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.JS Sim Phase 3-4-20 COPY > Week 6 > Flashcards

Week 6 Flashcards

1
Q
  • Unit 1 tripped from 100% full power.
  • SIAS, CIAS, MSIS, and AFAS-1 have initiated.
  • The RCS is in forced circulation.
  • Steam Generator #1 pressure is 750 psia and dropping rapidly.
  • Steam Generator #1 level is 8% WR and dropping rapidly
  • Steam Generator #2 pressure is 940 psia and slowly lowering.
  • Steam Generator #2 level is 37% WR and slowly lowering.
  • Auxiliary feedwater flow is > 2000 gpm to steam generator #1.
  • Auxiliary feedwater flow is 0 gpm to steam generator #2.

WHICH one of the following actions correctly addresses the existing symptoms?

A. Stop feeding SG #1 and ensure feedwater flow is restoring level in SG #2.
B. Throttle and balance flow to each steam generator.
C. Stop feeding SG #1 and allow SG #2 to feed in RTO.
D. Allow maximum flow to SG #1 until level is greater than 10% WR.

A

A. Stop feeding SG #1 and ensure feedwater flow is restoring level in SG #2.

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2
Q
  • An ESD has occurred due to a steam line break inside containment.
  • The Operating crew has just entered in the ESD procedure.
  • Containment pressure peaked and is stable at 9 psig
  • Containment temperature is 186°F.
  • PZR level is 12% and rising.
  • RVUH is 100%.
  • RCS subcooling is 112°F
  • SG 1 is at 24% WR (increasing) and being fed from AFW at 505 gpm.
  • SG 2 is below the indicated level.
  • Both HPSI pumps are injecting into the RCS.

Based on these conditions, the operator should…

A. throttle HPSI immediately.
B. maximize feedflow to SG 1 and throttle HPSI when PZR level reaches 15%.
C. throttle HPSI when PZR level reaches 15%.
D. maximize feedflow to SG 1.

A

C. throttle HPSI when PZR level reaches 15%.

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3
Q
  • The reactor has tripped.
  • An ESD has occurred on SG #1.
  • SG #1 has just reached dryout.
The following indications are available to the Secondary Operator: 
 •Loop 1 T-cold 392°F  
•Loop 1 T-hot 480°F  
•Loop 2 T-cold 460°F 
•Loop 2 T-hot 488°F

Which one of the following pressures indicates the pressure that SG # 2 should be reduced to?

A. 465 psia.
B. 225 psia.
C. 610 psia.
D. 565 psia.

A

B. 225 psia.

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4
Q
  • Pressurizer pressure 1650 psia and decreasing
  • Subcooled margin is 95°F and increasing
  • No activity in the Containment or Steam Plant
  • A single event is in progress with no other complications

The most likely diagnosis for this condition is:

A. ESD
B. LOCA
C. LOOP
D. SGTR

A

A. ESD

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5
Q

During an ESD, why should safety injection be throttled as soon as the throttle criteria is met?

A. Prevents excessive cooldown.
B. Minimizes erosion damage to the injection valves.
C. Minimizes the time SI pumps are running on mini-flow.
D. Minimizes the possibility of pressurized thermal shock.

A

D. Minimizes the possibility of pressurized thermal shock.

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6
Q
  • Pressurizer pressure is 2290 psia and slowly increasing.
  • Tc is 572°F and slowly increasing.
  • Subcooled margin is 45°F and lowering (getting worse).
  • No indications of activity in the Containment or Steam Plant.

The most likely diagnosis for this condition is:

A. Uncomplicated Reactor Trip.
B. Steam Line Break (ESD) outside containment.
C. Feedline break (ESD) outside containment.
D. Large Break LOCA.

A

C. Feedline break (ESD) outside containment.

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7
Q
  • The faulted S/G is isolated and the unisolated S/G is at 38% WR and slowly lowering.
  • All Reactor Coolant Pumps (RCPs) are secured.
  • RCS is subcooled (>34°F using CET’s).
  • Pressurizer level is 36% and stable.
  • 100% in the Upper Head is indicated by RVLMS.

