Regulatory Guide 4.1: Difference between revisions

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{{#Wiki_filter:1/18/73 U.S. ATOMIC ENERGY COMMISSION
{{#Wiki_filter:1/18/73 U.S. ATOMIC ENERGY COMMISSION
REGULATORY  
                                      REGULATORY
GUIDE DIRECTORATE  
                                      DIRECTORATE OF REGULATORY                                       STANDARDS
OF REGULATORY  
                                                                                                                                                    GUIDE
STANDARDS REGULATORY  
                                                                            REGULATORY GUIDE 4.1 MEASURING AND REPORTING OF RADIOACTIVITY
GUIDE 4.1 MEASURING  
                                                IN THE ENVIRONS OF NUCLEAR POWER PLANTS
AND REPORTING  
OF RADIOACTIVITY
IN THE ENVIRONS OF NUCLEAR POWER PLANTS  


==A. INTRODUCTION==
==A. INTRODUCTION==
(;Geneil Design ('C itein 4i .'o.nitoring Radioactivitv Releases." ol' Appendix A it) 1( ('FR Part 50. "'(Lennd I Desigji ('iteria Ior Nun:leair Power Plants.'requires that licensees provide for mroitioring the plant environs totr radioactivity that may lie released from normal oqperations.
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.


including anticipated operational occurrences, and fion pi!stulated accidents.
environs totr radioactivity that may lie released from normal oqperations. including anticipated operational                                                                        


Subpala, ,rapih tall 2) of § 50.36a of 10 CFR Part 50 requires Ihat technical specifications for each license include a requirement that the licensee submit a report to the * ('tnniissiotn within 60 days after Janutarv I and July I of each year which. iii addition to specifying the quantity of each of the principal radionucides released to unrestricted areas in liquid and airborne effluents duting the last six months of operation,'
==B. DISCUSSION==
provides sitflicient intormation to estimate annual radiation doses W to the public resulting from effluent releases.Paragraph (c) of § 20.106 of 10 CFR Part 20 states that the CoInjIssion nMav limit the quantities of radioactive materials released in air or water duringi a specified period of time to assure that the daily intake of radia ctive materials from air. water. or food by a suitable sample of all exposed population group.averaged over a time period not exceeding one year.would not exceed specified quantities.
occurrences, and fion pi!stulated accidents.
 
Section 20.201 of 10 CFR Part 20 further requires that a licensee conduct surveys of levels of radiation or con1centrations of radioactive itaterial as necessary to show compliance with AIC regiulatioims."riis ginde describe., an acceptable basis for designing a progrant to measture and report levels of I At, :acct-t:M,-i" pr,-grti is preseunt.l its saref v (.;tide 2 I (to)he re sitsed :,%; : Regtla, try Gttide). "M ,: avurini and I~ttep rling (fo Effluents frillr Ncttc'i:r llnwer Narls.'radiation and radioactivity in the plamt environs.


The provisions and principles in International (Commoissiotn on Radiological Protection (I('RI'l)
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.
P ulicanion
7-pertaining to the releases of radioauctivitv during ornmal plant operation should be used as additional guidance in developing a program of this nature.


==B. DISCUSSION==
sitflicient intormation to estimate annual radiation doses to the public resulting from effluent releases.
Present requirements to keep levels of radioactive material in effluents as low as practicable should assure that radiation doses to the puhlic resulinig front efflutent releases will continue to retnain mninimal.


The type of program described in this guide is considered adequate to provide information needed to determine whether exposures in the environment are within prescribed or expected limits and to assure that long-term buildup of specific radionuclides in the environment will not become hazardous.
W
                                                                                                        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.


A preoperational program should be conducted in the environs of cach proposed nuclear power plant site to: (I) identify probable critical'
suitable sample of all exposed population group.
pathways io be monitored after the plant is in operation:
(2) measore background levels and their variations along the anticipated critical pathways in the area surrounding the plant. (3) train personnel" and (4) evaluate procedures.


equipment, and techniques.
equipment, and techniques.


