Braidwood 2009 - ILTandMe

#1. – Unit 1 is at 100% power. – The VCT hydrogen pressure regulator is stuck closed. – All other systems are normally aligned. – Over several shifts VCT pressure drops to 10 psig. The effect of lowering VCT pressure on the operation of RCP seals is…

A. rising flow through the #2 RCP seal.

B. rising flow through the #3 RCP seal.

C. lowering flow through the #2 RCP seal.

D. lowering flow through the #1 RCP seal.

#2. – Unit 1 is in MODE 2, reactor start up in progress. – All U-1 systems are normally aligned for this mode. – Unit 2 is at 100% power, normal alignment. The following sequence of events occurs: – Unit 1 offsite power is LOST. – All equipment operates as designed. – The crew is performing step 1 of 1BwEP ES-0.1, REACTOR TRIP RESPONSE after determining SI was NOT required . – At the “CHECK RCS TEMPERATURES” step it is determined that emergency boration is required per 1BwOA PRI-2, EMERGENCY BORATION. – Non-ESF buses are still de-energized. – NO other operator actions have been taken. With the above conditions, the NSO will Borate the RCS from the …

A. BAST via 1CV8104, EMER BORATION VALVE, and normal charging header.

B. BAST via 1CV110A, BORIC ACID TO BLNDR VLV and 1CV110B, BORIC ACID BLNDR TO CHG PMPS VLV and normal charging header.

C. RWST via 1CV112D and/or 1CV112E, RWST TO CHG PUMP SUCT VLVS and normal charging header.

D. RWST via 1CV112D and/or 1CV112E, RWST TO CHG PUMP SUCT VLVS and high head injection header.

#3. – 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 Alignment”. With the 1A RH pp 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.

#4. Regarding the ECCS design: 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems, lists the maximum calculated fuel element cladding temperature shall NOT exceed…

A. 700F.

B. 2200F.

C. 4800F.

D. 5080F.

#5. With the Unit 1 reactor at full power, the Unit NSO notices a rising PRT level. In addition to the PZR PORVs and PZR Safety valves, the component(s) that could be causing PRT level rise is/are the …

A. Letdown Line Relief Valve.

B. #2 RCP Seal Leakoff lines.

C. SI Accumulator Drain Valve.

D. #3 RCP Seal Leakoff lines.

#6. – Unit 1 is in Mode 2 at 3% reactor power. – All systems are normally aligned for this power level. The following occurs: – A pressurizer safety valve sticks open. – Pressurizer pressure is dropping. – Pressurizer level is rising. With the above conditions and NO operator action, the red First Out annunciator reactor trip signal will be…

A. 1-11-C3 PZR PRESS LOW RX TRIP

B. 1-11-B4 OT DT RX TRIP

C. 1-11-A3 PZR LEVEL HIGH RX TRIP

D. 1-11-C1 PZR PRESS LOW SI/RX TRIP

#7. – Unit 1 is in Mode 4. – RCS cooldown commenced 2 hrs. 30 minutes ago. – 1B RH Train is in Shutdown Cooling Mode. – All systems are normally aligned for this mode. The following annunciator alarms in the MCR: – 1-2-C5, CC HX OUTLET TEMP HIGH The proper response to the alarm is throttle OPEN…

A. 1CC9503, SPENT FUEL PIT HX 1 OUTLT CC FCV.

B. 1CC9507B, RH HX 1B CC OUTLET FCV.

C. 1SX007, U-1 SX OUTLET FROM CC HX VLV.

D. 1RH607, RH HX 1B FLOW CONT VLV.

#8. – Unit 1 is in mode 5. – BwOP RC-19, “VACUUM FILLING AN ISOLATED REACTOR COOLANT LOOP/PRESSURIZER” is in progress. – Pressurizer level at 70% cold cal. – Pressurizer pressure at 20″ Hg vac. – Vacuum pump is shut down and isolated. – RH is in service with RCS loop temperatures at 115F. – Pressurizer heaters are energized. Assuming pressurizer pressure remains constant, what will be the pressurizer liquid temperature when the bubble STARTS forming in the pressurizer?

A. 162F

B. 193F

C. 212F

D. 228F

#9. – Unit 2 is at 100% power, all systems normally aligned. – An automatic reactor trip signal is generated. – Due to a malfunction, SSPS Train 2A Logic Cabinet does NOT process the Reactor Protection logic coincidence. – SSPS Train 2B functions as designed. Based on the above conditions and assuming NO operator actions are taken, which ONE of the following would occur?

A. 2A Reactor Trip Breaker REMAINS CLOSED. 2B Reactor Trip Breaker OPENS with ONLY UV trip signals.

B. 2A Reactor Trip Breaker OPENS with ONLY UV trip signal. 2B Reactor Trip Breaker OPENS with UV AND shunt trip signals.

C. 2A Reactor Trip Breaker REMAINS CLOSED. 2B Reactor Trip Breaker OPENS with UV AND shunt trip signals.

D. 2A Reactor Trip Breaker OPENS with ONLY shunt trip signal. 2B Reactor Trip Breaker OPENS with UV AND shunt trip signals.

#10. – Unit 2 is at 75% power. – 24 hours ago, Pressurizer Pressure channel 2PT-457 failed. – ALL actions of 2BwOA INST-2, OPERATION WITH FAILED INSTRUMENT CHANNEL have been completed. – ALL associated Tech Spec required actions have been taken. (regardless of completion times) – ALL other equipment (not associated with the 2PT-457 failure) is normally aligned. – Today, with the above conditions, Instrument Bus 213 faults and de-energizes. 15 seconds after the instrument bus failure, with NO operator action, Unit 2 will…

A. have automatically tripped WITH safety injection actuated.

B. continue to operate at 75% power.

C. have automatically tripped, but with NO safety injection.

D. have automatically runback, until operator action is taken.

#11. – Unit 1 was at 100% power normal alignment. – Subsequently, containment pressure transmitter 1PT934 has failed. – All required actions of Tech Specs have been completed. With the above conditions, the current coincidence logic for automatically actuating containment spray from OPERABLE pressure channels is…

A. 1 of 2.

B. 2 of 2.

C. 1 of 3.

D. 2 of 3.

#12. – A reactor trip and safety injection have occurred on Unit 1. – While performing step 7 of 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION, an NSO reports the Group 2 RCFC Accident Mode lights for 1A and 1C RCFCs are dark. Which of the following indications would explain the failure of the 1A and 1C RCFC Accident Mode lights to illuminate?

A. 1SX147A, 1A CNMT CHLR BYP ISOL VLV, OPEN light lit at 0PM02J.

B. 1SX027A, 1A/1C RCFC SX OUTLET VLV, OPEN light lit at 1PM06J.

C. 1SX016A, 1A/1C RCFC SX INLET VLV, OPEN light lit at 1PM06J.

D. 1SX112A, 1A CNMT CHLR INLET ISOL VLV, OPEN light lit at 0PM02J.

#13. – Unit 1 is at 100% power normal alignment. – 1A SX pump is RUNNING. – 1B SX pump is in STANDBY. The following annunciator alarms at 1PM06J: – 1-1-A2, CNMT LEAK DETECT FLOW HI – An NSO reports that U-1 SX discharge pressure has dropped 5 psig since his MCB walkdown 15 minutes ago. – 1PI-SX007, PP 1A DSCH PRESS is currently stable at 92 psig. – No other alarms have come in and primary system parameters are all normal. – The crew determines that a SX leak exists in U-1 containment and enter 1BwOA PRI-8, ESSENTIAL SERVICE WATER MALFUNCTION. With the above conditions, per 1BwOA PRI-8, the FIRST MCR action(s) the crew will take to identify the leak location is…

A. shutdown 1A & C RCFCs and close 1SX016A and 1SX027A, RCFC 1A & C SX INLET and OUTLET VLVS.

B. shutdown the 1A SX pump and monitor RF sump pump run time.

C. shutdown 1B & D RCFCs and close 1SX016B and 1SX027B, RCFC 1B & D SX INLET and OUTLET VLVS.

D. verify 1SX016B and 1SX027B, RCFC 1A & C SX INLET and OUTLET VLVS are open and start the 1B SX pump.

#14. – 10 minutes ago. a Unit 1 reactor trip and SI occurs due to a large steam break in containment. – CS automatically actuated and all equipment operated as designed. – NO operator actions have been taken on the CS system. – The CS signal has NOT been reset. – The crew is currently performing 1BwEP-1, LOSS OF REACTOR OR SECONDARY COOLANT. – The SM has directed the crew to isolate CS spray eductor flow by closing 1CS019A/B, EDUC SPRAY ADD VLVS, at the appropriate procedure step to minimize containment clean up. The MINIMUM MCR action(s) required to isolate CS spray eductor flow is/are…

A. push CS reset pushbuttons and momentarily place 1CS019A/B control switches to close.

B. momentarily place 1CS019A/B control switches to close ONLY.

C. push CS reset pushbuttons ONLY (1CS019A/B will then auto close).

D. place CS Pump Test Switches to TEST, and momentarily place 1CS019A/B control switches to close.

#15. – Unit 1 is 100% power normal alignment. – Following maintenance on valve 1CS009A, PP 1A SUMP SUCT VLV, an NSO is performing 1BwOSR 5.5.8.CS-1A, TRAIN A CONTAINMENT SPRAY SYSTEM VALVE STROKE SURVEILLANCE. – In order to meet the interlocks to open 1CS009A, EMD must install an electrical jumper to simulate which of the following valves is in the OPEN position?

