Regulatory Guide 4.1: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
(6 intermediate revisions by the same user not shown)
Line 1: Line 1:
{{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
                                      DIRECTORATE OF REGULATORY                                       STANDARDS
  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.
                                                                                                                                                    GUIDE
 
                                                                            REGULATORY GUIDE 4.1 MEASURING AND REPORTING OF RADIOACTIVITY
This guide was issued after consideration of comments received from the public.
                                                IN THE ENVIRONS OF NUCLEAR POWER PLANTS
 
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.
 
REGULATORY GUIDE 4.1 (Draft was issued as DG-4013, dated November 2008)
RADIOLOGICAL ENVIRONMENTAL MONITORING FOR  NUCLEAR POWER PLANTS  
 
==A. INTRODUCTION==
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:
 
* plant-specific technical specifications that establish a requirement for radiological environmental monitoring activities; 
* 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'
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==
==A. INTRODUCTION==
-----------------------...1
radiation and radioactivity in the plamt environs. The provisions and principles in International (Commoissiotn on
 
          (;Geneil Design ('C itein                                4i.     'o.nitoring            Radiological               Protection (I('RI'l) P ulicanion 7- Radioactivitv Releases." ol' Appendix A it) 1( ('FR Part                                      pertaining to the releases of radioauctivitv during ornmal
==B. DISCUSSION==
  50. "'(Lennd I Desigji ('iteria Ior Nun:leair Power Plants.'                                  plant operation should be used as additional guidance in requires that licensees provide for mroitioring the plant                                      developing a program of this nature.
-------------------------..4
1. Regulatory Guidance---------------------..4
2. Objectives of the Radiological Environmental Monitoring Program--- 5
 
==C. REGULATORY POSITION==
--------------------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==
----------------------.. 14 GLOSSARY-----------------------------.15
 
REFERENCES---------------------------- 17


BIBLIOGRAPHY--------------------------- 18 Revision 2 of RG 4.1, Page 4
environs totr radioactivity that may lie released from normal oqperations. including anticipated operational                                                                       


==B. DISCUSSION==
==B. DISCUSSION==
Regulatory Guidance Six basic documents contain the regulatory guidance for implementing the 10 CFR Part 20
occurrences, and fion pi!stulated accidents.
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);
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.
Present requirements to keep levels of radioactive Subpala, ,rapih tall 2) of § 50.36a of 10 CFR Part 50                                  material in effluents as low as practicable should assure that radiation doses to the puhlic resulinig front efflutent requires Ihat technical specifications for each license releases will continue to retnain mninimal. The type of include a requirement that the licensee submit a report program described in this guide is considered adequate to the * ('tnniissiotn within 60 days after Janutarv I and to provide information needed to determine whether July I of each year which. iii addition to specifying the exposures in the environment are within prescribed or quantity of each of the principal radionucides released expected limits and to assure that long-term buildup of to unrestricted areas in liquid and airborne effluents specific radionuclides in the environment will not duting the last six months of operation,' provides become hazardous.


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


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


Revision 2 of RG 4.1, Page 6
suitable sample of all exposed population group.


==C. REGULATORY POSITION==
equipment, and techniques.
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,
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). 
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.


Revision 2 of RG 4.1, Page 8 Figure 1.  Routinely Monitored Exposure Pathways
averaged over a time period not exceeding one year.
# 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 ===
would not exceed specified quantities. Section 20.201 of Years of experience at various Contitnissitt facilities
-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." 
  10 CFR Part 20 further requires that a licensee conduct have demonstrated that specific radionuclides behave in surveys of levels of radiation or con1centrations of                                           known ways under given environtmental cottditions.
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.
radioactive itaterial as necessary to show compliance                                          Therefore. comprehensive and detailed envitonlmenial with AIC regiulatioims.                                                                        studies may not be needed at sires wiilh well known
          "riis ginde describe., an acceptable basis for                                                  tCR P          ublication        "7. Iroin4p!            t'"  h'id','rt,o 'tlI
  designing a progrant to measture and report levels of                                          . Io,,itoring Related to thie' Il otdlhig of R idi., t'ti t .1"                    1,alriIt9.


