RPS 1

Question 1

Which ONE of the following describes a purpose of the automatic High Rate of Change
of Power reactor trip?
A. To protect against exceeding Technical Specification limits on thermal power.
B. To protect against operators starting up the reactor too fast.
C.To protect against an uncontrolled rod withdrawal.
O. To protect against an excessive feedwater event at low power

Answer 1

C’:’“To protect against an uncontrolled rod withdrawal.

Question 2

Which ONE of the following describes a purpose of the automatic High Rate of Change
of Power reactor trip?
A. To protect against exceeding Technical Specification limits on thermal power.
B. To protect against a boron dilution event while the reactor is critical at low power.
C. To protect against operators exceeding power escalation rate limits.
D. To protect against an excessive feedwater event at low power.

Answer 2

B~ To protect against a boron dilution event while the reactor is critical at low power

Question 3

Which ONE of the following describes the purpose of the automatic Low Reactor
Coolant Flow reactor trip?
A.To prevent possible fuel damage as a result of a loss of coolant flow.
B. To ensure the reactor is tripped in the event of a Loss of Coolant Accident.
C. To protect the fuel from debris in the event that a Primary Coolant Pump should fail.
D. To enable operators to more easily establish natural circulation cooling during
EOP-1.0 “Standard Post Trip Actions

Answer 3

A.To prevent possible fuel damage as a result of a loss of coolant flow

Question 4

Which ONE of the following describes the purpose of the automatic High Pressurizer
Pressure reactor trip?
A. To prevent operation of the Primary Relief valves.
B. To prevent pressurized thermal shock of the reactor vessel.
C. To prevent a loss of coolant accident when the pressure limit of the most limiting
Primary Coolant System component is exceeded.
D To prevent operation when the reactor is generating more power than the
secondary side is accepting.

Answer 4

D To prevent operation when the reactor is generating more power than the
secondary side is accepting

Question 5

Which ONE of the following describes the purpose of the automatic Low Steam
Generator Level reactor trip?
A. To initiate a reactor trip in anticipation of a Pressurizer High Pressure Trip.
B. To prepare the Primary Coolant System for Auxiliary Feedwater actuation.
C To initiate a reactor trip on a loss of steam generator heat removal capability.
D To prevent operation in a condition conducive to steam generator tube ruptures.

Answer 5

C To initiate a reactor trip on a loss of steam generator heat removal capability

Question 6

Which ONE of the following describes the purpose of the automatic Low Steam
Generator Pressure reactor trip?
A. To prevent operation when the reactor is generating more power than the
secondary side is accepting.
B. To protect against excessively high steam flow caused by a steam line break.
C To prevent operation in a condition conducive to steam generator tube rupture.
D. To protect against exceeding Technical Specification limits on thermal power.

Answer 6

B. To protect against excessively high steam flow caused by a steam line break.

Question 7

Which ONE of the following describes the purpose of the automatic Thermal
Margin/Low Pressure reactor trip?
A To prevent the violation of the minimum Departure from Nucleate Boiling Ration
(DNBR) condition.
B. To ensure the reactor is tripped in the event of a loss of coolant accident.
C. To protect against excessively high steam flow caused by a steam line break.
D. To prevent operation when the reactor is generating more power than the
secondary side is accepting

Answer 7

A To prevent the violation of the minimum Departure from Nucleate Boiling Ration
(DNBR) condition

Question 8

Which ONE of the following describes the purpose of the automatic Loss of Load
reactor trip?
A. To ensure the reactor is tripped in the event of a loss of coolant accident.
B. To protect against excessively high steam flow caused by a steam line break.
C. To prevent the violation of the minimum Departure from Nucleate Boiling Ration
(ONBR) condition.
D To limit the energy and pressure stored in the Primary Coolant System caused by a
suspension of normal steaming of the steam generators

Answer 8

D To limit the energy and pressure stored in the Primary Coolant System caused by a
suspension of normal steaming of the steam generators

Question 9

Which ONE of the following describes the purpose of the automatic Containment High
Pressure reactor trip?
A. To ensure the reactor is tripped should Primary Relief valves actuate.
B. To provide a backup trip for the Pressurizer High Pressure trip.
C.To provide a diverse trip with an earlier action than would be available with only a
thermal margin/low pressure trip, or steam generator low pressure trip.
D. To protect the Containment fission product barrier against an over-pressurization
which would challenge the containment structure.

