2012 Flashcards

1
Q

Which ONE of the following describes ALL the available locations that ALL (4) RTSG breaker positions can be verified after a Reactor Trip.

(1) PPS Status Panel
(2) Supplemental Protection Logic Actuation (SPLA) Cabinets
(3) B05 Phase Current Lights
(4) Locally at the Breaker

A. 1 and 4 Only
B. 1, 2 and 4 Only
C. 2, 3 and 4 Only
D. 1, 2, 3 and 4 Only

A

A. Incorrect: Each SPLA Cabinet has indication of their respective RTSG Breaker
B. Correct: RTSG Breaker position can be verified at these 3 locations
C. Incorrect: PPS status panels do proved indication and the phase current Lights on B05 only show the status of C and D legs not individual breakers
D. Incorrect: Phase current Lights on B05 only show the status of C and D legs not individual breakers

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2
Q
Given the following conditions:
 Unit 1 RCS pressure is at 2000 psia.
 A Pressurizer safety/relief valve is leaking to the RDT.
 The RDT is at 10 psig.
Which ONE of the following describes the temperature of the fluid downstream of the relief valve?
A. 215°F
B. 230°F
C. 240°F
D. 280°F
A

Directions on how to use Mollier Diagram and Steam Tables to determine tailpipe temperature of a
leaking PSV.
1. Find the enthalpy of the saturated vapor using Mollier diagram or Table 2.
2. Plot this on the Saturation Line.
3. Draw a horizontal (constant h) line to the pressure that corresponds to where the device is relieving
to.
4. If this point lies below the saturation line, follow the pressure line up the saturation line to determine
the temperature. If above, compare the point to the Constant Temperature lines.
Any choice is plausible if the examinee does not obtain the specific enthalpy for 2000 psia or is off on
drawing the lines to the correct values.
A. Incorrect: 215 0F corresponds to a RDT pressure of 15 psig if you go down on the curve.
B. Incorrect: 230 0F corresponds to a RDT pressure of 20 psig if you don’t move on the curve.
C. Correct: Steam Tables diagram for a RCS press of 2000 psia and a RDT pressure at 10 psig is
240 0F.
D. Incorrect: 280 0F corresponds to a RDT pressure of 50 psig.

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3
Q

Given the following conditions:
Unit 1 has tripped from 100% power.
Sub-Cooled Margin is 36°F 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 setpoint.
B. SIAS and CIAS ONLY due to exceeding the high containment pressure setpoint
C. SIAS, CIAS and MSIS ONLY due to exceeding the low pressurizer pressure setpoint.
D. SIAS, CIAS and MSIS ONLY due to exceeding the high containment pressure setpoint.

A

A. Correct: SIAS, CIAS and MSIS setpoint is > 3.0 psig in CTMT. SIAS and CIAS setpoint < 1837 psia
PZR Pressure.
B. Incorrect: SIAS/ CIAS setpoint is > 3.0 psig in CTMT.
C. Incorrect: SIAS and CIAS setpoint < 1837 psia PZR Pressure. MSIS is on High Cntmt pressure or
Low SG pressure.
D. Incorrect: SIAS/CIAS and MSIS setpoint is > 3.0 psig in CTMT.

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4
Q

Given the following conditions:
A LOCA event results in a Reactor trip.
Containment Pressure is 3.5 psig and rising.
The SPTAs are in progress.
RCS Subcooling indicates 20 °F.
Which ONE of the following describes the guidance regarding the operation of the RCPs?
A. Trip Two RCPs now (in SPTAs).
B. Trip Four RCPs now (in SPTAs).
C. The CRS shall not direct tripping of RCPs until an ORP is entered.
D. The running RCPs shall remain operating until saturation conditions exist (0 oF subcooling).

A

A. Incorrect – All RCPs are to be secured with subcooling < 24 0F. Candidate may confuse the trip 2
leave 2 strategy with RCS pressure remaining below the SIAS setpoint.
B. Correct – This is the SPTA contingency for loss of subcooling. RCPs should not be operated
without adequate subcooling.
C. Incorrect – The expectation is that these pumps will be secured prior to exiting the SPTAs.
Candidate may think that this is an early step of the LOCA EOP.
D. Incorrect – This does not meet the standards set by the EOP Technical Guideline. Candidate may
understand loss of subcooling as < 0 0F subcooling, not the procedurally directed < 24 0F.

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5
Q

Given the following conditions:
Unit 1 is operating at 100% power.
East and West switchyard voltage dropped to 516 kV.
East and West Bus switchyard Low-Low voltage alarms are locked in.
Which ONE of the following auto/manual action(s) is taken at this time to protect Engineered Safety
Function (ESF) equipment from a “double sequencing” event?
A. Water Reclamation Facility supply breakers will trip open.
B. Start both DGs and maintain them paralleled with offsite power
C. Block the NAN-S01/S02 to NAN-S03/S04 fast bus transfer capability.
D. Ensure that the Main Generator’s gross MVAR output is greater than zero.

A

A. Incorrect. WRF breakers will auto trip with a low voltage and SIAS actuation
B. Incorrect. An option is to start load DG and isolate class buses from offsite power.
C. Correct. actions directed by 41ST-1ZZ02, appendix G
D. Incorrect. ST directs that gross MVAR be less than 0 such that PVNGS is not supporting
switchyard voltage.

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6
Q

Given the following conditions:
Initial Conditions:
Unit 1 is operating at 100% power.
Charging has been secured due to a leak downstream of the Charging Pumps.
40AO-9ZZ04, RCP Emergencies, has been entered.
Subsequently:
The Unit trips due to a LOCA.
Pressurizer pressure is currently 1500 psia and stable.
Containment pressure is 2.1 psig and slowly increasing.
Pressurizer level is 20% and stable.
RCS T-cold is 560°F.
RCS T-hot is 563°F.
RCP 1A seal 2 outlet temperature is 260°F.
RCP 2A seal 2 outlet temperature is 252°F.
Safety Injection flow is adequate.
RCPs 1A/2A have been secured.
Which ONE of the following actions is procedurally required?
A. Trip the 1B/2B RCPs to prevent pump cavitation.
B. Initiate CIAS, containment pressure is greater than setpoint.
C. Isolate Seal bleedoff to the 1A/2A RCPs to prevent seal damage.
D. Override and energize the class pressurizer heaters to restore pressurizer pressure.

A

A. Incorrect: subcooled margin and NPSH requirements are met
B. Incorrect: containment pressure is less than setpoint of 3.0 psig
C. Correct: RCP in stby with no seal injection requires that the Bleed Off valve be closed prior to
exceeding 250 degrees on Seal 2 outlet temperature
D. Incorrect: PZR level is less than 25%, heater cutout

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7
Q

Given the following conditions:
Unit 1 is in Mode 4.
LPSI pump “B” is providing SDC flow.
RCS temperature 325°F.
Auxiliary Spray valve “B” fails open and the following conditions are observed.
LPSI pump “B” amps and flow are oscillating.
Window 2B06A, SDC TRAIN A/B FLOW LO is alarming.
This is an indication of…
A. LPSI pump B “cavitating”.
B. LPSI pump B in a “runout” condition.
C. CHB-HV-530 (RWT to Train B SI Pumps) closing.
D. an inadvertant B train Recirculation Actuation Signal (RAS).

