ML20114C510

Rev 2 to ODCM for Arkansas Nuclear One

ML20114C510
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/21/1992
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20114C501	List: 0CAN089211, Forwards Semiannual Radioactive Effluent Release Rept for Periods of Jan-June 1992 & Rev 2 to ODCM for Ano ML20114C503 ML20114C510
References
PROC-920121, NUDOCS 9209020245
Download: ML20114C510 (54)

Text

- ,

, LICENSE.075

-. Page 1 b

0FFSITE DOSE CALCULATION MANUAL FOR ARKANSAS NUCLEAR ONE REVISION 02 l

l l

t Approved // 2 1 ~

b Superintendent, Nuc er Chemistry Date l Approved 'pk,/ LbAam*Y /~ /f ' YI-I nt Manager,, Central Date 1 Approved oA \ \ 4\%U PSC Chairman Date Approved od d 7// n- /hr-fenergManager,plantOperations / Ddle Approved C.'<> 2d -<' / /b / !7 L l

SRC Chaf'rman / Dats

\

v *W 1 P ", [ -,

,, r -

.i g py

._ ?_ ' ',,, ..., e,)

t '

-". 7 . . .

,((, _ _ _(f ,

',.A:

g 5 .

,  ?

a' j -e+

• 9209020245 920829

'{DR ADOCK 06000313 PDR

LICENSE.075 Page 2 TABLE OF CONTENTS IAGE

1.0 INTRODUCTION

.......................... ........................... 4 2.0 LIQUID EFFLUENTS.................................................. 5 2.1 RADI0 ACTIVE LIQUID EFFLUENT MONITOR SETP0lNT................. 5 2.2 LIQUID " DOSE" CALCULATION.................................... 7 2.2.1- DOSE CALCULATIONS FOR AQUATIC F00DS................ 7 2.2.2 DOSE CALCULATIONS FOR POTABLE VATER................. 9 -

2.3 LIQUID " PROJECTED DOSE" CALCULATION... . . . . . . . . . . . . . . . . . . . . . . 11 3,0 GASEOUS EFFLUENTS................................................. 11 3.1 GASEOU5 MONITOR SETPOINTS....... . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 3.1.1 BATCH RELEASE SETPOINT CALCULATIONS................ 12 3.1.2 EBERLINE SPING MONITOR SETPOINT CALCULATIONS. . . . . . . 13 3.2 AIRBORNE RELEASE DOSE RATE EFFECTS........................... 15 3.2.1 NOBLE GAS RELEASE RATE............................. 15 0.2.2 I-131, TRITIUM AND PARTICULATE RELEASE DOSE RATE EFFECTS.................................. 18 3.? DOSE DUE TO NOBLE GASES...................................... 18 3.3.1 BETA AND GAMMA AIR DOSES FROM NOBLE GAS RELEASES........................................... 19 3.4. DOSE DUE TO I-131, TRITIUM AND PARTICULATES IN GASEOUS EFFLUENTS............................................ 19 3.4.1 TOTAL DOSE FROM ATM0 SPHERICALLY RELEASED RADIONUCLIDE....................................... 24 3.5 GASEOUS EFFLUENT " PROJECTED DOSE" CALCULATION................ 32 3.6 DOSE TO THE PUBLIC INSIDE THE SITE BOUNDARY.................. 33 3.6.1 LIQUID RELEASES.................................... 33 3.6.2 AIRBORNE RELEASE................................... 34 a- ~ ,

- LICENSE.075 Page 3 4.0 ENVIRONMENTAL SAMPLING STATIONS - RADIOLOGICAL.................... 35

\

fiqUEL 4-1 RADIOLOGICAL SAMPLE STATIONS...................... 37 IABLLS 4-1 ENVIRONMENTAL SAMPLING STATIONS- ~

RAD 10 LOGICAL...................................... 38 d

C l

. . . ~

LICENSE.075 Page 4 l

l 1.0 IN1 RODUCTION The Of fsite Dose Calculation Manual (ODCM) provides guidance for making release rate and dose calculations for radioactive liquid and gaseous  !

effluents from Arkansas Nuclear One - Units 1 and 2. The methodology is drawn I from NUREG-0133, Rev. O. Parameters contained within this manual were taken I from NUREG-0133 and Regulatory Guide 1.109 except as noted for site specific values. These numbers and the calculational method may be changed as provided for in the Technical Specifications. j 1

A specification for a given item will have a different specification number for each unit; therefore, in the ODCM, references to Technical Specifications will be made to the specification subjects. The specification subjects and numbers arc presented below:

Specification Number Subiect MQ .1 fdQ-2 Radioective Gaseous Effluents - Instrumentatica 3.5.7 3.3.3.9 Radioactive Liquid Effluents - Instrumentation 3. 5. 6 - 3.3.3.10 Radioactive Liquid Effluents - Concentration 3.25.1.1 3.11.1.1 Radioactive Liquid Ef fluents - Dose 3.25.1.2 3.11.1.2 Radfoactive Liquid Effluents - Waste Treatment 3.25.1.3 3.11.1.3 Radioactive Gaseous Effluents - Dose Rate 3.25.2.1 3.11.2.1 Radioactive Gaseous Effluents - Dose, Noble Gases 3.25.2.2 3.11.2.2 Radioactive Gaseous Effluents - Dose,-Particulates 3.25.2.3 3.11.2.3 Radioactive Gaseous Effluents - Radwaste Treatment 3.25.2.4 3.11.2.4 Radio 9ctive Gaseous Ef fluents - Gas Storage Tanks 3.25.2.5 3.11.2.6 Radiological Environmental Munitoring 4.30 3.12 L

l

_ - - . m ... m__ m _ . _ _ - . _ _ _ ~ . . _ - .. . __ _ - _.. . _ _ _ . _ .

4 - 8

~

. LICENSE.075

. Pace 5 a

2.0 LIQUID EFFLUENTS 2.1 Radioactive Liquid Effluent Monitor Setpoint The Radioactive Liquid Effluent Instrumentation Specification requires that the-radioactive liquid effluents be monitored with the alare/ trip setpoints adjusted'to ensure that the limits of the radioactive liquid effluent concentration specificat.ans are not exceeded. These concentrations are for the site. The alarm / trip setpoint en the liquid effluent monitor is dependent upon the dilution water flowrate, radwaste tank flowrate, isotopic composition of the radioactive liquid to be diccharged, a gross gamma count of the liquid to be dischcrged, background count rate of the moreitor , and the ef ficiency of the monitor.

Due to the fact that these are variables, an adjustable setpoint is used.

The setpoint must be calculated and the monitor setpoint set prior to the rel.ase of each batch of radioactive liquid effluents. The following methodology is used for the setpoint datermination for the following monitors.

ANo-1: RE-4642 Liquid Radwaste Monitor ANO-2: 2RE-2330 Liquid Radwaste Monitor 2RE-4423 Liquid Radwaste Monitor

1) A sample from each tank (batch) to be discharged is obtained and counted for gross gamma (Cs-137 equivalent) and a gamma isotopic snalysis is performed.

2) A dilution factor (DF) for the tank is calculated based upon the results of the gamma isotopic analysis cod the Maximum Permissible Concentration (MPC) of each detected radionuclide.

DF is calculated as follows:

DP = I, (C /MPC 3 g)  ! " TNG CTNG where, uf = dilution factor; Cy = concentration of isotope "i", (pC1/ml);

MPC f

= maximum permissible concentration of isotope "1",

(from 10CFR20, Appendix B, Table II, _ column 2 in .

pCi/ml);

C = total concentration of-noble gases (pCi/ml); and TNG

, MPC = 2E-4 (pCi/ml) per Technical Specifications.

TNG

3) The dilution water flowrate is, per Technical Specifications, the number of ANO-1 circulating water pumps in operation at the time of release. (Each circulating water pump has an approximate flowrate of 191,500 gpm.)

~ , -

~w w v e g r, s- - --

r -w.

LICENSE.075

'Page 6

4) The theoretical release rate, F , of the tank (bas.;h) to be released is expressed in terms of the difution water flowrate, such that for i cach volume of dilution water released, a given volume of liquid radwaste may be combined. This may be expressed as follows:

F, = PHPNUM x 191,500/DF ,

where:

F, = theoretical. release rate (gpm);

PHPNUM = number of ANO-1 circulating water pumps in operation; 191,500 = approximate flowrato of an ANO-1 circulating water pump (gpm); and DF = dilution factor as calculated in Step 2 above.

HEIE In the above equat.'.on, the theoretical release rate (F q) approaches zero as the dilution factor increases. The' actual flowrate (F ) will normally be equal to the A

theoretical release rate for high activity releases.

For_ low activity releases, the theoretical release rate becomes large and may exceed the capacity of the pump discharging the tank. In these cases, the actual release rate may be set to the maximum flowrate of the discharge pump.

l

5) The monitor setpoint is calculated by incorporating the monitor reading prior to starting the release (i.e., background countrate),

and a factor which is the amount of increase in the release concentration that would be needed to exceed the radioactive liquid concentration specification. The monitor setpoint is expressed as follows:

Mg = A*(K*Fg /F A ) +

where:

Mg = monitor setpoint (CFM);

A = allocation fraction for the specific unit. (Typically, these values are set at 0.65, but may be adjusted up or down as needed. However, the total site allocation can l not exceed 1.0.)

K = monitor countrate (CPM) expected based on the gross activity of the release. (This value is obtained-from a graph of activity (pCi/ml) versus output countrate for the monitor (CPM));

1 I

L

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

- LICENSE 075 Page 7 Fg/FA = number of times the activity would have to increase to exceed the radioactive liquid effluent-concentration specification; and B = background countrate (CPM) prior to the release.

To permit the computer to calculate the setpoint, an equation for the expected countrate (K) is expressed as follows:

K = Slope

• 10 A + Offset where:

Slope Loc of the detector resconse in CPM

" Log of activity concentration in pC1/ml S

g = Gross gamma (Cs-137 equivalent) cctivity for the tank (pCi/ml); and Offset = detector response (CPM) for the minimum detactable sample activity calculated from the calibration data.

HQIE I&C personnel use varying concentrations of Cs-137 to determine the response curve; therefore, a Cs-137 equivalent activity must be used to accurately predict the-countrate.

Combining terms, the equation for determining the monitor setpoint may be expressed as follows:

H = A * [(Slope

• 10 A + Offset)* F /F l +

3 A 2.2 Liquid Dose Calculation The " dose" or "dcae commitment" to an individual in the unrestricted arec shall be less than or equal to the limits specified in Radioactive Liquid Effluents-Dose Technical Specification. The dose limits are exi a per reactor basis. This value is cc1culated using the Adult as the maximum exposed individual via the aquatic foods (SPORT FRESHWATER FISH) and the potable water pathways.

2.2.1 Dose Calculations for Aquatic Foods The concentrations of radionuclides in aquatic foods are assumed to be directly related to the concentrations in water.

The equilibrium ratios between the two concentrations are called " bioaccumulation factors".

l N

-- - e e n

- .. m . __

E. .

LICENSE.075 Page'8 Two dif ferent pathways are calculated for aquatic foods: sport and commercial freshwater fish.

