2008 Reactor Operator Flashcards Preview

NRC Initial exams > 2008 Reactor Operator > Flashcards

Flashcards in 2008 Reactor Operator Deck (74):
1

Given the following conditions:
*A reactor trip from full power occurs
* Auxiliary Feedwater Actuation, AFAS, actuates as designed
* P-8A, AFW Pump, is in service
* Plant recovery is in progress in accordance with EOP-2.0, "Reactor Trip Recovery"
* AFW is aligned for normal operation in accordance with SOP-12 "Feedwater System"
* AFAS has NOT been reset
What will be the plant response if Auxiliary Feedwater Pump, P-8A, trips?

a. AFW Pump, P-8C, will immediately start.
b. AFW Pump, P-8B, will immediately start.
c. AFW Pump, P-8C, will start in approximately 30 seconds.
d. AFW Pump, P-8B, will start in approximately 30 seconds.

c. AFW Pump, P-8C, will start in approximately 30 seconds.

a. Plausible if the student believes that P-8C does not have a time delay from when low flow is sensed.
b. Plausible if the student believes that P-8B is next to start in the logic for AFW with no time delay.
c. CORRECT
d. Plausible if the student believes that P-8B is next to start in the logic for AFW.

2

A manual reactor trip has occurred due to a PZR vapor space LOCA event. The Reactor Operator
notes the following during the performance of EOP-1.0, "Standard Post Trip Actions":
* Pressurizer Pressure is 1250 psia and lowering slowly
*PCS Temperature is 524°F
The Reactor Operator trips P-50A and P-50D, Primary Coolant Pumps. Which one of the following
describes the reason for this action?

a. Prevents pump operation when PCS pressure is below the 25°F sub-cooling curve of EOP
Supplement 1.
b. Prevents pump operation when PCS pressure is below the minimum pressure limit of EOP
Supplement 1.
c. Minimizes PCS inventory loss while maintaining diametrically opposed PCPs in service for core
heat removal.
d. Minimizes PCS inventory loss while still maintaining PCS pressure control via Pressurizer spray
valves.

d. Minimizes PCS inventory loss while still maintaining PCS pressure control via Pressurizer spray
valves.

a. Plausible if the student does not fully understand the reason for trip 2-leave 2 strategy
b. Plausible if the student misinterprets EOP Supplement 1 and believes PCS pressure is

3

Following a manual reactor trip due to a small break LOCA, the following conditions are noted
during EOP-1.0, "Standard Post Trip Actions."
* Pressurizer Level Controller, LIC-0101B is in service
* Pressurizer level has slowly lowered to 34% on LIC-0101B
* Pressurizer Pressure is 1750 psia
* Charging and Letdown systems are aligned for normal operation in accordance with
SOP-2A, "Chemical and Volume Control System"
Which one of the following lists the response of the Chemical Volume Control System (CVCS)
components due to this event?
P-55B P-55C Orifice Stop
Status Status Valves Open
a. OFF OFF 1
b. ON ON 1
c. ON ON 0
d. OFF OFF 0

c. ON ON 0

a. Plausible if the student believes that B and C charging pumps are started by SIS signal only and does not correctly
apply PZR level low trip to CV-2003 (orifice stop) closing
b. Plausible if the student correct applies PLCS operation to B and C charging pumps but does not correctly apply PZR
level low trip to CV-2003 (orifice stop) closing
c. CORRECT
d. Plausible if the student believes that B and C charging pumps are started by SIS signal only and student correctly
applies PZR level low trip to CV-2003 (orifice stop) closing

4

With the plant operating at 35% power, a loss of Component Cooling Water event occurs. Alarm
EK-0908, "PRI COOLANT PUMP P-50B HI TEMP OVERLOAD" is annunciating. Which one of the
following conditions requires a manual reactor trip?
a. Thrust Bearing temperature indicates 191°F.
b. Controlled Bleedoff temperature indicates 178°F.
c. Pump Motor Stator Temperature indicates 135°C.
d. Lower Seal temperature indicates 177°F.

a. Thrust Bearing temperature indicates 191°F.

a. CORRECT
b. Plausible if the student believes that PCP trip criteria require a trip for this condition.
c. Plausible because the alarm setpoint is 140°F but this alarm does not require the pump be tripped.
d. Plausible if the student believes that PCP trip criteria require a trip for this condition

5

The Plant was operating at 50% power when ALL charging flow was lost. The following conditions
exist:
* PZR level was at program level when letdown was immediately isolated
*PZR level is lowering at a rate of 1% every fifteen (15) minutes (after letdown was isolated)
Assuming charging and letdown systems are NOT restored, approximately how long can PZR
heater operation be maintained?
a. 120 minutes
b. 205 minutes
c. 315 minutes
d. 360 minutes

b. 205 minutes

a. Plausible if low level cutout of 42% is used, this number is the minimum program level
b. CORRECT - PZR level at 50% power is ~49.5%. PZR Heater cutout is 36%, leaving 13.5% level until heaters
are off. PZR level lowering 1% every 15 minutes - 13.5 X 15 =203 minutes
c. Plausible if program level of 57% is used which is program for 100% power
d. Plausible and symmetrical

6

Given the following plant conditions:
* PCS cooldown is in progress with a 20°F/Hour cooldown rate
*Shutdown Cooling is in service
*A Loss of ALL Instrument Air occurs
Which one of the following describes the Shutdown Cooling System response to the loss of
Instrument Air?
Shutdown Cooling...
a. flow is lost.
b. heat removal is lost.
c. flow is degraded.
d. heat removal is maximum.

b. heat removal is lost.

a. Plausible if the student believes that the SDC HX inlet/outlet and bypass valves fail closed
b. CORRECT
c. Plausible if the student believes that the SDC HX bypass valve does not fail open on loss of air
d. Plausible if the student believes that the HX inlet fails open and the bypass fails closed

7

CV-0945 and CV-0946, CCW Heat Exchanger Inlet Valves, receive an open signal during
emergency conditions. What condition generates the open signal and what is the reason for this
signal?
a. Safety Injection Signal (SIS). Ensures 100% cooling is available post accident.
b. Recirculation Actuation Signal (RAS). Ensures 100% cooling is available post accident.
c. Safety Injection Signal (SIS). Maintains minimum flow for CCW pumps.
d. Recirculation Actuation Signal (RAS). Maintains minimum flow for CCW pumps.

b. Recirculation Actuation Signal (RAS). Ensures 100% cooling is available post accident.

a. Plausible if the student believes that these valves isolate on a SIS signal
b. CORRECT
c. Plausible if the student believes that these valves isolate on a SIS signal
d. Plausible if the student believes that both valves must be open to provide minimum flow requirements in the case
that all 3 CCW pumps start

8

Given the following:
* Annunciator EK-0744 "PRESSURIZER SAFETY VALVE RV-1039 DISCH HI TEMP" is
alarming
*ONP-23.1, "Primary Coolant Leak", is entered
* The CRS directs a manual reactor trip due to PCS leak rate trip criteria being exceeded
* Following the actions of EOP-1.0, "Standard Post Trip Actions," EOP-4.0, "Loss of Coolant
Accident Recovery," is entered
*PCS pressure is 1895 psia and lowering slowly
The Control Room Supervisor directs the Reactor Operator to lower PCS pressure to a band of
1690 - 1790 psia in accordance with EOP-4.0. Which one of the following describes the reason for
this action?
This pressure band is....
a. sufficiently above the Safety Injection Actuation setpoint yet is well below the Pressurizer Code
Safety Valve setpoint.
b. high enough to maintain at least 50°F PCS subcooling yet is well below the Pressurizer Code
Safety Valve setpoint.
c. high enough to maintain at least 50°F PCS subcooling yet is low enough to maximize the
amount of time until Quench Tank, T-73, rupture disc actuates.
d. sufficiently above the Safety Injection Actuation setpoint yet is low enough to maximize the
amount of time until Quench Tank, T-73, rupture disc actuates.

a. sufficiently above the Safety Injection Actuation setpoint yet is well below the Pressurizer Code
Safety Valve setpoint.

a. CORRECT
b. Plausible as subcooling is a concern during a PZR Safety Valve leak
c. Plausible as subcooling and quench tank rupture disc actuating are concerns during a PZR Safety Valve leak
d. Plausible as quench tank rupture disc actuating is a concern during a PZR Safety Valve leak

9

With the plant at 100% 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 Turbine NCO 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/42-2RPS and EK-0972, Reactor Trip Alarm Red Tile Annunciator?
a. 42-1RPS and 42-2RPS are CLOSED.
EK-0972 is OFF.
b. 42-1RPS and 42-2RPS are CLOSED.
EK-0972 is LIT.
c. 42-1RPS and 42-2RPS are TRIPPED.
EK-0972 is OFF.
d. 42-1RPS and 42-2RPS are TRIPPED.
EK-0972 is LIT.

