NRC INSPECTION MANUAL NMSS/FCSS

MANUAL CHAPTER 1247 APPENDIX C2

FUEL FACILITY HEALTH PHYSICS INSPECTOR TECHNICAL PROFICIENCY

TRAINING AND QUALIFICATION JOURNAL
Issue Date: 06/20/14 i 1247 Appendix C2

Table of Contents

Introduction................................................................................................................................ 1

Required Fuel Facility Health Physics Inspector Training Courses............................................. 1

Required Refresher Training...................................................................................................... 1

Post-Qualification Training Courses: .......................................................................................... 1

Fuel Facility Health Physics Inspector Study Guides.................................................................. 2

(SG-HP-1) Code of Federal Regulations (CFRs)............................................................ 3

(SG-HP-2) Licensee Documents for Health Physics Inspectors...................................... 6

(SG-HP-3) Worker Radiation Protection ......................................................................... 8

(SG-HP-4) Radioactive Material Transportation.............................................................15

(SG-HP-5) Solid Radwaste Management and Processing.............................................18

(SG-HP-6) Radiological Environmental Monitoring Program (REMP) ............................21

(SG-HP-7) Radioactive Airborne and Liquid Effluent Treatment and Monitoring Systems

..........................................................................................................................25

Fuel Facility Health Physics Inspector On-The-Job Training Activities ......................................28

(OJT-HP-1) Internal and External Dose Controls...........................................................29

(OJT-HP-2) Air Sampling Program ................................................................................33

(OJT-HP-3) Bioassay and In-vivo Counting ...................................................................36

(OJT-HP-4) Radioactive Material Transportation ...........................................................38

(OJT-HP-5) Solid Radwaste Management and Processing ...........................................40

(OJT-HP-6) Radiological Environmental Monitoring Program (REMP)...........................42

(OJT-HP-7) Radioactive Airborne and Liquid Effluent Treatment and Monitoring Systems

..........................................................................................................................45

Fuel Facility Health Physics Inspector Technical Proficiency Level ...........................................48

Form 1: Fuel Facility Health Physics Inspector Technical Level Proficiency Justification..........50

Attachment 1 Revision History Table ..................................................................................Att1-1
Issue date: 06/20/14 1 1247 Appendix C2

Introduction

Consult with your supervisor prior to beginning the activities or completing the courses in this 

qualification journal. In most cases, you will need to complete the Basic Inspector Certification 

Journal prior to beginning the activities in this Appendix. You may complete the General 

Proficiency requirements contained in Appendix B together with the Technical Proficiency 

requirements outlined in this journal.

Several of the topics have both an individual study guide and on-the-job training. You must 

complete the individual study guide before beginning the corresponding on-the-job training.

Before signing up for any course, be sure that you have checked and have met any 

prerequisites.

Required Fuel Facility Health Physics Inspector Training Courses: 

(These courses have the completion of Appendix A as a prerequisite)

 (H-201) Health Physics Technology

 (H-308) Transportation of Radioactive Materials

 (F-206S) Fire Protection for Fuel Cycle Facilities Self-Study

Required Refresher Training: 

(To be completed every three years)

 (16 Hours) Refresher Technical Training Seminar as approved by supervisor

 (8 hours) OSHA HAZWOPR Refresher Course or iLearn Health and Safety 

Training Suite as identified in Memorandum dated May 7, 2010, from Catherine 

Haney to NMSS Branch Chiefs (See ADAMS Accession No. ML100200563 for 

details of equivalent iLearn training modules).

Post-Qualification Training Courses:

(To be completed within three years of initial qualification)

 (H-111) Environmental Monitoring for Radioactive Materials

 (H-119) Air Sampling for Radioactive Materials

 (H-121) Multi-Agency Radiation Survey and Site Investigation Manual 

(MARSSIM) Course

 (H-311) Respiratory Protection

 (H-312) Internal Dosimetry and Whole Body Counting

 (F-210) Overview of MOX Production and Operational Safety for Reviewers
Issue Date: 06/20/14 2 1247 Appendix C2

Fuel Facility Health Physics Inspector

Study Guides
Issue Date: 06/20/14 3 1247 Appendix C2

Fuel Facility Health Physics Inspector Study Guide

TOPIC: (SG-HP-1) Code of Federal Regulations (CFRs)

PURPOSE: The Code of Federal Regulations (CFR) provides that licensees and 

certificatees (Note - the term licensee will be used throughout this 

document to represent both licensees and certificatees) comply with those 

Parts of the CFR that pertain to the possession, use, storage, disposal and 

transportation of radioactive materials. Fuel facilities are required to 

develop, document, and implement a radiation protection program 

commensurate with the scope and extent of licensed activities within the 

plants. The CFRs also require that integrated safety analyses (ISAs) be 

completed that include identification of radiological hazards, potential 

accident sequences and their likelihood, and engineering controls and 

management measures to limit the risk from such events. For this reason, 

it is mandatory that all radiation protection inspectors gain a general and 

comprehensive knowledge of the contents of relevant radiation protection 

requirements in the CFR. This activity will provide the inspector with 

detailed knowledge of the contents of the requirements and how to apply 

the appropriate radiation protection regulation requirements.

COMPETENCY 

AREA: REGULATORY FRAMEWORK

LEVEL OF 

EFFORT: 40 hours

REFERENCES: 1. 40 CFR Part 190, “Environmental Radiation Protection for Nuclear 

Power Operations” (Note - applicable to fuel cycle facilities providing 

fuel to commercial nuclear power plants)

2. 29 CFR Part 1910, “Occupational Safety & Health Standards”

3. 49 CFR Parts 100-189 Transportation

4. 10 CFR Part 190, “Notices, Instructions, and Reports to Workers: 

Inspection and Investigation”

5. 10 CFR Part 20, “Standards for Protection against Radiation”

6. 10 CFR Part 51, “Environmental Protection Regulations for 

Domestic Licensing and Related Regulatory Functions”

7. 10 CFR Part 61, “Licensing Requirements for Land Disposal of 

Radioactive Waste”

8. 10 CFR Part 70, “Domestic Licensing of Special Nuclear Material”
Issue Date: 06/20/14 4 1247 Appendix C2

9. 10 CFR Part 71, “Packaging and Transportation of Radioactive 

Material”

10. 10 CFR Part 73, “Physical Protection of Plants and Materials”

11. 10 CFR Part 74, “Material Control and Accounting of Special 

Nuclear Material”

12. NUREG-1600, “General Statement of Policy and Procedure for NRC 

Enforcement Actions” (ML003715971)

Note: Bolded CFRs are most important

EVALUATION 

CRITERIA: Upon completion of this activity, the inspector should be able to:

1. Identify, recognize and locate specific radiation protection topics 

presented in the CFRs.

2. Discuss and interpret the content of radiation protection 

requirements identified in the CFRs.

3. Discuss and interpret the definitions of radiation protection terms 

identified in the CFRs.

4. Recognize and discuss the regulatory bases for the ISA and 

management measures as found in 10 CFR Part 70. Relate 

radiation protection requirements to the content of license 

applications.

5. Relate the requirements of the CFRs related to health physics to the 

fuel facility inspection programs. Discuss how the enforcement 

process as described in the CFRs is reflected in the implementation 

of the health physics aspects of the Enforcement Policy and 

Manual. (NUREG-1600, “General Statement of Policy and 

Procedures for NRC Enforcement Actions”, on NRC Office of 

Enforcement Web site)

6. Relate the content of the CFRs to the inspection objectives of the 

radiation safety inspection procedures (IP) (IP 83822, IP 84850, IP 

86740, IP 88035, and IP 88045).

TASKS: 1. Locate and review general and specific radiation protection activities 

described in the CFRs. 

2. Compare and contrast the requirement contained in the health 

physics IP to the requirements of the CFRs.
Issue Date: 06/20/14 5 1247 Appendix C2

3. Review the CFR to identify the regulatory bases for the radiation 

protection programs at fuel facilities.

4. Review how the Enforcement Policy Supplements IV, V, and VI are 

related to the CFRs. 

5. Meet with your supervisor, the person designated as a resource, or 

a qualified Fuel Facility Health Physics Inspector to discuss any 

questions you may have as a result of these activities. Discuss the 

answers to the questions listed under the Evaluation Criteria section 

of this study guide with your supervisor or the person designated as 

a resource.

DOCUMENTATION: Fuel Facility Health Physics Proficiency Level Qualification 

Signature Card, Item SG-HP-1
Issue Date: 06/20/14 6 1247 Appendix C2

Fuel Facility Health Physics Inspector Study Guide

TOPIC: (SG-HP-2) Licensee Documents for Health Physics Inspectors

PURPOSE: The NRC requires that licensees develop an ISA and provide to the NRC 

an ISA Summary and develop an Environmental Report. For this reason, 

it is vital that health physics inspectors gain a detailed knowledge of 

certain aspects of the ISA Summaries and the ISAs where there are any 

key radiological protection issues, and of the Environmental Report. 

Additionally, the NRC requires that licensees operate their facilities in 

compliance with the license or certificate, Technical Safety Requirements 

(TSRs) (for enrichment plants), and the license application. It is vital that 

all health physics inspectors gain a detailed knowledge of these 

documents as they relate to radiation protection. This guide will provide 

health physics inspectors with the detailed knowledge of the contents of 

the ISA Summary, license, Environmental Report, TSRs, and license 

application, the location of the applicable information and requirements for 

specific topics, and how to apply the requirements.

