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{{#Wiki_filter:ES-401                        Site-Specific SRO Written Examination                Form ES-401-8 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:
Date:                                            Facility/Unit:
Region:          I    II      Ill  IV            Reactor Type: WE CE        D    BWEGE    E Start Time:                                      Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours to complete the combined examination, and 3 hours if you are only taking the SRO portion.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicants Signature Results RO/SRO-Only/Total Examination Values                                  /      I        Points Applicants Scores                                                    I      I        Points Applicants Grade                                                    I        I        Percent ES-401, Page 31 of 33
 
ILC-11-1 NRC Exam 1 Given the following plant conditions:
        - The Plant is at 100% RTP.
        - The reactor trips due to a RCS low flow condition.
        - Generator lockout occurs immediately.
        - Approximately 5 seconds after the generator lockout a fault on 4KV Bus 4 causes voltage on 480V Bus E-2 to drop to 290 VAC.
Approximately 7 seconds after the generator lockout breaker 52/19, 4KV BUS 3-4 TIE BKR, trips open on overcurrent.
Which ONE (1) of the following identifies the current alignment of the Emergency buses?
A. 480V Bus E-1 is being powered via A EDG.
480V Bus E-2 is being powered via 4KV Bus 3.
B. 480V Bus E-1 is being powered via 4KV Bus 2.
480V Bus E-2 is being powered via 4KV Bus 3.
C. 480V Bus E-1 is being powered via A EDG.
480V Bus E-2 is being powered via B EDG.
D. 480V Bus E-1 is being powered via 4KV Bus 2.
480V Bus E-2 is being powered via B EDG.
1
 
ILC-11-1 NRC Exam
: 2. Given the following plant conditions:
        - The plant is in Mode 5.
        - RCS Temperature: 170°F and stable.
        - RCS Pressure: 350 psig and stable.
Subsequently a loss of MCC-6 occurs resulting in the following:
        - PT-501, PZR Pressure, fails low.
Which ONE (1) of the following actions are required lAW AOP-020, Loss of Residual Heat Removal (Shutdown Cooling)?
A. Close PCV-455C using its RTGB control switch.
B. Close RC-536, PORV Block Valve, using the RTGB control switch.
C. Place the associated LTOPP Arming Switch to the Normal position.
D. Take Manual Control of PC-444J and Reduce the Controller Output to Zero.
2
 
ILC-i1-1 NRC Exam
: 3. Given the following plant conditions:
        -  LOCA occurred inside containment.
        - The crew is currently implementing PATH-i.
        - Containment pressure peaked at 9.5 psig and is currently at 4.2 psig and slowly lowering.
        - Core Exit T/Cs indicate 510°F and rising.
        - RCS pressure is 1100 psig and lowering.
        - Safety injection flow to the core is 500 gpm and steady.
Which ONE (1) of the following completes the statement below?
Based on these plant conditions, the Reactor Coolant Pumps will A. be secured due to inadequate subcooling.
B. NOT be secured due to adequate subcooling.
C. be secured due to loss of component cooling flow.
D. NOT be secured due to lower than expected SI flow.
3
 
ILC-11-1 NRC Exam
: 4. Which ONE (1) of the following describes reflux cooling?
Steam produced in the core rises in the hot legs to the SIGs where it is condensed and returned to the vessel via the (1) legs and to enhance this method of cooling, (2)
A. (1) cold (2) SIG levels must be maintained.
B. (1) cold (2) maintain SIG pressure higher than RCS pressure.
C. (1) hot (2) SIG levels must be maintained.
D. (1)hot (2) maintain SIG pressure higher than RCS pressure.
4
 
ILC-11-1 NRC Exam
: 5. The plant is at 25% RTP with GP-005, Power Operation, power ascension in progress when the A RCP trips on overcurrent.
Which ONE (1) of the following identifies the effect on Main Feedwater to the S/Cs from steady-state to steady-state conditions?
Feedwater flow...
A. to S/C A rises. Feedwater flow to S/Cs B and C lowers.
B. to S/C A lowers. Feedwater flow to S/Gs B and C rises.
C. lowers to all S/Cs.
D. remains constant.
5
 
ILC-11-1 NRC Exam
: 6. The plant is at 10% RTP with GP-005, Power Operation, power ascension in progress when the following occurs:
          - Annunciator APP-001-D2, RCP #1 SEAL LEAKOFF HI FLOW, alarms.
          - The RO reports #1 seal leakoff is 5.8 gpm for RCP A, and #1 seal leakoff for RCP B and RCP C has lowered from 3.0 to 2.0 gpm.
Which ONE (1) of the following identifies the required operator actions and proper sequence lAW AOP-0i 8, Reactor Coolant Pump Abnormal Conditions?
A. Trip the reactor and then stop RCP A.
Go to PATH-i while continuing with AOP-01 8 and then shut the #1 seal leakoff isolation valve within 3 to 5 minutes.
B. Trip the reactor and then stop RCP A.
Go to PATH-i while continuing with AOP-0i8 and then shut the #1 seal leakoff isolation valve within I to 2 minutes.
C. Stop RCP A and then trip the reactor.
Go to PATH-i while continuing with AOP-Oi 8 and then shut the #1 seal leakoff isolation valve within 3 to 5 minutes.
D. Stop RCP A and then trip the reactor.
Go to PATH-i while continuing with AOP-0i 8 and then shut the #1 seal leakoff isolation valve within 1 to 2 minutes.
6
 
ILC-11-1 NRC Exam
: 7. Given the following plant conditions:
          - Plant is in Mode 3 at 547°F.
          - The Charging Line in Pipe Alley has ruptured and sprayed water on FCV-626,THERM BARRIER OUTLET.
          - An electrical short causes FCV-626 to travel to the closed position.
          - The Crew has secured ALL Charging Pumps lAW AOP-018, Reactor Coolant Pump Abnormal Conditions.
How much time is allowed to restore RCP seal cooling AND what constitutes seal cooling restoration lAW AOP-018?
A. 15 minutes to restore EITHER thermal barrier cooling OR seal injection.
B. 15 minutes to restore BOTH thermal barrier cooling AND seal injection.
C. 30 minutes to restore EITHER thermal barrier cooling OR seal injection.
D. 30 minutes to restore BOTH thermal barrier cooling AND seal injection.
7
 
ILC-11-1 NRC Exam
: 8. Given the following plant conditions:
        - The plant is at 100% RTP.
        - CV Spray Pump A operating during the performance of OST-352-1, Containment Spray Component Test Train A.
                                                  -
        - The following alarm is received:
                - APP-002-E1, CV SRY PMP COOL WTR LO FLOW Which ONE (1) of the following identifies the alarm setpoint and the action required lAW APP-002-E1?
A. 30 GPM. Stop CV Spray Pump A.
B. 30 GPM. Continued operation of CV Spray Pump A is allowed.
C. 7 GPM. Stop CV Spray Pump A.
D. 7 GPM. Continued operation of CV Spray Pump A is allowed.
8
 
ILC-11-1 NRC Exam
: 9. Which ONE (1) of the following plant conditions requires entry into FRP-S.1, Response To Nuclear Power Generation/ATWS?
A. Source Range startup rate of +0.1 dpm.
B. Intermediate Range startup rate of -0.1 dpm.
C. Power Range indicates 3% with an Intermediate Range startup rate of +0.2 dpm.
D. Power Range indicates 3% with an Intermediate Range startup rate of -0.2 dpm.
9
 
ILC-11-1 NRC Exam
: 10. Which ONE (1) of the following identifies the ESFAS signal that will provide protection for a main steam line break adjacent to a Main Steam Safety Valve and the basis?
High Steam Line A. Delta P; Provides protection for steam line breaks upstream of the MSIVs.
B. Delta P; Provides protection for steam line breaks downstream of the MSIVs.
C. Flow with Low Tave; Provides protection for steam line breaks downstream of the MSIVs.
D. Flow with Low Tave; Provides protection for steam line breaks upstream of the MSIV5.
10
 
ILC-11-1 NRC Exam
: 11. The plant is at 68% RTP when the BOP observes the following indications for all 3 SIGs from the FE/SF Trend Recorders and Feed Reg. Valve Controllers:
          - S/G level is LOWERING.
          - Steam Flow is STABLE.
          - Feed Flow is LOWERING.
          - Feed Reg Valve positions are all OPENING.
Which ONE (1) of the following identifies the cause of the event in progress?
A. Heater Drain Pump Trip.
B. Main Feedwater Pump Trip.
C. FCV-1446, Condensate Recirc, fails OPEN.
D. FCV-1444, Feedwater Pump A Recirc Valve, fails OPEN.
11
 
ILC-11-1 NRC Exam
: 12. Given the following plant conditions:
          - The plant is at 100% RTP when offsite power is lost.
          - The crew has implemented EPP-5, Natural Circulation Cooldown.
Three hours has elapsed since the loss of offsite power and the following indications are observed:
          - RCS Temperature is 288°F and lowering.
          - RCS Pressure is 345 psig and stable.
Which ONE (1) of the following identifies the indications that are directed to be used lAW EPP-5 to determine if a Steam Void is present in the Reactor Vessel?
A. RVLIS upper range, Large PZR level changes B. RVLIS upper range, Core Exit Thermocouple Temperatures C. subcooling, Large PZR level changes D. subcooling, Core Exit Thermocouple Temperatures 12
 
ILC-11-1 NRC Exam
: 13. The plant is at 100% RTP.
The following annunciators are received:
            -  APP-036-D3, BATT A/B LOW VOLT
            -  APP-036-D2, BATT CHARGER BIB-i TROUBLE
            -  DC Bus B voltage indicates 123 volts and lowering.
OAO reports that B Battery Charger has tripped.
Which ONE (1) of the following describes the status of the DC Bus and the Operator action that will be required lAW OP-601, DC Supply System?
The      (1)    Battery Charger    (2)  . The B Batteries will be placed on (3) on the    (4)
A. (1)  B (2) will auto-start to become the In-service Battery Charger.
(3) equalize (4) B Battery Charger B. (1)  B (2) must be manually placed in service.
(3) float setting (4) B Battery Charger.
C. (1)  81 (2) will auto-start to become the In-service Battery Charger.
(3) equalize (4) B-i Battery Charger D. (1)  Bi (2) must be manually placed in service.
(3) float setting (4) B-i Battery Charger 13
 
ILC-11-1 NRC Exam
: 14. Given the following plant conditions.
          -  The plant is at 100% RTP.
          -  APP-008-F7, SOUTH SW HDR LO PRESS, and APP-008-F8, NORTH SW HDR LOW PRESS, alarms are received.
          -  A Security Guard reports a large amount of water flowing to the storm drains from the area between the Aux. Building and Radwaste Building.
          -  lAO identifies rupture at SW piping elbow on east side of Auxiliary Building.
Which ONE (1) of the following identifies the Service Water Header that is ruptured and the components that must be VERIFIED STOPPED or taken out of service lAW AOP-022, Loss of Service Water?
The      (1)    Header has ruptured and the      (2)  must be removed from service.
A. (1) South (2) B EDG B. (1) North (2) B EDG C. (1) South (2) A EDG D. (1) North (2) A EDG 14
 
ILC-11-1 NRC Exam
: 15. Given the following plant conditions:
          - The plant is operating at 85% RTP.
          - APP-009-D7, GEN LO FREQ, was received 30 seconds ago.
          - AOP-026, GRID INSTABILITY, has been entered.
          - Grid frequency is at 58.3 Hz and slowly lowering following a load rejection.
The crew has determined that the load rejection was 110 MWe.
Which ONE (1) of the following action(s) will be taken lAW AOP-026?
A. Trip the Reactor and Go to PATH-I ONLY.
B. Trip the Reactor, Stop the RCPs and Go to PATH-I.
C. Transition to AOP-015, Secondary Load Rejection ONLY.
D. Transition to AOP-015, Secondary Load Rejection, while continuing with AOP-026.
15
 
ILC-11-1 NRC Exam
: 16. Given the following plant conditions:
          - The crew is performing the actions in EPP-20, LOCA Outside Containment.
          - Auxiliary Building radiation levels are lowering.
          - Safety Injection flow is 80 GPM and lowering.
          - PZR level is off scale LOW.
          - RCS pressure is 1450 psig and rising.
Which ONE (1) of the following identifies the leak status lAW EPP-20 and the basis for determining that status?
The leak is A. isolated because RCS pressure is rising.
B. NOT isolated because SI pump flow still exists.
C. NOT isolated because PZR level is not on scale.
D. isolated because Auxiliary Building radiation levels are lowering.
16
 
ILC-1i-1 NRC Exam
: 17. Given the following plant conditions:
          -  A Reactor Trip and Safety Injection have occurred.
          -  The crew has performed the actions of PATH-i.
          -  AFW flow cannot be established.
          -  All SIG NR levels are off-scale low.
          -  The crew has entered FRP-H.i, Response to Loss of Secondary Heat Sink.
          -  RCS Pressure is 175 psig and stable.
          -  Intact S/G pressures are 300 psig and trending down.
Which ONE (1) of the following completes the statement below?
A    (1)    Break LOCA is in progress AND a Secondary Heat Sink  (2)
A. (1) Large (2) is required.
B. (1) Small (2) is required.
C. (1) Large (2) is NOT required.
D. (1) Small (2) is NOT required.
17
 
ILC-11-1 NRC Exam
: 18. Given the following plant conditions:
            -  A SBLOCA has occurred. Containment Pressure is 2.3 psig.
            -  CCW Pumps are not available.
            -  The operating crew has transitioned to EPP-15, Loss of Emergency Coolant Recirculation.
Which ONE (1) of the following correctly describes the reason for depressurizing the RCS and the terminating setpoint?
To      (1)    depressurize the RCS until PZR level is > 71%    (2)  RCS Subcooling is between 35°F and 45°F.
A. (1) minimize RCS leakage (2)OR B. (1) minimize RCS leakage (2) AND C. (1) inject the SI accumulators (2)OR D. (1) inject the SI accumulators (2) AND 18
 
ILC-11-1 NRC Exam
: 19. Given the following plant conditions:
          -  The plant is operating at 50% RTP EOL while supporting MFP A maintenance.
          -  Rod Control is in MANUAL.
          -  The RO withdraws Bank D two steps for Tavg control.
          -  When the Rod Control switch is released, Bank D rods continue to move an additional three steps until stopped by performing the immediate actions of AOP-001, Malfunction of Reactor Control System.
Which ONE (1) of the following describes the effect on Reactor Power from Steady-State to Steady-State?
(Assume no additional operator actions have occurred.)
A. Remains stable.
B. Rise and stabilize at a value greater than 50% RTP.
C. Rise initially, then trends back to less than 50% RTP.
D. Rise initially, then trends back to approximately 50% RTP.
                  -    t)cAtA\
19
 
ILC-11-1 NRC Exam
: 20. Given the following plant conditions:
          - The plant is in Mode 6 with a core offload in progress.
          - The CV Manipulator has just removed a fuel assembly from core location H-8 and is in transit to the CV upender.
          - The CV manipulator operator accidently places the gripper switch to the DISENGAGE position before the fuel assembly is lowered into the CV upender.
          -  The fuel assembly releases from the gripper while in the full up position and lands on the CV upender and damages several fuel rods.
Which ONE (1) of the following describes the interlock(s) that failed to prevent this action?
A. ONLY the Gripper Lock Interlock.
B. ONLY the Gripper-Weight Indicator Interlock.
C. BOTH the Gripper-Weight Indicator AND the Hoist/Gripper Interlocks.
D. BOTH the Gripper-Weight Indicator AND the Gripper Lock Interlocks.
20
 
ILC-ii-1 NRC Exam
: 21. Given the following plant conditions:
          - The plant is at 3% RTP with Tave at 549° F.
          - A 50 gpm tube leak has been identified in A SIG.
Which ONE (1) of the following describes the appropriate actions that should be taken lAW AOP-035?
AOP-035, SIG Tube Leak GP-006, Normal Plant Shutdown From Power Operation to Hot Shutdown Supplement G, Steam Generator Isolation A. Shutdown the plant lAW GP-006 and then Isolate A S/G lAW AOP-035.
B. Isolate A S/G lAW AOP-035 and then commence a plant shutdown lAW GP-006.
C. Trip the reactor and go to PATH-2. Isolate A S/G lAW Supplement G concurrent with PATH-2.
D. Trip the reactor and go to PATH-i. Transition to PATH-2 and isolate A S/G lAW Supplement G concurrent with PATH-2.
21
 
ILC-11-1 NRC Exam
: 22. Given the following plant conditions:
          - The plant is at 8% RTP with B T MFP under clearance for motor bearing repairs.
          - The Operating crew has entered AOP-0i2, Partial Loss of Condenser Vacuum or Circulating Water Pump Trip due to rising Condenser Back Pressure.
          - The Main Turbine has been manually tripped lAW AOP-0i2.
          - A MFP is subsequently secured due to an identified ground.
Which ONE (1) of the following actions is required by AOP-007, Turbine Trip Below P-8?
A. Trip the Reactor and go to PATH-I.
B. Trip the Reactor and go to PATH-i while continuing with AOP-007.
C. Position the control rods to maintain Reactor power between 7% and 10%.
D. Position the control rods to reduce Reactor power to less than or equal to 3%.
22
 
ILC-11-1 NRC Exam
: 23. Given the following plant conditions:
          - A Monitor Tank is currently at 40% and being released lAW OP-705, Waste Liquid Release and Recircu lation.
          - The Inside AO reports a nonisolable leak on A Monitor Tank.
Which ONE (1) of the following identifies the correct actions lAW AOP-008, Accidental Release of Liquid Waste?
Stop the release and transfer contents of the A Monitor Tank to  (1)  to minimize leakage to (2)
A. (1) Monitor Tank B (2) storm drains B. (1) CVCS Holdup Tank (2) storm drains C. (1) Monitor Tank B (2) Aux Building Sump D. (1) CVCS Holdup Tank (2) Aux Building Sump 23
 
ILC-11-l NRC Exam
: 24. Given the following plant conditions:
          - PATH-i has been entered.
          - SI or RHR flow cannot be established.
Time          CETC Temp            RVLIS Full Range 1000            675°F                    51%
1005            695°F                    39%
1010            705°F                    37%
1015            750°F                    30%
1030          1000°F                    29%
1045          1150°F                    28%
1100          1205°F                    25%
Based on the above indications, what is the earliest time at which entry conditions for FRP-C.1, Response to Inadequate Core Cooling, would be present?
A. 1005 B. 1010 C. 1015 D. 1100 24
 
ILC-11-1 NRC Exam
: 25. The crew is implementing EPP-8, Post-LOCA Cooldown and Depressurization, following a Small Break LOCA
            - Containment pressure peaked at 3.8 psig.
            - Steps have been taken to reduce SI flow by stopping C SI Pump.
            - A SI Pump remains running.
After C SI pump is stopped the following plant conditions are observed:
            - RCS subcooling is 32°F and lowering.
            - PZR level is 22% and lowering.
Which ONE of the following; (1) identifies the actions that will be taken AND (2) why will this action be taken?
A. (1) Start additional Charging Pump(s).
(2) Due to adequate pressurizer level.
B. (1) Start both SI pumps.
(2) Due to low pressurizer level.
C. (1) Start additional Charging Pump(s).
(2) Due to low subcooling.
D. (1) Start both SI pumps.
(2) Due to low subcooling.
25
 
ILC-11-1 NRC Exam
: 26. Given the following plant conditions:
            - A LOCA with a loss of off-site power has occurred.
            - The supply breaker to MCC-6 tripped open prior to CV Spray Actuation.
            - CV Pressure is 15 psig and both Containment Spray Pumps are operating.
Which ONE (1) of the following completes the statements below?
(1) is the status of the Containment Spray System AND      (2)  is the current status of the Component Cooling Water Pumps.
(Assume no local operator actions have been taken.)
A. (1) The discharge path is aligned from CV Spray Pump A ONLY.
(2) A CCW Pump is running.
B. (1) CV Spray Pumps A and B are providing spray flow.
(2) A CCW Pump is running.
C. (1) The discharge path is aligned from CV Spray Pump A ONLY.
(2) B and C CCW Pumps are secured.
D. (1) CV Spray Pumps A and B are providing spray flow.
(2) B and C CCW Pumps are secured.
26
 
ILC-11-1 NRC Exam
: 27. Which ONE (1) of the following identifies the operational concern associated with Containment Flooding?
Containment Flooding could lead to A. Submersion of the Reactor Coolant Drain Tank resulting in damage to the Gas Analyzer.
B. Critical system transmitter failures needed to ensure an orderly safe plant shutdown.
C. Submersion of CVC-200A, B, C, Letdown Orifice Isolations resulting in a loss of normal letdown capability.
D. Water potentially leaking through Containment Vessel Electrical Penetrations resulting in electrical shorts and/or grounds on components that are needed to ensure an orderly safe plant shutdown.
27
 
ILC-11-1 NRC Exam
: 28. Given the following plant conditions:
          - The plant is at 50% RTP.
          - FT-434 RCS LOOP Ci FLOW TRANSMITTER low pressure sensing line develops a leak to the CV atmosphere.
Which ONE (1) of the following describes the expected plant response to this event?
A. All Loop C flow channels read low.
B. All Loop C flow channels read high.
C. Flow indication will rise on ONLY the affected Loop C flow channel.
D. Flow indication will lower on ONLY the affected Loop C flow channel.
28
 
ILC-11-1 NRC Exam
: 29. Given the following plant conditions:
          - The plant is in Mode 5.
          - The RCS is solid with pressure being automatically maintained.
          - A clearance error results in PZR Backup Group A Heaters becoming energized.
Which ONE (1) of the following describes the FIRST (INITIAL) response to the rising Pressurizer temperature and pressure?
(Assume NO operator actions.)
A. Annunciator APP-OO1-D6, LP LTDN LN HI PRESS, actuates.
B. Annunciator APP-OO1-E6, LP LTDN RELIEF HI TEMP, actuates.
C. Letdown flow rises as HCV-142, RHR TO LETDOWN & PURIFICATION FLOW CONTROL, opens.
D. Letdown flow rises as PCV-145, LOW PRESSURE LETDOWN PRESSURE CONTROL VALVE, opens.
29
 
