ML20107F270

Nonproprietary Software Design Rept for Class a Model & Meteorological,Radiological Effluent & Dose Repts for Point Beach Nuclear Plant

ML20107F270
Person / Time
Site:	Point Beach
Issue date:	01/31/1984
From:	ENERGY IMPACT ASSOCIATES
To:
Shared Package
ML19269A730	List: ML20107F268 ML20107F270
References
TASK-3.A.2.2, TASK-TM C-399, TAC-46331, TAC-46332, NUDOCS 8411050393
Download: ML20107F270 (97)

Text

y ~, o C-399 fl SOFTWARE DESIGN REPORT l FOR THE il CLASS A MODEL, AN,D THE METEOROLOGICAL,

-l RADIOLOGICAL EFFLOENT AND DOSE REPORTS ll ,

FORO g };} POINT BEACH NUCLEAR PL# INT

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I . SOFTWARE DESIGN REPORT.

FOR THE.

CLASS A MODEL, AND THE METEOROLOGICAL, RADIOLOGICAL EFFLUENT AND DOSE REPORTS FOR POINT BEACH NUCLEAR PLANT Prepared for WISCONSIO ELECTRIC POWER COMPANY Milwaukee Wisconsin l

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January,1984

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Prepared by -

i ENERGY. IMPACT ASSOCIATES P. O. Box 1899 Pittsburgh, Pennsylvania 15230 g

TABLE OF CONTENTS Eag LIST OF TABLES iv

. vi

. LIST OF FIGURES vii LIST OF ABBREVIATIONS viii INTRODUCTION 1-1 1.0 PURPOSE OF SOFTWARE DEVELOPMENT

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1.1 Class A Software Package . - 1-1 1.2 Software for Meteorological, Radiological Effluent Releases 1-3 and Dose Reports

_2-1 2.0 TECilNICAL BASIS AND RATIONALE FOR MODEL OPERATIONS *

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TABLE OF C0ftTEllTS (Continued)

Page 2.2 Routine Radiological Dose Reports . 2-30 2.2.1 Definitions and Types of Dose Calculated 2-31 I

2-33 2.2.2.1 Relative Concentrations 2-34 I 2.2.2.2 tiixed Mode Release 2.2.2.2.1 Criteria for Determining the Release 2-34 to be Ground Level or Elevated 2-34 2'.2.2.2.2 Plume Rise 2-37 2.2.3 Radiological Dose Formulation I* P 2-41 L _

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2.2.3.2 Gama Air Dose from Ground Level Release of tioble Gases -

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_g- of floble Gases 2-43 2.2.3.4 Total- Body Dose from Elevated Release of tioble Gases 2-44 2.2.3.5 Skin Dose from Elevated Release of !!oble Gases 2-44 4 2.2.3.6 Total Body Dose from Ground Level Release of t{oble Gases 2-45 5

~ 2.2.3.7 Skin Dose from Ground Level Release of floble Gases 2-45

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l - 2.2.3.8 Dose from External Radiation Due to Radio-activity Deposited onto the Ground Surface 2-46

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2.2.3.9 Dose Due to Inhalation of Radionuclides in Air 2-48 d 2.2.3.10 Dose from Ingestion of Atmospherically Released Radionuclides in Food 2-48 I' 2.2.3.11 Population Integrated Dose 2-53 2.2.3.12 Tritium Dose 2-54 2.3 References 2-55 I .

J APPEllDIX A - EXAMPLES OF OUTPUT METEOROLOGICAL, RADIOLOGICAL EFFLUEllT 3-1 j

AttD DOSE TABLES . A-1 APPEftDIX B - TABLES OF VALUES FOR PARAMETERS USED Ill CALCULATittG Tile y I AIR DOSE FOR ELEVATED RELEASE FOR SELECTED RAD 10tlVCLIDES B-1 I APPEllDIX C - U.S. fluCLEAR REGULATORY C0t@lISS10tl REGULATORY GUIDES 1.101 AND 1.109 iii C-1

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• I LIST OF TABLES Table Title ,- Page 2-1 Classification of Atmospheric Stability by the Vertical Temperature Difference and by the Standard Deviation of the I- .

Horizontal Wind Direction Typing Schemes 2-10 I

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'l 2-9 Average and Maximum Annual Intake Rate (Usage) for Food for Individuals in the Age Group A 2-50 l -

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LIST OF TABLES (Continued)

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LIST OF FIGURES Figure Title Page I

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~I LIST OF ABBREVIATIONS EIA Energy Impact Associates, Inc.

MAD Meteorological and Dose Program SDR Software Design Report SVR Software Verification Report Software Verification Plan I

SVP .

WE Wisconsin Electric Power Company

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6 INTRODUCTION This document is intended to provide ~ the methodology used to develop the work-ing equations used in the Class A model, and the meteorological, radiological effluent and dose reports software. It is the framework upon which all software development and coding is based. Variances to the model design structure, specified in this document, during deyelopment will be documented in the.

Software Verification Report (SVR).

