|
Y 3.N 88:56-2/94-42
|
Cracking in the lower region of the core shroud in boiling water reactors |
1 |
|
Y 3.N 88:56-2/94-43
|
Determination of primary-secondary steam generator leak rate |
1 |
|
Y 3.N 88:56-2/94-44
|
Main steam isolation valve failure to close on demand because of inadequate maintenance and testing |
1 |
|
Y 3.N 88:56-2/94-45
|
Potential common-mode failure mechanism for large vertical pumps |
1 |
|
Y 3.N 88:56-2/94-46
|
Nonconservative reactor coolant system leakage calculation |
1 |
|
Y 3.N 88:56-2/94-47
|
Accuracy of Information provided to NRC during the licensing process |
1 |
|
Y 3.N 88:56-2/94-48
|
Snubber lubricant degradation in high-temperature environments |
1 |
|
Y 3.N 88:56-2/94-49
|
Failure of torque switch roll pins |
1 |
|
Y 3.N 88:56-2/94-50
|
Failure of General Electric contactors to pull in at the required voltage |
1 |
|
Y 3.N 88:56-2/94-51
|
Inappropriate greasing of double shielded motor bearings |
1 |
|
Y 3.N 88:56-2/94-52
|
Inadvertent containment spray and reactor vessel draindown at Millstone Unit 1 |
1 |
|
Y 3.N 88:56-2/94-53
|
Hydrogen gas burn inside pressurizer during welding |
1 |
|
Y 3.N 88:56-2/94-54
|
Failures of General Electric magne-blast circuit breakers to latch closed |
1 |
|
Y 3.N 88:56-2/94-55
|
Problems with Copes-Vulcan pressurized power-operated relief valves |
1 |
|
Y 3.N 88:56-2/94-56
|
Inaccuracy of safety valve set pressure determinations using assist devices |
1 |
|
Y 3.N 88:56-2/94-57
|
Debris in containment and the residual heat removal system |
1 |
|
Y 3.N 88:56-2/94-58
|
Reactor coolant pump lube oil fire |
1 |
|
Y 3.N 88:56-2/94-59
|
Accelerated dealloying of cast aluminum-bronze valves caused by microbiologically induced corrosion |
1 |
|
Y 3.N 88:56-2/94-60
|
Potential overpressurization of main steam system |
1 |
|
Y 3.N 88:56-2/94-61
|
Corrosion of William Powell gate valve disc holders |
1 |
