EOP Flashcards by Justin Selepec

Unit 1 was at 100% power with all systems in a normal lineup.
A catastrophic CEDMCS failure results in multiple dropped CEAs.
The reactor automatically tripped.
Fast-bus transfer for NAN-S01 to NAN-S03 failed.
The input breaker for the inverter for PND-D28 spuriously trips open.
‘E’ charging pump, powered from PGA-L35, automatically started, but was grounded. Its breaker failed to open, resulting in a lockout of PBA-S03
One Charging Pump is running.
Pressurizer level is 23% and rising.
Pressurizer pressure is 2200 psia and rising.
SG levels are 50% WR and rising, feeding with AFB.
SG pressures are 1160 psia and stable, controlled by ADVs.
All other SPTA contengiencies have been performed.
Which of the following is the correct ORP to enter following the SPTAs?
A. Enter 40EP-9EO02, Reactor Trip
B. Enter 40EP-9EO03, Loss of Coolant Accident
C. Enter 40EP-9EO07, LOOP/LOFC
D. There is no appropriate ORP. Enter 40EP-9EO09, Functional Recovery

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Unit 1 was at 100% power with all systems in a normal lineup.
A catastrophic CEDMCS failure results in multiple dropped CEAs.
The reactor automatically tripped.
Fast-bus transfer for NAN-S01 to NAN-S03 failed.
The ‘B’ NC pump trips on overcurrent.
Two charging pumps are running.
Pressurizer level is 23% and rising.
Pressurizer pressure is 2200 psia and rising.
SG levels are 50% WR and rising, feeding with AFB.
SG pressures are 1160 psia and stable, controlled by ADVs.
All other SPTA contengiencies have been performed.
Which of the following is the correct ORP to enter following the SPTAs?
A. Enter 40EP-9EO02, Reactor Trip
B. Enter 40EP-9EO03, Loss of Coolant Accident
C. Enter 40EP-9EO07, LOOP/LOFC
D. There is no appropriate ORP. Enter 40EP-9EO09, Functional Recovery

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Unit 2 was at 100% power with all systems in a normal lineup.
A catastrophic CEDMCS failure results in multiple dropped CEAs.
The reactor automatically tripped.
Fast-bus transfer for NAN-S01 to NAN-S03 failed.
The input breaker for the inverter for PNB-D26 spuriously trips open.
‘E’ charging pump, powered from PGA-L35, automatically started, but was grounded. Its breaker failed to open, resulting in a lockout of PBA-S03
One Charging Pump is running
Pressurizer level is 23% and rising.
Pressurizer pressure is 2200 psia and rising.
SG levels are 50% WR and rising, feeding with AFB.
SG pressures are 1160 psia and stable, controlled by ADVs.
All other SPTA contengiencies have been performed.
Which of the following is the correct ORP to enter following the SPTAs?
A. Enter 40EP-9EO02, Reactor Trip
B. Enter 40EP-9EO03, Loss of Coolant Accident
C. Enter 40EP-9EO07, LOOP/LOFC
D. There is no appropriate ORP. Enter 40EP-9EO09, Functional Recovery

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Unit 1 was at 100% power with all systems in a normal lineup.
The reactor automatically tripped.
SIAS and CIAS actuate on low pressurizer pressure.
Fast-bus transfer for NAN-S01 to NAN-S03 failed.
The input breaker for the inverter for PND-D28 spuriously trips open.
‘E’ charging pump, powered from PGA-L35, automatically started, but was grounded. Its breaker failed to open, resulting in a lockout of PBA-S03
One charging pump is running
Pressurizer level is 23% and stable.
Pressurizer pressure is 2200 psia and lowering.
SG levels are 50% WR and rising, feeding with AFB.
SG pressures are 1160 psia and stable, controlled by ADVs.
Containment pressure is 1 psig and stable.
Containment temperature is 125 degrees and stable.
All other SPTA contengiencies have been performed.
Which of the following is the correct ORP to enter following the SPTAs?
A. Enter 40EP-9EO02, Reactor Trip
B. Enter 40EP-9EO03, Loss of Coolant Accident
C. Enter 40EP-9EO07, LOOP/LOFC
D. There is no appropriate ORP. Enter 40EP-9EO09, Functional Recovery