I This document is consistent with Energy Impact Associates' (EIA's) Software Verification Plan (SVP) Revision 0 and contains the following: ,

o Section 1 Purpose of Software Development Section 2 Technical Basis and Rationale for Mod.el Operations o

o Section 3 Model Specifications and Flowcharts.

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SECTION 1.0 PURPOSE OF SOFTWARE DEVELOPMENT .

1.1 CLASS A SOFTWARE PACKAGE Energy Impact Associates (EIA) is designing and developing a Class A model for the Point Beach Nuclear Plant (PBNP) .to aid Wisconsin Electric Po'wer Company (WE) in satisfying the Nuclear Regulatory Commission (NRC) requirements for a real-time Class A model (Revision 1 to NUREG-0654).U ) The software for the Class A model is designed to interface the EIA puff-advection model and the dose model included in the WE Meteorological and Dose (MAD) program. This I software allows access to the WE meteorological data base once every 15 minutes to perform X/Q calculations based on a puff-advection model and dose calcula-tions based on the MAD fo:mulation. No changes are to be.made to the dose assessment portion of the MAD program.

EIA'.s real-time puff-advection model calculates the x/Q values at the receptor grid included in the dose model and consists of the following:

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The following assumptions are made regarding the release locations and the meteorological parameters:

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1.2 SOFTWARE FOR METEOROLOGICAL, RADIOLOGICAL EFFLUENT RELEASES AND DOSE I

REPORTS In addition to a Class A package, EIA is supplying Meteorological, Radiological Effluent Releases'and Dose Reports (MREDR) system to satisfy Regulatory Guides 1.21,(2)'l.23(3) and Appendix I of 10 CFR Part 50(4) requirements, respectively.

• This program allows quarterly, semi-annual and annual reports to be generated for direct submittal to the NRC.

I This package runs separate from the model and includes:

o Gaseous and Liquid Effluent Release Reports in accordance with Regulatory Guide 1.21;(2) o Meteorological Reports in accordance with Regulatory Guide 1.23;(3) o Radiological Dose Assessment Reports in accordance with Regulatory Guide 1.21(2) and-Appendix I of 10.CFR Part 50.(4)

The software will be developed in accordance with Task I.A.7, Task I.A.13, and Task V.C of the WE Scope of Services (April 7, 1983).

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SECTION 2.0 TECHNICAL BASIS AND RATIONALE FOR MODEL OPERATIONS I.

This section describes the technical basis and rationale used to develop EIA's i puff-advection model. Because dose assessment methodology was deve' loped by WE, its description is not included in this document. It is anticipated that WE will provide EIA with the detailed description for later inclu.sion in the Class A model documentation.

Also discussed in this section is the technical basis for the radiological dose assessment report designed to meet NRC Regulatory Guide 1.21 and Appendix I of g 10 CFR Part 50 requirements as a part of the meteorological, radiological effluent and dose reports.

2.1 THE PUFF-ADVECTION MODEL The puff-advection concept assumes that a continuous plume can be broken into an infinite number of individual puffs of infinitesimal source strength which have been serially released. The advection of the continuous plume is defined I by the movement of each component puff. This movement is, in turn, controlled by a wind field which can vary in both time and space. Diffusion of the con-tinuous plume is defined by the growth of each individual puff. The concentra-tion at a specific receptor point is obtained by integrating the contribution of all puffs in the vicinity of that receptor.

2.1.1 PUFF-ADVECTION CONCEPT

.I g The puff-advection concept is typically implemented in models which make the .

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o puff release o puff advection

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puff diffusion calculation of concentration.

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In the past, the following two techniques have been used to implement the puff-advection concept in nuclear applications: [

o the simulated release of individual puffs, and I, o the simulated. release of plume segments.

In both techniques the release, advection and diffusion processes are calcu-lated by tracking individual puffs which are sequentially released. The basic difference between the two techniques lies in the calculation of the l '

concentration field. A numerical integration (a sum of individual puff con-tributions) is used to calculate concentration in the first technique, while an analytical integration is used in the second technique. The use of the analytical technique ensures effective use of the host system's core storage.

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. e' TABLE 2-1 CLASSIFICATION OF ATMOSPHERIC STABILITY BY THE VERTICAL TEMPERATURE DIFFERENCE AND BY THE STANDARD DEVIATION OF THE HORIZONTAL WIND DIRECTION TYPING SCHEM Stabil'ity Pasquill Temperature Change "O, degrees With Height, 'C/100 m a0, degrees Median Value Classification Categories _

Extremely unstable A AT/aZ $ -1.9 og > 22.5 25.0 Moderately unstable B -1.9 < AT/aZ 1 -1.7 22.5 > 00 1 17.5 20.0 Slightly unstable C -1.7 < AT/aZ $ -1.5 17.5 > 00 1 12.5 15.0 Neutral D -1.5 < AT/aZ 1 -0.5 12.5 > og> 7.5 10.0 Slightly stable E -0.5 < AT/aZ 1 1.5 7.5 > og> 3.8 5.0 Moderately stable F 1.5 < AT/aZ i 4.0 3.8 > 00 1 2.1 2.5 y

Extremely stable 4.0 < AT/aZ 2.1 > 00 I7

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FORMULATION AND COEFFICIENTS USED TO CALCULATE o AND o Z

IN THE PUFF-ADVECTION MODEL FOR PBNP(5,6)Y I. oyFormulation and Coefficients I o y = (k) 00 +k 2 "O + k3 ) * ' 1 where,

~4 kI = 2.46 x 10 k2 = 5.76 x 10-3 k3 = 0.066 and oy and x are expressed in meters.

