Resolution of generic issue 79, "Unanalyzed reactor vessel (PWR) thermal stress during natural convection cooldown".

Potential overpressurization of the component cooling water system.
Published: (1989)

Degradation of reactor coolant system pressure boundary resulting from boric acid corrosion.
Published: (1986)

Turbine overspeed and reactor cooldown during shutdown evaluation.
Published: (1994)

GSI-191 PWR sump screen blockage chemical effects tests : thermodynamic simulations /
Published: (2006)

Unresolved safety issues : pressurized thermal shock : oversight hearing before the Subcommittee on Oversight and Investigations of the Committee on Interior and Insular Affairs, House of Representatives, Ninety-seventh Congress, second session, on unresolved safety issues, pressurized thermal shock; hearing held in Washington, D.C., May 7, 1983.
Published: (1984)

PWR low temperature overpressure protection.
Published: (1982)

Depressurization of reactor coolant systems in pressurized-water reactors.
Published: (1987)

Pressure vessel codes : their application to nuclear reactor systems /
Published: (1966)

Inter-system discharge of reactor coolant.
Published: (1990)

Design of the reactor pressure vessel support system.
Published: (1978)

Potential for loss of shutdown cooling while at low reactor coolant levels.
Published: (1990)

NRC position on radiation embrittlement of reactor vessel materials and its impact on plant operations.
Published: (1988)

Post-refueling outage reactor pressure vessel leak testing before core criticality.
Published: (1998)

Unanalyzed post-LOCA release paths.
Published: (1986)

Reactor vessel top guide and core plate cracking.
Published: (1995)

Excessive cooldown and depressurization of the reactor coolant system following a loss of offsite power.
Published: (1995)

Loss of residual heat removal (RHR) while the reactor coolant system (RCS) is partially filled.
Published: (1987)

Recurring inspection of nuclear reactor steel pressure vessels /
Published: (1968)

Resolution of generic issue 101 "Boiling water reactor water level redundancy".
Published: (1989)

Thermal shock to reactor pressure vessels.
Published: (1981)

Irradiation embrittlement of reactor pressure vessels (RPVs) in nuclear power plants /
Published: (2015)

Modeling of reactor components using FIDAP : a finite element computer code /
by: Gangadharan, Anand, 1963-
Published: (1989)

Summary of meeting held on October 12, 1979 to discuss responses to IE bulletins 79-05C and 79-06C and HPI termination criteria.
Published: (1979)

Removal of the schedule for the withdrawal of reactor vessel material specimens from technical specifications.
Published: (1991)

Inadvertent containment spray and reactor vessel draindown at Millstone Unit 1.
Published: (1994)

Prediction of thermal-hydraulic performance of gas-cooled fast breeder reactors /
Published: (1977)

Degraded coatings and corrosion of steel containment vessels.
Published: (1989)

Irradiation Embrittlement of Reactor Pressure Vessels in Nuclear Power Plants.
Published: (2014)

Unanalyzed condition of reactor coolant pump seal leakoff line during postulated fire scenarios or station blackout.
Published: (2003)

Overexposure of diver in pressurized water reactor (PWR) refueling cavity.
Published: (1984)

HPCI/RCIC high steam flow setpoints.
Published: (1982)

Loose parts in the secondary side of steam generators at pressurized water reactors.
Published: (1983)

Pipe cracks in stagnant borated water systems at PWR plants.
Published: (1979)

Overpressurization of reactor coolant system.
Published: (1982)

Undetected loss of reactor coolant.
Published: (1987)

Inadequate control of reactor coolant system conditions during shutdown.
Published: (1993)