A

A. Correct: these are classic cavitation indications with lowering PZR pressure and stable temperature
B. Incorrect: run out would be high amps and high flow
C. Incorrect: SDC suction is thru SI-HV-655 and LPSI suction valve SI-HV-692 is closed isolating SDC
flow from RWT
D. Incorrect: RAS would trip the LPSI pump

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8
Q

Given the following initial conditions:
Unit 1 has tripped from 100% power.
SIAS/CIAS have automatically initiated.
Pressurizer pressure is 1800 psia and stable.
RCS T-cold is 562 degrees and stable.
Containment pressure is 0.5 psig and stable.
Containment temperature is 115 degrees and stable.
RU-6, Nuclear Cooling Water Radiation Monitor is alarming.
Subsequently the CRS enters 40EP-9EO03, LOCA and directs the following actions.
Stop all RCPs.
Close the Nuclear Cooling Water Containment Isolation valves.
Why were the RCPs secured?
A. Loss of Seal Injection
B. Loss of RCS subcooling.
C. Harsh containment conditions.
D. Loss of cooling water to the RCPs.

A

A. Incorrect. Seal Injection has an automatic isolation on low temperature, examinee may also believe
that it isolates due to a SIAS/CIAS as numerous other CVCS valves.
B. Incorrect. Examinee will have to verify the status of subcooling with the reduced RCS pressure. 564
degrees + 24 = 588 = 1409 psi
C. Incorrect. Examinee will have to verify containment conditions
D. Correct. Examinee will have to know the cooling source of the RCPs and the requirement to secure
them.

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9
Q

Given the following conditions:
Unit 1 is at 30% power while shutting down in preparations for a refueling outage.
Rx coolant pump 1A has tripped
The reactor did not Automatically trip
All attempts to trip the Rx from the control room has failed.
Assuming NO other operator actions, initiating an 80 GPM boration would add…
A. Positive Reactivity to the core and cause RCS Temp to Increase
B. Positive Reactivity to the core and cause RCS temp to decrease
C. Negative reactivity to the core and cause RCS temp to increase
D. Negative reactivity to the core and cause RCS temp to decrease

A

A. Incorrect
B. Incorrect
C. Incorrect
D. Correct

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10
Q

Given the following conditions:
Unit 2 was tripped due to a Steam Generator Tube Rupture.
RCS pressure is 895 psia.
RCS subcooling is 55°F.
Steam Generator #1 pressure is 890 psia.
RU-4 in high alarm.
Steam generator #1 is isolated.
Steam generator #1 level is 78% NR and rising slowly.
Steam generator #2 level is 50% NR and steady.
Which ONE of the following is the preferred method to control level in the isolated steam generator with a
ruptured tube?
A. Steam the #1 steam generator to atmosphere via the ADVs.
B. Bypass the MSIV and steam the #1 steam generator to the condenser.
C. Line-up high rate blowdown to the condenser from #1 steam generator.
D. Lower RCS pressure below #1 steam generator pressure and allow backflow to the RCS.

A

A. Incorrect: This will lower SG pressure to further below RCS pressure which will increase SG level
and spread more contamination.
B. Incorrect: This will lower SG pressure to further below RCS pressure which will increase SG level,
steaming to the condenser would minimize the chance of release to the environment, but still
spread the contamination to the secondary.
C. Incorrect: Blowdown will lower level, but spread contamination to the secondary.
D. Correct: This will lower RCS pressure and reduce level of the SG by moving water into the RCS.
Contamination will be limited by putting the contaminated water back in the RCS.

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11
Q

If there is a station “Blackout” the class (PK) batteries are designed to maintain rated voltage for UP TO

A. 2 hours to provide continuous DC during a Design Basis Event.
B. 4 hours to provide continuous DC during a Design Basis Event.
C. 2 hours to provide sufficient power for the protection and control of transformers and switchgear.
D. 4 hours to provide sufficient power for the protection and control of transformers and switchgear.

A

A. Correct: 2 hours and concurrent DBE-LOCA concurrent with BO as found in FSAR
B. Incorrect: 4 hours is the old rating for the non-lass NK batteries
C. Incorrect: power for the protection and control of transformers is for the non-class NK batteries,
examinee may choose this believing that the ESF transformers use class power
D. Incorrect: 4 hours is the old rating for the non-lass NK batteries

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12
Q

Given the following conditions:
Unit 1 has tripped from 100% power due to a LOOP.
EDG ‘A’ Tripped on Low Lube Oil Pressure.
Which ONE of the following describes the operational status the the PZR Backup Heaters?
________ Backup Heater Banks(s) is/are available.
A. ZERO (0)
B. ONE (1)
C. TWO (2)
D. FOUR (4)

A

A. Incorrect: NBN-S01/S02 and PBA-S04 are de-energized due to the LOOP and the ‘A’ EDG tripped.
These provide power to all other Backup and Proportional Heaters. B class heaters powered from
DG “B” are still available.
B. Correct: Non class heaters come from NGN-L11/12 which are lost on the LOOP. PBB-S04 is the
only energized 4160V bus. There are only two banks of class backup heaters. “A” train lost power
with the DG tripping. The B Class Backup Heater bank is the only bank with power.
C. Incorrect: NBN-S01/S02 and PBA-S04 are de-energized due to the LOOP and the ‘A’ EDG tripped.
These provide power to all other Backup and Proportional Heaters.
D. Incorrect: NBN-S01/S02 and PBA-S04 are de-energized due to the LOOP and the ‘A’ EDG tripped.
These provide power to all other Backup and Proportional Heaters.

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13
Q

Given the following conditions:
Unit 1 is operating at 100% power.
120VAC IE PNL D27 Inverter C Trouble Alarm was received in the Control Room.
The area operator reports that DC power to 120VAC Class IE Inverter PNC-N13 has been lost.
Which ONE of the following describes the restoration of power to PNC?
PNC 120VAC power is restored by…
A. an auto shift to the battery.
B. a manual shift to the battery.
C. an auto shift to the voltage regulator.
D. a manual shift to the voltage regulator.

A

A. Incorrect: The battery is the normal supply to the inverter. Unit 1 is not equipped with a static
transfer switch.
B. Incorrect: The battery is the normal supply to the inverter. If the normal power supply was the
voltage regulator, a manual transfer to the battery would be required.
C. Incorrect: This would be correct in Unit 2 or 3 which is equipped with a Static Transfer switch that
would automatically transfer to the voltage regulator.
D. Correct: Unit 1 is NOT supplied with a Static Transfer switch as in Unit 2 and Unit 3. Therefore on
a loss of Power to the Inverter the operator must manually transfer the power supply from the
inverter to the voltage regulator.

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14
Q

Given the following conditions:
Unit 1 tripped from 100% power due to a Loss of Offsite Power, LOOP.
No ESFAS actuations have been initiated.
AFN-P01 (Essential Steam Driven AFW pump) is supplying feed to the SGs.
The Control Power Transfer Switch (PBA-U01) is selected to it’s alternate feed source from PKAH11.
SG pressure is being controlled with ADVs SGA-HV-179/184.
Both DGs are supplying their respective buses.
With no other Operator actions, what is the immediate operational implications of a loss of the “A” battery
charger, PKA-H11?
A. ADVs (SGA-HV-179/184) will fail closed.
B. DG “A” output breaker (PBA-S03B) can not be tripped from the control room.
C. Downcomer containment isolation valves SGA-UV-172 and SGA-UV-175 fail closed.
D. AFN-P01 (Non Essential Motor Driven Aux Feed Pump) can not be tripped from the control room.

