Regulatory Guide 4.1: Difference between revisions

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{{Adams
{{Adams
| number = ML091310141
| number = ML13350A200
| issue date = 06/30/2009
| issue date = 01/18/1973
| title = Radiological Environmental Monitoring for 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 =  
| docket =  
| docket =  
| license number =  
| license number =  
| contact person = O'Donnell, Edward, RES/RGB
| contact person =  
| case reference number = DG-4013
| document report number = RG-4.001
| document report number = RG-4.001, Rev. 2
| package number = ML091310135
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 20
| page count = 4
}}
}}
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION
{{#Wiki_filter:1/18/73 U.S. ATOMIC ENERGY COMMISSION
  June 2009 Revision 2 REGULATORY GUIDE
REGULATORY  
OFFICE OF NUCLEAR REGULATORY RESEARCH
GUIDE DIRECTORATE
  The NRC issues regulatory guides to describe and make available to the public methods that the NRC staff considers acceptable for use in implementing specific parts of the agency's regulations, techniques that the staff uses in evaluating specific problems or postulated accidents, and data that the staff needs in reviewing applications for permits and licenses.  Regulatory guides are not substitutes for regulations, and compliance with them is not required.  Methods and solutions that differ from those set forth in regulatory guides will be deemed acceptable if they provide a basis for the findings required for the issuance or continuance of a permit or license by the Commission.
OF REGULATORY  
STANDARDS REGULATORY
GUIDE 4.1 MEASURING
AND REPORTING
OF RADIOACTIVITY
IN THE ENVIRONS OF NUCLEAR POWER PLANTS


This guide was issued after consideration of comments received from the public.
==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.
Regulatory guides are issued in 10 broad divisions: 1, Power Reactors; 2, Research and Test Reactors; 3, Fuels and Materials Facilities; 4, Environmental and Siting; 5, Materials and Plant Protection; 6, Products; 7, Transportation; 8, Occupational Hea lth; 9, Antitrust and Financial Review; and 10, General.


Electronic copies of this guide and other recently issued guides are available through the NRC's public Web site under the Regulatory Guides document collection of the NRC's Electronic Reading Room at http://www.nrc.gov/reading-rm/doc-collections/reg-guides/ and through the NRC's Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under Accession No. ML091310141.
including anticipated operational occurrences, and fion pi!stulated accidents.


REGULATORY GUIDE 4.1 (Draft was issued as DG-4013, dated November 2008)  
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,'
RADIOLOGICAL ENVIRONMENTAL MONITORING FOR  NUCLEAR POWER PLANTS
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.


==A. INTRODUCTION==
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 method that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable for use in establishing and conducting an environmental monitoring program at nuclear power plants. The guide describes programs for preoperational and operational environmental monitoring.


The regulatory framework for the radiological environmental monitoring program (REMP) derives from the following:
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.


* plant-specific technical specifications that establish a requirement for radiological environmental monitoring activities; 
==B. DISCUSSION==
* Title 10 of the Code of Federal Regulations (10 CFR) Part 50, "Domestic Licensing of Production and Utilization Facilities," Appendix I, "Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion 'As Low As Is Reasonably Achievable'
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.
for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents" (Ref. 1); 
  Revision 2 of RG 4.1, Page 2
* 10 CFR 20.1302, "Compliance with Dose Limits for Individual Members of the Public" (Ref. 2),  which requires surveys of radiation levels in the unrestricted areas and radioactive materials in effluents to demonstrate compliance with the dose limits for individual members of the public; and
* 10 CFR 72.44, "License Conditions," paragraph 44(d)(2), which requires establishment of an environmental monitoring program to ensure compliance with technical specifications (for those facilities with a specific license under 10 CFR Part 72, "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Waste, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste" (Ref. 3)). 
* General Design Criterion 64, "Monitoring radioactivity releases," of Appendix A, "General Design Criteria for Nuclear Power Plants," to Title 10, Part 50, of the Code of Federal Regulations (10 CFR Part 50), "Domestic Licensing of Production and Utilization Facilities"
  Collectively, these regulations require that an environmental monitoring program be established and implemented to obtain data on measurable levels of radiation and radioactive materials.  The Annual Radiological Environmental Operating Report provides summaries of the data, interpretations, and analyses of trends of the results.  The licensee may submit the annual report required by 10 CFR 72.44 as part of the Annual Radiological Environmental Operating Report at the licensee's discretion (if the reporting dates, as outlined in the licensee's regulatory bases, are coincident). 
This regulatory guide contains information collection requirements covered by 10 CFR Part 20, "Standards for Protection Against Radiation," and 10 CFR Part 50 that the Office of Management and Budget (OMB) approved under OMB control numbers 3150-0014 and 3150-0011.  The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information collection request or requirement unless the requesting document displays a currently valid OMB control number.
 
Revision 2 of RG 4.1, Page 3CONTENTS


==A. INTRODUCTION==
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.
-----------------------...1


==B. DISCUSSION==
A preoperational program should be conducted in the environs of cach proposed nuclear power plant site to: (I) identify probable critical'
-------------------------..4
pathways io be monitored after the plant is in operation:
1. Regulatory Guidance---------------------..4  
(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.
2. Objectives of the Radiological Environmental Monitoring Program--- 5


==C. REGULATORY POSITION==
equipment, and techniques.
--------------------6
1. Preoperational Radiological Environmental Monitoring Program ----6
2. Operational Radiological Environmental Monitoring Program -----6
3.  Routinely Monitored Exposure Pathways ---------..---..7
4. New Routes of Exposure -------------------...9
5. Sample Media------------...----------- 9
6. Sampling and Analysis Schedule----------------..10
7. Analytical Detection Capabilities----------------..10
8. Deviations from the Radiological Environmental Monitoring .Program-..11
9. Land Use Census----------...------------.11 10. Reporting Levels----------...------------.12
11. Annual Radiological Environmental Operating Report ----- ---12 12. Environmental Program Review----...---------...--..13


==D. IMPLEMENTATION==
Years of experience at various Contitnissitt facilities have demonstrated that specific radionuclides behave in known ways under given environtmental cottditions.
----------------------.. 14 GLOSSARY-----------------------------.15


REFERENCES---------------------------- 17
Therefore.


