Braidwood 2016 - ILTandMe

#1. Braidwood U-1 is being ramped from 50% to 75% reactor power.During this ramp RCS loop Ts will change from their initial value (in degrees F.) of ____________

A. 15 F to 22.5 F.

B. 30 F to 45 F.

C. 50 F to 75 F.

D. 66 F to 99 F.

#2. Given:- Unit 1 was at 100% power normal alignment.- Subsequently Power Range N-41 failed HIGH.- Currently the RPS bistables for N-41 are in bypass.- The SM has directed the bistables be removed from bypass AND placed in trip to comply with administrative requirements.With the above conditions when N-41 bistables are removed from bypass AND placed in tripped the coincidence logic for Power Range NI RPS actuation will change from (bypassed) to __(tripped) .(bypassed) (tripped)

A. 1 of 3 2 of 3

B. 2 of 3 1 of 3

C. 2 of 3 3 of 3

D. 3 of 3 2 of 3

#3. Given: – Unit 1 is at 99.7% power normal alignment.- The crew has recently established excess letdown flow per BwOP CV-15 EXCESS LETDOWN OPERATIONS.With the above condition which of the chart recorders below indicate the EXPECTED plant response to establishing excess letdown flow?

A. A

B. B

C. C

D. D

#4. Given:- The spent fuel pool level is as indicated below.- The crew has recently swapped FC cooling pumps to support maintenance.- The newly started FC cooling pump develops a large leak between the pump and discharge check valve.- Spent Fuel Pool level is dropping and radiation levels at the pool surface are rising.With the above conditions and NO operator action which of the following is the approximate INDICATED water level that the Spent Fuel Pool will stabilize at?

A. 1′ – 2′

B. 4′ – 5′

C. 17′ – 18′

D. 23′ – 24′

#5. Given:- A Unit 1 xenon free reactor startup is in progress from a maintenance outage at MOL.- The reactor was taken critical by withdrawing control rods.- Reactor power was stable at 10-8 amps in the intermediate range for recording critical data.- The RO then withdraws control rods 10 steps.With the above conditions reactor power will rise…

A. continuously above Mode 1 UNLESS control rods are manually inserted.

B. and stabilize at a value above 10-8 amps AND below the POAH.

C. temporarily THEN drop back to 10-8 amps.

D. and stabilize at a value above the POAH AND below Mode 1.

#6. Given:- Unit 1 is at 100% power normal alignment.- An alarm on the RM-11 indicates 0PR16J SG Blowdown After Filter Outlet Rad Monitor has turned from Green to RED.With the above condition the…

A. 1SD02PA/B Blowdown Condenser Hotwell Pumps TRIP.

B. 1SD007 SG Blowdown Condenser Inlet Valve CLOSES.

C. 1PS179A-D SG Blowdown Sample Isolation Valves CLOSE.

D. 0WX119A CST Inlet Header Isolation from Blowdown Demin 0A Valve CLOSES.

#7. Given:- 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 69% power.

D. begin to OPEN at approximately 74% power.

#8. Given:- U-1 was at 100% power normally aligned.The following events then occur:- A reactor trip occurs.- Bus 144 Auto Bus Transfer fails and the Bus is DE-ENERGIZED.- The crew has cross tied bus 144 to Bus 142 and re-energized bus 144.With the above conditions which of the following PREVIOUSLY RUNNING bus 144 loads will require local operator action at the 4kv breaker to re-start the load?

A. Circulating Water Pump

B. Non-Essential Service Water Pump.

C. Station Air Compressor

D. Containment Chiller

#9. Given:- U-1 was at 100% power normally aligned.- The 1A SX Pump is OPERATING.The following then occurs:- DC Bus 111 is FAULTED and DE-ENERGIZES.- 15 seconds later the reactor is MANUALLY tripped.- 30 seconds after the reactor trip A LOSS OF OFF SITE (LOOP) power occurs.With the above conditions 40 seconds after the LOOP which (if any) SX pps will be OPERATING?

A. BOTH 1A and 1B SX pumps will be SHUTDOWN.

B. BOTH 1A and 1B SX pumps will be OPERATING.

C. 1A SX pump will be OPERATING and 1B SX pump will be SHUTDOWN.

D. 1B SX pump will be OPERATING and 1A SX pump will be SHUTDOWN.

#10. Given:- 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 alarm the MCR should receive in the associated 1PM09J detection zone?

A. TROUBLE

B. TROUBLE WIRE OPEN

C. FIRE

D. FIRE WIRE OPEN

#11. Given:- Unit 1 is at 100% power normal alignment.- An inadvertent Phase A actuation occurs.With the above conditions the RCP #1 seal leakoff flows are directed to the…

A. Pressurizer Relief Tank.

B. Reactor Coolant Drain Tank.

C. Containment Floor Drain Sump.

D. Containment Reactor Cavity Sump.

#12. Given:- Unit 1 was at 100% power normal alignment.The following occurs:- Bus 132X faults and is DE-ENERGIZED.- Simultaneously an RCS LOCA occurs causing a Reactor Trip and SI.With NO operator actions WHEN plant parameters meet the applicable low RWST level or low RCS pressure conditions ______________ will FAIL to stroke.

A. 1MOV-CV8110 1B CV PP MINIFLOW ISOL VLV

B. 1MOV-CV8111 1A CV PP MINIFLOW ISOL VLV

C. 1SOV-CV8114 1A CV PP MINIFLOW ISOL VLV

D. 1SOV-CV8116 1B CV PP MINIFLOW ISOL VLV

#13. Given:- The Unit 1 RO is re-aligning the 1A RH pump from shutdown cooling to ECCS cold leg injection.- The RO is about to OPEN 1SI8812A PP 1A SUCT FROM RWST ISOL VLV.With the above conditions which of the following is an interlock that must be met to OPEN 1SI8812A?

A. 1CS001A PP 1A RWST SUCT VLV must be OPEN.

B. 1CV8804A PP 1A SUMP SUCT VLV must be OPEN.

C. 1SI8811A CNMT SUMP 1A ISOL VLV must be CLOSED.

D. 1RH8701A RC LOOP 1A TO RH PP 1A SUCT ISOL VLV must be CLOSED.

#14. Given the following sequence of events:- Unit 1 is at 100% power with pressurizer pressure channel 1P-455 in test (bistables tripped).- ALL other equipment is in a 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 RO 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

#15. Given:- Unit 1 is at 100% power normal alignment. – A slow and steady rise in PRT level has been noted over several hours.- Annunciator 1-12-A7 PRT LEVEL HIGH/LOW has just alarmed.With the above conditions the PRT level will be lowered by

A. verifying 1RE1003 RCDT Pumps Discharge Cnmt Isol Valve auto opens on high PRT level then verify the 1A RCDT pump auto starts.

B. verifying 1RE1003 RCDT Pumps Discharge Cnmt Isol Valve auto opens on high PRT level then verify the 1B RCDT pump auto starts.

C. manually opening 1RY8031 PRT Drain Isol Valve and 1RE1003 RCDT Pumps Discharge Cnmt Isol Valve then verifying the 1A RCDT pump auto starts.

D. manually opening 1RY8031 PRT Drain Isol Valve and 1RE1003 RCDT Pumps Discharge Cnmt Isol Valve then verifying the 1B RCDT pump auto starts.