Answer 9

C.To provide a diverse trip with an earlier action than would be available with only a
thermal margin/low pressure trip, or steam generator low pressure trip.

Question 10

Which ONE of the following describes the reason that there is a manual reactor trip
capability?
A. Due to the limited reliability of the Reactor Protective System (RPS)
B. To provide an alternative to installing an automatic trip on Nuclear Flux Axial Shape
(ASI).
C.To provide the operator the capability to promptly shut down the reactor
D. Designers could not economically calculate setpoints for all desired reactor trip
parameters.

Answer 10

C.To provide the operator the capability to promptly shut down the reactor

Question 11

Each RPS trip unit and auxiliary trip unit provides …
A. three outputs to the RPS matrix logic.
B. an adjustment potentiometer to calibrate its setpoint.
C. an internal battery to prevent momentary power interruptions from initiating a
reactor trip.
D. sufficient outputs to the RPS matrix logic to initiate a reactor trip by itself.

Answer 11

A. three outputs to the RPS matrix logic.

Question 12

Which ONE of the Reactor Protection System Pre-trips will generate a Rod Withdrawal
Prohibit on one-out-of-four trip logic?
A. Variable High Power.
B. Thermal Margin/Low Pressure.
C. High Start Up Rate.
D. High Pressurizer Pressure.

Answer 12

C. High Start Up Rate.

Question 13

RPS CK06.0 002
The Reactor Protective System (RPS) K relays are located on the DC side of the
Clutch Power Supplies. Which ONE of the following describes a purpose of these
relays?
A. To interface with the 4160 VAC feeder breakers, initiating Bus 1A and Bus 1B fast
transfer on a reactor trip.
B. To interface with Control Rod Drives, initiating control rod rundown on a reactor trip.
C. To ensure that the RPS breakers RPS/42-1 and RPS/42-2 trip on a reactor trip.
D.To turn on the red “trip” light for each of the four RPS channels on panel C-06.

Answer 13

B. To interface with Control Rod Drives, initiating control rod rundown on a reactor trip

Question 14

The Anticipated Transient Without Scram Trip Relay is powered from ...
A. Y-10 and Y-20.
B. 0-11-1.
C. Y-30 and Y-40.
D. Y-230A.

Answer 14

D. Y-230A.

Question 15

Which ONE of the following are the power supplies for the Reactor Protective System
(RPS) BC Logic Matrix?
A. Y-10 and Y-20
B. Y-20 and Y-30
C. Y-10 and Y-40
D. Y-20 and Y-40

Answer 15

B. Y-20 and Y-30

Question 16

Which ONE of the following are the power supplies for the ATWS Matrix Relays and
ATWS 2/4 Actuation Matrix Circuitry?
A. Preferred AC buses Y-30 and Y-40, respectively
B. Lighting panels L-58 and L-59, and bus Y-230 from battery D-205
C. Lighting panel L-01 and Instrument AC bus Y-01, respectively
D. DC buses D11-1 and D11-2, respectively

Answer 16

B. Lighting panels L-58 and L-59, and bus Y-230 from batteryD-205

Question 17

Which of the following are the power supplies for the Reactor Protection System BC
logic matrix?
A. Y-10 and Y-30
B. Y-10 and Y-40
C. Y-20 and Y-30
D. Y-20 and Y-40

Answer 17

C. Y-20 and Y-30

Question 18

Given the following plant conditions:
The reactor is critical in MODE 2 at 1% power
Auxiliary Feedwater (AFW) Pump P-8C is operating
DC Bus D11-1 loses power
Which ONE of the following will occur?
A. AFW Pump P-8C will remain operating and AFW Pump P-8A will start.
B. AFW Pump P-8C will trip and AFW Pump P-8B will start.
C. The reactor will automatically trip.
D AFW Pump P-8C will remain operating and AFW Pump P-8B will start.

Answer 18

D AFW Pump P-8C will remain operating and AFW Pump P-8B will start
Loss of 011-1 causes auto start of P-8B via A TWS design. No effect on P-8A or C or
the reactor.
Monday,

Question 19

The manual method of tripping the reactor from the Control Room that is electrically
different than the automatic Reactor Protection System (RPS) trip is the:
A. Manual Reactor Trip push button on EC-02.
B. Manual Reactor Trip push button on EC-06.
C. Manual Turbine Trip push button.
D. RPS Circuit Breakers 42-1 and 42-2.