BIBLIOGRAPHY--------------------------- 18 Revision 2 of RG 4.1, Page 4
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


==B. DISCUSSION==
===9. Septemher ===
Regulatory Guidance Six basic documents contain the regulatory guidance for implementing the 10 CFR Part 20
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
regulatory requirements and plant technical specifications related to monitoring and reporting of radioactive material in effluents and environmental media, solid radioactive waste disposal, and resultant public dose:  1. Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants" (Ref. 4);
7. Sipra niote
2. Regulatory Guide 4.1, "Radiological Environmental Monitoring For Nuclear Power Plants," 
3. Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Inception Through Normal Operations to License Termination)-Effluent Streams and the Environment" (Ref. 5);
4. NUREG-1301, "Offsite Dose Calculation Manual Guidance:  Standard Radiological Effluent Controls for Pressurized Water Reactors," (Ref. 6); and
5. NUREG-1302, "Offsite Dose Calculation Manual Guidance:  Standard Radiological Effluent Controls for Boiling Water Reactors," (Ref. 7).
6. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Demonstrating Compliance with 10 CFR Part 50, Appendix I," (Ref. 8)  The above documents, when used in an integrated manner, provide the basic principles and implementation details for developing and maintaining effluent and environmental monitoring programs at nuclear power plants.  The three regulatory guides specify the guidance for radiological monitoring programs, whereas the two NUREGs present specific implementation details for effluent and environmental monitoring programs.  Regulatory Guide 1.21 addresses the measuring, evaluating, and reporting of effluent releases, solid radioactive waste, and public dose from nuclear power plants.  The guide describes the important concepts in planning and implementing an effluent and solid radioactive waste program.  Concepts covered include meteorology, hydrology, release points, monitoring methods, subsurface monitoring, identification of principal radionuclides, unrestricted area boundaries, continuous and batch release methods, representative sampling, composite sampling, radioactivity measurements, decay corrections, quality assurance, solid radioactive waste shipments, and public dose assessments.  Regulatory Guide 4.1 addresses the environmental monitoring program.  The guide discusses principles and concepts important to environmental monitoring at nuclear power plants.  The regulatory guide addresses the need for preoperational and background characterization of radioactivity.  The guide also addresses offsite monitoring, including the those exposure pathways that are important to a site.  The guide defines exposure pathways, the program scope of sampling media and sampling frequency, and the methods of comparing environmental measurements to effluent releases in the annual environmental report.


Revision 2 of RG 4.1, Page 5Regulatory Guide 4.15 provides the basic principles of quality assurance in all types of radiological monitoring programs for effluent streams and the environment.  The guide does not specifically address nuclear power plants but covers all types of licenses and licensees. It provides the guidance for structuring organizational lines of communication and responsibility, using qualified personnel, implementing standard operating procedures, defining data quality objectives, performing quality control checking for sampling and analysis, auditing the process, and taking corrective actions.  NUREG-1301 and NUREG-1302 provide the detailed implementation guidance by describing effluent and environmental monitoring programs.  The NUREGs specify effluent monitoring and environmental sampling requirements, surveillance requirements for effluent monitors, types of monitors and samplers, sampling and analysis frequencies, types of analysis and radionuclides analyzed, lower limits of detection (LLDs), specific environmental media to be sampled, and reporting and program evaluation and revision.
===2. USAEC REGULATORY ===
GUIDES ResfutAiorv Guide, Wi'. 1su"nf It' dtecr''ts amit flt~i't oAV.,Ihhtt In the p~ublic meiohorb.


Regulatory Guide 1.109 provides the detailed implementation guidance for demonstrating that radioactive effluents conform to the "As Low As Is Reasonably Achievable" (ALARA) design objectives of 10 CFR 50, Appendix I. The regulatory guide describes calculational models and parameters for estimating dose from effluent releases, including the dispersion of the effluent in the atmosphere and different water bodies.
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'
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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.


Objectives of the Radiological Environmental Monitoring Program (REMP)
Cofnrmwnis Anil wrgoo'sions tot ir19ifovenerflts int these quidei are en'couraged And %thisuit he lenti t) ihes" 5'c~fiatv of the Commissuions.
  The regulatory positions described in this document provide guidance on the establishment of the REMP.  The REMP has the following basic objectives: 1. Survey the radiological conditions in the vicinity of the facility before initial reactor operation to establish the baseline radiological conditions in the local environment. 2. Measure the levels of radiation and radioactive materials in the local environment during the lifetime of the facility. 3. Determine if any measurable levels of radiation or radioactive materials in the local environment are attributable to plant operation. 4. Determine if measurable levels of plant-related radiation and radioactive materials in the local environment are commensurate with the radioactive effluents and plant design objectives (e.g., as low as reasonably achievable). 5. Report measurement results, summaries, and trends regarding radiation and radioactive materials in the local environment. 6. Maintain the REMP by identifying changes in land use (e.g., agricultural land use in unrestricted areas) that may impact the measurements or measurement results associated with exposure pathways identified in the REMP.


Revision 2 of RG 4.1, Page 6
US. Atomic EnetfgY Commisitn.


