ML23123A299
| ML23123A299 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 05/03/2023 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| Download: ML23123A299 (1) | |
Text
L-23-1 NRC EXAM SECURE INFORMATION Page 1 RO Question # 1 Given the following:
x Unit 3 experiences a spurious reactor trip from 100% power at EOL.
x 3A Steam Generator Steam Dump to Atmosphere (SDTA) fails open.
Subsequently:
x 3A SG SDTA is locally isolated.
x RCS pressure lowers to 1900 psig.
Which one of the following completes the statement below?
IAW 3-EOP-ES-0.1, Reactor Trip Response, if RCS Tave lowers to a MINIMUM of (1), the RO is required to initiate a MINIMUM boration flowrate of (2).
A.
(1) 537°F (2) 20 gpm B.
(1) 537°F (2) 45 gpm C.
(1) 541°F (2) 20 gpm D.
(1) 541°F (2) 45 gpm ML23123A299
L-23-1 NRC EXAM SECURE INFORMATION Page 2 RO Question # 2 Given the following:
x Unit 3 experiences a safety injection.
x 3-EOP-E-1, Loss of Reactor or Secondary Coolant, is in progress.
x The RO observes the following:
ALSO PROVIDED IN LARGER FORMAT ON THE NEXT PAGE Which one of the following identifies the NEXT required operator action IAW 3-EOP-E-1?
A.
IMMEDIATELY take PCV-3-455C switch to CLOSE B.
wait for pressure to lower and then take PCV-3-455C switch to CLOSE C.
IMMEDIATELY take MOV-3-536 switch to CLOSE D.
wait for pressure to lower and then take MOV-3-536 switch to CLOSE
L-23-1 NRC EXAM SECURE INFORMATION Page 3
L-23-1 NRC EXAM SECURE INFORMATION Page 4 RO Question # 3 Given the following:
x Unit 3 is at 100% power.
x 3A and 3C Charging Pumps are running.
x 3B Charging Pump is secured.
Subsequently:
x Unit 3 experiences a small break LOCA.
x RCS pressure is 1690 psig and lowering.
x The crew enters 3-EOP-E-0, Reactor Trip or Safety Injection.
Which one of the following completes the statement below?
When the crew enters 3-EOP-E-0 the expected Charging Pump configuration is the following:
A.
L-23-1 NRC EXAM SECURE INFORMATION Page 5 RO Question # 4 Given the following:
x Unit 3 is at 40% power.
x A plant shutdown is in progress IAW 3-GOP-103, Power Operation to Hot Standby.
x 3A 4kV bus de-energizes due to an undervoltage condition.
Which one of the following completes the statement below?
(1) RCP(s) will trip and the reactor (2) AUTOMATICALLY trip.
A.
(1) only one (2) will B.
(1) only one (2) will NOT C.
(1) two (2) will D.
(1) two (2) will NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 6 RO Question # 5 Given the following:
x Unit 3 is at 100% power when a loss of all charging flow occurs.
x 3-ONOP-047.1, Loss of Charging flow in Modes 1-4, is entered.
x PZR level is 55%.
x VCT level is 2%.
x LCV-3-115B, Emergency Make up to Charging Pumps, is closed and will not open from the control room.
Which one of the following completes the statements below?
ANSWER BOTH QUESTION PARTS INDEPENDENTLY OF EACH OTHER.
IAW 3-ONOP-047.1, the crew (1) required to commence a power reduction IAW 3-GOP-100, Fast Load Reduction.
If a charging pump is subsequently available to be placed in service, the Unit Supervisor will direct the crew to (2) IAW 3-ONOP-047.1.
A.
(1) is (2) isolate instrument air and vent LCV-3-115B B.
(1) is (2) locally OPEN 3-358, RWST Emergency Makeup to the Chrg Pumps LCV-3-115B Bypass C.
(1) is NOT (2) isolate instrument air and vent LCV-3-115B D.
(1) is NOT (2) locally OPEN 3-358, RWST Emergency Makeup to the Chrg Pumps LCV-3-115B Bypass
L-23-1 NRC EXAM SECURE INFORMATION Page 7 RO Question # 6 Given the following:
x Unit 3 is in MODE 5 on RHR cooling.
x 3A RHR Pump is in service.
Subsequently:
x A pipe ruptures downstream of MOV-3-744A, RHR to Cold Leg Discharge Isolation.
x PZR Level indicates 0%.
x RCS draindown level indicates 20%.
x 3-ONOP-050, Loss of RHR, is entered.
Which one of the following completes the statements below?
(1) is expected to be in alarm.
IAW 3-ONOP-050, the RO (2) required to secure the 3A RHR Pump.
A.
(1) ANN G9/5, CNTMT SUMP HI LEVEL (2) is NOT B.
(1) ANN G9/5, CNTMT SUMP HI LEVEL (2) is C.
(1) ANN I7/6, RHR PUMP ROOM A SUMP TROUBLE (2) is NOT D.
(1) ANN I7/6, RHR PUMP ROOM A SUMP TROUBLE (2) is
L-23-1 NRC EXAM SECURE INFORMATION Page 8 RO Question # 7 Given the following:
x Unit 3 is in MODE 3 at normal operating temperature and pressure.
x LC-3-459G, Master Charging Pump Controller, is in MANUAL.
Subsequently x One PZR PORV, fails open.
x ANN A4/1, PORV/SAFETY VALVE OPEN, is in alarm.
x PZR level lowers to 18%.
Which one of the following completes the statements below?
CVCS normal Letdown (1) isolated.
IAW ANN A4/1 ARP, the RO is expected to correct this condition by performing (2) action.
A.
(1) is NOT (2) a prompt B.
(1) is NOT (2) an immediate C.
(1) is (2) a prompt D.
(1) is (2) an immediate
L-23-1 NRC EXAM SECURE INFORMATION Page 9 RO Question # 8 Given the following:
x Unit 3 experiences a Steam Generator Tube Rupture.
x SG levels are as follows:
x 3A SG NR Level 87%
x 3B SG NR Level 0%
x 3C SG NR Level 0%
Subsequently:
x The RO is performing Attachment 3, Prompt Action Verifications, of 3-EOP-E-0, Reactor Trip or Safety Injection.
Which one of the following completes the statement below?
The RO (1) required to verify that both Steam Generator Feedwater Pumps are secured.
(2) is (are) expected to have AUTOMATICALLY closed.
A.
(1) is (2) ONLY 3A Main Feed Reg Valve B.
(1) is (2) ALL Main Feed Reg Valves C.
(1) is NOT (2) ONLY 3A Main Feed Reg Valve D.
