ML17213B196

Rev 2 to Offsite Dose Calculation Manual

ML17213B196
Person / Time
Site:	Saint Lucie
Issue date:	03/28/1983
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17213B195	List: L-83-185, Forwards Rev 2 to Offsite Dose Calculation Manual ML17213B196
References
PROC-830328, NUDOCS 8303300254
Download: ML17213B196 (151)

Text

FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT OFFSITE DOSE CALCULATIONMANUAL Poa ssosioo 50oMs p

Revision 2 March 28, l983

7LORZDA POWER

~ XGKT. CO.f2AHY ST ~

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lPo 1

F TA3L"- OP CGN:='.iTS St

~

uc a

P ant Offsite Dose Cal "'t on..anua ocuc"'n Glossa g

1.0 Rad"'oac"'ve Releases of Liquid "=ffluents 1,1

~ 2 1.3

'1. 5 Liqu'd "-ffluent 4fodel Ass~~otions Dete.

='n."g the : act'on

(:-) of 0C:R20 NPC L'-'ts for Radioactive Liquid Re'eases Dete =ining Setpoints for Rad'oactive 'ou'c E =luent 'Aonitors Deteraining the Dose fr m Radioactive L'qu'd c.ffluents P

o J ect ng Dose For Radioac

've Lioui d

~f 1}

'6 2.0

~ Rad"'oact've Re eases of Gaseous

"=ffluents 2.1 2.2

.Gaseous

"-ffluent Mode Deter~ining

=he Total

=or iso'61 Gas Relea,se

=or ".ffluent i~!onitors Dete~ining th Rad'o To Any Organ From Zns Assuapt ons Body ai:d Sk'~ Dose Rat s

~

s anc

=5 ao1'n'ng bet'ooxnts DiSCUSSi01 iodin and Partic late Dose P.ata, tantaneous Gaseous Re<eases---------

17 "3

Z3

2. 3.'

3e 2

2. 3.3 3

/,

Z.3.5 Tnha'at Grourd Plane

.-1 i Trit<<U.il Total Dose R"te bv Ra'ease Source 25 o

2S 29 31 2 ~

2 5

De e~ining Radioac 've De e~ining Rad'oactive the Gar;a A'r Dose for Moo}.2 Gase Relaases the Beta A"'r Dose for Noole Gase Re eases 32 r

~ o Dete~ n'ng the Pad'oicdin and 'Part'c 'ate Dose To

&my Crgan

":roe.

C -.u'at've Releases O'ZSCJSS:Oil 7

ST:UC:"" PLAVZ

-ODC:!

o p go T "ig l ~ OP C~qT~qgS 2.6 (cont,)

2 ac

~

2o6o 2

~ 0

~

2.6.

2+6o 2o 7 Pro) inhalation 2

'Ground =lane

.~ITritium dose

( <ll Pathways) 5

.Total Organ Dose ecting Dose ".or Radioactive Gaseous 42 4g

$.0 40 O'R 190 Dose "-valuation.

4.0 Semiannual Report format 46 Appendix Appendix 3-Append'x C-Appendix D-Appendix AppeQdix F

MPC, Dose Factor and Historical Meteorological Ta'oles 57 Limited Analysis Dose 4,ssessment for Liauid Radioactive Zffluents 80 Technical Bases for

~ ffective Dose Factors Technical Bases for Eliminating Cu='e inventory Limit for Gaseous "las.e Storage Ta~s Current R.-.M.

Sample Point l ocation

.'~lap for Sts-A '5/4

~ i2 Descriptioa of Meteoroligical Dispersion Formulas Utilized for Historical Data and Nethodology for Determining Actual Net Data ST LUCT" PLAZA

-ODCN

Page 3

I;1TRODUCTIOH This manual provides the methodology to calculate radiation dose, to individuals in the vicinity or the St. i.ucie s't, fro. radio-act've gaseous and l'quid ef="uents.

It also provides methocology for calcu'ating e"fluent monitor setponts and al'owable release rates to ensure compliance with the STS and 10C:R20 release cr'itera.

The 'n-plant procedures specify what sections of the ODCN shoula be completed to calculate the dose to an individual.

The ODC1 :ollows, the methodolooy and models suggested by NlcZG-0133 (iNov 1978) and Regulato y Guide 1.109.

Simplifying assumptions.

have been applied where applicable to provide a more workable document for implementing the Technical Spec'='cation requi.rements.

Alternate calculation methods may be used from.those presented as long as the overal'ethodology does not change or as long as the alt rnative methods provide results that are more limiting.

Also, as available, the most up-to-date revision of th

..egulatory Guide 1.109 cose corversion factors and environmental t-.ansfer factors may be subst'tuted for those currently included and used in this document.

S:

LUC

- PLNT DC~i.

I 11

GLOSSARY Or CO?FOl<

T:-R:-!S Page cose (dose race) from Baca rad'ac'on cuo ic c en cime r e C'uries - a uni" oz radioactiv"'cy see

~Ci C

~i activity'"'or concentrat on of a nuclide in the release source.

Units of pCi, pCi/cc, or pCi/ml Code of E'ederal Regulations Dose The exposure, in mrem or mrad, the organ or the ind'v'd al receives from radioactive erfluents.

Dose Factor

Normally, a factor that conve ts the effect of ingesting radioactive material into the body, to dose to a specific organ.

Body elimination, radioactive decay, and organ uptake are some of che factors that dete~ine a dose factor for a given nuclide.

Dose Pathway - A specif 'c path that radioact ve material phys'cally travels through prior to e:cposing an individual to rad'ation.

The Grass-Cow-Miilk-Infant is a dose path-way.

Dose Rate The dose received pe" unit time.

(D/Q) a long term D over Q

a factor with units of 1/H wh'ch describes the deposition of particulate matter from a plume at a po'nc downrange from the source.

ic can be thought of as

-hac part of the cloud is going to fa'lout and deposit ove>>

one square meter of ground.

(See Appendiz P).

Gamma g

a gama photon the dose

=rom Carr.as in a'r et,c.

Ground Plane Rad'oactive marer.al deposited nifor ly over che ground emits radiation that produces an o"posure. pathway when an individual is sanding, sitting, etc. in rhe area.,

Et is assumed that an adu't receives the same ezposure as an infant, regarcless of the pnysical height d'erences.

Only the total body is cons'dered ror the ODD!.

H-3hydrogen-3, or Trit um, a

weak Beta em'tter.

E&8DP Radioiodines ard particulates w.th half-lives greater than 8 days Limiting condition for operation in STS cubic mete s

m2 square meters ST.

LUC-"-

P~~NT

- ODC.'!

Pace C

.'!~<=.um? armissible Concentrab 'on nucl'e o

he purposes of 'is manna '

radioac

~

2 iso ripe.

nuclide () signifies a 5pecif c nuclide

=he 'st 2nd) "rd one nce" consideration.

if nuclide (i) is '-l~'.:

~hen the Hi,dose factor) under cons.derat'on shoulc be ':!-.-.

=.or

'l

" example.

Organ Q.

For

='."'.e ODQf either the bone, l'ver, thy".o'd, kidney, 'ung',

Gl-LLX, or the T. Body,.

T. Body (Total Body) is cons.'de ed an organ for ease of writing the methodology i the ODC!.

Qi dotted Denotes a re'ease rate in gCi/sec

=or nuclide(c~.f,.

Denotes pCi of nuclide (i) re'eased ove" a specizied ti.e interval.

1 Receptor - The 'nd'vidual receiv.'ng the exposure in a g"ven location.

or who ingests food products "rom a animal for example.

A'eceptor can receive dose from one or more oathways.

Release Source(s)

A subsystem, tank, or vent where radioactive material can be released independently of other

,rad'oact've release points STS

The St. Lucie Plant Standard Techn'cal Spec'zcat ons pCi micro-Curies. l ~pCi = 10 Curies.

The pCi is the standard un' of radioactivity =or all cose calculatioys.in the ODCN.

(X/Q) a lo..g ierm Chi over Q.

"" descr.'bes the physical dispersion chare ter.'sties oz a se.'-'"z'..ite cloud oz nobl gases as the cloud t=averses downrange f"om the release point.

Since noble Gases are inert, tney do no tend to sett' out on the g o nd.

~ (See Appendix P).

(v/Q)D a long term Depleted Chi ove" Q. It descr'"oes the physical d'spersion characteristics of a se '-'nzinite cloud oz rad"'oac=ive ioc nes and part'culates as the cloud travels downrange.

S'nce Eodines and particulates tend to settle out (fall'out of the cloud) on the ground, t'h e

~X(

)D represents, what phys'cally emains of the clo'ud and its d'spers.'on qua 'ties at a driven location downrange from the release point.

(See Appendix F).

1.0LZ~JiDRELEASES METHODOLOGY

Radioactive L ou d 5 fluent ~!odel Assumntions The

"=S~R conta='ss the or" c'al descr'pc"'on o" t..e site char-acte >>sties.

The description

"'."."" =o laws 's a, br.'e=

summary for dose cz culation purposes:

The St.

Luc.'e Plant is located on an 'sland surrounded on cwo s'des by the Atlantic Ocean -,and the ind"'an River, an estuary of the A.tlant'c Ocean.

Nornally, all rad'oact've liqu d re-leases enter the Atlantic Ocean whe e che Circulat'.g ',v'acer Discharge Pipe tewinates on the ocean loo-zt a pow~t approx-imately 1200.feet of shore.

No.cred't

's tzken for subsequent m'zing or che discharge f"ume with che ocean.

he ci==nsion of radioaccive macerial into the ocean 's dependent on the cond'ions of, tide, wind, znd some eddy c rrents caused by the Gulf Stream.

The condit ons a

e surficiently random enough to dist ibute the discharges over a wide area and no concentrating ef=ects are assumed.

There are no direct discharge pa.chs for liqu d ef luents to e.'ther of the north or south p ivate proper"y boundary lines.

The Big Mud Creek (part of the indian R've ) does connect to a norm"lly locked shut dam, that is intended to provide an emergency supply of circulating water to che intake Cooling

'Pater Canal 'n the event a Hu icane causes blockage of the intake Canal.

Ho radioactive ware could be d scharged di-rectly into the intake Cooling Mater Canal because all p'anc piping is routed to the discharge canal and no back flow can occ ".

Consult the

"=SP2. for a detailed descr'pt'on of char-acteristics or the water booies

~ surround'ng t'e j an".site.

Only those nuc'ides that appear in the Liquid Dose

"-acto".

Tables will be cons'dered for dose czlc lzcion.

De"asinine the eraction

'2 of 10CPR20

~PC Limits, for A Licuid Re3.ease Sourc Discussion

- Technical Soeci 'cation 3.11.1.1 requ'res chat the samp ing and 'analysis results o= liquid waste. (prior to,disc..arge) be used w th calculation, mechods

~ 'n the in-plant proc du=es to assur chat the concent=ac'on of 1'cu'd rad'oact've material in the unrestricted areas wil'ot evceed t'e conc ntrat'ons spec. "ied in 10 CH, 20, Append'v 3, Table i.i.

Th's section pr sents che calc la"'on mechcd to 'oe used

=or ch's determinat-on.

Th's method o..ly addresses the calculation for

a. specific release source.

The in-plant procedures will prov'ce insc=uctions

="or determining that the summation or each release source'

" values do not exceed the s.'te's 10 C:-R 20 i!PC 1imic.

he values for release

~ race, d'ut'on rate, etc will also

'nave to be obt ined from in-plant orocedures.

The basic eouat-'on is:

Dago 3

1.2

{cont)

Where:

= "ae fract"'on of 10CH20 9C source "as d'scharged under chac woula result i= "he re

~ ease the conditions specixied.

The unduced release xate in gpm of the release source.

Liquid Rad Waste

~

gpm

~ 170 Steam Generator

125gpm/Steam Genexator D

The dilution flow in gpm of intake Cooling Water ox Circulating Water Pumps.

Incake Cooling flow is 14,500 gpm/pump Circulating Wat.er flow is 121,000 gpm/pump C

= The undiluted concentration ox nuclid

{ )

e {i) in C'/ml from sample assay.

(MC).

~ The maximum pe~~ssible concentration of nuc3.ide (i) in Ci/ml from Table L-1.

For dissolved or entrained n

lp noble gases the HPC value is 2 x 10, 0

Ci/ml for the sum ox all gases.

o of the 10 CFR 20 YPC limit may be determined by The traction of t e

for u

oses of simplifying a nuclide-by-nuclide evaluation or for purposes o

s'he calculation by a cumulative activityt evaluation.

Xf the simplifiea method is used, che value of 3 x 10

~ Ci/ml

{un'de tixied NPC value) should be substituted for (.

).

• ,.PC f all ident,ixied and the cumulative concentration

<sum of a i en radionuclide concentrations) or the gross concentration snoula be substi te or s

n d f C

As long as che diluted concentration 1<< 'e-b (C

.-) is less ban 3 x 10 pCi/ml, che nuc ide-y-nucx~ce calculac'on is no r'

ce t required co demonscxace compl'iance he 10 CrR 20 WC limit.

The following'section prov'aes a step-by-step procedure for determining t<<e;

1. 2. 1 Ca3.cu3.at'on Process for Sol" ds 1.2.1.1 Obcain from cne in-plane procedures, the re ease rate value (R) in gpm fox the'elease source.

1.2.1.2 Obtain from che in-plant procedures, the d'lut 'on rate (D) in gpm.

No credit is taken

=or any dilution beyond the discharge canal flow.

1.2.1.3 Obcain (C.),

che undiluc'ed assay value of nuclide (i) ki/ml. if the simpli <<ed mechoa

<<s i)~

n 4 i m

~

(c

)

used, tne cumulative concencrat"'on is used.

1.2.1.4 5'rom Table L-1, for nuc$ ide (i) 3 x 10 ipCi/ml f'ed method.

obtain the corresponding

{K2C).

in pCi/ml, The value oz snou3.d be used

=or the simpli-1.2.1.5 Divide C

bv

(~PC)<<

and write down che c<< ot=enc.

ST.

LUCK= PLA

<<T

-ODW

Page 1.2 (Cont)

1. 2. 1 (cont) one swnx'c method s used, oz-cae<

the next steo.

T.= dete~ining the

~PC -rect=on by the nuc'ide-by-nuclide evaluation, repeat steps

1. 2.1.3 through 1.2.1.5:or each nuclide reported

'n the assay, fo-H ~from previous month compos'te, and for SR89/90 and

":e55 from previous quarter com-posite.

Add each C./(K'C) quot.'ent from step 1.2.1.5 and solve

~oz c

P a unit-less value where:

L the value of could be

< or >i.

The pur-L pose of the ca~culation is to determine what the initial va'ue of

~s foz a given set of release conditions.

lr is >'1, adm'nistrative steps are taken to ensure that the actual release conditions oz di'ution will ensure that FLis 1 during the actual zelease.

L is called the fraction of 10CH20 HC because it should

-p'ever be allowed to be >1.

1.2.2 Calculat'on Process for Gases n rLiquid 1.2.1.1 Sum the uCi/ml of eacn no'ole gas act'vity reported in the re'ease.

1.2.1.2 1.2.1.3 The values of 3, and D from 1.2.1 above shall be used in the calculat'ons below:

(sun of 1.2. 1.1) uCi/ml R

g D

-Ci 7

shall be less than 2 x 10 uCi/M for g

the site for all releases in pzogress.

-"ach zelease point w 11 be acmin'st atively controlled.

Consul" in-plant procedures for ins true tions.

ST Li.'CI. PLAIT

-ODC.'i

I

Page 0

1.3 DetermininR Set@pints for Radioact've Licuid ='fluent.'!o.".'itors Disc ssion

- Techn'cal Spec'=

c -'on 3.3.3.8 reo ires

=ha.c

~'qu'd effluent monitoring instrumentation alarm/t"ip setpo'..=s be set to 'n" tiate an ala m or trio so lpga ~

~he radioactivity concentration in water in the unrestricted area Goes L'o't exceed the concent" t on of.10. C:-R 20> Appendix B, Tabl.e as a result of radioactivity in 'iquid effluents (Technical Speci='cation 3.11.1.1).

This section presents the method to be used

=or determiniIlf, ~~e ins ~rum axa~ion se ~yoin~s.

Gross cpm vs total liquid activ'ty curves are available or Liquid E luent ~~1onitors based on a composi" e o= real re'ease data.

A d'rect correlation between gross cpm a..d the concentrations that wou'd achieve 10 CR.

20 HPC levels in the discharge canal can be estimated.

The 1978 liquid release

data, rom sem'annual reports was used to determine the average undiluted release concentration.

These concentrations were then projected to a diluted concentration in the discharge cane,l.

assum'ng a

1 gpm release rate and a constant d.'lut.'on flow of 121,000 gpm from 1 c'rc water pump.

Tnis diluted activ'ty was d.'vided by the nuc'ide's respect've 10C.=320

'APC value (Table L-1) to obtain the Hi column on the taole that follows.

Table 1.3 r GLIDE SYMBOL 1978 UbDILUTED Cijm11 M.i (no units)

I-131 4.43 E-5

1. 22 E-3 I-132 I-'133

2. 23 E-7 3.17 E-6 2.30 E-7 2.62 E-5 I-135 Na-24 Cr-51 1.31 E-6 1.72 E-7 2.51 E-5 2.71.E-6 4.74 E-8 1 '4 E-7 Nn-54 5.64 E-6 4.66 E-7

~i'-56 Co-57 1.11 E-9 3.69 E-7

9. 17 E-11 7.62 E-9 Co-58 1.51 E-4 1,39 E-5 c9 2.92 E-6 83 ".-7 ST LUr-..P~~bT 'ODC:]

'LLUCL:DE S'~ BOL Table 3 (co~t) 1978 UHD:LUTED

~C1./nl 1.

(no ur ts)

Co-60 Zn-65 Ni-65 Ag-i lorn SG-113 Sb-122 Sb-124 V>>187 Hp-239 Br-82 3 ~ 60 E-5 4.55 E-7

~

8.23 E-7 1.96 E-6 5.75 E-7 2.16 E-6 8.40 E-6 3.51 E-6 3.64 E-7 1.00 E-5 I

3.76 E-8 6.80 E-8 I

5.40 E-7 5.94 E-8' 3.47 E-6 4.83 E-7 1.30 E-8 7.52 E-8 Zr-95 2.82 E-5 3.88 E-6 Zr-97 4.05 E-6 1.67 E-6 Ho>>99 R"-103 3.24 E-6 3.84 E-8 6.70 E>>7 4.00 E-9 Sb-125 2'.26 E-6 1.87 E-7 Cs-134 Cs-136 2.14 E-5 7.'82 E-7 1.96 E-5 1,08 E-7 Cs-137 4.85 E-5 Z.OO E-5 Ba>>140 6.44 E-7 2.66 E-8 Ce-141 CB-144 Atot 3.04 E-8 2.37 E-6 4.01 E-4 2

~ 80 E-9 1.96 E-6 Total

'..33 E-3 (1) 1978 Und'lvted Re ease Vole....

