AOP Flashcards by Justin Selepec

Unit 1 is at 100% power with all systems in a normal lineup.
LT HDR SYS TRBL alarm has come in.
Letdown flow is 0 gpm.
Letdown backpressure is 600 psig and oscillating.
Which of the following actions should the RO perform?
A. Close Letdown Isolation Valve CHB-UV-515
B. Throttle open the in-service letdown backpressure control valve CHN-PV-201P
C. Throttle open the in-service letdown control valve CHN-LV-110P
D. Bypass the letdown ion exchangers with CHN-HS-520

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Unit 2 is at 100% power with all systems in a normal lineup.
ESF service transformer NBN-X03 faults.
With no further operator action, what will be the condition of the following valves?
1) Letdown isolation valve CHB-UV-515
2) Letdown isolation valve CHA-UV-516
3) Letdown isolation valve CHB-UV-523

A. OPEN, OPEN, CLOSED
B. OPEN, CLOSED, OPEN
C. CLOSED, OPEN, OPEN
D. CLOSED, OPEN, CLOSED

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Unit 2 is at 100% power with all systems in a normal lineup.
Nuclear cooling water pump NCN-P01A trips on overcurrent.
Nuclear cooling water pump NCN-P01B does not automatically start.
With no further operator action, what will be the condition of the following valves?
1) Letdown isolation valve CHB-UV-515
2) Letdown isolation valve CHA-UV-516
3) Letdown isolation valve CHB-UV-523

A. OPEN, OPEN, CLOSED
B. OPEN, CLOSED, OPEN
C. CLOSED, OPEN, OPEN
D. CLOSED, OPEN, CLOSED

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Unit 3 is at 100% power with all systems in a normal lineup.
Nuclear cooling water pump NCN-P01A trips on overcurrent.
Nuclear cooling water pump NCN-P01B has a sheared shaft.
The CO cross-connects EW ‘A’ train to supply NC priority loads.
The RO has performed 40AO-9ZZ05, Loss of Letdown, Appendix C, Extended Operations Without Letdown, and has secured all charging pumps.
What is the expected pressurizer level trend?
A. Pressurizer level will rise by 10% in 55 minutes
B. Pressurizer level will lower by 10% in 55 minutes
C. Pressurizer level will rise by 5% in 55 minutes
D. Pressurizer level will lower by 5% in 55 minutes

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Unit 3 is at 100% power with all systems in a normal lineup.
Nuclear cooling water pump NCN-P01A trips on overcurrent.
Nuclear cooling water pump NCN-P01B has a sheared shaft.
The CO cross-connects EW ‘A’ train to supply NC priority loads.
The RO has performed 40AO-9ZZ05, Loss of Letdown, Appendix C, Extended Operations Without Letdown, and has secured all charging pumps.
Which of the following events would automatically isolate cooling water to the RCPs?
A. Containment pressure of 5 psig
B. EW ‘A’ surge tank high level alarm
C. Pressurizer pressure of 2400 psia
D. Fault on normal service transformer NBN-X01

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Unit 1 is at 100% power.
Charging Pump Selector Switch CHN-HS-4 is in 1-2-3.
CHE-P01, ‘E’ Charging Pump, is isolated for pulsation dampener adjustment.
All other systems are in a normal lineup.
CHA-P01, ‘A’ Charging Pump, trips on a ground fault.
CHB-P01, ‘B’ Charging Pump, continues to run.
CHB-UV-515 automatically closes on high regenerative heat exchanger outlet temperature.
Pressurizer level is 50% and trending down.
Pressurizer pressure is 2240 psia and trending down.
Which of the following actions should be taken first?
A. Perform 40AO-9ZZ12, Degraded Electrical Power, and restore PBA-S03.
B. Perform 40AO-9ZZ05, Loss of Letdown, and restore letdown.
C. Perform 40AO-9ZZ02, Excessive RCS Leakage, and commence a 4-hour plant shutdown.
D. Trip the reactor and enter 40EP-9EO01, Standard Post Trip Actions

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Unit 3 is at 100% power with all systems in a normal lineup.
All four channels of RU-142, Main Steam Line N-16 monitor, go into HIGH ALARM.
The CRS enters 40AO-9ZZ02, Excessive RCS Leakage.
Letdown flow lowers to 77 gpm and stabilizes.
Which of the following actions will be performed to mitigate the consequences of this event?
A. Immediately trip the reactor and enter 40EP-9EO01, Standard Post Trip Actions
B. Immediately start the standby charging pump.
C. Close ASN-V014 and ASN-V015 to isolate the unit from the auxiliary steam cross-tie header.
D. Place Steam Bypass Control System in EMERGENCY OFF.