What parameter is inadequate for throttling HPSI?

A. steam generator level.
B. subcooling margin.
C. pressurizer level.
D. Safety Injection flow.

A

A. steam generator level.

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8
Q
  • A ESD has occurred due to a steam line break on SG 2 inside containment.
  • The operating crew is in the process of performing the SPTAs.
  • Containment pressure is at 10 psig and rising.
  • Containment temperature is in excess of 200°F.
  • PZR level is 12% and rising.
  • RCS temperature is rising.
  • RCS subcooling is 112°F.
  • SG 1 is at 45% WR and being feed from AFW at 300 gpm.
  • HPSI flow to the RCS is acceptible per appendix 2.

Based on these conditions, the operator should:

A. Start all available charging pumps.
B. throttle HPSI immediately.
C. immediately reduce RCS pressure to lower subcooling to less than 100°F.
D. increase heat removal on SG 1 to stabilize Tc

A

D. increase heat removal on SG 1 to stabilize Tc

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9
Q
  • A steam leak occurs in the Turbine Building.
  • A manual reactor trip is initiated.
  • The turbine trip isolates the steam leak.
  • T-cold for both loops indicate 555°F.
  • The crew is performing the SPTAs.
  • SBCS is functioning properly.
  • No ESFAS actuations have occured

Based on these conditions, the Control Operator should…

A. stabilize RCS temperature at its present value with SBCS in manual.
B. continue the cooldown to a Tcold of 500°F.
C. initiate an MSIS and stabilize temperature using ADVs.
D. allow the RCS to heat up to its normal post trip band of 560° to 570°F Tcold.

A

D. allow the RCS to heat up to its normal post trip band of 560° to 570°F Tcold.

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10
Q
  • An overcooling transient occurred which dropped plant temperature uncontrollably to 470°F.
  • RCS temperature and pressure have been stablized on the left side of the 200°F subcooled line of Standard Appendix 2.

Which of the following actions is appropriate?

A. Cool down and repressurize the RCS.
B. Cool down and maintain RCS pressure constant.
C. Depressurize and maintain RCS temperature constant.
D. Heat up and repressurize the RCS.

A

C. Depressurize and maintain RCS temperature constant.

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11
Q

Which one of the following plant parameters is an indication that an excessive steam demand event is occurring? Assume the S/G is not dried out.

A. Lowering RCS temperature with increasing containment pressure.
B. Increasing reactor power with increasing RCS temperature.
C. Lowering RCS temperature with increasing pressurizer level.
D. Lowering RCS temperature with increasing pressurizer pressure.

A

A. Lowering RCS temperature with increasing containment pressure.

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12
Q
  • An excessive steam demand event is in progress with a S/G safety valve open.
  • S/G #2 has been determined to be the affected S/G.

Is there a concern with continuing to feed the affected S/G following an ESD event?

A. No, it will minimize the rebound effect.
B. Yes, it will fill the S/G and cover the tubes.
C. Yes, it will cause the RCS to cool down further and affect reactivity.
D. No, it will minimize the need for auxiliary feedwater.

A

C. Yes, it will cause the RCS to cool down further and affect reactivity.

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13
Q
  • The reactor has tripped.
  • An MSSV has stuck open on SG 1.
  • SG 1 is at 32% WR.
  • SG 1 is at 930 psia.
  • SG 2 is at 43% WR.
  • SG 2 is at 1060 psia.
  • LOOP 1 Tc 538°F, Th 559°F.
  • LOOP 2 Tc 556°F, Th 559°F.

With no operator action, which of the following describes the status of SG feedwater?

A. AFA and AFB are feeding both SGs.
B. Neither SG is receiving feedwater
C. AFA and AFB are feeding SG 1 only.
D. MFW is feeding both SGs in RTO at greater than 250 gpm.