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“An occurrence which results in the loss of capability of a component to perform its intended safety functions” describes which of the following?
A.	Single failure
B.	Limiting failure
C.	Limiting event
D.	Limiting fault

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\_\_\_\_\_\_\_ are not expected to occur, but are postulated nonetheless because their consequences include the potential for the release of significant amounts of radioactive material.
A.	Single failures
B.	Limiting failures
C.	Limiting events
D.	Limiting faults

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\_\_\_\_\_ require LCOs, procedures, plant design, etc. to minimize the consequences to the health and safety of nuclear workers and the public.
A.	Single failures
B.	Limiting failures
C.	Limiting events
D.	Limiting faults

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Unit 3 was at 100% power with all systems in a normal lineup.
NBN-X01 tripped on a fault. NBN-S01 failed to auto-transfer to NBN-S02.
‘B’ Main Feed Pump tripped on low suction pressure.
The CRS directed a reactor trip due to lowering SG levels.
All equipment actuated as designed, and the Reactor Trip ORP 40EP-9EO02 was entered following the SPTAs.
Subsequently, the ‘C’ condensate pump trips on overload, resulting in a low suction pressure trip of ‘A’ Main Feed Pump.
Which of the following is the appropriate action?
A. Concurrently perform 40AO-9ZZ12, Degraded Electrical Power, restore NBN-S01, and then restore a Main Feed Pump.
B. Remain in 40EP-9EO02, Reactor Trip, and establish feed with AFB-P01
C. Enter 40EP-9EO06, Loss of All Feed, and establish feed with AFB-P01
D. There is no appropriate ORP. Enter 40EP-9EO09, Functional Recovery and establish feed with AFB-P01

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Unit 1 was at 100% power when an event caused a reactor trip.
SIAS, CIAS, MSIS, and CSAS have actuated.
‘A’ EDG tripped on low lube oil pressure.
30 seconds after the trip, offsite power was lost.
‘B’ LPSI pump tripped on ground fault.
Pressurizer pressure is 1300 psia and stable.
Containment pressure is 15 psia and lowering.
Steam generator levels are 50% WR and rising.
Steam generator pressures are 1100 psia and lowering.
CET subcooling is 2 degrees and stable.
Following SPTAs, which is the appropriate ORP to enter?
A. 40EP-9EO03, Loss of Coolant Accident
B. 40EP-9EO04, Steam Generator Tube Rupture
C. 40EP-9EO05, Excessive Steam Demand
D. There is no appropriate ORP. Enter 40EP-9EO09, Functional Recovery

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Unit 1 was at 100% power when an event caused a reactor trip.
SIAS, CIAS, MSIS, and CSAS have actuated.
‘A’ EDG tripped on low lube oil pressure.
30 seconds after the trip, offsite power was lost.
Pressurizer pressure is 1100 psia and stable.
Containment pressure is 15 psia and lowering.
Steam generator levels are 50% WR and rising.
Steam generator pressures are 1100 psia and lowering.
CET subcooling is 2 degrees and stable.
Following SPTAs, which is the appropriate ORP to enter?
A. 40EP-9EO03, Loss of Coolant Accident
B. 40EP-9EO04, Steam Generator Tube Rupture
C. 40EP-9EO05, Excessive Steam Demand
D. There is no appropriate ORP. Enter 40EP-9EO09, Functional Recovery

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Unit 3 is in Mode 3 following a SGTR in Steam Generator #1.
Steam Generator #1 has been isolated.
Which of the following accurately describes how pressure will be controlled in the #1 SG?
A. Limit pressure to 1200 psia. If pressure nears this point, use only MSIV bypass valves and SBCVs to lower pressure.
B. Limit pressure to 1135 psia. If pressure nears this point, use only MSIV bypass valves and SBCVs to lower pressure.
C. Limit pressure to 1200 psia. If pressure nears this point, ADVs may be used to lower pressure.
D. Limit pressure to 1135 psia. If pressure nears this point, ADVs may be used to lower pressure.

