ML20082P771

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Rev 31 to Odcm,Mcguire Nuclear Station
ML20082P771
Person / Time
Site: Oconee, Mcguire, McGuire  Duke Energy icon.png
Issue date: 01/01/1991
From: Birch M, Mcconnell T, Stewart J
DUKE POWER CO.
To:
Shared Package
ML15217A128 List:
References
PROC-910101-02, NUDOCS 9109110053
Download: ML20082P771 (15)
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Text

.

-, December 28, 1990 (v .

SUBJECT:

McGuire Nuclear Station Offsite Dose Calculation Manual Revision 31 The General Office Radiation Protection staf f is transmitting t o you this date, Revision 31 of the Offsite Dose Calculation Manual. As this revision only affects McGuire Nuclear Station, the approval of other station managers is not required. Please update your copy No. _ ,

and discard the affected pages.

REMOVE THESE PAGES INSERT THESE PAGES B-6 Rev. 26 B-6 Rev. 31 B-7 Rev. 26 B-7 Rev. 31 B-12 thru B-19 Rev. 26 B-12 thru B-19 Rev. 31 B-21 Rev. 26 B-21 Rev. 31 Table B5.0-1 Rev. 26 Table B5.0-1 Rev. 31 Table B5.0-2 Rev. 22 Table 85.0-2 Rev. 31 NOTE: As this letter, with its attachments, contains "LOEP" information, please insert this letter in front of the

\ December 27, 1990 lotter.

b(^

Approval Date: /2krdo Approval Date: /J// 7/10 I /

Effective Date: 1/1/91 Effective Date: 1/1/91

/ n i

d $'

Mary L. Birch T. L. McConnell, Manager Radiation Protection Manager McGuire Nuclear Station If you have any questions concerning Revision 31, please call Jim Stewart at (704) 373-5444.

C*w?l -

Jame d . iart, Jr.

Scler?,th,tStg/

Radia' tion P Pitection JMS/prm.091 l

l

/ i A

9109110053 910829 DR ADOCK0500{g9 L

JUSTIFICATIOffS FOR REVISIO!1 31

~

Page B-6 Updated sections using dose Page B-7 calculations based on 1990 Pages B-12 thru D-19 Effluent Release Data (first nine months) and the 1990 Land Use Census Data.

Page B-21 Updated the dates the latest  :

Land Use Censua was performed. [

Table B5.0-1 Corrected mileage error on location

  1. 170. j I

Table B5.0-2 Corrected typo error at location [

  1. 130. l Clarified description at location
  1. 159. l t

t i

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u

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

n . _ _ _ _ _ _ _

t I

i B2.2.1 Noble Gases

( .

s  !

I (Kg [(X/Q)Q g) < 500 mrem /yr, and f i ,

I1 (L3 + 1.1 Mg ) [(X/Q)Qg ) < 3000 mrem /yr .

i I

where the terms are defined below.

i B2.2.2 Radiofodines. Particulates, and Others  !

I Pg [W Qg ] < 1500 mrem /yr i '

where: [

K g = The total body dose factor due to gamma emissions for each identified.

noble gas radionuclide, in mrem /yr per pC1/m' irom Table 1.2-1.

Lg = The skin dose factor due to beta emissions for each identified noble }

gas radionuclide, in urem/yr per pC1/m' from Table 1.2-1.

Hg = The air dose factor due to gamma emissions for each identified noble

('

s gas radionuclide, in mrad /yr per pCi/m from Table 1.2-1 (unit conver-8 sion constant of 1.1 mrem / mrad converts air dose to skin dose).

P g = The dose parameter for radionuclides other than noble gases for the inhalation pathway, in mrem /yr per pC1/m' and for the food and ground  !

plane pathways, in m*-(mrem /yr) per uC1/sec from Table 1.2-2. The dose i factors are based on the critical individual organ and most restrictive [

age group (child or infant). t i

I Qg = The release rate of radionuclides, i, in gaseous effluent from all f release points at the site, in WC1/sec.  !