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Stability Class "O A A 25 0.3658 B 20 0.2751

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LI TABLE 2-3 (Continued) g Values of Ag , By , and Cg used in formulating ogas a function of atmospheric stability and downwind distance x are:

Ag By C Stability Class i Usable Range i=1 A 0.00024' 2.094 - 9.6 >1000m B 0.055 '1.098 2.0 C 0.113 0.911 0.0 0 1.26 0.516 -13 E 6.73 0.305 -34 F 18.05 0.18 -48.6 G 12.04* 0.18* -32.4*

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• Assumes that og (Atmospheric Stability G) = 0.667 og (Atmospheric Stability F).

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2.1.4 BUILDING WAKE EFFECTS The EIA approach to handling building wake effects is identical to that recom-I monded by NRC in their Regulatory Guide 1.1110) and in NUREG/CR-29.19.0 0)

Accordingly, the vertical dispersion parameter, o7 , is modified to account for building wake ef fect any time the release is from a b611 ding or the release

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point is close to a large building or structure. The wake effect causes the plume to disperse much faster than a plume dispersed above flat topography in the absence of surface obstruction. The enhanced dispersion is due to the mechanical turbulence produced by the building structure. Beyond about 10 to 15 obstruction heights the plume's dispersion approaches the normal dispersion conditions that exist in the absence of the obstruction. .

The modified dispersion parameter that accounts for the building wake effect i's:

1 = min [(o 2 + 0.5 7D 2h)U2,/3a)] z (16) 7 7 where, I = m dified vertical dispersion parameters used under building z

wake conditions, m Dz = height of.the building, m. ,

Equ'ation (16) requires the calculation of two modified dispersion parameters i and the smallest of the two is used.

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gaseous effluent dose to total body of an individual:

5 mrem / year per unit gaseous effluent dose to skin of an individual: 5 mrem / year per unit I -

radioiodines and particulates dose to any organ from all pathways: 15 mrem / year per unit I o average individual that represents the average habits, physiological and metabolic characteristics of the population and is used to estimate the exposure to the population within 50 miles of the site.

I The population is considered to be made up of infants (0 to 1 year), children (1 to 11 years), teenagers (11 to 17 years) and adults (17 years and older).

The dose for the maximum individual is calculated for each age group. In the case of a population dose, the exposure of each age group is calculated and I weighted by the actual population age distribution and summed to yield the population dose within a 50-mile radius around the plant site. Population distribution is one of the required inputs to the radiological dose model.

The potential radioactive exposure pathways considered in the dose model include:

o Gamma and beta air dose from noble gas releases l o Total body dose from noble gas releases o Skin dose from noble gas releases c Organ dose from deposited activity on the ground o Inhalation organ dose

[ o Organ dose from ingested activity considering food pathways o Tritium dose.

Dose calculations are made for the various exposure pathways at selected

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receptor locations as follows:

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l. Gamma and beta air dose from noble gas releases are calculated at the center of each'of the 16 wind direction sectors for 10 down-I i

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I wind distances (0.5, 1.5, 2.5, 3.5, 4.5,7.5, 15, 25, 35, 45 miles) and_for the critical sector at site boundary.

2. Total body dose from noble gas releases, skin dose and dose due to ground deposition from radionuclides releases-to maximum individual are calculated at the same receptors included in (1).

3. Population integrated total body dose for each of the 16 wind direc-

~ tion sectors for'the 11 downwind distances under (1).

I 4. Organ dose due to inhalation to maximum individual for the four age I groups at the same receptors as included in (1) and population integrated doses. .

5. Organ dose due to ingestion to maximum individual

- at the critical dairy farm from the milk pathway

- at the critical cattle farm from the meat pathway

- at the critical vegetable farm from the produce pathway

- at the critical vegetable farm from the leafy vegetable pathway

- Tritium dose.

Critical is defined as the point of calculated maximum concentration

of radioactive materials in milk, meat, produce,'and leafy vegetable pathways. It is the nearest distance to these pathways in the case of PBNP.

lI Appendix A includes examples of output dose tables.

2.2.2 RELATIVE CONCENTRATIONS IN MIXED MODE RELEASE This section p'rovides a discussion of the methodology used to calculate the X/Q

, values used in the radiological dose model software including the mixed mode release consideration.

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I 2.2.2.1 RELATIVE CONCENTRATIONS Relative concentrations used in the radiological model are calculated using the formulation of the puff-advection model discussed in Section 2.1 with the provisions for average hourly calculations and the' use of the mixed mode release approach. Included here are tables for the plume depletion factor

. (DF), due to dry deposition, for elevated releases'used in deposition calcula-tions. Tables 2-7 and 2-8.contain the DF values for 30 m and 60 m release I heights. The 60 m DF values are used for release heights exceeding 45 m (structure height plus plume rise) and the 30 m DF values are used for release heights less than 45 m (build.ing downwash).

