ML18036A844

Revised Odcm.

ML18036A844
Person / Time
Site:	Browns Ferry
Issue date:	06/30/1992
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18036A840	List: ML18036A839 ML18036A842 ML18036A844
References
PROC-920630, NUDOCS 9209020227
Download: ML18036A844 (456)

Text

),.~q@g~ . ".,;~,-.; Pq-,)sq4'."..j~%4Qg~(y'. ~~,>,.tI~'~ ~ -c

&4'~t"Form ONP.STNAA4 Rav 1

'l~ g- ' A~gt A v Vt y g)P P f'gal'g

,.'. IO Cgk ~@gBShTIONS OF,." CHANGES ~.

~ AND EXPERINENTS~:"'";:

-.O'PRhCT ICE .

C w" ,."R EV.~ 000 1 g1fjvt <<fp~~ < I' ~

$ 8 >l S )( ggkg APPENDIX B t ~

SAFETY ASSESQKNT FORMAT

~ Page'~-"I r of ~d

=. Document No. (i.e., ECN No., procedure No.'nd revision,-

.-".'='special test No., r etc.): E7B ~Wctu < ~ red W C)

h. Description

l. Detailed description of the change, special activity, or condition including the systems, structures, and components affected.',= Includ the number of the activity proposed (e.g. ~ ECN/DCN No., procedure No. ) .. y~- +7r~Hd.))

( t

2. References.

gi". B. Impact on Safety "Is the cha ge acceptable from a nuclear safety standpoint'F',,'"..

g Yes ' , No g+l)e II t

Justification: Checklist (or IQR procedure change process/engineering criteria SSP-2.3).

If the answer is "No", it is an unsafe change which will require either revision to make it safe or cancellation. Environmental impacts are evaluated in accordance with SSP-13:3. "'='.

Potential Technical Specification (T/S) Impact Yes No Is a change to the T/S required for

, conducting or implementing the change,

~

test,'r experiment'7 Justification:

If the answer is "Yes", a T/S change is required prior to implementation or the activity needs to be revised or cancelled, proceed to Part E. If the answer to the question is "No"; proceed to Part D.

2973p TVA <0004 (ONP-124I) cy20P020227 9208282>9

t E

4 lg

'<6""0 SSP-12 13 Page""27.of 34

, j "~$"/~4"~@pidpA';!<4~~ RRV 1'p Ayth ( ~ ~~~' s~%%.sl+Wl'V.":~>e@btys +"'%~V."4>>>i+

~i~ '~a~>~&yj~l'f P>)g + ggQq 0 +i~+ ~>> ~tl~

"'~'q~~;"=,",'. >~/":~. '."-",'APPENDIX'Bq(Continued) ',-,

,, Do of /0 *4 1

~

0'ageos v --',' ' " '" -Fire'rotection (hppendix R) 20 Internal Flooding Protection (MELB)

' Pipe Breaks A~

""-~"~" Pipe" Mhip

"-'-' Modification to Non-Seismic hreas in

- "'>-'".>>'LhRA L-

'V ~ =.,: ', '", ,

"P-~>.. Jet Impingement Effects

~

-'s

~

4 P

8. <

.=,:~'~i ". Seismic/Dead Height P

~

P 9' -"'>'~r~;-'.'M ', ".t" 4.,""'-"': Internal/External Missiles '-

~

. 10. .- .';, <

~

,--"'~

~ 1

~Heavy Load Lifts or'.Safe Load Paths

"(NUREG-0612)

~s '5'i

';""-'oxic Gases ':

12. -,;, ='~>~'>'~ Hazardous Material< ~*;k4>>N' I 'yi

13. -. "'"~-~"=~.~ Human Factors h IE j ~L'4 '

Electrical Separation/Isolation

14. ,

15. .. Primary Containment,.

Integrity/Isolation l

16. ~Secondary Containment Integrity/

Isolation 4<+

Equipment Reliability Materials Compatibility

$ 01!

p, 4

2973p TVA 4000l (ONP-ll48)

,, ',a.

0 O' ~

Standad Sbeet! '.Focsn ONP.ST&4AA.S Rev I vy.'ir/.~,,A 4

V

.4 aa>> i~'a

g.-',,SITErg~j";-': yy, 10 CFR>59n59e EVALUATI@f CHANGES i%~

en/a /<<4@4 PRACTICE'"<~/~'4/)v*>>4'r

~,~ STANDARD+@.

.r'w~ ZESXSg &Q ','>>'Q; vt///d Nv~QQ?, <~s

'~'R EV-;.'".00'01 j;,g>

'j '4,=

4 ~ <<<<e>>h h A ~ . +p dvw'/+ r' g'<<h+t,/r t,

'4<<e<<.>>e<<%v~"""

,n;,-:,'< JLPPENDIX B, (Continued)

';.'-'.'a=. -~~:~'"~ - ",;-: ~ O8 (Document No *

""';;:P ', Page- 9'.'of;,/gj~

. DOES NOT POTENTIALLY '"Wi4>: '

DECREASE REDUCES, ~ f;M NUCLEAR NUCLEAR SAFETY SAFETY N/A Single Failure Criteria

<< lC'v I

'4 2O. Control Room Habitability 4 \at V

Environmental Qualification Category t<< a p-I, r,

'I Equipment Failure Modes

,>>P:>>.i A I

y Tornado or External Flood Protection'~~; 4 4>>

~\$$ t 4$~

$ 4<

24. ~Protective Coatings Inside Containment ~ >>'4 '5

25. Xt/ater Spray/Cnndeneatinn 'a /ail;-; 4.

V I 26.;; , System Design Parame ters Itth

."." Test and Retest Scoping Document."'.<'h~'

(Post Modification Test)

V4"v '28.'." Chemistry Changes or Chemical Release

'4

• 4 rt 4 29.- 'Equ'ipment Redundancy 4>>< ~

pe<<, >> 4 3o. Equipment Diversity hevh>>4>>>>h<<tt h <<hd>> tv 0>> 4>>h

31.

• Physical Separation r

lv 4 32- I Electrical Loads

,ti "<<V~

/

>>I' 33.'-" Response Time of Emergency Safeguards AV quipment 'I 4

~,a' 34 Safety Injection/Core Cooling '4 4~

apability

'5.

Decay Heat Removal Capability h'

36.'. r

'- Reactor'Coolant.Pressure Boundary 2973p

>>Il >>

'TVA iOXN (ONP-D4b) 4

'4 4 V 4

<<)

a>>

• I f e <<a+gfdt+4 IQP>> ~h

SIMBA.44 Rent 1" W 5 eP~~'(~<" ~; '

,sxzg KGTANDhRD i

~PRXCTICE? .

+h +'~+(l rQh i

'( '.gA

~ IZ 5 (Continued) j)P~~<<

r'hei

,.ir (,r~gj, '-I gjP>rrj~h'w

'MO(5'-' Page ~ of i~~ r-r -

j(;

'( rr i N/A

~ Reactor Core Parameters 38 '.'"' M Pipe Vibration

~Security System 40." Scaffolding

~ rr h ~

~Electrical Breaker Alignment Changes>,,"

~I-TABS, Protection Relay Settings' i

~

Compensatory,Measure lr Environmental Impact Statement; .

(See'STD-13.3.)"" -  ;.: ~

Design Basis Document h

Radwaste System Changes .

'r r V<<~ Valve "Alignment Changes '-;-". 'V':.'-"i='~'<'>~

'h

~Shield'. Building'Integri,ty (SQN/WBN). -,- .-

('. 'hrk r' yk 'h.;>>' ",h rr. g '<<'.hhh'rAfj'ghhr(A'ge 'rPNil

('"

New Radioa'ctive Effluent (Liquid i ~

~

r" ~

<<~ Release'athways -'--"- ""i~:-~or"'.'aseous)

P 50.

~ ~

Temporary Shielding

51. Instrument Setpoints 52 ASME Section XI r J 53 Unit Separation as defined in.

( SSP-12.50

'h h

52lo TVh 4000l (ONP-1245) r

~'

'r> 'i Saandard Sba@C Fcam ONP-ST&44.44 Rev l.:;:.: )~,. "4'@ - v"t'4s'v'W. s<Tr~~."~">>4klNQ'gt~4PQ'j~ '."h<<

'I I A

+i'~W 1;+ SITE4p+g, j) .r:@>>

h'..

~'j;10 'CFR~150o59$ EVhLUATIONS.OF CHANGESN/+ , '%4Pgrpq.

~h STANDARD.'~,',, ';,, ',

...i:.~YSB~ SS~lNSNgs."<<o.-':g'j>>.

h

"'RACTICE""* eh., tr(-'>>.

h h <<hh(, ~, ~ ',lh '<<r<<(<<( '~/V/avt/s'ttv<<<<h~ <<:>>>>gQ+<<<I M~ .1<<'(((yfg~+ 1-'~el

~~><~ . )~k

<<>>>>1 Document'o. ~4d',",~'.~C~++ I ~ ~ ',;-c'.;,gg'"++i ~v. Page y~~i Of>i~+++j~~  :.Cr <<, (. (~.,

D. 'otential S afety Analysis .Impact t h<<

Yes No

's a Sg obviously required (for example, ehaoge'o A 'lgte << l<<g(f a Radsaste System, special test, If yes, the remainder of Part or'xperiment)?

D ": ,

may be bypassed. (

Does the proposed activity affect significantly (directly or indirectly) any information presented in the SAR or deviate from the description given in the SAR:

Yes . ( No, ~ N/A By changing

~

l the system des ign or functional requirements?

<<( "'<<Yes("' ':"" No ~ h -": N/A By chaugiug"'the'text; tables,

graphs, or figures?.

Justif ication: 5+~, +y~d.~dd'p d ~

v

,', Does the proposed change involve new procedures or instructions or-;,,",:,1,,',.

-i,'"."<-'=.L revisions. thereof. that:.-,.

'es " No N/A Differ with or affect system",,;I characteristics from that-.

-...~.'..'peration s *<< described'n. the SAR? ~

N/A with or affect compliance

,'Yes No.

'iffer with Technical Specifications? I-

<<<<'s(eNN,<<r<<I/h

'es

<<nje(i( y<< qv ~, '<<

~'h <<

No' m ~ ha>><<>>>> fp N/A Conflict with or affect or procedure,,outlined, summarized, a process

• s or described in the SAR?

. I

(

Jus tification. gWW gy~gd'+d'=Z)

If the questions are answered "No", the activity may"be implemented without further evaluation. If the questions are answered "Yes", a 10 CFR 50.59 SE is required.

a/

2973p h 40004 tONP-1248) (,

<<s( h h

~ f I

@ply 1

(5( ~

PRhCTICEf~j"-'~G~ '

".<<CA . ->4~~ '"-(>',* B (Continued)

. - ~

"'age~31>.of",'34~,

R EV'~:000'ieQ

=-

',5,;..V)~;~g;~,(Sp-

',~ ~<-..<<.."4555 M4$QC"Pg;4(();

g<<g~%'45%5545&iF:A

~ 4, 5 4'

,-Z 5

<<$~

DocumentL'No'. e pV'cf 4

'E~(:,,"Review and Approvals

,'4

'+'4~> (5a54'.'~Z-PZ&r

'; Preparer.

,(Level

(

I) '..: Name ignatur 4~4.~-')

+g W~(e ~. Ni $

Date.. z'gl~ Pi

<<'>45( /

g@."~<-.~;,

~ Reviewer

+;-';-.";z'".;;;"', (Level I-IQR Name Signature '1

~~<yi~~~P>:."" or Level II) 4(Pg<,;O'", Approver . Date. IL-l1 II

,.gpA'mz'Line Mgr'. ) Name 4,;,.; Signature

<<5 hW'g "-.~'-" "(

~

5"4';.-'PPENDIX

>> Other Reviewers P~-'<<t'9~/ (as appropriate) Nam e/Organization

. (>"(4',

=,.: .- S ignature

.Date '

'+jP + >,Z5

~

kikF."<Special'equirements Yes (.'( a No

(

giga.'~Z>( 4'- 4* q( $$

'>'>>'4 8'

gPfP++tgr, ~$(>>Z... P(L.y >Z ~ ~

4

.;~".a~,;-If yes'ist all'pecie 1 requirements.;;;; ~

4 CZ>4  %

A 4>

~

,5

<<r;

>>A'(>q V'4( 45 " 'r, ~, >>4, 55A(V i&~5.<<wf"@(>> 5 Z

'* gj~f>4)<;>544<<>>>4>A() j>Z>>

4

'4

\>

A

'1

~

4

('

A<<

45

-2973p TVA

+Z-"j('5j, iXN (ONP-12')

'4

-,5 L@f4WPLQ $$44 I&(<<555'(Qgp"A <<<<+~'(5%N$ MbQ."y>>55 4>5> 44 <<, 5' > Q>>4>>4>Z(45>+'(4>>p(QZ)V+ ~ <<>>>,p ~ 4>p >

4

4 4 ~

re<+~~ ',QNN<<>>Q+4IN>> 4 't'5>>, ~ r.g 5',>> <<t>>~555~>> ~~(gp'j 4( << ~ @~+>>cc 0 Page)7) of 10

"'"~ ATTACHHENT 'TO'AFETY,'ASSESSMENT FOR;

- THE'- RADIOLOGICAL EFFLUENT@'TECBNICALN<<SPECIFICATION '(R"TS ).'w MANUAL CHANGE'--'TRACKING S>>' <<5>>

' Nr NUHBER OS 0 >>5<<",>>NN, 554,45I~5'<:4 *

l. The RETS Hanual contains three 'documents; the Radiological Effluent Manual (REM), the Offsite Dose Calculation Manual

)>>P "l'"ij'"' (ODCM> and the Process Control Program.

"~"

IP This revision to the RETS manual involv s one change to the ODCM and tvo changes to the PCP.

+5 g (1) The change to the ODCH is described in the Safety Assessment (SA) for RETS Hanual Change prepared by B.

5 I

.5 5' Eiford Lee on 2/7/91 (attached>.

(2) The changes to the PCP are:

a. The addition of the Pacific Nuclear System, Inc. Resin Drying DeMatering System as described in Safety Evaluation (SE) No. 77-9112-029 RO, prepared by B.N Mhetstine on 12/19/91 (attached).

k>>55f<< b. The addition of the Chem Nuclear Systems, Inc.

24-inch pressure vessel'ewatering system as"'.'-'-,'"

described in SE 77-9111-026 RO, prepared by L. K.

NC , Kuffel on 11/5/91'-(attached).<,:

5 The SA for the ODCM Change prepared by B. Eiford Lee on 2/7/91 Q~4~i 5; evaluates the ODCH changes of the RETS.

g7>c.'g "<<

SE No. 77-9111-026 RO, evaluates the initiation'nd revision 000 of F~P-025,. Devatering= Procedure for CNSI 24-inch Diameter Pressure Vessels.N SE No. 77-9112-029 RO, evaluates the PCP change Mhich'.

5+&, 'a includes the addition of the decratering of liners/high integrity containers (HIC's ) using the NuPac deuatering 5

system.

This SA encompasses these SA's and SE's prepared for:

the individual changes as mentioned above to fully address N

55/ this revision to the RETS Manual.

2. RM~Xmmm

1. Safety Evaluation No. 77-9112-029 RO,prepared by B.

'55 Whetstine on 12/19/91 and the references contained therein.

2. Safety Assessment for RETS Manual Change prepared by B.

Eiford Lee on 2/7/91 and the references contained'therein.

N<<55 4

3. Safety Evaluation No. 77-9111-026 RO, prepared by L. K.

0 Kuffel on 11/5/91 and the references contained therein.

>>>4 z<<

>> k

+@gal~<<>z<<)p<<>>>>>- 4 -.<<p, <<>>>>> <<<<"+ '%~"@A>.4~@A'.-<<:r>> %>4 Y.<<>k )

~ '> ~ ,<<<<'m

-';;,'.;c'.,'>, ATTACHMENT'TO SAFETY ASSESSMENT.FOR .~

THE RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATION (RETS)

MANUAL CHANGE - TRACKING NUHBER 08

>w, g

@ply

$~

B. J392kct ~ Q~t ) >>

B.B Seismic/Dead Weight a t >>

There are no seismic/dead weight concerns related to the change to the ODCM.

- The seismic/dead weight evaluation for the 2/>-inch pressure vessels is contained in Reference 3.

The SE in Reference 1 addresses the administrative changes to the PCP. The actual location and seismic evaluations vill be contained in the SE for the Operating Instruction of the NuPac system.

B.9 Internal/External Missiles',

<<>>'g<<> - There uith the are no missile concerns for the changes associated ODCM or the addition of the NuPac system.

","-. The eva)ua'tion of. the'4-inch" pressure vessels (as related g- to the creation of a missile> is contained in'Reference 3.

<<W B'.26>'System Design Parameters'= ~. '; "...,

- The change to the ODCM does'ot'nvolve system design '>>

. parameters'.

.z<<<<, >>>>p<<.>>). >>>><<F' zz

• >;-:; - The packaging of cret.iolid'radvaste in the'24-inch'-

h

. pressure vessels and the,NuPac containers comply arith the I a(Z-<<) . applicable regulations ofy'the NRC, in 10 CFR;'the," "'-'- >> <<

~ ><<:>>

>> Department of Transportation in 49 CFR and'the State of South Carolina containedin CNSI's Disposal, Site, Criteria.

Additionally, the Topical Reports for these devatering systems has been submitted to the NRC and are accepted for <<<<'>

reference. Therefore, since these criterion are the safety 4 '. Design Basis for the Solid Radvaste System, the system design parameter has'not been compromised. The addition of these systems trill'ot"reduce nuclear safety'.. '

VQ

>> ~

L

)>>

J>>

~

I>>>>

)

'P.,>>

">fw, /

>>'. >)

w' 'f>><<>> ~;, <<'. <<> '." S.>> . ~ . 'I~>>. ~ l., <<'~+'>. &<<+i;'p>>'m>>',

r, %. (

Page 9 of 10

. ATTACHHENT TO SAFEI7 ASRMSHENT FOR THE RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATION (RETS )

MANUAL CHANGE TRACKING NUHBER 08 B. ~~ ~ Qyf~z (continued )~; "

B.46 Radvaste System Changes

>> The change to the ODCH does not involve a change to the Radvaste System.

>> The addition of the dewatering of the 24-inch pressure vessels and the use of the NuPac dewatering system does not change the Design Basis of the Solid Radvaste System. The use of NRC approved packages vill be used without significant exposure to the personnel performing the dewatering. The packages vill contain shielding or vill be devatered within a shield. The containers are designed so that the filling and devatering connections can be quickly and easily disconnected. Therefore this change to PCP does not prevent the Radwaste System from performing its design function and nuclear safety is not compromised.

B.49 Nev Radioactive

~

Effluent (Liquid or Gaseous> release pathway.

CI T

- The change to the ODCM cannot create a nev radioactive effluent.

- The addition of the 24-inch pressure vessels and NuPac Dewatering system vill not create a new liquid or gaseous effluent. All liquids released from these systems vill be routed to 1) the'Radwaste Floor Drain system, 2> the Radwaste Equipment Drain system, or 3 > the Maste Package Drain tank. All of these three subsystems are processed and sampled as part of the existing Liquid Radwaste System. The discharge rate of the devatering systems is veil within the capacity of the Radvaste System.

During the devatering process, the discharge air is passed through a high efficiency particulate air (HEPA) filter prior to its release into the surrounding area. The dewatering is performed within a permanent plant building in which the air is monitored prior to its release.

Therefore, no nev gaseous effluent pathvay is created.

Based upon the evaluations of the items on the checklist, this activity is safe.

0 4

> e p

'age'."10" of'"10

.t

%(

~(r THE RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATION

- TRACKING NUHBER 08 .;-. (RETS)".i

-" mt.<".+~".@'.

.-)gt'."'ANUAL'HANGE amw~"hm I

,... 4u, ad@'.

'. B MLQ The evaluation of the .T/S impact as related to the ODCH i.-, "~s

~s r contained in Reference 2.

The changes to the PCP do not impact the Tech Specs. They have no impact on surveillance requirements, limiting conditions of operation or associated action statements. No Technical Specification change is required.

D. ~ILtt~lJ. gyes~ ~~~s ~~c The evaluation for the impact of the ODCH change is discussed in Q'

Reference 2.' I P

The BFN FSAR S" tion 9 '3 4 1 Met Solid Pastes describ s how'on"*:

.utP'r ". exchange resins are packaged and prepared for shipment in the r Radwaste building. This description refers to the ion exchange resin generated from the installed demineralizers. There is no reference to resin processing from portable demineralixers.'ecause of this difference," a SE was prepared for both the 24-inch pressure ,

'essel dewatering:(Reference 3 ) and the NuPac dewatering

'.' system".,"~iI-":'Reference').';"

KKLQRLH;-'.;;;; ~ ~ g.

Because, of its interface with the Radwaste Syitem and the changes to the,PCP may be construed as conflicting with the

. description of, the Radwaste system as described in the BFN FSAR, a Safety Evaluat'ion is,'required.

<<4(+~giQSA'. p: ~g The changes to the 'ODCH do not require a Safety Evaluation.,

SE No.'7-9111-026 RO'ritten for F~P-025 adequately addresses Unreviewed Safety Questions pertaining to changes-in the PCP for t

the 24-inch pressure vessel dewatering. SE No. 77-9112-029 RO was written specifically for the addition of the NuPac Dewatering,

~

System to the PCP. The specific installation'and operation of the Nupac System will be addressed by a site .specific version of Nupac's operating procedure. A SE. will be prepared for Revision 000 of that procedure.

X..." ..'. ~

Therefore, based upon the review of SE No's.'77-9111-026 RO, 77-9112-029 RO and the associated SA for the ODCH, this change to the RETS manual is safe and no unreviewed safety question exis'ts ~

I

<<~t ~

Lgp

'St aadittl'Sheet'titofOhii ON PSYCH,4,4 3 neVI' -

F RgV 00$-o+<-'-

St- .Pat;e

<<'~

31.>~<a.

SDSp-27

@c,SAFET+BFMl42G'/EVALUATIONOF

'age

't.

~~4)'CIIANG~ TES?S, AND EXPERIMENTS

~jg'"..j+I:. 9 '.. (10 CFR 5059);c~",. t31 of 39.'.

4/sc-Vrc~<<. 'CCS/S~+Ri%4~tt <<tf~>> t ~ /s<< ttt I<<CS <<P

'f S/// <<

/ ;/t.'f-&gp"'st"<<I,:-::cc':. ", SAFEIY ASSESSMENT FORMAT Page ~ of

';

Document. No. (that is, ECN No~cedure No. and revision, special;test No "etc): b A.. Description < 4e"C- No.).

"~

~4.r-pA F <<&;<<

r B. ~ -:; Impact on Safety <<

"-JI -.',~ /'.'>~""..'",Is.the change acccptablc froma.nuclear safety standpointT<"~",,'..".,', '.

+.4: .A';,.

4' I

I o'-'

• , '.;: 'Justification: Checklist B-1 (or IQR proccdurc change ..

~<<'t tA~=);."",process/engineering criteria)".+'Y~o.""",~: ":;""

...,;."',-.-'~",;-'~If the answer is "No", it. is an'u'nsafc change which willequir'c cithcr

~=-';<"."".~~/~revision'to make it safe or,cancccllation.'nvironmental impacts arc

'"4/' 'I "-i "<< evaluated in accordance with STD-52.1.