Years of experience at various Contitnissitt facilities have demonstrated that specific radionuclides behave in known ways under given environtmental cottditions.
averaged over a time period not exceeding one year.
 
Therefore.
 
comprehensive and detailed envitonlmenial studies may not be needed at sires wiilh well known t C R P ublication
"7. Iroin4 p! t'" h'id' ,'rt,o 'tlI.Io,,itoring Related to thie' Il otdlhig of R idi., t'ti t .1" 1,al riIt
 
===9. Septemher ===
13. 196S t(henrenin rir It.'RI' I'Ltsicali ,tt I7.t iF r the p ors've orf this. guite. thie Ierni "crilicar"t tit lit, same meaning as in t'RIt t'uhblication
7. Sipra niote
 
===2. USAEC REGULATORY ===
GUIDES ResfutAiorv Guide, Wi'. 1su"nf It' dtecr''ts amit flt~i't oAV.,Ihhtt In the p~ublic meiohorb.
 
Acc-titabl- lto the AEC stioclinoirs'taff of mtSiirmoni,roo
%s~eci'c patrts of'he Cnmm-n',s~
e.I55 to doiti-.1ie to-chnoriurs used hy the staff in"aWAiiung S1 s*f14 W911f9.'tthi Of9 tnSIUtSi'd a~ccidenrim of Is isoisvde 9lwdaneem to With thf-fsitt A '995! Itjit.'ti Mi 'h-c A", soloot-9'5 dii etenl friom those set Dor o the gui~de, i to"I beAcmteilef
-1 tt't'v p'ovide i ti.1t9% 1(5 the finings d flt9rlufsoi In ihm. issuane" ot cont~nUAA9CP'
Of .. pe~m9o is' teens't, the 95'Cnmmosvo'
Putftshpcj i qud$S.lit
~t~s~ ~ ,rti, 01Il 4199t' coI9or.91.'
In iro-iwrnrcommodi.'
..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 ir19ifovenerflts int these quidei are en'couraged And %thisuit he lenti t) ihes" 5'c~fiatv of the Commissuions.
 
US. Atomic EnetfgY Commisitn.
 
W.Iihinaroin, D.C. 21if"45.Aifent,nn:
Chief. Public Peooceed-nos Sitaf.The g,,.des ate issu~ed in itshe fotlhvittg tenr btirnd rss 1. Pow~er Reactor% in'. P,oducis 2. Research And Test Reiclto.'
7. Itasnsttimti"" J. Fuels And Mate.'3s Fscdmtm' B. orrciur.1iOn'si
9-J..111t 4. Environmintat and 5,5mm ' Anf-l'usl RteW,~5. Material%
A"tS'ii Pitotwe'rs'etiof
10) 6--M~s S
bleu1vJirlon1etal nrsport process".
Onc( e adequate sttudies have been done to assure that the tratisport processes are understood.
 
analyses otC "indicator organiis'ns may adequately define radiotuclide levels in tile envirtomnent.
 
The "'indicator orLalnis1t" concept of'environmental samplinl"g involves tile practice o I examining food chainls for selecied orga;nisins o0r materials which provide a sensitive and reliable mneatsure t' (lhe uti:Uatites of' eac'h (adiolluclide cycling throught each lood chaint. For example. ill the case where the plaitt'cow,'nilk-nian food chain is determined to be a critical palthway, it may not he necessar Ito extensively sample anld illeasure grazing plants :mnd f'odder to keep tliack of iodine-I 3l cycline in fhle food chain. sihce sampling and nieastiring tile milk produced by dairy cow\s in stirrotndine areas may be :dequate.At'ler the plant is iii operationt.
 
a program for radiation levels and radioactivity in the plant environs manst he maintained on :a cOnlintlilln basis to assist in verilt.,ing projected or ariicipated radioactivi
1v concentrations and related public exposures.
 