#16. Given:- Braidwood Station is in a dual unit outage.- Both Units are in Mode 4.- The U-0 Component Cooling HX is aligned to Unit 2.- The 1A RH Train is in Shutdown Cooling Mode.- The 2B RH Train is in Shutdown Cooling Mode.- The 1B & 2A RH Trains are aligned for ECCS cold leg injection.The MCR crew desires to raise SX flow to maximize cooldown rate capabilities. With the above conditions throttling OPEN 0SX007 U-0 SX OUTLET FROM CC HX VLV will raise cooldown rate capabilities for…

A. BOTH Units.

B. ONLY Unit 1.

C. ONLY Unit 2.

D. NEITHER unit.

#17. Given:- Unit 1 is at 50% power normal alignment.- PZR Pressure Control Channel Select switch is in the PT-455/PT-456 position.The following occurs:- 1PK-455A Master PZR Pressure Controller potentiometer setting fails from its normal setting to the equivalent of 3.0. With the above conditions and NO operator action RCS pressure will INITIALLY…

A. LOWER to the low PZR pressure reactor trip setpoint.

B. LOWER and stabilize ABOVE the low PZR pressure reactor trip setpoint.

C. RISE to the high PZR pressure reactor trip setpoint.

D. RISE and PZR pressure will be controlled near 2315-2335 psig by a PZR PORV.

#18. Given:- Unit 1 was at 100% power normal alignment.- Subsequently a loss of DC bus 111 occurs. – The crew initiates a manual reactor trip and enters 1BwEP-0 REACTOR TRIP OR SI. Note: – TSLB-4 is the NIS AND CONTAINMENT TRIP STATUS LIGHTS at 1PM05J.- Position indication lights are the red and green checkerboard lights at 1PM05J.With the above conditions the position of RTA (train A reactor trip breaker) can be obtained locally…

A. and from BOTH TSLB-4 and its position indication lights.

B. and from its position indication lights (but NOT from TSLB-4).

C. and from TSLB-4 (but NOT from its position indication lights).

D. but NOT from either its position indication lights OR TSLB-4 .

#19. Given:- Unit 1 is at 100% power.- The operating crew is performing 1BwOSR 3.3.1.4-2 UNIT ONE SSPS REACTOR TRIP BREAKER AND REACTOR TRIP BYPASS BREAKER SURVEILLANCE with the following conditions:- BOTH Reactor Trip Breakers (RTA and RTB) are CLOSED.- 1B Reactor Trip Bypass Breaker (BYB) is RACKED IN and CLOSED.- 1B Input Error Inhibit switch is in INHIBIT.- 1B Mode Selector switch is in TEST.- 1B Multiplexer Test switch is in INHIBIT.- 1A Multiplexer Test switch is in NORMAL.All other systems are normally aligned then:- Pressurizer Pressure drops below the automatic SI setpoint.Based on the above conditions and assuming NO operator actions are taken …

A. SI actuation will occur on ONLY the 1A SSPS train AND ONLY RTA will OPEN (RTB and BYB will remain CLOSED).

B. SI actuation will NOT occur on either SSPS train AND RTA RTB and BYB will ALL remain CLOSED.

C. SI actuation will occur on ONLY the 1A SSPS train AND ONLY RTA and BYB will OPEN (RTB will remain CLOSED).

D. SI actuation will occur on BOTH SSPS trains AND RTA RTB and BYB will ALL OPEN.

#20. Given:- Unit 1 is at full power.- 1A 1B and 1C RCFCs are running in high speed with the 1D RCFC in standby.- A reactor trip and Safety Injection occur due to high containment pressure.After the SI occurs what is the response of the RCFCs?

A. ALL RCFCs start immediately in low speed.

B. 1A 1B and 1C RCFCs start immediately in low speed and the 1D RCFC starts 20 seconds later in low speed.

C. 1A 1B and 1C RCFCs start 20 seconds later in low speed and the 1D RCFC starts immediately in low speed.

D. ALL RCFCs start 20 seconds later in low speed.

#21. Given: – Unit 2 has experienced a reactor trip and SI from full power due to an RCS LOCA.- 2SI8811A CNMT SUMP 2A ISOL VLV failed to automatically open when the appropriate plant conditions exist.- ALL other plant equipment operates as expected.- The crew is currently performing 2BwEP ES-1.3 TRANSFER TO COLD LEG RECIRC Attachment A MANUAL OPERATION OF CONTAINMENT SUMP ISOLATION VALVES.- 2SI8811A was JUST manually opened and the 2A RH Pump and the 2A CS Pump were restarted.- 2CS009A PP 2A SUMP SUCT VLV is CLOSED.- RWST level is 8% and slowly lowering.With the above conditions the crew will (1) because (2)_.

A. (1) ALLOW the 2A CS pump to continue running(2) RWST is still ABOVE the required level

B. (1) ALLOW the 2A CS pump to continue running(2) a flowpath from the ECCS sump currently EXISTS

C. (1) PLACE the 2A CS pump in PTL(2) RWST is BELOW the required level AND NO flowpath from the ECCS sump currently exists

D. (1) PLACE the 2A CS pump in PTL(2) NO flowpath from the ECCS sump NOR the RWST currently exists

#22. Given:- Unit 1 is at 50% power normal alignment.- The RO is about to initiate an MSR OOS.- The G1 IN SERVICE poke field was clicked on (see MSR control panel below).When the RO clicks on the OUT poke field in the pop-up window which of the following valves are expected to automatically CLOSE?

A. 1MS010A&B AND 1MS147A&B (only)

B. 1MS010A&C AND 1MS147A&C (only)

C. 1MS010A&D AND 1MS147A&D (only)

D. 1MS010ABC&D (only)

#23. Given:- 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.- U-1 SG levels are 50% and slowly dropping.The NSO immediately closed 1FW012C RECIRC VALVE then attempted to runback the turbine with both the Runback pushbutton and OWS graphic 5512 poke field. However the turbine load does NOT change.With the above conditions the NEXT crew action is to…

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.

#24. Given :- A U-2 plant heatup is in progress per 2BwGP 100-1 PLANT HEATUP.- RCS temperature is 300 F and slowly rising.With the above conditions feed flow should be maintained in the…

A. main feed line to prevent the 2FW079A-D FW FLOW CHECK VLV from failing closed.

B. main feed line to prevent water hammer in the main feedwater nozzle.

C. tempering feed line to prevent water hammer in the auxilary feedwater nozzle.

D. main feed line to prevent water hammer in the steam generator feedwater preheater.

#25. Given:- Unit 1 is at full power normal alignment with the following exception:- 1BwOSR 3.8.1.2-1 1A DIESEL GENERATOR OPERABILITY SURVEILLANCE is in progress.- The 1A DG is running and supplying bus 141 in parallel with the SATs.The following then occurs:- A Loss Of Offsite Power (LOOP) occurs due to a fault in SAT 142-1 actuating 86ST11A SAT 142-1 Lockout Relay.With the above conditions breaker ACB 1413 DG 1A FEED TO 4KV BUS 141 will ___(1)_. After the event the 1A DG will be operating in _(2)__ mode.

A. (1) REMAIN closed(2) Droop

B. (1) REMAIN closed(2) Isochronous

C. (1) TRIP open and RE-CLOSE(2) Droop

D. (1) TRIP open and RE-CLOSE(2) Isochronous

#26. Which of the following electrical busses supplies power to the 1TO05P Main Turbine Emergency Oil Pump?

A. AC Bus 132X

B. MCC 133Z2

C. DC Bus 111

D. DC Bus 123

#27. Given:- Unit 1 is at 100% power.- A loss of 4KV Bus 142 has occurred.- The 1B DG did NOT start.- An EO is locally performing 1BwOA ELEC-3 Attachment D LOCAL START OF 1B DG.- When the DC Control Power Available lights are checked they are noted to be NOT LIT.Which of the following DC buses will the EO check that the associated breaker is closed for each indicating light on the 1B DG local control panel?DC POWER ON/BUS # 1 Light DC POWER ON/BUS # 2 Light

A. Bus 111 Bus 112

B. Bus 112 Bus 111

C. Bus 112 Bus 112

D. Bus 112 Bus 114

#28. Given:- A release of 0WX01T Liquid RadWaste Release Tank is in progress with 0PR01J LIQUID RELEASE EFFLUENT RAD MON in service.The following occurs:- An audible alarm occurs on the RM-11.- The 0PS101 LIQ RADWASTE icon indicates DARK BLUE.- The channel status display indicates a loss of sample flow has occurred.With the above conditions the 0PR01J is in __(1)_ failure and the release _(2)___ AUTOMATICALLY isolate.

