LaSalle 2005 NRC - ILTandMe

#1. A differential temperature between the bottom of the RPV and the RPV flange thatis greater than 80F on LOA-RR-101; Attachment B; Monitoring of the Reactor WaterTemperature / Pressure During Loss of Both RR Pumps is indicative of…

A. inadequate natural circulation flow.

B. inadequate RT bottom head drain flow.

C. inadequate control rod cooling water flow.

D. excessive RT non-regenerative heat exchanger WR flow.

#2. Assume that AC Electrical Power is lost to the Division 1; 125 vde BatteryChargers.Continuing to operate without restoring AC Electrical Power to the Division 1; 125 vdeBattery Chargers will result in …

A. inoperability of RCIC due to loss of power to the governor electronics and several RCICinstruments.

B. inoperability of the 1A Diesel Generator due to loss of field flash and control power.

C. failure of the turbine lube oil to automatically start Emergency Bearing Oil Pump whenrequired.

D. automatic closure and isolation of many inboard primary containment isolation valves.

#3. Why will the Unit-1 reactor automatically scram as a result of simultaneous loss of111¥ and 112Y?

A. De-energizes both divisions of ARI initiation logic.

B. De-energizes both backup scram valves.

C. De-energizes control power to both TDRFPs.

D. De-energizes both divisions of isolation logic.

#4. Given the following initial conditions:- Reactor Power at 20% of RTP- Normal electrical lineup for Mode 1Considering the above initial conditions; which one of the following states the status of the eightwhite RPS Group Scram lights immediately following a Main Turbine trip when Turbine StopValve #1 sticks OPEN?

A. Top row LIT; and bottom row LIT

B. Top row OFF; and bottom row OFF

C. Top row LIT; and bottom row OFF

D. Top row OFF; and bottom row LIT

#5. Following a manual reactor scram from rated conditions; RPV water leveldecreased to -25 inches then started to recover.The RPV water level response is …

A. abnormal; the TDRFPs should respond quicker to minimize the transient.

B. normal; due to RR pumps downshifting to slow speed.

C. normal; due to void collapse causing shrink.

D. abnormal; the MDRFP should have started to minimize the transient.

#6. LGA-001 entry conditions have been met. Which one of the following conditions would require entering LGA-010?

A. one control rod is at position 04 and one at 02; all other control rods are at position 00.

B. two control rods are at position 04; all other control rods are at position 00

C. twenty-five control rods are at position 02; all other control rods are at position 00

D. one control rod is a position 48; all other contro! rods are at position 00

#7. You have been directed to transfer RHR from Suppression Pool ool Cooling toShutdown Cooling at the Remote Shutdown Panel (RSP).While performing the above task; there are NO interlocks that would prevent you from opening .1E12-F006B; Shutdown Cooling Suction if is already OPEN.|

A. 1E12-F016B; 1B RHR Upstream Drywell Spray Isolation

B. 1E12-F004B; 1B RHR Suppression Pool Suction

C. 1E12-F024B; 1B RHR Full Flow Test

D. 1E12-F027B; 1B RHR Suppression Chamber Spray

#8. The 1A Diesel Generator (DG) Cooling Water Pump tripped while the 1A DG was |running under load during surveillance testing.impact on continued 1A DG operation?|Assuming no operator action; which one of the following statements describes the expected |

A. The 1A DG governor will runback the load limiter to 10% to prevent damaging the 1A DG.

B. The pump trip will directly actuate the DG lockout which will trip the 1A DG.

C. The 1A DG will eventually trip on high cooling water temperature.

D. The 1A DG will eventually fail with possible damage due to lack of cooling.

#9. With the unit operating at near full power and the Off-Gas system in a normaloperating configuration; Instrument Air (IA) pressure to the Off-Gas system components startsto decrease and can NOT be corrected. Which one of the following describes the effect on the 2N62-F300A and 2N62-F300BCondenser Off-Gas Outlet valves as JA pressure decreases? ;

A. They will automatically CLOSE when IA pressure decreases to the closure trip setpoint.

B. They will automatically OPEN when IA pressure decreases to the opening trip setpoint.

C. They will fail CLOSED when IA pressure decreases to less than spring pressure.

D. They will fail OPEN when IA pressure decreases to less than spring pressure.

#10. The unit is operating in Mode 3 when it is discovered that 1E12-F009; Shutdown |Cooling Suction Inboard Isolation Valve will NOT open.The Unit Supervisor directs the following:- using 1A RHR to establish reactor water level +190 to +260 inches- opening 3 SRVs- throttling 1A RHR Full Flow Test valve (1E12-F024A) to maintain reactor water level in theband and a flow rate of 6500 gpm through the 1A RHR pumpFollowing the Unit Supervisor’s instructions will …

A. provide adequate flow to remove the decay heat load without damaging the SRVs.

B. cause runout and subsequent damage to the RHR system.

C. cause cavitation and subsequent damage to the 1E12-F024A.

D. provide adequate flow to remove the decay heat load but may damage the SRVs.

#11. The Fuel Pool Cooling and Cleanup (FC) system was operating with the 1A FCPump running and both Filter Demineralizers (F/Ds) were in service. The 1B FC Pump was instandby.Subsequently a large leak develops in the refueling bellows.Which one of the following correctly states the expected response assuming NO mitigatingoperator actions are taken?

A. An FC trouble alarm due to 1A FC Pump trip on low Spent Fuel Pool level and both F/DHold Pumps start.

B. Condensate Storage Tank (CST) level decreasing due to Cycled Condensate (CY)automatically aligning to maintain minimum Fuel Poo! level.

C. An FC trouble alarm due to 1A FC Pump trip on low Suction Pressure and both F/D HoldPumps start.

D. Makeup Condensate Storage Tank level decreasing due Clean Condensate (MC)automatically aligning to maintain minimum Fuel Pool level.

#12. An event occurred resulting in the following conditions:- Reactor scrammed; all control rods are full-in- HPCS; LPCS and LPCI automatically initiated- All three DGs are operating- RCIC is in standby- All plant equipment operated as designed The above response is expected when is the only initiating parameter.

A. high RPV pressure

B. low RPV level (Level-2)

C. low RPV level (Level-1)

D. high Drywell pressure

#13. Per the Technical Specification LCO; Drywell and Suppression Chamber pressure shall be maintained >-0.5 psig and in MODES 1; 2; and 3.

A. <0.60 psig

B. <0.75 psig

C. <1.00 psig

D. <1.77 psig

#14. Due to LOCA conditions in the Drywell; the following conditions exist:- Suppression Pool Temperature is 195F- Suppression Pool Level is +6 inches- Suppression Chamber Pressure is +0.5 psig- Drywell temperature is 195F- One Containment Vacuum Breaker is stuck OPENWhich one of the following would DECREASE the probability of damaging the LPCS pump ifoperated under the above conditions?

A. Starting all available Drywell Cooling per LGA-VP-01; Primary Containment TemperatureReduction.

B. Starting one loop of Drywell Spray per LGA-RH-103; Unit 1 A/B RHR Operations in theLGAs/LSAMGs.

C. Returning Suppression Pool level to within limits per LOP-RH-16; Raising and Lowering ofSuppression Pool Level.

D. Starting two loops of Suppression Pool Cooling per LGA-RH-103; Unit 1 A/B RHROperations in the LGAs/LSAMGs.

#15. A LOCA has occurred resulting in the following plant conditions:- Drywell Temperature indicates 290F- RPV Pressure indicates 50 psig- Reactor Building Temperature indicates 155F- Narrow Range Level indicates 0 inches- Wide Range Level indicates -90 inches- Upset Range Level indicates +20 inches- Shutdown Range Level indicates +20 inches- Fuel Zone Level indicates -120 inchesBased on the above conditions; which one of the following statements about RPV levelindication is true?

