ML15077A231

2015 Point Beach Nuclear Plant Initial License Examination Administered Written Examination

ML15077A231
Person / Time
Site:	Point Beach
Issue date:	03/06/2015
From:	McNeil D R NRC/RGN-III/DRS/OLB
To:	Florida Power & Light Energy Point Beach
Shared Package
ML14328A657	List: ML15077A231 ML15079A320 ML15079A322 ML15079A327
References
Download: ML15077A231 (101)

Text

Page 1 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 001 Given the following: Unit 1 is operating at Rated Thermal Power A leak equivalent to 1/2 inch in diameter has developed on the line connecting the pressurizer to the PORVs Which of the following describes the INITIAL response of the pressurizer pressure control and level control systems? (Assume no operator action)

Pressurizer Pressure Controller Charging Pump in Auto 1HC-431K 1HC-428A A. output will RISE (towards 100%) will speed up B. output will RISE (towards 100%) will slow down C. output will LOWER (towards 0%) will speed up D. output will LOWER (towards 0%) will slow down Page 2 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 002 Given the following: Unit 1 has experienced a plant transient that resulted in an automatic reactor trip and safety injection from 50% reactor power The crew is responding with EOP-0, Reactor Trip or Safety Injection The reactor operator notes that both Main Steam Isolation Valves (MSIVs) have automatically shut Assuming all equipment functioned as designed, which of the following initiating events could have caused BOTH MSIVs to automatically shut and why? A. Steam line 'A' faulted due to a failed-open safety valve. The MSIV closure prevents excessive cooldown due to both steam generators blowing down. B. Steam line 'B' faulted immediately downstream of 1MS-2018B, MSIV, in the façade. The MSIV closure prevents excessive cooldown due to either steam generator blowing down. C. Steam generator tube rupture on both steam generators. The MSIV closure prevents uncontrolled release of radioactivity from the containment. D. Large break LOCA which results in Containment Spray actuation. The MSIV closure prevents potential release of radioactivity from containment.

Page 3 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 003 Given the following: At 10:00, Unit 1 plant conditions were as follows: The Unit is operating at Rated Thermal Power The following parameters are observed: Letdown flow: 40 gpm Charging line flow: 25 gpm Seal Injection flow: 9.4 gpm per RCP Seal return flow: 2.2 gpm per RCP At 12:00, Unit 1 plant conditions were as follows: The Unit is operating at Rated Thermal Power 1RC-427, RC Loop B Cold Leg Letdown Isolation, has failed closed Normal letdown cannot be established Excess letdown has been placed in service The following parameters are observed: Excess Letdown flow has been determined to be 12 gpm Charging line flow: 0 gpm Seal injection flow: 9.4 gpm per RCP Seal return flow: 2.2 gpm per RCP Which of the following identifies the trend in Pressurizer level at 10:00 and 12:00?

Pressurizer level at 10:00 was __(1)__ and Pressurizer level at 12:00 was

___(2)___. (1) (2) A. Increasing Increasing B. Increasing Decreasing C. Decreasing Increasing D. Decreasing Decreasing

Page 4 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 004 Given the following: Unit 1 is operating at Rated Thermal Power Concerning the Component Cooling Water (CCW) system, a ___(1)___ will procedurally require the crew to ___(2)___ to prevent damage to components. (1) (2) A. Thermal Barrier leak immediately trip and stabilize the plant using EOP-0, Reactor Trip or Safety Injection, then stop the RCPs B. RCP Motor Bearings cooler leak verify seal injection supply, isolate cooling flow to the oil coolers, monitor RCP operation C. Seal Return Heat Exchanger leak commence a rapid load reduction, due to a loss of cooling to the VCT D. Surge Tank level at 5% immediately place CCW pumps in pullout, then trip and stabilize the plant using EOP-0, Reactor Trip or Safety Injection, then stop the RCPs

Page 5 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 005 Given the following: An ATWS has occurred on Unit 2 The crew is performing the actions in accordance with CSP-S.1, Response to Nuclear Power Generation/ATWS Boration flow was initiated by starting a boric acid transfer pump and positioning 2CV-350, Emergency Boration BA to CHG Pump MOV, to OPEN PZR pressure is 2390 psig Charging Line Flow is 28 gpm VCT level is Rising What action is the operator required to take next? A. Start an additional Boric Acid Pump B. Start a third Charging Pump and establish maximum charging C. Close 2CV-112C, the VCT Outlet to CHG Pump Suction valve D. Ensure PZR PORV(s) and block valves are open, until PZR pressure is less than 2335 psig

Page 6 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 006 Given the following: A Steam Generator Tube Rupture has occurred The crew is currently in EOP-3, Steam Generator Tube Rupture The crew has just completed the RCS cooldown to the target temperature of 495°F based on Core Exit Thermocouples The OS has just asked you to depressurize the RCS while maintaining a minimum of 35°F subcooling.

At the current RCS temperature, which of the following is the lowest that RCS pressure can be without violating the subcooling requirement? A. 900 psig B. 885 psig C. 871 psig D. 651 psig

Page 7 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 007 Given the following: Unit 1 was at Rated Thermal Power Twenty (20) minutes ago, an RCP flywheel catastrophically failed AFW flow of 115 gpm per Steam Generator was established in EOP-0, Reactor Trip or Safety Injection ECA-2.1, Uncontrolled Depressurization of Both Steam Generators, feed control step is in progress SG 'A' Wide Range level is 200 inches and lowering SG 'B' Wide Range level is 100 inches and lowering RCS temperature is now 400°F and lowering Which of the following actions will the crew take regarding AFW flow to the Steam Generators per ECA-2.1 and what is the reason for this action? A. Maintain AFW flow at 115 GPM to each SG, since 230 GPM flow is required to maintain adequate heat sink. B. Secure AFW flow to 'B' SG and raise AFW flow to 'A' SG to 230 GPM to isolate feed to the more severely faulted SG and maintain adequate heat sink. C. Secure AFW flow to 'B' SG and maintain AFW flow to 'A' SG at 115 GPM since 115 GPM flow is directed to minimize RCS cooldown and 'B' SG level is lowering faster. D. Reduce AFW flow to 50 GPM to each SG to minimize cooldown while maintaining both SGs in a wet condition.

Page 8 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 008 Given the following: Unit 2 is shutdown coming out of an outage The RCS is aligned to RHR with RCS temperature at 275°F and Stable The crew is testing 2CS-3124, Main Feed Isolation Valve, for PMT While 2CS-3124 was in the open position, the pneumatic operating supply was lost to the valve What is the final position of 2CS-3124 and the impact, if any, on LCO 3.7.3. Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulating Valves (MFRVs) and MFRV Bypass Valves? A. Open and LCO 3.7.3. is NOT MET. B. Open and LCO 3.7.3. IS MET. C. Closed and LCO 3.7.3. is NOT MET. D. Closed and LCO 3.7.3. IS MET.

Page 9 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 009 Given the following: A Station Blackout has occurred on Unit 2 The crew has worked through the EOP network to successfully restore an EDG locally A Component Cooling Water (CCW) Pump was restarted when power was restored on Unit 2 causing a pressure surge CC-721C, HX-12C CCW Heat Exchanger Relief Valve, has lifted and will not reseat What indications will be seen for this event? A. Continuously lowering level in Unit 2 CCW Surge Tank ONLY. B. Lowering level in Unit 2 CCW Surge Tank and rising level in Unit 1 CCW Surge Tank. C. Continuously lowering level in Unit 2 CCW Surge Tank and a rising level in the Waste Holdup Tank (WHUT). D. Level in Unit 2 CCW Surge Tank will NOT change.

Page 10 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 010 Considering the Safety Injection Load Sequencer operation during an accident with a Loss of Offsite Power, which of the following describes the reason(s) behind the SI Load Sequencer order and time to initiation of power to the various loads? A. The considerations deal ONLY with maintaining the diesel generator frequency and voltage within tolerance. B. The considerations deal ONLY with ensuring the starting of the various engineered safety features are within the required safety analysis response time values. C. The required response time values of the various emergency safety features are based on the accident analysis of the plant for the design basis accident AND the diesel generator capability. D. In order to ensure that the diesel generator's speed will not decrease below 95% of nominal value, the largest loads are started first when the diesel generator can best handle the starting currents.

Page 11 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 011 Given the following: A reactor startup on Unit 1 is in progress Reactor power is in the intermediate range and stable when the following occurred Most RED bistable status lights are LIT The following annunciators are LIT: RED INVERTER TROUBLE UNIT 1 INSTRUMENT BUS UNDER/OVER VOLTAGE What actions are required for this condition? A. Verify reactor trip AND isolate the Red Instrument Bus. B. Verify reactor trip AND restore power to the Red Instrument Bus from DYOA. C. Commence a reactor shutdown to insert all control and shutdown banks AND isolate the Red Instrument Bus. D. Commence a reactor shutdown to insert all control and shutdown banks AND restore power to the Red Instrument Bus from DYOA.

Page 12 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 012 Given the following: During a maintenance period the following DC system alignment exists: DC Bus D02 is aligned to D09, Swing Battery Charger and D305 Swing Battery D09, Swing Battery Charger develops a ground and the AC power breaker on D09 Trips Which of the following methods can be used to restore D02 to an acceptable alignment? A. Crosstie DC Bus D02 to DC Bus D04. B. Align 2D-205, Battery and 2D-207, Battery Charger to D-02. C. Restore D08, Battery Charger and D06, Battery to DC Bus D02. D. Align Swing Battery Charger D109 to DC Bus D02 and D305 Battery.

