AOP Flashcards
Given the following plant conditions:
Unit 3 is operating at 100% rated power.
A loss of NKN-M46 occurs.
Which one of the following procedures should be used to address this event?
A. 40EP-9EO01, SPTAs
B. 40AO-9ZZ13, Loss of Class Instrument or Control Power
C. 40AO-9ZZ12, Degraded Electrical
D. 40AO-9ZZ14, Loss of Non-Class Instrument or Control Power
Answer: D
Given the following plant conditions: Unit is operating at 100% power. Regulating Group 5 is at 135" RRS selected to Control Channel #1. Control Channel #1 fails high. CEDMCS in Auto Sequential Which one of the following is correct? CEAs......
A. may withdraw a few steps.
B. may insert a few steps.
C. will not move due to an AMI.
D. will insert until CEDMCS is taken out of automatic.
Answer: B
Which one of the following describes the operation of AFN-P01 following a loss of PKA-D21 in which PKA-D21 can NOT be re-energized?
Control power must be shifted to the ‘A’ battery…
A. output to restore remote operation of both the breaker and suction valves.
B. output to restore remote operation of the breaker.
C. charger output to restore remote operation of the AFN-P01 breaker.
D. charger output to restore remote operation of both the breaker and suction valves.
Answer: C
Given the following Plant conditions:
The CRS has entered 40AO-9ZZ08 due to an unexpected load reduction.
Megawatts had been 1300 MW but is no longer stable.
Secondary Operator reports that Main Generator frequency is oscillating between 59.8 and 60.2 hertz.
All systems are in their normal configuration.
Which of the following actions should the CRS first direct:
A. Perform appendix I, placing Main Turbine in Standby
B. Shift Gennerex to DC control.
C. Verify RPCS in service then trip the Reactor.
D. Reduce the load limit potentiometer until the “LOAD Limiting” light is on.
Answer: D
Given the following conditions:
Unit 1 is operating at rated power when backpressure in the Main Condenser starts to rise.
Regulating Group 5 is at 135 inches.
Turbine load is being shifted to SBCS valve 1007 in an effort to stabilize backpressure causing first stage pressure to decrease with reactor power remaining constant.
If CEDMCS is left in AUTO SEQUENTIAL, the Operating Crew should expect CEAs to…
A. start stepping in.
B. start stepping out.
C. remain in their present position due to an AMI.
D. remain in their present position as long as load is being removed.
Answer: A
Which one of the following describes how RRS develops CEA motion demand?
A. Power error compensated by rate of change of temperature error signal.
B. Power error signal ONLY.
C. Temperature error ONLY.
D. Temperature error compensated by rate of change of power error signal.
Answer: D
Given the following conditions:
Group 5 CEAs are 140 inches withdrawn with CEDMCS in Auto sequential.
A Control Channel detector fails high. RRS is selected to the failed detector.
Which of the following describes the RRS response?
A. No CEA motion will occur due to an AMI being generated.
B. CEAs may insert a few steps due to the Rate of Change circuit sensing a power error.
C. No CEA motion will occur due to the Rate of Change circuit eliminating the effects of the instrument failure.
D. CEAs may attempt to withdraw a few steps due to the Rate of Change circuit sensing a power error.
Answer: B
Given the following conditions:
The plant is operating at 100% power.
A single NI control channel has failed to 0%.
With no operator actions, which of the following is true concerning the DFWCS?
A. There will be no effect on the plant.
B. S/G levels will rapidly increase.
C. The unit will go through feedwater swapover.
D. Both downcomers control valves will go closed.
Answer: A
40AO-9ZZ07, Loss of Condenser Vacuum, has been entered. The cause of the degradation of vacuum has been corrected. Condenser pressure is
Answer: B
Given the following plant conditions:
Unit 1 is operating at 100% power.
