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
CFR Part: 
CFR Title: 

Content:
stems for Nuclear Power Plants,” Vienna, Austria, 2019.8 48. IAEA, Safety Guide No. NS-G-1.6, “Seismic Design and Qualification for Nuclear Power Plants,” Vienna, Austria, 2003. 49. IAEA, Safety Guide No. NS-G-2.6, “Maintenance, Surveillance and In-Service Inspections in Nuclear Power Plants,” Vienna, Austria, 2002. 50. IAEA, Safety Guide No. NS-G-3.6, “Geotechnical Aspects of Site Evaluation and Foundations for Nuclear Power Plants,” Vienna, Austria, 2004. 51. IAEA, Specific Safety Guide No. SSG-48, “Aging Management and Development of a Programme for Long Term Operations of Nuclear Power Plants,” Vienna, Austria, 2018. 52. IAEA, Nuclear Energy Series No. NP-T-2.5, “Construction Technologies for Nuclear Power Plants,” Vienna, Austria, 2011. 53. IAEA Specific Safety Guide SSG-38, “Construction for Nuclear Installations,” Vienna, Austria, 2015. 54. ASTM 370-18, “Standard Test Methods and Definitions for Mechanical Testing of Steel Products,” West Conshohocken, PA, 2018. 8 Copies of IAEA documents may be obtained through its Web site WWW.IAEA.Org/ or by writing the International Atomic Energy Agency, P.O. Box 100 Wagramer Strasse 5, A-1400, Vienna, Austria. DG-1372, Page 30 55. ASTM A1034/A1034M, “Standard Test Methods for Testing Mechanical Splices for Reinforcing Bars,” West Conshohocken, PA, 2010a (Reapproved 2015). 56. NRC, Management Directive 8.4, “Management of Backfitting, Forward Fitting, Issue Finality, and Information Requests,” Washington, DC. DG-1372, Appendix A, Page A-1 APPENDIX A STAFF POSITION ON BOILING-WATER REACTOR CONTAINMENT POOL DYNAMICS (SOURCE: APPENDIX A TO STANDARD REVIEW PLAN SECTION 3.8.1) A-1. LOSS-OF-COOLANT ACCIDENTS a. Loads associated with loss-of-coolant accidents (LOCAs) (such as drywell pressure; annulus pressurization; suppression pool pressures including chugging, condensation oscillation, vent clearing, and pool swell; and jet loads and drag loads acting on submerged structures/components