ML19221B258

Reg Guide 4.16, Measuring,Evaluation & Reporting Radioactivity in Releases of Radioactive Matls in Liquid & Airborne Effluents from Nuclear Fuel Processing & Fabrication Plants

ML19221B258
Person / Time
Issue date:	03/31/1978
From:	NRC OFFICE OF STANDARDS DEVELOPMENT
To:
References
REGGD-04.016, REGGD-4.016, NUDOCS 7907200113
Download: ML19221B258 (7)

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U.S. NUCLEAR REGULATORY COMMISSION March 1978

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We, =a) REGW_A~ORY GW DE

- v g9,..., "e OFFICE OF STANDARDS DEVELOPMENT REGULATORY GUIDE 4.16 MEASURING, EVALUATING, AND REPORTING RADIOACTIVITY IN RELEASES OF RADIOACTIVE MATERIALS IN LIQUID AND AIRBORNE EFFLUENTS FROM NUCLEAR FUEL PROCESSING AND FABRICATION PLANTS A. INTRODUCTION rication plants. meludmp scrap recmcry operations In some cases. m od it ic at ion s of the dew ribed pro-Set tion 20.106 'Radioactisits in Ettluents to Un.

orams m.n be accepteJ or required a.s license conJi-iest rit ted Areas. - of 10 L.I R Part 20 ' S.tandards ter depending on indn idual sue characteristics.

tions Piotection Acamst Radiation, pros; des that a hcen-plant design leatures, umque operations. or other f ac-see shall aot release to an unrestricted area radioac-tors..t he need l'or modified programs w ill be deter-ine materials m cont en. rat. ns 1.iat eu ced the lunits iiHned b) the NN(, Ntaf f on a case b)-case bJsn specified in lo C' " I u t 20 or as otherw ise au-

.Ihn guide n intended to appis to plants that proc-thorized in a licen-suca bs t he 's.uclear Regulatory and f abricate luel contaimng' either plutonium or ess

(.onuniwinn. Sech n 2.

01. ' S.urseys, t to Cl-R uramun-It shoulJ be used as a appropriate f or the Par t J, i turther requues that a l_censee co.uct sur i

radionuclides released f rom the parncular plant beine seys of wncentr oions of ravioactis e materials as c o n sidere d.

necessary to dem oc m om[lhnce with NRC, recu-Ra fa-lanor-Set t ron _- l!

'th a t Sun.r s 91

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8. DISCUSSION tion Monitor.ng, and Dnno f ' m.o :.

'e-of sur',eys Inth l'ia.lon on the identit), ( o n ce nt ra' ion. and Sec tiiin 'N I

' fil!II'ei i S.

'litoring Repo lIng i

Regilirem' is, if !(' #'s N '.i r l h) 5 p*' 'la! Nil-quantit) 01 r.iditinuclides in liuuid and air biir ne c! car Materi-ic, re s,,cci

• _ e s.mt hori/ed ti> [wu etBuents trinn nuclear tuel priicewing and f abrh.itisin a* mate ul f or processine plants is needed:

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anJ t uel labocat n..

ap reco-fi,, or cons ersion ot 1 For es aluation by the NRC stall of the en-uramum hesatla w ' su5n'il sennannual reports to s ironmental impact of radioactis e materials in the Comm.wien, specitying tne quantity at each ot' eltluents meluding estunates of the potentul annual the principal ra j uinuclides released to u n re s t r L !cil radiathm dmes to the public.

area s and such other mtormation the Comnn+n 2

~l o ascertain whether reculatory icq uire me nt s may require to estintate maitimum potentui annual bas e been inet and w hether concentrations of radioac-radiaMon dmes to the public resuhing f rom ellluent in c m. teruh in hqmd.ind gaseou s citluents base relea se s been kept as loh Js n rCJsonabl) A !Me s able.

