Y 3.N 88:56-2/2010-03
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Failures of motor-operated valves due to degraded stem lubricant |
1 |
Y 3.N 88:56-2/2010-04
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Diesel generator voltage regulation system component due to latent manufacturing defect |
1 |
Y 3.N 88:56-2/2010-05
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Management of steam generator loose parts and automated eddy current data analysis |
1 |
Y 3.N 88:56-2/2010-06
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Inadvertent control rod withdrawal event while shutdown |
1 |
Y 3.N 88:56-2/2010-07
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Welding defects in replacement steam generators |
1 |
Y 3.N 88:56-2/2010-08
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Welding and nondestructive examination issues |
1 |
Y 3.N 88:56-2/2010-09
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Importance of understanding circuit breaker control power indications |
1 |
Y 3.N 88:56-2/2010-10
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Implementation of a digital control system under 10 CFR 50.59 |
1 |
Y 3.N 88:56-2/2010-11
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Potential for steam voiding causing residential heat removal system inoperabilty |
1 |
Y 3.N 88:56-2/2010-12
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Containment liner corrosion |
1 |
Y 3.N 88:56-2/2010-13
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Failure to ensure that post-fire shutdown procedures can be performed |
1 |
Y 3.N 88:56-2/2010-14
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Containment concrete surface condition examination frequency and acceptance criteria |
1 |
Y 3.N 88:56-2/2010-15
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Fuel cycle facilty configuration management errors |
1 |
Y 3.N 88:56-2/2010-16
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Failure to disable unsafe geometry bandsaw reservior results in critcality safety-related alert |
1 |
Y 3.N 88:56-2/2011-01
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Commercial-grade dedication issues identified during NRC inspections. |
1 |
Y 3.N 88:56-2/2011-02
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Operator performance issues involving reactivity management at nuclear power plants. |
1 |
Y 3.N 88:56-2/2011-03
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Nonconservative criticality safety analyses for fuel storage. |
1 |
Y 3.N 88:56-2/2011-04
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Contaminants and stagnant conditions affecting stress corrosion cracking in stainless steel piping in pressurized water reactors. |
1 |
Y 3.N 88:56-2/2011-05
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Tohoku-Taiheiyou-Oki earthquake effects on Japanese nuclear power plants. |
1 |
Y 3.N 88:56-2/2011-06
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Erroneous criticality alarm monitoring signal caused by incorrect data acquisition module configuration. |
1 |