7 E

9 pills (2) H.

~ 1978 Und.'1. Act Nucl='e (')

~P" (i"on ~ab~ ~ L-: )

1 1

Ron ("elease "ate) 121000

=u~a (d'1 rate)

Page 12 1.3 (cont)

A 's the total average uCi/~

mix~uze and <<

's the -ract'on the re'ease con5itions specified

~~x,

-hich is the max'~ total to the !PC limit for the nuclide d"'scharges.

concentration or tne rere 2..ce of the '.PC of al'..uclices

=oz Dividing A by <<

yielcs tot ot act'vity conce..tzation eq iva ent d'stzibution typical or racwaste Tot The assumption that the mixture does not change is only used for calculational purposes.

1.3.1 The (C

) value in cpm should be obtained

=or the A

max

~4 (0.302 pCi/ml) from the release sources radioact.ve liquid effluent monitor curve of cpm vs >uCi/ml.

NOTL:

This setpoint is 'or a specified release of 1 gpm into 121000 gpm dilution flow.

1.3.2 For establishing the setpoint prior to liquid radwaste discharges, the (C

,) will be adjust'ed as needed to account for actual release conditions (ie, actual iqu'ic discharge flow rate and dilution flow).

Dete~inina the Dose for Radioactive Liquid Releases Discussion -

echnical Speci ication 3.11.1.2 requ'res ca'ulations be performed at least once pe" 31 days to ver.'

that cumu ative radioactive liquid e fluents do not cause a dose in excess o

1.>

mrem to the total body and 5 mrem to any organ during any calendar quazte and not in excess of 3 mrem to the total body and 10 mrem to any organ duzing any calendar year.

Th's section presents calculational method to be used for this ve if'cation.

This method is based on the methodology suggested by'sect'ons 4.3 and 4.3.1 of MZG-0133 Rev 1 Hov 1978.

The dose actors are a composite ot both tne

= 'sh and shel =isn pathways so t..at the fish-shell=ish pathway is the only pathway =or which dose will be calculated.

Foz St. Lucie Plant, the adult is the most limiting age gzoup, but, the dose

=or cni'd, and teenage can also be calculated by this metnod provided that their appropriate dose. factors are available for tne organ of nterest.

Only those nuclides that anoear in the.ables of his manual be considered.

ST L~C1Z P~~VT '-ODCH

I

Page 1.4 (cont) 1.4. 1 This method provides for a dose calculat-'on to the total body or any organ zor a given ag group based on real release conditions durmng a specified t"me enter;al.or radioactive liquid release sources.

The eauation is D

= A.

ht 0

1~ -j.=j.

1

~

where:

D

= dose commitment in mrem received. by organ Q of age 1

group (to be spec'=eed) during the release time interval At A.

~ the composite dose factor for the fish-shel'=esh pa"'hway for nuclide (i) for organ

". of age group (to oe specified)

The A, values 'sted in the Tables in this manua:

are indepenoenq oz any site speci c information end heve t'e units m".em-ml

,uti-ht I

4t> =

. the number o

hours th " the release occurs.

Q.

= The 'total auant'ty of ruc.'ide (i) released durin~

("Ci) r (DF)1 = The total volume the release time wa.ter flow t'mes o= d'lution that occurred curing per od Q ti(ie, the cercui ting time) he "oses assoceated with each release may then be summed to provide the cumulative dose over a desired time per'od (eg sum all doses for release du.ing a 31 day period, cala..der cuarter or a year).D,

=

D total ~

1 i

where:

DT

= the total dose commitment to organ+ due to al T

releases during the desired time interval (mrem)

ST LUCi:" PLAiNT

'-ODCi!

>>agsu 14 (cont) 1.4.1 (cont) oased on e

d ih red'onuc'ide distr'bution typica>. 'n radioa"i've the calculated doses to indivicuals ar cominated bv ihe radionuclides, "e-59, Co-58, Co-60, Zn-65>

. b-9>,

Cs-134 and Cs-137.

These nuclides typically cortrebute over 957. of the total body dose and over 907. of ihe GI-LLT.

dose which is the critical organ.

Therefore, the dose ose>

w xcn x commxtmen u

t d e to radioact vity in 1'quid er=-luents may be bl evaluated by.limiting the dose calculation p"ocess to these radionuclides for the adult rota o y process and adu t 1

Gi-LLI.

To allow -.or any unexpec" ed variaoility in the radionuclide distribution, a corservatis-factor of 0.8 is introduced into the equation.

After calculateng the dose based on these 7 nuclides, the cumulative dose h

ld be +vided by 0.8, the conservat'sm factor.

sou e~

(ie D~ =

0 %>.

R.efer to Appendix 8 for a deta.

e

~ iled xe>

evaluai+ion ana exp1.anation of this 1 m'ted analysis approach.

The methodology that follows is a step-by-st p breakdown to calculatedoses based on the above equation.

Refer'o the in-plane procedures to determine the apol ca b},e

organs, age groups>

zn pa

'thway factors.

T." the lim'ted analys 's aporoach is usea>

e h

'h calculat'on should be li iced to tne Adult total body dose and Adult Gi-LLI dose from the fish and shellfish pathways.

Only the 7 orev'ously soeci

'ed rad'onucli es s

ou e

1'd h

ld b evaluated.

For the dose calculat'ons eo be inn>eden in see'-annuai capon s> -ba doses "o the ss>n>'e groups ano all organs snoozed be ev23.u2ied

="o=. 21~

=2Q<0.;Dc '.Ge, identi"iec in the }.'quid ef=luen" s.

NOR:

Table 1.4 provides a convenient form =or compi},'ng tne dose accounting.

1.4.1.1 Determine the time interval At tnat tne release took place.

The in-plant procedures shall describe the procedure for calculat'ng

>>t for off'cial release pu poses.

1.4.1e2 Obta~

{D:")

for the time period Paste

'.>anagement Records for the re>ease source(s) of inr.e"est.

1.4.1.3 Obtain Q

~

for nuclide (i) fo" the t'me per'od C

At from the L'qu'd Paste

'Management Records.

1.4.1.4 Obtain A.

from the appropriate L'uid Dose i

ractor Table.

ST LUCI= P<~MT

-'ODCH

TASLE l..4

""T.SH

& SHELL@ ZSH PATHWAY T>1:"/DAT" ST> XT:

TLif"/DATE STOP:

".ov.

s TOTAL DILUTION VOLPii

~

z's AGE GROUP:

ORGY:

DOSE PACTOR TABLE Pr NQCll.de

( i )

Pe-59 Co-58 C~ (pC<)

Al.i Dose (i) mrem Co-60 Zn-65 Nb-95 Cs-13~

Cs-137 Othe s

Total Dose ii based on 1'mited analys's

, Q.3 imii. em ST 'UCZE PLAÃZ

- ODC'f

P 0

P age

1. 4 (cont)

1. 4. 1 (cont) 1.4.1.5 Solve for Dose (i)

Dose (i) = Q.~ ~ tl A.

(DF) 1 1.4.1.6 Repeat steps 1.4.1.3 through '.4.1.5 for each nuclide reported and e ch organ required.

If the lim'ted analysis method 's used, limit the radionuclides to Fe-59, Co-5S>

Co-60>

Zn-65>

Nb-95>

Cs-134>

and Cs-1.37 and determ. ne the adult total body dose and the adult GI-LLI dose.

1.4.1.7 Sum the Dose (i) values to obtain the total dose to organ w from the fish-shell ish pathway.

If the limited analys.s method 's being used> d'ide the cun lative dose by a conservatism factor of 0.8 to account for a~y unexpected variab'1 'ty 'n rad'onucl'de dist"'bution.

~

T DCT

?L~NT

.-ODCN

Page 17 Pro~ectina Dose for Midioactive Liquid Kff uents Discuss'on - Technical Speci"'c

""'on 3.11.1.3 requires that appropr'ate subsyste s of the liquid radwaste treat-ment system be used to reduce radioact've material l'quid e f"uents when the projected monthly dose due to liquid re eases to unrestricted areas when averaged over 31 days would exceed 0.06 mrem to the totz bodv or 0.2 mrem to. any organ.

Doses are to be projected at least once per 31 days.

The following calculation method is provided for per orming this dose projection.

The method is based on dose'as calculated in section 1.4 with the adult as the bases for projecting.

1.5. 1 Obtain the latest result of the monthly calculation of the adult total body dose and the adult's highest organ dose.

These doses can be obtained from the in-plant logs.

1.5.2 Divide each dose by the number of days the reactor plant was operational during the month.

'.fultiply the quot'ent of each dose by the number of days the reactor plant

's projected to be operational during the next month.

The produc"s are the projected dose for the next month.

These values should

'oe ad-j usted as needed to account fo" any changes

-'n failed fuel or other identif 'able operating condit'ons that could significantly alter the ac'tuel releases.

1.5.4 Xf the projected dose

's g.eater than 0.06 the total body or greater than 0.2 mre to highest e~osed

organ, the liquid rad"aste be used to reduce, the radioact'vity levels release.

mrem to the adu's system shall p ior to

-ODC.

2.0 G A S

E 0 U

S R

E L E A S E

S N E T H 0 D 0 L 0 G Y

Dage 1 0 Gaseous

=f luent Model AssumDt ons Description ci S'te

{The "-SAR conta'ns the cff=cia descr'pt'c,.

ci tne site characteristics.

The descr-'ption that =oi cws is a

brief summary zoz dose ca'culat"'on purposes only).;ne St. Lucie Plant is 'ocated on an island surrounded cn two sides by the Atlantic Ocean and the indian R'ver, an estuary oz the Atlantic Ocean.

Pzivat property adjoins the plant site in the north and south directions.

A meterological towe is located nozth oz the plant near the site property 'ine.

Theze aze 16 sectors, for dose calcu'ation

purposes, divided into 22.5 each.:he met towe

's calibrated such that a zero degree bearing coinc"des with TR1JE NORTH.

A. bearing of zero degrees d-'ssects the nor=h sector such that bearings of 348.75o and 11.25c dezine the boundaries of the north sector.

The nearest distance to private property occurs in the north sector at approximately 0.97 miles.

For ease of calculation, this 0.97 mile radius is assumed in all directions, a>>hough the real Unrestricted Area Boundary is de-fined in Pigur 5 1 of the STS.

Doses calculated over water areas do not apply to the STS LCO's or the annual report and may be listed as O.W. (over water) in 1'eu oz performing calcula-tions.

The 0.97 mile range in the bW sector is O.W., but it was chosen as the worst sector for conservative dose calculations using the h'stozical met data.

Historical Met Data - Met data, between Septem'cer 1<

1976 and August 31,

1978,

~ rom the St. Lucie Me Tower was analyzed by Dames

& Moore of Washington, D.C.

The methodology used by Dames

& Moore "as ccnsistant with methods suggested oy Regulatory Guide 1.111 Rev l.

Recirculation correct on factors were also calculated for the St.

Luc=e Site and ar

'ncorporated.into the h's'-or.'ca met tables (Ta'oles

~D, M6, and M7) in Append'x A oz this manual.

lt was determined that these two years are representative Data =or this locale.

Dose Calcu'at'ons Dose calculat.'ons fcr Techn'cal Specificat 'cn dose limits are normally calculated us"'ng histoz'cai met data and receptor location(s) whic'n yield ca'c lated doses no lower than the real location(s) exp riencing the most exposure.

Actual met data factors are calculated and used in dose calculations Xor the Semiannual Reports.

Live met data and hour-by-nou dose calculations are beyond the scope oz this annual.

Historica'nf orat'on and conservat"'ve receptor locations etc.,

are on'y used zoz ease oz STS LCO dose Umit calculations.

Dose calculations zor STS dose limits may be performed using acrual met dat'a, real receptor locations, and sector wind frequency distribution if desired.

Any dose calculations performed with actual data snou d note the source oz the data in the annual report.

Actual met data reduction should be performe'd in accordance wth Regu atory Gu de '.111 Rev 1 and shoulc incorporate Recirculation Cor.ection:actors from

~ able M-4 oz this manual.

ne St. Lucie s" te uses the 1ong term ground re'ase model for ail gaseous effiuents.

Only those radionuci'des that appear in the gaseous eff'uent dose

=actoz tables -ill be considered anv dose calculations.

Land Ca.,sus inioration wii apply to the'a anczr year foal'cwing the year that the census was admen to avo'd sp 'tt'ng quar"ers etc.

Pagp 20 2.2 Decermininz the To-al 3odv and Skin ~ose Pates'or

!soo'e Gas Re'eas s anc

" stablishine Setoo'its for

~ "='..t

! n'"ors D 'sc ssion

- Technical Soec'"ication 3.11.2..1 limits =he instantaneous dose rate from noble gaseous in airborne releases to less tnan 500 mrem/yr total body and less than 3000 rem/yr-sk n.

Technical Specification 3.3.3.9 requires that the gaseous radioactive effluent monitoring instrumentation, be operable with alarm/trip setpoints set to ensure that these dose rate I.imits are not exceeded.

'The results o

the sampling and ana'ysis program or Technical Specificat'on Tao'le 4.11-2 are used to demonstrate compliance witn these, 'm'ts.

The following calculation method is provided ror determining the instantaneous dose rates to the total body and skin from noble gaseous in airborne releases.

The alarm/trip setpoin" s are based on th dose rate calculations.

Tne Tecnnical Spec'=ication LCOs apply to all airborne releases on the s'e but all releases may be treated as i discharged from a singl release point.

Only those noble gases appearing in Table G-2 w'll be considered.

The calculation methods are based on Sections, 5.1 and 5.2 of NURZG-0133, Nov 1978.

The equations are:

Fo" Total Body Dose Rate DR R

=

Q K

(K/Q) Q.

i For Sk.n Dose Rate skin where:

DR B

= total body dose rate

=rom noble gases in air'oorne releases lB (mrem/yr)

DRskin skin dose rate from nob1e gases in airborne releases (mrem/yr) a mathematic 1 symbo'.

to signify the opera" ions to the.

right of the symbol are to be performed fo each noble gas nuclide

( i) through (n) and the individual nucl 'ce doses are summed to arrive at the total dose rate for the rel.ease source.

(

= "Ne 1

nob total body oose

= c "or du, to gamma emissions for e c' le Res nuclide zeposced in he ".eleese sousce (r ".eo-"...

'~"

page 21

2. 2 (cont)

L.

= The skin dose factor due to beta emissions

=or noble gas nuclide (i) re~orted in the assay of release source mrem-m g

pC>

1 N.

= The a'r dose factor due to gamma em ssions for each noble gas nucl'de (i) reoorted

'n the assay of the release source.

The constant 1.1 converts mrad to mrem since the units of H, are in mrad m

"Ci-yr (X/Q) = For ground leveli the highes" ca,lculated annual long term historic relati.ve conce..t ation for any of the 16 sectors>

at or beyond the exclusion area boundary (sec/m ).

Q.

= The release rate, of noble gas nuclide (i) in pCi/sec from the release sourc of 'nterest.

2.2.1 Simplified Total Body Dose Rate Calculation From en evaluation of past releases, an effective tota'ody dose factor (K

~

) 'can be derived.

Thi.s dose factor

~F" is in e "ect a Meignted average total body dose -actor, ie, weighted by the radonuclide d stribution "ypical or past ope ation.

(Ref er to Append i:

C for, a d'etai led.

ezplanat on and evaluat'on of K.~).

The value o

K has been derived from the radioac='ve noble gas e==l.ents for the years

1978, 1979, anc 1980.

The value is K

6.8x10 2 e

mr em-m pC i-yr This va'ue may be used 'n con~unction with the total noole gas r lease rate

(

Qi) to ve"ify that the instantaneous dose rate is within the allowable 'imlts.

To allow for any unexpected variabi'ty in the radionuclide distributioni a conservatism

'actor of 0.8 is introcuced into the calcu'ation.

The simplified equation is DR

=

K ~~ (X/0)

Q.

0.8 i

ST LUC::" PAINT

-ODC:".

2.2.1 (cont)

To further simplify the determination>

the his<rical annual average meteorological X/Q of I.6 x.'0 sec/m (from Table M-1) may be substituted into the ecuation.

Also, the dose limit of 500 mrem/yr may be substituted for DR MaRing these substitutions yields a single cumulaPive (or gross) noble gas release z'ate limit.

Th's value is 5

Noble gas release rat'e limit = 3.5 x 10 pCi/sec As long as the noble gas release rates do not exceed tnis value {3.5 x 10

)LCi/sec),

no additional dose rate calculations are needed to verify compliance with Technical Spec i icat 'n 3. 1'1. 2. 1.

2.2.2 Setpoint Determination To comoly wi.th Technical Soecifica"ion 3.3.3".9>

the alarm/trip setpoints are established to ensure that tho noble gas releases do not exceed tne value o

6.5 x;10 QCi/sec>

which corresponds to a total body dose rate of 500 mrem/yr.

The method that follows is a step-by-steo procedure for establish'ng the setpoints.

To allow for multiple sources of releases from oi==erent o-common release points>

the allowable operating setpoints.',.-'e controlled administrative'y by allocating a percentage of the total allowaole release to each oz tne release sources'2.2.2.1 Determine (V) the maximum vol me release rate potential from the in-plant procedures or the release source under consideration.

The un'ts o" (V) are ft /min.

2.2.2.2 Solve for A, the activity concentration

'n Ci/cc that should produce the Y

dose rate L~O A = 3.5xlO uCi x

..in x

sec (V) ft3 f

x 50 sec 3

/.

2.8zlO cc m'n A = yCi/cc 2.2.2.3 Refer to the pCi/cc vs cpm cu-ve o

ne Release Source's Caseous

""ff'.uen" Monito cpm value '(C),

corresponding to the value o" A a've.

2.2.2.4 C is

<<he 1007. setpo'nt, assuming tha-there are lI Dl

<<4h C

no other release sources on t.. s.'.

-OZCL4f

2ag 23

2. 2 (con

)

2.2 '

(cont) 2 2 ~ 2 5

obtain the cu

.ent

7. allocated

'"o this elePse source from the gaseous waste management l.ogs.

2.2.2e6 The Operating setpo'nt SP

.SP = (C) cpm x

7. allotted bv in-plant procedures 1007.

The total body dose is more limit.'ng than the calculated skin dose.

(Refer to Appendix C for a detailed evaluation.)

Therefozeg the skin dose rate calculations are not required if the simplified dose zate calculation is used

( ie, use of.K'eff to determ'ne release rate limits).

The calculation 'rocess of the following Section (2.2.3) are to be used if actual releases of noble gases exceed the above limit of 3.5 x 10 yCi/sec.

Unde-.

these condit'ons, a nuclide-by-nuc1.ide evaluat'on is required to evaluate compliance we th the dose rate limits of Techn'cal Specification 3.11.2.1.