- =

~~~j'(~aOC<<4.<<'c. A

~

I'

'4-C, ':"'Potential Technical Specification (T/S) Impact

,.I ~

<<C t

. -'"'cs No .": Is c'hcoSc to the rT/S rcttcircd for

'onducting or implemtcnting the change, CC tc44 <<4 test, or cxpcriment7's "-,,~," -;,-

I I Ir

• I Justification:

I If thc answer is "Ycs", a TIS change is rcquircd prior to, Idr I , implcmcntation or thc,activity nccds to bc rcviscd or canccllcd, f '; '

'g -.~~/,"".. 'procccd to Part E. If.thc'answer to thc question is."No" procccd to Part D. I'

<<4<< t"

<<,4 4

' I 0

VA 40004 tONP.124bl

<<Ic<<<<F'r t,ot"4's h e ht<<tp" '*" ' <<

. F/) ~f, PkP+/4 +W

1

<I <<I Vy 0 <<>!.r lV>~<<~r',"' ON>+N 'yy ~

STANDARD~@'..'>'.".',','SRNSTPihSESSIVIEI<<ITIEVhLUhTION:

"."= CHANGES, TESIS,"f'AND <<'ir<<, v j

jEXPERIMENTS@,"jy'.,":~,':

. (IO CFR"'5059)I++q,~g~y..I~4'~s"~~ "Page;.32. of, 39;.';'I

"'<<,6<<y<<r++L"I<<+~<<~gt> N'R Ar " 4i SS>+~~,&~INN hi@QS IE<<I<<~rrvr<<r! >+ <<~MPp44 iE.00tv>Ny>%

g:eA-~4'~4 ';;,!Vrj@$~@+7P;;:"

'.  ; ": <-g vv "- hate><<<</>ivy<<Tv<<or>N~,"NI@r<<rr<<>s<<- +<<~

APPENDIx"'D, (Continued)f,'-'~~I@~,' +w.;5/~~ ': .,-",~ ':-'- I

~ <<*--'y.yy <AA.+L A~iAk <<<<'I yrg~gi+i,.rP~'i ySSS gb~P, P'N-. ~

SAFETY ASSESSMENTvFORMAT (Continued)

$';Q!. 0" CHECKLIST (D-l) 'P-'~ '

-'." .'h.'~~','-.~'",'ROCEDURE/MODIFICATION

'r P.."',

Document No. $ ~~ JQhN&f (QV. l ) ..',-

• +<>"<<II' v<<vs>Iv y (r<<) <SE ~ <<~imp

"';~. "-':I~ ~;-,:~,';,.',.'Page g of ~

vr DOES NOT POTENTIALLY DECREASE 8.- ,. NUCLEAR NUCLEAR r

1.

2 --""

SAFETY SAFETY

~ N/A Fire Protection (Appendix R)

Internal Floodjpg Protection (MELB) .

<<I ivy~ + ~

N R<<!<<! Q i<< 'P.<<<<N 'R "y LNER/0'.INPO SOER 85-00/5 I

4. Pi Whi Iyrggr<<y 5.'I '- - -. '-'gModification to Non-Seismic Areas in ~

CB/AB y! <<N

, 6:".:: ~ ALARA IR'@~@ 'Iv7v<< ' ,; ~.Jct I Impingement Effects;.y,...

~",'Seismic/Dead Weight@.",,".',:."; .-=

.I"'>I>

. > ~". .y Internal/Extcr'nal'Missiles;; =.'"

"<< "<<I<<y VV '~~'Heavy'Load Lifts'or,":Safe Load Paths V <<V

'=>~> (NUREG4612).-'s'-<~I'f~'>"-'!~~-".""-'--.- - '- . r V."

<<*> ~

11.':".' '*." ' Toxtc Gases \

I "<<V<<<<Iv<<I 0

,;12.:,-,I'~ -"azardous Material '.-.,'--', ';- '<<<<

'~'uman Factors>-,'-',",',.'I~>-"<.'-,.-'. '-,'

., 14..='.'- '""'lectrical Scparatio'n/Isolation .,

<<h<<0)I<<SI>~ r-<<15 ~~y'tQ~ -':".'"'" ~~~Primary" Contairiment Integrity/Isolation " "":" <<r>I! ~a@Syr'

<<~

'6 >. >-' '~ Scco'ndary Containment r

Integrity/Isolation "-:! V,  !

~'7.

.,~ Equipmcnt Reliability, << l<<

, ~ v I <<

."Materials Compatibility

>5><<5I

18. ~"

19.

~

'ingle Failure Criteria' ~

Control Room Habitability

='-

Sf. g

~

~

20. <<

~ ~

Environmental Qualification Category V >

21.

22

~ Equipmcnt Failure Modes I<<"

y

~'

,g I<<

0 0> r L

TVA 40001 (ONP-lR 86) '<<

4l 2'4'a~

r 'ii<<4&</.y~j$$+p<<<< '"- . REV-,.OOX8 Patr,e'33 .'."; <<

ndad Sbeit~+Foim ONP4TDAAAO Rcv t;,"-g: :.<< ~ . '-; ~ .~,~p~~<<.,'egg<<~<p~>~+V SDSP..27+1@

'$ "V i c,g - SAFEVlP2KSESSMEHT/EVALUATION OF-".,: ,STD413 ~ "':~"wp. "g" $+p,,

,CHANGES, TESTS, AND*'EXPERIMEK1S .'"~

4'"% ~~V)STANDARD -'.'- ..'i'(10 CFR 5089) ", 33 of 39 P~-'-'-'" ~+i,wj 'Page 'kly

~~'-<<<<<<<<'<<'-"i';- i '., APPENDIX D (Continued),', '-'~"j",~,'-'-'~

r " ".',...

SAFETY ASSESSMENT FORMAT (Continued) ~

PROCED URE/MODIFICATION CHECKLIST (8-1) (Continued)

~ .i<<q pi Document No.~&Vs ~~<<l (Rwi sio n '~l Pa<e 3 of ~<<

C DOES NOT POTENTIALLY

..',;;", DECREASE REDUCES

':,;,:;". '4 'I NUCLEAR

~ '

NUCLEAR S

~4, SAFETY SAFETY N/A ~

g r

,23.- Tornado or External Flood Protection r

, 24.~

25::"' ~

~

Protcctivc Coatings Inside Containment

%atcr Spra'y/Condensation

~

\

26. System Design Parameters l

'p ~ s~/ ".4 ~ ..-,..- Test and Rctcst'Scoping Document (Post 'V Modification Test)'.;,,

lf (- ~

, 28." Chemistry Changes or Chemical Release ~,

~ Pathways,'="j;" ~:"...,'i ,-g"tl>

Equipmcnt Redundancy,,'.',

'>ij ~; <<prr 'i~a

+ y~

~

0

+r -;,'30.'j~".'"' Equipmcnt'DivcrsityII' Physical Separation=-.",,',-,',, . '...:i. <<

..'.5eP

<<w(

Il <<

Qj p 32-::

"33 Electrical Loads-','--'-.. -=-'~:,-',.

Response Time of,Emergency Safeguards

f,-...

• 34;.,- '~ 'afety Injection/Core Cooling Capability '( ,; ".;.Xy'..'

".:35 ':-'-" '- Decay Heat Removal Capability

';38.'

37-;-.

'~~ y . IK Reactor,Coolant Pressure Boundary ReactorCore Paramctcrs, Vibration'-'",>>'

"Jp (~A 0

'.M' y~t "= 39.=;-  !- ":~ Pipe Sccurrty Systcrn~--: "-

'40: . Scaffolding":~",'-"-'.

41. 'Ei Electrical Brcakcr Alignment Changes 7' 42:; I-I ABS,'Protection'elay Settings ~

43..<<

44. ~ Compensatory Mcasurc ~

,:; (scc STD-5.2.1)"-',.'~; ";;;:;:;.

,4 Environmental Impact Statcmcnt

='4 <<

~fpl4'~'"'45.

~" Design Basis Document J

i"

> ~, widow

~ -in ~

"C

<<a h

~~

~ ~

~""

j-$ 4+..'vh 4000i tONP l24S)

'4;>" <<1'

cccr

~ '@jL "'- 'jy<- -~g:3LWl', 4i"" '" ' '. rV"-<>,;,---'-:,REV"-GOES P

", Wpp, 34 Staydtzd'SR~op,- Fogyyi ONP STOMA~.4 2.. .4g,+lpx@8 ~ <'4t'SDSP-27.l.

s '-

'"; e sl I

" SNETFp'RSRSSMENT/EVALUATION OF. $3j'llMi.lD

~

CEIANGEQ)TESTSp'aAND, EXPERIMEN1S/". -Reve 3

,8:. STANDARD - I,"', ,Page 34 of 39 af <p, gage ', 'tXcarC.'Israel,V = A s g "y'/beet~ Mktigtiytt~"'g~s gsn/ -;,gs~Aa//seas, u~shaaw~

,:;4, '".;",'":".APPENDIX,D (Conttnucd):@, r:~g+.q:;"

"= SAFETYfhASSZSSMENT FORMAT (Continued) 'rg-:

u;.- d$ g",;~,,-,< ..-. PROCEDURE/MODIFICATION CHECKLIFf (13-1) (Continued) sb 'ac 4

c~

Page of ~

c. ~

",.:"; -'. DOES NOT POTENTIALLY >" -,

L

-: DECREASE REDUCES NUCLEAR SAFETY '""'.

UCLEAR

SAFETY

...~

N/A c

46.;. Radwaste System Changes 47'-,,'... af( Valve Alignment Changes

~

48. "'"

~ Shield Building Integrity (S QN/WBN)

~

l e

'9."' "" -,h ='

Ncw Radioactive Effluent (Liquid or Gaseous) Release Pathways 50.

51..

52."

c

~

.="

~

D;-",;"-'-:<Potential Safety Analysis

"'"-+ "-'-'::

Iinpact:,:<-

-'~"

Temporary Shielding Instrument Sctpoints ASME Section'XI-:

'No'~::.

~'s

.",,":.; Yes>> '" Is'a SB obviously reijiiircd (for example, change to ...,: v rg,cc

. ': c:, 'r -a Radwastc System,"special test, or, experiment)2 I, gctyct  ;";- If 'ycs,"the rernaindcr of Pa'rt D may be bypassed.,-' a . ehdl, 'pY v-, ~ * "

Docs the proposed activity affect (directly or indirectly) any information, presented in the SAR or dcviatc from thc description given in the SAR:

-';ir/-"'>>"

Yes ' No" 4 ":,.: N/A" By changingn'tlic system design or '.; '.;

Yes" "'" No'~"'N/A'"" .

functional rcguircments2 By'c'changing tlie text, tnbles, graphs, -'

or figurcs2

" e srs S /v w

~ tr r

Justification:

c v .

Does thc proposed change involve ncw procedures or instructions or revisions cw Xc "thereof that:

Yes No N/A sf Differ with or affect system operation characteristics from that described in 'l thc SAR? x . '* E N/A sd Diffc-. witli or af/cct compiiancc with,

~

Ycs No Specifications?

-,'.,'cchnical 2

~ 'es No N/A Conflict with or affect a process'or;,: ac, 'c, s proccdurc outlined, summarized, ct s in thc SAR? or,'cscribcd v F

TVA 40004 tONr.12 S8) v v

'c

~

Gt'-X 8

.' RE<

~ ~

Pat;e'35, >>-

Vh1- 't Standard Sheet Form ONP STOMA.0.3 ttav t rKV'4 v 1 .ul II ., Ju -'+ 3Qgp

~ " u h t "h ~

l h hV SAF~~~lN:SGRVALUATIONOl: Sf D4 ID t"Ip:~i J~~~ tl;rt'hv! I NP ClIANGES, TESTS, AND EXPERIMENTS (10 CFR 5089),'

• -.. hPPENDIX

• ut D (Continued) v+,),, + Irtu(+ hh u '

~

~ ~

SAFETY ASSESSMENT FORMAT (Continued)

Document No. QQ5Q3anual M9 ,.Page Q of Q Ih Justification:

u If thc questions are answered "No," the activity may be implemented without further evaluation. If thc questions are answered "Yes," a 10 CFR 50.59 safety evaluation is required.

E Review and Approvals Preparer I Date:

arne ature rhutuJuIu: .:IJV Signature .VI'A VC~~~~~X~<

r'h Reviewer (Level I-IQR

'lt or Level II)" Name J4 gh h'I J Approver (Line Mgr), Zckhuh Cl IU +IfVEtk/L Date: V.

Name Signature u t r

'I Other Rcvicwcrs, .,

I (As appropriate).h;" ' Name/Organization . Signature h

F, Special Requirements ~ i- h "r'h ~" h Ih J~

't

'%gV

~0

'I u.'t

~u TVA 40CO< (QNP-12-Sb)

'h

h. hhh" u

'+,'"~,'-'q~ '>0 P Attachment Ao-TPA. Form-40139 (Page 6 of 11)

Safety"&Pcs'iment foE ODCM Revision (Revision 9 to RATS Manual)

~ ~

q;g, ~, **

A. Description This revision to the ODCM will implement two sets of changes. The first set'of changes are corrections of typographical errors, grammatical errors, wording clarifications, and a complete renumbering of 'sections, tables and figures. These changes, since they o~. not intent changes, will require no evaluation for their effect. on nuclear safety, the SAR, or the Technical Specifications (T/S).

The second set of changes adds text to the ODCM which duplicates text currently found in the Technical Specifications and/or the Radiological Effluent Manual (REM). This change is in anticipation of a T/S change which will implement the NRC's Generic Letter 89-01. The Generic Letter recommended the relocation of all procedural details in the T/S dealing with radioactive gaseous and liquid effluents to the ODCM. The affected Sections of the T/S and REM are listed below:

Specifications 3.2.D, 3.2.K, most of Section 3.8/4.8 (with the exception of the explosive gases requirements which will remain in the T/S and the solid waste requirements which should be moved to the Process Control Program as recommended by the Generic Letter),

and all of the REM text is relocated to the ODCM. A detailed

'cross>>'reference for the current T/S, REM, and proposed ODCM Sections is given in the attachment. II I lW t

In addition to the recommended changes, applicable terms which are defined in the T/S will be duplicated in the ODCM so that it will be a self-contained document upon the implementation of a T/S change.

The duplicated definitions are also given in the attachment.

The text which is being duplicated is done so verbatim, with the exception of references between documents and correction of typographical errors. The current text in the TS and the REM cross references the ODCM, the REM and other TS sections. The new ODCM wording will only reference other sections of the ODCM and, in some cases, portions of the TS which will still be applicable.

The only systems potentially affected by a change to the ODCM will be the liquid and gaseous effluent and process monitoring systems described in the BFN FSAR. Since this revision does not change any calculational methodology, requirements, or processes, it will not have any effect on these systems.

0140v

lb IP (k

<<1.

Attachppqk 4~A +~"-40139 (Pago<7r.of"<Xl)@><~j:,"'@,-,=.', '.'..

Safety assessment for ODCM, Reyisi~on '~~,P;.

E

• 0 x ~ \

I A,. Description Re ferences

~ J I

1. BFN Technical Specifications, Definitions'Sectional.0 ~.-~.-"..

~

2. BFN Technical Specif:cation 3.2.D, "Radioactive Liquid Effluent Monitoring Instrumentation," September ll, 1987.

BFN Technical Specification 3.2.K, "Radioactive Gaseous Effluent 3~

Monitoring Instrumentation," September ll, 1987.

3~ BFN Technical Specification Table 3.2.D, "Radioactive Liquid Effluent Monitoring Instrumentation," February 11, 1987.

BFN Technical Specification Table 3.2.K, "Radioactive Gaseous Effluent Monitoring Instrumentation," February ll, 1987.

4'~'.'e

-BFN Technical Specification Table 4.2.D;i."Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements,"

February 11, 1987.

':;6.. BFN. Technical Specification Table 4.2.K,,"Radioactive Gaseous

-".":i ".'4""~,4'"'-.~A~~: Effluent Monitoring Instrumentation Surveillance," May 4, 1988 (Notes, for Table 4.2.K dated February 5, 1987);

~ ~

';l; "..W>'-':7. BFN Technical Specification Bases for 3/4;2;D and 3/4.2.K, April 13 1989 '

8. BFN Technical Specifications Section 3.8.A/4.8.A, "Radioactive Materials, Liquid Effluents," Page 1 dated February 5, 1987, page 2 dated September ll, 1987. P

9. BFN Technical Specifications Section 3.8.B/4.8.B,;, "Radioactive ll, WA Materials, Airborne Effluents " September 1987.

~ '

10. BFN Technical Specifications Section 3.8.C/4.8.C, "Radioactive Effluents - Dose," September 11, 1987.

10. BFN Technical Specifications Bases for Section 3.8, February 5, 1987.

ll. BFN Technical Specifications, Administrative Controls Section 6.0.

12. BFN Radiological Effluent Manual, Revision 8, June 22, 1990.

0140v

<<f') ) ~

j, pv.'

"...; z ) >>

! g,."rAg~g~C

.. g!>~~a,'.;.,> .~ ~

Attachment<crPR Fo440149 (Page 8 of 11)Yg,,-,.gg;,~.' ) c">-F Safety Assessment" for ODCM Revision""""."-~

- ~~+*:>>";.,:" .., .~ " . (Revision 9 to'ETS Manual)

)4 <<>>>>rW@

4 p" j>~A.;; A,. Description Wg;-.~44~~<f<<References (coatinued)

. 13. BFN FSAR Section 1.6.1.6, "Radioactive Waste Systems."

14. BFN FSAR Section 7.12, "Process Radiation Monitoring.".

~> ) > >r)) ~ "*

)>

15 'FN FSAR Chapter 9.0, "Radioactive Waste Control Systems."

',)r>)a"a" > ~

), r

16. BFN FSAR Section 10.17, "Process Sampling Systems."

<< r 10 ~ NRC Generic Letter 89-01, "Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the'elocation'f procedural details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program,"

(A02 890209 005). +') >. ~

~ ~~"i<0~.)~~r~~:~..

B. Impact on Safety yP%

>i\ )

The ODCM contains the methodology used to calculate setpoints for gaseous-and liquid effluent monitors.;; Since the revision, only adds p '>><< ~

text to" the ODCM which already appears'in the T/S, affect',.the methodology described:in the ODCMs hence no setpoints it vill'in'no vay vill be'changed due to this revision.4~'-"-'8-;".'".-'>>" '".; ;"'"r+'<:,>","',":>' <

Since there is no"effect on setpoints for effluent monitors,- and no other'afety concerns are impacted by this revision, concluded that the change is acceptable from a nuclear safety it may be r standpoint.

))

C Potentia1 Technical Specification (T/S) Impact

+!')"+'.! ~ r '<< '-<<~<% < r<<~+ 'V a:. > 'W)r)" .~n'Q)4'A>>>> '!!'))I4j%c'>- 'gEAA+) "<<>>x<< ~ =

Thii revision to the ODCM is ia preparation of a proposed T/S revision ufo<,,,),< ~ . vhich:vill,implementthe.NRC-',s Generic. Letter, 89-01.., The Generic ~ ~,

Letter recommended the relocation of all Specifications dealing with radioactive gaseous and liquid effluents to the ODCM. "This*includes ~

> ~

Specifications 3.2.D/4.2.D, 3.2.K/4.2.K, 3 ~ 8.A.1-4/4.8.A.1-5,

<< 3.8;A."1-8/4.8.B.1-4, 3.8.C/4'8;C,"'";,and all of the REM; Requirements remaining in Section 3.8/4.8 will 'deal vith the explosive gas.

requirements and activity limits for liquid tanks. The solid waste requirements in the T/S should be moved to the Process Control Program as recommended in the Generic~Letter. "In order to make the ODCM a self-contained document, definitions which are referenced in the relocated T/S requirements were also duplicated in the ODCM. The duplicated definitions are T/S Sections 1.0.E, 1.0.N, 1.0.V.11, 1 0 V 12>> 1 0 V 13>> 1 0 'C>> 1 0.FF, 1 ~ 0 ~ GG, 1 0.HH, 1 0 ~ II, 1.0

~ ~ ~ 'J, and jg ) )

i, 0140v

<< r r

! )>)

• ~ ~ '>

J"

- gAg$ . ~ <<~'rqgrA'>

gr'!h>+hhh>4i>'hp$ py~j!MQj~4>+a)>~gg~i'>

AttachmbPL~<TVJL. Pbr'hf 4M39 (page j '>>! -

9 of ll)

,pr ':.".<,Safety>kiseisment for ODCM Revision

.~4. r,',g """,=,<<,i,+5'-., (Re<<vision,'9 to RETs Manual) << .

.>!> r.

C. potential Technical Specification (T/S) Impact (continued) t>(>Q+'P~/+ 'gw~g4w ~> 'h, r

(~ '* The text" from the'T/S;and the REM has been duplicated in the ODCM

"> verbatim,~ withhthre>exception,o>f cross references, typographical errors and grammar corrections".y'.The ODCM will undergo extensive "eviews in

<= the approval process to'ensure that this has been accomplished.

'eferences between"Tables;.'Figures, Specifications and other documents were changed in order to ensure that the ODCM will be a self-contained document after the T/S revision. Until the T/S change recommended by the Generic Letter is prepared and processed, there will be no changes in any procedures or activities which implement the T/S. Since the ODCM revision simply duplicates T/S requirements and wording, it will not require a change to the T/S.

The definitions, located in Section 1-0 of the T/S, were not specifically addressed in the Generic Letter; however, there are terms defined in this section which are being relocated to the ODCM, The

>- rgb duplication of the definitions in the ODCM will ensure that the ODCM will be a self-contained document. The definitions are duplicated in the ODCM verbatim, therefore the revision will not require a change to the T/S.

ha'i~<>!>'. ~ >

$y v! Ph Since the additions to the ODCM duplicate the T/S ~ording, no processes or activities governed'.by<the current Technical Specifications will be."

affected by this change. This change will, therefore, have no impact h on the'Technical Specifications.

D. potential Safety Analysis Impact h

This ODCM revision places text in the ODCM which duplicates text found in T/S. It does not change any design characteristics, functional requirements, or methodology for dose calculations and setpoint calculations that are described in the FSAR. Any references in the FSAR to the T/S themselves will continue to be valid, as will references to the ODCM as the location for methodology for dose and setpoint calculations. Therefore, this revision will have no effect on the FSAR text.

This revision does not change any equipment, requirements, methodology, or descriptions of any of these, nor does it change the way in which All descriptions in the SAR will any requirements are implemented.

continue to be valid after this revision.

This ODCM revision will not require any new procedures or instructions or revisions to existing procedures or instructions.

~ ~

0140v

>h h

r'h!r!!~>

r'h>>,%.

~ >.> p >g > '}l !, " 4r'~>>5}i~>> 5QPPJ $ (+~1 Wh 1> > l

, @~4 e Yv

'\% C+E>W ., '* I

~

~

~

i)jQo~Mpp'~+$".~g>>,"cd "+j$'~. <<M$ Pe:iAFj>>"h'",fiji".>/Q4&E+k4~

~

",, ~"', " i%~ ":', 4,; ' '(a'~ g '. '~, " ',", ',g, 'pg

y

,'Apiary ', t%4$ ,32~, ~

', -. 'l, ," ".~ ~ ~

~C +'a gtQgl 'g$ , (,q~

'~' ~g y ey, j'a'Pt g '

y',e~ ~

' g a'~ ~l',~A ~ A  %~E~i~~l

~.. ~;>why," ..w.d C. ~

0 I

abpL~2p .<r'"4;4 p'+>>>2>@ap&v 4'2> '2., "a,' >h>*i r 2>attaataea>I(Pagegll>>>af>21)@j",g@~" '>2" >;,'>:, .""4>~~"if Cross R efermco&~ee++~eal Specifications/REM~,, 4.. ,~gr.,gp ~ ~<,

~4

>4-2el."1%1 >>2> Q>>>:,""',>>a'--",'".."."> >>ea.')~ .

4 ~ Se'A 4 1 4~4~8PaFS~ 2 2

2 e>e 3~2~2~2

~ 3 8 "Be6~">g>e'ak'7 3 2 2

~ '3:>2 0,",>>ai2> "'

',3 2't2', .gc 4,Q,~- 'fBf7>,'~'g.

'Bases for- 'a1lC appli'cahle; spechifications aree-relocated to:the BASES sectio@~>i g9i+4~PAa

.pi~, m g ~g .. -" ."'Wg' ., ~

@,4@>

ap(<j'q4>> fggf~t g(~ j'e,+. wp >ga 4'qt4>>'+>e;gQkg 3~+)+ ~QQPl ><<ji&+ ">4~ <<>,>+>>>2 f(4) >.$54~4>'..>~@4'++) kP(4$ +)+i(,$

~+~+>ggy'I

~ e>

te >,>' ' >'

~

>> " W> '>> 2, 'ee>

P 2

. f~-"+"- '.""" '"'":-: ""Ã"-' """ ~'~'~~' "~W"'" ":i"'""~""-'4' "" <<""'""."-.'.

TENNESSEE VALLEY AUTHORITY BROGANS .FERRY NUCLEAR PLANT RETS NARAL RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATION (RETS)

REVISION 9 gpss~>:,+R 'f P'Q PREPARED BY: D. NIX PHONE: 2682 RESPONSIBLE ORGANIZATION: CHEMICAL TECHNICAL SUPPORT APPROVED BY: J. SCALICE DATE: 01/02/92 EFFECTIVE DATE: 01/04/92 VALIDATIONDATE: NOT REQUIRED QUALITY-RELATED

RETS Manual Revision 9 Page 1 Brogans Ferry Nuclear Plant Radiological Effluent Technical Specification (RETS)

Manual 828o

RETS Manual Revision 9 Page 2 INDEX Section I. Introduction II. Radiological Ef fluent Manual (REM)

III. Offsite Dose Calculation Manual (ODCM)

IV. Process Control Program (PCP) 828o

RETS Manual Revision 9 Page 3 RETS Manual Section I Introduction 828o

RETS Manual Revision 9 Page 4 RETS Manual Section I INTRODUCTION The Radiological Effluent Technical Specification (RETS) Manual contains three documents; the Radiological Effluent Manual (REM), the Offsite Dose Calculation Manual (ODCM), and the Process Control Program (PCP). All three documents are referenced by the Radiological Effluent Technical Specifications which vere issued on February 5, 1987 as Technical Specification Amendments Nos. 132, 128, and 103 to unit 1, 2, and 3, respectively.

The REM and the ODCM vere approved by the NRC when they issued the RETS.

The REM is controlled by the NRC, so changes to the REM must be approved by the NRC before they are put in this manual. The ODCM and PCP are controlled b TVA 60 so cchanges to the ODCM and the PCP must be approved by PORC. Initial NRC approval of the PCP is required and has been requested.

828o

RETS Nanual Revision 9 Page 5 RETS NANUAL Section II RADIOLOGICAL EFFLUENT MANUAL (REM)

For the Browns Ferry Nuclear Plant Limestone County, Alabama Tennessee Valley Authority 828o

0

Revision 9 Page 6 RADIOLOGICAL EFFLUENT MANUAL TABLE OF CONTENTS SECTION PAGE NO. REV. NO.

A. INTRODUCTION A-1 B. RESPONSIBILITIES B-1 C. 1. LIQUID EFFLUENTS SAMPLING C-1 AND ANALYSIS PROGRAM

2. LIQUID WASTE TREATMENT C-5 D. 1. GASEOUS EFFLUENTS SAMPLING D-1 AND ANALYSIS PROGRAM

2. GASEOUS WASTE TREATMENT E. RADIOLOGICAL ENVIRONMENTAL MONITORING

1. SAMPLING AND ANALYSIS E-1

2. LAND USE CENSUS E-3

3. INTHKABORATORY E-5 COMPARISON PROGRAM F. REPORT CONTENT

1. ANNUAL RADIOLOGICAL '-1 ENVIRONMENTAL OPERATING REPORT

2. SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

3. SPECIAL REPORTS (RADIOLOGICAL F-3 ENVIRONMENTAL MONITORING) 828o

RETS Manual Revision 9 Page 7 The purpose of this manual is to provide the sampling and analysis programs which provide input to the ODCM for'calculating liquid and gaseous effluent concentrations and offsite doses. Guidelines are provided for operating radioactive waste treatment systems in order that offsite doses are kept as-low-as-reasonable-achievable (ALPS).

The Radiological Environmental Monitoring Program outlined within this manual provides confirmation that the measurable concentrations of radioactive material released as a result of operations at the Browns Ferry Plant are not higher than expected.

En addition, this manual outlines the information required to be submitted to the NRC in both the Annual Radiological Environmental Operating Report and the Semiannual Radioactive Effluent Release Report.

A-l 828o

RETS Manual Revision 9 Page 8 B. RESPONSIBILITIES All changes to this manual shall be reviewed by the Plant Operations Review Committee prior to implementation.

All changes to this manual shall be approved by the NRC prior to implementation.

It shall be the responsibility of the Plant Manager to ensure that this manual is used in performance of the surveillance requirements and administrative controls of the Technical Specifications.

B-1 828o

RETS Manual Revision 9 Page 9 C.l Radioactive liquid waste sampling and activity analysis of each liquid waste batch to be discharged shall be performed prior to release in accordance with Table C-l.

The results of the analysis of samples collected from release points shall be used with the calculational methodology in the ODCM to assure that the concentrations at the point of release are maintained within the limits of the Technical Specifications.

C-1 828o

RETS Hanual-Revision 8 Page 10 TABLE C-1 RADIOACTIVE Ll(EUID WASTE SAMPLING AND ANALYSIS PROGRAM SYSTEM DESIGN CAPABILITY LIQUID RELEASE SAHP LING HINIHUH ANALYSIS TYPE OF ACTIVITY LOHER LIMIT OF DETECTION TYPE FRE UENCY FRE ENCY ANALYSIS (LLO) (mCi/ml)

Batch Haste Each Batch Each Batch Prior Principal Gamma 5E-7(3) releases( 1) to Release Emitters(4)

One Batch Honthl y Dissolved and 1 E-5(3) per Month Entrained Gases(5)

Monthly Monthly Tritium 1 E-5 Proportional Composite (2) Gross a 1 E-7 Quarterly Sr-89, Sr-90 5 E-8 Proportional Quarter ly Composite (2) Fe-55 1 E-6 C-2 828o

RETS Manual Revision 9 Page 11 TABLE NOTATION TABLE C<<l (1) A batch release is the discharge of liquid wastes of a discrete volume.

The discharge shall be thoroughly mixed prior to sampling.

(2) A proportional composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant and is representative of the liquid discharged.

(3) The LLD is defined, for the purposes of these specifications as the smallest concentration of radioactive material in a sample that will yield a new count (above system background) that will be detected with 95K probability with only 5'X probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 sb E w V

• 2.22 x 10

• Y

• exp (-Xdt)

Where:

LLD is the "a priori" lower limit of detection as defined above (as microcuries per unit mass or volume),

sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per disintegration),

V is the sample size {in units of mass or volume),

2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

X is the radioactive decay constant for the particular radionuclide, and ht for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

Typical values of E, V, Y, and ht should be used in the calculation.

It should be recognised that the LID is defined as a priori (before the fact) limit representing the capability of a measurement system and not as an a posterior (after the fact) limit for a particular measurement.

C-3 828o

RETS Manual Revision 9 Page 12 TABLE NOTATION TABLE C-1 {Continued)

{4) The principal gamma emitters for which the LLD specification vill apply are exclusively the following radionuclides: Zn65, Co60, Csl37, Nn54, Co58, Cs134, Ce141, Ce144, Mo99, and Fe59 for liquid releases. This list does not mean that only these nuclides are to be detected and reported.

Other nuclides detected within a "=95K confidence level, together with the above nuclides, shall also be identified and reported as being present.

Nuclides which are below the LLD for the analysis may not be reported as being present at the LLD Level for that nuclide. I-131 shall have a LLD of <1 E-6.

{5) Ganma Emitters Only.

C-4 828o

RETS Manual Revision 9 Page 13 C.2 LI UID RADIOACTIVE WASTE TREATMENT This section requires that the appropriate portions of the liquid radwaste treatment system be used when specified. This provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section II.D of Appendix I to 10 CFR Part'50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

This section also requires submittal of a special report if the limiting values are exceeded and unexpected failures of non-redundant radwaste processing equipment halt waste treatment.

The liquid radwaste system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge from the site when the projected monthly dose would exceed 0.06 mrem to the total body or 0.21 mrem to any organ per unit (see Figure 4'.8-lb, Technical Specification).

Doses due to liquid releases to unrestricted areas shall be projected at least once per 31 days, in accordance with the ODCM.

With radioactive liquid waste being discharged for more than 31 days without treatment and when the projected dose is in excess of limits specified above prepare and submit the Special Report pursuant to Section 6.7.2 of the Technical Specifications.

C-5 828o

Revision 9 Page 14 D. GASEOUS EFFLUENTS SAMPLING AND ANALYSIS PROGRAM D.l Radioactive gaseous waste sampling and activity analysis shall be performed in accordance with Table D-1. Dose rates shall be determined to be within limits of the Technical Specifications using methods contained in the ODCM.

Samples of offgas system effluents shall be analyzed at least meekly to determine the identity and quantity of the principal radionuclides being released.

D-1 828o

RETS Hanual Revision 8 Page 15 TABLE D-1 RADIOACTIVE GASEOUS HASTE SAHPLING AND ANALYSIS PROGRAH SYSTEH DESIGN CAPABILITY GASEOUS RELEASE SAMPLING HI NIMUH ANALYSIS TYPE OF ACTIVITY LONER LIMIT OF DETECTION TYPE FRE ENCY FRE ENCY ANALYSIS (mCi /ml )

A. Containment Prior to Each Prior to Each Purge Principal Gamma Purge Purge Grab Sample Emitters{3)

N-3 1E-6 B. I. Stack Grab Sample Monthly(4) Principal Gamma 1E 4(1)

Emitters(3)

2. Building Grab Sample Monthly(4) N-3 1E-6 Ventilation

a. Reactor/

Turbine

b. Turbine Exhaust C. Radwaste C. All Release Continuous Charcoal Sample I-131 lE-12(2)

Points Listed Sampler Heekly<<)

in B. Above Continuous Part cu/ate Sample Principal Gamma lE-ll Sampler Heekly(RJ Emitters(3) and I-131 1E-12(2)

Continuous Compos te Particulate Gross A1pha 1 E-1 1 Sampler Sample Monthly Continuous Compos) te Particulate Sr-89, .Sr-90 1E-11 Sampler Sample Quarterly D-2 f328o

RETS Manual Revision 9 Page 16 TABLE NOTATION TABLE D>>1 (1) The LLD is defined, for the purposes of these specifications as the smallest. concentration of radioactive material in a sample that will yield a new count (above system background) that will be detected with 95'X probability with only 5'X probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 sb E + V + 2.22 x 10

• Y + exp (-Xht)

Where:

LLD is the "a priori" lower limit of detection as defined above (as microcuries per unit mass or volume),

sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute ),

E is the counting efficiency (as counts per disintegration),

V is the sample sire (in units of mass or volume),

2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

X is the radioactive decay constant for the particular radionuclide, and ht for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

Typical values of E, V, Y, and 4t should be used in the calculation.

lt should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posterior (after the fact) limit for a particular measurement.

(2) When samples are taken more often than that shown, the minimum detectable concentrations can be correspondingly higher.

D-3 828o

RETS Manual Revision 9 Page 17 (3) The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Hn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide.

(4) Analysis shall also be performed if the radiation monitor alarm exceeds the setpoint value.

828o

RETS Nanual Revision 9 Page 18 D.2 GASEOUS RADIOACTIVE WASTE TREATMZÃP Doses due to gaseous releases to areas at and beyond the site boundary shall be projected in accordance with the ODCM at least once per 31 days.

D-5 828o

RETS Manual Revision 9 Page 19 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLING AND ANALYSIS The radiological monitoring program required by this section provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation.

This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measureable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis, of the effluent measurements and modeling of the environmental exposure pathways.

The radiological environmental monitoring program shall be conducted as specified in Table E-l.

The radiological environmental monitoring samples shall be collected pursuant to Table E-1 from the locations given in the table and figure in the ODCM and shaLl be analyzed pursuant to the requirement of Table E-1 and the detection capabilities required by Table E-2.

With the radiological environmental monitoring program not being conducted as specified in 'Table E-l, in lieu of a LER, prepare and subm'.

to the Commission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability or malfunction of automatic sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be reported in the Annual Radiological Environmental Operating Report.

With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table E-3 when averaged over any calendar quarter, in lieu of a LER, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a report which identifies the cause(s) for exceeding the limit(s) and defines the corrective action to be taken to reduce radioactive effluents so that the potential annual dose to a member of the public is less than the calendar year limits of the Technical Specifications. When more than one of the radionuclides in Table E-3 are detected in the sampling medium, this report shall be submitted if:

Conc(1) + Conc(2) + ... > 1.0 Limit(l) Limit(2)

When radionuclides other than those in Table E-3 are detected and are result of plant effluents, this report shall be submitted if the potential annual dose to a member of the public is equal to or greater than the calendar year limits of the Technical Specification.

E-1 828o

RETS Nanual Revision 9 Page 20 Such reports are not required if the measured level of radioactivity was not the .result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

With milk or fresh leafy vegetabl.'e samples unavailable from one or more of the sample locations required by Table E-1 identify locations for obtaining replacement samples, if available, and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program.

In lieu of a LER, identify the cause of the unavailability of samples and identify the new location(s), if available, for obtaining replacement samples in the next Annual Radiological Environmental Operating Report and also include a revised figure(s) and table(s) for the ODCM reflecting the new locations.

The provisions of Technical Specification 1.0.C are not applicable.

The detection capabilities required by Table E-2 are state-of-the-art for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of the measurement system and not as an a osterior {after the fact) limit for particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions, Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

828o

RETS Manual Revision 9 Page 21 E.2 LAND USE CENSUS A land use cens us shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden* of greater than 500 square feet producing fresh leafy vegetables in each o the 16 meteorological sectors within a distance of five miles. (For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles).

With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the maximum value currently being calculated in section D.2 of this manual, in lieu of a LER, identify the new locations in the next Annual Radiological Environmental Operating Report.

With a land use census identifying a location(s) that yie1ds a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with section E.l, add the new location(s) to the radiological environmental monitoring programs .within 30 days if the owner consents. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s) (via the same exposure pathway) may be deleted from this monitoring program after October 3) of the year in which this land use census was conducted. ln lieu of a LER, identify the new location{s) in the next Annual Radiological Environmental Operating Report and provide a revised figure(s) and table for the ODCM reflecting the new location(s).

~Broad leaf vegetation sampling may be performed at the site boundary in the direction section with the highest Dig in lieu of the garden census.

828o

RETS Manual Revision 9 Page 22 The land use census shall be conducted at least once per calendar year between .the dates of April 1 and October 1 using the following techniques:

a~ Within a 2 mile radius from the plant or within the 15 mrem per year isodose line, whichever is larger, enumeration by a door<<to-door or equivalent counting technique.

b. Within a 5 mile radius from the plan, enumeration by using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other reliable sources.

This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this census.

The best survey information from the door-to-door, mail, telephone, aerial or consulting with local agricultural authorities shall be used.

This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via fy vegetables 1 cay g will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) o leafy vegetation assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20'X of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/square meter.

828o

RETS Manual Revision 9 Page 23 The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.

A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with the ODCM {or

, participants in the EPA cross check program shall provide the EPA program code designation for the unit) shall be included in the Annual Radiological Environmental Operating Report.

With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

828o

RETS Hanual Revision 8 Page 24 TABLE E-1 RADIOLOGICAL ENVIRONHENTAL HONI TORING PROGRAH Number of Samples Exposure Path~ay and Sampling and Type and Frequency

~dl S Sam le Locationsa Collection Fre uenc of Anal sis AIRBORNE Radioiodine and Hinimum of 5 locations Continuous operation of Radioiodine canister.

Particulates sampler with sample Analyze at least once collection as required by per 7 days for I-131.

dust loading but at least once per 7 days. Particulate sampler.

Analyze for gross beta radioactivity > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change.

Perform gamma isotopic analysis on each sample when gross beta activity is greater than 10 times the average of control samples. Perform gamma isotopic analysis on compos)te (by location) sample at least once per 92 days.

2. DIRECT RADIATION At least 40 locations At least once per 92 days. Gamma dose. At least with > 2 dosimeters once per 92 days.

at each location.

aSample locations are given in the OOCH.

E-6

RETS Hanual Revision 8 Page 25 TABLE E-1 (Continued)

RADIOLOGICAL ENVIRONHENTAL HONI TORING PROGRAH Number of Samples t;xposure Pathway and Sampl ing anil Type and Frequency

~dl d Sam le Locationsa Col lection Frequ~enc of Anal sis HATERBORNE

a. Surface 2 locations Compositeb sample collected Gamma isotopic analysis over a period of < 31 days. of each composite sample.

Tritium analysis of com-posite sample at least once per 92 days.

b. Drinking Hinimum of downstream 1 Composi teb sample collectedc Gross beta and gamma location, or all water over a period < 31 days. isotopic analysis of supplies within 10 miles each composite sample.

downstream which are Tritium analysis of taken from the Tennessee composite sample at least River. once per 92 days.

c. Sediment Hinimum of 1 location At least once per 184 days. Gamma isotopic analysis of each sample.

d. Groundd aSample locations are shown in the ODCH.

hComposite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours.

cComposite samples shall be collected over a period of < 14 days for 13 I if drinking water is obtained within 3 miles downstream of the plant.

dGi ound water movement in the area has been determined to be from the plant site toward the Tennessee River.

Since no drinking water wells exist between the plant and the river, ground water will not be monitored.

E-7 fl28o

0 RETS Manual Revision 8 Page 26 TABLE E-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM did Exposure Pathway INGE S T ION Number Sam of and Samples le Locationsa Sampling and Collection Fre uenc Type and Frequency of Anal sis

a. Mi lk 3 locations At least once per 15 days I-131 analysis of each when animals are on pasture; sample. Gamma isotopic at least once per 31 days analysis at least once at other times. per 31 days.

b. Fish 2 sampl es One sample in season, or at Gamma isotopic analysis least once per 184 days if on edible portions.

not seasonal. One sample of commercial and game species.

c. Food Productse 2 locations At least once per year Gamma isotopic analysis at time of harvest. on edible portion.

aSample locations are shown in the ODCH.

eSince water from the Tennessee River in the immediate area downstream is not used for irrigation purposes, the sampling of food products (primarily broad leaf vegetation) is not required unless milk sampling is not performed.

E-8 828o

RETS Manual Revision 8 Page 27 TABLE E-2 HAXIHUH VALUES FOR THE LOHER LIMITS OF OETECTION (LLO)abc Airborne Par t i cul a te Hater or Gas Fish Hi lk Food Products Sediment Analysis (pCi/1) (pCi/m3) (pCi/kg, wet) {pCi/1) {pCi/kg, wet) (pCi/kg, dry)

<lross beta 1 x10-2 N.A. N.A. N.A. N.A.

2000 N.A. N.A. N.A. N.A. N.A.

Hn-54 15 N.A. 130 N.A. N.A.

Fe-59 30 N.A. 260 N.A. N.A. N.A.

C0-58, 60 15 N.A. 130 N.A. N.A. N.AD ln-65 30 N.A. 260 N.A. N.A. N.A.

7r-95 30 N.A. N.A. N.A. N.A. N.A.

Nb-95 15 N.A. N.A. N.A. N.A. N.A.

l- l31 lb 7x102 N.A. 60 N,A.

Cs-134 15 5 x 10-2 130 15 60 150 Cs-137 18 6 x 10-2 150 18 80 180 Oa-140 60 N.A. N.A. 60 N.A. N.A.

l.a- l40 15 N.A. N.A. 15 N.A. N.A.

E-9 828o

lSC Lh "lBIluaJ.

Revision 9 Page 28 TABLE E-2 (Continued)

TABLE NOTATION The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95K probability with 5'X probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 sb E

• V

• 2.22

• Y

• exp (-Xbt)

Where:

LLD is the "a priori" lower limit of detection as defined above (as picocurie per unit mass or volume),

sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per disintegration),

V is the sample size (in units of mass or vcrlume),

2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),

X is the radioactive decay constant for the particular radionuclide, and ht is the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluent samples).

It should be recognized that the LLD is defined as a ~riori (before the fact) limit representing the capability of a measurement system and not E-10 828o

RETS Manual Revision 9 Page 29 TABLE E-2 (Continued)

TABLE NOTATION

b. The LLD for analysis of drinking ~ater and surface water samples shall be orme by gamma spectroscopy at approximately 15 pCi/1..

erformed per If levels greater than 15 pCi/L are identified in surface water samples downstream from the plant, or in the event of an unanticipated release of I-131, drinking water samples will be analyzed at an LLD of 1.0 pCi/L for I-131.

C ~ Other peaks which are measurable and identifiable, together with the radionuclides in Table E-3, shall be identified and reported.

E-11 828o

RETS Hanual Revision 8 Page 30 TABLE E-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONHENTAL SAHPLES Reporting Levels Hater Airborne Particulate Fish Mi1k Food Products

~Anal sls (AC)(1) or Gases ( Ci/m3) ( Ci/K wet) ~(C) /) ) ( Ci/K wet)

Il-3 2 x 104(>> N.A. N.A. N.A. N.A.

Hn-54 1 x 103 N.A. 3 x 104 N.A. N.A.

fe-59 4 x 102 N.A. 1 x 104 N.A. N.A.

Co-5B 1 x 103 N.A. 3 x 104 N.A. N.A.

Co-60 3 x 102 N.A. 1 x 104 N.A. N.A.

/n-65 3 x 102 N.A. 2 x 102 N.A. N.A.

lr-Nb-95 4 x 102 N.A. N.A. N.A. N.A.

1-l3l 0.9 N.A, 1 x 102 Cs-134 30 10 1 x 103 60 1 x103 Cs-137 50 20 2 x 103 70 2 x 103 Ba-La-140 2 x 102 N.A. N.A. 3 x 102 N.A.

<a)For drinking water samples. This is 40 CFR Part l41 value.

E-12 B2Bo

RETS Manual Revision 9 Page 31 F.l ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Routine Annual Radiological Environmental Operating Reports covering operation of the plant during the, previous calendar year shall be submitted prior to May 1 of each year.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the envizonment. The reports shall also include the results of land use censuses required by section E.2 of this manual. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problems and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missi~ data shall be submitted as soon as possible in a supplementary report.

The repozts shall also include the following: a sumnary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor', and the results of licensee participation in the Interlaboratory Comparison Program, required by section E.3 of this manual.

F-1 828o

RETS Manual Revision 9 Page 32 F.2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT A report on the radioactive discharges released from the site during the previous 6 months of operation shall be submitted to the Director of the Regional Office of Inspection and Enforcement within 60 days after January 1 and July 1 of each year. The report shall include summary of the quantities of radioactive liquid and gaseous effluents released and solid waste shipped from the plant as delineated in Regulatory Guide 1.21, Revision 1, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from LightMaterCooled Nuclear Power Plants," with data sumnarized on a quarterly basis following the format of Appendix B thereof.

The report shall include a suamary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, Revision 1, with data summarized on a quarterly basis following the format of Appendix B thereof. Calculated offsite dose to members of the public resulting from the release of liquid and gaseous effluents and their subsequent dispersion in the river and atmosphere shall be reported as recommended in Regulatory Guide 1.21, Revision 1. The Radioactive Effluent Release Report shall include the following information for each type of solid waste shipped offsite during the report period (a) container volume, (b) total curie quantity, (specify whether determined by measurement or estimate), (c) principal radionuclides (specify whether determined by measurement or estimate),

(d) sources of waste and processing employed (e.g. dewatered spent resins, compacted dry waste, etc.), (e) type of container (e.g., LSA, Type A, Type B, large quantity), and (f) solidification agent or absorbant (e.g. concrete, urea formaldehyde, etc.).

828o

0 RETS Manual Revision 9 Page 33 If measured levels of radioactivity in an environmental sampling medium are determined to exceed the reporting level. values of Table E-3 vhen averaged over any calendar quarter sampling period, a report shall be submitted to the Commission pursuant to Section E.l of this Manual.

828o

RETS Manual Revision 9 Page 34 RETS MANUAL Section III OFFSITE DOSE CALCULATION NANUAL (ODCM) 828o

sy~p.

RETS Manual Revision 9 Page 35 Brogans Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 1 of 10)

Section page INTRODUCTION ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 46 1/2 CONTROLS AND SURVEILLANCE REQUIREHTS . ~ ~ ~ ~ ~ ~ ~ . ~ ~... ~... ~ . ~ .. 48 1/2 ~ 0 APPLICABILITY ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

40 1/2.1 INSTRUMENTATION ..............-...... .... -...............-

~ .. 50 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ...... 50 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ..... 55 1/2.2 RADIOACTIVE EFFLUENTS .... . . ~..... ~.... -

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

~ ~ 60 1/2.2.1 LIQUID EFFLUENTS ...--....o.-................................ 60 t 1/2.2.1.1 1/2.2.1.2 1/2.2.1.3 1/2.2.2 1 /2 ~

CONCEhTRATION DOSE ~ ~ ~

GASEOUS EFFLUENTS 2 ~ 2 o 1 DOSE RATE

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

LIQUID RADWASTE TREAT%M'YSTEM

~ ~ .. ..

~ ~ . ~

.... ~...................,

~

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

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

60 c4 65 66 66 1/2.2.2.2 DOSE NOBLE GASES ........................................ 69 1/2.2.2.3 DOSE I-131, I-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYS . 70 1/2.2.2.4 GASEOUS RADWASTE TREATMENT ~ .. .............. ............. ~ 71 1/2.2.3 TOTAL DOSE . .................. .. .......... ..... ......... ~ 72 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING ......................... 73 1/2.3.1 MONITORING PROGRAM ........ ....... .........................

~ ~ 73 1 /2 o 3 ~ 2 LAND USE CENSUS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 81 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM ..... ~.... .. ~ ~ . ~ .. ~....... 83 828o

RETS Manual Revision 9 Page 36 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 2 of 10)

Section page BASES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I~ ~ ~ ~ ~ ~ ~ 84 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ...... 85 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ..... 85 1/2. 2 RADIOACTIVE EFFLUENTS ..... ~............. . ~.... ~... ~........

~ ~ ~ 85 1/2.2.1.1 CONCENTRATION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ . ~ .. ~ ~ ~ 85 1/2.2.1.2 DOSE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 86 1/2.2.1.3 LIQUID WASTE TREATMENT ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ .. ~ ~ ~ ~ 86 1/2.2.2.1 DOSE RATE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e 87 1/2.3.2.2 DOSE NOBLE GASES ................ . .-.......... ........ 87 1/2.2.2.3 DOSE I-131, I-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o. ~ 88 1/2.2.2.4 GASEOUS RADWASTE TREATMENT ... .. ~.... . ~...............

~ ~ ~ ~ ~ 89 1/2.2.3 TOTAL DOSE .................................................. 89 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING ........................ 89 1/2.3.1 MONITORING PROGRAM ........-................................. 89 1/2.3.2 LAND USE CENSUS ............................................. 90 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM .......................... 90 3.0 DEFINITIONS d]

3.0.A. CHANNEL CALIBRATION ~ . ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ~ ~ 92 3.0.B. CHANNEL FUNCTIONAL TEST ..... ~ ~ .~. ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .. ~ ~ ~ 92 3.0.C. GASEOUS WASTE TREATMENT SYSTEM ~... ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ - ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ ~ .- ~ 92 3.0.D. DOSE EQUIVALENT I-131 ...................................... . 92 3.0.E. MEMBER(S) OF THE PUBLIC ...................................... 92 3.0.F. OPERABLE OPERABILITY ................................ ~ ~ ~ ~ .. ~ 93 3.0.G. PURGE - PURGING .............................................. 93 828o

RETS Manual Revision 9 Page 37 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 3 of 10)

Section page 3.0.H. RATED POWER ...........-..... '...............-.-....-.... 93 3.0.I. SITE BOUNDARY . ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ~ ~ 93 3.0.J. SOURCE CHECK .................. .....-..............-.-....... 93 3 'oKo UNRESTRICTED AREA ~ ~ ~ ~ ~ ~ ~ ~ ooo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 04 9

3 ~ 0 ~ L o VENTING ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ j 94 4.0 (NOT USED) .........-.........-. .. .... . ................-.. 97 5.0 ADMINISTRATIVE CONTROLS ~ ~ ~ ~ . .

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

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

~ 98 5.1 ANNUAL RADIOLOGICAL ENVIRONNENTAL OPERATING REPORT .............. 99 5.2 SEMIANNUAL RADIOACTIVE EFFLUENT~ RELEASE REPORT .................. 99 5.3 OFFSITE DOSE CALCULATION MANUAL CHANGES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 100 5 ' SPECIAL REPORTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 100 6 ~0 LIQUID EFFLUENTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 101 RELEASE POINTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ o 102 6 ' LIQUID RELEASES ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 103 6.1.1 Pre-release Analysis/MPC - Sum of the Ratios .................. 103 6.1.2 Release Flow Rate Calculations ................................ 103 6.1.3 Post-release Analysxs ................-........................ 104 6 ' INSTRUMENT SETPOINTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ oo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 105 6.2.1 Radwaste Discharge Monitor .................................... 105 6.2.2 Raw Cooling Water and Residual Heat Removal Service Water M onl tors ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 106 6.3 CUMULATIVE LIQUID EFFLUENT DOSE CALCULATION ..................... 107 6.3.1 Monthly Analysis ...... ... ~ ~ o ~ 1&7 10 6.3.1.1 Water Ingestion ............................................. 108 828o

RETS Manual Revision 9 Page 38 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 4 of 10)

Section page 6.3.1.2 Fish Ingestion ..... .....

~ ~ .~. ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ . ~ ................ 109 6.3.1.3 Recreation ...... ...... .

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

~ ~ 110 6.3.1.4 Monthly Suaxnary ........ . - . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ~ ~ ~ ~ ~ .................. 111 6.4 LIQUID RADWASTE TREATMENT SYSTEM ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ................

~ 112 6.5 DOSE PROJECTIONS -.............. ................................ 113 6.6 DOSE CALCULATIONS FOR REPORTING PURPOSES ....................... 114 6.6.1 Water Ingestion ............................................... 1114 6.6.2 Fish Ingestion ..........o.............o....................... 115 6.6.3 Shoreline Recreation .......................................... 115 6.6.4 Total Maximum Individual Dose . ...............................

~ 116 6.6.5 Population Doses .............................................. 117 6.7 LIQUID DOSE FACTOR EQUATIONS .................................,.. 119 6.7. Water Ingestion Dose Factors ..................................

1 119 6.7.2 Fish Ingestion Dose Factors ................................... 119 6.7.3 Shoreline Recreation Dose Factors ............................. 119 7.0 GASEOUS EFFLUENTS ~ ~ ~ o ~ 139 RELEASE POINTS DESCRIPTION . ~ .., .. ~..............,....... ~...... 11400 7.1 RELEASE RATE LIMIT METHODOLOGY 141 7.2 GASEOUS EFFLUENT MONITOR INSTRUMENT SETPOINTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ..... 144 7.2.1 Alarm/Trap Setpoxnts

~ ~

144 7.2.2 Allowable Values 144 7.3 GASEOUS EFFLUENTS DOSE RATES .................................. 146 7.3.1 Noble Gas Dose Rates 146 828o

RETS Manual Revision 9 Page 39 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 5 of 10)

Section page 7.3.2 I-131, I-133, Tritium and all Radionuclides in Particulate Form ~ith Half-lives of Greater than 8 days Organ Dose Rate ...........-.......-....-.....--..--.......... 147 7 ~ 4 DOSE NOBLE GASES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ to ~ ~ 148 7.4.1 Monthly Noble Gas Dose ........................................ 148 7.4.1.1 Monthly Conservative Model Gamma Air Dose ................. 148 7.4.1.2 Monthly Conservative Model Beta Air Dose .................. 149 7.4.1.3 Cumulative Dose Noble Gas ................................. 149 7.4.1.4 Comparison to Limits ........................................ 149 7.5 CUMULATIVE DOSE - I-13l, I-133, TRITIUM AND RADIONUCLIDES IK PARTICULATE FORM WITH HALF LIVES GREATER THAN 8 DAYS . ~......... 150 7.5.1 Monthly Conservative Model Infant Thyroid Dose from Milk Ingestion .................................................... 151 7.5.2 Monthly Conservative Model Child Bone Dose from Vegetable Ingestion ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 152 7.5.3 Monthly Conservative Model - Teen Gastrointestina 1 Tract (GIT)

Dose from Vegetable Ingestion ................... ~ ~ ~ ~ ~ ~ 153 7.5.4 Cumulative Doses 1 g4 7.5.5 Total Monthly Dose - Comparison to Limits ..................... 154 7o6 GASEOUS RADWASTE TREATMENT ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ o 155 7..6.1 Dose Progections ......................... .................... ~ 155 7.6.2 System Descrxptxon ............................................ 155 7.7 DOSE CALCULATIONS FOR REPORTING PURPOSES ........................ 156 7.7.1 Noble Gas Dose ..............................-................. 156 7..7.1.1 Ganxna Dose to Axr ........-....-...........-......-.......... 157

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 157 828o

I RETS Manual Revision 9 Page 40 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 6 of 10)