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Unit 1 is in Mode 3 following a SGTR in Steam Generator #1.
Steam Generator #1 has been isolated.
Which of the following accurately describes how level will be controlled in the #1 SG?
A. Maintain level 45-60% NR. The preferred method of level control is backflow to the RCS.
B. Maintain level 45-80% NR. The preferred method of level control is backflow to the RCS.
C. Maintain level 45-60% NR. The preferred method of level control is blowdown to the main condenser.
D. Maintain level 45-80% NR. The preferred method of level control is blowdown to the main condenser.

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Unit 2 is at 100% power with all systems in a normal lineup.
A sheared shaft on the 1B RCP caused an automatic reactor trip.
Fast-bus transfer of NAN-S01 to NAN-S03 failed to actuate.
The operating crew performs the SPTAs and notes the following parameters:
Pressurizer pressure is 2100 psia and lowering slowly.
Pressurizer level is 15% and lowering slowly.
All charging pumps are running.
Both main feed pumps have tripped. AFAS did not actuate.
AFN is feeding both SGs at 400 gpm.
#1 SG level is at 40% NR and rising.
#2 SG level is at 56% WR and stable.
SG pressures are 1170 psia and stable.
RU-1 Containment area monitor, has elevated radiation levels.
Following SPTAs, which of the following is the appropriate ORP to enter?
A. 40EP-9EO03, LOCA
B. 40EP-9EO04, SGTR
C. 40EP-9EO07, LOOP/LOFC
D. There is no appropriate ORP. Enter 40EP-9EO09, FRP

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Unit 1 is at 100% power with all systems in a normal lineup.
The main turbine trips on high vibration.
Fast-bus transfer of NAN-S01 to NAN-S03 failed to actuate, causing a reactor trip.
The operating crew performs the SPTAs and notes the following parameters:
Pressurizer pressure is 2100 psia and lowering slowly.
Pressurizer level is 15% and lowering slowly.
All charging pumps are running.
Both main feed pumps have tripped. AFAS did not actuate.
AFN is feeding both SGs at 400 gpm.
#1 SG level is at 40% NR and rising.
#2 SG level is at 56% WR and stable.
SG pressures are 1170 psia and stable.
Following SPTAs, which of the following is the appropriate ORP to enter?
A. 40EP-9EO03, LOCA
B. 40EP-9EO04, SGTR
C. 40EP-9EO07, LOOP/LOFC
D. There is no appropriate ORP. Enter 40EP-9EO09, FRP

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Unit 3 is in Mode 3, at normal operating RCS temperature and pressure.
PBA-S03 is de-energized due to a bus fault.
‘E’ Charging Pump is tagged out for plunger replacement.
Letdown is isolated. ‘B’ Charging Pump is running.
Pressurizer level is 35% and slowly rising.
SG pressures are 1170 psia, maintained by SBCS in auto.
AFB is feeding both SGs at 100 gpm.
SG levels are 40% NR and stable.
All RCPs are running.
An event occurs that causes the following changes:
Pressurizer pressure is 2200 psia and lowering.
Pressurizer level is 30% and lowering.
SG #1 level is 42% NR and rising.
Which of the following is the appropriate procedure to enter?
A. 40AO-9ZZ02, Excessive RCS Leakrate
B. 40EP-9EO01, Standard Post Trip Actions
C. 40EP-9EO03, LOCA
D. 40EP-9EO04, SGTR

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A minimum level of 45% NR is maintained in a ruptured SG in order to:
A. provide iodine scrubbing to minimize radioactivity release.
B. prevent further RCS in-leakage.
C. maintain the SG available for RCS heat removal.
D. prevent further tube leaks by maintaining the U-tubes covered.

Unit 1 was at 100% power when an unisolable steam break occurred upstream of MSIV-170.
The reactor tripped automatically.
SIAS/CIAS/MSIS actuated automatically.
Which of the following actions should be taken to prevent pressurized thermal shock?
A. Stop HPSI pumps as soon as pressurizer level is in the indicating range.
B. Stop charging pumps as soon as pressurizer level is in the indicating range.
C. Stabilize Tc in the loop with an intact SG after the initial cooldown terminates.
D. Lower plant temperature to SDC entry conditions as soon as the faulted SG is isolated.