==C. REGULATORY POSITION==
W.Iihinaroin, D.C. 21if"45.Aifent,nn:
1. Preoperational Radiological Environmental Monitoring Program a. A REMP should be established and implemented at least 2 years before initial facility operation. The program will contain the routine surveillances necessary to adequately characterize the radiological conditions in the vicinity of the reactor site.  Once initiated, the collection of samples and analysis of data should follow the sampling and analyses schedule and should continue for the first 3 years of commercial operation.  For new reactor sites that are collocated with currently operating nuclear power plants (or previously operating nuclear power plants with a currently operating REMP program), the existing operational REMP associated with the operating (or previously operating) facility will normally meet the requirements for a preoperational REMP,  
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.'
given that the monitoring data is relevant to the time period . b.   The preoperational REMP should be conducted so that the preoperational radiological conditions are understood in sufficient detail to allow future reasonable, direct comparison with data collected after power operation of the facility.  The preoperational REMP should be updated when the land use census identifies new exposure pathways or receptor locations.  2. Operational Radiological Environmental Monitoring Program a.  Although all operating facilities will have a REMP associated with the operating reactors, some licensees may have other REMPs to satisfy other needs.  An operational radiological environmental monitoring program may consist of several different parts.  For example, a licensee may have (1) a REMP that is associated with the 10 CFR Part 50 licensed facility, (2) a REMP that is associated with the 10 CFR Part 72 specific-licensed facility, and (3) a REMP not explicitly required by NRC regulations (e.g., environmental samples of local community interest or samples deemed important for continuity with the preoperational REMP).  This regulatory guide addresses only those REMPs required by NRC regulations, but licensees may, at their discretion, apply this information to any aspect of a REMP conducted for purposes of local community interest. b.  If a licensee has a REMP as part of a 10 CFR Part 50 license and another REMP as part of a 10 CFR Part 72 specific license, the licensee may choose to establish totally separate REMPs, or it may choose to collocate surveillance equipment where practical.  In all cases, the licensee shall conduct the REMPs in accordance with the applicable regulations and the licensing bases at the site. c.  The REMP is sometimes conceptualized as an offsite monitoring program.  However, some portions of the REMP may be conducted on site.  For example, NUREG-1301/1302 states that the inner ring of thermoluminescent dosimeters (TLDs) may be located "in the general area of the site boundary."  The same is true for radioiodine and particulate sampling.  NUREG-1301/1302 also describes ground water monitoring if ground water is "likely to be affected" and describes the monitoring of drinking water supplies if they "could be affected."  Licensees should consider this when implementing a REMP (especially if the facility obtains drinking water from wells located down gradient from the site). In some situations, licensees should consider onsite Revision 2 of RG 4.1, Page 7monitoring with respect to NUREG-1301/1302, Section 3/4.12.2, "Land Use Census," Control 3.12.2. Action "a" of that control specifies that new locations be reported in the Annual Radioactive Effluent Release Report when the doses are higher than those at the current location. Action "b" of that control requires revising the REMP (and reporting to the NRC) if the licensee identifies a location yielding a dose or dose commitment that is 20 percent larger than the dose at locations from which samples are currently being taken. For example, where liquid effluents are stored in onsite ponds, and evaporation from those ponds may contribute to the inhalation pathway for residents at locations not currently identified in the REMP, licensees may need to evaluate the potential impact on the REMP. This could also apply in situations in which ground water transports seepage containing radionuclides from such onsite ponds to an offsite surface water body where commercial or recreational fishing is allowed. In addition, sites that contain onsite independent spent fuel storage installations (ISFSIs) may include onsite REMP samples. 3. Routinely Monitored Exposure Pathways a.  Figure 1 shows the three exposure pathways (i.e., inhalation, ingestion, and direct radiation) that are routinely monitored, along with some related characteristics. Each of the three exposure pathways consists of one or more routes of exposure.  For example, inspection of Figure 1 for "liquid effluents" reveals three types of sample media associated with the ingestion exposure pathway.  Each of these media is involved in a different route by which radioactive material may be transferred from the environment to an individual (causing an exposure).  These routes of exposure are identified based on site-specific information (e.g., receptors, receptor locations, distances, directions, and water usage) identified during the land use census. b.  Using the results of the land use census, each site should develop, implement, and maintain a site-specific REMP as outlined in NUREG-1301/1302. Some exposure pathways (e.g., inhalation) are considered to exist at all sites (because air, the transfer media, exists at all sites). 
7. Itasnsttimti"" J. Fuels And Mate.'3s Fscdmtm' B. orrciur.1iOn'si
Therefore, the REMP should always include air samples (e.g., particulate filters and charcoal cartridges).  Other exposure pathways and routes of exposure do not exist at all sites.  For example, the REMP includes drinking water samples only if drinking water sources are present and are likely to be affected by effluents.
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.


Revision 2 of RG 4.1, Page 8 Figure 1.  Routinely Monitored Exposure Pathways
analyses otC "indicator organiis'ns may adequately define radiotuclide levels in tile envirtomnent.
# Type of Effluent RG 1.109 Exposure Pathway Potential Sample Media Critical Receptor 1 Liquid Effluent (Waterborne) C.1.a Ingestion Drinking Water Organ (1) 2 C.1.b Ingestion Aquatic Foods Organ (1) 3 C.1.c Direct Radiation-Ground Plane Shoreline Deposits Organ (2) 4 C.1.d Ingestion Irrigated Foods Organ (1) 5 Noble Gases Discharged to Atmosphere (Airborne) C.2.a Gamma Air (3) Air (only if stack >80 m) Air 6 C.2.b Gamma Air and Beta Air (3) Air  Air 7 C.


===2. c Direct Radiation ===
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.
-Submersion Air (only if stack >80 m) Total Body(1) 8 C.2.d Air (only if stack >80 m) Skin 9 C.2.e Air  Total Body(1) 10 C.2.f Air  Skin 11 Iodines, Particulates, and Tritium Discharged to Atmosphere (Airborne) C.3.a Direct Radiation-Ground Plane Surface Soil Organ (2) 12 C.3.b Inhalation Air (particulate, iodine, tritium) Organ (1) 13 C.3.c Ingestion Food (produce, milk, leafy vegetables, meat) Organ (1) 14 N/A (4) N/A Direct Radiation-Shine TLDs (or other measurement device) Total Body (1)  1 The total body is considered as a critical organ in the 1959 International Commission on Radiological Protection (ICRP)-2, "Report of ICRP Committee II on Permissible Dose for Internal Radiation." 
2 Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Demonstrating Compliance with 10 CFR Part 50, Appendix I," specifies factors for two organs: the total body and the skin.