ILC-11-1 NRC Exam
: 30. Given the following plant conditions:
            -  The plant is operating at 100% RTP.
            -  C Charging Pump is currently running in Manual at minimum speed.
            -  A Charging Pump is running in MANUAL at 35% demand during the performance of OP-301-1, Section 8.4.7, Charging Pump Break-In After Maintenance.
            -  CVC-283C, Charging Pump A Discharge Relief, has lifted and has not reseated.
Which ONE (1) of the following identifies the impact on Seal Injection flow(s) AND how would this malfunction be addressed by AOP-01 8, Reactor Coolant Pump Abnormal Conditions?
Seal Injection flows will lower to    (1)    and AOP-018 directs the operators to    (2)
A. (1) ZERO flow (2) Isolate letdown, secure all Charging Pumps, manually isolate A Charging pump.
B. (1) MINIMUM flow      (- 6 gpm)
(2) Isolate letdown, secure all Charging Pumps, manually isolate A Charging pump.
C. (1) ZERO flow (2) Stop A Charging Pump and adjust the speed of C Charging Pump to restore normal seal injection flows.
D. (1) MINIMUM flow      (- 6 gpm)
(2) Stop A Charging Pump and adjust the speed of C Charging Pump to restore normal seal injection flows.
30
 
ILC-11-1 NRC Exam
: 31. Given the following plant conditions:
          - The plant is in Mode 6.
          -  RHR Train A is in service.
          -  FCV-605, RHR HX BYPASS, is set to maintain 3400 GPM.
          -  HCV-758, RHR HX OUTLET FLOW TO COLD LEGS, demand position set at 30%.
          - The Instrument Air supply line to RHR Heat Exchanger Flow Control Valve HCV-758 becomes severed and is completely detached.
          - No other air operated valves are impacted by the failure.
Which ONE (1) of the following identifies the changes in TR-604, PEN 2 RHR HX OUTLET TEMP, from the initial steady state conditions AND the RCS temperature at which refueling operations may continue lAW GP-01 0, Refueling?
RHR HX OUTLET TEMP                          RCS Temp for Refueling A.              Higher                                        135°F B.              Higher                                        150°F C.              Lower                                        135°F D.              Lower                                        150°F 31
 
ILC-11-1 NRC Exam
: 32. Given the following plant conditions:
          - Plant is shutdown for refueling.
          - GP-009-1, Filling the Refueling Cavity with Fuel in the Reactor Vessel, is in progress.
          - Safety Injection Pumps A and C are running.
          - SI-866A, LOOP 3 HOT LEG, is full open and Sl-866B, LOOP 2 HOT LEG, is being opened via its Control Power Switch to increase cavity fill rate.
          - Safety Injection Pump discharge pressure is at 530 psig and lowering.
Which ONE (1) of the following identifies the required actions to be taken lAW GP-009-1 to control the Safety Injection pump discharge pressure?
A. Close Sl-856A OR Sl-856B, SI Pump Recirc., valve.
B. Place Sl-866B Control Power Switch to NORMAL.
C. Place SI-866B Control Power Switch to DEFEAT.
D. Place Sl-866B Control Switch to CLOSE.
32
 
ILC-11-1 NRC Exam
: 33. Given the following plant conditions:
          -  LOCA recovery is in progress and RWST Level has lowered below 27%.
          -  The crew has transitioned to EPP-9, Transfer to Cold Leg Recirculation.
          -  While aligning the CV Sump To RHR valves, Sl-860A, CV Sump to RHR, fails to open and remains in the closed position.
Which ONE (1) of the following describes the impact on the ability to provide cold leg recirculation?
A. Both RHR pumps are available with full flow capability. Remain in EPP-9, Transfer to Cold Leg Recirculation.
B. ONLY B RHR pump is available for cold leg recirculation. Remain in EPP-9, Transfer to Cold Leg Recirculation.
C. ONLY B RHR pump is available for cold leg recirculation. Transition to EPP-15, Loss of Emergency Coolant Recirculation.
D. Both RHR pumps are available with reduced flow capability. Transition to EPP-15, Loss of Emergency Coolant Recirculation.
33
 
ILC-11-1 NRC Exam
: 34. The plant is at 100% RTP.
The following indications are reported by the RO:
          -  Tl-471, PRT Temperature is trending up over a period of 4 hours and is now at 148°F.
          -  P1-472, PRT Pressure is trending up and is now at 4 psig.
          -  PZR PRV RC-551A, B and C Acoustic Monitor Lights are extinguished.
Which ONE (1) of the following valve leakage is causing the given conditions?
A. PCV-456, PZR PORV, is leaking by its seat.
B. RC-551A, Pressurizer Safety Valve, is leaking by its seat.
C. CVC-382, RCP Seal Return Line Relief, is leaking by its seat.
D. CC-722A, RCP A Thermal Barrier Outlet Relief, is leaking by its seat.
34
 
ILC-11-1 NRC Exam
: 35. Given the following plant conditions:
          - Plant is at 100% RTP.
          - Grid disturbance results in a load rejection.
          - PCV-456 momentarily lifts due to the load rejection but does not fully reseat.
          - The operating crew has closed RC-535 to isolate PCV-456 leakage.
          - PRT pressure has been restored lAW APP-003-C3.
          - APP-003-B3, PRT HI TEMP, is illuminated.
          - PRT Temperature is currently 155°F.
Which ONE of the following completes the statements below?
The PRT rupture disc would have actuated if pressure reached      (1)  in the PRT.
lAW APP-003-B3, PRT HI TEMP, the PRT temperature will be lowered by (2)
A. (1) 100 psia (2) alternately adding primary water to the PRT and draining the PRT.
B. (1)l00psia (2) simultaneously adding primary water while draining the PRT.
C. (1) 100 psig (2) alternately adding primary water to the PRT and draining the PRT.
D. (1) 100 psig (2) simultaneously adding primary water while draining the PRT.
35
 
ILC-11-1 NRC Exam
: 36. Given the following plant conditions:
          - MODE I at 100% RTP.
          - B CCW pump is in service.
          - The normal supply breaker to 480V Bus E-1 Trips Open.
Which ONE (1) of the following identifies the status of the CCW pumps TWO (2) minutes after the event?
A. All CCW Pumps started on Low Pressure B. ONLY A CCW Pump started on Low Pressure B and C CCW Pumps started on Blackout Sequencer C. ONLY C CCW Pump started on Low Pressure B CCW Pump started on Blackout Sequencer D. A and C CCW Pumps started on Low Pressure B CCW Pump started on Blackout Sequencer 36
 
ILC-11-1 NRC Exam
: 37. A pressurizer code safety valve has indications of leakage.
The following indications exist:
          -  Pressurizer pressure is 2225 psig and stable.
          -  Safety Valve tailpipe temperature indicates 231°F and rising.
          -  PRT pressure is 6 psig and rising 1 psi every 10 minutes Which ONE (1) of the following completes the statement below?
The temperature downstream of the safety valves corresponds to A. the PRT saturation pressure because of the loss of enthalpy of a throttling process.
B. the PRT saturation pressure because of the constant enthalpy of a throttling process.
C. the saturation pressure of the presssurizer steam space because of the loss of enthalpy of a throttling process.
D. the saturation pressure of the presssurizer steam space because of the constant enthalpy of a throttling process.
37
 
ILC-11-1 NRC Exam
: 38. The plant is at 100% RTP and the following occurs:
            - The PZR pressure master controller (PC-444J) is failing HIGH.
            - The PZR spray valves are fully OPEN.
            - The PZR PORVs are CLOSED.
Which ONE (1) of the following identifies the value of the controller output (PC-444J) for this condition?
A. 75%
B. 70%
C. 65%
D. 60%
38
 
ILC-11-1 NRC Exam
: 39. The plant is at 100% RTP when A Condensate Pump trips due to electrical fault.
Which ONE (1) of the following completes the statement below?
The FIRST reactor trip signal will be generated as soon as bistable lights for (Assume no operator action.)
A. SC NO. 2 LO-LO Level LC484A1 AND SG NO. 2 LO-LO Level LC485A1 Illuminate.
B. SC NO. 2 LO-LO Level LC484A1 OR SC NO. 2 LO-LO Level LC485A1 Illuminate.
C. SG NO. 2 LO Level LC484B1 AND SC NO. 2 LO Level LC485B1 Illuminate.
D. SC NO. 2 LO Level LC484B1 OR SG NO. 2 LO Level LC485B1 Illuminate.
39
 
ILC-11-1 NRC Exam
: 40. Containment Spray Actuation requires  (1)  channels in (2) sets (or trains) of logic.
1 A. 2of3          lof2 B. 2of3          2of2 C. 2of4          lof2 D. 2of4          2of2 40
 
ILC-11-1 NRC Exam
: 41. Given the following Containment temperature indications:
Time            TI-950B            ERFIS Point CVT0001 1100            118.0°F                    118.3°F 1200            118.5°F                    118.7°F 1300            119.0°F                    119.2°F 1400            120.5°F                    119.8°F 1500            121.0°F                    120.2°F 1600            121.5°F                    120.6°F (RTGB) Tl-950B Containment Average Temperature
                      -
(ERFIS) CVT0001 Containment Average Air Temperature
                        -
Which ONE (1) of the following identifies when ITS LCO 3.6.5, Containment Air Temperature, must be entered lAW PLP-118, Hot Weather Operations?
A. 1200 B. 1300 C. 1400 D. 1500 41
 
ILC-11-1 NRC Exam
: 42. Given the following plant conditions:
            -  Plant is at 100% RTP.
            -  Breaker 52/17, START-UP TRANSFORMER TO 4KV BUS 3, trips.
            - A Large Break LOCA occurs 20 seconds later.
Which ONE (1) of the following identifies the configuration of the power supplies to CV Spray Pumps A and B?
CV Spray Pump A powered from        (1)  and CV Spray Pump B powered from      (2)
A. (1)SUT (2) B EDG B. (1)SUT (2) SUT C (1)AEDG (2) B EDG D. (1) A EDG (2) SUT 42
 
ILC-11-1 NRC Exam
: 43. Given the following plant conditions:
        -  The plant is at 100% RTP.
        -  The OAO reports a steam leak near the Main Steam Isolation Valves.
        -  The following indications are noted in the Control Room:
            -  Power Range Nuclear Instruments are rising.
            -  Tavg is lowering.
            -  Steam flow and feed flow have risen.
            -  Power Limit Warning alarm on ERFIS has been received.
            -  Reactor power is 100.3% and slowly rising.
Which ONE(1) of the following identifies both:
(1) the time in core life that will result in the largest reactivity excursion AND (2) the required operator actions to clear the Power Limit Warning alarm?
A. (1)BOL (2) reduce power by inserting control rods lAW OP-i 06, Normal Plant Operations.
B. (1)BOL (2) reduce power by using the Valve Position Limiter lAW OMM-00i-2, Shift Routines and Operating Practices.
C. (1)EOL (2) reduce power by inserting control rods lAW OP-106, Normal Plant Operations.
D. (1)EOL (2) reduce power by using the Valve Position Limiter lAW OMM-001-2, Shift Routines and Operating Practices.
43
 
ILC-11-1 NRC Exam
: 44. Given the following plant conditions:
          - A Steam Generator Tube Rupture (SGTR) is in progress.
          -  The crew is in PATH-2 and are commencing the RCS cooldown to target temperature.
          - The procedure has directed to Dump Steam to the condenser from intact S/Gs at the maximum rate.
Which ONE (1) of the following describes the term Maximum Rate as specified in the NOTE in PATH-2?
As fast as possible A. while not exceeding the High Steam Line AP limit.
B. while not exceeding Temp Limit A of the INTEGRITY Critical Safety Function Status Tree.
C. while keeping steam flow less than the High Steam Flow Main Steamline Isolation setpoint.
D. while keeping steam pressure above the Low Steamline Pressure Safety Injection setpoi nt.
44
 
ILC-11-1 NRC Exam
: 45. Given the following plant conditions:
          - The plant is at 60% RTP.
Which ONE (1) of the following describes the expected SIG Narrow Range Levels and the basis for that level?
The S/Gs will indicate      (1)    and the basis for this level is to  (2)
A. (1)39%
(2) maintain sufficient level to prevent a reactor trip from a 50% load rejection and is low enough to minimize moisture carryover.
B. (1)39%
(2) maintain the mass in the SIG great enough to stay above the reactor trip setpoints and minimizes the consequences of a steam break accident.
C. (1)52%
(2) maintain sufficient level to prevent a reactor trip from a 50% load rejection and is low enough to minimize moisture carryover.
D. (1)52%
(2) maintain the mass in the S/G great enough to stay above the reactor trip setpoints and minimizes the consequences of a steam break accident.
45
 
ILC-11-1 NRC Exam
: 46. B MFP is OOS for Maintenance and the following occurs:
          -  The Reactor was manually Tripped while operating at  20% RTP due to a trip of A MFP
          -  PZR Level is 20% and slowly lowering.
Tave is 545°F and lowering.
          -  RCS Pressure is 2050 psig and lowering.
          -  Steam Generator Blowdown is Isolated.
          -  S/G levels are as follows:
                  -  A SIG Narrow Range level is 40% and slowly  rising.
                  -  B S/G Narrow Range level is 41% and slowly  rising.
                  - C S/G Narrow Range level is 45% and slowly    rising.
Which ONE (1) of the following provides the action(s) that are required to be taken next lAW EPP-4, Reactor Trip Response?
A. Initiate Safety Injection.
B. Close MSIVs & MSIV Bypasses.
C. Borate to Cold Shutdown Boron.
D. Reduce Auxiliary Feedwater Flow.
46
 
ILC.-11--1 NRC Exam
: 47. Which ONE (1) of the following describes the 4160 Volt power supplies to the A and B RCPs2 RCP A        RCP B A.        Busi          Bus2 B.        Bus2          Bus4 C.        Busi          Bus4 D.        Bus2          Busi 47
 
ILC-11-1 NRC Exam
: 48. Given the following plant conditions:
          -  The plant is at 100% RTP.
          -  APP-036-D1, BATT CHARGER A/A-I TROUBLE, annunciated.
          -  OAO reports the following indications from Battery Charger A-I:
                  - +40 Volts on the Ground Detection Voltmeter.
                  - 140 Volts DC on Charger Voltage.
What are the adverse impacts of the reported indications and the actions required to be taken lAW APP-036-D1?
A. Normally non-energized portions of switchgear may be energized.
Isolate A Batteries by Aligning Battery Charger A to carry the bus load.
B. Normally non-energized portions of switchgear may be energized.
Swap Battery Chargers to place Battery Charger A In-service.
C. Over-voltage condition could damage A Batteries.
Isolate A Batteries by Aligning Battery Charger A to carry the bus load.
D. Over-voltage condition could damage A Batteries.
Swap Battery Chargers to place Battery Charger A In-service.
48
 
ILC-11-1 NRC Exam
: 49. Given the following plant conditions:
          - The plant is in Mode 3.
          - A fire has occurred in DC Distribution Panel B.
          - The panel has been de-energized.
Which ONE (1) of the following identifies the effect on the Electrical Distribution System?
Control Power lost to 4160 V Busses....
A. 1 & 2 and cannot be restored.
B. I & 2. Control Power can be restored using a safety switch in the 4160 V Switchgear Room.
C. 3 & 4 and cannot be restored.
D. 3 & 4. Control Power can be restored using a safety switch in the 4160 V Switchgear Room.
49
 
ILC-11-1 NRC Exam
: 50. Given the following plant conditions:
            - Plant is at 100% RTP.
            - An Electrician accidently opens breaker 52/1 8B, Normal Supply Breaker for E-1.
          -  A EDG starts on UV and energizes Emergency Bus E-1.
Which ONE (1) of the following identifies the effect of stopping A EDG from the RTGB while it is loaded on the isolated Emergency Bus E-1?
After taking the A EDG Control switch on the RTGB to STOP the A EDG will A. trip and must be manually reset prior to placing back in service.
B. maintain its current speed and voltage due to Shutdown Control Logic having a run priority.
C. attempt to shutdown but will restart due to the Shutdown Control Logic having a run priority.
D. maintain its current speed and voltage due to the App. R Isolation Switches being in the ISOLATE position.
50
 
ILC-11-1 NRC Exam
: 51. Which ONE(1) of the following describes the basis for initiating a Containment Ventilation Isolation signal during the performance of FRP-S.1, Response to Nuclear Power Generation I ATWS?
To isolate A. non-essential containment ventilation penetrations to prevent potential release of radioactive materials from containment.
B. R-11 and R-12, CV Air and Plant Stack Monitors, to prevent potential release of radioactive materials from containment.
C. non-essential containment ventilation penetrations due to delayed response time of R-11 and R-12 during an ATWS.
D. R-11 and R-12, CV Air and Plant Stack Monitors, due to delayed response time of R-11 and R-12 during an ATWS.
51
 
ILC-11-1 NRC Exam
: 52. SW-739, CCW HEAT EXCHANGER A RETURN, and SW-740, CCW HEAT EXCHANGER B RETURN, are throttled in the closed direction.
Which ONE(1) of the following completes the statement below?
This will cause Service Water Header Pressure to  (1)  and CCW Heat Exchanger OutletTemperatureto (2)
A. (1) lower (2) lower B. (1) lower (2) rise C. (1) rise (2) lower D. (1) rise (2) rise 52
 
ILC-11-1 NRC Exam
: 53. Which ONE(1) of the following identifies the fail position of TCV-144, NON-REG HX OUTLET TEMP CONTROL, valve on a loss of Instrument Air AND the effect this will have on reactivity?
TCV-144 will fail  (1) AND this will insert    (2)    reactivity.
A. (1) OPEN (2) Positive B. (1) OPEN (2) Negative C. (1) CLOSED (2) Positive D. (1) CLOSED (2) Negative 53
 
ILC-11-1 NRC Exam
: 54. Given the following plant conditions:
          - The plant is at 100% RTP.
          - APP-002-B7, CV NAR RANGE HI/LO PRESS illuminates.
          - CV Pressure indicates -0.4 psig, lowering.
Which ONE (1) of the following describes the action necessary to clear the alarm lAW OP-921, Containment Air Handling?
Open the Containment A. Pressure Relief Valves V12-l0 and V12-11 ONLY.
B. Pressure Relief Valves Vi 2-10 and V12-11 AND lower Service Water flow to the Containment HVH units.
C. Vacuum Relief Valves VI 2-12 and Vi 2-13 ONLY.
D. Vacuum Relief Valves Vi 2-12 and VI 2-13 AND lower Service Water flow to the Containment HVH units.
54
 
ILC-11-1 NRC Exam
: 55. Given the following plant conditions:
          - The RCS is at 275° F.
          - All RCPs are running.
          - CVC-381, RCP Seal Return Isolation, has been declared inoperable due to improperly set torque switches.
Which ONE (1) of the following statements is correct lAW the RNP ITS?
A. Close CVC-381 ONLY.
B. Close and deactivate CVC-381.
C. CVC-381 operability is NOT required for the given plant conditions.
D. Close CVC-380, Seal Water Return Filter Inlet, AND station a Dedicated Operator lAW OP-923, Containment Integrity.
55
 
ILC-11-1 NRC Exam
: 56. Plant is at 100% RTP.
Which ONE (1) of the following describes an INITIAL effect of one control rod dropping fully into the core?
This will cause the Charging Pump Speed to initially  (1)  due to the Pressurizer Reference Level      (2)
A. (1) lower (2) lowering B. (1) rise (2) lowering C. (1) lower (2) rising D. (1) rise (2) rising 56
 
ILC-11-1 NRC Exam
: 57. Given the following plant conditions:
          - The plant is at 100% RTP.
          - A loss of Inverter A occurs.
Which ONE (1) of the following identifies ALL the excore Nuclear Instrument channels that have lost power?
A. N-41 and N-51 B. N-43 and N-52 C. N-32, N-36 and N-42 D. N-31, N-35 and N-41 57
 
ILC-11-1 NRC Exam
: 58. The plant is at 50% RTP when the steam pressure input into the A SIG Level Control System fails high slowly.
Which ONE (1) of the following actions will occur?
Initially, feedwater flow to the A SIG will A. lower due to lower indicated steam flow.
The level error signal will NOT result in a rise in feedwater flow.
B. lower due to lower indicated steam flow.
Eventually, the level error signal will result in a rise in feedwater flow.
C. rise due to higher indicated steam flow.
The level error signal will NOT result in a reduction of feedwater flow.
D. rise due to higher indicated steam flow.
Eventually, the level error signal will result in a reduction of feedwater flow.
58
 
ILC-11-1 NRC Exam
: 59. Which ONE (1) of the following identifies the major source of hydrogen following a design basis LOCA with Inadequate Core Cooling AND is listed in the UFSAR criteria for ECCS performance following a LOCA?
A. Zirc-water reaction.
B. Radiolysis of RCS water.
C. Radiolysis of containment sump water.
D. Degradation of non-metallic insulation material.
59
 
ILC-11-1 NRC Exam
: 60. Given the following plant conditions:
          -  Plant is currently in Mode 6 during a scheduled refueling outage.
          -  Core re-load is in progress.
          -  The alarming radiation monitor on the refueling bridge loses power.
Which ONE (1) of the following identifies the impact to refueling operations and the proper actions of the refueling crew?
A. Fuel movement may continue as long as R-2, CV AREA, remains operable.
Replace the radiation monitor with an operable monitor with an alarm setpoint of 15 mr/hr.
B. Fuel movement may continue as long as R-2, CV AREA, remains operable.
Replace the radiation monitor with an operable monitor with an alarm setpoint of 25 mr/hr.
C. Fuel movement must be suspended until the radiation monitor is replaced.
Replace the radiation monitor with an operable monitor with an alarm setpoint of 15 mr/hr.
D. Fuel movement must be suspended until the radiation monitor is replaced.
Replace the radiation monitor with an operable monitor with an alarm setpoint of 25 mr/hr.
60
 