Page 13 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 013 Given the following: Unit 1 was operating at 100% when the unit tripped inadvertently Immediate actions are complete The following indications are observed: 1HX-15A Cont Ventilation SW Outlet Flow 580 gpm 1HX-15B Cont Ventilation SW Outlet Flow 400 gpm 1HX-15C Cont Ventilation SW Outlet Flow 590 gpm 1HX-15D Cont Ventilation SW Outlet Flow 575 gpm C01 C01B 1-4, UNIT 1 CONTAINMENT SUMP A LEVEL HIGH annunciator is LIT C01 C01B 2-3, UNIT 1 CONTAINMENT RECIRC COOLERS WATER FLOW LOW annunciator is NOT lit What actions are required to respond to the above indications? A. Isolate the North Service Water Header per AOP 9A, Service Water System Malfunction. B. The crew will have the Primary Auxiliary Building watch isolate affected component(s) per AOP 9A, Service Water System Malfunction. C. The crew will verify the service water system alignment per EOP 0, Reactor Trip or Safety Injection, Attachment A, Automatic Action Verification. D. Manually shut 1SW-2907/2908, Containment Ventilation Coolers Outlet Emergency Flow Control Valves, per Containment Sump A high level alarm response.

Page 14 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 014 Given the following: Both Units have been tripped due to a Loss of Instrument Air The instrument air headers are depressurized A Main Feedwater isolation signal has actuated How will this Loss of Instrument Air impact the Main Feedwater Isolation Valves and Main feed Regulating Valves?

MFIVs MFRVs A. Open Shut B. Open Open C. Shut Shut D. Shut Open Page 15 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 015 Given the following: A LOCA outside containment has resulted in RCS Subcooling dropping to 0°F The operating crew is performing the actions of ECA-1.2, LOCA Outside Containment Actions are being taken to identify and isolate the leak In accordance with ECA-1.2 . . . (1) which of the following valves will be sequentially SHUT and then OPENED for leak identification AND (2) what would be the indication used to confirm the LOCA has been isolated? A. (1) 1SI-852A and B, RHR Reactor Vessel Injection (2) RCS pressure rising B. (1) 1SI-852A and B, RHR Reactor Vessel Injection (2) Pressurizer level rising C. (1) 1SI-878A and C, SI Reactor Vessel Injection (2) RCS pressure rising D. (1) 1SI-878A and C, SI Reactor Vessel Injection (2) Pressurizer level rising

Page 16 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 016 Given the following: Unit 1 operators are attempting to place ECCS on Containment Sump recirculation following a LOCA Which of the following would prevent ANY sump recirculation flow from being established? A. RCS pressure is greater than 475 PSIG B. 1SI-896B, 'B' SI Pump Suction from RWST isolation valve OPEN C. BOTH 1SI-897A and B, SI Test Line Return isolation AOVs OPEN D. 1SI-857A, 'A' RHR Heat Exchanger Outlet to SI pump suction valve SHUT

Page 17 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 017 Given the following: Unit 1 was at Rated Thermal Power when a large break LOCA occurred The ECCS system is functioning as designed The crew has just transitioned to EOP-1, Loss of Reactor or Secondary Coolant Current Plant Parameters: Wide Range RCS Pressure 25 psig Stable Core Exit Thermocouples 237°F Stable RCS Cold Leg Loop Temperatures 150°F Stable Steam Generator Pressures 400 psig Stable Steam Generator 'A' Narrow Range Level 2% Slowly Rising Steam Generator 'B' Narrow Range Level 4% Slowly Rising Total AFW Flow to Both Steam Generators 230 gpm Stable Containment Pressure 25 psig Slowly Lowering Pressurizer Level 0 % --------- NR RVLIS 25 feet Slowly Lowering RWST Level 50% Slowly Lowering What is the current mechanism by which core decay heat is being removed? A. AFW flow B. RCS break flow C. Two phase flow through the core D. Heat transfer to Component Cooling from RHR

Page 18 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 018 Given the following: Unit 2 is in MODE 1 Grid disturbances have required the crew to lower turbine generator output to 470 MWE Generator Hydrogen pressure is 60 psig Which of the following is the maximum VAR loading per the capability curve the generator may carry without exceeding limits? (See provided reference) A. 235 Mvars overexcited B. 295 Mvars overexcited C. 320 Mvars overexcited D. 330 Mvars overexcited

Page 19 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 019 Given the following: Time = 1000 Reactor Power is 65% and Stable TAVG - TREF deviation is 0°F and Stable PZR level is 37% and Stable Rods are in AUTO Control Bank D step counters are at 165 steps Time = 1002 Reactor Power is approximately 66% and rising (no load change is in progress) TAVG - TREF deviation is approximately +2°F and Rising PZR level 38% and Rising PZR spray valves have throttled open Control Bank D step counters are at 174 steps and stepping out at 8 steps per minute Which of the following describes: (1) the event in progress AND (2) the FIRST action that must be performed per AOP-6C, Uncontrolled Motion of RCCA(s)? A. (1) First stage pressure channel high failure. (2) Trip the Reactor and go to EOP-0, Reactor Trip or Safety Injection. B. (1) First stage pressure channel high failure. (2) Place the Rod Control Bank Selector Switch to MANUAL. C. (1) Continuous Spurious Control Bank Withdrawal. (2) Trip the Reactor and go to EOP-0, Reactor Trip or Safety Injection. D. (1) Continuous Spurious Control Bank Withdrawal. (2) Place the Rod Control Bank Selector Switch to MANUAL.

Page 20 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 020 Given the following: Unit 2 reactor tripped Trip and Bypass breakers are open Neutron flux is lowering One control rod is stuck at 100 steps with the rod bottom light NOT lit The crew is responding to the stuck rod in EOP 0.1, Reactor Trip Response Is emergency boration required for the stuck rod and if so from where and why? A. Emergency boration is not required at this time for shutdown margin. No immediate action is required since the core is designed for adequate shutdown margin in the current condition. B. 2825 gallons of boration from a BAST is required. The shutdown reactivity margin must be made up through emergency boration to account for the reactivity worth of the stuck rod. C. Emergency boration is not required at this time for shutdown margin. Charging flow will provide sufficient borated water to ensure an adequate shutdown margin. D. 2825 gallons of boration from an RWST is required. The shutdown reactivity margin must be made up through emergency boration to account for the reactivity worth of the stuck rod.

Page 21 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 021 Given the following: Unit 1 is at Rated Thermal Power Charging pumps are in manual due to a Pressurizer level control malfunction Initial plant conditions are Pressurizer level is stable 1TI-126, Regenerative Heat Exchanger Charging Outlet temperature is 499°F 1TI-127, Regenerative Heat Exchanger Letdown Outlet temperature is 262°F 1PI-135, Letdown Line Pressure is 257 psig A Chemical and Volume Control System malfunction occurs resulting in the following conditions: Pressurizer level is lowering slowly 1TI-126, Regenerative Heat Exchanger Charging Outlet temperature is 539°F 1TI-127, Regenerative Heat Exchanger Letdown Outlet temperature is 376°F 1PI-135, Letdown Line Pressure is 257 psig Which of the following malfunctions would explain the observed change in indications? A. Loss of air to 1CV-142, Charging Header Flow Control Valve B. Loss of air to 1CV-135, Letdown Back Pressure Control Valve C. A Letdown line leak upstream of the Regenerative Heat Exchanger D. A Charging Header leak upstream of the Regenerative Heat Exchanger

Page 22 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 022 Given the following: A Reactor startup is in progress Intermediate Range N35 is undercompensated How will the channel's undercompensation affect its operation? A. The channel will begin to come on scale earlier/lower in the Source Range and indicate higher at 100% power. B. The channel will begin to come on scale earlier/lower in the Source Range but indicate correctly at 100% power. C. The channel will begin to come on scale later/higher in the Source Range and indicate lower at 100% power. D. The channel will begin to come on scale later/higher in the Source Range but indicate correctly at 100% power.

Page 23 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 023 Given the following: Unit 1 reactor power is 75% The following plant conditions currently exist: A Steam Generator Tube Leak is occurring The crew is responding per AOP-3, Steam Generator Tube Leak Pressurizer Level is 28% and Very Slowly Lowering Letdown has been isolated Charging flow is 138 gpm RCP Seal Injection supply flow is 9 gpm per pump RCP seal return flow is 1.6 gpm per pump The leaking Steam Generator Level is 64% and Stable RCS Subcooling is 28°F and Stable Based on the information provided above which of the following statements is correct? A. Charging flow is low for the given conditions and should be adjusted higher. B. Pressurizer Level is low for these conditions and the reactor should be tripped. C. RCP seal injection flow is high for these conditions and should be locally adjusted. D. Steam Generator Level is high for these conditions and should be manually adjusted.

