Text

Rev 0 to 6610-PLN-4200.01, Odcm
	ML20070U924
Person / Time
Site:	Three Mile Island
Issue date:	03/04/1991
From:	Good B, Shawn Williams; GENERAL PUBLIC UTILITIES CORP.
To:	;
Shared Package
ML20070U921	List: ML20070U920; ML20070U924;
References
	6610-PLN-4200.0, NUDOCS 9104100108
	Download: ML20070U924 (92)
	v • d • e

VCo s,. #.y p-_M,m.

.g EM ., a

- - ne;,u._,, '

f kT IN T@(

i L y ; t.wy l pfffs , con.' **

J,a p% guave. *'Y A & yf

.- a f

TNh.;m5lT SMd*

. b:ns S Li . O e u

w y! **

q w^-

l

- - w_;w ,eM

x" g; g '- ,

a n ; __ ~ --v__

w V i" 'r." , . } V. f yQ*yistff'gA Wy

y,_ L

. m n .a,_ p w,v u m ,h b,, wG ~n y,, p ) &,.,& p ' ' ~

3 ,

l h,s et;j, k } &g 4.}.

h 4g.p s 5 pyy,pd.y.,,,l;i)q s e g' c G M' whg , b. ,, 3' 4 , ' -

f4 u _ w. #W sk k l ,. .= rn l? [gj gg _; j f &_. l

_s gag o} if' y;l_

~

y'd 4

- 3, .it s ir p'_.

t gy *'

t f}

k gp me.u .

i i

i M

e h

N W. o rQ .v .

TL p

a yr

. 4 :t

y P

' ~' m,

,- 4 ,s d., -

". ea f

~ -

a, A , N ~.w, -.j ,

M * *fjh, I.

U $$ l u ) ' s ' '"- l9 ,

e

_ ,.Ol g Ar . s~ \ g) g nu

+\ % x, -' w-adf p ,e s %

-O/, g^ ' V -s,,; a , , , *

,J N

g M k,

my Q.. .

6:4 & 'RE D q n re f ,

-~ d +- "C ) . b % . ",' - - , , Q '%

y'% L

' ' ,e '

r hf , ly g y, Tn ,s..,%;, wdhkde.-

L r -

. . qJ _

m.v .

p ,,g g w%n ; ; m. s.a y ~

.e;sp w m g yl ; ,- e ,

,j 3-

,e* ;

?

.s

- e - .< . -

W ,r ,- ., .

$&, , v>&sQV3

.)m.h)

?

f ,

-- f.

4

+

hQQ+ )~ .:

~

Y),~4 M,Q

% . . yy (ma l{g.n'~gF g [nqq]Cs s Ii+ .%

mn y-TS ;f( '

5 %Q Q g/

a j W g, ' " . . n.g( 4 -c.

a -

g.an,- .

] *,

g,

.. ; a . ~ w y, *ge . . . , . ?

===' ,%.

p3 j- i ,,

x

- . ~ , . _ . x

s. l. ,f .

we . . -*

2- , NQ ,

h .' n Wpp[,,Q S4N.g,,_, ~ ww k b ..

.( .g

'~ <',~t '

q>.a a-f.eht

% Wg%y,sk. .:~W 254e .

et

- - - m h

4 .

<tx d ,'r . '

,#w

., y.

j wWy~- e m~

' a g

4. '

f '

. % + %.

.u ! . pi ,-_ ._ -

a

. .*p

y. .. . , < .

v. - .

y.. ,

q, p -Thre.e -Mile = . . , , ',' 8

7 IsinndA._ .

.i Ni O ....$ '. e ,I' , i -

g 4' .

d e + . k' ' O ,p .

, g 6 1 . . ~ 8[. . W ' . . .' . .

i -

9 .

'h' [t4 - .', ' '

e' ?, '

98 - . ' ,- .

,- l ..

...- - :. .; . , .7 -

7+

- s , , . - -

- .i. .# ' '

g,

, , , ^

I W' .

.' '~' '. . '"

k.. "

' . ~

.. w , ,g .

4 ,

6 *I '

j ,3 . ' '88" '

'g A

i.'

- . p a

l4 \ _.

f ' - i t , ,

3'

, a (',-[ , , 1.',', .

i

, -1 s .

. . .P P, ,.' , d3

.,l . h . ' '. . - - 1

. ,, . Q ., .

1 . '

- ' .' .i' .. . ! , .

l-

' ~ ' 'f.

.. - 4. .

.. -y i .., w.,, ,'. ,;.i O c

g ,. ' t , * . ', , . .

D , . 'f 6 ' .I ff.' .: E

'9illWd . , , , .

- ' i -

k ~s.u...

,.c ; , '4 s.'. ....: .; z

.. .g - .s

!' :t . ,. s' .

?

v;s .s. -

33 .gg.3

.a - . . . ...

. j. . .

i , ,,

. 4 % s .

. j 'i /%

gygg3py

$m 4tP _mM'=M M ,d N .t 3 _miihr sg? r w es m a s. :

A . ... .

3

.q

[4, T}l-)Q4g??$Q64l ; w;Nj4[+c . )hj' "L i

,#~ .-

,,... [. '

" ggl< ,,I

~ '

-i, .. u .

. - . - -. c

f, . -

r .,

i !

{*

l 1

i i

l l THREE MILE ISLAND UNIT 1 NUCLEAR GENERATING STATION <

Londonderry Township, Pennsylvania ,

i Three Mile Island Unit 1 is a pressurized water reactor (PWR). It produces over 800 net mega-j watts of electricity, enough to supply approximately 500,000 homes. The plant is located in Lon-

donderry Township, Dauphin County, about 10 miles south of llarrisburg, Pennsylvania.

! Construction of the plant began in 1968. Thil 1 was placed in commercial operation in Septem.

ber 1974. The plant has a liabcock and Wilcox nuclear steam supply system. The one million

)I horsepower turbine generator was supplied by General Electde, the architect enginter was Gilbert Associates and the construction was performed by United Enginem nd Construction. .

i TMI l operated from 1974 to 1979 at a cr.pacity factor of 77 pe. wit. TMI l was shutdown from l 1979 to October 1985 while undergoing hearings and chan es in response to the TMI 2 accident.

Three Mile Island Units 1 and 2 are owned by three sub::ldiaries of the General Public Utilities 1

System. Metropolitan Edison Company owns 50 percent, and Pennsylvania Electric Company and l Jersey Central Power and Light Company each own 25 percent. The plant is operated by GPU Nuclear Corporation - another subsidiary of General Public U;ilities Corporation. GPO Nuclear Corporation also is the licensed operator of TMI 2 and the Oyster Creek Nuclear Generating Station in Forked River, New Jersey. GPU Nuclea's headquarters are in Parsippany, New Jersey.

Their are more than 900 people in GPU Nuclear devoted to TMI l activities -li.ciuding 700 j located full time at TMI 1.

The plant's fuel core contains 177 fuel assemblies with a total of 90 tons o uranium. The. plant !

consumes about eight pounds of uranium a day during full power operation, sbout one third of the core is replaced during refueling outages.

l i

Y o

6 4

1 k..,~.- . _ . . . _ . . , _ . _ . _ . . . _ . . . , , _ . _ _ . . , . _ . _ . - . . _ . . _ , _ . . _ - - , , _ .%

FONATION OLY OFFSITE DOSE CALCULATION MANUAL CALCULATIONAL METHODOLOGIES l

THI Radiological controls Departmental Procedure 6610-PLN-4200.01 Revision No.

Title 0

Of f site Dese Calculation Manual (ODCM) calculate offsite coses Responsible office Applicability / scope due to radioactive ef fluents for demonstrating compliance with 6610 site technical specifications 10 Crn 20 & 10 CFR 50 - No Appendix ! _

Effective Date This document is within QA plan scope ,X , Yes ,,,

,X, Yes No S-fety Reviews Required ,,,

03/20/91 I

List of Effective Pages a Revision ga2'. Revision PaSe a Revision g Revision P,ajte 0 1-78 0 1.0 0 2-26 0 **52 1 ::3 0 2-79 0 0 2-27 0 2-1 0 2-80 0 0 1-28 0 1-64 2-2 0 1-81 0 0 1-29 0 1-55 1-3 0 1-82 0 0 1-30 0 I-56 1-4 2-83 0 2-5 0 2-31 0 I-57 0 2-58 0 1-84 0 1-6 0 2-32 0 2-59 0 1-85 0 2-7 0 1-33 0 0 2-60 0 1-86 0 1-0 0 1-34 0 2-35 0 1-61 0 2-87 T-9 0 <

1-36 0 1-62 0 2-10 0 2-37 0 2-63 0 2-11 0 2-12 0 I-38 0 1-64 0 2-13 0 1-39 0 I-65 0 0 2-40 0 1-66 0 3-14 0 2-16 0 1-41 0 2-67 2-16 0 1-42 0 1-68 0 0 2-43 0 1-69 0 2-17 0 3-18 0 I-44 0 2-70 2-19 0 I-45 0 I-71 0 0 1-46 0 1-72 0 1-20 0

-21 0 I-47 0 1-73 22 0 I-48 0 1-74 0 I-49 0 1-75 0 4-23 0 1-24 0 I-50 0 I-76 0 1-25 0 1-51 0 I-77 0 signature l Concurrino croanizational Element I Date 11 Oriainaterll I[ M I T I Radioloeical Encineer, TNT l.3-5-9/

I concurred ll I M M % M 'f d l Env. Controle l eMM9/

Sy ll -)L)I _ . EA L \ Rad. Enc. Manager, TMI l 2*G.Tl ll M ~

dh > l Rad. Con. Director, TMI l 2.

ld"N l l ll 1 I ll l ll l l 2pproved ll, NOktu k / l Rmd con and Env Controls, Director l J[M0/9 /

Sy ll b ) I Director. Nuclear Assurance I d /Y[Y/

1.0 2098c

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

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

) , i

- duClS8r THI Radiological Controls 6610-PLN-4200.01 l

Departmental Procedure Revision No.

T6tle 0

Offsite Dose calculation Manual (ODcM)

Table of contents 80etion D3 I-6 1.0 LIQUID ErrLUENTS SETPOINTS I-6 1.1 Liquid Effluent Monitor Setpoints 2-7 1.2 Liquid Release Points and Liquid Radiation Monitor Data I-11 8.0 LIQUID ErrLUENT DOSE ASSESSMENT Liquid Ef fluents - 10 Crn 60 Appendix ! I-11 2.1 Liquid Radweste System Dose Cale once per Month I-13 2.2 2.3 Alternative Dose calculation Methodology for Liquid Effluents I-14 I-19 3.0 LIQUID WASTE TREATHENT SYSTEM Description of the Liquid Radicactive Waste Treatment System I-19 1.1 I-19 3.2 Operability I-20 3.3 Representative Sampling Prior to Discharge I-23 4.0 CASEOUS EFTLUENTS HONITORING SETPOINTS 1-23 4.1 Noble Gas Monitors I-24 4.2 Particulate and Radiciodine Monitors 2-25 4.3 Gaseous Release Points and Gaseous Radiation Monitor Data

!*36 5.0 DOSE ASSESSMENT (GASEOUS EFTLUENTS)

I-36 5.1 Caseous Ef fluents - 10 CFR 20 Limits I-36 5.1.1 Noble cases I-36 5.1.1.1 Total Body 5.1.1.2 Skin I-37 Iodin 3s and Particulates 2-37 5.1.2 5.2 Gaseous Effluents - 10 CFR 50 Appendix ! I-39 5.2.1 Noble Cases I-39 5.2.2 Iodines and Particulates I-40 I-1 .2098c.

...___ . _ _ _ . __ ., _ . ._..,,___ _ . _ - . ~ . , , . _ ..__. _ _ _ _ . , _ _ _ . . _ . - . _ . - , . ._. _

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

. i l

THI Radiological Controls 6610-PLN-4200.01 Departmental Procedure Revision No.

Title 0

Of f site Dose Calculation Manual (ODCH)

Table of contents (Cont'd) g SOction Gaseous Radwaste System Dese calculation once per Month I 42 5.3 Alternative Calculational Nethodologies I-42 6.4 I-64 6.0 CASEOUS WASTE TREATMENT SYSTKH Description of the caseous Radwaste Treatment System I-64 6.1 I-64 6.2 Operability APPENDIX A-1 A. Pathway Dose Rate Parameter (P3 )

Inhalation Pathway Dose Factor (R g) 5-1 B.

Ground Plane Pathway Dose Factor (R g) C-1 C.

Grass-Cow-Hilk Pathway Dose Factor (Rg) D-1 D.

Cow-Heat Pathway Dose Factor (Rg ) E-1 E.

Vegetation Pathway Dose Factor (R ) F-1 F. g TABLES Liquid Release Point and Liquid Radiation Monitor Data I-9 Table 1.2 Liquid Dose conversion Factors (DCF): DF33 2-15 Table 2.1 Bioaccumulation Factors, BFg I-18 Table 2.2 Table 4.3 Gaseous Release Point and Gaseous Radiation Monitor Data .2-27 Dose Factors for Noble Gases and Daughters I-28 Table 4.2 Atmospheric Dispersion Factors for Three Mile Island - I-29 Table 4.3 Station Vent Atmospheric Dispersion Factors for Three Mile Island - I-30.

Table 4.4 Ground Release Dose Parameters for Radiciodines and Radioactivs I-31 l Table 4.5 l Particulate, Gaseous, Ef fluents Pathway Dose Factors, R3 - Infant, Inhalation I-43 Table 5.2.1 I-2 2098c 4

e , , - --- -- - - , ,- , . . . - . ~ ~ . . ,,n, ,-.- -

. . . , - . . . - . ,n. .-

___..___.._m - _ _ .._. _ _ _ _ _-_ _ . . _ _ _ . . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

. e THI Radiological controls Departmental Procedure 6610-PLe 4200.01 Revision No.

Title 0

l Offsite Dose calculation Manual (ODCH) f Table of Contents (Cont'd)

I l' age Metion Pathway Dome Factors, R3 - Child, Inhalation I-44 Table 5.2.2 I-45 Table 5.2.3 Pathway Dono Factors, R3 - Teen, Inhalation I-46 Table 5.2.4 Pathway Dose Factors, R3 - Adult, Inhalation I-47 Table 5.3.1 Pathway Dose Factors, R3 - All Age Groups, Ground Plane I-48 Table 5.4.1 Pathway Dose Factors, R3 - Infant, Grt.ss-Cow-Hilk Pathway Dose Factors, R3 - Child, Grass-Cow-Hilk I-49 Table 5.4.2 Pathway Dose Factors, R3 - Teen, Grass-Cow-Hilk I-50 Table 5.4.3 Pathway Dose Factors, R3 - Adult, Grass-Cow-Hilk I-51 <

Table 5.4.4 Pathway Dose Factors, R3 - Infant, Grass-Goat-Hilk I-52 l

Table 5.5.1 Pathway Dose Factors, R3 - Child, Grass-Goat-Hilk I-53 Table 5.5.2 Pathway Dose Factors, R3 - Teen, Grass-Goat-Hilt I-54 Table 5.5.3 Pathway Dose Factors, R3 - Adult, Grass-Goat-Hilk 2-55 Table 5.5.4 Pathway Dose Factors, Rg - Infant, Grtes-Co;*-Meat I-56 Table 5.6.1 Table 5.6.2 Pathway Dore Factors, Rg - Child, Grass-Cow-Heat I-57 Pathway Dose Factors, R3 - Teen, Grass-Cow-Heat I-58 Table 5.6.3 Table 5.6.4 Pathway Dose Factors, R3

Adult, Grass-Cow-Heat I-59 Pathway Dose Factors, R3 - Infant, Vegetation I-60 Table 5.7.1 Pathway Dose Factors, R3 - Child, Vegetation' I-61 Table 5.7.2 Pathway Dose Factors, R3 - Teen, Vegetation I-62 Table 5.7.3 Pathway Dose Factors, R3 - Adult, Vegetation I-63 Table 5.7.4 I-67 Table 7.1 THINS REMP Station Locations - Air Particulate and Air Iodine I-67 Table 7.2 THINS REMP Station Locations - Direct Radiation (TLD) 2-3 2098c

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

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

j e i i

THI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

Title 0

Offsite Dose calculation Manual (ODCH)

Table of contents (cont'd)

Page S*ction I-69 Table 7.3 TMINS REMP Station Locations - Surface Water THINS REMP Station Locations - Aquatic Sediment I-69

! Table 7.4 I-70 Table 7.5 THINS REKP Station Locations - Milk I-70 Table 7.6 THINS REMP Station Locations - Tish I-71 Table 7.7 THINS REMP Station Locations - Food Products-I-72 MAP 7.1 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations within 1 Hile of the Site I-73 MAP 7.2 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program

-Stations within 5 miles of the Site I-74 MAP 7.3 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations Greater than 5 miles from the site -

1-10 Figure 1.2 TH1 Liquid Effluent Pathways Liquid Radwaste I-21 Figure 3.1 Liquid Waste Evaporators I-22 Figure 3.2 THI Gaseous Effluent Pathways I-32 Figure 4.1 I-65 Figure 6.1 Waste Gas System I-4 2098c-f

. i

-(UCIS8r THI Radiological Controle (610-PLN-420D.01 i

1 Departmental Procedure Revision No, Title t

0 Offsite Dose Calculation Manual (ODCM)

INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the CPUNC Three Mile Island Nuclear Station Technical Specificatione. The CDCM describes the n:thodology and pt.rameters to be used in the calculation of of f site doses due to radioact.*.ve liquid and gaseous effluents and in the calculation of liquid and gaseous of fluent monitoring instrumentation alarm / trip setpoints. The ODCM contains a list and graphical description of the specific sample locations for the radiological environmental monitoring program. L! quid and caseous Radwaste Treatment system configurations are also included.

The ODCM will be maintained at the plant for ce as a reference guido and training documen*. of accepted methodologies and calculations. Changes in the calculation methods or paramecers will be incorporated into the ODCM inGPUNC order toinitiated assurechanges the ODCH represents to the CDCH the present methodology in all applicable areas.

will be implumented in accordance with the TM! Technical Specifications.

The ODCH follows the methodology and models suggested by NUREG-0133 (Ref erence 1), and for calculation of off site doses due Rsgulatory to plant offluent Guidereleases.

1.109, Revision 1 (Reference 2) Simplifying assumptions have been applied in t where applicabic to provide a more workable document f or implementation of the Radiological Effluent Control requirements.

GPUN impisments the THI Radiological Ef fluent Control Program and Regulatory Guide 1.21 (Semiannual Radioactive Effluent Release Report) requirements by use of computeriaed systehas to determine THI efiluent releases and update cumulative affluent doses.

l l

1-5 209Bc e .v.+.. ...w,..._3-..-s.....-.-

=_ , . * . - , . . - , _ , . , - , , - . . . , - . , . r- ,%--e.,,w,----.-ewe.m.,.-w, v. , + . . , . . . ..~-%, , , . , . , .

I , .

i Nuclear THI Radiological Controle Departmental Procedure 6610-PLN-4200.01__

i Revision No.

T6tle 0

Of f site Dose Calculation Manua! (ODcH) l a.0 L20UID trrLUENTS 1.1 Liciid Ef fluent Monitor __ set Points The liquid af fluent line monitors are set such that the concentration (s) of radionuclides in the liquid ef fluents will not exceed the concentration limits specified in 10 CFR 20, Appendix B Table II, Col 2. Table 1.2 and

'j Pigure 1.2 Itat Liquid Ef fluent Release Points and their parameters and a Liquid Release Pathway Diagram respectively.

To meet the above limit, the alarm / trip set points for liquid effluent monitors and flow measuring devices are set in accordance with the ic11owing equations

<C (eq 1.1) c*f r+t wherel in C= the effluent concentration limit implementing 10 CFR 20 for the gito, pC1/ml.

e= the set point, in pCi/mi, of_the liquid effluent monitor measuring the radioactivity concentration in the effluent line prior to dilution and release. The not point is proportional to the maximum volumetric flow-of the effluent line and inversely proportional to the minimal volumetric flow of the dilution stream plus the effluent stream. .The alert set point value is set to ensure that advance warning occurs prior to exceeding any limits. The high alarm set point value is such that if it were exceeded, it would result in concantrations exuoeding the 10 CrR l

20 limits for the unrestricted area.

fa flow set point as measured at the radiation monitor location, in volume per unit time, but in the same units as F below. Discharge flow ranges and flow recorder designations are listed in Table 1.2.

F= flow rate of dilution water measured prior to the release point, in volume per unit time. On site dilution minimal flows are listed in Table 1.2.

The set point concentration is reduced such that concentration contributions f rom multiple release points would not combine to exceed 10 CFR 20 limits.

i The set point concentration is converted to set point scale units using appropriate radiation monitor. calibration factors.

This section of the CDCM is implemerted by the Radiation Monitor System Set

' points procedure and for batch releases the Releasing Radioactive Liquid Waste procedure.

2-6 209Bc

r TMI Radiological controls Departmental Procedure 6610-PLN-4200.01 Revision No.

_ Title 0

l Offsite Dese calculation Manual (ODcM)

I I

1.2 Liquid Effluent Rolesse Points and Liquid Radiation Monitor Data I THI has three required liquid radiation monitors. These are RM-L6, RM-L10, and RM-L12. These liquid release point radiation monitors and sample points are shown in Table 1.2. RM-L7, the TMI outfall radiation monitor is also listed.

1.2.1 RM-L6 RM-L6 is an off line system, monitoring radioactive batch discharges f rom the THI-1 liquid radwaste system (see Figure 1.2).

These batch releases are sampled and analyzed per site procedures prior to release. The release rate is based on releasing one of two Waste Evaporator condensate Storage Tanks (WECST) at less than 10% MPC for each identified radionuclide, including conservative default values for Sr-89, Sr-90, and Fe-66. This ensures this batch release will meet the f ollowing equations

$ 0.10, (eq 1.2)

(C /NPC )

2 A where Ci = diluted concentration of the 1" radionuclide, MPC 3 = The most limiting concentration for that radionuclide in the unrestricted area (10 CFR 20, App. B, Table II, Col. 2). A valua of 3E-3 pCi/mi for dissolved and entrained noble games shall be used.

The set points for RM-L6 are set for each release based on the monitor response to each radionuclide identified in the gamma scan sample results as follows:

l (1.5)* (El (pci/cc)3*(CPN/pCL/cc)g) + (CPH,,,) = ALERT CPM (2.0)* [El (pci/cc)3 (CPM /pCL/cc)3) + (CPH,,,) = HIGE ALARN CPN where (pCL/cc)3 = positively idrntified radionuclides (CPM /pCL/cc)3 = RM-L6 sensitivity to radionuclide 1.

(CPMa n)

= RM-L6 background prior to batch release A high alarm on RM-L6 will close valve WDL-V-267 and terminate any WECST releases to the environment.

1.2.2 RM-L12 RM-L12 is an off line system, monitoring combin9d releases from the Industrial Waste Treatment System / Industrial Maste Filtration System (IWTS/IWFS). These set points are based on the maximum release rate from both IWTS and IWFS simultaneously, (see Figure 1.2) a minimum dilution flow rate, and 50% KPC for I-131, I-7 2098c

THI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

Title D

Offsite Dese calculation Manual (ODCM) which is the most limiting radionuclide at an HPC level of 3E-7 pCi/ml. These inputs are used in equation 1.1 to determine the P.H-L12 High Alarm set point. The alert set point is then 50% of the High Alarm set point. A high alarm on RM-L12 wi'.1 close !WT8 and IWrs release valves and trip release pumps to stop the release.

1.2.3 RM-L10 RM-L10 is a Na! detector submerged in the TMf-1 Turbine Building Sump (see rigure 1.2). The set points are based on the calculated RM-L12 sat point concentration, since the TBS discharges directly to the IWTS, which in turn discharges to the Susquehanna River.

Therefore, the concentration from the Turbine Building Sump should not exceed the set point calculated for the INT 8/IWrs release point. This monitor's high alarm will isolate power to the TBS sump pumps to terminate releases to the IWTS.

1.3 control of Liquid Releases TH! liquid ef fluent releases are controlled to less than 1.0 MPC by limiting RM-L6 the percentage KPC allowable f rom the two THI liquid releaue points.

and ef fluent sampling limits batch releases to less than or equel to 104 KPC, and RM-L12 and ef fluent sampling limits releases to less than or equal to 504 KPC for 3-131.

These radsatlan monitor set points also include built in meter error f actors to further ensure that THI liquid ef fluent releases are less than 1.0 HPC to the environment.

The radioactivity content of each batch of radioactive liquid waste is determined prior to release by sampling and analysis in accordance with Section II, Table 4.22-1. The results of pre-release analyses are used with the calculational methods in Section 1.1, to assure that the concentration at the point of release is maintained within the limits of control 3.22.1.1 in THI-1 Technical Specifications.

Post-release analysis of samples composited from batch releases are performed in accordance with Section II, Table 4.22-1. The results of the previous post-release analysis shall be used with the calculational methods in the ODcH to assure that the concentrations at the point of release were maintained within the limits of control 3.22.1.1.

The radioactivity concentration of liquide discharged f rom continuous release points are determined by collection and analysis of samples in accordance with Section II, Table 4.22-1. The results of the snalysis are used with the calculation &1 methods of the ODCH to assure that the concentration at the point of release is maintained within the limits of Control 3.22.1.1.

I I-B 2098c

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

. e 1

6510*PLN*4300 01 novision 0 TARLt 1.3 Lt7JtD PnUJtt P0!ert An LtW1D rat'I ATIDW Pt%!WP DA.TA (f) (F) (FR) (DF)

RIVI;M R11LA82 LipVID C183 TAR 33 RALIATION TO MIRATION i F14W T14W L!GUID RELEASE ON $1TE AATE ELAR FitLD mrt19R liritalock (

fat 1ATICs Potrl CPM CILVf1Ce SENt!T!VITY (YES/NO) l (Maattus (FLOW DILtft!DN OPM VALYts SN!10h Diw (kange) FA?!OA (CPM /pC1/ec) !

(CETT L"r0P) IbOATION Voluse) FJCORDER) e ss eee e ee ee ee ee e e ee ee e e ee e e e e e e ee e e e e e e ee e e ee ee ee ee sol.004 ft? AVE. ) (s 131 YE8 WtteT 0 30 gpa WDL*V267 RM LE tel' tievotion (1.4t6 6.480) 7.16t?

(tal) Auxiliary Blog. batch (rT.N) (P'T 3 4C )

kaleessa (6000 gal.)

p.A. 237 Avt. $ to.137 Yss RM L1 South end et station sol.000 7.16t? WDL*V28't TMI 1 @CT D16 charge (ttalet) (1.416*l.418) eWDL*h 1311 (Ba!)

eell,000 ft? Avt. A !=131 Yta Submerged in Turbine 0 400 gp ED-t9A, PM L10 1. !,3 9 (tal) Turbine 6Mg. Sulldiat (PT 301) (PT 144) (1.4t6 8.418) 30.rts tusp ausp (79 301)

(10,000 gal.) to.1}?