A

A. ADV will lose their permissive as the “A” battery dies and fail closed, NOT IMMEDIATELY
B. DG “A” output breaker can not be tripped on a loss of PKA-M41/D21. NOT IMMEDIATELY
C. Downcomer Isolation fail open on a loss of power. The economizer isolations would close
immediately if aligned to their alternate source PKA-M41.
D. The alternate supply for AFN-P01 is directly from the battery charger.
OPTRNG_

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15
Q

Given the following conditions:
Initial Conditions:
Unit 2 has tripped from 100% power.
SG #1 is 1000 psia and lowering.
SG #1 is 40% WR and lowering.
SG #2 is 800 psia and lowering.
SG #2 is 10% WR and lowering.
PZR level is at 30% and slowly lowering.
Containment Pressure is 1 psig and rising.
At the time that the ORP is entered the conditions are as follows:
Containment pressure peaked and is stable at 9.8 psig.
Containment temperature is 185°F.
PZR level is 18% and rising.
RVUH level is 67%.
RCS subcooling is 98°F.
SG #1 is at 34% WR (rising) and being fed from AFW at 500 gpm.
SG #2 is below the indicated level.
Both HPSI pumps are injecting into the RCS.
Based on these conditions, you should obtain CRS concurrence and throttle HPSI…
A. immediately.
B. when PZR level reaches 33%.
C. when RVUH is equal to 100%.
D. when SG #1 Level is 45%-60% NR.

A

A. Correct – PZR level requirement is > 15% for Harsh CTMT conditions.
B. Incorrect – PZR level requirement for throttling HPSI is > 15% level when in Harsh CTMT
conditions. 33% is the normal PZR Level Band per SPTAs
C. Incorrect – RVUH level must be greater than 16% to throttle HPSI, which it is. Candidate may not
understand RVUH and Plenum relationship.
D. Incorrect – The SG requirement is RESTORING to 45-60% NR level. Candidate may believe that
SG levels must be in the band.

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16
Q

Given the following conditions:

• Unit 1 is tripped from 100% power.
• Containment Pressure is 1.7 psig and rising.
• Containment Temperature is 120 0F and rising.
• Containment Humidity is rising.
• Containment sump levels are rising.
• PZR Pressure is 2250 psia and rising.
• PZR Level is 58% and rising.
• Tcold is 568 0F and rising.
• Subcooled Margin is 58 0F and lowering.
• SG 1 and 2 levels are 30% WR and lowering. Which ONE of the following describes the ongoing
event?
A. RCS Cold Leg LOCA.

B. PZR Steam Space LOCA.

C. Feedline Break (ESD) inside containment.

D. Steam Line Break (ESD) Inside Containment

A

A. Incorrect: CTMT parameters changing are indicative of a LOCA inside the CTMT, Sub
lowering is indicative of a LOCA. Tc and PZR parameters would lower.
B. Incorrect: CTMT parameter and PZR level rising support the PZR Steam Space LOCA as does
lowering subcooling. PZR Pressure would be lowering.
C. Correct: All of these parameters support the Feedline Break inside CTMT.
D. Incorrect: CTMT parameters support the Steam Line Break inside CTMT. Subcooling would rise,
Pressure and Level would lower. ESD procedure will mitigate both the Feedline and Steam Line
breaks.

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17
Q

Given the following conditions:
Unit 1 has experienced a Loss of Instrument Air (IA) to the Containment.
The CRS is implementing 40AO-9ZZ06 (Loss of Instrument Air).
Which ONE of the following valve handswitches must be taken to CLOSE prior to restoring IA to
Containment per 40AO-9ZZ06?
A. CHA-HV-507 (RCP Bleedoff Isolation to RDT)
B. CHA-UV-516 (Letdown to Regen Hx Isolation)
C. WCB-UV-61 (CHW Return HDR Inside CNTMT Isol VLV)
D. NCB-UV-403 (NCW CNTMT Downstream Return Isol VLV)

A

A. Incorrect: This is an IA operated valve inside the CTMT that fails open to allow Seal Bleed Off to
the RDT, it is not to be closed.
B. Correct: Per step 4 of section 3.0, this valve will fail closed but if the handswitch is not taken to
close the valve will open upon restoration of IA and possibly lead to damage of the letdown IXs.
C. Incorrect: This valve is a Motor Operated Valve that will not be affected by the loss of IA, it is the
inside CTMT isolation valve for WC.
D. Incorrect: This valve is a Motor Operated Valve that will not be affected by the loss of IA, it is the
inside CTMT isolation valve for NC.

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18
Q
Given the following conditions:
 Unit 3 is operating at 80%.
 Group 5 CEAs at 120 inches withdrawn.
 All others CEAs at UEL.
 Selected CEA is # 14.
 Selected CEA Group is # 5.
 A malfunction causes CEA 15 to move 12 steps out before STANDBY is selected and motion stops.
Based on this event the pulse counter selected Group position reads...
A. 120 inches.
B. 122.25 inches.
C. 124.5 inches.
D. 129 inches.
A

A. Incorrect: examinee may believe that that the pulse counter uses lowest CEA position (CPCs)
B. Correct: group position is the average position. 129 + 120 + 120 + 120 = 489/4 = 122.25
C. Incorrect: examinee may believe that the pulse counter uses average of high/low
D. Incorrect: examinee may believe that pulse counter uses highest cea position (CPCs)

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19
Q

Given the following conditions:
Multiple channels of CPCs (Lo DNBR) have trip lights illuminated on B05.
The reactor failed to automatically trip.
The CRS has directed the RO to open the supply breakers for L03 and L10 for a minimum of 5
seconds.
Which ONE of the following describes the reason for this action?
The 5 seconds allows time for the…
A. motor generator stop contacts to close.
B. CEAs to drop to the bottom of the core.
C. trip coils to actuate to open L03 and L10 breakers.
D. effects of the motor generator flywheel to taper off interrupting power to the CEAs.

A

A. Incorrect: MG stop contact does not get a signal to actuate, these actions remove power from the
MG set input, therefore no output.
B. Incorrect: CEAs do require to be inserted within 4 seconds per Tech Specs, but this is not the
reason for the 5 second wait.
C. Incorrect: Trip coils inside the breaker have no time delay associated with them, they open
instantaneously.
D. Correct: As the Load Center supplying power to the MG sets is de-energized, the MG set
flywheels will maintain the MG set output as inertial energy is dissipated.
OPTRNG_

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20
Q

Given the following conditions:
Unit 3 operating at 100% power.
RCN-LIC-110 (Pressurizer Level Master Controller) is in “REMOTE-AUTO”.
RCN-HS-110 (Level Control Selector Channel X/Y) is selected to channel ‘Y’.
RCN-HS-100-3 (Pressurizer Heater Control Selector Level Trip Channel) is selected to ‘X’.
A leak develops on the reference leg of RCN-LT-110Y (Level Transmitter 110Y). This leak exceeds
the capacity of the condensing chamber’s ability to keep the reference leg full.
Assuming NO operator action, which ONE of the following describes the plant response?
Pressurizer level indicates ….
A. low, presssurizer heaters will cut-out.
B. low, the standby charging pump will start.
C. high, letdown flow will be lost.
D. high, letdown flow will lower and stabilize at approximately 30 gpm.

A

A. Incorrect: PLCS senses a high level, the heaters cut out at 27% indicated level.
B. Incorrect:PLCS senses a high level, charging pumps will stop not start on deviation from setpoint.
C. Correct: The level control system will sense a high level. Letdown flow increases to maximum.
“Normally running” charging pump stops. Letdown will isolate due to the automatic closure of CHBUV-
0515 upon receipt of a hi-hi regenerative heat exchanger outlet temperature.
D. Incorrect: The level control system will sense a high level. Letdown flow decrease initially to 30
gpm, but not stabilize.

