LaSalle 2014 NRC - ILTandMe

#1. What is the reason for an automatic scram when thermal-hydraulic instabilities are sensed during a partial or complete loss of forced circulation core flow? The reactor scram avoids exceeding …

A. the MCPR Safety Limit during flux oscillations.

B. the MFLPD operating limit due to low coolant flow.

C. the MAPRAT operating limit due to low coolant flow.

D. the Reactor Pressure Safety Limit during flux oscillations.

#2. Operators are performing DC Load shedding IAW LOA-AP-101 “AC SYSTEM ABNORMAL” during a station Blackout event. After 6 hours into the event; operators will maintain …

A. availability of Reactor Building emergency lighting.

B. ability to operate Emergency Seal Oil Pump.

C. Plant Process Computer availability.

D. ADS operation.

#3. Both Units are at full power.U-2 SBGT is OOS for maintenance. Unit 2 has a Loss of Div 2 DC The Unit-1 NSO notes the U-1 SBGT is in standby(1) What LGA will be entered on Unit 1?(2) What is the correct action/report for the Unit-1 NSO?

A. (1) LGA-001(2) Start U-1 SBGT

B. (1) LGA-002(2) Start U-1 SBGT

C. (1) LGA-002(2) Report U-1 SBGT is unavailable due to the loss of U-2 Div 2 DC

D. (1) LGA-001(2) Report U-1 SBGT is unavailable due to the loss of U-2 Div 2 DC

#4. Unit 1 was at 100% power with RR FCV matched at 90% open indication when agenerator lockout occurred. The Unit scrammed with all rods inserted EHC Bypass valves failed to respond on turbine trip HPCS and RCIC actuated to restore reactor level Reactor level is being controlled per level band of LGA-001 at 20-50 inches NO other operator action has been takenWhat is the status of Reactor Recirculation?

A. Both pumps tripped to zero speedBoth FCV at 90% position

B. Both pumps operating In slow speedBoth FCV at 90% position

C. Both pumps tripped to zero speedBoth FCV at minimum position

D. Both pumps operating in slow speedBoth FCV at minimum position

#5. The reason for Setpoint Setdown of the RWLC (Reactor Water Level Control)System is to:

A. Momentarily lower the reactor water level setpoint when transferring from threeelement control to single element control.

B. Lower the reactor water level setpoint when there is only one feedpump running.

C. Ensure the feedpump turbines do NOT overspeed following a SCRAM.

D. Help maintain reactor water level below level 8 following a scram.

#6. Of the following choices; which choice ONLY lists SRVs that are available to usefrom the Remote Shutdown Panel?

A. 1B21-F013H and 1B21-F013K

B. 1B21-F013U and 1B21-F013S

C. 1B21-F013K and 1B21-F013U

D. 1B21-F013P and 1821-F013S

#7. Unit 1 is at 100% power when the following occurred. 1PM10J-A303 TURBINE BUILDING CLOSED COOLING WATER(TBCCW) EXPANSION TANK 1WT01T LEVEL LOW alarm is received 1 PM02J B505 EHC MINOR alarm is received. The following EHC work station alarms are received: EHC LEVEL INCREASING OVER TIME EHC RESERVOIR HI LEVEL The Unit rounds EO reports that the U-1 and common station air compressor oiltemperatures have risen by 5 degrees from the previous shiftThe operating crew will. ..

A. swap EHC coolers and isolate the affected EHC cooler.

B. swap EHC pumps; to isolate the online cooler.

C. start the U-2 Station Air Compressor.

D. scram U-1 and close MSIVs.

#8. Unit 1 and 2 are at 100% power; U-2 was in the process of re-inerting; when thefollowing occurred A rupture of the 4″ instrument air headers is reported(1) Without operator actions predict the response of the U-2 VQ air-operateddampers?(2) What is the containment isolation status of VQ dampers?

A. (1) Fail as-is(2) Isolation capability maintained

B. (1) Fail closed(2) Isolation capability maintained

C. (1)Failas-is(2) Isolation capability NOT maintained

D. (1) Fail closed(2) Isolation capability NOT maintained

#9. Unit 2 is in mode 4 with Shutdown Cooling (SDC) in operation. The Reactor Recirculation pumps are shutdown. Due to a spurious isolation of SDC; the system isolates and will NOT reset.Which one of the following is an operational requirement?Monitor …

A. to verify less than 25 gpm bottom head drain flow.

B. to detect if there is a loss of adequate core cooling.

C. for excess Reactor Recirculation Loop Delta temperatures.

D. for excessive thermal stresses between vessel bottom head and vessel top head flange.

#10. During Core Alterations on Unit 1; a spent fuel assembly is dropped. Bubbles are immediately seen rising from the area of the dropped fuel assemblyOn Unit 1; the following readings are observed on 1H13-P635 and 1H13-P636.The appropriate annunciators activate for the above conditions.Based on the above information only;VERIFY that (1) auto started and verify (2)

A. ( 1) ONLY Unit 1 SBGT train(2) ONLY U-1 VQ Primary Containment Isolation DampersNalves close

B. (1) ONLY Unit 1 SBGT train(2) BOTH U-1 and U-2 VQ Primary Containment Isolation Valves/Dampers close

C. (1) BOTH Unit 1 and Unit 2 SBGT trains(2) ONLY U-1 VQ Primary Containment Isolation Valves/Dampers close

D. (1) BOTH Unit 1 and Unit 2 SBGT trains(2) BOTH U-1 and U-2 VQ Primary Containment Isolation Valves/Dampers close

#11. With regards to starting Suppression chamber sprays ONLY.What is the impact of starting Suppression chamber sprays with suppression poolwater level between 723′ and 723.5′?

A. Challenge containment integrity when using drywell sprays.

B. Inability to Quench steam may result in containment failure.

C. Limiting the scrubbing action -0f the suppression pool if venting was required.

D. Hydraulic forces caused by chamber spray operation could damage the SRV tailpipes.

#12. The reason for the automatic actuation of Alternate Rod Insertion (ARI) on highreactor pressure is to …

A. act in conjunction with the Recirculation pumps to prevent exceeding the RPVpressure safety limit.

B. utilize the RPS trip units to provide an alternative vent path for the scram airheader as a backup to RPS.

C. anticipate a reactor scram and assists RPS by establishing alternate vent pathsfor the scram air header.

D. act independently of RPS to establish alternate vent paths during conditions thatshould have resulted in a reactor scram.

#13. U-2 was at rated power when a plant transient created the following conditions: Suppression Pool Level is -13′ Suppression Pool Temperature is 221F Suppression Chamber Pressure is 5 psigWhich one of the following changes in Suppression Pool parameters would mostlikely cause HPCS pump damage while operating the pump based on the graphbelow?

A. Suppression Pool Level drops by 18 inches

B. Suppression Pool Level is raised by 1 foot

C. Suppression Chamber Pressure lowers by 1 psig

D. Suppression Pool Temperature rises by 4F.

#14. Unit-1 was manually scrammed due to a small break LOCA in the primary containment. The following conditions exist: Drywell pressure is 2.0 psig and slowly rising Drywell temperature is 215F and slowly risingWhich one 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 acceptable; it is required to reduce containment temperatures to prevent level reference leg boiling.

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

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

#15. Unit 2 is in LGA-003 PRIMARY CONTAINMENT CONTROL procedure; due to a plant transient. RPV pressure is 500 psig. A Group 1 isolation has occurred. A and B RHR systems are not available. At what Suppression Pool Water Temperature and Level will a RPV blowdown be required?

A. Suppression Pool level -0.5 ft. Suppression Pool temperature 210F.

B. Suppression Pool level -8.0ft. Suppression Pool temperature 190F.

C. Suppression Pool level -4.0ft. Suppression Pool temperature 200F.

D. Suppression Pool level +1.0ft. Suppression Pool temperature 200F.

#16. Unit 2 was at 100% power with HPCS OOSThen a LOCA with a loss of the SAT occurred. Drywell pressure is 3 psig RPV level is -30 inches and dropping 10 inches/minute RPV pressure is 900 psig and dropping 50#/minuteAssuming NO operator action select the highest value below that would result in arising Reactor Water Level.