The internal dose "d" from the consumption of aquatic foods in pathway "p" to organ "j" of individuals of age group "a" from all nuclides "1" is computed as follows: (See Chapter 4 of NUREG-0133 and Regulatory Guide 1.109-12, equation A-3),

dp (r,0,a,j) =~If (1100*e I P*R g}*M*U,F-8*Qg D,f)

T1.e total dose from both aqvatic food pathways is then:

D(r,0,a,j) =Idp (r,0,a,j)

P where:

r n user-selected distance from the release point to the receptor Iccation, in kilometers. It may be different from the controlling distance _specified for the potable water psthway (0.4 km);

O = user-seleef.ed sector-(one cf sixteen 22.5* sectors surrounding the reactor site, designated N, NNE, NE,

... etc). This sector may be dif ferent from the controlling sector specified for the potable water pathway (S);

a = user-selected age group: infant, child, teen, adult.

It is the same controlling age group used in the potable watet pathway (adult);

j =- user-selected organ: -bone, liver, totn1 body, thyroid, kidney, lung, GI-LLI. It is the same controlling organ used'in the potable water pathway (liver);

{}= represents the :oncentration factor stored in the database; tid 15 Only one concentration factor is needed to represent the two pathways. since sport and commercial use the same bioaccumulation facto-for a given pathway.

1100 = factor -to convert from (Ci/yr)/(f t*/sec) to pC1/ liter;

-*~

LICENSE.075 Page 9 1

g

= decay constant of nuclide "i" in hr -8; tpu environmental transit time, release to receptor; HQII This value should be set to 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> (i.e., no decay correction) for the above equation in order to be consistent with the equation presented in Chapter 4 of NUREG-0133. For movieum individual dose calculations, this value is set to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, which is the minimum transit time recommended by Regulatory Cuide 1.109, Appendix A, 2.b.

B g

= bioaccumulation factor for nuclide "i", in pC1/kg per pCi/ liter. Cesium 1.as a site specific number based on carnivorous and bottom feeder sport fish of 400 pCi/kg pe. pCi/ liter (0CANOI.8408, dated April 13, 1984);

M = dimensionless mixing ratio (reciprocal of the dilution factor) at the point of exposure; U = annual usage factor that specifies the intake rate a

for an individual of age group "a", in kilograms / year. The program selects this usage factor in accordance with thu controlling age group "c" as specified previously by the user' F- = avetage flow rato in ft*/sec. This value is based on total dilution volume .for thm quarter divided by time into the quarter; Qg = number of curies of nuclide "i" released; and D = ingestion dose factor for age group "a", nuclide "i",

afj and organ "j", in mrem per pCi ingested. The program selects the ingestica dose factor ac rding to the-user-specified controlling age group "a" and controlling organ "j".

2.2.2 Dose Calculations for Potable Water The dose "D" from ingestion of watar to organ "j of individuals-of cge group "a" due to all nuclides "1" is caleMated at follows (See Chapter 4 of NUREG-013' and NRC

-Reg. Guide' 1.109-12, equation A-2):

LICENSE.075 Page 10

< NOTE 1

The potabl.e water pathway is used only during the time that the Russellville Water _ System is using the Arkansas River as-a water source. The Russellville Water Works will notify ANO when they are using the Arkansas River as L water source.

D (r,0,a,j) = I g 1100*e I I 'M*O*F-2*Q*D,g) where; r = user-selected distance (0.4 km) from the release point to the receptor location, in kilometers. It may be different frem the controlling distance selected for the aquatic food pathway; o = user-selected sector (s); (one of the sixteen 22.5' sectors surrounding the reac'c' si..e, designated N, NNE, NE, ... etc.). It may different from the controlling sector for the aque <c food pcttray; a = user-selected age group (infant, child, teen, adult).

The same controlling age group is used for all liquid pathways (adult);

j = user-selected organ (bone, liver, totnl body, thyroid, kidney, lung, GI-LLI). The same l ,

-controlling organ 18 used for all liquid pathways

! (liver).

{} = the expression in brackets represents the concentration factor, .tored-in the database; 1100- = factor to convert from (Ci/yr)/(ft 3 /sec) to pCi/ liter; M = dimensionless mixing ratie (reciprocal of the

! dilution factor) at the point of exposure; A

g

= decay constant of nuclide "1" in hr-8; and I

t = environmental transit time, release to receptor.

p l

NOTE l This value is set to 0. hours (i.e., no decay correct.fon) for the above equation l to be consistent with the equation presented in Chapter 4 of NUREG-0133.

t I

i l

I l

- LICENSE.075

• Page 11 U = annual usuge factor that specifies the intake rate for an individual of age group "a", in liters / year.

• The program selects this usage factor according to the user-specified controlling age group "a";

F = average flow rate in ft*/sec; this value is based on total dilution volume for one quarter divided by time into the quarter; Q3 = number of curies of nuclide "1" in the release; and D = ingestion dose factor, for age group "a", nuclide

• g3 "i", and organ "j", in mrem per pCi ingested. The program selects the ingestion dose factor according to the user-specifico controlling age group "a" and controlling organ "j". ~;

2.3 Lj, quid Pro _iected Dose Calculation The quarterly projected dose la based upon the methodology of Section 2.2 and is expressed as follows:

D =

qp 92*(DQC

• RP)I where:

D qp

= quarterly projected dose (mrem);

92 = number of days per quarter; D cumu ative dose for the quarter (mrem);

QC U s r current releasp (mrem); and RP T = current days into quarter; 3.0 GASEOUS EFFLUENTS 3.1 En gous Monitor Scipoints NOIE Sections 3.1.1 and 3.1.2 below detail two methods of calculating setpoints at ANO. These methods cover two dif ferent sets of monitors of which only one will be in-service at any one time.

LICENSE.075 Page 12 3 (1.1 - Batch Release Setpoint Calculations I-3.1.1.a This section applies to the following gaseous radiation ri.onitors (These releases are also monitored by the SPING aionitors in Section 3.1.2):

^

Ah0-1 RE-4830* Waste gas holdup system monitor bSD-2 2RE-8233 Containment purge 2RE-2429* Waste gas holdup system monitor

-* Theso monitors provide automatic isolation for the waste gas holdup systems.

The setpoints to be used during a batch type of release (i.e. , reactor building purge, release from the waste gas holdup system or any other non-routine release) will be calculated for each release before it occurs.

3 1.1.b The basic methodology for determining a monitor setpoint is based upon the expected concentration at the monitor (Cg ). This is in turn based upon the fraction of en MPC assigned to this release point.

Batch releases are maintained below the assigned HPC fraction by controlling the release rate. The calculated value of S may not exceed the equivalent of 1 MPC at site boundary.

S = 1.1 * (Cg*K) + (2.0

• B) where:

S = monitor setpoint (counts /sec);

Cg = Xe-133 equivalent concentration at the monitor (pri/ml);

K = conversion fsetor determined from response r curve of monitor (counts /sec per pCi/ml); and 2.0 = factor to acemmodate random coun; rate fluctuations; B = background count rate r the moniter (counts /sec).

. =. l LICENSE.075 l Page 13

, 3.1.2 Eberline SPING (Final Effluent) Monitor Setpoint Calculations 4 3.1.2.a This-section applies to the following gaseous radiation monitors:

AND-1 RX-9820 Containment Purge RX-9835 Hydrogen Purge /Emerg. Pen. Room Vent.

RX-9830 Fuel Handling Area RX-9825 Radwaste Area ANO-2 2RX-9820 Containment Purge 2RX-9840 PASS Bldg.

2RX-9845 Aux. Bldg. Ventilation 2RX-9835 Hydrogen Purge /Emerg. Pen. Room Vent.

2RX-9830 Fuel Handling Area 2RX-9825 Radwaste Area 2RX-9850 Low-Level Radwaste Storage Building The determination of setpoints for the above monitors is based on_ an assigned fraction of the MPC of noble gas _ activity at the site boundary, (XE-133 equivalent) released frem the above release points.

The total of these fractions is always less than 1.00. The assigned fractions are based on the vent; flow rates, atmospheric dilution rate, and the ventilation system (s) in operation.

NOTE The fact that an affluent monitor is in alarm does not necessarily mean that radioactive gases are being released at such a rate that the MPC limit is being exceeded. The alcrm would indicate that radioactive gases'are being releasea at a rate that is exceeding the fractional allocation of an MPC allotted to that particular release point. Consideration must be given to the release ~ rate of radiocctive gases via all of the release pathways. -

The initial fracticns of an MPC allocated to the i release points are given below. The allocations may l be changed as needed, to allow for operational I transients, but may_not exceed site total of 1.00.

p l

L li I

f

LICENSE.075 Page 14 Monitor Monitor Fractional g Number Name Allocation RX-9820 Containment Purge 0.1000 RX-9835 Hydr. Purge /Emerg. Pen. 0.0001 Rm Vent.

RX-9830 Fuel Handling 1.rea 0.1500 RX-9825 Radweste Area 0.2000 Monitor Monitor Fractional Number Name Allocation 2RX-9820 Containment Purge 0.1000 2RX-9840 PASS Bldg. 0.0100 2RX-9845 Aux. Bldg. Ventilation 0.0100 2RX-9835 Hydr. Purge /Emerg, Pen. 0.0001 Rm. Vent.

2RX-9830 Fuel Handling Area 0.1500 2RX-9825 Radwaste Area 0.2000 2RX-9850 Radweste Storage Bldg. 0.0100 1i0I1 The setpoints to be used during a batch release (i.e., reactor building purge, release from the waste gas holdup system) wi.il be calculated for each release before it occurs.

3.1.2.b SPING monitor setpoints may be calculated as follows:

Setpoint (pC1/cc) = A

• Xe-133 eo (uci/ce)

F*1.3215E-9*TMPC where.

A = allocation fraction (the fraction of an MPC at the site boundary (of Noble gas Xc-133 eq activity) assigned to the particular release point);

Xe-133 eq = Xenon-133 equivalent concentration; F = discharge flow of the particular release point in CFM; 1.3215E-9 = 2.8317E-2(cm/cf)* 2 8E-6(sec/m8 )

60(sec/ min) .

LICENSE.075 i

Page 15 l

where:

2.8E-6 = the annual average gaweous dispersion-factor (corrected for radioactive decay) as defined in Section 2.3 of the ANO-2 SAR; and -

TMPC = total MPCs at site boundary.

3.2 Airborne Release Dose Rate Eftects 3.2.1 Noble Gas Release Rate 3.2.1.a To calculate the noble gas release dose rate, the average ground-level concentration of radionuclide "i" at the receptor location must first be determined from the following equation. (See Regulatory Guide 1.109-20 equation B-4).

xg (0) = 3.17 x 10'

• Q 3

• D1X/Q(0) where:

xg (0) = average grcund level concentration in pCi/m' of nuclide "1" at the user-specified controlling distance in sector 0 (1.05km);

(0)  : one of the sixteen 22.5' sectors surrounding the reactor site, designated N, NNE, NE, ... etc. (WNW);

3.17x10"= number of pCi per Ci dividad b;' the number of seconds / year; Q3 = release rate of nuclide "1" in curies /yr and D1X/Q(0) = annual average gaseous dispersion factor (corrected for radioactive decay) in the sector at angle "0" at the receptor location in sec/m . This value is 3

2.8E-6 sec/m* for short term releases.

The annual dose to the total body and skin due to noble gas can be calculated according to Sections 3.1.2.b and 3.2.1.c.

