LaSalle 2010 NRC - ILTandMe

#1. Which of the following identifies the level instruments that input into RWLC?1. Upset2. Wide Range3. Narrow Range

a. 1; 2; and 3

b. 3 ONLY

c. 1 and 3 ONLY

d. 2 and 3 ONLY

#2. Unit 1 is at rated conditions. The 1A Post LOCA H2/O2 MONITOR ISOL VLVS switch is in the SP position. Drywell pressure rises to 2.5 psig.For the given conditions; the 1A Post LOCA H2/O2 monitors will be drawing a suctionfrom the (1) with return flow going to the (2) .

a. (1) Drywell ONLY(2) Suppression Chamber

b. (1) Suppression Chamber ONLY(2) Suppression Chamber

c. (1) Suppression Chamber and Drywell(2) Suppression Chamber

d. (1) Suppression Chamber and Drywell(2) Drywell

#3. Unit 1 is in Mode 2 with the shorting links INSTALLED.Which of the following identifies the immediate impact a loss of 24VDC Bus B willhave on Unit 1?

a. Full scram and Off-gas isolation.

b. 1/2 scram and Off-gas isolation.

c. Off-gas isolation ONLY.

d. 1/2 scram ONLY.

#4. Unit-1 has just started a refueling outage (shutdown was 3.5 hours ago).Unit-2 is critical with a 65F per hour heat-up rate established.Given this initial lineup; which one of the following combinations of failures would resultin a Loss of All Off-Site AC power to both units?

a. Unit-1 SAT and Unit-2 SAT.

b. Unit-1 SAT and Lines 0108 and 0101.

c. Unit-2 SAT and Lines 0112 and 0108.

d. Unit-1 Ring Bus and Lines 0112 and 0103.

#5. Unit 1 and 2 are operating at rated conditions. The following annunciators alarm:o 1H13-P601-F204; DIV 1 RB VENT RAD HI-HIo 1H13-P601-E204; DIV 2 RB VENT RAD HI-HI 1A VR EXH VENT RAD MONITOR 1D18-K609A indicates 12MR/HR 1B VR EXH VENT RAD MONITOR 1D18-K609B indicates 13MR/HR 1C VR EXH VENT RAD MONITOR 1D18-K609C indicates 12MR/HR 1D VR EXH VENT RAD MONITOR 1D18-K609D indicates 13MR/HRUnit 1 SBGT system fails to initiate.Which of the following identifies Unit 1 Reactor Building conditions following theseevents?The Unit 1 Reactor Building will . . .

a. slowly pressurize resulting in an unmonitored gaseous effluent release.

b. be maintained at a slightly negative pressure to collect and process allgaseous effluent prior to its release to the environment through the SBGTVent Stack ONLY.

c. be maintained at a slightly negative pressure to collect and process allgaseous effluent prior to its release to the environment through theStation Vent Stack ONLY.

d. be maintained at a slightly negative pressure to collect and process allgaseous effluent prior to its release to the environment through the SBGTand Station Vent Stacks.

#6. Units 1 and 2 have been scrammed due to a security related event. All Off-site power is lost. The 1A Diesel Generator (D/G) has been damaged and will NOT operate. Unit 1 RPV water level dropped to -148 and is currently +25 inches. Unit 2 RPV water level dropped to -25 and is currently +35 inches. CSCS supply to the Common and 2A Diesel Generators is lost. Suppression Pool Cooling has been placed in operation on BOTH units. ALL personnel have been restricted from entering the Power Block.Which of the following describes the effect on the continued operation of SuppressionPool Cooling for each unit based on the given conditions?Unit 1 Suppression Pool Cooling will remain in operation until the Common D/G (1) .Unit 2 Suppression Pool Cooling will remain in operation until the 2A D/G (2) .

a. (1) experiences component failure.(2) trips on high cooling temperature.

b. (1) trips on high cooling temperature.(2) experiences component failure.

c. (1) experiences component failure.(2) experiences component failure.

d. (1) trips on high cooling temperature.(2) trips on high cooling temperature.

#7. Which of the following Unit 1 DC busses has a design feature which allows the bus to becross-tied to Unit 2?1. 112Y; Unit 1 Division 2 125 VDC2. 113; Unit 1 Division 3 125 VDC3. 121Y; Unit 1 250 VDC

a. 1 ONLY

b. 1 and 2 ONLY

c. 1 and 3 ONLY

d. 1; 2 and 3.

#8. Unit 1 was operating at rated conditions when a leak in the drywell occurred. 1B RHR is OOS. Drywell pressure is 15 psig. Suppression Chamber Spray is in operation. Drywell Spray is in operation. The 1E12-F042A was overridden CLOSED Reactor pressure rose from 420 psig to 550 psig. ADS was then initiated and reactor pressure is dropping 50 psig per minute.Which of the following identifies the expected 1A RHR valve positions four minutes fromnow if no operator actions are taken with the system?

a. 1E12-F027A; 1A RHR SP SPRAY ISOL; OPEN1E12-F042A; 1A RHR LPCI INJ. VLV.; CLOSED

b. 1E12-F027A; 1A RHR SP SPRAY ISOL; CLOSED1E12-F042A; 1A RHR LPCI INJ. VLV.; OPEN

c. 1E12-F016A and F017A; 1A RHR DW SPRAY UPSTREAM ANDDOWNSTREAM ISOLs; OPEN1E12-F042A; 1A RHR LPCI INJ. VLV.; CLOSED

d. 1E12-F016A and F017A; 1A RHR DW SPRAY UPSTREAM ANDDOWNSTREAM ISOLs; CLOSED1E12-F042A; 1A RHR LPCI INJ. VLV.; OPEN

#9. Assuming RHR is in a standby configuration initially; which one of the followingstatements is TRUE concerning RHR shutdown cooling when all of the EmergencyTransfer Switches for RHR are taken to the EMERGENCY position at the Remote S/DPanel?

a. RHR Shutdown Cooling can NOT be placed in operation from the RSDpanel.

b. Shutdown Cooling can only be lined up using the ‘A’ (Div. 1) RHR HeatExchanger.

c. There is a greater potential to drain the RPV to the suppression poolsince ALL associated interlocks are bypassed.

d. The RHR suppression pool suction valve closed signal must be presentbefore shutdown cooling can be placed on-line.

#10. To provide an additional margin of safety; the APRM Flow Biased Simulated ThermalPower Upscale Trip and alarm setpoints are automatically adjusted in proportion to (1) flow rate signals. These signals are passed through a (2) valuegate to ensure conservatism is added to the flow biased trip circuits.

a. (1) Feedwater(2) low

b. (1) Feedwater(2) high

c. (1) Reactor Recirculation(2) low

d. (1) Reactor Recirculation(2) high

#11. Which of the following identifies how the Security UPS will respond to the loss of thenormal AC power supply?The Security UPS will transfer to the . . .

a. DC power supply fed from MCC 112X.

b. DC power supply fed from the TSC battery panel 0DC22E.

c. Alternate AC power supply 132B-2; which is regulated before supplyingsystem loads.

d. Alternate AC power supply 132B-2; which is NOT regulated beforesupplying system loads.

#12. Unit 1 is operating at rated conditions. LIS-NB-101A; Unit 1 Reactor Vessel Low Water Level 3 Scram Trip Logic A1and A2 and SDC Mode Isolation Calibration was completed last shift. Trip unit 1B21-N703A; Reactor Vessel Low Water Level 3 Trip in RPS Trip LogicA1 was unknowingly damaged and left in a condition such that it will NOTchange from its normal state.What effect will the condition of trip unit 1B21-N703A have on the RPS system if RPVwater level subsequently drops below the RPS scram setpoint?

a. RPS Channel [A1] will NOT actuate; PREVENTING a FULL reactorscram.

b. RPS Channels [B1] AND [B2] ONLY will actuate; CAUSING a FULLreactor scram.

c. RPS Channels [A2] AND [B1 AND / OR B2] will actuate; CAUSING aFULL reactor scram.

d. RPS Channels [A2] AND [B1 AND / OR B2] will actuate; CAUSING areactor HALF SCRAM ONLY.