F X/Q = 7.2E-5 sec/m'. The highest calculated annual average relative concentration (dispersion parameter) for any area at or beyond the ,

unrestricted area boundary. The location is the NNC sector @ 0.5  :

miles, i L

W = The annual average dispersion or deposition parameter for astimating  ;

the dose to an individual at a controlling location in the unrestricted area where the total inhalation, food and ground plane i pathway dose is determined to be a maximum based on operational sourco  !

term data, land use surveys, and NUREG-0133 guidance:

W = 2.9E-6 sec/m'. for the inhalation pathway. The location is D ,

the SE sector @ 1.0 miles, j

B-6 Revision 11 l 1/1/91 [

t t _ _ . . . __..____.__________________i

9 V = 7.6E-9 meter ~8, for the food and gound plane pathways. The location is the SE nector @ 1.0 miles.

l i

~  :

Qg =kCf+kg g

= 4.72T+2C gf '

where:

.C g = the concentration radionuclide, 1, in undiluted gaseous effluent, in pCi/ml.

f = the undiluted effluent flow, in cfm  ;

kg = conversion factor, 2.83E4 ml/ft' kg = conversion factor, 6El sec/ min i

i f

l

e l-B-/ Revision 31 1/1/91

B5.0 RADIOLOGICAL ENVIRONMENTAL HONITORING ,

The radiological environmental monitoring program shall be conducted in accor-dance with Technical Specification 3/4.12. The monitoring program locations and analyses are given in Tables B5.0 1 through B5.0 3 and Figure B5.0-1 Site specific characteristics make groundwater sampling unnecessary. Groundwater recharge is from Lake Norman and local precipitation. The groundwater gradient flows directly to the Catawba River; therefore, contamination of groundwater from liquid effluents is highly improbable. Additionally, two site boundary TLD locations in the NW and NNW sectors do not exist since the required loc-ations are over water.

The laboratory performing the radiological environmental analyses shall parti-cipate in an interlaboratory comparison program which has been approved by the NRC. This program is the Environmental Protection Agency's (EPA's)

Environmental Radioactivity Laboratory Intercomparison Studies (Crosscheck)

Program, our participation code is CP.

The dates of the lend-use census that was used to identify the contro111nt receptor locations was 05/14/90 - 05/18/90.

B-21 Revision 31 1/1/91 L _

B4.0 DOSE CALCULA_TIONS .

B4.1 FREQUENCY OF CALCULATIONS Dose contributions to the maximum exposed individual shall be calculated at least every 31 days, quarterly, semiannually, and annually (or as required by Technical Specifications) using the methodology in the generic information sections. This methodology shall also be used for any special reports. Dose calculations that are required for individual pre release calculations, and/or abnormal releases shall not be calculated by using the simplified dose calcula-tions. Station dose projections for these types and others that are known to vary from the station historical averages shall be calculated by using the methodology in the generic information sections. STATION Dose projections may be performed using simplified dose estimates. t t

Fuel cycle dose calculations shall be performed ant.ually or as required by  !

special reports. Dose contributions shall be calculated using the methodology  !

in the appropriate generic information sections. [

B4.2 DOSE MODELS FOR MAXIMUM EXPOSED 1NDIVIDUAL j I

B4.2.1 Liquid Effluents  ;

i For dose contributions from liquid radioactive releases, dose calculations  !

based on operational sot.rce term data and NUREG-0133 guidance indicate that [

the maximum exposed individual would be an adult who consumed fish caught in (

the discharge canal and who drank water from the nearest " downstream" potable l water intake. The dose from Cs-134 and Cs-137 is calculated to be 77% of that l l individual's total whole body dose. [

I B4.2.2 Gaseous Effluents

{

B4.2.2.1 Noble Gases For dose contribi.tions from exporure to beta and gamma radiation from noble '

i gases, it is assumed that the maximum exposed individual is an adult at a controlling location in the unrestricted area where the total nobic gas done is i determined to be a uaximum.  !

f B4.2.2.2 Radiciodines, Particulates, and Other Radionuclides T 1/2 >8 days  !

For dose contributions from radiciodines, particulates and other radionuclides; ,

it is assumed that the maximum exposed individual is a child or infant at a controlling location in the unrestricted area where the total inhalation, food and ground plane pathway dose is determined to be a maximum based on opera- I tional source term data, land use surveys, and NUREG-0133 guidance.  !

t f

B4.3 SIMPLIFIED DOSE ESTIMATE l

B4.3.1 Liquid Effluents For dose estimates -a simplified calculation based on the assumptions  ;

l presented in Section B4.2.1 and operational source term data is presented r below. Updated operational source term data shall be used to revise these j calculations as necessary, t i

i B-12 Revision 31 {

i 1/1/91 )

I j

4 6

, c D

VD

= .66EM (Fg )(Tg) (C Cs-134 + 0.59 CCs-137  !