A. 800 psig

B. 650 psig

C. 300 psig.

D. 200 psig

#17. An ATWS is in progress: The Mode switch is in shutdown “A” RPS failed to actuate ARI failed to actuate The SDV fuses were pulled per LGA-NB-01 The “A” RPS Fuses were pulled per LGA-NB-01; method 1 with some controlrod movement Reactor power is at 15%The MCR has just been notified that jumpers are installed per LGA-NB-01 method 4.Of the choices below; the next action is to …

A. install Scram Solenoid fuses

B. vent off the scram air header

C. install SDV Vent and Drain Valves fuses

D. re-scram reactor using manual push buttons

#18. Unit 2 was at 100% power when a transient with a high energy line break occurs.Which one of the following would be the Minimum sets of parameters that require entry into LGA-009 “RADIOACTIVITY RELEASE CONTROL”SBGT WRGM SVS ACTIVITY SVS WRGM

A.

B.

C.

D.

#19. Which of the following describes the response of the Fire Protection system to theactivation of an ionization smoke detector in the cable spreading room (Pre-actionSprinkler System)?

A. With FP piping dry and depressurized up to the sprinkler head; a vial at thesprinkler head breaks from high temperature and Fire Protection waterimmediately flows through the associated piping and the sprinkler head.

B. A deluge valve is automatically opened; water immediately sprays the entirearea.

C. A deluge valve is automatically opened; the vials at the sprinkler head breaksfrom high temperature; and then air in the system will depressurize out of thesprinkler head followed by water.

D. With FP piping filled with water up to the sprinkler head; a vial at the sprinklerhead breaks and Fire Protection water immediately flows through the associatedsprinkler head.

#20. Operators are directed to secure the loads listed in LOA-GRID-001; “Low GridVoltage”; Attachment “A”.What is the reason for this action?Attachment A loads are secured in order to prevent …

A. exceeding the generator capability curve.

B. SAT damage in case of a Main Generator trip.

C. grid damage due to instabilities from low voltage.

D. off-site power from becoming inoperable with a Unit scram.

#21. Units 1 and Unit 2 are at 100% power with VR in a normal alignment; with the “A”and “B” supply and exhaust fans running on both units; when the following occurs: The 2B VR supply fan trips due to overload. With NO operator action; select the statement describing which automatic actions will occur and why?

A. The 2C VR Supply Fan auto-starts to keep the Leak Detection instrumentation operable on Unit 2.

B. The 2A and 2B VR Exhaust Fans trip to protect against excessive negative Reactor Building pressure.

C. Both Units A and B Exhaust Fans trip to prevent excessive Dp on Reactor Building interlock doors.

D. The 2C VR Supply Fan auto-starts to maintain the Reactor Building air flow from lower to higher potentially contaminated areas.

#22. Unit 2 is at 100% reactor power when the following occurred. One of the running feed pumps trip.(1) Does the initial resultant transient bring the Unit closer to aCARRYOVER or CARRYUNDER condition?(2) What is the primary concern associated with this condition?

A. (1) CARRYUNDER(2) Decrease in core plate Op

B. (1) CARRYOVER(2) Excess erosion of the head vents

C. (1)CARRYUNDER(2) Reduction in Recirc Pump Net Positive Suction Head.

D. (1) CARRYOVER(2) Excess moisture impinging the blades of the Main Turbine

#23. Given the following initial plant conditions: The Unit-1 reactor is being shutdown in accordance with the Normal Shutdownprocedure The mode switch was placed in STARTUP from RUN NSOs were monitoring power on the IRMs All APRM downscale lights were lit Due to a leaking Safety Relief Valve (SRV); reactor pressure has dropped from920 psig to 700 psigThe control room operator reports that multiple Average Power Range Monitors(APRMs) downscale lights have cleared and reactor power is rising on theIntermediate Range Monitors (IRMs).( 1) Which of the following actions are you expected to take based on the above conditions?and(2) What is the reason for these actions?

A. (1) Stop rod movements and range the IRMs to follow the power change.(2) To terminate a recriticality event

B. (1) Discontinue driving rods and manually scram the reactor.(2) To prevent violating fuel clad integrity safety limit

C. (1) Stop rod movements and range the IRMs to follow the power change.(2) To prevent an IRM SCRAM

D. (1) Discontinue driving rods and manually scram the reactor.(2) To terminate a recriticality event

#24. Due to a security event Both Units are shutdown with the following conditions: Both Unit 1 and 2 SATs are NOT available. Both Unit 1 and 2 Division 1 and 2 DGs are NOT available.Which of the following is the Preferred action to be taken to mitigate an off-siterelease?

A. Line up B.5.b pump in Spent Fuel Pool Spray mode to directly cool fuelassemblies per LOA-SY-004 EXTREME DAMAGE MITIGATION STRATEGIES.

B. Line up FC pumps per LOA-FC-101 FUEL POOL COOLINGSYSTEM/REACTOR CAVITY LEVEL ABNORMAL to supply cooling to the spentfuel pool.

C. Line up B RH in Fuel Pool Cooling Assist per LOP-RH-15 RHR FUEL POOLCOOLING ASSIST AND ALTERNATE FUEL POOL COOLING MODES.

D. Line up B.5.b pump in Spent Fuel Pool Make Up mode to maintain fuelassemblies submerged per LOA-SY-004 EXTREME DAMAGE MITIGATIONSTRATEGIES.

#25. Unit-1 is at 100% Reactor Power.The following annunciator is in alarm1H13-P603-A204; CRD Charging Water Pressure LowThe following information is availableBased on the above conditions; what actions are required:

A. Perform the actions of the LOR for the tripped CRD pump

B. Perform LOA-RD-101 CONTROL ROD DRIVE ABNORMAL for the Stabilizing Valves that have failed closed

C. Perform LOA-RM-101 for loss of power to the CRD indications

D. Peform LOA-RD-101 CONTROL ROD DRIVE ABNORMAL for the CRD Flow Control Valve that has failed closed

#26. Unit 1 is in mode 4 with A RHR in Shutdown Cooling (SDC) operation when the following occurredWhat could have caused the event?

A. RHR SDC flow was lowered to 1400 GPM

B. B RHR Full Flow Test 1E12-F024B leaking by

C. Mis-operation of the Skimmer Surge Tank drain valve 1FC017

D. Mis-operation of RCIC Suction Valves 1E51-F010 and 1E51-F031 at the Remote Shutdown Panel

#27. Within the Secondary Containment what is the total number of PCIS groupisolations that will occur on high area temperature?(Do NOT include isolations that occur solely due to high delta temperatures)?

A. 2 PCIS groups

B. 3 PCIS groups

C. 4 PCIS groups

D. 5 PCIS groups

#28. With the 1A RHR system operating in the LPCI injection mode with an ECCSsignal present; a TRIP of the Common Diesel Generator Cooling Water Pump willdirectly result in which of the following?

A. The O DG will trip on high coolant temperature.

B. The A RHR pump room ambient temperature will be higher than expected due tothe loss of cooling water to the area coolers.

C. The A RHR pump seal temperatures will be higher than expected due to the lossof cooling water to the seal coolers.

D. The A RHR pump motor bearing temperatures will be higher than expected dueto the loss of cooling water to the motor cooler;

#29. Unit 2 is in Mode 4 following completion of a refueling outage. The vessel has been re-assembled. The B Loop of RHR is tagged out and drained. The C RHR Pump is available.The A loop of RHR was operating in the Shutdown Cooling mode but the A RHRPump has just tripped.The reactor coolant heatup rate will now be (1) the heatup rate would havebeen if this transient occurred just prior to the start of refueling activities thisoutage.(2) Of the following decay heat removal lineups; which one has the least potentialto damage other equipment?