3 This is dose to air, and it is not considered a pathway for exposure to man.
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.


4 While no type of effluent is associated with it, direct radiation is included here because it is an exposure pathway.
An entvironu ental tnonitoritng program shotld be flexible.aid, as results are obtained.


Revision 2 of RG 4.1, Page 9
tihe prograni should be reviewed to identil'y any\ necessary changes. The progra n shuhld then be appropriately nodified.
4. New Routes of Exposure a.  If the facility is modified or otherwise changed in a manner that results in the creation of a new point of release for radioactive material, the new release point could potentially impact a receptor or receptor location associated with the existing REMP.  Alternatively, plant modifications may result in the discovery of a previously unidentified effluent release point that could impact the REMP.  For example, installation of a new liquid effluent settling pond located some distance away from the center of the facility may create a new release point and cause a change to the nearest maximum exposed individual identified in the most recent land use census.  This change to the maximum exposed individual may be associated with (1) the receptor, (2) the receptor location, (3) the distance to the receptor, or (4) the direction of the receptor.  New routes of exposure, new sample locations, or new receptor locations may result from a radioactive leak or spill.  If conditions at a site create a new route of exposure, or alter the parameters associated with an existing route of exposure, the REMP may recognize such changes after the change has occurred through environmental sample results that are different than expected (or different than those identified in the preoperational REMP).  With REMP sample results different than expected (or different than those identified in the preoperational REMP), licensees may refer to the actions in NUREG-1301/1302, Controls 3.12.1 and 3.12.2.  This reactive approach is an appropriate and acceptable manner to conduct a REMP and, historically has been the basis of the REMP.  At the same time, operating experience indicates that, if licensees take a more proactive approach to the REMP, they may realize program improvements and reduce regulatory involvement, including regulatory actions.  Such a proactive approach includes recognizing how changes, modifications, or operational occurrences at the facility could affect the REMP with respect to actions described in NUREG-1301/1302, Controls 3.12.1 and 3.12.2. 5. Sample Media a.  Figure 1 lists some common sample media associated with various exposure pathways.  In general, sample media should be selected for environmental monitoring as outlined in NUREG-1301/1302.  The REMP need only include sample media that actually exists at a site and are utilized in sufficient quantities (consider availability and usage/consumption factors).  However, if the site-specific land use census identifies a new important route of exposure that contributes more than 20% to the calculated individual dose as determined by Regulatory Guide
1.109, then sample media associated with the route of exposure should be added to the REMP 
b. TLDs or other equivalent devices should be used to monitor direct radiation exposure as outlined in NUREG-1301/1302.  These results may be used, as outlined in the offsite dose calculation manual (ODCM), in demonstrating compliance with the 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operations" (Ref.  9), dose limits for members of the public in the unrestricted area. c. The sample media associated with the inhalation exposure pathway should be monitored as outlined in NUREG-1301/1302.


