Regulatory Guide 4.1: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 1: Line 1:
{{Adams
{{Adams
| number = ML003739496
| number = ML13350A200
| issue date = 04/30/1975
| issue date = 01/18/1973
| title = Programs for Monitoring Radioactivity in Environs of Nuclear Power Plants
| title = Measuring and Reporting of Radioactivity in the Environs of Nuclear Power Plants
| author name =  
| author name =  
| author affiliation = NRC/RES
| author affiliation = US Atomic Energy Commission (AEC)
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-4.1 Rev 1
| document report number = RG-4.001
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 4
| page count = 4
}}
}}
{{#Wiki_filter:U.S. NUCLEAR REGULATORY
{{#Wiki_filter:1/18/73 U.S. ATOMIC ENERGY COMMISSION
COMMISSION  
REGULATORY  
REGULATORY  
GUIDE OFFICE OF STANDARDS  
GUIDE DIRECTORATE
DEVELOPMENT
OF REGULATORY
REGULATORY  
STANDARDS REGULATORY  
GUIDE 4.1 PROGRAMS FOR MONITORING
GUIDE 4.1 MEASURING
RADIOACTIVITY  
AND REPORTING
OF RADIOACTIVITY
IN THE ENVIRONS OF NUCLEAR POWER PLANTS  
IN THE ENVIRONS OF NUCLEAR POWER PLANTS  


==A. INTRODUCTION==
==A. INTRODUCTION==
General Design Criterion
(;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.
64, "Monitoring Radio activity Releases," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Licensing of Production and Utilization Facilities," requires that licensees provide means for monitoring the plant environs for radioactivity that may be released from normal operations, including anticipated opera tional occurrences, and from postulated accidents.
 
including anticipated operational occurrences, and fion pi!stulated accidents.


Paragraph  
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,'
20.106(e)
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.
of 10 CFR Part 20, "Standards for Protection Against Radiation," provides that the Commission may limit the quantities of radioactive materials released in air or water during a specified period of time to ensure that the daily intake of radioactive materials from air, water, or food by a suitable sample of an exposed population group, averaged over a time period not exceeding one year, would not exceed specified quantities.


Section 20.201 of 10 CFR Part 20 further requires that a licensee conduct surveys of levels of radiation or concentrations of radioactive material as necessary to show compliance with Commission regulations.
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.


This guide describes a basis acceptable to the NRC staff for the design of programs for monitoring levels of radiation and radioactivity in the plant environs.
The provisions and principles in International (Commoissiotn on Radiological Protection (I('RI'l)
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==
==B. DISCUSSION==
Present requirements to keep levels of radioactive material in effluents as low as practicable (as specified in 10 CFR §50.34a) should ensure that radiation doses to the public resulting from effluent releases will continue to remain minimal. The principles presented in this guide are considered an acceptable basis for establishing preoperational and operational monitoring programs to provide information needed to determine whether ex posures in the environment are within established limits and to ensure that long-term buildup of specific radio nuclides in the environment will not become significant.
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.
 
A preoperational program should be conducted in the environs of cach proposed nuclear power plant site to: (I) identify probable critical'
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.
 
Years of experience at various Contitnissitt facilities have demonstrated that specific radionuclides behave in known ways under given environtmental cottditions.
 
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 preoperational program should be conducted in the environs of each proposed nuclear power plant site to (1) measure background levels and their variations in environ'mental media in the area surrounding the plant, (2) evaluate procedures, equipment, and techniques, and (3) provide experience to personnel.
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.


Years of experience at various Atomic Energy Commission facilities have demonstrated that specific radionuclides behave in known ways under given "environmental conditions.
An entvironu ental tnonitoritng program shotld be flexible.aid, as results are obtained.


Therefore, analyses of "indi cator media" can be used to define radionuclide levels in the environment.
tihe prograni should be reviewed to identil'y any\ necessary changes. The progra n shuhld then be appropriately nodified.


The "indicator medium" (or organism)
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.)
concept of environmental surveillance involves the sampling of organisms and media which are sensitive and reliable measures of the quantities of individual radio nuclides cycling through pathways.
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.