COMPETENCY

AREA: TECHNICAL AREA EXPERTISE

REGULATORY FRAMEWORK

LEVEL OF

EFFORT: 40 hours

REFERENCES: ISA Summary, ISA, license, license application, Environmental Report, 

TSRs if applicable, for a facility designated by your supervisor

EVALUATION

CRITERIA: Upon completion of this guide, you should be able to:

1. Identify the applicable sections of the designated facility’s ISA 

Summary and demonstration section of the license application 

(meteorology, engineered safety features ventilation/filtered

systems, radiation monitoring instrumentation, radiation protection, 

radioactive waste management, technical specifications, and quality 

assurance) and discuss the content.

2. Identify the applicable sections of the designated facility’s TSRs, 

license conditions, condition section of the license application 

(definitions, radiation monitoring instrumentation, engineered safety 

features, ventilation, radioactive effluents, solid radioactive waste, 

radiological environmental monitoring, administrative controls,

surveillance requirements, etc.), and discuss the content and basis 

for the requirements.
Issue Date: 06/20/14 7 1247 Appendix C2

3. Discuss the content and basis for the requirements of the 

designated facility’s offsite dose calculation process such as 

COMPLY.

4. Discuss definitions and terms found in the designated facility’s 

license and license application.

5. Discuss the legal basis, purpose, license conditions, and how these 

documents (ISAs, ISA summaries, TSRs, license applications) can 

be changed.

6. Discuss the delineated programs, processes, equipment, and limits, 

and the reasons they are required.

7. Discuss the requirements for surveillances, action statements, and 

reporting.

8. Discuss the license conditions section of the license application and 

the types of information located in this section. Focus on 

engineered and administrative controls for airborne radioactive 

material in controlled areas and internal dose monitoring and 

radioactive materials effluent section.

TASKS: 1. Review a copy of the ISA Summary and license application for the 

facility designated by your supervisor, with particular attention to the 

sections as listed in the Evaluation Criteria above.

2. Locate a copy of the license and/or TSRs for the facility designated 

by your supervisor and review the various sections as listed in the 

Evaluation Criteria above.

3. Review and familiarize yourself with the other documents listed in 

the reference list. Specifically, identify the purpose of each 

document and what guidance the document provides.

4. Meet with your supervisor, the person designated as a resource or a 

qualified Fuel Facility Health Physics Inspector to discuss any 

questions you may have as a result of this guide. Discuss the 

answers to the questions listed under the Evaluation Criteria section 

of this study guide with your supervisor or the person designated as 

a resource.

DOCUMENTATION: Fuel Facility Health Physics Inspector Proficiency Level Qualification 

Signature Card, Item SG-HP-2
Issue Date: 06/20/14 8 1247 Appendix C2

Fuel Facility Health Physics Inspector Study Guide

TOPIC: (SG-HP-3) Worker Radiation Protection

PURPOSE: The purpose of this guide is to familiarize you with the regulatory basis and 

historical agency positions related to occupational radiation protection. 

The information is addressed in generic correspondence, Regulatory 

Guides (RG) and regulations that pertain to access controls to radiation 

protection. The related IP is IP 83822, “Radiation Protection.”

The IP has three main objectives:

1. Evaluation of the effectiveness of a licensee’s program for internal 

dose control to assure that doses to workers are below NRC limits

2. Evaluation of the effectiveness of a licensee’s program for external 

dose control to assure that doses to workers are below NRC limits

3. Evaluation of the effectiveness of a licensee’s program to assure 

that worker doses are as low as is reasonably achievable (ALARA).

The inspection will determine whether the licensee has an adequate 

program, including administrative, operational, and engineering controls, to 

maintain occupational exposure ALARA.

ALARA is the central concept of occupational radiation protection. In the 

United States the linear non-threshold dose response model was selected 

for its ease of application in a regulatory environment. This model 

assumes that any exposure to ionizing radiation constitutes a risk and that 

risk increases proportionally with exposure. An outgrowth of this is the 

concept of maintaining collective dose ALARA, thereby minimizing the 

total risk associated with the use of radioactive materials. In order to 

minimize individual risk, individual exposures are also maintained ALARA 

with the collective exposure taking precedence.

National Committee for Radiation Protection (NCRP) Publication 116 

ALARA guidance can be summarized as follows:

Justification - The need to justify radiation dose on the basis of

benefit.

Optimization - The need to ensure the benefits are maximized.

Limitation - The need to apply dose limits.

COMPETENCY

AREA: REGULATORY FRAMEWORK

TECHNICAL AREA EXPERTISE
Issue Date: 06/20/14 9 1247 Appendix C2

LEVEL OF 

EFFORT: 80 hours

REFERENCES: 1. 10 CFR Parts 19 and 20

2. NUREG-1736, Consolidated Guidance: 10 CFR Part 20-

Standards for Protection Against Radiation read the sections 

that address the following:

10 CFR Part 20.1003

10 CFR Part 20.1101

10 CFR Part 20.1202 through 1204

10 CFR Part 20.1406 through 1502

10 CFR Part 20.1601 through 1602

10 CFR Part 20.1701 through 1906

3. RG 8.9, “Acceptable Concepts, Models, Equations, and 

Assumptions for a Bioassay Program” (Rev 1, ML003739554)

4. RG 8.10, “Operating Philosophy for Maintaining Occupational 

Radiation Exposures As Low As Is Reasonably Achievable” (Rev. 1-

R) (ML003739563)

5. RG 8.11, “Applications of Bioassay for Uranium” (ML003739450)

6. RG 8.13, “Instructions Concerning Prenatal Radiation Exposure” 

(Rev. 3, ML003739505)

7. RG 8.24, “Health Physics Surveys During Enriched Uranium-235 

Processing and Fuel Fabrication” (Rev. 1, ML003739609)

8. RG 8.25, “Air Sampling in the Workplace” (ML003739616)

9. RG 8.29, “Instruction Concerning Risks from Occupational Radiation 

Exposure” (Rev. 1, ML003739401)

10. RG 8.36, “Radiation Dose to the Embryo/Fetus” (ML003739548)

11. General Health Physics Practices for Fuel Cycle Facilities Course 

Trainee Guide

 

12. ANSI N13.1, “Guide to Sampling Airborne Radioactive 

Materials in Nuclear Facilities”

13. ANSI N42.17B, “Performance Specifications for Health Physics 

Instrumentation - Occupational Airborne Radioactivity Monitoring 

Instrumentation”
Issue Date: 06/20/14 10 1247 Appendix C2

14. ANSI Z88.2, “Respiratory Protection”

15. ANSI N13.6, “Performance Criteria for Instrumentation Used for InPlant Plutonium Monitoring”

16. NUREG/CR-0041, “Manual of Respiratory Protection Against 

Airborne Radioactive Materials” (Rev. 1, ML062350101)

17. Health Physics Positions (HPPOS)-018, 020, 021, 022, and 217 

(These papers are found on the NRC’s Public Website: About NRC 

> How NRC Protects You > Health Physics Positions Based on 10 

CFR Part 20)

18. NUREG/CR- 5569, Rev 1.

19. NUREG/CR-5631, “Contribution of Maternal Radionuclide Burdens 

to Prenatal Radiation Doses” (Rev 2, ML061870465) 

20. NCRP 128, “Radionuclide Exposure of Embryo/Fetus”

21. HPPOS-088, “Corrections for Sample Conditions for Air and Gas 

Monitoring”

22. HPPOS-279, “Technical Assistance Request Regarding Electronic 

Calibration of Survey Instruments”

23. Information Notice 85-87, “Hazards of Inerting Atmospheres”

24. Information Notice 98-20, “Problems with Emergency Preparedness 

Respiratory Protection Programs”

25. HPPOS-147, “Respirator User’s Notice -Use of Unapproved 

Subassemblies” (NIOSH warns against the use of unapproved 

subassemblies (parts and components) and unauthorized 

modifications for/of approved respirators)

26. Federal Register Notice 64, Page 54543, Part 20, Subpart H 

revision in 1999, Final Rule Summary, “Respiratory Protection and 

Controls to Restrict Internal Exposure.”

NOTE: This SG should be done in the office prior to performing the 

corresponding OJT at a licensee site.
Issue Date: 06/20/14 11 1247 Appendix C2

EVALUATION 

CRITERIA: Upon completion of this independent study guide you should be able to:

1. Discuss the regulatory requirements associated with airborne 

radioactivity areas, radiation areas and high radiation areas.

2. Discuss the regulatory requirements associated with surveys and be 

able to describe what may constitute a survey other than 

documented direct meter measurements.

3. Describe the essential elements of an internal dose control and 

monitoring system

4. Describe the essential elements of an air sampling and evaluation 

program to monitor intakes of airborne uranium, plutonium, and 

technetium-99.

5. Describe the responsibility of a licensee for limiting, monitoring and 

tracking the exposure of a declared pregnant worker.

a. Discuss the timing of licensee actions.

b. Discuss the embryo/fetus exposure limits

c. Discuss the inspection considerations detailed in IP 83822.

6. Describe the elements of an internal dosimetry program (in-vivo 

counting, urinalysis, and fecal analysis) for uranium and plutonium.

7. Describe the limitations of an air sampling program for monitoring 

internal dose (lapel and area air samplers).

8. Explain air sampler calibration techniques.

9. Describe appropriate calibration techniques for radiation survey 

meters.

10. Explain the complexities of neutron dose monitoring (for plutonium 

processing).

11. Describe the essential elements of a basic respiratory protection 

program that would be acceptable to the NRC based on 10 Part 20.

12. Explain the potential consequences of not using a Self Contained 

Breathing Apparatus (SCBA) in immediately dangerous to life or 

health (IDLH) environments (such as uranium hexafluoride [UF6] 

clouds or inert atmospheres).

