Consolidated Guidance 

About Materials Licenses

Program-Specific Guidance 

About Portable Gauge Licenses

Final Report

Office of Nuclear Material Safety and Safeguards

NUREG-1556

Volume 1, Rev. 2 

Consolidated Guidance 

About Materials Licenses

Program-Specific Guidance 

About Portable Gauge Licenses

Final Report

Manuscript Completed: May 2016 

Date Published: June 2016

Prepared by: 

J. Cook

T. Herrera

B. Juran

S. Lodhi

K. McDaniel

J.R. Mullauer

M. Reichard

Office of Nuclear Material Safety and Safeguards

NUREG-1556

Volume 1, Rev. 2 

iii

ABSTRACT

This technical report contains information intended to provide program-specific guidance and 

assist applicants and licensees in preparing applications for materials licenses for portable 

gauges. In particular, it describes the types of information needed to complete U.S. Nuclear 

Regulatory Commission (NRC) Form 313, “Application for Materials License.” This document 

describes both the methods acceptable to the NRC license reviewers in implementing the 

regulations and the techniques used by the reviewers in evaluating the application to determine 

whether the proposed activities are acceptable for licensing purposes.

Paperwork Reduction Act Statement

This NUREG references information collection requirements that are subject to the Paperwork 

Reduction Act of 1995 (44 U.S.C. 3501 et seq.). These information collections were approved 

by the Office of Management and Budget (OMB), approval numbers 3150-0001, 3150-0008,

3150-0014, 3150-0017, 3150-0035, 3150-044, 3150-0214, and 3150-120.

Public Protection Notification

The NRC may not conduct or sponsor, and a person is not required to respond to, a request for 

information or an information collection requirement unless the requesting document displays a 

currently valid OMB control number.

v

FOREWORD

The U.S. Nuclear Regulatory Commission’s (NRC’s) NUREG–1556 technical report series 

provides a comprehensive source of reference information about various aspects of materials 

licensing and materials program implementation. These reports, where applicable, describe a 

risk-informed, performance-based approach to licensing consistent with the current regulations. 

The reports are intended for use by applicants, licensees, license reviewers, and other NRC 

personnel. The NUREG–1556 series currently includes the following volumes:

Volume No. Volume Title

1 Program-Specific Guidance About Portable Gauge Licenses

2 Program-Specific Guidance About Industrial Radiography Licenses

3 Applications for Sealed Source and Device Evaluation and Registration

4 Program-Specific Guidance About Fixed Gauge Licenses

5 Program-Specific Guidance About Self-Shielded Irradiator Licenses

6 Program-Specific Guidance About 10 CFR Part 36 Irradiator Licenses 

7 Program-Specific Guidance About Academic, Research and Development, and 

Other Licenses of Limited Scope Including Electron Capture Devices and X-Ray 

Fluorescence Analyzers

8 Program-Specific Guidance About Exempt Distribution Licenses

9 Program-Specific Guidance About Medical Use Licenses

10 Program-Specific Guidance About Master Materials Licenses

11 Program-Specific Guidance About Licenses of Broad Scope

12 Program-Specific Guidance About Possession Licenses for Manufacturing 

and Distribution

13 Program-Specific Guidance About Commercial Radiopharmacy Licenses

14 Program-Specific Guidance About Well Logging, Tracer, and Field Flood 

Study Licenses

15 Guidance About Changes of Control and About Bankruptcy Involving 

Byproduct, Source, or Special Nuclear Materials Licenses

16 Program-Specific Guidance About Licenses Authorizing Distribution to 

General Licensees

17 Program-Specific Guidance About Special Nuclear Material of Less Than 

Critical Mass Licenses

18 Program-Specific Guidance About Service Provider Licenses

19 Guidance for Agreement State Licensees About NRC Form 241 “Report of 

Proposed Activities in Non-Agreement States, Areas of Exclusive Federal 

Jurisdiction, or Offshore Waters” and Guidance for NRC Licensees Proposing to 

Work in Agreement State Jurisdiction (Reciprocity)

20 Guidance About Administrative Licensing Procedures

21 Program-Specific Guidance About Possession Licenses for Production of 

Radioactive Material Using an Accelerator

The current document, NUREG–1556, Volume 1, Revision 2, “Consolidated Guidance About 

Materials Licenses: Program-Specific Guidance About Portable Gauge Licenses,” is intended 

for use by applicants, licensees, and NRC staff. This revision provides a general update to the 

previous information contained in NUREG–1556, Volume 1, Revision 1, issued November 2001, 

to incorporate certain security requirements and other regulatory and policy changes that have 

been implemented since the last revision was published.
vi

This report takes a risk-informed, performance-based approach to licensing portable gauges. A 

team composed of staff from NRC Headquarters, NRC regional offices, and Agreement States 

prepared this document, drawing on their collective experience in radiation safety in general and 

as specifically applied to portable gauges. 

NUREG–1556, Volume 1, Revision 2, is not a substitute for NRC or Agreement State 

regulations. The approaches and methods described in this report are provided for information 

only. Methods and solutions different from those described in this report may be acceptable if 

they include a basis for the staff to make the determinations needed to issue or renew a license.

The comments received during the public comment period for NUREG–1556, Volume 1, 

Revision 2, were summarized and addressed in a document that can be located on the NRC’s 

Agencywide Documents and Management System (ADAMS) under ML15069A043. Access to 

ADAMS is available on the public Web site at: http://www.nrc.gov/reading-rm/adams.html. The 

comments received by NRC included general corrections, comments on training, and comments 

on safety culture.

________________________________________

Daniel S. Collins, Director

Division of Material Safety, State, Tribal, and Rulemaking Programs

Office of Nuclear Material Safety and Safeguards
vii

TABLE OF CONTENTS

ABSTRACT...............................................................................................................................iii

FOREWORD ..............................................................................................................................v

FIGURES...................................................................................................................................ix

TABLES ....................................................................................................................................ix

ACKNOWLEDGMENTS............................................................................................................xi

ABBREVIATIONS ...................................................................................................................xiii

1 PURPOSE OF REPORT ..............................................................................................1-1

2 AGREEMENT STATES ...............................................................................................2-1

2.1 Jurisdiction Determination.....................................................................2-1

2.2 Reciprocal Recognition of Specific Licenses.............................................2-3

3 MANAGEMENT RESPONSIBILITY.............................................................................3-1

3.1 Commitments and Responsibilities ...................................................................3-1

3.2 Safety Culture...................................................................................................3-2

4 APPLICABLE REGULATIONS....................................................................................4-1

5 HOW TO FILE..............................................................................................................5-1

5.1 Application Preparation.....................................................................................5-1

5.2 Where to File ....................................................................................................5-1

5.3 Paper Applications............................................................................................5-2

5.4 Electronic Applications......................................................................................5-2

6 IDENTIFYING AND PROTECTING SENSITIVE INFORMATION.................................6-1

7 APPLICATION AND LICENSE FEES..........................................................................7-1

8 CONTENTS OF AN APPLICATION.............................................................................8-1

8.1 Item 1: License Action Type.............................................................................8-1

8.2 Item 2: Name and Mailing Address of Applicant...............................................8-2

8.2.1 Notification of Bankruptcy Proceedings .................................................8-2

8.3 Item 3: Address(es) Where Licensed Material Will Be Used 

or Possessed....................................................................................................8-3

8.4 Item 4: Person To Be Contacted About This Application..................................8-4

8.5 Item 5: Radioactive Material.............................................................................8-4

8.5.1 Sealed Sources and Devices.................................................................8-4

8.5.2 Financial Assurance and Recordkeeping for Decommissioning.............8-6

8.6 Item 6: Purpose(s) for Which Licensed Material Will Be Used..........................8-7

8.7 Item 7: Individual(s) Responsible for Radiation Safety Program and 

Their Training and Experience ..........................................................................8-7

8.7.1 Radiation Safety Officer.........................................................................8-7

8.8 Item 8: Training for Individuals Working In or Frequenting 

Restricted Areas ...............................................................................................8-9

8.8.1 Authorized Users...................................................................................8-9

8.9 Item 9: Facilities and Equipment ....................................................................8-10

8.10 Item 10: Radiation Safety Program ................................................................8-10

8.10.1 Audit Program .....................................................................................8-10
viii

8.10.2 Radiation Monitoring Instruments ........................................................8-11

8.10.3 Material Receipt and Accountability.....................................................8-12

8.10.4 Occupational Dose ..............................................................................8-13

8.10.5 Public Dose .........................................................................................8-16

8.10.6 Operating, Emergency, and Security Procedures................................8-17

8.10.7 Leak Tests...........................................................................................8-20

8.10.8 Maintenance........................................................................................8-21

8.10.9 Transportation .....................................................................................8-23

8.11 Item 11: Waste Management—Gauge Disposal and Transfer........................8-24

8.12 Item 12: License Fees....................................................................................8-24

8.13 Item 13: Certification......................................................................................8-24

9 LICENSE AMENDMENTS AND RENEWALS..............................................................9-1

9.1 Timely Notification of Transfer of Control ..........................................................9-1

10 APPLICATIONS FOR EXEMPTIONS ........................................................................10-1

11 TERMINATION OF ACTIVITIES ................................................................................11-1

APPENDICES

APPENDIX A U.S. NUCLEAR REGULATORY COMMISSION FORM 313........................ A–1

APPENDIX B SUGGESTED FORMAT FOR PROVIDING INFORMATION 

REQUESTED IN ITEMS 5 THROUGH 11 OF U.S. NUCLEAR 

REGULATORY COMMISSION FORM 313................................................... B–1

APPENDIX C CRITERIA FOR ACCEPTABLE TRAINING COURSES FOR 

PORTABLE GAUGE USERS ....................................................................... C–1

APPENDIX D TYPICAL DUTIES AND RESPONSIBILITIES OF THE

RADIATION SAFETY OFFICER................................................................... D–1

APPENDIX E PORTABLE GAUGE AUDIT CHECKLIST.................................................... E–1

APPENDIX F INFORMATION NEEDED TO SUPPORT APPLICANT’S REQUEST

TO PERFORM NONROUTINE MAINTENANCE............................................F–1

APPENDIX G OPERATING, EMERGENCY, AND SECURITY PROCEDURES..................G–1

APPENDIX H DOSIMETRY-RELATED GUIDANCE ........................................................... H–1

APPENDIX I MODEL LEAK TEST PROGRAM ...................................................................I–1

APPENDIX J U.S. DEPARTMENT OF TRANSPORTATION REGULATIONS ....................J–1

APPENDIX K SAFETY CULTURE POLICY STATEMENT.................................................. K–1

APPENDIX L CHECKLIST FOR REQUESTS TO WITHHOLD PROPRIETARY

INFORMATION FROM PUBLIC DISCLOSURE (UNDER 10 CFR 2.390)...... L-1
ix

FIGURES

Figure Page

2-1 U.S. Map: Locations of NRC Offices and Agreement States........................................2-1

8-1 Location of Use or Possession .....................................................................................8-3

8-2 Typical Duties and Responsibilities of RSOs ................................................................8-8

8-3 Annual Dose Limits for Adult Radiation Workers ........................................................8-14

8-4 Storing Gauges ..........................................................................................................8-16

8-5 Proper Handling of Incidents ......................................................................................8-18

8-6 Maintenance...............................................................................................................8-22

G–1 10 CFR 30.34(i) Example 1 ........................................................................................G–8

G–2 10 CFR 30.34(i) Example 2 ........................................................................................G–8

H–1 Diagram of Office and Gauge Storage Area in Examples 1 and 2 .............................. H–5

TABLES

Table Page

2-1 Who Regulates the Activity?.........................................................................................2-2

3-1 Traits of a Positive Safety Culture.................................................................................3-3

8-1 Record Maintenance ..................................................................................................8-13

G–1 Typical NRC Notification and Reporting Requirements for Incidents ..........................G–4

H–1 Dosimetry Evaluation..................................................................................................H–3

H–2 Information Known About Each Gauge....................................................................... H–5

H–3 Calculational Method, Part 1—Hourly and Annual Dose Received From Gauge 1 ..... H–6

H–4 Calculational Method, Part 1—Hourly and Annual Dose Received From Gauge 2 ..... H–6

H–5 Calculational Method, Part 1—Hourly and Annual Dose Received From Gauge 3 ..... H–7

H–6 Calculational Method, Part 1—Total Hourly and Annual Dose Received From

Gauges 1, 2, and 3.....................................................................................................H–7

H–7 Calculational Method, Part 2—Annual Dose Received From Gauges 1, 2, and 3 ....... H–8

H–8 Calculational Method, Part 3—Summary of Information ............................................. H–8

H–9 Calculational Method, Part 3—Annual Dose Received From Gauges 1, 2, and 3 ....... H–9

H–10 Combination Measurement—Calculational Method .................................................. H–11

xi

ACKNOWLEDGMENTS

The working group thanks the individuals listed here for assisting in the review and update of 

the report. All participants provided valuable insights, observations, and recommendations.

The working group would like to thank the staff in the regional offices of the U.S. Nuclear 

Regulatory Commission and all of the States who provided comments and technical information 

that assisted in the development of this report.

The working group also thanks Tomas Herrera for the pivotal role that he played in the 

development of this report.

The Participants for this Revision

Cook, Jackie

Juran, Brandon

Lodhi, Sattar

McDaniel, Keith

Mullauer, James R.

Reichard, Michael

xiii

ABBREVIATIONS

ADAMS Agencywide Documents and Management System

AEA Atomic Energy Act

ALARA as low as is reasonably achievable

bkg background

Bq becquerel

CFR Code of Federal Regulations

cpm counts per minute

DOT U.S. Department of Transportation

dpm disintegrations per minute

Gy Gray

HAZMAT hazardous material

IN Information Notice

L/C License Condition

MDA minimum detectable activity

mrem millirem

mSv millisievert

mSv/h millisievert/hour

NMSS Office of Nuclear Material Safety and Safeguards

NRC U.S. Nuclear Regulatory Commission

NVLAP National Voluntary Laboratory Accreditation Program

OMB Office of Management and Budget

PII personally identifiable information

Q quality factor

Rev. revision

RIS Regulatory Issue Summary

RQ reportable quantity

RSO radiation safety officer

SSD Sealed Source and Device [registration certificate]

std standard

Sv sievert

TEDE total effective dose equivalent

TI Transportation Index

TLD thermoluminescent dosimeters

U.S.C. United States Code

1-1

1 PURPOSE OF REPORT

This report provides guidance to an applicant applying for a portable gauge license and also 

provides the U.S. Nuclear Regulatory Commission (NRC) staff with the criteria for evaluating

such applications. It is not intended to address the research and development of portable

gauges or the commercial aspects of manufacturing, distributing, and nonroutine servicing of 

such devices. This document uses the terms “byproduct material,” “licensed material,” and 

“radioactive material” interchangeably. Within this document, the phrases “portable gauge” and

“gauge” are used interchangeably.

This report addresses a variety of radiation safety issues associated with portable gauges of 

different types. Portable gauges are of many different designs and may contain different sealed 

sources based, in part, on their intended use (e.g., to measure moisture content, density, 

thickness of asphalt, and to analyze paint). Because of differences in design, manufacturers

provide appropriate instructions and recommendations for proper operation and maintenance. 

In addition, with gauges of varying designs, the sealed sources may be oriented in different 

locations within the devices, resulting in different radiation safety considerations. Applicants 

should obtain this information from the manufacturers or suppliers if such information is not 

provided with the portable gauge.

Chapter 8, “Contents of an Application,” of this report identifies the information needed to 

complete NRC Form 313, “Application for Materials License” (see Appendix A of this NUREG),

for the use of sealed sources containing byproduct material in portable gauges. The Office of 

Management and Budget (OMB) has approved the information collection requirements in 

Title 10 of the Code of Federal Regulations (10 CFR) Part 30, “Rules of General Applicability 

to Domestic Licensing of Byproduct Material,” and NRC Form 313 under OMB Clearance 

Nos. 3150-0017 and 3150-0120, respectively.

The format within this document for each item of technical information is as follows:

• Regulations—references the regulations applicable to the item

• Criteria—outlines the criteria used to evaluate the applicant’s response

• Discussion—provides additional information about the topic

• Response from Applicant—provides suggested response or responses, offers the option 

of an alternative reply, or indicates that no response is needed on that topic during the 

licensing process

Notes and references are self-explanatory and may not be found for each item on

NRC Form 313.

NRC Form 313 does not have sufficient space for applicants to provide full responses to 

Items 5 through 11, as indicated on the form. Applicants should address those items on 

separate sheets of paper and submit them along with the completed NRC Form 313. For 

the convenience and streamlined handling of portable gauge applications, Appendix B of 

this NUREG, “Suggested Format for Providing Information Requested in Items 5 

through 11 of NRC Form 313,” may be used to provide supporting information.
1-2

In this document, dose or radiation dose 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 Part 20. To describe units of radiation exposure or dose, 

rem and its International System of Units equivalent, sievert (Sv) (1 rem = 0.01 Sv), are used. 

This is done because 10 CFR Part 20 sets dose limits in terms of rem (Sv), rather than rad or 

roentgen. When the radioactive material emits beta and gamma rays, 1 roentgen is assumed to 

equal 1 rad, which is assumed to equal 1 rem. For alpha and neutron-emitting radioactive 

material, 1 rad is not equal to 1 rem. Determination of dose equivalent (rem) from absorbed 

dose (rad) from alpha particles and neutrons requires the use of an appropriate quality factor 

(Q) value. These Q values are used to convert absorbed dose (rad) to dose equivalent (rem).

Tables 1004(b).1 and 2 in 10 CFR 20.1004, “Units of radiation dose,” address the Q values for 

alpha particles and neutrons.
2-1

2 AGREEMENT STATES

2.1 Jurisdiction Determination

Certain States, called Agreement States (see Figure 2-1), have entered into agreements with 

the U.S. Nuclear Regulatory Commission (NRC) that give them the authority to license and 

inspect byproduct, source, and special nuclear materials in quantities not sufficient to form a 

critical mass, which are used or possessed within their borders. Any applicant, other than a 

Federal entity, who wishes to possess or use licensed material in one of these Agreement 

States should contact the responsible officials in that State for guidance on preparing an 

application. These applications should be filed with State officials, not with the NRC. In areas 

under exclusive Federal jurisdiction within an Agreement State, NRC continues to be the 

regulatory authority.

Figure 2-1. U.S. Map: Locations of NRC Offices and Agreement States

In the special situation of work at federally controlled sites in Agreement States, it is necessary 

to ascertain the jurisdictional status of the area to determine whether the NRC or the Agreement 
2-2

State has regulatory authority. These areas can also include tribal lands of federally recognized 

Indian Tribes.

2

 

The NRC has regulatory authority over land determined to be “exclusive Federal jurisdiction,” 

while the Agreement State may have jurisdiction over nonexclusive Federal jurisdiction land. 

Applicants are responsible for determining, in advance, the jurisdictional status of the specific 

areas where they plan to conduct licensed operations. Additional guidance on determining 

jurisdictional status is found in the Office of Nuclear Material Safety and Safeguards (NMSS) 

procedures in the State Agreement series, SA-500, “Jurisdiction Determination,” which is 

available at https://scp.nrc.gov. Once on the Web site, use the link for “NMSS Procedures” in 

the left-hand column under “Resources & Tools.” 

Table 2-1 provides a quick way to evaluate whether the NRC or an Agreement State has 

regulatory authority.

Table 2-1. Who Regulates the Activity?

Applicant and Proposed Location of Work

Regulatory 

Agency

Federal agency regardless of location (except that the U.S. Department of 

Energy and, under most circumstances, its prime contractors are exempt 

from licensing, in accordance with 10 CFR 30.12, “Persons using 

byproduct material under certain U.S. Department of Energy and U.S. 

Nuclear Regulatory Commission contracts”)

NRC

Non-Federal entity in non-Agreement State, District of Columbia, 

U.S. territory or possession, or in offshore Federal waters NRC

Federally recognized Indian Tribe or tribal member on Indian Tribal land NRC

Non-Federal entity on federally recognized Indian Tribal land NRC3

Federally recognized Indian Tribe or tribal member outside of Indian Tribal 

land in Agreement State. Agreement State

Non-Federal entity in Agreement State Agreement State4

Non-Federal entity in Agreement State at federally controlled site not

subject to exclusive Federal jurisdiction Agreement State4

 2

For the purposes of this guidance, an “Indian Tribe” is defined as an Indian or Alaska Native tribe, band, nation,

pueblo, village, or community that the Secretary of the Interior acknowledges to exist as an Indian tribe pursuant to 

the Federally Recognized Indian Tribe List Act of 1994. A list of federally recognized tribes is available at 

www.bia.gov. 3The NRC can exercise jurisdiction as the regulatory authority on tribal land of a federally recognized Indian Tribe. 

Section 274b. agreements do not give States the authority to regulate nuclear material in these areas. However,

there may be States that exercise regulatory authority over these areas based on treaties or agreements with specific 

tribes. Companies owned or operated by federally recognized Indian Tribe members or non-Indians that wish to 

possess or use licensed material on tribal lands should contact the appropriate NRC regional office to determine the 

jurisdictional status of the tribal lands and identify the appropriate regulatory agency for licensing and reciprocity. 4

Section 274m. of the Atomic Energy Act (AEA) withholds to the NRC regulatory authority over radioactive materials 

covered under the Section 274b. agreements when the activity can affect the Commission’s authority to protect the 

common defense and security, to protect restricted data, or guard against the loss or diversion of special nuclear 

material. (This is an uncommon situation that NRC usually evaluates on a case-by-case basis.) Individuals or 

companies wishing to possess or use licensed material should contact the licensee to determine the jurisdictional 

status for specific AEA radioactive materials they intend to possess or use.
2-3

Table 2-1. Who Regulates the Activity?

Applicant and Proposed Location of Work

Regulatory 

Agency

Non-Federal entity in Agreement State at federally controlled site subject 

to exclusive Federal jurisdiction NRC

Non-Federal entity in Agreement State using radioactive materials (except 

industrial radiography) directly connected with 10 CFR Part 50 or 52 

reactor operations or needed during the construction and preoperational 

phases of a reactor. 

NRC

Non-Federal entity in Agreement State using radioactive materials not

directly connected with 10 CFR Part 50 or 52 reactor operations or needed 

during the construction and preoperational phases of a reactor.

Agreement State4

Reference: A current list of Agreement States (including names, addresses, and telephone 

numbers of responsible officials) is available at the NMSS public Web site, https://scp.nrc.gov. 

A request for the list can also be made to an NRC regional office.

2.2 Reciprocal Recognition of Specific Licenses

Performing licensed activities in other jurisdictions is possible through reciprocal recognition of 

specific licenses (i.e., reciprocity). Agreement States have reciprocity provisions that permit 

NRC licensees to perform licensed activities under circumstances when an Agreement State is 

the regulatory authority (See Section 2.1). NRC licensees and Agreement State licensees are 

subject to the regulations of the regulatory authority as indicated in Section 2.1. To ensure 

compliance with an Agreement State’s reciprocity requirements, licensees are advised to 

request authorization from the appropriate Agreement State radiation control program office well 

in advance of the scheduled use of licensed material. 

Agreement State licensees that wish to conduct licensed activities in areas under NRC 

jurisdiction must either obtain a specific NRC license or file for reciprocity with the appropriate 

NRC regional office for the Agreement State that issued their license. Failure to file for 

reciprocity or obtain a specific NRC license before working in areas under NRC jurisdiction can 

result in NRC enforcement action, which may include civil penalties. The reciprocity filing must 

be renewed annually.

Specific guidance regarding NRC licensees filing for reciprocity in Agreements States and 

Agreement State licensees filing for reciprocity with the NRC or another Agreement State are 

provided in NUREG–1556, Volume 19, “Consolidated Guidance About Materials 

Licenses: Guidance for Agreement State Licensees About NRC Form 241 “Report of Proposed 

Activities in Non-Agreement States, Areas of Exclusive Federal Jurisdiction, or Offshore Waters” 

and Guidance for NRC Licensees Proposing to Work in Agreement State Jurisdiction 

(Reciprocity).”