Unit 2 is at 100% power with all systems in a normal lineup.
An event occurs that causes an automatic reactor trip.
On the trip, a loss of PBA-S03, a loss of offsite power, and a stuck out CEA prevent operators from taking other actions to stabilize the plant.
Three minutes later, conditions are as follows:
• PBA-S03 is supplied by DG ‘A’
• ‘B’ charging pump is running, borating the RCS through CHE-UV-536
• Pressurizer Pressure is 1200 psia and stable
• Pressurizer Level is 100%
• Tc is 560 degrees and lowering
• SIAS/CIAS/MSIS/CSAS/AFAS-1 have actuated
• SG #1 level is 10% WR and lowering rapidly
• SG #2 level is 50% WR and stable
• SG #1 pressure is 1150 psia and lowering
• SG #2 pressure is 1190 psia and lowering
Which of the following actions is appropriate given these conditions?
A. Stop RCPs
B. Override AFAS and stop feed to #1 SG
C. Throttle HPSI to maintain pressurizer level 10-65%
D. Stop the ‘B’ charging pump

Which of the following single failures has the most negative effect on an increased heat removal accident?
A. Failure of a MSIV to close
B. Failure of HPSI pumps to start
C. Failure of AF pumps to start
D. Failure of ADVs to open on the intact SG

Which of the following reactivity anomalies is classified as a limiting fault?
A.	Uncontrolled CEA withdrawal at power
B.	Single dropped full-strength CEA
C.	Inadvertent boron dilution in Mode 5
D.	CEA ejection

Concerning the transient accident analyses for decreases in heat removal, which of the following is the limiting event?
A.	Feedwater Line Break
B.	Main Turbine Trip
C.	MSIV closure at power
D.	Loss of Condenser Vacuum

Unit 3 is at 100% power with all systems in a normal lineup.
A loss of condenser vacuum causes an automatic reactor trip.
PKA-M41 develops a ground and de-energizes.
Sudden pressure relay trips on ESF transformer NBN-X03.
AFB-P01 starts, but has no flow due to a sheared shaft.
Which of the following success paths are available for restoration of feed following the SPTAs?
A. Enter 40EP-9EO06, LOAF, and start AFN-P01 powered from PBB-S04.
B. Enter 40EP-9EO06, LOAF, lower pressure in one SG and feed with condensate pumps.
C. Enter 40EP-9EO06, LOAF, and manually feed with AFA-P01.
D. Enter 40EP-9EO06, LOAF, transfer control power for AFN-P01 to the ‘A’ battery charger and start the pump from the control room.

Unit 3 was at 100% power when a condensate pump trip caused a loss of both main feed pumps and a reactor trip.
AFB-P01 and AFN-P01 tripped when started from B06.
AFA-P01 started on AFAS-1 but tripped on overspeed one minute later.
Following completion of the SPTAs, the CRS transitioned to 40OP-9EO06, LOAF.
Which of the following actions should be performed?
A. Stop RCPs to minimize plant heatup
B. Initiate MSIS to conserve SG inventory
C. Open SG sample valves to confirm the event diagnosis
D. Shut Main Turbine Before Seat Drain valves to minimize plant cooldown

Unit 3 was at 100% power when a condensate pump trip caused a loss of both main feed pumps and a reactor trip.
AFB-P01 and AFN-P01 tripped when started from B06.
AFA-P01 started on AFAS-1 but tripped on overspeed one minute later.
Following completion of the SPTAs, the CRS transitioned to 40OP-9EO06, LOAF.
10 minutes later, AFA-P01 overspeed has been reset and AFA-P01 is running.
SG #1 and #2 pressures are 1170 psia and stable.
SG #1 level is 8% WR and lowering.
SG #2 level is 15% WR and lowering.
How should the SGs be fed?
A. Feed SG #1 only at less than 1000 gpm
B. Feed SG #2 only at less than 1000 gpm
C. Feed either SG, but only one, at less than 1000 gpm
D. Feed both SGs

