Call Number (LC) Title Results
Y 3.N 88:56-2/95-27 NRC review of Nuclear Energy Institute "thermo-lag 330-1 combustibility evaluation methodology plant screening guide" 1
Y 3.N 88:56-2/95-28 Emplacement of support pads for spent fuel dry storage installations at reactor sites 1
Y 3.N 88:56-2/95-29 Oversight of design and fabrication facilities for metal components used in spent fuel dry storage systems 1
Y 3.N 88:56-2/95-30 Suceptibility of low-pressure coolant injection and core spray injection valves to pressure locking 1
Y 3.N 88:56-2/95-31 Motor-operated valve failure caused by stem protector pipe interference 1
Y 3.N 88:56-2/95-32 Thermo-lag 330-1 flame spread test results 1
Y 3.N 88:56-2/95-33 Switchgear fire and partial loss of offsite power at Waterford Generating Station, Unit 3 1
Y 3.N 88:56-2/95-34 Air actuator and supply air regulator problems in Copes-Vulcan pressurizer power-operated reliel valves 1
Y 3.N 88:56-2/95-35 Degraded ablity of steam generators to remove decay heat by natural circulation 1
Y 3.N 88:56-2/95-36 Potential problems with post-fire emergency lighting 1
Y 3.N 88:56-2/95-37 Inadequate offsite power system voltages during design-basis events 1
Y 3.N 88:56-2/95-38 Degradation of Boraflex neutron absorber in spent fuel storage racks 1
Y 3.N 88:56-2/95-39 Brachytherapy incidents involving treatment planning errors 1
Y 3.N 88:56-2/95-40 Supplemental information to Generic Letter 95-03 "Circumferential cracking of steam generator tubes" 1
Y 3.N 88:56-2/95-41 Degradation of ventilation system charcoal resulting from chemical cleaning of steam generators 1
Y 3.N 88:56-2/95-42 Commission decision on the resolution of generic issue 23 " Reactor coolant pump seal failure" 1
Y 3.N 88:56-2/95-43 Failure of the bolt-locking device on the reactor coolant pump turning vane 1
Y 3.N 88:56-2/95-44 Ensuring compatible use of drive cables incorporating Industrial Nuclear Company ball-type male connectors 1
Y 3.N 88:56-2/95-45 American Power Service falsification of American Society for Nondestructive Testing (ASNT) certificates 1
Y 3.N 88:56-2/95-46 Unplanned, undetected release of radioactivity from the exhaust ventilation system of a boiling water reactor 1