Document: NUREG-0800
Document ID: 786da65a-4915-4af3-afb3-678b7df5bea7
Document Type: srp
Title: OTHER SEISMIC CATEGORY I STRUCTURES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070327.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.4
CFR Part: 
CFR Title: 

Content:
well as the welding procedure for the welding assembly shall be qualified in accordance with the applicable code. If spent fuel pool racks are fabricated from aluminum the guidance regarding material properties can be found in References 3.3 and 3.4. 130 TABLE 1 LOAD COMBINATION ACCEPTANCE LIMIT D + L Level A service limits D + L + T0 D + L + T + E 0 D + L + T + E Level B service limits a D + L + T + P 0 f D + L + T + E' Level D service limits a D + L + F The functional capability d of the fuel racks should be demonstrated Limit Analysis: 1.7 (D + L) Appendix XVII, Article 4000 of 131 ASME Code, Section III 1.3 (D + L + T ) 0 3.8.4-39 DRAFT Rev. 2 - April 1996 1.7 (D + L + E) 1.3 (D + L + E + T ) 0 1.3 (D + L + E + T ) a 1.3 (D + L + T(o) + P ) f 1.1 (D + L + T(a) + E') Notes: 1. The abbreviations in the table above are those used in subsection II.3.a of this SRP section where each term is defined except for T which is defined here as the highest a temperature associated with the postulated abnormal design conditions. 2. Deformation limits specified by the Design Specification limits shall be satisfied, and such deformation limits should preclude damage to the fuel assemblies. 3. The provisions of Subsection NF 3231.1 of Reference 3.1 shall be amended by the 132 requirements of paragraphs c.2.3 and 4 of Regulatory Guide 1.124 entitled "Design Limits and Load Combinations for Class 1 Linear-Type Component Supports." 4. F is the force caused by the accidental drop of the heaviest load from the maximum d possible height and P is upward force on the racks caused by postulated struck fuel f assembly. REFERENCES Regulatory Guides 1.1 1.29 - Seismic Design Classification 1.2 1.60 - Design Response Spectra for Seismic Design of Nuclear Power Plants 1.3 1.61 - Damping Values for Seismic Design of Nuclear Power Plants 1.4 1.76 - Design Basis Tornado for Nuclear Power Plants 1.5 1.92 - Combining Modal Responses and Spatial Components in Seismic Response Analysis 1.6 1.124 -