A. 1RH8701A, RC LOOP 1A TO RH PP 1A SUCT ISOL VLV

B. 1SI8812A, PP 1A SUCT FROM RWST ISOL VLV

C. 1CS001A, PP 1A RWST SUCT VLV

D. 1SI8811A, CNMT SUMP 1A ISOL VLV

#16. – Unit 1 is in Mode 3 following a normal reactor shutdown. – A cooldown commenced at 1500 following 2 hours of stable RCS temperature. The following data has been recorded on 1BwOSR 3.4.3.1, RCS PRESSURE/TEMPERATURE LIMIT SURVEILLANCE. Loop A Cold Temp (F) Rate Temp ChangeTime Leg Temp Change (F/hr) in 1 hr Period1500 557F 0 0 0 1515 525F 32 128 32 1530 499F 26 104 58 1545 479F 20 80 78 1600 460F 19 76 97 1615 430F 30 120 95 1630 395F 35 140 104 1645 380F 15 60 99 1700 374F 16 64 86 The RCS cooldown FIRST exceeded the limits of Tech Spec. 3.4.3, RCS P/T LIMITS, at _, which may have exceeded the assumed __ .

A. 1515, margin to RCS brittle failure.

B. 1630, shutdown margin.

C. 1515, shutdown margin.

D. 1630, margin to RCS brittle failure.

#17. – Unit 1 is at 80% power, normal alignment. – 1A Main Feedwater Pump is OOS. – 1B Main Feedwater Pump is running. – 1C Main Feedwater Pump just tripped. The NSO closes 1FW012C, RECIRC VALVE, then attempts to runback the turbine with both the Runback pushbutton and OWS graphic 5512 poke field. However, the turbine load does NOT change. The NSO should then …

A. program DEHC and initiate a 20 MW/min load drop to 780 MW.

B. manually trip the reactor and enter 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION.

C. start the S/U Feedwater Pump.

D. program DEHC and initiate a 250 MW/min load drop to 700 MW.

#18. – A Unit 1 RCS cooldown is in progress with the 1A AF pump maintaining stable level in all steam generators. – Then instrument power is lost to the 1AF005A controller. Assuming RCS heat input and SG steaming rate remain constant, 1AF005A, SG 1A FLOW CONT VLV …

A. fails closed and 1A SG level will drop.

B. fails open and 1A SG level will rise.

C. fails as is and 1A SG level will remain the same.

D. is NOT affected and 1A SG level will remain the same.

#19. – The MCR is receiving sporadic alarms from annunciator 1-4-D5, BUS 114 INVERTER TROUBLE. – Plant engineering suspects an intermittent ground on Instrument Bus 114, and is making preparations for trouble shooting. – The Unit Supervisor asks for Instrument Bus 114 current to be monitored for fluctuations. Instrument Bus 114 amps can best be monitored at…

A. Instrument Bus 114, in the U-1 Aux Electrical Equipment Room.

B. Instrument Inverter 114 in the U-1 Misc. Electrical Equipment Room.

C. Division 12 section of 1PM01J, in the Main Control Room.

D. N44 drawer of 1PM07J, in the Main Control Room.

#20. – Unit 1 is in mode 5, with 1BwGP 100-1, PLANT HEATUP, in progress. – The 1A CV pump has just been started. – Five seconds AFTER the pump start, DC control power is LOST to bus 141 due to a faulty fuse. – NO other plant components are damaged. After the loss of control power the 1A CV pump…

A. can ONLY be tripped locally by mechanically actuating the trip coil.

B. will trip immediately from a loss of DC control power.

C. can be tripped locally with the breaker local control switch.

D. can be tripped remotely from the MCR switch.

#21. – Unit 1 is at 100% power. – The 1A Diesel Generator has auto started and energized bus 141 due to a undervoltage condition on the bus. – Equipment repairs are complete and operators are currently performing BwOP AP-32, SYNCHRONIZING A SAT TO A BUS BEING FED BY A DG, to re-align bus 141 feed to normal. Currently: – DG 1A EMERG MODE SPEED/VOLT CONTROL switch is in MAN EMERG MODE. – The normal feed breaker to bus 141 is closed with the DG and SAT in parallel. With the above conditions, if the NSO places DG 1A EMERG MODE SPEED/VOLT CONTROL switch back to AUTO, initially the 1A DG…

A. engine will trip on reverse power.

B. will pick up real load (WATTS) from the grid.

C. will speed up to the mechanical governor set point.

D. will reject reactive load (VARS) to the grid.

#22. Which of the following combinations of Unit 1 breaker positions will initiate the division 11 Blackout Sequencer? 1412 1413 1414

A. CLOSED OPEN CLOSED

B. OPEN CLOSED CLOSED

C. OPEN CLOSED OPEN

D. CLOSED OPEN OPEN

#23. – Communications loop failures occur on ALL RM-11 grid 2 radiation monitors. With the above condition, ALL of the following listed grid 2 monitors can be monitored from a Main Control Room RM-23, EXCEPT…

A. 1PR11J, CNMT ATMOSPHERE

B. 1PR30J, VENT STACK 0A EFFLUENT

C. 0PR35J, MCR TURB BLDG AIR INLET

D. 0PR31J, MCR OUTSIDE AIR INLET

#24. – Both units are at 100% power. – 1A Circ Water Pump forebay is drained for silt removal. – 0SX115A, UPST ISOL TO SX PUMPS TRAIN A SUCTION HDR FROM 1A BAY, is danger tagged CLOSED. – All other SX system equipment is in normal alignment. An event occurs that causes debris in the 1B Circ Water Pump forebay to block flow at the inlet to the SX suction piping. ONLY the 1B Circ Water Pump forebay is affected. If ALL SX pumps were running with the above conditions, the control room NSO would likely see cavitation from the ________ SX Pump(s).

A. 1A AND 2A

B. 1A (ONLY)

C. 1A AND 1B

D. 1B AND 2B

#25. – A reactor trip and SI have occurred on Unit 1. – The crew is currently performing 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION, at step 3, VERIFY POWER TO 4 KV ESF BUSES. In the above situation, (1) the condition for which 1BwOA ELEC-3, LOSS OF 4KV ESF BUS, applies is… (2) the actual application of 1BwOA ELEC-3 is…

A. (1) a loss of ONLY one ESF bus. (2) perform immediately (while continuing with 1BwEP-0).

B. (1) a loss of ONLY one ESF bus. (2) perform when time permits (while continuing with 1BwEP-0).

C. (1) a loss of ONLY one ESF bus. (2) transition to (suspend usage of 1BwEP-0).

D. (1) a loss of BOTH ESF buses (2) transition to (suspend usage of 1BwEP-0).

#26. – Both units are at 100%, normal alignment. – Unit 1 SAC and IA drier are on line. An event occurs and the MCR receives the following alarms: – 0-37-C3, IA RCVR 1 PRESS LOW. – 0-37-D3, IA DRYER 1 TROUBLE (15 sec. later). NO other alarms come in. The NSO notes the following: – Station Air pressure is 115 psig and stable. – Instrument Air pressure dropped to 80 psig and is slowly rising. Based on the above indications, which of the following is the most likely event that occured?