#13. An ECCS condition occurred on Unit-1. Normal power is available; but the operator decided to load the Common DG andmanually close it onto Bus 141Y. Later; an ECCS and Undervoltage condition occurs on Unit-2.What indication would you expect to see for the SAT feed to 141Y and the CommonDG?SAT feed to 141Y amps will (1) AND Common DG amps will (2) .

a. (1) increase(2) decrease and remain lower

b. (1) increase(2) decrease then immediately increase

c. (1) increase(2) decrease and then increase after a 5 second time delay

d. (1) remain constant(2) remain constant

#14. Unit 2 is in an ATWS condition. ALL control rods remain out. The Main Turbine Generator remains on line. SBLC Storage Tank level is 4850 gallons The 2A SBLC PMP; 2C41-C001A; Key 63 keylock switch is PLACED to the SYSA position per LGA-SC-201; Unit 2 Initiation of Standby Liquid Control. The start sequence is CHECKED and the following abnormal indications areobserved:o 2C41-F004A; SBLC INJ SQUIB VLV; ON light is LIT.o 2C41-F001B; SBLC STRG TNK 2B OUTLET VLV indicates CLOSED.Based on the above conditions; the indicated SBLC tank level 5 minutes after all actionsto establish flow are complete; is predicted to be approximately gallons.Note: The actions have NOT resulted in any changes in abnormal indications.

a. 4850

b. 4640

c. 4535

d. 4430

#15. Unit-1 is in Mode 2 and beginning rod withdrawal for criticality. 1D SRM is reading approximately one decade higher than the other SRMs The NSO reports that relay 1C71-K13D; Non-Coincidental Neutron MonitoringScram Relay; on panel 1H13-P611 is cyclingBased on these conditions what would be the control room operator’s NEXT action?

a. Bypass 1D SRM.

b. Insert a half-scram on 1A RPS.

c. Insert a half-scram on 1B RPS.

d. Take the 1D SRM operate switch to STBY.

#16. Unit 1 is operating at rated conditions. SRVs C and P were replaced last outage and their B solenoids haveunknowingly failed and will NOT work as designed. A transient occurs and the reactor is scrammed. Bus 111Y is de-energized during the transient. Conditions have degraded to the point where an Emergency Depressurization isrequired; and ADS is manually initiated.Which of the following identifies the response of the C and P SRVs if ADS is manuallyinitiated; and what additional actions are required to be taken based on the conditionslisted above?

a. C and P SRVs will remain CLOSED and no additional actions arerequired.

b. C and P SRVs will remain CLOSED and one additional SRV must bemanually opened.

c. C SRV will OPEN and P SRV will remain CLOSED and no additionalactions are required.

d. C SRV will remain CLOSED and P SRV will OPEN and no additionalactions are required.

#17. Unit 1 is operating at rated conditions; and Unit 2 is shutdown for a refueling outage. 1A Service Water pump and 0A Service Water Jockey pump are in operation. All other Service Water pumps are unavailable to support Unit 1. Service Water Header pressure is stable. Unit 1 Service Water Strainer dP is 6 psid. Annunciator and WS system indication is as shown below: Given the above conditions; the Unit 1 Service Water Strainer (1) be automatically backwashing and a (2) is required in response to the alarm.

a. (1) should(2) SCRAM

b. (1) should(2) reduction in auxiliary Service Water loads

c. (1) should NOT(2) SCRAM

d. (1) should NOT(2) reduction in auxiliary Service Water loads

#18. Unit 1 was operating at rated conditions when a transient occurred; resulting in the HPCS annunciator indication shown below. Annunciator 1H13-P601-A108 was the last annunciator to alarm; 2 minutes ago. All annunciators have been confirmed and acknowledged; and none of the HPCS annunciators have been reset since the transient occurred.Which of the following identifies the current alignment of the Unit 1 HPCS system based on the given annunciator indications?The Unit 1 HPCS system was initiated (1) ; and the 1E22-F012; Unit 1 HPCS Pump Minimum Flow Bypass Stop Valve is (2) .

a. (1) manually(2) OPEN

b. (1) manually(2) CLOSED

c. (1) automatically(2) OPEN

d. (1) automatically(2) CLOSED

#19. Unit 1 scrammed from rated conditions. The panel 1H13-P601-E alarms are as shown below. Annunciators 1H13-P601-E103 and 1H13-P601-E503 just alarmed.Which of the following identifies the status of annunciators 1H13-P601-E202 and 1H13-P601-E203 in 12 minutes if plant parameters remain 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.

#20. Unit 1 scrammed from rated conditions 30 minutes ago. RCIC is the only injection source available and is being operated with the flowcontroller in MANUAL. RPV water level is -15 inches. RPV pressure is 900 psig; and due to a change in plant conditions; has juststarted to drop.Based on the above conditions and with no changes made to the RCIC controls; thereactor operator will observe RCIC discharge pressure (1) and reactor waterlevel (2) .

a. (1) stay the same(2) stay the same

b. (1) lowering(2) lowering

c. (1) rising(2) lowering

d. (1) lowering(2) rising

#21. The Common and Unit 1 Station Air Compressors (SAC) are in operation; with Unit 2SAC in stand-by.The Common SAC trips causing Unit 1 and Unit 2 Service Air Header pressure to dropto 95 psig.Which of the following identifies the Main Control Room panels you must go to in orderto check: 1) the control switch position and light indication for the running SAC(s) AND2) the Unit 2 Instrument Air Header Pressure indication?

a. 1) 1PM09J ONLY2) 1PM10J OR 2PM10J

b. 1) 1PM09J ONLY2) 2PM10J ONLY

c. 1) 1PM09J AND 2PM09J2) 1PM10J OR 2PM10J

d. 1) 1PM09J AND 2PM09J2) 2PM10J ONLY

#22. Unit 1 was operating at rated conditions when the following alarms on the 1H13-P603A annunciator panel were received.Which of the following actions should be taken first; based on the alarm indication shown below?

a. Depress RR FCV Lower pushbuttons.

b. Place Reactor Mode Switch to SHUTDOWN.

c. Arm and depress all RPS scram pushbuttons.

d. Place MG Sets Transfer Switch in ALT A position.

#23. Unit 1 is operating at rated conditions. RWLC is operating in the 3-element control mode. The Feedwater Header A and B flow indications below have remained steady forthe past 2 seconds. The related flow signals are being inputted into the RWLC system. Which of the following identifies how the RWLC system will respond to this condition?

a. The RWLC system will transfer to Single-element control.

b. The sum of the individual Feedwater Pump Discharge flow signals will beinput into the RWLC system.

c. The higher Feedwater Header flow signal will be used as the Feedwaterflow signal input for the RWLC system and then adjusted to stabilize RPVwater level.

d. The lower Feedwater Header flow signal will be used as the Feedwaterflow signal input for the RWLC system and then adjusted to stabilize RPVwater level.

#24. Both Units are at rated power. Bus 111Y de-energized. An earthquake results in a dual unit scram and a complete loss of off-site poweron BOTH units.How will the 0 Diesel Generator respond to this event?The 0 Diesel Generator will . . .

a. remain in stand-by.

b. automatically start using normal control power and then load onto Unit 2.

c. automatically start using emergency/alternate control power and thenload onto Unit 2.

d. automatically start using emergency/alternate control power and then rununloaded.

#25. Unit 1 is at rated conditions and in a normal electrical line-up. The Main Turbine/Generator trips. The fast transfer of the 4160 KV bus FAILS.Which of the following identifies 1)component(s) which would be de-energized and 2) theaction required to re-energize the affected bus?

a. 1) 1B CW pump2) Synchronize and close ACB 1425

b. 1) 1A and 1C CD pumps2) Synchronize and close ACB 1415

c. 1) 1B and 1D CD pumps2) Synchronize and close ACB 1425

d. 1) 1A and 1C CW pumps2) Synchronize and close ACB 1415

#26. Unit 1 scrammed from rated conditions. A LOCA has occurred and ECCS systems have initiated. RPV pressure is 550 psig. Pressure switch 1E12-N413B; which monitors pressure between the 1B RHRInjection valve and downstream check valve; has failed and is stuck at RPVpressure for rated conditions.Which of the following identifies how the 1E12-F042B; 1B RHR LPCI INJ VLV will beaffected by this failure if RPV pressure continues to drop to 400 psig?The 1E12-F042B; 1B RHR LPCI INJ VLV . . .

a. can only be opened remotely at the Remote Shutdown Panel (afterplacing the RSDP Emergency Transfer Switch in the EmergencyPosition).

b. will open automatically or can be opened manually from the Main ControlRoom or the Remote Shutdown Panel (after placing the RSDPEmergency Transfer Switch in the Emergency Position).

c. will NOT open automatically but can be opened manually from the MainControl Room or the Remote Shutdown Panel (after placing the RSDPEmergency Transfer Switch in the Emergency Position).

d. will NOT open automatically and can NOT be opened manually from theMain Control Room or the Remote Shutdown Panel (after placing theRSDP Emergency Transfer Switch in the Emergency Position).

