BOP ESFAS, PPS (Plant Protection System) Flashcards
Unit is at 100% power when a large break LOCA occurred.
Containment pressure is currently 22 psig.
SG levels are 22% WR and increasing slowly.
SG 1 pressure is 430 psia.
SG 2 pressure is 225 psia.
RWT level 33% and decreasing slowly.
What safety signal would you expect in addition to SIAS/CIAS?
A. CSAS, RAS, AFAS-1 (NO AFAS-2)
B. CSAS, MSIS, AFAS-2 (NO AFAS-1)
C. MSIS, CSAS, AFAS-1 (NO AFAS-2)
D. RAS, AFAS-1 and AFAS-2, MSIS
C. MSIS, CSAS, AFAS 1 (No AFAS 2)
MSIS (<960 psia) CSAS (>8.5 psig Wide Range) AFAS 1 (<25.8% Wide Range) No AFAS 2 (>185 psid between generators) RAS (<9.4% RWT Level)
Reactor is subcritical at 1.0 E-07% full power.
RCS Tc is 565 F.
RCS pressure is 2250 psia.
Shutdown and Part-strength CEA groups fully withdrawn.
The RCS is being inadvertently diluted.
A positive Start-up Rate now exists on all four meters with no CEA motion.
Which ONE of the following describes expected plant response to the dilution accident?
A. Reactor trips on Variable Overpower.
B. Reactor power increases to the point of adding heat.
C. Reactor trips on High Log Power.
D. Reactor power increases to approximately 3% full power.
C. Reactor trips on High Log Power.
Which One of the following describes the basis for the Reactor Protection System PZR press - high trip setpoint? (Do not consider the SPLA trip part of RPS)
A. Protect the reactor Coolant system in the event of a SG overfeed condition.
B. Prevent operation of the pressurizer safety valves in the event of a loss of off-site power.
C. Protect the reactor coolant system in the event of a loss of condenser vacuum
D. Minimize operation of the steam generator safety valves in the event of a decrease in heat removal by the secondary system
C. Protect the reactor coolant system in the event of a loss of condenser vacuum.
Which of the following ESFAS signals should not be initiated “on trend” (early)?
A. RAS
B. SIAS
C. CSAS
D. MSIS
A. RAS
The Emergency Core Cooling System is designed to ensure maximum design peak cladding temperature does not exceed?
A. 2150 F
B. 2200 F
C. 2250 F
D. 2300 F
B. 2200 F
The reactor has tripped.
An MSSV has stuck open on SG 1.
SG 1 is at 32% WR and 930 psia. SG 2 is at 43% WR and 1060 psia.
Loop 1 Tc 538 F, Th 559 F. Loop 2 Tc 556 F, Th 559 F.
A. AFA and AFB are feeding both SGs.
B. AFA and AFB are feeding SG 1 only.
C. Neither SG is receiving Feedwater.
D. MFW is feeding both SGs in RTO at greater than 250 gpm.
C. Neither SG is receiving Feedwater.
Note: <960 psia MSLI isolating feedwater and SG level is not low enough for AFAS <25.8%
PPS Trip Channel bypasses function by…
A. Blocking the ability of 1 of the associated logic matrix relays to trip.
B. Blocking the ability of the associated channel initiation relay to trip.
C. Closing contacts in parallel with the bistable output relay contacts in the logic matrix ‘Trip Ladders.’
D. Blocking the ability of two of the associated logic matrix relays to trip.
C. Closing contacts in parallel with the bistable output relay contacts in the logic matrix ‘Trip Ladders.’
The plant is at 100% power.
An operator incorrectly pushes one SG PRESS SET POINT RESET push button on the PPS remote operators module (ROM).