A. An instrument air system leak caused a stand-by air compressor to start.

B. The U-1 IA Receiver relief valve momentarily lifted and reclosed.

C. A U-1 IA dryer purge valve failed open and the air dryer bypass valve automatically opened.

D. The running station air compressor tripped and caused a stand-by compressor to start.

#27. – Both units are at 100% power, normal alignment. An air system leak in the plant causes the following alarms in the MCR: – 0-37-C2, SAC 1 RCVR PRESS LOW. – 0-37-C3, IA RCVR 1 PRESS LOW. – The U-1 MCR crew enters 1BwOA SEC-4, LOSS OF INSTRUMENT AIR. – The US instructs an extra NSO to monitor for reactor trip criteria per 1BwOA SEC-4. The correct meter the NSO should monitor is…

A. 0PI-IA007, INST AIR HDR PRESS at 0PM01J

B. 0PI-SA006, SERV AIR HDR PRESS at 0PM01J

C. 1PI-GS001, SUP HDR PRESS at 1PM02J

D. 1PI-ES043, EXH HOOD 1A PRESS at 1PM03J

#28. – Unit 2 is 100% power. – 2C RCFC HIGH AND LOW speed fans are danger tagged OOS. – All other equipment is normally aligned. While performing 2BwOSR 0.1-1,2,3, SHIFTLY DAILY OPERATING SURV, the NSO observes the following RCFC temperature indications on 2PM06J: – 2A INLET TEMP – 95F – 2A OUTLET TEMP – 70F – 2C INLET TEMP – 105F – 2C OUTLET TEMP – 75F – 2B INLET TEMP – 95F – 2B OUTLET TEMP – 70F – 2D INLET TEMP – 95F – 2D OUTLET TEMP – 70F With the above indications, which of the following is the containment average air temperature that should be recorded for Tech. Spec. 3.6.5. CONTAINMENT AIR TEMPERATURE surv. requirement?

A. 82.5 F

B. 84.4 F

C. 95.0F

D. 97.5 F

#29. – An RCS cooldown and depressurization is in progress following an RCS leak. Steady state plant conditions have been established. – CETCs are 532 F. – RCS pressure is 885 psig and STABLE. – S/G pressures are 910 psig. – Steam dumps are 5% open. – AF flow is 20 gpm to each S/G. Based on these conditions, the operator can aid in establishing subcooling by LOWERING…

A. RCS pressure.

B. Steam Dump demand.

C. Aux. Feedwater flows.

D. S/G pressures.

#30. – Unit 1 is at 50% power. – Pressurizer pressure is 2240 psig. – Tave = Tref. – 1FK-121 controller, CENT CHG PMPS FLOW CONT VLV is controlling charging flow in MANUAL. – Pressurizer level is 50%. – ALL other controls are in AUTOMATIC. – 1A and 1B backup heater groups have automatically energized. – 1D backup heater group is NOT energized. With the above conditions, the backup heaters groups are …

A. responding properly.

B. NOT responding properly, NO groups should be ENERGIZED.

C. NOT responding properly, ONLY the 1A group should be ENERGIZED.

D. NOT responding properly, ALL groups should be ENERGIZED.

#31. – 5 minutes ago, Unit 1 reactor was manually tripped from 5% power during a normal shutdown. – All systems operated as designed. – Current SG levels are ALL 50% and stable. – ALL alarms at 1PM05J have been acknowledged, but NOT reset. With the above conditions, if the NSO momentarily places the ROD CONT STARTUP switch on 1PM05J, to the START UP position …

A. all control rod group step counters will reset to zero.

B. alarm 1-10-E6, ROD AT BOTTOM will clear (slow flash).

C. the reactor trip breakers will close.

D. alarm 1-11-A1, MANUAL RX TRIP will clear (slow flash).

#32. – Unit 1 reactor is critical at 1×10-8 amps (BOTH IR channels). Then: – Instrument Bus 111 is deenergized. With the above condition and NO operator action, the reactor will trip on high flux due to the loss of power to _______.

A. Permissive P-10

B. SR channel N-31

C. IR channel N-35

D. PR channel N-41

#33. – Unit 1 is preparing to enter MODE 4 from MODE 3. – RCS pressure is being controlled at 650 psig. – ALL Wide Range RCS temperatures are 350F. – BOTH PZR PORV control switches are in the “ARM LOW TEMP” position at 1PM05J. With the above conditions, if 1TE413E, Loop 1B Tcold Wide Range temperature sensor, fails LOW, ______________________________ will automatically OPEN. (U1 PTLR Figure 3.1 is attached)

A. ONLY PZR PORV, 1RY455A

B. ONLY PZR PORV, 1RY456

C. BOTH PZR PORVs, 1RY455A and 1RY456

D. NEITHER PZR PORV, 1RY455A nor 1RY456

#34. – Unit 1 is at 100% power. – Steam pressure is 1005 psig. – Steam Dump Mode Select switch is in the STEAM PRESSURE mode. – 1PK-507, Steam Header Pressure Controller, is set at 6.93 (1039 psig). The following then occurs: – The U1 NSO initiates a load reduction to 50% power. With the above conditions, U1 Steam Dumps will…

A. NOT open prior to reaching 50% power.

B. begin to OPEN at approximately 61% power.

C. begin to OPEN at approximately 68% power.

D. begin to OPEN at approximately 77% power.

#35. – Unit 1 is raising power from 5% to full load, following a 3 day forced outage. In accordance with 1BwGP 100-3, POWER ASCENSION, Calorimetric Calculations must be performed at (1) %, (2) %, and (3) % power levels. (1) (2) (3)

A. 15 50 100

B. 30 75 90

C. 30 75 100

D. 50 90 100

#36. – Unit 1 is in a refuel outage. – 0A RHUT level has risen slowly for several hours due to RCS draining operations. – Concurrently, the waste gas compressor was ran several times, maintaining waste gas vent header pressure between 1.5 psig and 2.0 psig. With the above conditions, which of the following is an expected response?

A. ON COVER gas decay tank pressure has remained stable.

B. ON LINE gas decay tank pressure has lowered.

C. STANDBY gas decay tank pressure has lowered.

D. 0NT9318, N2 SUP HDR TO RHUT PCV has opened.

#37. – Both units are at 100% power. – The following equipment is OOS. 1B CW Pump 0A WS Pump U-0 SAC – All other equipment is normally aligned. The following occurs: – Unit 1 reactor is manually tripped. – All equipment operates as designed. ONE MINUTE LATER, bus 143 faults and is deenergized. With the above conditions and NO operator actions, which of the following will occur?

A. Unit 1 Pzr Backup Heater Group A energizes.

B. ALL unit 1 steam dump valves close.

C. Unit 1 loses Instrument Air.

D. WS header pressure drops on BOTH units.

#38. – Unit 1 experienced a SG tube rupture at full power. – Currently the crew is performing 1BwEP ES-3.1, POST SGTR COOLDOWN USING BACKFILL, at step 6, INITIATE RCS COOLDOWN TO 200F. The following note is prior to step 6. “Since ruptured SG(s) may continue to depressurize to less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should not be delayed.” The FIRST concern for RCP operation is…

A. excessive #1 seal leakoff.

B. net positive suction head (NPSH) requirements.

C. adequate #1 seal face gap.

D. causing an RCS pressure spike.

#39. – BOTH units were tripped from 100% power. – 1/2BwEP ES-0.1, “REACTOR TRIP RESPONSE”, are in progress. Condition 1: – BOTH units experience an RCS temperature drop to 540F Condition 2: – BOTH units have two (2) control rods that did NOT fully insert. Based on the above, which statement below is correct regarding the amount of boration required in each condition?

A. Unit 1 will require more boration for condition 1 AND Unit 2 will require more boration for condition 2.

B. Unit 2 will require more boration for condition 1 AND Unit 1 will require more boration for condition 2.

C. Unit 1 will require more boration for BOTH conditions.

D. Unit 2 will require more boration for BOTH conditions.

#40. – Unit 1 is operating at 100% power, normally aligned. – 1RY8010C, PZR SAFETY VLV inadvertently lifts. Thirty (30) seconds later: – 1PI-469 PRT PRESS indicates 10 psig. – 1PI-455A PZR PRESS indicates 1985 psig. With the above indications, which of the following, most closely approximates the expected temperature on 1TI-464, SAF REL VLV C TEMP?

A. 150F

B. 195F

C. 245F

D. 280F

#41. Given the following sequence of events: – A medium break RCS LOCA occurred on loop 1A – 1BwEP ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION was in progress at step 1, when status tree monitoring identified a red path for Integrity due to 1A cold leg temperature and excessive cool down rate. – The crew performed the actions of 1BwFR-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK and 1A loop temperature has stabilized. With the above conditions, which of the following describe the mitigation strategy that will be used for the LOCA?

A. Further RCS cooldown CANNOT commence until after a 1 hour soak. Subsequent cooldown must be <50F in any 1 hour period.

B. Further RCS cooldown CAN commence immediately. The maximum allowable cooldown must be <50F in any 1 hour period.

C. Further RCS cooldown CANNOT commence until after a 1 hour soak. Subsequent cooldown can be up to 200F in any 1 hour period.