"I where:

7.66E&S = 1.14E+05'(0,y/Dy + 0,g BFg ) DF,g (1.30) l where: i l

1.14E+05 = 10'pci/uCI x 10'ml/kg + 8760 hr/yr U, = 730 t/yr, adult water consumption 1 i

D" = 1, dilution factor from the near field area to the nearest poscible potable water intake (llunterville Water Intake).

U,g = 21 kg/yr, adult fish consumption BFg = 2.00E+03, bicaccumulation factor for Cesium (Table 3.1-1)

DF ah = 1.21E-04, adult total body ingestion dose factor for Cs-134 (Table 3.1-2) 1.30 = factor derived from the assumption that 77% of adult whole body dose is contributed by Cs-134 and Cs-137 via the fish and drinking water pathway or 100%

  • 77% = 1,30 O m = number of releases where: I 7 , fa t F+f I' where:

i f = liquid radwaste flow, in gpm

)' o = recirculation factor at equilibrium, 2.4 i

F = dilution flow, in gpm where:

i.

Tg = The length of time, in hours, over which CCs 134, CCs-137, and Ft are averaged. (The time period during which all releases (m) are made)

C Cs-134

= the average concentration of Cs-134 in undiluted effluent, in

pC1/ml, during the time period considered, ,

, C Cs-137 = the average concentration of Cs-137 in undiluted effluent, in 4 I pC1/m1, during the time period onsidered.

4 5

B-13 Revision 31 1/1/91

0.59 = The ratio of the adult total body ingestion dose factors for .

s Cs-134 and Cs-137 or 7.14E 05 + 1.21E-04 = 0.59 i B4.3.2 Gaseous Effluents Meteorological data is provided in Tables B4.0-1 and B4.0-2.

.B4.3.2.1 Noble Gases For dose estimates, simplified done calculations based on the assumptions in B4.2.2.1 and operational source term data are presented below. Updated opera-tional source term data shall be used to revise these calculations as neces-sary. These calculations further assume that the annual average dispersion parameter is used and that Xenon-133 centributes 72% of the gamma air dose and 82% of the beta air dose.

s D7 = 8.06E-10 ( Q]y,,333 (1. 38)

US =,2. OE-09 (Q]Xe-133 ( ' )

where:

X/Q = 7.2E-05 sec/m', as defined in Section B2.2.2 8.06E 10 = (3.17E-8)(353) (X/Q), derived from equation presented in Section 3.1.2.1.

  • 1.hBE-09 ' = (3.17E-08) (1050) (X/Q), derived from equation presented in N Section 3.1.2.1.

s

[Q)Xe-133 = the total Xenon-133 activity released in uCi ,

1.38 = factor derived from the assumption that 72% of the gamma air dose is '

contributed by Xe-133.

1.23 = factor derived from the assumption that 82% of the beta air dose is

contributed by Xe-133.

B4.3.2.2 Radiciodines, Particulates, and Other Radionuclides with T 1/2

> 8 days I

' For dose estimates, simplified dose calculations based on the assumptions in B4.2.2.2 and operational source term data are presented below, Updated opera-tional source term data shall be used to revise these calculations as neces- >

sary. These calculations further assume that the annual average dispersion /

deposition parameters are used and that 91% of the done results from Iodine-131 ingested by the maximally exposed individual via the cow milk- '

pathway at the controlling location. -The simplified dose estimate to the

!- thyroid of an infant ist D = 1,64E+4 W (Q)3,331 (1.10)

where

V = 7.6E-9 = D/Q for food and ground plane pathway, in sec/m from Table B4.0-2 for the controlling location (SE sector at 1.0 miles).

14 Revision 31 1/1/91 s - -

I

~

v (Q)y,331 = the total lodine-131 actfvity released in pC1.

t 1.64E+4 = (3.17E-08)(R [D/Q)) with the appropriate substitutions for infant-cow milk pathway factor, R [D/Q) for Iodine-131. See Section 3.1.2.2.