#27. Which of the following identifies points where the CRD system physically connects to theCondensate system?1. Condenser Hotwell Reject Line2. A Condensate Pump suction line from the Hotwell3. Condensate pumps discharge header

a. 1; 2 AND 3.

b. 1 AND 2 ONLY.

c. 1 AND 3 ONLY.

d. 2 AND 3 ONLY.

#28. Unit 1 is in Mode 4. Inboard and Outboard MSIVs are closed; with their control switches in the closedposition. The 1A RPS MG set tripped and cannot be restored. The Alternate RPS power supply is unavailable. The Shift Manager has directed that the MSIVs be re-opened.Based solely on available power to the MSIV solenoids; which of the following identifieswhich MSIVs; if any; that can be opened with ONLY the 1B RPS power supplyavailable?

a. None.

b. Inboard ONLY.

c. Outboard ONLY.

d. BOTH Inboard and Outboard.

#29. While moving a fuel bundle through the cattle chute; the air supply to the control rodgrapple is completely depressurized.What affect will this have on refueling activities; and why?Fuel movement . .

a. must be STOPPED immediately because the fuel bundle could becomedislodged with the grapple NOT air-loaded closed.

b. can CONTINUE to the point of releasing the grapple from the fuel bundlebecause the air supply is required to open the grapple.

c. must be STOPPED immediately because the refueling equipment doesNOT meet the requirements of SA-AA-03001; Exelon Nuclear IndustrySafety Pocket Guide 2010;page 40; Nuclear Fuel Handling.

d. can CONTINUE to the point of latching onto the next fuel bundle as thegrapple will spring open when the weight of the fuel bundle is removed;but an air supply is required to close the grapple onto the next fuelbundle.

#30. In order to ensure adequate NPSH for the Recirculation Pumps; the ReactorRecirculation pumps . . .

a. downshift if Feedwater flow <20%.

b. downshift if RPV Water Level drops to Level 3.

c. downshift if <10.1F dT exists between the steam dome and RR pumpsuction.

d. utilize start/upshift logic that requires RR Flow Control Valves to be at aminimum position of 20%.

#31. Which of the following identifies the design features associated with the approximately 10inch long space between the top of the stacked fuel pellets and the top of the fuel rod?The described space . . .1. provides an expansion space for axial pellet swelling2. provides an expansion space for pressure build-up from fission gases such asXenon3. houses a stainless steel spring which provides a compressive load on the fuelpellets

a. 1; 2; AND 3.

b. 1 AND 2 ONLY.

c. 2 AND 3 ONLY.

d. 1 AND 3 ONLY.

#32. Which of the following identifies the effect; if any; that the loss of 111X will have on theFire Protection system?

a. NO effect; the Fire Protection system detectors; inverters; and panels arepowered from 112X.

b. Diesel Generator Room CO2 pressure supply latching valves will unlatchand close and must be re-opened prior to restoring power.

c. Diesel Generator CO2 systems will swap to a back-up battery powersupply which will support system operation for approximately 24 hours.

d. Transformer deluge systems can NOT be actuated automatically ormanually due to the loss of power to the Deluge Valve vent valves whichutilize an energize to open solenoid.

#33. Unit 1 is operating at rated conditions. Annunciator 1N62-P600-B207; OFF GAS POST-TRTMT RAD HI has justalarmed. The Off Gas Post-treat sample pump is running.Which of the following are to be monitored in response to this alarm?1. Off-gas Pre-treat radiation indication.2. Charcoal Adsorber Vault radiation indication.3. Off-gas Hydrogen Recombiner Temperature indication.

a. 1; 2 and 3.

b. 1 and 2 ONLY.

c. 2 and 3 ONLY.

d. 1 and 3 ONLY.

#34. Unit 2 is operating at rated conditions. The RR Flow Control (RRFC) System is in Ganged Setpoint Mode. Annunciator 2H13-P602-A507; RRFCS TROUBLE alarms.o It is determined that the normal power supply to the RRFC system hasbeen lost and is the cause of the alarm.Which of the following identifies the actions to be taken in response to this event?

a. Refer to LOP-RR-07; Operation of the Reactor Recirculation FlowControl System to verify the RRFC system has properly transferred tothe Loop Manual Mode of operation.

b. Enter LOA-RR-201; Unit 2 Reactor Recirculation System Abnormal;section B.7 2A(2B) Recirculation FCV Locked-up and verify recirculationloop jet pump flows are less than the Tech Spec mismatch.

c. Verify the Unit 2 Reactor Recirculation Flow Control Valves are stableand refer to LOP-FW-16; 1(2) Operator Station Alarm MessageInterpretation to determine if any additional actions are required inresponse to the event.

d. Refer to LOP-RR-03; Start-up; Operation; and Shutdown of ReactorRecirc Hydraulic Power Unit; section E.2 Transfer of Reactor RecircHydraulic Power Unit A/B LEAD System Status from one Subloop to theOther to verify Back-up HPU subloops are operating properly.

#35. Unit 1 is operating at rated conditions with a TIP trace in progress. TIP A is at the top of the core position when a LOCA occurs. Drywell pressure quickly rises to 5 psig.At what point does the TIP Ball Valve close?The TIP Ball Valve closes . . .

a. immediately.

b. when the TIP stops withdrawing at the indexer position.

c. when the TIP stops withdrawing at the in-shield position.

d. when the TIP stops withdrawing at the core bottom limit position.

#36. Unit 1 is operating at rated conditions. MSOP discharge pressure dropped to 170 psig; and bearing supply headerpressure dropped to 12 psig. Both parameters have been restored to normal.Which of the following pumps would have running indication in the Main Control Roomfor the given conditions?

a. TGOP; EBOP; and AOP.

b. TGOP and EBOP ONLY.

c. TGOP and AOP ONLY.

d. TGOP ONLY.

#37. Unit 1 is in a refueling outage and Unit 2 is operating at rated conditions. The Fuel Handling Supervisor called to report that refueling activities are inprogress; including the removal of underwater tools from the fuel pool. A short time later; the three annunciators shown below alarmed and then wereable to be cleared after one minute. No other alarms were received.Which Emergency Operating Procedures (EOPs) must be entered; if any; based on thealarm indication below?

a. No EOPs require entry.

b. LGA-002; Secondary Containment Control ONLY.

c. LGA-009; Radioactivity Release Control ONLY.

d. LGA-002; Secondary Containment Control ANDLGA-009; Radioactivity Release Control ONLY.

#38. Unit 1 is operating at rated conditions. The Position Indication Probe (PIP) connector for control rod 30-31 hasdisconnected.The monitoring of which of the following Control Rod 30-31 parameters will be affectedbased on the given conditions?1. Control Rod position2. Control Rod Temperature3. Control Rod HCU pressure

a. 1; 2 and 3.

b. 1 and 2 ONLY.

c. 2 and 3 ONLY.

d. 1 and 3 ONLY.

