RPS 3 Flashcards

1
Q

Which ONE of the following describes how the Anticipated Transient Without Scram
trip signal is developed?
A. The two out of four, de-energize-to-trip signals occur on high Pressurizer Pressure
at 2375 psia.
B. The one out of four, energize-to-trip signal occurs on high-high Pressurizer
Pressure at 2375 psia.
C. The two out of four, energize-to-trip signals occur on high-high Pressurizer Pressure
at 2375 psia.
D. The two out of four, de-energize-to-trip signals occur on high Pressurizer Pressure
at 2235 psia.

A

C. The two out of four, energize-to-trip signals occur on high-high Pressurizer Pressure
at 2375 psia

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2
Q
Following a loss of 120 VAC Preferred Bus Y-20, the Anticipated Transient Without
Scram (ATWS) System trip logic is:
A. 1-out-of-3.
B. 2-out-of-3.
C. 1-out-of-4.
D. 2-out-of-4.
A

B. 2-out-of-3

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3
Q

Given the following:
• Plant is at 100% power
• Preferred AC Bus Y-30 was lost 5 minutes ago
• No operator actions have been taken to address the loss ofY-30
If Anticipated Transient Without Scram (ATWS) pressure sensor PSA-0102BHH were to fail
high, which of the following describes the effect?
A. ATWS trip logic will be 1-out-of-2
B. ATWS trip logic will be 2-out-of-3
c. ATWS will cause auto reactor trip
D. ATWS trip logic will be 1 out-of-3

A

A. ATWS trip logic will be 1-out-of-2
SOP-36 section 7.5.1: ATWS is energized to trip. Loss of one channel due to loss ofY-30
results in needing 2 other channels to trip … one of these would be the failed high pressure
sensor. Therefore, only need one of the remaining two to trip.

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4
Q

Under what conditions may the Anticipated Transient Without Scram (ATWS) trip be
bypassed?
A. Pressurizer Pressure bistable trip unit fails high.
B. Annunciator EK-06D5, “ATWS TROUBLE/TRIP” alarms.
C. Thermal Margin/Low Pressure trip unit fails low.
D. PCS Pressure sensor input to ATWS fails high.

A

D. PCS Pressure sensor input to ATWS fails high

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5
Q

Given that ATWS is operable.
Which ONE of the following describes a condition under which the Anticipated
Transient Without Scram (ATWS) trip may be bypassed?
A. Reactor power is less than or equal to 25%
B. Maintenance is required to be performed on Pressurizer Pressure channel
P-0102AHH.
C. Steam driven Auxiliary Feedwater Pump, P-88, is inoperable.
D. Pressurizer Pressure channel P-0102AHH failed high and ATWS was bypassed 8
days ago

A

B. Maintenance is required to be performed on Pressurizer Pressure channel
P-0102AHH.

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6
Q

The Reactor Protection System (RPS) Trip Unit Red Matrix lamps may only be
replaced as part of a planned work activity in order to prevent:
A. a shorted bulb causing a reactor trip from a loss of two Matrix Logic Ladder power
supplies.
B. grounding an RPS trip unit causing a potential for an Anticipated Transient Without
Scram.
C. a shorted bulb from rendering a trip unit inoperable causing unplanned entry into a
Tech Spec action.
D. personnel injury from the electrical shock hazard associated with a shorted
component.

A

A. a shorted bulb causing a reactor trip from a loss of two Matrix Logic Ladder power
supplie

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7
Q

The Reactor Protection System (RPS) Trip Unit Red Matrix lamps may only be
replaced as part of a planned work activity in order to prevent:
A. a shorted bulb causing a reactor trip from a loss of two Matrix Logic Ladder power
supplies.
B. grounding an RPS trip unit causing a potential for an Anticipated Transient Without
Scram.
C. an unplanned Action Statement entry due to rendering a trip unit inoperable.
D. personnel injury from the electrical shock hazard associated with a shorted
component.

A

A. a shorted bulb causing a reactor trip from a loss of two Matrix Logic Ladder power
supplies.
b. INCORRECT - Plausible because the RPS is designed to operate as an ungrounded system. The matrix
lights also serve as ground detection circuits.
c. INCORRECT - Plausible if the student believes that removing a matrix lamp causes the trip unit to be
inoperable.
d. INCORRECT - Plausible because many components of the RPS operate at voltages >50V.