ILC-11-1 NRC Exam
: 61. Which ONE (1) of the following action(s) is necessary to utilize the steam dumps to cooldown the plant lAW GP-007, Plant Cooldown from Hot Shutdown to Cold Shutdown?
A. Momentarily place the Steam Dump Mode Switch to RESET with Tave less than 543° F.
B. Momentarily place the Steam Dump Mode Switch to RESET with Tave less than 547°F.
C. Bypass the Low Tavg interlock by momentarily selecting BYPASS TAVG INTERLOCK on the Steam Dump Control switch with Tavg less than 543° F.
D. Bypass the Low Tavg interlock by momentarily selecting BYPASS TAVG INTERLOCK on the Steam Dump Control switch with Tavg less than 547° F.
61
 
ILC-1 1-1 NRC Exam
: 62. Given the following plant conditions:
          - Plant is at 100% RTP.
          - Waste Gas Release of A Waste Gas Decay Tank is in progress.
          - APP-010-B7, HVE-2A12B AIR FLOW LOST/OVLD, is received.
          - HVE-2A has tripped.
Which ONE (1) of the following describes the actions required by the operator AND the potential plant effect of a loss of the Reactor Auxiliary Building Exhaust Fan?
The operator will        (1)      AND the possible effect of a loss of Reactor Auxiliary Building Exhaust Fans is I has        (2)
A. (1) have to manually start HVE-2B (2) an unmonitored release from the Reactor Auxiliary Building.
B. (1) verify that HVE-2B starts automatically (2) an unmonitored release from the Reactor Auxiliary Building.
C. (1) have to manually start HVE-2B (2) no impact since HVE-5A or HVE-5B will automatically start.
D. (1) verify that the HVE-2B starts automatically (2) no impact since HVE-5A or HVE-5B will automatically start.
62
 
ILC.-11-1 NRC Exam
: 63. Given the following plant conditions:
          -  Plant is stable at 60% RTP.
          -  Charging pumps A & C are in service.
          -  Letdown orifice valves CVC-200A and CVC-200B are open.
          -  A valid alarm has been received on R-9, LETDOWN LINE AREA.
Which ONE (1) of the following identifies the correct operator response to a valid alarm on R-9, LETDOWN LINE AREA, lAW AOP-005, Radiation Monitoring System?
A. Shut CVC-200B to minimize letdown flow.
B. Isolate letdown flow by closing LCV-460A / B.
C. Secure Charging pump C and lower Charging pump A to minimal flow.
D. Dispatch an operator to Loose Parts Monitoring Cabinet to monitor for abnormal indications.
63
 
ILC-11-1 NRC Exam
: 64. A plant shutdown is in progress with the plant at 20% RTP with the steam dumps in STEAM PRESSURE mode.
          -  C Circulating Water Pump is Out of Service for Maintenance.
          -  A and B Circulating Water Pumps are in operation.
          -  B Circulating Water Pump trips and V6-50B, CIRC WATER PMP B DISCH, remains full open and will not close.
What impact will this have on Condenser Vacuum and Steam Dump Operation AND what actions are required lAW AOP-012, Partial Loss of Condenser Vacuum or Circulating Water Pump Trip?
Condenser Vacuum will A. rapidly degrade. Steam dump operation may continue as long as ONE (1)
Circulating Water Pump is running and Vacuum does not go below 19.7 Hg.
Dispatch an operator to manually close V6-50B.
B. rapidly degrade. Steam dump operation may continue as long as ONE (1)
Circulating Water Pump is running and Vacuum does not go below 18 Hg.
Manually trip the turbine and go to AOP-007, Turbine Trip Below P-8.
C. slowly degrade. Steam dump operation may continue as long as ONE (1)
Circulating Water Pump is running and Vacuum does not go below 18 Hg.
Dispatch an operator to manually close V6-50B.
D. slowly degrade. Steam dump operation may continue as long as ONE (1)
Circulating Water Pump is running and Vacuum does not go below 19.7 Hg.
Manually trip the turbine and go to AOP-007, Turbine Trip Below P-8.
64
 
ILC-11-1 NRC Exam
: 65. Which ONE (1) of the following lists the location(s) that the Motor Driven Fire Pump (MDFP) and the Engine Driven Fire Pump (EDFP) can be manually started?
The MDFP can be started at the      (1)    AND the EDFP can be started at the      (2)
A. (1) Unit 2 Control Room AND Unit 2 Intake Structure.
(2) Unit 2 Intake Structure ONLY.
B. (1) Unit 2 Control Room AND Unit 2 Intake Structure.
(2) Unit 2 Control Room AND Unit 2 Intake Structure.
C. (1) Unit 2 Control Room ONLY.
(2) Unit 2 Intake Structure ONLY.
D. (1) Unit 2 Control Room ONLY.
(2) Unit 2 Control Room AND Unit 2 Intake Structure.
65
 
ILC-11-1 NRC Exam
: 66. Given the following plant conditions:
          -  The plant was at 42% RTP and rising lAW GP-005, Power Operation.
          - A loss of feedwater occurs.
          - All three SIG NR levels are at 0%.
          -  It is now 29 seconds later and the Reactor Trip Breakers have remained closed.
Which ONE (1) of the following is the expected response of the ATWS Mitigation System Actuation Circuitry (AMSAC) and the purpose of those actions?
AMSAC will start      (1)  and the purpose of AMSAC is to prevent    (2)
A. (1) ONLY MDAFW pumps (2) exceeding the kW/ft limit of the fuel rods during an ATWS condition.
B. (1) ONLY MDAFW pumps (2) prevent voiding in the RCS during an ATWS condition and a loss of feedwater.
C. (1)ALLAFWpump5 (2) exceeding the kW/ft limit of the fuel rods during an ATWS condition.
D. (1)ALLAFWpump5 (2) voiding in the RCS during an ATWS condition and a loss of feedwater.
66
 
ILC-11-1 NRC Exam
: 67. In order to maintain an active license and qualification, a Reactor Operator must, at a MINIMUM, meet the following requirements:
A. Stand a minimum of four 12 hour shifts per calendar quarter as RO.
Participate in LOCT and be evaluated as an RO or BOP in LOCT.
Have a current annual medical exam.
B. Stand a minimum of four 12 hour shifts per calendar quarter as RO or BOP.
Participate in LOCT and be evaluated as an RO in LOCT.
Have a current biennial medical exam.
C. Stand a minimum of five 12 hour shifts per calendar quarter as RO.
Participate in LOCT and be evaluated as an RO or BOP in LOCT.
Have a current annual medical exam.
D. Stand a minimum of five 12 hour shifts per calendar quarter as RO or BOP.
Participate in LOCT and be evaluated as an RO in LOCT.
Have a current biennial medical exam.
67
 
ILC-11-1 NRC Exam
: 68. With the plant at 100% RTP what power level will be acceptable for performance of OST-206, Comprehensive Flow Test for the Steam Driven Auxiliary Feedwater Pump and what effects will forward flowing the SIG have on Reactor Power?
In accordance with OST-206, Reactor Power must be no greater than A. 99%
Running the SDAFW Pump results in a rise in reactor power solely due to the additional feedwater flow.
B. 98%
Running the SDAFW Pump results in a rise in reactor power due to using steam to run the pump and cooler feedwater being supplied to the SIG5.
C. 99%
Running the SDAFW Pump results in a rise in reactor power due to using steam to run the pump and cooler feedwater being supplied to the S/Gs.
D. 98%
Running the SDAFW Pump results in a rise in reactor power solely due to the additional feedwater flow.
68
 
ILC-11-1 NRC Exam
: 69. Given the following information:
      -  Plant is at 100% RTP.
      -  The current plant Risk Profile (EOOS profile) is an elevated GREEN due to scheduled repairs to Reactor Protection related components. These repairs are in-progress and will take 5 hours to restore, test and return to service.
An Electrical System Engineer has coordinated with the Work Week Coordinator and Plant Management to inspect the fuses and wiring inside 480V-E1 Compartment 1 8A, PTS & METERING EQUIPMENT to resolve a recent Vendor Notice as an Emergent Work Activity.
Which ONE (1) of the following describes the actions that must be taken prior to authorizing the Emergent Work Activity while the Reactor Protection work continues?
A. EOOS Risk Assessment will NOT be performed since opening the 480V-E1 Compartment door does NOT render any equipment unavailable. EOOS Risk Assessment is not necessary. Work may be released.
B. EOOS Risk Assessment will be performed assuming that 480V-E1 will be made unavailable. IF the assessment results in a YELLOW risk condition THEN the emergent work SHALL NOT be released.
C. EOOS Risk Assessment will be performed assuming that 480V-E1 will be made unavailable. IF the assessment results in an ORANGE risk condition THEN the emergent work SHALL NOT be released.
D. EOOS Risk Assessment will be performed assuming that 480V-E1 will be made unavailable. IF the assessment results in an ORANGE risk condition THEN the work may be released with SM approval.
69
 
ILC-11-1 NRC Exam
: 70. Given the following plant conditions:
          -  The plant is in Mode 1.
Which ONE (1) of the following sets of conditions represents a violation of a Technical Specification Safety Limit and required action lAW Technical Specifications?
(Reference Provided)
A. RTP  - 10%, PZR Pressure 2350 psig, RCS Highest Cold Leg Temp 650°F
                                  -                                          -
Restore compliance and be in Mode 3 within 1 hour.
B. RTP 80%, PZR Pressure 2250 psig, RCS Highest Cold Leg Temp 640°F
            -                      -                                          -
Restore compliance and be in Mode 3 within 1 hour.
C. RTP  -  10%, PZR Pressure 2350 psig, RCS Highest Cold Leg Temp 650°F
                                  -                                          -
Restore compliance within 5 minutes.
D. RTP 80%, PZR Pressure 2250 psig, RCS Highest Cold Leg Temp 640°F
            -                      -                                          -
Restore compliance within 5 minutes.
70
 
ILC-11-1 NRC Exam
: 71. What Technical Specification OPERATIONAL MODE is the plant in with RCS temperature being maintained at 380° F AND how many Safety Injection Pump(s) are required to be operable?
The plant is in Mode    (1)      AND there must be at least      (2) Safety Injection Pump(s) operable without entering a TS Action Statement.
A. (1)3 (2) 1 B. (1)4 (2) 1 C. (1)3 (2) 2 D. (1)4 (2) 2 71
 
ILC-11-1 NRC Exam
: 72. Given the following plant conditions:
            - A fuel handling accident occurs in containment and an evacuation is ordered via a PA announcement.
            -  R-14C, NG-LO, is reading normal with a steady reading.
            -  R-1 1 and R-1 2, Containment Particulate and Gas Radiation Monitors, indications are showing a slight rising trend.
            -  The Equipment Hatch is removed.
Which ONE (1) of the following is an action to be taken to mitigate the consequences of this event lAW AOP-013, FUEL HANDLING ACCIDENT?
A. Verify Control Room Ventilation System shifted to Emergency Recirculation Mode.
B. Place HVE-3 and HVE-4, CV Iodine RMVL Fan, in the PREPURGE position.
C. Place the Upper Fuel Handling Building Ventilation System in service.
D. Verify and maintain the CV Purge secured.
72
 
ILC-11-1 NRC Exam
: 73. Given the following:
          - A Progress Energy Mechanic has been assigned to repack a valve.
          -  Projected dose rate in the area is 500 mR/hr.
          - The Mechanic has a current yearly dose of 0.5 Rem TEDE.
What is the MAXIMUM time that the mechanic can work on the valve before reaching the Progress Energy Annual Administrative Dose Limit?
A. 1 hour B. 3 hours C. 4 hours D. 7 hours 73
 
ILC-11-1 NRC Exam
: 74. The plant was at 100% RTP when a LOCA occurred. The crew was implementing PATH-I when a loss of offsite power occurred due to an internal failure in the Startup Transformer.
          - Due to several equipment malfunctions, the following conditions exist:
                - A SIG N/R level is 10%, AFW flow is 110 gpm.
                - B SIG N/R level is 12%, AFW flow is 105 gpm.
                - C SIG N/R level is 13%, AFW flow is 110 gpm.
                - RCS pressure is 100 psig and lowering.
                - Core exit thermocouples are 708°F.
                - RVLIS Full Range is 43%.
                - Containment pressure is 41 psig and lowering.
                - Both CV spray pumps have tripped and cannot be restarted.
Which ONE (1) of the following identifies the proper procedure that will be entered based on priority of the procedures? (Assume that monitoring of CSFSTs is in effect.)
A. FRP-H.1, Response to Loss of Secondary Heat Sink.
B. FRP-J.1, Response to High Containment Pressure.
C. FRP-C.1, Response to Inadequate Core Cooling.
D. FRP-C.2, Response to Degraded Core Cooling.
74
 
ILC-11-1 NRC Exam
: 75. Which ONE(1) of the following identifies the mitigation strategy of EPP1 2, Post-SGTR Cooldown Using Backfill?
EPP-12 cools down and depressurizes the plant to Cold Shutdown conditions and A. cools the ruptured SIG by filling to 85% to 91% WR level.
B. cools the ruptured SIG by steaming with the steam line PORV.
C. depressurizes the ruptured SIG by draining the ruptured SIG through SIG blowdown.
D. depressurizes the ruptured SIG by draining the ruptured SIG through the ruptured tube(s).
75
 
ILC-ii-1 NRC Exam
: 76. Given the following plant conditions:
          -  The Unit is shutdown following a reactor trip.
          -  The crew has transitioned to EPP-4, REACTOR TRIP RESPONSE.
          -  Foldout A is in effect.
          -  RCS Tavg is 602°F and stable.
          -  RCS Pressure is 1985 psig and lowering.
          -  Pressurizer level is 72% and rising.
          -  Containment Pressure is 0.2 psig and stable.
          -  PZR PORV PCV-456 indicates intermediate (Red / Green).
          -  PZR PORV BLOCK RC-535 MOV breaker tripped while attempting to close from the RTGB.
Which ONE (1) of the following states the actions to be taken to mitigate the given plant conditions?
A. Trip all RCPs AND Continue in EPP-4.
B. Trip all RCPs AND Go to PATH-i, Entry Point A.
C. Initiate Safety Injection AND Go to PATH-i, Entry Point A.
D. Initiate Safety Injection AND Go to PATH-i, Entry Point C.
76
 
ILC-11-1 NRC Exam
: 77. Given the following plant conditions:
          - The plant was at 205°F and RHR Core Cooling was in service when a loss of Instrument Air occurred.
          - Actions have been taken up to the point where one RHR Pump has been started and RHR flow re-established.
Which ONE (1) of the following completes the statements below?
FC-605, RHR HX BYPASS FLOW Controller, will be adjusted to obtain      (1)    and HIC-758, RHR HX DISCH FLOW, will be adjusted to achieve desired cooling lAW (2)
A. (1)3lOOgpm (2) AOP-017, Loss of Instrument Air.
B. (1)3lOOgpm (2) AOP-020, Loss of Residual Heat Removal (Shutdown Cooling).
C. (1)4000gpm (2) AOP-01 7, Loss of Instrument Air.
D. (1) 4000 gpm (2) AOP-020, Loss of Residual Heat Removal (Shutdown Cooling).
77
 
ILC-Il-1 NRC Exam
: 78. Given the following plant conditions:
            - The Unit was at 30% RTP.
            - A EDG is under clearance.
            -  A tornado touches down in the switchyard and caused a Phase Differential on the Main Generator.
            - The SUT is destroyed by a tornadic missile.
Which ONE (1) of the following identifies the required implementation of procedures for this event?
Enter....
A. EPP-i, Loss of All AC Power,    ---> EPP-22, Energizing Plant Equipment using the DSDG, to energize MCC-5.
B. EPP-I, Loss of All AC Power, ---> EPP-25, Energizing Supplemental Plant Equipment using the DSDG, to energize MCC-5.
C. PATH-I ---> EPP-25, Energizing Supplemental Plant Equipment using the DSDG, to energize MCC-5 ---> EPP-4, Reactor Trip Response.
D. PATH-i ---> EPP-22, Energizing Plant Equipment using the DSDG, to energize MCC-5 ---> EPP-4, Reactor Trip Response.
78
 
ILC-11-1 NRC Exam
: 79. Given the following plant conditions:
            - The plant is in Mode 5.
            - The RCS is in solid plant operations.
          -  Annunciator APP-002-E7, INST AIR CMPR D Trip alarms.
            - Annunciator APP-002-F2, INST AIR HDR LO PRESS alarms.
            - Instrument Air pressure indicated on the RTGB is 80 psig, lowering rapidly.
            - RCS temperature is currently at 180°F and rising at 0.2°F/mm.
Which ONE (1) of the following completes the statement below?
(1)      is the cause of the loss of instrument air and      (2)    is the required actions that mitigate these plant conditions.
A. (1) IA-3834, D Instrument Air Dryer Relief, lifting and not reseating (2) Transition to AOP-020, Loss of Residual Heat Removal, while continuing in AOP-017, Loss of Instrument Air, B. (1) Rupture of IA piping in Pipe Alley (2) Exit AOP-017, Loss of Instrument Air, and Transition to AOP-020, Loss of Residual Heat Removal, C. (1) lA-3834, D Instrument Air Dryer Relief, lifting and not reseating (2) Exit AOP-01 7, Loss of Instrument Air, and Transition to AOP-020, Loss of Residual Heat Removal, D. (1) Rupture of IA piping in Pipe Alley (2) Transition to AOP-020, Loss of Residual Heat Removal, while continuing in AOP-017, Loss of Instrument Air, 79
 
ILC-il-l NRC Exam
: 80. Given the following plant conditions:
            - A Safety Injection has occurred due to lowering Pressurizer Level and Pressure.
            - PATH-i is in progress.
            - SPDS has not been reset.
            - Containment radiation parameters are normal.
            - R-14C, NG-Plant Vent, and R-4, Charging Pump Room, are in alarm.
Which ONE (1) of the following completes the statement below?
Procedure (1) would be entered based on the conditions provided and the first action taken would be to isolate (2)
A. (1) EPP-i5, Loss of Emergency Coolant Recirculation, (2) Hot Leg Safety Injection B. (1) EPP-20, LOCA Outside Containment, (2) Hot Leg Safety Injection C. (1) EPP-15, Loss of Emergency Coolant Recirculation, (2) RHR Loop Supply D. (1) EPP-20, LOCA Outside Containment, (2) RHR Loop Supply 80
 
ILC-l1-l NRC Exam
: 81. Given the following plant conditions:
            - Feed Line Break to A SIG has occurred.
            - RCS Pressure is 1345 psig and rising.
            - CV Pressure is 20 psig and lowering.
            - SIG pressures: A 0 psig, B 400 psig, C 400 psig.
                                  -          -              -
            - SIG WIDE RANGE levels: A 5%, B 21%, C 17%.
                                          -        -        -
            - No AFW flow is available.
            - PATH-I Immediate Actions are complete and have just been verified.
Which ONE (1) of the following correctly analyzes the current plant conditions and identification of the required procedural progression that mitigates these plant conditions?
A. RCS bleed-and-feed is required.
Continue in PATH-I until directed to FRP-H.I, Response to Loss of Secondary Heat Sink.
B. RCS bleed-and-feed is required.
Exit PATH-l and transition to FRP-H.I, Response to Loss of Secondary Heat Sink.
C. RCS bleed-and-feed is NOT required.
Continue in PATH-I until directed to FRP-H.1, Response to Loss of Secondary Heat Sink.
D. RCS bleed-and-feed is NOT required.
Exit PATH-l and transition to FRP-H.I, Response to Loss of Secondary Heat Sink.
81
 
ILC-11-1 NRC Exam
: 82. Given the following plant conditions:
          - Critical approach has just been completed.
          - Reactor is stable at the Point of Adding Heat.
          - APP-005-B2, N-35 LOSS OF COMP VOLT, alarm is received.
Which ONE(1) of the following correctly identifies the expected Power Range (PR) and Intermediate Range (IR) Nuclear Instrument indications and the required actions lAW Technical Specifications?
A. IR = 2.0 x 106 Amps; PR between 0.5 and 1%.
Lower Power to less than P-6 within 1 hour.
B. IR = 2.0 x 106 Amps; PR between 0.5 and 1%.
Lower Power to less than P-6 within 2 hours.
C. IR = 1.0 x io Amps; PR between 0 and <0.5%.
Lower Power to less than P-6 within 1 hour.
D. IR  1.0 x      Amps; PR between 0 and <0.5%.
Lower Power to less than P-6 within 2 hours.
82
 
ILC-11-1 NRC Exam
: 83. Given the following plant conditions:
          - High radiation alarms have just been received from R-20 and R-30, Fuel Handling Building Lower Level.
          - ERFIS trends indicate the following:
WGDT A is at 70  psig and is In-Service.
WGDT B is at 20  psig and is In Standby.
WGDT C is at 80  psig and is Selected for Cover Gas with pressure slowly lowering.
WGDT D is at 60  psig and is isolated.
Which ONE (1) of the following identifies the required action(s) that mitigate these plant conditions lAW AOP-005, Radiation Monitoring System, and/or AOP-009, Accidental Gas Release from a WGDT?
In accordance with A. AOP-009, Direct the AC to equalize WGDT C with WGDT B.
B. AOP-009, Isolate WGDT C and place HVE-15A in service.
C. AOP-005, Direct the AC to equalize WGDT C with WGDT B.
D. AOP-005, Isolate WGDT C and place HVE-15A in service.
83
 