3-1

3 MANAGEMENT RESPONSIBILITY

The U.S. Nuclear Regulatory Commission (NRC) recognizes that effective management of 

radiation safety programs is vital to achieving safe, secure, and compliant operations. 

Consistent compliance with NRC regulations provides reasonable assurance that licensed 

activities will be conducted safely and that effective management will result in increased safety, 

security, and compliance.

“Management,” as used in this volume, refers to the processes for conduct and control of a 

radiation safety program and to the individuals who are responsible for those processes and 

who have authority to provide necessary resources to achieve regulatory compliance.

3.1 Commitments and Responsibilities

Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 30.32(c), each application 

must be signed by the applicant or licensee or a person duly authorized to act for and on behalf 

of the applicant or licensee. If it is not clear whether the application was signed by someone 

duly authorized to act for and on behalf of the applicant or licensee, NRC license reviewers may 

ask for additional assurances that the individual who signed the application is duly authorized to 

act for and on behalf of the applicant or licensee. The signature on an application 

acknowledges the licensee’s commitments and responsibilities for the following:

• radiation safety, security, and control of radioactive materials and compliance 

with regulations

• completeness and accuracy of the radiation safety records and all information provided 

to the NRC (10 CFR 30.9, “Completeness and accuracy of information”)

• knowledge about the contents of the license and application

• compliance with current NRC and U.S. Department of Transportation (DOT) regulations,

the licensee’s operating, emergency, and security procedures, and NRC license 

commitments

• commitment to provide adequate resources (including space, equipment, personnel, 

time, and, if needed, contractors) to the radiation protection program to ensure that the 

public and workers are protected from radiation hazards and compliance with regulations 

is maintained

• commitment to report defects, noncompliances, or reportable events in accordance 

with regulations

• selection and assignment of a qualified individual to serve as the radiation safety officer 

(RSO) for licensed activities and confirmation that the RSO has independent authority to 

stop unsafe operations and will be given sufficient time to fulfill radiation safety duties 

and responsibilities

• commitment to ensure that radiation workers have adequate training
3-2

• prevention of discrimination of employees engaged in protected activities 

(10 CFR 30.7, “Employee protection”)

• commitment to provide information to employees about the employee protection 

and deliberate misconduct provisions in 10 CFR 30.7, “Employee protection,” and 

10 CFR 30.10, “Deliberate misconduct”

• commitment to obtain the NRC’s prior written consent before transferring control of the 

license (see Section 9.1, “Timely Notification of Transfer of Control,” of this report)

• notification of the appropriate NRC regional administrator, in writing, immediately 

following the filing of a petition for voluntary or involuntary bankruptcy [10 CFR 30.34(h)], 

as discussed further in Section 8.2.1, “Notification of Bankruptcy Proceedings,” of 

this report

For information on NRC inspection, investigation, enforcement, and other compliance programs, 

see the current version of the NRC’s Enforcement Policy and Inspection Procedures available in 

the NRC’s online library under “Document Collections” at http://www.nrc.gov/reading-rm.html.

3.2 Safety Culture

Individuals and organizations performing regulated activities are expected to establish and 

maintain a positive safety culture commensurate with the safety and security significance of 

their activities and the nature and complexity of their organizations and functions. This applies 

to all licensees; certificate holders; permit holders; authorization holders; holders of quality 

assurance program approvals; vendors and suppliers of safety-related components; and 

applicants for a license, certificate, permit, authorization, or quality assurance program approval, 

subject to NRC authority.

“Nuclear safety culture” is defined in the NRC’s safety culture policy statement (76 FR 34773; 

June 14, 2011) as “the core values and behaviors resulting from a collective commitment by 

leaders and individuals to emphasize safety over competing goals to ensure protection of 

people and the environment.” Individuals and organizations performing regulated activities bear 

the primary responsibility for safely handling and securing these materials. Experience has 

shown that certain personal and organizational traits are present in a positive safety culture. 

A trait, in this case, is a pattern of thinking, feeling, and behaving that emphasizes safety, 

particularly in goal-conflict situations (e.g., production versus safety, schedule versus safety, 

and cost of the effort versus safety). Refer to Table 3-1 for the traits of a positive safety culture

from NRC’s safety culture policy statement.

Organizations should ensure that personnel in the safety and security sectors have an 

appreciation for the importance of each, emphasizing the need for integration and balance to 

achieve both safety and security in their activities. Safety and security activities are closely 

intertwined. While many safety and security activities complement each other, there may be 

instances in which safety and security interests create competing goals. It is important that 

consideration of these activities be integrated so as not to diminish or adversely affect either; 

thus, mechanisms should be established to identify and resolve these differences. A safety 

culture that accomplishes this would include all nuclear safety and security issues associated 

with NRC-regulated activities.
3-3

The NRC, as the regulatory agency with an independent oversight role, reviews the 

performance of individuals and organizations to determine compliance with requirements and 

commitments through its existing inspection and assessment processes. However, NRC’s 

safety culture policy statement and traits are not incorporated into the regulations. Safety 

culture traits may be inherent to an organization’s existing radiation safety practices and 

programs. For instance, the security requirement for portable gauge licensees to use physical 

controls to secure portable gauges from unauthorized removal may correspond with the safety 

culture trait specified in Table 3-1 as “Work Processes” (the process of planning and controlling 

work activities to ensure that safety is maintained). However, licensees should be aware that 

this is just an example and should still consider reviewing their radiation safety programs in 

order to develop and implement a safety culture commensurate with the nature and complexity 

of their organizations and functions.

Refer to Appendix K of this NUREG for the NRC’s safety culture policy statement. More 

information on NRC activities relating to safety culture can be found at: 

http://www.nrc.gov/about-nrc/safety-culture.html.

Table 3-1. Traits of a Positive Safety Culture

Leadership Safety Values 

and Actions

Problem Identification and 

Resolution Personal Accountability

Leaders demonstrate a 

commitment to safety in their 

decisions and behaviors.

Issues potentially impacting 

safety are promptly 

identified, fully evaluated, 

and promptly addressed and 

corrected commensurate 

with their significance.

All individuals take personal 

responsibility for safety.

Work Processes Continuous Learning 

Environment for Raising 

Concerns 

The process of planning and 

controlling work activities is 

implemented so that safety 

is maintained.

Opportunities to learn about 

ways to ensure safety are 

sought out and 

implemented.

A safety conscious work 

environment is maintained 

where personnel feel free to 

raise safety concerns 

without fear of retaliation, 

intimidation, harassment, or 

discrimination.

Effective Safety 

Communications

Respectful Work 

Environment Questioning Attitude

Communications maintain a 

focus on safety.

Trust and respect permeate 

the organization.

Individuals avoid 

complacency and 

continuously challenge 

existing conditions and 

activities in order to identify 

discrepancies that might 

result in error or 

inappropriate action.

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4 APPLICABLE REGULATIONS

It is the applicant’s or licensee’s responsibility to obtain and have available up-to-date copies of 

applicable regulations, to read and understand the requirements of each of these regulations, 

and to comply with each applicable regulation. The following parts of Title 10 of the Code of 

Federal Regulations (10 CFR) contain regulations applicable to portable gauges. Some of 

these parts are specific to one type of license, while others are general and will apply to many, if 

not all, licensees.

The current versions of these parts can be found under the “Basic References” link at the 

U.S. Nuclear Regulatory Commission’s (NRC’s) online library at http://www.nrc.gov/readingrm.html. If viewing in a browser, the following list includes direct links to the rules:

• 10 CFR Part 2, “Agency Rules of Practice and Procedure”

• 10 CFR Part 19, “Notices, Instructions and Reports to Workers: Inspection 

and Investigations”

• 10 CFR Part 20, “Standards for Protection Against Radiation”

• 10 CFR Part 21, “Reporting of Defects and Noncompliance”

• 10 CFR Part 30, “Rules of General Applicability to Domestic Licensing of 

Byproduct Material”

• 10 CFR Part 71, “Packaging and Transportation of Radioactive Material”

• 10 CFR Part 150, “Exemptions and Continued Regulatory Authority in Agreement States 

and in Offshore Waters under Section 274”

• 10 CFR Part 170, “Fees for Facilities, Materials, Import and Export Licenses, and Other 

Regulatory Services Under the Atomic Energy Act of 1954, as Amended”

• 10 CFR Part 171, “Annual Fees for Reactor Licenses and Fuel Cycle Licenses and 

Materials Licenses, Including Holders of Certificates of Compliance, Registrations, and 

Quality Assurance Program Approvals and Government Agencies Licensed by the NRC”

Copies of these documents may be obtained by calling the Government Publishing Office

Customer Contact Center toll-free at 866-512-1800, in Washington, DC; calling 202-512-1800;

or ordering online at http://bookstore.gpo.gov. 

In addition, 10 CFR Parts 1 through 199 can be found on the NRC’s Web site at

http://www.nrc.gov/reading-rm/doc-collections/ under “Regulations (10 CFR).” 

NRC regulations can also be accessed from the “NRC Library” link on the NRC’s public 

Web site at http://www.nrc.gov. Regulations are periodically amended, and the NRC (as well 

as all other Federal agencies) is required to publish notice of such amendments in the 

Federal Register.

5-1

5 HOW TO FILE

5.1 Application Preparation

Applicants for a materials license should do the following:

• Use the most recent guidance in preparing an application.

• Complete U.S. Nuclear Regulatory Commission (NRC) Form 313 (Appendix B of this 

NUREG), Items 1 through 4, 12, and 13, on the form itself. A link to the form is available 

at http://www.nrc.gov/reading-rm/doc-collections/forms/.

• Complete NRC Form 313, Items 5 through 11, on supplementary pages or use 

Appendix C of this NUREG.

• Provide sufficient detail for the NRC to determine that the equipment, facilities, training, 

experience, and the radiation safety program are adequate to protect health and safety 

and minimize danger to life and property.

• For each separate sheet other than NRC Form 313 and Appendix C pages, as 

applicable, identify and cross-reference submitted information to the item number on the 

application or the topic to which it refers.

• Avoid submitting proprietary information and personally identifiable information. If 

submitted, proprietary, personal privacy, security-related, and other sensitive information 

should be clearly identified according to Title 10 of the Code of Federal Regulations

(10 CFR) Part 2.390, “Public inspections, exemptions, requests for withholding” 

(see Chapter 6, “Identifying and Protecting Sensitive Information”). 

5.2 Where to File

Applicants wishing to possess or use licensed material in any State, U.S. territory, or

U.S. possession subject to NRC jurisdiction must file an application with the NRC regional office

for the locale in which the material will be possessed or used. Figure 2-1 identifies the NRC’s 

four regional offices and their respective areas for licensing purposes and the Agreement 

States. Note that all materials applications are submitted to Regions I, III, or IV. All applicants 

for materials licenses located in the Region II geographical area should send their applications 

to Region I.

In general, applicants wishing to possess or use licensed material in Agreement States must file 

an application with the Agreement State and not with the NRC. However, if work will be 

conducted at federally controlled sites or federally recognized Indian Tribal lands in Agreement 

States, applicants must first determine the jurisdictional status of the land in order to determine 

whether the NRC or the Agreement State has regulatory authority. See Chapter 2, “Agreement 

States,” for additional information.
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5.3 Paper Applications

Paper applications received by the NRC are scanned through an optical character reader and 

converted to an electronic format. To ensure a smooth transfer to an electronic format, 

applicants should do the following:

• Submit all documents, typed, on 81⁄2 × 11-inch or legal-sized paper that will feed easily 

into a document scanner.

• Choose typeface designs that are sans serif, such as Arial, Helvetica, or Futura 

(the text of this document is in the Arial font).

• Use 11-point or larger font.

• Avoid stylized characters, such as script or italics.

• Ensure that the print is clear and sharp.

• Ensure that there is high contrast between the ink and paper (black ink on white paper 

is best).

Applications must be signed by the applicant, licensee, or a person duly authorized as 

required by 10 CFR 30.32(c) (see Section 8.13, “Certification”).

5.4 Electronic Applications

Applications may be submitted in electronic form via the NRC’s Electronic Information Exchange 

or CD-ROM. Detailed guidance on making electronic submissions can be obtained by visiting 

the NRC’s Web site at http://www.nrc.gov/site-help/e-submittals.html. The guidance discusses,

among other topics, the formats the NRC can accept, the use of electronic signatures, and the 

treatment of nonpublic information.
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6 IDENTIFYING AND PROTECTING SENSITIVE INFORMATION

All licensing applications, except for portions containing sensitive information, will be made 

available for review in the U.S. Nuclear Regulatory Commission (NRC) Public Document Room 

and electronically at the NRC Library. For more information on the NRC Library, visit 

www.nrc.gov.

The applicant or licensee should identify, mark, and protect sensitive information against 

unauthorized disclosure to the public. License applications that contain sensitive information 

should be marked, as indicated in the list that follows, in accordance with Title 10 of the Code of 

Federal Regulations (10 CFR) Part 2.390 before the information is submitted to the NRC. Key 

examples are as follows:

• Proprietary Information and Trade Secrets: If it is necessary to submit proprietary 

information or trade secrets, follow the procedure in 10 CFR 2.390(b). Failure to follow 

this procedure could result in disclosure of the proprietary information to the public or 

substantial delays in processing the application. Appendix L of this NUREG provides a 

checklist for requests for withholding proprietary information from public disclosure.

• Personally Identifiable Information: Personally identifiable information (PII) about 

employees or other individuals should not be submitted unless specifically requested by 

the NRC. Examples of PII are social security number, home address, home telephone 

number, date of birth, and radiation dose information. If PII is submitted, a cover letter 

should clearly state that the attached documents contain PII and the top of every page of 

a document that contains PII should be clearly marked as follows: “Privacy Act 

Information—Withhold Under 10 CFR 2.390.” For further information, see Regulatory 

Issue Summary (RIS) 2007-04, “Personally Identifiable Information Submitted to the 

U.S. Nuclear Regulatory Commission,” dated March 9, 2007, and Information Notice (IN) 

2013-22, “Recent Licensing Submittals Containing Personally Identifiable Information,” 

dated November 15, 2013, which can be found on the NRC’s Generic Communications 

Web page: http://www.nrc.gov/reading-rm/doc-collections/gen-comm/.

• Security-Related Information: Following the events of September 11, 2001, the NRC 

changed its procedures to avoid the release of information that terrorists could use to 

plan or execute an attack against facilities or citizens in the U.S. As a result, certain 

types of information are no longer routinely released and are treated as sensitive 

unclassified information. For example, certain information about the quantities and 

locations of radioactive material at licensed facilities, and associated security measures, 

are no longer released to the public. Therefore, a cover letter should clearly state that 

the attached documents contain sensitive security-related information and the top of 

every page of a document that contains such information should be clearly marked: 

“Security Related Information—Withhold under 10 CFR 2.390.” For the pages having 

security-related sensitive information, an additional marking should be included (e.g., an 

editorial note box) adjacent to that material. For further information, see RIS 2005-31, 

“Control of Security-Related Sensitive Unclassified Non-Safeguards Information Handled 

by Individuals, Firms, and Entities Subject to NRC Regulation of the Use of Source, 

Byproduct, and Special Nuclear Material,” dated December 22, 2005, which can be 

found on the NRC’s Generic Communications Web page under “Regulatory Issue 

Summaries”: http://www.nrc.gov/reading-rm/doc-collections/gen-comm/. Additional 
6-2

information on procedures and any updates is available at http://www.nrc.gov/readingrm/sensitive-info.html.

The regulations list various forms of information that can be protected from public disclosure. 

These include:

• trade secrets and commercial or financial information

• interagency or intra-agency memoranda or letters that would not be available by law to a 

party other than an agency in litigation with NRC

• certain records or information compiled for law enforcement purposes

• geological and geophysical information and data, including maps, or information 

concerning wells

• personnel, medical, and other information, the disclosure of which would constitute a 

clearly unwarranted invasion of personal privacy

In 10 CFR 2.390, NRC specifies the procedures and requirements for persons to submit 

sensitive information to NRC so that it may be properly protected from disclosure. This 

regulation is available electronically on the NRC Web site: http://www.nrc.gov/reading-rm/doccollections/cfr. 

Except for personal privacy information, which is not subject to the affidavit requirement, if NRC

determines that the application or affidavit is deficient (i.e., does not contain the required 

information as outlined in 10 CFR 2.390), the applicant will be notified that additional information 

is needed and that the review will continue when the required information is received.

If the request is denied, in whole or in part, NRC will give the applicant the option of withdrawing

the information or application, as permitted in 10 CFR 2.390. If the applicant decides not to 

withdraw the information or application, NRC will notify the applicant in writing that the request 

for withholding has been denied and that NRC will disregard any references concerning the 

proprietary status of the information.

Any part of a license application or information provided by a licensee or applicant that the NRC 

determines should be withheld from public disclosure will be handled in accordance with 

Management Directive 12.6, “NRC Sensitive Unclassified Information Security Program,” and 

the licensee or applicant will be notified in writing that NRC plans to honor the request. 

Management Directive 12.6 is available electronically on the NRC Web site: 

http://www.nrc.gov/reading-rm/doc-collections/management-directives/.
6-3

Anyone submitting a request to withhold information from public disclosure should thoroughly 

review 10 CFR 2.390 and be familiar with its requirements and limitations.

Withholding from public inspection shall not affect the right, if any, of persons properly and 

directly concerned to inspect the documents. If the need arises, NRC may send copies of this 

information to NRC consultants working in that area. NRC will ensure that the consultants 

have signed the appropriate agreements for handling proprietary information.

If the basis for withholding this information from public inspection should change in the future,

such that the information could then be made available for public inspection, the licensee or 

applicant should promptly notify the NRC. The licensee or applicant also should understand 

that NRC may have cause to review this determination in the future; for example, if the scope 

of a Freedom of Information Act request includes the information in question. In all review 

situations, if NRC makes a determination adverse to the above, the licensee or applicant will 

be notified in advance of any public disclosure. Anyone submitting commercial or financial 

information they believe to be privileged, confidential, or a trade secret must remember that 

the NRC’s policy is to achieve an effective balance between legitimate concerns for the 

protection of competitive positions and the right of the public to be fully apprised of the basis 

for, and the effects of, licensing or rulemaking actions. It is within NRC’s discretion to withhold 

such information from public disclosure.

7-1

7 APPLICATION AND LICENSE FEES

Each application for which a fee is specified must be accompanied by the appropriate fee. 

Refer to Title 10 of the Code of Federal Regulations (10 CFR) 170.31, “Schedule of fees for 

materials licenses and other regulatory services, including inspections, and import and export 

licenses,” to determine the amount of the fee. The U.S. Nuclear Regulatory Commission (NRC)

will not issue a license until the fee is received. Consult 10 CFR 170.11, “Exemptions,” for 

information on exemptions from these fees. Once the technical review of an application has 

begun, no fees will be refunded. Application fees will be charged regardless of the NRC’s 

disposition of an application or the withdrawal of an application.

Most NRC licensees are also subject to annual fees; refer to 10 CFR 171.16, “Annual fees: 

Materials licensees, holders of certificates of compliance, holders of sealed source and device 

registrations, holders of quality assurance program approvals, and government agencies 

licensed by the NRC.” Consult 10 CFR 171.11 for information on exemptions from annual fees 

and 10 CFR 171.16(c) on reduced annual fees for licensees that qualify as “small entities.” 

Note that in order to pay reduced fees, a licensee that qualifies as a “small entity” must provide 

proper certification of this status to the NRC each year, along with its annual fee payment.

Direct all questions about the NRC’s fees or completion of Item 12 of NRC Form 313 to the 

Office of the Chief Financial Officer at NRC Headquarters in Rockville, MD, 301-415-7554. 

Information about fees may also be obtained by calling NRC’s toll-free number, 800-368-5642, 

extension 415-7554. The e-mail address is Fees.Resource@nrc.gov.

8-1

8 CONTENTS OF AN APPLICATION

The following information applies to the indicated items on U.S. Nuclear Regulatory Commission 

(NRC) Form 313 (Appendix A of this NUREG).

All items in the application should be completed in enough detail for the NRC to determine 

whether the proposed equipment, facilities, training and experience, and radiation safety and 

security programs satisfy regulatory requirements and are adequate to protect public health and 

safety and minimize danger to life and property. Consideration should be given, when 

developing the application, to the concepts of keeping exposure as low as is reasonably 

achievable (ALARA), minimizing contamination, and maintaining control of radioactive materials.

Title 10 of the Code of Federal Regulations (10 CFR) 20.1101(b) states: “The licensee shall 

use, to the extent practical, procedures and engineering controls based upon sound radiation 

protection principles to achieve occupational doses and doses to members of the public that are 

as low as is reasonably achievable (ALARA).” Regulatory Guide 8.10, “Operating Philosophy 

for Maintaining Occupational Radiation Exposures as Low as Is Reasonably Achievable,” 

discusses the ALARA concepts and philosophy. The application should document ALARA 

considerations, including establishing administrative action levels and monitoring programs.

10 CFR 20.1406, “Minimization of contamination,” requires applicants for licenses to describe 

how facility design and procedures for operation will minimize, to the extent practicable, 

contamination of the facility and the environment; facilitate eventual decommissioning; and 

minimize, to the extent practicable, the generation of radioactive waste. As with ALARA

considerations, applicants should address concerns for all aspects of their programs.

The application should include information on how the licensee will implement the security 

requirements in 10 CFR 20.1801, “Security of stored material,” and 10 CFR 20.1802, “Control of 

material not in storage.”

All information submitted to the NRC during the licensing process may be incorporated as part 

of the license and will be subject to review during inspection.

8.1 Item 1: License Action Type

Item 1 of NRC Form 313 states the following:

This is an application for (check appropriate item):

Type of Action License No.

[ ] A. New License Not Applicable

[ ] B. Amendment XX-XXXXX-XX

[ ] C. Renewal XX-XXXXX-XX

Check box A for a new license request. Note that a prelicensing visit may be conducted prior to 

issuance of the license.

Check box B for an amendment to an existing license and provide the license number.
8-2

Check box C for a renewal of an existing license and provide the license number.

See “License Amendments and Renewals” in Chapter 9 of this report.

8.2 Item 2: Name and Mailing Address of Applicant

List the legal name of the applicant’s corporation or other legal entity with direct control over use 

of the radioactive material. A division or department within a legal entity may not be a licensee. 

An individual may be designated as the applicant only if the individual is acting in a private 

capacity and the use of the radioactive material is not connected with employment in a 

corporation or other legal entity. Provide the mailing address where correspondence should be 

sent. A post office box number is an acceptable mailing address.

Notify the NRC of changes in the mailing address. These changes do not require a fee.

 

Note: The NRC must be notified and the transfer approved before control of the license is 

transferred (see Section 9.1, “Timely Notification of Transfer of Control”). The NRC must also 

be notified when bankruptcy proceedings have been initiated (See Section 8.2.1, “Notification of 

Bankruptcy Proceedings”).

8.2.1 Notification of Bankruptcy Proceedings

Regulation: 10 CFR 30.34(h)

Criteria: Immediately following the filing of a voluntary or involuntary petition for bankruptcy for 

or against a licensee, the licensee must notify the appropriate NRC regional administrator, in 

writing, identifying the bankruptcy court in which the petition was filed and the date of filing.

Discussion: Even though a licensee may have filed for bankruptcy, the licensee remains 

subject to all applicable NRC regulatory requirements. The NRC must be notified when 

licensees are in bankruptcy proceedings in order to determine whether all licensed material is 

accounted for and adequately controlled and whether there are any public health and safety 

concerns (e.g., contaminated facility). The NRC shares the results of its determinations with 

other involved entities (e.g., trustee), so that health and safety issues can be resolved before 

bankruptcy actions are completed and may request that the U.S. Department of Justice

represent the NRC’s interests in the bankruptcy proceeding.

Response from Applicant: None is required at the time of application for a new license. 

Licensees must immediately notify the NRC in writing following the filing of a voluntary or 

involuntary petition for bankruptcy by or against the licensee.