A. (1) EQUIPMENT(2) did NOT

B. (1) EQUIPMENT(2) DID

C. (1) OPERATE(2) did NOT

D. (1) OPERATE(2) DID

#29. Given:- Unit 1 is at 100% power.- 2SX005 Unit 0 CC Heat Exchanger Inlet Valve is de-energized and closed for valve operator replacement.Subsequently:- 1A SX pump trips on overcurrent.- 1B SX pump can NOT be started.- Unit 1 reactor is tripped.- A feedwater isolation occurs.- Both Unit 1 AF pumps have automatically started.Given the conditions above and assuming SX can NOT be restored to Unit 1 within the next 30 minutes which of the following is correct?

A. 1A AF pump MUST be shutdown AND 1B AF pump may continue to operate.

B. 1B AF pump MUST be shutdown AND 1A AF pump may continue to operate.

C. BOTH Unit 1 AF pumps MUST be shutdown.

D. BOTH Unit 1 AF pumps may continue to operate.

#30. Given:- Unit 1 is at 100% power normal alignment.- The U-1 Station Air Compressor is in operation.- The U-1 Instrument Air Dryer is aligned.- Annunciators alarm and the RO notes the following 2 alarms LIT on 0PM01J.- NO other alarms are LIT.- Service air pressure has been stable as indicated below.- Instrument Air pressure has trended down from 108 psig to its current value below. As a result of the above conditions the automatic plant response is…

A. a standby station air compressor STARTED.

B. the U-1 instrument air dryer bypass valve OPENED.

C. the U-1 station air compressor unloader valve went full CLOSED.

D. BOTH U-1 instrument air dryer towers simultaneously went to drying mode for 5 minutes.

#31. Given:- Unit 1 is at 100% power normal alignment. Subsequently the following occurs:- A loss of bus 142 followed by a U-1 SI and Phase A isolation.With the above conditions the status of the RCFC WO containment penetrations will be… (consider ISOLATED to mean WO water prevented from flowing OUT of containment from the inlet or outlet header penetrations)

A. NEITHER train of penetrations ISOLATED by either a closed MOV or a check valve.

B. 0A train penetration ISOLATED by either a closed MOV or a check valve AND 0B train NOT isolated.

C. 0B train penetration ISOLATED by either a closed MOV or a check valve AND 0A train NOT isolated.

D. BOTH trains of penetrations ISOLATED by either a closed MOV or a check valve.

#32. Given:- Unit 1 is at 100% power normal alignment. – The U-1 Boric Acid Storage Tank system is aligned and running on recirculation per BwOP AB-10 RECIRCING A BORIC ACID TANK.- An EO performing field rounds reports the following to the MCR:- The U-1 Boric Acid Filter DP is at maximum (pegged high).- The U-1 Boric Acid system recirculation flow has dropped to ZERO.- 1AB03P Boric Acid Transfer Pump is running but NOT damaged.- In response to the plugged filter the U-1 RO then stops 1AB03P Boric Acid Transfer Pump.With the above conditions and NO further operator actions if Unit 1 requires blended flow make-up to the VCT boric acid flow from 1AB03P…

A. IS available and NO TRM entry is required.

B. is NOT available and NO TRM entry is required.

C. is NOT available and TRM 3.1.b BORATION FLOWPATHS OPERATING entry is required.

D. is NOT available and TRM 3.1.f BORATED WATER SOURCES OPERATING entry is required.

#33. Given:- Unit 1 is in Mode 5 with the 1A RH train in shutdown cooling mode.- The RO was monitoring RH system performance on the plant process computer (PPC) when the following trends were noted (see below PPC screen shot).With the above conditions which of the following equipment malfunctions caused the noted indications?

A. Instrument Air was lost to 1RH606 HX 1A FLOW CONT VLV.

B. Inadvertent stroke of 1RH610 PP 1A MINIFLOW VLV.

C. Instrument Air was lost to 1RH618 HX 1A BYP FLOW CONT VLV.

D. Inadvertent stroke of 1CC9412A CC TO RH HX 1A ISOL VLV.

#34. Given the following sequence of events:- Unit 1 was at full power normal alignment.- A U-1 SI actuation then occurs.With the above conditions which of the following Group 2 status lights would be the LAST to illuminate?(assume all valves have approximately the same stroke times)

A. 1CV112B/C CLOSED

B. 1CV112D/E OPEN

C. 1SI8801A/B OPEN

D. 1SI8105/8106 CLOSED

#35. Given:- Unit 1 is at full power normal alignment.An event then occurs and the following indications are noted:- Annunciator 1-2-E4 CC SURGE TANK AUTO-M/U ON alarms and the following SER points print:-1434 VALVE 1CC183 NOT CLOSED-1430 VALVE 1CC182 NOT CLOSED- Annunciator 1-2-A5 CC SURGE TANK LEVEL HIGH/LOW -0417 CC SURGE TANK LEVEL (PUMP 1A SUCT) LOW -2147 CC SURGE TANK LEVEL (PUMP 1B SUCT) LOW- Annunciator 1-2-E3 SX TO CC SURGE TANK TROUBLE alarms and the following SER points print:-0266 SX M/U TO CC SURGE TK VALVE 1CC202A OPEN-0264 SX M/U TO CC SURGE TK VALVE 1CC201A OPEN- NO other annunciators NOR SER points related to the CC system have alarmed OR cleared.- The RO notes CC Surge Tank level is currently STABLE. With the above conditions which of the following is the currently expected CC surge tank level range?

A. 0% – 22%

B. 23% – 30%

C. 31% – 45%

D. 46% – 50%

#36. Given:- Unit 1 has had a reactor trip and SI from full power.- The crew is currently performing 1BwEP-0 REACTOR TRIP OR SI step 7.a. Group 2 RCFC Accident Mode status lights – LIT – The RO notes that ONE of the FOUR RCFC Accident Mode status lights is NOT LIT.With the above conditions the single component that failed to realign to accident configuration is a…

A. Reactor Containment Fan Cooler.

B. SX Containment Isolation Valve.

C. SX Containment Chiller Isolation Valve.

D. SX Containment Chiller Bypass Valve.

#37. Given:- Unit 1 was operating at full power when a near simultaneous loss of an electrical bus and SI occurred- 5 minutes later the RO notes the following indications on 1PM06J.- NO operator actions have been taken since SI actuated.With the above conditions which of the following was the sequence of events that occurred?

A. AC Instrument Bus 111 was lost BEFORE the SI signal.

B. AC Instrument Bus 111 was lost AFTER the SI signal.

C. DC Bus 111 was lost BEFORE the SI signal.

D. DC Bus 111 was lost AFTER the SI signal.

#38. Given:- Unit 1 is at 100% power normal alignment.A MCR annunciator alarms on 1PM01J and the RO notes the following indications:Currently with above conditions which of the following malfunctions occurred?

A. DC Battery Charger 112 Supply Breaker TRIPPED.

B. DC Battery Charger 112 Output Breaker TRIPPED.

C. DC Bus 114 supply fuses OPENED.

D. DC Bus 112 Main Feed Breaker TRIPPED.

#39. Given:- Unit 1 is at 50% power.- Control Rods are in MANUAL.- All other equipment is in a normal alignment.An event then occurs and the RO notes the below indications on 1LR-0459 PZR Level Recorder.Which of the following failed HIGH would cause the above indications?