Answer 19

B. Manual Reactor Trip push button on EC-06.

Question 20

The manual method of tripping the reactor that is electrically the same as the automatic
Reactor Protection System (RPS) trip is the …
A. manual push button on control panel C-06.
B. CRDM Clutch Power toggle switches in control panel C-06.
C. RPS Breakers 42-1 and 42-2 in the Cable Spreading Room.
D.manual push button on control panel C-02.

Answer 20

D.manual push button on control panel C-02.

Question 21

From power operations, a transient occurs that requires the operators to manually trip
the reactor. The manual pushbutton methods of tripping the reactor (on Panels C-02
and C-06) have NOT been successful and the operators have determined that the
following action is required:
• OPEN CRD Clutch Power Feeder Breakers 42-1 RPS and 42-2RPS.
When 42-1 RPS and 42-2RPS are opened, which one of the following indications do
the control operators expect to see in the Control Room, including indicating lamps on
individual Clutch Power Supply panels (Panel C-06), and the RED tile annunciator for
EK-0972, Reactor Trip, on panel C-12?
PANEL C-06 C-12
AC ON DC ON TRIP EK-0972
WHITE WHITE RED RED TILE

A. OFF OFF OFF ON
B. ON OFF ON OFF
C. OFF OFF ON ON
D. ON OFF OFF OFF

Answer 21

C. OFF OFF ON ON
EK-0972, “Reactor Trip,” Vendor Drawing M1Q 114,
a. INCORRECT - Plausible if the student believes that the red “trip” light is powered from downstream of RPS
breakers 42-1 and 42-2.
b. INCORRECT - Plausible if the student believes that the “AC” and red “trip” lights are powered from upstream
of RPS breakers 42-1 and 42-2.
c. CORRECT
d. INCORRECT - Plausible if the student believes that the “AC” and K3 are powered from upstream of RPS
breakers 42-1 and 42-2.

Question 22

Refer to the attached Functional Block Diagram of the Reactor Protection System.
The trip logic for the Matrix Logic Ladders is:
A. two out of four.
B. one out of six.
C. two out of six.
D. one out of two.

Answer 22

B. one out of six

Question 23

The Reactor Trip from Steam Generator Low Level is calibrated to occur at:
A. 31.0%.
B. 28.0%.
C. 26.9%.
D. 25.9%.

Answer 23

B. 28.0%

Question 24

Which ONE of the following describes the loss of load and rate of change of power
RPS trips?
A. The loss of load trip bypass is enabled above 15% power and the rate of change of
power trip bypass is inserted above 15% by the wide range Nls.
B. The loss of load trip is bypassed below 15% power by the power range Nls and the
rate of change of power channel trip is inserted below 15% power by the wide range
Nls.
C. The loss of load trip is enabled above 15% power and the rate of change of power
trip is bypassed above 15% power by the power range Nls.
D. The loss of load trip is bypassed below 15% power by the wide range Nls and the
rate of change of power trip is inserted below 15% power by the power range Nls.

Answer 24

C. The loss of load trip is enabled above 15% power and the rate of change of power
trip is bypassed above 15% power by the power range Nls.

Question 25

The reactor trip due to Pressurizer High Pressure is calibrated to occur at. ..
A. 2100 psia
B. 2375 psia
C. 2500 psia
D. 2235 psia

Answer 25

D. 2235 psia

Question 26

Reactor Power is being held at 10% due to a chemistry sample problem. During the
hold a SR/WR NI-1/3A detector HV power supply amplifier malfunction causes the
output to fail high. The consequences of this failure will be…
A. VHPT on 1 of 4 channels and the Reactor does not trip
B. VHPT on 2 of 4 channels and the Reactor trips
C. High SUR Trip on 1 of 4 channels and the Reactor does not trip
D.High SUR Trip on 2 of 4 channels and the Reactor trips

Answer 26

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

Question 27

During normal full power operation, one of the Reactor Protection System (RPS) A-B
Matrix Power Supply output fuses fails open.
How will this failure impact the RPS?
A. RPS trip logic will be one out of three.
B. The reactor will trip on a loss of one logic ladder.
C. RPS trip logic will be two out of three.
D. The reactor will trip if a second power supply fails.

