crops are irrigated, dimens i onl ess.

iA The stable element transfer coefficient that relates the daily intake rate by an animal to the concen-tration in an edible portion of animal product, in pCi/liter (milk) per pCi/day or pCi/kg (animal pro-duct) per pCi/day.

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.

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

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

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

Qi The release rate of nuclide i, in Ci/yr.

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

15

AMENDMENT NO. 3 February 1986 The total annual dose to organ j of individuals of apJ 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, Revision 1).

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

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).

The radioactive half life of nuclide i, in days.

The average transit time required for nuclides to reach the point of exposure. For internal dose, t 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).

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

16

AHENDNENT NO. 6 November 1988 The shoreline width factor, dimensionless (Table A-2, Regulatory Guide 1.109, Revision 1).

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

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

-1 where XE. =X. +) w' Ei i 1

. is the radioactive decay constant, and x is the removal rate constant for physical loss by weathering (Regulatory Guide 1.109, Revision 1, Table 8-15).

The radioactive decay constant of nuclide i, in hr 1100 The factor to convert from (Ci/yr)/(ft /sec) to pCi/liter.

110,000 The factor to convert From (Ci/yr)/(ft /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.

2.7.2 Plant Parameters WNP-2 is a river shoreline site with a variable effluent discharge flow rate 0 to 7500 gpm. The population center nearest WNP-2 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 17

AMENDMENT NO. 6 November 1988 leased liquids to reach Richland, approximately 12 miles downstream, is esti-mated at 4.0 hours0 days 0 hours 0 weeks 0 months ., Richland is the "realistic case" location, and doses cal-culated 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 WNP-2 site is affected by the liquid effluents released. There is no significant commercial fish harvest in the 50-mile radius region around WNP-2. Sportfish harvest is estimated at 14,000 kg/year.

For irrigated foods exposure pathways, it can be assumed that production with-in the 50-mile radius region around WNP-2 is sufficient to satisfy consumption requirements.

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

Irri ation Rate Annual Yield Growin Period

~Food T e ( liter/m /mo) (kg/m ) (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.

Table 2-3 summarizes the LADTAP II input parameters. Documentation and/or calculations of these parameters are discussed in detail in R.P.I. 2.3, and Rad. Prog. calculation Log 88-3.

18

AMENDMENT NO. 3 February 1986 2.8 Compliance with Technical S ecification 3.11.1.4 2.8.1 Maximum Allowable Li uid Radwaste Activity in Tem orary Radwaste Hold-Up Tanks The use of temporary liquid radwaste hold-up tanks is planned for WNP-2.

Technical Specification 3.11.1.4 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 the limits specified in 10 CFR Part 20 Appendix B, Table II.

Equation 18 will be used to calculate the curie limit for-a temporary radwaste hold-up tank. The total tank concentration will be limited to less than or equal to ten ((10) curies, excluding tritium and dissolved or entrained gases.

Surveillance requirement 4.11.1.4,. states that 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.

Kd (18)

T where:

AT Total allowed activity in tank (curies).

A. Activity of radioisotope i (curies).

19

AMENDMENT NO. 3 February 1986 NPC- Maximum permissible concentration of radionuclide i (10 CFR 20, Appendix B, Table II, Column 2).

Decay constant (years ) radioisotope i.

Transit time of ground water from WNP-2 to WNP-1 well (WNP-2 FSAR Section 2. 4) = 67 year s.

Fraction of radioisotope ~.

A fi =gni

~

Index for all radioisotopes in tank except tritium and noble gases.

Kd Dispersion constant based on hydrological parameters, (2.4E+05 Ci per ~Ci/cc.)

19a

AMENDMENT NO. 3 February 1986 The total allowed activity (AT) is based on limiting WNP-1 well water to less than 1 NPC.1 of the entire liquid content of the tank spilled to ground and then migrated via ground water to the WHP-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 70-85 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 in less than several hundred years. However, allowed tank activity (AT) is conser vatively based on all liquid radwaste in the tank instantaneously reaching the water table.

The hydrological analysis performed for the WHP-2 FSAR (Section 2.4) deter-mined that the transit time through the ground water from WNP-2 to the WNP-1 well is 67 years for Strontium and 660 years for Cesium. These two radio-nuclides 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.) i is simply the con-centration in the tank (CT.) adjusted for radioactive decay during transit 1

(e') and divided by the minimum concentration reduction factor (CRF min).

Limiting well concentration to 1 MPC yields:

CT. e CW.

i =Z~g i IF i 2 4 f HNP- FSA . ) f19) 1 min a a 1/2 x ) (20)

CRF . = (4 L) x Y min 2 20

AMENDMENT NO. 3 February 1986 where:

L = Migration distance = 1 mile.

V = Volume of tank.

'x'v'z Dispersion constants.

Combining Equations 19 and 20 yields:

CTl 2V e 1 1 (21)

(4+ L) (a< aY a> ) MPCi Substituting A; for CTi V and reorganizing terms yields:

3/2 1/2 (4 m L) (ax a~ a ) A.

MPC,. e

~'22)

Making the following substitutions Ai = fi AT 3/2 1/2 (4 n. L) (a ay a )

Kd

= x 10 Ci/~Ci = 2.4 x 10 Ci per uC1 (23)

CC 21

NENDHENT NO. 3 February 1986 d TZ()p~ +At l

or Kd

-Z NPC.e 2.8. 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 WNP-2, Equation 18 will be used should such tanks become necessary in the future.

Li uid Process Monitors and Alarm Set pints Calculations

~ ~

2.9

~

As mentioned in Section 2.2 of this manual, all liquid radwaste effluent is discharged through a four-inch line that is monitored by an off-line sodium iodide radiation monitor. This monitor is located on the of the Radwaste Building. All WNP-2 radwaste liquid effluent is 437'evel discharged to the Columbia River through the 36-inch Cooling Mater Blowdown line. In addition to the liquid effluent discharge monitor there are three liquid streams that are normally non-radioactive but have a finite possibility of having radioactive material injected into them.

These liquid streams are:

o Standby Service Mater (SW) o Turbine Building Ser vice Mater (TSW) o Turbine Building Sump Water (FD) 22

AMENDMENT NO. 3 February 1986 To prevent any discharges of radioactive liquid from these streams, radiation monitoring systems have been installed to detect any increase above the normal background concentration of radioactive material.

Alarm/setpoints are established to prevent any release of radioactive material in concentrations greater than 10CFR20 limits. The maximum radiation detector setpoint calculation for the three systems is based on i concentration of Cs-137 which is 2. OE-05 pCi/ml; The follow-ing equation is used to calculate the maximum setpoint:

Setpoint max. = (2.0E-05 pCi/ml) (CF) (25)

(in cpm or cps) where:

2.0E-05 pCi/ml = MPC limit for Cs-137 CF = Monitor calibration factor - in cpm/ pCi/ml or cps/ pCi/ml 2.9.1 Standby Service Water (SW) Monitor - The Standby Service Water Monitors (SW) are located on the 522'evel of the Reactor Building.

The meter is located in the main control room on panel P-604.

The flow rate through the monitor is variable, from zero (0) to two (2) gpm with a normal flow of 1.0-.1.5 gpm.

To ensure 10CFR20 limits are never exceeded, the alarm setpoint shall be established at 80% or less of the maximum setpoint plus background.

If the setpoint is exceeded, an alarm will activate in the main control room. The control room operator can then terminate the discharge and mitigate any uncontrolled release of radioactive material.

23

AMENDMENT NO. 2 February 1985 2.9.2

~ ~ Turbine Buildin Service Water (TSW) Monitor - This monitor is located on the 441 'evel of the Turbine Building. The readout meter 'and recorder is located in the main control panel BD-RAD-24.

The flow rate through that monitor is variable, from zero (0) to six (6) gpm with a normal flow of 3-4 gpm.

To ensure 10CFR20 limits are never exceeded, the alarm setpoint shall be established at 80% or less of the maximum setpoint plus background.

If the setpoint is exceeded, an alarm will activate in the main control room. The control room operator can then terminate the discharge and mitigate any uncontrolled release of radioactive material.

2.9.3 Turbine Buildin Sum s Water (FD) Monitor - There are three detec-tors to measure the activity of each of the three non-radioactive sumps. The monitors are located on the 441'evel of the Turbine Building. The readout meters and recorder are located in the Rad-waste Control Room Panel BD-RAD-41.

The Turbine Building Sump Water Effluents are not released to the Columbia River. This effluent is discharged to the Storm Drain System which is an open pond by the WNP-2 Warehouse.

The hydrological analysis performed for the WNP-2 FSAR (Section 2.4) determined that the transmit time through the ground water from WNP-2 to the WNP-1 well is 67 years for strontium and 660 years for cesium.

In the event the setpoint is exceeded, the sump water will be automatically routed to the radioactive waste system.

AMENDMENT NO. 2 February 1985 To prevent the sum of the sump water discharged from the three pumps from exceeding 10CFR20 limits, the alarm/setpoint will be estab-lished at 80% or less of the maximum setpoint plus background.

25

AMENDMENT NO. 6 November 1988 Table 2-1 FISH BIOACCUMULATION FACTORS (BF.)

1 AND ADULT INGESTION DOSE CONVERSION FACTORS (DF.)

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)

H-3 9.0E-01 6.0E-OB (3) 6.0E-OB 6.0E-OB 6.0E-OB Na-24 1.0E+02 1.7E-06 1.7E-06 1.7E-06 1.7E-06 1.7E-06 P-32 1.0E+05 7.5E-06 1.9E-04 (3) 1.2E-05 2.2E-05 Cr-51 2.0E+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 4.0E+02 2.0E-OB (3) (3) 1.2E-07 3.7E-06 Fe-55 1.Of+02 4.4E-07 2.8E-06 (3) 1.9E-06 1.1E-06 Fe-59 1.0E+02 3.9E-06 4.3E-06. (3) 1.0E-05 3.4E-05 Co-58 5.0E+Ol 1.7E-06 (3) (3) 7.5E-07 1.5E-05 Co-60 5.0E+01 4.7E-06 (3) (3) 2.1E-06 4.0E-05 Ni-65 1.0E+02 3.1E-OB 5.3E-07 (3) 6.9E-OB 1.7E-06 CU-64 5.0E+Ol 3.9E-OB (3) (3) 8.3E-OB 7.1E-06 Zn-65 2.0E+03 7.0E-06 4.8E-06 (3) 1.5E-05 9.7E-06 Zn-69m 2.0E+03 3.7E-OB 1.7E-07 (3) 4.1E-07 2.5E-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. 4.0E-08 (3) (3) (3) 5.8E-08 Br-84 4.2E+02 5.2E-08 (3) (3) (3) 4.1E-13 Rb-89 2.0E+03 2.8E-OB (3) (3) 4.0E-OB 2.3E-21 Sr-89 3.0E+01 8.8E-06 3.1E-04 (3) (3) 4.9E-05 Sr-90 3.0E+01 1.8E-04 8.7E-03 (3) (3) 2.2E-04 26

AMENDMENT NO. 6 November 1988 Table 2-1 (contd.)

Dose Conversion Factor (DF,.)

Fish Bioaccumulation Total GI Nuclide actor BF. Body Bone Thyroid Li ver Tract (pCi/kg per (mRem per pCi Ingested) pCi/liter)

Sr-91 3.0E+Ol 2.3E-07 5.7E-06 (3) (3) 2.7E-05 Sr-92 3.0E+01 9.3E-OB 2.2E-06 (3) (3) 4.3E-05 Y-90 2.5E+01 2.6E-10 9.7E-09 (3) (3) 1.0E-04 Y-91m 2.5E+01 3.5E-12 9.1E-11 (3) (3) 2.7E-10 Y-91 2.5E+Ol 3.8E-09 1.4E-07 (3) (3) 7.8E-05 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 3.0E+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 3.0E+04 4.8E-12 5.2E-11 (3) 1.3E-ll 4.9E-OB Ho-99 1.0E+Ol 8.2E-07 (3) (3) 4.3E-06 1.0E-05 Tc-99m 1.5E+Ol 8.9E-09 2.5E-10 (3) 7.0E-10 4.1E-07 Tc-101 1.5E+Ol 3.6E-09 2.5E-10 (3) 3.7E-10 1.1E-21 Ru-103 1.0E+Ol 8.0E-OB 1.9E-07 (3) (3) 2.2E-05 Ru-105 1.0E+01 6.1E-09 1.5E-OB (3) (3) 9.4E-06 Rh-105 1.0E+Ol 5.8E-OB 1.2E-07 (3) 8.9E-OB 1.4E-05 Ru-106 1.0E+Ol 3.5E-07 2.8E-06 (3) (3) 1.8E-04 Ag-110m 2.3E+00 8.8E-OB 1.6E-07 (3) 1.5E-07 6.0E-05 Sb-124 1.0E+00 1.1E-06 2.8E-06 6.8E-09 5.3E-OB B.OE-05 Sb-125 1.0E+00 4.3E-07 1.8E-06 1.8E-09 2.0E-08 2.0E-05 Sb-126 1.0E+00 4.2E-07 1.2E-06 7.0E.09 2.3E-OB 9.4E-05 Sb-127 1.0E+00 9.9E-08 2.6E-07 3.1E-09 5.7E-09 5.9E-05 Te-127 4.0E+02 2.4E-OB 1.1E-07 8.2E-08 4.0E-OB 8.7E-06 Te-129m 4.0E+02 1.8E-06 1.2E-05 4.0E-06 4.3E-06 5.8E-05 Te-129 4.0E+02 7.7E-09 3.1E-08 2.4E-OB 1.2E-OB 2.4E-08 27

AMENDMENT NO. 5 April 1988 Table 2-1 (contd.)

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)

Te-1 31m 4.0E+02 7.1E-07 1.7E-06 1.3E-06 8.5E-07 8.4E-05 Te-131 4.0E+02 6.2E-09 2.0E-OB 1.6E-OB 8.2E-09 2.8E-09 Te-132 4.0E+02 1.5E-06 2.5E-06 1.8E-06 1.6E-06 7.7E-05 I-131 1.5E+01 3.4E-06 4.2E-06 2.0E-03 6.0E-06 1.6E-06 I-132 1.5E+Ol 1.9E-07 2.0E-07 1.9E-05 5.4E-07 1.0E-07 I-133 1.5E+Ol 7.5E-07 1.4E-06 3.6E-04 2.5E-06 2.2E-06 I-134 1.5E+01 1.0E-07 1.1E-07 5.0E-06 2.9E-07 2.5E-10 I-135 1.5E+01 4.3E-07 4.4E-07 7.7E-05 1.2E-06 1.3E-06 Cs-134 2.0E+03 1.2E-04 6.2E-05 (3) 1.5E-04 2.6E-06 Cs-136 2.0E+03 1.9E-05 6.5E-06 (3) 2.6E-05 2.9E-06 E

Cs-137 2.0E+03 7.1E-05 B.OE-05 (3) 1.1E-04 2.1E-06 Cs-138 2.0E+03 5.4E-OB 5.5E-OB (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-OB 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+Ol 1.6E-11 3.2E-10 (3) 9.9E-11 1.2E-05 La-142 2.5E+01 1.5E-11 1.3E-10 (3) 5.8E-ll 4.3E-07 Ce-141 1.0E+00 7.2E-10 9.4E-09 (3) 6.3E-09 2.4E-05 Ce-143 1.0E+00 1.4E-10 1.7E-09 (3) 1.2E-06 4.6E-05 Ce-144 1.0E+00 2.6E-OB 4.9E-07 (3) 2.0E-07 1.7E-04 Pr-143 2.5E+Ol 4.6E-10 9.2E-09 (3) 3.7E-09 4.0E-05 Nd-147 2.5E+Ol 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 28

ANENDHENT NO. 5 April 1988 Table 2-1 (contd.)

Dose Conversion Factor (DF;)

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

W-187 1.2E+03 3.0E-OB 1.0E-07 (3) 8.6E-08 2.8E-05 Np-239 1.0E+Ol 6. 5E-1 1 1.2E-09 (3) 1 .2E-'lO 2.4E-05 NRC NUREG/CR-4013.

NRC NUREG/CR-4013.

No data listed in NUREG/CR-4013.

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

28a

AHENDHENT NO. 6 November 1988 Table 2-2 INGESTION DOSE FACTORS (A . FOR TOTAL BODY AND CRITICAL ORGAN (in mrem/hr per Ci/ml)

Liquid Effluent Total Gi Nuclide ~Bod Bone ~Th roid 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.BE+06 4.6E+07 2.9E+06 5.3E+06 Cr-51 1.3E+00 7.7E-01 3.2E+02 Hn-54 8.3E+02 4.4E+03 1.3E+04 Hn-56 1.9E+Ol 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 1.0E+03 2.4E+03 8.2E+03 Co-58 2.1E+02 9.0E+Ol 1.BE+03 Co-60 5.7E+02 2.5E+02 4.BE+03 Ni-65 7.5E+00 1.3E+02 1.7E+Ol 4.1E+02 Cu-64 4.7E+00 1.0E+Ol 8.6E+02 Zn-65 3.4E+04 2.3E+04 7.2E+04 4.7E+04 Zn-69m 1.BE+02 8.1E+02 2.0E+03 1.2E+05 As-76 1.2E+03 1.1E+04 Br-82 2.3E+03 2.6E+03 Br-83 4.0E+01 5.BE+01 Br-84 5.2E+01 4.1E-04 Rb-89 1.3E+02 1.9E+02 1.1E-ll 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+Ol 4.1E+02 2.0E+03 Sr-92 6.BE+00 1.6E+02 3.1E+03 29

~

J f

I

)l

AMENDMfNT NO. 6 November 1988 Table 2-2'(contd.)

Total Gi Nuclide ~Bod Bone ~Th roid Liver Tract 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 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.BE+02 Nb-97 3.5E-01 3.7E+00 ** 9.3E-01 3.5E+03 Mo-99 2.0E+Ol 1.1E+02 2.5E+02 Tc-99m 3.3E-01 9.2E-03 2.6E-02 1.5E+Ol Tc-101 1.3E-01 9.2E-03 1.4E-02 4.0E-14 Ru-103 2.0E+00 4.7E+00 5.5E+02 Ru-105 1.5E-01 3.7E-01 2.3E+02 Rh-105 1.4E+00 3.0E+00 2.2E+00 3.5E+02 Ru-106 8.7E+00 6.9E+01 4.5E+03 Ag-llOm 5.6E-01 1.0E-OO 9.5E-Ol 3.BE+02 Sb-124 3.6E+00 9.0E+00 2.2E-02 1.7E-Ol 2.6E+02 Sb-125 1.4E+00 5.BE+00 5.8E-03 6.5E-02 6.5E+Ol Sb-126 1.4E+00 3.9E+00 2.3E-02 7.4E-02 3.0E+02 Sb-127 3.2E-01 8.4E-Ol 1.0E-02 1.8E-02 1.9E+02 Te-127 2.3E+Ol 1.1E+02 7.9E+Ol 3.BE+01 8.3E+03 Te-129m 1.7E+03 1.2E+04 3.BE+03 4.1E+03 5.6E+04 Te-129 7.4E+00 3.0E+01 2.3E+Ol 1.2E+01 2.3E+01 Te-131m 6.BE+02 1.6E+03 1.3E+03 8.2E+02 8.1E+04 Te-131 5.9E+00 1.9E+Ol 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 I-131 1.3E+02 1.5E+02 7.4E+04 2.2E+02 5.9E+Ol I-132 '7.0E+00 7.4E+00 7.0E+02 2.0E+Ol 3.7E+00 I-133 2.BE+01 5.1E+01 1.3E+04 9.2E+Ol 8.1E+Ol I-1 34 3.7E+00 4.Of+00 1.BE+02 1.1E+Ol 9.2E-03 I-135 1.6E+Ol 1.6E+Ol 2.BE+03 4.4E+01 4.BE+01 30

AMENDMENT NO. 6 November 1988 Table 2-2 (contd.)

