APPENDIX B1

TRAINING REQUIREMENTS AND QUALIFICATION JOURNAL FOR

SPENT FUEL STORAGE AND TRANSPORTATION

PROJECT MANAGER AND TECHNICAL REVIEWER

I. **TRAINING REQUIREMENTS**

A.  		Applicability

The training described below is required for all project managers and technical reviewers assigned to perform activities related to spent fuel storage and transportation facilities.  Section II, “Qualification Journal,” of this Appendix includes instructions to complete the requirements for the qualification of a project manger and/or a technical reviewer in the Division of Spent Fuel Storage and Transportation (SFST).

B.	 	Training

		1.	Required Initial Training.

			a)	Self-Study and On-The-Job Training:

				(1)	NRC Orientation.

				(2)	Code of Federal Regulations.

				(3)	NRC Management Directives.

				(4)	NMSS/SFST Orientation Reading.

				(5)	Regulatory Guidance.

				(6)	Formal Training.

				(7)	Directed Review of Selected Case Work.

				(8)	Inspection Accompaniments.

				(9)	Review of Discipline-Specific Documentation.

			b)		Core Training. These courses establish minimum formal classroom training requirements. Refer to Section 1246-09 for exceptions to these requirements.

				(1)	“NMSS Radiation Worker Training” (H-102), or “Site Access Training” (H-100)

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

II. **QUALIFICATION JOURNAL**

A.		Applicability

This of Office Nuclear Material Safety and Safeguards (NMSS) Qualification Journal for the Division of Spent Fuel Storage and Transportation (SFST) (hereafter, the SFST Qualification Journal) implements U.S. Nuclear Regulatory Commission (NRC) Inspection Manual Chapter (IMC) 1246, by establishing the minimum training requirements for a new project manager or technical reviewer in SFST.  These requirements provide a basis of knowledge for:

	1.	Performing technical reviews of various types of radioactive material package and spent fuel storage cask designs;

	2.	Managing license reviews for radioactive material package and spent fuel storage applications; and

	3.	Performing activities associated with the storage of spent fuel.

The SFST Qualification Journal serves as a guideline for the development of a Program Office Qualification Journal, and establishes the minimum training requirements consistent with NRC IMC 1246.  The Program Office Qualification Journal must provide traceable documentation to show that minimum requirements are met for each SFST staff member.  The employees supervisor has the discretion to modify the requirements, as needed, based on the employees previous experience, education, and course availability. The employees supervisor may add, delete, or substitute with alternate material, for course(s) that will not be available during the qualification period.  For exceptions to the SFST qualification process (e.g., grandfathering and individuals qualified under other NRCs divisions), refer to section 8 of the introduction of IMC 1246 and SFST Office Instruction number six (SFST-06).  For post qualification training, refer to section 6 of the introduction of IMC 1246 and Appendix A, of this IMC.

The SFST Qualification Journal consists of a series of qualification cards and signature cards. Each signature card is used to document task completion, as indicated by the appropriate signature block(s).  The corresponding qualification guide establishes the minimum knowledge levels or areas of study that must be completed for each signature card.  Employees to be qualified as project managers (PMs) or technical reviewers (TRs) should follow the guidance in Appendices A and B1, of NRCs IMC 1246, while employees to be qualified as inspectors should follow Appendices A and B2, of IMC 1246.

B.		Discussion

This SFST Qualification Journal contains a qualification summary sheet, qualification guides, and signature cards.  The supervisor should discuss the scope of this SFST Qualification Journal and expected knowledge level, as described later in this SFST Qualification Journal, with the staff member before the staff member starts the qualification process.  Each new staff member should complete signature cards 1 through 8, regardless of assigned work group. Signature Card 9 is specific to the various disciplines of technical reviewers within SFST. The new staff member is expected to complete only the signature card(s) applicable to his/her assigned work group. It may not be necessary to complete every requirement.  At the supervisors discretion, requirements may be deleted, or other requirements added, depending on the new staff members previous experience and/or training, etc.  To support the review of upper-tier documents, programs, and policies, the supervisor should consider assigning the staff member one or more review cases that involve NRC licensees and/or certificate of compliance licensing actions. The staff would work with a PM or Technical Mentor and his/her supervisor, as part of the qualification process. The selection of the case(s) is intended to provide the staff members management with the ability to tailor the qualification process to the experience and training level of the staff member, and to meet SFST’s needs.

The SFST staff member is expected to use the most current version or revision of each document cited in this SFST Qualification Journal.  Most of the documentation is readily available either on the: (1) IMC 1246 (NRCs internal web site); (2) NRCs Agency-wide Documents Access and Management System (ADAMS); or (3) SFST library. Unless otherwise indicated, the staff member is to initial and date each appropriate requirement sign-off and insert the appropriate revision number after the reference.