Revision 2 of RG 4.1, Page 10d.  The sample media associated with the ingestion and ground plane exposure pathways for liquid effluents should be monitored as outlined in NUREG-1301/1302.  Because Table 3.12-1 in NUREG-1301/1302 specifies ground water and drinking water separately, the REMP should include separate sampling and analysis for ground water and drinking water if they are likely to be affected by liquid releases.  For example, if liquid effluents are discharged to a local pond, the licensee should evaluate whether ground water is likely to be affected and take the appropriate action. e.  The sample media associated with the ingestion pathway for gaseous releases should be monitored as outlined in NUREG-1301/1302.  This includes sampling and analyzing sample media (i.e., milk, or if milk is not available, broad leaf vegetation) and other sample media if identified in accordance with Section 5.a above.  For example, sampling of domesticated meat may be needed if the land use census shows that a significant amount of meat is raised locally, and an evaluation shows that meat consumption contributes a 20% dose increment to the total individual dose.  Similarly, sampling meat from game animals may be necessary if hunting accounts for a significant amount of meat obtained for consumption (see usage factors in Regulatory Guide 1.109).  If goat milk is produced locally (e.g., within 5 miles or 8 km) for human consumption, then sampling and analysis may be required if sufficient quantities are available for sampling purposes.  However, if sufficient quantities are not available for sampling, then an alternate sample media should be sampled such as broad leaf vegetation. f.  Sample media other than those identified in Figure 1 that have special local interest or are otherwise locally important should be evaluated for inclusion in the REMP.  In these instances, from a regulatory perspective, the licensee need demonstrate only that the sample media and receptor location associated with the route(s) of exposure are appropriately evaluated (e.g., by using the criteria of NUREG-1301/1302, Control 3.12.2). g.  Control stations should be established and clearly distinguished from indicator stations for use in correlating control and indicator station results as specified in NUREG-1301/1302. 6. Sampling and Analysis Schedule a.  The environmental sampling and analysis program should be conducted at the frequencies specified in NUREG-1301/1302, unless otherwise evaluated and justified. The justification for deleting samples from the REMP should be based on the results of the local land use census (e.g., the census indicates the absence or unavailability of the sample media) or as otherwise justified.  The deletion of sample media from the REMP should be rare.  Reduction in sample frequency may be appropriate if it is shown that the reduction does not impact the effectiveness of the REMP.  Advances in remote telemetry of some air samplers may provide sufficient justification for reducing the frequency of air samples.  For example, it may be appropriate to reduce the frequency of analysis associated with an air sampler (from once per week to once per 2 weeks) if the licensee can demonstrate that the new equipment is more reliable and results in fewer "missed samples"  Changes to the sampling and analyses program can also be made based on operational experience. b.  In all cases where sample or analysis frequencies are reduced, the changes should not reduce the overall effectiveness of the environmental monitoring program.  If sample or analysis frequencies are reduced, the justification should also include an evaluation showing that the increased Revision 2 of RG 4.1, Page 11sampling interval does not impact the ability to detect radionuclides (e.g., because of half-life considerations).  The licensee should document and report the basis for changes to the environmental monitoring program in the Annual Radiological Environmental Operating Report. 7. Analytical Detection Capabilities a.  Sample analysis should employ analytical techniques so that an appropriate analytical sensitivity (e.g., a priori LLD) is achieved, as specified in NUREG-1301/1302.  Alternately, licensees may use the analytical detection sensitivities as determined by the licensee based on the "Multi- Agency Radiological Laboratory Analytical Protocols Manual" (MARLAP) (Ref.  10).  Selection of values different from those in NUREG-1301/1302 should be justified and documented. b.  The specified detection capabilities are normally achievable for routine environmental measurements. Deviations from the a priori analytical sensitivity levels are anticipated during actual sample analyses because of interference from other radionuclides or other factors but should be evaluated and documented.  Licensees should report the analytical sensitivity capabilities of the REMP in the Annual Radiological Environmental Operating Report. c.   If a licensee has reduced a sample frequency as outlined in Position 6 above, the licensee should evaluate the impact on the analytical detection capability. d. Analyses for C-14 in environmental media are not required since the plant produced component is a small fraction of the naturally occurring C-14. 8. Deviations from the Radiological Environmental Monitoring Program a.  Deviations from the sampling schedule are permitted if samples are unobtainable because of hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons.  Legitimate reasons with respect to seasonal unavailability may include consideration of the migratory routes of species or the growing season of crops but should generally not include unavailability which is within the control of the licensee.  Similarly, sample pump failures that occur at an unacceptably high rate or pump failure that continues to occur because of ineffective corrective actions would not be legitimate reasons for sample unavailability.  Hurricanes, tornadoes, or floods may qualify as legitimate reasons for temporary sample unavailability.  b.  If samples are unobtainable because of sampling equipment malfunction, reasonable effort under the circumstances should be made to complete corrective action before the end of the next sampling period, or else compensatory sampling and analysis are required.  The Annual Radiological Environmental Operating Report should document deviations from the sampling schedule.  Deviations that should be reported include loss of sample media, inability of the sample to meet the analytical sensitivity (e.g., the sample volume was too low to provide adequately sensitive analysis results), or invalid analyses results.  Minor deviations, such as use of alternate sampling media and short periods of missed collection time, do not need to be reported.
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.


Revision 2 of RG 4.1, Page 129. Land Use Census a.  Land use, exposure pathways, and the mechanisms of exposure may change over the operating life of the plant.  The REMP should contain provisions to identify changes in land use, and based on this information, the licensee should revise the REMP as necessary to identify and evaluate the site-specific parameters identified in NUREG-1301/1302 (e.g., receptors and receptor locations).  Licensees should refer to NUREG-1301/1302, Section 3/4.12.2, "Land Use Census," for additional information, including the distance over which the land use census is conducted. b.  In accordance with NUREG-1301/1302, a land use census should be conducted, typically annually during the growing season, to identify (1) changes in land use, (2) receptor locations, and (3) new exposure pathways (or route of exposure).  Monitoring of vegetation at the site boundary can be performed in lieu of the garden census as identified in NUREG-1301/1302.  The frequency of the land use census may be reduced provided that (1) the frequency is outlined in the procedures (e.g., the ODCM and related procedures), (2) the licensee can demonstrate that there is no reduction in the effectiveness of the REMP, and (3) persons knowledgeable in land use census monitor usage characteristics based on knowledge gained during routine sample collection. 10. Reporting Levels  a.  The results of the REMP must be evaluated using the reporting levels in NUREG-1301/1302.  When applying reporting levels, licensees may use the average of the measured radionuclide concentrations during the quarterly period.  The values selected for the reporting levels approximate the concentrations equivalent to the design objectives of Appendix I to 10 CFR Part 50 for the given pathway or media.  If the reporting levels are exceeded, the licensee must submit a special report to the NRC.  b.  If a principal radionuclide (as determined in accordance with Regulatory Guide 1.21) is detected in an environmental sample and if NUREG-1301/1302 does not provide a corresponding reporting level, licensees should calculate a reporting level for that radionuclide.  The basis for that calculation should be to approximate compliance with the numerical guides of Appendix I to 10 CFR Part 50.  c.  If it can be demonstrated that a detected radionuclide exceeding the reporting level is not the result of 10 CFR Part 50 licensed operation (e.g., from medical radioisotopes or by comparison with control station or preoperational data), a report need not be submitted.  However, the licensee should describe this occurrence in the Annual Radiological Environmental Operating Report, as discussed in NUREG-1301/1302. 11. Annual Radiological Environmental Operating Report a.  An Annual Radiological Environmental Operating Report must be prepared and must include measurement summaries and trends regarding radiation and radioactive materials in the local environment.  The report should include a summary description of the REMP, a map of indicator locations keyed to a table giving distances and directions from the reactor or site centerline, any changes identified in the land use census, measurements (i.e., indicator, control, and quality control), and trends in the measurements of levels of radiation and radioactive materials in the Revision 2 of RG 4.1, Page 13environment and other such information as NUREG-1301/1302 may specify.  NUREG-1301/1302 provides more guidance on preparing the Annual Radiological Environmental Operating Report. b.  This annual report should summarize the environmental data in the format specified in NUREG-1301/1302.  Data should be evaluated to identify the levels of plant-related environmental radioactivity above background levels (i.e., plant-related contributions that are distinguishable from background).  For data distinguishable from background levels, a comparison should be made of current environmental monitoring results with preoperational data as appropriate and previous operational measurements for the purpose of trending environmental radioactivity resulting from licensed plant operation.  c.  In addition, in cases where plant-related activity is detected in the environment (e.g., tritium discharged to lakes or ponds or subsurface ground water), a basic correlation should be made between predicted and measured environmental concentrations.  The purpose is to determine the adequacy of the effluent measurements and dispersion modeling.  In cases where plant-related activity in the environment is increasing, the impact of prior year effluent releases should be factored into the correlations to determine if the rate of increase is commensurate with plant effluents. d.  For direct radiation, the direct measurement data (e.g., TLD data) should be evaluated to determine if there is a dose contribution from plant operation.  For plants with onsite sources of radiation (e.g., ISFSI or low-level waste storage) that cause measurable changes in REMP TLDs, trend graphs may be appropriate to demonstrate the change in radiation levels from the preoperational (and previous operational) REMP results to current time periods.  e.  The Annual Radiological Environmental Operating Report for the previous calendar year should be submitted electronically or as a hard copy to the director of the NRC regional office (with a copy to the Director, Office of Nuclear Reactor Regulation) as a separate document by May 15 each year (unless otherwise specified in technical specifications or the ODCM).  Note that the period of the first report should begin with the date of initial criticality and end on December 31.  12. Environmental Program Review a.  A periodic environmental program review should be conducted to reexamine the adequacy and effectiveness of the REMP to achieve its objectives.  The review can be performed during preparation of the Annual Radiological Environmental Operating Report.  b.  The program review should evaluate the need to expand (or reduce) the environmental monitoring program given the results of the environmental data and trends in environmental radioactivity.  Note that any reductions must be thoroughly evaluated and justified, given that environmental data indicating the absence of plant-related radioactivity are important. c.  The review should confirm exposure pathways and sampling media. d.  The review should ensure that the principal radionuclides being discharged are the same nuclides being analyzed in the environmental program.
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.