A. Both Fuel Zone and Wide Range instruments are usable.

B. None of the level instruments are usable.

C. Fuel Zone is the ONLY instrument that is usable.

D. Wide Range is the ONLY instrument that is usable._ Provide LGA-001 to the examinee as a handout.

#16. Given the following initial plant conditions:- Suppression Pool Level is -3 feet- Suppression Pool Temperature is 210F- Drywell Pressure is 8 psig- Suppression Chamber Pressure is 3 psigWhich one of the following would most likely cause system damage while operating the 1BRHR pump in the LPCI mode?

A. Suppression Pool Level decreases by 18 inches.

B. Drywell Pressure increases by 4 psig.

C. Suppression Pool Temperature increases by 5F.

D. Suppression Chamber Pressure decreases by 2 psig.

#17. When using the Standby Liquid Control System injection line as an alternateinjection flowpath; the NSO can monitor proper operation by observing thatrunning with discharge pressure greater than reactor pressure and SBLC squib valve continuitylights out.|

A. TWO Makeup Condensate (MC) pumps are

B. ONE Diese} Fire Pump (DFP) is

C. TWO SBLC pumps are

D. ONE SBLC pump is

#18. While operating at full power in a normal electrical lineup; an event has occurred on Unit-1 and the following conditions exist:- Both RPS Motor Generator Sets have tripped- The Rod Worth Minimizer (RWM) shows multiple control rods are NOT full-in Assuming no operator action; how would you determine if Reactor Power is above 3%?

A. Digital power level indicated on the SPDS display screen.

B. One or more Main Turbine Bypass Valves OPEN.

C. IRMs reading >75 on Range 8.

D. White APRM Downscale lights are OUT.

#19. The lowest E-Plan event classification level that REQUIRES activation of theassembly siren based on off-site release rate with no danger to on-site personnel is …

A. an Unusual Event.

B. an Alert.

C. a Site Emergency.

D. a General Emergency.

#20. The control room received a report of an electrical fire in the 1B Diesel GeneratorRoom.The fire should be classified as a (1) type fire; and the immediate hazard toconsider when entering the room ts (2) in the area.

A. (1) Class C; (2) suffocation due to CO2

B. (1) Class B; (2) suffocation due to CO2

C. (1) Class C; (2) electrical shock due to water

D. (1) Class B; (2) electrical shock due to water

#21. Which one of the following actions are taken by the control room operators; toPREVENT cold water injection during an ATWS? |

A. Rapidly lowering level to lower reactor power during an anticipated transient without scramevent.

B. Holding the hand switches for 1(2)A and 1(2)B RHR injection valves in CLOSE while RPV& ipressure decreases through the automatic open permissive setpoints. |

C. Using only systems that inject inside the core shroud during an anticipated transient withoutscram event.

D. Injecting with Alternate ATWS Systems to restore and maintain RPV level on the WideRange level instruments. UN

#22. Following a reactor water level transient on Unit-2 the following conditions exist:- Reactor automatically scrammed on low reactor water level- All control rod are full-in~— – RCIC is in standby- The Emergency Diesel Generators are in standby The following valves indicate CLOSED on both the PCIS Status CRTs and the control panels: All other PCIS valves are in their normal; expected positions based on the transient. Based on the valve positions; a spurious PCIS_________ isolation has occurred.

A. Group 2

B. Group 3

C. Group 4

D. Group 7L

#23. Unit-1 is pulling rods for a startup. The reactor is critical below the Point of AddingHeat (POAH) when the following annunciators are received:- 1H13-P603-A303; CRD Feed Pump Suction Filter DP Hi- 1H13-P603-A103; 1A CRD Feed Pump Auto Trip- 1H13-P603-A204; CRD Charging Wtr Press LoThe NSO observes CRD Charging Header pressure at 1000 psig and pressure has decreased 30psig over the last minute.Based on the above information; the NSO’s first priority is to …

A. dispatch an NLO to determine the cause of 1A CRD pump trip per LOR-1H13-P603-A102;1A CRD Feed Pmp Auto Trip. ||

B. insert a manual scram per the scram hardcard and LGP-3-2; Reactor Scram.

C. dispatch an NLO to swap CRD Suction Filters per LOP-RD-14; CRD System Pump SuctionFilter Replacement.

D. start 1B CRD pump per LOA-RD-101; Control Rod Drive Abnormal.

#24. Which one of the following would explain an increase in HCU pressure with noaccumulator trouble alarm?

A. The nitrogen side of the accumulator is leaking through the fill connection.

B. CRD Pressure Control Valve was throttled closed.

C. Charging water leaked past the accumulator seals.

D. Reactor Building Area temperatures are approaching Max Normal.

#25. Unit-1 is operating near full power with two Circulating Water (CW) Pumpsoperating. Condensate Polisher (CP) inlet temperature is 128F.Differential pressure across one of the operating traveling screens increases to 16 inches ofwater.This would cause CP inlet temperature to …

A. remain at 128F because Turbine Hood Spray would automatically initiate.

B. increase above 128F as condenser vacuum decreases.

C. remain at 128F because Total Steam Flow would NOT change.

D. decrease below 128F as condensate depression decreases.

#26. Unit-1 is operating at full power with Reactor Building Ventilation (VR) in thefollowing lineup:- 1C VR Supply Fan OFF- 1B VR Exhaust Fan OFF- Two Unit-1 VR Supply and two Unit-1 VR Exhaust Fans are running- Unit-2 VR is shutdown and no Unit-2 VR fans are runningAssuming NO operator actions are taken; how will the VR System respond to a trip of the 1AVR Exhaust Fan?

A. All running VR Supply and Exhaust Fans will trip to OFF on high building differentialpressure.

B. 1A and 1B VR Supply Fans will cycle on high reactor building differential pressure.

C. 1C VR Exhaust Fan will cycle on low reactor building differential pressure.

D. 1A VR Supply Fan will cycle on high reactor building differential pressure and 1B VRSupply Fan will continue to run.

#27. The rounds NLO reports that the Unit-2 Northwest Reactor Building corner room ~sump is overflowing due to a blown pump shaft seal in the northwest corner room.Closing the suction isolation valve on which one of the following pumps would most likelyisolate the leak?

A. Division 1 Residual Heat Removal (RHR)

B. Reactor Core Isolation Cooling (RCIC)

C. Low Pressure Core Spray (LPCS)

D. High Pressure Core Spray (HPCS)

#28. The following conditions exist on Unit-1:- 100% power; steady state- All ECCS systems are lined up for STANDB. An ECCS initiation signal occurs concurrently with Bus 142Y undervoltage.When Bus 142Y re-energizes; the (1) starts immediately and (2) startsapproximately 5-seconds later.