A. A power range NI detector

B. A turbine impulse pressure transmitter

C. A narrow range Tcold RTD

D. An RCS loop Delta T channel

#40. While recovering a dropped Group 1 Rod on Control Bank C in accordance with 1BwOA ROD-3 DROPPED OR MISALIGNED ROD annunciator 1-10-C6 ROD CONTROL URGENT FAILURE alarm is EXPECTED from Unit 1 Rod Control Power Cabinet…

A. 1AC

B. 2AC

C. 1BD

D. 2BD

#41. Given:- A release of the 0A Gas Decay Tank (GDT) is in progress per BwOP GW-500T1 GAS DECAY TANK RELEASE FORM.- Subsequently the 0B (on line) GDT relief valve fails (sticks) OPEN.- The rise in flow past the 0PR02J GDT EFFLUENT rad monitor causes the skid to exceed the high radiation ALARM setpoint.With the above conditions…

A. BOTH the 0A and 0B GDT tanks effluent will be AUTOMATICALLY isolated.

B. the 0A GDT tank effluent must be MANUALLY isolated but the 0B GDT effluent can NOT be isolated.

C. BOTH the 0A and 0B GDT tanks effluent will be MANUALLY isolated by CLOSING 0GW014 WASTE GAS DISCH VLV.

D. the 0A GDT tank effluent will be AUTOMATICALLY isolated but the 0B GDT effluent can NOT be isolated.

#42. Given:- A fire has occurred in the plant and annunciator 0-37-A4 UNIT 1 AREA FIRE is in alarm.- The RO is reviewing BwAR 0-37-A4 for applicable actions.- It is determined that the fire meets criteria (in applicable fire zone and of sufficient magnitude) for specific actions listed in BwAR 0-37-A4.With the above conditions which of the following describes the actions listed in BwAR 0-37-A4?

A. Start the Auxiliary Feedwater Pumps to prevent a loss of an adequate heat sink.

B. Start the Emergency Diesel Generators and run unloaded to ensure readiness for a loss of an ESF bus.

C. Transfer the non-ESF bus feeds to the SATs and remove UAT feed breaker control power fuses to prevent a failure of an auto bus transfer from affecting on site power.

D. Swap the U-1 CV pump suction from the VCT to the RWST and de-energize the suction valves to prevent a loss of operating CV pump suction.

#43. Given:- Unit 1 was at 100% power normal alignment.- An event occurred causing a Phase A containment isolation. – Five minutes after the Phase A actuated the RO noted that several of the Phase A isolation valves did NOT close automatically.- After the event recovery the crew is investigating which train of Phase A did NOT auto actuate.- The US suspects that a SSPS master relay failed.Which of the following pairs of valves will the operators use to determine which train of Phase A failed to actuate?(assume only one valve in each pair automatically closed)

A. 1CV8100/8112 SEAL WTR RTRN CNMT ISOL VLVS

B. 1CV8149A/B LTDWN ORIF ISOL VLVS

C. 1CC9414/9416 CC FROM RC PUMPS ISOL VLVS

D. 1SD005A/B S/G 1A/1D BLWDN SAMPLE ISOL VLVS

#44. Given:- Unit 1 was at 100% power normal alignment.Then the following occurred:

– An RCS LOCA.- The reactor tripped coincident with a loss of offsite power (LOOP).- Bus 141 is ENERGIZED.- Bus 142 is FAULTED.- The 1A CV pump TRIPPED.- The inability to obtain adequate ECCS injection flow has caused an Inadequate Core Cooling condition.- The crew is attempting to depressurize the SGs per 1BwFR-C.1 RESPONSE TO INADEQUATE CORE COOLING.With the above conditions INITIALLY the ONLY available SG PORVs that can be used to MANUALLY depressurize the SGs from the MCR are the 1MS018…A. A & D

B. C & D

C. A B & D

D. A C & D

#45. Given:- An event has occurred on Unit 1 causing elevated containment radiation levels.- The crew has entered emergency procedures and is performing mitigation actions in the procedures.- The US assigned the BOP the task of monitoring the RM-11 for Adverse Containment conditions.The BOP will check for containment radiation levels on rad monitor…

A. 1PR01J CNMT PURGE.

B. 1AR011J CONTAINMENT FH ICDT.

C. 1PR11J CNMT ATMOS.

D. 1AR020J CONTAINMENT HI RNG.

#46. Given the following sequence of events: – Unit 1 has experienced a small break RCS LOCA.- RCS pressure is currently 2200 psig and stable.- The crew is performing 1BwEP ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION and is about to initiate an RCS cooldown using steam dumps.As PZR pressure drops during the cooldown which of the following is the MAXIMUM indicated PZR pressure that the NSO can block the Steamline Low Pressure SI signal?

A. 2100 psig

B. 2000 psig

C. 1900 psig

D. 1800 psig

#47. Given the following sequence of events:- Unit 1 has experienced an event resulting in natural circulation conditions.- The crew is currently performing 1BwEP ES-0.2 NATURAL CIRCULATION COOLDOWN.Per 1BwEP ES-0.2 Continuous Action Summary page the crew will verify all __(1)_ are running. The bases for this step is to aid in cooling of the (2)___.

A. (1) CRDM Fans(2) reactor upper internal instrumentation

B. (1) CRDM Fans(2) upper reactor vessel head

C. (1) Rx Cavity Vent Fans(2) Source Range NIs

D. (1) Rx Cavity Vent Fans(2) lower reactor vessel

#48. Given:- Unit 1 was MANUALLY tripped from 100% power due to lowering SG NR levels.- All equipment operated as designed.- Following the manual reactor trip the 1A SG NR level dropped below the LO-2 setpoint.- The Unit 1 NSO has just depressed the following annunciator push buttons associated with 1PM05J in the following order:1) SILENCE2) ACKNOWLEDGE3) RESET- NO other operator actions have been taken on the 1PM05J panel.- 1A SG NR level continues to remain below the LO-2 setpoint.With the above conditions which one of the following describes the Reactor Trip Annunciator Box status of the following?1-11-A1 MANUAL RX TRIP1-11-A8 S/G 1A LEVEL LO-2 RX TRIP

A. 1-11-A1 is LIT SOLID (RED) and 1-11-A8 is SLOW FLASHING (WHITE).

B. 1-11-A1 is SLOW FLASHING (RED) and 1-11-A8 is NOT LIT (DARK).

C. 1-11-A1 is SLOW FLASHING (RED) and 1-11-A8 is LIT SOLID (WHITE).

D. 1-11-A1 is SLOW FLASHING (RED) and 1-11-A8 is SLOW FLASHING (WHITE).

#49. Which of the following conditions is the OTDT reactor trip designed to protect against?

A. An uncontrolled rod withdrawal from start-up conditions.

B. A trip of all feedwater pumps from at power conditions.

C. A stuck open pressurizer safety valve from at power conditions.

D. A main steam line break from at power conditions.

#50. Given:- Unit 1 was at full power for the past 9 months normal alignment MOL.- An RCS LOCA occurred.- A reactor trip and SI were initiated and all equipment operated as designed. – Plant conditions indicated a small break LOCA.- The crew is currently performing 1BwEP ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION.Adequate shutdown margin must be verified because of which of the following major evolutions in 1BwEP ES-1.2?

A. The RCS cooldown to 200 F.

B. The RCS depressurization.

C. The restarting of an RCP.

D. The shutdown of the RH pumps from ECCS injection.

#51. Given:- Unit 1 has experienced a Large Break LOCA combined with a Loss of Offsite Power from 100% power.- ALL systems operate as designed.With the above conditions which of the following describes the ORDER that the ECCS pumps will start and provide flow to the RCS?

A. 1. RH2. CV3. SI

B. 1. CV2. RH3. SI

C. 1. CV2. SI3. RH

D. 1. SI2. CV3. RH

#52. Given the following sequence of events:- Unit 1 was in Mode 1 normal alignment.- A slave relay malfunction caused 1CC9414 CC FROM RC PUMPS ISOL VLV to CLOSE and it will NOT re-open.With the current CC valve alignment the U-1 RCPs…

A. can remain running if RCP seal injection flows are maintained in their normal operating range.

B. MUST be tripped due to a loss of CC to ONLY the motor bearing oil cooler heat exchangers.

C. MUST be tripped due to a loss of CC to ONLY the thermal barrier heat exchangers.

D. MUST be tripped due to a loss of CC to the motor bearing oil cooler heat exchangers AND thermal barrier heat exchangers.