3.2.1.b Annual Total Body Dose Rate The annual average total body dose rate to the maximally exposed individual is calculated as i

follows:

D (0) = RBPF*S7 *Ig x g(0)*DFB f

y ;i- ,

.. LICENSE.075

.' Pege 16 where:

D (0) = total body dose rate due to immersion in a semi-infinite cloud of gas at the controlling distance in sector "0",

in mrem /yr. The program computes one total body dose rate value for each sector in which the user has specified a controlling distance and reports only the maximum value; O = one of sixteen 22.5' sectors surrounding the reactor site, designated N,'NNE, NE, .... etc.;

(WNW); i RBPF = Reactor Building Purge Factor - This factor is used to calculate the length of time (fractional duty cycle) that the purge fans will be in operation.

It is calculated by comparing the highest dose rate (DOSER) to its applicable release limit, taking into account the allocation factor for the release point (RBPF = Allocation

• Limit / DOSER). This factor is calculated only for Unit One and Two Reactor Building Purges. For all other releases, this factor is set to 1.0; S

p = dimensionless attenuation factor accounting for the dose reduction due to shielding by residential structures. The NRC recommended value is-0.7 (for maximum individual);

xj (0) = average ground-level concentration of nuclide "1" at the receptor location in the sector at angle "0" from the release point, as defined in Section 3.2.1.a; and l DFB = total body dose factor for a semi-I infinite cloud of radionuclide "i",

which includes the attenuation of 5 g/cm2 of tissue, in mrem-m 8 /pCi-yr

[ _3.2.1.c Annual Skin Dose Rate

! The annual dose rate to the skin of the maximally exposed individual due to noble gases is calculated as follows. (See Regulatory Guide 1.109-20 equation B-9)

LICENSE.075 l

Page 17 S T D (0)=RBPF 1.11*S p *I j (x g(0)*DFg ) + I g (x g(0)*DFSg )

where:

D (0) = skin dose due to immersion in a semi-infinite cloud of gas at the user-specified controlling distance in sector 'IB", in mrem; EQIl The program computes a skin dose value for each __

sector in which the user has specified a controlling distance, but prints out only the maximum value.;

RBPF = Reactor Building Purge Factor as lefined in Section 3.2.1.b.

1.11 = average ratio of tissue to air energy absorption coefficient; S = d,xmensionless attenuation factor F

ac:ounting for the dose reduction due to shielding by residen' c lal strtctures. The value is 0.7 (for maximum individual);

=

x,(0) is the average ground-level _

concentration of nuclide "1" at the receptor location in the sector at angle "0" from the release point, as n defined in Section 3.2.1; O = one of sixteen 22.5' sectors surrounding the reactor site, designated N, NNE, NE, ... etc.,

(WNW);

i DF = gamma air dose factor for a semi-I infinite cloud of radionuclide "1",

in mrad-m 8 /pCi-yr; and

= beta skin dose factor for a DFS' semi-infinite cloud of radionuclide "i", which includes the attenuation by the outer " dead" layer of skin, in mrem-m 3

/pCi-yr.

LICENSE 075 Page le 3.2.2 1-131, Tritium'and Particulate Eolense Dose Rate Effects-The annual dose rate to the maximally exposed individual for 1-131, tritium and radionuclides in particulate form with half-lives greater than eight days is calculated as follows:

DR = RBPF

• DR + DR0 + DR wnare:

KBPF = Reactor Building Purge Factor as defined in Section 3.2.1.b; DR = dose rate to the controlling age group (infant) associated with the inhalation of radiciodines and particulates, as calculated in Section 3.4.1.b; O =

DR dose rate from direct exposure to activity deposited on the ground plane, as calculated in Section 3.4.1.a; and DR" = dose rate to the controlling age group (inf ant) and the controlling organ fo ingestion of food (milk),

as calculated in Section 3.4.1.d.

Calculation of the annual dose rate considers the infant as the most rastrictive age L.oup. The organs that are considered as '

contributing to the dose rate are: skin, bone, liver, total body, thyroid, kidney, lung, and GI-LLI. The food pathway for the infant is considered to be from milk only. All three pathways will contribute to _the total body dose, while the skin will be affected by only the ground plane-pathway. The other organs are affected only by the inhalation and food pathways.

3.3 Dose-Due to Noble Geses The air dose in unrestricted areas due to noble gases released in gaseous effluents shall be less than or equal to 5 mrad for gamma radiation and 10 mrad for beta radiation for any calendar quarter for each unit. The i objective of less than or equal to 10 mrad of gamma radiation and 20 mrad of beta radiation for a calendar year per unit (2.5 mrad and 5 mrad s respectively per quarter) should be used for planning releases.

1 i

u l

i

, a LICENSE.075 Page 19 NOTE 4 The following equations have beca simplified from equations in NUREG-0133, Rev. O, in that there are no free-standing stacks at ANO.

The equations were further simplified in that there are no long term (i.e., continuous) releases. The individual stack vents are sampled weekly and are assigned a release period of 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> per sample (i.e., considered as short term (batch) releases). Individual samples are to be taken for each vaste gas tank release and reactor building purge.

~

3.3.1 Beta and Gamma Air Doses from Noble Gas Releases Using the average ground level concentration of radionuclide "i" at'the receptor location calculated in Section 3.2.1.a. the associated annual gamma or beta air dose may be calculated by the following equation. (See Regulatory Guide 1.109-20 equation B-5.)

D (0) nr D0 (0) = I f --(xg (0)*(DF T t B gr DF j) where:

I O D (0) gr D (0) = the gamma or beta air dose for the controlling distance in sector "0". (Only the maximum value is reported), and T 0 DFg cI DF j = gamma or beta air dose factors for a uniform semi-infinite cloud of nuclide "1", in mrad-m8 /pC1-yr.

3.4 Dose Due to I-131, Tritium, and Particulates in Gaseous Effluents The calculational methodology for determining the dose to an individual from I-131, tritium, and radionuclides in particulate form with half-lives greater than 8. days in gaseous ef fluents released to unrestricted areas as specified in the Technical Specifications is in this section.

The child is the controlling age group unless stated otherwise.

The inhalation and ground plane pathways are conaldered to exist at all locations. The grass-cow-milk, grass-cow-meat, and vegetation pathways are used where' applicable.

It is assumed that fodines are in the elemental form.

A dispersion parameter of 2.8E-6 sec/m$ (per ANO-2 FSAR, Section 2.3.4.4) is used for "w" in the inhalation pathway since the majority of gaseous activity released from the site is within the 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time frame (i.e., reactor building purges and waste gas decay tanks).

t l

s e LICENSE.075 Pago 20 The equation is:

D OT = D +D +D +Db + D" + DF wheret D = total dose; D = dose contribution f rom ground plane deposition as calculated in Section 3.4.1.a; D = dose contribution from inhalation of radioiodines, tritium, and particulates (>8 days) as calculated in Section 3.4.1.b; Y

D = dose contributions from consumption of vegetation (defined as -

produce) for humans and stored feed for cattle. See Section 3.4.1.c for calculations; D = dose contributions from consumption of fresh leafy vegetables (defined as garden products) for humans and pasture grass 'or ca t t l e'. See Section 3.4.1.c for calculations; D" = dose contribution from consumption of cow's milk; and NOTE .<

> Consumption by the cow of both stored feeds and pasture grasses is t aken into account when calculating this dose contribution. Concentration factors for both food sources are calculated.

I =

D dcse contribution from consumption of meat.

NOTE Consumption by meat of both stored feeds and pasture grasses is taken into account when calculating this dose contribu-tion. Concentration factors for both types of animal feed are calculated.

3.4.1 Total Dose from Atmospherically Released Radionuclide After the calculation of the concentration factors from the spplicable parts of Section 3.4.1, the maximum ind.fvidual dose as calculated for controlling age group "a" and controlling organ "j", in sector 0 at the controlling distance "r" is given

.from:

D (r,0,j,a) (Section 3.4.1.a) for ground plane deposition

LICENSE.075 Page 21 I

D (r,0,j,a) (Section 3.4.1.b) for inhalation D (r,0,j,a) = I DFI 19{C"g(r,0)0 for produce b I D (r,0,j,a) = I DFI g U,'C ( r ,0 ) for leafy vegetables D"(r,0,j,a) = I DFI g ,U"c"(r,0) for cow's milk I

D (r,0,j,a) = I DFI jp U C (r,0) for meat where:

a = controlling age group (infant, chilt. , teen, or adult);

j = controlling organ (bone, liver, total body, thyroid, kidney, lung, or GI-LLI);

r = user-selected distance from the release point to the receptor location in a particular sector, in kilometers. (The controlling distance is the same for all airborne pathways, 1.05 km.);

J B = one of sixteen 22.5* sectors surrounding the reactor site, designated N, NNE, NE, ... etc., (WNW);

DFI = dose conversion factor for ingestion of nuclide "1",

ija organ "j", and age group "a", in mrem /pCi; SDIE Values used in these tables are taken from Tables E-11 through E-14 of Regulatory Guide 1.109. DFI is selected according to thecontrolkd$gorganandagegroupasspecified in the database.

U a

,U',U",U a a a

= ingestion rates for produce, leafy vegetables, cow's milk, and meat, respectively, for individuals in age group "a". Velues used are taken from Table E-5 of Regulatory Guide 1.109.);

LICENSE.075 Pcgo 22 C,D,C,D = concentration of nuclide "1" for produce, leafy vegetables, cow's milk, and meat, respectively, in pCi/kg or pCi/ liter.

The program calculates that scximum individual dose for each sector surrounding the plant in which the user has specified a controlling distance for each of the following pathways: A) ground plano deposition; B) inhalation and the ingestion of; C) produce; D) Icafy vegetabics; E) cow's milk; and F) meat.

Only the receptor point receiving the maximum dn== v41oa in printed.

3.4.1.a Dose from Ground Plane Deposition The dose D from direct exposure to activi+y deposited or the ground plane is calculated as follswr (see Regulatory Guide 1.109-24, equations C-1 and C-2):

-1 t D (r.0,j,a) e (Sp*1.0 x 10'2* I; X g

• (1 - e I h }

• D0Q( r ,0 )

• Q

• DFG )

3 3 where:

r = user-selected distance from the release point to tha receptor location in a particular sector, in kl.lometers. The controlling distance is the same for all airborne pathways (1.05km); /

0 n one of sixteen 22.5* sectors surrounding the reactor site, designated N, NNE, NE ...

etc., (WNW);

a = user elected age group (infant, child, teen adult) which is the same controlling age group used for all airborne pathways (child);

j = user-re acted organ (bone, liver, total

• body, thyroid, kidney, lung, GI LLI) which is the same controlling organ used for all airborne pathways;

(} = represents the concentration factor stored in the database; S = dimensi nless attenuation factor accounting F

for the dose reduction due to shielding by residential structures. The value is u.7 (for maximum individual);

h 1

,m ... . . , , ,,,

LICENSE.075 Pago 33 1.0 x 10 88 -

number of pCf per C1; y = decay constant of nuclide "1" in br ;

t h

= length of time over which the accumulation ja evaluated (nominally 15 yearr, which is  !

the approximate midpoint of facility ,

operating life or 1.31 x 10' hours)- 1 l

D0Q(1,0) = average relativo deposition of the effluent i at the receptor location "r" in sector "0",

consideting depletion of the plume during transport, f -8; Q3 = release of nuclide "1" in curies, and l

DrG = open field ground plane done conversion 33 (total body or skin) factor for organ'"p'"1", in mrem-m from radionuclide 8 /pC1-br.

The dosu factor is selected according to the usur-specified controlling age group "a" and controlling organ "j".