(1) is NOT (2) ALL Main Feed Reg Valves
L-23-1 NRC EXAM SECURE INFORMATION Page 10 RO Question # 9 Given the following:
x Unit 3 experiences an uncontrolled Depressurization of All Steam Generators x
3-EOP-ECA-2.1, uncontrolled Depressurization of All Steam Generators, is in progress.
Which one of the following completes the statement below?
IAW 3-EOP-ECA-2.1, the RO is required to verify CV-3-2803, Instrument Air Containment Isolation, is OPEN (1), then the RO checks instrument air pressure being greater than a MINIMUM of (2) before continuing with the normal procedure path A.
(1) since it was AUTOMATICALLY isolated on Phase A signal (2) 80 psig B.
(1) since it was AUTOMATICALLY isolated on Phase A signal (2) 95 psig C.
(1) to allow establishing normal charging to aid in meeting SI termination (2) 80 psig D.
(1) to allow establishing normal charging to aid in meeting SI termination (2) 95 psig
L-23-1 NRC EXAM SECURE INFORMATION Page 11 RO Question # 10 Given the following:
x Unit 3 is at 50% power x
B Standby Steam Generator Feedwater Pump OOS x
3A Steam Generator Feedwater Pump is OOS Subsequently:
x 3C 4kV Bus Locks out.
x Unit 3 Reactor trips.
x All AFW Pumps trip and will NOT restart.
x All SG Wide Range levels are 25% and lowering.
x The crew is transitioning out of 3-EOP-E-0, Reactor Trip or Safety Injection.
Which one of the following completes the statement below?
The crew (1) required to perform 3-EOP-FR-H.1, Response to Loss of Secondary Heat Sink.
IAW the applicable procedure, if required to depressurize a SG to feed with condensate pumps, lowering the SG pressure to 350 psig (2) comply with the procedure guidance.
A.
(1) is (2) will B.
(1) is (2) will NOT C.
(1) is NOT (2) will D.
(1) is NOT (2) will NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 12 RO Question # 11 Given the following:
x Both units experience a loss of all AC.
x Neither units A nor B 4kV buses can be PROMPTLY re-energized from the control room.
x 3/4-EOP-ECA-0.0, Loss of all AC power, are in progress.
Which one of the following completes the statement below?
IAW BD-ECA-0.0, Loss of All AC Power Basis Document, operators are directed to shed non-essential DC loads in order to (1).
IAW 3/4-EOP-ECA-0.0, Vital DC Load Shedding is required to be completed within a MAXUMUM of (2) minutes from event initiation.
A.
(1) lower battery discharge rates to lengthen availability of vital equipment (2) 60 B.
(1) lower battery hydrogen generation rates while no ventilation is available (2) 60 C.
(1) lower battery discharge rates to lengthen availability of vital equipment (2) 90 D.
(1) lower battery hydrogen generation rates while no ventilation is available (2) 90
L-23-1 NRC EXAM SECURE INFORMATION Page 13 RO Question # 12 Given the following initial conditions:
x Unit 3 is operating at 100% power.
x A loss of offsite power occurs.
x The crew enters 3-EOP-ES-0.1, Reactor Trip Response.
While performing Attachment 1, Natural Circulation Indications, the following plant conditions are observed:
x CET temperatures = 595°F and stable x
RCS hot leg temperatures = 585°F and stable x
RCS pressure = 1900 psig and stable x
All SG pressures = 985 psig and stable x
RCS cold leg temperatures = 540°F and stable Which one of the following (1) identifies the status of natural circulation and (2) the action required to enhance or establish natural circulation in accordance with 3-EOP-ES-0.1?
A.
(1) Established (2) Raise steam flow through steam dumps to condenser B.
(1) Established (2) Raise steam flow through steam dumps to atmosphere C.
(1) NOT established (2) Raise steam flow through steam dumps to condenser D.
(1) NOT established (2) Raise steam flow through steam dumps to atmosphere
L-23-1 NRC EXAM SECURE INFORMATION Page 14 RO Question # 13 Given the following:
x Unit 3 is at 100% power.
Subsequently:
x 3D23 Vital DC Bus de-energizes.
Which one of the following completes the statements below?
3C Normal Inverter (1) transfer to the CVT.
IAW 3-ONOP-003.5, Loss of DC Buses 3D23 and 3D23A (3B),
the (2) 3C inverter will be opened to support the DC bus restoration.
A.
(1) is expected to AUTOMATICALLY (2) DC feeder breaker to B.
(1) is expected to AUTOMATICALLY (2) AC output breaker from C.
(1) requires a MANUAL (2) DC feeder breaker to D.
(1) requires a MANUAL (2) AC output breaker from
L-23-1 NRC EXAM SECURE INFORMATION Page 15 RO Question # 14 Which one of the following completes the statements below?
An extended loss of instrument air will cause loss of ICW flow to (1) heat exchanger(s).
IAW 3-ONOP-019, Intake Cooling Water Malfunction, LOCALLY reopening the ICW system failed closed valves (2) require Unit 3 to enter a Tech Spec action statement.
A.
(1) the CCW and TPCW (2) does B.
(1) the CCW and TPCW (2) does NOT C.
(1) ONLY the TPCW (2) does D.
(1) ONLY the TPCW (2) does NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 16 RO Question # 15 Given the following:
x Both units are at 100% power.
x Unit 3 experiences a loss of instrument air while at 100%.
x 3-ONOP-013, Loss of Instrument Air, is in progress.
x Instrument Air lowers to a MINIMUM of 62 psig on Unit 3.
Subsequently:
x 3CD Instrument Air compressor is started.
x Instrument Air pressure is 90 psig and rising.
Which one of the following completes the statements below?
IAW 3-ONOP-013, Loss of Instrument Air, Unit 3 Reactor Trip Criteria (1) met during this plant transient.
IAW 3-ONOP-013, Loss of Instrument Air, CV-3-1605 and CV-4-1605, Instrument Air Cross Tie Isolation Control Valves, are (2).
A.
(1) was NOT (2) expected to be in the OPEN position B.
(1) was NOT (2) required to be LOCALLY OPENED C.
(1) was (2) expected to be in the OPEN position D.
(1) was (2) required to be LOCALLY OPENED
L-23-1 NRC EXAM SECURE INFORMATION Page 17 RO Question # 16 Given the following:
x 3A EDG is paralleled to the 3A 4kV Bus.
x 3A EDG indicates 800 kVAR in the LAG.
x Switchyard Voltage is 240.1 kV.
Subsequently:
x A grid disturbance causes switchyard voltage to lower to 236.5 kV.