It is recognized that some of the required formal training courses may not be immediately available. The supervisor may substitute an alternate course, provide another method to meet the requirement, or delete the requirement altogether. Any such change should be documented in this SFST Qualification Journal.  In addition, it should be noted that the supervisor and secretaries will provide each new employee with an NRC indoctrination checklist, apart from this qualification journal.  The purpose of the list is to familiarize the new employee with NRC processes; however, it is not part of the formal qualification program.

The time necessary to complete this SFST Qualification Journal will vary, depending the new staff members previous experience and education.  SFST management expectation is that this qualification journal should be completed within 18 months.  However, the availability of required training courses and the new staff members assigned workload may prolong this anticipated time frame.

NMSS SFST QUALIFICATION SUMMARY SHEET

PROJECT MANAGER AND TECHNICAL REVIEWER

Name: 				____________________________

Position Title:		____________________________

Branch:			____________________________

Date Training Started:	____________________________

Complete the following signature cards for a Spent Fuel Storage and Transportation project manager (PM) or technical reviewer (TR) as they may apply to you.  All sign-offs shall include the signature of the responsible reviewer and the date.  Maintain these cards in a notebook (hard copies of background or written material, required by the program, may also be kept for reference purposes).  This notebook will comprise your NRC PM/TR Qualification Journal.

SIGNATURE CARDS

SupervisorDate

CARD 1.	NRC ORIENTATION 				_____________		________

CARD 2.	CODE OF FEDERAL REGULATIONS	_____________		________

CARD 3.	NRC MANAGEMENT DIRECTIVES	_____________		________

CARD 4.	NMSS/SFST ORIENTATION		_____________		________

			READING

CARD 5.	REGULATORY GUIDANCE			_____________		________

CARD 6.	FORMAL TRAINING				_____________		________

CARD 7.	DIRECTED CASE WORK			_____________		________

CARD 8.	INSPECTION ACCOMPANIMENTS	_____________		________

NMSS SFST QUALIFICATION SUMMARY SHEET

PROJECT MANAGER AND TECHNICAL REVIEWER

(CONT.)

Name: 				____________________________

Position Title:		____________________________

Branch:			____________________________

Date Training Started:	____________________________

SIGNATURE CARDS

SupervisorDate

CARD 9.	REVIEW OF DISCIPLINE-SPECIFIC	_____________		________

			DOCUMENTATION

CARD 9A.	CONTAINMENT/CONFINEMENT		_____________		________

CARD 9B.	CRITICALITY					_____________		________

CARD 9C.	MATERIALS					_____________		________

CARD 9D.	SHIELDING/RAD PROTECTION		_____________		________

CARD 9E.	STRUCTURAL					_____________		________

CARD 9F.	THERMAL						_____________		________

QUALIFICATION BOARD CERTIFICATION

IMC 1246, Section 05.02, Final Qualification Activity, provides guidance on conduct of the Oral Qualification Board that should be used by the Board members.  Additional guidance is provided below, on documenting possible Board outcomes.

Board Recommendations

The Board will document the results of its assessment, in writing, as follows, to the Division Director, each time a Board examines an individual:

	a.	If the Boards assessment is favorable, the recommendation will be to grant Full Qualification.  The individual must complete any areas where he/she requires additional review (look up items) and an assigned member of the Board must verify this completion before forwarding the Boards decision to the division director.

	b.	If the Board has identified areas of weakness requiring formal remediation, the Board will identify the areas for improvement in writing and recommend that the individual appear before a Board for re-examination, when the remediation activities are complete.  The Board and the individuals supervisor will agree on a schedule for re-examination.

	c.	If the Board has identified performance deficiencies that could not be successfully addressed with a remediation effort, the Board will document the full scope of the deficiencies and recommend that the individual not be remediated nor re-examined.

	d.	A copy of each Qualification Boards results, identifying any weaknesses and deficiencies, will be placed in the individuals personnel file.  The employee will receive a copy of the Boards findings and recommendation. 

Re-examination Board:  A Re-examination Board must include at least one individual from the original Board.  The Board questioning during re-examination will focus on only the areas of identified weakness.

Board Documentation:  The Boards decisions are forwarded to the Division Director, for information.  The form on the following page shall be used to document the Boards decision.

