2016 Flashcards
Given the following conditions:
• Unit 1 was tripped from 100% power due to degrading condenser vacuum.
• Condenser vacuum degraded to 9.0 inches HgA and stabilized.
• 40EP-9EO02, Reactor Trip, has been implemented.
In this condition, Main Feedwater Pumps _____(1)_____ available for use, and maintaining
SG pressures in their normal post-trip band _____(2)_____ be accomplished using only
SBCS.
A. 1. ARE 2. CAN B. 1. ARE 2. can NOT C. 1. are NOT 2. CAN D. 1. are NOT 2. can NOT
A
A. Correct. Since Main Feedwater Pumps don’t trip until 13.5 inches HgA, they are still available and
although SBCS valves 1001-1006 are locked out due to the degraded vacuum, SBCS 1007-1008
are still available and can maintain SG pressure in the normal post-trip band.
B. First part is correct. Second part is plausible since the SBCS interlock actuates at 5.5 inches
backpressure, however SBCS valves 1007 and 1008 are still available and will maintain SG
pressures in their normal post-trip pressure band.
C. First part is plausible as Main Feed Pumps do trip on low vacuum, however not until vacuum
degrades to 13.5 inches HgA. Second part is correct.
D. First part is plausible as Main Feed Pumps do trip on low vacuum, however not until vacuum
degrades to 13.5 inches HgA. Second part is plausible since the SBCS interlock actuates at 5.5
inches backpressure, however SBCS valves 1007 and 1008 are still available and will maintain SG
pressures in their normal post-trip pressure band.
Given the following conditions:
• Unit 1 was tripped from 100% power due to a Pressurizer Safety lifting and sticking
open.
• SPTAs have been performed and the CRS has entered 40EP-9EO03, LOCA.
• The RCS is 35°F subcooled and stable.
• Indicated Pressurizer level is 90% and slowly rising.
• Both SGs are 15% NR and slowly rising, being fed from AFB-P01.
• QSPDS shows two HJTCs are uncovered in the vessel head (41% level in the head).
• Containment temperature is 150°F and slowly rising.
• Containment High Range Area Radiation Monitors RU-148 and RU-149 indicate
6.5 x 102 mR/hr and slowly rising.
The CRS directs you to determine whether or not HPSI throttle criteria is currently satisfied,
per Standard Appendix 2, HPSI Throttle Criteria.
HPSI throttle criteria…
A. IS currently satisfied.
B. IS NOT satisfied due to voiding in the vessel head.
C. IS NOT satisfied due to insufficient level in the SGs.
D. IS NOT satisfied due to insufficient RCS subcooling.
A
A. Correct. All criteria are satisfied per SA 2.
B. Plausible as there is voiding in the upper head, however level in the upper head needs to be 16%
or more to throttle HPSI, therefore with level in the upper head is at 67%, inventory is sufficient.
C. Plausible as level in the SGs is 30% less than the normal post trip SG level control band, however
since level is being restored, it meets HPSI throttle criteria.
D. Plausible since subcooling would be insufficient if containment conditions were harsh, and it is
plausible that containment conditions are harsh since temperature and radiation levels are
significantly higher than normal levels, however containment temperature and radiation levels are
below the threshold for declaring harsh containment conditions.
Given the following conditions:
• Unit 1 tripped from 100% power due to a failed closed Economizer Isolation valve on
SG #1.
• SPTAs have just been completed.
• The following conditions exist:
o Pressurizer level is 10% and lowering.
o Pressurizer pressure is 1700 psia and lowering.
o The 1A and 2A RCPs have been tripped.
o SG #1 level is 50% WR and rising.
o SG #2 level is 15% NR and rising.
o RCS subcooling is 20°F subcooled and slowly degrading.
o Containment pressure is 2.5 psig and slowly rising.
The CRS should enter _____(1)_____ and the crew should _____(2)_____ .
A. 1. 40EP-9EO03, LOCA
2. maintain forced circulation with 1B and 2B RCPs
B. 1. 40EP-9EO03, LOCA
2. trip the 1B and 2B RCPs and verify natural
circulation
C. 1. 40EP-9EO05, ESD
2. maintain forced circulation with 1B and 2B RCPs
D. 1. 40EP-9EO05, ESD
2. trip the 1B and 2B RCPs and verify natural
circulation
B
A. First part is correct. Second part is plausible since two pumps were correctly tripped due to
remaining below the SIAS setpoint, however since RCS subcooling has dropped below 24°F
subcooled, the remaining RCPs need to also be tripped.