A. (1) 1C RHR Pump; (2) 1B RHR Pump

B. (1) LPCS Pump; (2) 1A RHR Pump

C. (1) 1B RHR Pump; (2) 1C RHR Pump

D. (1) 1A RHR Pump; (2) LPCS Pump

#29. Unit-1 has been in Cold Shutdown for 7 days following an extended run:- 1B RHR is operating in Shutdown Cooling with a stable suction temperature of 190F- 1A RHR Pump is OOS- RPV water level is +145 inches- LA RR Pump is in slow speed- 1B RR Pump is OOSWhich one of the following describes the response of the Reactor Recirculation pump suctiontemperatures 15 minutes after a trip of the 1B RHR pump (assume NO operator action)? 1A RR Pump Pump Suction Temperature | 1B RR Suction Temperature

A. Remains relatively stable | Remains relatively stable

B. Increase | Increase

C. Increase | Remains relatively stable

D. Remains relatively stable | Increase

#30. Given the following initial plant conditions:- Low Pressure Core Spray (LPCS) was running for a surveillance.- Full Flow Test Valve; 1E21-F012 was throttled to achieve rated pump discharge pressure— – Injection Valve; 1E21-F005 was closed- Minimum Flow Valve 1E21-F011 was closedSubsequently a loss of Division 1; 125 vdc occurs; followed by Drywell pressure increasing to2.0 psig.Assuming no operator actions have been taken; what is the final status of the following LPCScomponents?! Full Flow Test Minimum Flow |Valve 1E21-F012 Valve 1E21-F011!: I

A. Closed Open

B. Throttled Closed

C. Closed Closed

D. Throttled Open

#31. The Reactor Core Isolation Cooling (RCIC) system is running for a surveillance inthe Condensate Storage Tank (CST) to CST test mode when a vehicle drives into the side of the |CST leaving only 2 feet of water in the tank. Suppression Pool (SP) level is normal.The RCIC turbine will continue to mun…|

A. in the CST to CST test mode.|

B. however the RCIC minimum flow valve will automatically open.

C. however RCIC will re-align to the SP to SP test mode.

D. however RCIC will re-align and pump the SP to the CST.

#32. DEGRADATION of the HPCS Water Leg pump will …

A. increase the probability of water hammer.

B. degrade HPCS Pump seal cooling flow.|

C. decrease the HPCS Pump suction pressure. |||

D. reduce the response time for HPCS injection. |

#33. An event has occurred on Unit-1 resulting in the following conditions:- Drywell pressure has increased to 1.0 psig- All ECCS pumps have automatically startedSubsequently RPV level reached +66 inches and then decreased to -10 inches.Which one of the following actions would cause the HPCS system to inject water into the RPV? ‘

A. Tum the injection valve handswitch to OPEN and THEN turn the minimum flow valve handswitch to CLOSE.

B. Depress the HPCS High Water Level reset pushbutton; then turn the injection valvehandswitch to OPEN.

C. Depress the HPCS High Drywell Pressure reset pushbutton; then tun the injection valvehandswitch to OPEN.

D. Arm and depress the HPCS System Manual Initiation pushbutton.

#34. During an ATWS; the NSO started the 1A Standby Liquid Control (SBLC) systemper the Scram Hardcard and verified proper operation of SBLC. After pumping 1000 gallons of boron solution; Bus 141Y tripped on overcurrent.Which one of the following actions should the NSO take; and why?

A. Verify both SBLC system handswitches are in STOP per LGA-010; Failure to Scrambecause cold shutdown boron has injected.

B. Inject boron using 1B SBLC system per LGA-SC-101; Initiation of Standby Liquid Control;because the 1A SBLC pump is lost.

C. Insert rods per LGA-NB-01; Alternate Rod Insertion; because neither SBLC system isavailable.

D. Lineup and inject boron per LGA-RT-103; Alternate Boron Injection Using RWCU; becauseneither SBLC system is available.

#35. Unit-1 was operating at 25% RTP with the 1B21-F028A; Main Steam IsolationValve closed. Subsequently MSIV 1B21-F022C spuriously closed .Based on the above MSIV closures; RPS relays in …

A. both channels should have de-energized causing a full scram.

B. both channels should remain energized.

C. Channel Al should have de-energized causing a 1/2 scram.

D. Channel B1 should have de-energized causing a 1/2 scram.

#36. Unit-1 is performing a startup. The reactor is critical below the point of adding heat. Using the figure below; which one of the following lights are expected to be lit for theconditions provided?

A. BOTH Upscale Alarm AND Upscale High

B. Inop ONLY

C. BOTH Inop AND Upscale Alarm

D. Upscale Alarm ONLY

#37. During a reactor startup; the NSO can more closely monitor the SRMs by …

A. selecting the SPDS computer screen.

B. change the indicating range.

C. changing the recorder chart speed.

D. adjusting the discriminator voltage.

#38. As the Local Power Range Monitor (LPRM) detectors age; the output of theAverage Power Range Monitors (APRMs) will .[Assume initial APRM Gain Adjustment Factors (AGAFs) were equal to 1.00 and actual powerremains the same as the LPRM ages.]

A. INCREASE and the AGAFs will be LESS than 1.00

B. DECREASE and the AGAFs will be GREATER than 1.00

C. DECREASE and the AGAFs will be LESS than 1.00

D. INCREASE and the AGAFs will be GREATER than 1.00

#39. Unit-1 is operating at 15% RTP following a reactor startup. During performance ofthe control room rounds; it is discovered that the AMBER light for the LPRM labeled 5D-40-25is lit on back panel 1H13-P608. Which one of the following would cause the above indication?

A. The output signal from the LPRM reading zero.

B. The LPRM mode switch in the B (bypass) position.

C. The LPRM mode switch in the C (calibrate) position.

D. The output signal from the LPRM reading upscale.

#40. How would a loss of 250 vde bus 121Y affect the Reactor Core Isolation Cooling(RCIC) system?RCIC (1) automatically start following an automatic initiation signal; and(2) automatically isolate following a PCIS high RCIC room temperatureisolation signal.

A. (1) would (2) would

B. (1) would NOT (2) would NOT

C. (1) would NOT; (2) would

D. (1) would (2) would NOT

#41. An event has occurred on Unit-1 resulting in the following conditions:- Bus 112Y is de-energized- Division 1 ADS High Drywell pressure transmitters are inoperable and transmitting 0 psig- Actual Drywell pressure is 2.0 psig- RPV pressure is approximately 450 psig and steadyRPV Level has just reached the Level-1 setpoint.Low pressure ECCS systems will start to inject …

A. inless than 1 minute.

B. in 9 to 10 minutes.

C. in 2 to 3 minutes.

D. in 11 to 12 minutes.

#42. LGA entry conditions exist on Unit-1 with the following conditions:- reactor pressure = 790 psig- Drywell pressure = 5 psig- Bus 111Y is de-energized. After depressing all four ADS Manual Initiation pushbuttons; you take the following SRV Tailpipe temperature readings from the appropriate back panel recorders:Based on the above tailpipe temperatures; how many ADS valves are open?

A. 7 ADS valves are open.

B. 6 ADS valves are open.

C. 5 ADS valves are open.

D. 4 ADS valves are open.

#43. While operating at 100%; level indicating switch 1B21-N704C which supports -PCIS Group 2 and 3; has failed downscale. This particular switch is powered from RPS A.Subsequently a leak in the Drywell has resulted in RPV level dropping to -100 inches. Levelthen returned to the normal control band. Based on the above event; PCIS Group 2 and 3 valves willisolate.

A. NEITHER Inboard NOR Outboard

B. ONLY the Outboard

C. ONLY the Inboard

D. BOTH Inboard AND Outboard)

#44. Which one of the following would be an indication that an SRV tail pipe hast|sheared at the T-quencher and the T-quencher is no longer performing as designed?

A. Greater than normal localized heating at the SRV tail pipe discharge.

B. Containment Vacuum breaker cycles each time the SRV opens.

C. Greater than normal SRV tail pipe temperature each time the SRV opens.

D. Large spike in Drywell pressure each time the SRV opens.

#45. Unit-1 is at 100% power with both TDRFPs in 3-element contro]. The level setpointis set at +36 inches.A fuse blows de-energizing 1A Narrow Range (NR) Level transmitter; 1C34-N004A.Assuming NO operator action; the reactor …

A. will scram because the main turbine will trip on high level.

B. will NOT scram because the RWLC System will ignore the 1A NR level indication.

C. will scram because level will decrease to the low level scram setpoint.

D. will NOT scram but power will be reduced due to an automatic RR Pump downshift.

#46. Standby Gas Treatment (VG) is being used to vent the containment. Drywellpressure is 1.4 psig and steady when the VG Train Flow Transmitter fails to 5000 cfm.Based on the VG train automatic response to this failure; Drywell pressure will …

A. decrease because the VG Flow will stabilize at 5000 cfm.

B. increase because the VG Flow Control Damper will close.

C. increase because the VG Primary Fan will trip.

D. remain constant and VG Flow will remain at 4000 cfm.

#47. Standby Gas Treatment (VG) has automatically initiated. Ten minutes later theNSO recognizes that the VG Outlet Isolation Damper (1 VG003) indicates intermediate.Which one of the following would confirm to the NSO that the 1VG003 is NOT full open?