Section page 7.7.2 Radioiodine, Particulate and Tritium - Maximum Organ Dose ..... 158 7.7.3 Population Doses .......................-..-................... 160 7.7.4 Reporting of Doses ............................................ 161 7.8 GASEOUS DOSE FACTOR EQUATIONS ....... ... . . . ... . ...... 163 7.8.1 Pasture Grass-Cow-Goat-Milk Ingestion Dose Factors ............ 163 7.8.2 Stored Feed-Cow/GoatMilk Ingestion Dose Factors .............. 164 7.8.3 Pasture Grass-Beef Ingestion Dose Factors ..................... 164 7.8.4 Stored Feed-Beef Ingestion Dose Factors ......................, 165 7.8.5 Fresh Leafy Vegetable Ingestion Dose Factors .................. 166 7.8.6 Stored Vegetable Ingestion Dose Factors ....................... 167 7.8.7 Tritium-Pasture Grass-Cow/Goat-Milk Dose Factor ....,........,. 168 7.8.8 Tritium-Stored Feed-Cow/GoatMilk Dose Factor ................. 169 7.8.9 Tritium-Pasture Grass-Beef Dose Factor ........................ 170 7.8.10 Tritium-Stored Feed-Beef Dose Factor ......................... 171 7.8.11 Tritium-Fresh Leafy Vegetable Dose Factor .................... 172 7.8.12 Tritium-Stored Vegetables Dose Factor ........................ 173 7.8.13 Inhalation Dose Factors ...................................... 174 7.8.14 Ground Plane Dose Factors ............-....................... 174 7.9 DISPERSION METHODOLOGY .................. . . . .-

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ~ ~ ~ ~ . .~ ~ 175 7.9. 1 Annual Average Air Concentration ..... ~ -. ~ ~ ~ -- ~ ~ - " ~ ~ ~ ~ ~ ~ ~ ~ ~ .. 176 7.9.2 Relative Concentration ..................... .. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ -. 177 7.9.3 Relative Dispersion ................................. ~ .~.~- ~ ~ ~ . 177 7.9.4 Effective Release Height h . ... 178 828o

RETS Manual Revision 9 Page 41 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 7 of 10)

Section page 8.0 TOTAL DOSE .............-......... . .....-..-................. 225 9.0 ENVIRONMENTAL MONITORING PROGRAM ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .. ~ . ~ .. 227 9.1 MONITORING PROGRAM DESCRIPTION .................................. 228 9.2 DETECTION CAPABILITIES ..........--. " .....-....-........-....... 228 9 ' LAND USE CENSUS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 228 9.4 INTERLABORATORY COMPARISON PROGRAM .......... ...................

~ 228 828o

RETS Manual Revision 9 Page 42 Brains Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 8 of 10)

LIST OF TABLES page Table 1.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION .. 51 Table 2.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE(UIREMENTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ 53 Table 1.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION . 56 Table 2.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE(UIREKZTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . 58 Table 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM .. 61 Table 2.2-2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM ~ ~ ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 67 Table 2.3-1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 75 Table 2.3-2 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION (LLD)

FOR ENVIRONHTAL SAMPLES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .. ~ ~ 78 Table 2.3-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 80 Table 3.1 FRE(UENCY NOTATION ........................................ 95 Table 6.1 RECEPTORS FOR LI(UID DOSE CALCULATIONS .................... 120 Table 6.2 RADIONUCLIDE DECAY AND STABLE ELENA TRANSFER DATA ....... 121 Table 6.3 DOSE CALCULATION FACTORS .................................. 124 Table 6.4 INGESTION DOSE FACTORS 126 Table 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH 134 Table 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 135 Table 7.1 BFN OFFSITE RECEPTOR LOCATION DATA ............-....-.... 179 Table 7.2 EXPECTED ANNUAL ROUTINE ATMOSPHERIC RELEASES FROM ONE UNIT AT BFN ~ ~ ~ ~ ~ a ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 18QO 1

Table 7.3 JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION .......,..... 181 Table 7.4 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES ................ 203 828o

RETS Manual Revision 9 Page 43 Brogans Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 9 of 10)

LIST OF TABLES page Table 7.5 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES .......... 204 Table 7.6 BFN 50-MILE POPULATION WITHIN EACH SECTOR ELEMENT ........ 205 Table 7.7 INHALATION DOSE FACTORS ..... ..-..-... .. ............... 206 Table 9.1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ............ 229 Table 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 234 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS ..................., 235 828o

RETS Manual Revision 9 Page 44 Brogans Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 10 of 10)

LIST OF FIGURES page Figure 3.1 LAND SITE BOUNDARY ~ ~ ~ - ~ ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~........... 96 Figure 6.1 LIQUID RELEASE POINTS . ~ . ~ . ~ ~ .~. ~ ~ ~ ~ ~ ~ . ~.................. 137 Figure 6.2 LIQUID RADWASTE SYSTEM ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~.................. 138 Figure 7.1 OFFGAS SYSTEM AND SGTS EFFLUENT MONITORING ............... 214 Figure 7.2 NORMAL BUILDING VENTILATION ~ ~ ~... ~ ~....................,, 215 Figure 7.3 PLUME DEPLETION EFFECT ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ~ ~ ~ ~ ~ . ~........... 216 Figure 7.4 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME ....... 220 Figure 7.5 RELATIVE DEPOSITION ...................................... 221 Figure 9.1 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS WITHIN 1 MILE OF THE PLANT . ~ ........ ~ . ~ . ~ .. ~ ~ ~ .... ~ . ~ .... ......

~ 236 Figure 9.2 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS FROM 1 TO 5 MILES FROM THE PLANT ..........o........o....o.......o.. 237 Figure 9.3 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS GREATER THAN 5 MILES FROM THE PLANT .. ~ . ~ . ~ .... ................

~ ~ ~ 238 828o

RETS Manual Revision 9 Page 45 SECTION 1.0 AND 2.0 CONTROLS AND SURVEILLANCE RE UIRENENTS 828o

RETS Manual Revision 9 Page 46 INTRODUCTION The Browns Ferry Nuclear Plant (BFN) Offsite Dose Calculation Manual (ODCM) is a supporting document of the BFN Technical Specifications. The ODCM is divided into two major parts. The first part of the ODCM contains: l) Radioactive Effluent Controls specified by the BFN Technical Specifications; 2) Radiological Environmental Monitoring Controls required by the BFN Technical Specifications; 3) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by BFN Technical Specifications; and, 4) Administrative Controls for the ODCM requirements. The second part of the ODCM contains the methodologies used to: 1) calculate offsite doses resulting from radioactive gaseous and liquid effluents; 2) calculate gaseous and liquid effluent monitor Alarm/Trip setpoints; and, 3) conduct the Environmental Radiological Monitoring Program.

The BFN ODCM is maintained for use as a reference guide on accepted methodologies and calculations. Changes in the calculation methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents the present methodology in all applicable areas. Any licensee initiated ODCM changes will be implemented in accordance with BFN Technnical Specifications.

828o

RETS Manual Revision 9 Page 47 i ive waste release levels to Radioactive UNRESTRICTED AREAS should be kept "as low as reasonably achievable" and are not to exceed the concentration limits specified in 10 CFR Part 20, Appendix B, Table II. At the same time, the requirements specified in this manual permit the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than design objectives but still within the concentration limits specified in 10 CFR Part 20. It is expected that by using this operational flexibility and exerting every effort to keep levels of radioactive releases "as low as reasonably achievable" in accordance with criteria established in 10 CFR Part 50, Appendix I, the annual releases will result in a small fraction of the annual average concentration limits specified in

~ ~

10 CFR Part 20, Appendix B, Table II.

The surveillance/testing requirements given in this manual provide assurance that liquid and gaseous wastes are properly controlled and monitored during any release of radioactive materials in the liquid and gaseous effluents. These requirements provide the data for the licensee and the Commission to evaluate the station's performance relative to radioactive materials released to the environment. Reports on the quantities of radioactive materials released in effluents shall be furnished to the Commission on the basis of Section 5.0 of this manual.

On the basis of such reports and any additional information the 1 Commission may obtain from the licensee or others, the Commission from time to time require the licensee to take such actions as the Commission deems appropriate.

may 828o

0 RETS Nanual Revision 9 Page 48 1/2 CONTROLS AND SURVEILLANCE RE UIRENENTS 1/2.0 APPLICABILITY CONTROLS 1.0.1 Compliance with the Controls con'tained in the succeeding sections is required during the conditions specified therein; except that upon failure to meet the Control, the associated ACTION requirements shall be met.

Noncompliance with a Control shall exist when the requirements of the Contxol and associated ACTION requirements are not met within the specified time intervals. If the Control is restored prior to the expiration of the specified intervals, completion of the ACTION requirements is not required.

828o

RETS Manual Revision 9 Page 49 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS l/2.0 APPLICABILITY SURVEILLANCE RE UIRENENTS 2.0.1 Surveillance Requirements shall 'be met during the conditions specified for individual Controls unless otherwise stated in the individual Surveillance Requirement.

2.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:

a. A maximum allowable extension not to exceed 25K of the surveillance interval, but

b. The combined time for any three consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval.

2.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance and OPERABILITY requirements for a Control and associated action statements unless otherwise required by these Controls. Surveillance Requirements do not have to be performed on inoperable equipment.

828o

0 RETS Manual Revision 9 Page 50 1'/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.1 INSTRUMENTATION 1/2.1.1 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUKPPZATION CONTROLS 1.1.1 The radioactive liquid effluent monitoring instrumentation listed in Table 1.1-1 shall be OPERABLE with the applicability as shown in Tables 1.1-1 and 2.1-1. Alarm/trip setpoints will be set in accordance with guidance given in ODCM Section 6.2 to ensure that the limits of Control 1.2.1.1 are not exceeded.

APPLICABILITY: This requirement is applicable as shown in Table 1.1-1.

ACTION:

a. With a radioactive liquid effluent monitoring channel alarm/trip setpoint less conservative than required by these requirements, suspend the release without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism required by these requirements.

b. The action required when the number of OPERABLE channels is less than the minimum channels OPERABLE requirement is specified in the notes for Table 1.1-1. Exert best efforts to return the instrument(s) to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

SURVEILLANCE RE UIREMENTS 2.1.1 Each of the radioactive liquid effluent monitoring instruments shall be demonstrated OPERABLE by performance of tests in accordance with Table 2.1-1.

828o

RETS Manual Revision 9 Page. 51 Table 1.1-1 (Page 1 of 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument* OPERABLE A licabilit Action

1. Liquid Radwaste Effluent Monitor (RM-90-130) A/B

2. RHR Service Water Monitor (RM-90-133, -134)

3. Raw Cooling Water Monitor (RM-90-132)

4. Liquid Radwaste Effluent Flow Rate (77-60 loop)

Alarm/trip setpoints will be calculated in accordance with the guidance given in Section 6.2.

During Releases via this pathway.

• +* During operation of an RHR loop and associated RHR service water system.

828o

RETS Manual Revision 9 Page 52 Table 1.1-1 (Page 2 of 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION ACTION A During release of radioactive wastes from the radwaste processing system, the following shall be met:

(1) liquid waste activity and flowrate shall be continuously monitored and recorded during release and shall be set to alarm and automatically close the waste discharge valve before exceeding the limits specified in Control 1.2.1.1, (2) if this cannot be met, two independent samples of the tank being in accordance with the sampling and discharged shall be analyzed analysis program specified in Table 2.2.1 and two qualified station personnel shall independently verify the release rate calculations and check valving before the discharge. Otherwise, suspend releases via this pathway.

ACTION B With a radioactive liquid effluent monitoring channel alarm/trip setpoint less

,conservative than required by these requirements,.suspend release via this pathway without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism required by these requirements.

ACTION C During operation of an RHR loop and associated RHR service water system, the effluent from that unit's service water shall be continuously monitored. If an installed monitoring system is not available, a temporary monitor or grab samples taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and an analysis with at least an LLD of lE-7 pCi/ml (gross) or ( applicable MPC ratio (y isotopic) shall be used to monitor the effluent.

ACTION D With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that a temporary monitor is installed or, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, grab samples are collected and analyzed for radioactivity with an LLD of 1E-7 pCi/ml (gross) or ( applicable MPC ratio (y isotopic).

ACTION E With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continued provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump curves may be used to estimate flow.

See Table 2.2-1, Table Notation for the definition of LLD.

828o

RETS Manual Revision 9 Page. 53 Table 2.1-1 (Page 1 of 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT SOURCE CHANNEL FUNCTIONAL Instrument CHECK CHECK CALZHRATION TEST

a. Liquid Radwaste Effluent D4 Ql Monitor (RM-90-130)

b. RHR Service Water D4 Q2 Monitor (RM-90-133,-134)

c. Raw Cooling Water D4 R5 Q2 Monitor (RM-90-132)

d. Liquid Radwaste Effluent D4 N/A Q3 Flow Rate (77-60 loop) 828o

RETS Manual Revision 9 Page 54 Table 2.1-1 (Page 2 of 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATION NOTE: Each requirement shall be performed within the specified time interval with: (1) a maximum allowable extension not to exceed 25K of the interval given, but (2) the combined time entered for any 3 consecutive intervals shall not exceed 3.25 times the specified interval.

1 The CHANNEL FUNCTIONAL TEST shall demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

a. Instrument indicates measured levels above the alarm/trip setpoint.

b. Instrument indicates an inoperative/downscale failure.

c. Instrument controls not set in operate mode.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

a. Instrument indicates measured levels above the alarm/trip setpoint.

b. Instrument indicates an inoperative/downscale failure.

c. Instrument controls not set in operate mode.

This functional test shall consist of measuring rate of tank decrease over a period of time and comparing this value with flow rate instrument reading.

4 INSTRUMENT CHECK sh ll consist of verifying indication during periods of release. INSTRUMENT CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days which continuous, periodic, or batch releases are made.

The CHANNEL CALIBRATION shall include the use of a known (traceable to the National Institute of Standards and Technology (NIST))

radioactive source(s) positioned in a reproducible geometry with respect to the sensor or using standards that have been obtained from suppliers that participate in measurement assurance activities with the NIST.

828o

RETS Manual Revision 9 Page 55 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2. 1 INSTRUMENTATION 1/2. l. 2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 1.1.2 The radioactive gaseous effluent monitoring instruments listed in Table 1.1-2 shall be OPERABLE with the applicability as shown in Table 1.1-2. Alarm/trip setpoints will be set in accordance with guidance given in ODCM Section 7.2 to ensure that the limits of ODCM Control 1.2.2.1 are not exceeded.

APPLICABILITY: As shown in Table 1.1-2.

ACTION:

a. Pith a radioactive gaseous effluent monitoring channel alarm/trip setpoint less conservative than required by these requirements, suspend the release without delay, declare the channel inoperable o" adjust the alarm/trip setpoint to establish the conservatism required by these requirements.

b. Both off-gas treatment monitors may be taken out of service for less than one hour for purging of monitors during SI performance.

c. The action required when the number of operable channels is less than the minimum channels operable requirement is specified in the notes for Table 1.1-2. Exert best efforts to return the instrument(s) to operable status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

SURVEILLANCE RE UIREMENTS 2.1.2 Each of the radioactive gaseous effluent monitoring instruments shall be demonstrated OPERABLE by performance of tests in accordance with Table 2.1-2.

0 828o

RETS Manual Revision 9 Page. 56 Table 1.1-2 (Page 1 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels/

Instrument Action

1. Stack (RM-90-147A & B)

a. Noble Gas Monitor A/C

b. Iodine Cartridge B/C

c. Particulate Filter B/C

d. Sampler Flow Abnormal D

e. Stack Flow (FT, FM, FI-90-271) D

2. Reactor/Turbine Building Ventilation (RM-90-250)

a. Noble Gas Monitor A/C

b. Iodine Sampler B/C

c. Particulate Sampler B/C

d. Sampler Flowmeter D

3. Turbine Building Exhaust (RM-90-249, 251)

a. Noble Gas Monitor A/C

b. Iodine Sampler B/C

c. Particulate Sampler B/C

e. Sampler Flowmeter D

4. Radwaste Building Vent (RM-90-252)

a. Noble Gas Monitor 1 A/C

b. Iodine Sampler ] B/C

c. Particulate Sampler 1 B/C

e. Sampler Flowmeter 1 D

5. Offgas Post Treatment

a. Noble Gas Activity Monitor (RM-90-265, <<266)

b. Sample Flow Abnormal (PA-90-262) 828o

RETS Manual Revision 9 Page 57 Table 1.1-2 (Page 2 of 2)

RADIOACTIUE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION

• At all times.

~ During releases via this pathway ACTION A With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided a temporary monitoring system is installed or grab samples are taken and analyzed at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

ACTION B With a number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment for periods on the order of seven (7) days and analyzed in accordance with the sampling and analysis program specified in Table 2.2-2 within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the end of the sampling period.

ACTION C A monitoring system may be out of service for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for functional testing, calibration, or repair without providing or initiating grab sampling.

ACTION D With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION F With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Purging during SI performance is not considered a loss of monitoring capability.

828o

RETS Manual Revision 9 Page 58 Table 2.1-2 (Page 1 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT SOURCE CHANNEL FUNCTIONAL Ins trument CHECK CHECK CALIBRATION TEST

1. STACK

a. Noble Gas Moni.tor4 M Rl Q2

b. Iodine Cartridge N/A N/A N/A

c. Particulate Fi.lter N/A N/A N/A

d. Sampler Flow Abnormal N/A R Q

e. Stack Flowmeter N/A R Q

2. REACTOR/TURBINE BUILDING VENT

a. Noble Gas Monitor5 M Rl Q2

b. Iodine Sampler N/A N/A N/A

c. Particulate Sampler N/A N/A N/A

b. Sampler Flowmeter N/A R Q

3. TURBINE BUILDING EXHAUST

a. Noble Gas Monitor5 M Rl Q2

b. Iodine Sampler N/A N/A N/A

c. Particulate Sampler N/A N/A N/A

b. Sampler Flowmeter N/A R Q

4. RADWASTE BUZLDZNG VENT

a. Noble Gas Monitor M Rl Q2

b. Iodine Sampler N/A N/A N/A

c. Particulate Sampler N/A N/A N/A

b. Sampler Flowmeter N/A R Q

5. OFF GAS POST TREATMENT4

a. Noble Gas Activity D Q3 Monitor

b. Sample Flow Abnormal D N/A 828o

RETS Manual Revision 9 Page 59 Table 2.1-2 (Page 2 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTE: Each requirement shall be performed within the specified time interval with: (1) a maximum allowable extension not to exceed 25K of the interval given, but (2) the combined time entered for any 3 consecutive intervals shall not exceed 3.25 times the specified interval.

1 The CHANNEL CALIBRATION shall include the use of a known (traceable to the National Institute of Standards and Technology (NIST))

radioactive source(s) positioned in a reproducible geometry with respect to the sensor or using standards that have been obtained from suppliers that participate in measurement assurance activities with the NIST.

2 The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists.'.

Instrument indicates measured levels above the alarm/trip setpoint.

2. Instrument indicates an inoperative/downscale failure.

3. Instrument controls not set in operate mode (stack only).

3 The CHANNEL FUNCTIONAL TEST shall demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

l. Instrument indicates measured levels above the alarm/trip setpoint.

2. Instrument indicates an inoperative/downscale failure.

3. Instrument controls not set in operate mode (stack only).

The two channels are arranged in a coincidence logic such that 2 upscale, or 1 downscale and 1 upscale or 2 downscale will isolate the offgas line.

" The noble gas monitor shall have a LLD of 1E-5 (Xe-133 Equivalent) 5 The noble gas monitor shall have a LLD of 1E-6 (Xe-133 Equivalent) 828o

RETS Manual Revision 9 Page 60 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2. 2 RADIOACTIVE EFFLUENTS 1/2.2.1 LI UID EFFLUENTS 1/2.2.1.1 CONCENTRATION CONTROLS 1.2.1.1 The concentration of radioactive material released at any time from the site to UNRESTRICTED AREAS (see Figure 3.1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pCi/ml total activity.

APPLICABILITY: At all times.

ACTION:

If the above limits are exceeded, appropriate action shall be initiated without delay to bring the release within limits. Provide prompt notification to the NRC pursuant to Technical Specification 6.9.1.4.

SURVEILLANCE RE UIRE%2lTS 2.2.1.1.1 Facility records shall be maintained of radioactive concentrations and volume before dilution of each batch of liquid effluent released, and of the average dilution flow and the length of time over which each discharge occurred.

2.2.1.1.2 Radioactive liquid waste sampling and activity analysis of each liquid waste batch to be discharged shall be performed prior to release in accordance with the sampling and analysis program specified in Table 2.2-1.

2.2.1.1.3 The operation of the automatic isolation valves and discharge tank selection valves shall be checked annually.

2.2.1.1.4 The results of the analysis of samples collected from release points shall be used with the calculational methodology in ODCM Section 6.1 to assure that the concentrations at the point of discharge are maintained within the above limits.

828o

RETS Manual Revision 9 Page 61 Table 2.2-1 (Page 1 of 3)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM

System Design

Capability Liquid Minimum Type of Lower Limit of Release Sampling Analysis Activity Detection (LLD)

Type Frequency Frequency Analysis (pCi/ml)

Batch Waste Each Each Batch Principal 5x10"~ 3 Releasesl Batch Prior to Gamma Release Emitters4 One Batch Monthly Dissolved and lxl0"5 3 per Month Entrained Gases5 Monthly Tritium lx10 5 Composite"'onthly Prooortional Gross Alpha lxl0 7 Quarterly Quarterly Sr-89, Sr-90 5x10-8 Proportional Composite2 lxl0 6 828o

RETS Manual Revision 9 Page 62 Table 2.2-1 (Page 2 of 3)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION A batch release is the discharge of liquid waste of a discrete volume. The discharge shall be thoroughly mixed prior to sampling.

2 A proportional composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant and is representative of the liquid discharged.

3 The LLD is defined for the purpose of these requi.rements as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 951 probability with only a 5X probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4 66sb E V 2.22E+06 Y exp (-Xht)

Where:

= the "a priori" lower limit of detection as defined above (microcurie per unit mass or volume) sb the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = the counting efficiency (counts per disintegration)

V = the sample size (units of mass or volume) 2.22E+06 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, X the radioactive decay constant for the particular radionuclide (s 1), and the elapsed time between midpoint of sample collection and time of counting (s).

Typical values of E, V, Y, and bt should be used in the calculation.

It should be recognized that the LLD is defined as an a~riori (before the fact) limit representing the capability of a measurement system and not an a 4 The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides'. Zn-65, Co-60, Cs-137, Mn-54, Co-58, Cs-134, Ce-141, Ce-144, Mo-99 and Fe-59 for 828o

RETS Manual Revision 9 Page 63 Table 2.2-1 (Page 3 of 3)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION liquid releases. This list does not mean that only these nuclides are to be detected and reported. Other nuclides detected within a =95%

confidence level, together with the above nuclides, shall also be identified and reported as being present. Nuclides which are below the LLD for the analysis may not be reported as being present at the LLD level for that nuclide. I-131 shall have a LLD of ( 1E-6.

5 Gamma Emitters Only.

828o

RETS Manual Revision 9 Page 64 1/2 CONTROLS AÃ) SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LI UID EFFLUENTS 1/2.2.1.2 DOSE CONTROLS 1.2.1.2 The doses or dose coaanitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS shall be limited:

a. During any calendar quarter to < 1.5 mrem to the total body and to

< 5 mrem to any organ, and

b. During any calendar year to < 3 mrem to the total body and to < 10 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

If the limits specified above are exceeded, prepare and submit a Special Report pursuant to Technical Specification 6.9.1.4.

SURVEILLANCE RE UIREK2G'S 2.2.1.2 Cumulative quarterly and yearly dose contributions from liquid effluents shall be determined as specified in ODCM Section 6.3 at least once every 31 days.

828o

RETS Manual Revision 9 Page 65 1/22 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2. 2 RADIOACTIVE EFFLUENTS 1/2.2.1 LI UID EFFLUENTS 1/2-2.1.3 LI UID RADWASTE TREATMENT SYSTEM CONTROLS 1.2.1.3 The liquid radwaste system shall be used to reduce the radioactive materials in liquid discharge from the site when the projected monthly dose ~ould exceed 0.06 mrem to the total body or 0.21 mrem to any other organ per unit.

APPLICABILITY: At all times.

ACTION:

With radioactive liquid waste being discharged for more than 31 days without treatment and when the projected dose is in excess of limits specified above, prepare and submit the Special Report pursuant to Section 6.9.1.4 of the Technical Speci ica"ions.

SURVE1LLANCE RE UIREMENTS 2.2.1.3 Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with ODCM Section 6.5.

828o

RETS Manual Revision 9 Page 66 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.1 DOSE RATE CONTROLS 1.2.2.1 The dose rate at any time to areas at and beyond the SITE BOUNDARY (see Figure 3.1) due to radioactivity released in gaseous effluents from the site shall be limited to the following values:

a. The dose rate limit for noble gases shall be <500 mrem/yr to the total body and <3000 mrem/yr to the skin, and

b. The dose rate limit for I-131, I-133, H-3 and particulates with greater than eight day half-lives shall be <1500 mrem/yr to any organ.

APPLICABILITY: At all times.

ACTION: If the limits above are exceeded, appropriate corrective action shall be icmediately initiated to bring the release within limits.

Provide prompt notification to the NRC pursuant to Technical Specification 6.9.1.4.

SURVEILLANCE RE UIR12KNTS 2.2.2.1.1 The gross B/y and particulate activity of gaseous wastes released to the environment shall be monitored and recorded.

a~ For effluent streams having continuous monitoring capability, the activity shall be monitored and flow rate evaluated and recorded to enable release rates of gross radioactivity to be determined at least once per shift using instruments specified in Table 1.1-2.

b. For effluent streams without continuous monitoring capability, the activity shall be monitored and recorded and the release through these streams controlled to within the limits specified above.

2.2.2.1.2 Radioactive gaseous waste sampling and activity analysis shall be performed in accordance with the sampling and analysis program specified in Table 2.2-2. Dose rates shall be determined to be within the above limits using methods contained in ODCM Section

7. 3.

2.2.2.1.3 Samples of offgas system effluents shall be analyzed at least weekly to determine the identity and quantity of the principal radionuclides being released.

828o

RETS Manual Revision 9 Page 67 Table 2.2-2 (Page 1 of 2)

RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM

System Design

Capability Gaseous Minimum Type of Lover Limit of Release Sampling Analysis Activity Detection (LLD)

Type Frequency Frequency Analysis (pCi/ml)

A.Containment Prior to Prior to Piincipal lxlO Purge Each PURGE Each PURGE Gamma Grab Emitters3 Sample lxlo-6 B.l. Stack Grab Sample Monthly Principal lx10 Gamma Emitters3

2. Building Grab Sample Monthly H-3 lxlO Ventilation

a. Reactor/

Turbine

b. Turbine Exhaust

c. Radvaste C.A11 Release Continuous Charcoal I-131 lx10 Points Sampler Sample Listed in Weekly4 B. Above Continuous Particulate Principal lx10 Sampler Sample Ganma Weekly Emitters3 I-131 lxl0 Continuous Composite Gross Alpha lxl0 Sampler Particulate Sample Monthly Continuous Composite Sr-89, Sr-90 lx10 Sampler Particulate Sample Quarterly 828o

RETS Manual Revision 9 Page 68 Table 2.2-2 {Page 2 of 2)

RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION 1 The LLD is defined, for the purpose of this requirement, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95K probability with only a 5X probability of falsely, concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66sb E V 2.22E+06 Y exp (-X 4t)

Where:

LLD = the "a priori" lower limit of detection (microcurie per unit mass or volume) sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = the counting efficiency (counts per disintegration)

V = the sample size (units of mass or volume) 2.22E+06 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, X = the radioactive decay constant for the particular radionuclide (s 1),

and 4t = the elapsed time between midpoint of sample collection and time of counting (s).

Typical values of E, V, Y, and 4t should be used in the calculation It should be recognized that the iLD is defined as an a~riori (before the fact) limit representing the capability of a measurement system and not an a 2 When samples are taken more often than that shown, the minimum detectable concentrations can be correspondingly higher.

3 The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.

This list does not mean that only these nuclides are to be detected and reported. Other pe'aks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide.

4 Analysis shall also be performed if the radiation monitor alarm exceeds the setpoint value.

828o

RETS Manual Revision 9 Page 69 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2. 2. 2 GASEOUS EFFLUENTS 1/2.2.2.2 DOSE NOBLE GASES CONTROLS 1.2.2.2 The air dose to areas at and beyond the SITE BOUNDARY (see Figure 3.1) due to noble gases released in gaseous effluents per unit shall be limited to the following:

a. During any calendar quarter, to < 5 mrad for gamma radiation and

<10 mrad for beta radiation;

b. During any calendar year, to < 10 mrad for gamma radiation and

< 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION:

If the calculated air dose exceeds the limits specified above, prepare and submit a special report pursuant to Technical Specification 6.9.1.4.

SURVEILLANCE RE UIREMENTS 2.2.2.2 Cumulative quarterly and yearly dose contributions from gaseous releases shall be determined using methods contained in ODCM Section 7.3 at least once every 31 days.

828o

RETS Manual Revision 9 Page 70 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.3 DOSE I-131 I-133 TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYS CONTROLS 1.2.2.3 The dose to a MEMBER OF THE PUBLIC from radioiodines, radioactive materials in particulate form, and radionuclides other than than noble gases with half-lives greater than 8 days in gaseous effluent released per unit to areas at and beyond the SITE BOUNDARY (see Figure 3.1) shall be limited to the following:

a. To any organ during any calendar quarter to < 7.5 mrem;

b. To any organ during any calendar year to < 15 mrem.

APPLICABILITY: At all times.

ACTION:

If the calculated doses exceed the limits specified above, prepare and submit a special report pursuant to Technical Specification 6.9.1.4.

SURVEILLANCE RE UIREMENTS 2.2.2.3 Cumulative quarterly and yearly dose contributions from gaseous releases shall be determined using methods contained in ODCM Section 7.4 at least once every 31 days.

828o

RETS Manual t

Revision 9 Page 71 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.4 GASEOUS RADWASTE TREATMENT CONTROLS 1.2.2.4 During operation above 25K po~er, the discharge of the SJAE must be routed through the charcoal adsorbers.

The GASEOUS RADWASTE TREATMENT SYSTEM shall be operable and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluents from each unit, to areas at and beyond the site boundary, would exceed:

a. 0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to air from beta radiation, or

c. 0.3 mrem to any organ of a MEMBER OF +E PUBLIC.

APPLICABILITY: At all times.

ACTION:

With the gaseous waste being discharged for more than 7 days without treatment through the charcoal adsorbers and in excess of the above limits, prepare and submit a special report pursuant to Technical Specification 6.9.1.4.

SURVEILLANCE RE UIREMENTS 2.2.2.4.1 During operation above 25K power, the position of the charcoal bed bypass valve will be verified daily.

2.2.2.4.2 Doses due to gaseous releases to areas at and beyond the SITE BOUNDARY shall be projected in accordance with Section 7.5 at least once per 31 days.

828o

RETS Manual Revision 9 Page 72 1/2 CONTROLS AND SURVEILLANCE RE UIRKZENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.3 TOTAL DOSE CONTROLS 1.2.3 The dose or dose comnitment to a real individual from all uranium fuel cycle sources is limited to < 25 mrem to the total body or any organ (except the thyroid, which is limited to c 75 mrem) over a period of one calendar year.

APPLICABILITY: At all times.

AO110N:

With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of ODCM Control 1.2.1.2, 1.2.2.2, or 1.2.2.3, prepare and submit a Special Report to the Comnission pursuant to Technical Specification 6.9.1.4 and limit the subsequent releases such that the above limits. are not exceeded.

SURVEILLANCE RE UIREMENTS 2.2.3 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with ODCM Sections 6.3, 7.3, and 7.4 and the methods in ODCM Section 8.0.

828o

RETS Manual Revision 9 Page 73 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM CONTROLS 1.3. 1 The radiological environmental monitoring program shall be conducted as specified in Table 2.3-1.

APPLICABILITY: At all times.

ACTION:

a. With the radiological environmental monitoring program not being conducted as specified in Table 2.3-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability or malfunction of automatic sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be reported in the Annual Radiological Environmental Operating Report.

b. With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 2.3-3 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected quarter a report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a member of the public is less than the calendar year limits of ODCM Controls 1.2.1.2, 1.2.2.2, and 1.2.2.3.

When one or more of the radionuclides in Table 2.3-2 is detected in the sampling medium, this report shall be submitted if:

concentration(1) concentration(2)

+ . . . > 1.0 limit level(1) limit level(2)

When radionuclides other than those in Table 2.3-3 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of ODCM Controls 1.2.1.2, 1.2.2.2, and 1.2.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

828o

RETS Manual Revision 9 Page 74 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM CONTROLS

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 2.3-1, identify locations for obtaining replacement samples, if available, and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Pursuant to Control 1.3.l.b, identify the cause of the unavailability of samples and identify the new location(s), if available, for obtaining replacement samples in the next Annual Radiological Environmental Operating Report and also include a revised figure(s) and table(s) for the ODCM reflecting the new location(s).

The detection capabilities required by Table 2.3-2 are state-of-the art for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit repreaectiap the capability of a measurement system and not as a osteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs vill be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing circumstances will be identified and described in the Annual Radiological Environmental Operating Report.

SURVEILLANCE RE UIREMENTS 2.3.1.1 The radiological environmental monitoring samples shall be collected pursuant to Table 2.3-1 from the locations given in the tables and figures listed below and shall be analyzed pursuant to the requirements of Table 2.3-1 and the detection capabilities required by Table 2.3-2.

2.3.1.2 If measured levels of radioactivity in a environmental sampling medium are determined to exceed the reporting level values of Table 2.3-3 when averaged over any calendar quarter sampling period, a report shall be submitted to the Commission pursuant to Control 1.3.l.b.

828o

RETS Manual Revision 9 Page 75 Table 2.3-1 (1 of 3)

MINIMUM RE UIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency

~Sam le Locationsa Collection Fre uenc of Anal sis

1. AIRBORNE Radioiodine/ Minimum of 5 Continuous operation Radioiodine canis ter:

Particulates locations of sampler with Analyze at least once sample collection as per 7 days for I-131.

required by dust loading but at least Particulate sampler:

once per 7 days. .Analyze for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change.

Perform gamma isotopic analysis on each sample when gross beta activity is > 10 times the average of control samples. Perform gamma isotopic analysis on composite (by location) sample at least once per 92 days.

2. DIRECT At least 40 At least once per Gamma Dose. At least RADIATION locations with 92 days. once per 92 days.

> 2 dosimeters at each location.

a Sample locations are given in ODCM Section 9.0.

828o

RETS Manual Revision 9 Page 76 Table 2.3-1 {2 of 3)

MINIMUM RE UIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency

~sam le Locationsa Collection Fre uenc of Anal sis

3. WATERBORNE

a. Surface 2 locations Composite sample Gamma isotopic collected over a analysis of each period of < 31 composite sample.

ays b Tritium analysis of composite sample at least once per 92 days.

b.Drinking Minimum of 1 Composite sample Gross beta and gamma downs tream collected over a isotopic analysis of location, or all period of < 31 each composite sample.

~ster supplies days bsc Tritium analysis of within 10 miles composite sample at downstream which least once per 92 are taken'rom days.

the Tennessee River

c. Sediment Minimum of 1 At least once per Gamma isotopic location. 184 days analysis of each sample.

d.Groundd Sample locations are given in ODCM Section 9.0.

Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Composite samples shall be collected over a period of < 14 days for I-131 if drinking water is obtained within 3 miles downstream of the plant.

Ground water movement in the area has been determined to be from the plant site toward the Tennessee River. Since no drinking water wells exist between the plant and the river, ground water will not be monitored; 828o

RETS Manual Revision 9 Page 77 Table 2.3-1 (3 of 3)

MINIMUM RE UIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Path~ay Number of Samples and/or and Sample Sampling and Type and Frequency

~sam le Locationsa Collection Fre uenc of Anal sis

4. INGESTION

a. Milk 3 locations At least once per 15 I-131 analysis of days when animals each sample. Gamma are on pasture; isotopic analysis at at least once per least once per 31 days 31 days at other times.

b.'ish 2 samples One sample in Gamma isotopic season, or at least analysis on edible once per 184 days portions.

if not seasonal.

One sample of commercial and game species.

c. Food 2 locations At least once per Gamma isotopic Productse year at time of analysis on edible harvest portion.

Sample locations are given in ODCM Section 9.0.

Since water from the Tennessee River in the immediate area downstream is not used for irrigation purposes, the sampling of food products (primarily broad leaf vegetation) is not required unless milk sampling is not performed.

828o

RETS Manual Revision 9 Page 78 Table 2.3-2 (1 of 2)

HAXIMUM VALUES FOR THE LOMER LIMIT OF DETECTION (LLD)a>c FOR ENVIRONMENTAL SAMPLES Airborne Food Particulate Fish Products Sediment Mater or Gases (pCi/kg, Milk (pCi/kg, (pCi/kg,

~Anal sis ~(Ci/L) ~(ci/m3) wet) ~(Ci/L) wet) dr )

gross beta 4 0.01 N/A N/A N/A N/A H-3 2000 N/A N/A N/A N/A N/A Mn-54 15 N/A 130 N/A . N/A N/A Fe-59 30 N/A 260 N/A N/A N/A Co-58, 60 15 N/A 130 N/A N/A N/A Zn-65 30 N/A 260 N/A N/A N/A Zr-95 30 N/A N/A N/A N/A N/A Nb-95 N/A N/A N/A N/A N/A I-131 lb 0.07 N/A 60 N/A Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 80 180 Ba-140 60 N/A N/A 60 N/A N/A La-140 15 N/A N/A 15 N/A N/A 828o

RETS Manual Revision 9 Page 79 Table 2.3-2 (2 of 2)

MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION (LLD)a c FOR ENVIRONMENTAL SAMPLES TABLE NOTATION a The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95 percent probability with 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4.66 s E V 2.22 Y exp(-Xht)

Where'.

LLD = the "a priori" lower limit of detection as defined above, (as picocuries per unit mass or volume).

sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, (as counts per minute).

E = the counting efficiency, (as counts per disintegration).

V = the sample size (in units of mass or volume).

2.22 = the number of disintegrations per minute per picocurie.

Y = the fractional radiochemical yield, (when applicable).

= the radioactive decay constant for the particular radionuclide, seconds 1 and ht ~ for environmental samples is the elapsed time between sample collection, (or end of the sample collection period), and time of counting (for environmental samples, not plant effluent samples),

seconds.

Typical values of E, V, Y, and ht should be used in the calculation.

It should be recognized that the LLD is defined as an a~riori (before the fact) limit representing the capability of a measurement system and not as b LLD for analysis of drinking water and surface water samples shall be performed by gamma spectroscopy at approximately 15 pCi/L. If levels greater than 15 pCi/L are identified in surface water samples downstream from the plant, or in the event of an unanticipated release of I-131, drinking water samples will be analyzed at an LLD of 1.0 pCi/L for I-131.

Other peaks which are measurable and identifiable shall be identified and reported.

828o

RETS Manual Revision 9 Page 80 Table 2.3-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulate Anal sis Water

~(ci/L) or gases Fish Milk

~(Ci/L)

Food Products

( Ci/K wet)

H-3 2 x 104<>> N.A N.A N.A. N.A.

Mn-54 1 x 103 N.A. 3 x 104 N.A. N.A.

Fe-59 4 x 102 N.A. 1 x 104 N.A. N.A.

Co-58 1 x 103 N.A. 3 x 104 N.A. N.A.

Co-60 3 x 102 N.A. 1 x 104 N.A. N.A.

Zn-65 3 x 102 N.A. 2 % 104 N.A. N.A.

Zr-Nb-95 4 x 102 N.A. N.A. N.A. N.A.

I-131 0.9 N.A. 1 x 102 Cs-134 30 10 1 x 103 60 1 x 103 Cs-137 50 20 2 x 103 70 2 x 103 Ba-La-140 2 x 102 N.A. N.A. 3x 102 N.A.

(a) For drinking water samples. This is 40 CFR Part 141 value.

828o

0 RETS Manual t

Revision 9 Page 81 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.2 LAND USE CENSUS CONTROLS 1.3.2 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest gardenl of greater than 500 square feet producing vegetables in each of the 16 meteorological sectors within a distance of 5 miles. (For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of all milk animals and gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.)

1 Broad leaf vegetation sampling may be performed at the SITE BOUNDARY in the direction sector with the highest D/Q in lieu of the garden census.

APPLICABILITY: At all times.

AC1 ION:

With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the maximum value currently being calculated in Section 7.5, identify the new location(s) in the next Annual Radiological Environmental Operating Report.

With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with ODCM Control 1.3.1, add the new location(s) to the radiological environmental monitoring program within 30 days if the owner consents. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s)

(via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Identify the new location(s) in the next Annual Radiological Environmental Operating Report and provide a revised figure(s) and table(s) reflecting the new location(s).

SURVEILLANCE RE UIREMENTS (see next page) 828o

RETS Manual Revision 9 Page 82 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.2 LAND USE CENSUS SURVEILLANCE RE UIREMENTS 2.3.2 The land use census shall be conducted at least once per calendar year between the dates of April 1 and October 1 using the following techniques:

1. Within a 2-mile radius from the plant or within the 15 mrem per year isodose line, whichever is larger, enumeration by a door-to-door or equivalent counting technique.

2. Within a 5-mile radius from the plant, enumeration by using appropriate techniques such as door-toMoor survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other reliable sources.

828o

RETS Manual Revision 9 Page 83 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 1.3.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.

APPLICABILITY: At all times.

ACTION:

With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

SURVEILLANCE RE UIRI'RENTS 2.3.3 A summary of the results obtained as part of the above required Interlaboratory Comparison Program (or participants in the Environmental Protection Agency (EPA) cross check program shall provide the EPA program code designation for the unit) shall be included in the Annual Radiological Environmental Operating Report.

828o

RETS Manual Revision 9 Page 84 BASES FOR SECTIONS 1.0 AND 2.0 CONTROLS SURVEILLANCE REQUIREMENTS NOTE The BASES contained in succeeding pages summarize the reasons for the Controls in Sections 1.0 and 2.0, but are not part of these Controls.

828o

RETS Manual Revision 9 Page 85 1/2. 1 EFFLUENT MONITORING INSTRUMENTATION 1/2.1 ~ 1 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with guidance provided in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits or 10 CFR Part 20 Appendix B, Table II, Column 2. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments will be calculated in accordance with Section 7.2.1 to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.

The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

The action required when the number of OPERABLE channels is less than the Minimum Channels Operable requirement is specified in the notes for Table 1.1-2. Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

1/2. 2 RADIOACTIVE EFFLUENTS 1/2.2.1.1 CONCENTRATION This requirement is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section II.A limits of Appendix I to 10 CFR Part 50 to the population. The concentration limit for noble gases is based upon the assumption that Xe-135 is the 828o

RETS Manual Revision 9 Page 86 BASES 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1.1 CONCENTRATION (continued) controlling radioisotope and its Maximum Permissible Concentration in air (submersion) was converted to an equivalent concentration in water using the methods described in International Comnission of Radiological Protection (ICRP) Publication 2.

1/2.2.1.2 DOSE This requirement is provided to implement the dose requirements of Section II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50. The requirement implements the guides set forth in Section II.A of Appendix I.

This action provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonable achievable". Also, for fresh water sites with drinking water supplies which can potentially be affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in Section 6.0 implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown. by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in Section 6.0 for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Implementing Appendix I," October 1977 and Regulatory Guide 1.1.13, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I" April 1977.

NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.

1/2.2.1.3 LI UID WASTE TREATMENT This section requires that the appropriate portions of the liquid radwaste treatment system be used when specified. This provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This requirement implements the requirements of 10 CFR Part 50.36a, 828o

0 RETS Manual Revision 9 Page 87 BASES 1/2. 2 RADIOACTIVE EFFLUENTS 1/2.2.1.3 LI UID WASTE TREATMENT (continued)

General Design Criterion 60 of Appends A to 10 CFR Part 50 and design objective Section II.D of Appendix I to 10 CFR 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Section II.A of Appendix I, 10 CFR 50, for liquid effluents.

This section also requires submittal of a special report if the limiting values are exceeded and unexpected failures of non-redundant radwaste processing equipment halt vaste treatment.

1/2.2.2.1 DOSE RATE This requirement is provided to ensure that the dose rate at anytime at the SITE BOUNDARY from gaseous effluents from all units on the site vill be vithin the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents vill not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either vithin or outside the SITE B'OUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For MEMBERS OF THE PUBLIC vho may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.

The specified release rate limits restrict, at all times, the corresponding gamna and beta dose rates to an individual at or beyond the SITE BOUNDARY to ( 500 mrem/year to the total body or

< 3000 mrem/year to the skin. These release rates also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to ( 1500 mrem/year for the nearest cow to the plant.

The action for this requirement requires that appropriate corrective action(s) be taken to reduce gaseous effluent releases if the limits are exceeded.

1/2.3.2.2 DOSE - NOBLE GASES This requirement is provided to implement the requirements of Section II.C, III.A, and IV of Appendix I, 10 CFR Part 50. The limits are the guides set forth in Section II.C of Appendix I.

828o

RETS Manual Revision 9 Page 88 BASES 1/2. 2 RADIOACTIVE EFFLUENTS 1/2.2.2.3 DOSE I-131 I-133 TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM This requirement is provided to implement the requirements of Section II.C, III.A, and IV of Appendix I, 10 CFR Part 50. The limits are the guides set forth in Section II.C of Appendix I.

The action to be taken for exceeding these limits provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as reasonably achievable." Section 7.0 calculational methods implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. Section 7.0 calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodologies provided in NUREG/CR-1004, "A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides," October 1979 and Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for iodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man in the UNRESTRICTED AREA. The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

If these limits are exceeded, this section requires that a special report be prepared and submitted to explain violations of the limiting doses contained in the section above.

828o

RETS Manual Revision 9 Page 89 BASES 1/2. 2 RADIOACTIVE EFFLUENTS 1/2. 2. 2. 4 GASEOUS RADWASTE TREATMENT This requires that the offgas charcoal adsorber beds be used when specified to treat gaseous effluents prior their release to the environment. This provides reasonable assurance that the release of radioactive materials in gaseous effluents will be kept "as low as is reasonable achievable". This requi.rement implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

This action requires that a special report be prepared and submitted to explain reasons for any failure to comply with the above requirements.

1/2.2.3 TOTAL DOSE This requirement is provided to meet the dose limi.tations of 40 CFR 190. This requirement requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for the calendar year to be wi.thin 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities within a radius of five miles must be considered.

1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM The radiological environmental monitoring program required by this section provides measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring 828o

RETS Manual Revision 9 Page 90 BASES 1/2. 3 RADIOLOGICAL ENVIRONMENTAL MONITORING

'1/2.3.1 MONITORING PROGRAM (continued) program by verifying that the measurable concentration of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.

