AOP Flashcards by Mike Jones

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

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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

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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

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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

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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

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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

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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

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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

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40AO-9ZZ07, Loss of Condenser Vacuum, has been entered. The cause of the degradation of vacuum has been corrected. Condenser pressure is

Answer: B

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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

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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

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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

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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

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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

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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

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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

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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

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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

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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

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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

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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

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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

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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

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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

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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

Unit 1 is operating at 5% power during a plant startup. The Pressurizer Level master Controller is in REMOTE and AUTO. The Pressurizer Level Control selector switch is in "X". RRS is aligned to monitor average Tave. A Tc instrument (RCN-TT-111Y) fails HIGH. Which one of the following describes the expected plant response? A. The standby charging pump starts. B. This failure will have no impact. C. Letdown flow will begin to decrease. D. The normally running charging pump stops.

Answer: C

The plant is operating at 50% power. RRS Tavg is selected to AVERAGE. Tcold loop 1 fails low. Which of the following describes RRS response to this failure? A. AMI is generated, PLCS auto setpoint increases, Tavg - Tref meter shows a temperature deviation. B. AMI is generated, PLCS auto setpoint decreases, Tavg - Tref meter shows a temperature deviation. C. AWP is generated, PLCS auto setpoint decreases, Tavg - Tref meter shows a temperature deviation. D. AWP is generated, PLCS auto setpoint increases, Tavg - Tref meter shows NO temperature deviation.

Answer: B

Which one of the following indicates why we would direct an Auxiliary Operator to open the hotwell makeup valves from the CST, CDN-HV-154 and 155, when hotwell makeup is insufficient? A. To allow the level in the hotwell and CST to equalize. B. If steaming to the atmosphere, hotwell level may decrease to 30 inches or less, which will cause a condensate pump to trip. C. To minimize cross-contamination of the hotwell and the CST. D. To prevent drawing a vacuum on the CST while making up to the hotwell.

Answer: B

Which one of the following RRS failures would result in an AMI (Automatic Motion Inhibit) and an AWP (Automatic Withdrawal Prohibit)? Assume all switches are in AVERAGE. A. UIC #1 fails low B. Tcold fails low C. TLI fails high D. Tcold fails high

Answer: D

Unit 1 is operating at 100% power. RRS Tave is selected to LOOP #2. TAVG - TREF HI-LO alarms. LOOPS TEMP Hi alarms. All Control Systems in their normal Full Power Line-up. Which of the following would be an immediate consequence of the above indications, if the alarms were caused by an instrument malfunction? A. Letdown increasing dramatically. B. Pressurizer spray full on. C. CEAs driving in. D. SBCS permissive signal in for all valves.

Answer: C

Unit 1 is operating at 80% power and is presently reducing power in response to a condenser tube rupture based on the following SG sample data... SG sodium: .7 ppm and cation conductivity rising SG sulfate: .4 ppm and cation conductivity rising SG chloride: .3 ppm and cation conductivity rising A new series of sample results has come from Chemistry which are... SG sodium: 2.2 ppm and cation conductivity rising SG sulfate: .8 ppm and cation conductivity rising SG chloride: .6 ppm and cation conductivity rising Based on these conditions, the Operating Crew must... A. trip the reactor and enter SPTA's. B. begin a plant shutdown within 2 hours. C. initiate a manual RPCB (LOFP). D. lower plant power to 40% within 2 hours.

Answer: A

Reactor power 50% and stable, CEDMCS in AS, RRS selected to Tave 1. T-hot instrument RCN-TI-111X fails low CEA's are withdrawing Crew selects Tave 2 at RRS Test Panel If no other actions are taken by the crew, the CEA's will: A. insert to match Tavg with Tref. B. continue to withdraw until stopped by an AWP. C. withddraw to match Tavg with Tref. D. stop moving due to the generated AMI.