13. Describe deficiencies that are commonly found in respiratory 

protection programs.
Issue Date: 06/20/14 12 1247 Appendix C2

14. Explain ALARA using a working definition that would be 

understandable to someone not affiliated with nuclear power or its 

regulation.

15. Name the activities which account for the greatest percentage of the 

collective dose received in a fuel facility.

16. Explain the NRC philosophy with regard to assigning a set dollar 

value for ALARA planning purposes.

17. State the regulatory basis of ALARA and identify what condition(s) 

must exist in order to cite a violation on basis of ALARA.

TASKS: 1. Review and familiarize yourself with the documents listed in the 

reference list. Specifically, identify the purpose of each document 

and what guidance the document provides.

2. Read the Radiation Protection sections of an assigned license 

application.

3. Read HPPOS-088 which pertains to calibration of air sampling 

equipment. (The following equation is provided to help with 

understanding the issue related to Gas Law Correction.)

)

T

T

)(

P

P

V =V (

c

s

s

c

s c

(See NUREG 1400 for further details)

Where:

Vs= volume under field conditions (appropriate volume unit)

Vc= volume under calibration conditions (appropriate volume 

unit)

Ps= absolute pressure during sampling (mm Hg)

Pc= absolute pressure during calibration (mm Hg)

Ts= absolute temperature during sampling (Kelvin)

Tc= absolute temperature during calibration (Kelvin)

4. Read RG 8.10 and be prepared to discuss the following:

a. The definition of ALARA. 

b. The factors that must be taken into account when making

ALARA recommendations.

c. The types of activities typically accounting for the majority of

the exposures.

d. The key elements of a radiation control program.

e. The NRC-defined dollar-per-rem amount to be used in these 

analyses for occupational exposure (if any).
Issue Date: 06/20/14 13 1247 Appendix C2

f. If an ALARA cost benefit analysis indicates that for a given 

action there is a net benefit, does that mean that a particular 

action must be performed?

g. If ALARA applies equally to internal and external exposures.

h. The roles of the Radiation Protection Manager:

- Where does (s)he normally fit in the reporting chain?

- Why does (s) he normally fit there?

- What are his/her specific responsibilities with regard to 

the ALARA program?

- What is his/her responsibility with respect to the sites 

radiation protection training program?

5. Review the regulatory basis, including the statements of 

consideration, for the application of the ALARA regulations.

6. Meet with your supervisor, the person designated as a resource or a 

qualified Fuel Facility Health Physics Inspector to discuss any 

questions you may have as a result of this training activity. Discuss 

the answers to the questions listed under the Evaluation Criteria 

section of this study guide with your supervisor or the person 

designated as a resource.

DOCUMENTATION: Fuel Facility Health Physics Inspector Proficiency Level Qualification 

Signature Card, Item SG-HP-3.

Other Important References Related to this Topic:

ANSI N42.17A-1989, Performance Specifications for Health Physics Instrumentation - Portable 

Instrumentation for Use in Normal Environmental Conditions

ANSI N42.17C-1989, Performance Specifications for Health Physics Instrumentation - Portable 

Instrumentation for Use in Extreme Environmental Conditions 

ANSI N323A-1997, Radiation Protection Instrumentation and Calibration, Portable Survey 

Instruments

Office of Inspection and Enforcement (IE) Information Notice 83-68, “Respirator User Warning: 

Defective Self Contained Breathing Apparatus Air Cylinders”

IE Information Notice 85-48, “Respirator User Warning: Defective Self Contained Breathing 

Apparatus Air Cylinders”

IE Information Notice 86-103, “Respirator Coupling Nut Assembly Failures”

IE Information Notice 89-47, “Potential Problems with Worn or Distorted Hose Clamps on Self 

Contained Breathing Apparatus”
Issue Date: 06/20/14 14 1247 Appendix C2

IE Information Notice 94-35, “National Institute for Occupational Safety and Health NIOSH 

Respirator User Notices, Inadvertent Separation of the Mask Mounted Regulator (MMR) from 

the Facepiece of the Mine Safety Appliances (MSA) Company Self Contained Breathing 

Apparatus (SCBA) and Status Update”

IE Information Notice 95-01, DOT Safety Advisory: High Pressure Aluminum Seamless and 

Aluminum Composite Hoop Wrapped Cylinders

Questions & Answers (Q&A) 91, Clarifies the need to comply with programmatic requirements 

when using respirators (These Q&As are found on the NRC’s Public website: About NRC > 

How NRC Protects You > Health Physics Positions Based on 10 CFR Part 20 > FAQ)

Q&A 124, Notes that this section’s requirements apply to respirators used during emergencies

Q&A 418, Explains that licensee’s need a formal program whenever a respirator is used to limit 

intake

HPPOS 103, Guidance for Medical Evaluations for Respiratory Users
Issue Date: 06/20/14 15 1247 Appendix C2

Fuel Facility Health Physics Inspector Study Guide

TOPIC: (SG-HP-4) Radioactive Material Transportation

PURPOSE: The purpose of this SG is to familiarize you with the regulatory bases and 

historical agency positions in the area of radioactive material 

transportation. Specifically, the information provides you the necessary 

technical knowledge to conduct inspections using IP 86740, Inspection of 

Transportation Activities. The NRC requires that licensees ensure 

adequate protection of public health and safety from exposure to 

radioactive material during shipment. Licensees must comply with the 

requirements of 10 CFR Part 20 and 10 CFR Part 71 and DOT regulations 

contained in 49 CFR Parts 100-189. This guide will provide you with 

detailed knowledge of the requirements contained in regulations and 

position documents.

COMPETENCY

AREA: REGULATORY FRAMEWORK 

 TECHNICAL AREA EXPERTISE

LEVEL OF

EFFORT: 40 hours

REFERENCES: 1. 10 CFR Part 20 and 10 CFR Part 71

2. 49 CFR Parts 100-189

3. NUREG-1608, “Categorizing and Transporting Low Specific Activity 

Materials and Surface Contaminated Objects”

4. NUREG-1660, “U.S. - Specific Schedules of Requirements for 

Transport of Specified Types of Radioactive Material Consignments”

5 DOT Emergency Response Guidebook

NOTE: This SG must be completed in the office before beginning the

related OJT Training at a licensee site.

EVALUATION

CRITERIA: Upon completion of this guide, you should be able to:

1. Discuss the packaging, labeling and marking requirements for 

various types of radioactive materials packages expected to be 

shipped from a facility, as presented in NUREG-1660 and 49 CFR 

parts 100-189. 
Issue Date: 06/20/14 16 1247 Appendix C2

2. Discuss the manifesting, labeling, and placarding requirements for 

non-exempt types of radioactive materials packages relative to 

NUREG 1660. 

3. Discuss the allowable radiation dose rate and contamination limits 

for shipment of packages of radioactive material specified in 

regulatory documents 49 CFR parts 100-189 and 10 CFR Part 71.4. 

The limits include transport vehicle dose limits, cab limits, and 

package limits, as appropriate. 

4. Discuss HAZMAT training and emergency response program 

requirements relative to guidance in Information Notices 92-62, 92-

72, 95-09, and 49 CFR Parts 100-189.

5. Discuss Quality Assurance Requirement for a radioactive materials 

shipping program, as described in 10 CFR Part 71. 

TASKS: 1. Review and familiarize yourself with the documents listed in the 

reference list and in the list of other important references. 

Specifically, identify the purpose of each document and what 

guidance the document provides.

2. Review the requirements for the transfer and receipt of radioactive 

material as specified in 10 CFR Part 20 and 10 CFR Part 71, 

including reporting requirements for problems identified.

3. Review the requirements in the area of training and emergency 

response as specified in 49 CFR parts 100-189. Identify minimum 

training requirements and minimum emergency response 

requirements.

4. Meet with your supervisor, the person designated as a resource or a 

qualified Fuel Facility Health Physics Inspector to discuss any 

questions you may have as a result of these activities. Discuss 

answers to the questions listed under the Evaluation Criteria section 

of this study guide with your supervisor or the person designated as 

a resource.

DOCUMENTATION: Fuel Facility Health Physics Inspector Proficiency Level Qualification 

Signature Card, Item SG-HP-4

Other Important References Related to this Topic:

IE Information Notice 90-50, “Minimization of Methane Gas in Plant Systems and Radwaste 

Shipping Containers”
Issue Date: 06/20/14 17 1247 Appendix C2

IE Information Notice 92-62, “Emergency Response Information Requirements for IE 

Radioactive Material Shipments”

IE Information Notice 92-72, “Employee Training and Shipper Registration Requirements for 

Transporting Radioactive Materials”

IE Information Notice 95-09, “Monitoring and Training of Shippers and carriers of Radioactive 

Materials”

NUREG/CR-5569, Rev. 1, “Health Physics Positions Data Base”

NUREG/CR-6204, “Questions and Answers Based on Revised 10 CFR 20”
Issue Date: 06/20/14 18 1247 Appendix C2

Fuel Facility Health Physics Inspector Study Guide

TOPIC: (SG-HP-5) Solid Radwaste Management and Processing

PURPOSE: The purpose of this SG is to familiarize you with the regulatory bases and 

historical agency positions in the area of solid radioactive waste control 

and processing (including control of contaminated items). Specifically, the 

information provides you the necessary technical knowledge to conduct 

inspections using the solid radioactive waste portions of IP 88035, 

“Radioactive Waste Management”, and IP 84850, “Radioactive Waste 

Management - Inspection of Waste Generator Requirements of 10 CFR 

Part 20 and 10 CFR Part 61.” This guide will provide you with detailed 

knowledge of the requirements contained in regulations and position 

documents.