Page 24 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 024 Which of the following statements lists the type of release that would be expected during an accidental spill of liquid from the tank listed? Tank Type of Release from Tank A. Holdup Tank Dissolved fission gases, mostly beta-gamma and alpha radiation B. Waste Holdup Tank Low levels of dissolved fission gases, some delayed neutron and alpha radiation C. Volume Control Tank Dissolved fission gases, mostly delayed neutron and alpha radiation D. Reactor Makeup Tank Low levels of dissolved fission gases, mostly beta-gamma radiation

Page 25 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 025 Given the following: Unit 2 has tripped The crew has entered CSP-H.2, Response to Steam Generator Overpressure, based upon a YELLOW condition on the Heat Sink CSF Status Tree SG 'A' pressure is 1150 psig SG 'B' pressure is 1050 psig SG 'A' Narrow range is 75% Instrument Air Header pressure has been lost to Unit 2 Which of the following actions will mitigate the Steam Generator overpressure condition in accordance with CSP-H.2? A. Raise the SG Blowdown flow rate for the 'A' S/G to lower level B. Open the 'A' SG MSIV Bypass Valve and/or steam 2P-29, TDAFW Pump from the 'A' SG C. Transition to CSP-H.3, Response to Steam Generator High Level to reduce the pressure in the 'A' SG D. Place the Condenser Steam Dump Mode Selector Switch in MANUAL and raise the demand on 2HFC-484, Cond Steam Dump Controller

Page 26 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 026 Given the following: Unit 2 is responding to a LOCA The STA has identified high radiation condition in containment The OS has you manually actuate Safety Injection and Containment Isolation You report the following to the OS: RS-SA-10, Radwaste Steam Supply is OPEN Isolation Panel B 2MS-2083, 'A' SG Sample Containment Isolation Valve is NOT LIT What actions are you required to take for these conditions? A. Only shutting 2MS-2083 from Control B. Shut 2MS-2083 from Control, and have the PAB AO shut RS-SA-10 C. Have the PAB AO locally shut both 2MS-2083 and RS-SA-10 D. Shut both 2MS-2083 and RS-SA-10 from Control

Page 27 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 027 Given the following: Unit 1 was operating at Rated Thermal Power when a loss of all off-site power to that unit caused a reactor trip Twenty minutes after the trip the following plant conditions exist: RCS Pressure 2235 psig Stable RCS Hot Leg Temperature 568°F Lowering RCS Cold Leg Temperature 555°F Lowering Core Exit Temperature 580°F Lowering Steam Generator Pressure 1065 psig Lowering Which of the following describes plant conditions? A. Heat removal IS BEING maintained by Condenser Steam Dumps. Natural Circulation EXISTS. B. Heat removal SHOULD BE established by opening the Atmospheric Steam Dumps. Natural Circulation DOES NOT exist. C. Heat removal SHOULD BE established by opening the Condenser Steam Dumps. Natural Circulation DOES NOT exist. D. Heat removal IS BEING maintained by Atmospheric Steam Dumps. Natural Circulation EXISTS.

Page 28 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 028 Per OP 4B, Reactor Coolant Pump Operation, select the acceptable condition(s) below for starting a Reactor Coolant Pump. A. The RCS is solid, LTOP is in service, and RCS pressure is 250 psig. B. The RCS Cold Leg temperature is 200°F and Steam Generator 'A' is 240°F, and 'B' is 245°F. C. The RCP Lift Pump has been running for 60 seconds, the amber RCP Lift Pressure light is illuminated. D. The Reactor Coolant Pump was started, run for one minute then stopped. 15 minutes has elapsed since the pump was shutdown.

Page 29 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 029 Given the following: Unit 1 is operating at Rated Thermal Power at middle of life (MOL) The standby CVCS HOH Mixed Bed was last placed in service 45 days ago The isolation valve for the standby HOH Mixed Bed has vibrated partially open What effect will this malfunction have on the operation of the plant? A. Reactor power will rise as RCS temperature rises. B. Reactor power will rise as RCS temperature lowers. C. Reactor power will lower as RCS temperature lowers. D. Reactor power will lower as RCS temperature rises.

Page 30 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 030 Given the following: Unit 1 is cooling down on RHR RCS temperature is 295 °F and Slowly Lowering RCS pressure is 310 psig and Lowering Pressurizer level is 80% and Slowly Lowering 'A' RCP is operating Sump 'A' level is 29% and Rising Which of the following would cause these indications and what action will be taken? A. 1CV-203, Letdown Orifice Outlet Relief valve lifting, enter AOP-1D, CVCS Malfunction. B. 1RH-861C, RHR Suction Header Relief valve lifting, enter SEP-2, Shutdown LOCA Analysis. C. Leak in the RHR heat exchanger aligned for RHR cooling, enter SEP 2, Shutdown LOCA Analysis. D. Leak in the RCP Seal Return heat exchanger, enter AOP-9B, Component Cooling System Malfunction.

Page 31 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 031 Given the following: Unit 1 is in Mode 3 preparing to enter Mode 2 SI Accumulator parameters are as follows: 'A' SI Accumulator Boron concentration - 3050 ppm Level - 43% Pressure - 810 psig 'B' SI Accumulator Boron concentration - 2690 ppm Level - 9% Pressure - 730 psig Which of the following describes the impact, if any, on LCO 3.5.1 Accumulators? A. Only 'A' SI Accumulator is Inoperable and LCO 3.5.1 is NOT MET. B. Only 'B' SI Accumulator is Inoperable and LCO 3.5.1 is NOT MET. C. Both 'A' and 'B' SI Accumulators are Inoperable and LCO 3.5.1 is NOT MET. D. Both 'A' and 'B' SI Accumulators are OPERABLE and LCO 3.5.1 is MET.

Page 32 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 032 Given the following: The reactor is operating at Rated Thermal Power The PRT PRESS HI TEMP HI LEVEL HI OR LO alarm is LIT The pressurizer PORVs and safety valves have been verified shut The following are indications for the PRT: PRT pressure: 6.0 psig PRT temperature: 115°F PRT level: 72%

Which of the following would cause this alarm condition, and what actions are required to mitigate? A. Seat leakage from RC-596, PRT Drain Valve to the RCDT. The PRT will need to be refilled to the required level. B. Back leakage from the Reactor Coolant System into the PRT. The PRT will need to be drained and filled to reduce the temperature to the required value. C. RH-861B, RHR Suction Relief Valve seat leakage into the PRT. The PRT will need to be drained to the required level. D. Leakage of nitrogen past valve RC-595, Nitrogen Regulator isolation for the PRT. The PRT will need to be vented to the required pressure.

Page 33 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 033 Given the following: Unit 2 is in Mode 3 2P-11A, CCW Pump, is in AUTO after START (running) 2P-11B, CCW Pump, is in AUTO after STOP (standby) A malfunction causes a trip of 2A05 4160 Safeguards Bus feeder breaker 2P-11A breaker will ___(1)___ and 2P-11B will ___(2)___. (1) (2) A. trip and need to be reset start on system low pressure when bus voltage returns B. trip and need to be reset get a start signal from the when bus voltage returns UV relays C. remain closed and the start on low system pressure pump will restart when and one pump will need to be voltage is restored secured D. remain closed and the will remain stopped since pump will restart when system pressure will be voltage is restored quickly restored

Page 34 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 034 Given the following: HC-431K, Pressurizer Master Pressure Controller will NOT control in AUTO. HC-431K was placed in MANUAL and demand lowered to 0%. Pressurizer pressure will . . . (Assume no operator actions) A. RISE until RC-430, PORV OPENS. RC-431C, PORV will remain CLOSED. B. RISE until RC-431C, PORV OPENS. RC-430, PORV will remain CLOSED. C. LOWER due to all Control and Backup Heaters remaining OFF. The Spray Valves remain CLOSED. D. LOWER due to all Control and Backup Heaters remaining OFF. The Spray Valves remain OPEN.

Page 35 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 035 Given the following: PT-429, Pressurizer Pressure (Red) instrument has been removed from service per 0-SOP-IC-001 Red, Routine Maintenance Procedure Removal of Safeguards or Protection Sensor from Service - Red Channels With the reactor at ___(1)___ power, if ___(2)___ a reactor trip will be caused? (1) (2) A. 30% N-36, IR NI (White) failed HIGH B. 30% TE-403B, THOT (Blue) failed HIGH C. 100% PT-485, Turbine First Stage Pressure (White) failed HIGH D. 100% TE-401B, Loop A Cold Leg Temperature (Red) fails HIGH Page 36 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 036 Given the following: Unit 2 is at Rated Thermal Power Power Range Channel N41 fails LOW Crew is removing N41 from service per 0-SOP-IC-001 Red, Routine Maintenance Procedure Removal of Safeguards or Protection Sensor from Service - Red Channels How are power range N41, LOW POW RANGE TRIP and HI POW RANGE TRIP bistables placed in the trip condition per 0-SOP-IC-001 Red? A. An operator trips the bistables from the instrument racks. B. The control power fuses are removed from the Power Range N41 drawer. C. The instrument power fuses are removed from the Power Range N41 drawer. D. The Comparator Channel Defeat switch is taken to the N41 position at the Comparator and Rate Drawer.

Page 37 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 037 Which of the following describes the expected response to resetting Safety Injection (SI) with an automatic signal STILL present? (Assume all systems functioned as designed, no faults other than the cause of the SI exist, and the SI Reset Pushbuttons are depressed 5 minutes after the SI actuation)

The SI ___(1)___ reset, the SI Reset Bypass Activated Lights on CO1R ___(2)___ light. (1) (2) A. will not will not B. will not will C. will will D. will will not

Page 38 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 038 Given the following: Both Units were at Rated Thermal Power Unit 2 Safety Injection occurs What is the expected response of the Service Water System to the Safety Injection? A. SW-2930A/2930B, SFP Heat Exchanger Outlet valves close AND SW-2927A/2927B, SFP Heat Exchanger Inlet valves remain open. B. 2SW-2880, Unit 2 Turbine Hall Service Water Supply valve closes to isolate water to Unit 2 Turbine Hall. C. SW-2869/2870, Service Water Cross-Connect valves close to isolate the West Service Water Header. D. 2SW-2907/2908, 2HX-15A-D Containment Recirc Heat Exchanger Emergency flow control valves open to raise flow to Containment Accident Fan Coolers.

Page 39 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 039 Given the following: Unit 1 is conducting a plant start-up per OP 1C, Startup to Power Operation The Main Turbine Generator is ready to synchronize to the grid A breaker malfunction causes 1W-1B, Containment Accident Fan to be de-energized What impact, if any, will this have on Technical Specifications? A. None, only 3 of the 4 Containment Accident Fans are required to be operable for the given MODE. B. LCO 3.6.6 Containment Spray and Cooling Systems is NOT met, take actions to restore 1W-1B back to service. C. LCO 3.6.6 Containment Spray and Cooling Systems is NOT met, you have one hour to raise cooling water to the other three fans. D. LCO 3.6.6 Containment Spray and Cooling Systems is NOT met, you have one hour to start all available Accident Fans.