3.4.1.b Dose from Inhalation of Radionuclides in Air The dose D I to organ "j" of age group "a" associated via. inhalation of radiotodines and particulates is (see Reg. Guide 1.109-23, Equations C-3 and C-4):

I D(r,0,j,a)=3.17x10'*R,*y Qg

• D2DPX/Q(r,0)

• DFAg where:

r = user-selected distance from the release point to the receptor location in a particular 4ector, in kilometers. The controlling distance is the same for all airborne pathways (1.05 km);

O = one of sixteen 22.5* sectors surrounding the reactor site, designated N, NNE, NE ...

etc. , (k'NW);

j = user-selected organ (bone, liver, total body, thyroid, kidney, lung, GI-LLI) and is the same controlling. organ as that used for all airborne pathways;

.' LICENSE 075

• Page 24 u = user-selected age group (infant, child, teen, adult) and is the same controlling -l 1, age group as that used for all airborne pathways; 3.17 x 10 6 = number of pCf/Ci divided by the number of

• seconds / year;

= annual air intake for individuals in age R" group "a" (in m*/ year). The air intake factor is selected in accordance with the user-specified controlling age group; Qg = release of nuclide "1" in curies; D2DPX/Q(r,0) = annual average atmospheric dispersion factor of the radionuclide at the receptor location "r" in sector "0" (in sec/m') as calculated; and NQII This includes depletion (for radiciodines and particulates) and radioactive decay of the plume.

l DFA,,, = inhalation dose factor for radionuclide l

'# "1", organ "j", and age group "a". The inhalation dose factor is selected in accordance with the user-specified controlling. age group "a" and controlling organ "j".

3.4.1.c Dose from Nuclide Concentrations in Vegetation l

l E01E To reduce the computational overhead of the computer, the calculations for done resulting from nuclide concentrations in forage, produce and leafy vegetables is performed in three steps.

First, the concentration t. ors (CF) are computed and stored in the database, ihe concentration factor

includes all the parameters that are considered conr ant for each nuclide and i 1 cultural activity, such as the radioactive decay constant, removal rate constant, exposure time, etc.

LICENSE.075

• Page 35 6

, Second, the deposition rate from the plume is multiplied by the concentration factor and the N' nuclide activity to produce the nuclide concentration as follows:

C{(r,0)=CFg* D0')(r,0)

• Q g where:

C{(r,0)=concentrationofnuclide"i"atthe receptor location (r,0);

CF g = concentration factor of nuclide "1"!

D0Q(r 0} = relative deposition of nuclide "1". For the short term dispersion option, D0Q is replaced by (F x D0Q), where F is the short term dispersion correction factor; Qg = quantity of nuclide "i" released in curies.

1 For carbon-14 and tritinm, the nuclide concentration is talculated from the concentration factor times the decayed-and depleted X/Q for radiofodines and p' articulates-(D2DPX/Q), times the quantity of nuclide 1" released in curies. For the short term dispersion option, D2DPX/Q is replaced by F x D2DPX/Q, where F in the shortl term dispersion correction factor. i C{(r,0)=CF.7

• D2DPX/Q(r 0)

• Q.7 for tritium, and C$. (r,0) = CFn '

• D2DPX/Q(r,0)

• Q . for carbon -14 Third,-the nuclide concentrations for'a particular pathway (produce, leafy vegetables, cow's milk, and meat) are summed and multiplied by: 1) the ingestion rate for a particular ago group and 2) the dose conversion factor:

D(r,0,j,a) = I g (DFi),*U,*C{(r,0) g where:

r = user-selected distance from the release point _to the receptor location in a particular_ sector, in kilometers (1.05 km);

O .= one of sixteen 22.S' sectors surrounding the reactor site, designated, N,-NNE, NE-

~

... etc., (WNW);

4

= -ve,m,~ ea, w 4- e- e -- 9,, - - . - e v er e ,,y wee,-- --.,,w,w..,wn---.,e-,,. ,,,,,-,,w---m.r,,m.,-w-. ..-,y- wn-w.,-,-g.,r-%,e- ,w ,y,,e w,w*

LICENSE.075 l Page 26 l j = user-selected organ (bone, liver, total body, thyroid, kidney, lung, G1-LL1), and i

is the same controlling organ as that used for all airbune pathways; a = user selected age group (infant, child, teen, adult), arid is the same controlling age group as that used for all airborno pathways; DTI fja

= dose conversion factor for itgestion of nuclide "i", organ "j", and age group "a",

in mrem /pC1, according to the controlling orgen and age group l l

0

= cnnual ingestion rate of food in a  !

particular pathway (kilograms / year or l Ifters/ year) for individuals in age group '

"a", according to the controlling age group; and >

C'g( r . 0 ) = concentration of nuclide "1" at the receptor location '.r,0).

3.4.1.c.1 Calculatin d egetation Concentration Factors NUREG-0133 calculations for radiojodines and

, particulata radionuclides (except tritium and carbon-14), the concentrat. ion factor of nuclide "1" in and on vegetation is estimated as follows:

t CF" =-

CONST*( q )*e g h,g v 1-where:

Y CT A

= concentration factor of radionuclide "1" in vegetation-(forage, produce, or.

leafy vegetables), it, m hr/kg; 8 CONST = 1.14 x 10' number of pC1 per C1 (10.88) divided by the number of hours per year (8760);

r = is the fraction of deposited activity retained on crops, leafy vegetables,

- or pasture grass, from airborne radiofodine and particulate deposition:

r = 1.00 for radioiodines r = 0.20 for particulates 4

e , .. ,.. , ..,.-,,,,,_,....,,,.,..+.n.-,n.., --,n..- .,n-w---_.,n.- ,.,,,.n.v-,w.-,.,.~.,. n., ,-..,,-~v.,-, . - ,, , _

LICENSE.075 Page 27 Y = ogricultural productivity (yield or v

vegetation area density), in kg (wet weight)/m8 :

Y = 2.0 kg/m8 for stored animal 8

feed for grass-animal-man pathways Y = 0.7 kg/m8 for pasture grass P

for grass-animal-man pathways Y = 2.0 kg/m8 for leafy 8

vegetatian (fresh) for crop / vegetation-man pathways Y = 2.0 kg/m8 for garden produce 8 (stored vegetables) for crop / vegetation man pathways 1

3

= is the decay constant of nuclide "1" in hr'8; t

h

= is a holdup time that represents the time interval between harvest and consumption of the food, in hours:

tf = 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> for pasture grass consumed by animals t

h r 2160 hours0.025 days <br />0.6 hours <br />0.00357 weeks <br />8.2188e-4 months <br /> for stored feed consumed by animals t = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for leafy h

vegetables consumed by humans ,

t = 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br /> for produce h

consumed by humans f = is_the fraction of leafy vegetables or_ "

produce grown-in garden of interests f = 0.76 for the fraction of produce ingested, grown in garden of interest. (This is f in equation C-13 of ReguIatory Guide 1.109)

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

LICENSE.075 Page 38 f = 1.00 for the fraction of  ;

leafy veratables grown in  !

garden of interest. (This  ;

is f i in equation C-13 of Regulatory Guide 1.109) i e

f = 1.00 for all other pathways 3.4.1.c.2 Concentration Factor for Carbon-14 i

For carbon-14, the concentration factor in and oli vegetation is estimated as follows (see Regulatory Guide 1.109 26, equation C-8): '

Cri. = 2.2 x 10'

• p I wheret Cri.= concentration factor of' carbon-14 in and on vegetation, in m 8hr/kg; and p = la defined as the rat 20 of total annual release time (for C-14 atmospheric releases) to the-total -

annual time during which

_ photosynthesis occurs _(taken to be 4400 hours0.0509 days <br />1.222 hours <br />0.00728 weeks <br />0.00167 months <br />), under the condition that the value of "p" should never exceed unity. For continuous C-14 releases, "p" is taken to be unity.-

(Thus,thevalueof2.2x10'isstoredforCri.

in lieu of a site specific value for."p".)

3.4,1.c.3 Concentration Factnr ter Tritium ,

The concentration f actor for tritium in vegetation is calculated from the tritium concentration in air surrounding the vegetation (see Regulatory Guide 1.109-27 equation C-9):

CF{= 1.2 x 10' '

11

where:

CT{= concentration ' factor for tritium in vegetation (in m 8 hr/kg); and 11 = absolute humidity at the location of the vegetation, in g/m*. . (The regulatory default value for "H" is 8.0 grams /m'.)

(Thus, the value 1.5

• 10' is stored for CF*T i" lieu of a site specific value for "ll".)

i E

i

~ . - . . .5.,. y , , ,, ...m.. .,. y.=-. u. , _

..r._ . - . , , . . .. p m ., o r w .%.. -, ,

. LICENSE.075 ,

Page 29 l 3.4.1.c.4 ((uclide Concentrations in Produce and Leafy y,egetables

[

The concentrations _in and s produce and leafy vegetables of a.11 radiofodine and particulate nulcidra "1" (except carbon 14 and tritium) are calculated as follows:

C{(r,0)=CF{*D0Q(r.0)*Q g for produce; and C (r,0)=CT

• D0Q(r,0)

• Q g for leafy vegetables where Cr}= concentration factor of nuclide "i" in produce; r

CFf = concentration factor of nuclide "1" in leafy-vegetables; (NotethatthedifferencebetweenCF{andCFf are the values for t and f .)

h i  ;

D0Q(r,0) = relative deposition of the radionuclide "1" at the receptor (r,0); and Qg = release of nuclide "1" (in curies).

The C ' and 11' nuclide concentrations are 5

calculated from the concentration = factors times the decayed and depleted radiolodine relative deposition D2DPX/Q times the fraction grown in the garden of interest (f = 0.76, f3 = 1.0): .

g V

• C"T( r ,0 ) =CFh*D2DPX/Q(r,0)*Q T g C (r,0) = CF

• D2DPX/Q(r,0)

• Q '* Il I#

T tritium ,

C!.(r.0)=CFi.*D2DPX/Q(r,0)*Q.*f g.

Ch.(r,0) = CFk.

• D2DPX/Q(r,0)

• Q .

• f for carbon-14 i

i L

1

..  ;....-_ .-,.-.=-.-..,..-.__.._.,__.-a_-..- , . , , , .- . , , , - . , , , , , , , . - .

~

.( 4 LICENSE.075 Page 30

.$.4.1.d Nuclide Concentration in Cow's tillk The radionuclide concentration in cow's milk is dependent upon the quantity and contaminetton level of feed consumed by the animal. The concentration is estimated (see Regulatory Guide 1.109 27, equations C-10 and C-11) as follows:

- C"(r,0) = {F,*QF* '*lI*I*CF{4 p s (1 - f )*CF p + f *(1 - f,)*CF ])*D(r,0)*Q 3 ,

where: ,

C"(r,d) = is the concentration of nuclide "1" in cow's milk at the receptor location (r,0),

in pCi/ liter;

{} = the expression in brackets represents the concentration factor. (Note that the concentration factor for cow's milk involves two different vegetation concentration factors (see below).);

F

= average fraction of the cow'- daily intake of radionuclido "1" (which appears in each liter of milk) _in days / liter;_

Qp = amount of feed consumed by the cow per day, in kg/ day (wet weight);

y = decay constant of nuclide "1" in br*8; a

t f

= average transport-time of the activity from the feed into the milk and to the receptor ,

(a value of 2 days is airsumed);

f = fraction of the year that cows graze on P

pasture; f = fraction of daily feed that is pasture 8

grass when the cow grazes on pasture; l

l- Cr{ = veg' etation concentration factor of nuclide L "I on pasture grass with the holdup time l t, 0 days, in pCi/kg. (Refer to the

=

elplanation of the vegetation concentration j' factor calculation);

t-

!- = vegetation concentration fa9 tor of nuclide CF"I ' 't" in stored feeds with the holdup time th j

! 90 days, in pC1/kg. (Refer to the l explanation of the vegetation concentration factor calculations);

l'

LICENSE.073 page 31 D(r,0) = relative deposition D0Q(r,0) of the radionuclides, except carbon-14 and i tritium. For carbon-14 and tritium, the  ;

decayed and depleted dispersion factor  :

D2DPX/Q(r,0) for radiolodines and  !

particulates (in sec/m') is used; and Qg = is the release of nuclide "i" in curies.