B. Correct.
C. ESD is plausible since Pressurizer level and pressure would lower and there would be a drastic
difference between SG levels, however RCS subcooling would be abnormally high in an ESD
instead of low. Second part is plausible since two pumps were correctly tripped due to remaining
below the SIAS setpoint, however since RCS subcooling has dropped below 24°F subcooled, the
remaining RCPs need to also be tripped.
D. ESD is plausible since Pressurizer level and pressure would lower and there would be a drastic
difference between SG levels, however RCS subcooling would be abnormally high in an ESD
instead of low. Second part is correct.
Following a large break LOCA, Standard Appendix 100, Hot Leg Injection, is implemented in
order to _____(1)_____ and should NOT be initiated until a MINIMUM of _____(2)_____ have
elapsed since the start of the LOCA.
A. 1. minimize the potential for boron precipitation which could restrict flow through the
core
2. 2 hours
B. 1. minimize the potential for boron precipitation which could restrict flow through the
core
2. 3 hours
C. 1. ensure sufficient boron exists in the core to prevent core restart as RCS temperature
lowers
2. 2 hours
D. 1. ensure sufficient boron exists in the core to prevent core restart as RCS temperature
lowers
2. 3 hours
A
A. Correct.
B. First part is correct. 3 hours is plausible since hot leg injection must be initiated no later than 3
hours have elapsed since the LOCA, however the minimum wait time to initiate is 2 hours.
C. First part is plausible since RCS temperature will lower which can result in reduced SDM, however
the reason for hot leg injection is to minimize boron precipitation. Second part is correct.
D. First part is plausible since RCS temperature will lower which can result in reduced SDM, however
the reason for hot leg injection is to minimize boron precipitation. 3 hours is plausible since hot leg
injection must be initiated no later than 3 hours have elapsed since the LOCA, however the
minimum wait time to initiate is 2 hours.
Given the following conditions:
• Unit 3 was operating at 100% when RCP 1A experienced a sheared shaft.
1. Based on these conditions, the FIRST RPS trip signal received will be…
2. During the performance of SPTAs, if RCS inventory and/or pressure control is challenged
(but adequate RCP NPSH remains), the crew should also trip RCP…
A. 1. Low DNBR 2. 2A B. 1. Low DNBR 2. 2B C. 1. Low RC Flow SG 1 2. 2A D. 1. Low RC Flow SG 1 2. 2B
A. First part is plausible since the low DNBR trip will be received, however it will not be calculated and
actuated until after the low RC flow trip comes in. Second part is correct.
B. First part is plausible since the low DNBR trip will be received, however it will not be calculated and
actuated until after the low RC flow trip comes in. Second part is plausible since a loop 2 RCP will
be tripped, however to avoid RCP bearing damage the correct pump to trip is 2A.
C. Correct. The reactor will trip on low RC flow as this will occur virtually immediately and low DNBR
is a calculated value which would then result in a trip signal, however it will not be the first trip
signal in this case. RCP 2A would be the next pump to be tripped since they are in opposite loops
and RCP 2A running solely in conjunction with 1B can result in bearing damage.
D. First part is correct. Second part is plausible since a loop 2 RCP will be tripped, however to avoid
RCP bearing damage the correct pump to trip is 2A.
Given the following conditions:
• Unit 3 is operating at 100% power, MOC.
• Auto makeup to the VCT is in progress.
Which of the following failures (individually) would cause the auto makeup to the VCT to stop?
1. VCT level transmitter, CHN-LT-227, fails to 100%
2. CHN-FIC-210X, RMW to VCT flow controller, fails to 100% output
3. CHN-FIC-210Y, Boric Acid Makeup to VCT flow controller, fails to 100% output
A. 1 ONLY
B. 2 ONLY
C. 1 and 3 ONLY
D. 2 and 3 ONLY
D
A. Plausible since high level in the VCT will stop auto make up, however LT-226 controls the auto
make up signal, not LT-227.
B. Plausible since 210X failing to 100% output will stop auto make up, however 210Y failing to 100%
will also stop auto make up. The system is designed such that a flow deviation of +/- 10 gpm will
stop auto makeup to prevent an inadvertent dilution or boration during auto makeup operations.
C. Plausible since high level in the VCT will stop auto make up, however LT-226 controls the auto
make up signal, not LT-227. 210Y failing to 100% is correct.
D. Correct.
Given the following conditions:
• Unit 1 is in MODE 5
• Train ‘A’ LPSI Pump is being used for SDC
• Train ‘B’ LPSI Pump suction is still aligned to the RWT.
