LaSalle 2018 NRC - ILTandMe

#1. Unit 1 is at 100% RTP, when the following occurs: Core Thermal power drops 2% MWE has a corresponding drop MSL flow drops Core Plate Differential Pressure drops Total jet pump flow rises What is causing these indications?

A. Leaking SRV

B. A Broken Jet Pump

C. Bi-stable flow oscillations

D. Reactor Recirculation Flow Control Valve RVDT failure

#2. Unit 1 is at 100% RTP. 135X-2 AC feed breaker to 1A RPS MG set trips on overcurrent.How will the plant respond in the first 5 minutes?

A. VR fans trip

B. Reactor scram

C. IN Compressors trip

D. Div 1 backup scram valves ENERGIZE

#3. Unit 1 is in Mode 2 with IRMs on ranges 3 and 4. A loss of 1A 24/48 VDC battery bus and charger occurs.What are the effects, if any, on the RCMS (Rod Control Management System) and RPS (Reactor Protection System)?

A. A Rod Block and a full scram

B. A Rod Block and a half scram

C. A Rod Block but NO RPS actuation

D. NEITHER Rod Block NOR an RPS actuation

#4. Unit 2 is at 23% RTP.A Spurious Power Load Unbalance signal is received, and the following is observed: All Main Stop Valves (MSVs) remain open All Control Valves (CVs) are closed The Combined Intermediate Valves (CIVs) are throttled openWhat is the status of reactor pressure control?

A. 1 to 2 Bypass valves are controlling reactor pressure.

B. 4 to 5 Bypass valves are controlling reactor pressure.

C. All Main Steam Isolation Valves (MSIVs) are closed, Safety Relief Valves (SRVs) are controlling Reactor pressure.

D. Turbine remains on line and controlling reactor pressure with no Bypass valves open.

#5. Which RWLC interlock works in conjunction with the scram profile and what function does it provide for?

A. Total Flow Control Setback, which will prevent reaching the Level 8 trip setpoint.

B. Total Flow Control Setback, which will prevent exceeding the maximum runout flow of the FW pumps.

C. Level Control System Setpoint Setdown, which will prevent reaching the Level 8 trip setpoint.

D. Level Control System Setpoint Setdown, which will prevent exceeding the maximum runout flow of the FW pumps.

#6. RCIC is injecting due to an initiation signal CY tank level is at 3′ RCIC suction is from the suppression poolA control room evacuation was necessary, and the 1E51-F010/31/68 component transfer switch was placed into the Emergency position.What is the status of RCIC operation 2 minutes after this action?

A. RCIC is not injecting, with the CY tank suction open only.

B. RCIC injecting into vessel, with suction from suppression pool only

C. RCIC is not injecting, both suppression pool and CY tank suctions open.

D. RCIC injecting into vessel, with suction from suppression pool and CY tank.

#7. Unit 1 is in Mode 4: Reactor Coolant temperature is 150 F Alternate shutdown cooling is in operation with heat removal provided by the reactor water cleanup system 2 RT filter demineralizers are in service The B RWCU Non-Regenerative Heat Exchanger is in use to maintain vessel temperature, with the local D/P gauge 1PDI-WR028, reading of 10.0 psidTwo minutes later: The local RBCCW D/P gauge 1PDI-WR028, reads 2 psid The WR head tank level is steadyWhat is the significance in the change of this D/P reading and the consequence of this change?

A. Reduced WR flow to the Non-Regenerative heat exchanger and a high motor temperature trip of the reactor water cleanup pumps.

B. Reduced WR flow to the Non-Regenerative heat exchanger and potential isolation of the RT filters.

C. Increased WR flow to the Non-Regenerative heat exchanger and could violate temperature limits on the reactor vesse

D. Increased WR flow to the Non-Regenerative heat exchanger and potential heat exchange cavitation

#8. Which of the following Instrument Air/Instrument Nitrogen restoration activities REQUIRE operations to be performed outside of the Main Control Room?

A. Starting a standby SA compressor.

B. Aligning ADS nitrogen supply after a group 10 isolation.

C. Raising pressure for the 100 psig air supply to the drywell.

D. Resetting station air compressor after the second air surge event.

#9. The reactor has been shutdown for 40 days after a 180 day run. RPV level is 50″ and steady. 1E12-F009 Shutdown cooling suction spuriously isolated and will not open. Reactor coolant temperature is currently 140°F and rising. Reactor recirculation pumps are not available. How long will it take to FIRST reach MODE 3?

A. 6 hours

B. 7.5 hours

C. 9 hours

D. 10.5 hours

#10. A fuel bundle was accidently dropped into the Unit 1 Spent Fuel Pool. What is the status of Unit 2 reactor building ventilation fans and release status?

A. Running and effluent monitored by VG WRGM

B. Running and effluent monitored by Stack WRGM

C. NOT running and effluent monitored by VG WRGM

D. NOT running and effluent monitored by Stack WRGM

#11. Which of the following describes the purpose of the Reactor Scram from High Drywell Pressure?

A. The scram limits the amount of energy transmitted to the drywell during a LOCA and limits fuel damage during LOCA.

B. The scram limits the amount of energy transmitted to the drywell during a LOCA and limits decreased core inlet subcooling and steam formation on clad.

C. The scram counteracts the pressure rise by reducing heat generation from the core, which limits drywell pressure from impeding operation of the VQ valves and SRV operation

D. The scram counteracts the pressure rise by reducing heat generation from the core. High drywell pressure directly affects the life span of EQ components located in the drywell.

#12. Unit 1 was at 100% RTP when all CW pumps tripped and were unable to be restarted.Assuming no operator actions, after 60-minutes you would expect to observe tO automatically control reactor pressure.

A. Turbine Bypass Valves throttling at 920 psig

B. Turbine Bypass Valves throttling at 1006 psig

C. One SRV cycling between 896 and 1006 psig

D. One SRV cycling between 976 and 1076 psig

#13. Unit 1 is at 100% RTP: A LOCA occurs Suppression pool temperature is 101 F and rising 2 F/min Reactor Pressure is 800 psig and lowering 10 psig/min All MSIVs are shut Drywell pressure is 8 psig and rising 0.2 psig/min Level is 20 and stable on Narrow Range with feedwaterPer LGA-003, PRIMARY CONTAINMENT CONTROL, if suppression pool temperature cannot be held below (1) all available pool cooling should be started.Given the plant conditions above, suppression pool cooling should be started (2)

A. (1) 105 F(2) After Exceeding 105F

B. (1) 110 F(2) After Exceeding 110 F

C. (1) 105 ‘F(2) Immediately

D. (1) 110 ‘F(2) Immediately

#14. Unit 1 was manually scrammed due to a small break LOCA in the primary containment. Drywell pressure is 2.0 psig and slowly rising Drywell temperature is 215 F and slowly risingWhich of the following identifies the operational implications of using LGA-VP-01, PRIMARY CONTAINMENT TEMPERATURE REDUCTION?