3.4.1.e Nuclide Concentration in Heat The radionuclide concentration in meat is dependent upon the quantity and contamination level of feed consumed by the animal. The concentration is esti- i mated (see Regulatory Guide 1.109-27, equations C-11 and C-12) as follows: -

- Cf(r,0) = (F g*Qp*e ** [ f *f,*CF" + (1 - f )*CF + f p*(1 - f,)*CF'g ]}*Drr 0)*Q g wheret lid 1L All parameters used in this pathway are for beef cattle.

f C j (r,0) -= concentrction of nuclide "i" in animal flesh at the receptor location (r,0) in-pCi/ liter;

{} = the expression in brackets represents the concentration factor (Note that the concentration factor for meat involves two different vegetation concentration factors);

F = average fraction of the animal's daily f

intake of radionuclide "1" which appears in esch kilograr. of 'ilesh (in days /kg);

Qj- = amount of feed consumed by the animal per day in kg/ day (wet weicht);

1 =- decay constant of nuclide "i" in hr*8; 3

h

++"* ret <cne-- - erw,---rue-4 cc w e- w r , - - , - . - .es-w-v-h<r-d-c- +,c e . s- y.v- -ty ..n *<--wry -

,. r ve ery e-+ tt

LICEllSE.075 Page 32 t- = average time from slaughter of the animal 8

to consumption by humans (20 days);

f = fraction of the year that animals graze on I) pasture; f = fraction of delly feed that is pasture a

grass when the animal grazes on pasture; V =

CF vegetation concentration factor of nuclide I "1" on pasture crass with the hoidup time th = 0 days in pCi#.g. (Refer to the explanation of the vegetation concentration factor calculation);

CFf = vegetation concentration factor of nucl(de "1" in stored feeds with the holdup time t h

= 90 days, in pC1/kg. (Refer to the explanation of the vegetation concentration factor calculation);

D(r,0) = relative deposition D0Q(r,0) of the radionuclidos, except carbon-14 and tritium. For carbon-14 and tritium, the decayed and depleted dispersion factor D2DPX/Q(r,0) for radiolodines and particulates (in sec/m') is used; Q3 = is the ralease of nuclide "1" (in curies).

3.5 Gaseous Effluent "Proiected Dose" Calculation 3.5.1 The quarterly projected dose is based upon the methodology of Sections 3.3 and 3.4, and is expressed as follows:

U U

= QC RP D

• 92 qp 7

where:

U qp

= Quarterly projected dose (mrem);

D cumulative dose for the quarter (mrem);- i QC-D gp = dose for current releree (mrem);

T' = current days into quarter; and 92 = number of days per quarter.

~ . _ _. ..~___ _ _ _ _ _ . _. _ _ _. _ . _ _ _ _ _ . ___ _ - _ . _ _ _ . _ _ _

~

LICENSE.075

. Page 33 3.6 Dose to the Public Inside the site Boundary. '

3.6.1 Liquid Releases Dose to the public inside the site boundary dae to liquid releases will be due to ingestion of fish caught from the -

discharge canal and exposure to sediment along the discharge

anal bank while fishing.

3.6.1.a Dosn Due to ingestion of Fish  ;

Dose due to ingestion of fish is calculated using the methodology given in Section 2.2, Liquid Done Calculation.

3.6.1.b Dose Due to Exposure to Shoreline Sediments Dose from external exposure to shoreline sediments is calculated from equation A-7 of Regulatory Guide 1.109, Rev. 1, 10/77.

U *H *W - -

= 11v,000 ap p *I '

R f *T*D,gg*(exp(-(t g )]*(1-exp(-Agbt )

where:

R apj

= is the total annus! dose to organ "j" of individuals of age group "a" from all of the nuclides "i" in pathway in mrem /yr; ,

U = is the usage f6ctor that specifies exposure >

1. P time for the riarimum individual of age group "a'? in hours from Table E-5 of Regulatory Guide 1.109. 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> for shoreline recreation for a teen was chosen. '

Adult is the controlling age group for ingestion but the maximum usage factor (teen) was used rather than the adult factor to ensure a conservative dose estimate; H = is the mixing ratio (reciprocal of dilution E facter);

W = is the shoreline width fistor from Table A-2 of Regulatory Guide 1.109< The discharge canal value of 0.1 was chosen; F = is the flow rate of the liquid effluent in ft*/sec. This war determined by:

1(ft'/sec) = waste volume-(gal /yr) * .134 ft'

• 1 vr

• 1 hr 1 gal 8760 hr 3600 sec

_ __ _ a _ J e n.

., - - . ,.-.,._.. . c.,- _ -- --,.,,-,.4._,.., ,,.e. , , , ,-----w ---9y-... -- r,, ,.y y

LICENSE.075 Page 34 Q3 = is the release of nuclide "1" in Cf/yr; 7 = is the radioactive half-life of nuclide i

"i", in days, from Radioactive Decay Data Tables. Technical Information Center, U. S.

Dept. of Energy, 1981; D = is the dot e factor specific to age group agp j "a", nuclide "i", and otgan "j" frem Table E-6 of Megulatory Guide 1.109; 1 = is the radioactive decay constant of I nuclide "i" in hr-3; t = is the average transit time for nuclides to E reach the point of exposure. A value of 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> was chosen due to the proximity of the discharge canal to the plant; and t

b

= is the period of time for which sediment is exposed to the contaminated water in hours.

The mid-point of plant operating life, 15 years was chosen per Regulat :y Guide 1.109.

3.6.2 Airborne Release 3.6.2.a Dose due to noble gases Dose to fisherman at the dis.narge canal can be calenlated by the ratio of dispersion factor for the distnarge canal (1.6E-4 sec/m' from Table 2-45 FSAR, Unit 1, 100 meters downwind in a southerly direction) and the usage factor of 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> of shoteline -

recreation to the values used in Section 3.3 of the ODCM.

Dose at discharge canal = D (0)* 1.6E-4

• 67 hr 2.8E-6 8670 hr /

T where D (0) is the noble gas dose calculated by Section 3.3.

3.6.2.b Dose due to iodina, tritium and particulates from gaseous effluents Section 3.4 calculates total dose for fodine, tritium and particulates as the sum of:

OT F >

D =D +D +D +D + D" 4 D

- . . . - = . - _ - - - _ - - . _ . _ . - . ~ _ . . . .

11 CENSE.075 Page 35 where:

' U D = ground plane deposition; DI = inhalation; D* =-consumption of vegetation; D = consumption of fresh leafy vegetabics; D* = consumption of milk; and DF = consumption of meat and poultry; The only contrJbutions relevant to fishing activities at the discherge cansf are gyound plane deposition and inhalation. As D and D are not independently avellable, a conservative estimate can be cbtained by using the some correction inctor developed for noble gas dose to the total dose calculated-in Section 3.4 for -f odino, t ritium and particulates. Depletion of the plume as it travels downwind can be ignored since the frcction remaining in the plume at 100 meters (discharge canal) and 1000 meters (site boundary) are both greater than 907,according to Figure 3 of Regulatory Guide 1.111.

The only activity ~inside the plant site by members of the public thet might contribute a significant ae is fishing along the banks of the discharge canal.

Travel along public roads would involve short exposure time and tours of the facility are conducted according to radiological control procedures enforced at the plant to control exposure. Fishing .is the only uncontrolled activity.

A0 ENYlRONMENTAL SAHpLING STATIONS - RADIOLOGICAL Environmental samples will be collected as specified in the Technical Specifications. The approximate locations of selected sample sites are shcwn on Figure _4-1 for illustrative purposes.

Table 4-1 lists the approximate distances cnd directions of the sample stations from the plant.

L E ,

,f - . . . . . -- .- _ _ - --. - - _. .-- . _ - - -

f. . . .

1

• LICENSE.075 ,

• Page 36  ;

L i

i ADIOLOG1 CAL SAMPLE STAT 1ONS

'I t

'.~.

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

'. p : ,,,, yjg:s (

k ]

rll ,

j ,, ; S i l '!il I i W V?%.% iwJ '

% kJ

?! M ! '@ ' ! 'j ' : T +bdl dlP 9":, d b' '>> li'lI i,e. #

..! i ' /

pt jptl ' i il l , :p 5 : - - - ', w 4 I ,  ;

,4 I O 1 j lt __. ^T*,

3. , g ,

L  ! ,.I A., , k ,,

^ ** I '

f ..l .. ,

f- e;dt ggr .,Tg /, . ,- [

J

.,.2 s s

/ s.;

4- -g.-.* f..- " t. +m s:

( & 'a

f. .;

~.*y[, .'

• . <.' s [ -*-C d j

. l$ '

• ,,. j . . ,./. f L , .

^*:..

!\ '

/ *s , ..

• j. y ,.-

g

...'l

~%( t

,i am )p e

s e 1

.[ ,.' .s ll. j }4,j i

I ;N ' .

~ . - 4p - . . . 4,q, . ] = , - . . .y g . ., .,

l

- 7 .., y - - - ya 7. _' f.. .

- f . I, flF h ~M i M i^t< g'(n $ *, p' .

'_'d((

lQ, s -..? /

Q ' f(K J M{(f/*f'] ' V ' .- ' I % s %. .g/f,& ; d jV t

. ,a -

, 'i a

/ 9-7 t ,~.

y l6 w

.(+y ' '.// g

_ K8-41 T '

r - .

f f g'j ,  ; p c ! h" ,x3,A P.

'i. '"*

g4 ./ .

$ '.' {m'

• 1 fs/..h N ,. / 'c ; t-g. ,

44

.j f"',\, \ 3:,,, C 1L

", Nk ,

{b O / .

(

'.3

.e / n j

g ._ .

.;_.-..- _. % . . ,< p y g y . .

. .m . .. . A4.gfq,_t .

. .w ,

es, . k ,s.3

< + i-q,hV .*g\ A ,' t,si

-

• t ,

a. h--.L J ~

] .). .; .

g,o j' 1 x ]/ '

g sp,,g." .m t

• h.hg/

F4

{jp- l,Qj p h.s p-: 1. ,l. @4i jp ,

i

. g, y i (4/

;l;=

,g y

- , g p'tg$

• s 1 , p..

. . - .,< ' ,h.y q .y ojA...J...g,;,pp;{

n ,? ye" n ,

z

. 1 . .< ./1 ~

..- ,.WE

? % _, ,MV (i ..r <**~ s N l ...~)  %.

w,, W s.

' [p. p[..