A. ( 1) more than(2) Draining reactor water through the RHR HX to the Suppression Pool and thenreturning it to the RPV withthe C RHR Pump

B. ( 1) more than(2) Pumping Suppression Pool water into the RPV and then returning it to theSuppression Pool through SRVs

C. (1)1essthan(2) Draining reactor water through the RHR HX and Full-Flow Test Valve to theSuppression Pool and then returning it to the RPV withthe C RHR Pump

D. (1) less than(2) Pumping Suppression Pool water into the RPV and then returning it to theSuppression Pool through SRVs

#30. 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 RHRpumps start five seconds later.

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

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

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

#31. Unit 2 is in a LOCA with LPCS injecting into the vessel with flow at 1800 GPM thefollowing occurs:The LPCS pump trips.What is the status of the LPCS min flow valve?The valve will. ..

A. travel to the open position.

B. remain open.

C. travel to the closed position.

D. remain closed.

#32. Unit-1 was at 100% reactor power when the following occurred: Small break LOCA in the drywell Drywell Pressure reached 2.0 psig HPCS initiated and injected into the vessel . Reactor level reached level 8 HPCS responded as designedIf it is desired to keep HPCS running after 30 minutes with these conditions presentwhat actions if any must the NSO take?

A. The NSO must secure the HPCS pump because operation is NOT allowed afterthirty minutes.

B. NONE; HPCS can remain in its current configuration since the min flow valve isopen.

C. The NSO must depress HI DRYWELL PRESSURE/LO WATER LEVELpushbutton reset and then open the full flow test valve.

D. The NSO must depress BOTH LEVEL 8 and HI DRYWELL PRESSURE/LOWATER LEVEL pushbutton resets and then open the full flow test valve.

#33. Unit 2 is in an ATWS condition. The keylock switch for the 2B SBLC Pump is placed in “SYS B”.Aside from starting the 2B SBLC pump; what else will this switch movement initiate?

A. ONLY the System B Squib valve energizesand RWCU inboard isolation valve; 2G33-F001 will close.

B. ONLY the System B Squib valve energizesand RWCU outboard isolation valve; 2G33-F004 will close.

C. Squib valves for BOTH System A and System B will energizeand RWCU inboard isolation valve; 2G33-F001 will close.

D. Squib valves for BOTH System A and System B will energizeand RWCU outboard isolation valve; 2G33-F004 will close.

#34. Unit 2 was operating at rated power when a scram occurred. The Reactor Mode Switch is in SHUTDOWN. The scram has NOT been reset.The Backup Scram Valves will be (1) and (2)

A. (1) energized(2) venting

B. (1) energized(2) NOT venting

C. (1) de-energized(2) venting

D. ( 1) de-energized(2) NOT venting

#35. Unit 2 is at 2% power with a Startup in progress and all IRMs on Range 9 or 10. Anevent occurs resulting in the following: IRM “A” has failed upscale IRM “A” Mode Switch placed in STANDBY I RM “A” has been bypassed The fault has NOT been cleared yetPredict the final status of the lights/alarms on 2H 13-P635 if the conditions aboveremain as-is and the operator manipulates the IRM “A” reset switch

A. The INOP; UPSCALE HIGH and UPSCALE HIGH HIGH will CLEAR.

B. The INOP; UPSCALE HIGH and UPSCALE HIGH HIGH will REMAIN LIT.

C. The INOP light will CLEAR but the UPSCALE HIGH and UPSCALE HIGH HIGH will REMAIN LIT.

D. The INOP light will REMAIN LIT but the UPSCALE HIGH and UPSCALE HIGH HIGH will CLEAR.

#36. A reactor startup is in progress following a refueling outage with NO SRMs or IRMsbypassed. Given the following: All IRMs are downscale on Range 1 SRM A reads 5 X 10;000 CPS SRM Breads 3 X 10;000 CPS SRM C reads 6 X 10;000 CPS SRM Dreads 4 X 10;000 CPS The shorting Links are installedWhich one of the following identifies the expected plant response if the HighVoltage Power Supply for SRM A is lost?

A. A full scram would occur.

B. NO automatic actions would occur.

C. ONLY a control rod block would occur.

D. BOTH a control rod block AND a half scram would occur.

#37. Unit 2 was at 100% power when the following occurred: A loss of off-site power. The O DG auto started and loaded onto Bus 241 .The 0 DG is the only source of power to 241Y LATER: Bus power restoration is in progress IAW LOP-AP-16 RETURNING 4160VOLT BUS 141Y(241Y) FROM DIESEL 0 POWER TO ITS NORMALSOURCE OF POWER.(1) What is the impact of leaving the 0 DG speed droop at 0% when synchronizingtothe SAT?(2) If left in this condition while synchronizing the DG to the grid what is the nextrequired action?

A. (1) Maximum instability condition in this mode of operation(2) Continue to offload DG per shutdown procedure.

B. (1) Minimum instability condition in this mode of operation(2) Continue to offload DG per shutdown procedure.

C. (1) Maximum instability condition in this mode of operation(2) Direct Local Operator to place maintenance switch in maintenance positionwhen the DG trips.

D. (1) Minimum instability condition in this mode of operation(2) Direct Local Operator to place maintenance switch in maintenance positionwhen the DG trips.

#38. Unit 2 is operating at 95% power with 80% Recirc Flow on all 4 Flow Units.If a RPV pressure increase transient began raising power; at which (nominal) valuewould the Reactor Scram occur?(Assume NO operator action and that a reactor scram occurs from the APRMsprior to exceeding the RPV high Pressure Scram setpoint)(Note: The current slope of the APRM Thermal Power Upscale Flow-Biased Scramsetpoint is defined as .61W + 68.2%.)

A. 113.5%

B. 117%

C. 118%

D. 129.2%

#39. With U-1 at 100% power:Which of the following describes the effect of a loss of 125 VDC Bus 111 X?

A. Reactor Water Level Control “C” Narrow range level indication will be lost.

B. 1A Diesel Generator field flashing source is lost.

C. 1A TDRFP has lost remote tripping capability.

D. MDRFP has lost auto start capability.

#40. Unit 1 is in hot shutdown: Unit 1 RCIC is operating in pressure control mode in AUTO at 600 GPM.Given the following parameters:Time Rx Pressure12:00 405 PSIG13:00 235 PSIG(1) Can your cool down rate be raised and still be within limits?(2) Based on cool down rate; how would you adjust RCIC operation?

A. (1) Yes(2) Throttle Open full flow test valve

B. (1) No(2) Throttle Open full flow test valve

C. (1) Yes(2) Throttle Closed full flow test valve

D. (1) No(2) Throttle Closed full flow test valve

#41. The panel 1H13-P601-E alarms are as shown. Annunciator 1H13-P601-E105 just alarmed. Which of the following identifies the status of annunciators 1H13-P601-E202 and 1H13-P601-E203 in 12 minutes if plant parameters remains stable

A. 1H13-P601-E202 will be LIT ONLY

B. 1H13-P601-E203 will be LIT ONLY

C. BOTH 1H13-P601-E202 AND 1H13-P601-E203 will be LIT

D. BOTH 1H13-P601-E202 AND 1H13-P601-E203 will be EXTINGUISHED

#42. Unit 1 is performing a plant shutdown.Per LGP-2-1 during the cool down; what RWCU isolation can be affected due towater density changes?

A. High Flow isolation

B. High Delta Flow isolation

C. Blow down flow (1G33-F033) isolation

D. High Demineralizer inlet temperature system isolation

#43. With Unit 1 is at 100% power; IAW LOP-MS-10; “Cycling Main Steam Line SafetyRelief Valves”; the following alarms are expected during the performance of SRVcycling. 1H13-P601-E102; ADS or SRV Leakage 1H13-P601-F102; ADS Valve Accumulator Press Lo 1H13-P601-F201; ADS Valve Fully Open 1H13-P601-F302; Safety Relief Valve Fully OpenAssume that an SRV has just been opened; verified open; and then closed duringa span of 10 seconds.All of the above alarms came in while the SRV was open.Which alarm will CLEAR LAST?

