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:
uipment hatches, and mechanical and electrical penetrations) are also designed in accordance with ASME Code, Section III, Division 1, Subsection NE. Seals provided at the penetrations must be designed to maintain containment integrity for design-basis accident conditions, including pressure, temperature, and radiation. Leaktightness of the containment structure must be tested at regular intervals during the life of the plant in accordance with the requirements of 10 CFR Part 50, Appendix J as described in the SRP Section 6.2.6. SRP Section 3.8.2 provides methods, including load combinations, acceptance criteria, standards, and codes, acceptable to the staff to ensure compliance with GDC 16. Meeting these criteria provides assurance that an uncontrolled release of radioactivity to the environment will be prevented and that the design conditions of the reactor coolant pressure boundary will be maintained for as long as required. 5. Compliance with GDC 50 requires that the reactor containment structure, including access openings, penetrations, and containment heat removal systems, be designed so that the structure and its internal compartments will have the capability to accommodate, without exceeding the design leakage rate and with sufficient margin, the calculated pressure and temperature conditions resulting from any LOCA. The calculated margin should reflect consideration of (1) the effects of potential energy sources that have not been included in the determination of the peak conditions (such as energy in steam generators) and, as required by 10 CFR 50.44, the energy from metal-water and other chemical reactions that may result from degradation but not total failure of emergency core cooling functioning, (2) the limited experience and experimental data available for defining accident phenomena and containment responses, and (3) the conservatism of the calculational model and input parameters. SRP Section 3.8.2 provides acceptable methods, including load