Braidwood 2013 - ILTandMe

#1. Given:- Unit 1 is at 250 Mwe (normal plant lineup) following a recent refueling outage.- The crew is preparing to raise load to 300 Mwe per 1BwGP 100-3 POWER ASCENSION.- Rod control is in automatic with control bank D at 145 steps.The following occur simultaneously:- The Tref programmer fails to 100%.- A malfunction of the Ovation Control System causes main generator load to drop to 160 Mwe.- The following bypass permissives lights are LIT:1-BP-5.7 TURBINE LO POWER INTLK C51-BP-3.7 LOW POWER TRIP BLOCKED P81-BP-5.8 AMS PERMISSIVE C-20With NO operator action control rods will

A. continuously withdraw until annunciator 1-10-D5 BANK D ROD STOP C-11 alarms.

B. continuously withdraw until annunciator 1-10-C5 OTT HIGH ROD STOP C-3 alarms.

C. remain stationary.

D. insert continuously.

#2. Given:- Unit 1 just completed main generator synchronization following a refueling outage.- Main Generator load is 150 Mwe.- Steam Dumps are in the STEAM PRESSURE MODE in AUTOMATIC.- Tave = 562oF.- 1UI-500 STM DMP DEMAND meter indicates 10%.The crew is about to start a turbine load ramp toward full power at 0.65 Mw/min to begin at 01:00 AM. Neglecting Xenon effects from the previous ramp at what time must the effects of the FIRST reactivity addition to the core occur in order to maintain Tave with NO rod motion?

A. 01:00

B. 02:18

C. 03:38

D. 04:15

#3. Given:- The Pressurizer Variable heater control switch was broken (inoperable) prior to the reactor trip.- Unit 2 experienced a Loss of Offsite Power following a reactor trip from full power.- All equipment responded as designed.- Pressurizer level is 35%.- Pressurizer pressure is 2235 psig.- All Pressurizer backup heater breakers and contactors are closed.After restoring power to bus 243 the Pressurizer heater groups that automatically re-energize (if any) are

A. none.

B. A and B.

C. B and D.

D. A and D.

#4. Given:Case 1: Unit 1 at 100% power steady-state. Average CETCs (10 highest): 631oF (TRN A); 626oF (TRN B).TH (each RCS loop): 617oF.PZR pressure: 2235 psig (all channels).Case 2: Unit 1 Tripped from 100% power.A loss of offsite power occurred (1 hour ago).The crew is performing 1BwEP ES-0.2 Natural Circulation Cooldown.Average CETCs (10 highest): 505oF (both Trains) RISING.RCS WR pressure: 680 psig STABLE.In regard to the cases above…

A. In Case 1 the CETCs are indicating abnormally high.In Case 2 indications are consistent with natural circulation occurring.

B. In Case 1 the CETCs are normal.In Case 2 indications are consistent with natural circulation occurring.

C. In Case 1 the CETCs are normal.In Case 2 indications are NOT consistent with natural circulation occurring.

D. In Case 1 the CETCs are indicating abnormally high.In Case 2 indications are NOT consistent with natural circulation occurring.

#5. Given:- Unit 1 is in a refueling outage.- Spent fuel is being unloaded from the core and moved into the spent fuel pool.- The following indications just occurred:- Annunciator 1-1-A1 SPENT FUEL PIT PUMP TRIP is in alarm.- Annunciator 1-1-B1 SPENT FUEL PIT TEMP HIGH is in alarm.- Local reports include a rise in humidity in the Fuel Handling Building.The alarms and reports meet at least one entry condition for…

A. ONLY 1BwOA Refuel-1 FUEL HANDLING EMERGENCY.

B. BOTH 1BwOA Refuel-1 FUEL HANDLING EMERGENCY and 0BwOA Refuel-3 LOSS OF SPENT FUEL PIT COOLING.

C. ONLY 1BwOA Refuel-2 REFUELING CAVITY OR SPENT FUEL POOL LEVEL LOSS UNIT 1.

D. ONLY 0BwOA Refuel-3 LOSS OF SPENT FUEL PIT COOLING.

#6. Given:- A Unit 1 plant heatup is in progress.- ALL Unit 1 MSIVs are CLOSED.- 1MS019A SG 1A ATMOSPHERIC RELIEF ISOLATION valve is CLOSED.At what pressure will steam flow FIRST be indicated on the 1A steam generator?

A. 1115 psig.

B. 1175 psig.

C. 1190 psig.

D. 1205 psig.

#7. Given:- Unit 1 at 100% power.In accordance with 1BwGP 100-3 POWER ASCENSION Unit One Main Condenser Hotwell level control at this power level is selected to the __(1)_ side where the CB pump recirculation and FW High Pressure cleanup physical connections are located. This method of control uses the _(2)__.

A. (1) West (2) highest controlling side to prevent damage to the LP Turbines.

B. (1) East (2) lowest controlling side to prevent cavitation of the CD pumps.

C. (1) West(2) lowest controlling side to prevent cavitation of the CD pumps.

D. (1) East(2) highest controlling side to prevent damage to the LP Turbines.

#8. Given:- Unit One is at 100% power.- Blowdown is established on ALL SGs with blowdown sampling in progress.- The RM-11 just alarmed and the NSO notes the following on Grid 1:1PR08J SG BLDN: DARK BLUE Based on this indication the crew will verify the automatic closure of

A. ONLY the 1PS179A-D Steam Generator Blowdown sample isolation valves.

B. ONLY the 1SD005A-D Steam Generator Blowdown sample isolation valves.

C. 1SD002A-H Steam Generator Blowdown isolation valves.

D. 1PS179A-D and 1SD005A-D Steam Generator Blowdown sample isolation valves and 1SD002A-H Steam Generator Blowdown isolation valves.

#9. Given:- Unit One is at 100% power.- The 0B Gas Decay Tank reached its maximum Curie limitation and was isolated.- Subsequently the 0B Gas Decay Tank relief valve inadvertently lifted and is stuck open.Based on this indication

A. ONLY 1/2PR28J Vent Stack Effluent will provide monitoring indication for the release and if the HIGH alarm is reached an interlock will isolate the release.

B. ONLY 1/2PR28J Vent Stack Effluent will provide monitoring indication for the release and if the HIGH alarm is reached NO automatic interlock will isolate the release.

C. 0PR02J Gas Decay Tank Effluent and 1/2PR28J Vent Stack Effluent will provide monitoring indication for the release. If a HIGH alarm occurs on ANY of these radiation monitors an interlock will isolate the release.

D. 0PR02J Gas Decay Tank Effluent and 1/2PR28J Vent Stack Effluent will provide monitoring indication for the release. A HIGH alarm on any of these radiation monitors will NOT actuate an interlock to isolate the release.

#10. The sample pump on the 0PR035J MCR Turbine Building Intake radiation monitor can be operated (started or stopped) LOCALLY

A. ONLY.

B. and from its RM-23 ONLY.

C. and from either RM-11 ONLY.

D. and from BOTH RM-11 units and its RM-23.

#11. Given:- Unit 1 at 100% power steady-state.Case 1: 1CC9414 CC FROM RC PUMPS ISOL VLV inadvertently closed and will NOT reopen.Case 2: 1CC9438 CC FROM RC PUMPS THERM BARR ISOL VLV inadvertently closed and will NOT reopen.Comparing the two cases

A. motor bearing temperatures will NOT CHANGE in either case. RCP seal outlet temperatures will RISE in BOTH cases.

B. motor bearing temperatures will RISE ONLY in Case 1. RCP seal outlet temperatures will RISE ONLY in Case 1.

C. motor bearing temperatures will RISE ONLY in Case 1. RCP seal outlet temperatures will NOT CHANGE in Case 1.

D. motor bearing temperatures will NOT CHANGE in either case. RCP seal outlet temperatures will RISE ONLY in Case 2.

#12. Given:- Unit 1 is in MODE 5.- At time T = 0 seconds the 1D RCP breaker was closed from the MCR.- The following 1D RCP observations are made over the next 40 seconds:Parameter 0.5 sec 1 sec 1.8 sec 30 sec 35 sec 40 secMotor Vibration 0.22 in/sec 0.22 in/sec 0.10 in/sec 0.10 in/sec 0.10 in/sec 0.10 in/secMotor Current 1200 amps 1200 amps 900 amps 755 amps 720 amps 500 ampsShaft Rotation Stationary Stationary Rotating Rotating Rotating RotatingBased on the above data the crew

A. should have tripped the 1D RCP at 1 second due to lack of shaft rotation.

B. completed a proper start of the 1D RCP.

C. should have tripped the 1D RCP at 35 seconds due to motor current.

D. should have tripped the 1D RCP at 1 second due to excessive vibration.

#13. Given:- Unit 1 is 100% power.- Pressurizer Pressure control is selected to 1PT-455.- Pressurizer Level control is selected to 1LT-459.- The 1A Regen Heat Exchanger is in service.- Instrument Bus 111 just de-energized due to a ground fault.As a result

A. the crew must select a different controlling Pressurizer Pressure channel.

B. the crew must select a different controlling Pressurizer Level channel.

C. 1CV8324A CHG TO REGEN HX 1A ISOL VLV will fail closed and can NOT be reopened from the MCR due to loss of solenoid power.

