Regulatory Guide 4.1

Measuring and Reporting of Radioactivity in the Environs of Nuclear Power Plants

ML13350A200
Person / Time
Issue date:	01/18/1973
From:	US Atomic Energy Commission (AEC)
To:
References
RG-4.001
Download: ML13350A200 (4)

1/18/73 U.S. ATOMIC ENERGY COMMISSION

REGULATORY

DIRECTORATE OF REGULATORY STANDARDS

GUIDE

REGULATORY GUIDE 4.1 MEASURING AND REPORTING OF RADIOACTIVITY

IN THE ENVIRONS OF NUCLEAR POWER PLANTS

A. INTRODUCTION

radiation and radioactivity in the plamt environs. The provisions and principles in International (Commoissiotn on

(;Geneil Design ('C itein 4i. 'o.nitoring Radiological Protection (I('RI'l) P ulicanion 7- Radioactivitv Releases." ol' Appendix A it) 1( ('FR Part pertaining to the releases of radioauctivitv during ornmal

50. "'(Lennd I Desigji ('iteria Ior Nun:leair Power Plants.' plant operation should be used as additional guidance in requires that licensees provide for mroitioring the plant developing a program of this nature.

environs totr radioactivity that may lie released from normal oqperations. including anticipated operational

B. DISCUSSION

occurrences, and fion pi!stulated accidents.

Present requirements to keep levels of radioactive Subpala, ,rapih tall 2) of § 50.36a of 10 CFR Part 50 material in effluents as low as practicable should assure that radiation doses to the puhlic resulinig front efflutent requires Ihat technical specifications for each license releases will continue to retnain mninimal. The type of include a requirement that the licensee submit a report program described in this guide is considered adequate to the * ('tnniissiotn within 60 days after Janutarv I and to provide information needed to determine whether July I of each year which. iii addition to specifying the exposures in the environment are within prescribed or quantity of each of the principal radionucides released expected limits and to assure that long-term buildup of to unrestricted areas in liquid and airborne effluents specific radionuclides in the environment will not duting the last six months of operation,' provides become hazardous.

sitflicient intormation to estimate annual radiation doses to the public resulting from effluent releases.

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A preoperational program should be conducted in the environs of cach proposed nuclear power plant site Paragraph (c) of § 20.106 of 10 CFR Part 20 states to: (I) identify probable critical' pathways io be that the CoInjIssion nMav limit the quantities of radioactive materials released in air or water duringi a monitored after the plant is in operation: (2) measore specified period of time to assure that the daily intake of background levels and their variations along the anticipated critical pathways in the area surrounding the radia ctive materials from air. water. or food by a plant. (3) train personnel" and (4) evaluate procedures.

suitable sample of all exposed population group.

equipment, and techniques.

averaged over a time period not exceeding one year.

would not exceed specified quantities. Section 20.201 of Years of experience at various Contitnissitt facilities

10 CFR Part 20 further requires that a licensee conduct have demonstrated that specific radionuclides behave in surveys of levels of radiation or con1centrations of known ways under given environtmental cottditions.

radioactive itaterial as necessary to show compliance Therefore. comprehensive and detailed envitonlmenial with AIC regiulatioims. studies may not be needed at sires wiilh well known

"riis ginde describe., an acceptable basis for tCR P ublication "7. Iroin4p! t'" h'id','rt,o 'tlI

designing a progrant to measture and report levels of . Io,,itoring Related to thie' Il otdlhig of R idi., t'ti t .1" 1,alriIt9.

Septemher 13. 196S t(henrenin rir It.'RI' I'Ltsicali ,tt I7.

I At, :acct-t:M,-i" pr,-grti is preseunt.l its saref v (.;tide 2 I (to)

tiF r the p ors'veorf this. guite. thie Ierni "crilicar"t tit lit, he re sitsed :,%;: Regtla, try Gttide). "M ,: avuriniand I~ttep rling (fo Effluents frillr Ncttc'i:r llnwer Narls.'

same meaning as in t'RIt t'uhblication 7. Sipra niote 2.