Which one of the following completes the statements below?
IAW 3-OSP-023.1, 3A EDG Operability Test, in order to return the 3A EDG reactive load to the initial value of 800 kVAR in the LAG, the RO is required to manipulate the (1) switch in the (2) direction.
A.
(1) speed changer (2) LOWER B.
(1) speed changer (2) RAISE C.
(1) voltage regulator (2) LOWER D.
(1) voltage regulator (2) RAISE
L-23-1 NRC EXAM SECURE INFORMATION Page 18 RO Question # 17 Given the following:
x Unit 3 experiences a loss of emergency recirculation.
x 3-EOP-ECA-1.1, Loss of Emergency Recirculation, is in progress.
x Unit 3 RWST level is 59,000 gallons.
Which one of the following completes the statements below?
IAW 3-EOP-ECA-1.1, the RO is NEXT required to (1) in order to (2).
A.
(1) establish SI flow from U4 RWST (2) extend the availability of RWST injection B.
(1) establish SI flow from U4 RWST (2) prevent a loss of NPSH to the ECCS Pumps C.
(1) secure all ECCS Pumps taking a suction on Unit 3 RWST (2) extend the availability of RWST injection D.
(1) secure all ECCS Pumps taking a suction on Unit 3 RWST (2) prevent a loss of NPSH to the ECCS Pumps
L-23-1 NRC EXAM SECURE INFORMATION Page 19 RO Question # 18 Given the following:
x 3-EOP-FR-H.1, Response to Loss of Secondary Heat Sink, is in progress.
x S/G Wide Range levels are as follows:
x 3A - 8%
x 3B - 5%
x 3C - 6%
x RCS hot leg temperatures are 580°F and rising slowly.
x The switchyard is DE-ENERGIZED.
x The BOP is preparing to feed the SGs using Standby Feed.
Which one of the following completes the statements below IAW 3-EOP-FR-H.1?
The (1) Standby Feedwater Pump, will be used.
The RO will control the feedwater flowrate by monitoring (2).
A.
(1) A (2) changes in RCS temperature and SG levels B.
(1) B (2) changes in RCS temperature and SG levels C.
(1) A (2) flow to each SG on main feed flow transmitters D.
(1) B (2) flow to each SG on main feed flow transmitters
L-23-1 NRC EXAM SECURE INFORMATION Page 20 RO Question # 19 Given the following:
x Unit 3 is at 100% power.
x Tavg and Tref are within 1°F.
Subsequently:
x Control rod E-11 drops fully into the core.
x The Rod Motion Control Selector switch is placed in MANUAL.
Which one of the following completes the statements below?
IAW, 3-ONOP-028.3, Dropped RCC, the crew is required to prioritize adjusting (1) to restore Tavg.
IAW, 3-ONOP-028.3, during the rod retrieval process, Annunciator B 9/4, ROD CONTROL URGENT FAILURE, (2) expected to actuate.
A.
(1) control-rod position (2) is B.
(1) control-rod position (2) is NOT C.
(1) turbine load (2) is D.
(1) turbine load (2) is NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 21 RO Question # 20 Given the following:
x Unit 4 RCS is in MODE 6.
x Core offload is in progress.
x N-4-31, Source Range Instrument, is OOS.
x N-4-32, Source Range Instrument, is providing audible count rate.
Subsequently:
x The Refueling SRO communicates to the Control Room that he can NO longer hear the audible count rate in containment.
Which one of the following completes the statements below?
IAW 4-ONOP-038.1, Loss of Refueling Equipment or Support Function, the crew (1) required to suspend Core alterations.
Gammametrics Excore Nuclear Instruments (2) capable of providing an audible count rate.
A.
(1) is (2) are B.
(1) is (2) are NOT C.
(1) is NOT (2) are D.
(1) is NOT (2) are NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 22 RO Question # 21 Given the following conditions on the NIS during a Unit 3 down power:
(N-3-35 indicates actual power)
Which one of the following completes the statements below?
N-3-36 is (1).
IAW 3-ONOP-059.7, Intermediate Range Nuclear Instrumentation Malfunction, in order to MANUALLY RE-ENERGIZE the Source Range NIs the RO (2) required to press both P-6 DEFEAT pushbuttons simultaneously.
A.
(1) undercompensated (2) is B.
(1) undercompensated (2) is NOT C.
(1) overcompensated (2) is D.
(1) overcompensated (2) is NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 23 RO Question # 22 Given the following:
x Both Units are at 100% power.
x A release of Gas Decay Tank A is in progress.
x DCS indicates as follows:
ALSO PROVIDED IN LARGER FORMAT ON THE NEXT PAGE Subsequently:
x The RO observes the following on DCS:
ALSO PROVIDED IN LARGER FORMAT ON THE NEXT PAGE Which one of the following completes the statements below?
The above DCS indication and controls is available (1).
The crew (2) required to perform the actions of ARP for ANN H1/4, PRMS HI RADIATION.
A.
(1) ONLY on Unit 3 (2) is NOT B.
(1) ONLY on Unit 3 (2) is C.
(1) on both Unit 3 and Unit 4 (2) is NOT D.
(1) on both Unit 3 and Unit 4 (2) is
L-23-1 NRC EXAM SECURE INFORMATION Page 24
L-23-1 NRC EXAM SECURE INFORMATION Page 25 RO Question # 23 Given the following:
x Unit 3 experiences a LOCA from 100% power.
x 3-EOP-E-0, Reactor Trip or Safety Injection, is in progress.
x ANN H1/5, CHRMS HI RADIATION, is in alarm.
x RAD 6311A, Containment High Radiation Monitor, reads 2.1 E5 R/hr.
x RAD 6311B, Containment High Radiation Monitor, reads 2.2 E5 R/hr.
Which one of the following completes the statements below?
IAW 3-EOP-E-0, the use of adverse containment setpoints (1) required.
The CHRMS circuitry (2) expected to send a signal to isolate the containment ventilation system.
A.
(1) is (2) is B.
(1) is (2) is NOT C.
(1) is NOT (2) is D.
(1) is NOT (2) is NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 26 RO Question # 24 Given the following:
x Unit 3 is at 100% power.
x R-3-20, Reactor Coolant Letdown, high alarm is lit.
Which one of the following completes the statements below?
Letdown flow (1) be AUTOMATICALLY isolated.
IAW 3-ONOP-067, Radioactive Effluent Release, the RO (2) required to place the control room on recirculation mode within MAXIMUM of 30 minutes.
A.
(1) will (2) is NOT B.
(1) will (2) is C.