This action will reset the low SG pressure trip set point:
A. 400 psia below existing SG pressure in all channels.
B. 200 psia below existing SG pressure in all channels.
C. 200 psia below existing SG pressure in the channel that the reset button was pushed.
D. 400 psia below existing SG pressure in the channel that the reset button was pushed.
C. 200 psia below existing SG pressure in the channel that the reset button was pushed.
Which of the following would be an acceptable configuration for actual PPS set point compared to Tech Spec required set point for SIAS (pressurizer pressure) and CSAS?
Actual CSAS set point _______ than TS set point.
Actual SIAS set point _______ than TS set point.
A. Less, greater
B. Less, less
C. Greater, greater
D. Greater, less
A. Less, greater
Note: Think Conservatively.
The bases for the minimum required volume of the RWT ensures that at the time of RAS initiation the water level in the containment sump will be enough to provide NPSH for the ESF pumps and the decay heat boil-off rate is less than…
A. The minimum design flow of two HPSI pumps.
B. The minimum design flow of one HPSI pump and one LPSI pump.
C. 75% of the minimum design flow of one HPSI pump.
D. The minimum design flow of two HPSI pumps and two LPSI pumps.
C. 75% of the minimum design flow of one HPSI pump.
The Reactor Coolant Flow Low RPS trip monitors…
A. RCP speed and provides protection in the event of an under frequency condition.
B. RCP speed and provides protection in the event of an RCP shaft sheared.
C. SG DP and provides protection in the event of an RCP shaft sheared.
D. SG DP and provides protection in the event of an under frequency condition.
C. SG DP and provides protection in the event of an RCP shaft sheared.
The plant is stable at 30% power.
Power is ramped up at a rate of 15% per minute.
Which no operator action, approximately when will PPS (not CPC aux trips) trip the reactor?
A. never.
B. 2 minutes.
C. 5 minutes.
D. 8 minutes.
B. 2 minutes.
A combination of manual reactor trip pushbutton which will NOT result in a reactor trip is:
A. 1 and 2.
B. 2 and 4.
C. 2 and 3.
D. 1 and 4.
B. 2 and 4.
Note: Same Train.
Which of the following failures will cause only one RTCB to open with no reactor trip?
A single…
A. PN power supply is lost.
B. Instrument channel trips.
C. Aux Relay cabinet fuse blows.
D. Matrix Relay fails.
D. Matrix Relay fails.
Note: RTCB (Reactor Trip Circuit Breaker)
In order to reset a SIAS initiation in the AUX relay cabinet the operator must press…
A. Both reset buttons, one at a time.
B. Both reset buttons simultaneously.
C. Either reset button.
D. Hold one reset button, for a minimum of 5 seconds.
C. Either Reset Button.
Reactor power at 104% full power and rising slowly.
Pressurizer pressure at 2390 psia and rising slowly.
Reactor trip circuit breakers 1 and 3 have failed to open.
Which ONE of the following identifies the expected plant response, with no operator action, as the transient continues?
A. Supplementary Protection System de-energizes the CEDMs.
B. DAFAS will immediately actuate to provide additional feed to the SGs.
C. Core bulk boiling will occur to shut down the reactor via void coefficient.
D. Reactor Protection System trips reactor when power reaches 110% full power.
A. Supplementary Protection System de-energizes the CEDMs.
Note: The stem leads to show that 1 and 3 failed to open so ATWAS
Diverse Auxiliary Feedwater Actuation System (DAFAS) actuations will be TERMINATED by:
A. MSIS
B. SIAS
C. Delays P Lockout
D. #1 S/G level increasing to 15.8% WR
A. MSIS
Note: DAFAS is reset when >40.3% WR or MSIS occurs. DAFAS relays become de-energized.
Reactor is tripped. SG 1 pressure - 1040 psia. SG 2 pressure - 1050 psia. SG 1 level - 92% NR. SG 2 level - 20% NR. PZR pressure - 400 psia. RWT level 6%. CNTMT Press - 45 psig. In addition to SIAS and CSAS, what ESF actuations should be present at this time? (No operator actions have been taken.)
