**IMC 1248, Appendix H**

**Training Requirements and Qualification Journal for Uranium Recover Inspectors**

1246, APPENDIX B	XII-30	Issue Date: 01/05/01

**APPENDIX H**

**TRAINING REQUIREMENTS FOR**

**URANIUM RECOVERY INSPECTORS**

A. APPLICABILITY

The training described below is required for all uranium recovery inspectors assigned to perform uranium recovery inspection at uranium mill sites.

B.	TRAINING

1.	Required Initial Training

a.	Self Study and On-the-Job Training

(1)	NRC Orientation

(2)	Code of Federal Regulations

(3)	Office Instructions

(4)	Regulatory Guidance

(5)	NRC Inspection Manual

(6)	Industry Codes and Standards

(7)	Inspection Accompaniments

(8)	NRC Management Directives

(9)	Review of Significant Events at Uranium Recovery Facilities

b.	Core Training. These courses establish minimum formal classroom training requirements.  Refer to Section 1248-11 for exceptions to these requirements. 

(1)	Fundamentals of Inspection Course (G-101) or Inspection Procedures Course (G-108)

(2)	Root Cause/Incident Investigation Workshop (G-205)

(3)	Inspecting for Performance Course - Materials Version (G-304)

(4)	Effective Communications for NRC Inspectors

(5)	OSHA Indoctrination Course (G-111)

(6)	NMSS Radiation Worker Training (H-102)

Issue Date:  04/19/13	 H-1	1248

(7)	General Health Physics Practices for Uranium Recovery Course (F-104) or General Health Physics Practices for Fuel Cycle Facilities Directed Self-Study Course (F-102S)

(8)	NRC Inspection Team Leader Workshop

c.	Specialized Training.  Depending on the employee's previous work experience and planned activities, additional courses may be required in order to gain knowledge necessary for specialized inspection activities.  Management will make this determination on an individual basis.

2.	Supplemental Training.  Additional training beyond that identified as Core Training.  This training will be determined by the individual's supervisor and will depend on the individual's previous work experience and planned inspection activities in specific areas.

3.	Refresher Training.  Refresher training will be conducted every three years following initial certification.  Refresher training will include the following:

(1)	Fundamentals of Inspection Refresher Course (G-102)

							END

Issue Date:  04/19/13	 H-2	1248

	URANIUM RECOVERY INSPECTOR

	NRC INSPECTOR QUALIFICATION JOURNAL

Applicability

This NRC Inspector Qualification Journal implements NRC Manual Chapter 1248, by establishing the minimum training requirements for personnel assigned to perform safety inspection activities at uranium recovery facilities.  The Qualification Journal must provide traceable documentation to show that minimum requirements are met for each inspector.

The NRC Inspector Qualification Journal consists of a series of qualification guides and signature cards.  Each signature card is used to document task completion, as indicated by the appropriate signature blocks.  Each signature card has a corresponding qualification guide which establishes the minimum knowledge levels or areas of study that must be completed for each signature card. 

Most of the qualification guides are divided into sections.  The review sections of the qualification guides identify references with general application to the inspector's qualification.  The inspector is expected to have a general familiarity with these references.  Other sections of the qualification guides identify specific references that have direct application to an inspection discipline.  The inspector is expected to demonstrate detailed knowledge of the inspection discipline specific references.

In order to support the review of upper tier documents, programs, and policies, the inspector's First Line Supervisor will assign one or more uranium recovery facilities as reference facilities.  The selection of a reference facility is intended to provide the inspector's management with the ability to tailor the qualification process to the experience and training level of the inspector, and to meet the inspection needs of the NRC.  The use of specific real world material will reinforce the qualification process.

Issue Date:  04/19/13	H-34	1248

INSPECTOR QUALIFICATION JOURNAL

	Uranium Recovery Inspector

Name                            Title                       Branch       Section

To complete your qualification as a Uranium Recovery Inspector you are to complete the following signature cards.  All signoffs shall include the signature of the responsible reviewer and the date.  Maintain these cards in a notebook along with any background or written material required by the program.  This notebook will comprise your NRC Inspector Qualification Journal.