A Regulating Group 4 CEA drops to the bottom of the core. Based on these conditions, the operating crew must:
A. begin efforts to restore the CEA in 10 minutes.
B. have the CEA restored within 15 minutes.
C. be less than 80% power within 30 minutes.
D. begin a power reduction within 10 minutes.
Answer: D
Given the following plant conditions:
Loss of PKD-M44 How many ADV’s are available from the control room?
A. 2
B. 0
C. 1
D. 4
Answer: A
Given the following plant conditions:
Unit 1 is operating at rated power with all rods 150 inches withdrawn.
A Regulating Group 3 CEA slips to 135 inches withdrawn. Shortly after this, a Regulating Group 5 CEA drops to the bottom of the core.
Based on these conditions, the operating crew must:
A. monitor CPC DNBR and LPD margins to trip and trip the reactor if either one approaches its trip setpoint.
B. monitor CPC ASI and trip the reactor if it approaches +0.5.
C. reduce turbine load to maintain Tavg and Tref within 3°F of each other.
D. immediately trip the reactor.
Answer: D
Given the following conditions:
Unit 1 is operating at rated power.
A CREFAS is manually initiated with both trains of Control Room Essential AFUs running.
Window 7B01A “INST AIR SYSTEM TROUBLE” alarms. Instrument Air header pressure is noticed to be lowering.
If the air problem continues to degrade, the Control Room Essential AFUs….
A. will trip.
B. ventilation lineup will not change.
C. will lose cooling water.
D. outside air dampers will fail open.
Answer: B
Given the following conditions:
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.
The Operating Crew desires to pick up load on the Main Turbine.
RPCB has been taken to Test Reset and Auto Actuate Out of Service.
In order to accomplish this, the Secondary Operator must…
A. simply raise the setting of the LOAD LIMIT potentiometer, since the setting of this control follows the SETBACK and RUNBACK down.
B. reduce turbine load below 15% to clear the SETBACK, then raise load as desired using the LOAD LIMIT potentiometer.
C. first reduce the LOAD LIMIT potentiometer until the LOAD LIMITING light comes on, then pick up load as necessary.
D. 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.
Answer: C
A condenser tube rupture exists in Train “A” of the main condenser. The control room has directed an auxiliary operator to close the inlet isolation valve for Drawoff to the CST . This action by the auxiliary operator will…
A. isolate the make-up function from the condensate storage tank to the condenser hotwells.
B. slow the rate at which condenser hotwell levels are increasing.
C. prevent contamination of the condensate storage tank by isolating hotwell draw off.
D. prevent condensate pump LO-LO level trips after the circ water overboard valves are opened.
Answer: C
Given the following plant conditions:
The plant is operating at 100% power.
A large load reject occurs due to degraded vacuum in the condenser.
Hotwell level is 35 inches and holding steady.
Which one of the following actions will need to be performed?
A. Open at least one Main Feed Pump Mini-flow Valve.
B. Trip the Reactor.
C. Trip the Main Turbine.
D. Open the Hotwell Manual Makeup Isolation Valve(s).
Answer: D
Given the following plant conditions:
The plant is operating at 100% power.
Condenser pressure is increasing.
Hotwell level is 35 inches and decreasing slowly.
Which one of the following actions might the AO need to perform, if directed by the Control Room, and why?
A. Monitor the nitrogen storage tank level to ensure CST cover gas remains available.
B. Ensure the hotwell drawoff valve is open to maximize available water in the CST.
C. Open the manual makeup valves to the hotwell to prevent a condensate pump trip at 30 inches hotwell level.
D. Increase the amount of cooling tower makeup to ensure proper NPSH to the Circulating Water Pumps.
Answer: C
An Emergency Boration using a HPSI pump is in progress. What is the flowrate required for the HPSI pump if the emergency boration must continue for 2 hours?
A. 185 gpm
B. 75 gpm
C. 85 gpm
D. 225 gpm
Answer: D
Unit 1 is operating at rated power with ARO.
