ML19225B090
| ML19225B090 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/20/1979 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML19225B086 | List: |
| References | |
| TR-790720, NUDOCS 7907230497 | |
| Download: ML19225B090 (61) | |
Text
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[. d 1 ( OFFSITE DOSE CALCULATION M'\NUAL [:. ~,? '~ ' n '. N CONIENTS: 7. [ '
.' ~ s' s 't .
r ' . , ', '.- r. I. I!;TRODUCTION & PURPOSE ~ M?'~ a' , .~; ,' ?.' ,
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II. LIQUID EFFLUE!;T DOSE CALCULATIO:;S A. METliODOLOGY & ASSUMPTIO:;S B. DOSE FACTOR INFORMATIO:1
~
C. Ai 1 (DOSE FACTOR TABLES) D. SETPOII;T DETERMINATIONS
-. II1. GASEQUS EFFLUEI;T DOSE CALCULATIONS A. MET 110DOLOGY & t SSUMPTIONS B. IMPLFMENTATION OF 10CFR20 - 10DII;ES & PARTICULATES C. IMPLEMENTv. TION OF 10CFR20 - I;0BLE GASES D. 10CFR20 DOSE FACTOR INFORMATION - Pi (Inhalation),
i
- (Ground P1ar.e), (Food) i E. GASEQUS MONITORS SETPOIIiT DETERMIN/sTION ~
F. IMPLEMENTATION OF 10CFR50 - 10DII;ES & PARTICULATES G. IMPLEMENTATION OF 10CFR50 - NOBLE G/sSES H. 10CFR50 DOSE FACTOR INFORMATIO:1 - Ri (Inhalation),
== (Ground Plane), (Grass-Co.-Milk), (Grass-Cow-Meat),
l (Vegetation) I. REFERENCES I.
.fr.,
g e) r) tu? f} un
i g . 1 1( I. I!;TRODUCTION & PURPOSE I The OFFSITE DOSE CALCUI.ATION MANUAL (ODCM) is the document
- that out lines JAFI;PP's basic rrethodology for calculating radiation (ioses resulting frem releases of both gaseous and liquid effluents. Thi s trethodology is adapted from the guidance i
I u p1oculgated via NUREG 0133 and deviates from that puidance in only two site specific cases. L In the case of liquid ef fluents JAFNPP has elected to use actual L F C. values (near field average dilution factor for Cil durinh any liquid effluent release. NUREG 0133 defines Ft as the ratio of the maxit:.u:r undiluted liquid was te flow during release to I the average flow from the site discharge structitre to unrestricted L receiving waters, JAFNPP feels that a more quantitative method
.zould b, to utili..e actual empirical information in the calcu-lation of F2 and subsequent dose assessments based in part on the Fi parameter-L In the case of gaseous ef fluents JAFNPP has elected to utilize empirical determinations of D/Q and X/Q for the site boundary location obtained from 1974-75 meteorological data, this we feel allows a r. ore accurate and realistic assessment of dose to the infant thyroid from the iodine contribution, m
In all other parareters and assumptions JAFNPP has utilized the a guidance of MUREG 0133 and associated supporting documents. t
= 44? 0:0 J
-1 r
i CALCUMIl0!L DE DOSE _IOEXIIiUR_EXE0 SED _lHDIYlDUAL fROR LIQUID _EEELUENI a.d Technical Spe ci fi ca ti ons state, "cumulati"e dose conti 2tions f rota ., licuid effluents shall be determined in accordance with the offsite e dose calculation manual at least once per 31 days," At J aft:P P , the cumulative dose contributions consider the dose con-r .1 t ribut i ons fro:r the maximuni exposed indivi dual's consu'.pr ion o f fi sh r emd pat au2 e water Invertebrate consumption is not a fact or as JAF:;PP l it a fresh water site. JAF;PP takes the position that the adult is the i maxin um .: . paced individual as is reconrended by liUREG 0133. (ref. 1) a s ub s e q u e r. t l y , J/sF:;PP ha s developed tables of Air fo r the adult case. The relationships and c.e tl.ods that fo r::t the calculational base for l d o.> e accounting for the liqui d ef fluent pathway are as follows:
,3 TR D ;e contributions for the total tin.e period i st will be determined I
i=1 by calculation at least once per 31 days and a cumulative sunration of 4 t h e:;e t otal body and critical organ doses will be maintained for each h calendar quarter. These dcse contributions will be calculated for f j all radionuclides i denti fied by JAFI;PP in liquid effluents released to
. unrest ricted areas using the following expression:
i y D, =- L i ' hi z v f=I
- . t i Cil Ft m
M.ere:
, D: = the cun.ul a t i ve dose c oan.i tmen t to the total body or any organ, m
1, from the liquid effluents for the total time period ttt, f=1 in trem vs I L.,
i 1 t.tf = the length of the fth time period over which Cif and Ff are " i averaged for all liqui d releases , in hours. 1
,t Cif = the average concentration of radionueli de, i. in undiluted 1
liquid ef fluent during titre period Itf f roin any liquid release, in a c i / r: f . a Ai1 = the site related ingestion dose conM trent factar to the total body or any organ T for each JAFUPP identified principal a a gat.ra and beta emitter listed in table L1-3 , in mrem-ml per hr-aci Ff = the near field average dilution factor for Cif during any 3 liquid ef fluent release. Defined as the ratio of the maximum undiluted liquid waste flow during release to the average a flow from the site discharge structure to unrestricted re-
, ceiving wa t ers .
I Tn e term Cif is the con:posite undiluted concent ration of radioactive h material in liquid waste at the release point ns determined by the I b radioactive liquid waste sampling and analysis program as contained in the technical snecifications. All dilution factors beyond the D sample noint are included in the Ff and Ai1 terms. D The term Ff is a near field average dilution factor and is determined r as folloes: b
, nec cm
't ' t / UJL
\l 9
& s a r
\
Ff = Liquid Radioactive Waste Flow i)liIcha rge St ruc ture Exi t Flow The liquid radioactive waste flow is the maximum flow from all continuous and batch radioactive effluent releases specified in Technical Speci fications from all liquid radioactive waste management systems. The discharge structure exit flow is the average flow during disposal from the discharge structure release point into the re-
'~
ceiving water body, is t JAFSPP, the maximum flow from all liquid effluent releases is 200 gpm and the discharge structure exit f l o ..; is 378,000 gpm with { all circulating pu gs in operation, thus; i
' FL = 200 =
5.29 E-04 375~,055 Hov;e ve r , in order to provide a more accurate estimate of Ff , J Ai ;,e will calculate FL hased c actual operating parameters that exiom at the time of releases. This affords a more quantitative a: ment of radiation dose resulting from liquid effluent releases at JAF:PP Therefore: Ff = Actual Liquid Effluent flow
- Actual Discharge Structure Exit Flow I
u A
^
r y ',) G~ us W
1 . , j r S DOSE FACIORlELATEDJO LIOUID_EEftUEUIS r I The equation for dose from liquid effluents requires the use of a [ s dose factor Air for each nuclide, i, which embodies the dose factors, p p.a i t n.;a y t rans fe r factor, pathway usage factors, and dilution factors 5 for the points of pathway origin. JAFNPP has fo. lowed the guidance of NUREG 0133 and has calculated Ai1 for the total body and critical arran of the maximun, exposed individual e.g. the adult. The dose ! factors were cor..pil ed f rom table E-ll of Regulatory Guide 1.109 (ref 2) The ;u'.ary dose factor is as follows: Ai1 = ko ( Uw / ' >,.y a UF BFi) D fi Uhere: Ai1 = co..posite Jose pa ra:Le t e r for the total body or critical organ of an adult for nuclide, i, for all appropriate pathway >, trem/hr per uci/mf ( ko = units conversion factor, 1,14E05 = 10'pci/aci f x 10 ml /k g i T
, 8760 hr/yr t
[ U.,. = 730 kg/yr, adult. wat er con a.: pti on BFi = Ricaccumulation factor for nuclide, i, in fish, pCi/kg per pCi/l f ro:r table A-1 of Regulatory Guide 1.109 L
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g, , 1 { .( k = dose conversion factor for nuclide i, for adults in DFi pre-selected organs, 1, in trem/pci, from table E-ll of Regulatory Guide 1.109 r i Du = dilution factor from the near field area within one quarter mile of the release point to the Oswego City and Ononega County intake. (nearest potable water intake) I A lake dilution factor of 9.2 was calculn+cd using the quasi-steady state model as described ui section C.3, "large lakes," of Regulatory Guide 1.113. (ref 3) For the JAFiPP site Ai1 can be expressed as:
% Ait =
1,14E05 (730/Dw + 21 BFi) DFi Given D w = 9.2 Ai1 = 1 14E05 (79.3 + 21 BFi) DFi JAF:;PP has compiled Air factors for total body and cri ti cal org ns - for the maximum e ; posed indivi dual . These are included as table L1-3 b Ene W l i 4 ,73 r. - r-gy ~I \ J em
a i ,< 1. i.i- t7m -. ~ ~~ ('e n.7 , o r . -a,1 I
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Case - Adult (M a nin i es:poned indiv) Air = (1.14E0 5 ) ( 7 30 / Dw
- 21BFi)DF Pathway Potable k'a re r & Finh ni- =
(1.14E05 ) ( 7. 0 3 4 21BFi)DF crope D.. B ri ( '~i M E ('. v'o od'G M (c'
- o r , mD N *if al o r " a n _. i -- M h o d'D Aj ' (C O 3
H : 9." ' 9.0E-01 1.05 E-07 '.05E-n- unole bodv 3.21E-01 i3. 21E-( l 2"c "
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;6.2sEn1 1.19 r.n. c
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I OE02 l 1 70E-06 1.70E-06 i
'Ja o l e b o dy 4.0SE02 k. 08E0:
4-' i i i P i 1.0E05 7 46E-06 1.93E-04 , Bone 1.78E06 p.62E0~ ' " r, o r. - 0 7 gr '
,o .nEn2 7.nrF no 6 GI-LLI '. 27E00 l3. 2 0EO.
54 u, , 4 . n__r n.,, F 7 ." r n7 1.l.n:.._n5 G ~1
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'o u n i " l 4.0En2 I 2 r/E-08 ' 3.67E-06 GI-LLI 1.95E01 3.51E0: Fe 1. O t:0 2 l. L'2E-07 2.75E-06 ~3 cn e '1.06E02 I {60E0: Fe t i 1.0E02 l , ole-06 3.40E-05 GI-LLI ,0.39E02 f.17E0: 5" " ' Co ! 5.0E01 1.67E-06 l.5]E-05 ! GI-LLI I2.01E02 ll . 82 EO . l
- c Co i l 5.0E01 ! 4.72E-06 _
, 4.02E-05 GI-LLI 5.60E02 p.84E0:
3 M l 1.DE02 l 4.3EE-06 1.30E-n4 1 done 1, c ' =.0 3 3.12EO. m i
- 1. n r:0 2 1 1.". - 0 8 1. 7 /.E- 0 6 i GI-LLI 7 ;2E00 L'4 .18E0:
' C u l ' 5.nE01 ' olk-n8 -/ 10E-06 l GI-LLI i. 71E00 t3. 5 6EO. 7 91 cn ;
.nEn' 6.06~.06 '
l.54E-05 Liver 3.33E04 i7. 3 7 EO. I la ver ' ' Zn I " 2.0E03 1 77E no 1 07E-08 6.5fE00 h43E0 "'gr -n . " 4 . g,_7 /.Oor_0g 5.70E-08 i GI-LLI 4.04E01 [5.82E0 s
" " Br 3 "
4 2E02 5.21~:-05 4 5.21E-08 h~n o ] e nodv IS.24E01 L5 . 24 E0
' B r i i 4.2E02 '
2 14E-09 l 2 . ll.E- 0 9 h~nole body ,2.15E00 j2 .15 EO . Rb ci " l 2.0E03 i 9.83E-06 ; 2.. I l E- 0 5 i Liver j4.70E04 l1. 01EO . Rb Y
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i 2.0E03 i 3.21E-08 6.05E-08 l Liver ,1.5.3E02 l2. 6 9 EO. Rb l ! 2.0E03 l 2.82E-08 4.01E-08 , Liver i1.a5EUz ji . 9 2 EO . 89 Sr I " i 3.0E01 . E.84E-06 3.0EE-04 i Bone '6.42E02 j2. 2 3EO. Sr l
" l 3.0E01 '
1.86E-03 7.5SE-03 , Bone 1.35E05 ?.31E0
- Sr !