4 i

t. . .t w ... s,h,'f h,f

4 g k'3"g_;hs i /'3Q Q, 1%'l'.l

.4, ~l ,.m k y. j_

1: ,5 . "%

L.

r , b f.. y

, y

. &g . -

.'. ~

,o 'ep'-

,, i ( /.j f t

. .- . ..e a i

. ,, - Ng.^[p t , ' , pp rqS .

, ,f .

. j. e

,Y W@Mhj, .c ~_

.:.y -NI }h;

@/N pkl'kbN'-f ,

h@EM%@ hd.,@lf}37 M .,

[ , r ,( --

j y

j

m,

, 4 -H- ( p, +.%

, 7 . *q *, t v . dh s cn y *v _ y ,

.. m 4.~...

J 3F

's i s .

l .x.,h/ . is r

-e :

. 1%*4u ,

• er m co J.0 m. .lh.-.a p

.-p q ' hr / . y.w; .,! .*4 l 4 N ~'.1) w ~.-,m . _ . _ ' ' 4__ IQ., Q> . , dM@. , ,-#\

, J b 1h

-~ .,ff*

~

• 7.p Q j [.h"? ;. '.-l

/

. q;. 3 j, p ,.4, i

- me ! e

-' pd . r m! .

g4

. hy ,. 4 ,! f,_ e 1;,e 3 a j{ .p

g. . .4 a

a 1.

h. ,'~ 9G <

,t .by ) ' gg ., %;'- ;gs y .

y-j].

-m. i e y . T, . '  ;:v '.,j .s

Qig- n- t 1 .2 7

n.. '

1F* h s tf/

\

j# . A h. Q )._ ....~ m h;e'c m y.,,ll'*: ., p i q g- f, . m <

h ;, > 2 i ' gy. ,. , 7:1' j

j

. kl g p5i; r . ij.,. /.i y == J T g s

. ,*p;i , ' .. h . t }  %

i-1 id, (1'9g r [(jJ.;.3_#t .,q(,a;y,-

y -

g y i

0174.w- {i=jg,(,.-Q, i ~

i q(

I ll .l f O .' = >p t 44 7 3

g,I . b, tl Qi ,, T .'f a ~[H],f;j1

[ . .

.L . . 1, g ,, ; 3

-; j- J -- j  ;- t ' '- !

p

. , .. -.. p . , c /,) g .g ,j ./l .

h- m

1. h

! l *

. A.,'. '

, YM*i i*hk f= ,I ,. .!:,

m m: It (I. 1j[t-d ,.

)A s__j d jjk n i li 9 .'w.< !.jW,t u f+. Ip Mp[cGw. . ,; = 4p i

s h.Jpl,/ 4i .

qh :u

. jj  : -

m 940'3SN331 I 4 38091.1

_ _._ _ m _ _ . . . _ . . _ _ _ _ . _ _ _ _ . . _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ . _ _ .

• i

. LICENSE.075 y . page 38 P ,

TABLE 4-1 Environmental Sampling Stations - Radiological i P

Sample Station Nun.ber 1 '

Approximate Direction end Distance from plant: 88' - 0.6 miles Eample Types: 1) Airborne radiciodines .

2) Airborno particulates I (o 3) Direct radiation

• Sample Station Location:

The sample station is near the meteorology tower approximately 0.6 miles east '

of ANO. ,

Sample Station Number: 2 Approximate Direction and Distance from_ plant: 235' - 0.4 alles Sample Types: 1) Airborne radioindines

2) Airborne particulates

3) Direct < radiation-Sample Station Location:

1E tra cling from AND, IEEN p spproximately 0.2 miles west toward Gate 4. Turn left and go approxie4tely 0.1 miles. Turn right and go approximately 0.1 miles. The sample station is on the right at the former Ap6L lodge location.

IE traveling south on Flatwood Road, IHES go approximately 0.25 miles from sample station 109. /ent left at fork in road and go approximately 0.2 miles. Turn right and go approximately 0.1 miles. . Turn right and go-approximately 0.1 miles. The sample station is on the right at the former Ap6L lodge location.

Sample Station Numbert 3 Approximate Direction and Distance from plant: O' - 0.6 miles Sample Types: 1) Airborne radiciodinew

2) Airborne particulates 3)-Direct radiation 4). Ground water (alternate)

S_ ample Station Location:

1E traveling west on liighway 333, IHEN go approximately 0.35 miles from Gate 2 at ANO. Turn left onto gravel

~

road an. 3o approximately 0.05 miler. The sample station is on the left.

jd traveling cast on liighway 333,-

L IHEN go approximately_0.9 miles from junction of Ilighway 333. and Flatwood l- Road; Turn _right onto gravel road and go approximately 0.05 miles. -The L- . sample station is on the left.

l-t .. _ , _ . _ _ . . _ . _ _ . . . - . . - _ - _ . _ . ~ . . . , . . _ - . _ . _ , . _ _ - . _, . . . _ _ _ . . . ..,

4 e s

LICENSE.075 Page 39 TABLE 4-1 Environmental Sampling Stations - Radiological Sample Station Nuuber: 4 .

Approximate ___Dir;ction and Distance from Plant: 180 - 0.7 miles  ;

Sanple Types 1) Airborne radiof odines l

2) Airborne particulates

3) Direct radiation Sample Station Location:

Go approximately 0.25 miles south from bridge over intake canal. Turn right onto gravel road. Proceed approximately 0.1 miles went of May Cemetery entrance. The sample station is on the left approximately 50 feet south of the road.

,Sagle Station Namber: $

Approximate Direction _and Distance from Plant: 298' - B.2 miles Sample Types: 1) Direct radiation Sample Station Location:

While traveling on Highway 64, turn onto Cherry Street in Knoxville, AR and go approximately 0.7 miles. Turn lef t onto liighway 64 South and go approximately 0.2 miles._ The sample station is on the right.

Sample Station Number: 6 Approximate;Ulrection and Distance from Plant: 111* - 7.0 miles ,

Sample Typea: 1) Airborne radiciodines

2) Airborne particulates

3) Direct radiation Sample Station Location:

Go to the AP&L local office which is located off Highway 77 in Russellville, AR (305 South Knoxville Avenue). The sample station is in the southeast '

corner of the back lot.

I t

t l

l-l

_ _ m . . _. _.~.-_2__. __- _ - . . . _ - . _ , _ - . . _ _ _. _._ -_ . _ _ _ _

$ LICENSE.075 Page 40 TABLE 4-1 Environmental 8ampling Stations - Radioingical  !

Sample Station Number: 7 Approximate Direction and Distance from Plantt 209' - 19.3 miles ,

Sample Types: 1) Airborno radiciodines -

2) Airborno particulates

3) Direct radiation i Sample Station Location:  !

i Turn west at junction of Highway 7 and Highway 27 in Dardanelle, AR. . Proceed to junction of Highway 27 and Highway 10 11. Danville, AR. Turn right onto Highway 10 and proceed.a short distance to the AP&L supply yard, which is 'n.

the.rfght adjacent. to an AP&L substation. The sample station is in the ,

southwest corner of the supply yard.

Sample Station Number: 8 Anproximate Direction and Distance from Plant: 180' - 0.1 miles Sampic lypes: 1) Surface water (composite)

2) Shoreline sediment-

. . 3) Fish Sample Station Location; Plant discharge canal Sample Station Number: 10 Approximate Direction and Distance from Plant: 95' - 0.9 miles (rhoreline sediment and fish) plant intake structure (surface water)

Sample Types: 1) Surface water (composite)

2) Shoreline sediment -'

-3) Fish-Sample Station Location:

Surface water (composite)-is collected at plant intake structure. Shoreline sediment ahd fish are collected at plant inlet canal.

Samply Station Number: 13 Approximate Direction and Distarice from Plant. 271* - 0.5 mfles Sample Types: 1)-Broad leaf vegetation Sample Station Location:

- if traveling . south.on r :3twooi Road, 1 HEN go approximately 0.2 miles from sample station 109. The sample station

• is on the left.

If_ traveling west from .$NO toward Gate 4, IHEN go approximately 0.a milesi from turn right onto Flatwood Road. Go a.

short distance (approximately 30 yardc). The sample station is on the right.

l L

l l

u, .

- ma . ...1_ , _ . _ . ,, , , _ . _ _ _ . _ . . _ _ _ _ _ _ , . - . _ . _ _ .._1,_---

LICENSE.075 Page 41 ,

TABLE 4 1 Environmental Sampling Stations - Radiological

- Sample Station humber: 14

&nproximate Direction and Distance from Plant: 70* - 5.3 miles Sample Tynes:

c

1) Drinking water Sample Station Location:

From junction of liighway 7 and Water Works Road, go approximately 0.8 miles west on Weter Works Road. The sample station is on the left at the intake to '

the Russellville city water system from the Illinois Bayou.

S_amt l e Station Number: 16 Apprfximate_ Direction and Distance from Plant:

290' - 5.9 miles F_emp_le J pes: 1) Shoreline sediment Sample Station Location: .

From junction of liighway 64 and Highway 359 (Flat Rock Piney Bay Recreational Area turnoff). go approximately 0.7 miles west on Highway 64. The sample station is at the Piney Creek area on hake Dardanelle.

Sample Station Number: 19 Approximate Direction and Distance from Plant: 95' - 3.1 miles

! amp _l e_Typf_s 1) Milk

- pample Station Location:

Turn f 4om liighway 7 onto Harrell Drive in Russellville, AR and go approximately 0.1 miles. Turn right and go approximately 0.25 miles. The sample station is on the left at the Arkansas Tech Dairy.

Sample Station Numbrr: 29 Approximate Direction and Distance from Plant: 24' - 6.9 miles L Sample Types: 1) Hilk (alternato)

Sample Station Location:

i- - Turn south from Highway 333 onto County Road 141 and to approximately 0.55 miles. -Turn Inf t and- go approximately 0.6 miles. Turn left and go.

approximately 0.05 miles. The cample 5tation is on the right at the Harold Steuber-Dalry.

L i

-3,-. y - p + -gA ,.-.u,-.e- g a,-. - eawyy g++r ,,--e.,_7m--,e .p -.ge9pywo u9 9 ye c w----,+,e--we.simev.9.-e-yy--.u..a.pg,*99 9 ,-Fe. +9 .y 9 gg y

O e LICENSE.075 Page 42 TABLE 4 1 L

Environmental Sampling Stations - Radiological I

Sannie Station Number 32 6pprcximate_ Direction and Distance from P_lant: 132' ~ 0.9 miles Sample Types: 1) Ground water i

2) Food

• oducts  !

Sample Station L 4 stion: '

Prom bridge over intake canal, go south approximately 0.25 miles. Turn left and go approximately 0.25 miles. Turn left on Bunker Hill Lane and go l approximately 0.05 miles. The sample station is on the right at '

C.?ffton Stewart's residence.  ;

Sample Station Number: 33 Approximate Directidn and Distance from Plant: 94' - 3.8 miles Espple Types: 1) Ground water .

Sample Strcion_ Location:

Trom junction of Highway 64 and Highway 326 (Dike Road). go approximately 0.3 miles east on Dike Road. The sample station is on the left at the Quita Lake Recreation Area on the Illinois Bayou.