USAEC REGULATORY GUIDES Copiei of oublishpil gui&ns m'sv be ObtainedI iv 10ourst .rsdic.lting ihe division%

desired io the US. Atomice EitefqV Commtttsi~to, VY-shIM9is.. D.C. 20Ob45.

Attention: Director of Regultfory Siend~itds. Cofnrmwnis Anil wrgoo'sions tot ResfutAiorv Guide, Wi'. 1su"nf It' dtecrts amit flt~i't oAV.,Ihhtt In the p~ublic ir19ifovenerflts int these quidei are en'couraged And %thisuithelenti t) ihes" 5'c~fiatv meiohorb. Acc-titabl- lto the AEC stioclinoirs'taff of mtSiirmoni,roo %s~eci'cpatrts of

'he Cnmm-n',s~ e.I55 to doiti-.1ie to-chnoriurs used hy the staff in of the Commissuions. US. Atomic EnetfgYCommisitn. W.Iihinaroin, D.C. 21if"45.

Aifent,nn: Chief. Public Peooceed-nos Sitaf.

S1 s*f14 W911f9.'tthi Of9 tnSIUtSi'd a~ccidenrim

"aWAiiung of Is isoisvde 9lwdaneem to The g,,.des ate issu~ed in itshe fotlhvittg tenr btirnd rss S

With thf-fsitt A '995! Itjit.'ti Mi 'h-c A", soloot-9'5 dii etenl friom those set Dor o the gui~de, beAcmteilef -1 tt't'v p'ovide i ti.1t9%1(5 the finings i to"I d flt9rlufsoi In 1. Pow~erReactor% in'. P,oducis ihm. issuane" ot cont~nUAA9CP'Of .. pe~m9o is' teens't, the95'Cnmmosvo' 2. Research AndTest Reiclto.' 7. Itasnsttimti""

J. Fuels And Mate.'3s Fscdmtm' B. orrciur.1iOn'si 9-J..111t

4.

Putftshpcj i qud$S.lit 01Il ~ ,rti,

~t~s~ coI9or.91.' 4199t' iro-iwrnrcommodi.'

In ..

5.

Environmintat and 5,5mm Material%A"tS'iiPitotwe'rs'etiof

' Anf-l'usl RteW,~

10) 6--M~s

bleu1vJirlon1etal nrsport process". Onc(e adequate radioactivity in the environs may all be useful for sttudies have been done to assure that the tratisport this purpose.) Inifornation of' this nature will be of processes are understood. analyses otC "indicator considerable help1 in inodil ying t[ie initial organiis'ns may adequately define radiotuclide levels in lnvilonllillentalti easure tut.nts program.

tile envirtomnent. The "'indicator orLalnis1t" concept of'

environmental samplinl"g involves tile practice o I hil'orimalion obthaied f'ront this programn will le examining food chainls for selecied orga;nisins o0r insed. in conjuintetion with data oil radioaclive effluents.

materials which provide a sensitive and reliable mneatsure to evaluate mneasulres taken by 'ite licensee to assure that t' (lhe uti:Uatites of' eac'h (adiolluclide cycling throught plantt releases to the environt1ient and radiation doses to each lood chaint. For example. ill the case where the the public are mailntinel wvitlhii the numerical dose plaitt'cow,'nilk-nian food chain is determined to be a limits determined by the Commission io be as low as critical palthway, it may not he necessar Ito extensively practicable. Also. licensees' data will be compiled andi sample anld illeasure grazing plants :mnd f'odder to keep co III pared. and a comlrprehlensive stimitiray ii 1'

tliack of iodine-I 3l cyclinein fhle food chain. sihce radioactivity in thle enivirons of nuttclkear power plants will sampling and nieastiring tile milk produced by dairy be prepared by tlie Coimmission.

cow\s in stirrotndine areas may be :dequate.