Subsequently:
• 5B06A, Leg 1-3 RAS ‘A’ Leg 2-4, annunciates (top and bottom halves).
• RWT level is 90% and stable.
What is the impact to SDC, and how should the crew restore SDC flow per 40AO-9ZZ17,
Inadvertent PPS-ESFAS Actuations?
A. The ‘A’ LPSI Pump will trip resulting in a loss of SDC. Restore SDC by placing Train
‘B’ SDC in service.
B. The ‘A’ LPSI Pump will trip resulting in a loss of SDC. Restore SDC by overriding and
restarting the ‘A’ LPSI Pump.
C. The ‘A’ LPSI Pump will cavitate resulting in degraded SDC. Restore SDC by placing
Train ‘B’ SDC in service.
D. The ‘A’ LPSI Pump will cavitate resulting in degraded SDC. Restore SDC by
overriding and closing Containment Sump to SI Train A valves SIA-UV-673 and SIAUV-
674.
B
A. Plausible since the ‘A’ LPSI Pump will trip causing a loss of SDC, and transitioning to Train ‘B’ per
the normal operating SDC procedure is a potential option, however the correct action is to override
and restart the pump per 40AO-9ZZ17 .
B. Correct.
C. Plausible that the ‘A’ LPSI Pump would cavitate since the suction valves from the containment
sump open on a RAS signal, however the pump will trip.
D. Plausible that the ‘A’ LPSI Pump would cavitate since the suction valves from the containment
sump open on a RAS signal, however the pump will trip.
Given the following conditions:
• Unit 2 is operating at 100% power.
• Both Nuclear Cooling Water Pumps have tripped on 86 lockout.
• 40AO-9ZZ03, Loss of Cooling Water, Appendix A, Cross-Connect EW to NC, is in
progress.
The RO will direct the AO to throttle EWA-HCV-53, SDCHX A Outlet Isolation, until cooling
flow to each RCP has been restored to a MINIMUM of _____(1)_____ or EW system flow
lowers to _____(2)_____, whichever happens first.
A. 1. 163 gpm 2. 8500 gpm B. 1. 163 gpm 2. 13,800 gpm C. 1. 491 gpm 2. 8500 gpm D. 1. 491 gpm 2. 13,800 gpm
C
A. First part is plausible because this is the minimum required NC flow to the RCP HP Coolers,
Thrust Bearing Lube Oil Coolers, and Seal Coolers, however the minimum flow to clear the low NC
flow alarm is 491 gpm.
B. First part is plausible because this is the minimum required NC flow to the RCP HP Coolers,
Thrust Bearing Lube Oil Coolers, and Seal Coolers, however the minimum flow to clear the low NC
flow alarm is 491 gpm. Second part is plausible because 13,800 gpm is the low end of the normal
EW system flow for manual EW Train A operations.
C. Correct.
D. First part is correct. Second part is plausible because 13,800 gpm is the low end of the normal
EW system flow for manual EW Train A operations.
Given the following conditions:
• Unit 2 is operating at 100% power.
• RCN-HS-100, Pressure Control Channel X/Y Selector, is selected to Channel X.
Subsequently:
• RCN-PT-100X, Pressurizer Control Channel X, failed to 100%.
With no operator action, RCN-PIC-100, Pressurizer Pressure Control, output will go to
_____(1)_____ and Steam Bypass Control System _____(2)_____ .
A. 1. 0%
2. Auto Modulate Permissive Light will illuminate
B. 1. 0%
2. Auto Modulation Setpoint will lower by approximately 220 psig
C. 1. 100%
2. Auto Modulate Permissive Light will illuminate
D. 1. 100%
2. Auto Modulation Setpoint will lower by approximately 220 psig
D
A. First part plausible that PIC-100 output would go to 0% since the system senses high pressure and
PIC-100 controls proportional heater output, however 0% output on PIC-100 will produce
maximum heating from the proportional heaters. Second part is plausible since auto modulate
permissive signals would be received on a high failure of PT-100Y, however this is not the case if
PT-100X fails high.
B. First part plausible that PIC-100 output would go to 0% since the system senses high pressure and
PIC-100 controls proportional heater output, however 0% output on PIC-100 will produce
maximum heating from the proportional heaters. Second part is correct.
C. First part is correct. Second part is plausible since auto modulate permissive signals would be
received on a high failure of PT-100Y, however this is not the case if PT-100X fails high.
D. Correct.
Given the following conditions:
• Unit 1 was operating at 100% power.
• Reactor Power Cutback System was out of service for testing.
• A Main Turbine trip occurred.