An entvironu ental tnonitoritng program shotld be flexible.aid, as results are obtained.


tihe prograni should be reviewed to identil'y any\ necessary changes. The progra n shuhld then be appropriately nodified.
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.


The initial pttogram should be designed in accordance vith the followinug criteria: I. It should be based on the pathwayIs for the types radionuclides released froni stlrtoundine envi rotinten I analysis of" critical and quanlities of the plant into the radioactivity in the environs may all be useful for this purpose.)
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
Inifornation of' this nature will be of considerable help1 in inodil ying t[ie initial lnvilonllillental ti easure tut.nts program.hil'orimalion obthaied f'ront this programn will le insed. in conjuintetion with data oil radioaclive effluents.
          "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.


to evaluate mneasulres taken by 'ite licensee to assure that plantt releases to the environt1ient and radiation doses to the public are mailntinel wvitlhii the numerical dose limits determined by the Commission io be as low as practicable.
Septemher 13. 196S t(henrenin rir It.'RI' I'Ltsicali ,tt I7.


Also. licensees'  
I At, :acct-t:M,-i" pr,-grti is preseunt.l          its saref    v (.;tide 2 I (to)
data will be compiled andi co III pared. and a comlrprehlensive stimitiray ii 1'radioactivity in thle enivirons of nuttclkear power plants will be prepared by tlie Coimmission.
                                                                                                        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.


'[e Commission's Regulator.'
USAEC REGULATORY GUIDES                                            Copiei of oublishpil gui&ns m'sv be ObtainedI iv 10ourst .rsdic.lting ihe division%
siarf has evaluated the types of fitforination needed to provide supporting evidence for assessing tile pert'ormance of 'he plant witli respect to keeping populatnit exposures as low :is practicable and to verify predictions of concentrations ohI speciflic radiontiucl ides in lie environment based ott effluent iieasurements at the plant. Based on 1his evailtation and oil a review and assessment of' existline licensees'
                                                                                                desired io the US. Atomice EitefqV Commtttsi~to, VY-shIM9is..                    D.C. 20Ob45.
monitoring anid reporli g prograins.


ihle s:tlt'has developed tile regulatory position set forth belo'v.C. REGULATORY
Attention: Director of Regultfory Siend~itds. Cofnrmwnis Anil wrgoo'sions tot ResfutAiorv Guide, Wi'. 1su"nf It' dtecr''ts 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
POSITION The proerani for nieasuring attd reporting clf radioactivity ill the environs ofi nuclear power plants must provide suitable inf'rs:auion from which levels of radiation and radioactivity in the environs of each plait carl be estimated.
  '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.


This inlfornation also may provide supporting evidence in evaluating tie perforniance of systems and equipment installed to control releases of'radioactive material it) tile environnenw.
Aifent,nn: Chief. Public Peooceed-nos      Sitaf.


The basic principles set forth in this guide constitute an acceptable basis tor use in establishing an en viro ini ental Imonitoring program. These sane principles will also b: used as bases in developing the licensee's corresponding technical specifications.
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.


1. Preoperational Program Potential critical pathways should he idemifiied prior to plant operation.
Putftshpcj i qud$S.lit  01Il              ~ ,rti,
                                ~t~s~ coI9or.91.'            4199t'    iro-iwrnrcommodi.'
                                                                            In              ..
                                                                                                  5.


l';,e provisions in ICRV FPtlblicaiion
Environmintat and 5,5mm Material%A"tS'iiPitotwe'rs'etiof
7 rela ted to operational releases of radioactivity to the environm-nt should be used as a guide in determining critical radionuclides and pathways.Other patlhways not directly related to humans should also be identified (see regulalory position 2.a. below).Wherevet possible.
                                                                                                                                                  '      Anf-l'usl RteW,~
                                                                                                                                                    10) 6--M~s


suitable indicator organisms or media should be identified in each pathway.2. Operational Program a. Sample Media Where practical.
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.