RESULT OF QUALIFICATION BOARD

FOR PROJECT MANAGER OR TECHNICAL REVIEWER

Date of Oral Board:  ________________

Successful or Unsuccessful (circle outcome) Completion of Oral Board:

________________________		______________

Chairperson					Date

________________________		______________

Member					Date	

________________________		______________

Member					Date

Qualification Completion Certification Memo Issued:

_____________________			______________

Supervisor						Date

Qualification Completion Certificate Issued/Ordered:

_____________________			______________

Supervisor						Date

The documentation review requirements, specified in the following Cards, reflect the minimum information that should be reviewed, understood, and successfully applied to perform technical review and project management activities in SFST.  It is recognized that some subjects require different levels of understanding to adequately perform assignments in SFST.  Accordingly, the training and documentation are marked with the following guidelines, to indicate the level of knowledge and understanding that is expected in the qualification process.  As discussed below, the employee should use a graded approach in reviewing and applying the document.  Similarly, qualification questions should be consistent with the prescribed knowledge level.

(F)	Familiarity:  The individual is knowledgeable of the document’s purpose and general content.  The individual is expected to have paged through the document, but not to have read it word-for-word.  Knowledge of specific contents is not expected.

(B)	Basic:  The individual is knowledgeable of the document’s purpose and scope, the major topical areas, and relationship to the roles, responsibilities, and assignments of position for which he/she is qualifying.  The individual is expected to have read the document and understand how it is used and/or the role it plays in the regulatory process.  

(I)		In-Depth:  The individual is expected to have read and studied the document.  Although rote memorization is not required, the individual should be able to describe basic requirements of the regulations and/or industry standards, guidance contents (within the individual’s area of qualification), analytical techniques and processes consistent with the individual’s grade level, and any associated limitations, and how the document is used in the review process.  Because rote memorization is not required, reference to the document is expected for complex questions concerning its content and use.

CARD 1

NRC ORIENTATION

(ALL STAFF)

The following documentation should be read to develop a general understanding of the U.S. NRC, as an organization, and from where its regulatory authority is derived.  This information should be discussed with the qualifying individuals (i.e., staff members) supervisor (or as directed).

										Employee	Supervisor	Date

	NUREG-1614	U.S. NRC Strategic Plan - 

				Vol. 4 (Purpose and 

				Strategic Goals) (32 pages)		_________	________	_____

The following training courses should be taken to develop a general understanding of NRC as an organization and to familiarize the individual with general tasks that the staff performs.

Orientation Classes Offered by Professional Development Center

										Employee	Supervisor	Date

“NRC: What It Is and What It Does” (2 days)		________	________    _____	

“Regulatory Process” (2 days)					________	________      _____

Training Offered On NRC Website

										Employee	Supervisor	Date

“Allegations” (3 hrs)						________	________      _____

(Management Directive 8.8)

“Information Security Awareness” (INFOSEC) (3 hrs)	________	________      _____

CARD 1

NRC ORIENTATION

(ALL STAFF)

(CONT.)

Other Orientation Material

										Employee	Supervisor	Date

	“Open, Collaborative, Work Environment” (3 hrs)	

	(Orientation Seminar or presentation slides at 

	NRC’s internal website:					________       ________     _____

http://www.internal.nrc.gov/OE/dva/index.html)

“Regulatory Review Philosophy” (1 hr)*			________	________      _____

*This training course is an orientation session to discuss practices that an NRC employee should follow when reviewing licensing documentation to make a regulatory decision.

CARD 2

CODE OF FEDERAL REGULATIONS

(ALL STAFF)

The qualifying individual should become familiar with the following sections of the Code of Federal Regulations (CFRs) as they are applicable to his/her area of expertise. After the qualifying individuals completion of the self-study of the listed CFR Parts, he/she will   discuss them with his/her supervisor.  To the extent possible, the supervisor should emphasize recent application of various sections, new regulatory initiatives, and current industry issues.

										Employee	Supervisor	Date

	10 CFR Part 71	“Packaging and Transportation	

				of Radioactive Material”		________	________  _____

				(~54 pages)

	10 CFR Part 72	“Licensing Requirements for the		

				Independent Storage of Spent 

				Nuclear Fuel, High-Level 

				Radioactive Waste, and Reactor – 

				Related Greater than Class C 

				Waste” (~58 pages)			________      ________   _____

B	10 CFR Part 20	“Standards for Protection		

				Against Radiation” – Overview

				of Subparts A Through K		________	________  _____					(~27 pages)	  

F	10 CFR Part 2	“Rules of Practice for Domestic	

				Licensing Proceedings and 

				Issuance of Orders” or On-line

				Training - Overview of Types of

				Hearings and 2.390			________	________   _____

F	10 CFR Part 21	“Reporting of Defects and		

				Noncompliance”(~7 pages)		________	________   _____

F	10 CFR Part 51	“Environmental Protection

				Regulations for Domestic 

				Licensing and Related 

				Regulatory Functions” – 

				Overview of Sections 1, 

				21-22, 25-35, 45, and 70		________	________   _____				(~10 pages)

Issue Date: 09/24/08	TBD-2	1246

Issue Date:  10/26/11	B1-1	1246

CARD 3

NMSS/NRC MANAGEMENT DIRECTIVES

(ALL STAFF)