2.2;3 Total Body and Sk'n Nuclide Specific Dose Rate Calculations The fo'lowing outline'orov.'des a seep-by-seep explanat'on o" how.the total body dose rate

's calculate on a nuclide-bv-nuclide basis to evaluate comoliance with echnical Soec. "'cation 3. 11. 2. 1.

Th' method is on y used if the actual releases exceed the value oi 3.5 x 10

>Ci/sec.

2.2.3.1 s

2.2.3.2 3

The (X/i)) vs lee

=

sec/m end is "he most limi"ing sec".o"-

a the exclusion ates..

3

""nter the release rate 'n ft /min o the release source and convert it to 3

4

) t x 2.63i)vlO cc x m'-'n t3 60 -ec cc/sec volume release ra" e 2.2.3.3 Solve for Q. for nuclide (i) by obtaini-..g the l Ci/cc assay value of the release source and mult'p'ying i-by the product of 2.2.3.2 above Q.

= (nuc1 'de( '

)

(PssPv)

C'

(

2.2, 0

g is CC sec Q.

=

Ci/sec for nuc'ice (i)

ST LUG l Z PL "qT

-ODC it[

Paga 2.2 (cont)

2. 2.3 (cont)

2. 2.3. 4 To evaluate the total body dose rate obtain the value for nuclide (i) f"om Table G-2.

2.2.3. S So lve or DR~.

TBi 3

DR

=

K (X/Q)Q

=

rem-m x sec:c -Ci

~Ci-yr m3 sec 0

DRTB.

TBi mrem total body dose yr from nuclide (i) zor the, speci ied release source 2.2.3.6 2.2.3.7 To evaluate the skin dose rate obtain the Li and values "rom Table G-2 =or nuclide (i).

i Solve for DR

,sxin i DR

= tL.

+ 1.1 H

I (X/Q) Q.

sk'n i I i.

1 DR

=

m"em skin dose from nucl de (i) for yr the specified release source 2.2.3.8 2'.2.3.9 Repeat steps 2.2.3.4 through 2.2.3.7 for eac'n r.oble gas nuclide

(~ ) reported in 'the assay of the release source.

V The Dose Rate to the Total Bccy z"om rad'oact've noble gas gamma rad'at'on from the speciziec release source is Jl DRTB DRTBi 2.2.3.10 The Dose from the DRsk'n Rate to the Skin from noble gas radiat'on specified release source is n

DRskin The dose rate contribution of this release source shall be added to all other gaseous release so rces I

that are in progress at the time of interest.

beezer to in-plant procedur s

and logs to ceterm'ne the Total Dose Rate to the Tot 1 Body and Skin rom noble gas ez=luents.

2. 3 De'rmininz the Rad oioc: ne Pa"." 'cu.'ac Dose,"

o a

r Gr".'.'.

":rom Tnstantaneous Gaseous Releas s

D.'scussion

- Technical Specification 3.11.2.1 limi"s "he dose rate from radioiod.nes and particulates with hal 1'ves g

e ter "hen eight days to (

1500 mrem/yr to any organ.

The fol'owing calculation me"hod, is provided for determining the dose rate from radioiodines and particulates and is based on Section 5.2.1 and 5.2.1.1 through 5.2.1.3 in iMURZG-0133, Nov 1978, The Enf nt is the controll.ng age group in the nhalation, grcund "lane, and cow/goa" milk pathways>

wnich are the only pathways con-sidered for instantaneous releases.

The long t rz (X/0)

(depleted) and'D/Q) values are based on historical met 3zta prior to implementing Appends~

E.

Only those nuclides that appear on their respective taole will be considered.

The equations

'are:

For inhalation Pathwa (excluding H-3):

>'~

Por Ground Plane:

Por Grass-Cow/Goat-;filk:

DRi 48DF'or Tritium Releases. (inhalation

& Grass-Cow/Goat-Vilk):

"or Total Dose Rate from T

& SDP and H-3 To an infant Organ ~:

~3ormallyshould oe P, but Ri-va ues are the

same, "hus use R'< tables 'n Appendix A.

p~ g~

O5 2.3 (cont) wne" e:

r = Tne organ or interesr for the 'nfant age group.

z = The applicable pathways DR DP

= Dose Rate in mrem/yr to the organ r from rcm iodines and 8 day particulates DR tp R<<3

= Dose Rate in mrem/yr to organ v from ritium r

= Total Dose Rate in nrem/yr to organ v from all pathways under consideration m

m a(

~ A mathematical symbol to signify the operations to the f

h b l are to be performed for each nuclide {i) th oug (n),

an e

h ( )

d th individual nuclide dose rates are summed to arrive at the tota'ose rate from the pathway.

= A mathematical symbol to indicate that the total dose rate

~

, D to organ x is

~ e su th sum of each of the pathways dose rates T

R

~ The dose factor'for nucl:de (') for organ

-. zor the "ath-ay specif'ed (units vary by pathway).,

p

=

h

~ <<actor og instantaneous

~.own p lane a,thwa-

i. e dos~

L in units o

mrem-m sec pCi-yr th adioactive releases nd environmenta,

."rom an eva 1uat ion o ~

~~<e the rass-cow/goat-milk pa hway has

'oeen icenti:ied as the most limiting oathway with toe in=ant s

y.

1 or an.

Th's pathway typical'y cont.butes greater than 901 of the total dose received by the in=ant s

y radio iodine contr ibu te esses t' 1 1 g a 1

il of th's dose.

he e"ore,

t is possible

<<o daemon bl t de. o s "~ate compliance with the.elease rate particulates by only evalu ting the infant's t. yro cose o"

tne re'ease oi ra io d'od'nes via tne grass-cow/goat-mk oathway.

The calcu,lat'on method oz Section

2. 3.3 s used o-tnis determination.

'Kf this lim'ted analysis approach is used>

the dose calcu ations or o

'1 i ther radioactive particulate mat"er an

~'nlv the cai cut at<one; t'her pathways need not be per orm c.

n,

Section 2.3.3 for the radioiocines need be "erformed to demonstrate comp'iance

w. th the Technica pe

- c

Page 27 2 ~ 3 (cont)

The calculations of Sect.'ons 2.3.1, 2.3.2, 2.3.~>

and 2.3.5 may be omitted.

The dose rate calculat'ons as speci='ed in these sections are 'ncluded

or completeness and are to be used only zor evaluating unusual circumstances where releases o

particulate materials other than radioiodines

'n a'rborne releases are abnormally high.

The calculations of Sections 2.3.1, 2.3.2>

2.3.4>

~ and 2.3.5 will typically be used to demonstrate compliance with the dose rate limit oz Technical Speciiecateon 3.11.2.1 for racsoiodines and particu>ates when the measured releases of particulate mate. ial (otner tnan radioiodines and with half lives greater than eegnt days) are greater tnan ten (10) times the measured releases oz radioiodines.

2.3. 1 The Instantaneous Inhalation Dose Rate ltfethod:

NOTE:

The H-3 dose is ca'c '1 ted as per 2.3.4 2.3.1.1 The controll'ng location is assumed to be an In-ant locatec

'n the sector at the sile range T.he (:(/Q)h or this locations is sec/m This value ss common to all nuc'des.

2.3.1.2 Enter the release rate in ft /min 3

source and convert to cc/sec.

o the release min ft 2.831':;10 cc man 3

X zt x

=

cc/sec 60 sec s

2.3.1.3 Solve for Q

for nuc'ide{') by obtai..'ng the pCi/cc assay value oz the release source act'vity and multiplying it by the product of 2..'.2 above.

Qi = (nucl'de(i)assa

) >C'Value 2.5.1.2) cc X

CC sec Q

s=i pC i/sec

=or nuclide (.'

2.

.1.4 Obtain the R.- value from T-ble G-5 fo-the organ -.

Qagsa

>Q

2. 3 (cont)

2. 3; 1 (cont) 1

~

~ J

~

~

Solve for DR.i DR.

= R.

(X/0) it it D i 3.

mrem-m sec gC'

~

X pCi-yr m

. sec DR.ii mrem the Dose Rate to o gan. t from nuclide(i)

2. 3.1.6 Repeat steps 2.3.1.3 through 2. 3.1.5 for each nuclide(i) reported in the assay of the elease source.

2.3. 1. 7 The Instantaneous Dose Rate to the Infants organ t from the inhalation Path~.-ay 's D nhalation

= DR

+ DR

+ - + DR 1

2 n

for all nuclides except H-3.

This dose rate shall be added to the other pathways as per 2.3.5-Total Organ Dose.

"lOTB:

Steps 2.3.1.3 through 2.3.1.7 need to b completed for each organ

-. oi the Infant.

2.3.2 The Instantaneous Ground P ane Dose Rate ':!ethod:.

NOT"=:

Tritium dose v a the ground plane is zero.

2.3.2.1

2. 3.2.2 s

The contro'ling locat on is assu...ed to be an Xn ant located n "he sector a

the range.

The (D/Q) "or this loca" ion is 1/m".

This value is common to all nuclides.

= 3

""nter the release rate in ft /min of the release source and conver-to cc/sec.

min

=.3

~l

2. 33':.10 'cc x

= cc/sec 60sec LUCrPLAiNT ODCh!

Page 2g

2. 3.2.3 Solve for Q. for nucde(')

'oy obtain'ng the i

pCi/cc assay value rom the release source activity and multiplying it by the product of 2.3.2.2 above.

Q.

= (nuclide(i)assa

) C'i CC (Ualue 2.3..2.2)cc s c Q

pCi/sec 'or nuclide (i) t 2.3.2.4 Obtain the P

~ va~ ue from Table G-3 2,3; 2.5 Solve for DR.

DR.

~ P.

(D/Q)

Q.

2 mre=m -sec 1

~Ci X ~

X p.Ci-yr m-sec DR.

mrem the Dose Rate to orga-.'.

from nuclide(i) 2.3. 2.6 Repeat steps 2.3.2.3 through 2.3.2.5 or each nuclide(i) repor"ec in the assay o

the release'ou ce 4

I 2.3.2.7 The instantaneous Dose Rate to the Tnfan-'s Tota'ody from the Ground Plane Pathway is DR

=DR

+DR

--:DR Gr Pl 1

2 for all nuclides.

Ths dose rata shall be added to the other path"ays as per 2,3.5

Page 30

2. 3 (cont) 2.3.3 The nstantaneous Grass-Cow/Goat-Milk Dose Race

.'!echoc NOTc..

H-3 dose is calculated as per 2.3.-'.3.3.1 The controll'..g animal

@as established as a.

located in the setto" at miles.

The (D/Q) ior t'nis locat-'on is 1/m This value is common. to all nuclides.

2.3.3.2 Enter the anticipated release rate in =" /min

=.3 of the release source and convert to cc/sec.

min ft 2.8317x10 cc min cc/sec 3

ft '0sec 2.3.3.3 Solve for Q. for nuclide(i) by obtaen'ng the i

pCi/cc assay value of the release source activicy and multiplying it by the product of 2.3.3.2 above.

Q.

~ (nuclide(i)assa

) Ci (va'ue 2.3'.3.2)cc CC sec Qi an pCi/sec for huel'e (i) 2.3.3.4 Obtain tne R

value from Table G-6(7 (vhichever 's the conc"oiling an'mal for 'n'anc).

)

goat/co+,

es

~

Xf.the limited an lysis approach

's being used, limit tha calculation co the infant thyroid.

2.3.3.5 Solve for DRiiT DR 2

it = R.

(D/Q) Q.

=

mrem-m ec 1

~CS iT i

x ~

pCi-yr m

sec DR.lT mrem/yr the Dose Rate to organ T

from nucl'de(i) 2.3.3.6 Repeat steps 2.3.3.3 through

2. 3.3.5 or each nuc 'de(i, repor"ad 'n cne ssay of che re ease source.

Only the radioiod'nes need to be ncl ced i" imited na'ys's approa"..

's being

.sec.

I

2.3 (cont) 2.3.4 (cont) r 2.3

~ 4.3 Solve for QH 3 for Trit'um, by obtaining the pCi/cc assay value of the release

source, and'ultiplying it by the product oz 2.3.4.2 above

()

3

= ~(H-3) Ci (2.3.4.2 velue)cc CC sec pCi/sec activity release ra" e 2.3.4.4 Obtain the Tritium dose factor (R.) for Tnfant 1

i) organ r from Path Table

)f Tnhalation G-5 Grass-

-ii!'lk G-6(7) 2.3.4.5 Solve for DH 3 (Tnhalation) using the. (Vq)D for inhalation from 2. 3.4. l and R

(Tnha'ation) ce om 2

3 4

4 H 3 Inh

('/Q)D Q-,. 3 mrem/yr from H-3 cinfant Instantaneous

'Inhalation for organ t 2.3.4.6 Solve for D.

3 (Grass-

-'Ailk) using the

()I;/Q) for "".ass-

."'k from

.3.

.1 and R.

(Grass-

-Hilk) from 2.3.4.4 G- -iif "-'rem/yr from H-3 infant instantaneous G-

-Milk for organ ST, vC-MfT I

Page 33

2. 3 (conc) 2.3.4 (conc) 2.3.4.7 Repeat steps 2.3.4.4 through 2.3.4.6 for each infant organ r of interest.

2.3.4.8 The ind'vidual organ dose races from E-3 shall be added to the other organ pathway dose races as per 2.3.5.

2.3.5 Determin'nz tne Total Or an Dose Race from ioa'nes.

SD-Particulates, and H-3 from instantaneous Release Source(s) 2.3.5.1 The following, table describes all tne pat'.r~ays that must be summed to-arrive at the total dose rate to an organ t:.

Pathway Dose Race Step fr'ef In'naia tion (i&SDP)

2. 3 ~ 1.7 Ground Pl.(XGSDP)

(T Pody only)

Gr-

-Hilk(l6SDP )

Tnhalation (H-3)

2. 3.2. /

'2. 3.3. 7

2. 3.4.'5 Gr-

-i~Lilk(H-3)

2. 3.4.o DR.i (sum of above) 2.3.5.2 Repeat che above summation

-"or each Xn:ant organ r.

2.3.5.3 The DR above snail be added to all other release sources that wil be in progress a" any ~~scant.

Refer to in-plant, procedures and 'ogs to decermine che Total DR to e ch organ.

Pago Dete~ininz 'the Gat-a Air Dose or Radioactive Noble Gas

'Release Source(s)

Discussion Technical Specificaton 3.11.2.2 limits the a

dose due to noble gases

'n gaseous efzluents zor kg~a radiac'on to less than 5

rads zor the. qua"-er and'.to less than '0 mraas 'n anv calendar vear.

The following calculation method, 's prov ded for detem ning the nobl gamma ai" dose and is oased on sect'ons 5.3.1 oi Hl73"G-0133, Hov 1978.

The dose calculation is independent of any age group.

The equation may be used for STS dose calculation, the dose calculation for the annual report or for vzojecting dose,

'rovided that the appropriate value of (X/Q) is used as outl'ned in the detaed e~planation that follows, The eouation zor gam=a air dose is e gas n

D -air 3.17 X 10 Mi (X/Q) Qi i

where:

D -a'r

~ gamma air dose in mrad from radioactive noble gases.

Y

= a mathematical symool to signify the ope.at'ons to the right side of the symbol are to oe,performed

=or each nuclide (i) through (n),

and su~ed to 'arr.'ve at the total dose, from all nucdes reported dur'ng the in-terval.

No units apply.

3. 17z10

= The inverse oz the number of seconds per year with

-8 un'ts of year/sec.

= The gamma air dose factor zor3radioactive noble gas nuclide(i) in un'ts of mrad-m 3lCi-yr ~

(X/Q) ~ The long term atmospner"c dispersion zactor zor ground level re'eases in units of sec/m The value oz

('.C/Q) is the same for all nuclides (i) in the dose calcu'ation, but the value oi (Z/Q) does vary depending on the Limiting Sector the L.C.O. is oased on etc.

~ The number of micro-cur"'es of nuclice{i) released (or l

projected) during the dose calculation ezposure per'od.

(eg.'month,

quarter, or year)

2age 3D 2.4 'cont)

"=rom an eva uat'on oz oast releases, a single e

=e "'ve ga=-a a.r dose factoi (N

) has been derived, which s r oresen"at've of the radionuclide abundances and cor" spond'..g dose cont=ibut ons typical oz past operation.

(Refer to Aooendix C

oz a cetailed explanation and evaluation of N

~'. )

The va'ue of >!,

has been derived from the radioactive noole gas effluents for ine years 1978>

1979>

and 1980.

The value is 1

2 M

= 7.4 x 10

~mrxd/

pCi/m" Th's value may be used in conjunction with the total noble g s.

releases

(

+I, Q.) to simpl'fy the dose evaluation and to verify that the cumulative gamma ai dose is withmn the 1'mits o

Spec.'cat'on 3.11.2.2.

To allow "or any unexpected variab'ity in the radionuclide distribution>

a conservatism actor of 0.8

-in int'roduced into the calculat'on.

The simplified equ t'on is D,'

3.17 x 10 M

X/Q 1

Q.

Y -a'r ef i

1 2'or purposes of calculations, the appropr'ate eieorologic 1

dispersion

()(/Q) from Table H-1 should be used.

Technical Speciz'cation 3.11.2.2 requires that the doses be evaluated once per

31. days> (ie, month'y).

The quarterly dose 1 mit 's 5 mrads>

which corresponds to a months.y allotment of 1.7 mr ds.

the 1.7 mzads is s bstituted fo" D'7/> - a.'r, a

c mulatdve noble gas montnly release objective can be calculated.

This val' is 60> 000 Ci/month> noble gases.

As long as this value is not exceeded in any month, no add't.'onal calculations are needed to ve i=y compliance with the quar" erly noble gas release limits of Specification 3.11.2. 2.

Also, the gamma air dose is more 1.'miting than the beta ai-cose.

Therefore, the beta air dose does not need to be calculated pe" Section 2.5 i= the H

dose fac'tor is used to determine the ga.=~a air dose.

Re er to.Zppendix C

or a detailed eval 'at'on anc explanation.

The calculations of Section 2.5 may be omitted when "...is 1=m'ted analysis approach is used but should be per orated i= t..e radio-nuc'ide speci='c dose analysis s oer ormed.

Also, the radio-nuclide specific calcu'at'ons will be performed

=."or inc on in se i-annual repc~M

Page 36

~

~

(cont)

The following steps provide' detai'ed explanation o

how rad onucl'de spec'='c dose is calc lated.

This method

s used to evaluate quarte ly doses in accordance with Technica'peci"ication 3.11.2.2 if there',ses of noble gase S

during any month of the quarter exceed 64,000

.Ci 2.4.1 To determine the applicable

(;</Q),refer ro Table N-1 to obtain the value for the type oi dose calculation being performed.

ie Quarterly L.C.O. or Dose ?rojection for

.examples.

This value of (X/Q) applies to eacn nuclide(').

2.4 '

Determine'N.)

the gamma air dose factor for nuclide(i) from Table G-2.i 2.4. 3 Obta'n rhe micro-Curies of nucl'de(.)

from the in-plant radioactive gaseous waste management logs for the sources under consideration during tne -

me interval.