Answer: A

If a valid CWP (CEA Withdrawal Prohibit) is present, CEAs... A. can be withdrawn in Manual Individual only. B. can be withdrawn only if CWP BYPASS is used. C. cannot physically be withdrawn until the initiating condition is cleared. D. can be withdrawn ONLY if the CWP was initiated from CPCs (vice PPS) and CWP BYPASS is used.

Answer: B

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

Answer: C

Unit 1 is operating at 85% power. A loss of NNN-D12 occurs. Both MFPs remain in operation. Based on these conditions, the operating crew MUST: A. take appropriate action to stop the ongoing boration. B. take appropriate action to stop the ongoing dilution. C. trip a MFP and verify that a RPCB (LOFP) is generated. D. trip a MFP, manually insert CEA's and verify turbine setback.

Answer: A

Unit 1 is BOC, 100% power Unit 2 is MOC, 60% power Unit 3 is EOC, 100% power ECC requests PVNGS reduce electrical output by maximum amount possible due to a grid disturbance resulting in system overloads. Which of the following unit(s) will be requested to reduce output and how much can total output be reduced? A. Unit 1 and Unit 3 by 200 MWe each. B. Unit 1 by 400 MWe. C. Unit 1 by 200 MWe. D. Unit 1 and Unit 2 by 200 MWe each.

Answer: C

Which one of the following describes why we place enough demineralizer beds in service to get the demineralizer bypass valve closed during a condenser tube rupture? A. Provide the maximum amount of condensate for cleanup. B. Evenly distribute the impurities to all demineralizer beds. C. To minimize the amount of contaminants we put into the steam generators. D. Reduce the differential pressure across each individual demineralizer bed.

Answer: C

Unit 1 is at 98% power. SBCS valve testing (with steam flow) is beginning. The Secondary Operator begins to OPEN SBCV 1006 while simultaneously reducing load on the turbine. Total steam flow remains constant. All CEAs are OUT. If CEDMCS is left in AUTO SEQUENTIAL, the Operating Crew should expect CEAs to... A. remain in their present position due to an AWP. B. receive a withdraw signal (with no rod motion). C. remain in their present position due to an AMI. D. start stepping in.

Answer: D

The crew has entered 40AO-9ZZ10, Condenser Tube Rupture. Which of the following is the correct relationship between circulating water trains and condenser hotwell halves? A. "A" Train (Loop AB) circulating water flows thru hotwells 2A, 2B, 2C. B. "A" Train (Loop AB) circulating water flows thru hotwells 1A, 1B, 1C. C. "B" Train (Loop CD ) circulating water flows thru hotwells 1B, 1C, 1D. D. "B" Train (Loop CD ) circulating water flows thru hotwells 2A, 2B, 2C.

Answer: A

With a condenser tube rupture in progress, how is the water level in the water boxes measured after the appropriate train is isolated for draining? A. Install a tygon tubing as a level indicator. B. Use existing level indicators. C. Use the installed delta-P gauges on the outlet of condenser. D. Use a standard 15 ft. calibrated sounding rod.

Answer: A

The plant is at 100% power when suddenly the following alarms and indications are observed in the Control Room: Reactor power decrease. Tavg/Tref Hi-Lo Alarm Window 4A08B on B04 with RCS temperatures decreasing. One four-fingered CEA bottom light on the core mimic and LEL lit. Pressurizer level and pressure decrease. COLSS, CPC, & PDIL alarms. Expected CVCS actions due to decreasing pressurizer level. Which ONE of the following conditions would MOST likely be observed in the next five minutes, if NO operator actions were taken? A. The reactor would have tripped due to low pressurizer pressure. B. Reactor power would stabilize at ~ 100% with a higher than full power Tavg. C. Reactor power would stabilize at 50% with a lower than full power Tavg. D. Reactor power would stabilize at ~ 100% power with a lower than full power Tavg.