Reference: See NUREG–1556, Volume 15, “Consolidated Guidance About Materials Licenses: 

Guidance About Changes of Control and About Bankruptcy Involving Byproduct, Source, or 

Special Nuclear Materials Licenses.” 
8-3

8.3 Item 3: Address(es) Where Licensed Material Will Be Used or Possessed

Most applicants need to provide two types of information in response to Item 3:

• the address(es) where the gauges will be stored when gauges are not in the field

• specification of whether they intend to use the portable gauge at temporary jobsites

Specify the street address, city, and State or other descriptive address (e.g., Highway 10, 

5 miles east of the intersection of Highway 10 and State Route 234, Anytown, State) for each 

facility. The descriptive address should be sufficient to allow an NRC inspector to find the 

facility location. A post office box address is not acceptable. In addition, applicants are 

encouraged to provide global positioning system coordinates, as appropriate, for each 

permanent storage or use facility and field station located in a remote area. A field station is a 

location in which licensed material may be stored or used and from which the applicant will 

dispatch equipment to jobsites. If devices will not be stored at a dispatch site or field station, 

indicate this. The applicant should also state whether a location will be used to perform portable

gauging operations or only for storage of portable gauges.

An acceptable location of use or possession specifies street address, city, State, 

and zip code and does not include a post office box number.

Figure 8-1. Location of Use or Possession

A license amendment is required before receiving, using, or storing licensed material at an 

address or location not already listed on the license. This applies whether the gauge is an 

additional device or a relocation of an existing device.

An NRC license does not relieve a licensee from complying with other applicable Federal, 

State, or local regulations (e.g., local zoning requirements).

To conduct operations at temporary jobsites (i.e., locations where work is conducted for 

limited periods of time), the address may be stated as “temporary jobsites anywhere in the U.S.

where the NRC maintains jurisdiction.”
8-4

If an applicant submits documents that give the exact location of use and storage for any 

amount of radioactive material, the applicant should mark these documents as “Security Related 

Information—Withhold under 10 CFR 2.390.” See Chapter 6, “Identifying and Protecting 

Sensitive Information,” for more details.

Note: As discussed in Section 8.5.2, “Financial Assurance and Recordkeeping for 

Decommissioning,” licensees must maintain permanent records describing where licensed 

material was used or stored while the license was in effect. This is important for making future 

determinations about the release of these locations for unrestricted use (e.g., before the license 

is terminated). For portable gauge licensees, acceptable records are leak test records, 

sketches, and written descriptions of specific locations or room numbers where each gauge was

used or stored, and any information relevant to damaged devices or leaking radioactive sources 

or other unusual occurrences involving the spread of contamination in or around the licensee’s 

facilities.

8.4 Item 4: Person To Be Contacted About This Application

Identify the individual who can answer questions about the application, and include a telephone 

number where the individual may be contacted as well as business cell phone numbers and email addresses. This individual, usually the radiation safety officer (RSO), will serve as the point 

of contact during the review of the application. If this individual is not a full-time employee of the 

licensed entity, his or her position and relationship to the licensee should be specified. The 

NRC should be notified if the person assigned to this function changes or if his or her telephone 

number, cell phone number, or e-mail address changes. Notification of a contact change is only 

provided for informational purposes and would not be considered an application for license 

amendment, unless the notification involves a change in the contact person who is also the 

RSO. 

As indicated on NRC Form 313 (see Appendix A of this NUREG), Items 5 through 11 should 

be submitted on separate sheets of paper. Applicants may use Appendix B of this NUREG for 

this purpose and should note that using the suggested wording of responses and committing 

to use the model procedures in this report will facilitate the NRC’s review.

8.5 Item 5: Radioactive Material 

8.5.1 Sealed Sources and Devices

Regulations: 10 CFR 30.32(g), 10 CFR 30.33(a)(2), 10 CFR 32.210

Criteria: Applicants must provide the radionuclide and nominal activity for each requested 

sealed source, the manufacturer’s or distributor’s name, and model number for each device, 

and the number of gauges for each model. Licensees will be authorized to possess and use 

only those sealed sources and devices specifically approved and registered by the NRC or an 

Agreement State. The applicant should also provide a description of the use of the gauges.

Discussion: The NRC or an Agreement State performs safety evaluations of portable gauges 

before distribution of the devices to specific licensees. The safety evaluation is documented in 

a Sealed Source and Device (SSD) registration certificate issued to the manufacturer. 
8-5

Licensees may not make any changes to the sealed source, device, or source/device 

combination that would alter the description or specifications from those indicated in the 

respective registration certificates without obtaining the NRC’s prior permission in a license 

amendment. Such changes may necessitate a custom registration review, increasing the time 

needed to process a licensing action.

SSD registration certificates contain sections on “Conditions of Normal Use” and “Limitation and 

Other Considerations of Use.” These sections may include limitations derived from, conditions 

imposed by the manufacturer or distributor, particular conditions of use that would reduce the 

radiation safety of the device, or circumstances unique to the sealed source and device. For 

example, the working life of the device or the appropriate temperature and other environmental 

conditions may be specified. Except as specifically approved by the NRC, licensees are 

required to use portable gauges according to their respective SSD registration certificates. 

Accordingly, applicants should obtain a copy of the certificate from the manufacturer or 

distributor. If the manufacturer and distributor are no longer in service, a copy of the SSD 

registration certificate may be requested from the NRC or the issuing Agreement State. The 

applicant should review the provisions of the SSD registration certificate with the manufacturer 

or distributor, the NRC, or the issuing Agreement State.

Generally, portable gauge licensees possess small quantities of radioactive material below the 

Category 2 quantities described in 10 CFR 37, “Physical Protection of Category 1 and Category 

2 Quantities of Radioactive Material.” Portable gauge licensees that possess an aggregated

Category 1 or Category 2 quantity of radioactive material must implement the requirements in 

10 CFR Part 37. For additional guidance on implementing the 10 CFR Part 37 requirements, 

see NUREG-2155, “Implementation Guidance for 10 CFR Part 37, ‘Physical Protection of 

Category 1 and Category 2 Quantities of Radioactive Material.’” Category 1 and Category 2 

sources regulated by the NRC and Agreement States must be tracked in the National Source 

Tracking System (NSTS) in accordance with 10 CFR 20.2207.

Response from Applicant: Provide all of the following:

• Identify each radionuclide and nominal activity in each portable gauge.

• Identify the manufacturer (or distributor) and model number of each type of

portable gauge.

• State the number of each type of portable gauge requested.

• Provide a description of the use of the gauges.

• Confirm that the activity per source and maximum activity per gauge being requested will 

not exceed the maximum activity listed in the approved certificate of registration issued 

by the NRC or by an Agreement State.

Reference: For more information about the SSD registration process, see NUREG–1556, 

Volume 3, “Consolidated Guidance About Materials Licenses: Applications for Sealed Source 

and Device Evaluation and Registration.”
8-6

8.5.2 Financial Assurance and Recordkeeping for Decommissioning

Regulations: 10 CFR 30.34(b), 10 CFR 30.35, 10 CFR 30.51(f)

Criteria: Portable gauge licensees authorized to possess sealed sources containing radioactive 

material in excess of the limits specified in 10 CFR 30.35, “Financial assurance and 

recordkeeping for decommissioning,” must provide evidence of financial assurance for 

decommissioning.

Licensees are required to maintain, in an identified location, decommissioning records related to 

leaking sources and to structures and equipment where portable gauges are used or stored. 

Pursuant to 10 CFR 30.35(g), licensees must transfer these records important to 

decommissioning to the new proposed licensee before licensed activities are transferred or 

assigned in accordance with 10 CFR 30.34(b). Furthermore, pursuant to 10 CFR 30.51(f), prior 

to license termination, each licensee must forward the records required by 10 CFR 30.35(g) to 

the appropriate NRC regional office.

Discussion: The requirements for financial assurance are specific to the types and quantities 

of byproduct material authorized on a license. Most portable gauge applicants and licensees do 

not need to take any action to comply with the financial assurance requirements because their 

possession limits do not exceed the thresholds in 10 CFR 30.35(d). A licensee would need to 

possess hundreds of gauges before the financial assurance requirements would apply. 

Applicants and licensees desiring to possess gauges exceeding the threshold amounts must 

submit evidence of financial assurance. Licensees should follow the guidance provided in 

NUREG–1757, Volume 3, “Consolidated Decommissioning Guidance—Financial Assurance, 

Recordkeeping, and Timeliness.”

The regulations in 10 CFR 30.35(g) require that licensees maintain records important to 

decommissioning in an identified location. All portable gauge licensees need to maintain 

records of structures and equipment where gauges were used or stored at locations specifically 

listed in the license. As-built drawings (not blueprints) with modifications of structures and 

equipment shown, as appropriate, fulfill this requirement. If drawings are not available, 

licensees must substitute appropriate records (e.g., a sketch of the room or building or a 

narrative description of the area) concerning these areas and locations. If no records exist 

regarding structures and equipment where gauges were used or stored, licensees must make 

all reasonable efforts to create such records based on historical information (e.g., employee 

recollections). In addition, if portable gauge licensees have experienced unusual occurrences

(e.g., leaking sources and other incidents that involve the spread of contamination) they also 

need to maintain records about possible contamination that remains after cleanup or that may 

have spread to inaccessible areas.

For portable gauge licensees whose sources have never leaked, acceptable records important 

to decommissioning are sketches or written descriptions of the specific locations where each 

gauge was used or stored at locations specifically listed in the license, copies of a current leak 

test for each gauge, and records of transfer or disposal.

Response from Applicant: No response is needed from most applicants. If financial 

assurance is required, submit the documentation required under 10 CFR 30.35 and follow the 

guidance of NUREG-1757.
8-7

Reference: NUREG–1757, Volume 3, “Consolidated Decommissioning Guidance—Financial 

Assurance, Recordkeeping, and Timeliness.”

8.6 Item 6: Purpose(s) for Which Licensed Material Will Be Used

Regulation: 10 CFR 30.33(a)(1)

Criteria: An application for a license will be approved if the proposed activity is authorized by 

the Atomic Energy Act of 1954, as amended, and devices will be used only for the purposes for 

which they were designed and according to the manufacturer’s recommendations for use, as 

specified in an approved SSD registration certificate.

Discussion: Uses other than those listed in the SSD registration certificate require review and 

approval by the NRC or an Agreement State. Requests to use portable gauges for purposes 

not listed in the SSD registration certificate will be reviewed on a case-by-case basis. 

Applicants need to submit sufficient information to demonstrate that the proposed use will not 

compromise the source integrity or shielding, or other components of the device critical to 

radiation safety. The NRC will evaluate the radiation safety program for each type and use of 

gauge requested.

An NRC license does not relieve a licensee from complying with other applicable Federal, 

State, or local regulations.

Response from Applicant: Specifically describe how each device will be used. If the gauging

device(s) will be used for the purposes listed on the SSD registration certificate, or as 

recommended by the manufacturer, the applicant may so state. If the gauging device(s) will be 

used for purposes other than those listed on the SSD registration certificate, specify these other 

purposes and include a safety analysis supporting the request.

Notes:

• The typical portable gauge license authorizes use “to measure physical properties 

of materials.”

• Unusual uses will be evaluated on a case-by-case basis, and the authorized use license 

condition will reflect approved uses.

8.7 Item 7: Individual(s) Responsible for Radiation Safety Program and Their

Training and Experience

8.7.1 Radiation Safety Officer

Regulation: 10 CFR 30.33(a)(3)

Criteria: RSOs must have adequate training and experience. In the past, the NRC has 

found successful completion of one of the following to be evidence of adequate training 

and experience:
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• portable gauge manufacturer’s course for users and RSOs, with hands-on experience 

with portable gauges

OR

• equivalent course that meets the criteria in Appendix C of this NUREG

Discussion: The person responsible for the radiation protection program is the RSO. The 

RSO is key to overseeing and ensuring safe operation of the licensee’s radiation protection

program. The RSO must have adequate training to understand the hazards associated with 

radioactive material and be familiar with all applicable regulatory requirements. The RSO 

should have independent authority to stop operations that he or she considers unsafe. He or 

she should have sufficient time and commitment from management to fulfill his or her duties and 

responsibilities to ensure that radioactive materials are used in a safe manner, approved 

radiation safety procedures are being implemented, and the required records of licensed 

activities are maintained. Typical RSO duties are illustrated in Figure 8-2 and described in 

Appendix D of this NUREG. The NRC requires the name of the RSO to be listed on the license 

to ensure that licensee management always has a responsible, qualified person identified and 

that the named individual knows of his or her designation as RSO. Appendix D also provides a 

model Delegation of Authority, which should be used to further emphasize the agreement on 

duties and responsibilities of the RSO by management and the designated RSO.

Figure 8-2. Typical Duties and Responsibilities of RSOs

The RSO may delegate certain day-to-day tasks of the radiation protection program to other 

responsible individuals, sometimes referred to as “alternate RSOs” or “site RSOs.” For 

example, a licensee with multiple permanent locations of use or use at temporary jobsites may 

appoint “site RSOs,” who assist the RSO and are responsible for the day-to-day activities at 

these locations. Licensees may also appoint “alternate RSOs” who may “step in” as an 

emergency contact when the RSO is unavailable. Such “alternate RSOs” or “site RSOs” do not

need to meet all RSO qualifications; however, they should be qualified, experienced authorized 

users who have adequate knowledge of the activities to which they are assigned. These 

individuals should have the same management support and decision-making authority as the 
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RSO that is necessary to accomplish the tasks to which they have been assigned. Please note 

that only the primary RSO is named on an NRC license.

Response from Applicant: Provide the following:

• name of the proposed RSO

• documentation demonstrating that the proposed RSO is qualified by training and 

experience (e.g., certificate of completion of the RSO’s course and/or the authorized 

user’s course)

Note: Licensees must notify the NRC and obtain a license amendment before making changes

in the designation of the RSO responsible for the radiation safety program.

8.8 Item 8: Training for Individuals Working In or Frequenting Restricted Areas

8.8.1 Authorized Users

Regulation: 10 CFR 30.33(a)(3)

Criteria: The individuals using the gauges are usually referred to as “authorized users.” 

Authorized users must have adequate training and experience in the use of portable gauges. In 

the past, the NRC has found successful completion of one of the following to be evidence of 

adequate training and experience:

• portable gauge manufacturer’s course for users and hands-on training in the use of 

portable gauges

OR

• equivalent course that meets the criteria in Appendix C of this NUREG

Discussion: Authorized users have the responsibility to ensure the surveillance, proper use, 

security, and routine maintenance of portable gauges containing licensed material.

Response from Applicant: Provide either of the following:

• the statement: “Before using licensed materials, authorized users will have successfully 

completed one of the training courses described under “Criteria” in the section titled 

“Training for Individuals Working in or Frequenting Restricted Areas” in NUREG–1556, 

Volume 1, Revision 2, ‘Consolidated Guidance About Materials Licenses: 

Program-Specific Guidance About Portable Gauge Licenses.’”

OR

• a description of the training for proposed authorized users
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Notes:

• Completion of online training should be supplemented by documentation of the 

individual’s hands-on training.

• Alternative responses will be evaluated against the previously listed criteria.

• Initial and recurrent (every 3 years) U.S. Department of Transportation hazardous 

material (HAZMAT) training is also required for all authorized users that transport 

gauges (see Section 8.10.9, “Transportation”).

8.9 Item 9: Facilities and Equipment 

Regulations: 10 CFR 20.1101(b), 10 CFR 20.1801, 10 CFR 30.33(a)(2), 10 CFR 30.34(i)

Criteria: Licensees must propose equipment and facilities that are adequate to protect health 

and minimize danger to life or property. Such equipment and facilities should contribute to 

ensuring that radiation doses to authorized users and members of the public are maintained 

ALARA, and that all licensed material is secured from unauthorized access or removal.

Discussion: The key elements for portable gauge applicants are ensuring compliance with 

public dose limits and maintaining adequate security and control over the gauges. See 

Section 8.10, “Radiation Safety Program,” for additional information.

Response from Applicant: Provide a facility diagram for each permanent portable gauge 

storage location. Include on the diagram the use of adjacent areas (including above and 

below), and information relevant to public dose and security as discussed in Sections 8.10.5, 

“Public Dose,” and 8.10.6, “Operating, Emergency, and Security Procedures,” respectively, in

NUREG–1556, Vol. 1, Rev. 2, “Consolidated Guidance About Materials Licenses: ProgramSpecific Guidance About Portable Gauge Licenses.”

8.10 Item 10: Radiation Safety Program

8.10.1 Audit Program

Regulations: 10 CFR 20.1101, 10 CFR 20.2102

Criteria: Licensees must review the content and implementation of their radiation protection 

programs at least annually to ensure the following:

• Programs comply with NRC and U.S. Department of Transportation (DOT) regulations 

(as applicable) and with the terms and conditions of the license.

• Occupational doses and doses to members of the public are ALARA.

Records of audits and other reviews of program content are maintained for 3 years after the 

record is made.

Discussion: Appendix E of this NUREG contains a suggested annual audit program that is 

specific to the use of portable gauges and is acceptable to the NRC. Since all areas indicated 
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in Appendix E may not be applicable to every licensee and all items may not need to be 

addressed during each audit, licensees may wish to develop a program-specific audit checklist.

The NRC encourages licensee management to conduct performance-based reviews by 

observing work in progress, interviewing staff, and spot-checking required records. As part of 

the audit program, licensees should consider including unannounced audits of gauge users in 

the field to observe whether radiation safety procedures are being followed.

It is essential that once problems are identified, comprehensive corrective actions are taken in a 

timely manner. Information Notice (IN) 96-28, “Suggested Guidance Relating to Development 

and Implementation of Corrective Action,” dated May 1, 1996, provides guidance on this 

subject. The NRC routinely reviews licensee’s records to verify whether appropriate corrective 

actions were implemented in a timely manner to address recurrence. It is in the best interest of 

the licensee to identify potential violations of regulatory requirements and take necessary steps 

to correct them. The NRC can opt to exercise discretion and may elect not to cite the licensee 

for these violations if prompt and effective corrective actions are implemented. The NRC’s 

Enforcement Policy may be found online at http://www.nrc.gov/aboutnrc/regulatory/enforcement/enforce-pol.html and the Enforcement Manual may be found online 

at http://www.nrc.gov/about-nrc/regulatory/enforcement/guidance.html. For examples of the 

NRC’s use of discretion in issuing a notice of violation, refer to the most recent version of NRC’s 

enforcement documents at http://www.nrc.gov/reading-rm/doc-collections/enforcement/. 

With regard to audit records, 10 CFR 20.2102 requires, in part, that licensees maintain records 

of “audits and other reviews of program content and implementation” for 3 years after the record 

is made. The NRC has found audit records that contain the following information to be 

acceptable: date of audit, name of person(s) who conducted the audit, persons contacted by 

the auditor(s), areas audited, audit findings, corrective actions, and followup.

Response from Applicant: The applicant should not submit its audit program to the NRC for 

review during the licensing phase. The audit program will be reviewed during NRC inspections.

Reference: Inspection Procedure 87124, “Fixed and Portable Gauge Programs”

8.10.2 Radiation Monitoring Instruments

Regulations: 10 CFR 20.1501, 10 CFR 20.2103(a), 10 CFR 30.33(a)(2)

Criteria: Licensees should possess, or have access to, radiation monitoring instruments, which 

are necessary to protect health and minimize danger to life or property, especially in 

circumstances related to incidents involving gauges at construction sites. Instruments used for 

quantitative radiation measurements must be calibrated periodically for the radiation measured.

Discussion: Each year, there are a number of incidents involving gauges at construction sites 

(e.g., construction equipment running over the gauge). It is important to determine as soon as 

possible after an incident, by the use of a radiation survey meter, whether the shielding and 

source are intact. Applicants should preplan how they will obtain and properly use a radiation 

survey instrument (e.g., use a radiation survey instrument located on site or obtain one from the 

applicant’s home office, another licensee, a consultant, or a local emergency response 

organization). The applicant should also consider the availability of a survey meter during 

non-business hours. 
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Response from Applicant: Provide either of the following:

• the statement: “We will either possess and use, or have access to and use, a radiation 

survey meter that meets the criteria in the section titled “Radiation Safety Program—

Radiation Monitoring Instruments” in NUREG–1556, Volume 1, Revision 2,

“Consolidated Guidance About Materials Licenses: Program-Specific Guidance About 

Portable Gauge Licenses,” in the event of an incident”

OR

• a description of an alternative procedure for determining source integrity after an incident 

involving the gauge

Notes:

• Alternative responses will be reviewed against the previously listed criteria.

• Applicants who plan to perform nonroutine maintenance that requires removing the 

source or source rod from the gauge should possess and use a radiation survey meter 

that meets more stringent criteria. Refer to Section 8.10.8 and to Appendix F of this 

NUREG for more information.

8.10.3 Material Receipt and Accountability

Regulations: 10 CFR 20.1801, 10 CFR 20.1802, 10 CFR 30.34(e), 10 CFR 30.41,

10 CFR 30.51, 49 CFR 172.201

Criteria: Licensees must do the following:

• maintain records of receipt, transfer, and disposal of gauges

• conduct physical inventories every 6 months (or at other intervals justified by the 

applicant and approved by the NRC) to account for all sealed sources

Discussion: Licensed materials must be tracked “from cradle to grave” in order to ensure 

gauge accountability; identify when sealed sources/gauges could be lost, stolen, or misplaced;

and ensure that possession limits listed on the license are not exceeded. Many licensees 

record daily use of gauges in a log book as part of their accountability program. See the 

suggested operating procedures in Appendix G of this NUREG. A log meeting the requirements 

of 49 CFR 172.201 is required if making multiple shipments using one shipping paper. 

Receipt, inventory, transfer, and disposal records must be maintained for the times specified in 

Table 8-1. Typically, these records contain the following types of information:

• radionuclide and the activity [in units of becquerels (Bq) or curies] of byproduct material 

in each sealed source

• manufacturer’s name, model number, and serial number (if appropriate) of each gauge 

containing byproduct material
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• location of each sealed source and device (if appropriate)

• for inventories, the date of the inventory, and name and signature of the individual 

conducting the inventory

• for materials transferred or disposed of, the date of the transfer or disposal, the name 

and license number of the recipient, and a description of the affected radioactive 

material (e.g., radionuclide, activity, manufacturer’s name and model number, serial 

number)

Table 8-1. Record Maintenance

Type of Record How Long Record Must Be Maintained

Receipt For as long as the material is possessed and for 3 years 

following the transfer or disposal of the material

Inventory For 5 years from the date of the inventory in accordance 

with license conditions

Transfer For 3 years after each transfer unless a specific requirement 

dictates otherwise

Disposal Until the NRC terminates the license

Important to Decommissioning* Until the site is released for unrestricted use

*See Section 8.5.2, “Financial Assurance and Recordkeeping for Decommissioning,” for more details.

Response from Applicant: Provide either of the following:

• the statement: “Physical inventories will be conducted every 6 months or at other 

intervals approved by the NRC to account for all sealed sources and devices received 

and possessed under the license.”

OR

• a description and justification of an alternate frequency and/or procedure to account for 

all sealed sources and devices received and possessed under the license

AND

• the statement: “We will develop, implement and maintain procedures for ensuring 

accountability of licensed materials at all times.”

8.10.4 Occupational Dose

Regulations: 10 CFR 19.13, 10 CFR 20.1201, 10 CFR 20.1207, 10 CFR 20.1208,

10 CFR 20.1501, 10 CFR 20.1502

Criteria: Applicants must do either of the following:

• perform a prospective evaluation demonstrating that unmonitored individuals are not 

likely to receive a radiation dose in excess of the limits in 10 CFR 20.1502(a), and 

maintain a record of this evaluation for inspection by the NRC

OR
8-14

• provide and require the use of individual monitoring devices (dosimetry) (All personnel 

dosimeters that require processing to determine the radiation dose must be processed 

and evaluated by a National Voluntary Laboratory Accreditation Program (NVLAP)-

approved processor.)