'[e Commission's Regulator.' siarf has evaluated At'ler the plant is iii operationt. a program for the types of fitforination needed to provide supporting me.*sturiniz radiation levels and radioactivity in the plant evidence for assessing tile pert'ormance of 'he plant witli environs manst he maintained on :a cOnlintlilln basis to respect to keeping populatnit exposures as low :is assist in verilt.,ing projected or ariicipated radioactivi 1v practicable and to verify predictions of concentrations concentrations and related public exposures. An ohI speciflic radiontiucl ides in lie environment based ott entvironu ental tnonitoritng program shotld be flexible. effluent iieasurements at the plant. Based on 1his aid, as results are obtained. tihe prograni should be evailtation and oil a review and assessment of' existline reviewed to identil'y any\ necessary changes. The progra n licensees' monitoring anid reporli g prograins. ihle s:tlt'

shuhld then be appropriately nodified. The initial has developed tile regulatory position set forth belo'v.

pttogram should be designed in accordance vith the followinug criteria:

C. REGULATORY POSITION

I. It should be based on the analysis of" critical The proerani for nieasuring attd reporting clf pathwayIs for the types and quanlities of radioactivity ill the environs ofinuclear power plants radionuclides released froni the plant into the must provide suitable inf'rs:auion from which levels of stlrtoundine envi rotinten I radiation and radioactivity in the environs of each plait carl be estimated. This inlfornation also may provide

2. It sihould consider tile possibility of buildup of long supporting evidence in evaluating tie perforniance of half-lived radiominclides in the environment and systems and equipment installed to control releases of'

identify physical and biological sites of radioactive material it) tile environnenw.

acctmniutlationt that ntaty contribute to huniani ex\posures: The basic principles set forth in this guide constitute an acceptable basis tor use in establishing an

3. It should be designed to facilitate use of reported en viro ini ental Imonitoring program. These sane levels of radiation and radioactivily in estimating principles will also b: used as bases in developing the annual radiation doses to tle public resulting froit licensee's corresponding technical specifications.

effluents:

1. Preoperational Program

4. It should consider the potential daimage to itttpot tant plants :mud arimals:'a Potential critical pathways should he idemifiied prior to plant operation. l';,e provisions in ICRV

i. It should be designed to establish correlations FPtlblicaiion 7 rela ted to operational releases of between levels of radiation atid radioactivity in the radioactivity to the environm-nt should be used as a environment and radioactive releases front plant guide in determining critical radionuclides and pathways.

Operation. (A variety of lechniques. including Other patlhways not directly related to humans should measurements at control locations. preoperational also be identified (see regulalory position 2.a. below).

surveys. correlations with effluent data, and Wherevet possible. suitable indicator organisms or media comparisons of operating versus shutdown levels of should be identified in each pathway.

2. Operational Program

'-A species. wthethe'r ainin ,tor plant is' "irnport:nlt'" (I) Kit is t'-nimeu 'rciatlv or r.creaLit ally vaitiau:tule. (2) if it is rare ir e~ndanlge~red. r 3) ifir t :iffect% thLe' ,vll-te.ing 'it stoF¢ importanI a. Sample Media sp¢i*c wiethin criteri: (I) and (2) ahiivc or (4) if it is critical to fit! structure and function (if (ht ¢crtiogical system. A "rare our Where practical. a suitable indicator organisin endulangetred" species is any species cufficiatty tiesignated as such hb the 1).S. Hih and wildlife Service. or ttedium in each critical pathway should be sampled

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and analyzed for the critical iadomliclidels? released Ilt sotmie cases. sat ll)lingll t.1

• ll illttitous b:sis from the plant. An abundant, readily available form with may be necessar\ (e.g.. air samttplinig and co,]ItitIotIs nowt habits should be selected. mile astire ie Illt f. c u ttInlaIive exterit1al ,:dia, itin exposure). Composites of some selected s:aiple types.