Total Gi Nuclide ~Bod Bone ~Th roid Liver Tract Cs-134 5.BE+05 3.0E+05 7.2E+05 1.3E+04 Cs-136 9 'E+04 3.1E+04 1.3E+05 1.4E+04 Cs-137 3.4E+05 3.BE+05 5.3E+05 1.Of+04 Cs-138 2.6E+02 2.6E+02 5.3E+02 2.3E-03 Ba-139 2.9E-02 1.0E-OO 7.2E-04 1.BE+00 Ba-140 1.4E+01 2.1E+02 2.7E-01 4.4E+02 La-140 2.0E-02 1.5E-01 7.9E-02 5.6E+03 La-141 9.7E-04 1.9E-02 6.0f-03 7.3E+02 La-142 9.1E-04 7.9E-03 3.5E-03 2.6E+01 Ce-141 2.3E-03 3.0E-02 2.0E-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-Ol 5.5E+02 Pr-143 2.8E-02 5.6E-Ol 2.3E-Ol 2.4E+03 Nd-147 2.7E-02 3.8E-01 4.4E-Ol 2.1E+03 Hf-179m 4.2E+01 3.6E+02 Hf-181 3.BE+01 3.6E+02 M-185 4.0E+Ol 1.2E+03 4.0E+02 4.6E+04 M-187 8 'E+Ol 2.9f+02 2.5E+02 8.1E+04 Np-239 1.6E-03 '3.0E-02 3.0E-03 6.0E+02

- No Ingestion Dose Factor (DF.) is 1

listed in NUREG/CR-4013. (Total body dose factor value Mill be used as an approximation.)

31

AMENDMENT NO. 6 November 1988 TABLE 2-3 INPUT PARAMETERS USED TO CALCULATE MAXIMUM INDIVIDUAL DOSE FROM LI UID EFFLUENTS 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 Boatin and A uatic Food River Dilution: 2,000 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: Adul t 18 hr/yr Teenager 100 hr/yr Child 21 hr/yr Irri ated 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 Ve etables Milk Meat Ve etables 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 1/m~ 200 1/m2 160 1/m2 200 1/m2 Annual Yield: 5.0 kg/m2 1.3 1/m2 2.0 kg/m2 1.5 kg/m2 Annual Growing Period: 70 days 30 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 32

AMENDMENT NO. 6 November 1988 COOLING TOWER SUMPS BLQWDQWN LINE WASTE WASTE RADVASTE BLDG SURGE TURBINE BLDG SAMPLE AND TANKS DRYWELL COLLECTOR (TWQ)

TANKS FLOOR DRAIN FLOOR COLLECTOR DRAIN MISC VASTE TANK SAMPLE TANK REACTOR BLDG DISTILLATE TANKS

<TVQ)

DETERGENT DRAIN TANKS FILTERS 8 DEHINERAL-IZERS

<STOLID WASTE> CHEHICAL VASTE TANKS SHOP DECQN CONDENSATE CHEM PUMPS STORAGE DECQN DRAIN PLANT TANKS REACTOR BLDG USE (TWQ)

TURBINE BLDG COLUMBIA RIVER SIMPLIFIEH BLOCK DIAGRAM OF LIQUID VASTE SYSTEM FIGURE 2-1 32a

S AMENDMENT NO. 6 November 1988 DEMINERALIZERS Condensate RWCU Phase Dewatering Di sposal EDR/FDR Separator Liners Site Radwaste Bead Dry Active Compactor. Disposal Waste Site SIMP L IF I ED B LOCK DIAGRAM OF SOLID RADWASTE SYSTEM Figure 2-2 32b

3.0 GASEOUS EFFLUENTS DOSE CALCULATIONS 3.1 Introduction WNP-2 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. The gaseous effluents released from WNP-2 will meet instanta-neous technical specification requirement at the site boundary.

Figure 3-1 delineates the WNP-2 Site boundary. There are several low occupancy unrestricted locations within the site boundary. These locations, with the exception of the WNP-2 visitor center, are not continuously controlled by the Supply System. The special locations are:

1. Wye burial site - normally controlled by DOE.

2. DOE train - two railroad lines pass through the site (approximately 3 miles of line). According to. DOE, the train makes one round trip a day, through the site at an average speed of 20 mph, 5 days a week, 52 weeks/year.

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 the Supply System but are involved in activ-ities directly in support of WNP-2.

4. WNP-2 - Supply System Visitor Center - assumed occupied 8 hrs/yr by non-Supply System individuals.

5. WNP-1 - occupied 2080 hrs/yr. This location is controlled by the Supply System. However, activities are not in direct support of WNP-2.

6. WNP-4 - occupied 2080 hrs/yr. This location is controlled by the Supply System. However, activities are not in direct support of WNP-2.

33

AHENDHENT NO. 6 November 1988 All other locations listed in Figure 3-1 support WNP-2 activities and are controlled by the Supply System. 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.

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 to 3-12). These doses are listed in Tables 3-16 and 3-17 along with the doses to the maximum exposed individual.

The most likel ex osed member of the ublic is considered to be residing in Taylor Flats (4.2 miles ESE of WNP-2). This is the closest residential area with the high- est X/Q and D/Q values.

3.2 Gaseous Effluent Radiation Honitorin S stem 3.2.1 Hain Plant Release Point The Hain Plant Release is instrument monitored for gaseous radioactivity prior to discharge to the environment via the main plant vent release point.

Particulates and iodine activity are accumulated in filters which will be changed and analyzed as per Technical Specification 4.11.2.1.2 and Table 4.11.2. 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.

Two 100-percent capacity vanaxial fans supply 98,000 CFH ventilation air. One is normally operating the other is in standby. The radiation monitors are located on the ventilation exhaust plenum.

Effluent monitoring consists of a low range beta scinti llator, an intermediate range beta scintillator and two ion chamber LOCA monitors. The beta scinti llators are mounted in thick lead shielded chambers. The low range beta scintillator has an approximate response of 80 cpm/pCi/cc to Kr-85, and 50 cpm/pCi/cc to Xe-133 and a meter range of 10-10 cpm. The intermediate 34

0 AHENDHENT NO. 6 November 1988 10 3 range has a response from 10 .qCi/cc Xe -133 equivalent, and reads with a meter range of 10 0 -10 PHU.

5 in panel meter units (PHU)

The readouts and recorder are located in the main control room panel BD-RAD-24. Power is provided from 125 VDC divisional buses. This monitor has no control function but annunciates in the main control room. The alarm will initiate proper action as deFined in the WNP-2 Plant Procedures.

3.2.2 Radwaste Buildin Ventilation Exhaust Honitor The radwaste building ventilation exhaust monitoring system monitors the radio-activity in the exhaust air prior to discharge. Radioactivity can originate from: radwaste tank vents, laboratory hoods, and various cubicles housing liquid process treatment equipment and systems.

The radwaste building exhaust system has three 50 percent capacity exhaust filter units of 42,000 cfm capacity. Each exhaust unit has a medium-efficiency preFilter, a high efficiency particulate air filter (HEPA) and two centrifugal fans. Total exhaust flow will vary as the combined exhaust unit maintains a radwaste building differential pressure of -0.25 inches H20 to the environment.

Particulate and iodine air sample filters are changed weekly for laboratory analysis. After the particulate and iodine filters, the air sample streams are combined in a manifold prior to being monitored by a beta scintillator.

The beta scinti llators, on the 487'evel are mounted in lead shielded chambers. The low range beta scintillator has an approximate response of 80 cpm/pCi/cc to Kr-85, and 50 cpm/pCi/cc to Xe-133 and a meter range of 6 10 3 10-10 cpm. The intermediate range has a response from 10 pCi/cc Xe -133 equivalent, and reads in panel meter units (PHU) with a meter range of 10 -10 PHU. The readouts and recorder are located in the main control room panel BD-RAD-24. Power is provided From 125 VDC divisional buses. This monitor has no control functions but annunciates in the main control room.

The alarm will initiate proper action as defined in the WNP-2 plant procedures.

35

AMENDMENT NO. 6 November 1988 3.2.3 Turbine Bui ldin 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.

The turbine building main exhaust system consists of Four roof-mounted centri-fugal fans which draw air from a central exhaust plenum. Three fans operate continuously, with one in standby to provide a flow of 260,000 cfm.

A representative sample is extracted from the exhaust vent and passed through a particulate and charcoal filter. The air sample then passes to a beta scintillator.

The beta scintillators are mounted in lead shielded chambers. The low range beta scinti llator has an approximate response of 80 cpm/pCi/cc to Kr-85, and 50 cpm/pCi/cc to Xe-133 and a meter range of 10-10 cpm. The intermediate

-2 3 range has a response from 10 10 pCi/cc Xe -133 equivalent, and reads in panel meter, units (PMU) with a meter range of 10 10 PMU. The monitors are on the 525'evel of the radwaste building and the readouts and the recorder are located in the main control room panel BD-RAD-24. Power is provided from the 125 VDC divisional buses. This monitor has no control functions but annunciates in the main control room. The alarm will initiate proper action as defined in the NNP-2 plant procedures.

3.3 10 CFR 20 Release Rate Limits Limits for release of airborne efFluents to the unrestricted area are stated in Technical Specification 3.11.2.1. The dose rate in unrestricted areas due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:

(a) "The dose rate limit for noble gases shall be <500 mrem/yr to the total body and <3000 mrem/yr to the skin.

(b) "The dose rate limit for all radioiodines and for all radio-active materials in particulate form and radionuclides other than noble gases with half-lives greater than eight days shall be < 1500 mrem/yr to any organ."

36

AMENDMENT NO. 6 November 1988 3.3.1 Noble Gases In order to comply with Technical Specification 3.11.2.1, the following equa-tions must hold:

Nhole body:

Z Ki [(X/Q) Q. + (X/Q) Q.

)] < 500 mrem/yr (1) 1 Skin

[(L. + 1.1H.)((X/0) Q. + (X/0) < 3000mrem/yr (2)

Q. )]

3.3.2 Radioiodines and Particulates Part "b" of Technical Specification 3.11.2.1 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:

gP [((< Q; + (t) 0; ] m)500 mrem/yr (3) 1 The terms used in equations 1 through 3 are defined as follows:

K.

1

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

L.

1

= The skin dose factor due to beta emissions for each iden-tified noble gas radionuclide i (mrem/yr per uCi/m ).

37

NENDNENT NO. 3 February 1986 The air dose factor due to gamma emissions for each identified noble gas r adionuclide in mrad/yr per pCi/m (unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose).

The dose parameter for all radionuclides other than noble 3

gases for the inhalation pathway, (mrem/yr per pCi/m )

and for food and ground plane pathways, m2 (mrem/yr per vCi/sec). The dose factors are based on the critical individual organ and the most restrictive age group.

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

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

(M)m (sec/m ). For partially elevated mixed mode releases from the main plant vent release point. The highest calculated partially elevated annual average relative concentration for any area at or beyond the site boundary.

(sec/m3). For all Turbine Building and Radwaste releases. The highest calculated ground level annual average relative concentration for any area at or beyond the site boundary.

38

AMEHDfdEHT HO. 3 February 1986 The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location due to all ground level releases.

(sec/m ). For the inhalation pathway. The location is the site boundary in the sector of maximum concentration.

W m . For ground plane pathways. The location g

is the site boundary in the sector of maximum

'I concentration.

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

W)) sec/m ; For inhalation pathway. The location is the site boundary in the sector of maximum concentration.

m . For ground plane pathways. The location is 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-l of Regulatory Guide 1.109, Revision 1, and in Table 3-1 of this manual.

The ~ values used in the equations Specification 3.11.2.1 are based upon for the implementation of Technical the maximum long-term annual average at the site boundary. The distances between the nearest unrestricted area and the WHP-2 site are listed in Table 3-2. The distances between WHP-2 and the nearest vegetable garden, milk cow, and beef animal are tabulated in Table 3-3, along with representative X/Q and D/Q values.

39

NENDMENT NO. 3 February 1986 The X/Q and D/Q values listed in Tables 3-10 through 3-12 reflect correct ac-quired meteorological data up to 1983 and were utilized in the initial GASPAR Computer runs. Subsequent reports will use updated X/Q and D/Q averages Char-acteristics of WNP-2 gaseous effluent release points are listed in Table 3-13.

3.3.2.1 Dose Parameter for Radionuclide i (P.)

The dose parameters used in Equation 3 are based on:

l. Inhalation and ground plane. (Note: Food pathway is not applicable to WNP-2 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.

Calculation of P.

1

( Inhalation): The following equation will be used to calcu-late I (Inhalation).

P.

P.I = KA (BR) DFA. 3 (Inhalation) (mrem/yr perpCi/m )

40

Al1ENDNENT NO. 3 February 1986 where:

K = A constant of conversion, 10 pCi/pCi.

3 BR = The breathing rate of the child age group, 3700 m /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 DFA..

The inhalation dose factor for DFA.1 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:

3 P. = (Inhalation) = (3.7 x 10 9 )(DFA.) (mrem/yr per pCi/m ) (6)

The P ~ (Inhalation) values for the child age group are tabulated in Table 3-4 1

of this manual.

3.4 10 CFR 50 Release Rate Limits The requirements pertaining to 10 CFR 50 release rate limits are specified in Technical Specifications 3.11.2.2 and 3.11.2.3.

Technical Specification 3.11.2.2 deals with the air dose from noble gases and requires that the air dose at or beyond the site boundary due to noble gases released in gaseous effluents shall be limited to the following:

(a) "During any calendar quarter, to <5 mrad for gamma radiation and to <10 mrad for beta radiation."

(b) "During any calendar year, to <10 mrad for gamma radiation and <20 mrad for beta radiation."

41

01ENDI1ENT NO. 3 February 1986 Technical Specification 3.11.2.3 deals with radioiodines and radioactive mate-rials in particulate form, and requires that the dose to an individual from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases 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, to <7.5 mrem."

(b) "During any calendar year, to <15 mrem."

3.4.1 Noble Gases (Technical S ecification 3.11.2.2)

The air dose at or beyond the site boundary due to noble gases released in the gaseous effluent will be determined by using the following equations.

a. During any calendar quarter, for gamma radiation:

3.17 x 10 g }(. t()(/0) 0. + (X/q) q. + ()(/(}) (}. + (X/q) q. ]~5 mrad (8)

During any calendar quarter, for beta radiation:

3.17 x 10 Z 1 N. C()(7(}) 0 + (X/q) q + (t/( (}. + (X/q) q. ]<10 mrad (9)

b. During any calendar year, for gamma radiation:

3.17 x 10 Z 1

                    }(. [()(/(}) 0.    +   (X/q) q.     +   (X7(}) 0.    + (X/q) q.  ]s10  mrad (10)

NENDHENT NO. 3 February 1986 During any calendar year, for beta radiation: 3.17 x 10 Zi N (770) (}. + (X/q) q. + ('V}') (). + (X/q) q. w 20 mrad (ll) where: M. 1

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

1 N. 1

                    =  The  air dose   factor due to beta emissions for each iden-tified noble gas radionuclide, in mrad/yr per pCi/m (N.1 values are listed in Table 3-1).

For ground level release points. The highest calculated annual average relative concentration for area at or beyond the site area boundary for long-term releases 3 (greater than 500 hr/yr). (Sec/m ) (X/q) For ground level release points. The relative concentration for areas at or beyond the site area boundary for short-term releases (equal to or less than 3 500 hr/yr). (Sec/m ) For partially elevated release points. The highest calculated annual average relative concentration for areas at or beyond the site boundary for long-term 3 releases (greater than 500 hr/yr). (Sec/m ) (X/q) For partially elevated release points. The relative concentration for areas at or beyond the site boundary for short-term releases (equal to or less than 3 500 hr/yr). (Sec/m ) 43

AMENDMENT NO. 6 November 1988 qim 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 pCi. Releases shall be cumulative over the calendar quarter or year, as appropriate. The average release of noble gas radionuclides in ig 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.

               ')im         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 I

calendar quarter or, year, as appropriate. 0;g 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 pCi. Releases shall be cumulative over the calendar quarter or year, as appropriate. 3.17 x 10 = The inverse of the number of seconds in a year. 3.4.2 Radioiodines Tritium and Particulates Technical S ecification 3.11 '.3 The following equation calculates the dose to an individual from radioiodines, tritium radioactive material in particulate form, and radionuclides other than noble gases with half-lives greater than eight days in gaseous effluents released to the unrestricted areas: 44

NENDHENT NO. 3 February 1986

a. During any calendar quarter:

3.17 x10 Zi R.IW 0. +w q. +W 0. +w q. I<7.5mrem (12)

b. During any calendar year:

3.17 x 10 g R. W 0. + w q. + W 0. + w q. I < 15 mrem (13) where: Oim Pig The releases of radionuclides, 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 pCi. Releases shall be cumu-lative over the calendar quarter or year, as appropriate (m is for mixed mode releases, g is for ground level releases). qim qig The releases of radionuclides, 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). 45

NENDHENT NO. 3 February 1986 M M The disper sion parameter for estimating the dose to an individual at the controlling location for long-term ( ) 500 hr.) releases (m is for mixed mode releases, g is for ground level releases). M = (X7g) for the inhalation pathway, in sec/m . M = (579) for the food and ground plane pathways in

                               -2 meters w  w       The    dispersion parameter for estimating the dose to an m, g individual at the controlling location for short-term

( g 500 hr.) releases (m is for mixed mode releases, g is for ground level releases). w = (77q) for the inhalation pathway, in sec/m . w = (D7q) for the food and ground plane pathways in

                               -2 meters 3.17 x 10    = The    inverse of the number of seconds in     a year.