D. Further RCS cooldown CAN commence immediately ONLY in the unaffected loops. The 1A loop temperature must remain stable for 1 hour.

#42. – A loss of CC flow to an RCP has occurred on Unit 1. – 1BwOA RCP-2 LOSS OF SEAL COOLING was entered and the NSO is monitoring the RCP lower radial bearing temperature. What RCP lower radial bearing temperature is listed in the Operator Action Summary of 1BwOA RCP-2 as requiring a reactor trip?

A. >150F

B. >184F

C. >225F

D. >235F

#43. – Unit 2 is at 75% power, MOL, normally aligned. – 2CV182, CHG HDR BACK PRESS CONTROL VLV controller has failed to zero demand. – The crew is performing 2BwOA PRI-15 LOSS OF NORMAL CHARGING. – Letdown has been isolated. – A VCT automatic makeup is occurring. When the NSO verifies proper RMCS operation, which of the following valve alignments is correct? BORIC ACID PW TO BORIC ACID BORIC ACID TO BLNDR BORIC ACID BLNDR TO BLNDR BLNDR CHG PMPS TO VCT 2CV110A 2CV111A 2CV110B 2CV111B

A. throttled closed open closed

B. throttled throttled open closed

C. closed throttled closed open

D. closed throttled open open

#44. – Unit 2 is in Mode 5. – RCS pressure is 100 psig. – 2A CV pump is in operation. – VCT pressure is 15 psig. – U-0 CC Pump and HX are mechanically aligned to Unit 2. – 2A RH pump is running in the shutdown cooling mode. – Unit 2 FC cooling loop is in operation. The following MCR indications are noted: – Annunciator 2-2-A5, CC SURGE TANK LEVEL HIGH LOW alarms. – CC Surge Tank level indication is 65% and slowly RISING. With the above conditions, a tube leak in which one of the following heat exchangers would cause the CC surge tank level rise?

A. 2A RH Hx

B. U-2 FC Hx

C. U-0 CC Hx

D. U-2 Seal Water Hx

#45. – Unit 1 is in a refuel outage . – Unit 2 is in Mode 4, in a forced outage. – 2B RH train is in shutdown cooling. – The Unit 0 CC HX is aligned to Unit 1 supplying BOTH 1A and 2A RH loops. The following occurs: – A large leak in the Unit 2 CC system causes both U-2 CC pumps to trip. – The crew enters 2BwOA PRI-6, COMPONENT COOLING MALFUNCTION. In the current system configuration, which of the following describes the preferred mitigation strategy for RCS heat removal?

A. Continue 2B RH train operation.

B. Secure 2B RH shutdown cooling AND steam the SGs.

C. Secure 2B RH shutdown cooling AND initiate bleed and feed.

D. Swap shutdown cooling to the 2A RH train.

#46. – Unit 1 is at 100% power. – Pzr pressure control is automatic. – PRESS CONT CH SELECT switch is in 457/458 position at 1PM05J. – Pzr pressure transmitter 1PT-457 has failed full scale HIGH. – No operator action is taken. Which ONE of the following describes the initial response of the Pzr PORVs?

A. 1RY-455A remains closed and 1RY-456 opens.

B. 1RY-455A opens and 1RY-456 remains closed.

C. BOTH PORVs remain closed.

D. BOTH PORVs open.

#47. – Unit 1 has experienced an ATWS condition and the crew is performing 1BwFR-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS, at step 2, VERIFY TURBINE TRIP. – Attempts to manually trip the turbine have been UNSUCCESSFUL from the trip pushbutton and the OWS graphic 5512. With the above conditions, per 1BwFR-S.1, the NSO will run back the turbine…

A. at OWS graphic 5501 by selecting MANUAL, then selecting RAPID, then selecting and holding GV lower arrow.

B. at 1PM02J by depressing 1HS-EH019 CD/FW runback pushbutton.

C. at OWS graphic 5501 by programming a REF DEMAND of 0, then programming a LOAD RATE of 250 MW/MIN, then selecting GO.

D. at OWS graphic 5512 by selecting START CD/FW RUNBACK.

#48. – BOTH units are at 100% power normal alignment. The following sequence of events occurs: – Lightning in the switchyard faults Unit 1 SATs. – Unit 1 trips and loses ALL AC power. – Both Unit 1 ESF buses are cross tied to Unit 2. – The NSO is currently crosstying bus 144 to 142 per 1BwCA-0.1, LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED. The MAJOR reason for cross tying bus 144 and bus 142 is to energize the…

A. 0A fire pump.

B. 0B WS pump.

C. Unit 1 SAC.

D. pressurizer heaters.

#49. – Unit 1 is at 100% power, normal alignment. – A loss of off site power occurs. Time Event 0 sec. 1A DG re-energizes bus 141. +17 sec. (now) The NSO is monitoring ESF equipment sequencing. From the following, which load will be sequenced on to bus 141 NEXT, and why?

A. 1A CV pump to ensure RCS inventory control.

B. 1A CC pump to ensure cooling of potentially contaminated equipment.

C. 1A AF pump to ensure a secondary heat sink.

D. 1A SX pump to ensure cooling of ESF equipment.

#50. – 1A DG is running in EMERGENCY mode and carrying the ESF bus loads following an undervoltage on bus 141. – Subsequently, a loss of DC bus 111 occurs. In response to the loss of DC, the 1A DG will…

A. NOT trip and continue to supply bus 141 loads.

B. trip due to an overspeed condition.

C. trip due to combustion air butterfly valve closing.

D. trip due to fuel control cylinder expanding to “OFF” position.

#51. – Unit 2 is at 75% power, normal alignment. – The 2A Regen Heat Exchanger is in service. The following sequence of events occurs: – A control power fuse for 2IA066, INSTRUMENT AIR INSIDE CNMT ISOL VLV, blows in 2PM11J. – Instrument Air to Unit 2 containment is isolated and ALL CVCS valves are in their fail position. – Five (5) minutes later, the defective fuse is replaced, and 2IA066 is re-opened. – Instrument air is fully restored to Unit 2 containment. NO other operator actions were taken. (i.e. assume all CVCS valve control switches have NOT been moved from their normal at power alignment) With the above conditions, the NSO monitoring 2PM05J will note which of the following letdown valves has automatically re-opened.

A. 2CV459, LTDWN LINE ISOL VLV

B. 2CV8389A, LTDWN TO REGEN HX 2A ISOL VLV

C. 2CV8149A, 45 GPM LTDWN ORIF 2A ISOL VLV

D. 2CV8160, LTDWN LINE CNMT ISOL VLV

#52. – Braidwood Station has been notified that the State Estimator alarm predicts a potential degraded grid condition in the event of a Braidwood unit trip. – The crew is performing 0BwOA ELEC-1, ABNORMAL GRID CONDITIONS, ATTACHMENT A, STEP 1, CALCULATE UNIT 1 4KV NON-ESF BUS LOADING. Which of the following parameters are MULTIPLIED TOGETHER to calculate NON-ESF BUS LOADING?

A. bus volts and feed breaker amps

B. UAT watts and bus volts

C. feed breaker amps and generator VARS

D. generator VARS and UAT watts

#53. – Unit 1 was at 100% power with ESF bus 142 de-energized due to a bus fault. – Subsequently, a manual reactor trip and SI occur due to a pressurizer safety valve stuck partially open. – The MCR receives a report that a large amount of water is leaking in the U-1 containment penetration area. – The crew transitions to 1BwCA-1.2, LOCA OUTSIDE CONTAINMENT, with all 1A train ECCS pumps still operating. The following indications are CURRENTLY noted on the MCB: – RCS pressure is 1700 psig and stable. – 1A RH discharge flow is 0 gpm. – 1A SI pump discharge flow is 200 gpm. – 1A CV pump flow is 300 gpm. The leak can be reduced by closing… (assume the leak is ALL RWST water)

A. 1SI8801A, CHG PMPS TO COLD LEG INJ ISOL VLV and stopping the 1A CV pump.

B. 1SI8835, SI PMPS TO COLD LEG ISOL VLV and stopping the 1A SI pump.

C. 1SI8809A, RH TO COLD LEG 1A & 1D ISOL VLV and stopping the 1A RH pump.

D. 1SI8809B, RH TO COLD LEG 1B & 1C ISOL VLV and stopping the 1A RH pump.

#54. – Unit 1 is experiencing a loss of heat sink condition with the following plant parameters: – ALL ECCS pumps are RUNNING. – ALL SG WR levels are 50%. – RCS pressure is 2200 psig. – Containment pressure is 1.4 psig. – The crew is performing 1BwFR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK at step 4, trying to re-establish AF flow. With the above conditions, which one of the following conditions would require the crew to immediately initiate Bleed and Feed? (consider each choice separately)