3.0E01 2.20E-07 2.70E-05 i GI-LLI 1.66E01 l1.96E0
' Sr l ! 3.0E01 l G 30E-08 i 4.26E-05 i GI-LLI '6.76E00 i l3.09E0
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! 2.5E01 2.58E-10 j 1.02E-04 GI-LLI l 1. 5 61.- 0 2 m.19E0
[ l
~~ -
- --1 7 T ,c t t __ [_ t : r '- -i e f-' l .
ni - Liquis affluent IAF"PP _ Case - Adult C 'a x i m"- expmec i n C 'O A1T = ( 1.14 E0 5 ) ( 7 3 0 / D.,, .
- 21 B Fi) DI Pathway Potable '.- l.' t e r & "- ni, AiT =
(1.14E05)(7 93 t 21 eft)DF
, t cm e D '.. ,m, (c; O ,-c. , , r. w> - - ;c- - em ,n) Crit cal orran A " n.nodv) /.i - ( C O) y l o,2 l 2.5E01 '
5?b ' / 'c. - 10 n ~ -I ' T ? ' V-n 4 1. 6?E r
'Y i i ? 51'0 . ' 7 -" - 0 0 7 7i1-05 G~- LI ? '9E-01 '4 . 71 E0 '
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te " i 1.5E01 ' Soit-09 6.59E-09 K.dne" 1.32E-01 b.42E-f Ru I " !
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A7- I t (iT R."c~-08 6.04'-05 G ~ -I.LI 2 "GE-01 1.09E0: 9e [ " ' 4.rra? 's .co!-n7 1.noE-05 : dne" l /- 4 r.0 2 1.04E0/ he P" ! 4.1r02 ' 8.'5E-07 i 2 75E-05 u dnev 7.90E02 2. 6 3 E0/ Te j " ' 4.0E0? 2 '8E-08 . i 8.68E-06 G~ LLI 2.2SE01 B.31E0: n t > " Te E. !. 4.DE02 1 E2E-06 5.70r-05 1 GI-LLI 1.74E03 5 54E04
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invroic J, . ,.,.;- .,r.0, ,1 6 . o. ;c r.0 i l 1.5E01 ' 3.41E-06 i 1 GSE-03 Th"roid 1.25F07 7.17E0/
! l 1.5E01 i 1.90E-07 '
l.00E-05 Tnvroid 6,09E00 h.99E0 I l l 1.5E01 1 7.53E-07 3.63E-04 i invrctd i 2.77E01 [1. 3 3 EO. T. t j . . _, cr.n, ,
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I 4 GCE-06 i Tnvroi d I 3.79E00 ll.83E0
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""{ " Y "'s Ca u - Adult - (Ma>.imum e>. posed indiv) /s i T ='
(1. ' 4E05 ) ( 7 30 /D w 21BFi)DF Pathway Potable 'ater & rich Ali = (1.14E05) (7,9 3 + 21BFi) DF n one "r4 (f4 nh1 .~1 (-
.o.e , o d 71 D i' (crit crran) Cri ri cal o rr'n I . - f(wh bod'c) Ai T (CO: '5 7 l o,, ,
57 1 f. eet_r-
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r' g s ' o , pgr, Cs
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1.48E-04 Liver 5 . 7 9 ~'0 5 ! 7. 0 8EC Cs I 2.0E03 1..F5r-05 2.57E-05 L.ver t.85E04 l 1. 23EC
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,u i1.80Ef Ba 4 . r. :'n n '.8/.r.-0G 1 ~2E-07 GI-LLI '. 07E-02 Ba i "
/. 0EOC 1 ,3E-06 4.18h-05 GI-LLI t
- 1. 39E01 l 4. 38EC L-
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- z. ornn 1 soE-no l 4 1E-08 'one i .ME n2 l 4.93E-Ba I " '
.. . h :0 0 1. '. ! ' t - 0 9 2 13E-08 Bone 1.40E-02 l 2. 23E-1c i La j "
' ' SZ01 3.s3E-10 ! o.2SE-05 GI-LL1 ?.C2E-02 l5.61Et Ta ' " '
SE01 1 45E-11 4.25E-07 i 'I-LLI 8.80E-04 l 2. 58EC Ce ! 1.1^E00 ' 18E-10 2.4?r-05 , Gi-LLI ? . 3 6 ~. - 0 3 l7.98EC Ce ! 1.0En0 1.15E-10 4 56E-05 GI-LLI L i.5E-04 l 1. 50E' Ce
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- crno ?.6?E-n8 i.65E-04 GI-LLI R 64E-02 l5.44Er Pr ,
'm} /, _r r_ __ ,n r, 4.03r.-05 GI-LLI 2.77E-02 l 2. 44E' 4 4 pr ! "
o R1 ' 1.53r.-22 3.01E-li Bone G 29E-05 i 1. 82E-
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2 . 5 I' i l ' 4 . 3 5 E - 10 3.LoE-05 GI-LLI 2.64E-02 l2.12Er W ! 1.Tr03 i 3.0;"-08 ?.8?E-05 GI-LLI 5.f4E01 !8.10Ef NP l 1.0E01 6.45E-11 i 2.40E-05 GI-LLI 1.60E-03 l5.96Ei l ,_ i ! ! l i i , , I m i i 1 (.d i l j j l r 1 l 4 I
; i
SETPOII;T DETEFJ41!1ATIO:1 ( LIQUID EFFLUE!!I' MO!;ITOR I The purpose of this section is to outline the metFod utilized at J AF:;PP to assure that the radioactivity release concentration in the discharge tunnel does not exceed the values speci fied in f j 10CFR20, Appendix B, Table II, Column II for unrestricted areas. The liquid effluent centrol n.onitor is set to alaru and auto-matic,11y close the wrste diacharge valve and terminate the release r i prior to exceeding the l i n. i t s referenced supra. A f The calculated setpeints for the liquid effluent n.onit or sa ti s f y J the folloling couation: a a I cf F fI -
< C 4
2 kb re: C = the e f f l u e n t. ccncentration l in;i t implenient ing 10CFR20 for J . the site in ;.ci/ nil. This value will he derived from j radioan11ytical analysis of liquid ef fluent to be released. This value will be supplied for each liquid release, ld c = the setpoint, in pei/ml, of the liqui d e f fluent monitor i n.casuring the radioactivity concentration in the ef fluent line prior to dilution and subsequent release. This set-point represents a value which, if exceeded, would result 7 in concentrations exceeding t he l i n:i t s of 10CFR20, Appendix E, Table II, C o l t..:.n II, to an unrest -ic t ed a rea. L m - 9 et f vs/ L
f , J t-G a ( F f = the liquid effluent flow as measured at the liquid effluent 1,~ monitor location in gallons /r:in, i the dilution water flow as determined via pump curves and { a F = current plant operating confi guration (measured in gallons / F min). g Note: F is large co.:. pared to f therefore F + f = I-r The value C will he calculated for each release and the parat:eters . a for f and F wil1 be supplied based on current plant operating configurations. The setpoint will be calculated in terms of pei/ml and the liquid effluent monitor will be adjusted to insure that liquid releases are secured prior to exceeding limits speci-fied in 10CFR 20, Appendix B, Table II, Colt:mn II to an unrestricted area. P The method by '-chich the liquid effluent monitor is calibrated involves a se ri es of det ailed steps that basically are as follows:
- 1. An external radiation survey in the area of the liquid ef fluent menitor is made to ascertain i f background radiation levels f have changed .;ubsequent to the previous calibration.
- 2. Detector high voltage is Ir.easured and various electronic para-b meters are reviewed to assure that the clectronics hardware
( is functional. L b, l\ ) ,
i n L r a i t p
- 3. A check source is inserted in the shield and the plateau of 1- naximum e f ficiency and stabili ty is selected.
1
- 4. An ef ficiency calibrat ion is performed by utilizing a series
( of cannisters containing actual liquid waste effluent of
,_ various radioactivity levels. Both the radioactivity level and isotopic content of the cannist ers are ascertained by
[ multi-channel pulse height analysis. i
- 5. The pei/ml concentrations for the above cannisters are plotted versus the liquid effluent monitor readit.g in c/s. A K-factor
,. is calculated (pci/ml per c/s) for each cannister. The average o f the K-f actors is calculated and recorded. t An e :> a r .p l e of a typical liquid release setpoint calculation is as foll cws : l A: sume C = 3E-07 pei/ml f = 100gpm (63. 3 ml /sec/ rpm) = 6. 33E03ml / sec F = 3.7EE05 rpm (6 3. 3nl / s e c/ gpm) = 2,39E07ml/sec l w c = i [_ Khere: c 1 CF 1 I c < 3E-07uci/ml ~~2.39E07 191/sec
- 6. 31E0 3 11/ s ec t
' e 1.13E-03 pei/ml 5
I L
,1 f U
'i y' j
't !
M
>l ; b J The setpoint of 1.13E-03 pci/ml will be applied to the liquid e f fl uent tr.on i t o r to insure concentrations of radioactive material b in liquid ef fluent released to unrestricted areas to not exceed i j the l i r.i t s speci fied in 10CFR 20 Appendix B, Table II, Column II. R a t+ e r , the 1iquid release will be determined via the operrition I of a autor.atic isolation valve. I t. I L L
~
N em M n r. fe $e l yo , s ed L
1 2( IMPLEMENTATION OF 10CFR20 - AIRBORNE RELEASE 3 i 10 DINES E PARTICUU\TES WITH llALF-LIVES GREATER THAN 8 DAYS 1 Technical Specifications state: "The instant aneous doce rate in 2 unrestricted areas due to radioactive materials released in gas-3 eaus effluents from the site shall be limited to the following values: I ,
- b. The dose rate limit for all radioiodine and for all radio-t o active materials in particulate form and radionuclides other than noble gases with half lives greater than 8 days shall be < 1500 mrem /yr to any organ."
This spoci fication shall be implemented using the following general releationships: E Pi 'lsQis + UvQiv
.- < 1500 r. rem /yr i
g L I Where: Pi = The dose p a r a:: e t e r for radionuclides other than noble 3 L gases for the inhalation pathway in rc. rem /yr per pCi/m and for food and ground plane pathways in ao crem/yr per pCi/second. The dose factors are based on the critical i individual organ and most restrictive age group (in f ant), Section PI of Gasecus Effluents - Calculation of Pi (inhalation), contains the bases and nodels for calculation of Pi (inhalation) and 6 its tabulated values, Designated Pi (in). 4 d ') 0:t ; a
W t Section PI-2 of this manual, Gaseous Effluents - Calculation of Pi (ground plane) contains the bases and models for calculation ,I a of Pi (ground plane) and its tabulated volumes. Designated Pi (gp), 4 i Section PI-3 o f this manual, Gaseous Effluents - Calculation ., of Pi(food) contains the bases and models for calculation of Pi (food) i and its tabulated values. Designated Pi(f). Pi (dep) = Pi (EP) + Pi (f) . Tabulated values of Pi(dep) are 'ncluded in this section. tL
=
6 Qis =- Thc release rate of radionuclide, i, in gaseous effluents [
,. from free-standing stack in pei/sec.
L Qiv = The release rate of radionuclides, i, in gaseous ef fluents i from all vent releases, in pCi/sec. L W3 = The highest calculated annual average dispersion para-I meter for estimating the dose to an individual at the L cont rolli ng l oca ti on due to free standing stack releases: L s(in) = 8.07E-08 sec/m 3 , for the inhalation pathway, stack release. The location is the unrestricted I area boundary in the ESE sector, i i m -2
- W s(dep) =
4.79E-09 , for the food and ground plane f { pathway, stack release. The location is the ( unrestricted area boundary in the east sector. w I
] ?
I P 1 Il v = The highest calculated annual average dispersion f parameter for estimating the dose to an indivi-a dual at the controlling location due to all vent releases:
'" 3 Ilv(in) = 6.73E-07 s/m , for the inhalation pathway release. Thc location is the F $ unrestricted area boundary in the Pt ENE sector.
