ML053250415

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Preliminary Issue List
ML053250415
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 11/15/2005
From:
NRC Region 4
To:
References
FOIA/PA-2004-0307
Download: ML053250415 (2)


Text

- A-cr - T5$S w Wt Preliminary Issue List Palo Verde Nuclear Generating Station Augmented Inspection Team NOTE: This is NOT an all-inclusive list.

  • A single phase to ground fault resulted in loss of offsite power and three unit trip

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  • Auxiliary Relay, Liberty Transmission Line Fault Detection/Protection System Failure
  • inadequate design resulted in single failure vulnerability
  • additional single failure design issues identified and corrected to extent practical
  • licensee also did not appear to make resolution of this issue a startup issue until the concern was raised by the AIT
  • Unit 1 Atmospheric Dump Valve 185 Failure
  • control room operator distraction with minimal impact on event response
  • apparent cause being determined
  • Unit 1 Letdown Heat Exchanger Isolation Failure
  • licensee performance deficiency associated with understanding implications of temporary modification installed in plant
  • little impact on control room response to event
  • some potential impact on fire response being reviewed by AIT
  • complicated event recovery efforts by delaying the return of offsite power to ESF buses
  • licensee determined apparent cause as "breaker not cycled frequently enough"
  • AIT challenged licensee on apparent cause, raised concern regarding current functionality of breakers
  • resident staff following as potential operability issue
  • resulted in a loss of power to Train "A" ESF busses following loss of offsite power
  • Unit 2, Train uE" Positive Displacement Charging Pump Trip
  • operator error resulted in suction line isolation and protective trip of pump
  • AIT identified that auxiliary operator was delayed approximately 10 minutes at the RCA access point even after the operator explained he was on a time critical mission
  • when RCA access delay was discussed with licensee, AIT determined that the licensee was unaware of delay .

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  • Unit 3 Bypass Valve/Control Cabinet Malfunctions
  • good operator actions minimized impact on plant, was operator distraction
  • potential design modification issue being reviewed by AIT as apparent cause
  • no impact on trip but some minor impacts on recovery
  • potential design issue associated with set point of thermal overloads
  • Unit 3 Low Pressure Safety Injection System In-leakage (Check Valve V217)
  • little impact on event, operator distraction to take manual actions to prevent over pressurization
  • apparent cause was Borg-Warner check valve leakage, potential maintenance issue
  • Unit 3 Variable Over Power Trip - Reactor Coolant Pump Speed Increase to 67 Hz
  • licensee investigating potential impacts on plant equipment
  • AIT raised questions about hydraulic affects, if any
  • apparent cause was test switch out of position
  • maintenance personnel failed to use restoration procedure six days prior to event following testing
  • some impact on emergency response organization which needed to use alternate TSC
  • complicated recovery efforts by delaying RCP restoration
  • appears minimum amperage basis involved NPSH limits
  • high voltage in switchyard resulted in low amperage I.

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  • Emergency Response Organization Notification Issues

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  • some delay in notification occurred but little impact
  • apparent cause associated with procedure adequacy and communication failures
  • Initial Notification of State and Local Official Issues
  • Unit 1 and Unit 3 did meet their guidelines on timeliness of initial notification
  • little overall impact because Unit 2 Alert Notification was timely
  • apparent cause being reviewed

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