Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities - Final Report (NUREG-2215)

On this page:

• Publication Information
• Abstract

Download complete document

• NUREG-2215 (PDF – 11.04 MB)

Chapters:

• Table of Contents, Introduction. (43 page(s))
• Chapter 1 – General Information for Evaluation. (14 page(s))
• Chapter 2 – Site Characteristics Evaluation for Dry Storage Facilities (SL). (24 page(s))
• Chapter 3 – Principal Design Criteria Evaluation. (32 page(s))
• Chapter 4 – Structural Evaluation. (42 page(s))
• Appendix 4A – Computational Modeling Software Technical Review Guidance. (4 page(s))
• Appendix 4B – Pool and Pool Confinement Facilities. (8 page(s))
• Chapter 5 – Thermal Evaluation. (26 page(s))
• Chapter 6 – Shielding Evaluation. (40 page(s))
• Chapter 7 – Criticality Evaluation. (31 page(s))
• Appendix 7A – Technical Recommendations for the Criticality Safety Review of PWR Transportation Packages and Storage Casks. (33 page(s))
• Chapter 8 – Materials Evaluation. (51 page(s))
• Appendix 8A – Clarifications, Guidance, and Expectations to ASTM Standard Practice C1671–15. (5 page(s))
• Appendix 8B – Fuel Cladding Creep. (2 page(s))
• Appendix 8C – Fuel Oxidation and Cladding Splitting. (4 page(s))
• Chapter 9 – Confinement Evaluation (22 page(s))
• Chapter 10A – Radiation Protection Evaluation for Dry Storage Facilities (SL). (46 page(s))
• Chapter 10B – Radiation Protection Evaluation for Dry Storage Systems (CoC). (18 page(s))
• Chapter 11 – Operation Procedures and Systems Evaluation. (26 page(s))
• Chapter 12 – Conduct of Operations Evaluation. (46 page(s))
• Chapter 13 – Waste Management Evaluation (SL). (22 page(s))
• Chapter 14 – Decommissioning Evaluation (SL). (8 page(s))
• Chapter 15 – Quality Assurance Evaluation. (20 page(s))
• Chapter 16 – Accident Analysis Evaluation. (30 page(s))
• Chapter 17 – Technical Specifications Evaluation. (12 page(s))
• Appendix A – Interim Staff Guidance (ISG) Incorporated into NUREG–2215. (6 page(s))

Publication Information

Manuscript Completed: February 2020
Date Published: April 2020

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 safety analysis reports (SARs) for (1) a Certificate of Compliance (CoC) for a dry storage system for use at a general license facility and (2) a specific license for a dry storage facility that is either an independent spent fuel storage installation (ISFSI) or a monitored retrievable storage installation (MRS). This SRP does not apply to wet storage ISFSIs or MRSs (e.g., GE-Morris). NUREG-2215 is a consolidation of existing guidance for staff’s use when reviewing applications for licenses and certificates for spent fuel dry storage systems and facilities, and as such, it is not intended to offer new or differing guidance.

The objectives of this SRP are to assist the NRC staff in its reviews by doing the following:

• promoting a consistent regulatory review of a SAR for an ISFSI or MRS license, or for a CoC
• promoting quality and uniformity of these reviews across each technical discipline
• 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 report

This SRP was published for public comment and the responses to those comments are available at ML19303C896. This NUREG is a rule as defined in the Congressional Review Act (5 U.S.C. 801-808). However, the Office of Management and Budget has not found it to be a major rule asdefined in the Congressional Review Act.

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 Division of 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 Fuel Management, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.