Page 40 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 040 Given the following: Unit 2 is at Rated Thermal Power At 0400, both trains of Containment Spray System are determined to be inoperable Which of the following correctly states the required Technical Specification action?

Within one (1) hour, the operators must. . . A. Return at least one train to service or initiate action to be in Hot Standby by no later than 1000. B. Initiate action in order to be in Hot Standby by no later than 1100. C. Return at least one train to service or initiate action to be in Hot Standby by no later than 1600. D. Initiate action in order to be in Hot Standby by no later than 1700.

Page 41 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 041 Given the following: Unit 1 is at Rated Thermal power The reactor tripped due to a failed reactor trip relay What happens to the steam stored in the Main Steam Reheaters (MSRs) and Turbine, and why A. Condenser Steam and Crossover Steam Dumps open for about 60 seconds and both continue to operate based on RCS temperature to stabilize the primary plant. B. The Turbine Generator stays tied to the grid for about 60 seconds and the Crossover Steam Dumps will open to protect the turbine from an overspeed condition if required. C. The Condenser Steam Dumps open to remove the initial decay heat from the primary, steam pressure in the MSRs and Turbine remain as designed. D. The Turbine Generator is removed from the grid, the Low Pressure Turbine rupture discs remove excess steam energy, protecting the turbine from an overspeed condition.

Page 42 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 042 Given the following: At 10:00, Unit 1 plant conditions were as follows: Unit 1 is in MODE 3, cooling down per OP 3C, Hot Standby to Cold Shutdown RCS TAVG at 495°F and Stable RCS Pressure is at 1750 psig and Stable Both Steam Generator pressures are 640 psig and Stable At 10:20, Unit 1 plant conditions were as follows: A Steam Line Break occurs on 'A' SG Main Steam line inside containment resulting in the following indications: Containment Pressure is 10 psig and Rising RCS Pressure is 1150 psig and Lowering 'A' SG Pressure is 400 psig and Lowering 'B' SG Pressure is 460 psig and Lowering Both 'A' SG HIGH STEAM FLOW bistables are LIT Both 'B' SG HIGH STEAM FLOW bistables are NOT LIT Which of the following describes the expected position of 1MS-2018, A Main Steam Line Isolation Valve and why? (Assume no operator action) A. OPEN, the valve will automatically close when Containment Pressure rises to 15 psig. B. OPEN, the valve will not automatically close due to the SI BLOCK, it must be manually closed. C. CLOSED, the valve will have automatically closed when 'A' SG Pressure reached 545 psig. D. CLOSED, the valve will have automatically closed due to the 'A' SG Steam Flow HIGH, and LOW Tavg with a SI signal.

Page 43 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 043 Given the following: Unit 1 is at 20% reactor power 1P-28A, Steam Generator Feed Pump, is running 1P-28B, Steam Generator Feed Pump, is in standby The Main Turbine Generator tripped due to an EHC malfunction What impact, if any, will this have on feeding the steam generators? 1P-28A 1P-28B 1P-53, MDAFW pump A. running standby standby B. tripped running standby C. tripped standby running D. running standby running

Page 44 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 044 Given the following: Unit 2 was operating at 100% reactor power All systems in their normal at-power alignment A failed air start motor caused G-02, Emergency Diesel Generator to be declared out of service The alternate emergency diesel power source was aligned to the affected bus Which of the following additional combinations of equipment malfunctions would result in a loss of normal and emergency power availability for the 2P-53, Motor-Driven AFW Pump? A. 2X-02 lockout and G-01 EDG failure B. 2X-02 lockout and G-04 EDG failure C. 2X-04 lockout and G-01 EDG failure D. 2X-04 lockout and G-04 EDG failure

Page 45 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 045 Given the following: Unit 1 is at Rated Thermal Power The Turbine Hall AO reports that the P-38A, Standby Steam Generator Feed Pump, casing is too hot to touch 1TR-2000B point 25, P-38A INBD PUMP BRG, is reading 180°F and slowly rising The Crew has entered AOP-2C, Auxiliary Feed Pump Steam Binding or Overheating Which of the following is the required action(s)? A. Manually re-seat P-38A discharge MOV's and monitor temperatures. B. Check shut P-38A discharge MOV's and start the pump to cool the casing. C. Start P-38A and vent the casing until a solid stream of water is observed to allow cooling. D. Check shut P-38A discharge MOV's and vent the pump casing until a solid stream of water is observed to allow cooling.

Page 46 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 046 Given the following: Units 1 and 2 are at Rated Thermal Power An electrical perturbation results in the following: 2A52-96, 2A04 to 2A-06 Bus Tie Breaker trips open 2B52-25B, 2B04 480 VAC Safeguards Bus normal feeder breaker trips open No faults are present on any bus Which of the following describes the availability of electrical power to 2P-15B, 'B' SI pump and 2P-10B, 'B' Residual Heat Removal pump 2 minutes later? (Assume no operator actions) 2P-15B 2P-10B A. available available B. available not available C. not available available D. not available not available

Page 47 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 047 According to AOP 0.0, Vital DC System Malfunction, a loss of which of the following would cause a DUAL UNIT TRIP? A. D01 B. D13 C. D18 D. D21

Page 48 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 048 Given the following: The unit suffered a loss of all AC power G01 EDG is being started locally G01 voltage is out of the normal band due to the field not flashing What action is needed to flash the field on G01 EDG? A. Shift DC control power fuse disconnects from D-28 to D-40. B. Depress the FFC relay inside the C-34 cabinet for 3 seconds. C. Take the EDG Mode Selector Switch in the C-64 cabinet to HYD. D. Depress the VOLTAGE SHUTDOWN reset pushbutton in the C-81 cabinet.

Page 49 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 049 Given the following: Unit 1 experienced a trip with a loss of all off-site power The unit has been stabilized using required procedures Due to equipment issues the steam generators are being fed as follows: 'A' S/G being fed by 1P-53 Motor Driven AFW Pump 'B' S/G being fed by P-38B Standby Steam Generator Pump Subsequently, G01 EDG output breaker opened and was re-closed to power up the associated safeguards bus What is the status of the feedwater to the Unit 1 S/G's? 1P-53 P-38B A. Remains running Is stripped and needs to be manually restarted B. Is stripped and will auto sequence Remains running back on C. Is stripped and will auto sequence Is stripped and needs to be back on manually restarted D. Remains running Remains running

Page 50 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 050 Given the following: Unit 2 is at Rated Thermal Power Excess Letdown is in service 2RE-217, Component Cooling Water Liquid Monitor, goes in to HIGH ALARM Which of the following will automatically shut? A. CCW-LW-63 and CCW-LW-64, Radwaste System CC Supply and Return B. 2CC-769, Excess Letdown Heat Exchanger Shell Side Outlet Valve C. 2CC-761A and 2CC-761B, RCP Thermal Barrier Outlets D. 2CC-17, Surge Tank Vent Isolation

Page 51 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 051 Given the following: Unit 1 has been operating at 100% power for several weeks 1SC-938C, 1RE-109 Failed Fuel Monitor Flow Throttle, which is normally in a throttled position, was inadvertently placed in a full open position after Reactor Coolant System sampling 1RE-109, Failed Fuel Monitor, indication will ____________. A. lower due to increased bypass flow around the detector B. rise because more N 16 gammas will reach the detector C. remain the same, because the activity of the reactor coolant has not changed D. lower due to the increased flow rate which lowers the exposure time of N 16 gammas to the detector

Page 52 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 052 Given the following: Both Units were at Rated Thermal Power P-32A, P-32B, and P-32D, Service Water pumps were running Subsequently, 1X04, LV Station Aux Transformer locks out Unit 1 Safety Injection occurred simultaneously with the 1X04 lockout G03 EDG Output breaker failed to close Which of the following is a COMPLETE list of which Service Water pumps will be running two minutes later? (Assume no operator action) A. A, B, and F B. D, E and F C. A, B, D and E D. A, B, D, E and F

Page 53 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 053 Given the following: Unit 1 is at Rated Thermal Power A Loss of Instrument Air has occurred South Instrument Air Header is reading 0 psig Which of the following describes the effect of the loss of control air on the Unit 1 Main Steam Isolation Valves (MSIVs)?

The MSIVs. . . A. will remain open and can only be closed locally by actuating the vent solenoid pushbuttons. B. will remain open due to instrument air not being required to hold the MSIV open. C. close due to loss of instrument air pressure holding the MSIV open. D. close due to the vent solenoids no longer being held closed by instrument air pressure.

Page 54 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 054 Given the following: Unit 1 is at 28% reactor power K3A, Service Air Compressor is running 1A04, 4160 Non-Safeguards Bus lockout has occurred, causing a momentary loss of power to 1A06, 4160 Safeguards Bus Required EDG is running and supplying 1A06 The crew is restoring previously running loads What actions, if any, are required to restore K3A Service Air Compressor to service? A. Nothing, K3A is unaffected by the loss of 1A04 B. Nothing, K3A restarts upon re-energizing of 1B04 C. Reset the K3A control switch from OFF to CONSTANT, at the C01R D. Close the breaker on 1B04 by pressing the CLOSE button, then start K3A

Page 55 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 055 Given the following: Unit 1 is in Mode 6 RCS temperature is 100°F and Stable RCS time to boil is 1.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Containment operability is not being maintained Containment purge is in operation per OP 9C, Containment Venting and Purging The Unit 1 containment upper personnel airlock has malfunctioned such that neither door can be shut Maintenance estimates that it will take 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to return at least one of the doors to service Which of the following is a valid concern about the status of the upper airlock? A. An unmonitored release to the atmosphere is taking place while both airlock doors are open. B. The lower airlock cannot be utilized because one of its bulkhead doors must be locked shut. C. The containment closure time requirements of CL 1E, Containment Closure Checklist, are not met. D. The upper airlock will not be returned to service before the one hour Technical Specification Action Condition time has expired.