A. Reactor Building differential pressure is -0.5 inches H20.

B. The VG Flow Control Damper; 1 VG002 indicates intermediate.

C. VG Train Flow indicates 4000 cfm.

D. The electric heater is de-energized.

#48. Unit-1 is shutdown with the UAT unavailable. Unit-2 is in a normal full powerelectrical lineup.Subsequently a spurious trip of the SAT Feed to 141 Y (breaker 1412) occurred.The 0 DG is running loaded with the following breaker lineup per the AC Power Abnormalprocedure LOA-AP-101:- SAT is available and carrying 142X; 142Y; and 143- ACB 1411; UAT Feed to 141X is OPEN (and NOT available)- ACB 1412; SAT Feed to 141 Y is OPEN (and NOT available)- ACB 1413; 0 DG Output is CLOSED- ACB 1414; Unit Tie Breaker is OPEN (and available)- ACB 1415; 141X/Y Tie Breaker is CLOSEDWhile operating in the above lineup; an ECCS initiation signal is received on Unit-1.The operator should expect (1) and then enter the appropriate section of :LOA-AP-101; Unit-1 AC Power System Abnormal; to (2)

A. (1) ACB 1415 to OPEN; de-energizing bus 141X and ACB 1413 to REMAIN CLOSED;(2) RE-ENERGIZE 141X if Service Water pumps are required to supply fire protection.

B. (1) ACBs 1413 and 1415 to REMAIN CLOSED; there is NO undervoltage on Unit-2;(2) VERIFY all electrical buses are energized and the 0 DG is NOT overloaded

C. (1) ACBs 1413 and 1415 to OPEN; and then 1413 to RECLOSE on undervoltage;(2) RE-ENERGIZE 141X if Service Water pumps are required to supply fire protection.

D. (1) ACB 1413 to OPEN and ACB 1414 to CLOSE; fast transferring to the Unit -2 SAT;(2) VERIFY all electrical buses are energized and return the 0 DG to Standby

#49. Which one of the following would indicate that the Plant Process Computer (PPC) |Uninterruptible Power Supply (UPS) should have automatically transferred to the AlternateSource?

A. INVERTER FAILURE light is ON

B. 250 vdc battery supply voltage reads zero

C. SYNC FAILURE light is ON :

D. Static Bypass Switch INVERTER light is ON :

#50. A loss of ALL 125 vde Battery Chargers has occurred on Unit-1.Assume equal loads of 25 amperes are being supplied by each battery; which one of thefollowing lists the expected relationship between the Unit-1 battery voltages after 2 hours?

A. Division 1; 2 and 3 battery voltages approximately equal.

B. Division 2 and 3 battery voltage approximately equal and greater than Division 1.

C. Division 1 and 2 battery voltage approximately equal and greater than Division 3.

D. Division 1 and 3 battery voltage approximately equal and greater than Division 2. 2003-01 ILT NRC Exam; Version: 5

#51. You have been directed by the Unit Supervisor to place the 1B DGMaintenance-Auto Transfer Switch in the MAINT position.Where is the switch located?

A. In the 1B DG Room on Local Contro! Panel (1E22-P301B).

B. In 143 Switchgear room in the auxiliary compartment above the 1B DG Output Breaker.

C. In the Main control room on panel 1H13-P601.

D. Inthe 1B DG Room next to the 1B DG Governor.

#52. With Unit-1 operating at full power; a spurious PCIS Group 10 isolation occurred.During the recovery; the NLO reports that the IN Rupture Disc; LIN22M has ruptured and needsto be replaced.Based on the above event; which one of the following describes the minimum actions requiredto ensure the Inboard MSIVs will remain open during the replacement of 1IN22M?NOTE:1) 1IN059 – DW Nitrogen Inst Air Downstream Stop Valve2) 1IN060 – DW Nitrogen Inst Air Upstream Stop Valve3) 1INO17 – DW Inst N2 Regulated Hdr Drywell Supply Valve

A. START 1A IN Compressor and OPEN 1IN0O17 ONLY

B. OPEN valve 1IN017 ONLY

C. OPEN valves 1INO59 and 1IN060 ONLY

D. OPEN vaives 1IN059; 1IN060; and HINO17

#53. Loss of bus 241Y will render inoperable due to loss of power.

A. both 0 and 2B RBCCW Pumps

B. ONLY the 2B RBCCW Pump

C. ONLY the 2A RBCCW Pump

D. both 2A and 2B RBCCW Pumps

#54. Unit-1 is operating at 60% reactor power on a 80% Flow Control Line.A control rod is being positioned from position 10 to 08. While settling; it is discovered that acomplete failure of the collet fingers has occurred.Based on the above failure and NO operator action; total core flow will …

A. decrease due to an increase in two-phase flow resistance.

B. increase due to a decrease reactor recirculation ratio.

C. remain constant since rod position does NOT affect total core flow.

D. increase due to a decrease in two-phase flow resistance.

#55. A rod position being displayed in magenta on the RWM indicates that …

A. that control rod has a substituted value.

B. only that control rod can be withdrawn.

C. only that control rod can be inserted.

D. that control rod is electrically out of service.

#56. A seal failure on the 1A Reactor Recirculation (RR) pump develops while operatingin Mode 1 with power <25%. This causes the following:- Drywell pressure increases to 2.0 psig- 1A RR pump trips on overcurrent- Narrow Range level indication remains on-scale during the eventWhich one of the following correctly states the expected loop flow controller indications for theRR Flow Control Valves (FC Vs) following the event?1A RR-FCV 1B RR-FCVPosition Position

A. 15% open Full-open

B. Full-open 15% open

C. Full-open Full-open

D. 15% open 15% open

#57. Following a reactor scram from full power; when the RWM Scram Mode isenabled; IF multiple rods are at unknown positions due to Rod Position Information System(RPIS) failures; and all other control rods indicate full-in; the box will say …

A. ROD UNKNOWN in a yellow box

B. ROD OUT in a red box

C. ROD OUT ina yellow box

D. ROD UNKNOWN in a red box[oe a. _ _. a

#58. The Unit-1 is at 100% power.An NLO reports that an RPV Instrument Line is cracked and is slowly venting to the Unit-1Reactor Building atmosphere.The NSO scanned RPV pressure and RPV level instruments associated with the crackedinstrument line.Which one of the following sets of readings would indicate that the leak is associated with aninstrument reference leg?Indicated IndicatedRPV Pressure: RPV Level:

A. 980 psig 40 inches

B. 1019 psig 34 inches

C. 960 psig 32 inches

D. 1015 psig 39 inches

#59. Unit-2; Division 2 RHR is running in Suppression Pool Cooling with flowestablished at 5000 gpm. 2E12-F048B; RHR Heat Exchanger Bypass and 2E12-F003B; RHRHeat Exchanger Outlet valves have been adjusted to mid-position in order to establish therequired cooldown rate. The Suppression Pool cooldown rate has NOT required adjustment forapproximately 1 hour.Subsequently a short causes the 2E12-F048B valve to travel to the full CLOSED position.As a result of the above event; the Suppression Pool cooldown rate will (1)and the NSO must throttle the 2E12-F003B; RHR Heat Exchanger Outlet valve in the(2) direction in order to re-establish the previous cooldown rate.