A. 1H13-P601-F102; ADS Valve Accumulator Press Lo

B. 1H13-P601-F302; Safety Relief Valve. Fully Open

C. 1 H13-P601-E102; ADS or SRV Leakage

D. 1H13-P601-F201; ADS Valve Fully Open

#44. Unit 1 is at 100% power; when the following occurs: An SRV spuriously lifts. Suppression Pool temperature is currently at 89F and rising 1F /minute. Both loops of Suppression Pool cooling are in operation.What is the Maximum amount of time before the mode switch is required to beplaced in shutdown?

A. 14 minutes

B. 16 minutes

C. 21 minutes

D. 31 minutes

#45. Unit 1 was at 80% power with Feed Flow and Steam Flow matched when the following occurred: The 1C Inboard MSIV failed closed No scram setpoints were exceeded when the MSIV closed 10 seconds have passed since the MSIV closed1) On the 1H13-P603 panel recorder for Feed Flow and Steam Flow; will theSteamFlow indication read LOWER or HIGHER than Feed Flow? 2) Assuming NO operator action; will Unit 1 trip on the RPV water LEVEL 3 or LEVEL 8 signal?

A. 1) LOWER than Feed Flow 2) LEVEL 3

B. 1) LOWER than Feed Flow 2) LEVEL 8

C. 1) HIGHER than Feed Flow 2) LEVEL 3

D. 1) HIGHER than Feed Flow 2) LEVEL 8

#46. What is the purpose of the 1VG023 SBGT-VQ XTIE VALVE on the Standby Gas Treatment System (SBGT)?

A. Enhance the ability to perform on-line maintenance.

B. Provide an isolation point for Local Leak Rate testing.

C. Prevent over pressurizing the VG System during the onset of a LOCA.

D. Prevent collapsing VG system ductwork during Normal VQ system start-up.

#47. Following a loss of coolant accident; the Standby Gas Treatment system has beenin service purging the Drywell; per LGA-VQ-03; PRIMARY CONTAINMENTPURGE: SBGT WRGM release rates were stable and then began to rise.Which one of the following explains the elevated release?

A. Relative Humidity in the drywell has lowered from 80% to 50%.

B. Charcoal Adsorber access door is NOT fully closed.

C. The Electric Heater is de-energized.

D. The SBGT stack loop seal is blown.

#48. Given the following initial plant information: Unit-1 is in a refueling outage. Unit-1 UAT is a qualified off-site source. Bus 13 is de-energized. Unit-2 is in Mode 2 with a start-up in progress.Given this initial lineup; which one of the following combinations of failures wouldresult in a loss of all Off-Site AC power to both units?

A. Unit 2 Ring Bus and TR-81

B. Unit-1 UAT and Unit-2 SAT

C. Unit-1 UAT and Lines L0101 and L0104

D. Unit-2 SAT and Lines L0102 and L0103

#49. Which of the following completes the statements?The Unit 1 and Unit 2 Process Computer are fed from (1 ) UPS(Uninterruptable Power Supply).If Inverter output is lost; describe the effect on the Unit 1 and Unit 2 Processcomputer?The alternate power supply swaps (2)

A. (1) a common(2) without interruption

B. (1) separate(2) without interruption

C. (1)acommon(2) after a 5 second time delay

D. (1) separate(2) after a 5 second time delay

#50. Which ONE of the following completes the statements relating to Station BatteryRoom HVAC Systems?If these systems are NOT operating properly; the Operational impact is that (1)Because of this; provisions are provided in plant procedures to (2)

A. (1) lead-calcium batteries tend to release sulfuric gas into the atmosphere attemperatures above 900 n(2) Install Portable Temporary Ventilation Equipment

B. (1) lead-calcium batteries tend to release sulfuric gas into the atmosphere attemperatures above 900 r r(2) start a special log; monitoring with portable gas monitor equipment

C. (1) the design limit for hydrogen concentration in the rooms may be reachedduring battery charging operations(2) start a special log; monitoring with portable gas monitor equipment

D. ( 1) the design limit for hydrogen concentration in the rooms may be reachedduring battery charging operations(2) Install Portable Temporary Ventilation Equipment

#51. LOS-DG-M2; 1A/2A DIESEL GENERATOR OPERABILITY TEST is in progressfor the 1A Diesel Generator.While performing this surveillance; you must NOT go below (1 ) _ load inorder to (2) __

A. (1) 200 kW(2) prevent excessive wear to turbocharger gear drive

B. (1)400kW(2) prevent excessive wear to turbocharger gear drive

C. (1)200kW(2) prevent the Diesel Generator from tripping on reverse power due to large loadchanges on the grid

D. (1) 400 kW(2) prevent the Diesel Generator from tripping on reverse power due to large loadchanges on the grid

#52. Both Units are at 100% power. All Traveling Screens are in Automatic All Traveling Screen differential levels are at 2 in wg. Lake Level as read on the PPC in the MCR is 699.3 ftWhat effect; if any; would a COMPLETE LOSS OF INSTRUMENT AIR have on:1) The Screen Wash capability of the Traveling Screens?2) Lake Level Indication in t.he MCR?

A. (1) Screen Wash capability would be LOST(2) Will be unreliable

B. (1) Screen Wash capability would be LOST(2) NO EFFECT

C. (1) Screen Wash capability would be AUTOMATICALLY MAXIMIZED(2) Will be unreliable

D. (1) Screen Wash capability would be AUTOMATICALLY MAXIMIZED(2) NO EFFECTLAS LICENSED OPS Page: 105 of 154 05 November 2014

#53. Unit 2 is 100% reactor power; when the following occurred: LOS-RH-01 RHR (LPCI) AND RHR SERVICE WATER PUMP AND VALVEINSERVICE TEST FOR MODES 1;2;3;4 AND 5 is in progress. The 2A RH WS strainer backwash motor tripped on thermal overload during abackwash.Which of the following statements describes the effect on 2A RHR WS system orthe action to take?

A. Immediately secure the system due to strainer unavailability.

B. Backwash feature is unavailable; system can continue to operate.

C. Backwash feature is still available; system can continue to operate.

D. System can continue to operate until high strainer Op Alarm; then secure system.

#54. Unit 2 is in Mode 2 at 8% Power. Control Rod withdrawal is in progress “BLOCKS TO FULL” is enabled on the Rod Worth Minimizer (RWM)From this condition; the TOTAL STEAM FLOW output signal from Digital ReactorWater Level Control to the Rod Worth Minimizer FAILS HIGH.How will subsequent rod motion be affected?The RWM will …

A. apply insert and withdrawal blocks to ALL rods.

B. allow rod motion by single notch increments ONLY.

C. apply rod blocks in accordance with the loaded rod sequence.

D. allow ALL rod motion independent of the loaded rod sequence.

#55. The Unit 1 Reactor Recirculation Flow Control system is operating in LoopAutomatic mode with the RR-FCVs 68% open and RVDT selected on both loops.Given the following from the 108001 panel. (see attached reference)Which one of the following describes the 1A Flow Control Valve (FCV) response?The Flow Control Valve has …

A. failed OPEN to 100%.

B. immediately LOCKED UP.

C. started to open then switched to its LVDT.

D. started to CLOSE then switched to its LVDT.

#56. The Reactor Water Cleanup System (RWCU) is in normal operation at full power.Based on the indications provided; in which position would the RWCU LOOPTEMP SELECT switch be in?Panel 1H13-P602 RWCU indication

A. 5

B. 4

C. 2

D. 1

#57. Unit 1 is at 100% power. Assume leakage flow has become just high enough to activate the Flow Switch1 FS-FC015 shown below.1) Does this Flow switch initiate an alarm in the MCR or at the Fuel Pool CoolingPanelin the Turbine Building?2) Will continued leakage require filling the Skimmer Surge Tank with CycledCondensate(CY) or filling the Fuel Pool with Clean Condensate(MC)?