(1) will NOT (2) is NOT D.
(1) will NOT (2) is
L-23-1 NRC EXAM SECURE INFORMATION Page 27 RO Question # 25 Which one of the following completes the statements below?
With a containment pressure of 5 psig, (1) is the MINIMUM Containment Recirculation Sump level that requires the entry into 3-EOP-FR-Z.2, Response to Containment Flooding.
IAW 3-EOP-FR-Z.2, the crew is required to (2).
A.
(1) 428 inches (2) direct nuclear chemistry to sample containment sumps B.
(1) 428 inches (2) ensure containment purge exhaust and supply fans OFF C.
(1) 448 inches (2) direct nuclear chemistry to sample containment sumps D.
(1) 448 inches (2) ensure containment purge exhaust and supply fans OFF
L-23-1 NRC EXAM SECURE INFORMATION Page 28 RO Question # 26 Given the following:
x Unit 4 experienced a LOCA 30 minutes ago.
x The crew just entered 4-EOP-FR-P.1, Response to Imminent Pressurized Thermal Shock (PTS).
x RCS pressure is 140 psig.
x RHR Flow is 1900 gpm.
Which one of the following completes the statements below?
The crew (1) required to start at least one Charging Pump, before exiting 4-EOP-FR-P.1.
The crew (2) required to perform an RCS temperature soak before exiting 4-EOP-FR-P.1.
A.
(1) is NOT (2) is B.
(1) is NOT (2) is NOT C.
(1) is (2) is D.
(1) is (2) is NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 29 RO Question # 27 Which one of the following completes the statements below?
If only 3A RCP is running Normal PZR Spray (1) available.
3B RCP (2) located on the same RCS loop as the PZR.
A.
(1) is NOT (2) is B.
(1) is NOT (2) is NOT C.
(1) is (2) is D.
(1) is (2) is NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 30 RO Question # 28 Given the following:
x Unit 3 is at 100% power.
x The 45 gpm letdown orifice is in service.
x Blended makeup flow is set for 60 gpm.
With no operator action, which one of the following failures will result in the Pressurizer heaters de-energizing?
A.
LT-3-115, VCT Level Transmitter, fails high B.
LT-3-112, VCT Level Transmitter, fails high C.
Instrument Air is lost to LCV-3-115A, VCT Divert to Hold Up Tank D.
Instrument Air is lost to HCV-3-121, Charging Flow to Regen Heat Exchanger
L-23-1 NRC EXAM SECURE INFORMATION Page 31 RO Question # 29 With Unit 3 at 100% power, which one of the following identifies a valve that will AUTOMATICALLY reposition on a Safety Injection signal?
A.
MOV-878A, HHSI Pump Header Isolation.
B.
MOV-3-864A, RWST Outlet Isolation.
C.
MOV-3-865A, 3A Accumulator Discharge.
D.
MOV-3-744A, RHR Disch to Cold Leg Isolation Valve.
L-23-1 NRC EXAM SECURE INFORMATION Page 32 RO Question # 30 Given the following:
x Unit 3 experiences a LOCA from 100% power.
x PZR pressure is 705 psig and slowly lowering.
x PZR level is off-scale low.
Which one of the following completes the statements below?
RHR Pumps (1) injecting into the RCS.
SI Accumulators (2) injected into the RCS.
A.
(1) are (2) have B.
(1) are (2) have NOT C.
(1) are NOT (2) have D.
(1) are NOT (2) have NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 33 RO Question # 31 Which one of the following completes the statements below?
3A HHSI CCW cooling is capable of being aligned (1).
3A RHR CCW cooling is capable of being aligned (2).
A.
(1) ONLY from Unit 3 (2) ONLY from Unit 3 B.
(1) ONLY from Unit 3 (2) from either unit C.
(1) from either unit (2) ONLY from Unit 3 D.
(1) from either unit (2) from either unit
L-23-1 NRC EXAM SECURE INFORMATION Page 34 RO Question # 32 Given the following on Unit 4:
Which one of the following complete the statement below?
The Unit 4 PRT is protected from overpressure by (1).
Given the PRT parameters below, the crew (2) to perform the actions of ARP for A7/1, PRT HI/LO LEVEL HI PRESS/TEMP.
PRT parameters:
x PRT temperature is 110°F x PRT level is 75%
x PRT pressure is 32 psig.
A.
(1) relief valve(s)
(2) is NOT B.
(1) relief valve(s)
(2) is C.
(1) rupture disk(s)
(2) is NOT D.
(1) rupture disk(s)
(2) is
L-23-1 NRC EXAM SECURE INFORMATION Page 35 RO Question # 33 Given the following:
x Unit 3 is in MODE 4.
x TCV-3-143, L/D Demineralizer Divert Valve, is aligned to AUTO.
x RHR is in service.
Subsequently:
x Annunciator A3/5, LTDN DEMIN HI TEMP/FLOW DIVERTED, alarms.
x FI-3-620, local NRHX CCW flow is reading 90 gpm.
Which one of the following completes the following statements below?
The LTDN DEMIN HI TEMP alarm setpoint is (1).
IAW 3-ARP-097.CR.A, A3/5, the RCO is required to MANUALLY adjust (2) to restore Letdown Temperature.
A.
(1) 135°F (2) TC-3-144A, L/D Temp Controller B.
(1) 135°F (2) HCV-3-142, RHR Ltdn to CVCS C.
(1) 125°F (2) TC-3-144A, L/D Temp Controller D.
(1) 125°F (2) HCV-3-142, RHR Ltdn to CVCS
L-23-1 NRC EXAM SECURE INFORMATION Page 36 RO Question # 34 Given the following:
x Unit 4 is at 100% power.
x 4A CCW Heat Exchanger is OOS.
Subsequently:
x 4B CCW Heat Exchanger develops a tube leak.
Which one of the following completes the statements below?
A (1) CCW Head Tank Level will confirm 4B CCW tube leak.
Upon isolation of the 4B CCW Heat Exchanger, Unit 4 (2) required to enter a Tech Spec action statement.
A.
(1) rising (2) is B.
(1) rising (2) is NOT C.
(1) lowering (2) is D.
(1) lowering (2) is NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 37 RO Question # 35 Given the following:
x Unit 3 is in Mode 2.
x PRZ pressure control is in automatic.
x Pressurizer pressure is 2150 psig and lowering.
x 3-ONOP-041.5, Pressurizer Pressure Control Malfunction, is entered.
Which one of the following completes the statements below?
IAW 3-ONOP-041.5, the RO is required to place PC-3-444J, PZR PRESS CONTROL, in MANUAL and (1) the output.