Signature When CompleteDate

 1.	NRC Orientation				_____

First Line Supervisor

 2.	Code of Federal Regulations		               _____

First Line Supervisor

 3.	Office Instructions				_	     _____

First Line Supervisor		

 4.	Regulatory Guidance			       _	     _____

First Line Supervisor

 5.	NRC Inspection Manual  			_      _____

Chapters (MC)				First Line Supervisor

 6.	Industry Codes and Standards		_	      _____

First Line Supervisor

 7.	Inspection Accompaniments		       _	      _____

First Line Supervisor  

 8.	NRC Management Directives		       _	      _____

First Line Supervisor

 9.    Review of Significant Events at

      Uranium Recovery Facilities and/

or Facilities for Disposal of Non-

Atomic Energy Act of 1954, Section

11e.(2) Byproduct Material			__	_____

First Line Supervisor

10.	Formal Training

__	_____	

First Line Supervisor

Qualification Board	

Requirement met                                        _____

Second Level Supervisor

or Board Chairman

Recommended as a qualified

Uranium Recovery Inspector                       ____      _____ 

Second Level Supervisor

Certification Memo issued                         _____________      _____

Second Level Supervisor

Qualification Card 1

NRC Orientation

A.     Site Orientation                                    Initials Date

1.	New employee processing			__________________	_____

package completed				Employee

2.     Facility tour and introduction		_____________________	_____

First Line Supervisor 

B.	NRC Organization

1.	Review of NRC headquarters

and NMSS organization			___________________	_____

Employee

2.     Discussion of NRC organization	_____________________	_____

First Line Supervisor 

Qualification Card 2

Code of Federal Regulations (CFR)

InitialsDate

A.	Familiarization with selected

CFR parts completed					___________________	_____

Employee

B.	Discussion completed on CFR parts

related to Uranium Recovery program		_____________________	_____

First Line Supervisor

	Qualification Card 3

	Office Instructions

InitialsDate

A.	Familiarization with office

policies and procedures                      _______________          _____

                                                     Employee

B.	Discussion completed on office

policies and procedures                      _________________        _____

                                                     First Line Supervisor

	Qualification Card 4

	Regulatory Guidance

InitialsDate

A.	Review of selected regulatory guidance

1.	Regulatory Guides				__________________	_____

Employee

2.	Information Notices/

Bulletins					__________________	_____

Employee

3.	NUREGs					__________________	_____

Employee

4.	Generic Letters				__________________	_____

Employee

5.    Federal Register Notices	__________________	_____

Employee

6.    Policy and Guidance Directives	__________________	_____

Employee

7.   NRC Branch Technical Positions	__________________	_____

Employee

8.   SECY Papers					__________________	_____

Employee

B.	Discussion of regulatory guidance

with application to the Uranium

Recovery program					_____________________	_____

First Line Supervisor 

	Qualification Card 5

	NRC Inspection Manual Chapters (MC)