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8
Q
Which ONE 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
A

C. Y-20 and Y-30

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9
Q

Given the following plant conditions:
• The plant is at 100% power
• Preferred AC Bus Y-30 de-energizes
Which ONE of the following describes the resulting status of an RPS component?
A. Clutch Power Supplies 1 and 3 are de-energized, and the Clutch DC Buses are
de-energized.
B.Clutch DC Power Supplies 1 and 3 are de-energized, but the Clutch DC Buses are
still powered.
C. Matrix logics AC, BC and CD are de-energized.
D. Channel C RPS trip units remain energized.

A

B.Clutch DC Power Supplies 1 and 3 are de-energized, but the Clutch DC Buses are
still powered

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10
Q

Given the following plant conditions:
• The plant is in MODE 3.
• Two Primary Coolant Pumps are operating.
• The plant is in the process of being taken to MODE 2.
Which ONE of the following describes whether the RPS may be placed in service?
A. The RPS may be placed in service in preparation for MODE 2 entry under the
above conditions.
B. The RPS may be placed in service in preparation for MODE 2 entry if the Zero
Power Mode bypass is in service.
C. The RPS may not be placed in service in preparation for MODE 2 entry until T-ave
is greater than 525°F.
D. The RPS may not be placed in service in preparation for MODE 2 entry until the last
two Primary Coolant Pumps have been started

A

D. The RPS may not be placed in service in preparation for MODE 2 entry until the last
two Primary Coolant Pumps have been started

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11
Q

In which ONE of the following conditions would the RPS be placed in service?
A. The plant is in MODE 3 heading for MODE 4 with all 4 Primary Coolant Pumps
operating.
B. The plant is in MODE 3 heading for MODE 4 with 2 Primary Coolant Pumps
operating.
C. The plant is in MODE 3 heading for MODE 2 with all 4 Primary Coolant Pumps
operating.
D. The plant is in MODE 3 heading for MODE 2 with 2 Primary Coolant Pumps
operating.

A

C. The plant is in MODE 3 heading for MODE 2 with all 4 Primary Coolant Pumps
operating.

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12
Q
Which Reactor Protection System (RPS) Bypass is automatically removed when
reactor power rises >1 E-4%?
A. Trip Channel Bypass
B. ZPM Bypass
C. Automatic Bypass
D. ATWS Bypass
A

B. ZPM Bypass

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13
Q

All but one of the following conditions would require bypassing a Reactor Protection
System (RPS) trip unit, Which ONE of the following is the exception?
A. Pressurizer Pressure input to ‘A’ Channel RPS becomes erratic.
B. Power Range NI-006 output to ‘B’ Channel RPS is questionable.
C.TM/LP input to ‘C’ Channel RPS has been inoperable for 7 days.
D. ‘B’ S/G Low Pressure input to ‘0’ Channel RPS is inoperable.

A

C.TM/LP input to ‘C’ Channel RPS has been inoperable for 7 days

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14
Q

Which ONE of the following conditions would require bypassing a Reactor Protective
System (RPS) trip unit?
A. During low power physics testing, momentary high start-up rates are sometimes
observed.
B. Channel “A” Pressurizer High Pressure input to the RPS has been inoperable for
more than 7 days.
C. Channel “A” TM/LP trip unit must be physically removed from the RPS rack for
maintenance.
D. Turbine trip testing is being performed while the reactor is being maintained critical
at low power.

A

C. Channel “A” TM/LP trip unit must be physically removed from the RPS rack for
maintenance.

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15
Q

Which ONE of the following conditions would require a Senior Reactor Operator to N/A
the procedure step to “VERIFY lit yellow light above bypass keyswitch” when bypassing
a Reactor Protection System (RPS) trip unit?
A. A trip unit is being bypassed due to 2 out of 3 of its red matrix LEDs being
locked-in.
B. Bypassing is being done to render a trip unit inoperable for I&C maintenance.
C. A trip unit is being bypassed prior to manually tripping it to comply with T.S. 3.3.1.
D. Trip units are being bypassed due to a loss of Preferred AC power to an RPS
channel.