For example, where the plant-cow-milk-man food chain is determined to be an important pathway, it may not be necessary to extensively sample and measure grazing plants and fodder to keep track of iodine-131 cycling in the food chain, since sampling and measuring the milk produced by dairy cows in surrounding areas may be adequate.
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.


After the plant is in operation, a program for measuring radiation levels and radioactivity in the plant environs must be maintained on a continuing basis to assist in verifying anticipated radioactivity concentra tions and related public exposures.
Also. licensees'
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.


The initial pre operational and operational monitoring programs should be designed in accordance with the following criteria:
'[e Commission's Regulator.'
1. They should be based on the analysis of important pathways for the anticipated types and quantities of radionuclides released from the plant into the surround ing environment;
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'
USNRC REGULATORY
monitoring anid reporli g prograins.
GUIDES Comments should be sent to the Secretary of the Commission.


U S Nuclear Regulatory Commission.
ihle s:tlt'has developed tile regulatory position set forth belo'v.C. REGULATORY
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.


Washington.
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.


0 C. 20656. Attention Docketing and Regulatory Guides are issued to describe and make avareble to the public Service Section methods acceptable to the NRC stall of implementing specificý
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.
parts of the Commission's regulations, to delineate techniques used by the staff in evalu The guides are Issued in'the following ten broad divisions.


sting specific problems or postulated accidents, or to provide guidance to appli cants Regulatory Guides are not substitutes tor regulations.
1. Preoperational Program Potential critical pathways should he idemifiied prior to plant operation.


and compliance I Power Reactors 6 Products with them is not required Methods and solutions different from those set out in 2 Research and Test Reactors 7 Transportation the guides will be acceptable if they provide a basis for the findings requisite to 3 Fuels and Materials Facilities
l';,e provisions in ICRV FPtlblicaiion
8 Occupational Health the issuance or continuance of a permit or license by the Commission
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.
4 Environmental and Siting 9 Antitrust Review Comments arid suggestriiis for improvements in these guides are encouraged
5 Materials and Plant Protection
10 General at all times and guides will be revised as appropriate, to accommodate corn ments and to reflect new inflrtmation or experience However. comments on Copies ot published guides may be obtained by written request indli am 9 the this guide. if received within about mwo rioniths after irs issuance will be par divisions desired to the U S Nuclear Regulatory Commission Washington
0 C ticularly useful in evaluating the need for ad early revision 206555 Attetion Director Office of Standards Development Revision 1 April 1975
2. They should consider the possibility of buildup of long-lived radionuclides in the environment and identify physical and biological sites of accunrulation that may contribute to human exposures;
3. They should conside'r the potential radiation ex posure to important plants and animals;1 4. They should be designed to establish correlations between levels of radiation and radioactivity in the environment and radioactive releases from plant opera tion. (A variety of techniques, including measurements at control locations, preoperational surveys, and com parisons of operating versus shutdown levels of radio activity in the environs may all be useful for this purpose.)  
Information of this nature will be of consider able help in modifying the initial environmental measurements program.


Data obtained from this program should be used by the licensee to show that environmental levels are consistent with those determined from the effluent radiation monitoring and sampling program. The latter program is used together with dispersion estimates to ensure that plant releases to the environment and radiation doses to the public are maintained within the numerical design objectives determined to be as low as practicable.
suitable indicator organisms or media should be identified in each pathway.2. Operational Program a. Sample Media Where practical.


The Commission's staff has evaluated the types of information needed to provide supporting evidence for assessing the performance of the plant with respect to keeping population exposures as low as practicable and to verify predictions of concentrations of specific radionuclides in the environment based on effluent measurements at the plant. Based on this evaluation and on a review and assessment of existing licensees'
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:
monitoring and reporting programs, the staff has de veloped the regulatory position set forth below. C. REGULATORY
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:
POSITION The program for monitoring radioactivity in the environs of nuclear power plants should provide suitable information from which levels of radiation and radio activity in the environs of each plant can be estimated.
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.