1/2.3.2 LAND USE CENSUS This requirement is provided to ensure that changes in the use of UNRESTRICTED AREAS are identified and that modifications to the monitoring program are made if required by the results of this census. The best survey information from the door-to-door, mail, telephone, aerial or consulting with local authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than SOO square feet provides assurance that significant exposure pathways via the leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetation assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20K of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/square meter.

1/2.3.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

828o

RETS Manual Revision 9 Page 91 SECTION 3-0 DEFINITIONS 828o

RETS Manual Revision 9 Page 92 3.0 DEFINITIONS The defined terms in this section appear in capitalized type in the text and are applicable throughout these controls.

3.0.A. CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.

The CHANNEL CALIBRATION shall encompass the entire channel including alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated. Non-calibratable components shall be excluded from this requirement, but will be included in CHANNEL FUNCTIONAL TEST and SOURCE CHECK.

3.0.B. CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b. Bistable channel - the injection of a simulated signal into the sensor to verify OPERABII.ITY including alarm and/or trip function.

3.AC. GASEOUS WASTE TREATMENT SYSTEM The GASEOUS WASTE TREATMENT SYSTEM consists of the charcoal adsorber vessels installed in the discharge of the steam jet air ejector to provide delay to a unit's offgas activity prior to release.

3.0.D. DOSE E UIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (pCi/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-13S actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites."

3.0.E. MEMBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant.

828o

RETS Manual Revision 9 Page 93 This category shall include non~mployees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions. This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter UNRESTRICTED AREAS.

3.0.F. OPERABLE - OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).

3.0.G. PURGE PURGING PURGE or PURGING is the controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

3.0.H. RATED POWER RATED POWER refers to operation at a reactor power of 3,293 %Jt; this is also termed 100 percent power and is the maximum power level authorised by the operating license. Rated steam flow, rated coolant flow, rated neutron flux, and rated nuclear system pressure refer to the values of these parameters when the reactor is at rated power.

Design power, the power to which the safety analysis applies, corresponds to 3,440 MWt.

3.0.I. SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by TVA (see Figure 3.1).

3.0.J. SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source or multiple of sources.

82So

RETS Manual Revision 9 Page 94 DEFINITIONS 3.0.K. UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area, at or beyond the S1TE BOUNDARY to vhich access is not controlled by the licensee for purposed of protection of individuals from exposure to radiation and radioactive materials or any area within the SITE BOUNDARY used for residential quarters or industrial, conmercial, institutional, and/or recreational purposes (see Figure 3.1).

3.0.L. VENTING VENTING is the controlled process of discharging air or gas from primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required. Vent, used in system names, does not imply a VENTING process.

828o

RETS Manual Revision 9 Page 95 Table 3.1 FRE UENCY NOTATION Notation ~Fre uenc At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

At least once per 24 hours.

At least once per 7 days.

At least once per 31 days.

At least once per 92 days.

SA At least once per 184 days.

At least once per 18 months.

S/U Prior to each reactor startup.

N.A. Not Applicable Completed prior to each release 828o

RETS Manual Revision 9 Page 96 Figure 3-1 LAND SITE BOUNDARY WOW

~0 BROWNS FERRY NuCLEAR PLANT W Svl P~

+~

S r

p>~

Sw'S&

Land Site Boundary (for gaseous effluents)

~0 t\ 0 ~ ~ 0 Ot t\ ~ Unrestricted Area Boundary (for liquid effluents)

B28o

RETS Manual Revision 9 Page 97 SECTION 4.0 (NOT USED)

S2ao

RETS Manual Revision 9 Page 98 SECTION 5.0 ADMINISTRATIVE CONTROLS 828o

RETS Manual Revision 9 Page 99 5.0 ADMINISTRATIVE CONTROLS F 1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The report shall also include the results of land use censuses required by Control 1.3.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problems and a planned course of action to alleviate the problem.

The Annual Radiological Environmental Operating Report shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplemen ary report.

The report shall also include the following: a summary description of the radiological environmental monitoring program', a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program required by Control 1.3.3.

5.2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Semiannual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste shipped from the plant as delineated in Regulatory Guide 1.21,

'Measuring, Evaluating, and Reporting Radioactivity in Solid Mastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Mater-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The report shall include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, Revision 1, with data sunmarized on a quarterly bases following the format of Appendix B thereof. Calculated offsite dose to members of the public resulting from the release of liquid and gaseous effluents and their subsequent dispersion in the river and atmosphere shall be reported as recommended in Regulatory Guide 1.21, Revision 1.

S28o

RETS Manual Revision 9 Page 100 5.0 ADMINISTRATIVE CONTROLS 5.2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (continued)

The Semiannual Radioactive Effluent Release Report shall include the information regarding solid waste as specified in the Process Control Pl ogl am+

5.3 OFFSITE DOSE CALCULATION MANUAL CHANGES As required by BFN TS 6.12, changes to the ODCM:

1. Shall be documented and records of reviews performed shall be retained as required by BFÃ TS 6.10.1. This documentation shall contain:

a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and

b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

2. Shall become effective after review and acceptance by the PORC.

3. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month/year) the change was implemented.

5.4 SPECIAL REPORTS Special Reports shall be submitted to the NRC in accordance with Section 50.73 to 10 CFR 50.

828o

RETS Manual Revision 9 Page 101 SECTION 6.0 LI UID EFFLUENTS 828o

RETS Manual Revision 9 Page 102 6.0 - LI UID EFFLUENTS RELEASE POINTS There is one liquid release point into the discharge canal by one of three possible modes:

~

Radwaste t 4

open 3 pumps 0 200,000 helper 3

+ closed 50,000 gpm gpm/pump-pumps 9 180,000 gpm/pump 4

> Discharge Conduit 828o

t RETS Manual Revision 9 Page 103 6.1 LI UID RELEASES 6.1.1 Pre-release Anal sis/MPC - Sum of the Ratios Prior to release, a grab sample will be analyzed to determine the concentration (Ci) of each gamma emitting radionuclide i in the radwaste tank. The following equation is used to calculate MPC fractions (Mi).

Ci Mi ~

MPCi where:

Mi = MPC fraction of radionuclide i.

C~ ~ concentration of radionuclide i in the radwaste tank, pCi/ml.

MPCi = MPC of radionuclide i as specified in Control 1.2.1.1, pCi/ml.

The sum of the ratios (R) will be calculated by the following relationship:

R= g Mi where:

R ~ the sum of the ratios.

i Mi ~ MPC fraction from equation 6.1.

6.1.2 Release Flow Rate Calculations The sum of the ratios at the diffuser pipes must be c 1 due to the releases from the above source. The following relationship will assure this criterion is met:

(R-1) ( F where:

f ~ the effluent flow rate (gallons/minute) before dilution.

R ~ the sum of the ratios as determined by Equation 6.2.

F ~ minimum dilution flow rate for prerelease analysis.

The allowable release rate is calculated before each release and the release rate is continuously monitored during the release so that the MPC limit is not exceeded.

828o

RETS Manual Revision 9 Page 104 6.1.3 Post-release Anal sis A post-release analysis vill be done using actual release data to ensure that the limits specified in Control 1.2.1.1 vere not exceeded.

A composite list of concentrations (Ci) by isotope, vill be used vith actual liquid radvaste (f) and dilution (F) flow rates (or volumes) during the release. The data vill be substituted into Equations 6.1, 6.2 and 6.3 to demonstrate compliance with the limits in Control 1.2.1.1. This data and setpoints vill be recorded in auditable records by plant personnel.

828o

RETS Manual Revision 9 Page 105 Alarm/trip setpoxnts for each liquid monitor will be established and set such that Equation 6.3 is satisfied. The locations and identification numbers for each liquid effluent radiation detector are shown in Figures 6.1 and 6.2. This section of the ODCM describes the methodology that will be used to determine allowable values. The allowable values are then used to determine the physical settings on the monitors. The physical settings are calculated in the applicable Scaling and Setpoint Documents 6.2.1 Radwaste Dischar e Monitor The allowable value for the radwaste discharge monitor (RM-90-130), shown in Figures 6.1 and 6.2, vill be established using the methodology below.

The alarm/trip allowable value will be set such that Equation 6.3 is satisfied. The trip allowable value for the monitor, which will automatically isolate the release, is set at less than or equal to the limit in Control 1.2.1.1. The alarm allowable value is set at 50K of the trip allowable value.

The maximum activity concentration of liauid radwaste that can be discharged into a Condenser Cooling Viater (CCV) condui. can be calculated as:

(MPCimi ) F Ac) f 1

where A "- maximum batch activity concentration, pCi/ml MPCi ~ Maximum Permissible Concentration, from 10 CFR 20 Appendix B for nuclide i, pCi/ml.

~ weighting factor for nuclide i, defined as the fraction of the total concentration which is attributed to nuclide i.

~ CCW dilution water flow rate, gpm.

= maximum discharge flow rate, gpm 1 The maximum activity concentration is based on a selected isotopic mixture so that an allowable value can be calculated. The selected isotopic mixture will be documented in TI 45. If the actual batch MPC is less restrictive than the MPC for the selected isotopic mixture, then the actual activity concentration may be higher than the calculated maximum activity concentration.

828o

RETS Manual Revision 9 Page 106 The monitor isolation allowable value, in cps, for releases to the CCW discharge conduit is calculated using the following equation'.

A Nooitor laolatiou Allocable Value = + B CF where:

A ~ maximum batch activity concentration as calculated above, pCi/ml CF ~ calibration factor for the monitor, pCi/ml/cps B ~ monitor background, cps The calculation of these allowable values are documented further in TI 45, including the numerical values for each of the parameters described above.

Releases can be simultaneously discharged to multiple CCW discharge conduits. If releases are routed to more than one CCW discharge conduit, the allowable activity concentration and hence the corresponding allowable value may be increased based on an increase in dilution flow.

6.2.2 Raw Coolin Water and Residual Heat Removal Service Water Monitors The allowable value for the Raw Cooling Water (RCW) monitors and the Residual Heat Removal Service Water (RHRSW) monitors (RN-90-132 and RM-90-133,134 respectively), shown in Figure 6.1, will be established using the methodology below. The alarm/trip allowable values will be set such that Equation 6.3 is satisfied. The allowable values for these monitors, which will alarm in the control room, are based on the 10 CFR 20 Appendix B concentration limits. These allowable values are also based on a selected isotopic mixture.

The monitor alarm allowable values, in cpm, for the RCW and RHRSW effluent monitors are calculated using the following equation:

MPCi

• WFi Monitor Allowable Values + B 1 Ei where MPCi = Maximum Permissible Concentration, from 10 CFR 20 Appendix B for nuclide i, pCi/ml.

WFi = weighting factor for nuclide i, defined as the fraction of the total concentration which is attributed to nuclide i."

Ei efficiency of the monitor for nuclide i, pCi/ml/cpm.

B = monitor background, cpm The calculation of these allowable values are documented further in TI 45, including the numerical values for each of the parameters described above.

828o

RETS Manual Revision 9 Page 107 6 ~ 3 CUMULATIVE LI UID EFFLUENT DOSE CALCULATION 6.3.1 Monthl Anal sis Principal radionuclides will be used to conservatively estimate the monthly contribution to the cumulative dose. If the projected dose calculated by this monthly method exceeds the monthly fraction of the annual limits in Control 1.2.1.2, then the methodology in Section 6.6 will be implemented.

The 20 nuclides listed below, based on operational source terms, contribute more than 95 percent of the total estimated dose to the total body and the most critical organ for both the water and fish ingestion pathways. The organs considered for both water ingestion and fish ingestion are the gastrointestinal tract (GIT), bone, thyroid and liver.

H-3 Fe-59 Sr-90 I-131 Na-24 Co-58 Zr/Nb-95 I-133 Cr-51 Co-60 Mo/Tc-99m C5-134 Mn-54 Zn-65 Ag-110m Cs-136 Fe-55 Sr-89 Sb-124 C5-137 A conservative calculation of the monthly dose will be done according to tne following procedure. First, the monthly operating repor. contain'ng the release data will be obtained and the activities reported (if any) for each of the above 20 radionuclides will be noted. This information will then be used in the following calculations.

828o

RETS Manual Revision 9 Page 108 6.3.1.1 Water In estion The dose to an individual from ingestion of water is described by the following equation.

20 Djk = ~~ p i=1 (DFL)ijk ik where:

Djk = dose for the jth organ and the kth age group from the 20 radionuclides, mrem.

= the organ of interest (bone, GIT, thyroid, liver or total body).

k = the age group being considered, child or adult.

1012 conversion factor, pCi/Ci.

0.95 = conservative correction factor, considering only 20 radionuclides.

DFLijk ~ ingestion dose comnitment factor for the ith radionuclide for the jth organ for the kth age group, mrem/pCi (Table 6.4)

Iik ~ monthly activity ingested of the ith radionuclide by the kth age group, Ci.

The activity ingested due to drinking water, Iik, is described by:

103 Ai Uwa (1/12) where:

103 = conversion factor, ml/L.

Ai = activity released of ith radionuclide during the month, Ci.

U wa = maximum individual water consumption rate corresponding to the kth age group (Table 6.3), L/yr.

1/12 = conversion factor, yr/month.

F = average river flow rate for the month (cubic feet per second) d = fraction of river flow available for dilution (0.30) 7.34E+10 = conversion from cubic feet per second to milliliters per month Inserting this for Iik in equation 6.4, the dose equation for water ingestion then becomes:

20 3.98E+03 Uwa DFLijk Ai (6.6) i=1 828o

RETS Manual Revision 9 Page 109 The dose to an individual from the consumption of fish is described by Equation 6.4.. In this case, the activity ingested of the ith radionuclide due to eating fish (Iik) is described by 103 Ai Bi Ufa (1/12)

I k ~ +

(6.7) where:

103 ~ conversion factor, g/kg.

AX = activity released of the ith radionuclide during the month, Ci B = bioaccumulation factor of ith radionuclide, pCi/g per pCi/ml.

(Table 6.5)

Ufa = amount of fish eaten yearly by the kth age group (Table 6.3),

kg/yr.

1/12 = conversion factor, yr/month.

F ~ average river flow rate for the month, cubic feet per second.

d = fraction of river flow available for dilution, 0.30.

7.34E+10 = conversion from cubic feet per second to milliliters per month.

Inserting this for Iik in equation 6.4, the dose equation for fish ingestion then becomes:

3.98E+03 Dk-3 Ai Bi Ufa DFLijk (6.8) i=1 828o

RETS Manual t

Revision 9 Page 111 The recreation dose equation then becomes:

D r=~ (29.8 Al

=

1

+ 1690 A2 + 539 A3 + 812 A4) where:

Al, A2, A3, A4, = the activities of Co-58, Co-60, Cs-134, and Cs-137, respectively, pCi.

6.3.1.4 Monthl Summa To obtain the total monthly dose to the total body, sum the total body dose from water ingestion, the total body dose from fish ingestion, and the recreation dose. This value will be compared to the limit for total body dose. To obtain the total monthly dose to the maximum organ, sum the maximum organ dose from water ingestion, the maximum organ dose from fish ingestion, and the recreation dose. This value will be compared to the limit for maximum organ dose. Calendar quarter and calendar year doses are first estimated by summing the doses calculated for each month in that year. However, if the annual doses determined in this manner exceed or approach the specification limits, doses calculated for previous quarters wi'th the methodology of ODCM Section 6.6 will be used instead of those quarterly doses estimated by summing monthly results. An annual check will be made to ensure that the monthly dose estimates account for at least 95 percent of the dose calculated by the method described in ODCM Section 6.6. If less than 95 percent of the dose has been estimated, either a new list of principal isotopes wi11 be prepared or. a new correction factor will be used. The latter option will not be used if less than 90 percent of the total dose is predicted.

828o

RETS Manual Revision 9 Page 112 6.4 LI UID RADWASTE TREATMENT SYSTEM The liquid radwaste treatment system shall be maintained and operated to keep releases ~QUA. A flow diagram for the LRTS is given in Figure 6.2.

828o

t RETS Manual Revision 9 Page 113 6.5 DOSE PROJECTIONS Dose projections will be done by averaging the calculated dose for the most recent month and the calculated dose for the previous month and assigning that average dose as the projection for the current month.

828o

RETS Manual Revision 9 Page 114 6.6 DOSE CALCULATIONS FOR REPORTING PURPOSES A complete dose analysis utilizing the total estimated liquid releases for each calendar quarter will be performed and reported as required in ODCM Administrative Control 5.2. Methodology for this analysis is that which is described in this section using the quarterly release values reported by the plant personnel. The; releases are assumed, for this calculation, to be continuous over the 90 day period.

The average dilution factor, D, used for these calculations is:

(for receptors upstream (6.13a)

RF *'0.30 of Wheeler Dam)

D- (for receptors downstream (6. 13b) of Wheeler Dam) where:

RF = the average actual riverflow for the location at which the dose is being determined, cfs.

0.30 = the fraction of the riverflow available for dilution in the near field, dimensionless.

6.6.1 Water In estion Water ingestion doses are calculated for each Public Water Supply (PWS) identified within a 50 mile radius downstream of BFK (Table 6.1). Water ingestion doses are calculated for the total body and each internal organ as described below:

Dorg = 10 9.8E-09 AWit Qi D exp(-8.64E+04 Xi (6.14) where 10 = conversion factor, pCi/Ci.

9.8E-09 = conversion factor, cfs per ml/hour.

AWit = Dose factor for water ingestion for nuclide i, age group t, mrem/hour per mCi/ml, as calculated in Section 6.7.1.

Qi = Quantity of nuclide i released during the quarter, Curies.

D = dilution factor, as described above, cfs 1.

Xi = radiological decay constant of nuclide i, seconds (Table 6.3).

= decay time for water ingestion, equal to the travel time from the plant to the water supply plus one-half day (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) to account for the time of processing at the water supply (per Regulatory Guide 1.109), days.

8.64E+04 = conversion factor, seconds per day.

828o

RETS Manual Revision 9 Page 115 Fash xn g estion doses are calculated for each identified reach within a 50 mile radius downstream of BFN (Table 6 1). Individual fish ingestion

~

doses are calculated for the total body and each internal organ as described below:

Dorg = 10 9.8E-09 0.25 AFit Qi D exp(-8.64E+04 Xi td) (6.15) where 10 ~ conversion factor, pCi/Ci.

9.8E-09 ~ conversion factor, cfs per ml/hour.

0.25 = fraction of the yearly fish consumption eaten in one quarter, dimensionless.

AFit. = Dose factor for fish ingestion for nuclide i, age group t, mrem/hour per pCi/ml, as calculated in ODCM Section 6.7.2.

= Quantity of nuclide i released during the quarter, Curies.

= dilution factor, as described above, "cfs

= radiological decay constant of nuclide i, seconds (Table 6.3).

= decay time for fish ingestion, equal to the travel time from the plant to the center of the reach plus one day to account for transit through the food chain and food preparation time (per Reguiatory Guide 1.109), days.

8.64E+04 = conversion factor, seconds per day.

6.6.3 Shoreline Recreation Recreation doses are calculated for each identified reach within a 50 mile radius downstream of BFN (Table 6.1). It is assumed that the maximum exposed individual spends 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year on the shoreline at a location immediately downstream from the diffusers. Individual recreation shoreline doses are calculated for the total body and skin as described below:

Dorg ~ 106 9.8E&9 rf ARit Qi D exp(&.64E+04 Xi where 10 = conversion factor, pCi/Ci.

9.8E-09 ~ conversion factor, cfs per ml/hour.

rf ~ recreation factor, used to account for the fact that the same amount of time will not be spent at a recreation site during each quarter. Recreation factors used are:

1st quarter - 0.1 2nd quarter 0.3 3rd quarter 0.4 4th quarter - 0.2.

828o

RETS Manual Revision 9 Page 116 ARit~ = Dose factor for shoreline recreation for nuclide i, age group t, mremlhour per pCilml, as calculated in ODCM Section 6.7.3.

Qi = Quantity of nuclide i released during the quarter, Curies.

= dilution factor, as described above, cfs l.

D Xi = radiological decay constant of nuclide i, seconds (Table 6.3).

d = decay time for recreation, equal to the travel time from the plant to the center of the reach, days.

8.64E+04 = conversion factor, seconds per day.

6.6.4 Total Maximum Individual Dose The total maximum individual total body dose is obtained by suaming the following for each age group: the highest total body water ingestion dose from among all the public water supplies; the highest total body ish ingestion dose from among all the reaches; and the total body maximum shoreline recreation dose. The total auucimum individual organ dose is obtained by suaming the following for each organ and each age group: that organ's highest water ingestion dose from among all the public water supplies; that organ's highest fish ingestion dose from among all the reaches and the total body maximum shoreline recreation dose. The total maximum individual skin dose is that skin dose calculated for the maximum shoreline dose.

828o

RETS Manual Revision 9 Page 117 6.6.5 Population Doses For determining population doses to the 50-mile population around the plant, an average dose is calculated for each age group and each pathway and then multiplied by the population.

For water ingestion, the general equation used for calculating the population doses, POPWTR, in man-rem for a given PWS is:

3 4 POPWTRt = 10 3 $ POPm $ POPa ATMWa TWDOSam (6.17) m=1 a=1 where:

POP WTRt = water ingestion population dose to organ t, man-rem.

POP <<- fraction of population in each age group a (from NUREG CR-1004, Table 3.39).

= 0.665 for adult

= 0.168 for child

= 0.015 for infant

= 0.153 for teen POPm -" population at PWS m. The 3 PWSs and their populations are listed in Table 6.1.

ATMWa ~ ratio of average to maximum water ingestion rates for each age group a. Maximum water ingestion rates are given in Table 6.3. Average water ingestion rates are obtained from R.G.

1.109 Table E-4). The ratios are:

= 0.5069 for adult

= 0.5098 for child

~ 0.7879 for infant

= 0.5098 for teen TWDosamt ~ total individual water ingestion dose to organ t at PWS m, to the age group a, as described in Section 6.6.1, mrem.

10 3 conversion factor for rem/mrem.

For population doses resulting from fish ingestion the calculation assumes that all fish caught within a 50-mile radius downstream of BFN are consumed by local population. An additional 7-days decay is added due to distribution time of sport fish. The general equation for calculating population doses, POPF, in man-rem from fish ingestion of all fish caught within a 50-mile radius downstream is:

3 3 45 3 ~ 6 HVST APRz POPFt 10 3 10 3 E E POPa TFDOSaz t r=l a~1 a a 828o

RETS Manual Revision 9 Page 118 where:

POPFt ~ total fish ingestion population dose to organ t, man-rem.

HVST = fish harvest for the Tennessee River, 8.32 lbs/acre/year.

APRr ~ size of reach r, acres (Table 6.1).

TFDOSart ~ total fish ingestion dose to organ t for reach r, for the age group a, as described in Section 6.6.2, mrem. Calculated with td in that equation equal to travel time plus 8 days.

POPa ~ fraction of population in each age group a, as given above.

FISHa ~ amount of fish ingested by each age group a, kg/year per person. The average fish ingestion rates (R.G. 1.109 Table E-4) are:

Adult ~ 6.9 Child ~ 2.2 Teen ~ 5.2 453.6 ~ conversion factor, g/lb.

10 3 conversion factor, rem/mrem.

103 conversion factor, g/kg.

For shoreline recreation, the general equation used for calculating the population doses, POPR, in man-rem is:

REQFRA POPRt 7. (6.19) where:

POPRt = total recreation population dose for all reaches to organ t, man-rem.

= fraction of yearly recreation which occurs in that quarter, as given in Section 6.6.3, year per quarter.

SHVISr ~ shoreline visits per year at each reach r, (Table 6.1).

HRSVISr = length of shoreline recreation visit at reach r, 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

103 conversion factor, mrem/rem.

TSHDOSrt = total shoreline dose rate for organ t, in reach r, mrem-quarter/h per quazter.

Qi exp( Xitr) Kc M DFGit 1012 24 103 Dr 2.22Ell Xi where:

Qi total activity released during the quarter, Ci.

'Ai decay constant for nuclide i, day 1.

tz. travel time from the plant to reach r, days.

Kc transfer coefficient from water to sediment, L/kg-hr, (Table 6.3).

M ~ mass density of sediment, kg/m2, (Table 6.3).

DFGit = dose conversion factor for standing on contaminated ground i for nuclide and organ t (total body and skin), mrem/hr per pCi/m .

1012 conversion factor, pCi/Ci.

24 = conversion factor, hr/day.

103 = conversion factor, ml/L.

Dr dilution factor for reach r, cfs l. Calculated as described in Equation 6.13.

2.22E11 ~ conversion factor, ml/quarter per cfs.

828o

RETS Manual Revision 9 Page 119 0 6.7 LI UID DOSE FACTOR E UATIONS 6.7.1 Water In estion Dose Factors DFLiat Uwa 10 10 where:

DFLiat ~ ingestion dose conversion factor for nuclide i, age group a, organ t, mrem/pCi, (Table 6.4).

Uw ~ water consumption rate for age group a, L/year, (Table 6.3).

10~ conversion factor, pCilpCi.

103 conversion factor, ml/L.

8760 = conversion factor, hours per year.

6.7.2 Fish In estion Dose Factors DFLiat Ufa Bi 10 10 AFit where:

DFLiat = inges ion dose conversion factor for nuclide i, age group a, organ t, mrem/pCi, (Table 6.4).

Ufa = fish consumption rate for age group a, kg/year, (Table 6.3).

Bi = bioaccumulation factor for nuclide i, pCi/kg per pCi/L, (Table 6.5).

106 conversion factor, pCi/pCi.

103 conversion factor, pl/L.

8760 ~ conversion factor, hours per year.

6.7.3 Shoreline Recreation Dose Factors DFGit Kc N W 103 106 U ARit ~ [1-exp(-) i tb)]

i where:

DFGit ~ dose conversion factor for standing on contaminated ground for i

nuclide and organ t (total body and skin), mrem/hr per pCi/m2, (Table 6.6).

Kc ~ transfer coefficient from water to shoreline sediment, L/kg-hr, (Table 6.3).

M ~ mass density of sediment, kg/m , (Table 6.3).

W ~ shoreline width factor, dimensionless, (Table 6.3).

103 conversion factor, ml/L.

106 conversion factor, pCilpCi .

3600 = conversion factor, seconds/hour.

Xi decay constant for nuclide i, seconds , (Table 6.2).

tb = time shoreline is exposed to the concentration in the water, seconds, (Table 6.3).

U = usage factor, 500 bours/year.

8760 ~ conversion factor, hours/year.

828o

RETS Manual Revision 9 Page 120 Table 6.1 RECEPTORS FOR LI UID DOSE CALCULATIONS Tennessee River Reaches Within 50 Mile Radius Downstream of BFN Beginning Ending Size Recreation Name TRN Wheeler Lake 294.0 275.0 26076 1%408%600 below BFN Wilson Lake 275.0 260.0 15930 3%816%800 Pickwick Lake 260.0 230.0 15048 705,500 Public Water Su lies Within 50 Mile Radius Downstream of BFN Name TRM ~Po elation Muscle Shoals, AL 259. 6 10,740 Sheffield, AL 254. 3 13%065 Cherokee, AL 239. 2 3%400

• TRM = Tennessee River Mile 828o

RETS Manual Revxsxon 9 Page 121 Table 6.2 (1 of 3)

RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life 'A Biv Fmi Fmi Ffi (minutes) (1/s) ,(cow) (goat) (beef)

H-3 6.46E+06 1.79E-09 4.80E+00 1.00E-02 1.70E-01 1.20E-02 C-14 3.01K+09 3.84E-12 5.50E+00 1.20E-02 1.00E-01 3.10E-02 Na-24 9.DOE+02 1.28E-05 5.20E-02 4.00E-02 4.00E-02 3.00E-02 P-32 2.06E+04 5.61E-07 1.10E+00 2.50E-02 2.50E-01 4.60E-D2 Cr-51 3.99E+04 2.90E-07 2.50E-04 2.20E-03 2.20E-03 2.40E-03 Mn-54 4.50K+05 2.57E-DS 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Mn-56 1.55K+02 7.45E<<05 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Fe-55 1.42K+06 8.13E-09 6.6DE-D4 1.20E-03 1.30E-04 1.20E-02 Fe-59 6.43K+04 1.80E-07 6.60E04 1.20E-03 1.30E-04 l. 20EW2 Co-57 3.90K+05 2.96E-08 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-S8 1. 02E+DS 1.13E-07 9.40E-03 1.00E-D3 1.00E-03 1.30E-02 Co-60 2.77E+06 4.17K-09 9.40E-03 1 DDE-03 1.00E-03 1.30E-02 Ni-63 5.27E+07 2.19E-10 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Ni-65 1.51E+02 7.65E-05 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Cu-64 7.62E+02 1.52E-05 1.20E-01 1.40E-02 1.30E-02 9.70E-04 Zn-65 3.52K+05 3.28E-08 4.00E-Ol 3.90E-02 3.90E-02 3.00E-02 Zn-69m 8.26E+02 1.40E-OS 4.00E-01 3.90E-O2 3.90E-02 3.00E-02 Zn-69 5.56E+01 2.08E-04 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Br-82 2.12K+03 5.45E-06 7.60E-01 5.00E-02 S.OOE-02 '.60K-02 Br-83 1.43E+02 8.08K&5 7.60E-01 5.00E-02 5.00E-02 2.60K&2 Br-84 3.18E+01 3. 63E-04 7.60K&1 5.00E-02 5.00E-02 2.60E-02 Br85 2.87E+00 4. 02K&3 7.60K&1 5 00E-02 5.00E-02 2.60E-02 Rb-86 2.69K+04 4. 29E-07 1.30E-01 3-OOK-02 3.00E-02 3.10E-02 Rb-88 1.78E+01 6.49E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Rb-89 1.54E+01 7.50E-04 1.30K-01 3.00E-02 3.00E-02 3.10E-02 Sr-89 7.28E+04 1.59E-07 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-90 1.50E+07 7.70E-10 1. 70K&2 1.40E-03 1.40E-02 6.00E-04 Sr-91 5.70E+02 2.03K&5 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-92 1.63E+02 7.09E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Y-90 3.85E+03 3.00E-06 2.60E-03 1.00E-O5 1 OOE-05 4.60E-03 Y-91m 4.97K+01 2.32E-04 2.60E-03 1.00E-05 1.00E-05 .4.60E-D3 Y-91 8.43K+04 1.37K&7 2. 60K&3 1.00E-OS 1.00K-05 4.60E-03 Y-92 2.12E+02 5.45E-05 2.60E-03 1 DOE-05 1.00E-05 4.60E-03 Y-93 6.06E+02 1.91E-05 2.60E-D3 1.00E-OS 1.00E-05 4.60E-03 Zr-95 9.22K+04 1.25E-07 1.70E-04 5.00E-06 5 ODE-06 3.40E-02 Zr-97 1.01E+03 1.14E-05 1.70E-04 5.00E-06 5 DDE-06 3.40E-02 Nb-95 5.05K+04 2.29E-07 9.40K&3 2.50E-03 2.50E-03 2.80K&1 Nb-97 7.21E+Ol 1.60E-04 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Mo-99 3.96E+03 2.92E-06 1. 20E-01 7.50E-03 7.50E-03 1.10E-03 Tc-99m 3.61E+02 3.20E-05 2.50K&1 2.50E-O2 2.50E-02 4.00E-01 Tc-101 1.42E+01 8.13K-04 2.50K-01 2 50E-02 2.50E-02 4.00E-01 Ru-103 5.67E+04 2.04E-07 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ru-105 2.66K+02 4.34E-05 5.00EW2 1 ODE-06 1.00E-06 4.00E-Ol Ru-106 S.aOK+05 2. 18K&8 5.00EW2 1.00E-D6 1.00E-06 4.00E-01 Ag-110m 3.60K+05 3. 21K&8 1.50K&1 5.00E-02 5.00K-02 1.70E-02 828o

RETS Manual Revision 9 Page 122 Table 6.2 (2 of 3)

RADIONUCLIDE DECAY AND"STABLE ELEMEKZ TRANSFER DATA Half.-Life Biv Fmi Fmi (minutes) (1/s) (cov) (goat) (beef )

Sb-124 8.67E+04 1 33E&7 N/A 1.50E-03 1.50E-03 N/A Sb-125 1.46E+06 7. 91E-09 N/A 1.50E-03 1.50E-03 N/A Te-125m 8.35K+04 1.38E-07 1 .

30E+05'.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-127m 1.57E+05 7.36E-08 1.00E-03 1.00E-03 7.70E-02 Te-127 5.61E+02 2. 06E&5 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-129m 4.84E+04 2.39E-07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-129 6.96E+01 1.66E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-131m 1.80E+03 6. 42E&6 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-131 2.50E+01 4. 62E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-132 4.69E+03 2.46E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 I-130 7.42E+02 1.56E&5 2.00E-02 1 20E-02 4.30E-01 2.90E-03 I-131 1.16E+04 9. 96E-07 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-132 1.38K+02 8. 37E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-133 1.25K+03 9.24E-06 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-134 5.26E+Ol 2.20E-04 2.00E-02 1.20E-02 4.30E-Ol 2.90E-03 I-135 3.97E+02 2.91E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 Cs-134 1.08E+06 1.06E-08 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-136 1.90E+04 6.08E-07 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-137 1.59E+07 7.26E-10 1.00E-02 8 '0K-03 3.00E-01 1.50E-02 Cs-138 3.22E+01 3.59E-04 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Ba-139 8.31E+01 1.39E-04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-140 1.84E+04 6.28E-07 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-141 1.83E+Ol 6.31E-04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-142 1.07K+01 1.08E-03 5.00E-03 4.00E-04 4.00E-04 3.20E-03 La-140 2.41E+03 4.79E-06 2.50E-03 5.00E-06 5.00E-06 2.00E&4 La-142 9.54E+Ol 1.21E-04 2.50E-03 5.00E-06 '.00E-06 2.00E&4 Ce-141 4.68E+04 2.47E-07 2.50E-03 1.00E-04 1.00E-04 1. 20E-03 Ce-143 1.98E+03 5.83E-06 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Ce-144 4.09E+05 2.82E-08 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Pr-143 1.95E+04 5.92E-07 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Pr-144 1.73E+01 6.68E-04 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Nd-147 1.58E+04 7.31E-07 2.40E-03 5.00E-06 5.00E-06 3.30E-03 W-187 1.43E+03 8.08E-06 1.80E-02 5.00E-04 5.00E-04 1.30E-03 Np-239 3.39E+03 3.41E-06 2.50E-03 5.00E-06 5.00E-06 2-OOE-04 Ar-41 1.10E+02 1. 05E-04 N/A N/A N/A N/A Kr-83m 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-85m 2.69E+02 4.29E-05 N/A N/A N/A N/A Kr-85 5.64K+06 2.05E-09 N/A N/A N/A N/A Kr-87 7.63E+01 1.51E-04 N/A N/A N/A N/A Kr-88 1.70E+02 6.79E-05 N/A N/A N/A N/A Kr-89 3.16K+00 3.66E-03 N/A N/A N/A N/A Kr-90 5.39E-01 2.14E-02 N/A N/A N/A N/A Xe-131m 1.70E+04 6. 79E-07 N/A N/A N/A N/A Xe-133m 3.15K+03 3. 67E-06 N/A N/A N/A N/A 828o

RETS Manual Revision 9 Page 123 Table 6.2 (3 of 3)

RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life Biv Fmi Fmi Ffi (minutes ) (1/s ) (co ) (goat) (beef)

Xe-133 7.55E+03 1.53E-06 N/A N/A N/A N/A Xe-135m 1.54E+01 7.50E&4 N/A N/A N/A N/A Xe-135 5.47E+02 2.11E-05 N/A N/A N/A N/A Xe-137 3.83E+00 3.02E-03 N/A N/A, N/A N/A Xe-138 1.41E+01 8.19E-04 N/A N/A N/A N/A

References:

Half lives for all nuclides: DOE-TIC-11026, "Radioactive Decay Data Tables A handbook of Decay Data for Application to Radiation Dosimetry and Radiological Assessment," D. C. Kocher, 1981.

Transfer factors for Sb- isotopes are from ORNL 4992, "Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment," March 1976, Table 2-7.

Cow-milk transfer factors for Iodine, Strontium, and Cesium nuclides are from NUREG/CR-1004, Table 3.17.

Goat-milk transfer factors for Iodine nuclides are from NUREG/CR-1004, Table 3.17.

Beef transfer factors for Iron, Copper, Molybdenum, and Cesium nuclides are from NUREG/CR-1004, Table 3.18.

All other nuclides'ransfer factors are from Regulatory Guide 1.109, Tables E-1 and E-2.

S2So

RETS Manual Revision 9 Page 124 Table 6.3 {1 of 2)

DOSE CALCULATION FACTORS Factor Value Units Reference BRa (infant) 1400 m3/year ICRP 23 BRa {child) 5500 m3/year ICRP 23 BRa (teen) 8000 m3/year ICRP 23 BRa (adult) 8100 m3/year ICRP 23 fg 1 TVA Assumption fL 1 R. G. 1.109 (Table E-15) fp 1 TVA Assumption fs 0 TVA Assumption H 9 g/m3 TVA Value Kc 0.072 L/kg-hr R. G. 1.109 (Section 2.C.)

M 40 kg/m2 R. G. 1.109 (Section 2.C.)

P 240 kg/m2 R. G. 1.109 {Table E-15)

Qf (cow) 64 kg/day NUREG/CR-1004 (Sect. 3.4)

Qf (goat) 08 kg/day NUREG/CR-1004 (Sect. 3.4) r 0.47 NUREG/CR-1004 (Sect. 3.2) tb 4.73E+08 seconds. R. G. 1.109 (Table E-15)

(15 years) tcb 7.78E+06 seconds SQN FSAR Section 11.3.9.1 (90 days) tcsf 1.56E+07 seconds SQN FSAR Section 11.3.9.1 (180 days) 5.18E+06 seconds R. G. 1.109 (Table E-15)

(60 days) tep 2.59E+06 seconds R. G. 1.109 (Table E-15)

(30 days) tesf 7.78E+06 seconds R. G. 1.109 (Table E-15)

(90 days) tfm 8.64E+04 seconds SQN FSAR Section 11.3.9.1 (1 day) thc 8.64E+04 seconds NUREG/CR-1004, Table 3.40 (1 day) ts 1.12E+06 seconds NUREG/CR-1004, Table 3.40 (13 days) tsv 2.38E+07 seconds SQN FSAR Section 11.3.9.1 (275 days )

Um (infant) 0 kg/year R. G. 1.109 (Table E-5)

U (child) 41 kg/year R- G. 1-109 (Table E-5)

Um (teen) 65 kg/year R. G. 1.109 (Table E-5)

Um (adult) 110 kg/year R. G. 1.109 (Table E-5)

Up (infant) 330 L/year R. G. 1.109 (Table E-5)

Up (child) 330 L/year R. G. 1.109 (Table E-5)

Up (teen) 400 L/year R. G. 1.109 (Table E-5)

Up (adult) 310 L/year R. G. 1.109 (Table E-5) 828o

0 RETS Manual Revision 9 Page 125 Table 6.3 (2 of 2)

DOSE CALCULATION FACTORS Factor Value Units Reference Uf(infant) 0 kg/year R. G. 1.109 (Table E-5)

Uf(child) 6.9 kg/year R. G. 1.109 (Table E-5)

Uf(teen) 16 kg/year R. G. 1.109 (Table E-5)

Uf(adult) 21 kg/year R. G. 1.109 (Table E-5)

UFL (infant) 0 kg/year R. G. 1.109 (Table E-5)

UFL (child) 26 kg/year R. G. 1.109 (Table E-5)

UFL (teen) 42 kg/year R. G. 1.109 (Table E-5)

UFL (adult) 64 kg/year R. G. 1.109 (Table E-5)

US (infant) 0 kg/year R. G. 1.109 (Table E-5)

US (child) 520 kg/year R. G. 1'.109 (Table E-5)

US (teen) 630 kg/year R. G. 1.109 (Table E-5)

US (adult) 520 kg/year R. G. 1.109 (Table E-5)

U~(infant) 330 L/year R. G. 1.109 (Table E-5)

Uz(child) 510 L/year R. G. 1.109 {Table E-5)

Uz(teen) 510 L/year R. G. 1.109 (Table E-5)

U~(adult) 730 L/year R. G. 1.109 (Table E-5)

W 0.3 none R. G. 1.109 (Table A-2)

Yf 1.85 kg/m" NUREG/CR-1004 (Table 3.4)

Yp 1.18 kg/m2 NUREG/CR-1004 (Table 3.3)

Ysf 0.64 kg/m2 NUREG/CR-1004 (Table 3.3)

Ysv 0.57 kg/m2 NUREG/CR-1004 (Table 3.4)

(value selected is for non-leafy vegetables)

Q {iodines) 7.71E-07 sec 1 NUREG/CR-1004 (Table 3.10)

(15.4 d half-life)

+ (particulates) 5.21E-07 (10.4 d sec 1 half-life)

NUREG/CR-1004 (Table 3 10) 828o

I .y ll

RETS Manual Revision 9 Page 126 Table 6.4 (1 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

ADULT bone liver t body thyroid kidney lung gi-lli 8-3 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1-05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 0.00E+00 0.00E+00 0.00K+00 2.17E-OS Cr-51 0.00E+00 0.00E+00 2-66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Hn-54 O.OOE+00 4.57E-06 8.72E-07 0.00E+00 1.36E-06 0.00K+00 1.40E-OS Mn-56 O.OOE+00 1.15E-07 2.04E-08 0.00E+00 1.46E-07 0.00K+00 3.67E&6 Fe-55 2. 75E-06 1.90E-06 4.43E-07 O.OOE+00 0.00E+00 1.06E-06 1.09E-06 Fe-59 4.34E-O6 1.02E-05 3.91E-06 O.OOE+00 0.00E+00 2.85E-06 3.40E-05 Co-57 0.00K+00 1. 75E-07 2.91E-07 O.OOE+00 O.OOE+00 O.OOE+00 4.44E-06 Co-58 0.00E+00 7.45E-07 1.67E-06 0.00E+00 O.OOE+00 O.OOE+00 1 51E-05 Co-60 0.00E+00 2. 14E-06 4.72E-06 0.00K+00 O.OOE+00 O.OOE+00 4.02E-OS Ni-63 1.30E-04 9-01E-06 4 36E-06 0.00E+00 O.OOE+00 O.OOE+00 1.88E-O6 Ni-65 5.28E-07 6.86E-08 3.13E-08 0.00K+00 O.OOE+00 0.00E+00 1.74E-06 Cu-64 0.00E+00 8.33E-08 3.91E-08 O.OOE+00 2.10E-07 0.00E+00 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 0.00E+00 1.03E-05 0.00E+00 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 0.00E+00 l. 28E&8 O.OOE+00 2.96E-09 Zn-69m 1.70E-07 4.08E-07 3.73E-08 0.00E+00 2. 47E-07 O.OOE+00 2.49E-05 Br-82 O.OOE+00 O.OOE+00 2 26E-06 0.00E+00 0.00E+00 0.00E+00 2.59E-06 Br-83 O.OOE+00 O.OOE+00 4.02E-OS 0.00E+00 O.OOE+00 0.00K+00 5.79E-08 Br-84 O.OOE+00 O.OOE+00 5 2lE-08 O.OOE+00 0.00E+00 0.00E+00 4.09E-13 Br-85 O.OOE+00 O.OOE+OO 2<<14E-09 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 Rb&6 0.00E+00 2.11E-05 9.83E-06 0.00E+00 O.OOE+00 O.OOE+00 4.16E-06 Rb-88 0 ~ OOE+00 6.05E-08 3.21E-08 0.00E+00 0.00E+00 O.OOE+00 8.36E-19 Rb-89 O.OOE+00 4.01E-08 2.82E-08 0.00E+00 0.00E+00 O.OOE+00 2.33E-21 Sr-89 3.08E-04 0.00E+00 8.84E-06 O.OOE+00 O.OOE+00 O.OOE+00 4.94E-05 Sr-90 7.58E-03 O.OOE+00 1.86E-03 0.00E+00 O.OOE+00 0.00E+00 2.19E-04 Sr-91 5.67E-06 O.OOE+00 2.29E-07 0.00E+00 0.00E+00 0.00E+00 2.70E-05 Sr-92 2.15E-06 0.00E+00 9.30E-08 0.00E+00 0.00E+00 0.00E+00 4.26E-05 Y-90 9. 62E-09 0.00E+00 2.58E-10 0.00E+00 O.OOE+00 0.00E+00 1.02E&4 Y-91m 9.09E-11 O.OOE+00 3.52E-12 0.00E+00 O.OOE+00 0.00E+00 2.67E>>10 Y-91 1.41E-O7 O.OOE+00 3.77E-09 O.OOE+00 O.OOE+00 O.OOE+00 7.76E-05 Y-92 8.45E-10 O.OOE+00 2.47E-11 O.OOE+00 O.OOE+00 O.OOE+00 1.48E-05 Y-93 2.68E-09 0.00E+00 7.40E-11 0.00E+00 O.OOE+00 O.OOE+00 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 O.OOE+00 1.53E-08 O.OOE+00 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 0.00E+00 5.12E-10 O.OOE+00 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3.42E-09 0.00E+00 2. 10E-05 Nb-97 5.22E-11 1.32E-ll 4.82E-12 O.OOE+00 1.54E-11 O.OOE+00 4.87E-08 Mo-99 O.OOE+00 4.31E-06 8.20E-07 O.OOE+00 9.76E-06 O.OOE+00 9.99E-06 Tc-99m 2.47E-10 6-98E-10 8.89E-09 0.00E+00 1.06E-OB 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 0.00E+00 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 0.00E+OO 7.97E-08 0.00E+00 7.06E-07 O.OOE+00 2.16E-05 Ru-105 1.54E-08 O.OOE+00 6.08E-09 0.00E+00 1.99E-07 0.00E+00 9.42E-06 RU-106 2.75E-06 O.OOE+00 3.48E-07 O.OOE+00 5.31E-06 0.00E+00 1.78E-04 Ag-110m 1.60E-07 1.48E-07 8.79E-08 O.OOE+00 2.91K-07 O.OOE+00 6.04E-OS 828o

RETS Nanual Revision 9 Page 127 Table 6.4 (2 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

ADULT bone liver t body thyroid kidney lung gi-lli Sb-124 2.80E-06 5. 29EWB 1 11E-06 6.79E-09 O.OOE-OO 2.18E-06 7.95E-05 Sb-125 1.79E-06 2. 00E&8 4. 26E-01 1.82E-09 O.OOE-OO 1.38E-06 1.97E-05 Te-125m 2.68E-06 9. 71E&7 3.59E-07 8.06E-07 1.09E-05 O.OOE+00 1.07E-05 Te-127m 6.77E-06 2. 42E-06 8.25E-07 1.73E-06 2.75E-05 O.OOE+00 2.27E-05 Te-127 1.10E-07 3.95E-OB 2.38E-OB 8.15E-OB 4.48E-07 O.OOE+00 8.68E-06 Te-129m 1.15E-05 4.29E-06 1. 82E&6 3.95E-06 4.80E-05 O.OOE+00 5.79E-05 Te-129 3.14E-OB 1.18E-OB 7.65E-09 2.41E-OB 1.32E-07 O.OOE+00 2.37E-OB Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 O.OOE+00 8.40E-05 Te-131 1.97E-OB 8.23E-09 6.22E-09 1.62E-OB 8.63E-OB O.OOE+00 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0.00E+00 7.71E-05 I-130 7.56E-07 2.23E-06 B.BOE-07 1.89E-04 3.48E-06 O.OOE+00 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 O.OOE+00 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E<<05 8.65E-07 O.OOE+00 1.02E-07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 O.OOE+00 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 O.OOE+00 2.51E-10 I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 O.OOE+00 1. 31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 O.OOE+00 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 O.OOE+00 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1 ~ 09E-04 7.14E&5 O.OOE+00 3. 70E&5 1.23E>>05 2.11E-06 Cs-138 5.52E-OB 1.09E-07 5.40E-OB 0 ~ OOE+00 8.01E-OB 7.91E-09 4.65E-13 Ba-139 9.70E-OB 6.91E-11 2.84E-09 O.OOE+00 6.46E-ll 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-OB 1.33E-06 0.00E+00 8.67K&9 1.46E-OB 4.18E-05 Ba-141 4. 71E&8 3.56E-ll 1.59E&9 0.00E+00 3.31E-11 2.02E-ll 2.22E-17 Ba-142 2. 13E&8 2.19E-11 l. 34E&9 O.OOE+00 1.85E<<11 1.24E-11 3.00E-26 La-140 2.50E-09 1. 26E&9 3.33E-10 O.OOE+00 O.OOE+00 O.OOE+00 9.25E-05 La-142 1.28E-10 5.82E-ll 1.45E-ll O.OOE+00 O.OOE+00 O.OOE+00 4.25E-07 Ce-141 9. 36EW9 6.33E-09 7.18E-10 O.OOE+00 2.94E-09 0 ~ OOE+00 2.42E-05 Ce-)43 1.65E-09 1.22E-06 1.35E-10 O.OOE+00 5.37E-10 O.OOE+00 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-OB 0.00E+00 1.21E-07 O.OOE+00 1.65E&4 Pr-143 9.20E-09 3.69E-09 4.56E-10 0.00E+00 2.13E-09 O.OOE+00 4.03E-05 Pr-144 3.01E-11 1.25E-ll 1.53E-12 0.00E+00 7.05E-12 0.00E+00 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 0.00E+00 4.25E-09 O.OOE+00 3.49E-05 M-187 1.03E-07 8. 61E&8 3.01E&8 O.OOE+00 0.00E+00 O.OOE+00 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-11 O.OOE+00 3.65E-10 O.OOE+00 2.40E-05

References:

Regulatory Guide 1.109, Table E-ll.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb<<125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake , November, 1977, Table 4.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

828o

RETS Manual Revision 9 Page 110 6.3.1.3 Recreation For the recreation dose calculation, the total dose is estimated based on a calculation of the shoreline dose for Co-58, Co-60, Cs-134, and Cs-137. The shoreline dose due to these four nuclides is expected to contribute over 95 percent of the total recreation dose. The total body and maximum organ dose to an individual via the shoreline recreation pathway are assumed to be equal. The recreation dose is described by the following equation:

4 1012 Dz ig 1 42 Dpi 4 where:

Dr ~ recreation dose from plant releases, mrem.

1012 ~ conversion factor, pCi/Ci.

0.95 ~ conservative correction factor for considering only 4 radionuclides.

42 ~ assumed monthly exposure time for maximum individual, hours DFGi = dose coamitment factor for standing on contaminated ground for the ith radionuclide, mrem/hr per pCi/m2 (Table 6.6).

concentration of ith radionuclide in shoreline sediment, Ci/m , as by the following equation (based on equation A-5 in 2'escribed Regulatory Guide 1.109).

~ 103 6 ~ 94E&4 100 RHLi W[1~(-'hitb] Ci (6.10) where.'03

= conversion factor, ml/L.

6.94E-04 ~ conversion factor, d/min.

RHLi ~ radiological half-life of the ith radioisotope, minutes (Table 1.11).

100 = conversion factor, L/Kg-hr (defined in Regulatory Guide 1.109).

W = shoreline width factor (Table 6.3).

X1 = decay constant of the ith radionuclide, sec (Table 1.11).

tb = buildup time in sediment, seconds (Table 6.3)

C i = concentration of ith radionuclide in the Tennessee River, Ci/ml.

Ai/{F d 7.34E+10) where:

A1. = activity released of ith radionuclide during the month, Ci/month.

F -" average river flow for the month, cfs.

d ~ fraction of river flow available for dilution, 0.30.

7.34E+10 = conversion from cfs to ml/month.

828o

RETS Manual Revision 9 Page 128 Table 6.4 (3 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

TEEN bone liver t body thyroid kidney lung gi-lli H-3 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E&7 C-14 4.06K&6 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8. 12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E-05 1.07E-05 0.00E+00 0.00K+00 0.00E+00 2.32E&5 Cr-51 0.00E+00 O.OOE+00 3.60E-09 2.00E-09 7.89E-10 5.14E-O9 6.05E-07 Mn-54 0.00K+00 5.90E-06 1.17E-06 O.OOE+00 1.76E-06 O.OOE+00 1.21E-05 Mn-56 0 'OE+00 1.58E-07 2.81E-OB 0.00E+00 2.00E-07 O.OOE+00 1.04E-05 Fe-55 3.78E-06 2.68E-06 6 '5E-07 0.00E+00 0.00E+00 1.70E-06 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 O.OOE+00 0.00E+00 4.32E-06 3.24E-05 Co-57 0.00E+00 2.38E-07 3. 99E&7 0.00E+00 0.00E+00 O.OOE+00 4.44E-06 Co-58 0 ~ OOE+00 9. 72E&7 2. 24E-06 0.00E+00 O.OOE+00 O.OOE+00 1.34E-05 Co-60 O.OOE+00 2.81E-06 6.33E-06 0.00E+00 0.00E+00 0.00E+00 3 '6E-05 Ni-63 1.77E-04 l. 25E-05 6.00E&6 0.00E+00 0.00E+00 0.00E+00 1.99E-06 Ni-65 7.49E-07 9.57E-OB 4.36E-OB O.OOE+00 0.00E+00 O.OOE+00 5.19E-06 Cu-64 0.00E+00 1.15E-07 5.41E-OB 0.00E+00 2.91E-07 O.OOE+00 8.92E-06 Zn-65 5.76E-06 2.00E-05 9.33E-06 0.00E+00 1.28E-05 O.OOE+00 8.47E-06 Zn-69 1.47E-OS 2.80E-OS 1.96E-09 O.OOE+00 1.S3E-OB 0.00E+00 5.16E-OB Zn-69m 2.40E-07 5.66E-07 5.19E-OB 0.00K+00 3.44E-07 0.00E+00 3.11E-05 Br-82 0.00E+00 0.00K+00 3.04E-06 0.00E+00 0.00E+00 0.00K+00 0.00E+00 Br-83 0.00E+00 0.00E+00 5.74E-OB 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 0.00E+00 0.00E+00 7.22E-OS O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 Br-85 0.00K+00 0.00E+00 3.05E-09 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 Rb-86 O.OOE+00 2.9SE-05 1.40E-05 O.OOE+00 0.00E+00 0.00E+00 4.41E-06 Rb-88 0.00E+00 8'52E-OB 4.54E-OS 0.00E+00 0.00E+00 0.00E+00 7.30E-15 Rb-89 0.00E+00 5.50E-OB 3.89E&8 0.00E+00 0 ~ OOE+00 0.00E+00 8.43E-17 Sr-89 4.40E-O4 O.OOE+00 1.26E-05 0.00E+00 O.OOE+00 O.OOE+00 5.24E-05 ,

Sr-90 8.30E-03 0.00E+00 2.05E-03 0.00E+00 O.OOE+00 O.OOE+00 2.33E-04 Sr-91 8.07E-06 0.00E+00 3.21E-07 O.OOE+00 O.OOE+00 O.OOE+00 3.66E-05 Sr-92 3.05E-06 0.00E+00 1.30E-07 0.00E+00 0.00E+00 O.OOE+00 7.77E-05 Y-90 1.37E-OS 0.00E+00 3.69E-10 0.00E+00 O.OOE+00 O.OOE+00 1.13E-04 Y-91m 1.29E-10 0.00E+00 4.93E-12 0.00E+00 0.00E+00 0.00E+00 6.09E-09 Y-91 2.01E-07 O.OOE+00 5.39E-09 0.00E+00 O.OOE+00 O.OOE+00 8.24E-05 Y-92 1.21E-09 0.00E+00 3.50E-11 O.OOE+00 0.00E+00 O.OOE+00 3.32E-05 Y-93 3.83E-09 O.OOE+00 1.05E-10 O.OOE+00 O.OOE+00 0.00E+00 1.17K-04 Zr-95 4.12E-OB 1.30E-OB 8.94E-09 0.00E+00 1. 91E-08 O.OOE+00 3.00E-05 Zr-97 2.37E-O9 4.69E-10 2.16E-10 0.00E+00 7.11E-10 0.00E+00 1.27E-04 Nb-95 8.22E-09 4 '6E-09 2.51E-09 O.OOE+00 4.42E-09 O.OOE+00 1.95E-05 Nb-97 7.37E-11 1.83E-11 6.68E-12 O.OOE+00 2.14E-ll O.OOE+00 4.37E-07 Mo-99 0.00E+00 6.03E-06 1.15E06 0.00E+00 1.38E-05 0.00K+00 1.08E-05 Tc-99m 3.32E-10 9.26E-10 1.20E-OB 0.00E+00 1.38E-OB 5.14E-10 6.08E-07 Tc-101 3.60E-10 5.12E-10 5.03E-09 0.00E+00 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 0.00E+00 1.09E-07 O.OOE+00 8.99E-07 O.OOE+00 2.13E-05 Ru-105 2.18E-OB 0.00E+00 8.46E-09 0.00E+00 2.75E-07 O.OOE+00 1.76E-05 Ru-106 3.92E-06 O.OOE+00 4.94E-07 O.OOE+00 7.56E-06 O.OOE+00 1.88E-04 Ag-110m 2.05E-07 1.94E-07 1.18E-07 O.OOE+00 3.70E>>07 0.00K+00 5.45E-05 828o

RETS Manual Revision 9 Page 129 Table 6.4 (4 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

TEEN bone liver t body thyroid kidney lung gi-lli Sb-124 3.87K-06 7.13E-OB 1.51E-06 8.78E-09 O.OOE-OO 3.38E-06 7.80E-05 Sb-125 2.4BE-06 2.71E-OB 5.80E-07 2.37E-09 0.00E+00 2.18E-06 1.93E-05 Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 O.OOE+00 O.OOE+00 1.13E-05 Te-127m 9.67E-06 3.43E&6 1.15E-06 2.30E-06 3.92E-05 O.OOE+00 2.41E-05 Te-127 1.58E-07 5.60E-OB 3.40E-OB 1.09E&7 6.40E-07 O.OOE+00 1.22E<<05 Te-129m 1.63E-05 6.05K&6 2.58E-06 5. 26E&6 6.82E-05 O.OOE+00 6.12E-05 Te-129 4.48E-OB 1. 67E-08 1.09E-OB 3.20E-OB 1.88E-07 O.OOE+00 2.45E-07 Te<<131m 2.44K-06 1.17EM6 9.76E-07 1.76E-06 1.22E-05 O.OOE+00 9.39E-05 Te-131 2.79E-OB 1.15E-OB 8.72E-09 2.15E-OB 1.22E-07 O.OOE+00 2.29E-09 Te-132 3.49E-06 2. 21E&6 2.08E-06 2.33E-06 2.12E-05 O.OOE+00 7.00E-05 I-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 O.OOE+00 2.29E-06 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 O.OOE+00 1.62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 O.OOE+00 3.18E-O7 I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 O.OOE+00 2.58E-06 I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 O.OOE+00 5.10E-09 I-135 6.10E-07 1.57E-06 5.82E-07 1.01E<<04 2.48E-06 O.OOE+00 1.74E-06 Cs-134 8.37K-05 1.97E-04 9.14E-05 O.OOE+00 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.3BE-05 2.27E-05 O.OOE+00 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 0.00E+00 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-OB 1.49E-07 7.45E-OB 0.00E+00 1.10E-07 1.28E-OB 6.76E-11 Ba-139 1.39E-07 9.78E-11 4.05E-09 O.OOE+00 9.22E-ll 6. 74E-11 1.24E-06 Ba-140 2.84E-05 3.48E-OB 1.83E-06 0 OOE+00 1. 18E-08 2.34E-OB 4;38E-05 Ba-141 6.71E-OB 5.01E-11 2.24E-09 0.00E+00 4.65E-11 3.43E-ll 1.43E-13 Ba-142 2.99E-OB 2.99E-11 1.84E-09 0.00E+00 2.53E-11 1.99E-ll 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 O.OOE+00 0.00K+00 O.OOE+00 9.82E<<05 La-142 1.79E-10 7.95E-11 1.98E-11 0.00E+00 0.00E+00 O.OOE+00 2.42E-06 Ce-141 1.33E-OB B.BBE-09 1-02E-09 O.OOE+00 4.18E-09 O.OOE+00 2.54E-05 Ce-143 2.35E-09 1.71E>>06 1.91E-10 O.OOE+00 7. 67E-10 O.OOE+00 5.14E-05 Ce-144 6.96K&7 2.88E-07 3.74E-OB 0.00E+00 1. 72E-07 O.OOE+00 1.75E-04 Pr-143 1.31E-OB 5.23E-09 6.52E-10 0.00E+00 3.04E-09 O.OOE+00 4.31E-05 Pr-144 4.30E-11 1.76E-11 2.18E-12 O.OOE+00 1.01E-ll O.OOE+00 4.74E-14 Nd-147 9.38E-09 1.02E-OB 6.11E-10 O.OOE+00 5.99E-09 O.OOE+00 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-OB O.OOE+00 O.OOE+00 O.OOE+00 3.22E-05 Np-239 1.76E-09 1.66E-10 9.22E-11 0.00E+00 5.21E-10 O.OOE+00 2.67E-05

References:

Regulatory Guide 1.109, Table E-12.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake , November, 1977, Table 3.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

828o

RETS Manual Revision 9 Page 130 Table 6.4 (5 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

CHILD bone liver t body thyroid kidney lung gi-lli H-3 2.03E-07 2.03E&7 2.03E-07 2.03E&7 2.03E-07 2.03E-07 2.03E-07 C-14 l. 21E&5 2.42E-06 2.42E-06 2.42E&6 2.42E&6 2.42E-06 2.42E-06 Na-24 5.80E-06 5.80E&6 5.80E&6 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8 25E-04 3.86E&5 3.18E-05 0.00E+00 O.OOE+00 O.OOE+00 2.28E-05 Cr-51 O.OOE+00 0.00E+00 8 90E-09 4.94E-09 1.35E&9 9.02E-09 4.72E-07 Mn-54 O.OOE+00 1.07E&5 2.85E-06 0.00E+00 3.00E-06 O.OOE+00 &.98E-06 Mn-56 O.OOE+00, 3.34E-07 7.54E-08 O.OOE+00 4.04E-07 O.OOE+00 4.84E-O5 Fe-55 1. 15E&5 6.10E-06 1.89E-06 O.OOE+00 O.OOE+00 3.45E-06 1.13E-06 Fe-59 1.65E-05 2.67E-05 1.33E-05 0.00K+00 O.OOE+00 7.74E-06 2. 78E&5 Co-57 0.00E+00 4.93E-07 9.98E-07 0.00K+00 0.00E+00 0.00E+00 4.04E-06 Co-58 0.00E+00 1.80E&6 5.51E-06 0 ~ OOE+00 0.00E+00 0.00E+00 1.05E-05 Co-60 O.OOE+00 5.29E-06 1.56E-05 O.OOE+00 0.00E+00 O.OOE+00 2.93E-05 Ni-63 5.38E-04 2.88E&5 1.83E-05 0.00E+00 0.00E+00 0.00E+00 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 0.00E+00 O.OOE+00 0.00E+00 2.56E-05 CU-64 0.00E+00 2.45E-07 1.48E&7 O.OOE+00 5.92E-07 0.00E+00 1.15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 0.00E+00 2.30E-05 0.00E+00 6.41E-O6 Zn-69 4.38E&8 6.33E-08 5.85E-09 O.OOE+00 3.84E-08 0.00E+00 3. 99E&6 Zn-69m 7.10E-07 1.21E-06 1.43E&7 0.00E+00 7.03E-07 0.00E+00 3.94E-05 Br-82 0.00E+00 O.OOE+00 7.55E-06 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 Br-83 0.00E+00 O.OOE+00 1.71E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 O.OOE+00 1.98E&7 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Br-85 O.OOE+00 0.00E+00 9.12E-09 O.OOE+00 O.OOEmo O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 6.70E-05 4.12E-05 0.00E+00 0.00E+00 0.00E+00 4.31E>>06 Rb-88 0.00E+00 1 ~ 90K-07 1.32E-07 0.00E+00 0.00E+00 O.OOE+00 9.32E-09 Rb-89 0.00E+00 1.17E-07 1.04E-07 0.00E+00 O.OOE+00 0.00E+00 1.02E-09 Sr-89 1.32E-03 O.OOE+00 3.77E-05 O.OOE+00 0.00E+00 O.OOE+00 5.11E-05 Sr-90 1. 70E-02 O.OOE+00 4.31E-03 O.OOE+00 0.00E+00 O.OOE+00 2.29E-04 Sr-91 2. 40E-05 O.OOE+00 9.06E-07 0.00E+00 O.OOE+00 0.00E+00 5.30E-05 Sr-92 9.03E&6 O.OOE+00 3.62E&7 O.OOE+00 0.00E+00 0.00E+00 1.71E>>04 Y-90 4.11E-08 0.00E+00 1.10E&9 0.00E+00 0.00E+00 0.00E+00 1.17E-04 Y-91m 3.82E-10 0.00E+00 1.39E-11 O.OOE+00 0.00E+00 0.00E+00 7.48E-07 Y-91 6.02E-07 0.00E+00 1.61E&8 O.OOE+00 O.OOE+00 O.OOE+00 8.02E-05 Y-92 3.60E-09 0.00E+00 1.03E-10 O.OOE+00 0.00E+00 O.OOE+00 1.04E-04 Y-93 1.14E-08 O.OOE+00 3.13E-10 O.OOE+00 0.00E+00 O.OOE+00 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 O.OOE+00 3.65E-08 O.OOE+00 2.66E-OS Zr-97 6. 99E&9 1.01E-09 5.96E-10 O.OOE+00 1.45E&9 0.00E+00 1.53E-04 Nb-95 2.25E-08 8. 76E&9 6.26E-09 O.OOE+00 8. 23E&9 O.OOE+00 1.62E-05 Nb-97 2.17E-10 3.92E-ll 1.83E-11 O.OOE+00 4.35E-11 O.OOE+00 1.21E-05 Mo-99 0.00E+00 1.33E-05 3.29E-06 O.OOE+00 2.84E-05 O.OOE+00 1.10E-05 Tc-99m 9.23E-10 1.81E&9 3.00E-08 0.00E+00 2. 63E&8 9.19E-10 1.03E-06 Tc-101 1.07E-09 l. 12E-09 1.42E-08 0.00E+00 1. 91E&8 5-92E-10 3.56E-09 Ru-103 7.31E-07 O.OOE+OO 2.81E-07 O.OOE+00 1.84E06 0.00E+00 1.89E<<05 Ru-105 6.45E-08 O.OOE+00 2.34E-08 0.00E+00 5.67E-07 0.00E+00 4.21E-05 Ru-106 1.17E-05 O.OOE+00 1.46E-06 O.OOE+00 1.58E-05 O.OOE+00 1.82E-04 Ag-110m 5.39E-07 3.64E>>07 2.91E-07 O.OOE+00 6.78E-07 O.OOE+00 4.33E-05 828o

