Document: NRC Regulatory Guide
Document ID: 8e45dce1-e1e7-4415-b1dd-7e2a610e545b
Document Type: regulatory_guide
Title: Fire Protection for Nuclear Power Plants (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2023/ML20231A835.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.189
CFR Part: 
CFR Title: 

Content:
ever practical throughout the unit, particularly in locations such as the containment and control room. Fire detection and firefighting systems of appropriate capacity and capability shall be provided and designed to minimize the adverse effects of fires on SSCs important to safety. GDC 3 also requires that firefighting systems be designed to ensure that their rupture or inadvertent operation does not significantly impair the safety capability of these SSCs. o 10 CFR Part 50, Appendix A, GDC 5, “Sharing of structures, systems, and components,” prohibits nuclear power units from sharing SSCs important to safety unless the licensees can show that such sharing will not significantly impair the units’ ability to perform their safety functions, including, in the event of an accident in one unit, an orderly shutdown and cooldown of the remaining units. o 10 CFR Part 50, Appendix A, GDC 19, “Control room,” requires that the licensee provide a control room from which actions can be taken to operate the nuclear power unit safely under normal conditions and to maintain it in a safe condition under accident conditions. Adequate radiation protection shall be provided to permit access and occupancy of the control room under accident conditions without personnel receiving radiation exposures in excess of 5 millirem (mrem) whole body, or its equivalent to any part of the body, for the duration of the accident. GDC 19 also requires that equipment at appropriate locations outside the control room have (1) a design capability for prompt hot shutdown of the reactor, including necessary instrumentation and controls to maintain the unit in a safe condition during hot shutdown, and DG-1359, Page 3 (2) the potential capability for subsequent cold shutdown of the reactor through the use of suitable procedures. o 10 CFR Part 50, Appendix A, GDC 23, “Protection system failure modes,” requires that the protection system be designed to fail into a safe state or into a state