A. CIAS, AFAS-2, RAS
B. MSIS, AFAS-1, RAS
C. CIAS, MSIS, RAS
D. MSIS, AFAS-2, RAS
C. CIAS, MSIS, RAS
Note: AFAS-2 is a distractors because AFAS-2 low level (25.8%) comes off WIDE range.
On the ‘A’ and ‘C’ PPS cabinets, the bistable status lights for ‘SG-1 LO FLOW’ and ‘SG-2 LO FLOW’ labeled ‘P’ and ‘T’ are lit.
None of the ‘BYPASS’ lights are lit.
The 3 lights under ‘SG-1 LO FLOW’ and ‘SG-2 LO FLOW’ labeled RPS are lit on the ‘A’ and ‘C’ PPS cabinets.
None of these lights are lit on the ‘B’ and ‘D’ modules?
What do these lights signify?
A. The 1 and 3 RTSGs should be open.
B. This indicates a ‘Half-Trip.’ No reactor trip occurs.
C. All four reactor trip breakers should be open, but no ESFAS actuations should occur.
D. All four reactor trip breakers should be open and ESFAS actuations should occur.
C. All four reactor trip breakers should be open, but no ESFAS actuations should occur.
The plant is at 100% power. Containment Pressure .1 psig. Leg 1-3 CSAS A Leg 2-4 - window 5B05A. Leg 1-3 CSAS B Leg 2-4 - window 5B05B. CSAS - window 5C04A. NO SIAS has actuated. The Reactor has not tripped. The operators stop the CS pumps as directed by procedure. If an SIAS were to now occur, which one of the following statements describes how the CS pumps would be restarted?
A. Taking the CS pump handswitch to START once.
B. The pumps must be started manually at then local breakers.
C. They pumps would auto start.
D. Taking the CS pump handswitch to START twice.
D. Taking the CS pump handswitch to START twice.
An inadvertent CSAS has occurred with no other ESFAS signals actuated. Choose the statement which correctly describes how the CS pumps would be stopped and what condition the breaker would be in.
A. Hold the handswitch in stop until the green light is on. The breaker is now anti-pumped.
B. Override and stop the CS pump. The breaker is now anti-pump.
C. Hold the handswitch in stop until the green light comes on. The breaker will respond to an active CSAS.
D. Override and stop the CS Pump. The breaker will respond to an actual CSAS.
A. Hold the handswitch in stop until the green light is on. The breaker is now anti-pumped.
Unit 2 is operating in mode 1 at 100% power. A loss of PKA-M41 occurs. Which of the following describes the impact on the reactor protection system?
A. All four RTSG breakers trip open
B. RTSG breakers A and C trip open
C. RTSG breaker A trips open
D. RTSG breaker A fails as is (no trips will function)
C. RTSG breaker A trips open
A loss of PNB-D26 occurs. Which of the following describes the impact on the reactor protection system?
A. RTSG breakers A and C trip open.
B. There is no impact on the reactor protective system.
C. Channel B input parameters all fail to trip set point value.
D. RTSG breakers B and D trip open.
D. RTSG breakers B and D trip open.
RCA-PT-101A (pressurizer pressure) fails high tripping it’s RPS channel.
This instrument is bypassed.
Subsequently, RCC-PT-101C fails low.
Based on these indications, the Operating Crew is required to…
A. Remove channel A pressurizer pressure high from bypass within 1 hour.
B. Bypass channel A and C pressurizer pressure within 1 hour.
C. Have Instrument Maintenance trip channel C pressurizer pressure high within 1 hour.
D. Take no action.
C. Have Instrument Maintenance trip channel C pressurizer pressure high within 1 hour.
Plant at 100% power.
Channels A and C sense a containment pressure of 3.2 psig.
Channels B and D are below the trip set point.
Which one of the following will occur?
A. No reactor trip, no RTCBs will open.
B. Reactor trip with all 4 RTCBs opening.
C. No reactor trip, but 2 RTCBs will open.
D. Reactor trip with only 2 RTCBs opening.
B. Reactor trip with all 4 RTCBs opening.
Reactor has tripped from 100% power.