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21
Q

Given the following conditions:
Unit 1 is operating at 100% power.
A waste gas system discharge is in progress.
RU-12 (Waste Gas Decay Tank Discharge) readings are stable.
RU-14 (Radwaste Building Ventilation Exhaust Filter Inlet) is in ALERT.
RU-15 (Waste Gas Area Combined Ventilation Exhaust) is in ALERT.
RU-143 (Plant Vent) readings are rising.
Which ONE of the following describes the event that is occurring?
A. Gas system discharge is exceeding limits, GRN-UV34A/B will auto CLOSE.
B. Gas system discharge is exceeding limits, GRN-UV34A/B will remain OPEN.
C. Waste Gas Decay Tank Leak is in progress, GRN-UV34A/B will auto CLOSE.
D. Waste Gas Decay Tank Leak is in progress, GRN-UV34A/B will remain OPEN.

A

a. Incorrect. RU-12 and RU-143 would both be rising or in alarm if a discharge was exceeding limits.
GRN-UV-34A/B auto close on RU-12 high alarm only.
b. Incorrect. RU-12 and RU-143 would both be rising or in alarm if a discharge was exceeding limits.
GRN-UV-34A/B auto close on RU-12 high alarm only.
c. Incorrect. ARM RU-14/15 and RU-143 would be rising or in alarm for GR system leak. GRN-UV-34A/B
auto close on RU-12 high alarm only.
d. Correct. ARM RU-14/15 and RU-143 would be rising or in alarm for GR system leak. GRN-UV-34A/B
auto close on RU-12 high alarm only.

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22
Q

G conditions:
• Unit 2 Control Room is experiencing a fire.
• The CRS has directed an evacuation of the Control Room.
• 40AO-9ZZ19 (Control Room Fire) has been entered.

Which ONE of the following describes the appropriate actions per the AOP?

A. Initiate a RPCB Loss of Feed Pump from B04.

B. Initiate a boration from the Remote Shutdown Panel.

C. Trip the Reactor by opening the RTSG breakers locally.

D. RTSG Pushbuttons on B05.

A

A. Incorrect: Numerous AOPs use the RPCB Loss of Feed Pump as a means of a rapid down
B. Incorrect: This is the correct action if after the trip is initiated from the CR, and a CEA
doesn’t fully insert into the core.
C. Incorrect: Tripping the Reactor is the correct direction, just not the location. Candidate may
think that due to the CR Fire that all actions must be taken outside of the control room.
D. Correct: Prior to and including Step 2a of the AOP, Steps 2-5 are expected to be performed in the control
room and 2a. states Trip the Reactor.

23
Q

Which of the following combination of valves failing OPEN would cause a loss of Containment Integrity
per Technical Specifications?
CHB-UV-515 (LETDOWN TO REGEN HX ISOL VLV UV-515)
CHA-UV-516 (LETDOWN TO REGEN HX ISOL VLV UV-516)
CHB-UV-523 (REGEN HX OUTLET ISOLATION VLV UV-523)
CHA-HV-524 (CHARGING PUMPS DSCH HDR TO REGEN HX VLV HV-524)
A. CHB-UV-515 and CHB-UV-523.
B. CHB-UV-515 and CHA-HV-524.
C. CHA-UV-516 and CHB-UV-523.
D. CHA-UV-516 and CHA-HV-524.

A

a) Incorrect: CHB-UV-515 does not receive a close signal on CIAS and is not listed in the TRM
T7.0.300 table .
b) Incorrect: CHB-UV-515 does not receive a close signal on CIAS and CHA-HV-524 and is not
listed in the TRM T7.0.300 table
c) Correct: CHA-UV-516 and CHB-UV-523 are the Only Tech Spec Isolation valves in the
letdown system. These valves receive a close signal on CTMT ISOL CIAS) and are listed in
the TRM T7.0.300 table.
d) Incorrect: CHB-UV-516 is a TS CTMT ISOL VLV, CHA-HV-524 and is not listed in the TRM
T7.0.300 table

24
Q

Given the following conditions:
Unit 1 is operating at 100% power.
Pressurizer level is slowly lowering.
RCS temperature is stable.
The in-service letdown control valve CHN-110P is slowly closing.
The CRS implements 40AO-9ZZ02, Excessive RCS Leakrate.
All available charging pumps are running.
Pressurizer level continues to lower.
40AO-9ZZ02 (Excessive RCS Leakrate) now directs…
A. isolating letdown to quantify leakage for E-plan classification.
B. an immediate reactor trip to minimize dose rates at the site boundary.
C. an immediate reactor trip due to leakage is excess of Tech Spec limits.
D. isolating letdown to determine if leakage exceeds CVCS makeup capacity.

A

A. Incorrect: The E-plan numbers are determined by performing appendix A/B of 40AO-9ZZ02.
B. Incorrect: Tripping the Reactor is determined as thresholds are exceeded after completing the
next step to isolate letdown then trip if Pzr level continues to lower.
C. Incorrect: TS limits are defined and if not met to be in mode 3 within 6 hours, not to trip
immediately. Candidate may think the TS limits are trip thresholds. The next step is to isolate
letdown then trip if Pzr level continues to lower.
D. Correct: Isolating letdown eliminates the Letdown system as a possible location of the leak, Plant
operation is allowed if the leak is isolated as exhibited by the restoration of Pzr Level. The step of
the procedure is to isolate letdown and determine if CVCS makeup capability is exceeded if so then
trip reactor

25
Q

Given the following conditions:
Unit 1 has been in a Blackout condition for 3 hours.
The crew is performing actions of 40EP-9EO08 (Blackout).
PBA-S03 has been energized by ONE Station Blackout Generator (SBOG) per Standard Appendix
80.
Attempts to restore power from other sources have been unsuccessful.
Natural circulation flow CAN NOT be verified.
In accordance with the Blackout procedure, which ONE of the following describes the action(s) that will be
taken by the crew?
A. Use Auxiliary Spray to lower RCS pressure.
B. Commence a cooldown to shutdown cooling entry conditions.
C. ENSURE Train “A” ADVs are throttled adequately to maintain RCS subcooling.
D. OVERRIDE and ENERGIZE Train “A” class backup heater to stabilize RCS pressure.

A

A. Incorrect - Lowering RCS pressure will cause subcooled margin to lower, which will not promote
natural circulation conditions.
B. Incorrect - This step is not required be performed unless AC power is not restored. PBA-S03 has
been energized with a SBOG.
C. Correct - Per Step 21 Blackout EOP, if the conditions are met, ENSURE proper control of steam
generator steaming and feeding.
D. Incorrect - Raising pressure would improve subcooling and promote natural circulation conditions.
But Pressurizer Level is below the heater cutout setpoint, therefore Heaters are not available.

26
Q

Given the following conditions:
• The Unit 2 CRS has entered the Functional Recovery procedure.
• RWT level is 6.4%.
• You have been directed to verify proper Recirculation Actuation Signal (RAS).
Which ONE of the following actions must be manually performed given a proper “A” train RAS
actuation?
A. Stop SIA-P01, LPSI pump A

B. Close SIA-UV-666, HPSI A pump Recirc valve

C. Open SIA-UV-674, Cntmt Sump to Safety Injection Valve
D. Close CHA-HV-531, RWT to Train A Safety Injection Valve

A

A. Incorrect: LPSI pump are tripped on a RAS actuation.
B. Incorrect: All SI miniflow valves close on RAS actuation.
C. Incorrect: RAS sump isolation valves open on RAS actuation.
D. Correct: RWT isolation valves must be manually operated on RAS actuation.

27
Q

Given the following conditions:
Unit 1 is operating at 100% power.
RCP 1A experiences a failure causing it to slow down at 1% per minute.
Assuming that all other input parameters remained the same, the CPC calculated value of DNBR will …
A. not change until RCP speed reaches 95% of rated speed, then a DNBR trip will occur.
B. not change until RCP speed reaches 95% of rated speed, then an Auxiliary trip will occur.
C. gradually lower until RCP speed reaches 95% of rated speed, then a DNBR trip will occur.
D. gradually lower until RCP speed reaches 95% of rated speed, then an Auxiliary trip will occur.

