ML20039G934

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Forwards Revised Pages of Radiological Effluent Tech Specs & Offsite Dose Calculation Manual for NRC Review & Insertion
ML20039G934
Person / Time
Site: Grand Gulf  Entergy icon.png
Issue date: 01/12/1982
From: Dale L
MISSISSIPPI POWER & LIGHT CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20039G935 List:
References
AECM-82-19, NUDOCS 8201190320
Download: ML20039G934 (20)
v • d • e


Text

-- - _-

4' t

MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi P. O. B O X 1640. J AC K SON MIS SIS SIP PI 3 9 2 05 j

January 12, 1982 T-I W j

Noctt An encoucilON fiPAHTMENT

.- m i

U. S. Nuclear liegulatory Commission 6

Office of Nuclear Reactor Regulation Washington, D. C.

20555 Q

.jMI131932.> C

,-4.,

,~3;...,-.-

,[ C Attention:

Mr. Harold R. Denton, Director O N

' ' 7 %

g' \\

Dear Mr. Denton:

'N,'lla

SUBJECT:

Grand Gulf Nuclear Station Units 1 and 2 Docket Nos. 50-416 and 50-417 File 0260/.15180 Revisions to GGNS Draft Radiological Effluent Technical Specifications AECM-82/19 Recent conversations between representatives of Mis 71ssippi Power & Light Company and the Nuclear Regulatory Commission have revealed the need for revising selected pages in the Grand Gulf Nuclear Station Radiological Effluent Technical Specifications (RETS) and the Offsite Dose Calculation Manual (ODCM). Accordingly, the revised pages are enclosed for your review and insertion.

Please contact us if you have any questions.

Yours truly,

[

L. F. Dale Manager of Nuclear Services LRM/JDR:rg cc:

Mr. N. L. Stampley (w/o)

Mr. R. B. McGehee (w/o)

Mr. T. B. Conner (w/o)

Mr. G. B. Taylor (w/c)

I Mr. Richard C. DeYoung, Director (w/o) 00 Office of Inspection & Enforcement 3

U. S. Nuclear Regulatory Commission Washington, D. C.

20555

/ I 1r. J. P. O'Reilly, Regional Administrator (w/o)

Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Region 11 101 Marietta St., N.W., Suite 3100 8201190320 820112 Atlanta, Georgia 30303 PDR ADOCK 05000416 l

A PDR Member Middle South Utilities System

_.g AECM-8T7561 MISSISSIPPI POWER & LIGHT COMPANY Page 2 Please contact us if you have any questions.

Yours truly, L. F. Dale Manager of Nuclear Services LRM/JDR:ph cc; Mr. N. L. Stampley (w/o)

Mr. R. B. McGehee (w/o)

Mr. T. B. Conner (w/o)

Mr. G. B. Taylor (w/o)

Mr. Richard C. DeYoung, Director (w/o)

Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Mr. J. P. O'Reilly, Regional Administrator (w/o)

Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Region II 101 Marietta St.,

N.W., Suite 3100 Atlanta, Georgia 30303 4

~ _ _ -

A;tachment to AECM-82/19 INSTRUCTIONS FOR INSERTING THE ENCLOSED REVISED PAGES Remove and insert the RETS AND ODCM pages shown below. Dashes (---)

in the remove or insert column indicate no action required.

Remove Insert ODCM:

1.0-5 1.0-5 2.0-1 2.0-1 2.0-2 2.0-2 2.0-3 2.0-3 2.0-4 2.0-4 2.0-4a 2.0-7 2.0-7 2.0-7a 2.0-24 2.0-24 2.0-25 2.0-25 2.0-26 2.0-26 2.0-27 2.0-27 2.0-28 2.0-28 2.0-33 2.0-33 3.0-6 3.0-6 3.0-7 3.0-7 3.0-8 3.0-8 RETS:

5-1 5-1 Figure 5.1.1-1 Figure 5.1.1-1 Figure 5.1.2-1 Figure 5,1.2-1 Figure 5.1.4-1 Figure 5.1.4-1 4

mw,.4y e.

.a

~h e

h 5

.M M

--"N'--

4'6*'h*'--

.a: D Step 5) The radioactivity monitor setpoint may now be specified based or, the values of [C, F, and f which were specified to provide compliance j

with the limits of 10CFR20, Appendix B, Table II, Column 2.