Answer: D

With a condenser tube rupture in progress, at approximately what power level will the condensate system be aligned to stop taking a suction on the affected hotwell? A. 0.6 B. 0.12 C. 0.4 D. 0.74

Answer: C

Unit 3 is at 70% power performing a normal downpower per 40AO-9ZZ10 Section 4 due to a confirmed Circ Water leak. All available condensate demineralizers are in service with CDN-PV-195 closed. Chemistry makes the following report: Steam Generator sodium is at 1 ppm and rising. Steam Generator cation conductivity is 19 mmho/cm and rising. Based on this report the Operating Crew should: A. continue with the downpower per Section 4 but increase the rate. B. initiate a manual RPCB (LOFP). C. trip a main feed water pump and verify RPCB. D. trip the reactor and enter standard post trip actions.

Answer: D

0100.....With the plant operating at rated power with ARO, a 4 finger CEA drops to the bottom of the core. 0230.....The operating crew is ready to realign the CEA with its group. Based on these conditions, which one of the following is an appropriate rate of CEA withdrawal to restore the CEA within the shortest time allowed by procedure? A. Unlimited, since it has been over an hour since the CEA has dropped. B. 5 inches per minute. C. 10 inches per minute. D. 15 inches per minute.

Answer: B

Unit 1 is operating at rated power. A loss of PKA-M41 occurs. Which of the following lists the method(s) available to the Operating Crew to control RCS pressure. A. The Main Spray valves ONLY. B. Auxiliary Spray 'A' or 'B'. C. Auxiliary Spray 'B' ONLY. D. Auxiliary Spray 'B' or the Main Spray valves.

Answer: C

Unit 1 is operating at rated power. A Regulating Group 5 CEA drops to the bottom. The Rod Bottom Light on the mimic illuminates, and the crew takes actions per 40AO-9ZZ11, CEA Malfunctions. The COLSS Power Operating Limit (POL) is -99.0. Based on these conditions, COLSS... A. is DEFINITELY inoperable due to the dropped rod, requiring 72ST-9RX03 (COLSS Inoperability) to be performed. B. is performing exactly the way it was designed, and is fully operable. C. is DEFINITELY inoperable and power should immediately be reduced at least 20%. D. MAY be inoperable, and requires a functional determination (77OP-9RJ04) to be performed.

Answer: D

Unit 2 is operating at 70% power. A Regulating Group 4 CEA drops to the bottom of the core. Based on these conditions, the operating crew must reduce power to... A. 55%. B. 50%. C. 60%. D. 65%.

Answer: A

When a CEA drops, the downpower that satisfies the requirements of 40AO-9ZZ11 (CEA Malfunction) is said to commence... A. the crew notices the effect of the boron on temperature. B. as soon as the CEA dropped. C. when the boration has been started. D. when load is taken off the turbine.

Answer: D

The plant is initially at 100% power when the following alarms and indications are observed in the Control Room: Reactor power decrease. Tavg/Tref Hi-Lo alarm. RCS temperatures decreasing. One four-fingered CEA bottom light on the core mimic and LEL lit. Pressurizer level and pressure decrease. COLSS, CPC, & PDIL alarms. Expected CVCS actions due to decreasing pressurizer level. Which ONE of the following conditions would be observed in the next five minutes if NO operator actions were taken? A. Reactor power would stabilize at 95% with a lower than full power Tavg. B. Reactor power would stabilize at about 100% power with a lower than full power Tavg. C. Reactor power would stabilize at 95% with a higher than full power Tavg. D. Reactor power would stabilize at about 100% with a higher than full power Tavg.

Answer: B

Unit 1 is at 100% power, 225 EFPD. The crew has entered 40AO-9ZZ10, Condenser Tube Rupture, due to a confirmed leak in the 1A Hotwell. The CRS has determined that a Manual RPCB is the appropriate action. In accordance with 40AO-9ZZ10, what would be the correct sequence of events that would occur for the affected Circ Water train? A. stop CWN-P01A and CWN-P01B, close CWN-HV-11, close CWN-HV-10, open CWN-HV-6. B. close CWN-HV-11, stop CWN-P01C and CWN-P01D, close CWN-HV-9, open CWN-HV-7. C. stop CWN-P01C and CWN-P01D, close CWN-HV-11, close CWN-HV-9, open CWN-HV-7. D. close CWN-HV-11, stop CWN-P01A and CWN-P01B, close CWN-HV-10, open CWN-HV-6.