• Careftul attenttioni should ble given to avoid such as air filters. niav be appropriate I'm" meastmrettiettt insdt(tLSng serious stress onl art ihmportan't species otf ot long-lived madi nit ticlides.

organism by a samipling program. Heavy sampling pressure added to natural prcdaliun and other When critical pathlways become firmdly elvironitSelillal stiesses could restil I in tenpora ry identified awtd correlations are developed between obliteration of desirable potpulations. In stich cases. concentraiJuis of radionuclides itt einvirontm.entaml media other indigenotts hut al mnda n spcies souch as rodents. anid planlt releases, or level, have been iotind too' low to rabbits or scrap lish. maylbe stilistituted as indicator detect. it is probable tltat saripling frequte .,ciesot'ccittil org:antisms IthatI vill provide an estimate of the media irmay be apprli mriaiel " iticreased or decreased.

radionuclides avai.lable to main through natiral f'ood Such chan6ges shtIould onlyl he titade on itidividual paOwer chains. In some instatnces. prop,!rly selected and sampled plants after considerable 'peraliotlal experienlce Ilsa vegetam 11my 'list) provide a good imteaslie of the accrued.

radionuclides in , critical FpatlIway.

c. Program Scope WhcLtre use of a single indicator tneditim is During (hft initial three years of commercial impractical. samples of' several media from each pathway power operation (or other period corresponditie to should be collected and analyzed. The C(ommission maximum fuel burnup it] the initial core cycle). tihe recomizes that some pathways do not have more than olne eiviromnittillal meditiht. c... external radialion mecastirememti program shotuld be relatively c11muipre- nensive in an attempt to verify anys' pr,*iected torle- exposures from clotds of uatnima-ray-emittitog radio- lations between radioactivc eflltuilts attd levels in nclides inlvol-.. onlV onle paithway the atmosphere.

environtmental media. The extetnt of measturettent of The actual tit:uhier of' media it he sampled in each environnmental media should be flexible and should pathwlay will be determined oni a case-by.case basis for depend on the type. quantity. and concentration of each site. Itt some cases field measurements may be radionuclides from the plant as well as the results prelerable to collecting samples for laboratory analysis.

obtained from previotus nmeasurements.

O The program should include sampling of 1f. after this period. the licensee is able to environmental media to estimate average radionuclide demonstrate from levels in environutetumal media or concentrations in important biota (see B.4. above). calculations (using measured effluents and appropriate Radiation exposures (external) and internal doses from dispersion and bioaccumulation factors) that the doses short half-lived nuelides may be estimated by from a particular pathway are sufficiently small, the calculationrs (,tisin g e[floeii mn easuremen ts and number of media sampled in the patlihway and the appropriate dispersion and concentration factors) rather frequency of sampling may be reduce

d. An adequate

[han by routine collection of samples of environmental program wiln i emphasis mml indicator o rganisins and media. In some cases field measurements at certain selected media should still be continued in order to locations to establish cotcert t rations of specific con firm that the levels of radioactivity in environmten tal radionucl ides may be necessar". initially. to confirm media remain small.

predictionls.

d. Analyses h. Sampling Frequency Samples should he analyzed for the critical When a critical radionuclide has a short hallflife radionticlide(s) released from the plani. (Gross belta and Imtinutes to days). it may be necessary to evaluate gainnia analyses of samples stuch as air and fresh water radiation expUsure by tuaking measurements in the field may be useful to indicate that the concenltralioni of a (e.g.. by use of thermoluminescen t dosimeters or critical radionuclide is not greater thall the delectioll portable multichannel gamma spectrometers). capability for that nuclide.

When ;I critical radionuclide with an 3. Detection Capabilities internnediate half-life (weeks to months) is released continuotisly or frequently. sampling and analysis of The detection capabilities associated with ,1,eaisiritmg etvirotlneinial media in the critical pathway should and atinalvzitt radioactivity levels shotild he eSltablished

. generally be carried omt at inltervals no greater than two primarily on the basis of poleittial hutnatt dose. The least or 'h ree half-lives of tIte iuclide. For long half[liife detectable dose will vary from facilitvy to facility dionuclides (years). measurements should be made at depending on the critical pathways ideI iifled arm d IItC

st once per year. Where seasonal eflects ,ay be stalof-tl'-he-art of sampling and analysis in these important. sampling should be on a quarterly or at least pathways. Because of tie need for a preoperational semiannual basis. monitoring program, detectiot capabilities for a