When adjusting the output on PC-3-444J, PCV-3-455C, PZR PORV, (2) expected to AUTOMATICALLY open if the controller output is driven to 90%.
A.
(1) raise (2) is B.
(1) lower (2) is C.
(1) raise (2) is NOT D.
(1) lower (2) is NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 38 RO Question # 36 Given the following:
x Unit 3 is at 18% power.
x PT-3-456, PZR Pressure, is OOS due to a failure.
x The actions of 3-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels, are complete.
x PZR level control selector switch is on position 3 (CH. 2 & 3.)
Subsequently:
x A line shears as indicated with and X below:
ALSO PROVIDED AS A REFERENCE IN LARGER FORMAT Which one of the following completes the statements below?
PZR heaters (1) expected to DE-ENERGIZE The reactor (2) expected to trip.
A.
(1) are (2) is NOT B.
(1) are (2) is C.
(1) are NOT (2) is NOT D.
(1) are NOT (2) is
L-23-1 NRC EXAM SECURE INFORMATION Page 39
L-23-1 NRC EXAM SECURE INFORMATION Page 40 RO Question # 37 Given the following:
x Unit 3 experiences a 3C Steam Generator Tube Rupture from 100% power.
Which one of the following completes the statements below?
(1) HHSI Pumps are expected to AUTOMATICALLY start.
IAW 3-EOP-E-3, Steam Generator Tube Rupture, the RO is required to CLOSE (2).
A.
(1) Four (2) ONLY 3C MSIV B.
(1) Four (2) ALL MSIVs C.
(1) ONLY two (2) ONLY 3C MSIV D.
(1) ONLY two (2) ALL MSIVs
L-23-1 NRC EXAM SECURE INFORMATION Page 41 RO Question # 38 Given the following:
x Unit 3 is in MODE 1, when it experiences a small-break LOCA.
x Containment pressure peaks at 15 psig.
x The BOP is starting to perform the foldout page actions of 3-EOP-E-0, Reactor Trip or Safety Injection.
Which one of the following completes the statements below?
CCW flow to the NCCs (1) interrupted.
CCW flow to the RCP motor bearings (2) interrupted.
A.
(1) is (2) is B.
(1) is (2) is NOT C.
(1) is NOT (2) is D.
(1) is NOT (2) is NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 42 RO Question # 39 Given the following:
x Unit 4 experiences a LOCA from 100% power.
x At 10:00 am Containment pressure is 17 psig and rising.
Which one of the following completes the statements below?
At 10:00 am, MOV-4-880B, Containment Spray Isolation (1) open.
Opening of MOV-4-880B, Containment Spray Isolation is initiated from the (2).
A.
(1) is (2) 4B sequencer B.
(1) is (2) Containment Isolation Racks C.
(1) is NOT (2) 4B sequencer D.
(1) is NOT (2) Containment Isolation Racks
L-23-1 NRC EXAM SECURE INFORMATION Page 43 RO Question # 40 Which one of the following completes the statements below?
IAW 3-OSP-072.1, Manual Steam Line Isolation Test, the RO will depress the Main Steam Line isolation pushbuttons located on the (1), triggering the closure of (2).
A.
(1) Safeguard Racks (2) the applicable MSIV and Main Steam Stop Bypass B.
(1) Safeguard Racks (2) ONLY the applicable MSIV C.
(1) VPB (2) the applicable MSIV and Main Steam Stop Bypass D.
(1) VPB (2) ONLY the applicable MSIV
L-23-1 NRC EXAM SECURE INFORMATION Page 44 RO Question # 41 Given the following:
x Unit 3 is in MODE 6.
x Unit 4 is at 100% power.
Subsequently:
x 4B SG experiences a fault and it completely depressurizes.
Which one of the following identifies the effect on the AFW system?
A.
Steam Supply remains available to ALL AFW Pumps B.
Steam Supply is lost to the A AFW Pump ONLY C.
Steam Supply is lost to the B AFW Pump ONLY D.
Steam Supply is lost to the C AFW Pump ONLY
L-23-1 NRC EXAM SECURE INFORMATION Page 45 RO Question # 42 Given the following:
x Unit 3 is at 55%.
x 3-GOP-301, Hot Standby to Power Operation, is in progress.
x 3A Steam Generator Feedwater Pump is in service.
Which one of the following completes the statements below?
In order to start the 3B Steam Generator Feedwater Pump a MIMIMUM of (1) Condensate Pumps are required to be in operation.
In order to start the 3B Steam Generator Feedwater Pump a MINIMUM suction pressure of (2) is required.
A.
(1) 2 (2) 225 psig B.
(1) 2 (2) 260 psig C.
(1) 3 (2) 225 psig D.
(1) 3 (2) 260 psig
L-23-1 NRC EXAM SECURE INFORMATION Page 46 RO Question # 43 Given the following:
x Unit 3 power ascension is in progress.
x Reactor Power 4%.
x 3B Steam Generator Feedwater Pump is operating, feeding the steam generators.
x 3A Steam Generator Feedwater Pump is OOS.
Subsequently:
x 3B SGFP trips.
Which one of the following completes the statement below?
The AFW Pumps are expected to AUTOMATICALLY start (1).
The RO (2) able to verify running AFW Pump(s) RPM indication in the control room A.
(1) IMMEDIATELY (2) is NOT B.
(1) IMMEDIATELY (2) is C.
(1) when SG NR level(s) lower below AutoStart setpoint (2) is NOT D.
(1) when SG NR level(s) lower below AutoStart setpoint (2) is
L-23-1 NRC EXAM SECURE INFORMATION Page 47 RO Question # 44 Which one of the following completes the statement below?
IAW 3-NOP-075, Auxiliary Feedwater System, the AFW pump discharge lines (1) required to be periodically vented on a monthly basis.
While venting of the A AFW pump following maintenance on the pump discharge piping, if the operator closes the vent valve after observing a steady stream of water for 1 minute, venting (2) considered satisfactory IAW 3-NOP-075.
A.
(1) are (2) is B.
(1) are (2) is NOT C.
(1) are NOT (2) is D.
(1) are NOT (2) is NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 48 RO Question # 45 Given the following:
x Unit 4 is at 100% power.
x The BS Inverter is in service aligned to Unit 4.
Subsequently:
x Unit 4 experiences a LOOP.
x 4A EDG is locked out.
x 4D Inverter DC input breaker OPENS.
Which one of the following identifies the 120V Vital AC Panel that is De-energized?
A.
4P06 B.
4P07 C.
4P08 D.