A. Use of LGA-VP-01 is NOT acceptable; its use could cause possible breach of the primary containment from water hammer.

B. Use of LGA-VP-01 is NOT acceptable; its use could cause possible breach of the primary containment due to evaporative cooling effect

C. Use of LGA-VP-01 IS acceptable; it is required to reduce containment temperatures to prevent level reference leg boiling.

D. Use of LGA-VP-01 IS acceptable; it is required to reduce containment temperatures to preserve SRV solenoid operability.

#15. What is the reason that -18 feet was chosen for the Suppression Pool Level at which ADS may not be initiated?

A. -18 feet is the lowest suppression pool level that can be read in the Control Room.

B. At -18 feet insufficient volume of water exists in the suppression pool to absorb the energy from an ADS blowdown.

C. At -18 feet the SRV T-quenchers are uncovered and steam suppression during an ADS blowdown can no longer be assured.

D. -18 feet is the lowest suppression pool level which can be maintained without exceeding the suppression pool boundary design load if SRVs are opened.

#16. Unit 2 was at 100% RTP when a LOCA occurred in the drywell: Reactor Pressure is 825 psig and lowering slowly Drywell Pressure peaked and stabilized at 1.1 psig Reactor water level is -130″ and lowering slowly All low pressure ECCS pumps are runningWhat is the status of ADS?

A. Initiated when the first low pressure ECCS pressure switch picked up.

B. Not Initiated. ADS will initiate 100 seconds after reactor water level dropped below level1.

C. Not Initiated, ADS will initiate 510 seconds after reactor water level dropped below level1.

D. Not Initiated, ADS will initiate 610 seconds after reactor water level dropped below level 1.

#17. When Cold Shutdown Boron Weight has been added and mixed uniformly, the reactor will remain shut down under which of the following conditions:1. All control rods are fully withdrawn.2. The reactor core is at its most reactive exposure.3. No xenon is present in the reactor core.4. No voids are present in the reactor core.5. RPV water level is at the high level trip setpoint.

A. 1, 2, 3, 4, 5

B. 2, 3, 4, 5 ONLY

C. 1, 3, 4, ONLY

D. 1, 2, 5 ONLY

#18. Effluent radiation release rate is 5.30 e +8 uCi/sec from the Standby Gas Treatment Wide Range Gas Monitor.What color is the SPDS RAD RELEASE NORM (HIGH) status box?

A. RED

B. CYAN

C. GREEN

D. YELLOW

#19. LOA-FX-101, UNIT 1 Safe Shutdown with a Fire in the MCR or AEER procedure directs you to OPEN RPS System A and B feed breakers (CB2A and CB2B) located at the (1) on the 749 foot elevation of the Auxiliary Building.These breakers are left open until recovery to (2)

A. (1) RPS Distribution Panel(2) close PCIVs and prevent valves from opening from electrical shorts

B. (1) RPS MG Sets(2) close PCIVs and prevent valves from opening from electrical shorts

C. (1) RPS Distribution Panel(2) prevent resetting the reactor scram

D. (1) RPS MG Sets(2) prevent resetting the reactor scram

#20. Unit 2 is operating at 100% RTP. HPCS is running in full flow test for pump surveillance testing. A transient on the grid causes a grid voltage disturbance. Bus 243 voltage drops to 3800 volts.What will be the Division 3 system response to these conditions?The Bus will load shed 1 , to prevent damaging HPCS pump motor 2

A. 1) Immediately2) on an Auto start condition

B. 1) Immediately2) from over current during the pump surveillance

C. 1) In 5 minutes2) on an Auto start condition

D. 1) In 5 minutes2) from over current during the pump surveillance

#21. Per LGA-003, PRIMARY CONTAINMENT CONTROL, Low Suppression Pool Level leg, a level of (1) in the suppression pool, is the first level where (2)

A. (1) -10 Feet(2) damage may occur to RHR pumps due to exceeding the ECCS Vortex limit

B. (1) -10 Feet(2) steam may not be adequately condensed and primary containment pressure could exceed allowable limits.

C (1) -12 Feet(2) damage may occur to RHR pumps due to exceeding the ECCS Vortex limit

D. (1) -12 Feet(2) steam may not be adequately condensed and primary containment pressure could exceed allowable limits.

#22. Per LGA-010, FAILURE TO SCRAM:You have (1) minutes to place (2) RHR Heat Exchanger(s) online during a power ATWS with all heat going to the primary containment.

A. (1) 15(2) two

B. (1) 10(2) two

C. (1) 15(2) one

D. (1) 10(2) one

#23. A 20 rod ATWS occurs on Unit 1.Per LGA-NB-01, ALTERNATE ROD INSERTION, which of the following steps must be completed to defeat any rod block(s) and insert control rods using theINSERT pushbutton?1) Bypass RWM 2) Bypass CRD drive flow trip circuit switch 3) Reset ARI 4) Reset RPS

A. 1 &; 2 ONLY

B. 1 &; 3 ONLY

C. 2 &; 4 ONLY

D. 1, 2, 3 &; 4

#24. A leak in the RWCU system has occurred causing a high temperature isolation.This isolation occurred at a temperature of (1) measured in the (2)

A. (1) 120 F(2) RT Pump Room

B. (1) 146 F(2) RT Pump Room

C. (1) 120 F(2) RT HX Room

D. (1) 146 F(2) RT HX Room

#25. Which of the following will cause a Reactor Building Ventilation Hi Rad condition?

A. A leak on the suction side of LPCS during a surveillance.

B. Swapping CD/CB Pumps with hydrogen water chemistry on-line.

C. Installed CY Reactor Cavity Sprays fail during vessel drain down.

D. Drywell Inerting in progress and a Reactor Recirc Pump Seal Fails.

#26. Unit 2 is in Mode 5 VR isolated and shutdown. Refueling operations are in progress.Unit 1 is in Mode 1 A steam leak in the Unit 1 main steam tunnel causes a high differential pressure condition in the steam tunnel.Reactor Building Differential pressure will challenge the operability of secondary containment on (1) Standby Gas Treatment (2)

A. (1) Neither Unit(2) starts on Unit 1 ONLY

B. (1) Neither Unit(2) starts on Unit 1 & Unit 2

C. (1) Unit 1 and Unit 2(2) starts on Unit 1 ONLY

D. (1) Unit 1 and Unit 2(2) does not start on either unit

#27. Unit 1 is at 100% RTP.Fire Protection is leaking into the reactor building 694 elevation, southwest corner room. What are the operational implications to the HPCS system, due to rising water level?

A. HPCS low water level transmitter failure.

B. HPCS full flow test valve trip overcurrent.

C. HPCS discharge valve trip on overcurrent.

D. HPCS Water Leg Pump trip on overcurrent.

#28. What are the normal and emergency power supplies to the 1A RHR Water Leg Pump?