I y l#v(dep) = 4.77E-09 m-2 for the food and ground plane pathway, vent release. The loca-I tion is the unrestricted area boundary in the east sector. rs I
-, To estima te the dose late for radiciodines and radioactive marerial in particulate form other than noble gases, and with half-lives greater ~
than S days the following relationship shall be used: g _. p (ils(dep)) [L Pi(in) (\ s(in))(Q)is + (llv (in) ) (Q) iv
+ Pi(dep) 1 g
(h) i. s + ('*1v(dep))(h)iv = dose rate (mrem /yr)
=
se I L me t h h I 1 6i C !i / V '1 s
f H i Pi(deposition) = Pi(food) + Pi(ground plane) Pi(food) + Pi(pround plane) = Pi(denosition) ISOTOPE 7.88E06 1.27E07 Cr-51 4.78E06 1.29E10 1.29E10 Mn-54 3.97E07 4.56E08 8.55E08 Fe-59 3.99E08 6.18E08 6.79E08 Co-58 6.17E07 5.17E09 '5.38E09 I Co-60 2.14E08 7.90E08 2 .0 2 E10 i Zn-65 1.94E10 1 3.58E04 1.28E10 Sr-89 1.28E10 1.24 Ell 1.24 Ell Sr-90 4.08E08 4.09E08 Zr-95 8.46E05 2.98E07 1.08E12 l-131 1.08E12 4.26E06 9.74E09 l-133 9.74E09 3.27E09 7.25E10 Cs-134 6 92E10 2.41E08 6.12E09
's Cs-136 5.88E09 1.34E09 6.26E10 , Cs-137 6.13E10 3.35E07 2.79E08 Ba-140 2.46E08 2.19E07 3.56E07 Ce-141 1.39E07 N _
- H-3 -
tt - 1.63Eli P-32 1.63E11 i
- 1.38E08
, Fe-55 1.38E08
- 2.38E09 C-14 2.38E09 concentrackon L
- The concentration of H-3 in milk is based on its airborne rather than the deposition rate.
3 for H-3 only Pi(dep) = 2.4 x 10 3 mrem /yr per pCi/m , L 34, c,..o
y a r t i IMPLEMEf1 TAT 10fl 0F 10CFR20 - AIRBORf1E RELEASES L [10BLE GASES Technical Speci fications state:
"The instantaneous dose rate in unrestricted areas due to radio-active materials released in gaseous effluents from the site shall be limited to the following values:
I
- a. The dose rate 1imit for noble gases shall be < 500 mrem /yr I to the total body and < 3000 mrem /yr to the skin, and "
This specification shall be i n.plen.ent ed using the following rela-tionship: Release rate limit for noble gases: j F _( Ei) (X /Q)s (Qis) + (Ki ) (x / Q)y(Q) iv) -
, <500 mrem /yr, and ! 1 E
i ((Li+1.1Mi) (x / Q) s (Q) + i s(Li+1. lMi) (E /Q)v(Q)iv ~
< 3000 mrem /yr
_ - 7
= iE [(Si ) (x /Q)(Q)is s + (S i. ) (x / Q) v (Q) i v -
< 3000 mrem /yr I
. b"n e r e :
Xi = The total body dose factor due to g an.ma emissions for
~
each identi fied noble gas radionuclide, in trem/yr per pCi/m3 u Li = Tn e skin dose factor due to beta emissions for each a i denti fied noble gas radionuclide, in mrem /yr per l pCi/m 3 ,
~
Si = (Li + 1.1 Mi) in trem/yr per pCi/m 3, (
- L
( r Mi = The air dose factor due to gamma emissions for each identi fied noble gas radionuclide, in mrad /yr per pCi/m 3 (unit conversion constant of 1.1 n: rem / mrad converts air dose to skin dose). Qis = The release rate of radionuclides, i in gaseous eff-luents from free-standing stack, in pCi/sec. Qiv = The release rate of radionuclides, i, in gaseous ef f-luent from all vent releases, in pCi/sec. (x/Q)s = 8.07E-08 sec/m . For free-standing stack releases. Th e h i gh e s t calculated annual average relative con-centration for any area beyond the unres tricted area boundary. (x/Q)v = 6 73E-07 sec/m 3 For all vent releases. The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary. b mems M .i
- O n *Q ii ., y l'r h ! U W
use
Table NG-1 I. 't TOTAL BODY DOSE FACTORS 4 Ki j i 3 NUCLIDE ) - BODY
- 106 (pCi / uCi) Ki 'c
- f Kr-83m 7.56x10-8 X 106 7.56x10-2 J
Kr-85m 1.17x10-3 X 306 1.17x103 $ Kr-85 1.61x10-5 x 106 1.61x10 1 6 3 Kr-87 5.92x10-3 X 10 5.92x10 9 1.47x10-2 X 106 1,47x19 4 J Kr-88 n Kr-89 1.66x10-2 X 106 1.66x10 4 Kr-90 1.56x10-2 X 10 6 1.56x10 4 Xe-131m 9.15x10-5 X 106 9.15x10 1 iL Xe-133m 2.51x10-4 X 10 6 2.51x10 1 i l 's e - 13 3 2.94x10-4 X 106 2.94x10 2 Xe-13Sm 3.12x10-3 X 106 3.12x10 3 Xe-135 1,81x10-3 X 10 6 1.81x10 1.42x10-3 x 106 1.42x10 3 { Xe-137 3
':e - 13 8
- 8.83x10-3 X 10 6 8.83x10
- Ar-41 8.84x10-3 X 10 6 8.84x103
- from Regulatory Guide 1.109, Table B-1 3
<- Ki (mrem /yr per pCi/m )
8
<,4 )
L a h
- Table NG-2 I
y SKIN DOSE FACTORS 1 u I 106(pCi/oCi) ,j NUCLIDE 6- SKIN
- Li **
., Kr-83m X 10 6 6
Kr-85m 1.46x10-3 X 10 1.46x10 3 Kr-85 1.34x10-3 X 106 1.34x10 3 '[ 3 K r- 8 7 9.73x10-3 X 106 9.73x10 '? 6 j Kr-88 2.37x10 ,~ X 10 2.37x103 6 Kr-89 1.01x10-2 X 10 1.01x104
'f' 6 Kr-90 7.29x10-3 X 10 7.29x10 3
( 2 Xe-131m 4.76x10-4 X 106 6 4.76x102 Xe-133m 9.94x10-4 :, 10 9.94x10 2 Xe-133 3.06x10-4 X 106 3.06x10 2 2
,- Xe-135m 7.11x10-4 X 10 6 7.11x10 Xe-135 1.86x10~ X 10 6 1.86x10 3 1.22x104
{ Xe-137 1.22x10-2 X 106 Xe-138 4.13x10-3 X 106 4.13x10 3 Ar-41 2.69x10-3 X 10 6 2.69x10 3
- fron. Regulatory Guide 1,,109, Table B-1 3
- Li (n.ren./yr per pCi/m )
(
; 4A1 J' i
Table NG-3 * ( AIR DOSE FACTORS NUCIIDE y.- Air
- 106(pCi/uCi) Mi **
Kr-83m 1.93x10-5 X 106 1.93x10 1
~
Kr-85m 1.23x10-3 X 106 1.23x10 3 6 Kr-85 1.72x10-5 X 10 1.72x10 1 Kr-87 6.17x10-5 X 106 6.17x10 3 6 Kr-88 1 52x10-2 X 10 1.52x10 4 Kr-89 1 73x10-2 X 106 1.73x10 4 10 6 Kr-90 1.63x10-2 X 1.63x104 Xe-131m 1.56x10-4 X 100 1.56x10 2 Xe-133m 3.27x10-4 X 106 3.27x10 2 6 Xe-133 3.53x10-4 X 10 3.53x102 i Xe-135m 3.36x10-3 X 106 3.36x10 3 Xe-135 1.92x10 -3 X 10 6 1.92x10 3 Xe-137 1.51x10 -3 X 10 0 1.51x103 Xe-138 9.21x10-3 X 10 6 9.21x10 3 L Ar-41 9.30x10-3 X 106 9.30x10 3 t
- from Regulatory Guide 1.109, Table B-1 L
i ** Mi (tr. rad /yr per pCi/m 3 ) N f
\
b 447 05J l w a
Table NG-4 .- AIP. DOSE FACTORS ( Si = (Li+1.1Mi)
!;UCLIDE Li Mi Si = (Li+1.1Mi)
Kr-83m 1.93x10 1 2.12E03 Kr-85m 1.46x10 3 1.23x10 3 2.81x10 3 Kr-85 1.34x10 1.72x10 1 1,. 36 x10 3 I Kr-87 9.73x10 3 6.17x10 3 1.62x104 I Kr-88 2.37x103 1.52x100 1.91x10 0 Kr-89 1.01x10 0 1.73x100 2.91x100 Kr-90 7.29x103 1.63x100 2.52x10 0 Xe-131m 4.76x10 2 1.56x102 6.48x10 2 l Xe-133m 9.94x10 2 3.27x102 1.35x103 1 Xe-133 3.06x10 2 3.53x102 6.94x102 Xe-1351a 7.11x102 3.36x103 4.41x10 Xe-135 1.86x10 3 1.92x103 3.97x103 Xe-137 1.22x10 0 1.51x10 3 1.39x10 3 Xe-138 4.13x10 3 9.21x10 3 1.43x10 0 Ar-41 2.69x10 3 9 30x10 3 1.29x10 0 m I L
- From Table !;G- 2 (mrad /yr per pCi/m3) 4 Frcm Table I;G- 3
, (mrad /yr per pCi/m )
c** 3 Si (mrem /yr per pCi/m ) L
,q
, I'd )
!,q r; ,
em
i( GASEQUS EFFLUENTS CALCULATION OF PI (INHALATION) { SECTION PI-1
. The Pi parameter contained in the radiciodine and particulates Speci-fication represents the transport pathway of the i th radionuclide, the receptors usage of the pathway tredia, and the dosin:etry of the exposure.
Pathway usage rated and the internal dosimetry are functions of the i receutor's age; however, the youngest age group, the in f ant, , .11
- always receive the maximum dose under the exposure conditions for Speci fi cation 3.11.2.1.
r Pi ( i r.h a l a t i on) = K' (BR)DFAi (arem/yr per pCi/m 3) Unere:
- K' = a constant of conversion, 10 6 pCi/pCi 3
BR = the breathing rate of the infant age group (1400m /yr) { DFAi = the maximum organ ini.alation dose factor for the infant F- [ age group for the ith radionuclide, in mrem /pCi. Taken from Table E-10 of Regulatory Guide 1.109, Resolution of units yields: Pi (inhalation) = 1.4 x 10 9 DFAi [ l r n
~
't(;.)