6.lt?

eell,000 ft? AVE. 6 !*131 Yta DM.Lil IWrs Building IVr8/JWTS 0100 pp IW V73, (I't.146) (1.4t6*6.488l 1.S*8 (pal) FW Corner Continuovo (FT 343)/ !W P16,11,10 helseosa 0 100 gps (30,000/ (s*137 (f7 173) 6.881 IW V279, 40,000 gal.)

IW-729,30 eWOL t 1311 has been flanged of f as a 'IM12 liquid outta11.

g.9 2096c

, i THI Radiological Controls Departrnental Procedure 6610-PLN-4200.01 Revistori No.

31tle 1

0 Offette Dose Calculation Mancal (ODCH)

FICURE 1.2 TMI Liould Effluent Patings T Ml.2 Pre 4pereuon Ausgary Buder Sump 8 l Blowoocn Creern Cleaning i Bas 6ns (2) f (Intermed.'6M i _ _

"" (6: iC)

' t Bump west '! '

i

! 'T j Turtune Bundeng ,

antermed. Bldg L j38"P f **8 I

l. Ah

> 13 1 imm.

Sundmg Barnstery l l /RML) tC; "'""" inaustrial ipown [ 'sD,--

Wasse q !Vesamie [tiy,g_ Pg8 BDP$YIts t

, TW11&2 l uI

- (') ! o, a ,,,e,,en,,,,en, 3

,,.e,, syunern

-3 Plant Neut. WECST Y ank p,,,p 'I j ,

Caredenesse hanse - IWT Carten F6her Stavage C

(B) T anko (sec6eash) ,o son

) Tank 18 Mme Pump (b-l solids p;,,,,l {

CO T.tB

p- Cne l Co so 9 y O

l industr6a! Waete - AethrNy bowage Tseatment ,

industrial waste Plant F 6hof C/ stem (0_ Ibl j

( {}

tu .)

ib) .> ORAB BAMPLE RMLi

~

i Wochanical Draft

@ .y /

l Cooien0 Tower ([i -> COMPOBfTE SAMPLER I

Una ,t tRMLi-> RADIATION WONITOli TO RIVER v

l Component Coo]6 l Emergency

! l overfkm > NO NORMAL FLOW 9 Water Unit .1 I

l I-10 2098c

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

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

1 I. a i

f 1

TH1 Radiological Controlo 6610-pin-4200.01__

Departmental Procedure Paviston No.

_T6tle 0

of f site Dose Calculatien Manual (oDUM) 2.1 tiquid Ef fluents .10 Crn F0 Appendix !

The dose from liquid effluents results from the consumption _of fish and drinking water. The location of the nearest potable water intake is FF&L

The use of Brunner Island Steam Electric Station located downstream of TH1.

the flow of the Susquehanna River as the dilution flow is justified based on the complete mixing in the river prior to the first potable water supply, adequately demonstrated by fiume tracer die studies and additional liquid ef fluent release studies conducted using actual THI-1 tritium-releases.

Other pathways contribute negligibly at Three Mile Island. The dose conteibution f rom all radionuclides in liquid ef fluente released to the unrestricted area is calculated using the following expressions f f 1 (eq 2.1)

Dose j = E E (4t) 1 (C ) 1 3 (AW3 E FR) + (AFg 1 FD I DF) '

i )

where Does j = the cumulative dose commitment to the total body or any organ, j, f rom the liquid ef fluents f or the total time period, in mrom.

P At = the length of the time period over which C and i are 3 averaged for all liquid releases, in hours.

the average concentration. of radionuclide,1, in undiluted liquid C3* af fluent during time perio3 At from any liquid release, in pC1/ml.

NOTE: For Fe-55, Sr-09, sr-90, prior to batch releases conserva-tive concentration values will be used in the initial dose calculation based on similar past plant conditions. LLD l values are not used in dose calculations. ........e f a undiluted liquid waste flow, in gpm.

FD = plant dilution water flowrate, in gpm FR = river flowrate, in gpm.

f DF a dilution f actor as a result of mixing ef fects in the near field of l the discharge structure of 0.2 (Reference 2, Table A-2) or taken to be 5 based on the inverse of 0.2.

AWg and AFy a the site-related ingestion dose commitment f actor to the total body or any organ, j, f or each identified principle gamma and beta emitter, in mrom/hr per NCL/ml. AW is the factor for the water pathway and AF is the factor for the fish pathway..

2-11 209Bc

_- _ ~ _ . _ .

[ENuclear TH1 Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

]

Titis 0

offsite Dese calculation Manual (oDcM) are determined by the following equation Values for AW33 (eq 2.2)

RW ) * (1.1455) x (0,) x (DF33) 3 where:

1.14E6 = (1.0E6 pC1/pci) x (1.0E3 al/kg) + (8760 hr/yr)

U, = Water consumption rate for adult from Reg. Guide 1.109 (Rev. 1),

taken to be 730 kg/yr.

DF = ingestion does conversion f actor f or radionuclide, i, for adults 33 total body and for " worst case" organ, j, in mrom/pci, from Table 2.1 (Reg. Guide 1.109 (Rev. 1))

Values for Ar33 are determined by the following equation:

(eq 2.2.2)

AF) = (1.14E5) x (U t) x (DFg3) x (Erg) 3 wheral 1.14E5 = defined abova U, = adult fish consumption, assumed to be 21 kg/yr f rom Reg. Guide -

1.109.

DF33 =

ingestion dose conversion factor for radionuclide, 1, for adult total body and for " worst case" organ, $, in mrera/pci, from Table 2.1 (from Reg. Guide 1.109 (Rev. 1)).

l BF3=

Bioaccumulation f ar tor for radionuclide, i, in fish, in pCi/kg per pci/1 from Table 2.2 (Reg. Guide 1.109 (Rev. 1]).

1-12 -2098c

I

""ab" l (UOlS8r TM1 Radiological Controle 6610-PLN-4200.01 j

Departmental Procedure

! Revision No.

Title 0

Offsite Dose calculation Manual (ODcM) 2.2 Liquid Radweste system Dose cales onee/ Month Liquid Radwaste Treatment System Controla 3.22.1.3 requires that appropriate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the monthly projected doses due to the liquid af fluent releases f rom each unit to unrestricted areas (see Figure $-3) would exceed 0.06 mram to the total body or 0.2 neem to any organ in any calendar month. The following calculational method is provided for performing this dose projection.

At least once a calendar month, the total dose f rom all liquid releases for the month will be integrated. An estLmated projected dose for the next month will be determined based on plant operation and the integrated dose for the previous month. If this estimated projected dose exceeds 0.06 mrom total body or 0.2 mrom any organ, appropriate portions of the Liquid Radwaste Treatment System shall be used to reduce radioactivity levels prior to release.

I-13 2098c

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

i THE Radiologscal Controls

-Departmental Procedure 6610-PLN-4200 01___

~

Revision No.

~ T6tle 0

Offsite Dose calculation Manual (ODCM) -

2.3 Alternative Dose calculation Methodology for Liquid Ef fluente As an alternative, models in, or based upon, those presented in Regulatory i

Guide 1.104 (Rev. 1) may be used to make a cotoprehensive dose assessment.

Default parameter values from Reg. Ouide 1 109 (Rev. 1) and/cr actual site specific data would be used where applicable.

i f

1 i

I i

(

1 l

1-14' 2098c

i 4

e TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

Title 0

Offsite Dese Calculation Manual (ODCH)

TABLE 2.1 LIQUID DOSE CONVERSION FACTORS (DCF)t D{,y Page 1 of 3 INCESTION DOSE FACTORS FOR ADULTS *

(MREM PER PCI INCESTED)

T. BODY THYROID KIDNEY LUNO __ CI-LLI__

NUCLIDE BONE ___ LIVER 1.05E-07 1.0$E-07 1.05E-07 1.0$E-07 1.05E-07 H 3 NO DATA 1.0$E-07 6.68E-07 6.68E-07 #

5.68E-07 5.68E-07 5.6BE-07 5.68E-07 C 14 2.841.-06 1.70E-06 1.70E-06 1.70E-06 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 NA 2.66E-09 1.59E-09 5.86E-10 3.63E-09 6 69E-07 CR 51 No DATA No DATA 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 54 No DATA 4.5 E-06 MN 2.04E-0P NO DATA 1.46E-07 NO DATA 3.672-06 KN 56 NO DATA 1.15E-07 1.09E-06 1.90E-06 4.43E-07 NO DATA NO DATA 1.06E-06 FE $$ 2.75E-06 2.85E-06 3.40E-06 1.02E-05 3.91E-06 NO DATA NO DATA 4.34E-06 FE 59

.. ..... ... ................... 1.67E-06

. NO..DATA NO DATA NO DATA

... 1.51E-05 CO $8 No DATA 7.45E-07 4.02E-05 4.72E-06 NO DATA NO DATA NO DATA CO 60 No DATA 2.14E-06 1.88E-06 4.36E-06 NO DATA NO DATA NO DATA NI 63 1.30E-04 9.01E-06 6.86E-08 3.13E-08 HO DATA NO DATA NO DATA- 1.74E-06 NI 65 5.28E-07 7.10E-06 NO DATA 8.33E-08 3.91E-08 NO DATA 2.10E-07 NO DATA CU 64 1.03E-05 NO DATA 9.70E-06 EN 65 4.84E-06 1.54E-05 6.96E-06 NO DATA

.................. ....... ........................... 1.37E-09 NO DATA 1.28E-08 NO DATA 2.96E-09 2N 69 1.03E-08 1.97E-08 NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 Bi. 83 -NO DATA NO DATA NO DATA 4.09E-13 BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA NO DATA 4.163-06 2.11E-05 9.83E-06 NO DATA.

RB 86 NO DATA NO DATA. NO DATA .8.36E-19

-6.05E-08 3.21E-08 NO DATA RB 88 NO DATA

.....m.............. ...... . ...

4.01E-00 2.82E-08 NO DATA NO DATA No DATA 2.33E-21 RB 89 NO DATA NO DATA NO DATA 4.94E-05 3.0BE-04 NO DATA 8.84E-06 NO DATA SR 89 NO DATA 2.19E-04 7.5BE-03 NO DATA 1.86E-03 NO DATA NO DATA SR 90 2.29E-07 No DATA NO DATA NO DATA 2.70E-06 SR 91 5.67E-06 NO DATA 4.26E-05 9.30E-08 No DATA NO DATA NO DATA SR 92 2.15E-06 NO DATA 1.02E-04 2.58E-10 NO DATA NO DATA NO DATA 90 9.62E-09 NO DATA Y

I-15 2098c i

- - - _ _ _ ,~ - . -

.-. ,_ _ _ . _ , , - . . _ , _ . _.__ _ _ , . _ _ . _ _ r _, , . . , _ _ , .

I TH! Radiological Controls Departmental Procedure 6610-PsN-4200.01 Revision No.

T6tle O

Of f eite Dese C61ruintion Manual l0DCM)...

TABLE 2 1_ (Cont'd) 1.10V!D DOSE CONVER$f 0N FACTORS (DCF): DF g

)

Page 2 of 3 INGESTION DOSE FACTORS EOR ADULTS *

(MREM PER PCI INGESTED)

T. BODY THYROID KIDNEY LUNG _ _O!-LL3_

NUCL7DE BONE _ liver NO DATA NO DATA NO DATA 2.67E-10 ~

Y 91H 9.09E-11 HD DATA 3.52E-12 7.1&E-05 3.77E-09 NO DATA NO DATA NO DATA Y 91 1.41E-07 NO DATA 1.48E-05 2.47E-11 No DATA NO DATA NO DATA 3 ................... ..,.... ......................................................-.

Y 92 0.45E-10 NO DATA NO DATA No DATA S.50E-05 No DATA 7.40E-11 NO DATA Y 93 2.66E-09 1.53E-08 No DATA 3.09E-05 9.75E-09 6.60E*09 NO DATA ER 95 3.04E-00 5.12E-10 No DATA 1.0$E-04 1.68E-09 3.39E-10 1.55E-10 No DATA-97 ER 1 06E-09 NO DATA 3.42E-09

.......NO...........-.-....

DATA 2.10E-05 ND 95 6.22E-09 3 46E-09 NO DATA 9.99E-06 4.31E-06 0.20E-07 NO DATA 9.76E-06 MO 99 NO DATA 3.42E-10 4.133-07 6.9BE-10 8.09E-09 No DATA 1.06E-08 TC 99H 2.47E-10 3.59E-09 NO DATA 6.59E-09 1 87E-10 1.107.-21 TC 101 2.54E-10 3.662-10 2.16E-05 NO DATA 7.97E-0B NO D ATA . 7 064-07 No DATA RU 103 1.05E-07 1 99E-07 -No DATA 9.425 06 NO DATA 6.0BE-09 NO DATA RU 105 1.54E-00

......................................-~..............-.....................-

3.4BE-07 NO DATA 5.31E-06 No DATA

..1.78E-04 RU 106 2.75E-06 NO DATA 0.79E-00 NO DATA 2 91E-07 No DATA 6.04E-05 A0 110H 1.60E-07 1.40E-07 1.38E-06 1.97E-05 2.00E 00 4.26E-07 1.82E-09 0.0 SD 125 1.79E-06 1.07E-05 9.71E-07 3.59E-07 0.06E-07 1 09E-05 NO DATA TE 125H 2.68E-06

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . NO . . DATA

. . . . . . . .2.27E-05

..---.~.

2.42E-06 6.25E-07 1 73E-06 2.75E-05 TE 127H 6.772-06 4.48E-07 NO DATA 8.68E-06 TE 127 1.10E-07 3.95E-00 2.30E-06 0.15E-08 1 82E-06 3.95E-06 4.80t<05 NO DATA- 5.79E-05 1.15E-05 4.29E-06 TE 129H 1.65E-09 2.41E-0B 1.32E-07 NO DATA

..-~.

1.37E-08.

TE 129 3.14E-00 1.18E-08 8.403-05 1.73E 06 B.46E-07 7.05E-07 1.34E-06 0.57E-06 NO DATA TE 131H 1.62E-00 B.63E-08 NO DATA 2.79E-09 TE 131 1.97E-06 0.23E-09 6.22E-09

. . . . . - . . . . . . . . . . . . . . . . . . . . . . ~ . . . . . . . . . . . . . . . . . . . . . . . . . . . NO . ~DATA

. ~ . . . .-7.71E-05 1.63E-06 1.53E-06 1.80E-06 1.57E-05 TE 132 2.52E-06 NO DATA. 1.92E-06 2.23E-06 8.00E-07 1.09E-04 3.48E-06 I 130 7.56E-07 1.57E-06 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA

. ...131.. .. ..... . ............ ...................-..........

I 1.90E-07 1.90E.05 8.65E.07 No DATA 1.02E-07 I 132 2.03E-07 5.43E-07 2.22E-06 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 NO DATA 2 133 2.51E-10 2.BBE-07 1.03E-07 4.99E-06 4.5BE-07 No DATA I

! 134 1.06E-07 2 2098c

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

4 TMI Radiological Controls Departmental Procedure _ 6610-PLN-4200.01 Revision No.

T6tle 0

Offsite Dose calculation Manual (OSCM)

TABLE 2.1 (Cont'd)

LIOUID DOSE COtNERSION TACTORS (DCF) DF,)

! Page 3 of 3 INGESTION DOSE FACTORS FOR ADULTS *

(MREM PER PCI INGESTED)

T. BODY THYROID KIDNF,Y_ LUNO GI-LLI_

ECLIDE DONE LIVER _

4.28E-07 7.65E-C5 1.86E-06 NO DATA 1 312-06 135 4.43E-07 1.16E-06 2.59E-06 I

1.21E-04 NO DATA 4.79E-05 1.59E-05 CS 134 6.22E-05 1.48E-04 1.96E-06 2.92E-06 2.57E-05 1.85E-05 NO DATA 1.4?E-05 136 6.51E-06 CS 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 CS 137 7.97E-05 1.09E-C4 4.65E-13 5 40E-08 NO DATA 8.01E-08 7.91E-09 CS 138 5.52E-08 1.09E-07 1.72E-07 J.91E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 BA 139 9.70E-08

............................. ................................................ 1.33E-06 NO DATA 8.67E-09 1.46E-08

.4.18E-05 BA 140 2.03E-05 2.55E-08 2.22E-17 3.56E-11 1 59E-09 NO DATA 3.31E-11 2.02E-11 BA 141 4.71E-08 1.85E-11 1.24E-11 3.00E-26 BA 142 2.13E-08 2.19E-11 1.34E-09 NO DATA 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA 140 2.50E-09 1.26E-09 4.25E-07 1 45E-11 NO DATA NO DATA NO DATA LA 142 1.2BE-10 5.82E-11 2.42E-05 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA CE 141 1.35E-10 NO DATA 5.37E-10 NO DATA 4.562-05 CE 143 1.65E-09 1.22E-06 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 CE 144 4.88E-07 2.04E-07 4.03E-06 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA PR 243 1.25E-11 1.53E-12 NO DATA 7.0$E-12 NO DATA 4.33E-18 PR 144 3.01E-11 3.49E-05 6.29E-09 7 27E-09 4.35E-10 NO DATA 4.25E-09 NO DATA ND 147 NO DATA 2.82E-05 8.61E-08 3.01E-08 NO DATA NO DATA W 187 1.03E-07 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E-05 NP 239 1.19E-09 o Dose f actors of internal exposure are for continuous intake ove r a one-year period and include the dose commitment over a 50-year period; from Reg. Guide 1.109, Reference 2. Additional dose f actor f or nuclides not included in this table may be obtained from NURFG-0172, ODCH Reference 6.

I-17 2098c

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

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

1 THI Radiological Controla Departmental Procedure 6610-PLN-4200.01 Revision No.

Title 0

Offsite Dese Calculation Manual (ODCM)

TABLE 2.2 B20 ACCUMULATION FACTORS, BF 3 B10 ACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF SITE-SPEC 7FIC DATA *

(pci/kg per pC1/ liter)

TRESNWATER FISH INVERTEBRATE ELEMENT H 9.0E-01 9.0E-01 C 4.6E+03 9.1E+03 NA 1.0E+02 2.0E+02 CR 2.0E+02 2.0E+03 MN 4.0E+02 9.0E+04 4

FE 1.0E+02 3.2E+03 CD 5.0E401 2.0E+02 NI 1.0E+02 1.0E+02~

CU 5.0E+01 4.0E+02 IN 2.0E+03 1.0E+04 BR 4.2E+02 3.3E+02 RB 2.0E+03 1.0E+03 SR 3.0E+01 1 0E+02 Y 2.5E+01 1.0E+03 ER 3.3E+00 6.7E+00 NB 3.0E+04 1.0E+02 MO 1.0E+01 1.0E+01 TC 1.5E+01 5.0E+00 RU 1.0E+01 3.0E+02 RH 1.0E+01 3.0E+02

- SB 1.0E+00 1.0E+00 TE 4.0E+02 6.1E+03 7 1.5E+01 5.0E+00 CS 2.0E+03 1.0E+03 BA 4.0E+00 2.0E+02 LA 2.5E+01 1.0E+03-CE 1.0E+00 - 1.0E+03 PR 2.5E+01 1.0E+03 ND 2.5E+01 1.0E+03 W 1.2E+03 1.0E+01 NP 1.0E+01 4.0E+02

Bioaccumulation f actor values are taken from Reg. Guide 1.109, Table A-lj, Reference 2.

- Sb bioaccumulation factor value is taken from EPRI NP-3840, Reference 7.

l I-18 2096c

_ . _ _ _ _ _ _ . _ 2._-___._. . _ _ . . . - , , _ _ . , - _.c_. , , , ,, . _ _ . , _ , , .

THI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

Tatle 0

Offsite D,ose Calculation Manual (ODCM) 3.0 LIQU.D ETTLUENT WASTE TREATHENT SYSTEM 3.1 Description of the Liquid Radioactive Waste Treatment System (see Figure 3.1) 3.1.1 Reactor Coolant Train

a. Water Sources - (3) Reactor Coolant Bleed Tanks (RCBT)

(1) Reactor Coolant Drain Tank (RCDT)

b. Liquid Processing - Reactor Coolant Waste Evaporator (see Figure 3.2)

- Domineralizers prior to release

c. Liquid Effluent f or Release - (2) Waste Evaporator Condensate Storage Tanks (WECST)

d. Dilution - Mechanical Draft Cooling Tower (0-60k gpm)

- River Flow (2E7 gpm average) 3.1.2 Miscellaneous Waste Train

a. Water sources: - Auxiliary Building Sump

- Reactor Building Sump

- Miscellareous Waste Storage Tank

- Laundry Waste Storage Tank

- Neutraliter Mixing Tank

- Neutraliter Feed Tank

- Used Precoat Tank f - Berated Water Tank Tunnel Sump

- Heat Exchanger Vault Sump

- Tendon Access Galley Sump

- Spent Fuel Pool Roma Sump

b. Liquid Processing - Miscellaneous Waste Evaporator, MWE (see Figure 3.2)

- Domineralisere prior to release

c. Liquid Effluent for Release - (2) Waste Evaporator Condensate Storage Tanks (WECST)

d. Dilution - Mechanical Draf t Cooling Towers, MDCT (0-60k gpm)

- River Flow (2E7 gpm average) 3.2 operability The Liquid Waste Treatment System as described in Section 11 of the Final Saf ety Analysis Report la considered to be operable when one of each of the following pieces of equipment is available to perform its intended functions a) Miscellaneous Waste Evaporator (WpL-gls) or Reactor coolant Evaporator (WDL-21A)

I-19 2098c

i TH! Radiological Controls Departmental Procedure 6610-PLN-4200.01 l Revision No.

l Title 0

Offsite Dese calculation Manual ~(ODcM) b) Waste Evaporator Condensate Domineraliser (WDL-K3 A or B) c) Waste Evaporator Condenette Storage Tank (WDL-T 11 A or B) d) Evaporator Condensate Pumps (WDL-p 24 A or B)

L 3.3 Representative Samplino Prior to Discharge

' All liquid releases from the Liquid Waste Treatment System are made through.

the Waste Evaporator Condensate Storage Tanks. .To provide thorough mixing l and a representative sample, the contents of the tank are recirculated using-one of the Waste Evaporator Condensate Transfer Pumps.

i 1

i r

I 1

l l-20 209hc.

. - - , . . . - - _ = _ . - - . . - - - . --_..-.;, ...- . . . - . - , . . - . - . .

TMI Radiological Controls Departmental Proceduce 6610-PLN*4200.01___

Revision No.

__ 76tle 0

Offrite Deee calculation Manuni (ODcM) r!OURE 3.1 LlCt,'lO R AOW ASTE

' '" I Alat?O8 ' lien G tons ("" 3,' g

'6">e- ,,,,t..,, , .t..... , ,,

'8 I

Wilf448 , f ! . P98V

-

W'lfitL&400U8 '

l #v"FE L&8f71volvil

' AUItitt IWup le 54 Anal Y Y YY Y ]

i i i l 6

I T TT T T T wilt wasti l +

alilllt i At84880 at tLisp !

tt 4 tr 3 f_l gg g l >

t, litteet il I l-4'lt WA871 at tasastiaavutt OO gg yg ggggg,eas,ti C ,, T O O W I T T I " "

"N ttitut gatige fittle pluie 11 Of !! 11 Of !)

T Y asses marts as warn ITM fvM

]

+ T I

t v

$8488staans pagM _ 6gg __ Rttwares tesWC I rTemasis '

inaal - we et il SP 11 11 af Il I i t08889?nafg8 gggggagig 44884tf1 mesvus N#'I P9#PS T t h l

..,, . , . tl..

lausspitatige DOWEBSTMAaB #5.Vl '

1880tu

(

teattesatt

$4mie maalth thMT watts typ i Il Of !)

t ael t Ia e t04Of tEatt pp gg 870 AA44 ft i "

N "', IIII Alta ett'

ff tR&48 ft O @ tenggggatt PWmP1 I-21 2098c

t l e I

i l

""- r l

l Muclear THI Radiological Controls 6610-PLN-4200.01

' Departmental Procedure Revision No.

Title 0

Offsite Dose Calculation Manual (ODCM) l

! FIGURE 3.2 O .. euere L40U80 W A$if f VAPORATORS m me.iais ein..

min g

ousee e.use, e

+-

un.iaai sio ne , **

[ 4'M s es ai mi

}

N* + 8 ,.=t**.s,

[4 gN- g% g q , ,_

o .,., . . .

. .-- OH =** * *

OH ....... . .,..

ii w inne ir ir 1,

' I - 44u

- - - "***'"' l' '**

saw .U!! 4 g% -

c t

===== (,:, W. x

' -)

t

' e l P anP

.u .

I-22 2098c

TMI Radiological Controls Departmental Procedure 6610=PLN-4200.01 Revision No.

T&tle O

{ Offsite Dese Calculation Manual (ODCH) l 4.0 CASE 00S EFTLUENT HONITORING SET POINTS 4.1 Noble Gas Monitors The gaseous ef fluent monitor set pointa are established for each gaseous ef fluent radiation mNeito- to assure concentrations of radionuclidesTe.ble in 4.1 gaseous affluents do not exceed the limits set forth in 10 CFR 20.

and Figures 4.1, 4.2, 4.3, 4.4 list Caseous Effluent Release Points and their associated parameters and a caseous Effluent Release Pathway Diagram, l

respectively.

I The set points are established to satisfy the more restrictive set point concentration in the f ollowing two equationst (eq 4.1.1) 600 > E (c3 )(F)(K )(Dv) 3 i

and (eq 4.1.2) 3000 > E (c )(L3+ 1.1 M )(Dv)(F) 3 3 i

W.o re c3 = set point concentration, in pC1/cc F = gaseous ef fluent flowrate at the monitor, in ec/ sac (Table 4.1) 3 K3 = total body dose factor, in mrom/yr per pci/m from Table 4.2 Dv = highest sector annual average atmospheric dispersion f actor (X/Q) at the unrestricted area boundary, in sec/m , from Table 4.3 for 3 station vent releases and Table 4.4 f or all other releases, (Condenser off gas, ESF THB, and ground releases). Maximum values presently used are 4.19E-7 sec/m3 at sector SE for station vent, and 1.16E 5 sec/m3 at sectors N and WNW for all other releases.

L3 = skin dose factor due to beta emissions from radionuclide i, in mram/yr per pci/m from Table 4.2.

3 M3=

air dose f actor due to gamma emissions f rom radionuclide i, in j

mrad /yr per pCi/m 3 from Table 4(2.

i 1.1 = mrom skin dose per mrad air dose.

500 = annual whole body dose limit for unrestricted areas, in mrom/yr.-

3000 = annual skin dose limit-for unrestricted areas, in mrom/yr The set point concrantration is further reduced such that the concentration contributions from multiple release points would not combine to exceed 10 CFR 20 limite I-23 2098c

l TH! Radiological Controls Departmental Procedure 6610-PLN-4200.01 1 Revision No,

,' Title i 0 j offsite Do,se calculation Manual (oocM)

The est point concentration is converted to set point scale units on each radiation monitor using appropriate calibration factors.