Discussion: Licensees must evaluate the potential occupational exposure of all workers and 

monitor occupational exposure. When personnel monitoring is required, for all personnel 

dosimeters that require processing to determine the radiation dose, licensees must use 

dosimeters supplied by an NVLAP-approved processor. The exchange frequency for 

dosimeters is typically monthly or quarterly. Applicants should consult with their 

NVLAP-approved processor for its recommendations for exchange frequency and proper use of 

the dosimeter.

The annual dose limits for adult radiation workers are shown in Figure 8-3. Note that in 

accordance with 10 CFR 20.1207, the annual occupational dose limits for minors are 10 percent 

of the annual dose limits specified for adult workers. Also, 10 CFR 20.1208 requires the 

licensee to ensure that the dose equivalent to the embryo/fetus during the entire pregnancy, 

due to the occupation exposure of a declared pregnant woman, does not exceed 0.5 rem [5 

millisieverts (mSv)].

Figure 8-3. Annual Dose Limits for Adult Radiation Workers

Total effective dose equivalent (TEDE) equals the effective dose equivalent (for external 

exposures) plus the committed effective dose equivalent (for internal exposures).

The use of individual monitoring devices for external dose is required, pursuant to 

10 CFR 20.1502(a), for

• adults who are likely to receive an annual dose in excess of any of the following 

(each evaluated separately)

— 5 mSv [0.5 rem] deep-dose equivalent
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— 15 mSv [1.5 rems] lens (of the eye) dose equivalent

— 50 mSv [5 rems] shallow-dose equivalent to the skin

— 50 mSv [5 rems] shallow-dose equivalent to any extremity

• minors who are likely to receive an annual dose in excess of any of the following 

(each evaluated separately)

— 1.0 mSv [0.1 rem] deep-dose equivalent

— 1.5 mSv [0.15 rem] lens (of the eye) dose equivalent

— 5 mSv [0.5 rem] shallow-dose equivalent to the skin

— 5 mSv [0.5 rem] shallow-dose equivalent to any extremity

• declared pregnant women who are likely to receive a dose from radiation sources 

external to the body during the entire pregnancy in excess of 1.0 mSv [0.1 rem]

deep-dose equivalent

• individuals entering a high or very high radiation area

Under conditions of routine use (including weekly cleaning and lubrication of the gauge 

according to the manufacturer’s instructions), the typical portable gauge user does not require a 

personnel monitoring device (dosimetry). In many accidents in which a gauge has been run 

over and has been damaged, the shielding of the source remains intact. However, there have 

been several instances in which a source did not remain in the shielded position. In such 

cases, the user must exercise care to ensure that workers at the jobsite are alerted about the 

radiation and protected from radiation exposure. A gauge user also does not require dosimetry 

when proper emergency procedures are used. Part 1 of Appendix H of this NUREG provides 

guidance on preparing a written evaluation demonstrating that gauge users are not likely 

to exceed the limits in 10 CFR 20.1502(a) and, therefore, are not required to have 

personnel dosimetry.

Response from Applicant: Provide one of the following:

• the statement: “We will maintain, for inspection by the NRC, documentation 

demonstrating that unmonitored individuals are not likely to receive a radiation dose in 

excess of the limits in 10 CFR 20.1502(a).”

OR

• the statement: “We will provide and require the use of individual monitoring devices 

(dosimetry). All personnel dosimeters that require processing to determine the radiation 

dose will be processed and evaluated by a NVLAP-approved processor.”

Notes:

• Alternative methods for demonstrating compliance with the referenced regulations will be 

evaluated against the previously listed criteria.
8-16

• Some licensees choose to provide personnel dosimetry to their workers for reasons 

other than compliance with NRC requirements (e.g., to respond to worker requests or to 

maintain records of personal exposure).

Reference: The National Institute of Standards and Technology maintains a directory of 

laboratories that are NVLAP-approved at http://ts.nist.gov/standards/scopes/dosim.htm.

8.10.5 Public Dose

Regulations: 10 CFR 20.1301, 10 CFR 20.1302, 10 CFR 20.1801, 10 CFR 20.1802, 10 CFR 

20.2107

Criteria: Licensees must do the following:

• ensure that portable gauges will be used, transported, and stored in such a way that 

members of the public will not receive more than 1 mSv [100 mrem] in a year, and the 

dose in any unrestricted area will not exceed 0.02 mSv [2 mrem] in any one hour, from 

licensed operations

• control and maintain constant surveillance over gauges that are not in storage and 

secure stored gauges from unauthorized removal or use

Figure 8-4. Storing Gauges. Gauges Should be Stored Away From Occupied Areas and

Must Be Secured Against Unauthorized Removal.

Discussion: Public dose is defined in 10 CFR Part 20 as “the dose received by a member of 

the public from exposure to radiation or to radioactive material released by a licensee, or to any 

other source of radiation under the control of a licensee.” Public dose excludes doses received 

from background radiation and medical procedures. Whether the dose to an individual is an 

occupational dose or a public dose depends on the individual’s assigned duties. It does not 

depend on the area (restricted, controlled, or unrestricted) where the individual is when he or 

she receives the dose.

Members of the public include persons who live, work, or may be near locations where portable 

gauges are used or stored and employees whose assigned duties do not include the use of 

licensed materials and who work in the vicinity where gauges are used or stored.
8-17

Operating, emergency, and security procedures for security and surveillance specified under 

Section 8.10.6 of this document should be sufficient to limit the exposure to the public during 

use or storage and after accidents. Public dose is controlled, in part, by ensuring that gauges 

not in use are stored securely (e.g., stored in a locked area) to prevent unauthorized access 

or use (see Figure 8-4). If gauges are not in storage, then authorized users must maintain 

constant surveillance and control to ensure that members of the public, who could be 

coworkers, do not get near the gauges or use them and thus receive unnecessary

radiation exposure.

Public dose is also affected by the choice of storage location and conditions. There always is a 

radiation field around the gauge; therefore, it must be stored so that the radiation level in an 

unrestricted area (e.g., an office, the exterior surface of an outside wall, or occupied areas of a 

personal residence) does not result in a dose that exceeds 1 mSv [100 mrem] in a year or 

0.02 mSv [2 mrem] in any one hour. Licensees should take time, distance, and shielding into 

consideration when choosing a permanent or temporary storage location. Decreasing the time 

spent near a portable gauge, increasing the distance from the gauge, and using shielding 

(i.e., brick, concrete, lead, or other solid walls) will reduce radiation exposure. As a rule of 

thumb, gauges should be stored as far away as possible from areas that normally are occupied 

by other employees and members of the public.

Licensees can determine the radiation levels adjacent to, including areas above and/or below,

the storage location by either calculations or a combination of direct measurements and 

calculations using some or all of the following: typical known radiation levels provided by the 

manufacturer, the “inverse square” law to evaluate the effect of distance on radiation levels, and 

occupancy factors to account for the actual presence of the member of the public and of the 

gauge(s). See Part 2 of Appendix H of this NUREG for examples.

If, after making an initial evaluation, a licensee makes changes affecting the storage area 

(e.g., changing the location of gauges within the storage area, removing shielding, adding 

gauges, changing the occupancy of adjacent areas, moving the storage area to a new location), 

then the licensee must ensure that gauges are properly secured, perform a new evaluation to 

ensure that the public dose limits are not exceeded, and take corrective action, as needed.

Response from Applicant: No response is required from the applicant in a license application, 

but the NRC will examine this matter during inspections.

8.10.6 Operating, Emergency, and Security Procedures

Regulations: 10 CFR 20.1101, 10 CFR 20.1801, 10 CFR 20.1802, 10 CFR 20.2201–2203, 

10 CFR 30.34(i), 10 CFR 30.50

Criteria: Each applicant should do the following:

• develop, implement, and maintain operating, emergency, and security procedures 

containing the following elements:

— instructions for using the portable gauge and performing routine maintenance 

according to the manufacturer’s recommendations and instructions

— instructions for maintaining security during storage and transportation
8-18

— instructions to keep the gauge under control and constant surveillance 

during field operations

— steps to take to keep radiation exposures ALARA

— steps to maintain accountability during use

— steps to control access to a damaged gauge

— steps to take and whom to contact when a gauge has been damaged

• if gauges are used for measurements with the unshielded source extended more than 

3 feet beneath the surface, licensees must, in accordance with standard license 

conditions, do the following:

— require the use of surface casing or alternative procedures to ensure that the 

source can move freely in the hole

— provide instructions for procedures to follow to retrieve a stuck source

— require reporting to the NRC, under 10 CFR 30.50(b)(2), when a stuck source 

cannot be retrieved

• provide copies of operating, emergency, and security procedures to all gauge users and 

have them available at each jobsite

Figure 8-5. Proper Handling of Incidents. Gauges Can Be Damaged By Heavy Equipment

at Jobsites; Therefore, Emergency Procedures Need To Be Followed To 

Minimize Radiation Safety Risk.

Discussion: Lost or stolen portable gauges and, as illustrated in Figure 8-5, gauges damaged 

by heavy equipment during use at jobsites are the most common occurrences that present a 

potentially significant radiation safety risk. Operating, emergency, and security procedures

should be developed to minimize these risks. 
8-19

Certain portable gauges are used to make measurements with the unshielded source extended 

more than 3 feet beneath the surface. Unless precautionary measures are taken, it is possible 

for the source to be buried under dirt or concrete that collapses around the source during the 

measurements. Precautionary measures need to be planned in advance to prevent these 

sources from being buried and to recover sources should they become stuck. To ensure that 

(1) the hole is free of debris; (2) it is not likely that debris will reenter the cased hole; and (3) the 

source will be able to move freely, the NRC will usually, through standard license conditions, 

require the use of surface casing from the lowest depth to 12 inches above the surface. If it is 

not feasible to extend the casing 12 inches above the surface, licensees may cap the hole and 

use dummy probes before making measurements with an unshielded source to ensure that the 

hole is free of obstructions.

Notify the NRC when gauges are lost, stolen, or damaged. Refer to the regulations in 

10 CFR 30.50 for a description of when and where such notifications are required. A list of 

reporting requirements is provided in Table G–1 of Appendix G of this NUREG. When in 

storage, gauges must be secured against unauthorized removal, in accordance with 

10 CFR 20.1801. When gauges are in use, the licensee must control and maintain constant 

surveillance over them, in accordance with 10 CFR 20.1802. Under 10 CFR 30.34(i), portable 

gauge licensees must use a minimum of two independent physical controls that form tangible 

barriers in order to secure their portable gauges from unauthorized removal, whenever such 

gauges are not under the control and constant surveillance of the licensee. Further guidance 

regarding the storage and control of gauges is provided in Appendix G of this NUREG.

Response from Applicant: Provide any one of the following:

• the statement: “We will implement and maintain the operating, emergency, and security 

procedures in Appendix G to NUREG–1556, Volume 1, Revision 2, “Consolidated 

Guidance About Materials Licenses: Program-Specific Guidance About Portable Gauge 

Licenses.” Copies of these procedures will be provided to all gauge users and will be 

available at each jobsite.”

OR

• the statement: “Operating, emergency, and security procedures will be developed, 

implemented, and maintained and will meet the criteria in section 8.10.6, “Radiation 

Safety Program—Operating, Emergency, and Security Procedures,” NUREG–1556, 

Volume 1, Revision 2, “Consolidated Guidance About Materials Licenses: 

Program-Specific Guidance About Portable Gauge Licenses.” Copies of these 

procedures will be provided to all gauge users and will be available at each jobsite.”

OR

• alternative procedures, and the statement, “Copies of these procedures will be provided 

to all gauge users and will be available at each jobsite.”

Note: Alternative procedures will be reviewed against the previously listed criteria.
8-20

References: 

• IN 93-18, “Portable Moisture-Density Gauge User Responsibilities During Field 

Operations,” dated March 10, 1993

• NUREG/BR–0133, “Working Safely with Nuclear Gauges,” issued February 1996 

• IN 98-01, “Thefts of Portable Gauges,” dated January 15, 1998

• IN 2001-11, “Thefts of Portable Gauges,” dated July 13, 2001

• IN 2002-30, “Control and Surveillance of Portable Gauges During Field Operations,” 

dated October 30, 2002

8.10.7 Leak Tests

Regulations: 10 CFR 20.1501, 10 CFR 20.2103, 10 CFR 30.50(c)(2), 10 CFR 30.53

Criteria: The NRC requires testing to determine whether there is any radioactive leakage from 

the source in the portable gauge. The NRC finds leak testing to be acceptable if it is conducted 

by an organization licensed by the NRC or an Agreement State. Licensees must maintain 

records of leak test results in accordance with license conditions or, if applicable, NRC 

regulations.

Discussion: When issued, a license will require the performance of leak tests at intervals 

approved by the NRC or an Agreement State, as specified in the device’s SSD registration 

certificate or at a more frequent interval that the licensee committed to in its license application. 

The measurement of the leak test sample is a quantitative analysis that requires instrumentation 

capable of detecting 185 Bq [0.005 microcurie] of radioactivity. If the test reveals the presence 

of 185 Bq [0.005 microcurie] or more of removable contamination, a report should be filed with 

the NRC in accordance with 10 CFR 30.50(c)(2).

Manufacturers, consultants, and other organizations may be authorized by the NRC or an 

Agreement State to either perform the entire leak test process for other licensees or provide 

leak test kits to licensees. In the latter case, the licensee is expected to take the leak test

sample according to the gauge manufacturer’s and the kit supplier’s instructions and return it to 

the kit supplier for analysis and reporting results. Leak test samples should be collected at the 

most accessible area where contamination would accumulate if the sealed source were leaking. 

The NRC or an Agreement State may, in a license condition, specifically authorize portable 

gauge licensees to conduct the entire leak test sequence themselves. Appendix I of this 

NUREG provides information to support a request to perform leak testing and sample analysis.

Response from Applicant: The applicant should provide one of the following:

• the statement: “Leak tests will be performed at intervals approved by the NRC or an 

Agreement State and specified in the Sealed Source and Device registration certificate. 

Leak tests will be performed by an organization licensed by the NRC or an Agreement 

State to provide leak testing services to other licensees; or by using a leak test sample 

collection kit supplied by an organization licensed by the NRC or an Agreement State to 
8-21

provide leak test kits and/or sample analysis services to other licensees and according 

to the kit supplier’s instructions. Records of leak test results will be maintained.”

OR

• the statement: “We will implement the model leak test program published in Appendix I 

of NUREG–1556, Volume 1, Revision 2, ‘Consolidated Guidance About Materials 

Licenses: Program-Specific Guidance About Portable Gauge Licenses.’ Records of 

leak tests will be maintained.”

OR

• a description of alternative equipment and/or procedures for determining whether there 

is any radioactive leakage from sources contained in gauges and the statement: 

“Records of leak tests will be maintained.”

Note: Requests for authorization to perform leak testing and sample analysis will be reviewed 

on a case-by-case basis and, if approved, will be authorized via a license condition.

8.10.8 Maintenance

Regulations: 10 CFR 20.1101, 10 CFR 30.34(e)

Criteria: Licensees should routinely clean and maintain gauges according to the 

manufacturer’s written recommendations and instructions. For gauges with a source rod, 

radiation safety procedures for routine cleaning and lubrication of the source rod and shutter 

mechanism (e.g., to remove caked dirt, mud, asphalt, or residues from the source rod; to

lubricate the shutter mechanism) should consider the possibility of receiving exposures to the 

whole body, as well as to the hands, from handling the source rod. Licensees, in accordance 

with 10 CFR 20.1101(b), are required to keep such exposures ALARA. Licensees should also 

ensure that the gauge functions as designed and source integrity is not compromised.

Nonroutine maintenance or repair (beyond routine cleaning and lubrication) that involves 

detaching the source or source rod from the device, and any other activities during which 

personnel could receive radiation doses exceeding NRC limits, must be performed by the gauge 

manufacturer or a person specifically authorized by the NRC or an Agreement State. Requests 

from portable gauge licensees for specific authorization to perform nonroutine maintenance or 

repair (see Appendix F of this NUREG) must demonstrate that personnel performing the work:

• have adequate training and experience

• use equipment and procedures that ensure compliance with regulatory requirements 

and consider ALARA

• ensure that the gauge functions as designed and that source integrity is 

not compromised
8-22

Figure 8-6. Maintenance. All Licensees Should Perform Routine Cleaning and 

Lubrication To Ensure Proper Operation of the Gauge. Most Licensees Rely on 

the Gauge Manufacturer Or Other Service Provider Companies to Perform 

Nonroutine Maintenance.

Discussion: Figure 8-6 illustrates routine cleaning and lubrication and nonroutine

maintenance. Generally, the NRC permits portable gauge licensees to perform routine 

maintenance of the gauges, provided that they follow the gauge manufacturer’s 

recommendations and instructions. Although manufacturers may use different terms, “routine 

maintenance” includes, but is not limited to, cleaning, lubrication, changing batteries or fuses, 

and repairing or replacing a handle. Routine maintenance does not include any activities that 

require removing the sealed source or source rod from the gauge.

Most licensees do not perform nonroutine maintenance or repair operations that require 

detaching the source or source rod from the gauge; they usually return the gauge to the 

manufacturer. Applicants seeking authorization to detach the source or source rod from the 

device must submit specific procedures for review. See Appendix F of this NUREG for 

more information.

Response from Applicant:

Routine cleaning and lubrication: Submit either of the following:

• the statement: “We will implement and maintain procedures for routine maintenance of 

our gauges according to each manufacturer’s written recommendations and instructions”

OR

• alternative procedures for NRC review

Nonroutine maintenance or repair operations that require detaching the source or source rod 

from the gauge: Submit either of the following:

• the statement: “The gauge manufacturer, or other person licensed by the NRC or an 

Agreement State will perform nonroutine maintenance or repair operations that require 

detaching the source or source rod from the gauge.”

OR
8-23

• a request to perform this work “in-house,” using the information in Appendix F of this 

NUREG to support the request

Notes:

• Alternative procedures for performing routine cleaning and lubrication will be evaluated 

using the criteria listed previously.

• Information requested in Appendix F of this NUREG will be reviewed on a case-by-case 

basis; if the request is approved, the license will contain a specific condition authorizing 

the licensee to perform nonroutine maintenance.

8.10.9 Transportation

Regulations: 10 CFR 20.1101, 10 CFR 71.5, 49 CFR 171–178, 390–397

Criteria: Applicants must follow DOT regulations for the offsite transport of radioactive material.

Discussion: The NRC uses the provisions of 10 CFR 71.5, “Transportation of licensed 

material,” to examine and enforce transportation requirements found in 49 CFR, 

“Transportation,” applicable to portable gauge licensees. Appendix J of this NUREG lists 

applicable DOT regulations. See also Section 8.10.6 for guidance on preventing loss or theft of 

gauges when they are not in use.

Some DOT requirements that are applicable to portable gauge licensees include:

• The labeling of the transport container must be maintained in a legible condition, per the 

requirements in 49 CFR 172.403(g) and 49 CFR 172.407(a).

• The licensee must properly block and brace the transportation case to ensure that the 

gauge does not shift during transport, per the requirement in 49 CFR 177.842(d).

• The licensee must have emergency response information, including current emergency 

response telephone numbers that meet the requirements of Subpart G, “Emergency 

Response Information,” of 49 CFR Part 172; “Hazardous Materials Table, Special 

Provisions, Hazardous Materials Communications, Emergency Response Information, 

Training Requirements, and Security Plans.” 

• Initial and recurrent training must be given to all HAZMAT employees who perform 

transport functions for portable gauges, per the requirements of Subpart H, “Training,” of 

49 CFR Part 172.

• The licensee shall maintain transportation shipping records, in accordance with the 

requirements of Subpart C, “Shipping Papers,” of 49 CFR Part 172, including the proper 

shipping name, hazard class (7), United Nations identification number, the name of the 

shipper, and the name and activity of each radionuclide.

Response from Applicant: No response is needed; the NRC will review this issue during 

inspection.
8-24

Reference: “Radioactive Material Regulations Review,” published by DOT, Pipeline and 

Hazardous Materials Safety Administration, in December 2008 (can be obtained at

http://www.phmsa.dot.gov)

8.11 Item 11: Waste Management—Gauge Disposal and Transfer

Regulations: 10 CFR 20.2001, 10 CFR 30.36, 10 CFR 30.41, 10 CFR 30.51

Criteria: Licensed materials must be disposed of in accordance with NRC requirements by 

transfer to an authorized recipient. Appropriate records must be maintained.

Discussion: Significant problems can arise from improper gauge transfer or failure to dispose 

of gauges in a proper and timely manner. Such problems include the possession of radioactive 

materials by unauthorized individuals, which could result in exposures to members of the 

general public. When disposing of portable gauges, licensees must transfer them to an 

authorized recipient. Authorized recipients are the original manufacturer of the device, a 

commercial firm licensed by the NRC or an Agreement State to accept radioactive waste from 

other persons, or another specific licensee authorized to possess the licensed material 

(i.e., their license specifically authorizes the manufacturer, model, isotope(s), and quantity of 

byproduct material). 

Before transferring radioactive material, the licensee must verify that the recipient is properly 

authorized to receive the licensed material using one of the methods described in 

10 CFR 30.41, “Transfer of byproduct material.” In addition, all packages containing radioactive 

sources must be prepared and shipped in accordance with NRC and DOT regulations. The 

licensee must maintain records of the transfer, as required by 10 CFR 30.51, “Records.”

Response from Applicant: The applicant does not need to provide a response to this item 

during the licensing process. However, the licensee should establish and include gauge 

transfer and waste disposal procedures in its radiation safety program.

8.12 Item 12: License Fees

On NRC Form 313, enter the appropriate fee category from 10 CFR 170.31 and the amount of 

the fee enclosed with the application. The appropriate fee is found in Category 3P.

Direct all questions about NRC’s fees or completion of Item 12 of NRC Form 313 to the Office of 

the Chief Financial Officer at NRC Headquarters in Rockville, MD, 301-415-7554. Information 

about fees may also be obtained by calling the NRC's toll-free number, 800-368-5642,

extension 415-7554. The e-mail address is Fees.Resource@nrc.gov.

8.13 Item 13: Certification

A representative of the corporation or legal entity filing the application must sign and date 

NRC Form 313. The representative signing the application must be authorized to make binding 

commitments and to sign official documents on behalf of the applicant. As discussed 

previously in Chapter 3, “Management Responsibility,” signing the application acknowledges 

management’s commitment to and responsibility for the radiation protection program. The

NRC will return all unsigned applications for proper signature.
8-25

Notes:

• It is a criminal offense to knowingly and willfully make a false statement or 

representation on applications or correspondence (18 U.S.C. 1001).

• When the application references commitments, those items will be incorporated into the 

license and, therefore, will become binding regulatory requirements.

9-1

9 LICENSE AMENDMENTS AND RENEWALS

It is the licensee’s obligation to keep the license current. If any of the information provided in 

the original application is to be modified or changed, the licensee must submit an application for 

a license amendment before the change takes place. The change is not in effect until the 

amendment has been issued. Also, to continue the license after its expiration date, the licensee 

must submit an application for a license renewal at least 30 days before the expiration date 

Title 10 of the Code of Federal Regulations (10 CFR) [10 CFR 2.109(a), 10 CFR 30.36(a)].

Applicants for license amendment or renewal should do the following:

• Use the most recent guidance in preparing an amendment or renewal request.

• Submit either a U.S. Nuclear Regulatory Commission (NRC) Form 313 or a letter 

requesting amendment or renewal.

• Provide the license number and docket number.

• For renewals, provide a complete and up-to-date application, including all required 

program elements outlined in Appendix B of this NUREG. Training documentation for 

personnel currently listed on the license does not need to be submitted as part of the 

renewal application.

9.1 Timely Notification of Transfer of Control

Regulation: 10 CFR 30.34(b)

Criteria: Licensees must provide all supporting information and obtain the NRC’s prior, written 

consent before transferring control of the license, also referred to as a “change of ownership” 

and/or “transferring the license.”