A

D. Trip units are being bypassed due to a loss of Preferred AC power to an RPS
channel.

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16
Q

Which ONE of the following describes the process for trip unit bypass?
A. Depress and hold the RPS reset push button; verify amber light above trip unit is
OFF.
B. Depress and hold the RPS reset push button; verify amber light above trip unit is lit.
C.. Insert RPS trip unit bypass key in keyswitch and turn; verify amber light above trip
unit is OFF.
D.Insert RPS trip unit bypass key in keyswitch and turn; verify amber light above trip
unit is lit.

A

D.Insert RPS trip unit bypass key in keyswitch and turn; verify amber light above trip
unit is lit

17
Q

How does Palisades prevent bypassing more than one of the same Reactor Protection
System (RPS) monitored parameter trip units at the same time?
A. Strict procedural compliance would prevent bypassing more than one monitored
parameter trip unit at a time.
B. The trip unit for each parameter of the RPS has a unique lock for which there is
only one normally accessible key.
C. Technical Specifications do not allow bypassing more than one at a time.
D. Matrix logic prevents disabling the other trips when any trip is bypassed.

A

B. The trip unit for each parameter of the RPS has a unique lock for which there is
only one normally accessible key.

18
Q

Reactor Protective System (RPS) channel “A” Pressurizer High Pressure trip unit has
been bypassed and removed from the RPS panel for maintenance. Operators
determine that PT-0102C is out of calibration and declare it and its associated RPS trip
channel inoperable. It has been 3 days since channel “A” was bypassed.
Which ONE of the following actions can be performed in response while waiting for
maintenance to make repairs?
A. One channel Pressurizer High Pressure bypassed, either “A” or “C,” the other is
tripped. Then perform orderly shutdown per Technical Specification if required.
B. Bypass both “A” and “C” channels of Pressurizer High Pressure. Then perform
orderly shutdown per Technical Specification if required.
C. Trip both “A” and “C” channels of Pressurizer High Pressure. Then perform orderly
shutdown per Technical Specification if required.
D. Bypass 3 out of 4 Pressurizer High Pressure trips to preclude an inadvertent reactor
trip on this parameter. Then perform orderly shutdown per Technical Specification
if required.

A

A. One channel Pressurizer High Pressure bypassed, either “A” or “C,” the other is
tripped. Then perform orderly shutdown per Technical Specification if required

19
Q

Which ONE of the following does NOT describe a design feature of the Reactor
Protection System (RPS) with respect to RPS matrix logic testing?
A. Testing circuit has isolated power supply
B. Test coil relay produces magnetic flux that aids affected RPS coil relay
C. Test coil relay produces magnetic flux that bucks affected RPS coil relay
D. Test signal is provided to the trip unit signal input circuit by an external test signal
generator

A

D. Test signal is provided to the trip unit signal input circuit by an external test signal
generator
FSAR section 7.2.6. Answer 0 is incorrect because it says “external” (internal is
correct).
Correct Answer = 0 ???????????????????????

20
Q

Which ONE of the following does NOT describe a design feature of the Reactor Protection System (RPS) with
respect to RPS matrix logic testing?
A. Testing circuit has isolated power supply
B. Test coil relay produces magnetic flux that aids affected RPS coil relay
C. Test coil relay produces magnetic flux that bucks affected RPS coil relay
D. Test signal is provided to the trip unit signal input circuit by an external test signal generator

A

D. Test signal is provided to the trip unit signal input circuit by an external test signal generator
Answer D is correct because it says “external” (internal is correct).

21
Q

Which of the following does NOT describe a design feature associated with bypassing an RPS
trip unit?
A. Corresponding trips in each of the four protective channels have the same cylinder
combination.
B. During bypass condition, the system logic reverts to 2/3 channels required for trip.
c. Each trip bypass has a different lock cylinder combination.
D. Turning the bypass key lock switch closes three separate contacts in series

A

D. Turning the bypass key lock switch closes three separate contacts in series

22
Q

Which ONE of the following is the proper method for unbypassing a Reactor Protection
System trip unit that had been manually bypassed?
A. Reinsert the trip unit until it is flush with the front panel.
B. Reinstall the P1 plug on the back of the individual trip unit.
C. Turn the bypass key 90° counterclockwise and remove it.
D. Trip the trip unit and then turn the bypass key 90° clockwise.

