RPS 2

Question 1

In addition to PCS temperature, which ONE of the following sets of three (3)
parameters are monitored by the Reactor Protection system to ensure MDNBR limits
are NOT exceeded?
A. Rx Power, PCS Flow, Steam Flow
B. Rx Power, PZR pressure, S/G level
C. Rx Power, PZR pressure, PCS flow
D. PZR pressure, PCS flow, Feedwater Flow

Answer 1

C. Rx Power, PZR pressure, PCS flow

Question 2

Which statement explains the relationship between Primary Coolant Pump (PCP) flow
rate and Primary Coolant System (PCS) / Reactor Core parameters?
A. Lowering PCP flow causes a higher Thot temperature into the steam generators
and thus a lower Steam Generator pressure for a given power level.
B. Loss of one PCP causes a larger temperature differential across the core leading to
quadrant power tilt concerns.
C.Lowering PCP flow causes a rise in PCS temperature leading to an increase in the
TM/LP setpoint.
D. Plugging Steam Generator tubes will reduce PCP flow which will reduce the
temperature differential across the core

Answer 2

C.Lowering PCP flow causes a rise in PCS temperature leading to an increase in the
TM/LP setpoint.

Question 3

Which ONE of the following describes a minimum combination of the 24 Reactor
Protective System (RPS) Matrix Relays which, when de-energized, would generate a
complete reactor trip with all full length rods dropping into the core?
A. All 24 must de-energize to have a complete reactor trip.
B 2 RPS Matrix Relays would generate the complete reactor trip, as long as one has
a contact in the Y-30 clutch power supply circuit, and the other has a contact in the
Y-40 circuit.
C. The 4 RPS Matrix Relays would generate the complete reactor trip, as long as each
one of them has a contact in each one of the 4 contact strings of the trip initiation
logic.
D. Anyone RPS Matrix Relay would generate the complete reactor trip.

Answer 3

B 2 RPS Matrix Relays would generate the complete reactor trip, as long as one has
a contact in the Y-30 clutch power supply circuit, and the other has a contact in the
Y-40 circuit

Question 4

How do the Reactor Protection System (RPS) Manual Reactor Trip push buttons (P/B)
on EC-02 and EC-06 de-energize the Clutch Power supplies?
A. The EC-02 P/B de-energizes the M relays and the EC-06 P/B de-energizes
the RPS Breaker UV coils.
B. Both P/Bs will de-energize the RPS Breaker UV coils.
C. The EC-02 P/B de-energizes the RPS Breaker UV coils and the EC-06 P/B deenergizes
the M relays.
D. Both P/Bs will de-energize the RPS Power Trip relays.

Answer 4

A. The EC-02 P/B de-energizes the M relays and the EC-06 P/B de-energizes
the RPS Breaker UV coils

Question 5

Which ONE of the following Reactor Protection System (RPS) Manual Reactor Trips
performs the same electrical function as the automatic RPS trip?
A. The EC-02 push button.
B. CROM toggle switches.
C. The EC-06 push button.
D. RPS Breakers 42-1 and 42-2.

Answer 5

A. The EC-02 push button

Question 6

The plant is at 100%. One Main Feedwater pumps trips. The Turbine Operator
initiates a trip from the CO-2 panel using the Manual Trip Push Button. The reactor
does not trip. The reactor does not trip due to any RPS setpoint initiated trip. The
reactor Operator trips the reactor using the Manual Trip push button on the RPS panel.
Which of the following indications indicate the RPS breakers have opened (refer to the
attached picture of the RPS cabinet clutch power supplies?
Red Trip Light A-C ON light D-C ON light
A. ON ON ON
B. ON OFF OFF
C. OFF OFF OFF
D. OFF ON ON

Answer 6

C. OFF OFF OFF
Is correct. The M2 relay is not energized as the RPS trips have not initiated as
designed. The “TRIP” stays OFF. The RPS panel pushbutton opens the RPS
breakers and the A-C ON and D-C On lights will be off