Appendix A includes examples of X/Q tables and meteorological data tables.

2.2.2.2 MIXED MODE RELEASE The mixed mode release approach is utilized under' normal release situations.

This mode allows considering vent releases as elevated if a certain wind con-dition is met, as elevated release for part of the time and as ground-level release for the remainder of the time under another wind condition, and as a

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ground-level release under a third wind condition. The methodology employed here is based upon the one outlined in the NRC Regulatory Guide 1.111.(0)

Plume rise is calculated for elevated releases using the Briggs plume rise

- formulation as presented in Regulatory Guide 1.111.(6) i

! 2.2.2.2.1 CRITERIA FOR DETERMINING THE RELEASE TO BE GROUND LEVEL OR ELEVATED l

The relative concentration equation for a mixed mode release is:

(X/Q)m = (X/Q), (1-Et ) + (X/Q)g Et ( )

where, 3

(X/Q)m = relative concentration under mixed mode release, sec/m (X/Q), = relative concentration due to elevated release, sec/m 3

l (X/Q)g = relative concentration due to ground-level release, sec/m E = an entrainment factor, d'imensior.less.

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F 1* ,

1.-,~,.-..._,... - - ~ . . , _ , _ - _ _ _ _ _ , - - - _ _ _ _ _ , _ _ _ _ _ _ _ _ _

I The entrainment factor varies between 0 to 1 according.to the W,/U ratio, where, g W,= vent exit velocity, m/sec U = mean wind speed, m/sec.

I That is:

1 (W,/U)il (30) 2.58-1.58(W,/U) 1<(W,/U)51.5 (31)

= (32)

I 0.3-0.06(W,/U) 1.5<(W,/U)i5 E

t ,

0 (W,/U)>5 (33)

Equation (29) represents ground release if condition (30) is met; mixed mode (part-time ground level and the remainder of the time elevated) release if con-d.ition (31) or (32) is met and elevated release if condition (33) is met.*

Once the puff is released, its release is treated .either as elevated or ground level and the status of the released puff is unchanged until it'is dropped

- from the calculations.

-a 2.2.2.2.2 PLUME RISE

'E Plume rise and final plume heights are calculated for elevated releases using the NRC-recommended methodology outlined by Sagendorf et al.(10) Basicially the rise of the plume is calculated from the Briggs plume rise equations.( )

Nuclear power stations generally have ambient or near ambient temperature plumes, so that the heat release is zero or near zero; the plume rise is calculated from the momentum equations (non-buoyant plumes). In the event l

heat is released from the stack, the plume rise is calculated accounting for both momentum and buoyancy considerations and the final plume rise equals the iI one-third power of the sum of the cubes of the momentum and buoyant plume rises.

I

• Additional criteria for determining release mode are presented in Reg.

l

! Guide 1.111 (pages 1.111-10 and 1.111-11). Also see page 2-2 of the l

document " Class A Model for P8NP, Volume I, User's Information."

g 2-37 .

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The effective plume height is:

I H = h, + h p

~

(34) where, H_= effective plume height, m hs = physical stack height, m hp= plume rise, m.

Momentum Plume Rise Equations for Neutral and Unstable Cond'itions For neutral and unstable atmospheric conaitions, plume rise is calculated from:

Wh 2/3 1/3 hp) = 1.44 .

h .D (35) where, .

I W, = stack or vent exit velocity, m/sec x = downwind distance, m U = wind speed at release height, m/sec D = internal stack diameter, m.

When the exit velocity is less than 1.5 times the wind speed, a correction (16)'

for plume downwash (C) is subtracted from'hpj { Equation (35)]:

'I I- C=3 1.5 - D (36)

The result from Equation (35) corrected by Equation (36), if necessary, is compared with:,

hp3 = 3 0 (3D and the smaller value is used as the plume rise in the dispersion calculations.

-g t W I

I I 2-38

,~,-,--r- , , . - - - - , , - , - - - . - -- - - - - - , ~ ,

I I Momentum Plume Rise Equations for Stable Conditions For stable conditions, plume rise equations for the unstable conditions

[ Equations (35) and (37)] are compared with results from the following two equations:

g hp4 = 4 (F,/S)I#4 (38) and .

hp5 = 1.5 (F,/U) .5 (39) where, I F,= (W,0/2)2 and S=yh g -

and, 4 2 F, = the inomentum flux parameter, m /sec S = stability parameter, sec g = gravitational acceleration, m/sec 2 T = ambient air temperature, K 80/0z = vertical potential temperature gradient, *K/m.