RETS Nanual Revision 9 Page 131 Table 6..4 (6 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

CHILD bone liver t body thyroid kidney lung gi-lli Sb-124 1.11E-05 1.44E>>07 3.89E-06 2.45E-OS O.OOE+00 6.16E-06 6.94E-05 Sb-1.25 7.16E-06 5.52E>>OB 1.50EWE 6.63E-09 0.00E+00 3.99E-06 1.71E-05 Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 O.OOE+00 O.OOE+00 1.10E-05 Te-127m 2.89E-OS 7.78E-06 3.43E-06 6.91E-06, 8.24E-05 O.OOE+00 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 O.OOE+00 1.84E-05 Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 O.OOE+00 5.94E-05 Te-129 1.34E-07 3.74E-OB 3.18E&8 9.56E-OS 3.92E-07 O.OOE+00 8.34E-06 Te-131m 7.20E-06 2.49E-06 2. 65EW6 5.12E-06 2.41E-05 O.OOE+00 1.01E-04 Te-131 8.30E-OB 2.53E-OB 2.47E-OS 6.35E&8 2.51E-07 O.OOE+00 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E&6 6.51E-06 4.15E-05 O.OOE+00 4.50E-05 I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 O.OOE+00 2.76E-06 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 O.OOE+00 1.54E-O6 I-132 S.OOE-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 O.OOE+00 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 O.OOE+00 2.95E-06 I-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 O.OOE+00 5.16E-07 I-135 1.75E-06 3. 15E-06 1.49E-06 2.79E-04 4.83E-06 O.OOE+00 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 O.OOE+00 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 O.OOE+00 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 O.OOE+00 1.02E>>04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 0.00E+00 2.23E-07 2.40E-OB 1.46E-07 Ba-139 4,14E-07 2.21E-10 1.20E-OS O.OOE+00 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-OB 4.85E-06 0.00E+00 2.37E-OB 4.34E-OB 4.21E-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 0.00K+00 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-OB 6.29E-11 4.88E-09 0.00E+00 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-OB 3.53E-09 1.19E-09 O.OOE+00 0.00K+00 O.OOE+00 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-ll O.OOE+00 O.OOE+00 O.OOE+00 3.31E-05 Ce-141 3.97E-OS 1.98E-OS 2.94E-09 O.OOE+00 8.68E-09 O.OOE+00 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 O.OOE+00 1.59E-09 O.OOE+00 5.55E-05 Ce-144 2.08E-06 6.52E-07 1 11E-07 O.OOE+00 3. 61E-07. O.OOE+00 1.70E-04 Pr-143 3.93E-OS 1.18E-OS l. 95E-09 O.OOE+00 6.39E-09 O.OOE+00 4.24E-05 Pr-144 1.29E-10 3.99E-ll 6.49E-12 O.OOE+00 2.11E-11 O.OOE+00 8.59E-OS Nd-147 2.79E>>OB 2.26E>>OB 1.75E-09 O.OOE+00 1.24E-OB O.OOE+00 3.58E-05 W-187 4.29E-07 2.54E-07 1.14E-07 0.00E+00 0.00E+00 O.OOE+00 3.57E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 O.OOE+00 1.09E-09 0.00E+00 2.79E-05

References:

Regulatory Guide 1.109, Table E-13.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake , November, 1977, Table 2.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

828o

0 RETS Manual Revision 9 Page 132 Table 6.4 (7 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

INFANT bone liver t body thyroid kidney lung gi-lli H-3 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C-14 2.37E>>05 5.06E06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-OS 1.01E-05 1.01E-05 1.01E&5 P-32 1.70E-03 1.00E-04 6.59E-05 O.OOE+00 O.OOE+00 O.OOE+00 2. 30E-05 Cr-51 O.OOE+00 0.00K+00 1.41E-08 9.20E&9 2.01E-09 1.79E-08 4.'11E-07 Mn-54 0.00E+00 1.99E-05 4.51E-06 0.00E+00 4.41E-06 0 'OE+00 7.31E-06 Mn-56 0.00E+00 8.18E-07 1.41E-07 O.OOE+00 7.03E-07 O.OOE+00 7.43E-OS Fe-55 1.39E-05 8.98E-06 2.40E-06 O.OOE+00 0.00E+00 4.39E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 0.00E+00 0.00E+00 1.59E-05 2.57E-05 Co-57 0.00E+00 1.15E-06 1.87E-06 0.00E+00 0.00E+00 O.OOE+00 3. 92E-06 Co-58 0.00E+00 3.60E-06 8.98E&6 O.OOE+00 O.OOE+00 O.OOE+00 8. 97E&6 Co-60 O.OOE+00 1.08E-05 2.55E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.57E-OS Ni-63 6.34E-04 3.92E-05 2.20E-05 0 'OE+00 0.00E+00 O.OOE+00 1.95E-06 Ni-65 4.70E-06 5. 32EW7 2.42E-07 O.OOE+00 0.00E+00 0 ~ OOE+00 4.05E-OS CG-64 0.00E+00 6.09E-07 2.82E-07 O.OOE+00 1.03E-06 O.OOE+00 1. 25E&5 Zn-65 1.84E-05 6.31E-05 2.91E-05 0.00K+00 3.06E-05 O.OOE+00 5.33E-05 Zn-69 9.33E-08 1.68E-07 1.25E-O8 O.OOE+00 6.98E-08 O.OOE+00 1.37E-05 Zn-69m 1.50E-06 3.06EM6 2.79EO7 O.OOE+00 1.24E-06 O.OOE+00 4. 24E-05 Br-82 O.OOE+00 O.OOE+00 1.27E-05 O.OOE+00 0 OOE+00 O.OOE+00 0.00E+00 Br-83 O.OOE+00 O.OOE+00 3.63E&7 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 3.82E&7 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 1.94E>>08 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 Rb-86 0.00E+00 1.70E-04 8.40E-05 0.00E+00 0.00E+00 0.00E+00 4.35E-06 Rb-88 O.OOE+00 4.98E-07 2.73E-07 0.00E+00 0.00E+00 0.00E+OO 4.85E-07 Rb-89 O.OOE+00 2.86E-07 1.97E&7 0.00E+00 O.OOE+00 O.OOE+00 9.74E-08 Sr-89 2.51E-03 O.OOE+00 7.20E-05 O.OOE+00 0.00E+00 0.00E+00 5.16E-05 Sr-90 1.85E-02 0.00E+00 4.71E-03 O.OOE+00 O.OOE+00 O.OOE+00 2.31E-04 Sr-91 5.00E-05 O.OOE+00 1.81E&6 0.00E+00 0.00K+00 O.OOE+00 5.92E-05 Sr-92 1.92E-OS 0.00E+00 7.13E-07 0.00K+00 0.00E+00 0.00E+00 2.07E-04 Y-90 8.69E-08 0.00E+00 2.33E-09 0.00E+00 0.00E+00 0.00E+00 1.20E-04 Y-91m 8.10E-10 O.OOE+00 2.76E-11 O.OOE+00 0.00E+00 0.00E+00 2.70E-06 Y-91 1.13E-06 0.00E+00 3.01E-08 0.00E+00 0.00E+00 O.OOE+00 8.10K-05 Y-92 7.65E-09 O.OOE+00 2.15E-10 O.OOE+0" O.OOE+00 0.00E+00 1.46E-04 Y-93 2.43E-08 O.OOE+00 6.62E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 O.OOE+00 5.41E-08 O.OOE+00 2.50E-05 Zr-97 1. 48E-08 2.54E-09 1.16E&9 0.00E+00 2.56E-09 0.00E+00 1.62E-04 Nb-95 4. 20E-08 1.73E-OS 1.00E-08 O.OOE+00 1.24E-08 O.OOE+00 1.46E-05 Nb-97 4.59E-10 9.79E-11 3.53E-11 O.OOE+00 7.65E-ll O.OOE+00 3.09E-05 Mo-99 0.00E+00 3.40E-05 6.63E-06 O.OOE+00 5.08E-05 0.00E+00 1.12E-05 Tc-99m 1.92E-09 3.96E-09 5.10E-08 O.OOE+OO 4.26E-O8 2.07E&9 1.15E-06 Tc-101 2.27E-09 2. 86E&9 2.83E-08 O.OOE+00 3. 40E-'08 1.56E-09 4.86E-07 Ru-103 1.48E-06 O.OOE+00 4.95E-07 0.00E+00 3.08E-06 0.00E+00 1.80E-05 Ru-105 1.36E-07 O.OOE+00 4.58E-08 O.OOE+00 1.00E-06 0.00E+00 5.41E-05 Ru-106 2.41E-05 0.00E+00 3.01E-06 O.OOE+00 2.85E-05 O.OOE+00 1.83K-04 Ag-110m 9.96E-07 7.27E-07 4.81E-07 O.OOE+00 1.04E-06 0.00E+00 3.77E-05 828o

RETS Manual Revision 9 Page 133 Table 6.4 (8 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

INFANT bone liver t body thyroid kidney lung gi-lli Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 O.OOE+00 1.34E-05 6.60E-05 Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-OS O.OOE+00 7.72E-06 1.64E-05.

Te-125m 2.33E-05 7.79E-06 3.15E-06 7.84E>>06 O.OOE+00 O.OOE+00 1.11E-05 Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 O.OOE+00 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 O.OOE+00 2.10E-05 Te-129m 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 O.OOE+00 5.97E-05 Te-129 2.84E-07 9.79E-OS 6.63E-OS 2.3SE-07 7.07E-07 O.OOE+00 2.27E-05 Te-131m 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 0.00E+00 1.03E-04 Te-131 1. 76EW7 6.50E-OS 4.94E-OS 1.57E-07 4.50E-07 O.OOE+00 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 O.OOE+00 3.81E-05 I-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 O.OOE+00 2.83E-06 I-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 O.OOE+00 1.51E-06 I-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 O.OOE+00 2.73E-06 I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 O.OOE+00 3.08E-06 I-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 O.OOE+00 1.84E-06 I-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 O.OOE+00 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 O.OOE+00 1. 81E-04 7.42E-05 1. 91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 O.OOE+00 5.38E-05 1. 10E-05 2.05E-06 Cs-137 5.22E-04 6. 11E-04 4.33E-05 O.OOE+00 1.64E&4 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 O.OOE+00 3.90E-07 6.09E-OS 1.25E-06 Ba-139 8.81E&7 5.84E-10 2.55EWS O.OOE+00 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 0.00E+00 4.06E-OS 1.05E-07 4.20E-05 Ba-141 4. 25E-07 2.91E-10 1.34E-OS 0.00E+00 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 O.OOE+00 8.81E-11 9.26E-11 7.59E&7 La-140 2.11E-OS 8. 32EW9 2.14E-09 0.00E+00 O.OOE+00 0.00E+00 9. 77E-05 La-142 l. 10E&9 4.04E-10 9.67E-11 O.OOE+00 O.OOE+00 O.OOE+00 6.86E-05 Ce-141 7.87E-OS 4.80E-OS 5.65E-09 O.OOE+00 1.48E-OS O.OOE+00 2.48E-05 Ce-143 1.48E-08 9.82:--06 1.12E-09 O.OOE+00 2.86E-09 O.OOE+00 5.73E-05 Ce-144 2. 98E&6 1. 22E&6 1.67E-07 0.00E+00 4.93E-07 O.OOE+00 1.71E-04 Pr-143 8. 13EWS 3.04E-OS 4.03E-09 O.OOE+00 1.13E-OS 0.00E+00 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-ll O.OOE+00 3.84E-11 0.00E+00 4.93E-06 Nd-147 5.53E-OS 5.68E-OS 3.48E-09 O.OOE+00 2.19E-08 O.OOE+00 3.60E-05 W-187 9.03E-07 6.28E-07 2.17E-07 O.OOE+00 0 'OE+00 0.00E+00 3.69E-05 Np-239 1. 11EWS 9.93E-10 5.61E-10 O.OOE+00 l. 98E&9 O.OOE+00 2. 87E&5

References:

Regulatory Guide 1.109, Table E-14.

Dose Factors for Co-57, Zn-69m, Br-S2, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake , November, 1977, Table 1.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

828o

RETS Manual Revision 9 Page 134 Table 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH 8-3 9.0E&1 Tc-99m 1.5E+01 C-14 4. 6E+03 Tc-101 1.5E+Ol Na-24 1.0E+02 RU-103 1.0E+01 P-32 1.0E+05 RG-105 1.0K+01 Cr-51 2.0E+02 Ru-106 1.0E+01 Mn-54 4.0E+02 Ag-110m O.0K+00 Mn-56 4.0E+02 ,Sb-124 1.0E+00 Fe-55 1.0E+02 Sb-125 1.0E+00 Fe-59 1.0E+02 Te-125m 4.0K+02 Co-57 5.0E+01 Te-127m 4.0E+02 Co>>58 5.0E+Ol Te-127 4.0E+02 Co-60 5.0E+01 Te-129m 4.0E+02 Ni-63 1.0K+02 Te-129 4.0E+02 Ni-65 '1.0E+02 Te-131m 4.0K+02 CLI-64 5 'E+01 Te-131 4.0E+02 Zn-65 2.0E+03 Te-132 4.0E+02 Zn-69 2.0E+03 I-130 4.0E+01 Zn-69m 2.0E+03 I-131 4.0E+01 Br-82 4.2E+02 I-'132 4.0K+01 Br-83 4.2K+02 I-133 4.0E+Ol Br-84 4.2E+02 I-134 4.0E+01 Br-85 4.2E+02 I-135 4.0E+01 Rb&6 2.0E+03 Cs-134 1.9E+03 Rb&8 2,0E+03 Cs-136 1.9E+03 Rb-89 2.0E+03 Cs-137 1.9E+03 Sr-89 5.6E+01 Cs-138 1.9K+03 Sr-90 5.6E+01 Ba-139 4.0E+00 Sr-91 5.6E+Ol Ba-140 4.0E+00 Sr-92 5.6E+01 Ba-141 4.0E+00 Y-90 2.5E+Ol Ba-142 4.0E+00 Y-91m 2.5E+Ol La-140 2.5E+01 Y-91 2.5E+01 La-142 2.5E+01 Y-92 2.5E+01 Ce-141 1.0E+00 Y-93 2.5E+01 Ce-143 1.0K+00 Zr-95 3.3E+00 Ce-144 1.0E+00 Zr-97 3.3E+00 Pr-143 2.5E+01 Nb-95 3.0E+04 Pr-144 2.5E+Ol Nb-97 3.0E+04 Nd-147 2 5E+01 Mo-99 1.0E+Ol M-187 1.2E+03 Np-239 1.0E+Ol

References:

Bioaccumulation factors for Antimony nuclides are from ORNL-4992, "A Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment, March 1976, Table 4.12A.

Bioaccumulation factors for Iodine, Cesium, and Strontium nuclides are from NUREG/CR-1004, Table 3.2.4.

All other nuclides'ioaccumulation factors u' are from Regulatory Guide 1.109, Table A-l.

828o

RETS Manual Revision 9 Page 135 Table 6.6.(l of 2)

~ERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem/h per pCi/m )

Nuclide Total Body Skin H-3 0.0 0.0

'-14 0'.'0 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2. 20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-57 1.77E-09 2.21E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 C0-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09.

Zn-69 0.0 0.0 Zn-69m 5.50E-09 6.59E-09 Br-82 3.18E-08 3.90E-08 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6. 30E-10 7.20E-10 Rb-88 3. 50E-09 4.00E-09 Rb&9 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91m 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Nb-97 8.11E-09 1.00E-08 Mo-99 1.90E-09 2.20E-09 Tc-99m 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 RQ-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5. 10EW9 Ru-106 1.50E-09 1.80E-09 Ag-110m 1. 80E&8 2.10E-08 Sb-124 2 17E-08 2.57E-08 828o

RETS Manual Revision 9 Page 136 Table 6.6 (2 of 2)

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem/h per pCi/m )

Nuclide Total Body Skin Sb-125 5.48E-09 6.80E-09 Te-125m 9."50E-11 4.80E-11 Te-127m 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129m 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131m 8.40E-09 9. 90E&9 Te-131 2. 20E&9 2. 60E-06 Te-132 l. 70E-09 2.00E-09 I-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2-OOE-08 I-133 3. 70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E&8 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2. 10E&8 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2. 10E-09 2.40E-09 Ba-141 4.30K&9 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09

References:

Regulatory Guide 1.109, Table E-6.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from Dose-Rate Conversion Factors for External Ex osure to Photon and Electron Radiation from Radionuclides Occurrin in Routine Releases from Nuclear Fuel C cle Facilities D. C. Kocher, Health Physics Volume 38, April 1980.

828o

RETS Manual Revision 9 Page 137 Figure 6.1 LI UID RELEASE POINTS BFN Liquid Effluent Monitora typical Unit end Common Aadwaate)

Cendenser Coehne W~

Intake Bay ItHR betvtw W&w RHR Rll eo.tae RHR Rll 00.104 R

ill V)

Vl

'fll lTl 2C m

Opontne ter H~ il (1) Turbine Building Equipment (2) Reactor Building Equipment To Cooantt (3) Condeneer Tessera From Ceeantt Taws 828o

RETS Manual Revision 9 Pege 138 Figure 6.2 LI UID RADMASTE SYSTEN Floor Drain Drain Floor Collector Filter Sample RM90-t 30 Fl ~~

Drains Tank Tanks Laundry Drain Tanks Equi pment rains Waste Waste Waste Condensate Collector Filter Demlnerallzer Sample Storage Tanks Tanks 828o

RETS Manual Revision 9 Page 139 SECTION 7.O GASEOUS EFFLUENTS 828o

RETS Manual Revision 9 Page 140 7.0 GASEOUS EFFLUENTS RELEASE POINTS DESCRIPTION There are eleven monitored discharge points at BFN: a Reactor Building exhaust for each unit, the Radwaste Building Exhaust, two sets of Turbine Deck Roof Fans for each unit, and the Stack. The Reactor and Radwaste Exhausts exit the plant on the roof of the reactor building.

The Reactor Building Exhausts include exhaust from the refuel floor of the reactor buildings, exhaust from the Primary Containment Purge System, and exhaust from the turbine buildings. These discharge points are moni.tored by radiation monitors 1-,2-,3-RM-90-250.

The Radwaste Building Exhaust includes exhaust from the common radwaste building. This discharge point is monitored by radiation monitor RM-90-252.

There are nine roof fans on the roof of each unit's turbine building to provide building ventilation. These are generally used in the warmer months to control building temperature. For each unit, there are two radiation monitors. One of these monitors the exhaust through four of the fans (1-,2-RM-90-249 and 3-RM-90-251). The other monitors the exhaust through the remaining five fans (1-,2-RM-90-251 and 3-RM-90-249) ~

The common 600 foot plant stack receives the Condenser Offgas exhaust, the Filter Cubicle exhaust, the Steam Packing and Mechanical Vacuum exhaust, and the Standby Gas Treatment System (SBGTS) exhaust. The stack effluents are monitored by radiation monitors RM-90-147 and 148.

Figures 7.1 and 7.2 show the Offgas System, the Standby Gas Treatment System and normal building ventilation with effluent monitor locations.

828o

RETS Manual Revision 9 Page 141 7.1 RELEASE RATE LIMIT METHODOLOGY A dose rate {DTB, DS, or DTH) is calculated based on the design objective source term mix used in the licensing of the plant. Dose rates are determined for {1) noble gases and (2) iodines and particulates as described in Section 7.3.

The dose rate limits of interest are:

Total Body = 500 mrem/yr Skin ~ 3000 mrem/yr Maximum Organ ~ 1500 mzem/yr These limits are divided by the corresponding calculated dose rates described above:

Total Body Dose Rate Limit RTB(vent or stack) = ven or s ac Skin Dose Rate Limit RS(vent or stack) = ven or s ac )

Maximum Organ Dose Rate Limit RTH(vent or stack) =

These ratios represent how far above or below the guidelines the dose rate calculations were.

A total release rate, Q, for each nuclide type {noble gas or iodine/particulate) and release point (building vent or stack) is calculated, using the source term data in Table 7.2. Thus, four total release rates are calculated:

Qngv ~ Total noble gas release rate from building exhaust vents, Ci/s.

Qngs ~ Total noble gas release rate from main stack, Ci/s.

ipv ~ Total iodine and particulate release rate from building exhaust vents, Ci/s.

Qips ~ Total iodine and particulate release rate from main stack, Ci/s.

To obtain a release rate limit, r, for each nuclide type and release point, the total release rate, Q, for that nuclide type and release point is multiplied by the corresponding ratio, R:

For noble gases released from building vents:

rngv = RTBv Qngv.

= RSv Qng 828o

RETS Manual Revision 9 Page 142 where rngv = Calculated release rate limit for noble gases released from building vents.

RTSv = Ratio pf total body dose rate limit to total body dose rate for building vent releases, as calculated above.

Qngv = Total Table 7.2 noble gas release rate from building vents.

RSv Ratio of skin dose rate limit to skin dose rate for building vent releases, as calculated above.

For noble gases released from the stack:

rngs = Res Qngs> or

= Rss Qngs whichever is more restrictive, i.e., smaller.

where rngs Calculated release rate limit for noble gases released from the stack.

Res = Ratio of total body dose rate limit to total body dose rate for stack releases, as calculated above.

Qngs

"- Total Table 7.2 noble gas release rate from stack.

RSs Ratio of skin dose rate limit to skin dose rate for stack releases, as calculated above.

For iodines and particulates with half-lives greater than 8 days released from building vents:

ripv = RTHv Qipv where ripv = Calculated release rate limit for iodines and particulates released from building vents.

RTHv = Ratio of maximum organ dose rate limit to maximum organ dose rate for building vent releases, as calculated above.

<ipv = Total Table 7.2 iodine and particulate release rate from building vents.

For iodines and particulates with half-lives greater than 8 days released from the stack:

rips = RTHs Qips where rips Calculated release rate limit for iodines and particulates released from the stack.

RTHs = Ratio of maximum organ dose rate limit to maximum organ dose rate for stack releases, as calculated above.

Qips = Total Table 7.2 iodine and particulate release rate from stack.

828o

I RETS Nanual Revision 9 Page 143 The release rate limits, r, calculated for BPN using this methodology are:

Noble Gas Iodine and Particulate Stack r ~ 1 44E+01 Ci/s rips = 3.57E-05 Ci/s Building Vents rngv ~ 1.50E-01 Ci/s ripv 2 ~ 19E 06 Ci/s The values listed are used as administrative guidelines for operation.

828o

RETS Manual Revision 9 Page 144 7.2 GASEOUS EFFLUENT MONITOR INSTRUMENT SETPOINTS 7.2.1 Alarm/Tri Set pints Contxol 1.1:2 requires gaseous effluent monitors to have alarm/trip setpoints to ensure that the above dose rates are not exceeded. This section of the ODCM describes the methodology that will be used to determine these allowable values which are used to calculate setpoints. Figures 7.1 and 7.2 show the Offgas System, the Standby Gas Treatment System and normal building ventilation with effluent monitor locations.

The methodology for determining alarm/trip allowable values is divided into two major parts. The first consists of backcalculating from a dose rate to a release rate limit, in pCi/s, for each nuclide and release point. The methodology for the calculation of these release rate limits is given in Section 7.1. The second consists of using the release rate limits to determine the allowable values which are used to calculate the physical

~

settings on the monitors. The methodology for the calculation of the allowable values is given below. The monitor setpoints are calculated in the applicable Scaling and Setpoint Document.

7.2.2 Allowable Values To determine allowable values for gaseous effluent monitors, shown in Figures 7.1 and 7.2, the noble gas release rate limits are used.

The allowable values are calculated using the following equation r f A Allowable Value < + B

~here r release rate limit for stack or ground level, pCi/sec. The release rate limits used for the allowab1.e value calculation are 1.44E+07 pCi/sec for the stack and 1.50E+05 pCi/sec for the building vents.

fraction of the limits r which is allowed for the release mode (elevated or ground level).

NOTE: The sum of the f values for elevated and ground levels must be less than or equal to 1. This lowers the limits to ensure that the site dose rate limit vill not be exceeded if both the stack and the ground level release rate limits were reached simultaneously.

allocation factor. This is the portion of the release rate limit r which is assigned to the release point under consideration. This ensures that the ground level release rate limit will not be exceeded if all building vents were to reach their limit simultaneously. This is equal to 1 for the stack. The building vent release rate limit is divided among the ten vents based on the flow rates.

828o

RETS Manual Revision 9 Page 145 flow rate for the vent, cc/sec. Maximum flow rates are used to ensure conservative setpoints.

efficiency of the monitor, (pCi/cc)/cpm (or (pCi/cc)/cps for the stack monitor) background of the monitor, cpm (cps for the stack monitor)

The calculation of these setpoints are documented further in Technical Instruction (TI) 15 and the applicable Scaling and Setpoint Document, including the numerical values for each of the parameters described above.

828o

RETS Manual Revision 9 Page 146 7.3 GASEOUS EFFLUENTS DOSE RATES 7.3.1 Noble Gas Dose Rates Dose rates are calculated for total body and skin, due to submersion within a cloud of noble gases, using a semi-infinite cloud model. The use of a finite cloud model would result in calculated doses of 0 to 10 percent higher than those calculations using the semi-infinite cloud model for Browns Ferry Nuclear Plant (BFN). The dose rates are evaluated at the offsite locations with the highest expected concentrations, i.e.,

the nearest SITE BOUNDARY points in each sector (from Table 7.1) and at other locations expected to be the maximum exposure points.

The noble gas radionuclide mix used in this calculation is based on the design objective source term given in Table 7.2. Dispersion of the released radioactivity is handled as described in Section 7.9 using historical annual 'average meteorological data given in Table 7.3. No credit is taken for shielding by residence.

To calculate the noble gas dose rate from radiological effluents discharged from a given release point for any one of the potential maximum-exposure points, the equations given in Section 7.7.1 are used.

The total body and skin dose rate calculations are repeated for each release point. Dose rates for releases from all building vents are summed. The maximum stack and building vent total body and skin dose rates will be used to determine release rate limits.

828o

RETS Manual Revision 9 Page 147 7' ' I 131 I-133 Tritium and all Radionuclides in Particulate Form with Half-lives of Greater than 8 da s - Or an Dose Rate Dose rates are calculated for the critical organ, thyroid, of the critical age group, infant. Pathways considered are inhalation, ground contamination and milk ingestion. The dose rates're evaluated at the offsite locations with the highest expected concentrations, i.e., the nearest SITE BOUNDARY points in each of the 16 sectors (from Table 7.1) and at other locations expected to be the maximum exposure points. This calculation assumes that a (hypothetical) cow is at each of these locations. These cows are assumed, conservatively, to obtain 100 percent of their food from pasture grass.

The inhalation, ground contamination, and milk ingestion dose rates (in mrem/year) for the selected organ (thyroid) and age group (infant) are calculated using Equation 7.9 as described in Section 7.6.2. For determining the total thyroid dose rate from iodines and particulates:

DTH = DTHI + DTBG + DTHM (7.1) where:

~ total thyroid dose rate, mrem/yr.

DTHZ = thyroid dose rate due to inhalation, mrem/yr.

DTBG = total body dose rate due to ground contamination, mrem/yr. The thyroid dose rate is assumed to be equal to the total body dose rate for this pathway.

DTHM = thyroid dose rate due to pasture grass-cow-milk ingestion, mrem/yr.

The iodine and particulate dose rates are calculated for the design objective source term given in Table 7.2. The above dose rate calculation is repeated for each release point. Dose rates for releases from all building vents are summed. The maximum stack and building vent thyroid dose rates will be used to determine release rate limits.

828o

RETS Manual Revision 9 Page 148 7.4 DOSE NOBLE GASES 7.4.1 Monthl Noble Gas Dose Doses to be calculated are ganma and beta air doses due to exposure to a semi-infinite cloud of noble gases. The use of a finite cloud model would result in calculated doses of 0 to 10 percent higher than those calculations using the semi-infinite cloud model for BFN. Releases of Ar-41, Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 are considered. Because only these nuclides are considered, the dose is divided by'.9, to account for a possible 10 percent contribution of dose from other nuclides.

The dispersion factor used will be the highest annual-average y/Q based on 1977-1979 meteorological data (Table 7.3). Dispersion factors are calculated using the methodology described by Equation 7.11. Stack releases are considered elevated releases. All other vent releases will be treated as ground level.

No credit is taken for radioactive decay.

7.4.1.1 Monthl Conservative Model - Gamma Air Dose D~ = (x/Q) 0.9 106 3.15K+07 Qi DF~i (7.2) where:

ih( = gamma dose to air, mrad.

x/Q = highest annual-average relative concentration at or beyond the SITE BOUNDARY, s/m3 (from Table 7.1).

= 1.84E-06 for ground level releases,

= 2.08E-08 for elevated releases (stack).

0.9 = fraction of total gamma dose expected to be contributed by the assumed nuclides.

106 pCi/Ci conversion factor.

3.15E+07 = s/yr conversion factor.

= monthly release of radionuclide i, Ci.

DFyi gamma-to-air dose factor for radionuclide i, mrad/yr per pCi/m3 (Table 7.4).

828o

l 7,4.].2 D0 where:

DB Monthl

~

(x/Q) 0.9 Conservative Model 3.150+07 i beta dose to air, mrad.

Qi

- Beta DFSi Air Dose RETS Manual Revision Page 149 (7.3) 9 x/Q ~ highest annual-average relative concentration at or beyond the SITE BOUNDARY, s/m3 (from Table 7.1).

~ 1.84E-06 for ground level releases,

= 2.08E-08 for elevated releases (stack).

0.9 ~ fraction of total beta dose expected to be contributed by the assumed nuclides.

106 pCi/Ci conversion factor.

3.15E+07 = s/yr conversion factor.

Qi = monthly release of radionuclide i, Ci.

DFai = beta-to-air dose factor for radionuclide i, mrad/yr per pCi/m3 (Table 7.4).

7.4.1.3 Cumulative Dose - Noble Gas Cumulative calendar quarter doses are estimated by summing the doses calculated for each month in that quarter. Cumulative calendar year doses are estimated by summing the doses calculated for each month in that year.

7.4.1.4 Com arison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits to determine compliance.

828o

RETS Manual Revision 9 Page 150 7.5 CUMULATIVE DOSE - 1-131 I-133 TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8 DAYS Doses are to .be calculated for the infant thyroid from milk ingestion and for the child bone and teen gastrointestinal tract (GIT) from vegetable ingestion. Releases of H-3, I-131, and I-133 are considered for the milk pathway. H-3, Sr-89, Sr-90, Cs-134, and Cs-137 releases are considered for the vegetable pathway to the child bone. H-3, Co-58, and Co-60 releases are considered for the vegetable pathway to the teen GIT. The most critical real cow location is considered for the milk pathway and the most critical location with a home-use garden is considered for the vegetable pathways (see Table 7.1). The cow is assumed to graze on pasture grass for the whole year.

The highest annual-average X/Q and D/Q based on 1977-1979 meteorological data (Table 7.3) will be" used for ingestion pathway locations.

Dispersion values are calculated as described by Equations 7.12 and 7.13. Stack releases are considered elevated releases. All other vent releases will be treated as ground level.

No credit is taken for radioactive decay.

Doses are divided by 0.9 to account for a possible 10 percent contribution from other nuclides.

The maximum monthly organ dose is the highest of the three doses calculated.

828o

t RETS Manual Revision 9 Page 151 7,5.1 Monthl Conservative Model - Infant Th roid Dose from Milk

~In cation The monthly thyroid dose from milk ingestion is calculated using the following equation:

E(Q RCP') D/Q + (QT RCPT) Ã/Q 10 (7.4) where 0.9 (3.15E+07)

= monthly release of iodine nuclide i, Ci.

= monthly release of H-3, Ci.

= I-131 or I-133 pasture grass-cow-milk ingestion dose factor for infant thyroid, mrem/yr per pCi/m2-s. Dose factors are calculated as described in Section 7.8.1.

RCPT = H-3 pasture grass-cow-milk ingestion dose factor for infant thyroid, mrem/yr per pCi/m . The dose factor is calculated as described in Section 7.8.7.

D/Q = highest relative deposition rate for a location with an identified milk cow, m (from Table 7.1).

= 3.16E-10 for ground level releases,

= 2.30E-10 for elevated releases (stack).

X/Q = highest relative air concentration for a location with an identified milk cow, s/m (from Table 7.1).

= 1.47E-07 for ground level releases,

= 1. 69E-08 for elevated releases (s tack) .

0.9 = fraction of dose expected to be contributed by I-131, I-133 and H-3.

3.15E+07 = s/yr.

106 ~ pCi/Ci.

828o

RETS Manual Revision 9 Page 152 7.5.2 Monthl Conservative Model Child Bone Dose from Ve etable

~in estion The monthly bone dose from vegetable ingestion is calculated using the following equation:

Z (Qi DFi) D/Q + QT DFT X/Q 10 DBC where

= monthly release of Sr or Cs nuclide i, Ci.

= monthly release of H-3, Ci.

DF ~ Total vegetable ingestion dose factor to child bone for Sr-89, Sr-90, Cs-134 or Cs-137, mrem/yr per pCi./m 2 -s.

= RyFi + RgSi, where R~i is the dose factor for fresh leafy vegetables (as calculated in Section 7.8.5) and RgSi is the dose factor for stored vegetables (as calculated in Section 7.8.6).

DFT ~ Total vegetable ingestion dose factor for child bone for H-3, mrem/yr per pCi/m3.

= R~ + EST, where RqFT is the tritium dose factor for fresh leafy vegetables (as calculated in Section 7.8.11) and RySi is.

the tritium dose factor for stored vegetables (as calculated in Section 7.8.12).

D/Q = highest relative deposition rate for a location with an identified home use garden, m (from Table 7.1).

= 4.46E-09 for ground level releases,

= 1.13E-09 for elevated releases (stack).

X/Q = highest relative air concentration for a location with an identified home use garden, s/m (from Table 7.1).

= 1.57E-06 for ground level releases,

= 9.50E-09 for elevated releases (stack).

3,15K+07 = s/yr.

106 = pCi/Ci.

0.9 = fraction of total child bone dose expected to be contributed by H-3, Sr-89, Sr-90, Cs-134, and Cs-137.

828o

RETS Manual Revision 9 Page 153 7 ',3

~ ~ Monthl Conservative Model - Teen Gastrointestinal Tract (GIT)

Dose from Ve etable In estion The monthly teen GIT dose from vegetable ingestion is calculated using the following equation:

DGT

$ (Q i DF')i D/Q + QT DFT X/Q, 10 where

= monthly release of cobalt nuclide i, Ci.

QT ~,monthly release of H-3, Ci.

DFi = Total vegetable ingestion dose factor to the teen GIT for Co-58 or Co-60, mrem/yr per pCi/m -s.

= R~i + RqSi, where R~i is the dose factor for fresh leafy vegetables (as calculated in Section 7.8.5) and RgSi is the dose factor for stored vegetables (as calculated in Section 7.8.6).

DFT -" Total vegetable ingestion dose factor to the teen GIT for H-3, mrem/yr per pCi/m .

= RpFT + RgSZ, where RgFT is the tritium dose factor for fresh leafy vegetables (as calculated in Section 7.8.11) and EST is the tritium dose factor for stored vegetables (as calculated in Section 7.8.12).

D/Q = highest relative deposition rate for a location with an identified home use garden, m 2 (from Table 7.1).

= 4.46E-09 for ground level releases,

= 1.13E-09 for elevated releases (stack).

X/Q = highest relative air concentration for a location with an identified home use garden, s/m3 (from Table 7.1).

= 1.57E-06 for ground level releases,

= 9.50E-09 for elevated releases (stack).

3.15E+07 = s/yr.

106 ~ pCi/Ci.

0.9 = fraction of total teen GIT dose expected to be contributed by H-3, Co-58, and Co60.

828o

RETS Manual Revision 9 Page 154 7.5.4 Cumulative Doses Cumulative calendar quarter doses are estimated by summing the doses calculated for. each month in that quarter. Cumulative calendar year doses are estimated by sunming the doses calculated for each month in that year.

7.5.5 Total Nonthl Dose - Co arison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits to determine compliance.

828o

RE~S 'lanual Revision 9 Page 155 7.6 GASEOUS RADWASTE TREATNENT 7.6.1 Dose Pro 'ections Dose projections will be performed by averaging the calculated dose for the most recent month and the calculated dose for the previous month and assigning that average dose as the projection for the current month.

If the results of the dose projection indicate potential doses in excess of the monthly fraction of the annual dose limit, efforts will be made to minimize future releases.

7.6.2 S stem Descri tion A flow diagram for the GRTS is given in Figure 7.1. The system includes the subsystems that process and dispose of the gases from the main condenser air ejectors, the startup vacuum pumps, and the gland seal condensers. One gaseous radwaste treatment system is provided for each unit. The processed gases from each unit are routed to the plant stack for dilution and elevated release to the atmosphere. The air-ejector off-gas line of each unit and the stack are continuously monitored by radiation monitors.

828o

~ '.a.lua I Revision 9 Page 156 7.7 DOSE CALCULATIONS FOR REPORTING PURPOSES A complete dose analysis utilizing the total estimated gaseous releases for each calendar quarter will be performed and reported as required in ODCM Administrative Control 5.2. Methodology for this analysis is that which is described below, using the quarterly release values reported by the plant personnel. For iodine releases, it will be assumed that half the iodines released are organic iodipes, which contribute only to the inhalation dose. All real pathways and receptor locations (as identified in the most recent land use survey) are considered. In addition, actual meteorological data representative of each corresponding calendar quarter will be used to calculate dispersion factors as described in Section 7.9. Stack releases will be considered elevated releases.

Radwaste and reactor building releases will be considered split-level releases. Turbine building releases will be treated as ground level.

7.7.1 Noble Gas Dose All measured radionuclides are used to calculate gamma and beta air doses. The dose is evaluated at the nearest SITE BOUNDARY point in each sector and at other locations expected to be maximum exposure points using a semi-infinite cloud model. The use of a finite cloud model would result in calculated doses of 0 to 10 percent 'higher than those calculations using the semi-infinite cloud model for BFN.

Radioactive decay is considered in this calculation. The quarterly release is averaged over one year to obtain an average release rate.

828o

RETS

~lanua'evision 9

Page 1.57 7.7.1.1 Gamma Dose to Air Yn

= E Xni yi (7.7) 1 where:

DYn gamma dose to air for sector n,.mrad.

Xni air concentration of radionuclide i in sector n, pCi-year/m3. Air concentrations are calculated as described by Equation 7.11.

DFYi gamma-to-air dose factor for radionuclide i, mrad/yr per pCi/m3 (Table 7.4).

7.7.1.2 Beta Dose to Air Qn = 7 Xni Qi (7.8) 1 where:

Dgn = beta dose to air for sector n, mrad.

= air concentration of radionuclide i in sector n, pCi-yea'r/m3. Air concen rations are calculated as described by Eauation 7.'1.

DFBl = beta to air dose factor for radionuclide i, mrad/yr per pCi/m3 (Table 7.4).

0 828o

RETS ~lanual Revision 9 Page 158 7.7.2 Radioiodine Particulate and Tritium Maximum Or an Dose Organ doses 'due to radioiodine, particulate and tritium releases are calculated using the following equation:

Dorg= 3.17E-08 [E( /Q ERpi + /Q RGi + X/Q Rli)Qi + E(X/Q RPT)QT~ (7 '

i P P where:

Dora Organ dose, mrem.

3.1/E-08 = conversion factor, year/second.

x/Q Relative concentration for location under consideration, sec/m . Relative concentrations are calculated as described by Equation 7.12.

RPi ingestion dose factor for pathway P for each identified nuclide i (except tritium), m -mrem/year per pCi/second.

Ingestion pathways available for consideration include:

pasture grass-cow-milk ingestion stored feed-cow-milk ingestion pasture grass-goat-milk ingestion stored feed-goat-milk ingestion pasture grass-beef ingestion stored feed-beef ingestion fresh leafy vegetable ingestion stored vegetable ingestion Equations for calculating these ingestion dose factors are given in Sections 7.8.1 through 7.8.6.

D/Q = Relative deposition for location under consideration, m Relative deposition is calculated as described in Equation 7.13.

Rci Dose factor for standing on contaminated ground, m"-mrem/year per pCi/second. The equation for calculating the ground plane dose factor is given in Section 7.8.14.

RIi Inhalation dose factor, mrem/year per pCi/m . The equation for calculating the inhalation dose factor is given in Section 7.8.13.

828o

0 Rr i> .aanua Revision 9 Page 159 adjusted release for nuclide i for location under consideration, pCi. The initial release is adjusted to account for decay between the release point and the location, depending on the frequency of wind speeds applicable to that sector. Hence, the adjusted release is equal to the actual release decayed for an average travel time during the period.

9 f exp(-Xi x/uj )

j=l j Qio Z where Qio = initial average release for nuclide i over the period, pCi ~

fj = joint relative frequency of occurrence of winds in windspeed class j blowing toward this exposure point, expressed as a fraction.

Xi = radiological decay constant for nuclide i, sec x = downwind distance, meters.

uj = midpoint value of wind speed class interval j, m/s .

RPT ingestion dose factor for pathway P for tritium, mrem/year per pCi/m3. Ing'estion pathways available for consideration are the same as those listed above for Rpi. Equations for calculating ingestion dose factors for tritium are given in Sections 7.8.7 through 7.8.12.

QT adjusted release for tritium for location under consideration, pCi. Calculated in the same manner as Qi above.

828o

RE S .'lanual Revision 9 Page 160 7.7.3 Po ulation Doses For determining population doses to the 50-mile population around the plant, each compass sector is broken down into elements. These elements are defined in Table 7.5. For each of these sector elements, an average dose is cal'culated, and then multiplied by the population in that sector element. Dispersion factors are calculated for the midpoint of each sector element (see Table 7.5). For population doses resulting from ingestion, it is conservatively assumed that all food eaten by the average individual is grown locally.

The general equation used for calculating the population dose in a given sector element is:

Dosepop P RATIOp

• POPN

• AGE

• 0 F 001

• DOSEP (7.10)

P where RATIOP ratio of average to maximum dose for pathway P. (Average ingestion rates are obtained from Regulatory Guide 1.109, Table E-4.)

= 0.5 for submersion and ground exposure pathways, a shielding/occupancy factor.

= 1.0 for the inhalation pathway.

= 0.515, 0.515, 0.5, and 0.355 for milk, for infant, child, teen and adult, respectively. (It is assumed that the ratio of average to maximum infant milk ingestion rates is the same as that for child.)

= 1.0, 0.90, 0.91, 0.86 for beef ingestion, for infant, child, teen and adult, respectively.

= 1.0, 0.38, 0.38, 0.37 for vegetable ingestion, for infant, child, teen and adult, respectively. (It is assumed that the average individual eats no fresh vegetables, only stored vegetables.)

POPN = the population of the sector element, persons (Table 7.6).

AGE = fraction of the population belonging to each age group.

= 0,015, 0.168, 0.153, 0.665 for infant, child, teen and adult, respectively (fractions taken from NUREG/CR-1004, Table 3.39).

0.001 = conversion from mrem to rem.

DOSEp the dose for pathway P to the maximum individual at the location under consideration, mrem. For ingestion pathways, this dose is multiplied by an average decay correction to account for decay as the food is moved through the food distribution cycle. This average decay correction, ADC, is defined as:

828o

RETS Manual Revision 9 Page 161 ADC = exp(-Kit), for milk and vegetables, where decay constant for nuclide i, seconds.

= distribution time for food product under consideration (from Regulatory Guide 2.109, Table D-l).

= 1.21E+06 seconds (14 days) for vegetables.

= 3.46E+05 seconds (4 days) for milk.

exP(-'hit) Kitch for meat, 1 exp(-X 1 cb) where Xi = decay constant for nuclide i, seconds.

= additional distribution time for meat, over and above the time for slaughter to consumption described in Section 7.8.3, 7 days (from Regulatory Guide 1.109, Table D-2).

= time to consume a whole beef, as described in Section 7.8.3.

For beef ingestion, the additional factors in the calculation of ADC negate the integration of the dose term over the period during which a whole beef is consumed, for the calculation of population dose. This assumes that the maximum individual freezes and eats a whole beef, but the average individual buys smaller portions at a time.

Population doses are summed over all sector elements to obtain a total population dose for the 50-mile population.

7.7.4 Re ortin of Doses The calculated quarterly doses and calculated population doses described in this section are reported in the Semiannual Radioactive Effluent Release Report as described in ODCN Administrative Control 5.2 828o

RETS .'manual Revision 9 Page 162 7.8 GASEOUS DOSE FACTOR E UATIONS 7.8.1 Pasture 'Grass-Cow-GoatMilk In estion Dose Factors (m2-mrem/year per pCi/sec)

Xi fm)fp r(l~xp(-step) ) Biv(l~xp( ~itb) )

RCPi = 10 DFLiaoUapFmi<fexP( +

p E L where:

106 conversion factor, pCi/pCi.

DFLiao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).

Uap = milk ingestion rate for age group a, L/year.

Fmi = transfer factor for nuclide i from animal's feed to milk, days/L (Table 6.2).

= animal's consumption rate, kg/day.

Xi decay constant for nuclide i, seconds " (Table 6.2).

tfm ~ transport time from milking to receptor, seconds.

fp = fraction of time animal spends on pasture, dimensionless.

r = fraction of activity retained on pasture grass, dimensionless.

XE the effective decay constant, due to radioactive decay and weathering, seconds 1, equal to Xi + X .

weathering decay constant for leaf and plant surfaces, seconds l.

tep = time pasture is exposed to deposition, seconds.

Yp = agricultural productivity by unit area of pasture grass, kg/m2.

Biv = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

tb = time period over which accumulation on the ground is evaluated, seconds.

= effective surface density of soil, kg/m2.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

828o

RETS Manual Revision 9 Page 163 7.8.2 Stored Feed-Cow/Goat-Nilk En estion Dose Factors (m2-mrem/year per pCi/second)

~itfm)

(1-exP( Xitcsf))

CSi = 1O D iao Uap mi Qf s P(

csf i r(l~xp(-XEtesf)) Biv(1-exp(-X1 tb))

+

Ysf >E P Ai where:

106 conversion factor, pCi/pCi.

DFLiao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).

Uap = milk ingestion rate for age group a, L/year.

Fmi = transfer factor for nuclide i from animal's feed to milk, days/L (Table 6.2).

Qf = animal's consumption rate, kg/day.

fs = fraction of time animal spends on stored feed, dimensionless.

'Ai decay constant for nuclide i, seconds (Table 6.2).

tfm = transport time from milking to receptor, seconds.

tcsf = time between harvest of stored feed and consumption by animal, seconds.

= fraction of activity retained on pasture grass, dimensionless.

the effective decay constant, due to radioactive decay and weathering, seconds , equal to Xi + Xw.

weathering decay constant for leaf and plant surfaces, seconds l.

tesf = time stored feed is exposed to deposition, seconds.

Ysf = agricultural productivity by unit area of stored feed, kg/m .

Biv = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

tb = time period over which accumulation on the ground is evaluated, seconds.

= effective surface density of soil, kg/m2.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

828o

RE:S ~1anual Revision 9 Page 164 7.8.3 Pasture Grass-Beef In estion Dose Factors (m2-mrem/year per pCi/second)

(1-exp(-X t b))

R~i 1O6 DFLiao Uam Ffi Qf i

cb exP(-Kits) r(l~xP(-XEtep)) Biv(lmxP( Xitb))

fp Yp XE P Xi where:

106 conversion factor, pCi/pCi.

DFLiao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).

Uam = meat ingestion rate for age group a, kg/year.

Ffi = transfer factor for nuclide i from cow's feed to meat, days/kg (Table 6.2.).

Qf = cow's consumption rate, kg/day.

Xi decay constant for nuclide i, seconds (Table 6.2).

tcb = time for receptor to consume a whole beef, seconds.

ts = transport tlat from slaughter to consumer, seconds.

fp = fraction of time cow spends on pasture, dimensionless.

r = fraction of activity retained on pasture grass, dimensionless.

'AE the effective decay constant, due to radioactive decay and weathering, seconds , equal to Xi + Q.

X weathering decay constant for leaf and plant surfaces, seconds 1.

tep = time pasture is exposed to deposition, seconda.

Yp = agricultural productivity by unit area of pasture grass, kg/m .

Biv = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

= time over which accumulation on the ground i's evaluated, seconds.

P b

i

= e ffec tive surf ace dens ty of soil, kg/m2.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

828o

t 7.8,4 Stored Feed-Beef In estion (m2-mrem/year per pCi/second)

~NSi = 1 DFLiao Uam Ffi Qf Dose Factors (1-exP( Xitcb)

. <<p(-Kit )

RETS Page Manual Revision 165 9

(I e P( ~i csf)) r(l-exP(-XEtesf)) Biv(l-exp(-), tb))

s +

~i tcsf Ysf P )i where:

106 conversion factor, pCi/pCi.

DFLiao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).

Uam = meat ingestion rate for age group a, kg/year.

Ffi = transfer factor for nuclide i from cow's feed to meat, days/kg (Table 6.2).

Qf = cow's consumption rate, kg/day.

decay constant for nucl,ide i, seconds (Table 6.2).

tcb = time for receptor to consume a ~hole beef, seconds.

ts = transport time from slaughter to consumer, seconds.

fs = fraction of time cow spends on stored feed, dimensionless.

cs time between harvest of stored feed and consumption by cow, seconds.

= fraction of activity retained on pasture grass, dimensionless.

tesf = time stored feed is exposed to deposition, seconds.

Ysf = agricultural productivity by unit area of stored feed, kg/m 2 .

the effective decay constant, due to radioactive decay and weathering, seconds , equal to Xi + +.

X weathering decay constant for leaf and plant surfaces, seconds Biv = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

tb = time over which accumulation on the ground is evaluated, seconds.

P = effective surface density of soil, kg/m 2 .

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

828o

RETS Manual Revision 9 Page 166 7.8.5 Fresh Leaf Ve etable In estion Dose Factors (m2-mrem/year. per pCi/second) ~

'( (->> ))

where:

106 conversion factor, pCi/pCi.

DF iao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).

decay constant for nuclide i, seconds"1 (Table 6.2).

thc = average time between harvest of vegetables and their consumption and/or storage, seconds.

= consumption rate of fresh leafy vegetables by the receptor in age group a, kg/year.

fL = fraction of fresh leafy vegetables grown locally, dimensionless.

r = fraction of deposited activity retained on vegetables, dimensionless.

the effective decay constant, due to radioactive decay and weathering, seconds

~Xi+A decay constant for removal of activity on leaf and plant surfaces by weathering, seconds l.

te = exposure time in garden for fresh leafy and/or stored vegetables, seconds.

Yf = vegetation areal density for fresh leafy vegetables, kg/m2.

Biv = transfer factor for nuclide i from soil to vegetables, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

tb = time period over which accumulation on the ground is evaluated, seconds.

= effective surface density of soil, kg/m2.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

828o

RETS ilanual Revision 9 Page 167 7.g.6 Stored Ve etable In estion Dose Factors m2-mrem/year per pCi/second)

(l-e(-),itsv))

Vsi = 1 FLiao exP( Lithe) "Sa g sv r(1-e(-%Etc) ) Biv(1~(-) 1 tb) )

+

Ysv XE P 'Ai where:

1O6 conversion factor, pCi/pCi.

D- Liao = inges ion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).

Xi decay constant for nuclide i, seconds 1 (Table 6.2).

thc = average time between harvest of vegetables and their consumption and/or storage, seconds.

USa = consumption rate of stored vegetables by the receptor in age group a, kg/year.

fg = fraction of stored vegetables grown locally, dimensionless.

tsv = time between storage of vegetables and their consumption, seconds.

= fraction of deposited act'vity retained on vegetables, dimensionless.

the effective decay constant, due to radioactive decay and weatnering, seconds

+ Q decay constant for removal of activity on leaf and plant surfaces by weathering, seconds

= exposure time in garden for fresh leafy and/or stored vegetables, seconds.

"sv = vegetation areal density for stored vegetables, kg/m2.

Biv = transfer factor for nuclide i from soil to vegetables, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

tb = time period over which accumulation on the ground is evaluated, seconds.

= effective surface density of soil, kg/m2.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

RE:5 .'!anuai Revision 9 Page 168 7.8.7 Tritium-Pasture Grass-Cow/Goat-Nilk Dose Factor (mrem/year per pCi/m )

RCTP = 10 10 DFLTao FmT Qf Uap [0.75(0.5/H)] fp exp(-XTtfm) where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).

FmT = transfer factor for tritium from animal's feed to milk, days/L (Table 6.2).

Qf = animal's consumption rate, kg/day.

= milk ingestion rate for age group a, L/year.

o.h = the fraction of total feed that is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m 3..

fp = fraction of time animal spends on pasture, dimensionless.

decay constant for tritium, seconds (Table 6.2).

tfm = transport time from milking to receptor, seconds.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

828o

RE:S;".anua'evision 9

Page 169 7.8.8 Tritium-Stored Feed-Cow/Goat-Nilk Dose Factor (mrem/year per pCi/m )

(1-exP( XTtcsf))

RCTS = 10 106 DFLTao FmT Qf Uap [0.75(0.5/H)~ s exp(-'ATtfm) where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).

FmT = transfer factor for tritium from animal's feed to milk, days/L (Table 6.2).

= animal's consumption rate, kg/day.

= milk ingestion rate for age group a, L/year.

= the fraction of total feed that is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m3.

fs = fraction of time animal spends on stored feed, dimensionless.

decay constant for tritium, seconds 1 (Table 6.2).

tcsf = time between harvest of stored feed and consumption by animal, seconds.

tfm = transport time from milking to receptor, seconds.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

828o

.e R" ..an ua 1

~

e ~

Revision 9 Page 170 7.8.9 Tritium-Pasture Grass-Beef Dose Factor (mrem/year per pCi/m )

R~ = 103 106 DFLTao FfT Qf Uam [0.75(0.5/H)] fp exp(-its)

(1-exP(-step)) . (1-exP(-XTtcb))

"T tep XT tcb where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).

FfT = transfer factor for tritium from cow's feed to meat, days/kg (Table 6.2).

Qf = cow's consumption rate, kg/day.

Uam = meat ingestion rate for age group a, kg/year.

0. 75 = the fraction of total feed that is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m3.

fp = fraction of time cow spends on pasture, dimensionless.

XT decay constant for tritium, seconds (Table 6.2).

ts = transport time from slaughter to consumer, seconds.

tep = time pasture is exposed to deposition, seconds.

tcb = time for receptor to consume a whole beef, seconds.

~VOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

828o

RETS lanual Revision 9 Page 171 7.8.10 Tritium-Stored Feed-Beef Dose Factor (mrem/year per pCi/m )

RNTS = 103 106 DFLTao FfT Qf "am ~0 75( /")~ s exp(-its)

(1-exP( ~Ttcsf)) (1-exP( XTtcb))

XT tosf XT tcb where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).

FfT = transfer factor for tritium from cow's feed to meat, days/kg (Table 6.2).

Qf = cow's consumption rate, kg/day.

U = meat ingestion rate for age group a, kg/year.

0. 75 = the fraction of total feed that is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m 3..

C 5

= fraction of time cow spends on stored feed, dimensionless.

XT decay constant for tritium, seconds 1 (Table 6.2).

ts = transport time from slaughter to consumer, seconds.

tcsf = time between harvest of stored feed and consumption by animal, seconds.

