Call Number (LC) Title Results
Y 3.N 88:56-2/93-57 Software problems involving digital control console systems at non-power reactors. 1
Y 3.N 88:56-2/93-58 Nonconservatism in low-temperature overpressure protection for pressurized-water reactors. 1
Y 3.N 88:56-2/93-59 Unexpected opening of both doors in an airlock. 1
Y 3.N 88:56-2/93-60 Reporting fuel cycle and materials events to the NRC Operations Center. 1
Y 3.N 88:56-2/93-61 Excessive reactor coolant leakage following a seal failure in a reactor coolant pump or reactor recirculation pump. 1
Y 3.N 88:56-2/93-62 Thermal stratification of water in BWR reactor vessels. 1
Y 3.N 88:56-2/93-63 Improper use of soluble weld purge dam material. 1
Y 3.N 88:56-2/93-64 Periodic testing and preventive maintenance of molded case circuit breakers. 1
Y 3.N 88:56-2/93-65 Reactor trips caused by breaker testing with fault protection bypassed 1
Y 3.N 88:56-2/93-66 Switchover to hot-leg injection following a loss-of-coolant accident in pressurized water reactors. 1
Y 3.N 88:56-2/93-67 Bursting of high pressure coolant injection steam line rupture discs injures plant personnel. 1
Y 3.N 88:56-2/93-68 Failure of pump shaft coupling caused by temper embrittlement during manufacture. 1
Y 3.N 88:56-2/93-69 Radiography events at operating power reactors. 1
Y 3.N 88:56-2/93-70 Deradation of boraflex neutron absorber coupons. 1
Y 3.N 88:56-2/93-71 Fire at Chernobyl Unit 2. 1
Y 3.N 88:56-2/93-72 Observations from recent shutdown risk and outage management pilot team inspections. 1
Y 3.N 88:56-2/93-73 Criminal prosecution of nuclear suppliers for wrongdoing. 1
Y 3.N 88:56-2/93-74 High temperatures reduce Limitorque AC motor operator torque. 1
Y 3.N 88:56-2/93-75 Spurious tripping of low-voltage power circuit breakers with GE RMS-9 digital trip units. 1
Y 3.N 88:56-2/93-76 Inadequate control of paint and cleaners for safety-related equipment. 1