Sample Station Number: 36-Approximate Direction and Distance from Plant: 140* - 0.05 miles Sample TJpen: 1) Pond water

2) Pond sediment Gample Station Location:

The sample station is at the Settling Pond on the ANO site eest of the discharge canal.  ;

Sample St_ation Number: 37 Approximate Direction ard Distance from Plant: 0* - 7.5 miles Samp_le_ Types : 1) Milk

' Sample Station Location:

If traveling north on Highway 333 IllES go approximately 3.5 miles f ron junction of Highw i 333 and Hill Creek Rond on Highway 333. Turn left and go approximately 0.1 miles. The sample-station is on the left at the Lawrence Steuber Dairy, lE traveling from junction of Highway 7 and Highway 333, _ .

IEES go app.sximately 6.0 miles west on Highway 333. Tarn right and go-I approximately 0.1 miles. The sample station is on the left at the Lawrence Steuber Da y.

I I

- , --. _.s..._. . . - . . ~ , , . . _ . , . , . . + - , , . .v.._ mr...

LICENSE.075 page 43 TABLE 4-1 Environmental Sampling Stations - Radiological Sample Station Number: 38 hpProximate Direct ion and Distance f rom plant: 314' - 2.4 miles Sample Typys: Tood products (alternate) l ecation:

Sampje St att..i_ptt Trom west junction of Highway 64 and liighway 333 in London, AR, go approximctely 0.4 miles went on liighuay 64 Turn right at llornet Estate and go approximately 0.1 miles. Turn left and go approximately 0.1 miles.

The sample station is on the lef t at Ronnie Jones' residence.

sample Station Number: 40 byproximate Direction and Distance fyom plant: 119' - 2.2 miles Sample lypfs: 1) Foods products Sample Station Locatfon:

From junction on liighway 64 and liighway 326 (Marina Road), go approxinately 2.0 miles on Marina Road. The sample station is on the 1 cit at florace lloll 's' residence just prior to curve.

Sappje Station Number: 41 Apprgximat e Dir_ pet f orLand Dist ance_f rom plant: 358* - 3.8 miles EgmpicJyngs: 1) Milk Eample Station _Lo_ cation:

II travelir.g f rom junction of liighway 333 and Mill Creek Road, IllDi go approximately 1.8 miles on Mill Creek Road. Turn right onto Lowe Lane and go approximately 0.1 miles. Turn right and go approximately 0.05 -

miles. The sample station is on the right at the James Gibson Dairy.

If traveling from junction of liighway 64 and Mill Creek Road, IllDi to approximately 3.6 miles on Mill Creek Road. Turn left onto Lowe Lane and go approximately 0.1 miles. Turn right and go approximately 0.05 miles.

The sample station is on the right at the James Gibt.on Dairy.

Sample Station Number: 42 hPyroximate Direction and Distance from plant: 73* - 12.4 milos

.Sampl eJype,s : 1) Milk Sampic_ Station Location:

From junction of liighway 124 and liighway 326 in Gum Log, AR, go approximately 1.1 miles northeast on liighway 124. Turn left onto Gravel ;1111 Road and go approximately 0.6 miles. Tyrn right onto iludson Loop and go apprcximately 0.3 miles. The sample station is on the Icft at the lludson Dairy.

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

• f LICENSE.075 page 44 ,

• l TABLE 4-1 Environmental Sampling Stations - Radiological l

Sample Station Number 45 f Approximate Direction and_ Distance from plant: 90' - 0.9 miles Eample Types: 1) Broad leaf vegetation E. ample _ Station _Lo:stion: {

r The sample station is located near mouth of intake canal.

Sample Station Number: 46 bpproximate Direct.fon and Distance __from pla.nt: 295' - 4.1 miles Sample _1ypes: 'l) Food products Sample Station Location:-

-From west junction of Ilighway 64 and liighway 333 in London, AR, go west on liighway 64 approximatoly- 2.4 miles. Turn right onto Scottie Len6 and go approximately 0.1 miles.-_The sample location is on the right at Dewey Gregory's residence.

Sample _ Station Number: 47 Approximate Direction and Distance from plant: 344' - 2.8 miles Sample Types: 1) Milk Sample Station Location:

1[ traveling _from junction of Highway-64 and Mill Creek Road, THEN so approximately 1.0 nile on Mill Creek Road. Turn left onto Bailey Loop Road and go approximately 2.4 miles. Turn _left at Sims Hollow Road and to approximately 0.35 mile. The sample station is on the right at the Bryan Irby residence.

1[ travelirg from junction of Highway 333 and Mill Crook-Road, THEN go approximately 1.1 miles on Hill Creek-Road. Turn right onto Bailey Loop Road which is located near East point Baptist Church and go approximately 1.7 miles. Turn right.at Sims Hollow Road and go approximately 0.35 mile.

The sample station is on the right at the Bryan Irby residence.

! ample Station Number: 108 Approximate Directjon and_Distapee from_Tiant: 301' - 0.9 miles Sample Types:- 1) Direct radiation Sample Station Location: .

II traveling from Highway 333, IhES turn south onto Tlatwood Road _and so approximately 0.4 miles. The sample station-is on a utility pole on the right.  ;

1E: traveling north on Tlatwood Road, ,

IEEE go approximately 0.4 miles from sample station 109. The sample station is on a utility pole on the left.

e 4 LICENSE.075 Page 45 TABLE 4-1  !

T.nvironmental Sampling Stations - Radiological Earple Station Number: 109 Approximate _ Direction and Distance from Plant: 285' - 0.5 miles Sample Types 1) Direct radiation Sample Station Location:

lE traveling selth on Flatwood Road, ,

IHES go approximately 0.4 miles from sample station 108. Sample station 109 is on a utility pole on the laf t across from the junction of Flatwood Road and Round Hountain Road just before pavement ends.

1E traveling west from ANO toward Gate 4, IIIIH 2,o approximately 0.4 miles and turn right onto F3atwood Road. Go approximately 0.2 miles. The sample station is on a utility pole on the right across from the junction of Flatwood Road and Round Mountain Road just after pavement begins.

Sample _ Station Number 110 6pproximata Direction _and Distance from Plant: 138' - 0.8 miles Sample Types 1). Direct radiation Sample Station Location:

Trom bridge over intake canal, go south approximately 0.25 miles. Turn left and go approximately 0.25 miles. Turn right on Bunker Hill Lane. The sample station is on the-first-utility pole on the left.

Sample Station _ Number: 111 AI p_roximate Direr,tir;n and Distance from Pla_nt: 121'

• 2.2 miles Sy p_l,e Types: -1) Direct radiation Sample Station Location:

From junction of Highway 64 and Highway 326 (Marina Foad), go approximately 2.1 miles on Marina Road. The sample station is on a utility pole on the left just prior to curve.

- Sample _ Station !?>mber: 112 ,

Approximate Direction and Distance from Plant: 74' - 2.6 milt a Sample Types: 1) Direct radiation

- Sample _ Station-Location:

Go to the junction of Highway 64 and the I-40 exit which is approximately 1.3 miles east of sample station 113. Sample station 112 is on a utility pole on the northeast corner of the junction.

N 3

M

-. rw wry e -wss ,m + + , ..,..sp.eev w,< + i,-= ~ - - - , - - ,+,w-m,=,-ase m ew.v..r--==-w,=-m.---u-.

ee>.

, . LICENSE.075 Page 46 e

TABLE 4-1 Environmental Sampling Stations - Radiological 1

t Sample Station Number: 113 l Approximate Direction and Distance from Plant: 52' - 1.5 miles '

Sample Types: 1) Direct radiation S_a.mple Station Location:

Go to the east junction of Highway 333 and Highway 64 The sample station is on a utility pole on the southwest corner of the junction.

Sampic Station _ Number: 114 Approximcte Direction and__ Distance from Plants 31' - 1.3 miles

!. ample Tynen: 1) Direct radiation Sa_mpic- Stat ion _Locat f on:

1E traveling west on Highway 64, '

IHEH go approximately 0.6 miles west of the east junction of Highway 64 and Highway 333. The sample station is on a utility pole on the right.

_lf trave'ing east on Highway 64, IHEH go approximately 1.1 miles from sample station 115. Sample station 114 is on a utility' pole on the icit.

Sample ftation Number: 115- .

Approximate Direction and Distance from Plant: 344' - 1.4 milta Sample Types: 1) Direct radiation Sample _ Station _ Location: ,

1 j

1E traveling west on Highway 64 l IHLH go approximately 1.1 miles west of sample station 114.- Sample station 115 is on a utility pole on the right.

If traveling east'on-Highway 64,

~_ IHES go approximately 0,8 miles f rom the west junction of Highway 64 and Highway 333 in London. AR. The sample station is on a utility pole on the left..

Engple a Station Ihmber: 116 Approximate Direction an_d Distand Crom Plant: 320' _i.8 alles Sample Types: 1) Direct radiation Sample Station Location:

Go one block south of the west junction of Highway 333 and Highway 64 in London, AR. The sample station is on a utility pole north of the railroad tracks.

D w -

ww-e -*- c e cww w g v w ,*-eevy---- e-

LICENSE.075 Page 47 TABLE 4-1 Environmental Sampling Stations - Radiological l'

Sample Station Number: 117 Approximate Direction and Distance from Plant: 305' - 17.2 miles Sample Types: . 1) Direr.t radiation Sample Station Location:

H traveling west on 1-40, EM take Exit 58 at Clarksvillo, AR. Turn right onto Rogers Street. At j junction of Rogers Street and liighway 64, turn left and proceed west to first i stop light. Turn left onto Cravens Street. The sample station is on a l utility pole on the right between the_ county courthouse and the post office. l H traveling west on liighway 64, dig go to first stop light past junction of Rogers Street and liighway 64.

Turn left onto Cravens Street. The sample station is on a utility pole on- '

the right between the county courthouse and the post office.

o l Sample Station' Number: 118 App _roximate Direction and Dir,tance from Plant: 294' - 5.6 miles S_ ample Types: 1) Direct radiation Samp1_c Station Location:

H traveling east on liighway 64, E M go approximately 0.3 miles from bridge which goes across Piney. The l

sample station is on a utility pole on the left.

H _ traveling west on 111ghway 64, ,

D12 go approximately 0.4_ miles past Flat Rock Piney Bay Recreational Area turnoff. The sample station is on n utility pole on the.right.

Sample Station Number: 119 Approximate Direction and Distance from Plant: 309' - 4.8 miles Sample Types: 1)_ Direct radiation Sample Station _ Location:-

Turn west from liighway 333 onto Will Baker Roau, which intersects liighway 333 approximately_1.4 miles north of the 1-40 Overpass near Lc , AR. Go approximately.2.0 miles. The sample station is on a utilft, . Ole on the left just prict to pavement-ending.

t

4 4

. LICENSE.075 Page 48 TABLE 4-1

, Environmental Sampling Stations - Radiological Sample Station Number: 120 Approximate Direction and Distance from Plant 33b' - 4.2 miles Sample _Typest 1) Direct radiation l Sample Station Location:

II traveling from I-40-Overpass in London, AR, IHEN go north on Highway 333 approximately 2.4 miles. The sample station is on a utility pole on the right near Martin Chapel.

If traveling from junction of Mill Creek Road and Highway 333, j IHLH go approximately 1.0 mile. south on Highway 333. The sample station is on a utility pole on the-left near Martin Chapel.

-l Sample Station Number: 121 Approximate Direction and Dist_ance from Plant: 349' - 4.6 miles Sample Types: 1) Direct radiation Sample Station Location lE traveling from I-40 Overpaso in London, AR, IHEN go north on Highway 333 approximate 1y 3.4 miles to Mill Creek Road.

Turn right-onto Hill Cteck Road and go approximately 0.7 miles. The sample station is on a utility pole on the right.

