Document: NRC Regulatory Guide
Document ID: 3c238fa7-baa2-41c1-ac85-868fcda6b038
Document Type: regulatory_guide
Title: Design Limits, Loading Combinations, Materials, Construction, and Testing of Concrete Containments + HISTORY – HISTORY 07/2020 – DG-1372 , Proposed Revision 4 05/2019 – Periodic Review of Revision 3 – Revise 10/2015 – Periodic Review of Revision 3 – Reviewed with issues identified for future consideration 10/2006 – DG-1159, Proposed Revision 3 Prior to the issuance of DG-1159, RG 1.136 was entitled "Materials, Construction, and Testing of Concrete Containments (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2010/ML20105A215.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.136
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CFR Title: 

Content:
onditions and dynamic effects (of missiles, pipe whipping, and discharging fluids) associated with normal operation, maintenance, testing, and postulated accidents, including loss-of-coolant accidents (LOCAs). o GDC 16, “Containment Design,” requires, in part, that a reactor containment shall be provided to establish an essentially leak tight barrier against the uncontrolled release of radioactivity to the environment for as long as postulated accident conditions require. o GDC 50, “Containment Design Basis,” requires, in part, that the reactor containment structure, including access openings, penetrations, and the containment heat removal system, shall be designed so that the containment structure and its internal compartments can accommodate, without exceeding the design leakage rate and with sufficient margin, the calculated pressure and temperature conditions resulting from any LOCA. • Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” to 10 CFR Part 50, provides quality assurance (QA) requirements that apply to all activities DG-1372, Page 3 (e.g., design, procurement, fabrication, erection, inspection, testing, modification) affecting the safety-related functions of SSCs. • Appendix J, “Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors,” to 10 CFR Part 50, describes required leakage testing of the primary reactor containment for water-cooled power reactors. Leaktightness of the containment structure must be tested at regular intervals during the life of the plant. • Appendix S, “Earthquake Engineering Criteria for Nuclear Power Plants,” to 10 CFR Part 50 provides, in part, criteria for the implementation of GDC 2 with respect to earthquakes. This regulation defines requirements for the operating-basis earthquake (OBE) and the safe-shutdown earthquake (SSE). • 10 CFR Part 52 governs the issuance of, among others, standard design certifications, combined licenses,