t s-f I
\,
Pi (inhalation) [ p Pi I;UCLIDE CONSTA!;T DFAi ORGAt! (mrem /yr pe: [( _._ (pCi/pCi) (r.. rem / p Ci) pCi/m 3) { _ _ H-3 1.4E09 4.62E-07 Total body 6.47E02 l Cr-51 9.17E-06 Lune 1.28E04 15-54 7.14E-04 Lung 1.00E06 Fe-59 7.25E-04 Lung 1.02F.06 Co-58 5.55E-04 Luv 7 ,, 7 7.E0 5 i c o - f,0 3.22E-03__ Lung _ _ _ _. 4,_5 ] E 0 E_ Zn - t> 5 4.62E-04 - - - - - Lung 6.47E05 Sr-L9 1.45E-03 Lung 1.03E06 Sr-90 2.92E-02 Bone 4.09E07 b _'4 E- 9 5 __ _ _ _ _ _ _ _ _ _ _1.25E-03___ ._ _ Lung.__ l 75E06 I-131 1.06E-02 Thyroid 1.48E07 I-133 ___ _ _ _____l. 2.54E-03 Thyroid 3.56E06
~
Cs-134 5.02E-04 Liver 7.03E05 [ Cs-136 - 9.61E-05 Liver 1.35E05 Cs-137 4.37E-04 Liver 6 l?E05 u Ea-140 1.14E-03 Lung 1.60E06 Ce-141 3.69E-04 Lun g 5.17E05 g __ P-32 2.03E06 _1 _. 4 5__E__0.-.3 _ . - _B o n e_ _ _ _ _ (
. Fe-55 6.21E-05 Lung 9.25E04 C-14 1.89E-05 Bone 2.65E04
( n p GASEOUS EFFLUENTS a i CALCULATION OF Pi (GROUND PLAT 1E) r' g SECTION PI-2 f The factor Pi (ground plane) teoresents the dose paran:eter contained in the radiciodine and particulates Specification for the ground plane a pathway. This dose factor is based on the critical individual organ P { (skin or total body), and the most restrictive age groups (infant). I Pi = K'K"DFGi (1-e->it)/Ai (m2 mrem /yr per pei/sec) l Where: K' = Constant of unit conversion, 106 pCi/pCi
~
K" = Constant of unit conversion, 8760 hr/yr li = Decay constant for the ith radionuclide sec -1 t = Exposure period, 3.15 x 107 see (- year) Resolution of units yields: I Pi (ground plane) = 8.76E09 DFGi (1 - e-l i t ) j y i I The deposition rate onto the ground plane results in a ground plane
- concentration that is assumed to persist over a year with radiological decay the only operatirg removal rec'aanism for each radienuclide. The
(~ ground plane dose conversion factors for the ith radionuclides, DFGi, I are taken from Regulatory Guide 1.109, Table E-6 F I 4 /J) 055 i i
~
Pi (ground plane) DFGi El
- I;UCL I DE COliSTAI;T I (r: ire m/h r Ai (m2mrea/yr per pCi/n.,) -
(nec~ ) per pCi/sec) g. l 0 11 - 3 8.76E09 0 1.78E-09 Cr-51 2.60E-10 2,89E-07 7 SSE06 Mn-54 6.80E-09 2.57E-08_ 1 2GE10 9,4E-09 1., 8 0 E- 0 7 4.56E08 i _ Je-59_ _ _ _ Co-S' 8.20E-09 1.13E-07 . 6.18E08 Co-60 , 2.00E-08 4.18E-09 5,17E09 Zn-65 4.60E-09 3.29E-08 7.90E08 S r: 8 9___ _ _ _ _ _ _ _ _ _ _ _ . _ _6 50_E-13___ _ 1.58E-07_ ._ _____3,5SF04 _ l Sr-90 not Elven 7.60E-10 0 r-Zr-95 1.22E-07 4.08E08 ( ) _ _5 . 8 0 !:- 0 9 r I 131 . 3.40E -- _ 9.95E 07 _ . ._ - - ___.98E0._7. 2 __ _ 4.50E-09 3,26E-J6 4.26E06 1_133 i Cs -134 1. LDE -0 3 1. 0 7 E - 0 8 3.27E09 Cs-136 ' 1.70E-08 6.17E-07 2.41E08 Cs-137 4.90E-09 7.2SE-10 1. 34 r09..
~
140 2.40E-G9 6.27E-07 3.35E07 l Ce-141 6.20E-10 2.48E-07 2.19E07 I.
' u ; (J I}
P-32 tn 0 5.61E-07 0 ( 8.14E ,, 0 Fe-55 0 Ll _
'_I C-14 0 3.84E-12 0 s
\
y 3 n ! GASEOUS EFFLUEtiTS f
-) CALCULATION OF Pi (FOOD)
I SECTION PI-3 n b ( The factor Pi ( food) represents the dose pararreter contained in the
= radioiodine and particulate Speci fi ca tion for the food pathway.
i The organ with the maximum ingestion dose factor will be the l i r..i t in g e organ, and the in fan t , the limiting age group. i Pi ( fo od) = K'r c. E@i( T)llu)
'i p l Fm DFL i{e-litf (m2 arem/yr per pCi/sec.
Where: l
- K' =
Constant of conversion 1 Qp = The cow's consumption rate, in Kg/d' (wet weight) Uap = The in fant 's milk consumption rate, in liters /yr Yp = The agri cul tural productivity by uni t area, in i o I Eg/m-Fm = The stable element trans fe r coefficients, in days / liter
; r = Fraction of deposited activity retained on cow's feed grass I
DFLi = The maximum organ ingestion dose factor for the
~
ith radionuclide, in m rem /pCi
)i = The decay constant for the ith radionuclide, in soc-1 Aw = The decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10-7 sec -1 (corresponding to a 14 day hal f-time) tf = The transport time from pasture to cow, to milk, r!
l to in f ant , in see -, t; t; c) 0;/
f n F l
\
r-k A fraction of the airborne deposition is captured by the ground plant ~ veretation cover. The ecpture d inat erial is removed from the tegetation b ( g rce, s ) hv both radiological decay and weathering processes, f a Regulatory Guide 1.109 provides the following parat nters : I' 1. QF
=
50Eg/ day (Table E-3) I
? Uap = 330 liters /yr (Table E-5) t 3. Yp =
0.7 Eg/m 2 (Table E-15)
- 4. tr
= 2 days (1.73 x 105 see) (Table E-15)
I
- 5. r =
1.0 for radioindines; r = 0.2 for particulates (Table I-15) 6
- 6. En values - Table E-1 I
- 7. DFLi values - Table E-14 1
1 Re ;olut ion of units yields (all radionuclides except 11 - 3 ) 2.4 x 10 10 rFm e -Ailf 2 j Pi (food) = li+;w DFLi (m m rem /yr per pCi/sec) i Ti.e con cent rat ion o f t ri t iuta in milk is based on its airborne concen-E tration rather than the deposition rate. Fo Pi = K'K" Fm QF Uap DFLi t .75(0.5/II)'_
'n n e r e :
K = Con i, t a n t o f conve rsi on , 10 3 gm/kg 11 = Absolute hur,idi ty o f the atnosphere in gm/Ir.3 ( 0 75 = Fraction of total feed that is water
+
0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water
- ,.o 7., ,
rq
.,o I
p* d F
\
E J. Regulatory Guide 1.109 provides the fo ll owi.ng pa ran.e t e rs :
- 1. Fm = 1.0 x 10-2 day / liter (Table E-1) p 2. DFLi = 3.08 x 10-7 m rem /pCi (Table E-14) i Assuming an average absolute humidity o f 8 grams /m3, the re sol uti on of unit s yields (11- 3 only) r I Pi (food) =
2.4 x 103 m rem /yr per pCi/m 3 r r I t O t i L l s , r ~. a L. L', l} q! GJ I
$I L
. . . s. _ ,
P
- 0:iSTM;T r Fm Ai Aw DFLi tf Pi
, ._ _ = _
Cr-51 2.4E10 0.2 2.2E-03 2.89E-0: 5.73E-0~/4.llE-07 1.73E05 4.78E06 y -54 2,5E-04 2,3]E-0] _ L90E-03 1 07F07 . i Fe-59 1.2E-03 1 80E-0; ,.38E-05 3.99E08 l Co-58 1.0E-03 1.13E-0 S.98E-06 6.17E07
, Co-60 1.0E-03 4.18E-0! 2.57E-05 ,> 2.14E08 3.9E-02 3.29E-Or 6.31E-05 1.94E10 Zn-65_
5 Sr-89 8.0E-04 1.58E-Oi ? 51E-O' 1=28E10 l Sr-90 8.0E-04 _7.60E _ _- l C __ 1.85E-02 _ 1.24 Ell g Zr-95 5.0E-06 1.22E-01 2.50E-05 8.46r.05 I-131 6.0E-03 9.95E-0; 1 39E-02 1.08E+12 1 1-133 6.0E-03 9. 2 6 E-Ot 3.31E-01 9.74E09 Cs-134 1.2E-02 1.07E-0; 7.03E-04 6.92E10 Cs-136 1.2E-02 6.17E-0 1.35E_06 5.SSE09 Cs-137 1.2E-02 7.28E-ll ' 6.11E-04 6.13E10 1 Ea-140 4.0E-0? 6.27E-0 . 1.71E-OL 2.46E08 a Ce-141 1.0E-06 2.4SE-0 2.48E-05 1.39E07
- - + - - - -
s m,__ . , , , %
+-e--+ - - - - e--.-- .
i 9 SE-02 5.61E-0 l.70E-0? 1.63 Ell
. P-39 ! Fe-55 1.2E-03 8.14E 1 1,39E-0: 1.3SE08 g __
3.84E-1/ 2.37E-05 2,38E09 C-14 1.2-02 L
l w l
's GASECUS EFFLUEI;TS p
- SETPOINT DETERMII;ATIONS I
r* $ Setpoint d e t e rn. i n a t i on s are provided in this section for the following P release points: I,
. 1. Reactor Euilding Ventilation Exhaust 2, Reactor Building Refueling Floor Ventilation Exhaust 3, Ra;h a s te Building Vent ila tion E:;haus t l+ . Turbine liuilding Ventilation Exhaust r-l 5. Main Stack Caleclated setpoints represent a safe margin of assurance that the instantaneous gaseous release rates will not produce a dose rate to an individual at or beyond the site boundary equal to or greater than 500 c. rem /yr tot al body, or 3000 mrem /yr skin, based on radioactive noble gases.
l I. Eases: I 6 i To achieve a reasonable level of operational flexibility while n.aintaining a 'afe margin of assurance that instantaneous Enseous
'I- rclease limits are not exceeded, the f ollowin!; calcula ti onal ba ses are c1m forth:
{ A. Limit apportionment i For col servatism 75?; of the dose rate limit will be allowed r with .he following release path apportionn.ent: I
- 1. 157. o f l i mi t applied to Reactor Building Vent Exhaust r
~
(d'u[ \, l(l ir) i
s 1 y . i t
- 2. 15% of limit applied to Reactor Building Refueling Floor Vent Exhaust.
4
- 3. 18.75% of limit applied to Radwaste Building Vent Exhaust
- 4. 18.75% of limit applied to Turbine Building Vent Exhaust i
- 5. 7.5% of limit applied to Main Stack i
i Using these conservative assumptions, simultaneous attainment of I [ all setpoints would actuate alarm / trip conditions at 75% of the allowable instantaneous release rate, not considering any e b other built-in conservatisms. t [_ B. Atmospheric dispersion factors 3
- 1. (X/Q) st ack =
8.07E-08 sec/m
- 2. (x/Q) vent =
6_73E-07 sec/m 3 The chosen atmospheric dispersion factors are the most restric-l6 tive, site boundary, vent and stack X/Q values calculated j using site historical annual average meterological data. C, Gaseous Effluent Component Determination 6 To reflect a conservative and realistic approach in deter-mining isot opic make-up and calculation of appropriate dose factors for application in setpoint determination, a " weighted i average" method is used. Thi s method reflects the contribu-tion of speci fic radionuelides in the effluent stream, and applies the requisite doce factor for that radionuclide in
= ,1 A q r/7 nn/ Juc .