R. = The dose factor for each identified radionuclide, i, in 2 3 m (mrem/yr per I Ci/sec) or mrem/yr per pCi/m . 46

AMENDMENT NO. 6 November 1988 3.4.2.1 Dose Parameter for Radionuclide i (R.) The R. values 1 used in equations 12 and 13 of this section are calculated separately For. each of the following potential exposure pathways: o Inhalation Ground plane contamination Grass-cow/goat-milk pathway Grass-cow-meat pathway Vegetation pathway Monthly dose assessments for WNP-2 gaseous effluent will be done for all age groups. Calculation of R.l (Inhalation Pathway Factor) I (Inhalation) R. = K I (BR) (OFA.) (mrem/yr per pCi/m 3 (14)

where: RI The inhalation pathway factor (mrem/yr per pCi/m ). 1 A constant of unit conversion, 10 pCi/pCi. (BR) The breathing rate of the receptor of age group (a) in meter 3 /yr. (Infant = 1400, child = 3,700, teen = 8,000, adult = 8,000. From P.32 NUREG-0133). 47

AMENDMENT NO. 6 November 1988 (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 (DFAi)a. (DFAi)a values are listed in Tables E-7 through E-10 of Regulatory Guide 1.109 manual, Revision 1 and NUREG/CR-4013. Values of R. are listed in 1 Table 3-5. Calculation of R. (Ground Plane 1 Pathway Factor) G A 8 1 2 R.(Ground Plane) = K K (SF)(DFG.) (1-e )/X ~ (m x mrem/yr per vCi/sec) (15) where: G R. l

            =  Ground plane pathway      factor   (m    x mrem/yr    per vCi/sec).

K A = A conversion constant of (10 6 pCi/uCi). B K = A conversion constant (8760 hr/yr). 1 The decay constant for the ith radionuclide (sec ). t = Exposure time, 6.31 x 10 8 sec (20 years). DFG. 1

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

SF = Shielding Factor (dimensionless) 0.7 if building is present, as suggested in Table E-15 of Regulatory Guide 1.109, Revision 1. 48

G The values of R. are 1 listed in Table 3-5 of this manual. r C Calculation of R. (Grass-Cow/Goat-Milk Pathway Factor) 1 C = R. (Grass-Cow/Goat-Milk Factor) 1

               ,q(u       )                         (1-f f  )e
                      +Xm i(F (     FL-)

i a Y Y (16) (m2 x mrem/yr per PCi/sec) where: 6 K A constant of unit conversion, 10 pCi/>Ci. The cow/goat consumption rate, in kg/day (wet weight). U The receptor's milk consumption rate for age (a), in liters/yr. Y The agricultural productivity by unit area of pasture feed grass, in kg/m 2 . Y s The agricultural productivity by unit area of stored feed, kg/m2 Fm

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

r = Fraction of deposited activity retained on feed grass. 49

AMENDMENT NO. 6 November 1988 (DFL ) The maximum organ ingestion dose factor for the ith radio-nuclide for the receptor in age group (a), in mrem/pCi (Tables E-ll to E-14 of Regulatory Guide 1.109, Revision 1 and NUREG/CR-4013). The decay constant for the ith radionuclide, in sec The decay constant for removal of activity on leaf and

                                                                  -7     -1 plant surfaces by weathering, 5.73 x 10 sec            (cor-responding to     a 10-day  half-life).

tf = The transport time from pasture to animal, to milk, to receptor, in sec. th = The transport time from pasture, to harvest, to animal, to milk, to receptor, in sec. Fraction of the year that the cow/goat is on pasture (dimensionless). fs Fraction of the cow/goat feed that is pasture grass'while the cow is on pasture (dimensionless). NOTE: For radioiodines, multiply R. value by 0.5 to obtain the amount of elemental iodi3e present. The input parameters used for calculating R. 1 are listed in Table 3-6 and the H R,. values are tabulated in Table 3-7. For Tritium: In calculating RT, pertaining to tritium in milk, the airborne concentration rather than the deposition will be used: C R T (Grass-Cow/Goat-Milk Factor) = AC l 1 (mrem/yr per >Ci/m3 )

K K F (} U (DFL.) ~0.75(0.5/H)] (17) 50

where:

      ,  K        =  A   constant unit conversion, 10     pCi/pCi.

constant of unit conversion, 10 3 gm/kg.

                                         ~         ~

C = K A H = Absolute humidity of the atmosphere, in gm/m . 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. M Calculation of R. (Grass-Cow-Meat Pathway Factor) 1 M = R. (Grass-Cow-Meat 1 Factor) OF(U ) (1-f f,) h -X 1 tf K ~> F<(r) (DFL.) (l8) 1 w (m2 x mrem/yr per vCi/sec) where: K = A constant unit conversion, 10 6 pCi/pCi. The stable element transfer coefficients, in days/kg. Ua = The receptor's meat consumption rate for age (a), in kg/yr. 51

AHENOHENT NO. 6 November 1988 tf = The transport time from pasture to receptor, in sec. h The transport time from crop field to receptor, in sec. NOTE: For radioiodines, multiply R. value by 0.5 to obtain the amount of elemental iodine preshnt. The input parameters needed for solving equation 18 are listed in Table 3-7. For Tritium: In calculating the RT for tritium in meat, the airborne concentration is used rather than the deposition rate. The following equation is used to calculate the R T values for tritium: H R (Grass-Cow-Heat Pathway) = T K K FfgU (DFL.) 0.75(0.5/H) (mrem/yr per pCi/m ) (19) Where the terms are as defined in equations 16-18, R. values for tritium pertaining to the infant age group is zero since there is no meat consumption by this age group. Calculation of R.l (Vegetation Pathway Factor) V = R. 1 (Vegetation Pathway Factor) 1 L

                                                               -X   th ULf            USf      1 (2O) aL             ag 2

(m x mrem/yr per >Ci/sec) 52

AMENDMENT NO. 6 November 1988 where: b A constant of unit conversion, 10 pCi/uCi. U a

         =   The consumption     rate of fresh leaFy vegetation by the receptor in  age  group (a), in kg/yr.

U a

         =   The consumption     rate of stored vegetation by the receptor in age 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 local ly. t = 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/m . NOTE: For radioiodines, multiply R. value by 0.5 to obtain the amount of elemental iodine present. All other items are as defined in equations 16-18. For Tritium: In calculating the RT for tritium, the concentration of tritium in vegetation is based on airborne concentration rather than the deposition rate. The fol-lowing equation is used to calculate R T for tritium: 53

NENDMENT NO. 3 February 1986 R T (Vegetation Pathway Factor) = K K U fL + U f (DFL ) 0.75(0.5/H) (mrem/yr per pCi/m ) (21) Where all terms have been defined above and in equations 16-18, the R. value for tritium is zero for the infant age group due to zero vegetation consump-tion rate by that age group. The input parameters needed for solving equations 20 and 21 are listed in Table 3-8. 3.4.3 Annual Doses At S ecial 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 radio-active 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 loca-tions using the NRC GASPAR 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. Of the locations listed within the site boundary, only two, the DOE Train and MNP-2 Visitor Center are considered as being occupied by a "Member of the Public". Annual doses to the maximum exposed "t1ember of the Public" shall be determined for an individual at the WNP-2 Visitor Center based on occupancy of 8 hours per year due to it being the higher of the two locations. 3.5 Com liance with Standard Technical S ecification 3.11.2.4 Standard Technical Specification 3.11.2.4 states:

           "The  GASEOUS RADMASTE TREA1MENT SYSTEM    shall be  in opera-tion in either the    normal or charcoal bypass mode. The charcoal bypass mode shall not be used unless the offgas post-treatment radiation monitor is OPERABLE as specified in Table 3.3.7.11-1."
           "APPLICABILITY: Whenever the' main condenser     steam  jet air yt           p

AMENDMENT NO. 5 April 1988 Prior to placing the Gaseous Radwaste Treatment System in the charcoal bypass mode, the alarm setpoints on the main plant vent release monitor shall be set to account for the increased percentages of short-lived noble gases. Noble gas percentages shall be based either on actual measured values or on primary coolant design base noble gas concentration percentages adjusted For 30-minute decay. Table 3-15 lists the percentage values for 30-minute decay. 3.5.1 Pro'ection of Doses The projected doses due to WNP-2 gaseous effluent releases will be determined at least once per 31 days as stated in Technical Specification 3.11.2.5. The projected dose when averaged over 31 days is not to exceed 0.3 mrem to any organ in a 31 day period to areas at and beyond the site boundary. Dose projection values will be determined by using a previous 31 day "Gaspar Output" (NRC Computer Code) for the site boundary and/or an area beyond the site boundary. Based on operating data, the projected dose should be adjusted accordingly to compensate for those anticipated changes in operations and/or source term values. 3.6 Calculation of Gaseous Effluent Monitor Alarm Set pints 3.6.1 Introduction The following procedure used to ensure that the dose rate in the unrestricted areas due to noble gases in the WNP-2 gaseous effluent do not exceed 500 5<a

ANENDNENT NO. 6 November 1988 mrem/yr to the whole body or 3000 mrem/yr to the skin. The initial setpoints determination is calculated using a conservative radionuclide mix obtained from the NNP-2 GALE code. Once the plant is operating and sufficient measur-able process fission gases are in the effluent, then the actual radionuclide mix will be used to calculate the alarm setpoint. 3.6.2 Set oint Determination for all Gaseous Release Paths The setpoints for gaseous effluent are based on instantaneous noble gas dose rates. Sampling and analysis of radioiodines and radionuclides in particulate form will be performed in accordance with technical specifications to ensure compliance with 10 CFR 20 and 10 CFR 50 Appendix I limits. The three release points will be partitioned such that their sum does not exceed 100 percent of the limit. Originally, the setpoints will be 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 technical specifica- tion. Both skin dose and whole body setpoints wi 11 be calculated and the lower limit will be used. 3.6.2.1 Set pints Calculations Based on Nhole Bod Dose Limits The fraction ( " i) 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: N. ~ ij (dimensionless) (22) NT. where: N.. = individual concentration oF radionuclide i in the lj The measured gaseous effluent release path j (pCi/cc). 55

AMENDMENT NO. 6 November 1988 HT. Tj

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

Based on Technical Specification 3.11.2.1, the maximum acceptable release rate of all noble gases in the gaseous effluent release path j is calculated by using the following equation: F'00 QT>

                             =          m                 (u Ci/sec)                    (23)

X/Q ~ gi = 1 (Ki)( m.j) where: QTJ

              =  The maximum   acceptable   release rate (q Ci /sec) of al 1 noble gases in the gaseous effluent release path j (qCi/cc).

Fj = Fraction of total dose allocated to release path j. 500 = Nhole body dose rate limit of 500 mrem/yr as specified in Tech-nical Specification 3.11.2.1a. Maximum normalized diffusion coefficient of effluent X/Q j

release path j at the site boundary (sec/m ). Turbine Building and Radwaste Building values are based on average annual ground level values. Hain plant vent release values are for mixed mode and may be either short term or average annual value dependent upon type of release. K. 1

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

56

AMENDMENT NO. 6 November 1988 defined in equation 22. lj As m = Total number of radionuclides in the gaseous effluent. j = Oifferent release pathways. The total maximum acceptable concentration (CT-) of noble gas radionuclides in the gaseous effluent release path j (>Ci/cc) will be calculated by using the following equation: OT.

                                            =                                           (24)

R. (1IC1/CC) C . Tj where: CT. Tj

            =   The  total allowed concentration of all noble gas radionucl ides in the gaseous ef fluent release path j (pCi/cc) .

0T. Tj

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

R. = The ef Fluent release rate (cc/sec) at the point of release. j To determine the maximum acceptable concentration (C,.-) of noble gas radio-nuclide i in the gaseous effluent for each individual noble gas in the gaseous eFFluent (vCi/cc), the following equation will be used: C,. ~ = ~ .CT. (qCi/cc) (25) 57

where: ij,

~..

TJ are as and CT~ defined in equations 22 and 24 respectively, the gaseous effluent monitor alarm setpoint will then be calculated as follows: m C.R.j = Q C..E.. (cpm) (26) where: C.R.j = Count rate above background (cpm) for gaseous release path j. The maximum acceptable concentration of noble gas nuclide i in the gaseous effluent release path j. >Ci/cc. ij Detection efficiency of the gaseous effluent monitor j for noble gas i (cpm/pCi/cc). 3.6.2.2 Setpoints Calculations Based on Skin Dose Limits The method for calculating the setpoints to ensure compliance with the skin dose limits specified in Technical Specification 3.11.2.la is similar to the one described for whole body dose limits (Section 3.6.2.1 of this manual), except Eq. 27 will be used instead of Eq. 23 for determining maximum accept-able release rate (QT.). Fj 3000

                     =
                                            +                   (PCi/sec)                    (27)

QT~ (X/Q ) (L 1~ ) (

i = 1 1 )

                                         ~ 58

AMENDMENT I'JO. 3 February 1986 where: The maximum acceptable release rate of all noble gases in the gaseous effluent release path j in pCi/sec. X/()j = The maximum annual normalized diffusion coefficient for release path j at the site boundary (sec/m ). F. = Fraction of total allowed dose. j L. 1 The skin dose factor due to beta emission for each identified noble gas radionuclide i in mrem/yr per pCi/m (L.1 values are listed in Table 3-1). M. i

            = The  air  dose  factor due to gamma emmissions for each identified noble gas radionuclide, in mrad/yr per pCi/m (M.1 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 Technical Specification 3.11.2.1. 59

le 3-1 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS* Total Body Gamma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor K. M. N. Radionuclide (mrem/yr per qCi/m ) (mrem/yr per pCi/m ) (mrad/yr per pCi/m ) (mrad/yr per pCi/m ) Kr-85m 1.17E+03** 1.46E+03 1. 23E+03 1.97E+03 Kr-85 1.61E+Ol 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

     +The  listed   dose factors are for radionuclides that   may be   detected in gaseous effluents.                lD cr m j
   ~7.56E-02      = 7.56 x 10 2.                                                                                     C  C7 The values     listed  above ivere taken from Table B-1 of NRC Regulatory Guide 1.109, Revision 1.      The  values 6                       -1      .        . -1                                               lO R

>vere multiplied by 10 to convert picocuries to microcuries

AMENDMENT NO. 6 November 1988 Table 3-2 DISTANCES (MILES) TO CONTROLLING LOCATIONS AS MEASURED FROM CENTER OF WNP-2 CONTAINMENT BUILDING* Location Distance Sector Comments (miles) Site Boundary 1.2 SE Air dose measurement. Taylor Flats 4.2 ESE The nearest significant residence in the southern direction with vegetable gardens, milk, and meat production. Ringol d 4.0 ENE The nearest significant residence in the northern direction with vegetable gardens, milk, and meat production.

    *Selection of location sector is  based  on the highest annual average X/Q values.

61

Table 3-3 MNP-2 ANNUAL AVERAGE DISPERSION (X/Q) AND DEPOSITION D/ VALUES FOR SPECIAL LOCATIONS X/Q X/Q X/Q 2.3 Days 8.0 Days No Decay Decay Decay Location Sector Distance Point of Release No De letion No De letion De leted D/ (miles) (sec/m ) (sec/m ) (sec/m ) (m ) Site Boundary SE 1.2 Containment Bldg. 1.8E-06 1.8E-06 1. 6E-06 1. OE-08 Turbine Bldg. 1.1E-05 1.1E-05 1.0E-05 8.3E-OB Radwaste Bldg. 1.1E-05 1.1E-05 1.0E-05 8.3E-OB Taylor Flats ESE 4.2 Containment Bldg. 4.1E-07 4.1E-07 3.8E-07 8.2E-10 Turbine Bldg. 8.9E-07 8.7E-07 6.8E-07 7.2E-10 Radwaste Bldg. 8.9E-07 8.7E-07 6.8E-07 7.2E-10 Ringold ENE 4.0 Containment Bldg. 2. 5E-07 2.5E-07 1.9E-07 3.3E-10 Turbine Bldg. 3.9E-07 3.8E-07 3.0E-07 3.3E-10 Radwaste Bldg. 3.9E-07 3.8E-07 3.0E-07 3.3E-10 BPA Ashe 0.5 Containment Bldg. 6.4E-06 6.4E-06 5.8E-06 3.7E-OB Substation 0 M Turbine Bldg. 3.0E-05 2.9E-05 2.7E-05 7.8E-OB C Pl CD D CP W Radwaste Bldg. 3.0E-05 2.9E-05 2.7E-05 7.8E-OB CD Dl CO Q) O

AHENDHENT NO. 6 November 1988 Table 3-4 DOSE RATE PARAHETERS IHPLEHENTATION OF 10 CFR 20 AIRBORNE RELEASES Child Dose Factor* PI 1 DFA. DFG. Inhalation mrem/hr m~rem/ r 3 Nuclide m~rem/ Ci ~Ci /m Ci/m H-3 1.8E-09 1.7E-07 0.0 6.3E+02 Na-24 1.3E-05 4.4E-06 2.9E-08 1.6E+04 Cr-51 2.9E-07 4.6E-06 2.6E-10 1.7E+04 Hn-54 2.6E-08 4.3E-04 6.8E-09 1.6E+06 Hn-56 7.5E-05 3.3E-05 1.3E-OB 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 3.0E-04 8.2E-09 1.1E+06 Co-60 4.2E-09 1.9E-03 2.0E-08 7.0E+06 CU-64 1.5E-05 9.9E-06 1.7E-09 3.7E+04 Zn-65 3.3E-08 2.7E-04 4.6E-09 1.0E+06 Zn-69m 1.4E-05 2.7E-05 3.4E-09 1.0E+05 As-76 7.3E-06 1.9E-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 1.0E-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.BE+04 Ho-99 2.9E-06 3.7E-05 2.2E-09 1.4E+05 Tc-99m 3.2E-05 1.3E-06 1.1E-09 4.BE+03 Ru-106 2.2E-08 3.9E-03 1.8E-09 1.4E+07 Ag-110m 3.2E-OB 1.5E-03 2.1E-08 5.6E+06 Sb-124 1.3E-07 8.8E-04 1.5E-OB 3.3E+06 Sb-125 7.9E-09 6.3E-04 3.5E-09 2.3E+06 Sb-126 6.5E-07 2.9E-04 1.0E-OB 1.1E+06 Sb-127 2.1E-06 6.2E-05 6.6E-09 2.3E+05 63

AHENDHENT NO. 6 November 1988 Table 3-4 DOSE RATE PARAHETERS IHPLEHENTATION OF 10 CFR 20 AIRBORNE RELEASES Child Dose Factor* PI 1 DFA. DFG. Inhalation mrem/hr m~rem/ r X -1 3 Nuclide sec m~rem/ Ci ~Ci /m ~Ci /m Te-127 2.1E-05 1.5E-05 1.1E-11 5.6E+04 Te-131m 6.4E-06 8.3E-05 9.9E-09 3.1E+05 I-131 1.0E-06 4.4E-03 3.4E-09 1.6E+07 I-132 8.4E-05 5.2E-05 2.0E-OB 1.9E+05 I-133 9.2E-06 1.0E-03 4.5E-09 3.7E+06 I-135 2.9E-05 2.1E-04 1.4E-OB 7.BE+05 Cs-134 1.1E-08 2.7E-04 1.4E-08 1.0E+06 Cs-137 7.3E-10 2.5E-04 4.9E-09 9.3E+05 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-OB 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 2.0E-05 NO DATA 7.4E+04 Hf-181 1.8E-07 6.0E-05 1.2E-08 2.2E+05 W-185 1.1E-07 1.9E-04 0.0 7.0E+05

Haximum Organ
- No data is listed for Sr-90 in Table E-6 of Regulatory Guide 1.109, Revi-sion l. Y-90 valves were used for dose conversion factor Sr-90.