1E traveling northwest on Mill Creek Road, IHEN go approximately 0.4 miles past East Point Baptist Church and Cemetery.

The sample station is on a utility pole on the left.

Sample Station Numbert 122 Approximate Direction and Distance from Plant: 18' - 3.3 miles Sample Typys: 1) Direct radiation Sample Station Location:

lE traveling north from junction of Highway 64 and Hill Creek Road, IHEN go approximately 2.5 miles. The sample station is on a utility pole on the right.

lE traveling southeast on Hill Creek Road, IEEH-go approximately 1.9 miles from East Point Baptist Church. The sample station is on a utility pole on the-Icft.- .

r o

e---- ,w-m . w- -.-- .'-..,,-,,.4, ,---.,,_,__..-y.,. .m. o.. .. . _ . . . ., , , , . , _ , , ,_4:,, , m,,_.,,_,,, ,,,_ _ , , , , , . , , , , ,,, ,, ,

LICENSE.075

. Page 49 4

TABLE 4-1 Environmental Sampling Stations - Radiological Bample_ Station Number: 123 Approximate Direction and Distance from Plant: 46' - 3.5 miles pample Type,s: 1) Direct radiation Sample Station Location:

Turn north from Pleasant View Road onto Ball Hill Road and go approximately 0.8 miles. The sample station is on a utility pole on the left.

Sample Station Number 124 Approximate Direction and_ Distance from Plant: 60' - 3.2 miles

! ample Types: 1) Direct radiation Sample _ Station Location:

lE traveling from junction of liighway 64 and Mill Creek Road, IHES go north on Mill Creek Road approximately 0.7 miles. Turn right onto Pleasant View Road and go approximately 1.3 miles. The sample station is on the right on a utility pole which is across from a siren and below n transmission line.

lE traveling west from junction of liighway 7 and Pleasant Vitw Road, IEN go approximately 3.1 miles. The sample station is on the left on a utility pole which is across from a siren and below a transmission line.

Sample Station Number: 125 Approximate Direction and Distance from Plant: 45' - 9.1 miles Sample Types: -1) Direct radiation Sample Station Location:

While traveling north on Highway 7, turn left onto Water Street in Dover, AR.

Go one block and turn left onto South Elizabeth Street. Go one block and turn right onto College Street. The sample station is on a utility pole at the southeast corner of the red brick school building, which is located on top of hill.

Sample Station Number: 126 Approximate Direction _and Distance from Plant: 81* - 5.5 miles Sample Types: 1) Direct radiation Saynle Station Location:

The sample station.is located on the west side of Highway 7 directly across f rom Shiloh _ Road, which is approv.4 Stely 1.3 miles north of the junction of liighway 7 and Dike Road.

,rr ~ v ,v-y-er --g ,r

LICENSE.075

• Page 50 TABLE 4-1 Environmental Sampling Stations - Kadiological Sample Station Number: 127 Approximate Direction o.pd Dis;33p; from Plant: 102' - 5.6 miles

.J Sampi d ypy : 1) Direct radD tion

"*.~ ,S_an.p_l e S t a t ion Loca t ion :

ri 3, The saxple station is lorsted on the Arkansas tech Campus on West 0 Street on s security light pole in front of Bryan Hall, which is the first building on

.. the left when traveling from North Arkansas on West 0 Street.

Sagple Station Number: 128 Approximate Direct)on and Distance frnellant:

113 -

i Sa,mple Types: 1) Direct radiation SaEple Station Location:

The sample station is on a utility pole inside .urity fence near the Russellville Airport Office. The airport is lou .cc off of East 16th Street and is well marked by airport signs.

i 23mple Station Number: 129 -

Appro::'= ate Direction an ' Distance f rom *iirst : 118' - 7.3 miles F s

'e : s es: 1) Dirnet radiation O i el Station Location:

The semp;e stat'on is on a utility pole north of the Russellville H'gh School sic a: which is in front of high school or, east side of Highway 7T.

~

hample Station Number: 130 Approximate Direction and Distance from plant: 245 - 4.6 miles Sample ])ggs: 1) Direct radiation Sag le Station Location:

At junction of Highway 7 s.nd Highway 22 in Dardanelle, AP, take Highway 22 toward Delaware, AR. Ga approximately 0.4 miles west cf Delaware Racreatien Area turnoff. The sar. pie station is on a utility pole an the right in Delaware, AR near Sh!ricy's Beauty Salon. 0 Q

W h% l W. e.( *

• jf g * , m

h

}

+ LICENSE.075

.- Page 51 l

TABLE 4-1 '

Environmental Sampling Stations - Radiological

. Sample Station Number: 131 .

, Approximate-Direction and Distancolfrom Plant: 244' - 2.4 miles Sample Types: 1) Direct radiation 4 Sample Station Location:

Turn north from Highway 22 onto Highway 393 at D'? are Recreation Area turnof f and go approximately 2.9 miles. The sa p.e station is located past the. boat ramp on an oak tree near crosstle steps 3.n northeast quadrant of circle drive.

Sample Station Number: 132 Approximate Direction and Distance fro.a Plant: 267' - 5.8 miles Sample Types: 1) Direct radiation Sample Station Location:

Turn north from Highway 22 onto Highway 393 at Delaware Recreation Area turnoffLand go-approximataly 0.9 miles. Turn left onto dirt road and go approximately 2.3 miles. The sample rtation is on a utility pole on the right.

Sample Station Number: 133 Approximate Direction and Distance from Plant: 233 - 3.7 miles Sample Types: .1) Direct radiation-Sample Station Location:

1E traveling-west on Highway 22, IHEH go approximately 2.0 miles from sample station 134. Sample station 133 s

is-on.the south side of the Highway-22 causeway attached to the first NO PARKING ANY' TIME sign west of the bridge.

If traveling east' on Highway 22 from Delaware, AR, IHEN go approximately 0.8 miles from Delaware Recreation Area ;urnoff. The r e <ple station is on the south side of the Highway 22 censeway attached to the first-N0 PARKING ANY TIME sign west of the bridge.

^ Sample Station Numberi 134 Approximate Direction and Distance from Plant: 200' - 2.8 miles Sample Types: 1) Direct radiation -

Sample Strtion Location:

Elf. traveling west en Highway 22, IEES go approximately 0.8 miles from sample station 135. Sample station 134 is on:a utility pole on tk right at Hockingbird Lene.

IE traveling east oa Highway 22, IEES go approximately 2.0 miles from_ sample station 133. Sample station 134 is on a. utility pole on the left at Hockingham Lane.

l

• ,, e. ,. -

rm. , , . . . - -

L10ENSE.075 Page 52 TABLE 4-1 Environmental Sampling Stations - Radiological t

Sample Station Number: 135 Approximate Direction and Distance from Plant: 188' - 3.2 miles Sample Types: 1) Direct radiation Samp_le Station Location:

IE traveling northwest on Highway 22, THEN go approximatr ly 1.7 miles f rom sample w tion 136. Sample ststion 135 is on a utility pole on the right.

-lE traveling east on Highway 22 THEN go approximately 0.8 miles from sample station 134. Sample station 135 is on a utility pole on the left.

Sample Station Number: 136-

'Arproximate Direction and Distance from Plant: 168' - 4,3 miles Sample Types: 1) Direct radiation Sample Station Location:

_lE traveling west on Highway 22 THEN go _approximately~-3.7 miles' from junction of Highway 22 and Highway 7.

The saeple station is'on the right on tha first utility pole west of the ,

Little Hays Creek Bridge.

_IE travnik.g east on Highway 22, IEEN go approximateily 1.7 miles from sample station 105. Sample station 136 is on_ the left on :he first utility pole west of tFa Little Hays Creek Bridge.

Sample Station Nurber: 137 Approximate Direction and Distance from Plant: 150' - 8.4 miles Sample Types: 1)-Direct radiation Sample Station Location:

At junction of Highway 7 and Highway 28 in Dardanelle, AR, go approximately

- 0.2 miles on Highway 26. The sample station is on a speed limit sign on the right in -fror.t of the Morris R. Moore Arkansas National Guard Armory.

I l1

!~

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

• LICENSE.075 Page 53 TABLE 4-1 Environmental Sampling Stations - Radiological Sample Station Number: 138 Approximate Direction and Di_ stance from Plant: 193' - 5.8 miles Sample Tynes:

1) Direct radiation

-Sample Station Location:

-At junction of Highwsy 22 and Highway 155 (Mt. Nebo Road) in Dardanelle, AR, turn west and go to top of mountain. Veer right at stop sign and proceed toward Sunset-Point. The sample station is down a dirt road on the right which is approximately 0.1 miles southeast of Sunset Point. The sample station is on the left side of the dirt road on a utility pnle near a TV tower.

Sample Station Number: 139 Approximate Direction and Distance from Plant: 178' - 19.2 miles Sample Types: 1) Direct radiation Sample Station LocatJon:

'Take Highway 7 South through Dardanelle, AR to Ola, AR. Turn left at junction of' Highway 7_and Highway 10 West in Oia, AR and go approximately j block. The sample station is on a utility pole on the left in front of the U. S. Post Office.

Sample Station Number: 140 Approximate Direction and Distance from Plant: 151' - 21.8 miles Timple Types: 1) Direct radiation

. Simple Station Location: $

Proceed through Ola,-AR and tcke Highway 10 East to Casa, AR, which is in Perry County. Turn right at the Perry-Casa High School. The sample station is on a utility pole at the southwest corner of the school.

Sample Station Number: 141 App:oximate Direction and Distance from Plant: 125' - 3.8 miles Sample Types: 1)~ Direct radiation-Sample Station Location:

While traveling southwest on Highway 326 (Marina Road), go approximately 2.4 miles from sample station 111. _ Sample station 141_is on the right on a utility pole, which_is approximately 50 yards east of a transmission line.

_(The sample station is.approximately 0.35 miles west of the junction of Hilltop Drive end Marina Road.)

f .

LICENSE.075 Page $4 TABLE 4-1 i Environmental Sampling Stations - Radiolo3 cal f

Sample Station Number 142 hpprox_imate Direction and Distance from Plant: 129 - 5.1 miles Sampl e_ Types : 1) Direct radiation Sample Station Location:

The sample station is on a utility pole at the junction of Skyline Drive and Nordin Lane in Russellsille, AR, near a peach orchard.

Sample Station Number: 143 Approximate Direction and Distance from Plant: 106* - 17.5 miles S_ ample Tyrm : 1) Direct radiation Sample Station Location:

lE traveling east on Highway 64 to Atkins, AR, IHLtj turn left at junction of Highway 64 and North Church Street. Proceed north. The sample station is on a utility pole on the left in front of Atkins H!gh School near stop sign at corner of North Church Street and Northeast 3rd Street.

II traveling east on Interstate 40, IHEN take Exit 94 at Atkins, AR. Turn left onto North Church Street and proceed south. The sample station is on a utility pole on the right in front of Atkins High School near stop sign at corner of North Church Street and Northeast 3rd Street.

Sample Station Number: 144 Apg ooximate Direction and_ Distance from Plant: 313 - 12.7 miles Sample Types: 1) Direct . tion Sample ' ation Location:

While traveling on Highway 64, turn south onto Cumberland Street in Lamar, AR, and go approximately 0.7 milee. Veer left at stop sign. The sample station l 18 on a utility pole across the one way fire lane in front of Lamar Elementary School.

1 I

l l

l l

!