I e
{ F i' , n { weighted manner to the overall effluent stream. To ascartain I a representative sample of effluent stream, 18 uonths of i typical operating data is used, s i l r' II. Calculations (ground level releases) i A. Calculation of weighted average Ki - Average Weighted Total i Body Dose Factor. r= 1. Reported releases for the first half of 1976 and a'l of I - 1977 - noble gases, ground level are used. I Nuclide _ Fraction of Total Ki # Weighted Ki l' Kr-85 0.000 1.61E01 0.00
- Kr-85m 0.023 1.17E03 2.69E01 ! 5.92E03 5.92E00 Kr-87 0.001 1 Kr-88 0.002 1.47E04 2.94E01 )
Xe-133 0.592 2.94E02 1.74E02 I-Xe-135 0.053 1.81E03 9.59E01
- Xe-135m 0.001 3.12E03 3.12E00 ' 8.83E03 0.00 Xe-138 0.000 Xe-133m 0.001 2.51E02 2.15E-01 Xe-131m 0.000 9.15E01 0.00 r ! Ar-41 0.001 8.84E03 8.84E00 0.324 1.66E04
- 5.38E03 f,i den t i fi ed 1 -
Weighted average Ki = 1.14E03 3 I; /; ') 063 Total body dose factor (mrem /yr per pCi/m )
- Unidentified nuclide assumes highest possible Ki (Kr-89) l l
** Nuclides with 0.001 fraction of total or less not included in weighted Ki
6 t a-i B. Reactor Building Vent Exhaust: F 1. Weighted average Ki = 1.,14E03 mrem /yr per pCi/m 3 1
- 2. Monitor calibration factor = 1.32E-02 pCi/sec per CPM (Ki) (X / Q) v(b) iv =
( .15) (500) n. rem /yr) I (l .14E0 3) (6. 7 3E-0 7) (Q) iv = 75 mrem /yr I (Q)iv = 9.78E04 pCi/sec l Setpoint = 9.78E04 pCi [ CPM sec
=
7.52E06 CPM sec 1.3E-02 pCi _ J m - l Assume 207 additional conservatism for instrument error, ete: I % ( 7. 5 2 E06 CPM) (0. 8) = 6.00E06 CPM Setnoint i C. Reactor Euilding Refueling Floor Vent Exhaust: l 1. Weighted average Ki = 1.14E03 mrem /yr per pCi/m 3
- 2. Monitor Calibration Factor = 1.8E-02 pCi/sec per CPM (Ki)(x/Q)v(Q)iv = ( 15)(500) crem/yr)
' 75 mrem /yr (1,. l!.E0 3 ) (6 ,. 7 3E- 0 7 ) (Q) iv =
t (Q)iv = 9.78E04 pCi/see i d [ 4 J amu
I .25-6 I .. _ _ i Setpoint = 9.78E04pCi CPM sec .- 5.43E06 CPM see 1.82E-02pCi L_ _ _ _ i l Assume 20% additional conservatism for instrument error, ete: (5. 4 3E06 CPM) (0. 8) = 4.3E06 CPM Setpoint D. Radwaste Building Vent Fxhaust:
- 1. (!eighted average Ki = 1.14E03 rrem/yr per pCi/m 3 lm
- 2. Monitor calibration Factor =
4.4E-01 pCi/sec per CPM (Ki)(X /Q)v(Q)iv = (.1875)(500 mrem /yr) l ( 1.14 E0 3 ) ( 6 . 7 3 E- 0 7 ) (Q) iv = 93.75 mrem /yr (Q) i.v = 1.22E05 pCi/sec g Setpoint =
- 1. 2 2 E0 51.Ci CPM sec
^
=
2.77E05 CPM sec 4.4E-OloCi Assure 20% additional conservatism for instrument error, ete: I- (2. / 7E0 5 CPM) (0. 8) = 2.2E05 CPM Setpoint L
~
E Turbine Building Vent Exhaust:
- 1. t?eighted average Ki =
1.14E03 mrem /yr per pCi/m 3
- 2. Monitor calibration factor =
4.3E-02 pCi/sec per CPM _ h) i L
p 1 M i - e .s I (Ki) (x /Q) v(Q) iv = (.1875)(500 mrem /yr) F (1.14E0 3) (6. 7 3E-0 7) (Q) iv = 93.75 mrem /yr i . (Q) v = 1.22E05 pCi/sec n
,,, Serpoint =
1.22E05uCi CPM see - 2.84E06 CPM l 4.3E-02 pCi sec n l r Ass ce 20% additional conservatism for instrimient error, ete: I s
, (2.84E06 CPM)(0.8) =
2.2E06 CPM Setpoint i I.
~
F. Cot:: pari son o f Total Body Dose vs Skin Dose: 1, Calculation of weighted average Ni - Average Weighted Skin l Dose Factor _ 2. Reported releases for the fi rs t half of 1976 and all o f 19 7 7 - nobl e gases, ground level are used. M e r e i
/
p } q -{t )
Fi n I (Ki) (x /Q) v(U) :- = (.1875)(500 mrem /yr) f (1.14E03) (6. 7 3 E-0 7) (h) iv = 93.75 mrem /yr i . (Q)iv = 1. 22E05 pCi /s ec as I _ . _ _ a Setpoint = 1.22E05pCi CPM see - 2.84E06 CPM sec 4.3E-02 pCi m I m Assume 20% additional conservatism for instrument erroi ete: I s
, (2.84E06 CPM)(0.8) = 2,2E06 CPM Setpoint l
F Compari son of Total Body Dose vs Skin Dose:
- 1. Calculation of wei.Eh red average Ni - Average Weighted Skin Dose Factor
. 2. Reported releases for the first half of 1976 and all of 1977 - noble gases, ground level are used.
me 1 M l em I i f gg 00 i
_a ..d I!uc l ide Fraction of Total Ilil! Weighted I?i 'l i Kr-85 0.000 1.36E03 0.000 a Kr-85m 0.023 2.81E03 6.46E01 Kr-87 0.001 1.59E04 1.59E01 Kr-88 0.002 1.9'E04 3.82E01 Xe-133 0.592 6.94E02 4.1lE02 "2-135 0.053 3.97E03 2.,30E02 Xe-135m 0.001 4.41E03 4.41E00 Xe-138 0.000 1.43E04 0.000 l
/,e-133m 0.001 1.35E03 1.35E00 Xe-131m 0.000 6.48E02 0.000 Ar-41 0.001 1.29E04 1.29E01
-i de n t i fie d 0.342 2.91E04
- 9.95E03 l
- We ighted Ave rage Ki =
2.13E03 I l
~
!! Skin Doce Factor (n.ren./yr per pCi/in3)
Uni denti fied nuclide assur.es highest nossible I!i (Kr - 89) A* I;uc li de s .;ith 0.001 fraction of total, or less not included in
- weighted fli.
I { 447 OG3 I
m f
\
- 1 1 G. Reactor Building Vent Exhaust:
f 1. Weighted average Ni = 2.13E03 mrem /yr per pCi/m 3 L (Ni)(x/Q)v(Q)iv = (0.15)(3000 inrem/yr) (2.13E0 3) (6. 7 3E-0 7) (Q) iv = 450 mrem /yr (Q)iv = 3.14E05 pCi/sec 1 Total Body More Restrictive .T H. Reactor Building Refueling Floor Vent Exhaust r 3 i a
- 1. Weighted average Ni =
2.13E03 n. rem /yr per pCi/m f (Ni ) ( X / Q) v(Q) iv = (0.15)(3000 mrem /yr) 1 ( 2.13E0 3) (6. 7 3E-0 7) (Q) iv = 450 mrem /yr
- (Q)iv = 3.14E05 pCi/sec *
- Total Body More Restrictive a
I. Fad.uaste Building Vent Exhaust
- 1. Weight ed average Ni = 2 13E03 inrem/yr per p Ci /in3 i-(Ni)(x/Q)v(Q)iv =
(0.1875)(3000 mrem /yr) (2 13E03) (6. 7 3E-0 7) (0)iv = 56 2. 5 n. rem /yr (Q)iv = 3.92E05 pCi/sec *
- Total Body More Restrictive n:yn/
et C'Q uv /
? i 18 \' I J. Turbine Building Vent Exhaust
' 1. Weighted average I!i =
2.13E03 mrem /yr per pCi/m 3 m . (I;i) (x /Q) v(Q) i v = (0.1875)(3000 mrem /yr) (2.13E0 3) (6. 7 3E-0 7) (h) iv = 56 2. 5 mrem /:- (Q)iv = 3.92E05 pCi/sec
=
- Total Body More Restrictive
. III. Calculations (elevated release)
A. Calculation of weighted average Ki - Average Wei ghted Total Body Dose Factor.
= 1. Reported releases for the first half of 1976 and all of 1977 - noble gases, elevated releases are used.
I M r i m L
,1
*)
- s. l r
I r i
x -- , . . ._ __
._-..-n-n-_, .~- .
~
. ? l( r k flucli de Fraction of Total Ki # Weighted Ki \~ Kr-85 0.032 1.61E01 5.15E-01 Kr-85m 0.081 1.17E03 9.48E01 Kr-87 0.035 5.92E03 2.07E02 Kr-88 0.087 1.47E04 1.28E03 Xe-133 0.392 2.94E02 1.15E02 Xe-135 0.302 1.81E03 5.47E02 Xe-135m O.000 3.12E03 0.000 Xe-138 0.012 8.83E03 1.06E02 Xe-133m 0.007 2.51E02 1.76E00 Xe-131m 0.042 9.15E01 3.84E00
/
Ar-41 0.009 8.84E03 7.96E01 p Unidenti fied 0.002 1.66E04
- 3.32E01 i
2.24E02 Weighted Average Ki =
# Total Body Dose Factor (crem/yr per pCi/m 3)
I i
- Uni dent i fi ed nucli de assumes highest possible Ki (Kr-89)
'c * :uclides with 0.000 fraction of total not included in weighted Ki I
B. Main Stack: 3
- 1. Weighted average Ki = . 24E02 mrem /yr per pCi/m l
- 2. Monitor calibration factor =
5.2E-01 pCi/sec per CPS i L m /, /; ) [:71 l L.
s. l I # ( (Ki) (X /Q) s (h)i s = (0.075)(500 mrem /yr) (2. 2 4 E0 2) (8. 0 7E-08) (Q)i s = 37.5 mrem /yr (Q)is = 2.07E06 pCi/sec e Setpoint = 2.07E06uCi CPS see 3.98E06 CPS sec 5.2E-01 pCi
, Assume 204 additional conservation for instrument error, ete:
s e ( 3. C 8 E0 6 CPS) (0. 8) = 3.0E6 CPS Setooint i i C. Comparison of Total Body Dose vs Skin Dose: 1 Calculation of weighted 'verage Ili - Average Weighted Skin r_ Dose Factor 2 Reported releases for first half of 1976 and all of 1977 t noble gases, elevated releases are used. I;uc l i d e Fraction of Total Ili f Weiebted Ili Kr-85 0.032 1.36E03 4.35E01 Er-85m 0.081 2.81E03 2.28E02 Kr-87 0.035 1.59E04 5.56E02 Kr-88 0.087 1.91E04 1.66E03 Xe-133 0.392 6.94E02 2.72E02 f _ 5) 5- 40 072
F L< ,[ Nuclide Fraction of Total Ni # Weighted Ni_ Xe-135 0.302 3.97E03 1.20E03 Xe-135m 0.000 4.41E03 0.000 Xe-138 0.012 1.43E04 1.72E02 Xe-133m 0.007 1.35E03 9.45E00 _ Xe-131m 0.042 6.48E02 2.72E01 Ar-41 0.009 1.29E04 1.16E02 " Jnidentified 0.002 2.91E04 5.82E01
- ** Weighted Average Ni =
3.96E02
# Skin Dose Factor (mrem /yr per pCi/m 3)
- Unidenti fied nuclide assumes highest possible Ni (Kr-89)
~
Y* Nuclides with 0.000 fraction of total are not included in weighted Nt. D. Main Stack 1, Weighted average Ni = 3.96E02 mrem /yr per pCi/m 3 l (Ni) (x /Q) s (Q)is = (0.075)(3000 mrem /yr) I (3.96E02)(8.07E-06)(Q)is = 225 mrem /yr , (Q)is = 7.04E06 pCi/sec
- l '-
L Total Body More Restrictive I L l 449 073 i L t L
m j m ( CALCUIATIO" 0F DOSE 10CFR50 1 10 DINES & PARTICULATES a
. Technical Speci fications limit the dose to an individual from I-radioiodines, radioactive materials in particulate form, and
- ~
radionuclides other than noble gases with half-lives greater 1 than 8. days in gaseous effluents released to unrestricted areas l to the following:
- 1. During any eclendar quarter to 1 7.5 mrem.
- 2. During any calendar year to i 15 mrem.
t 4 Dose is determined as follows: __ l. During any calendar quarter: _ s s s s 3.17 x 10-8 1ERi Wg Qis + usgis + W yQiy + wygiv] 1 7. 5 mrem 2 During any calendar year: 4
- m m s s _ , 3.17 x 10-8 E R i W g Qis + w g qis + W yQiv + w ygiv i 15 mrem L
1 i 1.~n e r e :
- l. ~
=
Q. 1 The releases of radionuclides, radioactive materials
, in particulate form, and radionuclides other than noble gases in gaseous effluents, i, for long term l
~
M' }. / 0/i w
P I, P 1
's M
l releases greater than 500 hrs /yr, in pCi. Releases shall be cumulative over the calendar quarter or f year as appropriate. 3 I q.1 = The releases of radionuclides, radioactive materials
=
in particulate form and radionuclides other than .. noble gases in gaseous effluents, i, for short term releases equal to or less than 500 hrs /yr, in pCi. Releases shall be cumulative over the calendar l quarter or year as appropriate. W = The dispersion parameter for estimaring the dose to an individual at the controlling location for { long term releases (greater than 500 hrs /yr) 3
%= (i7Q) for the inhalation pathway in sec/m .
l
- W= (D7Q) for the food and ground plane pathways ,- . -2 in meters .
