ML003739345

Draft Regulatory Guide DG-8004, Radiation Protection Programs for Nuclear Power Plants

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Issue date:	10/31/1991
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CO U.S.

NUCLEAR REGULATORY COMMISSION October 1991 OFFICE OF NUCLEAR REGULATORY RESEARCH Division 8 Task DG-8004 DRAFT REGULATORY GUIDE

Contact:

A. K. Roecklein (301) 492-3740 DRAFT REGULATORY GUIDE DG-8004 RADIATION PROTECTION PROGRAMS FOR NUCLEAR POWER PLANTS A.

INTRODUCTION Section 20.1101, "Radiation Protection Programs," of 10 CFR Part 20, "Standards for Protection Against Radiation," requires licensees to establish and use radiation protection programs.

In addition, 10 CFR 20.1101(b) requires that procedures and engineering controls based upon sound radiation protection principles be used, to the extent practicable, to achieve occupational doses and doses to the members of the public that are as low as is reasonably achievable (ALARA).

(ALARA and other terms are define~in the appendix to this guide.)

Furthermore, 10 CFR 20.2102 requires tý,,at',records of radiation protection pro grams be maintained, and 10 CFR 20.2102(b) provides the requirements for reten tion of records.

This guide describes the majo'r elem'ients of a nuclear power plant's radiation protection program that is'*cacceptable to the NRC staff.

Any information collection activities mentioned in this draft regulatory guide are contained as requi"rements in 10 CFR Part 20, which would provide the regulatory basis for this guide. Part 20 will be submitted to the Office of Management and Budget ifor cleArance that may be appropriate under the Paperwork Reduction Act.

Such clearance, if obtained, would also apply to any information collection activities mentioned in this guide.

This regulatory guide is being issued in draft form to involve the public in the early stages of the develop ment of a regulatory position in this area.

It has not received complete staff review and does not represent an official NRC staff position.

Public comments are being solicited on the draft guide (including any implementation schedule) and its associ ated regulatory analysis or value/impact statement.

Comments should be accompanied by appropriate supporting data.

Written comments may be submitted to the Regulatory Publications Branch, DFIPS, Office of Administra tion, U.S. Nuclear Regulatory Commission, Washington, DC 20555.

Copies of comments received may be examined at the NRC Public Document Room, 2120 L Street NW.,

Washington, DC.

Comments will be most helpful if received by January 3, 1992.

Requests for single copies of draft guides (which may be reproduced) or for placement on an automatic distri bution list for single copies of future draft guides In specific divisions should be made In writing to the U.S. Nuclear Regulatory Commission, Washington, DC 20555, Attention:

Director, Division of Information Support Services.

B.

DISCUSSION Establishing and conducting effective radiation protection programs at commercial nuclear power plants is considered to be important to ensure that individual and collective radiation exposures of employees and members of the public under the licensee's program are below the regulatory dose limits and are ALARA.

The ALARA concept is an integral part of the overall radiation protection program.

Although the NRC staff recognizes that licensees generally establish their own administrative control levels below the dose limits specified in the regulation, the NRC staff does not recommend any specific dose values for use as administrative control levels.

Licensees are encouraged to selectively use quantitative analyses to specify ALARA levels (see ICRP Publication No.

37, Ref. 1).

The quantitative approach is useful for situations in which both costs and benefits (dose reduc tion) can be quantified, such as for shielding design or analysis of large-scale equipment or system decontamination methods.

ALARA practices involve the bal ancing of costs and benefits, not dose minimization.

Furthermore, the magnitude of both individual and collective doses may be important to an analysis.

How ever, many ALARA implementing procedures, though based on sound operating practice, do not lend themselves to a quantified analysis.

Control of the sources of the radiation fields that result in occupational radiation exposure, "radiation source control," is an important component of the radiation protection program at a nuclear power plant.

Radiation source control is being accomplished through chemical control, cobalt source replacement, pre conditioning of metal surfaces, and decontamination, particularly chemical decontamination.

Although some aspects of radiation source control have been considered to be a part of the ALARA effort, radiation source control is included separately in this guide to emphasize its importance in controlling occupational radiation exposure.

Additional information on radiation protection programs for commercial nuclear power plants can be found in Section 12 of the NRC Standard Review Plan, "Radiation Protection" (Ref.