2.4. 4 Solve or D. as follows:

i-8 3

D

= 3.17xl0 yr x Y..mrad-m x (2/Q)sec x 0. pCi i

sec

)lCi yr m

1 D.i mrad the dose from "nucl'e {i) 2.4.5 Perform steps 2.4.2 through 2.4.~

=or each nucl'de(i) reported during the t' interval 'n.the source.

2.4. 6 The total gamma air dose fo" the pathway is determ'ned by summing the D. dose of each nuc'ide(i) to obtz'n D -air dose.

1 Y

D

=D

+D

+ -+D

~mrad y-air 1

2 n

NOT"-:

Compliance with a 1/31 day LCO,. Ouarter'y

LCO, yearly or 12 consecutive months LCO can be demonstrated by the limited analysis app oachl using if Using th's method only reouires that steos 2.4.2 tnrough 2.4. 5 be performed one t'me, remember'ng that the dose must be divided 'ov 0.8, the conservat'sm factor.

2.4. 7 Refer to in-plan" proc 'es

=or compar ng the ca.lcula ed dose to any appl cable lim'ts that might applv.

2.5 Determininc the Beta Air Dose for Radioactive Noble Gas eleases Discuss'on

- Technical Spec'"'cation 3.11.2.2 limits the cuarter y

air dose due to beta. radiac'on from nob'e g ses in gaseous effluerts to less than 10 mrads 'n any calendar quarter and less than 20 mrads in any calendar year.

The =ol'owing calcu'at'on

~+age 3

i'.

S (cont) method is provided for determining the beta

'" cose nd is based on Sections '5.3.'f iZR:-6-0133, Nov 197S.

The dose calculat'on is independent of any age group.

The equac.on may be used or STS dose calculation>

dose ca'culac'on

=or annual reports>

or for orojeccing dose>

provided tha" the aopropriate value of (X/Q) is used as outlined in the deta.iled explanation that follows.

The eouation for beta air dose is D

a 8-air where:

'.17x10 N.(X/Q)Q.

i i

C D

= beca air dose in mrad rom radioactive noble gases.

8-air a mathemat.'ca'ymbol to signify che operacions to cne right side of the symbol are to be performed for each nuclide(i) through (n),

and summed to arr-'ve at the total

dose, from all nuclides reported during, the interval.

No units apply.

3.17x10

= The inverse of the number of seconds per year w'th

-8 units of. year/sec.

= The beta air dose actor for in units OE ul ad m3 pCi-yr P

rad,'oactive no'ole,gas nuc 'de(i)

The long term atmospher 'c d'spersion faccoz for ground level releases in un'cs of sec/m~.

The value of

('.C/0) is the same for all nuclides(i) in tne dose calculat'on, buc che value of (X/Q) does vary depend'ng cn the Limi ing Sector tne LCO is based on etc.

Q,-

the number of micro-Cur'es of nuclide(i) released (or projected) during the dose calculation exposure per od.

ST LUC::"

?LANT

- ODCis

Page 98

2. 5

( cont)

The beta

- i" "ose does not have co be evaluated if the ncb'e gas g~nma a'r dose

's evaluated by the use o

che ffa t-'ve ai" dose =actor (A

).

However, i-" the nuclsce spec'='c dose ca,lcula.cion is usea co evaluate compliance w'th t.,e "uartarly g~a ai= dose limits (Section 2.4) 2 the beta a'r dose should also be evaluated as outlined below for the purpose of evaluating compli nce with the auarterly beta, ai-dose limits o Tech 'al Soecef cateon 3.11.2.2.

Tne following steps prov.de a, detailed explanation of how che dose is ca,lc 'aced.

2.5.1 To determine the applicable (X/Q) refer to Table ~f-1 co obtain the value fo-tne type of 'dose ca'culation being performed (ie. Ouarterly LCO or Dose Projection for examples).

This value o

(gQ) applies co each nucl'de(').

2.5. 2 Determine

('A.) the beta a'r aose factor for nucliae(i) l from Table G-2.

2.5.3 Obtain the micro-Curies of nucl'ae(')

from tne in-plant r d'ozctive gaseous waste management logs for the source unde" consideration dur'ng the c~me interval.

2.5. 4 Solve for D, as follows:

i-8 3

0

= 3.1)x)0 vr

'.I. ored-e (X/tX)sec X

1 X

sec pCi-yr 0.p.C '

1 mrad

= the aose from nuclide(i)

2. 3. 3 Per orxsceos

2. 3. 2 hroug.h

2. 3. ~

'=or e ch oocl'0oe

(.'r) reported during the time interval'n che re'ease source.

2.5.6 he total beta a'r dose for sum=.ing the D. aose o" each i

". e pathway is ete..'"..o" by nuclide'(')

co cota'n D

dose 3-air D

=D

+D

+ --:D

=

mrad 3-.air 1

2 2.v.7 Refe>> to in-plant procedures for comparin" the calc ac d

ose co any app 'cable

'm'ts that might apply.

0

Page 39 Dete~ininc he Radioiodine and Particulate

Dose, To v 0z"an Fzcm C= '.'ve Re'eases Discuss on - 'echn'cal Body Specif'cac'on

3. 1.2.3 'imi"s he aose co che :ota bocy o

any organ zesung from che ze:ease of rad'oiodines and particulates with hei=-lives greater than 8

davs to 'ss than oz eaual to 7. 5 mzem dur 'ng any calenaar cuazter and 'ess than or equal to 15 mrem during any calendar veaz.

The following ca'culation mechod 's proviaed for determining the criti-cal organ dose cue to releases of radioiodnes and part'culates and is based on Section 5.3.1 oi %LRZG-0133 Nov. 1978.

The ecuac'on can be used for any age group pzovidec chac tne appropz"'ate dose factors are usec and the total dose reflects on'y those parhwavs that are applicable ro the age group.

The

(:</Q)D symbol represencs a DEPLETH)-'(I/Q) which is different from the Noble Gas (X/Q) in that (Z/Q)D taices into accounc the loss of E&8DP and H-3 from the plume's the semi-infinite cloud travels over a given distance.

The (D/Q) dispersion factor represenr.s the rate oz fallour. from the cloud that azzects a sauare meter of ground at. various distances rom the site.

The T&8DP and H-3 notat'ons

".afar to Raaioiod'ne and Particulares having half-lives 8 days, and T" tium.

T 'tium calculations are always based on (7/g)D.

The first step is to calculate cne E&8DP and H-3 dose or each pathway thar. applies to a given age group.

The tocal aose to an organ can tnen be detezmned by summing the parhwavs that applv ro the zecepcor

'n the sector.

The equat'ons aze:

For Tnhalation

?achway (excluding H-3):

D.&8DP

=

'3.17xl0 8Ri (X/Q)DQ

":oz Ground ?'ane oz Grass-Cow/Goat-Nil'c 1 &8DP 3.17x R~

(D/Q)Qi

oz each pathway above (e'xcluaing Ground ?'ne) for Tritium:

Dw 3

3.'7x'0 Ri (UQ)DQ,

or Total Dose from Part'culate Gaseous effluent to organ

-. oi a specifiea age group:

D &8DP + DH-3

pa~ e y~O (cont) where:

the organ oz interest oz a specizied age group L

e z = the annlicable pathways for the age group or inta est

~ Dose in mrem to the organ T of a specizied age group radioiodines and 8D Particulates.

D

= Dose xn nrem oto the organ r of a specifxea age group H 3 from T.it D

~ T tal Dose in nrem to the organ t o p

f a s ecif'ied age groun o

from Gaseous Particulate zzluents.

g g

i h bol to signify the operations to

.e right, ym f

4 s

bol are to be performed for eac.

nuc e

o t,e syno

{ )

and the individual nuclice doses are ssurged to arrive at the total dose from the pathway of int

~ "

t rest to*oran t.

= A mathematical symbol to indicate thahat the total dose D

organ r is= the sum of each of the pata.wag dos doses of TKSDP

- and H-3 from gaseous part'culate ef luents.

"3.17xl0

= The inverse of the number of seco p

y

-8'conds er yea wigh-units oz year/sec.

R.

= Th dose factor for nuclide{i) (or H-3) zor pathway ~ ~o or an r of the specified age group.

The uni e

o "4.

f are either mrem-m -sec mrem-m v-- Ci

~o y=-pCi for.yaromays usieg (X/0), or y-.-p'i pathways using (D/Q)

{.

)

~ Th d

lated-('.C/Q) value for a spec'z'c lccat"'on ~here the recep)or is located (see d'scussion,.

are sec/m (D/Q)

= The deposition value for receptor is located (see 1/m where m = meters.

Z a spec'fic location where the d'scussion)

The un's are The number of micro-Curies of nuc i 1

1'de(i) released (or

)

d "'4 "ose calculat'on exposur period.

proj ec"ed p curing

~. e H-3

~

he number of micro<<Cur'es of-H-3 released (or projec ted)

during the dose ca'culation exposure per o

ST LUCTZ P~qT

-ODC~if

Page 41 2.6 (Cont'd)

As discussed

'n Section 2.5, the grass-cow/goat-milk pathway has been identified as the most imiting pathway with the

'nfant's thyroid being the czcal ozgan.

Th's pathway typical' contributes greater than 90lo of,6 tcrtal dose received by the infant's thyroid and the radioiodine contri-bute essentially all ox this dose.

There oze, '

is possible to demonstrate compl'ance with the dose limit of Technical Specification 3.11.2.3 for radioiodnes and particulates by only evaluating the 'nfant's thyroid dose due to the release of radioiodines v'a the grass-cow/goat-mi'k path~ay.

The ca'culation method, of Section 2.6.3 is used for this deter-mination.

The dose determined by Section 2.6.3 should be divided by a conservatism factor of 0.8.

This added conservatism provides assurance that the dose determined by this limited analysis approach will be less than the dose that wou'd be determined by eva'uating all radionuclides anc all pathways. If this 1~ted analysis approach is used, the dose calculations for othez radioactive particulate matter and other pathways need not be performed.

Only the calculations 'of Section 2.6.3 for the radioiodines aze required to demonstrate compliance with the Technica'pecif'cation dose 1~~ '.

However, for the dose assessment included in Semi Annual Reports, doses w'll be evaluated for the infant age groups and all organs via al'esignated path-ways from radioiodines and particulates measured in the gaseous effluents according to the sampl'ng and ana'ses requ'ed in Technical Specification Table 4.11-2.

The following steps provide a detailed ezplanation of how the dose

's calculated for the given pathways:

2.6.1 The Tnhalation Dose Pathway Method:

NOT:-:

The H-3 dose should be ca'culated as per 2.6.4.

Dete~jne the aool icable (g/Q)D rom Table &2 for the location where

=he receptor is located.

This value is common to each nucl'de(i).

ST LUCT.E P~~XT

- ODC.f

Page (cent) 2.6. 1 (cont) 2.6.1.2 Determine the R,

zac or of nucl'de(') fo" the organ r and age grouo rom Table G-3.

2.6.1.3 Obtain the micro-Curies (Q-) of nuclide.(i) f"om the radioactive gas waste management logs for the release source(s) unde considerat.'on during the time interval.

2.6.1.4 Solve for Di D.

~ 3.17xl0 3i.(:C/Q)DQ.

i D

mrem from nucde(i) 2.6. 1.5 Perform steps

2. 6. 1.2 "hrougn 2.

. 1.4 for each nucl'de(i) reported during the time interval for each organ.

2.6.1.6 The inhalation dose to organ r of the spec'z ed age group is determined by summing the D. Dose of each nuclide(i)

DEnha

? zion (Age Group) 1 2

n nrem Re er to 2. 6.5 to determine the total cose to organ z from radioiodines

& 8D Part culates; 2.6.2 The Grounc Plane Dose Pathway method:

NOTE:

Total Plane Tr'tium dose via the ground plane is sero.

The 3ocy is the only organ considered for tne Ground pathway dose.

2 0,2,1 Determine the applicable (D7() from Table &2 for the location where the receptor is located.

Th's (D/Q) value is common to each nuclide(i).

2.6,2.2 Determine the Ri zactor oz nucde(i) for the tota'ody from Table G-4.

The ground plane pathway dose is tne s

me for all age groups.

2-6-2.3 Obta'n the micro-Cur es (Q.) of nuclide(i) from the rad. oact've gas waste management ogs for the source under conside" tion.

Page

"'3 2.6 (conc)

2. 6.2 (cont)

2. 5.2.4 Solve or D.i D.

= 3.17x10 R. (D7$)Q.

mrem for nuclide(i)

2. 6.2.5

2. 6.2.6 Perform steps

2. 6.2.2 through 2. 6.2.4 =or each nucl'de(i) eported during the time interva The Ground Plane dose to the total body is determined by summing the D'ose of each nuclide(i)

D

~D

+D

+ -+D Gr.Pl.-TSody 1

2 mrem Refer to step 2.6.5 to calculat total organ dose.

2.6.3 The Grass-Cow/Goat-~sfilk Dose Pathway 'method:

NOTE:

Tritium does is calculated as per 2.6.,4 2.6.3.1 A cow, or a goat, will be the contro'lng animal; ie.

dose will not be the sum of eacn a'nimal, as the human receptor is assumed to drink milk from only the most restrictive an'mal.

Re e>> to Tab..'<e l&3 to determi.".e vh'ch an'ma's controlling based on its (D/0).

2. 6.3.2 Dete~ne the cose factor R. for nucl'de('), for C

organ t, from 2, 6.3.2.l From Table G-5 =or a cow, or;

2. 6.3

~ 2 ~ 2

rom Table G-6 for a goat.

2 Q ~ 3 ~ 3 the limited analys eooroach is being us limit, the cal culat'on to the in"ant t..yroic.

Obtain the m'cro-Cur'es (Q. ) of nuc 'de(')

from the radioactive gas waste management logs or the release sou ce urder cons derat'on during the time nterval.

ST lUCTE PL4NT ODI 'f

Pae (4

2.6 (cont) 5,3 (cont)

2. 6.3.4 Solve for D.l D. = 3.17xl0 8R.(D~Q)Q.

mzem fzom nuclide(i) 2.6.3.5 Perform steps 2.6.3.2 through 2.o.3.4 for e"-ch nuc'ide(')'eported

'dur"ng the t'-e intewal.

Only the radioiodines need to be, included iZ the limited analysis approach is used.

2. 6.3. 6'he Grass-Cow-Hi3.k (or Grass-Goat- !ilk) oathway dose to organ v 's determined by summing the 9i dose of each nucl'de(i).

D

~or D

X

=D

+D

+ -+D

=

mrem G-C-H ~

G-G-i!)

1 2

n The dose to each organ should oe c*'culatec 'n the same manner with steps 2.6'.3.2 through 2.6.3.6.

Refer to step 2.6.5 to determine the total cose to organ r from zadioiodinesg SD Part'cul tes.

I. the limited analysis aporoach is being used the infant'thyroid dose via the grass-cow(go*

).-

milk oat'hway is the only dose that neecs o

be.

detezm'nec.

Sec"ion 2.6.5 can be omitted.

2.o.4

he Gaseous Tritium Dose (r,ach ?athwav)

)!ethod:

2.6.4.1 The controlling locat'ons for the pathway(s) has alreacy been detezm'ned by".

Inhalation - as oez 2.6.1.1 Ground Plane not aoplicable foz H-3 Grass-Cow/Goat-~iL;lk as per 2.6.3.1 2.6.4.2 Tritium d'ose ca'culations use the depleted

(:0/Q)

'nstead (DjQ).

Table H-2 descr'oes w'nere the (gQ) value should be obtained

=rom.

2. 6.4.3 Determine the Pathway Trit'um dose factor (R.,

. rl-3 for the organ

-, of interest rrom the ab'e specified below.

MILK AGr.

Infant I>i r!ALATIONi CGil GOAT G-6 T Li.'CI"= ?LQT

- GDC'!

0 0

0

2age 45 2.6 (con

)

2;-6.4 (conc)

2. 6.4.4 Obtain the miczo-Cur es (0) of Tritium from t..e radioactive gas waste manage e..c 'ogs (for pro-jected doses - the m'cro-Curies oz nuc ide(i) to be projected), for the release source(s) under consideration during.

he time interval.

he dose can be calculated from a single release

source, but che total dose zor S.T.S. limits or auarteriy reports shall be from all gaseous release sources.

2.6.4.5 Solve for Dq 3

H D

3.17xlO R,

(X/Q)

Q H-3 mrem from Trit.'um 'n che speci f'd pa cn"ay =or og an of the specified age group.

2.6.5 Determininz che Total Organ Dose from

~ odires, SD-Particulates, and H-3 from Cumulat've Gaseous Releases

~k NOTE:

STS LCO dose l'mits for igSDP sha'l cons'de ose from all release sources zrom Sc. Lucie Unic 1.

2.6.5.1 The following p th;:ays shail be surged to arrive at the total dose co organ

. from

a. release

source, or if appl'cable to

STS, from all re'ease sources:

?AThNAY DOSE(mrem)

Step inhalation (iIISDP)

2. 6. 1.6 Ground Plane.(I"SDP)

(T. Body cr.')

2. 6.2.6 Grass-

.filk(~cSDo)

2. 6.3.7 inhalation (H-3)

Grass-

-M~1k(H-3)

2. 6.4.5

2. 6.4.5 Dose Sum of bove ST L~Ci-'LA'fT

-ODC~f

0

2.6 (cont) 2.o.5 (canc) 2 ~ Qo3

~ 2 The dose to each of the N'r.'iT's OB,G~NS sha

be calculated:

BOhr, LEVER, TZUOiD, KZ'Mr., LUhG )

TOT

~

3ODY

$'T-LLl The GiPANT organ rece.'v"'ng the hignes exposure relative to 'ts STS Limi.t is the most crit'ca'rg~

for the rad'oiodine g, BD Partic ates gaseous eifluents.

2.7 Proiectinu Dose for Radioactive Gaseous

".ifluents)

D scussion

- Technical Soecification 3.11.2.4 requires that the gaseous radwaste treatment system

'oe used.to reduce radioactive mater'als in waste prior to discharge when the projected dose.

due to gaseous ezfluents would exceed 0,2 mrzd for gama radiaticn and 0.4 m.ad for beta radiation.

The.

ollowing calculzt'on.

method

~s provided for determining the projected doses..a' method is be.sed on using the resul s of the calculat'ons oer=ormed in Sections 2.4 and 2.5.

2.7.1 Obtain the latest results of the monthly calculat'cns

- or the gamma a'r dose (Sect on 2.<)

'and the beta air doke i" performed (Section 2.5).

These doses can be obtainec iron the in-plant logs.

2.7.2 Div.'de these doses by tne number of days the p'anc was operational du ng the month.

2 ~ /o3 Hultiply the quot'ent by the number of days the plan=

is projected to be operat'onal during the next mon-h.

The product is the projected dose for the. next mon"h.