63a

AMENDMENT NO. 6 November 1988 TABLE 3-5 a OSE PARAMETERS FOR 10 CFR 5'0 EVALUATIONS AIRBORNE RELEASES AGE GROUP: ADULT ORGAN OF REFEREN(f: MAXIMUM ORGAN R(I), INDIVIDUAL PATHWAY DOSE PARAMETERS FOR RADIONUCLIDES OTHER THAN NOBLE GASES RADIO- INHALATION GROUND PLANE COW-MILK GOAT-MILK ANIMAL-MEAT VEGETABLES NUCLIDE (MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC) H 3 7.2E+02 O.OE-01 5.BE+02 1.2E+03 2.4E+02 1.6Et03 NA 24 1.0Et04 1.2Et07 1.2Et06 2.2E+05 7.2E-04 1.1Et05 CR 51 '.4E+04 4.7E+06 3.3Et06 5.9E+05 8.2E+05 2.3Et07 MN 54 1.4Et06 1.4E+09 1.4Et07 2.1Et06 1.5Et07 9.4Et08 MN 56 2.DE+04 9.DE+05 6.2E-02 1.1E-02 O.OE-01 2.0Et02 FE 55 7.2E+04 O.OE-01 1.4ft07 2.2Et06 1.6Et08 1.9Et08 FE 59 1.DE+06 2.7E+08 1.1f t08 2.DE+07 9.BE+08 1.5E+09 CO 58 9.3E+05 3.BE+08 4.7E+07 7.6Et06 1.8Et08 B.DE+08 CO 60 6.0E+06 2.3E+10 1.7Et08 2.Sf+07 B.OE+08 2.9E+09 CU 64 4.9E+04 6.1E+05 1.0E+06 1.7E+05 1.1E-OS 3.3Et05 ZN 65 8.6Et05 .7.5E+08 2.7ft09 4.0E+08 7.0E+08 1.3Et09 ZN 69M 1.4Et05 1.3E+06 1.3Et07 2.4E+06 1.2E-03 1.4Et06 AS 76 1.5E+05 3.BE+06 , 2.1Et07 3.BE+06 2.9E+01 B.OEt06 BR 82 1.4E+04 2.1E+07 1.9Et07 3.4E+06 7.0Et02 7.7Et05 SR 89 1.4E+06 2.2E+04 6.9Et08 2.0E+09 1.4E+08 1.5E+10 SR 90 2.9E+07 '6.7Et06 3.4Et10 8.3E+10 8.9E+09 7.4E+11 ZR 95 1.BE+06 2.5E+08 4.6Et05 7.6E+04 9.2E+08 1.6f+09 NB 95 5.1E+05 1.4Et08 1.3Et08 2.2E+07 3.6E+09 8.4E+08 ZR 97 5.2E+05 3.0E+06 1.4Et04 2.4E+03 6.4E-01 B.BE+06 NB 97 2.4Et03 1.BE+05 1.6E-09 2.9E-10 0.0E-01 8.1E-04 MO 99 2.5E+05 4.0E+06 2.9Et07 5.2E+06 1.2E+05 9.3E+06 TC 99M 4.2E+03 1.BEt05 2.BE+03 5.DE+02 3.6E-18 2.2E+03 RU106 9.4E+06 4.2E+08 7.3ft05 1.1E+05 1.0E+il 1.2E+10 AG110M 4.6Et06 3.5E+09 1.2Et10 1.8Et09 1.4Et09 4.4E+09 SB124 2.5E+06 6.Of+08 3.5Et08 S.BE+07 2.7E+08 '.0E+09 SB125 1.7E+06 2.4E+09 1.3Et08 1.8Et07 1.2E+08 1.4E+09 SB126 7.7E+05 8.4E+07 2.2Et08 4.0E+07 7.BE+07 1.6E+09 SB127 3.0Et05 1.7E+07 5.2Et07 9.3Et06 1.9Et06 1.2E+08 TE127 5.7E+04 .3.DE+03 2.6E+04 4.7E+03 8.4E-09 2.0E+05 TE131M 5.6Et05 B.OE+06 8.9Et06 1.BE+06 1.1E+04 2.0E+07 I 131 1.2E+07 8.6E+06 3.4E+10 6.1E+10 1.2E+09 4.4E+10 I 132 1.1E+05 6.2Et05 3.9Et00 6.9E+00 0.0E-01 1.1E+03 I 133 2.2E+06 1.2E+06 2.5E+08 4.5E+08 2.4E+01 1.1E+08 I 135 4.5E+05 1.3E+06 5.5Et05 9.BE+05 1.7E-15 1.4Et06 CS134 B.SE+05 6.9E+09 7.4Et09 2.7E+10 8.6E+08 1.DE+10 'S136 1.5f+05 1.5E+08 5.0Et08 2.2E+09 2.3Et07 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 3.6Et05 1.0E-23 4.6E-23 O.OE-OO 3 'E-11 BA140 1.3E+06 2.1E+07 2.7Et07 4.BE+06 2.8Et07 7.3E+08 LA140 4.6E+05 1.9f+07 8.4Et04 1.5E+04 . 7.0Et02 3.3E+07'.3E+08 CE141 3;6E+05 1.4E+07 S.BEt06 1.DE+06 1.7E+07 i CE144 ND147 7;BE+06 2.2E+05 7.DE+07 8.5E+06 6.4Et07 2.5E+05 9.6E+06 4.6E+04 2.6Et08 1.9E+07 1.1E+10 5.1E+08 HF179M 1.6E+05 0.0E-01 O.OE-01 O.OE-01 0.0E-01 , O.OE-01 HF181 4.BE+05 2.1E+08 5.5E+05 9.3E+04 1.2E+10 1.BE+09 W 185 4.5E+05 1.8Et04 2.4E+07 3.9E+06 1.9Et07 8.4Et08 P 64

AMFNDYiENT NO. 6 November 1988 TABLE 3-5 b DOSE PARANETERS FOR 10 CFR 50 EVALUATIONS AIRBORNE RELEASES AGE GROUP: TfEN ORGAN OF

REFERENCE:

MAXI'RGAN R(I), INDIVIDUAL PATHWAY DOSE PARAMETERS FOR RADIONUCLIDES OTHER THAN NOBLE GASES RADIO- INHALATION GROUND PLANE COW-MILK GOAT-MILK ANIMAL-NEAT VEGETABLES NUCLIDE (i%EN/YR (N2.%EN/YR (M2.NEW/YR (N2.%EN/YR = (H2.NEW/YR (H2.NEN/YR PER UCI/H3) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC) H 3 7.3Et02 O.OE-01 7.5Et02 1.5Et03 1.5Et02 1.9Et03 NA 24 1.4Et04 1.2E+07 2.1E+06 3.9E+05 5.8E-04 1.0Et05 CR 51 2.1Et04 4.7E+06 3.9Et06 6.8Et05 4.4E+05 2.SEt07 tS 54 '.0Et06 1 ~ 4E+09 1.6E+07 2.3E+06 7.8Et06 9.6Et08 HN 56 5.7ft04 9.0Et05 2.3E-01 4.1E-02 O.OE-OO 3.7Et02 FE 55 1.2Et05 O.OE-Oi 2.4E+07 3.8E+06 1.3E+08 3.0E+08 FE 59 1.5Et06 2.7Et08 1.3Et08 2.5Et07 5.5E+08 1.7Et09 CO 58 1.3E+06 3.8E+08 5.3E+07 8.7E+06 9.4E+07 8.3Et08 CO 60 8.7Et06 2.3Etio 2.1Et08 3.DE+07 4.3Et08 3.1Et09 CU 64 6.1Et04 6.1E+05 1.6E+06 2.7E+05 8.0E-06 2.7Et05 ZN 65 1.2Et06 7.5Et08 4.5Et09 6.7E+08 5.4Et08 2.0Et09 ZN 69M 1.7f+05 1.3E+06 2.1E+07 3.BE+06 9.1E-04 1.1E+06 AS 76 1.5Et05 3.8Et06 2.7E+07 4.9E+06 1.7E+01 5.3Et06 BR.82 1.8Et04 2.1E+07 2.8E+07 5.1E+06 4.9E+02 6.1E+05

'SR 89        2.4Et06       2.2Et04       1;3Et09        3.7E+09         1.2E+08            2.4Et10 SR 90        3.3E+07       6.7Et06       5.1E+10        1.3Etii         6.2E+09            1.0E+12 ZR  95       2.7Et06       2.5Et08       5.BE+05        9.5Et04         5.3E+08            1.8Et09 NB  95       7.SE+05       1.4E+08       1.6E+08        2.7E+07         2.DE+09            9.1Et08 ZR  97       6.3Et05       3.0Et06       2.1E+04        3.8Et03         4.6E-01            7.0E+06 NB  97       3.9Et03       1.8Et05       1.9E-08        3.3E-09         O.OE-Oi            4.8E-03 M   99       2.7Et05       4.0E+06       5.1E+07        9.2Et06         9.4Et04            1.1Et07 TC 99M       6.1E+03       1.8E+05       5.3E+03        9.5E+02         3.2E-18            2.1E+03 RU106        1.6Et07       4.2Et08       9.9Et05        1.5Et05         6.2Et10            1.5E+10 AGiiON       6.8E+06       3.5E+09       1.4E+10        2.1E+09         7.6E+08            4.6Et09 SB124        3.8Et06       6.DE+08       4.5E+08        7.3Et07         1.6Et08            4.6E+09 SB125        2.7Et06       2.4E+09       1.6E+08        2.3Et07         6.8E+07            1.6Et09 SB126        1.2Et06       8.4E+07       2.8Et08        5.1Et07                 '.5Et07 1.8Et09 SB127        3.2E+05       1.7E+07       6.9E+07        1.2Et07         1.2E+06            1.2Et08 TE127        8.1Et04       3.0Et03       4.8Et04        8.6E+03         7 'E-09            1.8Et05 TE131N       6.2Et05       8.0Et06       1.3E+07        2.3Et06         7.4E+03            1.5Et07 I 131       1.5Et07       8.6E+06       5.4E+10        9.7E+10         9.0Et08            6.1Et10 I 132       1.5E+05       6.2E+05       6.4E+00        1.2Et01         O.OE-OO            9.3Et02 I  133       2.9Et06       1.2Et06       4.2Et08        7.5Et08         1.8Et01            9.6Et07 I 135       6.2E+05       1.3E+06       9.3E+05        1.7E+06         1.3E-15            1 ~ 2E+06 CS134        1.1Et06       6.9Et09       1.3E+10        4.6Et10         6.8Et08            1.6Et10 CS136        1.9E+05       1.5E+08       8.4E+08        3.8E+09         1.8E+07            7.0Et08 CS137        8.5Et05       1.3Et10       1.1E+10        3.8Et10         5.7Et08            1.4Et10 CS138       8.6E+02       3.6E+05       1.8E-23        8.1E-23         O.OE-OO            2.7E-11 BA140        2.0Et06       2.1Et07       3.6E+07        6.4Et06         1.8Et07            8.8E+08 LA140       4.9Et05       1.9Et07       1.1E+05        2.1E+04         4.4E+02            2.4E+07 CE141       6.1E+05       1.4Et07       7.9Et06        1.4E+06         1.0Et07            1.1Et09 CE144        1.3Et07       7.0E+07       8.BE+07        1.3E+07         1.6E+08            1.3Et10 ND147        3.7Et05       8.5Et06       3.5Et05        6.2E+04         1.2Et07            6.1Et08 HF1 79M      7.1E+04       O.OE-01       O.OE-01        O.OE-01         O.OE-01            O.OE-01 HF181        4.8Et05       2.1E+08       7.1E+05        1.2Et05         7.0Et09            2.1Et09 W 185        7.7E+05       1.8E+04       3.3E+07        5.4E+06         1.2E+07            1.0Et09 65

AMENDMENT NO. 6 November 1988 TABLE 3-5 c DOSE PARAMETERS FOR 10 CFR 50 EVALUATIONS AIRBORNE RELEASES AGE GROUP: CHILD ORGAN OF REFEREN(E: MAXIMUM ORGAN R(I) s INDIVIDUAL PATS/AY DOSE PARAMETERS FOR RADIONUCLIDES OTHfR THAN NOBLE GASES RADIO- INHALATION GROUND PLANE COM-MILK GOAT-MILK ANIMAL-MEAT VEGETABLES NUCLIDE (MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC) PER UCI/SEC) H 3 6.4E+02 O.OE-01 1.2E+03 2.4E+03 1-.8Et02 2.9Et03 NA 24 1.6Et04 1.2Et07 4.5E+06 8.0Et05 9.2E-04 1.6Et05 CR 51 1.7Et04 4.7ft06 2.5E+06 4.4E+05 2.2E+05 1.6Et07 MN 54 1.6E+06 1.4Et09 1.1Et07 1.7Et06 4.3Et06 6.9Et08 MN 56 1.2E+05 9.0E+05 8.8E-.01 1.6E-01 O.OE-OO 1.1ft03 FE 55 1.1E+05 O.OE-01 6.1Et07 9.6Et06 2.5Et08 7.6Et08 FE 59 1.3E+06 2.7E+08 9.5Et07 1.7E+07 3.0E+08 1.2Et09 CO 58 1.1Et06 3.8Et08 3.4Et07 =5.6E+06 4.7E+07 5.3Et08 CO 60 7.1E+06 2.3E+10 1.4Et08 2.0E+07 2.2E+08 2.1Et09 CU 64 3.7E+04 6.1Et05 1.7f+06 2.9Et05 6.5E-06 2.2Et05 ,ZN 65 1.0E+06 7.5E+08 6.8E+09 1.0E+09 6.2E+08 3.0Et09 ZN 69M 1.0E+05 1.3Et06 2.2ft07 4.0E+06 7.2E-04 9.0Et05 AS 76 7.0E+04 3.8f+06 2.2E+07 4.0E+06 1.1E+01 3.3Et06 BR 82 2.1E+04 2.1Et07 .5.8ft07 1.0E+07 7.6E+02 9.5Et05 SR 89 2.2E+06 2.2E+04 3.1Et09 9.2E+09 2.3E+08 6.0E+10 SR 90 3.8Et07 6.7Et06 1 .OE+11 2.6E+11 9.8E+09 2.1E+12 ZR 95 2.2E+06 2.5E+08 4.2E+05 7.DE+04 3.0E+08 1.3Et09 NB 95 6.1Et05 1.4Et08 1.1Et08 1.8E+07 1.0E+09 6.2Et08 ZR 97 3.5f+05 3.0E+06 2.1Et04 3.BE+03 3.5E-01 5.2E+06 NB 97 2.8E+04 1.BE+05 4.2E-07 7.6E-08 0.0E-01 8.2E-02 MO 99 1.3E+05 4.0Et06 8.7E+07 1.6E+07 1.2E+05 1.6E+07 TC 99M 4.8E+03 1.8Et05 7.4Et03 1.3Et03 3.4E-18 2.2Et03 RU106 1.4E+07 4.2Et08 7.9E+05. 1.2E+05 3.8E+10 1. 2E+10 AG110M 5.5E+06 3.5Et09 9.4Et09 1.4E+09 3.BE+08 3.0Et09 SB124 3.2E+06 6.0Et08 3.3Et08 5.4E+07 8.8E+07 3.3Et09 SB125 2.3Et06 2.4Et09 1.2Et08 1.7E+07 3.8Et07 1.2Et09 SB126 1.1E+06 8.4E+07 2.2E+08 4.0E+07 2.7Et07 1.4Et09 SB127 2.3Et05 1.7E+07 5.5Et07 1.0E+07 7.2E+05 9.2Et07 TE127 5.6E+04 3.0Et03 5.9E+04 1.1E+04 6.7E-09 1.7E+05 7E131M 3.if+05 8.0Et06 1.1Et07 2.1E+06 5.0Et03 9.9Et06 I 131 1.6E+07 8.6Et06 1.1Et11 1.9E+11 1.4f+09 1.2E+11 I 132 1.9E+05 6.2Et05 1 .SEt01 2.7E+01 0.0f-00 1.6Et03 I 133 3.8E+06 1.2Et06 9.9Et08 1.BE+09 3.3E+01 1.7E+08 I 135 7.9E+05 1.3Et06 2.1Et06 3.8Et06 2.3E-15 2.1Et06 CS134 1.0E+06 6.9E+09 2.0E+10 7.5E+10 8.3E+08 2.6E+10 CS136 1.7E+05 1.5Et08 1.3Et09 6.0E+09 2.1Et07 1.1Et09 CS137 9.1E+05 1.3E+10 1.9Et10 6.8E+10 7.9E+08 2.5E+10 CS138 8.4Et02 3.6E+05 3.2E-23 1.4E-22 O.OE-OO 3.6E-11 BA140 1.7Et06 2.1E+07 5.6Et07 1.0E+07 2.1E+07 1.4E+09 LA140 2.3E+05 1.9E+07 9.5Et04 1./E+04 2.8Et02 1.6Et07 CE141 5.4E+05 1.4Et07 6.3E+06 1.1E+06 6.4E+06 9.0E+08 CE144 1.2E+07 7.0Et07 7.0Et07 1.1Et07 1.0E+08 1.1Et10 ND147 3.3E+05 8.5Et06 2.BE+05 5.0E+04 7.4E+06 4.8Et08 HF179M 7.4Et04 O.OE-01 0.0E-01 0.0E-01 0.0E-01 0.0E-01 HF181 2.2E+05 2.1E+08 5.9Et05 9.9E+04 4.4E+09 1.8E+09 W 185 6.9E+05 1.8Et04 2.7Et07 4.3E+06 7.3Et06 8.3Et08 66