The L

monitor response is primarily to gamma radiation; therefore, the actualsetpointisbasedon[g 1

C.

The setpoint concentration, g

C,is determined as follows:

L:

C Cg (pCi/ml)

(7)

=

m a

g where f is the actual (or maximum expected) effluent flow rate a

m The value of Cm (uCi/mi) is used to determine the monitpr setpoint (CPM) from the calibration curve of Figure 1.0-1.

1 NOTE: The setpoint contains a factor of conservatism, even:if the

} b calculated maximum. waste tank flow rate is attainable, since the calculated rate contains the safety factor margin,. waste tank

~

~

effluent flow rate margin, and the dilution-flow rate margin.

In practice, the actual waste tank effluent flow rate nonnally is many times less than the calculated tank flow rate,. thus providing an additional conservatism during release.

{.

1 i

s.4 j

mi s

4 GRAND GULF, UNIT 1 1.0-5 1/82

~

1 2.0 GASEOUS EFFLUENTS 2.1 Gaseous Effluent Monitor Setpoints 2.1.1 For the purpose of implementation of Specification 3.3.7.12 of the JJ RETS, the alarm setpoint level for continuous ventilation noble gas monitors will be calculated as follows:

n S

= Count rate of vent noble gas monitor at alarm setpoint level y

0.25 x RtxDTB the lesser of 4 or (1)

=

0.25 x R3 x Dss H

J 0.25 = safety factor allowing for cumulative uncertainties of 7

l J

measurements D

q T8

= Dose rate limit to the total body of an indiviaual in an 2

d unrestricted area required to limit dose to 500 mrem in one h

l year.

a i Tj]

]

= 500 - F [(X/Q) Ej K i

( 1-F)

O

- Dose rate limit to-the skin of the body of an individual in ss an unrestricted area required to limit dose to 3000 mrem in one year.

a

g..

O

= 3000 - F [( X/ Q) E j ( L j + 1.1 Mj ) Q j ]

(1-F)

Rt

= count rate per mrem /yr to the total body C*

X/Q

,Kj Qj See Note 2

=

..)

GRAND GULF, UNIT 1 2.0-1 1/82

l'

Wnere, h

C count rate of the vent monitor corresponding to grab sample

=

o radionuclide concentrations X/4 = highest sector annual average atmospheric dispersion at the unrestricted area boundary 5.176 x 10-6* sec/m3

~

in the WSW sector.

=

i Ki total body do.ie factor due to gamma emissions from each

=

ia 3

noble gas radionuclide 1 (mrem /yr per pCi/m ) from Table i

i J

2.1-1.

]

6 4 rate of release of noble gas radionuclide,1 (uCi/sec),

=

from release point F

fraction of current. year elapsed at time of' calculation

=

I ]

iij average rate of release of noole gas racionuclide i for the

=

j elapsed fraction of the year F (uCi/sec)(from release point j

Rs 1

count rate per mrem /yr to the skin

=

C --

X/Q

,( L i+1.1Mj)di See note 2

=

1

['

L j skin dose factor due to beta emissions frem isotope i

=

i L.

5 (mrem /yr per pCi/m ) from Table 2.1-1 4

[,

1.1 mrem skin dose per mrad air dose

=

j air dose f actor due to gamma emissions from isotope i M

=

3 (mradlyr per uCi/m ) from Table 2.1-1 2.1.2 Containment Purge Monitor The setpoint level for discharge through the containment purge system c,

monitor, S, will be calculated in a corresponding manner:

3 o

0.25 x r t x D'TB l

Sd the lesser of or (2)

=

0.25 x r s x D'ss

  • Value taken from Reference 4, Table 6.1.26.

i GRAND GULF, UNIT 1 2.0-2 1/82

4 Il J

where, irlr; D'TB

= 500 - F [(T/II) j Kj iij )

r I

[I

( 1-F )

d E

r?

D'ss

= 3000 - F [(X/Q) j ( L j + 1.1 Mj) iij ]

i I (1-F) m rt

= count rate per mrem /yr to the total body t.