InitialsDate

A.	Review of appropriate NRC

MCs completed

__________________	_____

Employee

B.	Discussion of NRC MCs and 

their relation to the Uranium

Recovery inspection program	_____________________	_____

First Line Supervisor

	Qualification Card 6

	Industry Codes and Standards

InitialsDate

A.	Review of selected Codes

and Standards completed				___________________	_____

Employee

B.	Discussion of the application

of Codes and Standards related

to the Uranium Recovery program		_____________________	_____

First Line Supervisor

Qualification Card 7

Inspection Accompaniments

InitialsDate

A.	Inspections completed

1.	____________________	______________		______

Facility			Employee

2	_________________		______________		______

Facility				Employee

3	____________________	______________		_____

Facility				Employee

4.	____________________	______________		______

Facility				Employee

B.	Discussion of inspection and 

employee's role	

1.	____________________		_____________________	_____

Facility					First Line Supervisor

2.	____________________		_____________________	_____

Facility					First Line Supervisor

3.	____________________		_____________________	_____

Facility					First Line Supervisor

4.	____________________		_____________________	_____

Facility					First Line Supervisor

	Qualification Card 8

	NRC Management Directives

InitialsDate

A.	Review of selected portions of

the NRC Management Directives 

completed						_________________	       _____

Employee

B.	Discussion of the application

of the NRC Management Directives

to the Uranium Recovery inspection

program						_____________________	_____

First Line Supervisor

	Qualification Card 9

	Review of Significant Uranium Recovery Events 

Initials				Date

A.	Review of selected significant

historical events					__________________	_____

Employee

B.	Discussion of the importance

of these events and lessons

learned						_____________________	_____

First Line Supervisor

	Qualification Card 10

	Formal Training

A. CORE TRAINING:                                   InitialsDate

1.	Fundamentals of Inspection

Course (G-101) or Inspection			       ____________________	_____

Procedures Course (G-108)	Training Coordinator

2.     Root Cause/Incident Investigation 	____________________	_____

Workshop (G-205)					Training Coordinator

3.     Inspecting for Performance	____________________	_____

Course - Materials Version (G-304)		Training Coordinator

4.     Effective Communications for NRC	____________________	_____

Inspectors		Training Coordinator

5.	OSHA Indoctrination Course (G-111)		        ____________________	_____

Training Coordinator

6.	NMSS Radiation Worker Training

Course (H-102)	____________________	_____

Training Coordinator

7.	General Health Physics Practices for

Uranium Recovery Course (F-104) or

General Health Physics Practices for	

Fuel Cycle Facilities Directed Self-

Study Course (F-102S)		____________________	_____ 

Training Coordinator

8.	NRC Inspection Team Leader Workshop	        ____________________	_____

Training Coordinator

B. SPECIALIZED TRAINING

Other specialized training/courses required for inspectors performing inspection in specific areas:

Course Title         Course or     InitialsInitialsDate

Training

____________	_________	___________	        ________________  ____

Supervisor		Training Coordinator

____________	_________	___________	        ________________  ____

Supervisor		Training Coordinator

____________	_________	___________	        ________________  ____

Supervisor	  	Training Coordinator

____________	_________	___________	        _______________    ____

Supervisor		Training Coordinator

	Qualification Guide 1

	NRC Orientation

 A.	Site Orientation

1.	The qualifying individual should read and complete, as appropriate, the following forms for processing into the NRC:

a.	Personnel information

b.	Health insurance elections

c.	Retirement plan elections

d.	Savings elections (e.g. U.S. Savings Bonds, TSP, etc.)

e.	Fitness for Duty requirements and physical examination

f.	Any other forms which may be required by NRC Office

of Human Resources

g.	Forms for issuance of tagged, controlled NRC equipment

h.	Payroll forms and time cards

i.	Regulatory Information Tracking System (RITS)

2.	The First Line Supervisor should orient the qualifying individual to the facility as follows:

a.	Tour the facility and introduce the qualifying individual to the staff

b.	Indicate to the qualifying individual the location of controlled documents, reference material, supplies, office equipment, etc.

B.	NRC Organization

1.	The qualifying individual should review and become familiar with:

a.	Organizational charts of region, NMSS, and headquarters and overall NRC organization (NUREG 0325)

b.	Role of Headquarters in policy and interpretation of regulations

c.	Role of NRC General Counsel

d.	Role of NRC Inspector General

e.	Role of NRC Public Affairs

f.	Role of NRC Office of Investigations

g.	Role of NRC Office of Enforcement

h.	Physical location of NRC offices and regions

i.	Role of NRC as a regulatory agency 

(1)	10 CFR Part 1 (Organization)

(2)	Atomic Energy Act of 1954, as amended

(3)	Energy Reorganization Act of 1974, as amended

(4)	NRC Enforcement Policy (NUREG 1600)

(5)	Incident Response Plan (NUREGs 0728 and 0845) 

 			(6)	Energy Policy Act of 1992

2.	The First Line Supervisor should discuss NRC organization and role with the qualifying individual to ensure the qualifying individual has a full understanding of NRC's organization and mission and the role of the inspector in that mission.

	Qualification Guide 2

	Code of Federal Regulations (CFR)

A.	A selection of currently applicable CFR Parts should be made by the First Line Supervisor. The selection should include the references listed below and be documented.  The qualifying individual should be expected to have a general knowledge of the topics addressed in the references.  This review may be accomplished by self-study, study-quizzes, briefings, or discussions. 