Parrrg h h-i ot ;20.1. 'Purpmc.

et in Cl R 4 1 or es aluation by the hcensee and the NRC Part 20 states that e. cry reasonable ellon should be statt of the aJequa< > and perf ormance of ellluent made b) lhcHsee s ti) nlalntain radiatitui espinure arnl cimtri Is re! eases til ladh uctis e IllatCrials !n ell'lue nt s hi u hre

(( is essential til h.ne a decree iil unitiirinity in the stricted areas as l'ar below the junits specified ni Part p rog ra m s f or measuring. es aluating, retorthng, and 2i) as n reauinabls athies able.

repiirtm; d.ita on radioattis e material in ettluent s t his emde JNribes progrann aacprable tii the I bis gu:Je pros ides a unilor ni basis f or somparmg

's RC su!! tor me.nuring reporong. anJ es aluanng d ua trom ditterent sou rc e s and pc:mntmg the prep-rel caw s iit raduu tis e materials in liqu d and air-arati.m of cinni lent suni:. iries til data li>r use by the borre ellluents trom ty pical tuel priNewmp and tab-NRC stall as bases f or awewing a licenseeN ettluent

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controls and the potential environmental impact of f or hatch releases a representath e sample ot each rmhoactis e materul in ettluents.

batch should be colletted.

T he sampling program should be suthcient to per-C. REGULATORY POSITION mit a determination of the quannnes of radionuclides and the aserace concemration or radionuciales beine

1. Methods of S.ampling Analysis didgd Nm the pin ~1he mpW me m M

'ihe sa aplig and maly sis met hod s used m the release point should be such that a representaris e ellluent monitoring programs shouiJ be t hosen to umple of the ettluent is collected The solume of prmide intornutmn on the quantity and concentration lyd enluem Amid be determined in order to cal-or the radionuelides m airborne and hquid ellluents culate the quantities of radionuclides dncharged INetul ref erences on methods for samphng and anal-s sis are meluded in the bibliography m tlus guiJe.

2.3 Quality of Samples 2 Sampling Program Prosiuons should be nia& to ensure that represen-1.itise samples are obtained by use of proper sampling 2 l Auborne I.f tluents equipment, proper locahons of sampling points. and Airborne etliuents f rom all operations a wociatc J propa proadams for coHuhon and storage of sam-with the plant should be sunpled, includine labora_

plev ul mfemnas on mdmA for samphng and tories, experonental areas. storage areas. 'tuel ele-anahsh am hued in the biMography.

ment assembly areas. and hot cells used for examina

,W umples coHuted at the unm loMon may N tion or irradiated fuel combined f or analy sis it thes represent a umpling i or auborne ettluents f rom process conimement penod ot one wak or lew.

sy stems and procew areas where material is handled Uyuid winples coHut.d at the same Wahon may m dispersible f orm. a representalise sunple of the be combmed d they represent a sample period of one nmnth or h w.

ettluent f rom each stack sent. or other pomt of re-lease should be collected continuously f or subsequent Lmples shouM not N combined it they are trom WHuent locahont deternunation of quantities and a'.erage concentra-tions of radionuclides released. This sampling should be conducted regardlew of the concentrations or 3 Analysis of Samples radioacti e material in the eitluent.

31 & M M Ln@

Other airborne ettluents should also be continu-ous!> sampled as mdicated unlew the licensee has ev All air samples should be analy /ed at least weekly f

tabhshed, by periodic stack vmpling or by other for gro w alpha and grow beta ac'is ity. All liquid means. that the ettluent rtleased is insigmticant In umples 6uld be analy fed at least monthly f or gross such cases. the ettluents shoul ' Se vmpled at least alpha and grow heta actnity.

quarterly. An esplanation of sucn a tinJing should be Radionuclide an.d ses should be perf ormed on 3

prosided as supplemental mtormation. For the pur-selected umples unless i!) the grow alpha and pross poses of this paragraph. a significant contribution n beta actisities are so low that indisidual radic"uchdes defined as a concentration equal to at least ten per.

could not be present in concemations greater than cent of the appropriate concentration hstcJ in Table 109 of the quantities specified in 10 CFR Part 20 11 of Appendn 11 to 10 Cl R Part 20. as erred oser a Appendix 11. Table 11 or (2) the radionuclide compov t alendar quarter ilmn of the umple is known through operational date

'T he samphng procram should be sutlicient to per-such as composition of feed material.

nut a deternunatmn of the quantities of radionuclides Fxamples of cases where operational data may not and the.n erage concentratmn of radionuclides being be sutlicient f or the determination of radionuclide dncharged f rom (ne plant I he s.unpling rate at ex h composition are as follow s: (Il plants processing release point should be such that a representaine uranium w here the ammomum diuranate protew or sample of the ettluent is collected. The solumes of other ion exchange procewes result in a separation auborne ettluents should be deternuned in order to and concentratmn of thonum isotopes (principally calculate the quantities of radionuclides dncharged.