1 This section of the ODCM is implemented by the Radiation Monitor System set Points procedure and the procedure for Releasing Radioactive Gaseous Waste, J

j y 4.2 Particulate and Radiolodine Monitort i

ses pointo f or monitors which detect radionuclides other than noble gases are

! albo established to assure that concentrations of these radionuclides in gaseous effluents do not exceed the limits in 10 CTR 20.

set points are established so as to satisfy the following equations 1

(eg 4.2) 1500 > E (e )(r)(P )(Dv) g g i

where:

c = set point concentration, in pC1/cc F = gaseous ef fluent flow rate at the monitor, in ec/sec (Table 4.1) 3 j Pg a pathway dose parameter, in mrom/yr per pCi/m for the inhalation j pathway from Table 4.5. The dose factors are based on the actual individual organ and most restrictive age group (infant). References i NUREG-0133 5.2.1.

1 ..................... ................................................... ..

j l NOTE: Appendix A contains Pg calculational methodoiogy. ........... ...

l

) 1500 = annual dose limit to any organ from particulates .nd radiciodines and radionuclides (other than nobio gases) with half lives greater than eight days.

i Dv = the annual average atmospheric dispersion factor for the worst-case sector; maximum X/Q, in sec/in , for the inhalation pathway at the 3

unrestricted area. Dispersion factors may be read or interpolated f rom Table 4.3 for releases f rom the station vent and Table 4.4 for all other releases. Maximum values of X/Q presently used are 4.192-7 sec/m3 for station vent, at sector SE, and 1.16E-5 sec/m3 for all other a

i. releases, at sectors N and WNW.

1 The set point concentration is further reduced such that concentration i contributions from multiple release points would not combine to exceed 10 CFR 20 limits.

~

i l

The set point concentration is converted to set _ point scale units on each radiation monitor usin7 appropriate calibration factors.

1 L

I-24 209Bc

-wni.,,. er 3n,w. - -e-cr mw<, . , - - - = . . - , - _ - - * , -----,-vmre v s.+ ,: w .rwv.,-m,,,,-m.,,w,,.-.r,-,.- -

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

TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

Title 0

Of f site Dese calculation Manual (ODCM)

This section of the ODCM is implemented by the Radiation Monitor Systems set Points procedure and the procedure for Releasing P4dioactive Gaseous Waste.

4.3 G,aaeous Ef fluent Release Points and Gaseous Radiation Monitor Data TMI-l has eight (8) required effluent gaseous radiation monitor $teseThese are gaseous RM-A4, RM-AS, RM-Al$, RM-A6, RM-A7, RM-AB, RM-A9 and RM-A14.

release points, radiation monitors, and sample points are shown in Table 4.1.

4.3.1 RM-A4/RM-A6 Fuel Handling and Auxiliary Building Exhaust RM-A4 is the particulate, radiciodine and gaseous radiation monitor for the THI-l Fuel Handling Building Ventilation (Eee Figurs 4.1 and 4.2). RM-A6 is the particulate, radiciodine, and gaseous radiation monitor f or the THI-l Auxiliary Building Ver.tilation (see 1.11 Figure 4.1). High alarms on RM-A4 or RM-A6 noble gas channeu:

initiate shutdown of the related building ventilation air supt system. These two radiation monitors concurrently will satisfy requirements for the Station Vent release point in place of RM-A8.

4.3.2 RM-A8 Station Venttiation Exhaust RM-A8 is the particulate, radiciodine and gaseous radiation monitor for the THI-l Station Ventilation (see Figure 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sample filters. High alarm on RM-A8 noble gas low channel will initiate- shutdown of the Station Ventilation air supply systems. (The Fuel Handling and Auxiliary Building ventilation). This radiation monitor satisfies requirements for *'- "tation Vent release point in place of.RM-A4 and RM-A6.

4.3.3 RM-A5/RM-A15 Condenser Of f Gas Exhaust RM-A5 is the gaseous radiation monitor for the TMI-l Condenser Of f Gas exhaust (see Figure 4.1 and 4.4) . RM-A15 is the back up gaseous radiation monitor for the TMI-l_ Condenser Off Gas exhaust (see Figura 4.1 and 4.4). High alarms on RM-A5 low channel or RM-A15 nable gas channet will initiate the KAP-5 Radioiodine Processor Station. Those two radiation monitors together satisfy requirements for the Condenser of f Gas release point.

4.3.4 RM-A7 Waste Gas Decay Tank Exhaust RM-A7 is the gaseous radiation monitor for the TMI-l Waste Gas Decay tanks ( see Figure 4.1 and 4.2 ) . This in plant effluent radiation monitor also has an associated sampling panol. High alarm on RM"A7 noble gas channel will initiate shutdown of- the Wtfte Gas Decay Tank release in progress. This radiation monitor sat.icfies requirements for batch gaseous releases to the Station Ver.t release point.

I-25 2098c

f THI Radiological Controls 6610-PLN-4200.01 Departmental Procedure Revision No.

T6tle 0

Of f site Dose._ Calculation Manual (ODCM) 4.3 t RM-A9 Reactor Building Purge Exhaust RN-A9 is the particulate, radiciodine and gaseous radiation monitor for the THI-1 Reactor Building Purge system (see Figure 4.1 and 4.3). 'his in plant effluent radiation monitor also has an assecteted sampling panel with sampling lines located before the ssm'de (ilters. High alarm on RM-A9 noble gas low channel will

(' in' tic;e shutdown of the Reactor Building Purge System. This radiation ect.itor satisfies requirements f or the Reactor Building Purgs system -eleaie point.

4.3.6 RM-A14 ESF FHB Ventilation System RM-A14 is the gaseous radiation monitor for the TMI-1 Emergency safeguards Features (ESF) Fuel Handling Building Exhaust system (soe figure 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sampler filtere. High alarm on RM-A14 noble gas channel will initiate shutdown of the ESF Fuel Handling Duilding Exhaust Sy s t*.m . This radiation monitor satisfies requirements for the ESF Fue, Hana:ing Building Exhaust System release point.

4.4 control of Gaseous Effluert Releases THI gaseous ef fluent combined releases are controlled (per Control 3.22.2.1) af effluent sampling and radiation monitor set points. These measures assure that releases f rom the various vents do not combine to produce dose rates at the site boundary exceeding the most restrictive of 500 mrom per year to the i

I total body or 3000 mrem per year to the skin, and 1500 mrem per year to the thyroid. This is done by restricting simultaneous releases and by limitingThe the dose rates that may be c",atributed .by the various vents at any time.

various vent radiation monitor set points are each based on f ractions of the above limits and do not exceed the above limits when summed toget..er. These effluent radiation monitar cet points are calculated using the methodology described in equations 4.1.1, or 4.1.2 and 4.2. The actual met points are then listed in Reference 10.

The radioective content of each betch of ghaeous waste is determined prior to release b) sampling and analyses in accordance with Section II Table 4.22-2.

The results :

rL-release analyses are used with the calculational methods in 4.1 and 4.2 to .-'are that the dose rates at the site boundary are maintained below th( limits in control 3.22.2.1.

Post-release analyses of samples composited from batrh and continuous releases are performed in accordance-with Section II Table 4.22-2. The resulta of the analyses are used to assure that the dose rates at the site boundary are maintained within the limits of Control 3.22.2.1.

1-26 2098c

. n .. .

6610 FLN 4200.01 Ren elon 0 TAti2 4.1 GASEOUS R11EA82 POINT AND CASEOtts RADIATION MONIT0r. DATA (F)

RADIAT10p RADIAT10N DADIAT10N BELEAst ExuAurt MRITOR MONITOR TE m1 RATION GASSOU8 TW MONIMR CFM BaaJ171Y!TY SERSITIVITY SEN81TIVITY IFFER 2CR RADIATION GAB 3008 RELEASE (FLOW (CPM / KIN / sci /cc) (CPM / MIN / sci /cc) (CPM / sci /cc) (38/B0)

MDNIMR QM VALVES POINT RE DRDER) PARTICL*. ATE ICCINE (DITECTOR) LOCATION eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeesseesseeeeeeeeeeeeeeeeeeeeeee 0-50,000 1.30t10 1.2229 3.96E7 YES RM-A4 306' tievotion Fuel Band. AB*S 10 Aux 111ery aldg. Building (FR 149) (St.90) (1*131) (Re*133)

As D*120 Exhauet AR 0 121 AR D 121 .

I 0-100,000 1.30510 1.22E9 3.96t7 YE8 RM*A6 304' tievation Auxiliary AB.R 10 I'

Auxiliary 31dg. Sw11 ding (TR-MO) (4t*90) (1 131) (Xe.133)

Exhaust 0+150,000 1.30E9 3.6987 YE8 RM.A8 RMA*0/9 Sieg. Station 1.60E10 (1 131) (Ke.133) WDC-V47 maar SwST Vent (TR 161) (8r.90)

AH.E*10 tuhaust AR*E*11 Starte HAP S Radiciodine Sampler

.................................................................................................................... t 0 200 ....- ....- 4.00E7 T38 BM A5 322' tievation condanser of f Gas FR*1113 (Xe.133) Starte MAP.5 Second Floor Turbine 316g. Exhaust 4.7031 Radioindies (Er.tS) sampler BM*All 322' tievation condenser 0-200 ..... ..... 3.25E7 YES Second Ficer off Gas TR 1113 (xe.133) 8tarta MAP $

TutD10e 81dg. Exhaust 9.1111 - Radioicdine

( Ar OS) Saapier 306' Elevation wasta Gao 0 10 ~ .* ..... 4.0035 MS ;

BM-A7 !

Decay Tante TR 123 -(Es.133) WDC.v47 Aux 111 sty Bldg.

(A,3,C)

RMA*l/9 Blog. Reactor 0-150,000 1.00E10 1.4059 3.94E7 YES ;

BM A9 hear swST Building TR-909/ (Br.90) -(1 131)' -(Xe 133) AR-V 1A/3/C/D Purge TRa140 WD0 534/535-Exhaust -Starta NAP.5 Radiciodine sampler 0 1000 .~ 1.0587 NO BM-A14 331' tievation Ist Fuel ---

ESF FEB - Bandling TR 1104A/S (Xe.133) Manual outelde Chem. Building 4.2121 Actione Addition 51dg. Exhaust (Ar-8$)

1 27 2090c

_ _ . - _ . . . _ _ . . _ _ . _ _ . - .m _ _ . . . . ~ . . . ._ _ _._- ____ _.._ _,_..~..~.__._ m _ _ m, ....m.- -.m_-,

g .-

6610.PLN-4200.01:

hovision 0-TABLE 4.2 '

Dost FA"! ORS Fcet N00Lt GAats AND DAUGIrftR88 Gasma total Dody heta Gamma Air tota Air Skia Dooo Factor (b) Dose Factor Does factor Dose Factor (s) 81 K1 L1 M1 (arent/yr per #01/s3) (mren/yt ist #01/a3) (ared/yr per pC1/s3) (arad/yr por WC1/s3)

Radio.nuclide

- - _1.938*01- 2 048*02 Er 63e 7.668 02 " 1.97B603 4~

1 178*03 1.468*03 1.238*03 Kr=05e 1.723*01 1 968*03 Kr*85 1 61t*01 .1.348*03 6 173*03 1.038*04 Kr* 07 8.925*03 9.735803 1.523604 2.938403 Kr.Se 1.475*04 2 373*03 1.738*04 1.Mf *04 -

Etatt 1.665*04 1.01**04 1 638*04 7643J'03 _}

5:*90 . 1 648*04 7.298*03 1.545*02 1 %.11B+03 9.158*01 4.765*02 Ke-131s 3.273*02 1. 48if

05 Ka-133s 2.81B*02 9.948*02

3.838602 1.093*03 2.945802 3.068*02 Ea=133 3.368*03 7. %8*03 Ka 135e 3.125*03 7.113*02 1,9Js*03 -2.44s+03.

Xa 135 1.81E*03 1.068*03 1.618*03 1.2YS604 Re-137 1.428*03 1.238*04 4.138*03 9. 213 + 0.) 4.750'03 Ke 134 4.838+03

-9.30t*03 3 288403 Ar*41 8.84E*03 2.698*03 spose tectors are for ammersion exposure it, uniform meal 1 infinite cloud of moble gas radionue116es that any be setecte gaseous offluents. Dooo factor values are taxon f rom Dagulatory Guide 1.100, Table 31. CDOt haforence 2.

e*7.568 02 e 7.56 x 10~ 2 (a) Total body dose f actor for gemise penetration depth of 6 cm into the body.

(b) Skin dose f acw at a tissue depth or tissue denalty thickness of 7 ag/cs2 f

I .

1 2 28 2096c r

, , - . . _ _ . . -,. , . . . . .,1-_,_- ..m._...-...,...,..~,....,, , , . . . . . . . . . . , - . , ,y , d

-. _ +-r 6610 F1.M 4200.01 Rr:-'on 0 TABLE 4.3 ADOBPRERIO D18FER$10N FACTORS F09 TERIE K!!.I IRLAND C1STANL

STATION VENT SEASON - ANNUAL (IN METERS) 0 SECTOR AVERACE A/G (!N SEC/M )

40225 l 56315 72405 4022 l 5631 7240 12067 l 24135 850!DR 610 l 2413 1.883-09 1.098 09 N 1.18307l5.32807 2.955-07 1.93307f1.39301 5.523-04f1.91508l502309 4.778 09 1.983-09 9.695 10 NNE 1.70307l7.171-07 3.45t=07 2.005 07 1.393 07 5.58308f1.70508 1.85t 09 9.93140 NE 1.12807l1.7530? 3.262 P7 1.863 07 1.21E-07 l 5.00E 08 l 1678 08 4.673-09 1 428-08 4.423 09 1.593 09 8.643 10 INE 1.09807l2.13107 2.67t*07 1.538-07 1.052 07 l 4.312 04 4.638 08 1.523 08 5.19t*09 2.483-09 1.508-09 1.528 07 1.493 07 1.065-01 1 2.312-07 l 1.73 07 3.983 08 1.50E 08 5.923 09 2.828 09 1.933 09 2.501-07 1.488 07 9.483-06 ESE 3.50E07l2.12E07 4.823-08 1.815 08 6.84t+09 3.30t*09 2.223 09 82 4.193 0? 3.791 01 2.533-07 1.55E 07 1.118 07 5.023 08 1.988-08 6.978 09 2.943 09 1.703 09 2.903 07 3.62E 07 2.552-07 1.492 07 1.112-07 881 4.093 08 1.403 08 4.36t=09 1.991 09 1.042 09 8 1 873-07 6.473 00 2.163-07 1.303 94 8.65t*08 9.742 09 3.03 09 1.50t*09 8.238 10 88W 6.133-08l4.16508 1.56E 07 1.035 07 6.81t-08l2.72108 2.723 09 1.338 09 8.33840 SW 5.76804l1.14501 1.708-07 1.052-07 l 6.932 08 l 2.512 08 l 9.341-09 1.393 09 9.698 10 Wsw 8.52808l3.75507 2.148-07 1.262-07l1.74308 3.088408 1.022-08l3.281-09 5.231-08 1.722-08 5.063-09 1.988 09 1.252 09 W 1.158 07 l5.80807 2.882 07 1.63207f1.18307 5.683-08 1.953 08 6.323 09 2.162-09 1.345-09 3.30E*07 2.191 07 1.482-07 WNW 1.41507l6.283-07 5.673 00 2.063*08 5.903 09 2.70E 09 1.453 09 pW l1.42507 l5.67307 3.173 07 1.933-07l1.30307 1.802-07 1.272 07 5.201 08 1.773*00 4.823 09 2.013 09 l1.22309 NNW 1.005-07 5.778-07 3.181 07 DIITANCE

STATION VENT

8tcTOR AVERAGE C/Q (!N M ~) (IN METERS) SEASON

ANNUAI.

24135 40225 56315 72405 880108 l 610 2413 4022 5631 7240 l 12067 2.503-10 8.57541 2.518 11 4.988 12 1.573 12 7.848 13 N 2.511 09 8.72140 4.848-10 2.983 10 3.383-10 6.065-12 2.10542 8.89143 RWE l3.89309 1.98809l9.548-10 4.99340 1.108-10 l 2.89241 2.878-11 6.018 12 1.99E-12 9.233 13 NE 2.58309f6.708-10 9.132 10 4.91210l2.971-10l1.048-10 1.633 12 7.643-13 ENE 2.153-09 5.85t40l5.54510l3.06E10 2.081-10 l 8.30E41 l 2.328 11 5.412 12 3.77142 1.971 12 2 5.54809(1.238-09 6.175-10 4.598 10 3.63340 l 1.34510 l 3.66311 l 9.445-12 1.822-10 5.773 11 1.725 11 7.078 12 4.07242 ESE 9.173 09 2.058-09l1.51809 8.66340f5.13t40 8.30241 2.343*11 9.422 43 5.515 12 SE 1.228-08l2.88509 1.841-09 1.021 09 6.852-10 l 2.60140 4.495 10 1.87340 6.165 11 1.612-11 5.675-12 2.832 12 883 7.508-09k1.62309 1.083-09 5.89140 3.053 11 8.102 12 2.731-12 1.233-12 a 3.863 09 l 6.53240 6.275-10 3.595-10 2.32340 l 1.06E40 1.641 12 7.84343 SSW 1.135 09 2.9 4E 40 4.193-10 2.53340 1.568 10 l 5.38541 i 1.688*11 3.91E*12 5.24E41 1.653 11 3.623-12 1.492-12 8.123*13 SW l1.198-09l3.64340f4.968-10 2.802-10 l 1.70E 10 1.892-11 4.585-12 1.638 12 9.902 43 WSW 1.775-09 l 8.31840 6.491-10 3.50140 1.99310 f t 73841 W 2.412-09 1.293-09l6.83-10 3.658-10 l 2.96340 1.12240 3.11841 l 6.90E-12 2.265-12 i 1.252 12 1.29242 WNW l3.20109l1.393-09 7.73340 l 5.91240 3.66E 10 l 1.19210 l 3.432-11 8.36212 f 2.395-12 1.36t+12 NW l3.25309f1.233-09l7.395-10 4.221 10 2.77810 l 1.14310 7.28E 11 7.61242 l 2.92242 3.053-10 2.23E40 l 8.2311 l 2.4341 f 4.93E42 l 1.728-12 9.03143 NNW 1.988-09 ! 9.88340 l 5.71340 DATA FRCN 1/1/78 THOUGH 12/31/86 USED IN CALCULATIONS I-29 2098c

1

.

I 6610-PLN 4200.01 hovision 0 TABLE 4.4 ATNOSPEERfl' CitPTR$!ON FACTORS FOR TERIt KILE ISLAND e Oxxnro RELEAst 01stAN:s season - ANNUAL

' steton AvrpAct X/Q (In sic /M3) (2s MrTEns) 12067 24135 40225 l 56315 72405 610 2413 4022 5631 l 7240 stcTOR 2.383 01 9.748 08 3.453-08 9.283 09 3.523 09 2.053 09 N 1.168-05 1.132-06 943-07l3.8307 9.558 08 3.112-08 8.94E-09 3.143 09 1 6tt 09 NNE 1.08E-05 1 103 Of f 5.668 07 } 3.412 07 3.385-01 l

2.103-07 9.012 08 3.108 08 8.873 09 3.548 09 1.913 09 NI 7.028-06 9.013 C 7 5.423-07l3.178-07 1.978 07 7.82E-00 2.648 08 8.345 09 3.042 09 1.665-09 ENE 7.145 06 3 7 4.92E 07 2.858 07 1.873 07 8.403-08 2.823-08 9.853 09 4.755-09 2.872 09 I 8.493-06 1.093 06 5.482 07 2.918 07 1.67E-07 7.203 00 2.775-08 1.125-08 5.548 09 3.683-09 EEE 6.915-06 9.023 07 4.493 07 2.575 07 2.038-07 8.94E-08 3.333 08 1.282 08 6.195 09 4.183 09 85 6.705 06 9.068-07 4.53t=07l2.86207 2.08I 07 9.10bO8 3.728 08 1.312 08 5.623-09 3.263 09 SSE 7.262 06 9.252-07 4.915 07 2.878 07 1.613-07 7.312 00 2.57E-08 l 9.231 09 3.748 09 1.958-09 8 l8.70806 9.085-07 3.99507l2.412-07 1.243-07 5.063-08 1.828 08 5.71E 09 2.872 09 1.583 09 83W l6.053-06 7.012-07 2.73207l1.86507 1.813 07 1.228 4.50E 08 1.72E 08 5.123-09 2.533 09 1.593 09 SW l5.94306 5.712-07 2.865 07 1.878 08 6.12b o9 2.623-09 1.838 09 W5W 8.00b o6 7.021-01 l 3.605-07 l 2.155 07 1.34807l5.50 soft 3.023 07 3.153-08 9.483 09 3.Wbo9 2.382 09 W 1,02b 05 1.07b 06 5.303 07 2.05bC7 l 9.312-08 3.673 07 2.533 07 1.002-01 3.56b08 1.185 08 4.07D 09 2.548 09 WW 1.168-05 1.135 06 5.988 07 5.70b 07 3.538 07 2.403 07 1.022 07 3.823-08 1.110 04 5.143 09 2.788-09 NW 1.138 05 1.06E 06 5.728 07 3.273-07 2.222-07 9.06E 08 3.203 08 8.891-09 3.753-09 2.295-09 NNW 1.083 05 1.042 06

se0UND RK!. East 013TANCE 8tA80p ANNUAL

8501oR AVERADE 0/Q (!N M ~ 2) (IN METEBS) 5631 7240 12067 24135 40225 56315 72405 arczon 610 2413 4022 l 2.705 10 0.96b11 2.53241 4.98342 1.573 12 7.84E 13 N 2.305-08 1.885 09 8.938-10l4.82b10 1.10E 40 2.898-11 6.068-12 2.10b 12 8.89b13 NNE l2.663-08 3.258-09 1.065 09 l 5.42240 3.381-10 2.98540 1.045 10 2.883-11 6.01243 1.99E-12 9.233-13 NE l1.15308l2.003-09l1.01b09l5.04b10 8.573 11 2.33341 5.41242 1.638-12 7.64b13 Ew! 1.683 08 1.85b09 l 8.65b10 l 4.28240 l 2.65t40 3.67b 10 1.35E 40 3.68341 9.42E 42 3.77b 12 1.973-12 2 2.883-06 2.991-09 1.393-09l6.34b10 3.808 09 5.15840 1.83E-10 5.783-11 1.1341 7.063-12 4.06E42 ESE h359508 1.77809l8.79210 4.55b09 2.135 09 1.155-09 7.50J4 0 2.72b 10 8.31341 2.34341 9.425 12 5.50E 12 SR 4.125-08 3.23b 09 1.59b 09 8.00E 10 5.20E40 1.88b 10 6.188 11 1.61241 5.66E-12 2.83E 42 855 3.122 08 2.655 08 4.75E 40 2.86t40 1.07E 40 3.06b 11 8.10E42 2.738 12 1.232-12 8 2.21E-09l9.078-10

! 1.45bO8 1.300 09 4.80E-10 l 2.82b 10 1. 70b 10 5.71b 11 1.695 11 3.91242 1.64842 7.84U13 Osw 1.713 10 5.24E 41 1.65241 3.623-12 1.495 12 8.123-13 sw 1.423 08 1.10E-09 5.15E10l2.82L40 Wsw 2.018-08 1.415-09 6.82E40 3.54b 10 2.005 10 6.76b11 1.898-11 4.58242 1.638-12 9.903-13 W 2.55E 08 2.16E 09 1.002-09 4.913 10 3.01b 10 1.12340 3.111-11 6.90142 2.27b 12 1.25b12 2.888 08 2.305 09 3.671-10 1.193 40 3.43E 41 8.36242 2.39b12 1.29242 WNW 1.13E 09 l 5.93240 2.15bo9 3.411 10 1.19340 3.57E 11 7.61b 12 2.92b 12 1.36b 12 l WW 1.78b O8' 1.063-09l5.58b10 2.175 08 2.572 40 8.55E41 2.42E41 9n-12l1.72342 9.033 13 f Nw 1.75009l8.751-10l4.242-10 OATA FRCH 1/1/78 TDOUGH 12/31/86 USED IN CALCt." ATICES D30 2098c

- -. ~ - ,

l TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revielon No.

Title 0

Offsite Dose Calculation Manual (ODcM)

TABLE 4.5 DOSE FARAMETERS FOR RADIOIODINES AND RADIOACTIVE PARTICULATE IN GASEOUS EFFLUENTS *

........,a............................................a.====...........====........=......'

CRITICAL ORGAN CRITICAL ORGAN Pi***

NUCLIDE ORGAN FACTOR OKGAN FACTOR Pi***

NUCLIDE

...................................................................u..................

Ru-105 GI-LLI 3.46E-05 4.8E+04 H-3** TOTAL BODY 4.62E-07 6.5E+02 1.2E+07 2 6E+04 Ru-106 LUNG 8.26E-03 C-14 BONE 1.89E-05 2.62E-03 3.7E+06 1.1E+04 Ag-110M LUNG Na-24 TOTAL BODY 7.54E-06 LUNG 1.17E-03 1.6E+06 9.17E-06 1.3E+04 Sb-125 Cr-51 LUNG To-125H LUNG 3.157-04 4.5E+05 Mn-54 LUNG 7.14E-04 1.0E+06 3.4E+05 8.7E+04 Te-132 LUNG 2.433-04 Fe-55 LUNG 6.21E-05 1.5E+07 1.0E+06 I-131 THYROID 1.06E-02 Fe-59 LUNG 7.25E-04 1.21E-04 1.7E+05 Co-58 LUNG 5.55E-04 7.8E+05 I-132 . THYROID 4.5E+06 I-133 THYROID 2.54E-03 3.6E+06 Co-60 LUNG 3.22E-03 4.5E+04 2.42E-04 3.4E+05 1-134 THYROID 3.18E-05 Ni-63 BONE 4.97E-04 7.0E+05 En-65 LUNG 4.62E-04 6.5E+05 .I-135 TRYROID 2.0E+06 Co-134 LIVER 5.02E-04 7.0E+05 Sr-89 LUNG 1.45E-03 1.3E+05 2.92E-02 4.1E+07 Co-136 LIVER 9.61E-05 Sr-90 BONE LIVER 4.37E-04 6.1E+05 Y-90 LUNG 1.92E-04 2.7E+05 Cs-137 1.8E+06 Ba-140 LUNG 1.14E-03 1.6E+06 Zr-95 LUNG 1.25E-03. 1.7E+05 1.00E-04 1.4E+05 La-140 LUNG 1.20E-04 Er-97 GI-LLI 3.69E-04 5.2E+05 Nb-95 LUNG 3.42E-04 4.8E+05 Ce-141 LUNG 1.3E+05 Ce-144 LUNG 7.03E-03 9.8E+06 Mo-99 LUNG 9.63E-05 2.0E+03. ~Pr-144 GI-LLI 3.06E-06 4.3E+03 Tc-99M GI-LLI 1.45E-06 _

Ru-103 LUNG 3.94E-04 5.5E+05

The listed dose parametere are for radionuclides, other than noble gases that may be detected in gaseous effluents. Pi factore include all nonatmospheric pathway transport parameters, the receptor's usage of pathway media, and are based on the most restrictive age group (infant) critical organ, per Tech. Spec. 3.22.2.1.