D. 1CV112A LTDWN TO VCT OR HUT DIVERT VLV will NOT full divert to the HUT based on VCT level channel 185.

#14. Given:- Unit 1 at 100% power.- 120 gpm letdown is in service.- RCS boron concentration is 540 ppm.- The current B10 Ratio Fraction is 0.185.- Unit 1 BAT boron concentration is 7200 ppm.The boric acid flow controller 1FK-110 potentiometer setting required to ensure that automatic VCT makeup maintains RCS Tave stable is

A. 0.90.

B. 2.09.

C. 2.25.

D. 2.42.

#15. Given the following sequence of events:- Unit 1 was at 100% power normal alignment.- An RCS LOCA and auto SI occur.- 1A RH pump tripped and will NOT re-start.- All other equipment functioned as designed.The crew has just completed ALL steps of 1BwEP ES-1.3 TRANSFER TO COLD LEG RECIRCULATION.With the 1A RH pump unavailable the cold leg recirc alignment status of the U1 CV pumps will be…

A. ONLY the 1B CV pump running with supply from SI Pumps suction cross-tie header via 1SI8924 SI AND CV PMPS SUCT HDR XTIE VLV.

B. BOTH CV pumps running with supply from 1B RH Pump discharge via 1CV8804A RH HX 1A TO CV PMP SUCT ISOL VLV.

C. BOTH CV pumps running with supply via 1CV112D/E RWST TO CHG PMPS SUCT VLV.

D. BOTH CV pumps running with supply from 1B RH Pump discharge via 1SI8804B RH HX 1B TO SI PMP SUCT ISOL VLV.

#16. Given:- Unit 1 experienced a LOCA in each of the following cases.- In BOTH cases the crew has entered 1BwEP ES-1.3 TRANSFER TO COLD LEG RECIRCULATION.Case 1: Containment Pressure is 6 psig and rising.Case 2: Containment Pressure is 3 psig and stable.The difference in the two cases is that

A. Case 1 requires a higher indicated containment floor water level to implement cold leg recirculation due to the higher water temperature reducing the NPSH available for ECCS recirculation.

B. Case 1 requires a higher indicated containment floor water level to implement cold leg recirculation due to the higher environmental temperature effects on containment floor water level instrumentation accuracy.

C. Case 2 requires a higher indicated containment floor water level to implement cold leg recirculation due to the lower overpressure reducing the NPSH available for ECCS recirculation.

D. BOTH cases require the same indicated containment floor water level to implement cold leg recirculation due to minimal change in instrumentation accuracy between the two cases.

#17. Given:- Unit 1 initially at 100% powerWhich of the following will result in PRT level staying constant?

A. Inadvertent SI.

B. SMALL Break LOCA (RCS stabilizes at 500 psig).

C. LARGE break LOCA (RCS pressure equalizes with the Containment).

D. Inadvertent Phase A.

#18. Given:- Unit 1 is in mode 4.- 1A RH train is aligned for shutdown cooling with RH letdown in service.- 1A CC pump is RUNNING.- 1B CC pump is in standby.- 1D RCP is running.- U-0 CC pump is mechanically AND electrically aligned to Bus 142.- The crew is maintaining RCS temperature stable (1RH606 at 50% demand) at 300oF.- PZR level is 26%.The following timeline then occurs: 0 sec: 1A CC pump TRIPS on overcurrent.2 sec: A crew member places the 1B CC pump control switch to START but the pump breaker closes and immediately trips open. 4 sec: 1B CC pump is placed in pull-out.5 sec: 1PI-CC107 CC PUMP DSCH PRESS indicates 85 psig dropping.Assume the U-0 CC pump functions as designed.Based on the above conditions the U-0 CC pump …

A. did NOT start.

B. started at 4 sec.

C. started at 5 sec.

D. started at 9 sec.

#19. Given:- DC power to Inverter 113 was lost 2 hours ago.- Unit 1 at 100% power.- 1PT-455 failed low 2 minutes ago.- The crew just entered 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL. – A loss of offsite power occurs.The crews NEXT actions will address

A. verification of a reactor trip with NO safety injection.

B. verification of a reactor trip with a safety injection.

C. verification that all safe shutdown loads started and the unit is stable at 100% power.

D. stabilization of the unit from an OTT runback.

#20. Given:- Unit 1 is preparing to conduct a reactor startup per 1BwGP 100-2 PLANT STARTUP.- Both reactor trip breakers are CLOSED.- Due to a concern with SRNI N31 the startup has been suspended.- Control Bank A is at 113 steps.- SRNI N32 indicates 55 cps.- IMD has placed the LEVEL TRIP BYPASS switch for N31 in BYPASS per a troubleshooting plan.Which of the following can be performed WITHOUT causing a reactor trip?

A. removing N31 instrument power fuses.

B. removing N31 control power fuses.

C. de-energizing instrument bus 111.

D. de-energizing instrument bus 112.

#21. During a loss of offsite power (LOOP) a loss of which of the following would prevent 1B CC and 1B SX pumps from sequencing on to perform their safety function?

A. Bus 132X.

B. DC bus 114.

C. Instrument bus 112.

D. Instrument bus 114.

#22. Given:- Unit 1 at 100% power.- CNMT CHILLER 1A is running.- 1WO01PA CHILLED WATER Pump 1A just tripped due to an internal ground.As a result of the chilled water pump trip CNMT CHILLER 1A will

A. remain running. 1WO01PB CHILLED WATER Pump 1B will automatically start to

support CNMT CHILLER 1B.B. trip. The crew will start 1WO01PB CHILLED WATER Pump 1B and then restart CNMT CHILLER 1A.

C. trip. The crew will start 1WO01PB CHILLED WATER Pump 1B and then start CNMT CHILLER 1B.

D. remain running. The crew will start 1WO01PB CHILLED WATER Pump 1B to support continued operation of CNMT CHILLER 1A.

#23. Given:- Unit 1 at 100% power all systems normally aligned.- Local investigation has determined the breaker for 1CS019B EDUC 1B SPRAY VLV is TRIPPED and will NOT reclose.- 1CS019B has been locally verified to be in its normal position at full power.With the above conditions if a U1 CS Signal is actuated the 1B CS pump will:

A. NOT automatically start and CANNOT be manually started from the MCR with suction aligned from the RWST.

B. automatically start and provide spray flow WITHOUT NaOH.

C. automatically start and provide spray flow WITH NaOH.

D. NOT automatically start but CAN be manually started from the MCR and provide spray flow from the RWST.

#24. Given:- Both units were at 100% power.- A fire in the MCR has occurred.- The crew is implementing 1BwOA PRI-5 and 2BwOA PRI-5 CONTROL ROOM INACCESSIBILITY.(1) LOCAL Equipment Operator/Reactor Operator actions include(2) What if any is/are the impact(s) of this/these actions?

A. (1) aligning local Containment Spray control switch control from each unit-specific Remote Shutdown Panel. (2) Automatic Containment Spray actuation for ALL Containment Spray trains is inhibited by this action.

B. (1) aligning local Containment Spray control switch control from each unit-specific Remote Shutdown Panel. (2) Automatic Containment Spray actuation for ALL Containment Spray trains remains available.

C. (1) pulling control power fuses for ONLY ONE Containment Spray pump on each unit. (2) If the automatic Containment Spray actuation setpoint and coincidence are reached ONE Containment Spray train will actuate on the affected unit.

D. (1) pulling control power fuses for ALL Containment Spray pumps. (2) If the automatic Containment Spray actuation setpoint and coincidence are reached NO Containment Spray trains will actuate on either unit.

#25. Given:- At 14:45 Unit 1 experienced a SGTR on 1D SG from full power.- The crew implemented appropriate emergency procedures and is now conducting a plant cooldown per 1BwEP ES-3.1 POST-SGTR COOLDOWN USING BACKFILL.- The following data has been recorded on 1BwOSR 3.4.3.1 RCS PRESSURE/TEMPERATURE LIMIT SURVEILLANCE and 1BwOS TRM 3.4.c.1 PRESSURIZER TEMPERATURE LIMIT SURVEILLANCE.1BwOSR 3.4.3.1__ _1BwOS TRM 3.4.c.1Loop A Cold Temp (F) Rate Temp Change PZR Rate Temp ChangeTime Leg Temp Change (F/hr) in 1 hr Period Water Temp (F/hr) in 1 hr Period1500 557F 0 0 0 650 0 01515 485F 72 288 72 581 276 691530 480F 5 20 77 540 164 1101545 479F 1 4 78 535 20 1151600 450F 29 116 107 530 20 1201615 430F 20 80 55 524 24 571630 425F 5 20 55 520 16 201645 420F 5 20 59 518 8 171700 418F 2 4 32 516 8 14The FIRST time a Tech Spec or TRM cooldown limit was exceeded was _(1) on the (2)_.

A. (1) 1515(2) PZR and RCS.

B. (1) 1530(2) PZR ONLY.

C. (1) 1515(2) RCS ONLY.

D. (1) 1600(2) RCS ONLY.

#26. Given:- Unit 1 is at 62% power (780 Mwe) ramping toward 100% power.- The 1A Motor Driven FW pump is out of service.- The 1C TDFWP just tripped.- Annunciator 1-16-E1 FW PUMP NPSH LOW is in ALARM.- The BOP confirms that an NPSH actuation has occurred.Expected plant response includes

A. rising GS condenser pressure. The crew must reduce turbine load at least 80 Mwe.

B. lowering GS condenser pressure. The crew must reduce turbine load at least 80 Mwe.

C. rising GS condenser pressure. The crew is NOT required to reduce turbine load.

D. lowering GS condenser pressure. The crew is NOT required to reduce turbine load.

#27. Given:- Case 1- Unit 1 is at 100% power.- The potentiometer at 1PM06J for 1AF005A 1A SG FLOW CONT VLV failed to a value of 50%.- Case 2- A fire required MCR evacuation.- The potentiometer at 1PL04J for 1AF005A 1A SG FLOW CONT VLV failed to a value of 50%.- The 1AF005A Local-Remote switch at 1PL04J is placed in LOCAL.The 1AF005A

A. response in Case 1 and 2 are identical BEFORE AND AFTER a 1A AF pump start.

B. remains FULL OPEN in Case 1 until the 1A AF pump starts then THROTTLES flow to maintain a constant flowrate. In Case 2 the 1AF005A THROTTLES to 50% open and remains in that position.