Reactor Coolant system pressure is 1650 psia and dropping.
Pressurizer level is 10% and dropping.
Steam generator levels have turned at 36% while range (they were never lower).
Steam generator pressures are 1020 psia and rising.
Containment pressure is 7.6 psig and rising.
Safety Injection and containment isolation actuations have occurred.
WHICH ONE of the following states the additional engineered safety features actuation(s) present assuming all systems functioned as designed?
A. Main Steam Isolation
B. Containment Spray Actuation
C. Auxiliary Feedwater Actuation
D. Auxiliary Feedwater Actuation and Main Steam Isolation
A. Main Steam Isolation
How does COLSS interface with RPS?
A. Incore detectors are used to calibrate NIs.
B. RCS flow from COLSS feeds the DNBR trip.
C. Incore detectors are monitored for the DNBR trips.
D. JSCALOR is used to calibrate safety channel NIs.
D. JSCALOR is used to calibrate safety channel NIs.
Plant at 100% power.
Channel ‘D’ PPS bypassed due to failed high RCS pressure (Narrow Range) transmitter.
Channel ‘B’ PPS SG-2 level low has tripped due to failed transmitter.
Channel ‘A’ RCS pressure (Narrow Range) transmitter now fails high.
Based on these conditions, which of the following is correct?
A. The operator can not bypass channel ‘A’ RCS pressure transmitter.
B. If the operator bypasses the channel ‘A’ RCS pressure transmitter, the channel would go into bypass, while removing the channel ‘D’ transmitter from bypass.
C. 2 Reactor Trip Circuit Breakers (RTCBs) would open when the channel ‘A’ RCS pressure transmitter failed, but the reactor would not trip.
D. The reactor would have tripped when the channel ‘A’ pressure transmitter failed.
B. If the operator bypasses the channel ‘A’ RCS pressure transmitter, the channel would go into bypass, while removing the channel ‘D’ transmitter from bypass.
If one of the six RPS matrices loses one of its two matrix power supplies which of the following will occur?
A. All four RTCBs will open and the reactor will trip.
B. No RTCBs will open and the reactor will not trip.
C. Two RTCBs will open and the reactor will not trip.
D. Two RTCBs will open and reactor will trip.
C. Two RTCBs will open and the reactor will not trip.
Channel ‘A’ LO PRESSURIZER PRESSURE PERMISSIVE light is lit.
If the channel ‘A’ LO PRESSURIZER PRESSURE BYPASS switch is turned to the BYPASS position, which of the following will occur.
A. The ‘A’ channel DNBR, LPD and low Pressurizer Pressure trips will be bypassed.
B. The ‘BYPASS’ light comes on. SIAS, CIAS, and LO Pressurizer Pressure Rx trip are now in 2 out of 3 logic.
C. There is no visible effect, and ‘A’ channel input to SIAS, CIAS, MSIS and Rx trip are unaffected.
D. The ‘BYPASS’ light comes on, all four (4) channels of SIAS, CIAS, MSIS, and Lo Pressurizer Pressure Rx trips are bypassed.
B. The ‘BYPASS’ light comes on. SIAS, CIAS, and LO Pressurizer Pressure Rx trip are now in 2 out of 3 logic.
Which of the following describes the operational bypass associated with the Core Protection Calculator trips?
These trips are automatically…
A. Bypassed when power drops to 1E-2%.
B. Placed in service when power increases to 1E-4%.
C. Bypassed when power drops to 1E-4%.
D. Placed in service when power increases to 1E-2%.
B. Placed in service when power increases to 1E-4%.
Channel B VOPT is bypassed and tripped.
Channel A VOPT is in tripped condition due to a power supply failure.
What the effect of depressing the Channel B VOPT bypass button?