,I Values of the stability parameters used in the model calculations are:

,5 Atmospheric Stability 5, sec -2 t E 8.7 x 10'4 F 1.75 x 10 -3

. G 2.4 x l'0 -3 The smallest of the plume rise calculations from Equations (35), (37), (38) and (39) is used in calculations for stable conditions.

l

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8 2-39 -

I Buoyant Plume Rise for Neutral and Unstable Conditions For a buoyant (heated) plume in neutral or unstable stability conditions, plume rise is calculated according to the following equations:

8 .

f(x) x < x*

h p

=4 f(x*) g(x) x* < x < 5x* -

(40) f(x*) g(5x*) 5x* < x where the following notation is used f(x) = 1.6 F 1/3 x /3/U 2

g(x) = (0.4 + y (0.64 + 2.2 v))/(1 + 0.8 v)2 I T = x/x*

x* = 2.16 F 2/5 h,3/5

,g

,a The length x* is a measure of the downwind distance at which atmospheric turbulence begins to dominate plume entrainment and is valid for stacks less than 305 meters in height. The buoyancy flux parameter, F, is given by:

F = 9.807 (D/2)2 W,(T3 -T)/T s (4I)

D = stack exit diameter, m l

T = stack exit temperature *K s

!5 l Buoyant Plume Rise for Stable Conditions Under stable conditions the buoyant plume rise is calculated according to:

, f(x) x < x*

l h = < (42) 2.4 (F/(US))1/3 x > x*

x* = 2,4 US -0.5 (43)

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~l I 2.2.3.2 GAMMA AIR DOSE FROM GROUND LEVEL RELEASE OF NOBLE GASES The hourly y dose from ground level releases [ Equations (7) and (8-5)] in Regulatory Guide 1.109] is given by:

I DY(r,0) = 10 12 O Di(X/Q)DFj (47)

S where, 5 DT (r,0) = the hourly air gamma dose at a distance r in sector at the angle 8 from the release point, mrad /hr I QDi = the depleted release rate, Ci/hr r = the radial distance to receptor, m 0 = the angular component of the receptor polar coordinates, degrees (X/Q) = the hourly average. dispersion factor at ' distance r (meters) in sector 0,sec/m 3

.. DFT = the gamma air dose factor for semi-infinite cloud of radionuclide

'i', (Table B-1 of Regulatory Guide 1.109), mrad-m 3/pCi-sec 10 12 = the. number of pCi per Ci, pCi/Ci.

I 2.2.3.3 BETA AIR DOSE FROM GROUND LEVEL RELEASE OF N0BLE GASES The hourly p dose from ground level releases [ Equations (7) and'(B-5) in l - Regulatory Guide 1.109] is given by:

!l 0 0 (r,0) = 10 12 (48)

ODi(X/Q)DFf i3 where, DO (r,0) = the hourly beta air dose at a distance r in a sector at the i angle 0 from the release point, mrad /hr l DF0=thebetaairdosefactorforasemi-infinitecloudofradio-

" 3 1, nuclide 'i' (Table B-1 of Regulatory Guide 1.109), mrad-m /pCi-sec.

L5 2-43 I

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2.2.3.4 TOTAL BODY DOSE FROM ELEVATED RELEASE OF N0BLE GASES I '

The hourly total body y dose from elevated release [ Equations (8) and (B-6) in Regulatory Guide 1.109] is given by:

DT (r,0) = 1.11 S (49) p ' D{(r,0) exp( pftd )

i where, DT (r,0) = the hourly total body dose at a distance r in sector 0, mrem /hr Sp = the attenuation factor that accounts for the dose reduction due to shielding provided by residential structures, (equals 0.7 for maximum individual; equals 0.5 for general population, Table E-15 Regulatory Guide 1.109), dimensionless D{ = the hourly gamma air dose from nuclide 'i' [ Equation (44)], mrad /hr 2

pf=thetissueenergyabsorptioncoefficient,fornuclide'i',cmfg td = the product of tissue density and depth used to determine total 8 body dose, g/cm 2 1.11 = average ratio of tissue to air energy absorption coefficient,

8. . mrem / mrad 2.2.3.5 SKIN DOSE FROM ELEVATED RELEASE OF NOBLE GASES The hourly y and p skin dose frcm elevated release [ Equations (9) and (B-7) in Regulatory Guide 1.109] is given by:

b 12 D (r,0) = 1.11 Sp D Y(p,g) 4 19 (50)

I ODi(X/hDFS 4 where,

• Db (r,0) = the hourly skin dose at a distance r in sector 0, mrem /br DFSj = the beta skin dose factor for a semi-infinite cloud of radio-nuclide 'i' (Table B-1 of Regulatory Guide 1.109), mrem-m 3/pCi-sec.

I It should be noted that the first term on the right hand side of Equation (50) contains the y air dose calculated from Equation (44).

2-44

E I

2.2.3.6 TOTAL BODY 00SE FROM GROUND LEVEL RELEASE OF NOBLE GASES E' The hourly total body y dose from a ground level release [ Equations (10) and (B-8) in Regulatory Guide 1.109] is given by:

D[(r,0)=S p x 10 12 ODi(x/Q)DFB j (51)

I where, D[(r,0)=thehourlytotalbodydoseduetoimmersioninasemi-infinite cloud at a distance r in sector 0, mrem /hr-DFB; = the total body dose factor for a semi-infinite cloud of the ,

radionuclide 'i', which includes the attenuation of 5 g/cm2 of tissue (Table B-1 in Regulatory Guide 1.109), mrem-m3/pCi-sec.

