2009 RO Flashcards Preview

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Flashcards in 2009 RO Deck (75):
1

Given the following:

The Plant has automatically tripped from 100% power

EOP-1.0, "Standard Post Trip Actions," are in progress

P-8A, AFW Pump, is out of service for maintenance
Which one of the following describes the response of P-8C, AFW Pump, for this event?
P-8C will start ...
a. immediately after both S/G levels lower to 30%.
b. immediately after either S/G level lower to 30%.
c. approximately 30 seconds after both S/G levels lower to 30%.
d. approximately 30 seconds after either S/G level lowers to 30%.

d. approximately 30 seconds after either S/G level lowers to 30%.

a. Plausible because the student believes that both S/Gs must be 30% and the 30 second time delay has elapsed.
b. Plausible because the student believes that the 30 second time delay has elapsed.
c. Plausible because the student believes that both S/Gs must be 30%.
d. CORRECT

2

Consider two Pressurizer Vapor Space accidents caused by a leaking Pressurizer Safety Valve with the following parameters:

Accident 1 Accident 2
Pressurizer press 2000 psia 1000 psia
Quench Tank press 20 psig 5 psig

Which one of the following describes the relationship between downstream tailpipe temperature for the two accidents and the reason?
Downstream tailpipe temperature for ...
a. Accident 1 will be higher because the fluid has more enthalpy.
b. Accident 1 will be higher because Quench Tank pressure is higher.
c. Accident 2 will be higher because Quench Tank pressure is lower.
d. Accident 2 will be higher because the fluid has more enthalpy.

d. Accident 2 will be higher because the fluid has more enthalpy.

a. Plausible because PZR temperature and pressure are higher, however, enthalpy is higher for accident 2.
b. Plausible because the student may believe that the fluid temperature will always correspond to saturation temperature for Quench Tank pressure.
c. Plausible because the student may think that since pressure is lower the fluid will become superheated and thus, a higher temperature.
d. CORRECT - Accident 1 tailpipe temperature will be ~260°F and accident 2 tailpipe temperature ~300°F. Fluid enthalpy for accident 1 is higher and the throttling process is a constant enthalpy process.

3

Operators are directed to monitor Containment Area Radiation Monitors, RIA-1805, RIA-1806, RIA-1807, and RIA-1808 during a Loss of Coolant Accident (LOCA) per EOP-4.0, "LOCA Recovery" to determine:
a. when Containment Spray is no longer needed for iodine removal.
b. when to initiate simultaneous hot and cold leg injection.
c. if a Containment Isolation signal should have initiated.
d. if an Emergency Classification threshold is exceeded.

c. if a Containment Isolation signal should have initiated.

a. Plausible but the high range gamma monitors are used for this function.
b. Plausible but this is performed 5.5 hours after LOCA.
c. CORRECT
d. Plausible, but EI-1.1 uses high range monitors to determine status of fission product barriers.

4

Given the following:

A Loss of Coolant Accident has occurred from 100% power

Containment Radiation Levels indicate 12R/Hour

Maximum Containment Pressure during the LOCA reached 3.4 psig
Which one of the following valves will automatically close based on the above conditions?
a. CV-0910, CCW Supply to Containment.
b. CV-2083, PCP Controlled Bleedoff Isolation.
c. CV-2111, Charging Line Containment Isolation.
d. CV-0510, S/G E-50A Main Steam Isolation Valve.

b. CV-2083, PCP Controlled Bleedoff Isolation.

a. Plausible because this valve closes on CHP only which has not occurred (setpoint 4 psig).
b. CORRECT
c. Plausible because Letdown Isolation closes on CHR but Charging does not.
d. Plausible because this valve closes on CHP only which has not occurred (setpoint 4 psig).

5

Given the following with the Plant operating at full power:

P-50A, Primary Coolant Pump, (PCP) ammeter lowers to approximately 100 amps

The reactor automatically trips approximately 1-2 seconds later

PCPs P-50B, C, D remain operating normally
Which one of the following would account for all of the above conditions?
a. P-50A pump shaft seized and the Reactor tripped due to low Primary Coolant flow.
b. P-50A pump shaft sheared and the Reactor tripped due to low Primary Coolant flow.
c. P-50A pump shaft seized and the Reactor tripped due to Thermal Margin/Low Pressure.
d. P-50A pump shaft sheared and the Reactor tripped due to Thermal Margin/Low Pressure.

b. P-50A pump shaft sheared and the Reactor tripped due to low Primary Coolant flow.

a. Plausible but if the pump shaft was seized, amps would be much higher or the output breaker would have tripped and amps would be zero.
b. CORRECT
c. Plausible but amps would be zero or max and the reactor would trip on low PCS flow.
d. Plausible but reactor will trip on low PCS flow (96%).

6

Given the following:

The Plant is in MODE 1 at full power

Charging and Letdown systems are aligned for normal operation

EK-0709, "VOLUME CONTROL TANK HI-LO LEVEL" alarm annunciates
While investigating the above alarm, EK-0710, "VOLUME CONTROL TANK LO-LO LEVEL" alarm annunciates. Which one of the following describes the effect on the Plant due to this condition and the reason?
a Reactor power will be lowering due to Charging Pumps swapping suction to Boric Acid Storage Tanks.
b. Reactor power will be lowering due to Charging Pumps swapping suction to the SIRW Tank.
c. Pressurizer level will be lowering due to all Charging Pumps automatically tripping.
d. Pressurizer level will be lowering due to all Letdown Orifice Stop Valves automatically opening.

b. Reactor power will be lowering due to Charging Pumps swapping suction to the SIRW Tank

a. Plausible if the student confuses the automatic swapover to the SIRW tank with Boric Acid Storage Tanks.
b. CORRECT
c. Plausible if the student believes that this is an automatic action, which it is not.
d. Plausible if the student believes that this is an automatic action, which it is not.

7

Given the following conditions:

The Plant is in MODE 5 with the Shutdown Cooling System in service

CV-3006, SDC Heat Exchangers Bypass, is being throttled 30% open in MANUAL by FIC-0306, SD CLG HXS Bypass Controller, on Panel C-02

Y01, Instrument AC Bus, de-energizes due to a loss of the normal power supply

Due to a malfunction, Y50, Instrument AC Bus Transfer Switch, transfers to the alternate power supply 10 seconds later
After Y01 is re-energized, CV-3006 will be ....
a. full closed.
b. 30% open.
c. 50% open.
d. full open.

d. full open.

a. Plausible if the student believes that this is the fail position for this valve.
b. Plausible if the student believes that the valve will "remember" what position it was in prior to the loss of power.
c. Plausible if the student confuses operation of CV-3006 with operation of CV-3055, SDC HX Inlet Valve, i.e., that it has air ported to the top of the cylinder and the bottom, therefore the valve would be 50% open.
d. CORRECT - This question tests the candidates knowledge of a re-energization of FIC-0306 after a loss of power for > 2seconds.

8

Given the following:

The Plant is in MODE 3 with a cooldown in progress in accordance with GOP-9, "MODE 3 ≥ 525°F TO MODE 4 OR MODE 5"

A loss of Component Cooling Water (CCW) event occurs

The Control Room team enters ONP-6.2, "Loss of Component Cooling"
Why does ONP-6.2 direct Operators to secure Charging Pump, P-55A, but NOT Charging Pumps P-55B or P-55C?
a. P-55A lubricating oil will reach a high temperature limit rapidly on a loss of CCW.
b. P-55B and P-55C have NO interface with CCW.
c. P-55A fluid drive will reach a high temperature limit rapidly on a loss of CCW.
d. P-55B and P-55C automatically trip on a loss of CCW.

c. P-55A fluid drive will reach a high temperature limit rapidly on a loss of CCW.

a. Plausible if the student believes that the lubricating oil is the same oil that operates the fluid drive (these are separate systems).
b. Plausible but CCW cools the oil system, however, the pump can operate for hours without CCW.
c. CORRECT
d. Plausible if the student believes that P-55B and P-55C trip on loss of CCW because P-55A is variable speed and stays in service

9

Given the following with the Plant at full power:

Pressurizer pressure is being controlled at setpoint by PIC-0101A (Channel 'A') in AUTOMATIC

I&C has just completed working on PIC-0101B (Channel 'B') and requests that control be transferred to Channel 'B' to verify proper operation of the controller

Currently, PIC-0101B is in MANUAL with the output at 100%
What will be the immediate effect of placing the Pressurizer Pressure Control Selector Switch, 1/PRC-0101, in the Channel 'B' position under these conditions?
a. Spray valves will both fully open and proportional heater amps go to minimum.
b. Spray valves will both fully open and proportional heater amps go to maximum.
c. Spray valves will both fully close and proportional heater amps go to maximum.
d. Spray valves will both fully close and proportional heater amps go to minimum.

a. Spray valves will both fully open and proportional heater amps go to minimum.

a. CORRECT
b. Plausible if the student believes that 100% output on the controller is spray valves open and heaters max.
c. Plausible if the student believes that 100% output on the controller is spray valves closed and heaters max.
d. Plausible if the student believes that 100% output on the controller is spray valves closed and heaters min.