tcb = time for receptor to consume a whole beef, seconds.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

828o

RETS ~ianna Revision 9 Page 172 7.8.11 Tritium-Fresh Leaf Ve etable Dose Factor (mrem/year per pCi/m ) 1 REF = 10 10 DFLTao I.0.75(0.5/H)J UFLa fL exP(-XTthc) where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).

0. 75 = the fraction of total vegetation that is water.

0.5 = the ratio of the specific activity of the vegetables water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m 3..

= consumption rate of fresh leafy vegetables by the receptor in age group a, kg/year.

fL = fraction of fresh leafy vegetables grown locally, dimensionless.

XT decay constant for tritium, seconds 1 (Table 6.2).

thc = time between harvest of vegetables and their consumption and/or storage, seconds.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

828o

RE S

.'lanua'evision 9

Page 173 7,8.12 Tzitium-Stored Ve etables Dose 'Factor (mrem/year per pCi/m )

(1-exp(-XTt ))

RVTS = 10 106 DFLTao ~ '0.5/H)] USa g exP(-XTthc) where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose convez'sion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).

0.75 = the fraction of total vegetation that is water.

0.5 = the ratio of the specific activity of the vegetation water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m 3..

USa = consumption rate of stored vegetables by the receptor in age group a, kg/year.

fg = fraction of stored vegetables grown locally, dimensionless.

XT decay constant for tritium, seconds (Table 6.2).

tsv = time between harvest of stored vegetables and their consumption and/or storage, seconds.

ime between harvest of vegetables and their storage, seconds.

NOTE: Factors defined above which do not reference a table fo" their numerical values, are listed in Table 6.3.

828o

RE, S .'!anuai Revision 9 Page 174 7.8.13 Inhalation Dose Factors (mrem/year per pCi/m )

Rll = DFAiao BRa 10 6 where:

DFAiao = inhalation dose conversion factor for nuclide i, age group a and organ o, mrem/pCi (Table 7.7).

BR = breathing rate for age group a, m /year (Table 6.3).

10 = conversion factor, pCi/pCi.

7.8.14 Ground Plane Dose Factors (m2-mrem/year per pCi/second)

RGi = DFGio (1/Xi) 10 8760 [1 exp( Xitb)~

where:

DFGio = dose conversion factor for standing on contaminated ground for nuclide i and organ o (total body and skin), mrem/hr per pCi/m (Table 6.6).

'Ai decay constant of nuclide i, seconds (Table 6.2).

106 conversion factor, pCi/pCi.

8760 = conversion factor, hours/year.

tb = time period over which the ground accumulation is evaluated seconds (Table 6.3).

828o

RE 5 ~manual Revision 9 Page 175 7.9 DISPERSION METHODOLOGY Dispersion factors are calculated for radioactive effluent releases using hourly average meteorological data collected onsite.

Meteorological data for ground level releases consist of windspeed and direction measurements at 10m and temperature measurements of 10m and 45 m.

Hourly average meteorological data for the ground level portion of a split level release consist of wind speeds and directions measured at the 10m level and temperature measurements at 10m and 45m. The elevated portion of the split level release uses wind speeds and directions measured at the 46m level and temperature measurements at 45m and 90m.

Raw meteorological data for the elevated releases consist of windspeed and directions measured at 93m. Stability class D is assumed to persist during the entire period for elevated releases, except for the dose calculations described in Section 7.7 when all stability classes will be used to evaluate the elevated results.

Meteorological data are expressed as a joint-frequency distribution of wind speed, wind direction, and atmospheric stability for each release level (ground, split and elevated). The joint-frequency distributions which represen the historical meteorological data for the period January 1977 to December 1979 are given in Table 7.3.

The wind speed classes that are used are as follows:

Number (0.3 0.13 0.3-0.6 0.45 0.7-1.5 1.10 1.6-2.4 1 ~ 99 2.5-3.3 2.88 3.4-5.5 4.45 5.6-8.2 6.91 8.3-10.9 9.59

>10.9 10.95 The stability classes that will be used are the standard A through G classifications. The stability classes 1-7 will correspond to A=1, B=2, ~ ~ ~ , G=7 ~

828o

0 RETS Manual Revision 9 Page 176 A sector-average dispersion equation consistent with Regulatory Guide 1.111 is:used. The dispersion model considers plume depletion (using information from Figure 7.3), and building wake effects. Terrain effects on dispersion are not considered except for reducing the effective height of an elevated release by the terrain height.

7.9.1 Annual Avera e Air Concentration X (pCi-year/m )

Air concentrations of nuclides at downwind locations are calculated using the following equation:

9 7 g(2/~)1/2 exp(-Xix/uj) exp(-he /2ozk2) 106 3.17E-08 (7.11) j=l k=1 Ezku j (2~/n) where:

fjkk = joint relative frequency of occurrence of winds in windspeed class j, stability class k, blowing toward this exposure point, expressed as a fraction.

Q>> = amount released of radionuclide i, Ci.

p = fraction of radionuclide remaining in plume (Figure 7.3).

Z zkk = vertical dispersion coefficient for stability class k which includes a building wake adjustment,

= (ozk2 + cA<<)lt2, or = 43 crzk, whichever is smaller (for ground level releases).

where oz k is the vertical dispersion coeffic.'ent for stabil.'ty class k (m) (Figure 7.4),

c is a building shape factor (c=0.5),

A is the minimum building cross-sectional area (2400 m2).

u ~ = midpoint value of wind speed class interval j, m/s.

x = downwind distance, m.

n = number of sectors, 16.

Xi = radioactive decay coefficient of radionuclide i, s 2@x/n = sector width at point of interest, m.

he = effective release height, m. The effective release height is calculated as described in Section 7.9.4.

106 = conversion factor, pCi per Ci.

3.17E-08 = conversion factor, years per second.

828o

RETS Manual Revision 9 Page 177 7.9.2 Relative Concentration

~ ~

X/Q (sec/m )

Relative concentrations of nuclides at downwind locations are calculated using the following equation:

9 7 x/Q = g g (2/~)1/2 exp( he2/2ozk2) (7.12) j=l k=1 Ezk uj (2~/n) where:

= joint relative frequency of occurrence of winds in windspeed class j, stability class k, olowing toward this exposure point, expressed as a fraction.

Ezk vertical dispersion coefficient for stability class k which includes a building wake adjustment, (ozk" + cA/e)1/2,

= l3 ozk, whichever is smaller (for ground level releases).

where ozk is the vertical dispersion coefficient for stability class k (m) (Figure 7.4),

c is a building shape facto" (c=O.S),

A is the minimum building cross-sectional area (2400 m2).

uj = midpoint value of wind speed class interval j, m/s.

x = downwind distance, m.

n = number of sectors, 16.

2m/n = sector width at point of interest, m.

he = effective release height, m. The effective release height is calculated as described in Section 7.9.4.

7.9.3 Relative Dis ersion D/Q (m )

Relative deposition of nuclides at downwind locations is calculated using the following equation:

D/Q = E fjk DR (7.13) j~l k~1 (2m/n) where:

fk s joint relative frequency of occurrence of winds in windspeed class j and stability class k, blowing toward this exposure point, expressed as a fraction.

DR = relative deposition rate, m (from Figure 7.5). The choice of figures is governed by the effective release height calculation described in Section 7.9.4. A linear interpolation is used for effluent release heights that fall in between the given curves.

x = downwind distance, m.

n = number of sectors, 16.

2'/n sector width at point of interest, m.

828o

RETS manual Revision 9 Page 178 7.9.4 Effective Release Hei ht For effluents exhausted from release points that are higher than twice the height of adjacent structures (elevated releases) the effective release height is determined by the following equation, consistent with Regulatory Guide 1.111 he = hs + hpr ht.,.c where:

c = downwash correction factor for low relative exit velocity, 3(1.5-Wo/u)d, where Wo = the vertical plume exit velocity, m/s.

u = mean wind speed at the height of the release, m/s.

d = inside diameter of the release point, m.

NOTE: If c is less than zero, it is set equal to zero.

hpr = plume rise above the release point, m.

hs = physical height of release point, m.

ht = maximum terrain height between release point and receptor location, m.

For effluents released from points less than the height of adjacent structures, a ground level release is assumed (he = 0).

For effluents released from points at the level of or above adjacent structures, bu't lower than elevated release points, releases are treated as follows:

Case 1 elevated if Wo/u ) 5.

Case 2 ground level (he = 0) if Wo/u l.

Case 3 split level if 1 < wo/u < 5.

Under Case 3 a split level dispersion approach is implemented using a model that requires for each release point two JFDs, one for elevated releases and one for ground level releases. The summation of the elevated and ground level JFDs account for the total period of record.

Releases are considered to be elevated 100(1-Et) percent of the time and ground level 100 Et percent of the time where the entrainment coefficient, Et, is defined by Et = 2 58 1 58{Wo/u) for 1 < Wo/u < 1.5 Et = 0' 0'06{Wo/u) for 1.5 < Wo/u < 5 828o

REIS .'lanua I Revision 9 Page 179 Table 7.1 BFN - OFFSITE RECEPTOR LOCATION DATA GROUND LEVEL ELEVATED DISTANCE Elev above X/Q D/Q X/Q D/Q POINT from plant plant grade (s/m ), (1/m ) (s/m ) (1/m )

(m) (m)

Site Boundary 1525 N 7 1.60E-06 5 '4E-09 N/A N/A Site Boundary 1300 NNE 4 7.88E-07 1.97E-09 N/A N/A Site Boundary 1250 NE 7 4.52E-07 1.56E-09 N/A N/A Site Boundary 1450 ENE 0 7.30E-07 2.92E-09 N/A iN/A Site Boundary 1375 E 0 8.24E-07 4.04E-09 N/A iN/A Site Boundary 1575 ESE 0 4.56E-07 3.28E-09 N/A N/A Site Boundary 5600 SE -6 7.61E-08 3.63E-10 N/A N/A Site Boundary 2875 SSE -6 4.86E-07 1.77E-09 N/A N/A Site Boundary 2550 S -6 8 '7E-07 2.24E-09 N/A iN/A Site Boundary 2425 SSW -6 1.08E-06 2.92E-09 N/A N/A Site Boundary 2300 SW -6 6.87E-07 1.75E-09 N/A N/A Site Boundary 2500 WSW -6 6.38E-07 1.14E-09 N/A N/A Site Boundary 2550 W -6 6.70E-07 1.25E-09 N/A N/A Site Boundary 3325 WNW -6 3.69E-07 9.07E-10 N/A N/A Site Boundary 2275 NW -6 1.69E-'06 4.92E-09 N/A N/A Site Boundary 1650 NhV -6 1.84E-06 5.29E-09 N/A N/A Air Dose Poin: 6100 NW -6 N/A N/A 2.08E-OB 4.75E-10 Garden 1830 NNW 34 1.57E-06 4.46E-09 N/A 1. 13E<<09 Garden 4437 E 19 N/A N/A 9.50E-09 N/A Milk Cow 8045 N 34 1.47E-07 3.16E-10 N/A 2.30E-10 Milk Cow 10975 NNW 34 N/A N/A 1.69E-08 N/A NOTE: For quarterly dose calculations, doses will also be calculated for all locations identified in the most recent land use census, and for any additional points deemed necessary.

828o

Ri:S Manual Revision 9 Page 180 Table 7.2 EXPECTED ANNUAL ROUTINE ATMOSPHERIC RELEASES FROM ONE UNIT AT BFN Buildin Vents (Ci/ r/Unit) Stack (Ci/ r/Unit)

Reactor Radwaste Turbine Gland Complex Building Building Seal and

~Isoto e Vent Vent Vent ~of! es MVP Kr-85m 6E+0 2E+0 1.66E+4 O.OE+0 Kr-85 6.3E+2 Kr-87 6E+0 < 1 9.5E+1 7.47E+2 O.OE+0 Kr-88 9E+0 < 1 1.02E+2 1.35K+4 O.OE+0 Kr-89 1E+0 3.4E+1 5.03K+2 4.10E+3 O.OE+0 Xe-131m 3.09E+2 O.0K+0 Xe-133m QE+0 6.0E+1 OE+0 8.51E+2 O.OE+0 Xe-133 1.03E+2 2.94E+2 5.81E+2 9.47E+4 3.0E+2 Xe-135m 1.11E+2 6.67E+2 4.64E+2 9.17E+2 O.OE+0 Xe-135 1.73K+2 3.28E+2 6.72E+2 5.99E+2 2.0E+2 Xe-137 7.8E+1 1.13E+2 3.86E+2 5.04E+3 O.OE+0 Xe-138 1.2E+1 2E+0 1.18E+3 3.15E+3 O.OE+0 I-131 I 5.94E-2 5.0E-3 1.56E-2 4.1E-3 8.5E-3 I-132 I 5.94E-1 5.0E-2 1.79E-1 4.69E-2 9.73E-2 I-133 I 2.97E-1 2.5E-2 1.23E-1 3.23E-2 6.71E-2 I-134 I 1.49E+0 1.25E-1 2.67E-2 7.0E-3 1.45E-2 I-135 I 5.94E-1 5.0E-2 1.23E-1 3.23E-2 6.71E-2 I-131 0 3.16E-2 2.9E-2 6.5E-3 3.32E-2 2.74E-1 I-132 0 3.16E-1 2.9E-1 7.44E-2 3.80E-1 3.14E+0 I-133 0 1.58E-1 1. 45E-1 5.13E-2 2.62E-1 2.16E+0 I-134 0 7.90E-1 7 '5E-1 1.11E-2 5.68E-2 4.69E-I I-135 0 3.16E-1 2.90E-1 5.13E-2 2.61E-1 2. 16E+0 Cr-51 3E-3 9E-4 lE-3 1E-4 O.OE+0 Mn-54 3E-3 5E-3 2E-3 4E-5 O.OE+0 Co-58 2E-3 4E-4 9E-5 2E-5 O.OE+0 Fe-59 lE-4 8E-4 4F-4 2E-4 O.OE+0 Co-60 3E-2 6E-3 3E-3 1E-5 O.OE+0 Zn-65 3E-3 2E-4 4E-4 9E-5 O.OE+0 Sr-89 lE-2 3E-1 O.OE+0 Sr-90 "E-3 4E-3 0.0E+0 Nb-95 3E-4 2E-4 9E-6 SE-5 O.OE+0 Zr-95 1E<<4 1E-4 SE-6 SE-5 O.OE+0 RQ-103 3E-5 1E-4 2E-4 1E-4 O.OE+0 Ag-110m 7E-6 O.OE+0 Sb-124 3E-5 3E-4 6E-5 SE-5 O.OE+0 Cs-134 5E-3 3E-4 5E-4 2E-5 O.OE+0 Cs-136 2E-3 5E-5 1E-4 9E-8 O.OE+0 Cs-137 7E-3 4E-4 2E-3 7E-4 0.0E+0 Ba-140 4E-3 5E-4 2E-2 SE-3 O.OE+0 Ce-141 4E-4 2E-4 2E-3 2E-5 O.OE+0 Ce-144 5E-6 4E-6 O.OE+0 Ar-41 2.5E+1 OE+0 OE+0 OE+0 O.OE+0 C-14 OE+0 OE+0 OE+0 9.5E+0 O.OE+0 H-3 OE+0 9.5E+0 OE+0 OE+0 O.OE+0

• Not available.

I denotes nonorganic iodine (elemental, particulate, HIO), 0 denotes organic iodine.

828o

RETS ilanual Revision 9 Page 181 Table 7.3 (1 of 22)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class A (Delta-T( -1.9 deg>ees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- , 7.5- 12.5- 18.5-1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.0 0.0 0.0 0.04 0.12 0.05 0.0 0.0 0. 21 NNE 0.0 0.0 0.0 0.05 0.19 0.10 0.0 0.0 0.34 NE 0.0 0.0 0.0 0.04 0.06 0.0 0.0 0.0 0.10 ENE 0.0 0.0 00 001 00 00 0.0 0.0 0.01 E 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.01 ESE 0.0 0.01 0.11 0.17 0.02 0.0 0.0 0.0 0.31 SE 0.0 0.03 1.11 0.40 0.02 0.0 0.0 0.0 1.56 SSE 0.0 0.04 0.52 0.10 0.02 0.0 0.0 0.0 0.68 S 0.0 0.01 0.38 0.11 0.04 0.0 0.0 0.0 0 . 5'4 SSW 0.0 0.0 0.04 0.05 0.01 ,0.0 0.0 0.0 0 . 10 SW 0.0 0.0 0.05 0.04 0.0 0.0 0.0 0.0 0 . 09 WSW 0.0 0.0 0.04 0.07 0.04 0.0 0.0 0.0 0.'

0.0 0.0 0.01 0.05 0.05 0.01 0.0 0.0 0 . 12 WNW 0.0 0.0 0.02 0.03 0.09 0.06 0.0 0.0 0 . 20 NW 0.0 0.0 0.0 0.02 0.17 0.11 0.0 0.0 0 . 30 NNW 0.0 0.0 0.01 0.01 0.06 0.09 0.02 0.0 0 . 19 Sub-total 0.0 0.09 2.29 1.19 0.90 0.42 0.02 0.0 4.91 Total hours of valid stability observations 25935 Total hours of Stability Class A 1262 Total hours of valid wind direction-wind speed-Stability Class A- 1259 Total hours calm 0 All columns and calm total 100 percent of joint valid observations Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed = 6.8 mph 828o

RE:S .'!anuai Revision 9 Page 182 Table 7.3 (2 of 22)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stab'ility Class B (-1.9 < Delta-T< -1. 7 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- ,. 7.5- 12.5- 18.5-1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total NN 0.0 0.0 0.05 0.09 0.30 0.04 0.01 0.0 0.49 NNE 0.0 0.0 0.05 0.07 0.27 0.05 0.0 0.0 0.44

'E 0.0 0.0 0.04 0.02 0.09 0.01 0.0 0.0 0.16 ENE 0.0 0.01 0.01 0.01 0.01 0.0 0.0 0.0 0.04 E 0.0 0.0 0.02 0.01 0.0 0.0 0.0 0.0 0.03 ESE 0.0 0.02 0.10 0.04 0.0 0.0 0.0 0.0 0.16 SE 0.0 0.'13 0.64 0.09 0.02 0.0 0.0 0.0 0.88 SSE 0.0 0.09 0.31 0.02 0.01 0.0 0.0 0.0 0.43 S 0.0 0.05 0.42 0.07 0.02 0.0 0.0 0.0 0.56 SSW 0.0 0.02 0.07 0.01 0.0 0.0 0.0 0.0 0.10 SW 0.0 0.0 0.17 0.02 0.0 0.0 0.0 0.0 0.19 WSW 0.0 0.0 0.11 0.13 0.05 0.01 0.0 0.0 0.30 W 0.0 0.02 0.04 0.17 0.17 0.03 0.0 0.0 0.43 WNW 0.0 0.0 0.07 0.11 0.23 0.08 0.04 0.0 0.53 NW 0.0 0.0 0.01 0.07 0.27 0.13 0.01 0.0 0.49 NNW 0.0 0.0 0.0 0.07 0.19 0.12 0.0 0.0 0.38 Sub-total 0.0 0.34 2.11 1.00 1.63 0.47 0.06 0.0 5.61 Total hours of val'd stability observations 25935 Total hours of Stability Class B 1445 Total hours of valid wind direction-wind speed-Stability Class B 1440 Total hours calm 0 All columns and calm total 100 percent of joint valid observations Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed = 7.2 mph 828o

RETS .'lanual Revision 9 Page 183 Table 7.3 (3 of 22)

JO NT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Sta>ility Class C (-1.7 < Delta-T< -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- . 7.5- 12.5- 18.5-1.4 3,4 5.4 7.4 12.4 18.4 24.4 )24.5 Total N 0.0 0.01 0.08 0.11 0.21 0.02 0.0 0.0 0.43 NNE 0.0 0.01 0.07 0.09 0.17 0.20 0.0 0.0 0.36 NE 0.0 0.0 0.03 0.08 0.05 0.0 0.0 0.0 0.16 ENE 0.0 0.0 0.02 0.02 0.0 0.0 0.0 0.0 0.04 E 0.0 0.0 0.03 0.02 0.0 0.0 0.0 0.0 0.05 ESE 0.0 0.01 0.05 0.02 0.0 0.0 0.0 0.0 0.08 SE 0.0 0.17 0.29 0.09 0.01 0.0 0.0 0.0 0.56 SSE 0.0 0.12 0.17 0.04 0.01 0.0 0.0 0.0 0.34 S 0.0 0.11 0.25 0.04 0.02 0.0 0.0 0.0 0.42 SSW 0.0 0.03 0.06 0.01 0.0 0.0 0.0 0.0 0.10 SW 0.0 0.03 0.12 0.03 0.01 0.0 0.0 0.0 0.19 WSW 0.0 0.0 0.11 0.07 0.07 0.0 0.0 0.0 0.25 W 0.0 0.0 0.05 0.12 0.10 0.02 0.01 0.0 0.30 WNW 0.0 0.01 0.12 0.13 0.17 0.07 0.04 0.0 0.54 NW 0.0 0.0 0.05 Oa09 0.22 0.10 0.01 0.0 0.47 NNW 0.0 0.0 0.02 0.08 0.18 0.10 0.0 0.0 0.38 Sub-total 0.0 0.50 1.52 1.04 1.22 0.33 0.06 0.0 4.67 Total hours of valid stability observations - 25935 Total hours of Stability Class C 1202 Total hours of valid wind direction-wind speed-Stability Class C- 1197 Total hours calm 0 All columns and calm total 100 percent of joint valid observations Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed. = 7.0 mph 828o

RETS a. uai Revision 9 Page 184 Table 7.3 (4 of 22)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class D (-1.5 ( Delta-T< -0.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1979 Wind Speed (mph)

0. 6- 1. 5- 3. 5- 5.5- , 7.5- 12.5- 18.5-1.4 3.4 5.4 7.4 12.4 18.4 24.4 )24.5 Total N 0.0 0.19 0.41 0.53 1.00 0.37 0.01 0.0 2.51 NNE 0.01 0.20 0.56 0.58 1.18 0.18 0.01 0.0 2.72 NE 0.01 0.12 0.38 0.43 0.52 0.01 0.0 0.0 1.47 ENE 0.0 0.26 0.23 0.15 0.05 0.01 0.0 0.0 0.70 E 0.0 0.20 0.31 0.17 0.05 0.0 0.0 0.0 0.73 ESE 0.0 0.24 0.51 0.30 0.08 0.0 0.0 0.0 1.13 SE 0.02 1.16 1.31 0.83 0.26 0.0 0.0 0.0 3.58 SSE 0.01 0.99 0.99 0.26 0.11 0.02 0.0 0.0 2.38 S 0.0 0.92 1.17 0.34 0.17 0.0 0.0 0.0 2.60 SSW 0.0 0.45 0.29 0.08 0.04 0.0 0.0 0.0 0.86 SW 0.0 0.24 0.29 0.09 0.02 0.01 0.0 0.0 0.65 WSW 0.0 0.32 0.70 0.29 0.33 0.11 0.0 0.0 1.75 W 0.0 0.18 0.55 0.62 0.63 0.22 0.03 0.0 2.23 WNW 0.0 0.13 0.39 0.42 1.10 0.82 0.22 0.01 3.09 NW 0.0 0.04 0.28 0.38 1.01 ~ 0.87 0.14 0.02 2.74 NNW 0.0 0.13 0.40 0.55 1.54 0.74 0.05 0.0 3.41 Sub-total 0.05 5.77 8.77 6.02 8.09 3.36 0.46 0.03 32.55 Total hours of valid stability observations - 25935

otal hours of Stability Class D 8438 Total hours of valid wind direction-wind speed-Stability Class D - 8341 Total hours calm 1 All columns and calm total 100 percent of joint valid observations Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed-= 7.1 mph 828o

Revision 9 Page 185 Table 7.3 (5 of 22)

JO NT PERCENTAGE FRE UENCIES OF WIND SPEED BY MIND DIRECTION Stability Class E (-0.5 ( Delta-T< 1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1979 Mind Speed (mph) 0.6- 1.5- 3.5- 5.5- ., 7.5- 12.5- 18.5-1.4 3.4 5.4 7.4 12.4 18.4 24.4 )24.5 Total N 0.04 0.47 0.54 0.43 0.41 0.05 0.01 0.0 l. 95 NNE 0.05 0.61 . 0.74 0.55 0.47 0.04 0.0 0.0 2.46 NE 0.05 0.57 0.63 0.42 0.27 0-02 0.0 0.0 1.96 ENE 0.05 0.71 0.45 0.17 0.08 0.02 0.0 0.0 1.48 E 0.04 0.61 0.74 0.16 0.07 0.0 0.0 0.0 1.62 ESE 0.03 0.76 1.01 0.53 0.16 0.01 0.0 0.0 2.50 SE 0.11 2.04 1.75 0.92 0.55 0.02 0.0 0.0 5.39 SSE 0.07 1.16 0.78 0.48 0.33 0.04 0.0 0.0 2.86 S 0.05 1.03 0.74 0,44 0.63 0.14 0.01 0.0 3.04 SSM 0.02 0.52 0.14 0.08 0.06 0.01 0.0 0.0 0.83 SW 0.04 0.30 0.07 0.02 0.03 0.0 0.0 0.0 0.46 WSW 0.01 0.53 0.60 0.14 0.11 0.04 0.0 0.0 1.43 W 0.02 0.37 0.77 0.42 0.27 0.04 0.0 0.0 .89 MNW 0.03 0.15 0.13 O.ll 0.22 0.09 0.02 0.0 0.75 NW 0.02 0.17 0.20 0.14 0.25 0.09 0.02 0.0 0.89 NNM 0.05 0.41 0.48 0.54 0.59 0.09 0.01 0.0 2.17 Sub-total 0.68 10.41 9.77 5.55 4.50 0.70 0.07 0.0 31.68 Total hours of valid stability observations - 25935 Total hours of Stability Class E - 8264 Total hours of valid wind direction-wind speed-Stability Class E 8098 Total hours calm - 3 All columns and calm total 100 percent of joint valid observations Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Nean wind speed 5.0 mph 828o

RE S ~1anual Revision 9 Page 186 Table 7.3 (6 of 22)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY MIND DIRECTION Stability Class F (1.5 < Delta-T< 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1979 Wind Speed (mph)

0. 6- 1 5- 3 5- 5 5- . 7 5- 12 5- 18. 5-1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.05 0.36 0-52 0.28 0.06 0.0 0.0 0.0 1.27 NNE 0.05 0.51 0.66 0.34 O.ll 0.0 0.0 0.0 1.67 NE 0.07 0.34 0.27 0.18 0.01 0.0 0.0 0.0 0.87 ENE 0.03 0.53 0.33 0.05 0.0 0.0 0.0 0.0 0.94 E 0.01 0.59 0.52 0.03 0.0 0.0 0.0 0.0 1.15 ESE 0.0 0.52 0.22 0.0 0.0 0.0 0.0 0.0 0.74 SE 0.09 0.97 0.48 0.17 0.13 0.01 0.0 0.0 1.85 SSE 0.05 0.54 0.34 0.17 0.25 0.02 0.01 0.0 1.38 S 0.03 0.29 0.18 0.20 0.27 0.01 0.0 0.0 0.98 SSW 0.03 0.13 0.03 0.0 0.01 0.0 0.0 0.0 0.20 SW 0.0 0.09 0.03 0.0 0.0 0.0 0.0 0.0 0.12 WSW 0.0 0.09 0.07 0.0 0.0 0.0 0.0 0.0 0.16 M 0.02 0.09 0.06 0.0 0.01 0.0 0.0 0.0 0.18 WNW 0.01 0.08 0.01 0.0 0.0 0.0 0.0 0.0 0.10 NW 0.01 0.08 0.04 0.01 0.0 0.0 0.0 0.0 0.14 NNW 0.05 0.27 0.27 0.16 0.05 0.0 0.0 0.0 0.80 Sub-total 0.50 5.48 4.03 1.59 0.90 0.04 0.01 0.0 12.55 Total hours of valid stability observations 25935 otal hours of Stability Class F 3268 Total hours of valid wind direction-wind speed-Stability Class F- 3223 Total hours calm 2 All columns and calm total 100 percent of joint valid observations Meteorological facility: located 1.3 hn ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed-= 4.0 mph 828o

RE.S .'lanuai Revision 9 Page 187 Table 7.3 (7 of 22)

JOINT PERCENTAGE FRE UENCIES OF MIND SPEED BY WIND DIRECTION Stability Class G (Delta-T> 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- . 7.5- 12.5- 18.5-1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.07 0.76 0.32 0.02 0.0 0.0 0.0 0.0 1.17 NNE 0.05 0.83 0.51 0.18 0.02 0.0 0.0 0.0 1.59 NE 0.04 0.34 0.12 0.02 0.0 0.0 0.0 0.0 0.52 ENE 0.04 0.48 0.18 0.02 0.0 0.0 0.0 0.0 0.72 E 0.02 0.52 0.34 0.0 0.0 0.0 0.0 0.0 0.88 ESE 0.01 0.18 0.01 0.0 0.0 0.0 0.0 0.0 0.20 SE 0.08 0.43 0.09 0.04 0.03 0.0 0.0 0.0 0.67 SSE 0.03 0.44 0.31 0.16 0.08 0.0 0.0 0.0 1.02 S 0.05 0.09 0.12 0.10 0.04 0.0 0.0 0.0 0.40 SSW 0.05 0.05 0.01 0.0 0.0 0.0 0.0 0.0 0.11 SW 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.01 MSW 0.02 0.02 0.0 0.0 0.0 0.0 0.0 0.0 0.04 M 0.01 0.01 0.0 0.0 , 0.0 0.0 0.0 0.0 0.02 MNW 0.01 0.02 0.0 0.0 0.0 0.0 0.0 0.0 0.03 0.04 0.04 0.0 0.0 0.0 0.0 0.0 0.0 0.08 0.05 0.23 0.12 0.03 0.0 0.0 0.0 0.0 0.43 total 0.57 4.45 2.13 0.57 , 0.17 0.0 0.0 0.0 7.89 Total hours of valid stability observations - 25935 Total hours of Stability Class G 2056 Total hours of valid wind direction-wind speed-Stability Class G- 2019 Total hours calm - 4 All columns and calm total 100 percent of joint valid observations Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Mind speed and direction measured at the 10.42 meter level Mean wind speed.= 3.2 mph 828o

Revision 9 Page 188 Table 7.3 (8 of 22)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Disregarding Stability Class FERRY NUCLEAR PLANT 'ROWNS January 1, 1977 December 31, 1979 Wind Speed (mph)

0. 6- 1. 5- 3.5- 5.5- 7.5- 12.5- 18.5-1.4 3.4 5.4 7 4 12 4 18 4 24 4 >24 5 Total N 0.02 0. 19 0.38 0.64 2.07 2.47 0.61 0.06 6.44 NNE 0.0 0.13 0.33 0.60 2.46 2.69 0.50 0.04 6.75 NE 0.0 0.12 0.35 0.64 2.16 1.85 0.58 0.02 5.72 ENE 0.02 0.14 0.32 0.36 1.15 0.95 0.34 0.04 3.32 E 0.0 0.22 0.47 0.45 0.99 0.43 0.08 0.01 2.65 ESE 0.01 0.23 0.53 0.66 1.79 1.63 0.42 0.09 5.36 SE 0.02 0.36 1.26 1.36 3.25 3.20 1.54 0 69 11 68 SSE 0.01 0.38 1.20 1.22 2.97 2.59 1.16 0.59 10.12 S 0.02 0.40 0.90 1.05 2.53 2.40 1.03 0.43 8.76 SSW 0.0 0.31 0.65 0.69 1.73 1.77 0.73 0.19 6.07 SW 0.02 0.38 0.66 0.69 1.55 1.62 0.50 0.14 5.56 WSW 0.01 0.26 0.69 0.68 1.15 1.05 0.36 0.17 4.37 W 0.02 0.20 0.66 0.81 1.76 1.04 0.42 0.35 5.26 WNW 0.01 0.17 0.46 0.69 2.03 1.54 0.76 0.30 5.96 NW 0.02 0.19 0.49 0.70 1.80 2.01 0.96 0.28 6.45 NNW 0.01 0.22 0.28 0.41 1.66 2.13 0.70 0.13 5.54 Sub-total 0.19 3. 90 9.63 11.65 31.05 29.37 10.69 3.53 100.01 Total hours of valid wind observations - 25784 Total hours of observations - 26280 Recoverability percentage 98.1 Total hours calm 2 All columns and calm total 100 percent of joint valid observations 4Ieteorological facility: located 1.3 km ESE of BFN Wind speed and direction measured at the 92.63 meter level Mean wind speed = 12.0 mph 828o

RE..S ilanua Revision 9 Page )89 Table 7.3.(9 of 22)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY MIND DIRECTION Stability Class A (Delta-T( -1.9 degrees C per 100 m)

BROMNS FERRY NUCLEAR PLANT Part 1 of 2 ground level release mode January 1, 1977 December 31, 1979 Mind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1 4 3 4 5 4 7 4 12 4 .18 4 24 4 >24 5 Total N 0.0 0.0 0.0 0.0 0.0 0.02 0.01 0.0 0.0 0.03 NNE 0.0 0.0 0.0 0.0 0.0 0.03 0.02 0.0 0.0 0.05 NE 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.01 ENE 0.0 0.0 0' 0.0 0.0 0.0 0.0 0.0 0.0 0.0 E 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ESE 0.0 0.0 0.0 0.0 0.02 0.0 0.0 0.0 0.0 0.02 SE 0.0 0.0 0.0 0.05 0.04 0.01 0.0 0.0 0.0 0.10 SSE 0.0 0.0 0.0 0.03 0.02 0.01 0.0 0.0 0.0 0.06 S 0.0 0.0 0.0 0.02 0.02 0.01 ,0.0 0.0 0.0 0.05 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.01 f

SSW SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSM C.O 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.02 W 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.01 WNW 0.0 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.02 NW 0.0 0.0 0.0 0.0 0.0 0.02 0.02 0.0 0.0 0.04 NNW 0.0 0.0 0.0 0.0 0.0 0.01 0.02 0.02 0.0 0.05 Sub-total 0.0 0.0 0.0 0.10 0.12 0.15 0.08 0.02 0.0 0.47 Total hours of valid observations 25482.0 Total hours of ground level release - 2832.4 otal hours of Stability Class A - 133.1 Total hours of ground level Stability Class A 127.5 Meteorological facility: located 1.3 lcm ESE of BFN Stability based on Delta-T between 10.03 and 45.30 meters Wind direction measured at 10.42 meter level Wind speed measured at 10.42 meter level Effluent velocity = 12.60 m/s 828o

i= a ..anual

%1 Revision 9 Page 190 Table 7.3 (10 of 22)

SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class B (-1.9 ( Delta T ( -1.7 degre'es C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 1 of 2 ground level release mode January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.0 0.0 0.0 0.0 0.01 0.05 0.01 0.01 0.0 0.08 NNE 0.0 0.0 0.0 0.0 0.01 0.05 0.01 0.0 0.0 0.07 NE 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.01 ENE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 E 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ESE 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.01 SE 0.0 0.0 0.0 0.02 0.02 0.01 0.0 0.0 0.0 0.05 SSE 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.02 S 0.0 0.0 0.0 0.02 0.01 0.01 0.0 0.0 0.0 0.04 SSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.02 0.01 0.0 0.0 0.0 0.03 W 0.0 0.0 0.0 0.0 0.01 0.02 0.02 0.01 0.0 0.06 WNW 0.0 0.0 0.0 0.0 0.01 0.03 0.02 0.03 0.0 0.09 NW 0.0 0.0 0.0 0.0 0.01 0.04 0.03 0.0 0.0 0.08 NNW 0.0 0.0 0.0 0.0 0.0 0.03 0.04 0.0 0.0 0.07 Sub-total 00 00 00 005 012 026 013 005 00 061 otal hours or valid observations - 25482.0 Total hours of ground level release 2832.4 Total hours of Stability Class B - 185.1 Total hours of ground level Stability Class B- 163.4 4ieteorological facil.'ty: located 1.3 km ESE of BFN Stability based on Delta-T between 10.03 and 45.30 meters Wind direction measured at 10.42 meter level Wind speed measured at 10.42 meter level Effluent velocity = 12.60 m/s 828o

RE:S Man a Revision 9 Page 191 Table 7.3 (11 of 22)

SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Sta>ility Class C (-1.7 < Delta-T( -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 1 of 2 ground level release mode January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3 ' 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.0 0.0 0.0 0.0 0.01 0.03 0.0 0.0 0.0 0.04 NNE 0.0 0.0 0.0 0.0 0.01 0.02 0.0 0.0 0.0 0.03 NE 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.02 ENE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 E 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ESE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SE 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.02 SSE 0.0 0.0 0.0 0.01 0.01 0.01 0.0 0.0 0.0 0.03 S 0.0 0.0 0.0 0.01 0.01 0.01 0.0 0.0 0.0 0.03 SSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSV G.O 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.02 W 0.0 0.0 0.0 0.0 0.01 0.01 0.01 0.01 0.0 0.04 WNW 0.0 0.0 0.0 0.0 0.01 0.02 0.02 0.03 0.0 0.08 NW 0.0 0.0 0.0 0.0 0.01 0.03 0.02 0.01 0.0 0.07 NNW 0.0 0.0 0.0 0.0 0.01 0.02 0.03 0.0 0.0 0.06 Sub-total 0.0 0.0 0.0 0.03 0.11 0.17 0.08 0.05 0.0 0.44 Total hours of valid observations - 25482.0 Total hours of ground level release 2832.4 Total hours of Stability Class C - 259.0 Total hours of ground level Stability Class C 106.3 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 10.03 and 45.30 meters Wind direction measured at 10.42 meter level Effluent velocity = 12.60 m/s 828o

RETS .'lanua1 Revision 9 Page 192 Table 7.3 (12 of 22)

SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class D (-1.5 < Delta-T< -0.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 1 of 2 ground level release mode January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.0 0.0 0.0 0.01 0. 04 0. 15 0. 10 0.01 0.0 0.31 NNE 0.0 0.0 0.0 0.01 0.05 0.18 0.05 0.01 0.0 0.30 NE 0.0 0.0 0.0 0.01 0.04 0.08 0.0 0.0 0.0 0.13 ENE 0.0 0.0 0.0 0.01 0.01 0.01 0.0 0.0 0.0 0.03 E 0.0 0.0 0.0 0.01 0.02 0.01 0.0 0.0 0.0 0.04 ESE 0.0 0.0 0.0 0.03 0.04 0.01 0.0 0.0 0.0 0.08 SE 0.0 0.0 0.01 0.11 0.13 0.06 0.0 0.0 0.0 0.31 SSE 0.0 0.0 0.02 0.09 0.06 0.05 0.02 0.0 0.0 0.24 S 0.0 0.0 0.02 0.09 0.06 0.06 0.0 0.0 0.0 0.23 SSW 0.0 0.0 0.01 0.02 0.01 0.01 0.0 0.0 0.0 0.05 SW 0.0 0.0 0.0 0.01 0.01 0.0 0.01 0.0 0.0 0.03 WSW 0.0 0.0 0.0 0.03 0.03 0.06 0.04 0.0 0.0 0.16 W 0.0 0.0 0.0 0.02 0.06 0.10 0.09 0.02 0.0 0.29 WNW 0.0 0.0 0.0 0.0 0.03 0.16 0.19 0.14 0.01 0.53 NW 0.0 0.0 0.0 0.0 0.03 0.15 0.23 0.10 0.02 . 0.53 NNW 0.0 0.0 0.0 0.01 0.05 0.25 0.19 0.04 0.0 0.54 Sub-total 0.0 0.0 0.6 0.46 0.67 1.34 0.92 0.32 0.03 3.80

=otal hours of valid observations 25482.0 Total hours of ground level release - 2832.4 Total hours of Stability Class D - 13904.1 Total hours of ground level Stability Class D- 968.6 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T'between 10.03 and 45.30 meters W'nd direction measured at 10.42 meter level Effluent velocity = 12.60 m/s 828o

Th .i1canna Revision 9 Page 193 Table 7.3 (13 of 22)

SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION S'tability Class E (-0.5<Delta-T< 1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 1 of 2 ground level release mode January 1, 1977 December 31, 1979 Wind /peed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.0 0.0 0.0 0.04 0.06 0.07 0.02 0.01 0.0 0. 20 NNE 0.0 0.0 0.01 0.06 0.07 0.08 0.02 0.0 0.0 0.24 NE 0.0 0.0 0.01 0.06 0.06 0.05 0.01 0.0 0.0 0.19 ENE 0.0 0.0 0.02 0.04 0.03 0.01 0.01 0.0 0.0 0.11 E 0.0 0.0 0.02 0.07 0.02 0.01 0.0 0.0 0.0 0.12 ESE 0.0 0.0 0.02 0.08 0.07 0.03 0.0 0.0 0.0 0.20 SE 0.0 0.0 0.08 0.22 0.16 0.18 0.02 0.0 0.0 0.66 SSE 0.0 0.0 0.05 0.12 0.12 0.19 0.04 0.0 0.0 0.52 S 0.0 0.0 0.06 0.10 0.09 0.27 0.13 0.01 0.0 0.66 SSW 0.0 0.0 0.02 0.02 0.02 0.02 0.01 0.0 0.0 0.09 SW 0.0 0.0 0.01 0.0 0.0 0.01 0.0 0.0 0.0 0.02 WSW 0.0 0.0 0.01 0.05 0.02 0.03 0.02 0.0 0.0 0.13 W 0.0 0.0 0.01 0.06 0.05 0.05 0.01 0.0 0.0 0.18 WNW 0.0 0.0 0.0 0.01 0.01 0.04 0.02 0.01 0.0 0.09 NW 0.0 0.0 0.0 0.01 0.02 0.04 0.03 0.01 0.0 0.11 NNW 0.0 0.0 0.0 0.03 0.07 0.10 0.02 0.01 0.0 0.23 Sub-total 0.0 0.0 0.32 0.97 0.87 1.18 0.36 , 0.05 0.0 3.75 Total hours of valid observations 25482.0 Total hours of ground level release 2832.4 Total hours of Stability Class E - 7920.6 Total hours of ground level Stability Class E 957.9 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 10.03 and 45.30 meters Wind direction measured at 10.42 meter level Wind speed measured at 10.42 meter level Effluent velocity = 12.60 m/s 828o

i=~~ :.anual Revision 9 Page 194 Table 7.3 (14 of 22)

SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class F (1.5 ( Delta-T< 4.0 degrees C per 100 m)

Part 1 of 2 ground level release mode BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3 4 5 4 7 4 12 4 18 4 24 4 >24 5 Total N 0.0 0.0 0.01 0.06 0.04 0.01 0.0 0.0 0.0 0.12 NNE 0.0 0.0 0.01 0.08 0.05 0.02 0.0 0.0 0.0 0.16 NE 0.0 0.0 0.01 0.03 0.03 0.0 0.0 0.0 0.0 0.07 ENE 0.0 0.0 0.02 0.03 0.01 0.0 0.0 0.0 0.0 0.06 E 0.0 0.0 0.01 0.04 0.0 0.0 0.0 0.0 0.0 0.05 ESE 0.0 0.0 0.02 0.02 0.0 0.0 0.0 0.0 0.0 0.04 SE 0.0 0.0 0.05 0.06 0.03 0.06 0.01 0.0 0.0 0.21 SSE 0.0 0.0 0.04 0.06 0.05 0.18 0.02 0.01 0.0 0.36 S 0.0 0.0 0.02 0.03 0.04 0.11 0.01 0.0 0.0 0.21 SSW 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.01 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.01 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNW 0.0 0.0 0.01 0.03 0.02 0.01 0.0 0.0 0.0 0.07 Sub-total 0.0 0.0 0.21 0.45 0.27 0.39 0.04 0.01 0.0 1.37 Total hours of val'd observat'ons 25482.0 Total hours of ground level release 2832.4 Total hours oi Stability Class F - 2385.0 Total hours of ground level Stability Class F 357.0 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 10.03 and 45.30 meters Wind speed measured at 10.42 meter level Effluent velocity = 12.60 m/s 828o

Revision 9 Page l 95 Table 7.3 (15 of 22)

SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class G (Delta-T> 4.0 degrees C per 100 m)

Part 1 of 2 ground level release mode BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1979 Mind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3.4 5.4 7.4 12.4 '8.4 24.4 >24.5 Total N 0.0 0.0 0.02 0.04 0.0 0.0 0.0 0.0 0.0 0.06 NNE 0.0 0.0 0.02 0.06 0.03 0.0 0.0 0.0 0.0 0.11 NE 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 ENE 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 E 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 ESE 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.01 SE 0.0 0.0 0.03 0.01 0.01 0.02 0.0 0.0 0.0 0.07 SSE S

SSV 0.0 0.0 0.0 0.0 0.0 0.0 0.04 0.01 0.0 0.05 0.02 0.0 0.03 0.02 0.0 0.06 0.01 0.0

'.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.18 0.06 0.0 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNV 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNW 0. 0 0.0 0.01 0.01 0.08 0.0 0.0 0.0 0.0 0.02 Sub-total 0.0 0.0 0.17 0.22 0.09 0.09 0.0 0.0 0.0 0.57 Total hours of valid observations 25482.0 Total hours of ground level release 2832.4 Total hours of Stability Class G - 694.7 Total hours of ground level Stability Class G- 151.7 Meteorological facility: located 1.3 lan ESE of BFN Stability based on Delta-T between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Effluent velocity = 12.60 m/s 828o

e RE:8:!anus 1 Revision 9 Page 196 Table 7.3 (16 of 22)

SPLIT UOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class A (Delta-T( -1.9 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 2 of 2 elevated release mode January 1, 1977 December 31, 1979 Wind .Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 )24.5 Total N 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0

'E 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ENE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 E 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ESE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SSE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 S 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SSW 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.01 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Sub-total 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.01 Total hours of val'd observations 25482.0 Total hours of elevated releases 22649.6 Total hours of Stability Class A 133.1 Total hours of elevated Stability Class A 5.6 Neteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Wind direction measured at 45.67 meter level Wind speed measured at 45.67 meter level Effluent velocity = 12.60 m/s 828o

RETS .'lanua Revision 9 Page 197 Table 7.3 (17 of 22)

SPLIT JOINT PERCENTAGE FRE UENCIES OF MIND SPEED BY W1ND DIRECTION Stability Class B (-1 ' < Delta-T( -1.7 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 2 of 2 elevated release mode January 1, 1977 - December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5<< 7.5- 12.5- 18.5-Calm 1.4 3.4 5.4 7.4 12.4 '18.4 24.4 >24.5 Total N 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ENE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 E 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ESE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SE 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 SSE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 S 0.0 0.0 0.0 0.0 0.0 0.0 "0.0 0.0 0.0 0.0 SSW 0.0 0.0 0.0 O.O O.O O.O1 0.0 0.0 0.0 0.01 SW 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.01 WSW 0.0 0.0 0.0 0.0 0.0 0.02 0.0 0.0 0.0 0.02 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NW 0.0 0.0 0.0 ~ 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Sub-total 0.0 0.0 0.01 0.01 0.01 0.03 0.0 0.0 0.0 0.06 Total hours of valid observations 25482.0 Total hours of elevated releases 22649.6 Total hours of Stability Class B 185.1 Total hours of elevated stability class B- 21.8 Neteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Wind direction measured at 45.67 meter level Mind speed measured at 45.67 meter level Effluent velocity 12.60 m/s

~

828o

R:-:S: lanua1 Revision 9 Page 198 Table 7.3 (18 of 22)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class C (-1.7 < Delta-T< -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 2 of 2 elevated release mode January 1, 1977 December 31, 1979 Wind .Speed (mph)

0. 6- 1. 5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNE 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.01 NE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ENE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 E 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ESE 0.0 0.0 0.0 0.01 0.01 0.01 0.0 0.0 0.0 0.03 SE 0.0 0.0 0.02 0.05 0.01 0.0 0.0 0.0 0.0 0.08 SSE 0.0 0.0 0.0 0.04 0.0 0.0 0.0 0.0 0.0 0.04 S 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 SSM 0.0 0.0 9.0 0.02 0.02 0.01 0.0 0.0 0.0 0.05 SW 0.0 0.0 0.0 0.05 0.05 0.02 0.01 0.0 0.0 0.13 WSW 0.0 0.0 0.0 0.0 0.03 0.05 0.01 0.0 0.0 0.09 W 0.0 0.0 0.0 0.0 0.01 0.03 0.02 0.02 0.0 0.08 WNW 0.0 0.0 0.0 0.0 0.0 0.02 0.02 0.0 0.0 0.04 NM 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.01 RW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Sub-total 0.0 0.0 0.03 0.18 0.14 0.14 0.07 0.02 0.0 0.58 Total hours of valid observations - 25482.0 Total hours of elevated releases 22649.6 Total hours of Stability Class C 259.0 Total hours of elevated Stability Class C 152. 7 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Mind speed and direction measured at the 45.67 meter level Effluent velocity = 12.60 m/s 828o

0 RETS '.lanua Revision 9 Page 199 Table 7.,3 (19 of 22)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class D (-1.5 < Delta-T< -0.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 2 of 2 elevated release mode January 1, 1977 December'1, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3.4 5.4 7.4 12.4 . 18.4 24.4 )24.5 Total N 0.0 0.0 0.12 0.40 0.62 1.49 0.87 0.12 0.0 3.62 NNE 0.0 0.01 0.13 0.46 0. 72 1.88 0.91 0.05 0.0 4.16 NE 0.0 0.0 0.09 0.36 0.48 1.04 0.14 0.02 0.0 2.13 ENE 0.0 0.01 O.ll 0.24 0.23 0.23 0.04 0.01 0.0 0.87 E 0.0 0.01 0.10 0.20 0.28 0.25 0.05 0.01 0.0 0.80 ESE 0.0 0.01 0 22 0.52 0.68 1.07 0.16 0.0 0.0 2.66 SE 0.0 0.01 0.67 1.66 0.89 1.75 0.84 0.16 0.01 5.99 SSE 0.0 0.01 0.48 0.90 0.63 1.49 1.08 0.26 0.02 4.871 S 0.0 0.0 0.34 0.99 0.67 0.99 0.93 0.33 0.02 4.27 SSW 0.0 0.01 0.20 0.52 0.37 0.69 0.34 0.11 0.0 2.24 SW 0.0 '0. 01 0.24 0.79 0.43 0.49 0.32 0.05 0.0 2.33 MSM 0.0 0.02 0.16 0.51 0.57 0.57 0.27 0.08 0.0 2.18 M 0.0 0.0 0.07 0.36 0.80 1.34 0.55 0.16 0.01 3.29 WNW 0. 0 0.0 0.09 0.33 0.48 1.25 0.94 0.32 0.01 3.42 0.0 0.07 0.36 0.55 1.40 1.44 0.37 0.01 4.20 0.0 0.09 0.29 0.53 1.36 1.15 0.19 0.0 3.61 Sub-total 0.0 0.10 3.18 8.89 8.93 17.29 10.03 , 2.24 0.08 50.74 Total hours of valid observations 25482.0 Total hours of elevated releases 22649.6 Total hours of Stability Class D 13904.1 Total hours of elevated Stability Class D 12935.5 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Mind speed and direction measured at the 45.67 meter level Effluent velocity = 12.60 m/s 828o

cf I sb:aanua'evision 9

Page 200 Table 7.3 (20 of 22)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION St.'ability Class E (-0.5 < Delta-T< 1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 2 of 2 elevated release mode January 1, 1977 - December 31, 1979 Wind Speed (mph)

0. 6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.0 0.0 0.13 0.22 0.31 0.80 0.15 0.0 0.0 1.61 NNE 0.0 0.0 0.15 0.24 0.39 1.04 0.28 0.0 0.0 2.10 NE 0.0 0.01 0.11 0.25 0.39 0.88 0.18 0.0 0.0 1.82 ENE 0.0 0.0 0.20 0.21 0.33 0.39 0.10 0.0 0.0 1.23 E 0.0 0.0 0.09 0.24 0.30 0.55 0.06 0.0 0.0 1.24 ESE 0.0 0.01 0.29 0.58 0.86 1.10 0.09 0.01 0.0 2.94 SE 0.0 0.02 0.41 1.04 1.02 1.37 0.55 '0.08 0.01 4.50 SSE 0.0 0.01 0.23 0.60 0.54 0.87 0.59 0.14 0.01 2.99 S 0.0 0.01 0.14 0.49 0.32 0.70 0.34 0.05 0.0 2.05 SSW 0.0 0.0 0.11 0.28 0.30 0.48 0.19 0.01 0.0 1.37 SW 0.0 0.01 0.17 0.27 0.28 0.29 0.09 0.0 0.0 1.11 WSW 0.0 0.01 0.12 0.25 0.24 0.28 0.06 0.0 0.0 0.96 W 0.0 0.0 0.09 0.19 0.26 0.34 0.05 0.0 0.0 0.93 WNW 0.0 0.0 0.06 0.13 0.11 0.20 0.04 O.O1 0.0 0.55 iNW 0.0 0.0 0.09 0.14 0.13 0.31 0.08 0.0 0.0 0.75 i'ub- 0.0 0.0 0.12 0.21 0.16 0.52 0.16 0.0 0.0 1.17 total 0.0 0.08 2.51 5.34 5.94 10.12 3.01 0.30 0.02 27.32 otal hours of valid observat'ons 25482.0 Total hours of elevated releases - 22649.6 Total hours of Stability Class E 7920.9 Total hours of elevated Stability Class E - 6962.9 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Wind speed and direction measured at the 45.67 meter level Effluent velocity = 12.60 m/s 828o

~ian 'a Revision 9 Page 201 Table 7.3 (21 of 22)

JOINT PERCENTAGE FRE UENCIES 'OF WIND SPEED BY MIND DIRECTION Stability Class F ( 1.5 < Delta-T< 4.0 <egrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 2 of 2 elevated release mode January 1, 1977 December 31, 1979 Mind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 )24.5 Total N 0.0 0.0 0.03 0.08 0.06 0.34 0.05 0.0 0.0 0.56 NNE 0.0 0.0 0.0 0.0 0.04 0.04 0.06 0.10 0.11 0.42 0.40 0.21 0.0 0.0 0 '4 NE 0.15 0.12 0.0 0.0 0.81 ENE 0.0 0.0 0.04 0.11 O.ll 0.29 0.07 0.0 0.0 0.62 E 0.0 0.0 0.03 0.07 0.11 0.32 0.02 0.0 0.0 0.55 ESE 0.0 0.0 0.13 0.26 0.24 0.24 0.0 0.0 0.0 0.87 SE 0.0 0.0 0.13 0.38 0.30 0.19 0.0 0.0 0.0 1.00 SSE 0.0 0.0 0.09 0.11 0.12 0.14 0.03 0.0 0.0 0.49 S 0.0 0.0 0.08 0.11 0.13 0.21 0.03 0.0 0.0 0.56 SSW 0.0 0.0 0.04 0.12 0.14 0.24 '.01 0.0 0.0 0.55 SW 0.0 0.0 0.04 0.09 0.10 0.06 0.0 0.0 0.0 0.29 WSW 0.0 0.0 0.03 0.07 0.06 0.05 0.0 0.0 0.0 0.21 W 0.0 0.01 0.04 0.04 0.05 0.04 0.0 0.0 0.0 0.18 MNW 0.0 0.0 0.02 0.04 0.01 0.01 0.0 0.0 0.0 0.08 NW 0.0 0.0 0.03 0.04 0.03 0.02 0.0 0.0 0.0 0.12 NNW 0.0 0.0 0.02 0.02 0.04 0.10 0.0 0.0 0.0 0.18 S ub total 0.0 0.01 0.83 1.70 1.76 3.07 0.54 0.0 0.0 7.91 Total hours of valid observations - 25482.0 Total hours of elevated releases 22649.6 Total hours of Stability Class F-- 2385.0 Total hours of elevated Stability Class F- 2028.0 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Wind speed and direction measured at the 45.67 meter level Effluent velocity = 12.60 m/s 828o

~a ~a:ianua ~

Revision 9 Page 202 Table 7.3 (22 of 22)

JOINT PERCENTAGE FRE UENCIES OF MIND SPEED BY MIND DIRECTION Stability Class G (Delta-T> 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 2 of 2 elevated release mode January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.0 0.0 0.0 0.0 0.02 0.06 0.01 0.0 0.0 0.09 NNE 0.0 0.0 0.01 0.02 0.04 0.11 0.04 0.0 0.0 0.22 NE 0.0 0.0 0.02 0.02 0.03 0.12 0.02 0.0 0.0 0.21 ENE 0.0 0.0 0.0 0.02 0.02 0.07 0.02 0.0 0.0 0.13 E 0.0 0.0 0.0 OA2 0.01 0.04 0.0 0.0 0.0 0.07 ESE 0.0 0.01 0.05 0.15 0.07 0.01 0.0 0.0 0.0 0.29 SE 0.0 0.0 0.12 0.20 0.13 0.04 0.0 0.0 0.0 0.49 SSE 0.0 0.0 0.03 0.06 0.06 0.02 0.0 0.0 0.0 0.17 S 0.0 0.0 0.02 0.07 0.06 0.01 0.0 0.0 0.0 0.16 SSM 0.0 0.0 0.0 0.02 0.02 0.06 0.0 0.0 0.0 0.10 SW 0.0 0.0 0.01 0.01 0.03 0.02 0.0 0.0 0.0 0.07 WSM 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.01 W 0.0 0.0 0.01 0.0 0.01 0.0 0.0 0.0 0.0 0.02 WNW 0.0 0.0 0.02 0.0 0.0 0.0 0.0 0.0 0.0 0.02 NW 0.0 0.0 0.0, 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNW 0.0 0.0 0.01 0.01 0.0 0.01 0.0 0.0 0.0 0.03 Sub-total 0.0 0.01 0.31 0.60 0.50 0.57 0.09 0.0 0.0 2.08 Total hours of valid observations - 25482.0 Total hours of elevated releases 22649.6 Total hours of Stability Class G 694.7 Total hours of elevated Stability Class G - 543.1

'meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Wind speed and direction measured at the 45.67 meter level Effluent velocity = 12.60 m/s 828o

RETS Nanual Revision 9 Page 203 Table 7.4 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES Submersion dose Air dose

- mrem/yr per pCi/m mrad/yr per pCi/m3 DFBi DFYi DFBi Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

Reference:

Regulatory Guide 1.109, Table B-l.

828o

RE. S: lanua 1 Revision 9 Page 204 Table 7.5 SECTOR ELEMENI'S CONSIDERED FOR POPULATION DOSES Range of Nidpoint of Sector Element Sector Element Site boundary 1 mile 0.8 mile 1 2 miles 1.5 miles 2 3 miles 2.5 miles 3 4 miles 3.5 miles 4 5 miles 4.5 miles 5 10 miles 7.5 miles 10 20 miles 15 miles 20 30 miles 25 miles 30 - 40 miles 35 miles 40 50 miles 45 miles 828o

RETS:lanua'evision 9

Page 205 Table 7.6 BFN 50-MILE POPULATION WITHIN EACH SECTOR ELEMENT 0.8 1.5 2.5 3-5 4.5 7.5 '5 Distance to Midpoint of Sector Element 25 35 45 0 10 55 35 85 670 1515 2615 10660 3690 0 5 15 65 55 915 2990 2230 3125 3420 NE 0 5 25 45 88 4180 14180 6625 5385 12625 0 15 50 40 70 1310 4990 9615 13860 5425 0 30 10 40 945 1910 73405 75125 4610 0 5 0 0 165 1880 2535 7465 9575 SE 0 0 0 20 10390 30945 4660 6230 13850 SSE 0 0 0 50 1630 6250 11630 15175 18945 0 20 35 90 1250 3805 1800 4475 3730 SSVi 0 60 75 175 845 5895 1270 1490 253o SW 0 20 35 90 685 2970 2280 2725 10675 WSW 0 35 15 135 295 3060 3005 11545 3755 25 30 625 2960 6830 35070 4785 25 55 50 885 9300 39875 5545 5 345 4345 5215 5485 3260 5 35 20 625 2090 2440 12350 7360 828o

RETS ~lanual Revision 9 Page 206 Table 7.7 (1 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

ADULT bone liver 1.58E-07 t body 1.58E-07 thyroid kidney lung gi-lli H-3 1. 58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C-14 2. 27E-06 4.26E-07 4.26E-OZ 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1. 28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1. 65E-04 9.64E-06 6.26E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.08E-05 Cr-51 0.00E+00 0.00E+00 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 0.00E+00 4.95E-06 7.87E-07 O.OOE+00 1.23E>>06 1.75E-04 9.67E-06 Mn-56 0.00E+00 1.55E-10 2.29E-11 0.00E+00 1.63E>>10 1.18E-06 2.53E-Q6 Fe-55 3.07E-06 2.12E-06 4.93E-07 0.00E+00 0.00E+00 9.01E-06 7.54E-07 Fe-59 1.47E-O6 3.47E-06 1.32E-O6 O.OOE+00 O.OOE+00 1.27E-04 2.35E-05 Co-57 0.00E+00 8.65E-08 8.39E-08 0.00E+00 O.OOE+00 4.62E-05 3.93E-06 Co-58 O.OOE+00 1.98E<<07 2.59E-07 0.00E+00 0.00E+00 1.16E-04 1.33E-05 Co-60 O.OOE+00'.40E-05 1.44E-06 1.85E-06 O.OOE+00 O.OOE+00 7.46E-04 3.56E-05 Ni-63 3.93E-06 1.81E-06 0.00E+00 O.OOE+00 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 O.OOE+00 0.00E+00 7.00E-07 1.54E-06 CLL-64 0.00E+00 1.83E-10 7.69E-11 O.OOE+00 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 0.00E+00 8.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 0.00E+00 5.27E-12 1.15E-07 2;04E-09 Zn-69m 1.02E-09 2.45E-09 2.24E<<10 O.OOE+00 1. 48E&9 2.38E-06 1.71E-05 Br-82 0.00E+00 O.OOE+00 1.69E-06 0.00E+00 0.00E+00 0.00E+00 1.30E-06 Br-83 0.00E+00 0.00E+00 3.01E-08 0.00E+00 O.OOE+00 O.OOE+00 2.90E-08 Br-84 0.00E+00 0.00E+00 3.91E-08 0.00E+00 O.OOE+00 0.00E+00 2.05E-13 Br-85 O.OOE+00 O.OOE+00 1.60E-09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 0.00E+00 1.69E-05 7.37E-06 0.00E+00 0.00E+00 0.00E+00 2.08E-06 Rb-88 0.00E+00 4.84E-08 2.41E-08 0.00E+00 0.00E+00 0.00E+00 4.18E-19 Rb-89 0.00E+00 3.20E-08 2.12E-08 O.OOE+00 0.00E+00 O.OOE+00 1.16E-21 Sr-89 3.80E-05 O.OOE+00 1.09E-06 O.OOE+00 O.OOE+00 1.75E-04 4.37E-05 Sr-90 1.24E-02 O.OOE+00 7.62E-04 O.OOE+00 O.OOE+00 1.20E-03 9.02E-05 Sr-91 7. 74E-09 O.OOE+00 3.13E-10 O.OOE+00 0.00E+00 4.56E-06 2.39E-05 Sr-92 8.43E-10 0.00E+00 3.64E-11 0.00E+00 0.00E+00 2.06E-06 5.38E-06 Y-90 2.61E-07 O.OOE+00 7.01E-09 O.OOE+00 O.OOE+00 2.12E-05 6.32E-05 Y-91m 3.26E-11 O.OOE+00 1.27E-12 O.OOE+00 O.OOE+00 2.40E-07 1.66E>>10 Y-91 5. 78E&5 O.OOE+00 1.55E-06 0.00E+00 O.OOE+00 2.13E-04 4.81E-05 Y-92 1.29E-09 0.00E+00 3.77E-11 O.OOE+00 O.OOE+00 1.96E-06 9.19E-06 Y-93 1.18E-OS 0.00E+00 3.26E-10 O.OOE+00 O.OOE+00 6.06E-06 5.27E-05 Zr-95 1.34E&5 4.30E-06 2.91E-O& O.OOE+00 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E<<09 0.00E+00 3. 71E&9 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 O.OOE+00 9.67E-07 6.31E-05 1.30E-05 Nb-97 2.78E-11 7.03E-12 2.56E-12 0.00E+00 8.18E-12 3.00E-07 3.02E-08 Mo-99 0.00E+00 1.51E-08 2.87E-09 0.00K+00 3.64E-08 1.14E-05 3.10E-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 O.OOE+00 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 0.00E+00 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 O.OOE+00 8.23E-08 O.OOE+00 7.29E-07 6.31E-05 1.38E-05 RG-105 9.88E-11 O.OOE+00 3.89E-11 0.00E+00 1.27E-10 1.37E-06 6.02E-06 RU-106 8.64E-06 O.OOE+00 1.09E-06 O.OOE+00 1.67E-05 1.17E-03 1.14E-04 Ag-110m 1.35E-06 1.25E-06 7.43E-07 O.OOE+00 2.46E-06 5.79E-04 3.78E-05 828o

RETS Nanuai Revision 9 Page 207 Table .7.7 (2 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

ADULT bone liver t body thyroid kidney lung gi-lli Sb-124 3.90E-06 7. 36E-08 1.55E-06 9.44E-09 O.OOE+00 3. 10E-04 5.08E-05 Sb-125 6.67E-06 7.44E-OS 1.58E-O& 6.75E-09 O.OOE+00 2.18E-04 1.26E-05 Te-125m 4.27E-07 1.98E-07 5.84E-OB 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-Q7 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E>>06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-OS Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-OB 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-OB 2.69E-OB 2.02E-OB 2.37E-QB 1.82E-07 3.60E-05 6.37E-05 I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 O.OOE+00 9.61E-07 I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 O.OOE+00 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 O.OOE+00 5.08E-OS I-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 Q.OOE+00 1.11E-06 I-134 8.05E<<OS 2.16E-07 7.69E-OB 3.73E-06 3.44E-07 O.OOE+00 1.26E-10 I-135 3.35E-07 8.73E-07 3. 21E-07 5.60E-05 1.39E-06 O.OOE+00 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.10E-05 O.OOE+00 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 O.OOE+00 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 0.00E+00 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-OS 7.76E-OB 4.05E-OB Q.OOE+00 6.00E-OB 6.07E>>09 '2,33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 O.QOE+00 7.78E-14 4.70E-47 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 O.OOE+00 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 O.OOE+00 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E>>12 3.38E-15 2.07E-13 O.OOE+00 2.86E-1.5 1.49E-07 1.96E-26 La-140 4.30E-OS 2.17E-OS 5.73E-09 Q.OOE+00 O.OOE+00 1.70E-05 5.73E<<05 La-142 8.54E-11 3.88E-11 9.65E-12 O.OOE+00 O.OOE+00 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E>>07 O.OOE+00 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-OB 1.72E-OS 1.91E-09 0.00E+00 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E&4 1 79E-04 2.30E-05 O.OOE+00 1.06K&4 9.72E-04 1.02E-04 Pr-143 1.17E&6 4.69E-07 5.80E-08 O.OQE+00 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 Q.OQE+00 8.81E-13 1. 27E-07 2.69E-18 Nd-147 6.59E&7 7.62E-07 4.56E-OS O.OOE+00 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E&9 8.85E-10 3.10E-10 0.00E+00 0.00E+00 3.63E-06 1.94E-05 Np-239 2.87E-OB 2.82E-09 1.55E-09 O.OOE+00 8. 75E&9 4.70E-06 1.49E-05

Reference:

Regulatory Guide 1.109, Table E-7.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 8.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

828o

RETS Manual Revision 9 Page 208 Table 7.7 (3 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

TEEN H-3 bone 1.59E-07 liver 1.59E-07 t body 1.59E-07 thyroid 1.59E-07 kidney lung gi-lli 1.59E-07 1. 59E-07 1.59E-07 C-14 3.25E-06 6.09E-07 6.09E-O7 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1.72E-O6 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 0.00E+00 0.00E+00 O.OOE+00 1.16E-05 Cr-51 0.00E+00 0.00E+00 1.69E-O8 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 0.00K+00 6.39E-06 1.05E-06 0.00E+00 1.59E-06 2.48E-04 8.35E-06 Mn-56 0.00E+00 2.12E-10 3.15E-11 0.00E+00 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 0.00E+00 0.00E+00 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 0.00K+00 0.00E+00 1.91E-04 2.23E-05 Co-57 0.00E+00 1.18E-07 1.15E-07 0.00E+00 0.00E+00 7.33E-05 3.93E-06 Co-58 0.00E+00 2. 59E-07 3.47E-07 0.00E+00 0.00E+00 1.68E-04 1.19E-05 Co-60 0.00E+00 1.89E-06 2.48E-06 0.00K+00 0.00E+00 1.09E-03 3.24E-05 Ni-63 7.25E-05 5.43E-06 2.47E-06 0.00E+00 O.OOE+00 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 0.00E+00 0.00E+00 1.17E-06 4.59E-06 Cu-64 O.OOE+00 2.54E-10 1.06E-10 0.00E+00 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 0.00E+00 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-ll 8.07E-13 0.00E+00 7.53E-12 1.98E-07 3.56E-08 Zn-69m 1.44E-09 3.39E&9 3.11E-10 0.00E+00 2.06E-09 3.92E-06 2.14E-05 Br-82 0.00E+00 0.00E+00 2.28E-O6 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Br-83 0.00E+00 0.00E+00 4.30E-OS 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 Br-84 O.OOE+00 0.00E+00 5.41E-08 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 Br-85 0.00E+00 0.00E+00 2.29E-09 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 Rb-86 0.00E+00 2.38E-05 1.05E-O5 0.00E+00 0.00E+00 0.00E+00 2.21E-06 Rb-88 0.00E+00 6.82E-08 3.40E-O8 0.00E+00 0.00E+00 0.00E+00 3.65E-15 Rb-89 O.OOE+00 4.40E-08 2.91E-OS O.OOE+00 O.OOE+00 O.OOE+00 4.22E-17 Sr-89 5.43E-O5 O.OOE+00 1.56E-06 O.OOE+00 O.OOE+00 3.02E-04 4.64E-05 Sr-90 1.35E-02 0.00E+00 8.35E-04 O.OOE+00 O.OOE+00 2.06E-03 9.56E-05 Sr-91 1.10E-08 O.OOE+00 4.39E-10 0.00E+00 O.OOE+00 7.59E-06 3.24E-05 Sr-92 1.19E-09 0.00E+00 5.08E-11 O.OOE+00 O.OOE+00 3.43E-06 1.49E-05 Y-90 3.73E-07 O.OOE+00 1.00E-08 0.00E+00 O.OOE+00 3.66E-05 6.99E-05 Y-91m 4.63E-ll 0.00E+00 1.77E-12 0.00E+00 O.OOE+00 4.00E-07 3.77E-09 Y-91 8.26E-05 0.00E+00 2.21E-06 0.00E+00 O.OOE+00 3.67E-04 5.11E-05 Y-92 1.84E-09 0.00E+00 5.36E-11 0.00E+00 0.00E+00 3.35E-06 2.06E-05 Y-93 1.69E-OS 0.00E+00 4.65E-10 0.00E+00 0.00E+00 1.04E-05 7.24E-05 Zr-95 1.82E&5 5.73E-06 3.94E-06 0.00E+00 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3. 40E&9 1.57E-09 0.00E+00 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 0.00K+00 1.25E-06 9.39E-05 1.21E-05 Nb>>97 3.92E-11 9.72E-12 3.55E-12 0.00E+00 1.14E-11 4.91E-07 2.71E-07 Mo-99 0.00E+00 2.11E-08 4.03E-09 0.00E+00 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 0.00E+00 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 0.00E+00 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 0.00E+00 1.12E-07 0.00E+00 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 0.00E+00 5.42E-11 0.00E+00 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 0.00E+00 1.55E-06 0.00K+00 2.38E-05 2.01E-03 1.20E-04 Ag-110m 1.73E-06 1.64E-06 9.99E-07 0.00E+00 3.13E-06 8.44E-04 3.41E-05 828o