• The Reactor Protection System failed to trip the reactor, resulting in an ATWS.
How will the Supplemental Protection System (SPS) respond to trip the reactor?
SPS will open…
1. Reactor Trip Circuit Breakers
2. L03 and L10 supply breakers
3. CEDMCS MG Set output contactors
A. 1 ONLY
B. 2 ONLY
C. 1 and 3 ONLY
D. 2 and 3 ONLY
C
A. Plausible since the RTCBs do open and on an ATWS, however CEDMCS MG Set output
contactors also open on an SPS signal.
B. Plausible since this is the manual action taken by the crew in the event of an ATWS, however SPS
does not open these breakers automatically.
C. Correct.
D. Plausible since the CEDMCS MG Set output contactors do open on an SPS signal, and L03 and
L10 breakers are manually opened by the crew in response to an ATWS, however L03 and L10
are not opened by SPS.
Given the following conditions:
• Unit 2 is operating at 100% power, MOC.
• A SGTL is in progress on SG #1.
• RU-139, Main Steam Line – SG #1, is in HIGH ALARM.
• RU-141, Condenser Vacuum /Gland Seal Exhaust, is in HIGH ALARM.
• Both alarms have been confirmed to be valid.
Per 74AL-9SQ01, Radiation Monitoring System Alarm Validation and Response, the crew
will _____(1)_____ in response to the high alarm on RU-139 and will _____(2)_____ in
response to the high alarm on RU-141.
A. 1. secure blowdown from SG #1
2. perform 40DP-9ZZ14, Contaminated Water
Management
B. 1. secure blowdown from SG #1
2. ensure the Post Filter Mode Select Switch, is in the
THRU FILTER MODE
C. 1. ensure AFA-P01 is not running
2. perform 40DP-9ZZ14, Contaminated Water
Management
D. 1. ensure AFA-P01 is not running
2. ensure the Post Filter Mode Select Switch, is in the
THRU FILTER MODE
B
A. First part is correct. Second part is plausible since this action is directed in the Excessive RCS
Leakrate (for SGTL) AOP and is a logical action to take in response to high activity in the main
steam line, however this is not directed in the RM ARP.
B. Correct.
C. First part is plausible since use of AFA-P01 with a SGTL in progress creates a direct release to the
environment, however this action is not directed in the RM ARP. Second part is plausible since
this action is directed in the Excessive RCS Leakrate (for SGTL) AOP and is a logical action to
take in response to high activity in the main steam line, however this is not directed in the RM
ARP.
D. First part is plausible since use of AFA-P01 with a SGTL in progress creates a direct release to the
environment, however this action is not directed in the RM ARP. Second part is correct.
Given the following conditions:
• Unit 1 has tripped from 100% power due to a loss of both Main Feedwater Pumps.
• AFA-P01 and AFB-P01 are unavailable for use.
• The CO has started AFN-P01 and commenced feeding both SGs.
Subsequently:
• An inadvertent Train ‘A’ SIAS occurred.
• The CO has taken the AFN-P01 handswitch to the “START” position one time.
AFN-P01…
A. is running and feeding both SGs.
B. is running, but not feeding either SG due to the Main Feedwater Block Valves
losing power.
C. is NOT running. The handswitch must be taken to “STOP” then “START” to start
the pump.
D. is NOT running. The pump can be started solely by taking the handswitch
directly to “START”.
Proposed Answer:
C
A. Plausible as this would normally start AFN, however the normal starting circuit is blocked due to
the inadvertent SIAS. Since AFN was initially lined up to feed, feeding would recommence if AFN
was running.
B. Plausible as this would normally start AFN, however the normal starting circuit is blocked due to
the inadvertent SIAS. Plausible that the SG would not be feeding since SIAS does kill power to
the block valves, however those valves fail as is.
C. Correct. Taking the handswitch to stop overrides the SIAS stop signal and taking the handswitch
back to start will start the pump.
D. Plausible as the pump will need to be manually started following the SIAS signal, however it must
be taken to stop first in order to start the pump.
- During a station blackout, the PREFERRED Class 4kV Bus to align an SBOG to is
________ . - Aligning the SBOG to the preferred bus within one hour of the blackout should provide
enough electrical capacity to satisfy the coping time of ________ hours.
A. 1. PBA-S03 2. 4 B. 1. PBA-S03 2. 16 C. 1. PBB-S04 2. 4 D. 1. PBB-S04 2. 16
B
A. First part is correct. Second part is plausible since 4 hours used to be the blackout coping time at
PVNGS, however modifications have increased that time to 16 hours.