1A species, whether animal or plant, is "important" if a specific causal link can be identified or hypothesized between the nuclear power plant and the species and if one or more of the following criteria applies: (I) the species is commercially or recreationally valuable, (2) the species is threatened or endan gcred, (3j the species affects the well-being of some important species within criteria (1) or (2), or (4) the species is critical to the structure and function of the ecological system or is a biological indicator of radionuclides in the environment.
including measurements at control locations.


A threatened or endangered species is any species officially designated as such by the Secretary of the Interior or the Secretary of Commerce.This information also may provide supporting evidence in evaluating the performance of systems and equipment installed to control releases of radioactive material to the environment.
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.


The basic principles set forth in this guide constitult an acceptable basis for usc in establishing an environ mental monitoring program. These same principles will also be used as bases in developing the licensee's corresponding technical specifications.
(2) if it is rare ir e~ndanlge~red.


Guidance mi (tle format, content, and preparation of Appendix B envi ronmental technical specifications for operating licenses is presented in Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants." i. Preoperational Program A preoperational monitoring program should be initiated two years prior to operation to provide a sufficient data base for comparison with operational data and to provide experience that will improve the efficiency of the operational program. It may not, be necessary for all media in the preoperational program to be sampled for the entire two-year period; i.e., for those media sampled frequently.
r 3) if ir t :iffect% thLe' ,vll-te.ing
'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.


a six-month or one-year period is usually sufficient.
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.


However, if the sampling period. is not representative, because of abnormal con ditions, the period may require extension until repre sentative samples are obtained.
prop,!rly selected and sampled vegetam 11my 'list) provide a good imteaslie of the radionuclides in , critical FpatlIway.


2. Operational Program Generally, the operational program should be an extension of the preoperational program to ensure that data from the two programs are compatible and that a smooth transition between programs is achieved.
WhcLtre use of a single indicator tneditim is impractical.


a. Sample Media Where practical, a suitable indicator medium or organism in each important pathway should be sampled and analyzed for the plant-contributed radionuclides released to the environment.
samples of' several media from each pathway should be collected and analyzed.


When sampling organisms, an abundant, readily available species with known habits should be selected.
The C(ommission recomizes that some pathways do not have more than olne eiviromnittillal meditiht.


Careful attention should be given to sampling programs to avoid inducing serious stress on populations of important species. Sampling of large numbers of organisms could result in a temporary decline or permanent loss of desirable populations.
c... external radialion exposures from clotds of uatnima-ray-emittitog radio-nclides inlvol-..
onlV onle paithway the atmosphere.


In such cases, other indigenous but abundant species should be substi tuted as indicator organisms to provide an estimate of the radionuclides available to man through natural food chains. In some instances, properly selected and sampled vegetation may also provide a good measure of the radionuclides in a pathway.4.1-2 Where use of a single indicator medium is impracti cal, samples of several media from each pathway should be collected and analyzed.
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)
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.


The Commission recognizes that some pathways do not have more than one environmental medium; e.g., external radiation expo sures from clouds of gamma-ray-emitting radionuclides involve only one pathway -the atmosphere.
to confirm predictionls.


The actual number of media to be sampled in each pathway should be determined on a case-by-case basis for each site. In some cases, field measurements may be preferable to collecting samples for laboratory analysis.
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).
When ;I critical radionuclide with an internnediate half-life (weeks to months) is released continuotisly or frequently.


The program should include sampling of environ mental media to estimate radionuclide concentrations in important biota (see B.3 above). Radiation exposures (external)  
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
and internal doses from short-lived nuclides may be estimated by calculations (using effluent measurements and appropriate dispersion and bioaccu mulation factors) rather than by routine collection of samples of environmental media. In some cases, field measurements at certain locations to establish concentra tions 'of specific radionuclides may be necessary, initially, to confirm predictions.
.dionuclides (years). measurements should be made at st once per year. Where seasonal eflects ,ay be important.


b. Sampling Frequency When a radionuclide has a short half-life (minutes to days), it may be necessary to evaluate concentrations or radiation exposure by making measurements in the field (e.g., by use of thermoluminescent dosimeters, pressurized ion chambers, or- in situ gamma spectro meters).
sampling should be on a quarterly or at least semiannual basis.Ilt sotmie cases. sat ll)lingll
When a radionuclide with an intermediate half-life (weeks to months) is released continuously or fre quently, sampling and analysis of environmental media in the associated pathway should generally be carried out at intervals no greater than two or three half-lives of the nuclide. For long-half-life radionuclides (years), measurements should generally be made at least once per year. Where seasonal or other temporal variations may be evident, the frequency of sampling should be planned to allow resolution of any important effects.
.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.