Unit 2 was at 100% power when a condensate pump trip caused a loss of both main feed pumps and a reactor trip. AFB-P01 and AFN-P01 tripped when started from B06. AFA-P01 started on AFAS-1 but tripped on overspeed one minute later. Following completion of the SPTAs, the CRS transitioned to 40OP-9EO06, LOAF. 10 minutes later, AFA-P01 overspeed has been reset and AFA-P01 is running. SG #1 and #2 pressures are 1170 psia and stable. SG #1 level is 0% WR. SG #2 level is 5% WR and lowering. How should the SGs be fed? A. Feed both SGs B. Feed SG #1 only until level is equalized with SG #2, then feed both SGs C. Feed SG #1 only, but limit flow to 1000 gpm D. Feed SG #2 only

Unit 1 is at 100% power with all systems in a normal lineup. A loss of which of the following busses concurrent with a reactor trip would require the operating crew to borate the RCS? A. PBA-S03 B. PKC-M43 C. PNB-D26 D. NNN-D11

Unit 3 is at 100% power with all systems in a normal lineup. NAN-X01 is out of service for planned maintenance. Fast bus transfer is blocked for NAN-S02 in Unit 3 in accordance with 40OP-9NA03. An electrical fault develops on Normal Service Transformer NBN-X01 and it locks out. Fifteen seconds later, a CEDM MG set fault results in a reactor trip. The operating crew performs the SPTAs and performs appropriate contingency actions. All other equipment works as designed. Following the SPTAs, the CRS should transition to: A. 40EP-9EO02, Reactor Trip. SGs are being fed by Main Feed. B. 40EP-9EO07, LOOP/LOFC. SGs are being fed by Auxiliary Feed. C. 40EP-9EO02, Reactor Trip. SGs are being fed by Auxiliary Feed. D. 40EP-9EO06, Loss of All Feed. The crew must manually start an Auxiliary Feed Pump.

Unit 2 is at 100% power with all systems in a normal lineup. A complete loss of offsite power results in a reactor trip. The operating crew performs the SPTAs and performs appropriate contingency actions. The SGs are being fed with AFB-P01 and pressure is being controlled with ADVs. The CRS transitions to 40OP-9EO07, LOOP/LOFC. ECC reports electrical power will be available to the PV switchyard in one hour. Which of the following actions should be performed by the operating crew? A. Energize NAN-S01 from an SBOG B. Restore letdown to maintain pressurizer level 10-65% C. Initiate MSIS D. Purge the main generator with carbon dioxide

Unit 1 was at 100% power, but suffered a loss of offsite power fifteen minutes ago. The operating crew is performing 40EP-9EO07, LOOP/LOFC. The RO is directed to check for natural circulation flow and notes the following parameters: • Th is 585 degrees and rising • Tc is 564 degrees and stable • Maximum CET temperature is 600 degrees • Pressurizer pressure is 2200 psia and rising What is the status of natural circulation? A. Natural circulation has been established. B. Natural circulation cannot be verified because the RCS is not subcooled. Continue to raise pressure. C. Natural circulation cannot be verified due to excessive temperature difference between loop temperatures and CETs. Head venting is required. D. Natural circulation is developing, but cannot be verified until loop temperatures have stabilized. Continue feeding and steaming the SGs.

Unit 1 was at 100% power. ‘A’ DG Mode Control Switch DGA-HS-7 at DGA-B01 has been placed to OFF to support scheduled maintenance. All other switches and associate equipment is in a normal lineup. A clearance has been prepared but no tags have been hung. A loss of offsite power results in a reactor trip. The operating crew performs the SPTAs and performs appropriate contingency actions. The SGs are being fed with AFB-P01 and pressure is being controlled with ADVs. The CRS transitions to 40OP-9EO07, LOOP/LOFC. ECC reports electrical power will be available to the PV switchyard in one hour. The Area 1 operator reports low oil bubbler levels for AFB-P01. The CRS desires to re-energize PBA-S03 from the ‘A’ DG. He should do this by: A. Remaining in 40EP-9EO07, LOOP/LOFC, and performing appendix 55 B. Performing 40OP-9DG01, Diesel Generator A Normal Operations C. Transitioning to 40EP-9EO08, Blackout, and performing appendix 55 D. Transitioning to 40EP-9EO09, Functional Recovery Procedure. No other procedure would be sufficient to restore the DG