a suitable indicator organisin or ttedium in each critical pathway should be sampled 2. It sihould consider tile possibility of buildup of long half-lived radiominclides in the environment and identify physical and biological sites of acctmniutlationt that ntaty contribute to huniani ex\posures:
tile envirtomnent. The "'indicator orLalnis1t" concept of'
3. It should be designed to facilitate use of reported levels of radiation and radioactivily in estimating annual radiation doses to tle public resulting froit effluents:
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.
4. It should consider the potential daimage to itttpot tant plants :mud arimals:'a i. It should be designed to establish correlations between levels of radiation atid radioactivity in the environment and radioactive releases front plant Operation. (A variety of lechniques.


including measurements at control locations.
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.


preoperational surveys. correlations with effluent data, and comparisons of operating versus shutdown levels of'-A species. wthethe'r ainin ,tor plant is' "irnport:nlt'" (I) Kit is t'-nimeu 'rciatlv or r.creaLit ally vaitiau:tule.
cow\s in stirrotndine areas may be :dequate.


(2) if it is rare ir e~ndanlge~red.
'[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.


r 3) if ir t :iffect% thLe' ,vll-te.ing
pttogram should be designed in accordance vith the followinug criteria:                                                                                 
'it stoF¢ importanIwiethin criteri: (I) and (2) ahiivc or (4) if it is critical to fit! structure and function (if (ht ¢crtiogical system. A "rare our endulangetred" species is any species cufficiatty tiesignated as such hb the 1).S. Hih and wildlife Service.4.1.2
:and analyzed for the critical iado mliclidels?
released from the plant. An abundant, readily available form with nowt habits should be selected.* Careftul attenttioni should ble given to avoid insdt(tLSng serious stress onl art ihm portan't species otf organism by a samipling program. Heavy sampling pressure added to natural prcdaliun and other elvironitSelillal stiesses could restil I in tenpora ry obliteration of desirable potpulations.


In stich cases.other indigenotts hut al mnda n spcies souch as rodents.rabbits or scrap lish. mayl be stilistituted as indicator org:antisms IthatI vill provide an estimate of the radionuclides avai.lable to main through natiral f'ood chains. In some instatnces.
==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.


prop,!rly selected and sampled vegetam 11my 'list) provide a good imteaslie of the radionuclides in , critical FpatlIway.
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.


WhcLtre use of a single indicator tneditim is impractical.
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.


samples of' several media from each pathway should be collected and analyzed.
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.


The C(ommission recomizes that some pathways do not have more than olne eiviromnittillal meditiht.
===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
                                                                              4.1.2


c... external radialion exposures from clotds of uatnima-ray-emittitog radio-nclides inlvol-..  
:and analyzed for the critical iadomliclidels? released                          Ilt sotmie cases. sat ll)lingll t.1
onlV onle paithway the atmosphere.
* 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.


The actual tit:uhier of' media it he sampled in each pathwlay will be determined oni a case-by.case basis for each site. Itt some cases field measurements may be prelerable to collecting samples for laboratory analysis.O The program should include sampling of environmental media to estimate average radionuclide concentrations in important biota (see B.4. above).Radiation exposures (external)
*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.
and internal doses from short half-lived nuelides may be estimated by calculationrs
(,tisin g e[floeii mn easuremen ts and appropriate dispersion and concentration factors) rather[han by routine collection of samples of environmental media. In some cases field measurements at certain locations to establish cotcert t rations of specific radionucl ides may be necessar".
initially.


to confirm predictionls.
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.


h. Sampling Frequency When a critical radionuclide has a short hallflife Imtinutes to days). it may be necessary to evaluate radiation expUsure by tuaking measurements in the field (e.g.. by use of thermoluminescen t dosimeters or portable multichannel gamma spectrometers).
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.
When ;I critical radionuclide with an internnediate half-life (weeks to months) is released continuotisly or frequently.


