ML19221A837

Reg Guide 1.3,Revision 2, Assumptions Used for Evaluating Potential Radiological Consequences of LOCA for Bwr

ML19221A837
Person / Time
Issue date:	06/30/1974
From:	NRC OFFICE OF STANDARDS DEVELOPMENT
To:
References
REGGD-01.003, REGGD-1.003, NUDOCS 7907100054
Download: ML19221A837 (12)

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{{#Wiki_filter:. Revision 2 c June 1974 U.S. ATOMIC ENERGY COMMISSION j T HM. REG L LATO RY G U1D E \\s d 6,4 ri s o* / DIRECTORATE OF REGULATORY STANDARDS REGULATORY GUIDE 1.3 ASSUMPTIONS USED FOR EWLUATING THE POTENTIAL RADIOLOGICAL CONSEQUENCES OF A LOSS OF COOLANT ACCIDENT FOR BOILING WATER REACTORS A. INTRODUCTION review, guidehne exposures of 20 rem whole body ;nd 150 rem thyroid should be used rather 'han the values Se aion 50.34 of 10 CFR Part 50 requires that each given in s 100.11 m order to allow for (i) uncertamties apphcani for a construction permit or operating license in Gnal design details and meteorology or (b) new data pnmde en analy sis and evaluation of the design and and calculational techniques that might influence the performance of structures, systems, and components of Gnal design of engineered safety features or the dose the facihty with the objective of assessing the risk to reduction factors allowed for these features.) pobhc health ed safety resulting from ciperation of the facih t y. The lesign basis loss of coolant accident C. REGULATORY POSITION t l OC M is one of the postulateo accidents used to evaluate the adequacy of these s'<"ctures, systems, and 1. The assumptions related to the release of radioactive components with respect to the pubhc health and <afef. matenal fmm the fuel arid contamment are as follows-This guide pes acseptable assumptions that may be a. Twenty he pe rcent of de equthbn u m ised in evaluating the radiological consequences of this radioactive iodine inventory developed from maximum accident f or a Lodmg water reactor. In some cases, fuH power operation of the core should be assumed to unusual site charactenstics plant design feature 3, or be immediately avaiSble for leakage from the primary other factors may requ re ditferent assumptions winch reactor contain men t. N me ty.one pe rcent of this 25 wdl be anudered on an mdmdual case basis. The percent is to be assumed to be in the form of elemental Advnorv Committee on Reactor Safeguards has been s-corsulted concernmg this guide and has concurred in the iodme, 5 percent of this 25 percent m the fonn of particulate mdme, and 4 percent of tlus 25 percent m regulatory posmon. the form of organic iodides. B. DISCUSSION b. One hundred percent of the equibbnum radioactive noble gas inventory developed from After reuew mg a number af appheations for maximum full power operation of the core should be construstion permits and operating licenses foi bothng assumed to be immediately available for leAage from water pow er reactors, the AEC Regulatory staff has the reactor containment. The effects of radiologiul decay during ho' dup developed a number of appropriately conse rvative c. assumptions, based on engmeermg judgment and on in the containment or other buildmgs should be taken appheable expenmental results from safety research into account. progra ms con d uc ted by the AEC and the nuclear d. The reduction in the amount of radioactise industry, that are used to evaluate calculations of the matyrial avadable for leakage to the environment by r a diolo gical consequences of various postulated sontamment sprays, recirculating filter systems, or other acciden ts. engineered safety teatures may be taken mto account, but the amount of reduction in conantration of flus guide lists acceptable assumptione that may be radioactive materials should be evaluated on an used to.: valuate the design basis LOCA of a Boding individual case basis. Th pamary contatnment should be assumed to Water Reattor (BWR). It should be shown that the e. offsne dose consequences will be withm the guidehnes leak at the leak rate incorporated or to Se incorporated of 10 CFR Part 100. (DurL.g the construction permit m the technical speciGeations for the Juration of the USAEC REGUL4 TORY GUIDES cop,ei of poca.shed gu. des mov be obie.ned by rmum nd.cet s the d..n.one desi red to the U.S. Atomic E neryv Commessoa. Vro Nngton, Of. 20546. Reuwietos v GuAes ar e.isued to desce be me d nwee eveaetro no the pubi.c Attent on' Director of Reguietory Stentsords Common s and suwstions for incroarrente en these puedes are encou eyed ead showed te sent to the Secrevery r me1huds accepta6.e to he a E C Regumenry staH of ernpaement.ng noecif tc perse of of the Comm eason. U.s. Atomac Eneryv Commesson. WeNegten. D4. 20645, t he Commes.m a regwiat.one. to oebnente te( h nigwee u.ed by the sta f.n tre pdes opset be acceptab.e si they pro de e heese for the fendmgs roQu.tste to Attent on Ch.e8.Pvtsc Proceedrigs siaH v eted su.oents oe to pro.wse guidants to n eweswating soec4c prossems or pos e oppiacants Reguietory Go den see not eutatitute, f or regu et ons and corrononce The guides are eeued an stie trun.,g ten breed thw.seems s ar th them o not requee ed Methoos ered sodwt. ors d'Herent frorn those **t out an Po R octors c{t

