Document: NUREG-0800
Document ID: bf02190e-dd85-4dc5-acdf-4e26bfa5492a
Document Type: srp
Title: Functional Design of Control Rod Drive System
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1211/ML12111A194.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.6
CFR Part: 
CFR Title: 

Content:
ssembly Withdrawal at Power DSRA SRSB 15.4.3 Control Rod Misoperation (System Malfunction or Operator Error) DSRA SRSB 15.4.4 - 15.4.5 Startup of an Inactive Loop or Recirculation Loop at an Incorrect Temperature, and Flow Controller Malfunction Causing an Increase in BWR Core Flow Rate DSRA SRSB 15.4.6 Inadvertent Decrease in Boron Concentration in the Reactor Coolant System (PWR) DSRA SRSB 15.4.7 Inadvertent Loading and Operation of a Fuel Assembly in an Improper Position DSRA SRSB 15.4.8 Spectrum of Rod Ejection Accidents (PWR) DSRA SRSB 15.4.8.A Radiological Consequences of a Control Rod Ejection Accident (PWR) DSEA RPAC 15.4.9 Spectrum of Rod Drop Accidents (BWR) DSRA SRSB 15.4.9.A Radiological Consequences of Control Rod Drop Accident (BWR) DSEA RPAC 15.5.1 - 15.5.2 Inadvertent Operation of ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory DSRA SRSB 15.6.1 Inadvertent Opening of a PWR Pressurizer Pressure Relief Valve or a BWR Pressure Relief Valve DSRA SRSB 15.6.2 Radiological Consequences of the Failure of Small Lines Carrying Primary Coolant Outside Containment DSEA RPAC 15.6.3 Radiological Consequences of Steam Generator Tube Failure (PWR) DSEA RPAC 15.6.4 Radiological Consequences of Main Steam Line Failure Outside Containment (BWR) DSEA RPAC 15.6.5 Loss of Coolant Accidents Resulting From Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary DSRA SRSB 15.6.5.A Radiological Consequences of a Design Basis Loss-of-Coolant Accident Including Containment Leakage Contribution DSEA RPAC DE CIB 15.6.5.B Radiological Consequences of a Design Basis Loss-of-Coolant Accident Leakage From Engineered Safety Feature Components Outside Containment DSEA RPAC 15.6.5.D Radiological Consequences of a Design Basis Loss-of-Coolant Accident: Leakage From Main Steam Isolation Valve Leakage Control System (BWR) DSEA RPAC 15.7.3 Postulated Radioactive Releases Due to Liquid-Containing Tank Failures DCIP