A. RCS pressure rises to 2300 psig.

B. Containment pressure rises to 5.2 psig.

C. ALL SG WR levels drop to 20%.

D. 1A CV pumps trips.

#55. – An RCS LOCA occurred on Unit 1. – 1SI8811A/B, CNMT SUMP ISOL VLVs, are CLOSED and CANNOT be opened. – 1BwCA-1.1 “LOSS OF EMERGENCY COOLANT RECIRCULATION” was entered. – Minimum ECCS flow to remove decay heat has been established per 1BwCA-1.1. With the above conditions and in accordance with 1BwCA-1.1, the NSO monitoring plant parameters will raise RCS make-up flow if…

A. pressurizer level drops to 0%.

B. RVLIS HEAD region drops to 31%.

C. hot leg wide range temperatures rise by 5F.

D. core exit thermocouples rise by 5F.

#56. – 10 minutes ago Unit 2 experienced a reactor trip and SI due to an unisolable fault of ALL steam generators. – Bus 242 is faulted. – The 2A AF pump has tripped on overcurrent. – 2BwCA-2.1″UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS” is in progress. – RCS Cold leg temperatures are 425F. – ALL SG narrow range levels indicate 0%. – The MCR valve controller for 2AF005H, 2D SG FLOW CONT VLV, is failed in the full demand (open) position. – All OTHER equipment operates as designed. With the above conditions, to meet the 2D SG AF flow requirement of 2BwCA-2.1, the…

A. 2AF005H valve can be throttled at the RSP or locally.

B. 2AF005H valve can ONLY be throttled at the RSP.

C. 2AF013D, SG 2D ISOL VLV, can be throttled from the MCR.

D. 2AF013H, SG 2D ISOL VLV, can be throttled from the MCR.

#57. – Unit 1 was at 95% power normal alignment, ramping to 100%, when the following occurs: – During an automatic rod step, Control Bank D, Rod M-12 drops part way into the core. – Rod M-12 DRPI now indicates 120 steps. – All other CB-D DRPI indications are 198 steps. – DRPI ACCURACY MODE SWITCH is in A+B position. – The crew enters 1BwOA ROD-3, DROPPED OR MISALIGNED ROD, and determines that the failure occurred in rod control, but NOT DRPI. Based on the above conditions, the LOWEST possible ACTUAL position of Rod M-12 is ______ steps.

A. 108

B. 110

C. 116

D. 120

#58. – Unit 1 is at 100% power, normal alignment. – A tube leak develops on the 1C S/G and the crew enters 1BwOA SEC-8, STEAM GENERATOR TUBE LEAK. – Leak rate conditions have stabilized, and the NSO is determining the tube leak rate. – The following are indications on 1PM05J. – 1FI-121A, CHG HDR FLOW 94.0 gpm – 1FI-132, LTDWN LINE FLOW 75.0 gpm – 1FI-142A thru 145A, RCP 1_ SEAL WTR FLOW 8.5 gpm per RCP – 1FT-158 thru 161, RCP 1_ SEAL LEAKOFF FLOW 3.4 gpm per RCP – 1LI-459A PZR LEVEL 60% and stable – Excess Letdown Isolated. Based on the above indications, U1 Primary to Secondary leakage is ____ gpm.

A. 5.4

B. 19.0

C. 39.4

D. 53.0

#59. – Liquid radwaste is being processed through the radwaste portable demineralizers in the truck bay. – A significant leak develops at the demineralizer inlet, spraying radioactive water into the surrounding area. – The leak has caused an ALERT condition alarm at the MCR RM-11. Which ONE of the following radiation monitors will indicate this ALERT condition?

A. 0PR11J, RADWASTE EVAP CUBICLE

B. 0PR26J, RADWASTE VENT

C. 1PR28J, UNIT 1 AUX BLDG VENT STACK EFFLUENT

D. 0AR55J, FHB FH INCIDENT

#60. – Maintenance is performing surveillance testing of fire (smoke) detectors on Unit 1. – One detector has failed to actuate and maintenance has requested to remove the detector from its base so it can be repaired/tested at the EM shop. – Currently all alarms are clear on panel 1PM09J. When the detector is removed, which is the correct alarm the MCR should receive in the associated 1PM09J detection zone?

A. TROUBLE

B. TROUBLE WIRE OPEN

C. FIRE

D. FIRE WIRE OPEN

#61. – Unit 1 is at 100% power. – Excess Letdown is in service due to normal letdown being unavailable. – A Unit one containment release is in progress. – All other systems are normally aligned. The following event occurs: – A reactor trip and SI. – The crew is performing 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION. During steps 8 and 9, checking Group 3 CNMT isol monitor lights and Group 6 CNMT VENT isol monitor lights, the following lights are NOT lit. – 1CC9437B, CC FROM EXC LTDWN HX ISOL VLV – 1CV8100, SEAL WTR RETURN CNMT ISOL VLV – 1VQ005C, MINI-FLOW PRG EXH OUTSIDE ISOL VLV – 1IA065, INST AIR HDR OUTSIDE CNMT ISOL VLV – All OTHER Group 3 CNMT isol and Group 6 CNMT VENT isol lights are LIT. With the above conditions, which of the following systems has a containment penetration that is NOT isolated?

A. Component Cooling Water (CC)

B. Seal Water Return (CV)

C. Containment Mini-Purge (VQ)

D. Instrument Air (IA)

#62. – Unit 1 reactor power is 65% and stable. – Main Generator load is 800 MW and stable. – 1C zone Main Condenser vacuum is 1.6 in. HgA and stable. The following occurs: – 1100: A Condenser air leak develops in the 1C zone causing Main Condenser pressure to RISE at a constant rate of 0.2 inches HgA/minute. – 1109: A ramp down at 10 MW/minute is commenced in an attempt to stabilize condenser pressure. – Field activities are ongoing to find and isolate the condenser leak. – The NSO is directed to monitor current parameters and keep the crew informed before reaching reactor trip criteria. With the above conditions, which of the following is the closest approximate time the unit will reach the unacceptable region of Figure 1BwOA SEC-3-1? (assuming the Load DROP rate remains constant and the rate of Main Condenser pressure RISE remains constant throughout the event) (Note: Figure 1BwOA SEC-3-1 is attached.)

A. 1119.

B. 1124.

C. 1127.

D. 1132.

#63. – Unit 1 is at 100% with pressurizer pressure channel, 1P-455 in test. – ALL other equipment is in normal alignment. – Subsequently, pressurizer pressure transmitter 1PT-458 fails low causing a low pressurizer pressure SI. – Five minutes later, the crew has transitioned to 1BwEP ES-1.1, SI TERMINATION. – The NSO depresses BOTH SI RESET pushbuttons. – The BYPASS – PERMISSIVE LIGHTS silence, acknowledge, and reset pushbuttons are depressed. With the above conditions, which of the following BYPASS – PERMISSIVE LIGHTS will be lit?

A. SI ACTUATED

B. PZR LOW PRESS SI BLOCK PERMISSIVE P11

C. PZR SI BLOCKED TRN A

D. AUTO SI BLOCKED

#64. – 1BwEP ES-0.2 “NATURAL CIRCULATION COOLDOWN” is in progress. – As RCS pressure is lowered through 1300 psig, a rapid rise in PZR level is observed. – Charging and letdown flow are approximately equal. – The RCS cooldown rate is 25 oF/hr. The rapid rise in PZR level indicates that…

A. natural circulation has stopped, RCS cooldown rate should be raised.

B. SI accumulators have injected, the accumulators should be isolated.

C. the reactor head is voiding, RCS pressure should be raised.

D. RCS mass is rising, excess letdown should be placed in service.

#65. – Unit 1 is at 100% power, normal alignment. – A loss of off site power occurs (LOOP). – All equipment operates as designed. Two minutes after the LOOP, the NSO monitoring 1PM04J notes two SG PORV controllers with abnormal indications. The NSO then depresses a pushbutton on both the 1A and 1D SG PORV controllers because…

A. the automatic function is currently NOT available and the controllers need to be placed in MANUAL for SG over pressure protection.

B. an integral function has accumulated in the controllers and the signal needs to be cleared for proper SG PORV operation.

C. the controllers are currently de-energized and need to be placed in manual to enable LOCAL SG PORV operation.

D. the controllers have defaulted to manual mode and the controllers need to be placed in AUTO for SG over pressure protection.