1.	10 CFR Part 1		Statement of organization and general information

2.     	10 CFR Part 2	Rules of practice for domestic licensing proceedings and issuance of orders

3.	10 CFR Part 9		Public Records

4.     	10 CFR Part 19	Notices, instructions and reports to workers; inspections

5.     	10 CFR Part 20  	Standards for protection against radiation (includes selected Questions and Answers, Q & As)

6.	10 CFR Part 21 	Reporting of defects and noncompliance

7.     	10 CFR Part 30  	Rules of general applicability to domestic licensing of byproduct material

8.	10 CFR Part 40  	Domestic licensing of source material

9.     	10 CFR Part 51	Environmental protection regulations for domestic licensing and related regulatory functions

10.    	29 CFR Part 1910	General Industry Standards - Respiratory Protection

(29 CFR1910.134)

11.    	30 CFR Part 828	Special Permanent Program Performance Standards - 

In-Situ Processing

12.    	40 CFR Part 141	National Primary Drinking Water Regulations

13.    	40 CFR Part 192	Health and Environmental Protection Standards for Uranium and Thorium Mill Tailings

B.	Following completion of the qualifying individuals self study of the listed CFR Parts, a discussion will be held with the qualifying inspector by the First Line Supervisor to test the qualifying individuals knowledge of these Parts.  To the extent possible, recent application of various sections, new regulatory initiatives, and current industry issues should be emphasized.

Qualification Guide 3

Office Instructions

A.	NMSS Office Policies and Procedures

1.	Read the NMSS Policy and Procedures Letters (PPLs)

1-8	Differing Professional Views and Opinions

1-11	Communications with Licensees

1-19	Notification of Regional Administrators

1-22	Quality Assurance

1-23 	Open Meetings

1-24 	Office of Investigation and the release of information on investigations/inspections

1-27	Management of Allegations

1-40	Legislative and Regulatory Review Requirements for the Office of the Inspector General

1-42	Radiation Protection Procedures for NMSS Employees

2. The qualifying individual should review the NMSS policies and

practices on:

a.	Travel, including Management Directive 14.1 Official Temporary Duty Travel

b.	Telephone use

c.	Policies on use of annual leave and sick leave and excused

leave, including Bulletin 4135, Leave Administration

d.	Work schedule, including NRC Appendix 4136, Hours of work and

Premium Pay

e. Use of government equipment, including computers (NUDOCS and ADAMS) and Management Directive 13.1, Property Management

f.	Union activities, including Management Directive 10.102, Labor-

Management Relations Program for Federal Employees

g.	Communications outside NRC

h.	Policies on outside employment and acceptance of gifts

i.	Participation in political activities

j.	Routing of mail and procedures for sending mail and materials (via U.S. Mail, Federal Express, etc.), including Management Directive 3.23, Mail Management

k.	Ordering of documents (e.g NUREGs)

l.	NMSS emergency and evacuation procedures

m.	Employee appraisal system and Individual Development Plan (IDP)

(1) 	Employee trial period (Management Directive 10.14

Employment and Staffing)

(2)	Employee appraisals (Management Directive 10.67 (Non-SES Performance Appraisal System)

n.	Differing Professional Views or Opinions (Management Directive

10.159, General Personnel Management Provisions)

o.	NMSS Delegation of Authority (September 18, 1995)

B.	The First Line Supervisor should discuss these policies and practices with the qualifying individual to ensure that the qualifying individual has a full and complete understanding. 

	Qualification Guide 4

	Regulatory Guidance

A.	A selection of currently applicable regulatory guidance should be identified by the First Line Supervisor.  These references should include those listed below and should be documented. The qualifying individual should be expected to have a general knowledge of the topics addressed in the references. The review may be accomplished by self-study, study-quizzes, briefings, or discussions.  Note that many Regulatory Guides reference or endorse industry codes and standards listed in Qualification Guide 6.  Study of corresponding and subtier codes and standards is recommended. 