d. 42-1RPS and 42-2RPS are TRIPPED.
EK-0972 is LIT.

a. The student misapplies the method of trip from C-06 and believes that the Reactor trip alarm may not annunciate if
C-06 method is used.
b. The student correctly applies that the Reactor trip alarm is 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 Reactor trip alarm may not
annunciate if C-06 method is used.
d. CORRECT

10

During implementation of EOP-5.0, "Steam Generator Tube Rupture Recovery," which one of the
following CANNOT be used to determine the most affected Steam Generator?
a. Steam Generator level change when not feeding.
b. Steam Generator sample analysis results.
c. Feed Regulating Valves position (prior to trip).
d. Steam Generator Blowdown Valves position.

d. Steam Generator Blowdown Valves position.

a. Plausible - listed in EOP-5.0, step 21
b. Plausible - listed in EOP-5.0, step 21
c. Plausible - feed flow mismatch between S/Gs listed in EOP-5.0, step 21
d. CORRECT - If S/G blowdown radiation monitor alarms, all blowdown valves isolate

11

Given the following:
*The plant is in MODE 1 at full power
* A steam line break occurs OUTSIDE the Containment Building UPSTREAM of CV-0510,
"A" Steam Generator Main Steam Isolation Valve (MSIV)
*"A" S/G Pressure indicates 475 psia
*"B" S/G Pressure indicates 850 psia
Which one of the following describes the expected response of the 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.

b. BOTH "A" and "B" S/G MSIVs close.
ONLY "A" S/G FRV closes.

a. Plausible if the student believes that all valves close similar to a CHP event.
b. CORRECT - S/G pressure is a diagnostic indication in determining entry into EOP-6.0, ESDE.
c. Plausible if the student misapplies the concept that only the "A" FRV closes.
d. Plausible if the student believes that the goal of a MSIS on low S/G pressure is to isolate only the affected S/G.

12

Given the following:
* Plant power is 76%
* 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?" Consider each choice separately.
a. EK-0160, "FDWTR PUMPS LO SUCTION," alarms with MFP suction pressure indicating 280
psig.
b. EK-0143, "FW PUMP P1A TURBINE K7A TRIP," alarms with associated Trip & Throttle Valves
indicating closed.
c. EK-0960, "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 58% and
lowering.

d. EK-0961, "STEAM GEN E-50A HI LEVEL," alarms with 'A' S/G level indicating 58% and
lowering.

a. Plausible but ONP-3 does not direct tripping reactor unless both MFPs trip as a result.
b. Plausible because if power were > 80%, ONP-3 directs the reactor to be tripped.
c. Plausible however, ONP-3 directs restoring level by manual control of FRVs and MFPs.
d. CORRECT - This indicates a failure of the high level override circuitry.

13

Given the following plant conditions:
* A reactor trip has occurred
*4160 Volt Buses 1A and 1B are de-energized
* EOP-1.0, "Standard Post Trip Actions" has been completed
* EOP-8.0, "Loss of Offsite Power/Forced Circulation Recovery," has been implemented
Which one of the following would indicate that natural circulation has NOT been established?
a. Loop hot leg and cold leg temperatures are constant.
b. Average CET temperature indicates 20°F PCS subcooling.
c. Average CET temperature is 43° above loop cold leg temperatures.
d. Loop hot leg temperatures are 10°F less than average CET temperature.

b. Average CET temperature indicates 20°F PCS subcooling.

a. Hot leg temps are constant and lowering
b. CORRECT - If CET indicates less than 25° subcooled
c. CET - TC is less than 50°F
d. Hot leg temps are within 15° of average CET temp

14

Give the following conditions:
* The plant is in MODE 2
*Charging Pump P-55A is operating
* Charging Pumps P-55B and P-55C are in AUTO
*Letdown is in service
* A loss of Instrument AC Bus Y01 occurs
ONP-24.5, "Loss of Instrument AC Bus Y01" directs the operators to isolate PCP bleedoff from the
Volume Control Tank (VCT) and realign it to the Primary System Drain Tank. Which one of the
following describes the reason for this action?
a. Minimizes the likelihood of gas intrusion in to the PCP seals.
b. Minimizes the amount of pressure reduction in the VCT.
c. Prevents a complete draining of the VCT.
d. Prevents overfilling of the VCT.

d. Prevents overfilling of the VCT

a. Plausible because the student misapplies the DIRECTION of inventory/energy exchange between VCT and PCP
bleedoff.
b. Plausible because the student misapplies the DIRECTION of inventory/energy exchange between VCT and PCP
bleedoff.
c. Plausible because the student misapplies the interface between VCT and PCP seal bleedoff.
d. CORRECT

15

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 125V DC Bus D-20 tie breaker, 72-20, tripping and
de-energizing DC Bus D-20L. Which one of the following actions will restore power to D-20L?
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 supplies D-20L, it actually supplies D-20R
b. Plausible if the student believes that charger #4 is powered from MCC-2, it is actually supplied by MCC-1
c. Plausible if the student believes that charger #2 supplies D-20L and it receives power from MCC-1
d. CORRECT

16

Given the following conditions:
* The plant is operating at 100% power
* Service Water Pump, P-7A, is tagged out for maintenance
*P-7B is in service with motor amps indicating 80 amps
*P-7C is in service with motor amps indicating 83 amps
A problem develops with the Service Water System. The NCO then notes the following indications:
* EK-1163, "CRITICAL SERV WATER HEADER "B" LO PRESSURE" is annunciating
* "B" Critical SW Header Pressure indicates 40 psig
*P-7B motor amps indicate 86 amps
* P-7C motor amps indicate 93 amps
NO operator actions have been taken. Which one of the following accounts for the above
conditions?
a. A break on the discharge pipe of P-7C, Service Water Pump.
b. A loss of instrument air to CV-0844, Critical SW Header B Isolation.
c. A loss of instrument air to CV-1318, P-7A SW Pump Cross Tie.
d. A plugged discharge basket strainer for P-7B and P-7C.

a. A break on the discharge pipe of P-7C, Service Water Pump.

a. CORRECT
b. Plausible if the student believes that this alarm switch is located downstream of CV-0844
c. Plausible if the student believes that if this valve fails closed, Critical Header 'B' pressure will be low
d. Plausible if the student believes that motor amps will rise for a plugged discharge strainer

17

A loss of instrument air has resulted in a plant trip from 100% power. All equipment operates as
designed under loss of air conditions. The correct method for maintaining the PCS heat removal
function from the Control Room following the reactor trip is to use the:
a. Atmospheric Dump Valves to control PCS temperature and AFW Pump, P-8C, for Aux
Feedwater to the S/Gs.
b. Turbine Bypass Valve to control PCS temperature and AFW Pump, P-8A, for Aux Feedwater to
the S/Gs.
c. Atmospheric Dump Valves to control PCS temperature and AFW Pump, P-8A, for Aux
Feedwater to the S/Gs.
d. Turbine Bypass Valve to control PCS temperature and AFW Pump, P-8C, for Aux Feedwater to
the S/Gs.

c. Atmospheric Dump Valves to control PCS temperature and AFW Pump, P-8A, for Aux
Feedwater to the S/Gs

a. Plausible however, P-8C control valves fail open on loss of instrument air
b. Plausible, however, the TBV fails closed on loss of instrument air
c. CORRECT - ADVs and P-8A control valves have nitrogen backup
d. Plausible, however, P -8C control valves fail open and TBV fails closed on loss of instrument air

18

Given the following initial conditions:
* Plant power is 100%
* Main Generator Load is 823 MW
*Main Generator Reactive load is zero (0) MVARs
A voltage disturbance occurs on the grid which causes Main Generator Reactive load to change to
300 MVARs IN. This is a concern because the Main Generator is now (1) which
can cause (2) .
a. (1) UNDER-excited
(2) High Stator end iron temperatures
b. (1) OVER-excited
(2) High Stator end iron temperatures
c. (1) UNDER-excited
(2) Rotor pole slippage
d. (1) OVER-excited
(2) Rotor pole slippage

a. (1) UNDER-excited
(2) High Stator end iron temperatures

a. CORRECT - Under-excitation causes circulating currents (eddy currents) in the laminations of the Generator
Stator frame which lead to high end iron temperatures.
b. MVARs IN is under excited, student misapplies this concept.
c. Student believes that if the rotor field is weak, pole slippage can occur, this applies only in motors.
d. Student misapplies concepts in both B and C above.