2).

This guide supplements and is consistent with previous guidance documents on radiation protection programs at commercial nuclear power plants, for example, Regulatory Guide 8.8, "Information Relevant to Ensuring that Occupational 2

Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable" (Ref.

3).

C.

REGULATORY POSITION

1.

GENERAL Radiation protection programs for nuclear power plants should describe the organization, training, procedures, and conduct of operations used by that par ticular plant and organization.

The details of each program should reflect the specific features and operating practices of the individual plant (e.g., surveys or surveillance frequencies, administrative limits on exposures).

More specifically, the radiation protection program should include eight basic elements, as illustrated in Figure 1, which can be grouped into three areas.

1. Establishment of the program with its associated organization and corporate policy, along with the qualification and training of the power plant staff;

2.

Conduct of the day-to-day radiation protection program; and

3.

Evaluation of the quality, content, and effectiveness of the program activities.

2.

ESTABLISHMENT OF A RADIATION PROTECTION PROGRAM The facility management's policy on radiation protection should be clearly stated and should include the following:

1. Written standards for strict adherence to radiation protection requirements;

2.

Periodic evaluations of radiation protection performance;

3.

Holding personnel accountable for their individual performance; and

4.

Quantitative and qualitative annual goals for program improvement.

Senior corporate and plant management should strongly support the radiation protection program by providing sufficient resources, becoming personally 3

FIGURE 1 ELEMENTS OF AN EFFECTIVE RADIATION PROTECTION PROGRAM Organization and Administration S Qualification and Training Control of the Workplace Conduct Prooram Radiation Source Control Dose Limits ALARA Surveillance Radioactive Material Control Contamination Control Work Practices Waste Management Compliance Evaluation Release Consequence Assessment Effluent Monitoring Environmental Monitoring and Dose Assessment Evaluate Program Performance 4

I Establish Progoram

involved in monitoring radiation protection performance, and holding workers, supervisors, and line managers accountable for their radiation protection performance.

Principal aspects of an effective radiation protection program include organization and administration as well as and qualification and training.

2.1 Organization and Administration The description of the radiation protection organization should provide details on the following:

1. Functions of individual components within the radiation protection organization;

2.

Radiation protection functions and responsibilities of support organizations other than the radiation protection organization, e.g.,

operations and engineering;

3.

Minimum staffing required, by shift, for each component in the radiation protection organization;

4.

Radiation protection functions performed by contractor services (especially those functions performed during outages unique to the situation being addressed);

5.

Radiation protection functions performed by a corporate or centralized licensee organization, including the responsible individuals by position and their responsibilities; and

6.

Functions and assignments of those persons with responsibilities in emergencies.

(See NUREG-0654, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of'Nuclear Power Plants," Ref. 4.)

Reference to an NRC-approved emer gency plan is acceptable.

The organizational structure of the plant should be such that the radiation protection manager has direct access to the plant manager on matters concerning radiation protection.

(See Regulatory Position L.b(3) of Regulatory Guide 8.8, Ref. 3.)

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2.2 Qualification and Training The following formal training, qualification, and retraining programs should be developed and implemented:

1.

Training of general employees for restricted area access, as specified in § 19.12, "Instructions to Workers," of 10 CFR Part 19, "Notices, Instructions, and Reports to Workers; Inspections"; and

2.

Training for radiation workers for access to and work in radiation areas, high radiation areas, very high radiation areas, and airborne radioactivity areas.

Documented testing should be conducted to demonstrate an individual's proficiency after the completion of training and before the assignment of cri tical safety functions.

Testing may also be used to confirm prior training and experience.

3.

CONDUCT OF THE PROGRAM An effective radiation protection program includes radiation exposure control, control of the workplace, and release consequence assessment.

3.1 Radiation Exposure Control To control radiation exposure, the radiation protection program includes radiation source control, methods to ensure compliance with regulatory dose limits, application of ALARA principles to each aspect of radiation exposure control, and surveillance of the work environment.

3.1.1 Radiation Source Control The radiation protection program should include methods for controlling the sources of radiation fields that result in occupational radiation exposure.

These methods include, but are not necessarily limited to, chemistry control, cobalt source replacement, preconditioning of metal surfaces, and decontamination (including chemical decontamination).