ANENDMcNT NO. 6 November 1988 TABLE 3-5 d

R(I),

                'GE     DOSE PARAMETERS FOR 10 CFR 50 EVALUATIONS AIRBORNE RELEASES GROUP: INFANT          ORGAN OF REFEREN(f: MAXIMUM ORGAN INDIVIDUAL PATHWAY DOSE PARAMETERS FOR RADIONUCLIDES OTHER THAN NOBLE GASES RADIO-     INHALATION       GROUND PLANE    COW-MILK        GOAT-MILK    ANIMAL-MEAT    VEGETABLES NUCLIDf      (MREM/YR       (M2.MREM/YR    (M2.MRfM/YR     (M2.MREM/YR   (M2.MREM/YR    (M2.MREM/YR PER   UCI/M3)    PER   UCI/SEC) PER UCI/SEC)    PER  UCI/SEC) PER   UCI/SEC) PER   UCI/SEC)

H 3 3.7Et02 O.OE-01 1.8Et03 3.7Et03 O.OE-Oi O.OE-01 NA 24 1.1E+04 1.2E+07 7.BE+06 1.4E+06 O.OE-Oi O.OE-01 CR 51 1.3E+04 4.7E+06 2.2Et06 3.8Et05 O.OE-01 O.OE-01 MN 54 1.0Et06 1.4E+09 2.1E+07 3.1E+06 O.OE-Oi O.OE-Oi MN 56 7.2Et04 9.0E+05 1.3Etoo 2.4E-01 O.OE-01 O.OE-01 FE 55 8.7E+04 O.OE-01 7.4Et07 1.2E+07 O.OE-01 O.OE-Ol FE 59 1.0Et06 2.7E+08 1.8Et08 3.4Et07 O.OE-01 O.OE-01 CO 58 7.BE+05 3.8Et08 2.9E+07 4.BE+06 O.OE-01 O.OE-01 CO 60 4.5Et06 2.3Et10 1.2Et08 1.7Et07 O.OE-01 0 ~ OE-01 CU 64 1.5E+04 6.1E+05 1.9E+06 3.2E+05 O.OE-01 O.OE-01 ZN 65 6.5Et05 7.5Et08 1.2EtiO 1.7Et09 O.OE-01 O.OE-01 ZN 69M 4.1Et04 1.3E+06 2.4E+07 4.3E+06 O.OE-01 O.OE-01 AS 76 2.7Et04 3.8Et06 2.2Et07 4.0ft06 O.OE-01 O.OE-01 BR 82 1.3E+04 2.1E+07 9.8Et07 1.BE+07 O.OE-01 O.OE-01 SR 89 2.0Et06 . 2.2E+04 6.0Et09 1.8Et10 O.OE-01 O.OE-01 SR 90 1.6E+07 6.7Et06 1.2E+11 2.9E+11 O.OE-Oi O.OE-01 ZR 95 1.8Et06 2.5Et08 4.0Et05 6.5E+04 O.OE-Oi O.OE-01 NB 95 4.8Et05 1.4E+08 9.Sf+07 1.7E+07 O.OE-01 O.OE-01 ZR 97 1.4Et05 3.0Et06 2.2E+04 4.0E+03 0 ~ OE-01 O.OE-01 NB 97 2.7E+04 1.8Et05 1.1E-06 1.9E-07 O.OE-01 O.OE-01 MO 99 1.3Et05 4.0Et06 1.6Et08 2.BE+07 O.OE-01 O.OE-01 TC 99M 2 AL OE+03 1.BE+05 8.2E+03 1.Sf+03 O.OE-Oi O.OE-01 RU106 1.2Et07 4.2Et08 B.OEt05 1.2Et05 O.OE-Oi O.OE-Oi AG110M 3.7f+06 3.5E+09 8.2E+09 1.2E+09 O.OE-01 O.OE-01 58124 2.6E+06 6.0Et08 3.1Et08 5.1E+07 O.OE-Oi O.OE-Ol SB125 1.6E+06 2.4E+09 1.1E+08 1.BE+07 O.OE-01 O.OE-01 SB126 9.6Et05 8.4E+07 2.1Et08 3.7E+07 O.,OE-01 O.OE-01 SB127 2.2E+05 1.7E+07 5.5Et07 9.9E+06 O.OE-01 O.OE-01 TE127 2.4Et04 3.DE+03 6.8Et04 1.2E+04 O.OE-01 O.OE-01 TE131M 2.0Et05 B.OE+06 1.2Et07 2.1E+06 O.OE-01 O.OE-01 I 131 1.5Et07 8.6Et06 2.6Etli 4.7f+11 O.OE-01 O.OE-01 I 132 1.7E+05 6.2E+05 3.4E+01 6.1E+01 O.OE-01 O.OE-Oi I 133 3.6Et06 1.2Et06 2.4Et09 4.3f+09 O.OE-01 O.OE-01 I 135 7.0E+05 1.3E+06 4.9Et06 8.9E+06 O.OE-01 O.OE-Oi CS134 7.0EtOS 6.9E+09 3.7Etlo 1.4E+11 O.OE-01 O.OE-01 CS136 1.3E+05 1.5E+08 2.8Et09 1.2E+10 0.0f-01 O.OE-01 CS137 6.1E+05 1.3E+10 3.6Et10 1.3Etii O.OE-Oi O.OE-Oi CS138 B.BE+02 3.6E+05 1.2E-22 5.6E-22 0.0E-01 O.OE-01 BA140 1.6Et06 2.1Et07 1.2Et08 2.1Et07 O.OE-01 O.OE-01 LA140 1.7E+05 '1.9E+07 9.4Et04 1.7Et04 O.OE-01 0.0f-01 CE141 5.2E+05 1 ~ 4E+07 6.4Et06 1.1Et06 O.OE-01 O.OE-01 CE144 9.BE+06 7.0E+07 7.1ft07 1.1Et07 O.OE-01 O.OE-01 ND147 3.2E+05 B.SEt06 2.8Et05 5.0Et04 O.OE-01 0.0f-01 HF179M 2.BE+04 O.OE-01 O.OE-01 O.OE-01 O.OE-01 0.0f-01 HF181 8.4E+04 2.1E+08 5.9Et05 9.9Et04 O.OE-01 O.OE-01 W 185 6.3f+05 1.BE+04 2.7E+07 4.4Et06 O.OE-01 O.OE-01 67

NENDMENT NO. 3 February 1986 Table 3-6 INPUT PARNETERS FOR CALCULATING R. Parameter Value Tabl e* r (dimensionless ) 1.0 for radioiodine 0.2 for particulates F (days/liter) Each stable element U ap (liters/yr) Infant 330

                       --Child   330 Teen     400                            E-5 Adult    310 (DFL-)a (mrem/pCi )          Each  radionucl ide       E-11  to E-14 Yp   (kg/m   )                0.7 Y    (kg/    )                2.0                            E-15 5

tf (seconds) 1.73 x 10 (2 days) E-15 6 th (seconds) 7.78 x 10 (90 days) E-15 g (k g/day) 50 for cow 6 for goat E-3 fs (dimensionl ess) 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.

68

AMENDMENT NO. 3 February 1986 Table 3-8 INPUT PARAMETERS FOR CALCULATING R. 1 Parameter Value Table* r (dimensionless ) 1.0 for radioiodine 0.2 for particulates (DFL.) (mrem/pCi) Each radionuclide E-11 to E-14 U L a (kg/yr) Infant 0 E-5

             --Child           26                                      E-5 Teen             42                                      E-5 Adul t           64 U

S a (kg/yr) Infant 0 E-5 Chil d 520 Teen 630

             --Adult           520                                     E-5 fL (dimensionless)              Si te speci  fi c  (de faul t = 1. 0) f    (dimensionless)            Site specific (default        = 0.76)   RG  1.109, p 28 tL (seconds    )                8.6 x 10     (1   day)                  E-15 6

th (seconds) 5.18 x 10 (60 days) E-15 Y(kg/m ) 2.0 E-15

      *Of Regulatory Guide 1.109, Revision     l.

70

AMENDMENT NO. 6 November 1988 Table 3-9 INPUT PARAMETERS NEEDED FOR CALCULATING DOSE SUMMARIES TO THE MAXIMUM INDIVIDUAL AND THE POPULATION HITHIN 50 MILES FROM NNP-2 GASEOUS EFFLUENT In ut 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 (X) 53.8 Ref 4 Annual average temperature (Fo) 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 mi 1 es. 252,356 Ref 6 Annual 50-mile milk production (1 i ters/yr) 2.8E+08 Refs 7 & 9 Annual 50-mile meat production (kg/yr) 2.3E+07 Refs 759 Annual 50-mile vegetable production (kg/yr) 3.5E+09 Refs 7 8 9 Source terms Ref 8 71

AMENDMENT NO. 3 February 1986

                               >> Table 3-9 (contd.)

In ut Parameter Value Reference X/g values by sector for each dis-tance )recirculation, no decay) See Tables 3-11 (sec/m ) through 3-12 Ref 10 X/g values by sector for each dis-tance (recirculation, 2.2g days See Tables 3-11 decay, undepleted) (sec/m~) through 3-12 Ref 10 X/g values by sector for each dis-tance (recirculation, 8 0 days See Table 3-11 decay, depleted) (sec/m ) through 3-12 Ref 10 D/() values by sector for each dis- See Table 3-11 tance (1/m2) through 3-12 Ref 10

     *References are  listed in  Table 3-14.

72

Table 3-10 REACTOR BUILDING STACK X/ AHD D/Q VALUES* a) No Deca Unde leted CHI/(} (sec/meter cubed) for each segment Direction From Site Se ent Boundaries in Hiles from the Site

                               -2                                    4-S       1.103E-06     3.229E-07    1.153E-07    6. 291E-08   4. 151E-08   2.056E-OB    6.109E-OB 4.956E-OB 3. 370E-08 2.530E-OB SSW       8.824E-07     2.569E-07    9.106E-OB    4.941E-OB    3.243E-OB    1.607E-OB   5.267E-OB  4.304E-OB 2.930E-OB  2.201E-OB SW       7.484E-07     2.220E-07    8.257E-OB    4.646E-OB    3.098E-OB    4.101E-OB   6.486E-OB  4.274E-OB 2. 917E-08 2.195E-OB WSW       5.687E-07     1.717E-07    6.362E-OB    3.543E-OB    2.341E-OB    2.882E-OB   4.367E-OB  2.851E-OB 1.940E-OB  1.457E-OB W       2.201E-07     7.362E-OB    2.829E-OB    1.604E-OB    1.065E-OB    5.201E-09   2.986E-OB  2.489E-OB 1.695E-OB  1.274E-OB WHW       3.037E-07     1.024E-07    3.926E-OB    2.208E-OB    1.459E-OB    7-801E-09    2.680E-OB 2.168E-OB 1.471E-OB  1.104E-OB NW       9.434E-07     2.769E-07    9.967E-OB    5.427E-OB    3.563E-OB    1.789E-OB    3.036E-OB 2.344E-OB 1.582E-OB  1.183E-OB NNW       3.010E-OG     8.542E-07    3 '77E-07    1.684E-07    1.121E-07    5.498E-OB    5.529E-OB 4.004E-OB 2.706E-OB  2.023E-OB N       3.675E-06     1.034E-06    3.712E-07    2.037E-07    1.343E-07    1.060E-07    8.208E-OB 4.484E-OB 3.033E-OB  2.269E-OB NHE       2.430E-06     6.639E-07    2.313E-07    1.237E-07    8.113E-OB    9.852E-OB    5.491E-OB 2.952E-OB 1.980E-OB  1.473E-OB NE       1.308E-06     3.571E-07    1.242E-07    6.798E-OB    7.999E-OB    9.512E-OB   4.486E-OB  2.428E-OB 1.634E-OB  1. 219E-08 ENE       1.086E-06     3.381E-07    2.229E-07    2.754E-07    2.056E-07    9.895E-OB   4.020E-OB  2.168E-OB 1.455E-OB  1.082E-OB E      1.218E-06     3.665E-07    2. 195E-07   2.582E-07    1.926E-07    9.269E-OB    3.768E-OB 2.036E-OB 1.369E-OB  1.020E-OB ESE       2.409E-06     7.211E-07    4.124E-07    4.440E-07    3.242E-07    1.423E-07    5.594E-OB 3.335E-OB 2.231E-OB  1.656E-OB SE       3.043E-06     8.555E-07    3.108E-07    2.844E-07    3. 417E-07   1.677E-07    8.760E-OB 5.311E-OB 3.586E-OB  2.680E-OB SSE       1.842E-06     5.373E-07    1.943E-07    1.064E-07    7.011E-OB    3.471E-OB    7.245E-OB 5.737E-OB 3.891E-OB  2.917E-OB "Desert Sigmas, Building wake effect.       All stability classes  A  through G.

Table 3-10 (contd.) b) 2.26-Da Deca Unde leted CHI/O (sec/meter cubed) For each segment Direction From Site Se nt Boundaries in Niles from the Site 5 1.101E-06 3. 218E-07 1. 146E-07 6.23BE-OB 4.106E-OG 2.202E-OS 5.876E-OS 4.683E-OB 3. 113E-08 2.285E-OB SSW 8.810E-07 2.561E-07 9-054E-08 4.900E-OB 3.208E-OB 1.58OE-OB 5.064E-OG 4.064E-OB 2.704E-OB 1.985E-OB SW 7.471E-07 2.212E-07 G.ZOBE-OB 4.608E-OG 3.065E-OG 4.023E-OS 6.259E-OG 4.036E-OG 2.692E-OG 1.980E-OS WSW 5.678E-07 1. 711E-07 6.326E-DB 3.515E-OG 2.317E-OG 2.827E-OB 4.213E-OG 2.691E-OB 1.789E-OB 1.313E-OB W 2.197E-07 7.334E-OG 2.810E-OB 1.589E-DB 1.053E-OS 5.107E-09 2.859E-OG 2.338E-OG 1.553E-OB 1.13SE-OG WNW 3.031E-07 1 ~ 020E-07 3.899E-OB 2.187E-OG 1;442E-08 7.652E-09 2.570E-OS 2.039E-OS 1.350E-OS 9.877E-09 NW 9.419E-07 2.760E-07 9.911E-OB 5.383E-OG 3.527E-OB 1.760E-OS 2.929E-OB 2.223E-OB 1.'469E-08 1.074E-DG NNW 3.006E-06 8.520E-07 3.063E-07 1.673E-07 l.lllE-07 5.42ZE-OG 5.369E-OS 3.830E-OG 2.542E-OG 1.867E-OG N 3.671E-06 1.031E-06 3.696E-D7 2.024E-07 1.332E-07 1.044E-07 7.996E-OS 4.291E-OB 2.852E-OG ., 2.096E-OB NNE 2.427E-06 6.624E-07 2.303E-07 1.230E-07 8.050E-OS 9.700E-OG 5.336E-OB 2.812E-OS 1.850E-OB 1.350E-OS NE 1.307E-06 3.562E-07 1.236E-07 6.753E-OB 7.927E-OG 9.359E-OS 4.343E-OB 2.300E-OB 1.514E-OG 1.104E-OG ENE 1.085E-06 3.371E-07 2.217E-07 2.733E-07 2.036E-07 9.737E-OG 3.890E-OB 2.051E-OG 1.346E-OG 9.792E-09 E 1.216E-06 3.655E-07 2.185E-07 2.563E-07 1.907E-07 9.125E-OB 3.649E-OG 1.928E-OB 1.268E-OB 9.243E-09 ESE 2.406E-06 7.193E-07 4.104E-07 4.40SE-07 3.212E-07 1.403E-07 5.420E-OG 3.164E-OG 2.072E-OG 1.506E-OG SE 3.039E-06 8.532E-07 3.093E-07 2.825E-07 3.389E-07 1.655E-07 8.498E-OB 5.050E-OB 3.341E-OB 2.446E-DS SSE 1.839E-06 5.356E-07 1.932E-07 1.055E-07 6.939E-OS 3. 414E-08 6.983E-OG 5.436E-OG 3.608E-DB 2.646E-DG

Table 3-10 (contd.) c) S.O-Da Deca , De leted CHI/O (sec/meter cubed) for each segment Direction From Site Se nt Boundaries in Hiles from the Site 2- 0-5 1.006E-06 2.858E-07 9.773E-OG 5.164E-OB 3.323E-OS 1.572E-OB 5.545E-OB 4.289E-OB 2.735E-OB 1.946E-OG SSW 8.039E-07 2.269E-07 7.694E-OB 4.035E-OG 2.578E-OB 1.221E-OB 4.794E-OB 3.733E-OB 2.383E-OB 1.697E-OG SW 6.775E-07 1.942E-07 6.924E-OB 3.784E-OS 2.462E-OB 3.644E-OB 5.757E-OS 3.520E-OB 2.246E-OG 1.597E-OG WSW 5.169E-07 1.515E-07 5.398E-OB 2.923E-OS 1.886E-OG 2.562E-OB 3.875E-OS 2.347E-OB 1.493E-OB 1.060E-OG M 2.038E-07 6.726E-OB 2. 521E-08 1.407E-OB 9.223E-09 4.395E-09 2.772E-OB 2.189E-OG 1.399E-OB 9.964E-09 MNM 2.813E-07 9.369E-OB 3.505E-OB 1.938E-OS 1.263E-OS 6.663E-09 2.393E-OB 1.828E-OB 1.161E-OG 8.239E-09 NW 8.584E-07 2.450E-07 8.465E-OB 4.468E-OS 2.865E-OB 1.391E-OB 2.688E-OB 1.987E<<OB 1.257E-OB 8.893E-09 NNM 2.714E-06 7.416E-07 2.547E-07 1.345E-07 8.724E-OS 4.071E-OG 4.583E-OG 3.202E-OB 2.021E-OB 1.427E.-OG N 3.312E-06 8.954E-07 3.060E-07 1.619E-07 1.037E-07 8.674E-OB 6.796E-OG 3.375E-OS 2. 123E-08 1.495E-OB NNE 2. 196E-06 5.789E-07 1.924E-07 .9.939E-OB 6.360E-OB 8.587E-OB 4.544E-OS 2.222E-OB 1.387E-OG 9.713E-09 NE 1.186E-06 3.134E-07 1.045E-07 5.570E-OB 7.080E-OB 8.611E-OG 3.736E-OS 1.841E-OS 1.153E-OG 8.096E-09 ENE 9.883E-07 3.011E-07 1.866E-07 2.147E-07 1.554E-07 7.012E-OB 2.504E-OB 1.187E-OG 7.208E-09 4.925E-09 E 1.107E-06 3.252E-07 1.832E-07 2 '13E-07 1.456E-07 6.569E-OB 2.347E-OG 1.115E-OG 6.784E-09 4.643E-09 ESE 2.182E-06 6.364E-07 3.437E-07 3.464E-07 2.451E-07 1.014E-07 3.460E-OB 1 ~ 827E-08 1.107E-OB 7.548E-09 SE 2.747E-06 7.450E-07 2.593E-07 2.509E-07 3.134E-07 1.463E-07 6.976E-OG 3.884E-OB 2.434E-OB 1.709E-OG 55E 1.671E-06 4.722E-07 1.634E-07 8.657E-OG 5.559E-OS 2.633E-OB 5.975E-OB 4.484E-OB 2.835E-OS 2.003E-OS

Table 3-10 (contd.) d) Reactor Buildin Stack Relative Oeposition Rate 0/0) Per Unit brea meter Oirection From Site Se nt Boundaries in Hiles from the Site

                              -2        2-         3-S         7.256E-09 1 ~ 756E-09 5.194E-10  2.494E-10     1.466E-10    5.865E-11   3.375E-11    1.798E-11  9.603E-12  5.944E-12.