thoF Jm-234 ), f2: plants wh( re uraninm of sarying ennchmenh n proawed duung We paind of cond 2.2 laquid Ettiuents cration, and (3) plants prsewmg plutonium w here Representaine samples should be collected at each significant variation in the plutonium-23R liqmd release point f or the subsequent determination plutonium-234 ratio among batches of plutonium and of the quantities and as erage concentrations of the continuous incrow th of americium-241 w ould radionuchdes discharged m any hquid eMluents that preclude the use of' feed material data in deterr.uning could reach an unrestncted arca, including discharges the radionuelide composition of ettiuents.

to a unitary sewerage sy stem.

Where radionaclide analy m is perf ormed to de-representatise umple ternune the rathonuclide compmition of effluents the I or contmuous releases, a shtmld be ctintinually cLillected Jt e.ich release Iwiint.

analy sis should be perhirmed at least quarterly on one he~

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sample collected for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from each sam-4.3 Calibration phng 'ocation Radionuclide anah ses should be made more otts n: (1) at the becinnine of the monitortne Indisidual written procedures should be prepued program, until a predictable radionuclide composition and used for specific methods of calibrating all sam-of ettluents is established. ( 2) w henes er there is a phng and measuring equipment, includmg ancillary sigmticant. unexplained increase in pross radioactis-equipnwnL The procedures should ensure that the it), or (3) whenesci a piotess thance or other cir.

equipment w dl operate with adequate as t macy and cumstance might cause a s'gnilicant S ariation in the

'tability oser the range of its intended use. (bhbu-radionuchde composition.

non prwedures may be conipilations of pubbshed in reports w here estnnates ot quantities of indi.

standett practices, manu f act uret, instructions that sidual radionuchJes are based on methods other than accompany purchased equipment, or procedures writ direct measurement, an explanation and justification ten by the licensee. Calibration procedurc s should of how the result w as obtamed should be ' included identify the specific equipmeni or group of instru-ihe resuhs of the analysis of the samples for each ments to which the procedures apply.

release pomt should be used to estimate (1) the total to the extent possible, calibrations of measuring pross alpha and gross beta actisity discharged. (2) the equipment should be perf ormed by usmg radioactis e aserage concennatmn of gross alpha and gross beta sources that hase been calibrated by a measurement actr.ity dischaged, and 13 e the total actisity and av.

sy stem traceable to the National llureau of Standardc erage concentrations of each of the radionuclides dis.

radiation measurements sy stem.*

t hagel Cahbranons should generally be perf ormed at reg-3.21 ower 1. unit of Detecnon ular inters als. Frequency of calibration should be based on the stabihty of the system. If appropriate,

'l he lower limits of detection f or analy sis should be equipment may be cahbrated before and alter use in-not more than 10', of the concentranon limits listed stead af at arbitrarily scheduled intersals. Equipment m Table II of Appendn 11 to 10 Cl-R Part 20 For should be recahbrated or replaced wheneser it is sue example, the lower'hmits of detection for soluble pected of being out of adju.tna nt, excessis ely worn, ununum-23s should be not more than 3 < In" mi-or otherwise damaced and not c roc u r ie s per milliliter f or air and 4 - 10 ' mi-operatine properh.

Function tests, i.c routine checks performed Io crocuries per milhhter for byuid-demonstrate that a gnen instrument is in s arkine 11 the actual concentrauons of radionuchdes being condition. mas be performed using sources

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e sampled are known to be lugher than the lower hmits not calibrated by a system traceable to the National of detection indicated abos e, the sampling and analy -

Ilureau of Standards.

procedures need only be adequate to merure the sis actual concentranons. How es er. in such cases, the 4 A Quahty of Results lower hmit 01 detection should be low enouch to ae-A co nuous program ouM be pwpacd and ind commodate fluctuanons in the concentrations of the plementN for ensunng the quahty of results and for c:lluent ng ran m and sy stematic uncertainties to a An acceptable method f or :alculation of lower lim-

"Y* hie procedures dould cosure that the samples are its of de'etoon is described m Appendn A to this

'em&

not attected prior to analy sis because of handimg or 4 Precision and Accurar af Results because of their storage ensironment For example, Equid samples may base to be chenucally treated to 4.1 Random Error present losses to the walls of storage containert 1 or each reported s alue, the tandaJ desianon lests should be applied to analy tical processes, in-should be calculated ;or the randon. error associated cluding duplicate analyses of selected effluent sam-with the analy sis of samples. The calculanon should ples and pericJic cross-check analy ses with inde-take into account all significant ranJom uncertainties, pendens laboratories.

