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.JS Sim Phase 3-4-20 COPY > Week 2 > Flashcards

Week 2 Flashcards

1
Q

Faults that are not expected to occur, but are postulated nonetheless because their consequences include the potential for the release of significant amounts of radiation.

The preceding statement is the definition of what?

A. Limiting Event
B. Safety Limit
C. Limiting Fault
D. Design Basis Accident

A

C. Limiting Fault

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2
Q

Which of the following is a consequence of NOT restoring electrical power to the Water Reclamation Facility in a timely fashion following a SIAS concurrent with low switchyard voltage?

A. Double Sequencing
B. Higher concentration of silica in Circulating Water System
C. NAN-S05 and NAN-S06 control power is lost after 2 hours
D. Station Blackout generators will not start

A

B. Higher concentration of silica in Circulating Water System

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3
Q

The Boron Dilution Alarms must be confirmed operable within _______ following a reactor trip

A. 30 minutes
B. 1 hour
C. 2 hours
D. 4 hours

A

B. 1 hour

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4
Q
  • The unit has tripped and the CRS has diagnosed a LOAF with an inadvertent SIAS.
  • The CRS directs you to start AFN-P01.
  • Tc is 565 °F
  • The SIAS load shed panels have been re-energized
  • Suction valves are open and downcomer valves are in remote-auto
  • Indicating lights for AFN-P01 are lit.
  • You have gone to “START” one time using its handswitch (AFN-HS-11).

AFN-P01 is…

A. running but not feeding either Steam Generator.
B. running and feeding both Steam Generators.
C. not running, AFN-P01 can be started by going to “STOP” then “START”.
D. not running, AFN-P01 will start by going to “START” one more time.

A

C. not running, AFN-P01 can be started by going to “STOP” then “START”.

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5
Q
  • The plant is at 100% power.
  • Containment Pressure .1 psig.
  • LEG 1-3 CSAS A LEG 2-4 - window 5B05A.
  • LEG 1-3 CSAS B LEG 2-4 - window 5B05B.
  • CSAS - window 5C04A.
  • NO SIAS has actuated.
  • The Reactor has not tripped.
  • The operators stop the CS pumps as directed by procedure.

If an SIAS were to now occur, which one of the following statements describes how the CS pumps would be restarted?

A. Taking the CS pump handswitch to START twice.
B. The pumps would auto start.
C. Taking the CS pump handswitch to START once.
D. The pumps must be started manually at the local breakers.

A

A. Taking the CS pump handswitch to START twice.

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6
Q
  • A plant startup is being performed and reactor power is 6% and slowly increasing.
  • An inadvertent MSIS occurs, but the reactor does not trip.

Which one of the following operator actions should be taken?

A. Adjust the ADVs position demand to 30% and modulate them.
B. Stabilize reactor power and reset MSIS.
C. Borate the reactor subcritical and maintain RCS temperatures with the Atmospheric Dump Valves (ADVs).
D. Trip the reactor and proceed to 40EP-9EO01, SPTAs.

A

D. Trip the reactor and proceed to 40EP-9EO01, SPTAs.

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7
Q

An inadvertent CSAS “A” has occurred. The “A” EDG has started accordingly. The DG mode control switch is in Remote. What actions must the Control Room Operator take to correctly stop the DG?

A. Go to “STOP” at the DG handswitch at B01.
B. Reset the CSAS then stop the DG.
C. Override the CSAS by turning the DG handswitch at B01 to “STOP” then “START”.
D. Direct the AO to push the Engine Control pushbutton DGA-HS-01 “STOP” at DGA-B01.

A

B. Reset the CSAS then stop the DG.

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8
Q
  • An inadvertent CSAS has occurred.
  • The crew has taken the appropriate actions to close the spray header isolation valve (SIB-UV-671) and stop Containment Spray (CS) Pump “B”.
  • Subsequently a LOP occurs on PBB-S04, followed by a successful EDG “B” start and loading.

Which ONE of the following describes the status of Containment Spray Pump “B” and SIB-UV-671?

A. Running with SIB-UV-671 closed.
B. Off with SIB-UV-671 closed.
C. Off with SIB-UV-671 open.
D. Running with SIB-UV-671 open.