This equation is also used under stable onshore flow conditions for elevated releases.

2.2.3.7 SKIN DOSE FROM GROUND LEVEL RELEASE OF NOBLE GASES The hourly y and p skin dose from a ground level release [ Equations (11) and (B-9) in Regulatory Guide 1.109] is given by:

[l Db (r,0) = 1.11 x Sp x 10 12 { ODi(X/Q)0F{.

i lE 10 12k' ODi(x/Q)DFS $

(52) ,

E where, Df(r,0)=hourlyskindoseduetoimmersioninasemi-infinite cloud at a distance r in sector 0, mrem /hr.

l All other parameters are defined in previous sections.

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2.2.3.8 DOSE FROM EXTERNAL RADIATION DUE TO RADI0 ACTIVITY DEPOSITED ONTO THE GROUND SURFACE I

The hourly organ dose due to deposited activity of radioiodines and particulates radionuclides on the ground [ Equations (12), (C-1) and C-2) in Regulatory Guide 1.109] is given by:

DO (r,0) = S p CO (r,0) DFGj ) (53) where, D (r,0) = the hourly ground deposition dose to organ 'j' at locatic,n (r,0),

mrem /hr 0

C (r,0) = the ground plane concentration of radionuclide 'i' at location 2

(r,0),pCi/m DFG j ) = the field ground plane dose conversion factor for organ 'j' from l

radionuclide 'i' (Table E-6 of Regulatory Guide 1.109),

' 2 mrem-m /pCi-hr. i 8 Values for the DFG j ) factors for the skin and total body are given in Table E-6 of Regulatory Guide 1.109. The annual dose to all other organs is taken to be equivalent to the total body dose. The factor S pis assumed to have the value of 0.7.

!I

~

The ground plane concentration of radionuclide 'i' at the location (r,0) rela- ,

tive to the release point is given by:

1.0 x 1.0 12 D '.

~ ~

l 3 0 5 C (r,0) = .

g 1-exp(-At gb (54) i -

E where, D ti = the hourly total deposition rate of radionuclide 'i' at (r,0) 8 2 considering plume depletion due to dry and wet-deposition, Ci/m -br

-I Ag = the radioactive decay constant of 'radionuclide 'i', hr tb = the time period over which the accumulation is evaluated which is 15 years or 1.314 x 105 hrs.

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5 2.2.3.9 DOSE DUE TO INHALATION OF RADIONUCLIDES IN AIR I The hourly organ dose due to inhalation of radiciodines and particulates radionuclides [ Equations (13) and (C-4) in Regulatory Guide 1.109] is given by:

D a(r,0) R, x 10 Q(x/Q)DFA Di ija (58) where, D (r,0) = the hourly inhalation dose to organ 'j' of an individual in age group 'a', mrem /hr R, = the hourly air intake rate for individuals in the age group i 'a', m3 /sec (equals 4.4394 x 10-5 ,3/sec for infant;

-4 3 -4 3 1.1733 x 10 m /sec for child; 2.5368 x 10 m /sec for teenager and adult)

DFA j ),= the inhalation dose factor for radionuclide 'i', organ 'j' and age group 'a', (Tables E-7 through E-10 of Regulatory Guide 1.'109), mrem /pCi.  !

8 2.2.3.10 DOSE FROM INGESTION OF ATM0 SPHERICALLY RELEASED RADIONUCLIDES IN FOOD 5

The organ dose due to ingestion of food containing radioactivity from radio-nuclides released into the atmosphere [Equa'tions (14) and (C-13) in Regulatory Guide 1.109] is given by:

4 V D (r,0) = 1.1416 x 10 DFI UfC{(r,0)+U"Cy(r,0)+

3g UC((r,0)+UfC(r,0))

g (59) where, -

D ,(r,0) = the hourly dose to organ 'j' of an individual in age group 'a' from ingestion of produce, milk, leafy vegetables and meat at location (r,0), mrem /hr DFIg ), = the ingestion dose factor for nuclide 'i', organ 'j' and age group 'a', mrem /pCi (Tables E-ll tiirough E-14 of Regulatory Guide 1.109) 2-48

1 I

C{(r,0), Cy(r,0),

C (r,0), C (r,0) = concentrations of radionuclide 'i' in produce (non-leafy-

,g vegr. tables, fruits, and grains), milk, leafy veget' ables, e and meat, respectively, at location (r,0), pCi/kg or pCi/E f g,f ~g = respective fractions of the ingestion rates of produce and leafy vegetables that are produced in the garden of interest; (f = 0.76, f = 1.0)

U{,U",U[,U = an ual intake (usage) of produce, milk, meat, and leafy vege-tables, respectively, for individuals in the age group 'a', in kg/yr or'f/yr (equivalent to Uap)*

1.1416 x 10-4 = conversion factor from year to hour (1/8760).

