Text

Reg Guide 1.4, Assumptions Used for Evaluating Potential Radiological Consequences of LOCA for Pwr
	ML19221A838
Person / Time
Issue date:	06/30/1974
From:	; NRC OFFICE OF STANDARDS DEVELOPMENT
To:	;
References
	REGGD-01.004, REGGD-1.004, NUDOCS 7907100058
	Download: ML19221A838 (6)
	v • d • e

k.

Revison 2

'e June 1974

'N-U.S. ATOMK: ENERGY COMMISSION

@ M ) R EGU LATO RY G U D D E o

k DIRECTORATE CF REGULATORY STANDARDS REGULATORY GUIDE 1.4 ASSUMf TIONS USED FOR EVALUATING THE POTENTIAL R ADIOLOGICAL CONSEQUtiNCES OF A LOSS OF COOLANT ACCIDENT FOR PRESSURIZED WATER REACTORS A. INTRODUCTICN piven "i s 100.11 in order to allow fer (a)uncertamties in final deugn detads and meteorology or (b) new data htior. 50.4 of 10 CFR Part 50 requires that ea,h and calculational techmques that might influence the a pphea n t f or a constna tion permit or u;wratmg h ene final design of er.gmeered safety features or the dose prov,de an analyus and evJuation of the design and reduction factors allowed for these festiires.)

performana of structures, systems, and components of the taaht$ with the obiectne of assessmg the rnk to prbhc health and safety resulting from operation of the C. REGULATORY POSITION facih t y. The design ba sis loss of coolant accident (IOCA) n one of the postulated accidents used t i

The assumptions related to the release of radioactive evaluate the adequacy of these sttucture', systems. and matenal from the fuel and cc7tamment are as follows components with respect to the pubhc health and safety a.

T w e n t y -five pera nt of the equibbnum Tha guide gnes acceptable assumptwns inat may be radioactive iodine mventory develope 1 front mmmum used in evaluatmg the rad:olopcal consequerxes of this full power operation of the core should be assumed to acciden t for a pressun ed water reactor. In some cases, be immediately avadaHe for leakage from the pomary unusual site charact nstics. pant design features. or reactor contamment. Nmety-one percent of this 25 9

mher fa.to s may requae datterent assumptions which percent ts to be assumed to be in the form of elemental w dl be considered on an mdnidual case basis. The iodme, 3 pe; cent of thu 25 percent m the fmm of Advisory C,ommittee on Reactor Safeguards has been particulate iodme, and 4 percent of tius 25 percent m consulted concernmg this guide and has con-red m the the form of organic iodides regulatory position.

b.

One hundred perc ent of the equibbrium B. DISCUSSION

~

r adioactive noble gas mventory develoned from I " #'

E* ' * " "

After reviewing a numbe r )! a pphcations for anumed to be immediately avadable for leakage from c o nstruction pe rmit s and o pe ratmg hcenses for the reactor contamment.

pressunzed water power reactors, the AEC Regu:atory c

dects f radiological decay dunng holdup a nu mbe r of appropnateg staff has developed m the contammen: or other buddmgs abould be taken con se r va t in assu m ptiens, based on engmeenng

C ""'

ju dpnent and on apphcable expenmental results from d.

The teduction m the amount of radioactive safety research programs conducted t y the AEC and the m tenal av&ble for leakage to the environment by nuclear mdustry, that are used to evaluate calculations c ntammmt sprays, recirculatmg 61ter systems. or other of the radiological consequences of vanous postulated engmeered safety features may be taken mio account, accide n ts.

but 'he amoun t of reduction m conceritrattori of This guide bsts acceptable assumption, that may be raAcactive matenals should be evaluated on an used to eva'uate the design basis LOCA of a Pressunzed

.ndmdual case basis.