( w = The dispersion parameter for estimating the dose to an individual at the controlling location for short
-- term releases (equal to or less than 500 hrs /yr)-
i 3 w= (i/q) for the inhalation pathway in sec/m I w= (D/q) for the food and ground plane pathway in
-2 meters .
r 447 01'5 1
__ m_ _, ,, w - , . ,m-1 ( r 5 3.17 x 10-8 = The inverse of the number of seconds in a year. f R.1 = The dose factor for each identified radionuclide> i, in m 2 (crem/yr) per pCi/sec or mrem /yr per - pCi/m 3 Dose shall be calculated using the following formula: I ,_ m m N N . 4 Dose 3.17E-08 E R W3 Qis + W s 4is + E v 9i v + u s is; + U sO is - = i 1 G C / V. % G C M i~ % _ R.1 + R.1 +R. + R-1 + w Sq1s- ,R.1 + R-1 + R.1 + R. + WV 0'lv
, 1 3 lj s
1 G C M V % - G C M V _,
+R}+wq +R
+ R
[E t i- Ri +Ri i y jy R + R i Li i i_ I t Where: l
- 1. all W and w factors in the first argument are the
! appropriate (y, / Q) values. L,
- 2. all W ind w factors in the 2nd, 3rd, 4th, and 5th terms t
,j of the equation are appropriate (D/Q) values. ll L
\
. 9 n 'j Olb
f i e [ _ __ Ri Factors In fan t Child Infant Child Child Child felide Rf [x /Q] Rf [x/Q) . Ri G(D/Q] RE[D/Q) Ef[D/Ol ((D/Q] D /C[
"r-51 1.28E04 1.70E04 5.52E06 4.71E06 5.41E06 4.67E05 6.23E0 j
tn-54 1.00E06 1.58E04 1.62F09 3.90E07 2.10E07 8.02E05 6.65EO l e-59 1.02E06 1.27E06 3.20E08 3.92E08 2.03E08 6.34E08 6.69E0 Co-58 7.77E05 1.llE06 4.45E08 6.06E07 7.08E07 9.59E07 3.76E0 ma-60 4.51E06 ' 07E06
. 2.53E10 2.10E08 2.39E08 3.84E08 1.71E0
'a-65. 6.47E07 9.95E05 8.57E08 1.91E10 1 10E10 1.00E09 2.16EO Sr-89 2.03E06 2.16E06 2.52E04 1.26E10 6.63E09 4.83E08 3.61L1 a-r-90 4.09E07 1.01E08 - - --
1.22E11 1,12E11 1.04E10 1.24El g 2r-95 1.75E06 2.23E06 2.92E08 8.3]E05 8.84E05 6.18E08 9.02E0 b-131 1.48E07 1.62E07 2.10E07 1.06E12 4.35E11 5.55E10 4.77El
'33 3.56E06 3.85E06 2.98E06 9.60E09 3.95E09 1.30E02 8.20E0 Cs-134 7.03E05 1.01E06 7.97E09 6.8]E10 3.72E10 1.51E09 2.63El
<!-136 1 35E05 1.71E05 1.69E08 5.77E09 2.76E09 4.38E07 2.22E0 C,-137 6.12E05 9 . 0 ~/ E 0 5 1.20E10 6.03E10 3.23E10 1.33E09 2.39El i nu-140 1.60E06 1,74E06 2.35E07 2.41E08 1.17E08 4.39E07 2.77EO ( -141 5.17E05 5.44E05 1.53E07 1 37E07 1.36E07 1.38E07 4.06LU e H-3 6.47E02 1.12E03 0 2.38E03 3.51E02 2.34E02 4. 01 E0 : L-32 2.03E06 2.60E06 0 1.61E11 7.79E10 7.43E09 3.38E0 1-55 8.69E04 1.llE05 0 1.35E08 1.12E08 4.58E08 8.01E0 C-14 2.65E04 3.59E04 0 2.34E09 1.20E09 3.84E08 8.89E0 L
-- L - - - - - - - -__ -- . , _ ---, --
=
*f
~
t u
1,-..,--..3,, . _ - ,
-. -- _ m -,,x-_e.~ 7.- ,_ _
., _ .7 I
- G C M ~V
. Ri + Ri + Ri + Ri 6
( i
. Nuclide _ . __ _ C h i l d __ _ . Infant i . Cr-51 1.76E07 1.02E07 i Mn-54 2.31E09 1.66E09 I Fe-59 1.83E09 7.12E08 a
Co-58 9.88E08 5.06E08 [ Co-60 2.76E10 2.55E10 Zn-65 1.50E10 2.00E10 Sr-89 4.32E10 1.26E10
- Sr-90 1,. 3 6 E 12 1.22E11 u
Zr-95 1.81E09 2.93E08 )u I-131 5.38El1 1.06E12 i I-133 4.77E09 9.60E09 i
~
Cs-134 7.30E10 7.61E10 C.-136 3.19E09 5.94E09 Cc-137 6.95E10 7.23E10 EU-140 4.61E08 2.65E08 Cc-141 4.49E08 2 . ') 0 E0 7
'~
H-3 4.60E03 2.38E03 P-32 8.87E10 1.61 Ell
, Fe-b 1.37E09 1 35EO8 L C-14 2.47E09 2.34E09 M
f R [ .r' At .)
^ Ulj t
m Y I
.A
.r ~- , a :_-_ a q -
-c m - ~ ~~~. _
-,y ~ ~ ,
i L - t I
"(' CALCULATION OF R.[X/Q 1e -
l IMHALATION PATHWAY FACTOR f R K' (BR)a(DFAi)a (mrem /yr per pCi/m {X/0] = L Where: 6 j K' = constant of unit conversion, 10 pCi/pci (BR) a = breathing rate of the receptor of age group (a) in m 3/yr. (DFAi)a = The maximum organ inhalation dose factor for the receptor of age group (a) for the ith radionuclide, in mrer./pCi. The total body is considered as an organ in the selection of (DFAi)a. Only the infant and the child R factors are calculated for the purpose of this manual, since they are the most restrictive age
== groups, P , Breathing Rates:
Infant = 1400 (m 3lyr)
- e Child = 3700 (m 3/yr) *
'
- From Table E-5 of Regulatory Guide 1.109 l
6 40 i c3 i b
s 1 I ' Ri Infant . 's b I
+
n (pCi/pCi) (m3 /yr) mrem /Pci I g Radionuelide _. K' BR DFAi Organ Ri treg/E per pCi/m 3 Cr-51 10 6 1.4E03 9.17E-06 Lung 1.28E04 3 1 Mn-54 7.14E-04 Lung 1.00E06 7 Fe-59 7.25E-04 Lung 1.02E06 A Co-58 5.55E-04 Lung 7.77E05 re 1 h Co-60 3.22E-03 Lung 4.51E06
, Zn-65 4.62E-04 Lung 6,47E07 Sr-89 1.45E-03 Lung 2.03E06 Sr-90 2.92E-02 Bone 4.09E07 I
t Zr-95 1.,25E-03 Lung 1.75E06
.m I-131 1.06E-02 Phyroid 1.48E07
{ n I-133 2.54E-03 Thyroid 3.56E06 Cs-134 5.02E-04 Liver 7.03E05 Cs-136 9.6]E-05 Liver 1.35E05 4.37E-04 Liver 6.,12E05 Cs-137 Ea-140
.14E-03 Lung 1.60E06
. Ce-141 3 . 6 9 E - 0 !< Lung 5.17E05 l
;;_3 4.62E-07 Body 6.47E02
~
P-32 1.45E-03 Bone 2.03E06 Fe-55 6.21E-05 Lung 8.69E04 C-14 1.89E-05 Bone 2.65E04 l s k From Table E-10, Regulatory Guide 1.109 l l l g 4' < v G () F
1'3 I Ri Child 3
\ +
n (pCi/pC1) (m 3 /yr) mrem /Pci I l Radionuclide K' BR DFAi Organ Ri mrem /yr per UCi/m 6 Cr-51 10 3.7E03 4.59E-06 Lung 1., 70 E 04 l Mn-54 4.26E-04 Lung 1.58E06 P Fe-59 3.43E-04 Lung 1,27E06 1 Co-58 2.99E-04 Lung 1.1lE06 A l Co-60 1.91E-03 Lung 7.07E06 p Zn-65 2.69E-04 Lung 9.95E05 Sr-89 5.83E-04 Lung 2.16E06 " Sr-90 2.73E-02 Bone 1.01E08 1 Zr-95 6.03E-04 Lung 2.23E06 n l I-131 4.39E-03 shyroid 1.62E07 n 1-133 1.04E-03 rhyroid 3.85E06 I Cs-134 2.74E-04 Liver 1.01E06 ," Cc-136 4.62E-05 Li 'z e r 1.71E05 1 Co-13/ 2.45E-04 Bone 9.07E05 m
. Ea-140 4.71E-04 Lung 1.74E06
== Ce-141 1.47E-04 Lung 5.44E05 H-3 3.04E-07 Eody 1.12E03 P-32 7.04E-04 Bone 2.60E06 Fe-55 3.00E-05 Lung 1,,1 LEOS su C-14 y 9.70E-06 Bone 3.59E04
.j
- From Table E-9, Regulatory Guide 1.109 . ,, c ,
g 3 ,. . uvl
3 ( CALCUIATION OF R G(D/Q) i r1 GROU"D PLANE PATllHAY FACTOR A l - n 2 G[D/Q] Ri = K'K (SF) DFG 1 (1-e -\ )/Ai (m - mrem /yr per l pCi/sec) n Where: n ! K' = A constant of conversion, 10 6 pCi/pCi n K = A constant of conversion, 8760 hr/yr G -1 Ai = Decay constant for the ith radionuclide, sec " t = The exposure t i r.e , 4.73 x 10 8 sec (15 years) G DFGi = The ground plane dose conversion factor for the ith 9 radionuclide (mrem /hr per pCi/m") n SF = Shielding factor (dimensicaless) a 5 se at M f i 4 4 ") 002 I
4 1 G 13 Ri i (pCi/pCi hbr/yr * ** (sec) (sec-1) G 1 Duclide K' K SF DFGi t li Ri k Cr-51 106 8.76E03 7.0E-01 2.6E-10 4.73E08 '!.89E-07 5.52E06 Mn-54 6.8E-09 !.57E-08 1.62E09 1 Fe-59 9.4E-09 l,,80E-07 3.20E08 g Co-58 8.2E-09 1.13E-07 4.45E08 Co-60 2.00E-08 '+,.18E-09 2.53E10 3 . 2n-65 4.6E-09 '3.29E-08' 8.57EOS
' Sr-89 6.5E-13 1.58E-07 2,3 2J 0; /3 3r-90 not given 7.60E-10 0 Zr-95 5.8E-09 1.22E-07 2.92E08 I-131 3.4E-09 3.95E-07 2.10E07 , I-133 4.5E-09 1.26E-06 2.98E06 Cs-134 1.4E-08 t.07E-08 7.97E09 m
Cs-136 1.7E-08 ) 17E-07 1.69E08
= Cs-137 4.9E-09 /,28E-10 1.,20E10 Ea-140 2 4E-09 ).27E-07 2.35E07 Ce-141 6.2E-10 ' 48E-07
. 1.53E07 li- 3 0 1.78E-09 0 P-32 0 2.61E-07 0
'Fe-55 0 3 3+E-09 0 C-14 0 1.84E-12 0
-
- From Table E-15 Regulatory Guide 1 109 6 ** From Table E-6 Regulatory Guide 1.109 y g , f f; r; , _,
r oa
c CALCULATION OF Ri Q)/Q} I - Grass - Cow - Milk Pathway Factor
- -Aith -Aitf
{f.o_fs 4 (1-fp_fs)e 2 R. 1 ;D/Q = K' QF_(7Uap_) Fm(r) (DFLi ) a _ e
.A i+Aw _I,p yg L.
u h"n e r e : 6 K' = Constant of conversion, 10 pCi/pCi QF
=
Cow's consumption rate, in Eg/ day (wet weight) Uap = Receptor's milk consumption rate for age (a), in 3 - )iters/yr 1 Y p
=
Agricultural productivity by unit area of stored feed, o in Kg/m' Yg = The agricultural productivity by unit area of stored
= - o teed, in Eg/m" l Em = St able eleirent transfer coefficients, in days / liter y = Fraction of deposited activity retained on c o .. ' s feed grass.