']

=

c X/Q Kj gj See Note 2 J

count rate of the containment purge monitor for c

=

radionuclide concentrations to be cascharged.

kg rate of release of noble gas radionuclide i (uCi/sec)

~

=

l 51 average rate of release of noble--gas racionuclide i from the ventilation system for the elapsed-fraction of the

}

.j year F (uCi/sec).

l s

count rate per mrem /yr to the skin r

=

7.

{

= c XIQ (Lj + 1.1 Mj).qj See note 2 NOTES a

I p

1) The calculated setpoint values will be regarded as upper bounds for the I,

actual setpoint adjustments.

That is, setpoint adjustments are not l

required to be performeo if the existing setpoint level corresponds to a i

g lower count rate than the calculated value.

i

2) For ease of implementation, the count rate setpoints may be calculated by J

l applying the methodologies presented in Sections 2.1.1 and 2.1.2 with the more restrictive assumption of continuous release at the limiting rate for a year as follows:

D"TB = DTB = D'TB = 500 mrem / year i

0"ss " Uss - D'ss = 3000 mrem / year GRAND GULF, ljNIT 1 2.0-3 1/82

.4-

,m.

I i

,J 3)

A more conservative setpoint may be calculated to minimize requirements I

for adjustment of the monitor as follows:

L.

D"TB 500 mrem /yr

=

L'I 0"33 3000 mrem /yr R"

t conservative count rate per mrem /yr to the total body (Xe-133

=

detection, Kr-89 dose)

+

C' i ('X/Q x K x 6")

l'

Where, ta h"

Assigned release rate value of, for example,1.0 pCi/sec, Xe-133.

=

lJ

( See definition of C' below.)

C' count rate of vent monitor for an. effluent concentration of '.e-133

=

o corresponding to a 1.0 uC1/sec release rate of Xe-133, i

f

( Note: Calculate the related concentration based on dilution flow.)

LJ total body dose factor for.Kr-89, the most restrictive isotope, K

=

2 j

from Table 2.1-1.

c nservative count rate per mrem /yr to the s' kin j

R" i

=

s L:

C'

- (L + 1.lM) x _ d".

X/Q x

=

l La

Where, i

skin dose factor for Kr-89, the most restrictive isotope, from

['

L

=

L.

Table 2.1-1, M

air dose factor for Kr-89, the most restrictive isotope, from

=

j Table 2.1-1.

D"TB 500 mrem /yr

=

4 0"ss 3000 mrem /yr

=

r" t

conservative count rate per mrem /yr to the total body for

=

containment purge only

.f c'

.- {X/Q x K x q" GRAND GULF, UNIT 1 2.0-4 1/82

3

~

Where, 7
jj q"

release rate from the containment purge (may be determined for

=

maximum flow from the system and the concentration specified for 6

c' above).

1 c'

count rate of the containment purge monitor corresponding to a

=

E f

^ ~ '

j 1.0 uCi/ml concentration of Xe-133, 1

j r"

conservative count rate per mrem /yr to the skin for containment

=

3

.s purge only, i

J 4

c, T

X/Q x (L + 1.lM) x q"

=

2 t

{

J l

4

,. )

A i

i i

4 h

.,l i

J i

1 l

2 I

+

l

.i t

d i

3 4

GRAND GULF, UNIT 1 2.0-4a 1/82 3

1

_,_--_.m.,

t b

c j

s i

1 2.2.2.a For the purpose of implementation of Specification 3.11.2.2, l'

F the air dose in unrestricted areas shall be determined as follows:

I O

i y

air dose due to gamma emissions from noble gas

=

P j

L, radionuclide 1 (mrad) 1

-8 S

3.17 x 10 E M X/Q' Qj (1) r

=

[

9 9

4 i'

i

Where,

,L 1

X/Q'-

relative concentration for unrestricted areas

=

1 r

-6*

3 5.176 x 10 sec/m, in the WSW sector

=

},

M g air dose fac,torudue to. gamma,emissionscfrom, noble gas

=

radionuclide i' ($irad/yr per uhi/m h from kible 2.1-1 3

r 4

.[

Q j

1..