The pnmary reactor containment should be Water Reactor (PWR). It should be s' ow n that the e.

oftute dose consequences w111 be with.n the guidehnes assumed to leak at the lesk rate mcorporated or to be 10 CFR Part 100. (Durmg the coutruction permit mcorpriated as a technical specincation reqmrement at j ot' rev ew, guidehne exposures of 20 rem whole body and peak accident pressure for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and at 50 I!50 rem thyroid should te used rather than the values percent of ttus leak rate for the remammg duration of USAEC REGULATORY ( UlD($

cop.se of p***hed sudse nww toe ot o-was tre roome wes ang N d~=oas dos red in the us Atomc E nore cor -neeman vesse=essoa of N Repeaterv G ueden are 'couse to dunes ehe end mete om iebie to the puth Artent on Owectar of Repne ory S ierderes car,woune eeuf euggestene far enTrowepume en these psome are **noweeged end showkg tes apt to me Lorestery 9

nothode arveptahee to the AEC Roguetney steH of errgeomq eperdic pode of of the Commessoa. U S Atomac E nery, Cassemesson, weshuigeon. D r. N.

tee c omsnee d s regt igt.one so doesnegge toep e equet weed by few st eH en A fteM 8on bheef. htp**C P'OCeed@ sted NueW eDedse probben9e os poetwisted scredente of to Droww9e p.wiente to eE@ utan's Repsle*ory C,weden ere ret outletalwtes f or regute'ione end crar'Esherese opth tW e not roQuered Metreoria and goest #e deMerent f orn thcJee tot out in Ife psdee are escued en the Sohoevery ten turOed dvteeUMa f

tee psides se+6a be ecceptstzee if they provede e tienes f or the findinge res3w.e te to 1 Poseer Reecton the weewance or continuence of e permat or heeree tW tow Come messon 2 Reesord% eid Test Il eertare se 3 F wese erus usteriese F ocdusse B Occi4:e'iore' Hearth P4.sehed p,wm ariH t2 re's. cost per se dirmey ee appopr ie's 90 ecremawMare 4 E nvor orument eaproj Lting 9 A nt" rwet Rewous

$ Meteriges gruj P*ent Peoneften 10 Gewer ed caemrrence erwS to redomet # wee M(e ngten cr empermance 790"i100057

j s

the accident Peak au.- n. preww: o toe maumum The sunace body dose rate from beta emitters in the preuure denned m the te ch m.a'. spsineanons for mfimte cloud can be apprcumated as being one half this centmnment kak testing amount (i.e., p 0.23 Ep.

2.

Acueptable assumption. for a tmosphe ris diffusion and dose conversion are For pmma emitting matenal the dose rate in ait at the a.

The 04 bout ground level r e lease doud anter es.

be redu ed by a factor ranging from t unt en t ra tion ma y one to a maumum of three (see Figure 1) ler addiuonal D1 = 0.507 EY drspersion produ<cd by the t urb ulent w ake of the 7

reactor b_11dmg m talculating potential exposures The volume tric building wake cor r ec t ion, as denned m section 3-3.5.2 of Me teoro ogy and Atomic Energy From a semi-infmite cloud the pmma dose rate in a.r ts -

1%S. should be med only in the 0+ hour penod,it is used with a shape factor of ll2 and the monirnum cross-sechona: area of the reactor buildmg on!)

p, = 0.25 Ep b.

N; cerrecuan shou:d be made for depletion of Whe re the e ffiten t plu rne cf rad,oac t ive iodine due to deposition on the ground. or for Qe raJolopea] decay g, = beta dow rate from an infmite cloud (rad!sec) of iodine in transit.

c.

For the firs: 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , the breathing rate of b

E* * "*

(rad'i ec) s persons off site shea W be usu me d t e be 3 47 x 10 '

"*' O I#'

cubic meiers per second From o to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months fellowing the accident, the breathiry rate shou!J be usumed to be aw rage pmma energs per 6 stn tegration E

=

1.75 x 10 cuba meters per second. After that unt0 the 7

end of the accident, the rate should be assumed to be

= concentranon of beta of gamma emrttmg x

1.75x10 ct.bic meters per second Af ter that tett! the isotope in the cloud (cune/m*)

end of the acudent the rate shouid be assumed to be 2.32 x 10' cubu meters per sewnd (These uiues were f.

The follo wmg specific a ssumptions are developed from the average daily breathmg rate [2 x 10, em / day} auumed m the report of ICRP. Committee cajcu$anons.wtth respect to the radioactive cloud dose ac e table 11-1959.)

(1) The dose at any 6 stance frora the reactor d.

The iodme he conversim fact. rs are pven m should be calculated based on the inaumum ICRP Pubhca tion 2.