C. response in Case 1 and 2 are identical BEFORE a start of the 1A AF pump. In Case 1 1AF005A THROTTLES flow to a constant flowrate AFTER a 1A AF pump start.

D. CLOSES fully in Case 1 until the 1A AF pump starts then THROTTLES flow to a constant flowrate. In Case 2 the 1AF005A THROTTLES to 50% open and remains in that position.

#28. Given:- The Unit 1 reactor is at full power.- A grid problem has JUST lowered ESF bus 141 & 142 voltage to 3700 volts (at time = 0 seconds).With NO operator action and ESF bus 141 & 142 voltages remaining at 3700 volts until the plant responds to this condition what is the SEQUENCE of events that will occur before the ESF bus loads are sequenced on?

A. The D/Gs start ~ 310 seconds LATER (at time = 310 seconds) then the ESF buses are deenergized followed by the D/Gs energizing the ESF buses.

B. The D/Gs start IMMEDIATELY (at time = 0 seconds) then the ESF buses are deenergized followed by the D/Gs energizing the ESF buses.

C. The ESF buses are deenergized IMMEDIATELY (at time = 0 seconds) then the D/Gs start and energize the ESF buses.

D. The ESF buses are deenergized ~ 310 seconds LATER (at time = 310 seconds) then the D/Gs start and energize the ESF buses.

#29. Given the following conditions (consider each independently):1 – Battery charger 111 DC output breaker CB-2 TRIPPED2 – Battery to bus feed breaker AF-2 TRIPPED3 – Bus 131X Voltage Low alarmThe condition(s) that would cause 125VDC Battery Charger 111 AC input breaker CB-1 to open is/are

A. 1 ONLY.

B. 1 and 2 ONLY.

C. 2 ONLY.

D. 1 2 and 3.

#30. Given:- Unit 1 at 100% power.Consider each event separately:- Event 1: Loss of DC bus 111.- Event 2: SAT 142-1 fault with a Bus 158 ABT failure.- Event 3: SAT 142-1 fault with a Bus 156 ABT failure.Of the events listed _______ result(s) in a Mode change within 1 hour.

A. ONLY event 1

B. ONLY events 1 and 2

C. ONLY events 1 and 3

D. events 1 2 and 3

#31. Given:- Unit 1 is at 100% power.- Major external corrosion and leakage have been discovered on the 1A and 1C EDG Fuel Oil Storage Tanks.- Both tanks are isolated and drained.As a result ________ meet the Technical Specification requirements for Diesel Fuel Oil.

A. NEITHER the 1A nor the 1B EDG

B. ONLY the 1A EDG does NOT

C. ONLY the 1B EDG does NOT

D. BOTH the 1A and 1B EDGs still

#32. Given:- Both Units were at 100% power.- A tornado swept through the switchyard causing a loss of offsite power (LOOP).- BOTH reactors tripped.- Unit 2 experienced a loss of all AC power.- Bus 141 is now supplying bus 241.The following indications have been present for the past 2 hours:1JI-DG002 DIESEL GEN 1A OUTPUT WATTS: 6100 KW1II-DG001 DIESEL GEN 1A OUTPUT CURRENT: 1010 AMPS1II-AP053 BUS 241 FEED TO BUS 141 CURRENT: 930 AMPSBased on the readings provided

A. NO limits are exceeded.

B. the limits on EDG current AND bus cross-tie current are exceeded.

C. the limits on EDG Watts AND bus cross-tie current are exceeded.

D. the limits on EDG Watts AND EDG output current are exceeded.

#33. Given:- You are in the process of performing a Gaseous Release of 0A GDT.- Concurrently a High Rad bag of material must be moved past 0PR02J GAS DECAY TANK EFFLUENT RADIATION MONITOR.Given:- ONLY one of the below cases will result in automatically terminating the release due to moving the Hi-Rad bag past the monitor.- Case 1: walking 1 meter away from 0PR02J with a 5 second transit time.- Case 2: walking 2 meters away from 0PR02J with a 20 second transit time.- Case 3: walking 3 meters away from 0PR02J with a 1 minute transit time.- Case 4: walking 5 meters away from 0PR02J with a 5 minute transit timeConsider the bag a point source.The release will automatically be terminated during Case

A. 1.

B. 2.

C. 3.

D. 4.

#34. Given:- Unit 1 at 100% power.- The NSO selects Grid 1 on the RM-11 and notes the following:- 1PR08J SG BLDN radiation monitor indicates White.- 1PR27J SJAE GS EXH radiation monitor indicates Magenta.- All OTHER process radiation monitors indicate Green.Grid one indicates that the 1PR08J status is (1) and 1PR27J is (2).

A. (1) Communications Failure(2) Monitor Poll Status

B. (1) Equipment Failure(2) Control Function

C. (1) Control Function(2) Equipment Failure

D. (1) Monitor Poll Status(2) Communications Failure

#35. Given:- BOTH units are at 100% power.- The 0B MCR Ventilation train is in service. – The 2A Containment Chiller is in service.- Unit 0 CC Hx is aligned to Unit 1.- 1SX005 CC HX 0 Inlet Valve is OPEN.- 2SX005 CC HX 0 Inlet Valve is CLOSED.- 2A SX pump is OOS for bearing replacement.- 1A SX pump is running.- 2B SX pump recently tripped.In response

A. the 2A Containment Chiller will trip. The crew will start the 1B SX pump shutdown ONE RCFC train on EACH unit isolate SX to the shutdown RCFCs then OPEN 2SX005 CC HX 0 Inlet Valve.

B. the 2A Containment Chiller will trip. The crew will start the 1B SX pump and then OPEN 2SX005 CC HX 0 Inlet Valve.

C. OB VC chiller will trip. The crew will start the 1B SX pump shutdown ONE RCFC train on EACH unit isolate SX to the shutdown RCFCs then OPEN 2SX005 CC HX 0 Inlet Valve.

D. OB VC chiller will trip. The crew will start the 1B SX pump and then OPEN 2SX005 CC HX 0 Inlet Valve.

#36. Given the following plant conditions on Units 1 & 2:- The U-1 SAC has just been made available (clearance order recently cleared).- The crew is preparing to start the U-1 SAC per BwOP SA-1 S TARTUP AND OPERATION OF STATION AIR COMPRESSORS.- The U-0 and the U-2 SACs are NOT available for a start.- IA pressure is currently 35 psig on the MCB.- Local control cabinet supply pressure for the U-1 SAC indicates 28 psig (due to a large leak that has been temporarily repaired).Under these conditions a Nitrogen bottle (1) be procedurally required to be used for the U-1 SAC startup and the U-1 SAC (2) .

A. (1) will(2) can be started locally or in the MCR.

B. (1) will(2) can ONLY be started in the MCR.

C. (1) will NOT(2) can be started locally or in the MCR.

D. (1) will NOT(2) can ONLY be started in the MCR.

#37. Given:- Unit 1 was at 25% power in a normal alignment for this power level.- A large plant transient has just occurred.With the above conditions which of the following MCR indications would procedurally require an immediate reactor trip?

A. 1PI-GS001 GS SUP HDR PRESS at 1PM02J indicates 40 psig.

B. 0PI-IA007 INST AIR HDR PRESS at 0PM01J indicates 50 psig

C. 1PI-HY005A MAIN GEN H2 PRESS at 1PM02J indicates 60 psig.

D. 0PI-SA006 SERV AIR HDR PRESS at 0PM01J indicates 70 psig.

#38. Given:- Unit 2 is in MODE 3 preparing for a reactor startup.- All Shutdown banks are withdrawn.- Redundant Steam Pressure instrumentation failures resulted in an inadvertent safety injection.- Both malfunctioning Steam Pressure channels are failed LOW.Subsequently:- Five minutes later the crew has depressed BOTH SI RESET pushbuttons.Regarding restoration of the normal containment cooling alignment (RCFCs and Containment Chillers)

A. Phase A must be reset.

B. no additional ESF actuations are required to be reset.

C. operators must place the STM LIME SI RESET/BLOCK switches (A and B train) to BLOCK. BOTH SI RESET pushbuttons must be depressed a second time. Resetting Phase A is NOT required.

D. operators must place the STM LIME SI RESET/BLOCK switches (A and B train) to BLOCK. BOTH SI RESET pushbuttons must be depressed a second time. Resetting Phase A is then required.

#39. Given:- Unit One at 100% power.- 1BwOSR 3.3.1.4-1 SSPS REACTOR TRIP BREAKER AND REACTOR TRIP BYPASS BREAKER SURVEILLANCE (TRAIN A) testing is in progress.- The last manipulation results in the following reactor trip/bypass breaker indications at 1PM05J:Note: Color Indications:- Bypass Permissive Status Light P4 RX TRIP is fast flashing after acknowledgment.- PRNIs N41-N44 ALL indicate 5% dropping.- ALL rod bottom lights are lit.- IRNI SUR is negative.Of the following the NEXT procedurally required action is to

A. check SI status.

B. go to 1BwFR-S.1 RESPONSE TO NUCLEAR POWER GENERATION/ATWS.

C. verify ALL turbine throttle and governor valves CLOSED.

D. manually trip the reactor.

#40. Given the following plant conditions on Unit 1:- The crew is responding to a reactor trip and SI.- 1BwEP-1 “LOSS OF REACTOR OR SECONDARY COOLANT” is in progress at step 2.- PZR level has risen continuously.- RCS pressure has dropped continuously.Based on these conditions the failure is a leak through the

A. PZR liquid space sample valve.

B. charging header connection to the RCS loop.

C. PZR connection to a safety valve.

D. 1B RCS hot leg valve body.

#41. Given:- Unit One initially at 100% power.- The 1A CV pump was OOS.- A LOCA occurred 10 minutes ago.- Bus 142 is faulted.- Containment pressure just peaked at 21 psig.- RCS pressure is 520 psig and STABLE.- RWST level is 75% and dropping at 0.3% per minute.- Assume all equipment responds as designed with the aforementioned exceptions.Of the following the parameter that is expected to RISE over the next five minutes is

A. RCP 1A Seal Outlet Temperature.

B. VCT Temperature.

C. Unit 1 CC HX Outlet Temperature.

D. Containment Chilled Water Expansion tank level.

#42. Given:- Unit 1 at 100% power.- 1B RCP #1 Seal Leakoff reads 6.8 gpm.- 1B RCP #2 Seal Leakoff has been reported at 1.4 gpm.- Other RCP parameters are initially normal.Based on the above conditions which ONE of the following correctly describes the required operator actions?

