Document: NUREG-0800
Document ID: 2b0752f4-9104-408c-b400-d0ec931a3dbf
Document Type: srp
Title: FIRE PROTECTION PROGRAM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350030.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.5.1
CFR Part: 
CFR Title: 

Content:
ms." NFPA 12A-1973, "Halon 1301 Systems." NFPA 12B-1973, "Halon 1211 Systems." NFPA 13-1976, "Sprinkler Systems." NFPA 14-1974, "Standpipe and Hose Systems." NFPA 15-1973, `Water Spray Fixed Systems." NEPA 16-1973, "Foam-Water Sprinkler and Spray Systems." NFPA 20-1973, "Centrifugal Fire Pumps." NFPA 24-1973, "Outside Protection." NFPA 26-1958, "Supervision of Valves." NFPA 27-1975, "Private Fire Brigade." NFPA 30-1973, "Flammable Combustible Liquids Code." NFPA 51B-1976 "Cutting and Welding Processes." NFPA 69-1973, "Explosion Prevention Systems." NFPA 70-1975, "National Electrical Code." NFPA 720-1975, "Proprietary Protective Signaling Systems." NFPA 72E-1974, "Automatic Fire Detectors." 9.5.1-50 Rev. 2 - July 1981 NFPA 80-1975, "Fire Doors and Windows." NFPA 92M-1972, "Waterproofing and Draining of Floors." NFPA 197-1966, "Initial Fire Attack, Training, Standard On." NFPA 204-1968, "Smoke and Heat Venting Guide." NFPA 220-1975, "Types of Building Construction." NFPA 251-1975, "Fire Tests, Building Construction and Materials." NFPA 259-1976, "Test Method for Potential Heat of Building Materials." NFPA 802-1974, "Recommended Fire Protection Practice for Nuclear Reactors." U.S. Nuclear Regulatory Commission Documents NUREG-0050, "Recommendations Related to Browns Ferry Fire," Report by Special Review Group, February 1976. WASH-1400 (NUREG-75/014), "Reactor Safety Study - An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants,' October 1975. NUREG-75/087, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants." Section 9.5.1, "Fire Protection Program." Section 3.6.1, "Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment." Section 6.4, "Habitability Systems." Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Licensing of Production and Utilization Facilities," General Design Criterion 3, "Fire Protection." Regulatory Guide 1.6,