A. 133, 0 DG

B. 135Y, 0 DG

C. 134, 1A DG

D. 136Y, 1A DG

#29. Unit 1 was at 100% power when the following occurs: Drywell pressure is 2 psig. 2 minutes later, Off-site power is lost on Unit 1.When the diesel generator output breakers close……

A. A and C RHR pumps start immediately, Low Pressure Core Spray and B RHR pumps start five seconds later.

B. Low Pressure Core Spray and B RHR pumps start immediately, A and C RHR pumps start five seconds later.

C. Low Pressure Core Spray and C RHR pumps start immediately, A and B RHR pumps start five seconds later.

D. A and B RHR pumps start immediately, Low Pressure Core Spray and C RHR pumps start five seconds later.

#30. Reactor Level is 20 on SHUTDOWN range. Reactor Coolant Temperature is 170 F. Shutdown cooling flow is 5000 GPM. Under these conditions, thermal stratification:

A. Is a concern, andRPV level must be raised to greater than 50 on NARROW range to make thermal stratification not a concern

B. Is a concern, andSDC flow must be raised to greater than 6000 GPM to make thermal stratification not a concern

C Is not a concern, andRPV level on shutdown range may be lowered to 0 inches before thermal stratification is a concern

D. Is not a concern, andSDC flow may be lowered to 4000 GPM before thermal stratification is a concern

#31. Unit 1 is in MODE 5.’B RHR pump is operating in Shutdown Cooling mode.Considering BOTH loops of RHR, if theB’ RHR pump had a shaft shear, what function of RHR is unavailable?

A. Alternate Shutdown Cooling

B. Fuel Pool Cooling Assist

C. Shutdown Cooling

D. Head Spray

#32. What conditions are REQUIRED for the LPCS Injection Valve (1E21-F005) to Automatically Open?1) ECCS Signal 2) Power to LPCS Pump 3) LPCS Pump Discharge Pressure 4) Pressure between the Injection Line check valve and Injection Valve is less than 500 psig 5) Reactor Pressure less than 500 psig

A. 1, 2, 3, &; 5

B. 1, 2, 3, &; 4

C. 1, 2, 4, &; 5

D. 3, 4, &; 5

#33. HPCS is injecting to the Unit 1 RPV. HPCS Initiation Logic 125 VDC Control Power fuse F1 blows Reactor water level reaches 45 on wide range and is rising at 5 /minAssuming no operator action, after five minutes, the HPCS Pump will be and the HPCS Injection Valve 1E22-F004 will be

A. Running; Closed

B. Running; Open

C. Not Running; Closed

D. Not Running; Open

#34. HPCS is operating in full flow test for a surveillance.HPCS indicates 2200 GPM on the 1 H13-P601.The HPCS Injection Valve breaker is OOS for maintenance.A LOCA brings in a high drywell pressure signal.What is the status of the HPCS MIN FLOW VLV, 1 E22-F012, PRIOR to the LOCA signal? What is the status of the HPCS MIN FLOW VLV, 1 E22-F012, ONE MINUTE AFTER the LOCA signal?

A. open open

B. open closed

C. closed open

D. closed closed

#35. The plant is operating at 100% RTP. Instrument air was inadvertently isolated to the Standby Liquid Control (SBLC) system. Reactor Building temperature is 84 F and steady. No other evolutions are being performed on the SBLC system.Which of the following Control Room Annunciators, if any, initially alert the Control Room of this isolation?

A. No Control Room Alarms will annunciate.

B. LOR-1H13-P603-A205 SBLC TANK LVL HI/LO for LOW level.

C. LOR-1H13-P603-A205 SBLC TANK LVL HI/LO for HIGH level.

D. LOR-1H13-P603-B502 Standby Liquid Tank Temp HI/LO for low temperature.

#36. A 20% RTP ATWS occurs on Unit 1 and SBLC is manually initiated.Which of the following is confirmation that the 1C41-F004A, Standby Liquid Control Squib Valve, is open AND SBLC is injecting into the RPV?

A. Reactor Water Cleanup is isolated

B. Discharge Pressure of the SBLC pump is 985 psig

C. Discharge Pressure of the SBLC pump is 1340 psig

D. SBLC INJ SQUIB VLV 1C41-F004A Continuity Light Lit

#37. Unit 1 is at 100% RTP with LIS-NB-105A, UNIT 1 REACTOR HIGH PRESSURE SCRAM CHANNELS AAND C CALIBRATION, in progress.IMD has discovered the High Pressure Scram Channel 1B21-N023AA will not trip.1) What effect will this condition have on RPS if RPV pressure reaches a RPS scram setpoint?2) What is the status of LCO 3.3.1.1 RPS Instrumentation?

A. 1) RPS Channels A2 and (B1 or B2) will actuate, causing a FULL reactor scram.2) LCO 3.3.1.1 is met

B. 1) RPS Channels A2 and (B1 or B2) will actuate, causing a FULL reactor scram.2) LCO 3.3.1.1 is NOT met.

C. 1) TheA RPS trip system will NOT actuate, preventing a scram from high pressure.2) LCO 3.3.1.1 is NOT met.

D. 1) TheA RPS trip system will NOT actuate, preventing a scram from high pressure.2) LCO 3.3.1.1 is NOT applicable.

#38. A reactor startup is in progress. IRM A reads 25 on Range 2. Reactor mode switch is in STARTUP.While selecting SRM detectors for withdrawal to maintain SRM Count rate between1 X 10e3 to 1 X 10e5 CPS, IRM A is also selected. The drive out pushbutton is then depressed and held depressed.The “A” IRM detector not full in limit switch will open causing…

A. a 1/2 scram only.

B. a rod block only.

C. no protective actions.

D. a rod block and a scram.

#39. The mode switch is inSTARTUP. IRMs are all on range 5 or 6.During performance of a surveillance for the mode switch, SRMA is moved out ofOPERATE and placed in theSTANDBY position.Which of the following alarm response procedures must be entered?

A. LOR-1H13-P603-A308, ROD OUT BLOCK &;LOR-1H13-P603-A106, SRM INOPERATIVE OR HI

B. LOR-1H13-P603-A308, ROD OUT BLOCK &; LOR-1H13-P603-A206, SRM DOWNSCALE

C. LOR-1H13-P603-B203, CHANNEL A1 REACTOR AUTO SCRAM &; LOR-1H13-P603-A206, SRM DOWNSCALE

D. LOR-1H13-P603-B203, CHANNEL A1 REACTOR AUTO SCRAM & LOR-1H13-P603-A106, SRM INOPERATIVE OR HI

#40. Then the following indication is discovered on channel “C” What effect will this have if the LPRM 6B-40-09 is placed into the bypass position on Unit 1?

A. APRM rod block only.

B. 1/2 scram on A RPS, and rod block.

C. 1/2 scram on B RPS, and rod block.

D. The Rod Block Monitor is generating a rod block.

#41. What is the trip setpoint for maximum disagreement between APRM flow comparator channels, and what signal is generated when it is reached?