A. Reactor trip.
B. No actual trip, but two trip breakers open.
C. Channel B VOPT will remain in bypass and Channel A VOPT will be in tripped condition.
D. Channel B VOPT will remain in bypass and a PPS Trouble alarm will be received.
A. Reactor trip.
‘SIAS A’ 1-3 is lit with 2-4 still dark on B05 due to a single matrix power supply loss.
Which one of the following is indicated?
A. SIAS ‘B’ 1-3 should be lit.
B. SIAS ‘A’ pumps should be running.
C. SIAS ‘A’ valves should be in their SIAS position.
D. SIAS ‘A’ 2-4 should be lit.
A. SIAS ‘B’ 1-3 should be lit.
The bypass of DAFAS can be accomplished by which of the following:
A. Using the 8 key switches in the PPS Cabinets.
B. Using the 4 key switches in Aux Relay Cabinets.
C. Using the 8 key switches in Aux Relay Cabinets.
D. By bypassing the 4 Steam Generator level trips at the PPS Cabinets.
C. Using the 8 key switches in Aux Relay Cabinets.
Diverse Auxiliary Feedwater Actuation System (DAFAS) actuations will be TERMINATED by:
A. #1 S/G level increasing to 20.8% WR.
B. Delta P lockout.
C. MSIS.
D. SIAS.
C. MSIS
SPS reactor trip occurred at 2409 psia. S/G 1 pressure 1170 psia. S/G 2 pressure 965 psia. Pressurizer pressure 1950 psia. Containment pressure 9.0 psig. S/G level 18% (WR). S/G level 0% (WR). SIAS and MSIS have occurred. What additional ESF actuations should be present at the time?
A. CSAS, AFAS-2, CIAS
B. CIAS, AFAS-1, AFAS-2, DAFAS
C. CSAS, AFAS-1, CIAS
D. DAFAS, CSAS, CIAS, AFAS-1
C. CSAS, AFAS-1, CIAS
Unit 1 has tripped from 100% power.
Sub-Cooled Margin is 36F and lowering slowly.
Containment Pressure is 2.7 psig and rising slowly.
Pressurizer level is 20% and lowering slowly.
RCS Pressure is 1780 psia and lowering slowly.
SG #1 level is 28% WR and rising slowly.
SG #2 level is 30% WR and rising slowly.
SPTAs are in progress.
NO ESFAS Actuations have occurred.
Which ONE of the following describes the ESFAS Actuations the RO must manually initiate?
A. SIAS and CIAS ONLY due to exceeding the low pressurizer pressure set point.
B. SIAS and CIAS ONLY due to exceeding the high containment pressure set point.
C. SIAS, CIAS, and MSIS ONLY due to exceeding the low pressurizer pressure set point.
D. SIAS, CIAS, and MISIS ONLY due to exceeding the high containment pressure set point.
A. SIAS and CIAS ONLY due to exceeding the low pressurizer pressure set point.
(Note: SIAS, CIAS and MSIS set point is > 3.0 psig in CTMT. SIAS and CIAS set point < 1837 psia PZR Pressure)
Which of the following describes the BOP ESFAS power supply arrangement?
Each cabinet receives power from its associated train of….
A. PK and PN, which is auctioneered so that a loss of either supply to the cabinet does not impact the operation of the system.
B. PK Only. A loss of this power supply to the cabinet will cause an auction of the components controlled by the train of BOP ESFAS.
C. PN Only. A loss of this power supply to the cabinet will cause an actuation of the components controlled by that train of BOP ESFAS.
D. PK and PN. A loss of either power supply to the cabinet will prevent those components controlled by the affected BOP ESFAS cabinet from actuating when needed.
A. PK and PN, which is auctioneered so that a loss of either supply to the cabinet does not impact the operation of the system.
Radiation monitor RU-31, Train ‘A’ Fuel Building are monitor, fails high.
Train ‘B’ Control Room Essential Filtration Actuation System module is in BYPASS.
Fuel Building Essential Filtration (FBVEAS) Train ‘A’ actuates.
All other systems and components are operating correctly.