SSW 5.752E-09 1 ~ 380E-09 4.082E-10 1.959E-10 1.150E-10 4.626E-11 2.608E-11 1.395E-11 7.448E-12 4.610E-12 SW 3.176E-09 7.513E-10 2. 191E-10 1.035E-10 6.028E-11 3. 817E-11 2.414E-11 9.646E-12 5.151E-12 3.188E-12 WSW 2.757E-09 6.889E-10 2.061E-10 9.796E-11 5. 718E-11 3.358E-11 1.980E-11 7.927E-12 4.233E-12 2.620E-12 W 1.601E-09 4.334E-10 1.358E-10 6.565E-11 3.861E-11 1.524E-11 1.094E-11 6.220E-12 3. 321E-12 2.056E-12 WNW 2.215E-OP 5.797E-10 1.816E-10 8.829E-11 5.204E-11 2.856E-11. 1.697E-11 7. 175E-12 3. 831E-12 2.372E-12 NW 4.901E-09 1.218E-09 3.728E-10 1.813E-10 1.068E-10 4.328E-11 2. 419E-11 1.286E-11 6.869E-12 4.252E-12 NNW 1.235E-OB 2.845E-09 8.198E-10 3.873E-10 2.303E-10 9.105E-11 4.558E-11 2.363E-11 1.262E-11 7.811E-12 N 1.914E-OB 4.304E-09 1. 213E-09 5.660E-10 3.273E-10 1.707E-10 7.090E-11 2.810E-11 1.501E-11 9. 288E-12 NNE 2.034E-OB 4.577E-09 1.284E-09 5.961E-10 3.471E-10 1.810E-10 6.374E-11 2.526E-11 1.349E-11 8. 350E-12 NE ~ 1.338E-OB 2.986E-09 8.341E-10 3.918E-10 2. 819E-10 1. 483E-10 4.323E-ll '.713E-11 9.150E-12 5. 663E-12 ENE 9.298E-09 2.169E-09 7.730E-10 4.579E-10 2.604E-10 1. 001E-10 2.897E-11 1. 148E-11 6.132E-12 3. 795E-12 E 1.017E-OB 2.355E-09 8.239E-10 4.749E-10 2.699E-10 1.038E-10 3.003E-11 1.190E-11 6.355E-12 3.934E-12 ESE 1.832E-OB 4.190E-09 1.440E-09 8.177E-10 4.647E-10 1 ~ 780E-10 5.136E-11 2. 049E-11 1.094E-ll 6.773E-12 SE 2.006E-OB 4.525E-09 1.262E-09 7.531E-10 6.421E-10 2.467E-10 7.197E-11 2.872E-11 1.534E-11 9.492E-12 SSE 9.321E-09 2.265E-09 6.764E-09 3.250E-10 1.905E-10 7.633E-ll 4.186E-11 2.224E-ll 1.187E-11 7.350E-12

Table 3-11 a) No Deca , Unde leted CHI/O {sec/meter cubed) for each segment Direction From Site Se ent Boundaries in Hiles from the Site S .1.791E-OS 5.032E-06 1.836E-06 1.019E-06 6.765E-07 3.337E-07 1.405E-07 7.BODE-OB 5.333E-OB 4.018E-OB SSW 1.513E-05 4.282E-06 1.568E-06 8.729E-07 5.803E-07 2. 781E-07 1.214E-07 6.758E-OB 4.627E-DB 3.489E-OB SW 1.419E-05 4.OBOE-06 1. 513E-06 8.468E-07 5.651E-07 2. 811E-07 1.198E-07 6.690E-OB 4.584E-OB 3.457E-OB KSW 1.004E-05 2.847E-06 1.044E-06 5.811E-07 3.862E-07 1.909E-07 8.059E-OB 4.481E-OB 3.066E-OB 2.311E-OB W 8.834E-06 2.512E-06 9.240E-07 5.149E-07 3.426E-07 1.695E-07 7.'171E-08 3.988E-OB 2.728E-OB 2.056E-OB WNW 8.324E-06 2.320E-06 8.416E-07 4.654E-07 3.080E-07 1.511E-07 6.317E-OB 3.489E-OB 2.380E-OB 1.791E-OG fg 9.578E-06 2.62DE-06 9.367E-07 5. 135E-D7 3.377E-07 1.639E-07 6.739E-OB 3.687E-OB 2.506E-OB 1.881E-OB NNW 1.520E-05 4.196E-06 1.494E-06 8.198E-07 5.393E-'07 2.620E-07 1.078E-07 5.905E-OB 4.107E-OB 3.015E-OB N 1.661E-05 4 '58E-06 1.636E-06 8.987E-07 6.918E-07 2.881E-07 1.189E-07 6.518E-OB 4.435E-OB 3,.329E-OB NNE 1.259E-05 3.378E-06 1.189E-06 6.456E-07 4.2I7E-07 2.025E-07 8. 191E-08 4.445E-OB 3.015E-OB 2.260E-OB NE 1.019E-05 2.764E-06 9.837E-07 5.377E-07 3.528E-07 1.707E-07 6.978E-08 3.804E-OB 2.581E-OG 1.935E-OB ENE 9.328E-06 2.528E-06 8.989E-07 4.907E-07 3.215E-07 1.550E-07 6.302E-OB 3.426E-OB 2.322E-OB 1.739E-OB E 8.659E-06 2.344E-06 8.336E-07 4.553E-07 2.985E-07 1.441E-07 5.868E-OB 3. 191E-08 2. 162E-08 1. 619E-08 ESE 1.452E-05 3.919E-06 1.391E-06 7.573E-07 4.950E-07 2.375E-07 9.577E-OB 5.173E-OB 3.494E-OB 2.611E-OG SE 2.052E-OS 5.657E-06 2.03BE-06 1.121E-06 7.387E-07 3.595E-07 1.482E-O7 8.123E-OB 5.519E-OB 4. 141E-08 SSE 2.128E-05 5.940E-06 2.156E-06 1.193E-06 7.895E-07 3.875E-07 1.619E-07 8.949E-OB 6 '08E-08 4.596E-OG . *Ground level release, Desert Sigmas. All stability classes A through G

Table 3-11 (Contd) b) 2.26-Da Deca Unde leted CHI/t) (sec/meter cubed) for each segment Direction From Site Se ment Boundaries in Hiles from the Site 1-2 2- 0- - 0 S 1.783E-05 4.991E-06 1.809E-06 9.984E-07 6.586E-D7 3.195E-07 1.287E-07 6.725E-OB 4.334E-OS 3.079E-OB SSW 1.506E-05 4.246E-06 1.545E-06 8.547E-07 5.647E-07 2.746E-07 1.110E-07 5.810E-OB 3.745E-OB 2.660E-OO SW 1.413E-05 4.046E-06 1.490E-06 8.292E-07 5.500E-07 2.689E-07 1.095E-07 5.754E-OB 3.712E-OB 2.637E-OS WSW 9.992E-06 2.823E-06 1.029E-06 5.689E-07 3.758E-07 1.825E-07 7.359E-OS 3.846E-OS 2;475E-08 1.756E-OS M 8.792E-06 2.489E-06 9.089E-07 5.030E-07 3.324E-07 1. 614E-07 6.487E-OB 3.368E-OO 2.152E-OS 1.515E-OS WttM 8.286E-06 2.300E-06 8.282E-07 4.549E-07 2 '90E-07 1.441E-07 5.731E-OS 2.961E-OB 1.891E-OS 1.332E-OG NM 9.550E-06 2.600E-06 9.244E-07 5.040E-07 3.295E-07 1.576E-07 6.218E-OB 3.220E-OS 2.073E-OO 1.475E-OS NttM 1.515E-05 4.145E-06 1.479E-06 8.080E-07 5.293E-07 2.541E-07 1.013E-07 5.321E-OS 3.473E-OO 2.503E-OS N 1.656E-05 4.532E-06 1.619E-06 8.858E-07 5.80GE-07 2.794E-07 1.117E-07 5.878E-OS 3.839E-OB 2.769E-OS, ttNE 1.255E-05 3.356E-06 1.175E-06 6.350E-07 4.128E-07 1.956E-07 7.628E-OB 3.941E-OO 2;548E-08 1.821E-OB ttE 1.015E-OS 2.743E-06 9.705E-07 5 '74E-07 3.441E-07 1 ~ 638E-07 6.419E-OB 3.303E-OO 2.117E-OS 1.500E-OB EttE 9.291E-06 2.508E-06 8.865E-07 4.810E-07 3 '33E-07 1.487E-07 5.788E-OO 2.966E-OB 1.897E-OB 1.342E-OG E 8.626E-06 2.326E-06 8.225E-07 4.467E-07 2.912E-07 1.384E-07 5.403E-OB 2.774E-OO 1.777E-OO 1.259E-OO ESE 1.446E-05 3.891E-06 1.373E-06 7.435E-07 4.834E-07 2.285E-07 8.846E-OB 4.521E-OB 2.893E-OO 2.049E-OB SE 2.045E-05 5.618E-06 2.013E-06 1.102E-06 7.222E-07 3.446E-07 1.376E-07 7.159E-OB 4.625E-OS 3.301E-OO SSE 2.120E-05 5.895E-06 2.127E-O6 1.170E-06 7.700E-07 3.721E-07 1.491E-07 7.790E-OS 5.030E-OS 3.583E-OG

Table 3-11 (Contd) c) B.O-Da Deca , De leted CNI/O (sec/meter cubed) for each segment Direction From Site Se ent Boundaries in Hiles from the Site S 1.602E-OS 4.299E-06 1. 468E-06 7 '20E-07 5.081E-07 2.342E-07 8.603E-OB 4.155E-OB 2.544E-OB 1.742E-OB SSW 1.353E-05 3.657E-06 1.269E-06 6.782E-07 4.358E-07 2.014E-07 7.428E-OB 3.596E-OB 2.205E-OB 1.510E-OB SW 1.269E-05 3.485E-06 1.224E-06 6.579E-07 4.244E-07 1.972E-07 7.328E-OB 3.561E-OB 2.184E-OB 1.497E-OB WSW 8.976E-06 2.432E-06 8.448E-07 4.515E-07 2.901E-07 1.339E-07 4.930E-OB 2.384E-OB 1.460E-OB 9.995E-09 W 7.901E-06 2.145E-06 7.473E-07 3.998E-07 2.571E-07 1.188E-07 4.375E-OB 2.112E-OB 1.291E-OB 8.819E-09 WNW 7.446E-06 1.982E-06 6.808E-07 3.614E-07 2.312E-07 1.060E-07 3.858E-DB 1.850E-OB 1.129E-OB 7.701E-09 tiW 8.579E-06 2. 239E-06 7.584E-07 3.993E-07 2.538E-07 1.152E-07 4. 137E-08 1.971E-OB 1.201E-OB 8.205E-09 NNW 1.360E-05 3.564E-06 1.211E-06 6.382E-07 4.061E-07 1.847E-07 6.652E-OB 3.185E-OB 1.950E-OB 1.337E-OB N 1.487E-05 3.897E-06 1.326E-06 6.996E-07 4.456E-07 2.030E-07 7.334E-OB 3.516E-OB 2. 153E-08 1.477E-OB NNE 1.127E-05 2.888E-06 9.630E-07 5.023E-07 3.173E-07 1.426E-07 5.042E-OB 2.386E-OB 1.454E-OB 9.933E-09 NE 9.117E-06 2.362E-06 7.964E-07 4.180E-07 2.651E-07 1.199E-07 4.280E-OB 2.030E-OB 1.235E-OB 8.415E ENE 8.348E-06 2.160E-06 7.277E-07 3.814E-07 2.416E-07 1.089E-07 3.864E-OB 1.827E-OB 1.109E-OB 7.752E-09 E 7.750E-06 2.003E-06 6.749E-07 3.539E-07 2.243E-07 1.013E-07 3. 601E-08 1.704E-OB 1.035E-OB 7.046E-09 ESE 1.299E-05 3.349E-06 1.126E-06 5.889E-07 3.722E-07 1 ~ 671E-07 5.883E-OB 2.766E-OB 1.676E-OB 1.139E-OB SE 1.836E-05 4.834E-06 1.650E-06 8.720E-07 5.555E-07 2.529E-07 9.116E-OB 4.353E-OB 2.656E-OB 1.815E-OB SSE 1.904E-05 5.075E-06 1.745E-06 9.273E-07 5.933E-07 2.723E-07 9.932E-OB 4.779E-OB 2.925E-OB 2.002E-OB

Table 3-11 (contd.) d) Turbine Buildin Relative Deposition Rate D/0) Per Unit Area (meter Direction from Site Se nt Boundaries in Miles from the Site 1-2 2-3 -4 -0 0- 0 20-S 2. 244 E-08 4.597E-09 1. 200E-09 5.390E-10 3.049E-10 1.173E-10 3.392E-11 1.344E-11 7.180E-12 4.444E-12 SSW 1.749E-OB 3.583E-09 9. 353E-10 4. 201E-10 2.376E-IO 9. 138E-11 3.644E-11 1.048E-11 5.595E-12 3.463E-12 SW ).218E-08 2.496E-09 6. 5'I SE-10 2.926E<<10 1.655E-10 6.366E-ll 1.842E-11 7.299E-12 3.898E-12 2.413E-12 WSW 1.010E-OB 2.069E-09 5.402E-10 2.426E-10 1.372E-10 5.178E-11 1.527E-11 6.051E-12 3.231E-12 2.000E-12 W 7.468E-09 1.530E-09 3.993E-10 1.794E-IO 1.015E-IO 3.902E-11 1.129E-11 4 '74E-12 2. 389E-12 1.479E-12 WNW 8.961E-09 1.836E-09 4.792E-IO 2.152E-10 1. 218E-10 4.682E-II 1.355E-II 5.368E-12 2.867E- I2 I -774E-12 NW 1.615E<<OB 3.309E-09 8.638E-10 3.880E-IO 2. 195E-10 8.440E-11 2:442E-ll 9.677E-12 5. 168E-12 3. 199E-12 NNW 3.066E-OB 6.280E-09 1.639E-09 7.363E-10 4.165E-.10 1.602E-10 4.634E-ll 1.837E-11 9.808E-12 6. 070E-12 N 3.891E-OB 7.970E-09 2.081E-09 9.345E-10 5.287E'-10 2.033E-10 5.881E-11 2.331E-11 1. 245E-11 7.705E-11 NNE 3.647E-OB 7.471E-09 1.950E-09 8.760E-10 4.956E-10 1.906E-10 5.513E-11 2.185E-11 1.167E-11 7.222E-12 NE 2.492E-OB 5.I04E-09 1.333E-09 5.985E-IO 3.386E-10 1. 302E-10 3.766E-11 1.493E-11 7.972E-12 4.934E-12 ENE 1.906E-OB 3.905E-09 1.019E>>09 4.578E-IO 2.590E-10 9.960E-11 2.881E-ll 1.142E-11 6.098E-12 3.775E-12 E= 1.977E-OB 4.050E-09 1.057E-09 4.748E-10 2.686E-10 1.033E-10 2.988E-10 1.184E-11 6.325E-12 3. 915E-12 ESE 3.404E-OB 6.972E-09 1.820E-09 8.175E-10 4.624E-10 1.778E-IO 5.145E- I I 2.039E-II 1.089E-II 6. 740E-12 SE 4.158E-OB 8.518E-09 2.224E-09 9.987E-IO 5.650E-10 2.173E-10 6.285E-11 2.491E-11 1.330E-II 8.234E-12 SSE 2.983E-OB 6.111E-09 1.595E-09 7.165E-IO 4.053E-10 1.559E-10 4.509E-11 1.787E-11 9.543E-12 5.907E-12

Table 3-12 RADWASTE BUILDING X/Q AND D/Q VALUES* a) No Deca Unde leted CNI/O (sec/meter cubed) for each segment Direction From Site Se nt Boundaries in Miles from the Site

                               -2         2-3          3-4                                                                     - 0 S       1. 791E-05    5.032E-06   1.836E-06    1.019E-06     6.765E-07     3.337E-07 1.405E-D7  7.800E-OB  5.333E-OB  4.018E-OB SSW       2.513E-05     4.282E-06   1.568E-06    8.729E-07     5.765E-07     2.871E-07 1. 214E-07 6.758E-OB  4.627E-OB  3.489E-OB SW       1.419E-05     4.080E-06   1.513E-06    8.468E-07     5. 651E-07    2.811E-07 1.19BE-07  6 '90E-08  4.584E-OB  3.457E-OB WSW       1.004E-05     2.847E-06   1.044E-06    5.811E-07     3.862E-07     1.909E-07 8.059E-OB  4.481E-OB  3.066E-OB  2.311E-OB W       8.834E-06     2.512E-06   9.240E-07    5.149E-07     3 '26E-07     1.695E-07 7.171E-OB  3.988E-OB  2.728E-OB  2.056E-OB WNW       8.324E-06     2.320E-06   8.416E-07    4.654E-07     3.080E-07     1.511E-07 6.317E-OB  3.489E-OB  2.380E-OB  1.791E-OB NW       9.587E-06     2.620E-06   9.367E-07    5.135E-07     3.377E-07     1.639E-07 6.739E-OB  3.687E-OB  2.506E-OB  1.881E-OB NN        1.520E-05     4.169E-06   1.494E-06    8.198E-07     5.393E-07     2.620E-07 1.07BE-07  5.905E-OB  4.017E-OB  3.015E-OB N       1. 661E-05    4.558E-06   1.636E-06    8.987E-07     5.91GE-07     2.881E-07 1.198E-07  6.518E-OB  4.435E-OB  3.329E-OB NNE       1.259E-05     3.378E-06   1.189E-06    6.456E-07     4.217E-07     2.025E-07 8. 191E-08 4.445E-OB  3.015E-OB  2.260E-OB NE       1.019E-05     2.764E-06   9.837E-07    5.377E-07     3.528E-07     1.707E-07 6 '78E-08  3.804E-OB  2.581E-DB  1.935E-OB ENE       9.328E-06     2.528E-06   8.989E-07    4.907E-07     3.215E-07     1.550E-07 6.302E-OB  3.426E-OG  2.322E-OB  1.739E-OB E       8.659E-06     2.344E-06   8.336E-07    4.553E-07     2.985E-07     1.441E-07 5.868E-OB  3. 191E-08 2. 162E-08 1.619E-OB ESE       1.452E-05     3.919E-06   1.391E-06    7.573E-07     4.950E-07     2.375E-07 9.577E-OB  5.173E-OB  3.494E-OB  2.611E-OG SE       2.052E-05     5.657E-06   2.038E-06    1.121E-06     7.387E-07     3.595E-07 1.483E-07  8.123E-OB  5.519E-OB  4. 141E-08 SSE       2.128E-05     5.940E-06   2.156E-06    1.193E-06     7.895E-07    ,3.875E-07 1.619E-07  8.949E-OG  6.108E-OB  4.596E-OG

Ground Level release.. Desert sigmas. All stability classes A through G.