A

A. Incorrect: Pump Speed is input to the Flow calculation which is used in the DNBR calculation. DNBR
will reduce as speed drops. A DNBR trip will be generated when RCP speed reaches 95%.
B. Incorrect: Pump Speed is input to the Flow calculation which is used in the DNBR calculation. DNBR
will reduce as speed drops. The auxiliary trip monitoring RCPs is generated when less than 2 RCPs
are running.
C. Pump Speed is input to the Flow calculation which is used in the DNBR calculation. DNBR will
reduce as speed drops. A DNBR trip will be generated when RCP speed reaches 95%.
D. Incorrect: DNBR will reduce as speed drops then generate a DNBR trip.The auxiliary trip monitoring
RCPs is generated when less than 2 RCPs are running.

28
Q

Given the following conditions:
• Nuclear Cooling Water (NC) has been lost due to a pipe rupture.
• Train ‘B’ Essential Cooling Water (EW) has been cross-connected to NC.
Which ONE of the following describes a condition that will isolate ‘B’ Essential Cooling Water to
the
RCPs?
A. Containment pressure rises to 9.0 psig.
B. Pressurizer pressure drops to 1800 psia.
C. Instrument air header pressure drops to 60 psig.
D. ‘B’ EW Surge Tank level drops to LO LEVEL setpoint.

A

A. Correct: Containment Spray Actuation Signal (CSAS) at 8.5 psig will close the CTMT Isolation
Valves for the NC system which are downstream of the EW cross tie valves.
B. Incorrect: EW ‘A’ will isolate on SIAS EW ‘B’ cross tie valves are manually operated valves
with no automatic features.
C. Incorrect: NC and EW valves are Motored Operated valves, the degraded Instrument Air Header
pressure will not effect EW to RCPs. 40AO-9ZZ06 (Loss of IA) describes hundreds of components that
are effected by the lowering IA header pressure.
D. Incorrect: LO ‘A’ EW Surge Tank Level. EW ‘B’ cross tie valves are manually operated valves with no automatic features.

29
Q

Given the following conditions:
• Unit 3 is operating at 100% power.
• All RCP seal injection controllers (CHN-FIC-241-244) are in automatic.
• The output SIGNAL of CHN-FIC-241, 1A RCP controller, is rising.
• Disregard the response of the remaining Seal Injection controllers.

Which ONE of the following describes the cause?

A. NNN-D11 is de-energized.

B. Inadvertent CSAS actuation.

C. Actual Seal Injection flow is below setpoint.

D. Regenerative Heat Exchanger outlet temperature has exceeded 413°F.

A

Justification:
A. Incorrect: Loss of NNN-011 will de-energize the controller therefore the output will be
failed as is.
B. Correct: CSAS actuation will isolate IA to the Containment and valves will slowly open,
therefore controller will try to lower flow by raising output. These controllers are reverse
acting.
C. Incorrect: Actual Flow less than setpoint will cause the controller output to lower.
Reverse Acting Controller.
D. Incorrect: This will provide a close signal to CHB-UV-515, This Loss of Letdown will not
effect seal injection flow.

30
Q

Given the following plant conditions:
• Refueling pool level is 137’ 6’ (>23 ft above the vessel flange).
• Core RE-LOAD is in progress.
• An irradiated fuel assembly is grappled and in the hoist box.
• Train ‘B’ is under clearance for maintenance.
• Train ‘A’ LPSI pump is gas bound.
Which ONE of the following complies with Technical Specifications 3.9.4 (Shutdown Cooling (SDC) and
Coolant Circulation - High Water Level) required actions ?

A. Core re-load may continue.

B. Immediately stop core re-load, leave the fuel assembly in the hoist box.

C. Complete placing the fuel assembly in its designated core location, then suspend core
re-load.

D. Immediately stop core re-load until you have verification that all activities that could
result in boron dilution have been suspended.

A

Justification:
A. Incorrect: Core Off Load would be permitted in this instance but Core Re Load would add
energy to the core.
B. Correct: Per TS 3.9.4 One SOC Cooling Loop shall be operable and in operation. The fact
that B has no power and A is gas bound Condition A is not met and loading irradiated fuel must be
suspended immediately.
C. Incorrect: The fuel assembly would be placed back in its original position in the Spent
Fuel Pool not the Core.
O. Incorrect: Immediately suspending core reload is correct but once the boron concentration
reduction is verified to not exist you may not restart the core re load.

31
Q

RCS Low Temperature Overpressure protection is provided by the LTOPs. Which ONE of the following
describes the Train ‘A’ LTOP?

Train ‘A’ LTOP is located between valves (1) and (2) , and lifts at (3) psig.
A. (1) SIA-UV-651 (2) SIC-UV-653 (3) 410

B. (1) SIC-UV-653 (2) SIA-UV-655 (3) 410

C. (1) SIA-UV-651 (2) SIC-UV-653 (3) 467

D. (1) SIC-UV-653 (2) SIA-UV-655 (3) 467

A

A. Incorrect: Wrong Location and setpoint. 410 psia is the setpoint for the SIT isolation
valves.
B. Incorrect: Correct Location wrong setpoint. 410 psia is the setpoint for the SIT
isolation valves.
C. Incorrect: Wrong Location and correct setpoint
D. Correct: This is the Correct Location and setpoint.

32
Q

Given the following conditions:
Unit 2 is at 100% power.
PSV-203 (PZR safety valve) has seat leakage.
Reactor Drain Tank (RDT) level is rising.
RDT pressure is 7.5 psig and rising slowly.
Window 3A07A (REAC DRN LOOP TRBL) is alarming.
Window 3A07B (REAC DRN TK PRESS HI) is alarming.
Which one of the following conditions is correct?
The Alarm Response procedure (40AL-9RK3A) directs the crew to vent the RDT to ….
A. containment before it isolates at 10 psig.
B. containment before it ruptures at 10 psig.
C. the gas surge header before it isolates at 10 psig.
D. the gas surge header before it ruptures at 10 psig.

A

A. Incorrect: Between 5 and 10 psig the ARP directs venting to the Gas Surge header, the RDT does
isolate at 10 psig.
B. Incorrect: Between 5 and 10 psig the ARP directs venting to the Gas Surge header, and the RDT
isolates at 10 psig not ruptures.
C. Correct: Between 5 and 10 psig the ARP directs venting to the Gas Surge header, and the RDT
isolates at 10 psig. CHN-UV-540 (Gas Surge Header) and CHA-UV-560 (containment isolation)
both close.
D. Incorrect: Between 5 and 10 psig the ARP directs venting to the Gas Surge header, but the RDT
isolates at 10 psig not ruptures.

33
Q

Given the following conditions:
Unit 1 is operating at 100% power.
NCN-P01A (NCW PUMP A) is in operation with NCN-P01B (NCW PUMP B) in standby.
The A Emergency Diesel Generator is under permit for maintenance.
NBN-X03 ESF Service Transformer fails.
This loss does NOT result in a Reactor Trip.
Based on these conditions, the Nuclear Cooling Water system will…
A. have no pumps running.
B. be unaffected (no change in pump operation).
C. remain in operation, NCN-P01B running and NCN-P01A off.
D. remain in operation, with both NCN-P01A and NCN-P01B running.