What other balance of plant engineered safety features actuations(s) in addition to FBEVAS Train ‘A’?
FBEVAS Train ‘B’ and CREFAS Trains ‘A’ and ‘B’.
Choose the statement below which describes the plant response if the Train ‘A’ FBEVAS Manual Switch on B05 is taken to TRIP.
A. Complete actuation of FBEVAS and CREFAS.
B. Actuation of Train ’A’ FBEVAS Only.
C. Actuation of Train ‘A’ and ‘B’ FBEVAS Only.
D. Actuation of Train ‘A’ FBEVAS and Train ‘A’ CREFAS Only.
B. Actuation of Train ‘A’ FBEVAS Only.
You are investigating a trip of CPIAS ‘A’ at the BOP ESFAS cabinets. The following lights are illuminated on the Train ‘A’ CPIAS Module:
Both the TRIP and RESEET halves of the TRIP/RESET button.
The ACTUATE half of the ACTUATE/MAN/RST button.
Based upon these indications, which one of the following has caused this trip?
A. High Radiation signal from RU-37 (Power Access Purge Monitor ‘A’) which has subsequently cleared.
B. Cross train trip signal.
C. Manual caution from B05.
D. High radiation signal from RU-37 (Power Access Purge Monitor ‘A’) which is still above its trip set point.
A. High Radiation signal from RU-37 (Power Access Purge Monitor ‘A’) which has subsequently cleared.
Choose the statement below which describes the plant response if the TEST push button is depressed on the Train ‘A’ FBEVAS module on the BOP ESFAS cabinet.
A. Actuation of Train ‘A’ FBEVAS ONLY.
B. Actuation of Train ‘A’ and ‘B’ FBEVAS ONLY.
C. Complete actuation of FBEVAS and CREFAS.
D. Actuation of Train ‘A’ FBEVAS and Train ‘A’ CREFAS ONLY.
C. Complete actuation of FBEVAS and CREFAS.
If the CR hand switch is used to initiate CREFAS and the hand switch is then returned to its pre-actuated position, which of the following pushbutton sections would you expect to see illuminated?
A. Actuate and Reset ONLY.
B. Actuate, Manual, and Reset.
C. Actuate ONLY.
D. Reset ONLY.
B. Actuate, Manual, and Reset.
Unit is operating at 40% power.
The Power Access Purge Unit has been started in preparation of a containment entry.
RU-37 (one of the PAPA radiation monitors) fails HIGH.
Which of the following describes the ESFAS actuations that result, if any?
A. CPIAS with a cross trip to CREFAS.
B. CPIAS only.
C. CPIAS with a cross trip to FBEVAS.
D. No actuation until RU-38 reaches its HIGH set point.
A. CPIAS with a cross trip to CREFAS.
The Steam Generator ‘Low Level’ trip set point is approximately ____ WR and is designed to…
A. 25.8%, prevent exceeding the design pressure of the RCS.
B. 44.2%, prevent exceeding the design pressure of the RCS.
C. 25.8%, protect against core damage due to the occurrence of locally saturated conditions in the limiting (hot) channel.
D. 44.2%, protect against core damage due to the occurrence of locally saturated conditions in the limiting (hot) channel.
B. 44.2%, prevent exceeding the design pressure of the RCS.
Containment pressure (NR) Channel A 3.2 psig. Containment pressure (NR) Channel B 2.7 psig. Containment pressure (NR) Channel C 3.1 psig. Containment pressure (NR) Channel D 2.6 psig. What is the effect on the Emergency Core Cooling System?
A. No CIAS/SIAS actuation, no safety injection pumps or valves have gone to their actuated condition.
B. Full CIAS/SIAS actuation, both trains of Safety Injection pumps and valves are in their actuated condition.
C. ‘A’ train CIAS/SIAS actuation, only the ‘A’ train Safety Injection pumps and valves have gone to their actuated condition.
D. ‘A’ train 1-3 Half leg CIAS/SIAS actuation, only the ‘A’ train Safety Injection valves have gone to their actuated condition, no pumps are running.