RETS ilanual Revision 9 Page 209 Table 7.7 (4 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

TEEN bone liver t body thyroid kidney lung gi-lli Sb-124 5.38E-06 9.92E-OS 2.10E-06 1.22E-OS O.OOE+00 4.81E-04 4.98E-05 Sb-125 9.23E-06 1.01E-07 2.15E-06 8.80E-09 O.OOE+00 3.42E-04 1.24E-05 Te-125m 6.10E-07 2.80E-07 8.34E-OS 1.75E-07 O.OOE+00 6.70E-05 9.38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E<<07 Te-131m 1.23E-OS 7.51E-09 5.03E-09 9.06E-09 5.49E-OS 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-OS 2.74E-08 3.07E-OS 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 O.OOE+00 1. 14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 O.OOE+00 8.11E-07 I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 O.OOE+00 1.59E-07 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 O.OOE+00 1.29E-06 I-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 O.OOE+00 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 O.OOE+00 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 O.OOE+00 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 O.OOE+00 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 O.OOE+00 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E<<OS 1.07E-07 5.58E-08 O.OOE+00 8.28E-OS 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 O.OOE+00 1.11E-13 S.OSE-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 O.OOE+00 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5. 93E-13 O.OOE+00 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 O.OOE+00 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-OS 7.82E-09 O.OOE+00 0.00E+00 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-11 O.OOE+00 O.OOE+00 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 O.OOE+00 1.11E<<06 7.67E-05 1.58E-05 Ce-143 3.32E-OS 2.42E-OS 2.70E-09 O.OOE+00 1.08E<<OS 1.63E-05 3. 19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 0.00E+00 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-OS O.OOE+00 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E>>12 2.20E-12 2.72E-13 0.00E+00 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-OS O.OOE+00 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1. 22E&9 4.29E-10 O.OOE+00 0.00E+00 5.92E-06 2. 21E-05 Np-239 4.23E-08 3.99E-09 2.21E-09 0.00E+00 1.25E-OS 8.11E-06 1.65E-05

Reference:

Regulatory Guide 1.109, Table E-S.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 7.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

828o

RE S .lanual Revision 9 Page 210 Table 7.7 (5 of 8)

INHALATION DOSE FACTORS (mremipCi inhaled)

CHILD H-3 bone 3.04E-07 liver 3.04E-07 t body 3.04E-07 thyroid 3.04E-'07 kidney lung gi-lli 3.04E-07 3.04E-07 3.04E-07 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1-82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 0.00E+00 0 'OE+00 0.00E+00 1.14E-05 Cr<<51 0.00E+00 O.OOE+00 4.17E-OS 2.31E-08 6.57E-09 4-59E-06 2.93E-07 Mn-54 0.00E+00 1.16E-05 2.57E-06 0.00E+00 2.71E-06 4.26E-04 6.19E-06 Mn-56 O.OOE+00 4.48E-10 8.43E-11 0.00E+00 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 0.00E+00 0.00E+00 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 0.00E+00 0.00E+00 3.43E-04 1.91E-05 Co-57 O.OOE+00 2.44E-07 2.88E-07 0.00E+00 0.00E+00 1.37E-04 3.58E-06 Co-58 0.00E+00 4.79E-07 8.55E-07 0.00E+00 0.00E+00 2.99E-04 9.29E-06 Co-60 0.00E+00 3.55E-06 6.12E-06 0.00E+00 0.00K+00 1.91E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 0.00E+00 0.00E+00 7.43E-05 1.71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 O.OOE+00 0.00K+00 2.21E-06 2.27E-05 CLI-64 0.00E+00 5.39E-10 2.90E-10 0.00E+00 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 0.008+00 1.93E-05 2.69E-04 4.41E-06 Zn-69 1.81E-11 2.61E-ll 2.41E-12 0.00E+00 1.58E>>11 3.84E-07 2.75E-06 Zn-69m 4.26E-09 7.28E>>09 8.59E-10 0.00E+00 4.22E-09 7.36E-06 2.71E-05 Br-82 0.00K+00 0.00E+00 5.66E-06 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Br-83 0.00E+00 0.00E+00 1.28E-07 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Br-84 0.00E+00 0.00E+00 1.48E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0. 00E+00. 6.84E-09 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 Rb-86 0.00E+00 5.36E-05 3.09E-05 0.00E+00 O.OOE+00 0.00E+00 2.16E-06 Rb-88 0.00E+00 1.52E-07 9.90E-08 0.00E+00 0.00E+00 0.00E+00 4.66E-09 Rb-89 O.OOE+00 9.33E-OS 7.83E-08 0.00E+00 0.00E+00 O.OOE+00 5.11E-10 Sr-89 1.62E-04 O.OOE+00 4.66E-06 0.00E+00 O.OOE+00 5.83E-04 4.52E-05 Sr-90 2.73E-02 O.OOE+00 1.74E-03 0.00E+00 0.00E+00 3.99E-03 9.28E-05 Sr-91 3.28E-08 O.OOE+00 1.24E-09 0.00E+00 0.00E+00 1.44E-05 4.70E-05 Sr-92 3.54E-09 0.00E+00 1.42E-10 0.00E+00 0.00E+00 6.49E-06 6.55E-05 Y-90 1.11E-06 O.OOE+00 2.99E-08 0.00E+00 O.OOE+00 7.07E-05 7.24E-05 Y-91m 1.37E-10 0.00E+00 4.98E-12 0.00E+00 0.00E+00 7.60E-07 4.64E-07 Y-91 2.47E-04 O.OOE+00 6.59E-06 0.00E+00 0.00E+00 7.10E-04 4.97E-05 Y-92 5.50E-09 O.OOE+00 1.57E-10 0.00E+00 O.OOE+00 6.46E-06 6.46E-05 Y-93 5.04E-08 0.00E+00 1.38E-09 0.00E+00 0.00E+00 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 0.00E+00 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 0.00E+00 1.05E-08 3.06E-O5 9.49E-05 Nb-95 &.35E-06 2.48E-06 1.77E-06 O.OOE+00 2.33E-06 1.66E-04 1.00E-05 Nb-97 1.16E-10 2.08E-11 9 '4E-12 0.00E+00 2.31E-11 9.23E-07 7.52E-06 Mo-99 0.00E+00 4.66E-08 1.15E-08 0.00E+00 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81E-13 9.41E-13 1.56E-11 0.00E+00 1.37E-11 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2.91E-13 0.00E+00 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 0.00E+00 2.90E-07 0.00E+00 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 0.00E+00 1.50E-10 O.OOE+00 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 O.OOE+00 4.57E-06 0.00K+00 4.97E-05 3.87E-03 1.16E-04 Ag-110m 4.56E-06 3.08E-06 2. 47E-06 0.00E+00 5.74E-06 1.48E-03 2.71E-05 828o

RETS .'lanual Revision 9 Page 211 Table 7.7 (6 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

CHILD Sb-124 bone 1.55E-05 liver 2.00E-07 t body 5.41E-06 thyroid 3.41E-OS kidney lung gi-lli O.OOE+00 8.76E-04 4.43E-05 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-OS O.OOE+00 6.27E-04 1.09E-05 Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0.00E+00 1.29E-04 9.13E-06 Te-127m 6.72E-06 2.31E-06 8.16E-07 1. 64E&6 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2-71E-06 1.52E-05 Te-129m 5.19E-06 1.85E-06 8.22E<<07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2.64E-ll 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 Te-131m 3.63E-OS 1.60E-OS 1.37E-08 2.64E<<OS 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-OS 7.12E-OS 8.58E-OS 4.79E-07 1.02E-04 3.72E-05 I-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 O.OOE+00 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 O.OOE+00 7.68E-07 I-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 O.OOE+00 8.65E-07 I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 O.OOE+00 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 O.OOE+00 2.58E-07 I-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 O.OOE+00 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 0.00E+00 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14E-05 O.OOE+00 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 0.00E+00 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 0.00E+00 1.68E-07 1.84E-OS 7.29E-OS Ba-139 4.98E-10 2.66E-13 1.45E-11 0.00E+00 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-OS 1.17E-06 0.00E+00 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 O.OOE+00 2.56E-14 7.89E-07 7.44E-OS Ba-142 1.35E-11 9.73E-15 7.54E-13 0.00K+00 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-OS 2.04E-08 0.00E+00 0.00E+00 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-ll 0.00E+00 O.OOE+00 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 0.00E+00 2.31E-06 1.47E>>04 1.53E-05 Ce-143 9 '9E-08 5.37E-08 7.77E-09 0.00E+00 2.26E-OS 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 0.00E+00 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E>>06 2.47E-07 0.00E+00 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-ll 4.99E-12 8.10E-13 0.00E+00 2.64E-12 4.23E-07 5.32E-OS Nd-147 2.92E-06 2.36E-06 1.84E-07 0.00E+00 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.61E>>09 1.17E-09 0.00E+00 0.00E+00 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 0.00E+00 2.63E-OS 1.57E&5 1.73E-05

Reference:

Regulatory Guide 1.109, Table E-9.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 6.

NOTE: The tritium dose factor for bone .is assumed to be equal to the total body dose factor.

828o

RETS manual Revision 9 Page 212 Table 7.7 (7 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

INFANT bone 4.62E-07 liver 4.62E-07 t body 4.62E-07 thyroid kidney lung gi-lli H-3 4.62E-07 4. 62E-07 4. 62E-07 4.62E-07 C-14 1.89E-05 3.79E-06 3. 79E-06'.54E-06 3.79E-06 3.79E<<06 3. 79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7. 54E-06 7.54E-06 P-32 1.45E-03 8.03E+05 5.53E-05 0.00E+00 0.00E+00 0.00E+00 1 ~ 15E-05 Cr-51 O.OOE+00 0.00E+00 6.39E-OB 4.11E-OS 9.45E-09 9.17E-06 2.55E-07 Hn-54 O.OOE+00 1.81E&5 3.56E-06 O.OOE+00 3.56E-06 7.14E-04 5.04E-06 Nn-56 0.00E+00 1.10E-09 1.58E-10 0.00E+00 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 0.00E+00 0.00E+00 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 O.OOE+00 0.00E+00 7.25E-04 1.77E-05 Co-57 O.OOE+00 4.65E-07 4.SBE-07 O.OOE+00 0.00E+00 2.71E-04 3.47E-06 Co-58 0 'OE+00 8.71E-07  %.30E-06 0.00E+00 0.00E+00 5.55E-04 7.95E-06 Co-60 0 ~ OOE+00 5.73E-06 8.41E-06 O.OOE+00 0.00E+00 3.22E-03 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 0.00E+00 0.00E+00 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-11 0.00E+00 0.00E+00 5.80E-06 3.58E-05 CQ-64 0.00E+00 1.34E&9 5.53E-10 0.00E+00 2.84E-09 6.64E-O6 l. 07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 0.00E+00 2.32E-05 4.62E>>04 3.67E-05 Zn-69 3.85E-11 6.91E-ll 5.13E-12 0.00E+00 2.87E-ll 1.05E-06 9.44E>>06 Zn-69m 8.98E-09 1. 84E-08 1.67E-09 0.00E+00 7.45E-09 1.91E-05 2.92E-05 Br-82 0.00E+00 O.OOE+00 9.49E-06 O.OOE+00 0.00E+00 0.00K+00 O.OOE+00 Br-83 O.OOE+00 0.00E+00 2.72E-07 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00K+00 2.86E-07 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 Br-85 O.OOE+00 0.00E+00 1.46E-OS O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Rb-86 0.00E+00 1.36E-04 6. 30E&5 0.00E+00 O.OOE+00 O.OOE+00 2.17E-06 Rb-88 O.OOE+00 3.98E-07 2.05E-07 0.00E+00 0.00E+00 0.00E+00 2.42E-07 Rb-89 O.OOE+00 2.29E-07 1.47E-O7 O.OOE+00 O.OOE+00 O.OOE+00 4.87E>>OS Sr-S9 2.84E-04 O.OOE+00 8.15E-06 O.OOE+00 O.OOE+00 1.45E-03 4.57E-05 Sr-90 2.92E-02 O.OOE+00 1.85E-03 0.00E+00 O.OOE+00 8.03E-03 9.36E-05 Sr-91 6.83E-OS 0.00E+00 2.47E-09 0.00E+00 O.OOE+00 3.76E-05 5.24E-05 Sr-92 7.50E-09 0.00E+00 2.79E-10 O.OOE+00 O.OOE+00 1.70E-05 1.00E-04 Y-90 2.35E-06 0.00E+00 6.30E-OB O.OOE+00 0.00E+00 1.92E>>04 7.43E-05 Y-91m 2.91E-10 O.OOE+00 9.90E-12 0.00E+00 O.OOE+00 1.99E-06 1.68E-06 Y-91 4 '0E-04 O.OOE+00 1.12E-05 O.OOE+00 0.00E+00 1.75E-03 5.02E-05 Y-9? 1.17E<<OB 0.00E+00 3.29E-10 0.00E+00 0.00E+00 1.75E-05 9.04E-05 Y-93 1.07E-07 0.00E+00 2.91E-09 0.00E+00 O.OOE+00 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 O.OOE+00 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-OS 8.36E-09 0.00E+00 1.85E-OS 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 0.00E+00 3.37E-06 3.42E-04 9.05E-06 M)-97 2.44E-10 5.21E>>11 1.88E-11 O.OOE+00 4.07E-11 2.37E-06 1.92E-05 No-99 O.OOE+00 l. 18E&7 2.31E-OB 0.00E+00 1.89E-07 9.63E-05 3.48E-05 Tc-99m 9.98E-13 2.06E-12 2.66E-11 0.00E+00 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E>>04 5.80E-13 0.00E+00 6.99E-13 4.17E-07 6.03E-07 RU-103 1.44E-06 0.00E+00 4.85E-07 0.00E+00 3.03E-06 3.94E-04 1 ~ 15E-05 Ru-105 8.74E-10 0.00E+00 2.93E-10 O.OOE+00 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 0. OOE+00 7.77E-06 0.00E+00 7.61E-05 8.26E-03 1.17E-04 Ag-110m 7.13E-06 5. 16E-06 3.57E-06 0.00E+00 7.80E-06 2. 62E&3 2.36E-05 828o

RETS Manual Revision 9 Page 213 Table 7.7 (8 of S)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

INFANT bone liver t body thyroid kidney lung gi-lli Sb-124 2.71E-05 3.97E-07 8.56E-06 7.18E-OS O.OOE+00 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 O.OOE+00 1'.17E-03 1.05E-05 Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 O.OOE+00 3-19E-04 9.22E-06 Te-127m 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E<<10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1-20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E-OS 3.93E-OS 2.59E-08 6.38E-OS 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-ll 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3. 15E-05 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 O.OOE+00 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 O.OOE+00 7.56E-07 I-132 1.21E>>06 2.53E>>06 8.99E-07 1.21E-04 2.82E-06 O.OOE+00 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 O.OOE+00 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 O.OOE+00 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 O.OOE+00 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 O.OOE+00 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 O.OOE+00 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.2SE-05 0.00E+00 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 O.OOE+00 2.93E-07 4.67E-OS 6.26E-07 Ba-139 1.06E>>09 7.03E>>13 3.07E-11 0.00E+00 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.00E>>O5 4.00E-OS 2.07E-06 O.OOE+00 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 0.00E+00 4.64E-14 2. 12E&6 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 O.OOE+00 1.36E-14 1. 11E&6 4.95E<<07 La-140 3.61E-07 1.43E-07 3.68E-08 0.00E+00 0.00E+00 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-ll 0.00E+00 O.OOE+00 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 0.00E+00 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-OS O.OOE+00 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.26E-04 0.00K+00 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E&5 3.74E-06 4.99E-07 0.00E+00 1.41E-06 3.09E-04 2. 66E&5 Pr-144 3.42E-11 1.32E-ll 1.72E<<12 0.00E+00 4.80E-12 l. 15E&6 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 0.00E+00 2.25E-06 2. 30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 O.OOE+00 O.OOE+00 2.83E-05 2.54E-05 Np-239 2. 65E.&7 2.37E-OS 1.34E-08 O.OOE+00 4.73E-OS 4.25E-05 1.78E-05

Reference:

Regulatory Guide 1.109, Table E-10.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 5.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

828o

RETS Manual Revision 9 Page 214 Figure 7.1 OFFGAS SYSTEM AND SGTS EFFLUENT MONITORING Elevated Release (600 feet) from common stack RM SO-147 A & B Fl 90-271 From SGTS (common) Dllutlon Alr Steam Packing Exhauster (1 of 3)

Mechanical Vacuum Pump SJAE Condenser Recombine re Charcoal Adsorber Vessels 8000 cubic foot Holdup Volume 828o

Cl sQ'~

f

RETS Menue>

Revision 9 page 215 Figure 7.2 NORMAL BUILDING VENTiLATION ROOF FANS r '\ a

~

a I

~ ~

~

I p t 'L

~

~ ir Refuel Turbine Oeck Floar RM 90.249 Turbine Building Control Reactor Building tTyplcal for each unit) Bay Qpical for each unit}

to eQTS (enwrap~

wahaeon)

" Used seasonally to control temperature 828o

RETS Manual Revision 9 Page 2l6 Figure 7.3 PLUME DEPLETION EFFECT (Page l of 4) 0S 0.7 O

R g 0.6 X

W 0ri z

O 6 0A 0,1 0.1 1.0 10.0 PLUME TRAVEL OfSTANCE fKILOfHETERS) plume oeoletion Effect for cround Lerel Releeeet {AllAtrrioroheric stability clatter) 828o

RETS Manual Revision 9 Page 217 Figure 7.3 PLUME DEPLETION EFFECT (Page 2 of 4)

NEUTRAL Iht GI ssr OA X

CL'NST 0.7 U

R X 0.6 IAB

~~ OS Z

O o OA 0.1 1A) 10.0 100$ ',f00.0 PLUME TRAVEL DISTANCE (KILOMETERS)'

Plssrne Depletson Effect for 30sn Relent. (Letters denote Pesqolfl StebBIty C4ssl.

828o

0 RETS Manual Revision 9 Page 218 Figure 7.3 PLUME DEPLETION EFFECT (Page 3 of 4)

STAS LE (E,F,CI IIEUTR ur OAt (D

~ 0.3 Z

0.6 X

~~ OS Z

0 OA 0.3 0.3 0.1 1A 10.0 (00.0 20 0 PLUME TRAVEL DISTANCE IKILOLIETERS)

Plums Dsolstioo E(fact (or 60m Rslsasst (Lsttsrs dsrtots Pasrtuill Stability Ctsts) 828o

RETS Manual Revision 9 Page 219 Figure 7.3 PLUME DEPLETION EFFECT (Page 4 of 4)

NEUTRAL IDJ

~ u 0$

UNSTABLE 0.7 fag)

STABLE IE.F.G) z NO DEPLETION.

z 0.0 C (FRACTION REMAINING ~

c 0$

O 0.4

(

t 0.2 0.1 0.1 1A) 10.0 PLUME TRAvEL DlsTANcE IKILDMETERs)

PIutoe Deyledon Effect for 10htt Reteetet ILettett denote&sqoiII Stability Cleat) 828o

RETS Manual Revision 9 Page 220 Figure 7.4 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME 1000 100

~: 10 0.1 1.0 10 100 PLUME TRAVEL DlSTANCE (KlLOMETERS)

Vertical Standard Deviation of Material in a Plume (Letters denote PasquWI Stability Class) 828o

4I RETS Manual Revision 9 Page 221 Figure 7,5 RELATIVE DEPOSITION (Page I of 4) 10<

10 7 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

Relative Deposition for Ground-Level Re<eases jAii Atmospheric Stability Classesi 828o

RETS Manual Revision 9 Page 222 Figure 7.5 RELATIVE DEPOSITION (Page 2 of 4) 10"3 UNSTABLE (A CC tu I

LLJ NEUTRAL UJ I-CL z NEUTRA L(D 10~ BLE CO O

0 I-ill tt:

STABLE (E,F,G) 10-7 0.1 1.0 10.0 100.0 200 0 PLUME TRAVEL DISTANCE (Kll OMETERS)

Relative Deposition for 30~ Releases (Letters denote Pasquill Stability Class) 828o

~ I ~

RETS Nanual Revision 9 Page 223 Figure 7.5 RELATIVE DEPOSITION (Page 3 of 4)

UNSTABLE (A,B C NEUTR AL (D)

UN ABLE NEUTRAL (E,F,G) 10-8 0.1 1.0 10.0t 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

Relative Deposition for 60~ Releases ILetters denote Pasquill Stability Class) 828o

RETS Manual Revision 9 Page 224 Figure 7.5 RELATIVE DEPOSITION (Page 4 of 4)

UNSTABLE( AP 10-S NEUTRAL (D)

LE (E,F,G)

NO DEPL'ET ION 10 7 10-8 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

Relative Deposition for 100.rn Releases (Letters denote Pasquill Stability Class) 828o

0 RETS Manual Revision 9 Page 225 SECTION 8.0 TOTAL DOSE 828o

0 RETS Manual Revision 9 Page 226 8.0 TOTAL DOSE To determine compliance with 40 CFR 190, the annual dose contributions to the maximum individual from BFN radioactive effluents and all other nearby uranium fuel cycle sources will be considered. The annual dose to the maximum individual will be conservatively'stimated by: first, suaaaing the total body air submersion dose, and the critical organ dose (except thyroid) from gaseous effluents; the total body dose, and critical organ dose (except thyroid) from liquid effluents for each quarter calculated in accordance with Sections 6.6 and 7.7. Then to this sum for each quarter is added any identifiable increase in direct radiation dose levels attributable to the plant as determined by the environmental monitoring program outlined in Section 9.0. These quarterly sums are then conservatively suaxned for the four calendar quarters to estimate the maximum individual dose for the year. This dose is compared to the limit in Control 3'.2.3, i.e., 25 mrem per year to the total body or any organ (except thyroid), to determine compliance.

The total annual thyroid dose to the maximum individual will be conservatively estimated in the following manner. For each calendar quarter, a total dose will be obtained by summing the total body gaseous submersion dose, the gaseous thyroid dose, the liquid total body dose, and the liquid thyroid dose. To this sum for each quarter is added any identifiable increase in direct radiation dose levels attributable to the plant as determined by the environmental monitoring program outlined in Section 9.0. These quarterly sums are then added together to estimate the maximum individual thyroid dose for the year. This dose is compared to the limit in Control 3.2.3, i.e., 75 mrem per year to determine compliance.

828o

RETS Manual Revision 9 Page 227 SECTION 9.0 ENVIRONMENTAL MONITORING PROGRAM 828o

RETS Manual Revision 9 Page 228 9.1 MONITORING PROGRAM DESCRIPTION An environmental radiological monitoring program as described in Tables 9.1, 9.2 and 9.3 and in Figures 9.1, 9.2, and 9.3 shall be conducted. Results of this program shall be reported in accordance with ODCM Administrative Control 5.1.

The atmospheric environmental radiological monitoring program shall consist of 10 monitoring stations from which samples of air particulates and radioiodine shall be collected.

The terrestrial monitoring program shall consist of the collection of milk, soil, drinking water, and food crops. In addition, direct gamma radiation levels will be measured at 40 or more locations in the vicinity of the plant.

The reservoir sampling program shall consist of the collection of samples of surface water, sediment, and fish.

9.2 DETECTION CAPABILITIES Analytical techniques shall be such that the detection capabilities listed in Table 2.3-2 are achieved.

9.3 LAND USE CENSUS A land use survey shall be conducted in accordance with the requirements in Control 1.3.2. The results of the survey shall be reported in the Annual Radiological Environmental Operating Report.

9.4 INTERLABORATORY COMPARISON PROGRAM Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the NRC. A summary of the results obtained in the intercomparison shall be included in the Annual Radiological Environmental Operating Report (or the EPA program code designation may be provided).

If analyses are not performed as required corrective actions taken to prevent, a recurrence shall be reported in the Annual Radiological Environmental Operating Report.

828o

RETS Manual Revision 9 Page 229 Table 9.1 (1 of 5)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency Sam le Locations Collection Fre uenc of Anal sis AIRBORNE Particulates 6 samples from Continuous sampler Particulate sampler.

locations (in operation with sam- Analyze for gross different sectors) ple collection as beta radioactivity at or near the required by dust )24 hrs following site boundary loading but at least filter change.

(LM-1, LM-2, once per 7 days. Perform gamma isotopic LM-3, LM-4, analysis on each LM-6, and LM-7) sample when gross beta activity is >10 2 samples from times the average of control locations control samples.

greater than 10 Perform gamma miles from isotopic analysis the plant on composite (by (RM-1 and RM-6) location) sample at least once per 3 samples from 31 days.

locations in communities approx-imately 10 miles from the plant (PM-1, PM-2 and PM-3)

Radioiodine Same locations as Continuous sampler I-131 every 7 days air particulates operation with charcoal canister collection at least once per 7 days SOIL Samples from same Once every year Gamma scan, Sr-.89, locations as air Sr-90 once per year particulates DIRECT 2 or more dosi- At least once per Gamma dose once per meters placed at 92 days 92 days locations (in dif-ferent sectors) at or near the site boundary in each of the 16 sectors 828o

RETS Manual Revision 9 Page 230 Table 9.1 (2 of 5)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Path~ay Number of Samples and/or and Sample Sampling and Type and Frequency Sam le Locations Collection Fre uenc of Anal sis DIRECT (con- 2 or more dosi- At least once per Gaama dose once per tinued) meters placed at 92 days. 92 days.

stations located approximately 5 miles from the plant in each of the 16 sectors 2 or morc dosi-meters in at least 8 additional locations of special interest WATERBORNE Surface 1 sample upstream Collected by auto- Ganana scan at (TRM 305.0) matic sequential- least once per 31 1 sample im- type sampler with days. Composite for mediately down- composite sample tritium at least once stream of dis- taken at least once per 92 days charge (TRM 293.5) per 31 daysa.

1 sample from plant down-'tream (TRM 285.2)

Drinking 1 sample at the Collected by auto- Gross beta and gamma first potable matic sequential- scan at least once surface water type sampler with per 31 days. Compo-supply downstream composite sample site for Sr-89, Sr-90 from the plant taken at least once and tritium at least (TRM 282.6) per 31 daysa b once per 92 days.

Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

b This assumes that the nearest drinking water intake is >3.0 mile downstream of the plant discharge. If a drinking water intake is constructed within 3.0 miles downstream of the plant discharge, sampling and analysis shall be every 2 weeks.

828o

RETS Manual Revision 9 Page 231 Table 9.) (3 of 5)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency Sam le Locations Collection Fre uenc of Anal sis Drinking 2 additional sam- Grab sample taken Gross beta and gamma (continued) ples of potable at least once per scan at least once surface water 31 days. per 31 days.

downstream from Composite for Sr-89 the plant and Sr-90 and tritium (TRM 274.9 and at least once per TRM 259.5) 92 days 1 sample at a control location (TRM 306) 1 additional Collected by auto-sample at a con- matic sequential-trol locationc type sampler with (TRM 305) composite sample taken at least once per 31 daysa GROUND 1 sample adjacent Collected by auto- Composite for gamma to the plant matic sequential- scan, Sr-89, Sr-90,

{well 06) type sampler with and tritium at least composite sample once per 92 days.

taken at least once per 31 days.

1 sample at a Grab sample taken Composite for gamma control location at least once per scan, Sr-89, Sr-90, upgradient from 31 days. and tritium at least the plant once per 92 days.

(Farm Bn)

AQUATIC Sediment 2 samples At least once per Gamma scan, Sr-89, upstream from 184 days and Sr-90 analyses discharge point (TRM 297.0 and TRM 307.52) a Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours.

The surface water control sample shall be considered a control for the drinking water sample.

828o

RETS Manual Revision 9 Page 232 Table 9.1 (4 of 5)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency Sam le Locations Collection Fre uenc of Anal sis Sediment 1 sample in At least once per Gamma scan, Sr-89 and (continued) iaxnediate down- 184 days Sr-90 analyses stream area of discharge point (TRM 293.7) 2 additional samples down-stream from the plant(TRM 288. 78 and 277.98)

INGESTION Milk At least 2 At least once per Gamma scan and I-131 samples from 15 days when animals on each sample.

dairy farms in are on pasture; at Sr-89 and Sr-90 at the immediate least once per 31 least once per 31 days vicinity of the days at other times.

plant {Farms B and Bn)

At least 1 sample from control lo-cations (Farm Gl or Be)

Fish 3 samples repre- At least once per Gamma scan at least senting commercial 184 days once per 184 days on and game species edible portions.

in Guntersville Reservoir above the plant 3 samples repres-enting commercial and game species in Wheeler Reservoir near the plant 828o

RETS Manual Revision 9 Page 233 Table 9.1 (5 of 5)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency

~Sam le Locations Collection Fre uenc of Anal sis Clams 1 sample down- At least once per Gamma scan on flesh stream from the 184 days. only discharge 1 sample upstream from the plant.

(No permanent stations established; depends on avail-ability of clams).

Fruits & Samples of food At least once per Gamma scan on edible Vegetables crops such as year at time 'of portion corn, green beans, harvest tomatoes, and potatoes grown at private gardens and/or farms in the immediate vicinity of the plant 1 sample of each of the same foods grown at greater than 10 miles distance from the plant Vegetation Samples from Once per 31 days I-131, gamma scan (pasturage) farms producing once per 31 days.

milk but not Sr-89 and Sr-90 providing a milk analysis on the last sample (Farm T). monthly sample of each quarter.

Control sample from ) control dairy farm (Farm Gl) 828o

RETS Manual Revision 9 Page 234 Table 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Map Approximate Indicator (I)

Location Distance or Samples Number a Station Sector (Mi'les) Control (C) Collected 1 PM-1 NW 13.8 I AP,CF,S 2 PM-2 NE , 10.9 I AP,CF,S 3 PM-3 SSE 7.5 I AP,CF,S 4 LM-7 W 2.1 I AP,CF,S 5 RM-1 W 31.3" C AP,CF,S 6 RM-6 E 24.2 C AP,CF,S 7 LM-1 N 1.0 I AP,CF,S 8 LM-2 NNE 0.9 I AP, CF, S 9 LM-3 ENE 0.9 I AP,CF,S 10 LMM NNW 1.7 I AP,CF,S 11 LM-6 SSW 3.0 I APe CFs S 12 Farm B NNW 6.8 I M 13 Farm Bn N 5.0 I M, W 18 Farm GI WSW 35 C M% V 22 Well 86 NW 0.02 I W 23 TRM 282.6 11.4d. I PW 24 TRM 303.0 12.0 C PW 25 TRM 259 ' 34.4d I PW 26 TRM 274.9 I PW 27 TRM 285.2 8.8d I SW 28 TRM 293.5 0.5d I SW 29 TRM 305.0 11.0d Ce SW 30 TRM 307.52 13.52 C SD 31 TRM 293.7 0-3d I SD 32 TRM 288.78 5.22d I SD 33 TRM 277.98 16.02d I SD 34 Farm Be NW 28.8 C M 36 Farm T WNW 3.2 I V 37 TRM 297 ~ 0 3.0 I F Wheeler Reservior I/O F, CL (TRM 275-349)

Guntersville Reservior (TRM 349-424)

See Figures 9.1, 9.2, and 9.3 Sample codes:

AP = Air particulate filter S = Soil SD = Sediment CF = Charcoal Filter SW = Surface Water CL = Clams F = Fish V = Vegetation PW = Public Water W = Well Water M = Milk TRM = Tennessee River Mile Miles from plant discharge (TRM 294)

Also used as a control for public water 828o

RETS Manual Revision 9 Page 235 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS Map Approximate Onsite (On)a Location Distance or Number Station Sector (Miles) Offsite (Off) 1 NW-3 NW 13.8 Off 2 NE-3 NE 10.9 Off 3 SSE-2 SSE 7.5 Off 5 W-3 W 31.3 Off 6 E-3 E 24.2 Off 7 N-1 N 1.0 8 NNE-1 NNE 0.9 On 9 ENE-1 ENE 0.9 10 NNW-2 NNW 1.7 38 N-2 N 5.0 Off 39 NNE-2 NNE 0.7 40 NNE-3 NNE 5.2 Off 41 NE-1 NE 0.8 42 NE-2 NE 5.0 Off 43 ENE-2 ENE 6.2 Off 44 E-1 E 0.8 45 E-2 E 5.2 Off 46 ESE-1 ESE 0.9 47 ESE<<2 ESE 3.0 Off 48 SE-1 SE 0.5 On 49 SE-2 SE 5,4 Off 50 SSE-1 SSE 5.1 Off 51 S-l S 3.1 Off 52 S-2 S 4.8 Off 53 SSW-2 SSW 3.0 Off 54 SSW-2 SSW 4.4 Off 55 SW-1 SW 1~9 On 56 SW-2 SW 4,7 Off 57 SW-3 SW 6.0 Off 58 WSW-1 WSW 2.7 Off 59 WSW-2 WSW 5.1 Off 60 WSW-3 WSW 10.5 Off 61 W-1 W 1.9 62 W-2 W 4' Off 63 W-4 W 32.1 Off 64 WNW-1 WNW 3.3 Off 65 WNW-2 WNW 4.4 Off 66 NW-1 NW 2.2 Off 67 NW-2 NW 5.3 Off 68 NNW-l NNW 1.0 On 69 NNW-3 NNW 5.2 Off TLDs designated onsite are those located two miles or less from the plant.

TLDs designated offsite are those located more than two miles from the plant.

828o

RETS Manual Revision 9 Page 236 Figure 9.1 SAMPLING LOCATIONS ENVIRONMENTAL RADIOLOGICAL WITHIN 1 MILE OF THE PLANT 348. 75 1 1.25 NNW NNE 326.2 33.75 68 ~ 8 NE 303.75 28 39'81.25 41'NE t,o~ 78.75 31e L ~ 44 101.25 258.? 5 BROWNS FERRY NUCLEAR PLANT ~ 46 48 WSW ESE 123.75 236.25 SW SE 213.75 146.25 SSW SSE 191.25 168.75 Scale Mlle 828o

~ R

~AL >>guz'e RADIOLOCIC 9.2 RET'S Revision Page 237 l%aaua1 9

%08 I TO S fILES 49'LINC PROD THE p~ LOOAZ'IONS 345,75 325>S 1125 4

l13 HW HHE 303.75 P~

++

dp 0

~rC 6

dp

~ fo

36. 6<

25d.yd 75.75 SSO11tHS

~op~

QC4+411

~dH1 5$

47 23d>5 P +101.2 5 g+ 0 A

ESE 56+

13.75 123.75

~ S4 SSQ 101,25 14d.25 SSE 155+1S SCW1,E 0.5 501 ES 828o

RETS Manual Revision 9 Page 238 Figure 9.3 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS GREATER THAN 5 MILES FROM THE PLANT 3S8.75 1 1.25 328.25 33.75 AWR E HCESIIR0 ROLASKI 303.75 FAYETTEVILLE 5&25 31 261.25 FLOREHC ATHENS 7&75 A

LAAI 6 I i+F FI 2

SE ~

2 SCLE SHOAl 43 45 TSVILLE 83 57 1

3 PF 258.75 SS DECATLI 101.25 RUSSFLVILLE l6 WSW OW4a VALC ARAS 326.25 HALEYVILLE 123.75 CVLLIAAH 213.75 148.25 SCALE SSW 10 I Q SS MILES 16 1.25 168.75 828o

RETS Manua1 Revision 9 Page 239 RETS MANUAL Section IV PROCESS CONTROL PROGRAM (PCP IV-1 828o

RETS Manual Revision 9 Page 240

1.0 INTRODUCTION

1.1 ~Sco e This Process Control Program (PCP) is applicable to radioactive waste solidification and dewatering of wet solid radioactive wastes generated as a result of the operation and maintenance of Browns Ferry Nuclear Plant. This PCP is not applicable to the treatment of mixed wastes.

1.2 ~Pur ose The PCP provides those controls necessary to ensure that disposal criteria are met by BFN processing techniques, or by vendor supplied systems, if used for dewatering or solidification.

2.0 DEFINITIONS 2.1 Absorb - To take liquid in through pores, or as if through pores or interstices of a material.

2.2 Absorbent Media or material used to absorb liquid.

2.3 Batch An isolated quantity of waste to be processed having constant physical and chemical characteristics.

2.4 Container - The primary receptacle in which processed wastes (dewatered, solidified or absorbed) are packaged for disposal.

2.5 Dewatered Wet solid wastes which have had excess water removed.

2.6 Free Liquid Uncombined liquid not bound by the solid matrix of the solid waste mass; capable of flowing.

2.7 Homogeneous Of uniform composition; the waste is uniformly distributed throughout the container.

2.8 Liquid waste For the purposes of this PCP, any aqueous or non-aqueous radioactive liquid which requires solidification or absorption before disposal. This may include oils, chemicals, water or other liquids unsuitable for in-plant clean-up or treatment.

IV-2 828o

.~

RETS Manual Revision 9 Page 241 2.9 Mixed waste Low level radioactive wastes containing chemical constituents which are hazardous under Environmental Protection Agency regulations in 40 CFR Part 261.

2.10 Solidification agent Material, which when mixed in prescribed proportions with liquid or wet solid wastes, can form a free standing product with no free liquid.

2.11 Solidify To inmobilize by use of a solidification agent or method which converts the liquid or wet solid waste to a free standing monolithic solid.

2.12 Stability A property of the waste form such that it is able to maintain its structural integrity under the expe'cted disposal conditions; stabilized waste should maintain its gross physical properties and identity over a 300 year period.

2.13 Wet solid wastes Spent powdered ion exchange resins, filter aid sludge, bead ion exchange resins, and other sludges or slurries consisting of liquids with a high insoluble solid content.

3.0 REFERENCES

3.1 Code of Federal Regulations (CFR) Title 10, Parts 20, 61, and 71

[10 CFR 20, 10 CFR 61, and 10 CFR 71] Energy 3.2 Code of Federal Regulations (CFR) Title 49 [49 CFR) Transportation 3.3 Browns Ferry Nuclear Plant Final Safety Analysis Report, Volume 4, Chapter 9.3, Solid Radwaste system 3.4 Browns Ferry Nuclear Plant Technical Specifications (BFN Tech Spec) 4.8.F.l, 3.8.F.1 & 3.8.F.2, 6.10.1.f, and 6.11.1, 2 & 3 3.5 TVA Office of Nuclear Power Radioactive Material Shipment Manual (RMSM) 3.6 Nuclear Regulatory Commission (NRC) Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Classification, May 1983, Rev. 0 3.7 Nuclear Regulatory Commission (NRC) Technical Position on Waste Form, May 1983, Rev. 0 3.8 Topical Report No. TP-02-NP-A Rev. 0 IV-3 828o

RETS Manual Revision 9 Page 242

4. 0 WASTE CHARACTERISTICS 4.1 Waste Streams Three general waste streams applicable to this PCP have been identified for Browns Ferry. These are the Condensate Waste Phase Separator (CWPS), Reactor Water Cleanup Phase Separator (RWCU), and Dry Active waste (DAW). Other waste streams may be established based upon plant operational needs.

CWPS is fed by several waste sub-streams, including the Equipment Drain, Chemical Waste, Floor Drain, Fuel Pool Cooling, and Condensate systems.

RWCU is fed by Reactor Water Cleanup only.

DAW is used for wastes generated within the regulated areas of the reactor buildings and turbine buildings which cannot be appropriately attributed to either RWCU or CWPS. DAW normally includes paper, plastic, wood, metal and other such material generated as a result of the operation and maintenance of the plant.

4.2 Waste Form Wet solid radioactive wastes consist of bead resins, filter aids (such as activated charcoals or carbons), powdered resins, and slurries or sludges.

Wastes which may require solidification may include, but are not limited to, liquids which cannot be processed using installed plant systems, oils, chemicals, aqueous filter media, and decontamination wastes.

Wastes are processed as appropriate to ensure that the minimum physical characteristics required by 10 CFR and disposal site criteria are met. All Class B and Class C waste is stabilized. On occasion, Class A waste (such as aqueous filter media with a concentration > 1 uCi/cc of isotopes with half-lives > 5 years) may be solidified or stabilized by BFN. Class A liquid wastes may be either solidified or packaged in sufficient absorbent material to absorb twice the volume of the liquid, as appropriate to the specific disposal site criteria or license requirements.

Tests are performed on those wastes which are solidified to ensure the adequacy of the solidification agent and procedural technique.

These tests are made on a minimum of three samples from each waste batch to be solidified.

IV-4 828o

RETS Manual Revision 9 Page 243 4.3 Waste Classification Scaling factors which relate hard-to-measure isotopes to key isotopes commonly measured at BFN have been developed for each waste stream. These scaling factors are used in the classification of the waste for disposal. Scaling factors may be developed on an as needed basis depending on changing plant operational conditions. Updates are performed at least every two years for waste normally considered to be Class A, on an annual basis for other wastes, or when the scaling factors are considered to be high or low by a factor of ten.

Batch samples, separator samples, or sludge samples are taken fox radiochemical analysis prior to processing the waste for shipment.

DAW samples or area smears are taken to establish the relative percent abundance of isotopes for, the DAW waste stream.

Materials which do not fit within the scope of existing scaling factors and waste streams are sampled. The samples are sent offsite for analysis and development of scaling factors prior to disposal of the materials.

5.0 SHIPMENT MANIFESTS 5.1 Manifest Pre aration Manifests axe prepared for each shipment of radioactive waste for disposal. Programmatic guidance for manifest preparation is provided through the TVA Office of Nuclear Power, Radwaste Branch to ensure that all 10 CFR and 49 CFR criteria are met. Procedures for manifest preparation implement the specific requirements of 10 CFR 20.311, Transfer for Disposal and Manifests.

5. 2 Manifest Trackin Acknowledgment of receipt for each shipment to a disposal site is sent to BFN Radwaste Group by the disposal site. Shipments for which acknowledgment is not received within the time limits allowed in 10 CFR 20.311 are traced by the TVA Office of Nuclear Power, Radwaste Branch.

IV-5 828o

RETS Manual Revision 9 Page 244

6. 0 ADMINISTRATIVE CONTROLS 6.1 Procedures and Surveillance Detailed procedures are written and maintained by BFN which cover plant process systems, waste packaging, and shipment requirements.

Surveillance Instructions are used to verify that plant Technical Specifications for waste processing are met.

Programmatic guidance is provided through the TVA Office of Nuclear Power, Radwaste Branch. The Radwaste Branch maintains the Radioactive Material Shipment Manual and the Package Quality Assurance Program (for packages licensed under 10 CFR 71).

6.2 ualit Assurance/ ualit Control Quality assurance audits are conducted by the BFN site Quality Assurance organisation, and by the TVA Division of Nuclear Quality Assurance (DNQA). Audit findings are reviewed by BFN management, ensuring prompt corrective actions when needed.

Quality control measures include quarterly tests of the resin dewatering system performed by BFN personnel upon actual dewatered High Integrity Containers (HICs) or liners, site review of all radwaste vendor procedures before use, and second party verification by BFN personnel of end points or acceptance criteria in vendor procedures. Quality control of solidification methods is performed through controlled testing of a minimum of three samples from each batch to be solidified. Proportions of solidification agents are established which meet the standards for waste form and free liquid criteria.

6. 3 ~Tra itin Personnel involved in processing radioactive waste for shipment are trained in site procedures, regulatory requirements, and disposal site criteria. Training and retraining sessions are held when needed to support operations. Retraining is required on an annual basis to maintain qualification. Personnel found not complying with procedures may have their qualifications revoked by the Radwaste Group Supervisor, if deemed necessary. Qualifications may be reestablished through completion of retraining, and approval of the Radwaste Group Supervisor.

IV-6 828o

RETS Manual Revision 9 Page 245 6.4 Retention of Records Records are maintained to furnish documentation of items or activities affecting quality. Quality assurance records are stored in accordance with plant instructions and the TVA Nuclear Quality Assurance Manual. Retention times for radwaste records are established in the Radioactive Material Shipment Manual.

7.0 APPENDICES 7.1 Solidification Descri tion Topical Report

Reference:

None System or method in use: None Plant/Equipment Interfaces: None 7.2 Dewaterin Descri tion Topical Report

Reference:

DW-11118-01-P-A, Chem Nuclear Systems, Inc., CNSI Dewatering Control Process Containers, and RDS-25506-01-P, Chem Nuclear Systems, Inc., RDS-1000 Radioactive Waste Dewatering System, Rev. 0 NOTE: See appended letter of interim approval from NRC to TVA of May 6, 1988.

Topical Report

Reference:

TP-02-NP-A, Nuclear Packing, Inc.

Covering Nuclear Packaging, Inc. Dewatering System, Rev. 0.

System or method in use: Vacuum dewatering using portable air driven diaphragm pumps and 10 HP electric high vacuum pump; and/or, Vacuum dewatering/high speed drying using the CNSI RDS-1000 Radioactive Waste Dewatering System; and/or pressure vessel dewatering using portable air driven pumps, and/or Nuclear Packaging, Inc. Dewatering System.

Plant/Equipment Interfaces: See appended letters of February ll, 1987 and October 16, 1987 from TVA to NRC.

{RIMS ffL44 870211 808 and OL44 871016 807), and Attachment 1 and 2.

IV-7 828o

0 RETS Manual Revision 9 Page 246 gt g i7;". 0 7 3 0 gy0811 808 5N 1578 Lookout Place

~HB'11887 U.S. Nuclear Regulatory Coswcission Attn: Document Control Desk Office of Nuclear'eactor Regulation Washington, D.C. 20555 Attention: Mr. D. R. Muller In the Matter of the Docket Nos. 50-259 Tennessee Valley Authority 50-260 50-296 BROGANS FERRY NUCLEAR PLANT (BFN) - PROCESS CONTROL PROGRAM FOR DEMINERALIZER RESIN DEMATERINC Demineralixer resin devatering is performed at BFN using equipmont fabricated by TYA to meet Chem-Nuclear Systems, Inc., (CNSI) equipment speciflcitions.

BFN has adopted the operating methodology outlined by CNSI in a topical report (CNSI-tN-11118-01-p) titled, "CNSI Dentering Control Process Containers Topical Report." NRC accepted this topical report for reference by license applicants in a letterfrom C. O. Thomas (NRC) to L. K. Poppe (CNSI) dated June 11, 1985.

The enclosure provides information required by NRC to revise applicability of the report to specific licensees as outlined in the associated safety evaluation. Me request that NRC revise the enclosed information and provide approval for use of this report as a process control program as defined in the Radiological Effluent Technical Specification (RETS) amendment (TVA BFN.

TS-221, dated September 30, 1986). It is further requested that NRC approval oF the process control program coincide arith the RETS implementation date or that the submittal be accepted on an interim basis until approval of the program is finalized.

If you have any questions concerning this request, please call L. V. Tonty at (205) 729-2677.

Very truly yours, TENNESSEE V+1+Y AUTHORITY (ggfgQ Sig

~ ~ Qridle7 R Cridley Director Nuclear Safety and Licensing Enclosure cc: See page 2 Dt-8 828o

o RETS Manual Revision 9 Page 247 U.s. Huclear Regulatory Commission FP.B 111357 CC (Enclosure):

U.S. Huclear Regulatory Coslnission Region II Attn: Dr. J. Helson Crace, Regional Administrator 101 Marietta Street., HM, Suite 2900 Atlanta, Georgia 30323 Mr. C. E. Gears Browns Ferry Project Manager U.S. Huclear Regulatory Comnlssion 7920 Hortolk Avenue Bethesda, Maryland 20814 Mr. C. C; Zech, Director TVA Projects U.S. Huclear Regulatory Commission 101 Marietta St., HQ, Suite 2900 Atlanta, Georgia 30323 Browns Ferry Resident Inspector Browns Ferry Huclear Plant P.O. Box 311 Athens, Alabama 35611 MJM: JDM:LVT:SJL cc (Enclosure):

RIMS, MR 4H 72A-C R. M. Cantrell, M12 A12 C-K E. S. Christenbury, Ell B33 C-K W. H. Hannum, BR 1H 76B-C R. L. Lewis, Browns Ferry M. J. May, BFN - Licensing D. R. Nichols, LP 5H 302B-C R. C. Parker, LP 4H 45A-C H. P. Pomrehn, Browns Ferry L. J. Riales, BR 5S 144X-C C. C. Robertson, LP 5S 83E-C R. K. Seiberling716C-C D. L. Milliams, M10 B85 C-K 0579c IV-9 828o

0 II It

RETS Manual Revision 9 Page 248 ENCLOSURE Dewatering is conducted at BFN using plant equipment and plant personnel.

Chem-Nuclear Systems, Inc., (CNSI) high-integrity containers and the CNSI dewatering procedures are used.

l. EKCEPTIONS OR DEVIATIONS TAKEN TO CNSI TOPICAL REPORT DATED DECEMBER 1983.

BFN dewaters powdered resin, filter media, and mixtures of powdered resin with small quantities of bead resin (normally less than 10 percent bead resin) using Chem-Nuclear Procedure FO-OP-022, "Ecodex Precoat/Powdex/Solka-Floe/Diatomaceous Earth Dewatering Procedure for CNSI 14-195 or Small Liners." The dewatering system was fabricated by TVA to meet the equipment specifications in FO-OP-022. The TVA dewatering system differs from the Chem-Nuclear system in that:

(a) TVA's system has no off-gas collector. The high integrity containers are open to the waste packaging room air during filling and dewatering. Air from this room is normally discharged through the Radwaste Building ventilation system. This air then flows through a HEPA filter and is released through a monitored release point on the Reactor Building roof.

(b) The valves on the pump suction manifold are manually operated. The system is not operated remotely. However, the high integrity containers are enclosed behind a shielded wall or inside a shielded cask during filling and dewatering to keep radiation levels in the vicinity of the system near background.

(c) There are no vacuum gauges at each inlet connection. A single vacuum gauge is provided at the flush inlet connection to the manifold. This vacuum gauge will indicate a break in vacuum in any active (not isolated) filter set. Loss of vacuum normally occurs in sequence from the top to the bottom set of filters. When vacuum breaks at a given filter level, that level is isolated. Therefore, vacuum is monitored continually for all active filter sets.

(d) There is no automatic level control or level indicating instrument in the TVA dewatering system. Level is determined by visual observations.

TVA has conducted tests which conclude that mixtures of bead and powdered resin, in proportions of up to 50-percent bead, can be adequately dewatered using a modified procedure for dewatering powdered resin.

These tests were conducted using TVA-fabricated steel liners with dewatering internals similar to those found in the Chem-Nuclear high-integrity containers and a dewatering pump which is inferior to that 828o

0 RETS Manual Revision 9 Page 249 specified in FO-OP&22, in that it is limited to a vacuum of 13" Hg and has a flow rate of six SCFM. In addition, the dewatering procedure used for the tests called for only four hours of bulk dewatering, as opposed to three eight-hour pumping cycles specified in FO-OP-022. The conditions of the test were clearly less conducive to proper dewatering than those specified in FO-OP-022 (this equipment and procedure is not used for normal operation). However, results show that adequate dewatering is guaranteed either by extending the dewatering time in the procedure or by applying an additional dewatering cycle at the end of the bulk dewatering process using a high flow rate (approximately 200 SCFM at 28" Hg) vacuum pump. TVA has modified FO-OP-022 to include two hours of additional dewatering with the 200 SCFM vacuum pump for all resin.

2. INTERFACES BETWEEN PLANT AND CNSI EQUIPMENT (a) The high-integrity container is filled with spent resin slurry through a one-inch flexible hose. Flow through the hose is controlled by way of a diaphragm-operated valve. The hose is connected to the high-integrity container with an Evertight quick disconnect fitting that has been modified for remote operation.

(b) The dewatering pump discharges through a one-inch flexible hose to the plant waste packaging drain header which leads to the waste package drain tank. The connection to the header is made by an OPW 633 D Kamlock quick disconnect fitting.

'(c) Radwaste compressed air is supplied through a flexible hose with Chicago connections to the air operated positive displacement pump.

(d) Demineralized water is provided by a flexible hose with Chicago connections to the flush-inlet valve on the dewatering pump suction manifold.

(e) The dewatering system is located inside the radwaste packaging room (see figure 1). Any leaks or spills will be contained inside this room by exterior doors which are closed during filling, and collected in radwaste floor drains. Failure of any of these resin processing components will not provide a pathway for radioactive materials into the environment or potable water supply.

3. LOCATION AND AMQNGEMENT OF DEWATERING SYSTEM IN PLANT See Figure 1.

IV-11 828o

RETS Manual Revision 9 Page 250 4~ WASTE CLASSIFICATION TO MEET 10 CFR 61.55 Radionuclide concentrations are determined by direct measurement.

Samples, or smears, as appropriate, of standard waste streams are sent offsite for analysis. An inferential measurement program is then established whereby concentrations of radioisotopes which cannot be readily measured are projected through ratioing to concentrations of similar behaving isotopes which can be readily measured. Scaling factors are developed on a waste stream specific basis. Scaling factors are periodically reconfirmed through sampling and analysis. A QC program is in place to ensure compliance with 10 CFR 61.55 and 61.56.

5~ DESCRIPTION OF WASTE CONTAINER High-integrity containers manufactured by CNSI are used for packaging resin. The following containers are used: 8-120,14-195, 14-170 and are discussed in a topical report dated December 1983 entitled, "Chem-Nuclear Systems, Inc., Topical Report Polyethylene High Integrity Containers CNSI-HIC-14571W1-NP . "

6 ~ CAPABILITY TO MEET 10 CFR 50 APPENDIX I This dewatering process does not cause any direct releases to the environment (note l.a above).

IV-12 828o

0 RETS > al Revision 9 Page 251 f

lleforence.'rowns F srry FIGURE 1 FsAR 9. 2 ) lz

~ ~

>0 >

~ ~

lflil

> oooooo o

~ ~

29/t.

Cnew' Oyo( ~ lot I l1II~ litt 3fn. ildol 4!n Cllan-c Syalons oa r

~

~ ~

~

Tn<)cn

~ ~ ~

P ~ ~

~ ~ ~

WIl Wc (W<l) Vlp Haste Packaging Room Layout for Chem Nuclear system Plan Elevation 565'

RETS Nanual Revision 9 Page 252 j44 8 i0 l6 SO ~

5H ~578 Lookoui P t 2ce OO~ ] 6 tag<

U.'~. Huclear'egulatory Caccmcissian A~: Document Control Desk Washington, D.C. 205 5 Centlemen:

Zn the 'Hatter of Docket Nos. 50-259 Tennessee Valley Authority S0-260

'50 296 BROMHS F~K'f HUCLEAR PLAHT (BFH) PROCESS COHTROL PROCRAH FOR DEKZHEBALZ BESQf DEMA~C By letter from ne to D. R. Huller. dated February 11, 1987, TVA descr'"ed '

process control program far demineralixer resin devatering and reques ed HRC t

to reviev and approve 3 as described in that letter. This resin.devater'ng, process vas time-consuming. Chem-Huclear Systems Inc. (CJSZ) has since improved t~ process by developing the RDS-IOOO, RapicL Devatering System, for accelerating the devatering process. The time savings in this.devatar'ng process vill al'lov BFH to accammaditm its spent resin generated dur'ng paver yaiduction. TVA"intendi ta implement'the RDS-lddO'rocess.htafore Pipit 2

~

.restar . Therefoia, khan submittal supersedes W.February..ll. 198$ letter..

~ConsecLuenhly, TVA has elected not to ansver NRC's rec(uest far'dditional infor~tion fram J. h. Zvalinski ta S. h. White datacL July 21, 1987 cancerning BFH's cu~t devatering process in a'separate submittal. Hovever, these items are addressed in the enclosures to this latter far the'RDS-1000 system.

Deminerali=e resin devatcring viU. be performed at BFLT using ClSZ equipment.

The operating methodology outlined by CJSZ in topical raper s DW-11118-01-p-h, "CJSI Devatering Control Pracass Containers Topical Raper " and RDS-25506-01-P, "RDS-1000 RacLioactive Waste Devatering System" vill be used.

HRC accepted CJSZ Topical Repar DW-11118-01-P-h for reference by license applicants in a letter from C. O. Thomas (HRC) to L. X.. Poppe (CHSZ) dated June 1' 19&5. CJSZ Topical Repor- RDS-25506-01-P vas submitted to HRC by CHSZ for approval by letter fram Q. B. House (CHSZ) ta R. L. Ench (HRC) dated Earch 26, 1987 and a nonproprietary copy is enclasecL ta this letter (enclosure 2). These CHSZ topical reparts vill fan the basis of the BFH deminerali=or resin devaterhg pracess and system.

Enclosure 1 provides information required by HRC to reviev applicability of the report to specific licensees as outlined in the safety evaluation for CHSZ Topical Raper DW-11118-01-p-h. Procedures for this nev process and system are schedulccL bc cintcrnally approved by October'987 ~ TVA recpiests that MRC reviev the enclosed information and provide approvai ~ vithin this sama tlmeframe, for use 'of this repor aa a process control program as defined in'~>>

the BFH technical specification 6.9 ~ - .. -"'..-... ' -."..',.-.-..","'. '.:"=t '-'":.

~

-'V-14 828o

RETS Manual Revxsxon 9 Page 253 U.S. Nuclear Regulatory Cocnu.ssio X you ha ~ ny ques o ming J. L,. Turner at. (205) 729-2B53.

Enclosed is a check for the '50 rcvxcv fee required by 10 C:R 170.'"

Very truly yours, TmnrESS"~ V ' AUmoa L . dley, D . cctor Nuclear Licensing and Regulatory hffairs Subse=ibed an/ suborn tn

.me on tMs ~~M da of ~+fore .

me 1987 .

Notary Public By Cannissi>>>>>>>> txpi>>>>1

.. y;i,oi

~>> ~

~

~>>

S ~

0 ~0 >>>>

~- ~ ~

~ ~>>

~

~ ~ ~ e ~ ~

~ ~

~ ~

End!osurcs'c fEnclosures):

Mr. C. C. Zcch, Assistant Director Regional Tnspec ions Division of TVA Projects Office of Spec.'al Projec s U.S. Nuclear Regulatory Commission Reg'on XX 101 Marietta St., HW, Suite 2900 htlanta, Ceorgia 30323 Mr. J. h. Xvolinskl, Assistant Director for Projects Division of Tvh Projects Office of Speeia! Projects U.S. Nuclear Regulatory Ccmeission 4350 East-Most Highway U4 322 Bethesda, Maryland 20814 J>>

Brooms Fe~ Resident Inspector Brows Route 2 Fe~ Nuclear Plant.