Answer: B

``` Which of the following must be completed before exiting the control room if a fire forces evacuation: Reactor trip MSIS initiation AFAS initiation SIAS/CIAS initiation ``` A. 1 and 2 only B. 1 only C. 1, 2, and 3 only D. 1, 2, 3 and 4

Answer: A

Unit 2 is at 85% power with both Circulating Water (CW) trains in service. The Reactor can be stabilized at 40%. Chemistry reports that Steam Generator sodium (Na) and chloride (Cl), although not at their Rx trip limits, will more than likely reach the limit within 40 minutes. Based on this report, 40AO-9ZZ10 (Condenser Tube Rupture) gives the following guidance... A. transition to a rapid shutdown (40OP-9ZZ05). B. consider initiating a manual RPCB (LOFP). C. manually trip a main feed pump and verify proper RPCB actuation. D. trip the reactor and implement SPTAs.

Answer: B

Which one of the following indications would require isolating a Reactor Coolant Pump's Controlled Bleedoff (CBO) valve following shutdown of the pump? A. Seal #2 Inlet pressure indicates 1900 psig and stable. B. Seal #2 Outlet temperature indicates 250 degrees and trending up. C. Controlled Bleedoff flow is indicating 8.0 gpm and trending down. D. RCP Motor Lower Journal bearing indicates 200 degrees and stable.

Answer: B

Nuclear Cooling water has been lost due to a pipe rupture Train 'A' EW has been cross-connected to NC Which one of the following identifies a plant condition that will isolate Essential Cooling Water to the RCP's? A. Containment pressure rises to 4.0 psig. B. Pressurizer pressure drops to 1900 psia. C. Instrument Air header pressure drops to 60 psig. D. Loss of power to the EW to NC cross connect valves.

Answer: A

What is shutdown margin? A. The amount of positive reactivity by which the reactor can or will be shutdown B. The amount of positive reactivity associated with boron and temperature C. The amount of negative reactivity associated with Xenon and temperature D. The amount of negative reactivity by which the reactor can or will be shutdown

Answer: D

WHICH ONE of the following states when boration due to a stuck CEA may be discontinued ? A. When the required boron concentration is reached. B. When RWT level drops to 73%. C. Anytime pressurizer level will exceed the program band. D. A plant cooldown has been directed by an emergency operating procedure.

Answer: A

Unit 1 is in Mode 1 'A' NCW Pump is under Permit 'B' NCW pump trips and is locked out The Operating Crew directed to restore Nuclear Cooling Water flow within ..... A. 3 minutes or commence a controlled shutdown. B. 10 minutes or trip the reactor, stop all RCPs, and ensure controlled bleedoff isolated. C. 3 minutes or trip the reactor, stop all RCPs, and ensure controlled bleedoff isolated. D. 10 minutes or commence a controlled shutdown.

Answer: B

Unit 1 is operating at rated power. A loss of NNN-D15 occurs. Based on these conditions, the operating crew MUST: A. transfer speed control of the "A" MFP to manual. B. trip the "A" MFP and verify a RPCB (LOFP) actuates. C. trip the "A" MFP, manually insert CEAs and runback turbine load to 65%. D. verify a RPCB (LOFP) actuates when the "A" MFP speed drops below 3000 rpm.

Answer: B

100% power. Loss of Nuclear Cooling Water. EW train "A" cross-connected to Nuclear Cooling Water. Which one of the following describes how the Essential Cooling Water system would respond to a Safety Injection Actuation Signal under these conditions? EW train 'B' pump would start and the EW Train "A"... A. to NC cross-connect valves would remain open and Train 'A' EW pump would stop due to load shedding and then restart according to the sequencer. B. would stop due to load shedding then restart according to the sequencer. C. to NC cross-connect valves would remain open and the Train 'A' EW pump would remain running. D. to NC cross-connect valves would close and the Train 'A' EW pump would remain running.

Answer: D

