Pressurized water reactors
Label
Pressurized water reactors
Name
Pressurized water reactors
Actions
Incoming Resources
- Technical resolution of Generic Issue No. B-59-(N-1) loop operation in BWRs and PWRs
- New information regarding insulation material performance and debris blockage of PWR containment sumps
- Bias estimates used in lieu of validation of fission products and minor actinides in MCNP Keff calculations for PWR burnup credit casks, prepared by D.E. Mueller [and three others]
- Unit startup with degraded high pressure safety injection system
- PWR low temperature overpressure protection
- Safety evaluation of Westinghouse topical reports dealing with elimination of postulated pipe breaks in PWR primary main loops
- RHR valve misalignment causes degradation of ECCS in PWRS
- Pressure boundary leakage identified on steam generator bowl drain welds
- Stress corrosion cracking in pressurized water reactor systems
- Inadvertent boron dilution events
- Supercritical-water-cooled reactor [SCWR]
- Knowledge and abilities catalog for nuclear power plant operators, pressurized water reactors, draft report for comment, prepared by D. Muller
- Spatial effects and uncertainty analysis for rod ejection accidents in a PWR, prepared by A. Avvakumov, V. Malofeev, V. Sidorov
- Flammable gas mixtures in the waste gas decay tanks in PWR plants
- Preliminary assessment of PWR steam generator modelling in RELAP5/MOD3, prepared by R.J. Preece, J.M. Putney
- Degradation or loss of charging systems at PWR nuclear power plants using swing-pump designs
- Plugging of safety injection pump lubrication oil coolers with lakeweed
- Questionnaire on steam generator operating history
- Undetected modification of flow characteristics in the high pressure safety Injection system
- Loss of thermal sleeves in reactor coolant system piping at certain Westinghouse Pwr power plants
- Assurance of sufficient net positive suction head for emergency core cooling and containment heat removal pumps
- Design of the reactor pressure vessel support system
- Degaded throttle valves in emergency core cooling system resulting from cavitation-induced erosion during a loss-of-coolant accident
- Pump shaft damage due to excessive hardness of shaft sleeve generator tubes
- Managing gas accumulation in emergency core cooling, decay heat removal, and containment spray systems
- Reliance on water level instrumentation with a common reference leg
- Overexposures in PWR cavities
- Inadvertent loss of capability for emergency core cooling system motors
- Knowledge base for the effect of debris on pressurized water reactor emergency core cooling sump performance, prepared by D.V. Rao, principal investigator ... [and others]
- Failure to detect freespan cracks in PWR steam generator tubes
- Potential failures of emergency core cooling systems caused by foreign material blockage
- Hydraulic transport of coating debris, a subtask of GSI-191, principal investigators, T. Fu and A. Fullerton ; prepared by A. Fullerton ... [and others]
- Long term low power operation in pressurized water reactors
- Assessment study of RELAP-5 MOD-2 cycle 36.01, based on the Doel-2 steam generator tube rupture incident of June 1979, prepared by E. J. Stubbe
- Steam generator tube ruptures at two PWR facilities
- Complete loss of main and auxiliary feedwater at a PWR designed by Babcock & Wilcox
- Forwarding of 2 tables of appendix I, draft radiological effluent technical specifications, PWR, and NUREG-0133
- Potential common cause vulnerabilities in essential service water systems
- Primary water stress corrosion cracking (PWSCC) of Inconel 600
- Potential loss of effective volume for containment recirculation spray at PWR facilities
- Main feedwater system degradation in safety-related ASME code class 2 piping inside the containment of a pressurized water reactor
- HPCI/RCIC high steam flow setpoints
- Stress corrosion cracking in PWR steam generator tubes
- Foreign material found in the emergency core cooling system
- Inadequate inservice testing of main steam isolation valves
- PWR auxiliary feedwater pump turbine control problems
- Westinghouse two-loop NSSS
- Potential impact of debris blockage on emergency recirculation during design basis accidents at pressurized-water reactors
- Inaccurate reactor water level indication and inadvertent draindown during shutdown
- Implementation of programmatic controls for radiological effluent technical specifications in the administrative controls section of the technical specifications and the relocation of procedural details of RETS to the offsite dose calculation manual or to the process control program