Question 7

One of the purposes of the 30 second time delay in the Reactor Protection System
reset circuit is to:
A. ensure any valid reactor trip signal is fully processed through the Reactor Protection
System.
B. prevent the Matrix Relay contacts from arcing thereby eliminating a potential future
ATWS.
C. protect Preferred AC Buses Y-30 and Y-40 inverter transformers from a damaging
current surge.
D. protect the clutch power supplies from an overcurrent condition should they reenergize
in mid-drop

Answer 7

A. ensure any valid reactor trip signal is fully processed through the Reactor Protection
System.

Question 8

Which ONE of the following describes the reason that the Reactor Protective System
(RPS) must be manually reset with a 30 second time delay from the time of the trip?
A. To ensure that the reset of the RPS is performed systematically and in accordance
ith approved procedures.
B. To prevent the RPS from automatically resetting itself and potentially damaging
CRDMs if rods were still dropping into the core.
C. To prevent operators from restarting the reactor too quickly following a reactor trip.
D. To give operators time to verify that a complete reactor trip had occurred with all
full-length control rods inserting completely

Answer 8

B. To prevent the RPS from automatically resetting itself and potentially damaging
CRDMs if rods were still dropping into the core

Question 9

The plant is preparing to perform a reactor startup following a refueling outage. Who
must authorize resetting the Reactor Protection System?
A. Reactivity Manager.
B. Reactor Engineer.
C. Plant Manager.
D. Shift Manager

Answer 9

D. Shift Manager

Question 10

During normal full power operation Primary Coolant System (PCS) digital Pressure
Indicator PI-01 04 on EC-02 suddenly indicates 0 psia.
Which ONE of the following would be an indication that the Reactor Protection System
(RPS) Thermal Margin/Low Pressure trip setpoint has been actuated?
A. TM/LP trip setpoint PIA amber lights are not lit.
B. The Clutch Power Supply trip lights are not lit.
C. TM/LP trip unit red relay LEOs are lit on all channels.
D. All six Matrix Relay Logic power supply lights are lit.

Answer 10

C. TM/LP trip unit red relay LEOs are lit on all channels

Question 11

During power operation Power Range Nuclear Power indication NI-06 upper chamber
fails to 125%. Total NI power indicated on that channel rises to 112%.
Which ONE of the following identifies how it can be determined whether the Reactor
Protective System (RPS) setpoint for only that channel of the Variable High Power Trip
(VHPT) was exceeded and is still exceeded?
A. The reactor is tripped. The red “trip” and white “pretrip” bistables for the VHPT
channel B are lit.
B. The reactor is not tripped. The rep “trip” and white “pretrip” bistables for the VHPT
channel B are lit.
C. The reactor is tripped. All three red matrix lights are lit on the VHPT trip unit
channel “B.”
D The reactor is not tripped. All three red matrix lights are lit on the VHPT trip unit
channel “B.”

Answer 11

D The reactor is not tripped. All three red matrix lights are lit on the VHPT trip unit
channel “B.”

Question 12

With the plant in Mode 3 Source/Wide Range NI-1/3 fails and the NI-1/3 High Start-Up
Rate (SUR) trips lock-in. I&C has requested resetting the Reactor Protection System
(RPS) as part of their approved troubleshooting plan.
Which ONE of the following must be performed in order to reset the RPS?
A. Insert and turn the Zero Power Mode Bypass keys.
B. Bypass either ‘A’ or ‘C’ RPS channel High SUR trips.
C. No actions can be taken to clear these locked-in trips.
D. Bypass ‘B’ and ensure tripped ‘0’ channel High SUR trips

Answer 12

B. Bypass either ‘A’ or ‘C’ RPS channel High SUR trips.

Question 13

Given that reactor power is more than 1E-4% and less than 15%.
Which ONE of the following would prevent the Reactor Protective System (RPS) from
being reset?
A Two out of four High Startup Rate bistables are tripped with all three red matrix
lights lit on each trip unit.
B. It has been more than 30 seconds from the time that a valid RPS trip was
processed.
C. The RPS TM/LP bistable “trip” and “pretrip” lights are lit and their Trip Relay lights
are OFF.
D. All Matrix Logic Ladder power supply lights indicate power is available to the Matrix
Relays.

