Document: NUREG-0800
Document ID: 757f66f9-1dd5-4125-9970-089087134ad9
Document Type: srp
Title: FIRE PROTECTION PROGRAM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0905/ML090510170.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.5.1.1
CFR Part: 
CFR Title: 

Content:
s,@ as it applies to shared fire protection systems and potential fire impacts on shared SSCs important to safety. 5. 10 CFR Part 50, Appendix A, GDC 19, AControl Room,@ as it applies to providing the capability both inside and outside the control room to operate plant systems necessary to achieve and maintain safe-shutdown conditions. 6. 10 CFR Part 50, Appendix A, GDC 23, AProtection System Failure Modes,@ as it applies to safe-failure states of the protection system when exposed to adverse conditions associated with fire events or inadvertent operation of fire protection systems. 7. 10 CFR Part 50, Appendix R, AFire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979,@ which establishes the FPP requirements for nuclear power plants operating prior to January 1, 1979, subject to the provisions in 10 CFR 50.48(b). Appendix R establishes, along with other fire protection requirements, the requirement to demonstrate that one success path of SSCs necessary to achieve and maintain safe shutdown of the reactor is protected from the effects of fire. The substantive provisions of Appendix R, or portions thereof, may apply to plants licensed to 9.5.1.1-6 Revision 0 – February 2009 operate after January 1, 1979, to the extent incorporated in or provided for in the fire protection licensing basis for the individual plants. 8. 10 CFR Part 52, AEarly Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants,@ which establishes regulatory requirements applicable to new reactors. 9. 10 CFR 52.47(b)(1), which requires that a DC application contain the proposed ITAAC that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, a plant that incorporates the DC is built and will operate in accordance with the DC, the provisions of the Atomic Energy Act (AEA), and the NRC's regulations; 10. 10 CFR 52.80(a), which