ILC-11-1 NRC Exam
: 84. Given the following information:
          -  The plant is at 100% RTP.
          -  RST-008, Calibration of Radiation Monitor System, Monitors R-1 through R-8, has been performed for R-1, Control Room Area Monitor.
          -  Based on technicians report, R-1 has been turned over to Operations and declared Operable.
          - The Acceptance Criteria for the AS-LEFT calibration of R-1 is 50 mr/hr +1- 10%
and 6500 mr/hr +1- 20% for the detector (RST-008 Test Exposure Rate).
          -  Prior to closing out the RST-008 paperwork, the RC Supervisor reports the following Final AS-LEFT calibration results for R-1 to the CRS:
RST-008 Test Exposure Rate              AS-LEFT Reading 50 mr/hr                          43 mr/hr 6500 mr/hr                        5225 mr/hr Which ONE(1) of the following states the Operability status of the equipment affected by the information given above?
A. BOTH CREFS trains are Inoperable.
B. CREFS Actuation Instrumentation is Operable.
C. ONLY CREFS Actuation Instrumentation is Inoperable.
D. BOTH CREFS trains AND the CREFS Actuation Instrumentation are Inoperable.
84
 
ILC-ll-l NRC Exam
: 85. Given the following plant conditions:
          - A LOCA is in progress. The crew is performing actions of PATH-i.
          - Core Exit TCs are at 705&deg;F and rising.
          - RVLIS Full Range indicates 40% and lowering.
          - Containment pressure is 44 psig and slowly rising.
          - RWST Level is 29% and lowering.
Which ONE (1) of the following completes the statement below?
Enter (1)      FIRST, then declare a    (2)    lAW the Emergency Action Level Matrices.
(References Provided)
A. (1) FRP-J.1, Response To High Containment Pressure (2) Site Area Emergency B. (1) FRP-C.1, Response to Inadequate Core Cooling (2) Site Area Emergency C. (1) FRP-J.1, Response To High Containment Pressure (2) General Emergency D. (1) FRP-C.1, Response to Inadequate Core Cooling (2) General Emergency 85
 
ILC-11-1 NRC Exam
: 86. Given the following plant conditions:
            - Mode 2 with a Plant Startup in Progress.
            - Train B Reactor Protection testing is in progress.
            - B Reactor Trip Bypass Breaker has been racked in and closed.
            - Reactor Trip Breaker B is currently closed.
            - B 125VDC Distribution Panel power is lost.
Which ONE (1) of the following completes the statements below regarding plant response due to a DIRECT RESULT of the failure AND what actions must be taken lAW Technical Specifications and AOP-024, Loss of Instrument Bus?
ONLY the Reactor          (1)    Breaker B will open.
The affected Instrument Bus must be re-energized within        (2) hrs.
Normal Power Supply to the affected Instrument Bus must be restored to OPERABLE status within    (3)  hrs.
A. (1) Trip (2) 2 (3) 24 B. (1) Trip Bypass (2) 2 (3) 24 C. (1) Trip (2) 8 (3) 16 D. (1) Trip Bypass (2) 8 (3) 16 86
 
ILC-11-1 NRC Exam
: 87. Given the following initial plant conditions:
            - The plant is at 100% RTP.
            - APP-036-C7, R-24 Monitor HI, has alarmed. R-24B indicates 5.1 gpd, with a rising trend.
            -  R-15, Condenser Air Ejector Gas Monitor, and R-19B, SIG B Liquid Sample Monitor, were observed to be rising.
Approximately 15 minutes later the following plant conditions exist:
            -  R-24B now is steady with a reading of 35 gpd.
            -  The warning alarm on RR-1, RMS RECORDER, for R-1 9B, S/G B Liquid Sample Monitor has alarmed.
            -  The crew has entered AOP-035, S/G Tube Leak.
Which ONE (1) of the following completes the statement below?
The crew will take required action to          (1)      due to the known leakrate and take action to        (2)      to mitigate the spread of contamination.
A. (1) initiate a Normal Plant Shutdown and be in Mode 3 within 6 hours (2) close ES-33, Heater 5B EXT Steam to PRV-1985, to isolate Main Steam from Auxiliary Steam THEN start the Auxiliary Boilers B. (1) initiate a Normal Plant Shutdown and be in Mode 3 within 6 hours (2) start the Auxiliary Boilers. Once Auxiliary Boilers have pressurized THEN close ES-33, Heater 5B EXT Steam to PRV-1 985, to isolate Main Steam from Auxiliary Steam C. (1) monitor for increased primary to secondary leakage by logging R-24 readings at 15 minute intervals (2) close ES-33, Heater 5B EXT Steam to PRV-1985, to isolate Main Steam from Auxiliary Steam THEN start the Auxiliary Boilers D. (1) monitor for increased primary to secondary leakage by logging R-24 readings at 15 minute intervals (2) start the Auxiliary Boilers. Once Auxiliary Boilers have pressurized THEN close ES-33, Heater 5B EXT Steam to PRV-1985, to isolate Main Steam from Auxiliary Steam 87
 
ILC-11-1 NRC Exam
: 88. Given the following plant conditions:
          - The plant is at 100% RTP.
          -  HVH-2 was started two (2) minutes ago following a test.
          - APP-009-E7, 480V GRD FAULT, has alarmed.
          - An AC was dispatched and reports that the GROUND FAULT light is illuminated and the GRD FAULT RELAY flag has dropped on SST-2F.
What action(s) should be taken lAW OMM-035, Ground Isolation, and OP-921, Containment Air Handling, and what impact on Operability (if any) will this have on the system?
A. Stop HVH-2 and remove control power fuses.
Containment Cooling Train A remains Operable.
B. Stop HVH-2.
Containment Cooling Train A remains Operable.
C. Stop HVH-2 and remove control power fuses.
Declare ONLY Containment Cooling Train A Inoperable.
D. Stop HVH-2.
Declare ONLY Containment Cooling Train A Inoperable.
88
 
ILC-11-1 NRC Exam
: 89. Given the following plant conditions:
            - The plant is at 100% RTP.
            - A two train fire alarm is received for the Unit 2 Cable Spread Room.
            - The crew has entered AOP-041, Response to Fire Event.
Which ONE (1) of the following completes the statement below?
After confirming the fire location the next crew action is to    (1)  and the basis for this action is to (2)
A. (1) place PCV-456 I -455C Isolation Switches in the ISOLATED position (2) prevent spurious operation of these valves due to a hot short B. (1) place PCV-456 I -455C Isolation Switches in the ISOLATED position (2) to allow for remote operation of ONLY PCV-456 from the 4 KV Switchgear Room C. (1) verify LCV-115B, EMERG MU TO CHG SUCTION, OPEN and LCV-115C, VCT OUTLET, CLOSED (2) maintain suction to the Charging Pumps due to potential hot shorts affecting the VCT level control circuitry D. (1)verify LCV-115B, EMERG MU TO CHG SUCTION, OPEN and LCV-115C, VCT OUTLET, CLOSED (2) maintain suction to the Charging Pumps due to potential hot shorts causing spurious operation of LCV-1 I 5C 89
 
ILC-11-1 NRC Exam
: 90. Given the following:
          - The Plant has just entered Mode I following a startup from a Refueling Outage.
          - A review of Work Orders reveals that the Containment Equipment Hatch was not properly torqued. Additionally, Post-Maintenance Testing (Local Leak Rate Test) on the Hatch seals was not performed.
          - Maintenance and Engineering reports that repairs and testing can be completed in 12 hours.
Which ONE (1) of the following completes the statement below?
lAW Technical Specifications the Containment Equipment Hatch must be restored to Operable status within    (1) hour(s) and lAW AP-030, NRC Reporting Requirements, the NRC must be notified within      (2)  hour(s) for Shutdown Required by ITS and within    (3)  hour(s) for Principal Safety Barriers Seriously Degraded.
A. (1)1 (2) 4 (3) 8 B. (1)4 (2) 4 (3) 8 C. (1)1 (2) 1 (3) 1 D. (1)4 (2) 1 (3) 1 90
 
ILC-11-1 NRC Exam
: 91. Given the following plant conditions:
          -  Plant is at 3% RTP.
GP-005, POWER OPERATION, is in progress. Preparations are being made to start rolling the Turbine.
          - The RO reports that PZR pressure is lowering and that PCV-455B appears to be open with a closed demand signal. AOP-019, Malfunction of RCS Pressure Control, Immediate Actions have been completed.
                  - Both PZR PORVs are closed.
                  - PCV-455B, SPRAY VALVE Controller has been placed in MAN and its output adjusted to zero.
                  - All PZR heaters are energized.
          - The STA reports that PZR pressure is at 2200 psig and lowering at approximately 30 psig/minute.
Which ONE (1) of the following completes the statements below?
Direct the Reactor Operator to stop the C RCP, adjust LC-459G potentiometer to maintain PZR level between        (1)
Place the plant in Mode 3 in      (2)    hours.
A. (1)17%-27%
(2) 12 B. (1)17%-27%
(2) 6 C. (1) 30% 40%
                -
(2) 12 D. (1)30%-40%
(2) 6 91
 
ILC-11-1 NRC Exam
: 92. Given the following information:
Date                Time          Activity 5/31/2011          0000          Plant Shutdown to Mode 3 commenced.
5/31/2011          0830          Reactor Trip Breakers opened.
5/31/2011            1500          Mode4 Entry.
5/31/2011          2330          Mode5 Entry.
Which ONE (1) of the following completes the statements below?
The EARLIEST time and date that core alterations can commence in accordance with GP-010, Refueling, is    (1)
The Manipulator Crane normal path from the CV Upender to core location H-8 is (2)
The    (3)  provides permission to deviate from the Manipulator Crane normal path.
A. (1)6/4/2011 at 1230 (2) Bridge south to 8 row and trolley east to H row (3) Shift Manager B. (1) 6/2/2011 at 1630 (2) Bridge south to 8 row and trolley east to H row (3) Refueling SRO C. (1) 6/4/2011 at 1230 (2) Bridge south to core area, trolley east to H row and then bridge south to 8 row.
(3) Shift Manager D. (1)6/2/2011 at 1630 (2) Bridge south to core area, trolley east to H row and then bridge south to 8 row.
(3) Refueling SRO 92
 
ILC-11-1 NRC Exam
: 93. Given the following:
      - Unit is operating in Mode I at 100% RTP.
      - The Engine Driven Fire Pump is inoperable for annual inspection and PMs.
      - The Motor Driven Fire Pump (MDFP) and Fire Jockey Pump are operating to supply the system pressure and flush water.
      - The breaker for the MDFP trips open and cannot be re-closed.
      - The Fire Jockey Pump continues to operate.
Which ONE (1) of the following describes the actions required lAW FP-012, Fire Protection Systems Minimum Equipment and Compensatory Actions?
A. Be in Mode 4 within 12 hours and Mode 5 within 36 hours.
B. Restore at least 1 Fire Pump to operable status within 7 days.
C. Restore at least I Fire Pump to operable status within 14 days.
D. Establish a backup fire suppression water system within 24 hours.
93
 
ILC-i1-1 NRC Exam
: 94. Given the following plant conditions:
            - The plant has been operating at 100% RTP for the past three weeks.
            - Chemistry has just provided the following results from a Reactor Coolant System sample that was taken 1 hour ago:
                  -  RCS Chloride: 0.1 ppm
                  -  RCS Oxygen: 0.15 ppm Which ONE(1) of the following completes the statement below?
The (1) concentration exceeds the TRM limit. Immediate action must be taken to initiate action to  (2)
A. (1) Oxygen (2) place the plant in Mode 3.
B. (1) Oxygen (2) bring the Oxygen concentration within limits.
C. (1) Chloride (2) place the plant in Mode 3.
D. (1) Chloride (2) bring the Chloride concentration within limits.
94
 
ILC-11-1 NRC Exam
: 94. Given the following plant conditions:
            - The plant has been operating at 100% RTP for the past three weeks.
            - Chemistry has just provided the following results from a Reactor Coolant System sample that was taken 1 hour ago:
                  -  RCS Chloride: 0.1 ppm
                  -  RCS Oxygen: 0.15 ppm Which ONE(1) of the following completes the statement below?
The (1) concentration exceeds the TRM limit. Immediate action must be taken to initiate action to (2)
A. (1) Oxygen (2) place the plant in Mode 3.
B. (1) Oxygen (2) bring the Oxygen concentration within limits.
C. (1) Chloride (2) place the plant in Mode 3.
D. (1) Chloride (2) bring the Chloride concentration within limits.
94
 
ILC-11-1 NRC Exam 95.
Which ONE (1) of the following identifies components assumed to operate at their setpoints to prevent exceeding the Technical Specification Safety Limit on RCS pressure?
A. All Pressurizer Safety Valves ONLY.
B. All Main Steam Safety Valves ONLY.
C. All Pressurizer Safety and Main Steam Safety Valves.
D. TWO (2) Pressurizer Safety Valves and THREE (3) Main Steam Safety Valves per line.
95
 
ILC-11-1 NRC Exam
: 96. Voltage regulator for the Main Generator has been replaced during the refueling outage.
SP-)O(XX has been developed and approved for acceptance testing to be used with GP-005, Power Operation.
Final testing must be performed with voltage regulator in service with unit paralled to the grid.
Which ONE (1) of the following is the appropriate CASE assignment for this evolution and who SHALL act as the Management Designated Monitor (MDM) for this evolution lAW PLP-037, Conduct of Infrequently Performed Tests or Evolutions and Pre-Job Briefs.
(Reference Provided)
A. CASE 2    - MDM shall be a Line Manager, Senior to the SM.
B. CASE 3    - MDM shall be a First Line Supervisor or above.
C. CASE 3    - MDM shall be assigned by PGM.
D. CASE 2    - MDM shall be assigned by PGM.
96
 
ILC-11-1 NRC Exam
: 97. Given the following plant conditions:
          -  Large Break LOCA with multiple equipment malfunctions.
          -  Fuel failure has been confirmed.
          -  A General Emergency has been declared and ERO positions staffed.
          -  The Dose Rate in Pipe Alley is 120 R/hr.
          -  An evolution in Pipe Alley is necessary to avoid extensive exposure of a large population.
          -  Individuals were selected by the OSC Leader to perform the evolution.
Which ONE (1) of the following completes the statements below?
The      (1)    can authorize performance of the evolution in Pipe Alley.
lAW EPOSC-04, Emergency Work Control,            (2)    is the maximum time allowed to perform the evolution in Pipe Alley without exceeding Emergency Work Dose Limits.
A. (1) Site Emergency Coordinator (2) 4.5 minutes B. (1) Site Emergency Coordinator (2) 12.4 minutes C. (1) Radiological Control Director (2) 4.5 minutes D. (1) Radiological Control Director (2) 12.4 minutes 97
 
ILC-11-1 NRC Exam
: 98. Given the following plant conditions:
          - A Large Break LOCA has occurred.
          - Containment pressure is 32 psig and rising.
          - A loss of off-site power has occurred.
          - B EDG has failed to start.
          - HVH-1 has tripped.
          - R-32A, CV High Range, has the current indication.
Which ONE (1) of the following completes the statement below?
Based on the information provided a      (1)  must be declared due to  (2)
(References Provided)
A. (1) Site Area Emergency (2) Loss of the Reactor Coolant AND Fuel Cladding Barriers.
B. (1) General Emergency (2) Loss of Reactor Coolant, Fuel Cladding AND Containment Barriers.
C. (1) Site Area Emergency (2) Loss of the Reactor Coolant Barrier AND a Potential Loss of Containment Barrier.
D. (1) General Emergency (2) Loss of the Reactor Coolant AND Fuel Cladding Barrier AND Potential Loss of Containment Barrier.
98
 
ILC-11-1 NRC Exam
: 99. A Site Area Emergency has been declared.
The Control Room Site Emergency Coordinator has the authority to delegate certain tasks to other available watch standers.
Which ONE (1) of the following tasks CAN be delegated?
A. Classification of the Event.
B. Conduct a Site Evacuation.
C. Decision to Notify Off-site Authorities.
D. Off-site Protective Action Recommendations.
99
 
ILC-11-1 NRC Exam 100. A General Emergency has been declared.
    - The SEC-CR is evaluating Protective Action Recommendations (PARs).
    - There are no known impediments to evacuation.
Which ONE (1) of the following is the MINIMUM PARs that shall be issued for the declared General Emergency?
Evacuate at least A. 5 mile radius and shelter 10 miles downwind.
B. 5 mile radius and 10 miles downwind.
C. 2 mile radius around and shelter 5 miles downwind.
D. 2 mile radius around and 5 miles downwind.
100
 
Reference Material Table of Contents
: 1. ITS Section 2.0, Figure 2.1.1-1, Reactor Core Safety Limits
: 2. PLP-037, Attachment 10.2, Procedure Evaluation and Case Determination
: 3. EAL Matrix ALL CONDITIONS
: 4. EAL Matrix HOT CONDITIONS
: 5. EAL Matrix COLD CONDITIONS
 
ANSWER KEY REPORT for ILC-1 1-1 NRC Written Exam 2-1 5-1 1 Test Form: 0 Answers
#      ID                                          Points Type  0 1      007 EK2.02 1                                  1.00 MCS    D 2      008 AK2.03 1                                  1.00 MCS    C 3      009 EK3.23 1                                  1.00 MCS    A 4      OI1EK1.01 1                                    1.00 MCS    C 5      015 AK1.041                                    1.00 MCS    B 6      015 AK2.10 1                                  1.00 MCS    A 7      022 AAI.09 1                                  1.00 MCS    A 8      026 AA1.06 1                                  1.00 MCS    A 9      029 EG2.4.21 1                                1.00 MCS    C 10    040 AK3.02 1                                  1.00 MCS    A 11    054 AA2.08 1                                  1.00 MCS    B 12    056 AG2.4.47 1                                1.00 MCS    A 13    058 AA2.01 1                                  1.00 MCS    D 14    062 AA2.01 1                                  1.00 MCS    B 15    077 AG2.4.45 1                                1.00 MCS    B 16    WIEO4EK3.2 1                                  1.00 MCS    A 17    W/E O5EK1.2 1                                  1.00 MCS    C 18    W/E 11EA1.3 1                                  1.00 MCS    A 19    001 AA2.04 1                                  1.00 MCS    D 20    036 AK2.01 1                                  1.00 MCS    D 21    037 AG2.4.9 1                                  1.00 MCS    A 22    051 AA1.04 1                                  1.00 MCS    D 23    059 AK3.01 1                                  1.00 MCS    B 24    074 EA2.07 1                                  1.00 MCS    B 25    WIE 03 EK 1.11                                1.00 MCS    D 26    WIE I4EAI.1 1                                  1.00 MCS    D 27    W/E 15EK3.1 1                                  1.00 MCS    B 28    003 A3.04 1                                    1.00 MCS    C 29    004 A3.15 1                                    1.00 MCS    D 30    004 K3.08 1                                    1.00 MCS    A 31    005 K3.07 1                                    1.00 MCS    A 32    006 A1.07 1                                    1.00 MCS    C 33    006K6.101                                      1.00 MCS    B 34    007 A1.03 1                                    1.00 MCS    A 35    007 A2.01 1                                    1.00 MCS    C 36    008 K4.09 1                                    1.00 MCS    D 37    010 K5.02 1                                    1.00 MCS    B 38    010 K6.01 1                                    1.00 MCS    B 39    012A4.041                                      1.00 MCS    D 40    013 K5.01 1                                    1.00 MCS    B 41    022 A4.05 1                                    1.00 MCS    D 42    026 K2.01 1                                    1.00 MCS    A 43    039 G2.1.7 1                                  1.00 MCS    D 44    039 G2.4.20 1                                  1.00 MCS    C 45    059 A3.02 1                                    1.00 MCS    C 46    061 K5.01 1                                    1.00 MCS    D Thursday, March 24, 2011 2:51 :54 PM
 
ANSWER KEY REPORT for ILC-1 1-1 NRC Written Exam 2-15-11 Test Form: 0 Answers
#      ID                                          Points Type U 47    062 K2.01 1                                    1.00 MCS  C 48    063 A2.01 1                                    1.00 MCS  B 49    063 K4.02 1                                    1.00 MCS  D 50    064A2.141                                      1.00 MCS  C 51    073 02.4.18 1                                  1.00 MCS  A 52    076 K1.01 1                                    1.00 MCS  D 53    078 K3.02 1                                    1.00 MCS  A 54    103 A4.01 1                                    1.00 MCS  C 55    103 K1.02 1                                    1.00 MCS  B 56    001 K3.01 1                                    1.00 MCS  A 57    015 K2.01 1                                    1.00 MCS  C 58    016 K1.12 1                                    1.00 MCS  D 59    028 K5.03 1                                    1.00 MCS  A 60    034 K6.02 1                                    1.00 MCS  C 61    041 K4.09 1                                    1.00 MCS  C 62    071 A1.06 1                                    1.00 MCS  B 63    072 G2.1.20 1                                  1.00 MCS  A 64    075 A2.03 1                                    1.00 MCS  A 65    086 A4.01 1                                    1.00 MCS  A 66    G2.1.28 1                                      1.00 MCS  D 67    G2.1.4 1                                      1.00 MCS  D 68    02.1.43 1                                      1.00 MCS  B 69    02.2.20 1                                      1.00 MCS  C 70    02.2.22 1                                      1.00 MCS  B 71    G2.2.35 1                                      1.00 MCS  C 72    G2.3.13 1                                      1.00 MCS  B 73    02.3.4 1                                      1.00 MCS  B 74    G2.4.22 1                                      1.00 MCS  D 75    G2.4.6 1                                      1.00 MCS  D 76    008 AG 2.1.23 SRO 1                            1.00 MCS  C 77    025 AA2.05 SRO 1                              1.00 MCS  B 78    056 AG2.4.4 SRO 1                              1.00 MCS  C 79    065 AA 2.01 SRO 1                              1.00 MCS  D 80    WIE 04 EG2.4. 1 SRO 1                          1.00 MCS  D 81    W/E 05 EA2. 1 SRO 1                            1.00 MCS  A 82    033 AA2.04 SRO 1                              1.00 MCS  B 83    060 AG2.2.44 SRO 1                            1.00 MCS  A 84    061 AA2.03 SRO 1                              1.00 MCS  C 85    W/E 14EG2.4.47 SRO 1                          1.00 MCS  D 86    012 A2.07 SRO 1                                1.00 MCS  A 87    039 A2.03 SRO 1                                1.00 MCS  C 88    062 A2.14 SRO 1                                1.00 MCS  C 89    063 G2.4.49 SRO 1                              1.00 MCS  A 90    103 G2.4.30 SRO 1                              1.00 MCS  A 91    011 A2.06 SRO 1                                1.00 MCS  D 92    034 A3 .01 SRO 1                              1.00 MCS  C Thursday, March 24, 2011 2:51:54 PM                                                  2
 
ANSWER KEY REPORT for ILC-11-1 NRC Written Exam 2-15-11 Test Form: 0 Answers
#      ID                                          Points Type 0 93    086 G2.2.40 SRO 1                            1.00 MCS  D 94    G2.1.34 SRO 1                                1.00 MCS  B 95    G2.2.25 SRO 1                                1.00 MCS  C 96    G2.2.7 SRO 1                                  1.00 MCS  D 97    G2.3.14SRO 1                                  1.00 MCS  B 98    G2.3.5 SRO 1                                  1.00 MCS  D 99    G2.4.40 SRO 1                                1.00 MCS  B 100  G2.4.44 SRO 1                                1.00 MCS  D SECTION 1 ( 100 items)                            100.00 Thursday, March 24, 2011 2:51:54 PM                                                3}}

Revision as of 01:42, 13 November 2019

Initial Exam 2011-301 Final SRO Written Exam
ML110840677
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 03/25/2011
From:
NRC/RGN-II
To:
Carolina Power & Light Co
References
50-261/11-301 50-261/OL-11-301
Download: ML110840677 (106)
v • d • e


Text

ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date: Facility/Unit:

Region: I II Ill IV Reactor Type: WE CE D BWEGE E Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicants Signature Results RO/SRO-Only/Total Examination Values / I Points Applicants Scores I I Points Applicants Grade I I Percent ES-401, Page 31 of 33

ILC-11-1 NRC Exam 1 Given the following plant conditions:

- The Plant is at 100% RTP.