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3.1.2 Dose Limits A dose control system should be established for evaluating, controlling, monitoring, and recording doses.

Occupational exposure is controlled by regu lating both external and internal exposures.

Guidance is being developed in a new draft regulatory guide, "Criteria for Monitoring Thresholds and Procedures for Summation of Internal and External Occupational Doses," that will provide guidance on summing external and internal doses.

Administrative dose control levels can be used by the licensee to help ensure that personnel exposures do not exceed regulatory dose limits.

These control levels also provide a manage ment tool for ensuring that individual and collective doses are as low as reasonably achievable.

External radiation exposures are controlled by incorporating ALARA considerations in the facility design as well as in system modifications, establishing administrative exposure controls, providing radiation exposure monitoring of personnel, and identifying and controlling sources of external radiation exposure in the facility.

Internal radiation exposure is controlled by identifying and controlling sources of surface contamination and airborne radioactivity, maximizing engi neered control of airborne radioactive material, monitoring work spaces for air borne radioactivity, establishing administrative exposure controls, optimizing the use of respiratory protective equipment, and monitoring workers for internal uptake of radionuclides.

3.1.3 ALARA Principles Licensee activities for meeting the ALARA requirement in 10 CFR 20.1101(b) should include measures to track and reduce exposures.

The licensee should conduct periodic reviews of performance to be sure that efforts have been made to achieve ALARA goals.

The licensee should also demonstrate that administrative control levels, designed to help keep doses to individuals well below the dose limits, have been selected as part of the radiation protection program and that a procedure for investigating conditions that cause or permit these levels to be exceeded has been established.

The radiation exposure control element of the radiation protection program should address ALARA principles in the following areas.

(See Regulatory Guide 8.8 (Ref.

3) for more detailed information.)

7

Control of access to radiation areas Radiation shielding Process instrumentation and controls Control of airborne contaminants and gaseous radiation sources Crud control Isolation and decontamination Resin and sludge treatment systems A licensee should have an administrative dose control system that tracks both planned and actual doses to individuals, especially when doses approach the administrative limits established for the facility or the annual dose limits of 10 CFR 20.1201.

In addition, the licensee's dose recordkeeping system should permit analysis for trends and ALARA purposes.

Tasks that involve significant total exposure should be reviewed by higher level management, such as the radiation protection manager.

Criteria should be established for approving tasks that involve high individual or collective doses.

Additional guidance on incorporating the ALARA principle into a radiation protection program, including area controls, monitoring, and radiation work practices, is provided in Regulatory Guide 8.8 (Ref. 3).

Further guidance is being developed in draft regulatory guides "Planned Special Exposures," and "Control of Access to High and Very High Radiation Areas in Nuclear Power Plants" that will be issued soon.

3.1.4 Surveillance The radiation protection program should ensure that the facility is adequately equipped for monitoring in-plant radiation, contamination, and air borne radioactivity for a broad range of routine and accident conditions.

The surveillance procedures should describe:

1.

The frequency required for surveys for radiation, radioactive contamination, airborne radioactivity, and location of radioactive materials;

2.

Situations for which surveys are required;

3.

Nature and extent of the surveys;

4.

Equipment to be used in the surveys; 8

5.

How the surveys will verify the radiological status of all facility areas; and

6.

How the survey data will be used in planning work, writing procedures, issuing radiation work permits, and performing similar functions.

3.2 Control of the Workplace The radiation protection program should address methods of controlling radioactive materials, contamination, work practices, and radioactive waste, as well as the individual's responsibility in the workplace.

3.2.1 Control of Radioactive Materials The description of the radiation protection program should address the means and responsibilities for the control, movement, storage, and inventory of radio active materials outside of controlled areas; for identification, control, move ment, and storage within controlled areas; and for receipt and shipment of radio active materials.

The description should also present criteria for the release of materials from controlled areas for use in uncontrolled areas.

3.2.2 Control of Contamination Radioactive contamination of areas, equipment, and personnel should be strictly controlled.

Control of radioactive surface contamination helps prevent contamination of personnel and equipment, reduces inhalation of radioactive materials by personnel, reduces skin dose from small' particles containing radio active material, and reduces the spread of radioactivity to the environment from operation of the nuclear facility.

3.2.3 Work Practices An integrated approach to work planning and work practices should include:

1.