A. Immediately trip the reactor AND then trip the 1B RCP.

B. Immediately trip the reactor AND trip the 1B RCP ONLY if the #2 seal Leakoff DROPSto < 0.2 gpm.

C. Initiate a plant shutdown AND trip the affected RCP within 8 hours.

D. Operation may continue however operators will have to trip the reactor AND 1B RCP if #1 Seal Leakoff RISES to > 8 gpm.

#43. Given:- Unit 1 is in MODE 3.- 1BwGP 100-1 Plant Heatup is in progress. – 1SI8808A-D SI Accumulator Isolation Valves are being restored to their normal at power alignment.- 1A CV pump is RUNNING.- The following then occurs:- 1A CV pump TRIPs.- The crew has implemented 1BwOA PRI-15 Loss of Normal Charging.- NO abnormal charging system indications were observed prior to the 1A CV pump trip. The crew will

A. vent the 1B CV pump BEFORE starting it to prevent gas binding.

B. throttle 1CV121 in manual to 5% demand BEFORE starting the 1B CV pump to provide adequate line resistance.

C. send a NSO to start the Auxiliary Oil Pump BEFORE starting the 1B CV pump to ensure proper lubrication.

D. start the 1B CV pump with 1CV121 FULL OPEN to minimize the time period with no charging flow.

#44. Given:- Unit 1 PZR is solid.- RCS temperature is 120oF.- RCS pressure is 100 psig.- The 1A RH train is operating in the shutdown cooling mode.- All Narrow Range SG levels are 20%.- 1RY8000A and B PORV ISOL VLVs are closed and de-energized.In this situation

A. the 1B RH train is aligned for shutdown cooling to allow the 450 psig suction relief to meet RCS overpressure protection requirements of LCO 3.4.12 Low Temperature Overpressure Protection.

B. the 1B RH train is aligned for shutdown cooling to meet LCO 3.4.7 RCS Loops MODE 5 (Loops Filled) requirements for OPERABLE loops.

C. normal letdown is aligned to allow the 600 psig relief to meet RCS overpressure protection requirements of LCO 3.4.12 Low Temperature Overpressure Protection.

D. at least one SG NR level must be raised to meet LCO 3.4.7 RCS Loops MODE 5 (Loops Filled) requirements for OPERABLE loops.

#45. Given:- Both units at 100% power.- The 0 CC HX and pump are aligned to Unit 2.Subsequently:- A CC system malfunction has resulted in placing ALL CC pumps aligned to Unit 2 in PTL.The current situation has resulted in

A. no effect on Unit 1.

B. a loss of CC flow capability to the Unit 1 RCPs.

C. a loss of CC flow capability to the 1A RH train.

D. a loss of ALL CC flow capability to spent fuel pool cooling.

#46. Given:- Unit 1 is at 100% power.- 1PK-455A Master PZR Pressure Controller output failed as is.- 1PK-455A will NOT transfer to Manual control.- A grid loss results in a rapid runback to 70% power.- The US directs the RO to manually operate Pressurizer Pressure controls during the runback.- Current parameters are as follows:- PZR Level 66% – PZR Pressure 2280 psig The RO will

A. turn OFF all heaters and initiate spray flow to compensate for the initial insurge.

B. turn ON all backup heaters and initiate spray flow to compensate for the initial insurge.

C. turn ON all backup heaters and CLOSE both Pressurizer spray valves to compensate for the initial outsurge.

D. turn OFF ONLY the backup heaters and fully OPEN both Pressurizer spray valves to compensate for the initial outsurge.

#47. Given:- Unit 1 has experienced a SGTR on the 1A SG.- Failures of BOTH SI and CV pumps occurred during the event.- The initial RCS cooldown has been completed.- The TSC has expressed concern that the RCS is experiencing reflux boiling.NOTE:- 1BwCA-3.1: SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED- 1BwCA-3.2: SGTR WITH LOSS OF REACTOR COOLANT-SATURATED RECOVERY DESIRED- 1BwEP-3: STEAM GENERATOR TUBE RUPTUREIf the TSC is correct the RCS is/has

A. lost natural circulation. The mitigating strategies in 1BwCA-3.1 and/or 1BwCA-3.2 apply.

B. continuing natural circulation. ONLY the mitigating strategies in 1BwEP-3 apply.

C. continuing natural circulation. The mitigating strategies in 1BwCA-3.1 and/or 1BwCA3.2 apply.

D. lost natural circulation. ONLY the mitigating strategies in 1BwEP-3 apply.

#48. Given:- Unit 2 at 100% power.Subsequently:- A fault occurred on the 2B SG inside containment.- ALL MSIVs failed to close.- Currently:- AFW flow is 45-50 gpm per SG.- ALL NR SG levels are 0%.- ALL WR SG levels are 30-40%.- Containment pressure is 18 psig dropping.- ONLY the 2A Train CS train actuated and is running.- The crew is implementing 2BwCA-2.1 UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS Step 4 Check Pzr PORVs and Isolation Valves.- 2BwFR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK was previously entered and exited.- 2MS001B Loop 2B MSIV just closed.- 2MS001A 2MS001C and 2MS001D MSIVs remain OPEN.- 2A 2C and 2D SG pressures are 70 psig and rising.In response to this event the crew will

A. IMMEDIATELY transition to 2BwFR-H.1 and initiate bleed and feed.

B. complete letdown restoration then transition to 2BwFR-H.1 and initiate bleed and feed.

C. IMMEDIATELY transition to 2BwEP-2 FAULTED STEAM GENERATOR ISOLATION.

D. complete letdown restoration then transition to 2BwEP-2 FAULTED STEAM GENERATOR ISOLATION.

#49. Given:- Unit 2 at 100% power.- The crew is implementing 2BwOA SEC-1 SECONDARY PUMP TRIP in response to a loss of the 2B FW pump.- A turbine runback was initiated.(1) In response to this event a reactor trip is most likely to occur as a result of (2) This is prevented by …

A. (1) Lo-2 SG level. (2) starting the standby HD pump.

B. (1) high Pressurizer water level. (2) initiating a boration concurrent with initiating the runback.

C. (1) high Pressurizer water level. (2) ensuring rod control is in automatic.

D. (1) Lo-2 SG level. (2) matching FW flow and steam flow on each SG.

#50. Given:- Unit 1 has experienced a Loss of All AC Power.- The crew is performing the immediate actions of 1BwCA-0.0 LOSS OF ALL AC POWER.The basis for verifying ALL MSIVs and MSIV bypass valves closed at step 2 is to

A. protect personnel in the turbine building.

B. limit the potential for high differential pressure across the SG tubes.

C. prevent an uncontrolled cooldown of the RCS.

D. protect the Main Condenser from overpressure.

#51. Given:- Unit 1 experienced a reactor trip from full power.- One minute later a loss of offsite power occurred.Currently (90 minutes after the loss of offsite power):- The crew is implementing 1BwEP ES-0.2 NATURAL CIRCULATION COOLDOWN.- RCS pressure is 885 psig.- SG pressures are ALL 763 psig.- CETCs indicate 532oF on 1PM05J.- RCS cold leg temperatures indicate 515.5oF .- SATURATED conditions are indicated in the _(1)_ . – In response operators will (2).

A. (1) reactor vessel plenum.(2) actuate safety injection.

B. (1) SG tubes.(2) repressurize the RCS to collapse the void.

C. (1) reactor vessel plenum.(2) repressurize the RCS to collapse the void.

D. (1) SG tubes.(2) actuate safety injection.

#52. Given:- Unit 1 at 100% power.- Pressurizer Level control is selected to 459/460.- A simultaneous loss of Instrument Bus 111 and the redundant power supply for 1PA01J occurs.In response to this event

A. letdown was unaffected. After an operable Pressurizer level channel is selected Pressurizer level controller 1LK459 will control level in automatic.

B. letdown was unaffected. After an operable Pressurizer level channel is selected Pressurizer level controller 1LK459 will NOT control level in automatic.

C. letdown automatically isolated. After an operable Pressurizer level channel is selected Pressurizer level controller 1LK459 will control level in automatic.

D. letdown automatically isolated. After an operable Pressurizer level channel is selected Pressurizer level controller 1LK459 will NOT control level in automatic.