(DFLi ) a = The maximum organ ingestion dose factor for the ith i r e. di onuc l i d e f >r the receptor in age group (a) in mrem /oCi
-1
'i
= Decay cons' ant for the ith radionuclide, in sec l
Aw = Decay constant for removat of activity on leaf and
-7 cec -1 .I plant sur face, by weathering, 5,73 X 10 4
9 fa %~ (corresponding to a 14 day half-life) 9- , L I 0%d
tr = The transport t itre from pasture, to cow, to milk, ( to receptor in sec. th = The transporm tine from pasture, to harvest, to cou, F to milk, to receptor, in sec .4 ' f p
=
Fraction of the year that the cow is on pasture, a f 3
=
Fraction of the cow feed that is pasture grass while the cow is on pasture O i . I "i i 11 449 005 U D M i f' l-
4 _45 II , Pr.rameters are taken from the following sources:
, (
lb Para::mten Value Table (R.G. 1.109) d
!n r ( d i n.e n s i onl e s s ) 1.0 for radiciodine E-15 t
0.2 for particulates E-15 i F (days / liter) Each stable e l e:re n t E-1 tJ U. a p (liters /yr) - infant 330 E-5
- child 330 E-5
- teen 400 E-5
- adult 310 E-5 II (DFL.) (mrem /pCi) Each radionuclide E-ll to E-14
;; I a 9
Y p(kg/m") 0.7 E-15 9 Y (k g /m') 2.0 E-15 s f tg (seconds) 1.73 X 105 (2 days) E-15 m t (seconds) 7.78 X 106 (90 days) E-15 h n E-3 Qg (kg/ day) 50 f *
,. s f3 and fp are assumed to be unity P
t C { Only the Ri values for the infant and the child are for the purpose
,. of this manual as they are the most restrictive agengroups. r ,. '
,l
}/ dOU.
J
i i I ( The concentration of tri tium in milk is based on the airborne con-t C centration rather than the deposition. Therefore, the R. is based on 1 ,
, x/Q c 3
{ R, h:/Q) = K'h' "F Q U (DFL ) 0 . 7 5 ( 0 . 5 / 11 ) (mrem /yr per pCi/m ) m F ap 1 a Mlere: K'" = a constant of unit conversion, 10 gn:/k g
'. ) . H =
absolute humidity of the atmosphere, in gm/m 3 . 0.75 = the fraction of total feed that is water. O.5 = the ratio of t he specific activity of the feed grass titer to the atu.ospheric water. il a
, and other parameters and values are given above. The value of H may 1
be considered as 8 grams /n.eter 3 , in lieu of site speci fic in forma tion. H 9 4
, t> 4 ') 007 t
'l J
_ gg _- , C Ri (D/(l Grarr,-Cow-Milk Pathway Factor (infant) I ! I l l 'c, ler C cl. F' Or[JanlYn. Ys I rm -
' nrLi Ornan l Ad i Iw rf I th Ri l l I >
l , l 2. 2E-0 3f 0. 2 4.11E-07
-51 10 6 50 330'O.7 2.0 t GI-LLI 2.89E-7 5.73E-7 1,73E5 7.78E6 1 I 1 4.71E06 l l i
,-54 2. 5E-04 0. 2 ' l . 9 9E-05 Liver l 2.5 7E-8 l 3.90E07 I l !
-59 1.2E-03 0.2: 5.3SE-05 Liver I i 3.92E08 l1.8E-7 l
,-58 !1.0E-03 0.2lS.98E-06' Body I 1.13E-7 I 6.06E07
' 1 o-60 1.0E-03'O.2 2.57E-05 CI-LLI t4.18E-9 2.10E08 i
! l : l l 7-65 ,3.9E-02:0.2 6.31E-05 Liver !3.29E-S ! 1.91E10 l i 1 !
i l l r-89 '8.0E-0410.21 2.51E-03 Bon 1.58E-7' l 1.26E10 j 1 I i i l ! j . I 1.22 Ell r-90 j I l8.0E-04!0.2l1.85E-0qBon '7.6E-10 l l
! i I f -95: ! 5.0E-06 0.2 2.50E-05 GI-LLI 1.22E-7 ,
j 8.31E05 l l i -131 '6.0E-03 1. 0 lj 1.39E-02 Thyroid 9.95E-7 I '! 1.06E12 i l l -133 1.0 I 3.31E-03 Thyroid 9.26E-6 i l 9.60E09 l6.0E-03 !
-134 c*
l1.2E-02l0.2 7.03E-04 Liver 1.07E-8 6.81E10 l ! l ; l 5.77E09
-136';
l
] l1.2E-02 0.2 1.35E-04 Liver
,6.17E-7 l
l l l l
-137 ll.2E-02l1 0.2. 6.llE-04' Liver ;7.28E-10 l 6.03E10 -140 lO l' l I l6.27E-7 2.41E08 l c3 l 4. 0E-04 l0. 2 ' l . 71E-04 Bone l l -141 l 1. 0E-C 4 l0. 2 ; 2. 48E-0] GI-LLI '2.48E-7 1.37E07 i j i e 3 'l.0E-02 0.2' 3.08E-07 Body 1.78E-9 2.38E03 I I l i ,
- 2 2.5E-02 .2l1.70E-03 Bone 5.61E-7 1.61 Ell l
-55 j 1.2E-03 0.2.l.,39E-05 Bone 8.14E-9 , l.-35E08 1.2E-020.2!2.37E-0$ Bone 3.84E-lg 2.34E09 14
! ! j ,
i i I t
w c _ ._ : 3
,
- 2 3. -- -t
~ *
, __ y~ - ~l
~ . -
C Ri [b/07 Grass-Cce-Min Pathway Factor (child)
$ l Nucl. K' Or Uno !Yp Ye '
r- - 1 Di7.i
! I l ! l I C Orrar i li I Aw i tf i th 4l ee l 1 Ri Cr-51 106 50 330 0.7 2.0 2.2E-03 0.2 4.72E-7 I '
GI-LLI 2.89E-7 5.73E-7 1.73E5 7 78E6 1 1 5. 41E0 l- i Mn-54 t > l l 2. 5E-04 0. 2 i 1. 0 7E-5 , Liver i2.57E-8 2.10E0 i ! ! t l Fe-59 I l1.2E-03,0.2 2.78E-5 'GI-LLI l1.8E-7 i l + i , . l 2.03E0 Co-58 , j 1.0E-03 0. 2 ' l . 05E-5 ' GI-LLI l
! I 1 .13E-7 7.08E0 i ,
I Co-60 l l 1. 0E-0 3 l0. 2 > 2. 9 3E-5 GI-LLI ! , l 2.39E0 Zn-65 i l4.18E-9 ' l
!3.9E-02lO.2 3.65E-5
! Liver .3.29E-8' !
1.10El i i t Sr-89 i S.0E-04 l0.2 ; 1.32E-3 l l Bone 1.58E-7' ' 6.63EO. l. Sr-90 '8.0E-04 0. 2 ' 1,,70E-2 ; Bone ' 7.6E-10 l l 1.12El' Zr-95
- 5. 0E-06 0. 2 i 2. 66E-5 , GI-LLI 1.22E_7 l 8.84E0 I-131 i l i
, 6.0E-03 fl.0 ; 5.72E-3 , Thyroid l 9,95E-7 l e i '
4.35El i i 1-133 ! l 6. 0E-03 1. 0 l 1. 36E-3 I Thyroid 9.26E-6 1
- j. 3.95E0.
Cs-134 1.2E-02:0.2 3.84E-4 Liver l i1.07E-8 3.72El l l 2s-136' I 1. 2E-02 l0. 2 , 6. 46E-5 ! Liver 6 ,,17 E- 7 l a i i i l 2.76E09
- l Cs-137 > 1. 2E-02 'O . 2 i l 3. 27E-4 , Bone i l
a : 3.23E10 t 7 . 2 S E- 10l ia-140' 4. 0E-O s b.2 8.31E-5l Bone 6.27E-7l 1.17E08 ca ! .e-141 c> e 1. 0E-04 l0. 2 l 2. 47E-5 l2.48E-7 GI-LLI 1.36E07 d-3 1.0E-02 O'.2 2.03E-7 iBody 1.78E-9 I l l 3.52E02
-32 2.5E-02 0.2 l 8.25E-4 ! Bone 1 l 5.61E-7f !
7.79E10 e-55 1. 2E-03 0. 2 jl 1.15 E-5Bone i 8.14E-9l 1.12E08
- -14 1.2E-02 0.2 1.21E-5 Bone 3.84E-12 1.20E09
- l. i
i M g CALCUIATIO:; OF R. LD/ 1 w GRASS - COW - MEAT PATilk%Y FACTOR 9.
*- , -Aith R7
= K' Qp _ (Main fF (r)(DFLi)a IP fE + -{ l - fPf1d e G-Ailf 1
- D/Q]
i1 l Ai+Aw Y p Yg Fi in units of (m 2 n. rem /yr per pCi/sec) Where: 6: Fr = Stable eletr.ent transfer coe f fi cients , in days /kg. i Uap - The receptor's meat consu::.ption rate for age (a), in kg/yr. tg
=
Tran'> port t i tre from nasture to receptor, in sec. [ th = The transport t i n.e from crop field to receptor, in sec. s l-and all other t e r: m are defined in the calculation of Grass - Cow - Milk Pat hway I' actor section of this manual.
*1 l I 4 [i 9 00 d
l-
i I' Paraneter Value Table (R.G. 1.109) r (d in:en s i onl e s s ) 1.0 for radioindine E-15 0.2 for particulates E-15 Fg (day s /k g) Each stable e l etre n t E-1 Uap (kg/yr) - infant 0 E-5
- child 41 E-5
- teen 65 E-5
- adult 110 E-5 L.
(DFL.)a (n.r e m/ p C i) Each radionuclide E-ll to E-14 1 Y (k g / n.9" ) 0.7 E-15 P 3 (k g/n o) ' 2.0 E-15 l tg (seconds) 1.73 X 10 6 (20 days) E-15 6 t h (i;e c nds) 7.78 X 10 (90 days) E-15 Qp (k g / day) 50 E-3 o The conce nt rati on of tr i tium in n eat is based on its airborne concen-M tration rather than the deposition. Therefore, the R i is based on x/Q
?A M - -
3 R. 1 x/Q = K'K' "F rQyU(lP (DFL.)0 1 - 0.75(0.5/H) (ntrem/yr per UCi/m I i-where all terms are defined above and in the Calculation of Grass - Cow - 4 Milk Pathway Factor section of this manual. Since the infant's c on s un:p-tion rate for this prthway is zero, the child becomes the limi ting at;e group and R values are tabulated for this group. kh) U<
, .- .- .- 1 -3
- L
~ .
= : -, o . n= u ~, i nq (r ., ; ,, n i
i i , , . I 1 I
) V
- ucl.I K' ! Or Man Ys ' Yn Dri , n- - ! .- rc l + -c ce c W l 1 1 1 1
;r-51 106 50 41 2.0 {0.7 2.39E-07l.2 4.72E-07 G1 u 3 / ;t.-07
- 2. 4E-0 3 l 7. 7 8E06 1.73E06l1 1 5.67E05
, i ,
Mn-54' l 1 l2.57E-08j 2 1.07E-05 Liver l 8.0E-04 lS.02E06 l l i i l 2 e-59' 1.8E-07 .2 ,'! 6.34E08
, 2.78E-05 GI-LLI '4.0E-02 '
i l i l i l
;o-58l l-i1.13E-07 .2 1.05E-05 G1-LLI il.3E-02 l ,
i i 1 4 I 9,59E07 i i I i l 8 j l 10-60l i
; 4.18E- Oc' '
' C3E-05 GI-LLI i 1.3E-02l l l I
3.84E08 2n-65 , 3.20E-08 .2 3.65E-05 Liver 3.CE-02 , 1.00E09 I i , i i : i ! l 6. 0E-04 4 Tr-89 l , l 1.58E-07j .2 1.32E-03 none , t , 4.83E08 i i i i i I i 1 - - 1 r-90I I l ./.00E-10. 2 1.10E-02' gonc ! l6.OE-04 l l 1.04E10 t ! , i i I Zr 95 i j I l
'1.22E-07i.2 '
- 2. 66E-Od GI-LLI i '
'3.4E-02i I 6.18E08 i
l t : I . l -131 I l l l l '9.05E-07,! 1 5.72E-02 T'rvroidi l 2. 9E-03 l -l l l ,5.55E10 l ! i i : I t , -133 I i
. ! !O,26E-06! 1 1.36E-03 Thvroic' ,
l2.9E-03l l l l, 1.30E02 i ' i ' . j l l i s-134 { ' I l1.07E-081' .2 3.84E-04 Liver l
,4.0E-03l l 1.51E09 l I -
l l c-136 l l l: !6.17E-07l.2 6.46E-0$ Liver i t l 4.0E-03 l 4.38E07
, i l
s-137 ;? I
,7.28E-10, .2 3.27E-OL' Bone I
4.0E-03 l i 1.33E09 {a t l i 4.39E07
- -140 .