A. (1) increase; (2) CLOSED;

B. (1) decrease; (2) OPEN

C. (1) increase; (2) OPEN

D. (1) decrease; (2) CLOSED

#60. Under which one of the following conditions would you expect the SuppressionChamber-to-Drywell Vacuum Breakers to remain CLOSED?

A. Isolating the steam leak following a LOCA.

B. Initiation of Suppression Chamber Spray during a LOCA.

C. Initiation of Drywell Spray during a LOCA.

D. Opening an SRV with a tail pipe broken in the Suppression Chamber air space.

#61. Unit-1 is operating in Mode 1. After receiving annunciator 1H13-P603-A508; 1A RPS MG Set Trouble; the following valvesindicate OPEN in the main control room:- 1E51-F086; RCIC Turbine Exhaust Vacuum Breaker Upstream Isolation Valve- 1B21-F019; MSIV Drain Header Outboard Stop Valve- 1CM022A; 1A Post LOCA H2/02 Monitor Drywell Suction Valve- 1WR040; RBCCW Return Header Outboard Isolation ValveWhich one of the listed valves is NOT in its expected position?

A. 1B21-F019

B. 1WRO040

C. 1E51-F086

D. 1CM022A

#62. An LGA event occurred on Unit-!:- the reactor scrammed following a trip of both TDRFPs- MSIVs automatically closed on low level— – RCIC is out of service for emergent maintenance- All control rods are full-in- Bus 152 tripped on overcurrent- HPCS has tripped on overcurrent- RPV level is -130 inches on WR and decreasing consistent with decay heat loadBased on the above conditions; which one of the following level control strategies would beappropriate?

A. Lineup but don’t start Alternate Injection Systems; wait until level is below -150 inches then 2start and control level with Alternate Injection Systems.

B. Start the Motor Driven Reactor Feed Pump; then control level using the FRVs.

C. Reduce RPV pressure using Safety Relief Valves; then control level using the CondensatePumps and the FRVs.

D. Initiate ADS per the LGAs; then control level with low pressure ECCS systems.

#63. Which one of the following tank levels will increase as a result of the Unit-1Drywell Equipment Drain Sump (1 REO2) pumping down?

A. Reactor Building Equipment Drain Tank (1REOIT)

B. Chem Waste Collector Tank (1 WZ01T)

C. Waste Surge Tank (1 WE02T)

D. Waste Collector Tank (1 WEOIT)

#64. All of the following will result in Reactor Building Differential Pressure becomingLESS negative; EXCEPT?1|

A. Loss of air to the VR Exhaust Differential Pressure Control dampers 1 VRO7YA/B/C/D.

B. Trip of the running Station Heat Recovery Pump.

C. Trip of the operating VR Blast Coils.

D. Loss of air to VR Supply Flow Control Damper 1 VRO6Y.

#65. Reactor Pressure Vessel Internal design provides for installation of Core Orifices inthe …|

A. Lower Fuel Tie Plate.

B. Baffle Plate.

C. Core Bottom Plate.

D. Fuel Support Pieces.

#66. A licensed operator worked on the following safety related hours during aseven-day period: All work periods began at 08:00 on each work day. Upon review; it was determined that thisemployee exceeded the overtime guidelines stated in LS-AA-119; Overtime Controls.When did the employee exceed the overtime guidelines?

A. Both Wednesday and Saturday

B. Saturday ONLY

C. Sunday ONLY

D. Both Saturday and Sunday

#67. Unit-1 and Unit-2 are both operating in Mode 1 with no equipment out of service. Avalving error caused Fire Protection Header Pressure to drop to 116 psig for 30 seconds.Based on the above event; the control room NSOs should verify proper operation of the DieselFire Pumps (DFPs) by observing on…

A. 1PMO9J that OA DFP red light is lit and on 2PM09J that OB DFP green light is lit.

B. 1PMO09J that 0A DFP red light is lit and on 2PMO09J that OB DFP red light is lit.

C. 1PMO09J that 0A DFP red light is lit and OB DFP green light is lit.

D. 1PM09J that both 0A and OB DFP red lights are lit.

#68. Which one of the following is considered a formal Temporary ConfigurationChange that would require an entry in the Operations Temporary Change Tracking Log asdescribed in CC-AA-112; Temporary Configuration Changes?

A. A temporary strip chart recorder connected to read the points normally monitored by aporary p yrecorder that has failed.

B. A temporary pressure gauge installed on an engineered test point being used fortroubleshooting. |

C. Removal of RHR Pump motor control power fuses as part of a Clearance Order to allowrepair of the pump motor.

D. A charging hose with a pressure gauge attached being used to charge an HCU accumulatorper LOP-RD-20.

#69. Refer to the ACTIONs Table provided in Technical Specification Example 1.3-6below to answer the following question. One channel is declared inoperable at 08:00 on June 1. The designated SurveillanceRequirement (SR 3.x.x.x) is completed at 12:00 on June 1.Including any extensions permitted by Technical Specifications; which one of the followingdescribes the LATEST time and date to perform the Surveillance next without requiring entryinto Condition B?

A. 20:00 on June 1

B. 22:00 on June 1

C. 00:00 on June 2

D. 02:00 on June 2

#70. Who maintains the master copy of the Nuclear Component Transfer List (NCTL)and is responsible for signing off the completed NCTL sheets while performing componentmovements within the Unit-2 reactor or spent fuel storage pool.

A. Refuel Hoist Operator

B. Fuel Handling Supervisor

C. Unit-2 Unit Supervisor

D. Unit-2 NSO

#71. You are a 25 year old Occupational Radiation Worker and have NOT exceeded anylegal or administrative exposure limits through the year 2003.In 2004 you received 3.0 Rem of Routine Exposure and 4.0 Rem of authorized Planned SpecialExposure (PSE).What is your 10 CFR 20 NRC Exposure Limit; for Routine Occupational Radiation Work; |during the year 2005?

A. 0.0 rem

B. 1.0 rem

C. 3.0 rem

D. 5.0 rem

#72. The Station Emergency Director is assigned the non-delegable responsibilityfor authorizing personnel exposure under emergency conditions recommended NOT toexceed Rem TEDE for protecting valuable property.

A. 10

B. 15

C. 20

D. 25

#73. Per HU-AA-101; Human Performance Tools and Verification Practices; which oneof the following correctly states the philosophy to be applied while performing IndependentVerification (IV) of safety related valves located in the Outboard MSIV Room while operatingin Mode 1? |

A. Request that the Shift Manager waive the IV due to the low frequency of personnel traffic inthe areas and complete the IV for the rest of the checklist. .

B. Request that the WEC SRO waive the IV due to the low frequency of personnel traffic in the |areas and complete the IV for the rest of the checklist.

C. Request that the Shift Manager waive the IV for these valves to reduce personnel exposureand complete the IV for the rest of the checklist.

D. Perform the IV after receiving High Radiation and ALARA briefs from the WEC SRO.

#74. During a ATWS with power greater than 3%; which one of the following actionscan the panel operators take without Unit Supervisor direction?