Concerning the decrease in flow accident analysis: The limiting event for the decreasing RCS flow safety analysis is ___(1)___. The reactor trip in this case would be provided by the ___(2)___. A. (1) Single RCP rotor seizure; (2) CPC DNBR trip B. (1) Single RCP rotor seizure; (2) Lo SG Differential Pressure trip C. (1) Single RCP shaft break; (2) CPC DNBR trip D. (1) Single RCP shaft break; (2) Lo SG Differential Pressure trip

Unit 3 is at 100% power with all systems in a normal lineup. Chemistry reports hotwell 1C sodium concentration is 5 ppm and trending up. The CRS enters 40AO-9ZZ10, Condenser Tube Rupture. While making initial preparations for a rapid downpower, Chemistry reports SG #1 sodium is 1.5 ppm and trending up. What action should be taken? A. Immediately place all available condensate polishers in service. B. Immediately initiate a LOFP Reactor Power Cutback and downpower to allow isolating the affected CW train. C. Trip the reactor, exit 40AO-9ZZ10, and perform the SPTAs. D. Trip the reactor, continue performance of 40AO-9ZZ10, and perform the SPTAs.

Unit 3 is at 100% power. ‘A’ DG is tagged out for scheduled maintenance. All other systems are in a normal lineup. Inclement weather causes a complete loss of offsite power. While performing the SPTAs, a ground develops on PKB-M42 and it de-energizes. All equipment operates as designed and appropriate SPTA contingencies are taken. Following the SPTAs, the CRS should transition to… A. 40EP-9EO02, Reactor Trip B. 40EP-9EO07, LOOP/LOFC C. 40EP-9EO08, Blackout D. 40EP-9EO09, Functional Recovery, as SFSCs cannot be met for any ORP.

Unit 3 is at 100% power. ‘B’ DG is tagged out for scheduled maintenance. All other systems are in a normal lineup. Inclement weather causes a complete loss of offsite power. While performing the SPTAs, a ground develops on PKA-M41 and it de-energizes. All equipment operates as designed and appropriate SPTA contingencies are taken. Following the SPTAs, the CRS should transition to… A. 40EP-9EO02, Reactor Trip B. 40EP-9EO07, LOOP/LOFC C. 40EP-9EO08, Blackout D. 40EP-9EO09, Functional Recovery, as SFSCs cannot be met for any ORP.

Unit 1 was at 100% power. Fast bus transfer was blocked for NAN-S01 and NAN-S02 due to degraded grid voltage. A stator cooling water system rupture causes a turbine trip. 5 seconds later, the sudden pressure relay on NBN-X03 trips and it locks out. A switchyard relay problem isolates NAN-X02 from the grid. ‘A’ Essential Spray Pond pump output breaker fails to close, so the operating crew emergency stops ‘A’ DG. A spurious differential relay trip on the ‘B’ DG de-energizes PBB-S04. All other systems operate as designed, and all appropriate contingencies are taken. The CRS enters 40EP-9EO08, Blackout. Which of the following actions could be used to re-energize a vital bus while remaining in the Blackout procedure? A. Energize PBB-S04 from a SBOG B. Energize PBB-S04 from NAN-X03 C. Energize PBB-S04 from ‘B’ DG D. Energize PBB-S04 from Unit 3’s NAN-S05

``` 40EP-9EO08, Blackout, may be exited when a 4.16 kV AC bus is energized from ANY of the following EXCEPT: A. a station blackout generator B. a startup transformer C. an affected unit diesel generator D. an unaffected unit diesel generator ```

Unit 1 was at 100% power when a lightning bolt struck the switchyard, causing a loss of offsite power. On the reactor trip, ‘A’ DG tripped due to a massive lube oil leak, and PBB-S04 de-energized due to a ground fault. The operating crew established feed with AFA-P01, steam generator pressure control with ADVs, and re-energized PBA-S03 from #1 SBOG. ECC reports the switchyard will not be re-energized for five hours due to continued storm activity near PVNGS. The operating crew should now… A. transition to 40EP-9EO07, LOOP/LOFC, and align Unit 3’s ‘B’ DG to supply PBA-S03 B. remain in 40EP-9EO08, Blackout, and align Unit 3’s ‘B’ DG to supply PBA-S03 C. energize switchyard loads using #1 SBOG D. borate the RCS with ‘A’ charging pump to maintain shutdown margin