COMPETENCY

AREA: REGULATORY FRAMEWORK

FUNDAMENTAL FACILITY DESIGN & OPERATION

TECHNICAL AREA EXPERTISE

LEVEL OF

EFFORT: 40 hours

REFERENCES: 1. 10 CFR Part 61, “Licensing Requirements for Land Disposal of

 Radioactive Waste.”

2. Radwaste system and facility description from the licensed facility

designated by your supervisor.

3. 10 CFR Part 20, “Standards for Protection against Radiation.”

a. Subpart F, “Surveys and Monitoring”; 20.1501(a) and 

20.1501(b)

b. Subpart K, “Waste Disposal.”

4. NRC Branch Technical Position, Waste Form Technical Position

5. NRC Branch Technical Position on Concentration Averaging and 

Encapsulation 

6. NUREG/BR-0204, Instructions for Completing NRC’s Uniform 

Low-level Radioactive Waste Manifest

7. IE Circular 81-07, Control of Radioactively Contaminated Material

8. IE Information Notice 85-92, “Surveys of Wastes Before Disposal

From Nuclear Reactor Facilities”
Issue Date: 06/20/14 19 1247 Appendix C2

9. NUREG/CR-5569, Rev. 1, “Health Physics Positions Data Base”

10. NUREG/CR-6204, “Questions and Answers Based on Revised 10 

CFR Part 20”

11. NUREG 1736, “Consolidated Guidance: 10 CFR Part 20

 Standards for Protection Against Radiation” (ML01330179)

12. IE Information Notice 83-05, “Obtaining Approval for Disposing of

Very-Low-Level Radioactive Waste - 10 CFR Section 20.302” 

 (current 10 CFR Part 20.2002).

NOTE: This SG should be completed in the office before beginning 

the related OJT at a licensee site.

EVALUATION

CRITERIA: Upon completion of this guide, you should be able to:

1. Discuss and highlight the key aspects of the plant’s solid radioactive 

waste processing systems, and their operation, as described in the 

license application.

2. Discuss the purpose and principal requirements of 10 CFR Part 61 

and NRC waste classification and characterization guidance. 

3. Discuss NRC guidance in the area of collection of representative 

samples of waste for the 10 CFR Part 61 program and how changes 

in waste streams should be identified for purposes of waste 

characterization and classification. 

4. Discuss the principal aspects of classification of low-level radwaste 

as outlined in 10 CFR Part 61.

5. Discuss and identify free release criteria for contaminated materials 

from Radiation Control Area (RCA) to the public domain.

6. Explain the “no detectable” licensed radioactive material release 

policy for surface contamination, volumetric contamination, and 

difficult to detect radionuclides.

7. Discuss the calibration technique for contamination monitors used to 

free release material (e.g., small article monitor (SAM), bag monitor, 

frisker) in order to conform to guidance in NRC Circular 81-07 and 

IE Information Notice 85-92.
Issue Date: 06/20/14 20 1247 Appendix C2

8. Describe the difference between a release limit and the Ano 

detectable” criteria.

9. Describe the minimum detection sensitivity criteria that licensees 

must use for radiation surveys of potentially contaminated material.

TASKS: 1. Review and familiarize yourself with the documents listed in the 

reference list and in the list of other important references. 

Specifically, identify the purpose of each document and what 

guidance the document provides.

2. Locate a copy of the solid radwaste section from the license 

application of your designated facility. Review the design and 

operation of the radwaste systems. Identify the various sources of 

solid radioactive waste.

3. Review and highlight the key aspects and requirements for low-level 

radioactive waste disposal as outlined in 10 CFR Part 61 and the 

burial site license.

4. Review free release criteria of contaminated materials from RCA to 

the public domain.

5. Meet with your supervisor, the person designated as a resource or a 

qualified Fuel Facility Health Physics Inspector to discuss any 

questions you may have as a result of this activity. Discuss 

answers to the questions listed under the Evaluation Criteria section 

of this study guide with your supervisor or the person designated as 

a resource.

DOCUMENTATION: Fuel Facility Health Physics Inspector Proficiency Level Qualification 

Signature Card, Item SG-HP-5

Other Important References Related to this Topic:

Information Notice 86-20, “Low-Level Radioactive Waste Scaling Factors – 10 CFR Part 61”

NRC Bulletin 80-10, “Contamination of Non-Radioactive System and Resulting Potential for 

Unmonitored, Uncontrolled Release to Environment”
Issue Date: 06/20/14 21 1247 Appendix C2

Fuel Facility Health Physics Inspector Study Guide

TOPIC: (SG-HP-6) Radiological Environmental Monitoring Program (REMP)

PURPOSE: The purpose of this SG is to familiarize you with the regulatory bases and 

historical agency positions in the area of radiological environmental 

monitoring. Specifically, the information provides you the necessary 

technical knowledge to conduct inspections using IP 88045, “Effluent 

Control and Environmental Protection.” The NRC requires that licensees 

ensure adequate protection of public health and safety from exposure to 

radioactive material released to the public domain as a result of routine 

operations. The REMP is required by the license. The REMP 

supplements the effluent monitoring program by verifying that the 

measurable concentrations of radioactive materials and levels of radiation 

in the environment are in agreement with the values predicted by the 

radioactive effluent monitoring program.

This guide will provide you with detailed knowledge of the requirements 

contained in regulations and position documents in the area of radiological 

environmental monitoring. 

COMPETENCY

AREA: REGULATORY FRAMEWORK 

TECHNICAL AREA EXPERTISE

LEVEL OF

EFFORT: 40 hours

REFERENCES: 1. 10 CFR Part 20

2. IP 88045, “Effluent Control and Environmental Protection.”

3. Plant license application

4. RG 4.15, “Quality Assurance for Radiological Monitoring Programs 

(Inception through Normal Operations to License Termination) 

“Effluent Streams and the Environment” (Rev. 2, ML071790506)

5. NUREG/CR-5569, Rev. 1, “Health Physics Positions Data Base”

6. NUREG/CR-6204, “Questions and Answers Based on Revised 10 

CFR Part 20”

7. NUREG 1736, “Consolidated Guidance: 10 CFR Part 20-

Standards for Protection Against Radiation” (ML01330179)
Issue Date: 06/20/14 22 1247 Appendix C2

EVALUATION 

CRITERIA: Upon completion of this guide, you should be able to:

1. Discuss the specific regulatory requirements that require a licensee 

to have a REMP.

2. Discuss the specific environmental sampling techniques (water, air 

particulate, vegetation, fish, and soil/sediment) required to be used 

in accordance with the REMP.

3. Discuss the different measuring techniques (proportional counter, 

gamma spectroscopy, liquid scintillation counter, and 

thermoluminescent dosimeter [TLD]) that may be used by the 

licensee and the capabilities and limitations of each.

4. Discuss and show how to calculate standard data reduction 

techniques, including minimum detectable activity (MDA) and lower 

limit of detection (LLD) highlighted in NRC and industry publications.

5. Discuss the NRC expectations for a licensee’s QA program for 

REMP including the use and bases for inter-laboratory and intralaboratory comparisons.

6. Discuss the NRC requirements for a Meteorological Monitoring 

Program, including calibration methodology for wind direction, wind 

speed, and delta temperature.

7. Be able to utilize /Q and D/Q, and annual average data in order to 

determine exposure rates associated with atmospheric dispersion.

8. Discuss the annual report of effluents and resulting offsite doses. 

9. Describe the man-made and natural radiation exposure pathways 

(plant effluents and the source of the natural background radiation) 

that are present at your assigned facility.

10. Identify the specific environmental sample requirements for your 

assigned facility as described in the license application.

11. Discuss any environmental contamination from licensed activities, 

including ponds, burial sites, and groundwater issues.

TASKS: 1. Review and familiarize yourself with the documents listed in the 

reference list and in the list of other important references. 

Specifically, identify the purpose of each document and what 

guidance the document provides.
Issue Date: 06/20/14 23 1247 Appendix C2

2. Locate and review the REMP requirements in the license application 

for your assigned facility.

3. Review the Environmental Report and any special environmental 

studies for your assigned facility.

4. Review counting statistics and data reduction, including MDA and 

LLDs.

5. Review radiological analytical methodology for likely releases from 

your facility such as isotopic uranium or plutonium, total uranium, 

technetium-99, thorium, gross alpha, and gross beta.

6. Review meteorological monitoring and calibration requirements for 

your facility.

7. Review the sequential relationship between Radiological Effluent 

Controls and the REMP for your facility.

8. Review man-made and natural radiation exposure pathways (plant 

effluents and the source of the natural background radiation) that 

are present at your assigned facility.

9. Review the process for any laboratory inter-comparison program at 

your assigned facility.

10. Meet with your supervisor, the person designated as a resource or a 

qualified Fuel Facility Health Physics Inspector to discuss any 

questions you may have as a result of these activities. Discuss 

answers to the questions listed under the Evaluation Criteria section 

of this study guide with your supervisor or the person designated as 

a resource.