Discussion: Transferring control may be the result of mergers, buyouts, or majority stock 

transfers. Although it is not the NRC’s intent to interfere with the business decisions of 

licensees, it is necessary for licensees to obtain prior NRC written consent to ensure 

the following:

• radioactive materials are possessed, used, or controlled only by persons who have valid 

NRC licenses or Agreement State licenses

• materials are properly handled and secured

• persons using these materials are capable, competent and committed to implementing

appropriate radiological controls

• a clear chain of custody is established to identify who is responsible for disposition of 

records and licensed material

• public health and safety are not compromised by the use of such materials
9-2

Response from Applicant: No response is required from an applicant for a new license. 

However, current licensees should refer to NUREG–1556, Volume 15, “Consolidated Guidance 

About Materials Licenses: Guidance About Changes of Control and About Bankruptcy Involving 

Byproduct, Source, or Special Nuclear Materials Licenses,” for more information about transfer 

of control (i.e., ownership).

Reference: For further information, see Regulatory Issue Summary (RIS) 2014-08, Revision 1, 

“Regulatory Requirements for Transfer of Control (Change of Ownership) of Specific Materials 

Licenses,” dated May 5, 2016, which can be found on the NRC’s Generic Communications Web

page under “Regulatory Issue Summaries”: http://www.nrc.gov/reading-rm/doc-collections/gencomm/.
10-1

10 APPLICATIONS FOR EXEMPTIONS

Regulations: 10 CFR 19.31, 10 CFR 20.2301, 10 CFR 30.11

Criteria: Licensees may request exemptions from regulations. The licensee must demonstrate 

that the exemption is authorized by law; will not endanger life, property, or the common defense 

and security; and is otherwise in the public interest.

Discussion: Various sections of the U.S. Nuclear Regulatory Commission’s (NRC’s)

regulations address requests for exemptions (e.g., 10 CFR 19.31, “Application for exemptions”;

10 CFR 20.2301, “Applications for exemptions”; 10 CFR 30.11, “Specific exemptions”). These 

regulations state that the NRC may grant an exemption, acting on its own initiative or on an 

application from an interested person.

Exemptions are not intended to revise regulations or apply to large classes of licensees and are 

generally limited to unique situations. Requests for exemptions submitted to the NRC must 

identify the regulation for which the exemption is being requested and include a justification for 

the requested exemption.

Unless the NRC has granted an exemption in writing, licensees must comply with all 

applicable regulations.

11-1

11 TERMINATION OF ACTIVITIES

Regulations: 10 CFR 30.34(b), 10 CFR 30.35(g), 10 CFR 30.36(d), 10 CFR 30.36(h), 10 CFR 

30.36(j)(1), 10 CFR 30.51(f)

Criteria: The licensee must do the following:

• Notify the U.S. Nuclear Regulatory Commission (NRC), in writing, within 60 days of the 

occurrence of any of the following:

— expiration of its license

— a decision to permanently cease principal activities1 at the entire site

— a decision to permanently cease principal activities1 in any separate building or 

outdoor area that contains residual radioactivity such that the building or area is 

unsuitable for release according to NRC requirements

— no principal activities1 under the license have been conducted for a period of 

24 months

— no principal activities1 have been conducted for a period of 24 months in any 

separate building or outdoor area that contains residual radioactivity such that 

the building or area is unsuitable for release according to NRC requirements

• Conduct decommissioning, as required by Title 10 of the Code of Federal Regulations

(10 CFR) 30.36(h).

• Submit, to the appropriate NRC regional office, a completed NRC Form 314, “Certificate 

of Disposition of Materials” (or equivalent information), and information demonstrating

that the premises are suitable for release for unrestricted use (e.g., results of final 

leak tests of sealed sources).

• Before a license is terminated, send records important to decommissioning that are 

required by 10 CFR 30.35(g) to the appropriate NRC regional office in accordance with 

10 CFR 30.51(f).

Discussion: Typically, a portable gauge termination request will meet the previously listed

criteria if the licensee has performed the following steps:

• The licensee must dispose of or transfer the gauges to an NRC or Agreement State 

licensee authorized to possess these devices, as described in Section 8.11, “Waste 

Management—Gauge Disposal and Transfer.”

• The licensee must copy applicable decommissioning records as described in Section 

8.5.2, “Financial Assurance and Recordkeeping for Decommissioning.” Typically, this 

includes transfer of records and final leak test records to the appropriate NRC regional 

 1‘Principal activities’ are activities which are essential to achieving the purpose(s) for which the license was issued or 

amended. Storage during which no licensed material is accessed for use or disposal and activities incidental to 

decontamination or decommissioning are not principal activities.
11-2

office. See Section 8.5.2 for additional recordkeeping requirements if leaking sealed 

sources or other incidents that involve the spreading of contamination have occurred.

• The licensee must submit a completed NRC Form 314 and a copy of the applicable 

decommissioning records to the appropriate NRC regional office.

Response from Applicant: The applicant is not required to submit a response to the NRC 

during the initial application. The licensee’s obligations in this matter begin when the license 

expires or at the time the licensee ceases operations, whichever is earlier. These obligations 

are to undertake the necessary decommissioning activities, to submit NRC Form 314 or 

equivalent information, and to perform any other actions summarized in the previously listed

“Criteria.” 

Reference: NRC Form 314 is available at http://www.nrc.gov/reading-rm/doc-collections/forms.
APPENDIX A

U.S. NUCLEAR REGULATORY COMMISSION FORM 313

A–1

U.S. Nuclear Regulatory Commission Form 313

Please use the most current version of this form, which may be found at: 

http://www.nrc.gov/reading-rm/doc-collections/forms/

APPENDIX B

SUGGESTED FORMAT FOR PROVIDING INFORMATION REQUESTED IN 

ITEMS 5 THROUGH 11 OF

U.S. NUCLEAR REGULATORY COMMISSION FORM 313

B–1

Suggested Format for Providing Information Requested in 

Items 5 through 11 of 

U.S. Nuclear Regulatory Commission Form 313

Items 5 and 6: Materials To Be Possessed and Proposed Uses

Yes No Radionuclide

Manufacturer or 

Distributor Model No. Quantity

Use as Listed on SSD Registration

Certificate

Specify Other 

Uses Not 

Listed on 

SSD 

Registration 

Certificate

Cesium-137 Gauge manufacturer 

(or distributor) and 

model number:

__________________

Specify activity 

per source and 

number of 

gauges 

requested.

___________

___________

Yes ❒

Specific description of the gauge use:

___________

___________

___________

___________

___________

____________

____________

❒ Not 

applicable

____________

❒ Uses are:

____________

(Submit safety 

analysis 

supporting 

safe use.)

Americium241Gauge manufacturer 

(or distributor) and 

model number:

___________________

Specify activity 

per source and 

number of 

gauges 

requested.

___________

___________

Yes ❒

Specific description of the gauge use:

___________

___________

___________

___________

___________

___________

___________

❒ Not 

applicable

____________

❒ Uses are:

____________

(Submit safety 

analysis 

supporting 

safe use.)
B–2

Yes No Radionuclide

Manufacturer or 

Distributor Model No. Quantity

Use as Listed on SSD Registration

Certificate

Specify Other 

Uses Not 

Listed on 

SSD 

Registration 

Certificate

Californium252

Gauge manufacturer 

(or distributor) and 

model number:

___________________

Specify activity 

per source and

number of 

gauges 

requested.

____________

____________

Yes ❒

Specific description of the gauge use:

____________

____________

____________

____________

____________

____________

____________

❒ Not 

applicable

____________

❒ Uses are:

____________

(Submit safety 

analysis 

supporting 

safe use.)

Radium-226 Gauge manufacturer 

(or distributor) and 

model number:

___________________

Specify activity 

per source and 

number of 

gauges 

requested. 

____________

____________

Yes ❒

Specific description of the gauge use:

____________

❒ Not 

applicable

____________

❒ Uses are:

____________

(Submit safety 

analysis 

supporting 

safe use.)

Other Isotope

(Specify):

Gauge manufacturer 

(or distributor) and 

model number:

___________________

Specify activity 

per source and 

number of 

gauges 

requested. 

____________

____________

Yes ❒

Specific description of the gauge use:

____________

❒ Not 

applicable

____________

❒ Uses are:

____________

(Submit safety 

analysis 

supporting 

safe use.)

Is financial assurance required? If yes, submit evidence of financial assurance.
B–3

Items 7 through 11: Training and Experience,

Facilities and Equipment, Radiation Safety Program, 

and Waste Disposal

Item No. and Title Suggested Response Yes Alternative 

Procedures 

Attached

7. INDIVIDUAL(S) 

RESPONSIBLE FOR 

RADIATION 

SAFETY PROGRAM 

AND THEIR 

TRAINING AND 

EXPERIENCE—

RADIATION 

SAFETY OFFICER

Name:_____________

Documentation demonstrating the 

proposed radiation safety officer’s 

training and experience (e.g., 

certificate of completion of the 

RSO’s course and/or the 

authorized user’s course).

Submit 

applicable 

documentation.

8. TRAINING FOR 

INDIVIDUALS 

WORKING IN OR 

FREQUENTING 

RESTRICTED 

AREAS

Before using licensed materials, 

authorized users will have 

successfully completed one of the 

training courses described in the 

“Criteria” part of the section titled,

“Training for Individuals Working in

or Frequenting Restricted Areas” 

in NUREG–1556, Vol. 1, Rev. 2, 

“Consolidated Guidance About 

Materials Licenses: ProgramSpecific Guidance About Portable 

Gauge Licenses.”

❒ ❒

9. FACILITIES AND 

EQUIPMENT

Provide a facility diagram for each 

permanent portable gauge storage 

location. Include on the diagram 

the use of adjacent areas 

(including above and below), and 

information relevant to public dose 

and security as discussed in 

Sections 8.10.5, “Public Dose,”

and 8.10.6, “Operating, 

Emergency, and Security 

Procedures,” respectively, in 

NUREG–1556, Vol. 1, Rev. 2, 

“Consolidated Guidance About 

Materials Licenses: ProgramSpecific Guidance About Portable 

Gauge Licenses”

Submit 

applicable 

documentation.
B–4

Item No. and Title Suggested Response Yes Alternative 

Procedures 

Attached

10.1 RADIATION 

SAFETY 

PROGRAM—AUDIT 

PROGRAM

The applicant should not submit its 

audit program to the NRC for 

review during the licensing phase.

The audit program will be 

reviewed during NRC inspections.

Need Not Be Submitted with

Application

10.2 RADIATION 

SAFETY 

PROGRAM—

RADIATION 

MONITORING

INSTRUMENTS

We will either possess and use, or 

have access to and use, a 

radiation survey meter that meets 

the criteria in the section titled,

“Radiation Safety Program—

Radiation Monitoring Instruments” 

in NUREG–1556, Vol. 1, Rev. 2,

“Consolidated Guidance About 

Materials Licenses: ProgramSpecific Guidance About Portable 

Gauge Licenses,” in the event of 

an incident.

❒ ❒

10.3 RADIATION 

SAFETY 

PROGRAM—

MATERIAL 

RECEIPT AND 

ACCOUNTABILITY

Physical inventories will be 

conducted every 6 months or at 

other intervals approved by the 

NRC to account for all sealed 

sources and devices received and 

possessed under the license. 

AND

We will develop, implement, and 

maintain procedures for ensuring 

accountability of licensed materials 

at all times.

❒ ❒

10.4 RADIATION 

SAFETY 

PROGRAM—

OCCUPATIONAL 

DOSE

We will maintain, for inspection by 

the NRC, documentation 

demonstrating that unmonitored 

individuals are not likely to receive

a radiation dose in excess of the 

limits in 10 CFR 20.1502(a).

OR

We will provide and require the 

use of individual monitoring 

devices (dosimetry). All personnel 

dosimeters that require processing 

to determine the radiation dose will 

be processed and evaluated by a 

NVLAP-approved processor.

❒

❒

❒
B–5

Item No. and Title Suggested Response Yes Alternative 

Procedures 

Attached

10.5 RADIATION 

SAFETY 

PROGRAM—

PUBLIC DOSE

The applicant is not required to 

submit a response to the public 

dose section in a license 

application. This matter will be 

examined during NRC inspections.

Need Not Be Submitted with

Application

10.6 RADIATION 

SAFETY 

PROGRAM—

OPERATING,

EMERGENCY, AND 

SECURITY

PROCEDURES

We will implement and maintain 

the operating, emergency, and

security procedures in Appendix G

to NUREG–1556, Vol. 1, Rev. 2, 

”Consolidated Guidance About 

Materials Licenses: ProgramSpecific Guidance About Portable 

Gauge Licenses.” Copies of these 

procedures will be provided to all 

gauge users and will be available 

at each jobsite.

OR

Operating, emergency, and 

security procedures will be 

developed, implemented, and 

maintained and will meet the 

criteria in section 8.10.6, 

“Radiation Safety Program—

Operating, Emergency, and 

Security Procedures,” 

NUREG–1556, Vol. 1, Rev. 2,

“Consolidated Guidance About 

Materials Licenses: ProgramSpecific Guidance About Portable 

Gauge Licenses.” Copies of these 

procedures will be provided to all 

gauge users and will be available 

at each jobsite.

❒

❒

❒ For this 

item, 

checking 

this box 

indicates 

that 

alternative 

procedures 

will be 

provided as 

part of the 

application 

and that 

these 

procedures 

will be 

provided to 

all gauge 

users and 

will be 

available at 

each jobsite. 
B–6

Item No. and Title Suggested Response Yes Alternative 

Procedures 

Attached

10.7 RADIATION 

SAFETY 

PROGRAM—LEAK 

TEST

Leak tests will be performed at 

intervals approved by the NRC or 

an Agreement State and specified 

in the SSD registration certificate. 

Leak tests will be performed by an 

organization licensed by the NRC 

or an Agreement State to provide 

leak testing services to other 

licensees; or by using a leak test 

sample collection kit supplied by 

an organization licensed by the 

NRC or an Agreement State to 

provide leak test kits and/or 

sample analysis services to other 

licensees and according to the kit 

supplier’s instructions. Records of 

leak test results will be maintained.

OR

We will implement the model leak 

test program published in 

Appendix I of NUREG–1556, 

Volume 1, Revision 2, 

“Consolidated Guidance About 

Materials Licenses: ProgramSpecific Guidance About Portable 

Gauge Licenses.” Records of leak 

tests will be maintained.

❒

❒

❒ For this 

item, 

checking 

this box 

indicates 

that 

alternative

equipment 

and/or

procedures 

will be 

provided as 

part of the 

application 

and that 

records of 

leak tests 

will be 

maintained.
B–7

Item No. and Title Suggested Response Yes Alternative 

Procedures 

Attached

10.8 RADIATION 

SAFETY 

PROGRAM—

MAINTENANCE

Routine Cleaning and Lubrication

We will implement and maintain 

procedures for routine 

maintenance of our gauges 

according to each manufacturer’s 

written recommendations and 

instructions.

Nonroutine Maintenance

The gauge manufacturer or other 

person licensed by the NRC or an 

Agreement State will perform 

nonroutine maintenance or repair 

operations that require detaching 

the source or source rod from the 

gauge.

❒

❒

❒

❒ The 

information 

listed in 

Appendix F 

of this 

NUREG 

supporting a 

request to 

perform 

nonroutine 

maintenance 

in house is 

attached.

10.9 RADIATION 

SAFETY

PROGRAM—

TRANSPORTATION

The applicant is not required to 

submit a response about

transportation during the licensing 

process. The NRC will review this 

issue during inspection. 

Need Not Be Submitted with 

Application

11. WASTE 

MANAGEMENT—

GAUGE DISPOSAL 

AND TRANSFER

The applicant is not required to 

submit a response about waste 

management during the licensing 

process; however, the licensee 

should establish and include 

gauge transfer and waste disposal 

procedures in its radiation safety 

program.

Need Not Be Submitted with 

Application

APPENDIX C

CRITERIA FOR ACCEPTABLE TRAINING COURSES FOR

PORTABLE GAUGE USERS

C–1

Criteria for Acceptable Training Courses for 

Portable Gauge Users

Course Content

Acceptable course content for training courses for portable gauge users includes the following:

• 1.5 to 2 hours of radiation safety and regulatory requirements, emphasizing practical 

subjects important to safe use of the gauge; radiation versus contamination; internal 

versus external exposure; concepts of time, distance, and shielding to minimize 

exposure; control and surveillance of gauges; location of the sealed source within the 

portable gauge; inventory; recordkeeping; incidents; licensing and inspection by the 

regulatory agency; need for complete and accurate information; employee protection; 

and deliberate misconduct

• 1.5 to 2 hours of practical training, to include portable gauge theory, operating

procedures, emergency procedures, security, maintenance, and transportation 

procedures; and field training emphasizing radiation safety, including dry runs of setting 

up and making measurements with the gauge, controlling and maintaining surveillance 

over the portable gauge, performing routine cleaning and lubrication, packaging 

and transporting the gauge, storing the gauge, and following emergency and 

security procedures

Course Examination

Prospective gauge users participating in training courses should achieve at least a 70-percent 

score on a 25- to 50-question written test. The test should include the following:

• an emphasis on radiation safety of portable gauge storage, security of gauges while on 

jobsites, use, sealed source location, maintenance, and transportation, rather than the 

theory and art of making portable gauge measurements

• review of correct answers to missed questions with the prospective gauge user following 

the scoring of the test

Instructor Training and Experience

Instructors should have, at a minimum, the following:

• successful completion of a portable gauge user course

• successful completion of an 8-hour radiation safety course or radiation safety officertraining course

• documentation of 8 hours of hands-on experience with portable gauges
C–2

Notes: 

• Licensees must maintain records of training for 3 years following the last use of licensed 

material by the authorized user.

• Initial and recurrent (every 3 years) U.S. Department of Transportation hazardous 

material (HAZMAT) training is also required for all gauge users that transport gauges

(see Section 8.10.9, “Transportation”).

Online Courses

Online training for portable gauge users is acceptable. The online training topics should 

follow the suggested Course Content on the previous page. Any online training should be 

supplemented by the practical hands-on training also described under Course Content. The 

applicant/licensee should demonstrate how it will meet the training described under Course 

Content and may consider providing a copy of the curricula covered in the course.

Online training courses should also include an examination described under 

Course Examination.
APPENDIX D

TYPICAL DUTIES AND RESPONSIBILITIES OF THE 

RADIATION SAFETY OFFICER

D–1

Typical Duties and Responsibilities of the

Radiation Safety Officer

The radiation safety officer’s (RSO’s) duties and responsibilities (illustrated in Figure 8-1)

typically include ensuring the following:

• Licensed activities that the RSO considers unsafe are stopped.

• Possession, use, storage, and maintenance of sources and gauges are consistent with 

the limitations in the license, the Sealed Source and Device registration certificate(s), 

and the manufacturer’s recommendations and instructions.

• Individuals who use gauges are properly trained.

• Radiation exposures are kept as low as is reasonably achievable (ALARA).

• Prospective evaluations are performed to demonstrate that unmonitored individuals are 

not likely to receive a radiation dose in excess of the limits in 10 CFR 20.1502(a) or that 

personnel monitoring devices are provided.

• When necessary, personnel monitoring devices are used and exchanged at the proper 

intervals, and records of the results of such monitoring are maintained.

• Up-to-date operating, emergency, and security procedures are developed, implemented, 

maintained, and distributed.

• Safety consequences of nonroutine operations are analyzed before conducting any such 

activities that have not been previously analyzed.

• Nonroutine operations are performed by the manufacturer, distributor, or person 

specifically authorized by the U.S. Nuclear Regulatory Commission (NRC) or an 

Agreement State.

• Documentation is maintained to demonstrate, by measurement or calculation, that the 

total effective dose equivalent to the individual member of the public likely to receive the 

highest dose from the licensed operation does not exceed the annual limit in Title 10 of 

the Code of Federal Regulations (10 CFR) Part 20.1301, “Dose limits for individual 

members of the public.”

• Gauges are properly secured.

• Proper authorities are notified in case of accident, damage to, or malfunction of gauges, 

fire, loss, or theft.

• Unusual occurrences involving the gauge (e.g., malfunctions, accident, damage, theft) 

are investigated, cause(s) are determined, and appropriate corrective action(s) are 

identified, and corrective action taken.
D–2

• Audits are performed at least annually and documented, and corrective actions 

are taken.

• When the licensee identifies violation(s) of regulations or license conditions or program 

weaknesses, corrective action(s) are developed, implemented, and documented.

• Licensed material is transported in accordance with all applicable NRC and U.S. 

Department of Transportation requirements.

• Licensed material is disposed of properly.

• All required records are maintained.

• An up-to-date license is maintained, and amendment and renewal requests are 

submitted in a timely manner.

• Documents are posted as required by 10 CFR 19.11, “Posting of notices to workers,”

(10 CFR Part 19, license documents, operating procedures, NRC Form 3, “Notice to 

Employees,”), and 10 CFR 21.6, “Posting Requirements,” (10 CFR Part 21 Section 206 

of the Energy Reorganization Act of 1974, procedures adopted under Part 21), or a 

noted is posted indicating where these documents can be examined.
D–3

Model Delegation of Authority to Radiation Safety Officer

Memo To: Radiation Safety Officer

From: Chief Executive Officer

Subject: Delegation of Authority

You, _______________________________, have been appointed radiation safety officer and 

are responsible for ensuring the safe use of radiation. You are responsible for managing the 

Radiation Protection Program; identifying radiation protection problems; initiating, 

recommending, or providing corrective actions; verifying implementation of corrective actions;

stopping unsafe activities; and ensuring compliance with regulations. You are hereby delegated 

the authority necessary to meet those responsibilities, including prohibiting the use of byproduct 

material by employees who do not meet the necessary requirements and shutting down 

operations, when justified, to maintain radiation safety. You are required to notify management 

if staff does not cooperate and does not address radiation safety issues. In addition, you are 

free to raise issues with the U.S. Nuclear Regulatory Commission at any time. It is estimated 

that you will spend _____ hours per week conducting radiation protection activities.

____________________________________ ____________________

Signature of Management Representative Date

I accept the above responsibilities,

_____________________________________ ____________________

Signature of Radiation Safety Officer Date

cc: Affected department heads

APPENDIX E

PORTABLE GAUGE AUDIT CHECKLIST

E–1

Portable Gauge Audit Checklist

Note: All areas indicated in audit notes may not be applicable to every license and may not 

need to be addressed during each audit. For example, licensees do not need to address areas 

that do not apply to their activities, and activities that have not occurred since the last audit need 

not be reviewed during the next audit.

Licensee’s name ___________________________ License No. ___________________

Date of This Audit __________________________ Date of Last Audit ______________

Audit Date Range __________________________

___________________________ __________________________ __________

Auditor Signature Auditor Printed Name Date

___________________________ __________________________ __________

Management Signature Management Printed Name Date

1. AUDIT HISTORY

a. Were previous audits conducted periodically (at least annually)? (10 CFR 20.1101)

b. Were records of previous audits maintained? (10 CFR 20.2102)

c. Were any deficiencies identified during the last two audits or 2 years, whichever 

is longer?

d. Were corrective actions taken? (Look for repeated deficiencies)

2. ORGANIZATION AND SCOPE OF PROGRAM

a. If the mailing address or places of use and/or storage changed, was the license 

amended? [License Condition (L/C)]

b. If ownership changed or bankruptcy was filed, did the licensee obtain prior U.S. Nuclear 

Regulatory Commission (NRC) consent or notify the NRC? [10 CFR 30.34(b)]

c. If the licensee changed the radiation safety officer (RSO), was the license amended? 

(L/C)

d. Sealed Sources and Devices

1. Does the license authorize all of the NRC-regulated radionuclides contained in the 

gauges possessed? (L/C)

2. Are the gauges as described in the Sealed Source and Device (SSD) registration 

certificate? (L/C)

3. Are copies of (or access to) SSD registration certificates available?
E–2

4. Are manufacturer’s manuals for operation and maintenance available? 

(10 CFR 32.210)

5. Are the actual uses of gauges consistent with the authorized uses listed on the 

license? (L/C)

6. Are the locations of use of the gauges compatible with the “Conditions of Normal 

Use” and “Limitations and/or Other Considerations of Use” on the SSD registration 

certificates? (L/C)

e. Is the current inventory of material below the possession limits listed on the license? 

