Item C-11: Assessment of Failure and Reliability of Pumps and Valves
DESCRIPTION
Historical Background
The operating experience of nuclear power plants indicates that a number of valves, valve operators, and pumps fail to oper
Item C-10: Effective Operation of Containment Sprays in a LOCA
DESCRIPTION
This NUREG-0471[1]task will respond to a concern of the ACRS about the effectiveness of vario
Item C-9: RHR Heat Exchanger Tube Failures
DESCRIPTION
Historical Background
A BWR RHR system is designed for: (1) containment spray/suppression pool cooling, (2) fuel pool cooling augmentation, (3) low pressure coolant injection,
Item C-8: Main Steam Line Leakage Control Systems
DESCRIPTION
Historical Background
Dose calculations by AAB/NRR in 1975 indicated that operation of the main steam isolation valve leakage control system (MSI
Item C-7: PWR System Piping
DESCRIPTION
Combinations of fabrication, stress, and environmental conditions have resulted in isolated instances of stress corrosion cracking of low pressure Schedule 10 Type 304 stainless steel
Item C-6: LOCA Heat Sources
DESCRIPTION
Historical Background
As identified in NUREG-0471,[1]this issue involved staff evaluations of vendors' data and appr
Item C-5: Decay Heat Update
DESCRIPTION
Historical Background
As identified in NUREG-0471,[1]this issue involved following the work of research groups in de
Item C-4: Statistical Methods for ECCS Analysis
DESCRIPTION
Historical Background
As identified in NUREG-0471,[1]Appendix K of 10 CFR 50 specifies the requirements for LWR ECCS
Item C-3: Insulation Usage Within Containment
DESCRIPTION
Various kinds of insulation are used on piping and components inside the containment of a nuclear power plant.
Item C-2: Study of Containment Depressurization by Inadvertent Spray Operation to Determine Adequacy of Containment External Design Pressu
DESCRIPTION
Inadvertent operation of containment sprays can result in a rapid depressurization of the containment building.