DOCUMENTATION: Fuel Facility Health Physics Inspector Proficiency Level Qualification 

Signature Card, Item SG-HP-6

Other Important References Related to this topic:

Environmental Measurement Laboratory, “HASL-300 Procedures Manual,” U.S. Department of 

Energy, New York, NY

NCRP Report No. 45, “Natural Background Radiation in the US”

NCRP Report No. 47, “Tritium measurement Techniques”

NCRP Report No. 50, “Environmental Radiation Measurements”
Issue Date: 06/20/14 24 1247 Appendix C2

NCRP Report No. 58, “Handbook of Radioactivity Measurements Procedures”

ANSI N545-1975, “Performance, Testing, and Procedural Specification for TLD, Environmental 

Application”

ANSI N13.1-1969, “Guide to Sampling Airborne Radioactive materials in Nuclear Facilities”
Issue Date: 06/20/14 25 1247 Appendix C2

Fuel Facility Health Physics Inspector Study Guide

TOPIC: (SG-HP-7) Radioactive Airborne and Liquid Effluent Treatment and 

Monitoring Systems

PURPOSE: The purpose of this SG is to familiarize you with the regulatory bases and 

historical agency positions in the area of radioactive airborne and liquid 

effluent treatment and monitoring systems. The NRC requires that 

licensees ensure adequate protection of public health and safety and the 

environment from exposure to radioactive materials released to the public 

domain. Radiation exposure to the public is to be below the 10 CFR Part 

20 limits and, for those facilities manufacturing uranium for the commercial 

fuel cycle, within 40 CFR Part 190 limits. This guide will provide you with 

detailed knowledge of the requirements contained in these regulations.

COMPETENCY

AREA: REGULATORY FRAMEWORK 

TECHNICAL AREA EXPERTISE

LEVEL OF

EFFORT: 45 hours

REFERENCES: 1. 10 CFR Part 20, 10 CFR Part 70, and 10 CFR Part 76

2. 40 CFR Part 190

3. Plant license application

4. IP 88035, “Radioactive Waste Management” (for liquid and airborne 

radioactive waste)

5. NUREG/CR-5569, Rev. 1, “Health Physics Positions Data Base”

6. NUREG/CR-6204, “Questions and Answers Based on Revised 10 

CFR Part 20”

7. NUREG 1736, “Consolidated Guidance: 10 CFR Part 20-

Standards for Protection Against Radiation” (ML01330179)

EVALUATION 

CRITERIA: Upon completion of this guide, you should be able to:

1. Discuss and identify effluent sampling techniques that may be used 

by the licensee for sampling effluents such as radioactive waste 

water, storm water runoff, and air particulate and non-particulate 

(such as soluble uranium).
Issue Date: 06/20/14 26 1247 Appendix C2

2. Discuss different measuring techniques, such as proportional 

counting, gamma spectroscopy, and liquid scintillation counting that 

a licensee may use to analyze its samples. Compare and contrast 

the techniques.

3. Discuss calibration techniques for a laboratory’s gamma 

spectroscopy, proportional counter, and liquid scintillation counter. 

Identify the types of sources to be used and expected MDA or LLDs.

4. Discuss laboratory analytical techniques for radionuclides such as 

isotopic uranium or plutonium, gross alpha/beta, total uranium, and 

technetium-99. Identify best methods. 

5. Discuss laboratory quality assurance and quality control (QA/QC) 

Policy and its implementation, including inter-laboratory and intralaboratory comparisons. Discuss NRC expectations in this area.

6. Discuss and calculate MDA and LLDs for hypothetical samples. 

7. Discuss the principles of air cleaning systems, such as in-place filter 

testing. Discuss applicable guidance documents and acceptable 

results

8. Review the air cleaning system and liquid effluent processing 

sections from your assigned facility’s license application. Discuss 

the principal components and their use. 

9. Identify the various sources of liquid and gaseous radwaste at your 

assigned facility by reviewing the license application and 

environmental report. Discuss the described waste streams, and 

technologies associated with liquid and airborne radwaste 

processing for the facility.

TASK: 1. Review and familiarize yourself with the documents listed in the 

reference list and in the list of other important references. 

Specifically, identify the purpose of each document and what 

guidance the document provides.

2. Review and evaluate effluent sampling techniques, such as 

radioactive waste water, soluble airborne, and air particulate.

3. Review and evaluate the different measuring techniques, such as 

proportional counter, gamma spectroscopy, and liquid scintillation 

counter.

4. Review and evaluate the calibration techniques and results for the 

measurement laboratory’s gamma spectroscopy, proportional 
Issue Date: 06/20/14 27 1247 Appendix C2

counter, and liquid scintillation counter.

5. Review and evaluate the characteristics of radiation monitoring 

systems (RMS), such as gamma-scintillation detector, betascintillation detector, Geiger-Müeller (GM), and ion chamber. 

Identify capabilities and limitations.

6. Review and evaluate principle air cleaning system tests, such as air 

in-place filter testing. Compare with applicable regulatory 

requirements for your facility.

7. Identify the various sources of liquid and airborne radwaste at 

assigned facility.

8. Meet with your supervisor, the person designated as a resource or a 

qualified Fuel Facility Health Physics Inspector to discuss any 

questions you may have as a result of these activities. Discuss 

answers to the questions listed under the Evaluation Criteria section 

of this study guide with your supervisor or the person designated as 

a resource.

DOCUMENTATION: Fuel Facility Health Physics Inspector Proficiency Level Qualification 

Signature Card, Item SG-HP-7

Other important references related to this topic:

Environmental Measurement Laboratory, “HASL-300 Procedures Manual,” U.S. Department of 

Energy, New York, NY

NCRP Report No. 58, “A Handbook of Radioactivity Measurements Procedures”

RG 1.52, “Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of PostAccident Engineered-Safety-Feature Atmosphere Cleanup System in Light-Water-Cooled 

Nuclear Power Plants” (ML011710176 - Endorsed ANSI N509-1976 and N510-1975)

RG 4.15, “Quality Assurance for Radiological Monitoring Programs (Inception through Normal 

Operations to License Termination) - Effluent Streams and the Environment” (ML071790506)

ANSI N13.1-1982, “Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities”

ANSI/ASME N510-1980, “Testing of Nuclear Air-Cleaning Systems”

IE Bulletin No. 80-10, “Contamination of Nonradioactive Systems and Resulting Potential for 

Unmonitored, Uncontrolled Release of Radioactivity to the Environment,” May 6, 1980

IE Information Notice No. 82-49, “Correction for Sample Conditions for Air and Gas Monitoring,” 

December 16, 1982
Issue Date: 06/20/14 28 1247 Appendix C2

Fuel Facility Health Physics Inspector 

On-The-Job Training Activities
Issue Date: 06/20/14 29 1247 Appendix C2

Fuel Facility Health Physics Inspector On-the-Job Training

TOPIC: (OJT-HP-1) Internal and External Dose Controls

PURPOSE: The purpose of this activity is to familiarize you with inspection activities in 

IP 83822, “Radiation Protection.”

COMPETENCY 

AREA: TECHNICAL AREA EXPERTISE

ASSESSMENT AND ENFORCEMENT

COMMUNICATION

INSPECTION

LEVEL OF 

EFFORT: 32 hours

NOTE: Successful completion of SG-HP-3 is a prerequisite to this 

activity

REFERENCES: All the references used in SG-HP-3 are appropriate for this module. Most 

of the efforts in this OJT will rely on licensee procedures and related 

regulatory documents. Any references other than licensee procedures will 

be used to determine the regulatory stance that has been historically 

applied by the NRC for a given situation. References selected should 

support the actual inspection effort.

1. Licensee Radiological Access Control, Radiological Postings, 

Radiation Work Permit, and Declared Pregnant Worker procedures

2. Licensee dose printout of individual doses for a work group 

identified by qualified inspector

EVALUATION

CRITERIA: Upon completion of the tasks in this OJT, you should be able to:

1. Describe areas that are considered radiologically risk significant and 

what kind of work would increase the risk significance.

2. Describe licensee controls for airborne radioactive materials, 

radiation areas, and high radiation areas.

3. Describe the licensee’s mechanism for making timely changes to 

controls and postings for airborne radioactivity and radiation areas, 

as a result of changing plant operations.
Issue Date: 06/20/14 30 1247 Appendix C2

4. Describe the results of the survey you performed and the survey 

performed by the licensee and explain what could cause the results 

to be different.

5. Describe the information communicated to the worker by the 

Radiation Work Permit (RWP), and the responsibilities of the 

radiation workers and health physics staff.

6. Explain licensee policy on the use of lapel and stationary air 

sampling, and how each is used to determine derived air 

concentration (DAC) hours and internal dose. 

7. Explain the actions expected from workers in response to a high 

airborne radioactivity alarm, criticality alarm, and a frisker alarm and 

malfunction.

8. Describe methods that could be employed to reduce or prevent the 

uptake of radioactive materials.

9. Describe expected licensee response to suspected or actual uptake 

of airborne radioactive material.

10. Explain why there are still some variations in the amount of dose 

received for plant workers.

11. Describe licensee source term trending techniques.

12. Describe considerations in determining whether temporary 

containment and ventilation are provided at RPs request.

13. Describe how the licensee ALARA program incorporates lessons 

learned, industry experience, historical data, and employee 

feedback/recommendations.

14. Describe the process used to determine and assign fetal dose. 

Describe a woman’s rights with respect to declaring her pregnancy. 

15. Describe the degree of documentation in the corrective action 

program with regards to threshold, detail, thoroughness, and 

timeliness and how the program should be assessed for adequacy.

NOTE: The following tasks are to be performed concurrent with an 

inspection at an operational fuel facility under the direction of a 

qualified inspector. Any unexpected findings or questions that you 

might have should be brought to the attention of the inspector. 

Any tasks previously completed as part of the course AGeneral 

Health Physics Practices for Fuel Cycle Facilities” need not be 

repeated if done on a separate inspection.
Issue Date: 06/20/14 31 1247 Appendix C2

TASKS: 1. Identify exposure significant work areas within the plant.

2. Identify appropriate licensee controls for internal uptakes and 

external exposure in process areas.