10

With the Plant at full power the following occurs:

The Main Turbine trips due to a low vacuum condition, but the reactor does NOT trip

The Reactor Operator attempts to trip the reactor using the pushbutton on panel C-02 but is unsuccessful

The Reactor Operator then successfully trips the reactor using the pushbutton on panel C-06
Based on the above conditions, which one of the following describes the status of Reactor Trip Breakers, 42-1RPS and 42-2RPS and the Red RPS "Trip" Lights on the CRDM Clutch Power Supply drawers on panel C-06? (refer to picture of a Clutch Power Supply drawer below)

a. 42-1RPS and 42-2RPS are CLOSED.
Red RPS "Trip" Lights are OFF.
b. 42-1RPS and 42-2RPS are CLOSED.
Red RPS "Trip" Lights are LIT.
c. 42-1RPS and 42-2RPS are TRIPPED.
Red RPS "Trip" Lights are OFF.
d. 42-1RPS and 42-2RPS are TRIPPED.
Red RPS "Trip" Lights are LIT.

d. 42-1RPS and 42-2RPS are TRIPPED.
Red RPS "Trip" Lights are LIT

a. The student misapplies the method of trip from C-06 and believes that the Red RPS "Trip" Lights may not light if C-06 method is used.
b. The student correctly applies that the Red RPS "Trip" Lights are lit but misapplies the method of reactor trip from C-06.
c. The student correctly applies the method of reactor trip from C-06 and believes that the Red RPS "Trip" Lights may not light if C-06 method is used.
d. CORRECT

11

Given the following:

The Plant was tripped due to a large tube rupture in the 'A' Steam Generator

EOP-1.0, "Standard Post Trip Actions," have been completed

The crew has transitioned to EOP-5.0, "Steam Generator Tube Rupture Recovery"

Average temperature of Qualified CETs is 506°F

All Primary Coolant Pumps have been secured
For the above conditions, which one of the following would indicate that natural circulation flow does NOT exist?
a. Loop Hot Leg and Cold Leg temperatures are constant.
b. Loop Cold Leg temperatures are 461°F.
c. Loop Hot Leg temperatures are 488°F.
d. PCS Pressure is 920 psia.

c. Loop Hot Leg temperatures are 488°F.

a. Loop THs and TCs must be constant or lowering.
b. Core ΔT must be 25°F ; Saturation temp for 920 psia is 534°F - CET Temp of 506°F = 28°F subcooling.

12

Given the following:

A Main Steam Line Break has occurred outside of Containment and upstream of CV-0510, 'A' Steam Generator (S/G) Main Steam Isolation Valve

The 'A' S/G has blown dry

An Operator has been directed to perform the actions outside the Control Room necessary for isolation of 'A' S/G
What effect, if any, will isolating the 'B' S/G (vice the 'A' S/G) have on the Control Room’s ability to mitigate this event?
a. No effect because the 'A' and 'B' main steam lines are cross-tied.
b No effect because the Turbine Bypass Valve can be used for PCS Heat Removal.
c. Will lose the ability to control PCS temperature using the ADVs.
d. Will lose the ability to control PCS pressure.

c. Will lose the ability to control PCS temperature using the ADVs.

a. Plausible if the student has a faulty mental picture of the Main Steam diagram and where the MSIVs are located in reference to the cross-tie line.
b. Plausible if the student once again has a faulty mental picture of the Main Steam diagram and believes the TBV can be used without cross-tying S/Gs and blowing them both dry.
c. CORRECT
d. Plausible if the student believes that the PORVs are not available to lower pressure.

13

Given the following:

The Plant is at 83% power

MFPs, P-1A and P-1B, are in service
Based on the above conditions, which one of the following requires an immediate reactor trip and entry into EOP-1.0, "Standard Post Trip Actions"?
a. EK-0160, "FDWTR PUMPS LO SUCTION," alarms with MFP suction pressure indicating 280 psig and stable.
b. EK-0143, "FW PUMP P1A TURBINE K7A TRIP," alarms with associated Trip & Throttle Valves indicating closed.
c. EK-0962, "STEAM GEN E-50A LO LEVEL," alarms with 'A' S/G level indicating 47% and lowering.
d. EK-0961, "STEAM GEN E-50A HI LEVEL," alarms with 'A' S/G level indicating 85% and stable.

a. Plausible but both MFPs will still be in service. ARP actions do not direct a trip for this alarm.
b. CORRECT
c. Plausible but reactor trip is not directed until level reaches 30%.
d. Plausible but reactor trip is not directed until level reaches 90%.

b. EK-0143, "FW PUMP P1A TURBINE K7A TRIP," alarms with associated Trip & Throttle Valves indicating closed

14

During a Station Blackout event, what is the preferred method of controlling PCS temperature?
a. Turbine Bypass Valve Controller, PIC-0511, in AUTO.
b. Atmospheric Dump Valves with Steam Dump Controller, HIC-0780A, in MANUAL.
c. Atmospheric Dump Valves with Steam Dump Controller, HIC-0780A, in AUTO.
d. Turbine Bypass Valve Controller, PIC-0511 in MANUAL.

b. Atmospheric Dump Valves with Steam Dump Controller, HIC-0780A, in MANUAL.

a. With a loss of power, there are no Cooling Tower Pps. or Condensate Pumps, and the resulting loss of Main Condenser vacuum will not allow use of the TBV. Also, there is no power to the TBV controller.
b. CORRECT
c. The ADV controllers are not tuned for automatic mode during natural circ operations.
d. With a loss of power, there are no Cooling Tower Pps. or Condensate Pumps, and the resulting loss of Main Condenser vacuum will not allow use of the TBV. Also, there is no power to the TBV controller.

15

With the Plant in MODE 5 and Shutdown Cooling in service, Y01, Instrument AC Bus, is de-energized. The Control Room team references ONP-24.5, "Loss of Instrument AC Bus Y01."
Why does ONP-24.5 direct the Operators to use ONP-17 "Loss of Shutdown Cooling," to mitigate this event?
a. CV-0937 and CV-0938, CCW to Shutdown Cooling HXs Inlet, fail closed upon a loss of Y01.
b. CV-3006, Shutdown Cooling HXs Bypass, fails open upon a loss of Y01.
c. MO-3015 and MO-3016, Shutdown Cooling from PCS Loop 2, fail closed upon a loss of Y01.
d. CV-3027 and CV-3056, SIRW Tank T-58 Recirc, fail open upon a loss of Y01.

b. CV-3006, Shutdown Cooling HXs Bypass, fails open upon a loss of Y01.

a. Plausible as this is the cooling water for SDC Heat Exchangers.
b. CORRECT - ONP-17 provides direction on taking manual control of CV-3006.
c. Plausible as this is the source of water to the LPSI pumps.
d. Plausible as this will divert water away from the SDC Heat Exchangers.

16

The following alarm is received in the control room:
EK-0548 "125V DC BUS UNDERVOLTAGE/TROUBLE"
The cause of the alarm is determined to be an inadvertent opening of 125 VDC Tie Breaker for DC Buses D20R and D20L, 72-20. Which one of the following actions will restore power to D20L?
a. Place Battery Charger #2 in service from MCC-2.
b. Place Battery Charger #4 in service from MCC-2.
c. Place Battery Charger #2 in service from MCC-1.
d. Place Battery Charger #4 in service from MCC-1.

d. Place Battery Charger #4 in service from MCC-1.

a. Plausible if the student believes that charger #2 is isolated from the station battery.
b. Plausible if the student believes that charger #4 is the non cross-connected battery charger.
c. Plausible if the student believes that charger #2 is isolated from the station battery and is the cross-connected battery charger.
d. CORRECT

17

Given the following with the Plant operating at full power:

Emergency Diesel Generator (EDG) 1-1 monthly surveillance test, MO-7A-1, is in progress

EDG 1-1 is loaded to 1000 kW

EK-0551, "DIESEL GEN NO 1-1 TROUBLE," annunciates

The Auxiliary Operator reports that EK-2011, "LOW RAW WATER PRESSURE," is annunciating on the local EDG 1-1 alarm panel

Raw water pressure on the 1-1 EDG local control panel indicates 0 (zero) psig
Which one of the following will occur if no operator action is taken?
EDG 1-1 will ...
a. trip when jacket water temperature reaches 195°F.
b. continue to operate until engine damage occurs from overheating.
c. trip when lube oil temperature reaches 205°F.
d. continue to operate normally since engine load is

b. continue to operate until engine damage occurs from overheating.

a. Plausible because an alarm will occur when jacket water temperature reaches 195°F but there is no auto trip.
b. CORRECT
c. Plausible because an alarm will occur when lube oil temperature reaches 200°F but there is no auto trip.
d. Plausible if the student believes that external sw cooling is only absolutely necessary for high EDG loads as in a DBA.

18

The Plant is operating at full power when a disturbance on the grid causes the following Main Generator indications:

832 MWe

350 MVARs OUT

22,500 Amps
The Control Room Supervisor then orders the NCO-T to adjust MVARs to 0 (zero). Upon completion of adjusting MVARs, amps will be ___(1)___ and MWe will be ___(2)___.
a. (1) lower
(2) lower
b. (1) lower
(2) unchanged
c. (1) unchanged
(2) lower
d. (1) unchanged
(2) unchanged

b. (1) lower
(2) unchanged

a. Plausible if the student believes that MWe will be affected by adjustment of MVARs.
b. CORRECT
c. Plausible if the student believes that the ammeter does not reflect changes in MVARs and that that MWe will be affected by adjustment of MVARs.
d. Plausible if the student believes that the ammeter does not reflect changes in MVARs.