A Regulating Group 3 CEA (non twelve finger) slips to 138 inches withdrawn. A Regulating Group 5 CEA slips to 145 inches withdrawn. The operating crew is required by procedure to …
A. reduce turbine load to maintain Tave and Tref within 5 degrees of each other and reduce reactor power within 10 minutes.
B. trip the reactor and implement the SPTAs.
C. reduce turbine load to maintain Tave and Tref within 3 degrees of each other and reduce reactor power within 20 minutes.
D. reduce turbine load to maintain Tave and Tref within 3 degrees of each other and reduce reactor power within 10 minutes.
Answer: D
According to 40AO-9ZZ04, when Seal Injection is isolated to the RCPs while at power, you can expect…
A. HP Seal Cooler inlet and outlet temperatures will rise to between 200°F and 220°F while all other temperatures remain the same.
B. NO change in the RCP temperature indications.
C. HP Seal Cooler inlet temperature will rise to between 200°F and 220°F, all other temperatures should increase by about 70°F.
D. HP Seal Cooler inlet temperature will rise to between 200°F and 220°F while all other temperatures remain the same.
Answer: D
The reactor has tripped, Two CEA’s have stuck out and cannot be tripped, RCS pressure is 1600 psia and stable. Which of the following could be used to emergency borate the RCS?
1. HPSI 2. LPSI 3. CS 4. Charging
A. only 4
B. 1 and 4
C. only 1
D. 1 and 2
Answer: B
Unit 1 is at 80% power and dropped a 4 finger CEA.
Unit 2 is at 80% power and dropped a 12 finger CEA.
Assume that the CEAs remained misaligned. What would be the impact on the respective CEACs?
A. Both units will eventually trip due to a penalty factors ramping in over the next 6 hours.
B. Neither unit will trip based on these misaligned CEAs.
C. In Unit 1 the 4 finger CEA will effectively generate NO CEAC penalty factor, whereas in Unit 2, the 12 finger CEA will eventually trip the reactor due to a penalty factor ramping in.
D. In Unit 2, the 12 finger CEA will effectively generate NO CEAC penalty factor, whereas In Unit 1, the 4 finger CEA will eventually trip the reactor due to a penalty factor ramping in.
Answer: C
Unit 1 is operating at rated power at 200 EFPD. A condenser tube rupture occurs. The four available condensate demineralizers have been placed in service. CDN-PDV-195 is still open. SG Sodium, based on the inline monitor, indicates 800 ppb and rising rapidly. Based on these conditions, the operations crew should:
A. conduct a controlled downpower.
B. initiate a manual RPCB (LOFP).
C. trip the reactor and enter standard post trip actions.
D. take manual control of the controller in order to close CDN-PDV-195.
Answer: C
Unit 1 is operating at rated power. EW Train A is in the process of being aligned to NC due to a problem with both NCW pumps. Each RCP has about 375 gpm of cooling water flow indicated on B04. An Operator is standing by in the Train A SDC Heat Exchanger room to throttle the EW outlet of the SDC Heat Exchanger using EWA-HCV-53. Based on the above conditions, you should direct the Operator to throttle EWA-HCV-53:
A. open to increase the EW pump’s flowrate.
B. closed to divert more flow to the NCW system.
C. closed to reduce the heat load on the EW Heat Exchangers.
D. open to overcome the increased head loss that the NCW places on the EW system.
Answer: B
Unit 2 is operating at rated power. A full load test of the ‘B’ D/G is in progress. The ‘B’ D/G output breaker has just been closed with the D/G carrying approximately 450 KW of load. A loss of PKB-M42 occurs due to a bus fault. Which one of the following describes the impact (if any) this has on the D/G?
A. The D/G begins to assume load uncontrollably, requiring the operator’s to manually trip its output breaker.
B. The D/G trips, its output breaker remains closed and PBA-S03 de-energizes.
C. The D/G continues to run at 450 KW, however output breaker control has been lost.
D. The D/G trips but its output breaker remains closed, causing the diesel to motorize.
Answer: D
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 smaller rise in pressurizer pressure.