3. Walk down a work area with a contamination survey instrument and 

determine if licensee surveys are accurate. Prior to performing the 

survey perform the following steps:

a. Select an appropriate instrument. (If you are uncertain, 

contact the qualified inspector.) 

b. Familiarize yourself with the operations of the instrument and 

any peculiarities/features that it may have. 

c. Turn the instrument on and check its batteries, check high 

voltage or instrument zero (if applicable), and physical 

condition, and perform a response test with appropriate 

source.

d. Verify that the instrument is within its calibration interval. (If 

there is any doubt about the operability of the instrument, do 

not use it.) 

4. Review RWPs used to access an area of anticipated high airborne 

radioactivity and identify what work control instructions are 

specified.

5. Discuss the engineering controls that would be expected for an area 

that was expected to exceed 20 DAC airborne being produced by 

maintenance. (A qualified inspector can identify an example and 

work through this with you.)

6. Review plant procedures for internal dose assessment. Walk the 

procedure through for a hypothetical uptake that involves either 

enriched uranium or plutonium.

7. Select several work stations and observe operators during the 

inspection. Discuss any observations with a qualified inspector.

8. Review at least two reports to management on plant radiological 

conditions (normally weekly or monthly). Discuss with the Radiation 

Protection Manager his/her evaluation of adverse trends in the 

reports.

9. Compare individual internal doses or lung counts for three 

workgroups and identify probable reasons for significant differences.

10. Determine the elements of the licensee’s source term control 

strategies.
Issue Date: 06/20/14 32 1247 Appendix C2

11. Review a licensee self assessment or audit. Select three findings 

from the report and determine if the identified problems are 

documented in the corrective action program for tracking and 

resolution.

12. Review Declared Pregnant Worker (or Woman) procedures. 

Review the exposure results and monitoring controls employed by 

the licensee with respect to the requirements. (Program should 

have provisions for determining fetal dose from internal deposition 

as well as external radiation.)

13. Meet with your supervisor, the person designated as a resource or a 

qualified Fuel Facility Health Physics Inspector to discuss any 

questions you may have as a result of these activities and to 

demonstrate that you can meet the evaluation criteria for this OJT.

DOCUMENTATION: Fuel Facility Health Physics Inspector Proficiency Level Qualification 

Signature Card, Item OJT-HP-1
Issue Date: 06/20/14 33 1247 Appendix C2

Fuel Facility Health Physics Inspector On-the-Job Training

TOPIC: (OJT-HP-2) Air Sampling Program

PURPOSE: The purpose of this activity is to familiarize you with air sampling and 

evaluation programs as they are used to show compliance with internal 

dose limits.

COMPETENCY 

AREA: TECHNICAL AREA EXPERTISE

INSPECTION

LEVEL OF

EFFORT: 36 hours

Note: Successful completion of SG-HP-3 is a prerequisite to this training

REFERENCES: References used in SG-HP-3 related to air sampling are appropriate for 

this module. Most of the efforts in this OJT will rely on licensee 

procedures and the license application. References selected should 

support the actual inspection effort.

1. Licensee procedures for routine and special air sampling, including 

sampler calibration and results evaluation, including work 

restrictions.

2. Licensee procedures for analyzing air samples and calculation to 

DAC-hours, uptakes, and internal dose.

3. Licensee procedures for determining the representativeness of 

stationary air samplers, including initial location and periodic reverification.

4. Licensee procedures for air sampler and bioassay or in-vivo 

counting results.

EVALUATION

CRITERIA: Upon Completion of this training you should be able to:

1. Describe a routine air sampling program for Low Enrichment 

Uranium (LEU), High Enrichment Uranium (HEU), and plutonium, 

including regulatory limits, DACs, and licensee action points.

2. Discuss typical actions for unexpected events that could cause 

increased airborne material.
Issue Date: 06/20/14 34 1247 Appendix C2

3. Discuss typical actions taken when there are airborne events or 

unexpectedly high air sample results.

4. Describe the methodology used to calibrate air sampling 

instruments. 

5. Describe the process used to resolve situations where instruments 

are found to be significantly out of calibration. What is the impact on 

surveys done with the instrument? 

6. Describe the methodology used to determine DACs and uptakes 

based on air sample results, limitations and areas for potential 

errors.

7. Discuss licensee documentation that is used to identify, report, and 

track problems involving personnel unexpected air sample results.

NOTE: The following tasks are to be performed concurrent with an 

inspection at an operational fuel facility under the direction of a qualified 

inspector. Any unexpected findings or questions that you may have 

should be brought to the attention of the inspector.

TASKS: 1. Observe air samplers in operation and observe routine change-out 

of samples.

2. Discuss the licensee air sampling program, limitations, and resultant 

licensee actions with the licensee individual in charge of the air 

sampling program.

3. Review results of air samples to determine if there were any results 

above action or restriction points. Determine if actions required by 

procedures were taken, including determination of internal dose. 

Determine whether air samples were properly measured utilizing 

calibrated equipment.

4. Review the equipment used to analyze air samplers. Review the 

latest calibration for this equipment. Discuss with the technician the 

process for preparing and analyzing samples.

5. Discuss with the individual in charge of the air sampling program the 

process for determining that lapel and stationary air samplers are 

representative.

6. Meet with your supervisor, the person designated as a resource or a 

qualified Fuel Facility Health Physics inspector to discuss any 

questions you may have as a result of these activities, and to 
Issue Date: 06/20/14 35 1247 Appendix C2

demonstrate that you can meet the evaluation criteria for this OJT.

DOCUMENTATION: Fuel Facility Health Physics Inspector Proficiency Level Qualification 

Signature Card, Item OJT-HP-2.
Issue Date: 06/20/14 36 1247 Appendix C2

Fuel Facility Health Physics Inspector On-the-Job Training

TOPIC: (OJT-HP-3) Bioassay and In-vivo Counting

PURPOSE: The purpose of this training is to familiarize you with bioassay and in-vivo 

counting programs.

COMPETENCY 

AREA: TECHNICAL AREA EXPERTISE

INSPECTION

LEVEL OF

EFFORT: 36 hours

Note: Successful completion of SG-HP-5 is a prerequisite to this training

REFERENCES: References used in SG-HP-5 related to bioassay and in-vivo counting are 

appropriate for this module. Most of the efforts in this OJT will rely on 

licensee procedures and the license application. Any references other 

than licensee procedures will be used to determine the regulatory stance 

that has been historically applied by the NRC for a given situation. 

References selected should support the actual inspection effort.

1. Licensee urine sampling, analysis, and evaluation procedures.

2. Licensee lung counting and internal dose assessment procedures

3. Licensee fecal sampling, analysis, and evaluation procedures.

4. Licensee procedures for actions as a result of internal depositions.

EVALUATION

CRITERIA: Upon completion of this training, you should be able to:

1. Discuss bioassay, and in-vivo counting programs, limitations, and 

resultant licensee actions.

2. Discuss regulatory requirements for bioassay and in-vivo counting 

programs.

3. Describe the calibration techniques used for in-vivo counters.

4. Describe the methods used for urine and fecal sample preparation, 

analysis, and evaluation, including typical action points for LEU and 

HEU.
Issue Date: 06/20/14 37 1247 Appendix C2

5. Describe a routine bioassay and in-vivo counting program, including 

frequency and bases, for-cause sampling or counting, and 

relationship to the air sampling program.

6. Discuss licensee documentation that is used to identify, report and 

track problems involving personnel contaminations, unexpected 

exposures, radiological incidents, and events involving uncontrolled 

or unmonitored internal or external exposure of workers. 

NOTE: The following tasks are to be performed concurrent with 

an inspection at an operational fuel facility under the direction of 

a qualified inspector. Any unexpected findings or questions that 

you may have should be brought to the attention of the 

inspector.

TASKS: 1. Review results of urinalyses and in-vivo counts to determine if there 

were any results above action or restriction points. Determine if 

actions required by procedures were taken, including determination 

of internal dose. Determine whether urine samples or personnel 

were properly measured utilizing calibrated equipment.

2. Review the most recent calibration of the in-vivo counter. Review 

the counting facility and discuss operating procedures with the 

counter operator.

3. Review the equipment used to evaluate urine samples. Review the 

latest calibration for this equipment. Discuss with the technician the 

process for preparing and analyzing samples.

4. Discuss with the individual in charge of the bioassay program the 

process for fecal sampling and analysis.

5. Review air sample results, personnel contaminations, and event 

evaluations to determine if bioassays or lung counts were made per 

the license. Discuss the relationship of bioassay sampling and invivo results to air sampling with the individual in charge of the 

program.

6. Meet with your supervisor, the person designated as a resource or a 

qualified Fuel Facility Health Physics inspector to discuss any 

questions you may have as a result of these activities and to 

demonstrate that you can meet the evaluation criteria for this OJT.

DOCUMENTATION: Fuel Facility Health Physics Inspector Proficiency Level Qualification 

Signature Card, Item OJT-HP-3.
Issue Date: 06/20/14 38 1247 Appendix C2

Fuel Facility Health Physics Inspector On-the-Job Training

TOPIC: (OJT-HP-4) Radioactive Material Transportation

PURPOSE: The purpose of this OJT training is to provide you tasks and information 

that will familiarize you with the inspection requirements contained in 

procedure IP 86740, “Inspection of Transportation Activities”, to allow you 

to independently conduct inspections in this area. The licensee’s 

radioactive material processing and shipping programs are required 10 

CFR Part 20 and 10 CFR Part 71, and DOT’s regulations contained in 49 

CFR Parts 100-189. 