Answer 27

D. The reactor will trip if a second power supply fails.

Question 28

The plant is operating at 100% power. One Primary Coolant Pump trips. Reactor
Protective System (RPS) sensors detect Low PCS Flow on each of the four channels.
The trip relay contacts in the third set, AB3, AC3, A03, BC3, B03, C03, are welded
shut due to arcing. There are no other RPS failures. Which ONE of the following
describes the effect this will have on the RPS.
A. Since contact set 3 does not operate, Clutch Power Supply 3 does not de-energize
and rods 1-24 do not drop.
B. Since contact set 3 does not operate, clutch Power Supplies 3 and 4 are not
energized resulting in a “half trip.”
C.Since contact sets 1, 2 and 4 all operate, the RPS will successfuly process the
reactor trip.
D. Since contact sets 1, 2 and 4 all operate, the RPS is now in one out of three logic
for a reactor trip.

Answer 28

C.Since contact sets 1, 2 and 4 all operate, the RPS will successfuly process the
reactor trip.

Question 29

What would the impact be of a failure of the Reactor Protection System Clutch Power
Supply arc suppression network?
A. Matrix Relay contacts may fail CLOSED thereby creating a future ATWS.
B. Overcurrent damage to the Preferred AC Bus inverter transformers.
C. Mechanical damage to the CRD mechanisms’ clutch faceplates.
D. Matrix Relay contacts may fail OPEN, thereby creating a future ATWS

Answer 29

A. Matrix Relay contacts may fail CLOSED thereby creating a future ATWS.

Question 30

Given the following conditions:
• The plant is operating at 11% power .
• ATWS Matrix Relay loses power.
Which ONE of the following will occur?
A. The turbine will automatically trip, but the reactor will remain critical.
B. The reactor and the turbine will automatically trip.
C. The reactor will automatically trip, but the turbine must be manually tripped.
D The reactor will remain critical and the turbine will remain on-line.

Answer 30

D The reactor will remain critical and the turbine will remain on-line.

Question 31

T •••.F A single ground on the matrix logic ladder relay power supply or CRDM clutch
AC power supply of the RPS will have no effect on AUTO/MANUAL RPS
Operation.

Answer 31

TRUE

Question 32

The plant is operating at approximately 4% power when a wide range nuclear
instrumentation channel instantaneously fails high. What effect will this failure have on
plant operation?
A. Plant must be shut down in an orderly manner until repair is made.
B. Power must be held constant at its present level until the channel is repaired.
C. Plant will trip on high startup rate.
D. Plant should be shut down by manually tripping.

Answer 32

C. Plant will trip on high startup rate

Question 33

How will a single ground on the Clutch Power Supply Power Trip Relay CM’ Coil) circuit
affect operation of the Reactor Protection System?
A. The arc suppression network may fail the next time a Reactor Trip is generated.
B. The affected Clutch Power Supply may not de-energize causing an ATWS.
C. A ‘half-trip’ will be generated from the affected RPS Clutch Power Supply only.
D. No effect until a second ground appears, at which point a ‘half-trip’ will be
generated.

Answer 33

D. No effect until a second ground appears, at which point a ‘half-trip’ will be
generated

Question 34

A single ground has occurred on the Reactor Protective System (RPS) BC Logic Matrix
circuit. Which ONE of the following describes the effect this will have on the RPS.
A. The red “hold” lights will dim and the four red “drop out” lights will brighten for each
of the four BC matrix relays.
B. One of two matrix indicating white lights for each of the four BC matrix relays will
dim and the other will brighten.
C. All four BC matrix relays will de-energize, and the RPS will process a reactor trip.
D. The matrix indicating white light, the red “hold” light, and the red “drop out” light will
dim on each of the four BC matrix relays

Answer 34

B. One of two matrix indicating white lights for each of the four BC matrix relays will
dim and the other will brighten

Question 35

A ground has occurred on the Reactor Protective System (RPS) Trip Initiation circuit.
The ground is located between the M1 coil and the RPS matrix contact CO-1.
Which ONE of the following describes how this ground would affect the RPS?
A. Lamp LT6 would dim.
B. Since the RPS Trip Initiation circuit is protected from grounds, there would be no
effect.
C. Lamp LT5 would dim.
D. The M1 coil would de-energize resulting in a “half trip” of the RPS.