In some cases, sampling on a continuous basis may be necessary (e.g., air sampling and continuous measure ment of cumulative external radiation exposure).
Such chan6ges shtIould onlyl he titade on itidividual paOwer plants after considerable
Composites of some selected sample types such as air filters may be appropriate for measurement of long-lived radionuclides.
'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.


c. Program Scope During the initial three years of commercial power operation (or other period corresponding to maximum fuel bumup in the initial core cycle), the measurement program should be relatively comprehensive in an attempt to verify any projected correlations between radioactive effluents and levels in environmental media.  The extent of measurement of environmental media should be based on the type, quantity, and concentra.
and concentration of radionuclides from the plant as well as the results obtained from previotus nmeasurements.


tion of radionuclides expected from the plant as well as the results obtained from previous measurements.
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)
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.


If, after this period, the licensee is able to demonstrate from levels in environmental media or calculations (using measured effluents and appropriate.
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.


dispersion and bioaccumulation factors) that the doses and concentrations associated with a particular pathway are sufficiently small, the number of media sampled in the pathway and the frequency of sampling may be reduced. An adequate program with emphasis on indi cator organisms and selected media should still be continued in order to confirm that the levels of radioactivity in environmental media remain small.  Results from all individual measurements should be retained by the licensee along with information on sampling location and date, sample size (e.g., wet/dry weight), sampling and analytical procedures, units of data presentation, and precision and accuracy associated with individual measurements.
The staff rc,.ognizes that direct tmeeas uremtetn ts of envirotnml enltal Imredia cannot1 alvays'cet ct levels lruepo -dine to Commissiti design , Iieclites.


Explanations of anoma lous measurements should be provided.
Nevertheless.


d. Analyses Samples should be analyzed for plant-contributed radionuclides released to the environment.
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
).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
or r:diation levels is measured in a p-Mricular critical pathway. the Commnission should he not, fied prontptl..
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.


Gross radio activity measurements alone are generally not adequate for radiological monitoring.
Consequently.


However, gross radioactivity measurements may be useful to indicate the concentra tion of a specific radionuclide when such measurements are shown to be truly indicative of the actual quantity or concentration of that radionuclide.
all assumptions.


e. Quality Control Control checks and tests should be applied to the analytical process by the use of blind duplicate analyses of selected samples and by cross-check analysis of selected samples with an independent laboratory.
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.


Quality controls should also be applied to the entire sample-collection procedure to ensure that representa tive samples are obtained and that samples are not changed, cross-contaminated, or otherwise affected prior to their analysis because of handling or because of their storage environment.
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%.
the duta taken in suppnrt of the lite'i.ee'" en.-iroiitnential monitoring programn shriuld also he ,,jonmia ltd s;emiannually.


3. Detection Capabilities The detection capabilities associated with measuring and analyzing radioactivity levels should be established primarily on the basis of potential human dose. These detection capabilities will vary depending on the instru ,mentation and analytical techniques used. Because of the need for a preoperational monitoring program, 4.1-3 detection capabilities for a particular program should be determined during an early stage of licensing.
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
3ind effluent niaiateirilg dat.a m.ere .mnihtited ilnto single reports.alpprolri:e.


Every reasonable effort should be made to achieve detection capabilities that will detect radiation levels or radio activity concentrations in pathways that could result in radiation doses corresponding to a few percent of the Federal Radiation Council's radiation protection guides (i.e., a few percent of 170 mrem/yr for whole body dose to a suitable sample of the exposed population).
Trie licensee should demtostiale that aill assutittiolts.
2 Similarly, the detection capability, of environmental measurements should be the most sensitive that is practicably achievable for measuring plant-contributed radionucides in the environment.