#39. Unit 2 was operating at rated conditions when the unit scrammed due to the failure of abushing on the Unit 2 SAT. The NSO has completed the initial action of HARDCARD – Unit 2 ImmediateActions For Reactor Scram and reports the following: 10 control rods remain out at position 02 AND 1 control rod remains out atposition 48.o ALL scram lights are EXTINGUISHEDo ALL scram pilot valves are openo Level dropped to -20 inches and is currently +25 inches and rising.o RPV pressure is being controlled with Bypass Valves.o APRM Downscale lights are LIT.Which of the following identifies actions which must be taken based on the aboveconditions?

a. Unit 2 is in an ATWS condition AND control rods must be inserted perHardcard – Unit 2 Immediate Actions for Alternate Rod Insertion onFailure to Scram; Method 3.

b. Unit 2 is in an ATWS condition; AND control rods must be inserted perHardcard – Unit 2 Immediate Actions for Alternate Rod Insertion onFailure to Scram; Method 3 AND boron injection is required.

c. Unit 2 is NOT in an ATWS condition AND control rods must be insertedper Hardcard – Unit 2 Immediate Actions for Alternate Rod Insertion onFailure to Scram; Method 3.

d. Unit 2 is NOT in an ATWS condition AND control rods must be insertedper Hardcard – Unit 2 Immediate Actions for Alternate Rod Insertion onFailure to Scram; Method 1.

#40. During a loss of Shutdown Cooling; in order to prevent excessive temperaturestratification; the NSO is required to . . .

a. maximize CRD flow into the RPV.

b. minimize RT Bottom Head Drain flow.

c. raise RPV water level above +50 inches.

d. lower the RR Flow Control Valves position.

#41. An ATWS has occurred: approximately one quarter of the control rods are inserted (140 rods did NOTinsert) RPV water level is being maintained between -100 and -60 inches reactor pressure is being maintained between 900 and 1000 psig hot shutdown boron weight has just been injectedUnder which one of the following conditions would you expect the reactor to go criticalagain?

a. Opening SRVs to cooldown the reactor.

b. Decaying of Xenon over the next seven hours.

c. Placing RCIC in service to maintain vessel level.

d. Placing RWCU in service to stabilize reactor pressure.

#42. Unit 1 is operating at rated conditions. The Main Turbine Generator trips on Generator Differential Current signal.What turbine valves must respond properly following the receipt of the trip signal toensure reactor pressure can be controlled automatically within normal operatingparameter limits for the given conditions?Main Turbine . . .

a. Bypass Valves ONLY.

b. Stop Valves OR Control Valves ONLY.

c. Stop Valves AND Bypass Valves ONLY.

d. Bypass Valves AND Stop Valves OR Control Valves.

#43. Which of the following design features are used to ensure the Outboard Main SteamIsolation Valves will close if the normal pneumatic supply is lost?1. Bottle bank2. Actuator springs3. Pneumatic accumulators4. Emergency pressurization station

a. 2 AND 3 ONLY.

b. 2; AND 4 ONLY.

c. 1; 3 AND 4 ONLY.

d. 1; 2; 3; AND 4.

#44. Unit 1 and Unit 2 are operating at rated conditions. The LaSalle Main Control Room was just notified by Transmission SwitchingOperations that voltage in the LaSalle switchyard has fallen below 353 kV due tothe scram of the Braidwood Unit 1 reactor.Which of the following actions will increase switchyard voltage?

a. Transfer loads from the Unit SATs to the Unit UATs.

b. Start the Division 1 and Division 2 Emergency Diesel Generators.

c. Rotate BOTH the Unit 1 and Unit 2 GENERATOR TERMINAL VOLTSADJUST controls in the CLOCKWISE direction.

d. Take BOTH the Unit 1 and Unit 2 GENERATOR FIELD VOLTSADJUST control switches to the RAISE position.

#45. Intentionally Blank Proprietary Information

a

b

c

d

#46. Which of the following identifies the reason(s) for placing the 1B Diesel Gen ControlSelector switch to LOCAL MANUAL when abandoning the control room?1. Defeat automatic initiation of the 1B Diesel Generator.2. Transfer control power from DC Bus 113 to AC Bus 143-1.3. Transfer manual control of the 1B Diesel Generator to the 1B DG Room.

a. 1; 2; AND 3.

b. 3 ONLY.

c. 1 AND 3 ONLY.

d. 2 AND 3 ONLY.

#47. The reason for the Low-Low Set relief mode of operation is to . . .

a. minimize containment fatigue due to SRV cycling.

b. evenly disperse heat input into the suppression pool.

c. minimize SRV cycling in order to prevent SRV seat damage.

d. prolong SRV operation in the event the normal pneumatic supply to theSRVs is lost.

#48. The Main Control Room has been evacuated and control has been established at theRemote Shutdown Panels.The following conditions exist on Unit 1: RPV pressure is 945 psig. RPV water level is +20 inches. ALL remote transfer switches are in the Emergency position. RCIC is injecting. SRV K is open. A loss of Bus 111Y occurs.Which of the following predicts the status of the RCIC Turbine and SRV K one minutefrom now?The RCIC turbine will be (1) and SRV K will be (2) .

a. (1) tripped(2) open

b. (1) tripped(2) closed

c. (1) running(2) open

d. (1) running(2) closed

#49. Unit 2 has scrammed from rated conditions. RCIC is OOS. Feedwater has been isolated due to a leak in the drywell. Drywell pressure is 3.4 psig RPV water level first dropped to -70; recovered and peaked at 59.5 and hasnow dropped to -65. No manual actions have been taken with the HPCS system. The Assist NSO checks HPCS system status and observes the HPCS pumprunning with the HPCS Min Flow Valve OPEN and the HPCS Injection ValveCLOSED. The 1.69# AND/OR -50 indicator is LIT The Level 8 TRIP indicator is LITWhich of the following identifies the action(s) required to be taken; if any; for the givenconditions?

a. No action required.

b. Depress the HI WTR LVL RESET pushbutton and then take the HPCSInjection Valve control switch to OPEN.

c. Take the HPCS Min Flow Valve control switch to CLOSE; and then takethe HPCS Injection Valve control switch to OPEN.

d. Depress the HI DW PRESS LO WTR LVL and HI WTR LVL RESETpushbuttons; and then Arm and Depress the HPCS Manual Initiationpushbutton.

#50. Unit 2 has scrammed from rated conditions. A leak has developed in the drywell.o Drywell pressure is 3.5 psig and stable.o Drywell Temperature is 200F. and stable.o RPV water level is +35.o RPV pressure is 850 psig.Which of the following statements describes the status of drywell cooling assuming nooperator actions have been taken?Drywell cooling is . . .

a. running in the same configuration it was before the scram.

b. isolated and procedurally allowed to be restarted after defeating isolationsignals.

c. isolated and procedurally prohibited from being restarted due to highdrywell pressure.

d. isolated and procedurally prohibited from being restarted due to highdrywell temperature.

#51. Unit 1 scrammed from rated conditions due to a spurious scram signal caused byseismic motion. RPV water level dropped to -20 and is now 25. RPV pressure is 750 psig and going down. One MSL indicates 1 Mlb/hr flow with ALL MSIVs closed. SRV H is stuck OPEN Drywell pressure is 8 psig. Suppression Chamber pressure is 3 psig. Suppression Pool water level is -11 feet and going down 6 per minute.Based on the given conditions; RPV pressure is currently being discharged . . .

a. into the Suppression Pool water volume ONLY.

b. into the Suppression Pool water volume AND Drywell ONLY.

c. into the Drywell AND Suppression Chamber air space ONLY.

d. into the Suppression Pool water volume; Drywell; AND SuppressionChamber air space.

#52. LGA-009; Radioactivity Release Control; directs operation of ventilation in areas thatmay be releasing radioactivity; including the Turbine Building.Which one of the following describes the relationship between this action and theradiation levels that may exist in the Turbine Building?

a. Results in recirculation of the Turbine Building; to limit the dispersion ofthe radioactivity.

b. Results in positive pressure inside the Turbine Building; to limit theintrusion of radioactivity from the Reactor Building.

c. Assures that any radioactivity in the Turbine Building is dischargedthrough a ground level release point to limit the dispersion of theradioactivity.

d. Assures that any radioactivity in the Turbine Building is dischargedthrough an elevated release point and allows the dispersion of theradioactivity to be monitored.

#53. Unit 1 is operating at rated conditions. Rod Line is 100%. RR loop flows are matched. The 1A RR FCV is locked up.The 1B RR Pump trips off and coasts to zero speed.Power stabilizes at 54%.What is core flow for the given conditions; using the reference provided?LOA-RR-101; Attachment A; provided for reference.

a. 41 M#/Hr.

b. 43 M#/Hr.

c. 50 M#/Hr.

d. 54 M#/Hr.