1.10 = factor derived from the assumption that 91*. of the total inhala- [

tion, food and ground plane pathway dose to the maximally exposed  ;

individual is contributed by 1-131 via the cow milk pathway.

r B4.4 FUEL CYCLE CALCULATIONS i

As discussed in Section 3.3.5, more than une nuclear power station site may contribute to the doses to be considered in accordance with 40CTR190. The fuel cycle dose assessments for McGuire Nuclear Station must include gaseous '

dose contributions from Catawba Nuclear Station, which is located i approximatelf thirty miles SSW of McGuire. For this dose assessment, the  !

total body and maximum organ dose contributions to the maximum exposed individual from McGuire liquid releases and the combined Catawba and McGuire i gaseous-releases are estimated using the following calculations: ,

DVBI "

WB( m) + DWB(8 m ) ' WB(Re )

D M0 )=DM0(I m) + UM0(8m) + DMOI8c) where: -

Dyg(T) = Totel estimated fuel cycle whole body dose commitment resulting [

from the combined 11guld and gaseous effluents of Catawba and  ;

McGuire during the calendar year of interest, in mrem. ,

1 D'M0(T) = Total estimated fuel cycle naxmium organ dose commitment resulting from the combined liquid and gaseous effluents of Catawba and McGuire during the calendar year of interest, in '

mrem.

B4.4.1 LIOU1D EFFLUENTS Liquid pathway dose estimates are based on values and assumptions presented in

.Section B4.3.1. Station operational source terms shall be used to update i these simplified calculations as necessary.  ;

B4.4.i.1 McGuire's Llauld ContL_butions 1

[ Based on operational history, the McGuire fuel cycle whole body dose resulting ,

'from McGuire liquid effluent releases (D I m)) is estimated using the i simplified dose calculation given below:WB l DVBlI)=(

m .66E+5) (F ) (T g ) MCs-134 g + 0.59 CCs-137} j B-15 Revision 31 1/1/91

4 where: .

7.66E+5 = 1.14E+05 (U, / Dy + U,g BFg ) (DFait) ( . 0) vhere:

1.14E+05 = (1.0E+06 pC1/uci x 1.0E+03 ml/kg) / (8760 hr/yr) i U,y = 730 t/yr, Adult water consumption Dy = 1, dilution factor from the near field area to the nearest possible

potable water intake (Huntersville Vater Intake).

U,g = 21 kg/yr, Adult fish consumption BF g = 2.00E+03, Bioaccumulation factor for Cesium (Table 3.1-1) 1.21E-04, Adult total body ingestion dose factor for DF,gg = Cs-134 (Table 3.1-2) ,

1.30 = Factor derived from the assumption that 77% of the dose is derived -

from Cs-134 and Cs-137 or 100% / 77% = 1.30

, where Fg = (f) (c) / (F + f) where:

, f = McGuire's average liquid radwaste flow for the calendar year of

, interest, in gpm F = McGuire's average dilution flow for the calendar year of interest, in gpm o = 2.4, the recirculation factor at equilibrium where:

^

Tt = 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br />, the time period over which C Cs-134' Cs-137 and Fg are averaged.

C Cs-134

= The average concentration of Cs-134 in McGuire's undiluted effluent, in uC1/ml, during the calendar year of interest.

C Cs-137

= The average concentration of Cs-137 in McGuire's undiluted effluent, in uCi/ml, during the calendar year of interest.

0.59 = The ratio of the adult total body ingestion dose factors for Cs-134 and Cs-137 or 7.14E-05 / 1.21E-04 = 0.59 Based on operational history, the McGuire fuel cycle organ dose (Adult GI-(,

track resulting from McGuire's liquid effluent releases (D II )) is estimated-MO m using the simplified dose calculation given below:

B-16 Revision 31 1/1/91

t 4

DMOC m ) = (1. 5 +06) (F g) (T )g (Nb-95)

  • where:

1.55E+06 = 1.14E+05 (U /D + V,g BFg )(DF,3 )(1. 35) where:

1.14E+05 = (1.0E+06 pC1/uCi x 1.0E+03 ml/kg) / (8760 hr/yr)

U, = 730 t/yr, Adult water consumption D, = 1, dilution factor from the near field area to the nearest possible potable water intake (lluntersville Water Intake).