4 While no type of effluent is associated with it, direct radiation is included here because it is an exposure pathway.
Septemher 13. 196S t(henrenin rir It.'RI' I'Ltsicali ,tt I7.


Revision 2 of RG 4.1, Page 9
I At, :acct-t:M,-i" pr,-grti is preseunt.l          its saref    v (.;tide 2 I (to)
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
                                                                                                        tiF r the p        ors'veorf this. guite. thie Ierni "crilicar"t              tit lit, he  re sitsed :,%;: Regtla, try Gttide). "M ,:              avuriniand I~ttep rling (fo Effluents frillr Ncttc'i:r llnwer Narls.'
1.109, then sample media associated with the route of exposure should be added to the REMP 
                                                                                                same meaning as in t'RIt t'uhblication 7. Sipra niote 2.
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.
USAEC REGULATORY GUIDES                                            Copiei of oublishpil gui&ns m'sv be ObtainedI iv 10ourst .rsdic.lting ihe division%
                                                                                                desired io the US. Atomice EitefqV Commtttsi~to, VY-shIM9is..                     D.C. 20Ob45.


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.
Attention: Director of Regultfory Siend~itds. Cofnrmwnis Anil wrgoo'sions tot ResfutAiorv Guide, Wi'. 1su"nf It' dtecr''ts amit flt~i't oAV.,Ihhtt In the p~ublic ir19ifovenerflts int these quidei are en'couraged And %thisuithelenti t) ihes"      5'c~fiatv meiohorb. Acc-titabl- lto the AEC stioclinoirs'taff of mtSiirmoni,roo %s~eci'cpatrts of
   'he Cnmm-n',s~          e.I55      to doiti-.1ie to-chnoriurs used hy the staff in of the Commissuions.     US. Atomic EnetfgYCommisitn. W.Iihinaroin, D.C. 21if"45.


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


==D. IMPLEMENTATION==
S1 s*f14 W911f9.'tthi Of9 tnSIUtSi'd a~ccidenrim
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.
  "aWAiiung                                                    of Is isoisvde 9lwdaneem to The g,,.des ate issu~ed in itshe fotlhvittg tenr btirnd rss S
  With thf-fsitt A '995! Itjit.'ti Mi  'h-c A", soloot-9'5 dii etenl friom those set Dor o the gui~de,        beAcmteilef -1 tt't'v p'ovide i ti.1t9%1(5 the finings i to"I                                                  d    flt9rlufsoi In    1. Pow~erReactor%                                in'. P,oducis ihm. issuane" ot cont~nUAA9CP'Of .. pe~m9o is' teens't, the95'Cnmmosvo'                        2.  Research AndTest Reiclto.'                     7. Itasnsttimti""
                                                                                                  J.  Fuels And Mate.'3s Fscdmtm'                    B. orrciur.1iOn'si 9-J..111t
                                                                                                  4.


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.
Putftshpcj i qud$S.lit 01Il              ~ ,rti,
                                ~t~s~ coI9or.91.'            4199t'    iro-iwrnrcommodi.'
                                                                            In              ..
                                                                                                  5.


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
Environmintat and 5,5mm Material%A"tS'iiPitotwe'rs'etiof
(2) consider supplementing their existing environmental monitoring program with the updated staff guidance.
                                                                                                                                                  '      Anf-l'usl RteW,~
                                                                                                                                                    10) 6--M~s


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


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.
tile envirtomnent. The "'indicator orLalnis1t" concept of'
environmental samplinl"g involves tile practice o I                                        hil'orimalion obthaied f'ront this programn will le examining food chainls for selecied orga;nisins o0r                                  insed. in conjuintetion with data oil radioaclive effluents.