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u aJent The leak age should be assume.i 10 pass desehped from the average duiy breathm ; rate {2 x 10' ducily to the emergency exhaust system without em / day) assumed m the report of ICRP, Comnuttee 2 2 n u s.mg m the surrounding reactor build:ng atmosphere 11 1954.) and should then be.mumed to be released as an elevated d. The iodme dose conversion facters are gnen m plume f or those faahues with stacks. 3 'RP Pubheation 2, Report of Cammit tec II. No credit should be given for retention of " Perm ssiole Dose for Interaal Radiationi 1959 i ml.ne m the suppression pool, e. thiernal whole body doses should he caladated using "Inimite Cloud" assumptions. i.e., t he duoem m heptab!c awampt.ons for atmospheric dif fusion of the doud are assumed to be large w nparco., i he and Jose somersion are. datance that the gamma rays and beta pit Jes Isasd 1 i levated ieleases should be considered to be at "Such a doud would be considered an mt. nite Joud f or hmhi equal to no more than the actual stad height. a receptor at the center because any aJJnonal lcamma a Fe r t a. n m Jependent conditions may cust. such as andl beta emit t m g matenal bey ond the cloud wrrounding e!evated topography or n arby structures dimensions would not alter the Oux of !ganm op whhh will have the effect of reduer g tne actual stack anJJ beta,mrtic'es to the receptor" (Meteo:oiogy and W ht The degree of stack height r. duction should be Atonne Eneay, Secuon 7.4.1.1 - edu o ial additions nahored on an mdmdual case t asis. Also, special made so that gaiema and beta emittmp ma:enal could be mercomlogical and geographical corchtions may eust considered). Under tFese conditions the rate 01 energy whhh can contnbute ,t o greate - ground level absorption per unit solume is equal to the rate ol energy the immediate neighborhood of a released per umt veaume. For an miiiate unilorm cloud mentranom in s uask for e xa m ple, funugation should always be .outainmg x cunes of beta radioactmty per cubic meter awawd M occur; however, the length of time that a the beta dose m air at the doud center is: i n u np t ion condition custs is strongly dependent on geographical and seasonal factors and should be gDI = 0.457 Ep esa!uated on a case-by-case basis. 4 (See Figures 1A thmugh ID for atmosphene diftusion factors for an The surface body dose rate f rom beta enutters m the elevated ie: case w;th fumiption.) inGnite cloud can be approumated as bemg one. half tha 5. No correction should be made for depletion of amount (i.e., gig = 0.23 [p). the efduent plu me of radioact ne iodme due t,o depoution on the ground, or or the radiolopeal decay For gamma emittmg raaterial the dose rate in air at the c of ioJme m transit. cloud cr a ter ir e For the first S hours, the breathing rate of pe rsons oilsite should be assumed to be 3.47 x 10' DI = 0.507 E x cubic meters per second. From S to 24 hours followmg 7 7 the acudent. the breathmg rate should be assumed to be 1.75 s 10' cubic meters per second. After that until the From a senu-m0mte doud, the ganuna dose rate m air end of the accident, the rate should be assumed to be IE TE x 10' tube meters per second.(These_ valuc; were N = 0.25 Eg Where ' ihe snat on con tan rnent leakage u nder a cide nt .oduens of fea t ures pr mided to r du6e the Icakage of i -ln et ne mamrials from the contamment wih be evaluated on DI beta dose rate from an mlimte daud (raJ/sec) g m indindual case N sa. Di= gamma dose rate from an mfimte doud 7 (rad /sec) ' in eme e.ncs. tredit for miur:g w dl be allowed. however. {$ E N. P# sn i ns a mount oi credit allowed w dl be evaluated on an indmdual u se N sn. (Mev/ dis) 2 average gamma energy per dism tegration = ' Crtda f or an cleuted release should be giwn only if the 7 (Mev/ dis)