'Federal Radiation Council Report No. 1, Background Material for the Development of Radiation Protection Standards, May 13, 1960. UNITED STATES NUCLEAR REGULATORY
parameters and methods, used are adcqumtte and compiele Ito allow Itwhere data pertii) a c omparison
COMMISSION
, 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.
WASHINGTON, D. C. 20M65 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300


==D. IMPLEMENTATION==
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)
The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for utilizing this regulatory guide. This guide reflects current regulatory practice.
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:
average and ttlaXIillttt values (for each medium. etc.)g. Background Value h. Analytical Method 7 j. Comparison of Observed Concentrations.


There fore, except in those cases in which the applicant proposes an alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used in the evaluation of submittals for operating license or construction permit applications docketed after the date of issue of this guide. If an applicant wishes to use this regulatory guide in developing submittals for applications docketed on or prior to the date of issue of this guide, the pertinent portions of the application will be evaluated on the basis of this guide.  POSTAGE AND FEES PAID UNITEO STATeS NUCtEAR REGU.A ORY COMMISSION
Depositions and Estimated Doses with Predicted Values (based on effluent measurenments)
4.1-4}}
j. Remarks (be sure to explain any tititstal measurements or deviations).
'I .stim-mtes i)f the error assoeinted with the: measurement of each environmental medium should he reported.O0 4.1.4}}


{{RG-Nav}}
{{RG-Nav}}

Revision as of 19:57, 12 October 2018

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)
v • d • e


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

REGULATORY

GUIDE DIRECTORATE

OF REGULATORY

STANDARDS REGULATORY

GUIDE 4.1 MEASURING

AND REPORTING

OF RADIOACTIVITY

IN THE ENVIRONS OF NUCLEAR POWER PLANTS

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.

including anticipated operational occurrences, and fion pi!stulated accidents.

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,'

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.

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)

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

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.

A preoperational program should be conducted in the environs of cach proposed nuclear power plant site to: (I) identify probable critical'

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.

Years of experience at various Contitnissitt facilities have demonstrated that specific radionuclides behave in known ways under given environtmental cottditions.

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' dtecrts 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.

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.)

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.

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.

Also. licensees'

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.

'[e Commission's Regulator.'

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'

monitoring anid reporli g prograins.

ihle s:tlt'has developed tile regulatory position set forth belo'v.C. REGULATORY

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.

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.

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.

1. Preoperational Program Potential critical pathways should he idemifiied prior to plant operation.

l';,e provisions in ICRV FPtlblicaiion

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.

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

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:

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:

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.

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.

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

r 3) if ir t :iffect% thLe' ,vll-te.ing

'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.

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

WhcLtre use of a single indicator tneditim is impractical.

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

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

c... external radialion exposures from clotds of uatnima-ray-emittitog radio-nclides inlvol-..

onlV onle paithway the atmosphere.

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)

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.

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).

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

.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

.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

'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.

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)

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.

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

Nevertheless.

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

).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

or r:diation levels is measured in a p-Mricular critical pathway. the Commnission should he not, fied prontptl..

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.

Consequently.

all assumptions.

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.

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%.

the duta taken in suppnrt of the lite'i.ee'" en.-iroiitnential monitoring programn shriuld also he ,,jonmia ltd s;emiannually.

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

3ind effluent niaiateirilg dat.a m.ere .mnihtited ilnto single reports.alpprolri:e.

Trie licensee should demtostiale that aill assutittiolts.

parameters and methods, used are adcqumtte and compiele Ito allow Itwhere data pertii) a c omparison

, 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.

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)

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:

average and ttlaXIillttt values (for each medium. etc.)g. Background Value h. Analytical Method 7 j. Comparison of Observed Concentrations.

Depositions and Estimated Doses with Predicted Values (based on effluent measurenments)

j. Remarks (be sure to explain any tititstal measurements or deviations).

'I .stim-mtes i)f the error assoeinted with the: measurement of each environmental medium should he reported.O0 4.1.4


Retrieved from "https://kanterella.com/w/index.php?title=Regulatory_Guide_4.1&oldid=1093805"