|
Y 3.N 88:56-2/97-15
|
Reporting of errors and changes in large-break loss-of-coolant accident evaluation models of fuel vendors and compliance with 10 CFR 50.46(a)(3) |
1 |
|
Y 3.N 88:56-2/97-16
|
Preconditioning of plant structures, systems, and components before ASME code inservice testing or technical specification surveillance testing |
1 |
|
Y 3.N 88:56-2/97-17
|
Cracking of vertical welds in the core shroud and degraded repair |
1 |
|
Y 3.N 88:56-2/97-18
|
Problems identified during maintenance rule baseline inspections |
1 |
|
Y 3.N 88:56-2/97-19
|
Safety injection system weld flaw at Sequoyah Nuclear Power Plant, Unit 2 |
1 |
|
Y 3.N 88:56-2/97-20
|
Identification of certain uranium hexafluoride hexafluoride cylinders that do not comply with ANSI N14.1 fabrication standards |
1 |
|
Y 3.N 88:56-2/97-21
|
Availability of alternate AC power source designed for station blackout event |
1 |
|
Y 3.N 88:56-2/97-22
|
Failure of welded-steel moment-resisting frames during the Northridge Earthquake |
1 |
|
Y 3.N 88:56-2/97-23
|
Evaluation and reporting of fires and unplanned chemical reaction events at fuel cycle facilities |
1 |
|
Y 3.N 88:56-2/97-24
|
Failure of packing nuts on one-inch uranium hexafluoride cylinder valves |
1 |
|
Y 3.N 88:56-2/97-25
|
Dynamic range uncertainties in the reactor vessel level instrumentation |
1 |
|
Y 3.N 88:56-2/97-26
|
Degradation in small-radius u-bend regions of steam generator tubes |
1 |
|
Y 3.N 88:56-2/97-27
|
Effect of incorrect strainer pressure drop on available net positive suction head |
1 |
|
Y 3.N 88:56-2/97-28
|
Elimination of instrument response time testing under the requirements of 10 CFR 50.59 |
1 |
|
Y 3.N 88:56-2/97-29
|
Containment inspection rule |
1 |
|
Y 3.N 88:56-2/97-30
|
Control of licensed material during reorganization employee-management disagreements, and financial crises |
1 |
|
Y 3.N 88:56-2/97-31
|
Failures of reactor coolant pump thermal barriers and check valves in foreign plants |
1 |
|
Y 3.N 88:56-2/97-32
|
Defective worm shaft clutch gears in Limitorque motor-operated valve actuators |
1 |
|
Y 3.N 88:56-2/97-33
|
Unanticipated effect of ventilation system on tank level indications and engineering safety features actuation system setpoint |
1 |
|
Y 3.N 88:56-2/97-34
|
Deficiencies in licensee submittals regarding technology for radiological emergency action levels in accordance with the new Part 20 |
1 |