Answer 35

C. Lamp LT5 would dim

Question 36

The plant is operating at 100% power. Main Turbine Autostop Oil Pressure Switch
63/AST-2 fails low. Which ONE of the following describes the effect this will have on
the Reactor Protective System (RPS)?
A. Two auxiliary relays are actuated providing input into each of the 4 Loss of Load
RPS trip units, resulting in the RPS processing a reactor trip.
B. Since only a single pressure switch has failed, only one RPS channel receives input
and no reactor trip is processed.
C. Two relay contacts are closed, provided input to two RPS channels, resulting in the
RPS processing a reactor trip.
D. Two relay contacts are closed, provided input to two RPS channels, resulting in a
“half trip.”

Answer 36

A. Two auxiliary relays are actuated providing input into each of the 4 Loss of Load
RPS trip units, resulting in the RPS processing a reactor trip.

Question 37

During a plant startup from a refueling outage the following alarm is received:
• EK-06D6, “RATE CHANNEL TRIP ENABLED”
This anunciator can be verified using instrumentation available in the Control Room by
observing:
A. NI-3 and NI-4 (Wide Range Nls) reading greater than 10-4%.
B. RPS High Startup Rate Pre-trip bistables have actuated.
C. NI-5, 6, 7 and 8 (Power Range Nls) reading greater than 15%.
D. EK-06D2, “LOSS OF LOAD TRIP CHANNEL BYPASS” not lit.

Answer 37

A. NI-3 and NI-4 (Wide Range Nls) reading greater than 10-4%.

Question 38

The white high power rate pre-trip bistable unit light on the RPS panel for channel "A"
has illuminated. The power level is 5%.
Which ONE of the following could cause the white bistable unit light to illuminate at this
power level?
A. ASI outside the COLR limits.
B. A start-up rate of 1.5 DPM.
C. A start-up rate of 0.5 DPM.
D. Axial offset outside COLR limits.

Answer 38

B. A start-up rate of 1.5 DPM.

Question 39

During a plant shutdown the following alarm is received:
• EK-06 C2, “LOSS OF LOAD TRIP CHANNEL BYPASSED”
This annunciator can be verified using instrumentation available in the Control Room
by observing …
A. Power Range Nuclear Instruments reading less than 15%
B. Wide Range Nuclear Instruments reading less than 15%
C. Wide Range Nuclear Instruments reading less than 1E-4%
D. The amber trip channel bypass light illuminated for one Loss of Load trip unit

Answer 39

A. Power Range Nuclear Instruments reading less than 15%

Question 40

During a plant shutdown the following alarm is received:
• EK-06 01, “ZERO POWER MODE BYPASS”
This annunciator can be verified using instrumentation available in the Control Room
by observing …
A. ZPM keyswitches and Power Range Nuclear Instruments.
B. ZPM keyswitches and Wide Range Nuclear Instruments.
C. Thermal Margin Monitors Nuclear/Delta T Power.
D. Variable High Power Trip Reset Pushbutton light status.

Answer 40

B. ZPM keyswitches and Wide Range Nuclear Instruments.

Question 41

Which ONE of the following conditions warrant a manual Reactor Trip?
A. Reactor Power at 105% and rising.
B. S/G level at 32% and lowering slowly.
C. Start-up Rate at 2 DPM and stable.
D. Pressurizer pressure at 2080 psia and slowly rising.

Answer 41

A. Reactor Power at 105% and rising.

Question 42

The plant is operating at 100% power. A transient occurs requiring operator
intervention to stabilize the plant. After which, operators monitor the status of the plant.
Which ONE of the following conditions, if observed at that time, warrant a manual
reactor trip?
A. Reactor power is 102% and stable
B. Pressurizer pressure is 2005 psia and stable
C. “A” Steam Generator level is 27% and stable
D. Pressurizer level is 65% and stable

Answer 42

C. “A” Steam Generator level is 27% and stable

Question 43

All but one of the following describe Technical Specification Actions which are required
to be performed within one hour or less. Which ONE is the exception?
A. If a ZPM Bypass Removal channel is inoperable in MODE 3, remove the affected
ZPM bypasses.
B. If both channel “A” and channel “B” Low Steam Generator Level trip units are
inoperable in MODE 2, trip one trip unit.
C. If one Trip Initiation Logic channel is inoperable in MODE 1, de-energize the
affected clutch power supplies.
D. If both channel “A” and channel “B” power range Nuclear Instruments are
inoperable, ensure power is less than or equal to 70% RTP.

