Document: NRC Regulatory Guide
Document ID: c256f223-ee35-43e0-82e7-aa7b14469259
Document Type: regulatory_guide
Title: Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors + HISTORY - HISTORY DG-1253 , Proposed Revision 2 (Rev. 2)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1101/ML110110480.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.79
CFR Part: 
CFR Title: 

Content:
provisions in 10 CFR Part 52. DG-1253, Page 12 GLOSSARY OF ACRONYMS ADAMS - Agency Document Access and Management System ADS – Automatic Depressurization System AP1000 – Advanced Passive 1000 ASME - American Society of Mechanical Engineers CFR – Code of Federal Regulations CMT – Core makeup tank ECCS – Emergency Core Cooling System HPSI- High Pressure Safety Injection IRWST – In- Containment Refueling Water Storage Tank LOCA- Loss of Coolant Accident LPSI- Low Pressure Safety Injection MPSI – Mid Pressure Safety Injection NFPA – National Fire Protection Association OMB – Office of Management and Budget PCCS – Passive Core Cooling System PRHR – Passive Residual Heat Removal PWR _ Pressured Water Reactor RG – Regulatory Guide RCS – Reactor Coolant System RHR – Residual Heat Removal SSCs – Structures, Systems and Components DG-1253, Page 13 US EPR - United States Evolutionary Power Reactor US APWR – United States Advanced PWR US NRC – Unites States Nuclear Regulatory Commission DG-1253, Page 14 REFERENCES4 1. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” U.S. Nuclear Regulatory Commission, Washington, DC. 2. 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” U.S. Nuclear Regulatory Commission, Washington, DC. 3. Regulatory Guide 1.68, “Initial Test Programs for Water-Cooled Nuclear Power Plants,” Revision 3, March 2007. 4. Regulatory Guide 1.79, “Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors,” September 1975. 5. National Fire Protection Association (NFPA) Standard 805, “Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants,” 2001 Edition.5 6. Boiler and Pressure Vessel (B&PV) Code, American Society of Mechanical Engineers, ASME Standard, ASME Section III, Section NB/NC/ND-3620, “Design Considerations,” NB/NC/ND-3622.3, “Vibration,” New York, NY.6 7.