I Values of the annual intake rate for food are given in Table 2-9. They are multiplied by the conversion factor 1.1416 x 10 ~4 to provide hourly intake values.

Conceiitration of Radionuclides in Produce and Leafy Vegetable The concentration of nuclide 'i' in produce at location (r,0) is given by

[ Equation (C-5) in Regulatory Guide 1.109]:

[ rl-exp(-A Eit e ' + Oiv'pg,exp(-A;t)'

1- b exp(-A t ) (60) l C{(r,0)=d(r,0)< j y3, jh v Ei i where, C{(r,0) = concentration of radionuclide 'i' in produce at location (r,0),

lg pCi/kg W dj (r,0) = deposition rate of radionuclide 'i' onto ground at location (r,0),

! pCi/m2 -br r = the fraction of deposited activity retained on the produce (equals 1.0 for iodines, and 0.2 for other particulates), dimensionless A

Ei = the effective removal rate constant for radionuclide 'i' from produce, which is'the sum of the radioactive decay constant (A j)

and the removal rate constant for physical loss by weathering

~I (equals 0.0021 hr-I), A$ +0.0021, hr 2-49

r a . ~,

3

I .

TABLE 2-9 ,

AVERAGE AND MAXIMUM ANNUAL INTAKE RATE (USAGE) FOR FOOD /

FOR INDIVIDUALS IN THE AGE GROUP A Usage of Food I' Pathway-Infant Child Maximum Average Maximum Average Maximum Average Maximum Average Teenager Adult V 520 200 630 240 520 190 0 0 Produce (U,),

kg/yr 310 190 I 330 170 400 240 Milk (( ), 330 0 A/yr 37 65 59 110 95 g Meat (U[), 0 0 41 E kglyr 26 --

59 42 64 g 0 --

Leafy Vegetable 5 (U ), kg/yr 8

lS L~I 6 l

8 -

g .

I l8 2-50 l

, . . , , _ _ - . ~ - , _ -_,-___.y--. -- ..----,, -

y- - - - - - -

5 I

t, = period of produce exposure during growing season, equals 1440 hr 2

Y, = agricultural productivity by unit area (yield), equals 2.0 kg/m Bgy = concentration factor for uptake of radionuclide 'i' from soil by edible parts of the produce (Table E-1 of Regulatory Guide 1.109),

I pCi/kg produce per pC1/kg soil t b=periodoflong-termbuildupforactivityinsedimentorsoil, 5

ncminally 15 yr = 1.31 x 10 hr P = effective surface density of t. oil, equals 240 kg/m2 t = time delay between harvest of produce and ingestion, equals h

1440 hr for produce and maximum individual and 24 he for leafy vegetable and maximum individual. .

Equation (60) is used to estimate concentration of radionuclides in produce I and leafy vegetable. The proper parameters must be used in each case. The deposition rate, d ,j from the plume [ Equation (C-7) in Regulatory Guide 1.109]

,I is given by:

' 1012 D ti ,

f r particulates dg (r,0) = < (61)

Il 5 x 10 D gg for radiciodines where, 2

1 D ti = the total deposition rate for radionuclide 'i', Ci/m -hr.

l Concentration of Radionuclides in Milk

,3 The radionuclide concentration in milk [ Equation (C-10) in Regulatory Guide 5

1.109] is given by:

l8 (62)

C"(r,0)=F.,C{(r,0)Qexp(-At) 7 gf lI where,

.C"(r,0) = the concentration in milk of nuclide 'i', pCi/ lite r 1l C{(r,0).=theconcentrationofradionuclide'i'intheanimal'sfeed, pCi/kg

- 2-51

I F,= the average fraction of the animal's daily intake of radio-nuclide 'i' which appears in each liter'of milk, days / liter (Tables E-1 and E-2 of Regulatory Guide 1.109 for cow and goat data, respectively; for nuclides not listed in Table E-2, the l values in Table E-1 are used)

Qp = consumption rate of contaminated feed and forage by an animal equals 50 kg/ day for cattle and 6 kg/ day for goats (Table E-3 of Regulatory Guide 1.109)

I tf = the average transport time o'f the activity from the feed into the milk and to the receptor equals 48 hr Ag = the radiological decay constant of nuclide 'i', hr-I .

The concentrations of radionuclide in the animal's feed is calculated as

'h [ Equation (C-ll) in Regulatory Guide 1.109]:

C{(r,0)=ff psC((r,0)+(1-f)Cf(r,0)+f(1-f)Cf(r,0) p p s (63) where, C{(r,0)=theconcentrationofradionuclide'i'intheanimal's~ feed, I pCi/kg C((r,0)=theconcentrationofradionuclide'i'onpasturegrass(calculated using Equation (60) with t p=0, t,=720 hr, Yy=0.7 kg/m2 ), pCi/kg

.. Cf(r,0)=theconcentrationofradionuclide'i'instoredfeeds(calculated 2

i using Eqution (60) with t =90 h days, t,=720 hr, Y =0.7 y kg/m , pCi/kg l l- f p= fraction of year that animals graze on pasture, equals 0.75 f s= fraction of daily feed that is pasture grass when the animal grazes on pasture, equals 1.0.

t g Concentration of Radionuclides in Meat l The concentration of radionuclid2 'i' in meat [ Equation (C-12) in Regulatory

= Guide 1.109] is given by:

Cf(r,0)=FC{(r,0)Qexp(-Aft) f f s (64)

LB lm 2-52

~

ol .

l-8 .