19

Given the following conditions:
* The plant is operating at 100% power
* Pressurizer Level Controller, LIC-0101B, is in service in the CASCADE mode
* Pressurizer Level Transmitter, LT-0101B, diaphragm ruptures, equalizing pressure across
the diaphragm
Indicated Pressurizer level will (1) and the Pressurizer level control system will respond
by (2) .

a. (1) rise
(2) opening CV-2004 and 2005, Letdown Stop Valves
b. (1) lower
(2) raising speed of P-55A, Charging pump
c. (1) rise
(2) securing P-55A, Charging pump
d. (1) lower
(2) closing CV-2003, Letdown Stop Valve

a. (1) rise
(2) opening CV-2004 and 2005, Letdown Stop Valves

a. CORRECT
b. Plausible if the student believes that the LT is a dry reference leg
c. Plausible but P-55A is not secured by the PLCS, only driven to minimum speed
d. Plausible if the student believes that the LT is a dry reference leg

20

The following conditions exist:
*The plant is in MODE 6
* The control room crew notices Reactor Cavity water level lowering on the refueling camera
* ONP-23.3, "Loss of Refueling Water Accident," is entered
ONP-23.3 requires the Containment to be evacuated if an alarm is received on either Fuel Handling
Area Monitor, RIA-2316/2317 (set @ 80mr/hour). Which one of the following annunciators would
indicate that radiation level exceeded 80mr/hr at the 649' level of Containment?
a. EK-1101, "CONTAINMENT INSTR AIR LO PRESS"
b. EK-0201, "CONT GAMMA RIA-2321 HIGH"
c. EK-1363, "CONTAINMENT HI RADIATION"
d. EK-1126, "CIS INITIATED"

d. EK-1126, "CIS INITIATED"

a. Plausible if the student thinks that a containment hi rad signal closes CV-1211 on a hi rad condition.
b. Plausible but the containment high range monitors do not feed this alarm.
c. Plausible but this alarm is actuated by rad monitors @ 10R/hour.
d. CORRECT

21

Which one of the following lists is inclusive of all Radiation Monitors that will all indicate an upward
trend during a Steam Generator Tube Leak event?
a. RIA-0631, Condenser Off-Gas Monitor, ONLY.
b. RIA-0631, Condenser Off-Gas Monitor, AND Stack Gas Effluent Monitor (RGEM).
c. RIA-0631, Condenser Off-Gas Monitor, AND RIA-1809, Radwaste Ventilation Monitor.
d. RIA-0631, Condenser Off-Gas Monitor, AND RIA-1809, Radwaste Ventilation Monitor, AND
Stack Gas Effluent Monitors (RGEM).

b. RIA-0631, Condenser Off-Gas Monitor, AND Stack Gas Effluent Monitor (RGEM).

a. Plausible if the student does not know that the flow path for air ejector exhaust into the stack is sampled by the
RGEM
b. CORRECT
c. Plausible if the student believes that the flow path for air ejector exhaust taps in to the radwaste ventilation system
(V-14A/B) and student does not know that the flow path for air ejector exhaust into the stack is sampled by the RGEM
d. Plausible if the student believes that the flow path for air ejector exhaust taps in to the radwaste ventilation system
(V-14A/B)

22

The following conditions exist:
* The plant is in MODE 6
*Alarm EK-1366, "PLANT AREA MONITORING HI RADIATION," has alarmed due to
RIA-2313, SFP Criticality Monitor
The Alarm Response Procedure for EK-1366, ARP-8, directs you to place HS-1893, Fuel Handling
Fan and Damper Emergency Trip switch, to the EMERGENCY TRIP position. Which one of the
following describes the resultant equipment actuation and the reason for this action?
a. Trips V-69, Fuel Handling Area Supply Fan, AND V-70A/B, Fuel Handling Area Exhaust Fans.
Isolates a direct path for radioactive release to the environment.
b. Trips V-69, Fuel Handling Area Supply Fan, ONLY. Maintains a negative pressure in the SFP
while minimizing exhaust flow rate.
c. Trips V-69, Fuel Handling Area Supply Fan, AND V-70A/B, Fuel Handling Area Exhaust Fans.
Ensures NO air is supplied to or removed from the SFP area.
d. Trips V-69, Fuel Handling Area Supply Fan, ONLY. Ensures contamination is not spread
throughout the SFP Area by the supply fan.

a. Trips V-69, Fuel Handling Area Supply Fan, AND V-70A/B, Fuel Handling Area Exhaust Fans.
Isolates a direct path for radioactive release to the environment.

a. CORRECT
b. Plausible as this is what occurs if RIA-5712, process monitor, alarms
c. Plausible but the fuel handling exhaust fans, V-8A/B will still be in service.
d. Plausible as this is what occurs if RIA-5712, process monitor, alarms

23

A fire occurs in the Service Building Annex which causes a significant amount of smoke to be
released to the site. Which one of the following modes of Control Room HVAC System operation
will allow the LEAST amount of smoke into the Control Room?
a. Normal.
b. Emergency.
c. Purge.
d. Recirculation.

d. Recirculation.

a. Plausible because the intake is farthest away from the source of smoke
b. Plausible if the student believes that the emergency HEPA and charcoal filters will remove maximum amount of
smoke
c. Plausible as this is the mode of operation to clear smoke from the control room
d. CORRECT

24

Given the following:
*The Reactor was tripped and the control room evacuated due to a fire in the CRHVAC
system
*ONP-25.2, "Alternate Safe Shutdown Procedure," has been implemented
* EOP-1.0, "Standard Post Trip Actions," have been completed
When verifying PCS/Core heat removal safety function, which one of the following locations does
ONP-25.2 direct Steam Generator pressure be determined?
a. Turbine Front Standard.
b. Redundant Safety Injection Panel, C-33.
c. Auxiliary Hot Shutdown panel, C-150A.
d. Auxiliary Feedwater Pump Room.

c. Auxiliary Hot Shutdown panel, C-150A.

a. Plausible because the student may believe that S/G pressure can be obtained by using main steam header pressure
b. Plausible because the student may know that S/G pressure indication is available outside the control room, they may
not know which panel.
c. CORRECT
d. Plausible because the student may believe that S/G pressure can be obtained from AFW pump discharge pressure

25

In various places throughout the Emergency Operating Procedures, the term "degraded
containment" is used. What is the definition of this term and its significance to the operating crew?
a. Containment integrity has been lost. The operating crew must now consider this safety function
as jeopardized, and initiate immediate actions to restore containment integrity.
b. Containment radiation monitors are indicating > 10R/hour. The operating crew must ensure
CHR has initiated.
c. Containment pressure has exceeded 3.0 psig AND temperature has exceeded 175° F. The
operating crew may resume use of the non-degraded containment operating curves once BOTH
containment parameters have returned to normal.
d. Containment pressure has exceeded 3.0 psig OR temperature has exceeded 175° F. Use of
degraded containment operating curves must continue throughout the remainder of the EOP,
even if containment parameters have returned to normal.

d. Containment pressure has exceeded 3.0 psig OR temperature has exceeded 175° F. Use of
degraded containment operating curves must continue throughout the remainder of the EOP,
even if containment parameters have returned to normal

a. Plausible if the student believes that degraded containment refers to containment safety function as being
jeopardized.
b. Plausible if the student believes that degraded containment refers to radiation levels above CHR setpoint.
c. Plausible if the student believes that normal curves can be used when degraded containment conditions no longer
are present.
d. CORRECT

26

Given the following:
* A Main Steam Line Break has occurred UPSTREAM of the 'B' S/G MSIV
* All AFW flow to 'B' S/G is isolated
* Main Steam Line Isolation has automatically actuated
Which one of the following is the basis for establishing a steaming path from 'A' Steam Generator
prior to dryout of the 'B' Steam Generator?
To prevent ...
a. a void formation is the Reactor Vessel upper head region.
b. a rapid rise in core exit temperatures causing a loss of natural circulation.
c. a rapid rise in TC of the unaffected loop which would result in a loss of natural circulation.
d. a rapid pressurization of the PCS and subsequent pressurized thermal shock.

d. a rapid pressurization of the PCS and subsequent pressurized thermal shock

a. Void formation is an undesirable condition, but the concern does not apply here.
b. Valid distractor since loss of natural circulation is a concern, but does not apply for given conditions.
c. Valid distractor since loss of natural circulation is a concern, but does not apply for given conditions.
d. CORRECT

27

Given the following:
* The plant is at 100% power
* CCW Surge Tank level is 50% and stable
*Then, a leak occurs in the Primary Coolant Pump Seal Cooler
Due to this leak, the following alarm annunciates:
EK-1365, "PROCESS LIQ MONITORING HI RADIATION"
Which one of the following describes the expected indication for CCW Surge Tank Vent, CV-0915,
and CCW Surge Tank Makeup Valve, CV-0918?
a. CV-0915 lined up to the Vent Gas Collection Header (VGCH).
CV-0918 closed.
b. CV-0915 lined up to the Vent Gas Collection Header (VGCH).
CV-0918 open.
c. CV-0915 lined up to the Waste Gas Surge Tank.
CV-0918 closed.
d. CV-0915 lined up to the Waste Gas Surge Tank.
CV-0918 open.