1.	Regulatory Guides (use latest revision)

3.11	Design, Construction, and Inspection of Embankment Retention Systems for Uranium Mills

3.56	General Guidance for Designing, Testing, Operating and Maintaining Emission Control Devices at Uranium Mills

3.59	Methods for Estimating Radioactive and Toxic Airborne Source Terms for Uranium Milling Operations

3.63	Onsite Meteorological Measurement Program for Uranium Recovery Facilities-Data Acquisition and Reporting

3.64	Calculation of Radon Flux Attenuation by Earthen Uranium Mill Tailings Covers

4.14	Radiological Effluent and Environmental Monitoring at Uranium Mills

4.15	Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment

8.2	Guide for Administrative Practices in Radiation Monitoring

8.7	Instructions for Recording and Reporting Occupational Radiation Exposure Data

8.9	Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program

8.10	Operating Philosophy for Maintaining Occupational Radiation Exposures As Low As Is Reasonably Achievable

8.11	Applications of Bioassay for Uranium

8.13	Instruction Concerning Prenatal Radiation Exposure

8.15	Acceptable Programs for Respiratory Protection

8.22	Bioassay at Uranium Mills

8.25	Air Sampling in the Workplace

8.29	Instruction Concerning Risks from Occupational Radiation Exposure

8.30	Health Physics Surveys in Uranium Mills

8.31	Information Relevant to Ensuring that Occupational Radiation Exposures at Uranium Mills Will Be As Low As Reasonably Achievable

8.34	Monitoring Criteria and Methods to Calculate Occupational Radiation Doses

8.36	Radiation Dose to the Embryo/fetus

8.37	ALARA Levels for Effluents from Material Facilities

10.1	Compilation of Reporting Requirements for Persons Subject to NRC Regulations

ES 114-4	Guidelines for Groundwater Monitoring at In-Situ Uranium Solution Mines

Others as selected by the First Line Supervisor

2.	Information Notices (IN) and Bulletins (BL)

IN 93-60	Reporting Fuel Cycle and Materials Events to the NRC Operations Center, Supplement 1

IN 94-023	Guidance to Hazardous, Radioactive and Mixed Waste Generators on Elements of Waste Minimization

IN 95-055	Handling Uncontaminated Yellowcakes Outside of Facility Processing Circuit

IN 96-047	Record Keeping, Decommissioning Notifications for Disposals of Radwaste by Land Burial

IN 97-050	Contaminated Lead Products

IN 97-055	Calculation of Surface Activity for Contaminated Equipment & Materials

IN 97-057	Leak Testing of Packaging used in Transport of Radioactive Material

IN 97-058	Mechanical Integrity of In-Situ Leach Injection Wells & Piping

Others as selected by the First Line Supervisor

3.	NUREGs (latest revision, where applicable)

NUREG 0325	NRC Functional Organization Chart

NUREG 1569	Draft Standard Review Plan (SRP) for In Situ Leach Uranium Extraction License Applications

NUREG-1600	General Statement of Policy and Procedures for NRC Enforcement Actions

NUREG 1621	Final SRP for the Review of Remedial Action of Inactive Mill Tailings Sites under Title I of the UMTRCA

NUREG/CR-4884	Interpretation of Bioassay Measurements

NUREG/CR-5849	Manual for Conducting Radiological Surveys in Support of License Termination

NUREG/CR-6232	Assessing the Environmental Availability of Uranium in Soils and Sediments

Others as selected by the First Line Supervisor

4.	Generic Letters (GL)

97-03	Annual Financial Surety Update Requirements for Uranium Recovery Licensees

Others as selected by the First Line Supervisor.

5.	Federal Register Notices

60 FR 49296	Final Revised Guidance on Disposal of Non-Atomic Energy Act of 1954, Section 11e.(2) Byproduct 

	Material in Tailings Impoundments (September 22, 1995)

Others as selected by the First Line Supervisor.

6.	Policy and Guidance Directives (PGD)

PGD 8-01	Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Byproduct, Source, and Special Nuclear Material Licensees, November 1983

UR 90-03	Memorandum of Understanding Between the U.S. Department of Energy and the NRC, November 1990

UR 91-01	Costs for Fencing Reclaimed Title II Sites, Letter from R.L. Bangart to A.B. Beach, February 1991

UR 91-02	Standard Format for Completion Review Report (CRR), LLUR, June 1991

UR 91-03	Position on Disposal Of In-Situ Wastes, LLWM, September 1991

UR 93-02	Standard Review Plan for the Review of Remedial Action of Inactive Mill Tailings Sites Under Title I of the Uranium Mill Tailings Radiation Control Act, Rev. 1, June 1993

Others as selected by the First Line Supervisor

7.	Branch Technical Position

Alternate Concentration Limits for Title II Uranium Mills (January 1996)

Design of Erosion Protection Covers for Stabilization of Uranium Mill Tailings Sites (August 1990)

Effluent Disposal at Licensed Uranium Recovery Facilities (April 1995)

Others As selected by the First Line Supervisor.