A. 10%Half scram

B. 10%Rod withdrawal block

C. 5%Half scram

D. 5%Rod withdrawal block

#42. Unit 1 is at 100% RTP: The Reactor Core Isolation Cooling (RCIC) turbine was started manually per LOS-RI-Q4 COLD QUICK START IN MODES 1, 2, AND 3 While raising turbine speed, a local operator reports steam leakage near the RCIC governor valveHow will the RCIC system respond, if at all, to the operator depressing the RCIC isolation pushbutton on the 1H13-P601 panel?

A. Neither of the RCIC system isolation valves will close.

B. ONLY the inboard isolation valve 1E51-F063 will close.

C. ONLY the outboard isolation valve 1E51-F008 will close.

D. The inboard and the outboard RCIC isolation valves 1E51-F063 and 1E51-F008 will close.

#43. Which of the following conditions require the ADS Inhibit Switches (S26A/S26B) to be placed inINHIBIT?1) A spurious ADS initiation occurs during a non ATWS scram IAW LGA-001, RPV CONTROL2) An ATWS is occurring with RPV water level being maintained -60 to -100 IAW LGA-010, FAILURE TO SCRAM3) A fire in the Main Control Room IAW LOA-FX-101, UNIT 1 SAFE SHUTDOWN WITH A FIRE IN THE CONTROL ROOM

A. 1 ONLY

B. 2 &; 3

C. 3 ONLY

D. 1 &; 2

#44. Unit 1 was operating at 100% RTP when a reactor level transient occurred: HPCS and RCIC automatically initiated LGA-001 was entered and RPV level is now being maintained between +20 and +50″ Drywell pressure is 0.1 psigYou have been directed to reset Group 2 isolations per LOA-PC-101 and have depressed the INBOARD and OUTBOARD isolation reset pushbuttons on the 1H13-P601 panel.Which of the following systems requires additional logic reset before the affected valves can be opened?

A. Drywell Floor Drains

B. Containment Monitoring

C. Primary Containment Cooling

D. Reactor Building Closed Cooling Water

#45. What is the power supply to the SRV solenoids that are operated by the 13 hand switches in the MCR?

A. 111Y

B. 112Y

C. 136X-2

D. 135Y-1

#46. Unit 1 is at 100% RTP: A TDRFP tripped offline The MDRFP failed to auto start Assuming no operator action…A Reactor Recirculation runback will occur

A. immediately and terminate once steam flow is less than 62% ONLY

B. immediately and terminate once reactor water level rises above 31.5″ ONLY

C. once reactor water level drops below 20 and terminate when the FCV reaches its minimum position

D. once reactor water level drops below 31.5 and terminate when steam flow is less than 62% or level exceeds 31.5

#47. The Standby Gas Treatment Cooling Fan starts (1) and the charcoal bed is designed to capture radioactive (2)

A. (1) on a Standby Gas Treatment Primary Fan stop signal(2) nitrogen

B. (1) on a Standby Gas Treatment Primary Fan stop signal(2) iodine

C. (1) when a low flow condition is sensed(2) nitrogen

D. (1) when a low flow condition is sensed(2) iodine

#48. With both Division 1 unit-tie breakers (1414 &; 2414) open, which of the following breakers must be closed to allow closing breaker 1414 from the Main Control Room?

A. SAT Feed to 141Y (1412)

B. SAT Feed to 241Y (2412)

C. Common DG Feed to 141Y (1413)

D. 141Y to 141X Bus Tie Breaker (1415)

#49. Unit 1 is at 100% RTP. The Unit 1 PPC UPS inverter has failed.What is currently powering the Unit 1 PPC UPS loads?

A. 135X

B. 235X

C. 121Y

D. 221Y

#50. The plant is operating at 100% RTP.A malfunction causes the 1A 24/48 VDC battery charger output voltage to change from the normal value to 22 VDC over one minute.Which of the following lists the status of 24/48 VDC battery “1A after the voltage change and the plant load that is affected by the change in voltage?

A. Charging Source Range Monitors A & C

B. Discharging Source Range Monitors A & C

C. Charging Local Power Range Monitors

D. Discharging Local Power Range Monitor

#51. While performing a unit startup in Mode 2, the SAT feed breaker to bus 142Y spuriously tripped.- The 1A Diesel Generator FAILED to automatically start- Attempts to start the 1A DG from the control room have NOT been successful1A DG was manually started locally and is running at 900 rpm. Attempts to raise DG output voltage above 3800 volts have been unsuccessful.With regards to the 1A Diesel Generator, what is the next procedurally required action?

A. Trip the 1A Diesel Generator.

B. Synchronize and close ACB 1423 to re-energize 142Y.

C. Synchronize and close ACB 1425 to re-energize 142Y.

D. Install a jumper on the 1A DG HACR Relay per LOA-DG-101 Attachment A

#52. Unit 1 is at 100% RTP with the followin conditions:Which of the following describes the plant status?

A. An air leak exists at the Instrument Air Receiver.

B. An air leak exists at the scram Instrument Header.

C. The Air compressors are operating in Modulate Mode.

D. The Air compressors are operating in a Surge condition.

#53. The following indications are present following a loss of 112Y. 1) Are these indications expected? 2) If the 1WR179/180 DW Equip RBCCW InIt/Otlt Inbd Isols Bypass Keylock Switch is taken to BYPASS and the 1WR179/180 Control Switch is taken to OPEN the valves will?

A. (1) No(2) Open

B. (1) No(2) Remain Closed

C. (1) Yes(2) Open

D. (1) Yes(2) Remain Closed

#54. While performing a startup with reactor pressure at 300 psig, what will be the major driving force for the Scram if the Scram Solenoid Pilot Valves lost power?

A. Reactor Pressure

B. Cooling Header Pressure

C. Scram Accumulator Pressure

D. Control Rod Drive Pump Discharge Pressure

#55. Reactor coolant temperature is 220 F Both reactor recirculation pumps are secured. Rx Vessel Bottom Head metal temperature is 170 F as read from the CRD temperature recorder.The following indications are found at the 1H13-P602 panell# 1603MPOiiJT TE*1nELE.’EHFIf starting Reactor Recirculation under these conditions, what point of temperature measurement would you verify for the bottom head area and what issue does this address?

A. Rx Bottom Head Drain temperature, to prevent challenging the 100 F/hr heat up on the bottom head

B. Rx Vessel Bottom Head Metal temperature to prevent challenging the 100 F/hr heat up on the bottom head.

C. Rx Bottom Head Drain temperature, to prevent dropping below the 10.1 F delta T limit.

D. Rx Vessel Bottom Head Metal temperature, to prevent dropping below the 10.1 F delta T limit.

#56. Unit 1 is at 100% RTP with 1B RT Pump online.Two minutes later… The Reactor was scrammed due to a feedwater leak in the Main Steam Tunnel All rods remained out SBLC is injecting Reactor water level is at -30 on Wide Range lowering at 2″/min What is the status of the 1B RT Pump?