4P09
L-23-1 NRC EXAM SECURE INFORMATION Page 49 RO Question # 46 Given the following:
x Unit 3 is in MODE 3.
Subsequently:
x Vital DC Bus 3D23 loses power due to a fault on the bus.
x 3-ONOP-003.5, Loss of DC Bus 3D23 and 3D23A (3B), is in progress.
x The fault has been isolated.
Which one of the following completes the statements below?
Power (1) available to 3B1 battery charger.
Vital DC bus voltage indication (2) available on VPA.
A.
(1) is (2) is NOT B.
(1) is (2) is C.
(1) is NOT (2) is NOT D.
(1) is NOT (2) is
L-23-1 NRC EXAM SECURE INFORMATION Page 50 RO Question # 47 Which one of the following identifies the DC load that is affected by a loss of 3D01, 3A Vital DC Bus?
A.
FCV-3-114A DEMIN WATER TO BLENDER CLOSE B.
FCV-3-114B BLENDER TO VCT CLOSE C.
MOV-3-1404, 3B STM Supply to Aux Feedwater Pumps D.
MOV-3-1405, 3C STM Supply to Aux Feedwater Pumps
L-23-1 NRC EXAM SECURE INFORMATION Page 51 RO Question # 48 Which one of the following identifies the power supply for the 3A EDG Starting Air Compressor?
A.
3A MCC B.
3C MCC C.
3K MCC D.
3L MCC
L-23-1 NRC EXAM SECURE INFORMATION Page 52 RO Question # 49 Given the following:
x 4-OSP-023.2, Diesel Generator 24 Hour Full Load Test and Load Rejection, is in progress.
x 4A EDG is loaded to 2874 kW.
Subsequently:
x 4AA20, 4A EDG Output Breaker, Inadvertently opens.
Which one of the following completes the statements below?
Power (1) expected to be lost to the 4A 4 kV Bus.
4A EDG (2) expected to trip as a result of this transient.
A.
(1) is (2) is B.
(1) is (2) is NOT C.
(1) is NOT (2) is D.
(1) is NOT (2) is NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 53 RO Question # 50 Given the following:
x Unit 3 is at 100% power.
Subsequently:
x Annunciator H-1/6, PRMS CHANNEL FAILURE actuates.
x R-19, SG Blowdown Radiation Monitor, is failed.
Which one of the following completes the statements below?
Blowdown Isolation Valves, CV-3-6275A, B and C (1) auto close.
S/G Liquid Sample Valves, MOV-3-1425, 1426 and 1427 (2) auto close.
A.
(1) will (2) will B.
(1) will (2) will NOT C.
(1) will NOT (2) will D.
(1) will NOT (2) will NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 54 RO Question # 51 Given the following:
x Unit 3 is at 100% power.
x 3A and 3C ICW Pumps are running.
Subsequently:
x Unit 3 experiences a safety injection actuation with a loss of voltage on the 3B 4kV Bus.
x 3B 4kV Bus RE-ENERGIZES from 3B EDG.
Which one of the following completes the statements below?
(1) ICW Pump(s) will be stripped.
(2) ICW Pump(s) will receive start signals from the Sequencers.
A.
(1) 3A and 3C (2) 3A and 3B B.
(1) 3A and 3C (2) 3A and 3C C.
(1) Only 3C (2) 3A and 3B D.
(1) Only 3C (2) 3A and 3C
L-23-1 NRC EXAM SECURE INFORMATION Page 55 RO Question # 52 Given the following:
x Unit 3 experiences a loss of instrument air from 100% power.
x Instrument air pressure on Unit 3 is 74 psig.
Which one of the following completes the statements below?
Unit 3 Main Feedwater Reg Valves, are expected to.
A.
drift OPEN B.
drift CLOSED C.
remain STABLE controlled with Compressed Nitrogen backup D.
remain STABLE controlled with Compressed Air backup
L-23-1 NRC EXAM SECURE INFORMATION Page 56 RO Question # 53 Given the following:
x Unit 3 experiences a Steam Line Break.
x 3-EOP-E-0, Reactor Trip or Safety Injection is in progress with the following conditions:
x Containment Temperature is 195°F.
x Containment Pressure is 30 psig.
x NO Containment Spray Pumps are running.
x Gammametrics indicates 3% reactor power.
x Intermediate Range NIs indicate a -0.2 dpm startup rate.
Which one of the following completes the statements below?
A/An (1) Path is present on the containment CSF, IAW with this, the crew (2) required to ensure all RCPs are secured.
A.
(1) Red (2) is B.
(1) Red (2) is NOT C.
(1) Orange (2) is D.
(1) Orange (2) is NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 57 RO Question # 54 Given the following:
x Unit 3 experiences a double ended shear on the 3A Cold Leg concurrently with a LOOP at 100% power.
x 3B 4KV Bus fails to re-energize from the 3B EDG.
Assuming no operator action, which one of the following completes the statements below?
3B ECC (1) expected to have electrical power.
The number of Containment Spray Pump(s) and ECC(s) that have electrical power is sufficient to maintain the containment below its design pressure of (2).
A.
(1) is (2) 53.85 psig B.
(1) is (2) 55.00 psig C.
(1) is NOT (2) 53.85 psig D.
(1) is NOT (2) 55.00 psig
L-23-1 NRC EXAM SECURE INFORMATION Page 58 RO Question # 55 Given the following:
x Unit 3 is at 75% power.
x Control Bank D is at 200 steps.
Subsequently:
x N-3-44, Power Range Nuclear Instrument Channel 4, fails LOW.
Which one of the following completes the statements below?
Control Rods (1) expected to AUTOMATICALLY move.
IAW 3-ONOP-059.8, Power Range Nuclear Instrumentation Malfunction, the RO (2) required to remove the Instrument Power Fuses for N-3-44.
A.
(1) are (2) is NOT B.
(1) are (2) is C.
(1) are NOT (2) is NOT D.
(1) are NOT (2) is
L-23-1 NRC EXAM SECURE INFORMATION Page 59 RO Question # 56 Given the following conditions:
x Unit 3 is in MODE 6.
x A Core offload is in progress.
x The Containment Equipment Hatch and Personnel Hatch are closed.
x Containment Purge is operating with Purge Supply and Exhaust fans running.
x A fuse blows for POV-3-2601, Containment Purge Supply Isolation.
Which one of the following completes the statements below?
Spent Fuel Pool Level is expected to (1).
The running Containment Purge Supply Fan (2) expected to trip as a direct result of the blown fuse.
A.
(1) rise (2) is NOT B.
(1) rise (2) is C.