A

D. Running with SIB-UV-671 open.

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9
Q
  • Unit 1 is operating in Mode 5 with SDC in service.
  • The ‘A’ LPSI pump is operating.
  • An inadvertent Train ‘A’ RAS occurs.

Based on these conditions, what actions, if any, are necessary to maintain and/or restore the plant to a stable condition?

A. No actions should be necessary, since the RAS is only Train ‘A’.
B. Override and start the ‘A’ LPSI pump and restore SDC to service.
C. Override and open the minimum recirc valves to restore minimum flow protection for the ‘A’ LPSI pump.
D. Override and open the LPSI injection valves to restore SDC to service.

A

B. Override and start the ‘A’ LPSI pump and restore SDC to service.

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10
Q
  • Unit 1 is in hot shutdown.
  • RCP 1A is in hot standby.
  • Seal injection has been lost.

Concerning the 1A RCP, the operator should close the seal bleedoff valve…

A. within 3 minutes.
B. within 10 minutes.
C. prior to seal #2 outlet temperature of 250°F.
D. prior to seal #2 inlet temperature of 250°F.

A

C. prior to seal #2 outlet temperature of 250°F.

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11
Q
  • Unit 2 is in Mode 3
  • RCP 2A is in standby
  • The Controlled Bleedoff Valve is open

Which of the following conditions does not require the Controlled Bleedoff Valve to be closed?

A. Two RCP 2A Seals indicate failed
B. High Pressure Seal Cooler Leak
C. Controlled bleedoff flow is 9.5 gpm
D. Loss of Nuclear Cooling Water and it cannot be restored

A

A. Two RCP 2A Seals indicate failed

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12
Q
  • NCW flow to each RCP - 500 gpm.
  • Controlled bleedoff containment isolation valve(s) - open.
  • 2B RCP controlled bleedoff valve - open.
  • 2B RCP #2 Seal inlet pressure - 2200 psig.
  • 2B RCP #2 Seal outlet pressure - 500 psig

These parameters are indicative of a failure of:

A. #1 Seal.
B. #2 Seal.
C. #1 and #2 Seals.
D. #3 Seal.

A

A. #1 Seal.

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13
Q

•Unit 3 operating at 100% full power.
•RCP 1A has the following stable indications:
Seal #1 inlet pressure……………2250 psia
Seal #2 inlet pressure……………1950 psia
Seal #2 outlet pressure…………1740 psia
Controlled bleedoff flow………..7.9 gpm
Seal #1 inlet temperature………107°F
Seal #2 inlet temperature………106°F
Seal #2 outlet temperature…….105°F

WHICH ONE of the following describes the required action(s) for these conditions?

A. Trip reactor, stop RCN-P01A, isolate controlled bleedoff.
B. Commence 40ST-9RC02, RCS Water Inventory Balance.
C. Trip reactor, stop all reactor coolant pumps, isolate controlled bleedoff.
D. Commence plant shutdown by 40OP-9ZZ05, Power Operations.

A

D. Commence plant shutdown by 40OP-9ZZ05, Power Operations.

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14
Q

With the plant operating at power, the following readings are observed for 1A RCP:
Seal Injection flow…………..6.8 gpm
NC flow…………………………520 gpm (Alarms clear)
#2 seal inlet pressure……….1300 psig
#2 seal outlet pressure……..320 psig
Seal Bleedoff flow…………..2.3 gpm

Based on these readings, the crew should…

A. enter RCP Emergencies AOP.
B. enter the Excessive RCS Leakrate AOP.
C. trip the reactor and trip 1A RCP.
D. continue plant operation at power, all parameters are acceptable.

A

D. continue plant operation at power, all parameters are acceptable.

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15
Q

An RCP maintained in hot standby following a simultaneous loss of Seal Injection and NC could experience seal damage in as few as _____ minutes.

A. 3
B. 10
C. 20
D. 60

A

C. 20

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16
Q 
The Unit is operating at power, 1A RCP has the following indications:
#1 seal inlet pressure2250 psig
#2 seal inlet pressure1200 psig
#2 seal outlet pressure80 psig
Seal bleedoff flow1.2 gpm

These readings are indicative of:

A. #1 seal failure.
B. #2 seal failure.
C. #3 seal failure.
D. No seal failure.

A

C. #3 seal failure.

17
Q
  • The unit is at 100% power.
  • It has been determined that a 150 gpm high pressure seal cooler leak exists.

Before the affected HPSC is isolated, which one of the following describes the limitations on plant operation?