The. value should be adjusted as neoded to account any changes in failed-fuel or other 'dentif'b e operating conditions that could sign'=icant:y alter the ac releases.

2.7.4 the orojected dose are greater than 0.2 mracs ga. ea z'r dose or.04

~ mrzds beta a'r dose, the appropr'e subsystems of the geseous radwaste system shall be used to reduce the radioact vity levels pr'or to release.

3.0 40 C:~

.0 Dose "vaiuac Discuss'n' camn cment co a rea> lndlv dual

~

Qn al 1 ur..'.

uel cycle sources be 1mited to C 25 nrem co che cot 1 body or any organ (except thyroid, which is 1'mited co < 75 nrem) over a period of '2 consecut've months.

The fo>law'ng app oach should be used to demonstrat campliance with these dose limits.

This aoproach is based on HUREG-0133>

Section 3.8.

3.0.

1 Kvalua"ion Bases Dose evaluations co demonstrate co..pl'ance w'th the above dose limits need only be performeci if the quarte ly doses calculated in Sect'ons 1.4> 2.4 and 2.6 exceed, twice the dose limits of Tecnnical Speci=,icacions 3.11.1.2.a>

3. lj,.2,2a, and 3.11.2.3a, respectively',

ie, cuarterly doses, exce ding 3 nrem to tne total body (1.'qu'd releases),

10 nrem to any organ (licuic releases) 10 mrads gamma air dose, 20 mrads beta a'r dose>

or 15 mrem to the thy.oid or any organ from rad'oiodines and particulates (atmospheric releases),

Otherwise>

no eva'uations are requ'red and the remainder of chis sect'on car. be om'tted.

3.0.2 Doses "rom E 'ouid Releases Por the eva,iuation of coses to real individuals from liquid relea,ses>

the sane cele "at 'on.

metnod s emploved 'n,,

Sect'on 1.4 w.'ll be used.

However, more realist.'c assumptions will be made concern'ng che ci}ut'on anc ingestion'z

= sh and shelifisn by individuals who live'nd fish in t'.re area.

Also, the results of "he Radiolog.ca'.nvirannenta Monitoring program will be

>nc>uded in determining more real'stic dose to these real peoole by providing data on acc ai measured levels o" plant relac d radio,. clides in che environment.

3.0.3 Doses "rom Atmospheric Releases

""or the evaluat'on of doses to rea.l 'ndividuals from the atmospheric

releases, tne sane calculation methods as employed in Section 2.4 ana 2.6 w'1'e used.

n Section 2.4>

the tocal body dose factor ('(.) should be suost'tuted

""or the gamma air dose factar (>i.) ta det,e.n'ne the tocal

'oody dose.

Otherwise the same calculz ion seouence appi>es.

However>

more realistic assumpt'ons will be made concern'ng the actual location of reandividuals, the meteorological conc'" 'ans>

ar.d the car.sumption o" -ood (eg, milk).

Daca. obca'ned

=rom che latest

'and use census

(.echnical Specification 3.;2.2) should be used to. determine locat'ons for evaluat n" doses.'l,so>

the results o'he B.aciologicai "nvironmencal '!onicoring p" gran wi 1 be included in determining nore realistic doses co these rea peop}e by prov ding d*"

on actual

...easured

>.eve s o=

rad>aac"'v> ty and "'adiatian a" locat'ons o= interest.

> >>i 'Tr 7LA >T ODC'hj

Page 48

~.G S:"A.'2UUAL R~Z"OACT VZ "":"."Lv~r..lT BZPORT Discuss='on - The in=ozmacion conca'red

'n a semiannual report sha

not apply to any STS LCO.

The zepozted values aze case 'n ac" a'e'ease cona'tions instead oi hstozical conditions char.

the STS LCO cose calculac'ons are based on.

The STS LCO dose i~ts aze there-foze included in item 1, of the report, for information only.

The KZC's n item 2, oz the report, shall be those 'isted 'n Tab'es and G-1 of th's manual.

The average energy in item 3, oz che zeport, is noc applicable co the St. Lucie Plant.

he

zozmac, ozaer of nucl'des, and any values shown as an example in Tables 3.3 through 3.8, aze samples only.

Other formats are acceptable if they conta'n equivalent information.

A cable oz contents should also accompany the report.

The follow.'ng format should be used.

RADIOACTIVE ""FH.b:"HTS SUPPLPUNTAL INFORMATION 1.

Regulatory Limits:

1.1

"or Rad'oactive liquid waste effluencs:

a)

The once diluced concenczat'on of radioactive mat ia zeleasea from the site co unrestz'ccea areas (see : igure 5.1 in STS-A) shall be limited co the concentrac'ons spec'z"'ed in 10CHQO, Append'x 8, Tab'e II, Column 2

zor raaionuclides other than dissolved or entzainec noble gases.

The once diluced concenczation zoz cotal dissolved or entrained. noble gases shall be limited to 2 x 10 "

uCi/mi.

.P Tne aose or aose commit ent to an 'ndividual from ad'o-active materials in liquid e fiuents ze'eased to I.nzesczicted areas (see Pigure 5.1 in STS-A) sha 1 be limited a z'ng arv calendar auaztez to

< 1.5 mzem to the total boay and to 5 mrem co any organ and 3 mrem co the cocal boay and

< 10 mrem to any organ during any calendar year.

1.2 Por Radioactive Gaseous Haste Zffluencs:

a)

The instantaneous dose race in unzestzic ed areas (see Piguze 5.1 in the STS-A) due co radioactive materials released in gaseous effluents

=rom the site sha' be ii.'ed to the following values; The dose

".are limit. zor noble gases shall be

< 500 mzem/yz to the total body and

< 3000 mrem/yr to the skin, and The dose rate limit zrom I-131, Tr'tium, and particulates with half-1'ves greater than 8 days shall be less than 1500 mrem/yz to any organ.

ST.

LUCI"-

PLAUDIT ODCA

?age

~9 T

~ C-T-.==:,'.ITS -

-PPL~N.AL:i:0?-"='.Tz08 (C

t

egulator r imits:,cont)

%of Rzdioactive Gaseous

'uaste

"= iluenrs:

(cont)

The dose in unrestricted areas (see Figure 5.'n the

'TS-A) due to noole gases released in gaseous e fluents shall be limited to the following:

During any calendar quarter, to 5 mrad."or gama radat on and

< 10 mrad =or beta radiation and dur=ng any calendar year to

< 10 mrad

=or gamma radiation and

< 20 mrad for beta radiation.

c)

Th'e dose to an individual from radioiodines, radioactive materials in particulate

form, and radionucl'des other than noble gases with hali-> 'ves g ea e" than 8 davs in gaseous ez luents released to unrestricted areas (see Pigure 5.1 in the STS-A) shall be limited to the following:

During any calendar quarter ro

< 7.5 mrem to any organ, and dur'ng any calendar year to

< 15 mrem to any organ.

2.

'Aaximum Perm'ssible Concentraticns.

Pwr as per attached Table G-l.

Water as per attached Table L-l.

3.

Average energy.

oz fssion and activation gases in gaseous effluents

s not applicable to the St. Luc'e Plant.

measurements and Approximations oz Total Radioactivity.

A summary o=

1 quid ezfluent accounting ethods 's cescribed in Table 3.1.

A summary of gaseous ef luent accounting methods is described in Table 3.2.

ST.

LUCI=- PL4~T ODC~

0

3'~.OAC:

s=

== ~ v~F~S - Su&9~~ f:: T i:OR~K ON {con<<)

."e surments z"c.~pprozmat c"s o=- iot 'zcioact 'v='t-

~ ~

s <<~ca vt, (a)

Sa'plI'

<<or The e.or associated v'th volte measurement easur<<"g dev='ces, e c.

based on " brac'oc tolerances has been conse amative'y est~tee o be less thaa av"'4I c s,:'oc anc

-"es

. g.I (o)

Aaz 't'cal:" or;or Nucl'ces AveraRe "

~uxmu Lccuid Gaseous

'able 3.3.

Radioac"ive Lieu'd.'= uent Sa ply g a"d A~lys's 1

O'P Pg~l I VS i l

I YETV 7~

iiOR TA%C Rs MS:"S ST:.~4M G~KTOR 3LOND04H R~ RASHES C8 EAZCZ 0~~~ CC~~OSi PU~ T~v Y C"~&OS NOh~ Y CC~QSi:=

PRLICWPZ.

CA~C~A ~i

.RS Tr t'M Gross. Aloca Sr-89.

Sr-"".0 P=f cipa'a=a

=-.'=" rs and Dissolved Cases T-> -~ua l

h 0

~ s ~

~ 0 ~

/

L.S.

I G.:.P C.S.& L.S.

>.h.a.

L S*.

I

/~JAZZY CC~OST.:-

Sr-89 Sr-90 C.S.&L.S.

TAZL"- liOT~'H:

labor.'c Acid vaporator condensate

's no~lly recovered to the'Pr'-a~y Nace-.

Storage ank for recycl'ng hto the r ac"or coo art sys" an'oes

..ot con-tr"'bu-e to 'auid vasce e==

uenc, tot4's.

p<< li 4<< - g~ snec. ~ pulse heigh analysis us'n~ 'th"- Ce~an'~

detectors.

A11 peaks are ident='=ied and aua t.

L. S.

Li"used Scinr~~at'on count'"g C. S.

>> Cne

~ca>

Separac'on

/\\V ~

~

~ - Gas ":l~ Prcpor='onal Count='ng

WZ:QAC iv.

"="Li~r,FZS - SUPPLc~'hTAL:ViOR"R ON {cont)

~o gj

<easure enrs and Approximations oz Total Racioactiv'"y (cont)

(b) Analytical ".rror =or Nucdes (cont)

Tab'e 3.2 Radioact ve Gaseous i~aste Samoline and Ana vsis Gaseous Source Haste Gas Decay Tank Releases Samp l'ng Preauencv

-ach Tank Tppe of Analvsis Princioal Gama ""mitters i<ethod of Anzlvsis (G

C P) - o.h.a.

L.S.

Contain-ment Pu"ge Releases "ach Purge Princioal G~ ""mitters E-3 G,

C P) - o.h.a.

L.S.

Plant Vent Weekly Monthly Comoosite (Part 'culates) quarterly Composite (Particulates)

Princioal Gamma cn'tters 3

Gross Aloha Sr-90, 89 G

C. P) o.h.a.

P - G.F.P.

C.S.

o L.S.

G C

L.S.

C.S.

p.h.a Gaseous Grab Sample Charcoal Pilter Sample Part'culate Pilter Sa-ole Liquid Sc'nt'l'ation Count'ng Chemical Separation Gamma spectrum pulse he'ght analysis using Lithium Ger'manium detectors.

All peaks are identified and cuantif'ed.

Gas Plov Proportion"l Count"ng

- ODC.f

Vg FD HAD OACT:7:":.:

4 "4 S - SUPPL~~V"AL 'EbrORMTIO'0 (cont) 5.

Bat.cn Releases A.

Liqu'd 1.

2.

3 ~

4.

5.

5.

Number of batch releases:

Total t.'me oeriod oi batch releases:

Max'mum time pe iod for a batch release:

Average time period or a batch release:

>Znimum time period tor a batch release:

Average stream flow curing periods of release or effluent into a flow'ng st"earn:

u es

.Mnutes

~anutes

~wnutes G?N All ~&quid releases are summarized in tables B.

Gaseous 1.

2.

3.

5.

Number of batch releases:

Total time period for batch releases:

F~Dmum rime period for a batch release:

Average time per'od for batch releases:

Minimum time period for a batch release:

2'utes

!4'nutes

.nut, es

~Knutes All gaseous waste releases are summar'zed in tables 6.

Unplanned Releases A.

Liouid 1.

Number of releases:

2.

Total act'vity releases:

Cur"'s B.

Gaseous 3..

Number of releases:

2.

Total activity released:

Curies C.

See attachments ('f applicable) for:

L ~

2.

0 ~

A description oi the event and equipment involved.

Cause(s) for the unplanned release.

Actions taken to prevent a recurrence.

Consequences oi the unplanned release.

7 ~

Descr 'tion of dose assessment, of radiation cose

=rom tad'oact,.'ve e fluents to the general public due to the'r act'vit'es inside the unrestricted area (see f'"ure 5-1

n STS-A) dur" ng the report-ing period:

ST.

LUCT:-

- LANT

- ODM

PR6e 33 FLGR:DR POWER

" LIGHT CGltPRfY ST.

LUCIE U'fI SENIhttNURL RE. vF;T JULY Xi "97.

THRC JGH CECEflF:ER 31.

197-'RBLE 3

3

/

LIQUID EFFLUEHTS SUNNRTIOtf GF RLL FELERSES

'UtfiT QURRTERQ QURRTERQ R.'ISSIGt(

FiND RCTIVRTIGtf F'FGDfJCTS TOTRL RELEFt= E-NGT IttCLUDIf tG TRI7 IUt'ti GR'S/

RLPHR >

CI

2. 379 E

2

9. ~"19 E RVEF'FiGE DILUTED CGf tCEtt-TRFiTIOH DiJPING PERIOD UCI/tlL

i. 983 E -8

7. 439 E -8 B.

TRIT IUN TOtRL REL":RSE 2.

RVERRGE DILUTED'GHCEH-TF;RTIGtt DtJRIt(G PERIOD DI-SvLVED RttD EHTF.'RIHED GRSE-TOTF!L RELE¹E 2.

RVEF;RGE DILUTED C tfCEN-TRRTIOH DUPIHG PERIVD D.

GROSS RLPHR RRD IGFiCTIVITY TGTFIL RELE,i-E CI UCIrt1L CI UCIPt1L CI 2.G29 E

1 4.

09 E

4 691 E -6

3. 416

7. 379 E -1

-2:9" 9 E

6. 55Q E -G

2. 2" 2

.GG8 E

8

.GGG E

8 E.

VOLUflE GF WFI=T" RELERSED (PRIOR TO DILUTIGtf>

LITERS E XS9 E

6

1. 559 F

6 r,.

VOLUt".E OF DILUTION WRTER USED DURittG PERIvD L'IT X99 E 10

~

3~M E 1u

~

~

FLOR IDF{ POllER 'IGHT COtlP..t tY

.ST.

LUCIE UtlIT tt SEt1IF{ttt{UF{L REPORT TRBLE'. 4.: LIQUID EFFLUEHTS 19( B THROUGH DECE!1-ER <<ii 19 78 COtlTItlUOUS t<OCE BF{TCH l'10DE ttVCLIDES RELEASED I I-1 5 HFI-24 CP-51 t1tl-54 C>3-FE-59 CO-68 ZH-65 HI-65 RG-1'l1 Sl (-11<<

SB ir..

td-187 HP-239 Po o5 HO-99 P,U-1C>-

CS-1<<4 CS-136 C<<

BR-14>3 CE-141 BR-82 ZR-97 SB-125 CE-144 SR-B9 SR-8 VtlIDE!lTIFIED TOTF'L FOf=:

PERIOD (RBQVE)

UNIT CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI.

C!

CI CI CI CI CI CI CI CI CI CI CI CI C!

CI CI CI CI QURRTERQ

. G>3>3 E

0

.GGO E

>3

~ Grs>3 E

8

.Qi38 F

8

. Gi38 E

8

. 8>3>3 E

8

. GOQ E

8

. Griri E 0

.C>GG E

8

. GQQ E

8 r~C>r>

E

~ Q>1>3 E

Q

. QAG

.G>30 E

8

.880 E

0

.GQO E

0

. GOrJ E

. Or>Q EQ GQi E

0

. G>3Q E

0

.Qi3u E

8

. GuQ E

v

. GOO E

0

.GGO

"=

8

.GOv E

8

. GGO E

8

.QQi3 E

8 GORY> c Q

. Qi3i3 E 8

.0>30 E

0

. QOG E

8

.GQv E,

Ci

.GQQ E

8 QQO

="8 C'UPRTEFN

. 08>3

.GOG E

. QQG Gr-Q E

. 888 c

~ 'QC>i s

. C>VQ E

. GOv E

G>3>3 E

. 000 E

. C~Ori

. 800 E

. OC>0 E

. QC>0 E

. >>rj>3

. fyQQ

. GuG E

. GQG E

. GOQ E

. QO>3

. GQ>3 E

. GOO

. OC>>3

. 00>3

GGO E,

. GGG E

. C~OG E

. G>3Q.E QQQ E

. Gvv' QOQ

.GGO E

.GQQ E

0

>3 0

8 0

0 8

8 8

Ci 0

Q 6

>3 0

8 0

8 8

8 v

8 8

0 u

8 0

8 8

0 QUF>, TEP"

1. ~~9 E -2 a.e:;G c

1. 6:-'9 E -4 7J Q

9. 479 E -<<

4. 27>3 E

7.

39 E

2 218

6. 199 E

4. 280 F

4. ~<0

9. 990 E -4 n>Q E

~

>. Ci80 c

. QOQ EQ

4. 599 E

"'. 848 E,

4. 610 E -5 2 599 E

5

.QGi3 E

0

1. 570 E -3

9. 209 E -4

1. 6" 9 E -3

. QuCi E cog c'

800

"=

>3

2. 375 QUF>RTER{'0'"

~. 988 c -5

1. 62v E

2 7

wt Ig<<E A

~

<<e

4. 279 F -3

1. 269 E -1

1. "'Z9 E

5. 970 E

4. 4<<9 E

8'.

43>3 E -4

.228 E -2

<<. 068 E

7-"8 E 6

E

9. 049 E

4. 770 E -s 6 219 E

3

.vGu E

0 c~9 c RR-41 YiE-1 if1

\\JN

'rlE-i<<5 CI CI CI CI CI CI

, QQsi

. GQQ

. Ovi3

. O'00

. QOC>

Q>3' E

8 E

0 E

0 F

0 E

0

. GQQ

. QO>3

>30>3

. Gvi3

. OQG

. vOv E

0 0

6.

E 0

'5.

E 0

E, 0

2.

E u

6.

390 689

~ ~

f 450 860 c,

5 E -3 c

5 O'8

1. 719

". 179

4. 689 E

cc c,

E

GLOR".DA P04~

& LEG;.Z CO~Ah~

St.

Luce Unit:J Table 3.5 Liquid Effluents

<< Dose Samzation Age Group:

Adult Exposure interval:

El OU1 Location:

Any Adult througn Pish

& Shellfish Pathway to ORGAN Ouarter J

Ouarte>>

DOSE (m an)

LiV:"R THYROID KIDNEY Gi T~l T.

30DY ST.

LUCRE P'NT ODC'f

FLOF:IDR PO'vtER 4 LIGHT COt1PRttY 5 i.

LUCIF UttITtl SEt1IAttttURL PE~OP.T JULY ir 1378 THROUGH DE'l1cER AI

~ V TABLE 3 ~6:

GR-EOUS EFF LUEllTS SUt1t1RTIOtl OF RLELEtRSES Ull IT QUFiF;TERn QUPPTEc",r R.