19

Given the following:

The Plant is operating at 100% power

'A' Channel of Pressurizer Level Control (LIC-0101A) is in service due to 'B' channel (LIC-0101B) failing low

ALL Pressurizer Heaters are tripped off and CV-2003, Orifice Stop Valve, is closed due to LIC-0101B failing low

Pressurizer Heater Control Channel Selector Switch (1/LIC-0101) is in the 'A' and 'B' position

Charging, Letdown, and Pressurizer Heater Controls are lined up for normal operation
Plant procedures direct the Pressurizer Heater Control Channel Selector Switch (1/LIC-0101) be placed in Channel 'A' for this condition. What will automatically occur when this is completed?
a. CV-2003 will open AND Pressurizer Heaters powered from ONLY Bus 1E will energize.
b. CV-2003 will open AND Pressurizer Heaters powered from Bus 1D AND Bus 1E will energize.
c. ONLY CV-2003 will open.
d. ONLY Pressurizer Heaters powered from Bus 1E will energize.

a. CV-2003 will open AND Pressurizer Heaters powered from ONLY Bus 1E will energize.

a. CORRECT
b. Plausible because this was the original intent of the control switch, but a modification was installed due to EDG loading such that when heaters from Bus 1D are tripped, manual initiation is required to re-energize them.
c. Plausible if the student does not know that pressurizer heaters trip on low level.
d. Plausible if the student believes that CV-2003 is not controlled from PZR Level.

20

Given the following:

The Plant is in MODE 6 with refueling operations in progress

Containment Refueling Monitors, RIA-2316 and RIA-2317, are in service (switches cut 'IN')
Which one of the following alarms, if any, would alert the Control Room team that RIA-2316 reached an alarm setpoint due to a fuel handling incident?
a. EK-1126, "CIS INITIATED."
b. EK-1363, "CONTAINMENT HI RADIATION."
c. EK-1366, "PLANT MONITORING HI RADIATION."
d. NONE, RIA-2316 AND RIA-2317 are BOTH required to alarm.

a. EK-1126, "CIS INITIATED."

a. CORRECT
b. Plausible because this for a CHR when the plant is on-line, this is the alarm that will be received in addition to EK-1126, however, this alarm is initiated by the Containment Radiation Monitors.
c. Plausible because various ARM systems initiate this alarm, however, RIA-2316 does not.
d. Plausible if the student misapplies the logic for CIS from the Refueling Monitors and believes that it is 2/2.

21

Given the following:

The Plant was tripped due to a tube leak in the 'A' Steam Generator (S/G)

EOP-1.0, "Standard Post Trip Actions," have been completed

The crew has transitioned to EOP-5.0, "Steam Generator Tube Rupture Recovery"

The Control Room team is reviewing the conditions necessary to isolate the 'A' Steam Generator per EOP Supplement 12, 'A' S/G SGTR Isolation Checklist"
Which one of the following would indicate to the Control Room team that isolation of the 'A' Steam Generator is NOT allowed per EOP-5.0?
a. PCS Pressure is 75 psi above 'A' Steam Generator Pressure.
b. Core Exit Thermocouple (CET) Temperature is 528°F.
c. 'A' Steam Generator Pressure is 920 psia.
d. Narrow Range Hot Leg Temperature is 526°F.

d. Narrow Range Hot Leg Temperature is 526°F.

a. Plausible if the student gets confused between isolation of the S/G and lowering PCS pressure to within 50 psi to allow backflow.
b. Plausible if the student does not know that EOP-5.0 specifies that the crew uses narrow range TH instruments only
c. Plausible because EOP-5.0 directs the crew to unisolate a S/G with an ASDV if pressure is >940 psia.
d. CORRECT

22

Given the following:

The Waste Gas System is lined up for normal operation

An inadvertent release to the Plant Stack from Waste Gas Decay Tank, T-101A, occurs

Waste Gas Discharge Monitor, RIA-1113, alarms
Which one of the following will automatically occur to stop the inadvertent gaseous release?
a. V-14A/B, Radwaste Area Exhaust Fans, will trip.
b. CV-1123, Waste Gas Decay Tank Discharge, will close.
c. V-6A/B, Main Exhaust Fans, will trip, and associated dampers will close.
d. C-50A/B, C-54, Waste Gas Compressors, will trip.

b. CV-1123, Waste Gas Decay Tank Discharge, will close

a. Plausible if the student misapplies the flow path of waste gas, i.e., through V-14A/B vice directly to stack.
b. CORRECT
c. Plausible if the student misapplies the flow path of waste gas, i.e., to the main exhaust plenum, instead of to the stack.
d. Plausible if the student believes that the compressor if required for flow from the WGDT to the stack.

23

The Containment Radiation Monitors, RIA-1805, RIA-1806, RIA-1807, and RIA-1808, can fail high during a LOCA or ESDE due to the harsh environmental effects on these instruments. Due to this condition, which one of the following actions is performed during EOP-1.0, "Standard Post Trip Actions," when Containment radiation levels indicate >10R/Hr?
a. Ensure operating all Containment Air Cooler Fans and open all Containment Air Cooler High Capacity Service Water Valves.
b. Verify EK-1363, "CONTAINMENT HI RADIATION," is NOT in an alarm condition.
c. Corroborate Containment radiation readings with Containment Ventilation System Radiation Monitor, RIA-1817, reading.
d. Corroborate Containment radiation readings with Containment High Range Monitors, RIA-2321/2322, readings.

d. Corroborate Containment radiation readings with Containment High Range Monitors, RIA-2321/2322, readings.

a. Plausible as this is an immediate action in EOP-1.0 for containment atmosphere.
b. Plausible but this alarm comes from the Containment Area Radiation Monitors.
c. Plausible but this is a gaseous monitor.
d. CORRECT

24

Given the following:

A fire occurs in the Cable Spreading Room which requires tripping the Reactor and evacuating the Control Room

The Shift Manager has directed C-150/C-150A, Auxiliary Hot Shutdown Panels, be placed in service

The AVG TEMP DISPLAY SELECT SWITCH on panel C-02 is in the "LOOP 1" position
ONP-25.2, "Alternate Safe Shutdown Procedure," directs placing the AVG TEMP DISPLAY SELECT SWITCH in the "LOOP 2" position prior to evacuating the Control Room.
If this step is NOT completed, when C-150/C-150A panels are placed in service ...
a. the Atmospheric Dump Valves will open.
b. the Atmospheric Dump Valves will not open, if required.
c. TAVE indication will not be accurate.
d. TAVE indication will not be available.

a. the Atmospheric Dump Valves will open

a. CORRECT
b. Plausible because the signal for opening the ADVs on a high TAVE signal is routed through this switch.
c. Plausible if the student believes that the switch routes the TH and TC signals to C-150A, however TAVE is not available at C-150/C-150A.
d. Plausible because the signal for opening the ADVs on a high TAVE signal is routed through this switch, however TAVE is not available at C-150/C-150A.

25

Given the following with the Plant in MODE 6 during a refueling outage:

The Reactor Cavity is full

Fuel handling is in progress

All Containment Building penetrations are OPERABLE

The Emergency Escape Airlock is closed

A loss of Shutdown Cooling event occurs

The time for the PCS to reach 200°F is 3 hours
Which one of the following describes when Containment closure shall be achieved and the minimum requirements for closure in accordance with ONP-17, "Loss of Shutdown Cooling"?
Containment closure shall be achieved prior to the time it takes...
a. for PCS temperature to heat up to 200°F.
Close the Equipment Hatch AND one door of the Personnel Air Lock.
b. for any Containment Refueling Monitor, RIA-2316 or RIA-2317, to alarm.
Close the Equipment Hatch AND one door of the Personnel Air Lock.
c. for PCS temperature to heat up to 200°F.
Close the Equipment Hatch ONLY.
d. for any Containment Refueling Monitor, RIA-2316 or RIA-2317, to alarm.
Close the Equipment Hatch ONLY.

a. for PCS temperature to heat up to 200°F.
Close the Equipment Hatch AND one door of the Personnel Air Lock.

a. CORRECT
b. Plausible but not required.
c. Plausible if the student believes that the Personnel Air lock can stay opened.
d. Plausible if the student believes that the Personnel Air lock can stay opened.

26


A fuel cladding failure event is in progress

The Control Room team has implemented ONP-11.1, "Fuel Cladding Failure"

Radioactive Gas Effluent Monitor (RGEM) annunciator EK-0207, “STACK EFF RAD C-169 HIGH” is received in the Control Room
Which one of the following will automatically occur based on the above conditions?
a. Both RGEM sample pumps, P-2301A and P-2301B, will start.
b. RGEM transfers to RIA-2327, High Range Noble Gas Monitor.
c. RIA-2327, High Range Monitor, transfers from R/hr mode to uCi/ml mode.
d. RIA-2325, Iodine and Particulate Monitor, is aligned for operation

b. RGEM transfers to RIA-2327, High Range Noble Gas Monitor

a. Plausible if the student believes that more flow is needed because there is two parallel flow paths in the accident mode.
b. CORRECT
c. Plausible if the student believes that the meter reads in uCi/ml for a more accurate off-site dose assessment.
d. Plausible because Iodine is an off-site dose concern.

27

Given the following during a Loss of Forced Circulation Event:

TH temperature is 578°F

TC temperature is 538°F

Average Qualified CET temperature is 582°F

TAVE is 556°F

Pressurizer Pressure is 2060 psia
Which one of the following is the correct value for PCS subcooling?
a. 58°F.
b. 62°F.
c. 84°F.
d. 102°F.

a. 58°F

a. CORRECT - per EOP-8.0, step 19, average CET temperature is used to determine subcooling. Saturation temperature for PCS pressure is 640°F - 582°F (Average CET temperature) is 58°F.
b. Plausible - this corresponds to hot leg temperature.
c. Plausible - this corresponds to average coolant temperature.
d. Plausible - this corresponds to cold leg temperature.