- The reactor trips due to a RCS low flow condition.

- Generator lockout occurs immediately.

- Approximately 5 seconds after the generator lockout a fault on 4KV Bus 4 causes voltage on 480V Bus E-2 to drop to 290 VAC.

Approximately 7 seconds after the generator lockout breaker 52/19, 4KV BUS 3-4 TIE BKR, trips open on overcurrent.

Which ONE (1) of the following identifies the current alignment of the Emergency buses?

A. 480V Bus E-1 is being powered via A EDG.

480V Bus E-2 is being powered via 4KV Bus 3.

B. 480V Bus E-1 is being powered via 4KV Bus 2.

480V Bus E-2 is being powered via 4KV Bus 3.

C. 480V Bus E-1 is being powered via A EDG.

480V Bus E-2 is being powered via B EDG.

D. 480V Bus E-1 is being powered via 4KV Bus 2.

480V Bus E-2 is being powered via B EDG.

1

ILC-11-1 NRC Exam

2. Given the following plant conditions:

- The plant is in Mode 5.

- RCS Temperature: 170°F and stable.

- RCS Pressure: 350 psig and stable.

Subsequently a loss of MCC-6 occurs resulting in the following:

- PT-501, PZR Pressure, fails low.

Which ONE (1) of the following actions are required lAW AOP-020, Loss of Residual Heat Removal (Shutdown Cooling)?

A. Close PCV-455C using its RTGB control switch.

B. Close RC-536, PORV Block Valve, using the RTGB control switch.

C. Place the associated LTOPP Arming Switch to the Normal position.

D. Take Manual Control of PC-444J and Reduce the Controller Output to Zero.

2

ILC-i1-1 NRC Exam

3. Given the following plant conditions:

- LOCA occurred inside containment.

- The crew is currently implementing PATH-i.

- Containment pressure peaked at 9.5 psig and is currently at 4.2 psig and slowly lowering.

- Core Exit T/Cs indicate 510°F and rising.

- RCS pressure is 1100 psig and lowering.

- Safety injection flow to the core is 500 gpm and steady.

Which ONE (1) of the following completes the statement below?

Based on these plant conditions, the Reactor Coolant Pumps will A. be secured due to inadequate subcooling.

B. NOT be secured due to adequate subcooling.

C. be secured due to loss of component cooling flow.

D. NOT be secured due to lower than expected SI flow.

3

ILC-11-1 NRC Exam

4. Which ONE (1) of the following describes reflux cooling?

Steam produced in the core rises in the hot legs to the SIGs where it is condensed and returned to the vessel via the (1) legs and to enhance this method of cooling, (2)

A. (1) cold (2) SIG levels must be maintained.

B. (1) cold (2) maintain SIG pressure higher than RCS pressure.

C. (1) hot (2) SIG levels must be maintained.

D. (1)hot (2) maintain SIG pressure higher than RCS pressure.

4

ILC-11-1 NRC Exam

5. The plant is at 25% RTP with GP-005, Power Operation, power ascension in progress when the A RCP trips on overcurrent.

Which ONE (1) of the following identifies the effect on Main Feedwater to the S/Cs from steady-state to steady-state conditions?

Feedwater flow...

A. to S/C A rises. Feedwater flow to S/Cs B and C lowers.

B. to S/C A lowers. Feedwater flow to S/Gs B and C rises.

C. lowers to all S/Cs.

D. remains constant.

5

ILC-11-1 NRC Exam

6. The plant is at 10% RTP with GP-005, Power Operation, power ascension in progress when the following occurs:

- Annunciator APP-001-D2, RCP #1 SEAL LEAKOFF HI FLOW, alarms.

- The RO reports #1 seal leakoff is 5.8 gpm for RCP A, and #1 seal leakoff for RCP B and RCP C has lowered from 3.0 to 2.0 gpm.

Which ONE (1) of the following identifies the required operator actions and proper sequence lAW AOP-0i 8, Reactor Coolant Pump Abnormal Conditions?

A. Trip the reactor and then stop RCP A.

Go to PATH-i while continuing with AOP-01 8 and then shut the #1 seal leakoff isolation valve within 3 to 5 minutes.

B. Trip the reactor and then stop RCP A.

Go to PATH-i while continuing with AOP-0i8 and then shut the #1 seal leakoff isolation valve within I to 2 minutes.

C. Stop RCP A and then trip the reactor.

Go to PATH-i while continuing with AOP-Oi 8 and then shut the #1 seal leakoff isolation valve within 3 to 5 minutes.

D. Stop RCP A and then trip the reactor.

Go to PATH-i while continuing with AOP-0i 8 and then shut the #1 seal leakoff isolation valve within 1 to 2 minutes.

6

ILC-11-1 NRC Exam

7. Given the following plant conditions:

- Plant is in Mode 3 at 547°F.

- The Charging Line in Pipe Alley has ruptured and sprayed water on FCV-626,THERM BARRIER OUTLET.

- An electrical short causes FCV-626 to travel to the closed position.

- The Crew has secured ALL Charging Pumps lAW AOP-018, Reactor Coolant Pump Abnormal Conditions.

How much time is allowed to restore RCP seal cooling AND what constitutes seal cooling restoration lAW AOP-018?

A. 15 minutes to restore EITHER thermal barrier cooling OR seal injection.

B. 15 minutes to restore BOTH thermal barrier cooling AND seal injection.

C. 30 minutes to restore EITHER thermal barrier cooling OR seal injection.

D. 30 minutes to restore BOTH thermal barrier cooling AND seal injection.

7

ILC-11-1 NRC Exam

8. Given the following plant conditions:

- The plant is at 100% RTP.

- CV Spray Pump A operating during the performance of OST-352-1, Containment Spray Component Test Train A.

-

- The following alarm is received:

- APP-002-E1, CV SRY PMP COOL WTR LO FLOW Which ONE (1) of the following identifies the alarm setpoint and the action required lAW APP-002-E1?

A. 30 GPM. Stop CV Spray Pump A.

B. 30 GPM. Continued operation of CV Spray Pump A is allowed.

C. 7 GPM. Stop CV Spray Pump A.

D. 7 GPM. Continued operation of CV Spray Pump A is allowed.

8

ILC-11-1 NRC Exam

9. Which ONE (1) of the following plant conditions requires entry into FRP-S.1, Response To Nuclear Power Generation/ATWS?

A. Source Range startup rate of +0.1 dpm.

B. Intermediate Range startup rate of -0.1 dpm.

C. Power Range indicates 3% with an Intermediate Range startup rate of +0.2 dpm.

D. Power Range indicates 3% with an Intermediate Range startup rate of -0.2 dpm.

9

ILC-11-1 NRC Exam

10. Which ONE (1) of the following identifies the ESFAS signal that will provide protection for a main steam line break adjacent to a Main Steam Safety Valve and the basis?

High Steam Line A. Delta P; Provides protection for steam line breaks upstream of the MSIVs.

B. Delta P; Provides protection for steam line breaks downstream of the MSIVs.

C. Flow with Low Tave; Provides protection for steam line breaks downstream of the MSIVs.

D. Flow with Low Tave; Provides protection for steam line breaks upstream of the MSIV5.

10

ILC-11-1 NRC Exam

11. The plant is at 68% RTP when the BOP observes the following indications for all 3 SIGs from the FE/SF Trend Recorders and Feed Reg. Valve Controllers:

- S/G level is LOWERING.

- Steam Flow is STABLE.

- Feed Flow is LOWERING.

- Feed Reg Valve positions are all OPENING.

Which ONE (1) of the following identifies the cause of the event in progress?

A. Heater Drain Pump Trip.

B. Main Feedwater Pump Trip.

C. FCV-1446, Condensate Recirc, fails OPEN.

D. FCV-1444, Feedwater Pump A Recirc Valve, fails OPEN.

11

ILC-11-1 NRC Exam

12. Given the following plant conditions:

- The plant is at 100% RTP when offsite power is lost.

- The crew has implemented EPP-5, Natural Circulation Cooldown.

Three hours has elapsed since the loss of offsite power and the following indications are observed:

- RCS Temperature is 288°F and lowering.

- RCS Pressure is 345 psig and stable.

Which ONE (1) of the following identifies the indications that are directed to be used lAW EPP-5 to determine if a Steam Void is present in the Reactor Vessel?

A. RVLIS upper range, Large PZR level changes B. RVLIS upper range, Core Exit Thermocouple Temperatures C. subcooling, Large PZR level changes D. subcooling, Core Exit Thermocouple Temperatures 12

ILC-11-1 NRC Exam

13. The plant is at 100% RTP.

The following annunciators are received:

- APP-036-D3, BATT A/B LOW VOLT

- APP-036-D2, BATT CHARGER BIB-i TROUBLE

- DC Bus B voltage indicates 123 volts and lowering.

OAO reports that B Battery Charger has tripped.

Which ONE (1) of the following describes the status of the DC Bus and the Operator action that will be required lAW OP-601, DC Supply System?

The (1) Battery Charger (2) . The B Batteries will be placed on (3) on the (4)

A. (1) B (2) will auto-start to become the In-service Battery Charger.

(3) equalize (4) B Battery Charger B. (1) B (2) must be manually placed in service.

(3) float setting (4) B Battery Charger.

C. (1) 81 (2) will auto-start to become the In-service Battery Charger.

(3) equalize (4) B-i Battery Charger D. (1) Bi (2) must be manually placed in service.

(3) float setting (4) B-i Battery Charger 13

ILC-11-1 NRC Exam

14. Given the following plant conditions.

- The plant is at 100% RTP.

- APP-008-F7, SOUTH SW HDR LO PRESS, and APP-008-F8, NORTH SW HDR LOW PRESS, alarms are received.

- A Security Guard reports a large amount of water flowing to the storm drains from the area between the Aux. Building and Radwaste Building.

- lAO identifies rupture at SW piping elbow on east side of Auxiliary Building.

Which ONE (1) of the following identifies the Service Water Header that is ruptured and the components that must be VERIFIED STOPPED or taken out of service lAW AOP-022, Loss of Service Water?

The (1) Header has ruptured and the (2) must be removed from service.

A. (1) South (2) B EDG B. (1) North (2) B EDG C. (1) South (2) A EDG D. (1) North (2) A EDG 14

ILC-11-1 NRC Exam

15. Given the following plant conditions:

- The plant is operating at 85% RTP.

- APP-009-D7, GEN LO FREQ, was received 30 seconds ago.

- AOP-026, GRID INSTABILITY, has been entered.

- Grid frequency is at 58.3 Hz and slowly lowering following a load rejection.

The crew has determined that the load rejection was 110 MWe.

Which ONE (1) of the following action(s) will be taken lAW AOP-026?

A. Trip the Reactor and Go to PATH-I ONLY.

B. Trip the Reactor, Stop the RCPs and Go to PATH-I.

C. Transition to AOP-015, Secondary Load Rejection ONLY.

D. Transition to AOP-015, Secondary Load Rejection, while continuing with AOP-026.

15

ILC-11-1 NRC Exam

16. Given the following plant conditions:

- The crew is performing the actions in EPP-20, LOCA Outside Containment.

- Auxiliary Building radiation levels are lowering.

- Safety Injection flow is 80 GPM and lowering.

- PZR level is off scale LOW.

- RCS pressure is 1450 psig and rising.

Which ONE (1) of the following identifies the leak status lAW EPP-20 and the basis for determining that status?

The leak is A. isolated because RCS pressure is rising.

B. NOT isolated because SI pump flow still exists.

C. NOT isolated because PZR level is not on scale.

D. isolated because Auxiliary Building radiation levels are lowering.

16

ILC-1i-1 NRC Exam

17. Given the following plant conditions:

- A Reactor Trip and Safety Injection have occurred.

- The crew has performed the actions of PATH-i.

- AFW flow cannot be established.

- All SIG NR levels are off-scale low.

- The crew has entered FRP-H.i, Response to Loss of Secondary Heat Sink.

- RCS Pressure is 175 psig and stable.

- Intact S/G pressures are 300 psig and trending down.

Which ONE (1) of the following completes the statement below?

A (1) Break LOCA is in progress AND a Secondary Heat Sink (2)

A. (1) Large (2) is required.

B. (1) Small (2) is required.

C. (1) Large (2) is NOT required.

D. (1) Small (2) is NOT required.

17

ILC-11-1 NRC Exam

18. Given the following plant conditions:

- A SBLOCA has occurred. Containment Pressure is 2.3 psig.

- CCW Pumps are not available.

- The operating crew has transitioned to EPP-15, Loss of Emergency Coolant Recirculation.

Which ONE (1) of the following correctly describes the reason for depressurizing the RCS and the terminating setpoint?

To (1) depressurize the RCS until PZR level is > 71% (2) RCS Subcooling is between 35°F and 45°F.

A. (1) minimize RCS leakage (2)OR B. (1) minimize RCS leakage (2) AND C. (1) inject the SI accumulators (2)OR D. (1) inject the SI accumulators (2) AND 18

ILC-11-1 NRC Exam

19. Given the following plant conditions:

- The plant is operating at 50% RTP EOL while supporting MFP A maintenance.

- Rod Control is in MANUAL.

- The RO withdraws Bank D two steps for Tavg control.

- When the Rod Control switch is released, Bank D rods continue to move an additional three steps until stopped by performing the immediate actions of AOP-001, Malfunction of Reactor Control System.

Which ONE (1) of the following describes the effect on Reactor Power from Steady-State to Steady-State?

(Assume no additional operator actions have occurred.)

A. Remains stable.

B. Rise and stabilize at a value greater than 50% RTP.

C. Rise initially, then trends back to less than 50% RTP.

D. Rise initially, then trends back to approximately 50% RTP.

- t)cAtA\

19

ILC-11-1 NRC Exam

20. Given the following plant conditions:

- The plant is in Mode 6 with a core offload in progress.

- The CV Manipulator has just removed a fuel assembly from core location H-8 and is in transit to the CV upender.

- The CV manipulator operator accidently places the gripper switch to the DISENGAGE position before the fuel assembly is lowered into the CV upender.

- The fuel assembly releases from the gripper while in the full up position and lands on the CV upender and damages several fuel rods.

Which ONE (1) of the following describes the interlock(s) that failed to prevent this action?

A. ONLY the Gripper Lock Interlock.

B. ONLY the Gripper-Weight Indicator Interlock.

C. BOTH the Gripper-Weight Indicator AND the Hoist/Gripper Interlocks.

D. BOTH the Gripper-Weight Indicator AND the Gripper Lock Interlocks.

20

ILC-ii-1 NRC Exam

21. Given the following plant conditions:

- The plant is at 3% RTP with Tave at 549° F.

- A 50 gpm tube leak has been identified in A SIG.

Which ONE (1) of the following describes the appropriate actions that should be taken lAW AOP-035?

AOP-035, SIG Tube Leak GP-006, Normal Plant Shutdown From Power Operation to Hot Shutdown Supplement G, Steam Generator Isolation A. Shutdown the plant lAW GP-006 and then Isolate A S/G lAW AOP-035.

B. Isolate A S/G lAW AOP-035 and then commence a plant shutdown lAW GP-006.

C. Trip the reactor and go to PATH-2. Isolate A S/G lAW Supplement G concurrent with PATH-2.

D. Trip the reactor and go to PATH-i. Transition to PATH-2 and isolate A S/G lAW Supplement G concurrent with PATH-2.

21

ILC-11-1 NRC Exam

22. Given the following plant conditions:

- The plant is at 8% RTP with B T MFP under clearance for motor bearing repairs.

- The Operating crew has entered AOP-0i2, Partial Loss of Condenser Vacuum or Circulating Water Pump Trip due to rising Condenser Back Pressure.

- The Main Turbine has been manually tripped lAW AOP-0i2.

- A MFP is subsequently secured due to an identified ground.

Which ONE (1) of the following actions is required by AOP-007, Turbine Trip Below P-8?

A. Trip the Reactor and go to PATH-I.

B. Trip the Reactor and go to PATH-i while continuing with AOP-007.

C. Position the control rods to maintain Reactor power between 7% and 10%.

D. Position the control rods to reduce Reactor power to less than or equal to 3%.

22

ILC-11-1 NRC Exam

23. Given the following plant conditions:

- A Monitor Tank is currently at 40% and being released lAW OP-705, Waste Liquid Release and Recircu lation.

- The Inside AO reports a nonisolable leak on A Monitor Tank.

Which ONE (1) of the following identifies the correct actions lAW AOP-008, Accidental Release of Liquid Waste?

Stop the release and transfer contents of the A Monitor Tank to (1) to minimize leakage to (2)

A. (1) Monitor Tank B (2) storm drains B. (1) CVCS Holdup Tank (2) storm drains C. (1) Monitor Tank B (2) Aux Building Sump D. (1) CVCS Holdup Tank (2) Aux Building Sump 23

ILC-11-l NRC Exam

24. Given the following plant conditions:

- PATH-i has been entered.

- SI or RHR flow cannot be established.

Time CETC Temp RVLIS Full Range 1000 675°F 51%

1005 695°F 39%

1010 705°F 37%

1015 750°F 30%

1030 1000°F 29%

1045 1150°F 28%

1100 1205°F 25%

Based on the above indications, what is the earliest time at which entry conditions for FRP-C.1, Response to Inadequate Core Cooling, would be present?

A. 1005 B. 1010 C. 1015 D. 1100 24

ILC-11-1 NRC Exam

25. The crew is implementing EPP-8, Post-LOCA Cooldown and Depressurization, following a Small Break LOCA

- Containment pressure peaked at 3.8 psig.

- Steps have been taken to reduce SI flow by stopping C SI Pump.

- A SI Pump remains running.

After C SI pump is stopped the following plant conditions are observed:

- RCS subcooling is 32°F and lowering.

- PZR level is 22% and lowering.

Which ONE of the following; (1) identifies the actions that will be taken AND (2) why will this action be taken?

A. (1) Start additional Charging Pump(s).

(2) Due to adequate pressurizer level.

B. (1) Start both SI pumps.

(2) Due to low pressurizer level.

C. (1) Start additional Charging Pump(s).

(2) Due to low subcooling.

D. (1) Start both SI pumps.

(2) Due to low subcooling.

25

ILC-11-1 NRC Exam

26. Given the following plant conditions:

- A LOCA with a loss of off-site power has occurred.

- The supply breaker to MCC-6 tripped open prior to CV Spray Actuation.

- CV Pressure is 15 psig and both Containment Spray Pumps are operating.

Which ONE (1) of the following completes the statements below?

(1) is the status of the Containment Spray System AND (2) is the current status of the Component Cooling Water Pumps.

(Assume no local operator actions have been taken.)

A. (1) The discharge path is aligned from CV Spray Pump A ONLY.

(2) A CCW Pump is running.

B. (1) CV Spray Pumps A and B are providing spray flow.

(2) A CCW Pump is running.

C. (1) The discharge path is aligned from CV Spray Pump A ONLY.

(2) B and C CCW Pumps are secured.

D. (1) CV Spray Pumps A and B are providing spray flow.

(2) B and C CCW Pumps are secured.

26

ILC-11-1 NRC Exam

27. Which ONE (1) of the following identifies the operational concern associated with Containment Flooding?

Containment Flooding could lead to A. Submersion of the Reactor Coolant Drain Tank resulting in damage to the Gas Analyzer.