B. Correct.
C. Plausible that the SBOG would be aligned to PBB-S04 since it is the fire hardened class bus and
alignment to PBB-S04 is allowed, however PBA-S03 is preferred since energizing the battery
chargers on train A ensures continued availability of the steam driven aux feedwater pump.
Second part is plausible since 4 hours used to be the blackout coping time at PVNGS, however
modifications have increased that time to 16 hours.
D. Plausible that the SBOG would be aligned to PBB-S04 since it is the fire hardened class bus and
alignment to PBB-S04 is allowed, however PBA-S03 is preferred since energizing the battery
chargers on train A ensures continued availability of the steam driven aux feedwater pump.
Second part is correct.
Given the following conditions:
• Unit 1 tripped from 100% power due to a loss of off-site power.
• The crew is verifying natural circulation has been established.
As natural circulation flow develops, the crew should expect to see loop ΔT indicating
_____(1)_____ 65°F and should expect a delay of approximately _____(2)_____ before the
RCS temperature response of feeding and steaming adjustments can be verified.
A. 1. less than 2. 1 to 2 minutes B. 1. less than 2. 5 to 15 minutes C. 1. greater than 2. 1 to 2 minutes D. 1. greater than 2. 5 to 15 minutes
B
A. First part is correct. First part is correct. Second part is plausible since frequent adjustments of
steaming and feeding are needed when controlling in manual (as is the case in a LOOP/LOFC) in
order to maintain parameters within post-trip control bands, however in natural circulation
conditions, the plant response to these adjustments will not be seen for ~ 5 to 15 minutes.
B. Correct.
C. First part is plausible since the driving head in natural circulation is developed by the difference in
density between the hot and cold legs, therefore a higher delta-T than with forced circulation is
plausible, however delta-T must be < 65°F (full power delta-T) in natural circulation conditions.
Second part is plausible since frequent adjustments of steaming and feeding are needed when
controlling in manual (as is the case in a LOOP/LOFC) in order to maintain parameters within posttrip
control bands, however in natural circulation conditions, the plant response to these
adjustments will not be seen for ~ 5 to 15 minutes.
D. First part is plausible since the driving head in natural circulation is developed by the difference in
density between the hot and cold legs, therefore a higher delta-T than with forced circulation is
plausible, however delta-T must be < 65°F (full power delta-T) in natural circulation conditions.
Second part is correct.
Given the following conditions:
• Unit 2 is operating at 100% power.
• Inverter PNC-N13 Bypass Disconnect Switch is in the Static Switch to Load position.
• The supply breaker to inverter PNC-N13 was inadvertently opened at PKC-M43.
Based on these conditions, PNC-D27 will…
A. NOT automatically align to its alternate power supply. Power can be restored by
manually pressing the Reverse Transfer pushbutton.
B. Automatically align to its alternate power supply and will automatically transfer back
to its normal source when the inverter is re-energized.
C. NOT automatically align to its alternate power supply. Power can be restored by
manually placing the Bypass Disconnect Switch to the Bypass Switch to Load
position.
D. Automatically align to its alternate power supply and can be manually realigned to
its normal source when the inverter is re-energized by pressing the Forward
Transfer pushbutton.
D
A. Plausible that it will NOT auto align to the alternate source since unit 1 does not have static
switches with automatic switching capabilities. Also, the examinee may very well think that the
reverse transfer pushbutton reverses the last transfer, which would realign the bus to the normal
source.
B. Plausible since it will auto transfer to the alternate source, however it will not auto transfer back to
the normal source.
C. Plausible that it will NOT auto align to the alternate source since unit 1 does not have static
switches with automatic switching capabilities. Also plausible that the transfer would not
automatically happen since the bypass disconnect switch is in the STATIC (meaning not moving)
position.
D. Correct.
Given the following conditions:
• Unit 1 has tripped from 100% power due to a complete loss of feed water.
• A fault on PKA-M41 has caused the ‘A’ Battery Charger Output Breaker,
PKA-M4104, to trip.
• AFA-P01 and AFB-P01 are unavailable for use.
In order to start Auxiliary Feedwater Pump AFN-P01, the crew must dispatch an AO to
manually _____(1)_____ and once AFN-P01 has been started, feed flow to both SGs
_____(2)_____ .
A. 1. open AFN-P01 Suction Valves HV-1 and HV-4
2. can be controlled from the control room
B. 1. open AFN-P01 Suction Valves HV-1 and HV-4
2. must be controlled via manual valve operation in
the field
C. 1. align AFN-P01 control power to the alternate source
2. can be controlled from the control room
D. 1. align AFN-P01 control power to the alternate source
2. must be controlled via manual valve operation in
the field
C
A. First part is plausible since HV-1 and HV-4 must be open to start AFN-P01 and both valves are
train ‘A’ motor operated valves, however the control power is AC. Second part is plausible since
AFA would require manual valve operation in the field to feed the SGs, however the feed valves
from AFN-P01 would still be able to be controlled from the control room.