(1) lower (2) is NOT D.
(1) lower (2) is
L-23-1 NRC EXAM SECURE INFORMATION Page 60 RO Question # 57 Given the following:
x Unit 3 is at 100% power.
x PC-3-444J, PRZ Pressure Controller, experiences a short circuit.
Which one of the following identifies the effect this fault will have on the Reactor Protection System?
The PC-3-444J controller fault is expected to.
A.
directly feed back into the RPS circuit, generating a 1/3 HI PRZ Pressure Bi-stable to actuate B.
directly feed back into the RPS circuit, generating a 1/3 LO PRZ Pressure Bi-stable to actuate C.
NOT directly feed back into the RPS circuit due to use of isolation devices D.
NOT directly feed back into the RPS circuit since separate transmitters are used
L-23-1 NRC EXAM SECURE INFORMATION Page 61 RO Question # 58 Given the following:
x Unit 3 is at 100% power.
x A Core Exit Thermocouple fails on the A QSPDS System.
x ANN A4/2 QSPDS INADEQUATE CORE COOLING, alarms.
Which one of the following completes the statement below?
3-NOP-042, QSPDS Inadequate Core Cooling Monitor, provides instruction to bypass (1).
A (2) is required to perform this operation.
A.
(1) ANN A4/2, on HMI (2) Computer Administrator Login B.
(1) ANN A4/2, on HMI (2) physical key C.
(1) the failed CET on QSPDS (2) Computer Administrator Login D.
(1) the failed CET on QSPDS (2) physical key
L-23-1 NRC EXAM SECURE INFORMATION Page 62 RO Question # 59 Given the following:
x Unit 3 is at 100% power.
x PZR level control selector switch is on position one (CH. 1 & 2.)
Subsequently:
x LT-3-460, PZR Level, fails to 0%.
Which one of the following completes the statements below?
Charging Pump Speed (1) expected to lower as a DIRECT result of LT-3-460, PZR Level, failing.
Letdown Isolation Valve, LCV-3-460, (2) expected to CLOSE.
A.
(1) is (2) is B.
(1) is (2) is NOT C.
(1) is NOT (2) is D.
(1) is NOT (2) is NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 63 RO Question # 60 Given the following:
x Unit 3 is in MODE 5.
x A Containment purge is initiated in accordance with 3-NOP-053, Containment Purge System.
x 3A NCC is running with the rest of the NCCs secured.
Which one of the following completes the statements below?
Containment Purge flow indication (1) available on VPB.
Unit 3 purge exhaust and supply fans (2) expected to trip as a DIRECT result of tripping the 3A NCC.
A.
(1) is NOT (2) are B.
(1) is (2) are C.
(1) is NOT (2) are NOT D.
(1) is (2) are NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 64 RO Question # 61 Given the following:
x A Unit 3 plant heatup is in progress.
x ALL Unit 3 MSIVs are CLOSED.
x All Steam Dump Valves are in AUTOMATIC.
Which one of the following completes the statement below?
Steam flow from the SGs is expected to commence when SG pressure is greater than as a MINIMUM.
A.
1005 psig.
B.
1060 psig.
C.
1085 psig.
D.
1100 psig.
L-23-1 NRC EXAM SECURE INFORMATION Page 65 RO Question # 62 Given the following:
x Unit 3 is at 100% power.
Subsequently:
x Unit 3 experiences a LOCA.
x D-1A, Ventilation Inlet Damper, green is OFF and red is ON.
x SF-1A, Emergency Air Supply Fan, is running.
x SF-1B, Emergency Air Supply Fan, is NOT running.
Which one of the following completes the statement below?
IAW with ATT 3 of 3-EOP-E-0, Reactor Trip or Safety Injection:
The RO (1) required to CLOSE D-1A, Ventilation Inlet Damper.
The RO (2) required to start SF-1B, Emergency Air Supply Fan.
A.
(1) is (2) is B.
(1) is (2) is NOT C.
(1) is NOT (2) is D.
(1) is NOT (2) is NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 66 RO Question # 63 Given the following:
x An RCS cooldown to MODE 5 is in progress on Unit 4 utilizing the Steam Dumps to the condenser.
Which one of the following completes the statement below?
Steam Dumps to Condenser are expected to AUTOMATICALLY CLOSE at Tave setpoint of.
A.
547°F B.
543°F C.
541°F D.
537°F
L-23-1 NRC EXAM SECURE INFORMATION Page 67 RO Question # 64 Which one of the following completes the statements below?
IAW OP-AA-100-1000, Conduct of Operations:
The receipt of an expected alarm.
A.
is not required to be announced on the FIRST occurrence or subsequent occurrences B.
is required to be announced on the FIRST occurrence and this announcement should include the reason. The CRS may permit subsequent alarms to not be announced C.
is required to be announced on the FIRST occurrence, but OP-AA-100-1000 does not state that the reason should be included in the announcement. The CRS may permit subsequent alarms to not be announced D.
is required to be announced on the FIRST occurrence and this announcement should include the reason. Announcement of subsequent annunciations of the alarm are required, but the operator is not required to announce the reason on subsequent annunciations
L-23-1 NRC EXAM SECURE INFORMATION Page 68 RO Question # 65 IAW OP-AA-100-1000, Conduct of Operations, which one of the following completes the statements below?
The RO at the controls is required to ensure that a licensed operator performs an end to end panel walkdown at least (1).
The RO at the controls (2) allowed to initiate a condition report from NAMS for equipment deficiencies.
A.
(1) HOURLY (2) is NOT B.
(1) HOURLY (2) is C.
(1) 8 HOURS (2) is NOT D.
(1) 8 HOURS (2) is
L-23-1 NRC EXAM SECURE INFORMATION Page 69 RO Question # 66 IAW 0-ADM-502, In-Service Testing Program, air-operated valves shall be in the pre-exercise position for at LEAST _____ minute(s) prior to full-stroke time testing.
A.
4 B.
3 C.
2 D.
1
L-23-1 NRC EXAM SECURE INFORMATION Page 70 RO Question # 67 Given the following:
x Unit 3 is at 100% power.
x An in-service test has just been completed for the 3B Component Cooling Water (CCW) Pump.
x The test results confirm that the pump's vibrations are in the ALERT range.
Per 0-ADM-502, In-Service Testing Program, which one of the following actions is required for the 3B CCW Pump?
A.
Immediately re-test the pump.
B.
Remove the pump from service.
C.
Increase the frequency of testing.
D.
No actions are required, unless the pump is in the REQUIRED ACTION range
L-23-1 NRC EXAM SECURE INFORMATION Page 71 RO Question # 68 Which one of the following completes the statements below?