B. Full CIAS/SIAS actuation, both trains of Safety Injection pumps and valves are in their actuated condition.
Unit 1 is at 100% power.
Channel ‘C’ parameter 5 HI PZR PRESS is bypassed for I and C maintenance.
Channel ‘B’ HI PZR PRESS has just tripped due to an instrument failure.
Which one of the following correctly describes the status of the Reactor Protection System if the Channel ‘B’ parameter 5 bypass pushbutton is depressed?
A. Both Channels ‘B’ and ‘C’ are in bypass.
B. Neither Channel ‘B’ and ‘C’ is in bypass.
C. Channels ‘B’ parameter 5 goes in bypass, Channel ‘C’ comes out of bypass.
D. Channel ‘C’ parameter 5 stays in bypass, Channel ‘B’ parameter 5 is not in bypass
C. Channels ‘B’ parameter 5 goes in bypass, Channel ‘C’ comes out of bypass.
The ‘A’ train BOP/ESFAS cabinet, SAA-C02A, has two power supplies which are…
A. PHA-M31 and PNC-D27
B. PHA-M31 and PKA-D21
C. PNA-D25 and PNC-D27
D. PNA-D25 and PKA-D21
D. PNA-D25 and PKA-D21
Which one of the following combination of set points/interlocks will ALL initiate a Main Steam Isolation Signal (MSIS).
A. SG pressure 920 psia, Containment pressure 3.5 psig, SG level 46%f WR.
B. SG level 89% NR, SG pressure 920 psia and Pressurizer pressure 1850 psia.
C. Containment pressure 3.1 psig, SG level 92% NR and SG pressure 950 psia.
D. SG level 40% WR, Containment pressure 3.5 psig and Pressurizer pressure 1800 psia.
C. Containment pressure 3.1 psig, SG level 92% NR and SG pressure 950 psia.
SG 1 level is 42% WR and lowering.
SG 1 pressure is 760 psig and lowering.
SG 2 level is 60%, WR and lowering.
SG 2 pressure is 950 psig and rising.
Containment pressure is 1.8 psig and rising.
RCS Tavg is 525F and lowering.
Alarm window 5B08C ‘SG-2 > SG-1 CH TRIP’ has locked in.
Any required ESFAS signals have properly actuated.
The Digital Feed Control system (DFWCS) is in Reactor Trip Override (RTO) and…
A. Neither SG is currently being fed. AFAS-1 will not initiate but AFAS-2 will at the required level.
B. Only SG 2 is currently being fed. AFAS-1 will not initiate but AFAS-2 will at the required level.
C. Neither SG is currently being fed. Neither AFAS-1 or AFAS-2 will initiate at the required level.
D. Both SGs are currently being fed. Neither AFAS-1 or AFAS-2 will initiate at the required level.
A. Neither SG is currently being fed. AFAS-1 will not initiate but AFAS-2 will at the required level.
What is the significance of the Control Room instruments that have a white placard attached?
These instruments…
A. Are appendix ‘R’/ Fire qualified.
B. Are associated with ESFAS actuation set points.
C. Can also be found at the Remote Shutdown panel.
D. Are post accident monitoring/harsh containment qualified.
D. Are post accident monitoring/harsh containment qualified.
Unit 1 is in Mode 6.
Core off-load is in progress.
The CRS is informed that a Fuel Assembly has been dropped in the Spent Fuel Pool.
The Fuel Assembly is being placed in a stable condition.
RU 31 is in alert alarm and readings are trending up.
RU 145 is in alert alarm and readings are trending up.
In addition to initiating a FBEVAS the crew is expected to…
A. Ensure all personnel have evacuated the area, no other actions are required.
B. Initiate or verify initiated CRVIAS and ensure all personnel have evacuated the area.
C. Initiate or verify initiated CREFAS and ensure all non-essential personnel have evacuated the area.
D. Initiate or verify initiated CREFAS, CRVIAS and ensure all non-essential personnel have evacuated the area.
C. Initiate or verify initiated CREFAS and ensure all non-essential personnel have evacuated the area.
Unit 1 has tripped from 100% power.