Additional dose parameters for-nuclides not included in this Table may be calculated using the methodology described in NUREG-0133, (Reference 1).

- Tritium dose factors include an increase of 50% to account for the additional-amount of this nuclide absorbed through the skin.

- - mrem / year per pCi/m).

I-31 2098c

- . 'M N (+

TMI Radiologica'. Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

gggle 0

Offeite Dose Calculation Manual (ODCM)

FIGURE 4.1 TMI G%SEOUS EFFLUENT PATHWAYS H

$1 Af10m i( Actot V(bl K0G.PURG(

L..J i <

1%

l 74 Aulltl AA1 & IU(t -

'" ""' EAI'AII O.10 Ciu 40,000 (fu > s.t.acaua i

'.. NuA '. A

...,; NMA.

WDG1't 6 0 '

,,g,g "\

br.P E I.i$ l'"'I

'"'t~ut ___

___ mi If 120.000 Um 30.000 U" -

g , , y, '[

, g mu. -

EID

"""j.ooo cf. l aa*-

l fv(t MAAJLInG tutt0lmG "0'000 (IM stiUttInG rtoos b

4k (Cn0(n5(R Of f.6A$

5f ACE an, .

22 eMA.

', RNA. MA.

0" i ... . a malm l CCh0(Rit h y

0. }g u m J

I-32 2098c l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

TMI Radiological Controls Departmental Procedure 6610-PLN-4200.03 Revision No.

__ Title 0

Offsite Dose Calculation Manual (ODCM)

FIGURE 4.2 AUXILIARi AND FUEL HANDLING BUILDING EFTLUENT PATHWAYS p,yj man i4a t ur

$ Ik AB W j i

TC(i

!RM-A3! !

j vuM.* B000 CfM fL0V % ,

j / P A Cj ; 30 r((;,

j /\ d, l

! A MAP $

'N W o '\

' 0-10 CTH

,^\ .. $AR( M*Al4j V / (bNM'/

\ HAXlHUM 40.000 CfM v t

%/

I ? [SFfUEL m

' P A CjH

. A AUX 1UARY q - HANDUNG

? BUllDING 7cco trm mat rttv i i 7 1 I FUEL HANDUNG j Bl (6 cI AyCaO' du ff A

(# h BUILDING d -

l AUXlLIARY AND FUEL HANDLIN3 BUILDINGS EXHAUST RADIAll0N lll$[

C DEPA MONITORS AND SAMPUNG STAIl0NS I-33 2098c

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

i

~

THI Radiological Controls Departmental Procedure 6610-PLN-42OO.01 Revision No.

TLBle 0

Offsite Dose calculation Manual (ODCM)

FIGURE 4.3 REACTOR BUILDING EFFLUENT PATHWAY

'l m

90 >M-

FEET -j-l:

! Na :

REAC10R BUILDING PURGE EXHAUST l **A9 Hi>

RAD!AllDN MDNITORS AND

0 1 SAMPLlNG SIAil0NS Pa y /\ l 7 % /- se u

! sma i

!- PAR 11 1 10DM -l R[A[]QR can.N (P.g O BUILDING - D -

=

Y '

$l

-l - MAX 1HLH 50.00) -

(TM PtSCC ft0V 3

i 7;ggg;

RCAti? !;!LE

! $AftiZ SYli!Mi FARIKRAil/IElllVP I'

i 10DKACLI CAS P 3 FARIKRATE i

A ABS 1UTC C's (WDL I-34 2098c

TMI Radiological Controle Departenental Procedure 6610-PLN-4200.01 Revision No.

T6tle 0

Offeite Doce calculation Manual (ODCH)

FIGURE 4.4 CONDENSER OFF GAS EFTLUENT PATHWAY

aNrcu:ce arr GA: ::Atu l

^ CONDENSER CIF GAS

,,. O . as,'

1 cxHAUST ui.

j

-) v RAMATION MONITCRS AND CAMDLING STAT CN; j .

m ,

!g

',es

...., , /in't::" 1 ;

W v I

\v~

.. nam. isc .! !

p i

i

[ .... , 's,

,- m ,

I v' / ., \

i en (:mt ) p MAIN I ...., ) x / v

'v' l Y ,

s CONDENSER i n -

1 i

l o ': too cc. l CONtt= ta e.hi", y i

I-35 2098c

TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 ,

76tle Revision No.

Offsite Dose Calculation Manual (ODCM) 0 5.0 DOSE ASSESSP2NT (CASEOUS EFFLUENTS) 5.1 Gaseous Ef fluents - 10 CFR 20 Limits (Instantaneous Release Limits) 5.1.1 Noble Gases For noble gases, the following equations apply for total body and skin dose rate at the unrestricted area boundary: ,

5.1.1.1 Total Body Dose Rate = E (K ) x. (Dv) x (Q ) 3 (eq 5.1.1.1) 3 i

where Dose Rate g = instantaneous total body dose rate limit, at the site boundary, in prem/yr.

K3 = total body dose f actor due to gamma emissions for each identified noble gas radionuclide, in mrem /vr per pCL/m 3 from Table 4.2.

Dv = average annual dispersion value X/Q at the site boundary for worst case sector, in sec/m3 . Values are obtained from Table 4.3 for releases from station vent; and Table 4.4 for all others (condenser Off Gas, ESF FHB, and ground releases).

Maximum values presently in use are 4.19E-7 sec/m 3 at sector SE for station vent, and 1.16E-5 sec/m3 for all other releases, at sectors N and WNW.

Release rate of radionuclide, i, in mci /sec. Calculated Q3=

using the concentration of noble gas radionuclide, i, in pC1/cc, tLmes the release pathway flow rate, in ec/second.

I-36 2098c 1

THI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

Title O

Offeite Dose Calculation Manual (ODCM) 5.1.1.2 Skin (eq 5.1.1.2)

Dose Rate, = E (Lg+ 1.1 M ) X (Dv) X (Q )

g 3 l

i l

where:

Dose Ratea=

instantaneous mrom/ year skin dose rate limit, at the j

site boundary, in mrom/yr.

L3= skin dose factor due to beta emiselons for each 3 identified noble gas radionuclide, in mram/yr per pCi/m from Table 4.2.

Hg - air dose f actor due to gamma amissions for each 3 identified noble gas radionuclide, in mrad /yr per pCi/m from Table 4.2.

1.1 = mrem skin dose per mrad air dose. Converts air dose to skin dose.

Og = rnlease rate of radionuclide, 1, in pC1/sec. Calculated using the concentration of noble gas radionuclide, i, times the release pathway flow rate, in ec/second.

Dv = average annual dispersion value X/Q at the site boundary for worst case sector, in sec/m3 . Values are obtained f rom Table 4.3 for releases f rom station vent; and Table 4.4 f or all others (condenser Of f Gas, EST THB. and ground releases). Maximum values presently in use are 4.19E-7 sec/m3 at sector SE for station vent, and 1.16E-5 sec/m3 for all other releases, at sectors N and WNW..

5.1.2 Iodine-131, Iodine-133 Tritium and Radionuclides in Particulate Form, with Half Lives Greater than 8 Dayr For I-131, I-133, Tritium and Radionuclides in Particulate Form, with half lives greater than 8 days, the following equation applies:

(eq 5.1.2)

Dose Rateg , = E (P3 ) (Dv) (Q ) 3 i

where Dose Rateg , = mrem / year organ dose rate.

I-37 2098c

l l

""*b" H YUCIS8r THI Radiological controle 6610-PLN-4200.01 j

Departmental Procedure Ruvision No.

T6tle

', 0 ;

of f site Dese calculation Manual (CDCM) 1 l

Pg= dose parameter for I-131,1-133, Tritium and

-Radionuclides in Particulate Form, with half lives for the inhalation pathway, in greaterthan8da{o, The dose factors are mrem /yr per uci/m , from Table 4.5.

based on the critical individual organ and most ,

restrictive age group (infant).

Dv = the annual average atmospheric dispersion parameter, for the sirst-case sector, f or estimating the dose -to the 1

critical receptor; X/Q for the inhalation pathway, in sec/m3 . Dispersion f actors may be read or interpolated 4

from Table 4.3 for releases from the station vent and

~

Table 4.4 for all other releases. - 3Maximum values of X/Q presently used are 4.19E-7 3sec/m for station vent, at sector SE, and 1.16E-5 occ/m for all other releases, at t

sectors N and WNW.

Og =

release rate of each radionuclide,11, in pci/sec.

Calculated using the concentration of each radionuclide, 1, times the release pathway flow rate, in ec/second.

4 I

i i

l 1

I-38 2098c i

- y , . - - , . - - - - -~ v ~ , - . . , - . . - . , , - . . - -

TMI Radiolor ical Controls 6610-PLN-4200.01 Departmental Procedure Revision No.

--7ggy, 0

offsite Dose Calculation Manual (oDCM) 5.2 Gaseous Effluents - 10 crR 50 Appendix _I 5.2.1 Noble cases The air doce in an unrestricted area due to noble gases released in gaseous ef fluents f rom the site is determined using the following expressions (eq 5.2.1)

Dose r = (3.17E-8) x E (M ) x (Dv) x (01) 3 i

and (eq 5.2.2)

Dose B = (3.175-8) x E (N3 ) x (Dv) x (QL) i where Dose r = mrad gamma air dose due to gamma emissions from noble gas radionuclides.

Doce D = mrad bsta air dose due to beta emissione from noble gas radionuclides.

H3 = air dose f actor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pCi/m , f rom Table 4.2.

3 N3= air dose factor due to beta emissions for each identified noble gas.radionuclide, in mrad /yr per-pCi/m3 , f rom Table - 4.2.

Dv = the maximum annual average atmospheric dispersion factor, Q/X, for the worst-case sector, for any area at 3 or beyond the unrestricted area boundary, in sec/m .

Values may be read or interpolated from Table 4.3 for releases from the station vent end Table 4.4 for all other. releases. Maximum values of X/Q presently used are 4.19E-7 sec/m3 for station vent at sector SE, and 1.16E-5 sec/m3 for all other releases at sectors N or WNW.

Q2 = release of noble gas radionuclido, i, in pCL, over the specified time period, (pci/second a seconds).

3.17E-8 = inverse of the .nwdaar of seconde in a year.

NOTE: If the methodology in this section is used in determining l dose to an individual,.rather than air dose due to noble-g gases, substitute Ki, f rom Table 4.2, for Mi, and (Li +

l 1.1 M1) for N1.

1-39 2098c 1

I - , . . . . - - --. , - . - . . -- . . . . - .

THI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

Title 0

Offeite Dose Calculation Manual (ODCM) 5.2.2 Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form. with Half Lives oreater than 8 Days The dese to an individual from I-131, I-133, Tritium and Radionuclides in Particulate Form with half lives greater than 8 days in gaseous ef fluents released f rom the site to an unrestricted area is deter:.ined by solving the following expressions (eq 5.2.2)

Dose, = (3.175-8) x E (R ) (Dv) (Qg) i i

where Dose, = dose to all real pathways, p, to organ, o, of an individual in age group, a, from I-131, I-133, Tritium and Radionuclides in Particulate Form, with half lives greater than 8 days, in mrom, during any desired time period.

R3=

the dose factor for each identified radionualide, 1, pathway, p, age group, a, and organ, o, in mrom/yr per pC1/m for the inhalation pathway and m2 - mrom/yr per 3

pCi/sec for other pathways, from Tables 5.2 to 5.7.

NOTE: Since there le minimal or no elumental iodine releasud from the condenser off-gas air ejector (see NUREG-0017) all Iodine R values for all pathways, except the inhalation pathway, g

are considered to be acro when performing dose calculations for releassa from the condenser off-gas air ejector. Only calculate the dose due to the inhalation pathway for condsr.aer off-gas air ejector iodines.

NOTE: Tritium, H-3, dose factor le mrom/ year per pCi/m3 for all pathways.

Dv = the annual average atmospheric dispersion parameter, for i the worst-case sector, for estimating the dose to an individual at the critical location; X/Q, in sec/m 3 , for the inhalation pathway, and D/Q, in m 2, for other pathways. Maximum values of X/Q in sec/m3 for station vent and all other releases are 4.19E-7 and 1.16E-5 for sectore SE and N,' WNW respectively. Maximum values of D/Q in m 3 for station vent and all other releason are 1.22E-B and 4.12E-8 for sector SE.

I-40 2098c

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

- TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

Title 0

offsite Dose calculation Manual (CDCM)

Dv(H-3) =

In the case of H-3 only X/Q's are used for all pathways.

Dispersion f actors may be read or interpolated from Table 4.3 for station vent releases and Table 4.4 for all other releases.

release of I-131, I-133, Tritium and Radionuclides, i, Q3= it, Particulate Form with half lives greater than 8 days, in pci, cumulative over the specified time period (pCL/second

seconds).

3.17E-8 = inverse of the number of seconds in a year.

i r

I-41 2098c

TMI Radiological-Controls Departmental Procedure 6610-PLN-4200.Ol Revision No.

T6tle Om Offsite Dose Calculation Manual (ODCM) 5.3 Gaseous Radioactive System Dose Calculations Once per Month Gaseous Radwaste Treatment system Controle 3.22.2.4 requires that appropriate subsystem of the Gaseous Radwaste Treatriant System shall be used to reduce When the radioactive materials in gaseous waste prior to their discharge.

the monthly project ' d doses due to the gaseous ef fluent releases f rom the site would exceed:

0.2 mrad to air from gamma radiations or 0.4 mrad to air from beta radiation; or 0.3 mrem to any organ.

The following calculational method is provided for performing this dose projection.

At least once a calendar month the gamma air dose, beta air dose and the -

maximum organ dose for the month will be integrated. An estimated projected gamma air dose, beta air dose, and the maximum organ dose for the next month will be determined based on plant operation and the integrated dose for the previous month. If these estimated projected doses exceed any of the values listed above, appropriate portions of the Gaseous Waste Processing System shall be used to reduce radioactivity levels prior to release.

5.4 Alternative Calculational Methodologies for Gasecut Effluents As an alternative to the methods described above, the models in/or based ,

upon, those presented in Regulatory-Guide 1.109 (Rev.1) may be used to make a comprehensive dose assessment. Default parameter values from Regulatory Guide 1.109 (Rev. 1) and/or actual site specific data can be used where applicable. Dispersion parameter values for such analyses may be drawn from Table 4.3 and 4.4 or may be computed from site meteorological data for the specified time period using acceptable models such as those presented in Regulatory Guide 1.111, 4

I-42 2098c I

I - -

THI Radiological Controls Departmental Procedure 6610-PLN-4200.01

,,, Revision No.

Title 0

Offsite Dose Calculation Manual (CDCM)

TABLE 5.2.1 PATHWAY DOSE FACTORS, Ri AGE GROUP INFANT PATHWAY: INHALATION

-~~-----~~--------~~~--------------

~~ ---------------~~-~~--~~~---~~-~~/

ORGAN DOSE FACTORS; mremyear per pCi/m 3

~~-----------------

NUCLIDE ---------------------~~------

BONE LIVER --------------------

T. BODY THYROID KIDN EY LUNG GI-LLI 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 H-3 0.00E+00 6.47E+02 5.31E+03 5.31E+03 5,31E+03 5.31E+03 5.31E+03 5.31E+03 C-14 2.65E+04 1.92E+01 1.28E+04 3.57E+02 CR-51 0.00E+00 0.00E+00 8.95E+01 5.75E+01 4.98E+03 0.00E+00 4.98E+03 1.00E+06 7.06E+03 MN-54 0.00E+00 2.53E+04 1.09E+03 1.17E+04 3.33E+03 0.00E+00 0.00E+00 8.69E+04 FE-55 1.97E+04 1.02E+06 2.48E+04 FE-59 1.36E+04 2.35E+04 9.48E+03 0.00E+00 0.00E+00 .......

-. --- ....--- ---...........----... ---...---...........................n 1.22E+03 1.82E+03 0.00E+00 0.00E+00 7.77E+05 1.11E+04 CC-58 0.00E+00 4.51E+06 3.19E+04 CO-60 0.00E+00 8.02E+03 1.18E+04 0.00E+00 0.00E+00 2.04E+04 1.16E+04 0.00E+00 0.00E+00 2.09E+05 2.42E+03 NZ-63 3.39E+05 6.26E+04 3.11E+04 0.00E+00 3.2SE+04 6.47E+05 5.14E+04 ZN-65 1.93E+04 0.00E+00 3.04E+03 RB-86 0.00E+00 1.90E+05 E.82E+04 0.00E+00 0.00E+00 3.98E+05 0.00E+00 1.14E+04 0.00E+00 0.00E+00 2.03E+06 6.40E+04 SR-89 4.09E+07 0.00E+00 2.59E+06 0.00E+00 0.00E+00 1.12E+07 1.31E+05 SR-90 7.03E+04 Y-@l 5.88E+05 0.00E+00 1.57E+04 0.00E+00 0.00E+00 2.45E+06 1.15E+05 2.79E+04 2.03E+04 0.00E+00 3.11E+04 1.75E+06 2.17E+04 ER-95 1.57E+04 6 43E+03 3.78E+03 0.00E+00 4.72E+03 4.79E+05 1.27E+04 NB-95 1.61E+04 RU-103 2.02E+03 L.00E+00 6.79E+02 0.00E+00 4.24E+03 5.52E+05 RU-106 8.68E+04 0.00E+00 1.09E+04 0.00E+00 1.07E+05 1.16E+07 1.64E+05 AG-110M 9.98E+03 7.22E+03 5.00E+03 0.00E+00 1.09E+04 3.67E+06 3.30E+04 4.76E+03 1.99E+03 6.58E+02 1.62E+03 0.00E+00 4.47E+05 1.29E+04 TE-125M 2.73E+04 TE-127M 1.67E+04 6.90E+03 2.07E+03 4.87E+03 3.75E+04 1.31E+06 TE-129M 1.41E+04 6.09E+03 2.23E+03 5.47E+03 3.18E+04 1.68E+06 6.90E+04 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04- 0.00E+00 1.06E+03 Z-111 0.00E+00 2.16E+03 2-133 1.32E+04 1.922+04 5.60E+03 3.56E+06 2.24E+04 CS-134 3.96E+05 7.03E+05 7.45E+04 0.00E+00 1.90E+05 7.97E+04 1.33E+03 CS-136 4.83E+04 1.35E+05 S.29E+04 0.00E+00 5.64E+04 1.18E+04 1.43E+03 CS-137 5.49E+05 6.12E+05 4.55E+04 0.00E+00 1.72E+05 7.13E+04 1.33E+03 BA-140 5.60E+04 5.60E+01 2.90E+03 0.00E+00 1.34E+01 1.60E+06 3.84E+04 CE-141 2.77E+04 1.67E+04 1.99E+03 0.00E+00 5.2SE+03 5.17E+05 2.16E+04 CE-144 3.19E+06 1.21E+06 1.76E+05 0.00E+00 5.38E+05. 9.84E+06 1.48E+05 PR-143 1.40E+04 5.24E+03 6.99E+02 0.00E+00 1.97E+03 4.33E+05 3.72E+04 ND-147 7.94E+03 8.13E+03 5.00E+02 0.00E+00 3.15E+03 3.22E+05 -3.12E+04 I-43 2098c l

- . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ __]

THI Radiological controls Departmental Procedure 6610-PLN-4200.01 Revision No.

T6tle 0

Offnite Dese Calculation Manual (ODCM)

TABLE 5.2.2 PATHWAY DOSE FACTORS, Ri ADE GROUP CHILD PATHWAY: INHALATION 3

ORGAN DOSE FACTORS; mram/ year per pC1/m NUCLIDE -----------"-----------------------------~~----KIDNEY LIVER T. BODY THYROID LUNG GI-LLI DONE 1.12E+03 1.12E+03 1.12E+03 1.12E+03 ....--... 1.12E+03 H-3 0.00E+00 1.12E+03 6.73E+03 6.73E+03 3.59E+04 6.73E+03 6.73E+03 6.73E+03 6.73E+03 C-14 2.43E+01 1.70E+04 1.08E+03 CR-51 0.00E+00 0.00E+00 1.54E+02 8.55E+01 9.51E+03 0.00E+00 1.00E+04 1.58E+06 2.29E+04 KN-54 0.00E+00 4.29E+04 1.11E+05 2.87E+03 4.74E+04 2.52E+04 7.77E+03 0.00E+00 0.00E+00 FE-55 0.00E+00 1.27E+06 7.07E+04 PE-59 2.07E+04 3.34E+04 1.67E+04 0.00E+00

. . . . . . . . . . . . . . . . . . . . . . . . - - . . . . . . . . . - . . . . . . . . . - - - . . - - - . . - - - - - - . . - . . - - - - - - - - 3.44E+04 -------.

0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 CO-58 7.07E+06 9.62E+04 CO-60 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 4.63E+04 2.00E+04 0.00E+00 0.00E+00 2.75E+05 6.33E+03 NI-63 8.21E+05 ..---....--.--

1.13E+05 7.03E+04 0.00E+00 7.14E+04 9.95E+05 1.63E+04 SN-65 4.26E+04 7.99E+03 0.00E+00 1.9BE+05 1.14E+05 0.00E+00 0.00E+00 0.00E+00 RBo86 2.16E+06- 1.67E+05 SR-89 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 1.01E+08 0.00E+00 6.44E+06 0.00Et00 0.00E+00 1.48E+07 3.43E+05 SR-90 2.63E+06 1.84E+05 Y-91 9.14E+05 0.00E+00 2.44E+04 0.00E+00 0.00E+00 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04- 2.23E+06 6.11E+04 ER-95 2.35E+04 9.18E+03 6.55E+03 0.00E+00. 8.62E+03 6.14E+05 3.70E+04 ND-95 4.48E+04 RU-103 2.795+03 0.00E+00 1.07E+03 0.00E+00 7.03E+03 6.62E+05 1.36E+05 0.00E+00 1.69E+04 0.00E+00 1.84E+05 1.43E+07. 4.29E+05 RU-106 AG-110M 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 5.48E+06 1.00E+05 6.73E+03 2.33E+03 9.14E+02 1.92E+03 0.00E+00 4.77E+05 3.38E+04 TE-125M 1.4BE+06 7.14E+04 TE-127M 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04' 1.76E+06 1.82E+05 TE-129M 2.84E+03 2 131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00E+00 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38t+04 0.00E+00 5.48E+03

[ 2-133 CS-134 6.51E+05 1.01E+06 2.25E+05 0.00E+00 3.30E+05 1.21E+05 3.85E+03 CS-136 6.51E+04 1.71E+05 1.16E+05 0.00E+0C 9.55E+04 1.45E+04 4.18E+03

> CS-137 9.07E+05 8.25E+05 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 BA-140 7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.11E+01 1.74E+06 1.02E+05 CE.141 3.92E+04 1.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04 CE-144 6.77E+06 2.12E+06 3.61E+05 0.00E+00 1.17E+06 1.20E+07 3.89E+05 PR-143 1.85E+04 5.55E+03 9.14E+02 0.00E+00 3.00E+03 4.33E+05 9.73E+04 ND-147 1.08E+04 8.73E+03 6.01E+02 0.00E+00 4.81E+03 3.28E+05 8.21E+04 I-44 2098c l

f l

-- .l

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

TMI Radiological Controle Departmental Procedure 6610-PLN-4200.01 Revision No.

T6tle 0

Offaite Dose Calculation Manual (ODCM)

TABLE 5.2.3 ,

PATHWAY DOSE FACTORS.,Ri PATHWAY: INEALATION AGE GROUP: TEEN ._w..........--... ......... .... .

._.................... ................... 3 ORGAN DOSE FACTORS; mrem / year per pCL/m NUCLIDE --------------------------- -----------OID THYA KIDNEY LUNG OI-LLI BotTE LIVER T. BODY 1.27E+03 1.27E+03 1.27Et03 1.27E+03 H-3 0.00E+00 1.27E+03 1.27E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 C-14 2.60E+04 3.07E+01- 2.10E+04 3.00E+03-CR-51 C.00E+00 0.00E+00 1.35E+02 -7.50E+01 0.00E+00 1.27E+04 1.98E+06 6.68E+04 HN-54 0.00E+00 5.11E+04 8.40E+03 1.24E+05 6.39E+03 3.34E+04 2.3BE+04 5.54E+03 0.00E+00 0.00E+00 FE-55 0.00E+00 0.00E+00 1.53E+06 1.78E+05 1.59E+04 3.70E+04 1.43E+04 TE-59 2.07E+03 2.98E+03 0.00E+00 0.00E+00- 1.34E+06 9.52E+04 CO-58 0.00E+00 0.00E+00 8.72E+06 2.59E+05 CO-60 0.00E+00 1.51E+04 1.58E+04 0.00E+00 1.98E+04 0.00E+00 0.00E+00 3.07E+05 1.42E+04 N2-63 5.80E+05 4.34E+04 0.00E+00 8.64E+04 1.24E+06 4.66E+04 EN-65 3.86E+04 1.34E+05 6.24E+04 1.77E+04 1.90E+05 8.40E+04 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 0.00E+00 2.42E+06- 3.71E+05 SR-89 4.34E+05 0.00E+00 1.2SE+04 0.00E+00 6.68E+06 0.00E+00 0.00E+00 1.65E+07 7.65E+05 SR-90 1.08E+08 0.00E+00 2.94E+06 4.09E+05 Y-91 6.61E+05 0.00E+00 1.'77E+04 0.00Ee00 0.00E+00 3.15E+04 0.00E+00 6.74E+04 2.69E+06 1.49E+05 ER-95 1.46F-05 4.58E+04 5.66E+03 0.00E+00 1.00E+04 7.51E+05 9.68E+04 NB-95 1.86E+04 1.03E+04 1.09E+05 2.10E+03 0.00E+00 8.96E+02 0.00E+00 7.43E+03- 7.83E+05 RU-103 1.90E+05 1.61E+07 9.60E+05 RU-106 9.01E+04 0.00E+00 1.24E+04 0.00E+00 1.31E+04 7.99E+03 0.00E+00 2.50E+04 6.75E+06 2.73E+05 AC-110M 1.38E+04 5.36E+05' 7.50E+04 TE-125M 4.88E+03 2.24E+03 6.67E+02 1.40E+03 0.00E+00 8.16E+03 2.18E+03 4.38E+03 6.54E+D4 1.66E+06 1.59E+05 TF -127M 1.80E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 TE-129M 1.39E+04 0.00E+00 6.49E+03 T-131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 0.00E+00 1.03E+04 I-133 1.22E+04 1.13E+06 5.49E+05 0.00E+00 3.75E+05 1.46E+05 -9.76E+03 CS-134 5.02E+05 1.7BE+04 1.09E+04 CS-136 5.15E+04 1.94E+05 1.37E+05 0.00E+03 1.10E+05 8.48E+05 3.11E+05 0.00E+00 3.04E+05 1.21E+05 8.48E+03 CS-137 6.70E+05 6.70E+01 3.52E+03' O.00E+00 2.28E+01- 2.03E+06 2.29E+05 BA-140 5.47E+04 1.26E+05 CE-141- 2.84E+04 1.90R+04 2.17E+03 0.00E+00 8.88E+03 6.14E+05 2.02E+06 2.62E+05 0.00E+00 1.21E+06 1.34E+07 8.64E+05 CE-144 4.89E+06 1.34E+04 5.31E+03 6.62E+02 0.00E+00 3.09E+03 4.83E+05 2.14E+05 PR-143 5.02E+03 3.72E+05 1.82E+05 ND-147 7.86E+03 8.56E+03 5.13E+02 0.00E+00 t

l 2098c l

l I-45 l

l

. l THI Radiological Controls 6610-PLN-4200.01 Departmental Procedure Revision No.