A. The plant must commence a normal shutdown within 72 hours.
B. The plant must be manually tripped and the affected RCP must be stopped.
C. The affected RCP must be stopped, resulting in a automatic trip.
D. Nuclear cooling water flow to the affected RCP must be increased.

A

B. The plant must be manually tripped and the affected RCP must be stopped.

18
Q
  • Unit 1 is at 100% power.
  • An RCS leak to the NC system is in progress.

Which of the following would be indicative of an RCS leak into the letdown heat exchanger?

A. backpressure control valve opening.
B. indicated letdown flow increasing.
C. backpressure control valve closing.
D. NC flow from the heat exchanger decreases.

A

C. backpressure control valve closing.

19
Q

The following alarms are received in control room:
•Regenerative Heat Exchanger high exit temperature alarm
•Letdown line low pressure alarm
•Low flow alarm in the process radiation monitor loop

Which of the following is the REQUIRED operator action?

A. Trip the reactor IMMEDIATELY
B. Trip the reactor in less than 10 minutes
C. Isolate letdown in less than 10 minutes
D. Restore seal injection in less than 3 minutes

A

C. Isolate letdown in less than 10 minutes

20
Q

Which of the following describes the required action upon receipt of a valid RU-1 containment radiation monitor HIGH alarm?

A. Initiate RCS leak rate calculation within 1 hour
B. Verify operability of the containment sump level monitors within 1 hour
C. Trip the reactor and manually initiate CIAS
D. Be in mode 3 within 6 hours

A

A. Initiate RCS leak rate calculation within 1 hour

21
Q

Technical Specification 3.1.4 places limits on both the positive and negative values of the core’s Moderator Temperature Coefficient (MTC) of Reactivity. These limits ensures that in the event of the limiting accident occuring, a violation of the accident analysis assumption(s) will NOT occur.

Of the choices below, which is the limiting accident for the NEGATIVE value of MTC?

A. CEA ejection.
B. Loss of all feedwater.
C. Continuous rod withdrawal.
D. Main steam line break.

A

D. Main steam line break.

22
Q
  • The plant is in Mode 3 with Reactor trip breakers open.
  • It is discovered that adequate SDM does not exist.

Based on these conditions, the crew is required to initiate boration to restore SDM…

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

A

B. within 15 minutes.

23
Q

The bases for meeting the LCO on Linear Heat Rate (13.1 kw/ft) is:

A. In the event of a LOCA, fuel clad temperature will not exceed 2200°F.
B. On loss of flow the calculated DNBR will be < actual DNBR.
C. It ensures that the POL based on linear heat rate will not be exceeded.
D. The measured radial peaking factors (RPF) will always be < calculated RPF.

A

A. In the event of a LOCA, fuel clad temperature will not exceed 2200°F.

24
Q
  • The plant is at 100% power.
  • A shutdown CEA slips into the core to 145” withdrawn.

In accordance with Tech Specs the operator should ….

A. not enter LCO 3.1.6, entry is not required for 2 hours.
B. enter LOC 3.1.6 immediately and restore shutdown CEAs to within limits in the next 4 hours.
C. no action is necessary.
D. enter LCO 3.1.6 immediately and restore shutdown CEAs to within limits in the next 2 hours.

A

D. enter LCO 3.1.6 immediately and restore shutdown CEAs to within limits in the next 2 hours.

25
Q
  • The plant is at 100% power.
  • A CEA misalignment has caused Azimuthal Power Tilt to exceed the limit specified in the Core Operating Limits Report (COLR).
  • COLSS is in service.

Which one of the following states the actions required by Tech. Specs?

A. Reduce the VOPT setpoints to < 35% within 16 hours.
B. Verify that COLSS is detecting the CEA alignment within 2 hours.
C. Restore measured Tq to less than the Tq allowance used in the CPC’s within 16 hours.
D. Reduce thermal power to < 50% RTP within 4 hours, and reduce VOPT setpoints to < 55% RTP within 16 hours.

A

D. Reduce thermal power to < 50% RTP within 4 hours, and reduce VOPT setpoints to < 55% RTP within 16 hours.

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

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