R eport et ' ommattee 11-concentranon in the plume at that distance takmg into "Perntuible Dose for Intemi Ra6 anon 1959.

accoun t specific meteorologicc. topopa phicaj, and e

Extemal whole 504 Jases shoc!d be ca!rulated other characteristics which may affect the maumum uung "Infimte Cloud" assumpuent i.e., the dimensions p ume concentration Thew site related charactenstics 2

of th cloud are anurned to be !arge cornpared io the must be evaluated on an indmetal case basts. In the case 6 stance that the pmma rays aad bet 4 p.rtcles travel.

of beta radiauon, the receptor is assumed to be exposed "Such a cloud *ould be conudered an mfmite cloud for to an innnite cloud at the maximum ground leJ a receptor at the unter because any adinona {pmma concentrauon at that distance from the reactor. In the and] be ta e mit tm g matertal hey an d the cloud case of gamma radiation, the receptor is assumed cc lx dimensions would not alter the hut of [pmma rays exposed to only one-half the cloud owing to the and] bet. parncles to the receptor" (Meteoiology and pr esence of the ound The maumum cloud Atomic EnerD. Sechon 7 41 i - edit ona' ad6t2ons concentrauon always should " assurned to be at gr Jund rnade so that ga mma and ? "a emiu mg matenal could be 3,n g~

consideredt. Ui. der these ci nitions the rate of energs (2) The appropnate average beta and gamma absorrnor per unn volume n ma! to the rate of enero.

enerpes emitted per disintegranon, as pven m the Table released per unit volume. For ar. tr.Brate umimm cloud of Isotopes. Sixth Edition. by C. M. Lederer, J. M

~ aning y cunes of neta raiaactmt> per cubic meter He!!ander,I.Perlman; University of Califorma, herkeley.

the beta dose m ir at the cloud center is Lawrence Ra&ation Laboratory, shotJd be used.

g.

The atmo:phenc 6ffusion model should be as DI = 0 4 57 Eg g

follows (1) The basic eq uation for a tmosphe nc 6ffuaon from a ground level pomt source is.

' ne errect on wru nmem ice a nc e-ac c2d ent co nd a m or feat en pr m ded r.. re h r the ink see or

(

rewine materiah fmm the.on t.mme nt m W be eva6aied on XN

W O O

V a n md a d a caw ba m YI i

1 4-2

p T' "*

Where F oliowing x = the short term average centeritne value of the 3

grotmd level concentration (cune/ meter )

04 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Pasquill 1ype F, wmdspeed I meter /sec, 0, amount of material released (cune/sec) v uniform direction

= wmdsped (m-ar/sec) u o = the horizontal so.dard deviation of the I

plume (meter.) [See Figure V 1, Page 48, 8 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Pasquill Type F wmdspeed I meter /sec, Nudcar Safety, June 1961, Volume 2, variable direction within a 22.5* sector Number 4."Use of Routine Meteorological Observations for Estimatmg Atmosphenc

!4 days (a) 46 Pasquall Type D, wmdspeed 3 Dispersion," F. A. Gifford, Jr.)

meter /sec o,

= the vertical so-dard deviation of the plume (b) 6% P15 quill Type F, wmdspeed 2 (meteis) [See Figt.re V., Page 48,Nudear meter /sec S:fety. June 1961, Volume 2, Number 4, (c) wmd direction variable withm a 22.5*

Use of Routine Me teorological sector Observations for Estimating Atmosphenc Dispersion," F. A. Gifford, J r.]

4-30 days (a) 33.3% Pasquill Type C, wmdspeed 3 meter /see (2) For time periods of greater than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months the plume should be assumed to meander and spread (b) 33.3% Pasqwil Type D, windspeed 3 nmformly over a 22.5* sector. The resultant equation is-meter /sec (c) 33.3% Pasquill Type F, wmdspeed 2 meter /sec x!O ~ 2.032 (d) wind direction 33.3% freoxncy on a

zux 22.5* sector where (4) Figures 2 A and 2B give the grot'rd level

= distance from pomt of release to the receptor; release atmospheric diffusion factors based on the x

other vanables are as given m g(1).

parameters given in g(3).

6 ground level reieases is based un the information in the 2 for

( i, The atmospheric diffusion rnodel C

ir,Ilowing table.

D. IMPLEMENTATION

This model sho uld be used untd adeq ua te site The revision to this guide (indicated by a hne in the meteorciogical data are obt.ined. In wme ca ses. avatadne gg gg g

irdormation, such as meteorology. topography and geographical revie w of construction permit appbcations; therefore.

kwstaan, may ontate the use of a more restrkt:ve rnodel to msure a conservative esttrnate of potenhat offste esposures.

this revision is effective immediately.

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