A

B. Neither SG is receiving feedwater

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14
Q
  • Unit 1 is operating at 82% power.
  • All systems are in normal lineup when the generator trips due to a loss of field.
  • SBCV #4 is OOS.
  • CEA’s are not selected for large load reject.

Based on these conditions, the operating crew should:

A. immediately select CEAs for large load reject and manually initiate a cutback.
B. start a rapid shutdown per 40OP-9ZZ05, Power Operations.
C. trip the reactor.
D. insert CEAs in manual sequential.

A

C. trip the reactor.

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15
Q
  • Unit 1 is operating at rated power.
  • A Main Turbine trip occurs.
  • A RPCB fails to automatically actuate.
  • The Primary Operator IMMEDIATELY depresses the following two pushbuttons simultaneously:
  • “DROP SUBGRPS”
  • “LOSS OF FEEDPUMP”

Comparing the plant response to this action versus how the plant would have responded if the “LARGE LOAD REJECT” pushbutton has been depressed, which of the following is accurate?

The actions taken would result in…

A. a larger rise in pressurizer pressure.
B. more CEAs dropped on the RPCB.
C. fewer CEAs dropped on the RPCB.
D. a smaller rise in pressurizer pressure.

A

A. a larger rise in pressurizer pressure.

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16
Q
  • Unit 1 is operating at rated power.
  • The “A” Main Feed Pump trips.
  • A RPCB fails to automatically occur.

In order to manually initiate the required RPCB, the crew must:

A. depress and hold the DROP SUBGROUPS pushbutton, and then depress SUBGROUP SELECT pushbuttons 4, 5 and 22.
B. simultaneously depress the DROP SUBGROUPS and LOSS OF FEED PUMP pushbuttons.
C. first depress the DROP SUBGROUPS pushbutton, release, and then depress the LOSS OF FEED PUMP pushbutton.
D. first depress and release the DROP SUBGROUPS pushbutton, then the LOSS OF FEED PUMP pushbutton followed by SUBGROUP SELECT pushbuttons 4, 5 and 22.

A

B. simultaneously depress the DROP SUBGROUPS and LOSS OF FEED PUMP pushbuttons.

17
Q
  • Unit 1 plant power being lowered due to a Main Condenser Circ Water leak
  • CRS is currently performing actions in accordance with section 4 of 40AO-9ZZ10, Condenser Tube Rupture
  • Plant systems are aligned per section 4 of 40AO-9ZZ10
  • Rx power currently 65%
  • Secondary Operator reports an EHC malfunction resulting in current Tave being 5°F off program low

Based on current plant conditions and no additional Operator actions taken which of the below listed circumstances would cause a Quick Open block to be generated…..

A. Main Feed Pump “B” trip
B. Loss of NNN-D15
C. Main Turbine trip
D. Reactor Trip

A

D. Reactor Trip

18
Q

A large load rejection has resulted in a RPCB. This load rejection was due to a spurious failure in the EHC system and did NOT result in a turbine trip. RPCB has been taken to Test Reset and Auto Actuate Out of Service. The Operating Crew desires to pick up load on the Main Turbine.

In order to accomplish this, the Secondary Operator must…

A. raise the setting of the LOAD LIMIT potentiometer, since the setting of this control follows the SETBACK and RUNBACK down.
B. first reduce the LOAD LIMIT potentiometer until the LOAD LIMITING light comes on, then pick up load as necessary.
C. perform this manipulation with the LOAD SET pushbutton since the LOAD LIMIT potentiometer is out of the circuit until the original (pre-rejection) load has been established.
D. reduce turbine load below 15% to clear the SETBACK, then raise load as desired using the LOAD LIMIT potentiometer.