I where, .

C((r0)=theconcentrationofnuclide'i'inanimalflesh,pCi/kg Ff = the fraction of the animal's daily intake of nuclide 'i' which appears in each kilogram of flesh, (Table. E-1 of Regulatory

.I -Guide 1.109), days /kg t

s the average time from slaughter to consumption, equals 20 days Qp = consumption rate of feed by animal, equals 50 kg/ day CV = calculated concentration of radionuclide 'i' in animal feed Equation (63), pCi/kg.

2.2.3.11

~

POPULATION INTEGRATED DOSE The equation for calculating hourly population-integrated dose [ Equation (D-1) in Regulatory Guide 1.109] is:

D = 0.001 P d

D jda fda (65) d a 8 where, D

jda

= the hourly dose to organ 'j' (total body or thyroid) of an average individual of age group 'a' in subregion 'd', mrem /hr P

D j = the hourly population-integrated dose to organ 'j' (total body or thyroid), man-Rems or thyroid man-Rems

, f da-

= the fraction of the population in subregion 'd' that is in age group 'a' Pd = the population associated with subregion 'd' O.001 = the conversion factor from mrem to Rem, mrem / Rem.

The hourly dose to organ 'j', D jda used to calculate the hourly population l

integrated dose includes: .

l^

o total body dose from elevated [ Equation (49)] or ground [ Equation (51)] releases o inhalation dose to total body or thyroid [ Equation (58)].

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2.3 REFERENCES

1. U.S. Nuclear Regulatory Commission and Federal Emergency Management Agency, I " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," NUREG-0654, FEMAREP-1, Revision 1, October 1980.

2. U.S. Nuclear Regulatory Commission, " Regulatory Guide 1.21, Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of l Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-e Cooled Nuclear Power Plants," June 1974.

3. U.S. Nuclear Regulatory Commission, " Regulatory Guide 1.23 (Revision 1)

I Meteorological Programs in Support of Nuclear Power Pla~nts," October 1981.

4. 10 CFR Part 50, Appendix I, Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion, "As low as is

, Reasonably Achievable for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents," April 18, 1977.

5. Eimutis, E. C. and Konicek, M. G., 1972: " Derivations of Continuous

-Functions for the Lateral and Vertical Atmospheric Dispersion Coeffic.ients,"

Atmospheric Environment, Pergamon Press, 1972, Vol. 6, pp. 859-863.

I Printed in Great Britain. .

6. U.S. Nuclear Regulatory Commission, " Regulatory Guide 1.111 (Revision 1)

Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," July 1977.

7. Slade, D. H., Editor, " Meteorology and Atomic Energy," TID-24190, 1968.

8. Sutton, O. G. , Micrometeorlogy, McGraw-Hill Book Company,1953.

9.' Mitchell, A. E., Jr. and Timbre, K. 0., Atmospheric Stability Class from Horizontal Wind Fluctuations, 72nd Annual Meeting APCA, Cincinnati, Ohio, l June 24,- 1979.

l 5 10. Sagendorf, J. F., Goll, J. T. and Sandusky, W. F., "X0QD0Q: Computer Program for the Meteorological Evaluation of Routine Effluent Releases

. at. Nuclear Power Stations," NUREG/CR-2919 (PNL-4380), September 1982.

, 11. Lyons, W. A., 1976: " Turbulent Diffusion and Pollutant Transport in' l

3 Shoreline Environments," Lectures on Air Pollution and Environmental l5 Impact Analysis, Duane A. Haugen (ed), AMS, Boston.

! 12. Lyons, W. A., et al, "An Updated Expanded Coastal Fumigation Model," The 74th Annual Meeting of the Air Pollution Control Association, Paper 81-31.4, June 21-26, 1981.

(Continued) 5 2-55 l

I - -. .

~l

13. Lyons, W. A. and Cole, H. S., " Fumigation and Plume Trapping on the Shores of Lake Michigan During Stable Onshore Flow," Journal of Applied Meteorology, Vol. 12, pp. 494-510, 1973.

14. U.S. Nuclear Regulatory Commission, " Regulatory Guide 1.109, Calculations of Annual Doses to Man from Routine Releases of Reactor Effluents for the I, .

Purpose of Evaluating Compliance with 10 CFR Part 50 Appendix I, October 1977.

15. Briggs, G. C. , " Plume Rise," TID-25075,1969.

16. Gifford, F. A., " Atmospheric Transport and Diffusion Over Cities,"

Nuclear Safety, Vol. 13, pp. 391-402, 1972.

17. Brenk, H. D. and Vogt, K. J., "The Calculation of Wet Deposition from Radioactive Plumes," Nuclear Safety, Vol. 22, No. 3, pp. 362-371, May-June 1981. .

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