ASSD

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Author:
heidin
ID:
156684
Filename:
ASSD
Updated:
2012-05-31 17:56:04
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ASSD ILC
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  1. ASSD-02 is being performed due to a Control Building fire. The following reactor pressure readings are obtained from the Unit Two Remote Shutdown Panel at the indicated times:

    0100 1050 psig
    0115 780 psig
    0130 600 psig
    0145 450 psig
    0200 360 psig

    The reactor cooldown rate is:


    A. within both Technical Specification limits, and limits specified by ASSD-02.

    B. outside both Technical Specification limits, and limits specified by ASSD-02.

    C. within Technical Specification limits, but outside limits specified by ASSD-02.

    D. outside Technical Specification limits, but within limits specified by ASSD-02.
    D. outside Technical Specification limits, but within limits specified by ASSD-02.


    • Using ASSD-02 , Section A, figures 1 and 2, reactor temp is approx 550°F @ 0100,
    • approx 520°F @ 0115, approx490°F @ 0130, approx 460°F @ 0145, and approx
    • 440°F @ 0200. This is a cooldown of 110°F over the last hour. This is outside the
    • Tech Spec limit of 100°F/hour, but within the procedurally required 100°F /hour to120°F/hour cooldown directed by ASSD-02.
  2. During execution of ASSD-02, the Diesel Building Operator is performing required manipulations on DG4. In placing the seven keylock Normal/Local switches to Local, one of those switches is in a row above the other six switches.

    This switch must be turned to the Local position:


    A. last to prevent tripping the diesel lockout relay.
    B. first to prevent tripping the diesel lockout relay.
    C. last to prevent loss of diesel engine control power.
    D. first to prevent loss of diesel engine control power.
    C. last to prevent loss of diesel engine control power.


    The six switches in a row isolate DG engine and generator control circuitry from the fire area since a fire induced fault in wiring in the fire area may result in loss of the DG. The seventh switch inserts redundant control power fuses to the circuitry that has been isolated in the event a fault has already resulted in blowing the normal fuses. This seventh switch must be turned last with the potentially faulted circuitry already isolated or the alternate fuses may also blow making the DG unavailable. The DG engine lockout is already tripped if the DG had been running since the operator is directed to trip the DG using emergency stop.
  3. When performing an ASSD Shutdown at the RSDP, which of the following conditions is NOT expected to cause the RCIC Turbine Trip "Red Light" to energize at the RSDP.

    A. RCIC Turbine Overspeed.
    B. RCIC Pump LOW Suction Pressure.
    C. RCIC Turbine High Exhaust Diaphragm Pressure.
    D. Manual TRIP Pushbutton is depressed at the RSDP.
    A. RCIC Turbine Overspeed.
  4. A fire in XU-5 has rendered the Control Room uninhabitable. A loss of off-site power has occurred and all 4 EDGs started and tied to their respective E-bus. Required ASSD actions were successfully performed prior to the crew evacuating the Control Room. Once all stations are manned, which of the following describes the initial ASSD field actions to be taken?

    A. Trip all four EDGs and restart EDG 2 and energize the associated E-Bus only.
    B. Trip EDGs 2 and 4, strip the associated E-Buses, restart EDGs 2 and 4, then re-energize the associated E-Buses.
    C. Trip all four EDGs and restart EDG 1 and energize the associated E-Bus only.
    D. Trip EDGs 1 and 3, strip the associated E-Buses, restart EDGs 1 and 3, then re-energize the associated E-Buses.
    B. Trip EDGs 2 and 4, strip the associated E-Buses, restart EDGs 2 and 4, then re-energize the associated E-Buses.


    Fire in the control room requires entry into 0ASSD-01, branching to 0ASSD-02. With all 4 EDGs initially running and tied to their respective E-bus, 0ASSD-02 Sections F & G are used to remove EDGs 2 & 4 from service, transfer their control power to the ASSD supply, and then restart them. Associated 4KV buses are stripped and then reloaded as well. RCIC is started for RPV level control, and SRVs are not used to depressurize until RCIC is maintaining level 170” – 200”. EDGs 1 & 3, if running, are tripped.
  5. A fire in the Control Building requires Control Room evacuation and entry into ASSD-02.ASSD-02 directs the Senior Control Operator to trip the Unit Two (2) RPS MG Set output breakers and open the DC supply breakers to Distribution Panels 4A and 4B.Failure to perform this action could result in:

    A. misoperation of RCIC.
    B. loss of drywell cooling.
    C. inability to operate SRVs.
    D. spurious operation of MSIVs.
    D. spurious operation of MSIVs.
  6. A fire in the control building fire area requires entry into 0PFP-013, General Fire Plan,
    and 0ASSD-01, Alternative Safe Shutdown Procedure Index. The SCO has determined that alternate safe shutdown actions are required.

    Which one of the following identifies the next action that is required in accordance with ASSD-01 after a manual scram of both units and also identifies what procedure(s) are performed following these actions?

    A. Place MSIV control switches in close;
    Perform 0ASSD-02, Control Building, only.
    B. Trip both Reactor Recirc pumps;
    Perform 0ASSD-02, Control Building, only.
    C. Trip both Reactor Recirc pumps;
    Perform 0AOP-32, Plant Shutdown From Outside the Control Room, concurrently with 0ASSD-02, Control Building.
    D. Place MSIV control switches in close;
    Perform 0AOP-32, Plant Shutdown From Outside the Control Room, concurrently with 0ASSD-02, Control Building.
    • A. Place MSIV control switches in close;
    • Perform 0ASSD-02, Control Building, only.


    All of the available responses are actions required for AOP-32 Plant Shutdown from Outside the Control Room, therefore plausible options. Of these actions, the only one directed from the applicable section of ASSD-01 is to place the MSIV control switches to close. If there is a fire, AOP states to exit this procedure.

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