Answer 13

A Two out of four High Startup Rate bistables are tripped with all three red matrix
lights lit on each trip unit

Question 14

The Reactor Protective System (RPS) is tripped, with the reactor ready for startup.
“A” Steam Generator level is 26%.
Which ONE of the following would allow the RPS to be reset?
A. Bypass one of the RPS “A” Steam Generator Low Level trip units.
B. Raise “A” Steam Generator level to greater than 28%.
C. Bypass all of the RPS “A” Steam Generator Low Level trip units.
D. Manually reset the RPS breakers 42-1/RPS and 42-2/RPS.

Answer 14

B. Raise “A” Steam Generator level to greater than 28%.

Question 15

The Reactor Protective System (RPS) is tripped, with the reactor ready for startup.
“A” Steam Generator Pressure is 500 psia.
Which ONE of the following would allow the RPS to be reset?
A. Bypass one of the RPS “A” Steam Generator Low Level trip units.
B. Bypass all of the RPS “A” Steam Generator Low Level trip units.
C. Place the Zero Power Mode Bypass in service for all four RPS channels.
D. Manually reset the RPS breakers 42-1/RPS and 42-2/RPS.

Answer 15

C. Place the Zero Power Mode Bypass in service for all four RPS channels.

Question 16

Which ONE of the following conditions would prevent the Reactor Protection System
(RPS) from being reset?
A.It has been less than 30 seconds from the time a valid RPS trip was processed.
B. RPS TM/LP Bistable Trip and Pre-trip lights are lit and their Trip Relay lights are
OFF.
C. Two out of four High Start-Up Rate bistables are tripped with reactor power less
than1 E-4%.
D. All Matrix Logic Ladder power supply lights indicate power is available to the Matrix
Relays.

Answer 16

A.It has been less than 30 seconds from the time a valid RPS trip was processed

Question 17

One of the purposes of the 30 second time delay in the Reactor Protection System
reset circuit is to:
A. preclude mechanical damage to the CRO mechanism clutches should they
re-energize in mid-drop.
B. prevent the Matrix Relay contacts from arcing thereby eliminating a potential future
ATWS.
C. protect the clutch power supplies from an overcurrent condition should they
re-energize in mid-drop.
O. protect Preferred AC Buses Y-30 and Y-40 inverter transformers from a damaging
current surge

Answer 17

A. preclude mechanical damage to the CRO mechanism clutches should they
re-energize in mid-drop

Question 18

Which ONE of the following Clutch Power Supply indications would verify that the
Reactor Protection System has been reset?
A. Trip indication lamps lit
B. DC On indication lamps not lit
C. AC On indication lamps lit
D. Ground detector lamps not lit

Answer 18

C. AC On indication lamps lit

Question 19

Which ONE of the following describes the three types of RPS trip unit bypasses?
A. Trip Channel bypass, Zero Power Mode bypass, Automatic bypass.
B. Nuclear Channel bypass, Zero Power Mode bypass, PCS Low Flow bypass.
C. Wide Range bypass, Zero Power Mode bypass, PCS Low Flow bypass.
D. Intermediate Power bypass, Zero Power Mode bypass, Technical Specification
Surveillance bypass.

Answer 19

A. Trip Channel bypass, Zero Power Mode bypass, Automatic bypass.

Question 20

All but one of the following describes a type of Reactor Protective System (RPS)
bypass. Which ONE is the exception?
A. Zero Power Mode bypass
B. Wide Range bypass
C. Trip Channel bypass
D. Automatic bypass

Answer 20

B. Wide Range bypass

Question 21

Which ONE of the following indications on control panel C-06 should be used as an
indication to verify that the Reactor Protective System (RPS) was properly reset?
A. “DC Ground” lights are off on all 4 clutch power supply panels.
B. All 24 Matrix Relay white lights are lit and equally illuminated.
C. AC Trouble” lights are lit on all 4 clutch power supply panels.
D. All four arc suppression network voltmeters indicate 120 VAC.