28

The Plant is operating at full power when a spurious Containment High Radiation (CHR) signal occurs. Which one of the following describes the effect of this condition on the Primary Coolant Pumps?
a. Seal temperatures will rise.
b. Controlled Bleedoff flow will lower to zero.
c. Controlled Bleedoff pressure will rise.
d. Controlled Bleedoff pressure will lower to zero.

c. Controlled Bleedoff pressure will rise.

a. Plausible if the student believes that a CHR causes a loss of CCW to the PCPs.
b. Plausible because backpressure rises, however, each stage pressure will rise to maintain flow stable.
c. CORRECT - Upon a CHR, normal CBO isolates causing RV-2082 to open at 145 psig; Normal CBO pressure is 25 - 100 psig.
d. Plausible because the PSDT is vented to atmosphere.

29

Given the following conditions:

The Plant is operating at full power

Pressurizer level is at program level and stable

P-55A, Charging Pump, is operating in CASCADE speed control

EK-0701, "REGEN HT EX TUBE OUTLET HI TEMP," annunciates on panel C-12

TICA-0201, Letdown Temp indication, fails off-scale high (> 600°F)

TI-0212, Charging Temp, indicates 400°F
Assuming no operator action, which one of the following identifies the resulting charging and letdown flow after several minutes?

Charging Letdown
a. 33 GPM 40 GPM
b. 0 GPM 40 GPM
c. 33 GPM 0 GPM
d. 0 GPM 0 GPM

c. 33 GPM 0 GPM

a. Plausible if the student believes that charging goes to minimum and one letdown orifice stop valve stays open.
b. Plausible if the student believes that charging only isolates on high temperature.
c. CORRECT - CV-2001, letdown stop valve, closes @ 470°F letdown temperature.
d. Plausible because the student may believe that charging flow isolates on high temperature in addition to letdown.

30

The following conditions exist during a Plant cooldown:

The Plant is in MODE 4 at 255°F

The PCS is in solid Plant pressure control at 255 psia

Shutdown cooling is in-service using P-67A, LPSI Pump

P-50B and P-50D, Primary Coolant Pumps, are in-service

All PCS and SDC temperatures are slowly lowering

SDC flow is being controlled at 3200 gpm using FIC-0306, SD CLG HXs Bypass Controller
The control room receives EK-1162, "LPSI PUMP LOW DISCHARGE PRESSURE." Following the alarm’s receipt the control room team observes the following indications:

Red indicating light for P-67A is ON

SDC Flow is 150 gpm
Which one of the following describes the impact of the above indications and the appropriate action(s) per ONP-17, "Loss of Shutdown Cooling"?
a. PCS pressure will lower rapidly; TRIP P-67A, LPSI Pump, ONLY.
b. PCS temperature will begin to rise; START P-67B, LPSI Pump, then TRIP P-67A, LPSI Pump.
c. PCS pressure will lower rapidly; START P-67B, LPSI Pump, then TRIP P-67A, LPSI Pump.
d. PCS temperature will begin to rise; TRIP P-67A, LPSI Pump, ONLY.

d. PCS temperature will begin to rise; TRIP P-67A, LPSI Pump, ONLY.

a. The student correctly diagnoses the action but believes that the LPSI pump is helping to maintain PCS pressure. This is plausible because the students are trained that the LPSI pump shutoff head is ~275 psig.
b. The student correctly diagnoses that PCS temperature will begin to rise but believes that it is acceptable to start the other train LPSI pump when ONP-17 states specifically not to.
c. The student believes that the LPSI pump is helping to maintain PCS pressure. This is plausible because the students are trained that the LPSI pump shutoff head is ~275 psig. The student also believes that it is acceptable to start the other train LPSI pump when ONP-17 states specifically not to.
d. CORRECT - per ONP-17 step 4.2.

31

Given the following:

The Plant is in MODE 3

Preparations are being made to perform a critical approach and enter MODE 2
Safety Injection Tank parameters are as follows:
SIT
PRESSURE
LEVEL (%narrow range)
BORON (ppm)
T-82A
207
52
2050

T-82B
217
25
1920

T-82C
219
67
1880

T-82D
215
55
1740
Based on the above parameters, which Safety Injection Tank will NOT be able to perform it's design function if the Plant is placed in MODE 2?
a. T-82A
b. T-82B
c. T-82C
d. T-82D

T-82C
219
67
1880


a. Plausible because the student may believe that the pressure is too low.
b. Plausible because the student may believe that level is too low.
c. CORRECT - Level must be between 18 - 66%. This question matches the K/A because SITs are passive components and if SIT pressure is not within the required tech spec range, they will not properly perform their function when automatically injected into the core.
d. Plausible because the student may believe that boron concentration is too low.

32

Following a Large Break Loss of Coolant Accident, the Pressurizer is being vented to the Quench Tank in accordance with EOP Supplement 26, "PCS Void Removal," using PRV-1069, Reactor Head Vent Pressurizer Vent Valve. Which one of the following describes the effect of a temporary loss of DC power to PRV-1069?
PRV-1069 will (1) upon loss of power and will (2) when power is restored.
a. (1) close
(2) remain closed
b. (1) close
(2) open
c. (1) remain open
(2) close
d. (1) remain open
(2) remain open

a. (1) close
(2) remain closed

a. CORRECT
b. Plausible if the student is not aware of the RESET feature of the valve.
c. Plausible if the student incorrectly applies the RESET feature of the valve.
d. Plausible if the student believes that loss of power does not effect the valve.

33

With the Plant on line at full power, a loss of Component Cooling Water event occurs. Which one of the following meets a condition for tripping the Reactor in accordance with ONP-6.2, "Loss of Component Cooling"?
a. EK-0908, "PRI COOLANT PUMP P-50B HI TEMP OVERLOAD" annunciates due to bearing temperature.
b. EK-0703, "LETDOWN HT EX TUBE OUTLET HI TEMP" annunciates.
c. CCW flow to Containment is lost for 2 minutes.
d. EK-0954, "ROD DRIVE SEAL LEAK OFF HI TEMP" annunciates due to seal leak off temperature for Control Rod 41.

a. EK-0908, "PRI COOLANT PUMP P-50B HI TEMP OVERLOAD" annunciates due to bearing temperature.

a. CORRECT
b. Plausible but the Demineralizers in the CVCS system can be bypassed.
c. Plausible but CCW flow must be lost for 10 minutes before a reactor trip is required.
d. Plausible but all or most of the CRDM leak off temperatures must be in alarm (>200°F).

34

The Plant is in MODE 3 at normal operating temperature and pressure when the following conditions are noted:

T-3, Component Cooling Water (CCW) Surge Tank, level is rising 2% per minute

RIA-0915, CCW Radiation Monitor, counts are rising
Which one of the following would indicate that the potential source of PCS leakage into the CCW System for these conditions is from P-50A, Primary Coolant Pump?
a. P-50A Lower Seal pressure rises to PCS pressure.
b. P-50A Lower Seal temperature rises by 10°F.
c. P-50A Cooling Water Outlet temperature lowers by 10°F.
d. P-50A Lower Seal temperature lowers by 10°F.

b. P-50A Lower Seal temperature rises by 10°F.

a. Plausible but this is a partial indication of a seal stage failure.
b. CORRECT
c. Plausible but PCS water would cause the CCW temperature to rise.
d. Plausible but temperature would rise because no CCW is entering the PCS side of the seal.

35

Given the following:

The Plant is operating at full power

PIC-0101A, 'A' Channel Pressurizer Pressure Controller, is in service
Which one of the following lists the power supply to PIC-0101A and the effect of a loss of power to PIC-0101A?
a. Preferred AC Bus Y10, PCS pressure lowers.
b. Preferred AC Bus Y30, PCS pressure lowers.
c. Preferred AC Bus Y10, PCS pressure rises.
d. Preferred AC Bus Y30, PCS pressure rises.

c. Preferred AC Bus Y10, PCS pressure rises.

a. Correct power supply, wrong effect.
b. Wrong power supply, wrong effect.
c. CORRECT
d. Wrong power supply, correct effect.

36

Given the following conditions with the Plant operating at full power:

PIC-0751C, E-50A Steam Generator Low Pressure Channel CKT #3, on panel C-12 has failed low

PA-0751C, S/G Low Pressure Trip Unit Channel 'C', on Reactor Protection System (RPS) Panel C-06, has been bypassed
Which one of the following describes (1) The current channel trip logic for RPS and (2) The effect on the Reactor, if any, if PIC-0751A, E-50A Steam Generator Low Pressure Channel CKT #1, fails low?
a. (1) Channel trip logic is now 1 out of 3
(2) The Reactor will NOT trip
b. (1) Channel trip logic is now 1 out of 3
(2) The Reactor will trip
c. (1) Channel trip logic is now 2 out of 3
(2) The Reactor will NOT trip
d. (1) Channel trip logic is now 2 out of 3
(2) The Reactor will trip

d. (1) Channel trip logic is now 2 out of 3
(2) The Reactor will trip

a. Plausible if the student believes that bypassing a channel causes the logic to be 1/3 and also believes that a S/G pressure indicator failing low will not cause the reactor to trip.
b. Plausible if the student believes that bypassing a channel causes the logic to be 1/3 and correctly diagnoses that the reactor will trip.
c. Plausible if the student correctly diagnoses that trip logic is 2/3 but believes that the reactor will not trip because an additional failure is required.
d. CORRECT - With one channel of RPS bypassed, trip logic is 2 out of 3. When the second PIC fails low, the MSIVs will close on low S/G pressure causing an automatic reactor trip.