#66. In accordance with OP-AA-111-101 Operating Narrative Logs and Records, if an erroneous log entry is on a hand written or printed record, the correction should be made by…

A. completely blacking out the erroneous entry and inserting corrected information.

B. drawing a single line through the erroneous entry and inserting corrected information.

C. discarding the erroneous record and recreating a correct record.

D. writing “DELETE” in the left hand column next to the erroneous entry and inserting corrected information.

#67. In accordance with OU-AP-200, ADMINISTRATIVE CONTROLS DURING FUEL HANDLING ACTIVITIES FOR BYRON AND BRAIDWOOD, which of the following requires suspension of fuel assembly movements in containment?

A. Loss of one Gamma Metrics source range post accident neutron monitor.

B. Refueling cavity boron concentration drops by 25 ppm from yesterday’s sample to today’s sample.

C. Sustained wind in the area of 35 mph.

D. Refueling cavity water level is 23′ 6″ above the top of the Reactor Vessel Flange.

#68. – Unit 1 is in a refueling outage. – Fuel movements began 24 hours ago and are currently in progress. – At 1700 hours, the Fuel Handling Supervisor calls the Control Room and requests that the operating RH pump be stopped to allow fuel movement near the hot leg nozzle. – NO other activities affecting the RCS are in progress. Upon reviewing the unit logs, the NSO determines the following: – The RH pump was stopped at 0700 for 15 minutes to allow fuel movement. – The RH pump was stopped again at 1300 for 30 minutes for the same purpose. At 1700 hours, per Tech Specs, the maximum time the RH pump can be secured without violating RHR loop requirements is…

A. 0 minutes.

B. an additional 15 minutes

C. an additional 30 minutes.

D. an additional 60 minutes

#69. – Unit 1 is at 100% power, normal alignment. – Maintenance is performing 4 KV and 6.9 KV breaker cubicle inspections. – The inspections require each breaker to be racked out, inspected/cleaned, then racked back in. Which one, of the following normally open breakers, would require an LCO 3.8.1, AC SOURCES OPERATING, entry during the inspection?

A. ACB 1411

B. ACB 1414

C. ACB 1432

D. ACB 1572

#70. – Plant conditions have been stable for the past 15 minutes. – Loop 1A TAVE is 572.0 F. – Loop 1B TAVE is 570.0 F. – Loop 1C TAVE is 570.0 F. – Loop 1D TAVE is 568.0 F. – TREF is 568.0 F. – The Rod Bank Select Switch is in MANUAL. If the Rod Bank Select Switch is placed in AUTO, the control rods would initially …

A. NOT step.

B. step IN at 8 steps/minute.

C. step IN at 40 steps/minute.

D. step IN at 54 steps/minute.

#71. The following conditions exist: – A General Emergency has been declared due to a Large Break LOCA. – A High Radiation area needs to be accessed to PROTECT VALUABLE PROPERTY. – An Emergency Responder has volunteered to perform the job. – The volunteer has a current year to date exposure of 3 Rem. Which one of the following describes the MAXIMUM dose the emergency responder is allowed to receive for this activity?

A. 7 REM TEDE

B. 10 REM TEDE

C. 22 REM TEDE

D. 25 REM TEDE

#72. – A Unit 2 Containment Release is in progress per BwRP 6110-13T1, CONTAINMENT RELEASE FORM. Currently, the RUNNING Aux Bldg Vent Stacks exhaust fans are: – 0VA02CA, VA EXH FAN 0A TRN 0A – 0VF01CA, FILTERED TANK VENTS EXH FAN – 0VL02CA, LAB HVAC FUME HOOD EXH FAN 0A – 0VW03CA, RADWASTE BLDG EXH FAN 0A – ALL other Aux Bldg Vent Stacks exhaust fans and charcoal booster fans are shutdown. With the above condition, which one of the following fan trips would require the operator to secure the Unit 2 Containment Release? (Consider each choice separately and do NOT assume ANY standby fans are started.)

A. 0VA02CA trips.

B. 0VF01CA trips.

C. 0VL02CA trips.

D. 0VW03CA trips.

#73. Concerning Radiation Monitors with interlock functions: Which one of the following RM-11 icon conditions will actuate the interlock function?

A. Magenta, COMMUNICATIONS

B. Dark Blue, OPERATE FAILURE

C. Yellow, CHANNEL ALERT ALARM

D. Half Cyan (grey), CONTROL FUNCTION

#74. While transitioning to 1BwEP-1, “Loss of Reactor or Secondary Coolant,” after completing the actions of 1BwEP-0, “Reactor Trip or Safety Injection,” an orange path is identified under SUBCRITICALITY. With regard to implementing 1BwFR-S.1, “Response to Nuclear Power Generation/ATWS”, procedure usage rules require the crew to…

A. continue current pass through the status trees, if NO red condition is encountered, then implement 1BwFR-S.1.

B. complete the actions of 1BwEP-1, then implement 1BwFR-S.1.

C. immediately implement 1BwFR-S.1, then continue current pass through the status trees.

D. implement 1BwFR-S.1 at the discretion of the Shift Manager.

#75. – Unit 1 is at 100% power, normal alignment, when a fire occurs in the plant. – MCR annunciator 0-37-A4, UNIT 1 AREA FIRE, alarms. – The assist NSO is performing the Immediate Operator Actions per BwAR 0-37-A4. – Personnel have been dispatched to investigate and extinguish the fire. – The fire is determined to be in a specific zone and of sufficient magnitude to prompt further Immediate Operator Actions. Per BwAR 0-37-A4, the further Immediate Operator Actions are intended to prevent…

A. loss of Diesel Generators’ control power.

B. inadvertent Reactor Head Vent Valves opening.

C. inadvertent Containment Spray actuation.

D. loss of Charging Pumps suction source.

#76. – Unit 1 is at 90% power, all systems normally aligned for the current power level. The following occurs: – A failure of 1CC130A controller causes letdown temperature to drop to 75F. Based on the above conditions and assuming NO operator actions are taken, the plant response will be (1) , AND the correct procedure the US will enter to mitigate the event is (2) .

A. (1) Control Rods will step IN (2) 1BwOA PRI-12 UNCONTROLLED DILUTION

B. (1) 1CV129, DEMIN HI TEMP LTDWN DIVERT VLV will OPEN (2) 1BwOA PRI-6 COMPONENT COOLING MALFUNCTION

C. (1) Control Rods will step OUT (2) 1BwOA PRI-6 COMPONENT COOLING MALFUNCTION

D. (1) Reactor Power will RISE above 100% (2) 1BwOA PRI-16 RESPONSE TO OVERPOWER CONDITION

#77. – Unit 2 is at 100% power, normal alignment. – An INADVERTENT SI occurs. – One minute later, the ECCS high head injection header ruptures BETWEEN 2SI8801A, CHG PMPS TO COLD LEG INJ ISOL VLV and containment. – NO other leaks exist. Current plant conditions are: – 2FI-917 HIGH HEAD SI FLOW is pegged HIGH. – Pressurizer level is 28% and STABLE. – Pressurizer pressure is 2100 psig and slowly RISING. – RCS temperature is 557F and STABLE. – The crew has just completed the Immediate Actions steps of 2BwEP-0, REACTOR TRIP OR SAFETY INJECTION. With the above conditions and in accordance with proper procedural usage, the leak will be isolated by MCR actions performed in…

A. 2BwEP ES-1.1, SI TERMINATION.

B. 2BwOA PRI-1, EXCESSIVE PRIMARY PLANT LEAKAGE.

C. 2BwEP-1, LOSS OF REACTOR OR SECONDARY COOLANT.

D. 2BwCA-1.2, LOCA OUTSIDE CONTAINMENT.

#78. – Both Units are at 100% power, normally aligned. – 1A SX Pump AND 2B SX Pump are RUNNING. Unusually warm weather has caused the following elevated temperatures: – 1A SX pp disch temp = 102.0F – 2B SX pp disch temp = 99.0F Concerning the following LCOs: 3.7.8 SX SYSTEM 3.7.9 ULTIMATE HEAT SINK With the above conditions, the Tech Spec LCO entry(ies) required is(are) (1) because ____(2) .

A. (1) ONLY 3.7.8 on Unit 1 ONLY (2) the SX train may not be sufficient to remove decay heat loads.

B. (1) ONLY 3.7.8 on BOTH units (2) the SX trains may not be sufficient to remove decay heat loads.

C. (1) 3.7.8 for Unit 1 ONLY AND 3.7.9 for Unit 1 ONLY (2) the containment air temperature may exceed the peak assumed temp in the accident analysis.

D. (1) ONLY 3.7.9 for BOTH units (2) the SX system loads may exceed maximum design temperatures within 30 days of a DBA LOCA.

