Document: NUREG-0800
Document ID: 9ff4c910-8dd7-451c-97cf-4b956e68d03e
Document Type: srp
Title: LIGHT LOAD HANDLING SYSTEM AND REFUELING CAVITY DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1331/ML13318A923.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.1.4
CFR Part: 
CFR Title: 

Content:
ategory I structures housing the system and supporting systems to withstand the effects of natural phenomena like the safe shutdown earthquake. 3. SRP Sections 3.9.1 through 3.9.3: review of codes and standards applied to the design of components, piping, and structures. 4. SRP Section 3.10: review of the seismic qualification of Category I instrumentation and electrical equipment. 5. SRP Sections 12.3 and 12.4: review of the designs of the fuel handling system and the spent fuel transfer process for whether occupational radiation exposures during spent fuel handling will be as low as reasonably achievable. 6. SRP Section 16: review of technical specifications for reactivity, power and cooling controls of fuel in storage locations 7. Chapter 17: review of quality assurance. 8. Chapter 19: review of the risk of shutdown operations when the refueling cavity is flooded as part of the applicant’s Low Power and Shutdown PRA. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements The LLHS is acceptable if the integrated design of the structural, mechanical, and electrical elements, the manual and automatic operating controls, and the safety interlocks and devices provide adequate system control for the specific procedures of handling operations; if the redundancy and diversity needed to protect against malfunctions or failures are provided; and if the design complies with applicable regulations. Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. GDC 2 as it relates to the ability of structures, equipment, and mechanisms to withstand the effects of earthquakes. 2. GDC 5 as it relates to the capability of shared equipment and components to perform safety functions. 9.1.4-4 Revision 4 - July 2014 3. GDC 61 as it relates to radioactivity release as a result of fuel damage and the avoidance of excessive personnel radiation exposure.