Answer 43

D. If both channel “A” and channel “B” power range Nuclear Instruments are
inoperable, ensure power is less than or equal to 70% RTP.

Question 44

Which ONE of the following describes a Technical Specification Action which is
required to be performed within one hour or less?
A. If both channel “A” and channel “B” power range Nuclear Instruments are
inoperable, ensure power is less than or equal to 70% RTP.
B. If a ZPM Bypass Removal channel is inoperable in MODE 3, remove the affected
ZPM bypasses.
C. If both channel “A” and channel “B” Low Steam Generator Level trip units are
inoperable in MODE 1, restore one trip unit to operable.
D. If one Matrix Logic channel is inoperable in MODE 2, restore the channel to
operable.

Answer 44

B. If a ZPM Bypass Removal channel is inoperable in MODE 3, remove the affected
ZPM bypasses

Question 45

Refer to T.S. 3.3. The plant is at 100% power operations when the ‘A’ S/G level
transmitter input to the ‘B’ Channel Reactor Protection System S/G Low Level trip unit
fails low.
The Technical Specification action statement that applies is:
A.place the affected trip unit in trip within 7 days.
B. place the affected trip unit in bypass immediately.
C. restore the trip unit to operable within 7 days.
D. restrict thermal power to less than or equal to 70% of rated thermal power.

Answer 45

A.place the affected trip unit in trip within 7 days

Question 46

The Plant is presently operating at 50% power. RPS “A” channel Variable High Power,
TM/LP, High Power Rate and Loss of Load trip units are bypassed due to a failed
power supply to the upper detector of NI-05. What is required to be done if the power
supply cannot be fixed in seven days?
A. The reactor shall be placed in Mode 3 within 6 hours and the reactor shall be
placed in a condition where the affected equipment is not required within 48 hours.
B. Place the channel “A” Variable High Power, TM/LP, High Power Rate and Loss of
Load trip units in the trip condition.
c. Restore the inoperable channels to operable status prior to the next reactor
start-up.
D. Place the Variable High Power and TM/LP trip units in the trip condition.

Answer 46

D. Place the Variable High Power and TM/LP trip units in the trip condition.

Question 47

During normal full power operations one of the Reactor Protection System Arc
Suppression Network voltmeters is noted to be reading a VAC. Further troubleshooting
reveals one of the Matrix Relay contacts to the M-1 Power Trip Relay coil is failed
closed.
The Technical Specification action statement that applies is:
A. restore the Matrix Logic channel to operable within 48 hours.
B. de-energize the affected clutch power supplies within one hour.
C. restore the Trip Initiation Logic to operable within 48 hours.
D. de-energize the affected clutch power supplies immediately.

Answer 47

A. restore the Matrix Logic channel to operable within 48 hours.

Question 48

During normal full power operations, a red matrix light on channel “A” Loss of Load Trip
has illuminated for no apparent reason. After some analysis it is determined that all
input sensor channels to all channels of Loss of Load Trip are operational, but there is
a failure in the “A” trip unit itself. “A” channel Loss of Load is declared inoperable.
The Technical Specification Action statement that applies is:
A. No TS Action is applicable since there is no applicable LCO for Loss of Load in
MODE 1.
B. Restore to operable within 48 hours.
C. Restore to operable prior to being equal to or greater than 17% RTP following
MODE 3.
D. Restore to operable within 7 days.

Answer 48

C. Restore to operable prior to being equal to or greater than 17% RTP following
MODE 3.

Question 49

(SRO Only)
Which ONE of the following Reactor Protection System trips protects the Primary
Coolant System from a rapid, uncontrolled cooldown?
A. Low PCS Flow
B. Low S/G Level
C. Low S/G Pressure
D. Loss of Load

Answer 49

C. Low S/G Pressure

Question 50

(SRO Only)
Which ONE of the following Reactor Protection System trips is an anticipatory trip used
to prevent lifting the pressurizer and main steam safety valves?
A. High PCS Pressure
B. Low S/G Level
C. Low S/G Pressure
D. Loss of Load

Answer 50

D. Loss of Load