(L/C)

3. TRAINING AND INSTRUCTIONS TO WORKERS

a. Were all workers who are likely to exceed 1 mSv [100 mrem] in a year instructed per 

10 CFR 19.12? Was refresher training provided, as needed? Were records 

maintained?

b. Is each gauge operator trained in accordance with license requirements? (L/C)

c. Are training records maintained for each gauge operator?

d. Did interviews with operators reveal that they know the operating, emergency and 

security procedures?

e. Did this audit1 include observation of operators using the gauge in a field situation? 

Operating the gauge? Performing routine cleaning and lubrication? Transporting the 

gauge? Storing the gauge? Was the use of the gauge in accordance with regulations?

f. Did the operator demonstrate safe handling and security during transportation, use, 

and storage?

g. Was U.S. Department of Transportation (DOT) hazardous material (HAZMAT) training

(required at least once every 3 years) provided as required? (49 CFR 172.700, 49 CFR 

172.701, 49 CFR 172.702, 49 CFR 172.704) 

4. RADIATION SURVEY INSTRUMENTS

a. If the licensee possesses its own survey meter, does the survey meter meet 

NRC requirements? [10 CFR 20.1501(c)]

b. Are calibration records maintained, if applicable? [10 CFR 20.2103(a)]

c. If the licensee does not possess a survey meter, are specific plans made to have one 

available in the event of an emergency?

 1The auditor should consider performing a performance-based review consisting of field observations and tours.
E–3

5. GAUGE INVENTORY

a. Is a record kept showing the receipt of each gauge? [10 CFR 30.51(a)(1)]

b. Are all gauges physically inventoried every 6 months or at other intervals approved by 

the NRC? (L/C)

c. Are records of inventory with appropriate information maintained? (L/C)

6. PERSONNEL RADIATION PROTECTION

a. Are considerations for keeping doses as low as is reasonably achievable (ALARA)

incorporated into the radiation protection program? [10 CFR 20.1101(b)]

b. Were prospective evaluations performed showing that unmonitored individuals receive 

less than the limits in 10 CFR 20.1502(a)? Did these evaluations consider doses to 

minors [10 CFR 20.1502(a)(2)] and declared pregnant women [10 CFR 20.1502(a)(3)]?

c. Did unmonitored individuals’ activities change during the year in a way that could put 

them over the limits in 10 CFR 20.1502(a)? If yes, was a new evaluation performed?

d. If external dosimetry is required [i.e., when individuals are likely to receive greater than 

the limits in 10 CFR 20.1502(a)], is dosimetry provided to these individuals? If yes, 

address the following:

1. Is the dosimetry supplier approved by the National Voluntary Laboratory 

Accreditation Program? [10 CFR 20.1501(c)]

2. Are the dosimeters exchanged at the appropriate frequency?

3. Are dosimetry reports reviewed and signed by the RSO when they are received?

4. Are the records based on NRC forms or the equivalent? [10 CFR 20.2104(d), 

10 CFR 20.2106(c)]

• Is NRC Form 4, “Cumulative Occupational Exposure History,” completed?

• Is NRC Form 5, “Occupational Dose Record for a Monitoring Period,” completed?

e. Are there any declared pregnant workers?

1. If a worker declared her pregnancy, did the licensee comply with 10 CFR 20.1208, 

“Dose equivalent to an embryo/fetus”? 

2. Were records kept of embryo/fetus dose per 10 CFR 20.2106(e)?

f. Are records of exposures, surveys, monitoring, and evaluations maintained? 

(10 CFR 20.2102, 10 CFR 20.2103, 10 CFR 20.2106)
E–4

7. PUBLIC DOSE

a. Are gauges stored in a manner to keep doses to members of the public below 

1 millisievert (mSv) (100 mrem) in a year? [10 CFR 20.1301(a)(1)]

b. Has a survey or evaluation been performed per 10 CFR 20.1501(a)? Have there been 

any additions or changes to the storage, security, or use of the surrounding areas that 

would necessitate a new survey or evaluation?

c. Do unrestricted area radiation levels exceed 0.02 mSv (2 mrem) in any one hour? 

[10 CFR 20.1301(a)(2)]

d. Are gauges being stored in a manner that would prevent unauthorized use or removal? 

(10 CFR 20.1801)

e. Are records of surveys maintained? (10 CFR 20.2103, 10 CFR 20.2107)

8. OPERATING, EMERGENCY, AND SECURITY PROCEDURES

Note: An ideal way to assess the adequacy and adherence to operating procedures is by 

observing work in progress.

a. Have operating, emergency, and security procedures been developed and updated to 

incorporate any new elements, practices, or requirements?

b. Does each operator have current copies of the operating, emergency, and security

procedures, including current emergency telephone numbers?

c. Did any emergencies occur?

1. If so, were they handled properly?

2. Were appropriate corrective actions taken?

d. Were gauges properly controlled or secured during use or storage? 

(10 CFR 20.1801, 10 CFR 20.1802) Are the gauges in storage being secured with two 

independent physical controls? [10 CFR 30.34(i)]

9. LEAK TESTS

a. Were sealed source leak tests performed every 6 months or at other authorized

intervals? (L/C)

b. Were leak tests performed in accordance with license requirements? (L/C)

c. Are records of leak test results retained with all of the required information

 included? (L/C)

d. Were any sources found to be leaking, and if yes, was the NRC notified? (L/C)
E–5

10. MAINTENANCE OF GAUGES

a. Are manufacturer’s procedures followed for routine cleaning and lubrication of 

the gauge?

b. Does the source rod remain attached to the gauge during cleaning? (L/C)

c. Is nonroutine maintenance performed where the source or source rod is detached from 

the gauge? If yes, was it performed according to license requirements (e.g., extent of 

work, individuals performing the work, procedures, dosimetry, survey instrument, 

compliance with limits under 10 CFR 20.1301, “Dose limits for individual members of 

the public”)?

d. Are labels, signs, and postings identifying gauges containing radioactive material,

radiation areas and warnings clean and legible?

11. TRANSPORTATION

a. Were U.S. Department of Transportation (DOT)-7A or other authorized packages used? 

[49 CFR 173.415, 49 CFR 173.416(b)]

b. Are Type A package, engineering drawings, and performance test records on file?

[49 CFR 171.2 (a, b, e), 49 CFR 173.415(a)]

c. For any special form source, is the International Atomic Energy Agency Certificate of 

Competent Authority or other safety analysis documentation maintained on file? 

[49 CFR 173.476(a)]

d. Were packages properly labeled? (49 CFR 172.400, 49 CFR 172.403, 49 CFR 172.406, 

49 CFR 172.407)

e. Were packages properly marked? (49 CFR 172.301, 49 CFR 172.304, 

49 CFR 172.310, 49 CFR 172.324)

f. Were packages closed and sealed (e.g., locked) during transport? [49 CFR 173.475(f)]

g. Were shipping papers prepared and used? [49 CFR 172.200(a)]

h. Did the shipping papers contain proper entries {e.g., proper shipping name, hazard 

class, identification number [United Nations (UN)] number, total quantity, package type, 

nuclide, reportable quantity (RQ)(if applicable), physical and chemical form, activity

(International System of Units required), category of label, Transportation Index (TI), 

shipper’s name, certification and signature, emergency response phone number, and 

cargo aircraft only (if applicable)}? (49 CFR 172.200, 49 CFR 172.201, 

49 CFR 172.202, 49 CFR 172.203, 49 CFR 172.204, 49 CFR 172.604)

i. Were the shipping papers within the driver’s reach and readily accessible during 

transport? [49 CFR 177. 817(e)]

j. Were packages secured against movement? (49 CFR 177.834)
E–6

k. Were placards on the vehicle, if needed? (49 CFR 172.504)

l. Were overpacks, if needed, used properly? (49 CFR 173.25)

m. Were any incidents reported to the DOT? (49 CFR 171.15, 49 CFR 171.16)

12. AUDITOR’S INDEPENDENT SURVEY MEASUREMENTS (IF MADE)

Describe the type, location, and results of the measurements. Does any radiation level

exceed regulatory limits? [10 CFR 20.1501(a), 10 CFR 20.1502(a)]

13. NOTIFICATION AND REPORTS

a. Did any reportable incidents occur? Were the appropriate notifications made to the NRC 

Emergency Operations Center (301-816-5100)? Examples of incidents with notification 

requirements are as follows:

1. Lost or stolen radioactive material (10 CFR 20.2201)

2. Overexposures or high radiation levels (10 CFR 20.2202)

3. Gauge is disabled or fails to function as designed [10 CFR 30.50(b)(2)]

4. Generic equipment issues identified by the licensee (10 CFR 21.21)

b. Were the required written reports made as followups to the events?

14. POSTING AND LABELING

a. Is NRC Form 3, “Notice to Employees,” posted? (10 CFR 19.11)

b. Are NRC regulations and license documents posted, or is a notice posted stating where 

these documents are located? (10 CFR 19.11, 10 CFR 21.6)

c. Are any other posting and labeling requirements met? (10 CFR 20.1902, 

 10 CFR 20.1904)

15. DECOMMISSIONING

a. Were any locations of use or separate buildings decommissioned since the last audit? 

Were appropriate notifications made or license amendments requested? 

(10 CFR 30.36)

b. Are records kept of information important to decommissioning? [10 CFR 30.35(g)]

c. Do records include all information outlined in 10 CFR 30.35(g)?
E–7

16. GENERIC COMMUNICATIONS AND NEWSLETTER

a. Are NRC Regulatory Issue Summaries, NRC Information Notices, and Office of Nuclear 

Material Safety and Safeguards quarterly newsletters received?

b. Is appropriate training and action taken in response to these?

17. SPECIAL LICENSE CONDITIONS OR ISSUES

Did the auditor review special license conditions or other issues (e.g., nonroutine

maintenance)? (L/C)

18. EVALUATION OF OTHER FACTORS

a. Is senior licensee management appropriately involved with the radiation protection 

program and/or RSO oversight?

b. Does the RSO have sufficient time to perform his or her radiation safety duties?

c. Does the licensee have sufficient staff to support the radiation protection program?

19. DEFICIENCIES IDENTIFIED IN AUDIT AND CORRECTIVE ACTIONS

a. Summarize problems and/or deficiencies identified during the audit.

b. If problems and/or deficiencies were identified in this audit, describe the corrective 

actions planned or taken. Are corrective actions planned or taken at all licensed

locations (not just the location audited)? Include date(s) when corrective actions are 

implemented.

c. Provide any other recommendations for improvement.

d. Describe communication with management about deficiencies.

APPENDIX F

INFORMATION NEEDED TO SUPPORT APPLICANT’S REQUEST TO 

PERFORM NONROUTINE MAINTENANCE

F–1

Information Needed To Support Applicant’s Request To 

Perform Nonroutine Maintenance

Nonroutine maintenance or repair (beyond routine cleaning and lubrication—see Figure 8-6 of 

NUREG–1556, Volume 1, Revision 2) may involve detaching the source rod from the portable 

gauge and other activities that could result in higher radiation doses. If this maintenance or 

repair is not performed properly, with attention to good radiation safety principles, the gauge 

may not operate as designed, and personnel performing these tasks could receive radiation 

doses exceeding U.S. Nuclear Regulatory Commission (NRC) limits.

In a short period of time (5–10 minutes), a typical moisture density gauge with its sources

unshielded can deliver 0.05 sievert (Sv) [5 rem] to a worker’s hands or fingers (i.e., extremities), 

assuming the extremities are 1 centimeter from the sources. The threshold for extremity 

monitoring is 0.05 Sv [5 rem] per year.

Thus, applicants wishing to perform nonroutine maintenance must use personnel with 

specialized training and follow appropriate procedures consistent with the manufacturer’s 

instructions and recommendations that address radiation safety concerns (e.g., use of radiation 

survey meter, shielded container for the source, personnel dosimetry). Accordingly, applicants 

should provide the following information:

• Describe the types of work (e.g., maintenance, cleaning, repair) to be performed that 

necessitate detaching the source or source rod from the device or that could cause 

personnel to receive radiation doses exceeding NRC limits. The principal reason for 

obtaining this information is to help evaluate the qualifications of individuals who will 

conduct the work and the radiation safety procedures they will follow.

• Identify who will perform nonroutine maintenance, and provide their training and 

experience in performing nonroutine maintenance. Provide the training and experience 

for the radiation safety officer who will oversee the performance of nonroutine 

maintenance.

• Provide procedures for safe handling of the radioactive source while the source or

source rod is detached from the gauge. These procedures should ensure the following:

— Doses to personnel and members of the public are within regulatory limits and as

low as is reasonably achievable (e.g., accomplished by the use of shielded

containers or shielding).

— The source or source rod is secured against unauthorized removal access or is 

under constant surveillance.

— Appropriate labels and signs are used.

— Manufacturer’s instructions and recommendations are followed.
F–2

• Confirm that individuals performing nonroutine maintenance on gauges will always wear 

both whole body and extremity-monitoring devices. The dose limits are illustrated in 

Figure 8-3 of NUREG–1556, Volume 1, Revision 2.

• Verify possession of at least one survey instrument meeting the following criteria:

— capable of detecting gamma radiation

— capable of measuring from 0.01 to 0.5 millisievert per hour

[1 to 50 millirem per hour]

— calibrated at least annually

— calibrated by a person specifically licensed by the NRC or an Agreement State to 

calibrate radiation detection instruments

— checked for functionality prior to use (e.g., with the gauge or a check source)

Note: Records of instrument calibration must be maintained for 3 years after the record is 

made in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 20.2103, 

“Records of surveys.”

• Describe steps to be taken to ensure that radiation levels in areas where nonroutine

maintenance will take place do not exceed the limits under 10 CFR 20.1301, “Dose 

Limits for individual members of the public.” For example, applicants can do 

the following:

— Commit to performing surveys with a survey instrument (as described above).

— Specify where and when surveys will be conducted during 

nonroutine maintenance.

— Commit to maintaining records of the survey (e.g., who performed the survey, 

survey date, instrument used, measured radiation levels correlated to location of 

those measurements) for 3 years after the record is made, as required by 

10 CFR 20.2103.
APPENDIX G

OPERATING, EMERGENCY, AND SECURITY PROCEDURES

G–1

Operating, Emergency, and Security Procedures

Operating Procedures

• If personnel dosimetry is provided, do the following:

— Always wear the assigned dosimetry when using the gauge.

— Never wear another person’s dosimetry.

— Never store dosimetry near the gauge.

• Before removing the gauge from its place of storage, ensure that, where applicable,

each gauge source is in the fully shielded position and that, in gauges with a movable 

rod containing a sealed source, the source rod is locked (e.g., keyed lock, padlock, 

mechanical control) in the shielded position. Place the gauge in the transport case and 

lock the case.

• Sign out the gauge in a log book (that remains at the storage location), including the 

date(s) of use, name(s) of the authorized users who will be responsible for the gauge, 

and the temporary jobsite(s) where the gauge will be used.

• Block and brace the gauge to prevent movement during transport, and lock the gauge 

in or to the vehicle. Follow all applicable U.S. Department of Transportation (DOT)

requirements when transporting the gauge.

• Use the gauge according to the manufacturer’s instructions and recommendations.

• Do not touch the unshielded source rod with your fingers, hands, or any part of 

your body.

• Do not place hands, fingers, feet, or other body parts in the radiation field from an 

unshielded source.

• Unless absolutely necessary, do not look under the gauge when the source rod is being 

lowered into the ground. If you must look under the gauge to align the source rod with 

the hole, follow the manufacturer’s procedures to minimize radiation exposure.

• After completing each measurement in which the source is unshielded, immediately 

return the source to the shielded position.

• Always maintain constant surveillance and immediate control of the gauge when it is 

not in storage. At jobsites, do not walk away from the gauge when it is left on the 

ground. Take action necessary to protect the gauge and yourself from danger of 

moving heavy equipment.

• Always keep unauthorized persons away from the gauge.

• Perform routine cleaning and maintenance according to the manufacturer’s instructions 

and recommendations.

• When the gauge is not in use at a temporary jobsite, place the gauge in a secured 

storage location.
G–2

• Before transporting the gauge, ensure that, where applicable, each gauge source is in 

the fully shielded position. Ensure that, in gauges with a movable source rod, the source 

rod is locked in the shielded position (e.g., keyed lock, padlock, mechanical control). 

Place the gauge in the transport case and lock the case. Block, brace, and lock the 

case to prevent movement during transportation. 

• Return the gauge to its proper locked storage location at the end of the work shift.

• Log the gauge into the daily use log when it is returned to storage.

• If gauges are used for measurements with the unshielded source extended more than

3 feet beneath the surface, use piping, tubing, or other casing material to line the hole 

from the lowest depth to 12 inches above the surface. If the piping, tubing, or other 

casing material cannot extend 12 inches above the surface, cap the hole liner or take 

other steps to ensure that the hole is free of debris (and it is unlikely that debris will 

reenter the cased hole) so that the unshielded source can move freely (e.g., use a 

dummy probe to verify that the hole is free of obstructions).

• After making changes affecting the gauge storage area (e.g., changing the location of 

gauges within the storage area, removing shielding, adding gauges, changing the 

occupancy of adjacent areas, moving the storage area to a new location), reevaluate 

compliance with public dose limits and ensure proper security of the gauges.

Emergency Procedures

If the source fails to return to the shielded position (e.g., the source becomes stuck below the 

surface as a result of being damaged), or if any other emergency or unusual situation arises 

such that it causes damage or compromises the gauge structure (e.g., the gauge is struck by a 

moving vehicle, is dropped, or is in a vehicle involved in an accident), do the following:

• Immediately secure the area and keep people at least 15 feet away from the gauge until 

the situation is assessed and radiation levels are known. However, perform first aid for 

any injured individuals and remove them from the area only when medically safe to 

do so.

• If any heavy equipment is involved, detain the equipment and operator until it is 

determined that there is no contamination present.

• Gauge users and other potentially contaminated individuals should not leave the scene 

until emergency assistance arrives. 

• Notify the following persons, in the order listed below, of the situation:
G–3

NAME1 WORK PHONE NUMBER ALTERNATE PHONE NUMBER

_______________ ____________________ ____________________

_______________ ____________________ ____________________

_______________ ____________________ ____________________

Follow the directions provided by the person contacted above.

Radiation Safety Officer and Licensee Management

• Arrange for a radiation survey to be conducted as soon as possible by a knowledgeable 

person using appropriate radiation detection instrumentation. This person could be a 

licensee employee using a survey meter located at the jobsite or a consultant. To 

accurately assess the radiation danger, it is essential that the person performing the 

survey be competent in the use of the survey meter.

• If gauges are used for measurements with the unshielded source extended more than 

3 feet below the surface, contact persons listed on the emergency procedures need to

know the steps to be followed to retrieve a stuck source and to convey those steps to the 

staff onsite.

• Make necessary notifications to local authorities, as well as to the U.S. Nuclear 

Regulatory Commission (NRC) as required. (Even if it is not required, any incident

may be reported to the NRC by calling the NRC’s Emergency Operations Center at 301-

816-5100, which is staffed 24 hours a day and accepts collect calls.) NRC notification is 

required when gauges containing licensed material are lost or stolen, when gauges are 

damaged or involved in incidents that result in doses in excess of Title 10 of the Code of 

Federal Regulations (10 CFR) Part 20.2203, “Reports of exposures, radiation levels, and 

concentrations of radioactive material exceeding the constraints or limits,” and when it 

becomes apparent that attempts to recover a source stuck below the surface will be 

unsuccessful.

• Reports to the NRC must be made within the reporting timeframes specified by 

the regulations.

Reporting requirements are found in 10 CFR 20.2201–2203 and 10 CFR 30.50 and are listed in 

Table G–1.

Note: The list of notification and reporting requirements in Table G–1 is provided to inform 

licensees about typical notification and reporting requirements that apply to their licensed 

activities. Licensees should note that the list is incomplete in that not all potentially applicable 

requirements have been included. Also, notification and reporting requirements change; 

therefore, licensees should consult the regulations for definitive information about current 

requirements.

 1

Fill in with (and update, as needed) the names and telephone numbers of appropriate personnel (e.g., the radiation 

safety officer or other knowledgeable licensee staff, licensee’s consultant, gauge manufacturer) to be contacted in 

case of emergency.
G–4

Table G–1. Typical NRC Notification and Reporting Requirements for Incidents

Event

Telephone 

Notification

Written 

Report Regulatory Requirement

Theft or loss of licensed material Immediate 30 days 10 CFR 20.2201(a)(1)(i)

10 CFR 20.2201(b)(1)

Whole body dose greater than 0.25 

Sv (25 rems)

Immediate 30 days 10 CFR 20.2202(a)(1)(i)

10 CFR 20.2203(a)(1)

Extremity dose greater than 2.5 Gy 

(250 rads)

Immediate 30 days 10 CFR 20.2202(a)(1)(iii)

10 CFR 20.2203(a)(1)

Whole body dose greater than 

0.05 Sv (5 rems) in 24 hours

24 hours 30 days 10 CFR 20.2202(b)(1)(i)

10 CFR 20.2203(a)(1)

Extremity dose greater than 0.5 Sv 

(50 rems) in 24 hours

24 hours 30 days 10 CFR 20.2202(b)(1)(iii)

10 CFR 20.2203(a)(1)

Whole body dose greater than 

0.05 Sv (5 rems)

None 30 days 10 CFR 20.2203(a)(2)(i)

Dose to individual member of public 

greater than 1 mSv (0.1 rem)

None 30 days 10 CFR 20.2203(a)(2)(iv)

Defect in equipment that could create 

a substantial safety hazard

2 days 30 days 10 CFR 21.21(d)(3)(i) & (ii)

Event that prevents immediate 

protective actions necessary to avoid 

exposures to radiation or radioactive 

materials that could exceed 

regulatory limits

Immediate 30 days 10 CFR 30.50(a) & (c)(2)

Equipment is disabled or fails to 

function as designed when required 

to prevent radiation exposure in 

excess of regulatory limits 

24 hours 30 days 10 CFR 30.50(b)(2) & 

(c)(2)

Unplanned fire or explosion that 

affects the integrity of any licensed 

material or device, container, or 

equipment with licensed material

24 hours 30 days 10 CFR 30.50(b)(4) & 

(c)(2)

Note: Telephone notifications must be made to the NRC Operations Center at 301-816-5100. 

Security Procedures

At all times the gauge must either be:

• under the control and constant surveillance of a gauge user;

OR

• secured with a minimum of two independent physical controls that form tangible barriers 

to secure gauges from unauthorized removal. This requirement must be met at all times 

when in storage, including storage at permanent storage locations, temporary jobsites, 
G–5

and when stored in the vehicle (e.g., when in a convenience store, restaurant, or 

restroom while the gauge is in the vehicle).

The following section describes methods that can be used to meet the security requirements.

Methods to Meet the Security Requirements

Different licensees have developed various methods of complying with 10 CFR 30.34(i) 

requirements. The following information provides guidance to assist the licensee in developing 

security procedures.

NRC regulations require a portable gauge licensee to use a minimum of two independent 

physical controls that form tangible barriers to secure portable gauges from unauthorized 

removal whenever the portable gauge is not under the control and constant surveillance of the 

licensee. See 10 CFR 30.34(i).

Note: “Control and maintain constant surveillance” of portable gauges means being 

immediately present or in close proximity to the portable gauge so as to be able to prevent 

unauthorized removal of the portable gauge. The objective of security requirements is 

to reduce the opportunity for unauthorized removal and/or theft by providing a delay and 

deterrent mechanism. 