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Unit 2 is at 60% power with all systems in a normal lineup.
‘A’ and ‘B’ Charging Pumps are running with Charging Pump Mode Selector CHN-HS-4 in 1-2-3.
Pressurizer level is 41% and lowering.
PZR TRBL, Tave-Tref HI-LO, and AUTOMATIC MOTION INHIBIT are in alarm.
Which of the following AOPs should be entered?
A. 40AO-9ZZ02, Excessive RCS Leakage
B. 40AO-9ZZ05, Loss of Letdown
C. 40AO-9ZZ11, CEA Malfunctions
D. 40AO-9ZZ16, RRS Malfunctions

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Unit 1 is at 100% power with all systems in a normal lineup.
A leak develops downstream of CHA-HV-524, Charging Header Isolation Valve.
40AO-9ZZ02, Excessive RCS Leakage, is entered, and Appendix E is performed to align the alternate discharge for all three Charging Pumps.
Which of the following charging system functions will be made available through this lineup?
A. Seal injection
B. RCS dilution
C. Auxiliary Spray
D. RHX cooling for letdown

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Unit 1 is at 100% power with ‘B’ LPSI pump tagged out for planned maintenance.
All other systems are in a normal lineup.
A leak develops downstream of CHA-HV-524, Charging Header Isolation Valve.
40AO-9ZZ02, Excessive RCS Leakage, is entered, and Appendix E is performed to align the alternate discharge for the ‘A’ Charging Pump.
Which injection lineup should be used for charging into the RCS?
A. SIE-V508, cold leg injection, with ‘A’ HPSI piping, using loop 1 injection valves.
B. SIE-V508, cold leg injection, with ‘A’ HPSI piping, using loop 2 injection valves.
C. SIE-V509, hot leg injection with ‘A’ HPSI piping.
D. SIE-V509, hot leg injection with ‘B’ HPSI piping.

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Unit 2 is at 100% power with all systems in a normal lineup.
Regulating group 5 CEAs are at 135” withdrawn. All others are fully withdrawn.
RCN-TT-111X, Loop 1A temperature, fails low.
Which of the following will occur within the next fifteen seconds?
A. CEAs will step inward
B. CEAs will step outward
C. Letdown flow will rise
D. Letdown flow will lower

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Unit 1 is at 100% power with all systems in a normal lineup.
‘B’ CSAS inadvertently actuates due to multiple fuse failures.
Which of the following describes an operational impact of this failure?
A. Cooling water flow will be isolated to the normal chillers
B. Instrument air will be isolated to containment
C. Letdown will isolate
D. RCP control bleedoff will be isolated from the VCT

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Unit 3 is at 100% power with all systems in a normal lineup.
‘A’ CSAS inadvertently actuates due to multiple fuse failures.
With no operator action, which of the following describes an operational impact of this failure?
A. Cooling water flow will be isolated to the normal chillers
B. Instrument air loads in containment will be supplied by backup nitrogen
C. SG blowdown will isolate
D. Letdown flow will rise

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IAN-PV-52, Nitrogen backup to Instrument Air, will automatically open at a low pressure of:
A.	75 psig
B.	85 psig
C.	95 psig
D.	105 psig

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Unit 2 is at 100% power with all systems in a normal lineup.
A pipe break downstream of the instrument air dryers causes a rapid drop in IA pressure
The CRS directs a reactor trip.
Which of the following valves will fail closed as IA system pressure drops?
A. Condensate pump mini-flow valves
B. Main feed pump mini-flow valves
C. Steam Bypass Control Valves
D. Atmospheric Dump Valves

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Unit 1 is at 100% power with all systems in a normal lineup.
The solenoid burns out on IAA-UV-2, IA isolation to containment.
The RO notes CHA-UV-506, Seal Bleedoff containment isolation valve, has gone closed.
With no further operator action, letdown flow will ___(1)___, and seal injection flow will ___(2)___.
A. (1) rise; (2) rise
B. (1) rise; (2) lower
C. (1) lower; (2) rise
D. (1) lower; (2) lower