#54. The purpose of the Critical L Path interlock is to keep the . . .

a. Reactor Building Overhead crane main hook aligned with a pre-determined path when transporting the reactor head between the reactorand the reactor head pedestal.

b. Refueling Main Hoist grapple a minimum of 2 feet away from the walls ofthe fuel pools in order to prevent damage to suspended fuel bundlesduring loading into the spent fuel racks.

c. Refueling Bridge Main Hoist grapple aligned with the centerline of thecattle chute in order to prevent damage to suspended fuel bundlesduring transport between the reactor and the fuel pool.

d. Reactor Building Overhead Crane from traveling over the Spent Fuel Poolduring spent fuel cask movement; and to allow the cask to travel onlyover strengthened structural members that can support a cask dropaccident.

#55. Unit 2 scrammed from rated conditions following the loss of the Unit 2 SAT. RCIC is OOS. FW has been isolated due to a leak outside the drywell. RPV water level is -65 and going down. RPV pressure is 900 psig and being controlled with Turbine Bypass Valves. The 2B Diesel Generator has failed to start.The given conditions will require entry into . . .1. LGA-001; RPV Control.2. LOA-AP-201; Unit 2; AC Power System Abnormal3. LOA-DG-201; DG Failure

a. 1; 2 AND 3.

b. 1 AND 2 ONLY.

c. 2 AND 3 ONLY.

d. 1 AND 3 ONLY.

#56. What is the significance of the 1/4-inch diameter black dot located on the label forControl Room recorder 1TR-CM037A AVG SP TEMP? The black dot signifies that the recorder . . .

a. is intended for use under accident conditions.

b. is a Technical Specification related instrument.

c. has redundant indication available at the Remote Shutdown Panel.

d. requires manual compensation based on environmental conditions.

#57. What is the primary concern associated with Drywell temperature exceeding 340F?

a. Loss of core circulation.

b. Loss of RPV pressure control.

c. Failure of primary penetration seals.

d. Loss of pressure suppression capability.

#58. Unit 1 is operating at rated conditions. The 1B TBCCW Pump is OOS. Annunciator 1PM10J-A304; TBCCW PMP DSC HDR PRESS LO alarms. Unit 1 TBCCW Discharge Header pressure is indicated below; and going down slowly: Which of the following action should be taken next?

a. SCRAM the reactor per LGP 3-2.

b. SWAP TBCCW heat exchangers.

c. Commence a Unit 1 SHUTDOWN.

d. Secure TBCCW flow through off-line equipment.

#59. Unit 1 is starting up from a refueling outage. RPV Water Level is 36 on narrow range MDRFP is on-line; in manual; with feedwater header flow at 3.8 MLB/HR. Reactor power is 15% and steady Pressure is being controlled with Turbine Bypass Valves. Steam flow is as indicated. (Note: Lower portion of band is displayed for clarity Based on the information provided; which of the following annunciators will alarm first if no operator action is taken regarding the operation of the MDRFP?

a. 1H13-P603 A512; RWLCS FAILURE

b. 1H13-P603 A110; RX VESSEL PRESS HI

c. 1H13-P603 A309; FW CONTROL RX VESSEL LVL 7 HI

d. 1H13-P603 A409; FW CONTROL RX VESSEL LO LVL 4

#60. Unit 1 is operating at rated conditions. 1A CRD pump is in the process of being returned to service At 06:55; 1B CRD pump trips At 06:57 1H13-P601-A503; CRD HYD ACCUM TROUBLE alarms due to HCU30-31 low accumulator pressure At 07:00 CRD charging water pressure drops below 940 psig At 07:03 1H13-P601-A503; CRD HYD ACCUM TROUBLE alarms due to HCU46-07 low accumulator pressureWhich of the following identifies 1) the action required to be taken for the givenconditions; and 2) the predicted response of control rods 30-31 and 46-07 if a scramsignal is inserted?

a. 1) An immediate scram is required.2) Control rods 30-31 and 46-07 will be fully inserted from the drivingforce created primarily by reactor water pressure.

b. 1) An immediate scram is required.2) Control rods 30-31 and 46-07 will be fully inserted from the drivingforce created primarily by HCU accumulator water pressure.

c. 1) A scram is required if CRD charging water pressure remainsbelow 940 psig until 07:20.2) Control rods 30-31 and 46-07 will be fully inserted from the drivingforce created primarily by reactor water pressure.

d. 1) A scram is required if CRD charging water pressure remainsbelow 940 psig until 07:20.2) Control rods 30-31 and 46-07 will be fully inserted from the drivingforce created primarily by HCU accumulator water pressure.

#61. What is the reason for the following note provided in LGA-001; RPV Control? It is okay to delay depressurization in order to restore systems; such as to reopenthe MSIVs and restore the Main Condenser (except in SBO).

a. To limit heat addition to the primary containment.

b. To improve pressure control during cooldown by using BPVs.

c. To eliminate the need to make up for reactor inventory discharged to thesuppression pool.

d. To prevent the need to lower suppression pool water level to remainwithin Tech Spec limits.

#62. Unit 2 just scrammed from rated conditions. Two control rods are NOT indicating 00 on the RCMS displays.Which of the following identifies a means for determining if the control rods NOTindicating 00 have inserted to at least position 01?

a. Check the Maintenance Display at the AEER RCMS Panel 2H13-P659.

b. Obtain and review a Detailed Scram Time Report using the OperableDemandable feature of the PPC.

c. Utilize the Rod Control Management System On Demand Function forRCMS Alarms and Messages.

d. Right click the SPDS Reactor Power Bar and check rod position inputsfor the two control rods NOT indicating 00 on the RCMS display.

#63. Unit 1 is operating at rated conditions. Annunciator 1H13-P601-C408; LPCS/RCIC PMP CUBICLE TEMP HI has justalarmed.Which indicator must be referenced to verify the alarm setpoint has been reached?

a. 1TI-VY021; LPCS VENT TEMPS – DUCT located on the 1H13-P601panel.

b. 1TI-VY022; LPCS VENT TEMPS – AREA located on the 1H13-P601panel.

c. 1E31-R001C; DIV 1 LD-RCIC/MSL TEMP RCDR; located on the 1H13-P632 Backpanel (ONLY).

d. 1E31-R001C; DIV 1 LD-RCIC/MSL TEMP RCDR or 1E31-R002C; DIV2 LD-RCIC/MSL TEMP RCDR located on the 1H13-P632/642Backpanel.

#64. Unit 1 is in an accident condition. The Unit 2 SBGT system is OOS. The Unit 1 SBGT system auto-initiated in response to the event. Annunciator 1PM07J; SBGT PRI FAN FLOW HI/LO is LIT. 1VG01C; U1 SBGT PRIMARY FAN is running 1VG001; U1 SBGT INLET ISOL VLV closed indication is EXTINGUISHED andopen indication is LIT. 1VG002Y; U1 SBGT FLOW CONT VLV closed indication is EXTINGUISHEDand open indication is LIT. U1 SBGT ELEC HEATING COIL 1VG01A off indication is LIT.Based on the above conditions; which of the following identifies:1 the panel location(s) the NSO can go to in order to determine if SBGTflow is Hi or Lo; and2) the action required to be taken first with the SBGT system?

a. 1 1PM07J – STANDBY GAS TREATMENT (ONLY)2 PLACE the 1VG003; DSCH ISOL VLV control switch in the OPENposition.

b. 1) 1PM07J – STANDBY GAS TREATMENT (ONLY)2) VERIFY 1VG002Y; U1 SBGT FLOW CONT VLV is modulating tocontrol flow.

c. 1) 1PM06J – HVAC CONTROL and 1PM07J – STANDBY GASTREATMENT2) PLACE the 1VG003; DSCH ISOL VLV control switch in the OPENposition.

d. 1) 1PM06J – HVAC CONTROL and 1PM07J – STANDBY GASTREATMENT2) VERIFY 1VG002Y; U1 SBGT FLOW CONT VLV is modulating tocontrol flow.