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.
materials which provide a sensitive and reliable mneatsure                          to evaluate mneasulres taken by 'ite licensee to assure that t' (lhe    uti:Uatites of' eac'h (adiolluclide cycling throught                  plantt releases to the environt1ient and radiation doses to each lood chaint. For example.                   ill the case where the              the public are mailntinel wvitlhii              the numerical dose plaitt'cow,'nilk-nian food chain is determined to be a                              limits determined by the Commission io be as low as critical palthway, it may not he necessar Ito extensively                            practicable. Also. licensees' data will be compiled andi sample anld illeasure grazing plants :mnd f'odder to keep                            co III pared. and a comlrprehlensive stimitiray ii 1'
tliack of iodine-I 3l cyclinein fhle food chain. sihce                              radioactivity in thle enivirons of nuttclkear power plants will sampling and nieastiring tile milk produced by dairy                                be prepared by tlie Coimmission.


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


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.
pttogram should be designed in accordance vith the followinug criteria:                                                                                 


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.
==C. REGULATORY POSITION==
 
I.      It should be         based    on    the analysis of" critical                    The      proerani      for    nieasuring  attd reporting  clf pathwayIs        for    the   types      and quanlities of               radioactivity ill the environs ofinuclear power plants radionuclides        released    froni the plant into the                  must provide suitable inf'rs:auion from which levels of stlrtoundine envi rotinten I                                                radiation and radioactivity in the environs of each plait carl be estimated. This inlfornation also may provide
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.     It sihould consider tile possibility of buildup of long                      supporting evidence in evaluating tie perforniance of half-lived radiominclides in the environment and                             systems and equipment installed to control releases of'
 
        identify physical and biological sites of                                   radioactive material it) tile environnenw.
REMP - Radiological Environmental Monitoring Program reporting levels -
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).
TLD - Thermoluminescent Dosimeter unrestricted area - Unrestricted area means an area, access to which is neither limited nor controlled by the licensee.
 
Revision 2 of RG 4.1, Page 18 REFERENCES
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                                               
acctmniutlationt      that ntaty contribute to huniani ex\posures:                                                                        The basic principles set forth in this guide constitute an acceptable basis tor use in establishing an
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.
3.     It should be designed to facilitate use of reported                          en viro ini ental Imonitoring program. These sane levels of radiation and radioactivily in estimating                          principles will also b: used as bases in developing the annual radiation doses to tle public resulting froit                        licensee's corresponding technical specifications.


Revision 2 of RG 4.1, Page 19BIBLIOGRAPHY 
effluents:
10 CFR Part 30, "Rules of General Applicability to Domestic Licensing of Byproduct Material," U.S. Nuclear Regulatory Commission, Washington, DC.
                                                                                    1.    Preoperational Program
4.     It should consider the potential                        daimage    to itttpot tant plants :mud arimals:'a                                                Potential critical pathways should he idemifiied prior to plant operation. l';,e provisions in ICRV
i.    It should be designed to establish correlations                              FPtlblicaiion 7 rela ted to operational releases of between levels of radiation atid radioactivity in the                        radioactivity to the environm-nt should be used as a environment and radioactive releases front plant                            guide in determining critical radionuclides and pathways.


40 CFR Part 141, "National Primary Drinking Water Regulations," U.S. Environmental Protection Agency, Washington, D.C.
Operation. (A variety of lechniques. including                              Other patlhways not directly related to humans should measurements at control locations. preoperational                            also be identified (see regulalory position 2.a. below).
        surveys. correlations with effluent data, and                                Wherevet possible. suitable indicator organisms or media comparisons of operating versus shutdown levels of                          should be identified in each pathway.


ANSI/HPS N13.30, "Performance Criteria for Radiobioassay," American National Standards Institute, New York, NY, May 1996.
===2. Operational Program===
      '-A species. wthethe'r ainin ,tor plant is' "irnport:nlt'" (I) Kit is t'-nimeu 'rciatlv or r.creaLit      ally vaitiau:tule. (2) if it is rare ir e~ndanlge~red.    r 3) ifir t :iffect% thLe' ,vll-te.ing 'it stoF¢ importanI              a.    Sample Media sp¢i*c      wiethin criteri: (I) and (2) ahiivc or (4) if it is critical to fit! structure and function (if (ht ¢crtiogical system. A "rare our                              Where practical. a suitable indicator organisin endulangetred" species is any species cufficiatty tiesignated as such hb the 1).S. Hih and wildlife Service.                                              or ttedium in each critical pathway should be sampled
                                                                              4.1.2