U,g = 16 kg/yr, Adult fish consumption BFg = 3.0E+4, Bioaccumulation factor for Niobium (Table 3.1-1)

DF,gt = 2.1E-5, Adult GI-track ingestion dose factor for Niobium (Table 3.1-3) ,, , , ,,

,0 b M K 1,35 = Factor derived from the assumption that 74% of the(Teen-liver dose is contributed by Nb-95 via the fish and drinking water pathway or 100% / 74% = 1.35 where:

Pg = (f) (c) / (F + f)

-where:

f = McGuire's liquid radwaste flow, in gpm F = McGuire's dilution flow, in gpm o = 2.4, the recirculation factor at equilibrium where!

Tg a 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br />, the time period of time over which Cs-134. Cs-137 and P g

are averaged 1

C = The average concentration of Nb-95 in McGuire's undiluted Nb-95 effluent, in WC1/ml, during the calendar year of interest.

l-l O

B-17 Revision 31 1/1/91 y

k s

B4.4.2 GASEOUS EFFLy"ES .

Airborne effluent pathway dose estimates are based on the values and assump-tions presented in Sections B4.3.2. and C4.3.2. Operational source term data shall be used to update these calculations as necessary.

B4,4.2.1 McGUIRE'S GASEOUS CONTRIBlTriON Based on operational history, the McGuire fuel cycle maximum whole body dose [

resulting from McGuire's gaseous effluent releases (Dy3(g,)) is estimated [

using the simplified dose calculation given below:

lt DWB(g,) = (9.32E+06)(w)(6Xe-133}(SF )(1.45) l where:  ;

w = 7.20E-05 = (X/Q) for the plume immersion pathway, in f i

sec/m 8 , which corresponds to a location 0.5 miles NNE of the McGuire site (See Table B4.0-1) i)Xe133 = The total Xe-133 activity released from McGuire during the calendar [

i year of interest, in uC1.

j

~

9 .32E-06 = (3.17E-08) (Kg [X/Q)), with appropriate substitutions for whole body O

exposure in a semi-infinite cloud of Xe-133. See Section 1.2.1. i i

Sp = 0.7 = External radiation shielding factor for individuals. f i

1.45 = The fartor derived from the assumption (based on historical data) that l 69*. of the whole body dose to the maximally exposed individual is l contributed by Xe-133.  ;

Based on operational history, the fuel cycle maximum organ dose is the F Adult GI-track. For McGuire gaseous releases the or,an dose (D g )) will be -

calculated for the Adult-G1 Track using the simplified dose calb(laffon given  !

below:

D M0(8,)=(8.27E-05)(w)(6H-3) (1.95) l where:

f w = 1.80E-5, X/Q 1o- the garden pathway, in sec/m' from Table B4.0-1,  ;

for the McGuire fuel cycle maximum organ dose controlling i location (E @ 0.5 miles). '

I),g,3 = The total H-3 activity released from McGuire during the  ;

calendar year of interest, in uCl.

V

("~ 8.27E-5 = (3.17E-08)(R j

[X/Q]) with appropriate substitions for the j s

V j garden pathway, Rg [X/Q] for 11-3. See Section 3.1.2.2.

i l B-18 Revision 31 1

1/1/91 e

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

1 e,

e t

t 1.95 = The f actor derived f rom the conservative assumption (based on .

Os historical data) tut $1*. of the total inhalation, food and ground plane pathway dose to the maximally exposed individual is fr contributed by H-3 via the inha.lation pathway.  ;

B4.4.2.2 CATAVBA'S GASEOUS CONTR!Nf!ON i i

Based on operational history, the McGuire fuel cycle maximum whole body dose [

resulting from Catawba's gaseous effluent releases (Dyg(g c )) is u timated

.asing the simplified dose calculation given below: I D yg(g)e(9.32E-06)(w)@Xe-133 c P where:

w = 3.30E 07, (X/Q) for the plume immersion pathway which corresponds to  !

a lot.ation 5 miles NNE of the Catevba site. (See Table  :

( ( C4.0 1)  !

t Qg ,,333_= The tocal Xe-133 activity released from Catawba during the calender i year of interest, in uCi. j i

9.32E-06 = (3.17E-08)(K g [X/Q]), with appropriate substitutions for whole body j exposure in a semi-infini+e cloud of Xe-133. See Section 1.2.1.