Eitle 0

Offsite Dose Calculation Manual (ODCM)

TABLE 5.2.4 PATHWAY DOSE FACTORS, RL PATHWAY: INHALATION AGE OROUP: ADUs.T 3

ORGAN DOSE FACTORS; mrom/ year per pC1/m NUCLIDE .--.-.-.---..---.-. - --------------.----

T. BODY THYROID

..- KIDNEY LUNG OI-LLI BONE LIVER 1.26E+03 1.26E+03- 1.26E+03 1.26E+03 1.26E+03 1.26E+03 3.41E+03 H-3 0.00E+00 3.41E+03 3.41E+03 3.41E+03 C-14 1.82E+04 3.41E+03 3.41E+03 1.44E+04 3.32E+03 1.00E+02 5.95E+01 2.28E+01 0.00E+00 0.00E+00 CR-51 3.96E+04 6.30E+03 0.00E+00 9.84E+03 1.40E+06..- ----..-

7.74E+04 .

NN-54 0.00E+00 0.00E+00 0.00E+00 7.21E+04 6.03E+03 FE-95 2.46E+04 1.70E+04 3.94E+03 1.02E+06 1.88E+05 1.06E+04 0.00E+00 0.00E+00 1.18E+04 2.78E+04 ..-

FE-59 1.58E+03 2.07E+03 0.00E+00 0.00E+00 ........-.

9.28E+05 1.06E+05 Co-58 0.00E+00 0.00E+00 0.00E+00 5.97E+06 2.85E+05 Co-60 0.00E+00 1.15E+04 1.48E+04 .1.78E+05 1.34E+04 3.14E+04 1.45E+04 0.00E+00 0.00E+00 4.32E+05 NI-63 3.24E+04 1.03E+05 4.66E+04

............ 0.00E+00 6.90t+04 8.64E+05 5.34E+04 EN-65 0.00E+00 0.00E+00 0.00E+00 -1.66E+04 RB-86 0.00E+00 1.35E+05 5.90E+04 1.40E+06 3.50E+05 0.00E+00 8.72E+03 0.00E+00 0.00E+00 SR-89 3.04E+05 0.00E+00 0.00E+00 9.60E+06 7.22E+05 SR-90 9.92E+07 0.00E+00 6.10E+06 1.70E+06 3.85E+05 0.00E+00 1.24E+04 0.00E+00 0.00E+00 Y-91 4.62E+05 5.42:+04 1.77E+06 1.50E+05 1.07E+05 3.44E+04 2.33E+04 0.00E+00 ZR.95 0.00E+00 7.74E+03 5.05E+05 1.04E+05 NB-95 1.41E+04 7.82E+03 4.21E+03 5.05E+05 1.10E+05 1.53E+03 0.00E+00 6.58E+02 0.00E+00 5.83E+03 RU-103 0.00E+00 1.34E+05 9.36E+06 9.12E+05 RU-106 6.91E+04 0.00E+00 8.72E+03 0.00E+00 1.97E+04- 4.63E+06 3.02E+05 AG-110M 1.00E&04 1.00E+04 5.94E+03 -7.06E+04-4.67E+02 1.05E+03 1.24E+04- 3.14E+05 TE-125M 3.42E+03 1.58E+03 9.60E+05 1.50E+05 5.77E+03 1.57E+03 3.29E+03 '4.58E+04 TE-127M 1.26E+04 1.58E+03 3.44E+03 3.66E+04 1.16t+06- 3.83E+05' TE-129M 9.76E+03 4.67E+03 0.00E+00 6.28E+03 3.58E+04 2.05E+04 1.19E+07 6.13E+04 8-131 2.52E+04 2.58E204 0.00E+00 8.88E+03 8.64E+03 1.48E+04 4.52E+03 2.15E+06 I.533 0.00E+00 2.87E+05 9.76E+04 '1.04E+04 CS-134 3.73E+05 8.48E+05 7.28E+05 1.17E+04 1.10E+05 0.00E+00 8.56E+04 1.20E+04 CS-136 3.90E+04 1.46E+05 2.22E+05 7.52E+04 8.40E+03 4.78E+05 6.21E+0E 4.2BE+05 0.00E+00 CS-137 0.00E+00- 1.67E+01- 1.27E+06 2.18E+05 BA-140 3.90E+04 4.90E+01 2.57E+03 3.62E+05 1.20E+05 1.35E+04 1.53E+03 0.00E+00 6.26E+03 CE-141 1.99E+04 8.48E+05 7.7BE+06 U.16E+05 3.43E+06 1.43E+06 1.84E+05 0.00E+00 CE-144 0.00E+00 2.16E+03 2.81E+05- 2.00E+05 PR-143 9.36E+03 3.75E+03 4.64E+02 1.73E+05 3.65E+02 -0.00E+00 3.56E+03 2.21E+05 5.27E+03 6.10E+03 ND-147 I 2098c I-46

' THI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

T6Ble 0

Offeite Dose Calculation Manual (CDCM)

TABLE 5.3.1 PATHWAY DOSE FACTORS, Ri AGE GROUPI ALL PATHWAY: GRDUND PLANE -------

ORGAN DOSE FACTORS

l l --------------------

l NUCLIDE T. BODY SKIN l lH-3 0.00E+00 0.00E+00l C-14 0.00E+00 lCR-51 4.65E+06 -0.00E+00l 5.50E+06 l MN-54 ~1.39E+09 1.62E+09l FE-55 0.00E+00 l FE-59 2.73E+08 0.00E+00l 3.21C+08 lCO-58 3.79E+08 4.44E+0Bl CO-60 2.15E+10 2.53E+10 l NI-63 0.00E+00 0.00E+00l lEN-65 7.47E+08 8.59E+08l RB-86 8.97E+06 1.03E+07 lSR-89 2.16E+04 2.51E+04l t

lSR-90 0.00E+00 0.00E+00l 1.07E+06 lY-91 ER-95 2.45E+0B 1.21E+06l 2.84E+08 lNB-95 1.37E+0B .1.61E+08l 1'.08E+08 1.26E+08 lRU-103 RU-106 4.22E+08 5.06E+08'l lAG-110M 3.44E+09' 4.01E+09l 1.55E+06 2.13E+06 lTE-125M TE-127M 9.17E+04 1.08E+05l lTE-129M 1.98E+07 2.31E+07 l 1.72E+07 2.09E+07 lI-131 I-133 2.45E+06 2.98E+06l lCS-134 6.86E+09 8.00E+09 1.51E+08 l~CS-136 CS-137 1.03E+10 .1.1.20E+10 71E+08 ' ll' lBA-14C 2.06E+07 2.36E+07l CE-141 1.37E+07 1.54E+07 '

lCE-144 6.96E+07 8.05E+07 lPR-143 0.00E+00 0.00E+00ll ND-147 8.39E+06 1.01E+07

m2 - mrem / year per pC1/sec.

I-47 2098c

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

l

. l TMI Radiological Controle Departmental Procedure 6610-PLN-4200.01 Revision No.

T6tle 0

Offsite Dose Calculation Manual (ODCM)

TABLE 5.4.1 PATHWAY DOSE TACTORS, Ri ACE OROUP INFANT PATHWAY: ORASS-COW-MILK OROAN DOSE FACTORS; m3 - mrom/ year per pC1/sec NUCLIDE ~~----------~~------------------ - LUNG OI-LLI THYROID KIDNEY BONE LIVER T. BODY 2.38E+03 2.38E+03 2.3BE+03 2.38E+03 H-3 0.00E+00 2.38E+03 2.38E+03 5.00E+08 5.00E+08 5.00E+0B 5.00E+08 5.00E+08 5 00E+0B C-14 2 34E+09 1.05E+05 2.30E+04 2.05E+05 4.70E+06 CR-51 0.00E+00 0.00E+00 1.61E+05 0.00E+00 8.65E+06 0.00E+00 1.43E+07 MN-54 0.00E+00 3.91E+07 8.85E+06 4.27E+07 1.11E+07 8.74E+07 2.34E+07 0.00E+00 0.00E+00 TE-55 1.35E+08 0.00E+00 1.16E+08 1.8BE+0B FE-09 2.25E+08 3.93E+0B 1.55E+0B 0.00E+00

.---------------------------.........- 6.06E+07

~~-------------

0.00E+00 0.00E+00 0.00E+00 6.05E+07 Co-58 0.00E+00 2.43E+07 0.00E+00 2.10E+08 0.00E+00 8.83E+07 2.0BE+08 0.00E+00 0.00E+00 CO-60 0.00E+00 0.00E+00 0.00E+00 1.08E+08 N8-63 3.50E+10 2.16E+09 1.21E+09 0.00E+00 9.24E+09 0.00E+00 1.61E+10 ZN-65 5.56E+09 1.91E+10 8.79E+09 5.70E+0B 2.23E+10 1.10E+10 0.00E+00- 0.00E+00 0.00E+00 RB-86 0.00E+00 0.00E+00 0.00E+00 2.59E+08 SR-89 1.26E+10 0.00E+00 3.62E+08 0.00E+00 3.10E+10 0.00E+00 0.00E+00 0.00E+00 1.52E+09 SR-90 1.22E+11 0.00E+00 5.26E+06 7.34E+04 0.00E+00 1.95E+03 0.00E+00 0.00E+00 0.00E+00 Y-91 0.00E+00 1.79E+03 0.00E+00 8.27E+05 ZR-95 6.81E+03 1.66E+03 1.18E+03 2.45E+05 1.41E+05 0.00E+00 1.75E+05 0.00E+00 2.07E+08 NB-95 5.94E+05 0.00E+00 1 06E+05 RU-103 8.68E+03 0.00E+00 2.90E+03 0.00E+00 1.81E+04 0.00E+00 2.38E+04 0.00E+00 2.25E+05 0.00E+00 3.45E+06 RU-106 1.91E+05 2.82E+08 1.87E+08 0.00E+00 4.03E+08 0.00E+00 1.46E+10 AG-110M 3.86E+08 7.19E+07 1.51E+08 5.05E+07 2.04E+07 5.08E+07 0.00E+00 0.00E+00 TE-125M 1.04E+09 0.00E+00 =1.70E+08 TE-127M 4.22E+08 1.40E+08 5.10E+07 1.22E+08 1.91E+08 8.59E+07 2.14E+08 1.39E+09 0.00E+00- 3.33E+08 TE-129M 5.5BE+0B 1.15E+08 2.72E+09 3.21E+09 1.41E+09 1.05E+12 3.75E+09 0.00E+00 Z-131 9.62E+09 6.22E+07 0.00E+00 B.96E+06 I-133 3.63E+07 5.29E+07 1.55E+07 6.81E+10 6.88E+09 0.00E+00 1.75E+10 7.19E+09 1.85E+08 CS-134 3.65E+10 8.85E+07 1.98E+09 5.83E+09 2.18E+09 0.00E+00 2.32E+09 4.75E+08 CS-136 1.62E+10 6.55E+09 1.89E+08 CS-137 5.15E+10 6.03E+10 4.27E+09 0.00E+00 2.42E+05 1.2SE+07 0.00E+00 5. '. 3E+04 1.49E+05 5.94E+07 BA-140 2.42E+0B 1.372+07

-CE-141 4.34E+04 2.65E+04 3.12E+03 0.00E+00 8.17E+03 0.00E+00 9.53E+05 1.30E+05 0.00E+00 3.85E+05 0.00E+00 1.34E+08 CE-144 2.33E+06 5.56E+02 7.37E+01 0.00E+00 2.07E+02 0.00E+00 7.84E+05 PR-143 1.49E+03 5.75E+05 8.83E+02 9.07E+02 5.55E+01 0.00E+00 3.50E+02 0.00E+00 ND-147

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

I-48 2098c n - w y ,..m, w,, m - - . , - - -w-g,-a.- , ,, -mw-, ,

r-

TMI Radiolo91 cal Controle Departmental Procedure __ 6610-PLN-4200.01 Revision No.

Title 0

Ofteito Dose Calculation Manual (ODCM)

TABLE 5.4.2 PATHWAY DOSE FACTORS, Ri AGE OROUP: Cl!ILD PATHWAY: ORASS-COW-MILK ORGAN DOSE FACTORS) m - mrom/ year per pCJ /see 2

NUCLIDE -----~~.----.---..-----...-.-.-------------.----------.-----'~-..--------

THYROID KIDNEY LUNG CI-LLI LIVER T. BODY BONE 1.57E+03 1.57E+03 1.57t+03 1.57E+03 1.57E+03 1.57E+03 H-3 0.00E+00 2.39E+08 2.39E+08 2.39E+08 C-14 1.20E+09 2.39E+08 2.39E+0B 2.39E+08 5.65E+04 1.54E+04 1.03E+05 5.40E+06 0.00E+00 0.00E+00 1.02E+05 CR-51 5.59E+06 0.00E+00 5.89E+06 0.00E+00 1.76E+07 HN-54 0.00E+00 2.10E+07 3.36E+07 1.10E+07 1.12E+0B 5.94E+07 1.84E+07 0.00E+00 0.00E+00 FE-55 0.00E+00 5.65E+07 2.03E+08 1.20E+08 1.95E+08 9.70E+07 0.00E+00 FE-59 1.21E+07 3.72E+07 0,00E+00 0.00E+00 0.00E+00 7.08E+07 CO-58 0.00E+00 0.00E+00 0.00E+00 2.39E+08 Co-60 0.00E+00 4.32E+07 1.27E+08 0.00E+00 1.01E+09 0.00E+00 0.00E+00 0.00E+00 1.07E+08 NI-63 2.97E+10 1.59E+09

..................-~... ........-.................--

1.10E+10 6.86E+09 0.00E+00 6.95E+09

-- 0.00E+00 1.94E+09 EN-65 4.14E+09 0.00E+00 5.65E+08 RD-86 0.00E+00 8.78E+09 5.40E+09 0.00E+00 0.00E+00 0.00E+00 1.89E+0B 0.00E+00 0.00E+00 0.00E+00 2.57E+08

. SR-89 6.63E+09 0.00E+00 2.84E+10 0.00E+00 0.00E+00 0.00E+00 1.51E+09 SR-90 1.12E+11 5.21E+06 3.91E+04 0.00E+00 1.05E+03 0.00E+00 0.00E+00 0.00E+00 Y-91 1.21E+03 0.00E+00 8.802+05 ER-95 3.84E+03 8.43E+02 7.51E+02. 0.00E+00 3.18E+05 1.24F&05 0.86E+04 0.00E+00 1.16E+05 0.00E+00 2.29E+08 N8-95 0.00E+00 1.11E+05 RU-103 4.29E+03 0.00E+00 1.65E+03 0.00E+00 1.08E+04 9.25E+04 0.00E+00 1.15E+04 0.00E+00 1.25E+05 0.00E+00 1.44E+06 RU-106 2.09E+08 1.41E+08 1.13E+08 0.00E+00 2.63E+08 0.00E+00 1.68E+10 AG-110M 0.00E+00 7.13E+07-TE-125M 7.39E+07 2.00E+07 9.85E+06 2.07E+07 0.00E+00 2.08E+08 5.61E+07 2.47E+07 4.98E+07 5.94E+0B 0.00E+00 1.69E+08 TE-127M 2.72E+0B 7.59E+07 4.22E+07 8.76E+07 7.98E+08 0.00E+00 3.31E+08 TE-129H 0.00E+00 1.17E+08 I-131 1.31E+09 1.31E+09 7.46E+08 4.34E+11 2.16E+09 1.72E+07 2.13E+07 8.05E+06 3.95E+09 3.55E+07 0.00E+00 8.58E+06 8-133 2.27E+10 3.72E+10 7.85E+09 0.00E+00 1.15E+10 .4.14E+09 2.01E+08 CS-134 9.80E+07 CS-136 1.01E+09 2.79E+09 1.80E+09 0.00E+00 1.49E+0' 2.21E+08 3.23E+10 3.09E+10 4.56E+09 0.00E+00 1.01E+10 3.62E+09 1.93E+08-CS-137 1.18E+08 1.03E+05 6.86E+06 0.00E+00 3.35E+04 6.14E+04 5.96E+07 BA-140 0.00E+00 1.36E+07 CE-141 2.19E+04 1.09E+04 1.62E+03 0.00E+00 4.79E+03 1.63E+06 5.09E+05 8.67E+04 0.00E+00 2.82E+05 0.00E+00 1.33E+08 CE-144 7.18E+02 2.16E+02 3.56E+01 0.00E+00 1.17E+02 0.00E+00 7.75E+05 PR-143 0.00E+00 5.71E+05 ND-147 4.45E+02 3.61E+02 2.79E+01 0.00E+00 1.98E+02 I-49 2098c

TMI Radiological Controls Departmental Procedure. 6610-PLN-4200.01 Revision No.

Title 0

Offsite Dose Calculation Manual (ODCM)

TABLE 5.4.3 ,

PATHWAY DOSE FACTORS, Ri ACE GROUPe TEEN PATHWAY : GRASS-COW-MILK ORGAN DOSE FACTORS; 8 m - mrom/ year per pCi/sec NUCLIDE -----------------------------------------D BONE LIVER T. BODY THYROI KIDNEY LUNG GI-LLI i

9.93E+02 9.93E+02 9.93E+02 9.93E+02 H-3 0.00E+00 9.93E+02 9.93E+02 9.73R+07 9.73E+07 9.73E+07 9.73E+07 9.73E+07 C-84 4.86E+08 9.73E+07 1.09E+04 7.13E+04 8.39t+06 CR-51 0.00E+00 0.00E+00 4.99E+04 2.77E+04 2.7BE+06 0.00E+00 4.19E+06 0.00E+00 2.8FJ+2' MN-54 0.00E+00 1.40E+07 2.01E+07 1.?/E+09 4.46E+07 3.16E+07 7.37E+06 0.00E+00 0.00E+00 FE-55 0.00E+00 3.82E+07- 2. LM +fJ FE-59 b.19E+07 1.21E+08 4.68E+07 0.00E+00 7.94E+06 1 83E+07 0.00E+00- 0.00E+00 0.00E+00 1. JOE +08 Co-58 0.00E+00 0.00E+00 0.00E+00 3.(2E+CV C0-60 0.00E+00 2.78E+07 6.27E+07 0.00E+00 4.01E+08 0.00E+00 0.00E+00 0.00E+00 1.34E+08 NZ-63 1.18E+10 8.36E+08 .. .

' 3.42E+09 0.00E+00 4.69E+09 0.00E+00 3.10E+09 ZN-65 2.11E+09 7.32E+09 0.00E+00 7.00E+0B 0.00E+00 4.73E+09 2.22E+09 0.00E+00 0.00E+00 RB-86 0.00E+00 0.00E+00 3.19E+0B SR-89 2.68E+09 0.00E+00 7.67E+07. 0.00E+00 -.... ......

1.63E+10 0.00E+00 0.00E+00 0.00E+00 1.86E+09 SR-90 6.62E+10 0.00E+00 6.4BE+06 0.00Ev00 4.24E+02 0.00E+00 0.00E+00 0.00E+00 Y-91 1.5BE+04 0.00E+00 1.20E+06 ER-95 1.65E+03 5.21E+02 .3.58E+02 0.00E+00 7.65E+02 ..

.---..- .-.... ~.-.

7.32E+04 4.30E+04 0.00E+00 7.5BE+04 0.00E+00 3.34E+08 NB-95 1.41E+05 0.00E+00 1.51E+05 RU-103 1.81E+03 0.00E+00 7.75E+02 0.00E+00 6.39E+03 0.00E+00 4.73E+03 0.00E+00 7.24E+04 0.00E+00 1.80E+06 RU-106 3.76E+04 .

4 9.12E+07 5.55E+07 0.00E+00 1.74E+08 0.00E+00 2.56E+10 AG-110M 9.64E+07 8.87E+07 3.01E+07 1.08E+07 4.02E+06 8.40E+06 0.00E+00 0.00E+00 TE-125M 3.42E+08 0.00E+00 2.11E+08 TE-127H 8.45E+07 3.00E+07 1.00E+07 2.01E+07 1.10E+08 4.09E+07- 1.74E+07 3.56E+07 4.61E+08- 0.00E+00 4.14E+08 TE-129M 0.00E+00 1.49E+0B I-131 5.38E+08 7.53E+08 4.05E+08 2.20E+11 1.30E+09 7.08E+06 1.20E+07 3.66E+06 1.68E+09- 2.11E+07 0.00E+00 9.09E+06 I-133 9 2.31E+10 1.07E+10 0.00E+00 7.35E+09 2.81E+09 2.88E+08 C3-134 1.52E+08 1.42E+08-Cs-136 J .77E+09 1.19E+09 0.00E+00 9.63E+08

,,78E+10 6.21E+09 0.00E+00 6.06E+09 2.36E+09 2.54E+08 CS-137 f 5.97E+04 3.14E+06 0.00E+00 2.02E+04 4.01E+04 7.51E+07 BA-140 0.00E+00 1.70E+07 CE-141 5.94E+03 6.82E+02 0.00E+00 2.80E+03 2.73E+05 3.54E+04 0.00E+00 1.63E+05 0.00E+00 1.66E+08 CE-144 1.16E+02 1.44E+01 0.00E+00 6.73E+01 0.00E+00 9.55E+05 PR-143 2.90Et.J 0.00E+00 7.12E+05 ND-147 1.81E+02 1.97E+02 1.18E+01 0.00E+00 1.16E+02 I-50 2098c

THI Radiological Controls Dopartmental Procedure 6610-PLN-4200.01 Revision No.

Title 0

Offsite Dore Calculation Manual (ODCM)

TABLE 5.4.4 PATHWAY DOSE FACTOR $, Ri ACE GROUP: ADUL" PATHWAY: GRASS-COW-MILK .

CRGAN DOSE FACTORSI m2 - mram/ year per pCi/sec

~~-----

NUCLIDE ----------------------~~-----------------------KIDNEY T. BODY THYROID LUNG OI-LLI BONE LIVER 7.62E+02 7.62E+02 7.62'E+C2 7.62E+02 H-3 0.00E+00 7.62E+02 7.62E+02 5.26t+07 5.26E+07 5.26E+07 5.26E+07 5.26E+07 C-14 2.63E+08 5.26E+07 3.78E+04' 7.17E+06 0.00E+00 2.85E+04 1.70E+04 6.28E+03 CR-51 0.00E+00 0.00E+00 2.50E+r6 0.00E+00 2.57E+07 MN-54 0.00E+00 8.40E+06 1.50E+06 9.93E+06 4.04E+06 0.00E+00 0.00E+00 9.66E+06 g FE-55 2.51E+07 1.73E+07 1.95E+07 2.32E+08 q 2.97E+07 6.97E+07 2.67E+07 0.00E+00 0.00E+00 FE-59 1.05E+07 0.00E+00 0.00E+00 0.00E+00 9.54E+07 Co-58 0.00E+00 4.71E+06 0.00E+00 3.08E+08 Co-60 0.00E+00 1.64E+07 3.61E+07 0.00E+00 0.00E+00 2.25E+0B 0.00E+00 0.00E+00 0.00E+00 9.71E+07 N2-63 6.72E+09 4.65E+08

- - . - - - - - . . . . . . - - - - - - - . . . . . - - . . . - - - . - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - 2.74E+09 4.36E+09 1.97E+09 0.00E+00 2.91E+09 0.00E+00 ZN-65 1.37E+09 0.00E+00 5.10E+08 RB-86 0.00E+00 2.59E+09 1.21E+09 0.00E+00 0.00E+00 0.00E+00 4.16E+07 0.00E+00 0.00E+00 0.00E+00 2.32E+08 SR-09 1.45E+09 0.00E+00 1.15E+10 0.00E+00 0.00E+00 0.00E+00 _1.35E+09 3 SR-90 4.67E+10 0.00E+00 4.722+06 Y-91 8 57E+03 0.00E+00 2.22E+02 0.00E+00 0.00E+00 2.04E+02 0.00E+00 4. '. 4E +02 0.00E+00 9.57E+05 2R-95 9.41E+02 3.02E+02 4.58E+04 2.46E+04 0.00E+00 4.53E+04 0.00E+00 2.78E+08 NB-95 S.24E+04 1.19E+05 1.02E+03 0.00E+00 4.38E+02 0.00E+00 3.88E+03 0.00E+00 RU-103 3.93E+04 0.00E+00 1.32E+06 RU-106 1.04E+04 0.00E+00 2.58E+03 0.00E+00 5.38E+07 3.19E+07 0.00E+00 1.06E+08 'O.00E+00 2.19E+10 A0-110M 5.81E+07 6.49E+07 1.63E+07 5.89E+06 2.18E+06 4.89E+06 S.61E+07 0.00E+00 TE-125M 1.53E+08 TE-127M 4. 57E*01 1.63E+07 5.57E406 1.11E+07 1.66E+08 - 0.COE+00

--n--------..--.----------.--.-~.--.--..--......--............----.------

2.24E+07 9.51E+05 2.06E+01 2.51E+08 0.00E+00 3 02M+08 TE-129M 6.012+07 0.00E+00 1.12E+08 I-131 2.96E+03 4.23E+08 2.42E+00 1.39E+11 7.25E+08 6.73E+06 2.05E+06 9.88E+08 1.17E+07 0.00E+00 6.04E+06 I-133 3.87E+06 .--w.-

5.64E+09 1.34E+10 1.10E+10 0.00E+00- 4.34E+09 1.44E+09- 2.35E+0B CS-134 7.92E+07 1.10 +08 cs-136 2.63E+08' 3.04E+09 7.48E+08 0.00E+00 1. 70E +08 0.00E+00 3.42 s+09 1.14E+09 1.9hg+08 CE-137 7.372+09 1.01E+10 6.60E+09 2.69E+07 3.38E+04 1.76E+06 0.00E:00 1.15E+04 1.94E+04 5.54E+07-BA-140 0.00E+00 1.25E+07 CE-141 4.84E+03 3.27E+03 3.71E+02 0. 00E +00 1.52E+03 3.57E+05 1.49E+05 1.92E+04 0.00E+00 8.85E+04 0.00E+00 1.21E+08 CE-144 . - - - - - , - -

6.32E+01 7.81E+00 0.00E+00 3.65E&O1 0.00E+00 6.90E+05 PR-143 1.57E+02 9.40E*01 1.03E402 6.50E+00 0.00E+00 6.35I+01 0.00E+00 5. 22E+0'S ND-147 I-51 2098c l

- --_--_- _ _1

TMI Radiological Controls Departmental Procedure 6610-PLN-4200.0 __

Revision No.