ANSI/ANS-3.11-2005, "Determining Meteorological Information at Nuclear Facilities," American National Standards Institute, New York, NY, December 2005.
:and analyzed for the critical iadomliclidels? released                          Ilt sotmie cases. sat ll)lingll t.1
* ll illttitous b:sis from the plant. An abundant, readily available form with              may be necessar\ (e.g.. air samttplinig and co,]ItitIotIs nowt habits should be selected.                                    mile astire ie Illt    f. c u ttInlaIive exterit1al ,:dia, itin exposure). Composites of some selected s:aiple types.


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


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


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


ANSI/NCSL Z540-2-1997 (reapproved 2002), "American National Standard for Expressing Uncertainty
radionuclides in , critical FpatlIway.
-U.S. Guide to the Expression of Uncertainty in Measurement," American National Standards Institute, New York, NY, January 1997.


EPRI Report No. 1011730, "Ground Water Monitoring Guidance for Nuclear Power Plants," Electric Power Research Institute, Palo Alto, CA, September 2005.
c. Program Scope WhcLtre use of a single indicator tneditim is During (hft initial three years of commercial impractical. samples of' several media from each pathway power operation (or other period corresponditie to should be collected and analyzed. The C(ommission maximum fuel burnup it] the initial core cycle). tihe recomizes that some pathways do not have more than olne eiviromnittillal meditiht. c... external radialion mecastirememti program shotuld be relatively c11muipre- nensive in an attempt to verify anys' pr,*iected torle- exposures from clotds of uatnima-ray-emittitog radio- lations between radioactivc eflltuilts attd levels in nclides inlvol-.. onlV onle paithway          the atmosphere.


"Liquid Radioactive Release Lessons Learned Task Force Final Report," U.S. Nuclear Regulatory Commission, Washington, DC, September 2006. (ADAMS Accession No. ML083220312)
environtmental media. The extetnt of measturettent of The actual tit:uhier of' media it he sampled in each environnmental media should be flexible and should pathwlay will be determined oni a case-by.case basis for depend on the type. quantity. and concentration of each site. Itt some cases field measurements may be radionuclides from the plant as well as the results prelerable to collecting samples for laboratory analysis.


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.
obtained from previotus nmeasurements.


NUREG-0475, "Radiological Environmental Monitoring by NRC Licensees for Routine Operation of Nuclear Facilities," October 1978.
O            The program should include sampling of                              1f. after this period. the licensee is able to environmental media to estimate average radionuclide                demonstrate from levels in environutetumal media or concentrations in important biota (see B.4. above).                  calculations (using measured effluents and appropriate Radiation exposures (external) and internal doses from              dispersion and bioaccumulation factors) that the doses short half-lived nuelides may be estimated by                        from a particular pathway are sufficiently small, the calculationrs (,tisin g e[floeii          mn easuremen ts and        number of media sampled in the patlihway and the appropriate dispersion and concentration factors) rather            frequency of sampling may be reduce


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


RIS 2008-03, Return/Reuse of Previously Discharged Radioactive Effluents, U.S. Nuclear Regulatory Commission, Washington, DC, February 2008.
predictionls.