p. u of release n (1) more t han tw o and one-half omes the

= concentration of beta or gamma emittine h i hr or am strutture dme enough to affect the dhreruon of

l.c plame or (2) knated far enough from any strutture whith isotope in the doud (cune/m- )

i ould have an cifett on the dnperuon of the plame l ur thosc n% D u hou um the a t mmp hent daTuuon factors f. The followmg specitic assu m pt ions are mmay eround i sel release given m section 2 h. should be used i acceptable with respect to the radioactne dood Jose h h r nom sac act.abihiy. i. calcula tions

• 'm e iouicd more ihan 2 maci armn we bodies or (I) The dose at any datance froii the reactor
• e c, sus h n means or one of the Great lakes, a fumphon should be calculated based on tht maimum ombhon should W momed in cuu at the un e of the a cideni concentration in the plume at that dniance takmg mio

.+1 onnnm nu one h.a hour. I or a cs footed icw th n 2 a ccoun t specine meteorologwal. t opoer iphical, and s i r om iecc bodies ni waier. a iumigation conJiaon shoulo ' l.e maimum N mmni n. cuu at the tune of the acident and cononue for othei characteristics which may affect t plume concentration. These site related enaraciens 4 %,n 125 0 1.3-2

mue bt ev luated on an mdividual case basis. In the case (3) The atmosphene ditfustor model' for an 01 het .Cion, the receptor is assumed to be exposed e!csated release as a function of the d stance from the to aa m onite -loud at the maumum ground le"-l reactor. is based on the information in the table below. Ngy wncentranon at that distance from the reactor. In the case of gamma radution the receptor is assumed to be Time e sposed to only one-half the cloud owing to the Followm9 ^ * * " * ^'* "#' enc cond t ons p r ese nce of the ground. The maxi:num cloud concentration always should be assumed to be at ground 0-8 hours See h.gure 1/A) Enselope of Pasqud! lesel diffusion categones based on Figure A7 (,) ~lhe approprute average beta and gamma mteorology and Atomie i nagy.19ps, eneroes emitted per disi:,tegration, as given in the Tab!e assummg vanous stad hegn wmapno I isotopes. Sixth E dition, by C. M, Lederer, J. M. meter /sec; uniform direction et ilol lander.1. Perlman, t niversity of Califomia. Berkeley; i a,s rence Radiation Laboratory; should be used. 8-24 hours See Figure 1/#1 E.ns elc pe of Pasquill g For BW R's with stacks the atmosphene diffusion categones;wmdsp:ed I meter /sec. datusion model should be as follows: vanable direction within a 22.5 sector. (1) T he basic egeatiun for atmosphe ne dif n.uon f rom an clesated release is: 14 days See Figure 1/C/ lins e:c pc ot Pasqudl diffusion categones with the follow mg e xpFh / 20,2 ) relationship used to represent maximum 2 UO" plume concentrations as a func tion of nuo o' F distance: Wh e r e Atmospheric Condition Case 1 = the short term average centerhne value of the 4g p, q4 x ground lesci concentration (cune/ meter ) E Pasqudi C Q = amount of mataul released (cunelsec) Atmosphene Condition Case 2 = w indspeed (meter lsec) 503 Pasquill C u o = the hon /ontal standard deviation of the 50'J Pasquill D plume (meters) [See Figure V.1, Page 48, Atmospheric Condition Case 3 Xaclear Safety, June 1961, Volume 2, 2 L37 Pequdi C Number 4. "Use of Routine Mete rological 33.3'1 Pasqudl D b Observations for Estimating Atmospheric 33.3'J Pasquill L Dn;rrsion." F. A. Gifford, J r.] Atmospheric Condition Case 4 = the scrtical standard deviatmn of the plume 33.3% Pasquill L) o, (meters) {See Figure V-2, Page 48, Nuclear 33.3') Pasqudl E Safety, June 1961, Volume 2. Number 4, 33.3>,: Pasqudl F Use of Routine M e te o r olo gt e t.1 Atmospheric Condition Case 5 Observations for Estimattng Atmospnenc SW Pasquill D Dispersion," F. A. GdTord, Jr.l 50% Pasquill F h = effective height of release (meters) wmd speed vanable (Pasqu.ll Ty pes A. B. L. and F windspeed 2 me te r / set. Pasqudl (2) or time penods of greater than 8 hours Types C and D windspeed 3 me ter 'sec ). F the plume from an elevated release should be assumed to vanable direction withm a 22 5 sec tor-meander and spread umfoimly over a 22.5 sector. The resultant equation is 4-30 days See Figure //D) Same ditt uuon relations as given above, w indspeed sanable dependent 2.03 2 exp( h j;g,2) on Pasquill Type used. w md direction m 2 frequency m a 22.5 sector. X/O = Thn m ulel sho uld be used u n al adeq ua t e ute 9, g. meteorokipeal data are obtamed. In ar te s ases au da ble mf ormation sush as mete irolon. topogrgh) and ceographhat more resiruine m: Jel to dnlante f rom the release point (meters). locanon, rnay datate t he uw o. a = other sanahles are as gisen in p 1), insure a conservative estimate of potentui onsite eeures. 125 015 1.3-3