A reactor trip has occurred from 100% power. Plant conditions require IMMEDIATE boration. RCS pressure is 2230 psia. RWT level is 65%. Which one (1) of the following methods is available for immediate boration given the above conditions? Gravity feed through... A. CH-V327 to charging pumps. B. CH-HV-536 to charging pumps. C. CH-V164 via CH-UV-514 to charging pumps. D. HPSI pumps and high pressure injection valves.

Answer: A

Essential Cooling Water (EW) will supply which of the following Nuclear Cooling Water (NC) loads when cross-tied to NC? A. Normal Chillers. B. Letdown heat exchanger. C. Containment Normal AHUs. D. Waste Gas Compressors.

Answer: A

Of the following AO actions, which would cause a decrease in RCS temperature? A. Manually starting the AFA-P01 pump to feed the S/G B. Manually isolating a main steam lead drain valve C. Shifting Aux Steam to be taken from the cross-tie header D. Manually taking control of an ADV and closing the valve

Answer: A

Nuclear cooling water has been lost due to a pipe rupture in the yard. Essential Cooling Water Train "A" has been cross-connected to supply priority loads. No other equipment is out of service or in an abnormal lineup. WHICH ONE of the following identifies the plant conditions that will isolate essential cooling water to the reactor coolant pumps? A. High level in the "A" EW surge tank B. RCS pressure of 1800 psia C. High EW "A" pump discharge pressure D. Containment pressure of 2.0 psig

Answer: B

Following a Control Room evacuation due to a fire, operators prepare to perform a Natural Circulation cooldown from remote locations. Which one of the following statements is correct with regards to why certain instrumentation at the RSP should be considered reliable for plant control during a Control Room fire? A. Only the "B" train instruments that deal with Pressurizer Level and pressure, RCS temperature, and Steam Generator level and pressure should be used because these instruments have LOCAL/REMOTE disconnects in their power supplies. B. Only the "A" train instruments that deal with Pressurizer Level and pressure, RCS temperature, and Steam Generator level and pressure should be used because these instruments have LOCAL/REMOTE disconnects in their power supplies. C. Only the "A" train instruments that deal with Pressurizer Level and pressure, RCS temperature, and Steam Generator level and pressure should be used because these instruments have isolators in their circuits. D. Only the "B" train instruments that deal with Pressurizer level and pressure, RCS temperature, and Steam Generator level and pressure should be used because these instruments have isolators in their circuits.

Answer: D

When using the Spent Fuel Pool (SFP) as a source for emergency boration, why must CHN-HV-532 be closed? A. A gravity flow path would be established between the SFP and RWT. B. The SFP boron concentration is higher than the RWT. C. PC Clean-up must be isolated if the valve is left open. D. Three charging pumps cannot run on the SFP with the valve open.

Answer: A

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

Answer: A

Unit 1 is operating at rated power. A failure of CHB-UV-515, letdown to regen heat exchanger, caused a loss of letdown. PZR level is 55%. The operating crew has stopped all charging pumps to establish conditions to support extended operations with letdown isolated. A loss of nuclear cooling water occurs. To avoid tripping the reactor and securing all RCPs, the operating crew must restore: A. both seal injection and NC within 10 minutes. B. seal injection within 10 minutes. C. both seal injection and NC within 3 minutes. D. NC within 3 minutes.

Answer: D

Plant conditions are such that shutdown margin is less than required. Regarding the use of gravity feed from the Safety Injection System through CH-V327 to the charging pumps, which one of the following statements is correct? A. When the RWT level reaches 40%, a charging pump low suction trip will occur. B. In order to use this method, manual valve operations must be performed outside the control room. C. The RWT level must be above 73% if this flow path is used to ensure charging pump suction. D. In order to satisfy Technical Specification requirements, the boration flow rate must be 50 gpm.

