Document: NUREG-0800
Document ID: 1d92e471-c01d-4c3b-8f23-e871a9de6e62
Document Type: srp
Title: describes the general procedures to be followed in reviewing any instrumentation and control
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500505.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.1
CFR Part: 
CFR Title: 

Content:
onal occurrences, – Provides the capability to operate with onsite electric power available (assuming offsite power is not available) and with offsite electric power available (assuming onsite power is not available), and – Provides the capability to be tested during reactor operation. • Single-failure criterion — The remote control stations and the equipment used to maintain safe shutdown should be designed to accommodate a single failure. See Appendix 7.1-B item 3 or Appendix 7.1-C item 4.1 • Independence — See Appendix 7.1-B item 7 and 8 and Appendix 7.1-C item 11 and 24. • Use of digital systems — See Appendix 7.0-A. • Periodic testing — See Appendix 7.1-B item 11 or see Appendix 7.1-C items 12 and 27. • Remote shutdown capability — Plant designs should provide for control in locations removed from the main control room that may be used for manual control and alignment of safe shutdown system equipment needed to achieve and maintain hot and cold shutdown. This control equipment should be capable of operating independently of (without interaction with) the equipment in the main control room. This equipment may include the remote shutdown station and other local controls. The design of remote shutdown stations should provide appropriate displays so that the operator can monitor the status of the shutdown. Typical parameters for PWR displays are steam generator level, steam generator pressure, pressurizer pressure, pressurizer level, reactor coolant temperature, and Rev. 4 — June 1997 SRP 7.4-6 auxiliary feedwater flow. Typical parameters for BWR displays are reactor vessel water level and pressure and high pressure core injection system flow. The remote shutdown capability should be capable of accommodating expected plant response following a reactor trip, including protective system actions which could occur as a result of plant cooldown. For example, in the cooldown of a PWR, reactor cooling system pressure will eventually drop below