h. For BWR's without stacks the atmospherie (4) The atmosphetic diffusian model fm ditTusmo model'should be as follows: ground level releases is based on the iniormation m the (1) The 04 hour ground level release table below, concentrations may be reduced by a factor rangmg from one io a mnimum of three (see Figure 2) for additional Tinw dnper sion produced by the turbulent wake of the F ollow mg A'm 'P *'ic const.ons h Ac*d*"' reactor building in calculating potential esposures. The mlumetric building wake correction factor, as defmed in 0-8 hours Pasquill Type F, windspeed I meterisec. sec tion 3 3.5.2 of Meteorology and Atomic Energy uniform direction 1%8, shou!d be used only in the 0-8 hour period;it is used with a shape factor of 1/2 and the mmimum cross-sectior.al area of the reactor building only. 8-24 hours Pasqu'U Type F, windspeed 1 meter /sec. varuble direction within a 22.5 sector (2) The basic equation for a tmospheric ditfusion from a ground level point source is: 1-4 days (a) 4M PasquiD Type D, windspeed 3 1 meter /see x/O = (b) (M Pasquiu Type F, windspeed 2 yz meter /sec (c) wind direction variable within a 22.9 SCClor Where = the short term average centerline value of the 4-30 days (a) 33.37c Pasquill Type C, windspeed 3 x 3 meter /sec ground level concentration (curic/ meter ) (b) 33.3's Pasquill Type D. wmdspeed 3 Q = amount of matenal released (curie /sec) meter /see = windspeed (meter /sec) (c) 33.3'7e Pasqmll Ty p F, wmdspeed 2 u the horizontal standard deviation of the = o, SC'#'/'#C plume (meters) [See Figure V-1. Page 48, (d) Wind direction 33.37c frequency ma Nuclear Safety, June 1961. Volume 2, ".5 sector Number 4,"Use of Routine Meteorological Observations for Estimattng Atmospheric (5) Figures 3A and 3B pve the ground level Dispersion," F. A.Gifford, Jr.j release armasphene diffusion factors bawd on the o' = the vertical standard deviatier of the plume parameters given in h(4). (meters) [See Figure V-2,6 ,e 48,Nuc/ car Safety, June 1961, Volume 2, Number 4, "Use of Routine Meteorological D. IMPLEMENTATION Observations for Estimating Atmospheric Dispersion," F. A.Gifford,Jr.] The purpose of the revision (indicated by a hne in the margin) to this guide is to reflect current Regulatory (3) For time periods of greater than 8 hours staff practice in the review of construction permit appi-the plume should be assumed to meander and spread canont and the revis:a guide, therefwe, is effective umformly over a 22.5 sector.Ute resultant equation is: inunediately. 2.032 xl0 = a ux z Where = d. stance from point of'.el ease to the receptor; x other vanables are as given in h(2). 125 016 u4

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