37

Given the following conditions:

A small break LOCA has occurred

Safety Injection has actuated

Containment pressure rose to 8.5 psig and has since lowered to 1.0 psig

The CHP signal is RESET

The Reactor Operator has placed the Containment Spray Pump hand switches in TRIP and returned them to mid-position

The Containment Spray valves are closed
If the PCS break size gets larger causing Containment Pressure to rise and exceed the Containment High Pressure (CHP) actuation setpoint, how will the Containment Spray System respond?
a. Containment Spray valves will open.
Containment Spray pumps will NOT start.
b. Containment Spray valves will open.
Containment Spray pumps will start.
c. Containment Spray valves will NOT open.
Containment Spray pumps will NOT start.
d. Containment Spray valves will NOT open.

a. Containment Spray valves will open.
Containment Spray pumps will NOT start

a. CORRECT - When the handswitch was taken to "TRIP", the SIS "ARM" signal was removed, the pump would not have started for this condition unless SIS was reset when pressure rose above 1687 psia.
b. Student misapplies the reset criteria.
c. Student misapplies the reset criteria.
d. Student misapplies the reset criteria.

38


The Plant is being cooled down and depressurized in preparation for a refueling outage

Safety Injection has been BLOCKED

A failure of the Pressurizer pressure controller causes PCS pressure to rise from 1550 psia to the following:
o
A Channel - 1700 psia
o
B Channel - 1685 psia
o
C Channel - 1695 psia
o
D Channel - 1705 psia
Based on the above conditions, the Safety Injection Signal is:
a. no longer blocked since 3/4 pressure channels have increased above the reset setpoint. Safety Injection WILL actuate when pressure is lowered to

a. no longer blocked since 3/4 pressure channels have increased above the reset setpoint. Safety Injection WILL actuate when pressure is lowered to

39

Which one of the following would indicate that a contingency action is required to be taken during the performance of EOP-1.0, "Standard Post Trip Actions"?
a. EK-1362, "CONTAINMENT PRESSURE OFF NORMAL," annunciates and Containment pressure indicates 4.2 psig.
b. EK-0546, "PREFERRED AC BUS NO 4 TROUBLE," annunciates and Preferred AC Bus Y40 is de-energized.
c. EK-1351, "CONTAINMENT SUMP HI LEVEL," annunciates and Containment Sump level indicates 585.5 feet.
d. EK-0962, "STEAM GEN E-50A LO LEVEL," annunciates and 'A' Steam Generator level indicates 40%.

a. EK-1362, "CONTAINMENT PRESSURE OFF NORMAL," annunciates and Containment pressure indicates 4.2 psig.

a. CORRECT - EOP-1.0 requires contingency actions to be taken if Cont. Pressure reaches 4.0 psig.
b. Plausible but EOP-1.0 requires 3/4 Preferred AC buses and there are no contingency actions if more than one bus was lost.
c. Plausible as this would indicate a PCS leak but there are no contingencies for sump level.
d. Plausible but contingency action is not required until 5%.

40

Given the following:

A Main Steam Line Break has occurred inside Containment

Containment Spray has actuated

Containment pressure rose to 10 psig and is now lowering

Operators are evaluating when Containment Spray may be secured
As Containment pressure lowers, which one of the following is the earliest allowable pressure at which all Containment Spray may be secured?
a. 3.5 psig.
b. 2.5 psig.
c. 1.5 psig.
d. 0.8 psig.

b. 2.5 psig.

a. Plausible if the student believes that spray can be secured as soon as pressure is less than the CHP setpoint.
b. CORRECT
c. Plausible if the student misapplies the maximum pressure limit.
d. Plausible as this is a pressure for a contingency in EOP-1.0.

41

The following conditions exist:

A Plant trip from 100% power occurs

386AST, Turbine Trip Relay, does NOT actuate when the turbine trips

All other equipment functions as designed
Which one of the following describes the effect on the Plant and the appropriate action?
a. Atmospheric Dump Valves only do NOT open. Verify Steam Generator Code Safety Valves are controlling Steam Generator pressure.
b. Atmospheric Dump Valves only do NOT open. Ensure PIC-0511, Turbine Bypass Valve Controller, is controlling Steam Generator pressure.
c. Atmospheric Dump Valves and Turbine Bypass Valve do NOT open. Verify Steam Generator Code Safety Valves are controlling Steam Generator pressure.
d. Atmospheric Dump Valves and Turbine Bypass Valve do NOT open. Place HIC-0780A, Steam Dump Controller, in MANUAL to control Steam Generator pressure.

b. Atmospheric Dump Valves only do NOT open. Ensure PIC-0511, Turbine Bypass Valve Controller, is controlling Steam Generator pressure.

a. Correct effect but student may believe that the MSIVs close which would actuate the S/G code safety valves.
b. CORRECT - 386AST actuation is required for ADVs to quick open or modulate in AUTO. EOP-1.0 specifies using the Turbine Bypass Valve.
c. Turbine Bypass Valve will still open, 386AST is not required to actuate as long as pressure is > 900 psia.
d. Turbine Bypass Valve will still open, 386AST is not required to actuate as long as pressure is > 900 psia.

42

Given the following:

The Plant is in MODE 1 at full power

A Steam Line Rupture occurs inside the Containment Building

Containment pressure indicates 5.7 psig

'A' Steam Generator (S/G) Pressure indicates 480 psia

'B' Steam Generator (S/G) Pressure indicates 545 psia
Which one of the following describes the expected response of the Main Steam Isolation Valves (MSIVs) and Feed Regulating Valves (FRVs) to this event?
a. BOTH 'A' and 'B' S/G MSIVs close.
BOTH 'A' and 'B' S/G FRVs close.
b. BOTH 'A' and 'B' S/G MSIVs close.
ONLY 'A' S/G FRV closes.
c. ONLY 'A' S/G MSIV closes.
BOTH 'A' and 'B' S/G FRVs close.
d. ONLY 'A' S/G MSIV closes.
ONLY 'A' S/G FRV closes.

a. BOTH 'A' and 'B' S/G MSIVs close.
BOTH 'A' and 'B' S/G FRVs close

a. CORRECT
b. Plausible because a low S/G pressure (4.0psig) will close both S/G FRVs.
c. Plausible if the student believes that low S/G pressure closes only the affected S/G MSIV but both FRVs.
d. Plausible if the student believes that low S/G pressure closes only the affected S/G MSIV and affected FRV.

43

Given the following conditions:

A Plant trip from full power occurs

Steam Generator Water Level Control was in AUTO at the time of the trip

NO operator actions have been taken.
As a result, both Steam Generator Water Level Control (SGWLC) controllers, LIC-0701 and LIC-0703, will ______(1)______ and the Feed Regulating Valves ______(2)______.
a. (1) transfer to MANUAL
(2) will automatically close
b. (1) transfer to MANUAL
(2) must be closed by the Operator
c. (1) remain in AUTO
(2) will automatically close
d. (1) remain in AUTO
(2) must be closed by the Operator

b. (1) transfer to MANUAL
(2) must be closed by the Operator

a. Plausible because the MFPs automatically ramp to minimum speed, student misapplies this.
b. CORRECT
c. Plausible because the MFPs automatically ramp to minimum speed, student misapplies this .
d. Plausible because this is an EOP operator action.

44

Given the following conditions:

The Control Room has been evacuated due to a fire

C-150, Auxiliary Hot Shutdown Panel, has been placed in service
As a result of placing C-150 in service, AFW Pump P-8B:
a. will NOT automatically trip on low suction pressure.
b. will NOT be available as a source of feedwater.
c. automatic speed control is disabled.
d. overspeed trip protection is disabled.

a. will NOT automatically trip on low suction pressure.

a. CORRECT
b. Plausible if the student believes that P-8B cannot be controlled from C-150
c. Plausible if the student believes that electrical power is required for speed control of P-8B.
d. Plausible if the student believes that electrical power is required for overspeed protection.

45

Given the following conditions:

The Plant is operating at 25% power

Emergency Diesel Generator 1-1 is loaded to 2450 kW in PARALLEL with Safeguards Transformer 1-1

A Reactor trip occurs
Based on the above conditions, EDG 1-1 output breaker, 152-107, will:
a. remain closed with load at 2450 kW.
b. immediately open and reclose after load shed.
c. immediately open and remain open.
d. remain closed unless a Safety Injection Signal occurs.

c. immediately open and remain open.

a. Student believes that plant trip has no effect on the Diesel Generator.
b. Student believes that Safeguards Transformer is lost and Diesel will sequence back on.
c. CORRECT
d. Student confuses with the DBA sequencer.

46

Given the following conditions:

A Plant cooldown is in progress in accordance with GOP-9, "MODE 3 ≥ 525°F TO MODE 4 OR MODE 5"

Two (2) diametrically opposed Primary Coolant Pumps (PCPs) are to be secured

One (1) Condensate Pump is to be secured
Which one of the following combinations of PCPs and Condensate Pumps will be left in service to distribute the load as evenly as possible between 4160VAC Buses 1A and 1B AND satisfy the above requirements?