B. First part is plausible since HV-1 and HV-4 must be open to start AFN-P01 and both valves are
train ‘A’ motor operated valves, however the control power is AC. Second part is correct.
C. Correct.
D. First part is correct. Second part is plausible since AFA would require manual valve operation in
the field to feed the SGs, however the feed valves from AFN-P01 would still be able to be
controlled from the control room.
Given the following conditions:
• Unit 2 is operating at 100% power.
• There was a leak in the Nuclear Cooling Water System header which resulted in a
complete loss of NC.
• Train ‘A’ Essential Cooling Water has been cross-connected to NC per 40AO-9ZZ03,
Loss of Cooling Water.
1. Which of the following identifies the ESFAS signal that will automatically close EWA-UV-
65 and EWA-UV-145, Cross-Tie Valves to/from Nuclear Cooling Water?
2. What is the purpose of these valves closing?
A. 1. SIAS
2. To ensure Containment Isolation is maintained
during accident conditions.
B. 1. SIAS
2. To ensure adequate cooling flow to the SDCHX
during accident conditions.
C. 1. CSAS
2. To ensure Containment Isolation is maintained
during accident conditions.
D. 1. CSAS
2. To ensure adequate cooling flow to the SDCHX
during accident conditions.
B
A. First part is correct. Second part is plausible since the NC system is divorced from the EW system
on the SIAS, however containment isolation is maintained by either the CIAS or CSAS signals.
B. Correct.
C. First part is plausible since CSAS does isolate NC valves to containment, however SIAS closes
the EW-NC cross-tie valves. Second part is plausible since the NC system is divorced from the
EW system on the SIAS, however containment isolation is maintained by either the CIAS or CSAS
signals.
D. First part is plausible since CSAS does isolate NC valves to containment, however SIAS closes
the EW-NC cross-tie valves. Second part is correct.
Given the following conditions:
• Unit 2 tripped from 100% power due to a seismic event.
• ADVs are being used to maintain SG pressures in their normal post-trip bands.
Subsequently:
• A complete loss of Instrument Air occurred in the Turbine Building.
1. Due to the loss of Instrument Air, ADVs will ________ .
2. When backup nitrogen is aligned, the ADVs can be operated for a MINIMUM of ________ .
A. 1. remain open due to backup nitrogen automatically
aligning to the ADVs
2. 2 hours
B. 1. remain open due to backup nitrogen automatically
aligning to the ADVs
2. 13.3 hours
C. 1. drift closed until backup nitrogen is manually
aligned to the ADVs
2. 2 hours
D. 1. drift closed until backup nitrogen is manually
aligned to the ADVs
2. 13.3 hours
B
A. First part is correct. Second part is plausible since 2 hours is the amount of time the ADVs would
remain operational following a loss of DC power, however on a loss of IA, there will be 13.3 hours
of operational time.
B. Correct.
C. First part is plausible since the ADV does fail closed on a loss of instrument air, and this would be
the correct failure method if nitrogen had to be manually aligned, however nitrogen is automatically
aligned keeping the ADV in its current position on the loss of IA. Second part is plausible since 2
hours is the amount of time the ADVs would remain operational following a loss of DC power,
however on a loss of IA, there will be 13.3 hours of operational time.
D. First part is plausible since the ADV does fail closed on a loss of instrument air, and this would be
the correct failure method if nitrogen had to be manually aligned, however nitrogen is automatically
aligned keeping the ADV in its current position on the loss of IA.
Given the following conditions:
• Unit 3 is operating at 2% power.
• CEAs are being withdrawn for a power ascension.
• On the last CEA pull, Regulating Group 4 CEA 18 continued to withdraw after releasing
the Withdraw/Insert Switch on B04.
• CEDMCS Mode Selector Switch was placed in Standby and CEA 18 stopped moving.
• CEA 18 stopped moving at 64” withdrawn.
• All other Regulating Group 4 CEAs are 56.5” withdrawn.
• I&C was able to quickly determine and correct the issue with CEA 18.
1. Per 40AO-9ZZ11, CEA Malfunctions, the crew will restore group alignment
by _____(1)_____ .