#53. Given:- Diagnostic monitoring is in progress to locate a suspected 0.5 gpm primary leak.- Normal charging and letdown are aligned with the 1A Regenerative Heat Exchanger in service.- You are monitoring computer points for:- Letdown flow- RCP Seal injection flowSubsequently:- A loss of DC bus 111 occurs.Which of the following indications will you observe on the two computer points?Letdown Flow RCP Seal Flow

A. drops to 0 gpm rising

B. no change rising

C. drops to 0 gpm drops slightly

D. no change drops slightly

#54. Given:- Both Units at 100% power.- Unit 0 CC HX and Pump are aligned to Unit 2.- 1A SX pump is OOS for bearing replacement.- 1B SX pump is running.- 2A SX pump is running.The following sequence of events then occurs:- 2A SX pump TRIPs on overcurrent.- 2B SX pump CANNOT be started.- The crew has implemented 2BwOA PRI-8 Essential Service Water Malfunction.Based on the above conditions PRIOR to OPENING 1SX005 Unit 0 CC HEAT EXCHANGER INLET VLV the crew MUST…

A. ISOLATE SX flow to ONE train of RCFCs on EACH unit.

B. ISOLATE SX flow to BOTH containment chillers on Unit 2.

C. ISOLATE SX flow to ONE AF pump on EACH unit and place the affected AF pumps in PTL.

D. THROTTLE SX flow to BOTH unit specific CC Heat Exchangers.

#55. Given:- Unit 1 at 100% power.- Normal charging aligned to 1B RC loop.- 1A Regenerative HX is aligned.- A malfunction results in isolation of Instrument Air to Unit 1 Containment.Annunciator 1-7-A2 RCP SEAL WTR INJ FLTR P HIGH is in alarm due to the position of

A. 1CV182 CHG HDR BACK PRESS CONT VLV.

B. 1CV8324A CHG TO REGEN HX ISOL VLV.

C. 1CV8146 CHG TO RC LOOP 1B ISOL VLV.

D. 1CV8141A-D RCP 1A-1D SEAL LEAKOFF ISOL VLVs.

#56. Given:- Unit 1 at 100% power in a normal alignment. – 1VI-MP006 MAIN GENERATOR 1 OUTPUT VARS indicates 200 MVAR out.Subsequently:- A grid disturbance results in grid voltage rising.- Power Team reports NO lines were lost and total grid reactive load did NOT change.In response to this event Unit 1 MVAR out

A. rose. To return MVAR load to a STABLE 200 MVAR the crew will take the VOLT adjustor control switch to LOWER.

B. lowered. To return MVAR load to a STABLE 200 MVAR the crew will take the VOLT adjustor control switch to RAISE.

C. did NOT change with the voltage regulator in Automatic. NO adjustment will be necessary.

D. lowered. To return MVAR load to a STABLE 200 MVAR the crew will take the BASE adjustor control switch to RAISE.

#57. Given:- Unit 2 at 90% power.- Control Bank D is at 210 steps with rods in AUTOMATIC control.Which of the following will INITIALLY cause the ROD OUT light to light at 2PM05J?

A. Tref programmer output fails high.

B. Power range N-44 fails low.

C. A loop 2A narrow range cold leg RTD fails high.

D. 2FK-110 BA potentiometer for is set 0.5 turns low followed by auto-makeup.

#58. Given:- Unit 1 at 75%.- PDMS is operable.- During the ramp to 100% power rod H8 in CBD stopped moving at 162 steps (determined NOT mechanically bound-misalignment was determined to exist starting two hours ago).- CBD rods (other than H8) are at 180 steps.- Appropriate Tech Spec actions are in progress.- It is estimated that the CRDM for rod H-8 will be functional in three hours. Per 1BwOA ROD-3 DROPPED OR MISALIGNED ROD to recover the misaligned rod:(1) What will be moved?(2) What is the maximum power level that will allow the recovery to begin?

A. (1) Rod H8(2) 49%

B. (1) The other rods in CBD(2) 49%

C. (1) Rod H8(2) 69%

D. (1) The other rods in CBD(2) 69%

#59. Given:- Unit 2 is performing a plant startup.- At 15% power a rod control malfunction resulted in the crew tripping the unit.- The crew has just manually re-energized the SRNIs. Currently:- BOTH SRNIs indicate 1.5 x 104 cps.- IRNI N35 indicates 5 x 10-11 amps.- IRNI N36 indicates 5 x 10-10 amps.Based on these indications

A. N35 indicates consistent with the SRNIs. The crew responded correctly because N36 indication is consistent with compensating voltage failing high.

B. N35 indicates consistent with the SRNIs. The crew responded correctly because N36 indication is consistent with compensating voltage failing low.

C. N36 indicates consistent with the SRNIs. The crew responded incorrectly because N35 indication is consistent with compensating voltage failing high.

D. N36 indicates consistent with the SRNIs. The crew responded incorrectly because N35 indication is consistent with compensating voltage failing low.

#60. Given:- Unit 1 is in a refueling outage. Which of the following would be the FIRST indication of a malfunction of the portable RCCA change tool dropping an RCCA onto a fuel assembly and causing a loss of cladding integrity?

A. Rising P across the Fuel Handling Building Filter Plenum.

B. Rising P across running Containment Building Charcoal filter units.

C. RM-11 1AR11J Ctmt Fuel Handling Incident in ALARM.

D. RM-11 0AR56J FHB Handling Incident in ALARM.

#61. Given:- A liquid release is in progress.- A faulty valve disc to stem interface results in CW blowdown flowrate dropping to 5200 gpm.In response to this event Monitor 0PR01J as indicated on the RM-11 display OPS101 LIQ RADWASTE 0WX01T will be

A. yellow.

B. grey blue (half cyan)

C. dark blue.

D. light blue (cyan).

#62. Given:- General radiation levels are rising in the Fuel Handling Building.The following timeline applies: (Time annotated in HR:MIN)00:00 0AR55J Fuel Handling Building Incident went into ALERT.00:30 0AR56J Fuel Handling Building Incident went into ALERT.00:40 0AR55J Fuel Handling Building Incident went into ALARM.00:50 0AR56J Fuel Handling Building Incident went into ALARM.In response to this event- 0VA04CA FHB Booster Fan 0A started and the Train A Charcoal Absorber automatically aligned at (1).- 0VA04CB FHB Booster Fan 0B (2).

A. (1) 00:00.(2) started and the Train B Charcoal Absorber automatically aligned at 00:30.

B. (1) 00:00.(2) did NOT start.

C. (1) 00:40.(2) started and the Train B Charcoal Absorber automatically aligned at 00:50.

D. (1) 00:40.(2) did NOT start.

#63. Given the following plant conditions on Unit 1:

– CS actuated during a RCS LOCA.- 1CS007A Pump 1A Hdr Isol Valve remained CLOSED with the 1A CS pump running.- The 1A CS pump control switch (C/S) was JUST placed in PULL OUT.The SEQUENCE of the MINIMUM Control Room actions that are required to initiate 1A CS train flow to the containment are to …A. immediately place the 1A CS test switch in “test” open 1CS007A then place the 1A CS pump C/S in after-trip.

B. immediately open 1CS007A then place the 1A CS pump C/S in after-trip.

C. wait 30 seconds place the 1A CS test switch in “test” open 1CS007A then place the 1A CS pump C/S in after-trip.

D. wait 30 seconds open 1CS007A then place the 1A CS pump C/S in after-trip.

#64. Given:- Unit 1 initially at 100% power.Subsequently:- A reactor trip and loss of offsite power occurred.- The reactor trip occurred 3 hours ago.- Bus 143 and 144 have been re-energized.- The crew is implementing 1BwEP ES-0.4 NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS).- Pressurizer level is 94%.- RCS temperature is 370oF.- 1A CV pump is running.- 1B CV pump is in standby.- Both SI pumps are in standby.- Normal letdown is established. – BOTH Pressurizer PORV control switches are selected to AUTO.The crew action(s) that will restore compliance with a Technical Specification license condition that is NOT CURRENTLY MET is/are to

A. place BOTH SI pumps and ONE CV pump in PULL OUT and administratively control them.

B. reduce pressurizer level.

C. align one RH train to the shutdown cooling mode.

D. place RCS Cold Overpressure Protection in service.

#65. The parameter and criteria that is FIRST evaluated to determine if a RED PATH exists on the INTEGRITY status tree is:Parameter Criteria

A. RCS Hot Leg ANY drop > 100oF in LAST 60 Minutes

B. RCS Hot Leg ALL dropped > 100oF in LAST 60 Minutes

C. RCS Cold Leg ANY drop > 100oF in LAST 60 Minutes

D. RCS Cold Leg ALL dropped > 100oF in LAST 60 Minutes

#66. Given:- A new ILT student assigned to Operations is performing his six month familiarization time.- The new student intends to come into the Main Control Room to observe shift operations. – He intends to walk down the Unit One main control boards including walking on the colored carpeting (Zone of Control) immediately adjacent to the control panels.The student will obtain

A. Shift Manager permission prior to entering the MCR. Once this permission is obtained the student has unlimited access to the control room as a member of the crew.

B. Shift Manager permission prior to entering the MCR. The Unit One Unit Supervisor OR Unit One Reactor Operator may authorize the control board walkdown in the Zone of Control.

C. permission from the WEC Supervisor prior to entering the MCR. Both the Unit One Unit Supervisor AND Unit One Reactor Operator must authorize the control board walkdown in the Zone of Control.

D. permission from the WEC Supervisor prior to entering the MCR. ONLY the Unit One Reactor Operator may authorize the control board walkdown in the Zone of Control.

#67. During the 1st quarter of the year an NSO took the shift as the Unit NSO as indicated below:Jan. 03 2012 – 8 hours plus turnovers.Jan. 13 2012 – 12 hours plus turnovers.Feb. 01 2012 – 8 hours plus turnovers.Mar. 25 2012 – 12 hours plus turnovers Mar. 31 2012 – 8 hours plus turnovers.The NSO was on medical leave from April 15 2012 through July 30 2012.This NSO’s license became INACTIVE on __ because more 8 hour shift(s) was/were required to maintain an active license.