#65. Unit 1 is in a Refueling Outage. HPCS is running for a post-maintenance test. LPCS is being drained for a pump inspection. A RHR is running in the SDC mode of operation. C RHR pump discharge valve repair is in progress. Annunciator 1PM13J-B304; RB SE-SW EQUIP DRN SUMP TROUBLE is LIT.o R1438 RB SE DRN SUMP TROUBLE is indicated on the SER display. Annunciator 1PM13J-402; RB SOUTH FLOOR DRN SUMP TROUBLE just LIT.o R1437 RB S FLR DRN SUMP TROUBLE is indicated on the SER display.Which of the following systems should be checked FIRST to determine the cause of thelisted alarms?

a. A RHR

b. C RHR

c. HPCS

d. LPCS

#66. Unit 1 is shutdown for a refueling outage. Reactor Engineering verified the Unit 1 reactor was subcritical at 00:05 on2/23/2010.Which of the following identifies the earliest time and date that core alterations canbegin?

a. 08:05; 2/23/2010

b. 12:05; 2/23/2010

c. 00:05; 2/24/2010

d. 12:05; 2/24/2010

#67. Which of the following describes the proper method for administratively controlling thekey for the Reactor Mode Switch when it is required to be LOCKED?Place Reactor Mode Switch in the required position; and then . . .

a. place the key to the lock position; do NOT remove the key from the modeswitch.

b. remove the key from the Reactor Mode Switch and place in the key lockerat the Center Desk area.

c. remove the key from the Reactor Mode Switch and place in the key lockerin the Shift Manager’s Office.

d. remove the key from the Reactor Mode Switch and locate the key at theReactor Mode Switch; but NOT in the lock.

#68. Units 1 and 2 are operating at rated conditions.Which of the following would require entry into a Technical Specification LCO?

a. DWFDs Fill-Up Rate 1.9 gpm.

b. Primary Containment Oxygen concentration 4.5%.

c. Average Circulating Water inlet temperature 100.25 degrees F.

d. Hydrogen concentration in the Main Condenser Offgas Treatment System3.8% by volume.

#69. What is the expected status of the HPCS and RBCCW system vent and drain valves ifMechanical Checklists were performed as written?VENT VALVES DRAIN VALVES

a. OPEN OPEN

b. OPEN CLOSED

c. CLOSED OPEN

d. CLOSED CLOSED

#70. Unit-1 is operating at 50% power when the 1C Inboard MSIV goes CLOSED. After theplant stabilizes; reactor power is 50% and reactor pressure has increased slightly.How do the MSL Radiation Monitor indications compare to those before the 1C MSIVclosed?Compared to the readings before the 1C MSIV closed; …

a. all four MSL Radiation Monitors indicate approximately the same.

b. 1C MSL Radiation Monitor indicates lower; the other monitors indicatehigher.

c. 1C MSL Radiation Monitor indicates lower; the other monitors indicateapproximately the same.

d. 1C AND 1D MSL Radiation Monitors indicate lower; the other monitorsindicate approximately the same.

#71. Unit 1 has scrammed from rated conditions. 5 Control rods failed to fully insert. Reactor power is less than 3%. You are assigned to perform in-plant actions to insert the 5 control rods using theSRI Test Switches Your current annual exposure is 0 mrem.What is the maximum TEDE exposure you are allowed to receive for the given task;without obtaining any extensions; in accordance with the guidance of RP-AA-203;Exposure Control and Authorization?

a. 2 rem

b. 5 rem

c. 25 rem

d. 40 rem

#72. Unit 2 is in an ATWS condition. RPV water level dropped to -140 and is currently being controlled at -100. Drywell pressure is 1.5 psig. You are an extra NSO and have been assigned to perform all the applicableactions of Hardcard – Unit 1 Using Main Condenser as Heat Sink in ATWS;including any actions needed to be performed outside of the main control room.Which of the following identifies actions; if any; needing to be performed outside of themain control room for the given conditions?

a. No actions are required to be performed outside of the main control room.

b. Bypass isolation logic for the 1IN017; DW PNEUMATICS 100lb HDRISOL. to restore pneumatic supply to the Drywell (ONLY).

c. Bypass isolation logic for the 1N62-F057; OFF GAS DISCHARGE TOSTACK to maintain condenser vacuum (ONLY).

d. Bypass isolation logic for BOTH the 1IN017; DW PNEUMATICS 100lbHDR ISOL to restore pneumatic supply to the Drywell and 1N62-F057;OFF GAS DISCHARGE TO STACK to maintain condenser vacuum.

#73. What LGA entry condition is aligned with an Emergency Action Level threshold?LGA EAL Threshold

a. LGA-001; RPV Control RPV water level

b. LGA-002; Secondary Containment Control Differential Pressure

c. LGA-003; Primary Containment Control Suppression pool level

d. LGA-009; Radioactivity Release Control Offsite release rate

#74. Which of the following methods are allowed for use when verifying a Direct (continuous)communication link between the Control Room and the Refueling Platform for theperformance of core alterations?1. Dial telephones (with an open communication line established)2. Sound Powered Phones3. Dedicated GAI-tronics PA system

a. 1; 2; AND 3.

b. 1 AND 2 ONLY.

c. 2 AND 3 ONLY.

d. 1 ONLY.

#75. LGA-RT-101; RPV Depressurization Using RWCU Blowdown is in progress and theMain Condenser is NOT available to accept RWCU flow.For the given conditions; LGA-RT-101 provides an ALARA warning for abnormally highairborne radiation levels in the . . .

a. Radwaste Control Room.

b. Division 3 Switchgear room.

c. vicinity of the Radwaste Tanks.

d. RWCU Heat Exchanger rooms.

#76. Unit 1 is in Mode 4. The 1A RHR loop is the SDC mode of operation. 1A and 1B RR pumps are secured. The Unit 1 Assist RO reports SDC flow is indicating 5800 gpm.Based on the above; the Unit Supervisor must direct the Unit 1 Assist RO to (1) in order to prevent (2) .

a. (1) raise flow per LOA-RH-101; Unit 1 RHR Abnormal.(2) temperature stratification

b. (1) lower flow per LOA-RH-101; Unit 1 RHR Abnormal.(2) damage to in-core instrumentation

c. (1) raise flow per LOP-RH-07; Shutdown Cooling System Startup;Operation and Transfer(2) temperature stratification

d. (1) lower flow per LOP-RH-07; Shutdown Cooling System Startup;Operation and Transfer(2) damage to in-core instrumentation

#77. Which of the following must occur in order to prevent exceeding 10CFR100 ReactorSite Criteria limits in the event of a design basis fuel handling accident?

a. VG must initiate; RB Ventilation must isolate and TB Ventilation must bemanually started.

b. VG must initiate and RB Ventilation must isolate ONLY.

c. RB Ventilation must isolate ONLY.

d. VG must initiate ONLY.

#78. Units 1 and 2 are operating at rated conditions. You are the Unit 1 Unit Supervisor The A VC/VE train is in operation A fire outside the plant has resulted in heavy smoke surrounding the VC airintake. The Unit 1 Assist Reactor Operator reports A VC train is in its normalconfiguration.Which of the following actions must be performed in response to the given conditions?Direct an available Reactor Operator to . . .

a. SWAP to the B VC train per LOP-VC-01; Control Room HVACOperation and immediately declare A VC Inoperable.

b. Manually place A VC train Emergency Make-up Unit on-line per LOP-VC-01;Control Room HVAC Operation and promptly evaluate the operabilityof the A VC System.

c. SWAP to the B VC train per LOA-VC-001; VC Abnormal Actions for anInoperable Control Room Envelope Boundary (CRE) and immediatelydeclare A VC Inoperable.

d. Manually place A VC train Emergency Make-up Unit on-line per LOA-VC-001;VC Abnormal Actions for an Inoperable Control Room EnvelopeBoundary (CRE) and promptly evaluate the operability of the A VCSystem.