not merely ccunting error. Tl appropriate calcula.

flecause mus h of the data to be reported may be tiens will depend on whelbJr the repor:ed s alue is based on gross radioactn ity measurements, the pro-based on i11 a sinnie coun;. (2) an aserage of counts gram should melude periodic tesis to ensure that such f rom ses cal samples, mne of whhh mas be below measurements represent actual quantities of indi-the lower linut of detecnon, or (3) indirect methods sidual radionuchdes in samples. For exaniple, in

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suc h as cah ulatioas based on gross alpha counts.

pl.mts handhng uranium. a uramum analysis should be performed at least monthly on selected samples for 4._, Sy stematic !.rre r comparison to gross analy sis.

If the analy st estimates that sy stematic errors as-socuted with the analy sis a.e significant relatise to

,t y g g g,,. u g gm, was m.

the random crror, the magnitude of the systemane

% acmem m ommnt i,cus u %, /,m,,, n g f crror shiniid be estimated.

m.'as. Ed 112.rr ' is.1971 O

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5. Hmrting of Results plc, calculation of radionuclide quantities using pross radioactivits meaurementt 5.1 Sampling and Analy sis Results

5. DiscuUion of random and sy stematie error esti-All data should be summarized on a semiannual mates, including methods of calculation and sources ba si s.

"f sy stematic error.

For each release point, the f ollowing should be re-

6. Descriptbn of the calculation of the h>wer limit poned:

of detection.

I. Type of sample tair or liquidi

7. Discussion of the program for ensurine the qual-

2. Samphne location ity of results.

3. Dates dursg which wmples were collected S. Description of calibranon procedures

4. The quantities of grow alpha actisity grow

9. Discussion of any unusual releases, including beta activity. and each radionuclide the circumstances of the release and any data asail-

5. ~lhe aserage concentrations released of grow able on the quantities of radionuclides released alpha actisity. gross beta actn ity, and each

10. The basis f or any determination that a stack or radionuclide liquid release point need not be continuously sam-6 The percentace of the appropriate 10 CFR Part pied 20, Appendn B. Table 11 concentration limit.

The followine sununary should be meluded m each 5.4 l' nits report:

Radionuclide quantnies should be reported in

1. For all airborne releases, the total quantities of cm achonu e conantradons douM be re-cros, alpha at tis ity grow beta actisity ar.d each iadionuchde.

poned in nuaocunes per milliliter (In the Interna-N"""I b "C * "I C"U'

" " "C C4" h

1. I" 2 i or all hquid releases, the total quantitie-of qude

,an oC u riC equJb C 10' M grow alpha actuity, pross beta actisity, and each qumh. and a milliliter equals 10 " cubic meterv )

radionuchde tanhM des iations f or randon; enor ouM be re-

3. For the airborne sample obsersed to coniain poned m the sune units as the result itself. Estimates the hiehest as erage concentrations of radioactisity f or of emahe mor shouM be reponed as a puntage the semiannual period, the contentrations of cross o

e resul alpha at tn its, cross beta acta its, and each radibnuc-

,onuntwion ha W mund the use in

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m lide. along w'nh the percentajes of the appropriate 10 n

of We spaial o.c dehninons for CI R Part 20 Appe nd a B. Table il concentration natural uramum and natural thorium t W 1-R 219W.

limih Repons to the Conunission s! ould une

4. For the liquid sample obsersed to contain the uw un cons nt w nh dus change hiehest.ncrape concentranons of raJioactisity f or the semlannual period. the Ct.ncentrations of crow a!pha 5.5 Signdicant Figures actis ity, crow beta acin ity. and each radionuclide.

. dong with the percentages of the appropnate 10 Cl R Results should not be reported with escewne sig-Part 20 \\ppendis B. lable 11 concentration lunits.

nibcant figures. sut h that they appear inore precise 5.2 Error l stimates than they actuahy are lhe reported estimate of error should contain no mitre than two sienificant fieuret Reported results should alway s indude error esti-The reported result itself should contain the same mates T he standard desianon representmg the ran-number of decimal places as the reported error.

dom error of the analy sis should be reported f or each re sult it significant, an estim ite of the magnitude of 5 3 1.onnat the sy stematic error should be reporteJ separately.