A. 1) Alarms in the MCR 2) Fill the Fuel Pool with Demineralized Water

B. 1) Alarms in the MCR 2) Fill the Skimmer Surge Tank with Cycled Condensate

C. 1) Alarms in the Turbine Building at the Fuel Pool Cooling Panel 2) Fill the Fuel Pool with Demineralized Water

D. 1) Alarms in the Turbine Building at the Fuel Pool Cooling Panel 2) Fill the Skimmer Surge Tank with Cycled Condensate

#58. Fuel movements are in progress. The reactor mode switch is locked in the REFUEL position All Rods are fully inserted One rod is selected A fuel assembly has been grappled in the Fuel Pool and is being transferred tothe reactor core for installationWhich statement; if any; describes the refueling interlock(s) that will be in effect;when the refueling bridge closes the over-the-core limit switches?

A. No refueling interlock is in effect.

B. ONLY a rod block interlock is in effect.

C. ONLY bridge motion towards the core is stopped.

D. A Rod block interlock AND bridge motion towards the core is stopped.

#59. Unit 2 is in Mode 2; Reactor start-up in progress with the following conditions. Reactor pressure is at 145# with 1 /2 turbine bypass valve open Pressurization is on hold in preparation of RCIC testing LOP-OG-09 pre-warming OG recombiner is in progress(1) IAW LGP-1-1 UNIT START-UP what is the preferred method to controlcondensateflow?(2) What is the minimum flow requirement for each operating condensate pump?

A. (1) Control Flow with the TDRFP min flow(2) Minimum flow requirement is at least 5000 GPM.

B. (1) Control Flow with hotwell reject to CY tank(2) Minimum flow requirement is at least 5000 GPM.

C. (1) Control Flow with the CB pump Min flow valves(2) Minimum flow requirement is at least 1500 GPM.

D. (1) Control flow with Condensate recirc. to condenser via heater drain system(2) Minimum flow requirement is at least 1500 GPM.

#60. IAW LOP-CD-03 STARTUP AND OPERATION OF THE CONDENSATE ANDCONDENSATE BOOSTER SYSTEM; a precaution step states that on a loss ofCD system at normal pressures do not restart the CD system until FW (FeedWater) has had sufficient time to cool; or FW is isolated by the FW pump suctionvalves and the FW seal injection system.This prevents …

A. high water level trips in the HP heaters.

B. water hammer within the condensate system.

C. pump run out conditions in the Condensate Pump.

D. windmilling a TDRFP during Condensate pump restart.

#61. Unit 1 is operating at power when a loss of RPS A occurs.Which of the following Process Radiation Monitoring systems would be affected by the loss?

A. Off Gas Post Treatment Monitor

B. Main Steam Line Radiation Monitors

C. Off Gas Pretreatment Linear Monitor

D. Control Room Air Intake Radiation Monitors

#62. What are the Operational implications of the 0 DG room temperature reaching 109 F and the 0 DG is in operation. When the 0 DG is secured …

A. the ventilation fan will immediately automatically stop.

B. the ventilation fan will continue to run and manual shutdown is required.

C. the ventilation fan will continue to run until room temperature lowers to approximately 104F.

D. the ventilation fan will automatically stop when the DG is secured; but restart if room temperature reaches 110F

#63. Unit 2 is at 100% power; when the following occurs: A contractor calls the Main Control Room and reports that they are in the 710elevation air lock from Reactor building to the Off-gas building and CANNOTopen the Off-gas building airlock door. Assume this interlock is original design and has NOT been modified.What is the cause for them NOT being able to exit into the Off-gas building?

A. Power to door interlock is de-energized.

B. The door from the Reactor Building is open.

C. Reactor Building track way Door 19 or 20 is open.

D. The Reactor Building to atmosphere Dp is at 0.4 inches/WG.

#64. Which one of the following combinations of U-1 Control Room HVAC (VC) Air Intake Monitoring System detectors with an upscale high trip will close the VC outside air damper and start the VC emergency makeup train?

A. 1D18-K751A and 1D18-K751C

B. 1D18-K751A and 1D18-K751B

C. 1D18-K751B and 1D18-K751C

D. 1D18-K751B and 1D18-K751D

#65. At 100% power what would be the effect of the MS IVs closing faster than 3seconds?

A. Prevent over torquing of the MSIV actuators.

B. Loss of RPV water inventory below the wide range level indication.

C. Excessive hydraulic shock to the downstream components in the main steamsystem.

D. RPS may NOT protect the fuel assemblies and reactor coolant pressureboundary.

#66. Unit 1 is operating at 100% power: There have been NO Condensate Polisher or RWCU Filter Demin changeoutsfor 2 days. Hotwell and Condensate Polisher inlet conductivity levels were both atapproximately 0.1 umho/cm when they started rising by 0.1 umho/cm every 10minutes. While Operators and Chem Techs are investigating IAW LOA-COND-101;UNIT 1 REACTOR WATER/CONDENSATE HIGH CONDUCTIVITY; theconductivity at both points continues to rise.A Manual Scram is required when Condensate Polisher Inlet Conductivity firstrises to …

A. 1.0 umho/cm

B. 2.0 umho/cm

C. 5.0 umho/cm

D. 10.0 umho/cm

#67. A locked manual valve in a safety-related system is to be verified locked in theOPEN position. Per OP-AA-108-101-1001; COMPONENT POSITIONDETERMINATION; which of the following is required?(Note: Assume locking device will allow some valve movement.)INITIALLY attempt to move the valve in the …

A. CLOSED direction with the locking device INSTALLED.

B. CLOSED direction with the locking device REMOVED.

C. OPEN direction with the locking device INSTALLED.

D. OPEN direction with the locking device REMOVED.

#68. A motor operated valve (MOV) has been torqued into its seat.Which ONE of the following describes:(1) Preferred source to find the valve’s physical location?(2) The method to be used the next time the valve must be unseated?

A. (1) The system startup procedure(2) Electrically with the handswitch

B. (1) Passport(2) Electrically with the handswitch

C. (1) The system startup procedure(2) Manually

D. (1) Passport(2) Manually

#69. A sample valve needs to be electrically isolated to allow maintenance to work onthe valve. It is determined that: Opening the associated breaker or pulling the individual fuses will affect a largeportion of the containment isolation system. Taking the control switch in the control room to OFF will electrically isolate thesample valve.Using the above information; select the statement that describes how to continuewith the Clearance Order (CO) utilizing the control switch as the boundary.The CO will need to be …

A. a routine CO with an INFO card on the control switch.

B. a routine CO with a Danger card on the control switch.

C. an exceptional CO with a Danger card on the control switch.

D. an exceptional CO with an INFO card on the control switch.

#70. From the following; which statement describes “Operable-Operability”; inaccordance with LaSalle Technical Specifications?The condition of a system; subsystem; division; component; or device …

A. capable of performing its specified safety function with some of its supportsystems inoperable.

B. that will allow testing; calibration or inspection to assure operation is within SafetyLimits and LCOs.

C. necessary to protect the integrity of certain physical barriers to guard against theuncontrolled release of radioactivity.

D. capable of performing its specified safety function with its support systemscapable of performing their required support functions.

#71. Given the following: A reactor startup is in progress NO control rods have been withdrawn Initial SRM count rates are: SRM A 30 SRM B 35 SRM C 50 SRM D 45Which of the following is the requirement IAW LGP-1-1 “Unit Startup” to STARTsingle notch withdrawal of control rods?

A. RWM is Inoperable

B. SRM C count rate of 200

C. Group 1 control rods all at position 48

D. The reactor is NOT critical after reaching the ECP estimated critical prediction

#72. Unit 2 is in a Refueling Outage. All vessel work has been completed and thereactor cavity water level is being lowered to the flange.(1) Which of the following is a concern IAW LOP-FC-16 REACTOR VESSEL/CAVITY DRAINDOWN VIA RHR SDC? (2) What is to be done to mitigate the problem?