Revision 2 of RG 4.1, Page 14e.  The review should identify whether the land use census is able to identify potential changes in exposure pathways (e.g., new drinking water locations or irrigation systems in use). f.  The review should examine 10 CFR 50.75(g) files to identify leaks, spills, or other events that could affect radioactivity levels in the unrestricted area.  g.  The review should identify any REMP changes or special studies that may be needed as a follow-up to evaluations made when comparing effluent and environmental program results. h. The review should evaluate whether the sampling and measurement techniques meet the objectives of the REMP.
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.


==D. IMPLEMENTATION==
'[e Commission's Regulator.'
The purpose of this section is to provide information to applicants and licensees regarding the NRC's plans for using this regulatory guide.  The NRC does not intend or approve any imposition or backfit in connection with its issuance.
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.


In some cases, applicants or licensees may propose or use a previously established acceptable alternative method for complying with specified portions of the NRC's regulations.  Otherwise, the methods described in this guide will be used in evaluating compliance with the applicable regulations for license applications, license amendment applications, and amendment requests.
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.


Licensees who are committed in their licensing bases to Revision 1 of this regulatory guide may retain that commitment.  In the 35 years since the NRC published Revision 1, the industry has gained important operating experience.  The staff guidance contained in Revision 2 addresses that operating experience and clarifies some issues that Revision 1 addressed only broadly.  Licensees may wish to review the guidance in this document and adopt those practices they determine are appropriate for use at their site.  Licensees are encouraged to (1) review the guidance provided in this document and
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.
(2) consider supplementing their existing environmental monitoring program with the updated staff guidance.


Revision 2 of RG 4.1, Page 15GLOSSARY ALARA - As Low As Is Reasonably Achievable a priori - Before the fact limit representing the capability of a measurement system and not as an after the fact (a posteriori) limit for a particular measurement.
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.


AREOR - Annual Radiological Environmental Operating Report controlled area (10 CFR 20) - Means an area, outside of a restricted area but inside the site boundary, access to which is limited by the licensee for any reason.
1. Preoperational Program Potential critical pathways should he idemifiied prior to plant operation.


controlled area (10 CFR 72) - Means that area immediately surrounding an ISFSI (Independent Spent Fuel Storage Installation) or MRS (Monitored Retrievable Storage Installation) for which the licensee exercises authority over its use and within which ISFSI or MRSI operations are performed. control station - An environmental monitoring location (station) remote from the nuclear power plant beyond the influence from the plant's effluents or direct radiation.
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.


determination - A quantitative evaluation of the release or presence of radioactive material under a specific set of conditions.  A determination may be made by direct or indirect measurements (e.g., with the use of scaling factors). drinking water -
suitable indicator organisms or media should be identified in each pathway.2. Operational Program a. Sample Media Where practical.
Water that does not contain an objectionable pollutant, contamination, minerals, or infective agent and is considered satisfactory for domestic consumption.  This is sometimes called potable water.  Potable water is water that is safe and satisfactory for drinking and cooking. Although EPA regulations only apply to public drinking water sources supplying 25 or more people (refer to EPA for more information), for purposes of the effluent and environmental monitoring programs, the term drinking water includes water from single-use residential drinking water wells. effluent-Liquid or gaseous waste containing plant-related, licensed radioactive material, emitted at the boundary of the facility (e.g., buildings, end-of-pipe, stack, or container) as described in the FSAR. effluent discharge (radioactive) - Any evolution in which plant-related, licensed radioactive material is released from a system, structure, or component and enters the unrestricted area.  exposure pathway - A mechanism by which radioactive material is transferred from the (local) environment to humans. There are three commonly recognized exposure pathways; inhalation, ingestion, and direct radiation. For example, ingestion is an exposure pathway, and it may include dose contributions from one or more routes of exposure. For example, one route of exposure that may contribute to the ingestion exposure pathway is often referred to as grass-cow- milk-infant-thyroid route of exposure.