' Title 0

Offsite Dome Calculation Manual (ODCM* .

TABLE 5.5.1 PATHWAY DOSE FACTORS, Ri AGE GROUP INFANT PATHWAY: ORASS-DOAT-MILK ORGAN DOSE FACTORS; m2 - mram/ year per pC1/sec NUCLIDE ----------------------------------------ID BONE LIVER T. BODY THYRO KIDNEY LUNO OZ-LLI 4.86E+03 4.06t+03 4.86E+03 4.86E+03 4.86E+03 H-3 0.00E+00 4.86E+03 5.00E+08 5.00E+08 5.00E+08 5.00E+0B 5.00E+08 5.00E+08 C-14 2.34E+09 2.76E+03 2. 46E4 04 5.64E+05 0.00E+00 0.00E+00 1.94E+04 1.26E+04 CR-51 1.06E+06 0.00E+00 1.04E+06 0.00E+00 1.72E+06 HN-54 0.00E+00 4.68E+06 5.55E+05 1.44E+05 1.76E+06 1.14E+06 3.03E+05 0.00E+00 0.00E+00 FE-55 0.00E+00 0.00E+00 1.51E+06 2.44E+06 FE-59 2.92E+06 5.10E+06 2.01E+06

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

7.26E+06 0.00E+00 0.00E+00 '0.00E+00 7.25E+06 CO-58 0.00E+00 2.91E+06 2.52E+07 1.06E+07 2.50E+07 0.00E+00 0.00E+00 0.00E+00 Co-60 0.00E+00 0.00E+00 0.00E+00 1.29E+07 N2-63 4.19E+09 2.59E+08 1.46E+08 0.00E+00 1.05E+09 0.00E+00 1.11E+09 0,00E+00 1.93E+09 ZN-65 6.67E+09 2.29E+09 6.83E+07 0.00E+00 2.67E+09 1.32E+09 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 0.00E+00 0.00E+00 5.44E+08 SR-89 2.65E+10 0.00E+00 7.59E+08 0.00E+00 6.50E+10 0.00E+00 0.00E+00 0.00E+00 3.19E+09 SR-90 2.55E+11 0.00E+00 6.31E+05 Y-91 8.80E+03 0.00E+00 2.34E+02 0.00E+00 0.00E+00 8.17E+02 1.99E+02 1.41E+02 0.00E+00 2.15E+02 0.00E+00 9.91E+04 2R-95 7.13E+04 2.93E+04 1.70E+04 0.COE+00 2.10E+04 0.00E+00 2.48E+07 NB-95 -0.00E+00 1.27E+04 RU-103 1.04E+03 0.00E+00 3.48E+02 0.00E+00 1.17E+03 2.28E+04 0.00E+00 2.85E+03 0.00E+00 1 70E+04 0.00E+00 1.73E+05 RU-106 4.63E+07 3.'38E+07 2.24E+07 0.00E+00 4.64E+07 0.00E+00 1.75E+09 AG-110H 0.00E+00 -8.62E+06 TE-125M 1.81E+07 6.05E+06 2.45E+06 6.09E+06 0.00E+00 5.06E+07 1.6BE+07 6.12E+06 1.46E+07 1.24E+08 0.00E+00 2.04E+07 TE-127H 6.69E+07 2.29E+07 1.03E+07 2.57E+07 1.67E+08- 0.00E+00 3.99E+07 TE-129M 0.00E+00 1.37E+08 I-131 3.27E+09 3.85E+09 1.69E+09 1.27E+12 4.50E+09 g-133 4.36E+07 6.35E+07 1.86t+07 1.15E+10 7.46E+07 0.00E+00 1.07E+07 1.09E+11 2.04E+11 2.06E+10 0.00E+00 5.26E+10 12.15E+10 5.55E+08 CS-134 1.42E+09 2.65E+08 CS-136 5.94E+09 1.75E+10 6.52E+09 0.00E+00 6.96E+09 1.54E+11 1.81E+11 1.28E+10 0.00E+00 4.85E+10 1.96E+10 5.65E+08 CS-137 . . - . - - - - - _ - - - - - -

2.90E+07 2.90E+04 1.50E+06 0.00E+00 6.89E+03 1.78E+04 7.13E+06 BA-140 0.00E+00 1 64E+06 CE-141 5.21E+03 -3.18E+03 3.74E+02 0.00E+00 9.79E+02 2.79E+05 1.14E+05 1.56E+04 0.00E+00 4.62E+04= 0.00E+00 1.60E+07 CE-144 1.78E+02 6.66E+01 8.83E+00 0.00E+00 2.48E+01 0.00E+00- 9.40E+04 PR-143 0.00E+00 6.89E+04 ND-147 1.06E+02 1.09E+02 6.66E+00 0.00E+00 4.19E+01 I-52 2098c l

1 , .

i THf Radiological Contecis Departmental Proced fe_ 66102_ ,1-4200.01__

Revision No.

T& tic 0

_ Of f ette Dose Calculat ion Manual (ODCM)

TABLE b 3 2 PATHWAY DOSE FACTORS. Ri AGE CROUP: CHILD PATHWAYS ORA 88-00AT-MILK l

................................. ORGAN 003E FACTORSl ................................

m' ~ mrom/ year per pCi/sec ......... .....

NUCL!DE - - ~ ~ - - - . ~ . . - ~ ~ ~ - - - - -THYR - - 0!D

- - - - -KIDNEY - - ~ ~ . - . -LUNG - - - - LLI ---~~~~----

BONE LIVER T. BODY

........................................ 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 H-3 0.00E+00 3.20E+03 2.39E+0B 2.39E+08 2.39E+0B 2.39E+08 2.39E+08 2.39E+08 6.48E+05 C.14 1.20E+09 6 78E+03 1.85E+03 1.24E+04 CR-51 0.00E+00 0.00E+00 1.22E+04 7.06E+05 0.00E+00 2.11E+06 0.00E+00 2.52E+06 6.71E+05 0.00E+00 1.43E+05 NN-54 0.00E+00 0.00E+00 4.362+05 2.39E+05

! PE-55 1.45E+06 7.71E+05 0.00E+00 7.34E+05 2.64E+06 1.56E406 2 53E+06 1.26E+06 0.00E+00 TE.59 0.00E+00 1 4 6E+06 4.46E+06 0 00E+00 -0.00E+00= 0.00E+00

........................ 8.49E+06 2.87t+07 Co.5B 1.0JE+07 0.00E+00 0.00E+00 0.00E+00 Co-60 0.00E+00 5 18E+06 0.00E+00 1.00E+00 1.2BE+07 3.56E+09 1 91E+08 1.21E+08 0 00E+00 N3 63 4.96E+08 1 32E+09 8.22E+08 0.00E+00 8.33E+0B 0 00E+00 .............2.32E+08 6.773+07 EH.66 6.47E408 0.00E+00 0.00E+00 0 00E+00 RB.86 0.00E+00 1 0$E+09 0.00E+00 0 00E+00 5.39E+08 1.36E+10 0 00E+00 3.97E+08 0.00E+00 SR.83 0.00E+00 =0.00E+00 0.00E+00 3.16E+09 SR-90 2.35E+11 0 00E+00 5.95E+10 0 00E+00 6.24E+05 0 00E+00 1.25E+02 0.00E+00 0.00E+00 Y.91 4.69E+03 1.45E+02 0.00E+00 1.05E+05-4.60E+02 1 01E+02 9.00E+01 0.00E+00 ER.95

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .0.00E+00 . . . . . . . .1.40E+04 . . . . . . . 0.00E+00 . . . . . . . . .2.75E+07...............

NB-S$ 3.82E+04 1 49E+04 1.06E+04 1.33E+04 1.98t+02 0.00E+Al 1.29E+03 0.00E+00 RU-103 5.14E+02 0.00E+00 0.00E+00 1.73E+05 1.11E+04 0.00E+00 1.383+03 0.00E+00 1 50E+04 RU-106 2.51E+07 1.69E+07 1.35E+07 0.00E+00 3.15E+07 0.00E+00 .. .... 2.01E+09 ....

AG.110H 2.49E+06 0.00E+00 0.00E+00 8.55E+06 TE-125H 8.86E+06 2.40E+06 1.18t+06 0.00E+00 2.02E+07 6.72E+06 2.96E+06 5.97E+06 7.12E+07 TE-127H 2 50E+07

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0$E+07 . . . . . . . . 9.56E+07. . . . . . . . 0.00E+00 . . . . . . . . .3.973407 ...............

TE.129H 3.26E+07 9.10E+06 5.06E+06 1.40Es08 8.95E+0B 5.21E+11 2.5BE+09 0.00E+00 1 131 1.57E+09 1.57E+09 0.00E+00 1.03E+C7 2.55E+07 9.662+06 4.74E+09 4.25E+07 I.133 2.06t+07 0.00E000 3.46E+10 1.24E+10 6.01E+0L Cs.134 6.80E+10 1.12E+11 2.35E+10 2.94E+08 5.41E+09 0.00t+00 4.45E+09 6.64E+0B C8 136 3.04E+09 8.1(t+09 3.02E+10- 1.09E+10 5.80E+08 9.68E+10 9.262+10 1.37E+10 0.00E+00 Cs-137 0.00E+00 4.02E+03 7.37E+03 7.15E+06 BA-140 1.41E+07 1.24E+04 8.23E+03 1.63E+06 1.95E+02 0.00E+00 5.74E+02 0.00E+00 CE.141 2.63E+03 1.31E+03 0.00E+00 1.59E+07-6.11E+04 1.04E+04 0.00E+00 3.38E+04 CE.144 1.95E+05 B.61E+01 2.59E+01 4.27E+00 0.00E+00 1.40E+01 .. ..9.29E+04 0.00E+00 PR.14L 0.00E+00 2.37E+01 0.00E+00 6.8bE+04 ND.147- 5.34E+01 4.33E+01 3.35E+00 I-53 209Bc

TNT Radiological Controls Departmental Procedure 6A10-PLN-4200.01 Revid&on No.

T6the 0

Of f site Do6e Calculation Manual (ODCH)

TAEtt 5.5.3 PATHWAY DOSE FACTORS. Ri ACE GROUPS TEEN PATHWAY ORASS-GOAT-HILK ORGAN DOSE TACTOR 8; 28 - mrom/ year per pCi/sec

--~~~~~-~~~--------~~~~~~~-~~~~---

NUCLIDE --------~~~~--------~~~~~--~~~~-~~~~~---

T.SODY THYROI D KIONEY LUNG C1-LLI LIV 4R BONE 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 ....

2.04E+03 H-3 0.00E+00 9.72E+07- -9.72E+07- 9.* 2E+07 0-14 4.86E+08 9.72E+07 9.72E+07 9.72E+07 3.33E+03 1.31E+03 8.55E+03 1.01E+06 CA-51 0.00E400 0.00E+00 5.99E+03 3.34E+05 0.00E+00~ 5.02E+05 0.00E+00 3.45E+06 HN-54 0.00E+00 1.68E+06 2.61E+05 1.785+05 5.79E+05 4.11E+06 9.58E+04 0.00E+00 0.00E+00 FE-55 0.00E+00 4.96E+05 3.72E+06-TE-59 6.74E+0b 1.57E+06 6.08E+05 0.00E+00 2.20E+06 0.00E+00 0.00E+00 0 00E+00 1.31E+07 Co-58 0.00E+00 9.53E+05 f.00E+00 4.J5E+07 0.00E+00 3.34E+06 7.52E+06 0.00E+00 0.00E+00 t Co-60 0.00E+00 4.00E+00 1.60E+01 N3-63 1.42E+09 1.00E+0B 4.01E+07 0.00E+00 8.78E+08 4.10E+08 0.00E+00 5.62E+08 0.00E+00 3.72E+06 EN-66 2.53E+08 0.00E+00 8.40E+07.

RB-86 0.00E+00 5.67E+08 2.67E+08 0.00E+00 0.00E+00 0.00E+00 1.61E+08 0.00E+00 0.00E+00 0 00E+00 6.69E+0B SR-89 5.62E+09 0.00E+00 3.43E+10 0.00E+00 0.00E+00 0.00E+00 3.90E+09 l SR-90 1.39E+11 0.00E+00 7.788+05 Y-91 1.90E+03 0.00E+00 5.09E+01 0.00E+00 0.00E+00 6.25E+01 4.30E+01 0.00E+00 9.18t+01 0.00E+00 1.44E+05 ER-95 1.98E+02 1.69E+04 9.38E+03 5.16E+03 0.00E+00 9.09E+03 0.00E+00 4.01E+07 NB-95 0.00E+00 1.82E+04 RU-103 2.17E+02 0.00E+00 9.29E+01 0.00E+00 7.66E+02-4.50E+03 0.00E+00 5.68E+02 0.00E+00 8.69E+03 0.00E+00 2.16E+05 RU-106 1.16E+07 1,09E+07 6.65E+06 0.00E+00 2.09E+07 0.00E+00 3.07E+09 A0-110H 0.00E+00 1.06E+07 TE-125H 3.61E+06 1.30E+06 4.82E+05 1.01E+06 0.00E+00 1.01E+07 3.59E+06 1.20E+06 2.41E+06 4.11E+07 0.00E+00 2.52E+07 TE-127H 1.32E+07 4.90E+06 2.09E+06 4. 26E+ 06 5.53E+07 0.00E+00 4.96E+07 TE-129H 1.79E+0B 3-131 6.45E+0B 9.03E+08 4.85E+08 2.64E+11 1.56E+09 0.00E+00 8.49E+06 1.44E+07 4.40E+06 2.01E+09 2.53E+07 0.00E+00 1.09E+07.

8-133 2.95E+10 6.93E+10 3.22E+10 0.00E+00 2.20E+10 B.41E+09 8.62E+08 CS-134 4.27E+08 CS-136 1.35E+09 5.30E+09 3.56t+09 0.00E+0! 2.89E+09 4.55E+08 4.02E+10 6.34E+10 1.86E+10 -0.00E+(u 1.82E+10 7.075+09 7.60E+08 Cs-137 5.84E+06 7.16E+03 3.76E+05 0.00E+0D 2.43E+03 4.81E+03 9.01E+06 BA-140 2.04E+06 CE*141 1.07E+03 7.12E+02 8.13E+01 0.00E+00 3.35E+02 0.00E+00 7.90E+04 3.27E+04 4.25E+03 0.00E+00 1.95E+04 0.00E+00 1.99E+07 CE-144 ................. . ............ .......

3.48Et0) 1.39E+01 '1.73E+00 0.00E+00 8.08E+00 0.00E+00 1.15E+05 ,

PR-143 8.54E+04 ND-147 2.182+01 2.37E+01 1.42E+00 0.00E+00 1.39E+01- 0.00E+00 . l l

~

1-54 2098c

MUClS8r TH! Radiological Controle Departmental Procedure 6610-PLN-4200.01 Tigt, Rev$ston No. =

0 Of f eite Dose Calculation Manual (ODCM) i TAB 1.E 5.5.4 PATHWAY DOSE TACTORS. El ACE GROUPI ADUIT PATHWAY: ORASS-00AT-MILK ORGAN DOSE FACTORS) m 8 - mrem / year per pCi/see

--~~~-*--------*-------

NUCL!DE -.--~~-~~~~---------------~~~------------***----***NEY KID LUNG 01 LL2 BONE LIVER T. BODY THYRQ10 1.56E+03 1.56t+03 1.56t+03 1.56t+03 1.56E+03-H-3 0.00E+00 1.56E403 5.27E+07 2.6#**08 5.27E+07 5.37E+07 5.27E+07 5.27E+07 5.27E+07 C-14 7.56t+02 4.55E+03 8.63E+05 CR-51 0.0M 00 0.00E+00 3.43E+03 2 05E+03 1.93E+05 0.00E+00 3.01E+05 0.00E+00 3.10E+06 KN-54 0.00E+00 1.01E+06 3.27t+05 2.26E+05 5.26E+04 0.00E+00 0.00E+00 1.26E+0E 1.30E+05 TE-55 2.54E+05 3.03E+06 TE-59 3.87t+05 9.09E+05 3.48E+05 0 00E+00 0.00E+00 0.00E+00 5.66E+05 1.27E+06 0.00E+00 0.00E+00 0.00E+00 1.15E+07 Co-58 3.70E+07 Co-60 0.00E+00 1.97t+06 4.35E+06 0.00E+00 0.00E+00 0.00E+00 N8-63 8.08E+0B 5.60E+07 2.71E+07 0.00E+00 0.00E+00 0.00E+00 1.17t+07 1.65E+0B 5.24E+08 2.37E+0B 0.00E+00 3.51E+0B 0.00E+00 3.30E+08 EN-65 6.14E+07 RB-86 0.00E+00 3.12E+08 1.45E+08 0.00E+00 0.00E+00 0.00E+00 SR-89 3.05E+09 0.00E+00 8.16E+07 0.00E+00 0.00E+00 0 00E+00 4.89E+0B SR-90 9.84E+10 0.00E+00 2.41E+10 0.00E+00 0.00E+00 0.00E+00 2.84E+09 Y.91 1 03E+03 0.00E+00 2.76E+01 0.00E+00 0.00E+00 0.00E+00 5.6BE+05 era 95 1.13E+02 3.63E+01 2.46E+01 0.00E+00 5.70E+01 0.00E+00 1.15E+05 NB-95 9.91E+03 5.52E+03 2.97E+03 0.00E+00 5.45E+03 0.00E+00 3.35E+07

RU-103 1.22E+02 0.00E+00 5.27t+01 0.00E+00 4 67E+02 0.00E+00 1 43E+04 RU 106 2.45E+03 0.00E+00 3.10E+02 0.00E+00 4.73E+03 0.00E+00 1.59E+05 AG-110M 6.99E+06 6.47t+06 3.84E+06 0.00E+00 1.27E+07 0.00E+00 2.64E+09 TE.125M 1.96E+06 7.09E+05 2.62E+05 5.89E+05 7.96t+06 0.00E+00 7.81E+06 .

TE-127M 5.50E+06 1.97E+06 6.70E+05 1.41E+06 2.23E+07 0.00E+00 1.84E+07 TE-129M 7.23E+06 2.70E+06 1.14E+06 2.48E+06 3.02E+07 0.00E+00 3.64E+07 2 131 3.56E+0B 5.09E+0B 2.92E+08 1.67E+11 8.73E+0B 0.00E+00 1.34E+08 2-133 4.65E+06 8.10E+06 2.47t+06 1.19E+09 1.41E+07 0.00E+00 7.28E+06 i CS-134 1.70E+10 4.04r+10 3.30E+10 0.00E+00 1.31E+10 4.34E+09 7.07t+0B C5-136 7.92E+0B 3.13M+09 2.25E+09 0.00E+00 1.74E+09 2.3BE+0B 3.55E+08-CS-137 k.22Z410 3.03E+10 1.99E*0 0.00E+00 1.03E+10- 3.42E+09 5.87E+08

.......................................................... e.......................

BA-140 3.24E+06 4.07t+03 2.12E+05 0.00E+00 1.38E+03 2.33E+03 6.67E+06 CE-141 5.82E+02 3.94E+02 4.47E+01 0.00E+00 1.83E+02 0.00E+00 1.51E+06 CE-144 4.30E+04 1.80E+04 2.31E+03 0.00E+00 1.07E+04 0.00E+00 1.45E+07 PR-143 1.90E+01 7.60E+00 9.40e-01 0.00E+00 -4.39E+00 0.00E+00 8.30E+04 ND-147 1.13E+01 1.31E+01 7.82e-01 0.00E+00 7.65E+00 0.00E+00 6.2BE+04 ;

l I-55 2098c P

et

1 1

TH! Radiological Controls Departmental Procedure 6610-PLN-d'(0.01 Revision No.

Title 0

Offsite Dose calculation Manual (ODCM) i TABLE 6.6.1 PATHWAY Dost FACTORR. Ri INFANT PATHWAY ORASS-COW-HEAT AGE CROUPI ORGAN Dost FACTOR $l m' . mrom/ year per pC1/sec NUCLIDE - - .-~~~.-.....~..--***--*************************************************

T.80DY THYROID K!DNEY LUNO O!-LLI BONE LIVER .....-...........-... ....

..........,.......................................s.. 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00

/

0.00E+00 0.00E+00 0.00E+00 0.00E+00 C-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CR-El 0 00E+00 0.00E+00 0.00E+00

................................ ..................................................0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 MN-54 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 FE-66 0.00E+00 0.00E+00 0.00E+00 TE-59 0 00E+00 0.00E+00

....................................................................................0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO-68 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 N3-63 0.00E+00

....................................................................................0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 EN-66 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 SR-89 0.00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00

R-90 0.00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ER-96

............. ................................. ..................................0 0.00E+00 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NB-95 0.00E+00 0.0;J+00 0.00E+00 0.00E+00 0 00E+00 RU-103 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 RU-106 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 AQ-110H 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE-125H 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 TE-127H 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 TE-129H 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

%.131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I.133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00.....

CS-134 0.00E+00 0.00E+00 0.00E+00- 0.00E+00 C8-136 0.00E+00 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00.

0.00E+00 0.00E+00

..................... 0.00E+00 CS-137 0.00E+90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BA-140 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+LO 0.00E+00 CE.141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+CD CE.144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00.....

PR.143 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ND-147 I-66 2098c

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

j TMI Radiological controls Departmental _ Procedure 6610-PLN-4200.0)_,

Revision No.

~ T6tle 0 ,,

Offsite Dome Calculation Manual (ODCH) 1 TABLE 5.6.2 PATHWAY DOSE TACTORS._,R,1, ACE OROUP CHILD PATKWAY: GRASS-COW-KEAT ORGAN DOSE TACTOR 5; ml - mrom/ year per pCi/see NUC&lDE --------------~~--~~--~~-.--~~-----~~-------~~~~~~~~~~~-----~~------~~-----

THYROID KIDNEY LUNO GI-LLI BONE LIVER T. BODY 0.00E+00 2.34E+02 2.34E+02

....................~.....................

2.34E+02 2.k4E+02 2.34E+02 2.34E+02 H-3 7.67E+07 7.67E+07 7.67E+07 7.67E+07 C-34 3.84E+08 7.67E+07 7.67E+07 8.90E+03 4.66E+05 0.00E+00 8.78E+03 4.88E+03 1.33E+03 CR-51 On70E+00 0.00E+00 2.2EE+06 0.00E+00 6.73E+06 MN-54 0.00E+00 8.01E+06 2.13E+06 1.37E+0B 4.49E+07 4.57E+08 2.43E+0B 7.52E+07 0.00E+00 0.00E+00 TE-55 0.00E+00 0.00E+00 1.77E+08 6.35E+08 TE-59 3.77E+08 6.10E+08 3.04E+08 0.00E+00 0.00E+00 0.00E+*O 9.58E+07 Co-58 0.00E+00 1.64E+07 5.03E+07 3.84E+08 2.04Ee08 0.00E+00 0.00E+00 0.00E+00 Co-60 0.00E+00 6.93E+07 0.00E+00 1.05E+08 2.91E+10 1.56E+09 9.91E+08 0.00E+00 0.00E+00 N8-63 0.00E+00 6.31E+08 0.00E+00 1.76E+08 EN-65 3.76E+08 1.00E+09 6.22E+0B 3.71E+07 5.76E*08 3.54E+08 0.00F+00 0.00E+00 0.00E+00 RS-86 0.00E+00 0.00E+00 0.00E+00 1.87E+07 4.82E*06 0.00E+00 1.3BE+07 0.00E+00 BR-89 1.04E+10 0.00E+00 2.64E+09 0.00E+00 0.00E+00 0.00E+00 1.40E+08 SR-90 0.00E+00 0.00E+00 2.40E+08 Y-91 2.80E+06 0.00E+00 4.82E+04 0.00E+00 5.21E+05 0.00E+00 8.38E+05 0.00E+00 6.11E+08 ER.95 2.66E+06 5.86E+05 ............... .....

................................ ......... ............ 2.23E+09 3.10E+06 1.21E+06 8.63E+05 0.00E+00 1.13E+06 0.00E+00 N8-95 3.90E+08 0.00E+00 4.01E+09 RU.103 1.55E+08 0.00E+00 5.96E+07 0.00E+00 5.54E+0B 0.00E+00 6.00E+09 0.00E+00 6.91E+10 4.44E+09 0.00E+00 RU-106 5.67E+06 4.53E+06 0.00E+00 1.06E+07 0.00E+00 6.74E+08 AG.110M 8.39E+06 0.00E+00 5.49E+08 Tr-125H 5.69E+0B 1.54E+08 7.59E+07 1.60E+08 0.00E+00 2.11E+08 4.25E+0B 5.06E+09 0.00E+00 1.44E+09 1.7BE+09 4.7BE+08 TE.127H 5.00E+08 2.78E+0B 5.77E+08 5.26t+09 0.00E+00 2.18E+09 TE-129M 1.79E+09 1.48t+06 1.66E+07 1.67E+07 9.48E+06 5.52E+09 2.74E+07 0.00E+00 Z-131 1.18E+00 0.00E+00 2.85e-01 8-133 5.72e-01 7.00e=01 2.60s-01 1.31E+02

..........................................n.........................................

1.51E+09 3.19E+08 0.00E+00 4.69E+08 1.68E+08 8.165+06 Cs.134 9.23E+08 1.57E+06 1.63E+07 4.48E+07 2.90E+S7 0.00E+00 2.39E+07 3.56E+06 CS-136 4.16E+0B 1.50E+08 8.00E+06 CS-137 1.33E+09 1.20E+09 1.89E+0L 0.00E+00 .... .....

3.87t+04 2.5BE+06 0.00E+00 1.26E+04 2.31E+04 2.24E+07 BA-140 4.42E+07 1.3aE+07 2.22E+04 1.11E+04 1.65E+03 0.00E+00 4.86t+03 0.00E+00 CE.141 4.02E+05 0.00E+00 1.89E+0B CE.144 2.32E+06 7.26E+05 1.24E+05 0.00E+00 1.00E+04 1.65E+03 0.00E+00 5.42E+03 0.00E+00 3.60E+07 PR-143 3.33E+04 1.50E+07 1.17E+04 9.4BE+03 7.34E+02 0.00E+00 5.20E+03 0.00E+00 ND-147 l

{

l l-I-57 2098c

e THI Radiol 091 cal Controls 6610-PLN-4200 01 Departmental Procedure Reviston No.

