Document: NUREG-0800
Document ID: 072325a8-02ea-4d59-bb3f-06592c340804
Document Type: srp
Title: The Aluminum Association, Specification for Aluminum Structures
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070327.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.4
CFR Part: 
CFR Title: 

Content:
does not reference specific issues This Integrated Impact concerns of industry standards, implying that the latest edition outdated Regulatory Guide 1.142 endorsed by a regulatory guide is to be used. RGs and the ACI 349 Code. No change endorse standards by date of issue. For example, was made to SRP Section 3.8.4. RG 1.142, "Safety-Related Concrete Structures for Nuclear Power Plants (Other Than Reactor Vessels and Containments)" Rev. 1, October 1981, endorses ACI 349-76 and its 1979 supplement, except for Appendix B. Meanwhile, the ACI 349 Code has been revised and the latest revision, as indicated in the NUREG/CR 5973, was issued in 1990. The revisions of the ACI 349 Code may not be acceptable to the staff. Therefore, a critical review of the revised Codes is needed. 771 10 CFR 100 Appendix A, V(d)(4), requires that AREAS OF REVIEW, I.f distant safety-related structures should be designed to withstand the effects of the SSE. 772 RGs 1.10, 1.15, and 1.55, all listed in ACCEPTANCE CRITERIA, II.2; SRP Section 3.8.4, have been withdrawn. REFERENCES 773 The SRP has been revised to refer to the new AREAS OF REVIEW, Review leak-before-break (LBB) load definitions in SRP Interfaces 5 Section 3.6.3 (to be developed). 774 RG 1.142 provides staff positions related to the use AREAS OF REVIEW, I.4; of ACI 349-76, "Code Requirements for Nuclear ACCEPTANCE CRITERIA, II.2 Safety-Related Concrete Structures." RG 1.142 and II.4.a; excludes Appendix B, "Steel Embedments," of Appendix E. ACI 349-76 in its consideration. Staff positions on steel embedments have been incorporated in the SRP Section 3.8.4 as Appendix E. SRP Draft Section 3.8.4 Attachment B - Cross Reference of Integrated Impacts Integrated Issue SRP Subsections Affected Impact No. DRAFT Rev. 2 - April 1996 3.8.4-66 775 In FSERs for the System 80+ and ABWR, the staff AREAS OF REVIEW, I.4; found the use of ANSI/AISC N690-1984, "Nuclear ACCEPTANCE CRITERIA, 3.c(i) Facilities: Steel Safety-Related Structures," to be and