Answer 21

C. AC Trouble” lights are lit on all 4 clutch power supply panels

Question 22

The purpose of the Reactor Protection System (RPS) Zero Power Mode Bypass (ZPM)
is to:
A. bypass Loss of Load and High SUR RPS trips at 1 E-4% reactor power.
B. enable automatic bypassing of the Loss of Load and High SUR trips.
C. bypass RPS trips that would prevent Control Rod Drive testing.
D. disable bypassing S/G Low Pressure, TM/LP and Low pes Flow trips

Answer 22

C. bypass RPS trips that would prevent Control Rod Drive testing

Question 23

Which ONE of the following describes the purpose of the Zero Power Mode bypass of
the Reactor Protective System (RPS)?
A. Prevents resetting the RPS when reactor power is less than 1E-4%.
B. Prevents operating the reactor when certain RPS trips are not available.
C.Permits control rod testing when the plant is shutdown or assures a reserve
shutdown margin during low power testing.
D. Permits power operation less than 25% when one of four Primary Coolant Pumps is
out of service for maintenance.

Answer 23

C.Permits control rod testing when the plant is shutdown or assures a reserve
shutdown margin during low power testing

Question 24

Which ONE of the following reactor trip signals are bypassed by the Zero Power Mode
Bypass keys?
A. Steam Generator Low Level
B. Thermal Margin/Low Pressure
C. Variable High Power Trip
D. Loss of Load and High SUR

Answer 24

B. Thermal Margin/Low Pressure

Question 25

All but one of the following Reactor Protection System trips are bypassed by the Zero
Power Mode bypass. Which ONE is the exception?
A. Thermal Margin/Low Pressure
B. Low PCS Flow
C. Low Steam Generator Pressure
D. Low Steam Generator Level

Answer 25

D. Low Steam Generator Level

Question 26

Given the following plant conditions:
Reactor power is less than 1E-4%
Low power physics testing is in progress
Which one of the following sets of RPS trips are bypassed when placing the Zero
Power Mode Bypass switch on the RPS channel in BYPASS?
A. High Start-up Rate, Low S/G Pressure, and Low S/G Level
B. High Start-up Rate, TM/LP, and Low S/G Pressure
C. PCS Low Flow, TM/LP, and Low S/G Pressure
D. PCS Low Flow, TM/LP, and Low S/G Level

Answer 26

C. PCS Low Flow, TM/LP, and Low S/G Pressure

Question 27

Which ONE of the following must be operable prior to placing the Zero Power Mode
Bypass in operation?
A. ATWS trip circuitry
B. NI-1/3 and NI-2/4
C. ZPM Bypass lamps
D. All other RPS trips

Answer 27

B. NI-1/3 and NI-2/4

Question 28

Criteria for placing the Zero Power Mode (ZPM) bypass in operation have been verified
as met.
Which ONE of the following describes an action needed to place the ZPM bypass in
operation such that a reactor trip is not processed by one of the four affected Reactor
Protective System (RPS) trips?
A. Bypass each of the four affected RPS trip units in all four channels
B. Insert and turn a ZPM channel bypass key in at least 3 out of 4 channels
C. Bypass at least one of the four affected RPS trip units in all four channels
D. Insert and turn a ZPM channel bypass key in as least 2 out of 4 channels

Answer 28

B. Insert and turn a ZPM channel bypass key in at least 3 out of 4 channels

Question 29

Which ONE of the following conditions would not allow insertion of the Zero Power
Mode (ZPM) Bypass?
A. Reactor Power

Answer 29

B. PCS [B] 50 ppm below estimated critical conditions

Question 30

Which ONE of the following conditions must be satisfied in order to place the Zero
Power Mode bypass in operation?
A.Primary Coolant System boron concentration greater than Cold Shutdown boron
concentration
B. Steam Generator Pressure greater than 512 psia
C. Reactor Power 1E-4% to 15%
D. PCS Pressure 2020 to 2100 psia

Answer 30

A.Primary Coolant System boron concentration greater than Cold Shutdown boron
concentration

Question 31

Which ONE of the following conditions would remove the Zero Power Mode (ZPM)
Bypass?
A. Reactor Power 1 E-4% and rising
D. ZPM Bypass test push buttons depressed