COMPETENCY 

AREA: INSPECTION

TECHNICAL AREA EXPERTISE

LEVEL OF 

EFFORT: 40 hours

REFERENCES: References used in SG-HP-4 are appropriate for this module. Most of the 

efforts in this OJT will rely on licensee procedures and the license 

application. References selected should support the actual inspection 

effort.

1. Licensee licensed material shipping and transportation procedures.

2. Licensee procedures for transportation QA.

EVALUATION 

CRITERIA: Upon completion of the tasks, you should be able to:

1. Discuss the packaging, labeling, and marking requirements for 

various types of radioactive materials packages which are expected 

to be shipped from the facility. Identify in NUREG-1660 and 49 CFR 

the specific labeling and placarding requirements. 

2. Discuss the manifesting and placarding requirements for the various 

types of radioactive materials packages you inspected. Show in 

NUREG 1660 the specific requirements. Discuss conformance with 

NUREG/BR-0204.

3. For typical product and radwaste shipments, identify the allowable 

radiation and contamination dose limits specified in regulatory 

documents 49 CFR 100-189, and compare and contrast them with 

the values the licensee identified. 

4. Discuss the HAZMAT training and emergency response program 
Issue Date: 06/20/14 39 1247 Appendix C2

used by the licensee to meet regulatory requirements. Discuss this 

information relative to guidance in Information Notices 92-62, 92-72, 

95-09, and 49 CFR.

5. Locate Certificates of Compliance (COC) and discuss the checks 

required by the COC before shipment.

6. Discuss the licensee’s corrective action program in the area of 

radioactive material shipping.

NOTE: The following tasks are to be performed concurrent with 

an inspection at an operational fuel facility under the direction of 

a qualified inspector. Any unexpected findings or questions that 

you may have should be brought to the attention of the 

inspector.

TASKS: 1. Review and familiarize yourself with the documents listed in the 

reference list. Specifically, identify the purpose of each document 

and what guidance the document does provide. 

2. Review the licensee’s implementation of the regulations in the area 

of training and emergency response as specified in 49 CFR. 

3. Select at least five non-exempt radioactive materials shipments and 

review for compliance with all appropriate regulatory requirements, 

including conformance with the container certificate of compliance 

for the packages used.

4. Observe the packaging, surveying, labeling, marking, vehicle 

checks, emergency instruction, disposal manifests, shipping papers, 

and loading of a radioactive waste shipment (preferably a nonexempt shipment). Inter-compare your findings with applicable 

regulatory requirements.

5. Review records of (and if possible observe), licensee QA checks of 

a shipment.

6. Review corrective action reports in the area of transportation to 

identify problems in this area and to understand the licensee’s 

corrective action process.

7. Meet with your supervisor, the person designated as a resource or a 

qualified Fuel Facility Health Physics inspector to discuss any 

questions you may have as a result of these activities and to 

demonstrate that you can meet the evaluation criteria for this OJT.

DOCUMENTATION: Fuel Facility Health Physics Inspector Proficiency Level Qualification 

Signature Card, Item OJT-HP-4
Issue Date: 06/20/14 40 1247 Appendix C2

Fuel Facility Health Physics Inspector On-the-Job Training

TOPIC: (OJT-HP-5) Solid Radwaste Management and Processing

PURPOSE: The purpose of this OJT is to provide you tasks and information that will 

familiarize you with the inspection requirements contained in the solid 

radwaste sections of IP 88035, “Radioactive Waste Management,” and IP 

84850, “Radioactive Waste Management - Inspection of Waste Generator 

Requirements of 10 CFR 20 and 10 CFR 61.”

COMPETENCY 

AREA: INSPECTION

TECHNICAL AREA EXPERTISE

LEVEL OF

EFFORT: 40 hours

REFERENCES: References used in SG-HP-5 are appropriate for this module. Most of the 

efforts in this OJT will rely on licensee procedures and the license 

application. References selected should support the actual inspection 

effort.

1. Licensee solid waste processing procedures, including, where 

applicable, incinerator operation, waste sorting, compaction, and 

other processing.

2. Licensee procedures for release of materials for unrestricted use.

EVALUATION 

CRITERIA: Upon completion of the tasks, you should be able to describe the 

inspection requirements contained in the solid radwaste sections of IP 

88035, “Radioactive Waste Management,” and IP 84850, “Radioactive 

Waste Management - Inspection of Waste Generator Requirements of 10 

CFR 20 and 10 CFR 61.”

NOTE: The following tasks are to be performed concurrent with an 

inspection at an operational fuel facility under the direction of a 

qualified inspector. Any unexpected findings or questions that you 

may have should be brought to the attention of the inspector.

TASKS: 1. Review and familiarize yourself with the documents listed in the 

reference list. Specifically, identify the purpose of each document 

and what guidance the document does provide. 

2. Review the contents of the licensee’s program for use of scaling 

factors for hard to detect nuclides, and the waste form and 
Issue Date: 06/20/14 41 1247 Appendix C2

characteristics requirements for disposal of solid radioactive waste. 

Identify how the licensee quantifies those radionuclides listed in 10 

CFR Part 61 Tables 1 and 2.

3. Review the requirements for the transfer of radioactive material 

contained in licensee procedures and compare that with 

requirements contained in 10 CFR Part 20 and license conditions.

4. Review the burial license requirements for a low-level radioactive 

waste disposal facility used by the licensee and discuss the specific 

requirements, in the area of waste characteristics, for burial of the 

waste.

5. Review the requirements for determination of the quantity of 

material in waste shipment containers (such as drum monitors). 

Discuss the limitations on such determinations.

6. Review operation of a box or drum compactor.

7. Review operation of an incinerator.

8. Review corrective action reports in the area of radioactive waste 

processing to identify problems in this area and to understand the 

licensee’s corrective action process.

9. Discuss the calibration technique for radiation instruments used to 

screen and clear potentially contaminated materials/articles (e.g., a 

small article monitor [SAM] and a bag monitor) based on IE Circular 

81-07 and IE Information Notice 85-92.

10. Meet with your supervisor, the person designated as a resource or a 

qualified Fuel Facility Health Physics inspector to discuss any 

questions you may have as a result of these activities and to 

demonstrate that you can meet the evaluation criteria for this OJT.

DOCUMENTATION: Fuel Facility Health Physics Inspector Proficiency Level Qualification 

Signature Card, Item OJT-HP-5
Issue Date: 06/20/14 42 1247 Appendix C2

Fuel Facility Health Physics Inspector On-the-Job Training

TOPIC: (OJT-HP-6) Radiological Environmental Monitoring Program (REMP)

PURPOSE: The purpose of this OJT is to provide you with tasks and information that 

will familiarize you with the inspection requirements contained in IP 88045, 

“Effluent Control and Environmental Protection,” to allow you to 

independently conduct inspections in these areas. The NRC requires that 

licensees ensure adequate protection of public health and safety from 

exposure to radioactive material released to the public domain as a result 

of routine operations. The REMP is required by the license and 

application and supplements the effluent monitoring program by verifying 

that the measurable concentrations of radioactive materials and levels of 

radiation in the environment are in agreement with the values predicted by 

the radioactive effluent monitoring program and Environmental Report. 

COMPETENCY

AREA: INSPECTION

TECHNICAL AREA EXPERTISE

LEVEL OF

EFFORT: 40 hours

REFERENCES: References used in SG-HP-6 are appropriate for this module. Most of the 

efforts in this OJT will rely on licensee procedures and the license 

application. References selected should support the actual inspection 

effort.

1. Licensee environmental sampling, monitoring, and evaluation 

program procedures.

2. Licensee procedures for decontamination and decommissioning, if 

applicable.

EVALUATION

CRITERIA: Upon completion of the tasks, you should be able to:

1. Discuss the environmental sampling techniques (water, milk, air 

iodine, air particulate, vegetation, fish, and soil/sediment) that you 

inspected.

2. Discuss the radiological environmental conditions in the 

surroundings of the facility, including any indications of onsite 

contamination, offsite positive results, and groundwater conditions.
Issue Date: 06/20/14 43 1247 Appendix C2

3. Discuss the different measuring techniques (proportional counter, 

gamma spectroscopy, liquid scintillation counter, and TLD reader) 

that you inspected. Compare and contrast the methods.

4. Discuss data reduction techniques used by the licensee, including 

MDA and LLD.

5. Discuss the Laboratory’s QA Policy and QC implementation, 

including inter-laboratory and intra-laboratory comparisons.

6. Discuss the Meteorological Monitoring Program, including 

calibration methodology for wind direction, wind speed, and delta 

temperature.

7. Discuss the licensee’s determination of the characteristics of 

atmospheric dispersion; χ/Q, D/Q, and annual average data.

NOTE: The following tasks are to be performed concurrent 

with an inspection at an operational fuel facility under the 

direction of a qualified inspector. Any unexpected findings or 

questions that you may have should be brought to the attention 

of the inspector.

TASKS: 1. Review and become familiar with the documents listed in the 

reference list.

2. Review the REMP section from the license application.

3. Review the radiological measurement instrument data (proportional 

counter, gamma spectroscopy, liquid scintillation counter, and TLD 

reader).

4. Review the counting statistics used by the licensee, including MDA 

and LLD.

5. Review and evaluate the radiological analytical methodology for 

isotopic uranium, total uranium, plutonium, technetium-99, ambient 

radiation (using TLD), and gross alpha and beta. Compare the 

licensee’s techniques to standard analytical techniques. 

