Document: NRC Regulatory Guide
Document ID: 6f0a99f2-d25a-44e3-b7f2-3286449a9752
Document Type: regulatory_guide
Title: Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident (Rev. 5)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2126/ML21266A185.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.82
CFR Part: 
CFR Title: 

Content:
Water Reactor Owners Group, Project No. 694,” December 20, 2007, ADAMS Accession No. ML073520295. 33. Westinghouse Electric Company, LLC, “Evaluation of Long-Term Cooling Considering Particulate, Fibrous and Chemical Debris in the Recirculating Fluid,” WCAP-16793-NP-A, Rev. 2, Pittsburgh, PA, July 2013, ADAMS Accession Nos. ML13239A114 and ML13239A115 (not publicly available). 34. Westinghouse Electric Company, LLC, “Comprehensive Analysis and Test Program for GSI-191 Closure (PA-SEE-1090),” WCAP-17788-P, Rev. 1, Pittsburgh, PA, July 17, 2015, ADAMS Accession No. ML20010F181 (package (contains both proprietary and non-proprietary versions of documents, proprietary versions are not publicly available). 35. Westinghouse Electric Company, LLC, “Evaluation of Post-Accident Chemical Effects in Containment Sump Fluids to Support GSI-191,” WCAP-16530-NP-A, Pittsburgh, PA, March 2008, ADAMS Accession No. ML081150379. 36. U.S. Nuclear Regulatory Commission, “Final Safety Evaluation by the Office of Nuclear Reactor Regulation, Topical Report WCAP-16530-NP ‘Evaluation of Post-Accident Chemical Effects in Containment Sump Fluids to Support GSI-191,’ Pressurized Water Reactor Owners Group, Project No. 694,” December 21, 2007, ADAMS Accession No. ML073520891. 37. U.S. Nuclear Regulatory Commission, “Use of Containment Accident Pressure in Analyzing Emergency Core Cooling System and Containment Heat Removal System Pump Performance in Postulated Accidents,” Commission Paper SECY-11-0014, January 31, 2011, ADAMS Accession No. ML102780586 (package). 2 Copies of International Atomic Energy Agency (IAEA) documents may be obtained through their 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-1385, Page 46 38. Nuclear Energy Institute, “Pressurized Water Reactor Sump Performance Evaluation Methodology,” NEI 04-07, Vol. 1, Rev. 0, Washington, DC, December 2004, ADAMS