IAW Tech Specs, areas accessible to personnel, where radiation levels exceeds as MINIMUM of (1) at 30 cm, are required to be provided with locked doors.
IAW RP-AA-103-1002, High Radiation Area Controls, at PTN the RP Manager (2) required to approve a NON-Urgent entry into the Containment building in MODES 1,2 or 3.
A.
(1) 100 mr/hr (2) is NOT B.
(1) 100 mr/hr (2) is C.
(1) 1000 mr/hr (2) is NOT D.
(1) 1000 mr/hr (2) is
L-23-1 NRC EXAM SECURE INFORMATION Page 72 RO Question # 69 Which one of the following completes the statement below?
IAW 0-ADM-219, Annunciator Response Procedure Usage, a Priority 2 alarm is distinguished by a (1) border and it (2) require immediate response.
A.
(1) yellow (2) does B.
(1) yellow (2) does NOT C.
(1) blue (2) does D.
(1) blue (2) does NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 73 RO Question # 70 Following a reactor trip from 100% power:
Shutdown margin 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor trip will be (1) shutdown margin immediately following the reactor trip - AND - Xe-135 concentration 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> after reactor trip will be (2) than the Xe-135 concentration immediately following the reactor trip.
A. (1) HIGHER THAN (2) HIGHER B. (1) HIGHER THAN (2) LOWER C. (1) THE SAME AS (2) HIGHER D. (1) THE SAME AS (2) LOWER
L-23-1 NRC EXAM SECURE INFORMATION Page 74 RO Question # 71 Which one of the following completes the statement below?
Offset the effects of control rod burnout (1) a function performed by burnable poisons.
Allow higher fuel enrichment of initial core load (2) a function performed by burnable poisons.
A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 75 RO Question # 72 Given the following:
x Unit 3 is performing a reactor startup from a xenon-free condition at EOL.
x After recording critical data, a (+) 0.4 dpm SUR is established.
Subsequently:
x Within 10 minutes and prior to reaching the point of adding heat, reactor power stops increasing and begins to slowly decrease.
Which one of the following changes could have caused this behavior?
A. Letdown temperature increase.
B. Xenon buildup in the core.
C. Gradual cooling of the RCS.
D. Fission-induced heating of the fuel.
L-23-1 NRC EXAM SECURE INFORMATION Page 76 RO Question # 73 Given the following:
x Unit 3 is at 100% power.
x All SG level controls are selected to the BLUE channel.
Subsequently:
x BLUE channel, PT-3-475, 3A SG Pressure, drifts HIGH.
Which one of the following completes the statements below?
Figure (1) identifies the expected SG level control system response.
Unit 3 (2) required to enter a TS action statement.
- 1.
2.
ALSO PROVIDED IN LARGER FORMAT ON THE NEXT PAGE A.
(1) 1 (2) is B.
(1) 1 (2) is NOT C.
(1) 2 (2) is D.
(1) 2 (2) is NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 77
- 1.
- 2.
L-23-1 NRC EXAM SECURE INFORMATION Page 78 RO Question # 74 Which one of the following explains why condensate subcooling is necessary in a nuclear power plant steam cycle?
A. To provide a better condenser vacuum.
B. To maximize overall secondary efficiency.
C. To provide net positive suction head for the condensate pumps.
D. To minimize turbine blade and condenser tube erosion by entrained moisture.
L-23-1 NRC EXAM SECURE INFORMATION Page 79 RO Question # 75 Given the following:
x Unit 4 is operating at 80 percent power near the middle of a fuel cycle.
x All control rods are fully withdrawn and in manual control. Core axial power distribution is peaked below the core midplane.
Which one of the following identifies (1) which manipulation will cause the LARGEST reduction on core axial peaking (or hot channel) factor?
And (2) Which RPS feature protects against DNB?
A.
(1) One bank of control rods is inserted 10 percent.
(2) OPDT B.
(1) One bank of control rods is inserted 10 percent.
(2) OTDT C.
(1) Turbine load/reactor power is reduced by 20 percent.
(2) OPDT D.
(1) Turbine load/reactor power is reduced by 20 percent.
(2) OTDT
L-23-1 NRC Exam Reference List RO & SRO References Steam Tables SRO Only References EAL Tables PCB Section 4 Figure 2 TS 3.5.2
L-23-1 NRC EXAM SECURE INFORMATION Question #
KEY RO 01 A
RO 02 A
RO 03 D
RO 04 B
RO 05 D
RO 06 B
RO 07 A
RO 08 B
RO 09 D
RO 10 A
RO 11 C
RO 12 B
RO 13 A
RO 14 C
RO 15 D
RO 16 C
RO 17 D
RO 18 B
RO 19 C
RO 20 B
RO 21 A
RO 22 B
RO 23 B
RO 24 D
RO 25 C
RO 26 B
RO 27 A
RO 28 A
RO 29 D
RO 30 D
RO 31 C
RO 32 D
RO 33 A
RO 34 C
RO 35 D
RO 36 D
RO 37 A
RO 38 B
RO 39 D
RO 40 C
RO 41 A
RO 42 B
RO 43 B
RO 44 C
RO 45 D
RO 46 A
RO 47 D
L-23-1 NRC EXAM SECURE INFORMATION RO 48 A
RO 49 D
RO 50 D
RO 51 C
RO 52 B
RO 53 C
RO 54 B
RO 55 D
RO 56 C
RO 57 D
RO 58 D
RO 59 C
RO 60 C
RO 61 A
RO 62 B
RO 63 B
RO 64 B
RO 65 A
RO 66 B
RO 67 C
RO 68 D
RO 69 A
RO 70 B
RO 71 C
RO 72 A
RO 73 C
RO 74 C
RO 75 D
SRO 1 / 76 C
SRO 2 / 77 A
SRO 3 / 78 C
SRO 4 / 79 C
SRO 5 / 80 A
SRO 6 / 81 B
SRO 7 / 82 A
SRO 8 / 83 A
SRO 9 / 84 B
SRO 10 / 85 D
SRO 11 / 86 B
SRO 12 / 87 A
SRO 13 / 88 C
SRO 14 / 89 B
SRO 15 / 90 D
SRO 16 / 91 A
SRO 17 / 92 C
SRO 18 / 93 C
SRO 19 / 94 A
SRO 20 / 95 B
L-23-1 NRC EXAM SECURE INFORMATION SRO 21 / 96 A
SRO 22 / 97 C
SRO 23 / 98 A
SRO 24 / 99 C
SRO 25 / 100 C