Page 56 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 056 Given the following: Unit 1 is at Rated Thermal Power Train 'B' reactor trip breaker testing in progress with the following line up: 'A' Reactor Trip Breaker (RTA) is shut 'B' Reactor Trip Bypass breaker (BYB) is shut An ACTUAL reactor trip condition occurs The 'A' Reactor Trip Breaker (RTA) UV coil does not function Which of the following, if any, would be the FIRST to open the 'A' Reactor Trip Breaker (RTA): A. Breaker would not trip B. RTA shunt trip coil actuates C. RTA redundant UV coil actuates D. Local breaker trip pushbutton is pressed

Page 57 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 057 Given the following: Unit 2 is at Rated Thermal Power Volume Control Tank (VCT) level is at 38% 2LT-428, Pressurizer Level transmitter (Blue) loses the level in its reference leg No ESF actuations occur as a result of the reference leg leak Which of the following describes the VCT Level response as the plant stabilizes? (Assume no operator actions) A. rise and be maintained between 56% and 78%. B. lower, then be maintained between 17% and 28%. C. lower to 4%, cause charging pump suction to transfer to the RWST. D. rise to between 56% and 78%, then lower and be maintained between 17% and 28%.

Page 58 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 058 Given the following: The reactor is initially critical below the Point of Adding Heat Both Reactor Coolant Pumps are running Main Steam Isolation Valves (MSIV) and MSIV bypass valves are closed Moderator Temperature Coefficient is negative RCS TAVE is 547°F and stable with heat removal through the Atmospheric Steam Dumps Intermediate Range Nuclear Instruments N-35 and N-36 indicate 4x10-7 amps and Stable If both Atmospheric Steam Dumps fail CLOSED and NO operator action is taken, how will reactor power respond?

Reactor power will lower . . . A. initially, then return to 4x10-7 amps on Intermediate Range instruments due to subcritical multiplication. B. to a subcritical power level and stabilize at a value in the source range based on subcritical multiplication. C. initially, then return to 4x10-7 amps on Intermediate Range instruments due to the resulting rise in RCS TAVE. D. until the positive reactivity from the temperature rise causes the reactor to stabilize at a critical power level in the Source Range.

Page 59 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 059 Given the following: Unit 2 is at Rated Thermal Power Containment Forced Vent is in progress per OP 9C, Containment Venting and Purging 2P-707B, Containment Forced Vent Pump, is running. IF 2RE-212, Unit 2 Containment Noble Gas Monitor, goes to the HIGH ALARM condition, which of the following automatic actions will occur AND what actions will the Unit 2 operators take? (CVI - Containment Ventilation Isolation CI - Containment Isolation) A. No automatic actions will occur. Operators will compare 2RE-212 readings to other Containment radiation monitors and determine whether forced vent may continue. B. CVI will automatically occur. Operators will need to manually secure 2P-707B, to prevent it from running without a discharge path. C. CVI will automatically occur. Operators will verify that 2P-707B, is off and that 2RM-3200H, Containment Forced Vent Pump Discharge Valve, is closed. D. CI and CVI will automatically occur. Operators will verify 2P-707B, is off and 2RM-3200H, Containment Forced Vent Pump Discharge Valve is closed and that all Containment Isolation Valves repositioned as required.

Page 60 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 060 Which of the following describes when the Spent Fuel Bridge Hoist should be placed in 'bypass'? A. To allow the bridge to access new fuel elevator. B. To bypass the maximum weight limit interlock of the hoist when raising the hoist. C. To allow the bridge to use the offset fuel handling tool in the SFP perimeter racks. D. To bypass the minimum weight limit interlock of the hoist when lowering the hoist.

Page 61 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 061 Given the following: Unit 1 is operating at Rated Thermal Power 1PT-486, HP First Stage Turbine Pressure Transmitter fails as is If the turbine were to trip, the transmitter failure will __________. (Assume no operator action) A. have no effect, the condenser steam dumps will operate as designed causing RCS TAVE to lower to a value of 547°F B. prevent the condenser steam dump valves from "arming", the deviation signal caused by the rising RCS temperature will have no effect C. cause all of the steam dumps to "blow open"; the operator must place the mode selector switch to MANUAL to prevent an excessive RCS cooldown D. prevent the condenser steam dump valves from modulating; RCS TAVE will be maintained at the lowest "blow open" temperature value of 547°F

Page 62 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 062 Given the following: The Unit is at Rated Thermal Power Main Condenser Vacuum has degraded several inches to a new steady state value The Crew is responding to the event per the Abnormal Operating Procedures Vacuum was recovered by stopping condenser air in-leakage, this was the only action taken to recover vacuum Which of the following will result as vacuum recovers? A. Rising megawatt output with lowering hotwell temperature. B. Rising megawatt output with rising hotwell temperature. C. Lowering megawatt output with lowering hotwell temperature. D. Lowering megawatt output with rising hotwell temperature.

Page 63 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 063 Given the following: A discharge of the 'A' Monitor Tank is in progress Which of the following would provide the Control Operator indication that WL-18, Waste Condensate Overboard Discharge to SW Header Control Valve, should have automatically closed? A. The COMMON PROCESS RADIATION MONITOR HIGH annunciator alarms. B. RE-218, Waste Disposal System Liquid Monitor, status indication on the RMS server changes from green to red. C. RE-223, Waste Distillate Tank Overboard Monitor, status indication on the RMS server changes from green to blue. D. The status light for WL-18, Waste Condensate Overboard to SW header control valve is lit on the Containment Isolation Panel.

Page 64 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 064 What automatic actions occur when a RE-214, Auxiliary Building Vent Stack Monitor, goes into high alarm and why? A. Shifts the Auxiliary Building ventilation to 100 % recirculation to minimize radioactive release from the PAB. B. All PAB ventilation fans trip and associated dampers close to isolate any potential release to outside the PAB. C. W-35, PAB Supply Fan stops to create a more negative pressure in the PAB to minimize radioactive release to the outside environment. D. F-23, PAB Charcoal Filter isolation dampers open and F-29, PAB HEPA Filter isolation damper closes to filter and minimize the release.

Page 65 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 065 Given the following: A Loss of Instrument Air has occurred The crew is performing actions of AOP-5B, Loss of Instrument Air Instrument Air header pressure is 80 psig and Lowering Slowly Which of the following is the required action related to IA-3079 and IA-3014, North and South Header Service Air to Instrument Air Backup valves? A. Ensure IA-3079 and IA-3014 automatically opened; the valves opened at 85 psig and lowering. B. Manually open IA-3079 and IA-3014; the valves have no automatic features. C. Ensure IA-3079 and IA-3014 automatically closed; the valves closed at 85 psig lowering. D. Manually close IA-3079 and IA-3014; the valves have no automatic features.

Page 66 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 066 Given the following: The mid shift is at minimum crew composition per OM 3.1, Operations Shift Staffing Requirements The STA holds an inactive SRO license At 0130 the 4th reactor operator leaves the site due to an emergency at home What action, if any, is required to restore shift staffing? A. An emergency call out must begin immediately to restore shift staffing. B. The OS2 must turn over command and control and assume the duties of the 4th license. C. The STA must report to the control room and remain there until the next crew arrives at 0650. D. No action is required as long as the licensed operators assigned to each unit remain in the control room until the next crew arrives at 0650.

Page 67 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 067 Given the following: A Unit 1 Core reload is in progress per RP-1C, Refueling You are the Unit 1 Reactor Operator Which of the following conditions would require the refueling operation to cease? A. RCS boron concentration has lowered from 2430 to 2375 PPM. B. RHR Heat Exchanger inlet temperature has risen from 90°F to 110°F. C. Source Range channel N-31 indicates a rise above the baseline count rate by a factor of 3.5. D. Source Range channels N-32 AND N-40 indicate a rise above the baseline count rate by a factor of 1.5.

Page 68 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 068 Given the following: Unit 1 is at Rated Thermal Power Pressurizer Level Channel Selector Switch is in OPERATE position Letdown isolates due to a Pressurizer level instrument failure The Control Operator states that the controlling level channel has failed Which of the following would validate the accuracy of the operator's diagnosis that the controlling channel, and not the backup channel, has failed? A. Backup heaters turn off B. Letdown orifice valves close C. The speed of the Charging Pump in AUTO is rising D. 1C04 1C 1-3, PRESSURIZER LEVEL HIGH OR LOW is LIT

Page 69 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 069 See the PROVIDED information from the ROD 3.2, ICRR for a Unit 1 Reactor Startup. Which of the following actions are required to be performed per OP 1B, Reactor Startup? A. Perform a 100 pcm control rod withdraw. B. Perform the next 400 pcm control rod withdraw. C. Notify the Shift Manager and insert control bank rods. D. Immediately trip the reactor and notify the Shift Manager.

Page 70 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 070 Given the following: Unit 2 is being started up per OP 1B, Reactor Startup, following a mid-cycle trip Control Bank 'A' has been withdrawn to 35 steps 'A' and 'B' RCPs both trip due to a bus voltage fluctuation which quickly stabilizes back to normal voltage What actions are required to be taken? A. Respond to the automatic reactor trip in accordance with EOP-0, Reactor Trip or Safety Injection. B. Manually trip Unit 2 reactor and respond to manual trip in accordance with EOP-0, Reactor Trip or Safety Injection. C. Abort the startup and drive control bank rods to 0 steps. When RCPs are restored, initiate a new copy of OP 1B and recommence startup. D. Suspend the startup; enter AOP-1B, Reactor Coolant Pump Malfunction, to restart the RCPs and continue with the startup with the Shift Manager's permission.