a. CV-0915 lined up to the Vent Gas Collection Header (VGCH).
CV-0918 closed

a. CORRECT
b. Plausible if the student believes that the CCW Surge tank will lower causing the makeup valve to open
c. Plausible if the student believes that the surge tank vent can alternately be aligned to the waste gas surge tank
d. Plausible combination of b and c

28

Given the attached drawing of PR-0140B, Primary Coolant Pump, P-50D, Seal Pressure Recorder,
which one of the following seal stages have failed?

shows first line going down to 1100 # and second line going up to 1100#.

a. 1st stage only.
b. 2nd stage only.
c. 1st and 2nd stage only.
d. 2nd and 3rd stage only.

b. 2nd stage only.

a. Plausible if the student believes that when the 1st stage fails, the reading equalizes with 2nd stage
b. CORRECT
c. Plausible if the student believes that when 1st and 2nd stages fail, they equalize.
d. Plausible if the student believes that 1st stage reading is on left and 2nd and 3rd stages equalize.

29

Given the following plant conditions:
* The plant is at full power
* A severe thunderstorm is in progress
* An undetermined transient causes the following to occur:
-Plant trip
- An overcurrent fault condition on Startup Transformer 1-3
- Clearing of Switchyard 'R' Bus due to the fault
Assuming NO additional malfunctions and all other equipment functions as designed, which, if any,
Primary Coolant Pumps will be operating?
a. ALL Primary Coolant Pumps.
b. ONLY P-50A and P-50C.
c. ONLY P-50B and P-50D.
d. NO Primary Coolant Pumps.

d. NO Primary Coolant Pumps

a. Plausible if the student believes that A and B bus will fast transfer to S/U XFMR 1-1
b. Plausible if the student believes that S/U XFMR will stay energized, however 'R' bus will trip
c. Plausible if the student misapplies power supplies for PCPs and believes that S/U XFMR 1-1 will stay energized
d. CORRECT

30

Which statement describes the consequence of a high Volume Control Tank (VCT) pressure with
Primary Coolant Pump Controlled Bleed-Off (CBO) in service during a plant startup?
a. Excessive operator dose because the VCT must be manually vented locally to prevent PCP
seal damage.
b. Potential PCP seal failure due to reverse CBO flow if VCT pressure is greater than PCS
pressure.
c. Potential PCP seal failure due to excessive CBO flow if RV-2082, PCP CBO Relief Valve, lifts.
d. Auto isolation of Controlled Bleed-Off (CBO) due to closure of CV-2099, PCP CBO Cont.
Isolation, on high VCT pressure.

b. Potential PCP seal failure due to reverse CBO flow if VCT pressure is greater than PCS
pressure.

a. Plausible because the pressure regulator for gas to the VCT is located in a high dose area
b. CORRECT
c. Plausible because RV-2082 is located on the CBO line to the VCT but the piping is only 3/4"
d. Plausible if the student believes that the function of this valve is to isolate the VCT on high pressure

31

Given the following conditions:
* The plant is in MODE 5
* Shutdown Cooling System is in service
* PCS temperature is 175°F
*

d. (1) CV-3006, SDC Heat Exchanger Bypass, failed open.
(2) 40°F/Hour.

a. Incorrect reason, CV-3025 failing open will cause PCS temperature to lower
b. Possible reason, incorrect H/U rate limit
c. Possible reason, incorrect H/U rate limit
d. CORRECT

32

Given the following:
*A large break LOCA has occurred
* SIRWT Level is 20%
*PCS pressure is 275 psia
* Safety injection has actuated and all equipment operates as designed
LPSI Pumps, P-67A and P-67B, ____(1)____ currently injecting water into the PCS and will trip on
a low SIRWT Level (RAS) of 2% __________(2)__________.

a. (1) are
(2) to prevent clogging the Containment Sump screens
b. (1) are NOT
(2) to prevent clogging the Containment Sump screens
c. (1) are
(2) because there is insufficient net positive suction head (NPSH) during RAS
d. (1) are NOT
(2) because there is insufficient net positive suction head (NPSH) during RAS

d. (1) are NOT
(2) because there is insufficient net positive suction head (NPSH) during RAS

a. Student misapplies the minimum shutoff head of LPSI and the reason for trip.
b. Student applies the correct minimum shutoff head but misapplies the reason.
c. Student misapplies the minimum shutoff head and correctly applies the reason for the trip.
d. CORRECT - This question meets the intent of the K/A because the HPSI and LPSI pumps operate in parallel
during SIS actuation, but have different shutoff heads, 1250 psia for HPSI, 200 psia for LPSI. Due to this, the
LPSI pumps must be tripped on a RAS because of insufficient NPSH while the HPSI pumps have
containment spray discharge aligned to their suction to satisfy NPSH requirements.

33

With the plant in MODE 4 and Pressurizer steam bubble formation in progress in accordance with
SOP-1C, "Primary Coolant System - Heatup," which one of the following methods are relied upon
for PCS overpressure protection?
a. LTOP in the "SDC" mode.
b. LTOP in the "LTOP" mode.
c. Shutdown Cooling Relief Valve, RV-3164.
d. Pressurizer Code Safety Relief Valves.

b. LTOP in the "LTOP" mode

a. Plausible if the student believes that LTOP is still in the SDC mode in MODE 4 during PCS heatup.
b. CORRECT - Shutdown cooling is secured and safety valves are not required to be operable in MODE 4
c. Plausible if the student believes that SDC in still in operation.
d. Plausible if the student believes that LTOP is not in service in MODE 4.

34

With the plant in MODE 1 at 100% power the following occurs:
* EK-0733, QUENCH TANK HI-LO LEVEL, alarm annunciates
* EK-0732, QUENCH TANK HI PRESS, alarm annunciates
* Quench Tank level indicates 81% with pressure indicating 12 psig
* The control room crew has diagnosed that RV-1039, Pressurizer Relief Valve, is leaking
* ONP-23.1, "Primary Coolant Leak," has been entered
What action will the control room crew take to prevent RUD-0162, Quench Tank Rupture Disc, from
actuating?
a. Drain the Quench Tank to T-74, Primary System Drain Tank.
b. Drain the Quench Tank to T-80, Equipment Drain Tank.
c. Vent the Quench Tank to the Containment.
d. Vent the Quench Tank to the Vent Gas Collection Header (VGCH).

a. Drain the Quench Tank to T-74, Primary System Drain Tank.

a. CORRECT
b. Correct action (drain) but to wrong place.
c. The quench tank is vented to the Containment Vent Header, not the Containment Building.
d. Wrong vent path.

35

Given the following conditions with the plant in MODE 1 at full power:
* EK-1170 "COMPONENT CLG EX E-54A HI-LO TEMP," has annunciated
* CCW temperature is 89°F and rising slowly
*CCW Pump P-52A is in service
* CCW Pump discharge header pressure is 107 psig
* CV-0821 and CV-0822, CCW HX E-54A and E-54B Temp. Control Valves, are full open
* Lake Michigan water temperature is 81°F with all 3 SW pumps in service
Which one of the following describes the effect on the plant due to the above conditions and the
appropriate crew response?
a. CCW flow is inadequate for current plant conditions. Start P-52B or P-52C, CCW Pump, in
accordance with SOP-16, "Component Cooling Water System."
b. Service Water flow is inadequate for current plant conditions. Throttle open CV-0823 and 0826,
CCW HX SW High Cap. Outlet Valves, via their local air regulators.
c. Service Water flow is inadequate for current plant conditions. Make preparations to commence
a normal plant shutdown to MODE 3 in accordance with LCO 3.0.3.
d. CCW flow is inadequate for current plant conditions. Place CV-2023, Demineralizers T-51A/B &
T-52 Bypass Valve, to the BYPASS position.

b. Service Water flow is inadequate for current plant conditions. Throttle open CV-0823 and 0826,
CCW HX SW High Cap. Outlet Valves, via their local air regulators.

a. Plausible if the student believes that CCW flow is degraded, however with pump discharge pressure at 107 psig, this
is not true
b. CORRECT
c. Plausible if the student believes that lake temperature is above the limit. The max lake temperature is 85°F (83.5
with instrument inaccuracies)
d. Plausible if the student believes that bypassing the CVCS demineralizers is important for degraded CCW flow.