#53. In 1BwOA PRI-15 LOSS OF NORMAL CHARGING the operator is directed to check the following indications:- RCP No.1 Seal Leakoff Flow- Charging Pump Flow- Charging Pump Discharge Pressure- Charging Pump AmpsThe reason these parameters are monitored is to determine if there are indications of a…

A. seized pump shaft.

B. gas bound pump.

C. sheared pump shaft.

D. degraded pump impeller.

#54. Given:- Unit 2 is in Mode 5.- All systems are normally aligned.- 2A RH pump is running in the shutdown cooling mode per BwOP RH-6.- 2RH606 2A RH HX OUTLET FCV is throttled 10% open with stable RCS temperature.- 2RH618 2A RH HX BYPASS FCV is in AUTOMATIC.- Pressurizer level is approx. 50% and being MANUALLY raised toward a solid condition.The following occurs:- A 100 gpm leak develops immediately DOWNSTREAM of the 2A RH Heat Exchanger.- Pressurizer level is slowly lowering.Based on the above conditions and assuming NO operator actions 15 minutes later RCS temperature is now (assume decay heat load remains constant)

A. HIGHER and 2FI-618 PP 2A DISCH FLOW is THE SAME.

B. HIGHER and 2FI-618 PP 2A DISCH FLOW is LOWER.

C. THE SAME and 2FI-618 PP 2A DISCH FLOW is LOWER.

D. THE SAME and 2FI-618 PP 2A DISCH FLOW is THE SAME.

#55. Given:- Unit 1 is in Mode 3 at NOP/NOT.- Pressurizer pressure control is selected to channel 455/456 in automatic.- PZR pressure channel 1P-457 is in TEST (all required bistables tripped).Subsequently the following occurs:- 1PT-458 fails LOW.- SI ACTUATES and all equipment functions as designed.5 minutes later NO manual operator actions have been taken and the following conditions are noted:- Tave is 555 F and slowly LOWERING.- Pressurizer level is 35% and slowly RISING.- Pressurizer pressure is 2280 psig and slowly RISING.- 1PK-455A MASTER PZR PRESS CONT demand is 50%.With the above conditions PZR Backup Heaters will be _(1)_ and PZR spray valves will be _(2)_.

A. (1) Off(2) Closed

B. (1) Off(2) Open

C. (1) On(2) Closed

D. (1) On(2) Open

#56. RCS over pressurization is the PRIMARY concern during a/an __(1)_ event and prompt operator mitigation actions may prevent RCS pressure from exceeding the TECH SPEC RCS PRESSURE SAFETY LIMIT of _(2)___.

A. (1) Anticipated Transient Without Scram(2) 3107 psig

B. (1) Anticipated Transient Without Scram(2) 2735 psig

C. (1) Loss of Heat Sink(2) 3107 psig

D. (1) Loss of Heat Sink(2) 2735 psig

#57. Given: – A SGTR event occurred on Unit 1.- Currently the crew is performing 1BwEP-3 STEAM GENERATOR TUBE RUPTURE at step 6 Initiate RCS Cooldown. – ALL INTACT SG NR levels are at 50% and stable with AF isolated prior to the RCS cooldown.- The crew is about to re-initiate AF flow to the intact SGs and then commence an RCS cooldown at maximum rate with the steam dumps.With the above conditions regarding the INTACT SGs how will the operator actions affect the INITIAL indicated SG NR level?(Consider each action separately)1. A rapid addition of AF flow will cause SG NR level to (1).2. Rapidly opening the steam dumps will cause SG NR level to (2).

A. (1) Shrink(2) Shrink

B. (1) Swell(2) Swell

C. (1) Shrink(2) Swell

D. (1) Swell(2) Shrink

#58. Given:- Unit 1 plant startup was in progress.- A main steamline break then occurred.- The crew has implemented 1BwFR-P.1 RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION. – During performance of 1BwFR-P.1 conditions requiring a RCS temperature soak were identified.In accordance with 1BwFR-P.1 the temperature soak specifies that…

A. an immediate RCS cooldown CAN continue BUT the cooldown rate is restricted to LESS than Tech Spec limits.

B. NO further RCS cooldown UNTIL an engineering evaluation is performed to determine restrictions.

C. NO further RCS cooldown for a specified time period THEN the cooldown rate is restricted TO Tech Spec RCS cooldown limits.

D. NO further RCS cooldown for a specified time period THEN the cooldown rate is restricted to LESS than Tech Spec RCS cooldown limits.

#59. Given:- Unit 1 is experiencing a loss of heat sink condition with the following plant conditions:- 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 attempting 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 25%.

D. 1A CV pumps trips.

#60. Given:- Unit 1 has experienced an extended Loss of All AC Power.- The crew is performing 1BwCA-0.0 LOSS OF ALL AC POWER Attachment B step 10 DEPRESSURIZE ALL INTACT SGs TO 260 PSIG.With the above conditions which of the following is the basis for depressurizing the SGs?

A. Maximize Aux. Feed flow rates.

B. Prevent lifting PZR safety valves.

C. Minimize SG tube differential pressure.

D. Minimize RCS inventory loss.

#61. Given:- Unit 1 was at 100% power normal alignment.Subsequently:- A SAT fault results in a loss of offsite power.- All equipment operates as designed.Given the above conditions with NO operator action over the next 30 minutes SG level will…

A. rise slightly then stabilize back at normal level.

B. rise and then stabilize at a slightly higher than normal level.

C. slowly rise to the SG level P-14 setpoint.

D. slowly lower to the SG level LO-2 setpoint.

#62. Given:- Unit 2 was at full power normal alignment.The following sequence of events then occurred:- A loss of BOTH U-2 SX pumps occurred last shift.- The crew SHUTDOWN and ISOLATED the 2A and 2C RCFC trains and cross tied the U-1 and U-2 SX systems.- Per 2BwOA PRI-8 ESSENTIAL SERVICE WATER MALFUNCTION the RO is monitoring containment temperatures by performing 2BwOSR 0.1-123 SHIFTLY DAILY OPERATING SURV.The NSO observes the following RCFC temperature indications on 2PM06J:- 2A INLET TEMP – 109 F- 2A OUTLET TEMP – 82 F- 2C INLET TEMP – 107 F- 2C OUTLET TEMP – 78 F- 2B INLET TEMP – 100 F- 2B OUTLET TEMP – 75 F- 2D INLET TEMP – 102 F- 2D OUTLET TEMP – 75 FWith the above indications which of the following is the containment average air temperature that must be recorded for Tech. Spec. 3.6.5. CONTAINMENT AIR TEMPERATURE surveillance requirement?

A. 88.0 F

B. 91.0 F

C. 101.0 F

D. 104.5 F

#63. Given the following sequence of events:- Unit 1 was at 100% power.- ESF bus 142 is de-energized due to a bus fault.Subsequently:- A Manual reactor trip and SI occurred 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 1PM05J/6J:- RCS wide range pressure is 1700 psig and stable.- 1A RH discharge flow is 0 gpm.- 1A SI pump discharge flow is 200 gpm.- High Head SI flow is 300 gpm.The leak can be reduced by closing…(assume the leak is ALL RWST water)

A. 1RH8716A RH HX 1A DSCH XTIE VLV.

B. 1SI8801A CHG PMPS TO COLD LEGS INJ ISOL VLV.

C. 1SI8809A RH TO COLD LEGS 1A & 1D ISOL VLV.

D. 1SI8835 SI PMPS TO COLD LEGS ISOL VLV.

#64. Given:- 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 1BwCA-1.1 requires that the NSO maintain a MINIMUM primary plant inventory of…

A. 4% in the Pressurizer.

B. 14% in the Pressurizer.

C. 31% in RVLIS HEAD region.

D. 15% in RVLIS PLENUM region.

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

A. lowered. To return MVAR load to a STABLE 200 MVARS OUT the crew will take the VOLT adjuster control switch to RAISE.

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

C. rose. To return MVAR load to a STABLE 200 MVARS OUT the crew will take the BASE adjuster control switch to LOWER.

D. rose. To return MVAR load to a STABLE 200 MVARS OUT the crew will take the VOLT adjuster control switch to LOWER.

#66. Given:- Unit 1 reactor power is 65% and stable.- Main Generator load is 800 MW and stable.- 1C zone Main Condenser pressure is 1.6 inches 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 air leak.- The RO 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 that the unit will first reach the unacceptable region of Figure 1BwOA SEC-3-1?(assume the Load DROP rate remains constant and the rate of Main Condenser pressure RISE remains constant throughout the event)