A. Initiate Standby Liquid Control

B. Trip RR pumps

C. Inhibit ADS

D. Prevent injection from ECCS

#75. LOA-RX-101; Unit-1 Control Room Evacuation Abnormal 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 areleft open until recovery to (2)i

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

B. (1) RPS Distribution Panel(2) ensure against inadvertent isolation reset and valve opening caused by shorts

C. (1) RPS MG Sets(2) ensure against inadvertent isolation reset and valve opening caused by shorts

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

#76. A breaker trip event occurred on Unit-2; some of the equipment de-energized islisted below:- 2A Diesel Cooling Water Pump- 2C and 2D RHR Service Water Pump- 2B Fuel Pool Emergency Makeup Pump- 2B Primary Containment Vent Fan- 2B Primary Containment ChillerTechnical Specification 3.6.3.1 (Primary Containment Hydrogen Recombiner) is not being metbecause (1) Hydrogen Recombiner is OPERABLE for Unit-2; and the UnitSupervisor should direct actions to recover power per LOA-AP-201; Unit-2 AC Power SystemAbnormal for (2)

A. (1) ONLY Unit-1 (2) Loss of Bus 235X/Y;

B. (1) neither (2) Loss of Bus 236X/Y;

C. (1) ONLY Unit-1 (2) Loss of Bus 236X/Y;

D. (1) neither (2) Loss of Bus 235X/Y;

#77. While operating at full power with the RCIC turbine running at 600 gpm for asurveillance; an event occurred on Unit-1. ;The NSO observed the following indications as a direct result of the event:- RCIC turbine tripped on overspeed but no trip alarm was received- Division 1 Post LOCA monitor automatically started- All SRV OPEN and CLOSED position indicating lights are out- PCIS Group 4 outboard valves automatically closedAs the Unit Supervisor; your FIRST priority is to direct the NSO to enter …

A. LOA-PC-101; Primary/Secondary Containment Trouble due to a Group 2 isolation.

B. LOA-PC-101; Primary/Secondary Containment Trouble due to a Group 4 isolation.

C. LOA-DC-101; Unit 1 DC Power System Failure due to loss of 112Y.

D. LOA-DC-101; Unit DC Power System Failure due to loss of 111 Y.

#78. The Remote Shutdown Monitoring System LCO provides for operability ofinstrumentation that is required for all of the following EXCEPT?

A. RPV pressure control using SRVs

B. RPV inventory control using RCIC

C. Decay heat removal using Shutdown Cooling

D. Containment control using Drywell Spray

#79. Unit-1 is in Mode 4 with reactor coolant temperature at 190F. The |operating loop of Shutdown Cooling trips and can NOT be restarted. Both Reactor |Recirculation pumps are out of service and Reactor Water Cleanup (RWCU) is isolated. |It has been determined that it will take 2 hours to align and start the standby Shutdown |||Cooling loop.As the Shift Manager you should …

A. authorize raising RPV level to between 50 and 60 inches in order to provide the extra NetPositive Suction Head (NPSH) needed to start the standby Shutdown Cooling pump whencoolant temperature is above 180F.

B. authorize raising RPV level to between 220 and 260 inches in order to more accuratelydetermine vessel metal temperatures and demonstrate that stratification is NOT occurring. |

C. authorize raising RPV level to between 220 and 260 inches in order to increase the watervolume available for removal of decay heat which increases heat transfer rate to thecontainment atmosphere.

D. direct maintaining RPV level between 30 and 40 inches in order to increase the Time to Boil |allowing extra time to start the standby Shutdown Cooling loop. |

#80. An event occurs on Unit-2 that results in the following alarms:~ 2H13-P601-E306; Fuel Pool Vent Rad Hi- 1H13-P601-E306; Fuel Pool Vent Rad Hi- 2H13-P601-F205; Div 1 Fuel Pool Rad Hi-HiAn Extra NSO verified that Fuel Pool Monitors 2A and 2B have tripped.The crew should be directed to enter (1) to verify isolations are complete toprevent (2)

A. (1) both Unit-1 and Unit-2 LGAs;(2) off-site doses from exceeding 10 CFR limits

B. (1) only the Unit-2 LGA;(2) over exposure of personnel on the refuel floor

C. (1) both Unit-1 and Unit-2 LGAs;(2) over exposure of personnel on the refuel floor

D. (1) only the Unit-2 LGA;(2) off-site doses from exceeding 10 CFR limits

#81. Unit-1 was manually scrammed due to a small leak in the primary containment. The |following conditions exist:- Drywell pressure is 2.0 psig and slowly rising- Drywell temperature is 215F and slowly rising|||Which one of the following identifies whether LGA-VP-01; Primary Containment TemperatureReduction can be used to reduce Drywell temperature and the basis for that decision?

A. No; because neither LGA-001; RPV Control nor LGA-003; Primary Containment Controlhave entry conditions that are met.

B. No; because even though LGA-003; Primary Containment Control has entry conditions that |are met; Drywell temperature is greater than 212F with a LOCA in the containment. |

C. Yes; because LGA-001; RPV Control and LGA-003; Primary Containment Control bothhave LOCA entry conditions that are met.

D. Yes; because LGA-003; Primary Containment Control has entry conditions met; andtemperature in the drywell is greater than 135F. |

#82. An ATWS event has occurred on Unit-1.- Drywell pressure is +0.5 psig- A PCIS Group 1 Isolation has occurred- One SRV was open and maintaining reactor pressure in LLSYou are maintaining RPV level per the level band prescribed by step 9 of LGA-010 when the;Unit NSO reports that at -100 inches on the Wide Range the SRV went closed. Reactor pressure |is approximately 900 psig and steady.As the Unit Supervisor; you should …

A. exit level band 9 and control level per level band 8 because power is still ABOVE 3%.

B. continue to control level in the currently prescribed level band because power is stillABOVE 3%.

C. exit level band 9 and control level per level band 7 because power has decreasedBELOW 3%;

D. continue to control level in the currently prescribed level band even though power hasdecreased BELOW 3%.

#83. Unit-2 was operating in Mode 2. RWCU Reject to the Main Condenser is beingused to control RPV level per LOP-RT-09; RWCU Sytem – Coolant Rejection.- RPV Water Level was +34 inches and steadyThe NSO made an adjustment to the blowdown flow rate; and 20 minutes later the RPV LowWater Level alarm (Level-4) was received.Based on the above information; the NSO increased the reject flow rate by approximately(1) and the Unit Supervisor should then direct the NSO to restore RPV levelto the band directed by (2)

A. (1) 50 gallons per minute;(2) LOP-RL-01; Operation of the Reactor Water Level Control System

B. (1) 25 gallons per minute;(2) LGP-1-1 Normal Unit Startup

C. (1) 25 gallons per minute;(2) LOP-RL-01; Operation of the Reactor Water Level Control System

D. (1) 50 gallons per minute;(2) LGP-1-1 Normal Unit Startup

#84. During a reactor pressure transient; 4 Safety Relief Valves (SRVs) automaticallyopened when RPV pressure reached 1090 psig. All other SRVs have remained closed during the |transient. Which one of the following correctly states the status of the SRVs and the actions that should bedirected by the Unit Supervisor?

A. Four SRYs have opened before their relief setpoint; close the SRVs per LOA-SRV-101;Stuck Open Safety Relief Vales.

B. All thirteen SRVs have functioned as designed; control pressure below 1059 psig perLGA-001; RPV Control.

C. Two SRVs have failed to open at their relief setpoint; control pressure below 1059 psig perLGA-001; RPV Control.

D. One SRV has opened before its relief setpoint; close the SRV per LOA-SRV-101; StuckOpen Safety Relief Valve.

#85. Following an event on Unit-1; the control room operators gather the followinginformation:- RB RCIC Room Area Radiation Monitor is pegged high- RB North HCU Area Radiation Monitor is pegged high- SBGT Area Radiation Monitor is reading 100 mrem/hr- RCIC has received an isolation signal however the isolation valves have failed to close- Unit-1 continues to operate in MODE 1The above conditions require a (1) because two (2) valuesfor the same parameter have been exceeded.