#79. You are the Unit 2 Unit Supervisor U1 SBGT is OOS Unit 2 has scrammed from rated conditions 56 control rods have failed to insert Reactor power is 34% RPV Water level is within the required band A large steam leak has developed in the heater bay The inboard and outboard MSIVs for A MSL can NOT be closed U2 SBGT is unable to be started Which of the following actions are required to be directed based on the instrument indication shown below?

a. Immediately perform a Blowdown per LGA-004; RPV Blowdown.

b. Wait until the recorder reading goes up an additional 0.4 E+08 uCi/sec;and then perform a Blowdown per LGA-004; RPV Blowdown.

c. Immediately terminate and prevent ALL RPV injection except Boron;CRD; and RCIC; and then perform a Blowdown per LGA-006; ATWSBlowdown.

d. Wait until the recorder reading goes up an additional 0.4 E+08 uCi/sec;next terminate and prevent ALL RPV injection except Boron; CRD; andRCIC; and then perform a Blowdown per LGA-006; ATWS Blowdown.

#80. Unit 1 is operating at rated conditions when an SRV spuriously opened. The Main Control Room actions of LOA-SRV-101; Unit 1 Stuck Open Safety Relief Valve were completed and did NOT close the SRV. Suppression Pool Temperature is rising 1/3F per minute. Based on the recorder indication above; which of the following identifies the MainControl Room action(s) required to be directed and in the proper order?

a. Direct the Unit 1 Assist NSO to start ONE loop of SP cooling ONLY.

b. Direct the Unit 1 Assist NSO to start BOTH loops of SP cooling ONLY.

c. Direct the Unit 1 NSO to SCRAM the Unit 1 reactor; and then direct the Unit 1 Assist NSO to start BOTH loops of SP cooling.

d. Direct the Unit 1 Assist NSO to start BOTH loops of SP cooling and then immediately direct the Unit 1 NSO to SCRAM the Unit 1 reactor.

#81. Unit 1 is operating at rated conditions; with the 1B CW pump OOS. Bus 141X experiences an overcurrent trip. The crew responds to the event per:o LOA-AP-101; Unit 1 AC Power System Abnormal ando LOA-CW-101; Unit 1 Circulating Water System Abnormal.Which of the following technical specification actions must be taken for the givenconditions?Perform a functional test of each within the next 12 hours.

a. Safety Relief Valve

b. Main Steam Isolation Valve

c. Main Turbine Bypass Valve

d. Suppression Chamber to Drywell Vacuum Breaker

#82. Unit 2 has scrammed and experienced a DBA LOCA. RPV pressure is 15 psig and going down slow.Based on the following indications; determine if adequate core cooling exists; and why

a. Does NOT exist. RPV water level is too low.

b. Does NOT exist. Core spray flow is too low for the indicated RPV waterlevel.

c. Does exist. RPV water level alone is high enough to ensure adequatecore cooling.

d. Does exist. Core spray flow and RPV water level are high enough to ensure adequate core cooling.

#83. Unit 1 is operating at rated conditions with 1A VP in-service; when an inadvertent Group2 Isolation occurs.Drywell temperature was recorded as 95F at the time of the isolation; 1 minute ago.Which of the following identifies the procedure to be directed for use for bulk drywelltemperature determination while recovering from the isolation signal?

a. LGA-003; Primary Containment Control

b. LOP-CX-02; Safety Parameter Display System

c. LOA-PC-101; Primary Secondary Containment Trouble

d. LOP-CM-04; Primary Containment Temperature Determination

#84. LaSalle Station is in an accident condition. An offsite release rate of 5.7 E+09 uCi/sec is in progress. A Controlled Direct Containment Vent was started at 0845 and was stopped at0915. The off site dose assessment is 1.5R TEDE. A loss of the ‘Fuel’ AND ‘RCS’ Fission Product Barriers has occurred.Which of the following identifies the Protective Action Recommendations; if any; that arerequired to be made based on the given conditions?EP-AA-111-F-05; LaSalle Plant Based PAR Flowchart provided.

a. No PARs required.

b. Shelter 2 Mile Radius & 5 miles Downwind.

c. Evacuate 2 Mile Radius & 5 miles Downwind.

d. Evacuate 5 Mile Radius & 10 miles Downwind.

#85. The reactor vessel water level Safety Limit (SL) ensures that adequate core coolingcapability is maintained during (1) of reactor operation. Establishment ofEmergency Core Cooling System (2) provides margin such that the SL willNOT be reached or exceeded.

a. (1) all MODES(2) divisional separation

b. (1) all MODES(2) instrumentation setpoints higher than the SL

c. (1) MODES 1; 2; and 3 (ONLY)(2) divisional separation

d. (1) MODES 1; 2; and 3 (ONLY)(2) instrumentation setpoints higher than the SL

#86. Unit 1 is operating at rated conditions when the Unit 1 Process Computer UPS Normaland Alternate AC power feed breakers trip. It has been determined it will be at least one hour before the Normal and/orAlternate Power Supplies will be restored.Which of the following identifies the procedure to be directed in response to this eventand the actions; if any; required to be taken?

a. LOP-CX-08; Uninterruptible Power Supply Startup; Operation; andShutdownNo immediate actions required.

b. LOP-CX-08; Uninterruptible Power Supply Startup; Operation; andShutdownLimit PPC operation to less than 30 minutes.

c. LOA-RM-101; Unit 1 RCMS Abnormal OperationVerify RCMS controllers have automatically rebooted.

d. LOA-RM-101; Unit 1 RCMS Abnormal OperationVerify RCMS automatically transferred to the Alternate Power Supply.

#87. Unit 2 is operating at rated conditions The 2A SBLC pump is OOS. Annunciator 2H13-P603-B502; STANDBY LIQ TANK TEMP HI/LO just alarmed. An Equipment Operator is dispatched to investigate the cause of the alarm andreports that the circuit breaker to the A 10kW heater for the SBLC Storage Tankis tripped and will NOT reset. Standby Liquid Tank Temperature is 69 degrees F.What action must be directed to mitigate the consequences of the situation; and why?Place the Standby Liquid Tank Heater Control Switch in B ON to allow the B 40kWheater to be used to (1) control Standby Liquid Tank temperature to ensurethe boron does NOT (2)

a. 1) MANUALLY2) precipitate out in the storage tank.

b. 1) MANUALLY2) clog the SBLC injection sparger if injected.

c. 1) AUTOMATICALLY2) precipitate out in the storage tank.

d. 1) AUTOMATICALLY2) clog the SBLC injection sparger if injected.

#88. Unit 2 scrammed from rated conditions 4 hours ago due to a spurious Group 1 isolationsignal that will not clear. RPV level dropped to -25 and is now +35 and being controlled with theMDRFP. Drywell pressure is 1.2 psig 2A RHR was placed in the SDC mode of operation 30 minutes ago. The 2A RHR motor just tripped due to an Instantaneous Overcurrent condition.Which of the following procedures can be directed for use to mitigate the consequencesof the loss of SDC for the given conditions?1. LGA-MS-012. LGA-RH-201 3. LOA-RH-201 4.LOP-RT-09

a. 1 AND 2 ONLY.

b. 2 AND 3 ONLY.

c. 3 AND 4 ONLY.

d. 2; 3; AND 4 ONLY.

#89. Unit 2 is in Mode 5. You are the Unit 2 Control Room Supervisor Fuel movements are scheduled to begin; for the first time in the outage; later thisshift. Non-Spiral off-loading is being utilized. 24/48VDC Bus A is de-energized. The Fuel Handling Supervisor has called you to request permission tocommence fuel movements. The only item remaining to be checked is the operability of required nuclearinstrumentation.Based on the given conditions; fuel movements (1) as (2) .NOTE: Technical Specification 3.3.1.2 SRM Instrumentation provided.

a. (1) can begin(2) the required number of SRMs and their locations meet LCOrequirements.

b. (1) can NOT begin(2) the required number of SRMs will NOT meet LCO requirements(ONLY).

c. (1) can NOT begin(2) the location of operable SRMs will NOT meet LCO requirements(ONLY).

d. (1) can NOT begin(2) the required number AND location of operable SRMs will NOTmeet LCO requirements.

#90. The 1B Diesel Generator received a spurious start signal and has been running loadedfor approximately one minute.In response to this event; a Reactor Operator must be directed to enter (1) andthen (2) .

a. (1) LOP-DG-03; Diesel Generator Shutdown(2) shutdown the diesel immediately to prevent excessive wear to theturbocharger gear drive.

b. (1) LOP-DG-03; Diesel Generator Shutdown(2) run the diesel for a total of 5 to 10 minutes before shutdown toallow temperatures to reach equilibrium values.

c. (1) LOS-DG-M3; 1B(2B) Diesel Generator Operability Test(2) load the diesel for a total 5 to 15 minutes to allow diesel andgenerator temperatures to stabilize.

d. (1) LOS-DG-M3; 1B(2B) Diesel Generator Operability Test(2) run the diesel for a total of 5 to 10 minutes before shutdown toallow temperatures to reach equilibrium values.