The security requirements of 10 CFR 30.34(i) apply whenever gauges are not under control and 

constant surveillance, including (1) storage in vehicles, (2) storage at temporary facilities

(e.g., residence, jobsite trailer), and (3) storage at permanent facilities. At all times, licensees 

are required to maintain control and constant surveillance of the portable gauge when it is in use 

and, at a minimum, use two independent physical controls to secure the portable gauge from 

unauthorized removal while it is in storage. The physical controls used should be designed and 

constructed of materials suitable for securing the portable gauge from unauthorized removal, 

and both physical controls must be defeated in order for the portable gauge to be removed. The 

construction and design of the physical controls should be such that they will deter theft by 

requiring a more determined effort to remove the portable gauge. The security procedures 

should ensure that the two physical controls chosen increase the deterrence value over that of a 

single physical control, and that the two physical controls would make unauthorized removal of 

the portable gauge more difficult.

To provide adequate security, licensees are encouraged to use combinations of physical 

controls. 10 CFR 30.34(i) requires that each portable gauge licensee shall use a minimum of 

two independent physical controls. For example, if two chains are used, each chain and lock 

combination should be physically robust enough to provide both a deterrent and a reasonable 

delay mechanism. When two chains or cables are used, the second chain or cable should be 

substantially more robust and more difficult to cut than the first chain or cable.

If possible, the licensee should consider storing its portable gauges inside a locked facility or 

other nonportable structure overnight, instead of storing them in a vehicle.

As long as the licensee maintains constant control and surveillance while transporting the 

portable gauges, the licensee need only comply with the DOT requirements for transportation 

(e.g., placarding, labeling, shipping papers, blocking and bracing). However, if the licensee 
G–6

leaves the vehicle and portable gauge unattended (e.g., while visiting a gas station, restaurant, 

store), the portable gauge must be secured by two independent controls, as required by

10 CFR 30.34(i).

While transporting a portable gauge, a licensee should not modify the transportation case if it is 

being used as the Type A container for transporting the device. This includes, but is not limited 

to, drilling holes to mount the case to the vehicle or to mount brackets or other devices used for 

securing the case to the vehicle. In the event the package is modified, the modified package 

must be reevaluated by any of the methods described in 49 CFR 178.350, “Specification 7A; 

General Packaging, Type A,” or 49 CFR 173.461(a). The reevaluation must be documented 

and maintained on file in accordance with DOT regulations.

Physical controls may include, but are not limited to, a metal chain with a lock, a steel cable with 

a lock, a secured enclosure, a locked tool box, a locked camper, a locked trailer, a locked trunk 

of a car, inside a locked vehicle, a locked shelter, a secured fenced-in area, a locked garage, a 

locked nonportable cabinet, a locked room, or a secured building. To assist licensees, the list 

below provides some common examples of the use of two independent physical controls.

Securing a Portable Gauge at a Licensed Facility

Long-term storage of a portable gauge is usually at a permanent facility listed in the license or 

license application. Routine storage of a portable gauge in a vehicle or at temporary or 

permanent residential quarters is usually reviewed by the NRC and may be authorized during 

the licensing process. In accordance with NRC security regulations, when a portable gauge is 

stored at a licensed facility, the licensee would be specifically required to use a minimum of two 

independent physical controls to secure the gauge.

The following are examples of how two independent physical controls can be used to 

secure a portable gauge when it is stored at a licensed facility:

(1) The portable gauge or transportation case containing the portable gauge is stored inside 

a locked storage shed within a secured outdoor area, such as a fenced parking area with 

a locked gate.

(2) The portable gauge or transportation case containing the portable gauge is stored in a 

room with a locked door within a secured building, access to which the licensee controls

by lock and key or by a security guard.

(3) The portable gauge or transportation case containing the portable gauge is stored

inside a locked, nonportable cabinet inside a room with a locked door, if the building 

is not secured.

(4) The portable gauge or transportation case containing the portable gauge is stored in

a separate secured area inside a secured mini-warehouse or storage facility.

(5) The portable gauge or transportation case containing the portable gauge is physically 

secured to the inside structure of a secured mini-warehouse or storage facility.
G–7

Securing a Portable Gauge in a Vehicle

The regulations in 10 CFR 71.5, “Transportation of Licensed Material,” require that licensees 

who transport licensed material, or who may offer such material to a carrier for transport, must 

comply with the applicable DOT requirements that are found in 49 CFR. 

Licensees commonly use a chain and a padlock to secure a portable gauge in its transportation 

case to the open bed of a pickup truck while using the vehicle for storage. This is not 

considered to be adequate security because there is only one physical control. The 

transportation case is portable and a theft could occur if the chain is cut and the transportation 

case with the portable gauge is taken. Similarly, if a licensee simply loops the chain through the 

handles of the transportation case, a thief could open the transportation case and take the 

portable gauge without removing the chain or the case. Because the transportation case is also 

portable, it must be protected by two independent physical controls if the portable gauge is 

inside. A lock on the transportation case, or a lock on the portable gauge source rod handle, is 

not sufficient because both the case and the gauge are portable.

A vehicle may be used for storage; however, the NRC and DOT recommend that this practice 

only be used for short periods of time or when a portable gauge is in transit. A portable gauge 

should only be kept in a vehicle overnight if it is not practicable to provide temporary storage in 

a permanent structure. When a portable gauge is being stored in a vehicle, the licensee is 

specifically required to use a minimum of two independent physical controls to secure the 

portable gauge.

The following are examples of how two independent physical controls, approved by the 

NRC, can be used to secure portable gauges in a vehicle:

(1) The locked transportation case containing the portable gauge is physically secured to a 

vehicle with brackets, and two chains (attached to the vehicle) are wrapped around the

transportation case such that the case cannot be opened unless the chains are

removed. See Figure G–1.

(2) The portable gauge or transportation case containing the portable gauge is stored in a 

locked trunk, camper shell, van, or other similar enclosure and is physically secured to 

the vehicle by a chain in such a manner that one would not be able to open the case 

or remove the portable gauge without removal of the chain or cable. After the 

transportation case is properly secured, additional blocking and bracing will have to 

be added. See Figure G–2.
G–8

Figure G–1. 10 CFR 30.34(i) Example 1

Figure G–2. 10 CFR 30.34(i) Example 2
G–9

Note: The drawings in Figures G–1 and G–2 are only two examples of securing portable 

gauges. There are other ways that licensees may choose to secure their portable gauges.

Securing a Portable Gauge at a Temporary Jobsite or at Locations Other Than a

Licensed Facility

When a job requires storage of a portable gauge at a temporary jobsite or at a location other 

than a licensed facility, the licensee should use a permanent structure for storage, if practicable 

to do so. When storing a portable gauge in temporary or permanent residential quarters, the 

licensee should limit access by storing the gauge in a separate room away from residents and 

other members of the public. The licensee must also meet the radiation exposure limits 

specified in 10 CFR Part 20, “Standards for Protection against Radiation.” When a portable 

gauge is stored at a temporary jobsite or at a location other than an authorized facility, the 

licensee is required to use a minimum of two independent physical controls to secure the 

portable gauge.

The following are examples of how two independent physical controls are used to secure 

portable gauges at these locations:

(1) At a temporary jobsite, the portable gauge or transportation case containing the portable 

gauge is stored inside a locked building or in a locked nonportable structure

(e.g., construction trailer, intermodal container) and is physically secured by a chain or

steel cable to a nonportable structure in such a manner that an individual would not be

able to open the transportation case or remove the portable gauge without removing the

chain or cable. A lock on the transportation case or a lock on the portable gauge 

source rod handle would not be sufficient, because the case and the portable gauge 

are portable.

(2) The portable gauge or transportation case containing the portable gauge is stored inside 

a locked room within temporary or permanent residential quarters and is physically 

secured by a chain or steel cable to a permanent or nonportable structure (e.g., large 

metal drain pipe, support column) such that an individual would not be able to open the 

transportation case or remove the portable gauge without removing the chain or cable.

(3) The portable gauge or transportation case containing the portable gauge is stored in a 

locked garage and is within a locked vehicle or is physically secured by a chain or steel 

cable to the vehicle in such a manner that an individual would not be able to open the 

transportation case or remove the portable gauge without removing the chain or cable.

(4) The portable gauge or transportation case containing the portable gauge is stored in a 

locked garage and is within a locked enclosure or is physically secured by a chain or

steel cable to a permanent or nonportable structure in such a manner that an individual

would not be able to open the transportation case or remove the portable gauge without

removing the chain or cable.

APPENDIX H

DOSIMETRY-RELATED GUIDANCE

H–1

Dosimetry-Related Guidance

Part 1: Guidance for Demonstrating That Unmonitored Workers Are Not Likely To

Exceed the Limits in 10 CFR 20.1502(a)

Dosimetry is required for individuals likely to receive, from sources external to the body, a dose 

in excess of the limits in Title 10 of the Code of Federal Regulations (10 CFR) Part 20.1502(a). 

Therefore, a licensee should evaluate the doses its workers receive in performing their duties to 

assess whether dosimetry is required.

Example

The most common way that individuals might exceed the limits in 10 CFR 20.1502(a) is by 

performing frequent routine cleaning and lubrication of gauges. Therefore, a licensee should

evaluate the doses its workers receive in performing these tasks to assess whether dosimetry is 

required. Gauge manufacturers can provide estimated doses to the extremities and whole body 

of a person performing routine cleaning and lubrication of one of their series of gauges. The 

manufacturer based its estimate on observations of individuals performing the recommended 

procedure according to good radiation safety practices. The manufacturer used the following 

types of information:

• time needed to perform the entire procedure (e.g., 10 minutes)

• expected dose rate received by the whole body of the individual, associated with the 

shielded source and determined using measured or manufacturer-determined data 

{e.g., 0.2 millisievert/hour (mSv/h) [20 millirem/hour (mrem/h)] at contact with the shield}

• time the hands were exposed to the unshielded source (e.g., 3 minutes)

• expected dose rate received by the extremities of the individual, associated with the 

unshielded source and determined using measured or manufacturer-determined data for 

the typical distance that the hands would be from the sealed source {e.g., 9 mSv/h 

[900 mrem/h] or 0.15 mSv/minute [15 mrem/minute]}

From this information, the manufacturer estimated that the individual performing each routine 

cleaning and lubrication could receive the following:

• less than 0.04 mSv [4 mrem] total effective dose equivalent (TEDE) (whole body)

• 0.45 mSv [45 mrem] to the hands

For adult radiation workers, the applicable limit TEDE (whole body) is 50 mSv [5 rem] per year,

and the corresponding limit in 10 CFR 20.1502(a) (i.e., 10 percent of that value) is 5 mSv [500 

mrem] per year. If one cleaning and lubrication delivers 0.04 mSv [4 mrem], then an adult 

radiation worker could perform 125 of these operations each year and remain within 10 percent 

of the applicable limit.

The applicable whole body dose limit for minors is 10 percent of the annual dose limits specified 

for adult workers {i.e., 5 mSv [500 mrem] per year}, with individual monitoring devices required 

when it is likely that a minor will receive a deep dose equivalent in excess of 1 mSv [100 mrem]. 
H–2

If one of these procedures delivers 0.04 mSv [4 mrem], then a minor could perform 25 such 

procedures each year without exceeding the individual monitoring device threshold. 

For declared pregnant women, individual monitoring devices are required when these 

individuals are likely to receive during the entire pregnancy, from radiation sources external to 

the body, a deep dose equivalent in excess of 1 mSv [0.1 rem]. If one of these procedures 

delivers 0.04 mSv [4 mrem], then a declared pregnant woman could perform 25 of these 

procedures during her entire pregnancy without exceeding the individual monitoring 

device threshold.

For adult radiation workers, the applicable limit for the extremities is 500 mSv [50 rem] per year,

and the corresponding limit in 10 CFR 20.1502(a) (i.e., 10 percent of that value) is 50 mSv 

[5 rem or 5,000 mrem] per year. If one cleaning and lubrication delivers 0.45 mSv [45 mrem], 

then an adult radiation worker could perform 111 of these operations each year and remain 

within 10 percent of the applicable limit.

The applicable extremity dose limit for minors is 10 percent of the annual dose limits specified 

for adult workers {i.e., 50 mSv [5 rem] per year}, with individual monitoring devices required 

when it is likely that a minor will receive a dose to the extremities in excess of 5 mSv [0.5 rem]. 

If one of these procedures delivers 0.45 mSv [45 mrem], then a minor could perform 11 of these 

procedures each year and remain within 10 percent of the applicable limit.

Declared pregnant women have no requirements concerning dose to the extremities or the 

monitoring thereof. 

Based on this example, no dosimetry is required if an adult radiation worker performs fewer than 

111 procedures per year; minors perform fewer than 11 procedures per year; or declared 

pregnant women perform fewer than 25 procedures during the entire pregnancy.

Guidance to Licensees

Licensees who wish to demonstrate that they are not required to provide dosimetry to their 

workers must prepare a written evaluation similar to that shown in the example above. The 

expected dose rates, times, and distances used in the above example may not be appropriate 

to individual licensee situations. In their evaluations, licensees must use information 

appropriate to the various types of gauges on which they will perform routine cleaning and 

lubrication; this information generally is available from gauge manufacturers or the Sealed 

Sources and Device (SSD) registration certificate maintained by the U.S. Nuclear Regulatory 

Commission (NRC) and Agreement States.

Table H–1 may be helpful in documenting a licensee’s evaluation.

Licensees should review evaluations periodically and revise them as needed. They should 

check assumptions used in their evaluations to ensure that the assumptions are up-to-date and 

accurate. For example, if workers became lax in following good radiation safety practices in the

example used above, the extremities could be closer to the unshielded source, and the workers 

would receive more than 0.15 mSv [15 mrem] per minute. Alternatively, workers could perform 

the task more slowly than the estimated 10 minutes total and 3 minutes with the hands near the 

unshielded source. Also, using new gauges containing sources of different activities, different 

radionuclides, or different cleaning and lubrication procedures requires a new evaluation.
H–3

Table H–1. Dosimetry Evaluation

Dosimetry Evaluation for Manufacturer _________________ Model _________________ 

A. Time needed to perform the entire routine 

cleaning and lubrication procedure on 

the gauge

_________ minutes/60 _________ hour

B. Expected whole body dose rate that the 

individual will encounter; determined using 

measured or manufacturer-provided data

____________ mrem/h

C. Time the hands were exposed to the 

unshielded source

_________ minutes/60 _________ hour

D. Expected extremity dose rate that the 

individual will encounter; determined using 

measured or manufacturer-provided data for 

the unshielded source at the typical distance 

from the hands to the unshielded source

____________ mrem/h

E. Formula: (_____#hours in Row A) × (______mrem/h in Row B) = (_____estimated mrem) ×

(_____# of cleaning and lubrications conducted each year) = _______ mrem 

Whole Body Dose Equivalent*

F. Formula: (_____#hours in Row C) × (______mrem/h in Row D) = (_____estimated mrem) 

× (_____# of cleaning and lubrications conducted each year) = _______ mrem 

Extremity Dose Equivalent†

*An expected whole body dose equivalent less than 500 mrem for adult radiation workers requires no dosimetry. 

The corresponding value for minors is 100 mrem. The corresponding value for declared pregnant women during 

the entire pregnancy is 100 mrem.

†An expected extremity dose equivalent less than 5000 mrem for adult radiation workers requires no dosimetry. 

The corresponding value for minors is 500 mrem. There is no corresponding value for declared pregnant women.
H–4

Part 2: Guidance for Demonstrating That Individual Members of the Public Will 

Not Receive Doses Exceeding the Allowable Limits

Licensees must ensure the following:

• The radiation dose received by individual members of the public does not exceed 1 mSv 

[100 mrem] in a calendar year resulting from the licensee’s possession and/or use of 

licensed materials.

Members of the public include persons who live, work, or may be near locations where 

portable gauges are used or stored. (For storage of gauges in personal residences, 

occupants are considered to be members of the public.) Employees whose assigned 

duties do not include the use of licensed materials but who work in the vicinity where 

gauges are used or stored are also considered to be members of the public.

• The radiation dose in unrestricted areas does not exceed 0.02 mSv [2 mrem] in any 

one hour.

Unrestricted areas are areas, access to which is neither limited nor controlled by the 

licensee. Typical unrestricted areas may include offices, shops, laboratories (where 

licensed material is not used or stored), areas outside buildings, property, and storage 

areas. 

Licensees must show compliance with both portions of the regulation. Calculations and/or 

measurements (e.g., using a dosimeter to monitor an area) often are used to prove compliance.

Calculational Method

The calculational method takes a tiered approach, using a three-part process, starting with a 

worst case situation and moving toward more realistic situations. It makes the following 

simplifications: (1) each gauge is a point source, (2) typical radiation levels encountered when 

the source is in the shielded position are taken from either the SSD registration certificate or the 

manufacturer’s literature, and (3) no credit is taken for any shielding found between the gauges 

and the unrestricted areas.

Part 1 of this method is simple but conservative. It assumes that an affected member of the 

public is present 24 hours a day and uses only the “inverse square law” to determine if the 

distance between the gauge and the affected member of the public is sufficient to show 

compliance with the public dose limits. Part 2 considers not only distance but also the time that 

the affected member of the public is actually in the area under consideration. Part 3 considers 

distance and the amount of time that both the gauge and the affected member of the public are 

present. Using this approach, licensees make only those calculations that are needed to 

demonstrate compliance. In many cases, licensees will need to use the calculational method 

through Part 1 or Part 2. The results of these calculations typically result in higher radiation

levels than would exist at typical facilities but provide a method for estimating conservative 

doses that could be received.
H–5

Example 1

To better understand the calculational method, we will look at Moisture-Density 

Measurements, Inc., a portable gauge licensee. Yesterday, the company’s president noted 

that the new gauge storage area is very close to his secretary’s desk and he asked Joe, the 

radiation safety officer (RSO), to determine if the company is complying with NRC regulations.

The secretary’s desk is near the wall separating the reception area from the designated, locked, 

gauge storage area, where the company stores its three gauges. Joe measures the distances 

from each gauge to the wall and looks up in the manufacturer’s literature the radiation levels 

that individuals would encounter for each gauge. Figure H–1 is Joe’s sketch of the areas in 

question, and Table H–2 summarizes the information Joe has about each gauge.

Figure H–1. Diagram of Office and Gauge Storage Area in Examples 1 and 2

Table H–2. Information Known About Each Gauge

DESCRIPTION OF KNOWN 

INFORMATION GAUGE 1 GAUGE 2 GAUGE 3

How gauge is stored Gauge in transport 

container

Gauge in transport 

container

Gauge out of 

transport container 

and being 

recharged

Dose rate in mrem/h 

encountered at specified 

distance from the gauge (from 

manufacturer’s literature)

2 mrem/h at 1 ft 8 mrem/h at 1 ft 2 mrem/h at 3 ft

Distance in feet to secretary’s 

chair

8 ft 12 ft 15 ft

Example 1: Part 1

Joe’s first thought is that the distance between the gauges and the secretary’s chair may be 

sufficient to show compliance with the regulation in 10 CFR 20.1301, “Dose Limits for Individual 

Members of the Public.” So, taking a “worst case” approach, he assumes that (1) the gauges 
H–6

are constantly present (i.e., 24 hours per day), (2) all three gauges remain in storage with no 

other use, and (3) the secretary is constantly sitting in the desk chair (i.e., 24 hours per day). 

Joe proceeds to calculate the dose the secretary might receive hourly and yearly from each 

gauge, as shown in Tables H–3, H–4, and H–5.

Table H–3. Calculational Method, Part 1—Hourly and Annual Dose Received 

From Gauge 1

GAUGE 1

Step 

No. Description Input Data Results

1 Dose received in one hour at known distance from gauge 

(e.g., from manufacturer’s data), in mrem/h

2 2

2 Square of the distance (ft) at which the Step 1 rate was 

measured, in ft2

(1)2 1

3 Square of the distance (ft) from the gauge to the 

secretary’s desk in an unrestricted area, in ft2

(8)2 64

4 Multiply the results of Step 1 by the results of Step 2 (this 

is an intermediate result)

2 × 1 =2

5 Divide the result of Step 4 by the result of Step 3 to 

calculate the dose received by an individual at the 

secretary’s desk = HOURLY DOSE RECEIVED FROM 

GAUGE 1, in mrem per hour

2/64 = 0.031

6 Multiply the result of Step 5 by 24 hours per day ×

365 days per year = MAXIMUM ANNUAL DOSE 

RECEIVED FROM GAUGE 1, in mrem per year

0.031 × 24 × 365 = 

0.031 × 8,760 = 272

Table H–4. Calculational Method, Part 1—Hourly and Annual Dose Received From

Gauge 2

GAUGE 2

Step 

No. Description Input Data Results

1 Dose received in one hour at known distance from gauge 

(e.g., from manufacturer’s data), in mrem/h

8 8

2 Square of the distance (ft) at which the Step 1 rate was 

measured, in ft2

(1) 2 1

3 Square of the distance (ft) from the gauge to the 

secretary’s desk in an unrestricted area, in ft2

(12) 2 144

4 Multiply the results of Step 1 by the results of Step 2 (this 

is an intermediate result)

8 × 1 = 8

5 Divide the result of Step 4 by the result of Step 3 to 

calculate dose received in one hour by an individual at 

the secretary’s desk = HOURLY DOSE RECEIVED 

FROM GAUGE 2, in mrem per hour

8/144 = .056

6 Multiply the result of Step 5 by 24 hours per day × 365 

days per year = MAXIMUM ANNUAL DOSE RECEIVED 

FROM GAUGE 2, in mrem per year

0.056 × 24 × 365 =

0.056 × 8,760 = 491
H–7

Table H–5. Calculational Method, Part 1—Hourly and Annual Dose Received From

Gauge 3

GAUGE 3

Step 

No. Description Input Data Results

1 Dose received in one hour at known distance from gauge 

(e.g., from manufacturer’s data), in mrem/h

2 2

2 Square of the distance (ft) at which the Step 1 rate was 

measured, in ft2

(3)2 9

3 Square of the distance (ft) from the gauge to the 

secretary’s desk in an unrestricted area, in ft2

(15)2 225

4 Multiply the results of Step 1 by the results of Step 2 (this 

is an intermediate result)

2 × 9 =18

5 Divide the result of Step 4 by the result of Step 3 to 

calculate dose received by an individual at the secretary’s 

desk = HOURLY DOSE RECEIVED FROM GAUGE 3, in 

mrem per hour

18/225 = 0.08

6 Multiply the result of Step 5 by 24 hours per day × 365 

days per year = MAXIMUM ANNUAL DOSE RECEIVED 

FROM GAUGE 3, in mrem per year

0.08 × 24 × 365 = 

0.08 × 8,760 = 701

To determine the total hourly and total annual dose received, Joe adds the pertinent data from 

the preceding tables (see Table H–6).

Table H–6. Calculational Method, Part 1—Total Hourly and Annual Dose Received From

Gauges 1, 2, and 3

Step No. Description Gauge 1 Gauge 2 Gauge 3 Sum

7 TOTAL HOURLY DOSE 

RECEIVED from Step 5 of 

Tables H–3, H–4, and H–5, in 

mrem in one hour.

0.031 0.056 0.08 0.031 + 0.056 + 

0.08 = 0.167

8 TOTAL ANNUAL DOSE 

RECEIVED from Step 6 of 

Tables H–3, H–4, and H–5, in 

mrem in a year.

272 491 701 272 + 491 + 701 

= 1464

Note: The Sum in Step 7 demonstrates compliance with the limit of 2 mrem in any one hour. Reevaluate if 

assumptions change. If the Sum in Step 8 exceeds 100 mrem in a year, proceed to Part 2 of the calculational 

method.

At this point, Joe is pleased to see that the total dose that an individual could receive in any 

one hour is only 0.167 mrem, but he notes that an individual could receive a dose of 

1,464 mrem in a year, much higher than the 100-mrem limit.

Example 1: Part 2

Joe reviews his assumptions and recognizes that the secretary is not at the desk 24 hours per 

day. He decides to make a realistic estimate of the number of hours the secretary sits in the 

chair at the desk, keeping his other assumptions constant {i.e., the gauges are constantly 

present (24 hours per day) and all three gauges remain in storage with no other use}. He then 

recalculates the annual dose received (see Table H–7).
H–8

Table H–7. Calculational Method, Part 2—Annual Dose Received from 

Gauges 1, 2, and 3

Step 

No. Description Results

9 A. Average number of hours per day that individual spends in 

area of concern (e.g., secretary sits at desk 5 hours per 

day; the rest of the day the secretary is away from the desk 

area copying, filing, etc.)