A. 1119.

B. 1124.

C. 1127.

D. 1132.

#67. Given:- Unit 1 is performing an INITIAL power ascension following a refueling outage.- Current reactor power level is 50% and slowly rising.With the above conditions Rod Control will be maintained in…

A. AUTOMATIC to ensure Tave/Tref deviations are maintained within 1BwGP 100-8 GENERIC REACTOR CONTROL GUIDANCE limits.

B. AUTOMATIC to ensure Shutdown Margin is maintained in accordance with Tech Spec Rod Insertion Limits.

C. MANUAL to ensure Axial Flux Distribution limits in the COLR are NOT exceeded.

D. MANUAL to ensure fuel conditioning rod withdrawal rate limits are NOT exceeded.

#68. Given:- 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 and 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

#69. Given:- Unit 1 is preparing for a reactor startup following a refueling outage.- An NSO has been assigned the task of performing low power physics testing.Prior to performing the low power physics test the minimum required briefing level for this task is a…

A. Standard Pre-Job Briefing.

B. Tailored Pre-Job Briefing.

C. Heightened Level of Awareness Briefing.

D. Infrequent Plant Activity Briefing.

#70. Given the following plant conditions on Unit 1:- 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 570.0 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. step IN at 48 steps/minute.

B. step IN at 8 steps/minute.

C. NOT step.

D. step OUT at 8 steps/minute.

#71. Given the following plant conditions on Unit 1:- An audible alarm on the RM-11 is received.- The RO notes the below indications.Which of the following plant evolutions (based on plant location) would be most likely to cause the alarm?(Analyze each evolution separately and assume each evolution causes local radiation levels to rise above the alert setpoint on the nearest area detector on the same elevation)

A. A reactor coolant filter is being removed from its filter vault.

B. The Hi Level Spent Resin Storage Tank is being de-watered.

C. A radwaste vendor demineralizer resin bed is being transferred to a bulk radwaste liner.

D. Radiography of the U-1 CC surge tank vent valve line.

#72. Given:- Both units are at full power normal alignment.- The 0A VC train is in normal operation per BwOP VC-1 STARTUP OF CONTROL ROOM HVAC SYSTEM.- The 0B VC train is in standby.The following then occurs:- An event that has the potential for an accidental radioactive release in the Unit 2 Turbine Building trackway is reported to the MCR.- The US 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 OA.

B. 0PR33J or 0PR34J OUT AIR IN OB.

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

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

#73. Given:- The unit 1 RO is responding to a reactor trip.- 1BwEP-0 REACTOR TRIP OR SAFETY INJECTION step 1 has just been completed by the RO.With the above conditions which of the following tasks would take precedent over continuing the Immediate Actions of 1BwEP-0?

A. The RO manually tripping RCPs after RCP trip criteria has been met.

B. The RO dispatching an EO to LOCALLY trip the PMG output breaker after a loss of DC bus 113 occurred.

C. The RO manually actuating Main Steam Isolation after a Main Steamline Break has been diagnosed.

D. The RO manually starting an ECCS pump that failed to automatically start after an RCS LOCA occurred.

#74. Given:- Unit 1 was at full power normal alignment.- A condition occurs requiring a reactor trip when an automatic reactor trip fails to happen.- The RO was NOT able to trip the reactor from either of the main control room reactor trip switches.- The Unit 1 main turbine was tripped.- Control rods are in automatic and stepping in at 24 steps per minute.- Current reactor power is 75% and slowly dropping.With the above conditions and in accordance with 1BwFR-S-1 RESPONSE TO NUCLEAR POWER GENERATION/ATWS the RO will…

A. allow rods to continue to insert in automatic.

B. place the ROD BANK SELECT switch in MAN and insert rods.

C. place the ROD BANK SELECT switch in CBD and insert rods.

D. place the ROD BANK SELECT switch in SBD and insert rods.

#75. The Braidwood Emergency Procedures are organized into two complimentary categories. These include EVENT based responses of (1) and Fission Product Barrier based responses of (2).

A. (1) BwEPs (2) BwCAs and BwFRs

B. (1) BwFRs(2) BwEPs and BwCAs

C. (1) BwEPs and BwCAs(2) BwFRs

D. (1) BwEPs and BwFRs(2) BwCAs

#76. Operating within Tech Spec limiting conditions for operations (LCOs) 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

#77. Given: – Unit-1 was shutdown 5 DAYS AGO and is currently in Mode 6.- Fuel moves are in progress inside containment.- A fuel handing malfunction results in slightly elevated radiation levels in containment.With the above conditions the 1AR011/012J Containment Fuel Handling Incident Radiation Monitors actuation function (1) required to be OPERABLE per Tech Specs because (2)_.

A. (1) IS(2) the potential for radioactive releases in this condition may EXCEED post-accident offsite doses being maintained within the limits of 10CFR50.67.

B. (1) IS(2) each penetration providing access from the containment atmosphere to the outside atmosphere MAY be open and operator action CANNOT ensure post-accident offsite doses are maintained within the limits of 10CFR50.67.

C. (1) is NOT(2) each penetration providing access from the containment atmosphere to the outside atmosphere MUST be closed by a manual or automatic isolation valve or blind flange.

D. (1) is NOT(2) the potential for radioactive releases is minimized and operator action is sufficient to ensure post-accident offsite doses are maintained within the limits of 10CFR50.67.

#78. Given:- Unit 1 is at full power normal alignment.- 1BwOS MS-Q1 MAIN STEAM DUMP VALVE STROKE SURVEILLANCE is in progress.- During the stroke test of 1MS004C Steam Dump Valve the valve stuck OPEN and would not re-close.- The US directed the crew to MAINTAIN 1MS003C Steam Dump Valve Upsteam Manual Isolation Valve CLOSED and complete the surveillance for all the other steam dump valves.- 1BwOS MS-Q1 has been completed (with 1MS003C left CLOSED) and it was noted the acceptance criteria was not met for 1MS004C.Currently with 1MS003C closed the 1MS004C will be unavailable to respond as expected to a steam dump demand signal of _(1)_ and the US will track the position of 1MS003C in the (2)_.

A. (1) 0% to 50%(2) Equipment Status Tag (EST) Log

B. (1) 0% to 50%(2) Degraded Equipment Log (Dequip)

C. (1) 51% to 100%(2) Equipment Status Tag (EST) Log

D. (1) 51% to 100%(2) Degraded Equipment Log (Dequip)

#79. 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 CC flow to the RCPs and high bearing 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 available. – CETCs are 1235 F and slowly rising.- Containment is ADVERSE.- SG NR Levels are as follows:1A 18 21 24 28% With the above conditions the NEXT action the US will direct the crew to perform is…

A. opening both Pressurizer PORVs.

B. remain at step 16 until support conditions are established then start the 1D RCP.

C. immediately start the 1D RCP.

D. transition to SACRG-1 SEVERE ACCIDENT CONTROL ROOM GUIDELINE INITIAL RESPONSE.

#80. Given:- A SGTR is in progress on Unit 1.- The crew is performing 1BwEP-3 STEAM GENERATOR TUBE RUPTURE step 16 Depressurize RCS to Minimize Break Flow and Refill PZR.- The crew opens BOTH pressurizer spray valves BUT one spray valve will only open to an INTERMEDIATE position (will NOT fully open).Current plant conditions are:- Containment Pressure is 0.3 psig and STABLE.- Ruptured SG pressure is 1115 psig and STABLE.- RCS pressure is 2000 psig and DROPPING at 50 psig/min.- Pressurizer level is 10% and RISING at 10%/min.(assume parameter trends remain constant)With the above conditions the PZR spray flow is _(1)_ and the SRO will direct the crew to (2)_.