2. Per LCO 3.1.5, CEA Alignment, Condition A, the two-hour completion time for re-aligning
CEA 18 starts _____(2)_____ was >6.6 inches from the rest of Group 4.
A. 1. inserting CEA 18 to within 6.6”of Regulating Group 4
2. the moment CEA 18
B. 1. inserting CEA 18 to within 6.6” of Regulating Group 4
2. no more than two hours after CEA 18
C. 1. withdrawing the other 7 Regulating Group 4 CEAs to
within 6.6” of CEA 18
2. the moment CEA 18
D. 1. withdrawing the other 7 Regulating Group 4 CEAs to
within 6.6” of CEA 18
2. no more than two hours after CEA 18
A
A. Correct.
B. First part is correct. Second part is plausible since LCO 3.1.7, Regulating CEA Insertion Limits,
contains a note stating “This LCO is not applicable while conducting SR 3.1.5.3 or for up to 2
hours following a reactor power cutback”.
C. First part is plausible since Appendix I, CEA Realignment, allows for moving the non-affected
CEAs to realign all CEAs to within 6.6” of each other, and since a power ascension is in progress,
it would make sense to continue moving rods out instead of in, however this is only directed if the
affected CEA cannot be moved. Compliance with LCO 3.1.5 is the correct reason for the CEA
realignment. Second part is correct.
D. First part is plausible since Appendix I, CEA Realignment, allows for moving the non-affected
CEAs to realign all CEAs to within 6.6” of each other, and since a power ascension is in progress,
it would make sense to continue moving rods out instead of in, however this is only directed if the
affected CEA cannot be moved. Second part is plausible since LCO 3.1.7, Regulating CEA
Insertion Limits, contains a note stating “This LCO is not applicable while conducting SR 3.1.5.3 or
for up to 2 hours following a reactor power cutback”.
Given the following conditions:
• Unit 2 has tripped from 100% power.
• A boration is required to meet Reactivity Control acceptance criteria in SPTAs.
Assuming depressurizing the RCS for HPSI injection is NOT desired, which ONE of the
following conditions or failures would require the use of local manual valve operation in order
to borate the RCS?
A. Refueling Water Tank level of 65%.
B. A loss of BOTH Boric Acid Makeup Pumps.
C. Boric Acid Flow Controller CHN-FIC-210Y fails to zero output.
D. Makeup to CHRG PMPS (VCT Bypass) CHN-UV-527 seized closed.
A
A. Correct.
B. Plausible since the normal boration flowpath utilizes at least one Boric Acid Makeup Pump,
however in this condition a boration may still be performed using Appendix 103-D using CHE-HV-
536, and all actions can be taken from the control room.
C. Plausible since the normal boration flowpath goes through CHN-FV-210Y (controlled by CHN-FIC-
210Y), however if this controller is not available, the boration may still be achieved from the control
room using Appendix 103-D using CHE-HV-536.
D. Plausible since the normal boration flowpath goes through CHN-UV-527, however if this controller
is not available, the boration may still be achieved from the control room using Appendix 103-D
using CHE-HV-536.
Given the following conditions:
• A reactor startup following a refueling outage is in progress on Unit 2.
• The reactor is at the ECP -1000 pcm position.
Subsequently:
• The Channel ‘A’ Log Safety Channel NI failed low due to a transmitter failure.
Based on the listed conditions, what LCO actions, if any, must be taken in response to this
failure?
‘A. Immediately determine RCS boron concentration per LCO 3.3.12, Boron Dilution
Alarm System.
B. Immediately suspend positive reactivity additions per LCO 3.9.2, Nuclear
Instrumentation.
C. Place the applicable RPS bistables in bypass or trip within one hour per LCO 3.3.1,
RPS Instrumentation – Operating.
D. Place the applicable RPS bistables in bypass or trip within one hour per LCO 3.3.2,
RPS Instrumentation – Shutdown.
Proposed Answer:
D
A. Plausible since LCO 3.3.12 is applicable in MODE 3 and a failure of an NI will result in LCO 3.3.12
not being met, however the NIs which are required by LCO 3.3.12 are the startup NIs, not the log
power NIs.
B. Plausible since LCO 3.9.2 requires two NIs to be operable, however LCO 3.9.2 is only applicable
in MODE 6.
C. Plausible since this is the correct action to take, however LCO 3.3.1 is only applicable in MODEs 1
and 2 and at the -1000 pcm position, the unit is in MODE 3.
D. Correct.
Given the following conditions:
• Unit 1 is operating at 50% power.
• Main Condenser vacuum is 7.0 inches HgA and slowly degrading.