Answer 31

C.Reactor Power >1 E-4% and rising

Question 32

Which ONE of the following conditions would remove the Zero Power Mode (ZPM)
bypass?
A. Lower reactor power to less than 1E-4%
B. Raise Steam Generator Pressure to greater than 512 psia
C. Turn ZPM keyswitch counterclockwise and remove the key for each of the four
channels
D. Start at least one Primary Coolant Pump

Answer 32

C. Turn ZPM keyswitch counterclockwise and remove the key for each of the four
channels

Question 33

During a plant startup, the following conditions exist:
• The crew has taken actions to change Plant mode to MODE 2.
• The NCO was directed to remove all channels of Zero Power Mode (ZPM)
Bypass from operation, but has NOT taken any action.
• All keyswitches for ZPM Bypass are still in the enabled position (fully clockwise).
• Reactor power has risen to 1OE-3% on all available indications.
• “A” Steam Generator (S/G) level has lowered to 24%.
What are the consequences of the above plant conditions?
A. The Reactor has NOT tripped, but it would trip if the ZPM Bypass enable
keyswitches were operated to the disable position (fully counterclockwise)
B. The Reactor has NOT tripped, and it would NOT trip even if the ZPM enable
keyswitches were operated to the disable position (fully counterclockwise).
C. The Reactor has tripped since the ZPM Bypass was automatically removed when
“A” S/G level lowered to 30%.
D The Reactor has tripped since the ZPM Bypass was automatically removed when
Reactor power reached 10E-4%.

Answer 33

D The Reactor has tripped since the ZPM Bypass was automatically removed when
Reactor power reached 10E-4%.

Question 34

RPS E02.05004
During a plant startup, the following conditions exist:
The crew has taken actions to change Plant mode to MODE 2.
The NCO was directed to remove all channels of Zero Power Mode (ZPM) Bypass
from operation, but has NOT taken any action.
All keyswitches for ZPM Bypass are still in the enabled position (fully clockwise).
Reactor power has risen to 10E-3% on all available indications.
“A” Steam Generator (S/G) level has lowered to 24%.
What are the consequences of the above plant conditions?
A. The Reactor has tripped since the ZPM Bypass was automatically removed when
Reactor power reached 10E-4%.
B. The Reactor has NOT tripped, but it would trip if the ZPM Bypass enable
keyswitches were operated to the disable position (fully counterclockwise).
C. The Reactor has NOT tripped, and it would NOT trip even if the ZPM enable
keyswitches were operated to the disable position (fully counterclockwise).
D. The Reactor has tripped since the ZPM Bypass was automatically removed when
“A” S/G level lowered to 30%.

Answer 34

A. The Reactor has tripped since the ZPM Bypass was automatically removed when
Reactor power reached 10E-4%.
CORRECT - per the given reference, the ZPM Bypass function is automatically
removed by the Nls when Reactor power is ~ 10-4%. Given S/G level is below
RPS trip setpoint.

Question 35

The Zero Power Mode (ZPM) Bypass test push buttons should only be depressed one
at a time in order to:
A. ensure ZPM bypass automatic removal is enabled.
B. preclude generating a false RPS trip enabled indication.
C. verify ZPM ‘Auto Disable’ and ‘SW’ lamps are operable.
D. prevent generation of an inadvertent reactor trip.

Answer 35

D. prevent generation of an inadvertent reactor trip

Question 36

During testing of the Zero Power Mode (ZPM) bypass following placing the system in
service, the operator inadvertently presses two ZPM test push buttons simultaneously.
What are the potential consequences?
A. May result in a Reactor Protective System (RPS) trip
B. May damage the two affected ZPM channels
C. May not provide accurate readout on the status of either of the affected ZPM
channels
D. May remove the ZPM bypass from service for all four channels

Answer 36

A. May result in a Reactor Protective System (RPS) trip

Question 37

Given the following conditions:
• During normal full power operations the ‘A’ Channel S/G #1 Low Pressure input
to the Reactor Protection System (RPS) exhibits erratic indication and its trip unit
is bypassed.
• 7 days later it is determined that the pressure transmitter is INOPERABLE and
CANNOT be repaired until the next outage.
The ‘A’ Channel RPS S/G #1 Low Pressure trip unit should be:
A. restored to operable status.
B. declared inoperable and left in bypass.
C, placed in the trip condition.
D. unbypassed to allow the trip unit to trip.