FI SIOtt RHD RCTIVRTICtt GR-c,.

TOTAL RELEASE CI 7.077 E

3

&.7S& E 2.

FA'E.";RG RELEASE PFtTF FOP. PERIOD UCI '-EC c.976E 2

"ZS E B.

ICDIt<ES TOTAL IODIttE-13~

CI R 976 E -2

4. GCG E -2 2.

5"ERRGE RELEASE RFtTE FOR PERIOD UC.~SEC e'O7 c'og g

3 C.

PARTICULATES l

PARTICULATES T ~M2 >

DRYS 2.

AVERAGE RELEASE RATE FOF; PEfÃOD CI 970 c.,

2 UCIi'SEC

. 2. SG7 E -3

4. 66~ E"-2 5&RE GROSS FILPHFl PRD I CACTI'v'IT IY TRITIU!1 CI

. GGG E G

. GGQ E

0 TOTRL RELEASE CI

%.261 E

2

2. 526 E

2 2

RVE..RQE RELERSF RRT~

FOR PERIOD UCI/SEC 6QG E

3.

'0 '

T.

LUCZ:.

PLAIT ODC:I

Fl OP IDR PrJ'ldER 4~ LIGHT Cot'tPRHY ST.

LUCIc. UttIT SEl1IRttltUAL REPORT

'ULY 1 197B TRBLE 3. 7:

GFISEOUS Er FLUEttTS I

COttTIttUOUS fCODE THROUGH DECFMBER 31<

197B BRTCH tIODE t(UCLIDES RELERSED UttIT QUARTER ~

FISSIOtt GASES QURRTERn

'URRTERA QUFiRTER" RR-41 B5 nclq VLR B7 KR-Bo

-1 1M 4<X-1. 3M

<Yr-135M Ut<IDEtliIF I ED TOTAL FOR PERIOD'ABOVE)

CI CI CI CI CI CI CI CI CI CI CI CI CI

. GriG

.. OGO

. 000

. GCiG

. GGG

. GriG 7

B4c>

3. 569

3. 669

. OCio

. Grio

. GGO E

"G E

G E

G E

0 E

G E

0ri C

E 0

A C

E 0

E 0

E 0

8.302 E

2

. Goo

, 5>OG 419

. GGG

. Gorj

4. 109 0~9

~ 000

. OGv

. GOG E

0 0

E 0

E 0

E G

E G

c' E

0 E

G c.

0 4.267 E

3

3. 429 E

1. 939 E

p

.< cr9

7. 479 E

4. 139 E

4. -'G9 E

5. G39 E

". 049 c.

2;439 E

459 E

oor<

6. 249 E

0

~

2 1

1 G

2.

9.

3.

3.

C

~

L

>9 r.9@<

G< '0 nr~9 car4 44>>

r g w9 GVO E

G C

E E

2 E

2 E

C E

1 E

0 F

1 E

G

5. 494. E 3

IOD It/ES I-D I-5 3 I-135 TOTRL FOR PERIOD

<ABOVE)

CI

%=29 E -2

~049 E -2 CI 43?9E 1,279 c

1 CI

.GAG E 0

.GGG E

G CI

4. 582 E -"

2. 4B4 E -1

7. 460 E -3

4. 5?0 E -6

. OGG E

G

7. 464 E -3

2. 609 E

1. 12v E

2. 619 E

C

~ p C'

3.

PRRTI CULRTES c'n SR-u<

SR-90 CI

'.GriG E

0 3.

B9

-" -6

.OGO E

0

.GCG

=

0 CI 4.=00 c -=-

.OOv E

G

.OOG O

.Gov

="

0 CI 8.220 F -6:00G E

0

.000 E

G

.GGO E

G

'- ODC:f

E/I FI.ORTI)A I'OWI'.R 6 I,IGIIT C(81PANY St.

I,>>cJ.e Un.l.L'I Tlble 3.8 Gaseous Effluents Dose S>>mmation guartertI Age Group:

Infant Exposure Intervall From thrOugll Pal L'IIWagj BONI.'ll re Ill I.IVER Illrelll TIIYROID mrem)

KIDNEY AlrcIll I.UNG mrem GI-LII Illr C III T.

HOI)Y

~lln'e Ill)

Ground Plane Grass-

-Hilk In I1a 1 eltJ 0 n Total Sector:

Range:

mJ.l es Cow/Goat Sector:

Range:

~iilee Noble Gllses Quarter (Above time J>>terval) mrnd Calendar Year (mrad)

Gallllna AIr Dos e Beta AI.r Dose Sector:

~gao a:

0.91 mlles IQ IO on Vt 1 Tile dose values below were calc>>lated using act>>a1 meteorological.

daLa dur lnl, I bu spul I I luil time interval witll met data r~educed as per Reg.

G>>ide 1.111, Hllrch 1976.

%g

Page i9 APPENDS(

A

HPC, DOSE

."ACTOR, HISTORIC'. ~~i.TEOROLOGZCPJ.

TABLES

- ODC';1

TABLE L-1 Page -0

'.maximum P emissible Concentrac.ons in Mater.n Unrestr cted A"eas I

Nuclide

;3

~

Na-24 P-32 Cr-51

'vg 54

<w-56 Fe-55 Ee-59 Co-57 Co-58 Co-60 Ni-63 Cu-64 Zn-65 Zn-69

,Br-82 Br-83 Br-84 Br-85 Rb-86

. b-88

.Rb-89

'Sr-89 Sr-90 Sr-91 Sr-92 WC (~Ci/ml) 3 E

3 3 E-5 2 E-5 2 E 3

1 E-4 1 E-4 8 E-4 5 E-5 4 E-4 9 E-5,

'3 E-5 1 E-4 2 E-4 1 E-4 2

D 3

4 E-5 3 E-6 None2 None 2 E-5 None None 3 ""-7 5 E-5 6 E-5 Nucl'de Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Hb-97 Ho-99 TC-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-110m Sn-113 in-113m Sb-122 Sb-124

'b-125 Te-125M Te-127m Te-3.27 Te-129m 2

3 3

6 3

6 2

1

, 9

'3 No 8

1 1

3 8

E 3

E-5 E-5

".-5 5

E-5 E-4 E-4 E-5 E 3 ne E-5 E-4 E

5 E;5 E-5 1

E 3

3 E-5 2 E-5 4

-4 5 E-5 2 E-4

~C (uCi/ml) t.

Nuc 1 de Te-129 Te-1 31m Te-131 Te-132 i-130 i-131 L 132 i-133 I-134

'i'-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 L'a-140 La-1 42 Ce-141

'e-143 Ce-144 P

144 V-187 Hp-239

ZC (,uC'ml)

.8 E-4 4 E-5 None 2 E-5 3 E-6 3 E-7 8 E-6 1 E-6 2 E-5 4 E-6 9 E-6 6 E-5 2 E-5 Hone None 2 E-5 Hone

'None 2 E-5 None 9 E-5 4.E-.5 1 E-5 None 6 E-5 1 E-4 (2) if a nuc1'ae is not 1'sted, refer to 10 C:R 20, Appendix B, and use the most consevat've insolu'ole/soluble lPC wnere they a'e give".. in Table ii, Column 2.

Nore-(As pe" 10 CPR 20, Appendiv B)

'No WC limit "or any s"'ngle radionuclide not 1'sted above with aecay mode other than apha emission or spontaneous fission and I

with radioactive half-life less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

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.wzimum Permissible Ccncentrations in Air in Unrestricted

.reas Nucde

.i'PC pCi/cc Nuclide "PC ~Ci/cc Ar-41 Kr-83m K"-85m K"-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 H-3 P-32 Cr-51 i~~w-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Rb-86 Sr-89 Sr-90 Rb-88 4 E-8 3 E-8 1'-7 3 E-7 2 E-8 2 E-8 3 E-8 3 E-8 4 E-7 3 E-7 E-7 3 E-8 1 E-7 3 E-8 3 E;8 2

E 7

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'I-132 E-133 T-134 l-135 Cs-134 Cs-136 Cs-137 Ba-140 La-140 Ce-141 Ce-144 1

1 3

3 2

3 2

2 1

1 7

9 4

1 1

1 1

3 4

6 1

6 5

1 0

2 9

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E-9 E-9

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E-9 E-10 o

E-10 E-9 E-9 10 Ef a nucl'de is not listed, ref e" to 10 CFR 20, Appendix B, and use the most conservat've insoluble/so ub e K'C vhere they are given in Table li., Column 1.

E 4

ST.

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'I'ABI.E G-2 DOSE FACTOllS FOR NOBLE GASES" lhQ(lionuclide I'-83)n Kr-85lll Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-l35m Xe-135 Xe-137 Xe-138 Ar-41 Total Body Dose 1'actor Ki (mrem/yr per IICi/m )

7. 5GE-02 ">

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2. 51L-I.02

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8. 84i E.I.03 Sl<in Dose Factor Li

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l. 46L-I-03

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9. 94L'-1-02

3. 061';I.02

7. 11E.I.02 I. 86 r;-I.03

1. 221'.+04

4. 13L'I.03 2.69E+03 Gamma Air.

Dose Factor Hi (mrnd/yr per IICi/))i )

l. 931!a 01

1. 23r;I-03

1. 72E.I.O I

6. 17 '3

1. 52L'.I.04

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1. 63L) I.04

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3. 53'.02 3.36r+03

1. 92L'-I.03

l. 51F;I 03 9.21L-I03 9.30L'+03 Beta hir Dose I'actor.

Hi (mrail/yr l)er IICi/m )

2. 881 I.02

1. 97E.I 03

1. 95)';I 03 1.03LI04 2.93L'IO3,

1. OGI';I 04 7.83E-I03

1. 111 I 03

1. 48E.H)3

1. 05F:I 03 7.39l':I02 2.4GI:I03

1. 27I::I 04 4.75I':I03 3.28EI03

"'The listed do.e factors are for radionuclides that i))ay be detected in gaseous cffluents.

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I Ut;I/Sfc t(ELLA~t kA(f OF EACII ISOIOI E II( A<<o A;VALUE of I. foR x/a. oLI'Lflfo X/II A<to I(tl Allvt otluSI(lu<<

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?age 75 TABL""

Selectina the Appropriate Long Te~ (X/0) for Dose Calcu'at'ons Tnvolvina Noble Gases or:

(1)

Total body dose from instantaneous releases (2)

Skin dose from instantaneous releases (3)

Gamma air dose (cumulative).

(4)

Beta air dose (cumulative)

Type of Dose Calculation Limiting Range (miles)

Limiting Sector (X/Q) Value sec/m3 Xns tan taneous-LCO 0.97 1.6 x 10 6

1/31 days LCO Quaiterly LCO yearly

'2 Consecutive

-onths LCO Semi-A~ual Reoort 0.97 0.97 0.97 0.97 1.

Normally (X/'Q) ~ 1.6 x.10 6 sec/m 2.

Ray use option of actual mererolo-gical data for t'me of concern r

Hot e-'ore-1 The (X/Q)'as to be, calculated based on actual meterological data that occurred during the per'od of 'nterest.

The sector of 'nterest is.HA because the limiting X/Q will oe determined

.rom the actual meterological data and may occur in any sector.

0.97 miles - Corresponds to the minimum site boundary distance in the north direction and 0.97 miles was chosen for al'ther sectors

=or ease of calculations when the averaging is done :or'uarterly reports.

ODCN

a TA11LI'. H-2 Selecting tile Appropriate Long Term (X/(})D or (D/g) for Dose Calculations Involving Radioiodines 6

0 D Particulates for:

(1) Inllalation, (2) Tritium (All gas patllways),

(3) Groun<l Plane Type of Dose Calculation Limiting Range Hiles Limiting Sector (OI.)

(D/Q) 1/m Instantaneous LCO 0.97 NW g/N1A I,l x lO 8,<x lO (quarterly for Seuliannual Reports 0.97 0.97 h

1/31 day'CO, gtr - yearly I.CO, 12 consecutive mu>>tll LCO.

0. 97 0.97 1.5 x]O Q,2. x lo (Ol.) Over land areas only A.

'1'o be deLermlned by re(luctlon of actulll llleL'ata occurriug durinp eacll uuarLer.

~V PI IN IP

Page 77 TABLE ~-3 Selectinz the AooroDriate Lone Term (D/0) for Dose Calculations Tnvolvine Rad'oiod'nes a

8 D Particulates

=or Grass-Cow-Milk or Grass-Goat Milk:

l Tvpe o

Dose Calculat'on Limiting Range Lim'ing Sector (D/Q) value 1/m-

'Release Rate-LCO

":,1/31 Days LCO I

Quarterly-Yearly LCO

,.12 Consecutive

Months LCO

'Se

'-annual Report A.

The worst cow or. goat as per locations from land census.

f no "ilk animal in anv sec".or, assume a cow at 4.5

'les 'n t'h e highes-(D/Q) sector over land.

B.

The historical (D/Q) of all land sectors wi"n the wors-cow or goat from each sector as reported in the Land Census.

A 4.5 mile cow should be assumed in the worst sector

'when no milk animal is reported.

C.

The (D/Q) of all land sectors as reported in the Land Census.

Actual met data should be used for the reporti g perod.

A 4.5 mile cow should be assumed

'n land sectors where no milk animal was reported.

he h'storical wind frequency fractions for each sector are listed in

able

.'1-8.