A

B. first reduce the LOAD LIMIT potentiometer until the LOAD LIMITING light comes on, then pick up load as necessary.

19
Q
  • Unit 1 is operating at 100%.
  • The Main Turbine trips due to low EHC pressure (leak).
  • The Reactor Power Cutback and Steam Bypass Control systems operate correctly and Reactor power stabilizes at 35%.
  • Engineering has determined that it will take at least 12 hours to correct the condition and it is desirable to bring the turbine back on line at that time.

At what power level should the reactor be stabilized?

A. 2%
B. 12%
C. 35%
D. 40%

A

B. 12%

20
Q
  • The unit is at 100% power.
  • The reactor power cutback system is in service with subgroups 4, 5 and 22 selected for a loss of feedpump event.
  • An operator at the Reactor Power Cutback System module (B04) pushes the TEST/RESET pushbutton twice.

What actions will occur if the operator now simultaneously pushes the LOSS OF FEEDPUMP and DROP SUBGROUPS pushbuttons?

A. No actions will occur.
B. Subgroups 4, 5 and 22 will drop. A turbine setback and runback will occur and the load limiter will engage.
C. ONLY a turbine runback will occur.
D. ONLY a turbine setback and turbine runback will occur.

A

D. ONLY a turbine setback and turbine runback will occur.

21
Q

Following a Reactor Power Cutback, how should the operating crew comply with Technical Specification 3.1.7, Regulating Control Element Assembly (CEA) Insertion Limits?

A. Enter the appropriate action, but add 2 hours to the completion time.
B. Enter the appropriate action, but add 4 hours to the completion time.
C. Do not apply the limiting condition for operation for up to 4 hours following the RPCB.
D. Do not apply the limiting condition for operation for up to 2 hours following the RPCB.

A

D. Do not apply the limiting condition for operation for up to 2 hours following the RPCB.

22
Q
  • Unit 2 has experienced a RPCB due to a loss of the ‘A’ Main Feed Pump
  • CEA subgroups 4, 5 and 22 have inserted
  • Reactor power is 65%
  • Main Turbine load is 925 MW

Based on these conditions the operator is directed to….

A. trip the reactor and perform SPTA’s.
B. depress the ‘Drop Sub Grps’ and ‘Loss of Feed Pump’ pushbuttons.
C. reduce the load limit potentiometer to 845 MW.
D. reduce the load limit potentiometer to 890 MW.

A

D. reduce the load limit potentiometer to 890 MW.

23
Q
  • Unit 1 is operating at rated power.
  • RPCS is in service with subgroups 4, 5 and 22 selected.
  • A Main Feed Pump trips.
  • In an unrelated failure, a Steam Header Pressure Transmitter (PT- 1024) fails low.

Based on this, the RPCS will drop selected CEAs and the Main Turbine will…

A. Setback, Not Runback.
B. Setback, Continuously Runback.
C. Not Setback, Not Runback.
D. Not Setback, Continuously Runback.

A

B. Setback, Continuously Runback.

24
Q
  • Unit 1 is operating at rated power.
  • Subgroup 5 has been transferred to the hold bus.
  • The ‘B’ Main Feed Pump trips.

Which of the following describe the plant response?

A. A normal RPCB will be initiated.
B. The reactor will trip if group 5 is not inserted manually within 40 seconds following the RPCB signal.
C. A RPCB will initiate with group four providing sufficient negative reactivity to offset the reduction of feedwater.
D. The reactor will trip immediately.

A

D. The reactor will trip immediately.

25
Q
  • Unit 1 is operating at rated power.
  • CEDMCS has been placed in STANDBY for maintenance activities.
  • The ‘B’ Main Feed Pump trips.

Which of the following describe the plant response?

A. A normal RPCB will be initiated.
B. RCS temperature will stabilize above program T- Ave.
C. RCS temperature will stabilize below program T- Ave.
D. The reactor will trip immediately.

A

B. RCS temperature will stabilize above program T- Ave.

26
Q

Regarding Mode 6 operations, (and using Tech Specs); The operating SDC (shutdown cooling) loop may be removed from service for:

A. testing only, not to exceed 8 hours in 24 hours.
B. 4 hour periods, with water level > 23’ above the vessel flange.
C. 1 hour in each 8 hour period, with no reduction in RCS Boron Concentration.
D. an unlimited time period, with no fuel movement.