Answer: B

Unit 1 is operating in Mode 1. Due to a loss of the NC pumps, EW 'A" has been crosstied to NC. Based on these conditions, EW 'A' is... A. considered OPERABLE since it was analyzed to support the plant during accident conditions while supplying the priority loads of NC. B. considered OPERABLE as long as it is NOT supplying Fuel Pool Cooling at the same time it is aligned to NC. C. INOPERABLE. D. considered OPERABLE since the crosstie valves have an automatic feature that will close them when EW is required to support its safety function.

Answer: C

Nuclear cooling water has been lost due to a pipe rupture in the yard. Essential Cooling Water Train "B" has been cross-connected to supply priority loads. No other equipment is out of service or in an abnormal lineup. WHICH ONE of the following identifies the plant conditions that will isolate essential cooling water to the reactor coolant pumps? A. Containment pressure 9.0 psig. B. Pressurizer pressure 1800 psia. C. Instrument air header pressure 60 psig. D. Low level in the B train essential cooling water tank.

Answer: A

Upon evacuating the control room due to a fire, operators proceed to the remote shutdown panel (RSP). Which one of the following parameters is reliably measured at this panel? A. SG #1 pressure. B. RCS Tavg. C. RCS Loop 1 Thot. D. Source Range Nuclear Instrumentation.

Answer: A

An emergency boration is required and the path through CHN-UV-514 has been chosen. If the BAMPs are not available, which additional valve must be opened to ensure adequate NPSH exists for the charging pumps? A. CHN-V164 B. CHN-V144 C. CHN-UV-536 D. CHN-UV-514

Answer: A

The unit is operating at rated power. EW 'A' has been crosstied to NC due to a loss of BOTH NC pumps. ESS CLG WTR SYS TRBL ALARM (2A09A) is in alarm for Ess Cooling Water Surge Tank A level Hi-Lo. Containment Sump alarms have come in. EWA-UV-65 and EWA-UV-145 (EW to NC Crossties) have just auto-closed. No ESFAS actuations have occurred. Based on these conditions, 40AO-9ZZ03 (Loss of Cooling Water) directs the Operating Crew to: close the NC CNMT isolation valves, trip the reactor, stop all RCPs and ... A. isolate seal bleedoff. B. restart essential chillers. C. verify the isolation of EW to NC isolates the leak. D. check containment RU monitors for activity.

Answer: A

Unit 1 is operating at 80% power and is presently reducing power in response to a condenser tube rupture based on the following SG sample data... SG sodium: .7 ppm and cation conductivity rising SG sulfate: .4 ppm and cation conductivity rising SG chloride: .3 ppm and cation conductivity rising A new series of sample results has come from Chemistry which are... SG sodium: 1.2 ppm and cation conductivity rising SG sulfate: .6 ppm and cation conductivity rising SG chloride: .4 ppm and cation conductivity rising Based on these conditions, the Operating Crew needs to... A. continue with the ongoing shutdown. B. initiate a RPCB. C. trip the reactor and enter SPTAs. D. shift to a rapid shutdown per 40OP-9ZZ05.

Answer: C

The Reactor was tripped due to a degrading condenser vacuum. Immediately after the trip, the Secondary Operator became involved with the B01 report. When this operator returned to B06, condenser backpressure was 9.0" HgA (highest shell). Steam Generator levels are both 65% WR. Assuming no other operator performed actions on B06, in what condition can this operator expect to find the secondary plant? A. Main Feed Pumps feeding in RTO with SBCS valves 1001 & 1004 maintaining SG pressure. B. No feed with SBCS valves 1001 & 1004 maintaining SG pressure. C. No feed with SBCS valves 1007 & 1008 maintaining SG pressure. D. Main Feed Pumps feeding in RTO with SBCS valves 1007 & 1008 maintaining SG pressure.