PCPs Condensate pump
a. P-50A P-2A
P-50C

b. P-50A P-2B
P-50D

c. P-50B P-2B
P-50C

d. P-50B P-2A
P-50D

d. P-50B P-2A
P-50D

a. This satisfies the requirement for diametrically opposed PCPs but all of these loads are powered from 4160V bus 1A.
b. This satisfies the requirement to distribute load evenly but P-50A and P-50D are not diametrically opposed.
c. This satisfies the requirement to distribute load evenly but P-50B and P-50C are not diametrically opposed.
d. CORRECT

47

A DC Bus ground has occurred causing the fuse supplying D21A, 125 VDC Distribution Panel, to actuate and open. Which one of the following describes the expected consequence of this failure?
a. MO-2160, SIRWT to Charging Pumps, opens and MO-2087, VCT Outlet, closes.
b. Automatic start for Emergency Diesel Generator 1-1 on bus undervoltage is lost.
c. All breakers on Bus 1D must be manually operated.
d. All control room annunciators are lost.

c. All breakers on Bus 1D must be manually operated.

a. This is the effect of a loss of Y01, Instrument AC Bus.
b. This is the effect from a loss of D21-1.
c. CORRECT
d. This is the effect from a loss of D-21-2.

48

Following an Excess Steam Demand Event due to a Steam Line Break inside the Containment, the following conditions exist:

The Reactor is manually tripped

Containment pressure reaches 4.4 psig

Bus 1C de-energizes, load shed completes, EDG 1-1 output breaker, 152-107, closes

Bus 1D is being powered by the Safeguards Transformer
Which one of the following describes the Sequencer, if any, that is operating?
a. Left Channel DBA Sequencer is operating.
NO Right Channel Sequencer is operating.
b. Left Channel DBA Sequencer is operating.
Right Channel DBA Sequencer is operating.
c. Left Channel NSD Sequencer is operating.
Right Channel NSD Sequencer is operating.
d. Left Channel NSD Sequencer is operating.
NO Right Channel Sequencer is operating.

a. Left Channel DBA Sequencer is operating.
NO Right Channel Sequencer is operating.

a. CORRECT
b. Plausible if the student believes that the right channel will actuate due to the CHP signal and disregards the fact that bus 1D is not lost.
c. Same reason as 'b' above and the student also believes that an SIS signal is not received.
d. Student believes that an SIS signal is not received.

49

Given the following conditions:

The Plant has experienced a loss of all offsite power

Emergency Diesel Generator (EDG) 1-1 is loaded to 2200 kW

EDG 1-2 is NOT available

T-10A, Fuel Oil Storage Tank, level is 85" by dipstick

There is an unrecoverable leak of 1.1 gpm from T-10A
For the above conditions, how long will T-10A inventory be able to support EDG 1-1 operation?
a. 5.8 days.
b. 6.4 days.
c. 8.2 days.
d. 8.5 days.

a. 5.8 days.

a. CORRECT - EDG uses ~2.6 gpm @ 2200 kW(from attachment 2)+ 1.1 gpm for leak = 3.7 gpm. 31000usable gallons(from attachment 3)/3.7 gpm = 5.8 days.
b. Student adds 15 hours from the day tank.
c. Student does not take into account 1.1 gpm leak.
d. Student misreads the attachment 3 graph and uses 85% instead of 85 inches.

50

RE-1113, Waste Gas Process Monitor radiation element, consists of a detector mounted on one side of the Waste Gas discharge pipe with a window through the pipe wall, with the pipe 4 inches in diameter (see below). The detector is a point detector located 1 inch from the ID of the pipe.

Compare the differences in radiation readings for a hot particle that passes along the side of the pipe closest to the detector (Position 'A' above) to the same hot particle that passes along the side of the pipe farthest away from the detector (Position 'B' above).

The radiation reading at Position 'A' will be greater than the reading at Position 'B'.
a. 4 times
b. 5 times
c. 16 times
d. 25 times

d. 25 times

a. Uses linear proportionality and does not account for the inch.
b. Uses linear proportionality.
c. Uses correct proportionality (squared) but does not account for the inch.
d. CORRECT - Dose is proportional to the square of the distance. A count rate of 25 dpm at 1 inch would be equivalent of a count rate of 1 dpm at 5 inches.

51

Given the following:

The Plant is operating at full power

No Equipment is out of service

P-7A and P-7C, Service Water Pumps, are in service

All Containment Air Cooler (CAC) High Capacity SW Outlet Valves are open

Lake Michigan water temperature has steadily risen over the last few hours from 68°F to 80.5°F
As Lake Michigan water temperature rises, Service Water Pump discharge pressure will (1) and (2) to prevent components from overheating.
a. (1) rise
(2) P-7B, Service Water Pump, will be started
b. (1) rise
(2) CAC High Capacity SW Outlet valves will be closed
c. (1) lower
(2) P-7B, Service Water Pump, will be started
d. (1) lower
(2) CAC High Capacity SW Outlet valves will be closed

c. (1) lower
(2) P-7B, Service Water Pump, will be started

a. Incorrect effect, correct action.
b. Incorrect effect, incorrect action.
c. CORRECT - Temperature control valves open to maintain temperatures so discharge pressure lowers.
d. Correct effect, incorrect action.

52

Given the following after a Plant trip due to a loss of all off site power:

EOP-1.0, "Standard Post Trip Actions," are in progress

Bus 1D is being supplied by EDG 1-2; Bus 1C is de-energized

P-7C, Service Water Pump, is in service with Critical Service Water header pressure indicating 35 psig

P-52B, Component Cooling Water Pump, is in service with CCW Header Pressure indicating 98 psig

P-7A, Service Water Pump, is out of service for shaft replacement

A Safety Injection Actuation Signal (SIAS) is NOT present
Which one of the following describes the operational concern due to the above conditions and the correct action to take?
a. Possible Service Water Pump damage due to runout. Close Containment Air Cooler high capacity outlet valves to raise critical Service Water pressure > 42 psig.
b. Possible Component Cooling Water Pump damage due to runout. Close CV-0944A, CCW Supply to SFP HXs, RW Evaporators, and C-50/54.
c. Possible Service Water Pump damage due to runout. Start P-7B, Service Water Pump, to raise Critical Service Water pressure > 42 psig.
d. Possible Component Cooling Water Pump damage due to runout. Close CV-0910, CV-0911, and CV-0940, CCW Supply to and from Containment.

a. Possible Service Water Pump damage due to runout. Close Containment Air Cooler high capacity outlet valves to raise critical Service Water pressure > 42 psig.

a. CORRECT - Operators are expected to know immediate actions from memory.
b. Plausible if student believes that 98 psig CCW header pressure is a threshold for an EOP-1.0 contingency action. This pressure is less than normal (120 psig) but not alarming (80 psig). Closing CV-0944A would restore pressure.
c. Correct Effect, however P-7B has no power available due to bus 1C being de-energized.
d. Plausible if student believes that 98 psig CCW header pressure is a threshold for an EOP-1.0 contingency action. This pressure is less than normal (120 psig) but not alarming (80 psig). Closing CCW supply to and from Containment would restore pressure but is not directed unless there is a Containment Isolation.

53

The following conditions exist:

Instrument Air Compressor C-2A control switch is in HAND

Instrument Air Compressors C-2B and C-2C control switches are in AUTO

Instrument Air Header is currently 90 psig and lowering
Based upon the above Plant conditions, which one of the following describes the response of the Instrument Air System if Instrument Air pressure continues to lower?
Instrument Air Compressors C-2B and C-2C will auto start when Instrument Air header pressure sensed ...
a. UPstream of the filter and dryer reaches 85 psig.
b. DOWNstream of the filter and dryer reaches 85 psig.
c. DOWNstream of the filter and dryer reaches 88 psig.
d. UPstream of the filter and dryer reaches 88 psig.

d. UPstream of the filter and dryer reaches 88 psig

a. Plausible if the student confuses the setpoint for automatic service air isolation.
b. Plausible if the student confuses the setpoint for automatic service air isolation and the location where pressure is sensed.
c. Plausible if the student believes that the standby compressor will start if there is a clogged air dryer or filter.
d. CORRECT

54


The Plant is operating at full power

A leak in the Instrument Air System occurs causing the following alarms:
o
EK-1101, "CONTAINMENT INSTR AIR LO PRESS"
o
EK-1102, "INSTRUMENT AIR LO PRESS"
o
EK-1105, "AIR COMPRESSORS STANDBY COMP RUNNING"

Instrument Air pressure indicates 82 psig and stable on PIA-1210, Instrument Air Pressure gauge on panel C-13
Which one of the following additional alarms would be expected based on these indications? Assume no operator actions have been taken and Instrument Air pressure remains stable.
a. EK-3322, "CLG TWR E-30A FIRE."
b. EK-1134, "MOTOR DRIVEN FIRE PUMP RUNNING."
c. EK-1171, "COMPONENT CLG HX E-54B LO TEMP."
d. EK-1165, "NON CRITICAL SERV WATER LO PRESS."

b. EK-1134, "MOTOR DRIVEN FIRE PUMP RUNNING."

a. Plausible because the student could think that the deluge valves fail open on lowering Air pressure but these are actually nitrogen supplied.
b. CORRECT - Service Air is automatically isolated when Instrument Air pressure is 85 psig which causes Track Alley and VRS deluge to actuate which will start the Motor Driven Fire Pump.
c. Plausible because the Hi-cap valves fail open on loss of instrument air and could overcool the CCW, however, these valves don't fail open until air pressure is 50 psig.
d. Plausible because this valve is air to open, however, this valve will not close until Instrument Air pressure in nearly zero psig.