A

C. 1 hour in each 8 hour period, with no reduction in RCS Boron Concentration.

27
Q
  • Unit 1 is operating in Mode 1.
  • A Pressurizer Safety valve becomes inoperable.
  • All other safety valves are operable.

What actions (if any) are required per Technical Specifications?

A. Restore the safety valve to OPERABLE status in 15 minutes.
B. No actions since the LCO is met.
C. Restore the safety valve to OPERABLE status in 30 minutes.
D. Restore the safety valve to OPERABLE status in 1 hour.

A

A. Restore the safety valve to OPERABLE status in 15 minutes.

28
Q
  • A plant cooldown is in progress.
  • RCS temperature is currently 362°F.
  • The secondary operator reports RCS cooldown rate for the last hour has been 120°F.

The operator is required to restore the cooldown rate to within limits in:

A. immediately.
B. 15 minutes.
C. 30 minutes.
D. 60 minutes.

A

C. 30 minutes.

29
Q

The bases for requiring all four SITs to be operable in Mode 1 are to ensure which of the following?

A. 50% of one SIT and 100% of 2 SITs will reach the core during a LOCA.
B. 100% of 2 SITs will reach the core during a LOCA.
C. 100% of all 4 SITs will reach the core during a LOCA.
D. 100% of 3 SITs will reach the core during a LOCA.

A

D. 100% of 3 SITs will reach the core during a LOCA.

30
Q

The Bases of Tech Spec 3.5.5, RWT, states:
The RWT ensures that an adequate supply of borated water is available to…

Which of the following is NOT part of the bases for this LCO?

A. maintain the reactor subcritical following a DBA.
B. cool and depressurize the containment in the event of a DBA and to cool and cover the core in the event of a LOCA.
C. ensure that an adequate level exists in the containment sump to support ESF operation in the recirculation mode.
D. ensure that the SI pumps can deliver at least 30 minutes of full flow (plus a 10% margin).

A

D. ensure that the SI pumps can deliver at least 30 minutes of full flow (plus a 10% margin).

31
Q

With an initial containment average air temperature less than or equal to the LCO temperature limit (3.6.5, Containment Air Temperature), we are assured that…

A. all instrumentation within containment is guaranteed to function properly.
B. during a LOCA Design Basis Accident (but NOT all Main Steam Line Breaks), the resultant peak accident temperature is maintained below the containment design temperature.
C. during a Design Basis Accident, the resultant peak accident temperature is maintained below the containment design temperature.
D. during a Main Steam Line Break Design Basis Accident (but NOT all LOCAs), the resultant peak accident temperature is maintained below the containment design temperature.

A

C. during a Design Basis Accident, the resultant peak accident temperature is maintained below the containment design temperature.

32
Q

The LCO on containment pressure prevents exceeding the…

A. containment maximum pressure design limit during a Design Basis Accident and minimum pressure design limit during an inadvertent CSAS.
B. containment maximum pressure design limit during a Design Basis Accident and minimum pressure during containment venting operations.
C. assumed time to Containment Spray flow during Design Basis Accident and minimum pressure design limit during an inadvertent CSAS.
D. assumed time to Containment Spray flow during Design Basis Accident and minimum pressure design limit during containment venting operations.

A

A. containment maximum pressure design limit during a Design Basis Accident and minimum pressure design limit during an inadvertent CSAS.

33
Q

Which of the following Containment conditions does NOT require a Technical Specification action to be performed within 1 hour?

A. Both CS pumps inoperable.
B. Containment pressure greater than the LCO limit.
C. One containment air lock inoperable.
D. Containment temperature above LCO limit.

A

D. Containment temperature above LCO limit.

.JS Sim Phase 3-4-20 COPY (5 decks)

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