#91. Unit 1 is operating at rated conditions. At 07:00 annunciator 1H13-P603-A102; SCRAM PILOT VLV AIR HDR PRESSLO alarms An Equipment Operator dispatched to investigate the alarm reports that a crack has developed between the Scram Air Header pressure transmitter 1C11-N052and root stop valve 1C11-F416. While actions are taken to close root stop valve 1C11-F416; the full core displayfor control rods 30-59; 30-55; 50-51; and 30-47 are as shown below; withchanges in indication at the given times.In response to these events and indications; as the Unit 1 Control Room Supervisor; you must direct the crew to enter (1) ; and a reactor scram per LGP-3-2 (2) required.

a. (1) LOA-RD-101; Control Rod Drive Abnormal ONLY(2) IS

b. (1) LOA-RD-101; Control Rod Drive Abnormal ANDLOA-RM-101; Unit 1 RCMS Abnormal Situations(2) IS

c. (1) LOA-RD-101; Control Rod Drive Abnormal ONLY(2) is NOT

d. (1) LOA-RD-101; Control Rod Drive Abnormal ANDLOA-RM-101; Unit 1 RCMS Abnormal Situations(2) is NOT

#92. Given the following initial plant conditions: RPV water level is -195 on Fuel Zone indicators. RPV pressure is 125 psig. Suppression Pool temperature is 197.5F. Suppression Pool level is -12 feet. Suppression Chamber pressure is 2 psig. Drywell pressure is 7 psig.Which one of the following identifies a parameter change that could result in damage toan RHR pump; and the direction to be provided for the use of the A and B RHR pumps?

a. Drywell pressure increases an additional 5 psig.Continue to inject with A and B RHR.

b. Suppression Pool level decreases an additional 2 feet.Continue to inject with A and B RHR.

c. Suppression Pool temperature increases an additional 10.0F.Re-align A or B RHR to the SPC mode of operation.

d. Suppression Chamber pressure increases an additional 2 psig.Re-align A or B RHR to the SPC mode of operation.

#93. Which of the following identifies why the Turbine Bypass System is required to beoperable at >25% reactor power?To ensure that the (1) safety limit(s) is/are NOT violated during the (2) transient(s).

a. (1) MCPR (only)(2) turbine trip and feedwater controller failure maximum demand(only)

b. (1) MCPR (only)(2) turbine trip; feedwater controller failure maximum demand; andturbine generator load rejection

c. (1) MCPR and Reactor Pressure(2) turbine trip and feedwater controller failure maximum demand(only)

d. (1) MCPR and Reactor Pressure(2) turbine trip; feedwater controller failure maximum demand; andturbine generator load rejection

#94. You are reviewing the shift manning schedule and identify that two of the fourReactor Operators (RO) scheduled for the next shift have No-solo Operationrestrictions on their license.What action; if any; is required to be taken regarding shift staffing for the next shift?

a. No action is required to be taken.

b. Assign the ROs with No-solo Operation restrictions to the Unit 1 andUnit 2 Assist RO positions.

c. Replace one of the ROs with the No-solo Operation restriction with anRO that does NOT have the restriction.

d. Separate the ROs No-solo Operation restrictions such that only one ROwith a No-Solo Operation restriction is assigned to each unit.

#95. Unit 1 is in an emergency condition and cannot maintain RPV water level above theBottom of Active Fuel. The on-shift crew has identified an innovative method to restore RPV water levelabove the Top of Active Fuel; however the method has NOT been previouslyreviewed or approved for use.Which of the following is required; at a MINIMUM; to permit implementing the action torestore RPV water level?

a. Approval by one licensed SRO.

b. Approval by two licensed SROs.

c. A completed 50.59 Safety Evaluation.

d. Approval by one licensed SRO AND the Shift Emergency Director.

#96. What is the relationship between the Station Emergency Director and the performance ofan emergency containment vent per LGA-VQ-02; Emergency Containment Vent?The Station Emergency Director the primary containment.

a. must direct the emergency venting of

b. must be informed prior to emergency venting

c. has NO responsibilities related to emergency venting

d. must approve the release permit for emergency venting

#97. Which of the following is a non-delegable action of the Shift Emergency Directorfollowing the classification of a Site Area Emergency?

a. Transmit a NARS form.

b. Authorize exposure extension.

c. Activate the Emergency Response Organization.

d. Initiate an Emergency Plant Announcement for the classification.

#98. Unit 1 is in a refueling outage. LOP-WR-01; Filling and Venting or Draining of the Reactor Building ClosedCooling Water System was started at the beginning of the current shift to refill aportion of the WR system. Step E.1.3 states:As necessary; OPEN 1WR093; RBCCW Expansion Tank Level Control1WR091 Bypass Valve (01 RB 820 C-11 RB 820′ by RBCCW Tank) tomaintain the expansion tank level between 24 to 42 inches. Step E.1.9 states:If 1WR093; RBCCW Expansion Tank Level Control 1WR091 BypassValve was used to fill expansion tank; CLOSE valve. Valve 1WR093 was NOT manipulated during the filling of the WR system.The Equipment Operator performing the surveillance has requested direction on how toplacekeep steps E.1.3 and E.1.9 based on the given conditions.As the Unit Supervisor; direct the Equipment Operator performing the procedure to . . .

a. leave steps E.1.3 and E1.9 blank.

b. mark steps E.1.3 and E1.9 as complete.

c. mark steps E.1.3 and E1.9 C/M (Condition Met).

d. mark steps E.1.3 and E1.9 N/A (Not Applicable).

#99. Unit 2 has experienced a LOCA. The Division 1 POST-LOCA monitor is the only monitor available for use. Group 2 PCIS logic failed to actuate. The Shift Manager has requested the current Oxygen levels in the containment.For the given conditions; the Division 1 POST-LOCA monitor must be aligned to samplethe (1) and local action must be taken to (2) of the POST-LOCAmonitor.

a. (1) Drywell(2) re-align valves per LGA-CM-01; Emergency Operation of thePOST-LOCA Accident Primary Containment AtmosphereHydrogen and Oxygen Monitoring System to prevent erraticindication.

b. (1) Drywell(2) adjust system flow per LOP-CM-02; Startup; Operation andShutdown of POST-LOCA Accident Primary ContainmentAtmosphere Hydrogen and Oxygen Monitoring System to ensureaccurate indication.

c. (1) Suppression Chamber(2) re-align valves per LGA-CM-01; Emergency Operation of thePOST-LOCA Accident Primary Containment AtmosphereHydrogen and Oxygen Monitoring System to prevent erraticindication.

d. (1) Suppression Chamber(2) adjust system flow per LOP-CM-02; Startup; Operation andShutdown of POST-LOCA Accident Primary ContainmentAtmosphere Hydrogen and Oxygen Monitoring System to ensureaccurate indication.

#100. Unit 1 is operating at rated conditions. You are the Unit 1 Unit Supervisor responsible for preparing a brief for the returnto service of the 1A TDRFP min flow valve; and have identified that IndependentVerification (IV) will be used when removing the C/O.Per HU-AA-101; Human Performance Tools and Verification Practices; which one of thefollowing correctly states the philosophy to be applied for removal of the C/O cardslocated in the Unit 1 Heater Bay?

a. Perform the IV for the C/O cards located in the Unit 1 Heater Bay afterreceiving High Radiation and ALARA briefs.

b. Direct that Concurrent Verification be used for the C/O cards located inthe Unit 1 Heater Bay; and complete IV for the rest of the checklist.

c. Request that the Shift Manager waive the IV for the C/O cards located inthe Unit 1 Heater Bay; and complete IV for the rest of the checklist.

d. Request that the Rad Protection Manager waive the IV for the C/O cardslocated in the Unit 1 Heater Bay; and complete IV for the rest of thechecklist.