36

During a power escalation a transient occurs which causes Pressurizer pressure to change
to 2045 psia. Assuming all equipment is functioning properly, what are the expected
indications for the in service Pressurizer Pressure Controller?
a. Process Indication > Setpoint Indication.
Output signal > 66%.
b. Process Indication 66%.
c. Process Indication Setpoint Indication.
Output signal

c. Process Indication

37

The following plant conditions exist:
* The reactor has tripped from 100% power due to a Loss of all Offsite Power
* EDG 1-1 and 1-2 are running and loaded
*PCS pressure is 1975 psia and lowering
* PZR level is at program level
Which one of the following describes how power is restored to the PZR Heaters per ONP-18,
"Pressurizer Pressure Control Malfunctions" for the above conditions?
a. Restore Pressurizer Heaters by closing the Pressurizer Heater transformer feeder breakers
from both Buses 1D and 1E.
b. Select Pressurizer Heater Control switches for ALL heaters to OFF then reclose Pressurizer
Heater transformer feeder breaker from Bus 1D AND Bus 1E.
c. Select Pressurizer Heater Control switches for heaters powered from Bus 1D to OFF then
reclose Pressurizer Heater transformer feeder breaker from Bus 1D.
d. Select Pressurizer Heater Control switches for heaters powered from Bus 1E to OFF then
reclose Pressurizer Heater transformer feeder breaker from Bus 1E.

c. Select Pressurizer Heater Control switches for heaters powered from Bus 1D to OFF then
reclose Pressurizer Heater transformer feeder breaker from Bus 1D.

a. Plausible if the student believes that heater switches must be placed in OFF
b. Plausible if the student believes that power is available to bus 1E
c. CORRECT
d. Plausible if the student believes that power is available to bus 1E

38

With the plant operating in MODE 1 the following alarm annunciates:
EK-0543, "PREFERRED AC BUS NO. 1 TROUBLE"
Which one of the following describes the effect on the Reactor Protection System (RPS) reactor trip
logic?
Trip logic is now ____(1)____ and after Channel 'A' RPS trips are bypassed will be _____(2)_____.
a. (1) one out of three
(2) two out of three
b. (1) two out of three
(2) one out of three
c. (1) one out of three
(2) one out of three
d. (1) two out of three
(2) two out of three

a. (1) one out of three
(2) two out of three

a. CORRECT - A loss of Y30 will cause all 'C' channel RPS trips to trip. Only one other trip will cause a reactor
trip
b. Incorrect - Plausible alternative
c. Incorrect - Plausible alternative
d. Incorrect - Plausible alternative

39

During normal full power operation, a Reactor Protection System (RPS) Logic Matrix Power Supply
fails. How will this failure impact the RPS?
a. RPS trip logic will be one out of three.
b. The reactor will trip if another power supply associated with a different Logic Matrix fails.
c. RPS trip logic will be two out of three.
d. The reactor will trip if another power supply associated with the same Logic Matrix fails.

d. The reactor will trip if another power supply associated with the same Logic Matrix fails.

a. Plausible if the student believes that the failure causes on channel to be tripped, similar to loss of a preferred AC bus
b. Plausible if the student misapplies the matrix logic, i.e., two matrices are required to be tripped to trip the reactor
c. Plausible if the student believes that the failure causes a channel to be bypassed
d. CORRECT

40

Given the following with the plant operating in MODE 1:
* A fault occurs on Preferred AC Bus Y-40 which subsequently de-energizes Y-40
* The crew enters ONP-24.4, "Loss of Preferred AC Bus Y-40"
* Subsequently, the plant is manually tripped due to a Main Steam Line Break inside the
Containment
* PCS pressure is 1720 psia
- Containment pressure is 5.3 psig
Due to these conditions, which one of the following describes the correct action(s), if any, to take?
a. Push PB1-2 (Right) INJECTION INITIATE pushbutton to initiate Right Channel SIS ONLY.
b. Open CV-3002, Spray Valve, and start, P-54A, Spray Pump ONLY
c. Push PB1-2 (Right) INJECTION INITIATE pushbutton AND Open CV-3002, Spray Valve, AND
start, P-54A, Spray Pump.
d. No actions are necessary, Containment Spray and Safety Injection Actuation will operate
automatically for this event.

c. Push PB1-2 (Right) INJECTION INITIATE pushbutton AND Open CV-3002, Spray Valve, AND
start, P-54A, Spray Pump

a. Plausible if the student believes that spray valve and pump actuation are supplied by a different power supply
b. Plausible if the student believes that SIS actuation is supplied by a different power supply
c. CORRECT
d. Plausible if the student believes Y-40 does not supply CHP or SIS actuation circuits

41

Consider two separate excess steam demand events inside containment on the 'A' Steam
Generator. During both events the leak size is the same. The only difference between the two
events is that service water to containment is secured on the second event.
During the second event, Pressurizer level indication will be ___(1)___ and 'B' Steam Generator
level indication will be ____(2)____ than the first event. (Assume 1 to 2 hours into each event)
a. (1) Higher
(2) Lower
b. (1) Higher
(2) Higher
c. (1) Lower
(2) Higher
d. (1) Lower
(2) Lower

b. (1) Higher
(2) Higher

a. Plausible alternative
b. CORRECT - Both of these level instruments have external wet reference legs that are exposed to
containment conditions. The higher containment temperature caused by the lack of service water would
raise the temperature in these reference legs and lower the waters density. This would cause them to
indicate high.
c. Plausible alternative
d. Plausible alternative

42

Consider a Loss of Coolant Accident event in which SIRWT Level has reached the setpoint for a
Recirculation Actuation (RAS). In the event that West Safeguards Containment Sump Isolation
Valve, CV-3030, does not open on a RAS, which one of the following will occur? Assume all other
equipment is operable and functioning.
a. ONLY CV-3070, HPSI Pump, P-66B, Subcooling Valve, will not open.
b. CV-3070, HPSI Pump, P-66B, Subcooling Valve, will not open AND CV-3001, Containment
Spray Valve, will close.
c. ONLY CV-3001, Containment Spray Valve, will close.
d. Operator action is required to close CV-3070, HPSI Pump, P-66B, Subcooling Valve, AND
CV-3001, Containment Spray Valve.

b. CV-3070, HPSI Pump, P-66B, Subcooling Valve, will not open AND CV-3001, Containment
Spray Valve, will close.

a. Plausible if the student believes that there is an interlock with CV-3030 for CV-3070 but not CV-3001
b. CORRECT
c. Plausible if the student believes that there is an interlock with CV-3030 for CV-3001 but not CV-3070
d. Plausible if the student believes that the post RAS actions are necessary to correct the lineup

43

The following plant conditions exist:
* A 75 gpm tube leak has occurred on the 'B' S/G
* A loss of offsite power occurred immediately following the reactor trip
*PCS pressure is 1900 psia
* PCS temperature is 535°F
* The CRS directs a cooldown be commenced per EOP-5.0, "Steam Generator Tube
Rupture Recovery"
The preferred method of cooldown will be established using the (1) .
The most limiting component for the specified cooldown rate limit is the (2) .
a. (1) Turbine Bypass Valve
(2) Reactor Vessel
b. (1) Turbine Bypass Valve
(2) Pressurizer
c. (1) Atmospheric Dump Valves
(2) Reactor Vessel
d. (1) Atmospheric Dump Valves
(2) Pressurizer

c. (1) Atmospheric Dump Valves
(2) Reactor Vessel

a. Plausible if the student does not recognize that the TBV is not available due to loss of all AC.
b. Plausible if the student does not recognize that the TBV is not available due to loss of all AC.
c. CORRECT, cooldown limit for reactor is 100°F/Hr, PZR is 200°F/Hr
d. Plausible because there are several instances in procedures where it is required to record PZR and PCS

44

Given the following conditions:
* A Reactor trip from 100% power has just occurred
* The Main Turbine tripped as designed
* Main Feed Pump speed control was in CASCADE at the time of the trip
* NO operator actions have been taken
As a result, Steam Generator Water Level Control (SGWLC) controllers, LIC-0701 and LIC-0703,
will _______(1)_______ and the Main Feed Pumps will _______(2)_______.
a. (1) transfer to MANUAL
(2) ramp to minimum speed
b. (1) transfer to MANUAL
(2) remain at full speed
c. (1) remain in AUTO
(2) remain at full speed
d. (1) remain in AUTO
(2) ramp to minimum speed

a. (1) transfer to MANUAL
(2) ramp to minimum speed

a. CORRECT
b. Plausible because operator action is required to manually ramp MFP speed to minimum to avoid overfeeding SG
c. Plausible because operator action is required to manually close the FRVs and ramp MFP speed to minimum to avoid
overfeeding SG
d. Plausible because operator action is required to manually close the FRVs