8.	SECY Papers

97-110	Status Report on Implementation of Dam Safety Program (May 29, 1997)

95-155	Review of Previously Approved Reclamation Plans (June 14, 1995)

90-316	Decommissioning Records Plan, Records Management Guidelines (RMG)

Others as selected by the First Line Supervisor.

	Qualification Guide 5

	NRC Inspection Manual Chapters (MC)

A.	A selection of currently applicable NRC MC and Inspection Procedure (IP) references with direct application to the Uranium Recovery inspection should be identified by the First Line Supervisor.  The application of the specific references to the inspection program should be studied in detail by the qualifying individual. 

	1.	 REPORTS/COMMUNICATIONS/FOLLOW-UP

MC 0230	Morning Report

MC 0610	Inspection Reports

MC 0620	Inspection Documents and Records

MC 0720	NRC Bulletins and Information Notices

MC 0801	Inspector Feedback

MC 1120	Preliminary Notifications

IP 92701	Follow-up

IP 92703	Follow-up of Confirmatory Action Letters

2. INSPECTIONS

MC 0300	Announced and Unannounced Inspections

MC 1248	Qualification Programs For Federal and State Materials and 

		Environmental Management Programs

MC 2620	On-Site Construction Reviews of Remedial Actions at Inactive Uranium Mill Tailings Sites (Title I UMTRCA)

MC 2641	In-Situ Leach Facilities Inspection Program

MC 2801	Uranium Mill and 11e.(2) Byproduct Material Disposal Site and Facility Inspection Program

IP 37001	10 CFR 50.59 Safety Evaluation Program

IP 87654	Uranium Mill Site Decommissioning Inspection

IP 88001	On-site Construction

IP 89001	In-Situ Leach (ISL) Facilities

3. INTERACTIONS WITH OTHER FEDERAL AGENCIES

MC 1007	Interfacing Activities between Regional Offices of NRC and OSHA

IP 87102	Maintaining Effluents from Materials Facilities As Low As Is Reasonably Achievable (ALARA) [EPA][footnoteRef:1] [1:  Required for non-sealed source licensees.] 

4. RADIATION PROTECTION

MC 8300	Radiation Protection

IP 83726	Control of Radioactive Materials and Contamination, Surveys, and Monitoring

IP 83728	Maintaining Occupational Exposures ALARA

IP 83750	Occupational Radiation Exposure

IP 83822	Radiation Protection

5. TRANSPORTATION

MC 1330	Response to Transportation Accidents Involving Radioactive Materials

IP 86721	Transportation (Basic)

IP 86740	Inspection of Transportation Activities

IP 86750	Solid Radioactive Waste Management and Transportation of 

Radioactive Materials

6. OTHER

MC 1010	Independent Assessment and Analysis

MC 1100	Notification of Significant Meetings

MC 1201	Conduct of Employees

MC 2900	Performance Appraisal Program

B.		The First Line Supervisor will hold discussions, interviews, or oral quizzes to test the qualifying individual's knowledge and understanding of the application of the selected references to the Uranium Recovery program.

	Qualification Guide 6

	Industry Codes and Standards

A.		A selection of currently applicable industry codes and standards should be identified by the First Line Supervisor.  The qualifying individual should be expected to have a general knowledge of the topics addressed in the references.  This review may be accomplished by self study, study quizzes, briefings, or discussions.  Standards selected should be documented by the First Line Supervisor

B.		The First Line Supervisor should test the qualifying individual's knowledge of application of these codes and standards to the Uranium Recovery program by discussions, interviews, or oral quizzes.

	Qualification Guide 7

	Inspection Accompaniments

A.		Each inspector should accompany certified inspectors on at least four inspections.  At least two of these inspections should be performed at a facility other than the designated lead facility.

B.		The following is a guide for material that should be studied and discussed with the inspector in charge during these inspection accompaniments.  The First Line Supervisor will discuss these items, as appropriate, following each inspection accompaniment.