6. Review and evaluate the meteorological monitoring requirements 

and evaluate the adequacy of the calibration results for wind 

direction, wind speed, and delta temperature.
Issue Date: 06/20/14 44 1247 Appendix C2

7. Conduct walk downs of selected REMP sampling stations such as 

the meteorological monitoring tower, air sampling location, stream 

sampler location. If possible, accompany a technician during 

sample acquisition.

8. Review the man-made and natural radiation exposure pathways 

(licensed materials and the source of the natural background 

radiation). Evaluate how the licensee takes these into consideration 

when analyzing its samples.

9. Review corrective action reports in the area of radiological 

environmental monitoring and radioactive material controls to 

identify problems in this area and understand the licensee’s 

corrective action process.

10. Meet with your supervisor, the person designated as a resource or a 

qualified Fuel Facility Health Physics inspector to discuss any 

questions you may have as a result of these activities and to 

demonstrate that you can meet the evaluation criteria for this OJT.

DOCUMENTATION: Fuel Facility Health Physics Inspector Proficiency Level Qualification 

Signature Card, Item OJT-HP-6
Issue Date: 06/20/14 45 1247 Appendix C2

Fuel Facility Health Physics Inspector On-the-Job Training

TOPIC: (OJT-HP-7) Radioactive Airborne and Liquid Effluent Treatment and 

Monitoring Systems

PURPOSE: The purpose of this OJT is to provide you tasks and information that will 

familiarize you with the liquid and airborne effluent inspection requirements 

contained in IP 88035, “Radioactive Waste Management,” to allow you to 

independently conduct inspections in this area. Inspections are to 

determine whether radiation dose to the public is to be below the 10 CFR

Part 20 and 40 CFR Part 190 limits, where applicable.

COMPETENCY

AREA: INSPECTION

TECHNICAL AREA EXPERTISE

LEVEL OF

EFFORT: 90 hours

REFERENCES: References used in SG-HP-7 are appropriate for this module. Most of the 

efforts in this OJT will rely on licensee procedures and the license 

application. References selected should support the actual inspection 

effort.

1. Licensee liquid and airborne control and processing procedures.

EVALUATION

CRITERIA: Upon completion of the tasks, you should be able to:

1. Discuss the conformance of the facility’s liquid radioactive and 

airborne effluent processing systems, and their operation, with that 

described in the license application.

2. Discuss your review of recent changes to radioactive waste 

processing systems and if the changes were in accordance with 10 

CFR Part 50.59. Discuss the licensee’s estimates of doses to 

members of the public for these changes.

3. Discuss the effluent sampling techniques (water, air iodine, and air 

particulate) that you inspected. Compare and contrast the 

capabilities and limitations of each method.

4. Discuss the different measuring techniques (proportional counter, 

gamma spectroscopy, and liquid scintillation counter) that you 

inspected and compare and contrast their capabilities and 

limitations.
Issue Date: 06/20/14 46 1247 Appendix C2

5. Discuss data reduction techniques, including MDA and LLD. Verify 

licensee MDA and LLD calculations for each release pathway. 

6. Discuss the radioactive liquid treatment, monitoring, and sampling 

systems and the effluent release pathways, and compare them to 

those in the license application.

7. Discuss the radioactive airborne effluent treatment, monitoring, and 

sampling systems, and compare them to those in the license 

application. Discuss the air cleaning systems and their functions 

(e.g., HEPA filters, scrubbers).

NOTE: The following tasks are to be performed concurrent with an 

inspection at an operational fuel facility under the direction of a 

qualified inspector. Any unexpected findings or questions that you 

may have should be brought to the attention of the inspector.

TASKS: 1. Review and become familiar with the documents listed in the 

reference list.

2. Locate a copy of the air cleaning system section from the license 

application. Conduct walk downs of as much of the facility as 

possible. Compare your observations with descriptions in the 

license application.

3. Identify the various sources of liquid and gaseous radwaste, waste 

streams, and technologies associated with liquid and gaseous 

radwaste processing for the facility. Compare your observations 

with descriptions in the license application.

4. Locate a copy of the liquid radwaste section from the license 

application. Conduct walkdowns (considering ALARA and safety 

constraints) of as much of the facility’s liquid radwaste processing 

systems as possible. Assess the licensee’s conformance of the 

facility with the license application.

5. Identify the various sources of liquid radioactive waste, waste 

streams, and technologies associated with liquid radioactive waste 

processing for the facility.

6. Review and evaluate the public dose calculation made by the 

licensee.

7. Review and evaluate the results of a recent in-place HEPA test and 

observe such a test if possible.
Issue Date: 06/20/14 47 1247 Appendix C2

8. Review and understand the radioactive liquid release permits.

9. Review and understand the Annual Radioactive Effluent Release 

Report.

10. Review corrective action reports in the area of radioactive gaseous 

and liquid effluent and monitoring systems to identify problems in 

this area and to understand the licensee’s corrective action process.

11. Meet with your supervisor, the person designated as a resource or a 

qualified Fuel Facility Health Physics inspector to discuss any 

questions you may have as a result of these activities and to

demonstrate that you can meet the evaluation criteria for this OJT.

DOCUMENTATION: Fuel Facility Health Physics Inspector Proficiency Level Qualification 

Signature Card, Item OJT-HP-7
Issue Date: 06/20/14 48 1247 Appendix C2

Fuel Facility Health Physics Inspector Technical Proficiency Level

Signature Card and Certification

Inspector Name: ________________________________

Employee

Initials / Date

Supervisor’s 

Signature / Date

A. Training Courses

Health Physics Technology (H-201)

Transportation of Radioactive Materials (H-308)

Fire Protection for Fuel Cycle Facilities Self-Study (F206S)

B. Study Guides (SG)

(SG-HP-1) Code of Federal Regulations (CFRs)

(SG-HP-2) Licensee Documents for Health Physics 

Inspectors

(SG-HP-3) Worker Radiation Protection

(SG-HP-4) Radioactive Material Transportation

(SG-HP-5) Solid Radwaste Management and 

Processing

(SG-HP-6) Radiological Environmental Monitoring 

Program (REMP)

(SG-HP-7) Radioactive Airborne and Liquid Effluent 

Treatment and Monitoring Systems

C. On-the-Job Training (OJT) Activities

(OJT-HP-1) Internal and External Dose Controls

(OJT-HP-2) Air Sampling Program

(OJT-HP-3) Bioassay and In-vivo Counting 

(OJT-HP-4) Radioactive Material Transportation

(OJT-HP-5) Solid Radwaste Management and 

Processing

(OJT-HP-6) Radiological Environmental Monitoring 

Program (REMP)

(OJT-HP-7) Radioactive Airborne and Liquid Effluent 

Treatment and Monitoring Systems

Supervisor’s signature indicates successful completion of all required courses and activities 

listed in this journal and readiness to appear before the Oral Board.

Supervisor’s Signature: ________________________________ Date: _____________
Issue Date: 06/20/14 49 1247 Appendix C2

This signature card and certification must be accompanied by Form 1, Fuel Facility Health 

Physics Inspector Technical Proficiency Level Equivalency Justification, if applicable.

Copies: Inspector

HR Office

Supervisor
Issue Date: 06/20/14 50 1247 Appendix C2

Form 1: Fuel Facility Health Physics Inspector Technical Level Proficiency Justification

Inspector Name:

____________________________

Identify equivalent training and experience 

for which the inspector is to be given 

credit.

A. Training Courses

Health Physics Technology (H-201)

Transportation of Radioactive Materials (H-308)

Fire Protection for Fuel Cycle Facilities SelfStudy (F-206S)

B. Study Guides (SG)

(SG-HP-1) Code of Federal Regulations 

(CFRs)

(SG-HP-2) Licensee Documents for Health 

Physics

 Inspectors

(SG-HP-3) Worker Radiation Protection

(SG-HP-4) Radioactive Material Transportation

(SG-HP-5) Solid Radwaste Management and 

Processing

(SG-HP-6) Radiological Environmental 

Monitoring Program (REMP)

(SG-HP-7) Radioactive Airborne and Liquid 

Effluent

 Treatment and Monitoring Systems

C. On-the-Job Training (OJT) Activities

(OJT-HP-1) Internal and External Dose Controls

(OJT-HP-2) Air Sampling Program

(OJT-HP-3) Bioassay and In-vivo Counting 

(OJT-HP-4) Radioactive Material Transportation

(OJT-HP-5) Solid Radwaste Management and 

Processing

(OJT-HP-6) Radiological Environmental 

Monitoring 

 Program (REMP)
Issue Date: 06/20/14 51 1247 Appendix C2

(OJT-HP-7) Radioactive Airborne and Liquid 

Effluent Treatment and Monitoring Systems

Supervisor’s Recommendation: ______________________________ Date: __________

Division Director’s Approval: _________________________________ Date: __________

Copies to: Inspector 

 HR Office

 Supervisor
Issue Date: 06/20/14 Att1-1 1247 Appendix C2

Attachment 1

Revision History for IMC 1247 Appendix C-2

Commitment 

Tracking 

Number

Accession 

Number

Issue Date

Change Notice

Description of Change Description of 

Training Required 

and Completion Date

Comment and 

Feedback Resolution 

Accession Number

N/A 02/18/09

CN 09-006

Researched commitments for 4 years and 

found none.

New inspection manual chapter to specify 

qualification requirements for NRC fuel 

facility operations, health physics, 

emergency preparedness, security, 

material control and accounting, and 

construction inspectors.

N/A ML090400794

N/A ML13217A216

06/20/14

CN 14-013

This document has been revised to update 

required and refresher training 

requirements. Some of the trainings have

been replaced or removed because they 

are no longer offered. OSHA HAZWOPER 

course has been moved to IMC 1247 App 

A.

None ML14084A480