A

A. Incorrect: Candidate may think that the NCW pumps are powered from PB buses and
may think this situation has resulted in a loss of power to both.
B. Correct: NCW pumps are powered from non-class 4160v busses NBN-S01 and NBNS02.
Losing transformer NBN-X03 with the A Diesel Generator tagged out will result in
a loss of Class 4160v power on the A train, but will not affect power to the NCW
pumps.
C. Incorrect: May think that PBA has lost power and NCW A with it, NCW B would start on
low header pressure.
D. Incorrect: May think that the power transfer from off site to the EDG would result in both
pumps running.

34
Q

Given the following conditions:

•   Unit 2 has experienced a LOCA.
•   PZR Temperature is 470°.
•   PZR Pressure is 300 psia.
Which ONE of the following describes the state of the PZR fluid?
A.  Saturated water
B.  Saturated steam
C.  Subcooled water
D.  Superheated steam
A

A. Incorrect: The temperature at which water first begins to evaporate into steam, while under a
given
pressure, such as 14.7 psia (atmospheric pressure), is known as the saturation temperature.Water at
this temperature and pressure configuration is said to be “saturated water.”
B. Incorrect: The mixture is defined as saturated vapor (or dry vapor) at the point when the last
of the d off and becomes vapor. The further addition of heat will now increase the
temperature of the vapor.
C. Incorrect: A subcooled liquid or compressed liquid is defined as a liquid existing to
the left of the
urated liquid line.
D. Correct: Superheated vapor is defined as vapor heated beyond the saturated Vapor State

35
Q

The DNBR/LPD Reactor Protection System Operational Bypass is inserted (1) when the Excore NI Power decreases below (2) %
A. (1) manually (2) 1E-2%.

B. (1) manually (2) 1E-4%.

C. (1) automatically (2) 1E-2%.

D. (1) automatically (2) 1E-4%.

A

A. Incorrect: It is inserted manually but is enabled below 1E-4%. 1E-2% is the Log Power
Bypass.
B. Correct:The bypass must be manually inserted from key switches at the remote CPC modules on
B05 when ex-core safety channel NI power is less than 10-4% power.
C. Incorrect: It is inserted manually. 1E-2% is the Log Power Bypass.
D. Incorrect: It is inserted manually.

36
Q

Given the following conditions:

• Unit 1 is operating at 100% power
• 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.

A

A. Incorrect: The operator CAN bypass the A RCS Press Transmitter.
B. Incorrect: In this case the coincidence is 2/3 with the D channel bypassed. 2/4 is the
normal coincidence which would result in a trip.
C. Incorrect: This will not result in any RTSG breakers opening. RTSG breakers do not open on
the specific parameter, only the Channel trip.
D. Correct: Per the explanation above, the hierarchy of the system would cause the D channel
to come out of bypass when the A channel is placed in bypass.

37
Q

Given the following conditions:
• 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 pushbuttons simultaneously on the “A” train.
• Depresses the 1-3 and 2-4 MSIS trip pushbuttons sequentially (push then release) on the “B”
train.
Assuming that SG pressures remains above the MSIS setpoint, 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
pushbutton.

C. no initiation of the “B” train, “A” MSIS can only be reset by depressing both reset
pushbuttons simultaneously.

D. a half leg initiation of the “B” train, “A” MSIS can only be reset by depressing both reset
pushbuttons simultaneously.

A

A. Correct: To initiate an ESFAS actuation both buttons must be pushed sim. pushing and releasing
gives no initiation half leg or otherwise, power is still available to all relays. Resetting
requires that either reset button on the train be depressed.
B. Incorrect: No initiation of the B train will occur, the MSIS can be reset by pushing either Aux
Relay Cabinet Pushbutton.
C. Incorrect: No initiation is correct for the B train, but you don’t have to press both Aux
Relay Cabinet Pushbuttons to reset.
D. Incorrect: No initiation of the B train will occur, but you don’t have to press both Aux Relay
Cabinet Pushbuttons to reset.

38
Q
Given the following conditions:
•   Unit 3 is operating at 100% power.
•   An Inadvertent SIAS has occurred.
Which ONE of the following describes the status of the Containment Normal ACUs?
The Containment Normal ACUs...

A. continue to run.

B. are load shed and must be manually started by an operator.

C. are load shed and will sequence back on after 120 seconds.

D. shift to take suction on elevations 100’ and below in containment.

A

A. Incorrect: Not all HVAC system respond to a SIAS, the AUX Building HVAC system does not
respond to a SIAS.
B. Correct: This is correct, the Containment Normal ACUs will receive a Load Shed signal
on the SIAS and need to be manually restarted by a operator.
C. Incorrect: The Load Shed portion is correct but the 120 Seconds is the time delay
associated with the CEOM ACUs.
D. Incorrect: On a SIAS the Fuel Building HVAC system will shift suctions to the Aux
Building 100 foot elevation and below.

39
Q

Given the following conditions:
• Unit 1 has tripped from 100% power due to a LOCA.
• PZR Pressure is 1500 psia and lowering.
• CTMT Pressure is 6.5 psia and rising.
Which ONE of the following describes the CURRENT status of the Containment Spray System?
The CTMT Spray Pumps are (1)and the CTMT Spray Header Isolation Valves are (2)

A. (1) off (2) open
B. (1) off (2) closed
C. (1) running (2) open
D. (1) running (2) closed

A

A. Incorrect: Candidate may think the valves open on SIAS and the pump starts on CSAS.The CS
pumps start on SIAS when the RCS pressure is <1837 psia or the CTMT > 3.0 psig. The CTMT Spray
Header isolation valves do not open until the CSAS setpoint of 8.5 psig is met.
B. Incorrect: Candidate may think the CS Pump and Valves actuate at the CSAS setpoint.
C. Incorrect: Candidate may not know the CSAS setpoint of 8.5 psia and therefore the full CS
actuation has occurred.
D. Correct The CS pumps start on Sias when RCS pressure is <1837 psia or the CTMT > 3.0 psig.
The CTMT Spray Header isolation valves do not open until the CSAS setpoint of 8.5 psig is met.

40
Q

Given the following conditions:
Unit 2 has tripped from 100% power.
S/G #1 level is 23% WR and lowering rapidly.
S/G #1 pressure is 900 psia and lowering rapidly.
S/G #2 level is 45% WR and lowering slowly.
S/G #2 pressure is 1050 psia and stable.
Subsequently
S/G #1 level is 19% WR and lowering rapidly.
S/G #1 pressure is 780 psia and lowering rapidly.
S/G #2 level is 43% WR and lowering slowly.
S/G #2 pressure is 1050 psia and stable.
Assuming NO operator action, AFA-P01 (Essential Turbine Driven Aux Feed Pump) is…
A. still in standby.
B. operating and aligned to receive steam from BOTH SGs.
C. operating and aligned to receive steam from SG #1 ONLY.
D. operating and aligned to receive steam from SG #2 ONLY.

A

a. Incorrect: Both MOVs will open on the AFAS signal that was received at 25.8% WR on the #1 SG.
Candidate may not know the AFAS setpoint. Also, Candidate may think the D/P lockout of 185
psid will not allow the lower pressure SG to supply steam to AFA-P01.
b. Correct: Both Main Steam Supply valves AUTO open on an AFAS actuation, regardless of which
SG has experienced the low level. In addition, the D/P lockout does NOT impact the operation of
the steam supply valves.
c. Incorrect: Candidate may think only the SG that is below the AFAS setpoint will supply steam to
AFA-P01.
d. Incorrect: Candidate may think only the SG that is INTACT will supply steam to AFA-P01 due to
the D/P lockout.

41
Q

Which one of the followoing describes the operation of the Main Feedwater Pumps during a power ascension above 20% power?