.. ~

4 cumulative release of noble gas radionuclide i

=

z,.

y over the perfo@of sint'erest'(u'C[)Y

'i Note:

3.17.~x' 10~0 'is"the, inverse ofo the nusb.er of5econds per year, and I

I' D

air dose due to beta emissions from nbble gas S

=

radionuclide i (mrad) d 2

i (3217 x 10'8 E[N[X/Q (2)

=c d

Where, i,

N g air dose factor due to beta emissions from noble gas

=

j radionuclide i (mrad /yr per uCi/m ) from Table 2.1-1 I,

l l

Values taken from Reference 4, Table 6.1.26 I

l GRAtlD Gl]LF, 'JillT 1 2.0-7 1/82 a

l

i

\\

~l

)

i s

t X/Q' relative concentration for unrestricted areas

=

-6*

3 Il 5.176 x 10 sec/m, in the WSW sector

=

t n,

O g

cumulative release of noble gas radionuclide i

=

over the period of interest (uCi).

f 2.2.2.b Dose to an individual from tritium, radiciodines and radioactive materials in particulate form, with half-lives greater than eight (8) days will be calculated for the purpose of implementation of Specification 3.11.2.3 as follows:

  • Values taken.from Reference 4. Table 6.1:.26

.-r

?

m lJ r,

GRAND GULF, UNIT 1 2.0-7a 1/82 J

P

~.

~' ~

~

D

[

1 TABLE 2.3-1 ATMOSPHERIC DISPERSION PARAMETERS

SECTOR X/Q 0/Q N

5.468 x 10-7 1.840 x 10-9 NNE 4.079 x 10-7 1.600 x 10-9

-6 NE 1.121 x 10 5.759 x 10-9 i-ENE 7.044 x 10-8 3.207 x 10-10 E

2.283 x 10-7 1.093 x 10-9 ESE 7.188 x 10-8 3.520 x 10-10 SE 1.817 x 10 8.420 x 10-10 l

2 SSE 7.600 x 10-7 3.300 x 10-9 S

1.219 x 10 :3.809 x 10-9 SSW 4.113 x 10-7 8.261'x 10-10 SW 3.001'x 10-6

.4.440 x 10-9 WSW-3.931 x 10-7 3~.177 x 10-10 W

4.259 x 10-7 3.'476 x 10-10 WNW 4.359 x 10-7 4.662 x 10-10 NW 1.548 x 10-7 2.733 x 10-10 NNW l.073 x 10-6 4.174 x 10-9 f

l

Reference:

Grand Gulf Nuclear Station, Environmental Report, Table 6.1.26 l

L GRAND GULF, UNIT 1 2.0-24 1/82

, - - - + -.,- - - - -, -

-m

-~

,weq<

r N -6h w-6>

.m-.

p I

)

J 2.4 Definitions of Gaseous Effluents Parameters P

1 height of reactor building (m) (2.3.1) o b

=

n C

count rate of the station vent monitor corresponding to grab i

g sample radionuclide concentrations (2.1.1) 3' C'

count rate of station vent monitor corresponding to a 1.0

[

]

pCi/ml concentration of Xe-133 (2.1.2) r count rate of the containment purge monitor for radionuclide c

y, concentrations to be discharged (2.1.2) c' count rate of the containment purge monitor corresponding to a 1.0 uCi/ml concentration of Xe-133 (2.1.2) relative eposition rate for ground level releases from Figure O

g 2.3-3 (m- ) (2.3.2) n Do average organ dose rate in current year (mrem)

(2.2.1.b) a O

dose to an Individual from radioiodines~and radionuclides in p

particulate form, with half-life greater than'eight days u

(mrem)

(2.2.2.b)

D 7

u 3

average skin dose rate in current year _(mrem)

(2.2.1.a)

Dtb average total body' dose rate in current year (mrem)

(2.2.1.a)

Dg air dose due to beta emissions from noble gas radionuclide 1 (mrad) (2.2.2.a)

D air dose due to gamma emissions from noble > gas radionuclide 1 y

(mrad) (2.2.2.a) relative deposition per unit area (m-2)

(2.3.2) i D/Q plume depletion f actor at distance r for appropriate stability 6

class and effective neight from Figures 2.3-2 and 2.3-3.

(2.3.1) i F

fraction of current year elapsed at time of calculation (2.1.1)

=

open terrain recirculation factor at distance r from Figure k

2.3-1 (2.3.1)

K total body dose factor for Kr-89, the most restrictive isotope 3

~

(mrem /yr per pCi/m ), from Table 2.1-1 (2.1.2)

Kj total body dose faqtor due to gamma emissions from isotope 1 (mrem /yr per uCi/mJ) from Table 2.1-1 (2.1.1) limiting dose rate to the total body based on the limit of 500 DTB

=

mrem in one year.