TatAs 0

,,0ffsite Dose Calculation Manual _(ODCH)

TABLE 6_.6 3 PATHWAY DOSE FACTORS, Ri TEEN PATHWAY GRASS-COW-MEAT AGE GROUP ORGAN 00SE TACTORS; m8 - mrom/ year per pol /soe ~-----

NUCLIDE -----------~~~-------------------* T. BODY THYROID---------------~~----~~~~--------~01-LLI KIDNEY LUNG BONE LIVER 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 4.0BE+07 H-3 0.00E+00 4.08t+07 -4.08E+07 4.08E+07 C-14 2.04E+08 4.08E+07 4.08t+07 0.03E+03 9.46E+05 l

5.63E+03 3.13E+03 1.23E+03 0.00E+00 0.00E+00 CR-51 7.00E+06 1.39E+06 0.00E+00 2.09E+06 0.00E+00 1.44E+07 7.31E+07 MN-54 0.00E+00 0.00E+0C 0.00E+00 1.07E+08 TE-55 2.38E+08 1.69E+08 3.94E407 1.56E+08 1.17E+09 4.95E+0B 1.91E+08 0.00E+00 0.00E+00 2.12E+08 TE-59 1.40E+07 3.24E+07 0.00E+00 0.00E+00 ......................-

0.00E+00 1.94E+08 CO-58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.60E+08 Co-60 0.00E+00 5.83E+07 1.31E+08 0.00E+00 1.71E+08 1.07E+09 5.15E+0B 0.00E+00 0.00E+00 1.62E+10 NZ-63 2.50E+08 8.68E+08 4.05E+08 0.00E+00 5.56E+08 0.00E+00 3.68E+08 6.00E+07 EN-65 1.91E+08 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 4.06E+08 0.00E+00 0.00E+00 3.03E+07 2.55E+08 0.00E+00 7.29E+06 0.00E+00 SR-89 8.04E+09 0.00E+00 1.99E+09 0.00E+00 0.00E+00 0.00E+00 2.26E+08 SR-90 0.00E+00 0.00T.+00 0.00E+00 3.91E+08 Y-91 9.54E+05 0.00E+00 2.56E+04 0.00E+00 1.09E+09 4.73E+05 3.25E+05 0.00E+00 6.96E+05 ER-95 1.50E+06 0.00E+00 9.64E+05 0.00E+00 4.25E+09 NB-95 1.79E+06 9.95E+05 5.48E+05 7.15E+09 3.66E+07 0.00E+00 3.02E+0B 0.00E+00

-RU-103 8.56E+07 0.00E+00 4.54E+09 0.00E+00 1.13E+11 2.36E+09 0.00E+00 2.97E+08 0.00E+00 RU-106 4.78E+06 2.91E+06 0.00E+00 9.13E+06 0.00E+00 1.34E+09 A0-110M 5.06E+06 0.00E+00 0,00E+00 0,94E+08 3.03E+08 1.09E+08 4.05E+07 8.46E+07 TE-126M 2.24E+08 3.81E+09 0.00E+00 2.35E+09 9.41E+08 3.34E+08 1.12.E +08 TE-127H 3.52E+08 1.50E+08 3.06E+08 3.97E+09 0.00E+00 .......... 3.56E+09 TE-129M 9.49E+0B 2.15E+07 0.00E+00 2.47E+06 0.93E+06 1.25E+07 6.72E+06 3.65E+09 Z-131 1.59e-01 7.29E+01 9.16e 0.00E+00 3.95e+01 3.08e-01 5.22e-01 2-533 1.23E+09 5.71E+08 0.00E+00 3.91E+08 1.49E+08 1.53E+07 CS-134 5.23E+08 2.02E+07 3.18E+06 2.99E+06 CS-136 9.43E+06 3.71E+07 ?. 49E+07 0.00E+00 0.00E+00 3.28E+0B 1.27E+0B 1.37E+07 7.24E+08 9.63E+08 3.35E+0B CS-137 2.39E+07 2.93E+04 1.54E+06 0.00E+00 9.94E+03 1.97E+04 3.69E+07 BA-140 0.00E+00 3.71E+03 0.00E+00 2.25E+07 CE-141 1.18E+04 7.87E+03 9.05E+02 3.09E+08 6.60E+04 0.00E+00 3.03E+05 0.00E+00 1.23E+06 5.08E+05 CE-144 7.03E+03 8.76E+02 0.00E+00 4.08E+03 0.00E+00 .............. 5.79E+07 PR-143 1.76E+04 3.98E+03 0.00E+00 2.44E+07 6.23E+03 6.78E+03 4.06E+02 0.00E+00 ND-147 2-58 209Be

TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

T6tle 0

Offsite Dese Calculation Manual (ODCM)