sampling and analysis of etvirotlneinial media in the critical pathway should generally be carried omt at inltervals no greater than two or 'h ree half-lives of tIte iuclide. For long half[liife
radionuclides in , critical FpatlIway.
.dionuclides (years). measurements should be made at st once per year. Where seasonal eflects ,ay be important.


sampling should be on a quarterly or at least semiannual basis.Ilt sotmie cases. sat ll)lingll
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.
.1 t ll illttitous b:sis may be necessar\ (e.g.. air samttplinig and co,]ItitIotIs mile astire ie Illt f. c u ttInlaIive exterit1al
,:dia, it in exposure).  
Composites of some selected s:aiple types.such as air filters. niav be appropriate I'm" meastmrettiettt ot long-lived madi nit ticlides.When critical pathlways become firmdly identified awtd correlations are developed between concentraiJuis of radionuclides itt einvirontm.entaml media anid planlt releases, or level, have been iotind too' low to detect. it is probable tltat saripling frequte .,cies ot'ccittil media irmay be apprli mriaiel " iticreased or decreased.


Such chan6ges shtIould onlyl he titade on itidividual paOwer plants after considerable
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.
'peraliotlal experienlce Ilsa accrued.c. Program Scope During (hft initial three years of commercial power operation (or other period corresponditie to maximum fuel burnup it] the initial core cycle). tihe mecastirememti program shotuld be relatively c11muipre- nensive in an attempt to verify anys'
torle-lations between radioactivc eflltuilts attd levels in environtmental media. The extetnt of measturettent of environnmental media should be flexible and should depend on the type. quantity.


and concentration of radionuclides from the plant as well as the results obtained from previotus nmeasurements.
obtained from previotus nmeasurements.


1f. after this period. the licensee is able to demonstrate from levels in environutetumal media or calculations (using measured effluents and appropriate dispersion and bioaccumulation factors) that the doses from a particular pathway are sufficiently small, the number of media sampled in the patlihway and the frequency of sampling may be reduced. An adequate program wiln i emphasis m ml indicator o rganisins and selected media should still be continued in order to con firm that the levels of radioactivity in environmten tal media remain small.d. Analyses Samples should he analyzed for the critical radionticlide(s)
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
released from the plani. (Gross belta and gainnia analyses of samples stuch as air and fresh water may be useful to indicate that the concenltralioni of a critical radionuclide is not greater thall the delectioll capability for that nuclide.3. Detection Capabilities The detection capabilities associated with ,1,eaisiritmg and atinalvzitt radioactivity levels shotild he eSltablished primarily on the basis of poleittial hutnatt dose. The least detectable dose will vary from facilitvy to facility depending on the critical pathways ideI iifled arm d IItC stalof-tl'-he-art of sampling and analysis in these pathways.


Because of tie need for a preoperational monitoring program, detectiot capabilities for a 4.1-3 W pat tcular piorat11 should he deternmined during :n early staLc of licensing.
====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.


The staff rc,.ognizes that direct tmeeas uremtetn ts of envirotnml enltal Imredia cannot1 alvays'cet ct levels lruepo -dine to Commissiti design , Iieclites.
predictionls.


