Document: NUREG-0800
Document ID: b172ba61-9651-45f8-ac8e-6d6e00e27060
Document Type: srp
Title: STEEL CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1006/ML100630179.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.2
CFR Part: 
CFR Title: 

Content:
Compliance with 10 CFR 50.44 requires that containments accommodate loadings associated with combustible gas generated from a metal-water reaction of the fuel cladding. SRP Section 3.8.2 provides load combinations and acceptance criteria that demonstrate that the steel containment structural integrity is maintained under these loads. RG 1.7, Revision 2, is referenced for further guidance on the analytical technique, loading combination, and acceptance criteria. Meeting these requirements provides assurance that the containment will be able to withstand loads from the sources specified above and will perform its intended safety function. 8. Compliance with 10 CFR 50.55a requires that (1) SSCs be designed, fabricated, erected, constructed, tested, and inspected to quality standards commensurate with the importance of the safety function to be performed, (2) containments, systems, and components of boiling and pressurized water-cooled nuclear power reactors meet the requirements of the ASME Code, and (3) RGs 1.84 and 1.147 provide guidance related to NRC approved ASME Code cases that may be applied to the design, fabrication, erection, construction, testing, and inspection of containments, systems, and components. Compliance with 10 CFR 50.55a also requires that examination of steel containments be performed in accordance with the requirements of ASME Code, Section XI, Subsection IWE, and supplemental requirements specified in 10 CFR 50.55a(b)(2)(ix). Subsection IWE provides requirements for preservice examination and inservice inspection, acceptance criteria, and repair/replacement requirements. 3.8.2-23 Revision 3 - May 2010 SRP Section 3.8.2 provides review guidance to ensure that the requirements of 10 CFR 50.55a have been appropriately addressed for steel containments. Meeting the requirements of this subsection provides assurance that the containment structure will perform its safety function to limit the release of radioactive material throughout its licensing