Revision 2 of RG 4.1, Page 20
d.    Analyses h.  Sampling Frequency Samples should he analyzed for the critical When a critical radionuclide has a short hallflife      radionticlide(s) released from the plani. (Gross belta and Imtinutes to days). it may be necessary to evaluate                  gainnia analyses of samples stuch as air and fresh water radiation expUsure by tuaking measurements in the field              may be useful to indicate that the concenltralioni of a (e.g.. by use of thermoluminescen t dosimeters or                    critical radionuclide is not greater thall the delectioll portable multichannel gamma spectrometers).                         capability for that nuclide.
  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.
When ;I critical radionuclide with an                    3.    Detection Capabilities internnediate half-life (weeks to months) is released continuotisly or frequently. sampling and analysis of                      The detection capabilities associated with ,1,eaisiritmg etvirotlneinial media in the critical pathway should                and atinalvzitt radioactivity levels shotild he eSltablished
. generally be carried omt at inltervals no greater than two          primarily on the basis of poleittial hutnatt dose. The least or 'h ree half-lives of tIte      iuclide. For long half[liife      detectable dose will vary from facilitvy to facility dionuclides (years). measurements should be made at              depending on the critical pathways ideI iifled arm              d IItC
    st once per year. Where seasonal eflects            ,ay be      stalof-tl'-he-art of sampling and analysis in these important. sampling should be on a quarterly or at least            pathways. Because of tie need for a preoperational semiannual basis.                                                   monitoring program, detectiot capabilities for a
                                                                4.1-3


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.
W
  pat tcular piorat11 should he deternmined during :n early                            alpprolri:e. Trie licensee should demtostiale that aill staLc of licensing. The staff rc,.ognizes that direct                                assutittiolts. parameters and methods, used are adcqumtte tmeeas uremtetn ts of envirotnml enltal Imredia cannot1 alvays                      and compieleIto allow Itwhere data pertii) a c omparison            ,
          'cctetlruepo levels                    -dine to Commissiti design                with predicted concei.ratitms and doses based ol
    , Iieclites. Nevertheless. every reasonable effort should                        effluents from each nuclear power plant under license.


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.
be made to achieve detection capabilities which will                                (See Safety (uide 21).
dewclt ratdiition levels or radioactiVityI ol0cent-rat ions ill critical pathways that could result in radiatiom doses                                      To petlmit comparison of signi'icart entvironmental cor respudindg to a 11ew 1'ercen t of thie Federal Radiation                          mIolnitoritng data willh predicted eoncent ratiotls anid doses
(',tmcil's radiation protection guides Ie.g.. a ftw percent                          (bhaid on reluiretletts ol' I0 CFR Part 50). the report i! !70 mren'years for whole body dose to a stiiable                                  should include Ilie following i tents for each
-ample tithe exposed population ).                                                    enviro*mttlenttal tttedii: :1:
  4.        Reporting of Results                                                            a.    Samnple Type I. Biological (it tile extent practicable. list Data sholtld he reported to the Commission in the                        specics. life' stage. age. weight or size. biolog.ical r..,ort suhmitted within t,-0 days aflter January I and                            conditiot, tissue or m1terial sampled. sample weight.


Regulatory Guide 1.23, "Meteorological Monitoring Programs for Nuclear Power Plants," U.S. Nuclear Regulatory Commission, Washington, DC.
July I of each year.' InI the eveut that all unexpected                              etc.).
  mclea,ýe iln radjoaCtivMI or r:diation levels is measured in                                    2. Non-Biological (identify type - soil, air.


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.
a p-Mricular critical pathway. the Commnission should he                            etc.: list actual area. depth and weight or volume not, fied prontptl.. Appropriate levels and reporting                              sampled as appropriate, whether grab or continuous inetvals will he determined on an individual plant basis                            sample. number of samples. etc.).
  and included in the technical specifications for each                                      b. Sample Localtion (also !tipply mtap showing license.                                                                            locations)
                                                                                            c. Collection Period (continuous samples) or Dale The Commission utilizes the data from these reports                      of Collection to provide assurance that man and his environment are                                      d. Critical Pathway not heinu subjc,:ted It unacceptable radiation exposures.                                  e. Radionuclide Consequently. all assumptions. parameters and methods                                        f. Concentration (mCi/ml or g. specifying wet or used to measure and report radioactivity concentrations                              standard dry. weight) and/or Deposilion (jiCi/mh                  ori and radiation levels should be specified in the licensee's                            other apprupriate units of tteastire). (List conversionti, initial report aid updated in subsequent reports as                                  factors relating sample activity and volume - depth X
                                                                                      cross section - It) total area deposition: average and s t-'d,.at      Radiatiiin  Councit  Report    No.  I. bIac'kgroutnd      ttlaXIillttt values (for each medium. etc.)
.llawrnelkrth'e"Dere'ml-Feat '',.RadiathOnPro'tetion Srandards.