A. (1) ADEQUATE(2) CONTINUE the depressurization with current spray flow

B. (1) NOT adequate(2) KEEP the spray valves open AND open ONE PZR PORV ONLY

C. (1) NOT adequate(2) KEEP the spray valves open AND open BOTH PZR PORVs

D. (1) NOT adequate(2) CLOSE the spray valves open AND open BOTH PZR PORVs

#81. Given:- Unit 1 was at 100% power normal alignment.- The 1A SG FAULTED INSIDE containment.- The crew tripped the reactor actuated SI and entered the appropriate emergency procedures.- Currently the crew is performing 1BwEP-2 FAULTED SG ISOLATION at step 1 Check Main Steamline Isolation.- ALL MSIVs are CLOSED.- An audible alarm is then noted on the RM-11. (see below indication)- Channel 4AA122 is reading 3.35 E-01 mr/hr.- Channel 4AD422 is reading 2.49 E+01 mr/hr.With the above conditions ___(1)_ and the procedural flowpath going forward will be (2)___.

A. (1) 1A SG has also ruptured(2) complete 1A SG isolation in 1BwEP-2 THEN transition to 1BwEP-3 SG TUBE RUPTURE.

B. (1) a DIFFERENT SG (NOT 1A) has ruptured(2) complete 1A SG isolation in 1BwEP-2 THEN transition to 1BwEP-3 SG TUBE RUPTURE.

C. (1) 1A SG has also ruptured(2) IMMEDIATELY transition to 1BwEP-3 SG TUBE RUPTURE.

D. (1) a DIFFERENT SG (NOT 1A) has ruptured(2) IMMEDIATELY transition to 1BwEP-3 SG TUBE RUPTURE.

#82. Given the following plant conditions on BOTH Units:- 1PR030J AND 2PR030J Unit 1 AND Unit 2 Wide Range Gas Monitors are INOPERABLE.- 0VA019 and 0VA020 Unit 1 AND Unit 2 Vent Stack Effluent Flow Monitors are UNAVAILABLE.- 0VA01JA AND 0VA01JC Flow Indicators are INOPERABLE.- 0VA01CA Aux Building Supply Fan 0A is RUNNING.- 0VA02CA Aux Building Exhaust Fan 0A is RUNNING.- ALL other Aux Building Supply and Exhaust Fans are STOPPED.- 0VL02CA Lab Exhaust Fan 0A is RUNNING.- 0VW03CA Service Building and Solid Radwaste Fan 0A is RUNNING.- 0VF01CA Aux Building Filtered Vent Fan 0A is RUNNING.- 1PB128 Unit 1 Vent Stack Effluent Low Range Gas is 5.0 E-07 microCi/cc.- 1PD428 Unit 1 Vent Stack Effluent High Range Gas is 4.5 E-03 microCi/cc..- 2PB128 Unit 2 Vent Stack Effluent Low Range Gas is 4.15 E-07 microCi/cc- 2PD428 Unit 2 Vent Stack Effluent High Range Gas is 9.5 E-04 microCi/cc.Based on the above conditions the station TOTAL release rate is…

A. 2.92 E+05 microCi/sec

B. 4.59 E+05 microCi/sec.

C. 5.20 E+01microCi/sec

D. 9.73 E+02 microCi/sec

#83. The Tech Spec limits for the amount of stored diesel fuel oil that is required to be maintained on site is based upon having sufficient supply for each diesel generator to supply…Note: LOCA – Loss of Coolant AccidentLOOP – Loss of Off Site Power

A. 3 days of post design basis LOCA load demand.

B. 7 days of post design basis LOCA load demand.

C. 14 days of post LOOP shutdown load demand.

D. 30 days of post LOOP shutdown load demand.

#84. Given:- Unit 1 is in Mode 2 reactor start-up in progress.- As the RO is inserting control rods to level power ONE CBD rod sticks and will NOT insert.- The misaligned rod is 13 steps above its group demand.- The crew enters 1BwOA ROD-3 DROPPED OR MISALIGNED ROD.With the above conditions the SRO will direct the crew to ____(1)_ and then (2)_.

A. (1) INSERT Control Banks (only) in reverse order(2) TRANSITION to 1BwGP 100-2 REACTOR STARTUP step 1

B. (1) INSERT ALL Control and Shutdown Banks in reverse order(2) TRANSITION to 1BwGP 100-2 REACTOR STARTUP step 1

C. (1) TRIP the reactor(2) perform 1BwEP-0 REACTOR TRIP OR SI CONCURRENTLY with 1BwOA ROD-3

D. (1) TRIP the reactor(2) TRANSITION to 1BwEP-0 REACTOR TRIP OR SI ONLY

#85. Given:- Unit 2 is at full power normal alignment.- A rising trend in 2PR027J SJAE Radiation Monitor is detected.- The crew enters 2BwOA SEC-8 STEAM GENERATOR TUBE LEAK.- The SRO is attempting to determine the leak size and the affected SG to evaluate for Tech Spec entry conditions.- At step 4 Identify Leaking SG the 2AR022J/023J Main Steamline Radiation Monitors indicate NO discernable rise in radiation levels on any channel.With the above conditions an alternate method to evaluate WHICH SG is leaking is to ____(1)_.If Tech Spec entry conditions are met the bases for MAXIMUM allowable Primary to Secondary leak rate is (2)_.

A. (1) obtain activity levels of N-16 monitor(s) from chemistry.(2) the leakage amount that can be detected within 1 hour.

B. (1) obtain activity levels of N-16 monitor(s) from chemistry.(2) the leakage amount that would likely escalate to a tube rupture.

C. (1) check indications of 2PR08J SG Blowdown Sample Radiation Monitor.(2) the leakage amount that would likely escalate to a tube rupture.

D. (1) check indications of 2PR08J SG Blowdown Sample Radiation Monitor.(2) the leakage amount that can be detected within 1 hour.

#86. Given:- Unit 1 was at full power normal alignment.- An event occurred requiring Main Control Room evacuation.- The crew entered 1BwOA PRI-5 CONTROL ROOM INACCESSIBILITY.- The reactor is tripped.- TWO control rods did NOT fully insert after the reactor trip.- ALL other equipment operated as expected.- The crew initiates boration from the MCR in accordance with 1BwOA PRI-5.- When the Remote Shutdown Panel is activated the following indications are noted. (assume the conditions are constant)- The SRO has decided to use guidance in 1BwEP ES-0.1 REACTOR TRIP OR SI for emergency boration.With the above conditions the emergency boration will first MEET the MINIMUM requirements of 1BwEP ES-0.1 for the stuck control rods in…(assume total boration time)

A. 3 minutes.

B. 33 minutes.

C. 75 minutes.

D. 138 minutes.EXAMINATION ANSWER KEY2016 NRCBWD OPS ILT CERT/NRC EXAM 2015 Page: 241 of 283 29 July 2016

#87. Given:An event occurs on Unit 1 and the STA monitoring status trees notes the following indications:- CETCs are 650 F.- RCS pressure is 2100 psig.With the above conditions the result of the Core Cooling status tree will be a(n) __(1)_ path and the bases for Reactor Core Safety Limits (Tech Spec 2.1.1) NOT being exceeded AT POWER is by maintaining an adequate(2)__.

A. (1) YELLOW(2) DNBR

B. (1) YELLOW(2) SDM

C. (1) ORANGE(2) DNBR

D. (1) ORANGE(2) SDM

#88. Given:- Unit 1 is at full power normal alignment.The following occurs:- Annunciator 1-7-E4 RCP THERM BARR CC WTR FLOW HIGH LOW alarms.- The RO verifies proper automatic actions HAVE occurred per the BwAR.- The crew enters 1BwOA PRI-6 COMPONENT COOLING MALFUNCTION and determines that ONE RCP has a thermal barrier leak.With the above conditions and NO OTHER operator actions the leak is __(1)_.IF the Shift Manager then directs the crew to restore CC flow to the UNAFFECTED RCPs per 1BwOA PRI-6 the administrative requirement the SRO must complete is (2)___.