TABLE 5.6.4 PATHWAY DOSE TACTORS, Ri AGE GROUP ADULT PATHWAY: ORASS-COW-MEAT ORGAN DOSE TACTORSI m8 - mrom/ year per pCi/sec

~~~---- ;f NUCLIDE ----.------------------------------------D BONE LIVER T. BODY THYROI KIDNEY LUNO CI-LLI 3.24E+02 3.24E+02 3.24E+02 3.24E+02- 3.14E+02 11 - 3 0.00E+00 3.24E+02 4.83E+07 4.843+07 4.83E+07 4.83E+07 4.83E+07 4.83E+07 C-14 2 42E+08 1.55E+03 9.35E+03 1. '7E+06 CR-51 0.00E+00 0.00E+00 7.04E+03 4.21E+03 2.73E+06 0.00E+00 2.8;E*07 0.00E+00 9.18E+06 1.75E+06 0.00E+00 M?8-5 4 4.73E+07 0.00E+00 0.00E+00 1.13E+08 1.10 1J8 ft +55 2 93E+08 2.03E+08 1. 7 5E+ 08 2.08E409 2 66E+08 6.25E+08 2.39E+08 0.00E+00 0.00E+00 TE*39 1.82E+07 4.09E+07' O.00E+00 0.00E+00 0.00E+00 3.70E+08 CO-58 0.00E+00 0.00E+00 1.41E+09 CO-60 0.00E+00 7.62E+07 1.66E+08 0.00E+00 0.00E+00 1.31E+09 6.33E+0B 0.00E+00 0.00E+00 0.00E+00 2 73E+08 1.89E+10 NZ-63 1.13E+09 5.12E+08 0.00E+00 7.57E+08 0.00E+00 7.13E+08 EN-65 3.56E+08 0.00E+00 9.59E+07 RB-86 0.00E+00 4.87E+08 2.27E+08 0.00E+00 0.00E+00 0.00E+00 8.66E+06 0.00E+00 0.00E+00 0.00E+00 4.84E+07 3.02E+08 SR-89 3.05E+09 0.00E+00 0.00E+00 0.00E+00 3.60E+08 SR-90 1.24E+10 0.00E+00 0.00E+00 3.03E+04 0.00E+00 0.00E+00 0.00E+00 6.24E+08 Y-91 1.13E+06 1.90E+09 ER-95 1.87E+06 6.01E+05 4.07E+05 0.00E+00 9.43E+05 0.00E+00 1.28E+06 6.87E+05 0.00E+00 1.26t+06 0.00E+00 7.76E+09 NB-95 2.30E+06 1.23E+10 RU-103 1.0$E+08 0 00E+00 4.53E+07 0.00E+00 4.02E+08 0.00E+00 2.80E+09 0.00E+00 3.54E+08 0.00E+00 5.41E+09 0.00E+00 1.81E+11 RU-106 6.68E+06 6.18E+06 3.67E+06 0.00E+00 1.22E+07 0.00E+00 2.52E+09 AG-110M 1.43E+09 TE-125H 3.59E+08 1.30E+08 4.81E+07 1.08E+08 1.46t+09 0.00E+00 1.12E+09 3.99E+08 1.36E+0B 2.85E+08 4.53E+09 0.00E+00 3.74E+09 TE-127M 1.13E+09 4.23E+08 1.79E+08 3.89E+0P 4.73E+09 0.00E+00 5.71E+09 TE-129M 0.00E+00 4.06E+06 8 131 1.08E+07 1.54E+07 8.82E+06 5. 04P.405 2.64E+07 3.68e-01 6.41e-01 1.95e-01 9.42E+0i 1.12E+00 0.00E+00 5.76e-01 8-133 6.58E+08 1.57E+09 1.28E+09 0.00E+00 5.07E+08 1.68E+0B 2.74E+07 CS-134 3,65E+06 5.43E+06 CS-136 1.21E+07 4.78E+07 3.44E+07 0.00E+00 2.66E+07 8.72E+08 1.19E+09 7.82E+08 0.00E+00 4.05E+08 1.35E+08 2.31E+07 Cs-137 2.90E+07 3.64E+04 1.90E+06 0.00E+00 1.24E+04 2.08E+04 5.96E+07 BA-140 0.00E+00 3.64E+07 CE-141 1.41E+04 9.51E+03 1.0BE+03 0.00E+00 4.42E+03 1.46E+06 6.10E+05 7.83E+04 0.00E+00 3.62E+05 0.00E+00 4.93E+08 CE-144 2.09E+04 8,10E+03 1.04E+03 0.00E+00 4.85E+03 0.00E+00 9.17E+07 PR-143 0.00E+00 3.93E+07 ND-147 7.08E+03 b.10E+03 4.90E+02 0.00E+00 4.78E+03 I-59 2098c

- . .. . - - - - - - - - - _ _ _ - . - _ _ _ _ _ l

THI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

T6tle O

Of f site Dose calculation Manual (ODCM) t TABLE 5.7.1 PATHWAY DOSE FACTORS, Ri INFANT PATHWAY VE0ETATION ACE GROUP ORGAN DOSE FA0 TORS) m' - mram/ year per pC1/sec ----

NUCLIDE ----------------------------~~------ THYROID--------~~~----------~~----------!-LLI KIDNEY LUNO O BONE LIVER T. BODY 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 0.00E+00 0.00E+00 0.00E+00 0 00E+00- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CR-51 0.00E+00 0. 00E4 00 0.00E+00 .

.. .... ............... ........ 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 HN-54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 FE-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 00-58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E+00 N3-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 EN-65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 0.00E+00 0.00E+00 0.00F+00 0.00E+00 SR-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ER-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NB-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU-103 0.00E+00 0.00E+00 0.00E+00 RU-106 0.00E+00 0.03k+00 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 A0-110M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE-125H 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE-127H 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE-129H 0.00E+00 0,00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3-131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3 133 0.00E+00 0.00E+00 0.00E+00

........ .................................... 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS-134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS-136 0.00E+00 0.00E+00 0.00E+00 CS-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RA-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PR-143 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ND-147 ............... ............

1-60 2098c

THI Radiological Centrols Departmental Procedure 6610-PLN-4200.01 Revision No.

Title 0

Of f site Do** Cal *ulation Man 941 (DDCM)

TABLE 5.7.2 PATHWAY DOSE FACTORS, RL AGE GROUPS CHILD PATHWAY: VEGETATION ORGAN DOSE FACTORS; m2 - mram/ year per pC1/sec

-----~~-----------------------

NUCLIDE --------------------------------------ROID THY KIDNEY LUNG GI-LLI BONE LIVER T. BODY 4.02E+03 4.02E+03 4.02E+03 4.02E+03 H-3 0.00E+00 4.02E+03 4.02E+03 1.78E+0B 1.7BE+08 1.78E+08 1.78E+0B 1.7BE+0B C-14 8.89E+08 1.78E+08 1.18E+05 6.20E+06 0.00E+00 0.00E+00 1.17E+05 6.49E+04 . 77E+04 CR-51 1.77E+08 0.00E+00 1.86E+08 0.00E+00 5.58t+08 MN-54 0.00E+00 6.65E+08 2.40E+08 7.87E+07 8.01E+08 4.25E+08 1.32E+08 0.00E+00 0.00E+00 FE-55 0.00E+00 0.00E+00 1.87E+08 6.71E+08 3 98E+08 6.44E+0B 3.21E+08 FE-59 6.44E+07 1.97E+08 0.00E+00 0.00E+00 0.00E+00 3.76E+08 CO-58 0.00E+00 0.00E+00 0.00E+00 2.10E+09 Co-60 0.00E+00 3.78E+08 1.12E+09 0.00E+00 1.34E+09 0.00E+00 0.00E+00 0.00E+00 1.42K+08 NZ-63 3.95E+10 2.11E+09 1.35E+09 0.00E+00 1.36E+09 0.00E+00 3.80E+08 EN-65 8.12E+08 2.16E+09 2.90E+07 0.00E+00 4.51E+08 2.77E+0B 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 0.00E+00 1.39E+09 SR-89 3.60E+10 0.00E+00 1.03E+09 0.00E+00 0.00E+00 3.15E+11 0.00E+00 0.00E+00 0.00E+00 1.67E+10 SR-90 1.24E+12 0.00E+00 2.49E+09 1.87E+07 0.00E+00 4.99E+05 0.00E+00 0.00E+00 Y-91 1.21E+06 0.00E+00 8.85E+08 ER-95 3.86E+06 8.485+05 7.55E+05 0.00E+00 1.60E+05 1.14E+05 0.00E+00 1.50E+05 0.00E+00 2.96E+08 NB-95 4.11E+05 3.97E+08 1.53E+07 0.00E+00 5.90E+06 0.00E+00 3.86E+07 0.00E+00 RU-103 0.00E+00 1.16E+10 RU-106 7.45E+08 0.00k+00 9.30E+07 0.00E+00 1.01E+09 2.17E+07 1.73E+07 0.00E+00 4.04E+07 0.00E+00 2.58E+09 AG-110M 3.21E+07 3.3BE+08 3.51E+08 9.50E+07 4.67E+07 9.84E+07 0.00E+00 0.00E+00 TE-125M 3.772+09 0.00E+00 1.07E+09 TE-127H 1.32E+09 3.56E+08 1.57E+08 3.16E+0B 2.35E+0B 1.30E+08 2.71E+08 2.47E+09 0.00E+00 1.02E+09 TE-129M 8.40E+08 1.2BE+07 1.43E+0B 1.44E+0B 8.18E+07 4.76E+10 2.36E+0B 0.00E+00 8-131 8.12E+08 7.2BE+06 0.00E+00 1.76E+06 8-133 3.53E+06 4.37E+06 1.65E 06 2.63E+10 5.55E+09 0.00E+00 8.15E+09 2.93E+09 1.42E+08 Cs-134 1.60E+10 0.00E+06 8.28E+07 2.28E+08 1.47E+08 0.00E+00 1.21E+08 1.81E+07 CS-136 7.46E+09 2.6BE+09 1.43E+0B CS-137 2.39E+10 2.29E+10 3.38E+09 0.00E+00 2.44E+05 1.63E+07 0.00E+00 7.96E+04 1.46E+05 1.41E+08 BA-140 2.79E+08 4.09E+08 6.57E+05 3.28E+05 4.86E+04 0.00E+00 1.44E+05 0.00E+00 CE-141 2.21E+07 0.00E+00 1.04E+10 CE-144 1.27E+0B 3.99E+07 6.79E+06 0.00E+00 4.36E+04 7.21E+03 0.00E+00 2.36E+04 0.00E+00 1.57E+08 PR-143 1.45E+05 9.18E+07 7.15E+04 5.79E+04 4.49E+03 0.00E+00 3.18E+04 0.00E+00 ND-147 I-61 2098c

TMI Radiological Controle Departmental Procedure 6610-PLN-4200.01

_,, novaston No.

Title 0

Offeite Doce Calculation Manual (ODCM)

TABLE 5.7.3 PATHWAY DOSE TACTORS, Ri AGE GROUP: TEEN PATHWAY: VE0ETATION ORGAN DOSE TACTORS) m' . mrem / year per pC1/see HUCLIDE . . - . . . . . . . . . . . - - - - . . . . . . . . . . . . . . . - . . - KIDNEY - . . . . . . . . - -LUNO

+ . - - - -G1-LLI LIVER T. BODY THYROID DONE 2.59E+03 2 59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 H-3 C-14 0.00E+00 3.69E+0B 7.38E+07 7.30E+07 6 16E+04 7.38E+07 3.42E+04 7.3BE+07 1.35E+04 7.38E+07 8.79E+04 7.3BE+07 1.03E+07 ll 0.00E400 0.00E+00 CR-51 4.54E+08 9.01E+07 0.00E+00 1.36E+0B 0.00E+00 9.32E+08 MH-64 0.00E+00 0.00E+00 1.47E+08 1.00E+0B 3.26E+0B 2.31E+0B 5.39E+07 0.00E+00 FE-5b 0.00E+00 0.00E+00 1.32E+08 9.91E+08 1.00E+0B 4.19E+08 1.62E+0B TE-59 4.36E+07 1.01E+0B 0.00E+00 0.00E+00 0.00E+00 6.01E+08 00-5' O.00E+00 5.60E+08 0.00E+00 0.00E+00 0.00E+00 3.24E+09 CO-61 0.00E+00 2.49E+08 0.00E+00 1.81E+08 1.61E*10 1.13E+09 5 45E+0B 0.00E+00 0.00E+00 NI.63 1.47E+09 6.86E+0B 0.00E+00 0.42E+08 0.00E+00 6.23E+08 EN-65 4.24E+08 0.00E+00 0.00E+00 4.04E+07 P,0-86 0.00E+00 2.73E+08 1.28E+0B 0.00E+00 4.34E+08 0.00E+00 0.00E+00 0.00E+00 1.80E+09 ER-69 1 52E+10 0.00E+00 1.BSE+11 0.00E+00 0.00E+00 0.00E+00 2.11E+10 SR.90 7.51E+11 0.00E+00 0.00E+00 3.22E+09 7.84E+06 0.00E+00 2.10E+05 0.00E+00 0.00E+00 Y.91 0.00E+00 7.98E+05 0.00E+00 1 25E+09 i tR-95 1.72E+06 5.43E+05 3.73E+05 5.07t+04 0.00E+00 1.03E+05 0.00E+00 4.56E+08 N8-95 1.92E+05 1.07E+05 5.70E+08 i

0.00E+00 2.92E+06 0.00E+00 2.41E+07 0.00E+00 RU.103 6 82E+06 5.97E+08 0.00E+00 1.48E+10 RU-106 3 09E+08 0.00E+00 3.90E+07 0.00E+00 8.72E+06 0.00E+00 2.74E+07 0.00E+00 4.03E+09 AC-110M 1.52E+07 1.43E+07 4.37E+08 5.34E+07 1.98E+07 4.14E+07 0.00E+00 0.00E+00 TE.125M 1.40E+08 0.00E+00 1.37E+09 5.52E+08 1.96E+08 6.56E+07 1.31E+08 2.24E+09 TE-127H 1.34E+08 5.72E+0? 1.17E+08 1.51E+09 0.00E+00 1.36E+09 TE-129H 3.61E+0B 0.00E+00 2.13E+07 1 131 7.69E+07 1.00E+0B 5.7BE+07 3.14E+10 1.85E+08 1.00E+06 4.59E+08 5.77E+06 0.00E+00 2.49E+06 I.133 1.94E+06 3.29E+06 7.75E+09 0.00E+00 5.31E+09 2.03E+09 2.08E+08 Cs-134 7.10E+09 1.67E+10 1.39E+07 1.73E+0B 1.16E+0B 0.00E+00 9.41E+07 1.48E+07 CS-136 4.39E+07 4.59E+09 1.78E+09 1.92E+08 CS-137 1.01E+10 1 35E+10 4.69E+09 0.00E+00 l ................................................................ 8.97E+06 0.00E+00 5.78E+04 1.15E+05 2.15E+08 BA-140 1.39E+0B 1.71E+05 5.41E+08 1.89E+05 2.17E+04 0.00E+00 8.90E+04 0.00E+00 CE-141 2.83E+?$ 0.00E+00 1.33E+10 5.2BE*i7 2.18E+07 2.83E+06 0.00E+00 1.30E+07 CE-144

....................................................................... 3.4BE+03 0.00E+00 1.62E+04 0.00E+00 2.30E+08 PR-143 6.99E+04 2.79E+04 1.42E+08 3.94E+04 2.36E+03 0.00E+00 2.31E+04 0.00E+00 3.62E+04 ND-147 I

I-62 2098c e

hj

TMI Radiological Controls Department al Procedure 6610-PLN-4200.01 Revision No.

Title 0

Offette Dose Calculation Panual (ODCK)

TABLE 5. 7. 4 PATHWAY DOSE FACTORS, Ri AGE CROUP: ADULT PATHWAY: VEGETATION ORGAN DOSE FACTORS; m 8 - mrem / year per pCi/sec NUCLIDE -------

+-------*----~~-----------~~~~ROID T. BODY THY KIDNEY LUNO GI-LLI LIVER BONE 2.26E+03 2.26t+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 H-3 0.00E+00 4.55E+07 4.55E+07 4.55E+07 r C-14 2.2BE+08 4.55E+07 4.55E+07 4.64E+04 4.55E+07 2 77E+04 1.02E+04 6.15E+04 1.17E+07 (

0.00t+00 0.00E+00 CR-51 5.97F+07 0.00E+00 9.31E+07 0.00E+00 9.58E+08 MN-54 0.00E+00 3.13E+0B 8.08E+07 8.31E+07 2.10E+08 1.45E+08 3.38E+07 0.00E+00 0.00E+00 TE-55 0.00E+00 0.00E+00 8.29E+07 9.89E+08 1.26E+0B 2.97E+0B 1.14E+08 FE-59 3.07E+07 6.89E+07 0.00E+00 0.00E+00 0.00E+00 6.23E+08 Co-58 0.00E+00 0.00E+00 3.14E+09 0.00E+00 1.67E+08 3.69E+08 0.00E+00 0.00E+00 Co-60 0.00E+00 0.00E+00 1.50E+08 NI-63 1.04E+10 7.21E+08 3.49E+08 0.00E+00 1.01E+09 4.56E+08 0.00E+00 6.75E+08 0.00E+00 6.36E+08 (

1N-65 3.17E+08 0.00E+00 4.32E+07 (

0.00E+00 2.19E+08 1.02E+08 0.00E+00 0.00E+00 RB-86 0.00E+00 0.00E+00 1.60E+09 SR-89 9.9BE+09 0.00E+00 2.86E+08 0.00E+00 0.00E+00 1.48E+11 0.00E+00 0.00E+00 0.00E+00 1.75E+10 SR-90 6.0$E+11 2.82E+09 5.12E+06 0.00E+00 1.37E+05 0.00E+00 0.00E+00 0.00E+00 Y-91 5.91E+05 0.00E+00 1.19E+09 ER-95 1.17E+06 3.77E+05 2.55E+05 0.00E+00 7.92E+04 4.26E+04 0.00E+00 7.83E+04 0.00E+00 4.81E+08 NB-95 1.42E+05 5.57E+08 4.77E+06 0.00E+00 2.06E+06 0.00E+00 1.82E+07 0.00E+00 RU-103 0.00E+00 1.25E+10 RU-106 1.93E+08 0.00E+00 2.44E+07 0.00E+00 3.72E+C8 1.05E+07 9.75E+06 5.79E+06 0.00E+00 1.92E+07 0.00E+00 3.98E+09 AG-110M 0.00E+00 3.86E+08 TE-125M 9.66E+07 3.50E+07 1.29E+07 2.90E+07 3.93E+08 3.49E+0B 1.25E+08 4.26E+07 8.93E+07 1.42E+09 0.00E+00 1.17E+09 8 TE-127M 2.51E+0B 9.37E+07 3.97E+07 8.63E+07 1.05E+09 0.00E+00 1.26E+09 TE-129M 0.00E+00 3.05E+07 I-131 8.08E+07 1.16E+08 6.62E+07 3.79E+10 1.98E+08 2.09E+06 3.63E+06 1.11E+06 5.34E+08 6.33E+06 0.00E+00 3.26E+06 I-133 4.67E+09 1.11E+10 9.08E+09 0.00E+00 3.59E+09 1.19E+09 1.94E+08 CS-134 1.29E+07 1.92E+07 CS-136 4.28E+07 1.69E+08 1.22E+08 0.00E+00 9.41E+07 6.36E+09 8.70E+09 5.70E+09 0.00E+00 2.95E+09 9.81E+08 1.68E+08 CS-137 1.29E+08 1.62E+05 8.47E+06 0.00E+00 5.52E+04 9.29E+04 2.66E+08 BA-140 0.00E+00 5..0E+08 CE-141 1.97E+05 1.33E+05 1.51E+04 0.00E+00 6.20E+04 3.29E+07 1.38E+07 1.77E+06 0.00E+00 8.16E+06 0.00E+00 3.11E+10 CE-144 6.25E+04 2.51E+04 3.10E+03 0.(JE+00 1.45E+04 0.00E+00 2.74E+08 PR-143 0.00E+00 1.85E+08 ND-147 3.34E+04 3.85E+04 2.31E+03 0.00E+00 2.25E+04 7

4 Q

I-63 209Be

~~ --- - _ _ _ _ _ _ _

l TH1 Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

T6tle O

Of f site __ Dope Cilsulation Manual (ODCH) ;

6.0 GASEOUS WASTE TREATMENT SYSTEM 6.1 Description of the Gaseous Radwaste Treatment System (see Figure 6.1) 6.1.1 Waste Gas System

a. Reactor Building

- Reactor Coolant Drain Tank (RCDT) header

b. Auxf.11ary Daildings

- Vent Header from

1. Miscellaneous Waste Storage Tank (HWST)

2. '.'hree (3) Reactor Coolant Bleed Tanks (RCBT) l

- Wasts Gas Delay Tank

- Two (2) Waste Gas Compressors

- Three (3) Wasta Gas Decay Tanks (WGDT)

c. Filtration and dilution provided by the Station Vantilation System.

6.2 operability ,

Operability of the Gaseous Waste Treatment System is defined as the ability to remove gas f rom the vent header / tank gas spaces and store it under a higher pressure in the Waste cas Decay Tanks for subsequent release.

Except for initiating the make up tank sample and waste gas venting and the recycle or disposal of compressed waste gases stored in the waste gas deca */

tanks, the operation of the waste gas system is entirely automatic. One waste gas compressor comes on automatically, removing gases f/om the vent header system as required, to maintain the pressure in the system at a maxLmum of about 16.4 psia.

1-64 2098c

[ ----

TM Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

._ Title 0

Of f site Dose Calculation Manual (ODCM)

FIGURT 6.1 tainonina WASTE GAS SYSTEM a Atton sensias "I t 'i n as onut 85 I is l

. .. . , i . .s , .

[ n n

(

"' O' F-~~~ + - E E E l ,g;u,n, atar! "l r.' "! "!

l o ss - --- a l -

44 W&llt sal 4p WDs V6. 10 WitlH &ilot DiLAll&bn sius suona sititas MI H ',yt,"","" g 1

1 masst was v. p sat 5,6mP8,isson wh, ,,,

on on on WAllt g sal -

o "

wasu sas wasis sas wuta sas courats**14. s vis gigailana DtCAllatt DiC AT I Att i 8 I C 4 A

,,3 s ,. ...;,;-) g L l, >Lg.,,pp,,,,go < -

I-65 2098c

THI Radiological Controls Departmental Proecdure 6610-PLN-4200.01 Reviston No.

T6tl6 0

Offeite Dose calculation Manual (ODOM) 7.0 EtNIRONMENTE MONITORING INFORMATION The Radiological Environmental Monitoring Program shall be conducted te outlined in Parts II and III of this document. Sampling locations will be as indicated in Tables 7.1 through 7.7 and as depicted on the Hape 7.1 through 7.3.

I-66 2098c

Tr! Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

Tit 19 0

Of f eite Dese..Ch)culation Manual (00cM)

Table 7.1

[MTN$ REMP STATION LOOATIONS-ATR PARTICULATE AND ATR 10 DINE I

NUREG Agimuth Map No.

8tation Code Distanee 0.8 mi. 28' 60 81-4 -2

-0.4 95

-El-2 105 10 r1-3 0.6 1.4 125 75- ,

02-1 3 13 253 M2-1 4 2.6 358 A3-1 5 H3-1 23 159 2.9 181 71 J3-2 92 3.5 325 04-1 127 6 010-! 9.0 180 7 015-1 12 6 305 8 Q15-1 13.5 Table 7.2 THINS REMP STATION LOCATIONS-DIRECT RADI ATION {TLD)

NUREO Map No.

station code Cistance Animuth Al-1 0 4 mi. O' 1 0.3 5 9 A1-4 B1-1 0.6 25 10 0.4 26 11 B1-2 0.5 15 12 B1-3 03 54 13 C1-2 0.2 74 14 D1-1 El-1 0.2 95 15 El-2 04 55 2 0.2 90 16 El-4 T1-2 0.2 109- 17 01-3 0.3 129 18 H1-1 0.5 167 19 H1-9 0.3 167 20 J1-1 0.6 104 21 Ji-3 0.3 189 22 J1-4 0.4 180 23 K1-4 0.2 200 .24 Ki-5 0.2 202 25-L1-1 0.1 235- 26 M1-1 0.1 249 27 N1-3 0.1 270 28 P1-1 v.4 293 29 . j P1-2 0.2 '290 30 I-67 2098c

THI Radiclogical controls Departmental Procedure 6610-PLN-4200.01 Revisten No.

T6tas 0

Of f site Deep calculation Manual (ODCM)

Table 7.2 (Cont'd)

NUREG

-Dietanee Asimuth Her No.

8tation code 0.2 mL 318' 31-01-2 32 R1 1 0.2 335 1.6 48 33 C2-1 .34 K2-1 11 200 253 3 M2-1 1.3 26 358 4-A3-1 2.3 159 5 H3-1 26 338 35 R3*1 4.8 18 36 86-1 4.5 42 37 l C6-1 46 81 38 E5-1 39 .i T6-1 4.7 107 4.8 131 40 )

06-1 i 4.1 157 41 H5-1 4.9 182 42 Jb-1 5.0 200 43 K5-1 4.1 228 44 L5-1 4.3 249 45 M6-1 N61 4.9 268 46 4.9- 286 47 P5 1 5.0 318 48 06-1 R6-1 4.9 -339 49 D6-1 5.2 65 50 E7-1 6.8 .86 51 8.5 308 - 52 09-1 B10-1 9.4 21 53 010-1 9.8 127. 6 016-1 14.4 124 54 J16-1 12.6 180 7 13.5 305 0-Q15-1 R16-2 12.4 329 55 l

1-68 209Bc

" ~ ' ,.. ...___ _

TMI Radiological Controls Departmental Procedure 6 610- Pt.N-4 2 00. 01 Revision No.

Title 0

Of f eite Dore calculation Manual (ODcM)

Table 7.3 THINS REMP STATION LOCATIONS-SURFACE WATER HUREG Map No.

Station code Distance Animuth 0.1 mi. 204' 56 PI-3 (R) 186 57 J1-2 (R) 0.5 1.5 182 58 J2-1 (R) 355 59 A3-2 (R) 2.5 4.2 157 61 H5-2 (r) 300 52 Q9-1 (F) 8.5 14.4 124 54 015-1 (F) 120 62 015-2 (r) 13.6 14.0 124 63 015-3 (T) 178 64 J15-2 (T) 14.7 12.6 122 65 r15-1 (R)

(R) = Raw Water (r) = rinished Water Table 7.4 THIh5 REMP STATION LOCATIONS- AQUATIC SEDIKENT NUREC Distance Azimuth Map No.

Station code Al-2 0.8 mi. 6' 66 Al-3 0.5 0 67 01-1 0.3 137 68 Ki-3 0.3 202 69 J2-1 1.6 182 50 1-69 209Bc

THI Radiological controls Departmental Procedure 6610-PLN-4200.01 Revision No.

76%1e 0

Of f site Dose Calculation Manual (ODCM)

Table 7.6 TMtNS REMP STATION LOCATIONS-HILK NUREO Map No.

Station Code Distance Asimuth A2-1 (HO) 1.2 mi. $' 72 14.2 9 73-A16-2 (HO) 66 74 D2-1 (H) 1.1 1.4 126 76 02-1 (H) 76 P7-1 (H) 6.7 293 12.8 208 77 K16-2 (H) 78 F3-1 (H) 2.3 104 1.1 93 79 E2-2 (H) 93 A4-1 (H) 3.3 10 (MG) = Goat Hilk (H) = cow Hilk Table 7.6 THINS REMP STATION LOCATIONS-FISH.

Station Code Station Designation TM-AQF-IND Downstream of' Station Discharge TH-AQF-BKG Upstream of Station Discharge AQF = Fish I-70 2098c

THI Radiological Controls Departmental Procedure 6610-FLN-4200.01 Revision No.

Title 0

Offsite Dese Calculation Manual (ODCM)

Table 7.7 THINS REMP STATION LOCATIONS-TOOD PRODUCTS Azimuth Map No.

Sta Code Distance 65' 74 D2-1 1.1 mi.

1,4 125 75 G2-1 M 9,3 357 A9-2 81 2.6 293 P3-1 82 10.5 10 A15-1 83 0.7 90 El-3 84 1.1 80 E2-1 85 H1-2 0.9 150 5.9 100 86 E6-1 87 M15-2 13.6 253 0.5 65 88 D1-3 72 1,2 5 A2-1 6.7 293 76 P7-1 77 K15-2 12.8 208 9 7 A15-2 14.2 2,3 104 78 F3-1 1.1 93 79 E2-2 10.3 12 89 B15-1 0.4 95 2 El-2 12.4 329 55 R15-2 117 91 F1-1 0.5 J2-2 1.5 178 90 A4-1 3,3 10 93 1.3 252 94 M2-2 N2-2 1.3 265 95 H1-3 0.7 150 96 1.

I-71 2098c

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

THI Radiological Controls Departenental Procedure 6610-PLN-4200.01 Revision No.

Title 0

Of f mite Dose Cgeg,t ten Manual (ODCM) ,

ttAP 7.1

'N "" N i s a . e. , e 3

ts Y \

\a, ll n. ,, /

,x ste;s ,

, a

\ " s

\ Qk i ',, e s e..s Mtway \

')

s

\ koda wo C

/

Jesj,N [4 t -

,\ JM *M,"s * !

,is.fs

( 00sjMoon /

i

/ N '

v.* / 0 t e ,5

!p ;

k. '

ou p.

<o rs % - .I10,

~ g'u M ij M

/ c s u SMtgity I O

C..h, ,

p ,,,, , ,

"' \

h'/,{a\ F j

w /T E y LE

\

ty" I4

\ \ * *#0 tis.,s F / ,,,

n '\

}

N' s t., N y ,,,. ,,

\

I \ \ \' \m

\\/ \br y "r' ..J,, l

% I i

\

THRtt M!Lt !$(Ac sv;ttAt stA7:es LO;AT!Dh5 0F RA0!OLOGl:AL l' V!RCWINTAL MONITOR!hG PROGRAM STAT 10hs wlTHlh ! MILE OF THE SITE MAP 7.1 TIGLEE MILE ISLAND !!UCLE V. STATION LOCATICHS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 1 MILE OF THE SITE I-72 209se

l TM1 Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision FO.

Title offsite Dose calculation Manual (ODCH)

MAP 7.2 y

a * ;

x s ....

'N '

... ..[7_

'N

\

N"' lA

/' 'Nt h {

K

( ,,

i ,,1 z x " n .. ..

, 1 w ^4 @#TFl'N

/ , Nj \

A M,

g 6 0 h,0,0,h t t # # f x

i,

.4,

/ s p w ?! *

,'/s I. ,"* / '

l n -

, 1s . ,

/e '

I i f}

': f 8

'W@ @A , ,,

i

.:g.R\'g.g,q% /,,,---

\ / /

j

. .. . r

,N x .,ItP',,,,, , .,-

,/

x, w 1 x x ,0

~..

\, f; ;X.n ,

..a.

..t ..

'Q \

i i

THRit M!Lt !$ LAND I4UCLEAR STATION ,

LO:AT!0h5 or RADIOLOGICAL ttivlRONMthTAL MONITOR!t4G PROGRAM

$TATION5 w!THlh 5 MILT $ OF THE $1TE ,

HAP ?.7 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL EINIRONMENTAL HONITORING PROGRAM STATIONS WITHIN 5 MILES OF THE SITE I-73 2098c

. . . . S l .

Ir L)] Nuclear THI Radiological Controle Departmental Procedure 6610-Pt.N-4200.01 (

t Revision No.

76tle

(

0 Offeite Doce calculatten Manual (ODCH) i MAP 7.3 l

I t

.. . .=

, e N l f - == A I

! \ \ _

N ll r\ ' .,

.?b[ /_ .U.,'t_\

I "'!?'"'

/

'5=

\ ! 2

'!.* \ -

ma s

oN %~ -xsp .. _.

-+==

( n & ~

so

\

y \

' 8

u

, h wi ee.

%W\-.'2.QjW / &

, 1

/ "'

i a-- /* /.- ,J' / """~ ,

rw+

/Q\ '

\ ,f,, l

.s* N i k s. \ Q n ..

== , n THRit MILI ltLAND NUCLI AR STATION LOCATIONS OF RADIOLOG!tAL INylRONMENTAL MONITORING FROGRAM STATIONS GREATER THAN 5 MILT $ FROM THE $1Tt l

HAP 7.3 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM STATIONS GREATER THAN 5 MILES TROM THE SITE I-74 209Be j

THI Radiological Controls Depertmental Procedure 6610-PLN-4200.01 Revisten No.

Title 0

Offsite Dose Calculation Manual (ODCM)

APPENDIX A P - PATifWAY DOSE RATE PARAKETER (EQ A-1)

P (Lnhalation) = k' g (BR) DFA3 Where P3 = the pathway dose rate parameter for radionuclide,1, (other than noble gasca) for the inhalation pathway, in mrom/yr per microcurie /m#. Thw does factors are based on the critical individual organ for the infant age group.

k' = conversion factor, lE6 pC1/ microcurie RR = 1400 m /yr, breathing rate f or inf ant (Ref . 2, Table E-5) 3 DFA3 = the maximum organ inhalation dose factor for the infant age group for the ith radionuclide (nRem/pci). Values are taken from Table E-10. Reg.

Guide 1.109 (Ref. 2).

Resolution of the units yields: (Table 4.5)

(Eq A-2)

P3 (Lnnalation) = 1.4E9 DFA3 (mrom/yr ger pC1/m )

3 NOTE: 'the lateDt KRC Guidance has deleted the requirement te determine P (ground plane) and P3 (food). In addition, 3

the critical age group has been changed f rom inf ant to child. However, Tech. Spec. 3.22.2.1 currently states inf ant as the critical age group.

I-75 2098c

[e L'J1 Nuclear THI Radiological controls Departrnental Procedure 6610-PLN-4200.01 Revision No.

Title 0

Of f site Dese Calculation Manual (ODCM)

APPENDIX B Ri - TN}tA1.ATION PATHWAY DOSE FACTOR (aram/yr per microcurie /m3 ) (Eq B-1)

R3 = k' (BR) (DFA 3 ,,,,)

Whores k' = .tonversion f actor,1E6 p01/ microcurie 3

ER = breathing rate, 1400, 3700, 8000, 8'J00 m /yr for inf ant, child, teenager, and adult age groups, respw+.ively. (Ref. 2, Table E-5)

D FAg ,,,, = the inhalation dose factor for organ, o, of the receptor of a given age group, a, and for the ith radionuclide, in mrom/pci. The total body is considered as an organ in the selection of DFA ,,,. Values are taken 3 from Tables E-7 through E-10, Reg. Guide 1.109 (Ref. 2).

Resolutions of the units yieldet R1 = (1.4E9) (DFA 3 ,,,,) intant (Table 5.2.1)

R1 * (3.7E9) (DFA 3 ,,,,) chlid (Table 5.2.2)

R1 = (8.0E9) (DFA 3 ,,,,) teen and adult (Tables 5.2.3 and 5.2.4)

I-76 2098c

TH1 Radiological Controle Departn+ntal Procedure 6610-PLN-4200.01 Revision No.

Title 0

Offeite Doce Calcult. tion Mk1,al_(ODCM)

APPENDIX C pl - GROUND PLANE FATHWAY DOSE FActoh R, o k' k" (SF) (DF0 ) ((l** *l')/At l 3

Wherst k' = conversion f actor,1E6 p0L/ microcurie k" = conversion **eter, 8760 hr/yr l

i a decov constant fe the 1" radionuclide, sec 'I t a the expos.** tlaie (thie calculation assumes that decay le the only operating removal rocenar'.am; d. 73 x 10' ecc. (15 yre), Reg. Guide 1.109, Appendix C DF03

the ground plane dose conversion f actor f or the ith radionuclide (mrom/hr per pci/m ) . Values are taken f rom Table E-6, Reg. Guide 1.109 (Ref. 2).

8 These values apply to all 40e Croups.

SF = 0.7, chielding factor, from Table E-15 Reg. Guide 1.109 (Ref. 2)

Reierence Table 6.3.1 g.99 209Be

THI Radiological Controls Departroental Procedure .

6610-PLN-4200.01 Revision No.

Title 0

Offsite Dose Calculation Manual (ODCM)

APPENDIX D Ri - GRASS COW-M!t.F PATHWAY DOSE FACTOR x (r) x (DFL x R se k' ( (Q, x Uo) / (kg + A,) ) x ( F.) A 'h) /Y ] e4 1*g,,,,)

3 f (Eq D-1)

[((f, a f )/Yp ) + ((1-f a f,) e

i p Whoren k' = conversion factor, 1E6 picoeurie/ microcurie (pci/pci)

Q, = cow consumption rate, 50 kg/ day, (Reg. Guide 1.109) coat consumption rate, 6 kg/ day, (Reg. Guide 1.109, Ta,blo E*2)

Un = Receptor's milk consumption rate; 330, 330, 400, 310 lite)rs/yr for infant, child, teenager, and adult age groups, respectivo1y (Reg.

, Guide 1.109) 2 Y, = agricultural productivity by unit area of paature feed grass, 0.7 kJ/m (NUREG-0133) 2 Y, = agricultural produJtivity by unit area of etored feed, 2.0 kg/m (NUREG-0133)

F, a stable element transfer coefficient (Table E-1, neg. Guide A.109) r = fraction of deposited activity retained in cow's f eed grase. 0.2 f or particulates, 1.0 for radiciodine (Table E-15, Reg. Guide 1.109)

D FL 3 ,,,, =

the ingestion dose factor for organ, o, and the ith radionuclido for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109) 13 = decay constant fo', the ith radionuclide, sec'1 1, = decay constant f or weathering, 5.73 x 10 sec'l (NUREG-0133); dated on a 14 day half life t-g

= 1.73 x 10 5 sec, the transport time f rom pasture to cew to milk to receptor (Table E-15, Reg. Cuide 1.109), or 2 days t, = 7.78 x 10' see, the transport time f rom pasture to harvest to cow to milk to receptor (Table E-15, Reg. Quide 1.109), or 90 days fp = 1.0, the fraction of the year that the cow is on pasture q f, = 1.0, the f raction of the cow feed that is pacture grass while the cow is on pasture I-78 2096c

?

~ w us 4 v THI Radiological Controle Departmental Procedur,e 6610-PLN-4200.01 Title Revisto! No.

0 Offsite Dese calculation Manual ( OM4)_

EPENDIX D (Cont'd)

The concentration of tritium in milk is based on the cirborno concentration rather than ths deposition. Therefore, P3 is baasd on (X/Qin (Eq D-2)

U R g ,,,, a It'k F, Q, Un9FLg ,,,, ( .75 [ .5/H))

Wh res k = 1E3 grama/Xg U = 8 grame/m), absolate humidity of the atmosphere

.75 = fraction of the total feed grace mass that is water

.h = ratio of the specific activity cf the feed grase water to the atmospheric water (NUREG-013.1)

DFLg ,,,,= the ingestion dose dactor for tritium and organ, o, f or each respective age group, a (Tables 1-11 to E-14, Reg. Ouide 1.109)

All other paraanters and values are as given above.

--..-.............................----......-------~~...------.....-....

NOTE: coat-milk pat'away f actnr, R , wil( be computed using the 3

cow-milk pathway factor equation. F, factor for goat-milk will be from Table E-2 Reg. Guide 1.109. ,

e R0ference: Tablae 5.4.1-5, 5.5.1-4 k

I *19 2098:

- ~ _ _ _ - _ _ _ _ _ - - - _

TM1 Radiological Controls Departmental Procedure 6610-PtN-4200.01 Adv1Plon No.

Title 0

, _o g y Dose Calcui g,4 M anual_l0DCH) ..,,,.

APPENDIX E Ri - tTW KltT PATHWAY DOSE FACTOR R3= k' l (0, x Uu) / (kg+ 1,) ) : (1-J )hl/Y,) x (r) x (DFL ,,,,)

i x

[((f', u f )/Yp ) + ((1*fp f.) e a e dl*f (E9 E*l)

Wheren k' = cu. tactor, i 6 picoeurie/ microcurie (pci/pci)

Q, = cow consumptiLn rate, 50 kg/doy, (Reg. Guide 1.109)

Un = Receptor's meat consumption rate 0, 41, 66, 110 kg/yr for infane, mila, teenager, and adult age groups, respectively (heg. Guide 1Mb F, a the stable ei.unent f ransf er coef ficients, days /kg (Table E-1, Reg.

Guide 1.109) r = f ractica of depo' ated a tvity retained in cow's f eed grass, 0.2 for partientates, 1.0 !ct rt ( Lolodine (Table E-15, Reg. Guide 1.109)

DFL,,,

t

= the ingeor.Lon dose f actc> for organ, o, and the ith radionuclide for each respective age oro ip, n (Tables E-11 to E-14, Reg. Guide 1.109) 1 3

= decay constant for the radionuclide 1, sec'1 1, a decay constant f r. weathering, 5.73 n 10*' sec*l (NUREG-0133), based on a 14 day half lif's tg = 1. 7 3 x 3 4' JQ, s wa transport tin.e f rom pasture to receptor (NUREG-0133) t, = 7.77 x 10' nec, the o-annert tirae trom nop to receptor (NUREG-0133)

Y, = ag':Lculturn productivit v by unP rea of pasture feed grass, 0.7 kg/m 3 (NI!R) G-0133 )

Y, a age tcultural productivity ty o % ares of stored feed, 2.0 kg/m 3 (Nmt?.G-0133 )

fp u 1.0, the fraction of the year t!iat the cow is on pasture f, a 1.C, the f raction of the cow feed - at is paMure grass while the cow is on paature I-80 209 dt.

we .

TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

T t 41'e 0

Offeite Dome calculation Manual (ODCM)

APPENDIX E (Cont'd) k Th2 concentration of tritium in meat is based on the airborne concentration rather than the deposition. Therefore, Ri is based on (X/Q):

(Eq E-2)

Rs ,,,, = k ' k ' ' ' Fr Qr D u (DrLg,,3,) x 0.75 x (0.5/H))

Wh3 ret All terme are as defined above and in Appendix D.

R2ference: Tables 5.6.1-4 I-83 2098c

u TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

Title O

Offsite Done Calculation Manual (ODCM)

APPENDIX F Ri

VEGETATION PATHWAY DOSE FACTOR k,)) ) x (DFL ,,,,) x ( (U'a) f 5 e d i'L + U 5 fee'l ti h) 8 (Eq F-1)

R3= k' x (r/ (Y, (lg 4 i _

Wh:res k' = 1E6 picoeurie/ microcurie (pC1/pci)

D'a

= the consumption rate of fresh leafy vegetation, 0, 26, 42, 64 kg/yr for infant, child, teenager, or adult age groups, respectively (Reg.

Guide 1.109) 0, 4 = the consumption rate ot otored vegetation, 0, 520, 630, 520 kg/yr for infant, child, teenager, or adult age groupe respectively (Reg.

Guide 1.109) fg a the traction of the annual intake of fresh leafy vegetation grown locally, = 1.0 (NUREG-0133) f,

= the fraction of the stored vegetation grown locally = 0.76 (NUREG-0133) tg = the average time between harvest of leafy vegetation and its consumption, 8.6 x 10' secondo (Table E-15, Reg. Guide 1.109 (24 hre)]

t, = the average time between harvest of stored leafy vegetation and its censumption, 5.18 x 10' seconds, (Table E-15, Reg. Guide 1.109 (60 days))

y, = the vegetation area density, 2.0 kg/m 3 (Table E-15, Reg. Guide 1.109)

All other parameters are as previously defined.

The concentration of tritium in vegetation le based on the airborne concentration rather thiin the deposition. Therefore, R is based on-(X/Q) 3 R. ,,,,, = k ' k ' ' ' [U L

f,) (DFL g ,,,,) - ( .75 ( .5/H]) - (Eq F-2) g f3 + Ua g

'4here s >

All termo are as definec above and in Appendix D.

Reference:

Tables 5.7.1-4 I-82 2098c

TMI Radiological Controls Departmental Procedure 6610 PLN-4200.01 Revision No.

Tatle 0

Offeite Dose Calculation Manuni (ODCM) ,,

APPENDIX A-F REFERENCES (Page 1 of 4)

PARAMETERS USED IN DOSE FACTOR CALCULATIONS v

Origin of Value Parameter Value Table in Section of Site-R.C. 1.109 _NUREG-0133 specific

*

For P, * *

DFA. Each radionuclide E-9 Note 1 BR I 1400 m 3 /yr (inf ant) E-5

- - For R1 (Vegetation)***

r Each element type E-1 Y.m 2.0 kg/m2 E-15 kw 5.73 E-7 sec t 5.3.1.3 DFL 3 Each age group and E-11 thru radionuclide E-14 Note 1 U,L Each ace group E-5

f. 1.0 5.3.1.5 ---

t. 8.6 E + 4 seconde E-15 U ,s Each age group E-5 f, 0.76 5.3.1.5 t, 5.18 E + 6 seconds E-15 H 8.0 grame/kg 5.2.1.3 m

- - For Ri (Inhalation)***

BR Each age group E-5 DFA 3 Each age group and E-7 thru nuclide E=10 Note 1 I-83 2098c l

THI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

V6tle 0

Of f site Does calculation Manual (ODCM)

APPENDIX A-F REFERENCES (Page 2 of 4)

PARM .TERS USED IN DOSE FACTOR CALCULATIONS Origin of Value Value Table in Section of Site-Parameter R.G. 1.109 NUREG-0133 specific

- - *or R (Ground 3

Plane) ***

SP 0.7 E-15 DFG, Each radionuclide E-6 t 4.73 E + 8 see 5.3.1.2

- - For R1 (Grame/ Animal / Meat)

Q,< cow) 50 kg/ day E-3 6 kg/ day E-3 Ref. Only Q, (Coat)

U., Each age croup E-5 kW 5.73 E-7 sec l 5.3.1.3 F, (Both) Each element E-1 r Each ,alement type E-15 ,,

DFL t Each age group and E-11 thru nuclido E-14 Note 1

f. 1.0 5.3.1.3 No,te 2 1.0 5.3.1.3 Note 2 f.

Y, 0.7 kg/m 3 E-15 ts 7.78 E + 6 see E-15 Y. 2.0 kg/m2 E-15

t. 1.73 E + 6 see E-15 H 8.0 grams /kg 5.2.1.3 I-84 2098c

TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

Title 0

Of f eite Doso Calculation Manual (ODCM)

APPENDIX A-F REFERENCES (Page 3 of 4)

PARAMETERS USED IN DOSE FACTOR CALCULATIONS Origin of Value Table in Section of Site-Parameter Value specific R.G. 1.109 _ NUREG-0133

- - For Rg (cranc/ cow / Milk) ***

Q, 50 kg/ day E-3 U., Each age group E-5 iw 5.73 E-7 soc i 5.3.1.3 F. Each element E-1 r Each element type E-15 DFL 1 ' Each age group and E-11 thru nuclide E-14 Note 1 Y, 0.7 kg/m2 E-15 t, 7.78 E + 6 see E-15 Y. 2.0 kg/m2 E-15 t, 1.73 E + 5 eec E-15 f, 1.0 5.3.1.3 1.0 5.3.1.3 f.

H B.O orame/ka 5.2.1.3 I-BS 2098c 1

- - _ - - ~ _ - - - _ _ - _ _ _ _ - _ _ _ _

l 'e L'dlNuclear TMI Radiological Controle Departmental Procedure 6610-PLN-4200.01 Revision No.

Ti%1e O

Offsite Dose calculation Manual (ODCM) ,,

APPENDIK A-F REFERENCES (Page 4 of 4)

NOTES For

1. Inhalation and ingestion dose factors were taken from the indicated source.

each age group, for each nuclide, the organ dose factor used was the highast dose f actor for that nuclide and age group in the ref erenced table.

Annual land surveys have

3. Typically beef cattle are raised all year on pasture.

indicated that the small number of goats raised within 5 miles typically are used for grues control and not food or milk. Nevertheless, the goats can be treated as full meat sources where present, despite the fact that their numbers cannot sustain the meat consumption rates of Tabla E-5 of Reference 3.

\

I-86 2098c

e c

TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No.

TAtle 0

__ offsite Dose calculation Manual (ODCM)

References

1. Boegli, J.S., W.L. Britz, R.R. Bellamy, and R.L. Waterfield, " Preparation of Radiological Ef fluent Technical Specifications for Nuclear Power Plants".

NUREG-0133. October 1978.

8. " Calculation of Annual Doses to Man frna Poutine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I". U.S. MRC Regulatory Guide 1.109 (Rev 1). October 1977.

3. " Evaluation of the Three M14e Island Nuclear Station Unit 1 to Demonstrate Conf ormance to the Desiga objectives of 10 CFR 50, Appendix I". . . Nuclear Safety Associates. May 19765

4. Technical Specification for the Three Mile Island Nuclear Generating Station Unit 1, Amendment No. 72, Operating License No. DPR-50, Docket No. 50-289. August 1981.

5. NUREG -0017, PB-251 718, " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Ef fluents f rom PRR", Revision 1, 1985.

6. G.R. Hoenee, J.K. Soldat, " Age-Specific Radiation Dose Commitment Factors For A one-Year Chronic Intake". NUREG - 0172. November 1977. Regulator Guide 1.109 Supplement.

7. "Environn. ental Radiation Dosee From Difficult-To-Measure Nuclidos", EPRI NT-3840, RP 1560-3 Final Report January 1985.

8. Meteoro)ogical Information and Doce Assessment System (MIDAS)

9. TMI Recirculation Factor Memos, April 12, 1988, and March 17, 1988

10. Operationo Procedures 1101-2.1, Radiation Monitor Set Points al. Simplified Environmental Ef fluent Dosimetry System (EEEDS)

12. Reg. Gute.e 1.21

13. Reg. ',uide 1.111

14. Reg. Guide 1.112

15. Reg. Guide 1.113 I-87 2098c

- - _ - _ - _ _

ML20070U924

Text

Reference:

Navigation menu

Search