Answer 37

C, placed in the trip condition.

Question 38

Which ONE of the following describes a condition under which the Reactor Protection
System (RPS) channellB” Pressurizer High Pressure trip unit would be either tripped
or bypassed?
A. Pressurizer pressure instrument PIA-01 02BLL is reading about 2 psia higher than
the other 3 channels.
B. RPS ChannellA” Pressurizer High Pressure trip unit has been bypassed and this
will maintain a two out of three trip logic.
C. RPS ChannellB” Thermal Margin Monitor, which uses PCS pressure as one input
to determine the Thermal Margin/Low Pressure setpoint, is being calibrated.
D. Pressurizer pressure instrument PIA-01 02BLL is erratic and is declared inoperable.

Answer 38

D. Pressurizer pressure instrument PIA-01 02BLL is erratic and is declared inoperable

Question 39

During normal full power operations NI-1/3 High Start-Up Rate (SUR) trip input to the
Reactor Protection System (RPS) Channel ‘C’ fails high. I&C has requested
de-energizing NI-1/3 to facilitate troubleshooting.
This activity should …
A. be allowed. The High SUR trips are automatically bypassed.
B. not be allowed. It will violate Tech Specs for NI operability.
C. be allowed. Both High SUR trips can be manually bypassed.
D. not be allowed. It would generate an inadvertent reactor trip.

Answer 39

A. be allowed. The High SUR trips are automatically bypassed.

Question 40

During a reactor startup with reactor power at 2% NI-1/3 High Startup Rate (SUR) trip
input to the Reactor Protective System (RPS) channel “C” fails high. I&C has
requested de-energizing NI-1/3 to facilitate troubleshooting.
This activity should …
A be allowed. The High SUR trips are enabled. Bypassing one channel leaves a 2
out of 3 logic.
B. not be allowed. It will violate Technical Specification requirements for operability.
C. be allowed. High SUR trips are automatically bypassed less than 15% power.
D. not be allowed. Since NI-1/3 supplies a signal to two RPS trip units, it would
generate a reactor trip.

Answer 40

A be allowed. The High SUR trips are enabled. Bypassing one channel leaves a 2
out of 3 logic

Question 41

Which ONE of the following is the proper method for placing a Reactor Protection
System trip unit in the trip condition?
A. Remove the P1 plug from the back of the individual trip unit.
B. Withdraw the trip unit at least two inches from the front panel.
C. Insert the Trip Bypass key and turn it 90° counterclockwise.
D. Open the interconnection module on the back of the trip unit.

Answer 41

B. Withdraw the trip unit at least two inches from the front panel.

Question 42

Which ONE of the following is the proper method for untripping a Reactor Protection
System trip unit that had been manually tripped?
A. Turn the Trip Bypass key 90° clockwise and remove it.
B. Reinstall the P1 plug on the back of the individual trip unit.
C. Reinsert the trip unit until it is flush with the front panel.
D. Close the interconnection module on the back of the trip unit

Answer 42

C. Reinsert the trip unit until it is flush with the front panel.

Question 43

Which ONE of the following describes proper actions for placing a manually tripped
Reactor Protective System (RPS) trip unit back in service?
A. Turn the RPS bypass keyswitch 90° counterclockwise. Remove key. Reset RPS
trip light.
B.Insert RPS trip unit until flush with panel. Tighten screws. Reset RPS trip light.
C. Insert RPS bypass key. Turn keyswitch 90° clockwise. Reset RPS trip light.
D. Insert RPS trip unit until flush with panel. Tighten screws. Reset RPS trip light.

Answer 43

B.Insert RPS trip unit until flush with panel. Tighten screws. Reset RPS trip light.