A. April 1 2012 one

B. April 1 2012 two

C. July 1 2012 six

D. July 1 2012 seven

#68. Given:- Unit 1 at 26% power.- The crew is performing a plant startup following a forced outage near the end of a fuel cycle.- Steam dumps are in the Tave mode.Subsequently:- The main turbine trips.Assuming NO operator action and that all equipment operates as designed

A. Unit 1 reactor trips. Steam Dumps maintain Tave at 557oF.

B. control banks A-D drive inward and eventually fully insert making the reactor subcritical. Steam dumps open and then close at 550 oF and remain closed.

C. control banks A-D drive inward until Tave is within 1oF of Tref and then stop. Steam dumps open but then close when Tave is 560 oF. The reactor remains critical between the POAH and 1% power.

D. control banks A-D drive inward and eventually fully insert making the reactor subcritical. Steam dumps open intermittently and maintain Tave at approximately 560 oF.

#69. – The Reactor Core Safety Limits in section 2.0 of Technical Specifications include limits on __(1)_.- The functioning of the (2)___ are credited to AUTOMATICALLY preserve the Reactor Core Safety Limits.

A. (1) Highest Loop Tave.(2) Main Steam Safety Valves AND RPS

B. (1) Average of the 10 highest CETCs.(2) ONLY the Main Steam Safety Valves

C. (1) Highest Loop Tave.(2) ONLY the Main Steam Safety Valves

D. (1) Average of the 10 highest CETCs.(2) Main Steam Safety Valves AND RPS

#70. Given:- Unit 1 is at 10% power- A plant transient occurs resulting in the following: – Loop 1A Tave = 550 oF.- Loop 1B Tave = 551 oF.- Loop 1C Tave = 549 oF.- Loop 1D Tave = 550 oF.Under these conditions Technical Specifications require the crew to

A. immediately open the reactor trip breakers.

B. take no specific action.

C. restore RCS Tave within 30 minutes.

D. verify shutdown margin is within the limits of the COLR within 1 hour.

#71. Given:- Both units are at full power normal alignment.- The 0A VC train is in standby.- The 0B VC train is in normal operation.The following occurs:- An event that has the potential for an accidental radioactive release in the Unit 2 Auxiliary Building is reported to the MCR. – The MCR SRO directs an RO to monitor control room intake air for elevated radiation trends.- The RO notes all MCR rad monitor icons on the RM-11 GRID 2 PROCESS AIR MONITORS are currently GREEN.With the above conditions to monitor control room intake air on the RM-11 the RO will trend the…

A. 0PR31J or 0PR32J OUT AIR IN.

B. 0A0PR33J or 0PR34J OUT AIR IN 0B.

C. 0PR35J or 0PR36J TURB AIR IN 0A.

D. 0PR37J or 0PR38J TURB AIR IN 0B.

#72. Given:- A RCS LOCA resulted in core damage on Unit 1.Which ONE of the following correctly describes the evolution that constitutes the LEAST potentialfor RAISING radiation levels in the Auxiliary Building?

A. placing one train of Unit 1 RH in service per BwOP RH-6 PLACING THE RH SYSTEM IN SHUTDOWN COOLING.

B. restarting one reactor coolant pump per 1BwOA ESP-1 REACTOR COOLANT PUMP STARTUP DURING ABNORMAL CONDITIONS without unisolating seal return.

C. implementing 1BwOA ESP-2 REESTABLISHING CV LETDOWN DURING ABNORMAL CONDITIONS.

D. implementing 1BwEP ES-1.3 TRANSFER TO COLD LEG RECIRCULATION.

#73. Given:- BOTH Units are at 100% power all systems are normally aligned.- The Unit 1 Unit Supervisor receives a report from the NRC via the red ENS phone that an airborne threat is PROBABLE.- The crew has implemented 0BwOA SECURITY-1 Security Threat.Based on the EXISTING threat status AND assuming it is safe to send personnel into the plant which ONE of the following correctly describes an action the crew will perform as directed by 0BwOA SECURITY-1?

A. Immediately trip BOTH units.

B. Start the in-service VC Train Makeup Filter unit.

C. Start all emergency diesel generators.

D. Initiate a rapid downpower of BOTH units.

#74. Given:- Unit 1 experienced a loss of all AC power.- 1BwCA-0.0 LOSS OF ALL AC POWER is in progress at step 10.- STA informs the US of the following Status Tree results:Subcriticality: GreenCore Cooling: OrangeHeat Sink: RedIntegrity: RedContainment: YellowInventory: YellowUnder these conditions the crew will…

A. remain in 1BwCA-0.0 LOSS OF ALL AC POWER.

B. IMMEDIATELY transition to 1BwFR-H.1 RESPONSE TO A LOSS OF SECONDARY HEAT SINK.

C. IMMEDIATELY transition to 1BwFR-P.1 RESPONSE TO IMMINENT PTS CONDITION.

D. IMMEDIATELY transition to 1BwEP ES-0.0 REDIAGNOSIS.

#75. Given:- Unit 1 was initially at 100% power.- A LOCA occurred.Currently:- The crew is implementing 1BwEP ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION.- Step 8 Initiate RCS Cooldown to 200oF has just been initiated.- RCS WR pressure is 1315 psig- PZR level is 0%.- CETCs indicate 512oF.The NEXT mitigating strategy the crew will implement is

A. reduce RCS injection flow by securing ECCS pumps.

B. stop all but one RCP.

C. depressurize the RCS.

D. isolate SI accumulators.

#76. Given:- Both units at 100% power.- 1A SX pump is running.- 2A SX pump is OOS.Subsequently:- A LOCA occurs on Unit 1.- 1A SX pump tripped.- 1B SX pump would NOT start. – RCS pressure is currently 1700 psig.- Unit 2 SX is cross-tied to Unit 1 per 1BwOA PRI-8 ESSENTIAL SERVICE WATER MALFUNCTION. .- Unit 2 SX pump discharge pressure is 82 psig.- 1A and 1B CV pump bearing temperatures are rising and within 3oF of the Table A VITAL EQUIPMENT TEMPERATURE LIMITS in 1BwOA PRI-8.(1) With NO further operator action(2) Under CURRENT conditions 1BwOA PRI-8 directs

A. (1) ECCS CANNOT be relied upon to perform its UFSAR safety function.(2) isolating SX to the associated CV pump room(s) cubicle cooler(s).

B. (1) ECCS will perform its UFSAR safety function.(2) aligning fire protection to the affected CV pump(s) and shutting down any CV pump that EXCEEDS a table A limit.

C. (1) ECCS CANNOT be relied upon to perform its UFSAR safety function.(2) aligning fire protection to the affected CV pump(s) and shutting down any CV pump that EXCEEDS a table A limit.

D. (1) ECCS will perform its UFSAR safety function.(2) shutting down ALL RCFCs on Unit 1.

#77. Given:CASE 1:- Unit 1 in Mode 1.- Bus 141 is de-energized for 1 hour to allow maintenance to replace a grounded breaker cubicle connector.CASE 2:- Unit 1 is in Mode 4.- SAT 142-1 requires an emergent OOS and is de-energized.- Bus 141 is energized by the 1A EDG during the OOS.CASE 3:- Unit 1 is in Mode 3.- Maintenance is replacing the motor for 1SX027A 1A & 1C SX INLT VLV over the next 24 hours.- The 1A and 1C RCFC breakers are all in PTL per the clearance order.In accordance with Braidwood Technical Specifications LCO 3.6.6 Containment Spray and Cooling Systems Condition C One or more containment cooling trains inoperable must be entered for

A. ALL three CASES.

B. CASES 1 AND 3 ONLY.

C. CASES 2 AND 3 ONLY.

D. CASE 3 ONLY.

#78. Given:- Unit 1 is in Mode 4.- 1A RH train is aligned for shutdown cooling.- 1A CC pump is RUNNING.- 1B CC pump is OOS.- 1D RCP is running.- U-0 CC pump is mechanically AND electrically aligned to Bus 142.- The crew is maintaining RCS temperature stable at 210oF.- PZR level is 26%.Subsequently:- CC surge tank level rapidly dropped to 9% before stabilizing.- 1A RH pump discharge temperature indicates 212oF and rising.- The crew entered 1BwOA PRI-6 COMPONENT COOLING MALFUNCTION.- ALL CC pumps are in pull-out and the crew has stopped the 1D RCP.Of the following the NEXT action the US will direct the crew to perform is to…

A. stop the 1A RH pump.

B. align and start a SI pump for hotleg injection.

C. close 1CC9412A CC TO RH HX 1A ISOL VLV.

D. start the 1B RH pump in shutdown cooling.

#79. Given:- Unit 2 is in Mode 6.- All required Technical Specification LCOs for Mode 6 are met.- SSPS is restored to at power configuration.- Final reactor vessel head bolt tensioning is in progress for preparation to enter Mode 5.Then:- PRNI N41 failed to a value of 15%.- PRNI N42 failed high.- The NI failures resulted from faulty detectors that CANNOT be immediately replaced due to parts availability.- Assume all other equipment is OPERABLE as needed for higher Tech Spec Modes.- Assume the PRNIs remain in the current condition.(1) The above conditions have resulted in (1).(2) Currently the HIGHEST Mode Unit 2 may enter is _(2)____.

A. (1) LCO 3.9.3 Nuclear Instrumentation entry conditions.(2) Mode 6.

B. (1) LCO 3.9.3 Nuclear Instrumentation entry conditions.(2) Mode 3 without requiring a specific risk assessment for the NI failures.

C. (1) NO change in compliance with the LCO 3.9.3 Nuclear Instrumentation.(2) Mode 3 but rods must be maintained in a condition where they are NOT capable of withdrawal.