B. more CEAs dropped on the RPCB.
C. fewer CEAs dropped on the RPCB.
D. a larger rise in pressurizer pressure.
Answer: D
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. first depress the DROP SUBGROUPS pushbutton, release, and then depress the LOSS OF FEED PUMP pushbutton.
B. simultaneously depress the DROP SUBGROUPS and LOSS OF FEED PUMP pushbuttons.
C. depress and hold the DROP SUBGROUPS pushbutton, and then depress SUBGROUP SELECT pushbuttons 4, 5 and 22.
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.
Answer: B
Unit 1 is operating at rated power. The following parameters are indicated for the 1B RCP:
Seal #1 inlet pressure…………2250 psia
Seal #2 inlet pressure…………2225 psia
Seal #2 outlet pressure……….440 psia
Controlled bleedoff flow………5.9 gpm
Seal #1 inlet temperature…….110°F
Seal #2 inlet temperature…….105°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-P01B and isolate controlled bleedoff.
B. Commence plant shutdown by 40OP-9ZZ05, Power Operations.
C. Trip reactor, stop all reactor coolant pumps and isolate controlled bleedoff.
D. Initiate a RPCB to rapidly reduce power, then continue the shutdown using 40OP-9ZZ05, Power Operations.
Answer: B
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. 0.02
B. 0.12
C. 0.35
D. 0.4
Answer: B
Unit 1 is operating at rated power. Seal Injection is isolated to the RCPs due to a leak in the Aux building. Which of the following describes the effect (if any) that this has on the RCP temperatures?
A. HP Seal Cooler inlet temperature will rise to between 200°F and 220°F, all other seal temperatures should increase by about 70°F.
B. Isolating Seal Injection should have NO impact on the seal temperatures.
C. HP Seal Cooler inlet temperature will rise to between 200°F and 220°F while all other seal temperatures remain normal.
D. HP Seal Cooler inlet temperature should remain relatively constant, while all other seal temperatures should increase by about 70°F.
Answer: C
The reactor is at 100% power ‘A’ PW Pump is tagged out of service and disassembled. The ‘B’ PW Pump trips and locks out on instantaneous overcurrent due to a locked rotor. The crew should…
A. place the ‘B’ PW pump in ‘PULL TO LOCK’ and perform 40AO-9ZZ12, Degraded Electrical.
B. immediately cross tie EW to NC and SFP cooling.
C. immediately reset the 86 lock out and attempt to restart the ‘B’ PW pump.
D. immediately trip the reactor and perform SPTAs.
Answer: D
With RRS Tavg selected to AVERAGE, which of the following will generate a Reactor Regulating System Automatic Motion Inhibit (AMI):
A. Th > 575°F.
B. Tavg deviation > 5°F.
C. Tc > 575°F.
D. Tavg - Tref > 6°F.
Answer: B
Unit 1 is operating at rated power. A loss of PNA-D25 occurs. Which of the following is correct concerning PPS Channel A?
A. Only those parameters with setpoints below the normal value, LOW, have tripped, requiring the crew to bypass only those parameters.
B. Only those parameters with setpoints below the normal value, LOW, have tripped and the crew bypasses all parameters in that channel.
C. All parameters in that channel have tripped due to the loss of power and must be bypassed.
D. All parameters in that channel have tripped due to the loss of power. However, since the bypass system is also without power, bypassing these parameters serves no purpose.
Answer: C
Which of the following instrument(s) can be considered reliable at the Remote Shutdown Panel during a Control room Fire ?