45

The plant is operating at full power. The control room crew is preparing to bypass Feedwater
Heaters, E-3A and E-4A, due to a tube leak inside E-3A. What action is required to be taken prior
to bypassing E-3A and E-4A and why?
a. Lower plant power to

c. Lower turbine load to

46

Given the following plant conditions:
* A Plant Startup is in progress in MODE 3
* Auxiliary Feedwater (AFW) Pump, P-8A, is in service
*EK-1108 "CONDENSATE STORAGE TANK T-2 HI-LO LEVEL" annunciates
* Moments later EK-1115 "CONDENSATE STORAGE TANK T-2 LO-LO LEVEL"
annunciates
* Condensate Storage Tank, T-2, level indicates 7% and lowering
Which one of the following describes the impact on the plant due to this event and the appropriate
action to take?
a. AFW Pump damage will occur due to suction vortexing in T-2. Ensure all AFW Pumps are
tripped and placed in MANUAL.
b. AFW Pump damage will occur due to suction vortexing in T-2. Continue P-8A operation while
aligning Fire Water to P-8A/B suction.
c. Buckling on the bottom plate of T-2 will occur. Ensure all AFW Pumps are tripped and placed in
MANUAL.
d. Buckling on the bottom plate of T-2 will occur. Continue P-8A operation while aligning Fire
Water to P-8A/B suction.

a. AFW Pump damage will occur due to suction vortexing in T-2. Ensure all AFW Pumps are
tripped and placed in MANUAL.

a. CORRECT
b. Correct reason, however allowing P-8A to continue operating will cause damage. Align FPS would be a long term
action.
c. Plausible reason because this damage occurs to the SIRWT at 4% - student misapplies. Correct Action.
d. Plausible for same reason as b and c.

47

The "In Sync" light on the front panel of ED-08, Preferred AC Inverter #3, compares the frequency
of ______(1)______ to the frequency of ______(2)______ to ensure they are synchronized.
a. (1) the output of the inverter
(2) the input of the inverter
b. (1) the output of the inverter
(2) the Bypass Source, Y01
c. (1) Preferred AC Bus, Y30
(2) the Bypass Source, Y01
d. (1) the output of the inverter
(2) Preferred AC Bus, Y30

b. (1) the output of the inverter
(2) the Bypass Source, Y01

a. Plausible because the student misinterprets what "In Sync" means
b. CORRECT
c. Plausible because the student believes that, if the inverter is not operating, the green light should be on
d. Plausible because the student thinks the light is on during normal operation

48

EOP-3.0, "Station Blackout Recovery," directs operators to ensure all Primary Coolant Pump DC
Lift Pumps secured after ____(1)____ minutes to prevent __________(2)___________.
a. (1) Ten
(2) Excessive DC Battery drain
b. (1) Ten
(2) Excessive oil transfer from the PCP motor lower to upper oil reservoir
c. (1) Five
(2) Excessive DC Battery drain
d. (1) Five
(2) Excessive oil transfer from the PCP motor lower to upper oil reservoir

c. (1) Five
(2) Excessive DC Battery drain

a. Plausible time, correct time
b. Plausible time, plausible reason as this has occurred for prolonged operation
c. CORRECT
d. Correct time, plausible reason

49

Given a loss of all AC power with no Diesel Generator operating, you are directed to depress the
Shunt Trip push button on panel D-11A. Where is this panel located and what will be the resultant
effect?
a. Bus 1C room. Isolates all loads from Station Battery #1 EXCEPT DC Panel D-11A.
b. D/G 1-2 room. Isolates all loads from Station Battery #1 EXCEPT DC Panel D-11A.
c. D/G 1-2 room. Isolates all loads from Station Battery #1 INCLUDING DC Panel D-11A.
d. Bus 1C room. Isolates all loads from Station Battery #1 INCLUDING DC Panel D-11A.

a. Bus 1C room. Isolates all loads from Station Battery #1 EXCEPT DC Panel D-11A.

a. CORRECT
b. Plausible because the shunt trip push button for Station Battery #2 is in this location
c. Plausible because the shunt trip push button for Station Battery #2 is in this location. Also because the push button
is located on the panel is it plausible that D-11A could be lost.
d. Plausible because the push button is located on the panel.

50

Given the following plant conditions:
* The plant is operating at full power
*Emergency Diesel Generator 1-1 is supplying Bus 1C in parallel with Safeguards
Transformer 1-1
Which one of the following describes the response if all off-site power is lost?
a. Diesel Generator 1-1 will remain operating, output breaker 152-107 will trip and then reclose,
the NSD sequencer will load Bus 1C.
b. Diesel Generator 1-1 will trip then restart, output breaker 152-107 will trip and Bus 1C will be
de-energized.
c. Diesel Generator 1-1 will remain operating, output breaker 152-107 will trip and then reclose,
the DBA sequencer will load Bus 1C.
d. Diesel Generator 1-1 will remain running, output breaker 152-107 will trip and Bus 1C will be
de-energized.

a. Diesel Generator 1-1 will remain operating, output breaker 152-107 will trip and then reclose,
the NSD sequencer will load Bus 1C.

a. CORRECT
b. Plausible because the student could reason that the EDG will trip on overspeed due to loss of load. However the
EDG won't restart
c. Plausible if the student misapplies the operation of the NSD and DBA sequencers
d. Plausible if the student does not know that the NSD sequencer will energize

51

Given the following conditions:
*T-101B, Waste Gas Decay Tank, release is in progress
* Annunciator EK-0207, “STACK EFF RAD C-169 HIGH” is received in the Control Room due
to RIA-2326, Normal Range Noble Gas Monitor, in alarm
Which one of the following will occur?
a. Main Exhaust Fans, V-6A/V-6B, automatically trip and their associated dampers close.
b. RIA-2326, Normal Range Noble Gas Monitor, meter transfers from cpm to R/Hr.
c. RGEM transfers from Normal (RIA-2326) to High Range (RIA-2327) Noble Gas Monitor.
d. CWRT Vent Valves, CV-1064/1065, automatically close.

c. RGEM transfers from Normal (RIA-2326) to High Range (RIA-2327) Noble Gas Monitor.

a. Plausible because this could stop the release
b. Plausible because these radiation monitors have two scales
c. CORRECT
d. Plausible because this is a manual action of the ARP

52

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 will allow initiating the release EXCEPT:
a. Setup local portable monitoring equipment at release point.
b. Perform independent verification of the discharge flowpath lineup.
c. Obtain an additional sample of the tank contents.
d. Perform independent verification of the release rate calculations.

a. Setup local portable monitoring equipment at release point.

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

53

Which one of the following conditions will result in CV-1359, Non-Critical Service Water Isolation
Valve, automatically closing? (Consider each condition separately)
a. A steam line break results in Containment pressure rising to 3.6 psig.
b. A fuel element failure results in Containment radiation rising to 12R/Hr.
c. A Primary Coolant leak results in Pressurizer pressure lowering to 1550 psia.
d. A Service Water leak results in SW Critical Header pressure lowering to 40 psig.

c. A Primary Coolant leak results in Pressurizer pressure lowering to 1550 psia

a. Plausible because candidate misapplies setpoint for CHP, which is 4#.
b. Plausible because candidate believes that a CHR will close valve, CHR does initiate a CIS.
c. CORRECT
d. Plausible because candidate believes that valve closes on low header pressure to supply critical loads. Standby
pump starts on low header pressure of 40#.

54

From full power, a Safety Injection occurs concurrent with a loss of Instrument Air. Instrument Air
pressure indicates 10 psig and lowering. Several minutes later, it is noted that FWP Air Cross-tie
Valve, CV-1221, indicating RED light is ON. The GREEN light is OFF. The handswitch remains
selected to CLOSE.
Which one of the following accounts for the status of CV-1221?
CV-1221 has ...
a. opened automatically due to the Safety Injection Signal.
b. received an open signal when Instrument Air header pressure lowered to 85 psig.
c. failed open due to a loss of Instrument Air to the operator.
d. failed open due to a loss of control power from 1E bus.

c. failed open due to a loss of Instrument Air to the operator

a. Plausible if the student incorrectly believes SIS causes CV-1221 to open.
b. Plausible if the student believes there is an interlock to automatically open CV-1221 on lowering instrument air
pressure.
c. CORRECT
d. Plausible if the student believes that CV-1221 receives control power from bus 1E.