Job-specific training, including the use of facility and equipment mock-ups when appropriate;

2.

Control of work in radiation areas to ensure that exposures are maintained ALARA and radiation protection procedures are properly carried out, especially for work involving high-activity radiation sources, highly contaminated materials, relatively high individual or collective doses, or complex protective measures; 9

3.

Establishment of radiation protection standards and responsibilities to control work, including the use of radiation work permits; and

_b

4.

Program evaluations as discussed in Regulatory Position 4 of this guide.

An effective radiation work permit (RWP) program should include training and a clear description of authorities and responsibilities within the program, and it should be integrated with other control activities.

3.2.4 Waste Management Control of solid radioactive waste is an integral part of plant operations and an indicator of the quality of the facility's radiation protection program.

The program should address control of solid radioactive waste to ensure safe packaging of radioactive materials for transportation and to minimize the volume of radioactive waste generated.

The volume of solid radioactive waste can be minimized by vigorous implementation of the ALARA principle in work practices.

Many of the techniques used to control exposures to ALARA levels, such as work planning and use of good contamination-control practices, result in a decrease in the amount of waste generated.

3.2.5 Individual Responsibility Day-to-day activities related to radiation protection should be conducted in a manner that adheres to "good operating practices."

Individuals should be encouraged to maintain a high degree of awareness of their own work practices and those of other personnel, to maintain high standards for quality, and to comply with the plant's radiation protection requirements.

3.3 Release Consequence Assessment Assessing the consequences of radioactive releases should include effluent monitoring, environmental monitoring, and dose assessment.

3.3.1 Effluent Monitoring Section 20.1302 requires measurement of radioactive material in effluents to unrestricted areas to demonstrate compliance with the annual dose limit for individual members of the public.

In addition, 10 CFR 50.36a, "Technical Speci fications on Effluents from Nuclear Power Reactors," and Appendix I to 10 CFR 10

Part 50, "Domestic Licensing of Production and Utilization Facilities," require that radioactive effluents to unrestricted areas in the environment be kept as low as is reasonably achievable.

Detailed requirements for effluent monitoring programs have historically been contained in the technical specifications (TS) that are part of a nuclear power plant's operating license.

This situation has changed somewhat with the promulgation of Generic Letter (GL) 89-01 (Ref.

5).

GL 89-01 allows licensees, on a voluntary basis, to transfer the detailed requirements for such programs to the offsite dose calculation manual (ODCM),

leaving only general requirements for effluent monitoring programs remaining in the technical specifications.

Independently of GL 89-01, the technical specifications also require that an ODCM contain the methodology and parameters used for (1) determining the alarm/

trip set points for the effluent monitors and (2) calculating offsite doses from the plant's effluents.

Additional guidance on measuring, evaluating, and reporting radioactive effluents and the calculation of offsite doses from the effluents is provided by 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. 6); Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appen dix I" (Ref. 7); Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light Water-Cooled Reactors" (Ref. 8); Generic Letter 89-01, "Implementation of Pro grammatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Reloca tion of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program" (Ref. 5); and NUREG-0133, "Preparation of Radio logical Effluent Technical Specifications for Nuclear Power Plants" (Ref.

9).

3.3.2 Environmental Monitoring and Dose Assessment Radiological environmental monitoring programs are required to provide data on measurable levels of radiation and radioactive materials in the site environs.

Section 20.1302 requires surveys of radiation levels in unrestricted areas to demonstrate compliance with the annual dose limit for individual members of the public.

In addition, Appendix I to 10 CFR Part 50 requires evaluation of the 11

relationship between the quantities of radioactive material released in effluents during normal operation and the resultant radiation doses to individuals from the principal environmental pathways of exposure.

An example of an acceptable minimum environmental monitoring program, a Branch Technical Position "An Acceptable Radiological Environmental Monitoring Program" (Ref.

10), was provided to nuclear power plant licensees.

Further information on the basis and rationale for radiological environmental monitoring programs is available in NUREG-0475, "Radiological Environmental Monitoring by NRC Licensees for Routine Operations of Nuclear Facilities" (Ref. 11); and Health Physics Society Committee Report HPSR-1, "Upgrading Environmental Radiation Data" (Ref.

12).

4.