• The CRS has entered 40AO-9ZZ07, Loss of Condenser Vacuum.
What action should the CRS direct and what is the reason for this action?
The CRS should direct a…
A. Reactor trip due to the imminent loss of both Main Feedwater Pumps.
B. Reactor trip due to the inability of SBCS to accommodate a load rejection at this power
level.
C. Main Turbine trip to prevent damage to the Main Condenser due to the degrading
vacuum.
D. Main Turbine trip due to the ability of the Reactor Power Cutback System and RCS to
accommodate a turbine trip from this power level.
B
A. Plausible since the MFPs do trip on degraded vacuum, however the main turbine will trip first at
7.5” which will result in the reactor tripping on high RCS pressure within ~ 10 seconds of the
turbine trip, therefore the loss of both main feedwater pumps will not happen until after the reactor
trips on high RCS pressure.
B. Correct. Each SBCS valve can accommodate ~ 8% steam load and with only 2 SBCS valves
available, a turbine trip would result in the reactor tripping on high RCS pressure and challenge
primary relief valves.
C. Plausible since the condenser may incur damage due to degrading vacuum, however a turbine trip
with only 2 SBCS valves available at 50% power will challenge primary relief valves.
D. Plausible since the RPCB system would be able to accommodate a load rejection from this power
level, however RPCB is taken out of service at < 74% power, therefore a turbine trip at this level
would result in a high RCS pressure reactor trip.
Given the following conditions:
• A leak has occurred on a Waste Gas Decay Tank due to a crack in the tank wall.
• The waste gas is escaping to outside atmosphere through the Plant Vent.
Before the waste gas exits through the Plant Vent, the waste gas will be monitored by
Radiation Monitor _____(1)_____ and will be filtered by _____(2)_____ .
A. 1. RU-12, Waste Gas Decay Tank Monitor
2. GRN-F01, Gaseous Discharge Filter
B. 1. RU-12, Waste Gas Decay Tank Monitor
2. HRN-J01A/B, Radwaste Building Normal AFUs
C. 1. RU-15, Waste Gas System Area Combined
Ventilation Exhaust Monitor
2. GRN-F01, Gaseous Discharge Filter
D. 1. RU-15, Waste Gas System Area Combined
Ventilation Exhaust Monitor
2. HRN-J01A/B, Radwaste Building Normal AFUs
D
A. First part is plausible since RU-12 does monitor WGDT releases, however only during a normal
WGDT release. Second part is plausible since the Gaseous Discharge Filter does filter WGDT
release gas, however only during a normal release.
B. First part is plausible since RU-12 does monitor WGDT releases, however only during a normal
WGDT release. Second part is correct.
C. First part is correct. Second part is plausible since the Gaseous Discharge Filter does filter WGDT
release gas, however only during a normal release.
D. Correct.
Given the following conditions:
• Unit 3 was tripped from 100% power due to a large break LOCA.
• On the trip, offsite power was lost.
• SPTAs have been completed.
• 40EP-9EO03, LOCA, has been entered.
• Containment temperature is 200°F and slowly rising.
• RCS pressure is currently 500 psia and stable.
• CET temperature is 530°F and stable.
• RCS Thot is 515°F and stable.
• QSPDS CET subcooling indicates 63°F superheat and stable.
• QSPDS RCS subcooling indicates 48°F superheat and stable.
Based on the current conditions, the crew should use _____(1)_____ to determine current
subcooling and determine that core cooling is _____(2)_____ .
A. 1. QSPDS subcooling 2. adequate B. 1. QSPDS subcooling 2. inadequate C. 1. Standard Appendix 2, Figures 2. adequate D. 1. Standard Appendix 2, Figures 2. inadequate
B
A. First part is correct. Second part is plausible if RCS subcooling is used since RCS subcooling is
less than the harsh containment value of 60°F superheat to determine adequate core cooling,
however in natural circulation, CET subcooling is the correct parameter to use.
B. Correct.
C. First part is plausible since subcooling is determined using appendix 2, and appendix 2 is the
required tool to use when RCS pressure is < 350 psia, however at 500 psia QSPDS subcooling is
the correct tool to determine subcooling. Second part is plausible if RCS subcooling is used since
RCS subcooling is less than the harsh containment value of 60°F superheat to determine
adequate core cooling, however in natural circulation, CET subcooling is the correct parameter to
use.
D. First part is plausible since subcooling is determined using appendix 2, and appendix 2 is the
required tool to use when RCS pressure is < 350 psia, however at 500 psia QSPDS subcooling is
the correct tool to determine subcooling. Second part is correct.