A. (1) Elevated Refuel Floor general area dose-rates (2) Can Only be mitigated by setting the reactor vessel head

B. (1) High Airborne radiation (2) Verify reactor cavity walls are being sprayed as level is being lowered

C. (1) Foreign material introduction into the reactor (2) Re-establish the reactor cavity as an FME Zone 2

D. (1) Elevated dose rates in the Drywell (2) Restrict access to the upper levels of the Drywell

#73. Which of the following ARM indication is alarming High; would require entry into an EOP?

A. RB Trackway

B. RB 820 SBGT

C. New Fuel Storage Vault

D. Aux Bldg Vent Stack Sample 820 Aux

#74. Unit 2 is at 100% power when the following occurred: A U-2 Main Generator lockoutIAW OP-LA-103-102-1003 “STRATEGIES FOR SUCCESSFUL TRANSIENTMITIGATION” which of the following annunciators received should the crewaddress first?

A. 2H13-P603-B406 “CHANNEL A1 AND 81 CRD DISCHARGE VOLUME HIGHLEVEL”

B. 2H13-P603-B106 “Channel A1/B1 TURBINE CONTROL VALVE FASTCLOSURE”

C. 2H13-P603-B505 “Channel A1/B1 Rx Vessel Level 3 Low”

D. 1 PM02J 8308 ” Main Turbine Trip”

#75. LOA-FX-201; UNIT 2 SAFE SHUTDOWN WITH A LOSS OF OFFSITE POWERAND A FIRE IN THE CONTROL ROOM OR AEER; has been entered due to a fireand evacuation (abandonment) of the Control Room. Actions are directed todisable specific plant equipment.These directions are intended to …

A. mitigate the consequence of Hot Shorts.

B. ensures that the fire CANNOT spread to the opposite unit.

C. prevent unnecessary primary containment isolations.

D. ensures that operator action will NOT cause cooldown limits to be exceeded.

#76. Unit 1 was operating at 100% power when a Generator Load Reject event resultedin a turbine trip and reactor scram. The following were noted: RPV water level dropped to a low of -60″; and is now being raised using HPCSand Feedwater for injection. ONE control rod failed to fully insert; ALL other control rods are full in. Bypass valves failed to operate as designed. One Turbine control valve remained Open.Reactor pressure peaked at 1155 psig; and pressure is 1000 psig and loweringslowly; with one SRV currently open as a result of the event. Drywell pressure is 1.5 psig and stable.Which of the following identifies the issue that will be addressed first and. theprocedure that must be directed?The crew will address the …

A. failure of the TCVs to Close; enter LOA-EH-101 EHC ABNORMAL.

B. operation of the Open SRV; enter LOA-SRV-101 STUCK OPEN SAFETYRELIEF VALVE

C. control rod that did NOT fully insert; enter LOA-RD-101 CONTROL ROD DRIVEABNORMAL.

D. loss of core circulation; enter LOA-RR-101 REACTOR RECIRCULATIONABNORMAL.

#77. Refer To Plant Process Computer PPC Turbine DisplayU-1 was at 100% power when the Unit scrammed with the following conditions. Condenser vacuum is at 3 inches backpressure Hg and stable.What are the required actions to be directed by the Unit Supervisor?

A. Enter LOA-T0-101 Turbine Oil Abnormal; RAISE TLO temp to reduce vibrations.

B. Enter LOA-T0-101 Turbine Oil Abnormal; LOWER TLO temp to reducevibrations.

C. Enter LOA-TG-101 Turbine Generator Abnormal; FULLY Open the 1TE111;Condenser Vacuum Breaker; to Stop the Main Turbine.

D. Enter LOA-TG-101 Turbine Generator Abnormal; THROTTLE Open the 1TE111;Condenser Vacuum Breaker; to Slow down the Main Turbine.

#78. Unit 1 is operating at 100% power when the Unit NSO performing his hourly controlroom walk down identified the following abnormal system parameters: System Pressure is degrading for the Reactor Building Closed Cooling WaterSystem (RBCCW). The Reactor Water Cleanup (RWCU) System Non-Regenerative HeatExchanger discharge outlet temperature is 105F and slowly trending upward1F PER MINUTE.(1) If this trend is NOT reversed when will the high temperature isolation signal bereceived resulting in an automatic isolation of the RWCU Inlet OutboardIsolation Valve; 1 G33-F004?(2) What procedure will the Unit Supervisor direct first?

A. (1) In 35 minutes(2) LOA-RT-101 LOSS OF REACTOR WATER CLEANUP SYSTEM

B. (1) In 25 minutes(2) LOA-RT-101 LOSS OF REACTOR WATER CLEANUP SYSTEM

C. (1) In 35 minutes(2) LOA-WR-101 LOSS OF RBCCW REACTOR BUILDING CLOSED COOLINGWATER SYSTEM

D. (1) In 25 minutes(2) LOA-WR-101 LOSS OF RBCCW REACTOR BUILDING CLOSED COOLINGWATER SYSTEM

#79. Unit 1 is operating at 100% power when an Instrument Air line in the TurbineBuilding ruptures. The air compressors are unable to keep up with the loss of air and InstrumentAir pressure is lowering. The operators insert a manual scram. The STA (Shift Technical Advisor) has determined that there is NO RPVleakage.IAW OP-LA-103-102-1002 STRATEGIES FOR SUCCESSFUL TRANSIENTMITIGATION. What (1) reactor pressure and (2) reactor level should the SROdirect?

A. (1) Maintain Rx Pressure 450-650 psig with SRVs and RCIC for pressurecontrol.(2) Maintain Rx level 20″ to 50″ with MDRFP.

B. (1) Maintain Rx Pressure 800-1000 psig with SRVs and RCIC for pressurecontrol.(2) Maintain Rx level -30″ to 50″ with CD/CB control.

C. (1) Maintain Rx Pressure 450-650 psig with SRVs and RCIC for pressurecontrol.(2) Maintain Rx level -30″ to 50″ with CD/CB control.

D. (1) Maintain Rx Pressure 800-1000 psig with SRVs and RCIC for pressurecontrol.(2) Maintain Rx level 20″ to 50″ with MDRFP.

#80. Unit 2 was at 93% reactor power when the following event took place: A HIGH STEAMLINE FLOW signal has resulted in a Group 1 isolation. There was a report from the field that steam was coming from the Div 3 switchgear room. Control rods DID NOT fully insert. SBLC has been initiated. RPV water level is currently-145″ and being intentionally lowered. Low-Low Set SRVs are controlling RPV pressure.Would it be required for the US to direct installation of LGA-MS-01; “MSIV ANDMSL DRAIN RX LO-LO-LO LEVEL ISOLATION DEFEAT” and why or why not?

A. NOT REQUIRED; There are indications of a Steam Line break.

B. NOT REQUIRED; LGA-MS-01 CANNOT be performed after the MSIVs haveclosed.

C. REQUIRED; The main condenser is available and reopening of the MSIVs/MSLDrains will help stabilize RPV pressure.

D. REQUIRED; The main condenser is available and reopening of the MSIVs/MSLDrains will reduce the challenge to Primary Containment.

#81. Unit 1 was scrammed and the following conditions exist: Multiple control rods failed to insert. A blowdown has been initiated. Only Six SRVs would open. RPV Pressure is 210 psig and dropping as expected. The appropriate procedures are in progress.Based on the above information:(1) What is the next action the U-1 Control Room should perform to controlreactor water level?(2) What is the Basis for re-injecting at the procedure required ReactorPressure?

A. (1) Immediately inject using ONLY preferred ATWS systems to slowly raise levelabove-150″ on WR or -183″ on FZ.(2) To ensure adequate core cooling.

B. (1) Immediately inject using ONLY preferred ATWS systems to slowly raise levelabove-150″ on WR or -183″ on FZ.(2) To prevent inadvertent criticality.

C. (1) Wait until pressure is below 185 psig; then inject using ONLY preferred ATWSsystems to slowly raise level above -150″ on WR or -183″ on FZ.(2) To ensure adequate core cooling.