ST LUCT.E

~~~li

- ODCN L

VI TABI,E H /I TERRAIH CORRECTION FACTORS

>-3 O

n

~>:

FLOftlDA PUufA At)D I.l/I)T Ctl ~

5 T ~

Lt)CIE t)N I T tiltTCII)ttsnt< ISLAHII FLDIITna IIA)IES At)t) t)00)IE JAI) t)0 ~ I 45')0 -

112 TE)It)alt) CD)tt)ECTII)tt FACID)ts tt'I)FF I ST)ta)0)tT Llt)EI PE)t )no AF ttECufID I

tlr2)r/I In Ar3lr7)I t)ASE t) tsTatJCf ltt )IILf5 r KTLD)IETFt/S AF Tt)

DESIG)t SECT DIST

.25

)Il

~ 40

~ 75 I ~ 21

) "2'5 2'l

) ~ 75 2.u2 2'5 3 ~ hi?

2.75 4'2 3'5 5.23 3,75 '

03 4*25 h 04 75 7

/>4 t.lut.'

~

ttt 0 ~

t'IIE o.

0 ~

ESE n.

st.

n.

ssF.

o.

s n.

SSu o ~

Su n.

u'.iu 0 ~

u 0 ~

uttu n ~

ttu 0

)Ittu 0 ~

tt 0 ~

1.9nh 1.007 I ~ 452 I ~ /i62

).t9O I. t))A

).tt)2

1. 39h

).S34 I ~ 40'5 I.t 2n

) ~ 651 1,720 1.60)

I ~ 739

)

F 016 1.5/6

).SI)l I.z )n

)

F 425

)

~ 4)I'I I ~ 6') I I i tit)h 1 ~:)?. I I ~ 4) I Ccj?

I

)1'I I 415 I ~ 4 lo 1.>.n7 I ~ 4AU I ~ 574 I o4/>5 4/> I I.)72 I ~ 2/'/

I ~ ii) >)

I ~ 470 I ltn

)-125 I ~ ?9>>

I ~ i>94 ~

I ~ 21)I-1.?9A I

~ i'.t'/

I ~ 2'> 7

).3)6 I ~ '3tl9 I ~ CAC I' 3') I

).AUI I ~ )91

~ I.?60

) F 427 IIl)>'

~ Anl I I'/?

).2'33 I ~ I '/3 I ~ 2) II I ~ It)5 I..)7:)

Ii>>?.12 I ".205 3'jt)

I ~ 310 1.047 I ~ 151 I ~ 246 435 I 2/0 I ~ Ioo l,?AS I ~ 2no

).n02 I

)SC I ~ ISA I ~ 119 I ~ I /2 I ~ 25/

1.318 I. 25'3 1.033 I

)23 1.190 1.361 1,26.)

1-127 I ~ 132 I.2?2

).n) I O'/9 I ~ 133 1.07U 1,122 I ~ 263 I 334 l,)64 1.0')7 1.134 1.366 1.229 I ~ 073 1.135 1.160 099 1.001

).125

).OU3 1.)35 1.205 l>306 1.120

.941 I ~ I i? I

).n 34 I 311 I ~ 19:I I

06;I

) > I lh I Ihn 1,056 1.067 I ~ 0t)5 9'35 1.000 I ~ 267 I ~ 346 I

I A)

~ 906 I >) 2'l I. 03i'.

1.279 I ~ I 7.l

).n,7

).0'/7 1.19U I 034 1.091

).03')

.99U I. 0'/9 1.23l I ~ llo I ~ I I />

.9n2 I l?d

.9/>A 1.2)9 1.)SI I

024 I.nho I I')4 I.AAC I.nnl l,ncs

.9'/)I I ~ 0'I I I.i'I)

NOT)t l A))y l)IL'er))t)lUL)OIIs bl'I wee)I sLUte(I III'Ile/I),es will be IIo)Ie by.Io);-lo);

lAIILr. H-5 IIXSTOltXCAI. LONG i'EliH (X/ )

(fre nenc corrected)

TCIIIIAIt) I IIFCIACULATlntt AIIJUSIII)

PIIOGIIA<I Attrtxon9 vEttslott -

I lzlnrr6 Fl.At)it)A PALEA AHO LIGIIT Cn.

5'I ~

I.I)C IF. VIII1 l

IIUTctlltlsntt I 5I.Atto ~ f'l.ntt I AA I)A)ICS At)0 IIOOOC JOI)

IIO I 4598 - I 12 AVCIIAGC AWtIUAL IIELATIVC COWCEWTOAT IOII )SEC ~ ICUOIC IIETEA)

PEnlon nf IICtottu I

9i Irr6 10 Ar3Iirn OASE OISTAIICE III IIILFS / KILOHETETIS AfTn OC 5 I Gtt SECT l)IST

~ 25

~ 15 I 25 I <75 III

<40 I.7l 2.0l Z.A2 2'5 3'2 2'S 4'2 3.25 5 23 3 ~ 15 6'3 4'5 F 04 4 ~ 15 7'4 n<<E o.

Uf; n.

CIIE o.

E'.

CSE 0 ~

SC 0 ~

55E n.

5 0 ~

554 0 ~

S<t 0.

vstt n.

n.

M<IV 0 ~

ltu 0.

Ittlu 0.

n.

tttAt)If'll Of

<>ntftt Of Ittt<<IICII Ol

~ III>>I)It)I OF I. If.-05 1.3f-ns 9 3E-06 9.nt-o6 I.7C-05 I.4L-OS I ~ II'-05 6.2f.-06 5 ~ 1L-06

6. I f.-06 7 ~ lt-06 7.6C-06 I.4f"05 I ~ f<f -05 I ~ 5C-05 9.lf.-A6 vAI. IO nl)SCnvAT lntts It)VAI.IO nllSEIIVAIIl)Its QAI.)ts.l.nvfIt Lf.vtL cAL)ts ltl'PC)I LEvCL I.1C-06 I.nf.-nr 4.'SF.-01 2 ~ IE-06 0-')C-01 5. IC-01 I.4f-ot< 6.2C-or 3.1E-or I. 6l:-06 6. Sf.- 01 1. TC-0 1 l.vf.-o6 A. If.-07 4 ~ nf.-or 2 ~ 4f.-06 9, rf;-01 5 ~ rf:-01 I. )f-06 1. 3F:-01 4 ~ 3L'-01 I.nt-o6 4.2F.-O) z.sc-or, 9.oF.-or 4.nc-or z.lt.-nr 9.4C-or 3.9C-or 2;7C-01 I ~ IF.-06

'< ~ 6F-01 Z ~ 1C-01 I ~ 2C-06 5 ~ 2E-01 2.')f-01 2< IF.-06 ') ~ lC."01 S.ZC" 0 I 2.IF.-n6 l.of.-n6 5. )c-0 1 2.2L'-06 ').6C-01 S.SC-or

'I.4f.-06 6 ~ 1f.-n I '3.6L-O )

I 1 I 35 3)IS 95;.

~

5<<

3, IE-07 3.4E"01 2.5C-01 Z. SC-01 3.2C-01 of-or 2<')C-01 I.AE-01 I.6L-OT I.6C-or I

< TC-01 2.OE-or 3 'C-07 3-<)C"07 1.6C-O) 2 ~ At"01 2.2E-or I.1E-07 2.4C-or I.TC-or l.9c-nr I.JE-or l.nE-or l.4E-07 2-4C" 01 l.nE-o1

2. 9E-0 1

2. 3E-07 2.IE-01 I ~ 6C-01 I. E-or I.nc-or ITIC-01 0.9C"00 I. IE-or 0.6C-oo I,3E-07 I ~ OC-07 l.3C-07 I.OC-01 2 6E-01 2 'E-07 2.0E-07 Z. IE-01 2 'E-01 2.0C-O)

I ~ AE-07 1.4C"07 I ~ 5E-07 I ~ 4C"07 I ~ IE-01 1.2E,-Or I.4C-or I <')F."01 I ~ 3E-0 1 A ~ 0E"00 7 'E"On 7<OE-00 O<OE-00 tlat 4E-00 l<SC-07 I.7C"01 l.6E-01 I'E-07 I ~ ZE-07 I ~ IC"07 n<AE-nn 9.9f'.-00 I. IE-or I ~ 4C-07 l.lf.-or 6 'E-00 5'l.-nn 6 ~ OF-00 6.5C-OO 1.2E-OO I ~ 2E-07 l,4E-AT I <3C-01 9 'E-00 I.oC-or 9.nC-oo

1. IE-OII 0

4F.-OA

).nf.-oo I <2t-01 9.IC-on 5.SC-oo 4.0C-un

5. IC-On 5<4E"00 6.IC-OO I ~ AC-01 I'E-07 I'E-01 7.')C-Ou NO'l'E l Any 9nterpnltttfono between otatetl mlleageo will be done by log-log

'fhDLE kf-6 IIISTORIGAL LONG TERN DEPLE'fED (X/A)D (fre uenc corrected

/se2 TEN(t4(N r

>IFCI(iCuLAIION AO)uS(LO I>RU( I(AH At(NXOQ )

vfitS ION - 11/I or 76 I'(.OIII(IA I>ouER At(t) I. IC>til CD.

57. LtiCIE Iinl7 1

II(ITC>II((SON I SLAt)D > fLntt I(IA DAI(f5 A(ID HUO(tf JUU IIU ~ I 59U -

112 AVE))AGE At)ttt)AI. (IfLAT IVE CONCEII(t)AIIUN DEPLElEI)

(SEC/CuulC )IE(ftt)

PElt I 0() Of (IECOIIO

)

9/ I'/76 10 tt/31/1)3 i)ASC O(S(A(iCE (N II(LES / I(ILO(4L(CI(S At II)

OESIC>ti SEC(

DISt III

~ 25

~ 40

~ 15 I ~ 25 I ~ 75 2,?5 1.21 2.AI 2.u2 3.62 2 ~ 75 4 ~ 42 3.25 3.75 5.23 6.03

,4>25 6 ~ 04 4 ~ 15 1.64 IUJC 0 ~

tif 0.

t IIL 0

L'.

LSE 0 ~

Sf n.

Sot 0 ~

0 ~

SSu n.

Su 0 ~

usu n.

>I 0

uNu n.

Itu 0 ~

i>>iu O.

ti 0 ~

I. IE-O5 1.2E-OS 0.')C-at 9.) t.-ah 1.2L-05 1.3(-AS

(-11.-05 S.9C-A6 S ~ 4t -0(i 5-7K -06 1-OE-06 7.3f-oh I-3L-O'S I ~ 5t 05 I. 4('-A5 0.1(.-nh 1.6F.-06

1. 1(.-06 I 2f-06 I..\\t-nh I.t f-ah

2. I)f.-06 I. ~)C-UI)

9. It.-07 U.nc-ul OS 4E-AI

9. I)E-01

1. IE-06 I ~ >it -uh 2 ~ lf-ah 2, IE-uh

). lf-nh 6.6f:-AI 1.0E-01 2.4E"07 7.tl:.-ol 4.3E-AI 2.nc-ol 5.3f-nl 3.of.-ol 2.0E-07 5.61 -0 I 3. It.-a 1.2. ) f-07 6.9('-nl.7.9F.-nl 2.( E-01 0.2(:-ul

>>. I(;-Ol 3.3(.-O1 ti ~ 3(.'-ul 3 ~.'if.-07 2 ~ 4C-01 3.t)t.-nl g,)C>>OI

).>>C 01 3.4c-nl I. 9c>>u 7

1. 3E -O'I 3 4l.-nl I.I)C->) I I 2f-07 OC-07 2.2C-O7 I ~ 4(-nl 4.4C-O7),2

~ 4C nl I.t,f 01 I.'if'-n7'.4f-nl 2.9(.-0 I I).9t:-nl 4.')I -01 3.1).-UI u..')t:-n'I 4;st.'1 2.')L-01 5.4('-OI ).bf-nl 2 'E-07 I ~ 76-07 I >9f:-01 I.> E-ol 1.5L-01 1.')E-07 2.3E-01 I.IIE-07

'I ~ IE-07 A.')E-0(I 9.21. -OU I ~ UL-07 I. I f.-01 2.0E-07

>>. 3L'-0 I 2.nt:-01 I, >>E 01 I 3E-A7 1 IE-07 1.4E-01 1.1k:-07 I.of-ol 0.4E-ou I ~ )E-07 9.1E-OO I. 4t:-07 I ~ IE-07 I.ut.-ol I ~ 3E-ol I

4E "01 I ~ OE-07 7 ~ If.-0 >I 6. 2E- 0 0 6.9f -OU 5.5E-AU 6.7t.

OU 5'C 00 U.AC-AU 6> IE-00 0.2t:-00 6.4E"00 I.ht."07 1>2E-07 I ~ lf"U1 I 3L'"01 1.6t;-ol I.?f.-ol I.IL-07 0.)C-OU 9.2E-no 0 ~ hf-00

6. (E-nt>

7.!>I -an 0>SC-AA I ~ 'I t -07 It. 2E-nu 5.af -ou 4.:)I -00 4 it>t'-00 5 ~ 0K-au 5.5t'-nu 9, lf-AO I ~ OC-O'I I.nf-ol 7.nf-ou 7 ~ 6t'-ou 1.4f-un S.t E-00 6..)L -Uu (I ~ ll -00 9.01 -o>I 6.0C-OU

4. It:-UI>

3 ~ t)g -uu

1. I)F. - 0 >)

4 'L-au 4 ~ 4f, -0>>

1 ~ >)I:-nu It SL OU tt. Iit:- 0 It 5, >)t.-ou tu>>tl>t'll Of VALI() OIISL'(IVAIIONS I I I ')5 NI>>I(iL)t Of It(VAL(O Oltst(IVA(l>>ti5

=

3I)'i tn>>IIIC)t Of CAL>iS t.u>IE(I I.fVFL

')5 Iiuilt)L(t Of CAI.IIS I)l>t>EI> LFVt'L 0

HO'I'I; I hny interpol )tloi)s between stuted mlle()I,'es will be done by 1I>I;-lot;

V>

nI.I I<l IIISTORIChL LONG TERM (D (fre Uenc corrected)

/R2 TtlulAIN / l<FCIIICULA1ION AOJUSlfll I>uufIIAII ANNxooo vENSIAN - II/lo/)6 FLOIIIQA Pouf fl AN!I L IGIIT co ~

ST l.UCIE UN11 l IIUTCIIINSON I SI.ANO ~

FLOIIIOA l)AIIES AND lloollt Jnll No. I 45')u -

112 AVEOAGE ANNUAl. AEI.ATIvf IIC! OS I 1 ION liATE ISOUAlIE NE1ETI -I I

I'LII1 00 OF. TlfCnllo 9/

I/I4 Tu u/31/70 UASE NISI AIICC IN I!ILES / KILO<<tTENS AfTII l)tSIGN Sf CT Dl Sl III NNE n.

NC 0 ~.

LNE 0>

E.

n.

ESC 0

Sf 0

SSt.

0 ~

s n.

SSu 0 ~

Su n.

usu o.

u 0 ~

uIIu n.

Nu 0 ~

NIIu 0 ~

II 0 ~

~ i5 75

~ 40 I ~ 21 I>.SE-OO 9.1C-A9 6.0E-nu u.9f-nv 3.2E-ou 4.uf-09 3 'L-On '>.4F.-09 3.7E-Ou S.uf-n'I 6 'L-nu.1>AE-ou 6.2E -ou 'I.!iC-u')

4.2C-OO 7.AF-09 3.4f-oo 5.< E-n) 4.5f-nu ).nf-o) 5.3V-AO 7.'IC-09 S.nf-nu 7.5f-o9 II. OE -0 0 I. 3!:-Au 0.2f-nu 1.2f-oil II-?f-ou 1.2f-ou S.lt-ou 2 3F-o9 IIII<<IIfII Of'ALIO OUSEI<VAT 1nNS NU<<IIEI< nf INvALID llus>t'IlvAIION Inl<<III:Il Ol CALLS l.ouEII LfvE'L NIAI>>tu Ol CALI<5 Ul>l'Ell I.I.VCL =

I 25 I ~ 75 2 ~ ol 2.02 3 'll "09 2 ~ ll.-A9 3 ~ 'St-0')

I >9E-09 I.')I:-09 I.nC-o9 I.uf-09 9.5E-.III 2.3l -nv I.ZE-A9 4.0c-n) 2.ll;-09 3.4f.-oo 2.of -o9 2 Al:-0')

I ~ At',-09 2.2f-o) I;IE-n9 2.4C-09 1.5E-09 3.nt'-nv I.IF -n9 3.0I-,-II) 1.6E-09

4. 9l;;0') 2. 6f-09 4.)l:-o) 2.5L'-no 4 ~ t C-O'I 2.4C" 09 2.9f-uv I i<f-09

>)

I 7 l 35 5

a

'3>>5 95 0

2 25 3.62 I

3L"0')

1,2C-09 6.6f-lo 6 'E-Io U>nf-Io 1.4t'-n9 1.2f -0')

9.5E-I 0 7.5E-IO 9 'E-10 I.nf.-oo 9.I!f-I 0 I. )C-09 I. bE-0')

I ~ SC-09

') ~ uf I 0 2

'IS 4 ~ < 2

). of-In O.IE-lo 4 ~ 6E'- ln 4 ~ ZC-10 5 ~ 4C-ln

9. )E-In u, 7l.- I 0 6 ~ 9E-I 0 5.0E-IO 6 'E-10 7.:lf-I 0 4.'lf-10 I ~ lf-09 I ~ IE-09 I IE-0')

2.1E-IO F 25 5>23 3'5 6.03 6 ut-I 0 5 ~ SE-I 0 5,4E-IO 4 ~ 3E-10 3.2t-ln 2 ~ 4E-ln 3.1E."IQ 2.<iE-IO 3 ~ 9F-10 3.0F.-IO 7,2L'-10 5 6F.-IO 6 4F."10 4 ~ 91.-10 4.9f-lo 3.of-lo 3 ~ IE-lo 2 9E-10 4.6f-lo 3 ~ 6E-lo 5.5E-IO 4.1E-10 5.0L-I 0 3.Elf.-l 0 O.)E-IO 6 6E-IO 7 ~ ')F-10 5 ~ uf-10 O.lf-lo 5.9f-lo 5.4E-IO 4 2E-lo 4 ~ 25 6'4 4 't-10 3.3E-10 I ~ 9E-I 0 2.AE-IO 2.2l.-ln 4 ~ 3t-I 0 3 ~ 9L-10 3.0E-IA

2. 3E-10 3>nl.-ln

3. 31.-10 3.2f" IO 5.1E-IO 4>7E-lo

'< ~ ul.- I 0 3.2E-IO 4.7'.i

7. I <.

3.!if-I 0 2, nf.- I 0

'I.Sf -10 1.6C-ln 1.7E-I n 3 5E-I 0

3. If-l0 2.<if-ln I.OL-I0 2.5L-IA 2 'C-IA 2 ~ AC-10

<<. ZL'- I 0

3. OF.- I 0 nf 10

2. )F.- I 0

I6 HOTI.'

hny interpolations between stated lnileaI',es will be done by loI;-I,ol,

/I!2

D,3L" if-8

?age 82 JO! HT 'NO PEOUENCY 3]S

~ !5LII]ON Oc TA oc

'>70 c SEoTE'SE>>

j o

]976 AUGUS

3) ~

1978 g ]NOS GAIA SO<>PCE:

Ot'-S]TE

'i lNO 5

'<Si>c>

"=LGnI:

10

~ 00 4cTERS I '8l vEN l< c.::.

L2/05/78 ~

07 ~ 42 ~ 18 ~

5

~ L>JC]E UN 1 HUT w )N50N

'. Sl AHG ~

c LOP '>OC Fl 0>> ]0>> PorEP>>NO

>~ 1 ovI CO ~

OA>>ES ANO io

c. Job No:

'98 -

1 ) 2 -

Z7 v]NO SECTOP NNE c'Nc'"SE 71 F43 52

~ 3)L 50

~ 36 eo

~ 42 115

~ 70 183 1> ll ZO5 1 ~ 25 292 1+77 334 2'2 352 2>]5 684 4 ~ j4 660 3 ~ 99 318 1 ~ 92 385 Zo33 505 F 06 510 3'9 7 44.

4'0 749 4o53 7)

~ 43 128

+77 15o

~ 96 76

~ 46 72 28

~ ]7

]29 579 656

>7S 3'0 3'7 93

.56 w]NO 5PE 0

C>>T GO% j S(NETEPS 0

0

] i5 1 ~ 5 3

0 3 ~ 0 5>>0 5 ~ 0 7 ~ 5 SECQNO) 7 ~ 5-10 ~ 0 3

~ 02 0

0000 0

0000 0

0>>00 1

~ Ol 0

0 F 00

.oI

> !Oio 0

0 00 0000 0 F 00 0

0 F 00 0

0 F 00 0

0 ~ 00 0

0 ~ OO TOTAL eo9 4 F 05 867 5'5

! 057 ei>>0 SPEEO 3'2 3 ~ '3 3 Sl

)010 3+25 6.!]

1616 3 04 9 ~ 78 620 2.88

~ 81 l45o 3o)0 F 82 esp

,Sv NN>>

72

~ 4>>

84 oS)

!29

+IS j55

~ 9>>

1'74

)>05 203 1.23 143

~ 87 P.5 oS]

91

>5" 310 1+88 372 2'5 440 2'o 320 l>94 257 F 62 304 1 +64

)8 3'<

379 2'9 1 ~ 17 407 2>46 4we 2+70 335 2'3

]85 1

~ 13 119

~

2 172 1.04 424 2 F 57 535 3 ~ Zc 531 3+2]

99

.60 lo5

~ 6>>

106

~ 64 29

~ !8 37

~ 22 17 o 10 co

~ 30 70

~ 42

)48 e90 8

F 05 33

~ 20

)4 F 08 5

~ 03 2

oO]'

0 F 00 0

0 F 00'

.Ol

~ 03

.0!

~ 02 0

0 00 0'

~ Oo 0

0 F 00 0

Oooo

~ '

0 F 00 0 F 00 0

0 F 00 897 5 F 43 3'6 1044 F 48 5'2 1025 5'0 695 3 ~ 10 F 59 LO7O 0 ~ <<4 3.22 959 3'9 Sade 599 2'43 3.63

~ J 695

.-2.34 4 '1 1]35

'2.85 6'7 CAL>

99 7

TOTAl.

, 1920 6214 7023

'l l ~ o2 37 ~ o 1 42.51 NU oEP 0

VAL]0 OSSEPVAT]n>~S

!6 22'U<i-P 0-L.'OVAL]0 0> SERVAT]ONS TOTAL NU>>8 OF 0

5

>Ii>47!ONS

]7520

'<EY ZXX NV~Sco OF OCCUPPENCES xzz

>ERIC-N'I OCCURP NC

)287 94 30 PCT 5'0 PCs 100 ~ 00 PC>

73

~ 44 5

F03 CAL" F57 16 i522 3.) 0

]00 F 00 1

Totals below are given in

~e nours for percent wind frequency by sectors.

ST LUC'5" PLANT

-ODC'A

Page 83 APPENDIX 2 Limited Analysis Dose Assessment for Liquid Radioactive

"='= 1uents The radioact've liquid effluents for the years 1978>

1979, and 1980 were evaluated to determine the dose contr "out=on or tne radionucl'de distr.'bution.

This analysis was performed to evaluate the use of a limited dose analysis fo determining environmental doses.

Lim ting the dose calculation to a few selected radionucl'des that contr'bute the majority of the dose provides a simplified method oz determ'ning compl'ance with the dose Limits of Technic 1 Specification 3.11.1.2.

Tables B-l and 8-2 present the results oz this eva'u? tion.

Table B-l presents the fraction oz the adult total body dose co..t".'buted by the major radionuclides.

Table S-2 presents the same data

=or the Adult GI-LLI dose.

The acult total bocy and adult GI-LLI were determined to be the limiting doses based on an evaluation oz all age groups (adult, teenager>

ch ld>

and 'nf nt) and all organs (oone>

live"., kidney>

1> ng>

and GI-LLI).

As "he d? ta. in the tables

show, the

?d o luclides "e-59

> Co-58, Co-60, Zn-65, Cs-13<>

and Cs -137 dom 'ate the ".otal body dose; the radionucl> des,

":e-59, Co-58, Co-60, Zn-65>

and

>Nb-95 dominate the GI-LLI dose.

In al'ut one case (1979 zish>

GI-LLI dose) these "adionuclides cont= bute 90'. or.ore of the total dose.

If for 1979 the fish and shell=

sh pathways are comoined as is done to determine the total dose>

the cont=ibut'on from these nucl'des is 847. of the total GI-LLI dose.

There ore, the dose commitment cue to radioactive mate".'al liquid e==luents can be reasonably est.'mated by limiting he dose calculation to the r dionucl'des,

""e-59, Co-58, Co'-60, Zn-65>>lb-95>

Cs-134>

and Cs-137>

which cumulatively contr'bute the ma j'ority oz he total dose calculated by using all radionuclides cetected.

This 1'mit d analysis dose assessment method 's a s'mp'ified ca'culat'on th - prov>des a reaso..

ble evaluation of doses cue to 'iquid rad oac- 've e fluents.

-ODCM

Tr'tium is not incluaed in the 1'mited analysis dose assessment

"or liauid re eases because the potent'a dose esu' ng =r"m

".."".="'e ctor releases is negligible and is essent'al'y independent'=