B. Critical system transmitter failures needed to ensure an orderly safe plant shutdown.

C. Submersion of CVC-200A, B, C, Letdown Orifice Isolations resulting in a loss of normal letdown capability.

D. Water potentially leaking through Containment Vessel Electrical Penetrations resulting in electrical shorts and/or grounds on components that are needed to ensure an orderly safe plant shutdown.

27

ILC-11-1 NRC Exam

28. Given the following plant conditions:

- The plant is at 50% RTP.

- FT-434 RCS LOOP Ci FLOW TRANSMITTER low pressure sensing line develops a leak to the CV atmosphere.

Which ONE (1) of the following describes the expected plant response to this event?

A. All Loop C flow channels read low.

B. All Loop C flow channels read high.

C. Flow indication will rise on ONLY the affected Loop C flow channel.

D. Flow indication will lower on ONLY the affected Loop C flow channel.

28

ILC-11-1 NRC Exam

29. Given the following plant conditions:

- The plant is in Mode 5.

- The RCS is solid with pressure being automatically maintained.

- A clearance error results in PZR Backup Group A Heaters becoming energized.

Which ONE (1) of the following describes the FIRST (INITIAL) response to the rising Pressurizer temperature and pressure?

(Assume NO operator actions.)

A. Annunciator APP-OO1-D6, LP LTDN LN HI PRESS, actuates.

B. Annunciator APP-OO1-E6, LP LTDN RELIEF HI TEMP, actuates.

C. Letdown flow rises as HCV-142, RHR TO LETDOWN & PURIFICATION FLOW CONTROL, opens.

D. Letdown flow rises as PCV-145, LOW PRESSURE LETDOWN PRESSURE CONTROL VALVE, opens.

29

ILC-11-1 NRC Exam

30. Given the following plant conditions:

- The plant is operating at 100% RTP.

- C Charging Pump is currently running in Manual at minimum speed.

- A Charging Pump is running in MANUAL at 35% demand during the performance of OP-301-1, Section 8.4.7, Charging Pump Break-In After Maintenance.

- CVC-283C, Charging Pump A Discharge Relief, has lifted and has not reseated.

Which ONE (1) of the following identifies the impact on Seal Injection flow(s) AND how would this malfunction be addressed by AOP-01 8, Reactor Coolant Pump Abnormal Conditions?

Seal Injection flows will lower to (1) and AOP-018 directs the operators to (2)

A. (1) ZERO flow (2) Isolate letdown, secure all Charging Pumps, manually isolate A Charging pump.

B. (1) MINIMUM flow (- 6 gpm)

(2) Isolate letdown, secure all Charging Pumps, manually isolate A Charging pump.

C. (1) ZERO flow (2) Stop A Charging Pump and adjust the speed of C Charging Pump to restore normal seal injection flows.

D. (1) MINIMUM flow (- 6 gpm)

(2) Stop A Charging Pump and adjust the speed of C Charging Pump to restore normal seal injection flows.

30

ILC-11-1 NRC Exam

31. Given the following plant conditions:

- The plant is in Mode 6.

- RHR Train A is in service.

- FCV-605, RHR HX BYPASS, is set to maintain 3400 GPM.

- HCV-758, RHR HX OUTLET FLOW TO COLD LEGS, demand position set at 30%.

- The Instrument Air supply line to RHR Heat Exchanger Flow Control Valve HCV-758 becomes severed and is completely detached.

- No other air operated valves are impacted by the failure.

Which ONE (1) of the following identifies the changes in TR-604, PEN 2 RHR HX OUTLET TEMP, from the initial steady state conditions AND the RCS temperature at which refueling operations may continue lAW GP-01 0, Refueling?

RHR HX OUTLET TEMP RCS Temp for Refueling A. Higher 135°F B. Higher 150°F C. Lower 135°F D. Lower 150°F 31

ILC-11-1 NRC Exam

32. Given the following plant conditions:

- Plant is shutdown for refueling.

- GP-009-1, Filling the Refueling Cavity with Fuel in the Reactor Vessel, is in progress.

- Safety Injection Pumps A and C are running.

- SI-866A, LOOP 3 HOT LEG, is full open and Sl-866B, LOOP 2 HOT LEG, is being opened via its Control Power Switch to increase cavity fill rate.

- Safety Injection Pump discharge pressure is at 530 psig and lowering.

Which ONE (1) of the following identifies the required actions to be taken lAW GP-009-1 to control the Safety Injection pump discharge pressure?

A. Close Sl-856A OR Sl-856B, SI Pump Recirc., valve.

B. Place Sl-866B Control Power Switch to NORMAL.

C. Place SI-866B Control Power Switch to DEFEAT.

D. Place Sl-866B Control Switch to CLOSE.

32

ILC-11-1 NRC Exam

33. Given the following plant conditions:

- LOCA recovery is in progress and RWST Level has lowered below 27%.

- The crew has transitioned to EPP-9, Transfer to Cold Leg Recirculation.

- While aligning the CV Sump To RHR valves, Sl-860A, CV Sump to RHR, fails to open and remains in the closed position.

Which ONE (1) of the following describes the impact on the ability to provide cold leg recirculation?

A. Both RHR pumps are available with full flow capability. Remain in EPP-9, Transfer to Cold Leg Recirculation.

B. ONLY B RHR pump is available for cold leg recirculation. Remain in EPP-9, Transfer to Cold Leg Recirculation.

C. ONLY B RHR pump is available for cold leg recirculation. Transition to EPP-15, Loss of Emergency Coolant Recirculation.

D. Both RHR pumps are available with reduced flow capability. Transition to EPP-15, Loss of Emergency Coolant Recirculation.

33

ILC-11-1 NRC Exam

34. The plant is at 100% RTP.

The following indications are reported by the RO:

- Tl-471, PRT Temperature is trending up over a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and is now at 148°F.

- P1-472, PRT Pressure is trending up and is now at 4 psig.

- PZR PRV RC-551A, B and C Acoustic Monitor Lights are extinguished.

Which ONE (1) of the following valve leakage is causing the given conditions?

A. PCV-456, PZR PORV, is leaking by its seat.

B. RC-551A, Pressurizer Safety Valve, is leaking by its seat.

C. CVC-382, RCP Seal Return Line Relief, is leaking by its seat.

D. CC-722A, RCP A Thermal Barrier Outlet Relief, is leaking by its seat.

34

ILC-11-1 NRC Exam

35. Given the following plant conditions:

- Plant is at 100% RTP.

- Grid disturbance results in a load rejection.

- PCV-456 momentarily lifts due to the load rejection but does not fully reseat.

- The operating crew has closed RC-535 to isolate PCV-456 leakage.

- PRT pressure has been restored lAW APP-003-C3.

- APP-003-B3, PRT HI TEMP, is illuminated.

- PRT Temperature is currently 155°F.

Which ONE of the following completes the statements below?

The PRT rupture disc would have actuated if pressure reached (1) in the PRT.

lAW APP-003-B3, PRT HI TEMP, the PRT temperature will be lowered by (2)

A. (1) 100 psia (2) alternately adding primary water to the PRT and draining the PRT.

B. (1)l00psia (2) simultaneously adding primary water while draining the PRT.

C. (1) 100 psig (2) alternately adding primary water to the PRT and draining the PRT.

D. (1) 100 psig (2) simultaneously adding primary water while draining the PRT.

35

ILC-11-1 NRC Exam

36. Given the following plant conditions:

- MODE I at 100% RTP.

- B CCW pump is in service.

- The normal supply breaker to 480V Bus E-1 Trips Open.

Which ONE (1) of the following identifies the status of the CCW pumps TWO (2) minutes after the event?

A. All CCW Pumps started on Low Pressure B. ONLY A CCW Pump started on Low Pressure B and C CCW Pumps started on Blackout Sequencer C. ONLY C CCW Pump started on Low Pressure B CCW Pump started on Blackout Sequencer D. A and C CCW Pumps started on Low Pressure B CCW Pump started on Blackout Sequencer 36

ILC-11-1 NRC Exam

37. A pressurizer code safety valve has indications of leakage.

The following indications exist:

- Pressurizer pressure is 2225 psig and stable.

- Safety Valve tailpipe temperature indicates 231°F and rising.

- PRT pressure is 6 psig and rising 1 psi every 10 minutes Which ONE (1) of the following completes the statement below?

The temperature downstream of the safety valves corresponds to A. the PRT saturation pressure because of the loss of enthalpy of a throttling process.

B. the PRT saturation pressure because of the constant enthalpy of a throttling process.

C. the saturation pressure of the presssurizer steam space because of the loss of enthalpy of a throttling process.

D. the saturation pressure of the presssurizer steam space because of the constant enthalpy of a throttling process.

37

ILC-11-1 NRC Exam

38. The plant is at 100% RTP and the following occurs:

- The PZR pressure master controller (PC-444J) is failing HIGH.

- The PZR spray valves are fully OPEN.

- The PZR PORVs are CLOSED.

Which ONE (1) of the following identifies the value of the controller output (PC-444J) for this condition?

A. 75%

B. 70%

C. 65%

D. 60%

38

ILC-11-1 NRC Exam

39. The plant is at 100% RTP when A Condensate Pump trips due to electrical fault.

Which ONE (1) of the following completes the statement below?

The FIRST reactor trip signal will be generated as soon as bistable lights for (Assume no operator action.)

A. SC NO. 2 LO-LO Level LC484A1 AND SG NO. 2 LO-LO Level LC485A1 Illuminate.

B. SC NO. 2 LO-LO Level LC484A1 OR SC NO. 2 LO-LO Level LC485A1 Illuminate.

C. SG NO. 2 LO Level LC484B1 AND SC NO. 2 LO Level LC485B1 Illuminate.

D. SC NO. 2 LO Level LC484B1 OR SG NO. 2 LO Level LC485B1 Illuminate.

39

ILC-11-1 NRC Exam

40. Containment Spray Actuation requires (1) channels in (2) sets (or trains) of logic.

1 A. 2of3 lof2 B. 2of3 2of2 C. 2of4 lof2 D. 2of4 2of2 40

ILC-11-1 NRC Exam

41. Given the following Containment temperature indications:

Time TI-950B ERFIS Point CVT0001 1100 118.0°F 118.3°F 1200 118.5°F 118.7°F 1300 119.0°F 119.2°F 1400 120.5°F 119.8°F 1500 121.0°F 120.2°F 1600 121.5°F 120.6°F (RTGB) Tl-950B Containment Average Temperature

-

(ERFIS) CVT0001 Containment Average Air Temperature

-

Which ONE (1) of the following identifies when ITS LCO 3.6.5, Containment Air Temperature, must be entered lAW PLP-118, Hot Weather Operations?

A. 1200 B. 1300 C. 1400 D. 1500 41

ILC-11-1 NRC Exam

42. Given the following plant conditions:

- Plant is at 100% RTP.

- Breaker 52/17, START-UP TRANSFORMER TO 4KV BUS 3, trips.

- A Large Break LOCA occurs 20 seconds later.

Which ONE (1) of the following identifies the configuration of the power supplies to CV Spray Pumps A and B?

CV Spray Pump A powered from (1) and CV Spray Pump B powered from (2)

A. (1)SUT (2) B EDG B. (1)SUT (2) SUT C (1)AEDG (2) B EDG D. (1) A EDG (2) SUT 42

ILC-11-1 NRC Exam

43. Given the following plant conditions:

- The plant is at 100% RTP.

- The OAO reports a steam leak near the Main Steam Isolation Valves.

- The following indications are noted in the Control Room:

- Power Range Nuclear Instruments are rising.

- Tavg is lowering.

- Steam flow and feed flow have risen.

- Power Limit Warning alarm on ERFIS has been received.

- Reactor power is 100.3% and slowly rising.

Which ONE(1) of the following identifies both:

(1) the time in core life that will result in the largest reactivity excursion AND (2) the required operator actions to clear the Power Limit Warning alarm?

A. (1)BOL (2) reduce power by inserting control rods lAW OP-i 06, Normal Plant Operations.

B. (1)BOL (2) reduce power by using the Valve Position Limiter lAW OMM-00i-2, Shift Routines and Operating Practices.

C. (1)EOL (2) reduce power by inserting control rods lAW OP-106, Normal Plant Operations.

D. (1)EOL (2) reduce power by using the Valve Position Limiter lAW OMM-001-2, Shift Routines and Operating Practices.

43

ILC-11-1 NRC Exam

44. Given the following plant conditions:

- A Steam Generator Tube Rupture (SGTR) is in progress.

- The crew is in PATH-2 and are commencing the RCS cooldown to target temperature.

- The procedure has directed to Dump Steam to the condenser from intact S/Gs at the maximum rate.

Which ONE (1) of the following describes the term Maximum Rate as specified in the NOTE in PATH-2?

As fast as possible A. while not exceeding the High Steam Line AP limit.

B. while not exceeding Temp Limit A of the INTEGRITY Critical Safety Function Status Tree.

C. while keeping steam flow less than the High Steam Flow Main Steamline Isolation setpoint.

D. while keeping steam pressure above the Low Steamline Pressure Safety Injection setpoi nt.

44

ILC-11-1 NRC Exam

45. Given the following plant conditions:

- The plant is at 60% RTP.

Which ONE (1) of the following describes the expected SIG Narrow Range Levels and the basis for that level?

The S/Gs will indicate (1) and the basis for this level is to (2)

A. (1)39%

(2) maintain sufficient level to prevent a reactor trip from a 50% load rejection and is low enough to minimize moisture carryover.

B. (1)39%

(2) maintain the mass in the SIG great enough to stay above the reactor trip setpoints and minimizes the consequences of a steam break accident.

C. (1)52%

(2) maintain sufficient level to prevent a reactor trip from a 50% load rejection and is low enough to minimize moisture carryover.

D. (1)52%

(2) maintain the mass in the S/G great enough to stay above the reactor trip setpoints and minimizes the consequences of a steam break accident.

45

ILC-11-1 NRC Exam

46. B MFP is OOS for Maintenance and the following occurs:

- The Reactor was manually Tripped while operating at 20% RTP due to a trip of A MFP

- PZR Level is 20% and slowly lowering.

Tave is 545°F and lowering.

- RCS Pressure is 2050 psig and lowering.

- Steam Generator Blowdown is Isolated.

- S/G levels are as follows:

- A SIG Narrow Range level is 40% and slowly rising.

- B S/G Narrow Range level is 41% and slowly rising.

- C S/G Narrow Range level is 45% and slowly rising.

Which ONE (1) of the following provides the action(s) that are required to be taken next lAW EPP-4, Reactor Trip Response?

A. Initiate Safety Injection.

B. Close MSIVs & MSIV Bypasses.

C. Borate to Cold Shutdown Boron.

D. Reduce Auxiliary Feedwater Flow.

46

ILC.-11--1 NRC Exam

47. Which ONE (1) of the following describes the 4160 Volt power supplies to the A and B RCPs2 RCP A RCP B A. Busi Bus2 B. Bus2 Bus4 C. Busi Bus4 D. Bus2 Busi 47

ILC-11-1 NRC Exam

48. Given the following plant conditions:

- The plant is at 100% RTP.

- APP-036-D1, BATT CHARGER A/A-I TROUBLE, annunciated.

- OAO reports the following indications from Battery Charger A-I:

- +40 Volts on the Ground Detection Voltmeter.

- 140 Volts DC on Charger Voltage.

What are the adverse impacts of the reported indications and the actions required to be taken lAW APP-036-D1?

A. Normally non-energized portions of switchgear may be energized.

Isolate A Batteries by Aligning Battery Charger A to carry the bus load.

B. Normally non-energized portions of switchgear may be energized.

Swap Battery Chargers to place Battery Charger A In-service.

C. Over-voltage condition could damage A Batteries.

Isolate A Batteries by Aligning Battery Charger A to carry the bus load.

D. Over-voltage condition could damage A Batteries.

Swap Battery Chargers to place Battery Charger A In-service.

48

ILC-11-1 NRC Exam

49. Given the following plant conditions:

- The plant is in Mode 3.

- A fire has occurred in DC Distribution Panel B.

- The panel has been de-energized.

Which ONE (1) of the following identifies the effect on the Electrical Distribution System?

Control Power lost to 4160 V Busses....

A. 1 & 2 and cannot be restored.

B. I & 2. Control Power can be restored using a safety switch in the 4160 V Switchgear Room.

C. 3 & 4 and cannot be restored.

D. 3 & 4. Control Power can be restored using a safety switch in the 4160 V Switchgear Room.

49

ILC-11-1 NRC Exam

50. Given the following plant conditions:

- Plant is at 100% RTP.

- An Electrician accidently opens breaker 52/1 8B, Normal Supply Breaker for E-1.

- A EDG starts on UV and energizes Emergency Bus E-1.

Which ONE (1) of the following identifies the effect of stopping A EDG from the RTGB while it is loaded on the isolated Emergency Bus E-1?

After taking the A EDG Control switch on the RTGB to STOP the A EDG will A. trip and must be manually reset prior to placing back in service.

B. maintain its current speed and voltage due to Shutdown Control Logic having a run priority.

C. attempt to shutdown but will restart due to the Shutdown Control Logic having a run priority.

D. maintain its current speed and voltage due to the App. R Isolation Switches being in the ISOLATE position.

50

ILC-11-1 NRC Exam

51. Which ONE(1) of the following describes the basis for initiating a Containment Ventilation Isolation signal during the performance of FRP-S.1, Response to Nuclear Power Generation I ATWS?

To isolate A. non-essential containment ventilation penetrations to prevent potential release of radioactive materials from containment.

B. R-11 and R-12, CV Air and Plant Stack Monitors, to prevent potential release of radioactive materials from containment.

C. non-essential containment ventilation penetrations due to delayed response time of R-11 and R-12 during an ATWS.

D. R-11 and R-12, CV Air and Plant Stack Monitors, due to delayed response time of R-11 and R-12 during an ATWS.

51

ILC-11-1 NRC Exam

52. SW-739, CCW HEAT EXCHANGER A RETURN, and SW-740, CCW HEAT EXCHANGER B RETURN, are throttled in the closed direction.

Which ONE(1) of the following completes the statement below?

This will cause Service Water Header Pressure to (1) and CCW Heat Exchanger OutletTemperatureto (2)

A. (1) lower (2) lower B. (1) lower (2) rise C. (1) rise (2) lower D. (1) rise (2) rise 52

ILC-11-1 NRC Exam

53. Which ONE(1) of the following identifies the fail position of TCV-144, NON-REG HX OUTLET TEMP CONTROL, valve on a loss of Instrument Air AND the effect this will have on reactivity?

TCV-144 will fail (1) AND this will insert (2) reactivity.

A. (1) OPEN (2) Positive B. (1) OPEN (2) Negative C. (1) CLOSED (2) Positive D. (1) CLOSED (2) Negative 53

ILC-11-1 NRC Exam

54. Given the following plant conditions:

- The plant is at 100% RTP.

- APP-002-B7, CV NAR RANGE HI/LO PRESS illuminates.

- CV Pressure indicates -0.4 psig, lowering.

Which ONE (1) of the following describes the action necessary to clear the alarm lAW OP-921, Containment Air Handling?

Open the Containment A. Pressure Relief Valves V12-l0 and V12-11 ONLY.

B. Pressure Relief Valves Vi 2-10 and V12-11 AND lower Service Water flow to the Containment HVH units.

C. Vacuum Relief Valves VI 2-12 and Vi 2-13 ONLY.

D. Vacuum Relief Valves Vi 2-12 and VI 2-13 AND lower Service Water flow to the Containment HVH units.

54

ILC-11-1 NRC Exam

55. Given the following plant conditions:

- The RCS is at 275° F.

- All RCPs are running.

- CVC-381, RCP Seal Return Isolation, has been declared inoperable due to improperly set torque switches.

Which ONE (1) of the following statements is correct lAW the RNP ITS?

A. Close CVC-381 ONLY.

B. Close and deactivate CVC-381.

C. CVC-381 operability is NOT required for the given plant conditions.

D. Close CVC-380, Seal Water Return Filter Inlet, AND station a Dedicated Operator lAW OP-923, Containment Integrity.

55

ILC-11-1 NRC Exam

56. Plant is at 100% RTP.

Which ONE (1) of the following describes an INITIAL effect of one control rod dropping fully into the core?

This will cause the Charging Pump Speed to initially (1) due to the Pressurizer Reference Level (2)

A. (1) lower (2) lowering B. (1) rise (2) lowering C. (1) lower (2) rising D. (1) rise (2) rising 56

ILC-11-1 NRC Exam

57. Given the following plant conditions:

- The plant is at 100% RTP.

- A loss of Inverter A occurs.

Which ONE (1) of the following identifies ALL the excore Nuclear Instrument channels that have lost power?

A. N-41 and N-51 B. N-43 and N-52 C. N-32, N-36 and N-42 D. N-31, N-35 and N-41 57

ILC-11-1 NRC Exam

58. The plant is at 50% RTP when the steam pressure input into the A SIG Level Control System fails high slowly.

Which ONE (1) of the following actions will occur?

Initially, feedwater flow to the A SIG will A. lower due to lower indicated steam flow.

The level error signal will NOT result in a rise in feedwater flow.

B. lower due to lower indicated steam flow.

Eventually, the level error signal will result in a rise in feedwater flow.

C. rise due to higher indicated steam flow.

The level error signal will NOT result in a reduction of feedwater flow.

D. rise due to higher indicated steam flow.

Eventually, the level error signal will result in a reduction of feedwater flow.

58

ILC-11-1 NRC Exam

59. Which ONE (1) of the following identifies the major source of hydrogen following a design basis LOCA with Inadequate Core Cooling AND is listed in the UFSAR criteria for ECCS performance following a LOCA?

A. Zirc-water reaction.

B. Radiolysis of RCS water.

C. Radiolysis of containment sump water.

D. Degradation of non-metallic insulation material.

59

ILC-11-1 NRC Exam

60. Given the following plant conditions:

- Plant is currently in Mode 6 during a scheduled refueling outage.

- Core re-load is in progress.