(2.1.1)

GRAND GULF, UNIT 1 2.0-25 1/82

o iJ 2.4 Definitions of Gaseous Effluents Parameters (Continued)

I i3 D33 limiting dose rate to the skin based on the limit of 3000

=

mrem in one year. (2.1.1) l D'TB limiting dose rate to the total body based on the limit of

=

500 mrem in one year (containment purge) (2.1.2) c, D'ss limiting dose rate to the skin based on the limit of 3000

=

mrem in one year (containment purge) (2.1.2) limiting dose rate to the total body based on the D"TB

=

conservative dose rate of 500 mrem / year.

(Note 2) a limiting dose rate to the skin based on the conservative dose 0"33

=

{j rate of 3000 mrem / year.

(Note 2) r, L

skin dose factor for Kr-89, the most restrictive isotope

=

3 ij (mrem /yr per pCi/m ), from Table 2.1-1 (2.1.2)

Lj skin dose factor due to. beta emissions from isotope i

=

?

(mrem /yr per 'uCi/m3) from Table.2.1-li (2.1.1) o M

airdosefactorfog)Kr-89,themostrestrictiveisotope

=

(mraa/yr per uCi/m, from Table 2.1-1 (2.1.2)

]

~

Mj air dose factor'due to gamma emissions from isotope i

=

3 (mrad /yr per pCi/m ) from Table 2.1-1 (2.1.1)

J air dose factor due to beta emissions from noble gas radio-Nj

=

3 nuclide i (mrad /yr per uCi/m ) from Table' 2.1-1

( 2. 2.'2. a) dose parameter for radionuclide i, (mrem /yr per pCi/m3) for Pj a

=

inhalation and (m2. mrem /yr per uCi/sec) for other r

pathways, from Table 2.2 (2.2.1.b).

I" Qj rate of release of noble gas radionuclide i (pCi/sec) (2.1.1)

Uj average rate of release of noble gas radionuclide i for the

=

elapsed fraction of the year F (pCi/sec) (2.1.1)

Q'i average release rate of isotope i of radiciodine or other

=

radionuclide in particulate form, with half-life greater than eignt (8) days in the current year (uCi/sec)

(2.2.1.b) i Qj cumulative release of noble gas radionuclide i over the

=

period of interest (uCi)

(2.2.2.a) 9'i cumulative release of radionuclide i of iodine or material in particulate form over the period of interest (uCi)

(2.2.2.b) rate of release of noble gas radionuclide i (pCi/sec)

(2.1.2) qi

=

51 average rate of release of noble gas radionuclide i from the elapsed fraction of the year F (pCi/sec)

(2.1.2)

[

GRAND GULF, UNIT 1 2.0-26 1/82

I l

2.4 Definitions of Gaseous Effluents Parameters (Continued) n i

i!

IJ Q"

assigned release rate value of, for example, 1.0 uCi/sec,

=

Xe-133; related to definition of C' for the vent. ( Note 3)

!j q"

release rate from containement purge associated with maximum

=

4 flow from system and concentration specifieo for c'.

(Note 3) dose factor for radionuclide i, (mrem /yr per uCi/m3) or

,j Rj

=

(m2. mrem /yr per uCi/sec)

I R s count rate per mrem /yr to the skin. ( 2.1.1)

=

t count rate per mrem /yr to the total body. ( 2.1.1)

R

=

R"3 conservative count rate per mrem /yr to the skin. ( 2.1.2)

=

p R"t conservative count rate per mrem /yr to the total body (Xe-133

=

y detection, Kr-89 dose). ( 2.1.2 )

oistance (m) from release point to location of interest for r

J dispersion calculation. (2.3.1) a count rate per mrem /yr to the skin for containment purge r

=

s

{

monitor only. ( 2.1.2 )

ts count rate per mrem /yr to the. total body for containment rt

=

q purge monitor only. ( 2.1.2 )

J r" s conservative count rate per mrem /yr to the skin for

=

containment purge only. (2.1.2) r" t conservative count rate per mrem /yr to the total body for

=

containment purge only. - (2.1.2)

Sd count rate of containment purge noble gas monitor at alarm

=

setpoint level. (2.1.2)

S count rate of station vent noble gas monitor at alarm y

setpoint level. ( 2.1.1)

[

vertical standard deviation of the plume with building wake

=

correction (m). (2.3.1) vertical standard deviation (m) of the plume at distance r o

for effective height under stability c.ategory indicated by T(m) from Figure 2.3-2.