55

Which one of the following describes interlock features on the Personnel Air Lock and Escape Air
Lock doors which are designed to ensure Containment integrity?
a. Personnel Air Lock doors cannot be opened at the same time as Escape Air Lock doors.
b. Neither door can be opened after a Containment High Pressure (CHP) or Containment High
Radiation (CHR) condition.
c. An electrical device prevents the inner door from being opened at the same time as the outer
door for the Personnel and Escape Air Locks.
d. A mechanical device prevents the inner door from being opened at the same time as the outer
door for the Personnel and Escape Air Locks.

d. A mechanical device prevents the inner door from being opened at the same time as the outer
door for the Personnel and Escape Air Lock

a. Though this may sound like a desirable feature, these doors are on opposite sides of containment and there is NO
interlock between them.
b. Another desirable sounding feature, since there are a number of component auto operations affected by CHP/CHR;
however, there is no such design feature.
c. There is no such design feature.
d. CORRECT - Per design, both doors are mechanically interlocked so that only one can be opened at a time
to maintain containment integrity.

56

Given the following:
* A reactor trip from 100% power occurs
* The control room crew observes that 4 full length control rods are indicating NOT fully
inserted on the Core Matrix display
* The Reactor Operator attempts to emergency borate but VCT Isolation, MO-2087, will NOT
close
Which one of the following actions will allow successful completion of emergency boration in
accordance with SOP-2A, "Chemical and Volume Control System?"
a. Open MO-2169 and MO-2170, Boric Acid Gravity Feed Valves.
b. Start P-56A, Boric Acid Pump, and open MO-2140, Pumped Feed Valve.
c. Open MO-3072, HPSI Train 2/Charging Cross Connect Valve.
d. Open MO-2160, SIRWT to Charging Pump Isolation.

b. Start P-56A, Boric Acid Pump, and open MO-2140, Pumped Feed Valve.

a. Plausible because this is acceptable if MO-2087 is capable of closing
b. CORRECT
c. Plausible because this could inject boron if PCS pressure was low enough, however this is not acceptable per
SOP-2A
d. Plausible because this could inject boron, however this is not acceptable per SOP-2A

57

The Reactor Vessel Level Monitoring System (RVLMS) lights indicate ALL GREEN lights OFF and
ALL RED lights ON. This indicates that Reactor Vessel water level is approximately:
a. at or above the Reactor Vessel flange.
b. at or below the top of the fuel assemblies.
c. at or below the center of the hot and cold legs.
d. at or above the In-Core instrument flanges.

b. at or below the top of the fuel assemblies

a. Plausible as this is a key level in determining reduced inventory conditions
b. CORRECT
c. Plausible as this is the minimum allowable level during reduced inventory conditions
d. Plausible as this is where the RVLMS probes enter the reactor vessel closure head

58

With the plant operating in MODE 1, Pressurizer Pressure Controller, PIC-0101A, loses power due
to an internal fault within the controller. Assuming PIC-0101A is in service, which one of the
following describes the immediate impact on the plant?
a. RPS TM/LP Channel 'A' trips AND Pressurizer Proportional heaters receive full amps.
b. Pressurizer Proportional heaters receive full amps AND Pressurizer Spray valves close.
c. RPS TM/LP Channel 'A' trips AND Pressurizer Spray valves close.
d. Pressurizer Proportional heaters receive full amps ONLY.

b. Pressurizer Proportional heaters receive full amps AND Pressurizer Spray valves close

a. Plausible if student believes that PPCS controller sends a signal to RPS.
b. CORRECT
c. Plausible if student believes that PPCS controller sends a signal to RPS.
d. Plausible if student misapplies the low signal and believes that heaters only receive full power.

59

With the plant operating in MODE 1, the following alarm is received in the control room:
EK-1309, "SPENT FUEL POOL HI/LO LEVEL"
The control room crew determines the alarm is due to a LOW level condition in the Spent Fuel Pool
(SFP) and is due to normal evaporative losses. The Control Room Supervisor directs SFP level be
raised to 6" below the skimmers. Which one of the following describes (1) the source of water that
will be used to refill the SFP under these conditions AND (2) the monitoring requirements during the
fill operation?
a. (1) T-90, Primary System Makeup Storage Tank.
(2) The Control Room SFP TV Monitor is acceptable to be used to monitor SFP level.
b. (1) T-90, Primary System Makeup Storage Tank.
(2) An Operator must be stationed at the SFP in addition to monitoring the Control Room TV
Monitor.
c. (1) T-91, Utility Water Storage Tank.
(2) The Control Room SFP TV Monitor is acceptable to be used to monitor SFP level.
d. (1) T-91, Utility Water Storage Tank.
(2) An Operator must be stationed at the SFP in addition to monitoring the Control Room TV
Monitor.

a. (1) T-90, Primary System Makeup Storage Tank.
(2) The Control Room SFP TV Monitor is acceptable to be used to monitor SFP level.

a. CORRECT
b. Plausible as this is the correct source but it is acceptable to use the control room TV monitor.
c. Plausible as this is a source that could be used for decontamination activities.
d. Plausible as this is a source but it is acceptable to use the control room TV monitor.

60

The plant is operating in MODE 1 at full power when a turbine trip causes a reactor trip. During
subsequent actions per EOP-1.0, "Standard Post Trip Actions," the Turbine NCO discovers that 'A'
Main Feed Pump speed will NOT lower. Which one of the following describes the impact of this
condition and the appropriate action?
a. The Safety Injection Actuation setpoint may be reached due to PCS overcooling. Trip Main
Feed Pump, P-1A.
b. Inadequate Shutdown Margin may occur due to PCS overcooling. Trip Main Feed Pump, P-1A.
c. The Safety Injection Actuation setpoint may be reached due to PCS overcooling. Trip Main
Feed Pumps, P-1A AND P-1B.
d. Inadequate Shutdown Margin may occur due to PCS overcooling. Trip Main Feed Pumps, P-1A
AND P-1B.

a. The Safety Injection Actuation setpoint may be reached due to PCS overcooling. Trip Main
Feed Pump, P-1A

a. CORRECT
b. Correct action but wrong implication. This does happen, however, it is not a concern due to meeting the reactivity
control safety function.
c. Correct implication but wrong action.
d. Wrong implication and wrong action.

61

Given the following conditions:
* The plant is in MODE 3 following a reactor trip from 100% power
*PCS temperature is being controlled with the Turbine Bypass Valve in AUTO
* The Atmospheric Steam Dumps are closed with Steam Dump Controller, HIC-0780A, in
AUTO
* The Average Temperature Display Select Switch is in the LOOP 2 position
Which one of the following describes the effect of TAVE failing LOW from TYT-0200, Loop 2 TAVE
Calculator, on the plant. (Assume NO operator action has been taken)

a. The only means of PCS heat removal with the secondary plant is via the Main Steam Code
Safety valves.
b. The Turbine Bypass Valve fails closed and will NOT open until the Average Temperature
Display Select Switch is placed in LOOP 1 position.
c. The Turbine Bypass Valve fails closed and will NOT open. The ADVs will open on a quick open
signal.
d. The TBV will modulate open/closed to maintain Main Steam pressure at setpoint. The ADVs
will NOT modulate open.

d. The TBV will modulate open/closed to maintain Main Steam pressure at setpoint. The ADVs
will NOT modulate open

a. Plausible if the student believes that TAVE signal feeds both TBV and ADVs.
b. Plausible if the student believes that TAVE signal feeds only TBV.
c. Plausible if the student believes that TAVE signal feeds only TBV and correctly identifies the response of the ADVs.
d. CORRECT

62

The following plant conditions exist:
* The plant is in MODE 1 at 100% power
* EHC Pump, P-19A, is selected to RUN and is operating
* EHC Pump, P-19B, is selected to AUTO and is off
* Control Room annunciator EK-0113, “EH SYSTEM LO-LO LEVEL TRIP” annunciates
Which one of the following describes the expected configuration of EHC Pumps, P-19A/B?
a. Both EHC pumps operating.
b. Both EHC pumps off.
c. P-19A operating, P-19B off.
d. P-19A off, P-19B operating.

c. P-19A operating, P-19B off

a. Plausible if the student misapplies the concept of low EHC level, i.e., pressure with tank level
b. Plausible if the student believes that the pumps trip for protection due to low tank level
c. CORRECT
d. Plausible if the student believes that the system will swap pumps in the case of a leak in the operating pump

63

Given the following conditions:
* The plant is at 100% power
* A Steam Generator tube leak has been diagnosed by the crew
* Preparations are being made to estimate the size of the tube leak per ONP-23.2
* The Off-Gas flow rate was reported at 3 scfm earlier in the shift
* Unknown to the crew, Off-Gas flow rate rises to 10 scfm
What would be the effect of using the LOWER Off Gas flow rate of 3 scfm to estimate the tube leak
rate?

a. No effect as long as Off-Gas Monitor, RIA-0631, reading is correct.
b. The estimated leak rate will be lower than the actual leak rate.
c. No effect because the PCS Activity value corrects for variations in Off Gas flow.
d. The estimated leak rate will be higher than the actual leak rate.

b. The estimated leak rate will be lower than the actual leak rate.

a. Plausible if the student misunderstands the purpose of the off-gas flow reading in determining tube leak rate
b. CORRECT
c. Plausible because Operations reports off-gas flow to chemistry daily.
d. Plausible if the student misapplies the dilution effect of the off-gas flow.