P O. Box 311 hthens, Alabama 35411 Ig-15 828o

Revision 9 Page 254

~ ~ U.S. Nuclear Regulatory cc (Enclosures):

C omm'alon ~7t Iv'0(

C.

C C. Xech, Ass'stant Di-ec or Reg'onal Xnspections Div'sion of ~IA rojects

. ce of Special P 0 oje c ts Pro'f~:

~

,S. Nuclear Regulatory CootttmI.ssion U,S Region

... 101 Marietta St., ?Q, Suite 2900

'tlanta, Ceorgia 30323

. >~lety Hr. J. A.. Zvolinski, Assistant Director 'p~ns Fer /

for Projects t Division of TVA Projects, Off'ce of Special P ojects v2 U.S. Nuclear lat Re gula'to'ry C~ssLon t-Meat High@ay l ntFC UM 322 I I

I Bethesda, Haryland 20814 I t

I t

Fe~

0 ~ ~

I Brdvns Res j,dent::Xnspector st> I t3t&~

~

. BroMns Fe~.Nuclear Plant ~ 1J outa 2', P. 0 .. Box. 311 ~ ~ ~

1 V

thens, Alibama Ath 35&11 JDM: JLT: XBL:

Ftt E

):

CE'c.

( Enclosures

~

KL 48 72A-C C. F.. Ayers, LP &N 25D-C K. S. Christenhury, E11 B33 C-K M. H. Hannum, BR Lf 77B-C A. Zppoli o, Bethesd'a N. C Laxanas, L7 48 45A C Bet U.censin Of f A. Klrkebo, QL2 ALE C>>K C>>

H. J.. Hay, Brogans Ferry C. R . Bailee, BR 5S l&8A~

D. R Hkchols, BR 5S 100A-C He P ~ Pomr omrehn, Bro~s Ferry S. J. Smith,'LP &N 38A~

D. l Milliams, M10 B85 C-K IV>>16 828o

RETS Manual Revision 9 Page 255 ENCLOSURE 1 Dewatering will be conducted at BFN using the Chem-Nuclear Systems, Inc.

(CNSI) Rapid Dewatering System (RDS-1000). CNSI high-integrity containers and/or steel liners and plant specific versions of CNSI Procedure FO-OP-032, "Setup and Operating Procedure for the RDS-1000 Unit" and CNSI Procedure F~P-035, "Setup and Operating Procedure for Dewatering Pre-Coat Media in a 21-300 Liner Using the RDS-1000" will be used.

I. EKCEPTIONS OR DEVIATIONS TAKEN TO CNSI TOPICAL REPORTS DW-11118&1-P-A AND RDS-25506-01-P TVA's system has no off-gas system connection available for interface with the RDS-1000. The rapid dewatering skid of the RDS-1000 system has a HEPA filter installed downstream of the safety relief valve and manual bypass valve. Liners will be vented through this HEPA filter to the waste packaging room. Air from this room is normally discharged through the radwaste building ventilation system. This air then flows through an installed HEPA filter before release through a monitored release point on the reactor building roof. Exterior doors from the waste packaging room are closed during liner filling and dewatering operations.

2. INTERFACES BETWEEN PLANT AND CNSI EQUIPMENT A. A plant connection stand (PCS) is provided as part of the RDS-1000 system. Its components are:

1. A remotely operated valve to control influent to the liner;

2. A diaphragm pump with connections to the liner fillhead for initial gross dewatering;

3. Manifolds for air and service water supplies to control elements and flushing systems.

B. Radwaste building compressed service air will be provided to the PCS at approximately 40 SCFM at 80 psig (+20, -10 psig) through a flexible hose. The connection to plant air and water is made via quick-disconnect fittings. The PCS connection to CNSI equipment is also a quick-disconnect fitting.

828o

RETS Manual Revision, 9 Page 256 C. Radwaste building service water (demineralized) will be provided to the PCS at approximately 25 gpm at 80 psig (+20 psig) through a flexible hose. Both connection points (plant and PCS) are equipped with quick-disconnect fittings.

D. The dewatering pump discharge is provided by a 1.5 inch flexible hose to the plant waste packaging drain header which leads to the waste package drain tank. The connection to the drain header is made by a 1-inch Kamlock quick-disconnect fitting. The dewatering pump connection is a 1.5 inch Kamlock quick-disconnect fitting. A 1 to 1.5-inch Kamlock adaptor will be used at the drain header.

E. The connection to the plant waste media line will be made either by a 1.5-inch 150 ANSI flat faced flange connection or by a flange connection to Kamlock quick-disconnect adaptor utilizing existing flexible hose. A waste isolation valve .will be installed downstream of this connection, providing local control by the CNSI operator over the flow of waste to the liners being filled. The waste isolation is controlled remotely, and is interlocked to close on high waste level, high-high level, decreasing air pressure, or loss of electrical power.

3. LOCATION AND ARRANGEMENT OF DEWATERING SYSTEM IN PLANT See Figure 1 The RDS-1000 system will be located inside the radwaste packaging room, elevation 565'. Any leaks or spills will be contained inside this room by exterior doors, which are closed during liner filling and dewatering operations. Any spillage will be collected in the radwaste floor drains.

Failure of any of these resin processing components will not provide a pathway for radioactive, materials into the environment or potable water supply.

IV-18 828o

RETS Manual Revision 9 Page 257

4. WASTE CLASSIFICATION TO MEET 10 CFR 61.55 Radionuclxde concentrations are determined by direct measurement. Samples or smears, as appropriate, of standard waste streams are sent offsite for analysis. An inferential measurement program is then established ~hereby concentrations of radioisotopes which cannot be readily measured are projected through ratioing to concentrations of similarly behaving isotopes which can be readily measured. Scaling factors are developed on a waste stream specific basis. Scaling factors are periodically reconfirmed through sampling and analysis. Computerized calculation of individual container isotopic contents is performed. Maintenance, testing, and independent verification of this program ascertain correct data manipulation. TVA QA audits of the vendor laboratory conducting the periodic sample analysis confirm quality practices at that location.

Procedural controls, corporate assessments of the radwaste program, periodic QA audits of the program, and management evaluation of audit findings ensure quality in the plant program.

5. DESCRIPTION OF WASTE CONTAINER High-integrity containers manufactured by CNSI are used for packaging resin. The following containers are used: 8-120,14-195, and 14-170.

They are discussed in a topical report dated December 1983 entitled, "Chem-Nuclear Systems, Inc., Topical Report Polyethylene High Integrity Containers CNSI-HIC-14571-01-NP." CNSI 21-300 steel liners are compatible with the dewatering system and may also be used.

6. CAPABILITY TO MEET 10 CFR 50 APPENDIX I This dewatering process does not cause any direct releases to the environment.

IV-19 828o

0 RETS Hanual Revision 9 Page 258 FIGURE 2

~

t llcfcr'erlco.'rowns Ferry or Q'l.ocul l<>>i liir re~nl ~ eiinlrol pnnol FSn,r< o.2 Otal I'Iunt cn>>uL;ellen) otoliil anil IIIIS-Illlul ul Iil local I<in lllll Ii>cnl I<>>l

~

Ql IIIC Iocnt Itin (alternate)

~ ~

)Ol. fl.:5 tll.'

j OI ISO ~ OO ~ OO ~ t100 o is'o ~ ~ ~ ~~ o~~ ~

Cnsno Opeeulor ..

20fl. Bin. C I

~

I'lullviin ~ llofll A!

IQ .Idolathi t I. jclc~ir lllllc:I( I II II.

1 Syt> I olII 6

Waste Packaging Room Layout for Chem Nuclear System Plant Elevation 565'0

ta a~

~ ~<C

~~ e ~~

0 UNIiEQ s ~ Es NUCLEAR REGULATORY COMMtSSIQN YlASHIMCrOH, O. e. 055 $

Hay 6, '988 RETS Page Manual Revision 259 Licensing jr~

9 end S~itrr c~ ~$ + H~

'gYi3 A ~ Pl

'oekt Has. 50-259/260/296 I I ~en< I Mr, S. A, Mhi te Manactr a; Nuclear Power Tennessc Valley Autnoritr

.6H 38'ookout Place 1101 Harkrt Stree.

Chattanooaa, Tennesse 37402-2801 o~ I I

Dear Hr. Mhitc:

SVBJECT: IHT RIM APPROVAL OF 8RONS . =RRY PROC:.SS CONTROL PROGRAM (TAC 64700, 647CI, 64702) t Qe have comoitted our review o. the arowns Ferry revised "rocess canthi praaram (PCP) Submitted with yOur le.ttr d? ted,0eaatr '5, '987.

In the Sr owns Ferri PCP for. implementina the requirements af See:ian 6.9 c; Dc Technical Specificatians, tne licensee has referenced the fallawinc vendor's licensina topical rtports:

1. D~'-$ 11184 Ol-P-A; Chem-Huelear. Syst'ems Ine., QSI Dewattrina'ontrol

.Proc ss Con:ainers Topical Rtpor ... ~ Oo RDS-25506-01-P, Chem-Huclear System, Inc., ROS-1000 Radioactive Vast Dewat rir:a System. Rev. 0.

Topical Reoor = Ho. 1 above has been approved by thc sta.. and accepted .or refcrencina in future licensina aoolica:ions. The remainina topical r cr:

( o. ) is unacr review by the NRC sta... The NRC sta .'s review o. this tooical reoor: has aeneratcd auestions reauirina .he vendor of th e process

- uclcar Systems Inc.) ta provioe responses. The vendor responses wer

(

submitted to thc HRC by letter dated Hareh 31, 1988. The staff

revieww oof t h ese responses hts indicated .hat this topical repor: is acceptable s pr t iminar for mettina he requirements in Section $ 1.4 o, Standard Rev iew Pl an ((S"P) a ) and 10 CFR 61.

Based on our review, wc find the revised PCP tor Browns Ferrv, Vnits I, 2 and 3 aeetptab)e as an interim approval effective un"il 'the NRC staff completes its'eview of the topical report (Reference 2) described above. You may proceed'i D solidification of radioactive wastes and dewatcrina of resin in accordance with tne revised Browns Ferry PCP. Tht bases forspent aectptance are conformance to .ht licensct's PCP to Branch T ec hn'lca P asst on Section 11.', and to the requirements in Section 6.9 of the technical Speeifica.ions.

IV-21 828o

RETS Manual Revision 9 Page 260 Ht. S. A. Mhite May 6 70Po

~ 1~

If vou have any oues.ions (oncerninc .his issue, p1ease c ntac yo, pro-Manaaer, G. Gears a 3Q1-49K-0767.

Sincer 1y, Robert A. Hernann, Ac.ino Assistant Oire ="r

'NA Project Oivision Offi=e of Specia1 Projec=s cc: S next paoe IV-22 828o

RETS Manual Revision 9 Page 261 ATTACHMENT 1 Dewatering is conducted at BFN using Chem-Nuclear System, Inc (CNSI) supplied portable air driven pumps. Dewatering will be performed on CNSI 24 inch diameter pressure vessels.

1. EXCEPTIONS OR DEVIATIONS TAKEN TO CNSI TOPICAL REPORT None. Plant specific versions of CNSI Procedure FO-OP-025 and vendor supplied equipment will be used to dewater vessels.

2. INTERFACES BETWEEN PLANT AND CNSI EQUIPMENT (a) The dewatering pump discharges through a flexible to a plant floor drain. This water will be processed through Radwaste.

(b) Compressed air is supplied from the plant air system through a flexible hose with Chicago connections to the air driven pump.

(c) The dewatering system will be located in a permanent plant building.

Any leaks or spills will be contained inside this building and collected in floor drains. Failure of any of the components will not provide a pathway for radioactive releases to the environment or to a portable water supply.

The dewatering will be performed in a permanent plant building. The dewatering pump will be located in the immediate vicinity of the pressure vessels and as close as possible to a floor drain.

4. WASTE CLASSIFICATION TO MEET 10 CFR 61.55 Radionuclide concentrations are determined by direct measurement. Samples or smears, as appropriate, of standard waste streams are sent off site for analysis. An inferential measurement program is then established whereby concentrations of radioisotopes which cannot be readily measured are projected through ratioing to concentrations of similar behaving isotopes which can be readily measured. Scaling factors are developed on a waste stream specific basis. Scaling factors are periodically reconfirmed through sampling and analysis. A QC program is in place to ensure compliance with 10 CFR 61.55 and 61.56.

5. DESCRIPTION OF WASTE CONTAINER The waste containers are the CNSI 24 inch diameter carbon steel and fiberglass re-inforced plastic pressure vessels.

6. CAPABILITY TO MEET 10CFR50 Appendix I This dewatering process does not cause any direct releases to the environment (see note 2C above).

IV-23 828o

RETS Manual Revision 9 Page 262 ATTACHMENT 2 Dewatering will be conducted at BFN using the Pacific Nuclear Systems, Inc./Nu pac Services Division, Inc. Resin Drying (Dewatering) System. Pacific Nuclear Systems, Inc./Nu Pac Services Division, Inc. high-integrity containers and plant specific versions of Pacific Nuclear Systems, Inc./Nu Pac Services Division, Inc. procedures OMW3-NS, "Operating Procedure for the Resin Drying (Dewatering) System," and OM-16-NS, "Users Guide for the Nu Pac Crosslinked Polyethylene High Integrity Containers" will be used.

1. EXCEPTIONS OR DEVIATIONS TAKEN TO PACIFIC NUCLEAR TOPICAL REPORT TP-02-NP-A I

TVA's system has no off-gas connection available for connection to the Resin Drying System. The Resin Drying System blower skid contains a HEPA filter which removes airborne particulate matter from the container vent pathway during the container filling cycle and vents this air to the general area around the skid. This air is then discharged through the plant ventilation system. This air flows through an installed HEPA filter through a monitored release point prior to its release to the environment.

2. INTERFACES BETWEEN PLANT AND PACIFIC NUCLEAR SYSTEMS, INC EQUIPMENT A. Plant compressed service air will be supplied to the Resin Drying System at approximately 40 SCFM at 100 psi through a flexible hose.

B. Plant service water (demineralized) will be supplied to the Resin Drying System at approximately 25 gpm at 80 psi through a flexible hose.

C. The Resin Drying System will discharge the water removed from the high>>integrity container to the plant radwaste system through a flexible hose.

D. The connection to the waste transfer line is made via a high pressure flexible hose to the fillhead which is connected to the high-integrity container. A waste isolation valve provides the Pacific Nuclear System operator local control over the flow of waste to the liners. The waste transfer isolation is controlled remotely and the fillhead is interlock to close automatically on high waste level, or high fillhead pressure alarms.

3. LOCATION AND AR14NGEMENT OF DEWATERING SYSTEM IN PLANT The Resin Drying System will be located inside a permanent plant building. Any leaks or spills would be contained inside this building.

Any spillage would be collected in the plant floor drains. Failure of any of these resin processing components will not provide a pathway for radioactive materials into the environment or a portable water supply.

IV-24 828o

RETS Manual Revision 9 Page 263 4 WASTE CLASSIFICATION TO MEET 10 CFR 61.55 Radionuclide concentrations are determined by direct measurement. Samples or smears, as appropriate, of standard waste streams are sent offsite for analysis. An inferential measurement program is then established whereby concentrations of radioisotopes which cannot be readily measured are projected through ratioing to concentrations of similarly behaving isotopes which can be readily measured. Scaling factors are developed on a waste stream specific basis. Scaling factors are periodically reconfirmed through sampling and analysis. Computerized calculation of individual container isotopic contents is performed. Maintenance, testing, and independent verification of this program ascertain correct data manipulation. TVA QA audits of the vendor laboratory conducting the periodic sample analysis confirm quality practices at that location.

Procedural controls, corporate assessments of the Radwaste program, periodic QC audits of the program, and management evaluation of audit finding ensure qualify in the plant program.

5. DESCRIPTION OF WASTE CONTAINERS High-integrity containers manufactured by Pacific Nuclear, Systems, inc.

are used for packaging resin.

This dewatering process does not cause any direct releases to the environment.

IV-25 LAST PAGE 828o

r

~

wHIr mm"

~

Standard Sheet I'onqt ONI'-ST&4AAQ ftcv I 10 CFR 50 59 BVALQAXXOHS OF CBAHGESs STD-12 13 TESTS s AHD EXPE!%MENTS Bev 0 Page 25 of 31 APPENDIX B S3U!ETX ASSESSHERX FOIMAX Page ~ of ~

Document No. (i.e. ECN No., procedure o. and revision+-" -'-s-,,

special test No., etc.). W 15 r Description

1. Detailed description of the change special activity, or condition including the systems structures and components affected.

Include the number of the activity proposed (e.g., ECN/DCH No.s procedure No.).

2. References.

B" "Is the Yes ~

Impact on Safety change acceptable So Justification: Checklist process/engineering from a nuclear safety standpoint7 B-1 (or ZQR criteria STD-2.3) - ~

procedure cpange tX@l<ktg, If the answer is Ho" it is an unsafe change which will require either revision to make it safe or cancellation. Environmental

~

impacts are evaluated in accordance with STD-13 3 C Potential Technical Specification (T/S) Impact Yes No Zs a chaaqe to the T/S required for conducting or implementing the charge, test or experiment?

Justification: ~ IZ+g~

If the answer is "Yes", a T/S change is required prior to implementation or the activity needs to be revised or cancelled proceed to Part E. If the answer to the question is "No". proceed to Part D.

TVA 10004 IONI'!248I 7530C

El Standard Slxet I'onn OHP.~AA-3 Rcv t 10 CFR 50 59 BVALUATIONS OF CHANGES~ SXQ-12 13 TESTS~ AND EXPERIMENTS Bev 0 Page 26 of 31 APPENDIX B (Continued)

Document No. ~LR4U9 Page ~ oi ~

DOES NOT POTENTIALS DECREASE REDUCES NUCLEAR NUCLEAR SAFETY SAFETY H,re Protection (Appendix R) 20 Internal Floodiag Protection (MELB) 3~ Pipe Brea)cs Pipe Whip 5 Modification to Noa-Seismic Areas in CB/AB r

6

'eavy 70 Jet Impingement Effects 8 Seismic/Dead Weight 9 Internal/External Missiles 10 Load Lifts or Safe Load Paths (NUREG-0612)

Toxic Gases 12 Hazardous Material 13 Human Factors 14 ~ Electrical Separation/Isolation

15. Primary Containment Integrity/Isolation 16 Secondary Coataiameat Integrity/

Isolation

17. Equipment Reliability 18 19.

20 'ontrol TVA 400ot t074P.t2-6bl 7530C Materials Compatibility Single Failure Criteria Room Habitability

10 CFR 50 59 EVALUATXONS OP CHANTS<< STD-12 13 TESTS AND EXPERXMB1TS Rev 0 Page 27 of 31 APPENDXX S (Continued)

Doc~<<<< ~o. 6BLMuUCo) Pago ~. of ~

DOES NOT POTENTX ALLY DECREASE REDUCES NUCLEAR NUCLEAR SAFETY SAFETY 21 Environmental Qualificatioa Category 22 Ecptipment Failure Modes 23 Tornado or External Flood Protection 24 Protective Coatings Inside Coatainmeat

'5.

Water Spray/Condensation 26 System Design Parameters 27 Test aad Retest Scoping Document (Post Modificatioa Test) 28 Chemistry Changes or Chemical Release Pathways 29 Ecptipment Redundancy

'0.

Equipmeat Diversity

31. Physica1 Separation 32 Electrical Loads 33 Response Time of Emergency Safeguards Ecptipmeat 34 Safety Xnjection/Core Cooling Capability

35. Decay Heat Removal Capability

36. Reactor Coolant Pressure Boundary

37. Reactor Core Parameters 38 Pipe Vibration

39. Security System 40 Scaffolding TVA 40ON cONP-12451 7530C

~r D N N rs? r I SLuMard Sheet Form ONP ST&4AA4 Rev I 10 CFR 50.59 @VACATIONS Or CHANGES. STD-12 13 TESTS AHD EXPERIME?iTS Rev 0 Page 28 of 31 APPE2IDIX B (Continued) coo~at??o. 8~@~~) Page + of ~

DOES NOT POTENTIALLY DECREASE REDUCES NUCLEAR NUCLEAR SAFETY SAFETY N/A 4le Electrical Breaker Alignment Changes 42 I-TABS Protection Relay Settings 43 Compensatory Measure Environmental Impact Statement (See STD-13.3 )

45 Design Basis Document 46 Radqgaste System Changes 47 Valve Alignment Changes

48. Shield Building Integrity (SQN/WBN) 49o Ne~ Radioactive Effluent (Liquid or Gaseous) Release Pathways 50 Temporary Shielding

51. Instrument Setpoints 52 ASME Section XZ D Potential Safety Analysis Impact Yes Ho Is a SE obviously required {for example, change to a Radggaste System, special test or experiment)7 Zf yes the remainder of Part D may be bypassed.

Does the proposed activity affect significantly (directly or indirectly) any information presented in the SAR or deviate from the description given in the SAR:

~ N/h By chaagiag the systea gesiga or

~

Yes No tuactioaal requireaeats?

po N/h ay chaagiag the text, tables, graphs, or figures?

TVA 4000l <QNlr-)g.05) 7530C

e 10 CFR 50 59 EVALUATIONS OF CRANNIES// STD-12 13o Rev 0 TESTSo AND EXPFBIMBPXS Interim Change 1 ST Page 29 of 3l.

APPENDIX 8 (Continued)

Doccaeet Yo. 6~<gJLRQ) Page 5 of ~

Justification=

the proposed change involve new procedures or instructions or

~

Does revisions thereof that:

Yes Yo D/a Differ with or a fact sfstea operation characteristics from that described in the SAR?

Yes Yo Y/a Differ with or affect compliance with Yes No a/a ~ 'Technical Specif ications'T coaflict with or affect a process or procedure outlined summarized, or described in the SAR7 Justification:

If the questions are answered "Noes the activity may be implemented Xf the questions are answered "Yes", a IO without further evaluation. CFR 50.59 SE is required.

E. Review and Approvals I Preparer (Level 1) Date:

Na'm'e S Reviewer (Level I-IQR Date:

or Level II) ~fp~. pl>p(Name Approver Date:/'

(Line Mgr.) Name Si ature Other Reviewers Date:

(as appropriate) Name/Organisation Signature 7880C

~<<Mr <<MMH a Attachment to TVA Form 40139 (Page 6 of 7)

Safety Assessment for ODCM Revision (Revision 10 to RETS Manual)

A. Description This change adds text to the ODCM which duplicates text currently found in the BFN Technical Specifications. This change is a followup to ODCM Revision 9 which was made in anticipation of a T/S change to implement the NRC's Generic Letter 89-01. The Generic Letter recommended the relocation of all procedural details in the T/S dealing with radioactive gaseous and liquid effluents to the ODCM. A. review of Revision 9 against. the T/S change package showed that some of the text in the Bases section was omitted from the final ODCM package. Two paragraphs are being added to the bases for ODCM Control 1/2.3.2.2 Dose --Noble Gases describing the action to be taken if limits are exceeded and a mention of the required report to the NRC The text which is heing duplicated is done so verbena fram the T/S wording.

The review of the change also compared revision g of the ODCM to revision 'LQ]ayThis review indicated that several paragraphs/sections were

$ 7@

omitted during @Be reformatting process.

IRK+1 These include the section describing the equations for the calculation of dose rates (added on page 141), and the equations which must be met for all release rates out of the plant (added on page 143}.

The only systems potentially affected by a change to the ODCM will be the liquid and gaseous effluent and process monitoring systems described in the BFN FSAR. Since this revision does not change any calculational methodology, requirements, or processes, these systems it will not have any effect on References

1. BFN Technical Specifications Bases for Section 3.8. February 5 1987.

2. BFN FSAR Section 1.6.1.6 "Radioactive Waste Systems."

3. BFN FSAR Section 7.12, "Process Radiation Monitoring."

4. BFN FSAR Chapter 9.0, "Radioactive Haste Control Systems.-

5. BFN FSAR Section 10.17'Process Sampling Systems."

6. NRC Generic Letter 89-01, "Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the relocation of procedural details of RETS to the Offsito Dose Calculation Manual or to the Process Control Program." (A02 890209 005).

B. Impact on Safety The ODCM contains the methodology used to calculate setpoints for gaseous and liquid effluent monitors. Since the revision only adds text to the ODCM which already appears in the T/S or appeared in the previous ODCM, it will in no way affect the methodology described in tho plant procedures; hence no setpoints will be changed due to this revision.

Attachment to TVA Form 40139 (Page 7 of 7)

Safety Assessment for ODCM Revision (Revision 10 to RETS Manual)

B. Impact on Safety (continued)

Since there is no effect on setpoints for effluent monitors. and no other safety concerns are impacted by this revision. it may be concluded that the change is acceptable from a nuclear safety standpoint.

C. Potential Technical Specification (T/S) Impact This revision to the ODCM is in preparation of a proposed T/S revision which will implement the NRC's Generic Letter 89-01. The Generic Letter recommended the relocation of all Specifications dealing with radioactive gaseous and liquid effluents to the ODCM.

The text from the T/S has been duplicated in the ODCM verbatim. References between Tables, Figures Specifications and other documents were changed in order to ensure that the ODCM will be a self-contained document after the T/S revision.. Until the T/S change recommended by the Generic Letter is prepared and processed~ there will be no changes in any procedures or activities which implement the T/S. Since the ODCM revision simply duplicates T/S requirements and wording, the T/S it will not require a change to Since the additions to the ODCM duplicate the T/S wording, no processes or activities governed by the current Technical Specifications will be affected by this change. This change will, therefore, have no impact on the Technical Specifications.

D. Potential Safety Analysis Impact This ODCM revision places text in the ODCM which duplicates text found in T/S and the previous revision of the ODCM. It does not change any design characteristics, functional requirements, or methodology for dose calculations and setpoint calculations that are described in the FSAR. Any references in the FSAR to the T/S themselves will continue to be valid. as will references to the ODCM as the location for methodology for dose and setpoint calculations. Therefore, this revision will have no effect on the FSAR text.

This revision does not change any equipment. requirements, methodology. or descriptions of any of these nor does it change the way in which any requirements are implemented. All descriptions in the SAR will continue to be valid after this revision.

This ODCM revision will not require any new procedures or instructions or revisions to existing procedures or instructions.

0274

RETS Manual Revision 10 Page 36 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 2 of 10)

Section page L &EL BAS F47 S ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 84 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ~ ~ ~ ~ ~ ~ 85 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ~ . ~ ~ . 85 1/2.2 RADIOACTIVE EFFLUENTS ooo o ~ oooooooo..ooo ~ oooooooo o o ~ ooo.oo. 85 1/2.2.1.1 CONCENTRATION . ~ ~ .~. " ... . .... ...~ ~ ~ . ~ .. ... . ~ .. . " .. 85 1/2 ~ 2o 1 ~ 2 DOSE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 86 1/2.2.1.3 LIQUID WASTE TREATMENT ~ ~ ~ ~ ~ " ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .~~~ 86 1 /2 ~ 2 ~ 2 1 DOSE RATE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ 87 1/2.2.2.2 DOSE - NOBLE GASES ......... " .... ... " ............. .... 88 1/2 '.2 '

~ ~ DOSE I-131i I-133 'RITIUM AND RADIONUCLIDES IN PARTICULATE FORM ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 89 1/2.2.2.4 GASEOUS RADWASTE TREATMENT o ~ ~ ..o..o .o. o..o.....o...o.o 90 1/2.2.3 TOTAL DOSE ...... ~ .. ~ . ........... .........................

~ 90 1/2.3 RADIOLOGICAL ENVIRONNEÃTAL MONITORING . .. ...... ........... ~ ~ ~ 90 1/2.3.1 MONITORING PROGRAM ....... . ...... ...........ooo .... .....

~ ~ ~ 90 1/2.3.2 LAND USE CENSUS .............. . . ................... .....

~ ~ ~ ~ ~ 91 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM ..... . ....... .... .. ..

~ ~ ~ ~ ~ 91 3.0 DEFINITIONS ... . ... . ~ ~ ~ ~ ~ ~ ~ . . . .. . .......... " . . .....

~ ~ ~ ~ ~ ~ ~ 92 3.0.A. CHANNEL CALIBRATION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 93 3.0.B. CHANNEL FUNCTIONAL TEST ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 93 3.0.C.

t GASEOUS WASTE TREATMENT SYSTEM ~ ~ ~ ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 93 3.0.D. DOSE EQUIVALENT I-131 ....................<<.. ............ .. ~ 93 3 ~ 0 o Eo MEMBER {S ) OF THE PUBLIC ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 93 3.0.F. OPERABLE - OPERABILITY .. ~ ~... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 94 3.0.G. PURGE PURGING ... .. .......... ... ........ .o... .......

~ ~ ~ ~ ~ o4 1890o

RETS Manual Revision 10 Page 37 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 3 of 10)

Section page 3 ~ 0 oHo RATED POWER ~ ~ o ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o o ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 94 f 3 o0~ I ~ I S TE BOUNDARY ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 94 I 3~0 oJ ~ SOURCE CHECK ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ 94 )

3 'oKo UNRESTRICTED AREA 3 A0 7L ~ 17 oooooooING

~ o ~ ~ ~ ~ o ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

o ~ ~ ~ ~

o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

95 95 I 4 ~ 0 (NOT USED) ~ o ~ ~ ~ o ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 98 I 5' ADMINISTRATIVE CONTROLS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 99 l F 1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ... .......

~ ~ ~ ~ 100 I 5.2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT .................. ioo 101 5 ~ 4 SPEC IAL REPORTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 101 6 ~0 LIQUID EFFLUENTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 102 R ELEASE POINTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 103 I 6.1 LIQUID RELEASES 104 I 6.1.1 Pre-release Analysis/MPC - Sum of the Ratios .................. 104 6.1.2 Release Flow Rate Calculations 104 I 6.1.3 Post-release Analysxs .......... ~................,......,....,. 105 6 ' INSTRUMENT SETPOINTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 106 6.2.1 Radwaste Discharge Monitor .................................... 106 t 6.2.2 Raw Cooling Water and Residual Heat Removal Service Water MOnl tOrS ~ o ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ 107 6.3 CUMULATIVE LIQUID EFFLUENT DOSE CALCULATION ~ ~ . ~ ~ ~ ~ .. . ~....

~ ~ . ~ .. 108 I 6.3.1 Monthly Analysxs ........................... ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 108 6.3.1.1 Water Ingestion .......................... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ o ~ o ~ ~ ~ 109 I 1890o

RETS Manual Revision 10 Page 38 Brogans Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 4 of 10)

Section 6.3.1.2 Fish Ingest]on ..... ........... ............................

~ 110 6..3.1.3 Recreation ........-...- -.....-..---... '..- .-....... ..... 111 6.3.1.4 Monthly Suaxnary . ~ ~ ~ ~ ~ ~ - ~ ~ ~ " - -

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

~ ~ 112 6 ' LIQUID RADWASTE TREATMENT SYSTEM ~ ~ ~ ~ .. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .. ~ ~ 113 6.5 DOSE PROJECTIONS .. ....... ... ... ... . .. .... . ....... ..... 114 6 ' DOSE CALCULATIONS FOR REPORTING PURPOSES ... ~ . ~ ~ ~ ~ ... ... ...

~ ~ ~ ~ 1]5 6.6.1 Water Ingestion ............. " ......-.... .................... 115 6..6.2 Fish Ingestion -."......."..-. """.."...-............... 116 6.6.3 Shoreline Recreation ..................... ....-............... 116 6.6.4 Total Maximum Individual Dose ~ ". ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ 117 6.6.5 Population Doses ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 118 6.7 LIQUID DOSE FACTOR EQUATIONS .................................... 120 6.7.1 Water Ingestion Dose Factors .................................. 120 6.7.2 Fish Ingestion Dose Factors ................................... 120 6.7.3 Shoreline Recreation Dose Factors ............................. 120 7 ' GASEOUS EFFLUEhTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 140 RELEASE POINTS DESCRIPTION .... . ......... ......... ...... ~ ~ ~ ~ . ... 141 7.1 RELEASE RATE LIMIT METHODOLOGY ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 142 7.2 GASEOUS EFFLUENT MONITOR INSTRUMENT SETPOINTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .. ~ ~ .. ~ 147 7.2.1 Alarm/Trip Setpoxnts ........................................,, 147 7.2.2 Allowable Values ..... " ....................................... 147 7.3 GASEOUS EFFLUENTS - DOSE RATES oooo' ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 149

' 149 7.3.1 Noble Gas Dose Rates ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

1890o

RETS Manual Revision 10 Page 39 0 Brogans Offsite Ferry Nuclear Plant Dose Calculation Manual TABLE OF CONTENTS (Page 5 of 10)

Section 7.3.2 I-131, I-133, Tritium and all Radionuclides in Particulate Form vith Half-lives of Greater than 8 days Organ Dose Rate .... ..................- -.-- . . -. -. .--. 150 7 o 4 DOSE ~ NOBLE GASES ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 151 7.4.1 Monthly Noble Gas Dose . " " . " . ".. " . " " .-..-.-...-. " .. " . 151 7.4.1.1 Monthly Conservative Model - Gamma Air Dose ................. 151 7.4.1.2 Monthly Conservative Model - Beta Air Dose .. ............... ~ 152 7.4.1.3 Cumulative Dose - Noble Gas . " ...-" -. " .................... 152 7.4.1.4 Comparison to Limits ........................................

I 152 7.5 CUNJLATIVE DOSE - I-131'-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF LIVES GREATER THAN 8 DAYS . ~ ~ ~ ~ ~ ~ ~ ~ .. 153 7.5.1 Monthly Conservative Model - Infant Thyroid Dose from Millr.

Ingestl.on ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 154 7.5.2 Monthly Conservative Model - Child Bone Dose from Vegetable Ingestion ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 155 7.5.3 Monthly Conservative Model - Teen Gastro intestinal Trac t (GIT)

Dose from Vegetable Ingestion .......... ~ ~ ~ ~ ~ ~ ~ 156 7.5.4 Cumulative Doses ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 157 7.5.5 Total Monthly Dose - Comparison to Limits ..................... 157 7 ~ 6 GASEOUS RADWASTE TREATMENT ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ 158 7.~ 6 ~ 1 Dose Progections ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 158 7.6.2 System Description ............................................ 158 7.7 DOSE CALCULATIONS FOR REPORTING PURPOSES ............ .... .... ~ ~ ~ . 159 7.7.1 Noble Gas Dose ................................................ 159 7.~ 7 1 1 Gamma Dose to Alr ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 160

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 160 1890o

RETS Manual Revision 10 Page 40 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 6 of 10)

Section page 7 ~ 7.2 Radioiodine, Particulate and Tritium - Maximum Organ Dose ..... 161 7.7.3 Population Doses ~ oooo.a ~ .a..oo ~ ooo.o ~ soo.. ~ ~ o.oooo.- ~ ..o.woo.. 163 7.7.4 Reporting of Doses ..............i... " ..i... ..........-.i.i-i 164

~

7.8 GASEOUS DOSE FACTOR EQUATIONS . " . .... .. .-.. .....-.. ....... 165

~ ~

7.8.1 Pasture Grass-Cow-Goat-Milk Ingestion Dose Factors ............ 165 7.8.2 Stored Feed-Cow/Goat&ilk Ingestion Dose Factors ...... ....... 166 ~

7.8.3 Pasture Grass-Beef Ingestion Dose Factors .........,.....,,.... 167 7.8.4 Stored Feed-Beef Ingestion Dose Factors ....................... 168 7.8.5 Fresh Leafy Vegetable Ingestion Dose Factors .......... " ..... 169 7.8.6 Stored Vegetable Ingestion Dose Factors ....................... 170 7.8.7 Tritium-Pasture Grass-Cow/GoatMilk Dose Factor ............... 171 7.8.8 Tritium-Stored FeedCow/GoatMilk Dose Factor ................. 172 7.8.9 Tritium-Pasture Grass-Beef Dose Factor ........................ 173 7.8.10 Tritium-Stored Feed-Beef Dose Factor ........ ................ 174 7.8.11 Tritium-Fresh Leafy Vegetable Dose Factor .................... 175 7.8.12 Tritium-Stored Vegetables Dose Factor ........................ 176 7.8.13 Inhalation Dose Factors ...................................... 177 7.8.14 Ground Plane Dose Factors " . ..-. " . "" " " " . " ...... 177 7.9 DISPERSION METHODOLOGY .. ..

~ ~ .~ ...... ~ . . . .~ .~~~~ .~ .... ~ ~ . 178 7.9.1 Annual Average Air Concentration ............................., 179 t 7.9.2 7.9.3 7.9.4 1890o Relative Concentration ... . " ... " .......

Relative Dispersion .................,......

Effective Release Height ...................

~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ o 180 180 181

RETS Manual Revision 10 Page 41 Broom Ferry Nuclear Plant Offcfte Dose Calculation Manual TABLE OF CONTENTS (Page 7 of 10)

Section page 8 0 TOTAL DOSE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ zzs l 9.0 ENVIRONMENTAL MONITORING PROGRAM .............'................... 230 9 1 MONITORING PROGRAM DESCRIPTION ~ ~ ~ ~ ~ ~ ~ . ~ . ~ ~ .~.~ . ~ ~ . ~ .. ~ ~ ~ ~ ~ ~ ~ ~ ~ 231 9.2 DETECTION CAPABILITIES . ....... ......................,.......

~ ~ 231 9 ' LAND USE CENSUS ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

9.4 INTERLABORATORY COMPARISON PROGRAM .. .. . ~ ~ ~ . ~ ...... .. ~ ~ ~ ~ .... ~ I 1890o

RETS Manual Revise.on 10 Page 42 Browne Ferry Nuclear Plant Offsi,te Dose Calculation Manual TABLE OF CONTENTS (Page 8 of 10)

LIST OF TABLES Table l. 1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION .. 51 Table 2.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ oo ~ ~ ~ ~ ~ ~ ~ 53 Table 1.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION . 56 Table 2.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREKNTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 58 Table 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM ~ ~ 61 Table 2.2-2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND t

ANALYSIS PROGRAM ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ .o ~ o ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ 67 Table 2.3-1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ~ ~ ~ ~ ~ ~ ii ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ s ~ ~ o ~ ~ ~ o ~ ~ ~ ~ oi ~ o ~ ~ .~ ~ ~ . 75 Table 2.3-2 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION (LLD)

FOR ENVIRONMENTAL SAMPLES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 78 Table 2.3-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 80 Table 3.1 FREQUENCY NOTATION . " " ...... " ........................... 96 j Table 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS -................... 121 I Table 6.2 RADIONUCLIDE DECAY hND STABLE ELEMENT TRANSFER DATA ~ ~ ~ . ~ ~ . 122 I Table 6.3 DOSE CALCULATION FACTORS ............................,,.... 125 I Table 6.4 INGESTION DOSE FACTORS .. . ". ~ .~.~ ... ~ ". .... .... .....

~ ~ ~ ~ 127 j Table 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH ~ ~ .~.~ ~ .. 135 Table 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND.. 136 l Table 7.1 BFN - OFFSITE RECEPTOR LOCATION DATA ...................... 182 i Table 7.2 EXPECTED ANNUAL ROUTINE ATMOSPHERIC RELEASES FROM ONE UNIT AT BFN ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 183 Table 7.3 JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND D IRECTION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 184 Table 7.4 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES ... ...~ ~ ~ . . . . 206 1890o

RETS Manual Revision 10 Page 43 Brogans Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 9 of 10)

LIST OF TABLES Table 7.5 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES .... .....

~ 207 Table 7.6 BFN 50-MILE POPULATION WITHIN EACH SECTOR ELEMENT ........ 208 Table 7.7 INHALATION DOSE FACTORS ... ... .. ..

~ ~ ~ . .... . .. . 209 Table 9.1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM .~.~ ........ 232 Table 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS . .... " ... ....... -. . . ... . .. . 237 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 238 1890o

RETS Manual Revision 10 Page 44 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 10 of 10)

LIST OF FIGURES Figure 3.1 LAND SITE BOUNDARY .~~~~~~ ~ ~ ~ ~ ~ -~ ~ ~ ~ ~ ~ -~~~ - ~ ~ ~ ~ o ~ 97 Figure 6@i LIQUID RELEASE POINTS e ~ ~ ~ ~ ~ ~ ~ ~ a ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 138 Figure 6.2 LIQUID RADMASTE SYSTEM . " " .. . " . " .. .................

~ ~ 139 Figure 7.1 OFFGAS SYSTEM AND SGTS EFFLUENT MONITORING ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 217 Figure 7.2 NORMAL BUILDING VENTILATION .............................. 218 Figure 7.3 PLUME DEPLETION EFFECT ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ . ~ ~ ~ ~ 219 Figure 7.4 VERTICAL STANDARD DEVIATION OF MATERIAL IN h PLUME ....... 223 Figure 7.5 RELATIVE DEPOSITION ........ ............. .... .... ....

~ ~ ~ ~ 224 Figure 9.1 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS WITHIN 1 MILE OF THE PLANT ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 239 Figure 9.2 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS FROM 1 TO 5 MILES FROM THE PLANT ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 240 Figure 9.3 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS GREATER THAN 5 MILES FROM THE PLANT ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 241 1890o

RETS Manual Revision 10 0 aaszs Page 88 1/2.2 RADIOhCTIVE EFFLUENTS 1/2.2.2.2 DOSE - NOBLE GASES This requirement is provided to implement thc requirements of Section II.B, III.h, and IV.A of Appendix I, 10'CFR Part 50. The limits are the guides set forth in Section II.C of hppendix I.

The action to be taken for exceeding these limits provi.des the required operating flexibility and at the same tine implemeats the guides set forth in Section IV.h of Appendix I to assure that the releases of radioactive material in gaseous cfflucnts will be kept "as low as reasonably achievable." Section 7.0 calculational methods implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. Section 7.0 calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodologies provided in NUREG/CR-1004, "h Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides." October 1979 and Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, "Appendix I," Revision 1, October 1977 and Regulatory Guide l.ill, "Methods for Estimating htmospheric Transport and Dispersion of Gaseous Effluents ia Routine Releases from Light-Mater Cooled Reactors," Revision 1, July 1977. These ODCM equations also provide for determining the air doses at the exclusioa area boundary are based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.

If these limits are exceeded, this section requires that a special report be prepared and submitted to explain violations of the limiting doses contained in the section above.

1890o

RETS Manual Revision 10 Page 94 DEFINITIONS This category shall include non~loyees of the licensee who are permitted to use portions of the site for recreational'ccupational'r other purposes not associated with plant functions. This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function,.occasionally enter RESTRICTED AREAS.

3.0.F. OPERABLE - OPERABILITY h system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are t

also capable of performing their related support function(s).

3.0.G. PURGE PURGING PURGE or PURGING is the controlled process of discharging air or gas fr o m the p rimar y co ntainment to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the containment.

3.0.H. RATED POWER RATED POWER refers to operation at a reactor power of 3,293 MWt; this is also termed 100 percent power and is the maximum power level authorized by the operating license. Rated steam flow, rated coolant flow, rated neutron flux, and rated nuclear system pressure refer to the values of these parameters when the reactor is at rated power.

Design power, the power to which the safety analysis applies, corresponds to 3,440 MWt.

3.0.I. SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by TVA (see Figure 3.1).

3.0.J. SOURCE CHECK h SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source or multiple of sources'890o

RETS Manual Revision 10 Page 142 h dose rate {DTB, DS, or DTH) is calculated based on the design objective source term mix used in the licensing of the plant. Dose rates are determined for (1) noble gases and (2) iodines and particulates as described below.

Total Bod Dose Rate The dose rate to the total body from nuclide i, DTBi in mrem/year, is calculated using the following equation:

( /Q) Qi DFBi where X/Q a relative concentration, s/m . Relative air concentrations are calculated for the land-site boundary in each of the sixteen sectors as described in Section 7.9.2 using the historical meteorological data for the period 1977-1979 given in Table 7.3.

Qi ~ release rate of noble gas nuclide i, pCi/sec.

DFB ~ total body dose factor due to gamma radiation for noble gas nuclide i, mrem/y per pCi/m3 (Table 7.4).

The dose rate to the skin for nuclide i, Dsi in mrem/year, is calculated using the following equation:

Dsi ~ (X/Q) Qi{DFSi + 1 11 DF~i) where X/Q ~ relative concentration, s/m3. Relative air concentrations are calculated for the land-site boundary in each of the sixteen sectors as described in Section 7.9.2 using the historical meteorological data for the period 1977-1979 given in Table 7.3.

.Qi ~ release rate of noble gas nuclide i, pCi/sec.

DFSi ~ skin dose factor due to beta radiation for noble gas nuclide i, mrem/y per pCi/m3 (Table 7.4).

l. 11 ~ the average ratio of tissue to air energy absorption coefficients, mrem/mrad.

>>n ~ dose conversion factor for external gamaa for noble gas nuclide i, mrad/year per pCi/m3 (Table 7.4).

1890o

RETS Manual Revision 10 Page 143 r an Dose Rate due to I-131 I-133 Tritium and hll Radionuclidcs in Particulate Form with Half-lives of Greater Than 8 Da s Organ dose rates are calculated for all agc groups (adult, teen, child, and infant) and all organs (bone, liver, total body, thyroid, kidney, lung, and GI Tract) using the following equation:

For tritium, Dorg QT(X/Q) (RZT + RCTP]

For all other particulates, Dorg Qit("/Q>>li + ( /Q) iRCPi+RGil>

+here a release rate of tritium in, pCi/sec.

a relative concentration, s/m3. Relative air concentrations are calculated for the land-site boundary in each of the sixteen sectors as described in Section 7.9.2 using the historical meteorological data for the period 1977-1979 given in Table 7.3.

RZT ~ inhalation dose factor for tritium, mrem/year per pCi/m 3 . Dose factor is calculated as described in Section 7.8.13.

~ w~

RZi

~

~

~

Grass-cow-milk dost factor for tritium, mrem/year per pCi/m3.

Dose factor is calculated as described in Section 7.8.7.

release rate of nuclide i, pCi/sec.

inhalation dose factor for each identified nuclide i, mrem/year per pCi/m3. Dose factors are calculated as described in Section 7.8.13.

D/Q ~ relative deposition, 1/m2. Relative deposition is calculated for the land-site boundary in each of the sixteen sectors as described in Section 7.9.3 using the historical meteorological data for the period 1977-1979 given in Table 7.3.

~ Grass-cow-milk dose factor for each identified nuclide i, m2-mrem/year per pCi/s. Dose factors are calculated as described in Section 7.8.1.

RGi ~ ground plane dose factor for each idcntificd nuclide i, m2-modem/year per pCi,/s. Dose factors are calculated as described in Section 7.8.14.

1890o

RETS Nsnual Revision 10 Page 146 The release rate limits, r, calculated for BFN using this methodology are:

Noble Gas Iodine and Particulate Stack rags 1.44E+Ol Ci/s rips ~ 3.57E-05 Ci/s Building Vents rngv ~ 1.50E&l Ci/s ripv 2 '9K-06 Ci/s The values listed are used as administrative guidelines for operation.

The instantaneous release rates, r in Ci/sec, for each nuclide type and release point are limited by the following equations:

For noble gases,

~rn + ~rn s c 1

0. 15 14. 4 For iodines and particulates,

~

ripv 19EW6

+ ~ri s 3.57K&5 i i 1890o

o RETS Manual Revision 10 Page 237 Table 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Approximate Indicator (I)

Location Distance or Samples Number a Station Sector 1 PM-1 NW 13.8 I hP,CF,S 2 PM-2 NE 10.9 I AP0 CF% S 3 PM-3 SSE 7.5 I AP0 CF, S 4 LM-7 W 2.1 I hP, CF, S 5 RM-1 W 31.3 C AP,CF,S 6 RMW E 24.2 C AP% CF, S 7 IA-1 N 1.0 I AP,CF,S 8 IA-2 NNE 0.9 I AP,CF,S 9 LM-3 ENE 0.9 I AP% CF, S 10 LMW NNW 1.7 I AP,CF,S ll 12 IA-6 Farm B SSW NNW 3.0 6.8 I

I AP, M

CF,S 13 Farm Bn N 5.0 I M0 W 18 Farm Gl WSW 35 C M% V 22 Well 06 NW 0.02 I W 23 c 282.6 I PW 24 TRM 303.0 12.0 C PW 25 TRM 259.6 34.4d PW 26 TRM 274.9 19.1d I PW 27 TRM 285.2 8.8d I SW 28 TRM 293.5 0.5d I SW 29 TRM 305.0 ll.od Ce SW 30 TRM 307.52 13.52 C SD 31 TRM 293.7 0.3d I SD 32 TRM 288.78 5.22d I SD 33 TRM 277.98 16.02d I SD 34 Farm Be NW 28.8 C M 36 Farm T WNW 3.2 I V 37 TRM 297.0 3 Od C SD Wheeler Reservoir I/O F, CL (TRM 275-349)

Guntersville Reservoir (TRM 349-424) a See Figures 9.1, 9.2, and 9.3

'b Sample codes:

AP ~ Air particulate filter S i Soil SD ~ Sediment CF ~ Charcoal Filter SW ~ Surface Water CL ~ Clams F ~ Fish V ~ Vegetation PW ~ Public Water W ~ Well Water M ~ Milk TRM = Tennessee River Mile Miles from plant discharge (TRM 294)

Also used as a control for public eater 1890o

S ITE ADMINISTRATION OF SSP-2.3 STANDARD SITE PROCEDURES PRACTICE NOY D 4 l991 FORM SSP-2 Page 1 of 2 SAFETY ASSESSMENT FORM Procedure No. ETS YAa~hp Tracking No. I YES NO Does a previous safety assessment adequately address this change?

If yes, go to page 2, and state in the summary section which previous assessment is applicable.

List the specifi Tech Spec requirements (by number) associated with this procedure:

9 Z b. Q,.A.I YES NO NA A. Does this procedure (or source notes) specify the Tech Spec requirements it implements? (If a procedure does not fully satisfy a Tech Spec requirement, it must state what part of the requirements it does fulfill.)

B. Does this procedure satisfy all associated Tech Spec requirements?

is this ptocedute consistent with the basis tot the applicable Tech Spec requirements?

If any of the preceding questions A through C are answered "NO", then l) Change the procedure to achieve a "YES" answer, or

2) Obtain a License Amendment from NRC before proceeding.

List the SAR sections and documents related to this procedure:

A 7.l dP. 9.

D. Does the procedure require system operation consistent with the SAR?

E. Are setpoints and acceptance criteria consistent with the SAR?

F. Is the procedure consistent with personnel duties and responsibilities specified in the SAR?

Are prerequisites for plant systems status and equipment d' d q te and consistent with safe operation?

TVA <NN4 (ONP-u-8s)

0

~ I

~ ~

I ~

l~ ~ ~ ~

~ ~

~ ~

' ~ ~ II ~

~ ~ ~ ~ ~

~ ~ ~

~ I ~ ~ ~ ~

I~ ~ ~ ~ 'l ~

~ I ~

~

~

~ ~ ~ ~ II

~ ~ ~ ~ ~ '

~ ~ II> ~ ~ ~

~ I t g ~ I r ~ f ~

I~ ~ I ii o ~~ tOO 'u 4 O.'alu i I )a ~ ~ 0 ~ Wf! e 4~ O'II ~ ~ . eg ~

~ '

j j ~

4 II 0

~ ~

~ ~ I' ~ ~ ~

~ ~ ~ ~

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT RETS MANUAL RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATION (RETS)

REltISION ll PREPARED BY: DALE W. NIX PHONE: 2682 RESPONSIBLE ORGANIZATION: CHEMICAL TECHNICAL SUPPORT APPROVED BY: J. SCALICE DATE: 06/22/92 EFFECTIVE DATE: 06/25/92 VALIDATION DATE: NOT REQUIRED QUALITY-RELATED

(1496)

REVISION LOG Procedure Number: RETS MANUAL Revision Number: 11 Pages Affected: 103, 106, 107 Pagination Pages: 1-102, 104, 105, 108-266 Description of Change:

The release point description has been revised to more accurately reflect the minimum dilution flow expected when closed or helper mode is entered. The equations given for liquid monitor setpoints are revised to correct mathematical errors identified during a review.

RETS Manual ll t

Revision Page 103 6.0 LI UID EFFLUENTS RELEASE POINTS The minimum flows available for dilution of radwaste are shown below:

+ open 3 pumps 8 200,000 gpm/pump 4

Radwaste- Discharge 4 Conduit

+ closed/helper 50,000 gpm 1442p

g~ I RETS Manual t

Revision 11 Page 106 6.2 INSTRUMENT SETPOINTS Alarm/triP set P oints for each liquid monitor will be established and set such that Equation 6.3 is satisfied. The locations and identification numbers for each liquid effluent radiation detector are shown in Figures 6.1 and 6.2. This section of the ODCM describes the methodology that will be used to determine allowable values. The allowable values are then used to determine the physical settings on the monitors. The physical settings are calculated in the applicable Scaling and Setpoint Document.

6.2.1 Radwaste Dischar e Monitor The allowable value for the radwaste discharge monitor (RM-90-130), shown in Figures 6.1 and 6.2, will be established using the methodology below.

The alarm/trip allowable value will be set such that Equation 6.3 is satisfied. The trip allowable value for the monitor, which will automatically isolate the release, is set at less than or equal to the limit in Control 1.2.1.1. The alarm allowable value is set at 50K of the trip allowable value.

The maximum activity concentration of liquid radwaste that can be discharged can be calculated as:

1 A = F +

f*L f

MFi MPC.

where:

A maximum batch activity concentration, pCi/ml.

Mpci Maximum Permissible Concentration, from 10 CFR 20 Appendix B for nuclide i, pCi/ml.

weighting factor for nuclide i, defined as the fraction of the total concentration which is attributed to nuclide i.

dilution water flow rate, gpm.

maximum discharge flow rate, gpm.

The maximum activity concentration is based on a selected isotopic mixture so that an allowable value can be calculated. The selected isotopic mixture will be documented in TI 45. If the actual batch MPC is less restrictive than the MPC for the selected isotopic mixture, then the actual activity concentration may be higher than the calculated maximum activity concentration.

1442p

0 RETS Manual Revision Page 107 ll I

The monitor isolation allowable value, in cps, for releases

~ ~ ~ ~

is calculated using the following equation:

~ ~ ~

Monitor Isolation Allowable Value = (A *

~ ~

E WF *Ei) + B where:

A maximum batch activity concentration as calculated above, pCi/ml WFi weighting factor for nuclide i, defined as the fraction of the total concentration which is attributed to nuclide efficiency of the monitor for nuclide i, cps/pCi/ml i

Ei B monitor background, cps The calculation of these allowable values are documented further in TI 45, including the numerical values for each of the parameters described above.

6.2.2 Raw Coolin Water and Residual Heat Removal Service Water Monitors The allowable value for the Raw Cooling Water (RCW) monitors and the Residual Heat Removal Service Water (RHRSW) monitors (RM-90-132 and RM-90-133,134 respectively), shown in Figure 6.1, will be established using the methodology below. The alarm/trip allowable values will be set t such that Equation 6.3 is satisfied.

The a

The allowable values for these monitors, which will alarm in the control room, are based on the 10 CFR 20 APP endix B concentration limits. Th ese allo wable value s are also based on selected isotopic mixture.

monitor alarm allowable values, in cpm, for the RCW and RHRSW effluent monitors are calculated using the following equation:

Monitor Allowable Values

• C

< (A g WFi*Ei) + B i

where:

A total activity concentration, pCi/ml.

WFi weighting factor for nuclide i, defined as the fraction of the total concentration which is attributed to nuclide i.

Ei efficiency of the monitor for nuclide i, cpm/pCi/ml.

B monitor background, cpm.

The calculation of these allowable values are documented further in TI 45, including the numerical values for each of the parameters described above.

1442p