The first-line supervisor should select some currently applicable NRC Management Directive (MD) references and discuss the application of the selected NRC MDs with the qualifying individual.  (The first line supervisor should also discuss where MDs are located including how to access these documents in NRC’s internal website.)  These references should include those listed below and be documented.  The qualifying individual should be expected to have a general knowledge of the topics addressed in the references.  He/she may learn the information by studying, study-quizzes, briefings, or discussions.  The selection should include:

										Employee	Supervisor	Date

B	NRC MD 10.131		“Protection of NRC 

					Employees against 

					Ionizing Radiation” 

					(76 pages)				________      ________   _____	

F	NRC MD 3.1		“Freedom of Information 

					Act”	(97 pages)			________	________      _____

F	NRC MD 3.5		“Attendance at NRC Staff -			

					Sponsored Meetings” 	________	________      _____

					(50 pages)

(Management directives can be found in the following link in NRCs internal website: http://www.internal.nrc.gov/ADM/DAS/cag/Management_Directives/index.html.)

CARD 4

NMSS/SFST ORIENTATION READING

(ALL STAFF)

The qualifying individuals supervisor should discuss these policies and practices with the employee to ensure that he/she has a general understanding of the material.

General Overview

										Employee	Supervisor	Date

F	“Enforcement Policy” (Introduction and Purpose) 

	(2 pages)								________	________     _____

(http://www.nrc.gov/about-nrc/regulatory/enforcement/enforc-pol.pdf)

SFST Reading

										Employee	Supervisor 	Date

B	“SFST Office Instructions” (ADAMS Document		

	Manager Folder: NMSS/NMSS-SFPO/Office

	Instructions)							________	________      _____

F	“U.S. DOT/NRC Memorandum of Understanding,”	

	dated 7/02/79 (FRN 44FR38690) (9 pages)		________	________      _____

F	“U.S. OSHA/NRC Memorandum of Understanding”		

	(see IMC 1007, “Interfacing Activities Between 

	Regional Offices of NRC and OSHA,” and		________	________ _____	http://r12k3web.nrc.gov/dnms/Training/MOU06_2003.htm)

NRC Inspection Manual Chapter

										Employee	Supervisor	Date

F	IMC 1201	“Conduct of Employees” (35 pages)	________	________  _____

CARD 4

NMSS/SFST ORIENTATION READING

(ALL STAFF)

(CONT.)

The qualifying individuals supervisor should discuss these policies and practices with the employee to ensure that he/she has a general understanding of the material.

Policy and Procedures Letters

The following NMSS’ Policy and Procedure Letters (P&PLs) should be discussed with the qualifying individual to develop a general understanding of NMSS as an organization and to familiarize the individual with general tasks that the staff performs. (The first line supervisor should also discuss where P&PLs are located in ADAMS.)

									Employee	Supervisor	Date

F  P&PL1-13		“Signature Level on NMSS 

	Correspondence”

	(Revised Nov99, 1 page)	________	________	_____

	(ML032180768)

F  P&PL1-28	“Preparation of Responses to 

	Congressional Inquiries”

	(01/1993; 1 page)			________	________	_____

	(ML032230067)

F  P&PL1-39	“Review of Speeches, Papers and

	Journal Articles Revised”

	(Sept 99; 2 pages) 			________	________	_____

	(ML032240298)

F  P&PL1-84	“10 CFR Part 72 Backfit Guidance

	for NMSS” (11/6/04; 45 pages)	________	________	_____

	(ML040330332, ML050350399)

F  P&PL1-85	“Handling Requests to Withhold 

	Proprietary Information from Public

	Disclosure” (3/3/05; 15 pages) 	________	________	_____

			(ML050340352)

CARD 5

REGULATORY GUIDANCE

(ALL STAFF)

The supervisor should select currently applicable regulatory guidance related to the individuals tasks.  These references should include those listed below and should be documented. The qualifying individual should be expected, as appropriate, to have a general knowledge of the topics in the references. The level of knowledge of standard review plans (SRPs) may be caveated with respect to PMs and TRs roles.  In terms of SRPs, PMs and TRs will need in-depth knowledge of some chapters, and familiarity with others.  The individual can review the topics by self-study, study-quizzes, briefings, or discussions. 

