Document: NUREG-0800
Document ID: 988a555f-fdfa-4452-829d-c06654bfbba5
Document Type: srp
Title: Initial Plant Test Program - Design Certification and New License Applicants
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070660618.pdf
Revision Date: 2023-06
Chapter: 14
Section ID: 14.2
CFR Part: 
CFR Title: 

Content:
priate controls should be provided to maintain these variables and systems within prescribed operating ranges. • GDC 19, as it pertains to control room requirements. The ITAAC should verify that (1) actions can be taken in the control room to safely operate the nuclear power unit under normal conditions, and maintain it in a safe condition under accident conditions, including LOCAs, and (2) adequate radiation protection has been provided to permit access to, and occupancy of, the control room under accident conditions, for the duration of the accident, without personnel receiving radiation exposures in excess of the total effective dose equivalent (TEDE) of 0.05 Sv (5 rem) specified in 10 CFR 50.2. 14.3-43 March 2007 • GDC 20, as it pertains to protection system design requirements. The ITAAC should verify that the protection system was designed to automatically initiate the operation of appropriate systems, including the reactivity control systems, to (1) ensure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences, (2) sense accident conditions, and (3) initiate the operation of systems and components important to safety. • GDC 21, as it pertains to protection system reliability and testability. The ITAAC should verify that the safety-related I&C systems were designed for high functional reliability and inservice testability. The ITAAC should also verify that the redundancy and independence designed into the systems should be sufficient to ensure that (1) no single failure results in loss of the protection function, and (2) removing any component or channel from service should not result in loss of the required minimum redundancy unless the acceptable reliability of protection system operation can otherwise be demonstrated. In addition, the ITAAC should verify that the protection system was designed to permit periodic testing of its functioning with the reactor in operation, and this capability