EVALUATE PROGRAM PERFORMANCE The third area of an effective radiation protection program consists of active self-evaluation of the content and quality of the program activities.

Corporate management and experts from outside the facility should perform inde pendent reviews of the facility's program, which may include suggested goals and standards that foster improvements in the program.

4.1 Trends and Deficiencies Plant performance in radiological protection should be monitored through the identification, evaluation, and recording of radiological protection prob lems and trends.

The recording system should include a tracking and analysis feature to identify trends in work practices and in the control of radiation exposure, contamination, and airborne radioactivity.

This information can be used to improve the radiation protection program.

ANSI N13.6, "Practice for Occupational Radiation Exposure Records Systems" (Ref.

13), describes the use of records related to review of radiation protection programs.

Licensees should establish a system, with appropriate criteria, to identify and track radiation incidents, unusual occurrences, and deficiencies related to radiation protection, as well as to evaluate the circumstances and root causes of these situations.

12

4.2 Corrective Action and Follow-up Short-and long-term corrective actions should be developed to preclude recurrence of radiation incidents or deficiencies, as well as to preclude the development of adverse trends.

Lessons learned from analyses of previous experience should be integrated into the system.

4.3 Reviews and Audits The purpose of reviews and audits is to:

1.

Identify areas where present performance, if continued, could result in noncompliance with Federal and licensee radiation protection requirements;

2.

Evaluate performance using data on individual dose, collective dose, and dose trends;

3.

Identify work practices that could be improved, particularly those that result in unnecessary radiation exposure;

4.

Evaluate the effectiveness of the radiation protection training; and

5.

Identify radiation control problems and determine the root causes of radiation protection incidents.

Reviews and audits should incorporate the following features to assess procedural compliance, technical performance, implenientation, and effectiveness of the facility radiation protection program.

"* Radiation protection supervisory reviews Onstte radiation protection supervisors should periodically perform and document reviews of the effectiveness of the radiation protection staff in such areas as radiological work practices, work monitoring, procedural compliance, and survey adequacy.

"* Quality assurance audits Quality assurance audits should be performed by the onsite auditing group.

Personnel in the auditing group should have sufficient radia tion protection training or experience so they can determine whether 13

radiation protection functions are being performed as required.

The quality assurance program audits should meet the requirements of Appendix B to 10 CFR Part 50.

Corporate or contract audits Offsite (corporate or contract) audits and evaluations should be performed to determine whether the radiation protection program com plies with the regulations and other requirements and whether plant wide objectives are being met as well as to identify needed program improvements.

D.

IMPLEMENTATION This section of the guide provides information to license applicants and licensees regarding the NRC staff's plans for using this regulatory guide.

This draft guide has been released to encourage public participation in its development.

Except in those cases in which an applicant proposes an acceptable alternative method of complying with specified portions of the Commission's regulations, the method to be described in the active guide reflecting public comments will be used in the evaluation of applications for license renewal or new licenses and for evaluating compliance with 10 CFR 20.1001-20.2401.

Adop tion of the revised 10 CFR Part 20 is not required until January 1, 1993.

14

REFERENCES

1.

International Commission on Radiological Protection, "Cost Benefit Analysis in the Optimization of Radiation Protection," ICRP Publication No.

37, Annals of the ICRP, Vol.

10, No (2/3), 1983.

2.

U.S. Nuclear Regulatory Commission, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants --

LWR Edition," Section 12, "Radiation Protection," NUREG-0800,* July 1981.

3.

U.S. Nuclear Regulatory Commission, "Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable," Regulatory Guide 8.8,* Revision 3, June 1978.

4.

U.S. Nuclear Regulatory Commission, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," NUREG-0654,* February 1980.

5.

U.S. Nuclear Regulatory Commission, "Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Pro cedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program, (Generic Letter 89-01)," which is Appendix C in "Offsite Dose Calculation Manual Guidance:

Standard Radiological Effluent Controls for Pressurized Water Reactors," NUREG-1301,* April 1991; and in "Offsite Dose Calculation Manual Guidance:

Standard Radiological Effluent Controls for Boiling Water Reactors," NUREG-1302,* April 1991.

• Available for copying for a fee or inspection in the NRC Public Document Room, 2120 L Street NW.,

Washington, DC; or for sale at the U.S. Government Printing Office, P.O. Box 37082, Washington, DC 20013-7082, and at the National Tech nical Information Service, 5285 Port Royal Road, Springfield, VA 22161.