55

During a Loss of Coolant Accident event, the following parameters exist:

PZR pressure is 1000 psia

Containment pressure is 3.2 psig

Containment temperature is 166°F
A few minutes after Containment Spray actuates, the following parameters are noted:

PZR pressure is 900 psia

Containment pressure is 1.7 psig

Containment temperature is 135°F
Which one of the following describes the use of EOP Supplement 1, Pressure/Temperature Limit Curves, for this event?
a. Use degraded Containment curves throughout the event because Containment temperature was greater than 165°F.
b. Use non-degraded Containment curves throughout the event because Containment temperature and Containment pressure are within the limits.
c. Use degraded Containment curves throughout the event because Containment pressure was greater than 3.0 psig.
d. Use non-degraded Containment curves prior to Containment Spray actuation and degraded Containment curves after Containment Spray actuation.

c. Use degraded Containment curves throughout the event because Containment pressure was greater than 3.0 psig.

a. Plausible if student misapplies the limit for considering Containment as degraded.
b. Plausible if student misapplies the limit for considering Containment as degraded.
c. CORRECT
d. Plausible if the student believes that the use of degraded curves is due to the fact that all the instruments are wet from the containment spray.

56

The Plant is at operating at full power. Which one of the following describes the impact on the Control Rod Drive System upon receipt of annunciator EK-0918, “PIP TROUBLE"?
a. A Rod Withdrawal Prohibit will be generated for the Shutdown and Regulating Control Rods.
b. Control Rod position indication will be unavailable from the Palisades Plant Computer.
c. A Rod Withdrawal Prohibit will be generated for the Regulating Control Rods only.
d. The Regulating Control Rods will have to be manually sequenced if rod motion is necessary.

d. The Regulating Control Rods will have to be manually sequenced if rod motion is necessary.

a. Plausible because PIP performs rod sequencing, however withdrawal is allowed, they just need to be manually sequenced.
b. Plausible because the PPC displays rod positions, however, SPI (reed switch) indication will be available from the PPC.
c. Plausible because PIP performs rod sequencing, however withdrawal is allowed, they just need to be manually sequenced.
d. CORRECT

57

The Low Temperature Overpressure Protection System (LTOP) is designed to relieve pressure in the Primary Coolant System to protect the (1) and shall be in service prior to PCS temperature reaching (2) during a normal Plant cooldown.
a. (1) Reactor Vessel
(2) 480°F
b. (1) Pressurizer Vessel
(2) 480°F
c. (1) Reactor Vessel
(2) 430°F
d. (1) Pressurizer Vessel
(2) 430°F

c. (1) Reactor Vessel
(2) 430°F

a. Student misapplies the temperature requirement band (430-480).
b. Student misapplies the temperature requirement band (430-480) and believes that LTOP protects the PZR.
c. CORRECT - GOP-9 states that LTOP is placed in service between 430 and 480 degrees.
d. Student believes that LTOP protects the PZR.

58

Given the following conditions:
• A rapid power reduction occurred several minutes ago in accordance with ONP-26, "Rapid Power Reduction," and the Plant has stabilized at 80% power

ONP-26 has been exited

The Control Room team is attempting to restore control rods to meet Regulating Rod Group insertion limits

An electrical malfunction results in Group 4 regulating rods becoming stuck at 80 inches
In order for Group 4 Control Rods to be less than or equal to the Pre Power Dependent Insertion Limit (PPDIL), power must be reduced to a maximum of ...
a. 33%.
b. 68%.
c. 70%.
d. 74%.

b. 68%

a. This corresponds to 80" on Group 3 rods.
b. CORRECT
c. This is the PPC PDIL value for Group 4.
d. This is the Tech Spec PDIL value for Group 4.

59

Given the following:
• The Plant is in MODE 6
• Refueling Operations are in progress in the Containment Building
• A Containment High Radiation Signal is received due to a high alarm from Containment Refueling Monitors, RIA-2316 and RIA-2317
W
hich one of the following occurs within the Ventilation System as a result of this condition?
a. V-1B, V-2B, V-3B, and V-4B, Containment Air Cooler Fans, receive a trip signal.
b. V-46, Containment Air Room Purge Fan, receives a trip signal.
c. VF-66, Refueling Area Charcoal Filter, aligns for operation.
d. V-8A/B, Refueling Area Exhaust Fans, receive a trip signal.

b. V-46, Containment Air Room Purge Fan, receives a trip signal

a. Plausible if the student confuses actions for a Containment High Pressure signal with CHR.
b. CORRECT
c. Plausible because the containment equipment hatch is open in MODE 6 but this is not an automatic action.
d. Plausible because the containment equipment hatch is open in MODE 6 but this is not an automatic action.

60

Given the following:
• A manual Plant trip from full power has occurred in response to a stuck open Steam Generator Code Safety Relief Valve on 'A' Steam Generator
• EOP-1.0, "Standard Post Trip Actions," have been completed
• The Control Room crew is transitioning to EOP-6.0, "Excess Steam Demand Event"
W
hich one of the following describes the strategy for controlling Auxiliary Feedwater flow to the 'A' Steam Generator?
AFW flow to 'A' Steam Generator will be ...
a. 165 gpm.
b. 165 gpm until level is > 60%.
c. 165 gpm until level is > 5%.
d 0 gpm.

d 0 gpm.

a. This is the normal programmed flow when AFAS initiates.
b. This is the normal programmed flow and the long term strategy for an unfaulted S/G in EOP-1.0.
c. This is the normal programmed flow and the initial short term level that is required in EOP-1.0.
d. CORRECT - EOP-1.0 immediate action 8 requires all feedwater flow to a faulted S/G be secured.

61

Given the following:
• The Plant was manually tripped in response to a small steam line break from the 'B' Steam Generator
• A Plant cooldown has been commenced using HIC-0780A, Steam Dump Controller, in manual via the Atmospheric Steam Dump Valves (ADVs)
• The Main Steam Isolation Valves are closed

386AST, Turbine Trip Relay, has NOT been reset

TAVE is currently 532°F

An Operator notices that CV-0511, Turbine Bypass Valve (TBV), is indicating partially open
F
or the above condition, which one of the following is true for CV-0511?
CV-0511 should be ...
a. closed because TAVE is

d. open because HIC-0780A is sending a signal to the TBV circuit.

a. Plausible because this is the TAVE at which the TBV should start to open in AUTO.
b. Plausible because this relay actuation is what causes the TBV to quick open, however, TAVE is

62

Given the following:
• Plant power is being held at 10% with the Main Turbine rotating at 1800 RPM
• Preparations are being made to synchronize the Turbine Generator with the grid
• Then, Preferred AC Bus Y30 de-energizes due to a fault
T
he consequence of this failure will be ...
a. Loss of Load Trip on 1 of 4 RPS channels and the Reactor does NOT trip.
b. Loss of Load Trip on 2 of 4 RPS channels and the Reactor trips.
c. High SUR Trip on 1 of 4 RPS channels and the Reactor does NOT trip.
d. High SUR Trip on 2 of 4 RPS channels and the Reactor trips.

d. High SUR Trip on 2 of 4 RPS channels and the Reactor trips.

a. Plausible if the student believes WR power indication will rise causing the loss of load trip bypass on one channel to be removed. This is incorrect because the bypass is removed by the Power Range NIs.
b. Plausible if the student believes WR power indication will rise causing the loss of load trip bypass on two channels to be removed meeting the 2/4 trip logic. This is incorrect because the bypass is removed by the Power Range NIs.
c. Plausible if the student believes that each RPS channel is supplied by a separate WR NI.
d. CORRECT - There are only 2 Wide Range Instruments that feed the High SUR trip, if one fails the 2/4 trip logic is met.

63

Given the following:
• A batch release of T-91, Utility Water Storage Tank, is in progress
• The release flow path is via CV-1051, One-Inch (1") Treated Waste Monitor P-58A/B Bypass
T
he following then occurs:
• EK-1365, "PROCESS LIQUID MONITORING HI RADIATION," annunciates
• RIA-1049, Liquid Radwaste Discharge Process Radiation Monitor, is verified to be alarming
• CV-1051 indicates open on C-40, Radwaste Panel
W
hich one of the following describes the consequence of this condition and the correct action to isolate the batch?
a. Off-Site Dose Calculation Manual (ODCM) limits may be exceeded.
Direct an Auxiliary Operator to close MV-CRW172, RIA-1049 Discharge to Canal.
b. National Pollutant Discharge Elimination System (NPDES) limits may be exceeded.
Direct an Auxiliary Operator to close MV-CRW172, RIA-1049 Discharge to Canal.
c. Off-Site Dose Calculation Manual (ODCM) limits may be exceeded.
Close MO-5311 and MO-5312, Dilution Water to Mixing Basin Isolations.
d. National Pollutant Discharge Elimination System (NPDES) limits may be exceeded.
Close MO-5311 and MO-5312, Dilution Water to Mixing Basin Isolations.

a. Off-Site Dose Calculation Manual (ODCM) limits may be exceeded.
Direct an Auxiliary Operator to close MV-CRW172, RIA-1049 Discharge to Canal.

a. CORRECT
b. Plausible if the student knows the correct action but believes that the limits for radioactivity discharge are contained in the NPDES permit. Student should understand the basis for the alarm setpoints on liquid monitors.
c. Plausible if the student knows where the requirements for the basis for the alarm setpoints are contained but believes that isolating the dilution water to the mixing basin will isolate the batch - student believes that the radwaste discharge taps in upstream of these valves instead of downstream.
d. Plausible if the student believes that the limits for radioactivity discharge are contained in the NPDES permit and believes that isolating the dilution water to the mixing basin will isolate the batch - student believes that the radwaste discharge taps in upstream of these valves instead of downstream.