10 CFR Part 71

										Employee	Supervisor	Date

I	NUREG-1609	SRP for Transportation Packages

				for Radioactive Material -

				Selected Portions (149 pages)	________	________    _____	

I	NUREG-1617	SRP for Transportation Packages

				for Spent Nuclear Fuel -

				Selected Portions (162 pages)	________	________      _____

F	NUREG/		Engineering Drawings for	

	CR-5502		10 CFR 71 Package Approvals	________	________   _____				http://www.rampac.com/NRCinfo/NUREG_5502.pdf

F	IAEA Safety	Regulations for the Safe		

	Standard,		Transport of Radioactive

	No. TS-R-1	Material [Types B(U) and B(M) 

	2005		Only] - IAEA Safety Standards

				Section I; Section VI – pages 81-83; 

				86; 89-92; Section VII – 

				pages 99-105; 108 (top);

				Section VIII – pages 111-126, 

				general (~48 pages)			________	________    _____

F   RAMREG      Radioactive Material

	XXX-XX	       Regulations Review (U.S.DOT)   	

	(formerly	       Sections I-V, and X-XII			________	______    _______

	RAMREG-	       (~57 pages)

	001-98)

CARD 5

REGULATORY GUIDANCE (CONT.)

(ALL STAFF)

(CONT.)

10 CFR Part 72

										Employee	Supervisor	Date

I	Regulatory 	Guidance for Implementation of

	Guide 3.72	10 CFR 72.48, Changes, Tests,

				and Experiments (7 pages)	________	________	____

				(ML010710153)

I	NUREG-1536	SRP for Dry Cask Storage		

				Systems-Selected Portions	________	________	____

				(232 pages)	

I	NUREG-1567	SRP for Spent Fuel Dry

				Storage Facilities-

				Selected Portions (410 pages)	________	________	____

I	NUREG 1745	Standard Format and 

				Content for Technical 

				Specifications for 10 CFR 

				Part 72 Cask Certificates

				of Compliance				________	________	____

F	NUREG 1748	Environmental Review Guidance

				for Licensing Actions Associated

				with NMSS Programs - 

				Introduction				________	________	____

Interim Staff Guidance

										Employee	Supervisor	Date

I	Interim Staff Guidance (ISG) memoranda		

	(Selected Reading) (http://www.nrc.gov/reading-

	rm/doc-collections/isg/spent-fuel.html) (B for PMs)	________	________	____

CARD 5

REGULATORY GUIDANCE (CONT.)

(ALL STAFF)

(CONT.)

Quality Assurance (if applicable – Rules, Inspections, and Operations Branch only)

										Employee	Supervisor	Date

F	Regulatory		Establishing Quality Assurance

	Guide 7.10	Programs for Packaging Used

				in the Transport of Radioactive

				Material					________	________	____

				(28 pages) – ML050540330

Generic Communications

									Employee	Supervisor	Date

F	IN 91-039, “Compliance with 10 CFR Part 21,

	Reporting of Defects and Noncompliance		_________	________	____

	(4 pages)

F	IN 95-029, Oversight of Design and Fabrication	

	Activities for Metal Components Used in Spent

	Fuel Dry Storage Systems (4 pages)	 		_________	________	____

F	IN 97-051, Problems Experienced Loading and	

	Unloading Spent Nuclear Fuel Storage and

	Transportation Casks (5 pages)				_________	________	____

F	IN 97-057, Leak Testing of Packaging	

	Used in the Transport of Radioactive 

	Material (4 pages)						_________	________	____

F	IN 99-029, Authorized Contents of Spent	

	Fuel Casks(1-2 pages)					_________	________	____

F	IN 2004-13, Quality Assurance of Transportation	

	Packages (9 pages)						_________	________	____

F	IN 2005-10, Changes to Part 71 Packages		_________	________	____

	(3 pages)	

CARD 5

REGULATORY GUIDANCE (CONT.)

(ALL STAFF)

(CONT.)

Generic Communications

										Employee	Supervisor	Date

F	RIS 2006-22 Lessons Learned from Recent 10	

	CFR Part 72 Dry Cask Storage Campaigns		________	________	____

	(10 pages)

F	RIS 2007-09, Examples of Recurring Requests	

	for Additional Information (RAIs) for 10 CFR Part

	71 and 72 Applications (20 pages)			________	________	____

B	RIS 2005-27, Rev. 1, “NRC Timeliness Goals, 

	Prioritization of Incoming License

	Applications and Voluntary Submittal of 

	Schedule for Future Actions for NRC

	Review” (9 pages)						________	________	____

F	BL 96-04, Chemical, Galvanic, or Other		

	Reactions in Spent Fuel Storage and

	Transportation Casks (9 pages)				________	________	____

CARD 6

FORMAL TRAINING

(ALL STAFF)

A.		CORE TRAINING

										Employee	Supervisor	Date

“Site Access Training” (H-100) or “NMSS Radiation	

Worker Training” (H-102)						________	________	____

B.		SPECIALIZED TRAINING

Other specialized training and/or courses required for PMs or TRs in performing regulatory activities in specific areas.