radwast syst m operat'on.

The amount oz -"t'um

'eases annually is about 300 c ries.

At St'. Luc'e, 300 Ci/yr releases to the Atlantic

-7 Ocean produces a calculated

~hole body dose of 5 x 10 mre=/yr via the fish and shellfish pathways.

This amounts to less than 0.0017 oz the design objective dose of 3 mzem/yr.

Furthermore, the release o"

t=itium is a zunction of operating time and power level and is essent'ally unrelated to radwaste s'stem operat'on.

-Oi C'iI

Paoe Taole B-l Adult Total Body Dose Cont" butions F.act.on oz otal B.ad 'onuc'de rish 1078 S'ne'1:'sh

"'sn 1979Shel'"'sh C ~ ~

1080 Shel 1='sz Co-58 Co-60 Fe-59 Zn-65 Cs-134 Cs-137 Total

0. 08

0. 05

0. 10

0. 01

0. 31

0. 42

0. 97

0. 27

0. 19

0. 25 0;10 0.07 0.10 0.98

0. 06

0. 03

0. 0.4

0. 02

0. 46

0. 38 0.99

0. 28

0. 15

0. 13

0. 19

0. 14

0. 11

1. 00 Q. 02

0. 20

0. 15 0.04

0. 27 Q. 30 0.98

0. 05

0. 44

0. 22

0. 20 0.04 0.00 0.99 Table B-2 Adult GT.-LLI Dose Contribution Fraction o

Total B.adionuclide r 'sh 1978S"ne'=ish r'sh 1979 Shell=

sh ish "1980 S'ne'=ish Co-58 Co-60 Fe-59 Zn-65 Nb-95 Total

0. 03

0. 02

0. 03

0. 01 0,89

0. 98 0.36

0. 23 Q ~ 31

0. 02

0. 01

0. 92

0. 25

0. 12

0. 16

0. 01 0.

2'.

75 Q. 44

0. 22 Q ~ 10

0. 05 0.01 0.90

0. 01

~ 0. 05 0.04

0. 01

0. 88

0. 97

0. 07

0. 57

0. 29

0. 04

0. 01 0.97

+age R5 A2PZNDlX C Technical 3ases for.==ective Dose ".ac=ors Overview The eva'uat'on oz.doses due to'eleases o= radioactive material to the atmospher can be simplif ed by the use oz eff c 've dose transfer factors instead of using dose factors which are rad'anuclide specif'c.

These effective factors>

which a e,based on "he typical rad'onuc'de dis ribution in.the releases>

can be applied to the total radioactiv.'ty released to approximate the dose in the environment, ie, instead og having to sum the isotopic distr bution multiplied by the isotope specific dose factor only a single mult'plicat'on (K f, M f or iM

) times the total qua..tity oz

'ff eff efz rad=oactive mate ial.eleased) would be ne dec.

Th's approach provides a reasonable estimate of the actual dose wh'le eliminating the need for a detailed calculat'onal technique.

be used to derive equa ions.

single e>> ective factors Determination of Effective Dose Factors The e =ective dose transfer zactors are data.

The radioact've e zluent dist=ibution based on pas-ooe a" ing, ~

for the past yea".s

-"can bv the fo 1 lowing K

where K f K

the ezfect've total body dose zactor due to gamma em ssions f=om all no'ole gases re'eased the total body dose factor due to gamma em.'ssions zrom each noble gas rad'onucl'de released the, fractional abundance oz noble gas radionucl'de i is of the "otal noble gas radionuclides

~age

('- + l. l M)

=

g (L.. '.1 H.)

1 (C-2) where (L + 1.1 M)

= the effective skin dose, factor d

e "o bet ef=

and gamma emiss'ons from all noble gases released (L

+ 1.1 M.)

= the s¹n dose

=actor due to beta and gamma L

emissions from each noole gas rzd'onuc lide i released Meff M~

. f.

where M f

= the effective air dose factor due to gamma emiss'ons ef from all noble gases released M.

= the air dose factor due to gamma emissions from each 1

noble gas radionuclide i released N c>>=

7 N

eff

+ i i

'(C-4) where N z+ = the ef=ective air dose actor cue to beta emissions eff from a'1 noble gases released H.

= the ai" dose actor due to beta em'ss ons. f=om eacn noble gas radionuclide i 1

To determine the appropriate e =ect've factors to be'sed and to evaluate the deg ee of variabil'ty, the atmospher'c "ad'oact've e =luents for the past 3 years have

'oeen evalua ed.

Tables C-1 and C-2 present the results of th's evaluat'on.

As can be'seen rom Tables C-1 and C-2, the ef ect've dose trans"e>> factors varies little from yea" to year.

he maximum obse ved variab il'y from the average va, lue is 18'. ~

This va zb m nor considering ot..er a" eas of uncer "ainty and conservat'sm inhe ent in the environmenta'ose calcu'at'on models.

-07)CM

Page o provide an additional degree of conserva" ism, a "actor o=

O.B.s introduced into the dose calculat.on

. process when the ef=ect've dose transfer factor is used.

Th's added conserv tism provides addit'onal assurance tha" the evaluat'on oz doses by the use of

a. single ef ective z ctor w.'ll not significantly underest

=ato any actual doses in the environment.

Reeval a"ion The doses due to the gaseous e

luents are evaluat d by the more detailed calculation methods (ie, use of nuclide spec.'f"c dose factors) on a yearly bases.

At this time a comoarison can be made between the simpl:fied method and the detailed method to assure the ove all reasonableness of this limited analysis approach. lf this comoarison indicates that the radionuclide distribution has changed s'gni.ficantly causing the simplified method to underestimate the doses by more than 207.i the value of the ef ect've factors will need to be reex mined to assure the overall acceptab'l=ty oz this approach.

However, this reexamination will only be needed 'f the doses as calculated by the de "iled analysis exceec 50"'. of the desig>-

bases doses

( ie, greater than 5 mrads gamm air dose or 10 mrads-.

beta air dose).

En any case, the appropriateness of the A

value periodically evaluated to assume the applicability o a

dose factor. =or evaluating environmental doses.

will be singl e-oc"'ve

>T LUCY~ Pl.~

-()7'C N

Table C-1

""ffective Dose Factors Noble Gases Total Body and Sk~ Doses veer

.Total Body Effect've Dose "-actor eff 3

mrem-m WCi-vr Sk'n "=f=ect.ve Dose "..actor

(~-:l. m) 3 mrem-m uCi-vr 1978 1979 1980 Avg 7.3 x 10 2 7.4 x 10 2 5.6 x 10 6.8 x 10 2 1.4 z 10 3 1.< x 10 3 1.2 x 10 3 1.3 x 10 3

Page

which yields a

app ox'mately 43>000 Ci.

By assuming a typical rad'onuciide 1 mit'ng total 'nventory oi d'st"'but'on an equivalen" Xe-133 invento~

can be determined.

Table D-l prov.'des the typical radionuclide (noble gases) dist 'but'cn and the Xe-133 equivalent concentrat'on.

The equivalent concentrarion is determined by multiplying the radionuclide concentrat on by ehe ratio of the nuclide total 'oody dose actor to the Xe-133 tata'ody dose factor.

Summing a'1 the ind.'vidual radionuclide equ-valent concentrations provides the overall reactor coolant Xe-'33 equivalent concentrat.on.

The data show that the equ valent conco. =ation s

a factor o 2 larger than the gross concentration (ie, 24 'Ci/gm total versus 47 Ci/gm equivalent.

The resulting Xe-133 eq" ivalent curie inventory of the reactor coolant system is aporox'mately 86,000 C'.

Page 9

There=ore, even iz the total primary systm at the zaz='mum ech n

Soec a'lowable concentrat"'on was degassed to a s'ngle aste gas decay

tank, the tank curie inventory would be we'l below the 285)000 Ci limit.

Based on this evaluation; the curie inventorv limit on a single waste gas storage tank cannot exceed the Technical Spec

'ication reau'rement.

Ta'ole D-l Reactor Coolant Xe-133:- ="ect 'e Conc..Crat=on Rad. on@el ide Reactor Coolant+

Concen~ ation

.(yC'/gm)

Reg Gu ce

1. 109

'j'Total Body Dr.

mrem/. -.

Rat. o

'TB DP

. Xe-133 Dp.

Ze-133

~zzect~ ve

'Concent>>et'on

('-'Cf./ pm Kr-85m, N."-87 Kr-88 Xe-13 lm Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Tot 1 "0. 19

0. 83 0.16

0. 31 8.8

0. 20 12.

0. 11

'.2

0. 02

0. 12 24.

1.2 x 1.6 i 5.9 x

~ 1.5 x 9.2 x 2.5 x 2.9 x 3.1 x 1.8 x 1.4 x 8.8 x 10 10 10 10 10 10

'L 0 1 Q 10 10 10 4

0;06 20.

52.

0. 32

0. 86 1.0 6.2 30.

0 78

. 0.05 3.2 16 2.8 0

17 12.

1 2

3.6 kData adapted Crom the NRC GA>~ Code

v)

APPL'Ht)IX I'.

RADIOLOGICht. EHVIIIOttHEHTAL SUR)EILLAttCE ST.

LUCIE PLAHT Key to Sample Locations Path~ay DIRECT RAOIATIOtt Location Description Horth of Ollnd Creek Sample Col lection Approx tmate Olr<<ct ton Samples Collected Frequency Distance (mlles)

Sector TLO quarterly I

H DIRECT BAO IATI OH HtN-5 South of Pete Stone Creek

'LD

'uarterly 5

DIRECT ttAOIATIOtt tttN-10 C.

G. Qtatlon DIRECT ltAI)IATIOtt tN-5 Indian River Or. 9 Rlo Vista Or.

DIRECT RAOIATIOtt HW-10 Intersection of Slt 60 an<t SR 607 OlltECT BAOIATIOH WttW-2 Cenietary Soutl> of 7107 Indian Itiver Or.

I) IRECT RADIATIOtt WttW-5 US-1 9 SR 712 OlttECT IIAOIATIDtt tttN-IO Stt 70, W<<st of Turnpike OlttECT RAOIA[IOtt

~

W-2 7609 Indian !liver Or.

I) tttt'CT ttht) IATIOH lt-5 Oleander and Sager Sts.

TLO TLO TLO TLO TLD TLO TLD qua rter ly quarter.ly quarterly quarter ly quarterly qua rt<<. rIy iluarCarly quarterly 10 10 HflW Hit WIN Wttu ltttW I) lttECT ttAI)IATIOH DtitCCT ttAOIATIOH 0 lttECT RAO Ihl'IOtt W-10 WSW-2 1-95 anil Stt 709 0503 Indian Illver Or.

WSW-5 Prlnia Vista Ulvd.

t~

Yacht Club TLD TLO qua riorIy quar t<<rly quarler ly IISW WSW

c' IH tu

~u I

I O

APPL?Ht)IX E (co>>ti>>>>ed)

RADIOLOGICAL EHVIROt0tEHTAL SURVE ILLAHCE ST.

LUCIE PLhttT Key to Sample Locations Pathway Location Description

Sample Collection hpproxtmate Ulrcct ion Samples Collected Frequency Distance (cities)

Sect.or DlttECT lthDIATIOtl WSW-10 Oel Rio and Davis Sts.

OlttECT RAD IATIOH SW-2 9207 Indian ttiver Or.

OlttECT lthOIATIOH Slt-5 US-1 and VilI age Green Dr.

TLD quarterly TLD quarterly TLD quarterly 5

SH DIRECT tthOIATtOH Slt-10 Point St. Luclc Blvd. and Cairo Rd.

TLO quart.erly 10 t) IR"CT tthOIATIOtt SSlt-2 10307 Indtaii River Or.

UlttL'CI tthDIATIOH SSW-5 Point St.

Luc le t)1vd. anil US-I OlttECT Rht) IATIOH SSW-10 Pine Va1 I ey and ltcstrnorcl and Rds.

OlttECT RADIATIOtt 5-5 13179 Indian ttivcr Or.

DlttECT ftAOIATIOH S-10 US-1 and Stt 714 DlttECT Rht) IATIOtt S/SSE-IO Indian River Ur.

and qua I 1 ttun Lane

'fLO fLD TLU'LD TLD quarterly quarterly qua rter 1y quarterly quarterly quarterly 10 1U 0 IREC'I RAO I ATIOH SSE-5 Entrance of ttcttles TLD Island ituarterly I) lttECT fthDIATIDtt SSE-10 El 1 lot ttuscum DlttECT tthl)lhflUH SE-1 South of Cool in9 Canal TLO T).D quarterly.

quar ter ly 10

C<

lu

//

'I AP1'EHI)IX E (continuect)

Q C7 itAO IOLOG ICAL EW I IIOINEI'TAL SUItVE ILLAIICE ST.

LUCIE PLNIT Key to Sample Locations Pathway Location Description Sa<npl e Collection Approximate Dir<<ction Sa<nples Collected Frcqucncy t)i stance

(<nl les)

Sector D IIIECT IIAOIATIOII II32 U. of Florida -

IFAS Enten<OIOgy Lab, Vere Oeach quarterly Altt00ftIIE IIOO FPL Substation

-Wcatherby Itd.

. -Ita<tiolodlne and Part I cul a tos weekly Wttw AIttOOIIIIE II12 FPL Substat,ion

-Itadiolodine and 'eekly

-Sit 76, Stuart Particulates t2 AIAOOIIIIE Ilt4 Ons Itc

-near south property line

-Itadioiodlne and weekly Particulates AI IIOOftIIE II30 Power Line

-Itadioiodinc and weekly

-7609 Indian Itivcr Or.

Particulates AI lt00IIIIE II34 Ons I te

-at Iteteoroiogtcat Tower

-itadloiodtne and wcckly Part,iculatcs 0.5 WATEItooltIIE ill5 Atlantic Ocean

-Surface water vicinity of public

.(oc<<an) b<<aches east.

side of

-Scdi<ncnt. fron

!toute AIA sliore I inc weekly L. IIL/L/LSt WATEIIIIOIIIIE II59 Itcar soul.h c..s of Ilutchinsun Island

-Surface water (ocitan)

-Scd i<ncnt trom s I<o< c I inc

<nunthly IU-20 Ocnotcs control sample

AI'I'I'NI)IXE (contgnrrc(J)

RADIOLOGICAL EIIVIROINENTAL SURVE ILLAHCE ST.

LUCIE PLAnT Key to Sample Locations Pathway Location Oescr Ipt I on Sample Collection Approximate lllr<<ctiun Samples Collected Frequency Oistancc (inllcs)

S<<ctur FOOO PROOUCTS ll15 Ocean side

-Crustacca srnni-annually

<I ERE/L/ESE Vicinity of St. Lucie

-Fish soni-annually FOOO PROOUCTS IISI Offsite near north

-I}roarl leaf monthly property line vegetation (when availai}le (mangrove) rr/IIrrr}

FOOO PROOUCTS FOUO PRODUCTS ll52 Offsite near south prolierty line ll59 tlcar south cnd of Ilutchinson Island

-IIroad leaf vegetation (rnangrovc)

-Crustacca

-fish

-Or oad leaf vegetation (mangrove) monthly (wlren ava ilanal c) semi-annually semi-annually monthly 10-20 10-20 Ocnotcs control sample

j<<)

k r/

/

I,),

r

/

~

~

3 n

C C/

5/

C3 ~

4 r

P acr

/ ~

r 5/

<<r,

~ I

/.

I t,,

I Yhh-2 Inset Oetail

,c I

a'4 I h.

h..

+~L H15 I

H30 cXCLUSION AREA 't0.97 /n))

AND l OW PPPUI.>TION ZONE (I m))

.i

~

s I/

I I

UNIT I

UNIT 2

/

)Sr -1 "o +'l y'.

4,'4

~

/P

~ /

~ /

It

~ g

'5 gJ I I

',1

/ "',

'Y<<> t

/ I li~I/

WS vi-2 0

J

~

NOTES L-l.iquid Radwaste Release Point Oue!o the Scale ol the F)gvre the Qzctus)on "reo Rod)us (OS57 miles) ond Ihe Low Populat)on Zone (Imite) Are Shown as Se)ni; Ihe Some Sire.

FPBI.

s PROPERT Y

I. INE 4 ~ )

(/)~+'"

rt>2

~ 5

\\

~

~ I

~,

0 5/5

~/

5J C

0 I/r2 SCA~c tN g II. g S P)OPr>Q'/r<P~)

I i r+TC<<.ALP 5T.

I UCIE PLAH T 5i i " AR E>> 5A>>P FIGURE

~.1.1

~4~

~M 'QNvvvE~

4 ~

f

~

• ~

~

' ~

c,

"- ~...

~

l

~, ~~~

~

ar C

~

~

i >"

"-v v'C t

~

I

~P

, v S.td 'v

~

v 5

V.hvigl+

v

.'vv.4~

'A v

<e" y

L X C)5 ~>> ~

~

gl v

~

~

4

~

~ A II V

v vv vI ~

~

.~2P

%IX F

.Z EOROLOGiCAL DISPERSION FOR'.ALAS*

"=or X/0:

X/Q 2.032 6

+

Li.D cV 8

EQ (1) 2.032 Z/Q EQ (2)

Where C =.5 V = 207.5 zt (63 2 meters),

/R2 X/Q was calculated using each of the above EQ's

~ for each hour.

The highest X/Q

/R2 rom EQ (1) or EQ (2) was selected.

The total inreg aced relative concentration at each sector and distance was then divided by the total number oz nours

n the data base.

For Denleted XI (X/Q)D

=

(X/Q) X(Depletion factor of figure 2 of R.G. 1.111-R1)

/R2 For Deposition D/0:

D/Q RDen/ (2 sin (11. 2S) y)

'Z (Freq

. distrbution}

/R2 where D/Q

=.

Ground deposit'on rate Calculation distance RDep Relative ground deposition rare from F'gure 6 of R.G. 1.111 Rl

+. Terrain cor ect"'on factors given by Table.'i-4 were also app'ed to Dispers'on Fondles S:.

LUC E P>~%' ODCN