Question 44

When a Reactor Protection System (RPS) trip unit is placed in trip the RPS Matrix
Logic Ladder trip coincidence is:
A. one out of four.
B. two out of four.
C. one out of three.
D. one out of six.

Answer 44

D. one out of six

Question 45

Given:
• One failed high pressurizer pressure RPS trip channel has been BYPASSED
• A second high pressurizer pressure trip channel has failed HIGH but NO other
action has been taken.
Which ONE of the following is correct?
A. Reactor has tripped.
B. Reactor trip logic is 1-out-of-3.
C. Reactor trip logic is 2-out-of-3.
D. Reactor trip logic is 1-out-of-2.

Answer 45

A. Reactor has tripped.

Question 46

The method by which Palisades provides an independent and diverse reactor trip is
the:
A. anticipated Transient Without Scram circuitry.
B. manual reactor trip pushbutton on the EC-02 panel.
C. loss of Load and High Start-up Rate trip signals.
D. manual reactor trip via the CROM clutch toggle switches.

Answer 46

A. anticipated Transient Without Scram circuitry

Question 47

Given a plant condition in which the Reactor Protection System should have processed
a reactor trip, but failed to do so, a reactor trip may still be achieved. All but one of the
following describe a means of accomplishing the reactor trip in this situation. Which
ONE is the exception?
A. Manually trip the reactor from Control Room panel C-06 using the Reactor Trip
Pushbutton.
B. Manually trip the reactor from the Cable Spreading Room using the breakers
RPS/42-1 and RPS/42-2.
C. Automatically trip the reactor using the Anticipated Transient Without Scram
(ATWS) trip.
D. Automatically trip the reactor using the Turbine Trip push button in the Control
Room

Answer 47

D. Automatically trip the reactor using the Turbine Trip push button in the Control
Room

Question 48

Title 10 of the Code of Federal Regulations Part 50.62 requires pressurized water
reactors to have a diverse method for mitigating the consequences of an operational
transient accompanied by a failure of the Reactor Protection System.
Palisades accomplished this by installing and/or modifying which of the following
automatic actuation systems?
A. Safety Injection System and Aux Feed Actuation System.
B. Aux Feed Actuation System and Anticipated Transient Without Scram.
C. Reactor Protection System and Safety Injection System.
D. Anticipated Transient Without Scram and Reactor Protection System

Answer 48

B. Aux Feed Actuation System and Anticipated Transient Without Scram.

Question 49

Which ONE of the following describes why the Anticipated Transient Without Scram
(ATWS) trip circuitry is considered “diverse.”
A.ATWS equipment is independent of the Reactor Protective System from sensor to
final actuation device.
B. ATWS trip logic is developed from a different parameter than any of the Reactor
Protective System trips.
C. ATWS circuitry uses a different mathematical logic than the Reactor Protective
System.
D. ATWS trip logic may be made up from more than one of several diverse
paramenters.

Answer 49

A.ATWS equipment is independent of the Reactor Protective System from sensor to
final actuation device.

Question 50

For a Loss of Load event, which one of the following describes the impact of a failure
of the Reactor Protection System to automatically trip the reactor, and what procedure
is used to mitigate the condition?
(Assume NO operator action.)
Pressurizer pressure rises to …
A. 2235 psia and the reactor automatically trips. Implement EOP-1.0, “Standard Post
Trip Actions”.
B. 2235 psia and the reactor automatically trips. Implement EOP-9.0, “Functional
Recovery Procedure”.
C. 2375 psia and the reactor automatically trips. Implement EOP-1.0, “Standard Post
Trip Actions”.
D. 2375 psia and the reactor automatically trips. Implement EOP-9.0, “Functional
Recovery Procedure”.

Answer 50

C. 2375 psia and the reactor automatically trips. Implement EOP-1.0, “Standard Post
Trip Actions”
a. Incorrect pressure, correct procedure.
b. Incorrect pressure, incorrect procedure. Candidate believes an ATWS warrants
functional recovery entry.
c. CORRECT - Correct pressure and procedure.
d. Correct pressure, incorrect procedure. Candidate believes an ATWS warrants
functional recovery entry.