A. (1) ISOLATED(2) BwAP 1450-1 ACCESS TO CONTAINMENT Attachment 2 Containment Entry Checklist.

B. (1) ISOLATED(2) 1BwOL 3.7.7 LCOAR COMPONENT COOLING WATER SYSTEM

C. (1) NOT isolated(2) 1BwOL 3.7.7 LCOAR COMPONENT COOLING WATER SYSTEM

D. (1) NOT isolated(2) BwAP 1450-1 ACCESS TO CONTAINMENT Attachment 2 Containment Entry Checklist

#89. Given:- Unit 1 was at full power normal alignment.The following occurs:- The 1A SG PORV fails OPEN and CANNOT be closed.- The crew trips the reactor and attempts to main steam isolate but NO MSIVs will close.- An EO locally CLOSES the 1MS019A 1A SG PORV Block Valve.With the above conditions concerning the OPERABILITY status of the 1A SG PORV and the BASES for the status the 1A SG PORV is…

A. NOT required per Tech Specs because the SG PORV does not have a UPS.

B. INOPERABLE because the BLOCK valve is CLOSED ONLY.

C. INOPERABLE because the PORV CANNOT stroke fully ONLY.

D. INOPERABLE because the SG PORV CANNOT stroke fully AND INOPERABLE because the BLOCK valve is CLOSED.

#90. Given:- Unit 1 was ramping up from 80% to full power.- ALL systems were normally aligned- The NSO was performing intermittent MANUAL rod withdrawals per the reactivity plan.The following occurs:- Instrument bus 113 faults and is de-energized.- The RO notes annunciator 1-10-B5 PWR RNG FLUX HIGH ROD STOP is in alarm.With the above conditions MANUAL control rod withdrawal is _(1) and the procedure steps the crew will perform to clear the annunciator 1-10-B5 alarm are in (2)___.

A. (1) AVAILABLE(2) 1BwOA ELEC-2 LOSS OF INSTRUMENT BUS

B. (1) AVAILABLE(2) 1BwOA INST-1 NUCLEAR INSTRUMENTATION MALFUNCTION

C. (1) NOT available(2) 1BwOA ELEC-2 LOSS OF INSTRUMENT BUS

D. (1) NOT available(2) 1BwOA INST-1 NUCLEAR INSTRUMENTATION MALFUNCTION

#91. Given:- Unit 1 was at full power normal alignment.The following occurs:- DC bus 113 faults and is de-energized.- The crew manually trips the reactor. – 30 seconds later an EO locally trips the PMG output breaker.- All equipment operates as expected.With the above conditions and NO additional operator actions one minute AFTER the reactor trip _(1) MCR annunciators will be UNAVAILABLE and after 15 minutes _(2)____ EAL condition is applicable.

A. (1) ALL(2) NO

B. (1) ALL(2) an ALERT

C. (1) NON-safety related ONLY(2) an ALERT

D. (1) NON-safety related ONLY(2) NO

#92. Given:- Unit 1 is at 50% power.Subsequently:- 1IA066 IA Inside CNMT Isol Valve fails and slowly closes.- The crew enters 1BwOA SEC-4 LOSS OF INSTRUMENT AIR.- 1CV121 CV Pump Flow Control Valve controller was taken to manual and throttled to reduce charging flow to 40 gpm.- PZR pressure is 2275 psig and slowly rising.- PZR level is 45% and slowly rising.- VCT level is 50% and lowering.Given the above conditions per 1BwOA SEC-4 which of the following would require an IMMEDIATE reactor trip?

A. Pressurizer level rises to 80%.

B. The operating CV pump is tripped.

C. Pressurizer pressure rises to 2350 psig.

D. Volume Control Tank level drops to 37%.

#93. Given:- A 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 is 6 psig and rising.- CETCs indicate 720 F.- 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 30sed 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.

#94. Given:- 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.

#95. Given below are 4 different evolutions of MOVING spent fuel:(1) Moving RECENTLY Irradiated Spent Fuel in the REACTOR VESSEL.(2) Moving RECENTLY Irradiated Spent Fuel in the SPENT FUEL POOL.(3) Moving IRRADIATED Spent Fuel in the REACTOR VESSEL.(4) Moving IRRADIATED Spent Fuel in the SPENT FUEL POOL.Which of the following list the evolutions that REQUIRE a Licensed Supervisor with an active SRO License to be present?

A. 1 ONLY

B. 1 & 2 ONLY

C. 1 & 3 ONLY

D. 1 2 3 & 4

#96. Given:- Unit 1 is at full power normal alignment.The following sequence of events then occur on 1/1/16:- At 1200: Bus 141 is declared INOPERABLE for an emergent maintenance issue.- LCO 3.8.9 Distribution Systems Cond. A is entered with an 8 hour completion time to restore the bus to operable.- At 1800: The rounds EO discovers an UNISOLABLE SX leak (ASME code piping thru wall leak) in the 1A SI pump room. NO other equipment is affected by the leak.- LCO 3.7.8 SX System Cond. A is entered with an 72 hour completion time to repair SX to the 1A SI pump.- At 1900: Bus 141 repairs are complete and the bus is declared operable.- LCO 3.8.9 is exited.Currently the SRO is evaluating 1BwOL 3.5.2 LOCAR ECCS-OPERATING entry for the 1A SI pump.With the above conditions LCO 3.5.2 entry is REQUIRED NO later than…

A. 1800 on 1/4/16.

B. 1900 on 1/4/16.

C. 1200 on 1/8/16.

D. 1800 on 1/15/16.

#97. Given:- Unit 1 Main Turbine was just runback 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 LIT.- Annunciator 1-10-B6 ROD BANK LOW INSERTION LIMIT is LIT.- 1BwOSR 3.1.1.1-2 SDM SURVEILLANCE DURING OPERATIONS resulted in 1200 pcm available shutdown reactivity.Note: procedure names given for reference.- 1BwOA PRI-2 EMERGENCY BORATION- BwOP CV-6 OPERATION OF THE REACTOR MAKEUP SYSTEM IN THE BORATE MODE/BATCH BORATION METHODWith the above conditions in accordance with 1BwOA SEC-1 the US will direct the crew to borate the RCS per…

A. 1BwOA PRI-2 and boration is required by Tech Specs.

B. 1BwOA PRI-2 but boration is NOT required by Tech Specs.

C. BwOP CV-6 but boration is NOT required by Tech Specs.

D. BwOP CV-6 and boration is required by Tech Specs.

#98. Given:- A Unit 2 containment release is pending. – The SRO is filling out RP-BR-980 CONTAINMENT RELEASE FORM and evaluating whether to approve the release with the current exhaust fan configuration.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 SRO to NOT APPROVE 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.

#99. Given:- An RCS LOCA occurred on Unit 1.- The crew has implemented 1BwCA-1.2 LOCA OUTSIDE CONTAINMENT.- Containment Floor Water Level is 0 inches.- RWST level is 50% and slowly lowering.- After completing the actions of 1BwCA-1.2 RCS pressure is still lowering.Based on the above conditions the NEXT procedure the Unit Supervisor will implement is

A. 1BwCA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION.

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

C. 1BwEP ES-1.3 TRANSFER TO COLD LEG RECIRCULATION.

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

#100. Given:- A security event has been declared at Braidwood Station.- The crew has entered 0BwOA SECURITY-1 SECURITY THREAT.- The event has resulted in an explosion with a breach of containment integrity.Which of the following documents will be used to provide a framework for the Operations and Security Personnel interface?

A. Extensive Damage Mitigation Guidelines (EDMG)

B. Operational Contingency Action Guideline (OCAG)

C. Severe Accident Management Guidelines (SAMG)

D. Offsite Dose Calculation Manual (ODCM)

Results