Revision 2 of RG 4.1, Page 16ground water - All water in the surface soil, the subsurface soil, or any other subsurface water. Ground water is simply water in the ground regardless of its quality, including saline, brackish, or fresh water. Ground water can be moisture in the ground that is above the regional water table in the unsaturated (or vadose) zone, or ground water can be at and below the water table in the saturated zone. ISFSI - Independent Spent Fuel Storage Installation indicator station - An environmental monitoring location (station) near the nuclear power plant where there may be an influence from the plant's effluents or direct radiation.
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.


licensed material - Means source material, special nuclear material, or byproduct material received, possessed, used, transferred, or disposed of under a general or specific license issued by the Commission. lower limit of detection (LLD) - The a priori smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only a 5% probability of falsely concluding that a blank observation represents a real signal (see NUREG-1301, NUREG-1302). member of the public (10 CFR 20) - Means any individual except when that individual is receiving an occupational dose.
including measurements at control locations.


member of the public (40 CFR 190) - Means any individual that can receive a radiation dose in the general environment, whether he may or may not also be exposed to radiation in an occupation associated with a nuclear fuel cycle.  However, an individual is not considered a member of the public during any period in which the individual is engaged in carrying out any operation which is part of a nuclear fuel cycle.  monitoring - (Radiation monitoring, radiation protection monitoring) means the measurement of radiation levels, concentrations, surface area concentrations or quantities of radioactive material and the use of results of these measurements to evaluate potential exposures and doses. pre-operational data - Environmental monitoring data collected prior to nuclear plant operation that is used to characterize the preoperational radiological conditions prior to influence from the plant's operation. ODCM-The Offsite Dose Calculation Manual (ODCM) shall contain the methodology and parameters used in the calculation of the offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program.  The ODCM shall also contain (1) the Radioactive Effluent Controls Program and Radiological Environmental Monitoring Program and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Technical Specifications.  (NUREG-1301/1302 has additional information related to ODCMs.)  principal radionuclide - A principal radionuclide is one of the principal gamma emitters listed in NUREG-1301 and NUREG-1302, Tables 4.11-1 and Table 4.11-2, or alternatively, from a risk-informed perspective, a radionuclide is considered a principal radionuclide if it contributes either Revision 2 of RG 4.1, Page 17(1) greater than 1 percent of the 10 CFR Part 50, Appendix I, design objective dose when all radionuclides in the type of effluent are considered, or (2) greater than 1 percent of the activity of all nuclides in the type of effluent being considered.  Regulatory Guide 1.109 lists the three types of effluents as (1) liquid effluents, (2) noble gases discharged to the atmosphere, and (3) all other nuclides discharged to the atmosphere. In this document, the terms "principal nuclide" and "principal nuclide" are synonymous since this document is only concerned with measuring, evaluating, and reporting radioactive materials in effluents.
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.


release point - A location from which radioactive materials are released from a system, structure, or component (including evaporative releases and leaching from ponds in the controlled or restricted area before release under 10 CFR 20.2001).  For release points monitored by plant process radiation monitoring systems, the release point is associated with the piping immediately downstream of the radiation monitor.  (See also the definition for "significant release point.")  Several release sources may contribute to a common release point.
(2) if it is rare ir e~ndanlge~red.


REMP - Radiological Environmental Monitoring Program reporting levels -
r 3) if ir t :iffect% thLe' ,vll-te.ing
Levels of radioactivity in the unrestricted area from licensed operation that must be reported to the NRC within 30 days via a special report in accordance with 10 CFR 50.4, "Written Communications."  (See also NUREG-1301 and NUREG-1302.)   route of exposure - A specific path (or delivery mechanism) by which radioactive material, originally in the environment at a specified location, can eventually cause a radiation dose to an individual.  The path typically includes a type of environmental medium (e.g., air, grass, meat, or water) as the starting point and a recipient's organ or body as the end point. For example, the grass-cow-milk-infant-thyroid route of exposure may contribute to the ingestion exposure pathway. Additionally, several routes of exposure may contribute to a single exposure pathway.   site boundary - Site boundary means that line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee. site environs - Locations outside of the nuclear power plant systems, structures, or components as described in the final safety analysis report or the Off Site Dose Calculation Manual (ODCM). surface water - Water on the land surface, whether intermittent or permanent (e.g., streams, rivers, lakes, and wetlands).
'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
TLD - Thermoluminescent Dosimeter unrestricted area - Unrestricted area means an area, access to which is neither limited nor controlled by the licensee.
: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.


Revision 2 of RG 4.1, Page 18 REFERENCES
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.
1  1 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," U.S. Nuclear Regulatory Commission, Washington, DC. 2.  10 CFR Part 20, "Standards for Protection Against Radiation," U.S. Nuclear Regulatory Commission, Washington, DC. 3. 10 CFR Part 72, "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Waste, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C
Waste," U.S. Nuclear Regulatory Commission, Washington, DC. 4.  Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," U.S. Nuclear Regulatory Commission, Washington, DC. 5. Regulatory Guide 4.15 (Rev. 1 or Rev. 2 as applicable), "Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination)-Effluent Streams and the Environment," U.S. Nuclear Regulatory Commission, Washington, DC. 6.  NUREG-1301, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors," U.S. Nuclear Regulatory Commission, Washington, DC, April 1991. 7.  NUREG-1302, "Offsite Dose Calculation Manual Guidance:  Standard Radiological Effluent Controls for Boiling Water Reactors," U.S. Nuclear Regulatory Commission, Washington, DC, April 1991. 8 Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Demonstrating Compliance with 10 CFR Part 50, Appendix I," U.S. Nuclear Regulatory Commission, Washington, DC. 9.  40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operations," U.S. Environmental Protection Agency, Washington, DC. 10.  EPA 402-B-04-001A, "Multi-Agency Radiological Laboratory Analytical Protocols Manual," U.S. Environmental Protection Agency, Washington, DC, July 2004.