Sub-Cooled Margin in 36F and lowering slowly.
Containment Pressure is 2.7 psig and rising slowly.
Pressurizer level is 20% and lowering slowly.
SG #1 level is 28% WR and rising slowly.
SG #2 level is 30% WR and rising slowly.
SPTAs are in progress.
NO ESFAS Actuations have occurred.
Which ONE of the following describes the ESFAS Actuations the RO must manually initiate?
A. SIAS and CIAS ONLY due to exceeding the low pressurizer pressure set point.
B. SIAS and CIAS ONLY due to exceeding the high containment pressure set point.
C. SIAS, CIAS and MSIS ONLY due to exceeding the low pressurizer pressure set point.
D. SIAS, CIAS and MSIS ONLY due to exceeding the high containment pressure set point.
A. SIAS and CIAS ONLY due to exceeding the low pressurizer pressure set point.
The DNBR/LPD Reactor Protection System Operational Bypass is inserted ____ when the Excore NI Power decreases below ____.
A. (1) Manually (2) 1E-2%
B. (1) Manually (2) 1E-4%
C. (1) Automatically (2) 1E-2%
D. (1) Automatically (2) 1E-4%
B. (1) Manually (2) 1E-4%
Unit 1 is operating at 100%
Channel ‘D’ PPS HI PZR PRESS is BYPASSED due to a failed high RCS pressure (Narrow Range) transmitter.
Channel ‘B’ PPS SG-2 level low has TRIPPED due to failed transmitter.
Channel ‘A’ RCS pressure (Narrow Range) transmitter now FAILS HIGH.
Based on these conditions, which ONE of the following is correct?
A. The Operator can NOT physically bypass channel ‘A’ HI PZR PRESS bistable.
B. The reactor would have tripped when the channel ‘A’ pressure transmitter failed.
C. 2 Reactor Trip Circuit Breakers (RTCBs) would open when the channel ‘A’ RCS pressure transmitter failed, but the reactor would not trip.
D. If the operator bypasses the ‘A’ HI PZR PRESS bistable, that channel would go into bypass, while removing the channel ‘D’ HI PZR PRESS bistable from bypass.
D. If the operator bypasses the ‘A’ HI PZR PRESS bistable, that channel would go into bypass, while removing the channel ‘D’ HI PZR PRESS bistable from bypass.
(Note: The hierarchy of the system would cause the D channel to come out of bypass when the A channel is placed in bypass)
Unit 1 is operating at 100% power.
The CRS directs an RO to initiate a MSIS from the Aux Relay Cabinets.
The RO performs the following actions.
Depresses the 1-3 and 2-4 MSIS trip push buttons simultaneously on the ‘A’ train.
Depresses the 1-3 and 2-4 MSIS trip push buttons sequentially (push then release) on the ‘B’ train.
Assuming that SG pressures remains above the MSIS set point, you would expect an ‘A’ train MSIS full initiation with…
A. No initiation of the ‘B’ train, ‘A’ MSIS can be reset by depressing either reset pushbutton.
B. A half leg initiation of the ‘B’ train, ‘A’ MSIS can be reset by depressing either reset push button.
C. No initiation of the ‘B’ train, ‘A’ MSIS can only be reset by depressing both reset push buttons simultaneously.
D. A half leg initiation of the ‘B’ train, ‘A’ MSIS can only be reset by depressing both reset pushbuttons simultaneously.
A. No initiation of the ‘B’ train, ‘A’ MSIS can be reset by depressing either reset pushbutton.
(Note: To initiate an ESFAS actuation both buttons must be pushed simultaneously pushing and releasing gives no initiation half leg or otherwise, power is still available to all relays. Resetting requires that either rest button on the train be depressed.)