A. The 1B RT Pump is online

B. The 1B RT Pump tripped due to 1G33-F001 (RT inboard isolation valve) closing

C. The 1B RT Pump tripped due to 1G33-F004 (RT outboard isolation valve) closing

D. The 1B RT Pump tripped due to a Group 5 isolation caused by low reactor water level

#57. Which of the following APRM and RBM Channel combinations will be affected by a downscale failure of FLOW UNITD?APRM Channel

A. A A

B. D A

C. E B

D. F B

#58. Unit 1 was scrammed due to a small unisolable feedwater leak.A RHR Pump is running in suppression pool cooling RCIC is injecting Suppression pool level is 1.5 feet below its normal operating level and stableWhich of the following are valid methods to monitor Suppression Pool Temperature from the Main Control Room?1) Suppression Pool Temperature Monitors (Numac)2) RCIC Discharge Temperature3) A RHR Heat Exchanger Inlet4) PPC

A. 1, 2 &; 4

B. 1 ONLY

C. 2 &; 3

D. 3 &; 4

#59. Unit 1 is at 100% Power. LOS-RH-Q1, RHR (LPCI) AND RHR SERVICE WATER PUMP AND VALVE INSERVICE TEST FOR MODES 1, 2, 3, 4 AND 5, is in progress. 1E12-F027A RHR, Chamber Spray Valve, failed its exercise test and is unable to be opened remotely or locally.LCO 3.6.2.4 (RHR Suppression Pool Spray) and applies in Modes

A. IS MET1, 2, 3, 4, and 5

B. IS MET1, 2, and 3 ONLY

C. IS NOT MET1, 2, 3, 4, and 5

D. IS NOT MET1, 2, and 3 ONLY

#60. Unit 1 is in MODE 2 at 3% RTP:At this power what will be the position of the Reactor Head Vents 1B21-F001 and 1B21-F002 and why?

A. Open; to prevent noble gas release in the drywell.

B. Open; to prevent non-condensables from accumulating in the reactor head area.LAS OPS ILT NRC EXAM Page: 141 of 239 15 November 2018EXAMINATION ANSWER KEY17-1 NRCEXAM

C. Closed; to prevent noble gas release in the drywell.

D. Closed; to prevent non-condensables from accumulating in the reactor head area.

#61. The following is displayed on the 1PM02J:With NO operator action, how will the plant respond?1) Turbine Trip2) Reactor Scram3) Reactor Recirc Pump Downshift4) ES Non-Return Check Valves Close

A. 1 and 3

B. 2 and 3

C. 1 and 4

D. 2 and 4

#62. What is the Power Supply to 1C Condensate/Condensate Booster Pump?

A. Bus 141X

B. Bus 142X

C. Bus 151

D. Bus 152

#63. What design feature of the Offgas system prevents the poisoning of the recombiner catalyst by the presence of water?

A. Offgas reheater

B. Offgas preheater

C. Offgas condenser

D. Offgas moisture separator

#64. Which of the following conditions could cause the VC Emergency Makeup Unit to automatically actuate?

A. Smoke in the outside air intake.

B. Smoke in the return air plenum.

C. Ammonia in the outside air intake.

D. Ammonia in return air plenum.

#65. Units 1 and 2 are at 100% RTP. During a Fire Protection Surveillance, theA VC Charcoal train was accidently deluged.What are the required actions? Enter……1). LCO 3.7.4 for Control Room Area Filtration Inoperable2). LCO 3.7.5 for Control Room Area Ventilation Air Conditioning Inoperable 3). TRM 3.3.p for Fire Protection Instrumentation Inoperable4). TRM 3.7.k for Deluge Spray and Sprinkler System Inoperable

A. 1 and 2.

B. 2 and 3.

C. 3 and 4.

D. 1 and 4.

#66. Unit 1 is at 100% RTP: LIS-MS-305A, UNIT 1 MAIN STEAM LINE PIPE TUNNEL HIGH DIFFERENTIAL TEMPERATURE ISOLATION (DIV 1) FUNCTIONAL TEST is in progress. Alarms have been flagged.Subsequently: LOR-1H13-P601-F501, DIV 1 MSL PIPE TUNNEL DIFF TEMP HI Alarms. (The first annunciation of the shift). This alarm has no flag.What action(s) is/are required? Acknowledge the annunciator…

A. ONLY.

B. AND announce, “expected alarm”

C. AND announce, “DIV 1 MSL PIPE TUNNEL DIFF TEMP HI” ONLY.

D. AND announce, “DIV 1 MSL PIPE TUNNEL DIFF TEMP HI” AND reference the LOR.

#67. Unit 2 is at 100% RTP: 2A and 2C CW pumps are running A loss of 211Y occursThe Assist NSO will dispatch the equipment operator to…

A. check condenser pit level at the Lake Screen House.

B. verify traveling screen differential pressure is less than 12 inches.

C. verify the slip guard relay for the 2B CW pump is clear and start the 2B CW pump from 2PM03J.

D. throttle discharge structure sluice gate 2 closed, after starting the 2B CW pump from the 2PM03J.

#68. Which of the following plant conditions is allowed to be communicated during the Scram Choreography? Updating the crew on a…

A. spurious Group 4 Isolation.

B. valid Group 7 Isolation on a Reactor Level signal.

C. valid Group 1 Isolation on Low Condenser Vacuum.

D. SINGLE Level 8 channel light illuminated with Reactor Level at 0″ and slowly rising.

#69. The reactor water cleanup system is tagged out for maintenance.A valve that will have maintenance performed on it is discovered with an info tag placed on it. What action by the work supervisor is acceptable and why?

A. Contact the Shift for permission to work on this valve because INFO cards are only used for Condition Dependent Clearance Orders to obtain the condition.

B. Inform the Outage Control Center no work can be done on this valve because INFO cards are signed off as placed and therefore are a part of the Clearance Order.

C. Contact the Shift for permission to work on this valve because INFO cards may NOT hold a boundary point, but only contain information.

D. Inform the Contract Supervisor no work can be done on this valve because this would violate the Clearance Order zone of protection.

#70. Which of the following identifies a Tech Spec LCO condition which would require entry into the Required Action Statement and logged per OP-AA-111-101, OPERATING NARRATIVE LOGS AND RECORDS?

A. ‘V’ SRV INOP with Thermal Power at 30%

B. ‘A’ and ‘D’ SRMs INOP with Thermal Power at 20%

C. ‘A’ Rod Block Monitor (RBM) INOP with Thermal Power at 20%

D. ‘A’ and ‘E’ OPRM Modules are INOP with Thermal Power at 30%

#71. Unit 2 is at 100% RTP: Reactor water level is +36 inches and stable Drywell pressure is 0.2 psig and stable The Division 1 ADS Manual Initiation pushbuttons (2B21-S32A and 2B21-S33A) are armed, depressed, and releasedTen seconds later the Division 1 ADS Low Level Logic Reset Pushbutton (2B21-S31A) is depressed and released.What is the status of the following relays?K4A K8A

A. De-Energized De-Energized

B. Energized De-Energized

C. De-Energized Energized

D. Energized Energized

Reference provided during examination: 1E-2-4201AB

#72. Unit 1 is at rated power and annunciator 1H13-P601-B110, Reactor Building Radiation HI is in alarm. Based on the given conditions, which indication would require entry into Emergency Operating Procedures?

