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 various containment sprays to remo
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, and (4) bringing the reactor
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 (MSIVLCS) required for some BWRs
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 piping systems.
Item C-6: LOCA Heat Sources
DESCRIPTION
Historical Background
As identified in NUREG-0471,[1]this issue involved staff evaluations of vendors' data and approaches for determining LOCA h
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 determining best estimate decay
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 analysis. These requirements
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.
Item C-1: Assurance of Continuous Long-Term Capability of Hermetic Seals on Instrumentation and Electrical Equipment
DESCRIPTION
Historical Background
This NUREG-0471[1]item was developed because of concerns regarding the long-term capability