Answer: D

The Reactor was tripped due to a degrading condenser vacuum. Immediately after the trip, the Secondary Operator got involved with the B01 report. When this operator returned to B06, condenser backpressure was 14.0" HgA (highest shell). Steam Generator levels are both 65% WR. Assuming no other operator performed actions on B06, in what condition can this operator expect to find the secondary plant? A. No feed with SBCS maintaining SG pressure. B. No feed with MSSVs maintaining SG pressure. C. Main Feed Pumps feeding in RTO with SBCS maintaining SG pressure. D. Main Feed Pumps feeding in RTO with MSSVs maintaining SG pressure.

Answer: A

Main generator output is 700 MW(e) Condenser vacuum indicates: 4.5 in Hg in A shell and degrading 4.8 in Hg in B shell and degrading 5.0 in Hg in C shell and degrading Steam bypass control system is in "REMOTE/AUTO" and a SBCS permissive has been received. The Crew is coordinating manual insertion of CEAs while unloading the Main Turbine. 20 gpm Boration in progress. Tave is 4 degrees greater than Tref. Tave continues to diverge and exceeds Tref by greater than 5 degrees. In accordance with 40AO-9ZZ07, the required Crew response would be to... A. place CEDMCS in AS to stabilize Tave. B. control secondary pressure with SBCS valves 1007 and 1008. C. stop the turbine load reduction until Tave matches Tref ±4°F. D. allow automatic SBCS actuation to stabilize Condenser vacuum.

Answer: B

A down-power is in progress in accordance with 40AO-9ZZ07 due to an air inleakage problem on the Main Condenser. The Main Generator is presently operating at 400 Mwe. Backpressure is noted to increase to 5.2" HgA on the 'C' shell. Based on these conditions, the operating crew: A. must reduce backpressure to less than 4" HgA within one hour. B. can continue operating indefinitely. C. must immediately trip the Reactor and perform SPTA's. D. must immediately trip the Main Turbine and take actions iaw 40AO-9ZZ08

Answer: C

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

Answer: A

Which of the following statements correctly identifies when a HPSI pump is to be used for Emergency Boration per 40AO-9ZZ01, "Emergency Boration"? A. Anytime RCS pressure is less than HPSI shutoff head. B. Anytime a SIAS/CIAS occurs. C. Only if Charging pumps are unavailable. D. Only if Reactor Coolant System Tcold is less than 350 degrees F.

Answer: C

Plant conditions require IMMEDIATE boration. RCS pressure is 2230 psia. RWT level is 65%. WHICH ONE (1) of the following methods is available for immediate boration given the above conditions? Align Charging pump... A. suction to the RWT through CHN-UV-514, ensuring the Boric Acid Makeup filter is bypassed. B. suction to the RWT through CHE-UV-536. C. suction to the RWT through CHN-UV-514, ensuring a BAMP pump is operating. D. alternate suction through CHB-V327.

Answer: D

An inadvertent containment spray actuation, CSAS, occurs. The operator places both Containment Spray Pump hand switches in the stop position and overrides and closes both containment spray valves. The reactor trips and a valid Safety Injection Actuation Signal SIAS is received. Which one of the following is correct concerning starting the CS pumps? A. Reset and then re-initiate CSAS. B. Place the CS pump handswitch to START twice. C. The CS pump control power must be cycled. D. Place the CS pump handswitch to START once.

Answer: B

Nuclear Cooling water has been lost due to a pipe rupture Train 'B' EW has been cross-connected to NC Which one of the following identifies a plant condition that will isolate essential cooling water to the RCPs? A. Instrument air header pressure drops to 60 psig. B. Pressurizer pressure drops to 1800 psia. C. B' EW Surge Tank level drops to LO LEVEL setpoint. D. Containment pressure rises to 9.0 psig.

Answer: D