Results reported as below the lower limit of detec-The term 'not detected' or snuilar terms should tion need not include error estimatet llowes er, the neser be used. Each reported result should be a li a salue of the lower limit ot detection shomld be in-salue and its awociated stanJard desiation or (2) an cluded.

indication that the result w as below the lower limit i t detection with the value of the lower limit of detec-5.,$ S.upplemental Inf ormanon tion.

II,e f ollowing information should be included in the first ettluent monitoring report. (Subsequent re-D. Implementation port s should include only changes in tlus inf orma-Lon )

The purpose of thi, section is to prmide inf onna-1 Description of sampling equipment tion to applicants and licensees regarding the NRC

2. Desenption of sampling procedures. including statt's plans f or using this regulatory guide.

sampling times. rates and s olumet Escept in those cases in w hich the aoplicant pro-

3. Description of anal)tical procedures.

poses an acceptable alternalise metho I tor complying

4. Descoption of talculational methods. for exam-with specified portions of the ConunissionN regula-

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tions, the metho.1 described herein will be used in the in.te. eloping submittals f or applications docketcJ on esaluation at. cense applications docketed al'ter or before Nosember 1.1978 the pertinent portions of Nosen:her 1.197S.

the application will be esaluated on the basis of this if an applicant wishes to use tnis regulatory guide guide.

h 157 230 6

4 16-5

Appendix A LOWER LIMIT OF DETECTION 1:or Ine purposes of this guide, the Lower Limit of V

is the sample solume (milliliters);

Deta on (l.LD) is defined as the smallest concentra-Y is the fractional radiochemical yield tion of radicactise material sampleJ that has a 959 (when applicable);

probabilits of being detected. (Radioactise material A

is the radioactne decas constant for the is detected' if it yit.ss an instrunient response that particular radionuclide; and leads the analy st to conclude that activity above the 3r is the elapsed time between sample col-sy stem background is present.)

lection and counting.

l'or a particular measurement sy stem (which :nay The salue of s, used in the calculation of the LLD r

include radiochemical separation):

for a particular measurement system should be based on the actual obsersed sariance of the instrument 4.66 s,,

background counting rate rather than an unscrified I l.D -

theoretically predicted sariance.

3.7 < lO' EVY exp (' A3t>

Since the LI D is a funcoon of sample solume, countine ef ficienes, radiochemical yield, etc., it may w hm vary for different ampling and analy sis procedures Ll.D is the lower limit of detection (mi-Wheneser there is a signiticant change in the crocuries per milliliter;;

parameter < of the measurement sy stem, t he 1.1.D s i, is the standard desiation of the instru-sh"Jo be recalculated

• ment background counting rate (coi -

per second);

• i or a more complete discuoton of the 1.1.l) see H ANI. Pos e.

3.7 IW is the number of disintegrations per Jurm Manual, John 11 Harley. cJitor, t' S ! A partment of second per microcurb.

in f or' Qualitain e I)crettien and Quantilen e I)etermination ~

1:

is the countine ef ficienes (counts per

.sppheanen to R aJ n s he m ni ry. i.w / ( hem. u.! 40 197x.

disintegrationI:

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BlBLIOGRAPHY A N SI N 13.1 - 1969, ' Guide to Sampling Airborne 71,1916 Race Street, Philadelphia, Pa.19103.

Radioactis e Materials in Nuclear I acilities. Ameri-can National Standards Institute, Inc. 1430 llroad.

Energy Research and Deselopment Administration, w ay, New York, N.Y.10018.

' A Guide for Ensironmental Radiological Surseil-lance at ERDA Installations, liRDA 77-24. March ANSI N 13. lO 1974, 'Specitication and Performance 1 y77 of Onsite Instrumentation f or Continuou sly Monitor-ing Radioactisity in E'iluents, American National Ensironmental Protection Agency, ' Sampling and Standards Institute, Inc.

1430 Broadw ay, New Data Reporting Considerations f or Airborne Particu-York, N. Y. LOU IS.

late Radioactis ity. ' ORP.1,V-76 9,197(.

American Society f or f esting and Materials, ' Sam-Ilarley. John II. editor, // ISL /'rocc&er< s lla neal, pling Stacks.or Particulate Matter,' ASTM D292S-Il ASL-300, l'SER DA, res ised annually.

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