- The alarming radiation monitor on the refueling bridge loses power.

Which ONE (1) of the following identifies the impact to refueling operations and the proper actions of the refueling crew?

A. Fuel movement may continue as long as R-2, CV AREA, remains operable.

Replace the radiation monitor with an operable monitor with an alarm setpoint of 15 mr/hr.

B. Fuel movement may continue as long as R-2, CV AREA, remains operable.

Replace the radiation monitor with an operable monitor with an alarm setpoint of 25 mr/hr.

C. Fuel movement must be suspended until the radiation monitor is replaced.

Replace the radiation monitor with an operable monitor with an alarm setpoint of 15 mr/hr.

D. Fuel movement must be suspended until the radiation monitor is replaced.

Replace the radiation monitor with an operable monitor with an alarm setpoint of 25 mr/hr.

60

ILC-11-1 NRC Exam

61. Which ONE (1) of the following action(s) is necessary to utilize the steam dumps to cooldown the plant lAW GP-007, Plant Cooldown from Hot Shutdown to Cold Shutdown?

A. Momentarily place the Steam Dump Mode Switch to RESET with Tave less than 543° F.

B. Momentarily place the Steam Dump Mode Switch to RESET with Tave less than 547°F.

C. Bypass the Low Tavg interlock by momentarily selecting BYPASS TAVG INTERLOCK on the Steam Dump Control switch with Tavg less than 543° F.

D. Bypass the Low Tavg interlock by momentarily selecting BYPASS TAVG INTERLOCK on the Steam Dump Control switch with Tavg less than 547° F.

61

ILC-1 1-1 NRC Exam

62. Given the following plant conditions:

- Plant is at 100% RTP.

- Waste Gas Release of A Waste Gas Decay Tank is in progress.

- APP-010-B7, HVE-2A12B AIR FLOW LOST/OVLD, is received.

- HVE-2A has tripped.

Which ONE (1) of the following describes the actions required by the operator AND the potential plant effect of a loss of the Reactor Auxiliary Building Exhaust Fan?

The operator will (1) AND the possible effect of a loss of Reactor Auxiliary Building Exhaust Fans is I has (2)

A. (1) have to manually start HVE-2B (2) an unmonitored release from the Reactor Auxiliary Building.

B. (1) verify that HVE-2B starts automatically (2) an unmonitored release from the Reactor Auxiliary Building.

C. (1) have to manually start HVE-2B (2) no impact since HVE-5A or HVE-5B will automatically start.

D. (1) verify that the HVE-2B starts automatically (2) no impact since HVE-5A or HVE-5B will automatically start.

62

ILC.-11-1 NRC Exam

63. Given the following plant conditions:

- Plant is stable at 60% RTP.

- Charging pumps A & C are in service.

- Letdown orifice valves CVC-200A and CVC-200B are open.

- A valid alarm has been received on R-9, LETDOWN LINE AREA.

Which ONE (1) of the following identifies the correct operator response to a valid alarm on R-9, LETDOWN LINE AREA, lAW AOP-005, Radiation Monitoring System?

A. Shut CVC-200B to minimize letdown flow.

B. Isolate letdown flow by closing LCV-460A / B.

C. Secure Charging pump C and lower Charging pump A to minimal flow.

D. Dispatch an operator to Loose Parts Monitoring Cabinet to monitor for abnormal indications.

63

ILC-11-1 NRC Exam

64. A plant shutdown is in progress with the plant at 20% RTP with the steam dumps in STEAM PRESSURE mode.

- C Circulating Water Pump is Out of Service for Maintenance.

- A and B Circulating Water Pumps are in operation.

- B Circulating Water Pump trips and V6-50B, CIRC WATER PMP B DISCH, remains full open and will not close.

What impact will this have on Condenser Vacuum and Steam Dump Operation AND what actions are required lAW AOP-012, Partial Loss of Condenser Vacuum or Circulating Water Pump Trip?

Condenser Vacuum will A. rapidly degrade. Steam dump operation may continue as long as ONE (1)

Circulating Water Pump is running and Vacuum does not go below 19.7 Hg.

Dispatch an operator to manually close V6-50B.

B. rapidly degrade. Steam dump operation may continue as long as ONE (1)

Circulating Water Pump is running and Vacuum does not go below 18 Hg.

Manually trip the turbine and go to AOP-007, Turbine Trip Below P-8.

C. slowly degrade. Steam dump operation may continue as long as ONE (1)

Circulating Water Pump is running and Vacuum does not go below 18 Hg.

Dispatch an operator to manually close V6-50B.

D. slowly degrade. Steam dump operation may continue as long as ONE (1)

Circulating Water Pump is running and Vacuum does not go below 19.7 Hg.

Manually trip the turbine and go to AOP-007, Turbine Trip Below P-8.

64

ILC-11-1 NRC Exam

65. Which ONE (1) of the following lists the location(s) that the Motor Driven Fire Pump (MDFP) and the Engine Driven Fire Pump (EDFP) can be manually started?

The MDFP can be started at the (1) AND the EDFP can be started at the (2)

A. (1) Unit 2 Control Room AND Unit 2 Intake Structure.

(2) Unit 2 Intake Structure ONLY.

B. (1) Unit 2 Control Room AND Unit 2 Intake Structure.

(2) Unit 2 Control Room AND Unit 2 Intake Structure.

C. (1) Unit 2 Control Room ONLY.

(2) Unit 2 Intake Structure ONLY.

D. (1) Unit 2 Control Room ONLY.

(2) Unit 2 Control Room AND Unit 2 Intake Structure.

65

ILC-11-1 NRC Exam

66. Given the following plant conditions:

- The plant was at 42% RTP and rising lAW GP-005, Power Operation.

- A loss of feedwater occurs.

- All three SIG NR levels are at 0%.

- It is now 29 seconds later and the Reactor Trip Breakers have remained closed.

Which ONE (1) of the following is the expected response of the ATWS Mitigation System Actuation Circuitry (AMSAC) and the purpose of those actions?

AMSAC will start (1) and the purpose of AMSAC is to prevent (2)

A. (1) ONLY MDAFW pumps (2) exceeding the kW/ft limit of the fuel rods during an ATWS condition.

B. (1) ONLY MDAFW pumps (2) prevent voiding in the RCS during an ATWS condition and a loss of feedwater.

C. (1)ALLAFWpump5 (2) exceeding the kW/ft limit of the fuel rods during an ATWS condition.

D. (1)ALLAFWpump5 (2) voiding in the RCS during an ATWS condition and a loss of feedwater.

66

ILC-11-1 NRC Exam

67. In order to maintain an active license and qualification, a Reactor Operator must, at a MINIMUM, meet the following requirements:

A. Stand a minimum of four 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts per calendar quarter as RO.

Participate in LOCT and be evaluated as an RO or BOP in LOCT.

Have a current annual medical exam.

B. Stand a minimum of four 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts per calendar quarter as RO or BOP.

Participate in LOCT and be evaluated as an RO in LOCT.

Have a current biennial medical exam.

C. Stand a minimum of five 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts per calendar quarter as RO.

Participate in LOCT and be evaluated as an RO or BOP in LOCT.

Have a current annual medical exam.

D. Stand a minimum of five 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts per calendar quarter as RO or BOP.

Participate in LOCT and be evaluated as an RO in LOCT.

Have a current biennial medical exam.

67

ILC-11-1 NRC Exam

68. With the plant at 100% RTP what power level will be acceptable for performance of OST-206, Comprehensive Flow Test for the Steam Driven Auxiliary Feedwater Pump and what effects will forward flowing the SIG have on Reactor Power?

In accordance with OST-206, Reactor Power must be no greater than A. 99%

Running the SDAFW Pump results in a rise in reactor power solely due to the additional feedwater flow.

B. 98%

Running the SDAFW Pump results in a rise in reactor power due to using steam to run the pump and cooler feedwater being supplied to the SIG5.

C. 99%

Running the SDAFW Pump results in a rise in reactor power due to using steam to run the pump and cooler feedwater being supplied to the S/Gs.

D. 98%

Running the SDAFW Pump results in a rise in reactor power solely due to the additional feedwater flow.

68

ILC-11-1 NRC Exam

69. Given the following information:

- Plant is at 100% RTP.

- The current plant Risk Profile (EOOS profile) is an elevated GREEN due to scheduled repairs to Reactor Protection related components. These repairs are in-progress and will take 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to restore, test and return to service.

An Electrical System Engineer has coordinated with the Work Week Coordinator and Plant Management to inspect the fuses and wiring inside 480V-E1 Compartment 1 8A, PTS & METERING EQUIPMENT to resolve a recent Vendor Notice as an Emergent Work Activity.

Which ONE (1) of the following describes the actions that must be taken prior to authorizing the Emergent Work Activity while the Reactor Protection work continues?

A. EOOS Risk Assessment will NOT be performed since opening the 480V-E1 Compartment door does NOT render any equipment unavailable. EOOS Risk Assessment is not necessary. Work may be released.

B. EOOS Risk Assessment will be performed assuming that 480V-E1 will be made unavailable. IF the assessment results in a YELLOW risk condition THEN the emergent work SHALL NOT be released.

C. EOOS Risk Assessment will be performed assuming that 480V-E1 will be made unavailable. IF the assessment results in an ORANGE risk condition THEN the emergent work SHALL NOT be released.

D. EOOS Risk Assessment will be performed assuming that 480V-E1 will be made unavailable. IF the assessment results in an ORANGE risk condition THEN the work may be released with SM approval.

69

ILC-11-1 NRC Exam

70. Given the following plant conditions:

- The plant is in Mode 1.

Which ONE (1) of the following sets of conditions represents a violation of a Technical Specification Safety Limit and required action lAW Technical Specifications?

(Reference Provided)

A. RTP - 10%, PZR Pressure 2350 psig, RCS Highest Cold Leg Temp 650°F

- -

Restore compliance and be in Mode 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

B. RTP 80%, PZR Pressure 2250 psig, RCS Highest Cold Leg Temp 640°F

- - -

Restore compliance and be in Mode 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

C. RTP - 10%, PZR Pressure 2350 psig, RCS Highest Cold Leg Temp 650°F

- -

Restore compliance within 5 minutes.

D. RTP 80%, PZR Pressure 2250 psig, RCS Highest Cold Leg Temp 640°F

- - -

Restore compliance within 5 minutes.

70

ILC-11-1 NRC Exam

71. What Technical Specification OPERATIONAL MODE is the plant in with RCS temperature being maintained at 380° F AND how many Safety Injection Pump(s) are required to be operable?

The plant is in Mode (1) AND there must be at least (2) Safety Injection Pump(s) operable without entering a TS Action Statement.

A. (1)3 (2) 1 B. (1)4 (2) 1 C. (1)3 (2) 2 D. (1)4 (2) 2 71

ILC-11-1 NRC Exam

72. Given the following plant conditions:

- A fuel handling accident occurs in containment and an evacuation is ordered via a PA announcement.

- R-14C, NG-LO, is reading normal with a steady reading.

- R-1 1 and R-1 2, Containment Particulate and Gas Radiation Monitors, indications are showing a slight rising trend.

- The Equipment Hatch is removed.

Which ONE (1) of the following is an action to be taken to mitigate the consequences of this event lAW AOP-013, FUEL HANDLING ACCIDENT?

A. Verify Control Room Ventilation System shifted to Emergency Recirculation Mode.

B. Place HVE-3 and HVE-4, CV Iodine RMVL Fan, in the PREPURGE position.

C. Place the Upper Fuel Handling Building Ventilation System in service.

D. Verify and maintain the CV Purge secured.

72

ILC-11-1 NRC Exam

73. Given the following:

- A Progress Energy Mechanic has been assigned to repack a valve.

- Projected dose rate in the area is 500 mR/hr.

- The Mechanic has a current yearly dose of 0.5 Rem TEDE.

What is the MAXIMUM time that the mechanic can work on the valve before reaching the Progress Energy Annual Administrative Dose Limit?

A. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> C. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> D. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> 73

ILC-11-1 NRC Exam

74. The plant was at 100% RTP when a LOCA occurred. The crew was implementing PATH-I when a loss of offsite power occurred due to an internal failure in the Startup Transformer.

- Due to several equipment malfunctions, the following conditions exist:

- A SIG N/R level is 10%, AFW flow is 110 gpm.

- B SIG N/R level is 12%, AFW flow is 105 gpm.

- C SIG N/R level is 13%, AFW flow is 110 gpm.

- RCS pressure is 100 psig and lowering.

- Core exit thermocouples are 708°F.

- RVLIS Full Range is 43%.

- Containment pressure is 41 psig and lowering.

- Both CV spray pumps have tripped and cannot be restarted.

Which ONE (1) of the following identifies the proper procedure that will be entered based on priority of the procedures? (Assume that monitoring of CSFSTs is in effect.)

A. FRP-H.1, Response to Loss of Secondary Heat Sink.

B. FRP-J.1, Response to High Containment Pressure.

C. FRP-C.1, Response to Inadequate Core Cooling.

D. FRP-C.2, Response to Degraded Core Cooling.

74

ILC-11-1 NRC Exam

75. Which ONE(1) of the following identifies the mitigation strategy of EPP1 2, Post-SGTR Cooldown Using Backfill?

EPP-12 cools down and depressurizes the plant to Cold Shutdown conditions and A. cools the ruptured SIG by filling to 85% to 91% WR level.

B. cools the ruptured SIG by steaming with the steam line PORV.

C. depressurizes the ruptured SIG by draining the ruptured SIG through SIG blowdown.

D. depressurizes the ruptured SIG by draining the ruptured SIG through the ruptured tube(s).

75

ILC-ii-1 NRC Exam

76. Given the following plant conditions:

- The Unit is shutdown following a reactor trip.

- The crew has transitioned to EPP-4, REACTOR TRIP RESPONSE.

- Foldout A is in effect.

- RCS Tavg is 602°F and stable.

- RCS Pressure is 1985 psig and lowering.

- Pressurizer level is 72% and rising.

- Containment Pressure is 0.2 psig and stable.

- PZR PORV PCV-456 indicates intermediate (Red / Green).

- PZR PORV BLOCK RC-535 MOV breaker tripped while attempting to close from the RTGB.

Which ONE (1) of the following states the actions to be taken to mitigate the given plant conditions?

A. Trip all RCPs AND Continue in EPP-4.

B. Trip all RCPs AND Go to PATH-i, Entry Point A.

C. Initiate Safety Injection AND Go to PATH-i, Entry Point A.

D. Initiate Safety Injection AND Go to PATH-i, Entry Point C.

76

ILC-11-1 NRC Exam

77. Given the following plant conditions:

- The plant was at 205°F and RHR Core Cooling was in service when a loss of Instrument Air occurred.

- Actions have been taken up to the point where one RHR Pump has been started and RHR flow re-established.

Which ONE (1) of the following completes the statements below?

FC-605, RHR HX BYPASS FLOW Controller, will be adjusted to obtain (1) and HIC-758, RHR HX DISCH FLOW, will be adjusted to achieve desired cooling lAW (2)

A. (1)3lOOgpm (2) AOP-017, Loss of Instrument Air.

B. (1)3lOOgpm (2) AOP-020, Loss of Residual Heat Removal (Shutdown Cooling).

C. (1)4000gpm (2) AOP-01 7, Loss of Instrument Air.

D. (1) 4000 gpm (2) AOP-020, Loss of Residual Heat Removal (Shutdown Cooling).

77

ILC-Il-1 NRC Exam

78. Given the following plant conditions:

- The Unit was at 30% RTP.

- A EDG is under clearance.

- A tornado touches down in the switchyard and caused a Phase Differential on the Main Generator.

- The SUT is destroyed by a tornadic missile.

Which ONE (1) of the following identifies the required implementation of procedures for this event?

Enter....

A. EPP-i, Loss of All AC Power, ---> EPP-22, Energizing Plant Equipment using the DSDG, to energize MCC-5.

B. EPP-I, Loss of All AC Power, ---> EPP-25, Energizing Supplemental Plant Equipment using the DSDG, to energize MCC-5.

C. PATH-I ---> EPP-25, Energizing Supplemental Plant Equipment using the DSDG, to energize MCC-5 ---> EPP-4, Reactor Trip Response.

D. PATH-i ---> EPP-22, Energizing Plant Equipment using the DSDG, to energize MCC-5 ---> EPP-4, Reactor Trip Response.

78

ILC-11-1 NRC Exam

79. Given the following plant conditions:

- The plant is in Mode 5.

- The RCS is in solid plant operations.

- Annunciator APP-002-E7, INST AIR CMPR D Trip alarms.

- Annunciator APP-002-F2, INST AIR HDR LO PRESS alarms.

- Instrument Air pressure indicated on the RTGB is 80 psig, lowering rapidly.

- RCS temperature is currently at 180°F and rising at 0.2°F/mm.

Which ONE (1) of the following completes the statement below?

(1) is the cause of the loss of instrument air and (2) is the required actions that mitigate these plant conditions.

A. (1) IA-3834, D Instrument Air Dryer Relief, lifting and not reseating (2) Transition to AOP-020, Loss of Residual Heat Removal, while continuing in AOP-017, Loss of Instrument Air, B. (1) Rupture of IA piping in Pipe Alley (2) Exit AOP-017, Loss of Instrument Air, and Transition to AOP-020, Loss of Residual Heat Removal, C. (1) lA-3834, D Instrument Air Dryer Relief, lifting and not reseating (2) Exit AOP-01 7, Loss of Instrument Air, and Transition to AOP-020, Loss of Residual Heat Removal, D. (1) Rupture of IA piping in Pipe Alley (2) Transition to AOP-020, Loss of Residual Heat Removal, while continuing in AOP-017, Loss of Instrument Air, 79

ILC-il-l NRC Exam

80. Given the following plant conditions:

- A Safety Injection has occurred due to lowering Pressurizer Level and Pressure.

- PATH-i is in progress.

- SPDS has not been reset.

- Containment radiation parameters are normal.

- R-14C, NG-Plant Vent, and R-4, Charging Pump Room, are in alarm.

Which ONE (1) of the following completes the statement below?

Procedure (1) would be entered based on the conditions provided and the first action taken would be to isolate (2)

A. (1) EPP-i5, Loss of Emergency Coolant Recirculation, (2) Hot Leg Safety Injection B. (1) EPP-20, LOCA Outside Containment, (2) Hot Leg Safety Injection C. (1) EPP-15, Loss of Emergency Coolant Recirculation, (2) RHR Loop Supply D. (1) EPP-20, LOCA Outside Containment, (2) RHR Loop Supply 80

ILC-l1-l NRC Exam

81. Given the following plant conditions:

- Feed Line Break to A SIG has occurred.

- RCS Pressure is 1345 psig and rising.

- CV Pressure is 20 psig and lowering.

- SIG pressures: A 0 psig, B 400 psig, C 400 psig.

- - -

- SIG WIDE RANGE levels: A 5%, B 21%, C 17%.

- - -

- No AFW flow is available.

- PATH-I Immediate Actions are complete and have just been verified.

Which ONE (1) of the following correctly analyzes the current plant conditions and identification of the required procedural progression that mitigates these plant conditions?

A. RCS bleed-and-feed is required.

Continue in PATH-I until directed to FRP-H.I, Response to Loss of Secondary Heat Sink.

B. RCS bleed-and-feed is required.

Exit PATH-l and transition to FRP-H.I, Response to Loss of Secondary Heat Sink.

C. RCS bleed-and-feed is NOT required.

Continue in PATH-I until directed to FRP-H.1, Response to Loss of Secondary Heat Sink.

D. RCS bleed-and-feed is NOT required.

Exit PATH-l and transition to FRP-H.I, Response to Loss of Secondary Heat Sink.

81

ILC-11-1 NRC Exam

82. Given the following plant conditions:

- Critical approach has just been completed.

- Reactor is stable at the Point of Adding Heat.

- APP-005-B2, N-35 LOSS OF COMP VOLT, alarm is received.

Which ONE(1) of the following correctly identifies the expected Power Range (PR) and Intermediate Range (IR) Nuclear Instrument indications and the required actions lAW Technical Specifications?

A. IR = 2.0 x 106 Amps; PR between 0.5 and 1%.

Lower Power to less than P-6 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

B. IR = 2.0 x 106 Amps; PR between 0.5 and 1%.

Lower Power to less than P-6 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

C. IR = 1.0 x io Amps; PR between 0 and <0.5%.

Lower Power to less than P-6 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

D. IR 1.0 x Amps; PR between 0 and <0.5%.

Lower Power to less than P-6 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

82

ILC-11-1 NRC Exam

83. Given the following plant conditions:

- High radiation alarms have just been received from R-20 and R-30, Fuel Handling Building Lower Level.

- ERFIS trends indicate the following:

WGDT A is at 70 psig and is In-Service.

WGDT B is at 20 psig and is In Standby.

WGDT C is at 80 psig and is Selected for Cover Gas with pressure slowly lowering.

WGDT D is at 60 psig and is isolated.

Which ONE (1) of the following identifies the required action(s) that mitigate these plant conditions lAW AOP-005, Radiation Monitoring System, and/or AOP-009, Accidental Gas Release from a WGDT?

In accordance with A. AOP-009, Direct the AC to equalize WGDT C with WGDT B.

B. AOP-009, Isolate WGDT C and place HVE-15A in service.

C. AOP-005, Direct the AC to equalize WGDT C with WGDT B.

D. AOP-005, Isolate WGDT C and place HVE-15A in service.

83

ILC-11-1 NRC Exam

84. Given the following information:

- The plant is at 100% RTP.

- RST-008, Calibration of Radiation Monitor System, Monitors R-1 through R-8, has been performed for R-1, Control Room Area Monitor.

- Based on technicians report, R-1 has been turned over to Operations and declared Operable.

- The Acceptance Criteria for the AS-LEFT calibration of R-1 is 50 mr/hr +1- 10%

and 6500 mr/hr +1- 20% for the detector (RST-008 Test Exposure Rate).