D. (1) NO change in compliance with the LCO 3.9.3 Nuclear Instrumentation.(2) Mode 6.

#80. Given:- Unit 1 at 100% power.- The controlling Pressurizer Pressure Channel failed HIGH.- The crew is implementing 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL.- Pressurizer Pressure Control has been swapped to an operable channel.- 1RY455B PZR SPRAY VLV remains stuck full OPEN.NOTE the following procedure list:1BwEP-0 REACTOR TRIP OR SAFETY INJECTION.1BwEP ES-0.1 REACTOR TRIP RESPONSE.1BwEP ES-1.1 SI TERMINATIONIn accordance with 1BwOA INST-2 the crew will manually trip the reactor then _(1).The crew will then _(2)___.

A. (1) trip the 1B RCP.(2) implement 1BwEP-0 followed by 1BwEP ES-0.1.

B. (1) trip the 1D RCP.(2) implement 1BwEP-0 followed by 1BwEP ES-0.1.

C. (1) perform the immediate actions of 1BwEP-0.(2) trip the 1B RCP continue implementation of 1BwEP-0 followed by 1BwEP ES-1.1.

D. (1) perform the immediate actions of 1BwEP-0.(2) trip the 1D RCP continue implementation of 1BwEP-0 followed by 1BwEP ES-1.1.

#81. Given:- A Unit 1 Main Turbine runback is in progress from 100% power due to a secondary pump trip.- The crew is performing 1BwOA SEC-1 SECONDARY PUMP TRIP.- Annunciator 1-10-A6 ROD BANK LO-2 INSERTION LIMIT is NOT lit.- Annunciator 1-10-B6 ROD BANK LOW INSERTION LIMIT is LITCurrently:- Main Generator Load is 820 Mwe dropping (runback still in progress).- All feed flows are LESS THAN steam flows.- ALL NR SG levels 25-28% SLOWLY LOWERING. – Control Rods are stepping IN.With the above conditions the US will direct the crew to…

A. stop the runback and place the ROD BANK SELECT switch to MANUAL.

B. stop the runback and keep rod control in AUTOMATIC.

C. continue the runback until SG levels begin to rise while keeping rod control in AUTOMATIC.

D. continue the runback until SG levels begin to rise and place the ROD BANK SELECT switch to MANUAL.

#82. Given:- Unit 1 is in Mode 5.- The pressurizer is in SOLID condition.- 1B RH shutdown cooling is in service with RH letdown established.- 1A CV pump is running.- Unit 1 Station Air Compressor is supplying ALL instrument and service air loads.- Unit 2 is at 100% power.- Unit 2 Station Air Compressor is OOS.- The Unit 0 SAC is in standby.Subsequently:- A four inch diameter turbine building SERVICE AIR header ruptures.- The Unit 0 Station Air Compressor failed to start. (1) In response to this event ___(1)_.(2) Unit 1 RCS pressure is now 402 psig and rising. In response the crew will _(2)___.

A. (1) Unit 2 reactor will trip. The crew will enter 2BwEP-0 REACTOR TRIP OR SAFETY INJECTION and concurrently perform 2BWOA SEC-4 LOSS OF INSTRUMENT AIR.(2) stop the 1A CV pump.

B. (1) Unit 2 will remain at power. Instrument Air for Unit 2 will be unaffected due to isolation check valves between the SERVICE AIR header and Unit 2 INSTRUMENT AIR headers.(2) stop the 1A CV pump.

C. (1) Unit 2 reactor will trip. The crew will enter 2BwEP-0 REACTOR TRIP OR SAFETY INJECTION and concurrently perform 2BWOA SEC-4 LOSS OF INSTRUMENT AIR.(2) stop the 1B RH train and isolate it from the RCS.

D. (1) Unit 2 will remain at power. Instrument Air for Unit 2 will be unaffected due to isolation check valves between the SERVICE AIR header and Unit 2 INSTRUMENT AIR headers.(2) stop the 1B RH train and isolate it from the RCS.

#83. Given:- Unit 1 is at 100% power.- Unit 2 is in Mode 3.- Current sample results and levels for each of the Unit Specific Spray Additive tanks are shown below:- Unit 1:Level: 79%NaOH Concentration: 29%- Unit 2:Level: 77%NaOH Concentration: 30% Based on these conditions _(1)_ the requirements of LCO 3.6.7 Spray Additive System and _(2)_.

A. (1) BOTH units meet (2) there is NO effect on a design basis accident.

B. (1) NEITHER unit meets (2) could result in excessive re-evolution of iodine due to inadequate containment sump pH following a design basis accident.

C. (1) NEITHER unit meets (2) invalidates the safety analysis assumptions for hydrogen generation during a design basis accident.

D. (1) UNIT 2 is NOT in a Mode of applicability for AND UNIT 1 does NOT meet (2) BOTH the safety analysis assumptions for hydrogen generation in the containment atmosphere AND the assumed prevention of re-evolution of iodine from the containment sump are invalidated by the Unit 1 situation.

#84. Given the following plant conditions on Unit 1:- At 1200 an RCS LOCA occurred.- At 1230 the following conditions exist:- RCS pressure is 200 psig and dropping.- CETCs are 546 F and stable.- RWST level is 48% and dropping.- Containment floor water level is 18 inches.At 1700 the RH pumps suction will be aligned from the __(1) and provide water to the RCS (2)._(1)_ _(2)___

A. Containment Sumps Cold Legs

B. RCS Hot Legs Hot Legs

C. RCS Hot Legs Cold Legs

D. Containment Sumps Hot Legs

#85. Given:- Unit 1 was initially at 100% power.- The following equipment is OOS: – 1B CV pump- 1B SI pumpSubsequently:- An ATWS occurred.- The crew performed 1BwFR-S.1 RESPONSE TO NUCLEAR POWER GENERATION/ATWS.- A loss of offsite power occurred.- Bus 141 faulted.- 1B AF pump started then failed catastrophically.- SI actuated during the event. – The following parameters/trends exist:PRNIs 0%IRNI SURs -0.25 DPMCETCs 720oF RISINGSG NR levels 0%SG WR levels 30-31% DROPPINGWR RCS Loop Temps 670-700 oFContainment Pressure 4.0 psig STEADYThe crew transitioned from 1BwFR-S.1 to 1BwEP-0 REACTOR TRIP OR SAFETY INJECTION and are currently at step 5. Starting with the current plant conditions and ASSUMING IDENTIFIED TRENDS CONTINUE as described the crew will NEXT implementNOTE:1BwFR-C.1 RESPONSE TO INADEQUATE CORE COOLING1BwFR-C.2 RESPONSE TO DEGRADED CORE COOLING1BwFR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK

A. 1BwFR-H.1 immediately then transition to 1BwFR-C.1.

B. 1BwFR-H.1 when directed in 1BwEP-0 then transition to 1BwFR-C.1.

C. 1BwFR-C.2 when directed to initiate monitoring of critical safety function status trees then transition to 1BwFR-H.1.

D. 1BwFR-C.2 immediately then transition to 1BwFR-H.1 then transition to 1BwFR-C.1.

#86. Given:- Unit 1 experienced a fault inside containment on the 1A SG from 100% power.- The reactor was manually tripped and appropriate ESF actuations initiated.- ALL RCPs were tripped.- The crew has completed 1BwEP-2 FAULTED STEAM GENERATOR ISOLATION.- The 1A CENT CHG pump was stopped at step 4 of 1BwEP ES-1.1 SI TERMINATION.- The crew is at step 5 Check RCS Pressure of 1BwEP ES-1.1.The following indications are noted:- Annunciator 1-9-E1 CHG PUMP ISOLATION VALVE CLOSED just CLEARED.- Subsequently Bypass Permissive P-11 CLEARED.- 1B 1C & 1D SG pressures: 740 psig STABLEIn response to the latest indications the crew will

A. transition to 1BwEP ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION.

B. transition back to 1BwEP-2 FAULTED STEAM GENERATOR ISOLATION.

C. remain in 1BwEP ES-1.1 SI TERMINATION.

D. transition to 1BwEP ES-0.2 NATURAL CIRCULATION COOLDOWN.

#87. Given:- Unit 2 was at 100% power.Subsequently:

– The crew manually tripped Unit 2 and initiated SI in response to a LOCA.- The crew transitioned to 2BwCA-1.2 LOCA OUTSIDE CONTAINMENT with all ECCS pumps operating.- The leak has been confirmed in the 2B RH and CS pump room.- RCS temperature is 520oF.- The 2B RH pump is in PTL.The crew has determined that the following valves must be CLOSED to isolate the leakage:- 2SI8809B RH TO COLD LEG 2B & 2C ISOL VLV- 2RH8716B HX 2B XTIE VLV- 2SI8812B PP 2B SUCT FROM RWST ISOL VLVAssume that the valves listed above remain closed for the duration of the event and continued plant cooldown. The Unit Supervisor will declare BOTH ECCS trains inoperable A. however 100% flow equivalent is available for the 2A ECCS train. Once Mode 4 is reached ECCS operability requirements are met.

B. however 100% flow equivalent is available for the 2A ECCS train. Once Mode 4 is reached ECCS operability requirements are NOT met.

C. causing entry into LCO 3.0.3. Once Mode 4 is reached ECCS operability requirements are NOT met.

D. causing entry into LCO 3.0.3. Once Mode 4 is reached ECCS operability requirements are met.

#88. Given the following on Unit 1:- A RCS LOCA occurred from full power.- 1A RH pump tripped and could NOT be started.- 1B RH pump is running.- RWST level is 46%.- 1BwEP ES-1.3 TRANSFER TO COLD LEG RECIRCULATION has just been entered.- 1SI8811A CNMT SUMP 1A ISOL VALVE is closed.- 1SI8811B CNMT SUMP 1B ISOL VALVE is open.- Cnmt pressure is 8 psig.- Cnmt floor water level is 9 inches.In response to this event the crew will

A. complete 1BwEP ES-1.3 Attachment A MANUAL OPERATION OF CONTAINMENT SUMP ISOLATION VALVES which will direct 1SI8811A to be manually OPENED.