#79. – Unit 1 is at 100% power. – Instrument Bus 114 is faulted. – An overcurrent relay problem has caused breaker 1415X, Bus 141 Feed to Xfmr 131X, to trip open and bus 131X CANNOT be reenergized. The following subsequently occurred:

– A large break RCS LOCA. – Containment pressure is 26 psig. – The crew has just completed the Immediate Actions steps of 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION. – NO other operator actions have been taken. Currently, with the above conditions, the US will…A. continue in 1BwEP-0, because there is at least one CS pump running.

B. transition to 1BwFR-Z.1 RESPONSE TO HIGH CONTAINMENT PRESSURE, because there are NO CS pumps running.

C. perform 1BwOA ELEC-2 LOSS OF INSTRUMENT BUS, while continuing with 1BwEP-0, even though one CS pump is running.

D. continue in 1BwEP-0, even though there are NO CS pumps running.

#80. – Unit 1 has experienced a loss of all AC power. – Unit 2 has NOT been affected. – The 1A DG is OOS in maintenance outage mode. – The 1B DG is running, but breaker 1423 failed to close automatically AND manually. – The crew is performing 1BwCA-0.0 LOSS OF ALL AC POWER, at step 5, TRY TO RESTORE POWER TO ANY/BOTH UNIT 1 4KV ESF BUSES. With the above conditions, the NEXT action the US will direct is…

A. depress the SI RECIRC SUMP ISOL VLV pushbuttons to remove a trip signal from breakers 1411 and 1421 to allow for ESF bus to non-ESF bus cross ties.

B. place the 1B DG control switch at 1PM01J in PTL to prevent the blackout sequencer from automatically loading bus 142.

C. depress the EMERGENCY STOP pushbutton on the 1B DG to remove a trip signal from breaker 1424 to allow for ESF bus 142 cross tie to Unit 2.

D. SYNC and close breaker 1424 to prepare for ESF bus 142 cross tie to Unit 2.

#81. – New Fuel receipt activities are being conducted in compliance with applicable procedure and Tech Spec/TRM requirements. – A cask containing new fuel is being transferred from the transport vehicle to the new fuel inspection area where another cask containing new fuel is already placed. – During transfer, the fuel handling building crane hoist brake fails, and the cask is descending quickly. Based on the above conditions, identify the ONE selection below that predicts the impact of the load drop?

A. The cask may damage spent fuel in the pool because the crane must travel over the pool to reach the new fuel inspection area.

B. The cask will not damage spent fuel in the pool because the crane is administratively AND mechanically/electrically prohibited from traveling over the pool.

C. The cask should not damage spent fuel in the pool because the crane is administratively ONLY (not mechanically/electrically) prohibited from traveling over the pool.

D. If the descending cask contacts the second cask, the minimum “edge to edge” distance requirement for new fuel will be violated.

#82. – A small break LOCA has occurred on Unit 1. During the initial performance of 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION, at step 15, the following plant conditions are noted: – Containment pressure 6 psig and rising. – CETCs indicate 820F. – RCS pressure is 1750 psig and stable. – S/G pressures are 1175 psig. – Both AF pumps failed to start and CANNOT be manually started. – S/G levels (NR): 1A S/G 25%, 1B S/G 24%, 1C S/G 26%, 1D S/G 30% Based on the above conditions, the NEXT procedure the US will transition to is…

A. 1BwEP-1 LOSS OF REACTOR OR SECONDARY COOLANT, because SG levels are currently adequate.

B. 1BwFR-C.2 RESPONSE TO DEGRADED CORE COOLING, because core cooling is the highest priority safety function not being met.

C. 1BwFR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK, and 1BwFR-H.1 will be performed because a secondary heat sink is necessary.

D. 1BwFR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK, then immediately transition to 1BwFR-C.2 RESPONSE TO DEGRADED CORE COOLING because a secondary heat sink is NOT required.

#83. – Unit 1 is in MODE 4 after a normal shutdown and cooldown in accordance with all procedures. – RCS Pressure was manually depressurized to 350 psig. – SI Accumulators are ISOLATED. A few minutes ago a Containment Area Rad monitor alarmed and the crew noted the following: – PZR Level is DROPPING. – Letdown is ISOLATED. – Charging flow is 200 gpm. With the above conditions, the next procedure the US will enter is ____________________, because it contains the specific actions to mitigate these conditions.

A. 1BwOA PRI-1 EXCESSIVE PRIMARY PLANT LEAKAGE.

B. 1BwOA S/D-2 SHUTDOWN LOCA.

C. 1BwOA PRI-4 HIGH REACTOR COOLANT ACTIVITY.

D. 1BwEP-1 LOSS OF REACTOR OR SECONDARY COOLANT.

#84. – Unit 1 is at 400F during a plant startup. – 1C and 1D RCPs are in OPERATION. – Due to unsatisfactory oil samples, 1A and 1B RCPs are OOS for maintenance. – The Control Rod Drive MG sets are operating and the Reactor Trip Breakers are closed for testing. – The RCS is being diluted to ECC boron concentration. The following occurs: – A seal leakoff problem develops with the 1C RCP and the 1C RCP is tripped. With the above conditions, which one of the following actions must be taken?

A. Initiate action to place 1 train of RH in service immediately.

B. Initiate action to restore one RCP immediately.

C. Verify Shutdown Margin is within limits of the COLR within one hour.

D. Open the Reactor Trip Breakers within one hour.

#85. Operating within Tech Spec limiting conditions, ensures that during a steam generator tube rupture the dose limits of 10 CFR 50.67 are NOT exceeded. These limits are (1) rem TEDE for an individual at the boundary of the exclusion area for 2 hours OR (2) rem TEDE for an individual in the Main Control Room for the duration of the event.

A. (1) 50 (2) 25

B. (1) 10 (2) 15

C. (1) 15 (2) 10

D. (1) 25 (2) 5

#86. – Unit 1 is at 100% power normal alignment. An event occurs and one minute later the following indications are noted: – Annunciator 1-1-A2, CNMT DRAIN LEAK DETECT FLOW HIGH is in alarm. – Reactor Power is 102% and slowly rising. – Auctioneered Tavg is 585F and slowly lowering. – Containment Pressure is approximately 2 psig and slowly rising. – Pressurizer level is 57% and slowly lowering. – Pressurizer pressure is 2210 psig and slowly lowering. With the above indications, the US will direct the crew to…

A. trip the reactor and enter 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION, because there is a primary RCS break in containment.

B. enter 1BwOA PRI-16, RESPONSE TO OVERPOWER CONDITION, and reduce turbine load because there is a dilution event in progress.

C. enter 1BwOA PRI-1, EXCESSIVE PRIMARY PLANT LEAKAGE, because there is a primary RCS break in containment.

D. trip the reactor and enter 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION, because there is a secondary steam break in containment.

#87. – Unit 1 was operating at 100% power, normal alignment for the past 6 months. – 30 minutes ago, a feedwater malfunction caused the crew to perform a CD/FW RUNBACK from 100% power. With the above condition, which of the following LCO/TRM surveillance frequencies specifically require an additional performance of the surveillance because of the unit ramp? (assume all required pre-transient surveillances were completed within the 12 hours preceding the ramp)

A. 3.4.b RCS CHEMISTRY verifying RCS chemistry is within limits.

B. 3.4.13 RCS OPERATIONAL LEAKAGE verifying operational leakage is within limits.

C. 3.4.16 RCS SPECIFIC ACTIVITY verifying dose equivalent I-131 within limits.

D. 3.7.3 SECONDARY SPECIFIC ACTIVITY verifying dose equivalent I-131 within limits.

#88. – Unit 1 has experienced a reactor trip and SI from 100% power. – All equipment operated as designed. – The crew has transitioned to 1BwEP ES-1.1, “SI TERMINATION” from 1BwEP-1 “LOSS OF REACTOR OR SECONDARY COOLANT”. – At step 4 of 1BwEP ES-1.1, the team secures all but one charging pump as directed. – After one charging pump is secured, RCS Pressure begins to slowly and steadily LOWER. With the above conditions, the US will direct the crew to…