Table 3-12 (Cont'd) b) 2.26-Da Deca Unde leted CNI/0 (sec/meter cubed) for each segnent Direction From Site Se nt Boundaries in Wiles from the Site S 1.783E-05 4.991E-O6 1.809E-06 9.984E-07 6.586E-07 3. 195E-07 1.287E-07 6.725E-OB 4.334E-OB 3.079E-OB SSM 1.506E-05 4 '46E-06 1.545E-06 8.547E-07 5.647E-07 2.746E-07 1.110E-07 5,810E-OG 3.745E-OB 2.660E-OB SW 1.413E-05 4.056E-06 1.490E-06 8.292E-07 5.500E-07 2.689E-07 1.095E-07 5.754E-OB 3.712E-OB 2.637E-OB WSM 9.992E-06 2.823E-06 1.029E-06 5.689E;07 3.758E-07 1.825E-07 7.359E-OB 3.846E-OB 2.475E-OB 1.756E-OB W 8.792E-06 2.489E-06 9.089E-07 5.030E-07 3.324E-07 1.614E-07 6.487E-OB 3.36GE-OB 2.152E-OB 1.515E-OB WNW 8.286E-06 2.300E-06 8.282E-07 4.549E-07 2.990E-07 1.441E-07 5.731E-07 2.961E-OB 1.891E-OB 1.332E-OB NM 9.550E-06 2.600E-06 9.244E-07 5.040E-07 3.295E-07 1.576E-07 6.218E-OB 3.220E-OB 2.073E-OB 1.475E-OB NNM 1.515E-05 4.145E-06 1.479E-06 8.080E-07 5.293E-07 2.541E-07 1.013E-07 5.321E-OB 3.473E-OB 2.503E-OG N 1.656E-05 4.532E-06 1.619E-06 8.858E-07 5.808E-07 2.794E-07 1.117E-07 5.878E-OB 3.839E-OB 2.769E-OB NNE 1.255E-05 3.356E-06 1.175E-06 6.350E-07 4.128E-07 1.956E-07 7.628E-OB 3.941E-OB 2.548E-OB 1.821E-OB NE 1.015E-05 2.743E-06 9.705E-07. 5.274E-07 3.441E-07 1.638E-07 6.419E-OB 3.303E-OB 2. 117E-08 1.500E-OB ENE 9.291E-06 2.50BE-06 8.865E-07 4.810E-07 '3.133E-07 1.487E-07 5.788E-OB 1.897E-DB 1.342E-OB 2.966E-OB'.774E-OB E 8.626E-O6 2.326E-06 8.225E-07 4.467E-07 2.912E-07 1.384E-07 5.403E-OB 1.777E-OB 1.259E-OB ESE 1.446E-05 3.891E-06 1.383E-06 7.435E-07 4.834E-07 2 '85E-07 8.846E-OB 4.521E-OB 2.893E-OB 2.049E-OB SE 2.045E-05 5.618E-06 2.013E-06 1.103E-06 7.222E-07 3.466E-07 1.376E-07 7.159E-OB 4.625E-OB 3.301E-OB SSE 2.120E-05 5.895E-06 2. 127E-06 1.170E-06 7.700E-07 3.721E-07 1.491E-07 7.790E-OB 5.030E-GO 3.583E-OB

Table 3-12 (Cont'd) c) 8.0 Da Oeca De leted (Corrected for Open Terrain Recirculation) CHI/I) (sec/meter cubed) for each segment Direction Fr'om Site Seqment Boundaries in tiiles from the Site

                               -2                                      4 S      1.602E-05    4.299E-06    1.486E-06     7.920E-07     5.081E-07    2.342E-07    8.603E-OB 4.155E-OS 2.544E-OS   1.742E-OB SSM        1.353E-05     3.657E-06   1 ~ 269E-06   6.782E-07     4.358E-07    2.014E-07    7.428E-OB 3.596E-OS 2.205E-OB   1. 510E-08 SW       1.269E-05    3.485E-06     1.224E-06    6.579E-07     4.244E-07    1.972E-07    7.328E-OS 3.561E-OS 1.460E-OB   1.497E-OS WSM        8.976E-06     2.432E-06   8.44BE-07     4.515E-07     2.901E-07    1.339E-07    4.930E-OB 2.384E-OS 1.460E-OS   9.995E-09 W      7.901E-06    2. 145E-06   7.473E-07     3.998E-07     2.571E-07    1.188E-07    4.375E-OB 2.112E-OS 1.291E-OS   8.819E-09 Mtl, . 7.446E-06     1.982E-06   6.BOSE-07     3:614E-07     2.312E-07    1.060E-07    3.858E-OB 1.850E-OS 1 ~ 129E-08 7.701E-09 tN       8.579E-06     2.239E-06   7.584E-07     3.993E-07     2.538E-07    1.152E-07    4.137E-OB 1.971E-OS 1.201E-OB   8.205E-09 ttNW       1.360E-05     3.564E-06   1.211E-06     6.382E-07     4.061E-07    1.847E-07    6.652E-OB 3.185E-OB 1.950E-OS   1.337E-OS ti     1.487E-05     3.897E-06    1.326E-06    6.996E-07     4.456E-07    2.030E;07    7.334E-OB 3.516E-OB 2. 153E-08  1.477E-OS tittE      1.127E-05     2.888E-06   9.630E-07     5.023E-07     3.173E-07    1.426E-07    5.042E-OS 2.386E-OS 1.454E-OB   9.933E-09 NE       9.117E-06     2.362E-06   7.964E-07     4.180E-07     2.651E-07    1.199E-07    4.280E-OB 2.030E-OS 1.235E-OS   8.415E-09 EtiE       8.348E-06     2.160E-06   7.277E-07     3.814E-07     2.416E-07    1.089E-07    3.864E-OB 1.827E-OB 1.109E-OS   7.552E-09 E      7.750E-06     2.003E-06   6.749E-07     3.539E-07     2.243E-07    1.013E-07    3.601E-OB 1.704E-OB 1.035E-OS   7.046E-09 ESE        1.299E-05     3.349E-06    1. 126E-06   5 '89E-07     3.722E-07    1.671E-07    5 '83E-08 2.766E-OB 1.676E-OB   1.139E-OB SE       1.836E-OS     4.834E-06    1.650E-06    8.720E-07     5.555E-07    2.529E-07    9.116E-OB 4.353E-OB 2.656E-OS   1.815E-OS SSE        1.904E-05     5.075E-06   1.745E-06     9.273E-07     5.933E-07    2.723E-07    9.932E-OS 4.779E-OS 2.925E-OS   2.002E-OB

Table 3-12 (Cont'd) d) Radkaste Buildin Relative De osition Rate 0/Q Per Unit Area Heter 2) Direction From Site Se ment Boundaries in Hiles from the Site S 2.244E-OB 4.597E-09 1.200E-09 5.390E-10 3.049E-10 1.173E-10 3.392E-11 1.344E-11 7.180E-12 4.444E-12 SSW 1.749E-OB 3.583E-09 9.353E-10 4. 201E-10 2. 376E-10 9.138E-11 2.644E-ll 1.048E-11 5. 595E-12 3. 463E-12 SM 1.218E-OB 2.496E-09 6.515E-10 2.926E-10 1.655E-10 6.366E-ll 1.842E-11 7.299E-12 3. 898E-12 2.413E-12 WSW 1.010E-08 2.069E-09 5.402E-10 2.426E-10 1. 372E-10 5.278E-11 1.527E-11 6.051E-12 3. 231E-12 2.000E-12 M 7.468E-09 1.530E-09 3.993E-10 1.794E-10 1.015E-10 3.902E-11 1.129E-11 4.474E-12 2. 389E-12 1.479E-12

WNW 8.961E-09 1.836E-09 4.792E-10 2.152E-10 1. 218E-10 4.682E-11 1.355E-11 5.368E-12 2.867E-12 1.774E-12 NW 1.615E-OB 3.309E-09 8.638E-10 3.880E-10 2. 195E-10 8.440E-11 2.442E-ll 9.677E-12 5.168E-12 3. 199E-12 HNM 3.066E-OB 6 '80E-09 1.639E-09 7.363E-10 4.165E-10 1.602E-10 4.634E-ll 1.837E-11 9.808E-12 6.070E-12 N 3.891E-OB 7.970E-09 2.081E-09 9.345E-10 5.287E-10 2. 033E-10 5.881E-11 2.331E-11 1.245E-11 7.705E-12 NNE 3.647E-08 7.471E-09 1.950E-09 8 '60E-10 4.956E-.10 1.906E-10 5.513E-11 2.185E-11 1. 167E-11 7.222E-12 NE 2.492E-OB 5.104E-09 1.333E-09 5.985E-10 3.386E-10 1. 302E-10 3.766E-11 1.493E-11 7.972E-12 4.934E-12 EHE 1.906E-OB 3.905E-09 1. 019E-09 4.578E-10 2.590E-10 9.960E-11 2.881E-11 1.142E-11 6 '98E-12 3.775E-12 4.748E-10 2.686E-10 1.033E-10 2.988E-11 ' 184E-11 6.325E-12 3. 915E-12 E 1.977E-OB 4.050E-09 1.057E-09 ~ ESE 3.404E-OB 6.972E-09 1.820E-09 8.175E-10 4.624E-10 1.778E-10 5.145E-11 2.039E-11 1.089E-ll 6. 740E-12 SE 4.158E-OB 8.518E-09 2.224E-09 9.987E-10 5.650E-10 2.173E-10 6.285E-11 2.491E-ll 1.330E-1'1 8.234E-12 SSE 2.983E-OB 6.111E-09 1.595E-09 7.165E-10 4.053E-10 1.559E-10 4.509E-11 1.787E-11 9.543E-12 5.907E-12

Tab 1 e 3-13 CHARACTERISTICS OF WNP-2 GASEOUS EFFLUENT RELEASE POINTS Reactor Radwaste Turbine din 'uil Buildin Buildin Height of release point above ground level (m) 70.6m 31.1 27.7 Annual average rate of air flow from release point (m3/sec) 44.8 38.7 125.6 Annual average heat flow from release point (cal/sec) 1.06 x 106 2.9 x 106 9.1 x 105 Type and size of release Duct 3 Louver houses 4 Exhaust fans point (m) 1.14 x 3.05 1.4 x 2.4 x 0.8 1.45 x 2.01 Each Each Effective vent area (m2) 3. 48 2x 2.7 3 x 2.91 Vent velocity (m/sec)* 12.9 2 x 525 cfm** 14.4 Effective diameter (m) 1.0 ( n r2 = area) Building height (m) 70.1 70.1 70.1

      *Reactor Building exhaust in vertical direction. Radwaste and Turbine Building exhaust in horizontal plane.
    **FSAR Drawing 6-41, 525 cfm x 2 out of 3, will run at any one time.

85

AMENDMENT NO. 6 November 1988 Table 3-14 REFERENCES FOR VALUES LISTED IN TABLE 3-9 Reference 1 U.S. Hap Reference 2 Site Specific Reference 3 Regulatory Guide 1.109, Revision 1, Table E-15 Reference 4 Section 2.3, WNP-2 FSAR, Table 2.3-1 Reference 5 , Section 2.3, WNP-2 FSAR, page 2.3-3 Reference 6 WNP-1 8 WNP-2 Emergency Preparedness Plan Table 12.1, Permanent Population Distribution, Rev 5, Feb. 88 Reference 7 1986 50-Nile Land Use Census, WPPSS REHP Reference 8 WNP-2 Effluent Analysis for Applicable Time Period Reference 9 Radiological Programs Calculation Log No. 88-3 Reference 10 WNP-2 XOQDOQ Computer Run 86

Table 3-15 DESIGN BASE PERCENT NOBLE GAS 30-MINUTE DECAY)* Isoto e Percent of Total Activit Kr-83M 2.9 Kr-85M 5.6 Kr-85 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 Table 11.3-1 WNP-2 FSAR 87

AMENDMENT NO. 6 November 1988 TABLE 3-16 ANNUAL DOSES AT SPECIAL LOCATIONS WITHIN WNP-2 SITE BOUNDARY Source: WNP-2 Gaseous Ef fluent Whol e Thyroid Distance Occupancy Body Dose Dose Location Ni les hrs/ r mrem/ r mrem/ r BPA Ashe Substation 0.5 N 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 4.1E-03 6.5E-03 WNP-1 1.2 ESE 2080 3.8E-02 1.3E-01 WNP-4 1.0 ENE 2080 7.0E-02 1.1E-01 WNP-2 Visitor Center 0.08 ESE 8.6E-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/(} values (within 0-0.5 mile radius)        was Used.
   **Not within site boundary.      Closest residental 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.

88

WENDrnENT NO. 3 February 1986 TABLE 3-17 ANNUAL OCCUPIED AIR DOSE AT SPECIAL LOCATIONS S T B UNDAR Annual Annual Beta Air dose Gamma Air Dose Location (mrad) (mrad) BPA Ashe Substation 8.9E-01 1.5E+00 DOE Train 5.3E-02 9.2E-02 Hye Burial Site 3.2E-03 5.7E-03 HNP-1 3.3E-02 2.8E-02 HNP-4 5.3E-02 8.5E-02 HNP-2 Visitor Center 7.0E-02 1.2E-01 Taylor Flats* 2.3E-02 1.4E-02 Site Boundary 8.7E-01 1.5E+00

  *Not within site boundary. Closest residential area.      Included for comparison.

89

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AMENDMENT NO. 6 November 1988 Plenum Monitors ~Rx Bld Refueling Exhaust To Pump Rooms Plenum Elevated Main Steam Tunnels Release Plenum Monitors Turbine Bld .. Cond. Pump Rm. Exhaust To Turb. Opr. Deck Plenum Atmosphere Condenser Area Radwaste Bld

                    ~
                 .

Hot Hach. Shop Filter To Chem. Labs Units Atmosphere Demin. Room Radwaste Proc. Area RN Control Room SIMPLIFIED BLOCK DIAGRAM OF GASEOUS HASTE SYSTEM Figure 3-2 90a

0 AMENDMENT NO. 6

                                                        -November 1988 Main Condenser        Air: Ejector,          Off-Gas Condensers             Preheaters Hater,                Off-Gas                Off-Gas Separator             Condenser              Recombiners Gycol                 Off-Gas                Off-Gas Cooler                Moisture               Pre-Filters Condenser.            Separ.ator.s Charcoal              Coolers                Dryers Absorbers Post Treatment Monitor.

After Filters Elevated Release SIMPLIFIED BLOCK DIAGRAM OF OFF"GAS TREATMENT SYSTEM Figure 3-3 90b

i AMENDMENT NO. 3 February 1986 4.0 COMPLIANCE WITH 40 CFR 190 4.1 Technical S ecification Re uirement Technical Specification 3.11.4 states, "The annual (calendar year) dose or dose commitment to any Member of the Public, due to release 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, which shall be limited to less than or equal to 75 mrems. 4.2 ODCM Methodolo for Determinin 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 radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents. e) Dose due to direct radiation from the plant. 91

AMENDMENT NO. 4 August 1986 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 Technical Specification 3. 11.1.2a, 3. 11.1.2b, 3.11.2.2a, 3.11.2;2b; 3.11.2.3a,'r 3.11.2.3b. Direct radiation measurements will also be made to determine if the limits of Specification 3. 11.4 have been exceeded. 4.2.1 Total Dose from Li uid Effluents The annual dose to a Member of the Public from liquid effluents will be determined using NRC LADTAP computer code, and methodology presented by equation (5) in Section 2.4. 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 computer code, and methodology presented by equations (10), (ll) and (13) in Section 3.4. Appropriate atmospheric dispersion parameters will be used. 4.2.3 Direct Radiation Contribution The dose to a Member of the Public due to direct radiation from the reactor plant will be determined using thermoluminescent dosimeters (TLDs) or may be calculated. TLDs are placed at sample locations and analyzed as per Table 5-1. The direct radiation contribution will be documented in the Radioactive Effluent Release Report submitted 60 days after January 1 of each year. TLD stations 1S-16S are special interest stations and will not be used for direct radiation dose determinations to a Member of the Public. 9la

AMENDMENT NO. 1 May 1984 5.0 RADIOLOGICAL ENVIRONMENTAL.MONITORING Radiological environm ntal monitoring is intended to supplement radiological effluent monitoring by verifying that measur able 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 WNP-2 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 WNP-2 REMP is designed to conform to regulatory guidance provided by Regulatory Guide 4.1, 4.8 and the Radiological Assessment Branch Technical Position (BTP), taking into consideration certain site specific character-istics. The unique nature of the WNP-2 site on Federally owned and admin-istered land (Hanford Reservation) dedicated to energy facilities, research, waste management and as a natural reserve, forms the basis for many of the site specific parameters. Amongst the many site specific parameters con-sidered is demographic data such as:

1) 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.

2) No private residences are located on the Hanford Reservation.

