Document: 10 CFR Part 50
Document ID: 07c52eb1-b952-4f98-bfad-2525695d6ad5
Document Type: cfr
Title: Licensee event report system.
Source: 10 CFR Part 50
Source URL: https://www.ecfr.gov/current/title-10/part-50/section-50.73
Revision Date: 
Chapter: 
Section ID: 50.73
CFR Part: 50
CFR Title: 10

Content:
ant's Technical Specifications authorized pursuant to § 50.54(x) of this part . ( ii ) Any event or condition that resulted in: ( A ) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded; or ( B ) The nuclear power plant being in an unanalyzed condition that significantly degraded plant safety. ( iii ) Any natural phenomenon or other external condition that posed an actual threat to the safety of the nuclear power plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the nuclear power plant. ( iv ) ( A ) Any event or condition that resulted in manual or automatic actuation of any of the systems listed in paragraph (a)(2)(iv)(B) of this section, except when: ( 1 ) The actuation resulted from and was part of a pre-planned sequence during testing or reactor operation; or ( 2 ) The actuation was invalid and; ( i ) Occurred while the system was properly removed from service; or ( ii ) Occurred after the safety function had been already completed. ( B ) The systems to which the requirements of paragraph (a)(2)(iv)(A) of this section apply are: ( 1 ) Reactor protection system (RPS) including: reactor scram or reactor trip. ( 2 ) General containment isolation signals affecting containment isolation valves in more than one system or multiple main steam isolation valves (MSIVs). ( 3 ) Emergency core cooling systems (ECCS) for pressurized water reactors (PWRs) including: high-head, intermediate-head, and low-head injection systems and the low pressure injection function of residual (decay) heat removal systems. ( 4 ) ECCS for boiling water reactors (BWRs) including: high-pressure and low-pressure core spray systems; high-pressure coolant injection system; low pressure injection function of the residual heat removal system. ( 5 ) BWR reactor core isolation cooling system; isolation condenser system; and feedwater coolant injection system. ( 6 ) PWR auxiliary or