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          NRC Library  Document Collections  NUREG-Series Publications  Publications Prepared by NRC StaffStandard Review Plan for Transportation Packages for Spent Fuel and Radioactive Material: Final Report (NUREG-2216)

On this page:

Publication Information
	AbstractDownload complete document

NUREG-2216 (PDF – 12.2 MB)**Chapters:**

Cover, Table of Contents and Introduction (32 page(s))
	Chapter 1 General Evaluation Information (16 page(s))
	Chapter 2 Structural Evaluation (24 page(s))
	Attachment 2A Computational Modeling Software Technical Review Guidance (4 page(s))
	Chapter 3 Thermal Evaluation (28 page(s))
	Chapter 4 Containment Evaluation (16 page(s))
	Chapter 5 Shielding Evaluation (36 page(s))
	Chapter 6 Criticality Evaluation (34 page(s))
	Attachment 6A Technical Recommendations (34 page(s))
	Chapter 7 Materials Evaluation (42 page(s))
	Attachment 7A Clarifications, Guidance and Exceptions to ASTM Standard Practice (6 page(s))
	Attachment 7B Fuel Selection (4 page(s))
	Chapter 8 Operating Procedures Evaluation (8 page(s))
	Chapter 9 Acceptance Tests and Maintenance Program Evaluation (10 page(s))
	Chapter 10 Quality Assurance Evaluation (18 page(s))
	Chapter 11 Glossary (4 page(s))
	Appendix A Description, Safety Features, and Areas of Review for Different Types of Radioactive Material Transportation Packages (50 page(s))
	Appendix B Differences Between Thermal and Radiation Properties of Mixed Oxide and Low-Enriched Uranium Radioactive Materials (8 page(s))
	Appendix C Differences Between Thermal and Radiation Properties of Mixes Oxide and Low-Enriched Uranium Spent Nuclear Feul (10 page(s))
	Appendix D Benchmark Considerations for Mixed Oxide Radioactive Materials and Spent Nuclear Fuel (12 page(s))
	Appendix E Description and Review Procedures for Irradiated Tritium-Producing Burnable Absorber Rods Packages (34 page(s))
	Attachment A Physical and Chemical Properties of Tritium (16 page(s))
	Attachment B Biological Properties of Tritium and Tritium Health Physics (31 page(s))Publication Information

**Manuscript Completed:** February 2020**Date Published:** August 2020

**Prepared by:**
Joseph Borowski
Michel Call
Darrell Dunn
Antonio Rigato
Jeremy Smith
Jorge Solis
Jeremy Tapp
Bernard White

Office of Nuclear Materials Safety and Safeguards
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

Availability Notice

Abstract

This Standard Review Plan (SRP) provides guidance to the U.S. Nuclear Regulatory Commission (NRC) staff for reviewing an application for package approval issued under Title 10 of the *Code of Federal Regulations* (10 CFR), Part 71, "Packaging and Transportation of Radioactive Material." NRC approval of a package design typically results in issuance of a certificate of compliance (CoC) or a letter amendment for a transportation package.

The objectives of this SRP are to assist the NRC staff in its reviews by

providing a basis that promotes uniform quality and a consistent regulatory review of an application for a CoC for a transportation package
	presenting a basis for the review's scope
	identifying acceptable approaches to meeting regulatory requirements
	suggesting possible evaluation findings that can be used in the safety evaluation reportThis SRP was published for public comment, and the responses to those comments are available at ML20023A361. This SRP may be revised and updated as the need arises on a chapter-by-chapter basis to clarify the content, correct errors, or incorporate modifications approved by the Director of the NRC Division of Spent Fuel Management. Comments, suggestions for improvement, and notices of errors or omissions should be sent to and will be considered by the Director, Division of Spent Fuel Management, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.



      
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