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Unit 3 is at 100% power with all systems in normal lineup.
The solenoid burns out on IAA-UV-2, IA isolation to containment. IAA-UV-2 fails closed.
Which of the following mitigating strategies should be performed first?
A. Cross tie service air to the containment instrument air header
B. Cross tie the containment low pressure nitrogen header to the containment instrument air header.
C. Trip the reactor, trip the RCPs, and isolate controlled bleedoff using CHA-UV-506, CHB-UV-505, and CHA-HV-507.
D. Perform 40AO-9ZZ05 and restore letdown

Unit 3 is at 4% reactor power, currently performing power ascension.
‘A’ MFP is feeding steam generators in automatic.
A ‘B’ train MSIS actuates due to multiple fuse failures.
In accordance with 40AO-9ZZ17, Inadvertant PPS-ESFAS Actuations, which pumps may be used to feed steam generators?
A. Main feed pumps or Auxiliary Feed Pumps
B. AFN, AFA, or AFB feed pumps ONLY
C. AFA or AFB feed pumps ONLY
D. AFN or AFB feed pumps ONLY

Unit 2 is at 100% power with all systems in a normal lineup.
An inadvertent ‘A’ train actuation of which of the following systems will require entry into LCO 3.0.3?
A. CIAS
B. MSIS
C. CSAS
D. RAS

Unit 1 is at 100% power with all systems in a normal lineup.
All CEAs are at the Upper Electrical Limit.
CPC/CEAC trouble alarm is received.
CEAC shows CEA #8, a shutdown group A CEA, is now at 145 inches withdrawn.
The reactor has not tripped. What action is required?
A. CPCs should have tripped the reactor. Immediately perform a manual reactor trip.
B. Enter 40AO-9ZZ11, CEA Malfunctions, and commence a 20% power reduction.
C. AOP/EOP entry is not required. Enter LCO 3.1.6 condition A and withdraw the CEA to within limits in two hours.
D. AOP/EOP entry is not required. LCO 3.1.6 is currently met.

Unit 1 is at 100% power with all systems in a normal lineup.
A slipped CEA causes the following indications:
Pressurizer level is trending down.
Reactor Power lowers to 99% and stabilizes.
‘A’ CPC has tripped on Hi LPD and Lo DNBR. The other CPCs have not tripped.
Which of the following events would cause these indications?
A. A Regulating Group 5 CEA has slipped to 120” withdrawn.
B. A Regulating Group 4 CEA has slipped to 120” withdrawn.
C. A Regulating Group 1 CEA has slipped to 120” withdrawn.
D. A Shutdown Group B CEA has slipped to 120” withdrawn.

Unit 3 is at 100% power with all systems in a normal lineup.
A RRS failure causes continuous inward CEA motion.
After entering 40AO-9ZZ17, RRS Malfunctions, CEDMCS is placed in STANDBY.
CEA motion stops with Regulating Group 5 at 90”.
Tcold stabilizes at 555 degrees.
Reactor power stabilizes at 96%.
Subsequently, CEA 87, a Regulating Group 4 CEA, slips to 138” withdrawn.
What is the required action?
A. Trip the reactor and perform SPTAs.
B. Enter 40AO-9ZZ11, CEA Malfunctions, and commence a power reduction of at least 20%.
C. Enter 40AO-9ZZ11, CEA Malfunctions, and withdraw CEA 87 to the height of the other CEAs in its group when the problem has been identified. Power reduction not required.
D. Withdraw CEA 87 to the height of the other CEAs in its group when the problem has been identified. AOP entry is not required.

Unit 2 is at 100% power with all systems in a normal lineup.
A RRS failure causes continuous inward CEA motion.
After entering 40AO-9ZZ17, RRS Malfunctions, CEDMCS is placed in STANDBY.
CEA motion stops with Regulating Group 5 at 55”.
Tcold stabilizes at 553 degrees.
Reactor power stabilizes at 94%.
Subsequently, the CO notices CEA 87, a Regulating Group 4 CEA,is at 143” withdrawn.
What is the required action?
A. Trip the reactor and perform SPTAs.
B. Enter 40AO-9ZZ11, CEA Malfunctions, and commence a power reduction of at least 20%.
C. Enter 40AO-9ZZ11, CEA Malfunctions, and adjust CEA 87 to the height of the other CEAs in its group when the problem has been identified. Power reduction not required.
D. Adjust CEA 87 to the height of the other CEAs in its group when the problem has been identified. AOP entry is not required.

