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  1. 1
    Removal of a fuel element from a research reactor core while critical.

    Removal of a fuel element from a research reactor core while critical.

    Published 1992
    “…NRC information notice ;…”
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  2. 2
    Effect of incorrect strainer pressure drop on available net positive suction head

    Effect of incorrect strainer pressure drop on available net positive suction head

    Published 1997
    “…NRC information notice ;…”
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  3. 3
    Containment inspection rule

    Containment inspection rule

    Published 1997
    “…NRC information notice ;…”
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  4. 4
    Power oscillations at Washington Nuclear Power Unit 2.

    Power oscillations at Washington Nuclear Power Unit 2.

    Published 1992
    “…NRC information notice ;…”
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  5. 5
    Suceptibility of low-pressure coolant injection and core spray injection valves to pressure locking

    Suceptibility of low-pressure coolant injection and core spray injection valves to pressure locking

    Published 1995
    “…NRC information notice ;…”
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  6. 6
    Failure of reactor trip breaker to open because of cutoff switch material lodged in the trip latch mechanism

    Failure of reactor trip breaker to open because of cutoff switch material lodged in the trip latch mechanism

    Published 1995
    “…NRC information notice ;…”
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  7. 7
    Inadequate offsite power system voltages during design-basis events

    Inadequate offsite power system voltages during design-basis events

    Published 1995
    “…NRC information notice ;…”
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  8. 8
    Unanticipated reactor water drainage draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, and Fitzpatrick

    Unanticipated reactor water drainage draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, and Fitzpatrick

    Published 1999
    “…NRC information notice ;…”
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  9. 9
    Inadequate logic testing of safety-related circuits

    Inadequate logic testing of safety-related circuits

    Published 1995
    “…NRC information notice ;…”
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  10. 10
    Additional adverse effect of boric acid leakage potential impact on post-accident coolant ph.

    Additional adverse effect of boric acid leakage potential impact on post-accident coolant ph.

    Published 2004
    “…NRC information notice ;…”
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  11. 11
    Traversing in-core probe withdrawn at LaSalle County Station, Unit 1

    Traversing in-core probe withdrawn at LaSalle County Station, Unit 1

    Published 1996
    “…NRC information notice ;…”
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  12. 12
    Criticality monitoring system degradation at BWX Technologies, Inc., Nuclear Products Division, Lynchburg, VA.

    Criticality monitoring system degradation at BWX Technologies, Inc., Nuclear Products Division, Lynchburg, VA.

    Published 2003
    “…NRC information notice ;…”
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  13. 13
    Effect of adding gas into water storage tanks on the net positive suction head for pumps

    Effect of adding gas into water storage tanks on the net positive suction head for pumps

    Published 2002
    “…NRC information notice ;…”
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  14. 14
    Degradation of prestressing tendon systems in prestressed concrete containments

    Degradation of prestressing tendon systems in prestressed concrete containments

    Published 1999
    “…NRC information notice ;…”
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  15. 15
    Degradation of prestressing tendon systems in prestressed concrete containments

    Degradation of prestressing tendon systems in prestressed concrete containments

    Published 1999
    “…NRC information notice ;…”
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  16. 16
    Liner plate corrosion in concrete containments

    Liner plate corrosion in concrete containments

    Published 1997
    “…NRC information notice ;…”
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  17. 17
    Cement erosion from containment subfoundations at nuclear power plants

    Cement erosion from containment subfoundations at nuclear power plants

    Published 1997
    “…NRC information notice ;…”
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  18. 18
    Environmental qualification deficiency for cables and containment penetration pigtails

    Environmental qualification deficiency for cables and containment penetration pigtails

    Published 1997
    “…NRC information notice ;…”
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  19. 19
    Potential for high post-accident closed-cycle cooling water temperatures to disable equipment important to safety

    Potential for high post-accident closed-cycle cooling water temperatures to disable equipment important to safety

    Published 1996
    “…NRC information notice ;…”
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  20. 20
    Partial bypass of shutdown cooling flow from the reactor vessel

    Partial bypass of shutdown cooling flow from the reactor vessel

    Published 1996
    “…NRC information notice ;…”
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