I 6.27E-07l.2 8.31E-05, Bone j 3.2E-03 ! I i i i l
-141 t .
ca I
!4Sr-07f.2
. 2.47E-05 GI-LLI !
i f 1.2E-03 ; i l 1.38E07 i, i ,
, I N 2.03E-07; Bocy d-3 I 1.78E-09 .2 ! 1.2E-02 '
! 2.34E02 i r ,
i l ! { ' 32 t l l5.61E-07l.2 8.25E-OlqBone l 4.6E-02 , j 7.43E09 l 1 i l Bone l e-55 ' i 8.14E-09l . 2 ' 1.15E-05. 4.0E-02 !' I
- j4.58E08 i I t .
6 1 l l 3.84E12 i t , l.21E-05i Bone j is, tr.-0o i
,i 3.84E08 -14 i t
i l , l 1 I i i , i ! ! i i .
*1 V
( CALCULATIOIl OF Ri {D/Q_ ,, \t VEGETATIOIl PATilWAY FACTOR
~
y L -AitL s -Aith R1 [D/Q_
= K' ( r)._
_ (DFLt )a U fe L + Ua f L'e
'3 , __Y __( A i a d)_
y
~
?
=
(m- n. rem /yr per pCi/sec) Where: a K' = constant of conversion, 10 pCi/pCi Ub = consun.ption rate of fresh leafy vegetation by the recept or in age group (a), in Kg/yr. (\ f,i
=
fraction of annual intake of fresh leafy vegeta-tion grown locally. f ., = the fraction of the annual intake of stored vege-t tation grown locally. t 7,
=
the average time between harvest of leafy vege-m tation and its consumption, in seconds. th = the average t in e be t t;een hars es t of stored vege-n i tation and its c onstap t i on , in seconds. o Yy = the vegetation area density, in kg/m~. all other factors are de fined in the Cal culati on o f Gras s-Cow-Mi lk { Pathway Factor section o f this manual . 1 7
. G
.l.i) r,J d/
{,.
i Parameter Value Table (R.G. 1.10! r (d.mensionless) 1.0 for radiciodines E-1 0.2 for particulates s (DFLt )a (mrem /pCi) Eoch radionuclide E-11 to E-14 U (kg/yr) - i n f ant 0 E-5 a child 26 E-5 teen 42 E-5 adult 64 E-5 S U (kg/yr) - infant 0 E-5
. 3 child 520 E-5 teen 630 E-5 adult 520 E-5 f site specific (default =
1.0) L (dimensionless) f, (dimensionless) site specific (default = 0.76) (see Ref. 6, p g . 2 8 ', LL (seconds) 8.6 X 10 0 (1 day) E-15
. t pec ads) 5.18 X 10 6 (60 days) E-15 h
9 Y, ( k g / m'- ) 2.0 E-15 1he concentratien of tritium in vegetation is based on the airborne V concentration rather than the deposition. The re fo re , the R. is based ! l i . on X/Q V L 3 R. x/Q = K'K'" U f +U f (mrem /yr
- 1 aL ag (DFL.)a i {0.75(0.5/H)}
3 per pCi/m ). t'-, i
i where all terms have been defined above and in the grass-cow-milk Pathway Calculation section of this manual. Since the infant consumption rate is zero, only the child R values i are calculated. f m Wune I A/Q n / U!
,.35 a
=
i
' ass ene
_y_ _,
.,V
[~D / 0l Is l l V i T l { l l
- cl . ; K' IC ua ' Yv l h DFL, ai l c1 cc i tT tk Ri l
6
-51 10 : 26 520' 2.0 ;5.73E-07l0.2 4.27E-07'2.89E-07 1.0 0.76 8.6E4 5.18E6 , 6.23E06 l
j ! l ! i
-54 l0.2;1.07E-05.2.57E-08 l I 6.65E08 i I j
-59 l l0.2!2.78E-05l1.SE-07l 6.69E08 l
; ! i
-58 i
0.2;1.05E-05:1.13E-07l 3.76E08 ,-60l . 10.2;2.93E-05 4.18E-09! 1.71E09 l l i j ! ' l
-65 i! i !
l 'O.2;3.65E-05!3.29E-08 I t i 2.16E09
- , I
-89 l ! f I, 0.2!1.32E-03 1.58E-07 ' ! 3.61E10 I ! ! l l l 1 0. 2 i 1. 7 0E-0 2 ; 7. 6 E- 10 I -90 ! i i
I j j 1.24E12 -
! I j l l i
-95 l
! 9.02E08 l
l
! l
! l0. 2 l 2. 6 6E-0 5 ! 1,. 2 ! 2E-0 7, l 1 131 l 'l.0'5.725-03 9.95E-07!
1 i i
! , 4.77E10 i
l , i l i l 1 I . l j l 133 l l l1. 0 ; 1. 36E-0 3 ' 9. 2E-06 i l
, l' 8.20E08 i ! l ! l l -134 l l ,0.2!3.84E-04 1.07E-08!
i i
!2.63E10 I i i i
-136i ! *- O.2 6.46E-05!6.17E-07! ! !2.22E08 l > j t
! l s-137 G 1 0.2'3.27E-04!7.28E-10' l 2.39E10 l
I l !
-140 lO 0.2!8.3d-05j6.27E-07j 2.77E08 l4
!so !
t
-141 ! I os 0.2!2.47F-05,2.48E-07 6.06E08 I l j l l l- 3 .
'O . 2 ! 2. 03E-07 ; 1. 78E-09; 4.01E03 i
1 l
-32 l 3.38E09 e-55 i
l0.2!8.25E-04!5.61E-07 i
'O.2.1.15E-05 8.14E-09 l l 8 -14 'I 0.2 ! 1.21E-05 3.84E-12, l '
f.01E08 8.89E08 l i I i 1
' l l I ! i i I, .
i IMPLEMEI;TATIO:; OF 10CFR50 ( AIR 130RI;E RELEASES
!;0BLE GASES Techn cal Speci fications rtate:
- a. "The air dc>se in unrestricted areas due to noble gases released in gaseous ef fluents shall be limited to the f ol l owing :
- 1. During any calendar quarter, to <_ 5 mrad for gamma radiation and S 10 mrad for beta radiation.
- 2. During any calendar year < 10 mrad for ganana radiation and < 20 mrad for beta radiation.
I Ti' i s spe ci ficat i on shall be in:plemented using the following Ielationships: I
- a. During any calendar quarter, for gamma radiation:
I 3.17 x 30-8 ? {M.1 - (x/Q) 1, Qiy + (x/q)yqiy + (x/Q)gQ g + (y /q) sqi s i }' 5:Iad 5. a
; During any calendat quarter, fer beta ra d i a t i o--
3.17 x 10-8 " { t; -(x/Q),,qiy + (3/q)yqiy a l , (x/Q)g Qs+ i (X/9)isy s _
} i 10n m 3
'I* y L 4/17 0 9 ~/ I
4 __( b.
~~
During any calendar year for ga:: ara radiation: s s 1 s 3.17 x 10-8 1{M.' 1-(x/Q)yQiy 4 (x/q)mqiy 0 (x/Q)cQ ; b. + ( y / q ) ,>q i s }<- 10 mrad
- o . -
. 1
_J l
~
During any calendar year for beta radiation: s s s
, 3.17 x 10-8 l!N (?/Q)y]iv+ (X/4)v4iv + (X /Q) sQis + (X/4)34is } 1 20 n. rad d
1
! (i/Q) y
_6 . 7. 3 E - 0. _7 nec/n For vent releases. The highest calcul at ed atmual average relative concentration f f for area at or beyond the unrestricted area boundary for long terra releases (greater than 500 brs/ year). 1 (i/ii)y 4.20E-06 sec/m 3 For vent releases. The relatise
- ceneentration for areas at or beyond the unrestricted area boundary for short terra releases (equal to oc less than 500 hrs / year)
( .7Q) a
=
8.07E-08 sec/m 3 For free-standing stack releases. The highest calculated annual average relative con-
~
cent ra t i on f3r areas at or beyond the unrestrict ed I 1' 2 area boundary for long term releases (greater than f 500 brs/ year) ,, u9 0 y, c,8 1 i it
1 '( (i7ii) g = 2.00E-08 sec/m3 For free-standing stack releases. The relative concentration for areas at or beyond the unrestricted area boundary for short term releases (less than or equal to 500 hrs /yr).
; M1 =
The air dose factor due to gamma emi s s i on for each identi fied noble gas radionuclide in mrad /yr per pCi/m
!:1
=
The air dose factor due to beta emissions for each i dentified noble gas radionuclide, in mrad /yr per pCi/m3 qis
= The average release of noble gas ra d i onu c l i. d e s in gaseous I
l e f fluents , i, for short term releases (equal to or less than 500 brs/ year) from the free-standing stack, in pCi. Releases shril be cumulative ove r the calendar l quarter or year as appropriate. n. giy = The average release of noble gas radionuclides in gaseous effluents, i, for short term releases (equal to or less I t than 500 brs/ year) from all vents, in pCi Releases shall be cumul ative over the calendar quarter or year as appropriate.
~
pnO
; 4k) d/ /
L. M
it ( O t3 = The average release of noble gas radionuclides in gaseous releases, i, for long term releases (greater than 500 hrs / year) from the free standing stack, in pCi Release il shall be cumulative over the calendar quarter of year as appropriate. s 2 Qjy = The average release of noble gas radionuclides in gaseous effluents, i, for long term releases (greater than SC J H hrs /yr) frca all vents, in pCi. Releases shall be
, c un.u l a t i ve over the calendar quarter or year as app-ropriate.
W I 3.17 x 10-8 = The inverse of t he nunber of seconds in a year. i I f j1: a/ ' c
. .und M
a 1 I-
e - AIR DOSE FACTORS (! i Nuclide Mi
- N
-_.._-_i*.'.
Kr-83m 1.93E01 2.88E02 Kr-85m 1.23E03 1.97E03 Kr-85 1.72E01 1.95E03 Kr-87 6.17E03 1.03E04 Kr-88 1.52E04 2.93E03 Kr-89 1.73E04 1.06E04 Kr-90 1.63E04 7.83E03 Xe-131m 1.56EC2 1.1lE03 Xc-133m 3.27E02 1.48E03 Xe-133 3.53E02 1.05E03 Xe-135m 3.36E03 7.39E02 Xe-135 1.92E03 2.46E03 Xe-137 1.51E03 1.27E04 Xe-138 9.21F03 4.75E03 Ar-41 9.30E03 3.28E03 1 i
~
l
?
I.t"
? 'a/ *R)
'd Y
L -- _____-__x-- _ - _ - - - - , - - l Ii
- From Table B-1, Regulatory Guide 1.109
** From Table B-1, Regulatory Guide 1 109 multiplied by 106 pCi /uCi to yield units of mrad /yr
~
(! Values arg per pCi/m
4 t1 REF_E_R_ENCES t 61
- 1. " Preparation of Radiological Effluent Technical Speci fications fut I;uclear Power Plants", ::UREG-0133, Oct. 1978 US:;RC.
4
- 2. " Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents For The Purpose of Evaluating Compliance With 10CFR Part 50, Appendix I", Regulatory Guide 1.109, Oct. 1977, Rev 1, U S:;RC .
I
- 3. " James A. FitzPatrick I;uclear Power Plant, Compliance With 10CFR50, Appendix I", Submi t ted to USt;RC in 1976, Prepared by Stone & Webster - yp. 1.3-9.
I
- 4. " Code of Federal Regulations, Title 10 Parts 20, 50, 100",
US::KC . (
- 5. "Envi ron::.en L al Techni ca1 Speci fi ca ti ons , Appendix B to Facility Operating License # DPR-59 for James A. FitnPatrick I;uelear Power Plant, Pcnzer liuthority State of I;ew York "
October 1974, US::RC. O t
- 6. "llandbook of Radionuclides", Yen Wang, Chemical Rubber Company, 1969.
- 7. "B adi ologi cal lleal th llan dbook", U.S. Department of HEW, Jan. 1970.
p9 102 I f
.}}