Unit 1 was at 100% power with all systems in a normal lineup.
CEA 14, a Regulating Group 5 CEA, slips to 120” at 1200.
The CRS entered 40AO-9ZZ11, CEA Malfunctions.
The plant has been downpowered to 80% power.
Troubleshooting has determined that CEA 14 cannot be moved by CEDMCS.
What action is required?
A. The unit may not remain at power indefinitely. The unit must be in MODE 3 by 1600.
B. The unit may not remain at power indefinitely. The unit must be in MODE 3 by 1800.
C. The unit may not remain at power indefinitely. The unit must be in MODE 3 by 2000.
D. Align the remaining Regulating Group 5 CEAs with CEA 14. In this condition, compliance with all LCOs can be established.

Unit 1 was at 100% power with all systems in a normal lineup. CEA 14, a Regulating Group 5 CEA, slips to 120” at 1200. The CRS entered 40AO-9ZZ11, CEA Malfunctions. The plant has been downpowered to 80% power. The Area 3 operator reports that the individual breaker for CEA 14 is tripped open. What action is required? A. The unit may not remain at power indefinitely. The unit must be in MODE 3 by 1600. B. The unit may not remain at power indefinitely. The unit must be in MODE 3 by 1800. C. The unit may not remain at power indefinitely. The unit must be in MODE 3 by 2000. D. Align the remaining Regulating Group 5 CEAs with CEA 14. In this condition, compliance with all LCOs can be established.

Unit 1 was at 100% power with all systems in a normal lineup. CEA 66, a Regulating Group 2 CEA, slips to 120” at 1200. The CRS entered 40AO-9ZZ11, CEA Malfunctions. The plant has been downpowered to 80% power. Troubleshooting has determined that CEA 66 cannot be moved by CEDMCS. What action is required? A. The unit may not remain at power indefinitely. The unit must be in MODE 3 by 1600. B. The unit may not remain at power indefinitely. The unit must be in MODE 3 by 1800. C. The unit may not remain at power indefinitely. The unit must be in MODE 3 by 2000. D. Align the remaining Regulating Group 2 CEAs with CEA 66. In this condition, compliance with all LCOs can be established.

Unit 1 is at 15% power, performing a power ascension. The main generator has been synchronized to the grid, currently loaded to 200MW. A blown water seal causes condenser backpressure to rise to 5.2” HgA. Which of the following statements is true? A. ‘D’ AR pump is aligned to all condenser shells. The reactor must be tripped in one hour. B. ‘D’ AR pump is aligned to ‘A’ and ‘B’ condenser shells only. The reactor must be tripped in one hour. C. ‘D’ AR pump is aligned to all condenser shells. The reactor must be tripped immediately. D. ‘D’ AR pump is aligned to ‘A’ and ‘B’ condenser shells only. The reactor must be tripped immediately.

Unit 1 is at 100% power with all systems in a normal lineup. The RO notes the following parameters on RCP 1B: 1) Motor current is 500A 2) HP seal cooler inlet temperature is 260 degrees 3) Seal bleedoff flow is 9 gpm ``` Which parameters meet RCP trip criteria? A. 1 only B. 2 only C. 1 and 3 only D. 2 and 3 only ```

Which of the following is NOT a reason for lowering reactor power to 12% following a turbine trip? A. Enables CPCs to use canned values for ASI B. Reduces condenser tube erosion C. Feed SGs with the economizer control valves D. Places the plant below the applicability requirements for LCO 3.2.3, Azimuthal Power Tilt

Unit 3 was at 100% with all systems in a normal lineup. Regulating group 5 CEAs are at 135” withdrawn for ASI control. ECC directed site loading to be reduced by 600 MW to support switching operations. Unit 3 lowered load by 200 MW using 40AO-9ZZ25, ECC Directed Load Reduction. One hour later, switching operations were completed and Unit 3 began to raise turbine load. Which of the following events is expected to occur? A. Automatic outward CEA motion due to raising Tref above Tavg. B. Automatic inward CEA motion due to raising control channel power greater than TLI. C. PC COLSS MARGIN alarm due to NKCBTFSP rising above the COLSS licensed power limit. D. Closure of SBCVs due to loss of the automatic permissive signal.