1.	The Inspection Program

MC 2620	On-Site Construction Reviews of Remedial Actions at Inactive Uranium Mill Tailings Sites (Title I UMTRCA)

MC 2641	In-Situ Leach Facilities Inspection Program

MC 2801	Uranium Mill and 11e.(2) Byproduct Material Disposal Site and Facility Inspection Program

2.	Scheduling and Preparation for Inspections

MC 0300	Announced and Unannounced Inspections

3.	Scope of Inspection

4.	Entrance/Exit Interviews

5.	Conduct of Inspection, Accumulation of Data

6.	Post-inspection Activities of Inspectors

MC 0610	Inspection Reports

MC 0620	Inspection Documents and Records

MC 1100	Notification of Significant Meetings

7.	Morning Reports

MC 0230	Morning Report

8.	Non-routine Licensee Events

MC 1110	Potential Abnormal Occurrences

IP 90714	Nonroutine Reporting Program

Management Directive 8.3 NRC Incident Investigation Program

Management Directive 8.9 Accident Investigation

9.	Preliminary Notification

MC 1120	Preliminary Notifications

10.	Bulletins/Information Notices

MC 0720	NRC Bulletins and Information Notices

MC 0730	Generic Communications Regarding Materials and 

Fuel Cycle Issues

11.	Use of Consultants of NRC

MC 1360 Use of Physician and Scientific Consultants in the Medical 

Consultant Program

Management Directive 10.6 Use of Consultants & Experts

12.	Allegations and Investigations

Management Directive 8.8  Management of Allegations

13.	Communication outside NRC

MC 1007	Interfacing Activities Between Regional Offices of  NRC and OSHA

Management Directive 5.5 Public Affairs Program

Management Directive 3.6 Distribution of Unclassified NRC Staff/Contractor-Generated Reports

	Qualification Guide 8

	NRC Management Directives

A.		A selection of currently applicable NRC Management Directive (MD) references should be identified by the First Line Supervisor.  These references should include those listed below and be documented.  The qualifying inspector should be expected to have a general knowledge of the topics addressed in the references.  This review may be accomplished by self-study, study-quizzes, briefings, or discussions.  The selection should include:

1.	NRC MD 9.1	Organization Management

2.	NRC MD 9.29	Organization and Function of Regional Offices

3.	NRC MD 3.2 	Privacy Act

4.	NRC MD 3.1	Freedom of Information Act

5.	NRC MD 10.130 	Safety and Health Program Under the Occupational Safety and Health Act

6.	NRC MD 10.131	Protection of NRC Employees Against Ionizing Radiation

7.	NRC MD 14.1	Official Temporary Duty Travel

8.	NRC MD 10.159	Differing Professional Views or Opinions

9.	NRC MD 10.42	Hours of Work and Premium Pay

10.	NRC MD 10.43	Time and Attendance Reporting

11.	NRC MD 10.67	Non-SES Performance Appraisal System

12.	NRC MD 10.101	Employee Grievances

NRC MD 8.3	NRC Incident Investigation Program

14.	NRC MD 8.8	Management of Allegations

15.	NRC MD 4.6	License Fee Management Program

16.	NRC MD 5.1	Intergovernmental Consultation

17.	NRC MD 5.2	Memorandum of Understanding With States

18.	NRC MD 5.5	Public Affairs Program

19.	NRC MD 8.11	Review Process for 10 CFR 2.206 Petitions

20.	NRC MD 10.5	Oath of Office

21.	NRC MD 10.160	Open Door Policy

B.		Application of the selected NRC Management Directives to the Uranium Recovery program will be discussed with the qualifying individual by the First Line Supervisor to test the qualifying individual's knowledge.

	Qualification Guide 9

	Review of Significant Uranium Recovery Events

A.		A selection of significant historical related events should be identified by the First Line Supervisor.  These events should be documented and studied in detail by the qualifying individual.

B.		The First Line Supervisor should discuss the selected events in detail with the qualifying individual and go over recommendations made, lessons learned, and changes identified to prevent recurrence. The relevance of the event to the Uranium Recovery program should be stressed.

	Qualification Guide 10

	Formal Training

The standards for each Training Course are provided in the NRC Technical Training Division Course Catalog and will not be duplicated in the Qualification Guide.

Attachment 1

Revision History for IMC 1248, Appendix H

Issue Date:  04/19/13	 Att1-1	1248