( 2.3.1)

T temperature differential with vertical seperation ( *K/100m).

=

( 2.3.1) l-wind speed at ground level (m/sec). ( 2.3.1) u

=

GRAND GULF, UNIT 1 2.0-27 1/82

9 2.4 Definitions of Gaseous Effluents Parameters (Continued) a 1

i j

.j W

controlling sector annual average atmospheric oispersion at the

=

]

site boundary for the appropriate pathway (sec/m ).

(2.2.1.0) 3

.3[j relative concentration for unrestricted areas (sec/m3),

W' (2.2.2.D)

I r)i i

atmospheric dispersion (sec/m3)

(2.3.1)

J X/Q L

X/Q highest sector annual average atmgspheric dispersion at the

=

[]

unrestricted area boundary (sec/F )

(2.1.1) s.

X/Q' -

relative concentration for unrestricted areas (sec/m3)

]

(2.2.2.a) a i

i Y

s7 Li

^'

J 1

i i

fl

? L; i

+

e 1

+

l GRAND GULF, UNIT 1 2.0-28 1/82 h.

g

' 2. 5 GASEOUS RA0 WASTE TREATMENT SYSTEM l9 The essential components of the gaseous radwaste treaticent system for the l

'3 OPERABILITY requirement of RETS Specification 3/4.11.2.5 are indicated below.

n

.l d

4 MAIN VENT NARDWASTE BUILDlWG, b,

4

.J 9,o, no0F TOP CATALYT!C

'O 4

40 Scfm 2 STAGE taglallD*

RECCMS:NE5 0FF GAS AIR

}Q MIN F.JN1108 i

'l fROM MAIN EJECTOR

[

[

Moto up y/

t CONDEN5ER _

(

i f

PIPE i

~ ' k ONDEN5ER h

C"CO*'

q (REPRESENTATIVE

,8

" 85 '

,{

oF 1 PER UNIT) s

,;[;'s s;[;'n I

g (A55UME 16 HOURS PER TEAR OPERATION)

IA A

VE l-

,,m,!,"!;;.

]

'a:A;agr NECH. VAC. PUMP I

c saosasit '

C"yjDAL

.,a

""I' f!LTERI DU DE/

RA0WA5TE il-n 8UILDING

'; ( AlnOSPutRI te,

{

[

i U

eiE!!.! r;!;l,.-

,7ll;,{

n

- caj;;;aR-rit1ERi

(..OUTSIDE/

[n BulLDING BUILDlhG AIR.

> VENillATION SYSTEM FUEL HANDELING A

10 A1nespntail AREA anosat:0n f,>

i

,g h04tTOP '

I FILTER l Aut!LIARY, OUTSIDEf l

8UILUING

,j 70 aino$Pntaf' PRI ntPa n[Pa il Il i

FILife t1Lita FILitt FILTERl CONTAINMENT SLOG.

~

_~

,,, cnnacca;_

/

OugDEj Elf l

nangrop t

U l

10 aiPO$ Putti; flL k iL R f 1e iL STANOBY l

GAS

' ')

caseccas TREATMENT

'._ _ g

}

"n SYSTEM

  • 0uring normal operations the lemister and filter units

$$f' (REPRESENTATIVE f_

(prefilters, charcoal filters and HEPA filters) are not OF 2 PER UNIT)

U U

installed in the filter train. However, the filter train m

is available to be operable at a later date when the filter and demister are installe_.

\\

Taken from Reference 4, Figure 3-8.

GRAND GULF, UNIT 1 2.0-33 1/82

3

...R 2

3

.)

c,

)

{

LJ

/

N

~}

DELH1 LI

\\

TALLULAH

._x

~

.K BURG I

.,y,cK3gy e

cuN To.

' - " YO NA 2

s

/

'N

['

f

" ^

f WEL 1"

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