Unit 3 is at 100% power with all systems in a normal lineup. NAN-S05 locks out on a ground fault. All systems operate as designed. Subsequently, PNA-D25 develops a ground and deenergizes. Which of the following accurately describes a plant condition? A. AFA-P01 has tripped B. ‘A’ Essential Chiller has tripped C. The reactor has tripped D. ‘A’ DG has tripped

Unit 2 is at 100% power with all systems in a normal lineup. A battery short and breaker fault cause a loss of PKA-M41. Auxiliary Feed Pump ‘A’ may be started ___(1)___, and Auxiliary Feed Pump ‘N’ may be started ___(2)___. A. (1) locally and from the control room; (2) locally and from the control room B. (1) locally and from the control room; (2) locally only C. (1) locally only; (2) locally and from the control room D. (1) locally only; (2) locally only

Unit 3 is at 100% power with all systems in a normal lineup. A bus fault causes a loss of PNC-D27. Which of the following statements correctly describes the status of the CEACs? A. CEAC 1 is inoperable in ‘A’ and ‘C’ CPCs B. CEAC 1 is inoperable in all CPCs C. CEAC 2 is inoperable in ‘A’ and ‘C’ CPCs D. CEAC 2 is inoperable in all CPCs

``` A loss of which of the following power supplies would prevent starting all pressurizer heaters from the control room? A. NKN-D41 B. NKN-D42 C. PKA-M41 D. PKB-M42 ```

Unit 1 is at 100% power with all systems in a normal lineup. PKB-M42 de-energizes on a bus fault. What is the status of the following equipment? (1) Fuel Building Essential AHU HFA-J01 (2) Control Room Essential AFU HJA-F04 A. (1) running; (2) running B. (1) running; (2) not running C. (1) not running; (2) running D. (1) not running; (2) not running

Unit 2 is at 100% power with all systems in a normal lineup. PKA-M41 de-energizes on a bus fault. What is the status of the following equipment? (1) Fuel Building Essential AHU HFB-J01 (2) Control Room Essential AFU HJB-F04 A. (1) running; (2) running B. (1) running; (2) not running C. (1) not running; (2) running D. (1) not running; (2) not running

Unit 3 is at 100% power with all systems in a normal lineup. A massive CEDMCS failure causes a reactor trip. All CEAs fully insert. A loss of offsite power occurs one minute following the trip. AFAS-1 and AFAS-2 automatically initiate. Five minutes later, PKB-M42 is lost due to a bus fault. What is the status of the following equipment? (1) ‘B’ Diesel Generator (2) ‘B’ Auxiliary Feed Pump A. (1) running; (2) running B. (1) running; (2) not running C. (1) not running; (2) running D. (1) not running; (2) not running

``` Loss of which of the following power supplies will cause both CVCS Hold Up Tank Pumps to stop? (CHN-P05A and CHN-P05B) A. NNN-D11 B. NNN-D12 C. NNN-D15 D. NNN-D16 ```

Unit 2 is at 100% power. Current time is 2000. ‘B’ DG has been tagged out for scheduled maintenance for 5 days. Power Access Purge system is running in preparation for containment entry during the following shift. All other systems are in a normal lineup. The National Weather Service issues a severe thunderstorm warning for Western Maricopa County. What actions should be taken per 40AO-9ZZ21, Acts of Nature? A. Start AFA-P01 and have the Area 1 operator staged at the 80’ MSSS. B. Start a SBOG and energize NAN-S07. C. Direct all non-essential unit operations to be suspended. D. Initiate CPIAS.

``` On a loss of CEDM ACUs, the reactor trip switchgear breakers must be opened within ___(1)___ of the loss, and the plant must be cooled down to ___(2)___ within four hours of the reactor trip. A. (1) 30 minutes; (2) 300 degrees B. (1) 40 minutes; (2) 300 degrees C. (1) 30 minutes; (2) 350 degrees D. (1) 40 minutes; (2) 350 degrees ```

A sustained loss of which of the following HVAC systems will cause the operating crew to shut down the plant as directed by 40AO-9ZZ20, Loss of HVAC? A. Auxiliary Building Normal Air Handling Units B. Containment Building CEDM Air Cooling Units C. Control Building Normal Air Handling Units D. Turbine Building Battery Room Exhaust Fans

Unit 1 is in Mode 3, performing a heatup in preparation for reactor startup. Th is 510 degrees. Pressurizer pressure is 2000 psia. Performance of the last 72ST-9RX14 showed that shutdown margin is inadequate. The CRS enters 40AO-9ZZ01, Emergency Boration. Which of the following boration lineups could be used to borate the RCS, using this procedure? A. Using a BAMP, borate to the VCT through CHN-UV-512 B. Using a BAMP, borate to the suction of the charging pumps through CHN-UV-527. C. Using ‘A’ HPSI pump, borate to the RCS through loop 1A injection valve SIA-UV-616. D. Using ‘A’ LPSI pump, borate to the RCS through loop 1A injection valve SIA-UV-635