[

i V CF = 0.7 = External radiation shielding factor for individuals. [

i 1.E2 = The factor derived from the consurvative assumption (based on historical data) that SS*. of the wnole body dose to the maximally l exposed indivdual is contributed by Xe-133 via the plume immersion pathway. [

Based on operational history, the fuel cycle maximum organ dose for McGuire is '

the Adult GI-track. For Catawba gaseous releases the organ doso (D I8 })  !

will be calculated for the Adult GI track using the simplified doseMO c [

calculation given below-Dg(g ) = (8.27E-05)(w)(Qg,3)(3,38) where: )

w = 3.3E-07 =X7Qforthefoodandgroundplanepathwayinsec/m', for a

{

Iccation 5 miles NNE of the Catawba site (see Table  ;

C4.0-1). r 1

Og ,3 = The total H-3 activity released from Catawba during the calendar l l year of interest, in uC1. I

\ ,  ;

8.27E-05 = (3.17E-08)(R [X/Q]) with appropriate substitutions for

[

theAdult-vegetablegardenpathway,k(X/Q)forH-3. See Section j

3.1.2.2. -

I B-19 Revision 31  !

I y 1/1/91

(" O -

(v/ lV) (v') - s TABLE B5.0-1 (1 of 1)

MCGUIRE RADIOIIXTICAL MONI'II) RING PROGRAM SAMPLING LOCATIONS (TIR IDCALONS)

SAMPLING LOCATION DESCRIPTION

  • SAMPLING LOCATION DESCRIPTION
  • 143 SITE BOUNDARY (0.5 MILES hV) 163 4-5 MILE RADIUS (5.0 MILES SE) 144 SITE BOUNDARY (0.6 MILES NNE) 164 4-5 MILE FADIUS (4.5 MILES SSE) 145 SITE BOUNDARY (0.5 MILES NE) 165 4-5 MILE RADIUS (5.0 MILES S) 146 SITE BOUNDARY (0.5 MILES ENE) 166 4-5 MILE RADIUS (5.2 MILES SSV) 147 SITE BOUNDARY (0.5 MILES E) 167 4-5 MILE RADIUS (4.9 MILES SW) 148 SI'II BOUNDARY (0.5 MILES ESE) 168 4-5 MIE RADIUS (4.7 MILES WSW) 149 SITE BOUNDARY (0.7 MILES SE) 169 4-5 MILE RADIUS (4.4 MILES V) 150 SITE BOUNDARY (0.5 MILES SSE) 170 4-5 MILE RADIUS (4.5 MILES WNW) 151 SITE BOUNDARY (0.5 MILES S) 171 4-5 MILE RADIUS l (4.5 MILES hv) ,

152 SITE BOUNDARY (0.5 MILES SSW) 172 4-5 MILE RADIUS (5.2 MILES NSV) 153 SITE BOUNDARY (0.5 MILES SV) 173 SPECIAL Ih"IIREST (8.5 MILES NNW) 154 SITE BOUNDARY (0.7 MILES WSW) 174 SPECIAL INTEREST (8.7 MILES Whv) 155 SITE BOUNDARY (0.7 MILES V) 175 CONTROL (12.7 MILES WNW) 156 SITE BOUNDARY (0.5 MILES WhV) 176 SPECIAL INTEREST (11.0 MILES SW) 157 4-5 MILE RADIUS (4.8 MILES N) 177 SPECIAL INTEREST (8.6 MILES S) 158 4-5 MILE RADIUS (4.4 MILES NNE) 178 SPECIAL INTEREST (9.2 MIIIS SE) 159 4-5 MILE RADIUS (5.0 MILES NE) 179 SPECI AL INTEREST (10.4 MIIIS ESE) 160 4-5 MILE RADIUS (4.9 MILES ENE) 180 SPECI AL INIEREST (11.5 MILES NNE) 161 4-5 MILE RADIUS (4.7 MILES E) 181 SPECIAL IRIEFEST (6.7 MILES NE) 162 4-5 MILE RADIUS (4.6 MILES ESE) 182 SPECI AL IhTEREST (6.0 MILES NE) 183 SPECIAL IhTEREST (5.5 MILES S)

  • All TLD sa:nples are collected quarterly Revision 31 I/1/91

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