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

Additional site information is available in the WNP-2 Environmental Report, Operating License Stage. 92

AMENDMENT NO. 3 February 1986 Radiological environmental monitoring activities implemented by PPM 1.11.1 "Radiological Environmental Monitoring Program (REMP) Implementation Proce-dure", as detailed in the following sections, meet or exceed the criteria of the REMP plan as specified by Plant Technical Specifications, 3/4.12. 5.1 Radiolo ical Environmental Monitoring Program (REMP) Environmental samples for the REMP are collected in accordance with Table 5-1. This table provides a detailed outline of the environmental sampl'ing plan including both Technical Specification and non Technical Specification items by sample type, sample location code, sampling and collection frequency, and type and frequency of analysis of samples collected within exposure path-way. Deviations from the sampling frequency detailed in Table 5-1 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 speci-men. All deviations from the sampling plan Technical Specification items detailed in Table 5-1 shall be documented and reported in the Annual Radio-logical Environmental Operating Report in accordance with PPM 1.10.2, "Routine or Periodic Reports Required by Regulatory Agencies", Regulatory Guide 4.8 and BTP. In the event that it becomes impossible or impractical to continue sampling a media of choice at currently established location(s) or time, an evaluation shall be made to determine a suitable alternative media and/or location to provide appropriate exposure pathway evaluations. The evaluation and any sub-stitution made shall be implemented in the sampling program within 30 days of identification of the problem. All changes implemented in the sampling pro-gram due to unavailability of samples shall be fully documented in the next Semiannual Radioactive Effluent Release Report and ODCM per PPM 1.10.1, "Reportable Events and Occurrences Required by Regulatory Agencies". Revised sampling plan table(s) and figure(s) reflecting the new locations and/or media shall be included with the documentation. 93

AMENDMENT NO. 3 February 1986 WNP-2 sampling stations are described in Table 5-2. Each station is identi-fied by an as'signed number or alphanumeric designation, meteorological sector (16 different, 22-1/2 compass sections) in which the station is located, and radial distance from WNP-2 containment as estimated from map positions. Also included in Table 5-2 is information identifying the type(s) of samples col-lected at each station and whether or not the specific sample type satisfies a Technical Specification criteria. Figures 5-1 and 5-2 depict the geographical locations of each of the sample stations listed in Table 5-2. 5.2 Land Use Census A land use census shall be conducted in accordance with the requirements of Plant Technical Specifications. Field activities pertaining to the land use census (LUC) 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 committment. More specific data within each of the 16 meteorological sectors, such as distance to nearest resident, 2 nearest milk animal, and nearest garden greater than 50m (500 ft2

                                                                     ) in size producing broad leaf vegetation shall be identified to support recalcula-tion of maximum individual dose estimates. Site-specific considerations such as the Department of Energy's Hanford Reservation Site Boundary, within which WNP-2  is located,  may require that specific information be collected beyond a 5-mile (8 km) radius in certain meteorological sectors to adequately identify pertinent data.

The results of the land use census will be submitted no later than October 31 of each year for evaluation of individual and population doses. All changes, such as a location yielding a greater estimated dose or different location with a 20 percent greater estimated dose than a currently sampled location,

AMENDMENT NO. 4 August 1986 will d be reported in the next Semiannual Radiological Effluent Report in accor-dance with PPM 1.10.2 and Technical Specification.

The REMP plan, ODCM, will be changed to r'eflect new sampling locations. The best available census information, whether obtained by aerial survey, door-to-door survey, or consultation with local authorities, shall be used to complete the Land Use Survey and the results reported in the Annual Radiologi-cal Environmental Operating Report in accordance with PPM 1.10.2 and Technical Specification requirements. 5.3 Laboratory Intercom arison Pro ram Analysis of REMP samples is contracted to a provider of radiological analyti-cal services. By contract, this analytical service vendor is required to con-duct 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 participa-tion in the Environmental Protection Agency's (EPA) Environmental Radioactiv-ity Laboratory Intercomparison Studies (Crosscheck) Program. A precontract award survey and annual audit at the contractor's facility ensure that the contractor is participating in the Crosscheck Program, as reported. The results of the contractor's analysis of Crosscheck samples shall be included in the Annual Radiological Environmental Operating Report in accordance with PPM 1.10.2 and Technical Specification. Besides the vendor's required participation in the EPA's Crosscheck Program, the Department of Social and Health Services (DSHS) of the State of Washington oversees an analytical program for the Energy facility Site Evaluation Council (EFSEC) to provide an independent test of WNP-2 REMP sample analyses. The WNP-2/DSHS split samples are analyzed by Washington State's Office of Public Health Laboratories and Epidemiology, Environmental Radiation Laboratory (ERL). The State's ERL participates in the EPA Crosscheck Program, as well as

AMENDMENT NO. 4 August 1986 inclusion in the annual report within the specified time frame. The missing ~ ~ ~ data shall be submitted as soon as possible upon receipt of the results.

Along with the 'missing data, the supplementary report shall include an explanation as to the cause for the delay in completion of the analysis within the report period. A nonroutine radiological environmental operating report is required to be submitted within 30 days from the end of any quarter in which a confirmed measured radionuclide concentration in an environmental sample averaged over the quarter sampling period exceeds a reporting level. Table 5-4 specifies the reporting level (RL) for most radionuclides of environmental importance due to potential impact from plant operations. When more than one of the nuclides listed in Table 5-4 is detected in a sample, the reporting level is considered to be exceeded and a nonroutine report required if the following conditions are satisfied: Concentration (1) Concentration (2) Reporting Level 1 Reporting Level 2 For radionuclides other than those listed in Table 5-4, the reporting level is considered to have been exceeded if the potential annual dose to an indi-vidual is greater than or equal to the design objective doses of Appendix I, 10 CFR 50.'hen a nonroutine report on an unlisted (Table 5-4) radionuclide must be issued, it shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous sample results. When it can be demonstrated that the anomolous sample result(s) exceeding reporting levels is not the result of plant effluents, a nonroutine report does not have to be submitted. A full discussion of the sample result and subsequent evaluation or investigation of the anomolous result will be included in the Annual Radiological Environmental Operational Report. 97

TABLE 5-1 CD RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PLAN I CO CO 2: Ch Lsl Type and frequency g OM D Sampling and le lY Sample Ty e Sam le Location Code*. Collection fre uenc of Anal sis 1 . AIRBORNE

a. Particulates and 1, 4-9, 21, 23, 40, Continuous sampl ing Particulate: Gross radioiodine 48 and 57 Weekly collection (6/12) gamma'isotopic3 quarterly composite (by location)

Radioiodine: I-131 k1

b. SoillO 9,1,7,21,and23 Annually Gamma isotopic>

(O/5)

2. DIRECT RADIATION TLD4 1-9, 10-25, 40-47, quarterly, annually Gamma, quarterly data (34/56) 49-51, 53-56, 1S-16S review

3. WATERBORNE

a. Surface/ 26, 27, 28 and 29 Composite aliquots5, Gamma isotopic3, Drinking6 monthly Gross , tritium (3/4) quarterly composite

b. Ground water 31, 32, and 52 quarterly Gamma isotopic3 (2/3) and tritium, quarterly

TABLE 5-1 (contd.) l Sampling and Type and Frequency C> Sam le Ty e ll Sam le Location Code* Collection Fre uenc of Anal sis CQ lCO R lsJ R g WATERBORNE (contd.) HM Semiannually isotopic3 UJ M c. Sediment from 33 and 34 Gamma shoreline (1/2)

4. INGESTION

a. Nil k7 9,36,40,59 Semimonthly during Gamma isotopic3 (4/5) and 96 grazing season, Iodine-131 monthly at other times b Fish8 30, 38, or 39 Seasonal or Gamma isotopic (2/2) Semiannually

c. Garden produceg (2/2) 9, 37 and 91

                                                                                                  'amma Monthly during grow-ing season in the Riverview area of isotopic3 Pasco and a    control near Grandview.

Annually for the apple sample collection at Station 91

             *Sample locations are         graphically depicted in Figures           5-1 and   5-2.

1Deviations are permitted if samples are unobtainable due to hazardous conditions, seasonal avail-All deviations will ability, malfunction of automatic sampling equipment, or other legitimate reasons. be documented in the Annual Radiological Environmental Ilonitoring Report. 2particulate sample filters will be analyzed for gross beta after at least 24-hour decay. If gross beta activity is greater than~ 1 0 times the mean of the control sample, garma isotopic analysis should be performed on the individual sample. isotopic means identification and quant ation of gamma-emitting radionuclides that

                       ~      ~             ~     ~                                ~

3Gamma may attributable to the effluents of the facility.

           ~                                                  ~  ~
                                                                      ~

TABLE 5-1 (contd.) C) 4TLD refers to thermoluminescent dosimeter. For purposes of WNP-2 REMP, a TLD is a phosphor card CO ( 32mm x 45mm x 0.5mm) with eight individual read-out areas (four main dosimeter areas and four back-up dosimeter areas) in each badge case. TLDs used in REMP meet the requirements of Regulatory Guide 4.13 I CO R Ch UJ I (ANSI N545-1975), except for specified energy-dependence response. Correction factors are available for energy ranges with response outside of the specified tolerances. TLD stations 1S-16S are special interest bJ required by Plant Technical Specifi-CY M CL stations and are not included amongst the 34 routine TLD stations cation, Table 3.12-1. 5Composite samples will be collected with equipment which is capable of collecting an aliquot at time intervals which are short relative to the compositing period. 6Station 26, WNP-2 makeup water intake from the Columbia River, satisfies the Technical Specifica-tion criteria for upstream surface water and drinking water control samples. The discharge water (Station

27) samples are used to fulfill the Technical Specification criteria for a downstream sample. However, they provide very conservative estimates of downstream concentrations. Drinking water samples are not routinely analyzed for I-131 from two week composite. I-131 analysis will be performed when the calculated dose for the consumption of water is greater than 1 mrem per year to the maximum organ.

7Milk samples will be obtained from farms or individual milk animals which are located in sectors with high calculated annual average ground-level D/gs and high dose potential. There are no milk animals located within 5 km of WNP-2. If Cesium-134 or Cesium-137 is measured in an individual milk sample in excess of 30 pCi/1, then Strontium-90 analysis should be performed. 8There are no commercially important species in the Hanford reach of the Columbia River. Most recreationally important species in the area are anadromous, primarily salminoids. Four fish specimen will normally be collected by electroshock technique in the vicinity of the plant discharge (Station 30). If electroshocking produces insufficient fish samples, anadromous species may be obtained from Ringold Fish Hatchery (Station 39). Control samples are normally collected in the vicinity of Ice Harbor Dam (salminoids may be obtained through the National Marine Fisheries Service at Lower Granite Dam).

Garden produce will routinely be obtained from farms or gardens using Columbia River water for irrigation. One sample of a root crop, leafy vegetable, and a fruit should be collected each sample period if available. The variety of the produce sample will be dependent on seasonal availability. 10Soil samples are collected to satisfy the requirements of the Site Certification Agreement (SCA), WNP-2.

TABLE 5-1 contd.)

    " The  fraction in parenthesis under each sample type gives the ratio of the number of Technical Specificaton sample locations to the total number of sample locations for the sample type that is currently included in the overall WNP-2 radiological environmental monitoring program.

                                       .4 WNP-2 REJIG'OCATIONS Station Sector Radi a1 Mi1esa TLD  AP/AI  SM     DW    GW SE MI FI GP SO b

1 S 1.3 0 X 2 NNE 1.8 0 3 SE 2.0 X 4 SSE 9.3 0 0 5 ESE 7.7 0 X 6 S 7.7 0 X 7 WNW 2.7 0 X 8 ESE 4.7 0 0 9A* MSW 30. 0 0 0 9B* WSW 35.0 9C WSM 33.0 10 E 3.1 0 11 ENE 3.1 X 12 NNW 6.1 X 13 SM 1.4 0 14 WSM 1.4 0 15 1.4 0 m m W C CA Z 16 MNW 0 Pl 17 HNW 1.2 0 CO Ql K C)

TA 5-2 (Continued) Station Sector Radial Miles TLD AP/AI SM DW GM SE Ial FI GP SO> 18 N 0 19 NE 1.8 0 20 ENE 1.9 0 21 ENE 1.5 X X 22 E 2.1 0 23 ESE 3.0 X X 24 SE 1.9 0 25 SSE 1.6 0 26* f 3.2 27 E 3.2 28 SSE 7.4 29 SSE 11.0 30 E 3.5 31 E 1.1 32 E 1.2 33* ENE 3.3 34 ESE 3.3 ID U Pl 35 ENE 10. 5 c o 36 ESE- 7.2 S PTI 37A SSE 17.0 CO O Ch I 378 SSE 16.0 38* E 26.5 (95.0)

OI.E 5-2 (Continued) Station Sector Radial Miles TLD AP/AI SW DW GW SE NI FI GP SOb 39 NE 4.3 40 SE 6.4 0 0 41 SE 5.8 0 42 ESE 5.6 43 E 5.7 44 ENE 5.7 45 ENE 4.2 46 NE 4.7 47 N 0.5 48 NE 4.3 49 . NW 1.2 50 SSW 1.2 51 ESE 2.1 52 N 0.1 53 N 7.5 54 NNE 6.5 55 SSE 7.0

'56     SSW         7.0 57    N           0.7 59    SE          9.6                                               o ~

mm HZ 91 ESE 4.5 I C7 96 WSW 36.0 ~m ED M CO CO H C)

TA 5-2 (Continued) Station Sector Radial Miles TLD AP/AI SW DW GW SE tlI FI GP SOb 1S H 0.3 2S NHE 0.4 3S NE 0.5 4S EHE 0.4 5S E 0.4 6S ESE 0,4 7S SE 0.5 8S SSE 0.7 9S S 0.7 10S SSW 0.8 11S SW 0.7 12S MSM 0.5 13S M 0.5 14S WNM 0.5 15S NW 0.5 16S NNW 0.4 Contro ocation. X-Sample collected at station (non-RETS) 0-Radiological Environmental Technical Specification (RETS) sample collected at station. aEstimated from center of WNP-2 Containment from map positions. Included in sampling program to satisfy requirements for Site Certification Agreement with the State of Washington. AP/AI = Air Particulate and Iodine SM = Surface Mater (River Water) DW = Drinking Water GM = Ground Mater SE = Shoreline Sediment MI = Milk FI = Fish GP = Garden Produce SO = Soil

AMENDMENT NO. 6 November 1988 l 0 ~ AIOV I 10 0 OOSCNLN awe

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IV% SUPPLY SYSTEM 880334 RADIOLOGICAL ENYIRONMENTAL MONITORING SAMPLE LOCATIONS INSIDE OF 10 NILE RADIUS Figure 5-1 106

Othello WASHINGTON 3&B Connell Lower Snake Rivor Granite Dam Priosl Rapids 1 IDAHO llanlord Reservation I Lower Little Goose htonumontat Dam Pomeroy IVNP.2 I Dam Clatkston Dayton Sunnyslde ~ 9A - 9 Eureka 9B ~" Bonton Clt yt West i~(Richland~ Richland 3&A 4/ W~~e ~ e Gran dvlew os Pasco 96 37A,B ~~ ~a~. Prosser Kennewlck Dam Walla Walla I AtcNary Dam tn m OREGON tn et M

&m Z oo ch R C) 1 Inch      16 mlles Ld    I I .I.J I..I   3 L Sample Locations            0   ~      S        ta Radlotogtcat Envtronmentat Monltorlno Sample Locations Outside ol 10-Mlle Radius Figure 5-2 822171 Rev. 1   tttN4)

TABLE 5-3 ENVIRONEHTAL RADIOLOGICAL MONITOR IttG PROGRAM ANNUAL SUHHARYa Name of Facility Docket tto. Location of Facility Reporting Period ounty, tate Location with ttighest Hedium or Type and All Indicator Annual Hean Number of Pathway Sampled Total Number Lower Limit Locations cane ncaa if Control Locat tons Nonrout inc (Unit of of Analyses of Detection Hean (f) Distance and ttean (f) Reported Heasurement Per formed ~LLO Ran e earectenn ~Ran e Air particulates Gross 416 0.01 0.08 (200/312) Niddletown 0.10 (5/52) 0.08 (8/104) (pCi/m3) (0.05-2.0) 5 Bii. 3400 (0.08-2.0) (1.05-1.40)

                        -Spec 32 137Cs                 0.01          0.05 (4/24)          Smithville      0.08 (2/4)       LLO (0.03-0.13)          2.5 mi. 160'0.03-2.0) 1311                  0.07          0.12 (2/24)          Podunk          0.20 (2/4)      0.02 (2/4)

(0.09-0.18) 4.0 mi. 270'0.10-0.31) Fish (pCi/kq) -Spec. 8 (wet weight) 137Cs 130 LLD LLD 90 (1/4) 130 LLD LLO LLD 134Cs 60Co 130 180 (3/4) River Nile 35 See Column 4 LLD r (150-225) ~

~ ~

l,e aSumnary Table is taken from the HRC's Branch Technical Position, Rev. 1, Nov. 1979, and provided for illustrative purposes only. cHean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is ~ ne indicated in parentheses (f).

TABLE 5-4 REPORTING LEVELS FOR NONROUTINE OPERATING REPORTS Reporting Leve RL Airborne Particulate Broad Leaf

    ~Anal  sis      Water            or Gases                 Fish        ilk   ~V (pCi/1)           (pCi/m3)            (pCi/kg, wet) (pCi/1)  (pCi/Kg, wet)

H-3 2 x 104* Mn-54 1 x 103 3 x 104 Fe-59 4 x 102 1 x104 Co-58 1 x 103 3x 104 Co-60 3 x 102 1 x 104 Zn-65 3 x 102 2x 104 Zr-Nb-95 4 x 102 I-131 0.9 1 x 102 Cs-134 30 10 1 x 103 60 1 x 103 Cs-137 50 20 2 x 103 70 2x 103 Ba-La-140 2 x 102 3 x 102

For drinking water samples. This is 40 CFR Part 141 value.

AMENDMENT NO. 3 February 1986 6.0 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Routine Radioactive Effluent Release Reports covering the operation of WNP-2 during the previous 6 months of operation are submitted within 60 days after January 1 and July 1 of each year. These reports shall include a summary of the quantities of radioactive liquid and gaseous effluents released from the unit (WNP-2). Reports shall include each class of soild waste (as defined by 10 CFR 61) shipped offsite during the reporting period with the following information; container volume, total curie quantity, principal radionuclides, source of waste and processing employed, container type, and solidification agent or absorbent. The Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid made during the repor ting period. The Radioactive Effluent Release Reports include any changes made during the reporting period to the Process Control Program and to the ODCM pursuant to Technical Specification 6.13 and 6.14, respectively, as well as any major change to Liquid, Gaseous, or Solid Radwaste Treatment System, pursuant to Technical Specification 6.15. It also includes a listing of new locations for dose calculations and or environmental monitoring identified by the Land Use Census pursuant to Technical Specification 3.12.2. The Radioactive Effluent Release Reports also include an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Technical Specification 3.3.7.11 or 3.3.7.12, respectively; and a description of the events leading to liquid holdup tanks exceeding the limits of Technical Specification 3.11.1.4. 110

WENDMENT NO. 3 February 1986 The Radioactive Effluent Report to be submitted within 60 days after January 1 of each year includes an annual summary of meteorological data collected over the previous year. This annual summary will be in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report includes an assessment of the radiation doses due to the radio-active liquid and gaseous effluents released from the unit during the previous calendar year. This same report also includes, an assessment of the radiation doses from radioactive liquid and gaseous effluents to Members of the Public due to their activities inside the Site Boundary during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time and location, are included in these reports. The assessment of radiation doses is'performed in accordance with the method-ology and parameters in the ODCM. The Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year also includes, as required by Technical Specification 3.11.4, an assessment of radiation doses to the likely most exposed Member of the Public from MNP-2 reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR 190, "Environ-mental Radiation Protection Standards for Nuclear Power Operation".

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ML17285A251: Difference between revisions

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ML17285A251: Difference between revisions

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