64

Given the following with the Plant operating at full power:
• P-7A and P-7B, Service Water Pumps, are in service
• Maintenance on P-7C, Service Water Pump, has just been completed
• 152-205, P-7C Breaker, has been racked in with control power fuses installed

P-7C is NOT in Standby

A Plant trip occurs due to a loss of all off site power

Both Diesel Generators start and sequence 2400VAC Buses 1C and 1D per design
W
hich one of the following describes the status of the Service Water Pumps?
a. P-7A and P-7B in service. P-7C will start if header pressure lowers to

d. ALL three Service Water Pumps will be in service

a. Plausible because the standby pump will start if discharge pressure of either 2 in service pumps lowers to

65

Given the following:
• The Plant has experienced a loss of all feedwater event
• EOP-7.0, "Loss of All Feedwater Recovery," is the in use procedure
• P-8A, Auxiliary Feedwater Pump, is available

Main Feedwater is NOT available

T-2, Condensate Storage Tank, is NOT available

Preparations are being made to place P-8A in service using EOP Supplement 31, "Supply AFW Pumps From Alternate Sources"
W
hich one of the following will be (1) the source of water to P-8A and (2) the approximate level in which flow to the Steam Generators will be initiated?
a. (1) Fire Protection System.
(2) -125%.
b. (1) Service Water System.
(2) -125%.
c. (1) Fire Protection System.
(2) -75%.
d. (1) Service Water System.
(2) -75%.

c. (1) Fire Protection System.
(2) -75%

a. Correct source of water but incorrect level, this is the level at which a S/G is considered dry.
b. Incorrect source of water, this is a backup to P-8C. Incorrect level, this is the level at which a S/G is considered dry.
c. CORRECT
d. Correct level, incorrect source of water, this is a backup to P-8C.

66

You are monitoring Plant status using the Plant Process Computer (PPC) when you notice a parameter value is displayed in orange (see example below).
199 in ORANGE
This color signifies that the parameter value ...
a. has exceeded its “Alarm” setpoint.
b. has exceeded its “Warning” setpoint.
c. is bad data or out of range.
d. was manually entered.

c. is bad data or out of range.

a. Plausible distractor
b. Plausible distractor
c. CORRECT
d. Plausible distractor

67

Given the following conditions:
• The Plant is at full power
• T-2, Condensate Storage Tank, temperature is 80°F
• T-81, Primary System Makeup Storage Tank, temperature is 100°F

Auxiliary Feedwater flow will be initiated to BOTH Steam Generators at the programmed value for an Auxiliary Feedwater Actuation (AFAS)
H
eat Balance power must be lowered to a maximum of (1) prior to initiating Auxiliary Feedwater flow because (2) .
a. (1) 99.3%
(2) AFW flow is not a parameter used to calculate heat balance power
b. (1) 99.3%
(2) AFW temperature input is out of range for the heat balance power calculation
c. (1) 99.2%
(2) AFW flow is not a parameter used to calculate heat balance power
d. (1) 99.2%
(2) AFW temperature input is out of range for the heat balance power calculation

c. (1) 99.2%
(2) AFW flow is not a parameter used to calculate heat balance power

a. Correct reason, however, this is the power if T-81 temperature is used.
b. Wrong reason and this is the power if T-81 temperature is used.
c. CORRECT
d. Correct power level but wrong reason.

68

During refueling operations, which one of the following Spent Fuel Pool (SFP) water levels is the LOWEST allowable level for performing irradiated fuel handling activities in the SFP?
a. 8" below skimmers.
b. 10" below skimmers.
c. 12" below skimmers.
d. 14" below skimmers.

c. 12" below skimmers.

a. Plausible level
b. Plausible level
c. CORRECT
d. Plausible level

69

Which one of the following activities does NOT require an Infrequently Performed Test or Evolution Brief in accordance with EN-OP-116, "Infrequently Performed Tests or Evolutions"?
a. Securing Dilution Water Pump, P-40A, at 100% power.
b. Overspeed Trip test of Emergency Diesel Generator 1-1.
c. Performance of Containment Integrated Leak Rate Test.
d. Cutting of Incore Instruments in the Reactor Cavity.

a. Securing Dilution Water Pump, P-40A, at 100% power

a. CORRECT
b. Plausible because the student thinks EDG testing is performed frequently.
c. Plausible because the student thinks that the test relies heavily on engineering.
d. Plausible because the student thinks that this is usually performed by a vendor (Westinghouse).

70

Which one of the following correctly describes how inoperable Control Room alarms are tracked?
The inoperable alarm shall be documented ...
a. on the SRO Turnover Sheet ONLY.
b. via an "Alarm Tab" for identification ONLY.
c. on the SRO Turnover Sheet AND the NCO Turnover Sheet.
d. in the Operations Log AND on the NCO Turnover Sheet.

d. in the Operations Log AND on the NCO Turnover Sheet.

a. Plausible but not tracked on the SRO T/O sheet.
b. Alarm Tabs are used to identify expected alarms.
c. Plausible but not tracked on the SRO T/O sheet.
d. CORRECT

71

• An Operator is preparing to transfer 4160VAC Buses from Station Power to Startup Power
• Breaker 252-201, Bus 1B Station Power Incoming Breaker, indicating lights on panel C-04 are as follows (see picture below):
o RED light is lit
o
GREEN light is NOT lit
o
WHITE light is NOT lit

Which one of the following describes the response when 252-202, Bus 1B Startup Power Incoming Breaker, control switch is positioned to CLOSE? (Assume all bulbs and fuses are good)
a. 252-201 will NOT trip to transfer bus. 252-201 will need to be tripped locally.
b. 252-201 will trip to transfer bus but 252-202 will NOT close; Bus 1B will de-energize.
c. 252-201 will trip to transfer bus but will NOT be able to be closed remotely from C-04.
d. 252-201 will trip to transfer bus and will be able to be closed remotely from C-04.

c. 252-201 will trip to transfer bus but will NOT be able to be closed remotely from C-04

a. Plausible if the student believes that Charging power (white light) is required to trip breaker.
b. Plausible if the student believes that breaker will trip but that the white light powers circuitry for the logic that allows 252-202 to close.
c. CORRECT
d. Plausible if the student believes that there will be one more breaker cycle left, which may be true, however, in this case it is not.

72

A Waste Gas Decay Tank batch release is planned, but the Waste Gas Monitor, RIA-1113, is INOPERABLE.
For this condition, all of the following are actions that are required prior to initiating the release EXCEPT:
a. Obtain an additional sample of the tank contents.
b. Perform an independent verification of the discharge lineup.
c. Perform independent verification of the release rate calculations.
d. Setup local portable monitoring equipment at release point.

d. Setup local portable monitoring equipment at release point.

a. A valid alternative/compensatory action.
b. A valid alternative action.
c. A valid compensatory action.
d. CORRECT

73

The Containment Gas Radiation Monitor, RIA-1817, is normally lined up to sample from the:
a. Containment Dome.
b. Containment Air Room.
c. Containment Air Cooler Fan discharge.
d. Control Rod Drive Motor Cooling Fan discharge.

c. Containment Air Cooler Fan discharge.

a. Plausible location.
b. Plausible location.
c. CORRECT
d. Plausible location.

74

Given the following:
• A Loss of Coolant Accident (LOCA) has occurred with the Plant in MODE 1
• Containment Isolation has actuated due to high Containment Pressure
• EOP-1.0, "Standard Post Trip Actions," are in progress
W
hich one of the following Pressurizer Level conditions will satisfy the Inventory Control (IC) safety function?
a. 60% and rising.
b. 26% and rising.
c. 40% and lowering.
d. 88% and lowering.

b. 26% and rising

75

Given the following with the Plant at 28% power:
• EK-0606A, "HIGH POWER RATE CHANNEL PRE-TRIP/ASI," annunciates
• The white High Power Rate pre-trip light for RPS Channel 'A' is lit (see picture below)
Which one of the following describes the cause of this condition and the action the operator will perform to verify the cause per the associated Alarm Response Procedure?
a. Axial Shape Index (ASI) is approaching a limit. Check the "Power Density" status on each Thermal Margin Monitor.
b. Axial Shape Index (ASI) is approaching a limit. Check the "Alarms" screen on each Thermal Margin Monitor.
c. Startup Rate has reached the pre-trip setpoint. Verify EK-0917, "ROD WITHDRAWAL PROHIBIT," is annunciating on panel C-12.
d. Startup Rate has reached the pre-trip setpoint. Verify SUR is less than 2.6 DPM on Wide Range Nuclear Instrument indication on Panel C-12.

a. Axial Shape Index (ASI) is approaching a limit. Check the "Power Density" status on each Thermal Margin Monitor.

a. CORRECT
b. Plausible but the ARP specifies to check power density status.
c. Plausible as this is a shared alarm but high SUR trip is disabled >15% power.
d. Plausible as this is a shared alarm but high SUR trip is disabled >15% power.