A. (1) manual scram (LGP-3-2) and blowdown (LGA-004 or LGA-006);(2) Max Safe

B. (1) unit shutdown (LGP-2-1);(2) Max Normal

C. (1) manual scram (LGP-3-2) and blowdown (LGA-004 or LGA-006);(2) Max Normal

D. (1) unit shutdown (LGP-2-1);(2) Max Safe

#86. A transient has occurred on Unit-1 resulting in the following conditions:- 142Y is de-energized- RPV pressure is 290 psig and slowly decreasing- RPV level is -30 inches and rising at 50 inches per minuteSubsequently; annunciator 1PMO01J-A313 Feed to 135X/Y 133 Auto Trip (SER R-point R0O218Bus 141Y Fd Bkr to 135X/Y A-Trip) is received.Based on the above conditions; the Unit Supervisor should direct action to …

A. trip the LPCS pump and locally close the LPCS Injection valve per LOP-AA-04; Operationof valves.

B. locally close the LPCS Injection valve per LOP-AA-04; Operation of Valves; but leave theLPCS Pump running until plant conditions are stabilized.

C. return the LPCS system to standby when level is above the scram setpoint per LOP-LP-03;Shutdown of LPCS After an Automatic Initiation.

D. return the LPCS system to standby when level is above the LPCS initiation setpoint perLOP-LP-03; Shutdown of LPCS After an Automatic Initiation.

#87. Unit-2 was operating at full rated conditions when an event occurred requiring amanual scram:1) The NSO armed and depressed all manual scram pushbuttons2) All group scram lights remained lit and control rods did NOT move3) The NSO manually initiated both divisions of ARI4) All control rods fully inserted following ARI initiationBased on the above event; (1) and therefore; (2) arerequired to be notified per Nuclear Accident Reporting System (NARS)

A. (1) NONE of the EALs are applicable;(2) NO outside agencies

B. (1) EAL MA3 is the highest applicable EAL;(2) ONLY Illinois EMA and REAC

C. (1) EAL MS3 is the highest applicable EAL;(2) Illinois EMA and REAC; the local county Sheriff and EMA; and LaSalle County ESDA|

D. (1) EAL MS3 is the highest applicable EAL;(2) ONLY Illinois EMA and REAC

#88. Several hours after an automatic initiation during a LOCA; and with the initiationsignal still present; the Unit-1 Standby Gas Treatment Primary Fan trips.After the trip; the Unit-1 Assist NSO observed the following at panel 1PM07J:- SBGT Primary Fan – OFF- SBGT Cooling Fan – OFF- SBGT Heater – OFF- SBGT Flow – 0 scfm- 1VG001; SBGT Inlet Isolation damper – CLOSED- 1¥VG003; SBGT Outlet Isolation damper – OPENThe SBGT train (1) to the Primary Fan trip and the Unit Supervisor shoulddirect the operator to (2) .

A. (1) responded as expected;(2) SHUTDOWN the SBGT train per LOP-VG-02; Shutdown of the SBGT System

B. (1) responded as expected;(2) START the standby SBGT per LGA-VG-101; Secondary Containment PressureControl

C. (1) did NOT respond correctly;(2) manually START the Cooling Fan per LOR-1PM07J-A502; SBGT Pri Fan AutoTrip

D. (1) did NOT respond correctly; /(2) CLOSE the Outlet Isolation damper per LOR-1PM07J-A502; SBGT Pri Fan AutoTrip

#89. Unit-1 is being shutdown for emergent maintenance. The Shutdown CoolingIsolation Interlocks have just cleared and Main Turbine Bypass valves are being used tocontro! reactor pressure.While troubleshooting ADS Accmulator alarms; the FIN Team reports that the ADSAccumulator Supply header pressures are reading 145 psig.Based on the above information; which one of the following is appropriate for the UnitSupervisor?

A. Direct actions per annunciator procedures ONLY because ECCS subsystems are capable ofproviding flow into the RPV.

B. Direct actions per the IN abnormal procedure AND take actions per TS 3.5.1 required actionG.1 AND G.2 because ADS does not meet the single failure criteria used in the accidentanalysis.

C. Direct actions per the IN abnormal procedure AND take actions per TS 3.5.1 required actionG.2 ONLY because low pressure ECCS subsystems are currently incapable of providingflow into the RPV.

D. Direct actions per annunciator procedures AND take actions per TS 3.5.1 required action F.1 |ONLY because even though portions of ADS are inoperable; ADS still meets the singlefailure criteria used in the accident analysis.

#90. Unit-1 is operating at full power and Unit-2 is in an extended maintenance outage.The Ice Melt Line was just taken out of service to support emergent maintenance activities onthe Unit-2 Circulating Water Piping. Maintenance is expected to last another 4 days.The following conditions exit:- Circulating Water Inlet temperature is 55F- Outside Air Temperature is 10F and forecasted to drop over the coming week- The 0A Service Water Jockey Pump is the only Service Water Pump running- Service Water Pressure is 107 psigOver the next week; Service Water pressure is expected to (1) ; and the UnitSupervisor should direct system pressure be controlled by (2)

A. (1) decrease;(2) isolating unnecessary Service Water loads per LOA-WS-101; Service WaterSystem Abnormal.

B. (1) decrease;(2) start an additional Service Water Pump per LOP-WS-02; Service Water Pump andService Water Jockey Pump Startup and Operation.

C. (1) increase;(2) throttling flow through an idle RBCCW Heat Exchanger Outlet Valve perLOP-WS-02; Service Water Pump and Service Water Jockey Pump Startup andOperation.

D. (1) increase;(2) placing a Service Water Strainer on continuous backwash per LOP-WS-05;Service Water Strainer Operations.

#91. The Shift Manager is REQUIRED to notify the Duty Station Manager perOP-AA-106-101; Significant Event Reporting; for which one of the following events?

A. Entering a 12 hour shutdown time clock due to an inoperable RR Flow Control Valve.1

B. Entering a 4 hour time clock requiring restoration of ECCS due to a scheduled surveillance.

C. Personnel injury that was treated and released by the site nurse.

D. Load reduction of 20% per a pre-approved Electric Power Operations request.

#92. An ATWS and LOCA have occurred on Unit-1 and the appropriate LGAs havebeen entered. Power was 6% and the NSO was trying to maintain level at -130 inches; howeverlevel continued to drop slowly. |The following conditions exist now:- Power is 5% and decreasing slowly- Seven ADS valves are open- RPV Pressure is 40 psig and decreasing slowly- Drywell pressure is 22 psig and steady- Suppression Pool temperature is 102F and rising slowly- Drywell temperature is 290F and steady |- Fuel Zone is reading upscale- All other RPV water level instruments indicate on-scale and rising quickly |Which one of the following represents the next required LGA action and why?

A. Wait until RPV pressure is below that indicated in Table G to take advantage of steamcooling before re-injecting into the vessel.

B. Cool down to Cold Shutdown using Shutdown Cooling per LOP-RH-07 to allow enteringthe recovery phase of EOP actions.

C. Enter the EOP for RPV Flooding because reference legs have flashed.

D. Bypass isolations per LGA-MS-01 to maintain the condenser as a heat sink.|Provide LGA-003; LGA-005 and LGA-610 to the examinee as a handout.

#93. During a refueling outage the reactor core is being loaded.- All SRMs are fully inserted- All control rods are fully inserted- The signal to noise ratio for all SRMs is 15:1- There are at least 6 fuel assemblies adjacent to each SRM- There are more than 10 fuel assemblies loaded in each quadrant- Fuel assemblies are being loaded into the same quadrant where SRM A is located While lowering a Fuel Assembly into the same quadrant as SRM A is located; the NSO takes thefollowing SRM readings:SRM A = 2.5 SRM B= 2.0 SRM C = 4.0 SRM D = 3.0Based on the above SRM indications core alterations should be …|

A. allowed to continue because SRM D is operable and is located in an adjacent quadrant towhere core alterations are taking place.