D. (1) Wait until pressure is below 185 psig; then inject using ONLY preferred ATWSsystems to slowly raise level above -150″ on WR or -183″ on FZ.(2) To prevent inadvertent criticality.

#82. Unit 1 is in a General Emergency with a loss of coolant accident and a Loss ofDivision 1 AC power.Prior to venting the primary containment to stay within the PCPL; the followingoccurred: Light Indication was lost for a VQ inboard and its associated outboard primarycontainment damper Drywell pressure started to drop quickly Multiple fire sirens are Alarming on the 815′ and 786′ Aux Building elevations Multiple Area Rad Monitors (ARMs) are Alarming on the 815′ and 786′ AuxBuilding elevations Station Vent Stack WRGM radiation readings are not available Standby Gas WRGM radiation readings are steady There are NO hostile activities in progress There are NO impediments to evacuation NO PARS have been determined for this event RPT had determined Dose Projection as <1 REM TEDE and ; <5 REM CDE forcontainment venting(1) Is a release is in progress?(2) If a release is in progress what are PAR actions?

A. (1) No release is in progress;(2) No Par Required.

B. (1) Yes a release is in progress;(2) No PAR required.

C. (1) Yes a release is in progress;(2) Shelter 2-mile radius and 5-mile downwind.

D. (1) Yes a release is in progress;(2) Evacuate 2 mile radius and 5 mile downwind.

#83. U-1 is at 100% power; with the B VP Chill Water Pump removed from service;when the following occurred: Trip of the running Primary Containment Ventilation Fan The crew was unable to restart the VP fan LGA-003 “PRIMARY CONTAINMENT CONTROL” was entered 1H13-P603 8501 Primary Containment Pressure High alarm was received The crew commenced venting per LGA-VQ-01 “CONTAINMENT VENT” 20 minutes after the start of LGA-VQ-01; the Primary Containment Pressure High alarm cleared 10 minutes later the following alarms were received 1PM13J 8501 PRIMARY CONTAINMENT CONTINUOUS AIR MONITORPANEL 1 PL75J RAD HI 1PM13J A501 ATMOSPHERE MONITORING PANEL 1PL 15J RAD HI are received 1 minute later the following alarms were received 1N62-P600-B304 STA VENT STACK WIDE RANGE RAD HI alarm 1H13-P603-B501 Primary Containment Pressure High alarm was received again What action will the Unit Supervisor direct next?

A. Secure the LGA-VQ-01 containment venting line up and perform LGP-3-2.

B. Continue venting per LGA-VQ-01 Containment Vent; the cycling of the alarm is an expected response.

C. Continue venting per LGA-VQ-01 Containment Vent; and have chemistry samplethe Primary Containment.

D. Secure the LGA-VQ-01 containment venting line up and have Chemistry sample the Primary Containment.

#84. Given the following conditions: Reactor pressure is 800 psig and stable A LOCA with an ATWS is in progress Reactor water level is 12″ and stable Drywell temperature is 345F and rising Drywell pressure is 4 psig and rising Suppression Pool temperature is 190F and stable Suppression Pool level is +1 foot RR pumps are tripped 1A and 1 B RHR pumps are running in Suppression Pool cooling Which of the following actions will be directed next to control containment temperature?

A. Start Drywell Sprays

B. Blowdown per LGA-006; ATWS BLOWDOWN

C. Open Turbine Bypass Valves; OK to exceed 100F per hour

D. Perform LGA-VP-01; PRIMARY CONTAINMENT TEMPERATURE REDUCTION

#85. Unit 1 is at 100% power:Which of the following events requires notification to a State Agency?

A. HPCS corner room with water level at the 30″ level

B. Suppression Chamber oxygen concentration discovered at 6%

C. Unidentified or pressure boundary leakage into Drywell of 5 GPM

D. Completing a plant Shutdown to mode 3 in12 hours per TS LCO 3.0.3

#86. Unit 1 is at 100% Power. LOS-RH-M1 RHR SYSTEM OPERABILITY TEST FOR MODE 1;2; and 3 for1A RHR is in progress with Engineering performing ultrasonic testing for fill andvent verification. Engineering has reported that the ultrasonic testing for the 1A RHR dischargepiping did NOT meet maximum acceptance criteria for the size of the void in thesystem piping; and normal venting methods did NOT remove the voids.What actions are required for Tech SpecsfTRM?

A. Enter 72 hour timeclock per TRM 3.7.i for system snubbers.

B. Enter 7 day timeclock per TS 3.5.1 for ECCS pump operability.

C. Enter 8 day timeclock per TS 3.3.5.1 for ECCS Instrumentation.

D. Enter 24 hour timeclock for TRM 3.3.e for ECCS Discharge Line keep filled alarminstrumentation.

#87. 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 wasreceived. Local reading was confirmed to be reading 1 psid to the left of zero; indicating aproblem with LPCS injection line. IMO was dispatched and the calibration was confirmed in tolerance for the DPswitch per LOR actions.(1) Based on the above condition a LPCS Core Spray piping leak/break may haveoccurred. ______ _(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 start a plant shutdown.

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 start a plant shutdown.

#88. What is the basis in TS 3.9.8 “RESIDUAL HEAT REMOVAL (RHR) HIGH WATERLEVEL” for the requirement for only one loop of RHR Shutdown Cooling isrequired to be Operable when the reactor cavity is flooded up and the gates areout?

A. Because the volume of water above the RPV flange provides backup decay heat removal capability.

B. Because decay heat is low enough to credit cooling capability being availablefrom CRD cooling water flow as a backup decay heat removal system.

C. Because the volume of water above the spent fuel in the fuel pool providesbackup decay heat removal capability.

D. Because decay heat is low enough to credit cooling capability being availablefrom RWCU per LOP-RT-13 RWCU LINEUP FOR HEAT REMOVAL.

#89. Unit 1 has scrammed due to a Loss of Off-Site Power. Both Div 1 and 2 DGs failed to start. HPCS DG tripped 15 minutes into the event. RCIC is maintaining level at -75″.(1) What are the required actions to keep RCIC available for injection after4 hours?(2) What procedure will the Unit Supervisor direct after 4 hours?

A. (1) Transfer to local operation in the RCIC room.(2) Operate RCIC IAW LGA-Rl-101 U-1 ALTERNATE VESSEL INJECTION USING RCIC INClUDING DEFEAT OF RCIC ISOLATIONS.

B. (1) Transfer control to Remote operation at the remote shutdown panel1C91-P001.(2) Operate RCIC IAW LOP-RX-04 STARTUP AND OPERATION OF RCICFROM THE REMOTE SHUTDOWN PANEL.

C. (1) Transfer control to Remote operation at the remote shutdown panel1C91-P001.(2) Operate RCIC IAW LGA-Rl-103 U-1 RPV INJECTION USING RCIC WHEN ALOSS OF DC IS IMMINENT OR HAS OCCURRED.

D. (1) Transfer to local operation in the RCIC room.(2) Operate RCIC IAW LGA-Rl-103 U-1 RPV INJECTION USING RCIC WHEN ALOSS OF DC IS IMMINENT OR HAS OCCURRED.

#90. Unit 2 is at 100% power when the following occurred: 2PM13J-A404 Instrument Nitrogen System Trouble R-point 0601 Southside N2 Bank Press Lo EO reports Southside bottle bank pressure is at 550 psig The EO reports that after valving in the reserve bottle; due to a loose fitting thereserve pressure is at 750 psig and steady(1) What is the status of ADS prior to bottle change out?(2) What is the status of ADS during southside bottle change out with the aboveconditions?

A. (1) Inoperable(2) Operable

B. (1) Operable(2) Operable

C. (1) Inoperable(2) Inoperable

D. (1) Operable(2) Inoperable

#91. Unit 2 is at 100% Reactor Power when the following conditions take place. IMO is performing both LIS-NB-205A/B; UNIT 2 REACTOR HIGH PRESSURESCRAM CHANNELS for all four channels. During the calibration of the second HIGH PRESSURE SCRAM CHANNEL; itstrip setting is discovered at 1061 psig.Which ONE of the following describes the Technical Specification requiredActions?