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.
IaJ3. 19 h (.                                                                    


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.
====g. Background Value====
                                                                                                                        7


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.
====h. Analytical Method====
        ";uhpalragraph        (a)(2)  of  *50.3fia  (,f  1o C0 R Part 50
                                                                                            j. Comparison of Observed Concentrations.


Regulatory Issue Summary (RIS) 2008-03, "Return/Re-use of Previously Discharged Radioactive Effluents," U.S. Nuclear Regulatory Commission, Washington, DC, February 13, 2008.
requites the subtinjsimi or a report within ot, d-'s after Jainuary I :ie-d Jul ' Ii f eacit )'ear speciriflin the quantitv of eac oliht .              Depositions and Estimated Doses with Predicted Values prin` iial radimiuclidts released lto unrestricted areas in liquid                    (based on effluent measurenments)
andll in g'awous erffenlt%. the duta taken in suppnrt of the lite'i.ee'" en.-iroiitnential monitoring programn shriuld also he j.     Remarks (be sure to explain any tititstal
,,jonmia ltd s;emiannually. Ir additional lime is needed, the repnrt                  measurements or deviations).
stler*th            indicane :md the d*t:n shoulJ he carried o*er into the
                .sit;
Io'et ,emiannua:ll report. it would greatl, r:ocililgte comparismns rnd 7.'ierrlaitil        ot    t ta if the en sir.*inieint    3ind  effluent          'I .stim-mtes i)f the error assoeinted with the: measurement of niaiateirilg dat.a m.ere .mnihtited ilnto single reports.                            each environmental medium should he reported.


SECY-03-0069, "Results of the License Termination Rule Analysis," U.S. Nuclear Regulatory Commission, Washington, DC, May 2, 2003.}}
O0
                                                                                4.1.4}}


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

Latest revision as of 00:28, 20 March 2020

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

DIRECTORATE OF REGULATORY STANDARDS

GUIDE

REGULATORY GUIDE 4.1 MEASURING AND REPORTING OF RADIOACTIVITY

IN THE ENVIRONS OF NUCLEAR POWER PLANTS

A. INTRODUCTION

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

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

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

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

B. DISCUSSION

occurrences, and fion pi!stulated accidents.

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

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

W

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

suitable sample of all exposed population group.

equipment, and techniques.

averaged over a time period not exceeding one year.

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

4.

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

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

In ..

5.

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

' Anf-l'usl RteW,~

10) 6--M~s

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

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

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

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

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

cow\s in stirrotndine areas may be :dequate.

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

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

pttogram should be designed in accordance vith the followinug criteria:

C. REGULATORY POSITION

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

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

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

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

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

effluents:

1. Preoperational Program

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

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

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

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

2. Operational Program

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

4.1.2

and analyzed for the critical iadomliclidels? released Ilt sotmie cases. sat ll)lingll t.1
  • ll illttitous b:sis from the plant. An abundant, readily available form with may be necessar\ (e.g.. air samttplinig and co,]ItitIotIs nowt habits should be selected. mile astire ie Illt f. c u ttInlaIive exterit1al ,:dia, itin exposure). Composites of some selected s:aiple types.
  • Careftul attenttioni should ble given to avoid such as air filters. niav be appropriate I'm" meastmrettiettt insdt(tLSng serious stress onl art ihmportan't species otf ot long-lived madi nit ticlides.

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

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

radionuclides in , critical FpatlIway.

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

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

obtained from previotus nmeasurements.

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

d. An adequate

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

predictionls.

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

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

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

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

4.1-3

W

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

IaJ3. 19 h (.

g. Background Value

7

h. Analytical Method

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

j. Comparison of Observed Concentrations.

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

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

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

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

.sit;

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

O0

4.1.4


Retrieved from "https://kanterella.com/w/index.php?title=Regulatory_Guide_4.1&oldid=2635262"