Document: NUREG-0800
Document ID: a41f4aae-e975-45f3-aebc-5519bec72c6e
Document Type: srp
Title: CRITICALITY SAFETY OF FRESH AND SPENT FUEL STORAGE AND HANDLING
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070570006.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.1.1
CFR Part: 
CFR Title: 

Content:
ith the additional design and analysis requirements specified in 10 CFR 50.68. For DC and COL reviews, the findings will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and site parameters) and COL action items relevant to this SRP section. In addition, to the extent that the review is not discussed in other SER sections, the findings will summarize the staff’s evaluation of the ITAAC, including design acceptance criteria, as applicable. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI. REFERENCES 1. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion 62, “Prevention of Criticality in Fuel Storage and Handling.” 9.1.1-11 Revision 3 - March 2007 2. 10 CFR 50.68, “Criticality Accident Requirements.” 3. ANSI/ANS 57.1-1992, “Design Requirements for Light Water Reactor Fuel Handling Systems,” reaffirmed 2005. 4. ANSI/ANS 57.2-1983, “Design Requirements for Light Water Reactor Spent Fuel Storage Facilities at Nuclear Power Plants,” withdrawn 1999 (reaffirmation in progress). 5. ANSI/ANS 57.3-1983, “Design Requirements for New Fuel Storage Facilities at Light Water Reactor Plants,” withdrawn 1993 (reaffirmation in progress). 6. Regulatory Guide 1.13, Revision 2, “Spent Fuel Storage Facility Design