B. transition to 1BwCA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION due to the status of Cnmt floor water level.

C. complete 1BwEP ES-1.3 Attachment A MANUAL OPERATION OF CONTAINMENT

SUMP ISOLATION VALVES which will leave 1SI8811A CLOSED.D. transition to 1BwCA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION due to the status of the RH pumps.

#89. Given:- Unit 1 is recovering from a loss of Heat Sink condition.- Bleed and Feed was NOT established during the event.- Feed flow has been established to the 1C and 1D SGs per Attachment B of 1BwFR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK.- The following conditions currently exist:- 1C and 1D Narrow Range SG levels: 2% SLOWLY RISING.- 1A and 1B Wide Range SG levels: 30% STABLE.- RCS temperature: 558oF.- NO RCPs are running.- Both reactor trip breakers are OPEN- Containment pressure: 0.2 psig STABLE.- The crew is currently in 1BwEP ES-0.1 REACTOR TRIP RESPONSE at step 9 CHECK RCP 1D RUNNING.In order to comply with current Technical Specification requirements for RCS Loops the

A. ONLY action the crew must complete is to start ONE RCP.

B. crew must start ONLY ONE RCP raise its associated SG level and raise another SG level.

C. ONLY action the crew must complete is to start TWO RCPs.

D. crew must start at least TWO RCPs AND raise their associated SG levels.

#90. Given:- Unit 1 initially at 100% power.Subsequently:- A LOCA inside containment occurred.- The crew is evaluating if RCS Cooldown and Depressurization is required per 1BwEP-1 LOSS OF REACTOR OR SECONDARY COOLANT.- Current indications include the following:- PRNIs: 0%- IRNIs SUR: fluctuating between negative 0.2 and zero DPM.- CETCs: 620oF.- Containment Pressure: 2.0 psig RISING.- PZR Level: Offscale LOW.- WR RCS Pressure: 1800 psig DROPPING slowly.Based on these conditions the crew will transition to

A. 1BwFR-S.1 RESPONSE TO NUCLEAR POWER GENERATION ATWS.

B. 1BwFR-C.2 RESPONSE TO DEGRADED CORE COOLING.

C. 1BwEP ES 1.1 SI TERMINATION.

D. 1BwEP ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION.

#91. Given:- BOTH units at 100% power.- A fire has initiated in the Auxiliary Electrical Equipment Room.Consider each condition separately:(1) MCR evacuation is required.(2) The fire is NOT extinguished in 30 minutes.(3) Donning SCBAs is necessary in the MCR.Under which of the following conditions must the US order a reactor trip?

A. ONLY condition 1.

B. ONLY conditions 1 and 2.

C. ONLY conditions 1 and 3..

D. conditions 1 2 and 3.

#92. Given:- Unit 1 is in Mode 1.- Unit 1 Main Control Room is being evacuated in accordance with 1BwOA PRI-5 CONTROL ROOM INACCESSIBILITY.- NO fire is present in the MCR. Based on the above conditions and in accordance with 1BwOA PRI-5 EACH of the following actions/verifications is REQUIRED PRIOR TO evacuating the main control room EXCEPT…

A. VERIFY ALL turbine throttle and governor valves are CLOSED.

B. OPEN RCS Loop Sample Containment isolation valves.

C. VERIFY ALL Reactor Trip and Bypass breakers are OPEN.

D. TRIPPING ALL RCPs.

#93. Given:- Unit 1 has been at 100% power for 3 weeks following a refueling outage.- A review of work packages has just determined that blocking devices were NOT removed from ONE Unit 1 SG safety valve on EACH of the four steam generators.- Of the following choices which ones must be REDUCED in accordance with Braidwood Technical Specifications?(1) OTT reactor trip setpoint.(2) OPT reactor trip setpoint.(3) Power Range neutron flux high reactor trip setpoint.(4) Reactor power.

A. (1) and (2) ONLY.

B. (1) (2) and (4) ONLY.

C. (1) and (3) ONLY.

D. (3) and (4) ONLY.

#94. Given:- Core reload on Unit 1 is in progress.- The 14th fuel assembly is being lowered into the reactor vessel (has penetrated the plane of the Reactor Vessel flange).- The following has occurred:- The most recent successive RCS boron concentration samples show an UNEXPECTED DROP from 2340 ppm to 2310 ppm.In response to this event of the following options

A. the fuel assembly MUST be returned to the spent fuel pool.

B. the crew MUST initiate containment closure.

C. the fuel assembly MUST be placed in a designated core location.

D. the crew MUST emergency borate.

#95. Each of the following are Licensed SRO fuel handling supervision responsibilities EXCEPT…

A. visual core alignment inspection to check for gaps or misalignments that would prevent the upper internals from meeting properly with the fuel assemblies.

B. maintain direct communications with the Control Room.

C. control of access to the refuel floor areas.

D. approve changes to the move sheet.

#96. Which of the following work control activities REQUIRES a Senior Reactor Operator and CANNOT be delegated to someone else?

A. Classification prioritization and categorizing of work orders for safety related equipment.

B. Supervision of configuration control within a clearance order boundary after the clearance order is hung.

C. Approve issuance of keys in the Work Execution Center.

D. Independent verification of component positioning while hanging safety related clearance orders.

#97. Given:- Unit 2 at 100% power.- An idle RCFC train was recently started.- 2BwOS RF-1 CONTAINMENT FLOOR DRAIN MONITORING SYSTEM NON ROUTINE SURVEILLANCE is current using Containment Floor Water Level Meters 2LI-PC002 and 2LI-PC003.With the above conditions a Tech Spec LCO entry would result from ___(1)_.This would (2)_.

A. (1) 1.1 gpm flow of water into the Containment Floor drain sump from RCFC condensation.(2) cause a loss of ALL capability to detect a 1 gpm RCS leak within 1 hour.

B. (1) 1.1 gpm flow of water into the Containment Floor drain sump from RCFC condensation.(2) NOT result in a loss of REDUNDANT capability to detect a 1 gpm RCS leak within 1 hour.

C. (1) NEGATIVE 0.2 psig Containment Pressure.(2) negate assurance the design NEGATIVE Containment pressure would NOT be exceeded if Containment Spray inadvertently actuates.

D. (1) NEGATIVE 0.2 psig Containment Pressure.(2) result in exceeding superheat assumptions that form the basis for equipment qualification in Containment during an assumed LOCA.

#98. In accordance with RP-BR-980 CONTAINMENT VENT AND MINI PURGE GASEOUSEFFLUENTS which of the following is an SRO responsibility for a containment release?

A. Initial determination that sample results of the containment atmosphere are acceptable for the Mini-purge flowpath.

B. Initial determination of Rad Monitor release alarm setpoints.

C. Ensure the containment release is initiated within 48 hrs of a routine analyzed sample of containment atmosphere.

D. Recording of initial and final containment pressures.

#99. Given:- BOTH Units were at 100% power.Subsequently:- A plant transient caused a Unit 1 reactor trip.- A SAT 142-1 fault occurred.- The 1B EDG failed to start.- The 1A EDG is running unloaded.- The crew has just entered 1BwCA-0.0 LOSS OF ALL AC POWER.- Bus 141 Breakers 1413 1411 1412 & 1414 have been placed in PTL.- RCS subcooling is ACCEPTABLE per ICONIC DISPLAY.- Pressurizer level is 27% STABLE.- Containment pressure is 0.2 psig STABLE.- NO ECCS equipment actuates upon power restoration.- The following annunciators are LIT:1-21-A7 BUS 141 FD BRKR 1412 TRIP1-21-B9 DG 1A OVERLOAD1-21-C7 BUS 141 OVERLOAD OR VOLT LOW1-21-C8 DG 1A TROUBLE/FAIL TO STARTIn response to this event the Unit 1 US will direct the crew to cross-tie

A. bus 142 to Unit 2 then transition to 1BwCA-0.2 LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED.

B. BOTH bus 141 and 142 to Unit 2 then transition to 1BwCA-0.2 LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED.

C. BOTH bus 141 and 142 to Unit 2 then transition to 1BwCA-0.1 LOSS OF ALL AC

POWER RECOVERY WITHOUT SI REQUIRED.D. bus 142 to Unit 2 then transition to 1BwCA-0.1 LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED.

#100. Given:- An inadequate core cooling event is in progress on Unit 1.- The crew is performing 1BwFR-C.1 RESPONSE TO INADEQUATE CORE COOLING.- At step 3 CHECK RCP SUPPORT CONDITIONS support conditions were NOT established due to NO seal injection flow and high RCP leakoff temperatures.- Continued attempts to re-establish RCP support conditions have been UNSUCCESSFUL so far.- Currently the crew is at step 16 CHECK IF RCPs SHOULD BE STARTED.- All RCPs are shutdown. – CETCs are 35oF ABOVE the 1BwFR-C.1 entry condition and slowly rising.- RCS pressure is 1500 psig.- 1A and 1B CV pumps are unavailable.- 1RE-AR020 and 021 High Range Containment Radiation Monitors indicate 3 x 105 R/hr.- SG NR Levels are as follows:1A 38 27 34 28% With the above conditions the US will direct the crew to…

A. NOT start an RCP and continue with the next mitigating strategy by opening both PZR PORVs.

B. remain at step 16 until support conditions are established then start the 1A and 1C RCPs.

C. immediately start EITHER the 1A or 1C RCP regardless of the support conditions.

D. immediately start BOTH 1A and 1C RCP regardless of the support conditions.

Results