64

RIA-1113, Waste Gas Discharge Monitor, has alarmed to stop an Authorized Waste Gas Batch.
Which one of the following actions must be performed OUTSIDE the control room before the batch
can be re-started?
a. Place HS-1113, Waste Gas Surge Tank Discharge control valve, to close then back to open.
b. Push CV-1113, Waste Gas Surge Tank Discharge, HIGH RADIATION RESET pushbutton.
c. Place HS-1123, Waste Gas Decay Tanks Discharge control valve, to close then back to open.
d. Push CV-1123, Waste Gas Decay Tank Discharge, HIGH RADIATION RESET pushbutton.

d. Push CV-1123, Waste Gas Decay Tank Discharge, HIGH RADIATION RESET pushbutton.

a. Plausible as this is a local control on radwaste panel C-40, however, this valve should already be closed. Student
misapplies the flow path for a waste gas batch.
b. Plausible as this is a local control on radwaste panel C-40, however, this will not re-open the valve
c. Plausible as this is a local control on radwaste panel C-40, however this valve should be closed. Student misapplies
the flow path for a waste gas batch.
d. CORRECT

65

All of the following Fire Alarms on Panel C-47B require IMMEDIATE sounding of the Fire Alarm and
call out of the Fire Brigade EXCEPT:
a. Charging Pump Areas.
b. Corridor 106 on Elev. 590’.
c. Remote Shutdown Panel & Stairwell.
d. Injection & Spray Pumps.

d. Injection & Spray Pumps.

a. Plausible area
b. Plausible area
c. Plausible area
d. CORRECT

66

Given the following conditions:
* The plant is at full power
* T-2, Condensate Storage Tank, temperature is 100°F
* T-81, Primary System Makeup Storage Tank, temperature is 80°F
* QO-21, "Inservice Test Procedure - Auxiliary Feedwater Pumps" is to be performed
* Auxiliary Feedwater flow will be initiated to BOTH Steam Generators at the programmed
value for an Auxiliary Feedwater Actuation (AFAS)
Immediately prior to initiation of AFW flow, which one of the following is the MAXIMUM allowable
Heat Balance power level?
a. 99.5%
b. 99.4%
c. 99.3%
d. 99.2%

c. 99.3%

a. Plausible as this is the value for flow to one S/G (165 gpm)
b. Plausible as this is symmetric
c. CORRECT
d. Plausible as this is the value if 80°F is used for AFW temp

67

The Operational Decision Making Issue (ODMI) process would most likely be used for which one of
the following conditions?
a. Control Rod Drive seal leakage is steadily trending upwards and will reach a limit in 2 weeks.
b. The Operations Department staffing level is below the fleet recommended standard.
c. A Technical Specification Surveillance Test procedure cannot be performed as written.
d. The control room crew is preparing to maneuver the plant from MODE 2 to MODE 1.

a. Control Rod Drive seal leakage is steadily trending upwards and will reach a limit in 2 weeks

a. CORRECT
b. Plausible - people issue
c. Plausible - procedure issue
d. Plausible - process issue

68

Preparations are being made to enter MODE 6.
Minimum PCS boron concentration must be at least (1) and sufficient to ensure that with
all control rods withdrawn, the reactor remains shutdown by at least (2) .
a. (1) 1720 ppm
(2) 5.0%
b. (1) 2500 ppm
(2) 5.0%
c. (1) 2500 ppm
(2) 2.0%
d. (1) 1720 ppm
(2) 2.0%

a. (1) 1720 ppm
(2) 5.0%

a. CORRECT
b. Correct SD Margin, incorrect boron concentration - this is the upper boron concentration limit for the SIRWT
c. Incorrect SD margin - plausible because this is the required SD margin when the PCS if full, incorrect boron
concentration
d. Correct boron, incorrect SD Margin

69

When developing a tagout for a pump, which one of the following describes the correct component
tagging sequence?
a. Discharge valve.
Suction valve.
Breaker for main power.
b. Breaker for main power.
Suction valve.
Discharge valve.
c. Breaker for main power.
Discharge valve.
Suction valve.
d. Suction valve.
Discharge valve.
Breaker for main power.

c. Breaker for main power.
Discharge valve.
Suction valve

a. Plausible if the student believes that power is turned off last
b. Plausible if the student believes that the suction valve is tagged first
c. CORRECT
d. Plausible due to a combination of 'a' and 'b'

70

Which one of the following describes when ALL Auxiliary Feedwater Pumps are required to be
OPERABLE during a Plant Startup from MODE 5?
All AFW Pumps must be operable prior to ....
a. PCS reaching 325 °F.
b. Reactor criticality.
c. entering MODE 4.
d. entering MODE 3.

b. Reactor criticality

a. Plausible, similar to HPSI pump operability
b. CORRECT
c. Plausible because only one AFW motor driven pump is required to be operable in MODE 4.
d. Plausible because both AFW motor driven pumps are required to be operable in MODE 3.

71

Which one of the following lists the minimum Containment Air Cooler Fans required to be in service
to support operability of Containment Gas Radiation Monitor, RIA-1817?
a. None, RIA-1817 has a sample pump.
b. One Containment Air Cooler Fan.
c. Two Containment Air Cooler Fans.
d. Three Containment Air Cooler Fans.

b. One Containment Air Cooler Fan.

a. Plausible as this has a sample pump, but if no CACs are in operation there is no representative flow path
b. CORRECT
c. Plausible alternative
d. Plausible alternative

72

During a batch release of T-68B, Waste Gas Decay Tank, with V-6A, Main Exhaust Fan, tagged for
maintenance, the in-service Main Exhaust Fan, V-6B, trips. Which one of the following actions is
required in accordance with SOP-18A, "RADIOACTIVE WASTE SYSTEM - GASEOUS?"
a. Depress the HIGH pushbutton on Waste Gas Discharge Radiation Monitor, RIA-1113.
b. Secure Radwaste Area Ventilation fans, V-10 and V-14A/B.
c. Lower Waste Gas Discharge Radiation Monitor, RIA-1113, trip setpoint.
d. Ensure CV-1816 and CV-1817, Main Exhaust Fan discharge dampers, are closed.

c. Lower Waste Gas Discharge Radiation Monitor, RIA-1113, trip setpoint.

a. Plausible but this simply displays the current HIGH alarm setpoint.
b. Plausible if student believes WGDTs discharge into the exhaust plenum for V-14A/B.
c. CORRECT
d. Plausible as this is similar to an action to take in ARP-7 for High Main Exhaust Plenum pressure.

73

EOP-7.0, "Loss of All Feedwater Recovery," contains the following guidance concerning restoration
of feedwater to a dry Steam Generator. What is the reason for this guidance?

CAUTION
Limit feed flow to less than 300 gpm
for any S/G with level less than -84%

a. Avoids a loss of PCS pressure control due to Pressurizer insurges and outsurges.
b. Prevents a rapid PCS cooldown, avoiding a Pressurized Thermal Shock to the Rx vessel.
c. Prevents uneven cooling of the PCS which may result in a localized reactivity excursion.
d. Minimizes the probability of causing significant damage to the S/G tube bundle.

d. Minimizes the probability of causing significant damage to the S/G tube bundle.

a. Plausible as this is a precaution in ONP-25.2 for fire in the plant and evacuation of control room
b. Plausible as this could occur but is not the reason for the Caution
c. Plausible as this will occur but is not a concern in this case
d. CORRECT

74

Which one of the following describes the minimum requirements for receiving an alarm in the
control room that is unexpected (i.e., not part of a planned activity)?
a. Announce the alarm ONLY if it is deemed critical by the ATC operator and reference the
appropriate alarm response procedure EACH time the alarm comes in.
b. Announce the alarm to the operating crew for each occurrence and reference the appropriate
alarm response procedure EACH time the alarm comes in.
c. Announce the alarm to the operating crew for each occurrence and reference the alarm
response procedure the FIRST time the alarm comes in on each shift.
d. Announce the alarm ONLY if it is deemed critical by the ATC operator and reference the alarm
response procedure the FIRST time the alarm comes in on each shift.

c. Announce the alarm to the operating crew for each occurrence and reference the alarm
response procedure the FIRST time the alarm comes in on each shift.

a. Plausible - similar to the requirements for annunciator response for EOP/ONP activities
b. Plausible - similar to the requirements for repeat annunciators
c. CORRECT
d. Plausible combination of a and b