Page 71 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 071 Which of the following conditions defines MODE 3 per Technical Specifications? A. Keff < 0.99 TAVE <350°F B. Keff > 0.99 TAVE >350°F C. Keff > 0.99 TAVE <350°F D. Keff < 0.99 TAVE >350°F Page 72 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 072 Given the following: You are a Relief Crew CO, performing a valve lineup in the PAB during a Refueling Outage The valve line up requires the you to go 10' into the overhead to operate a valve What action are you going to take, if any, per the Operations Routine Job RWP? A. No action is required, the PAB is routinely surveyed, any hazards will be posted. B. No action is required if less than a shift since the last survey was performed. C. You are required to notify RP prior to taking any actions > 6ft in the overhead. D. You are required to have a meter to check dose rates when going > 6 ft in the overhead.

Page 73 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 073 Prior to moving irradiated fuel assemblies with the Spent Fuel Bridge and the Spent Fuel Handling Tool, we ensure that long-handled tools have holes drilled in them. Why do we require long handled tools to fill with water while working in the SFP? A. To prevent radiation streaming from highly radioactive material stored under water. B. Filling the tools with water helps minimize buoyancy for easier handling of fuel assemblies. C. The water provides shielding which minimizes spurious Spent Fuel Pool Area Radiation Monitor Alarms. D. Keeping the inside of the tool wet prevents airborne conditions from developing thus minimizing personnel exposure.

Page 74 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 074 Many of PBNP's Emergency Operating Procedures (EOPs) contain the following note: "RCPs should be run in order of priority to provide normal PZR spray . . ."

Concerning this note, which choice completes the following statement:

The correct starting order of the pumps is ___(1)___ and the bases is that with the plant design of one surge line and two spray lines, the RCP in the loop

___(2)___ the pressurizer surge line, if running, provides normal pressurizer spray.

(1) (2) A. A then B with B. A then B opposite C. B then A with D. B then A opposite

Page 75 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 075 Given the following: Unit 2 is at Rated Thermal Power The following events happen: 2105 Power is lost to all Control Room annunciators 2120 The Shift Manager (SM) declares an Unusual Event 2125 The NARS form is completed, and the SM directs an operator to make the notification to the state and counties 2130 A reactor trip occurs on Unit 1 and the SM declares a Site Area Emergency 2135 The SM completes a new Emergency Notification Form and directs the notification of state and counties Which of the following indicates the latest time when the initial state and county notifications must be completed? A. 2135 B. 2140 C. 2145 D. 2150 Page 76 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 076 Given the following: A loss of Coolant Accident (LOCA) occurred from 100% power on Unit 1. The crew is performing the actions of EOP-0, Reactor Trip or Safety Injection currently at Step 21, Check if RCPs Should be Stopped. Tcold is 315°F and Lowering. RCS pressure is 90 psig and Lowering. Containment pressure has peaked at 10 psig and is Stable. All Engineered Safeguards Equipment functions as designed with the exception of Safety Injection Pumps which cannot be started. Reactor Coolant Pumps (RCPs) are running. What actions are required regarding the RCPs AND what procedure transition, if any, is required? A. Trip RCPs AND continue in EOP-0, Reactor Trip or Safety Injection. B. Trip RCPs AND transition to CSP-P.2, Response to Anticipated Pressurized Thermal Shock Condition C. Keep RCPs running AND continue in EOP-0, Reactor Trip or Safety Injection. D. Keep RCPs running AND transition to CSP-P.2, Response to Anticipated Pressurized Thermal Shock Condition.

Page 77 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 077 Given the following: Unit 1 is at Rated Thermal Power Unit 2 is in MODE 5 The following issues happen to the Component Cooling Water (CCW) System 1 February at 0600, HX-12B, CCW Heat Exchanger develops a tube leak and is declared inoperable 2 February at 0200, 1P-11A, CCW Pump is declared inoperable due to vibrations 4 February at 1400, HX-12C, CCW Heat Exchanger is declared inoperable due to a tubesheet leak 4 February at 2200, 1P-11A is repaired, tested and declared OPERABLE 6 February at 2100, 1P-11B, CCW Pump is declared inoperable for a bearing failure 7 February at 1300, HX-12B is repaired, tested and declared OPERABLE Assuming that the current inoperable components cannot be repaired and brought to an OPERABLE status, which describes the latest allowable date and time which Unit 1 must be in MODE 3? (See provided reference) A. 7 February at 2000 B. 8 February at 0800 C. 10 February at 0300 D. 10 February at 2000

Page 78 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 078 Given the following: Unit 1 was at Rated Thermal Power A steam line break developed inside containment The conditions immediately following the steam line break were: Reactor tripped Containment pressure was 7 psig and Rising Pressurizer Level was 30% and Lowering Pressurizer Pressure was 1745 psig and Lowering Rapidly Mitigating the event, the crew has transitioned to and completed the actions required in EOP-2, Faulted Steam Generator Isolation Current plant conditions are: Containment pressure is 26 psig (maximum) and Lowering Pressurizer Level is 22% and Rising RCS Pressure is 1735 psig and Slowly Rising RCS Subcooling is 100°F and Rising Which of the following identifies: (1) Using the conditions immediately following the steam line break, which SI initiation signal was generated when 2 pressure bistables reached the setpoint AND (2) when transitioning from EOP-2, to which procedure should the SRO transition? A. (1) Low Pressurizer Pressure (2) EOP-1.1, SI Termination B. (1) Low Pressurizer Pressure (2) EOP-1, Loss of Reactor or Secondary Coolant C. (1) High Containment Pressure (2) EOP-1.1, SI Termination D. (1) High Containment Pressure (2) EOP-1, Loss of Reactor or Secondary Coolant

Page 79 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 079 Given the following: Unit 1 is at Rated Thermal Power A Reactor Trip occurred coincident with a Loss of Offsite Power Only 1A-06 and 1B-04 are energized from its Emergency Diesel Generator Buses 1A-05, and 1B-03 are NOT energized The crew transitions to CSP-H.1, Response to Loss of Secondary Heat Sink, and is performing the first step The diesel generator output breaker supplying 1A-06 trips open for no apparent cause Which of the following identifies: (1) the required action(s) AND (2) the basis for the action(s)? A. (1) Transition to ECA-0.0, Loss of All AC Power (2) because the ECA will direct actions to establish a heat sink with the TDAFW pump B. (1) Transition to ECA-0.0, Loss of All AC Power (2) because all CSPs are written on the premise that at least one AC safeguards train is energized. C. (1) Remain in CSP-H.1, to recover and establish a heat sink with the TDAFW pump (2) because restoring heat sink is the highest priority evolution in progress D. (1) Remain in CSP-H.1 and perform AOP-19B, Train 'B' Safeguards Bus Restoration, in parallel to restore the breaker alignment and power to 1A-06 (2) because all CSPs are written on the premise that at least one AC safeguards train is energized.

Page 80 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 080 Given the following: Unit 1 and Unit 2 are at Rated Thermal Power K-2B, Instrument Air Compressor is out of service for repair A Service Water (SW) leak occurs in the plant K-2A, Instrument Air Compressor, AND K-3A, Service Air Compressor trip The crew enters AOP-9A, Service Water System Malfunction, and isolates the South SW header to isolate the SW leak Complete the following statement K-3B will ___(1)___, an OS will enter AOP-5B, Loss of Instrument Air and ___(2)___. (1) (2) A. trip on high SW discharge remain in AOP-5B, no transitions temperature from AOP-5B are required B. continue to run, SW remain in AOP-5B, no transitions cooling is not required from AOP-5B are required C. trip on high SW discharge trip both reactors and enter temperature EOP-0, Reactor Trip or Safety Injection, while concurrently performing AOP-5B, Loss of Instrument Air D. continue to run, SW trip both reactors and enter cooling is not required EOP-0, Reactor Trip or Safety Injection, while concurrently performing AOP-5B, Loss of Instrument Air

Page 81 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 081 Given the following: American Transmission Company (ATC) notified PBNP that a Solar Magnetic Disturbance (SMD) warning of Kp8 has been issued The crew has implemented AOP-31, Solar Magnetic Disturbance Alert Response Generator MVARS are in the OUT direction Attachment B, GSU Power Transformer DC Neutral Ground Current Data has been started for both 1X01 and 2X01, Main Transformers Which of the following actions should you direct per AOP-31?

Enter AOP-17A, Rapid Power Reduction and . . . (See provided reference) A. only reduce load on Unit 1 to 78%. B. only reduce load on Unit 2 to 63%. C. reduce load in both Units to 78%. D. reduce Unit 1 load to 78% and Unit 2 load to 63%.

Page 82 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 082 Given the following: Unit 1 is entering a refueling outage RCS temperature is 130°F and stable RCPs are secured Both trains of RHR are aligned for decay heat removal with 'A' train providing cooling Draindown to 40% Pressurizer level per OP 4D Part 1, Draining the Reactor Coolant System, was just completed The Control Operator then reports the following information to you: Pressurizer level is slowly rising Source range counts are rising on both N-31 and N-32 1C04 1C 2-8 BA FLOW DEVIATION OR POTENTIAL DILUTION IN PROGRESS alarm is LIT As the Operations Supervisor of that unit what actions are you going to take? A. Use OP 4A, Filling and Venting Reactor Coolant System, Attachment D, Blending Operation for Unit 1 and Unit 2, to borate the RCS from the blender using an available Charging Pump. B. Enter AOP-6F, Low Concentration Water Pockets in RCS, and borate the RCS from the RWST using a Safety Injection Pump. C. Enter SEP-1, Degraded RHR System Capability, in an effort to raise RHR flow to 3000 gpm ensuring prompt mixing of the RCS. D. Enter CSP-S.1, Response to Nuclear Power Generation/ATWS, and emergency borate the RCS from the RWST using all available Charging Pumps.