A. The channel must be placed in trip within 12 hours following the completion of the6-hour Surveillance Requirement delay period.

B. The channel must be placed in trip within the 6-hour Note 2 SurveillanceRequirement even though all of the trip unit calibrations are NOT complete.

C. Immediately exit the 6-hour Note 2 Surveillance Requirement delay period. Thechannel must be placed in trip within the next 12 hours; even though all of the tripunit calibrations are NOT complete.

D. Immediately exit the 6-hour Note 2 Surveillance Requirement delay period. Thechannel must be placed in trip within 12 hours from the start of the surveillance;even though all of the trip unit calibrations are NOT complete.

#92. Unit 1 is at 100% power:if fuse 1D18-J013-F502 were to blow;(1) What annunciator will come in first?(2) What is/are the ODCM required action(s)?

A. (1 )1 N62-P600-B207 OFF-GAS POST TREATMENT RADIATION HIGH(2) Enter ODCM 12.2.2.A RA D.1 and D.2 and D.3

B. (1) 1N62-P600-B208 “OFF GAS POST-TREATMENT RADIATION TROUBLE”(2) Enter ODCM 12.2.2.A RA C.1

C. (1) 1N62-P600-B208 “OFF GAS POST-TREATMENT RADIATION TROUBLE”(2) Enter ODCM 12.2.2.A RA D.1 and D.2 and D.3

D. (1) 1N62-P600-B207 OFF-GAS POST TREATMENT RADIATION HIGH(2) Enter ODCM 12.2.2.A RA C.1

#93. Both Units are at 100 % power. EMD has just completed and restored fromLES-FP-06 PREACTION SPRINKLER/SPRAY SYSTEMS IONIZATION SMOKEDETECTOR TEST for the U-2 cable spreading room with the following results: 14 smoke detectors passed the surveillance requirements. Current hourly fire watch for the LES-FP-06 is still in place. Fire detection outside the cable spreading room is inoperable withcompensatory actions in place.When leaving the room; they discovered the Fire Door #279 to the Cablespreading room inoperable.Identify the required compensatory actions; if any; for this situation.

A. Continue the HOURLY Fire Watch.

B. Establish a CONTINUOUS Fire Watch.

C. NONE; the HOURLY Fire Watch may be secured after the LES-FP-06 has beensigned off.

D. Stage an extra fire hose in the area AND establish a CONTINUOUS Fire Watchafter the LES-FP-06 has been signed off.

#94. IAW LFP-100-1 MASTER REFUEL PROCEDURE; in order to move fuel within theRPV; at a minimum; a Licensed Fuel Handling Supervisor (SROL) or SeniorReactor Operator (SRO) must be an active license holder …

A. directly supervising core alterations from the refuel floor.

B. directly supervising core alterations from the refuel bridge.

C. within 10 minutes of the refuel floor AND knowledgeable of the status of refuelfloor activities.

D. supervising core alterations in constant communication from the 1H13-P603while observing SRMs.

#95. The following conditions exist on Unit-1: Core alterations are in progress between the Spent Fuel Pool and the ReactorCavity The Refuel Floor Fire Siren has begun annunciating without warningWhich one of the following describes the course of action to be followed on theRefuel Floor?

A. Immediately evacuate the Refuel Floor until the cause of the alarm is resolvedand the alarm is reset.

B. Fuel movement may continue until the report of an actual fire inside the ProtectedArea is reported.

C. Suspend all fuel movement after placing the fuel assemblies in a safe condition until the fire alarm is reset.

D. Contact the Main Control Room for further information and wait for evacuationorders; fuel movement may continue unless otherwise directed.

#96. The U-1 is at 8% Reactor Power with the mode switch in START-UP.An outboard containment isolation valve that is required to be operable in MODES1; 2; and 3; FAILED its stroke time testing. To comply with the associated LCO TS3.6.1.3 Primary Containment Isolation Valves; the inoperable valve has beenclosed and deactivated.After 6 hours maintenance has been completed and Post Maintenance Testing(PMT) requires the valve to be opened and timed closed.Which of the following actions is required to perform the PMT?

A. Enter LCO 3.0.3 complete the Post Maintenance Test; then exit LCO 3.0.3.

B. Prior to entering MODE 1; enter LCO 3.0.4; perform the Post Maintenance Testthen exit LCO 3.0.4.

C. Perform the electrical stroke timing ONLY if the valve is reclosed within 4 hours tocomply with Tech Specs 3.6.1.3 Primary Containment Isolation Valves.

D. Enter LCO 3.0.5; only for time required to prove Operability without furthermaintenance; then exit LCO 3.0.5.

#97. Given the following Conditions: Reactor Mode Switch is in Shutdown. Average Reactor Coolant Temperature is 205 F. Reactor Vessel Head Closure bolt tensioning will be complete in 2 hours.The Unit is currently in (1) and the (2) __ must be completed prior to the completion of Reactor Vessel Head closure bolt tensioning.

A. (1)MODE5(2) MODE 4 Checklist

B. (1) MODE 5(2) MODE 3 Checklist

C. (1) MODE 4(2) MODE 3 Checklist

D. (1) MODE 4(2) cooldown to less than or equal to 200 degrees F.

#98. A major event has occurred on Unit-1.The following conditions exist several hours later: Drywell Pressure is 10 psig and steady. Suppression Chamber pressure is 5 psig and steady. The hydrogen recombiner is in operation for mixing. Division 1 and 2 Post-LOCA monitors indicate 7% hydrogen in the Drywell andrising slowly. Division 1 and 2 Post-LOCA monitors indicate 2% oxygen in the Drywell andrising slowly. Containment venting per LGA-VQ-02 EMERGENCY CONTAINMENT VENThas just been started IAW LGA-011 HYDROGEN CONTROL.The following sequence of events take place next: The NSO reports oxygen levels in the containment are now at 4% and steady. Then 1N62-P600-B304 STATION VENT STACK RADIATION HIGH alarms.What will the Unit Supervisor direct next?

A. Continue venting per LGA-VQ-02 EMERGENCY CONTAINMENT VENT; okay toexceed ODCM limits and Secure Recombiner IAW LGA-HG-101 OPERATION OF THE RECOMBINER AS A MIXING SYSTEM.

B. Secure venting per LGA-VQ-02 EMERGENCY CONTAINMENT VENT due toexceeding ODCM limits and Continue to run Recombiner IAW LGA-HG-101OPERATION OF THE RECOMBINER AS A MIXING SYSTEM.

C. Continue venting per LGA-VQ-02 EMERGENCY CONTAINMENT VENT, okay to exceed ODCM limits and Continue to run Recombiner IAW LGA-HG-101 OPERATION OF THE RECOMBINER AS A MIXING SYSTEM.

D. Secure venting per LGA-VQ-02 EMERGENCY CONTAINMENT VENT due toexceeding ODCM limits and Secure Recombiner IAW LGA-HG-101OPERATION OF THE RECOMBINER AS A MIXING SYSTEM.

#99. You are the SRO in the control room when the following conditions exist: 10: 10 Event occurred. 10:20 an Alert is declared.What is the Latest time by which the reports to the State and NRC must be made?

A. State 10:25 and NRC 11:10.

B. State 10:35 and NRC 11:10.

C. State 10:35 and NRC 11 :20.

D. State 10:25 and NRC 11 :20.

#100. Unit 1 has scrammed and experienced a LOCA: RPV pressure is 15 psig and going DOWN SLOWLY. The TSC is NOT Prepared to provide SAMG decisions. The NSO reports the following indicationsDoes adequate core cooling exists; and what are the required procedural actions?

A. Does Exist; Enter all LSAMGs.

B. Does NOT exist; Enter All LSAMGs

C. Does Exist; Continue with LGA-001.

D. Does NOT exist; Continue with LGA-001.

Results