A. manually re-initiate SI and transition to 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION.

B. re-start the charging pump to stabilize RCS pressure and continue with 1BwEP ES-1.1.

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

D. re-start the charging pump to stabilize RCS pressure and transition back to 1BwEP-1.

#89. – Unit 1 at 100% power. – 1B CV pump danger tagged OOS, 24 hours ago and LCO 3.5.2, ECCS OPERATING has been entered. – 0B Fire Pump is danger tagged OOS. – All other systems are normally aligned. The following event occurs: – The SX header supply to “1A” train ECCS pumps ruptures and manual valve 1SX013A, SX SUP TO TRAIN A HXs, is locally closed, isolating SX to ALL the 1A train ECCS pumps AND cubicle coolers. – The crew entered LCO 3.7.8, SX SYSTEM and is performing 1BwOA PRI-8, ESSENTIAL SERVICE WATER MALFUNCTION. – An EO is having difficulty aligning fire protection (FP) to the 1A CV pump oil coolers. – At 0901 hours, the 1A CV pump temperatures are: All pump bearing temps – 130F and RISING at 5F/min. Gear drive oil temp – 95F and RISING at 10F/min. (assume the rates of temperature rise remain constant unless cooling is restored) (1) Assuming FP is NOT aligned to the 1A CV pump oil coolers, 1A CV pump temperatures will initially reach trip limits at… Note: 1BwOA PRI-8, Table A is attached. (2) Assuming FP IS aligned to the 1A CV pump oil coolers prior to reaching a pump trip limit AND the plant remains in that configuration, per Tech Specs the 1A CV pump will be considered…

A. (1) 0909 (2) OPERABLE with no loss of safety function.

B. (1) 0909 (2) INOPERABLE because a loss of safety function exists.

C. (1) 0916 (2) OPERABLE with no loss of safety function.

D. (1) 0916 (2) INOPERABLE because a loss of safety function exists.

#90. – Unit 1 was at 100% power normal alignment. An event occurs and the following indications are noted at 1PM05J. – Multiple block 10 annunciators are in alarm. – Auctioneered high Tave is 4F BELOW Tref and stable. – ONE DRPI Rod Bottom light is LIT. – Control rods bank D automatically stepped OUT 3 steps and then STOPPED stepping. – Power Range NIs are stable at: N41- 101% N42- 101% N43- 77% N44- 105% With the above conditions the US will direct the crew to…

A. enter 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION, due to the NI channel indications.

B. enter 1BwOA ROD-1, UNCONTROLLED ROD MOTION, due to the outward rod motion.

C. enter 1BwOA ROD-2, FAILURE OF RODS TO MOVE, due to the Tave/Tref mismatch.

D. enter 1BwOA ROD-3, DROPPED OR MISALIGNED ROD, due to the DRPI indications.

#91. – A reactor trip and Safety Injection have occurred on Unit 1. – The crew was performing actions of 1BwEP-1, LOSS OF REACTOR OR SECONDARY COOLANT. – Due to conflicting indications, the crew entered 1BwEP ES-0.0, REDIAGNOSIS. – While performing 1BwEP ES-0.0, the crew determines that there is a rising trend on secondary plant radiation monitors AND one SG level is rising faster than the other three with Auxiliary Feedwater flow being equal. Which one of the following describes how the US will transition from 1BwEP ES-0.0, REDIAGNOSIS to the correct procedure?

A. Return to 1BwEP-0 diagnostic steps to verify indications then transition to 1BwEP-3.

B. Go directly to 1BwEP-3 or 1BwCA-3 series procedure.

C. Return to 1BwEP-1 step in effect and use the Operator Action Summary page for transition to 1BwEP-3.

D. Use Heat Sink status tree for transition to 1BwFR-H.3, RESPONSE TO STEAM GENERATOR HIGH LEVEL.

#92. – 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 and the RCS loops are available. – CETCs are 1235F and slowly rising. With the above conditions, the US will direct the crew to…

A. immediately start an RCP regardless of the support conditions.

B. remain at step 16 until support conditions are established, then start an RCP.

C. NOT start an RCP and continue with the procedure using another mitigation strategy.

D. continue with the procedure while attempting to establish support conditions, then return to step 16 when support conditions are established.

#93. – Unit 1 experienced a faulted SG in containment. – The crew is performing 1BwEP ES-0.2, NATURAL CIRCULATION COOLDOWN. The STA monitoring the Critical Safety Functions notes the following indications: – Reactor Power 6 % – SUR on both IR and SR channels 0.2 DPM – Containment Pressure 21 psig – CETCs Average of 10 highest 280F – RCS Pressure 480 psig 1A 1B 1C 1D- RCS Cold leg temperatures. 245F 260F 275F 275F – Narrow Range S/G Levels 0% 40% 42% 41% – Total available Feed Flow to S/Gs 0 gpm 0 gpm 0 gpm 0 gpm With the above indications, the US will transition to…

A. 1BwFR S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS.

B. 1BwFR H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK.

C. 1BwFR P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION.

D. 1BwFR Z.1, RESPONSE TO HIGH CONTAINMENT PRESSURE.

#94. Per BwAP 340-1, USE OF PROCEDURES FOR OPERATING DEPARTMENT, which of the following correctly describe when an emergency procedure step on the Continuous Action Summary page, is applicable?

A. Only PRIOR to performing the step in the main body of the procedure, AND it MAY apply after a transition is made to another procedure.

B. Only after proceeding PAST the step in the main body of the procedure, AND it MAY apply after a transition is made to another procedure.

C. Only after proceeding PAST the step in the main body of the procedure, BUT it will NEVER apply after a transition is made to another procedure.

D. ANY time during the procedure performance, BUT it will NEVER apply after a transition is made to another procedure.

#95. – The Unit 1 Unit Supervisor determines that the number of people in the control room is creating a distraction. Per OP-AA-103-101, CONTROL ROOM ACCESS CONTROL, which of the following personnel will the US direct to leave the control room?

A. A Nuclear Oversight auditor who is performing Control Room observations.

B. The Station Manager who is performing “day-in-the-plant” observations.

C. The Illinois Dept. of Nuclear Safety inspector and the admin NSO who are reviewing an IDNS report.

D. The Field Supervisor and an Equipment Operator who are performing a pre-job brief of an oil separator surveillance.

#96. – An SRO is screening the following shift activities for possible temporary configuration changes. Per CC-AA-112, TEMPORARY CONFIGURATION CHANGES, which activity will the US have to enter into the Temp Change Log?

A. A hose is being connected to the RCS to support draining activities per the operating procedure.

B. Thermal overloads are being removed from a breaker that are specified on a clearance order.

C. An electrical jumper is being placed in a component’s start circuit as part of a surveillance procedure to prevent inadvertent auto start.

D. A blocking device is being installed on a safety valve to stop leakage for which a work request has been written.

#97. – Work planning has contacted an SRO to discuss the need to modify the scope of a work order, that is attached to an active clearance order (C/O). – Based on this discussion, the SRO determines that the C/O will need to be revised before the new work can take place. With the above conditions, prior to revising, the SRO will ensure the electronic C/O has a Holder Acceptance Lock applied OR the C/O status is placed in…

A. SUSPEND.

B. APPROVED.

C. TEMP LIFT.

D. DISTRIBUTED.

#98. – A reactor trip and SI occurred 6 hours ago due to a small break RCS LOCA. – CETCs are 675 F. – BOTH SR channels are 1500 cps and lowering. – RCS pressure is 600 psig. – ALL RCPs are tripped. – RVLIS plenum level is 15%. – Cnmt floor water level is 20

A. Unusual Event.

B. Alert.

C. Site Area Emergency.

D. General Emergency.

#99. – Unit 1 is at 99% power, normally aligned. – The on-coming Unit 1 SRO, reviewing the turnover, notes several activities pending during the next shift. – Shortly after shift turnover, Rad Protection requests that a containment entry be made during the shift, to obtain rad conditions, for upcoming maintenance on a pressurizer spray valve. In accordance with BwAP 1450-1, ACCESS TO CONTAINMENT, which one of the following pending Unit 1 activities, must the US ensure does NOT occur during the containment entry?

A. A flux map.

B. A containment release.

C. Raise turbine load by 5 MW.

D. A 10 gallon boration.

#100. – Unit 1 is in mode 4 during a refuel outage. – 1A RH train is in shutdown cooling mode. – 1B RH Pump is OOS. The following event occurs: – The I/P converter for 1RH606, HX 1A FLOW CONT VLV fails such that the valve goes full open. – The Unit 1 SRO has dispatched an equipment operator (EO) to install a temporary regulator, with a pneumatic jumper, around the failed I/P converter to re-enable RH temperature control. With the above conditions, the US will direct the EO to follow the pneumatic jumper installation instructions found in…

A. 1BwOA SEC-4, LOSS OF INSTRUMENT AIR.

B. 1BwOA ELEC-2, LOSS OF INSTRUMENT BUS.

C. 1BwOA PRI-5, CONTROL ROOM INACCESSIBILITY.

D. 1BwOA PRI-10, LOSS OF RH COOLING.

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