B. suspended immediately because the capability to detect local reactivity changes in the core isdegraded with SRM B inoperable. |

C. allowed to continue because SRMs D and A are operable and are located in an adjacentquadrant and a quadrant where core alterations are taking place.

D. suspended immediately because the capability to detect local reactivity changes in the core is.degraded with SRM A inoperable. Provide Technical Specification 3.3.1.2; pages 3.3.1.2-1 through 3.3.1.2-6 to the examinee as a handout.

#94. Unit-1 is performing a normal unit shutdown. The containment is being de-inertedwhen annunciator 1H13-P603-B501; Pri Cnmt Pressure Hi/Lo is received. Drywell pressureindication is verified to read negative 0.6 psig (-0.6 psig).The NEXT action required by Technical Specifications is to …

A. restore pressure to within the limits in 1 hour so that containment pressure remains withindesign values if Drywell Spray is initiated.

B. place the mode switch in SHUTDOWN immediately because containment design limits willbe exceeded if Suppression Chamber Spray is initiated. |

C. place the mode switch in SHUTDOWN immediately because containment design limits willbe exceeded if Drywell Spray is initiated.

D. restore pressure to within the limits in 1 hour so that containment pressure remains within |design values if Suppression Chamber Spray is initiated. |

#95. A casualty has occurred resulting in the following:- A leak has developed in the Reactor Water Cleanup (RWCU) Heat Exchanger room andoff-site release rates are increasing- RWCU has failed to automatically isolate and can NOT be isolated from the main contro]rooma!Ten minutes following the initial transient; it was deemed necessary to dispatch an NLO tomanually close the 1G33-F004; RWCU Suction Outboard Isolation valve. It is estimated that theNLO will exceed his federal exposure limits.The Technical Support Center (TSC) is NOT ready to assume command and control.As the Unit Supervisor; you should …

A. Obtain RP Manager AND Station Manager authorization AND then direct the NLO to enterthe room and close the valve per EP-AA-113; Personnel Protective Actions.

B. Obtain Emergency Director authorization AND then allow the NLO to enter the room toclose the valve per EP-AA-113; Personnel Protective Actions.

C. Authorize the NLO to enter the room AND close the valve per RP-AA-460; Controls forHigh and Very High Radiation Areas.

D. Obtain RP Manager authorization AND then direct the NLO to enter the room and close thevalve RP-AA-460; Controls for High and Very High Radiation Areas.|!_ !

#96. Unit-1 is in Mode 1 at 100% power:- at 12:00 on June 1; the 1A RHR WS pump is declared inoperable- at 20:00 on June 1; the 1B RHR WS pump is declared inoperable- at 15:00 on June 2; the 1A RHR WS pump is restored to OPERABLEIncluding any extensions permitted by Technical Specifications; which one of the following isthe latest time and date allowed to restore the 1B RHR WS pump to OPERABLE status withoutentering a shutdown timeclock?

A. 20:00 on June 1

B. 04:00 on June 2

C. 12:00 on June 8

D. 20:00 on June 8

#97. You are the Unit Supervisor when an IMD Technician requests to troubleshootsluggish response of the selected CRD Flow Valve. The troubleshooting activity would involvethe lowering CRD Flow Controller Setpoint by 5 gpm; then returning the controller to itsoriginal setpoint while IMD observes the CRD Flow Contro! Valve in the field. As the Unit Supervisor; you should …

A. require the IMD Technicians to produce a work package with a troubleshooting planpreviously approved by the Work Week Manager per MA-AA-716-004; Conduct ofTroubleshooting.

B. permit the troubleshooting activity; provided the Licensed NSO makes all adjustments to the |controller setpoint per LOP-RD-29; Determination of CRD System Problems.

C. require the IMD Technician to produce a work package with a troubleshooting plan prior toapproving the troubleshooting activity per MA-AA-716-004; Conduct of Troubleshooting.

D. permit the IMD Technicians to perform the troubleshooting activity ONLY under the directsupervision of a Licensed NSO per LOP-RD-29; Determination of CRD System Problems.

#98. Rad Protection (RP) has surveyed a work site and determined that personnelworking in the area would be exposed to 300 mrem/hr gamma radiation. During an ALARAreview; four options were discussed.Which one of the following four options listed would be in alignment with ALARA principles?

A. Option 1 : TWO mechanics install 2 layers of lead shielding in a 300 mremhour field for 20 minutes, then ONE operator completes the task in a 60 mremhour field in 30 minutes, then the TWO mechanics return to remove the shielding in a 300 mremhour field for 20 minutes.

B. Option 2 : ONE mechanic installs 1 layers of lead shielding in a 300 mremhour field for 20 minutes, then ONE operator completes the task in a 80 mremhour field in 30 minutes, then the ONE mechanic returns to remove the shielding in a 300 mremhour field for 20 minutes.

C. Option 3: TWO mechanics install 2 layers of lead shielding in a 300 mremhour field for 20 minutes, then TWO operators completes the task in a 50 mremhour field in 30 minutes, then the TWO mechanics return to remove the shielding in a 300 mremhour field for 20 minutes.

D. Option 4: ONE mechanic installs 1 layer of lead shielding in a 300 mremhour field for 20 minutes, then TWO operators completes the task in a 100 mremhour field in 30 minutes, then the mechanic returns to remove the shielding in a 300 mremhour field for 20 minutes.

B

#99. Given the following plant conditions:- Suppression Pool level is +15 inches and slowly increasing- Suppression Chamber pressure is 11 psig and slowly increasing- Drywell pressure is 15 psig and slowly increasing- Suppression Pool temperature is 190F and steady- RPV level is -165 inches and decreasing- RPV pressure is 200 psig and steady- All control rods are full-in- RCIC is injecting into the RPV |- RR Pumps are in Pull-To-Lock- MSIVs are isolatedWhen returmed to service; the Unit Supervisor should direct the 2B RHR Pump to be used … !

A. Per LGA-003; start lowering Suppression Pool level to prevent exceeding the SRV Tail PipeLevel Limit because of the high Suppression Poo! level.

B. Per LGA-003; start Drywell Spray to prevent exceeding the PSP limit because of highSuppression Chamber pressure.

C. Per LGA-001; start injecting into the RPV to prevent loosing adequate core cooling because |of low RPV water level.

D. Per LGA-003; start Suppression Pool Cooling to prevent exceeding the HCTL because of theincreasing Suppression Pool temperature. Provide LGA-001 and LGA-003 to the examinee as a handout.

#100. Unit-1 is at 100% power and Unit-2 is in Cold Shutdown. The 0A VC/VE Trainis_out-of-service for scheduled maintenance and the appropriate Technical Specification timeclocks per LCO 3.7.4 have been entered.Subsequently the 0B VC Supply Fan trips and can NOT be restarted.Which one of the following actions is directed by Technical Specifications?

A. Immediately enter and take actions per LCO 3.0.3 since two Control Room Air Filtration(CRAF) subsystems are inoperable and may be incapable of performing their intendedfunction.

B. Immediately place the Unit-1 Reactor Mode Switch to shutdown since both Control RoomAir Filtration (CRAF) subsystems are inoperable and may be incapable of performing theirintended function.

C. Start the OB Emergency Makeup Unit Fan within 1 hour since both Control Room AirFiltration (CRAF) subsystems are inoperable and may be incapable of performing theirintended function.

D. No additional time clocks are required since the OB Emergency Makeup Fan will stilloperate without the OB VC Supply Fan and it is capable of performing its intended function.

Results