A. RB TIP ROOM

B. RB South HCU

C. RB TIP Drive Units

D. TB OFF GAS SAMPLE STATION

#73. Unit 2 is at 5% RTP: The Reactor Mode Switch is in ‘STARTUP’. A Drywell entry is in progress with personnel currently investigating a suspected leak Subsequently A high worth Control Rod begins to drift OUT The crew will…

A. Scram Unit 2 AND evacuate the Drywell.

B. Scram Unit 2 AND continue to investigate the leak.

C. evacuate the Drywell AND follow-up with actions to insert ONLY the drifting control rod.

D. continue to investigate the leak AND follow-up with actions to insert ONLY the drifting control rod.

#74. During an emergency condition, Reactor Operator actions that DEVIATE from plant Technical Specifications are needed to protect the health and safety of the public.In accordance with HU-AA-104-101, Procedure Use and Adherence, these actions require…

A. approval of the Plant Manager (non-licensed).

B. approval of a licensed Senior Reactor Operator.

C. concurrence of a second licensed Reactor Operator.

D. approval of the Nuclear Regulatory Commission (NRC).

#75. 1) Which emergency facility assumes responsibility for communications with offsite agencies including the NRC once it is activated?2) What is the lowest classification level that requires this facility’s activation during a non-security event?

A. 1) Technical Support Center (TSC)2) Alert

B. 1) Technical Support Center (TSC)2) Unusual Event

C. 1) Operations Support Center (OSC)2) Alert

D. 1) Operations Support Center (OSC)2) Unusual Event

#76. Unit 2 is at 100% RTP with the Division 1 Diesel Generator OOS: Loss of SAT occurs ACB 2415 FAILS to Fast Transfer Bus 242Y trips on overcurrent(1) What Attachment of LOA-AP-201, Unit 2 AC Power System Trouble will be directed by the Unit Supervisor?(2) What Reactor Water Level Instrument is available?

A. (1) Attachment K, Station Blackout Contingencies(2) B Narrow Range Instrument

B. (1) Attachment J, Restore Power to 242Y Using Unit Tie Breakers, 142Y Powered from SAT 142 and 142Y – 142X Bus Tie Breaker Closed(2) B Narrow Range Instrument

C. (1) Attachment K, Station Blackout Contingencies(2) A Narrow Range Instrument

D. (1) Attachment J, Restore Power to 242Y Using Unit Tie Breakers, 142Y Powered from SAT 142 and 142Y – 142X Bus Tie Breaker Closed(2) A Narrow Range Instrument

#77. A loss of SAT occurs on Unit 1 141Y tripped on overcurrent 1A EDG has Failed 142Y failed to fast transfer causing a scram 142Y was manually transferred within 5 minutes and is being powered by Unit 2 HPCS is maintaining Reactor Level automatically between its high and low level injection setpointsAs the Shift Manager what is the Emergency Classification Level that should be declared for Unit 1?

A. Unusual Event

B. Alert

C. Site Area Emergency

D. General Emergency

#78. Unit 2 is in MODE 3.2A RHR is running in shutdown cooling. A level transient causes a HPCS initiation. The 2E12-F009, RHR shutdown cooling suction header inboard Isolation valve, closes and will not re-open.1) What reactor level causes the trip of Shut Down Cooling?2) Which alternate decay heat removal plan should the Unit Supervisor select from OU-LA-104 Shutdown safety management?

A. 1) SDC trips on reactor level 22) LOP-RH-17, Alternate SDC using SRVs

B. 1) SDC trips on reactor level 32) LOP-RH-17, Alternate SDC using SRVs

C. 1) SDC trips on reactor level 22) LOP-RT-13, RWCU Alternate Decay Removal

D. 1) SDC trips on reactor level 32) LOP-RT-13, RWCU Alternate Decay Removal

#79. A LOCA occurred on Unit 1: Drywell pressure is 67 PSIG Containment Flood Level is 700 Feet Hydrogen concentration is 3% Oxygen concentration is 2% Stack WRGM reads 8.56 E+09 uCi/sec VG WRGM reads 1.21 E+02 uCi/sec(1) What is the required status of containment venting per LGA-VQ-102, UNIT 1 EMERGENCY CONTAINMENT VENT?(2) Why?

A. (1) In progress(2) to lower pressure within PCPL

B. (1) In progress(2) to reduce hydrogen and oxygen concentrations below deflagration limits

C. (1) NOT in progress(2) LGA-009 entry criteria is met

D. (1) NOT in progress(2) The WRGM high-high rad release alarm is in

#80. The Heat Capacity Temperature Limit (HCTL) is

A. the maximum primary containment temperature at which SRVs can be opened and will remain open.

B. the highest suppression chamber temperature which can occur without steam in thesuppression chamber airspace

C the highest suppression pool temperature at which opening an SRV will not result in exceeding the code allowable stresses in the SRV tail pipe, tail pipe supports, quencher, or quencher supports

D. the highest suppression pool temperature at which emergency RPV depressurization will not raise Suppression chamber temperature above maximum temperature capability of the suppression chamber.

#81. The Technical Requirements Manual (TRM) Basis for the Automatic Depressurization System (ADS) Manual Inhibit Switches is to prevent…

A. core damage from low pressure ECCS systems injecting at low pressures from an automatic ADS during an ATWS.

B. an automatic ADS from reducing reactor pressure below 150 psig, ensuring RCIC is available for injection during an ATWS.

C. the ADS logic from being initiated from an external hot short by limiting the voltage across the relay coil with the shorting contact.

D. ADS SRVs from opening during an Anticipated Transient Without Scram (ATWS), ensuring all energy is diverted to the Main Condenser.

#82. Unit 1 and Unit 2 are at 100% RTP: TSO Informs you Braidwood Unit 1 is going offline Grid Voltage changes from 362KV to 357KV At LaSalle on Unit 1: MVAR changes from 200 MVARs to 600 MVARs Machine Gas pressure is 60 psig MWe changes from 1180 MWe to 1160 MWeThe main generator is currently operating (1) , and the unit supervisor should direct (2)

A. (1) outside the Unit 1 generator capability curve(2) lowering U1 main generator by 50 MVARs, IAW OP-AA-108-107-1002 (Interface Procedure Between Corned and Exelon Generation for Transmission Operations)

B. (1) outside the Unit 1 generator capability curve(2) raising machine gas pressure 15 psig, IAW LOP-HY-07 (Increasing Generator Hydrogen Pressure)

C (1) within the Unit 1 generator capability curve(2) documenting minimum and projected switchyard voltage IAW attachmentC of LOA- GRID-001 (Low Grid Voltage)

D. (1) within the Unit 1 generator capability curve(2) contacting Gen Dispatch for an unplanned change of >10 MWe, IAW OP-AA-102- 101 (Management of Nuclear Generation)

Reference provided during examination: LOP-HY-07 Unit 1 Generator Capability Curve

#83. A LOCA has occurred on Unit 1: Drywell Temperature is 210 F Reactor Building Temperature is 145 F Reactor Pressure is 600 psig and stableWhich of the following RPV Level Instruments may be used AND is also Tech Spec required Post Accident Monitoring (PAM) Instrumentation?