- Prior to closing out the RST-008 paperwork, the RC Supervisor reports the following Final AS-LEFT calibration results for R-1 to the CRS:

RST-008 Test Exposure Rate AS-LEFT Reading 50 mr/hr 43 mr/hr 6500 mr/hr 5225 mr/hr Which ONE(1) of the following states the Operability status of the equipment affected by the information given above?

A. BOTH CREFS trains are Inoperable.

B. CREFS Actuation Instrumentation is Operable.

C. ONLY CREFS Actuation Instrumentation is Inoperable.

D. BOTH CREFS trains AND the CREFS Actuation Instrumentation are Inoperable.

84

ILC-ll-l NRC Exam

85. Given the following plant conditions:

- A LOCA is in progress. The crew is performing actions of PATH-i.

- Core Exit TCs are at 705°F and rising.

- RVLIS Full Range indicates 40% and lowering.

- Containment pressure is 44 psig and slowly rising.

- RWST Level is 29% and lowering.

Which ONE (1) of the following completes the statement below?

Enter (1) FIRST, then declare a (2) lAW the Emergency Action Level Matrices.

(References Provided)

A. (1) FRP-J.1, Response To High Containment Pressure (2) Site Area Emergency B. (1) FRP-C.1, Response to Inadequate Core Cooling (2) Site Area Emergency C. (1) FRP-J.1, Response To High Containment Pressure (2) General Emergency D. (1) FRP-C.1, Response to Inadequate Core Cooling (2) General Emergency 85

ILC-11-1 NRC Exam

86. Given the following plant conditions:

- Mode 2 with a Plant Startup in Progress.

- Train B Reactor Protection testing is in progress.

- B Reactor Trip Bypass Breaker has been racked in and closed.

- Reactor Trip Breaker B is currently closed.

- B 125VDC Distribution Panel power is lost.

Which ONE (1) of the following completes the statements below regarding plant response due to a DIRECT RESULT of the failure AND what actions must be taken lAW Technical Specifications and AOP-024, Loss of Instrument Bus?

ONLY the Reactor (1) Breaker B will open.

The affected Instrument Bus must be re-energized within (2) hrs.

Normal Power Supply to the affected Instrument Bus must be restored to OPERABLE status within (3) hrs.

A. (1) Trip (2) 2 (3) 24 B. (1) Trip Bypass (2) 2 (3) 24 C. (1) Trip (2) 8 (3) 16 D. (1) Trip Bypass (2) 8 (3) 16 86

ILC-11-1 NRC Exam

87. Given the following initial plant conditions:

- The plant is at 100% RTP.

- APP-036-C7, R-24 Monitor HI, has alarmed. R-24B indicates 5.1 gpd, with a rising trend.

- R-15, Condenser Air Ejector Gas Monitor, and R-19B, SIG B Liquid Sample Monitor, were observed to be rising.

Approximately 15 minutes later the following plant conditions exist:

- R-24B now is steady with a reading of 35 gpd.

- The warning alarm on RR-1, RMS RECORDER, for R-1 9B, S/G B Liquid Sample Monitor has alarmed.

- The crew has entered AOP-035, S/G Tube Leak.

Which ONE (1) of the following completes the statement below?

The crew will take required action to (1) due to the known leakrate and take action to (2) to mitigate the spread of contamination.

A. (1) initiate a Normal Plant Shutdown and be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (2) close ES-33, Heater 5B EXT Steam to PRV-1985, to isolate Main Steam from Auxiliary Steam THEN start the Auxiliary Boilers B. (1) initiate a Normal Plant Shutdown and be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (2) start the Auxiliary Boilers. Once Auxiliary Boilers have pressurized THEN close ES-33, Heater 5B EXT Steam to PRV-1 985, to isolate Main Steam from Auxiliary Steam C. (1) monitor for increased primary to secondary leakage by logging R-24 readings at 15 minute intervals (2) close ES-33, Heater 5B EXT Steam to PRV-1985, to isolate Main Steam from Auxiliary Steam THEN start the Auxiliary Boilers D. (1) monitor for increased primary to secondary leakage by logging R-24 readings at 15 minute intervals (2) start the Auxiliary Boilers. Once Auxiliary Boilers have pressurized THEN close ES-33, Heater 5B EXT Steam to PRV-1985, to isolate Main Steam from Auxiliary Steam 87

ILC-11-1 NRC Exam

88. Given the following plant conditions:

- The plant is at 100% RTP.

- HVH-2 was started two (2) minutes ago following a test.

- APP-009-E7, 480V GRD FAULT, has alarmed.

- An AC was dispatched and reports that the GROUND FAULT light is illuminated and the GRD FAULT RELAY flag has dropped on SST-2F.

What action(s) should be taken lAW OMM-035, Ground Isolation, and OP-921, Containment Air Handling, and what impact on Operability (if any) will this have on the system?

A. Stop HVH-2 and remove control power fuses.

Containment Cooling Train A remains Operable.

B. Stop HVH-2.

Containment Cooling Train A remains Operable.

C. Stop HVH-2 and remove control power fuses.

Declare ONLY Containment Cooling Train A Inoperable.

D. Stop HVH-2.

Declare ONLY Containment Cooling Train A Inoperable.

88

ILC-11-1 NRC Exam

89. Given the following plant conditions:

- The plant is at 100% RTP.

- A two train fire alarm is received for the Unit 2 Cable Spread Room.

- The crew has entered AOP-041, Response to Fire Event.

Which ONE (1) of the following completes the statement below?

After confirming the fire location the next crew action is to (1) and the basis for this action is to (2)

A. (1) place PCV-456 I -455C Isolation Switches in the ISOLATED position (2) prevent spurious operation of these valves due to a hot short B. (1) place PCV-456 I -455C Isolation Switches in the ISOLATED position (2) to allow for remote operation of ONLY PCV-456 from the 4 KV Switchgear Room C. (1) verify LCV-115B, EMERG MU TO CHG SUCTION, OPEN and LCV-115C, VCT OUTLET, CLOSED (2) maintain suction to the Charging Pumps due to potential hot shorts affecting the VCT level control circuitry D. (1)verify LCV-115B, EMERG MU TO CHG SUCTION, OPEN and LCV-115C, VCT OUTLET, CLOSED (2) maintain suction to the Charging Pumps due to potential hot shorts causing spurious operation of LCV-1 I 5C 89

ILC-11-1 NRC Exam

90. Given the following:

- The Plant has just entered Mode I following a startup from a Refueling Outage.

- A review of Work Orders reveals that the Containment Equipment Hatch was not properly torqued. Additionally, Post-Maintenance Testing (Local Leak Rate Test) on the Hatch seals was not performed.

- Maintenance and Engineering reports that repairs and testing can be completed in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Which ONE (1) of the following completes the statement below?

lAW Technical Specifications the Containment Equipment Hatch must be restored to Operable status within (1) hour(s) and lAW AP-030, NRC Reporting Requirements, the NRC must be notified within (2) hour(s) for Shutdown Required by ITS and within (3) hour(s) for Principal Safety Barriers Seriously Degraded.

A. (1)1 (2) 4 (3) 8 B. (1)4 (2) 4 (3) 8 C. (1)1 (2) 1 (3) 1 D. (1)4 (2) 1 (3) 1 90

ILC-11-1 NRC Exam

91. Given the following plant conditions:

- Plant is at 3% RTP.

GP-005, POWER OPERATION, is in progress. Preparations are being made to start rolling the Turbine.

- The RO reports that PZR pressure is lowering and that PCV-455B appears to be open with a closed demand signal. AOP-019, Malfunction of RCS Pressure Control, Immediate Actions have been completed.

- Both PZR PORVs are closed.

- PCV-455B, SPRAY VALVE Controller has been placed in MAN and its output adjusted to zero.

- All PZR heaters are energized.

- The STA reports that PZR pressure is at 2200 psig and lowering at approximately 30 psig/minute.

Which ONE (1) of the following completes the statements below?

Direct the Reactor Operator to stop the C RCP, adjust LC-459G potentiometer to maintain PZR level between (1)

Place the plant in Mode 3 in (2) hours.

A. (1)17%-27%

(2) 12 B. (1)17%-27%

(2) 6 C. (1) 30% 40%

-

(2) 12 D. (1)30%-40%

(2) 6 91

ILC-11-1 NRC Exam

92. Given the following information:

Date Time Activity 5/31/2011 0000 Plant Shutdown to Mode 3 commenced.

5/31/2011 0830 Reactor Trip Breakers opened.

5/31/2011 1500 Mode4 Entry.

5/31/2011 2330 Mode5 Entry.

Which ONE (1) of the following completes the statements below?

The EARLIEST time and date that core alterations can commence in accordance with GP-010, Refueling, is (1)

The Manipulator Crane normal path from the CV Upender to core location H-8 is(2)

The (3) provides permission to deviate from the Manipulator Crane normal path.

A. (1)6/4/2011 at 1230 (2) Bridge south to 8 row and trolley east to H row (3) Shift Manager B. (1) 6/2/2011 at 1630 (2) Bridge south to 8 row and trolley east to H row (3) Refueling SRO C. (1) 6/4/2011 at 1230 (2) Bridge south to core area, trolley east to H row and then bridge south to 8 row.

(3) Shift Manager D. (1)6/2/2011 at 1630 (2) Bridge south to core area, trolley east to H row and then bridge south to 8 row.

(3) Refueling SRO 92

ILC-11-1 NRC Exam

93. Given the following:

- Unit is operating in Mode I at 100% RTP.

- The Engine Driven Fire Pump is inoperable for annual inspection and PMs.

- The Motor Driven Fire Pump (MDFP) and Fire Jockey Pump are operating to supply the system pressure and flush water.

- The breaker for the MDFP trips open and cannot be re-closed.

- The Fire Jockey Pump continues to operate.

Which ONE (1) of the following describes the actions required lAW FP-012, Fire Protection Systems Minimum Equipment and Compensatory Actions?

A. Be in Mode 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Mode 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

B. Restore at least 1 Fire Pump to operable status within 7 days.

C. Restore at least I Fire Pump to operable status within 14 days.

D. Establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

93

ILC-i1-1 NRC Exam

94. Given the following plant conditions:

- The plant has been operating at 100% RTP for the past three weeks.

- Chemistry has just provided the following results from a Reactor Coolant System sample that was taken 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago:

- RCS Chloride: 0.1 ppm

- RCS Oxygen: 0.15 ppm Which ONE(1) of the following completes the statement below?

The (1) concentration exceeds the TRM limit. Immediate action must be taken to initiate action to (2)

A. (1) Oxygen (2) place the plant in Mode 3.

B. (1) Oxygen (2) bring the Oxygen concentration within limits.

C. (1) Chloride (2) place the plant in Mode 3.

D. (1) Chloride (2) bring the Chloride concentration within limits.

94

ILC-11-1 NRC Exam

94. Given the following plant conditions:

- The plant has been operating at 100% RTP for the past three weeks.

- Chemistry has just provided the following results from a Reactor Coolant System sample that was taken 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago:

- RCS Chloride: 0.1 ppm

- RCS Oxygen: 0.15 ppm Which ONE(1) of the following completes the statement below?

The (1) concentration exceeds the TRM limit. Immediate action must be taken to initiate action to (2)

A. (1) Oxygen (2) place the plant in Mode 3.

B. (1) Oxygen (2) bring the Oxygen concentration within limits.

C. (1) Chloride (2) place the plant in Mode 3.

D. (1) Chloride (2) bring the Chloride concentration within limits.

94

ILC-11-1 NRC Exam 95.

Which ONE (1) of the following identifies components assumed to operate at their setpoints to prevent exceeding the Technical Specification Safety Limit on RCS pressure?

A. All Pressurizer Safety Valves ONLY.

B. All Main Steam Safety Valves ONLY.

C. All Pressurizer Safety and Main Steam Safety Valves.

D. TWO (2) Pressurizer Safety Valves and THREE (3) Main Steam Safety Valves per line.

95

ILC-11-1 NRC Exam

96. Voltage regulator for the Main Generator has been replaced during the refueling outage.

SP-)O(XX has been developed and approved for acceptance testing to be used with GP-005, Power Operation.

Final testing must be performed with voltage regulator in service with unit paralled to the grid.

Which ONE (1) of the following is the appropriate CASE assignment for this evolution and who SHALL act as the Management Designated Monitor (MDM) for this evolution lAW PLP-037, Conduct of Infrequently Performed Tests or Evolutions and Pre-Job Briefs.

(Reference Provided)

A. CASE 2 - MDM shall be a Line Manager, Senior to the SM.

B. CASE 3 - MDM shall be a First Line Supervisor or above.

C. CASE 3 - MDM shall be assigned by PGM.

D. CASE 2 - MDM shall be assigned by PGM.

96

ILC-11-1 NRC Exam

97. Given the following plant conditions:

- Large Break LOCA with multiple equipment malfunctions.

- Fuel failure has been confirmed.

- A General Emergency has been declared and ERO positions staffed.

- The Dose Rate in Pipe Alley is 120 R/hr.

- An evolution in Pipe Alley is necessary to avoid extensive exposure of a large population.

- Individuals were selected by the OSC Leader to perform the evolution.

Which ONE (1) of the following completes the statements below?

The (1) can authorize performance of the evolution in Pipe Alley.

lAW EPOSC-04, Emergency Work Control, (2) is the maximum time allowed to perform the evolution in Pipe Alley without exceeding Emergency Work Dose Limits.

A. (1) Site Emergency Coordinator (2) 4.5 minutes B. (1) Site Emergency Coordinator (2) 12.4 minutes C. (1) Radiological Control Director (2) 4.5 minutes D. (1) Radiological Control Director (2) 12.4 minutes 97

ILC-11-1 NRC Exam

98. Given the following plant conditions:

- A Large Break LOCA has occurred.

- Containment pressure is 32 psig and rising.

- A loss of off-site power has occurred.

- B EDG has failed to start.

- HVH-1 has tripped.

- R-32A, CV High Range, has the current indication.

Which ONE (1) of the following completes the statement below?

Based on the information provided a (1) must be declared due to (2)

(References Provided)

A. (1) Site Area Emergency (2) Loss of the Reactor Coolant AND Fuel Cladding Barriers.

B. (1) General Emergency (2) Loss of Reactor Coolant, Fuel Cladding AND Containment Barriers.

C. (1) Site Area Emergency (2) Loss of the Reactor Coolant Barrier AND a Potential Loss of Containment Barrier.

D. (1) General Emergency (2) Loss of the Reactor Coolant AND Fuel Cladding Barrier AND Potential Loss of Containment Barrier.

98

ILC-11-1 NRC Exam

99. A Site Area Emergency has been declared.

The Control Room Site Emergency Coordinator has the authority to delegate certain tasks to other available watch standers.

Which ONE (1) of the following tasks CAN be delegated?

A. Classification of the Event.

B. Conduct a Site Evacuation.

C. Decision to Notify Off-site Authorities.

D. Off-site Protective Action Recommendations.

99

ILC-11-1 NRC Exam 100. A General Emergency has been declared.

- The SEC-CR is evaluating Protective Action Recommendations (PARs).

- There are no known impediments to evacuation.

Which ONE (1) of the following is the MINIMUM PARs that shall be issued for the declared General Emergency?

Evacuate at least A. 5 mile radius and shelter 10 miles downwind.

B. 5 mile radius and 10 miles downwind.

C. 2 mile radius around and shelter 5 miles downwind.

D. 2 mile radius around and 5 miles downwind.

100

Reference Material Table of Contents

1. ITS Section 2.0, Figure 2.1.1-1, Reactor Core Safety Limits
2. PLP-037, Attachment 10.2, Procedure Evaluation and Case Determination
3. EAL Matrix ALL CONDITIONS
4. EAL Matrix HOT CONDITIONS
5. EAL Matrix COLD CONDITIONS

ANSWER KEY REPORT for ILC-1 1-1 NRC Written Exam 2-1 5-1 1 Test Form: 0 Answers

  1. ID Points Type 0 1 007 EK2.02 1 1.00 MCS D 2 008 AK2.03 1 1.00 MCS C 3 009 EK3.23 1 1.00 MCS A 4 OI1EK1.01 1 1.00 MCS C 5 015 AK1.041 1.00 MCS B 6 015 AK2.10 1 1.00 MCS A 7 022 AAI.09 1 1.00 MCS A 8 026 AA1.06 1 1.00 MCS A 9 029 EG2.4.21 1 1.00 MCS C 10 040 AK3.02 1 1.00 MCS A 11 054 AA2.08 1 1.00 MCS B 12 056 AG2.4.47 1 1.00 MCS A 13 058 AA2.01 1 1.00 MCS D 14 062 AA2.01 1 1.00 MCS B 15 077 AG2.4.45 1 1.00 MCS B 16 WIEO4EK3.2 1 1.00 MCS A 17 W/E O5EK1.2 1 1.00 MCS C 18 W/E 11EA1.3 1 1.00 MCS A 19 001 AA2.04 1 1.00 MCS D 20 036 AK2.01 1 1.00 MCS D 21 037 AG2.4.9 1 1.00 MCS A 22 051 AA1.04 1 1.00 MCS D 23 059 AK3.01 1 1.00 MCS B 24 074 EA2.07 1 1.00 MCS B 25 WIE 03 EK 1.11 1.00 MCS D 26 WIE I4EAI.1 1 1.00 MCS D 27 W/E 15EK3.1 1 1.00 MCS B 28 003 A3.04 1 1.00 MCS C 29 004 A3.15 1 1.00 MCS D 30 004 K3.08 1 1.00 MCS A 31 005 K3.07 1 1.00 MCS A 32 006 A1.07 1 1.00 MCS C 33 006K6.101 1.00 MCS B 34 007 A1.03 1 1.00 MCS A 35 007 A2.01 1 1.00 MCS C 36 008 K4.09 1 1.00 MCS D 37 010 K5.02 1 1.00 MCS B 38 010 K6.01 1 1.00 MCS B 39 012A4.041 1.00 MCS D 40 013 K5.01 1 1.00 MCS B 41 022 A4.05 1 1.00 MCS D 42 026 K2.01 1 1.00 MCS A 43 039 G2.1.7 1 1.00 MCS D 44 039 G2.4.20 1 1.00 MCS C 45 059 A3.02 1 1.00 MCS C 46 061 K5.01 1 1.00 MCS D Thursday, March 24, 2011 2:51 :54 PM

ANSWER KEY REPORT for ILC-1 1-1 NRC Written Exam 2-15-11 Test Form: 0 Answers

  1. ID Points Type U 47 062 K2.01 1 1.00 MCS C 48 063 A2.01 1 1.00 MCS B 49 063 K4.02 1 1.00 MCS D 50 064A2.141 1.00 MCS C 51 073 02.4.18 1 1.00 MCS A 52 076 K1.01 1 1.00 MCS D 53 078 K3.02 1 1.00 MCS A 54 103 A4.01 1 1.00 MCS C 55 103 K1.02 1 1.00 MCS B 56 001 K3.01 1 1.00 MCS A 57 015 K2.01 1 1.00 MCS C 58 016 K1.12 1 1.00 MCS D 59 028 K5.03 1 1.00 MCS A 60 034 K6.02 1 1.00 MCS C 61 041 K4.09 1 1.00 MCS C 62 071 A1.06 1 1.00 MCS B 63 072 G2.1.20 1 1.00 MCS A 64 075 A2.03 1 1.00 MCS A 65 086 A4.01 1 1.00 MCS A 66 G2.1.28 1 1.00 MCS D 67 G2.1.4 1 1.00 MCS D 68 02.1.43 1 1.00 MCS B 69 02.2.20 1 1.00 MCS C 70 02.2.22 1 1.00 MCS B 71 G2.2.35 1 1.00 MCS C 72 G2.3.13 1 1.00 MCS B 73 02.3.4 1 1.00 MCS B 74 G2.4.22 1 1.00 MCS D 75 G2.4.6 1 1.00 MCS D 76 008 AG 2.1.23 SRO 1 1.00 MCS C 77 025 AA2.05 SRO 1 1.00 MCS B 78 056 AG2.4.4 SRO 1 1.00 MCS C 79 065 AA 2.01 SRO 1 1.00 MCS D 80 WIE 04 EG2.4. 1 SRO 1 1.00 MCS D 81 W/E 05 EA2. 1 SRO 1 1.00 MCS A 82 033 AA2.04 SRO 1 1.00 MCS B 83 060 AG2.2.44 SRO 1 1.00 MCS A 84 061 AA2.03 SRO 1 1.00 MCS C 85 W/E 14EG2.4.47 SRO 1 1.00 MCS D 86 012 A2.07 SRO 1 1.00 MCS A 87 039 A2.03 SRO 1 1.00 MCS C 88 062 A2.14 SRO 1 1.00 MCS C 89 063 G2.4.49 SRO 1 1.00 MCS A 90 103 G2.4.30 SRO 1 1.00 MCS A 91 011 A2.06 SRO 1 1.00 MCS D 92 034 A3 .01 SRO 1 1.00 MCS C Thursday, March 24, 2011 2:51:54 PM 2

ANSWER KEY REPORT for ILC-11-1 NRC Written Exam 2-15-11 Test Form: 0 Answers

  1. ID Points Type 0 93 086 G2.2.40 SRO 1 1.00 MCS D 94 G2.1.34 SRO 1 1.00 MCS B 95 G2.2.25 SRO 1 1.00 MCS C 96 G2.2.7 SRO 1 1.00 MCS D 97 G2.3.14SRO 1 1.00 MCS B 98 G2.3.5 SRO 1 1.00 MCS D 99 G2.4.40 SRO 1 1.00 MCS B 100 G2.4.44 SRO 1 1.00 MCS D SECTION 1 ( 100 items) 100.00 Thursday, March 24, 2011 2:51:54 PM 3
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