CARD 7

DIRECTED CASE STUDY

Complete the Directed Case Study card as applicable to PMs or TRs.  At the completion of the assignment, lessons learned should be discussed with the experienced PM and/or supervisor. These tasks can be performed either individually or in groups of two or three individuals, depending on the availability of case studies.

A.		PROJECT MANAGERS

Job Performance Measures

Perform one (1) project management assignment under the oversight of an experienced PM.

								_____________________

								Project Manager

B.		TECHNICAL REVIEWER

DISCIPLINE:  ______________________________________

Job Performance Measures

Perform at least one technical review that is moderate to complex in nature, either related to 10 CFR Part 71, or to 10 CFR Part 72. The individual should lead the development of a request for additional information (RAI), a safety evaluation report (SER), and other interactions with the applicant, as appropriate.  The review should be performed under the oversight of the appropriate technical specialty individual and/or supervisor, in the employees assigned technical discipline.  As appropriate, within certain technical disciplines, the supervisor may require completion of additional technical reviews (or portions) to qualify the individual for review methods and acceptance criteria that may be unique to either a Part 71 or Part 72 licensing action.

								______________________

								Supervisor or Assignee

Participate in, and assist, the licensing process, from the receipt of a licensing request (e.g., developing schedules, arranging meetings, coordinating reviews, briefing and updating management documentation; new package and new certificate of compliance application request; and/or amendment to an existing certificate of compliance) by working with an experienced PM.

								_____________________

								Project Manager

CARD 8

INSPECTION ACCOMPANIMENTS

(ALL STAFF)

The qualifying individual should accompany staff on at least one site visit or inspection of a fabrication facility or certificate holder.  These tasks can be performed either individually or in groups, depending on the availability of site visits or inspections.  The following is a guide for material that the individual may discuss, as applicable, with the lead staff member of the site visit or lead inspector before/after/during the accompaniment:

1. Type of facility

2. Applicability to staff’s duties

3. Logistics (e.g., scheduling and preparation of site visits or inspections)

4. Inspection program 

a. Entrance and exit interviews

b. Accumulation of data

c. Importance of inspection procedures and reports (e.g., Form 591S)

5. Post-site visit or post-inspection activities

The individuals supervisor may also discuss these items, as appropriate, after the accompaniment.

Record of Accompaniments

	Location/Facility:				___________________________________

	Date(s):					___________________________________

	Type (71/72):				___________________________________

	Successful Completion:		___________________________________

								Staff Member/Supervisor

CARD 9

REVIEW OF DISCIPLINE-SPECIFIC DOCUMENTATION

WORK GROUP SPECIALTY TRAINING

The following signature cards contain the specialty training requirements for the following technical branches in SFST:

Structural, Mechanics, and Materials Branch (SMMB)

Criticality, Shielding, and Dose Assessment Branch (CSDAB)

Thermal and Containment Branch (TCB)

Work group specialty training is performed in addition to the requirements in qualification cards 1 through 8.  Each signature card may contain a mixture of reading and formal classroom instruction.  The employees supervisor has the discretion to modify the requirements, as needed, based on the employees previous experience, education, and course availability.

There are six technical specialty disciplines comprising the bulk of the technical evaluations performed by the technical review staff: (1) containment/confinement; (2) criticality; (3) materials; (4) shielding/radiological/security assessment protection; (5) structural; and (6) thermal. The employees supervisor will assign the employee one or more technical specialty disciplines. The employees supervisor and/or the technical specialty individual, if so designated, will determine what training within a technical specialty discipline is required based on the employees educational background and experience. The technical specialty training listed here may not be all-inclusive, and may be adjusted as desired by the employees supervisor. To the extent practical, knowledge of some of the required documents may be demonstrated, in part, through discussion and completion of the job performance measures described in Card 7.  For each specialty card, the technical reviewer should have an appropriate level of knowledge (as marked) of the following documents, in order to be qualified to independently perform technical reviews in that area for his or her grade level.

CARD 9A

CONTAINMENT/CONFINEMENT

										Employee	Supervisor	Date

	NUREG/		Containment Analysis for Type B	

	CR-6487 		Packages with Various Contents	________	________   _____	

A NSI N14.5		Leakage Tests on Packages for 	

				Shipment					________	________      _____

B	ASME, 		“Containment Systems and	

	Section III, 	Transport Packaging”		 	________	________     _____

	Division 3

B	ANSI N14.1	“UF6 Packages”				________	________     _____

F	Regulatory		Atmospheric Dispersion Models for	

	Guide 1.145	Potential Accident Consequence

				Assessments at Nuclear Power 

				Plants					________	________     _____

F	Regulatory		Leakage Tests on Packages for		

	Guide 7.4		Shipment of Radioactive Material________	________     _____

F	NUREG 1736	Consolidated Guidance:  10 CFR

				Part 20, Standards for Protection 

				Against Radiation			________	________     _____

Training Courses.