2                                               
prop,!rly selected and sampled vegetam 11my 'list) provide a good imteaslie of the radionuclides in , critical FpatlIway.
1  Publicly available NRC published documents such as regulations, regulatory guides, NUREGs, and generic letters listed herein are available electronically through the Electronic Reading Room on the NRC's public Web site at: http://www.nrc.gov/reading-rm/doc-collections/.  Copies are also available for inspection or copying for a fee from the NRC's Public Document Room (PDR) at 11555 Rockville Pike, Rockville, MD; the mailing address is USNRC PDR, Washington, DC 20555; telephone 301-415-4737 or (800) 397-4209; fax (301) 415-3548; and e-mail PDR.Resource@nrc.gov.  2 Copies of the non-NRC documents included in these references may be obtained directly from the publishing  organization.


Revision 2 of RG 4.1, Page 19BIBLIOGRAPHY 
WhcLtre use of a single indicator tneditim is impractical.
10 CFR Part 30, "Rules of General Applicability to Domestic Licensing of Byproduct Material," U.S. Nuclear Regulatory Commission, Washington, DC.


40 CFR Part 141, "National Primary Drinking Water Regulations," U.S. Environmental Protection Agency, Washington, D.C.
samples of' several media from each pathway should be collected and analyzed.


ANSI/HPS N13.30, "Performance Criteria for Radiobioassay," American National Standards Institute, New York, NY, May 1996.
The C(ommission recomizes that some pathways do not have more than olne eiviromnittillal meditiht.


ANSI/ANS-3.11-2005, "Determining Meteorological Information at Nuclear Facilities," American National Standards Institute, New York, NY, December 2005.
c... external radialion exposures from clotds of uatnima-ray-emittitog radio-nclides inlvol-..
onlV onle paithway the atmosphere.


ANSI/HPS N13.1-1999, "Sampling and Monitoring Releases of Airborne Radioactive Substances from the Stacks and Ducts of Nuclear Facilities," American National Standards Institute, New York, NY, January 1999.
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.


ANSI N42.18-2004, "Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents," American National Standards Institute, New York, NY, January 2004.
to confirm predictionls.


ANSI N42.14-1999, "Calibration and Use of Germanium Spectrometers for the Measurement of Gamma-Ray Emission Rates of Radionuclides," American National Standards Institute, New York, NY, May 1999.
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.


ANSI/NCSL Z540-2-1997 (reapproved 2002), "American National Standard for Expressing Uncertainty
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
-U.S. Guide to the Expression of Uncertainty in Measurement," American National Standards Institute, New York, NY, January 1997.
.dionuclides (years). measurements should be made at st once per year. Where seasonal eflects ,ay be important.


EPRI Report No. 1011730, "Ground Water Monitoring Guidance for Nuclear Power Plants," Electric Power Research Institute, Palo Alto, CA, September 2005.
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.


"Liquid Radioactive Release Lessons Learned Task Force Final Report," U.S. Nuclear Regulatory Commission, Washington, DC, September 2006. (ADAMS Accession No. ML083220312)
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.


NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants" (Section 2.3.5), U.S. Nuclear Regulatory Commission, Washington, DC, March 2007.
and concentration of radionuclides from the plant as well as the results obtained from previotus nmeasurements.


NUREG-0475, "Radiological Environmental Monitoring by NRC Licensees for Routine Operation of Nuclear Facilities," October 1978.
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.


NUREG-0543, "Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190)," U.S. Nuclear Regulatory Commission, Washington, DC, February 1980.
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.


RIS 2008-03, Return/Reuse of Previously Discharged Radioactive Effluents, U.S. Nuclear Regulatory Commission, Washington, DC, February 2008.
The staff rc,.ognizes that direct tmeeas uremtetn ts of envirotnml enltal Imredia cannot1 alvays'cet ct levels lruepo -dine to Commissiti design , Iieclites.


Revision 2 of RG 4.1, Page 20
Nevertheless.
  NUREG-1757, "Consolidated Decommissioning Guidance," U.S. Nuclear Regulatory Commission, Washington, DC, September 2006.


NUREG/CR-4007, "Lower Limit of Detection:  Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," U.S. Nuclear Regulatory Commission, Washington, DC, September 1984.
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.


NUREG/CR-6805, "A Comprehensive Strategy of Hydrogeologic Modeling and Uncertainty Analysis for Nuclear Facilities and Sites," U.S. Nuclear Regulatory Commission, Washington, DC, September 2007.
Consequently.


NUREG/CR-6948, "Integrated Ground-Water Monitoring Strategy for NRC-Licensed Facilities and Sites:  Logic, Strategic Approach and Discussion," U.S. Nuclear Regulatory Commission, Washington, DC, July 2003.
all assumptions.


Regulatory Guide 1.23, "Meteorological Monitoring Programs for Nuclear Power Plants," U.S. Nuclear Regulatory Commission, Washington, DC.
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.


Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Demonstrating Compliance with 10 CFR Part 50, Appendix I," U.S. Nuclear Regulatory Commission, Washington, DC.
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.


Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," U.S. Nuclear Regulatory Commission, Washington, DC.
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.


Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," U.S. Nuclear Regulatory Commission, Washington, DC.
Trie licensee should demtostiale that aill assutittiolts.


Regulatory Guide 1.143, "Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants," U.S. Nuclear Regulatory Commission, Washington, DC.
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.


Regulatory Issue Summary (RIS) 2008-03, "Return/Re-use of Previously Discharged Radioactive Effluents," U.S. Nuclear Regulatory Commission, Washington, DC, February 13, 2008.
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.


SECY-03-0069, "Results of the License Termination Rule Analysis," U.S. Nuclear Regulatory Commission, Washington, DC, May 2, 2003.}}
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}}


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

Revision as of 00:09, 15 July 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)
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


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