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:
tandards Institute ASME American Society of Mechanical Engineers ATWS anticipated transient without scram BWR boiling-water reactor BWROG Boiling Water Reactor Owners’ Group CAP containment accident pressure CS core spray DBA design-basis accident ECCS emergency core cooling system GDC general design criterion (criteria) HI Hydraulic Institute LCO limiting condition for operation LOCA loss-of-coolant accident NPSH net positive suction head NPSHa net positive suction head available NPSH margin net positive suction head margin (NPSHa – NPSHr) NPSH margin ratio net positive suction head ratio (NPSHa/NPSHr) NPSHr net positive suction head required NRC U.S. Nuclear Regulatory Commission PWR pressurized-water reactor RHR residual heat removal SBO station blackout TDH total dynamic head TS technical specification(s) DG-1385, Appendix B, Page B-28 REFERENCES B-1 Grist, E., Cavitation and the Centrifugal Pump: A Guide for Pump Users, Taylor and Francis, Philadelphia, PA, 1998. B-2 American National Standards Institute/Hydraulic Institute, ANSI/HI 14.6-2016, “American National Standard for Rotodynamic Pumps for Hydraulic Performance Acceptance Tests,” Parsippany, NJ. B-3 Bonaca, Mario V., Chairman, Advisory Committee on Reactor Safeguards, letter to R.W. Borchardt, Executive Director for Operations, U.S. Nuclear Regulatory Commission, “Crediting Containment Overpressure in Meeting the Net Positive Suction Head Required to Demonstrate That the Safety Systems Can Mitigate the Accidents as Designed,” March 18, 2009, Agencywide Documents Access and Management System (ADAMS) Accession No. ML090700464. B-4 Vietti-Cook, Annette L., Secretary, letter to R.W. Borchardt, Executive Director for Operations, U.S. Nuclear Regulatory Commission, “Staff Requirements—SECY-11-0014—Use of Containment Accident Pressure in Analyzing Emergency Core Cooling System and Containment Heat Removal System Pump Performance in Postulated Accidents,” March 15, 2011, ADAMS Accession No.