A. Wide Range reading -135 inches

B. Upset Range reading +15 inches

C. Narrow Range reading +30 inches

D. Fuel Zone Range reading -300 inches

#84. (1) What caused the above condition?(2) Prior to restarting the VR fans, what action will be directed first by the Unit Supervisor?

A. (1) Loss of A RPS Bus(2) Bypass Main Steam Tunnel delta T trips per LOA-VR-101, UNIT 1 RECOVERY FROM A GROUP 4 ISOLATION OR SPURIOUS TRIP OF REACTOR BUILDING VENTILATION

B. (1) Loss of 111Y(2) Bypass Main Steam Tunnel delta T trips per LOA-VR-101 UNIT 1 RECOVERY FROM A GROUP 4 ISOLATION OR SPURIOUS TRIP OF REACTOR BUILDING VENTILATION

C. (1) Loss of A RPS Bus(2) Secure Standby Gas Treatment per LOP-VG-02, SHUTDOWN OF THE STANDBY GAS TREATMENT SYSTEM

D. (1) Loss of 111Y(2) Secure Standby Gas Treatment per LOP-VG-02, SHUTDOWN OF THE STANDBY GAS TREATMENT SYSTEM

#85. There is a LOCA on Unit 1. Water level is -140 on WR and stable Hydrogen concentration is 3% and rising at 0.1%/min Oxygen concentration is 6% and rising at 0.1%/min Unit 1 Hydrogen Recombiner is in service on the U1 Drywell The primary containment is currently being vented per LGA-VQ-102, UNIT 1 EMERGENCY CONTAINMENT VENT Drywell pressure is 15.0 psig and continues to rise at 0.1 psig/minThe U1 Hydrogen Recombiner should be (1) because the recombiner (2)

A. (1) secured(2) is a potential source for hydrogen deflagration or detonation

B. (1) secured(2) discharge line loop seal will blow out at drywell pressures >15.3 psig

C. (1) left in service(2) reduces hydrogen accumulation in the RX head and pedestal areas

D. (1) left in service(2) is sized to maintain hydrogen concentration below 4% at the recombiner inlet

#86. Unit 2 is at 100% Power with NO active time clocks, when the following occurred: 2H13-P601-C404 RHR 2A and LPCS LINE INTEGRITY MONITOR Alarm was received. Local reading was confirmed to be reading 1 psid to the left of zero, indicating a problem with LPCS injection line. IMD was dispatched and the calibration was confirmed in tolerance for the DP switch per LOR actions.(1) Based on the above conditions, a LPCS Core Spray piping leak/break may have occurred (2) What is the status of the LPCS system?

A. (1) inside the shroud(2) Requires an operability determination.

B. (1) inside the shroud(2) Declare the system inoperable and IMMEDIATELY enter LCO 3.0.3.

C. (1) between the Reactor Pressure Vessel and the Core Shroud(2) Requires an operability determination.

D. (1) between the Reactor Pressure Vessel and the Core Shroud(2) Declare the system inoperable and IMMEDIATELY enter LCO 3.0.3.

#87. Both units are at 100% power.The alternate RPS power supply is out of service for corrective maintenance.- 0830 on June 1, the underfrequency protection for one of the EPMAs on the 1A RPS MG Set is declared INOPERABLE.- 0930 on June 1, the undervoltage protection for one of the EPMAs on the 1B RPS MG Set is declared INOPERABLE.- The RPS Alternate Power Supply cannot be restored to serviceIncluding any extensions allowed by Technical Specifications, when must the 1A RPS MG Set EPMA be restored to OPERABLE status to prevent removing the EPMA from service OR entering a Condition requiring a shutdown?

A. 1030 on June 1

B. 0830 on June 4

C. 0930 on June 4

D. 0830 on June 5

#88. A LOOP occurred on Unit 1 and Unit 2: The RCIC corner room fan trips on overcurrent. RCIC EQP ROOM temperature reads 185 F and is rising. RCIC is online and maintaining reactor water level in band.Unit 1 RCIC is….

A. operable but will be INOP if corner room temperature is not lowered below 150 F within 4 hours.

B. inoperable because RB ventilation and room cooling are both lost to the RCIC corner room.

C. operable until an analysis is performed that demonstrates inoperability of the equipment.

D. inoperable until room temperature lowers below 150F.

#89. Unit 2 is at 100% RTP: ‘A Reactor Recirc Flow Control Valve Locked-up for Maintenance Moments later On the DS001 Alarm Screen “TDRFP A/B Soft Trip” appears 2H13-P603-A409, Feedwater Control Reactor Water Level Low – Level 4 Annunciates 2C Motor Driven Reactor Feed Pump Starts Reactor Water Level is recovering(1) What condition caused the above alarm on the DS001?(2) What procedure will the Unit Supervisor direct as the highest PRIORITY?

A. (1) High Pressure Stop Valve and Low Pressure Stop Valve not full open and a Trip device in the tripped position(2) LOA-FW-201, Reactor Level/Feedwater Pump Control Trouble

B. (1) Greater than 60% mismatch between expected discharge flow and actual discharge flow for 3 seconds, provided there is no mismatch between total pump flow and total header flow.(2) LOA-FW-201, Reactor Level/Feedwater Pump Control Trouble

C. (1) High Pressure Stop Valve and Low Pressure Stop Valve not full open and a Trip device in the tripped position(2) LOA-RR-201, Unit 2 Reactor Recirculation System Trouble

D. (1) Greater than 60% mismatch between expected discharge flow and actual discharge flow for 3 seconds, provided there is no mismatch between total pump flow and total header flow.(2) LOA-RR-201, Unit 2 Reactor Recirculation System Trouble

#90. Unit 1 is at 100% RTP with LOS-RI-Q5 REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM PUMP OPERABILITY, VALVE INSERVICE TESTS IN MODES 1,2,3 AND COLD QUICK START is inprogress. When the RCIC system is started in full flow test, the following alarm is received. LOR-1PM01J-A409 125VDC Panel 111X/Y Panel Ground Detector Alarm. The Rounds Equipment Operator reports that the ground is at 115 Volts to the left.1). What is the consequence of a large ground?2). What actions should the Unit Supervisor direct next?

A. 1). Large ground will drain the battery and lower terminal voltage 2). Secure RCIC operation per LOS-RI-Q5

B. 1). Large ground will drain the battery and lower terminal voltage.2). Place the backup battery charger online and isolate the on service battery charger per LOP-DC-04, 125 VDC DIV 1 GROUND LOCATION AND ISOLATION

C. 1). Large ground could energize or defeat protective relays 2). Secure RCIC operation per LOS-RI-Q5

D. 1). Large ground could energize or defeat protective relays2). Place the backup battery charger online and isolate the on service battery charger per LOP-DC-04, 125 VDC DIV 1 GROUND LOCATION AND ISOLATION

#91. Unit 1 is shutting down RCMS shows INSERT and WITHDRAW blocks RCMS shows power below the Low Power Setpoint (LPSP) and Low Power Alarm Point (LPAP) box 1H13-P603-A308, Rod Out Block is LITWhat is the Technical Specification Basis for the CURRENT Rod Out Block? To prevent exceeding …..