IAW 40OP-9ZZ05 (Power Operations) the second Main Feedwater Pump must be started prior to…

A. Exceeding 60% reactor power
B. Placing 2nd stage Reheat in service
C. MFW Pump suction pressure lowering below 300 psia
D. MFWP discharge pressure and SG delta P dropping below 100 psid.

A

A. Correct
B. Incorrect: Minimum suction pressure for the MFWP is 300 psig. This threshold has you start a third condensate pump
C. Incorrect: 2nd stage Reheat is done after reaching 15% power. This is not a milestone for placing a 2nd MFW pump in service.
D. Incorrect 100psid is the lower limit at 100% power and is not a parameter used for starting a 2nd MFWP.

42
Q

Given the following conditions:
Unit 2 is in Mode 5 following refueling.
Shutdown Cooling in service using LPSI ‘A’.
It is desired to place SDC Train B in a “standby” SDC lineup.
Which ONE of the following describes what must be done prior to placing SDC train B in a standby
lineup?
Recirculate SDC train B from the ….
A. RCS thru only SIB-UV-668 (LPSI Pump B Recirc valve).
B. RWT thru only SIB-UV-668 (LPSI Pump B Recirc valve).
C. RCS thru SIB-HV-690 (S/D Cooling Warmup Bypass valve) and SIB-UV-668 (LPSI Pump B Recirc
valve).
D. RWT thru SIB-HV-690 (S/D Cooling Warmup Bypass valve) and SIB-UV-668 (LPSI Pump B Recirc
valve)

A

a) Incorrect: This would recirculate the SDC loop with the RWT thru the miniflow. This is a valid
alignment that is used to maintain RCS level during reduced inventory operations. This alignment
is only used to maintain an already established level such as midloop.
b) Incorrect: This would recirculate the SDC loop with the RWT thru the miniflow but would not
equalize the entire train and is not directed by the procedure.
c) Incorrect: This is a valid alignment for temperature control using the LP injection valves. This
alignment is used prior to placing the SDC train in service NOT placing it in a standby alignment.
d) Correct: The Precautions and Limitations of the OP describe the fact that an Idle SDC loop may
have a different boron concentration. This lineup is directed by the procedure to equalize boron
concentration.

43
Q

Given the following conditions:

Initial Conditions:

Unit 1 is in Mode 3 following an automatic rx trip
AFN-P01 is feeding both SGs at 350 gpm
AFB-P01 is in STBY
AFA-P01 is in STBY

Subsequently:
Pressurizer pressure lowers to 1700psia

Which one of the following describes the status of the AFW system One minute after the PZR pressure reaches 1700psia.

A

A. Incorrect. AFN will trip and AFB will auto start but will not auto align to feed SGs
B. Incorrect. AFN will trip on the SIAS signal
C. Correct.
D. Incorrect. AFN will trip but the feed path will not isolate. AFB starts but does not auto align to SGs. Only AFAS will auto align feed path.

44
Q

Given the following list of conditions:
1. The BUS XFR SWITCH must be in AUTO
2. A generator trip must have occurred
3. The synchroscope must be on
4. The synch check reley must be satisfied
5. A Unit Aux Transformer trip must have occurred
6. A lockout of the Normal Supply breaker must have occurred
Which one of the following describes the conditins that must be met for an automatic Fast Bus Transfer of NAN-S01 to NAN-S03 to occurr? This is not an all inclusive list.

A. 1, 2 and 4
B. 1, 4 and 6
C. 2, 3 and 6
D. 3, 4 and 5

A

A. Correct
B. Incorrect: 1 and 4 are required but 6 is not
C. Incorrect: 2 is correct but 3 and 6 are not
D. Incorrect: 4 is correct but 3 and 5 are not

45
Q
Given the following conditions:
 Unit 2 has tripped from 100% power.
 NAN-X01 (S/U XFMR #1) has faulted.
 SIAS has actuated.
 EDG 'A' is at 60.1 Hz and 4200 VAC.
 No 86 Lockouts on PBA-S03.
 Normal/Alternate Supply Breakers to PBA-S03 have operated as designed.
Which ONE of the following describes the status of the...
(1) EDG 'A' output breaker?
(2) NHN-M71 Energized/Not Energized?
A. (1) OPEN (2) ENERGIZED
B. (1) CLOSED (2) ENERGIZED
C. (1) CLOSED (2) NOT ENERGIZED
D. (1) OPEN (2) NOT ENERGIZED
A

NAN-X01 (Startup Transformer #1) is the normal supply to NAN-S05 which supplies PBA-S03 thru its
associated ESF Transformer. This fault will cause an undervoltage condition on PBA-S03.
Candidate may not know the S/U XFMR arrangement and believe that PBA-S03 is still being
powered from off site power. EDG ‘A’ meets the requirements to automatically close in on PBAS03 and power the bus. These requirements are Frequency between 59.9 and 60.5 Hz. Voltage
between 4080 and 4300 Volts. No lockouts on the bus. Normal and Alternate supply breakers are
open. Due to the EDG ‘A’ supplying PBA-S03 Amps will be indicated. NHN-M71 is a SIAS Load
Shed Panel that will be de-energized due to the SIAS.
A. Incorrect: (1) EDG ‘A’ meets the requirements to automatically close in on PBA-S03 and power the
bus. (2) Due to the EDG ‘A’ supplying PBA-S03 Amps will be indicated. (3) NHN-M71 is a SIAS
Load Shed Panel that will be de-energized due to the SIAS.
B. Incorrect: (1) EDG ‘A’ meets the requirements to automatically close in on PBA-S03 and power the
bus. (2) Due to the EDG ‘A’ supplying PBA-S03 Amps will be indicated. (3) NHN-M71 is a SIAS
Load Shed Panel that will be de-energized due to the SIAS.
C. Correct: These are all correct.
D. Incorrect: (1) EDG ‘A’ meets the requirements to automatically close in on PBA-S03 and power the
bus. (2) Due to the EDG ‘A’ supplying PBA-S03 Amps will be indicated. (3) NHN-M71 is a SIAS
Load Shed Panel that will be de-energized due to the SIAS.

46
Q

Which ONE of the following valves are powered from a vital 125 VDC control center?
A. SIA-UV-644, SIT Isolation
B. SID-UV-654, Shutdown Cooling Isolation
C. SIE-HV-661, Combined SIT Drain to RDT
D. SIB-HV-690, Shutdown Cooling Loop 1 Warm-up Bypass

A

A. Incorrect: The SIT Isolation valves are powered by class 480v MCCs.
B. Correct: Class DC electrical distribution trains “C” and “D” provide power to the Shutdown Cooling
Isolation Valves through inverters PKC-N43 and PKD-N44.
C. Incorrect:The SIT Drains are air operated.
D. Incorrect: The Shutdown Cooling Loop Warm-up Bypasses are powered class 480 v MCCs

47
Q

Given the Following Conditions:

Unit 1 is in Mode 5
Battery Charger “A” (PKA-H11) has tripped
Battery Charger “AC” (PKA-H15) is connected to the “C” Battery Bus (PKC-M43)

Can “AC” Battery Charger be aligned to both PKA-M41 and PKC-M43 at this time?

A. Yes, Provided the Unit remains in Mode 5
B. No, a mechanical interlock prevents this alignment
C. Yes, Provided the “A” batter is disconnected from PKA-M41
D. No, this action may only occur while restoring the MVDC safety functions as implemented by the Lower Mode Functional Recovery Procedure.