ORIGEN - ARP/TRITON Course (F368)			________	________   _____	

CARD 9B

CRITICALITY

										Employee	Supervisor	Date

	NUREG/		Recommendations for Preparing	

	CR-5661		 Criticality Safety Evaluations of 

		 		 Transportation Packages		________	________     _____            

	ANSI/ANS-8.1	Nuclear Criticality Safety in		

				Operations with Fissionable 

				Material Outside Reactors		________	________	_____  

	ANSI/ANS-8.15	Nuclear Criticality Control of		

				 Special Actinide Elements		________	________      _____

	ANSI/ANS-8.17	Handling, Storage, and Transport	

				 of LWR Fuel Outside Reactors	________	________   _____	

B	NUREG/ 		Criticality Benchmark Guide for	

	CR-6361		 Light-Water Reactor Fuel in 

				 Transportation and Storage 

				 Packages				________	  _______     _____

B	NUREG/ 		Experience with the Scale	

	CR-6686 		 Criticality Safety Cross-Sections 

	(ORNL/TM-	 Libraries											1999/322)								________	________     _____

B	ANSI/ANS-8.21	Fixed Neutron Absorbers		________	_______      _____

B	NEA/NCS/		International Handbook 

	DOC (95)03	of Evaluated Criticality Safety 

				Benchmark Experiments- NEA 

				Nuclear Science Committee	________	________   _____	

F	10 CFR Part 50	“Domestic Licensing of Production		

				and Utilization Facilities” - Overview

				of Section 59 and Appendix B 

				(Section 68; Criticality only) 

				(~6 pages)					________	_______       _____

F	NUREG/		Adequacy of the 123-Group 

	CR-6328		Cross-Section Library for Criticality

	(ORNL/TM-	Analyses of Water-Moderated		

	12970)		Uranium Systems			________	_______      _____

CARD 9B

CRITICALITY

(CONT.)

Training Courses

										Employee	Supervisor	Date

	SCALE Training Course (e.g., KENO-5, KENO-6)	________	_______       _____

	MCNP Training Course					________	_______       _____

CARD 9C

MATERIALS

										Employee	Supervisor	Date

B	ASME B&PVC	Specifications for Welding Rods	

	Section II, 		 Electrodes, and Filler Metal	________	________      _____

	Part C	

F	NUREG/ 		“Recommendations for Protecting 

	BR-1815		Against Failure by Brittle Fracture

				in Ferritic	Shipping Containers...”________	________	_____

F	NUREG/		Engineering Drawings for	

	CR-5502		10 CFR 71 Package Approvals	________	_______     _____				http://www.rampac.com/NRCinfo/NUREG_5502.pdf

F	ASME B&PVC	Material Properties			________	_______        _____

	Section II, 

	Part D

F	ASTM		(Supervisor selected reading)*	________	________	_____

	Specifications

F	ACI-318-XX	“Building Code requirements for 

				Structural Concrete”			________	_______        _____

Training Courses

ASM:	“Stainless Steels”						________	______        ______

NACE:	“Basic Corrosion”						________	______        ______

* The level of understanding [i.e., familiarity (F), basic (B), or in-depth (I)] will depend on the section selected by the supervisor for self-study.

CARD 9D

SHIELDING/RADIOLOGICAL PROTECTION/SECURITY ASSESSMENT

										Employee	Supervisor	Date

	NUREG/		Recommendations for Shielding	

	CR-6802 		Evaluations for Transport and

				Storage Packages”		 	________	________    _____

	ANSI/ANS 6.1.1	Flux to Dose Rate Conversion	

				Factors					________	________    _____

	“Supplement to the Communication Plan for the 

	Security Assessment of Materials and Research 

	and Test Reactor Licensees” (ML070890305)	________	________    _____

	“Guidance for Security Assessments of Storage

	and Transportation of Radioactive Material”

	(ML073110136)							________	________   _____

	B	10 CFR		“Occupational Radiation		

	Part 835		Protection” 				________	________  _____	

B	Regulatory 	Information Relevant to Ensuring		

	Guide 8.8 		the Occupational Radiation Exposures

				at Nuclear Power Stations Will Be 

				As Low As Reasonably 

				Achievable				________	________   _____

B	ANSI N14.1	UF6 Packages				________	________   _____

F	49 CFR		“Shippers - General Requirements	

	Part 173		for Shippers,” Subpart I		________	________   _____

F	40 CFR		“Radiation Protection Programs”	________	________  _____

	Part 190

F	Regulatory 	Operating Philosophy for Maintaining 

	Guide 8.10 	Occupational Radiation Exposures 

				As Low As Reasonably 

				Achievable				________	________  _____	

F	NUREG 1736	Consolidated Guidance: 10 CFR	

				Part 20-Standards for Protection 

				Against Radiation			________	________  _____	

CARD 9D

SHIELDING/RADIOLOGICAL PROTECTION/SECURITY ASSESSMENT

(CONT.)