Page 83 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 083 Given the following: Refueling operations are in progress on Unit 2 It has been 7 days since shutdown The Containment Equipment hatch is removed Irradiated fuel is being moved with the manipulator from the core to the containment upender for transfer to the Spent Fuel Pool A leak is reported from the refueling cavity drain line cleanout flange Refueling Cavity water level is slowly lowering Identify the direction the Core Load Supervisor should provide during this event. A. Store the irradiated fuel assembly in any available core location, THEN shut the Transfer Tube Gate Valve. B. Store the irradiated fuel assembly in the Spent Fuel Pool upender Frame Down, THEN shut the Spent Fuel Pool Transfer Canal Doors. C. Store the irradiated fuel assembly in any available core location, THEN have the Control Room secure Unit 2 Purge Supply and Exhaust Fans. D. Store the irradiated fuel assembly in the containment upender Frame Down, THEN shut the Transfer Tube Gate Valve AND the Spent Fuel Pool Transfer Canal Doors.

Page 84 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 084 Given the following: A LOCA occurred on Unit 1 EOP-1, Loss of Reactor or Secondary Coolant is in progress The following plant conditions are noted: Reactor Coolant System Pressure 460 psig Slowly Lowering Core Exit Thermocouples 470°F Slowly Lowering Containment pressure 23 psig Slowly Lowering Containment Sump 'B' level 88 inches Slowly Rising Containment Radiation Monitor 31 R/hr Stable Reactor Vessel Narrow Range Level 19 ft Slowly Rising Reactor Vessel Wide Range Level 45 ft Slowly Rising Reactor Coolant Pumps are secured Which CSP will the OS direct transition to? A. CSP-C.1, Response to Inadequate Core Cooling B. CSP-C.2, Response to Degraded Core Cooling C. CSP-Z.1, Response to High Containment Pressure D. CSP-Z.2, Response to Containment Flooding

Page 85 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 085 Given the following: Unit 1 was operating at Rated Thermal Power A rapid uncontrolled depressurization of both steam generators occurs The crew transitioned to CSP-P.1 Response to Imminent Pressurized Thermal Shock Condition The crew is assessing whether an RCS Temperature Soak is required Which of the following states the procedure requirement that determines if an RCS Temperature Soak is required, and the bases? RCS Cooldown Bases for requirement A. Greater than 200°F Prevent flaw growth due to excessive tensile in any 60 minutes stresses on Reactor Vessel outer wall B. Greater than 100°F Prevent flaw growth due to excessive tensile in any 60 minutes stresses on Reactor Vessel inner wall. C. Greater than 200°F Prevent flaw growth due to excessive tensile in any 60 minutes stresses on Reactor Vessel inner wall. D. Greater than 100°F Prevent flaw growth due to excessive tensile in any 60 minutes stresses on Reactor Vessel outer wall

Page 86 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 086 Given the following: Unit 1 is being started up after a refueling outage The turbine is being synchronized with the grid The following annunciators are LIT 1C03 1D 2-1, 1P-1A OR B RCP LABYR SEAL DELTA-P LOW 1C03 1D 3-3, 1P-1B RCP NO. 1 SEAL WATER FLOW HIGH OR LOW The following indications are noted on the control boards 1P-1B RCP Labyrinth seal Delta-P (-)30"H20 Stable 1P-1B RCP No. 1 Seal Outlet Temperature 132°F Slowly Rising RCP B Seal leakage High Range Flow 6 gpm Stable The OS1 will direct which of the following sequences of actions? A. 1. Enter AOP-1A, Reactor Coolant Leak 2. Trip the Reactor 3. Transition to EOP-0, Reactor Trip or Safety Injection to stabilize the plant 4. Trip 'B' RCP 5. Shut 1RC-431B, PZR Normal Spray Valve 6. After 3 minutes, open 1CV-386, RCP Seal Water Bypass Control Valve B. 1. Enter AOP-1A, Reactor Coolant Leak 2. Transition to AOP-1B, Reactor Coolant Pump Malfunction 3. Trip 'B' RCP 4. Transition to EOP-0, Reactor Trip or Safety Injection 5. Trip the Reactor and to stabilize the plant 6. Shut 1RC-431 A AND 1RC-431B, PZR Normal Spray Valve 7. After 3 minutes, shut 1CV-270B, RCP 'B' No. 1 Seal Water Return MOV C. 1. Enter AOP-1B, Reactor Coolant Pump Malfunction 2. Trip the Reactor 3. Transition to EOP-0, Reactor Trip or Safety Injection to stabilize the plant 4. Trip 'B' RCP 5. Shut 1RC-431B, PZR Normal Spray Valve 6. After 3 minutes, shut 1CV-270B, RCP 'B' No. 1 Seal Water Return MOV D. 1. Enter AOP-1B, Reactor Coolant Pump Malfunction 2. Transition to EOP-0, Reactor Trip or Safety Injection 3. Trip the Reactor AND both RCPs concurrently 4. Stabilize the plant using EOP-0 5. Place steam dump mode selector in MANUAL

6. Shut 1RC-431B, PZR Normal Spray Valve 7. After 3 minutes, open 1CV-386, RCP Seal Water Bypass Control Valve

Page 87 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 087 Given the following: Unit 1 is at 50% of Rated Thermal Power 1RC-431C, Pressurizer PORV has failed open 1RC-515, PRZ PORV Isolation MOV does NOT close when operated 1. Which of the following will be the indication that the PRT rupture disc has ruptured? AND 2. What sequence of procedures would be required to mitigate this event?

EOP-0, Reactor Trip or Safety Injection EOP-0.1, Reactor Trip Response EOP-1, Loss of Reactor or Secondary Coolant EOP-1.1, SI Termination EOP-1.2, Post LOCA Cooldown and Depressurization A. 1. PRT temperature trending up. 2. EOP-0 to EOP-0.1 B. 1. PRT temperature trending up. 2. EOP-0 to EOP-1 to EOP-1.1 C. 1. Pressurizer relief valves outlet temperature trending down. 2. EOP-0 to EOP-0.1 to EOP-1.2 D. 1. Pressurizer relief valves outlet temperature trending down. 2. EOP-0 to EOP-1 to EOP-1.2

Page 88 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 088 Given the following: A Large Break LOCA has occurred on Unit 1 Crew is currently in EOP-1.3, Transfer to Containment Sump Recirculation - Low Head Injection Crew is unable to open 1SI-850A, Train 'A' RHR Pump Suction From Containment Sump 'B', from the control room What direction should be provided to the crew to address this malfunction? A. Continue in EOP-1.3 after directing the PAB AO to locally open 1SI-850A, in order to align 'A' train of sump recirc. B. Direct the PAB AO to locally open 1SI-850A, in order to align 'A' train of sump recirc. Continue in EOP-1.3 only if this is successful. C. Enter ECA-1.1, Loss of Containment Sump Recirculation, to perform the alternate alignment. Continue in parallel with actions in EOP-1.3 to recover 'A' train of sump recirc. D. Perform applicable sections of OP 7A, Placing Residual Heat Removal System in Operation, in parallel with EOP-1.3 to establish 'A' train sump recirc.

Page 89 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 089 Given the following: Unit 1 is operating at full power with operators responding to the following transient: Containment pressure is 1.5 psig and Rising C01 B 1-4, UNIT 1 CONTAINMENT SUMP A LEVEL HIGH annunciator is LIT Steam Generator 'A' level is 45% and Lowering Slowly Steam Generator 'B' level is 64% and Stable Both Steam Generator pressures are approximately 800 psig and Stable The Operating Supervisor directs a manual Reactor Trip and Safety Injection Which of the following events is occurring and what is the required procedural flow path for the event? EOP-0, Reactor Trip and Safety Injection EOP-1 Loss of Reactor or Secondary Coolant EOP-2, Faulted Steam Generator Isolation EOP-1.1, SI Termination A. Main Steam Line Break EOP-0, to EOP-2, to EOP-1, to EOP-1.1 B. Main Feed Line Break EOP-0, to EOP-2, to EOP-1, to EOP-1.1 C. Main Steam Line Break EOP-0, to EOP-2, to EOP-1.1 D. Main Feed Line Break EOP-0, to EOP-1, to EOP-1.1

Page 90 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 090 Given the following: Unit 1 Service Water overboard is isolated T-104A, 'A' Waste Distillate Tank, is discharging to the Unit 2 Service Water overboard per OI 140B, Standard Radioactive Batch Liquid Release-Waste Distillate Tanks Prior to the discharge the RO recorded the following values for RE-223, Waste Distillate Tank Overboard Monitor on the discharge permit: Background reading 2.67 E-5 µCi/cc Source check reading 1.42 E-4 µCi/cc Alert setpoint reading 7.67 E-4 µCi/cc Alarm setpoint reading 6.18 E-3 µCi/cc One hour after commencing the discharge the RO noted the following conditions: RE-223, Waste Distillate Tank Overboard Monitor is reading 5.14 E-7 µCi/cc 2RE-229 SW Overboard Monitor Unit 2 is NOT in alarm What actions will the OS take? A. (1) Determine TLCO 3.3.1 Instrumentation MET. (2) The OS will direct the PAB AO to secure the discharge lineup and place the 'A' Waste Distillate Tank on recirculation. (3) Have Chemistry sample the 'A' Waste Distillate Tank to validate the current discharge permit is good once RE-223 is repaired. B. (1) Declare TLCO 3.3.1 Instrumentation NOT MET and enter TLCO 3.3.1.A and 3.3.1.B immediately. (2) The OS will direct the PAB AO to secure the discharge lineup and place the 'A' Waste Distillate Tank on recirculation. (3) Chemistry will resample the 'A' Waste Distillate Tank and issue a new discharge permit after RE-223 is repaired. C. (1) Determine TLCO 3.3.1 Instrumentation MET. (2) The OS will direct the PAB AO to bypass RE-223 and generate a work order to have RP to calibrate RE-223. (3) Have Chemistry commence grab samples of the Unit 2 SW Overboard every hour until the 'A' Waste Distillate Tank is discharged. D. (1) Declare TLCO 3.3.1 Instrumentation NOT MET and enter TLCO 3.3.1.A and 3.3.1.B immediately. (2) The OS will direct the PAB AO to bypass RE-223 and generate a work order to have RP calibrate RE-223. (3) The discharge of the 'A' Waste Distillate Tank can continue as long as 2RE-229 remains operable and Chemistry performs hourly grab samples from the 'A' Waste Distillate Tank.