A
A. Incorrect:  Tech Spec 3.8.1 do not allow for the class busses to be cross tied in Modes 1-4.  Candidate may think that since the unit is in mode 5 that this does not apply.
B. Correct: PVNGS has a mechanical interlock that prevents the Swing chargers from connecting to multiple DC busses simultaneously.
C. Incorrect: Batteries are not allowed to be crosstied to the same bus, if the "A" battery was disconnected this would remove that obstacle to crosstying the busses, but the mechanical interlock is not disables when the battery is disconnected from the bus.
D. Incorrect: LMFRP has many instances where DC busses are restored.  Candidate may belive that the crosstying is one of them.
48
Q

Given the following list of conditions:
Unit 1 is operating at 100% power.
The DG A right bank Starting Air Receiver is tagged out.
There was an Inadvertent Containment Spray System Actuation.
The remaining left bank receiver and starting air subsystem will apply air to ____(1)____ diesel cylinder
bank(s) and the diesel starts in the ____(2)_____ mode.
A. (1) both (2) Test Run
B. (1) both (2) Emergency
C. (1) only the left (2) Test Run
D. (1) only the left (2) Emergency

A

A. Correct: Crossover piping allows starting air to to be supplied to both banks of diesel cylinders. The
diesel starts in the test run mode of operation on an inadvertent Containment Spray System
actuation.
B. Incorrect:Crossover piping allows starting air to to be supplied to both banks of diesel cylinders.
The diesel does not start in the Emergency run mode of operation on an inadvertent Containment
Spray System actuation.
C. Incorrect:Crossover piping allows starting air to to be supplied to both banks of diesel cylinders.
The diesel starts in the test run mode of operation on an inadvertent Containment Spray System
actuation.
D. Incorrect:Crossover piping allows starting air to to be supplied to both banks of diesel cylinders.
The diesel does not start in the Emergency run mode of operation on an inadvertent Containment
Spray System actuation.

49
Q

While setting up a Diesel Generator to be paralleled with off-site power the following parameters are
noted just before the output breaker is closed;
The synchroscope is moving slowly in the fast direction.
Grid frequency 59.9 Hz
Diesel RPM 600
Bus Voltage 4160v
Generator Voltage 4150v
Upon closure of the Diesel Generator output breaker the operator must immediately raise ____(1)____ to
avoid a ____(2)____ trip.
A. (1) speed (2) over current
B. (1) speed (2) reverse power
C. (1) voltage (2) over current
D. (1) voltage (2) reverse power

A

A. Incorrect: Going to raise on the speed controller with the generator output breaker closed will raise
load and is directed by procedure however, this will also raise output current.
B. Correct: Going to raise on the speed controller with the generator output breaker closed will raise
load and is directed by procedure. The basis for this step is to avoid a reverse power trip.
C. Incorrect: Raising voltage setpoint will change reactive loading however, under the conditions
stated an overcurrent condition will not be approached.
D. Incorrect: Raising voltage setpoint will change reactive loading however, raising voltage will not
mitigate a reverse power condition.

50
Q

Given the following conditions:
Unit 1 is in Mode 6.
Fuel movement is in progress.
It is discovered that both channels of CREFAS (RU-29 and RU-30) are INOPERABLE.
Which of the following is the MINIMUM actions required to comply with Tech Spec 3.3.9, Control Room
Essential Filtration Actuation Signal?
A. Immediately place one train of CREFS in operation OR suspend movement of irradiated fuel
assemblies, positive reactivity additions and core alterations.
B. Immediately place one train of CREFS in operation AND suspend movement of irradiated fuel
assemblies, positive reactivity additions and core alterations.
C. Within 1 hour place one train of CREFS in operation OR suspend movement of irradiated fuel
assemblies, positive reactivity additions and core alterations.
D. Within 1 hour place one train of CREFS in operation AND suspend movement of irradiated fuel
assemblies, positive reactivity additions and core alterations

A

A. Correct – Immediately and OR meet the minimum requirements.
B. Incorrect – Immediately is right but AND is not required to meet the action.
C. Incorrect – 1 hour is wrong Mode 1 action w/o movement of irradiated fuel.
D. Incorrect – 1 hour is wrong Mode 1 action w/o movement of irradiated fuel.

51
Q

Given the following conditions:
Unit 1 is operating at 100% power.
The Plant Cooling Water System develops a large unisolable leak in the common pump discharge
header.
Plant Cooling Water Header Pressure Low Alarm Annunciates in the Control Room.
Essential Cooling Water train “A” is crosstied and supplying Nuclear Cooling Water priority loads.
40AO-9ZZ03 Loss Of Cooling Water has been entered.
Which ONE of the following systems are affected and what actions should the crew take?
A. Turbine Cooling Water System, Trip the Reactor.
B. Essential Cooling Water System, Trip the Reactor.
C. Turbine Cooling Water System, Trip the Main Turbine.
D. Essential Cooling Water System, Trip the Main Turbine

A

A. Correct: Plant Cooling Water System cools the Turbine Cooling Water Heat Exchanger and,
40AO-9ZZ03 Loss of Cooling Water requires a Reactor Trip.
B. Incorrect: The loss of Essential Cooling Water System in this case would require a Reactor Trip
however, the loss of Plant Cooling Water will not affect Essential Cooling Water.
C. Incorrect: It is true that the Plant Cooling Water System cools the Turbine Cooling Water Heat
Exchanger however, 40AO-9ZZ03, Loss of Cooling Water requires a Reactor Trip.
D. Incorrect: The loss of Essential Cooling Water System in this case would require a Reactor Trip
however, the loss of Plant Cooling Water will not affect Essential Cooling Water. 40AO-9ZZ03,
Loss of Cooling Water requires a Reactor Trip

52
Q

Given the following conditions:
Unit 1 is operating at 100% power
Both Nuclear Cooling Water Pumps are unavailable
Essential Cooling Water is crosstied to supply Nuclear Cooling Water

Which one of the following describes the NC priority heat load that will be supplied from EW?

A. Normal Chillers
B. Letdwon Heat Exchanger
C. Waste Gas Compressors
D. Containment Normal AHUs

A

A. Correct
B. Incorrect
C. Incorrect
D. Incorrect

53
Q

Which of the following is true regarding an Instrument Air pipe rupture in the Main Steam Support
Structure (MSSS)?
A. Service Air will supply all loads.
B. Accumulator will provide ADV operation.
C. Low Pressure Nitrogen will supply all loads.
D. Economizer Feedwater Isolation valves fast closure and slow mode of operation are available via
the accumulator.

A

A. Incorrect:The break will prevent backup sources supplying loads, Service Air no longer is a backup.
B. Correct: Accumulator will allow ADV operation for up to 8 hours.
C. Incorrect: Nitrogen backup may open on low pressure but the pipe break makes this useless.
D. Incorrect: Accumulator provides fast closure but not slow mode of operation.

54
Q

Given the Following Conditions

Unit 1 has tripped due to a LOCA inside Containment
SIAS/CIAS/MSIS/CSAS have initiated
Both containment spray trains have failed to actuate
CRS has entered the Functional Recovery Procedure
CTPC-2 is being implemented to supply CS flow using LPSI pump A

Which ONE of the below sets of parameters wull be monitored to satisfy CPTC-2

A. Humidity and CS flow
B. Pressure and CS flow
C. Humidity and LPSI pump amps
D. Pressure and LPSI pump amps

A

A. Incorrect: When LPSI is cross tied to CS, CS header flow is not available.
B. Incorrect: When LPSI is cross tied to CS, CS header flow is not available.
C. Incorrect: Humidity will be high initially from the LOCA, so a change would not be seen.
D. Correct: 40EP-9EO09, CTPC-2 step 3.1.f limits amps to ensure continued operation of the LPSI pump. Containment Pressure will drop if the section is performed correctly.