A

C. Turn the bypass key 90° counterclockwise and remove it.

23
Q

Which ONE of the following indications are used to verify that a Reactor Protection
System (RPS) trip unit has been properly unbypassed? (Assume all bulbs are good)
A. The annunciators for the associated trip unit clear.
B. The associated trip unit red matrix LEOs are not lit.
c. The annunciators for the associated trip unit alarm.
D. The amber light above the bypass keyswitch is not lit

A

D. The amber light above the bypass keyswitch is not lit

24
Q

What is the Reactor Protection System (RPS) trip logic when an individual channel trip
unit is bypassed?
A”! Two out of four for all parameters except the bypassed parameter, which is two out
of three.
8. Two out of three for all parameters except the bypassed parameter, which is one
out of three.
C. Two out of four for all parameters except the bypassed parameter, which is one out
of three.
D. Two out of three for all parameters except the bypassed parameter, which is two
out of four.

A

D.. Two out of three for all parameters except the bypassed parameter, which is two
out of four.

25
Q

Reactor Protective System (RPS) “A” channel trip for Containment High Pressure has
been bypassed. Which ONE of the following describes the correct response of the
RPS logic to further actions?
A. If one different channel trip unit of Containment High Pressure is removed from the
panel the RPS will process a reactor trip.
B. If two different channel trip units for Containment High Pressure are removed from
the panel the RPS will process a reactor trip.
C. If three different channel trip units of Containment High Pressure is removed from
the panel the RPS will not process a reactor trip.
D. If two different channel trip units for Containment High Pressure are removed from
the panel the RPS will not process a reactor trip.

A

B. If two different channel trip units for Containment High Pressure are removed from
the panel the RPS will process a reactor trip

26
Q

The plant is at 100% power. RPS Channel B for “A” Steam Generator Low Level is
BYPASSED due to a failure of L1-0751B.
Refer to the attached graphic of Steam Generator level instrumentation.
Which one of the following additional instrument failures will result in a Reactor trip?
(Assume no operator action.)
A. L1-0751A fails LOW.
B. L1-0751A fails HIGH.
C. L1A-0702 fails LOW.
D. L1A-0702 fails HIGH.

A

D. L1A-0702 fails HIGH.
CORRECT - This instrument is part of the steam generator water level (high
level override) control circuit. If the instrument fails high, the feedwater
regulating valves will close down to prevent a high level. With no operator
action, LOW steam generator levels will result in a trip

27
Q

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 Rx 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.

A

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

28
Q

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.

A

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

29
Q
In addition to pes 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
A

C. Rx Power
PZR pressure
PCS flow

30
Q
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
A

B. Y-20 and Y-30

31
Q

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 bistq)fes have actuated.
C. NI-5, 6, 7 and 8 (Power Range Nls) reading greater than 15%. X
D. EK-06D2, “LOSS OF LOAD TRIP CHANNEL BYPASS” not lit.

A

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

32
Q

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 lite
A. OFF OFF OFF ON
B. ON OFF ON OFF
C. OFF OFF ON ON
D. ON OFF OFF OFFF

A

C. OFF OFF ON ON

33
Q

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
C. The loss of load trip is enabled above 15% power and the rate of change is bypassed above 15% power by the power range NIs
D. The loss of load trip is bypassed below 15% power by the wide range NIs and the rate of change of power trip is inserte below 15% power by the power range NIs.

A

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

34
Q

RPS_E04.03 003
Given the following:
• Plant is at 100% power
• Preferred AC Bus Y-30 was lost 5 minutes ago
• No operator actions have been taken to address the loss of Y-30
If Anticipated Transient Without Scram (ATWS) pressure sensor PSA-OI02BHH were to fail
high, which of the following describes the effect?
A. ATWS trip logic will be 1-out-of-2
B. ATWS trip logic will be 2-out-of-3
C. ATWS will cause auto reactor trip
D. ATWS trip logic will be lout-of-3

A

A. ATWS trip logic will be 1-out-of-2

35
Q

Which of the following does NOT describe a design feature associated with bypassing an RPS
trip unit?
A. Corresponding trips in each of the four protective channels have the same cylinder
combination.
B During bypass condition, the system logic reverts to 2/3 channels required for trip .
C. Each trip bypass has a different lock cylinder combination.
D. Turning the bypass key lock switch closes three separate contacts in series

A

D. Turning the bypass key lock switch closes three separate contacts in series