Page 91 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 091 Which of the following describes the applicability and Technical Specification Basis for the High Pressurizer Water Level reactor trip? A. Modes 1 and 2; Provides a backup trip to PZR High Pressure reactor trip and ensures that water relief through the PZR safety valves will not occur B. Modes 1 and 2; Provides primary protection for loss of load events and ensures that on a PZR level channel failure, the PZR safety valves will not lift prior to the PZR High Pressure reactor trip. C. Mode 1 above P-7; Provides a backup trip to PZR High Pressure reactor trip and ensures that water relief through the PZR safety valves will not occur. D. Mode 1 above P-7; Provides primary protection for loss of load events and ensures that on a PZR level channel failure, the PZR safety valves will not lift prior to the PZR High Pressure reactor trip.

Page 92 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 092 Given the following: A severe accident has occurred on Unit 1 The operators are currently implementing the Emergency Operating Procedures The following conditions exist: The containment is adverse All Reactor Coolant Pumps are off Pressurizer level is off-scale low Narrow Range Reactor Vessel Level is 20 ft Wide Range RCS pressure is 400 psig Core exit thermocouples are reading 750°F Which of the following states the procedure transition that will be directed by the Operating Supervisor and the reason for the transition? A. Transition to CSP-C.1, Response to Inadequate Core Cooling because core damage is occurring B. Transition to CSP-C.1, Response to Inadequate Core Cooling because core uncovery is occurring C. Transition to CSP-C.2 Response to Degraded Core Cooling because core damage is occurring D. Transition to CSP-C.2 Response to Degraded Core Cooling because core uncovery is occurring

Page 93 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 093 Given the following Units 1 and 2 are at Rated Thermal Power A loaded Dry Cask is being removed from the Spent Fuel Pool per RP 17, NUHOMS Dry Cask Loading and Storage, Part 4, Remove DSC/TC from Spent Fuel Pool During the critical lift, the rigging catastrophically fails, causing the Cask to fall back into the Spent Fuel Pool and come to rest on spent fuel racks which causes bubbles to rise from the fuel in the racks The dropped cask caused damage to the Spent Fuel Pool liner The Spent Fuel Pool water level is slowly lowering What procedural flow path will the OS1 direct to mitigate this event? A. Transition to AOP-8F, Loss of Spent Fuel Pool Cooling. B. Remain in RP 17, NUHOMS Dry Cask Loading and Storage, Part 4, Remove DSC/TC from Spent Fuel Pool, no transitions are necessary. C. Transition to AOP-8C, Fuel Handling Accident in Primary Auxiliary Building, and when directed branch to AOP-8F, Loss of Spent Fuel Pool Cooling and perform in parallel. D. Transition to AOP-8G, Dry Fuel Storage Cask Drop Tipover, and when directed branch to AOP-8C, Fuel Handling Accident in Primary Auxiliary Building and perform in parallel.

Page 94 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 094 Given the following: A severe storm has passed through the area The following items were damaged and are reported out of service Electrical Feeder Mishicot -122 Electrical Feed East Krok-242 Siren Site P 002 Siren Site P 003 Siren Site P 013 Siren Site P 014 Which of the following is the Total Lost Coverage due to the storm?? (See provided reference) A. 24.1% B. 33.4% C. 34.5% D. 38.5%

Page 95 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 095 Given the following: Unit 2 is being refueled following a complete core offload. Any deviation from the specified core refueling approved sequence, while transporting fuel to or from the Spent Fuel Pool or the core, requires the concurrence of the ______ before any changes are made? A. Reactor Engineering Duty and Call Supervisor B. Core Loading Supervisor and the Shift Manager C. Assigned Reactor Engineer and the Shift Manager D. Assigned Reactor Engineer and the Core Load Supervisor

Page 96 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 096 Given the following: P-32B, Service Water Pump, is isolated with a Clearance Order for preventative maintenance The Clearance Order for P-32B has been released and work has begun Mechanical Maintenance has contacted the Work Control Center with a change in the scope of work for P-32B Maintenance Planning has generated a new Work Order for the additional work What action(s) will be needed to add the new Work Order to the existing Clearance Order for P-32B per OP-AA-101-1000, Fleet Clearance and Tagging? A. Only an SRO, with a peer check, is required to verify the current clearance isolations support the new work and approve the Clearance Order. B. An SRO or Clearance Owner, with a peer check, will verify the current Clearance isolations support the new work and approve the Clearance Order. C. A Clearance Owner and Lead Mechanic from the cognizant work group are required to approve the Work Order is supported by the current Clearance Order. D. An SRO, with a peer check, and a Clearance Owner from the cognizant work group will verify the Work Order is supported by the current Clearance isolations.

Page 97 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 097 Given the following: Unit 1 is in a refueling outage with a core offload in progress You are the Relief Crew SRO and have two Operators who need to hang a danger tag in containment on the 21' behind the LHRA refueling boundary What must be done prior to sending your Operators into the LHRA to hang the tag? A. Sign on specific Operations Outage RWP, establish radio communication with the Core Load Supervisor (CLS), and obtain authorization from the CLS prior to entering the area. Fuel may NOT be moved through the transfer tube. B. Sign on the fuel motion RWP. Entry is allowed with concurrence of the CLS. Fuel may be moved through the transfer tube. C. No entry into fuel motion LHRA's is allowed unless the fuel transfer tube gate valve is danger tagged shut. D. The Operations standing RWP allows for a short duration entry into areas posted due to fuel motion for such activities as hanging tags. Outage Manager permission is required as long as fuel is not actively being transferred between the SFP and Containment.

Page 98 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 098 Which of the following completes the statement? (1) The Technical Specification 3.4.16 Reactor Coolant System - Specific Activity, limit for dose equivalent I-131 in the Reactor Coolant System is _______. AND (2) During an emergency, in order to declare an ACTUAL LOSS of the Fuel Clad Barrier, the dose equivalent I-131 in the Reactor Coolant must be greater than _______ as identified in EPIP-1.2, Emergency Classification, Fission Product Barriers Table. A. (1) 0.5 µCi/gm (2) 300 µCi/gm B. (1) 0.5 µCi/gm (2) 1500 µCi/gm C. (1) 50 µCi/gm (2) 300 µCi/gm D. (1) 50 µCi/gm (2) 1500 µCi/gm

Page 99 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 099 Given the following: Unit 2 is experiencing an event which has resulted in an ALERT EAL being exceeded and recognized by the crew After five (5) minutes of actions being taken by the crew, the ALERT EAL is no longer met and conditions for an UNUSUAL EVENT now are present No emergency declaration has been made Which of the following identifies the actions required by the Emergency Director? A. Declare an ALERT, terminate the ALERT, declare an UNUSUAL EVENT B. Declare an ALERT, then de-escalate the Emergency Classification to an UNUSUAL EVENT C. Declare an UNUSUAL EVENT, and make a non-emergency update within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> report to document the ALERT D. Declare an UNUSUAL EVENT, and ensure the ALERT which was present is communicated to the NRC, via the Event Notification Worksheet

Page 100 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION SENIOR REACTOR OPERATOR QUESTION # 100 In accordance with EPIP 1.1, Course of Actions, which of the following identifies an action that may be delegated by Emergency Director (ED)? A. Approval of dose extensions B. Authorizing the use of potassium iodide C. Issuing Protective Action Recommendations D. Directing assembly, accountability and evacuation

Page 101 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION EXAMINATION KEY 001 D 002 D 003 C 004 D 005 D 006 C 007 D 008 A 009 D 010 C 011 B 012 C 013 B 014 C 015 A 016 C 017 B 018 B 019 D 020 A 021 D 022 B 023 B 024 A 025 B 026 B 027 D 028 B 029 C 030 B 031 C 032 D 033 C 034 A 035 B 036 C 037 C 038 D 039 B 040 B 041 B 042 D 043 A 044 C 045 D 046 B 047 A 048 B 049 D 050 D 051 B 052 D 053 C 054 D 055 C 056 B 057 D 058 B 059 C 060 D 061 B 062 A 063 B 064 D 065 A 066 A 067 C 068 C 069 B 070 B 071 D 072 C 073 A 074 C 075 A 076 C 077 B 078 D 079 B 080 C 081 D 082 B 083 A 084 D 085 B 086 C 087 D 088 A 089 B 090 B 091 C 092 D 093 C 094 B 095 D 096 D 097 A 098 A 099 B 100 D