B. Average number of days per week in area (e.g., secretary is 

part time and works 3 days a week)

C. Average number of weeks per year in area (e.g., secretary 

works all year)

5

3

52

10 Multiply the results of Step 9A by the results of Step 9B by the 

results of Step 9C = AVERAGE NUMBER OF HOURS IN 

AREA OF CONCERN PER YEAR

5 × 3 × 52 = 780

11 Multiply the sum in Step 7 by the results of Step 10 = ANNUAL 

DOSE RECEIVED FROM GAUGES CONSIDERING 

REALISTIC ESTIMATE OF TIME SPENT IN AREA OF 

CONCERN, in mrem per year

0.167 × 780 = 130

Although Joe is pleased to note that the calculated annual dose received is significantly lower, 

he realizes that it still exceeds the limit of 100 mrem per year.

Example 1: Part 3

Again Joe reviews his assumptions and recognizes that the gauges are not always in storage 

when the secretary is seated at the desk. As he examines the situation, he realizes he must 

consider each gauge individually (see Tables H–8 and H–9).

Table H–8. Calculational Method, Part 3—Summary of Information

INFORMATION ON WHEN GAUGES ARE PRESENT IN THE STORAGE AREA:

• GAUGE 1: an old gauge located in the storage area continuously (24 hours per day).

• GAUGE 2: a new gauge located in the storage area continuously (24 hours per day) for 

8 months of the year; for the remaining 4 months of the year it is at temporary jobsites.

• GAUGE 3: a new gauge located in the storage area overnight; it is used every day at 

temporary jobsites all year and returned to the storage location at the end of each day. 

The gauge usually is present during the secretary’s first and last hours of work each day.

INFORMATION FROM EXAMPLE 1, PART 2 ON WHEN THE SECRETARY IS SITTING AT 

THE DESK:

• 5 hours per day

• 3 days per week

• 52 weeks per year
H–9

Table H–9. Calculational Method, Part 3—Annual Dose Received from 

Gauges 1, 2, and 3

Step 

No. Description GAUGE 1 GAUGE 2 GAUGE 3

12 Average number of hours per day gauge is in 

storage while secretary is present

5 5 2

13 Average number of days per week gauge is 

in storage while secretary is present

3 3 3

14 Average number of weeks per year gauge is 

in storage while secretary is present

52 32 52

15 Multiply the results of Step 12 by the results 

of Step 13 by the results of Step 14 = TOTAL 

HOURS EACH GAUGE IS STORED PER 

YEAR WHILE SECRETARY IS PRESENT

5 × 3 × 52 

= 780

5 × 3 × 32 

= 480

2 × 3 × 52 

= 312

16 Multiply the results of Step 15 by the results 

of Step 7 = ANNUAL DOSE RECEIVED 

FROM EACH GAUGE, in mrem in a year

780 ×

0.031 = 24 

480 ×

0.056 = 27

312 × 0.08 

= 25

17 Sum the results of Step 16 for each gauge = 

TOTAL ANNUAL DOSE RECEIVED 

CONSIDERING REALISTIC ESTIMATE OF 

TIME SPENT IN AREA OF CONCERN AND 

TIME GAUGE IS IN STORAGE, in mrem in 

a year.

24 + 27 + 25 = 76

NOTE: If the result in Step 17 is greater than 100 mrem/yr, the licensee must take corrective action.

Joe is pleased that the result in Step 17 shows compliance with the 100 mrem/yr limit. Had the 

result in Step 17 been higher than 100 mrem/yr, then Joe could have done one or more of 

the following:

• Consider whether the assumptions used to determine occupancy and the time each 

gauge is in storage are accurate, revise the assumptions as needed, and recalculate 

using the new assumptions.

• Calculate the effect of any shielding located between the gauge storage area and the 

secretarial workstation—such calculation is beyond the scope of this appendix.

• Take corrective action (e.g., move gauges within storage area, move the storage 

area, move the secretarial workstation) and perform new calculations to 

demonstrate compliance.

• Designate the area outside the storage area as a restricted area and the secretary as an 

occupationally exposed individual. This would require controlling access to the area for 

purposes of radiation protection and training the secretary as required by 10 CFR 19.12, 

“Instruction to Workers.”

Note that, in the example, Joe evaluated the unrestricted area outside only one wall of the 

gauge storage area. Licensees also need to make similar evaluations for other unrestricted 

areas and to keep in mind the as low as is reasonably achievable (ALARA) principle, taking 

reasonable steps to keep radiation dose received below regulatory requirements. In addition, 

licensees need to be alert to changes in situations (e.g., moving any of the gauges closer to the 
H–10

secretarial workstation, adding a gauge to the storage area, changing the secretary to a full-time 

worker, or changing the estimate of the portion of time spent at the desk) and to perform 

additional evaluations, as needed.

RECORDKEEPING: In 10 CFR 20.2107, “Records of Dose to Individual Members of the 

Public,” the NRC requires licensees to maintain records demonstrating compliance with the 

dose limits for individual members of the public.

Combination Measurement—Calculational Method

This method, which allows the licensee to take credit for shielding between the gauge and the 

area in question, begins by measuring radiation levels in the areas, as opposed to using 

manufacturer-supplied rates at a specified distance from each gauge. These measurements 

must be made with calibrated survey meters sufficiently sensitive to measure background levels 

of radiation. However, licensees must exercise caution when making measurements with 

currently calibrated radiation survey instruments. A maximum dose of 1 mSv [100 mrem]

received by an individual over a period of 2,080 hours (40 hours per week for 52 weeks per 

year) is less than 0.5 microsievert [0.05 mrem] per hour.

This rate is well below the minimum sensitivity of most commonly available Geiger–Mueller

survey instruments.

Instruments used to make measurements for calculations must be sufficiently sensitive. An 

instrument equipped with a scintillation-type detector [e.g., NaI(Tl)] or a micro-R meter used in 

making very low gamma radiation measurements should be adequate.

Licensees may also choose to use environmental thermoluminescent dosimeters (TLDs)1 in 

unrestricted areas next to the gauge storage area for monitoring. This direct measurement 

method would provide a definitive measurement of actual radiation levels in unrestricted areas 

without any restrictive assumptions. Records of these measurements then can be evaluated to 

ensure that rates in unrestricted areas do not exceed the 1 mSv in a yr [100 mrem in a yr] limit.

Example 2

As in Example 1, Joe is the RSO for Moisture-Density Measurements, Inc., a portable gauge 

licensee. The company has three gauges stored in a designated, locked storage area that 

adjoins an unrestricted area where a secretarial work station is located. See Figure H–1 and 

Table H–2 for information about storing gauges near an unrestricted area. Joe wants to see if 

the company complies with the public dose limits at the secretarial station.

During the winter, while all the gauges were in storage, Joe placed an environmental TLD 

badge in the secretarial workspace for 30 days. Joe chose a winter month so that he did not 

 1

TLDs used for personnel monitoring (e.g., lithium fluoride) may not have sufficient sensitivity for this purpose. 

Generally, the minimum reportable dose received is 0.1 mSv [10 mrem]. Suppose a TLD is used to monitor dose 

received and is changed once a month. If the measurements are at the minimum reportable level, the annual dose 

received could have been about 1.2 mSv [120 mrem], a value in excess of the 1 mSv in a yr [100 mrem in a yr] limit. 

If licensees use TLDs to evaluate compliance with the public dose limits, they should consult with their TLD supplier 

and choose more sensitive TLDs, such as those containing CaF2, that are used for environmental monitoring.
H–11

have to keep track of the number of hours that each gauge was in the storage area. The TLD 

processor sent Joe a report indicating that the TLD received 100 mrem.

Table H–10. Combination Measurement—Calculational Method

Step No. Description Input Data and Results

PART 1

1 Dose received by TLD, in mrem 100

2 Total hours TLD exposed 24 h/d × 30 d = 720

3 Divide the results of Step 1 by the results of 

Step 2 to determine HOURLY DOSE 

RECEIVED, in mrem per hour

0.14

4 Multiply the results of Step 3 by 365 days per 

year × 24 hours per day = 8,760 hours in one 

year = MAXIMUM ANNUAL DOSE RECEIVED 

FROM GAUGES, in mrem in a year

365 × 24 × 0.14 = 

8,760 × 0.14 = 

1,226

NOTE: For the conditions described above, Step 3 indicates that the dose received in any one hour is less than the 

limit of 2 mrem in any one hour. However, if there are any changes, then the licensee would need to reevaluate the 

potential doses that could be received in any one hour. Step 4 indicates that the annual dose received would be 

much greater than the 100 mrem in a year allowed by the regulations.

PART 2

At this point, Joe can adjust for a realistic estimate of the time the secretary spends in the 

area, as he did in Part 2 of Example 1.

PART 3

If the results of Joe’s evaluation in Part 2 show that the annual dose received in a year 

exceeds 100 mrem, then he can make adjustments for realistic estimates of the time spent in 

the area of concern while the gauges are actually in storage, as in Part 3 of Example 1. 

(Recall that the TLD measurement was made while all of the gauges were in storage;

i.e., 24 hours per day for the 30 days that the TLD was in place.)

APPENDIX I

MODEL LEAK TEST PROGRAM

I–1

Model Leak Test Program

Training

Before allowing an individual to perform leak testing, the licensee must ensure that he or she 

has sufficient classroom and on-the-job training to show competency in performing leak testing 

and sample analysis independently.

Classroom training may be in the form of lecture, online, video, hands-on, or self-study, and 

should cover the following subject areas:

• principles and practices of radiation protection

• radioactivity measurements, monitoring techniques, and instrument use

• mathematics and calculations used for measuring radioactivity

• biological effects of radiation

Appropriate on-the-job-training consists of the following:

• observing authorized personnel collecting and analyzing leak test samples

• collecting and analyzing leak test samples under the supervision and in the physical 

presence of an individual authorized to perform leak testing and sample analysis

Facilities and Equipment

• To ensure achieving the required sensitivity of measurements, analyze leak tests in a 

low-background area.

• Use a calibrated and operable radiation survey instrument to check leak test samples for 

gross contamination before they are analyzed.

• Analyze the leak test sample using an instrument that is appropriate for the type of 

radiation to be measured [e.g., NaI (Tl) well-counter system for gamma-emitters, liquid

scintillation for beta-emitters, and gas-flow proportional counter for alpha-emitters].

• If the sensitivity of the counting system is unknown, determine the minimum detectable 

activity (MDA). The MDA may be determined using the following formula:

MDA = 2.71 + 4.65 �bkg × t

t × E

where: MDA = minimum detectable activity in disintegrations per minute (dpm)

bkg = background count rate in counts per minute (cpm)

t = background counting time in minutes

E = detector efficiency in counts per disintegration
I–2

For example,

where: bkg = 200 cpm

E = 0.1 counts per disintegration (10 percent efficient)

t = 2 minutes

MDA = 

2.71 + 4.65 �200 cpm × 2 minutes

2 × 0.1 = 

2.71 + 4.65 √400

0.2

= 2.71 + 4.65(20)

0.2 = 

2.71 + 93

0.2 = 

95.71

0.2

= 478.55 disintegrations

minute

becquerels (Bq) = 1 disintegration

second

MDA = 

478.55 disintegration

minutes

×

minute

60 seconds = 7.976 Bq

Note: The MDA equation shown above assumes that counting times for the background 

measurement and for the sample will be equal. MDA equations for non-equal counting times, 

as well as derivations of equations and discussions of limitations, can be found in 

“Decommissioning Health Physics—A Handbook for MARSSIM Users,” Eric W. Abelquist, 

published by Taylor & Francis Group, 2001.

Frequency for Conducting Leak Tests of Sealed Sources

Leak tests will be conducted at the frequency specified in the respective Sealed Source and 

Device registration certificate. If a sealed source is not registered, leak tests should be 

conducted at 6 month intervals, unless a different interval is established during the licensing 

process. Leak testing of sealed sources may be required by license condition.

Procedure for Performing Leak Testing and Analysis

• For each source to be tested, list identifying information such as sealed source serial 

number, manufacturer, model number, radionuclide, and activity.

• Use a radiation survey meter to monitor exposure.

• Prepare a separate wipe sample (e.g., cotton swab or filter paper) for each source.

• Number each wipe to correlate with identifying information for each source.
I–3

• Wipe the most accessible area where contamination would accumulate if the sealed 

source were leaking (see manufacturer’s instructions).

• Select instrumentation that is sensitive enough to detect 185 Bq [0.005 microcuries] of 

the radionuclide contained in the gauge.

• Using the selected instrument, count and record background count rate.

• Check the instrument’s counting efficiency using a standard source of the same 

radionuclide as the source being tested or one with similar energy characteristics. The 

calibration source must be in the same configuration as the sample. Accuracy of 

standards should be within plus or minus 5 percent of the stated value and traceable to 

primary radiation standards such as those maintained by the National Institute of 

Standards and Technology.

• Calculate the counting efficiency of the detector.

Efficiency in cpm/Bq = [(cpm from std) – (cpm from bkg)]

activity of std in Bq

where: cpm = counts per minute

std = standard

bkg = background

Bq = becquerel

• Count each wipe sample; determine net count rate.

• For each sample, calculate and record estimated activity in Bq (or microcuries). The 

activity of the sample in becquerels may be calculated using the following formula:

Activity of sample [Bq] = [(cpm from wipe sample) - (cpm from bkg)]

efficiency in cpm/Bq

• Sign and date the list of sources, data, and calculations. Retain records for 3 years

[under Title 10 of the Code of Federal Regulations (10 CFR) 20.2103(a)]. 

• If the wipe test activity is 185 Bq [0.005 microcurie] or greater, notify the radiation safety 

officer so that the source can be withdrawn from use and disposed of properly. Also, 

notify the U.S. Nuclear Regulatory Commission.

APPENDIX J

U.S. DEPARTMENT OF TRANSPORTATION REGULATIONS

J–1

U.S. Department of Transportation Regulations

Note: The following list of U.S. Department of Transportation (DOT) regulations is provided to 

inform licensees about typical requirements that apply to the transportation of licensed material 

including the preparation of shipments of licensed material. Licensees should note that the list 

is incomplete in that not all potentially applicable requirements have been included. Also, 

transportation requirements change; therefore, licensees should consult the regulations for 

definitive information about current requirements. Additional information on transportation 

requirements may be found at the DOT Web site: http://www.dot.gov/.

• Table of Hazardous Materials and Special Provisions—49 CFR 172, Subpart B

– 49 CFR 172.101—Hazardous Materials Table [proper shipping name, hazard 

class, identification number]

– 49 CFR 172.101—List of Hazardous Substances and Reportable Quantities, 

Table 2 to Appendix A—Radionuclides

• Shipping Papers—49 CFR 172, Subpart C

– 49 CFR 172.201—Preparation and retention of shipping papers

– 49 CFR 172.202—Description of hazardous material on shipping papers

– 49 CFR 172.203—Additional description requirements

– 49 CFR 172.204—Shipper’s certification 

• Marking—49 CFR 172, Subpart D

– 49 CFR 172.300—Applicability

– 49 CFR 172.301—General marking requirements for non-bulk packagings

– 49 CFR 172.304—Marking requirements

– 49 CFR 172.310—Class 7 (radioactive) materials

– 49 CFR 172.324—Hazardous substances in non-bulk packagings [designation of 

“reportable quantities” with the letters “RQ”]

• Labeling—49 CFR 172, Subpart E

– 49 CFR 172.400—General labeling requirements

– 49 CFR 172.400a—Exceptions from labeling

– 49 CFR 172.401—Prohibited labeling

– 49 CFR 172.403—Class 7 (radioactive) material

– 49 CFR 172.406—Placement of labels

– 49 CFR 172.436—RADIOACTIVE WHITE-I label

– 49 CFR 172.438—RADIOACTIVE YELLOW-II label

– 49 CFR 172.440—RADIOACTIVE YELLOW-III label

• Emergency Response Information—49 CFR 172, Subpart G

– 49 CFR 172.600—Applicability and general requirements

– 49 CFR 172.602—Emergency response information

– 49 CFR 172.604—Emergency response telephone number
J–2

• Training—49 CFR 172, Subpart H

– 49 CFR 172.702—Applicability and responsibility for training and testing

– 49 CFR 172.704—Training requirements

• Shippers—General Requirements for Shipments and Packagings—49 CFR Part 173

– 49 CFR 173.25—Authorized packagings and overpacks

– 49 CFR 173.403—Definitions

– 49 CFR 173.411—Industrial packages

– 49 CFR 173.412—Additional design requirements for Type A packages

– 49 CFR 173.415—Authorized Type A packages

– 49 CFR 173.433—Requirements for determining basic radionuclide values, and 

for the listing of radionuclides on shipping papers and labels

– 49 CFR 173.435—Table of A1 and A2 values for radionuclides

– 49 CFR 173.441—Radiation level limitations and exclusive use provisions

– 49 CFR 173.471—Requirements for U.S. Nuclear Regulatory Commission 

approved packages

– 49 CFR 173.475—Quality control requirements prior to each shipment of Class 7 

(radioactive) materials

– 49 CFR 173.476—Approval of special form Class 7 (radioactive) materials

• Carriage by Public Highway—49 CFR Part 177

– 49 CFR 177.817—Shipping papers

– 49 CFR 177.842—Class 7 (radioactive) material [includes requirement for 

blocking and bracing during transport]

Note: The following reference charts are for reference only and are not a substitute for DOT and 

U.S. Nuclear Regulatory Commission transportation regulations.
J–3
J–4
J–5
J–6
J–7
J–8
J–9
J–10
APPENDIX K

SAFETY CULTURE POLICY STATEMENT

K-1

Safety Culture

The safety culture policy statement was published in the Federal Register (76 FR 34773) on 

June 14, 2011, and can be found at: http://www.gpo.gov/fdsys/pkg/FR-2011-06-14/pdf/2011-

14656.pdf. It is also posted in the NRC’s Agencywide Documents Access and Management 

System (ADAMS) and can be found using Accession Number ML11146A047. 

Safety Culture Policy Statement

The purpose of this Statement of Policy is to set forth the Commission’s expectation that 

individuals and organizations establish and maintain a positive safety culture commensurate

with the safety and security significance of their activities and the nature and complexity of their 

organizations and functions. This includes all licensees, certificate holders, permit holders,

authorization holders, holders of quality assurance program approvals, vendors and suppliers of 

safety-related components, and applicants for a license, certificate, permit, authorization, or 

quality assurance program approval, subject to NRC authority. The Commission encourages

the Agreement States, Agreement State licensees and other organizations interested in nuclear 

safety to support the development and maintenance of a positive safety culture, as articulated in

this Statement of Policy.

Nuclear Safety Culture is defined as the core values and behaviors resulting from a collective 

commitment by leaders and individuals to emphasize safety over competing goals to ensure

protection of people and the environment. Individuals and organizations performing regulated

activities bear the primary responsibility for safety and security. The performance of individuals 

and organizations can be monitored and trended and, therefore, may be used to determine 

compliance with requirements and commitments and may serve as an indicator of possible 

problem areas in an organization’s safety culture. The NRC will not monitor or trend values. 

These will be the organization’s responsibility as part of its safety culture program.

Organizations should ensure that personnel in the safety and security sectors have an 

appreciation for the importance of each, emphasizing the need for integration and balance to

achieve both safety and security in their activities. Safety and security activities are closely 

intertwined. While many safety and security activities complement each other, there may be

instances in which safety and security interests create competing goals. It is important that 

consideration of these activities be integrated so as not to diminish or adversely affect either; 

thus, mechanisms should be established to identify and resolve these differences. A safety 

culture that accomplishes this would include all nuclear safety and security issues associated 

with NRC regulated activities.

Experience has shown that certain personal and organizational traits are present in a positive 

safety culture. A trait, in this case, is a pattern of thinking, feeling, and behaving that

emphasizes safety, particularly in goal conflict situations (e.g., production, schedule, and the 

cost of the effort versus safety). It should be noted that although the term ‘‘security’’ is not

expressly included in the following traits, safety and security are the primary pillars of the NRC’s 

regulatory mission. Consequently, consideration of both safety and security issues,

commensurate with their significance, is an underlying principle of this Statement of Policy.
K-2

The following are traits of a positive safety culture:

(1) Leadership Safety Values and Actions—Leaders demonstrate a commitment to safety in 

their decisions and behaviors;

(2) Problem Identification and Resolution—Issues potentially impacting safety are promptly

identified, fully evaluated, and promptly addressed and corrected commensurate with their 

significance;

(3) Personal Accountability—All individuals take personal responsibility for safety;

(4) Work Processes—The process of planning and controlling work activities is implemented so 

that safety is maintained;

(5) Continuous Learning—Opportunities to learn about ways to ensure safety are sought out 

and implemented;

(6) Environment for Raising Concerns—A safety conscious work environment is maintained 

where personnel feel free to raise safety concerns without fear of retaliation, intimidation, 

harassment, or discrimination;

(7) Effective Safety Communication—Communications maintain a focus on safety;

(8) Respectful Work Environment—Trust and respect permeate the organization; and

(9) Questioning Attitude—Individuals avoid complacency and continuously challenge existing 

conditions and activities in order to identify discrepancies that might result in error or 

inappropriate action.

There may be traits not included in this Statement of Policy that are also important in a positive 

safety culture. It should be noted that these traits were not developed to be used for inspection

purposes.

It is the Commission’s expectation that all individuals and organizations, performing or 

overseeing regulated activities involving nuclear materials, should take the necessary steps to

promote a positive safety culture by fostering these traits as they apply to their organizational 

environments. The Commission recognizes the diversity of these organizations and 

acknowledges that some organizations have already spent significant time and resources in the 

development of a positive safety culture. The Commission will take this into consideration as 

the regulated community addresses the Statement of Policy.
APPENDIX L

CHECKLIST FOR REQUESTS TO WITHHOLD PROPRIETARY 

INFORMATION FROM PUBLIC DISCLOSURE (UNDER 10 CFR 2.390)

L–1

Checklist for Requests to Withhold Proprietary 

Information From Public Disclosure (Under 10 CFR 2.390)

In order to request that the U.S. Nuclear Regulatory Commission (NRC) withhold information 

from public disclosure, the applicant or licensee must submit the information, including an 

affidavit, in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, 

“Public Inspections, Exemptions, Requests for Withholding.” The applicant should submit all 

of the following:

 A proprietary copy of the information. Brackets should be placed around the material 

considered to be proprietary. This copy should be marked as proprietary.

 A non-proprietary copy of the information. Applicants should white out or black out the 

proprietary portions (i.e., those in the brackets), leaving the non-proprietary portions 

intact. This copy should not be marked as proprietary.

 An affidavit that:

 Is signed under oath and affirmation (notarization may suffice).

 Clearly identifies (such as by name or title and date) the document to be withheld.

 Clearly identifies the position of the person executing the affidavit. This person 

must be an officer or upper-level management official who has been delegated the 

function of reviewing the information the organization is seeking to withhold and is 

authorized to apply for withholding on behalf of the organization.

 States that the organization submitting the information is the owner of the 

information or is required, by agreement with the owner of the information, to treat 

the information as proprietary.

 Provides a rational basis for holding the information in confidence.

 Fully addresses the following issues:

 Is the information submitted to, and received by, the NRC in confidence? 

Provide details.

 To the best of the applicant’s knowledge, is the information currently available 

in public sources?

 Does the applicant customarily treat this information, or this type of 

information, as confidential? Explain why.

 Would public disclosure of the information be likely to cause substantial harm 

to the competitive position of the applicant? If so, explain why in detail. The 

explanation should include the value of the information to your organization, 

the amount of effort or money expended in developing the information, and the 

ease or difficulty for others to acquire the information.







NUREG-1556, Vol. 1

Revision 2, Final

Consolidated Guidance About Materials Licenses:

Program-Specific Guidance About Portable Gauge Licenses