A. Loop 1B TT-121C1
B. Steam Generator 1 Pressure PT-1013B
C. Pressurizer Level 110X-1
D. Steam Generator 1 Level LT-1113A
Answer: B
A condenser tube rupture occurs. There are three condensate demineralizers available for service. CDN-PV-195 is open. SG Sodium, based on the inline monitors, indicates .3 ppm and rising. Based on these conditions, the operating crew should:
A. initiate a manual RPCB (LOFP).
B. trip the reactor and enter standard post trip actions.
C. commence a normal downpower to
Answer: B
During a Control Room Fire event, which one of the following indicates the components that will be used to facilitate heat removal from the Reactor Coolant System?
A. ADVs and Aux Feed Pump “B”.
B. SBCS and Aux Feed Pump “N”.
C. ADVs and Aux Feed Pump “A”.
D. SBCS and Aux Feed Pump “A”.
Answer: A
Given the following plant conditions:
Loss of PNA-D25 How many ADV’s are available from the control room?
A. 0
B. 2
C. 1
D. 4
Answer: B
40AO-9ZZ07, Loss of Condenser Vacuum has been entered. Reactor power has been lowered to 65%. RPCB has removed from service. Hotwell level is 45 inches and holding steady. Which one of the following actions will need to be performed?
A. Place BOTH Heater Drain Tank Level Control Valves in Manual.
B. Ensure BOTH Heater Drain Tank Level Control Valves are in Remote Auto.
C. Place BOTH Heater Drain Tank Level Control Valves in Local Auto.
D. Open the Hotwell Makeup Bypass Valves.
Answer: C
The Unit is at 100% power with the CEDMCS in AUTO SEQUENTIAL when the following alarms and indications are observed in the Control Room: Board Annunciators:
AWP (4A09A) Alarming.
REAC PWR CUTBACK SYS TRBL (4A11A) Alarming.
TURB BYP DEMAND (4A12B) Alarming.
MN TURB TRIP (6B02A) Alarming.
All available steam bypass valves are full open.
Pressurizer pressure is 2255 psia and slowly increasing.
Tcold is 555°F and slowly increasing.
Group 5 rods are at 138 inches and driving in.
Subgroups 4, 5, 22 are selected for RPCB.
Which one of the following operator actions should be taken?
A. Place Steam Bypass Control System into emergency off and control secondary pressure with ADVs.
B. Manually initiate a “feed pump” trip Reactor Power Cutback.
C. Initiate maximum boration using all available charging pumps.
D. Manually initiate a “large load reject” Reactor Power Cutback.
Answer: D
With the plant operating at 100% power steady state conditions, which of the following describes plant response to a T-hot input failing high when RRS is selected to that channel? (Assume all controls are in automatic and NO operator action) RRS will send….
A. an AWP signal to CEDMCS due to Tref > Tave.
B. an AMI signal to CEDMCS.
C. a signal to CEDMCS causing CEA’s to insert.
D. a signal to CEDMCS causing CEA’s to withdraw.
Answer: C
The unit is operating at rated power. A twelve finger CEA slips. Based on these conditions, the Operating Crew is required to…
A. trip the reactor if the CEA can not be restored within 1 hour.
B. immediately trip the reactor.
C. monitor the CPC DNBR and LPD margins to trip for the unaffected quadrants.
D. trip the reactor if the CEA can not be restored within 3 hour.
Answer: C
The unit is at rated power. All equipment is aligned normally/ in automatic. No evolutions are in progress.
Then: Condenser back pressure degrades rapidly from:
(A) 2.2, to (A) 8.0, (B) 2.3, (B) 8.0, (C) 2.5, (C) 8.3inches HGA. With no operator action, what would the unit status be at this point in the event?