A. 280 cal/gram during a control rod drop accident.

B. 1% plastic strain during a control rod drop accident.

C. 280 cal/gram during a control rod withdrawal accident.

D. 1% plastic strain during a control rod withdrawal accident.

#92. Unit 1 is at 100% power:LOR-1N62-P600-B208, OFF GAS POST-TREATMENT RADIATION TROUBLE is in alarm.At the 1H13-P604 the1A &1B Off Gas Post-Treatment Rad Monitors (1D18-K601A & 1D18-K601B) fail downscale.(1) What is the status of the 1N62-F057, Off Gas Vent Stack Discharge Valve?(2) What is/are the ODCM required action(s)?

A. (1) OPEN(2) Enter ODCM 12.2.2 RA D.1 and D.2 and D.3

B. (1) OPEN (2) Enter ODCM 12.2.2 RA C.1

C. (1) CLOSED(2) Enter ODCM 12.2.2 RA C.1

D. (1) CLOSED(2) Enter ODCM 12.2.2 RA C.1

#93. A DBA LOCA is occuring on Unit 1: HPCS is injecting at 6500 gpm 141Y tripped on overcurrent Drywell and Chamber Sprays are on ‘1B’ RHR ‘1C’ RHR pump tripped on overcurrent RPV Pressure is 20 psig DW pressure is 20 psig RPV Water level is -220″ on Fuel Zone and lowering 2″/min An RPV blowdown per LGA-004, RPV BLOWDOWN, has been initiated(1) Adequate core cooling is not met because(2) Per LGA-001, RPV CONTROL, the next action directed by the Unit Supervisor will be to

A. (1) spray flow is inadequate, and the top 1/3 of the fuel is not adequately cooled.(2) maximize injection using preferred and alternate injection sources

B. (1) RPV water level is too low, and the top of jet pump risers are uncovered.(2) maximize injection using preferred and alternate injection sources

C. (1) spray flow is inadequate, and the top 1/3 of the fuel is not adequately cooled.(2) exit all LGAs and Enter all SAMGs

D. (1) RPV water level is too low, and the top of jet pump risers are uncovered.(2) exit all LGAs and Enter all SAMGs

#94. In order to maintain an active Senior Reactor Operator (SRO) License, quarterly, the MINIMUM the License Holder must stand is…

A. five (5) twelve (12) hour shifts as the Unit Supervisor or Shift Manager.

B. four (4) twelve (12) hour shifts as the Unit Supervisor or Shift Manager.

C. five (5) twelve (12) hour shifts as Work Execution Control (WEC) Supervisor.

D. four (4) twelve (12) hour shifts as the Field Supervisor fulfilling the role of Shift Technical Advisor (STA).

#95. A high power ATWS is in progress on Unit 2: Hardcard actions for ATWS are completed LGA-MS-201, USING MAIN CONDENSER AS A HEAT SINK IN ATWS, is in progress with the hardcard actions complete. MSL radiation monitors indicate a Hi/Hi radiation condition Off Gas post treatment rad monitor indicates Hi radiation Main Steam Tunnel temperature is 200 F and rising MSL flow is risingWhat is the NEXT required action?

A. OPEN MSIVs to use the Main Condenser as a heat sink.

B. Verify MSIVs REMAIN OPEN to use the Main Condenser as a heat sink

C. CLOSE MSIVs so that the Containment is used as a heat sink.

D. Verify MSIVs REMAIN CLOSED so that the Containment is used as a heat sink.

#96. What weather condition would trigger an On-line risk re-evaluation in Paragon per the On-Line Work Control Process?

A. Tornado Watch

B. Wind gust of 45 mph

C. Sustained winds of 35 mph

D. Severe Thunderstorm warning

#97. 165 F.The Unit is currently in (1) and the (2) must be completed prior to Reactor Vessel Head closure bolt detensioning.

A. (1) Mode 3(2) Mode Change Checklist From Mode 3 To Mode 4A.

B. (1) Mode 4(2) Mode Change Checklist From Mode 4 To Mode 5

C. (1) Mode 4(2) Mode Change Checklist FromAt All Times To Mode 5

D. (1) Mode 5(2) Mode Change Checklist From Mode S To Mode 4

#98. An electrical ATWS has occurred from rated conditions on Unit 1:B RPS remains energized following the ATWS choreography ARI has FAILED to actuate LGA-NB-01 (Alternate Rod Insertion) Method 1 is in progress LGA-NB-01 Attachment 1B is complete (Scram Solenoid Fuses Removal) LGA-NB-01 Attachment 1E (SDV Vent and Drain Fuses Removal) has been ordered but has NOT yet been started(1) What is the current status of the Scram Discharge Volume Vent and Drain Valves?(2) What should be ordered NEXT if Attachment 1E is NOT successful in repositioning SDV Vent and Drain Valves?

A. (1) OPEN (2) Evacuate unnecessary personnel from the Reactor Building

B. (1) OPEN(2) Perform Method 6 (Single Rod Scram) of LGA-NB-01

C. (1) CLOSED(2) Evacuate unnecessary personnel from the Reactor Building

D. (1) CLOSED(2) Perform Method 6 (Single Rod Scram) of LGA-NB-01

#99. Reactor Pressure is 1002 psig Turbine Generator is 1193 MWeMoments later the following changes were noted… Average Power Range Monitors (APRM’s) indicate 98.3% and are stableN cv 100 W IU2 100 W V’ Q0 #2. 1 100 % 2. %Bypass Valves1 2 3 4KL L IIWLLIF FrTPI OieB ResetD at erimsLackThe Unit Supervisor should direct the crew to enter…

A. LOA-EH-101 (Unit 1 EHC Abnormal) to reduce reactor power to less than 85% to maintain within the COLR assumptions

B. LOA-PWR-101 (Unit 1 Unplanned Reactivity Addition) to reduce Reactor power using Control Rods

C. LOA-EH-101 (Unit 1 EHC Abnormal) to check Reactor Pressure consistent with EHC Active Pressure Setpoint

D. LOA-PWR-101 (Unit 1 Unplanned Reactivity Addition) to reduce Reactor power using RR FCVs

#100. Which of the following must the Work Execution Center perform when terminating a fire impairment? 1) Verify the condition causing the fire watch is corrected2) Notify supervisor in charge of the fire watch that it may be terminated3) Retain a copy of the completed fire watch log sheets in the WEC for 1 year4) Notify NEIL of any fire pump or suppression system impairments that exceeded 48 hours

A. 1 &; 2

B. 1 &; 3

C. 2 &; 4