15

6.

U.S. Nuclear Regulatory Commission, "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,"

Regulatory Guide 1.21,* Revision 1, June 1974.

7.

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

Revision 1, October 1977.

8.

U.S. Nuclear Regulatory Commission, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Regulatory Guide 1.111,* Revision 1, July 1977

9.

U.S. Nuclear Regulatory Commission, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG-0133,* November 1978.

10.

U.S. Nuclear Regulatory Commission, "An Acceptable Radiological Environ mental Monitoring Program (NPPs)"

(Revision 1, November 27, 1979), which is Appendix A in "Offsite Dose Calculation Manual Guidance:

Standard Radiological Effluent Controls for Pressurized Water Reactors,"

NUREG-1301,* April 1991; and in "Offsite Dose Calculation Manual Guidance:

Standard Radiological Effluent Controls for Boiling Water Reactors,"

NUREG-1302,* April 1991.

11.

U.S. Nuclear Regulatory Commission, "Radiological Environmental Monitoring for Routine Operations of Nuclear Facilities Operated by NRC Licensees,"

NUREG-0475,* November 1978.

12.

"Upgrading Environmental Radiation Data:

Health Physics Society Committee Report HPSR-1,"

EPA 520/1-80-012 (PB-81-100364),

Environmental Protection Agency, Washington, DC, August 1980.

13.

American National Standards Institute, "Practice for Occupational Radiation Exposure Records Systems," ANSI N13.6-1966 (Revised 1982), 1982.

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APPENDIX Definitions ALARA (acronym for "as low as is reasonably achievable") means making every reasonable effort to maintain exposures to radiation as far below the dose limits in the revised 10 CFR Part 20 as is practical consistent with the purpose for which the licensed activity is undertaken, taking into account the state of technology, the economics of improvements in relation to state of technology, the economics of improvements in relation to benefits to the public health and safety, and other societal and socioeconomic considerations, and in relation to utilization of nuclear energy and licensed materials in the public interest.

Collective dose is the sum of the individual doses received in a given period of time by a specified population from exposure to a specified source of radiation.

Dose or radiation dose is a generic term that means absorbed dose, dose equivalent, effective dose equivalent, committed dose equivalent, committed effective dose equivalent, or total effective dose equivalent, as defined in 10 CFR 20.1003.

Dose equivalent (HT) means the product of the ab'sorbed dose in tissue, quality factor, and all other necessary modifying factors at the location of interest.

The units of dose equivalent are the rem and sievert (Sv).

Exposure means being exposed to ionizing radiation or to radioactive material.

Individual means any human being.

Licensee means the holder of a license.

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 the results of these measurements to evaluate potential exposures and doses.

17

NRC means the Nuclear Regulatory Commission or its duly authorized representatives.

Occupational dose means the dose received by an individual in a restricted area or in the course of employment in which the individual's assigned duties involve exposure to radiation and to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person.

Occupational dose does not include dose received from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the general public.

Radiation (ionizing radiation) means alpha particles, beta particles, gamma rays, x-rays, neutrons, high-speed electrons, high-speed protons, and other particles capable of producing ions.

Radiation, as used in this part, does not include non-ionizing radiation, such as radio-or microwaves, or visible, infrared, or ultraviolet light.

Survey means an evaluation of the radiological conditions and potential hazards incident to the production, use, transfer, release, disposal, or presence of radioactive material or other sources of radiation.

When appropriate, such an evaluation includes a physical survey of the location of radioactive material and measurements or calculations of levels of radiation, or concentrations or quantities of radioactive material present.

18

REGULATORY ANALYSIS A separate regulatory analysis was not prepared for this regulatory guide.

The regulatory analysis prepared for 10 CFR Part 20, "Standards for Protection Against Radiation" (56 FR 23360), provides the regulatory basis for this guide and examines the costs and benefits of the rule as implemented by the guide.

A copy of the "Regulatory Analysis for the Revision of 10 CFR Part 20" (PNL-6712, November 1988), is available for inspection and copying for a fee at the NRC Public Document Room, 2120 L Street NW.,

Washington, DC, as an enclosure to Part 20.

19

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