A. Main Turbine Tripped, MFWPs Running, SBCS Condenser Interlock in.
B. Main Turbine Tripped, MFWPs Tripped, SBCS Normal/Auto.
C. Main Turbine On Line, MFWPs Running, SBCS Normal/Auto.
D. Main Turbine On Line, MFWPs Tripped, SBCS Condenser Interlock in.
Answer: A
A down-power is in progress in accordance with 40OP-9ZZ07 due to an air in leakage problem on the Main Condenser. The Main Generator is presently operating at 380 Mwe and 120 MVARs boost. Backpressure is noted to degrade to 4.2” HgA on the ‘C’ shell. Based on these conditions, the operating crew:
A. must reduce backpressure to less than 4” HgA in one hour.
B. must immediately trip the turbine.
C. can continue operation indefinitely.
D. must reduce excitation to establish a unity power factor.
Answer: A
The Unit 2 power uprate and SG replacement are complete. The plant is at 100% power. Condenser vacuum begins to degrade The crew enters the Loss of Vacuum, 40AO9ZZ07, AOP. What plant response would be most affected in Unit 2 when compared to the other units?
A. Charging flow would be more responsive to Pressurizer level changes.
B. SBCVs 1007 & 1008 would be more responsive to thumbwheel changes.
C. Letdown would be more responsive to Pressurizer level changes.
D. Turbine power would be more responsive to load limit pot changes.
Answer: D
The Unit 2 power uprate and SG replacement are complete. The plant is operating at 100% power Which AOP would be most impacted by operating in full arc admission when compared to the unit(s) operating in partial arc admission?
A. Control Room Fire, 40AO-9ZZ19
B. Loss of Letdown, 40AO-9ZZ05
C. Loss of Vacuum, 40AO-9ZZ07
D. Inadvertent PPS-ESFAS actuations, 40AO-9ZZ17
Answer: C
The Unit 2 power uprate and SG replacement are complete. The plant is at 100% power. A loss of vacuum occurs. The crew enters the 40AO-9ZZ07, Loss of Vacuum AOP. The secondary operator is told to reduce turbine load using the load limit pot. When compared to Unit 1 and 3, what plant response should the secondary operator expect from the load limit potentiometer?
A. More responsive.
B. Less responsive.
C. The same response.
D. Same response in the throttling range but more responsive outside the throttling range.
Answer: A
Which one of the following will a Non-Licensed Operator be expected to check after 40AO-9ZZ07, Loss of Condenser Vacuum, has been entered?
A. SBCV 1007 & 1008 operation
B. Main Feed Pump operation
C. Seal Oil Vacuum Tank level
D. Air Removal Pump operation
Answer: D
40AO-9ZZ07, Loss of Condenser Vacuum, has been entered. Which of the following is a list of components that the AO should check and replenish the water seal on during a Loss of Condenser Vacuum?
A. Condenser Expansion Joints, Vacuum Breakers, Gland Exhaust Packing Exhauster Drain.
B. Condenser Expansion Joints, Gland Exhaust Packing Exhauster Drain, Main Turbine Gland Seals.
C. Condenser Expansion Joints, Circulating Water Pump Seals, Gland Exhaust Packing Exhauster Drain.
D. Extraction Drain Valve Packing, Condenser Expansion Joints, Vacuum Breakers.
Answer: A
Reactor power is at 50%, the following plant conditions exist: Tc (RCN-TI-111Y) indicates 564°F.
Tc (RCN-TI-121Y) indicates 650°F.
Th (RCN-TI-111X and 121X) indicate 592°F.
RRS is selected to Tavg 2.
Board Annunciators in alarm:
Tavg/Tref Hi-Lo
RC Loop Temp
Hi CEA high rate insertion demand indicator is lit. CEA auto insertion occurring. Turbine load matches Reactor power. If there is no operator actions taken, which of the following describes this event?
A. SBCS will receive a runback inhibit.
B. Pressurizer pressure will increase.
C. Pressurizer pressure will lower.
D. SBCS will receive a quick open block.
Answer: C
100% power. RRS in Auto and selected to AVERAGE Tave Loop 2 Tc fails HI
Which one of the following is correct?
A. Turbine runback initiated to bring Tavg - Tref within +2°F.
B. AMI generated by LOOP 1 Tc indicated > 575°F.
C. CEA high withdrawal occurring to mismatch between temperature error and power error.
D. AMI generated by Tavg deviation.
Answer: D