Training Course

										Employee	Supervisor	Date

	“Shielding Code Training Code” (e.g.,		

	MCNP, SCALE)							________	________     _____

CARD 9E

STRUCTURAL

										Employee	Supervisor	Date

	NUREG/		Engineering Drawings for	

	CR-5502		10 CFR 71 Package Approvals	________	________   _____				http://www.rampac.com/NRCinfo/NUREG_5502.pdf

B	Regulatory 	“Design of an ISFSI 

	Guide 3.60	(Dry Storage)”				________	________	_____

B	Regulatory 	“Leakage Tests for Packages for 

	Guide 7.4		Shipments of Radioactive 

				Materials”					________	________	_____

B	Regulatory 	Design Criteria for the	Structural	

	Guide 7.6		Analysis of Shipping Cask 

				Containment Vessels			________	________	_____

B	Regulatory 	Load Combinations for the	

	Guide 7.8		Structural Analysis of Shipping

				 Casks for	Radioactive Material	________	________	_____

B	NUREG/		Recommendations for Protecting

	CR-1815		 Against Failure by Brittle Fracture in 

				Ferritic Steel Shipping Containers 

				Up to Four Inches Thick		________	________	_____

B	NUREG/ 		Stress Analysis of Closure Bolts

	CR-6007		for Shipping Casks			________	________	_____

B	NUREG/		“Transporting Spent Fuel” 		________	________	_____	BR-0111

B	ACI-318-XX,	Building Code Requirements			

	(As Directed)	for Structural Concrete		________	________	_____

F	NUREG/ 		SCANS (Shipping Cask Analysis

	CR-4554		System) A Microcomputer-Based

				Analysis System for Shipping

				Cask Design Review			________	________	_____

F	ASME		“Containment Systems and

	Section III		Transport Packaging” 			________	________	_____

CARD 9E

STRUCTURAL

(CONT.)

										Employee	Supervisor	Date

F	IN 97-057, Leak Testing of Packaging Used in	

	the Transport of Radioactive Material (4 pages)	________	________	_____

Training Course

										Employee	Supervisor	Date

Introduction to ANSYS		 				________	________	_____

CARD 9F

THERMAL

										Employee	Supervisor	Date

B	NUREG/ 		“Spent Fuel Transportation	

	CR-6886,		Package Response to the Baltimore 

	Rev. 1		Tunnel Fire Scenario”			________	________	_____

	PNNL-15313

B	NUREG/		“Spent Fuel Transportation Package	

	CR-6894,		Response to the Caldecott Tunnel

	Rev. 1		Fire Scenario”				________	________	_____

	PNNL-15364

B	CFD Analysis and Validation for Ventilated Concrete

	 Cask,” Internal Report, for Official Use Only, Prepared

	 for SFST by Office of Nuclear Regulatory Research

	(ML0729505470 )						________	________	_____

F	Regulatory		Spent Fuel Heat Generation in an		

	Guide 3.54	Independent Spent Fuel Storage

				Installation”				 ________	________	_____

F	ASTM E 		Standard Practice for Thermal	

	2230-02  		Qualification of Type B Packages 

				or Radioactive Material		________	________	_____

F	PNNL-14962	“Analysis Package for the 

				Transnuclear TN-24P Cask”

				(ML0506106170)			________	________	_____

F	PNNL-14930	“Analysis Package for the

				VSC-17 Ventilated Concrete

				Cask” (ML0506106360)		________	________	_____

F	PNNL-14863	“Analysis Package for the 

				CASTOR-V/21 Cask”

				(ML0506106460) 			________	________	_____

F	Spent Nuclear Fuel Effective Thermal Conductivity

	Report,” July 11, 1966.  Prepared for the Department

	 of Energy by TRW Environmental Safety Systems	________	________	_____

F	The TN-24P Spent Fuel Storage Cask: Testing and

	 Analyses,” EPRI NP-5128, PNL-6054, UC-85 

	(April 1987)							________	________	_____

CARD 9F

THERMAL

(CONT.)

										Employee	Supervisor	Date

Training Courses (any TWO of the listed courses)

“Introduction to FLUENT/GAMBIT”				________	________	_____

“Introduction to ANSYS/ICEM-CFD Course”		________	________	_____

“Introduction to STAR-CCM+/STAR-CD Course”	________	________	_____

Attachment 1

Revision History for IMC 1246 B1 

Issue Date: 10/26/11	Att1-1		1246