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pat tcular piorat11 should he deternmined during :n early alpprolri:e. Trie licensee should demtostiale that aill staLc of licensing. The staff rc,.ognizes that direct assutittiolts. parameters and methods, used are adcqumtte tmeeas uremtetn ts of envirotnml enltal Imredia cannot1 alvays and compieleIto allow Itwhere data pertii) a c omparison ,

'cctetlruepo levels -dine to Commissiti design with predicted concei.ratitms and doses based ol

, Iieclites. Nevertheless. every reasonable effort should effluents from each nuclear power plant under license.

be made to achieve detection capabilities which will (See Safety (uide 21).

dewclt ratdiition levels or radioactiVityI ol0cent-rat ions ill critical pathways that could result in radiatiom doses To petlmit comparison of signi'icart entvironmental cor respudindg to a 11ew 1'ercen t of thie Federal Radiation mIolnitoritng data willh predicted eoncent ratiotls anid doses

(',tmcil's radiation protection guides Ie.g.. a ftw percent (bhaid on reluiretletts ol' I0 CFR Part 50). the report i! !70 mren'years for whole body dose to a stiiable should include Ilie following i tents for each

-ample tithe exposed population ). enviro*mttlenttal tttedii: :1:

4. Reporting of Results a. Samnple Type I. Biological (it tile extent practicable. list Data sholtld he reported to the Commission in the specics. life' stage. age. weight or size. biolog.ical r..,ort suhmitted within t,-0 days aflter January I and conditiot, tissue or m1terial sampled. sample weight.

July I of each year.' InI the eveut that all unexpected etc.).

mclea,ýe iln radjoaCtivMI or r:diation levels is measured in 2. Non-Biological (identify type - soil, air.

a p-Mricular critical pathway. the Commnission should he etc.: list actual area. depth and weight or volume not, fied prontptl.. Appropriate levels and reporting sampled as appropriate, whether grab or continuous inetvals will he determined on an individual plant basis sample. number of samples. etc.).

and included in the technical specifications for each b. Sample Localtion (also !tipply mtap showing license. locations)

c. Collection Period (continuous samples) or Dale The Commission utilizes the data from these reports of Collection to provide assurance that man and his environment are d. Critical Pathway not heinu subjc,:ted It unacceptable radiation exposures. e. Radionuclide Consequently. all assumptions. parameters and methods f. Concentration (mCi/ml or g. specifying wet or used to measure and report radioactivity concentrations standard dry. weight) and/or Deposilion (jiCi/mh ori and radiation levels should be specified in the licensee's other apprupriate units of tteastire). (List conversionti, initial report aid updated in subsequent reports as factors relating sample activity and volume - depth X

cross section - It) total area deposition: average and s t-'d,.at Radiatiiin Councit Report No. I. bIac'kgroutnd ttlaXIillttt values (for each medium. etc.)

.llawrnelkrth'e"Dere'ml-Feat ,.RadiathOnPro'tetion Srandards.

IaJ3. 19 h (.

g. Background Value

7

h. Analytical Method

";uhpalragraph (a)(2) of *50.3fia (,f 1o C0 R Part 50

j. Comparison of Observed Concentrations.

requites the subtinjsimi or a report within ot, d-'s after Jainuary I :ie-d Jul ' Ii f eacit )'ear speciriflin the quantitv of eac oliht . Depositions and Estimated Doses with Predicted Values prin` iial radimiuclidts released lto unrestricted areas in liquid (based on effluent measurenments)

andll in g'awous erffenlt%. the duta taken in suppnrt of the lite'i.ee'" en.-iroiitnential monitoring programn shriuld also he j. Remarks (be sure to explain any tititstal

,,jonmia ltd s;emiannually. Ir additional lime is needed, the repnrt measurements or deviations).

stler*th indicane :md the d*t:n shoulJ he carried o*er into the

.sit;

Io'et ,emiannua:ll report. it would greatl, r:ocililgte comparismns rnd 7.'ierrlaitil ot t ta if the en sir.*inieint 3ind effluent 'I .stim-mtes i)f the error assoeinted with the: measurement of niaiateirilg dat.a m.ere .mnihtited ilnto single reports. each environmental medium should he reported.

O0

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