Nevertheless.
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.


every reasonable effort should be made to achieve detection capabilities which will dewclt ratdiition levels or radioactiVity I ol0cent-rat ions ill critical pathways that could result in radiatiom doses cor respudindg to a 11ew 1'ercen t of thie Federal Radiation (',tmcil's radiation protection guides Ie.g.. a ftw percent i! !70 mren'years for whole body dose to a stiiable-ample tithe exposed population
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
).4. Reporting of Results Data sholtld he reported to the Commission in the r..,ort suhmitted within t,-0 days aflter January I and July I of each year.' InI the eveut that all unexpected mclea,ýe iln radjoaCtivMI
. 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
or r:diation levels is measured in a p-Mricular critical pathway. the Commnission should he not, fied prontptl..
    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
Appropriate levels and reporting inetvals will he determined on an individual plant basis and included in the technical specifications for each license.The Commission utilizes the data from these reports to provide assurance that man and his environment are not heinu subjc,:ted It unacceptable radiation exposures.
                                                                4.1-3


Consequently.
W
  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.


all assumptions.
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.


parameters and methods used to measure and report radioactivity concentrations and radiation levels should be specified in the licensee's initial report aid updated in subsequent reports as s t-'d,.at Radiatiiin Councit Report No. I. bIac'kgroutnd.llawrnelkr th'e" Dere'ml-Fea t '',.RadiathOn Pro'tetion Srandards.
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.


Ia J3. 19 h (.";uhpalragraph (a)(2) of (,f 1o C0 R Part 50 requites the subtinjsimi or a report within ot, d-'s after Jainuary I :ie-d Jul ' I i f eacit )'ear speciriflin the quantitv of eac lih o t .prin` iial radimiuclidts released lto unrestricted areas in liquid andll in g'awous erffenlt%.  
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.).
the duta taken in suppnrt of the lite'i.ee'" en.-iroiitnential monitoring programn shriuld also he ,,jonmia ltd s;emiannually.
  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.


Ir additional lime is needed, the repnrt.sit; indicane :md the shoulJ he carried into the Io'et ,emiannua:ll report. it would greatl, r:ocililgte comparismns rnd 7.'ierrlaitil ot t ta if the en
IaJ3. 19 h (.                                                                    
3ind effluent niaiateirilg dat.a m.ere .mnihtited ilnto single reports.alpprolri:e.


Trie licensee should demtostiale that aill assutittiolts.
====g. Background Value====
                                                                                                                        7


parameters and methods, used are adcqumtte and compiele Ito allow Itwhere data pertii) a c omparison
====h. Analytical Method====
, with predicted concei.ratitms and doses based ol effluents from each nuclear power plant under license.(See Safety (uide 21).To petlmit comparison of signi'icart entvironmental mIolnitoritng data willh predicted eoncent ratiotls anid doses (bhaid on reluiretletts ol' I0 CFR Part 50). the report should include Ilie following i tents for each tttedii: :1: a. Samnple Type I. Biological (it tile extent practicable.
        ";uhpalragraph        (a)(2)   of  *50.3fia  (,f  1o C0 R Part 50
                                                                                            j. Comparison of Observed Concentrations.


list specics. life' stage. age. weight or size. biolog.ical conditiot, tissue or m1terial sampled. sample weight.etc.).2. Non-Biological (identify type -soil, air.etc.: list actual area. depth and weight or volume sampled as appropriate, whether grab or continuous sample. number of samples. etc.).b. Sample Localtion (also !tipply mtap showing locations)
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)
c. Collection Period (continuous samples) or Dale of Collection d. Critical Pathway e. Radionuclide f. Concentration (mCi/ml or g. specifying wet or standard dry. weight) and/or Deposilion (jiCi/mh ori other apprupriate units of tteastire). (List conversionti, factors relating sample activity and volume -depth X cross section -It) total area deposition:  
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
average and ttlaXIillttt values (for each medium. etc.)g. Background Value h. Analytical Method 7 j. Comparison of Observed Concentrations.
,,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.


Depositions and Estimated Doses with Predicted Values (based on effluent measurenments)
O0
j. Remarks (be sure to explain any tititstal measurements or deviations).
                                                                                4.1.4}}
'I .stim-mtes i)f the error assoeinted with the: measurement of each environmental medium should he reported.O0 4.1.4}}


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Revision as of 10:24, 4 November 2019

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.

W

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

4.1.2

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

4.1-3

W

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

4.1.4