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. first reduce the LOAD LIMIT potentiometer until the LOAD LIMITING light comes on, then pick up load as necessary. B. reduce turbine load below 15% to clear the SETBACK, then raise load as desired using the LOAD LIMIT potentiometer. C. simply raise the setting of the LOAD LIMIT potentiometer, since the setting of this control follows the SETBACK and RUNBACK down. 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: A

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

Answer: C

Unit 1 is operating at rated power. An inadvertent Train A CSAS occurs. Based on these conditions, what actions, if any, are necessary to maintain the RCPs operating? A. No actions should be necessary, since the CSAS is only Train A. B. Cross-tie Essential Cooling Water with Nuclear Cooling Water. C. Override and open NCA-UV-402, outside containment isolation valve on the NC return header. D. Locally open NCA-UV-402, outside containment isolation valve on the NC return header.

Answer: C

The unit has experienced a Loss of Instrument Air. What correctly describes the status of the Condensate system? A. CDN-LV-81, Hotwell Makeup, has failed open. B. CDN-PV-195, Demin Bypass Valve, has failed closed. C. CDN-FV-28, CD Pump 'C' miniflow, has failed closed. D. CDN-FV-27, CD Pump 'B' miniflow, has failed open.

Answer: D

The unit has experienced a complete loss of Instrument Air. What of the following correctly identifies the status of the Low Pressure Feed Water Heater Normal level control valves? A. heaters # 1 & 2 open, heaters # 3 & 4 closed. B. heaters # 1,2,3 & 4 open. C. heaters # 1,2,3 & 4 closed. D. heater # 1 open, heaters # 2,3 & 4 closed.

Answer: D

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

The Unit has just experienced a Large Load reject due to an EHC system failure. The CRS has entered 40AO-9ZZ08. Reactor power currently 43%. CEA motion has stopped due to AMI. The Secondary Operator reports that both SGs levels are oscillating from 5 to 20% NR and continuing to diverge. Based on procedural guidance what actions should the CRS first direct? A. Lower SG level controller setpoint to 5% NR, to avoid Hi SG level trip setpoint. B. Place the controlling SBCV in manual and stabilize RCS temperature. C. Fast close Economizer Isolation valves to stop leakage past the Flow Control valves. D. Select single element control on a single SG and adjust level controller output to maintain level.

Answer: B

The Unit has just experienced a Large Load reject (Turbine trip) due to an EHC system failure. The CRS has entered 40AO-9ZZ08. Rx power currently 43% CEA motion has stopped due to AMI. Which of the following conditions would require a Rx trip based on guidance found in 40AO-9ZZ08: A. SGN-PT-1024 failed low, SG pressure 1190 psi controlling with ADVs. B. CPC Point ID 187 (minus).43 and trending to the bottom of the Core. C. SG #1 level 70% NR and stable D. Manual actuation of RPCS Large Load Reject has failed.

Answer: D

The Unit has just experienced a Large Load reject due to an EHC system failure. The CRS has entered 40AO-9ZZ08. Rx power currently 43%. CEA motion has stopped due to AMI. Which of the following conditions (if met) would require a Reactor Trip based on guidance found in 40AO-9ZZ08: A. PLCEA subgroup deviation of 4 inches. B. SG #1 WR level 65% and slowly dropping. C. CPC Point ID 187 is negative .45 and trending to the top of the core. D. SGN-PT-1024 failed low, SG pressure 1190 psi controlling with ADVs.

Answer: C

The plant is at 100% power CEA #15 (4 fingered group 5 rod) drops fully into the bottom of the core. The crew does not dilute to maintain Tavg to Tref. In accordance with 72ST-9RX16, Shutdown Margin Modes 1 and 2, Appendix A, Shutdown Margin is: A. not met because any dropped CEA always reduces shutdown margin. B. met because no dilution was performed. C. not met because CEA is below the PDIL. D. met because the affected CEA #15 is not a shutdown bank CEA.

Answer: B

Answer: A

Answer: D

Answer: A

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

Answer: B

Answer: A